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R 2.1 199^ ^.EN GINEERING DATA TRANSMITTAL<br />
1.EDT<br />
.. ., t-' :'l<br />
. To: (Receiving Organization) 3. From: ( Originating Organization) 4. Related EDT No.:<br />
Distribution WRAP Technolo gy 132766<br />
5. Proj./Prog./Dept-/Div.: 6. Cog. Engr.: 7. Purchase Order No.:<br />
WRAO-24910 CJ Benar N / A<br />
i. ` c 1<br />
Page 1 of 1<br />
3. Originator Remarkse 9. Equip./COnponent No.:<br />
WHC-SD-W100-TI-003, rev. 0, "WRAP Module 2A Waste Form N / A<br />
Qualification Status Report". TO. System/Bldg•/Facility:<br />
WRAP 2A / W-100<br />
11. Receiver Remarks: r0 ?4<br />
g = Fi<br />
12. Major Assm. Dwg. No.:<br />
ti ^<br />
N / A<br />
^lE^^<br />
cs<br />
13. Permit/Permit Application No.:<br />
N/A<br />
14 . R equ i red Response<br />
N/A<br />
Date:<br />
. 15. DATA TTgD ^- (F) G) (H) (I)<br />
' ( A )<br />
Item<br />
-<br />
(BI <strong>Document</strong>/Drawing No.<br />
- iCi -<br />
Sheet<br />
- -<br />
Rev.<br />
- - -<br />
(E) Title or Descdptbn of Data<br />
- --<br />
Impact I Reason<br />
-<br />
^ ,.. No.<br />
No. No. Transmitted Level<br />
for<br />
Trans-<br />
Ortginator<br />
Dispo-<br />
Receivor<br />
Dispo-<br />
mittal eition sition<br />
I WHC-SD-W100-TI-003 0 WRAP Module 2A Waste 4 2<br />
Form Qualification<br />
Status Re ort<br />
16. KEY<br />
Impact Level ( F) Reason for Transmittal (G) Disposition ( H) &(I)<br />
1. 2, 3, or 4 Isee 1. Approval 4. Review 1. Approved 4. Reviewed no/comment<br />
MRP 5.43) 2. Release 5. Post-Review 2. Approved w/comment 5. Reviewed w/comment<br />
3. Information 6. Dist. (Receipt Acknow. Required) 3. Disapprovad w/comment S. Receipt acknowledged<br />
iGi (H)<br />
Reaeun<br />
17. SIGNATURE/DISTAIBUTION<br />
( See Impact Level for required signatures)<br />
Disp. ( JI Name (K) Signature ( U Data ( M) MSIN (J) Name (K) Signature IL) Date (M) MSIN<br />
2 ( Cog.Eng.CJ Bener Lf X60<br />
2 ^ Cog. Mgf•.CA Peter n H1-60<br />
OA<br />
Safety<br />
Env.<br />
I 1B• 19. 20. 21. DOE APPROVAL (if required)<br />
Ltr. No.<br />
q Approved<br />
q Approved u/comments<br />
Signature of EDT Date Authorized Representative Date Cognizant/Project t [) Disapproved w/comments<br />
l7riginator for Raceiving Organization EngineeYs Manager<br />
BD-7400-172-2 ( 07/91) GEF097<br />
(Gl iH)<br />
Reason<br />
Disp.<br />
BD-7400-1721 102/89)<br />
' ..
u.<br />
= THIS PAGE INTENT9ONALLY<br />
...._- LEFT BLANK<br />
^::_^;
Date Received%<br />
• I INFORMATION RELEASE REQUEST<br />
I Reference:<br />
4 /,h/ d3 i WHC-CM-3-4<br />
q<br />
_.<br />
SpeechorPresentation<br />
.PUr se- __--- -_-_-q<br />
Reference<br />
- 1 ID- N:abar (inelude revision, volume,<br />
WHC-SD-W100-TI-003 Rev. 0<br />
etc.)<br />
[I<br />
[]<br />
F ull Paper<br />
Summary<br />
(Check<br />
only one<br />
suffix)<br />
[x]<br />
q<br />
[]<br />
Technical Report<br />
Thesis or Dissertation<br />
Manual<br />
L i st attachments.<br />
[] Abstract [] Brochure/Flier appendices A through G<br />
[] Visual Aid [] Software/Database<br />
[] Speakers Bureau [] Controlled <strong>Document</strong><br />
Date Release Required<br />
[] Poster Session Q Other 4/6/93<br />
t] Videotape<br />
Title WRAP Module 2A Waste Form Qualification Status Unclassified Category Impact<br />
Level 4<br />
Rep ort UC-NA<br />
New or novel (patentable) subject matter) [ X] No [ l yes<br />
f 'Ves', has disclosure been submitted by WHC or other company7<br />
Information received from others in confidence, such as proprietary data,<br />
trade secrets, and/or inventions)<br />
[l No [l Yes Discbsure Nolsl.<br />
[X] No [ l Yes (Identify)<br />
Copyrights? [X] No [l Ves<br />
Trademarksi<br />
If'Ves-,haswrittenpermisaionbeenprantedT [l No [Xl Veslldentify) Sorbond, Envirostone,<br />
[1 No [1 Yes IAttach Permissionl Cel1 te, Hobart<br />
tle of Journal<br />
or Meeting I Group or Society Sponsoring<br />
Conference or Meeting I City/State I Willproceedinpsbepublished7 [l Yes<br />
Re view Required per WHC-CM-3-4<br />
tesification/UnclesaifiedControlled<br />
clear Information<br />
Patent - General Counsel<br />
eneral Counsel -<br />
Applied Technology/Export Controlled<br />
Information or International Program<br />
WHC Program/Project<br />
Communications<br />
RL Proaram/Project<br />
Publication Services<br />
Other Program/Project<br />
References Available to Intended Audience<br />
Transmit to DOE-HQ/Office of Scientific<br />
and Technical Information<br />
Will material be handed out? [] Yes<br />
Yes No Reviewer - Signature Indicates Approval<br />
Name (printed) Signature<br />
[l [ X'- l+ ,<br />
r"<br />
WC1p;<br />
W<br />
[l 1XI<br />
[l 1XI ,<br />
[l 1XI<br />
[l 1XI<br />
1XI [l<br />
[l 1XI<br />
e reauirements.<br />
Yes No<br />
1XI [l<br />
[l 1XI<br />
Author/Requestor rinted/Signeture) Date<br />
CJ Benar<br />
Intended Audi ce<br />
VW<br />
[l internal all sponsor ^ External<br />
-sponsible Manager ( Print gp/ Stgnature) Date<br />
r.^A Petersen 4/2/93<br />
BD-7600-062 ( 08/91) WEF074<br />
4/2/93<br />
THIS PAGE INTENTIONALU<br />
LEFT BLANK<br />
^^^
.<br />
SUPPORTING DOCUMENT 1. Total Pages 360<br />
2. Title 3. Number 4. Rev No.<br />
WRAP 2A Module 2A Waste Form Qualification Status WHC-SD-W100-TI-003 0<br />
Re p ort<br />
5. Key Vords 6. Author<br />
Solidification, Stabilization, Cementitious, Name: CJ Benar, DA Burbank, KM<br />
Polymer, Thermosetting, Grout, Waste Forms, Weingardt<br />
Immobilization, Matrix, Parametric Studies ^<br />
• ^ ^: _^<br />
^ C ^:<br />
7. Abstract<br />
'^ • S ^ .-(<br />
- v :. .<br />
E L n 4<br />
C` !<br />
.<br />
ig ture<br />
Organization/Charge Code 24910/A55E2<br />
This report summarizes the results of the testing program conducted by WHC to<br />
confirm the baseline waste form selection for use in WRAP (Waste Receiving and<br />
Processing) Module 2A. WRAP 2A will provide treatment required to properly dispose<br />
of Contact Handled (CH) Mixed Low Level Waste (MLLW) accumulating at the DOE <strong>Hanford</strong><br />
<strong>Site</strong> in Richland, WA. Screening tests were performed using the major chemical<br />
constituent of each waste type to measure the gross compatibility with the<br />
immobilization media. Positive results were obtained resulting in the production of<br />
a solid monolith from each major chemical constituent with the selected<br />
immobilization medium. This indicated that more advanced testing should be<br />
performed to confirm that a detailed surrogate waste in the immobilization matrix<br />
could pass all applicable test criteria imposed the final waste form.<br />
8. PURPOS AND USE OF DOCUMENT - This documen as prepar use 10. RELEASE STAMP<br />
within U.S. Department of Ene nd its c ractors is to<br />
be use nly to perform, or i n ate k under<br />
U.S. Depar nt of Energy c s. This doc i t approved<br />
for public ease untit ed.<br />
PATENT STATUS Thi^^ument copy, since it smitted in<br />
=dv ,.. .,,<br />
fore ° ^ us<br />
,,,.te#<br />
• ^' ....<br />
in `manceof<br />
,.,ad .otabte<br />
uork°,under<br />
cnfi<br />
tracts<br />
ce soleLy<br />
'th the<br />
U.S. Depart rgy. This document is to be pubt ed nor<br />
its conten erwi disseminated or use r purposes o[h than<br />
specifi e befor tent approval f ch release or u has<br />
been d, upon requ from the Pate ounsel, U.S. Department<br />
of E Field Office, R Land , WA.<br />
DISCLAIMER - This report was prepared as an account of work<br />
sponsored by an agency of the United States Goverment. Neither the<br />
United States Government nor any agency thereof , nor any of their t I^<br />
emp l oyees, nor any o f t h e i r contractors, subcontractors or their !J C 3<br />
employees, makes any warranty, express or implied, or assumes any<br />
f<br />
legal liability or responsibility for the accuracy, completeness, or<br />
any third party's use or the results of such use of any information,<br />
apparatus, product, or process disclosed, or represents that its use<br />
would not infringe privately owned rights. Reference herein to any<br />
specific commercial product, process, or service by trade name,<br />
trademark, manufacturer, or otherwise, does not necessarily<br />
constitute or imply its endorsement, recommndation, or favoring by<br />
the United States Government or any agency thereof or its<br />
contractors or subcontractors. The views and opinions of authors<br />
expressed herein do not necessarily state or reflect those of the<br />
United States Government or any a g enc y thereof.<br />
1 9. Impact Level 4<br />
A-6400-073 (11/91) ( EF) WEF124<br />
YI
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_.^<br />
r<br />
^.,.
WHC-SD-W100-TI-003 Rev. 0<br />
EXECUTIVE SUMMARY<br />
A testing program has been conducted by the Westinghouse <strong>Hanford</strong> Company<br />
(WHC) to confirm the baseline waste form selection for use in WRAP (Waste<br />
Receiving and Processing) Module 2A. The WRAP Module 2A will provide<br />
treatment required to properly dispose of contact handled mixed low-level<br />
waste accumulating at the U.S. Department of Energy (DOE) <strong>Hanford</strong> <strong>Site</strong> in<br />
Richland, Washington. Solidification/stabilization has been selected as the<br />
appropriate treatment for this waste to reduce its toxicity and mobility in<br />
the disposal site. This work is intended to test various solidification media<br />
and confirm the baseline technologies selected for WRAP 2A.<br />
The testing used a phased approach, consisting of first screening the<br />
compatibility of surrogate wastes with the immobilization media, then<br />
performing detailed physical and chemical tests on laboratory-prepared<br />
=`} surrogate waste forms. This will be followed by performance testing of<br />
surrogate waste form specimens prepared by full-scale mixing equipment.<br />
Further testing will be performed during startup of the plant and introduction<br />
-cf-new--waste--streams:--it-fis-conceived that-similar-testing as described above<br />
will be required throughout the life of the plant as new wastes and variations<br />
to the process are encountered. This report details the efforts and results<br />
obtained from the initial phase of testing (waste form compatibility screening<br />
and surrogate performance testing).<br />
The current focus of this test work is to verify the ability of the<br />
immobilization media identified in the conceptual design report to adequately<br />
solidify certain waste types (UE&C 1992). As such, the first efforts of this<br />
testing focus on using two matrices for waste solidification; cement-based<br />
materials and thermosetting polymer resins. Project background, feedstream<br />
overview, and the conceptual design baseline approach are discussed in this<br />
rep^rt to further clarify the focus of the test work.<br />
ii
WHC-SD-W100-TI-003 Rev. 0<br />
Eight different waste types, representing about 80% of the projected feed<br />
to WRAP 2A were used for these initial phases of testing. The remaining 20%<br />
consists of small quantities of various waste types that require better<br />
characterization data before testing. This 20% will be tested as better<br />
information becomes available. Four of the waste types were tested with<br />
cementitious waste forms, and four different waste types were tested with the<br />
thermosetting polymer. The split as to which waste was to be treated with<br />
which immobilization medium was based on the conceptual design baseline.<br />
Screening tests were performed using the major chemical constituent of<br />
each waste type to measure the gross compatibility with the immobilization<br />
media. Positive results were obtained here in that a solid monolith was<br />
successfully prepared from each major chemical constituent with the selected<br />
immobilization medium. This indicated that more advanced testing should be<br />
performed to confirm that a detailed surrogate waste in the immobilization<br />
matrix could pass all applicable test criteria imposed on the final waste<br />
form.<br />
Test criteria for solidified mixed waste were assembled from applicable<br />
-- - -----r_egulaiiory=documeQtation (DDEArder 5820-2A--[D4E -1-988], Washingtpn<br />
Administrative Code 173-303 [WAC 1990], and 10 CFR 261 [NRC 1992]), including<br />
guidance documents from the U.S. Nuclear Regulatory Commission (NRC Technical<br />
--- - ---Posi#iop-on-Waste-Faxm.[NRC-184T])-and the U.S. Er^vironmental Protection<br />
Agency Handbook for Stabilization_and Solidification of Hazardous Wastes<br />
(EPA 1984).<br />
Waste surrogates were then prepared by WHC to represent each of the eight<br />
waste types for testing. Surrogates for polymer testing were sent to the<br />
vendor commissioned for that portion of the test work. Surrogates for the<br />
cementitious testing were used in the WHC laboratory responsible for the grout<br />
performance testing.<br />
Test specimens were prepared with the surrogate wastes, and tests were<br />
performed. Detailed discussion of the laboratory work and results are<br />
contained in this report. All cementitious specimens performed as expected<br />
and confirmed baseline process selection. Successful test results have also<br />
iii
WHC-SD-W100-TI-003 Rev. 0<br />
been achieved with some of the polymer specimens. All surrogates have been<br />
successfully solidified and have formed free-standing monoliths that exceed<br />
strength criteria. Some additional formulation work is necessary with the<br />
polymer-wastetypss to ensure adequate encapsulation of some key constituents.<br />
If the remaining tests show positive results, then the baseline process<br />
selection will be confirmed and the next stage of testing will proceed. The<br />
-follow-on tests will consist of laboratory parametric studies, mixing<br />
-----€qu#-pmer,t tests, and confirmatory testing using actual waste. These tests<br />
-- will_qenera_teprocess €ontxol data, detailed design data, and data required<br />
for pe%mit approval.<br />
iv
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__ _ _ MHC-SIL-yJ3,00-TI-D03 Rev. 0<br />
CONTENTS<br />
1.0 INTRODUCTION . . . . . . . . . . . . . . . . . . . . . . 1-1<br />
1.1 WRAP 2A BACKGROUND . . . . . . . . . . . . . . . . . 1-1<br />
1.2 WRAP 2A FEEDSTREAM OVERVIEW . . . . . . . . . . . 1-2<br />
1.2.1 Feedstream 1: 183H Solar Basin Waste ........ 1-3<br />
1.2.2 Feedstream 2: Liquid Effluent Treatment<br />
Facilities Secondary Solids . . . . . . . . . . . 1-4<br />
1.2.3 Feedstream 3: Compactible Solids . . . . . . . . . . 1-4<br />
1,2,4 _ Feedstream 4; Noncompactible Solids_._. . . . . . . . 1-5<br />
1.2.5 Feedstream 5: Metals . . . . . . . . . . 1-5<br />
1.2.6 Feedstream 6: Absorbed Chemicals/<br />
Solidified Liquids . . . . . . 1-6<br />
1.2.7 Feedstream 7: Ash From Thermal Treatment ...... 1-6<br />
1.2.8 Feedstream 8: Contaminated Soils . . . . . . . . . . 1-6<br />
1.3 WRAP 2A CONCEPTUAL DESIGN BASELINE APPROACH . . . . . . . . . 1-6<br />
2.0 WAST E FORM PERFORMANCE SPECIFICATIONS . . . . . . . . . . . . . . 2-1<br />
2.1 REGULATORY FRAMEWORK . . . . . . . . . . . . . . . . . . . 2-1<br />
2.1.1 Federal Regulations . . . . . . . . . . . . . . . . . 2-1<br />
2.2.2 State of Washington ..... 2-1<br />
2.2.3 <strong>Hanford</strong> <strong>Site</strong> Solid Waste Acceptance Criteria ..... 2-1<br />
2.2 PROGRAMMATIC AND FUNCTIONAL REQUIREMENTS . . . . . . . . . . 2-1<br />
2.3 TEST SELECTION AND ACCEPTANCE CRITERIA . . . . . . . . . . . 2-2<br />
2.3.1 Compressive Strength . . . . . . . . . . . . . . . . . 2-2<br />
2.3.2 Leachability Index . . . . . . . . . . . . . . . . . . 2-3<br />
2.3.3 Biodegradation . . . . . . . . . . . . . . . . . . . . 2-4<br />
2.3.4 Thermal Cycling . . . . . . . . . . . . . . . . . . 2-4<br />
2.3.5 Radiation Stability . . . . . . . . . . . . . . . . . 2-4<br />
2.3.6 Water Immersion . . . . . . . . . . . . . . . . . . . 2-4<br />
2.3.7 Free Liquids . . . . . . . . . . . . . . . . 2-5<br />
2.3.8 Hazardous Characteristics . . . . . . . . . . . . . . 2-5<br />
3.0 TESTING SCOPE AND DESCRIPTION . . . . . . . . . . . . 3-1<br />
3.1 SELECTION OF WASTE TYPES FOR TESTING . . . . . . . . . . . . 3-1<br />
3.2 SELECTION OF WASTE FORMS FOR TESTING . . . . . . . . . . . . 3-2<br />
3.3 TESTING APPROACH . . 3-5<br />
3.3.1 Confirm Process Design . . . . . . . . . . . . . . . . 3-5<br />
3.3.2 Process Optimization . . . . . . . . . . . . . . . . . 3-8<br />
3.3.3 Hot Verification . . . . . . . . . . . . . . . . . . 3-8<br />
3.3.4 Additional Objectives . . . . . . . . . . . . . . . . 3-8<br />
4.0 TEST RESULTS . . . . . . 4-1<br />
4.1 SCREENING TEST RESULTS ... . 4-1<br />
4.1.1 Cement-Based Waste Form Screening Test Results ... . 4-1<br />
4.1.2 Thermosetting Polymer Screening Test Results ..... 4-2<br />
4.1.3 Thermosetting Polymer Results Summary . . . . . . . . 4-5<br />
4.2 SURROGATE PERFORMANCE TESTS . . . . . . . . . . . . . . 4-5<br />
4.2.1 Cement-Based Waste Form Results ..... 4-5<br />
4.2.2 Thermosetting Polymer Waste Form Test Results .... 4-9<br />
4.3 FOLLOW-ON TESTING . . . . . . . . . . . . . . . . . . . . . . 4-11<br />
5.0 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . 5-1<br />
v
WHC-SD-W100-TI-003 Rev. 0<br />
LIST OF FIGURES<br />
3-1 Waste Form Qualification Strategy . . . . . . . . .<br />
3-2 WRAP 2A Process Development Waste Form Qualification<br />
Project Logic . . . . . . . . . . . . . . . . . . .<br />
LIST OF TABLES<br />
1-1 <strong>Hanford</strong> <strong>Site</strong> Solid Waste Treatment Facilities . . . . . . . . . .<br />
1-2 WRAP 2A Design Basis Summary . . . . . . . . . . . . . . . . . . .<br />
2-1 WRAP 2A Waste Form Performance Specifications . . . . . . . . . .<br />
3-1 Initial Testing Phase of Large Volume Feedstreams ........<br />
3-2 Solidification Technologies . . . . . . . . . . . . . . . . . . .<br />
3-3 Formulations for Cement Solidification Testing . . . . . . . . . .<br />
4-1 WRAP 2A Waste Form Characteristics . . . . . . . . . . . . . . . .<br />
4-2 WRAP 2A Cement Waste Form Tests Results . . . . . . . . . . . . .<br />
4-3 TCLP Results for WRAP 2A Cement Waste Forms . . . . . . . . . . .<br />
4-4 Formulation Parameters . . . . . . . . . . . . . . . . . . . . . .<br />
4 5 Rcpl IVatG JpGVImGnS TGJ40Y . . . . . . . . . . . . . . . . . . . .<br />
4-6 Summary of Polymer Waste Form Testing Results . . . . . . . . . .<br />
4-7 Follow-On Testing Results . . . . . . . . . . . . . . . . . . . .<br />
vi<br />
3-6<br />
3-7<br />
1-2<br />
1-8<br />
2-3<br />
3-1<br />
3-2<br />
3-4<br />
4-6<br />
4-7<br />
4-9<br />
4-10<br />
4-10<br />
4-12<br />
4-13
F`=<br />
WHC-SD-W100-TI-003 Rev. 0<br />
DESCRIPTION OF APPENDICES<br />
A. Statement of Work - Thermosetting Polymer<br />
Statement of Work prepared by Westinghouse <strong>Hanford</strong> Company (WHC) as part<br />
of the bid package soliciting qualified vendors to perform waste form<br />
performance testing using a thermosetting polymer with WHC-prepared<br />
surrogate waste.<br />
B. Technical Task Plan - Grout<br />
Technical Task Plan prepared by WHC for an "in-house" (WHC) testing<br />
program for waste form performance testing using cement-based waste forms<br />
and surrogate waste. Similar to the statement of work for thermosetting<br />
polymer.<br />
= C. Thermosetting Polymer Test Plan<br />
Detailed Test Plan prepared by the vendor awarded the contract for<br />
° thermosetting polymer testing described in Appendix A. Outlines test<br />
procedures, quality control, and testing deliverables.<br />
0. Characterization Data<br />
1. Two memos prepared by WHC Chemical Process Engineering Group. The<br />
first summarizes the "to date" characterization data on the<br />
183H basin wastes ( the largest volume of the currently stored<br />
low-level mixed waste types. The second memo describes the<br />
recommended waste forms for the various basin wastes and some to the<br />
future generated waste streams (Liquid Effluent Treatment Facility<br />
[L ETF,--?nd--Iacanerator Ash).<br />
2.<br />
Memo 1: JBW-183-001<br />
Memo 2: CPE-WOG-002<br />
Four WHC-generated Internal Letter Reports reviewing the records of<br />
the contents of all currently stored low-level mixed waste at the<br />
<strong>Hanford</strong> <strong>Site</strong>. The characterization data and the U.S. Environmental<br />
Protection Agency waste codes were used to group the containers into<br />
lots of similar waste types for processing. A technical evaluation<br />
was-then performed (by a solidification technology expert) as to the<br />
best treatment approach for each lot. The rationale for the<br />
treatment selection is included.<br />
Memo No.s: 87330-92-MLS-023, - 025, -026 -028.<br />
vii
Literature Search Results<br />
WHC-SD-W100-TI-003 Rev. 0<br />
DESCRIPTION OF APPENDICES (cont.)<br />
1. This WHC Letter Report (CEP-WOG-001) contains a thorough literature<br />
search and review of solidification technologies. This review was<br />
done in support of the Waste Receiving and Processing (WRAP)<br />
Facility, Module 2A, Waste Form Qualification efforts. It included<br />
a review of all known solidification technologies.<br />
This report (generated by solidification expert Earl McDanial,<br />
Oak Ridge National Laboratory) is a review specifically of grouting<br />
technology (cement-based solidification) used throughout the world.<br />
This report was done to support the selection of a grout technology<br />
in WRAP 2A.<br />
F. Thermosetting Polymer Test Results<br />
Contained under four reports:<br />
Test Status Report (1) - WHC Trip<br />
Thermosetting Polymer Test Report<br />
Thermosetting Polymer Test Report<br />
Thermosetting Polymer Test Report<br />
G. Overview of Solidification Technologies<br />
Report to Stock Equipment Company<br />
(2) - Stock Equipment Company<br />
(3) - Stock Equipment Company<br />
(4) - Stock Equipment Company<br />
This is an internal WHC memo report that was prepared as a review of all<br />
avaiiable solidification technologies, important processing<br />
considerations,_and general advantages and disadvantages of various<br />
technologies. The report is not specific to WRAP 2A and is intended to<br />
provide--general--trackground needed to begin evaluating the various waste<br />
forms.<br />
viii
WHC-SD-W100-TI-003 Rev. 0<br />
LIST OF TERMS<br />
ANS American Nuclear Society<br />
ASTM American Society for Testing and Materials<br />
BDAT Best Demonstrated Achievable Technology<br />
CDR Conceptual Design Report<br />
CH contact handled<br />
CH-MLLW contact handled mixed low-level waste<br />
DOE U.S. Department of Energy<br />
EPA U.S. Environmental Protection Agency<br />
LETF Liquid Effluent Treatment Facilities<br />
LLW low-level waste<br />
MLLW mixed low-level waste<br />
NRC U.S. Nuclear Regulatory Commission<br />
RCRA ---_tespur^&_C=ser-vaLior. -and-Ttecevery Act<br />
RH remote handled<br />
RMW radioactive mixed waste<br />
TCLP Toxicity Characteristic Leaching Procedure<br />
UE&C United Engineers and Constructors, Inc.<br />
WFQ Waste Form Qualification<br />
WHC Westinghouse <strong>Hanford</strong> Company<br />
WRAP Waste Receiving and Processing<br />
ix
WHC-SD-W100-TI-003 Rev. 0<br />
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x
WHC-SD-W100-TI-003 Rev. 0<br />
WASTE RECEIVING AND PROCESSING MODULE 2A<br />
WASTE FORM QUALIFICATION<br />
STATUS REPORT<br />
1.0 INTRODUCTION<br />
_This-repart-provides a status of the waste form testing work being<br />
performed in support of Waste Receiving and Processing ( WRAP) Facility,<br />
Module 2A. The WRAP 2A will provide treatment-required to properly dispose of<br />
inorganic contact-handled ( CH) mixed low-level waste ( MLLW) ( CH-MLLW). It has<br />
been determined that solidification/stabilization is the appropriate treatment<br />
for this waste to reduce its toxicity and mobility in the disposal site. This<br />
work is intended to test various solidification media to confirm the baseline<br />
technologies selected for the WRAP 2A.<br />
The testing used a phased approach, consisting of first screening the<br />
compatibility of surrogate wastes with the immobilization media, then<br />
performing detailed physical and chemical tests on laboratory-prepared<br />
surrogate waste forms. This will be followed by testing of surrogate waste<br />
form specimens prepared by full-scale mixing equipment. Details of the test<br />
program can be found in the WRAP Module 2A Waste Form Qualification Plan<br />
(WHC 1993). This report details the testing efforts performed during calendar<br />
year 1992.<br />
The current focus of this test work is to verify the ability of the<br />
immobilization media identified in the WRAP Module 2A Conceptual Design Report<br />
(UE&C 1992) to adequately treat certain waste types. As such, the first<br />
efforts of this testing focus on using two matrices for waste solidification:<br />
cement-based materials and thermosetting polymer resins. Project background,<br />
feedstream overview, and the conceptual design baseline approach are discussed<br />
in the following sections to further clarify the focus of the test work.<br />
1.1 WRAP 2A BACKGROUND<br />
The WRAP Module 2A, provided by Project W-100, is the proposed second<br />
module of the WRAP Facility. This facility will provide treatment for CH-MLLW<br />
to allow its permanent disposal. The treatment process will reduce the<br />
toxicity and mobility of the waste by using nonthermal solidification and<br />
stabilization technologies. The facility will only treat those wastes that<br />
are amenable to this approach. Wastes with regulated levels of organic<br />
contamination that require thermal treatment will be treated at another<br />
facility. The WRAP 2A will be designed to provide the capacity to treat both<br />
the stored waste and the future generated <strong>Hanford</strong> <strong>Site</strong> MLLW. The WRAP 2A is<br />
part of-Mil-estone-M-19-00-in the-Tri-Party Agreement (Ecology, EPA, and<br />
DOE 1992) to begin operation of the second module of WRAP in 1999.<br />
Several<br />
capabilities<br />
<strong>Site</strong>. Table<br />
handle-trans<br />
different facilities will be needed to<br />
required to handle the different solid<br />
1-1 lists the facilities. The WRAP 1<br />
iranic-waste. The waste with the least<br />
1-1<br />
provide all of the<br />
wastes at the <strong>Hanford</strong><br />
is a facility that will<br />
amount of uncertainties,
WHC-SD-W100-TI-003 Rev. 0<br />
best characterization data, and most immediate need 'was determined to be<br />
CH-MLLW. The hazards and technical uncertainties associated with performing<br />
the required thermal treatment for organic wastes would impede the progress of<br />
dealing with inorganic wastes. Hence, organic wastes were deferred to a<br />
ttrermrall facility project scope; and WRAP 2A was initiated as a treatment<br />
-facil-ity--for--inorganic -CH-MLLW- conta-ined -in -drums-or -wast-e boxes.<br />
The WRAP 2B is proposed as a follow-on project to WRAP 2A, which will<br />
provide treatment for remote handled (RH), large, or otherwise noncompliant<br />
waste. The need for WRAP 2B as a separate project is based on the uncertainty<br />
in the characteristics of these waste types, the uncertainty in dispositioning<br />
these waste types, and the inherent design differences between a facility that<br />
handles CH waste and one that handles RH waste.<br />
Table 1-1. <strong>Hanford</strong> <strong>Site</strong> Solid Waste Treatment Facilities.<br />
Project Facility Waste type Line item<br />
W-026 WRAP Module 1 CH-TRU and CH-LLW FY 1991<br />
W-100 WRAP Module 2A Inorganic CH-MLLW FY 1994<br />
W-255 WRAP Module 2B RH and irregular FY 1995<br />
W-242 Thermal treatment Organic LL-MW FY 1996<br />
NOTE: WRAP 2A is scheduled to be operational by 1999.<br />
CH - contact handled.<br />
FY - fiscal year.<br />
LL - low level.<br />
MLLW = mixed low-level waste.<br />
MW - mixed waste.<br />
RH = remote hand l elJl.<br />
TRU - transuranic.<br />
WRAP - Waste Receiving<br />
1.2 WRAP 2A FEEDSTREAM OVERVIEW<br />
and Processing.<br />
The feedstreams for WRAP 2A have been identified by a review of the<br />
records of the_waste that is currently in storage and a survey of the<br />
-- ---^ T tI1rP Y- -r-4 T1.<br />
------ generatQrap.-tu__. -a+as-P-at the^iar+€o.^ S^^^2. The wastes have been broken<br />
into several feedstream categories based on similarity in waste type and<br />
source and the perceived treatability of the wastes by various technologies.<br />
For the purposes of conceptual design for the facility, the wastes have been<br />
grouped into eight major categories and several subcategories. The total<br />
throughput to WRAP 2A is estimated to be on the order of 850 m3 (30,000 ft3)<br />
each year. The feedstreams are described in the following sections.<br />
1-2<br />
,,.<br />
G
WHC-SD-W100-TI-003 Rev. 0<br />
1.2.1 Feedstream 1: 183H Solar Basin Waste<br />
The 183H Solar Evaporation Basins were used to reduce waste by means of<br />
natural evaporation of liquid chemical wastes generated as part of N Reactor<br />
fuel fabrication activities. The liquid waste discharged to the four concrete<br />
basins consisted primarily of spent acid etch solutions (sulfuric, nitric, and<br />
hydrofluoric acids). This waste was neutralized with sodium hydroxide before<br />
--discharge to the basins.--The wastes contained various metallic contaminants.<br />
Several types of nonroutine wastes were also discharged to the basins. The<br />
basins eventually ceased accepting waste and subsequently were found to be<br />
leaking. A timely cleanup and closure of th? basins was then pursued. This<br />
cleanup activity resulted in roughly 2,605 m (92,000 ft) of waste divided<br />
into the four types discussed in the following sections.<br />
1.2.1.1 183H Solidified Liquid. The liquid portion of the waste remaining in<br />
--the-basins--consi-s*.ed-of-slightly radioactively contaminated (uranium and<br />
9::V technetium) saturated sodium nitrate solution. The liquid was removed from<br />
k..;.° in a<br />
the ..,,^ Uo.,1114 1 ^^ „rums and solidified ( in the drums) with,a product called<br />
^e^..„cnd s^ ^_ LPC-iI: An-absorbant was adaed^ -on-top o# t^ne soiidified waste.<br />
Several problems with the-sofiidification, including swelling and cracking of<br />
c:v; the waste form and incomplete solidification, has lead to the decision that<br />
--th4_waste must tte-retr-eated-in_WRAP-2A.-Tha th oughput of this waste to<br />
WRAP 2A is estimated to be around 23 ms (800 ft^) each year.<br />
^4y<br />
1.2.1.2 183H Crystalline Solid. The evaporation of the liquid waste also<br />
produced a crystalline solid consisting mostly of salts of nitrate, sulfate,<br />
fluoride, and sodium. These wastes were removed from the basins and packaged<br />
in 2j8-L ( 55-ga31) drums without further treatment. They account for about<br />
37 m (1,300 ft ) each year throughput to WRAP 2A.<br />
1.2.1.3 183H Sludge. The remaining fraction of waste in the 183H basins was<br />
a sludge like material consisting of a mixture of mostly sodium sulfate and<br />
sodium nitrate. This fraction was also relatively high in copper content and<br />
had more apparent water content than the other wastes (thus its sludge-like<br />
consistency). The sludge was packageg in drums yith an absorbent material but<br />
had no further treatment. About 40 m (1,400 ft ) each year of this waste is<br />
planned to be treated at WRAP 2A.<br />
1.2.1.4 183H Miscellaneous Cleanup. After removal of the waste from the<br />
basins, contamination remained on the concrete floors and walls. These areas<br />
were sandblasted to remove this contamination, resulting in another waste<br />
form. Also, tumbleweeds and various tools and structures used in the cleanup<br />
operation were packaged as additional waste. The sandplast grit and other<br />
cleanup debris account for an additional 11 m3 (400 ft ) each year throughput<br />
to WRAP 2A.<br />
'Sorbond is a trademark of the American Colloid Company.<br />
1-3
WHC-SD-W100-TI-003 Rev. 0<br />
1.2.2 Feedstream 2: Liquid Effluent Treatment<br />
Facilities Secondary Solids<br />
Two Liquid Effluent Treatment Facilities (LETF) are planned for<br />
construction at the <strong>Hanford</strong> <strong>Site</strong> in the near future. The C-018 Facility in<br />
the 200 East Area will treat evaporator condensate from selected double-shell<br />
tanks and-wi11_begin operation in 1995, The L-045 Facility will be<br />
constructed at the <strong>Hanford</strong> <strong>Site</strong>'s 300 Area and will treat the combined sewer<br />
effluents from various laboratory buildings. It will also begin operation in<br />
1995. Both facilities will produce several secondary waste streams that may<br />
be both radiologically and chemically hazardous. It is assumed that these<br />
streams will require treatment to meet federal and state land disposal<br />
regulations.<br />
1.2.2.1 Ammonium Sulfate. The major secondary waste from the C-018 process<br />
-vil} -i€ an ammonium sulfate salt produced in an evaporative crystallization<br />
process. The high ammonia content of many of the double-shell tanks and the<br />
addition of sulfuric acid in the C-018 process leads to the formation of<br />
ammonium sulfate. This waste stream will be generally
^s.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
contaminated with hazardous chemicals and are radioactive. Such debris could<br />
result from cleanup or construction work performed'`in contaminated areas. It<br />
is assumed that these wastes will have low levels of contamination and would<br />
be easily size reduced for compatibility with immobilization. Much of this<br />
waste will need to be dealt with on a case-by-case basis as it is generated in<br />
rela ively small quantities from various sources. This waste will add about<br />
59 m^ (2,100 ft3) each year of throughput to the WRAP 2A Facility.<br />
1.2.4 Feedstream 4: Noncompactible Solids<br />
Noncompactible solids will come from similar sources as compactible<br />
solids but will consist of hard debris, such als metal piping, ng, brick, concrete<br />
or glass. It will account for as much as 34 m (1,200 ft ) each year of<br />
throughput to WRAP 2A.<br />
1.2.5 Feedstream 5: Metals<br />
:-, This feedstream has been subgrouped into three categories. It consists<br />
of both currently stored and future generated wastes that contain metals that<br />
are--knnwn to -rPqyire P 1 ^<br />
- C_p..^i-a>--handT:ng--o M or treatment bgF .are o„^r a s par t „ wC<br />
, .<br />
^ the<br />
immobilization process. These are generally small volume waste streams that<br />
will not be treated in the main process line at WRAP 2A. The subcategories<br />
are discussed in the following sections.<br />
1.2.5.1 Mercury/Mercury Contaminated Solids. This waste consists of<br />
elemental mercury and bulk contaminated solid wastes, such as fluorescent<br />
light bulbs, laboratory thermometers, manometers, and mercury absorbents.<br />
Elemental mercury will be treated in accordance with Best Demonstrated<br />
Achievable Technology (BDAT), which requires amalgamation. Bulk contaminated<br />
solids will be shredded and residual mercury metal removed as required by<br />
BDAT.<br />
1.2.5.2 Reactive Metals. This stream contains zirconium and beryllium, which<br />
are easily ignited or oxidized in air if the particle size is fine enough and<br />
an ignition source is available. It is assumed that 50 wt% of the total<br />
incoming feedstream must be deactivated by pretreatment before encapsulation;<br />
the rest will require no pretreatment before encapsulation. No distinction is<br />
made between zirconium or beryllium metals for treatment requirements. It is<br />
assumed that no other reactive metals, such as sodium, potassium, or calcium,<br />
are present in this feedstream. These react_ive metals would require entirely<br />
different treatment techniques because of their reactive properties.<br />
___L 2.5_3__Lead/Lead_Contaminated-Sol!ds.Th-ts-feedstream consists of le'ad<br />
and lead contaminated bulk solids. Elemental lead will be treated in<br />
accordance with BDAT, which requires macroencapsulation. Bulk contaminated<br />
solids will_beshredded befnre encansulatinn<br />
1-5
WHC-SD-W100-TI-003 Rev. 0<br />
1.2.6 Feedstream 6: Absorbed Chemicals/<br />
Solidified Liquids<br />
This waste consists of both currently stored and future generated waste.<br />
It includes things, such as regulated chemicals absorbed on rags or liquid waste<br />
absorbed on other absorbents, such as vermiculite. This waste stream will<br />
consist -o€-very -small-lots-of simfilar-wastes.-- This is-due to the fact that this<br />
stream will be generated, as with the compactible and noncompactible solids,<br />
as part of isolated operations at various generatin sites. T^e throughput of<br />
this waste to WRAP 2A is estimated to be about 48 m^ ( 1,700 ft ) each year.<br />
1.2.7 Feedstream 7: Ash From Thermal Treatment<br />
This waste will be produced by the proposed thermal treatment facility<br />
for organic mixed waste. The ash residue from this process may need to be<br />
treated to account for residual contamination in the waste or to meet BDAT<br />
treatment standards for mixtures of waste types ( i.e., a waste may contain a<br />
mixture of waste types in which one type requires thermal treatment and the<br />
other requires immobilizajtion). The generation of this waste is estimated to<br />
add about 65 m3 (2,300 ft ) each year to the throughput of WRAP 2A.<br />
1.2.8 Feedstream 8: Contaminated Soils<br />
= This waste consists of both currently stored and future generated contaminated<br />
soils. Similar to some of the other wastes, it will mostly be generated<br />
from isolated operations, such as the excavation of soils in contaminated zones<br />
for construction or remediation. As such, most of this waste will bein small<br />
lots and handled on a case-by-case ba^is. The throughput of this waste to<br />
1WRAP-2A is estimated to be about 20 m' (700 ft') each year.<br />
1.3 WRAP 2A CONCEPTUAL DESIGN BASELINE APPROACH<br />
The aforementioned feedstreams represent a broad variety of wastes both<br />
in-physical f.3riTi and i.iieiTiiL'i ^T^akeup. All of the wastes, however, require<br />
some form of immobilization treatment before disposal. The selection of a<br />
dual technologyprocess approach is documentedin-theKRAP-?preconceptua7<br />
Design Additional Follow-On Activities Report ( UE&C 1992b). In this approach<br />
a standardcement-based--soli-di -ic ation--syst-em-wou-ld-be emrl-oyed-to process the<br />
bulk of the waste, and a more sophisticated system would be employed to handle<br />
those wastes that were not amenable to cementation. This approach is expected<br />
to eliminate the various pretreatment operations that would be required to<br />
make all wastes amenable to a single technology approach.<br />
The cement-based system uses relatively inexpensive materials and simple<br />
processing systems. This would be the method of choice for the bulk of the<br />
----- ---wast€-.----The secondary--systger was thostirr to use a-thermosetting polymer system.<br />
This technology was chosen because of the high degree of confidence in this<br />
waste form to immobilize wastes that were identified to cause problems with<br />
cement. This technology also represents a conservative approach for<br />
conceptual design cost estimation in that it represents a level of equipment<br />
complexitythat is unlikely to be surpassed by alternative technologies.<br />
1-6
__-'°'2<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Both process lines will use "in-drum" mixing techniques consisting of<br />
both agitated drum and vibrating drum systems. Agitated mixing will be used<br />
for sludges, powders, and particulate wastes. These wastes will be processed<br />
through a pug mill and measured into 208-L (55-gal) drums with installed<br />
agitators before movement to the solidification systems. The drums will then<br />
be coupled to an agitator drive and fill station. The stabilization agents<br />
are then added and mixing begins. When mixing is complete the drum is removed<br />
from the fill station with the agitator remaining in the drum. The drum is<br />
then inspected and capped for movement to the curing storage area. The<br />
vibrating drum system will be used for debris wastes that have been size<br />
reduced by shredders. The operation is similar to the agitated system except<br />
the drum is vibrated to achieve the required mixing, and no agitator is<br />
involved.<br />
The baseline approach for the cement-based system offers the capability<br />
to blend portland cements with various pozzolonic additives, including blast<br />
^ furnace slag, pulverized fly ash, and other dry mixtures, as well as small<br />
y; quantities of specialized additives. The system will allow tailoring the<br />
--_fQrmul-a ona Tot-by-let or-a -drum-by-dr;.1m basis. The agitated grout line will<br />
add the necessary water to the drum, followed by preblended dry materials.<br />
- _; The initial addition of water is to ensure that the waste is easily before the<br />
powders are added. The vibrated grout line will preblend the water and dry<br />
= materials before charging the drum.<br />
Y:S1<br />
The thermosetting polymer system uses several components to achieve<br />
solidification: a vinyl ester-based liquid resin, a promoter, a catalyst, and<br />
an extender. The resin, promoter, and extender are premixed in a day storage<br />
---tank. In the agitated polymer system, this mix is charged to the waste loaded<br />
drum and mixing begins. The catalyst is then added to the mix and the<br />
polymerization reaction begins. Mixing is then stopped and the drum allowed<br />
to cure. As with the cement side, the mixer is left in the drum and the drum<br />
is capped and removed from the station. On the vibrated polymer system, the<br />
promoter, catalyst, and extender are premixed, as on the agitated side. The<br />
catalyst is then mixed in line with this mixture as it is charged to the drum.<br />
The drum is then agitated to achieve proper distribution of the polymer into<br />
the void spaces.<br />
Drum curing storage, inspection, and monitoring, are also required as<br />
part of these systems; however, the details are still under development.<br />
The overall process philosophy for WRAP 2A is that drums of waste will be<br />
------- --&aracter-i-zed-and-group°cd into lots of similar waste before<br />
facility. The WRAP 2A will perform verification testing to<br />
receipt at the<br />
confirm the<br />
--identi-ty-af +_he--incaring-waste lots.-- The-waste-will-then be- ;rze --reduced-in<br />
shredder or homogenized in a pug mill to make the waste suitable for<br />
solidification. The waste will then be premeasured into drums for<br />
solidification. After the drums have cured and been inspected they will be<br />
transferred out of the WRAP 2A Facility for final disposal.<br />
a<br />
Table 1-2 illustrates the proposed conceptual design split as to which<br />
technology will be used for the various feedstreams. This split is reflected<br />
in the approach used in the test work described in this report.<br />
1-7
Waste source Waste type<br />
Sorbomd' liquids Sodium nitrate<br />
Table 1-2. WRAP 2A Design Ba sis Summary.<br />
ilajor chemical species<br />
Projected<br />
total<br />
o f concern i nven or<br />
(ft)<br />
®®<br />
Anhual<br />
Annual<br />
feed<br />
Treatment<br />
th<br />
production<br />
`f 1put<br />
l,<br />
process outpu t<br />
(drums)<br />
183-H Solar<br />
Evaporation<br />
Crysta!lline solibds Sodium sulfate 87,912 3,525 Polymer 999<br />
Basins<br />
(in storage)<br />
Sludge<br />
----<br />
^---_...----<br />
Miscel---l-ane--ous<br />
cleanup<br />
Copper sulfate!<br />
----------------- ------------<br />
Contaminated debris<br />
------------<br />
9,471<br />
---°--------<br />
385<br />
------- -<br />
Grout<br />
----------<br />
53<br />
C-018 evaporator<br />
salt cake<br />
Ammonium sulfate<br />
Liquid Effluent<br />
Treatment Ion exchange resins Nitrates and<br />
277,000 12,600 Pol;ymer 3,288<br />
Facilities<br />
(forecast)<br />
------- -----------------<br />
L-045 metal sludge<br />
radionuclides<br />
------------------------------<br />
Heavy metal hydroxides<br />
RO filter elements Contaminated debris<br />
Dry active waste<br />
Operations<br />
fins orectorage<br />
Construction debris<br />
and<br />
ast)<br />
---- -- --------- --- --<br />
Metal wast^es -<br />
---------- -••--- -----<br />
Absorbed chemicals<br />
Thermal<br />
Treatment<br />
Facility<br />
Incinerator ash<br />
(forecast)<br />
-----------------<br />
Retrieval<br />
(forecast)<br />
---------------------<br />
Contaminated soils<br />
------------ -------------- ------ ---- ---------<br />
75,000 3,400 Grout 873<br />
Contaminated debris 65,100 3,255 Grout 443<br />
_ -<br />
^----`<br />
------------------- ---- ----<br />
2<br />
------------<br />
Lead, mercury, reactives 21,500 Warie;z ol rmer Varies<br />
----------------------------- - ------------ --------- --_ ------------ -<br />
Inorganics and heavy<br />
34,000<br />
1,701)<br />
metals<br />
Polymer<br />
- ------- '-_-_-<br />
495<br />
Heavy metals 59,600 2,980 Grout 809<br />
'Sorbond is a trademark of American Colloid Company.<br />
zMetal waste is campaigned. Throughput varies with campaign length and waste volume.<br />
r..<br />
;?<br />
x<br />
y<br />
E<br />
0<br />
_i<br />
5• 00w<br />
m<br />
<<br />
0
2.1 REGULATORY FRAMEWORK<br />
WHC-SD-W100-TI-003 Rev. 0<br />
2."0 WASTE FORM PERFORMANCE SPECIFICATIONS<br />
The purpose of WRAP 2A is to manage CH-MLLW by treating it in such a way<br />
as to produce a final waste form that meets all applicable, relevant, and<br />
appropriate regulations and ensures its suitability for land disposal in the<br />
mixed waste disposal trench at the <strong>Hanford</strong> <strong>Site</strong>. The regulations that apply<br />
to radioactive mixed waste (RMW) come from three main sources.<br />
2.1.1 Federal Regulations<br />
The federal regulations regarding disposal of RMW can be divided into two<br />
categories. The first set of regulations is concerned with the radioactive<br />
c^ portion of the waste and is embodied in 10 CFR 61 (NRC 1992). These<br />
regulations establish technical requirements for the land disposal of<br />
tommrrcial l-ow-levei waste, including site selection, site design, facility<br />
operation, and closure. Although not legally required, these regulations have<br />
y== been used for guiaance. The second set of regulations was promulgated after<br />
passage of the Resource Conservation and Recovery Act of 1976 (RCRA) and is<br />
>y, concerned with the chemical hazards of the waste, embodied in 40 CFR 261-268<br />
(EPA 1992). These regulations establish minimum standards for packaging,<br />
labeling, record keeping, and reporting for all generators, transporters,<br />
owners, and operators of hazardous waste treatment, storage, and disposal<br />
facilities. They also impose restrictions on land disposal of hazardous waste<br />
and identify acceptable treatment technologies that can be used to meet the<br />
land disposal restrictions.<br />
2.2.2 State of Washington<br />
The State of Washington has established regulations that are applicable<br />
to RMW through the Washington Administrative Code, WAC-173-303. These<br />
regulations overlap the federal RCRA regulations but include some additional<br />
requirements for management of dangerous and hazardous wastes.<br />
2.2.3 <strong>Hanford</strong> <strong>Site</strong> Solid Waste Acceptance Criteria<br />
The <strong>Hanford</strong> <strong>Site</strong> Solid Waste Acceptance Criteria, WHC-EP-0063-3<br />
(WHC 1991), includes additional reporting requirements and limitations on<br />
radionuclide content of low-level waste ( LLW) and RMW to be disposed of at the<br />
<strong>Hanford</strong> <strong>Site</strong>. These requirements are based on U.S. Department of Energy (DOE)<br />
Orders 5820.2A ( DOE 1988) and 5400.3 ( DOE 1989) and will include requirements<br />
-------- -- imposed-by--performance-assessments of the disposai grounds.<br />
2.2 PROGRAMMATIC AND FUNCTIONAL REQUIREMENTS<br />
The WRAP 2A Facility will serve to treat all inorganic CH-MLLW received<br />
by the <strong>Hanford</strong> Central Waste Complex. Major waste streams that have been<br />
identified for treatment in WRAP 2A contain oxidizers, corrosives, toxic heavy<br />
2-1
WHC-SD-W100-TI-003 Rev. 0<br />
metals, soluble salts, and reactive metals. TheAphysical characteristics<br />
range from semiliquid sludges and salt cake to dry powders, ash, soils, and<br />
contaminated debris.<br />
The wide variety of chemical and physical characteristics expected in<br />
WRAP 2A feedstreams precludes the use of a single immobilization technology<br />
for all waste types. The desire to minimize operating costs suggests the use<br />
of cement-based binders whenever possible. However, several feedstreams are<br />
known to be incompatible with cement-based materials, so a second technology<br />
is required. The objective of this approach is to provide two immobilization<br />
technologies that together can successfully treat all known and anticipated<br />
WRAP 2A feedstreams.<br />
The conceptual design of WRAP Module 2A thus includes two immobilization<br />
process trains: a cement-based grouting train and a vinyl ester styrene<br />
,-; polymer train. Both systems provide the capability to mix binder and waste<br />
either-in the waste drum or use a vibratory mixing technique. Additionally,<br />
the design of the grout system includes the flexibility to allow use of<br />
multiple formulations of inorganic binders, ( i.e., portland cement, slag<br />
cement, or gypsum cement). The available combination of technologies is<br />
--; expected to be able to successfully treat all WRAP 2A feeds.<br />
2.3 TEST SELECTION AND ACCEPTANCE CRITERIA<br />
The WRAP 2A waste forms are subject to rules and regulations promulgated<br />
by several entities. Primary performance requirements are described in<br />
U.S. Environmental Protection Agency (EPA) regulations, Washington<br />
Administrative Code, and DOE orders. Other applicable guidance comes from the<br />
<strong>Hanford</strong> <strong>Site</strong> So1id Waste Acceptance Criteria (WHC 1991) and U.S. Nuclear<br />
Aegul-atory^u^t,s^ic^t (NRC) re-yulations. Since there is no single regulation<br />
or guidance document that contains all applicable performance requirements and<br />
some discrepancies exist between similar requirements in different<br />
regulations, the WRAP 2A WFQ program has developed project-specific waste form<br />
performance specifications that ensure that waste forms that meet the<br />
specifications will also be compliant with all applicable regulatory<br />
requirements and guidance documents. The WRAP 2A waste form performance<br />
soer;fications- are-summartzed in-?abl-s--2-I: The following sections describe<br />
aV-<br />
-- -- -- -- the t..^$ a_lf^r"lan re£}S.S _&pe^. } . fl . ^ f3r WD11D "n ....`t ° r.,"__ :<br />
a^.,,r Gn wa^6e r^ruu in uL d. all<br />
2.3.1 Compressive Strength<br />
T!}e-neaszrement of the compressive strength is the key method of<br />
determining the stability and structural integrity of the waste form. The<br />
need for adequate compressive strength is a result of the desire to control<br />
subsidence in the disposal grounds, thus requiring the waste form to be able<br />
to withstand the full pressure of the overburden after it is buried.<br />
The most stringent compressive strength requirements are based on NRC<br />
requirements in 10 CFR 61 (NRC 1992) for shallow land disposal of Class B and<br />
Class C LLW. There are presently two NRC standards, depending on the nature<br />
of the matrix. For cementitious matrices, the minimum acceptable compressive<br />
2-2
^..."<br />
;_:..<br />
:.^<br />
.^.y^<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Table 2-1. WRAP 2A Waste Form Performance Specifications.<br />
Waste form characteristic Test method Acceptance criteria<br />
Compressive strength orTASTMM 5<br />
Strength >500 lbf/in2<br />
Leachability index ANS 16.1 Leach Index >6<br />
Biodegradation<br />
ASTM G21 and<br />
ASTM D695<br />
or ASTM C39<br />
G22,<br />
Thermal cycling<br />
Radiation stability<br />
Immersion<br />
No growth,<br />
Strength >500 lbf/in 2<br />
ASTM<br />
ASTM D695, Strength >500 lbf/inZ after<br />
30 thermal cycles<br />
or ASTM C39<br />
ASTM D695 Strength >500 lbfjinz after<br />
or ASTM C39 irradiation to 10 rad<br />
ASTM 0695 Strength >500 lbf/in 2 after<br />
or ASTM C39 90-day water immersion<br />
Free liquids ANS 55.1 Free liquid
WHC-SD-W100-TI-003 Rev. 0<br />
to support 10 CFR 61 (NRC 1992) radioactive waste disposal regulations. The<br />
WRAP 2A performance specification of a minimum leach index of 6.0 for all<br />
waste forms is the same as the NRC requirements.<br />
Leachate characteristics will also be analyzed and compared with the<br />
design basis for performance modeling-of the mixed waste disposal facility to<br />
ensure that the performance of the liner leachate collection system will not<br />
be compromised. Leachate aggressiveness shall be less than that used for<br />
EPA 9090 performance testing of the W-025 disposal trench liner system.<br />
2.3.3 Biodegradation<br />
The long-term durability of waste forms can be adversely affected if they<br />
are susceptible to microbial degradation. Therefore, the waste form specimens<br />
are tested for resistance to fungal growth ( ASTM G21)-and bacterial growth<br />
(ASTM G22). -The-'tests provide ideal conditions for microbial growth, such as<br />
proper moisture, temperature, and nutrients. After 21 days of incubation, the<br />
specimen is inspected for growth and tested for compressive strength. The<br />
.., WRAP 2A performance specification is for ng observable microbial growth and a<br />
minimum-compressive strength of 5J00 ibf/in following the test.<br />
2.3.4 Thermal Cycling<br />
Thermal cycle testing is used to determine the durability of the waste<br />
form when exposed to extremes of temperature that may be experienced during<br />
storage, transportation, or disposal. The standard method for thermal cycling<br />
is ASTM B-553, which involves exposing the test specimen to temperature<br />
extremes of -40 °C to +60 °C (-40 OF to 140 °F) for a total of 30 five-hour<br />
periods. After cyiling, the compressive strength must continue to meet the<br />
minimum 500 lbf/in performance specification requirement.<br />
2.3.5 Radiation Stability<br />
Exposure of waste matrices to radiation can cause chemical changes in the<br />
molecuiar structure, such as-radiolysis or crosslinking, which can in turn<br />
affect the physical properties of the material. Therefore, 10 CFR 61<br />
(NRC 1992) regulations-require that the waste form be tested to determine the<br />
effects that long-term exposure to radiation may have on the Vaste form. The<br />
t!RAP 2A-perfor„^aner syeci^icati-n cr is for<br />
strength after exposure to a total gamma<br />
NRC regulations.<br />
a minimum *06 ibfjin` compressive<br />
dose of 10 radiation, as required by<br />
2.3.6 Water Immersion<br />
Waste forms in the shallow land disposal environment will inevitably be<br />
exposed to moisture. Depending on the type of waste and the immobilization<br />
matrix, exposure to moisture can cause swelling, cracking, and other adverse<br />
__--_---changes in__tha -waste formr- To e.n.sure adequ ate performance under these<br />
conditions, the waste form specimens are immersed in water for 90 days, after<br />
2-4<br />
x<br />
^
WHC-SD-W100-TI-003 Rev. 0<br />
which the compressive strength is measured to determine the effects of the<br />
exposure. The WRAP 2A performance specification is fo r a minimum compressive<br />
strength of 500 lbf/inZ following the 90-day immersion period.<br />
2.3.7 Free Liquids<br />
The regulations in 10 CFR 61 (NRC 1992) and DOE Order 5820.2A (DOE 1988)<br />
prohibit the disposal of liquid ?ow-level waste and require that all<br />
solidified liquids contain no more than 0.5% by volume of free liquids. The<br />
ANS 55.1 Standard is the accepted method for determination of the amount of<br />
free liquids in a waste form. The WRAP 2A waste form performance<br />
specifications also require that the waste form have no more than 0.5% free<br />
liquids.<br />
2.3.8 Hazardous Characteristics<br />
The RCRA land disposal restriction regulations ( 40 CFR 268 [EPA 1992])<br />
prohibit land disposal of any waste that exhibits a hazardous characteristic.<br />
The four hazardous waste characteristics are ignitibility, corrosivity,<br />
reactivity, and toxicity. The tests used for determination of these<br />
characteristics depend on the physical properties of the waste but generally<br />
involve measurement of the flash point or autoignition point, the pH of the<br />
waste or waste extract, and comparisons against reference oxidizing materials.<br />
The toxicity characteristic is determined by using EPA Method 1311,<br />
,_. Toxicity Characteristic Leaching Procedure (TCLP), to obtain an extract from<br />
the waste form and by analyzing the extract for toxic constituents. The<br />
WRAP 2A performance specification requires that the maximum allowable<br />
concentrationsfor wasteform_TCLPextracts-be-below the limits stated in<br />
40 CFR 268.41, Table CCWE.<br />
2-5
WHC-SD-WIOO-TI-003 Rev. 0<br />
This page intentionally left blank.<br />
2-6<br />
^<br />
^
kIHC-S^u-Wi"v"u-Ti-u03 Rev. V<br />
,--,, 3.0 TESTING SCOPE AND DESCRIPTION<br />
The current focus of this test work is to verify the ability of various<br />
immobilization media to adequately solidify the waste feedstreams identified<br />
€or-WRAP--2A----The-base}}ne-destgn--as provid'd in the conceptual design for<br />
this facility was used as guidance in selecting which technologies should be<br />
applied for testing ( i.e., thermosetting polymer and cement based immobilization<br />
matrices). The following sections describe the logic in selecting the<br />
waste types and waste forms for testing, as well as a description of the<br />
testing approach. Detailed test plans are provided in the Appendixes A, B,<br />
and C.<br />
1 i erIrrrrnu ... • vc&co 1av^^ OF vr WASTE TYPES FOR TESTING<br />
Because of the lack of definition for some of the feedstreams identified<br />
for WRAP 2A, not all streams have been addressed in this initial testing<br />
phase. Instead, the approach taken was to address the large volume<br />
feedstreams that would have the greatest impact on facility design. These<br />
include 183H Basin Waste, LETF Secondary Solids (C-018 and L-045), and ash<br />
from thermal treatment. Together these represent the majority of the total<br />
feed to WRAP 2A. Certain other feedstreams, such as ion exchange resins and<br />
elemental lead, were not chosen for this testing phase because successful<br />
treatment of these streams has been sufficiently demonstrated commercially.<br />
The other smaller feedstreams for WRAP 2A will be tested at a later date.<br />
The specific waste types selected for this phase of testing are shown in<br />
Table 3-1.<br />
Feedstream<br />
number<br />
(test ID)<br />
Table 3-1. Initial Testing Phase of Large Volume Feedstreams.<br />
2A (Type 1) C-018 Ammonium sulfate<br />
1C (Type 2) 183H Sludge ( Basins 1 and 2)<br />
1C (Type 3) 183H Sludge ( Basins 3 and 4)<br />
lA (Type 4) 183H Crystalline solid<br />
1D (Type 5)<br />
183H Miscellaneous cleanup<br />
copper])<br />
Feedstream title<br />
(contaminated sandblast grit [high<br />
1D (Type 6) 183H Miscellaneous cleanup (sandblast grit [high nitrate])<br />
2C (Type 7) L-045 Metal sludge<br />
7 (Type 8) Ash from thermal treatment<br />
3-1
z.-<br />
^:-<br />
0<br />
- -- WHC-SU-riiVV I1-VVJ RCV.<br />
Surrogates were based on anticipated waste feedstreams: Characterization data<br />
for these wastes have been compiled (Appendix Q. Based on this data,<br />
surrogate recipes were prepared and are documented in Appendix F.<br />
-3-.-2 -3ELECTION OF WASTE FORMS FOR TESTING<br />
Vendor contacts, literature reviews ( Appendix G), and discussions with<br />
specialists in the field of nuclear waste solidification have led to the<br />
selection of the various waste forms chosen for testing in this phase of the<br />
WFQ Program. An overall discussion of the various waste forms, their<br />
-advantages and disadvantages, a description of the equipment needed for the<br />
various processes, and other pertinent terminology are provided in Appendix J.<br />
The waste forms chosen, as mentioned earlier, consist of cement-based waste<br />
forms and a thermosetting polymer waste form. The overall analysis of the<br />
-informat-ion _gathered-has led to the selection of which waste types should be<br />
tested in which of the above two waste forms. This selection is similar to<br />
the selection provided in the CDR for the project and is provided in<br />
Table 3-2.<br />
Table 3-2. Solidification Technologies.<br />
Feedstream Cement- Thermosetting<br />
number Title based polymer<br />
(test ID) testing testing<br />
2A (Type 1) C-018 Ammonium sulfate Yes* Yes<br />
IC (Type 2) 183H Sludge (Basins 1 and 2) -- Yes<br />
1C (Type 3) 183H Sludge (Basins 3 and 4) -- Yes<br />
1A (Type 4) 183H Crystalline solid -- Yes<br />
1D (Type 5)<br />
1D (Type 6)<br />
183H Miscellaneous cleanup<br />
(high copper)<br />
183H Miscellaneous cleanup<br />
(high nitrate)<br />
Yes --<br />
Yes --<br />
2C (Type 7) L-045 Metal sludge Yes --<br />
7 (Type 8) Ash from thermal treatment Yes --<br />
*Envirostone is a trademark of the United States Gypsum Company.<br />
The first four waste types were chosen for testing with the thermosetting<br />
polymer because of their high soluble salt content (including high nitrate<br />
content), which are known to cause problems with cement solidification. The<br />
last four waste types (5-8) were chosen for testing with cement waste forms<br />
because they did not contain high concentrations of any constituents that<br />
interfere with cement solidification.<br />
3-2
WHC-SD-W100-TI-003 Rev. 0<br />
Type 1 waste demonstrates a special problem with cement in that the<br />
' acidic nature of the ammonium sulfate would react with the pH solytions in<br />
ordinary portland cement, thus evolving ammonia gas. Envirostone was<br />
selected as an alternative to ordinary portland cement for this waste stream.<br />
This is a gypsum-based cement, which exhibits a neutral pH. Using Envirostone<br />
would be similar to using an ordinary cement and would not require additional<br />
equipment ( i.e., this process could use the same equipment as the cement<br />
solidification system). Also, if successful, its use may provide a<br />
substantial cost savings over polymer for this large volume waste stream.<br />
The actual formulations, chemicals, and waste loadings to be used in the<br />
thermosetting polymer test work were developed by the vendor ( Stock Equipment<br />
Company of Chagrin Falls, Ohio) and are included in the test reports on this<br />
phase of work contained in the Appendix F and Section 4.22.<br />
The formulations for the cement solidification testing have been<br />
developed by Westinghouse <strong>Hanford</strong> Company (WHC) personnel and the test work<br />
was performed onsite at the <strong>Hanford</strong> <strong>Site</strong> by WHC. The selection of cement<br />
^ type, the general composition used, and the target waste loadings for the five<br />
wastes are given in Table 3-3.<br />
3,^ 1<br />
- - r... -<br />
Portland cement type III was selected for Grit 1 because the grit<br />
contained_cQpper, wh_ich retards the setting of ordinary portland cement. The<br />
,type III sets fast and achieves a high strength comparatively early. Thus, it<br />
was selected in lieu of the type I or II cement. Also, a quick screening<br />
experiment using slag and type III cement indicated type III cement was<br />
achieving the better set.<br />
The blast furnace slag cement was selected for Grit 2 because the grit<br />
contained a large quantity of nitrate. Based on a literature review, the slag<br />
cement contains the nitrate better than the portland cements. The slag cement<br />
produced a good product in a laboratory screening experiment and, thus, was<br />
selected for testing.<br />
Portland cement type III was selected for the ferric oxide mix because<br />
the iron acts similar to copper and interferes with the cement set. The fast<br />
Set4f_Lhetype_III-minimizes the aat-ratarriinn offects.<br />
Slag cement was selected for incinerator ash because of its good<br />
retention properties. It is expected to retain the chemical and radionuclide<br />
wL.. .<br />
better th an<br />
a^ ^<br />
------ ^ YCItCr ^nportiiana cement.<br />
As mentioned earlier, Envirostone is a gypsum cement, which was selected<br />
for solidifying the stabilized evaporator residues because of the large<br />
quantity of ammonium sulfate. Portland cement slurry matrices are strongly<br />
basic exhibiting pHs characteristically around 12 and 13.<br />
ZEnvirostone is a trademark of the United States Gypsum Company.<br />
3-3
WHC-SD-W100-TI-003 Rev. 0<br />
Table 3-3. Formulations for Cement Sol,.idification Testing.<br />
Type General composition<br />
Portland Cement Type III Solidifier<br />
-4,2%- -Basan-l-skudge--powder<br />
5 37.5% Grit (garnet)<br />
41.6% Portland cement type III<br />
16.7% Water<br />
Blast Furnace Slag Cement Solidifier<br />
4.2% Basin 4 crystal powder<br />
37.5% Grit (garnet)<br />
6 37.5% Slag cement<br />
4.2% Portland cement type III<br />
16.7% Water<br />
Portiand Cement Type III Solidifier<br />
15.4% Ferric oxide mix<br />
7 46.2% Portland cement type III<br />
3V.5% Wal+.er<br />
Blast Furnace Slag Cement Solidifier<br />
30.0% Ash mix<br />
8 40.5% Slag cement<br />
4.5% Portland cement type III<br />
25.0% Water<br />
Envirostone* Solidifier<br />
11.5% Ai:^ionlum sulfat°c mix<br />
1.1% Citric acid<br />
1.1% Sodium bicarbonate<br />
28.7% Water<br />
