ML20079E008

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Rev 1 to Test Plan WVNS-TPL-70-11, Test Plan for Waste Form Qualification Program for Cement Solidification of Sludge Wash Liquid
ML20079E008
Person / Time
Site: West Valley Demonstration Project
Issue date: 09/05/1991
From:
WEST VALLEY NUCLEAR SERVICES CO., INC.
To:
Shared Package
ML20079E011 List:
References
REF-PROJ-M-32 WVNS-TPL-70-11, NUDOCS 9110040276
Download: ML20079E008 (10)


Text

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West Valley Doo. s ter xvsS m .,0.,,

Demonstration Project Revielen "mnter i Revision Date 09-05-91 Engineering Release #2044 ECN #4534 TEST PLAN FOR THE WASTE FCRM QUALIFICATION PROGRAM FOR CEMENT SOLIDIFIC ATION OF SLUDGE WASH LIQUID PREPARED BY AOf# M. N. Baker Cognizant Engineer APPROVED BY - .

FL 3.0.N@ D. C. Meess (ogni:.'ant Syateq Design Manager APPROVED BY c d .\): L Ar P. J. Valenti FaETytyRepresentative APPROVED BY -

/ l -5' / . . . .- / li fD. L. Shugars Quality A48urance Manager APPROVED BY h L. [ s -

[ D. J. Harward

' Radiation & "prety Manager /

APPROVED BY k .l bm.. J. C. Cwynar IRI) Process Control Engineering l West Valley Nuclear Services Co., Inc.

P.O Box 191 SAJ0062: 3RM West Valley, NY 14171-0191

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OI WV 1816, Rev.' 1 ,(P[i . F'R ug em

i ., WNS .TPL. 70 11 l -

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RECORD OF REVISION PROCEDURE If there are changes to the procedure, the revision number inct .ses by one.

These changes are indicated in the left mars i n of the body by an arrow (>) at the beginning of the paragraph that contains a change.

Example:

> The arrou in the margin indica *es a change.

Revision On Rev. No. Description of Changes Page(s) Dated 0 Original Issue All 03 25 91 1 Per ECN 4534 2 thru 4 09 05 91 l

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, W.1807, Rev. 1 i l SAJ0062:3RM

  • WNS TPL.70 11 Rev. 1 RECORD OF REVISION (CONTINUATION SHEET)

Revision on Rev. No. Description of Changes l'a ge ( s ) Dated W 1807, Rev. 1 11 SAJ0062:3RM

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VVNS TPL 70 11 TEST PLAN FOR THE WASTE FORM QUALITICATION PROGRAM /OR CEMENT SOLIDIFICATION OF SLUDGE VASH LIQUID REV. 1 1.0 PURPOSE l

l The purpose of this test plan is to :.uscribe the Waste ferm Qualification Progran for Cement Solidification of Sludge Wash Liquid. The plan specifies the testin5 required to develop and qualify a stable u m a forn in accordance with the requirements of 10 CFR 61, Code of Feieral Regulations, Title 10, " Licensing Requirements for Land Disposal (J l Radioactive Vaste" and the USNRC Branch Technical Position on Waste Form, Revision 1, draft dated December 1990.

2.0 APPLICABILITY This program applies to the qualification testing required to demonstrate that the waste form developed herein for the Sludge Wash vaste strea2n meets the waste stability criteria of 10CFR61.56. The scope includes the' experimental work performed from waste characterization through full-scale testing in the Cement Solidification System (CSS).

3.0 CENERAL REQUIREMENTS 3.1 All procedures for conducting tests and documenting and avaluating l test results will be prepared, reviewed, and approved in accordance l with the requirements of the VVNS Policy and Procedure Manual, l En51 neering Procedures EP 11 001, EP 11 003, and SOP 00 2.

3.2 Test requirements will be as specified in Test Requests (TRQ) issued by the IRTS Process Control Engineering organization in accordance with EP 11 003, 3.3 Testing in response to the Test Resquests shall be perfc id in accordance with the Test Procedures (TP) issued by the . ytical &

Process Chemistry Laboratory in accordance with EP-11-003, 3.4 Operation of the Cement Solidification System (CSS) will be by qualified CSS Operations personnel in accordance with SIP 91 1 and existing Standard Operari.ng Procedures (SOP's).

3.5 Lab testing will be performed by qualified Analytical & Process Chemistry Technicians using Analytical Chemircry Methods (ACM's).

3.6 All data collection, reporting, and documentation will be performed in accordance with EP 11 001 and EP 11 003 as applicable.

SAJ0062:3RM 1-

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WNS TPL 70 11

Rev. 1 l

l 4.0 SCOPE 4.1 The scope of the qualification program will be as described in docu:nents summarized in the flowchart (Figure 1).

l l 4.2 Nominal Recipe Development (WNS TRQ 025)

Developtrent of the " nominal" recipe will include determination of the "notainal" Water to Cement' Ratio, as well as the " nominal" addition rates for the recipe enhancers: Calcium Nitrate, Antifoam, j and Sodiurs Silicate.