57.5% Envirostone<br />
NOTE: T he ammonium sulfate mix that was used in the<br />
experiment was dry. The C-018 ammonium sulfate feedstream<br />
would normally be an aqueous liquid, and the waste loading of<br />
60% to 70% would be expected.<br />
*Envirostone is a trademark of the United Sta'tes_G.vosum<br />
Company.<br />
This strongly basic liquid will cause the ammonium sulfate salt to hydrolyze<br />
to ammonium hydroxide leading to the generation of ammonia gas. The gypsum<br />
(plaster of paris) slurry matrix is neutral, exhibiting a pH of 6 to 7. The<br />
ammonium sulfate is stable in the neutral matrix, no appreciable ammonium<br />
hydroxide is generated and, therefore, no ammonia gas is released.<br />
3-4
3.3 TESTING APPROACH<br />
WHC-SD-W100-TI-003 Rev. 0<br />
The WFQ test work is directed toward three goals. First, suitable<br />
formulations that can produce waste forms meeting all performance<br />
specifications and regulatory requirements must be developed. Second, the<br />
in-drum mixing process must be developed to determine the effect the mixing<br />
process has on waste form performance and to evaluate the ability of the<br />
mixing process to achieve the required process objectives. Third, hot testing<br />
------- ---- +xill--deronstrate-the-tmmo'silizatioA-;,rocesses on actual WRAP 2A feedstreams<br />
for verification of results obtained with waste surrogates. Figure 3-1<br />
depicts the strategy for the WFQ program.<br />
The objectives of the WFQ programare to_c9nfi-m irhe technical basis for<br />
the process design by demonstrating successful MLLW immobilization<br />
r`ormulations and mixing processes. A further objective is to gather the data<br />
needed for support of detailed facility design and regulatory permitting<br />
^>rt efforts and to develop baseline process control parameters for use in<br />
. ' preparing operating procedures for the WRAP 2A immobilization systems.<br />
The test results reported in this status report have been focused on<br />
formulation development efforts. Screening tests and performance testing have<br />
=`= been performed on surrogate waste forms representing 80% of the design basis<br />
feed volume. Future testing, described in detail in Section 5.3 of this<br />
0°'1 report, will be directed toward mixing process demonstration and optimization<br />
of the formulations and immobilization processes.<br />
^:^...<br />
A brief description of the major objectives of the WFQ program and the<br />
interfaces between WFQ and other key project activities is presented in the<br />
following text. Figure 3-2 presents a logic diagram outlining the test<br />
-program and the flow-3f iPf"rmation between the various project activities<br />
relating to the WFQ program.<br />
3.3.1 Confirm Process Design<br />
Confirmation of the immobilization systems process design is the primary<br />
objective of the WFQ program. The process design basis will be confirmed when<br />
a successful immobilization formulation has been developed for each feedstream<br />
and when the in-drum mixing process has been demonstrated.<br />
Development of a successful formulation is achieved when a surrogate that<br />
is chemically similar to the waste stream in question is successfully<br />
immobilized. Successful immobilization is defined as production of final<br />
waste form specimens that meet or exceed the WRAP 2A waste form performance<br />
specifications, as measured through laboratory tests of waste form<br />
performance.<br />
The in-drum mixing process will be demonstrated when surrogates that are<br />
physically similar to the WRAP feedstreams have been successfully mixed with<br />
^amoaillzAti-on ana'trices using the in-drum mixing equipment. Successful mixing<br />
- is defined as production of a mixture that meets or exceeds the mixing process<br />
objectives, as measured through tests on full size pilot plant mixing<br />
equipment.<br />
3-5
n<br />
DEVELOP FORMULATIONS<br />
o Screeninp tests<br />
- Chemical compatibility<br />
- Free Water generation<br />
- Solid monolith<br />
o Surropate Performance Testing<br />
- Chemical surrogates ^<br />
- TCLP, ANS16.1, Compressive<br />
strength, etc.<br />
o Laboratory Parametric studies<br />
- Formulation ranges and limits<br />
o Laboratory Parametric tests<br />
- Physical surrogates<br />
- Measure mixing process parameters<br />
- Determine effect on performance<br />
o Mixing Equipment tests<br />
- Full scale ( 55-gal) mixing equipment<br />
- Scale-up of mixing process<br />
o Full Scale Parametric studies<br />
- Equipment operating ranges and limits<br />
- Process Control Parameteirs<br />
- Operability / studies<br />
i i<br />
HOT DEMONS S$Q^ TION<br />
o Laboratory IHot uerification<br />
- Verify formulations<br />
o Pilot hot deinom:iration<br />
- Verify imixin+o oroce<br />
o Cold testing<br />
- Verify process<br />
o Hot testing<br />
- nualified Wast<br />
^<br />
^ c<br />
A<br />
w<br />
.r<br />
_w<br />
IA<br />
PF<br />
^<br />
^<br />
0<br />
A=<br />
ca^<br />
-n<br />
CI<br />
w er<br />
0 z<br />
CA<br />
^<br />
a<br />
m<br />
^<br />
^<br />
(/^1<br />
QI<br />
^i<br />
0<br />
w<br />
^<<br />
0
^.:<br />
fi<br />
WNC-SD-W100-TI-003 Rev. 0<br />
Figure 3-2. WRAP 2A Process Development Waste Form<br />
Qualification Project Logic.<br />
3-7
3.3.2 Process Optimization<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Confirmation of the baseline process design basis will be subject to<br />
independent review by an outside panel of experts. A report summarizing the<br />
findings of the review panel will provide the basis fo r approval of<br />
commencement of Title I preliminary design activities.<br />
The second major objective of the WFQ program is to optimize the<br />
immobilization formulations and mixing processes. These studies will serve to<br />
expand and define the limits of the "windows" of formulations and mixing<br />
process operating conditions within which waste forms exhibiting acceptable<br />
performance can be produced. Process optimization will consist of methodical<br />
variation of formulations and mixing parameters in factorial experiments<br />
covering the full range of achievable conditions.<br />
Results from process optimization studies will provide the majority of<br />
data required to prepare the Process Control Plan for the immobilization<br />
systems. The Process Control Plan will provide the interface with the RCRA<br />
facility permit, describing the formulation and mixing parameters that must be<br />
maintained to ensure production of fully compliant waste forms. It also will<br />
provide the foundation for development of operating procedures to be used with<br />
the immobilization systems equipment.<br />
3.3.3 Hot Verification<br />
The ±hi;-d major objective is verification testing of the formulations and<br />
mixing process performance on actual WRAP 2A feedstreams. Hot verification<br />
testswi11==le perfarmed on the-fieedstreams as they became availabie.<br />
Formulationtestingwill be perfnrmed in the laboratory, and, if any<br />
discrepancies in waste form performance are encountered, drum-scale hot<br />
testing will also be performed. Hot testing results that create modifications<br />
or additional requirements in the formulation or mixing conditions will be<br />
------ --- documented in the Process Control Plan.<br />
3.3.4 Additional Objectives<br />
Additional WFQ activities will include participation in the Polymer<br />
Solidification National Program at Brookhaven National Laboratory for<br />
development of a thermoplastic polymer encapsulation process using a heated<br />
extruder. Demonstration of BDAT technologies for special processes, such as<br />
mercury amalgamation ' r-reactive metais treatment,, will also be included in<br />
the WFQ testing program. The scope of these additional activities has not yet<br />
been fully defined.<br />
3-8<br />
i
4.1 SCREENING TEST RESULTS<br />
WHC-SD-W100-TI-003 Rev. 0<br />
4.0 TEST RESULTS<br />
4.1.1 Cement-Based Waste Form Screening Test Results<br />
Waste surrogates for each waste type were immobilized with various<br />
cementitious binders to determine which would be selected for the grout<br />
formulations. Three things were considered when selecting the cementitious<br />
----- ----linders: (1) as h,ard Set muJt be aChieved within 48 hours, ( 2) a hard set must<br />
not occur within 6hours1_and ( 3) a reasonable waste loading must be achieved.<br />
4.1.1.1 Type 5- 183H Sandblast Grit 1 (High Copper Content). The binders<br />
that were evaluated were portland cement type III, a combination of portland<br />
cemeni:-types i and ii, and slag cement. Portland cement type III is a rapid<br />
setting cement and was selected to balance the effect of the copper in the<br />
waste, which is known as a set retarder. A hard set was achieved in 48 hours.<br />
The combination of portland cement types I and II gave a set time of 72 hours.<br />
The siag cement required more time to achieve a hard set and was not<br />
considered for further evaluation. Portland cement type III was selected as<br />
the cementitious binder.<br />
Mix formulation for sand grit/sludge ratio of 90:10:<br />
Waste loading - 41.7 wt%<br />
Water/cement ratio - 0.4<br />
Binder - 100 % portland cement type III.<br />
4.1.1.2 Type 6 - 183H Sandblast Grit 2 ( High Nitrate). The same cementitious<br />
binders as above were evaluated for this waste type. Because the nitrate<br />
content apparently did not interfere with the set time, a mixture of slag<br />
cement and portland cement type III was selected as the binder. A hard set<br />
was achieved in 24 to 48 hours using slag cement with portland cement type III<br />
as the initiator.<br />
Mix formulation for sand grit/sludge ratio of 90:10:<br />
Waste loading - 41.7 wt%<br />
Water/cement ratio - 0.4<br />
Binder - 0.11 ratio of portland type III/slag cement.<br />
4.1.1.3 Type 7 - L-045 Metal Sludge (Iron). The transition metal ions,<br />
including iron, tend to interfere with the setting properties of the cement<br />
matrix. Several cementitious binders were considered to immobilize the iron<br />
sludge surrogate, including portland cement type III, lime or a lime-portland<br />
cement mixture, a combination of portland cement types I and II, and slag<br />
cement. The lime (natural cement) produced a soft set and the lime/portland<br />
cement mixtures had to be added in excess to achieve a reasonable set. The<br />
4-1
WHC-SD-W100-TI-003 Rev. 0<br />
combination of portland cement types I and II and the slag cement performed<br />
adequately but not as well as the type III. The cementitious binder that<br />
produced the best results was the portland cement type III.<br />
Mix formulation:<br />
Waste loading - 15.4 wt%<br />
Water/cement ratio - 0.83<br />
Binder - 100% portland cement type III.<br />
4.1.1.4 Type 8 - ASH from Thermal Treatment. Slag cement was chosen for<br />
testing because of the similarity of the ash to slag cement. Slag cement was<br />
also selected based on its high chemical retention capability. A hard set was<br />
achieved within 24 hours.<br />
Mix formulation:<br />
• Waste loading - 30 wt%<br />
• Water/cement ratio - 0.55<br />
{8inder-- O:ii ratio of partiand cement type III to slag cement.<br />
4.1.1.5 Type 1(Alternate Waste Form) - C-018 Ammonium Sulfate. Envirostone<br />
(gypsum cement) was selected to immobilized this waste stream because of its<br />
ability to solidify acidic waste. Envirostone remains neutral when mixed with<br />
water as opposed to most cementitious binders, which are strongly basic when<br />
mixed with water. A strongly basic media would readily react with ammonium<br />
sulfate or other ammonium salts to form ammonium hydroxide, which decomposes<br />
to ammonia gas. The one problem with Envirostone is that when it mixes with<br />
-ammon4uir-sulfate, the set occurs too rapidly to be of use in a typical<br />
mechanical mixer. Additional testing was performed and results indicated that<br />
the addition of citric acid or sodium citrate would retard the set time.<br />
Mix formulation:<br />
Waste loading - 20 wt%<br />
Water/cement ratio - 0.5<br />
Binder - 0.02 ratio of retardant to Envirostone.<br />
4.1.2---Thermosetting--Fol „ er-Screening Test Results<br />
Screening<br />
performed at a<br />
tests for the thermosetting polymer immobilization<br />
private vendor's ( Diversified Technologies) rented<br />
process were<br />
laboratory<br />
.__space<br />
at Saginaw vaitey State University. Fifteen screening tests were<br />
performed using the Diversified Technologies vinyl ester polymer immobilization<br />
process. The technique was observed by the attenders and videotaped by<br />
WHC. The materials that were solidified were meant to represent the major<br />
chemical characteristics of the wastes selected for thermosetting polymer<br />
-test3ng ( see Section 3.2) as well as some waste samples that the vendor had<br />
prepared for demonstration purposes. The materials that were solidified and<br />
the_testresul+s are described .vcv in .^^ *h; ^ l.on i- sel.° L1 °- .<br />
4-2
,^.<br />
----- --<br />
WHC-SD-W100-TI-003 Rev. 0<br />
The process used in all cases involved adding a measured amount of<br />
_binder; either 100-g--t3>5-oz) or-5Q-g--(-1.8-oz), depending on the amount of<br />
final product desired, to a paper cup. Extender was added to the binder for<br />
the first 11 samples, then the process was tried without extender for the<br />
remaining samples. Surrogate waste was then added, at waste:binder ratios of<br />
either 1.5:1 or 1:1 ( weight basis). Following mixing of the waste and binder,<br />
a catalyst was added and allowed to mix for 1 minute. The promoter was then<br />
added, mixed for 1 minute, and the agitator withdrawn. The gel time was<br />
measured and the samples allowed to cure.<br />
Sample 1: Wet ammoniated powdex resin. The material was supplied by<br />
Diversified and consisted of a thick sludge of resin that had been<br />
drained of free water. 150 g (5.3 oz) of resin was added to 100 g<br />
(3.5 oz) of binder, for a waste loading of 60 wt%. The formulation was<br />
successful.<br />
Sample 2: Ammoniated powdex resin, 30 wt% slurry in water. Processed as<br />
described for Sample 1. The formulation was successful.<br />
Sample 3: Ammonium sulfate crystals (Type 1 Waste). 75 g (2.6 oz) of<br />
crystals were added to 50 g (1.8 oz) of binder. Processing was as<br />
described for Sample 1. The formulation was successful.<br />
Sample 4A/48: Ammonium sulfate crystals (Type 1 Waste). Processed as<br />
for Sample 3 but double the quantities. This material was transferred to<br />
specimen vials before curing. The vials were retained by WHC.<br />
Sample 5: Surrogate basin sludge (Type 2 or 3 Waste). The sludge was<br />
formulated to represent the average composition of the basin 183-H<br />
sludge. This material was prepared to the UE&C recipe, where 100 g<br />
(3.5 oz) of sodium nitrate, 42 g (1.5 oz) of sodium sulfate decahydrate,<br />
and 79 g (2.8 oz) of water were mixed well. The water was not sufficient<br />
to fully dissolve he crystals. The crystal slurry was added to 79 g<br />
-(2.8 oz) of Celitel 545 diatomaceous earth filter aid. This resulted in<br />
a moist cakey powder consistency. 75 g (2.6 oz) of this material was<br />
added to 50 g (1.8 oz) of binder and processed. The mixture formed a<br />
stable emulsion, but free water was exuded as the polymerization exotherm<br />
progressed. Following solidification, the free water was apparently<br />
reabsorbed into the matrix.<br />
Sample 6: Wet basin sludge slurry (Type 2, 3 or 4 Waste). The WHC and<br />
UE&C observers agreed that the original recipe appeared to contain less<br />
moisture than the actual basin sludge, so this material was prepared by<br />
adding water to the above recipe until the desired consistency was<br />
obtained. This resulted in a recipe that contained 35% water. 85 g<br />
(3.0 oz) of the slurry was added to 50 g (1.8 oz) of binder and processed<br />
as above. The matrix exuded water during the exothermal reaction, and<br />
the water was not reabsorbed. Approximately 2 wt% free liquid was<br />
produced.<br />
°=y zCelite is a trademark of Celite Corporation.<br />
4-3
:..,^<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Sample 7: Sodium nitrate•crystals (Type 4.Waste). 75 g(2.6 oz) was<br />
added to 50 g (1.8 oz) binder and processed. The material was<br />
successfully solidified.<br />
Sample 8A/8B: Wet basin sludge slurry (Type 2, 3, or 4 Waste). 150 g<br />
(5.3 oz) of Sample 6 material was added to 100 g (3.5 oz) of binder and<br />
processed. The material was transferred into specimen vials and allowed<br />
to cure. Free water was exuded during the exothermal reaction. The<br />
vials were retained by WHC.<br />
Sample 9A/9B: Sodium nitrate crystals (Type 2, 3, or 4 Waste). 150 g<br />
(5.3 oz) of crystals was added to 100 g(3.5 oz) of binder and processed.<br />
The material was transferred into two specimen vials and allowed to cure.<br />
The cured vials were retained by WHC.<br />
Sample 10: Sodium sulfate decahydrate (Type 4 Waste). 50 g(1.8 oz) of<br />
crystals were added to 50 g of binder and processed. Water was exuded<br />
during the exotherm. The water evaporated, leaving behind salt crystals.<br />
Sample 11: Wet basin sludgeslurry (Type 2, 3, or 4 Waste). This sample<br />
was processed at 50:50 waste:binder ratio in an attempt to prevent<br />
formation of free water. During the exothermal reaction, about 2.3 wt%<br />
free water was produced.<br />
Sample 12: Sodium sulfate decahydrate (Type 4 Waste). 75 g(2.6 oz) of<br />
crystais were added to 50 g(1.8 oz) of binder. For this test, the<br />
polymer extender was not added to the binder. This caused less heat to<br />
be produced during the exothermal reaction and a significant reduction in<br />
the amount of free water produced. The free liquid evaporated, leaving<br />
dry crystalline powder on the surface of the sample. The observers<br />
estimated that less than 0.5 wt% free liquid had been produced.<br />
Sample 13: Wet basin sludge slurry (Type 2, 3, or 4 Waste). This sample<br />
was processed at 75 g (2.6 oz) waste to 50 g (1.8 oz) binder. No<br />
extender was added to the binder. The material produced 2.1 wt% free<br />
liquid.<br />
Sample 14: Wet ammonium sulfate (Type 1 Waste). Water was added to the<br />
ammonium sulfate crystals to produce 10 wt% moisture to simulate LETF<br />
filter cake. The material was successfully solidified at 60 wt% loading<br />
(75 g[2.6 oz] wet salt:50 g [1.8 oz] binder) with no extender added to<br />
the binder.<br />
Sample 15A/158: Sodium sulfate decahydrate (Type 4 Waste). 150 g<br />
(5.3 oz) of the crystals was added to 100 g (3.5 oz) of binder without<br />
extender. The material was transferred into two specimen vials retained<br />
by WHC. Traces of water were exuded, leaving small spots of dry crystals<br />
on the surface of the specimens.<br />
4-4
WHC-SD-W100-TI-003 Rev. 0<br />
4.1.3 Thermosetting Polymer Results Summary<br />
The technology shows promise as an alternative to conventional cementbased<br />
grout for immobilization of the materials tested. Further development<br />
of the formulation will be required to eliminate the free liquids that were<br />
formed when processing the materials, which contained hydrated sodium sulfate<br />
crystals. The process was able to successfully immobilize sodium nitrate and<br />
ammonium sulfate, at 60 wt% loading, with no apparent side reactions. The<br />
immobilized material appears to be homogeneous and possesses considerable<br />
structural strength and durability.<br />
Based on the results of these initial screening tests, it was recommended<br />
that the technology be considered for further WFQ testing to support possible<br />
use in WRAP 2A for the immobilization of mixed wastes containing nitrates and<br />
amnonium salts. Additional development will be required to determine if the<br />
polymer formulation can be adjusted to prevent the formation of free liquids<br />
when processing material containing hydrated sodium sulfate salts.<br />
4.2 SURROGATE PERFORMANCE TESTS<br />
4.2.1 Cement-Based Waste Form Results<br />
Sample Preparation<br />
The cementitious waste forms were prepared by combining the waste<br />
_ ^------$!:r!3gat@°, i<br />
and tile £e^Tientitioua binderS according to the formulations<br />
^^^ developed during the screening tests, as shown in Section 4.1.1. The<br />
surrogate material and the cementitiPus binder were measured into a 19-L-<br />
(5-gal-) capacity, heavy duty Hobart variable mixer, where they were mixed<br />
-until a homogeneous mixture was obtained. A minimum of 9.5 L(2.5 gal) of<br />
cement-waste slurry was required for each set of experiments. For each waste<br />
type tested, a cement-waste slurry was prepared in three batches and poured<br />
out separately into the appropriate sized molds. Sample molds included 5 cm<br />
by 5 cm by 5 cm (2 in. by 2 in. by 2 in.) cubes, small cylinders 7.6 cm in<br />
diameter by 15 cm high ( 3 in. in diameter by 6 in. high), and large cylinders<br />
15 cm in diameter by 30.5 cm high ( 6 in. in diameter by 12 in. high). The wet<br />
specimens were covered with plastic or placed in plastic bags to simulate<br />
placement in a 208-L (55-gal) drum or another sealed container. The cube<br />
samples were removed from their metal molds after about 3 days. The samples<br />
were labeled and placed in plastic bags at room temperature until the<br />
appropriate cure time was ac-hieved. After curing, the samples were weighed<br />
and then-i
RESULTS<br />
Compressive Strengths<br />
Wi1C-SD-W100-TI-003 Rev. 0<br />
The first set of waste forms tested were 5 cm by 5 cm by 5 cm (2 in. by<br />
2 in. by 2 in.) cubes. The compressive strength tests were performed on two<br />
cube samples for each waste type. The first cube for each waste type was<br />
tested after 14 days of curing, the second cube for each waste type was tested<br />
after 28 days of curing. The results are shown on Table 4-1.<br />
3he second-set of waste forms were small cyiinders, 15 cm ( 6 in.) high<br />
with a 7.6-cm ( 3-in.) diameter. The cylinders were allowed to cure for<br />
28 days before the compressive strength tests were performed. The small<br />
cylinder results are shown in Table 4-2.<br />
Sample Solidifier<br />
Typ e 5<br />
Type 5<br />
Portland<br />
^ype Iii<br />
Table 4-1. WRAP 2A Waste Form Characteristics.<br />
Compressive strength<br />
Dens ity F ree li qu id<br />
(g/cc) (vol.%) 14 day 28 day<br />
(lbf/inZ) (lbf/in 2)<br />
Portland<br />
Type I and II 2.5 0<br />
2.5 - ------ 0------ 6,800 5,000<br />
4,600 5,600<br />
( 28d) (42d)<br />
Slag<br />
Type 6 Cement/portland 2.4 0 3,800 3,000<br />
Type III<br />
Type , Portland<br />
Type III<br />
1.7 0 1,000 1,300<br />
Siag . .<br />
Type 8- Cement/portland - 1.7 0 3,100 1,800<br />
Type III<br />
I<br />
Type 1 Environstone*<br />
I<br />
1.5<br />
2.6 at 1 day<br />
1.6 at 2 day<br />
0.0 at 3 day<br />
(Liquid oH_is 6)<br />
70 60<br />
-<br />
*Envirostone is a trademar o t e United States Gvosum Comoanv_<br />
4-6
p<br />
Sam le<br />
Compressive Radiation<br />
strength stability<br />
Small Large Compressive<br />
cylinder<br />
(l bf / i n<br />
2 )<br />
cylinder<br />
( lbf /in `^ )<br />
strength<br />
( lbf/in<br />
2 )<br />
^ _"' .<br />
^ws{ J 7'<br />
Table 4-2. WRAP 2A Cement Waste Form Tests Results.<br />
Biodegradation<br />
Compressive<br />
strength<br />
(sample/control)<br />
(lbf/in )<br />
h<br />
Was e immersion<br />
Thermal<br />
cycling<br />
Compressive strength<br />
Leachability<br />
Index<br />
14d<br />
(lbf/in)<br />
42d 90d<br />
C ompress iv e<br />
strength<br />
/ Z)<br />
(lbf in<br />
Control 7,400 4,500 -- -- -- - -<br />
Type 5 7,100 5,400 8,500/9,100<br />
Type 6 3,500 4,200 3,800/4,800<br />
Type 7 2,800 2,100 2,500/2,000<br />
Type 8 3,400 2,400 4,100/3,900<br />
Type 1 50<br />
9.9 (Ce)<br />
No data (Sr)<br />
8900 3900 8400 5500/8000<br />
5300 2600 5500 4000/4400<br />
2400 1100 3000 2200/2400<br />
3900 2500 4380 2900/3100<br />
Failed
WHC-SD-W100-TI-003 Rev. 0<br />
The third set of waste forms were the large cylinders, 30.5 cm (12 in.)<br />
high with a 15-cm (6-in.) diameter. The large cylinder waste forms were<br />
allowed to cure for 28 days before they were compressive strength tested. The<br />
large cylinder test results are shown in Table 4-2.<br />
Radiation Stability<br />
Two identical waste form cubes for each waste type were irradiated to a<br />
total dose of 108 radiation in a gamma irradiation faci_lity,_ Each_cube- was<br />
then compressive strength tested. Weights for each of the ten samples were<br />
recorded before and after irradiation. No weight change was observed and no<br />
visual change in color or appearance was observed. The compressive strength<br />
test results are shown in Table 4-2.<br />
Biodegradation<br />
Ten waste form cubes, two duplicate cubes for each waste type, were<br />
subject to ideal growth conditions for bacteria, for a period of 21 days.<br />
After this incubation period, the waste forms were tested for compressive<br />
strength. The results are shown in Table 4-2.<br />
T Leachability Index<br />
Cube samples for each waste type were subject to the leachability index<br />
test. The test results are shown in Table 4-2.<br />
Water Immersion<br />
Three cube samples for each waste type were stored in moist conditions<br />
over a period of time. After 14 days, one of the cubes for each of the waste<br />
types was compressive strength tested. After 42 days, the second cube sample<br />
was compressive-strength tested. _After 90 days, the third sample was tested.<br />
The results are shown in Table 4-2.<br />
Thermal Cycling<br />
Two cube samples for each waste stream were heated to +60 °C (140 °F),<br />
cooled, frozen to -40 °C (-40 °F), and then thawed. The cycle was repeated<br />
30 times and then a compressive strength test was performed on each cube<br />
sample. Results are shown in Table 4-2.<br />
Free Liquid<br />
The samples were prepared by pouring the slurry mix into 13 cmZ (2-in 2)<br />
plastic bottles to a 5-cm (2-in.) height, for each of the waste types.<br />
Duplicate samples for each waste type were prepared. At the end of a 24-hour<br />
period each sample was visually inspected for the presence of liquid. The<br />
amount of liquid, if any, was measured. The results are shown in Table 4-1.<br />
EPA (TCLP) Tests<br />
The test involves obtaining an extract from the waste form and analyzing<br />
the extract for toxic constituents. The test results for the TCLP tests are<br />
summarized in Table 4-3.<br />
4-8
WHC-SD-W100-TI-003 Rev. 0<br />
Table 4-3. TCLP Results for WRAP 2A Cement Waste Forms.<br />
Sample Specie<br />
Type 5<br />
0riginal<br />
Cont.<br />
TCLP Cont. Limit Pass/fail<br />
Chromium 50 ppm 0.07 ppm 5 ppm Pass<br />
Copper 1.7% 0.09 ppm No limit N/A<br />
Type 6 Chromium 50 ppm
^- -'^<br />
WHC-SD-W100-TI-003 Rev. 0<br />
-----mai-erial,- TaYle 4-4 suarfzes the formulations that were used to prepare the<br />
waste form specimens.<br />
Table 4-4. Formulation Parameters.<br />
Formulation parameter Type 1 Type 2 Type 3 Type 4<br />
Waste/binder ratio, ( kg/kg) 4/2 3/3 4/2 3/2<br />
Binder type 411-45 470-45 411-45 470-45<br />
Catalyst dose ( wt% of binder) 2.5_ 7.5 2.5 5.0<br />
Promoter dose ( wt% of binder) 0.1 2.0 0.1 1.0<br />
Total mixing time ( minutes) 25 8.5 8.5 10.5<br />
Peak-m}xing power (W) ---- 45 12.3 -9.9 13.9<br />
Peak exotherm (°C) 38.2 70 57.5 63<br />
Peak exotherm time ( minutes) 75 30 120 25<br />
SPECIMEN PREPARATION<br />
Test specimens were prepared from waste surrogates at the Stock Equipment<br />
Company laboratories. Batch size was approximately 4.7 L (1.25 gal).<br />
A variable speed laboratory mixer with propeller blade operating at 1,800 rpm<br />
was used. Each set of specimens was made from a single batch and poured into<br />
cylindrical molds. The tests described in Section 2.0 were performed on the<br />
specimens. Replicate tests were performed as described in Table 4-5.<br />
--- Table 4-5. Repiicate Specimens Tested.<br />
Performance test Number of replicates tested<br />
Compressive strength 10 @ 5-day cure, 10 @ 90-day cure<br />
Biodegradation 3<br />
Radiation stability 3<br />
Leachability/immersion 6 spiked, 6 unspiked<br />
7hermai cycling 3<br />
I Toxicity characteristic 2 + 1@ independent lab<br />
4-10<br />
i1<br />
-syr
..., TESTING RESULTS<br />
.^.CSSD-W-1OO-•TT-MQ<br />
Dnv n<br />
^ • v v.. nc ^ . v<br />
Results of the testing are summarized in Table 4-6. All specimens were<br />
successfully immobilized and exhibited strength and durability characteristics<br />
meeting or exceeding the waste form performance specifications. Type 3<br />
surrogate met all of the performance specifications. Leaching characteristics<br />
for all surrogates met the requirements for LLW, but some TCLP constituents of<br />
Types 1; 2, and 4 surrogates exceeded the allowable limits. Additional<br />
formulation development will be required for these waste types.<br />
CONCLUSIONS<br />
Surrogate waste form specimens were successfully immobilized at waste<br />
loadings ranging from 50 wt% to 67 wt%. Type I surrogate met all performance<br />
specifications with the exception of TCLP mercury. Type 2 surrogate met all<br />
performance specifications with the exception of TCLP mercury and chromium.<br />
Type 3 surrogate met all performance specifications. Type 4 surrogate met all<br />
performance specifications with the exception of TCLP chromium.<br />
The results show that the technology is capable of producing a waste form<br />
_that__meetsor_exceeds all appLi_cable performance requirements. Additional<br />
formulation development will be required to optimize the waste loading for<br />
,.; waste Types 1, 2, and 4 to enable the waste form to meet the TCLP limits for<br />
mercury and chromium.<br />
4.3 FOLLOW-ON TESTING<br />
The TCLP results prompted additional work to develop formulations that<br />
could meet the regulatory limits for chromium and mercury. Additional testing<br />
was performed using waste loading of 25 wt%. Three methods for preparing the<br />
TCLP extraction specimens were investigated. One method involved casting<br />
pellets from the mixture so no size reduction was required. The other two<br />
methods used larger specimens that were crushed to meet the size requirements<br />
for TCLP; all material was used in the extraction for one method and the other<br />
method discarded fines less than 1 mm screen size before extraction.<br />
The results of the follow-on TCLP testing are summarized in Table 4-7.<br />
The samples prepared as pellets passed for all TCLP constituents present.<br />
Neither of the crushing methods were able to meet TCLP limits for mercury.<br />
The results show that reduced waste loading is effective for controlling the<br />
chromium concentrations. The use of reduced waste loadings was successful in<br />
decreasing the concentrations of all TCLP metals observed in the waste<br />
extracts, but the sample preparation method apparently has a larger influence<br />
on the final results than waste loading. Further investigation is planned to<br />
address these concerns.<br />
4-11
WHC-SD-W100-TI-003 Rev. 0<br />
Table 4-6. Summary of Polymer Waste Form Testing Results.<br />
Waste form Acceptance Test results<br />
characteristic criteria Type 1 Type 2 Type 3 Type 4<br />
Compressive<br />
strength<br />
Leachability<br />
index<br />
Strength..<br />
>500 psi<br />
2,472 psi 1,085 psi 1,411 psi 942 psi<br />
Leach<br />
index >6<br />
Cs 7.7/7.4 7.0/7.0 7.3/7.2 7.1/7.1<br />
Demin/sea<br />
water<br />
Co<br />
Sr<br />
8.2/7.9<br />
8.9/8.7<br />
9.2/9.3<br />
9.3/9.1<br />
10.1/10.3<br />
10.2/9.4<br />
7.5/7.7<br />
9.1/9.0<br />
No growth, No growth No growth No growth No growth<br />
Bi o d egra d a ti on s t reng th<br />
-' >506 psi 2,247 psi 3,710 psi 994 psi 1,114 psi<br />
Thermal cycling<br />
Radiation<br />
stability<br />
Immersion<br />
Free liquids<br />
Strength<br />
>500 psi after<br />
30 thermal<br />
cycles<br />
Strength<br />
>500 psi after<br />
irradiation to<br />
10 rad<br />
Strength<br />
>500 psi after<br />
90-day immersion<br />
Free liquid<br />
A I<br />
w<br />
^^',; ^^ ;J<br />
?1Fasf^.}: "q<br />
-? : ll .(„ F ^d^.ie J. ..<br />
Table 4-7. Follow-On Testing Results.<br />
Acceptance Test results<br />
Waste form<br />
criteria Wast.e type 1 Waste type 2 Waste type 4<br />
characteristic Sample<br />
preparation<br />
method*<br />
A B C A B C A B C<br />
Toxicity<br />
characteristics<br />
Ba<br />
0.022 0.320<br />
N/A N/A N/A<br />
0.268<br />
100<br />
N/A N/A N/A<br />
pass pass pass<br />
TCLP<br />
leachable<br />
Cd<br />
1 . 0<br />
N/A N/A N/A N/A N/A N/A N/A N/A N/A<br />
metals<br />
below EPA<br />
limits<br />
Cr<br />
5.0<br />
0.275<br />
P ass<br />
0.844<br />
P ass<br />
1.056<br />
p ass<br />
1.76<br />
P ass<br />
4.37<br />
P ass<br />
4.82<br />
P ass<br />
2.03<br />
pass<br />
2.19<br />
pass<br />
2.46<br />
pass<br />
(parts per<br />
million)<br />
Hg<br />
0.2<br />
0.182<br />
pass<br />
0.385<br />
fail<br />
0.350<br />
fail<br />
0.194<br />
pass<br />
0.270<br />
fail<br />
0.245<br />
fail<br />
N/A N/A N/A<br />
0.045 0.040 0.066<br />
A9 N/A N/A N/A<br />
5.0 pass pass pass<br />
*Method A= Pellets; Method B= Crushing; Method C= Crush, discard fines.<br />
N/A = not applicable.<br />
TCLP = Toxicity Characteristic Leaching Procedure.<br />
N/A N/A N/A<br />
x<br />
^ ^^c<br />
E<br />
0 0<br />
-d<br />
M<br />
^<br />
0 0w<br />
Am<br />
<<br />
0
CONCLUSIONS<br />
WHC-SD-W100-TI-003 Rev. 0<br />
The immobilization/stabilization technologies selected for use in WRAP 2A<br />
have been tested on waste surrogates approximately reflecting the chemical<br />
characteristics of 80% of the baseline feed volume. The baseline process<br />
selection has been confirmed for the feed streams studied. Suitable<br />
formulations have been developed and waste form performance testing has shown<br />
that the technologies are capable of meeting all applicable regulatory<br />
acceptance criteria.<br />
ThQrmosetting -pn]ymer fermul.ationshavebeen-deveTuped-for four baseline<br />
WRAP 2A waste streams. Waste surrogates were successfully immobilized at<br />
waste loadings from 50 wt% to 66 wt%. Performance test results at these waste<br />
loadings met all specifications except TCLP for chromium and mercury.<br />
Specimens prepared as pellets with a 25 wt% waste loading met TCLP limits for<br />
all constituents. TCLP results for polymer waste forms were shown to be<br />
highly dependent on the method used for TCLP sample preparation and somewhat<br />
less strongly influenced by waste loading.<br />
4-14
;..;:<br />
.^:.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
5.0 REFERENCES<br />
DOE 1988, DOE Order 5820.2A, "Radioactive Waste Management," U.S. Department<br />
of Energy, Washington, D.C.<br />
DOE 1989, DOE Order 5400.3, "Hazardous and Radioactiv€ 1Mixed-Waste-Program,"<br />
U.S. Department of Energy, Washington, D.C.<br />
Ecology, EPA, and DOE, 1992, <strong>Hanford</strong> Federal Facility Agreement and Consent<br />
Order, 2 Vols., Washington State Department of Ecology,<br />
U.S. Environmental Protection Agency, and U.S. Department of Energy.<br />
EPA 1984, Handbook for Stabilization and Solidification of Hazardous Wastes,<br />
U.S. Environmental Protection Agency, Washington, D.C.<br />
EPA 1992, Code of Federal Regulations, 1989, 40 CFR 260-268, Office of the<br />
Federal Register National Archives and Records Administration,<br />
Washington, D.C.<br />
NRC 1991, "Technical Position on Waste Form, Revision 1," Final Waste<br />
Classification and Waste Form Technical Position Papers, U.S. Nuclear<br />
Regulatory Commission, Washington, D.C.<br />
NRC 1992, Code of Federal Regulations, 1992, 10 CFR 61, "Licensing<br />
Requirements for Land Disposal of Radioactive Waste," Office of the<br />
Federal Register, National Archives and Records Administration,<br />
Washington, D.C.<br />
llEgC ^ gg2a, W,PAD Module 2A Conceptual Design Report, United Engineers and<br />
Constructors, Englewood, Colorado.<br />
UE&C 1992b, WRAP 2 Preconceptual Design Additional Fo11ow-On Activities<br />
Report,_Draft_Letter_Report, From M-.-J. W3lters-to-A:-W. Kello-yg,<br />
dated February 7, 1992, United_E_ng-ineers_andConstructors, Englewood,<br />
Colorado. -<br />
WAC 173-303, Department of Ecology, 1991, Washington Administrative Code<br />
"Dangerous Waste Regulations," WAC-173-303.<br />
WHC 1991, <strong>Hanford</strong> <strong>Site</strong> Solid Waste Acceptance Criteria, WHC-EP-0063-3,<br />
Westinghouse <strong>Hanford</strong> Company, Richland, Washington.<br />
WHC 1993, WRAP Module 2A Waste Form Qualification Plan, WHC-SD-W100-TP-002,<br />
Rev. 0, Westinghouse <strong>Hanford</strong> Company, Richland, Washington.<br />
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WHC-SD-WI00-TI-003 Rev. 0<br />
APPENDIX A<br />
STATEMENT OF WORK - THERMOSETTING POLYMER<br />
Statement of Work (SOW) prepared by Westinghouse <strong>Hanford</strong> Company ( WHC) as<br />
part of the bid package soliciting qualified vendors to perform waste form<br />
_{aer#-ormance-tPsxing using a thermosetting polymer with WHC prepared surrogate<br />
waste.<br />
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1.0 INTRODUCTION<br />
WHC-SD-W100-TI-003 Rev. 0<br />
STATEMENT OF WORK - THERMOSETTING POLYMER<br />
Waste Form Qualification Testing<br />
Statemeni-of Work W-277587<br />
May 14, 1992<br />
The Westinghouse <strong>Hanford</strong> Company ( WHC), under contract to the United States<br />
r. Department of Energy ( DOE), is currently responsible for the design,<br />
'=e construc'tion,- startup, and operation of the Waste Receiving and Processing<br />
Facility ( WRAP) at the DOE's <strong>Hanford</strong> site. The second module of the facility<br />
(WRAP 2A) will handle and process contact-handled low level mixed (hazardous<br />
'-^=- anfi radioactive) wastes ( CH-LLMW). The WRAP 2A project is currently in the<br />
conceptual design stage, with architect/engineer services being provided by<br />
United Engineers and Constructors ( UE&C).<br />
As part of the conceptual design effort for this project, WHC is seeking<br />
contractors to provide services in support of the polymer immobilization<br />
technology waste form qualification program. The required services will<br />
involve the formulation, preparation and testing of vinyl ester styrene waste<br />
forms, - and doCilmenta-tion 3f-t!12 waste-f3r"F -content, fCrT!llatiCn, prOCess<br />
parameters, and analytical results.<br />
This document describes the work to be done by the contractor in support of<br />
the WRAP 2A waste form qualification program. The contractor shall comply<br />
with all provisions of this statement of work during the performance of the<br />
work.<br />
2.0 PURPOSE<br />
The first purpose of this phase of the WRAP 2A waste form qualification<br />
program is to develop polymer immobilization formulations for the four CH-LLMW<br />
waste types of concern, and to demonstrate the ability of the immobilization<br />
process to create a final waste form which is chemically and physically<br />
stable, and which meets all applicable regulatory requirements with respect to<br />
low-level radioactive and hazardous waste disposal.<br />
The second purpose of the program is to provide full and complete<br />
documentation of the qualification testing procedures, practices, and results.<br />
The documentation must be of sufficient quality to support ongoing efforts for<br />
regulatory compliance and detailed facility design. The test program will be<br />
performed in laboratories which are qualified to perform the work described.<br />
The results of this test program will be used to evaluate the suitability of<br />
-----ttie immobilization process for use in WRAP 2A. Successful demonstration of<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
suitable immobilization technologies is a critical element in the completion<br />
of the WRAP 2A conceptual design effort.<br />
3.0 SCOPE OF WORK<br />
The scope of work includes the following work elements:<br />
a.d-- Prepare- a- plan--tc perfarm-all elements of the work described for<br />
approval by WHC prior to the start of work.<br />
3.2 Prepare a quality assurance plan for approval by WHC prior to the<br />
start of work.<br />
3.3 Develop optimum formulations for the immobilization of the<br />
surrogate wastes supplied by WHC.<br />
3.4 Prepare waste form qualification specimens as necessary to<br />
complete all required laboratory tests.<br />
31 5 --Dprform laboratory qualif3caxien testing and analyses of °<br />
immobilized waste forms.<br />
3.6 Support the conceptual design effort for the WRAP 2A polymer<br />
immobilization process facilities.<br />
3.7 Prepare progress reports and a final report to fully document all<br />
development and testing activities associated with this work.<br />
4.0 DESCRIPTION OF TESTING<br />
Thirty-j36j pounds each of the four surrogate waste simulants will be prepared<br />
and furnished by WHC for use in the testing. Table 1 summarizes the<br />
approximate chemical compositions of the surrogate wastes. The surrogates<br />
will be prepared by dissolving the required salts in water and evaporating to<br />
the desired moisture content. A complete description of the procedures used<br />
to prepare the surrogates, and full chemical analysis of each surrogate waste<br />
shal-l-be-supplied-by-WHC,--including-material-safety-data-sheets for all<br />
ingredients used to prepare the surrogates. The surrogate wastes will not<br />
contain any radionuclides.<br />
The contractor shall be responsible for developing the optimum formulation to<br />
be used for preparing the qualification specimens. Qualification testing<br />
specimens shall then be prepared using the optimum formulation for each<br />
surrogate waste type.<br />
A-minimum o-f-ei-ght quaT1firation specimens shall be prepared from each of the<br />
su{-rugat^ wastes suppiied 'ey WHC. All qualification specimens shall be<br />
prepared from a single batch of processed waste. The minimum batch size shall<br />
3<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
be one liter. The process shall be monitored for the parameters listed in<br />
Table 2 during the preparation of the qualification specimens.<br />
The specimens shall be tested to determine the final waste form properties as<br />
listed in Table 3. <strong>Document</strong>ation supporting laboratory qualification to<br />
perform the required testing shall be included with the work plan. The vendor<br />
shall propose additional process parameters or waste form properties to be<br />
monitored or tested, as may be necessary or desirable to fully define the<br />
pr-ocessor_demonstrate_superior waste-form qualities.<br />
5.0 ACCEPTANCE CRITERIA<br />
Waste form testing acceptance criteria are shown in Table 3. Polymer waste<br />
forms which do not meet all of the test acceptance criteria will not be<br />
considered for further evaluation or for use in the WRAP 2A facility.<br />
6.0 CONCEPTUAL DESIGN SUPPORT<br />
The contractor shall provide support to WHC during the development of the<br />
conceptual design report (CDR) for the WRAP 2A facility. The contractor's<br />
technical staff shall be available for occasional telephone consultation as<br />
required to answer questions regarding the conceptual design. Support shall<br />
include providing process design parameters, recommendations for process<br />
equipment selection, and review of the immobilization process conceptual<br />
design documents. This design review will include a 2-day meeting at UE&C's<br />
offices in Denver. The contractor shall prepare and submit a summary letter<br />
report describing the conclusions and recommendations resulting from this<br />
design review.<br />
7.0 TEST PROCEDURE<br />
The work plan shall include complete detailed descriptions of all proposed<br />
processing equipment and laboratory apparatus to be used for preparation and<br />
testing of the qualification specimens. Laboratory testing procedures to be<br />
used shall conform with the methods shown in Table 3. The tests shall be<br />
performed by laboratories which are qualified in the required test methods.<br />
Laboratory qualification shall be demonstrated by an established QA/QC program<br />
and- pr-ior- experi ence i-n- the- test- methods 3peci#ied. - An,- de.i ati on #rom the<br />
test procedures listed in Table 3 must be approved in writing by WHC prior. to<br />
performing the tests.<br />
8.0 SAFETY<br />
The contractor shall comply with all applicable safety regulations during the<br />
performance of the work. Any unusual safety hazards, such as flammability,<br />
chemical toxicity, or reactivity associated with the process technology shall<br />
be described in the work plan, along with the procedures and equipment which<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
will be used to mitigate safety hazards. Material safety data sheets for all<br />
process reagents shall be submitted with the work plan.<br />
9.0 QUALITY ASSURANCE<br />
The contractor shall prepare a quality assurance plan describing the QA/QC<br />
activities to be performed during the work. WHC shall review and approve the<br />
QA plan prior to the start of testing. The plan shall include, but not be<br />
limited to, descriptions of laboratory instrument and equipment calibration,<br />
analysis of duplicates and blanks, and statistical validity of analytical<br />
results. All reported results shall be fully traceable to the original data<br />
sources. The testing laboratory shall follow QA/QC procedures that conform to<br />
d•'-. the requirements of the testing methods in Table 3.<br />
10.0 SCHEDULE<br />
The schedule for performance of this work is shown in Figure 1. The<br />
--^_--- ----iAntraCtiSi"-s-ifiail--suf"im-it the-iv0rk plan and quality assurance plan within two<br />
weeks after award of contract. WHC review and approval of these documents<br />
will require one week. The contractor shall submit interim progress reports<br />
- on the work at four week intervals following approval of the work plan and<br />
release to proceed. The second progress report should contain the results of<br />
all laboratory testing with the exception of the long-term immersion,<br />
biodegradation, and leachability testing. Work shall be completed by<br />
October 16, with submittal of the final report no later than October 30, 1992.<br />
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^-:<br />
-- ^<br />
Component Waste Type 1<br />
LETF Salts<br />
WHC-SD-W100-TI-003 Reve 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
TABLE 1<br />
Surrogate Wastes Approximate Composition<br />
Waste Type 2<br />
Basins #1,#2<br />
Sludge<br />
Waste Type 3<br />
Basins #3,#4<br />
Sludge<br />
Silver (ppm) M 190<br />
Waste Type 4<br />
Basin Crystal<br />
Solids<br />
Barium (pp m ) 24 100<br />
Ber llium m 6 2.3<br />
Cadmium (ppm ) 6<br />
Chromium (pp m ) 187.5 900 390 500<br />
Co pp er (pp m ) 201.0 130,000 112,000 63,000<br />
Mercury (pp m ) 9.2 1.3<br />
Nickel (oom)_ 46.5 100 130 400<br />
SUBTOTAL Ippml 444.20 131,225.30 112,742.30 84,000.00<br />
Ammonium % 22.83<br />
Fluoride % 6.0 1.3 7.1<br />
Nitrate % 1.1 13.5 26 1.6<br />
Sodium ( % ) 20.0 24 22.9<br />
Sulfate_ %) 64.61 __20.2 _3,7 35.5<br />
Water ( % ) 10.0 21.58 25.03 24.5<br />
SUBTOTAL I%) 98.54 81.28 80.03 91.60<br />
Inerts % 1.42 5.6 8.7 2.0<br />
TOTAL 1%1 100.00 100.00 100.00 100.00<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
TABLE 2<br />
Key Process Parameters<br />
PARAMETER UNITS<br />
Mixer s p eed revolutions p er minute<br />
Mixer- p ower watts -<br />
Batch wei g ht g rams<br />
Batch volume cubic centimeters<br />
Curin g exotherm de g rees Centi g rade<br />
Waste loadin g wei ht p ercent<br />
Matrix chemistry wei ht percent<br />
7<br />
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--1vHC-SD iii00- T i-003 Rev. 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
TABLE 3<br />
Immobilized Waste Testing Requirements<br />
Waste Form Characteristic Test Method Acce tance Criteria<br />
Com pressive Stren gth ASTM D695 Stren g th > 60 p si<br />
Leachability Index ANS 16.1 Leach Index > 6<br />
Biodegradation ASTM G21 & G22, No growth,<br />
ASTM D695 Stren th > 60 p si<br />
Thermal Cycling ASTM B553, Strength > 60 psi after 30<br />
ASTM 0695 thermal c y cles<br />
Radiation Stability ASTM D695 Strength > 60 psi after<br />
irradiation to 108 rad<br />
Immersion ASTM 0695 Strength > 60 psi after 90day<br />
water immersion<br />
Free Li q uids ANS 55.1 Free li uid < 0.5%<br />
Hazardous Characteristics 40 CFR 261 Not ignitible, not<br />
corrosive, not reactive<br />
Toxicity Characteristics EPA 1311 (TCLP), TCLP leachable constituents<br />
€FA 6010 bel ow EPA l imi tsc°' ce'<br />
-(")Basin-waste-texit-ctu!stituentzare_AgBa,-Be,-Cd,Cr,_-Cu, Hg, and Ni.<br />
LETr' toxic constituents are Cr, Cu, Hg, and Ni.<br />
cWEPA limits as described in 40 CFR 268.41, Table CCWE.<br />
8<br />
A-9
,<br />
TASK<br />
Bid period<br />
Award contract<br />
Prepare work plan<br />
Submit work plan<br />
Review & approve plan<br />
Release to proceed<br />
Develop formulations<br />
Prepare specimens<br />
Laboratory anaiyses<br />
Progress reports<br />
Final report<br />
Support CDR preparation<br />
WHC formulate surrogate<br />
WHC prepare surrogate =<br />
WHC ship surrogate =<br />
Vendor receive surrogate *<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Waste Form Qualification Testing<br />
Statement of Work W-277587<br />
May 14, 1992<br />
CIrIfPr I<br />
SCHEDULE<br />
May June July Aug Sept Oct<br />
*<br />
*<br />
9<br />
A-10
WHC-SD-W: JV-TI-VVJ ^cv. v<br />
APPENDIX B<br />
TECHNICAL TASK PLAN - GROUT<br />
Technical Task Plan (TTP) prepared by WHC for an "in-house" (WHC) testing<br />
_--program fQrwast_e fnrmpp-rfnrmanee testing-using-e^ment-based waste forms and<br />
surrogate waste. Similar to the SOW for thermosetting polymer.<br />
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B-2
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^^ln^l<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TECHNICAL TASK PLAN - GROUT<br />
FY 1992 Technical Task Plan<br />
Support of the Waste Receivinq and Processing (WRAP)<br />
Module 2A<br />
TIP #A5202<br />
Princ pa1 Inv i a or Date<br />
naineer<br />
Date<br />
Date<br />
AP rogram Manager Da e<br />
B-3
Date: 05/04/92<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Tec hnical Task Plan<br />
Title: Waste Disposal Studies in Support of WRAP (Module 2A)<br />
Technical Manager: J. A. Hunter<br />
Technical Investigator: W. 0. Greenhalgh<br />
Program Coordinator: J. L. Westcott<br />
Fiscal Year: 1992<br />
B-4
Scope<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Support WRAP validation (August 15, 1992) by providing the following:<br />
Awast.e characterization summary for all WRAP 2A feed streams including<br />
C-01811, L-04511, 18311 basin, ash residue, etc.<br />
• Immobilization technology li,terature search for these feeds.<br />
• Cold laboratory testing of cement solidification systems on C-018H and 183H<br />
basin waste simulants.<br />
• Publish status report to support validation application.<br />
Budget<br />
FY 1992 - $60K expense.<br />
^`:,,,.`:<br />
^^.^r^^,v2<br />
To prepare, in report form, waste characterization data and summary,<br />
-immobilization candidates, and compatible immobilization options that can be<br />
- srwli-2d in-the Module 2A facility of WRAP to meet present and near future<br />
waste disposal criteria and regulations.<br />
Backaround<br />
The WRAP Module 2A Facility is scheduled to be constructed as a 1994 Line Item<br />
Project Number W-100. The conceptual design is currently underway and<br />
scheduled for completion in July of 1992. The facility is to start operation<br />
in September 1999 in accordance with the Tri-Party Agreement Milestone M-19.<br />
The Waste Receiving and Processing ( WRAP) Module 2A facility conceptual design<br />
is a contact handled ( CH) solid low-level radioactive mixed waste (LLMW)<br />
-- treatmer,t--€aci'i-t-y: -Tfie---facilaty will provide nnn-tharmal (
Task Descri ption<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Sampling and characterization daLa already available for waste scheduled for<br />
treatment in the WRAP 2A module will be collected, evaluated, analyzed, and<br />
summarized.- -Tlr,'s data-wi-ll form-the basis for--defining the -requirea -disposal<br />
criteria. Technical literature searches will be made to define waste<br />
immobilization and solidification options that can be applied to the different<br />
summarized waste streams. Lab screening tests will be made to verify<br />
appiication-of imnrooiiizatian- or solidification eptions to the C-018H and 183H<br />
WRAP waste streams. This information and the status of the disposal work will<br />
be made available in a brief report prior to the validation application<br />
(August 15, 1992). The balance of FY 1992 will be devoted to resolving any<br />
validation questions.<br />
Activitie s and Mile stones<br />
Waste activities and milestones are given in a chart on the following page.<br />
Costs and completion dates are given on a second chart.<br />
Deliverables<br />
The following deliverables are anticipated:<br />
D ate Deliv erable<br />
^` ," ,M' ^i^. ,,,<br />
u^/.) i/Vc ^^rin^^ir^c search results<br />
06/01/92 Recommended solidification methods For lab screening<br />
06/30/92 Waste characterization summary<br />
07/15/92 Recomniended solidification methods for all WRAP 2A wastes<br />
08/01/92 BrieF laboratory report<br />
• Recommended solidification methods for C-018H and 183H wastes.<br />
• Waste form characteristics<br />
B-6
00<br />
V<br />
F-'<br />
Activity and Miltstone Chart (FY 199 2),<br />
Activit.y Apr May Jun Jul Aug Sep FY 19 93<br />
1. Summarize Characterization Work<br />
• Collect Waste Data ^<br />
• Evaluate & Analyze Data --- ---1%<br />
• Summarize Information ^<br />
2. Literature Search<br />
• Perform literature search -----o<br />
• Review literat^re and --- ----o<br />
summarize results<br />
• Evaluate waste forms ---- -----^<br />
3. Laboratory Screening<br />
• Recommend lab tests ---- a V<br />
• Initiate lab sc:reen ^ -<br />
• Complete lab screen - __^^<br />
• Write brief status report °--o<br />
• Validation preparation/ --^<br />
response<br />
August - Validation Approval<br />
E<br />
y<br />
E<br />
0<br />
1<br />
H<br />
0<br />
w<br />
T <<br />
0
WHC-SD-W100-TI-003 Rev. 0<br />
Activity Completion Date Cost ($K)<br />
1. Summarize Characterization Work<br />
• Collect Waste Analysis Data 4/30 $ 5<br />
• EvaluaLe and Analyze Data 5/31 10<br />
• Summarize information - 6/30 - 10<br />
2. Literature Search<br />
-- • - perform literature searcii i^or 4/30 - 5<br />
alternate waste forms<br />
• Review literature and summarize 5/31 5<br />
results<br />
• Evaluate candidate waste forms for 6/30 5<br />
screen tests<br />
3. Laboratory Screening<br />
• Recommend waste forms to test 6/1 --<br />
• Initiate lab screening 6/7 5<br />
•Gomplete lah-screeri,n,g . ?/15 10<br />
• Write brief status report 8/1 5<br />
• Resolve an y validation questions 8/15 --<br />
I DOE PRESENTATION AUGUST 15<br />
TOTAL $60<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Laboratory Screenin g C riteria (will make "best effort" try to perform the<br />
appropriate listed tests)<br />
1. Must meet WIIC-EP-0063-3 criteria.<br />
• Jtable iJaSte fGrni<br />
• No free liquid<br />
• Not explosive, Flammable, reactive, nor corrosive<br />
2. Must pass TCLP test for any hazardous constituents.<br />
3. Should appear to meet NRC waste Form characteristics.<br />
• Compressive strength >500 psi for 28-day cure materials.<br />
• Leachability ANS 16.1 leach index >6, stop at 30 days (90-day is<br />
standard).<br />
• Immersion >60 psi after 30-day water inunersion ( 90-day is standard).<br />
• Radiation stability<br />
• Thermal cycling<br />
• Biodegradation<br />
• Free liquid measurement<br />
Exoected Result s<br />
.<br />
-The task plan is expected to provide the necessary support<br />
(Modu}e--2A) fa^^^;}},,^`y_.,,}ida+ =- ^tsn a^vp,;^,aFi^^. ^^^^, A^ summary of<br />
for<br />
the<br />
successful WRAP<br />
waste to be<br />
treated, general applicable treatment methods, and the basic equipment needed<br />
for the work is expected to be available for the validation application.<br />
Issues<br />
• It is assumed that sufficient waste sampling and characterization data is<br />
already available.<br />
• Lab screening tests will verify laboratory solidification and<br />
immobilization methods.<br />
• Certification of waste disposal compliance for specific waste streams will<br />
be eittmilted Irl f1 1992.<br />
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B-10<br />
.e.,
WHC-SD-WIOO-TI-003 Rev. 0<br />
APPENDIX C<br />
THERMOSETTING POLYMER TEST PLAN<br />
Detailed Test Plan prepared by the vendor awarded the contract for<br />
thermosetting polymer testing described in Appendix A. Outlines test<br />
procedures, quality control, and testing deliverables.<br />
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16490 Chiaccothe Itoad<br />
Chagrin Falls, Ohio 440224398<br />
(316) J43-6000<br />
Telex 196071<br />
Telefax (216) 543-6678<br />
WHC-SD-W100-TI-003 Rev. 0<br />
THERMOSETTING POLYMER TEST PLAN<br />
EXPRESS 92RACWH002 DOCUMENT TRANSMITTAL<br />
9 2 0 2 9 7 4<br />
Date July 23. 1992 Page 1 of i<br />
To: Westinghouse <strong>Hanford</strong> Company Subject STOCK Polymer Immobilization<br />
2355 Stevens Drive<br />
Richland, Washington 99352 Tech. Waste Form Oualification Testine<br />
Plant/Station<br />
ATTN: Mr. Dewey Burbank Contract #<br />
.,e H1-60<br />
Req'n #<br />
P.O. # MMW-SVV-277587<br />
Stock Re[. S.O. 6996<br />
The follc^Wg item(s) are enclosed for your revievc<br />
Drawing 0 <strong>Document</strong> it Procedure 0 Manuals q<br />
Print _ Mylar _ Copies _ Copies<br />
Sepia Vellum _ Other-Specify<br />
., _ Apt. Grd<br />
Reference No. Rev. Description ePurpose<br />
6996-0 0 Quality Plan 1<br />
90110 0 Test Procedure 1<br />
MSDS <strong>Document</strong>s 1<br />
90109 0 Leaching Procedures 1<br />
Comments: The above items are submitted for your approval in accordance with your order requirements. We respectfully<br />
request your approval on or before July 31, 1992. We confirm surrogate waste requirements of 25 to 30 pounds each.<br />
•e<br />
ar a.'^-- turwcr ^-0---•^-- uuututauun ^- u ---°^--' rcyuucu, -t---- ptc^uc auvuc. -'.^--<br />
c: - O.M. Wevihotf/G1-59 = W.H.C.%Transmittal only<br />
T. Litchney<br />
S.O. 6996<br />
•wrpore Code<br />
1. Ftst Issue, For Approval<br />
2. Final Isaue. For Records<br />
S. Other-Specify<br />
Stock Equipment Company<br />
A Unit of General Signal<br />
RECEIVED<br />
WRAP DMC)<br />
3. Itevision for<br />
2G rl 1^2<br />
4. Information Onty ^f[« „ 7<br />
C-3<br />
Russell A. CzellSth, Manager<br />
Contract Administration
WHC-SO-W100-TI-003 Rev. 0<br />
SPOCK EQUIPMENT COMPANY<br />
16490 Chllllcothe Road<br />
Chagrin Falls, Ohio 44022<br />
RADWASTE TEST PROCEDURE<br />
10 CFR 61 WASTE FORM<br />
VERIFICATION PROGRAM<br />
t n<br />
Prepared By: Date: ^ Z^ 49 Z<br />
Fria Podmore<br />
Nuclear ngineering<br />
Reviewed By j ^ Date: ZZ<br />
Thomas C. Litchney, Manager<br />
Nuclear Engineering<br />
Approved By. "' Date: ^ ZZ<br />
Michael J. Pavkov, ager<br />
Quality Assurance<br />
Test Performed By:<br />
Test Reviewed By:<br />
SECTION:<br />
SUBJECT:<br />
Technician<br />
Technician<br />
Quality Assurance Engineer<br />
pRl1rFn11RF - GFNFRAI<br />
Date:<br />
Date:<br />
Date:<br />
Revision Letter - 0<br />
Date issueo - JuIv 22, 199^<br />
10 CFR 61 'dASTE FORM VERIFICATION PROGRAM Page at 37<br />
Stock Eouipment Comoany StanCarCs Number -:'01 : 0<br />
C-A
ca-.<br />
tY•^_E<br />
Q .<br />
- - StoGkE4uip+!nent Comoanv<br />
A Unit of General Signal<br />
90.T 6+99•5O•91e6<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TA-BLI+;tSFCf`ii.^c.^,'S<br />
10 CFR 61 WASTE FORM<br />
VERIFICATION PROGRAM<br />
1.0 Specimen Preparation . . . . . . . . . .. .. . ... .. .. . . . . . 3<br />
1.1 Lab Scale, One (1) Crellon Specimens . . . . . . . . . . . . 3<br />
2.0 Testing Procedures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7<br />
2.1 Compressive Strength Test Procedure . : . . . . . . . . . . 7<br />
2.2 Leachability Test Procedure . . . . . . . . . . . . . . . . . 13<br />
2.3 Ninety (90) Day Immersion Test Procedure ...... 20<br />
2.4 Thermal Degradation Test Procedure . . . . . . . . . . . 20<br />
2.5 Bibdeqradatiofi-Test Procedure . . . . . . . . . . . . . . . . 23<br />
2.6 Radiation Test Procedure . . . . . . . . . . . . . . . . . . . . 26<br />
2.7 Presence of Free liquid Test Procedure ..... .... 28<br />
3.0 Assay for Metals . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 30<br />
3.1 Instrumentation . . . . . . . . . . . . . . . . . . . . . . . . . . . 30<br />
3.2 Methods Description . . . . . . . . . . . . . . . . . . . . . . . 30<br />
4.0 Leachability Index Calculations . . . : . . . . . . . . . . . . . . . . 33<br />
4.1 Method of Calculating . . . . . . . . . . . ;. . . . . . . . . . 33<br />
4.2 Data Recording . . . . . . . . . . . . . . . . . . . . . . . . . . . 33<br />
Appendix A - ASTM Standards . . . . . . . . . . . . . . . . . . . . . . . 35<br />
Appendix B - Solidificatioe Liossary . . . . . . . . . . . . . . . . . . : .36<br />
C-5<br />
Paee<br />
Pa,e i, of 37_
.^( SPECIMEN PREPARATION<br />
WHC-SD-W100-TI-003 Rev. 0<br />
STOCK EQUIPMENT COMPANY<br />
10 CFR 61 WASTE FORM<br />
VERIFICATION PROGRAM<br />
1.1 LAB SCALE, ONE (1) GALLON SPECIMENS<br />
1.1.1 Specimen Preparation<br />
PROCEDURE 90110-0<br />
Lab scale, one (1) gallon size specimens, will be prepared for this testing program.<br />
The three (3) groups of specimens prepared for testing are listed in Table 13.<br />
Table 1.1 • Labels, One (1) Gallon Specimen<br />
Group I<br />
Polymer Control<br />
Group II<br />
Waste Stream<br />
Without Co, Sr, Cs<br />
Group III<br />
Waste Stream<br />
With Co. Sr, Cs<br />
Control Ll - -<br />
Waste Number 1 - L2 L3<br />
Waste Number 2 - LA IS<br />
Waste Number 3 - L6 L7<br />
Waste Number 4 - L8 L9<br />
The waste streams listed containing Co, Sr, Cs (Group III), will have between 0.20<br />
and 0.25 weight percent (of the total solidification) as metal, added to them, The<br />
three (3) metal salts that will be added to each of the waste streams listed in<br />
Group III are:<br />
Co (as CoCL2 • 6H20) ACS Reagent Grade,<br />
Sr (as SrCL2 • 61-120) ACS Rea,ent Grade, and<br />
Cs (as CsCL) ACS Reagent Grade.<br />
Mixing of the waste streams and polymer will be accomplished using a high shear<br />
energy mi;ting technique.<br />
Stock Eauipment Companv C-6<br />
A Unit of General Signal<br />
^mm 9199-5n•9^96<br />
Pagc = of
^..<br />
WHC-SD-W100-TI-003 Rev. 0<br />
. , I PROCEDURE 90110-0<br />
i<br />
1.1.2 Sample Tube Insertion<br />
Tubes with the nominal dimensions of 1-7/16' I.D. and two inches (2') s 1/4'<br />
in length will be made. Maximum departure from perpendicularity to the as;s by<br />
either end: 1.0 degree. Maximum out of plane allowance for ends; 0.025 inch.<br />
After the specimens have been cast, the test specimens will be sealed and allowed<br />
to remain undisturbed for a seven (7) day period to permit the polymer/waste<br />
mixture to cure. At the end of the curing period, each specimen will be opened<br />
and the core tube removed. Labeling will be accomplished using the procedure<br />
with the exception that each specimen is not directly labeled, but placed in a<br />
prelabeled, sealed container. For example, the second specimen from the tube<br />
of specimen LZ will carry a label LZA2 on the container. Six (6) specimens<br />
obtained from each solidification, three (3) will be leached in distilled water and<br />
three (3) will be leached in synthetic sea water (per ANSI 16.1 and Section 2.2).<br />
All six ( 6) samples per specimen will be used for the ninety (90) day immersion<br />
test (Section 2.3).<br />
1.13 Mibng of the waste streams and polymer will be accomplished using a high shear<br />
energy mixing technique.<br />
In preparing for the solidification, the polymer will be mixed. This is done to<br />
minimiz e introduction of a random variable into any solidification. The<br />
surrogated waste will be mixed to minimize introduction of a random variable into<br />
any solidification. All components will be preweighed prior to the start of<br />
solidi5cation.<br />
1.1.4 Specimen Cast Preparation<br />
After mixdttg of all the components, the polymer/waste mixture will be poured<br />
into the tubes. All the specimens generated will be covered and allowed to cure<br />
for seven (7) days. The remainder of the polymer/waste mixnue will be used to<br />
obtain a esothertn profile and to determine Free L'quids ( Section 2.7).<br />
Table 1.1a<br />
Test Description Test Procedure Section Number Samples Required<br />
Compressive Strength 2.1<br />
Biodegradation 2.5 3<br />
Radiation 2.6 3<br />
Tnermai Cycie<br />
Degradation<br />
Stock cquipment Company<br />
A Unit of General Signal<br />
ImT W!-SDAIN C-7<br />
zi 3<br />
Page 4 of 3?
WHC-SD-W100-TI-003 Rev. 0<br />
1.15 Laboratory Standard Compression Specimens<br />
PROCEDURE 90110-0<br />
A gallon control specimen will prepared. It will yield at least twenty-four (24)<br />
specimens. The extended curing period will minimize differences in compressive<br />
strength. The standards will be used to minimize differences that may occur<br />
throughout the program due to uncontrollable variations in the experiment. At<br />
least three (3) standards will be selected at random and compression tested each<br />
day that compression testing is planned in the test program.<br />
Stock Equipment Company C-$<br />
A Unit of General Signal<br />
Form 6499•SD•9196<br />
Pa,c .; ot.;7<br />
;:.
Waste Type:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
SPECIMEN PREPARATION DATA SHEET<br />
Specimen Size: Gallon Specimen Label:<br />
Waste Stream Data:<br />
A. pH<br />
B. Temperature °C<br />
C. % Total Solids %<br />
D. % Free Standing Water<br />
E. Density g/cc<br />
Solidification Formula Used:<br />
F. Total Waste Volume 1 Gallons<br />
G. Polymer and Weight kg IN<br />
H. Weight of Waste (F'1000cdi'G) kg lbs<br />
1. Weight of Solidified Product (H+I+J) kg IN<br />
Weight of Metal Salts added to Waste Stream (.25% of K)<br />
Weight ratio of Co in CoCL2.6HZ0 = 4.0375<br />
Weight of CoCL2.6HZO required (.0025K4.0375) kg<br />
Weight ratio of Sr in SrC12.6H,0 = 3.0429<br />
Weight of Sr CL2.H20 required (.0025K3.0429) kg<br />
Weight ratio of Cs in CsCL = 1.2668<br />
Weight of CsCL required (.0025K.1.2663) kg<br />
Mixing Speed rpm<br />
Peak Exotherm °C<br />
Record additional solidification observations on reverse.<br />
Stock E G uipment Company C-9<br />
A Unit of General Signal<br />
gWm 649e-50+91ee<br />
PROCEDURE 90110•0<br />
Technician Date<br />
Technician Date<br />
Pa_c h of "7
,,..<br />
ZA TESTING PROCEDURES<br />
WHC-SD-W100-TI-003 Rev. 0<br />
2.1 COMPRESSIVE STRENGTH TEST PROCEDURE<br />
PROCEDURE 90110-0<br />
This test will be performed as per ASTM D695 (Appendix A) for those samples requiring<br />
compressive strength testing.<br />
2.1.1 Laboratory standard samples shall be chosen at random from the laboratory<br />
standard lot and compression tested. The compressive strength test data shall be<br />
recorded on the Compression Strength Data Sheet at the end of this section. The<br />
average compressive strength and density shall be calculated and recorded. One<br />
standard deviation value for the compressive strength and density will also be<br />
calculated and recorded on the Compressive Strength Data Sheets at the end of<br />
this section.<br />
2.1.2 Prior to beginning the day's compressive strength testing, at least three (3)<br />
random samples from the laboratory standard lot shall be compression tested and<br />
----reC3rded-orrthe-COmpresstve-.citr'cnoth Data Sheets at the end of this section.<br />
2.13 For each sample to be tested, the height, diameter, and mass will be determined<br />
and recorded on the Compressive Strength Data Sheet at the end of this section.<br />
2.1.4 The samples will be compressed individually using a Detroit testing machine<br />
-(Lfodel NTS•1,-number 836)-to-detarnrnethe-tttaximuiztoad.-irrpounds; applied<br />
to the specimen. As the compressive strength tests shall be performed throughout<br />
the program, the Detroit testing machine shall be calibrated by. -a- sertified<br />
calibration technician or by the Stock laboratory technician using a calibration<br />
ring.<br />
2.1.5 The compressive strength of each sample will be calculated by the formula.<br />
C.S. - load<br />
(D2)2><<br />
where C.S. = Compressive Strength, PSI<br />
load - maximum load applied, in pounds<br />
D = diameter of sample in inches<br />
2.1.6 The density of each sample tested will be calculated by the equation.<br />
p = „J(d")Zha<br />
wh_e_re p = dcnsitv. Jcc<br />
m = mass.<br />
h = hei.-Iht. cm<br />
-^^--- ^ --- ^ - d = diameter, rm<br />
Stock EG lLpment Company<br />
A Unit of General Signal<br />
=vi* 5a9e•50-9ie6<br />
of 7<br />
^<br />
,Y
Stock E quipment Company<br />
A Unit of General Signal<br />
Fa.n "98•50A1e6<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
2.1.7 The following information will be entered onto the Compressive Strength Data<br />
Sheet at the end of this section.<br />
a. Specimen Label<br />
b. Diameter of Sample, inches/cm<br />
c. Height of Sample, cm<br />
d. Mass of Sample, g<br />
e. Maximum Load Applied, lbs<br />
f. Calculated Comoressive Strenath, psi<br />
g Densi.., g;w<br />
2.1.8 The average compressive strength and density will be calculated and recorded for<br />
each waste form solidification. One (1) standard deviation value will also be<br />
calculated and recorded for the compressive strength and density of each waste<br />
form solidification.<br />
4<br />
C_l I<br />
Page ? of^
T:5<br />
; i..,<br />
WHC-SD-W100-TI-003 Rev. 0<br />
COMPRESSiVE STRENGTH DATA SHEET<br />
Waste Type: LAHORATORY STANDARD<br />
Date:<br />
Specimen Diameter Height Mass Load C.S.<br />
Label in h m CM ` lbs nsi<br />
Record Additional Observations on Reverse<br />
Technician Datc Technician<br />
Stock Equipment Comoany<br />
A Unit of General Signal<br />
%o.. a+se-so-v^ea<br />
C-12<br />
PROCEDURE 90110-0<br />
Date<br />
Density<br />
z1o;<br />
Pagc a of 37
G' ,.,.<br />
d,_ s<br />
WHC-0-W100-TI-003 Rev. 0<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
Waste Type: LABORATORY STANDARD<br />
Date:<br />
PROCEDURE 90110-0<br />
Specimen Diameter Height Mass Load C.S. Density<br />
Label in hk Sm ° lbs 051 -1LSF^<br />
Record Additional Observations on Reverse<br />
Technician Date Technician Date<br />
Stock E Q uipment Company<br />
A Unit of General Signal<br />
-o.m 6^9e-5n-9/66<br />
C-13<br />
Pa,,,e 9A of 37
^-.-^<br />
Waste Type:<br />
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Speeimen Diameter Height Mass Load C.S. Density<br />
Label in h m cm g lbs nsi rLoc<br />
Rccord Additional Observations on Reverse<br />
Technician Date Technician Date<br />
Stock ECuipment Company<br />
A Unit of General Signal L-14<br />
°e- 5-99-50•916E<br />
Pa;e 10 of _7
Cx<br />
U:<br />
r°...<br />
.• ,<br />
.ti<br />
Waste Type:<br />
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Specimen Diameter Height Mass Load C.S. Density<br />
.<br />
Label in chicint cm l^ lbs ns!_ 1Sc<br />
Rccord Additional Observations on Reverse<br />
Technician Date Technician Date<br />
Stock Equipment Company<br />
A Unit of General Signal<br />
=01m eA98-50-9166 C-15<br />
Pa:c If1A of 37
J<br />
Leachant Solution:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
LEACHABILITY TEST<br />
CnnqPRR.CSNA S'PRFNt:TH DATA SHEET<br />
Specimen Diameter Height Mass<br />
Label in ch/cm cm --L-<br />
Record Additional Observations on Reversc<br />
PROCEDURE 90110-01<br />
Load C.S.<br />
lbs osi<br />
Technician Date Technician Date<br />
Stock Equipment Company<br />
A Unit ot General Signal<br />
Form 6^9e-50-9/!6<br />
C-16<br />
Pa_c II of _?<br />
^ v
-.<br />
LeachantSolution:<br />
Specimen Diameter<br />
T^bel inch/cm<br />
Record Additional Observations on Reverse<br />
WHC-SD-W100-TI-003 Rev. 0<br />
LEACHABILITY TEST<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Height Mass Load C.S.<br />
cm _L- lbs ps!<br />
Technician Date Technician Date<br />
Stock Equipment Company<br />
A Unit of General Signal y_I7<br />
'arm 6A9a-5n-9/66<br />
Page 1 I A of 37
WHC-SD-W100-TI-003 Rev. 0<br />
THERMAL CYCLING<br />
COMPR_ESSIVE ST_RENC:TH DATA SHEET<br />
PROCEDURE go111)•0<br />
Specimen Diameter Height Mass Load C.S.<br />
Label insh/cm cm ^ lbs psi<br />
Record Additional Observations on Reverse<br />
Technician----- Date Tcchtiician Date<br />
Stock Eqwpment Company<br />
A Unit of General Signal<br />
°arm 6+98-50-9i86<br />
C-18<br />
Pagc 12 of 3-1<br />
.r:^
c^1,<br />
WHC-SD-W100-TI-003 Rev. 0<br />
THERMAL CYCLING<br />
COMPRESSiVE STRENCTH DATA SHEET<br />
Specimen Diameter Height Mass Load<br />
Label in ch/cm cm 1!_ Itis<br />
Rccord Additional Observations on Reverse<br />
Technician Date Technician Datc<br />
Stock Equipment Company<br />
A Unit of General Signal<br />
%onn e49e•60-919e<br />
C-I9<br />
PROCEDURE 90110-0<br />
C.S.<br />
nsi<br />
Pa^c 12A of 17
-..-y<br />
- `-=<br />
4y.,<br />
Stock Eouipment Company<br />
A Unit of General Signal<br />
:orm 5498-50-9196<br />
WHC-SD-W100-TI-003 Rev. 0<br />
21 LEACHAB[LITY'PEST PROCEDURE<br />
PROCEDURE 90110-0<br />
The following procedure will be performed for those specimens requiring<br />
Iparhahilirv r^crin..en<br />
.---..--..... .-..-.. -<br />
2.2.1 Leachant Solution Preparation<br />
Two (2) leachant solutions will be used for the leachability testing<br />
portion of this program. The following procedures will be used to<br />
oreoaro the leachant solutions.<br />
'--11.1 Distilled Water<br />
1. Distilled water will be prepared using a corning<br />
Meoa-Pure three (3) liter automatic distiller.<br />
2. The distilled water obtained in Step 1 will be passed<br />
through an ion exchange resin column, and collected<br />
in fifty (50) liter carboys.<br />
3. The carboys will be securely capped, labeled and<br />
stored until needed.<br />
2.2.1.2 Syn thetic Sea Water<br />
2.= Specimen Preparation<br />
1. The synthetic sea water Icachant solution will be<br />
prepared as per ANS 16.1, Appendix D, Page 40.<br />
2. The sea water leachant will be prepared in 20 liter<br />
batches and these batches will be combined and<br />
stored in fifty (50) liter carboys.<br />
3. The carboys will be tightly capped, labeled, and<br />
stored until needed.<br />
2.2.2.1 The following information will be recorded on the Core<br />
Specimen Data Sheet at the end of this section, for cach of<br />
the specimens obtained.<br />
a. Label number<br />
b. Hei^ht, cm<br />
c. Diameter, cm<br />
d. Calculated surface area, (cm2)<br />
C. Volume of leachant solution rcquired, (ml).<br />
f. Leachant time point<br />
C - 20<br />
Pa:•e I;of 17
.....<br />
lry"<br />
-<br />
Stock E a uipment Company<br />
A Unit of General Signal<br />
Fe,m 6.96-50-9/B6 C-21<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
2122 If the height or diameter of a given core specimen has<br />
changed due to swelling, decomposition or any other affect,<br />
the surface area will have changed and the volume of<br />
leachant solution must be adjusted appropriately. In all<br />
cases, the ratio of the volume of Ieachant solution to<br />
surface area of the core specimen will be 10.0.<br />
2.2Z3 Prior to immersion in the Ieachant solution, the specimen<br />
will be attached to the container lid by the following<br />
method.<br />
The specimen will have a plastic fishnet tied around its<br />
exterior surface. A length of dental floss will be used to<br />
suspend the specimen in the Ieachant solution. The dental<br />
floss will be attached to the container lid, and to the plastic<br />
----- ----fishnet aroun d-the spe{:Slfler4 See Figure la and lb.<br />
2.2 .2.4 The following procedure will be followed for the insertion<br />
of the specimen into the leachant solution, and the storage<br />
of each container for the appropriate time period.<br />
--i. For each specimen, the appropriate amount of<br />
Ieachant solution will be determined from the<br />
Specimen Data Sheet.<br />
2. The correct amount of leachant solution will be<br />
placed into the leachant container.<br />
3. The leachant container and cap will be labeled with<br />
the following information.<br />
a. Specimen label<br />
b. Leachant solution (distilled water, sea water)<br />
c. Volume of Ieachant solution (ml)<br />
4. At the start of any given leaching period, the<br />
specimen will be placed into the leachant solution.<br />
The top of the specimen will be covered by the<br />
leachant solution, whilc the bottom of the specimen<br />
will-be suspendcd above the botcom of the Icachant<br />
container, see Figure la and lb.<br />
5. The leachant container will be capped and allowed to<br />
remain undisturbed until the end of the leaching<br />
period.<br />
Page Il of 3?
- - - -<br />
WHC-SD-W100-TI-003 Rev. 0<br />
2.23 Leachant Sample Preparation<br />
Stock c G uipment Company<br />
A Unit of General Signal<br />
^e:m8a0o->p ::a: f:-ZZ<br />
PROCGllURL 90110-0<br />
22.3.1 All liquid samples for the leachability test will be obtaincd<br />
by the use of a volumetric pipet. Prior to the pipetting of<br />
the liquid sample, the leachant solution will be stirred<br />
thoroughly. If necessary, the solution can also be shaken.<br />
Regardless of the mixing procedure used, the leachant<br />
solution must be thoroughly mixed.<br />
3r^Z--- If _tha_Ieachattt_solution- ,ontains- a- p recir^.^t,••, . the<br />
preeipitate must also be assayed ( reference steps 2.23.7<br />
2Z33 An aliquot of the liquid will be extracted from the leachant<br />
solution (minimum of five (5) ml) and deposited into a<br />
volumetric flask. The size (volume, mis) of the aliquot will<br />
be recorded on the Leachant Sample Preparation Data<br />
Sheet at the end of this section.<br />
213.4 The aliquot of sample taken in Step 4 will be diluted<br />
volumetrically using 1% by weight Nitric Acid (HNO3).<br />
The volume to which the aliquot of sample has been diluted<br />
will be recorded on the Leachant Sample Preparation Data<br />
Sheet at the end of this section.<br />
2135 A four (4) ounce (125 ml) polyethylene bottie to be used<br />
for storing the sample will be rinsed with the diluted liquid<br />
sample solution. From five (5) to ten (10) mis of the<br />
diluted liquid sample solution will be poured into the bottle.<br />
The bottle will be capped and shaken. The rinse liquid will<br />
then be discarded.'Ihe remaining diluted liquid sample will<br />
be poured into the rinsed bottle. The bottle will be tightly<br />
capped and stored_ypriehc itt_a cool darkplace-(cupboard).<br />
2.23.6 Each sample bottle will be labclcd with the following<br />
information.<br />
a. Leach specimen label<br />
b. Lcachant solution (sea water or distilled water)<br />
L. Date and time sample obtained<br />
d. Dilution ratio<br />
\OTL: Proceed only after steps 1:J.1 through =?3.6<br />
have been completed.<br />
Pa_e IS of ?7
;=.<br />
.:^;.<br />
WHC-SD-W100-TI-003 Rev< 0<br />
PP.6CEDL']tk 90110-0<br />
Dental Lacl»nt<br />
-Fioss ^ - Solution<br />
Level<br />
Pl.stiC<br />
FisMet Llter<br />
Cor.;si^cr<br />
Figure la<br />
Dentsl ^ / Ltac.`..,t !<br />
r'CSS<br />
Le+tl<br />
J /<br />
'lastic z euart<br />
^<br />
Figure !D<br />
Stcck Equ,ar.ent Com;3ry<br />
A ums -?r 3entr2. Sl:,nei C-23<br />
s^:. y.ve.sav,u,<br />
i':.._ 16 ot=_
2.2.4<br />
Stock E q uipment Company<br />
A Unit of General Signal<br />
Ge,n E499-50-91e6<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
223.7 If the leachant solution contains a precipitate, the entire<br />
precipitate will be collected by filtration. The filter paper<br />
will be either a Whatman 2 or Whatman 5 qualitative filter<br />
paper. The precipitate will be gravity filtered and will not<br />
be washed.<br />
223.8 After the filtration step, the precipitate will be oven dried<br />
at 50-60'C for at lea.st three (3) hours. The precipitate will<br />
then be weighed, the mass of solids determined and<br />
recorded on the Leachant Sample Preparation Data Sheet<br />
at the end of this section. After weighing, the dried<br />
precipitate will be stored in a four (4) ounce polyethylene<br />
bottle. The bottle will be tightly capped and labeled with<br />
the following information:<br />
a. Leach specimen label<br />
b. Leachant solution (sea water or distilled water)<br />
c. Date and time sample obtained<br />
d. Mass of sample<br />
223.9 The filtered leachant solution will then be discarded.<br />
Leachability Specimen Compressive Strength Test<br />
Upon completion of ninety (90) day leachability testing the leachability<br />
- test spe citnens will be com^r•«i ,,. _.... ^.,.. ^ r._ ^sted per Section 2.1 Compressive<br />
Strength Test Procedure. Compression test results will be recorded on<br />
the Leachability Test Compressive Strength Data Sheet at the end of<br />
Section 2.1.<br />
C-24<br />
Pa,c I? of?<br />
^ y
(.7<br />
..^^<br />
-„n<br />
f^.<br />
[Y^.<br />
Waste Type:<br />
Solidification Size:<br />
Specimen Label:<br />
LeaehancSoluuon:<br />
YIHC-SD-W100-TI-003 Rev. 0<br />
SPECIMEN DATA SHEET<br />
olon<br />
PROCEDURE 90110-0<br />
Leachant<br />
Heieht (em) Diameter (cm) Surface Area (cmZ) Volume(ml) Time Point<br />
Record Additional Observations on Reserve<br />
Technician Date Technician Date<br />
Stock Equipment Company<br />
A Unit of General Signal<br />
•a.. s.sa-eo-61ee<br />
-C-25<br />
Page 14 of 37
Waste Type:<br />
Solidification Size:<br />
Specimen Label:<br />
Leachant Solution:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
SPECIMEN DATA SHEET<br />
gallon<br />
PROCEDURE 90110-0<br />
Leachant<br />
Heieht (cm) Diameter (cm) Surface Area (em2) Volume(ml) Time Point<br />
Record Additional Observations on Rcserve<br />
Technician Date Technician Date<br />
Stock Eouipment Company<br />
A Unit of General Signal<br />
va.. 6.ve•so•siea C-26<br />
Pa_e ISA ofi<br />
,:,;
Date: _<br />
Leachability Time Point<br />
Leachant Sample<br />
Label<br />
Record Additional Observations on Reserve<br />
WHC-SO-W100-TI-003 Rev. 0<br />
LEACHANT SAMPLE PREPARATION DATA SHEET<br />
Diluted<br />
Aliouot (ml) Volume (mil<br />
TrrhR:_i2n 1-1 --<br />
Date Technician<br />
3tock E9u_:m:^t comPany C-27<br />
PROCEDURE 90110-0<br />
Solid Mass<br />
Datc<br />
Page<br />
19 of^
LGIG]<br />
_._!-ueacF:ability, Time PoinC<br />
WHC-SD-W100-TI-003 Rev. 0<br />
LEACHANT SAMPLE PREPARATfON DATA SHEET<br />
PROCEDURE 90110-0<br />
Leachant Sample Diluted<br />
Label Aliauot (ml) Volume fmll Solid Mass<br />
Record Additional Observations on Reserve<br />
Technician Date Technician Date<br />
• e^i ^..:. ^^ i:a....^i c:^,:...y,i ^°<br />
_^<br />
Page 19A of 37<br />
A
23 Ninety ( 90) Day Immersion Test Procedure<br />
WHC-SD-W100-TI-003 Rev. 0<br />
90110-0<br />
23.1 The same specimens and data used in the Leachability Test will be used for the<br />
ninety (90) day immersion test.<br />
231 For each specimen the following information will be collected from the<br />
Leachability Test Compressive Strength Data Sheets at the end of Section 2.1.<br />
a. Specimen label<br />
b. Diameter, in/cm<br />
c. Height, cm<br />
d. Mass, g<br />
e. Load, lbs.<br />
t Compressive Strength, PSI<br />
233 The average strength for each type of waste stream and leachant are also<br />
calcuiated and recorded on the Leachability Test Compressive Strength Data<br />
Sheet at the end of Section 2.1.<br />
2.4 Thermal Degradation Test Procedure<br />
2.4.1 Three (3) specimens will be obtained. These specimens will be 2 inches z 1/4'<br />
high, and 1- 7/16' in diameter. Each specimen has been labeled.<br />
2.4.2 All of the specimens to be tested will be placed on a metal (aluminum or steel)<br />
tray, and placed into an oven maintained at 60`C = i'C for one hour. The<br />
temperature of the oven at the start of the one (1) hour heating period, at thirty<br />
(30) minutes into the heating period and at the end of the one (1) hour heating<br />
period will be recorded on the Thermal Cycling Temperature Data Sheet at the<br />
end of this section. The samples will not be disturbed until the end of the one<br />
(1) hour heating period.<br />
2.43 Upon completion of the one (1) hour period, the specimens will be removed from<br />
the environmental chamber and allowed to stand at room temperature for one (1)<br />
hour. The temperature of the room at the start, at thirty (30) minutes and at the<br />
end of the one (1) hour room temperature period will be recorded on the<br />
Thermal Cycling Temperature Data Sheet at the end of this section.<br />
2.4.4 Upon completion of the room temperature period, the specimens will be placed<br />
into a cold chamber, maintained at -40' x I'C, for one (1) hour. The initial<br />
temperature, thirty ( 30) minute and final cold chamber temperatures will be<br />
recorded on the Thermal Cycli.^.g Temperature Data Sheet at the end of this<br />
section.<br />
2.4a At the end of the cold chamber cycle, Step 2.33 will be repeated.<br />
2.4.6 Steps 2.4.2 through 2.45 constitute a single thermal c,vcle. All of the specimens<br />
to be tested will be subjected to thirty (30) full thermal rycles.<br />
Stock = a uioment Company C-29<br />
A Unit n( ' -neralSianal<br />
Pa_e 1.0 of _;7
Stock °7uipment Company<br />
e ^ in^r !) .nosl Cinnal<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
2.4.7 At the end of thirty (30) full thermal eycles, the Compressive Strength Test of<br />
each sample will be performed per Section 2.1. The following data will be<br />
recorded on the Thermal Cycling Compressive Strength Data Sheets at the end<br />
of Section 2.1.<br />
a. Specimen label<br />
b. Diameter, in/cm<br />
c. Height, cm<br />
d. Mass, g<br />
e. Max load, lbs.<br />
f. Compressive Strength, psi<br />
The average compressive strength for each waste type will be calculated and<br />
recorded on the Thermal Cycling Compressive Strength Data Sheets at the end<br />
of Section 2.1.<br />
C-30<br />
pnce it ofi
ty ,..<br />
='`F<br />
r...,,<br />
b<br />
Ly..<br />
Specimen Labels<br />
WHC-SD-W100-TI-003 Rev. 0<br />
THERMAL CYCLING'rF'MPEFtA1'IiRE DATA SHEET<br />
PROCEDURE 90110-0<br />
Initial Temp. Thirty Minute Temp. Final Temp. Average<br />
• Cvale 'C 'C 6C S<br />
Record Additional Observations on Reserve<br />
Technician Date<br />
•a - Heating chamber temperature<br />
h - Room temperatures<br />
C , `.^..^.tin<br />
b..-...___<br />
n chamber temneratures<br />
d - Room temperatures<br />
Stock E9uipment Company<br />
A I Imt nRinnal<br />
C-31<br />
Technician Date<br />
Page s;,. of -",
Specimen Labels<br />
WHC-SD-W100-TI-003 Rev. 0<br />
THERMAL CYCLING TEMPERATURE DATA SHEET<br />
PROCEDURE 90110-0<br />
Initial Temp. Thirty Minute Temp. Final Temp. Average<br />
Cycl e 'C 'C oc- S'`<br />
Record Additional Observations on Reserve<br />
Technician Date<br />
•a - Hcatin,; chamber temperaturc<br />
b - Room temperatures<br />
c - Looiing chamber temperatures<br />
d - Room temperatures<br />
Stock Equipment Company<br />
e i ^.... ..^ r ..-.^^ c.....,^ C-32<br />
Technician Date<br />
`<br />
Pa^^e 22A of 3'<br />
I l
25 BIODEGRADATION TEST PROCEDURE<br />
Stock Equipment Company<br />
A I IMt M GRnPIAl 1ienAi<br />
WNC-SD-W100-TI-003 Rev. 0<br />
ZS.1 new samples will be taken from each solidification prepared.<br />
PROCEDURE 90110-0<br />
25.2 All test work with the exception of compression strength tesring, will be<br />
subcontracted. United States Testing Company, 1415 Park Avenue, Hoboken,<br />
New Jersey will perform this work.<br />
153 The testing will be performed as per ASTM G22-76 and ASTM G21-70.<br />
25.4 The incubation time for the samples will be at least thirty (30) days.<br />
255 After the incubation period, the samples will be returned to Stock, where they will<br />
be compression tested, as per ASTM D695. Compression test results will be<br />
recorded on the Biodegradation Test Compressive Strength Data Sheet at the end<br />
of Section 2.1.<br />
C-33<br />
Page 23 of 3 7
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
BIODECRADATION TEST<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Specimen Diameter Height Mass Load C-S. Density<br />
1.3bSlL inch1S= CM! E lbs pa1 Picc<br />
Rccord Additional Observations on Reverse<br />
Technician Datc Technician Date<br />
Stock Equipment Company<br />
A I lnit nf Qonoral Sinnal<br />
C-34<br />
_-_ P0°c a of 3",<br />
;is
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
BIODEGRADATTON TEST<br />
POMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0 I<br />
Specimen Diameter Height Mass Load C.S. Density<br />
Label sBShLsm sM t lbs osi _rlcc_<br />
Record Additional Observations on Reverse<br />
Technician Date Technician Datc<br />
Stock Equipment Company<br />
] I Ini^ nl l:^nsrel Cinwa^<br />
C-35<br />
Pa,e _.1A ' of= I
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
BIODEGRADATION TEST<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Specimen Diameter Height Mass Load C.S. Density<br />
Label inch/cm cm_ _'L_ lbs pi!_<br />
Record Additional Observations on Reverse<br />
Technician Date Technician Date<br />
c.__.. ^_..:-_e . r.......e....<br />
Pagc ^ of ;;7<br />
=-.
^_...<br />
..^^<br />
C:i1<br />
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
RiODEGRADAT[ON TEST<br />
CQMPRFSSiVE DATA SHEEP<br />
PROCEDURE 90110-0<br />
Specimen Diameter Height Mass Load GS. Density<br />
Label iOchL®_ cm i. lbs psi _s62L-<br />
Reeord Additional Observation.s on Reverse<br />
Technician Date Technician Date<br />
Stock Eauipment Company<br />
C-37<br />
Page 25A of J'^
`v..<br />
2.6 RADIATION TEST PROCEDURE<br />
Stnetr Fnuinmant Cmmnan.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
2.6.1 Three (3) samples from each soGdification will be tested.<br />
PROCEDURE 90110-0<br />
2.6.2 The samples will be sent to the Phoenix Memorial Laboratory, The Universiry of<br />
Michigan.<br />
2.6.3 The test procedure used by the Phoenix Memorial Laboratory will be returned<br />
with the samples upon completion of irradiation.<br />
2.6.4 Each sample will be irradiated until all accumulated dose of one (1) x 103 rads of<br />
gamma radiation had been achieved.<br />
=.6.s The samples will be returned to Stock where they will be compression tested per<br />
Section 2.1 Compressive Strength Test Procedure. Compression test results will<br />
be recorded on the Radiation Test Compressive Strength Data Sheet at the end<br />
of Scction 2.1.<br />
Page -;6 of ?7
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
-- --- - -^-ncDwii^vF1 "cE<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Specimen Diameter Height Mass Load CS. Density<br />
Label inch/cm cm 1! lbs 031___ Y1cc<br />
Record Additional Observations on Reverse<br />
Technician Date Technician Date<br />
Stock Eqt^ipment Company C-39<br />
Page _7 of 37
Date:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
RADIATION TEST<br />
COMPRESSIVE STRENGTH DATA SHEET<br />
PROCEDURE 90110-0<br />
Soecimen_ Diameter Heieht Mass Load C.S. Density<br />
1aheL sahLSL cm i lbs 8i sLoc<br />
Record Additional Observations on Reverse<br />
Technician Date Technician Date<br />
Stock Equipment Company<br />
C-40<br />
Page 27A of _L7_<br />
^:^'
f-^<br />
--<br />
WHC-SD-W100-TI-003 Rev. 0<br />
2.7 PRESENCE OF FREE LIQUID TEST PROCEDURE<br />
PROCEDURE 90110-0<br />
2.7.1 The surface of the polymer matrix will be inspected for free liquid. If liquid is present<br />
it will be collected and the pH determined. The volume of liquid and pH will be<br />
recorded on the Presence of Free Liquid Data Sheet.<br />
2.7.2 The ullage for that particular container will be measured and recorded on the Presence<br />
of Free Liquid Data .cih'cet. -<br />
2.73 A.125' hole will be drilled into the side of the container one inch (1') below the top of<br />
the polymer matrix Any liquid that leaked from the hole will be collected, and the pH<br />
determined. The volume of liquid and pH will be recorded on the Presence of Free<br />
Ijquid Data Sheet<br />
2.7A At increments of one inch (I'), a.125' hole will be drilled and any liquid present will be<br />
collected and the pH determined. 'I7te volume of liquid and pH will be recorded on the<br />
Presence of Free Liquid Data Sheet.<br />
2.7.5 A final .125' hole will be drilled into the center of the bottom of the container. Any free<br />
liquid present will be collected and the pH determined. The volume of liquid and pH will<br />
be recorded on the Presence of Free l.iquid Data Sheet.<br />
2.7.6 The total volume of free liquid will be calculated and recorded on the Presence of Free<br />
liquid Data Sheet<br />
Stook Equipment CompanY<br />
C-41<br />
Page 2$ of 37,
Specimen Label:<br />
Date:<br />
Ullage: inehes<br />
Height of Polymer Matrix: inches<br />
ist Hole<br />
2nd Hole<br />
3rd Hole<br />
4th Hole<br />
5th Hole<br />
6th Hole<br />
Bottom Hole<br />
Total Free Liquid Collected<br />
Record additional observations on reserve<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PRESENCE OF FREE LIQUID<br />
DATA SHEET<br />
Liauid Volume (mis)<br />
Technician<br />
Technician<br />
Engineering<br />
Stock Eauioment Comoam, C-42<br />
PROCEDURr 90ll0-0<br />
Date<br />
Date<br />
Date<br />
Pace -2L of 37<br />
;
^-...,<br />
3•0<br />
ASSAY FOR MEI'ALS<br />
3.1 INSTRUMENTATION<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
The method chosen for the quantitive determination of cobalt, cesium, and strontium is<br />
atomic absorption spearophotometry. An Inmumentation Laboratories Video 11<br />
-pItoMlleter^ Model Number 07570. Serial Number 1207, will be used for all assay<br />
work. 7-e approprim itotlow--eathode lamps to be used a.... -<br />
Cobalt Cat. No. 62928-02<br />
Cesium Cat. No. 62823<br />
Strontium Cat. No. 62835<br />
3.2 MLTHODS DESCRIPTION<br />
The methods used to atomize the samples will be either flame or flameless. The<br />
flameless method involves aspirating the sample into a graphite furnace buvette, which is<br />
electrically heated to the temperature required for atomization.<br />
Due to the nature of the samples to be tested, it is not possible to provide a step-by-step<br />
procedure for the assay of these samples. However, the following procedure will be<br />
adhered to for all assays.<br />
- ^^a- ----- --- - ---- - _ + + + The ,K. a.^.a ...., ,..,,. ^rt^e.r_ ..._ .L,.1enraHon iahnratnries<br />
--- --- Methods Manual for flame and flameless<br />
operations will be used whenever possible.<br />
3A calibration curve of each metal of interest, in each matrix (D.L water or sea<br />
.vACer), will be prepared. Thesc calibration curves will be replicated as often as<br />
netestary<br />
-- --- -- gw^ Any chemical ,estnx modifiers (ie+ ammonium ttitnte) used in the assay will be<br />
identified and recorded on the Atomic Absorption Data Sheet.<br />
3.2.4 The element, matrix, wavelength, bandwidth, deposition time and background<br />
correction will be recorded on the Atomic Absorption Data Sheet.<br />
3.25 Any dilution required to bring the absorbance of a metal specie into the detection<br />
range of the instrument will be recorded. All dilutions will be volumetric<br />
dilutions.<br />
3.16 The method of atomization, flame or tlameless, will be recorded.<br />
3.2.7 Any modifications to the Instrumentation Laboratories methods used will be<br />
recorded. -<br />
3: .8 The Atomic Absorption Data Sheet will be kept in the separate binder. Each<br />
^ data sheet will be photocopies and stored in the Ouality Assurance vault.<br />
a"{ -<br />
Stock Eouioment Company C-43<br />
Page 30 of .47
...4..._^^ ^<br />
---StOOk Cquipm@nt i.ompanr<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
3Z9 For all assays, the original tape record of the values measure by the<br />
spectrophotometer will be labeled and stored with the Atomic Absorption Data<br />
•.^ . ^_<br />
..._a-__e<br />
^.<br />
60t in [ . hc .,...<br />
. ..<br />
Jn<br />
VuYUty t^ u^w n.uL.^. -<br />
C-44<br />
Page .3J_ of 37
t..f<br />
f....,..<br />
P....^<br />
.-- ^<br />
: .^<br />
^-.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
ATOMIC ABSORPTION DATA SHEET<br />
Dats_ Operators(s) :<br />
Element: Matrbc<br />
PROCEDURE 90110-0<br />
Wavelength: nM Bandwidth: nM<br />
Disposition Timr. sec. Background Correction:<br />
Other.<br />
Average<br />
Specimen Concentration<br />
S.N. Label Time Point nb D ilution S.D. R.S.D.<br />
Stock Equipment Company<br />
C-45<br />
Page }L of 'M
:4^<br />
4.0 LEACHABILITY INDEX CALCULATIONS<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
4.1 The method of calculating the leaehab0ity index will be the method used in ANS 16.1,<br />
June 20, 1984 Revision, Pages 20 to 33.<br />
If the cumulative fraction released of a given element exceed 20% of the original amount<br />
.-_ __bf-mef$1,Yite-pYdYfer-shape fSt4or-will-be-SlSed in calculating the eu'cct'iVe diffusivity.<br />
4.2 DATA RECORDINC<br />
Stock Equipment Company<br />
AN leachabiity index calculations will be performed on the Leaehability Index Calculations<br />
Forms (see example at the end of this section). When all leachability calculations for a<br />
specimen are complete, the form will be photocopied and stored in the Quality Assurance<br />
vault<br />
C-46<br />
Page IL of 37
^c.<br />
v<br />
3<br />
0 w.3<br />
cn<br />
a<br />
v<br />
t[ACeRUtIIY IOPtxcnu%AYloNrlloN<br />
----<br />
O<br />
w<br />
lo -<br />
M<br />
m -_^<br />
.- _<br />
d<br />
M<br />
I.rech<br />
1-lerv3l<br />
[lewent _ _ . 3 0, RInse Cont, (PPf) Oete<br />
Mstrle _<br />
An<br />
(^Os)<br />
-<br />
9<br />
!.<br />
OPentorft<br />
Senyile 1.0. - S.A. - cwt 11-_ ce<br />
6..c•<br />
M/r./Y<br />
ilwe<br />
In out<br />
,-<br />
IAI)<br />
f<br />
1-[(AtIn<br />
f<br />
Cone.<br />
Pr0 en ^<br />
-- - - -<br />
en/A°' bn)'b 01 L<br />
- - --•• M<br />
-<br />
M<br />
SIC<br />
2<br />
^1<br />
lA v1<br />
xc<br />
0<br />
1<br />
-4<br />
.,<br />
1<br />
0<br />
w<br />
7tf<br />
CD<br />
<<br />
0
WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX A<br />
ASTM STANDARDS<br />
ASTM B553-79 Standard Test Method for Thermal Cycling of Electroplated Plastics<br />
ASTM D695 Standard Test Method for Compressive Properties of Rigid Plastics.<br />
PROCEDURE 90110-0<br />
ASTM 021-70 Standard Practice for Determining Resistance of Synthetic Polymeric Materials<br />
to Fungi. •<br />
ASTM 022-76 Standard Practice for Determining Resistance of Plastic to Bacteria<br />
These modifications are made for the following reason:<br />
1. Since the compression test stand used is accurate to twenty (20) pounds load<br />
(approximately ten (10) psi compressive strength), the maAmurn aocurary in compressrve<br />
strength is = ten (10) psi. The above modifications do not cause the compressive<br />
strength to vary by more than ten (10) psi at one thousand (1,000) psi (0.1%). Reference<br />
Stock Equipment Company Calculation Number 058-0.<br />
Stock Eq uipment Company<br />
A I Inil nf fiwnwrwl Rinnwl C-48<br />
Page-35 of _37
WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX B<br />
SOLiDff7CATION GLOSSARY<br />
PROCEDURE 90110-0<br />
CATALYSf Atry substance of which a fractional percentage notably affects the<br />
rateAfz chemical rea_^*on without itself consumed or undergoing<br />
-- - a chemical change.<br />
COMPRESSIVE STRENGTH Th e maximum load per unit area that an object can withstand prior<br />
to breaking.<br />
SPECIMENS Cylindera of the solidified produce with the nominal dimensions: 1-<br />
7/16' Dia, Z' Height These cylinders are used for the testing of<br />
compressive strength.<br />
DISSOLVED SOLIDS In an aqueous system, the relative percentage of the total solids that<br />
exist in solution.<br />
EXOTHERM A plot of the temperature versus time.<br />
FINES Particles with a diameter less than 74 mierons, as determined by a<br />
Tyler sleeve.<br />
FREE STANDING LIQUID Liquid that is either.<br />
1. Visible on the surface of a solidifieation sample.<br />
2. Pours or leaks from a container upon the coetainen being<br />
breached or punctured.<br />
LAB SCALE Approximately one (1) gallon in volume.<br />
ONSET The start of a reaction. When used in conjunction with the term<br />
"exotherm', the start of the rise in temperature as a function of<br />
time.<br />
PARTS PER BILLION ppb 1 microgram per liter or one (1) mg per Itiloliter.<br />
PARTS PER MILLION ppm 1 milligram per gram, one (1) g per liter.<br />
PEAK The highest value attained. When used in conjunction with the<br />
tertn 'exotherm'.the highest temperature achieved.<br />
PLATEAU A region in the curve where 9X = 0.<br />
dx<br />
Stock Equipment Company<br />
A I rft;f of C,w%.Hm Sinnal<br />
C-49<br />
Page J6 of ?^7
WHC-SD-W100-TI-003 Rev. 0<br />
PROCEDURE 90110-0<br />
PROMOTER A substance which, when added in relatively small quantities to a<br />
catalyst, increases the catalyst's activity.<br />
SUSPENDED SOLIDS In an aqueous system, the relative percentage of the total solids<br />
more or less uniformly dispersed in the water.<br />
TOTAL SOLIDS In an aqueous system, the residue left after the evaporation of all<br />
the water.<br />
Stock Eq uipment Company<br />
A Unit nf Gwnwrnl Sional<br />
C-50<br />
Page -27 of 37<br />
V.;
WHC-SD-W100-TI-003 Rev. 0<br />
STOCK EQUIPMENT COMPANY<br />
16490 Chillicothe Road<br />
Chagrin Falls, Ohio 4402Z<br />
___ PROMT)RIrNUMBER: 90109-0<br />
Toxicity Characteristic Leaching Procedure<br />
(TCLP)<br />
Prepared Br. ^^1• _ """<br />
Fria Podmore<br />
Nudear eering<br />
Reviewed By: ItC. I.itchney, Manager<br />
Nuclear Engineering<br />
A11proved Bx - r-, ti^^wC 1 4 4^<br />
Michael J. Pavkov, ager<br />
Qual.., °.J^nw -<br />
SECTION: PROCEDURE - GENERAL<br />
SUBJECT: TOXICITY CHARACTERISTIC LEACHING PROCEDURE<br />
Date: t /94L<br />
Date:<br />
? Z Z 9 z<br />
Date: 22 2<br />
Revi s i o n L e tte r - 0<br />
Date Issued - Ju ly 22 . 1<br />
Page 1 of 22<br />
I Stock Eouipment Company Standa rds I Number - 90109 ^<br />
sam No. 639-3-Daiee C-51
.^E<br />
Stock Ea uipment Company<br />
A Unit of General Signal<br />
fermlN¢SDA/a!<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TABLE OF CONTENTS<br />
Toxicity Characteristic Leaching Procedure<br />
(TCLP)<br />
Pace<br />
1.0 Scope and Application . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
2.0 Summary of Method . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
3.0 Interferences .................................. 3<br />
4.0 Apparatus and Materials . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
4.1 Agitation Apparatus . . . . . . . . . . . . . . . . . . . . . . . . . . 3<br />
4.2 Extraction Vessel . . . . . . . . . . . . . . . . . . . . . . . . . . : . 4<br />
43 Filtration Devices . . . . . . . . . . . . . . . . . . . . . . . . . . . . 4<br />
4.4 Filters ..................................... 5<br />
45 pI'I Metcrs . .. .. . . . . . . . .. . .. . . .. . . . . . . . . . . . . S<br />
4.6 Laboratory Balance . . . . . . . . . . . . . . . . . . . . . . . . . . . 5<br />
5.0 Reagents ..................................... 5<br />
6.0 Sample Collection, Preservation, and Handling . . . . . . . . . 6<br />
7.0 Preliminary TCLP Evaluation . . . . . . . . . . . . . . . . . . . . . . 6<br />
7.1 Preliminary Determination of Percent Solids ........ 7<br />
7.2 Determination of Whether Waste is liquid<br />
or Has Insignificant Amounts of Solid Material ... 8<br />
7.3 Determinapon of `wnethEr the Wastes Require<br />
Particle-Size Reduction . . . . . . . . . . . . . . . . . . . . . 9<br />
7.4 Determination of Appropriate Extraction Fluid ..... 9<br />
8.0 Procedure when Volatiles are not Involved . . . . . . . . . . . 10<br />
9.0 Quality Assurance Requirements . . . . . . . . . . . . . . . . . . . 14<br />
.b ..... ........... ........... . , . . . . . . . . . . . . . . . . . . . . . . . . ...<br />
F9gure Number 2 - Rotary Agitation . . . . . . . . . . . . . . . . . . . . . 16<br />
Table Number I - Volatile Contaminates . . . . . . . . . . . . . . . . . . 17<br />
Table Number 2 - Suitable Rotary Agitation Apparatusl ...... 18<br />
Table Number 3 - Suitable Zero-Headspaa Extractor Vessels . 19<br />
Table Number 4 - Suitable Filter Holdersl . . . . . . . . . . . . . . . . 20<br />
Table Number 5 - Suitable Filter Media . . . . . . . . . . . . . . . . . . 21<br />
Appendix A ....................................... 22<br />
C-52<br />
Procedure 90109-0<br />
Page 2„ of 22<br />
. :a
19 SCOPE AND APPLICATION<br />
WHC-SD-W100-TI-003 Rev. 0<br />
STOCK EQUIPMENT COMPANY<br />
Toxicity Characteristic I.each Procedure<br />
F:'C•..P)<br />
Procedure 90109-0<br />
1.1 The TC4P is designed to determine the mobility of both organic and inorganic<br />
contaminates present in liquid, solid, and multiphasic wastes.<br />
1.2 If a total analysis of the waste demonstrates that individual contaminates are not present<br />
in the waste, or that they are present but at such low concentrations that the appropriate<br />
regulatory thresholds could not possibly be exceeded, the TCLP need not be run.<br />
Us SUMMARY OF METHOD<br />
3.0<br />
21 For liquid wastes ( i.e, those containing insignificant solid material), the waste, after<br />
filtration through a 0.6-0.8 an glass fiber filter, is defined as the TCLP extract.<br />
2.2 For wastes comprised of solids or for wastes containing significant amounts of solid<br />
material, the particle-size of the waste is reduced (if necessary); the liquid phase, if any,<br />
is separated from the solid phase and stored for later analysis. The solid phase is<br />
extraeted with an amount of extraction fluid equal to twenty (20) times the weight of the<br />
solid phase. The extraction fluid employed is a function of alkalinity of the solid phase of<br />
the waste. A special extractor vessel is used when testing for volatiles (Reference Table<br />
1, Page 17). Following extraction, the liquid extract is separated from the solid phase by<br />
0.6 to 0.8 µtn glass fiber filter filtration.<br />
2.3 If compatible (i.e., multiple phases will not form on combination), the initial liquid phase<br />
of the waste is added to the liquid extract, and these liquids are analyzed together. If<br />
incompatible, the liquids are analyzed separately and the results are mathematically<br />
combined to yield a volume-weighted average connection.<br />
J 2- P-otcaaal--inte rznces _-strtriy__ - eacoynterea_dunnn ' anA ^ are discuSSed in<br />
-- - ^ -"-'^<br />
the<br />
individual analytical methods.<br />
4.0 APPARATUS AND MATERIALS<br />
4.1 AGITATION APPARATUS<br />
Stock E p uipment Company<br />
A Unit of General Signal<br />
Fp,n 41408-11tM/a6<br />
An aeceptable agitation apparatus is one which is capable of routing the extraction vessel<br />
in an end-over-end fashion (Reference Table 2, Page 18) at thirty (30) s two (2) rpm.<br />
Suitable devices known to EPA are identified in Table 2.<br />
C-53<br />
Page _I of 22
4.2i cna'""ianCiivN va:jSEL<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
4.2.1 When the waste is being evaluated for other than volatile contaminates, an<br />
extraction vessel that does not preclude headspace (e.g. a two (2)-liter bottle)<br />
is used. Suitable extraction vessels include bottles made from various materials,<br />
depending on the contaminants to be analyzed, and the nature of the waste.<br />
It is recommended that borosilicate glass bottles be used over other types of<br />
glass, especially when inorganics are of concern. Plastic bottles may be used<br />
only if inorganics are to be investigated. Bottles are available from a number<br />
of laboratory suppliers. When this type of extraction vessel is used, the<br />
filtration device discussed in Step 43.1 is used for initial liquid/solid separation<br />
and final exuaet filtration.<br />
43 FILTRATION DLVICES<br />
Stock Eyuipment Company<br />
A Unit of General Signal<br />
r^ ene.so-vss<br />
It is recommended that all filtrations be performed in a hood.<br />
43.1 Filter Holder<br />
When the waste is being evaluated for other than volatile compounds, a filter<br />
folder capable of supporting a glass fiber filter and able to withstand the<br />
pressure needed to accomplish separation is used. Suitable filter holders range<br />
from simple vacuum units to relatively complex systems capable of exerting<br />
pressures of up to fifty (50) psi or more. The type of filter holder used<br />
depends on the properties of the material to be filtered (Reference Step 432).<br />
These devices shall have a minimum internal volume of three hundred (300)<br />
mL and be equipped to accommodate a minimum filter size of forty-seven (47)<br />
mm. (Filter holders having an integral capacity of 1.5 liters or greater and<br />
equipped to accommodate a one hundred and forty two (142) mm diameter<br />
filter are recommended.) Vacuum filtration is only recommended for wastes<br />
with low solids content (less than ten percent (10%)) and for highly granular<br />
(liquid-containing) wastes. All other types of wastes should be filtered using<br />
positive pressure filtration. Filter holders known to EPA to be suitable for use<br />
are shown in Table 4 on Page 20.<br />
4.3.2 Materials of Construction<br />
Extraction vessels and filtration devices shall be made of inert materials which<br />
will not leaeh or absorb waste components. Glass, polytetrafluoroethylene<br />
(PTF'E), or type 316 stainless steel equipment may be used when evaluating the<br />
mobility of both organic and inorganic components. Devices made of highdensity<br />
polyethylene (HPDE), polypropylene, or polyvinyl chloride may be used<br />
only when evaluating the mobility of metals. Borosilicate glass bottles are<br />
recommended for use over other types of glass bottles, especially when<br />
inorganics are constituents of concern.<br />
C-54<br />
Page ^i of 22
L:^3<br />
ll<br />
Q.<br />
4 AA :'ILTEP.S<br />
WHC-0-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
Filters shall be made or borosilicate glass fiber, shall contain no binder materials, and shall<br />
have an effective pore size of 0.6-0.8 v.m or equivalent. Filters known to EPA to meet<br />
these specificaaons are identified in Table 5 on Page 21. Prefilters must not be used.<br />
When evaluating the mobility of metals, filtets shall be acid-washed prior to use by rinsing<br />
--with }.ONritrie-ac6d-folhnyed bythree{3}eonsecutivt rinses with doionized dist'led oter<br />
(a minimum of one (1) liter per rinse is recommended). Glass fiber filters are fragile and<br />
_U_..^a U_ L__.u_a ....<br />
5.1GiiilY uc Itauaucu w1u, MrG. -<br />
4S pH METERS<br />
Any of the commonly available pH meters are acceptable.<br />
4.6 LABORATORY BALANCE<br />
^.0 REAGENTS<br />
Any-laboratory-ba}an'te-awr^,trate--Ylthin =0.01 g7a^T; may be used ( all weight<br />
measurements are to be within ± 0.1 gtam).<br />
5.1 REAGENT WATER<br />
Reagent water is defined as water in which an interferant is not observed at or above the<br />
method detection limit of the analyte(s) of interest. For nonvolatile extractions, ASTM<br />
Type II water, or equivalent meets the definition of reagent water. For volatile<br />
extractions, it is recommended that reagent water be generated by any of the following<br />
methods. Reagent water should be monitored periodically for impurities.<br />
5.2 1.ON hydrochloric add (HCl) made from ACS reagent grade.<br />
53 1.0N nitric acid (HNO3) made from ACS reagent grade.<br />
5.4 1.ON sodium hydro)dde (NaOH) made from ACS reagent grade.<br />
55 Glacial acetic acid (HOAJ ACS reagent grade water.<br />
5.6 EXTRACTION FLUID<br />
Stock Equipment Company<br />
A Unit of General Signal<br />
s^ sna•ao.ane<br />
5.6.1 Eztraction Fluid Number 1<br />
This fluid is made by adding 5.7 mL glacial HOAe to five hundred (500) mL<br />
of the appropriate water (Reference Step 5.1), adding 643 mL of 1.ON NaOH,<br />
and diluting to a volume of one ( 1) liter. When correctly prepared, the pH of<br />
this fluid will be 4.93 =0.05.<br />
C-55<br />
Page _L of 22
5.6.2 Extr9ction Fluid Number 2<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
This fluid is made by diluting 5.7 mL glacial HOA, with ASTM Type II water<br />
(Reference Step 5.1) to a volume of one (1) liter. When correctly prepared,<br />
the pH of this fluid will be 2.88 x0.05.<br />
NOTE. It is suggested that these extrection fluids be monitored frequently<br />
for impurities. The pH should be checked prior to use to ensure that<br />
these fluids are made up accurately.<br />
5-7 Analytical-standardsshall br- preparcd atxording totheappxogria e-analyti^l -method.<br />
6_0 SAMPLE COLLECTION. PRESERVATION. AND HANDLINC<br />
6.1 All samples shall be collected using an appropriate sampling plan.<br />
62 At least three (3) separate representative samples of a waste should be collected. The<br />
first sample is used in several preliminary TCLP evaluations (e.g., to determine the<br />
percent solids of the waste; to determine if the waste contains insignificant solids (i.e., the<br />
waste is its own extract after filtration); to determine if a solid portion of the waste<br />
requires particle-size reduction; and to determine which of the two (2) extraction fluids<br />
are to-bc-used-for-the-nenvolatite T.^.._P e..;actior. of waste). The preliminary evaluations<br />
are identified in Seetlon 7.0.<br />
63 Preservatives shall not be added to samples.<br />
6.4 Samples can be refrigerated unless refrigeration results in irreversible physical change to<br />
the waste (e.g., precipitation).<br />
6.5 TCLP estracts should be prepared for analysis and analyzed as soon as possible following<br />
ratraction. -If-theyneed-to-bestored,-evea!s,+ras.hor*.-period of-tittte, storage^ sh ll be at<br />
4°C, and samples for volatile analysis shall not be allowed to come into contact with the<br />
atmosphere ( i.e. no headspace). Reference Section 9.0, Quality Assurance Requirements,<br />
for acceptable sample and excaet holding times.<br />
7_0 PRELIMINARY TCLP EVALUATION<br />
The-prelaninary-'d'CLP-evaluaeons are perfo.^ned on a minimum of one hundred ( 100) grams<br />
representative sample of waste that will not actually undergo TCLP extraction ( designated as<br />
the first sample in Step 6.2). These evaluations include preliminary determination of the<br />
percent solids of the waste; determination of whether the waste contains insignificant solids, and<br />
is therefore, its own extract after filtration; determination of whether the solid potion of the<br />
waste required particle-size reduction; and determination of which of the two (2) extraction<br />
fluids are to be used for the nonvolatile TCLP extraction of the waste.<br />
Stock E uipment Company<br />
A Unit o^ General Signal C-56<br />
F^ YOe-SOA/y<br />
Page A. of 22
4_T<br />
tJrD<br />
o,...Ys<br />
j<br />
^,.,.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
7.1 PRELIMINARY DETERMINATION OF PERCENT SOLIDS<br />
Stock EQ uipment Company<br />
A Unit of General Signal<br />
Fp,n Me.3D•o/M<br />
Procedure 90109-0<br />
Percent solids is defined as that fraction of a waste sample ( as a percentage of the total<br />
_Sample)--fr9tn-wl!lG3nn-llquld- n`a''--bl-ft:._<br />
below.<br />
^1ttt by an wi nppl.FU -applied --nrE -CS--.^iT..<br />
AF ^<br />
- • -<br />
described<br />
r<br />
7.1.1 If the sample is liquid or multiphasic, liquid/solid separation to make a<br />
preliminary determination of percent solids is required. This involves the<br />
filtration device described in Step 43.1 and is outlined in Steps 7.13 through<br />
7.13.<br />
7.1.2 Preweigh the filter and the container that will receive the filtrate.<br />
7.13 Assemble the filter holder and fill following the manufacturer's instructions.<br />
Place the filter on the supportsereen and secure.<br />
7.1.4 Weigh out a representative subsample of the waste (one hundred (100) grams<br />
minimum) and record the wei;ht.<br />
7.1-5 Alow slu*ries to stand to permit the solid phase to settle. Wastes that settle<br />
slowly may be centrifuged prior to filtration. Centrifugation is to be used only<br />
as an aid to filtration. If used, the liquid should be decanted and filtered<br />
followed by filtration of the.solid portion of the waste through the same<br />
filtration system.<br />
7.1.6 Quantitatively transfer the waste sample to the filter holder ( liquid and solid<br />
phases). If filtration of the waste at 4•C reduces the amount of expressed<br />
liquid over what would be expressed at room temperature then allow the<br />
sample to warm up to room temperature in the device before filtering.<br />
NOTE If waste material (greater than one percent (1%) of original sample<br />
weight) has obviously adhered to the container used to transfer the<br />
sample to the filtntion apparatus, determine the weight of this<br />
residue and subtract it from the sample weight determined in Step<br />
7.15 to determine the weight of the waste sample that will be filtered.<br />
Graduallyapp4vaeuum or VxsleTrcv.re of one+-'# totgtl(10}-psi,-u^.r^l air<br />
--orpressurizingr"overthrough the filter.-if-this point is not reached under<br />
ten (10) psi, and if no additional liquid has passed through the filter in any two<br />
(2) minute interval, slowly increase the pressure in ten (10) psi increments to<br />
a maximum of fifty (50) psi. After each incremental increase of ten (10) psi,<br />
if the pressurizing gas has not moved through the filter, and if no additional<br />
liquid has passed through the filter in any two (2) minute interval, proceed to<br />
- the next ten (10) psi inerement. When the pressurizing gas begins to move<br />
through the filter, or when liquid flow has ceased at fifty (50) psi (i.e., filtration<br />
does not result in any additional filtrate within any two (2) minute period),<br />
filtration is stopped.<br />
C-57<br />
Page 7 of
WyC--c0141W- T_I-003 Rev. 0<br />
Procedure 90109-0<br />
NOTL Instantaneous application of high pressure can degrade the glass<br />
_fiher filter and may cause premature plugging.<br />
7.1.7 The material in the filter holder is defined as the solid phase of the waste, and<br />
the filtrate is defined as the liquid phase.<br />
7.1.8 Determine the weight of the liquid phase by subtracting the weight of the<br />
filtrate container (Reference Step 7.1.2) from the total weight of the filtratefilled<br />
container. The weight of the solid phase of the waste sample is<br />
determined by subtracting the weight of the liquid phase from the weight of the<br />
total waste sample, as determined in Step 7.1.4 or 7.1.6. Record the weight of<br />
the liquid and solid phases. Calculate the percent solids using the following.<br />
Percent Solids = Weieht of Solid (Step 7.1.9)<br />
Total Weight of Waste x 100<br />
(Step 7.13 x 7.1.7)<br />
7.2 Determination of Whether Waste is Liquid or Has Insignificant Amounts of Solid<br />
Material<br />
Stock Ea uipment Company<br />
A Unit of General Signal<br />
Fem,M116-3041116<br />
If the sample obviously has a significant amount of solid material, the solid phase must be<br />
subjected to extract5on; proceed to Step 7.3 to determine if the waste requires particle-size<br />
reduction (and to reduce particle-size, if necessary). Determine whether the waste is<br />
liquid or has insignificant amounts of solid material (which need not undergo extraetion)<br />
as follows.<br />
7 21 Remove the solid phase and filter from the filtration apparatus.<br />
72.2 Dry the filter solid phase at one hundred (100) ^20'C until two (2) successive<br />
Weighings yieldzitesame_value within _1°Ja. Record final weight.<br />
NOTE Caution should be taken to ensure that the subject solid will not<br />
flash upon heating. It is recommended that the drying oven be<br />
vented to a hood or appropriate device.<br />
723 Calculate the percent dry solids as follows:<br />
Weight of Dry Waste and Filter -<br />
Percent Dry Solids = Tared Weiaht of Filter x 100<br />
Initial Weight of Waste<br />
(Step 7.1.4)<br />
C-58<br />
Page fi of 22
WHC-SD-W100-TI-003 Rev. 0<br />
-, Procedure 90109-0<br />
f:^q<br />
--i^•.-<br />
s<br />
72.4 If the percent dry solids is less than 0S%u, consult Step 6.2 and proceed to<br />
Section 8.0 if nonvolatiles in the waste are of concern. In this case, the waste,<br />
after filtration is defined as the TCLP extract. If the percent dry solids is<br />
greater than or equal to 0.5%, and if the nonvolatile TCLP is to be performed,<br />
return to the beginning of this Section 7.0 with a new representative waste<br />
sample, so that it can be determined if particle-size reduction is necessary (Step<br />
7.3), and so that the appropriate extraction fluid may be determined ( Step 7.4)<br />
on a fresh portion of the solid phase of the waste. If only the volatile TCLP<br />
is to be performed, reference the NOTE in Step 7.4.<br />
7.3 Determination of Whether the Wastes Require Particle-Size Reduction (Particle-Size<br />
Reduced During this Step)<br />
is<br />
Using the solid portion of the waste, evaluate the solid for particle-size. If the solid has<br />
a surface area per gram of material equal to or greater than 3.1 em2, or is smaller than<br />
one (1) an in its narrowest dimension ( e.g, is capable of passing through a 95 mm (0375<br />
inch) standard sieve), particle-size reduction is not required (Proceed to Step 7.4). If the<br />
-surfaee area is smaller or-the particle=size irrger than described above, the solid portion<br />
-of thewaste is prepared for eatraation by er,ts.:ing, .:uarlr,g, or grinding the waste to a<br />
surface area or particle-size as described above.<br />
NOTE: Surface area requirements are meant for filamentous (e.g., paper, cloth) and<br />
similar waste materials. Actual measurement of surface area is not required;<br />
nor is it recommended.<br />
7 4 Deiermiaatien OfA'rv naie Facvaciinn rjiiiA<br />
PP P<br />
Stock Eouipment Company<br />
A Unit of General Signal<br />
r,,,,, Moa•so.ans<br />
If the solid content is greater than or equal to 05% of the waste and if TCLP extraction<br />
for nonvolatile constituents will take place (Section 8.0), determination of the appropriate<br />
fluid (Step 5.6) to use for the nonvolatiles extraction is performed as follows.<br />
7.4.1 Weigh out a small subsample of the solid phase of the waste, reduce the solid,<br />
if necessary, to a particle-size of approximately one (1) mm in diameter or less,<br />
and transfer 5.0 grams of the solid phase of the waste to a five hundred 500<br />
mL beaker of Erienmeyer flask.<br />
7.4.2 Add 96S mL of reagent waster (ASTM Type II) to the beaker, cover with a<br />
watchglass and stir vigorously for five (5) minutes using a magnetic stirrer.<br />
Measure and record the pH. If the pH is less than 5.0, extraction fluid number<br />
one (1) is used. Proceed to Section 8.0.<br />
7.4.3 If the pH from Step 7.4.2 is greater than 5.0, add 3S mL 1.ON HCI, slurry<br />
briefly, cover with a watchglass, heat to 50'G and hold at 50°C for ten (10)<br />
minutes.<br />
C-59<br />
Page 9 of_71
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
7.4.4 Let the solution cool to room temperature and record the pH. If the pH is<br />
less than 5.0, use extraction fluid number one (1). If the pH is greater than<br />