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4.3 Waste Form Qualification (WNS TRQ 026) l l

Qualification of the " nominal" recipe will include establishing a )

l curve of compressive strength vs. t iene , deterraination of the maximurn l l practical compressive strength, verification of compressive strength af ter thermal cycling, deterinination of resistance of 1 caching of I radionuclidos, and verification of compressive strength after I imrne rs ion. ,

j 4.4 Full Scale Verification (WNS TRQ 030)

Full scale verification cf the " nominal" recipe will take place after curing of the full scale drums processed under SIP 91 1. The drums will be core drilled, and the cores will be evaluated for j cotapressive strength, as well as compressive strength af ter immersion.

l 4.5 Development of Process Control Parameters (WNS TRQ 028) l

Recipe boundaries will be deterinined for the following parameters,

, as a minimum: Total Dissolved Solids (TDS) in the vaste stream, Water to Cement Ratio, variations in the Cement /Calciurn Nitrate Blend, amount of Antifoam recipe enhancer, and the arnount of Sodium Silicate recipe enhancer.

The effects of variations in the waste stream will be evaluated for 1

the following parameters: Aluminurn content, Sodium content, Organics, Sulfates, pil. Nitites, and Phosphates.

> Plackett-Burman Screening Tests (WNS-TP 028A)

> 28 cubes will be produced from 28 solutions representing variations in the liquid waste chemical compositions and recipe enhancers.

l These cubes will be used to screen the degree of interaction between 13 individual components.

> The effects of variations will be evaluated for: bleedwater, gel time, and penetration resistance.

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l SAJ0062:3RM l

. WNS TPl. 70 11 Rev. 1 1

> Box Behnhen Tests (WNS TP 02898)

> Based on the results of WNS TP 02SA above, additional tests of the key variables (those with significant interactions) will be conducted to precisely define the recipe limits for each key variable.

4.6 Confirtsatory Testing (WNS TRQ 029)

For this test, a quantity of actual liigh Level Vaste Tank sludge will be decontaminated in the laboratory, and the resulting liquid will be solidified using the " nominal" recipe. The compressive strength of the solidified sample will be determined.

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Figure 1

> WASTE FORM QUALIFICATION PROGRAM FOR SLUDGE WASil LIQUID f LEST Pt An D r.9es- IR 11 I L >

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WNS.TPL. 70 11 1 Rev. 1 l l l i

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5.0 DESCRIPTION

5.1 Mixing of lab scale specimens shall be performed under conditions l which duplicate the full. scale mixing conditions mixer speed, mix  !

time, etc., to the maximum extent practical, as discussed in the Branch Technical Position Appendix A.III.A.

I j 5.2 Curing of lab. scale specimens shall be performed under conditions  !

i which duplicate the full. scale curing conditions to the maximum  !

l extent practical, as discussed in the Branch Technical Position.

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Appendix A.III.B. The centerline temperature vs. time of a full.

i scale drum will be established, and this profile will be followed to ,

l the maximum extent practical.

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5.3 Compressive strength testing of 2" x 2a x 2" cubes will be performed  ;

j in accordance with the applicable steps of ASTM Standard C 109.  !

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j 5.4 Compressive strength testing of cylinders (both cast and core.

l drilled) will be performed in accordance with the applicable steps of ASTM Standard C 39 and the Branch Technical Position, .

Appendix A.II.B.

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! 5.5 Testing of thermal sesbility will be performed in accordance with

the applicable sections of ASTM Standard B 553 as discussed in the l Branch Technical Position, Appendix A.II.C.

5.6 Resiseence to leaching of radionuclides will be performed in j accordance with section C.2.e of the main body of ANSI /ANS 16.1, as i

discussed in the Branch Technical Position, Appendix A.II.F. Prior l to leach testing, the most aggressive leachant, deionised water or synthetic sea vatt.r will be determined by a 24. hour test.

5.7 Development of process control parameters will be performed in accordance with existing ACM's, and as discussed in the Branch Technical Position, Appendix A.VI.A.

5.8 Immersion testing vill be performed in accordance with the Test Procedures (TP's) for that work, and as discussed in the Branch Technical Position, Appendix A.II.C. The immersion testing will be performed using the most aggressive leachant (deionized water or synthetic sea water) as determined in section 5.6 above. Immersion testing may take place for up to 180 days, as discussed in the l Branch Technical Position.

l 5.9 Waste test specimens shall have less chan 0.5 percent by volume of the waste specimen as free liquid as discussed in the Branch

! Technical Position, Appendix A.II.H. Any free liquid encountered j shall have a pH greater than or equal to 9.

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WVNS TPL.70 11

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Rev. 1 5.10 Sufficient samplaw shall be tested to provide enough data to establish a mean and a standard deviation, as discussed in the Branch Technical Position. Appendix A.IV 5.11 Irradiation testing of the vaste form will NOT be performed, because no ion exchange resins or other organic media are contained in the waste stream, as discussed in the Branch Technical Position.

Appendix A.II.D.

5.12 Biedegrads. tion testing of the vaste form will NCT be performed, because the waste liquid contains no carbonaceous materials, as discussed in the Branch Technical Position, Appendix A.II,E.

6.0 REFERENCES

6.1 10CFR61

Code of Federal Reguletions, Title 10, Part 61,

" Licensing Requirements for Land Disposal of Radioactive Waste" 6.2 ASTM C 39: Standard 9.,st Method for Compressive Strength of Cylindrical concrete Specimens 6.3 ASTM C 109: Standard test Method for Compressive Strength of Hydraulic Co.ient Mortars Using 2 inch or 50 mm Cube Specimens 6.4 ASTM B-553: Test Method for Thermal Cycling of Electroplated Plastics 6.5 ASTM C-617: Standard Practice for Capping Cylindrical Coner te Specimens 6.6 ANSI /(NS 16.1: Standard Measurement of the Leachtbility of Solidif.'ed Low-Level Radioactive Vasces by a Short-term Procedure SAJ0062 :3RM  !

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