5.0, use extraction fluid number 2. Proceed to Section 8.0.<br />
75 The sample of waste used for performance of the section shall not be used any further.<br />
Other samples of the waste (Reference Step 6.2) should be employed for the Section 8.0.<br />
L& PROCEDURE WHEN VOLATILES ARE NOT INVOLVED<br />
Although a minimum sample size of one hundred (100) grams (solid and liquid phases) is<br />
required, a larger sample size may be more appropriate, depending on the solids content of the<br />
waste sample (pereent solids, Reference Step 7.1) whether the initial liquid phase of the waste<br />
will be miscible with the aqueous exvact of the solid, and whether inorganies, semivolan'le<br />
organira, pesticides, and herbicides are all analytes of concern. Enough solids should be<br />
generated for extraction such that the volume of TCLP extraet will be sufficient to support all<br />
of the analyses required. If the amount of the extract generated$y the-performaiice of a'single<br />
TCLP extraction will not be sufficient to perform all of the analyses to be conducted, it is<br />
recommended that more than one (1) extraction be performed and that the extracts from each<br />
ern-action be combined and then aliquoted for analysis.<br />
8.1 If the waste will obviously yield no liquid when subjected to pressure filtration (Le. is one<br />
hundred percent (100%) solid Reference Step 7.1), weigh out a representative subsample<br />
of the waste (one hundred (100) grams minimum) and proceed to Step 8.9.<br />
8.2 If the sample is liquid or multiphasic, liquid/solid separation is required. This involves the<br />
filtration device described in Step 43.2 and is outlined in Steps 83 to B.S.<br />
83 Preweigh the container that will receive the filtrate.<br />
---- -----8.4-Aater.^.ble4lacfilter itolder and flater followint: the manufaeturer's instruetions. Place the<br />
filter on the support screen and seeure. Acid wash the filter if evaluating the mobility of<br />
metals (Reference Step 4.4).<br />
NOTE Acid washed filters may be used for all nonvolatile extractions even when<br />
metals are not of concern.<br />
85 Weigh out a representative subsample of the waste ( 110 grams minimum) and record the<br />
weight. If the waste was shown to contain less than 0.5% dry solids ( Step 7.3), the waste,<br />
after filtration is defined as the'f'Q,P extract. Therefore, enough of the sample should<br />
be filtered so that the amount of filtered liquid will support all of the analyses required<br />
of the TCLP eztract. For wastes containing greater than 05% dry solids ( Step 7.1 or 7.2),<br />
use the percent solids information obtained in Step 7.1 to determine the optimum sample<br />
size ( one hundred (100) grams minimum) for filtration. Enough solids should be<br />
generated after filtration to support the analyses to be performed on the TCLP extract.<br />
Stock Equipment Company<br />
A Unit ot General Signal<br />
Fpm 6NdSDA/w<br />
C-60<br />
Page „]Q of 2^^<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
8.6 Allow slurries to stand to permit the solid phase to settle. Wastes that settle slowly may<br />
be eenfused prior to filtration. Centrifugation is to be used only as an aid to filtration.<br />
If used, the liquid should be decanted and filtered followed by filtration of the solid<br />
portion of the waste through the same filtration system.<br />
8.7 Quandtatively transfer the waste sample (liquid and solid phases) to the filter holder<br />
(Reference Step 43.2). If filtration of the waste at 4•C reduces the amount of expressed<br />
liquid over what would be expressed at room temperature, then allow the sample to warm<br />
up to room temperature in the device before filtering.<br />
NOTE If waste material (greater than one percent ( 1%) of the original sample weight)<br />
has obviously adhered to the container used to transfer the sample to the<br />
filtration apparatus, determine the weight of this residue and subtract it from<br />
the sample weight determined In Step 85, to determine the weight of the waste<br />
sample that will be filtered.<br />
Gradually apply vacuum or gentle pressure of one ( 1) to ten (10) psi, until air or<br />
pressurizing gas moves through the filter. If this point is not reached under ten (10) psi,<br />
and if no additional liquid has passed through the filter in any two (2) minute interval,<br />
slowly increase the pressure in ten ( 10), two ( 2) minute intervals, slowly increase the<br />
pressure irrten{18}* inaetnettts-tsriasdmum-offuty{i0)psi.- After-each incremental<br />
-ir.crcax of-rsn ( lm p^, if the pressurizing gas has not moved through the filter, and if no<br />
additional liquid has passed through the filter in any two (2) minute interval, proceed to<br />
the next ten ( 10) psi inaement. When the pressurizing gas begins to move through the<br />
_fiiter,Dr wherLtheJiquidflow-has-=asedacfifty(S0)psi ( 's,e« filtration does not result in<br />
any additional filtration within a two (2) minute period), filtration is stopped.<br />
NOTE Instantaneous application of high pressure can degrade the glass fiber filter<br />
and may cause premature plugging.<br />
8.8 The material in the filter holder is defined as the solid phase of the waste, and the filtrate<br />
is defined as the liquid phase. Weigh the filtrate. The liquid phase may now be either<br />
analyzed (Reference Step 8.13) or stored at 4•C until time of analysis.<br />
NOTE: Some wastes, such as oily wastes and some paint wastes, will obviously contain<br />
some material that appears to be a liquid. But even after applying vacuum or<br />
pressure filtration, as outlined in Step 8.7, this material may not filter. If this<br />
is the case, the material within the filtration device Is defined as a solid and<br />
is carried through the extragtiQn-a3-a solid. The-original filter is not to be<br />
replaced with a fresh filter under any circumstances. Only one (1) filter is<br />
used.<br />
stook Eq uipment Company<br />
A Unit of General Signal<br />
F.,o, ena.w.ve, C-61<br />
Page I I of -M
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
8.9 If the waste contains less than 0.5% dry solids (Reference Step 7.2), proceed to Step 8.13.<br />
If the waste contains greater than U3% dry soiids (Reference Step 7:1-or 7.2), and if<br />
particle-size reduction of the solid was needed in Step 73, proceed to Step 8.10. If<br />
particle-size reduction was not required in Step 73, quantitatively transfer the solid<br />
material into the extractor vessel, including the filter used to separate the initial liquid<br />
from the solid phase. Proceed to Step 8.11.<br />
8.10 The solid portion of the waste is prepared for extraction by crushing, cutting, or grinding<br />
the waste to a surface area of particle size as described in Step 73. When the surface<br />
area of particle-size has been appropriately aitered, quantitauvely transfer the solid<br />
material into the extractor vessel, including the filter used to separate the initial liquid<br />
from the solid phase.<br />
NOTE: Sieving of the waste through a sieve that is not Teflon coated should not be<br />
done due to avoiding possible contamination of the sample. Surface area<br />
requirements are meant for filamentous (e.g. paper, cloth) and similar waste<br />
materials. Actual measurement of surface area is not recommended.<br />
8.41-Determine-GRe-Amout:t-af-F.xtraetion-F;uid-to-Add to t,he-Exterior-Vessel<br />
20 x Percent Solids (Step 7.1) x Weight of Waste Filtered<br />
Weight of Extraction Fluid = Steo 8.5 or 8.7<br />
100<br />
Slowly add this amount of appropriate extraction fluid (Reference Step 7.4) to the<br />
extractor vessel. Close the extractor bottle tightly (it is recommended that Teflon tape be<br />
used to ensure a tight seal), secure in rotary extractor device, and rotate at 30 =2 rpm for<br />
18 _2 hours. Ambient temperature (f.e., temperature of room in which extraction is to<br />
take place) shall be maintained at 2Y _3'C during extraction period.<br />
NOTE As agitation continues, pressure may build up within the extractor bottle for<br />
some type of wastes (e.g, limed or calcium carbonate waste may evolve gases<br />
such as carbon dioxide). To relieve excess pressure, the extractor bottle may<br />
be periodically opened (e.g, after fifteen (15) minutes, thirty (30) minutes, and<br />
one (1) hour) and vented into a hood.<br />
8.12 Following the 18 s2 hour extraction, the material in the extractor vessel is separated into<br />
its component liquid and solid phases by filtering through a new glass fiber filter, as<br />
outlined in Step 8.7. For final filtration of the TCl-P extract, the glass fiber filter may be<br />
chanaed, i_f_necessary^tofacilitate filtration. Filter(s) shall be acid washed (Reference Step<br />
4.4) if evaluating the mobility of metals.<br />
8.13 The TCLP Extract is Now Prepared<br />
8.13.1 If the waste contained no initial liquid phase, the filtered liquid material<br />
obtained from Step 8.12 is defined as the TCLP extract. Proceed to Step 8.14.<br />
Stock Eq uipment Company<br />
A Unit of General Signal C-62<br />
fen„ 449a-SDA1e6<br />
Page JL of ^7
(FM<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
8.132 If compatible ( e.g. multiple phases will not result on combination), the filtered<br />
liquid resulting from Step 8.12 is combined with the initial liquid phase of the<br />
waste as obtained in Step 8.7. This combined liquid is defined as the TCLP<br />
extract. Proceed to Step 8.14.<br />
8.13.3 If the initial liquid phase of the waste, as obtained from Step 8.7, is not or may<br />
not be compatible with the filtered liquid resulting from Step 8.12, these liquids<br />
are not combined. The liquids collectively defined as the TCLP eztract, are<br />
analyzed separately, and the results are combined mathematically. Proceed to<br />
Step 8.14.<br />
&14 Following collection of the TCLP extract, it is recommended that the pH of the extract<br />
be recorded. The extract should be immediately aliquoted for analysis and properly<br />
preserved (metal aliquots must be acidified with nitric acid to pH ±2; all other aliquots<br />
must be stored under refrigei•ation (40C) until anaiyzed)-.fhe-TCLP eztiract shaii be<br />
prepared and analyzed to appropriate analytical methods. TCLP extraess.to be analyzed<br />
for metals, other than mercury shall be acid digested. If the individual phases are to be<br />
analyzed separately, determine the volume of the individual phase (to ±0S%), conduct<br />
the appropriate analyses, and combine the results mathematically by using a simple volume<br />
wnivhMrl ..^. -- avernvf.<br />
-D_ -<br />
Final Analyte Concentration = L.V1=ILE21X21<br />
V1+V2<br />
Where:<br />
Vt - The volume of the first phase (liters).<br />
C1 - The concentration of the contaminant of concern in the first phase (mg/liters).<br />
V2 - The volume of the second phase (liters).<br />
C2 - The concentration of the contaminant of concern in the second phase<br />
(mg/liters).<br />
8.15 The contaminant concentrations in the TCLP extract are compared with the thresholds<br />
identified in the appropriate regulations. Refer to Section 9.0, Quality Assurance<br />
Requi l Cments.<br />
4,Q QiJAI.ITY ASSURANCE REOUIREMENTS<br />
9.1 AII data, including quality assuranee data, should be maintained and available for reference<br />
or inspection. -<br />
9.2 A minimum of one (1) blank (extraction fluid number 1) for every ten (10) extractions<br />
that have been conducted in an extraction vessel shall be employed as a check to<br />
determine if any memory effects from the extraction equipment arc occurring.<br />
Stock Eq uipment Company<br />
A Unit of General Signal<br />
Fmm 41,011-SD-0/06<br />
C-63<br />
Page _I;Z of 22,
^^T^•=<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Procedure 90109-0<br />
93 For each analytieal batch (up to twenty (20) samples), it is recommended that a matrix<br />
----spike=oe--performed. Addition of matrix spikes should occur once the TCLP extract has<br />
been generated (i.e., should not occur prior to performance of the TCLP procedure). The<br />
purpose of the matrix spike is to monitor the adequacy of the analytical methods used on<br />
the TCLP extraet and for determining if matrix interferences exist in analyte detection.<br />
9A All quality control measures described in the appropriate analytical methods shall be<br />
followed.<br />
- - ---9§-"Ahe-method-of standard addition shall be employed for each anaiyte if.<br />
1. recovery of the compound from the TCLP extract is not between 50% and<br />
150%; or<br />
2. if the concentration of the constituent measured in the extract is within 20%<br />
of the appropriate regulatory threshold. If more than one (1) extraction is<br />
being-r-unon samples of the same waste (up to twenty (20) samples), the<br />
method of standard addition need be applied only once and the percent<br />
recoveries applied to the remainder of the extractions.<br />
9.6 Samples must undergo TQ.P extraction within the following time period after sample<br />
receipt.<br />
Stock EDuiomentCompany<br />
A Unit of General Signal<br />
Fpm 64053DA/86<br />
Volatiles - Fourteen (14) Days<br />
Semivolatiles - Forty (40) Days<br />
Mercury - Twenty-Eight (28) Days<br />
Other Metals - One Hundred and Eighty (180) Days<br />
Extraction of the solid portion of the waste should be initiated as soon as possible<br />
following initial solidAiquid separation. TCLP exeracts shall be analyzed after generation<br />
and preservation within the following periods.<br />
Volatiles - Fourteen (14) Days<br />
Semivolatiles - Forty (40) Days<br />
Mercury - Twenty-Eight (28) Days<br />
Other Metals - One Hundred and Eighty (180) Days<br />
C-b4<br />
Page ]4 of 22
C... 6<br />
Wet Waste Sample<br />
Contains no or<br />
Insignifitxnt Nonfilterable<br />
Solids<br />
Liquid/SoGd<br />
Separation:<br />
0.6-0$ µm<br />
Glass Fiber<br />
Filtiation<br />
Liquid<br />
NIiC-Sfa-'d100-T1-003 Rev. 0<br />
FICURE NUMBER I<br />
TCLP FLOWCHART<br />
Representative<br />
Waste Sample<br />
Discard Dry Waste<br />
Solid Sample<br />
Reduce Partiek-Size if<br />
> I an in narrowest<br />
dimension or surface<br />
area
Stock Ec^uiD.^.tent Cam08ny<br />
A iJnM c Ganaral Sipnat C-66<br />
fp^w<br />
WHC-SD-W100-TI-003 Rev. 0
^...,<br />
. ,.y^<br />
h:.r<br />
WHC-SD-WI00-Ti-003 Rev. 0<br />
TABLE 1<br />
VOLATILE CONTAMINANTS<br />
COMPO CAS NUMBER<br />
ACETONE 67-64-1<br />
N-BUTYL ALCOHOL 71-36-6<br />
CARBON DISULFIDE 75-15-0<br />
CARBON TETRA RIDE 56-23-5<br />
CHLOROBENZENE 108-90-7<br />
METHYLENE CHLORIDE 75-09-2<br />
METHYL ETHYL KETONE 78-93-3<br />
M^I.IJOBUIIL I^L1ONE--.-.-_ ivv-iv-i - - -<br />
TETRACHLOROETHYLENE 127-18-4<br />
TOLUENE 108-88-3<br />
1.1.1 - TRICHLOROETHANE 71-55-6<br />
TRIClII.OROETHYL.ENE 79-01-6<br />
TRICHLOROFLUOROMETHANE 75-694<br />
XYLENE 1330-20-7<br />
Procedure 90109-0<br />
Includes eompoundidentified in the Land Disposal Restrictions Rule. If any or all of these<br />
compounds are of eoneern, the zero-headspace extractor vessel shall be used. If other<br />
( nonvolatile) compounds are of ooneern, the conventional bottle extractor shall be used.<br />
Stock Eq uipment Company<br />
A Unit of General Signal C-67<br />
iynn NfaMind/M<br />
Page _7 of ,22
?A.`<br />
f ?'<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TABLE 2<br />
SUITABLE ROTARY AGiTATION APPARATUSI<br />
COMPANY LOCATION MODEL<br />
Procedure 90109.0<br />
Associated Design and Manufacturing Alexandria, Virginia 4-Vessel Device<br />
Com pany (703) 549-5999 6-Vessel Device<br />
Lars Lande Manufacturing Ulhivnore Lake, Michigan 10-Vessel Device<br />
(313) 449-4116 5-Vessel Device<br />
IRA Machine Shop and Laboratory Santurce, Puerto Rico 16-Vessel Device<br />
(809) 752-4004<br />
EPRI Extractor 6-Vessel Device2<br />
Rexnord Milwaukee, Wisconsin 6-Vessel Device<br />
(414) 643-2850<br />
Analytical Testing and Consulting Warrington, Pennsylvania 4-Vessel Device<br />
Services, Inc. (215) 343-4490<br />
Any device that rotates the extraction vessel in an end-over-end fashion at 30 _2 rpm<br />
is acceptable.<br />
2 Although this device is suitable, it is not commercially made. It may also require<br />
retrofitting to accommodate ZHE devices.<br />
Stock Eq uipment Company<br />
A Unit of General Signal C-68<br />
Fam 64911-0A/86<br />
Page ]8 of 22
:.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TA3i.E 3<br />
SUITABLE ZERO-HEADSPACE HXTRACTOR VESSELS<br />
Procedure 90109-0<br />
COMPANY LOCATION MODEL<br />
Associated Design and Manufacturing Alexandria, Virginia 3740-ZHB, Gas<br />
Company (703) 549-5999 Pressure Device<br />
MHlipore Corporation Bedford Massachusetts SD1 P581 C5. Gas<br />
(800) 225-3384 Pressure Devices<br />
Analytical Testing and Consulting Warrington, Pennsylvania C102, Mechanical<br />
Services, Inc. (215) 343-4490 Pressure Device<br />
Stock Ea uipment Company<br />
A Unit o( General Signal C-69<br />
- - - -- Fane vmsdiiaiY<br />
Page _19 of 22
WHC-SD-W100-TI-003 Rev. 0<br />
TABLE 4<br />
SUITABLE FII-TER HOLDERS'<br />
Procedure 90109-0<br />
COMPANY LOCATION MODEL SIZE<br />
Nuclepore Corporation Pleasanton, California 425910 142 mm<br />
(800)182-7711 - 410400 47 mm<br />
Micro F-iltration Systems Dublin, California 302400 142 mm<br />
(415) 828-6010<br />
Millipore Corporation Bedford, Massachusetts YT30142HW 142 mm<br />
(800) 225-3384 )0C1004700 47 mm<br />
Any device capable of separating the liquid from the solid phase of the waste is suitable,<br />
providing that it is chemically compatible with the waste and the constituents to be<br />
analyzed. Plastic devices (not listed above) may be used when only inorganic<br />
eontaminants are of concern. The 142 mm size filters are recommended.<br />
Stock EGuipment Company<br />
A Unit of General Signal C-70<br />
Fenn 6495-SD-9199<br />
Page 20 of 22
^' .<br />
WHC-SD-W100-T1-003 Rev. 0<br />
TABLE 5<br />
SUITABLE FQ.TER MEDIA<br />
Whatman Laboratory Products, Uifton, New Jersey OFF 0.7<br />
Incorpo rated (201) 773-5800<br />
Stock Equipment Company<br />
A Unit of Caeneral Signal C-71<br />
Psnn MhSD-^^w<br />
Procedure 90109-0<br />
- ^^^? :^ LOCATION MODEL PORE SIZE1<br />
1 Nominal Pore Size<br />
Page ] of 22
WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX A<br />
Procedure 90109-0<br />
Hazardous characteristics of the solidified specimens will be performed per 40 CFR 261. The<br />
following characteristics will be determined:<br />
Flammab7ity,<br />
Corrosiveness, and<br />
Reaetivity.<br />
Stook Eouipment Company<br />
A Unit o( General Signal C-72<br />
F^ 6Y09-SD-9/16<br />
Page _;2 of _22
^-<br />
^-><br />
^<br />
C^Jl<br />
I I^t<br />
^.:<br />
l<br />
WHC-St]-W100-TI-003 Rev. 0
THIS PAGE INTENTIONALLY<br />
LEF'i° BLANK
c.<br />
03<br />
00<br />
r=3<br />
^t<br />
C^'<br />
II 6.0 II Calibration of Laboratory II PhysicaUMechanical Equipment List II<br />
I11<br />
All I W-277587 II Vendor Certificate f<br />
Instruments and Test Equipment Chemical as applicable Table<br />
I<br />
3 Test All ACS of Cemnlianne I<br />
$1 Lcachability Index and Inamersion Leachability and Leach Index is S^ (6) samples ANS 16.1 and Test Report<br />
Tests . Immersion greater than six (6) per waste fortr.t ASTM D695<br />
and strength is, (^4)<br />
greater than 60 psi, ^<br />
after ninety (90) day<br />
immersio n.<br />
$3 Btodcgradanon Tests No growth.<br />
Strength is greates<br />
;:<br />
than<br />
P:rsisiance to<br />
btologica!<br />
':- Titrec (3) ,'<br />
samples per;.<br />
ASTM 021 and 022<br />
fASTM D695<br />
I ab Repoa'<br />
Test Renort<br />
60 ps mlestanon and w^iste form -<br />
, wtirificanon of (12)<br />
a^ mP ressrve<br />
strength ,<br />
WHC-SD-4i100-TI-003 Rev. 0
THIS PAGE INTENTIONALLY<br />
LEF7 BLANK
LY;<br />
^<br />
C=l .<br />
^.^<br />
.^,..,,<br />
€:^.<br />
MHC-SD-N100-TI-003 Rev. 0
THIS PAGE INTENTIONALLY<br />
LEF'i°BLANK
R:<br />
C=1<br />
rIj<br />
s^ ^<br />
^..<br />
WHC-SD-YlI00-TI-003 Rev. 0<br />
C-79/C-•80
THIS PAGE iNTENTIQNALLY<br />
LEFT BLANK
.,,_..1<br />
---^ - -<br />
i-•_E<br />
?*^^<br />
Material Safety Data Sheet<br />
Product Code: 19631<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Product Name: DERAKANE 011 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Data Printed: 07/14/92<br />
1. INGREDIENTS: (% w/w, unless otherwise noted)<br />
Dow U.S.A.<br />
T^^''^0n^'^^mn~<br />
Mq4tq, MKnqan 48574<br />
Em.wnry S17 • p6-Ya0<br />
Page: 1<br />
MSDS:000660<br />
Styrene monomer CAS/ 000100-42-5 35-505*<br />
Vinyl astiet-tesin "cASi 036425-16-8 BAL.<br />
*for specific percentage of styrene monomer found in this product,<br />
see section 9.<br />
This document is prepared pursuant to the OSHA Hazard<br />
Communication Standard (29 CFR 1910.1200). In addition, other<br />
substances not 'Hazardous' per this OSHA Standard may be listed.<br />
Where proprietary ingredient shows, the identity may be made<br />
available as provided in this standard.<br />
2. PHYSICAL DATA:<br />
BOILING POINT: 294F. 146C*<br />
VAP. PRESS: 7 essNg e20C*<br />
VAP. DENSITY: 3.6*<br />
SOL. IN WATER: Insoluble.<br />
SP. GRAVITY: 1.025-1.075<br />
APPEARANCE L ODOR: Straw yellow, viscous<br />
ODOR: Pungent styrene odor.<br />
*Based on styrene<br />
3. FIRE AND EXPLOSION HAZARD DATA.<br />
FLASH POINT: 74-84F<br />
METHOD USED: PMCC, ASTM 0-93<br />
FLAMMARL; IIMtT!<br />
LFL: 1.15<br />
UFL: 6.12<br />
(Continued on page 2)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
C-81<br />
Iiquid - pungent
WHC-SD-W100-TI-003 Rev. 0<br />
Dow Chemical U.S.A• Midland. MI 48674 Emergency Phone•. 517-636-4400<br />
Product Code: 19631 Page: 2<br />
Product Namc DERAKANE Otl 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSDS:000660<br />
3. FIRE AND EXPLOSION HAZARD DATA: (CONTINUED)<br />
EXTINGUISHING MEDIA: Water fog, foam, alcohol foam, CD2, dry<br />
chemical.<br />
FIRE & EXPLOSION HAZARDS: Upon exposure to heat or flame, an<br />
^_>.. exothermic reaction can develop, followed by decomposition of<br />
product. Keep vapors away from possible ignition sources.<br />
- - - - - - --FiRf`fiGHTiNG EQU1PMEkT: WEar-gLyy!es -..- and ,^r-^•*•"_^ ^-!..• r _SSUre,<br />
nr•<br />
- self-contained breathing apparatus.<br />
4. REACTIVITY DATA:.<br />
STABILITY: (CONDITIONS TO AVOID) Avoid storage in direct<br />
sunlight and at temperatures above 120F, 49C.<br />
INCOMPATIBILITY: (SPECIFIC MATERIALS TO AVOID) Oxidizing<br />
material<br />
HAZARDOUS DECOMPOSITION PRODUCTS: Pyrolysis products such as CO.<br />
HAZARDOUS POLYMERIZATION: May occur. Avoid contact with metal<br />
salts such as ferric and aluminum chlorides, unintended contact<br />
with peroxides, and depletion of inhibitor levels. Avoid<br />
exposure to direct sunlight or temperatures above 120F (49C).<br />
5. ENVIRONMENTAL AND DISPOSAL INFORMATION:<br />
----------- ACTION T0 TAKE FOR SPILLS/LEAKS: Treat as flammable liquid; keep<br />
heat, flame. or spark producing equipment away. Protect<br />
yE'S01nal-f-.•Exo- s;YLene-yapors.---Soak-up s{!iJ-1s iArabserbent<br />
material such as sand and collect in suitable containers.<br />
Residual resin may be removed using steam or hot soapy water.<br />
Solvents are not recommended for cleanup unless the recommended<br />
(Continued on page 3)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
e An Operating Unit of The Dow Chemical Company<br />
C-82<br />
.:J
WHC-SD-W100-TI-003 Rev. 0<br />
Dow Chemical U.S.IIa Midland. MI 48674 Emergency Phone 517-636-4400<br />
Product Code: 19631 Page: 3<br />
Product Name: DERAKANE (R) 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSOS:000660<br />
5. ENVIRONMENTAL AND DISPOSAL INFORMATION: (CONTINUED)<br />
exposure guidelines and safe handling practices for the specific<br />
solvent are followed. Consult appropriate solvent MSOS for<br />
handling inforwation and exposure guidelines. For large<br />
spills, evacuate upwind of spills and contain with dike.<br />
DISPOSAL METHOD: Resin can be disposed of through burning in an<br />
adequate incinerator or burying in an approved landfill in<br />
accordance with federal, state and local regulations.<br />
6. HEALTH HAZARD DATA.<br />
`'. EYE: May cause moderate irritation with corneal injury. Vapors<br />
may irritate eyes. May cause lachrymation (tears).<br />
SKIN CONTACT: Prolonged or repeated exposure may cause skin<br />
irritation. Material may stick to skin causing irritation<br />
upon removal.<br />
SKIN ABSORPTION: A single prolonged exposure is not likely to<br />
result in the material being absorbed through skin in harmful<br />
amounts. The LD50 for skin absorption in rabbits is expected to<br />
be >2000 mg/kg.<br />
INGESTION: Single dose oral toxicity is low. The oral LD50<br />
for rats is >4000 mg/kg. If aspirated (liquid enters the<br />
lung), may be rapidly absorbid through the lunys and result<br />
in injury to other body systems. _<br />
INHALATION: Excessive vapor concentrations are attainable and<br />
could be hazardous on single exposure. Signs and symptoms of<br />
excessive exposure may be anesthetic or narcotic effects.<br />
Excessive exposure may cause irritation to upper respiratory<br />
tract.<br />
(Continued on page 4)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
n An Operatiny Unit of The Dow Chemical Company<br />
C-is3
WHC-SD-W100-TI-003 Rev. 0<br />
Dow Chemical U.SAa Midland MI 48674 Emergency Phone 517-636-4400<br />
Product Code: 19631 Page: 4<br />
Product Name DERAKANE Oil 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Oate Printed: 07/14/92 MSDS:000660<br />
6. HEALTH HAZARD DATA: (CONTINUED)<br />
SYSTEMIC (OTHER TARGET ORGAN) EFFECTS:<br />
Repeated excessive exposures to high amounts may cause central<br />
nervous system, liver, kidney effects and respiratory or eye<br />
irritation. Repeated excessive exposures to smaller amounts<br />
may cause central nervous system effects and respiratory or<br />
,..<br />
;..,<br />
..--------- -- ---------- e,vg iltaz!-EiaQ-.._.$tyrene is reeorred to have caused hearing<br />
loss in laboratory animals upon exposure to high concentrations<br />
(sixteen times the TLV and higher); however, the relevance of<br />
this to humans is unknown.<br />
CANCER INFORMATION:<br />
This mixture contains a component which is listed as a<br />
potential carcinogen for hazard communication purposes _<br />
under OSHA Standard 29 CFR 1910.1200. Components listed<br />
by IARC: styrene. Neither the data from various Iong-term<br />
animal studies nor from epidemiology of workers exposed to<br />
styrene provide an adequate basis to conclude that styrene<br />
is carcinogenic.<br />
TERATOLOGY ( BIRTH DEFECTS):<br />
------ 4e--l4boratory animals, styrene did not produce any effects<br />
on the fetus even at exposure concentrations having an<br />
adverse effect on the mother.<br />
REPRODUCTIVE EFFECTS:<br />
In animal studies, styrene has been shown not to interfere<br />
with reproduction.<br />
MUTAGENICITY (EFFECTS ON GENETIC MATERIAL):<br />
Results of in vitro ('test tube') and animal mutagenicity<br />
tests on styrene have been inconclusive.<br />
(Continued on page 5)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
A An Operating Unit of The Dow Chemical Company<br />
C-84
^<br />
±.£:a<br />
[7.p<br />
-;^<br />
--- ---------<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Dow U.S.A.<br />
Material Safety Data Sheet '""^ro"^"'^;.,,`°";^;;<br />
Esuqsesy m ^ 176-N00<br />
Product Code: 19631<br />
Product Name DERAKANE Otl 411-50 V(NYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92<br />
1. INGHEOOiNiS: (% w/w, wkss atMrw(se aond)<br />
Styrene monomer<br />
Vinyl ester resin<br />
Page: I<br />
MSOS:000660<br />
CASI 000100-42-5 35-50f*<br />
CAS/ 036425-16-8 SAL.<br />
-A7orfpee,tie pzrttentaya of styrar.e mon-c-er found in this prOduet,<br />
see section 9.<br />
_ This docueent is prepared pursuant to the OSHA Hazard<br />
Coenwnication Standard (29 CFR 1910.1200). In addition, other<br />
substances not 'Hazardous' per this OSHA Standard may be listed.<br />
Where proprietary ingredient shovs, the identity may be made<br />
available as provided in this standard.<br />
Z PHYSICAL DATA.<br />
BOILING POINT: 294F, 146C*<br />
VAP. PRESS: 7 essNG e20C*<br />
VAP. DENSITY: 3.6*<br />
SOL. IN WATER: Insoluble.<br />
SP. GRAVITY: 1.025-1.075<br />
APPEARANCE & ODOR: Straw yellow. viscous 18quid - punqent<br />
ODOR: Pungent styrene odor.<br />
*Based on styrene<br />
1 F1RE AND EXPLOSION HAZARD DATk<br />
FLASH 74-84F<br />
METHOD USED: PMCC. ASTM 0-93<br />
FLAMMABLE LIMITS<br />
LFL: 1.15<br />
UFL: 6.15<br />
(Continued on page 2)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
C-85
WHC-SD-W100-TI-003 Rev. 0<br />
Dow Chemical U.S.Ae Midland. MI 48674 Emergency Phone: 517-636-4400<br />
Product Code: 19631 Page: 2<br />
Product Name: DERAKANE (RI 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSDS:000660<br />
3. FIRE AND EXPLOSION HAZARD DATA: (CDNTINUED)<br />
EXTINGUISHING MEDIA: Water fog, foam, alcohol foam. C02. dry<br />
Chela i ca l .<br />
X-) FIRE 6 EXPLOSION HAZARDS: Upon exposure to heat or flame, an<br />
`^-^^'----- -- --- -------- ---e:
WHC-S®-hi1.00-T'.-00?, Rev.<br />
Dow Chemical Midlan4 MI 48674 Emergency Phont 517-636-4400<br />
Code: 19631 Page: 3<br />
Product Name DERAKANE (R) 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSDS:000660<br />
- S--MlRDNMEBRAI.-AA10 DISPOSAL INFORMATION: (CONTINOED)<br />
exposure guidelines and safe handling practices for the specific<br />
solvent are followed. Consult appropriate solvent MSDS for<br />
handling information and exposure guidelines. For large<br />
spills. evacuate upwind of spills and contain with dike.<br />
DISPOSAL METNOD: Resin can be disposed of through burning in an<br />
adequate incinerator or burying in an approved landfill in<br />
accordance with federal. state and local regulations.<br />
6. HEALTII NAZARO OATII•<br />
EYE: May cause moderate irritation with corneal injury. Vapors<br />
may irritate eyes. May cause lachrpsation (tears).<br />
SKIN CONTACT: Prolonged or repeated exposure may cause skin<br />
irritation. Material may stick to skin causing irritation<br />
upon removal.<br />
SKIN ABSORPTION: A single prolonged exposure is not likely to<br />
result in the material being absorbed through skin in harmful<br />
--------- amounts. The L050 for skin absorption in rabbits is expected to<br />
be >2000 mg/kg.<br />
INGESTION: Single dose oral toxicity is low. The oral LD50<br />
for rats is>i000 mqf>-Cq: -if aspirated (li0uid eRters the<br />
lung). may be rapidly absorbed through the lungs and result<br />
in injury to other body systems.<br />
INHALATION: Excessive vapor concentrations are attainable and<br />
could be hazardous on single exposure. Signs and syeptoms of<br />
eIIc!lsiVe i7lposiire may be a.e'thetic or narcotic effects.<br />
Excessive exposure may cause irritation to upper respiratory<br />
tract.<br />
(Continued on page 4)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
* An Operating Unit of The Dow Chemical Company<br />
C-87
WHC-SD-W100-TI-003 Rev. 0<br />
Dow Chemicai USAe niidiand, nni 48674 Emergency Phonr. 517-636-4400<br />
Product Code: 19631 Page: 4<br />
Product Name: DERAKANE Otl 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSDS:000660<br />
6. HEALTH NAZARD DATII• (CONTINUED)<br />
SYSTEMIC ( OTHER TARGET ORGAN) EFFECTS:<br />
Repeated excessive exposures to high amounts may cause central<br />
-------- nervous systes, liver, kidney effects and respiratory or eye<br />
irritation. Repeated excessive exposures to smaller aswunts<br />
-^-! may cause central nervous system effects and respiratory or<br />
eye irritation. Styrene is reported to have caused hearing<br />
^l`- -_...:. ---- - --------lost--ifi-PabBrttLry--ania.}!S -upori exposure to high concentrations<br />
(sixteen times the TLV and higher); however, the relevance of<br />
----- -- tlti-s--to husans is unknown.<br />
CANCER INFORMATION:<br />
This mixture contains a component which is listed as a<br />
--------- ----------- ---<br />
-- -<br />
- w--•. -..•:..^ ., '._.rrt,.enen- for haiard commrnication purposes<br />
'-'- - -<br />
under•05MA Standard 29 CFR 1910.1200. Components listed<br />
_ by i1RCo styr.rw. °_+ ,^, ...r, t.e data _._ from rvarious lo nq-term<br />
animal studies nor from epidemiology of workers exposed to<br />
styrene provide an adequate basis to conclude that styrene<br />
is carcinogenic.<br />
TERATOLOGY ( BIRTH DEFECTS):<br />
--- In laboratory animals. styrene did not produce any effects<br />
on the fetus even at exposure concentrations having an<br />
adverse effect an the sother.<br />
REPRODUCTIVE EFFECTS:<br />
In animal studies, styrene has been shown not to interfere<br />
with reproduction.<br />
MUTAGENICITY ( EFFECTS ON GENETIC iMATERiAL)e<br />
Results of in vitre ( 'test tube') and anioal outagenicity<br />
---- ---- ------ -- tests--a.^. styrene have been inconclusive.<br />
(Continued on oaae 5)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
* An Operating Unit of The Dow Chemical Company<br />
C-88
t;7_7<br />
,...:: -----------<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Dow Chemical U.SA• Midland. NO 48674 Emergency Phone: 517-636-4400<br />
Product Code: 19631 Page: 5<br />
Product Namt: DERAKANE DO 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSOS:000660<br />
7. FIRST AID:<br />
EYES: Irriqate with flowing water immediately and continuously<br />
for 15 minutes. Consult medical personnel.<br />
SKIN: Wash off in flowing water or shower.<br />
INGESTION: Do not induce"vomiting. Call a physician and/or<br />
transport to emergency facility immediately.<br />
INHALATION: Remove to fresh air. If not breathing, give<br />
mouth-to-mouth resuscitation. If breathing is difficult, give<br />
oxygen. Call a physician.<br />
NOTE TO PHYSICIAN: The decision of whether to induce vomiting<br />
or not should be made by the attending physician. If lavage is<br />
... performed, suggest endotracheal and/or esophaqeal control.<br />
Danger from lung aspiration must be weighed against toxicity<br />
when considering emptying the stomach. No specific antidote.<br />
Supportive -^-•-, Treatment based on judgment of the physician<br />
in response to reactions of the patient.<br />
8. HANDLING PRECAUTIONS:<br />
ERPOSURE GUIDELINE(S): Styrene, monomer: ACGIN TLV and OSHA PEL<br />
are 50 Pont TWA. 100 ppm STEL.<br />
VENTILATION: Provide general and/or local exhaust ventilation<br />
to control airborne concentrationsbelow the exposure<br />
guideline.<br />
RESPIRATORY PROTECTION: Atmospheric levels should be maintained<br />
below the exposure guideline. When respiratory protection<br />
is reouired for certain operations, use an approved airpurifying<br />
respirator.<br />
(Continued on page 6)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
* An Operating Unit of The Dow Chemical Company<br />
C-89
'NJ^.' _11-'M.,:' ;,'- .,-.v.<br />
Dow Chemital U.S.A.* -(Nidiand, n"1 49674 Emergency<br />
Phone: 517-636-4400<br />
Product Code: 19631 ---- -Page: 6<br />
Product Name: DERAK/WE OD 411-50 VIN1'L ESTER RESIN<br />
Effective Date: 06/18/9l Date Printed: 07/14/92 RSDS:000660<br />
& HANDLING PRECAUTIDNS.` ICONi1NUED1<br />
...._e SKIN PROTECTION: For brief contact, no preeautions other than<br />
clean body-covering clothing should be needed. When prolonged<br />
or freQuently repeated contact could occur. use protective<br />
clothing impervious to this material. Selection of specific<br />
itps such as gloves, boots, apron or full-body suit will<br />
t<br />
depend on operation.<br />
.-;.., --- -----<br />
_____ ----EYE PROTECTfON: Use chemical goggles. If veDOr exposure causes<br />
eye discomfort. use a full-face respirator.<br />
9. IIDD(TIONAL INFORNIATION:<br />
SPECIAL PRECAUTIONS TO BE TAKEN IN HANDLING AND STORAGE:<br />
Practice good care and caution to avoid skin and eye contact<br />
and to avoid breath:ng vapors. For additional precautions, see<br />
Oow Bulietin. OERAKANE (R) Vinyl Ester Resins - Fabricating<br />
Tips.<br />
RSDS STATUS: Revised section 9.<br />
The following products are represented by master 1660. The specific<br />
composition of styrene monomer found within each product is<br />
indicated as follows:<br />
Derakane 111-35 VER ( 19691) ......................................35`.<br />
Derakane 411-35 Low Inhibitor VER (19774)........................ 35`+<br />
Derakane 411-45 VER ( 19633) ......................................45:<br />
Ozrikane :)1-49 Low Inhibitor VER (19678) ........................ 45<br />
Intermediate Vinyl Ester Res7n 145 ( 08e08) ........... :::........ 45$<br />
Oerakane #Ti-50 ( :a63))...: .....................................505<br />
Intermediate Vinyl Ester Resin 150 (08809) .......................§0S<br />
For information regarding state/provincial and federal regulations see<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
* An Operating Unit of The Dow Chemical Company<br />
C-90
WHC-SD-W100-TI-003 Rev. 0<br />
Daw M.. u^e Mldland, MI 48674 Emergency Phone 517-636-4400<br />
Product Code: 19631 Page: R-1<br />
Product Name: DERAKANE gri 411-50 VINYL ESTER RESIN<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSDS:000660<br />
REGULATORY INFORMATION: (Not meanl to be all-inclusive--seleead<br />
regutmfeas represemedJ<br />
NOTICE: The information herein is presented in good faith and believed<br />
to be accurate as the effective date shown above. Mowever, no<br />
warranty, express or ioplied, is given. Regulatory requirements are<br />
subject to change and may differ from one location to another; it is<br />
the buyer's responsibility to ensure that its activities comply with<br />
federal, state or provincial. and local laws. The following specific<br />
- ---- - °-information ' ^ 8 for the -rpo±e of eomplyiny with numberous federal,<br />
state or provincial, and local laws and regulations. See MSb Sheet for<br />
health and safety information.<br />
U.S. REGUUITIONS<br />
.............r<br />
SARA 313 INFORMATION: This product contains the following substances<br />
subject to the reporting requirements of Section 313 of Title III of<br />
the Superfund Amendments and Reauthorization Act of 1986 and 40 CFR<br />
Part 372:<br />
CHEMICAL NAME CAS NUMBER CONCENTRATION<br />
----------------------------------------------------------------------<br />
STYRENE 000100-42-5 35 -50 =<br />
SARA HAZARD CATEGORY: This product has been reviewed according to the<br />
------€PA"1a3ard-Categories" promulgated under Sections 311 and 312 of the<br />
Superfund Amendment and Reauthorization Act of 1906 (SARA Title III) and<br />
is considered• under appiiEahl- _efinitiens, to meet the following<br />
categories:<br />
An inaediate heaith hazard<br />
A delayed health hazard<br />
A fire haxard<br />
A reactive hazard<br />
(Continued on page R-2)<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
* An Operating Unit of The Dow Chemical Company<br />
C-91
Dow Chemical U.SAa Mid!and, MI 48674 Emergency Phone: 517-636-4400<br />
Product Code: 19631 Page: R-2<br />
Product Blame: UERAKANE uu 411-50 .^:'4: E.,( ,o,ES!N<br />
Effective Date: 06/18/91 Date Printed: 07/14/92 MSDS:000660<br />
REGULATORY INFORMATION (CONTINUED)<br />
CANADIAN REGULATOINS<br />
-- --------- Ti.. Werkelace Mazardous Materials Information System (W.M.M.!.S.)<br />
C!assificat!on for this product is:<br />
82<br />
02A<br />
^ 026<br />
-----------------------------<br />
The Transportation of Dangerous Goods Act (T.D.G.A.) classification for<br />
this product is:<br />
Resin Solution/Class 3.3/UN1866/111<br />
(R) Indicates a Trademark of The Dow Chemical Company<br />
The Information <strong>Here</strong>in Is Given In Good Faith. But No Warranty.<br />
Express Or Implied, is Made. Consult The Dow Chemical Company<br />
For further Information.<br />
* An Operatinq Unit of The Dow Chemical Company<br />
C-92<br />
a:
^ ^..rYfl VF •UIYb<br />
1 1<br />
AGA GllS. NC. Cr6) 642Ee0o<br />
s225 oAKTRE£ eotaFVario<br />
P.O. 6oX 94737<br />
CLEVBJWD, OH 441011TS7<br />
Rev. 0<br />
PnOO . NN+ CA4 •<br />
Carbon Dioxide 124-38-9<br />
TaAOE wW[ A.,o sYNaWw<br />
OOT u^. ra:<br />
.'..Ok YL<br />
MATERIAL<br />
SAFETY<br />
DATA SHEET<br />
NO. 15<br />
Carbon Dioxide ; Carbonic Anhyd rid e ^„^^<br />
UN 1013<br />
014EMIrxwwE•w3Ynonr Oivision 2.2<br />
Carbon Dioxide<br />
fSSUE oAT[ An011EN40N9 Ch@yy FavYr<br />
Revised February 1991 CaT.bonate<br />
HEaLTH wsfeQn nere<br />
TI AYEfiA EY Rfe UMI ---<br />
5,000 Mo1ar PPM• ST0. = 30,000 Molar PPM (AC6IH I990-1991). ' OSHA 1989 TWA = 10,000 Nola<br />
PPM; SiEL a 30,600 Motar PPM<br />
J.wi.IV.IJVa'LV'VJYaar . . - .<br />
Inhalation : Low concentrations (3-5 molar %) cause increased respiration and headache.<br />
Eight to 15 molar S concentrations cause headache, nausea and vomiting which may lead to<br />
unconsciousness if not moved to open air or given oxygen.<br />
High concentrations cause rapid circulatory insufficiency leading to cooB and death.<br />
TOXICq60pIC/1L PROPEfiT1ES<br />
Carbon dioxide is the most powerful cerebral vasodilator known. Inhaling large concentTations<br />
causes r=apid circuiaPrry insufficiency leading to colrm and death. Chronic,<br />
harmful effects are not known frxn repeated inhalation of low (3-5 molar Z)<br />
' _^..--..-.-..-..-.<br />
Carbon dioxide is not listed in the IARC, NTP or by OSHA as a carcinogen or potential<br />
carcinogen.<br />
Persons in ill health where such illness would be aggravated by exposure to carbon<br />
dioxide should not be allowed to work with or handle this product.<br />
MGOMrEMDED qRaf AIO TREAif/elYf •<br />
PROMPT MEDICAL ATTENTION IS MANDATORY IN ALL CASES OF OvEREXPOSURE TO CARBON DIOXIDE.<br />
RESCUE PERSONNEL SHOULD BE EpUIPPED NITH SELF-CONTAINED BREATHING APPARATUS.<br />
Inhalation : Conscious persons should be assisted to an uncontaminated area and inhale<br />
fresh air. Quick removal from the contaminated area is most important. Unconscious<br />
persons should be moved to an uncontaminated area, given assisted respiration and<br />
supplemental oxygen. Assure that vomited material does not obstruct the airway by use<br />
of positional drainage. Further tr'eatment should be symptomatic and supportive.<br />
C-93<br />
C02
WHC-SD-W100-TI-003 Rev. 0<br />
This page intentionally left blank.<br />
C-94
WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX D<br />
CHARACTERIZATION DATA<br />
A. An overview of characterization data used in this stage of Waste Form<br />
Qua7ification testing.<br />
B. Two memos prepared by WHC Chemical Process Engineering Group. The first<br />
summarizes the "to date" characterization data on the 183H Basin wastes -<br />
the largest volume of the currently stored low level mixed waste types.<br />
The second memo describes the recommended waste forms for the various<br />
basin wastes and some to the future generated waste streams (LETF and<br />
Incinerator Ash).<br />
memo i: JBW-183-I701<br />
Memo 2: CPE-WOG-002<br />
C. Four WHC generated Internal Letter Reports reviewing the records of the<br />
contents of all currently stored low-level mixed waste at the <strong>Hanford</strong><br />
<strong>Site</strong>. The characterization data and the EPA waste codes were used to<br />
group the containers into lots of similar waste types for processing.<br />
A technical evaluation was then performed (by a solidification technology<br />
expert) as to the best treatment approach for each lot. The rationale<br />
for the treatment selection is included.<br />
Memo numbers: 87330-92-MLS-023, -025, -026, and -028.<br />
D-1
WHC-SD-W100-TI-003 Rev. 0<br />
This page intentionally left blank.<br />
R_. 9<br />
- u-G<br />
r"T
CHARACTERIZATION DATA<br />
Part A: Overview of Characterization Data<br />
The purpose of the WRAP 2A facility is to receive and process for disposal<br />
mixed radioactive-hazardous wastes received at the <strong>Hanford</strong> <strong>Site</strong>. These wastes<br />
C iiz%"wid%^'%#'tEt}^$f<br />
r rr ^<br />
Tr^'at£Y'i%i^ fruiii a i^uiiiGEr Or d1TTerellt faC11it1eS.<br />
A any of these wastes are already in storage, but some are anticipated from<br />
near-term future facilities. The largest volume generators include the<br />
following: 183-H Basin, the C-018 Liquid Effluent Treatment Facility (LETF)<br />
to treat the 300 Area Process Sewer, the Low Level Mixed Waste ( LLMW) thermal<br />
treatment facility, and the L-045 LETF ( treat or stabilize evaporator<br />
overheads). This represents roughly 80% of the waste expected at WRAP 2A. A<br />
detailed search of the waste generating and receiving records have been made<br />
to collect and summarize the available waste characterization data.<br />
183-H Basin Wastes<br />
A summary of the basin wastes (in dry form) is given below. It includes the<br />
ae:^ basin sand blasting grit from cleaning up the basins after removal of basin<br />
solid and liquid wastes.<br />
„"._F<br />
f_n_p.r_ _<br />
in ^i.nn rl..'n_ra<br />
Sodium 29%Zirconium4%<br />
Sulfate 29%Silical%<br />
Copper 17%Uraniumtrace<br />
Nitrate 11%Technetium-99 trace<br />
Fluoride 9%<br />
Basin 1 - Outer Sludge<br />
Sodium 29%Silicon3%<br />
Sulfate 46%Nitrate2%<br />
Fluoride 9%Uraniumtrace<br />
Copper 8%Technetium-99 trace<br />
Zirconium 3%<br />
Basin 1 - Sorbed Liauid<br />
The 1iq;rid, wet-sludge-,- asrd eryst-aili-ne rrteriai was removed and sorbed onto<br />
probably a diatomaceous earth absorbent. The liquid fraction was probably<br />
mostly sodium nitrate, possibly some sodium sulfate, with a slight trace of<br />
- uranium and possibly technetium.<br />
Basin 2 - Sludge<br />
Copper 28%Zirconium6%<br />
Nitrate 30%Silicon4%<br />
Sodium 21%Fluoride2%<br />
Sulfate 9%Uraniumtrace<br />
D-3
Y:,Cse<br />
Basin 3 - Sludqe<br />
Sodium 31%Sulfate5%<br />
Nitrate 35%Fluoride2%<br />
Copper 15%Uraniumtrace<br />
Zirconium 12%<br />
Basin 3 - Crystals<br />
Sodium 62%Nitrate2%<br />
Sulfate 30%Uraniumslight trace<br />
Fluoride 6%<br />
Ba5 i n 4 -<br />
Sodium<br />
IJ;+^.^+..<br />
1.1 1 GLO<br />
Sulfate<br />
Sludae<br />
38%Fiuoride2%<br />
47%iiraPi i uiTitrace<br />
13%<br />
Basin 4 - Crystals<br />
;N`^<br />
v>,<br />
Sodium<br />
Nitrate<br />
Copper<br />
Zirconium<br />
38%Sulfate3%<br />
35%Fluoride2%<br />
16%Uraniumslight<br />
6%<br />
trace<br />
Basin 2 - Sorbed Liauid<br />
WHC-SD-W100-TI-003 Rev. 0<br />
The liquid and entrained solids was thought to be sorbed on to Sorbond LPC-II,<br />
a calcium type absorbent. The chemical content of the liquid is given below:<br />
Sodium 27%Uraniumtrace<br />
Nitrate 73%Technetiumslight trace possible<br />
Sand Blast Grit<br />
The grit is at least 90% grit, the balance being a mixture of basin salt,<br />
sludge, dirt and sand, and liner material.<br />
Wastes designated Grit 1 and Grit 2 constitute a large volume of drummed basin<br />
wastes at the present time. The grit wastes were generated from cleaning<br />
basins I and 4. Gr_it_1 wasamixturQ of_sand blast grit plus the residual<br />
basin sludge. Grit 2 was a mixture of sand blast grit plus basin 4 sludge.<br />
These wastes are top priority for WRAP 2A processing. The waste compositions<br />
and representative surrogate wastes composition procedure for cement based<br />
testing is given below:<br />
D-4
Grit<br />
Specie or MaterialOverall Content<br />
Sand Blast Grit 90%<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Basin I Sludgel0%<br />
• Sodium = 29%<br />
• Sulfate - 29%<br />
• Copper - 17%<br />
• Nitrate - 11%<br />
• Fluoride - 9%<br />
• Zirconium - 4%<br />
• Silica - 1%<br />
• Molybdenum - 0.05% (uranium stand-in)<br />
• Ruthenium - 0.05% (technetium stand-in)<br />
• Chromium VI - 0.05%<br />
Grit 2 :<br />
Soecie or Material0vera1l Content<br />
Sand Blast Grit90%<br />
Basin 4 Crysta110%<br />
• Sodium - 38%<br />
• Nitrate - 47%<br />
• Sulfate - 13%<br />
• Fluoride - 2%<br />
• Molybdenum - 0.05% (uranium stand-in)<br />
• Chromiur VI - 0.05%<br />
• Cobalt i: - 0.01%<br />
• Strontium II - 0.01%<br />
The basin sludge portion of the Grit 1 surrogate was produced by weighing the<br />
appropriate amount of copper metal powder and dissolving it in dilute nitric<br />
acid which provided the nitrate. Zirconium powder, sulfuric acid, and<br />
hydrofluoric was added and mixed with the liquid in the preceding sequence.<br />
Sodium carbonate was used to neutralize the liquid, and then the chemical<br />
tracer compounds were added. The final pH was adjusted to a neutral value<br />
with nitric acid and sodium carbonate as appropriate. The liquid was dried,<br />
-- mil_fied, cieved to =20 mesh,--and- blended p^rior to use.<br />
The basin crystal portion of Grit 2 surrogate waste was made by weighing and<br />
dissolving the appropriate proportions of sodium nitrate, sodium sulfate,<br />
sodium fluoride, and sodium carbonate in water. The trace compounds were also<br />
added and stirred into the mixture. The liquid was then dried, milled, sieved<br />
to -20 mesh, and blended prior to use. Some carbonate was added as a source<br />
of sodium.<br />
L-045 LETF (300 Area Process Sewer Treatment Sludge)<br />
i.y -The 300 Area, in the past, has typically generated in excess of a million<br />
gallons per day of process water. The process sewer stream is monitored<br />
D-5
WHC-SD-W100-TI-003 Rev. 0<br />
for radioactivity at-keylocations_and di-versioncapability is available to<br />
prevent all but very low level contamination in the stream. There has been<br />
and continues to be some light chemical contamination of the system at times,<br />
making the waste stream hazardous. A waste minimization effort is presently<br />
in place to reduce the overall volume by a factor of 5 to 10 by eliminating<br />
cooling water and other large volume flows. However, this is expected to<br />
increase chemical concentrations in the stream increasing the risk of it being<br />
hazardous more of-the time. A LETF is planned that will use a ferrichydroxide-sulfide<br />
flocculation water treatment method to remove the bulk of<br />
--the chemical contaminants and any residual radionuclides that might be<br />
present. This proposed facility has yet to define-exactl. whatvalume or<br />
composition of mixed waste might be generated. However, ferric hydroxide is<br />
unstable in air to decomposition to ferric oxide hydrate (rust). A surrogate<br />
waste composition of ferric ( iron) oxide, sodium sulfide, polymer flock, and<br />
trace chemicals was weighed, milled, and blended. The chemicals were all dry<br />
(water free) so no drying was performed. There was a batch of ferrichydroxide-sulfide<br />
flock produced, washed, dried, and milled. A sample of the<br />
flock was submitted for analysis and two test cubes were made to verify the<br />
ferric oxi-de surrogate mixture.<br />
The actual ferric oxide mixture used is given below:<br />
r'erric Oxide Sludge Mix<br />
98.7% -<br />
1.3% -<br />
0.07%-<br />
0.01%-<br />
0.01%-<br />
0.01%-<br />
ferric oxide reagent<br />
sodium sulfide<br />
Polymer flock<br />
mercury chloride<br />
trichlorethylene<br />
chromium oxide<br />
ow-Level Mixed Waste Incinerator<br />
---- -- - i'+=Lt^,^J -i-ncj nerator--or -siatfl ar--equipmert i s- pi afiReu' for future i nstal l ati on at<br />
the WRAP facility. The primary waste generated by the incinerator is ash.<br />
Tfie composition of the ash is very dependent upon the materials to be<br />
processed. - Rubber products such as gloves have a high solids residue (>5%).<br />
Plastic materials and resins have a very low residue content (
WHC-SD-W100-TI-003 Rev. 0<br />
The incinerator ash mix used is given below:<br />
Incinerator Ash Mix<br />
Specie or MaterialOverall Content<br />
Fly ash 90%<br />
Clay 8%<br />
Sand<br />
Chromium VI<br />
Cooeer iT<br />
2%<br />
0.01%<br />
O . A1%<br />
-rr-•<br />
Cesium<br />
0.01%<br />
Cerium 0.01% (transuranic stand-in)<br />
Ruthenium 0.01% (technetium stand-in)<br />
Mercury II 0.01%<br />
^.. Barium 0.01%<br />
Lead 0.01%<br />
Silver 0.01%<br />
Selenium 0.01%<br />
Cadmium 0.01%<br />
=.`<br />
C-018 LETF<br />
The C-018 LETF is planned to treat the evaporator overhead liquids. The<br />
primary waste in the overheads is ammonia plus residues of_organics. The LETF<br />
facility will be designed to stabilize the ammonia as ammonium sulfate using<br />
sulfuric acid to neutralize it and destroy the organics chemically (ozone,<br />
ultraviolet). The ammonium sulfate will likely contain a slight trace of<br />
radioactivity (tritium and volatile radionuclides) plus some trace chemicals<br />
making it a ca ndidate mixed waste material. A representative surrogate waste<br />
mixture is giv en below:<br />
C-018 LETF:<br />
Soecie or MaterialOverall Content<br />
Ammonium Ion 26%<br />
Sulfate72%<br />
Nitratel.2%<br />
Silicon0.6%<br />
Chromium VI 0.07%<br />
Fluoride 0.05%<br />
Copper II 0.02%<br />
Cerium 0.02% ( transuranic stand-in)<br />
Nickel II 0.005%<br />
Mercury II 0.001%<br />
Cesium 0.001%<br />
Strontium 0.001%<br />
The materials were weighed in the dry form milled to -20 mesh, and blended.<br />
---------f,ummerc;al- grade fertilizer was used for the basic ammonium sulfate material.<br />
D-7
WHC-SD-W100-TI-003 Rev. 0<br />
From: Chemical Process Engineering JWB-183H-001<br />
Phone: 6-1778 L5-31<br />
--- Date: .June 25, 1go2<br />
Subject: 183-H Solar Basin Waste Characterization<br />
To: J.L. Wescott H2-58<br />
cc: D.A. Burbank H1-60<br />
W.O. Greenhalgh L5-31<br />
J.A. Hunter L5-31<br />
C.A. Petersen H1-60<br />
J.G. Riddelle H2-58<br />
K.M. Weingardt H1-60<br />
E.A. McDaniel ORNL<br />
Attached is the "to date" characterization data for the 183-H Basin wastes.<br />
With the characterization data is a summary chronology, as best as can be<br />
determined, of events involved in the cleanup of the 183-H Basins.<br />
The information contained in the attachment was gathered from several sources.<br />
The primary source for the characterization data was the 183-H Solar<br />
Evaporization Basins Closure/Post-Closure Plan (Rev. 2). Other information<br />
was obtained from various letters and field notes generated during the cleanup<br />
operations.<br />
Since some of the information is 6 to 7 years old it is very difficult to<br />
verify any of the information. Therefore, all data should be viewed with some<br />
degree of uncertainty.<br />
As- more inforrttatien is fourd lt wrl te trammitted as an updaie to this<br />
letter.<br />
It<br />
Biglin<br />
D-8
WHC-SD-W100-TI-003 Rev. 0<br />
183-H BASINS<br />
CLEANUP CHRONOLOGY<br />
Oct 1984 Basin 1 sampled<br />
Wet sludge ( inner basin)<br />
Dry crystalline ( outer basin)<br />
Liquid phase<br />
6-25-92<br />
BASIN 1 SOLID SAMPLES<br />
CONTSTITUENTS GREATER THAN 19'.<br />
(Table I .A-5 183-H Basin Closu re Plan)<br />
' Inner' Basin 'Outer' Basin<br />
Sludge content ( Y) Sludge co ntent (Y.)<br />
Constituent A v e ra ge Ranoe Samole 0-0 Samole 0-9<br />
= Sodium 20.0 17.7 - 23.5 20.5 22 . 9<br />
Co;,per -- 11.9* 10.0 - I1.-2 - 5.4<br />
Zirconium 3.2 1.9 - 3.9 1.6 1.8<br />
Flouride ion 6.0 5.4 - 6.4 7.1 6.7<br />
Nitrate ion 8.0 6.1 - 10.4 1.4 1.6<br />
Sulfate ion 20.2 17.7 - 23.5 35.5 32.7<br />
Water ( dried to<br />
105- C) 22.2 18.7 - 24.5 22.8 23.1<br />
Silicon
WHC-SD-W100-TI-003 Rev. 0<br />
BASIN 1 SOLIDS SAMP LES<br />
EXTRACTION PROCEDURE TOXICITY RESULTS<br />
(Table I.A-21 183-H Basin Closure Plan)<br />
'Inner' Basin 'Outer' Basin<br />
Sludge content (mg/1) Sludge content (mg/1)<br />
Constituent Averane _ Range. Sample 0-0 Samole 0-9<br />
Arsenic
WHC-SD-W100-TI-003 Rev. 0<br />
June - Sept 1985 Basin 1 liquids transfered to adjacent basins.<br />
Jan 1986 Basin 2 sampled<br />
Wet sludge<br />
Liquid phase<br />
Wet sludge and crystalline material removed from<br />
basin. Materials were not segregated. Absorbant used.<br />
Waste volume estimated at 7,646 cubic feet (1700 barrels).<br />
Barrel's contain 4.5 Cu ft of waste and 3 cu ft of<br />
absorbant (type of absorbant unknown - probably<br />
aa..+°'"„'-",.' ".'-<br />
Y_ 16LYq16l_GllY.l Cdf-LII; _<br />
BASIN 2 SLUDGE SAMPLES<br />
CONSTITUENTS GREATER THAN 1%<br />
Constituent content ( %) Range (%)<br />
Copper 13.0 9.9 - 15.4<br />
Sodium 9.7 4.2 - 15.9<br />
Silicon 2.4 0.06 - 9.3<br />
Zirconium 3.2 2.8 - 3.5<br />
Flouride ion 1.1 0.57 - 1.81<br />
Nitrate ion 13.5 8.2 - 17.5<br />
Sulfate ion 3.8 0.65 - 15.2<br />
Moisture 52.7 45.7 - 57.7<br />
pH range 10.8 - 11.9 (liquid phase in contact<br />
- --- w-i-th -s1 udge)<br />
BASIN 2 SLUDGE SAMPLES<br />
TRACE CONSTITUENTS DETECTED<br />
(Table I.A-8 183-H Basin Closure Plan)<br />
Average<br />
Constituent content ( DDm) Ranae (oom)<br />
Aluminum 1950 540 - 4470<br />
Beryllium 6 4.4 - 7.8<br />
Calcium 334 158 - 634<br />
Chromium 450 292 - 727<br />
Mercury 1.3a
WHC-SD-W100-TI-003 Rev. 0<br />
Average<br />
Uranium 1,250 ppm 28 - 2,500<br />
Technetium-99 1.170 pCi/1<br />
WASRE DESIGNATIONS: Basin 2 sludge; WT02 - Toxicity ( DW), D007 - EP TOX (Cr)<br />
U123,PO29, P030, P098, P120<br />
July_-Sept_1985>aiqu_id__from-Basin_2 transfered to Basins 3 & 4.<br />
Basin 2 sludge packaged.<br />
E-'t: 8,955 Cli^i3ic PEet 11990 oarT°elr - 4.5 cu ft<br />
waste and 3 cu ft of absorbant).<br />
Basin 2 sludge PIN #'s:<br />
183H-86-0001S thru 183H-86-00265 48 drums/number<br />
183H-86-0027S thru 183H-86-0035S 72 drums/number<br />
183H-86-0036S 48 drums<br />
183H-86-0037S 46 drums<br />
36 mil Hypalon liner installed in Basin 2.<br />
Liquids from Basins 3 & 4 transfered to relined Basin 2.<br />
March 1987 Basins 3 & 4 sampled<br />
Wet sludge<br />
Crystalline<br />
BASINS 3 & 4 SAMPLES<br />
MAJOR INORGANIC CONSTITUENTS<br />
(Table I.A-9 183-H Basin Closure Plan)<br />
Basin 4 Sludge (9'e)<br />
Constituent A vera g e Rang e<br />
Copper 10.3 9.7 - 12.0<br />
Sodium 24.0 23.0 - 26.0<br />
Zirconium 4.4 0.34 - 13.0<br />
Flouride ion 1.1 0.98 - 1.2<br />
Nitrate ion 22.0 20.0 - 24.0<br />
Sulfate ion 1.9 1.3 - 3.9<br />
Moisture 46.0 43.0 - 51.0<br />
pH 9.7 - 9.9<br />
Basin 4 Crystalline (%)<br />
Constituent Average Rana e<br />
Sodium 38.0 30.0 - 50.0<br />
Sulfate ion 13.0 1.5 - 31.0<br />
Flouride ion 2.2 0.28 - 5.8<br />
Nitrate ion 46.6 7.1 - 71.0<br />
Moisture 6.6 1.1 - 25.0<br />
pH 9.2 - 9.9<br />
D-12<br />
asin_3 Sludoe (%<br />
Average Rang e<br />
11.2 8.8 - 14.0<br />
23.0 20.0 - 30.0<br />
8.7 2.2 - 22.0<br />
1.3 0.98 - 1.5<br />
26.0 17.0 - 29.0<br />
3.7 1.9 - 5.3<br />
42.0 35.0 - 51.0<br />
10.2 - 12.1<br />
Basin 3 Crvstallin e (%)<br />
Avera g e Rang e<br />
42.0 35.0 - 55.0<br />
20.0 16.0 - 26.0<br />
3.6 2.9 - 4.9<br />
WHC-SD-W100-TI-003 Rev. 0<br />
BASINS 3 & 4 SLUDGE SAMPLES<br />
TRACE I NORGANIC CONSTITUENTS DETECTED<br />
(Table I .A-10 1 83-H Basin Cl osure Plan)<br />
Concentration in Basin 4 Concentration in Ba sin 3<br />
sludge content (oom) sludae content (o om)<br />
Constituent Average Ran ae Averaae Ranae<br />
Aluminum 430 390 - 490 8900 1100 - 17000<br />
Barium 24a
WHC-SD-W100-TI-003 Rev. 0<br />
BASINS 3 & 4 CRYSTALLINE SAMPLES<br />
TRACE INORGANIC CONSTITUENTS DETECTED<br />
(Table I.A-11 183-H Basin Closure Plan)<br />
Concentration in Basin 4 Concentration in Basin 3<br />
crystalline content (oom) crystalline samole (oom)<br />
Constituent Av ra Ranoe Average Ranae<br />
Aluminum 440 200 - 610 810 780 -<br />
Barium 2.3 -- - 0.96 - 3-4 8b ?.5--<br />
Beryllium 0.4a
WHC-SD-W100-TI-003 Rev. 0<br />
BASINS 3 & 4 RADIONUCLIDE CONTENT<br />
URANIUM RESULTS<br />
(Table I.A-15 183-H Basin Closure Plan)<br />
Samole stratum Average content (oCi/a) * dry weight Rance (oCi/a)<br />
$asin 3 sludge 870 -- -- 320 - 1,500<br />
Basin 3 crystalline 25 8 - 62<br />
Basin 4 sludge 520 44 - 820<br />
Basin 4 crystalline 12 7 - 20<br />
NOTE: Technetium-99 believed to be present but was not analyzed for.<br />
WASTE DESIGNATION : Basins 3 & 4 sludge/crystalline; WT01 - Toxicity (EHW)<br />
U123, P029, P030, P098, P120<br />
March 1987 Basin 2 liquid sampled.<br />
Estimated volume of Basin 2 is 470,000 gallons. Estimate<br />
is by extrapolation backwards from later volume estimates<br />
and estimates of evaporation rates.<br />
BASIN 2 LIQUID SAMPLES<br />
MAJOR INORGANIC CONSTITUENTS<br />
(Table I.A-16 183-H Basin Closure Plan)<br />
Constituents - Average concentration (ma/1) Rang e (ma/1)<br />
Sodium 140,000 120,000 - 160,000<br />
Nitrate ion 380,000 310,000 - 430,000<br />
Moisture (57%) (57 - 58%)<br />
PH 10.5 - 10.7<br />
D-15
WHC-SD-W100-TI-003 Rev. 0<br />
BASIN 2 LIQUID SAMPLES<br />
TRACE INORGANIC CONSTITUENTS<br />
(Table I.A-17 183-H Basin Clos ure Plan)<br />
Constituents Average contents ( mg/1) Range (ma/1)<br />
Aluminum 36 30 - 44<br />
Boron 63a
^-<br />
WHC-SD-W100-TI-003 Rev. 0<br />
BASIN 2 LIQUID RADIONUCLIDE CONTENT<br />
Constituent Averaae oCi/1 Range oCi/l<br />
Uranium 82,400 74,000 - 94,000 ± 5,000<br />
Technetium - believed present but not analyzed for.<br />
WASTE DESIGNATIONS: Basin 2 liquid; WT01 - Toxicity (EHW)<br />
U123. P029, P030, P098, P120<br />
May - Sept 1987 Basin 3 sludge and crystalline material removed.<br />
Volume - 14,535 cubic feet (3230 barrels - 4.5/3 ratio).<br />
36 mil Hypalon liner installed in Basin 3.<br />
Jan 1988 Status - Basin I Empty except for rainwater<br />
Basin 2 Liquids - volume unknown<br />
Basin 3 Empty except for rainwater<br />
Basin 4 Sludge and crystalline material remain.<br />
May - Sept 1988 Basin 4 sludge and crystalline material removed.<br />
Volume - 6,259 cubic feet (1391 barrels - 4.5/3 ratio).<br />
Sept 1988 All original sludge/crystalline material removed and<br />
packaged.<br />
1988/1989 Basins 1& 4 sandblasted.<br />
- - -- -- Basin 1 approximately 1/8 to 1/4 inch of concrete was<br />
removed during sandblasting.<br />
Basin 4 original liner (Gray butyl material with white<br />
Hypalon sprayed cover remained after sandblasting).<br />
All sandblast materials were packaged. Sampling data of<br />
sandbiast grit unknown. Packaging requirements unknown.<br />
Volume of sandblast waste unknown.<br />
Evaporation of approximately 33,760 gallons of liquid with<br />
a resultant crystallized solid with a volume of<br />
approximately 21,900 cubic feet.<br />
Solidified -60,000gallons_of liquid frnm Basins 2 & 3.<br />
Liquid solidification - 40 gallons liquid mixed with<br />
-290:4 ibs-of Sorbond LPC-II absorbant.<br />
D-17
WHC-SD-W100-TI-003 Rev. 0<br />
Sorbond LPC-II Formula<br />
Componds Range (%)<br />
Silicon dioxide 14.4 - 15.6<br />
Aluminum oxide 3.1 - 3.5<br />
Ferous oxide 1.6 - 1.9<br />
Calcium oxide 63.2 - 73.2<br />
Manganese oxide 5.1 - 6.0<br />
Sulfate ion 1.4 - 1.8<br />
Potassium 0.4 - 0.7<br />
Sodium oxide 0.8 - 1.2<br />
Calcium carbonate 0.3 - 0.5<br />
Fnn+<br />
_Gulk--deflsity 'a -70 - 80 pnunde pnr<br />
- J VY.\YJ G. cubic VYVI\. .VVY•<br />
183-H Basin 2<br />
Absorbed Aoueous Waste<br />
Waste mixture: Waste per barrel - 40 gallons.<br />
Assumed bulk density of waste is 9.2 lbs. per gallon.<br />
Weight of 40 gallons waste - 368 lbs.<br />
Sorbond LPC-II used per barrel - 290.4 lbs.<br />
Total weight of absorbed waste per barrel - 658.4 lbs.<br />
Wt Y. of waste per barrel - 567.<br />
Wt y of Sorbond LPC-II per barrel - 44%.<br />
NOTE: 2 to 3 inches of absorbant was placed on top of<br />
cured waste to fill void space and absorb any<br />
condensate that formed.<br />
Note: Records show 1616 barrels ( @ 65,000 gallons of<br />
liquid) of material generated from 6/89 tO 12/89<br />
during solidification of liquid. However, records at<br />
the Central Waste Complex show that there are 2767<br />
barrels of solidified liquid. The extra 1151 barrels<br />
may be of material which solidified during<br />
evaporation stages of volume reduction that took<br />
place from 1987 to 1989. SWITS records indicate that<br />
all 2767 barrels are considered as solidified liquid.<br />
Estimates of material in Basins 2 & 3 in Sept. 1989<br />
were 111,142 gallons of liquid and crystalline<br />
evaporate. This .would correspond with the amount<br />
needed to fill about 2767 barrels with 40 gallons of<br />
material each.<br />
Basin 2 & 3 Liners removed and boxed up. Basins 2 & 3 were<br />
not sandblasted.<br />
D-18
WHC-SD-W100-TI-003 Rev. 0<br />
-------------- WestBngho::ea Internal<br />
<strong>Hanford</strong> Company Memo<br />
From: Chemical Process Engineering CPE-WOG-002<br />
Phone: 6-9616 L5-31<br />
Date: June 1, 1992<br />
Subject: RECOMMENDED WASTE FORMS FOR WRAP 2A MODULE WASTES<br />
To: J. L. Westcott<br />
H2-58<br />
cc: J. W. Biglin L5-31<br />
D. A. Burbank H1-60<br />
J. A. Hunter L5-31<br />
C. A. Petersen H1-60<br />
--J G. -Riddel-le ---H2-58<br />
WOG/File-LB<br />
The purpose of this letter is to recommend some waste forms to use to<br />
solidify WRAP 2A Module mixed wastes. The waste forms recommended here will<br />
undergo laboratory testing in the very near future to verify or negate their<br />
planned use. A comprehensive literature search has been performed during<br />
the last month to help assist with--the_effort.In addition; E. W. McDaniel<br />
of ORNL, a solidification con sultant, will review this recommendation before<br />
the laboratory work gets very far.<br />
The waste to be treated in WRAP 2A varies in chemical characteristics,<br />
physical characteristics, radionuclide contamination, and hazardous<br />
constituents. The bulk of the waste is expected to come from the 183-H<br />
8-asin-clean-up, the C-018 Liquid Effluent Treatment Facility (LETF), ash<br />
from thermal treatment of combustible low-level mixed waste ( LLMW), and<br />
possibly some from the L-045H LETF. This represents about 80% of the waste,<br />
the balance will be varied mixed waste residues including soil, spent resin,<br />
salts, chemicals, etc. from facilities throughout the <strong>Hanford</strong> <strong>Site</strong>. The<br />
major waste streams are given below with their approximate chemical content<br />
in dry form:<br />
1. Basin 1 -Inner-Sludge<br />
Sodium 29% Zirconium 4%<br />
Sulfate 29% Silica 1%<br />
Copper 17% Uranium trace<br />
Nitrate 11% Technetium49 trace<br />
Fluoride 9%<br />
2. Basin 1 -<br />
Sodium<br />
Sulfate<br />
Fluoride<br />
Copper<br />
Zirconium<br />
Outer Sludge<br />
29% Silicon 3%<br />
46% Nitrate 2%<br />
9% Uranium trace<br />
8% Technetium-99 trace<br />
3%<br />
0-19<br />
<strong>Hanford</strong> oper.tion..na enyhwrfirq emm.ccor for n» US o.oarmen, of en.ryr
J. L. Westcott<br />
Page 2<br />
June 1, 1992<br />
3. Basin 1- Sorbed Liquid<br />
WHC-SD-W100-TI-003 Rev. 0<br />
CPE-WOG-002<br />
The liquid, wet sludge, and crystalline material was removed and sorbed<br />
---------- anzo--px-0bably--a-di-ato„aceous earth absorbent. The liquid fraction was<br />
probably mostly sodium nitrate, possibly some sodium sulfate, with a<br />
-s ight ^raEe<br />
:^, .__^-_.:.._<br />
of i:raffTUnt an u"55y ue^nneum.<br />
4. Basin 2 - Sludge<br />
Copper ^coro now<br />
Nitrate 30%<br />
^:__-_:.._m<br />
circoniu<br />
Silicon<br />
^<br />
6%<br />
4%<br />
Sodium 21% Fluoride 2%<br />
Sulfate 9% Uranium trace<br />
S. Basin 3 - Sludge<br />
Sodium 31% Sulfate 5%<br />
Nitrate 35% Fluoride 2%<br />
Copper 15% Uranium trace<br />
Zirconium 12%<br />
6. Basin 3 - Salt<br />
Sodium 62%<br />
Sulfate 30%<br />
Fluoride 6%<br />
7. Basin 4 - Sludge<br />
Nitrate 2%<br />
Uranium slight trace<br />
Sodium 38% Fluoride 2%<br />
Nitrate 47% Uranium trace<br />
Sulfate 13%<br />
8. Basin 4 - Salt<br />
Sodium 38% Sulfate 3%<br />
Nitrate 35% Fluoride 2%<br />
Copper 16% Uranium slight trace<br />
Zirconium 6%<br />
9. Basin 2 - Sorbed Liquid<br />
The liquid and entrained solids was thought to be sorbed on to Sorbond<br />
LPC-II, a calcium type absorbent. The chemical content of the liquid<br />
is given below:<br />
Sodium 27% Uranium trace<br />
Nitrate 73% Technetium slight trace possible<br />
D-20<br />
'i
J. L. Westcott<br />
Page 3<br />
June 1, 1992<br />
10. Sand Blast Grit<br />
WHC-SD-W100-TI-003 Rev. 0<br />
CPE-WOG-002<br />
The grit is expected to be at least 90% grit, the balance being a<br />
mixture of basin salt, sludge, dirt and sand, and liner material. This<br />
is not expected to be designated hazardous from the contents, but if<br />
designated it would probably be by association.<br />
11. C-018 LETF Facility ( Stabilized Distillate Residue)<br />
Ammonium Sulfate (in dry form) > 95%<br />
Volatile Radionuclides - Trace levels<br />
12. C-018 LETF Facility<br />
Spent ion exchange resin<br />
13. C-045 LETF Facility (300 Area Process Sewer Treatment)<br />
Ferric Hydroxide Sludge ( on Occasion)<br />
14. C-045 LETF Facility<br />
Spent ion exchange resin (Duolite) - on Occasion<br />
15. LLMW Incineration or Destruction Facility<br />
Ash Residue<br />
RECDMMEnDATIUnS<br />
_The-foll3wing recommended methods will made and the appropriate waste forms<br />
tested in the laboratory:<br />
A. Cement is recommended and will be tested on the basin wastes numbered 1<br />
through 10. Slag cement appears from the literature search to provide<br />
the best waste product performance in regards to leachability and EPA<br />
toxicity testing. Therefore, it is the prime candidate; however,<br />
portland cement type I-II, or type III will be used as back-up if any<br />
of the basin mixes appear to yield a poor product with slag cement. In<br />
addition, a cement modifier suggested by E. W. McDaniel of ORNL will be<br />
obtained and tested for its ability to increase retention of salt<br />
materials such as nitrates.<br />
B. Gypsum cement is recommended for ammonium sulfate listed as waste<br />
no. 11. Slag and portland cements exhibit strongly basic slurries in<br />
the mixing stage, this would release ammonia gas. Gypsum cement<br />
however is neutral during mixing and stabilizes the ammonium sulfate in<br />
the ammonium ion form. Laboratory screening experiments will be used<br />
to determine whether plaster of paris or a modified gypsum cement is<br />
used. Gypsum cement can be handled in the same type equipment as slag<br />
cement if the set is retarded. Either a slow setting material or a<br />
retarder will be added to provide a reasonable set time.<br />
D-21
--;-.y<br />
J. L. Westcott<br />
Page 4<br />
June 1, 1992<br />
WHC-SD-W100-TI-003 Rev. 0<br />
C. Spent ion exchange resins (nos. 12 and 14) will be processed with<br />
cement after a pretreatment process wherein the resin beads or granules<br />
are destroyed. A chop blending method will be used for slurries or wet<br />
resin, and milling will be used for dry resin.<br />
D.<br />
CPE-WOG-002<br />
A lime or lime-flyash treatment will be used for ferric (iron)<br />
-Sy4 J .^ •= nxide _f1_ock f'+&sti: ri} === ^; \<br />
- = The ^_ C1 I. O d....^......w<br />
- , s^,^-^^^ cement setting<br />
properties and the flock is too basic for materials such as sulfur<br />
polymer cement. The use of trade mark Aquaset or Petroset from Fluid<br />
Tech, Inc. could be lab tested for this application.<br />
E' , The ash residue (no. 15) as well as the basin'grit (no. 10) would best<br />
be used as blending agents to stretch the cement and improve its<br />
strength and containment characteristics. It will be tested in this<br />
__manner._Ash_i.s_a good candidate for sulfur polymer cement, but this<br />
would require a different type of facility equipment. An effort will<br />
be made-to prouide-some- i-nformation-on the use of sulfur polymer cement<br />
for ash immobilization. There are other miscellaneous wastes that<br />
would probably be immobilized better in sulfur polymer cement than the<br />
other cements.<br />
Work on these waste immobilization methods will begin in the laboratory<br />
within the next week with the intent to show that they meet present and<br />
anticipated future waste disposal criteria.<br />
W. 0. Greenhalgh, Principal Scientist<br />
f'homiral Process Engineering<br />
dfm<br />
D-22
u...^^,<br />
WHC-SD-W100-TI-003 Rev. 0 Internal<br />
O WBsHngtrouse<br />
HaniDrd CDmpany Memo<br />
From: Restoration Projects 87330-92-MLS-023<br />
Phone: 372-1362, H2-58<br />
Date: August 7, 1992<br />
Subject: SOLID WASTE INFORMATION AND TRACKING SYSTEM LOW-LEVEL MIXED WASTE<br />
CHARACTERIZATION TO SUPPORT WASTE RECEIVING AND PROCESSING 2A<br />
To: J. L. Westcott H2-58<br />
cc: S. R. Briggs G6-47* J. G. Riddelle H2-5844<br />
D. A. Burbank H1-60 V. M. Weingardt H1-60:<br />
W. 0. Greenhulgh L5-31 RP Characterization File<br />
R. S. Kelley H2-58* MLS File/LB<br />
D. R. Lucas G6-46* *w/o attachment<br />
Per your request on June 9, 1992 a Solid Waste Information and Tracking System<br />
(SWITS) data run was pulled on all low-level mixed waste (LLMW) in storage<br />
except the 183H basin. This data summed up to some 2547 containers. The raw<br />
data was analyzed to determine that which was to be treated at WRAP 2A. To<br />
determine this the data with
WHC-SD-W100-TI-003 Rev. 0<br />
Attachment<br />
87330-92-MLS-023<br />
Pages 1 through 16<br />
D-24
•N`^C-Sf1-"d100-71-003 Rev. 0<br />
,S'FIPcE`f19oX!_S<br />
LO'^VlFR-A.,P2A,i 7/27/92<br />
CONTAINER INFORMATION<br />
SIZE: 55 GAL GENERATOR:313 BLDG. 300 AREA<br />
AMOUNT:83 FUEL FABRICATION OPERATION<br />
DOSE:tmr<br />
WASTE CODE:WT02 GROSS WEIGHT: 281-345 KG<br />
HAZARDOUS CONSTITUENTS<br />
CHROMIUM<br />
------ -------- COPPER<br />
SODIUM FLUORIDE<br />
SODIUM HYDROXIDE<br />
SODIUM NITRATE<br />
(--§;ZIRCONIUM<br />
TOTAL HAZARDOUS WEIGHT<br />
PHYSICAL DESCRIPT(ON<br />
ABSORBENT(POZZOLAN/ OIA.EARTH)<br />
PLASTICIPOLY(90 MIL LINER)<br />
SLUDGES(ABOVE)<br />
RADIONUCLIDE DISTRIBUTION<br />
TOTAL BETA/GAMMA: .05 CURIES<br />
ENRICHED URANIUM RANGE:159.2 p through 839.8 p<br />
AVERAGE:382.12<br />
P IN #<br />
364 365 368 369 376 388 398<br />
366 367 370 371 391 395 402<br />
387 372 374 404 392 397 412<br />
--389 373 375 405 399 401 413<br />
390.B 378 377 406 403 408 414<br />
393 379 380 407 423 409 415<br />
394 382 381.8 420 424 410 416<br />
396 383 384 - 421 425 411 417<br />
400 386 385 422 426 419 418<br />
RECOMMENDED TREATMENT:<br />
1.TAILORED GROUT<br />
2.POLYrL1ER<br />
3.GYPSUM CEMENT<br />
WEIGH (Kal<br />
0.23<br />
31.3<br />
49.89<br />
36.29<br />
31.75<br />
O,R2<br />
150.28<br />
X<br />
25<br />
5<br />
70<br />
ACID NEUTRALIZATION CENTERFUGE SLUDGE<br />
ABSORBED IN POZZOLAN OR DIATAMACEOUS<br />
EARTH PER SOAR/ 3-1 B-7HM-2<br />
17CGALV.DRUM, 90 MIL LINER<br />
ABSORBED WASTE DIRECT TO<br />
LINER<br />
EPA LABEL:<br />
'WT02 TOXIC FOR NsF•<br />
COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
D-25<br />
4eapa4 -
a^.<br />
:_f<br />
WHC-SD-W100-TI-003 Rev. 0<br />
LOT WRAP 2A.1 - -<br />
SHEET 5.XLS<br />
RECOMMENDED TREATMENT:<br />
1. TAILORED GROUT<br />
2. POLYMER<br />
3. GYPSUM CEMENT<br />
RATIONALE FOR TREATMENT RECOMMENDATION:<br />
Tailored grout is a convient waste form in that: ( I) thawaste-exists -a a sludge; (2)--sodium--saltsare<br />
absorbed on either_a-poxzntan or c:a, e:;r,h, i3) Total noiariiy of soittable salts are approx. 0. 1 M.<br />
Nitrate conccentration is 0.03 M. Chromium concrentation is approx. 100 ppm which just makes<br />
material a mixed waste.<br />
Polymer could also be used<br />
Gypsum cement is aso acceptable<br />
Major effort is t convert sludge to a solid form.<br />
D-26<br />
^
CONTAINER /NFORMATlO N:<br />
`d"-C-Sn-'w°'.00-TF-003 RBv. 0<br />
ikli^E'1':3.XI_S<br />
(^Q1,_WRAP2A.3 07/27/92<br />
SIZE AMOUNT GENERATOR: WASTE CODE:<br />
5 GAL I tO0N.100N AREA D002,WTO2<br />
55 GAL 16 2ETF,200E AREA, TANK FARMS<br />
163PA,10oN AREA. WATER FILTER PLANT<br />
DOSE: AMOUNT<br />
0-iMr 11<br />
20Mr I<br />
25Mr I<br />
3SMr 2<br />
36Mr I<br />
42Mr 1<br />
AHYS/CAL DESCR/PTlON:<br />
CONWED PADS: 10 53%, 6@ 26%, 1@ 27%. it 28%, it 29%, 4@ 12%. 2@ 14%<br />
LIQUID: 1@ 12%, 6@ 7%, it 6%, 1@ 4%, it 3%, 3@ 20%, it 19%, it 17%, 1@ 14%, 1@ 40%<br />
PLA/POLY: 1@ 35%, 9@ 1%, 6@ 3%<br />
ABSMITY LTRNERM: 1 @ 60%<br />
ACID: 9@ 1%. 3@ 26%. 1@ 24%, 1@ 22%. 1@ 18%<br />
DIRT/SOIL/DIA.EARTH: 50 61%. 10 80%, 3@ 82%.3@39%,_1@32%; 1@A4%,-1@ 51%<br />
GLASS: 9@ 4%<br />
HAZARDOUS CONST/TUEMSlKoI:<br />
/OF H2SO4 H20 KOH HN03 H3P04<br />
1 0.0094 0.8904<br />
1 56.25<br />
9 0.12<br />
3 28.558<br />
1 25.2015<br />
1 21.2779<br />
1 18.4793<br />
RAD/ONVCL/DE D/STR/8UT/ONew4tl:<br />
0 OF TOTAL B/G Co 60 F. 59 Mn 54<br />
1 0.002 0.00015 0.00002 0.00003<br />
1 0.001<br />
9 0.00002 0.00002<br />
2 0.018 0.009 0.009<br />
3 0.012 0.006 0.006<br />
1 0.01 0.005 0.005<br />
N /•<br />
IOSN-90-220 10514-90-205 10514-90-219<br />
IOSN-90-201 1OSN-90-206 105N-90-220<br />
105N-90-201 10514-90-207 10514-90-221<br />
10514-90-202 10514-90-208 10514-90-222<br />
105N-90-203 105N-90-209 10514-90-223<br />
10514-90-204 10514-90-218 2EFT-87-02285<br />
RECOMMENDED TREATMENT:<br />
1.TAILORED GROUT<br />
3.POLYMER<br />
COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
2.GYPSUM CEMENT<br />
D-27
LOT WRAP 2A.3<br />
SHEET 3.XLS<br />
kE(:OMNIENDED TKEAT NIENT<br />
WHC-SD-W100-TI-003 Rev. 0<br />
15 of the 17 drums are listed as containing significant amounts of H3P04. It is best to neutralize this<br />
acid with lime prior to solidification.<br />
1. TAILORED GROUT<br />
2. GYPSUM CEMENT<br />
3. POLYMER<br />
RATIONALE FOR TREATMENT RECOMMENDATION:<br />
When the H3P04 is neutralized with lime it is no longer hazardous and can be solidified with either grout<br />
gypsum cement or polymer.<br />
There should be no difficulty in passing TCLP.<br />
D-28
ONTANVER BVFORMA<br />
SI7 E: AMOUN=i<br />
8 GAL 2<br />
85 GAL 17<br />
55 GAL 31<br />
WASTE CODE:WT02<br />
GENERATORS: ,<br />
fl.4T WRAP2A.4<br />
329,300 AREA CHEMICAL SCIENCE LA8<br />
Sh,_ /.XLS<br />
325,300 AREA APPLIED r,HEMISTY LAB<br />
1234,300 AREA PNL<br />
202A,200E AREA PUREX<br />
2718,200E AREA BPLANT<br />
2345Z,200W AREA ZPLANT<br />
163PA,100N AREA<br />
NALAB, FERMI NATIONAL ACCELERATOR LABS<br />
GLASS: 1010%<br />
CONWED: 1022 %<br />
DIRT/SORJDIA.EARTH: 10 48%,1@ 57%, 1@33%, 10 16%,<br />
1@ 24%, 15@ 100%<br />
C7 LIOUID: 1@ 26%,1 @ 61 %<br />
N PLA/POLY:2541 1%, 1@ 8%, 1@ 47%, 20 12%. 1@ 20%, 1@ 5%<br />
^ CLOTHIRAGS/NYLON: 1@ 34%, 1@ 61 %<br />
RUBBER: 1@ 3%, 1414%<br />
METALARON/GALV./SHEET: 1@ 2%, 3419%<br />
CONCRETE: 3@ 60%<br />
STAINLESS STEEL:3@ 10%<br />
PAPER/CARDpOARD: 1@ 12%, 1@ 48%<br />
CLAY:22@ 1%<br />
RESINS: 24@ 2%<br />
ASHES: 1@ 12%<br />
RAD/ONUCLDE.•<br />
NAZAIROQ'J8 CONSTl7UENTS<br />
13@ 173.9u971K8, 3@ 172A013 M:B, 10<br />
155.9896 K8, 261 187.0152 K8, 140186.0173 1<br />
10 199.9878 KBi, 10 179.9845 Kq'i, 10175.9929<br />
K8, 10 172.999'y't K8, 2@ 182.978R K8, 10<br />
190.0089 K8, 1ti71P 178.9986 K8, 1(0 170.0055 Kp,<br />
1@180.9824120 184.0215 11@'193.0025<br />
Ka, 1@ S2 K8<br />
'NOT'E: FOR HAZ. TOTALS SEE ATT)ICHED<br />
105N-90-155 91031-01^0014<br />
211-089038 9103-01 -•0015<br />
0213-089002 910:1-01-0016<br />
1271B-91-0135 91031-01a0017<br />
°325-88-03 9103-01 -0018<br />
325W88001 9103-01 •0019<br />
325W88002 9103-01-0020<br />
329-90-022112Mr) 9103-01-0021<br />
9103-01-0012' 9103-01-0022<br />
9103-01-0013 9103-01-0023<br />
RECOMMENDED TREATMENT:<br />
1.POLYMER<br />
2.GYPSUM CEMENT<br />
LOT WRAP2A.4<br />
SHEt, /.XLS<br />
Ferrio Oxide: 15@ 5.62 K8<br />
Sodium Oxide: 15@48.26 K8<br />
HCI: 1@.1 K8<br />
HN03: 1 @ .9 1<br />
SODA ASH: 1@3 1<br />
Ni 1 @1.18 Kg<br />
FsOH: 1 @ .2 Kg<br />
i f<br />
0, i-' ^.. {.! ^',. .<br />
9103-01-0024 9103-01-0034 PNL88013<br />
9103-01-0025 9103-01-0035 PNL88014<br />
9103-01-0026 PNL88005 PNL88015<br />
9103-01-0027 PNL88006 PNL88016<br />
9103-01-0028 PNL88007 PNL88017<br />
9103-01-0029 PNL88008 PNL88018<br />
9103-01-0030 PNL88009 PNL88019<br />
9103-01-0031 PNL88010 RHZ-219-92--28<br />
9103-01-0032 PNL88011 WHC-A-91-822<br />
9103-01-0033 PNL88012 WHCA-91-000825<br />
COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
r .2<br />
Vf<br />
0 i<br />
E<br />
0 0<br />
^<br />
0<br />
w<br />
to<br />
<<br />
0
LOT WRAP 2A.4<br />
SHEET 7.XLS<br />
RECOMMENDED TREATMENT<br />
1. POLYMER<br />
2. GYPSUM CEMENT<br />
RATIONALE FOR TREATMENT CHOICE:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Polymer is treatment of choice because: ( l) 24 containers contain resins, resins are best stabilized by<br />
f_,mrt polymer in that resigns tend to swell in a cement-based matrix. (2) Oxalic acid crystals exist in at least<br />
one container, oxalate would cause a delay in set time of a cement matrix which could be excessive.<br />
--•--<br />
(3) A number of containers contain ammonium salts. The high Ph of cement could liberate ammonia gas.<br />
(4) NaCl in a system such as cement containing pore fluids would react with encapsulated metals possibly<br />
causing expansion and cracking.<br />
Gypsum cement could well serve as an alternate treatment for many of the above reasons. Also each<br />
represents a single component system which facilitates ease of handling.<br />
D-31
_--<br />
jY^EC'L4nLS<br />
_<br />
i nr lninnn1 n 07/27192<br />
CONTAINER INPoRMATION:<br />
5_5_ GA_L_ 53 WASTE CODE:<br />
F003,F005<br />
DOSE: AMOUNT
LOT WRAP 2A.5<br />
SHEET 8.XLS<br />
RECOMMENDED TREATMENT<br />
1. POLYMER 2. TAILORED GROUT<br />
WHC-SD-W100-TI-003 Rev. 0<br />
RATIONALE FOR TREATMENT RECOMMENDATION:<br />
A tailored grout could be used if the aluminum were removed from one drum. The high caustic content<br />
of cement would react with aluminum metal to produce hydrogen gas. One drum contains II % resin<br />
which is incompatibte with cement. Waste form would likely swell.<br />
D-33
CONTAINER 1NFORM4 T/ON:<br />
55 GAL 22<br />
DOSE: I Mr<br />
pNYS/CAL DESCR/PT/ON:<br />
CLOTHRIAGS/NYLON:<br />
DIRT/SORJDIA.EARTH:<br />
HAZARDOUS CONSTITUENT:<br />
PAPER/CARDBOARD:<br />
PLAS.RWLY:<br />
WOOD:<br />
ASBESTOS:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
SHEET9eXLS<br />
LOT WRAP2A.6<br />
GENERATORS:<br />
202A.200W AREA<br />
PUREX<br />
10 40%,1@25%,1@5%<br />
WASTE CODES:<br />
D001.D002,WTO2<br />
07/27/92<br />
20 1%,8@ 3%,5@ 5%,5@ 8%,1@ 28%,1@ 33%,1@ 88%,1@ 93%<br />
1502%<br />
10 15%,1@ 10%,1@30%<br />
180 10%,30 35%,1 @ 80%,1 @ 90%<br />
1@ 10%<br />
20 80%,5@ 83%,8@ 85%,2@ 87%<br />
NITRIC ACID: 80 .05K8.3@ .04Kp,30 .08Kp,2@ .O1Kp,2@ .02Kp,2@ .07Kp,1@ .08Kp,30 .09Kg<br />
URANYL NITRATE HEXAHYD.: 10 1.3898K9<br />
ASBESTOS: 15@11-23Ka - - _l.vC: 15.93<br />
HNt:<br />
WHC•A-89-820<br />
WHC-A-89•821<br />
WHC-A-89-822<br />
WHC•A-89-823<br />
WHC-A-89-824<br />
WHC•A-89•825<br />
WHC-A-89-826<br />
WHC-A•89-828<br />
WHC•A-89-829<br />
WHC•A-89-830<br />
YYFi{;-A-89431<br />
WHC-A-89-832<br />
WHC•A-89•833<br />
WHC-A-89-834<br />
WHC•A-89-835<br />
WHC-A-89-837<br />
WHC•A-89•838<br />
WHC-A-89-839<br />
WHC•A-89•840<br />
WHC-A-89-841<br />
WHC-A-89-842<br />
WHC-A-89-843<br />
RECOMMENDED TREATMENT: COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
1.TAILORED GROUT<br />
2.POLYMER<br />
3.GYPSUM CEMENT<br />
D-34<br />
-P+grt
.:•n-,,,<br />
LOT WRAP 2A.6<br />
SHEET 9.XLS<br />
RECOMMENDED TREATMENT<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Code required that acid be deactivated prior to solidification/stabilization.<br />
1. TAILORED GROUT<br />
2. POLYMER<br />
3. GYPSUM CEMENT<br />
RATIONALE FOR TREATMENT RECOMMENDATIONS<br />
Nitric acid which is most probably absorbed in the soil and/or dia. earth can be treated with either lime<br />
or caustic soda solution. the deactivated material then can be solidified in a cement-based matrix. Also<br />
Polymer or gypsum cement is suit:ihle.<br />
0-35
CONTA/NER /NFORMAT/ON:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
SHEETIO.XLS<br />
LOT WRAP2A.7 07/27/92<br />
55 GAL 15 WASTE CODES:D009,WT01<br />
20 GAI. I<br />
8-GAL------ 1 GENERATORS:<br />
2258,200E AREA BPLANT ENCASULATION<br />
DOSE: 0-1 Mr 2345Z,200W AREA ZPLANT<br />
202A,200E AREA PUREX<br />
2225,200W AREA LABORATORY<br />
340,300 AREA RETENTION & NUETRALIZATION<br />
325.300 AREA APPLIED CHEMISTRY LABS<br />
PNYS/CAL DESCR/PT/ON.•<br />
-------- -A$SORBENT:-- -- 1@25%,i@607r,,10 85%,10 30%<br />
CLOTH/RAGS/NYLON: 1@ 5%,1@ 10%,1@ 80%<br />
GLASS: 10 1%,4@ 7%,30 10%•3@ 90%<br />
METdifl.%f•ALV/STEEL: - 2@1 % +a '% "•r^'<br />
..r., +i'v%,iiy20%,1@2B%,4@84%,1@90%<br />
-" PLAS..?OLY: 9@ 3%,2@ 10%.1@ 12%,1@ 21%,1@ 40%<br />
'..^ p RUBBER: 6@ 6%,1@ 4%<br />
DIRT/SOIL/DIA.EARTH: 1@10 %,1@ 55%•1@ 80%,1@ 93%<br />
MFRCIIRY• .<br />
,^. FLOOR TILE: 1 @ 26%<br />
i n<br />
.r<br />
1 d ^..2i.,1ue3%,i@s%,i@i5%<br />
"
LOT WRAP 2A.7<br />
SHEET 10.XLS<br />
RECOMMENDED TREATMENT<br />
WHC-SD-W100-TI-003 Revo 0<br />
AMALGAMATION WITH SULFUR, ZINC OR NICKEL<br />
RATIONALE FOR TREATMENT RECOMMENDATIONS<br />
Waste code D009 requires that contained amount of mercury be amalgamated. It may be necessary to<br />
evaporate mercury from solid waste prior to amalgamation. Remainder of solid waste could be treated<br />
with a tailored grout.<br />
D-37
NTA/NfR lNPoRMAT/<br />
DOSE: 0-1-Mr- -<br />
8 GAL 3<br />
30 GAL 2<br />
5 GAL. 3<br />
55 GAL 48<br />
%NIr<br />
100K-92-003900<br />
IOSN-89-1064<br />
fOSN-89-1075<br />
tOSN-89-741<br />
105N-89-742<br />
105N-89-743<br />
105N-89-950<br />
--- 105N-90-12<br />
^.. 211-089008<br />
211-A18584<br />
211-A18888<br />
L11-A19523<br />
_,. 211-A19624<br />
211-A19726<br />
212-089006<br />
221T-91-00065<br />
2225-89-587<br />
2225-89-1119<br />
222S2W-90-861<br />
22242W-90-662<br />
-- - - - 22252W-90-685 ---<br />
222S2W-90-687<br />
222S2W-90-689<br />
222S2W-90-690<br />
222S2W-90-892<br />
222S2W-90-695<br />
222S2W-90-969<br />
22252W-90-697<br />
222S2W-90-713<br />
222S2W-90-714<br />
222S2W-90-715<br />
222S2W-90-718<br />
222S2W-90-719<br />
224U-91-011<br />
225B-90-20<br />
2713-89-v72<br />
271U-91-90601<br />
271U-91-90802<br />
325-91-007<br />
340-91-00031<br />
ETF-241-901020<br />
ETF-91-068-02<br />
ETF-91-123-03<br />
KEHN-91-52-001<br />
KEHN-91-52-002<br />
WHC-SD-W100-TI-003 Rev. 0<br />
SHEETI2.XLS<br />
LOT WRAP2A.8 07/29/92<br />
GEiveRATORS:<br />
340,300 AREA,RET.bNEUTRL.<br />
t00KE,100K AREA<br />
221T,200W AREA,EOUIP.DECON<br />
202A,200E AREA,PUREX<br />
2327,200W AREA,WST.INCINERAT.<br />
271U,200W AREA,U PLANT<br />
241AW,200E AREA, TANK FARM<br />
224U,200E,U PLANT<br />
241C,200E AREA,TANK FARM<br />
241BX,200E AREA,TANK FARM<br />
222S,200W AREA,LABS<br />
2218,200E AREA. 8 PLANT<br />
183PA,100N AREA<br />
2258,200E AREA, ENCAPSULATION<br />
t00N,1O0N AREA<br />
2345Z,200W AREA, Z PLANT<br />
325,300 AREA, APP.CHEM.<br />
KEHN-91-52-003<br />
KEHN-91-52-004<br />
WHC-A-90-800<br />
WHC-A-90-804<br />
WHC-A-91-801<br />
W14C-A-91-809<br />
WHC-A-91-821<br />
WHC-A89-805<br />
WHC-A89-807<br />
WHCA-91-000828<br />
WHCA-91-000827<br />
WASTE CODES:<br />
U151,D009<br />
D008,D009<br />
D005,0009,U151<br />
D009,D005,0006<br />
D009<br />
D006,D009,WC02<br />
DOOS,D007,D008,D009,<br />
D01 O,D011,WT02<br />
D002, D006, D009,WCO i,<br />
WT01<br />
D001,D006,D009,WT01<br />
D009,D002,WCO1,WT01<br />
D005,D006,D009,WC02<br />
WT01<br />
D006,D008,0009,Wi02<br />
D002,D009,WT02<br />
D002,D009<br />
D006,D009,WC02,WT01<br />
D009,WT01<br />
- DOOx0003.DCi09,--ro i<br />
0004,0005,0008,0007<br />
D009,D010.D011<br />
RECOMMENDED TREATMENT: COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
1.MERCURY TO BE AMALGAMATED AND ENCAPSULATED<br />
2.LEAD TO BE ENCAPSULATED<br />
3.TAILORED GROUT FOR REMAINDER OF SOUDS<br />
4.POLYMER IS ALSO ACCEPTABLE<br />
D-38
PHYSICAL DESCR/PTTON:<br />
V-r-S?-W100-TZ-003 Rev. 0<br />
LOT WRAP2A. 8<br />
SNEE71'i.XLS<br />
RNG. AVG. IOF RANGE AVG. IOF<br />
CONWED 5-97% AVG:14.7% 9 PAINTS NA 095% 1<br />
DIRT,ETC. 2-97% AVG:56.1% 10 ROCK NA @40% 1<br />
HAZ.CONST!T- - a^54% -A-Vfd:7.5%- 1^a --- -- -SI'L-ICA GEL NA 020% 1<br />
METAL.ETC. 1-70% AVG:12.8% 19 SLUDGE NA @30% 15<br />
. PL,.45T!C,ETC.- -1-50% -AiSGt10.'a% - 42 BATTERIE NA @24% 1<br />
GLASS 1-97% AVG:56.8% 24 UQUIO 4•25% AVG:13.6% 3<br />
Hp 1-70% AVG:12.5% 6 CEMENT NA @10% 1<br />
H20 NA 015% 1 CLOTH 1•15% AVG:7% 4<br />
- RUBBER 2-76% AVG:32.6% 3 MISC.,ETC. 2-58% AVG.23% 12<br />
OXIDES 1-3% AVG:2.0% 2 ABSORB,ETC. 10-76% AVG.30.8% 12<br />
PAPER,ETC. 1-40% AVG:17% 3 Al NA @1% 1<br />
"'V ' HA7ARDOUS C0NS7rTf/ENTS:<br />
f OF RANGE AVG. 8 OF RANGE AVG.<br />
'°--' AMMAL. HQ 1 NA 0.028K9 NaOH 1 NA @.085K9<br />
•- H9 55 0-24.1Kp AVG:1.46Kg ZnC12 4 0-.22Kp AVG:.16Kp<br />
t :..a Pb 17 0-.113K8 AVG:025Kp Zn 2 NA 0.28Kp<br />
^-^ Ba OXIDE 1 NA @2Kp ANTIMONY 2 NA @.02K0<br />
-- - °ca 30 0-38Ky AVG:2.4Ka MQ 1 NA 9.02Kp<br />
Cd 19 0-13.2Kp AVG:1.7Kp CaCHL.FLU. 10 0-5.1Kp AVG:2.7Kg<br />
Cr 16 0-.014Kp AVG:.0115Kp Mg02 I NA 0.95Kp<br />
Ss 16 0-.0003K9 AVG:.00022K8 HpTHIO.CYA. 1 NA 0.0004K9<br />
Ag 16 O-.OO3Kg AVG:.002Kp FsN03 1 NA @.0105K0<br />
NH4C!2 4 0-r35Kp---- -AVG..21R0 N03 I NA 9.1974Ka<br />
CdOH 1 NA 0.205K9 HNO3 1 NA 0.0315Kp<br />
CoOH i NA 0.02Kp BoTRIFLUO. 1 NA 9.0045Kp<br />
H90H 1 NA @.2Kp Mn 1 NA @.06Kp<br />
MON 3 O-.38Kg AVG:.184Kp ARSENIC 1 NA 0.0002K9<br />
KOH 3 0-.37Kp AVG:.23Kg<br />
EADIONUCLIDE D/sTR(armn;v;<br />
/ OF RANGE AVG. / OF RANGE AVG.<br />
Cv137/3a137 34 0-.0085C1 5.7E-03 C-14 7 NA 00.00<br />
TOTAL B/G 49 0-.1614C1 5.5E03 S^151 7 0-00480 1.14E-03<br />
Sv90,'Y90 - 14- 0=.-0073CI 8./E-04 U ENRICHED 2 0-12.42 Gr 6.235Gr<br />
Ca60 26 0-.0002C! 2.67E-05 Eu-155 1 NA @O.OC!<br />
NI-60 1 NA 0 Eu-154 I NA 81E-05<br />
Ru1O6lRh106 9 O-.0102Ci 1.77E-03 ----- --- -An!24l It 0-.00002C1 I.SE-05<br />
Ca134 I NA 3E-05 Fa-59 2 NA 02E-05<br />
Cs144/Pr144 8 0-.0423C1 8.25E-03 Mn-54 2 NA 03E-05<br />
PM-147 7 0-.01890 4.44E-03 PU 3 0..00132Gr 1.14E-03<br />
H-3 7 0-.000040 5.71 E-06<br />
D-39
^ '.'.<br />
JLL-31-1992 09:37 FROM EDS/ORF$ihA1ES TO 815093721253 P.03/03<br />
e f'l<br />
LOT WRAP^AS 7^t l t?^IHY [H 6<br />
SHhC1 1l.JC'LS<br />
RECOMMENDED TREATMENT<br />
wNC-SD-YI100-TI-003 Rev. 0<br />
1. MERCURY TO BE AMALGAMATED AND ENCAPSULATED.<br />
2 LEAD TO BE ENCAPSULATED<br />
3. TAILORED GROUT FOR REMAINDER OF SOLIDS<br />
4. POLYMER IS ALSO ACCEPTABLE<br />
RATIONALE FOR TREATMENT RECOMMENDATIONS<br />
Regulations reevire-thatmerculy and]eadhetncapsulated._Ihe-drums-containingthrce materials<br />
should be isolated and sorted to segregate as much of the mercury and lead bearing waste as possible.<br />
-The-tnerc;:ry ",2avaeuurtmkhelmaily-distiiled-andamalgarated peior to encapsulation. Assumption<br />
is that batteries in waste are lead storage batteries. These must also be sorted for encapsulation.<br />
After sorting and pretreatment to remove mercury, the residue can be stabilized In a tailored grout.<br />
Polymer encapsulation is also acccptable.<br />
AN AREA OF CONCERN IS DRUM CONTAINING MERCURY THIO CYANIDE.<br />
D-40<br />
)<br />
.^%
,.:<br />
Westinoause<br />
Harlford COMM<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Fmm: Restoration Projects 87330-92-MLS-026<br />
Phone: 372-1362, H2-58<br />
Date: August 17, 1992<br />
Subiect:_ -SOL I-DWAST-E INFOR.MATIONA.ND ?PACKING-SX-STEM LOW-LEVEL MIXED WASTE<br />
CHARACTERIZATION TO SUPPORT WASTE RECEIVING AND PROCESSING 2A<br />
To: J. L. Westcott H2-58<br />
YI Q Gi1C-/1 D<br />
...,,. 19L^ f 1 1 ^ L<br />
cc: S. R. Briggs G6-47*<br />
D. A. Burbank, Jr. H1-60<br />
W. 0. Greenhulgh L5-31<br />
H2-58<br />
D. R. Lucas G6-46*<br />
J. G. Riddelle H2-58<br />
K. M. Weingardt H1-60<br />
RP Characterization File H2-58<br />
*w/o attach O<br />
ment<br />
Per your on June 9, 1992 a Solid Waste Information and Tracking System<br />
data run was-puUe-d on-atl 1Qw-leveimi-xed-was-te i-n-s_toraae except the<br />
183H basir. Five of the last seven lots have been reviewed by Earl<br />
McDaniel and are attached. Once again a summary sheet along with<br />
rationale for treatment recommendations have been assembled. The lots<br />
are WRAP2A.9 through WRAP2A.12. The last two lots will be evaluation and<br />
summarized in the coming week.<br />
If you have any questions or require additional information, please feel<br />
free to contact me on 372-1362.<br />
4ML gff ^<br />
. . Sheri<br />
Engineering Technician<br />
pss<br />
Attachment<br />
D-41<br />
*<br />
Internal<br />
Memo
COIV/ABVER /VfORMAT/ON:<br />
il i M^OUNTi<br />
55 GAL 280<br />
2 GAL 1<br />
85 GAL 28<br />
10 GAL 1<br />
8 GAL 1<br />
4•4•8 1<br />
4•4•7 18<br />
UNKNOWN 1 IVOL.3.21 M3)<br />
SEE ATTACHED FOR PIN i<br />
G 1A<br />
N<br />
SHEETII.MLS<br />
1.OT WRAP2A ,?<br />
CODES: WT01,D008<br />
POSE Rz :AMQU!+I:<br />
0-10 301<br />
11-20 1<br />
21-30 3<br />
31-40 1<br />
41-50 0<br />
51-100 6<br />
RECOMMENDED TREATMENT: COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
1. ENCAPSULATION FOR LEAD.<br />
2. INCENERATION FOR SOLVENTS AND GREASE<br />
3.TAILORED GROUT OR POLYMER FOR SHREDDED SOUDS<br />
Page<br />
J Y ?<br />
GENERATORS:<br />
202A,200E AREA.PUREX<br />
SPAP,OFFSITE,SHIPPINGPORT<br />
07/23I82<br />
221B,200E AREA.PROCESS TREATMENT<br />
AMES,OFFSITE,IOWA ST.UNIV.LAB<br />
2345Z,200W AREA,ZPLANT<br />
2225, 200W AREA, ANAL.LAB<br />
324,300 AREA.WASTE TECH.ENG.LAB<br />
2ETF,200W AREA, TANK FARMS<br />
313.300 AREA,FUELS MANUF.<br />
2258,200E AREA,ENCAPSULATION<br />
209E,200E AREA,CRIT.MASS LAB<br />
325,300 AREA.APPUED CHEM. LAB<br />
242B,200E AREA.CASK BLDG.BPLANT<br />
2WB,200W AREA. BURIAL GROUNDS<br />
221TS,200 W AREA,EOUIP.DECON<br />
3720,300 AREA, CHEM. METALS LAB<br />
305,300 AREA,HOT CELL VERIF.FAC.<br />
NALAB,OFFSITE,FERMI NAT.ACCEL.LAB<br />
100N,100NAREA<br />
333,300 AREA,N FUELS MAN.<br />
2710.200E AREA,ELEC.MAINTENANCE<br />
224U,200W AREA,U03<br />
E<br />
S<br />
V1<br />
4<br />
E<br />
^<br />
O<br />
O 1<br />
--1<br />
O<br />
W<br />
m <<br />
O<br />
A W H<br />
1° ^ n<br />
r ^o<br />
M 3<br />
rr<br />
WfA<br />
N<br />
ON
O I<br />
tA<br />
SHEETII.XLS<br />
;,<br />
LOT WRAP2A.2<br />
WMA FEnRAPPOk<br />
LEAD 275 CONT. 1-100% AVG.84% RADIONUCLIDES.,<br />
PAPER/ETC. 28 COINT. 1•309A AVG.B% A^241 1 CONT. 118Gr NA<br />
PLASTIC/ETC. 143 PONT. 1-83% AVG.7% C-14 1 CONT. NA AVG.1.71Ci<br />
RUBBER 16 C471NT. 1-17% AVG.4% G144/Pr14 35 CONT. 0-,148C1 AVG..027CI<br />
METALIETC. 64 CqNT. 1-100% AVG.39.5% Co-58 1 CONT. NA AVG.148G<br />
BTANNLESS/ETC. 13 CQNT. 2-1576 AVG.6% Co-60 17 CONT. .01•250000 AVG147OC1<br />
ABSORBENT/ETC. 39 CqNT. 1-63% AVG.16% Cr•51 1 CONT. NA AVG..34G<br />
DIRT/ETC. 17 CNNT. 6•90% AVG.30% Cs137/B03 72 CONT. O•.51C1 AVG..017CI<br />
CLOTHIETC. 42CQNT. 1-909i1 AVG.7% Fa55 1 CONT. NA AVG.18400Cf<br />
ASBESTOS<br />
WOOD<br />
I COIrIT.<br />
27 CONT.<br />
NA<br />
1-74%.<br />
AVG.1%<br />
AVG.36%<br />
Fs-59<br />
H-3<br />
1 CONT.<br />
6 CONT.<br />
NA<br />
0Y72.4 Cl<br />
AVG..39CI<br />
AVG.12.06C1<br />
GLASS 16 CONT. 1-98% AVG.22% Mo-54 3 CONT. 3•339q AVG.113G<br />
CONVVED PADS 34 CONT. 1-72%. AVG.11% Mo-93 1 CONT. NA .02CI<br />
FILTEIRS I COWT. 67X. NA Nb-94 I CONT. NA AVG..01CI<br />
SAND/ETC. 2 CONT. 18+35% NA Ni-59 1 CONT. NA AVG.127 Cl<br />
CU MiETAL 5 COINT. 1•20'1i 7% Ni-63 1 CONT. NA AVG.18800G<br />
GREASE 1 COINT. 5% NA Pm•147 35 CONT. O•.06901 AVG..014CI<br />
SOLVITHSY 1 COIVT. 5% NA Pu-239 1 CONT. .0002Gr NA<br />
LIQUID 5 CONT. ALL 1116, NA Ru106/Rh10 26 CONT. 0-.035C3 AVG..008Ci<br />
OR6 1 i<br />
8 CONT. 48-60% AVG.55% Sm-151 13 CONT. 0•A16G AVG...005G<br />
BATTIERIES 3 COI,ff. 40-66% AVG.52% Sr90/Y90 23 CONT. 0-.03Ci AVG..007C1<br />
AIR 2 CONT. 40+49% NA Th-232 2 CONT. ALL 5Gr NA<br />
TOTAL B/G 309 CONT. 0•62900G AVG.203G<br />
! ARDOUS CONSTITUfNfS: U DEPLETED 8 CONT. O•.255 Gr AVG...036Gr<br />
LEAD 274 C:ONT. .0003-17640.12K9 AVG.456K8 U ENRICHED 11 CONT. 0-1.23Gr AVG.231Gr<br />
LEAD SHEILDING 6 C011T 29.0^978•91000K8 AVG.47158.8169K8 U NATURAL 2 CONT. ALL 1OGr NA<br />
LEAD BRICK 32 CONT. 33.65-384.96K8 AVG.248.969K8 Zr95INb85 I CONT. NA AVG..01CI<br />
LEAD GLASS 3 CONT. 9.32-218.718K9 AVG.112.71K8<br />
ASBESTOS 2 CONT. 4.O8-122.47K9 AVG.63.27K8<br />
LEAD NO 1 CONT. 59.1 ^1 K8 NA<br />
LEAD SALTS 1 CONT. .04 M:e NA<br />
BUTOXYETHANOL I CONT. . 15Kip NA<br />
LEAD GLOVES 1 CONT. 4.451C8 NA<br />
Pap6 2<br />
A !F<br />
m<br />
VI<br />
Oo<br />
S<br />
O O<br />
--1<br />
O<br />
0<br />
w<br />
s 3<br />
w^<br />
N I ^<br />
^<br />
M ^<br />
r<br />
w I O
_OX--41--1oa2 ag: e7 FROM FnS/ruPNL/MMF-4 TO 815093721253<br />
ATTACHMENT<br />
P. 02/k!7<br />
WHC-SD-WI00-TI-003 Rev.<br />
87330-92-MLS-026<br />
Page 3 of 13<br />
0<br />
LUl' W1LU' 2A,12<br />
SF^F.F.T 11.aZS<br />
it1iCY)MMENDED TREATMLNT<br />
1. 13NCAPSUtAT1ON FOR LEAD.<br />
2 INCINSRA'IION tult 5ULVENTS AND ORIiASF.<br />
3. TAILOItED ORO[1T OR POLYMER FOR SHREDDED SOLIm<br />
RA7TONAI.E POR TRBA1 Mk:lv'P RECOh4sQNDA9T0N<br />
llrumt eoptainiaj lead he ar.Itarated. Aftet septuttion iead must be weapsulated per<br />
regulntions. It is assumed that battcries are lead stnra;e Ind ir.dta also. They must be scponted and<br />
encrpsutated. eonminert with solvents and ;reaao ato bcst Incinerated. Hi:wever if this matedai<br />
proves to be absorbed on an inuripuile sorbet It is aeceptabla to sotidlty/ttabilira with either a utL eir,t<br />
grout of polymer. Gypsutn ecment would he ,.rr.ptable.<br />
D-44<br />
r4<br />
,..,^
CONTAINER /NFORMAT/ON:<br />
DOSE: SIZE:<br />
1@ 20 Mr 8 GAL<br />
BAL.@ 1-6 Mr 30 GAL<br />
P/N1:<br />
t00K-91-0092<br />
105N-89-1117<br />
10SN-89-441<br />
1OSN-B9-442<br />
105N-89-873<br />
202L-92-000703<br />
21 4 -^.89W5<br />
211-090026.e<br />
21 1-A21187<br />
212-A18652<br />
212-A19972<br />
212-A200005<br />
212-A21228<br />
212-A21790<br />
212-A21853<br />
219-091247<br />
220-A19943<br />
2718-91-0026<br />
2718-91-0156<br />
PNL-89047<br />
PNL-89048<br />
RHZ-219-091321<br />
WHC-A-89-845<br />
WHC-A-89-846<br />
WHC-A-89-847<br />
WHC-A-90-805<br />
-- ---- WHC-A"a0-829<br />
WHC-A90-844<br />
WHC3-89-50<br />
WHC3-89-51<br />
WHC3-89-52<br />
WHC3-89-53<br />
WHC3-89-54<br />
55 GAL<br />
PHYSICAL DESCR/PT/ON:<br />
S9-IEEI'13.XLS<br />
LOT WRAP2A.9<br />
r,evo 0<br />
ATTACHMENT<br />
87330-92-MLS-026<br />
Page 4 of 13<br />
07/31 /92<br />
GENERATORS: CODES:<br />
3 NALAB,FERMI NATIONAL ECC. LA8 0002<br />
5 271 B,200E AREA.B PLANT D002, WT01<br />
30 202A,200E AREA. PUREX D001,WTO2<br />
2345Z,200W AREA, Z PLANT DOO1,WT01<br />
RTL,3000 AREA.PNL FACILITY D002,WCO2<br />
333,300 AREA.N FUELS MAN. D001<br />
10oN,100N AREA<br />
202AL.200E AREA,PUREX ANAL.LAB<br />
1706K,100K AREA<br />
f OF AVG. RANGE<br />
OT C!C<br />
- Inl, G^Y. 20 44.455% 7-`^.li%<br />
GLASS 5 4% 1-9%<br />
HAZ.CONS. 23 11.78% 1-75%<br />
ASBESTOS 11 9.818% 3-15%<br />
CLOTH,ETC 18 20.2% 1-75%<br />
PLAS. ETC. 22 23.63% 1-95%<br />
KOTEX,ETC 1 @10 % NA<br />
RUBBER 9 '21.2% 1-80%<br />
FILTERS 2 14.5% 5-24%<br />
ABSORB. 5 33% 15-69%<br />
SLUDGES 9 @90% NA<br />
LIQUID 4 7.25% 1-14%<br />
ACID 2 13% 9-17%<br />
METAL,fFC- 8 36.,`, A .. v0 %<br />
WOOD 1 @15% NA<br />
H20 2 62.5% 60-85%<br />
PAPER,ETC 2 8% 1-15%<br />
CONWED 2 6% 5-7%<br />
HAZ4RDOUS CONSTITUENTS:<br />
URANYL IOF AVG.<br />
NITRATE 4 .244Kq<br />
ASBESTOS 1 0.25K8<br />
NaOH 7 3.83K0<br />
HN03 5 1.54Kp<br />
KN03 1 @.47K8<br />
A1N03 1 @,4999<br />
NeC12 2 @10.99K0<br />
NaN03 11 11.845Kg<br />
WHC3-89-55 NaF 9 3.306K0<br />
WHC3-89-56 HCI 2<br />
--- --------.----<br />
.819Kn<br />
WHC3-89-57 ACID 1 @1.0002Kp<br />
WHC3-89-58 H3PO4 3 .713Kg<br />
KOH . 4 3.6Kp<br />
RECOMMENDED TREATMENT: H3PO4HCI 1 019KQ<br />
COMPLETE RATIONALE FOR __- K2S207 1 ® a5K0<br />
TREATMENT ATTACHED. H2S04 1 @.2K8<br />
la,;y 1. POLYMER Na3PO4 1 @34.1Kp<br />
FaN03 1 @.1K8<br />
D-45<br />
RANGE<br />
.05-.89Kp<br />
NA<br />
.1-11Kp<br />
.46-4Kp<br />
NA<br />
NA<br />
NA<br />
.67•25.BKp<br />
1.09-7.26Kg<br />
-.499-1.13K.-<br />
NA<br />
.47-1 Kg<br />
1-10K8<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA
RADIONUCLIDE AVG.<br />
lOF 6.47E-03<br />
TOTAL B/G 37 1905.8Gr<br />
U DEPL. 14 1.35E•03CI<br />
Sr/Y 90 8 1.55E•03CI<br />
Cs/Bra 137 8 2.48E-03<br />
Ru/Rh 108 6 1.03E-02CI<br />
CO(^I 144 V 7.YVLN3W<br />
Pm 147 8 2.5E-05C1<br />
H 3 2 1.23E-03CI<br />
Sm 151<br />
6 2.27E-02Gr<br />
Pu ^<br />
4 1.11E-03Ci<br />
Co 60 4 2.25E•04C7<br />
Fe 59 2 3.65E-04Cf<br />
Mn 54 2 .7 Gr<br />
U ENRICH. 3<br />
WHC-SD-W100-TI-003 Rev. 0<br />
ATTACHMENT<br />
87330-92-MLS-026<br />
SHEET13.XLS<br />
Page 5 of 13<br />
LOT WRAP2A.9<br />
RANGE<br />
0-.1504Ci<br />
0-10200Gr<br />
0-8.8E•03CI<br />
0•7.9E•03Cf<br />
0-9.5E-03CI<br />
0-3.9E•02C1<br />
0-1.9E-02C(<br />
0-4E-05Cf<br />
W4.SCG3C1<br />
0-5.1 E-02Gr<br />
0-3.3E-03Cf<br />
0-4.5E-04Ci<br />
0-8.7E-04Ci<br />
0-.9 Cr<br />
D-46<br />
Y^<br />
Z..'
PU33-11-1992 09:48 FROM EDS/qRI$ir•P1ES TO 81S093721253 P.03i0°f<br />
LOT W1L1Y 2A.9<br />
SIIL•ET 13.XZS<br />
RFC'OMMENllbll TILEAT.IIENT<br />
1. POLl'1`iL•R<br />
RATIONALE FOR 'l'1LLATb1ENT R[COMMENDATlON<br />
ATTACHMENT<br />
87330-92-MLS-026<br />
WHC-SD-WI00-TI-003 Rev. 0 Page 6 of 13<br />
'!bo drum eontaintnp auJ must first be Irotated and ooid ncutralisd. 'ILes srllx and shredded solids<br />
are then enoapsuloted in polymer. This avlitUflcrtlnn r¢romroendatioa is consistent with plant dcwiYn.<br />
D-47
CONTA/NER /NFORMATION<br />
WHC-SD-W100-TI-003 Rev. 0 ATTACHMENT<br />
87330-92-MLS-026<br />
SHEETI4.XLS Page 7 of 13<br />
LOT WRAP2A.10 08ro3/92<br />
SIZE: DOSE: GENERATORS:<br />
30 GAL. 1 0-10 Mr 17 221TS,200E AREA. EOUIP.DECON<br />
55 GAL 22 11-50 Mr 6 244AR,200E AREA,VAULT<br />
2225,200W AREA.ANALYTICAL LAB<br />
CODES: WT02,WC02,WP02,FO01,F002 ORGANICS
LOT WRAP 2A 10<br />
Slf-EET 14.)C,S<br />
RECOMMENDED TREATMENT<br />
1. ENCAPSULATION FOR LEAD<br />
2. INCINERATION<br />
WHC-SO-W100-TI-003 Rev<br />
RATIONALE FOR TREATMENT RECOMMENDAT[ONS<br />
ATTACBMF t iT09372 ]. 253<br />
87330-92.--M[.S-026<br />
Page 8 c:,r'. 13<br />
0<br />
M Regulations require that lead be encapsulated. Drums must first be sorted. Solvents are suited<br />
"X9<br />
for<br />
incineration. Any solidif'ication technology that produces heat will tend to volltize solvents.<br />
, + These<br />
m.. .., ..o;,,^ue b encapsnrated in po(vrrter or ¢Vnsum r^ ntne .^t but would tend to volatilize<br />
^ - -- -- - _. ...<br />
^<br />
v.,.._.,<br />
IT IS NOTED THAT T""r„cTED C.ODES F-001'-003 ADDRESS SPENT SOLVENTS<br />
D-49<br />
R. Q4iQl?
SIZE: DOSE:<br />
30 GAL. 2 1@5 Mr<br />
8 GAL. I BALANCE.1 Mr<br />
5 GAL. 1<br />
85 GAL. i<br />
55 GAL. 12<br />
CODES:<br />
D002,D005,WT01<br />
D002,D00e,WT02<br />
0001,0002,001 1 , WC02, WT02<br />
D002,D011<br />
0002,0007,D010,WT01<br />
D002,0010,WT02<br />
D002,D007,WT01<br />
0001,D007<br />
D002,D007,WT02<br />
0002.DOOB,WT01,WC01<br />
DOO1,0007,0011, WCO2, WTO2<br />
HAZARDOUS CONSTITUENTS:<br />
IF OF AVERAGE<br />
ASBESTOS 1 .54 K8<br />
BaOH 1 .45 Kg<br />
KF 1 1.35 K8<br />
KOH 1 7.41 Kg<br />
SRJCA 1 .04 Kg<br />
NaOH 1 5.22 Kg<br />
Cd 2 .07 Kp<br />
Co 1 .002 KB<br />
Ni 1 A5 KB<br />
K 1 .004 K8<br />
AIN03 1 .2 Kg<br />
H202 2 . 12875K8<br />
M8(CI04)2 1 .1 Kg<br />
KMn04 1 .8 Kg<br />
ABN03 2 .058 Kg<br />
HCI 2 .904 Kg<br />
HF 2 12.27 Kg<br />
HN03 2 12.43 Kg<br />
NaC03 1 .027 Kg<br />
Cr 9 .0068 Kg<br />
H3P04 8 14.29 Kg<br />
H2SO4 2 .049 Kg<br />
Na 1 2.56 Kg<br />
ZnCRO4 1 1.59 Kg<br />
NI/Cd BATT. 1 7.73 Kg<br />
Cr2(S04)3 1 .52 Kg<br />
CuSO4 1 .1 Kg<br />
- ----- RECOMMENDED TREATMENT:<br />
1.POLYMER<br />
2. ENCAPSULATION FOR LEAD<br />
WHC-SD-W100-TI-003 Rev. (bTTAC04EN2<br />
87330-92-MLS-026<br />
SHEET15.XLS Page 9 of 13<br />
LOT WRAP2A.11 8/8/92<br />
GENERATORS:<br />
202AL, 200E AREA, ANALYTICAL LAB<br />
202A, 200E AREA,PUREX<br />
221T, 200W AREA.EQIP.DECON<br />
329, 300 AREA,CHEM.SCIENCE LAB<br />
163PA, IOON AREA<br />
333,300 AREA. N FUELS MANUFACT<br />
241AY, 200E AREA. TANK FARM<br />
105KE,100K AREA<br />
lOON, 100N AREA<br />
1234. 3000 AREA. STORAGE<br />
PHYSICAC DESCR/PTION:<br />
/ OF AVERAGE RANGE<br />
ABSORB. 3 48% 20-74%<br />
CONWED 3 38% 7-90%<br />
GLASS 4 8% 1-18%<br />
HAZ.CONS. 10 16% 1-37%<br />
PLAST.ETC 18 15% 1-99%<br />
BATTERIES 1 9% NA<br />
DIRT,ETC 12 54% 1-93%<br />
RANGE LIQUID 3 6% 2-14%<br />
NA ACID 3 41% 4-95%<br />
NA CLOTH,ETC 1 10% NA<br />
NA METAL,ETC 2 11% 1-20%<br />
NA WOOD,ETC 1 20% NA<br />
NA<br />
NA<br />
EQUIPT. 3 57% 5459%<br />
.03-.1 1 Kg RADIONUCLID E O/STR/BUT/ON.•<br />
NA I OF AVERAGE RANGE<br />
NA TOTAL B/G 17 2.83E-02Ci 0-.43 Cl<br />
NA U DEP. 3 3.SE-02 Gr .001-.1 Gr<br />
NA Sr/Y 90 3 4.3-04 Ci 0-.0005Ci<br />
.1-.157 Kg Ru/Rh 106 2 1.4E-03 Ci .0008-.002C1<br />
NA Ca/Ba 137 6 2.7E-04 Ci 0-8E-09 Ci<br />
NA Ce/Pr 144 2 3.SE-03 Ci SEE ATT<br />
.01-.1 K8 Pm 147 2 1.75E-03 Ci SEE ATT<br />
.82-.88 Kg H 3 2 2.OSE-04 Cl 0-4E-04 Ci<br />
0-24K0 1 129 1 .0001 CI NA<br />
0-24 KB To 99 1 .0001 Cl NA<br />
NA Pd 107 1 .0001 CI NA<br />
SEE ATT Ce 135 1 .0001 Ci NA<br />
.05-50 Kg Sm 151 2 .00025 Cl SEE ATT<br />
.008-.09Kp Zr 90 1 .0001 Ci NA<br />
NA Co 60 9 2.0E-04 Ci 0-4.0E-04 Ci<br />
NA Ni 83 1 2.3E-04 Ci NA<br />
NA F. 55 1 .433 Cl NA<br />
NA Pu 1 .00004 Gr NA<br />
NA<br />
COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
D-50<br />
;.. \
qN i:<br />
105N-89-1097<br />
105N-89-1098<br />
105N-89-1099<br />
10 5 N-69-1 1 v,v<br />
105N-89-1101<br />
tOSN-89-1102<br />
106N-89-1108<br />
lOSN-90-337<br />
202L-92-000702<br />
221-T-91-00066<br />
329-90-46<br />
329-91-010<br />
ETF241-900722<br />
PNL-88031<br />
WHC-3-89-64.B<br />
WHC-A-91-828<br />
4m^=<br />
w°•^ WHC-A89-802<br />
MIHC-SD-M100-T1-003 Rev. 0 ATTACHMENT<br />
87330--92-MLS-026<br />
SHEETI5.XLS Paqe 10 of 13<br />
D-51<br />
-pswe
LOT WRAP 2A.11<br />
SHEET 15.XLS<br />
RECOMMENDED TREATMENT<br />
1. POLYMER<br />
2. ENCAPSUTA7TON FOR LEAD<br />
RATIONALE FOR TREATMENT RECOMMENDATION<br />
_ N:. P.B5/<br />
ATTACHMEIIT<br />
8733O-42-MLS-026<br />
Page 11 of 13<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Drums containing acid must be sorted, acid removed and neutralized. Drum containing hydrogen<br />
peroxide must be isolated and the peroxide which is a strong oxidizer should be treated as an acid<br />
and neutralized. Batteries are assumed to be lead storage batterlcs(D008 code is for lead). Plant<br />
design basis requires salt rich waste be encapsulated in polymer.<br />
D-52
SIZE: DOSE:<br />
5 GAL 1 1@15 Mr<br />
30 GAL 1 4@3 Mr<br />
10 GAL 2 BAL.@1Mr<br />
85 GAL I<br />
56 GAL 10<br />
PHYSICAL DESCR/PT/ON:<br />
TOTAL AVERAGE<br />
ABSOR.ETC 5 29 %<br />
CONWED 1 30 %<br />
GLASS 3 4.3%<br />
HAZ.CONS. 7 13.8 %<br />
PLAST.ETC 9 11.1 %<br />
METAL,ETC 2 25 %<br />
DIRT,ETC 8 84.5 %<br />
PAPER,ETC 1 15%<br />
RUBBER 3 21.6 %<br />
ACID 3 75 %<br />
NITRATE 3 25 %<br />
LIQUID 1 9 %<br />
HAZf1RO0US CONST?UENTS:<br />
TOTAL AVERAGE<br />
ARSENAZO 1 .21 K8<br />
BARIUM 2 .34 Kg<br />
CHROMIUM 5 . 1348 Kg<br />
SILVER 3 1.49 Kg<br />
Nrr2Cr207 1 .9 Kg<br />
BrrC03 1 .1 Kg<br />
_ CADMwM 1 .0014 Kg<br />
SELENIUM 1 1.0002 Kg<br />
COPPER 1 .1 K8<br />
NIOH 1 .3 Kg<br />
NrrCL2 1 . 6001 Kg<br />
ZINC 1 .25 Kg<br />
Cd OXIDE 1 .44 Kg<br />
Cr OXIDE 1 1.49 Kg<br />
Ag OXIDE 1 .39 Kg<br />
No OXIDE 1 .51 Kg<br />
CdN03 2 . 9001 Kg<br />
pN1:<br />
202L-92-000705<br />
325-91-008<br />
221-T-91-00072<br />
221-T-91-00073<br />
221-T-91-00074<br />
WHC-A81-814<br />
3314-90-001<br />
WHC-A-91-802<br />
WHC-A-91-803<br />
WHC-A-91-804<br />
211-089038<br />
211-089065.A<br />
PNL88003<br />
WHC-A88-800<br />
WHC-SD-W100-TI-003 Rev. 0<br />
SHEET18.XLS<br />
LOT WRAP2A.12<br />
GENERATORS:<br />
202AL.200E AREA,ANALYTICAL LAB<br />
325,300 AREA,APPLIED.CHEM.LAB<br />
221T,200W AREA,EQUP.DECON<br />
202A,200E AREA,PUREX<br />
2EBG,200E AREA,BURIEL GROUNDS<br />
2345Z,200W AREA,Z PLANT<br />
1234,3000 AREA.STORAGE<br />
RANGE<br />
5-45%<br />
NA<br />
2-8 %<br />
1-80 %<br />
1-50 %<br />
10-40%<br />
50-100 %<br />
NA<br />
10-30%<br />
@75 %<br />
@25 %<br />
NA<br />
RANGE<br />
NA<br />
.2-.49 Kg<br />
.008-.4 Kg<br />
.1-4.1 Kg<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
NA<br />
.55-1.25 Kg<br />
A2TACHMENT<br />
87330-92-MLS-026<br />
Page 12 of 13<br />
8/10/92<br />
CODES:<br />
D007, WT01<br />
D006,WT02<br />
D008,0007,D011,WC02<br />
WT02<br />
0004,D005,DO10,WC01<br />
WT01<br />
D007<br />
D018, WC02<br />
D008<br />
DO11<br />
D007,WCO1,WT02<br />
D005,WT02<br />
D005.0007,D011, WC01<br />
0004<br />
TOTAL AVERAGE RANGE<br />
TOTAL B/G 15 8.48E-03Ci 0-.03 Ci<br />
U DEPL. 1 S.SE-04 Gr NA<br />
5rlY 90 4 2.6E-03 Cl . 0005-.008<br />
Co 60 1 3.BE-03 Cl NA<br />
Ru/Rh 108 3 1.0E-03 Cl .0008-.0015<br />
GR'r 144 3 4.2E-03 Cl .003-.0015<br />
Pm 147 3 .002 Cl .0003-.0015<br />
H 3 1 1.0E-05 Cl NA<br />
Sm 151 3 S.OE-04 Ci .0004.0007<br />
Th 232 3 5235 Gr @5235 Gr<br />
U 233 3 .007 Gr @.007 Gr<br />
Eu 155 3 6.0E-OS Cl @B.OE-05<br />
Pb 212 3 3.0E-04 Ci @3.0E-04<br />
Ac 228 3 4.OE-04 Cl @4.OE-04<br />
Rrr 224 3 3.OE-04 Cl @3.0E-04<br />
11 208 3 1.0E-04 Cl 01.0E-04<br />
81 212 3 5.0E-04 CI @S.OE-04<br />
Se 75 1 1.41 E-03 Cl NA<br />
B. 133 1 3.76E-03 Cl NA<br />
WHC-A89-804<br />
RECOMMENDED TREATMENT:<br />
COMPLETE RATIONALE FOR TREATMENT ATT.<br />
1. TAILORED GROUT<br />
2. POLYMER<br />
3. GYPSUM CEMENT<br />
D-53
LOT 2A.12<br />
SHEET 16.XLS<br />
RECOMMENDEIlTREATMENT<br />
1. TAILORED GROUT<br />
2 POLYMER<br />
3. GYPSUM CEIVLfiNT<br />
WHC-SD-W100-TI-003 Rev. 0<br />
.. C.. - C..G.<br />
ATTACHMENT<br />
87330-92-MLS-026<br />
Page 13 of 13<br />
=-- RATIONALE FOR TREATMENT RECOMMENDATTONS<br />
e..i
WHC-SD-W100-TI-003 Rev. 0<br />
Westtnghouse<br />
Internal<br />
<strong>Hanford</strong> Company Memo<br />
From: Restoration Projects 87330-92-MLS-025<br />
Phone: 372-1362, H2-58<br />
Date: August 17, 1992<br />
Subject: SOLID WASTE INFORMATION AND TRACKING SYSTEM LOW-LEVEL MIXED WASTE<br />
CHARACTERIZATION TO SUPPORT WASTE RECEIVING AND PROCESSING 2A<br />
To: J. L. Westcott 142-58<br />
cc: S. R. Briggs G6-47*<br />
D. A. Burbank, Jr. H1-60<br />
W. 0. Greenhulgh LS-31<br />
R S Kelley H2-58*<br />
D. R. Lucas G6-46*<br />
J. G. Riddelle 142-58<br />
K. M. Weingardt H1-60<br />
RP Characterization File H2-58<br />
MLS File/LB<br />
*w/o attachment<br />
Per your on June 9, 1992 a Solid Waste Information and Tracking System<br />
data run was pulled on all low-level mixed waste in storage except the<br />
183H basin. The last two treatment lots have been reviewed by Earl<br />
McDaniel and are attached. Once again a summary sheet along with<br />
rationale for treatment recommendations have been assembled. The lots<br />
are WRAP2A.13 and WRAP2A.14.<br />
if you have any ciiestiofls or require additional information, please feel<br />
free to contact me on 372-1362.<br />
M. L. Sheriff<br />
Engineering Technician<br />
pss<br />
eaa...L-....4<br />
MllQU1111C114<br />
D-55<br />
Hanbre Ope.sNent and EngMeeHnq CeMrsetor for the US Devsmnent of EneRy
WHC-SD-W100-TI-003 Rev. 0 ATTACHMEtaT<br />
87330-92-MLS-025<br />
Page 1 of 4<br />
SHEET18.XLS<br />
LDT_]NRAP2A.14 8111192<br />
CONTAINER INFORMATlON:<br />
- --- - - 7NR€E55 GAL. nnew r.cycanrnac-<br />
ONE 10 GAL. ALL AT I Mr 221T,200E AREA,EQUIP.DECON<br />
202A.200E AREA,PUREX<br />
CODES: 2345Z,200W AREA,Z PLANT<br />
D002,D003,D009,WT01<br />
D002,D003,D008,WT01<br />
D001,D003,WT01 HAZARDOUS CONST/TUENTS:<br />
D002,0003 TOTAL AVERAGE RANGE<br />
Cs OXIDE 1 .5 Kg NA<br />
PHYSICAL DESCRlPTION: ALN03 1 2.27 Kg NA<br />
TOTAL AVERAGE RANGE BoFL3 2 .05 Kg . 004-.1 Kg<br />
DIRT.ETC 2 70% 48-94% Pb 1 3.4 Kg NA<br />
HAZ.CON. 1 1% NA MERCURY 1 .4999 Kg NA<br />
PLAS.ETC 4 5.75% 5-7%<br />
CLOTH 1 95% NA<br />
BORON 1 1% NA RADIONUCLIDE DlSTR/BU T10N:<br />
LEAD 1 49% NA TOTAL AVERAGE RANGE<br />
^"- METAL,ETC 2 43% NA TOTAL B/G 4 3.25E-03 Ci SEE ATT<br />
CONWED 1 5% NA Sr/Y 90 1 S.OE-04 Ci NA<br />
Ru/Rh 106 1 B.OE-04 Ci NA<br />
Cs/Bs 137 1 6.0E-04 Ci NA<br />
P/N Iy Cs/Pr 144 1 3.1 E-03 Ci NA<br />
221-T-91-00069 Pm 147 1 1.SE-03 Cl NA<br />
WHC-A89-806 Sm 151 1 4.OE-04 Cl NA<br />
211-089-024<br />
212-089006<br />
fi'cCOMM'cNDE'u TREATMENT: COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
1. ENCAPSULATION FOR LEAD AND MERCU RY<br />
2. TAILORED GROUT<br />
3.POLYMER<br />
D-56<br />
^<br />
„
LOT WRAP A2.14<br />
SHEET 18.XLS<br />
RECOMMENDED TREATMENT<br />
WHC-SD-W100-TI-003 Reve 0<br />
1. ENCAPSULATION FOR LEAD AND MERCURY<br />
Z. TAILORED GROUT<br />
3. POLYMER<br />
RATIONALE FOR TREATMENT RECOMMENDATIONS<br />
ATTACFIMENT<br />
87330-92-MLS-025<br />
Page 2 of 4<br />
Material containing lead and mercury must be sorted. ThC lead is then encapsulated. Mercury is<br />
distilled from material. Mercury is then encapsulated. Other material may be solidified In either it<br />
tailored ¢rc,nt or polymer.<br />
D-57<br />
TnT^,^ C n-
A:: ii(:<br />
WHC-SD-W100-TI-003 87330-92-Mrs-025<br />
Rev. 0 Page .3 of 4<br />
SHEETI7.XLS<br />
LOT WRAP2A.13 anlroz<br />
CONTAINER INFORMATION:<br />
SIX 55 GAL. GENERATORS: CODES:<br />
ALL AT 1 Mr 202AL.200E AREA,ANALYTICAL LAB D007,DOO8,WCOI,WP01<br />
23452,200W AREA,Z PLANT<br />
WTO1<br />
218W2A,200W AREA.BURIEL GROUNDS DO02,D008<br />
D007,000B,WC01<br />
DOOI,DOO6,WCOI,WTO2<br />
PNYSIC.4L DESCR/PTIONt<br />
TOTAL AVERAGE RANGE MAZARDOUS CONST/TUENTS:<br />
ABSOR._ETC 3 73% 80-80% TOTAL AVERAGE RANGE<br />
GLASS 1 7% NA CERIUM NO3 1 .11 KO NA<br />
HAZ.CON. 1 25% NA Pb02 1 . 45 Kg NA<br />
PLAS,ETC 6 13% 5-34% KBr2 1.45 Kg NA<br />
METAL,ETC 3 7% 5-9% KC12 1 .45 Kp NA<br />
DIRT.ETC 3 55% 44-70% KN02 1.45 Kg NA<br />
PAINTS * 3 11% 2-19% K PERIODAT 1 .22 Kg NA<br />
WOOD,ETC 1 9% NA KMN04 1 .9 Kp NA<br />
ACID 2 15% 10-20% ThN03 1.45 Kp NA<br />
CLOTH.ETC 1 7% NA PbCr2 3 .71 Kg . 0641.9 Kg<br />
RUBBER 1 1% NA Pb 2 50 Kp 18-84 Kg<br />
H2SO4 2 . 15 Kp .1-.2 KQ<br />
RADIONUCLIDE DISTRIBUTION:<br />
TOTAL AVERAGE RANGE<br />
TOTAL B/G 6 2.SE-04 Ci SEE ATT<br />
UUaPL. ---- 1 1.0ec-03 ur NA<br />
Sr/Y 90 2 1.0E-05 Ci NA<br />
P%<br />
202L-92-000704<br />
RHZ-219-091442<br />
RHZ-219-091443<br />
S172-91-001<br />
S 172-91-002<br />
219=A21581<br />
RECOMMENDED TREATMENT: COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
1. ENCAPSULATION FOR LEAD<br />
2. TAILORED GROUT<br />
3. POLYMER<br />
D-58<br />
--aawx
---- -<br />
LOT WRAP ZA.13<br />
SHEET 17.XLS<br />
RECOMMENDED TREATMENT<br />
1. ENCAPSULATION FOR LEAD<br />
2. TAILORED GROUT<br />
3. POLYMER<br />
WHC-Sq-W100-TI-003<br />
Rev. 0<br />
^ - -- - R,4117ON^,.-*-,E FOR-°REAcTNfE1V"r RECOMMENDATiONS<br />
'C g1„509372].253<br />
RZ3'AC#1MFi^^<br />
87330-92--twl.s-0z5<br />
P.02[0.3<br />
Page 4 of, 4<br />
Requlations require that lead be encapsulated. Drums containing lead must be sorted and lead<br />
A,,a removed. Drum containing sulfuric acfd must be segregated and acid neutralized prior to<br />
solidificatioNstabilization.<br />
Cr'<br />
..°'<br />
'^.<br />
D-59
W Westinghouse WHC-SD-W100-TI-003 Rev . 0 Internal<br />
- <strong>Hanford</strong> Company Memo<br />
From: Restoration Pro,jects 87330-92-MLS-028<br />
Phone: 372-1362, 1-12-58<br />
Date: August 24, 1992<br />
Subject: SOLID WASTE INFORMATION AND TRACKING SYSTEM LOW-LEVEL MIXED WASTE<br />
-€HARACTfR1ZATI0N T{!-SUPP'JP.T V.'ASTE-RECEIVING AND PROCESSING 2A<br />
To: J. L. Westcott H2-58<br />
cc: S. R. Briggs G6-47*<br />
D. A. Burbank, Jr. H1-60<br />
w. o. Greenhuigh L5-31<br />
R. S. Kelley H2-58*<br />
U. R. Lucas G6-46*<br />
J. G. Riddelle H2-58<br />
K. M. Weingardt H1-60<br />
RP Characterization File H2-58<br />
MLS File/LB<br />
*w/o attachment<br />
Per your request on June 9, 1992 a Solid Waste Information and Tracking<br />
System data run was pulled on all low-level mixed waste in storage except<br />
the 183H basin. This lot represents those containers that have only<br />
Washington State codes. Once again a summary sheet along with rationale<br />
for treatment recommendations have been assembled. The lot is WRAP2A.15.<br />
If you have any questions or require additional information, please feel<br />
free to contact me on 372-1362.<br />
M. L. Sheritt<br />
Engineering Technician<br />
pss<br />
Attachment<br />
D-60<br />
y^, HanbrA Opeyllm and EnlineerIng Conlracla for IM US Depsnrnenl of Energy<br />
a.
n .-.^..-n..^^- .. ... .dJ. ^<br />
ShIEE1°1 9.XILS<br />
LOT WRAP2A.15<br />
CONTAINER /NfORMA T/ON.•<br />
SIZE: DOSE: GENERATORS:<br />
5 GAL 2 1@4 Mr 328,300 AREA<br />
8 GAL. 1 1@3 Mr 163PA.IOON AREA<br />
7.609.3615 1 BAL.@1 Mr 331.300 AREA<br />
55 GAL _._._-302AL,200v AREA.ANALLAB<br />
241S,200W AREA<br />
333.300 AREA<br />
100N,100MAREA<br />
202A,200E AREA,PUREX<br />
TRWSG,OFFSITE,TRW INC.<br />
PHYSICAL DESCR/PTR)N: HAZAROOUS CONS T?VENTS:<br />
8/20/92<br />
WASTE CODES:<br />
WT01<br />
WT01,WC01<br />
WC02<br />
/ OF AVERAGE RANGE / OF AVERAGE RANGE<br />
HAZ.CONS. 11 8.8% 1-20% BERYLLIUM 2 3.5 KU .005-7 KU<br />
CLOTH 2 17.5% 10-25% NiOH 2 .088 Kg .002-.135 K8<br />
GLASS 8 5% 3-10% NaF 1 .9 Kp NA<br />
METAL 5 10% 1-30% NAOH 1 . 285 Kg NA<br />
-_W PAPER 3 17% 10-23% NrrNO2 1 .265 KU NA<br />
PLASTIC 10 13.7% 1-55% HF 1 52.3 Kg NA<br />
DIRT 7 73% 85-93% KCI 1 1.5 Kg NA<br />
CONWE}---- 5 33.8%- -- - 1-93-W- - - - 1iN03 3 2.11 KU 1.9-2.3 kp<br />
ABSORB. 5 55.8% 1-100% H31`04 2 24.5 Kg 20.29 Kg<br />
FIBERGLS. 1 20% NA ETHY.GLYCOL 1 36.29 Kp NA<br />
LIQUID 3 3% NA COPPER 1 8.35 Kg NA<br />
BRICK 1 99% NA<br />
RAD/ONUCL/DE D/STR/BUT/ON: PIN1<br />
! OF AVERAGE RANGE 328-90-031 WHA-88-303<br />
TOTAL B/G 15 9.8E-4 Cl 0-1.47E-3C1 105N-90-231 6803-1-1-34<br />
H-3 1 2.3E-4 Cl NA PNL-89019<br />
Mn-54 3 1.3E-4Ci 0-2.2E-4CI 328-88-00125<br />
Fs-55 1 3.OE-SCI NA 2021-92-000708<br />
Co-60 3 6.4E-4C1 0-1.1E-3C1 WTF-91-148-05<br />
C-14 I 1.OE-4Ci NA WHC-3-90-83<br />
U-OEPL. 2 t 2see Gr •n.Z Rea4G• 10eu-90-232<br />
U-ENR 1 .1 at NA 105N-90-157<br />
Sr/Y-90 4 3.SE-5Ci '0-4.OE-SCi 105N-90-158<br />
Fr59 2 1.3E-4CI 0-1.SE-4Ci IOSN-90-159<br />
U-NATR. 1 94300 Gr NA 105N-89-874<br />
105N-89-875<br />
RECOMMENDED TREATMENT: COMPLETE RATIONALE FOR TREATMENT ATTACHED.<br />
1. POLYMER<br />
2. TAILORED GROUT<br />
D-61<br />
pspsll
LOT WRAP 2A.15<br />
SHEET 19.XLS<br />
TREATMENT RECOMMENDATIONS<br />
1. POLYMER<br />
2. TAILORED GROUT<br />
WHC-SD-W100-TI-003 Rev. 0<br />
RATIONALE FOR TREATMENT RECOMENDATIONS<br />
Acids must be removed from containers and neutralized prior to treatment. Ethylene glycol should be<br />
removed and stored for incineration. Since material contains salt, polymer use is design basis.<br />
nW-uc 6,<br />
IJ5
--^<br />
WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX E<br />
LITERATURE SEARCH RESULTS<br />
A. This WHC Letter Report (CEP-W06-001) contains a thorough literature<br />
search and review of solidification technologies. This review was done<br />
in support of the WRAP 2A WFQ efforts. It included a review of all known<br />
solidification technologies.<br />
B. This report (generated by solidification expert Earl McDanial, ORNL) is a<br />
review specifically of grouting technology (cement based solidification)<br />
used throughout the world. This report was done to support the selection<br />
of a grout technology in WRAP 2A.<br />
E-1
WHC-SD-W100-TI-003 Rev. 0<br />
This page intentionally left blank.<br />
E-2
WHC-SD-W100-TI-003 Rev. 0<br />
Westinghouse<br />
<strong>Hanford</strong> Company LITERATURE SEARCH RESULTS<br />
From: Chemical Process Engineering<br />
Phone: 6-9616 L5-31<br />
Date: May 27, 1992<br />
Subject: WRAP 2A LITERATURE SEARCH<br />
To: J. L. Westcott H2-58<br />
cc: J. W. Biglin L5-31<br />
D. A. Burbank H1-60<br />
J. A. Hunter L5-31<br />
J, G. Riddelle H2-58<br />
C. A. Petersen H1-60<br />
WOG/F ile-LB<br />
Internal<br />
Memo<br />
CPE-WOG-001<br />
A detailed literature search of waste solidification methods has been<br />
completed and several packets of information generated by the search are<br />
provided. The typically used materials such as portland cement and<br />
variations of it are still the primary referenced solidification material.<br />
However, a couple of new or newer materials are available. These include<br />
sulfur polymer cement, a thermosetting inorganic binder, Aquaset® and<br />
Petroset® inorganic binders used for aqueous and organic liquids<br />
respectively, and Syncrete® a synthetic concrete. These materials will be<br />
considered, evaluated, or tested along with the more familiar materials;<br />
information and test samples of all three have been requested.<br />
To minimize cost and make processing as simple as possible, thermal<br />
processing was limited to s500°F for WRAP 2A. This eliminates<br />
vitrification, synthetic rocks, metal matrices, calcines and ceramic waste<br />
forms from consideration. Also, absorbent materials were not considered<br />
viable candidates since they could be used as solidification matrices for<br />
low-level waste, but not mixed waste since they are not expected to retain<br />
hazardous components and would not normally pass the TCLP test. Some<br />
searches were done for all solidification methods including vitrification so<br />
as not to exclude any references that are potentially useful. A summary of<br />
waste solidification agents is given in Table 1. Table 2 lists the<br />
-sol-itiifirati-on methods ±hat--are--expected to-be--consi-dered-for application at<br />
the WRAP 2A Module.<br />
The use of portland cement and similar materials continues to be the most<br />
referenced of solidification materials. Slag cement references, however,<br />
seem to z^ inmr^ro ' nca J`--`- rna ::^t it might retain radionuclide and hazardous elements<br />
more completelyethan cement. Pozzolan and latex cement might offer<br />
additional advantages over portland cement for certain chemicals or<br />
matrfieere iii^ewise ^rwirosioRee and Rlaster-of paris are gypsum cements<br />
that set well with neutral and acidic wastes. Other cementitious materials<br />
to consider include grout mixes, polymer modified cement, and SyncreteA. In<br />
contrast, organic binders offer solidification agents that are expected to<br />
form waste products exhibiting lower leach characteristics and higher waste<br />
loadings than cement products. Thus, they will be considered, but they will<br />
E-3<br />
NrNOnI oNr°Hnns and EnpYwekV CpNnetor for the US Wo^nt at Emryy
[•.^^<br />
h_:...<br />
J. L. Westcott<br />
Page 2<br />
May 27, 1992<br />
WHC-SD-W100-TI-003 Rev. 0<br />
- - - - - * CPE-WOG-001<br />
also be examined for unacceotable flammability or combustibility<br />
characteristics. The other class of solidifiers is inorganic binders which<br />
offer some of the characteristics of both cementitious agents and organic<br />
binders.<br />
The most useful literature packet is one entitled "Literature Search for<br />
WRAP Solidifiers." It summarizes most of the important references. The<br />
literature pointed out a number of additives or modifiers that improve waste<br />
product performance particularly for cement. Materials such as lime,<br />
silica, or alumina can improve cement leachability. For gypsum cements,<br />
retardant modifiers are probably necessary for proper solidification of<br />
phscerxfoarisand Envirostane*was*.e products' A1so, materials or<br />
reagents to avoid are important in considering the use of organic binders or<br />
polymers. A number of these guidelines are included in the literature<br />
references and summaries.<br />
This completes the initial phase of the WRAP literature search. We will<br />
attempi to keep the iiterature search current with time and periodically<br />
update to support the design work. If you have any questions or comments,<br />
please call me on 6-9616.<br />
W. 0. Greenhalgh, Principal Scientist<br />
Chemical Process Engineering<br />
dfm<br />
Attachments<br />
'Envirostone0 is available in a slow set formulation. We have<br />
submitted a procurement request to obtain some for laboratory testing and<br />
evaluation.<br />
E-4<br />
.
Table 1<br />
Candidate Waste Forms<br />
Absorbents Cementitious Materials Or anic Binders<br />
•Vermiculite •Portland Cement Type I •Bitumen<br />
Kitty-L#tter - -•Partland Cement •Coid Working Polymers<br />
•Zeolites Type III -Dow Polymer®<br />
•Diatomaceous Earth •Pozzolan Cement -Water Extended<br />
•Calcium Sulfate •Envirostone® Polyester (WEP)<br />
Dissicants .Plaster of Paris -Epoxies, etc.<br />
•Silica Gel •Grout ( <strong>Hanford</strong>- •Heat Setting Polymers<br />
•Agricuiturai Products Nitrate Mix) -Polyethylene<br />
(cellulose, corn cobs, •Slag Cement -Polypropylene<br />
-etc.) •Polymer Modified -Polyurethane<br />
Cement -Polymethyl<br />
•Latex Cement Methacrylate, etc.<br />
•Syncrete® •Polymer Impregnated<br />
•FUETAP Concrete Concrete ( PIC) or<br />
•Concreted Pellets other waste form<br />
•Grout Mixes<br />
-Salt Resistant<br />
-Sulfate Resistant<br />
-Weather Resistant<br />
-High Density<br />
-E p oxy Grout<br />
Calcines Ceramics Inor g anic Binders<br />
•Salt Cake •Pellets •Sulfur Polymer Cement<br />
•Metal Oxides •Alkali-Clay Fixation •High Temp Sulfur<br />
•Granules/Pellets ( Cancrinite) -Water Glass ( Sodium<br />
•Formed Clay Silicate)<br />
•Fired Inorganic Resins •Acid Anhydride Melts<br />
•Aquaset®<br />
•Petroset®<br />
Metal Matrices Synthetic Rocks Vitrification<br />
•Alloy Melts •Titanates (Synroc) •Borosilicate Glass<br />
•Hardware Fusion -Hydrothermal Process •Phosphate Glass<br />
•Alumino Silicate Glass<br />
•Soda Glass<br />
•Other - Flint/<br />
Borate/etc.<br />
•Fused Soils<br />
®Envirostone is a trademark of U.S. Gypsum Company.<br />
--®Dow- Polymet•-is--a trademark of Davr Chemica i Company.<br />
•Aquaset is a trademark of Fluid Tech, Inc.<br />
•Petroset is a trademark of Fluid Tech, Inc.<br />
®Syncrete is a trademark of STMI of France.<br />
E-5
WHC-SD-W100-TI-003 Rev. 0<br />
Table 2<br />
Viable Candidate Waste Forms<br />
for WRAP 2A<br />
Cementitious Materials Organic Binders Inorganic Binders<br />
•Portland Cement Type<br />
•Portland Cement<br />
Type III<br />
-+Poaaol-an Cement<br />
•Envirostone®<br />
•Plaster of Paris<br />
•Slag Cement<br />
;Polymer Modified<br />
Cement<br />
•Latex Cement<br />
•Syncretem<br />
•Concreted Pellets<br />
•Grout Mixes<br />
-Salt Resistant<br />
-Sulfate Resistant<br />
-Weather Resistant<br />
I •Bitumen<br />
•Cold Working Polymers<br />
-Dow Polymer®<br />
=Water Extended<br />
Polyester (WEP)<br />
-Epoxies, etc.<br />
•Heat Setting Polymers<br />
-Polyethylene<br />
-Polypropylene<br />
-Polyurethane<br />
-Polymethyl<br />
Methacrylate, etc.<br />
•Polymer Impregnated<br />
Concrete<br />
•Sulfur Polymer Cement<br />
•High Temp Sulfur<br />
•Water Glass (Sodium<br />
Silicate)<br />
•Acid Anhydride Melts<br />
•Aquasetm<br />
•Petrosetm<br />
-Hiah Densitv<br />
_<br />
-Epoxy Grout '<br />
®Envirostone is a trademark of U.S. Gypsum Company.<br />
®Dow Polymer is a trademark of Dow Chemical Company.<br />
®Aquaset is a trademark of Fluid Tech, Inc.<br />
®Petroset is a trademark of Fluid Tech, Inc.<br />
®Syncrete is a trademark of STMI of France.<br />
E-6
--- -Aauaspt and Pe-liroset<br />
WHC-SD-W100-TI-003 Rev. 0<br />
LITERATURE SEARCH FOR WRAP SOLIDIFIERS<br />
1. "Aquaset and Petroset," Technical Data Sheet, Fluid Tech, Inc.,<br />
Las Vegas, NV.<br />
B itume n<br />
Aquaset is designed for aqueous waste and Petroset is designed for<br />
organic liquids. Up to 40 to 48 gallons of liquid can be solidified in<br />
a 55 gallon drum. -<br />
1. S. Simpson, H.-lidal, and M. Morris, "Mixed and Chelated Waste Test<br />
Programs with Bitumen Solidification," Spectrum '88,<br />
September 11-15, 1988, Pasco, WA, pp 323-325.<br />
;-, Bitumen solidification tests with mixed and chelated wastes were carried<br />
=- • out. Test results are still being evaluated for 10 CFR-61 type<br />
v.,* analyses.<br />
= 2. M. Snellman and M. Valkiainen, "Long Term Behavior of Bituminized<br />
Waste," Waste<br />
,... cni_Sn7<br />
rN .<br />
Management '86, Vol. 3, March 2-6, 1986, Tucson, AZ,<br />
^Y<br />
Water uptake by bitumen solidified ion exchange resin was studied.<br />
Water uptake corresponded to the resin content, but no unacceptable<br />
bitumen product long term effects were observed.<br />
3. A. J. Mattus, R. D. Doyle, and D. P. Swindlehurst, "Asphalt<br />
Solidification of Mixed Wastes," Waste Management '88, Vol. 1,<br />
February 28 - March 3, 1988, Tucson, AZ, pp 229-234.<br />
Solidification of some mixed waste with bitumen can be used to "delist"<br />
the waste so it can be disposed of as a radioactive waste.<br />
4. A. Bernard, A. C. Nomine, G. Cornec, A. Bonnet, and L. Farges, "Long<br />
Term Leaching Tests on Full-Scale Blocks of Radioactive Wastes," Nuclear<br />
and Chemical Waste Management , Vol. 3, pp 161-168, 1982.<br />
Cement<br />
Leaching tests on full size waste blocks showed bitumen exhibited leach<br />
advantages over cement based waste products.<br />
1. C. V. Mclsaac, D. W. Akers, J. W. McConnell, and N. Morcos, "Leach<br />
Studies on Cement-Solidified Ion Exchange Resins from Decontamination<br />
Processes at Operating Nuclear Power Stations," EGG-M-92090, Idaho<br />
National Engineering Laboratory, EG&G Idaho, Inc., Idaho Falls, ID.<br />
Tested Cemented resin samples against NRC requirements, the samples did<br />
not pass the tests.<br />
2. L. Weitzman and L. E. Hamel, "Evaluation of Solidification/Stabilization<br />
as a Best Demonstrated Available Technology for Contaminated Soils,"<br />
PB89-169908, Acurex Corporation, Research Triangle Park, NC, March 1989.<br />
E-7
WHC-SD-W100-TI-003 Rev. 0<br />
Literature Search WRAP 2A<br />
Page 2 of 9<br />
Soils with metals and organics was solidified with cement, lime, and<br />
flyash.<br />
The resul-ting rCLp tests sh,owed metal leach rates were lowered but<br />
little or no retention effects were shown with the organics.<br />
3. B. G. Place, "Treatment Technology for Transuranic Waste Streams--<br />
Cementation, Vitrification, and Incineration Testing for the Treatment<br />
of Spent Ion Exchange Media," WHC-EP-0462, Technical Report,<br />
Westinghouse <strong>Hanford</strong> Company, Richland, WA, April 1992.<br />
Physical pretreatment of ion exchange resin prior to cement<br />
solidification enhances product characteristics and waste packing<br />
efficiencies.<br />
4._-_ C. G-.Howard, "Advanced-Cementatinn Concepts Final Report," AEEW-R2398,<br />
Winfrith Technology Centre, Winfrith, United Kingdom, October 1989.<br />
The addition of limestone flour or microsilica to cement solidifications<br />
reduces the cesium leachability. Microsilica acts as a pore blocker,<br />
and limestone flour acts as a cesium absorber.<br />
5. G. W. Veazey, "The Cement Solidification Systems at LANL,"<br />
LA-UR-90-4161, Los Alamos National Laboratory, Los Alamos, NM.<br />
They used an "End Over End" mixer applying cement solidification to<br />
basic sludges, and Envirostonem solidification to acidic wastes and<br />
organic compounds.<br />
6._ S. Hoyle and M. W. Grutzeck, "Effects of Phase Composition on the Cesium<br />
Leachability of Cement-Based Waste Forms," Waste Management '86, Vol. 3,<br />
Tucson, AZ, pp 491-496.<br />
Cesium leachability performance is improved by increasing the silica or<br />
alumina content of the binding cement matrix.<br />
7. S. L. Unger and R. W. Telles, "Surface Encapsulation Process for<br />
Managing Low-Level Radioactive Wastes," Waste Management '86, Vol. 1,<br />
Tucson, AZ, pp. 555-558.<br />
They applied surface encapsulation polymers namely polyethylene and poly<br />
butadiene to seal the cement solidified waste material.<br />
8. D. F. Fischer and T. R. Johnson, "Immobilization of IFR Salt Wastes in<br />
Mortar," Spectrum '88, September 11-15, 1988, Pasco, WA, pp 102-104.<br />
The addition of flyash to the cement enhanced chloride leachability<br />
performance for calcium and potassium chloride salt wastes. Leach<br />
indices were above 7 for the 10% salt mixtures.<br />
9 L. Jaouen-and-B. ^igreux, "Cement Soiidification of Spent ion Exchange<br />
Resins Produced by the Nuclear Industry," Spectrum '88,<br />
September 11-15, 1988, Pasco, WA, pp 105-108. .:°<br />
r n<br />
C-O
-<br />
'^ -<br />
qev. r'<br />
Literature Search WRAP 2A<br />
Page 3 of 9<br />
They chemically pretreated the resin wastes prior to solidification to<br />
enhance immobilization. They achieved a 40 to 75% encapsulation ratio.<br />
10. B. M. Rzyski and A. A. Suarez, "Setting Temperature Evolution of Nitrate<br />
Radwaste Immobilized in Ordinary Portland Cement," Spectrum '88,<br />
September 11-15, 1988, Pasco, WA, pp 112-114.<br />
Nitrates change the"cement hydration reaction and lower the hydration<br />
temperature.<br />
ii. J. W. McConnell, Jr., R. M. Neilson, Jr., and R. D. Rogers, "Testing<br />
Waste Forms Containing High Radionuclide Loadings," Waste Management<br />
'86, Vol.1, Tucson, AZ, March 2-6, 1986, pp 259-266.<br />
.<br />
EPiCDR Il--resins from-T-,14I-2-were so3idi€ied with port,'and cement and Dow<br />
Polymer ( vinyl ester-styrene). The waste forms were tested against NRC<br />
(10-CFR-61) requirements, the Dow polymer was attacked by fungus;<br />
otherwise all tests were positive.<br />
- Il: T. F. Schuier and "u. L. Charlesworth, "Solidification of Radioactive<br />
Incinerator Ash," Waste Management '86, Vol. 1, Tucson, AZ,<br />
March 2-6, 1986, pp 489-493.<br />
ASHCRETE. The ashcrete process uses an automatic tumbler mixer from<br />
Stock Equipment Co. that adds ash waste to cement, sand and water to<br />
form an ash concrete.<br />
13. W. 0. Greenhalgh, "The Immobilization of Organic Liquid Wastes," Waste<br />
Management '86, Vo1.3, Tucsor, AZ, March 2-6, 1986, pp 255-260.<br />
Report described immobilization of organic liquids ( oil, NPN, etc.)<br />
using cement in combination with emulsifiers.<br />
-14.---ifi:-G-. towgil1,-"A Comparison of Solidification Media for the<br />
Stabilization of Low-Level Radioactive Wastes," BNL-52304, Brookhaven<br />
National Laboratory, Upton, NY, October 1991.<br />
The document compares the solidification characteristics of Cement,<br />
thermoplastic polymers, Thermosetting polymers, and Gypsum. The binding<br />
of cesium and certain other elements is difficult for cement and gypsum;<br />
flammability and incorporation of oxidizing agents are difficult with<br />
the polymer media. A comparisvn-tabie is included.<br />
15. R. L. Gay and L. F. Grantham, "High Strength Cementized Dried Resins,"<br />
Waste Management '86, Vol. 3, March 2-6, 1986, Tucson, AZ, pp 479-483.<br />
Chemically spent resins pretreated in a high efficiency drier were found<br />
to be nearly impermeable to water and therefore formed satisfactory<br />
products when solidified with cement. Swelling is often a problem<br />
when -H and -OH type resins are solidified with cement.<br />
16. --8.- Siskind-,- :i.-kt. .4dams,- 1. H. C.l-i-aton,- and P:1. Pici„1o, "The Effect<br />
of Cure Cor,diti-0ns on the Stability-^f r ..O ... ^^ant ^.. Waste Forms after<br />
inonersion in Water," Waste Management '88, Vol. 1, February 28 -<br />
March 3, 1988, Tucson, AZ, pp 613-618.<br />
E-9
WHC-SD-W100-TI-003 Rev. 0<br />
Literature Search WRAP 2A<br />
Page 4 of 9<br />
Some formulations exhibited typical cure patterns, others did not<br />
particularly those with high resin loadings.<br />
17. B. L. Ganser, "Cementation - A Solution for Final Disposal," Waste<br />
Management '90, Vol. 2, February 25 - March 1, 1990, Tucson, AZ,<br />
pp 527-533.<br />
Rlast furnaie s7ay^-Cement showed-Iower -radionuclide<br />
r leach results than<br />
portland cement. Cement products formed by direct cementation of liquid<br />
wastes showed excellent mechanical properties. Tong term stability of<br />
cement looked good except under unrealistic harsh conditions.<br />
18. K. Sauda, F. Todo, T. Nakashima, T. Kagawa, and H. Kuribayashi,<br />
"Advanced Cement-Solidification Process for Spent Ion-Exchange Resins,"<br />
Waste Management '90, February 25 - March 1, 1990, Tucson, AZ,<br />
pp 299-303.<br />
-_ ,<br />
Spent ion-exchange resins were pretreated and modification made to<br />
enhance cement solidification. They included ( 1) adsorption of Na, Ca,<br />
^- --- -- andotherionss ( 2) improvement of the cement binder, (3) coating the<br />
resin with polyester or other sealant, and (4) resin pretreatment to<br />
increase the water content.<br />
19. H. J. Funk and R. Pfeiffer, "Solidification by Cementation of Liquid<br />
Radioactive Primary Waste Mixes," Waste Management '90, February 25 -<br />
March 1, 1990, Tucson, AZ, pp 803-807.<br />
They used an in-drum cement mixing method to solidify evaporator and<br />
other process residues of primarily sodium nitrate. A water to cement<br />
ratio of O.a5 was used to yield a compressive strength product of 10<br />
N/sq mm.<br />
--- ZD.-__A,_M_ Boehmer_and-M. M.Larsen,_"So1.idi-firat9om o-f-tlazardous and M,;xed<br />
Radioactive Waste at the Idaho National Engineering Laboratory," Waste<br />
Management '86, Vol. 1, March 2-6, 1986, Tucson, AZ, pp 635-642.<br />
Mixed wastes were successfully solidified using cement, cement-silicate,<br />
or Envirostone to produce non-toxic stable waste forms. In-drum mixers<br />
or rotary drum mixers were used to prepare the test drums.<br />
21. J. A. Stone and P. D. d'Entremont, "Measurement and Control of Cement<br />
Set Times in Waste Solidification," DP-1404, Technical Report, Savannah<br />
River Laboratory, Aiken, SC, September 1976.<br />
The report addresses the use of set retarders particularly Pozzolith<br />
122-R and showed that retarders could be used to control the cementwaste<br />
set times.<br />
22. "Atcor Radwaste Solidification Systems," Technical Data Sheet, Atcor<br />
Engineered Systems, Inc., Chem-Nuclear Company, Avon, CT.<br />
Atcor has cement and Dow polymer feed storage systems, in-line or incontainer<br />
(steel liners) mixer systems, and support systems to provide<br />
waste solidification services per customer needs.<br />
E-10
Dow Polymer<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Literature Search WRAP 2A<br />
Page 5 of 9<br />
1. H. E. Filter and K. Roberson, "The Dow System for Solidification of Low<br />
Level Radioactive Wastes from Nuclear Power Plants," Technical Report,<br />
Dow Chemical Company, Midland, MI, May 1977.<br />
Envirostone<br />
This is one of the initia7 Company reports describing Dow Polymer and it<br />
use as a solidification agent.<br />
1. T. L. Rosenstiel, S. P. Bodett, and R. G. Lange, "Envirostone Gypsum<br />
Cement," 1984 Topical Report, United States Gypsum, Libertyville, IL.<br />
This report details the qualification of Envirostone Gypsum Cement per<br />
e` .P 10 CFR-61 type tests. Test samples include boric acid, ion exchange<br />
resin, and oil wastes; all waste products tested were qualified.<br />
2. T. L. Rosenstiel and R. G. Lange, "The Solidification of Low Level<br />
Radioactive Organic Fluids with Envirostone Gypsum Cement," Waste<br />
Management '84, March 11-15, 1984, Tucson, AZ, pp 169-172.<br />
Grout<br />
The report covers the successful solidification of oils using<br />
emulsifiers in conjunction with Envirostone cement.<br />
I. E: L. Wiihite and R. L. Hooker, "Saltstone Processing Startup at the<br />
Savannah River Plant," Spectrum '88, September 11-15, 1988, Pasco, WA,<br />
pp 99-101.<br />
Predicted maximum ground-water concentration of all contaminants from<br />
saltstone disposal are below ground-water standards based on modeling<br />
studins_<br />
2. T. M. Gilliam, R. D. Spence, B. S. Evans-Brown, I. L. Morgan,<br />
J. L. Shoemaker, and W. D. Bostick, "Performance Testing of Blast<br />
Furnace Slag for Immobilization of Technetium in Grout". Spectrum '88,<br />
September 11-15, 1988, Pasco, WA, pp 109-111.<br />
The addition of slag cement improved the retention of technetium and to<br />
a lesser extent nitrate.<br />
3. C. A. Langton, "Metal Toxicity Evaluation of Savannah River Plant<br />
Saltstone Comparison of EP and TCLP Test Results," Waste Management '88,<br />
Vol. 1, February 28 - March 3, 1988, Tucson, AZ, pp 197-203.<br />
Based on EP and TCLP tests, chromium Is chemically stabilized in s7ag<br />
based-3&l-titone and physically entrapped in the cement based saltstone.<br />
The_chemica7 stabilization is preferred ( better)!<br />
4. T. L. Sams and E. W. McDaniel, "Development of a Cement-Based Grout for<br />
Immobilization of a Low Level Waste Stream containing Sodium Sulfate,"<br />
Waste Management '88, Vol. 1, February 28 - March 3, 1988, Tucson, AZ,<br />
pp 703-708.<br />
- E-11
WHC-SD-W100-TI-003 Rev. 0<br />
Literature Search WRAP 2A<br />
Page 6 of 9<br />
The grout contained cement type III, flyash, attapulgite clay, and<br />
indian red pottery clay. The formulations are on page 705.<br />
5. E. G. Collins and G. Magnin, "Final Design and Start-up of the<br />
Transportable Grout Equipment Facility at <strong>Hanford</strong>," Waste Management<br />
'88; VoT.--i, February 28 - March 3, 1988, Tucson, AZ, pp 751-759.<br />
The TGE facility is a remote operating grout mixing facility.<br />
f:. -- - J. E. Van Beek-a.n.d-D.-D. Wodrich,--"Gro!^± Disposal System for <strong>Hanford</strong><br />
rfiized Waste;" Waste Management '90; Vol.--!, February 25 - March 1, 1990,<br />
Tucson, AZ, pp 797-802.<br />
The system has been designed to meet hazardous waste regulations and has<br />
^L.---<br />
1lI)LIdLPO (l(IPI'.il//)/I5.<br />
7: C. A. Langton, M. D. Dukes, and R. V. Simmons, "Cement-Based Waste Forms<br />
for Disposal of Savannah River Plant Low-Level Radioactive Salt Waste,"<br />
DP-MS-83-71, Technical Report, Savannah River Laboratory, Aiken, SC,<br />
November 14-17, 1983.<br />
A cement based grout waste form has been designed to treat 100 million<br />
liters of soluble salt waste, the waste form is termed "salt stone".<br />
8. 0. K. Tallent, E. W. McDaniel, G. D. Del Cul, K. E. Dodson, and<br />
R6-$A^<br />
- . . . -_""---- ---='v: R:`-rr-^`itter ,-'"ifTlilR'i i iizatTii ui ia^h netlum-an -Ni$rate in Cement-Based<br />
Materials," Mat. Res. Soc. Symp. Proc., Vol 112, 1988, pp 23-32.<br />
The Ieachabilities of technetium and nitrate wastes immobilized in<br />
cement-based grouts have been investigated using ANS 16.1 test<br />
prgcedures.- -factors found to affect the leachabilities include grout<br />
mix ratio, fluid density, blend composition, and waste composition.<br />
9.--------'r!: 0: Greenhaigh, R:-J:-Cash, and M.-A. Christif,- "T-Rti- Waste- im-mobiiized<br />
---- -- ---------- - inGr-out;^Waste Management '88, Vol. 2, Tucson, Arizona, February 28 -<br />
March 3, 1988, pp 309-316.<br />
Various portland cement based grout compositions mixed with shredded<br />
solid waste was tested for WIPP and NRC compliance criteria. Some<br />
compositions passed all tests.<br />
Hydrothermal Solidification Process<br />
1. Y. Nishihara, T. Kashiwai, and N. Yamazaki, "Development of the Waste<br />
Solidification Process Utilizing Hydrothermal Reaction," Waste<br />
Management '86, Vol. 3, March 2-6, 1986, Tucson, AZ, pp 485-490.<br />
The hydrothermal reaction is characterized by reacting mixed powders<br />
---- ---------- surh-as-?nE-ineratnr ashes, solidification material, and aqueous alkali<br />
at relatively high temperatures and pressures to form a synthesized<br />
rock.<br />
E-12
L im e<br />
Literature Search WRAP 2A<br />
Page 7 of 9<br />
1. A. Dupont, "Lime Treatment of Liquid Waste Containing Heavy Metals,<br />
Radionuclides, and Organics", Technical Fact Sheet, National Lime<br />
Association, Arlington, Virginia, August 1, 1986.<br />
Polvethvlene<br />
1. _ _P. 0, _Kal b _and P. Colombo, _"PoLve-thyl ene -Sol Ui ficati on of Low-Level<br />
Wastes," BNL 51867, Topical Report, Brookhaven National Laboratory,<br />
Upton, NY, October 1984.<br />
Polyethylene was tested and evaluated as a radwaste immobilization<br />
media; recommendations are given on sodium sulfate, boric acid,<br />
incinerator ash, and ion exchange resin wastes.<br />
2. P. D. Kalb, J. H. Heiser, and P. Colombo, "Polyethylene Encapsulation of<br />
Nitrate Salt Wastes: Waste form Stability, Process Scale-Up, and<br />
Economics," BNL-52293, Topical Report, Brookhaven National Laboratory,<br />
Upton, NY, July 1991.<br />
A polyethylene encapsulation system for treatment of 1ow-Ieve1<br />
radioactive, hazardous, and mixed waste has been developed and appears<br />
to offer several advantages over more conventional methods such as<br />
cement.<br />
Polymer Imoreanated Concrete (PIC)<br />
1. Brookhaven National Laboratory Progress Reports for the Development of<br />
Durable Lono-Term Radioactive Waste Composite Materials , No. 1-10,<br />
_ __zluly 1972 - Apri1 1_975,_Bronkhavan Natinnal Laboratory, Upton, NY.<br />
2. Brookhaven National Laboratory Progress Reports for the SRL Lono-Term<br />
Waste Storaae Suooort Progress , No. 1-8, July 1973 - January 1975,<br />
Brookhaven National Laboratory, Upton, NY.<br />
Cemented waste is impregnated with a Iow viscosity polymer such as<br />
styrene after the cement has been cured. The catalyst (benzoyl<br />
peroxide) is then added at 0.5 wt% and the material polymerized within 3<br />
to 4 hours at 50 to 70'C. Product leaching performance is improved a<br />
factor of 100 and compression strengths are 3 to 10 fold higher.<br />
Sulfur Polymer Cement<br />
1. P. 0. Kalb and P. Colombo, "Modified Sulfur Cement Solidification of<br />
Low-Level Wastes,"BNL 51923, Topical Report, Brookhaven National<br />
---Lab4ratory,_U¢ton,_NYr-Qctober-1-985:<br />
Sulfur Polymer Cement was tested as a radwaste solidification agent. It<br />
appears to produce an acceptable waste form and recommendations for<br />
sodium sulfate, boric acid, and incinerator ash wastes are provided.<br />
E-13
WHC-SD-W100-TI-003 Rev. 0<br />
Literature Search WRAP 2A<br />
Page 8 of 9<br />
2. P. D. Kalb, J. H. Heiser III, and P. Colombo, "Encapsulation of Mixed<br />
Radioactive and Hazardous Waste Contaminated Incinerator Ash in Modified<br />
Sulfur Cement," BNL-43691, Technical Report, Brookhaven National<br />
Laboratory, Upton, NY.<br />
The sulfur polymer cement will hold about three times more incinerator<br />
ash than regular cement waste products.<br />
3. P. D. Kalb, J. H. Heiser III, and P. Colombo, "Comparison of Modified<br />
Sulfur Cement and Hydraulic Cement for Encapsulation of Radioactive and<br />
Mixed Wastes," BNL-45163, Technical Report, Brookhaven National<br />
I 1. e+....., nn+nn klv<br />
LGVVr14V1^, V'/FVI1, 1.1.<br />
The report claims significantly greater waste loadings-for the sulfur<br />
polymer cement versus the regular hydraulic cement for radwastes.<br />
4. G. R. Darnell, W. C. Aldrich, and J. A Logan, "Full-Scale Tests of<br />
Sulfur Polymer Cement and Non-Radioactive Waste in Heated and Unheated<br />
Prototypical Containers," Informal Report, EGG-WM-10109, Idaho National<br />
Engineering Laboratory, Idaho Falls, Idaho, February 1992.<br />
Syncrete<br />
They found sulfur polymer cement to be superior to portland cement in<br />
so7idfying ash material.<br />
1. S. Cohen and P. Crouzet, "A High Efficient Polymer Cement Embedding<br />
Matrix for Waste Processing," Waste Management '86, Vol. 1,<br />
March 2-6, 1986, Tucson, AZ, pp 583-588.<br />
Other<br />
Syncrete (synthetic concrete) is a composite matrix of ordinary<br />
hydraulic cement and a thermosetting polymer mixture. The Syncrete<br />
exhibits a significantly reduced water uptake.<br />
1. K. D. Wiel^lers, J. E. Mendel, A. A. Kruger, L. R. Bunnell, and<br />
G. B. Mellinger, "Preliminary Assessment of Candidate Immobilization<br />
Technologies for Retrieved Single-Shell Tank Wastes," PNL-7918,<br />
Technical Report, Pacific Northwest Laboratory, Richland, WA,<br />
January 1992.<br />
It lists candidate waste forms for low-level, transuranic, and highlevel<br />
wastes.<br />
2. W. 0. Greenhalgh, "Disposal Concepts for Wastes in Underground Single-<br />
Shell Storage Tanks at the <strong>Hanford</strong> <strong>Site</strong>," WHC-SA-1344-FP, Technical<br />
Report, Westinghouse <strong>Hanford</strong> Company, Richland, WA, January 1992.<br />
----- ------ -------Jieport-lists-candidate-waste-f-orms-or-methods-being considered for<br />
Immobilization of radioactive tank waste.<br />
3. P. D. Kalb and P. Colombo, "Full Scale Leaching of Commercial Reactor<br />
"--`- easte F-^ rvrms, " BNL 35561, Technical Report, Brookhaven National<br />
Laboratory, Upton, NY, September 1984.<br />
E-14 -
The report compares the 7eachability of<br />
and masonry cement versus Dow polymer.<br />
rates for transition metal ions such as<br />
cesium. The Dow polymer showed similar<br />
radionuclides indicating an encapsulatii<br />
Literature Search WRAP 2A<br />
Page 9 of 9<br />
several cements, type I, III,<br />
The cements showed lower 7each<br />
cobalt and higher ones for<br />
leach rates for cesium and other<br />
ig mechanism.<br />
4. Alternatives for Manaqino Wastes from R eacto rs and Fissi onOoe rations i<br />
the LWR Fuel Cycle . EROA-76-43, Vol. 2, May 1976, Pacific Northwest<br />
Laboratories, Richiand, WA, Sections 12.0 to 12.41.<br />
The included Section provides a comprehensive summary of solidification<br />
methods used prior to 1976 for low-level wastes.<br />
r ' e<br />
C-18
WHC-SD-W100-TI-003 Rev. 0<br />
Westinghouse Internal<br />
<strong>Hanford</strong> Company Memo<br />
From: Chemical Process Engineering<br />
Phone: 6-9616 L5-42<br />
Date: May 29, 1992<br />
Subject: WRAP 2A LITERATURE SEARCH UPDATE - NOTE ON SULFUR POLYMER CEMENT<br />
To: J. L. Westcott H2-58<br />
cc: J. W. Biglin L5-31<br />
J. A. Hunter L5-31<br />
J. G. Riddelle H2-58<br />
WOG/File-LB<br />
The hotte^t sC?id1-fiCation-med-i-a ^rr the-market- in recent years is sulfur<br />
polymer cement, sold as CHEMENT 2000. It is elementary sulfur<br />
(approximately 95%) mixed with a thermosetting polymer (dicyclopentadiene)<br />
that melts at 119°C. The sulfur polymer cement (SPC) was developed by the<br />
,.; Sulfur institute of Washington D.C. to provide an additional market for<br />
suifur materiais. it was found to be very useful in coating, covering, or<br />
actually replacing concrete in applications where acidic or salt corrosion<br />
were severe. It has been shown in many of these applications to be superior<br />
to portland type concrete or cement products with the possible exception of<br />
polymer impregnated concrete. The reason for its enhanced performance in<br />
the above mentioned areas is probably the chemistry of the system.<br />
Portland cement mixes and concrete matrices are basic exhibiting an initial<br />
pH of about 13. Sulfur on the other hand is probably best considered as an<br />
Arhennius type acid. This means that sulfur would likely provide an<br />
excellent solidification media for acidic materials or provide protection<br />
from attack by acidic materials, but would likely react with or be attacked<br />
by basic materials. Cement or concrete on the other hand stabilizes base<br />
type materials well and the product matrix is stable to attacks by bases.<br />
It turns out both materials are fairly compatible with neutral materials and<br />
are generally stable in a neutral environment. It is recommended that SPC<br />
not be used to solidify any base as strong or stronger than sodium carbonate<br />
to avoid forming an unstable product, particularly if water is present. An<br />
example of an acid-base reaction is given below.<br />
Na2CO3 + H2O + S =- NaHCO3 + NaHS + 1/202<br />
In addition to sulfur exhibiting acidic properties, sulfur is also a<br />
reducing agent. That means that it should not be mixed with, nor used to<br />
immobilize, oxidizing materials or materials with significant quantities of<br />
axidantsY The amounts of nitrite or nitrate material that can be present in<br />
SPC treated waste materials needs to be defined. In addition, sulfur is a<br />
combustible material (flashpoint 188°C) which burns with a very light blue,<br />
E-16<br />
<strong>Hanford</strong> Operatione and EnpineeAnp Contractor for the US Department of Enarpy
J. L. Westcott<br />
Page 2<br />
May 29, 1992<br />
WHC-SD-W100-TI-003 Rev. 0<br />
almost invisible, flame that emits sulfuric acid type fumes. Care should be<br />
taken to limit SPC mixing or handling temperatures well below the flashpoint<br />
region.<br />
^1 /• ^ ^ l^ ^,<br />
W. 0. Greenhalgh, Principal Scientist<br />
rhamiral Drnroee Fnninuurinn<br />
-..-....--. ..---^^ -.^...^^...7<br />
ldc<br />
E-17
,RTIN MARIETTA ENERGY SYSTEMS, INC.<br />
Mr. J. L. Westcott<br />
Westinghouse <strong>Hanford</strong> Company<br />
Post Office Box 1970, H2-58<br />
Richland, Washington 99352<br />
De,jr Jeff:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Reports and Papers Discussing Alternate Solidification Technologies<br />
POST OFFICE BOX 2008<br />
OAK RIDGE. TENNESSEE 37831<br />
April 24, 1992<br />
Enclosed is a list of the vendor reports, technical data sheets and papers that I am mailing to you as<br />
I promised to do when I returned from my vacation.<br />
These are being mailed to you in two separate packages and will be labeled #1 and #2.<br />
EWM:jew<br />
Enclosures<br />
cc: C. H. Brown, Jr.<br />
^:. : Ta::e;^<br />
E-18<br />
Best Regards,<br />
Earl W. McDaniel<br />
Chemical Technology Division
Package #1:<br />
Package #2:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
LIST OF REPORTS AND PAPERS<br />
DISCUSSING ALTERNATE SOLIDIFICATION TECHNOLOGIES<br />
(1) Nuclear Waste: Solidification Programs<br />
(2) __ Lime_Treatment of Liquid Waste Containing Heavy Metals, Radionuclides, and<br />
Organics - Part I - Processes for Treatment<br />
(3) Immobilization of Rocky Flats Wastes Using the Inert Carrier Process<br />
(4) Reaction of Formaldehyde and Nitric Acid in a Remotely Operated Thermosiphon<br />
Evaporator<br />
(5) Envirostone - Gypsum Cement<br />
(6) Waste Generation Reduction - Nitrates Comprehensive Report of Dcnitr': cation<br />
Technologies<br />
(7) Syncrete - A High Efficient Polymer Cement Embedding Matrix for Waste Processing<br />
(8) Solidi6cation/Stabilization - Mechanisms & Applications<br />
(9) Solidification of Nitrate Salt Wastes - RMN-15-86<br />
(10) VERI (Vinyl Ester Resin In Situ) Solidification Process for Low-Level Radioactive<br />
Waste<br />
(11) Service Summary - Diversified Technologies<br />
(12) A Waste Management System Utilizing WPS, HVV, and VERI Process Systems and<br />
Technology<br />
(13)-- Radioactive Waste Management and Disposal<br />
(14) Solid Solutions for Your Toxic Metal and Organic Wastes<br />
(15) Report of Note (LLRW)<br />
(16) Low-TemperatureCeramicRadioactiveWasteFormCharacterizationofSupercalcine-<br />
Based Monazite-Cement Composites<br />
(17) Operating Cost Estimate Low Level Radioactive Waste Volume Reduction and<br />
Packaging Options<br />
(18) Abbreviated Statement of Qualifications<br />
E-19
Internal Correspondence<br />
Mr. Jeff Wuestcott<br />
Westinghouse <strong>Hanford</strong> Company<br />
P. O. Box 1970, N3-12<br />
Richland, Washington 99352<br />
Dear Jeff:<br />
WHC-SD-W100-TI-003 Rev. F<br />
MARTIN MARIETTA ENERGY SYSTEMS, INC.<br />
August 21, 1991<br />
Milestone Letter Report: Cement Grout Technology Final Report Due August, 1991<br />
Enclosed is a copy of the above milestone titled, "Survey of Grouting Technology in Support of<br />
WRAP's Shred-Grout Module, Final Report."<br />
if there are any questions or comments,rtease call F1S 624-0439.<br />
EWMcD:jen<br />
Enclosure<br />
Best Regards,<br />
Earl W. McDaniel, Manager<br />
------- --$anfordfrrout Program<br />
Chemical Technology Division<br />
E-20
WHC-SD-W100-TI-003 Rev. 0<br />
SURVEY OF_GROUTING TECHNOTO('TY<br />
IN SUPPORT OF<br />
WRAP'S SHRED GROUT MODULE<br />
FINAL REPORT<br />
A Letter Report Prepared<br />
for Westinghouse <strong>Hanford</strong> Company<br />
Richland, WA<br />
L^-^ ^:.a.. :::. .*.",cDaniel<br />
Chemical Technology Division<br />
Oak Ridge National Iaboratory^<br />
Oak Ridge, Tennessee 37831-6044<br />
'Managed by Martin Marietta Energy Systems. Inc., for the U.S. Department of Energy<br />
under contract DE-AC05-34OR21400.<br />
E-21
WHC-SD-W100-TI-003 Rev. 0<br />
SURVEY OF GROUTING TECHNOLOGY IN SUPPORT OF<br />
WRAP'S SHRED-GROUT MODULE<br />
•- L ------<br />
MliJt^ XcPURT<br />
Introduction<br />
This ftnal letter report in support of WRAP's shred-grout module is more an extension of the<br />
April 1991 draft report than a final version. The April 1991 report discussed ;routint, facilities at a<br />
variety.of US DOE sites and provided informatior;ab9sttthe-use of--routsinrhe iru France,<br />
Germany, Korea, Japan, Finland, and Taiwan. Over fifty reports and papers were supplied as<br />
supporting documents. Very little information from the draft report will be repeated in this letter<br />
report, only the executive summary and the introduction. The draft report made no<br />
--recammendations, dr'w no conclusions or discussed lessons learned. This Threport will address these<br />
4epics.--Also included are -a number of-additionai reports and documents in support of WRAP's<br />
shred-grout module.<br />
LESSONS LEARNED<br />
.. .<br />
--- --- --- -Processand-.ormtlafion developmert in listed papers and reporis aescnoed success stories. IF vou<br />
do things in the prescribed manner the end result will be an acceptable product. The major lesson<br />
learned was from information provided by the Martin Marietta Energy Systems K-25 <strong>Site</strong> Sludge<br />
Fixation Facility. The problems at this facility have received wide press coverage. This facility can<br />
serve as an example as what not to do or what happens when processes are not properly developed<br />
prior to plant operations.<br />
Little process development was performed prior to plant design and construction. The feelings were<br />
t hat we were just making concrete, not doing brain surgery, and anyone can make good concrete.<br />
It is a well established art.<br />
- ^-«
f ..;'<br />
WHC-SD-W100-TI-003 Rev. 0<br />
A summary of plant operations is as follows: the manner in which -the sludge tieation facility was<br />
operated was generally sloppy and not governed by any established operating procedures. Training<br />
for the operators was on-the-job with no written tests or performance testing. Little attention was<br />
given to quality assurance planning or execution. There was no apparent effort in quality control of<br />
the product.<br />
A minimal level of outside expertise and advice was sought throughout the project. No concrete<br />
batch experience was acquired or used in the development work and virtually none was sought for<br />
plant operations.<br />
Pressutes to keep cost of the sludge fixation facility operation down were immense. It should be<br />
noted that a development program costing between SO.75M and S1.5M up front could have avoided<br />
a 550-100M retrofit. The perception that the sludge fixation facility was not important affected both<br />
funding and operator attitude.<br />
The principal causes of the problem were: (1) the process equipment utilized was inadequate to<br />
solidify low solids containing sludge, (2) no final product inspections of solidified waste forms were<br />
conducted, (3) a "self-inflicted" schedule for solidification was imposed, (4) there were no personnel<br />
primarily dedicated to managing the project, (5) there was no involvement of middle and upper<br />
management, and (6) the quality assurance program was ineffective.<br />
$^.rther c:rr.tple offaihne is the RocRy ;,ats pondcrete problem, in which little or no development<br />
effort was done and no attention given to final product quality. The Rocky Flats issue appears to<br />
be headed for court, so little else will be said beyond there appears to be both a legal and technical<br />
problem there.<br />
One example of well-developed processes is the Savannah River <strong>Site</strong> Saltcrete process, which was<br />
well developed and has been operating for several months with no problems. Support documentation<br />
is supplied in the April 1941 dra€^repcrt. The Han^rd Grout Treatment facility has also completed<br />
one successful campaign and is in the process of developing formulae for additional waste streams.<br />
This effort is also documented in the earlier letter report.<br />
E-23
WHC-SD-W100-TI-003 Rev. 0<br />
The above examples are listed only to serve as what can happen if proper attention is not devoted<br />
to up-front development and is not intended to be all-inclusive.<br />
CONCLUSIONS AND RECOMMENDATIONS<br />
The major conclusions to be drawn from the literature search are: (1) much development effort has<br />
been devoted to tixing a variety of waste in a cement-based matrix, and (2) each waste stream must<br />
be carefully characterized prior to any successful development effort.<br />
The following recommendation is germane: a well defined technology development effort that starts<br />
with lab scale, progresses through pilot scale, and ends in full scale testing and demonstration is<br />
necessary to assure successful plant design and operation.<br />
It is recommended that the Shred-grout development effort in support of WRAP start in FY-1992<br />
to assure that adequate information in process development and equipment selection be available<br />
when needed.<br />
It is recommended-that a team be-organized consisting of at least the following persons: (1) a R&D<br />
manager. ( 2) a R&D engineer. (3) a QA specialist, and (4) a compliance specialist.<br />
The manager should be the point of contact for information flow and should be dedicated full-time<br />
to the effort. The (project) engineei should be responsible for any design, construction, or<br />
--- -- - engir:eering-work-needed to support development work. l}te engineer should also be responsible for<br />
costs and budgets. The QA specialist will be necessary to insure quality is "built in" throughout the<br />
development effort. The compliance specialist will assure that the end product meets or exceeds<br />
regulatory requirements. The compliance specialist will be responsible for assuring that all activities<br />
are carried out in compliance with federal, state, and local regulations, laws, and standards for<br />
protection of the environment and the safety and health of involved employees and the public.<br />
----_A closing Statemen-twotSldbr tFtat-}t ts-Chealpe-Ftt3do it Co.i°ccth% the first time.<br />
E-24
WHC-SD-W100-TI-003 Rev. 0<br />
SURVEY OF GROUTING TECHNOLOGY IN SUPPORT OF<br />
WRAP'S SHRED GROUT MODULE<br />
E. W. McDaniel<br />
EXECUTIVE SUMMARY OF APRIL 1991 DRAFT REPORT<br />
This letter report covers a wide variety of grouting and other information that may be<br />
applicable to WRAP's Shred-Grout Task. Very little information is available on past, or present,<br />
operations of fixing shredded solids in a cement-based matrix.<br />
Information is provided about ORNL's Hydrofracture Process, the K-25 <strong>Site</strong> Sludge<br />
Fixation Facility, SRS Saltstone, <strong>Hanford</strong>'s Grout Treatment Facility, and PPEPP at INEL.<br />
Limited information is provided on grouting efforts at Rocky Flats, West Valley, and Mound<br />
Labs.<br />
Information is provided on cement-based fixation efforts in a number of European and<br />
Asian countries.<br />
A literature search is included that addressed low-level waste solidification technology.<br />
Also, included is a strategic planning document on low-level waste disposal and demonstration<br />
programs at Oak Ridge, Tennessee. This report also contains a three volume report about waste<br />
management processes in the nuclear industry.<br />
E-25
WHC-SD-W100-TI-003 Rev. 0<br />
IN'I'RODUCTION FROM APRII.1991 DRAFT REPORT<br />
This letter report covers a variety of cement-based grouting technologies, both national<br />
and international, that may be applicable to Westinghouse <strong>Hanford</strong> Company's Waste Receiving<br />
and Processing (WRAP) Shred-Grout effort. WRAP's mission is to process past and currently<br />
guenerated solid low-level (SLLW), mixed (MLW), and transuranic (TRU) waste at the <strong>Hanford</strong><br />
site. Richland, Washington. As this is an internal letter report, no background on WRAP is<br />
provided.<br />
The waste to be processed by WRAP has been generated in defense related efforts and<br />
are, in many cases, unique to this industry. However, the commercial sector of the nuclear<br />
industry has developed, both in the United States and abroad, grouting technology that, with<br />
modification, is applicable to WRAP ( i.e., the solidification/stabilization of spent ion-exchange<br />
resins).<br />
Infortnation_is provided on USDOE grouting efforts at Oak Ridge, Tennessee<br />
(Hydrofracture at ORINL and the Sludge Fixation Facility at the K-25 <strong>Site</strong>), PREPP at INEL,<br />
Saltstone at SRS, West Valley, NY, and Soilcrete at 1NEL. A brief description is given of the<br />
Rocky Flats plant inert carrier process. A manual laboratory process for making pellets of TRU<br />
waste is mentioned. It should be pointed out that little work has been reported on grouting<br />
shredded solids as is the mission of WRAP's shred-grout module.<br />
Most of the international information reported is from nuclear utilities. It is difficult to<br />
obtain information on defense reiated efforts in countries that have nuclear weapons programs,<br />
such as the United Kingdom (UK), France, and the USSR. West Germany (now just Germany)<br />
has a small shred-grout facility at NUKEM's Hanau plant. This operation was covered in<br />
R. Wotojack's 1986 trip report and will not be repeated here.<br />
It is noted that the majority of grouting information reported in the open literature<br />
addresses the use of cement-based materials ( i.e.. grouts) to solidify liquids and slurries. Most<br />
E-26
WHC-SD-W100-TI-003 Rev. 0<br />
commercial processes are in drum or batch type mixing. Larger operations are: the ORNL,<br />
hydrofracture facility for liquid waste (which is no longer operational), the K-25 Sludge Fi.eation<br />
------- ---- ---Facility,-the SRS-Saltcreteplaat,the <strong>Hanford</strong> Grout TrEatmentFacility, PREPP at TNFT<br />
^,;•<br />
West Valley's grout facility.<br />
Information is also provided on the use of grouts in the UK, France. Germany, Korea,<br />
Japan, Finland, and Taiwan.<br />
E-27
WHC-SD-W100-TI-003 Rev. 0<br />
Copies of all reports listed in the bibliography are included in this report.<br />
E-28
WHC-SD-W100-TI-003 Revo 0<br />
Bibliogranhy<br />
A. Bernard, J. C. Nomine, G. Cornec, A. Bonnet, and L. Farges, "Long-Term Leaching Tests on Full-<br />
Scale Blocks of Radioactive Wastes," Nuclear and Chemical Waste Management, v. 3, 161-5,<br />
1982.<br />
L. G. Butler, F. K. Cartledge, D. Chalasani, H. C. Eaton, F. Frey, M. E. Tittlebaum, and S.-L. Yang,<br />
"Immobilization Mechanisms in Solidification/Stabilization Using Cement/Silicate Fixing<br />
Agents," Proceedings, LSU HWRC Symposium, Oct. 1988.<br />
-- D. Chalasani, F. IC.-CardedgP,- H. C,- Eaton,--M. F'.T'.tttlebaum, and M. R. Walsh, "The Effects of<br />
Ethylene Glycol on a Cement-Based Solidification Process," Hazardous Waste & Hazardous<br />
Materials, v. 3, 2, 167-71, 1986.<br />
A- C. Chou, H. C. Eaton, F. W. Cartledge, and M. E. Tittlebaum, "A transmission Electron<br />
Microscopic Study of Solidified/Stabilized Organics," Hazardous Waste & Hazardous<br />
Materials, v. 5, 2, 145-53, 1988.<br />
A. I. Clark, C. S. Poon, and R. Perry, "The Rational Use of Cement-Based Stabilization Techniques<br />
for the Disposal of Hazardous Wastes," Proccedings: International Conf. on New Frontiers<br />
for Hazardous Waste Management, U.S. EPA/60019-85/025, Sept. 1985, 339-47.<br />
E. L: Davis, J. S: Falcone, S. D. Boyce: and P. H. i{rumrine; "Mechanisms for the Fixation of Heavv<br />
Metals in Solidified Wastes Using Soluble Silicates," The PQ Corp., Lafayette, PA.<br />
H. C. Eaton. M. E. Tittlebaum, and F. K Cartledge. "Innovative Techniques for the Evaluation of<br />
Solidified Hazardous Waste Systems," Louisiana State Univ., Baton Rouge, LA-<br />
H. C. Eaton, M. B. Walsh, M. E. Tittlebaum, F. K. Cartledge, and D. Chalasani, "Organic<br />
Interference_of-Solidified/Stabilized-Hazardous--Wastes," Er.viror.mental Monitoring and<br />
Assessment, 9 (1987), 133-42.<br />
IVI. Fuhrmann, R. M. Neilson, Jr., and P. Colombo, "A Survey of Agents and Techniques Applicable<br />
to the SolidiBcation o€-,'_ow-Lerel Radioactive Wastes," BNL-51521, Brookhaven National<br />
Laboratory Assoc. Univ., Inc., Upton, New York, Dec. 1981.<br />
P. D. Kalb and P. Colombo, "Full Scale Leaching of Commercial Reactor Waste Forms," BNL-33931,<br />
Brookhaven National Laboratory Associated Universities, Inc., Upton, New York. Nov. 1983.<br />
R. L A. viaiek; D. M. Roy, P. H.-Licastro, and C A. Langton, 'Slag Cement-Low Level Radioactive<br />
Waste Forms at Savannah River Plant," American Ceramic Soc. Bulletin, 65 (12). 1578-83,<br />
1986.<br />
H. Matsuzuru and A. Ito, "Effect of Dimension of Specimen an Amounts of Cesium-137, Strontium-<br />
90 and Cobalt-60 Leached from Matrix of Hardened Cement Grout," Journal of Nuclear<br />
Science and Technolow, v. 15, 1, 60-5.<br />
1. McGraw, "Hazardous Waste Management System; Identification and Listing of Hazardous<br />
Waste," Federal Reaister. 50, 94, 20239-48.<br />
E-29
WHC-SD-W100-TI-003 Rev. 0<br />
D. J. Naus, "Concrete Material Systems in Nuclear Safety Related Structures - A Review of Factors<br />
Relating to their Durability, Degradation Detection and Evaluation, and Remedial Measures<br />
for Areas of Distress," Internal Report, Gas-Cooled Reactor Programs, Oak Ridge National<br />
Laboratory, July 1954.<br />
T. Ohnuki, H. Ogawa, Y. Ohtsuka, T. Yamamoto, and Y. Wadachi, "Retardation Factor of<br />
Radioactive Strontium in a Japanese Sandy Soil Layer," Japan Atomic Enetgy-Reasearch<br />
Institute, Tokyo, Japan, 1989.<br />
I. Ple6aJ: J. Drl}aala, A. Peri6, and A.- KostadinoviF, "Immobilizatior, of Cs-137, Co-60, Mn-54, and<br />
Sr-85 in Cement-Waste Composition," "Boris KidriV Institute of Nuclear Sciences-VinCa,<br />
Belgrade, Yugoslavia.<br />
C. S. Poon, A. I. Clark, R. Perry, A. P. Barker, and P. Barnes, "Permeability Study on the Cement<br />
Based Solidification Process for the Disposal of Hazardous Wastes," Cement and Concrete<br />
Research. v. 16, 161-72, 1986.<br />
--c:F -----R:-H.-. .i ' L'I A..L--<br />
A .eisny er, " r` ^ .. nsc4idaaor o f r,y tvucs and Are Furnace Dusts Usin; Sodium Silicates,"<br />
Technical Report WTF#12, The PQ Corp., Lafayette, PA, June 1982.<br />
J<br />
R. Shuman, N. Chau, and E. A. Jennrich, "Long-Term Structural and Radiological Performance<br />
^•,^<br />
Assessment For an Enhanced Abovegrade Earth-Mounded Concrete Vault," DOE/LLW-7ST,<br />
Defense Low-Level Radioactive Waste Management Program, EG&G Idaho, Idaho Falls,<br />
Dec. 1989.<br />
D. G. Skipper, H. C. Eaton, F. K. Cartledge, and M. E. Tittlebaum, "Scanning Electron<br />
Microscopy/Energy Dispersive X-Ray Analysis of Type I Portland Cement Passtes Containing<br />
Parachlorophenol," Cement and Concrete Research, v. 17, 851-63, 1987.<br />
D. G. Skipper, H. C. Eaton, F. K. Cartledge, and M. E. Tittlebaum, "The Microscopic Fracture<br />
Morphology of Hardened Type I Portland Cement Paste Containing Parachlorophenol;<br />
Hazardous Waste & Hazardous Materials v. 4, 4, 389-402, 1987.<br />
A. Sheffield, S. Makena, M. Tittlebaum, H. Eaton, and F. Cartledge, "The Effects of Three Organics<br />
on Selected Physical Properties of Type I Portland Cement," v. 4, 3, 273-86, 1987.<br />
R. W. Spencer, R. H. Reifsnyder, and J. C. Falcone, "Applications of Soluble Silicates and Derivative<br />
--- --- - --:iateAaw iit the Management of Hazardous Wastes," The PQ Corp., Lafayette, PA.<br />
L. M. Thomas, "Hazardous Waste Management System; Identification and Listing of Hazardous<br />
Waste, " Federal Register, 49. 206, 4258Q 93. ,<br />
M. E. Tittlebaum, F. K . Cartledge, D. Ch?lasani, H. Eaton, and M. Walsh, "A Procedure for<br />
-r't'--- ^cterizing ,a^a<br />
interactions of Organics with Cement: Effects of Organics on<br />
Solidification/Stabilization," Louisiana State Univ., Baton Rouge, LA.<br />
M. E. Tittlebaum, H. C. Eaton, F. K. Cartledge, M. B. Walsh, and A. Roy, "Procedures for<br />
Characterizing Effects of Organics on Solidification/Stabilization of Hazardous Wastes,"<br />
Special Technical Publication 933 1987, American Soc. for Testing and Materials,<br />
Philadelphia, 1987.<br />
E-30<br />
ji-
WHC-SD-W100-TI-003 Rev. 0<br />
A. P. Toste, L. J. Kirby, W. H. Rickard, and D. W. Robertson, "Radionuclide Characterization,<br />
>-' Migration and Monitoring at a Commercial Low-Level Waste Disposal <strong>Site</strong>," Radioactive<br />
Waste Management, v. 5, 213-26.<br />
r i=<br />
A. P. Toste and T. J. Lechner-Fish, "Organic Diagenesis in Commercial Nuclear Wastes ," Transactions<br />
of the American Nuclear Societv, v. 56, Proc. of the 1988 Meeting of the Am. Nuc. Soc.. June<br />
1988.<br />
A. P. Toste, T. J. Lechner-Fish. D. J. Hendren, R. D. Sheele, W. G. Richmond. "Analysis of Organics<br />
in Highly Radioactive Nuclear Wastes," Journal of Radioanalvtical and Nuclear Chemistrv ,<br />
Articles, v. 123, 1(1988), 149-166.<br />
A. P. Toste and R. B. Myers, 'The Relative Contributions of Natural and Waste-Derived Organics<br />
to the Subsurface Transport of Radionuclides," The Effects of Natural Oraanic Comoounds<br />
and of Microoreanisms on Radionuclide Transoort. Proc. of NEA Workshop, Paris, June<br />
1985.<br />
A. P. Toste, T. R. Pahl, R. B. Lucke, and R. B. Myers, "Analysis of Complex Mixtures in Nuclear<br />
Wastes," Health & Environmental Research on Complex Organic Mixtures. Proc. of 24th<br />
<strong>Hanford</strong> Life Sci. Symposium, Oct. 1985.<br />
U. S. General Accounting Office, "Nuclear Waste: Information on DOE's Interim Transuranic Waste<br />
Storage Facilities," U.S. GAO/RCED-90-166, June 1990.<br />
_ (J. SGeneral_ACCOUAttPg Off Cer °NUClear W3S?e: Transl ran:G Was 8 Steragc' i.iiitations at ROCky<br />
Flats Plant," U.S. GAO/RCED-90-109, February 1990.<br />
L. D. Wakeley, "Dependence of Expansion of a Salt-Saturated Concrete on Temperature and<br />
Mixing and Handling Procedures," U. S. Army Engineer Waterways Eeperiment Station,<br />
Vicksburg, MS, July 1987.<br />
M. B. Walsh, H. C. Eaton, M. E. Ti ttlebaum, F. K. Cartledge, and D.<br />
- - - - -<br />
Chalasani, "The Effect of Two<br />
-------- -Orga£IC-COmp9Un4i4-Jn-aPCrtlandCement-Bascd Sta`viii2atiun ivtatrix," Hazardous Waste &<br />
Hazardous Materials, v. 3, 1, 111-23, 1986.<br />
M. Weber, Y. Dedegil, and H. H. Homann, "Transport of Waste into Caverns by Vertical Flow of<br />
Concrete Suspensions," Scientific Basis for Radioactive Management - V, Elsevier Science<br />
Publishing, 873-77.<br />
E-31
DON'T SAY IT<br />
TO: Distribution<br />
cc E. P. Mertens<br />
R. J. Roberts<br />
J. L. Scott<br />
J. A. Swenson<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Write It ^ DATE: May 6, 1991<br />
N3-13<br />
N3-13<br />
N3-12<br />
G6-45<br />
FROM: L. A. Fort<br />
SUBJECT: E. W. McDANIEL LETTER REPORT "SURVEY OF GROUTING TECHNOLOGY IN<br />
SUPPORT OF WRAP'S SHRED GROUT MODULE"<br />
Please find attached a copy of Mr. E. W. McDaniel's initial letter reoort<br />
HaCeQ[ar3i '-^-' A 29-r-19 9 i^ on ^^, "sub'ect ^.. J of<br />
Suooort of WRAP's Shred Grout Module."<br />
"Surve y of Grouting Technolo Qy in<br />
This activity is to assess the international and DOE Complex waste<br />
immobilization technology development and defense waste management grout<br />
techniques applicable to the Waste Receiving and Processing (WRAP) Facility<br />
Shred-Grout operation. During the April 9, 1991 Exchange Meeting,<br />
Mr. E. W. McDaniel provided a preliminary draft letter report in compliance<br />
with the 5/24/91 milestone. The edited version of the earlier preliminary<br />
draft report is attached. The preliminary draft report was distributed as<br />
Attachment 2 to the April 9, 1991 Exchange Meeting report. Again, copies of<br />
the approximately 60 references identified within the draft report (over 15<br />
inches of documents) are available in my office for referral.<br />
As stated in the April 9, 1991 Exchange Meeting report, the draft report<br />
essentially formulates a"road map" to all the referenced documents. The<br />
evaluation does provide the current information on grout formulations, lessons<br />
learned at other DOE <strong>Site</strong>s, and any pertinent information relative to<br />
imnobilization technology. The final Cementation/Grout Technology Evaluation<br />
report is due by 8/30/91. After the final report has been delivered, I will<br />
edit and format the formal report so it can be issued internally.<br />
v<br />
E-32<br />
RECEIVED<br />
MAY 0 6 1991<br />
E.P. MERSELa
OAK R1DGE NATIONAL LABORATORY<br />
OPERATED EY MARTIN MARIETTA ENERGY SYSTEMS, INC.<br />
FOR THE U.S. DEPARTMENT OF ENERGY<br />
Mr. L. A. Fort<br />
Westinghouse <strong>Hanford</strong> Company<br />
P.O. Box 1970, R2-37<br />
Richland, Washington 99352<br />
Dear Les:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
POST OFFICE BOX 2008<br />
OAK RIDGE. TENNESSEE 37831<br />
April 29. 1991<br />
Milestone Letter Report: Cement Grout Technology Evaluation Report due May 1991<br />
Enclosed is a clean copy of the above milestone titled. "Survey of Grouting Technology in<br />
Support of WRAP'S Shred-Grout Module." I hope the fifty or so documents that I brou,ght out<br />
to you in support of the above milestone provide you with much useful information.<br />
EWM:jml<br />
cc: O. K Tallent<br />
E-33<br />
Best Regards.<br />
C.C1%-f r.c1.^^^^<br />
Earl W. McDaniel, ivlanager<br />
<strong>Hanford</strong> Grout Program<br />
Chemical Technology Division
WHC-SD-W100-TI-003 Rev. 0<br />
SURVEY OF GROUTING TECHNOLOGY<br />
IN SUPPORT OF<br />
WRAP'S SHRED GROUT MODULE<br />
A Letter Report Prepared<br />
for Westinghouse <strong>Hanford</strong> Company<br />
Richland, WA<br />
Earl W. NfcDaniel<br />
Chemical Technology Division<br />
Oak Ridge National Laboratory'<br />
Oak Ridge, Tennessee 37831-6044<br />
Managed by Nfartin Marietta Energy Systems. Inc., for the U.S. Department of Energy<br />
under contract DE-AC05-&3OR21400.<br />
E-34
WHC-SD-W100-TI-003 Rev. 0<br />
SURVEY OF GROUTING TECHNOLOGY IN SUPPORT OF<br />
WRAP'S SHRED GROUT MODULE<br />
E. W. iVlcDaniel<br />
ENBCUTNE SUMMARY<br />
This letter report covers a wide variety of grouting and other information that may be<br />
applicable to WRAP's Shred-Grout Task. Very little information is available on past, or present,<br />
operations of tiring shredded solids in a cement-based matrix.<br />
Information is provided about ORNL's Hydrofracture Process, the K-25 <strong>Site</strong> Sludge<br />
Fixation Facility, SRS Saltstone, <strong>Hanford</strong>'s Grout Treatment Facility, and PPEPP at INEL.<br />
Limited information is provided on grouting efforts at Rocky Flats, West Valley, and Mound<br />
Labs.<br />
Information is provided on cement-based fixation efforts in a number of European and<br />
Asian countries.<br />
A literature search is included that addressed low-level waste solidification technology.<br />
Also. included is a strategic planning document on low-level waste disposal and demonstration<br />
programs at Oak Ridge, Tennessee. This report also contains a three volume report about waste<br />
management processes in the nuclear industry.<br />
E-35
WHC-$D-W100-TI-003 Rev. 0<br />
1. INTRODUCTION<br />
This letter report covers a variety of cement-based grouting technologies, both national<br />
and international, that may be applicable to Westinghouse <strong>Hanford</strong> Company's Waste Receiving<br />
and Processing-(WR-AP) Shred=GTout eaort. iivxAP's mission is to process past and currently<br />
generated solid low-level (SLLW), mixed (MLW), and transuranic (TRU) waste at the <strong>Hanford</strong><br />
site, Richland. Washington. As this is an internal letter report, no background on WRAP is<br />
provided.<br />
The waste to be processed by WRAP has been generated in defense related efforts and<br />
are,-in zrtanycases,vnique-to this industry.- tiowever, the commercial sector of the nuclear<br />
industry has developed, both in the United States and abroad, grouting technology that, with<br />
- modification, is applicable to WRAP ( i.e., the solidification/stabilization of spent ion-exchange<br />
resins).<br />
Information is provided on USDOE grouting efforts at Oak Ridge, Tennessee<br />
/Hydrefracture at ORYL and the Sludge Fixation Faciliry at the K-25 <strong>Site</strong>), PREPP at INEL,<br />
Saltstone at SRS, West Valley, NY, and Soilcrete at INEL A brief description is given of the<br />
Rocky Flats plant inert carrier process. A manual laboratory process for making pellets of TRU<br />
waste is mentioned. It should be pointed out that little work has been reported on grouting<br />
shredded solids as is the mission of WRAP's shred-grout module.<br />
Most of the international information reported is from nuclear utilities. It is difficult to<br />
obtain information on defense related efforts in countries that have nuclear weapons programs.<br />
such as the United Kingdom (UK), France, and the USSR. West Germany (now just German,v)<br />
has a small shred-grout facility at NUKEM's Hanau plant. This operation was covered in<br />
R. ::'otojack> 1»^ trip report and will not be repeated here.<br />
It is noted that the majority of grouting information reported in the open literature<br />
addresses the use of cement-based materials (i.e.. grouts) to solidify liquids and slurries. Most<br />
E-36<br />
:A
WHC-SD-W100-TI-003 Rev. 0<br />
commercial processes are in drum or batch type mixing. Larger operations are: the ORNL<br />
hydrofracture facility for liquid waste (which is no longer operational), the K-25 Sludge Fixation<br />
Facility, the SRS Saltcrete plant, the <strong>Hanford</strong> Grout Treatment Facility, PREPP at INEL, and<br />
West Valley's grout facility.<br />
Information is also provided on the use of grouts in the UK, France, Germany, Korea,<br />
Japan, Finland, and Taiwan.<br />
2. NATIONAL<br />
2.1 OAK RIDGE NATIONAL LABORATORY HYDROFRACTURE FACILITY<br />
The concept of fluid waste disposal by hydraulic fracturing was borrowed from the<br />
=. - petroleum industry and developed at ORNL for the disposal of liquid low-level waste (LLLW).<br />
The original pilot plant was modified into an operational facility and was used from 1966 to 1979<br />
to routinely dispose of liquid waste.<br />
In the mid-1970s, a new facility was built that was capable of processing both liquids and<br />
sludges. This facility was completed in 1981 and operated until 1984. The facility is described in<br />
"Conceptual Design Report New Hydrofracture Facility." by H. 0. Weeren et al.<br />
(ORNLT(-4826, July 1975) and in "Design Criteria for New Hydrofracture Facility." Project<br />
No. 78-18-d X-OE-57. For mix design and other details please refer to reports listed in literature<br />
search.<br />
The facility is no longer used to dispose of waste at ORYL.<br />
2.2 SLUDGE FDCATION FACILITY AT THE K-25 SITE<br />
In the mid-1980s, a concrete batch plant surplused from the Clinch River Breeder Reactor<br />
(CRBR) Project was modified for solidifying a variety of pond sludges at the Oak Ridge K-25<br />
<strong>Site</strong>, previously known as the Oak Ridge Gaseous Diffusion Plant (ORGDP).<br />
E-37
WHC-SD-W100-TI-003 Rev. 0<br />
This plant experienced a variety of problems and presently is not operating. These<br />
problems are described in reports provided to Westinghouse <strong>Hanford</strong> Company in the first<br />
quarter of FY 1991 and will not be repeated here.<br />
Zi ORNL HLW CONCRETES FORMED UNDER ELEVATED TEiviPERATURE AND<br />
PRESSURE<br />
--ORZ'L-developeirtement=basedvraste hosts-thai were formed under eievated temperatures<br />
and pressures, (FUETAP). FUETAP concretes were shown to be effective hosts for hi;h-level<br />
radioactive defense waste and may even be considered for commercial HLW applications. The<br />
tailored formulas developed at ORNL were prepared from common portland cement, fly ashes,<br />
sand, and clays with wastes like calcines, frits, and sludges. These concretes are provided by an<br />
accelerated cure under mild autoclave conditions (85-200°C, 0.1-1.5 Mpa) for up to 24 h. The<br />
solids are subsequently dewatered at 250°C or 24 h to remove the unbound pore water.<br />
The resulting products were strong (unconfined compressive strengths of 40-60 MPa),<br />
leach resistant (plutonium leaches at a rate of 10 pg/cm= • d), and radiolytically stable, monolithic<br />
waste forms ( total gas G-values of 0.005 molecule/100 eV). This study concluded that these<br />
dewatered, autoclaved, cement-based waste hosts were suited for the disposal of HLW.<br />
Since 1981, no further development studies have been conducted at ORYL, and the DOE<br />
defense community has no plans to continue this work. However, a 1984 study by GA<br />
Technologies chose FUETAP as a-potential_process to stabilize Tiigh Temperature Gas Reactor<br />
(HTGR) fuel pellets. This study reaffirmed the cost-effectiveness of using cement-based waste<br />
forms and is the basis for a continuing development program. GA will use this ORNL process to<br />
perform a demonstration with unirradiated HTGR fuel pellets, and perhaps irradiated fuel from<br />
the Fort St. Vrain reactor.<br />
L_ZA
WHC-SD-W100-TI-003 Revo 0<br />
A report "Cement-Base Radioactive Hosts Formed Under Elevated Temperatures and<br />
Pressures (FUETAP Concretes) for Savannah River High-level Defense Waste," ORNL(I;M-8579,<br />
March 198.1, is included.<br />
2.4 IDAHO NATIONAL ENGINEERING LABORATORY PROCESS EXPERI,vfENTAL<br />
PILOT PLANT (PREPP)<br />
During the early 1980s, INEL embarked on an effort to develop a facility to treat past and<br />
future TRU solid waste at the INEL in order to certify it for disposal at the Waste Isolation Pilot<br />
Plant (WIPP).<br />
The conceot was to shred, incinerate, and solidifynoncombustibles and ash residues in a<br />
cement matrix.<br />
A report prepared by Ralph M. Parsons Co., "Study Report for RWivfC Process<br />
Experimental Pilot Plant Cementing," is included. This report contains the results of a study on<br />
grout mixtures, mixing equipment, and methods to be used in the Process Experimental Pilot<br />
Plant (new building) conceptual design. Even though this report was prepared in the 1930-51<br />
timeframe, it is still a valid document.<br />
This report assumed a new building. INEL chose to build the facility in an existing<br />
building. The facility never became operational and is being closed out during FY 1991.<br />
^4lso,-ittcluded:s "Conce-ptual-Zesig:t Criteria for TA.^!:=5/w? Process Experimental Pilot<br />
Plant (PREPP) by EG&G Idaho, Inc.<br />
25 SOILCRETE AT INEL<br />
In the mid 1980s, INEL considered solidifying contaminated soil in a cement-based matrix.<br />
bfi.x design was performed at the Oak Ridge National Laboratory. No funds were appropriated<br />
for plant design.<br />
E-39
WHC-SD-W100-TI-003 Rev. 0<br />
A.report entitled "Grout Testing and Characterization for Shallow-Land Burial Trenches at<br />
the Idaho National Engineering Laboratory," ORNL/I',^f-9881, October 1936, is included.<br />
2.6 SAVANNAH RIVER SITE (SRS)<br />
SRS chose a cement-based matrie to solidify contaminated salt for disposal. This matrix is<br />
called saltstone and is described in the following handout provided by SRS. For additional<br />
information, see literature search and proceedings of Spectrum '88 folder which is included.<br />
27 ROCKY FLATS PLANT (RFP)<br />
The Rocky Flats Plant, together with Quadrex, Inc., took a novel approach with some of<br />
their TRU streams that are difficult to process with standard processing equipment. Quadrex<br />
developed a processing technique that fluidizes both waste and cement-based components with an<br />
inert volatile halocarbon carrier, i.e., the "Inert Carrier Concrete process." This process is<br />
described in Dole and Row's "Development Programs in the United States of America for the<br />
Application of Cement-Based Grouts in Radioactive Waste Management " A copy of the report<br />
is included.<br />
?R PnN1^C RFiF.<br />
RFP chose to fix some of their pond sludge in a cement-based matrix. The waste form<br />
failed to meet necessa'ry criteria. No report is available.<br />
2.9 MOUND LABORATORY (MI.) WASTE P?=11.F117e TION PROCESS<br />
DEMONSTRATION<br />
TMound Laboratory (ML) developed a TRU waste immobilization method for the 3,IL<br />
cyclone-incinerator ash, sludges, salt residues, and contaminated soil. The Materials Research<br />
Laboratory (MRL) at the Pennsylvania State University had shown that strong, dense, and<br />
E-40
WHC-SD-W100-TI-003 Rev. 0<br />
impermeable cement-based waste forms could be formed with radioactive wastes at moderate<br />
temperatures and high pressures [150-250°C and 177-344 .1vIpa (25,000-50,000 psi)].<br />
Subsequently, ML developed and demonstrated a process that pressed 1 in.-diam pellets of waste<br />
and Portland cement at 177 Mpa (25,000 psi). This process was demonstrated with "hot" materials<br />
in 1982 and the leaching and radiolysis characteristics were studied and documented. Since 1982,<br />
no further development has been done, and there are no current applications of this technology.<br />
2.10 HANFORD, WASHINGTON<br />
In Fy 1983, waste management officials at the <strong>Hanford</strong> site chose cement-based grout as<br />
the method for futation and disposal of low-level radioactive waste. This facility, first called the<br />
transportable grout facility (TGF) now the Grout Treatment Facility (GTF) has many features in<br />
common with the SRS Saltstone Process and ORNL's Hydrofracture Facility. It was developed in<br />
conjunction with PNL and ORNL. Both institutions continue to contribute to the GTF effort at<br />
<strong>Hanford</strong>. This facility is best described in a paper entitled "The Grout Treatment Facility<br />
Processing Facilities for Low-Level Waste Immobilization and Disposal" by R. H. Guyman et al.<br />
A copy of this paper is included (In the folder labeled Proceedings of Spectrum '38). Several<br />
other reports that discuss formulation development for a variety of waste streams are included.<br />
2.11 WEST VALLEY DEMONSTRATION PROJECT<br />
The West Valley Demonstration Project selected cement as the solidification medium for<br />
the disposal of liquid and wet solid low-level radioactive (LLW) as well as for transuranic (TRU)<br />
waste. The system is designed around a high-shear cement mixing system. The process is<br />
described in the paper by J. C. Cwynar et al., "Retrofit of Low-Level Radwaste Solidilication<br />
System," which is included.<br />
E-41
3.1 UMTED KINGDOM<br />
WHC-SD-W100-TI-003 Rev. 0<br />
3. INTERNATIONAL<br />
British Nuclear Fuels. Ltd. (BNFL) is building encapsulation plants at Sellafield that will<br />
contain intermediate level waste (ILW) by encasing it first in cement then inside steel drums.<br />
The long-term solution adopted by BNFL is to store the encapsulated waste on site until the<br />
commissioning of permanent storage facilities. This facility was visited by Randy Roberts. WHC,<br />
in June 1989.<br />
A more complete description is given in "Report of Foreign Travel" by Earl McDaniel<br />
(ORNL/FIR-3114, November 1935) which is included).<br />
Also, included is "Flowsheet Finalization for Immobilization of SGHWR Wastes" by D. J<br />
Lee , t^E W-R-109,i, Mach 1983.<br />
3.?. .°.I:CE<br />
France uses a cement matrix to solidify a variety of waste. To my knowledge all processes<br />
are in drum mixing. Several papers are included in Spectrum '86 and '83 folders.<br />
Also, included is a brochure describing ANDRA, the French government agency for<br />
managing radioactive waste.<br />
33 GERLfANY<br />
German law requires that all radioactive waste be disposed of in a geologic repository.<br />
German waste is classified as heat producing, which will be disposed of in a salt mine, and non-<br />
heat producing, which wiii be disposed of in an iron mine. All radioactive waste in Germany is<br />
the result of nuclear utilities and institutional use. Germany has abandoned its plans for a fuel<br />
E-42<br />
-..^
WHC-SD-W100-TI-003 Rev. 0<br />
reprocessing facility. Randy Roberts visited the KFK Facility at Karlshrue in June 1959. Please<br />
see his Foreign Trip Report for details.<br />
A shred-grout facility for Alpha waste exists at NUKEM's Hanau plant. I am unable o<br />
find a paper describing this facility.<br />
Several papers from Germany are included in the Spectrum '86 and '98 folders.<br />
3.4 JAPAN<br />
Japan has a very active nuclear energy program and, therefore, a very aggressive waste<br />
management effort. This program is best described in two enclosed documents:<br />
folders.<br />
1. Low-Level Radwaste Disposal Concepts in Japan<br />
2. Outline of Radioactive Waste IManagement Center<br />
Several papers related to Japan's waste disposal program are included in the Spectrum<br />
3S SOUTH KOREA<br />
Even though South Korea has a very aggressive nuclear power program, little has been<br />
accomplished in efficient waste management. Most of the waste solidification systems are either<br />
bitumen or cement and have been bought from U.S. companies. A brochure "Nuclear Industry in<br />
the Republic of Korea" is included.<br />
3.6 REPUBLIC OF CHINA (TAIWAN)<br />
The Republic of China has a very aggressive nuclear energyv development program. Their<br />
waste management practices are some of the safest in the world. A paper describing the National<br />
LAN-YU storage sites is included.<br />
E-43
3.7 FINLAND<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Finland has two nuclear power plants, one of western design and one of USSR design. In<br />
Finland, all radioactive waste will be disposed of in an on-site repository. The Finnish program is<br />
described in the enclosed document "Radioactive Waste Management in Finland" (Status Report,<br />
August 1988). Also, included is a paper "Half -Scale Cementation of Spent Ion-Erchange Resins<br />
at theLouiisa Planc;" hy a,_ O. L^patti, and "Disposal of Low and Intermediate Level Waste in<br />
Finland" by Esko Ruakola.<br />
4.0 OTHER INFORMATION<br />
included:<br />
A three volume report on Low-Level Waste from Commercial Nuclear Reactors is<br />
Part 1. Open Literature Abstracts for Low-Level Waste, ORNLTM-9846/V3-P1<br />
Part 2. Bibliographic Abstracts of Significant Source References,<br />
ORNLlItif-98446N3-P2<br />
Part 3. Treatment, Storage, Disposal and Transportation Technologies and Constraints,<br />
OR1NLII',`V[-9846/V2<br />
Also, included is A. H. Kibbey and H. W. Godbee's report entitled "A State-of-the-Art<br />
Report on Low-Level Waste Treatment," ORYLIIM-7427, September 1980.<br />
5.0 LPIERATURE REVIEW<br />
A draft report by A. J. Mattus, "A Literature Review of Potential Candidate Fixation<br />
Mediums for the Immobilization of Low-Level Waste," October 1985, is included.<br />
A literature search by Earl W. McDaniel is included which lists 55 titles. Many of the<br />
reports and papers are being transferred to WHC as part of this milestone.<br />
E-44
WHC-SD-W100-TI-003 Rev. 0<br />
STR?.THGIC PLANNING DOCiJMENT<br />
This document summarizes the process which will lead to an integrated strategy and<br />
associated implementation plan for LLW management on the ORR. It is not intended to be a<br />
final summary of actions needed to address the management of LLW on the ORR.<br />
E-45
WHC-SD-W100-TI-003 Rev. 0<br />
This page intentionally left blank.<br />
E-46
Contained under four reports:<br />
WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX F<br />
THERMOSETTING POLYMER TEST RESULTS<br />
WHC Trip Report - Test Status (1)<br />
Thermosetting Polymer Test Report<br />
Thermosetting Polymer Test Report<br />
Thermosetting Polymer Test Report<br />
F-1<br />
(2) - Stock Equipment Company<br />
(3) - Stock Equipment Company<br />
(4) - Stock Equipment Company
WHC-SD-W100-TI-003 Revo 0<br />
This page intentionally left blank.<br />
F-2
^.yo<br />
F-SD-W"00-7-003 Rev. 0<br />
THERMOSET`IING PAI.YNER TEST' RESULTS<br />
DON'T SAY IT --- Write It! DATE: September 21, 1992<br />
TO: C. A. Petersen FROM: Dewey A. Burbank, Jr.<br />
J. A. Swenson<br />
Telephone: 2 -0 855<br />
cc: C.<br />
D.<br />
n^.<br />
J.<br />
W.<br />
K.<br />
J.<br />
T.<br />
J.<br />
L.<br />
D^.<br />
K.<br />
G.<br />
R.<br />
M.<br />
L.<br />
L.<br />
Benar<br />
Lamberd<br />
Lucas<br />
Pauly<br />
Riddelle<br />
Swita<br />
Weingardt<br />
Westcott<br />
Yount<br />
SUBJECT: Trip Report - Stock Equipment Company, Chagrin Falls, OH, 9/16/92<br />
Attendees: Dewey Burbank, WHC<br />
Rich Henkel, UE&C<br />
Bill Phillips, Stock<br />
Fred Podmore, Stock<br />
The attendees met for breakfast and drove to the Stock Equipment Company<br />
facility in the Bainbridge district near Chagrin Falls. A brief meeting was<br />
held, where Stock reviewed the progress to date. Successful formulations have<br />
been developed for waste surrogates type 1(LETF salts, ammonium sulfate) and<br />
type 3 (183H basin sludge, high nitrate), but problems have been encountered<br />
with types 2 (Basin sludge, nitrate/sulfate) and 4 (basin crystalline solids,<br />
high sulfate). The suspected reason is the presence of ionic copper in the<br />
surrogates. It was explained that transition metal ions are an inhibitor to<br />
the polymerization reaction due to thier ability to scavenge the free radicals<br />
that propogate the solidification reaction. Presumably, the copper in type 3<br />
surrogate is in the non-ionic cupric oxide form.<br />
Following a brief tour of the manufacturing facilities, we went to the<br />
laboratoryto prepare the test specimens from types 1 and 3 surrogate, as well<br />
as a set of control specimens of neat polymer (zero waste loading). A total<br />
of 54 specimens were poured for each immobilization batch. The test specimen<br />
molds were made of polypropylene pipe sections, approximately 2 inches long by<br />
1 inch inside diameter, glued to a plastic base.<br />
Batch #1 was the control batch. The formulation for this batch was:<br />
Binder, 5000 grams<br />
Catalyst, 125 grams<br />
Promoter, 5 grams<br />
The batch was mixed in a plastic bucket using a Lightning lab mixer. A<br />
specimen was transferred to a paper cup for measurement of the exotherm, while<br />
the remainder was used to pour the test specimens. The batch began to gel<br />
after Qnly abos(t-20_specimens hadbeen poured. It was decided that although<br />
54-3000-101 (9/59) (EF) CEF014<br />
DSI<br />
F-3
WHC-SD-W100-TI-003 Rev. 0<br />
the statement of work requires all specimens to be prepared from a single<br />
batch, this was not critical for the control specimens and preparation of the<br />
rest of the control samples could be completed later.<br />
Batch #2 was the Type 1 surrogate LETF salt. The formula for this batch was:<br />
Binder, 2000 grams<br />
Catalyst, 50 grams<br />
Promoter, 2 grams<br />
Surrogate, 4000 grams<br />
Spiking salts:<br />
Cobalt Chloride, 61.08 grams<br />
Strontium Chloride, 46.04 grams<br />
Cesium Chloride, 19.17 grams<br />
The promoter and binder were mixed, then the spiking salts were added. The<br />
salts did not appear to get mixed very well, due to the small size of the<br />
mixer and large batch container size. the surrogate was then added in<br />
portions, until roughly halfway through, when the mixer stalled several times.<br />
After this point, mixing was only possible in the top few inches of the batch,<br />
since the mixer wo.:ldstall if it was submerged more than about 2 to 3 inches.<br />
After about 20 minutes, the entire quantity of surrogate had been added, and<br />
the catalyst was added in two portions. The mix was then scooped into the<br />
specimen molds. A portion of the mix was placed in a paper cup for<br />
measurement of the exotherm. ,<br />
Batch #3 was Type 3 surrogate basin sludge. The formula for this batch was<br />
the -same--as-fcr Type-1 sttrrogat-e--sb ive. The mixing procedure was the same,<br />
with the exception that the spiking salts were added directly into the<br />
surrogate and mixed with a spatula, due to the semi-liquid consistency of the-<br />
surrogate. No mixing problems were encountered, and the mixture was poured<br />
into the specimen molds and a paper cup for exotherm measurement.<br />
After breaking for lunch, we met in the conference room to discuss the details<br />
of the formulation development work for types 2 and 4 surrogate. Various<br />
_ techniyueshad been attempted,_including increasing the amount of promoter<br />
added, adding ammonium solutions to complex the copper, mixing types I and 2,<br />
changing the waste loading, roasting the surrogate, and changing order of<br />
addition of the polymer reagents and the waste. None of these techniques were<br />
successful. Detailed laboratory notes are attached, and the first progress<br />
report from Stock will include further discussion of this work.<br />
After reviewing the results of the formulation work, we concluded that two<br />
additional attempts should be tried. The first test involves adjusting the pH<br />
of the surrogate type 2 to around 10. This should result in a surrogate that<br />
more closely resembles the pH of the actual waste. In the second test, a<br />
mixture of sodium fluoride and sodium sulfate will be processed to examine the<br />
possibility that fluoride may be interfering with the polymerization reaction.<br />
Verbal authorization to proceed with these trials was given by WHC.<br />
--- -- --Follcwing the-cisctassion of the- polyyner-fttrmulaticn dYvelopment work, we were<br />
presented with information on Stock's equipment development work for in-drum<br />
mixing equipment, using preloaded waste and double planetary mixer equipment.<br />
54-3000-101 (9/59) (EF) GEF014<br />
DS1<br />
F-4<br />
>._r<br />
;?7
WHC-SD-W100-TI-003 Rev. 0<br />
The technology appears to be a very close match with the current conceptual<br />
design for WRAP 2A and this development work should be followed closely.<br />
CONCLUSIONS<br />
The formulation development work that Stock is performing is proceeding more<br />
slowly than expected for the type 2 and type 4 surrogates, due to apparent<br />
chemical interactions between the surrogate materials and the polymer system<br />
chemistry. Several different techniques have been attempted to address the<br />
problem, with no success. The interaction inhibits the polymerization<br />
reaction, resulting in a waste form with compressive strength below the<br />
acceptance criterion of 60 psi. Limited additional development work has been<br />
authorized to investigate the effects of surrogate pH and fluoride content on<br />
the final waste form. Successful formulations have been developed for type 1<br />
and type 3 surrogates. Test specimens have been prepared and testing is<br />
proceeding as planned.<br />
We observed three incidents that would indicate improvements could be made in<br />
the quality of the work being performed. First, the development work was<br />
performed under an erroneous identification of the waste types; the Stock<br />
technician had mistakenly_transposed the identities of types 3 and 4<br />
surrogates. Secondly, the unexpectedly quick gelling of the control batch<br />
indicates that not enough work-had been done aithth'rs-firrmura to reaHze-that<br />
there would not be enough time to pour all of the specimens. Thirdly, the<br />
laboratory mixer used for mixing of Batch #2 ( waste type 1) appeared to be<br />
inadequate to assure that a homogeneous mixture was obtained in the batch size<br />
used for specimen preparation.<br />
The manufacturing facilities are quite modern, with state-of-the-art digitally<br />
controlled machine tools and fabrication capabilities. The machine design and<br />
fabrication capabilities are resources that should be considered for possible<br />
use in fabrication of WRAP facilities specialty mechanical equipment.<br />
54-3000-101 (9/59) (EF) GEF014 F-5<br />
ual
.=^...<br />
^^^5<br />
WHC-SD-WI00-TI-003 Rev. 0<br />
CORRESPONDENCE DISTRIBUTION COVERSHEET<br />
Author Addressee Correspowdence No.<br />
CZELLATH RA/STOCK BURDANK DA/WHC 9205858<br />
sub;ect: STOCK POLYMER IMMOBILIZATION TECH. WASTE FORM QUALIFICATION TESTING PURCHASE ORDER<br />
MANAGEMENT PROJECT ENGINEERING WRAP PROJECT CONTROL<br />
JA Swenson G6-46 X TA Carlson G6-46 KP Brown G6-47<br />
DE Ball G6-46 AW Hinkle G6-46 SE Bussman G6-47 -<br />
SR Briggs G6-47 FH Lee G6-46 C Malstrom G6-47 -<br />
JE Filip G6-47 ^- JB Payne G6-46 - SW McKinley G6-47 _-<br />
no 1Uca-s---- - G6-46- - -X -- jG Starkey- G6-46 ------- u"C Riee G6-47<br />
CA P_etersen --H1-60 -X WR Swita -66-45 ^- BL Trumpour G6-47 -<br />
TL Yount H1-60 _X RR Wyer G6-46 _X_ ^^ -<br />
WRAP TECHNOLOGY SW SYSTEMS ENGINEERING SW SYSTEMS ENGINEERING<br />
CJ Benar H1-60 X<br />
DA Burbank H1-60 -X _ _<br />
oF Campbeil Hi-60<br />
JD Keck G6-46<br />
CE McDonald H1-60<br />
JL Nelson H1-60 -<br />
KE Parker H1-60 _-<br />
RM Ybarra H1-60<br />
SW INTEGRATION SW PROJECTS<br />
GF Booth G6-46 DR Broz G6-46 _<br />
MD LeClair H1-60 ML DeWitt G6-46<br />
OW Mertz H1-60 EG Erpenbeck G6-46 -<br />
CR Nash HI-60 TM Greager G6-46 -<br />
TR Pauly G6-46 RL Louie G6-46 -<br />
JL Stroup G6-46 KE Smith G6-46 -<br />
KM Weingardt H1-60 ^- HE Wellsfry G6-46 _<br />
RL Anderson G6-45 RJ Roberts N3-13<br />
Al Ball H1-60 + JG Riddelle H1-79 -X-<br />
BJ Gire G6-46 _ BA Mayancsik H1-79 --<br />
SA Niebel G6-46 MM McCarthy N3-13<br />
- JB Myers G6-46<br />
COMMENTS TO LEAD ENGINEER BY:<br />
SPECIAL INSTRUCTIONS:<br />
EG Berglin G6-46 VP Ocampo G6-46<br />
KJ Hull G6-46 - DT Ruff G6-46 -<br />
RM Horgus H1-60 RA Sexton H1-60 ^<br />
SL Kooiker G6-46 JR Weber G6-46 -<br />
DL Lamberd H1-60 ^ JR Weidert G6-46 -<br />
ML Lee G6-46 - RH Winkleman G6-46 i<br />
KJ Leist G6-46 ^ A Zabarauskas G6-46 -<br />
NJ Monroe H1-60 ^ -<br />
QA RECORD YES NO<br />
r e<br />
r-o<br />
SUPPORT<br />
Corr Control<br />
WRAP DMC<br />
JR McGee<br />
E Pennala<br />
DR Porten<br />
JM Seimer<br />
WW Olson<br />
X<br />
G6-51 -X<br />
G6-47<br />
E2-30 -<br />
G6-47 -<br />
G6-47 -<br />
N1-83 ^<br />
DA Smith G6-16 X<br />
^
loomi^^lC&<br />
111111111111F .^^.\<br />
Westinghouse <strong>Hanford</strong> Company<br />
2355 Stevens Drive<br />
Richland, Washington 99352<br />
Attention: Mr. Dewey Burbank, H1-60<br />
WHC-SD-W100-TI-003 Rev* 0 9205858<br />
Subject: STOCK Polymer Immobilization Tech.<br />
Waste Form Qualification Testing<br />
Purchase Order No. MMW-SVV-277587<br />
Stock Reference No. 6996<br />
Gentlemen:<br />
October 15, 1992<br />
Enclosed please find a copy of our Progress Report No. 2 for the subject project.<br />
This report represents progress through September, 1992.<br />
Should additional information be required, please advise.<br />
RAC/kh<br />
Enclosure<br />
c: Westinghouse <strong>Hanford</strong> - Attn: G.M. Wemhoff, Buyer<br />
S.O.6996<br />
T. Litchney<br />
Tickler 11/1/92 w/report<br />
Very truly yours,<br />
w/<br />
Russell A. Czellath<br />
Manager-Contracts<br />
R!7:;=i`JED<br />
VJR6tP DMC<br />
OCT 211942<br />
Stock Equipment Company • 16490 Chillicothe Road • Chagrin Falls, Ohio 44022-4398, U.SA •( 216) 543-6000 • Telex 196071<br />
A Unit-9f-General Signal F-7 Telefax (216) 543-6678
Stock Equipment Company<br />
WHC-SD-W100-TI-003 Rev. 0<br />
WESTINGHOUSE HANFORD COMPANY<br />
STnru Fni rrPT,rRTrr rn<br />
POLYMER IMMOBILLIZATION TECH.<br />
WASTE FORM QUALIFICATION TESTING<br />
MONTHLY PROGRESS REPORT<br />
NO. 2<br />
THROUGH SEPTEMBER, 1992<br />
Stock Equipment Company<br />
Westinghouse <strong>Hanford</strong> Purchase Order No. MMW-SVV-277587<br />
Stock Order No. 6996<br />
F-8<br />
;;:,:•
^u9^c<br />
?fi. ...^<br />
.._-,<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TABLE OF CONTENTS<br />
Page<br />
i0 SUMMARY 1& 2<br />
2.0 SCHEDULE 3<br />
BAR CHART SCHEDULE 4<br />
F-9
Stock Equipment Company<br />
1.0<br />
WHC-SD-W100-TI-003 Rev. 0<br />
PROGRESS REPORT<br />
SEPTEMBER 1992 .<br />
S^;Ry ^/ W^^o Wa 5{ ° -7<br />
Week Number 1<br />
Primary effort concentrated on optimizing waste loading of the<br />
four different surrogate waste forms. Type 1 LETF Salts<br />
successfully solidified at a loading ratio of 2:1 waste to<br />
polymer. Initial formulations for Type 2 (Basin #1, #2 Sludge)<br />
and T;Ye 4(Basin Crystal Solids) proved inconclusive.<br />
Successful solidification of Type 3 (Basins #3, #4 Sludge) at a<br />
loading ratio of 2:1 waste to polymer was achieved.<br />
-BeYow is a synopsis of the experiments to achieve polymer/Type 2<br />
waste (Basin #1, #2 Sludge) solidification:<br />
1. Reduced waste loading to 0.5:1 waste to polymer ratio.<br />
2. Increased the amount of promotor to forty times the required<br />
amount.<br />
... 3. Increased the amount of catalyst to twice the required<br />
amount, along with an increase in promotor (20 times).<br />
4. Changing the sequence of addition ( the standard way would be -<br />
polymer and promotor mixed together first, add waste and mix, ".^<br />
sd3--the-catall;st- and -firrish -mixing) - th®-promstcsr- and polymer<br />
were mixedfirst then catalyst was added and "mixed in" the<br />
waste.<br />
5. Attempted mixing Type 1 and Type 2 waste together ( equal<br />
weight ratios 1:1).<br />
6. Experimented with ammonia water as a corrective additive to<br />
induce this type of waste to solidify.<br />
These experiments produced unacceptable results. The samples<br />
gelled but did not get "rock hard".<br />
All leach containers and bottles were acid rinsed in preparation<br />
for the leachability and immersion testing. The core samples<br />
were prepared. Fifty liter carboys of demineralized water and<br />
synthetic sea water were prepared.<br />
Wednesdav. Sentember 16. 1992<br />
Mr. Dewey Burbank, Westinghouse <strong>Hanford</strong>, and Mr. Richard Henkle,<br />
United Engineers & Constructors, visited Stock to observe the<br />
preparation of samples to be tested. In the morning they<br />
witnessed the making of the polymer control; Type 1 LETF Salts<br />
and Type- 3--Basins J+3,#4--Sludge.--- Iviv the--afternoorr we--di.-scussed<br />
the complications with Type 2 and Type 3 surrogate waste streams<br />
F-10<br />
;^x^
Stock Equipment Company<br />
WHC-SD-WI00-TI-003 Rev. 0<br />
and the following two-fold course of action for further testing<br />
of these waste streams.<br />
1> Adjust the rH of Type 2 wastestream to 10-.5 and *_hen proceed<br />
with solidification. Actual pH of Type 2 waste was 3.5.<br />
Mr. Burbank indicated that the pH should be between 10 and<br />
11. He also indicated that the color of the waste stream<br />
should be black and appear like surrogate waste stream<br />
Type 3.<br />
2. Initially, copper ions were thought to be interfering with<br />
the polymerization of the polymer since we were able to<br />
solidify Type 3 waste (concentration of copper equal 112,000<br />
ppm or 11.2%) and not able to solidify Type 4 waste which has<br />
less copper. The next consideration was that there is an<br />
interference from fluoride ion. We discussed trying a<br />
hydrat_e_d sa__lt__(sodium -sulfa_te 10H.,0) and adding 7% fluoride<br />
ion to it. Once the fluoride ion^is evenly distributed in<br />
the sodium sulfate, try to solidify in polymer resin. This<br />
test is designed to indicate if the fluoride will inhibit<br />
polymerization. If it does, we can concentrate on isolating<br />
the fluoride or try to prevent it from interfering in the<br />
polymerization.<br />
= Thursday. September 17. 1992<br />
_Control samples for the leachability/immersion testing were made.<br />
These samples will not contain any spiking salts.<br />
- Saturday, Setitember 19. 1992<br />
Samples were prepared for the leachability/immersion part of the<br />
= testing. Weights, heights and diameters were recorded and the<br />
surface area of the samples were calculated so that the<br />
appropriate amount of leachant solution could be poured for the<br />
various time points. Leachant was poured for the following time<br />
points: 30 second rinse, 2 hours, 7 hours and 24 hours.<br />
Mondav. September 21. 1992<br />
The leachability/immersion test was started at approximately 8:30<br />
AM. Time points have been collected for the 30 second rinse, 2<br />
hours, 7 hours, 24 hours, 2 days, 3 days, 4 days and 5 days. The<br />
s^pec ime.^.s are currently in the 18 day segment of the test.<br />
Samples were also taken for compressive strength testing.<br />
Week of September 29, 1992<br />
Analysis of the leach samples began.<br />
r-e--<br />
r 11<br />
r-aa
SIVIR EyUi'y^Tiein P^.vniyany ----<br />
LV<br />
Jl..lILDVLL<br />
Activitv<br />
- Prepare Work Plan<br />
- Submit Work Plan<br />
- Approve Plan<br />
- Develop Formulations<br />
- Prepare Specimens<br />
- Lab - Analysis<br />
- Final Report<br />
WHC-SD-W100-TI-003 Rev. 0<br />
+3-- -<br />
F-12<br />
Scheduled Actual<br />
Date Date<br />
08/01/92 08/01/92<br />
08/01/92 08/01/92<br />
08/10/92 08/10/92<br />
08/21/92 08/21/42<br />
09/01/92 09/16/92<br />
12/10/92<br />
12/23/92<br />
. ,,
^ i<br />
w<br />
STOCK EOUIPMENT COMPANY<br />
14-OCt-92<br />
PROJECYSCHEDULE<br />
WESTINGHOUSE MONTHLY PROGRESS REPORT<br />
HANFORD COMPANY<br />
P.O. MMW-SW-277587 PREPARED BY: RUSS A. CZELLATH<br />
STOCK ORDER: 6996<br />
1992<br />
TASK J U L I A U G I S E P I O C T I N O V I D E C<br />
PREPARE WORK PLAN<br />
SUBMIT WORK PLAN<br />
APPROVE WORK PLAN<br />
DEVELOP FORMULATIONS ^..^^<br />
PREPARE SPECIMENS<br />
LABORATORY ANALYSIS : n<br />
FINAL REPORT I I I I<br />
i s<br />
of<br />
I E=<br />
r_<br />
i<br />
r<br />
us<br />
i^<br />
`c)<br />
c)<br />
ui<br />
xi<br />
(D <<br />
c>
samipleN WEIGHT HEIGHT DIAMETER DENSITY AVG. LOAD P'SI ' AVG.<br />
gnama cm cm grama/cc LBS Itve iiay<br />
I compressive<br />
sMrenight<br />
L1-1 51.4 4.54 3.812 1.104897 17160 108434.37<br />
11-2 58.8 5.116 3.612 1.12166 17160 10804.37<br />
L1-3<br />
1 51 4.502 3.609 1.107391 17^20 10797.11<br />
11-4 55.3 4.869 3.611 1.109D23 17360 110936.35<br />
11-5 51.7 4.483 3.611 1.1261 17360 110908.35<br />
11-6 58.9 5.024 3.609 1.146048 1.12 17400 I10973.7 10,926<br />
11-7 56.3 4.923 3.611 1.116693 17480 110111.94<br />
11-8 54.9 4.798 3.611 1.117759 17480 1110111.94<br />
11-9 56.3 4.991 3.607 1.103923 17520 111061.64<br />
1-1-10 56.7 4.968 3.609 1.115675 17320 10923.25<br />
L3-1 73.9 5.112 3.618 1.406134 3520 2208.936<br />
^ 1-3-2 72.5 5.23 3.616 1.349863 3600 22611 . 639<br />
p 1-3-3 71.9 5.1 3.614 1.374335 3600 2314.457<br />
1-3-4 71.1 5.067 3.678 1.320704 4320 2623.239<br />
L3-5 73.3 5.245 3.663 1.326156 42f10 2595.79<br />
1-3-6 71.7 5.108 3.668 1.328372 1.33 4280 2613.14 2472<br />
L3-7 67.1 5.024 3.68 1.255704 3920 2377.76<br />
1-3-8 72.9 5.212 3.653 1.334547 41150 2560.778<br />
1-3-9 71.2 5.065 3.683 1.319493 4400 2664.568<br />
L3-10 72.3 5.194 3.665 1.319467 4080 2495.11<br />
1-7-1 77.2 5.001 3.614 1.504854 2480 15S9.743<br />
L7-2 72.8 4.829 3.615 1.468817 2410 1533.737<br />
1.7-3 76.4 4.837 3.617 1.5372 2490 1506.925<br />
1-7-4 75.9 4.935 3.611 1.501792 1600 1007.956<br />
173 73.1 4.976 3.632 1.417932 244,0 1519.413<br />
L7-6 72.6 4.724 3.627 1.487448 1.48 22fj0 1373.742 1411<br />
1.7-7 77.4 5.017 3.632 1.489071 2240 1394.871<br />
L7-8 75.8 5.078 3.627 1.444746 2360 1473.65<br />
1-7-9 76 5.017 3.614 1.476738 1800 1132.071<br />
1-7-10 72.6 4.956 3.617 1.425668 2560 1607.387<br />
E<br />
N<br />
L<br />
^O<br />
--1<br />
..<br />
O<br />
O<br />
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CD <<br />
O
\. . 1 .: lh,lf^<br />
LEACH / IMMERSIONI SAMPLES<br />
SAMPLE INEIGHT HEIGHT DIAMETER suAacp area volume density AVG<br />
grams cm cm cm2 ml's gms/co<br />
L1A1 54.5 4.941 3.607 78.4288 764.268 1.07944<br />
LIA2 54.9 4.932 3.609 76.37^85 763.785 1.08814<br />
L1A3 54.4 4.837 3.609 75.3014 753.014 1.09941 1.1<br />
1181 58 4.946 3.61 76.5641 765.641 11.10619<br />
1182 55.2 4.833 3.611 75.3091 753.091 1.11526<br />
1183 53.4 4.722 3.611 74.04i99 740.499 11.10426<br />
12A1 71.5 5.002 3.615 77.3345 773.345 1.39269<br />
L2A2 76.2 5.222 3.617 79.8886 798.886 1.42014<br />
L2A3 73.4 5.113 3.617 78.65 786.5 1.39712 1.4<br />
1281 70.7 4.941 3.616 76.6668 766.686 1.39334<br />
L2B2 71.1 4.942 3.616 78.68 766.8 1.40094<br />
1-2133 75.4 5.218 3.617 79.8431 798.431 1.40631<br />
c^n 13A1 76.1 5.116 3.615 78.6292 786.292 1.44926<br />
13A2 71.5 5.002 3.616 77.3616 773.618 1.39192<br />
L3A3 78 5.11 3.72 81.4505 814.565 1.36841 1.41<br />
1381 71.1 4.948 3.616 78.74132 767.482 1.39924<br />
L3B2 75.6 5.117 3.614 78.6131 786.131 1.44026<br />
L3B3 71.3 5.002 3.618 77.4157 774.157 1.3865<br />
L6AI 74.8 4.721 3.616 74.1694 741.694 1.54284<br />
L6A2 73.1 4.508 3.614 71.6987 716.987 1.58076<br />
L6A3 72.5 4.507 3.615 71.7129 717.129 1.56727<br />
1681 70.5 4.443 3.618 71.0114 710.114 1.54513 1.56<br />
L6B2 70.8 4.443 3.618 71.0114 710.114 1.55171<br />
L683 75.7 4.724 3.616 74.2035 742.035 1.56041<br />
L7AI 76.3 4.94 3.616 76.6573 766.573 1.50401<br />
17A2 83.7 5.008 3.616 77.4298 774.298 1.62748<br />
L7A3 75.5 4.94 3.616 76.6573 766.573 1.48824<br />
L7B1 78.4 4.945 3.618 76.7679 767.679 1.54214 1.52<br />
L7B2 76.4 4.941 3.614 76.6149 766.149 t.50734<br />
L7B3 77 5.11 3.614 78.5337 785.337 1.46894<br />
^<br />
C<br />
N<br />
E<br />
.. 00<br />
1<br />
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0<br />
CO<br />
w<br />
CD <<br />
0
$-%<br />
^_.. 4<br />
Sample ID L7A1<br />
Elemem COBALT<br />
Matriz DI water<br />
(dt)n<br />
S<br />
t-sum(dt)<br />
S<br />
WHC-SD-W100-TI-003 Rev. 0<br />
S.A V Ao<br />
78.7 50.7 0.191a<br />
Cone.<br />
PPM<br />
an 9 an/Ao SUM<br />
an/Ao<br />
DATE OCT 12 1992<br />
Di L<br />
7200 7200 0.001 0.0000 0.0000 0.0000 7.81 E-16 15.1184<br />
2 18000 25200 0.5 0.0004 0.0020 0.0020 2.51 E-10 9.6003<br />
3 81200 86400 1 0.0008 0.0040 0.0060 3E-10 9.5230<br />
4 88400 172800 0.5 0.0004 0.0020 0.0080 9.26E-11 10.0341<br />
5 86400 259200 0.4 0.0003 0.0016 0.0098 1 E-10 9.9978<br />
6 86400 345600 0.8 0.0006 0.0032 0.0128 5.66E-10 9.2475<br />
86400 432000 1.2 0.0009 0. 0.0176 164E-00 8.7853<br />
1382400 1814400 0.0000 0.0000 0.0176 0 ERR<br />
2160000 3974400 0.0000 0.0176 0 ERR<br />
510<br />
3888000 7862400 0.0000 0.0000 0.0176 0 ERR<br />
Sample ID L7A2<br />
F_leman} O_f_]R_AI T<br />
Matric DI WATER<br />
S.A. V Ao<br />
T l e1 a ^^<br />
DATE OCT 12 1992<br />
(dnn tssum(dt) Cone. an 9 an/AO SUM<br />
Di L<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 0.2 0.0002 0.0008 0.0008 3.OSE-11 10.5163<br />
2 18000 25200 0.6 0.0005 0.0024 0.0032 3.61 E-10 9.4419<br />
3 61200 86400 1.3 0.0010 0.0052 0.0084 5.07E-10 9.2951<br />
4 86400 172800 0.6 0.0005 0.0024 0.0108 1.33E-10 9.8757<br />
5 86400 259200 0.5 0.0004 0.0020 0.0128 1.57E-10 9.8040<br />
8 86400 345800 0.9 0.0007 0.0036 0.0164 7.16E-10 9.1452<br />
7 86400 432000 1.3 0.0010 0.0052 0.0216 1.92E^9 8.7157<br />
6 1382400 1814400 0.0000 0.0000 0.0216 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0216 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0216 0 ERR<br />
Sample ID L7A3<br />
- r(emar(. COBALT<br />
Matriz DI WATER<br />
S.A. V Ao<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Conc. an 9 an/Ao SUM<br />
IN L<br />
S<br />
S PPM<br />
en/Ao<br />
1 7200 7200 0.2 0.0002 0.0008 0.0008 3.05E-11 10.5163<br />
2 18000 25200 0.4 0.0003 0.0016 0.0024 1.61 E-10 9.7941<br />
3 61200 88400 1.4 0.0011 0.0056 0.0080 5.88E-10 9.2307<br />
4 86400 172800 0.5 0.0004 0.0020 0.0100 9.25E-11 10.0341<br />
5 86400 259200 0.3 0.0002 0.0012 0.0112 5.65E-11 10.2477<br />
8 86400 345600 1.1 0.0008 0.0044 0.0156 1.07E-09 8.9709<br />
- 7 ------ - 864'0 4320ini 1.1 0.0008 O.OOaa 0.0200 1.38E-09 8.8808<br />
B 1382400 1814400 0.0000 0.0000 0.0200 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0200 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0200 0 ERR<br />
f-16
^;-<br />
v.4'?<br />
Sampls ID L781<br />
Elsment COBALT<br />
Matri: SEA WATER<br />
WHC-SD-W100-TI-003 Rev. 0<br />
S.A. V Ao<br />
76.8 50.8 0.1976<br />
DATI: 6CT 12 1992<br />
(dt)n t-sum(dt) Cone. an Q aMAO SUM<br />
Di L<br />
S<br />
S PPM<br />
an/Ao<br />
7200 7200 0.1 0.0001 0.0004 0.0004 7.61 E•12 11.1184<br />
2 18000 25200 0.3 0.0002 0.0012 0.0016 9.04E-11 10.0440<br />
3 61200 88400 1.3 0.0010 0.0052 0.0068 5.07E-10 9.2951<br />
4 86400 172800 0.3 0.0002 0.0012 0.0080 3.33E-11 10.4778<br />
5 86400 250200 0.2 0.0002 0.0006 0.0088 2.51 E-11 10.5999<br />
8 86400 345600 1.1 0.0008 0.0044 0.0132 1.07E-09 8.9700<br />
7_ 3ot00 -43200F - _4:4 -C.0'v1i- 058 'v.OtoB 2.23'cvo 8.wi4<br />
8 1382400 1814400 0.0000 0.0000 0.0188 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0188 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0188 0 ERR<br />
Sampls ID L7B2<br />
ElNmsn! COBALT<br />
Matr& SEA WATER<br />
S.A. V Ao<br />
78.8 50.7 0.1928<br />
DATE OCT 12 1992<br />
(d9n t-sYm(dt COne. an a an/Ao SUM<br />
Di L<br />
S<br />
S PPM<br />
aNAo<br />
7200 7200 0.1 0.0001 0.0004 0.0004 7.81 E-12 11.1184<br />
2 18000 25200 0.1 0.0001 0.0004 0.0008 1 E-11 10.9982<br />
3 61200 86400 1.1 0.0008 0.0044 0.0052 3.63E-10 9.4402<br />
4 86400 172800 0.1 0.0001 0.0004 0.0056 3.7E-12 11.4320<br />
5 88400 259200 0.1 0.0001 0.0004 0.0060 6.28E-12 11.2020<br />
8 86400 345800 1.1 0.0008 0.0044 0.0104 1.07E-09 8.9709<br />
7 86400 d32000 1.3 0.0010 0.0052 0.0166 1.92E-09 8.7157<br />
- 8 1382400 1814400 0.0000 0.0000 0.0156 0 ERR<br />
9 2100000 3974400 0.0000 0.0000 0.0156 0 ERR<br />
10 3888000 7852400 0.0000 0.0000 0.0156 0 ERR<br />
Sa-N':ID L78"<br />
Elament COBALT<br />
Mahix SEA WATER<br />
S.A. V Ac<br />
78.5 52.4 0.1941<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Cone. an p an/Ao SUM<br />
DI L<br />
S<br />
S PPM<br />
an/Ac<br />
7200 7200 0.1 0.0001 0.0004 0.0004 7.61E-12 11.1154<br />
2 18000 25200 0.2 0.0002 0.0008 0.0012 4.02E-11 10.3962<br />
3 61200 86400 1.5 0.0012 0.0060 0.0072 6.75E-10 9.1708<br />
4 88400 172800 0.2 0.0002 0.0008 0.0060 1.48E-11 10.8299<br />
3 86400 259200 0.3 0.0002 0.0012 0:0092 5.65E-11 10.2477<br />
6 86400 345600 1.2 0.0009 0.0048 0.0140 1.27E-09 8.8953<br />
7 86400 432000 1.5 0.0012 0.0080 0.0200 2.58E-09 8.5914<br />
6 1382400 1814400 0.0000 0.0000 0.0200 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0200 0 ERR<br />
10 3888000 7882400 0.0000 0.0000 0.0200 0 ERR<br />
F-17
sI-d<br />
tlN3 0 99CL'0 0000'0 0000'0 00+Z99L 000899C Ol<br />
Htl3 0 98EL'0 0000'0 0000'0 004+L6C 00009/Z 6<br />
SHE 0 98CL'0 0000'0 0000'0 00++L9L 00498C1 9<br />
LIIC'9 t0•389Y 99CL'0 LZBO'0 6SL0'0 L'OZ 000Z£+ 00+99 L<br />
LSO4'9 L0-3C6'C 6959'0 £+90'0 Z9L0'0 l'lZ 0099+C 00198 9<br />
190+'9 LO-3C66C 9149'0 6860'0 Z6L0'0 SZ OOL69Z 00+98 9<br />
490Z19 L03LZ'9 9LL+'0 _ 6£9L'0 _ 4l£0'0 _ L+ _ O09ZLL_ 00t99 _ +<br />
99L1'9 L0P3C8'9 9C0E'0 649C0 09£0'0 L+ 00+98 0031.9 C<br />
LG9+'9<br />
0096'9<br />
Ltr3SZ'E<br />
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BlLO'0<br />
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8Et00<br />
Z600'0<br />
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20Z9Z<br />
00ZL<br />
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!0 wns oyM 6 uv rouo0 (Lp)ums_L u(Lp)<br />
Z66lZ1170 31y0<br />
COBI'0 co; L'9L<br />
GM •<br />
tl31tlM 10 X1+WW<br />
WnIS30 N+vuN13<br />
- YYL1 Y16)d^^i<br />
!!tl3 0 9996'0 0000'0 0000'0 OO+39BL 0009996 01<br />
Htl3 0 9986'0 00000 0000'0 OOriL6E 000091Z 6<br />
HF13 0 8996'0 0000'0 0000'0 00ri19L OOYZB£l 9<br />
£6£Z'9 L0-39L'S B996'0 6690'0 CCl0'0 S'ZZ OOOZC+ 00484 L<br />
09 L'9 L0tr324'9 6949'0 91L 1'0 +LZO'0 6'4Z 0099+C 00198 9<br />
4Zb0'9 GO-3L0'e +L9L'0 619Lb L6Z0'0 9C 00369Z 00t94 9<br />
99£6'9<br />
1966'9<br />
90-39L'L<br />
90-310'1<br />
99L9'0<br />
L16C'0<br />
BC33'0<br />
9l£SO<br />
0£90'0<br />
9+f0'0<br />
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0093L1<br />
00+99<br />
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BLEZ'9 LO•34L'4 669L'0 6960'0 f4/0'0 It OOZ93 OOOBI Z<br />
LOLG'9 LO-3S6'L e£90'0 6E80'0 EZl0'0 9L oOZL 00ZL I.<br />
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Z66LZtL7O31V0<br />
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WnS oyM 6 w<br />
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lLZ'0 1 1 +'l9 LL<br />
oV A 'y'S<br />
S<br />
(lplwnv-i<br />
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ON<br />
Ll31yM 10 nMW<br />
WnIS30 Luau+a!3<br />
ZVL1 01 vIdwvS<br />
ldtl3 0 ZZ9G'0 0000'0 0000'0<br />
OOOB9BE Ol "--'<br />
tltl3 0 ZZ9L'0 0000'0 0000'0 I<br />
00Y+L6C 000091Z 6 _<br />
583 0 ZZ9L'0 0000'0 0000'0 00ri101 00+Z9C1 9<br />
L+91'9 L0tr3L ZZ9L'0 1660'0 0610'0 0003C+ 00199 L<br />
+£1.1119 10-399'£ 1C99'0 9£90'0 091,0'0 640Z 0092/C 00099 9<br />
OZLE'9 LO-3CZY SeLS'o 6COl'0 eel0•0 9Z OOZ6SZ 00f94 9<br />
eLR•a LO•3Z6•5 951t•0 - d6sL•0 - L6£o^ - 0>-- - -- -009U L - - -00l9a- -- - -- --- - - -- -^-- - - - -<br />
099Z•9 Lo-39919 991 £•o e14L•0 oEEO•0 C+ 00999 oozl9 £<br />
BCSE'9 to-3E+'r 6E+0 6£BO'0 L9LO•0 LZ o0Z9Z 0009 L Z<br />
za9L'9 co-3LCl 0090•0 0090ro sllo'a sL oozL ooZL t<br />
^<br />
10<br />
z6e1 4 1. lOO31y0<br />
oyluv<br />
WnS oyNs 6 uv<br />
Wdd<br />
^uo0<br />
+Z61'0 4'O9 1.'91.<br />
oy A rS<br />
S<br />
(LP)uLnv-i<br />
0 'nea £00-Il-OOIM-US-7HM<br />
S<br />
upp)<br />
»LvM 10 xi+lvW<br />
WnIS3J Luawvl3<br />
LrL-1 OI •IduLVg<br />
.i?<br />
;..,^
4.a
^ _•<br />
Sample ID L7AI<br />
- EIamenY JIROI\IIVM<br />
Matrix DI water<br />
---<br />
e<br />
-^<br />
S<br />
WHC-SD-W100-TI-003 Rev. 0<br />
=wm(tl1)<br />
S<br />
S.A. V Ao<br />
x<br />
PPM<br />
^u./ 0.1024<br />
sn0 ayAa SUM<br />
aNAo<br />
DATE OCT 12 1992<br />
- - -- - - i - - - - - iz00 7200 0.38 0.0003 0.0013 0.0015 1.1 E-10 9.9588<br />
2 - - -- - 18000 25200 0.54 0.0004 0.0022 0.0037 2.93E-10 9.5335<br />
3 61200 86400 0.9 0.0007 0.0036 0.0073 2.43E-10 9.8145<br />
4 88400 172800 0.72 0.0000 0.0029 0.0102 1.92E-10 9.7173<br />
5 86400 259200 0.87 0.0007 0.0035 0.0136 4.75E-10 9.3229<br />
e e6400 345600 0.1 0.0001 0.0004 0.0140 8.84E-12 11.0537<br />
7 88400 432000 0.007 0.0000 0.0000 0.0141 5.58E-14 13.2534<br />
8 1382400 1614400 0.0000 0.0000 0.0141 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0141 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0141 0 ERR<br />
Sample ID L7A2<br />
Element STRONTIUM<br />
Matrix DI WATER<br />
(dt)n<br />
S<br />
t-sum(dt)<br />
S<br />
S.A. V Ao<br />
77.4 51.4 0.211<br />
Cone.<br />
PPM<br />
an9 an/Ao SUM<br />
en/Ao<br />
Di<br />
.<br />
^<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 0.17 0.0001 0.0007 0.0007 2.2E-1 1 10.6575<br />
2 18000 25200 0.33 0.0003 0.0013 0.0020 1.09E-10 9.9612<br />
3 61200 86400 0.76 0.0006 0.0030 0.0050 1.73E-10 9.7613<br />
4 86400 172800 0.41 0.0003 0.0016 0.0067 8.22E-11 10.2064<br />
5 88400 259200 0.35 0.0003 0.0014 0.0081 7.68E-11 10.1138<br />
8 88400 345800 0.15 0.0001 0.0008 0.0087 1.99E-11 10.7015<br />
7 86400 432000 0.18 0.0001 0,p007 0.0094 3.69E-11 10.4331<br />
8 1382400 11f14400 0.0000 0.0000 0.0094 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0094 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0094 0 ERR<br />
Sample ID L7A3<br />
Element STRONTIUM<br />
Matrix DI WATER<br />
S.A. V Ao<br />
76.7 50.7 0.1903<br />
DATE OCT 12 1992<br />
-<br />
(dt)n t-sum(dt) Cone* an g an/AO SUM<br />
DI L<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 0.42 0.0003 0.0017 0.0017 1.34E-10 9.8719<br />
2 18000 25200 0.22 0.0002 0.0009 0.0026 4.88E-11 10.3134<br />
3 61200 86400 0.83 0.0005 0.0025 0.0051 1.19E-10 9.9243<br />
4 85400 172800 0.57 0.0004 0.0023 0.0074 1.2E-10 9.9203<br />
5 88400 259200 0.33 0.0003 0.0013 0.0087 6.84E-11 10.1649<br />
6 86400 345800 0.4 0.0003 0.0016 0.0103 1.41 E-10 9.8495<br />
7 86400 432000 0.44 0.0003 0.0018 0.0120 2.2E-10 9.6567<br />
8 1382400 1814400 0.0000 0.0000 0.0120 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0120 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0120 0 ERR<br />
F-20
Sanp)a ID L781<br />
Elamant STRONTIUM<br />
Matrix SEA WATER<br />
(dt)n<br />
S<br />
WHC-SD-W100-TI-003 Rev. 0<br />
t-sum(dt)<br />
S<br />
S.A. V Ae<br />
76.9 so.8 0.1976<br />
Cone.<br />
PPM<br />
an9 an/AO SUM<br />
an/Ao<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 0.85 0.0007 0.0034 0.0034 5.5E-10 9.2595<br />
2 18000 25200 1.23 0.0009 0.0049 0.0083 1.52E-09 8.8184<br />
3 81200 86400 1.99 0.0015 0.0060 0.0163 1.19E-09 8.9253<br />
4 06400 172800 1.43 0.0011 0.0057 0.0220 7.56E-10 9.1213<br />
6 06400 259200 1.44 0.0011 0.0058 0.0277 1.3E-09 8.8852<br />
6 86400 345800 0.79 0.0006 0.0032 0.0309 5.52E-10 9.2584<br />
7 8100 432000 0.71 0.0005 • 0.0028 0.0337 5.74E-10 9.2411<br />
8 1382400 1814400 0.0000 0.0000 0.0337 0 ERR<br />
9 2160000 3074400 0.0000 0.0000 0.0337 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0337 0 ERR<br />
Sampla ID L782<br />
Elamant STRONTIUM<br />
Matrix SEA WATER<br />
S.A. V Ao<br />
78.8 50.7 0.1926<br />
DATE OCT 12 1992<br />
(dqn t-sum(dq Cone. an 9 an/Ao SUM<br />
Di L<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 0.99 0.0008 0.0040 0.0040 7.46E-10 9.1271<br />
--- - 2 - - - - - - - - - - - - - 18000 =e3200 0.4 0.0003 0.6616 0.0056 1.61 E-10 9.7941<br />
3 01200 86400 1.87 0.0014 0.0075 0.0130 1.05E-09 8.9793<br />
4 86400 172800 1.3 0.0010 0.0052 0.0182 6.25E-10 9.2041<br />
5 86400 259200 1.07 0.0008 0.0043 0.0225 7.19E-10 9.1432<br />
8 86400 345600 1.13 0.0009 0.0045 0.0270 1.13E-09 8.9475<br />
7 86400 432000 0.94 0.0007 0.0038 0.0308 1.01 E-09 6.9974<br />
8 1382400 1814400 0.0000 0.0000 0.0306 0 ERR<br />
9 2160000 3074400 0.0000 0.0000 0.0308 0 ERR<br />
t0 3888000 7862400 0.0000 0.0000 0.0308 0 ERR<br />
Sampla ID L783<br />
Elanant STRONTIUM<br />
Matrix SEA WATER<br />
--------^ ---- DATEOCTt21992<br />
S.A. V Ao<br />
78.3 52.4 0.1941<br />
(dt)n t-sum(dt) Cone. an9 an/Ao SUM<br />
Di L<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 0.65 0.0005 0.0028 0.0026 3.22E-10 9.4925<br />
2 18000 25200 0.39 0.0003 0.0016 0.0042 1.53E-10 9.8161<br />
3 61200 86400 1.73 0.0013 0.0069 0.0111 8.98E-70 9.0469<br />
4 86400 172800 1.1 0.0008 0.0044 0.0155 4.47E-10 9.3492<br />
5 86400 259200 1.32 0.0010 0.0053 0.0207 1.09E-09 8.9808<br />
8 86400 345600 1.03 0.0008 0.0041 0.0249 9.38E-10 9.0280<br />
7 88400 432000 0.9 0.0007 0.0036 0.0285 9.22E-10 9.0351<br />
8 1382400 1814400 0.0000 0.0000 0.0285 0 ERR<br />
9 2180000 3974400 0.0000 0.0000 0.0285 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0285 0 ERR<br />
F-21
Sample ID L3A1<br />
Element COBALT<br />
Matrix DI watar<br />
(dt)n<br />
S<br />
t.sum(dt)<br />
S<br />
WHC-SD-W100-TI-003 Rev. 0<br />
S.A. V Ao<br />
76.7 50.7 0.1919<br />
Cone.<br />
PPM<br />
an 9 eryAO SUM<br />
WAo<br />
DATE OCT 12 1992<br />
1 L<br />
1 7200 7200 8.4 0.0064 0.0336 0.0338 5.37E-08 7.2898<br />
2 18000 25200 7.5 0.0058 0.0300 0.0636 5.65E-08 7.2481<br />
3 61200 86400 7.8 0.0060 0.0312 0.0947 1.82E-08 7.7388<br />
4 86400 172800 10.7 0.0082 0.0428 0.1375 4.23E.08 7.3732<br />
5 86400 259200 8.9 0.0068 0.0356 0.1731 4.98E-08 7.3032<br />
6 86400 345600 9.2 0.0071 0.0368 0.2098 7.48E-08 7.1261<br />
7 86400 432000 7.9 0.0061 0.0316 0.2414 7.11 E-08 7.1484<br />
6 1382400 1814400 0.0000 0.0000 0.2414 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.2414 0 ERR<br />
3888000 7862400 0.0000 0.0000 0.2414 0 ERR<br />
Sample ID L3A2<br />
Element COBALT<br />
Matrix DI WATER<br />
S.A. V Ao<br />
77.4 51.4 0.1803<br />
DATE OCT 12 1992<br />
(dt)n t>•sum(dt) Cone. an 0 WAO SUM<br />
Di L<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 7.1 0.0054 0.0284 0.0284 3.84E-08 7.4159<br />
2 18000 25200 6.3 0.0048 0.0252 0.0538 3.99E-08 7.3996<br />
3 81200 85400 15.6 0.0120 00624 0.1159 7.3E-08 7.1367<br />
4 86400 172800 11.4 0.0087 0.0456 0.1615 4.81 E-08 7.3182<br />
5 88400 259200 10 0.0077 0.0400 0.2014 6.28E-08 7.2020<br />
8 86400 345600 9.9 0.0076 0.0396 0.2410 8.66E.08 7.0624<br />
7 86400 432000 6.8 0.0052 0.0272 0.2682 5.26E-08 7.2786<br />
8 1382400 1814400 0.0000 0.0000 0.2682 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.2682 0 ERR<br />
10 3888000 7882400 0.0000 0.0000 0.2682 0 ERR<br />
Sample ID L3A3<br />
Element COBALT<br />
matriz DI WATER<br />
(dt)n<br />
S<br />
t-sutn(dt)<br />
S<br />
S.A. V Ae<br />
81.5 55.5 0.1918<br />
Cone,<br />
PPM<br />
an 9 an/AO SUM<br />
an/Ao<br />
DATE OCT 12 1992<br />
DI L<br />
1 7200 7200 5.2 0.0040 0.0208 0.0208 2.06E-08 7.6864<br />
2 18000 25200 8.1 0.0047 0.0244 0.0452 3.74E-08 7.4276<br />
3 61200 86400 14.8 0.0114 0.0592 0.1043 6.57E-08 7.1824<br />
4 86400 172800 10.2 0.0078 0.0408 0.1451 3.85E-08 7.4148<br />
5 86400 259200 9.2 0.0071 0.0368 0.1819 5.32E-08 7.2744<br />
6 86400 345600 12.6 0.0097 0.0504 0.2322 1.4E-07 6.8529<br />
7 86400 432000 13 0.0100 0.0520 02842 i '.92E-07 6.7157<br />
8 1362400 1814400 0.0000 0.0000 0.2842 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.2842 0 ERR<br />
_10. 3atumn 7nw2am 0.0000 0.0000 0.2842 0 ERR<br />
F-22<br />
J6
.^<br />
"-; SampI81D L3B2<br />
Z<br />
e"-<br />
^.;;.<br />
Sample ID L3B1<br />
Eiemsnt COBALT<br />
Metra SEA WATER<br />
MVOAL^<br />
Metta SEA WATER<br />
WHC-SD-W100-TI-003 Rev. 0<br />
S.A. V Ao<br />
78.8 50.8 0.1792<br />
DATE OCT 12 1992<br />
(dUn t-sum(dt) Cone. an 0 WAO SUM Of L<br />
S S PPM an/Ao<br />
7200 7200 6.6 0.0051 0.0204 0,0264 3.32E-08 7.4793<br />
2 18000 25200 8.8 0.0052 0.0272 0.0538 4.64E-08 7.3332<br />
3 61200 68400 20 0.0153 0.0799 0.1335 1.2E-07 8.9209<br />
4 66400 172600 19.4 0.0149 0.0775 0.2110 1.39E-07 8.8564<br />
-3 --38400 --259200 -I.2.B -0.0096 -0,0512 --02622 t.03E-07 6.9875<br />
6 86400 345600 14.6 0.0112 0.0584 0.3205 1.88E-07 6.7250<br />
7 - - 86400 432000 14.6 0.0112 0.0064 --6.3789 1.43E-07 -8.et49<br />
8 1382400 1814400 0.0000 0.0000 0.3789 0 ERR<br />
9 2180000 3974400 0.0000 0.0000 0.3789 0 ERR<br />
10 3868000 7862400 0.0000 0.0000 0.3789 0 ERR<br />
(dqn<br />
S<br />
t-sum(dQ<br />
S<br />
S.A V Ao<br />
Cone.<br />
PPM<br />
an 9 an/Ao SUM<br />
anlAo<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 5.1 0.0039 0.0204 0.0204 1.98E-08 7.7032<br />
2 18000 25200 5.6 0.0043 0.0224 0.0428 3.15E-08 7.5019<br />
3 61200 88400 15.4 0.0118 0.0616 0.1043 7.11 E-08 7.1479<br />
4 86400 172800 10.2 0.0078 0.0408 0.1451 3.85E-08 7.4148<br />
S 86400 259200 9.2 0.0071 0.0388 0.1819 5.32E-08 7.2744<br />
6 86400 345600 8.8 0.0066 0.0344 0.2162 6.54E-08 7.1847<br />
7 88400 432000 10.8 0.0083 0.0432 0.2594 1.33E-07 6.8768<br />
8 1382400 1814400 0.0000 0.0000 0.2394 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.2594 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.2594 0 ERR<br />
2<br />
3<br />
6<br />
7<br />
8<br />
9<br />
10<br />
Sampls ID 1393 S.A. V Ao<br />
Element COBALT 77.4 31•4 0.-1797<br />
Miwi SEA WA<br />
DATE OCT 12 1992<br />
- - - -<br />
(dt)n t-sum(dt) Cone. en p WAe SUM<br />
Di L<br />
5<br />
S PPM<br />
WAo<br />
7200 7200 6.3 0.0048 0.0252 0.0252 3.02E-08 7.5197<br />
18000 25200 4.1 0.0031 0.0164 0.0416 1.89E-08 7.7727<br />
81200 66400 13.8 0.0106 0.0552 0.0967 5.71 E-08 7.2432<br />
- - -- -6e400 172806 --11 A 00091 -0-.5472- -01439 315E-08 7.2882<br />
-259200-----_94--t0072-<br />
N471. 0.0376 0.1615 SSSE08 7.2357<br />
345800 12.4 0.0095 0.0496 0.2310 1.36E-07 8.8668<br />
43zooo 13.2 0.0101 0.os28 0.2838 1.98E-07 8.7025<br />
814400 0.0000 0.0000 0.2638 0 ERR<br />
974400 0.0000 0.0000 0.2838 0 ERR<br />
862400 0.0000 0.0000 0.2838 0 ERR<br />
F-23
ti<br />
Sampla ID L3A7<br />
Element CESIUM<br />
Matrix DI water<br />
(dt)n<br />
S<br />
WHC-SD-W100-TI-003 Rev. 0<br />
t-sum(dt)<br />
S<br />
S.A V Ao<br />
76.7 80.7 0.1919<br />
Cone.<br />
PPM<br />
an 9 anlAo SUM<br />
anlAo<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 23 0.0176 0.0919 0.0919 4.03E-07 6.3949<br />
2 18000 25200 21 0.0161 0.0839 0.1759 4.43E-07 8.3538<br />
3 81200 86400 29 0.0222 0.1159 0.2918 2.52E-07 8.5982<br />
4 86400 172800 27 0.0207 0.1079 0.3997 2.7E-07 6.5693<br />
5 66400 259200 23 0.0176 0.0919 0.4916 3.32E-07 6.4785<br />
8 86400 345600 15.2 0.0117 0.0608 0.5524 2.04E-07 6.6900<br />
7 88400 432000 12 0.0092 0.0480 0.8003 1.84E-07 8.7853<br />
8 1382400 1814400 0.0000 0.0000 0.6003 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.6003 0 ERR<br />
10 3888000 7802400 0.0000 0.0000 0.6003 0 ERR<br />
Sampie ID L3A2<br />
Elament CESIUM<br />
Matrct DI WATER<br />
(dt)n<br />
9<br />
t-sum(dt)<br />
S<br />
.A .<br />
77.4<br />
P<br />
Cone.<br />
PPM<br />
51.4 0.1803<br />
an g an/Ao SUM<br />
an/Ae<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 19 0.0146 0.0759 0.0759 2.75E-07 8.5809<br />
2 18000 2_5 200 20 0.0153 0.0799 0.1550 4.02E-07 8.3962<br />
3 61200 86400 28 0.0215 0.1119 0.2678 2.35E-07 6.8288<br />
4 88400 172800 29 0.0222 0.1159 0.3837 3.11 E-07 6.5072<br />
5 86400 259200 24 0.0184 0.0959 0.4796 3.62E-07 6.4415<br />
8 86400 345600 13.6 0.0104 0.0544 0.5340 1.63E-07 6.7886<br />
7 86400 432000 8.6 0.0086 0.0344 0.54 68 8.42E-08 7.0746<br />
8 1382400 1814400 0.0000 0.0000 0.5684 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.5684 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.5684 0 ERR<br />
Sample ID L3A3<br />
Element CESIUM<br />
Matrix DI WATER<br />
- - -<br />
(dt)n<br />
S<br />
t-sum(dt)<br />
S<br />
S.A. V Ao<br />
81.5 55.5 0.1916<br />
Cone.<br />
PPM<br />
an 9 eNAo SUM<br />
anlAo<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 19 0.0146 0.0759 0.0759 2.75E-07 6.5609<br />
2 18000 25200 20 0.0153 0.0799 0.1559 4.02E-07 6.3962<br />
3 61200 86400 29 0.0222 0.1159 0.2718 2.52E-07 6.5982<br />
4 86400 172800 27 0.0207 0.1079 0.3797 2.7E-07 8.5693<br />
5 88400 259200 23 0.0176 0.0919 0.4716 3.32E-07 6.4785<br />
6 86400 345600 15.4 0.0118 0.0616 0.5332 2.1 E-07 6.6786<br />
- - - 7 ---- - - - -- - -- - -664D0- -d32000- -- 14.1 0. 01 We 0.0564 0.5895 2.26E-07 6.6452<br />
8 1382400 1814400 0.0000 0.0000 0.5895 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.5895 0 ERR<br />
10 3888000 7882400 0.0000 0.0000 0.5895 0 ERR<br />
F-24<br />
4
Sample 10 L3B1<br />
Elsmant CESIUM<br />
Matrix Sve wstER<br />
WHC-SD-W100-TI-003 Rev. 0<br />
S.A. ^ V Ao<br />
78.6 50.8 0.1702<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Cone. en 0 eNAo SUM<br />
DI L<br />
----- - - 1- -- - --- -<br />
S<br />
7200<br />
S<br />
7200<br />
PPM<br />
31 0.0238 0.1230<br />
aNAo<br />
0.1239 7.32E-07 6.1357<br />
2 18000 25200 29 0.0222 0.1159 0.2398 8.44E-07 8.0734<br />
3 61200 66400 55 0.0422 0.2198 0.4596 9.07E-07 0.0422<br />
4 86400 172800 42 0.0322 0.1679 0.6275 6.52E-07 6.1855<br />
5 86400 250200 31 0.0238 0.1239 0.7514 6.04E-07 6.2192<br />
6 86400 346600 30.3 0.0232 0.1211 0.8725 8.11 E-07 6.0908<br />
7 86400 432000 18.4 0.0141 0.0735 0.9461 3.85E-07 6.4140<br />
Sample ID L3B2<br />
= `^! Elsnlsnt CESIUM<br />
Matrix SEA WATER<br />
6 1382400 1814400 0.0000 0.0000 0.9461 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.9461 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.9461 0 ERR<br />
S.A. V Ao<br />
78.6 52.5 0.1906<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Cono. an 9 aNAo SUM<br />
Di L<br />
S<br />
S PPM<br />
eNAo<br />
1 7200 7200 20 0.0153 0.0799 0.0799 3.05E-07 6.5163<br />
2 18000 25200 24 0.0164 0.0959 0.1759 5.78E-07 6.2378<br />
3 61200 86400 36 0.0276 0.1439 0.3197 3.89E-07 6.4104<br />
4 86400 _172800 27 0.0207 0.1079 0.4277 2.7E-07 6.5693<br />
5 86400 259200 22 0.0169 0.0879 0.5156 3.04E-07 6.5171<br />
8 88400 345600 13.0 0.0107 0.0558 0.5712 1.71 E-07 6.7676<br />
7 86400 432000 11.4 0.0087 0.0456 0.6167 1.48E-07 8.8298<br />
8 1382400 1814400 0.0000 0.0000 0.6167 0 ERR<br />
9 2180000 3974400 0.0000 0.0000 0.8167 0 ERR<br />
io 3888000 7862a00 0.0000 0.0000 0.t1167 0 ERR<br />
_ _ `=n€!e!0 l-4B..'<br />
Elwnsnt CESIUM<br />
Mstrix SEA WATER<br />
V Ao<br />
V'77.a s1.4 0.1797<br />
DATE OCT 12 1992<br />
- - - (dt)n t-sum(dt) Cone. an 0 aNAo SUM<br />
DI L<br />
S .8 PPM<br />
anfAo<br />
1 7200 7200 22 0.0169 0.0879 0.0879 3.69E-07 6.4335<br />
2 18000 25200 20 0.0153 0.0799 0.1679 4.02E-07 6.3962<br />
3 61200 86400 32 0.0245 0.1279 0.2958 3.07E-07 8.5127<br />
4 86400 172800 29 0.0222 0.1159 0,4117 3.11 E-07 6.5072<br />
5 86400 259200 23 0.0178 0.0919 0.5036 3.32E-07 6.4785<br />
6 88400 345600 19.3 0.0148 0.0771 0.5807 3.29E^07 6.4825<br />
7 864 432000 12.2 0.0004 0.0a88 0.6295 7.89E07 6.7709<br />
B 13824 22 00 1 1874400 0.0000 0.0000 0.6293 0 ERR<br />
9<br />
10<br />
n^^<br />
7888000<br />
3ff74400<br />
7862400<br />
--- - O.vOvO<br />
0.0000<br />
0.0000<br />
0.0000<br />
0.8295<br />
0.6295<br />
0<br />
0<br />
ERR<br />
ERR<br />
F-25
^-s<br />
".^.<br />
z,<br />
...,..4<br />
-: ^<br />
...i^^;.,.<br />
Sample ID L3AI<br />
Element STRONTIUM<br />
Matrix DI water<br />
,:..,<br />
Wur-SD-W100-TI-003 Rev. 0<br />
S.A V Ao<br />
78.7 30.7 O.1B1B<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Cone. an 9 an/Ao SUM<br />
Di l<br />
8<br />
S PPM<br />
aNAo<br />
1 7200 7200 1.51 0.0012 0.0060 0.0080 t.74E-09 8.7604<br />
2 18000 25200 1.88 0.0014 0.0075 0.0135 3.55E.09 8.4499<br />
3 61200 86400 2.06 0.0016 0.0082 0.0218 1.27E-09 8.8982<br />
4 86400 172800 1.92 0.0015 0.0077 0.0295 1.36E-09 8.8854<br />
8 86400 259200 1.86 0.0014 0.0074 0.0369 2.17E-09 8.6629<br />
- - - - 11- -- - - - - - - - - 66400 345600 i.32 0.0010 0.0053 0.0422 1.54 E-09 8.8125<br />
7 86400 d32000 1.03 0.0008 0.0042 0.0464 1.26E-09 8.9013<br />
8 1382400 1814400 0.0000 0.0000 0.0464 0 ERR<br />
0 2160000 3974400 0.0000 0.0000 0.0464 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0464 0 Co.<br />
Sample ID L3A2<br />
Element STRONTIUM<br />
Matrix DI WATER<br />
S.A. V Ac<br />
77.4 s1.4 0.1803<br />
DATE OCT 12 1992<br />
(dt)n t-sum(tlt) Conc. an p aNAo SUM<br />
Di I.<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 1.75 0.0013 0.0070 0.0070 2.33E-09 8.6323<br />
2 18000 25200 2.04 0.0016 0.0082 0.0151 4.18E-09 8.3790<br />
3 61200 88400 2.15 0.0016 0.0086 0.0237 1.39E-09 8.8581<br />
4 86400 172800 1.83 0.0014 0.0073 0.0311 1.24E-09 8.9071<br />
5 86400 259200 1.48 0.0011 0.0059 0.0370 1.38E.09 8.8614<br />
8<br />
7<br />
8 1 1<br />
86400<br />
86400<br />
1382400<br />
345800<br />
432000<br />
1814400<br />
1.19<br />
1.31<br />
0.0009<br />
0.0010<br />
0.0000<br />
0.0048<br />
0.0052<br />
0.0000<br />
0.0417<br />
0.0470<br />
0.0470<br />
1.23E-09<br />
1.93E-09<br />
0<br />
8.9026<br />
8.7091<br />
ERR<br />
9 2180000 3974400 0.0000 0.0000 0.0470 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0470 0 ERR<br />
Sample ID L3A3<br />
Element STRONTIUM<br />
Matrix DI WATER<br />
S.A. V Ao<br />
81.5 33.3 0.1916<br />
DATE OCT 121992<br />
(dt)n t-sum(tlt) Conc. an p aNAO SUM<br />
Di L<br />
S<br />
S PPM<br />
aNAo<br />
1 7200 7200 1.21 0.0009 0.0048 0.0048 1L11 EO9 8.9528<br />
2 16000 25200 1.77 0.0014 0.0071 0.0119 3.15E-09 8.5023<br />
3 61200 86400 2.02 0.0015 0.0081 0.0200 1.22E-09 8.9123<br />
4 86400 172800 1.08 0.0005 0.0043 0.0243 4.31 E-10 9.3652<br />
8 86400 259200 1.35 0.0010 0.0054 0.0297 1.14E-09 8.9413<br />
8 86400 345600 0.93 0.0007 0.0037 0.0334 7.64E-10 9.1167<br />
7 86400 432000 1.36 0.0010 0.0054 0.0388 2.11 E-09 8.8766<br />
8 1382400 1814400 0.0000 0.0000 0.0388 0 ERR<br />
9 2180000 3974400 0.0000 0.0000 0.0388 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0388 0 ERR<br />
F-26<br />
rl
Sample ID W B1<br />
Elemant STRONIIUM<br />
Matrix SEA WATER<br />
- ----- - -- - - - - (a'Yn<br />
S<br />
WHC-SD-W100-TI-003 Rev. 0<br />
R,<br />
lasum(di)<br />
S<br />
S.A V Ao<br />
76.7 50.8 0.1792<br />
Conc.<br />
PPM<br />
an0 an/Ao SUM<br />
udAo<br />
DATE OCT 12 1992<br />
Di L<br />
1 7200 7200 2.46 0.0019 0.0098 0.0098 4.81 E-09 8.3365<br />
2 18000 25200 1.92 0.0015 0.0077 0.0175 3.7E-09 8.4318<br />
3 61200 86400 3.32 0.0025 0.0133 0.0306 3.31 E-W 8.4807<br />
4 86600 172800 2.36 0.0018 0.0094 0.0402 2.06E-09 6.6862<br />
5 86400 259200 1.83 0.0014 0.0073 0.0475 2.1 E-09 8.6771<br />
8 86400 345800 1.98 0.0015 0.0079 0.0554 3.46E-09 8.4803<br />
7 66400 432000 1.9 _ 0.0015 0.0076- 0.0630 4,11E-08 8,3681<br />
6 1382400 1814400 0.0000 0.0000 0.0630 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0830 0 ERR<br />
10 3866000 7882400 0.0000 0.0000 0.0630 0 ERR<br />
Sample ID L382<br />
Elnnant STRONTIUM<br />
Matrix SEAWATER<br />
S.A. V Ao<br />
78.8 52.5 0.7908<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Cone, an 9 aNAo SUM<br />
Di L<br />
S<br />
S PPM<br />
an/Ao<br />
1 7200 7200 2.99 0.0023 0.0120 0.0120 6.81 E-09 8.1670<br />
2 18000 25200 1.81 0.0014 0.0072 0.0192 3.29E-09 8.4829<br />
3 61200- 8_6400 __- _2.45 00019_ .__0,0098 0.0290 1 eF-m 8.7448<br />
4 86400 172800 1.37 0.0011 0.0053 0.0343 6.94E-10 9.1586<br />
5 86400 259200 1.65 0.0013 0.0066 0.0410 1.71 E-09 8.7670<br />
8E400- 345800 0.1,111 ^v.006.5 0.0476 2.35E.09 8.6293<br />
7 68400 432000 1.7 0.0013 0.0088 0.0544 3.29E-09 8.4827<br />
8 1382400 1814400 0.0000 0.0000 0.0544 0 ERR<br />
9 2160000 3974400 0.0000 0.0000 0.0544 0 ERR<br />
3866000 7862400- 0.0003 - 0.0006 - 0.0544 0 ERR<br />
Sample ID L383<br />
Element STRONTIUM<br />
Matrix SEA WATER<br />
S.A. V Ao<br />
77.4 61.4 0.1797<br />
DATE OCT 12 1992<br />
(dt)n t-sum(dt) Cone. ang an/Ao SUM<br />
DI L<br />
S<br />
S PPM<br />
an/Ao<br />
7200 7200 3.05 0.0023 0.0122 0.0122 7.08E09 8.1498<br />
2 16000 25200 1.63 0.0013 0.0065 0.0187 2.67E-09 8.5739<br />
3 61200 86400 2.81 0.0022 0.0112 0.0299 2.37E-09 8.6255<br />
4 86400 172600 1.55 0.0012 0.0062 0.0361 8.88E•10 9.0513<br />
5 86400 259200 1.3 0.0010 0.0052 0.0413 1.06E-09 8.9741<br />
6 86400 345600 2.08 0.0016 0.0083 0.0496 3.82E.09 5.4175<br />
7 86400 432000 1.79 0.0014 0.0072 0.0368 3.86E09 8.4379<br />
6 1382400 1814400 0.0000 0.0000 0.0568 0 ERR 11<br />
9 2160000 3974400 0.0000 0.0000 0.0568 0 ERR<br />
10 3888000 7862400 0.0000 0.0000 0.0568 0 ERR<br />
F-27
WHC-SD-W100-TI-003 Rev. 0<br />
-f'^ORR-EsP£3'^14I3ENC€VI3;R1BU TiOU MIERjHEEi<br />
Author Addreaaee Correepondance No.<br />
RA CZELLATH/STOCK DA BURBANK/WHC 9205883<br />
swlect: STOCK POLYMER IMMOBILIZATION TECH. WASTE FORM QUALIFICATION TESTING PURCHASE ORDER<br />
NO. MMW-SVV-277587 STOCK REFERENCE NO. 6996<br />
I9AnAUG7tn1 rKUJCGI enulKttKlnG tlKAr rKUJtt.l GUnIKUL<br />
JA Swenson G6-46 TA Carlson G6-46 KP Brown G6-47<br />
DE Ball G6-46 AW Hinkle G6-46 SE Bussman G6-47 -<br />
SR Briggs G6-47 FH Lee G6-46 C Malstrom G6-47 -<br />
JE Filip G6-47 _ _<br />
JB Payne G6-46 SW McKinley G6-47 -<br />
DR Lucas G6-46 X- JG Starke _v<br />
G6-45__ GC-Jtice G6-47 -<br />
CA Petersen Hl-60 -X WR Swita G6-46 -7- BL Trumpour G6-47 -<br />
Ti Yount H1-60 _<br />
X_ RR Wyer G6-46 =X_<br />
-<br />
WRAP TECHNOLOISY SW SYSTEMS ENGINEERING SW SYSTEMS ENGINEERING<br />
CJ Benar HI-60 K EG Berglin<br />
DA Burbank H1-60 X KJ Hull<br />
BF Campbell HI-60 RM Horgus<br />
JD Keck G6-46 ! SL Kooiker<br />
CE McDonald Hi-60 DL Lamberd<br />
JL Nelson H1-60 ML Lee<br />
KE Parker H1-60 - KJ Leist<br />
RM Ybarra HI-60 _-- 1 N.t Monroe<br />
G6-46 VP Ocampo G6-46<br />
G6-46 - DT Ruff G6-46 -<br />
H1-60 RA Sexton H1-60 -<br />
G6-46 _ JR Weber G6-46 _<br />
H1-60 _ JR Weidert G6-46<br />
G6-46 RH Winkleman _<br />
G6-46<br />
G6-46 - A Zabarauskas G6-46 -<br />
H1-60<br />
SW INTEGRATION SW PROJECTS SUPPORT<br />
GF Booth G6-46 DR Broz G6-46 Corr Control X<br />
MD LeClair H1-60 - ML DeWitt G6-46 = WRAP DMC G6-51 _X=<br />
DW Mer_tz_ H1-6Q_- , rG ErnenherL G6-46 JR McGee G6-47<br />
CR Nash H1-60 TM Greager G6-46 - E Pennala E2-30<br />
TR Pauly G6-46 RL Louie G6-46 DR Porten G6-47 ^<br />
Jt Stroup G6=46 KE Smith--- G6-46 JM Seimer G6-47 -<br />
KM Weingardt H1-60 ^- HE Wellsfry G6-46 ^ I WW Olson N1-83 =<br />
StLKt 1 AK 1 tJ rKUIaKHI94 U 1 RC.KJ<br />
RL Anderson G6-45 RJ Roberts N3-13 DA Smith _G6-16<br />
Al Ball H1-60 = JG Riddelle H5-33 - -<br />
BJ Gire<br />
G6-46 BA Mayancsik H5-33<br />
SA Niebel G6-46 MM McCarthy N3-13 -<br />
I JB Myers G6-46<br />
COMMENTS TO LEAD ENGINEER BY:<br />
SPECIAL INSTRUCTIONS:<br />
QA RECORD - YES - NO<br />
F-28<br />
_
Westinghouse <strong>Hanford</strong> Company<br />
2355 Stevens Drive<br />
Richland, Washington 99352<br />
Attention: Mr. Dewey Burbank, H1-60<br />
WHC-SD-W100-TI-003 Rev. 0<br />
. .__^ . ,.. -<br />
Sublect: cUCKolymer lmmobtlization Tech.<br />
Waste Form Qualification Testing<br />
Purchase Order No. MMW-SVV-277587<br />
Stock Reference No. 6996<br />
Gentlemen:<br />
November 4, i9it<br />
92RAC WH008<br />
9205883<br />
Enclosed please find a copy of our Progress Report No. 3 for the subject project.<br />
This report represents progress through October, 1992.<br />
Should additional information be required, please advise.<br />
RAC/kh<br />
Enclosure<br />
c: Westinghouse <strong>Hanford</strong> - Attn: G.M. Wemhoff, Buyer<br />
S.O. 6996<br />
T. i.itcfiney<br />
-Tickier 1211192 w%report<br />
Very truly yours,<br />
Russell A. Czellath<br />
Manager-Contracts<br />
R :'sq; ; ^0<br />
^py 2 41992<br />
Stock Equipment Company • 16490 Chillicothe Road • Chagrin Falls, Ohio 44022-4398, U.S.A. • (216) 543-6000 • Telex 196071<br />
A Unit of General Signal Telefax ( 216) 543-6678<br />
F-29
Stock Equipment Company WHC-SD-W100-TI-003 Rev. 0<br />
WESTINGHOUSE HANFORD COMPANY<br />
STOCK EQUIPMENT CO.<br />
POLYMER IMMOBILLIZATION TECH.<br />
WASTE FORM QUALIFICATION TESTING<br />
MONTHLY PROGRESS REPORT<br />
NO. 3<br />
THROUGH OCTOBER, 1992<br />
Stock Equipment Company<br />
Westinghouse <strong>Hanford</strong> Purchase Order No. MMW-SW-277587<br />
Stock Order No. 6996<br />
F-30
--- - ftCR-e4Uip1P1eFf Company WHC-SD-W100-TI-003 Rev. 0<br />
1.0 SUMMARY<br />
2.0 SCHEDULE<br />
BAR CHART SCHEDULE<br />
TABLE OF CONTENTS<br />
F-31<br />
PaEg<br />
1,2&3<br />
4<br />
5
1.0 SUNYNARY<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Weeks of September 28. 199 2 and October 5. 1992<br />
I started and completed the assays for the following leach time<br />
points: 30 second, 2 hour, 7 hour, 24 hour, 2 day, 3 day, 4<br />
day, and 5 day. The leachants were assayed for the following<br />
elements: Cesium, Cobalt and Strontium. I have calculated the<br />
leachability index numbers for the above time points. The 18<br />
day leach interval has arrived and the samples were changed.<br />
= The samples are intact; no apparent degradation. I have<br />
assayed the 18 day leach interval. The leachability<br />
calculations have been updated with the 18 day leach interval.<br />
------------<br />
Week of October 19. 1992<br />
I started the thermal cycling portion of the test. The thermal<br />
__-----cymli^g-test-will be complete early November. The compressive<br />
strength results will be noted in the November progress report.<br />
Stock contracted with a consultant from the University of Akron<br />
Polymer Department to discuss the problem in trying to solidify<br />
TYPE 2 & 4 surrogate waste streams. The consultant has<br />
S'2ige
WHC-SD-W100-TI-003 Rev. 0<br />
Russ Czellath -2- November 2. 1992<br />
--------------I-also-tr3Ed-more--experimentG-involving TYPE 2 surrogate waste.<br />
I adjusted the pH of the waste to 10.5 and tried to solidified<br />
it. The best result obtained was a gell. I also tried the<br />
same thing to surrogate waste TYPE 4 with the same results. I<br />
tried to minimize the amount of energy input for mixing the<br />
waste. The theory here is that oxygen may inhibit<br />
polymerization, so I decided to hand mix two (2)<br />
se3idificatio.^.s, a type 2(pH 10.5) and a type 4(pH 10.5)<br />
surrogate. These solidifications have obtained the best gell<br />
of all the variations tried (these gells are very firm).<br />
I.. _y<br />
p*:;<br />
I ordered copper sulfate to attempt solidification with the<br />
derakane resin; it's possible the compound that the copper is<br />
in might be inhibiting the polymerization. I have ordered<br />
another polymer that is more reactive than the current polymer<br />
being used for this testing program. Early indications show<br />
that TYPE 4 surroaate waste can be solidified in this new<br />
polymer. I have been working on optimizing the loading ratio<br />
(waste to binder) for TYPE 4 surrogate waste. The following<br />
experiments have been performed:<br />
ID BINDER<br />
(gms)<br />
A 100<br />
B --100<br />
C --- -<br />
lnn<br />
D 100<br />
CATALYST PROMOTOR WASTE<br />
(gms) (gms) (gms)<br />
2.5 1.0<br />
- - 2,5 0.2<br />
-2=5<br />
0.4<br />
2.5 1.0<br />
E 100 2.5 1.0<br />
100<br />
200<br />
200<br />
200<br />
150<br />
SPEED POWER<br />
(rpm) (watts)<br />
1800 6.1<br />
1799 8.4<br />
1815 8.1<br />
1000 3.8<br />
1000 2.2<br />
Sample "A° set up rock hard in a very few minutes, this waste<br />
had a pH adjustment of 10.5. All the samples after "A" have no<br />
pH adjustment. Sample "B" has set up but not rock hard.<br />
Sample "C" a little better results than "B". Sample "D"<br />
results are the same as "C". Sample "E" set rock hard. I can<br />
only assume that the maximum waste to binder loading will be<br />
greater than 1.5/1 but less than 2/1. Type 2 surrogate waste<br />
solidification is promising but there still maybe the problem<br />
of copper concentration.<br />
F-33
WHC-SD-WIOO-TI-003 Rev. 0<br />
-3- Nov<br />
I assayed type 2,3,4 surrogate waste for it's copper<br />
concentration. Type 2,3 surrogate wastes fall in line with the<br />
reported concentration supplied by Westinghouse Handford. Type<br />
4 surrogate waste was approximately 30 percent higher than the<br />
reported concentration provided by Westinghouse Handford. The<br />
results are as follows:<br />
TYPE 2 - 127,875 ppm<br />
TYPE 3 - 108,747 ppm<br />
TYPE 4 - 87,175 ppm<br />
F-34
Stock Equipment Company<br />
3:0 -SCFIEDLTLE<br />
WHC-SD4100-TI-003 Rev. 0<br />
Scheduled Actual<br />
Activity Date Date<br />
- Prepare Work Plan 08/01/92 08/01/92<br />
- Submit Work Plan 08/01/92 08/01/92<br />
- Approve Plan 08/10/92 08/10/92<br />
- Develop Formulations 08/21/92 08/21/92<br />
- Prepare Specimens 09/01/92 09/16/92<br />
Lab - Anaiysis 17/10i^<br />
Final Report 12/23/92<br />
F-35<br />
,...4.-
0<br />
co<br />
Cr'<br />
°``^,.<br />
04-Nov-92<br />
PROUECT SCHEDULE<br />
WESTINGHOUSE<br />
HANFORD COMPANY<br />
P.O. MMW-SVV-277587<br />
STOCK ORDER: 6996<br />
TASK<br />
PREPARE WORK PLAN<br />
SUBMIT WORK PLAN<br />
APPROVE WORK PLAN<br />
DEVELOP FORMULATIONS<br />
PREPARE SPECIMENS<br />
LABORATORY ANALYSIS<br />
FINAL REPORT<br />
MONTHLY PROGRESS REPORT<br />
PREPARED BY: RUSS A. CZELL.ATH<br />
JUL 1 A UG<br />
^<br />
STONJK EOUIPMEINT COMPANY<br />
1992<br />
E P O C T N O V I D E C<br />
0<br />
3r x<br />
c<br />
1/1<br />
3r6<br />
. 0<br />
^<br />
..<br />
0 w<br />
m <<br />
0
THERMAL CYCLING SAMPLES<br />
BEFORE THE START OF THE TEST<br />
.. 1 !.4 U..<br />
SAMPLE ID HEIGHT.(in) DIAMETER (in) WEIGHT (gms) DENSITY (gnns/cc) DENSITY<br />
avg<br />
ILi-11 1.937 1.418 56.112 1.12<br />
1-1-12 1.915 1.420 55.01 1.11 1.11<br />
1-1-13 1.919 1.423 54.85 1.10<br />
1.3-11 2.039 1.452 78.09 1.41<br />
1 . 3-12<br />
L.3-13<br />
2.063<br />
2.019<br />
1.445<br />
1.447<br />
77.96<br />
77.25<br />
1.41<br />
1.42<br />
1.41 = C -)<br />
v°,<br />
0<br />
^<br />
g<br />
w<br />
^.<br />
t<br />
o<br />
V L.7-11 2.035 1.464 84.9 1.51<br />
°<br />
1-7-12 2.036 1.458 84.72 1.52 1.52<br />
L7-13 2.009 1.455 83.65 1.53 o<br />
<<br />
0
co<br />
SAMPLE ID<br />
L1-17<br />
L1-'18<br />
L1-'19<br />
L3-17<br />
L3-118<br />
L3-19<br />
L7-17<br />
L7-18<br />
L7-19<br />
K,.<br />
'^;. ^c<br />
RADIATION SAMPLES BEFORE<br />
THE START OF THE TEST<br />
DIAMETER (in) HEIGHT (in)<br />
1.424 1.884<br />
1.426 1.839<br />
1.430 1.892<br />
WEIGFIT (gms) DENSITY (gms/ccc DENSITY' (gms/cc)<br />
AVG<br />
54.67 1.11<br />
53.64 1.12 1.11<br />
55.17 1.11<br />
1.454 2.048 73.55 1.32<br />
1.456 2.082 76.93 1.35 1.35<br />
1.454 2.076 77.67 1.38<br />
1.464 2.052 82.68 1.46<br />
1.461 2.049 86.57 1.54 1.51<br />
1.461 2.027 84.90 1.53<br />
s<br />
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,..<br />
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0<br />
^<br />
C.<br />
0<br />
w<br />
z<br />
m <<br />
0
BIODEGRADATION SAMPLES<br />
BEFORE THE START OF TEST<br />
SAMPLE ID DIAMETER (in) HEIGHT (in) WEIGHT (gms) DENSITY (gms/cc DENSITY<br />
AVG<br />
L1-14 1.423 1.846 53.38 1.11<br />
Li -15 1.422 2.022 56.84 1.08 1.08<br />
L1-16 1.425 1.948 53„37 1.05<br />
L3-14 1.4$8 2.060 73.24 1.30<br />
L3-15 1.453 1.996 74.66 1.38 1.36<br />
1-3-16 1.461 2.023 76.85 1.40<br />
L7-14 1.430 1.981 78.31 1.50<br />
L7-15 1.425 2.006 81.68 1.56 1.47<br />
'O 1-7-16 1.430 1.865 66.84 1.36<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
---CAORRFSP-OMDEI`ICE ^?ISTRIBUT1ON Cl]VERSHFFT<br />
- Author Addressee Correspondenoe No.<br />
RA CZELLATH/STOCK DA BURBANK/WHC 9208502<br />
s:^ieatT- STP.CK-POLY-MER-IMMOLBILIZ_AT10N TELH, WASTE FORM I1llAL1FICATION-TESTINGPllRCHASE<br />
ORDE-ft-NO. MMW-SVY-277587--STOCK--REFERENrE NO. FoaF<br />
9XnXhG9cnI rnvact.i cnaanc¢nana wnnr rnvucul wninv6<br />
.ia cwer.son G6-46 - -- -- - TA CarlcIIn G6-46-------- KP $rown G6-47<br />
DE Ball G6-46 _ AW Hinkle G6-46 SE Bussman G6-47 -<br />
SR Briggs G6-47 _ FH Lee G6-46 - C Malstrom G6-47 -<br />
JE Filip G6-47<br />
JB Payne G6-46 SW McKinley G6-47 -<br />
DR Lucas G6-46 ^ JG Starkey G6-46 GC Rice G6-47 -<br />
CA Petersen H1-60 _X WR Swita G6-46 ^ BL Trumpour G6-47<br />
TL Yount H1-60 =X_ RR Wyer G6-46 =X= -<br />
WRAP TECHNOLOGY SW SYSTEMS ENGINEERING SW SYSTEMS ENGINEERING<br />
CJ Benar H1-60 X EG Berglin G6-46 _ VP Ocampo G6-46 _<br />
DA Burbank _ N1-6n -X _ KJ Hull<br />
G6-46 _ DT Ruff G6-46 _<br />
BF Campbell H1-60<br />
RM Horgus H1-60 _ RA Sexton H1-60 _<br />
JD Keck G6-46 SL Kooiker G6-46 JR Weber G6-46<br />
CE McDonald- H1-60 _ DL Lamberd Hi-60 - JR Weidert G6-46 -<br />
JL Nelson H1-60 = ML Lee G6-46 - RH Winkleman G6-46 -<br />
KE Parker H1-60 KJ Leist G6-46 - A Zabarauskas G6-46<br />
RM Ybarra H1-60<br />
NJ Monroe H1-60<br />
n<br />
SW INTEGRATION SW PROJECTS SUPPORT<br />
GF Booth G6-46 _ DR Broz G6-46 _ Corr Control _X<br />
MD LeClair H1-60 ML DeWitt G6-46 WRAP DMC G6-51 X<br />
DW Mertz H1-60 EG Erpenbeck G6-46 JR McGee G6-47. _<br />
CR Nash H1-60 TM Greager G6-46 E Pennala E2-30 _<br />
TR Pauly G6-46 RL Louie G6-46 DR Porten G6-47 _<br />
JL Stroup G6-46 KE Smith G6-46 JM Seimer G6-47<br />
KM Weingardt H1-60 HE Wellsfry G6-46 _ WW Olson N1-83 _<br />
RL Anderson G6-45 = RJ Roberts N3-13 -<br />
I DA Smith_ _G6-16 _X =<br />
AI Ball H1-60<br />
JG Riddelle H5-33<br />
. . .<br />
ts^ Gi uiG6-4'<br />
re<br />
BA Mayan^^iw ---' H-33<br />
SA-Niebel --------G6-46 MM McCarthy- ---N3-17 -<br />
JB Myers G6-46<br />
OL Kruger H5-33<br />
COMMENTS TO LEAD ENGINEER BY:<br />
SPECIAL INST RUCTIONS:<br />
QA RECORD YES NO
' iO`F*'P\^<br />
Westinghouse <strong>Hanford</strong> Company<br />
2355 Stevens Drive<br />
Richland, Washington 99352<br />
WHC-SD-W100-TI-003 Rev. 0 9208502<br />
Lf= Attention: Mr. Dewey Burbank, H1-60<br />
0^^.<br />
Subject: STOCK Polymer Immobilization Tech.<br />
Waste Form Qualification Testing<br />
Purchase Order No. MMW-SVV-277587<br />
Stock Reference No. 6996<br />
Gentlemen:<br />
December 1, 1992<br />
92RAC WH007<br />
Enclosed please find a copy of our Progress Report No. 4 for the subject project.<br />
This-reportrepresents-progress through ^:rember, 19Q2.<br />
Should additional information be required, please advise.<br />
RAC/kh<br />
Enclosure<br />
c: Westinghouse <strong>Hanford</strong> - Attn: G.M. Wemhoff, Buyer<br />
S.O. 6996<br />
T. Litchney<br />
Tickler 1/1/93 w/report<br />
Very truly yours,<br />
RussellA. Czellath<br />
Manager-Contracts<br />
RECEIVED<br />
WRAP DMC<br />
t?EC 141942<br />
Stock Equipment Company • 16490 Chillicothe Road • Chagrin Falls, Ohio 44022-4398, U.SA • (216) 543-6000 • Telex 196071<br />
A Unit of General Signal<br />
Telefax (216) 543-6678<br />
F-53
Stock Equipment Company<br />
WHC-SD-W100-TI-003 Rev. 0<br />
WESTINGHOUSE HANFORD COMPANY<br />
STOCK EQUIPMENT CO.<br />
POLYMER IMMOBILLIZATION TECH.<br />
WASTE FORM QUALIFICATION TESTING<br />
MONTHLY PROGRESS REPORT<br />
NO. 4<br />
THROUGH NOVEMBER, 1992<br />
Stock Equipment Company<br />
Westinghouse <strong>Hanford</strong> Purchase Order No. MMW-SW-277587<br />
Stock Order No. 6996<br />
F-54
Stock Equipment Company<br />
1.0 SUMMARY<br />
WHC-SD-W100-TI-003 Rev. 0<br />
TABLE OF CONTENTS<br />
2.0 SCHEDULE 4<br />
BAR CHART SCHEDULE<br />
F-55<br />
Pam<br />
1,2&3
Stock Equipment Company<br />
1.0 SUq91RY<br />
November 5, 1992<br />
The 45 day leach interval.<br />
WHC-SD-W100-TI-003 Rev. 0<br />
The samples are in intact with no apparent degradation. They<br />
---- ------ -- -- will be assayed for cesium, cobalt, and strontium. The current<br />
leachability calculations have been included.<br />
---.-<br />
November 6, 1992<br />
The Thermal Cycling Test for samples L1, L3, and L7 were<br />
completed. The results are as follows:<br />
SAMPLE<br />
ID<br />
HEIGHT<br />
(inch)<br />
DIA.<br />
(inch)<br />
WEIGHT<br />
( grams)<br />
DENSITY<br />
( gm/cc)<br />
LOAD<br />
(lbs)<br />
FORCE<br />
(psi)<br />
L1-11 1.954 1.418 56.11 1.11 17,520 11,094<br />
-Li-12 1.926 3.425 55.01 1.09 17,560 11,010<br />
L1-13 1.913 1.42i 54:84 1.10 17,600 11,082<br />
L3-11 2.046 1.453 77.51 1.39 7,200 4,342<br />
L3-12 2.113 1.453 77.22 1.34 8,400 5,066<br />
L3-13 2.044 1.454 76.71 1.38 9,840 5,926<br />
L7=11 2.049 1.456 81.59 1..46 1,400 841 -<br />
L_7-12 2.025---- 1.446 81.01---- 1.49----- 1,720 1,047<br />
L7-13 1.987 1.448 80.01 1.49 1,780 1081<br />
November 17. 1992<br />
Thermal cycling was initiated for the samples L5 (TYPE 2) and<br />
L9 (TYPE 4).<br />
Week of November 9. 1992<br />
Surrogate waste samples Type 2 and Type 4 were sent out to have<br />
the following tests performed:<br />
irrariiatinn<br />
.......... .. .,<br />
biodegradation, and<br />
TCLP.<br />
-i<br />
F-56
Stock Equipment Company<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Due to combustible considerations the samples prepared for TCLP<br />
were ground-at-Steck prior to submittal to the contracted<br />
laboratory.<br />
Samples L5 and L9 (Type 2 and Type 4) were spiked with cobalt,<br />
cesium, and strontium. Then casted into 1.5" by 2" cylinders.<br />
An exotherm profile on the prepared samples was obtain.<br />
November 16. 1992<br />
The leachability study was started for surrogate waste Types 2<br />
and 4. The following time points have been pulled:<br />
30 seconds,<br />
2 hour,<br />
5 hour,<br />
-24_hnur,<br />
2 day,<br />
3 day,<br />
4 day, and<br />
5 day.<br />
The 90 day sample will be pulled on February 15, 1993. An<br />
amendment to the original report will follow within a week of<br />
the 90 day leach interval for TYPE 2 and TYPE 4 surrogate waste<br />
streams.<br />
All time points up to and including 5 days have been assayed.<br />
Leachability calculations are in progress.<br />
Samples of surrogate wastes TYPE a. and-TYPE-1_were-successfully<br />
solidified in the alternate polymer, exotherm data was<br />
recorded. The formulations are identical to the one used for<br />
the sample preparation for all the testing. I also have done<br />
an exotherm profile on TYPE 4 surrogate waste.<br />
November 23, 1992<br />
TCLP extraction was started on L3, L5, L7 and L9 samples. The<br />
samples will be assayed for their metals.<br />
F-57<br />
--M@---
Stock Equipment Company<br />
FORMULATION DATA FOR EXOTHERMS<br />
Sample Binder<br />
(gms)<br />
WHC-SD-W100-TI-003 Rev. 0<br />
BPO<br />
(gms)<br />
DMT<br />
(gms)<br />
Waste<br />
(gms)<br />
Speed<br />
(rpm)<br />
Power<br />
watts<br />
peak<br />
tmp °C<br />
Control 100 2.58 0.1 0 500 0.1 105<br />
LETF 100 2.53 0.1 200 1800 14.6 67<br />
TYPE 2 100 T.50 2.0 100 1800 `` 11 5.7 70<br />
TYPE 3 100 2.60 0.1 200 1797 6.4 54<br />
TYPE 4 1 00 5. 1 6 1.1 150 180 3 5.7 64<br />
All the samples have been returned from the irradiation testing<br />
facility. The samples were tested for compressive strength.<br />
The compressive strength has increased for the samples tested.<br />
This increase is due to the probability of the embrittlement of<br />
the vinyl esther resin. Reference the attached Data Sheet for<br />
the results.<br />
We are currently collecting data toward preparation of the<br />
final report which will include the December Monthly Report.<br />
Awaiting purchase order revision concerning Westinghouse <strong>Hanford</strong> decision<br />
to proceed with additional testing.<br />
F-58<br />
...d=.
2a0 SCHEDULE<br />
Activitv<br />
- Prepare Work Plan<br />
- Submit Work Plan<br />
- Approve Plan<br />
- Develop Formulations<br />
Prepate Specimens<br />
- iab - Analysis<br />
- Final Report<br />
WHC-SD-W100-TI-003 Rev. 0<br />
--4 F-59<br />
Scheduled<br />
D ate<br />
08/01/92<br />
08/01/92<br />
08/10P92<br />
08R1/92<br />
09/01/92<br />
i2ii0iy2<br />
1223/'92<br />
Actual<br />
Date<br />
08/01/92<br />
08/01/92<br />
08/10/92<br />
0821/92<br />
09/16N2
^<br />
Ti<br />
rn<br />
0<br />
01-Dec-92<br />
PROJECT SCHEDULE<br />
WESTINGHOUSE<br />
HANFORD COMPANY<br />
P.O. MMW-SW-277587<br />
STOCK ORDER: 6996<br />
TASK<br />
PREPARE WORK PLAN<br />
SUBMIT WORK PLAN<br />
APPROVE WORK PLAN<br />
DEVELOP FORMULATIONS<br />
PREPARE SPECIMENS<br />
LABORATORY ANALYSIS<br />
FINAL REPORT<br />
^t,y<br />
MONTHLY PROGRESS REPORT<br />
PREPARED BY: RUSS A. CZELLATH<br />
1992<br />
J U L A U G S E P O C T<br />
0<br />
!;` f<br />
STOCK EQU IPMENT COMPANY<br />
N O V I D E C<br />
E<br />
x<br />
N<br />
S<br />
0<br />
21<br />
0<br />
w<br />
m<br />
<<br />
0
T 1<br />
o+<br />
THERMAL CYCLWG SAMPLES<br />
BEFORE THE STARfOF THE TEST<br />
SAMPLE ID HEIGHT (Inp DIAMETER pn) WEIGHT (pms) DENSITY (pms/cc) DENSITY (pms/cc)<br />
avq<br />
LI-11 1.937 1.418 56.12 1.12<br />
11-12 1.915 1.420 55.01 1.11 1.11<br />
11-13 1A19 1.423 54.85 1.10<br />
1341 2.039 1.452 78.09 1.41<br />
L3-12 12.063 1.445 77.98 1.41 1.41<br />
1.3-13 2.019 1.447 77.25 1.42<br />
17-11 2.035 1.484 64.9 1.51<br />
17-12 2.036 1.458 84.72 1.52 1-52<br />
1-7-13 2.009 1.455 83.65 1.53<br />
THERMAL CYCLING SAMPLES<br />
AT THE COIMPLETION OF THE TEST<br />
SAMPLE ID HEIGHT QMI DIAMETER (IN) WEIGHT (9ms) DENSITY (pms/cc) LOAD (Ibs)<br />
11-11 1.954 1.416 56.11 1.11 17520<br />
L I-12 1.926 1.425 55.01 1.09 17560<br />
11-13 1.913 1.422 54.84 1.1 17800<br />
L3-11 2.046 1.453 77.51 1.39 7200<br />
L3-12 2.113 1.453 77.22 1.34 8400<br />
L3-13 2.044 1.454 76.71 1.38 9840<br />
L7-11 2.049 1.456 81.59 1.48 1400<br />
L7-12 2.028 1.446 81.01 1.49 1720<br />
17-13 1.967 1.448 80.01 1.49 1780<br />
COMPRESSIVE STRENGHT (psq<br />
11094<br />
11010<br />
11082<br />
4342<br />
5066<br />
5928<br />
841<br />
1047<br />
1081<br />
..^
"<br />
N<br />
^^.<br />
U<br />
w<br />
w<br />
V<br />
w<br />
0<br />
WE:STING1-'^OUSE HANDFORD<br />
LETF SURROGATE WASTE<br />
0.0 19.9 40.8 61.8 83.9 106.0 130.3 154.7 180.2 205.8 227.5<br />
TIME minutes<br />
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OI<br />
80<br />
70<br />
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WESTINGHOUSE HANDFORD<br />
TYPE 2 SURROGATE WASTE<br />
WASTE LOADING 1 TO 1<br />
. 00 27.65 56.4.1 13627 114313 1 37 .x;fl 1 R1 AS 1 R7 4-q 91 d 19<br />
TIME minutes<br />
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TYPE 3 SURROGATE WASTE<br />
WASTE LOADING 2TO 1<br />
20 -<br />
15 0.0 16.9 34.4 52.6 71.2 90.5 110.3 130.7 151.9 173.6 195.0<br />
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65 --<br />
60<br />
55<br />
50<br />
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20<br />
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15 0.0 16.9 34.4 52.6 71.2 90.5 110.3 130.7 151.9 173.6 195.0<br />
TIME minutes<br />
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CONTROL 470-45 RESIN<br />
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SAMPLE ID<br />
Li-117<br />
L1-118<br />
L1-19<br />
L3-17<br />
L3-18<br />
L3-19<br />
L5-17<br />
L5-18<br />
L5-19<br />
^<br />
^ L7-17<br />
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L7-16<br />
L7-19<br />
L9-17<br />
L9-18<br />
L9-19<br />
RADIATION SAMPLES AFTER TEST<br />
DIAMETER (cm) HEIGHT (cm) WEIGHT (gms)<br />
AVG<br />
DENSITY (gms/cc) DENSITY (gms/cc) LOAD (Ibs)<br />
3.640 4.830 54.64 1.0871 17720<br />
3.640 4.745 53.61 1.0857 1.0928 17520<br />
3.615 4.860 55.15 1.1056 17520<br />
3.670 5.250 72.79 1.3107 5920<br />
3.700 5.320 76.25 1.3330 1.3253 10320<br />
3.7135 5.335 76.62 1.3321 9320<br />
3.615 4.965 63.43 1.2311 11400<br />
3.6'15 4.940 62.71 1.2368 1.2367 7880<br />
3.620 4.815 61.56 1.2422 9640<br />
3.710 5.230 80.95 1.4318 1480<br />
3.690 5.215 84.07 1.5075 1.4801 1520<br />
3.680 5.160 82.39 1.5012 1800<br />
3.810 5.105 84.05 1.4441 3840<br />
3.820 4.850 79.73 1.4254 1.4409 3440<br />
3.765 5.050 81.70 1.4532 6240<br />
,pu'1r<br />
.^i<br />
COMPRESSIVE AVG<br />
STRENGTH (psi) STRENGT<br />
10986<br />
10862 10954<br />
11013<br />
3610<br />
6192 5127<br />
5577<br />
7087 E<br />
4953 6028 n<br />
6043 rn<br />
883 O<br />
917 964 °0<br />
1092<br />
0<br />
2173<br />
1936 2575 ;o<br />
3616<br />
0
WHC-SD-W100-TI-003 Rev. 0<br />
wnplM WEIGHT HEIGHT DIAMEfER DENSRY AVG. LOAD PSI AVG.<br />
Oremi cm em grams/cc LBS 6vo day<br />
comprMdvw<br />
s1nnOM<br />
1.1-1 51.4 4.540 3.612 1.1049 17160 10804<br />
L1-2 68.6 5,116 3.612 1.1217 17160 10604<br />
L1 J 51.0 4.502 3.609 1.1074 17120 10797<br />
Lt-4 55.3 4.869 3.611 1.1090 17360 10936<br />
---- L+.-5 51..' 4453 3.611 1.1261 17380 10936<br />
U$-_ __Sl"9 S.r_24 --- 3.809- ----7:146D 1.12- ---17400- i 0974 iw26<br />
L1-7 56.3 4.923 3.811 1.1167 17480 11012<br />
1.1-8 54.9 4.796 3.811 1.1178 17480 11012<br />
L?a 56.3 4 .:94. 3.^'^••7 1.1039 17520 11062<br />
Lt-10 66.7 4.968 3.609 1.1157 17320 10923<br />
1.3-1 73.9 5.112 3.618 1.4061 3520 2209<br />
1.3-2 72-3 5.230 3.616 1.3490 3600 2262<br />
1.3.1 71.9 5.100 3.614 1.3743 3680 2314<br />
1.34 71.1 5.067 3.678 1.3207 4320 2623<br />
L7-5 . 73.3 5.245 3.663 1.3262 4240 2596<br />
.,a.--.<br />
71.7 5.108 3.868 1.3284 1.33 4280 2613 2472<br />
--- - 1.3-7 ---- ---- 67.1 5.024 3.680 1.2557 3920 2378<br />
13-8 72.9 5.212 3.653 1.3345 4180 2561<br />
134 71.2 5.065 3.883 1.3106 4400 2665<br />
'-'-' 1.3-10 72.3 5.194 3.665 1.3195 4080 2495<br />
L8-1 82.7 4.885 3.665 1.6047 1840 1125<br />
1.6-2 80.7 4.745 3.655 1.6210 1760 1082<br />
1.53 82.7 4.890. 3.660 1.6075 1800 1104<br />
1.54 80.6 4.865 3.645 1.5877 1800 1113<br />
1.5-5 82.3 4.850 3.860 1.6129 1.63 1800 1104 1065<br />
1.5-6 90.3 5.175 3.650 1.6676 1680 1036<br />
1.5-7 87.4 5.095 3.610 1.6760 1680 1059<br />
1-54 84.9 5.000 3.640 1.6317 1720 1066<br />
L3-9 - - -- O5.8 5.033 3.625--- ..,,.... 1720 1075<br />
t3-10 77.3 4.890 3.695 1.5370 2680 1612<br />
L?-? 77.2 5.001 3.614 1.5049 2480 1560<br />
1.7-2 72.8 4.829 3.815 1.4688 2440 1534<br />
1.7.7 76.4 4.837 3.617 1.5372 2400 1507<br />
1.74 75.9 4.935 3.611 1.5018 1600 1008<br />
1.7.5 73.1 4.976 3.632 1.4179 2440 1519<br />
1.7-0 72.6 4.724 3.627 1.4874 1.48 2200 1374 1411<br />
1.7-7 77.4 5.017 3.632 1.4891 2240 1396<br />
1.7-0 75.8 5.078 3.627 1.4447 2380 1474<br />
1.7-0 76.0 5.017 3.614 1.4767 1800 1132<br />
1.7-10 72.6 4.956 3.617 1.4257 2560 1607<br />
1.9-1 63.3 4.725 3.550 1.3535 1640 1089<br />
19-2 58.3 4.890 3.595 1.1746 1640 1042<br />
1.9.1 74.3 4.805 3.650 1.4506 1520 937<br />
L9-4 70.2 4.845 3.635 1.3962 1600 905<br />
1.9-5 64.7 4.850 3.630 1.3445 1.36 1600 997 941.7<br />
1.94 55.6 4.500 3.570 1.2343 1360 877<br />
1.9-7 78.7 4.990 3.660 1.4991 1320 809<br />
L9-0 70.6 4.990 3.595 1.3939 1400 890<br />
L9-0 74.7 4.950 3.6880 1.4344 1400 859<br />
1.9-10 69.9 4.990 3.575 1.3955 1400 900<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
APPENDIX G<br />
OVERVIEW OF SOLIDIFICATION TECHNOLOGIES<br />
This is an internal WHC memo report that was prepared as a review of all<br />
available solidification technologies, important processing considerations,<br />
general advantages and disadvantages of various technologies. The report is<br />
not specific to WRAP 2A and is intended to provide general background needed<br />
to begin evaluating the various waste forms.<br />
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Waste immobilization matrices fall into several general categories. Inorganic<br />
--- binders, thermoplastics, organic polymers, ceramics, and glasses are the<br />
matrices that have been widely used for radioactive waste immobilization.<br />
Inora anic Binders<br />
Inorganic binders are commonly used materials for waste stabilization and<br />
immobilization. They are inexpensive, readily available, and well established<br />
in the radioactive waste management field.<br />
Portland cement<br />
Portland cement is the most common immobilization matrix. It is the same<br />
material used in construction of concrete structures. Portland cement<br />
consists mostly of hydrated calcium silicates, with some aluminates and<br />
magnesium content. The calcium hydroxide content causes portland cement to<br />
exhibit a high pH. The three predominant types are described below.<br />
Type I (ordinary)<br />
Ordinary portland cement ( OPC) is widely used for construction purposes. It<br />
requires about one month to cure to full strength.<br />
Type II ( sulfate-resistant)<br />
Type II cement is resistant to sulfate ions. This gives increased durability<br />
in saline environments.<br />
Type III ( high-early-strength)<br />
Type III cement is ground more finely thus increasing its reactivity. High<br />
early strength creates higher curing exotherms.<br />
Pozzolanic cement additives<br />
Pozzolanic additives are used to modify the reactivity, curing time, and<br />
ultimate strength of cement grout. Two commonly used additives are ground<br />
blast furnace slag, and pulverized coal fly ash.<br />
Blast furnace slag<br />
Blast furnace slag his a higher silica content that cement. This decreases<br />
the reactivity and eliminates the high curing exotherm. It also increases the<br />
curing time required to attain full strength.<br />
Pulverized fly ash<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Pulverized fly ash contains mostly silica and alumina, with very little<br />
calcium. The lack of calcium requires addition of lime or cement to activate<br />
this material. Fly ash can be added in ratios as high as 10:1 and still<br />
obtain a suitable final waste form.<br />
Gypsum cement<br />
Gypsum cement is composed of hydrated calcium sulfate. It has a lower<br />
compressive strength than portland cement. The elimination of calcium<br />
hydroxide gives this material a lower pH than OPC.<br />
Plaster of paris<br />
Plaster of paris is the most recognizable gypsum cement. This same material<br />
is also used in wallboard.<br />
Envirostone"'")<br />
This material is a proprietary mixture based on gypsum cement. The<br />
proprietary additives are claimed to make this mix more compatible with<br />
organic and acidic wastes.<br />
Modified cements<br />
Cement mixtures can be modified to enhance their ability to incorporate<br />
difficult wastes, and to increase their resistance to loss of soluble waste<br />
constituents through leaching.<br />
Physical absorbents<br />
Physical absorbents are used to incorporate non-hydraulic materials such as<br />
_liquid arganics _into the -waste matrix.<br />
Polymer impregnated cement<br />
Polymer impregnation is a method to decrease leachability be filling the<br />
interstitial pores with water-resistant polymer.<br />
Thermoplastic Polymers<br />
Thermoplastic polymers are a class of materials that melt at elevated<br />
temperatures. These matrices can be used to immobilize materials through<br />
micro- and macro- encapsulation.<br />
Bitumen ( asphalt)<br />
Bituminous polymers are familiar materials used in the construction of roads,<br />
and in the roofing industry. They are produced from crude oil, and can have<br />
varying physical properties.<br />
Straight run<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
This is the raw material as is comes directly from the distillation column.<br />
It has a low softening temperature, high penetration, and low compressive<br />
strength.<br />
Pitch<br />
This is straight-run bitumen that has been<br />
solvents. The material solidifies when the<br />
controls are required.<br />
Oxidized<br />
liquefied by dilution with organic<br />
solvent evaporates. Solvent vapor<br />
Oxidized bitumen is produced by blowing air through straight-run material. It<br />
is commonly used for roofing applications. This material is stronger, harder,<br />
and less sensitive to temperature changes than straight-run. This results in<br />
hig,i'cr nieitiny^ p"uint proccssing temperatures.<br />
Cracked<br />
Cracked bitumen is more fe^Ci *ive to temperature changes than other types.<br />
This imparts a quick-hardening nature, giving high strength combined with low<br />
penetrat-ion--and--a high softening point. Cracked bitumens can become brittle<br />
at low temperature.<br />
Emulsions<br />
Bitumen emulsions are similar to pitch, except the solvent is aqueous with<br />
surfactants to prevent phase separation. The material solidifies when the<br />
wat2r--i-s-evaporated.<br />
Sulfur<br />
Sulfur has several possible uses in radioactive waste treatment in WRAP Module<br />
2A. It can be used as a solidification matrix, a hardener, and as an amalgam<br />
for mercury treatment.<br />
Immobilization matrix<br />
Sulfur "cement" can be used in a manner similar to other thermopolymers. It<br />
exhibits high strength and low penetration. Vapor controls are necessary and<br />
there is some concern about potential phase changes in the final waste form<br />
causing ioss of structural properties over time.<br />
Bitumen hardener<br />
_-____Sulfur can be added to straight-run bitumen to increase its hardness and<br />
compressive strength. Sulfur hardening of bitumen is a non-reversible<br />
process.<br />
Polyethylene<br />
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WHC-SD-W100-TI-003 Rev. 0<br />
Polyethylene (and other thermoplastics) can be used to encapsulate wastes, by<br />
using melt processes similar to those used for bitumens. The molten material<br />
is mixed with waste and allowed to cool, forming a solid plastic block.<br />
Encapsulation<br />
Macro-encapsulation is used to isolate large waste items from the surroundings<br />
by use of primary physical barriers. Thermoplastics are well suited for this<br />
application. Micro-encapsulation involves the intimate mixing of waste and<br />
polyethylene, as in a screw-type extruder, to form a thorough coating on<br />
particulate waste. Although such a process does not chemically bind the waste<br />
constituents, the coating would be complete enough to prohibit release by<br />
normal mechanisms (ie. leaching).<br />
Chemical (Thermosetting) Polymers<br />
Thermosetting polymers are produced through chemical reaction between organic<br />
monomers. They are strong, tough, and are not adversely affected by high<br />
temperatures. The exact types and proportions of the raw materials is often<br />
proprietary information. Many of the raw materials are hazardous or toxic<br />
chemicals.<br />
Polystyrene<br />
Polystyrene is formed by adding a catalyst (i.e acrylonitrile) to styrene.<br />
-The-re-acti3n i-s-exathermic;-producing a-strong, forittie piastic matrix. The<br />
material is not useful for encapsulating water-bearing wastes.<br />
"o • iyester resins<br />
Pnlyester resins ,arre formed-by a chemical reaction between a resin (i.e.<br />
styrene), promoter ( i.e. phthalic acid), and a catalyst ( i.e organic<br />
peroxide), to form a encapsulating matrix around the waste. The reaction is<br />
exothermal and can produce temperatures around 60°C. Modified polyesters have<br />
been developed with enhanced water encapsulation abilities.<br />
Urea-formaldehyde resin<br />
Urea-formaldehyde polymers are created by<br />
aqueous emulsion of urea and formaldehyde<br />
reaction, and this process has been used<br />
material is susceptible to embrittlement<br />
time.<br />
Epoxy resins<br />
adding a mineral acid catalyst to an<br />
Water is a byproduct of the<br />
to encapsulate aqueous wastes. The<br />
by dehydration and "bleeding" over<br />
Epoxies are produced by reactions between phenols and epoxides, in the<br />
presence of alkali to neutralize the HC1 byproduct. Chemicals which enhance<br />
water compatibility and modify structural properties_can_be added. The<br />
reaction is only mildly exothermic, but the materials are generally more<br />
expensive than other polymers.<br />
Other<br />
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Ceramics and glass<br />
WHC-SD-W200-TI-003 Rev. 0<br />
Ceram-ir- and- -g1 ass matr-i ces - .a-re -fo^med by subj^'cti^ig ^rastes to high temperature<br />
treatment. Ceramic aluminosilicates or vitreous borosilicates are added to<br />
- produce a strong, almost impervious final waste form.<br />
Calcination<br />
Calcination refers to processes that heat the waste to just below the point of<br />
fusion (melting). The final product is a granular material that can be<br />
processed by ceramic and powder metallurgy techniques into a suitable final<br />
form.<br />
Vitrification<br />
Vitrification refers to processes where the waste is heated to a temperature<br />
above its melting point. Glass-forming minerals are often added to modify the<br />
`.a properties of the final waste form.<br />
IMMOBILIZATION PROCESSES<br />
The physical and mechanical systems used to incorporate waste materials into<br />
= the immobiiization matrix are dependent on the chemical and physical<br />
3; properties of the waste, the type of immobilization matrix, and the treatment<br />
process. A brief description of process technologies follows.<br />
^<br />
Cementation<br />
Cementation processes are typified by dry materials handling using bins,<br />
hoppers, and solids mixers. If properly configured, the same equipment may be<br />
used to prepare several different immobilization matrices (i.e. ordinary<br />
cement, pozzolanic cements, and gypsum cements).<br />
Dry material handling<br />
Bins & hoppers<br />
Bulk and day storage equipment for dry solids require proper bin and hopper<br />
design to assure free flow of the powders. Storage facilities should be<br />
designed with mass flow hoppers to maximize storage capacity.<br />
Pneumatic conveying<br />
Most dry powder handling systems use pneumatic conveyors for unloading bulk<br />
trucks and transfer from storage to process units. Pneumatic conveyor systems<br />
are subject to erosion failure, and improper design can cause plugging or<br />
unsteady flow problems.<br />
Dust control<br />
ThEnature-o€--cem*nt-raw-arater-i^ls-regu3res the-use of dust control equipment.<br />
The use of cyclones, bag filters and air recirculation are typical methods for<br />
controlling dust.<br />
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In-drum mixing<br />
Drum tumbler<br />
WHC-SD-W100-TI-003 Rev. 0<br />
In this method of mixing,<br />
along with a dense mixing<br />
several minutes while the<br />
the materials to be mixed are added to the drum<br />
weight. The drum is then lifted and tumbled for<br />
weight mixes the contents. The weight remains<br />
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inside<br />
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the<br />
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arcer mixing.<br />
Lost-paddle mixing<br />
In this method, a collapsible mixing blade is inserted through the bung hole<br />
and attached to a motor. the drum is stationary while mixing proceeds. The<br />
mixing blades remain in the drum following mixing.<br />
Batch mixing<br />
Screw mixers<br />
A slow-speed screw is positioned at the bottom of a V-shaped trough. The dry<br />
materials are added to the trough and mixed.<br />
Planetary mixers<br />
Planetary mixers areused in vertical tanks to provide higher shear and more<br />
complete mixing than screw or paddle mixers.<br />
Mixing pumps<br />
Positive-displacement pumps which have been modified to provide enhanced<br />
mixing are available for processing high-viscosity grout mixtures.<br />
Melt Processes<br />
Melt processes are used with thermoplastic polymer matrices. These processes<br />
typically operate near 150°C and require control of gaseous effluents from the<br />
melter.<br />
Batch melter/mixer<br />
The batch process consists of a heated, stirred tank, where the matrix<br />
material is melted prior to addition of the waste. After the.wastes are<br />
added, the mixture is transferred to disposal containers and allowed to cool<br />
and solidify.<br />
Thin-film evaporator<br />
The thin-film evaporator process is used with bitumen emulsions of aqueous<br />
wastes. As the emulsion passes through the evaporator, the water is driven<br />
off, and the remaining waste materials are mixed into the bitumen. The molten<br />
mixture then flows into disposal containers, where it solidifies upon cooling.<br />
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,. .,<br />
Extruder/melter<br />
WHC-SD-W100-TI-003 Rev. 0<br />
In this process, the waste and matrix material are added to a screw-type<br />
extruder. The mechanical power applied to the extruder screws heats and melts<br />
the matrix, mixing it with the waste and evaporating any water that may be<br />
present. Some extruders also use external heating. The mixture is then<br />
transferred to the disposal container and allowed to cool and solidify.<br />
Polymer Encapsulation<br />
Polymer encapsulation processes require facilities to store, transfer, and mix<br />
the organic liquid reactants with the waste. Control of volatile vapors from<br />
the process is also required.<br />
Liquid handling<br />
The raw ingredients for thermosetting polymers are liquid organic chemicals.<br />
These chemicals may be flammable but can be handled with conventional<br />
processing equipment.<br />
Tanks & pumps<br />
Carbon steel tanks and centrifugal pumps are suitable for most applications.<br />
Some organic acids ( promotors or catalysts) may require stainless steel<br />
equipment.<br />
Pipes & val'ves<br />
Materials are transferred through piping and control valves. Fugitive<br />
emissions from piping systems must be minimized.<br />
Vent vapor control<br />
Control of flammable or corrosive organic vapors from tank vents is required<br />
for raw materials storage systems.<br />
In-drum mixing<br />
In-drum mixing can be used when the waste is granular, powdery, or a<br />
reasonably fluid material. In-drum mixing methods are similar to those used<br />
for cementation.<br />
High-shear mixing<br />
The organic binder material is charged to the drum. The waste is added while<br />
the binder is mixed with a propeller type mixer. When mixing is complete, the<br />
mixer is withdrawn and excess binder is flung off into an empty drum.<br />
Lost-paddle mixer<br />
The collapsible mixer is inserted tkrough-the bung hole of the drum.<br />
- - Following mixing, the paddle remains in the drum.<br />
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Batch processes<br />
WHC-SD-W100-TI-003 Rev. 0<br />
Thermosetting polymers can be processed in batch equipment with the capacity<br />
for filling large containers or many drums. There are two approaches for<br />
using batch mixers.<br />
Microencapsulation<br />
In this method, the waste and binder are mixed in a vessel. As the mixture is<br />
transferred to the drum, the catalyst and promotor are added and mixed in-line<br />
just before entering the drum.<br />
Macroencapsulation<br />
In this method, the mixing tank does not contain waste. The polymer mixture<br />
is added to the drum which contains_large_waste_items._The drum is on a<br />
vibrating table to remove air bubbles.<br />
G-10<br />
N,