ML20082M352

Forwards Revs to Operational Safety Requirements/Technical Requirements,Vol VI

ML20082M352
Person / Time
Site:	West Valley Demonstration Project
Issue date:	08/27/1991
From:	Lindbergh B, Schiffhauer C WEST VALLEY NUCLEAR SERVICES CO., INC.
To:	WEST VALLEY NUCLEAR SERVICES CO., INC.
References
REF-PROJ-M-32 HF:91:1023, NUDOCS 9109050157
Download: ML20082M352 (160)

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• HF:91:1023 Cre August 27, 1991 x.: ea controlled Distribution of Revis.ons to the Operational Safety Requirements / Technical Requirements, Volume VI Distribution

-c cc: HF Letter Log, MS-52 Original, MS-MRC Attached are the following revisions to the Operational Safety Requirements / Technical Requirements, Volume VI, which has been assigned to you under controlled dis 'bution: o Latest Table if Contents o OSR/CP 1, Res 2 "WVDP Airborne Radioactivity Release Limits" o OSR/CP 3, Rev. 4 - " Building and Vessel Ventilation Systems Operability" o OSR/CP 4, Rev. 2 - " Effluent and Environmental Monitoring" o OSR/CP-5, Rev 3 - "WVDP Emergency Power Requirements" o TR/CP-6, Rev. 2 - " Storage Requirements for Low Level Waste" o OSR/CP 7, Rev. 2 - " Criticality Safety for Liquid Transfers" o TR/CP-8, Rev. 2 - " Water Activity Alarms" o TR/GP-9, Rev. 2 - " Control of Plant Equipment Function and Configuration" o OSR/CP-10, Rev. 2 " Airborne Effluent Monitoring System operability" o OSR/CP-ll, Rev. 3 " Storage Canister Loading and Spacing" o OSR/GP-12, Rev. 2- " Fissile Material Limits and Requirements of Waste Packages" o TR/CP-16, Rev. 2 - " Plant Fire Protection Systems" o OSR/IRTS-1, Rev. 3 " Maintenance of Carbon Steel High Level Waste Tank Integrity" o TR/IRTS-2, Rev. 3 " Control of CSS Recipe for Decontaminated Supernatant" o OSR/IRTS-3, Rev. 3- " Maintenance of Spare HLW Storage Capacity" o TR/IRTS-4, Rev. 4 - "Depressurization of STS for Maintenance" o TR/IRTS 5, Rev. 6 "STS Process Limits" o TR/IRTS-8, Rev. 4 " Sampling and Analysis Requirements for Tanks 5-D-15-Al and A2" Replace the current table of contents; OSR/TR-CP-1, Rev. 1; OSR/GP-3, Rev. 3; OSR/TR GP 4, Rev. 1; OSR/CP-5, Rev. 2; OSR/TR-CP 6, Rev. 1; OSR/TR-GP-7, Rev. 1; OSR/TR-GP-8, Rev. 1; OSR/TR-CP-9, Rev. 1; OSR/TR-CP-10, Rev 1; OSR/CP-il, Rev. 2; OSR/TR-CP 12, Rev. 1; OSR/TR-GP 16, Rev. 1; OSR/IRTS 1, Rev. 2; TR-IRTS 2, Rev. 2; OSR/TR-IRTS-3, Rev 2: TR-IRTS 4, Rev. 3. TR-IRTS-5, Rev. 5; and TR-IRTS-8, Rev. 3, with the attached in your manual. rr l i tid i i, a - l 'J ) .\\; PRC0024: 12RM ? { 91090";O157 910927 ) V' PDR P R O.) M-32 pg

4 HF:91:1023 2- -August 27, 1991 Copies made from a controlled document are to be marked UNCONTROI.L.ED before distribution, To acknowledge receipt of this document, sign, date, and return the attached controlled distribution receipt acknowledgement to the undersigned by September 10, 1991. For your convenience, a stamped (off-site recipients only) return address has been placed on the reverse side of the controlled distribution receipt acknowledgement; fold, staple, and place in the mail. x dPDLV . E. LindbWgTC Itecords Proce,t]r Records Management West Valley Nuclear Services Co., Inc. Approved: , l'}]. 3 - fgaxf4 C. M. Schif fhauer, Supervisor

Attachment:

As stated above O ( PRC0024: 12RM L /

- 3 TA n_. L) O (,V CONTROLLED DISTRIBUTION OPERATIONAL SAFETY REQUIREMENTS / TECHNICAL REQUIREMENTS, VOLUME VI O PAGE 1 0F 2 DATE COPY MAIL OF NUMBER STOP RECIPIENT DEPARTMENT RECEIPT W. D. Jensen DOE-ID _f_/91 3. T. W. McIntosh DOE IQ _f_/91 4. R. D. Hurt NRC-HQ _f_/91 6. R. D. Hurt NRC-HQ _/jI 7. '8. -R. D. Hurt' NRC.HQ _f_/91 R. D. Hurt NRC HQ _f_f 91 9. R. D. Hurt NRC HQ _f_/91 10. 12. 201 R. F. Cessner Plant Operations _f_f 91 15. 41A J. L. Knabenschuh Radiological & Environmental Safety _f_/91 16. 305 T. Hughes Site Engineering j_f 91 19. W J. C. Gwynar Process Control _/_/91 22. 42 R. A, Humphrey Site Services and Support _/ j 91 23. 45 T. M. Centner Emergency Operations Center _/_f 91 T. K. DeBoer NYSERDA _f_f 91 25. 26. NYSERDA T. L. Sonntag NYSERDA _f_f 91 27, 307 W. G. Poulson Exec. VP & Deputy General Manager _f_/91 28. R D. H. Carland Waste Management Operations _f j 91 29. N W. J. Cry: Plant Security _/_f 91 30. W K E. Sanders STS Control Room _f_f 91 0 31. PSO S. Church Shift Supervisors Office _/_f 91 32. X R. J. Tussner LWTS/ CSS Control Room _f_f 91 33. R D. G. Feldman Drum Cell Control Room _f_f 91 34. DOE J, A. Yeazel DOE - West Valley _ /_f 91 35. 1 S. P. McKenzie Training and Development j _/91 39, 2t5 D. J. Sawyer Main Plant Operations j,_j91 40, 305 D. K. Ploet: Plant Engineering _f_f 91 42. B D. L. Shugars Quality Assurance _/_f 91 43. 51 R. W. Devlin Systems Engineering and Support _f_/91 Signed: Dated Update of Manual HF:91:1023 08 27-91 O FOLD, STAPLE, AND PLACE IN MAIL PRC0061:12PJi

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.~ .... -.. ~. ..~ O. OPERATIONAL SAFETY REQUIREMENTS /TECl!NICAL RF4UIREMENTS \\j VEST VALLEY DEMONSTRATION PF0 JECT WVDP Former WVDP, NFS Identif f er Rev. Title / Contents Identifiers OSR/GP-1 2 WDP Airborne Radioactivity H,11.5.2.4 Release Limits WVDP 4.1 OSR CP 1 OSR/TR GP 1 OSR-CP-2 1 Radioactivity Content of Liquid M.11.5.2.5. Ef fluents Released from the WDP WDP 4.2 OSR-CP-2 OSR/TR CP 2 OSR/GP 3 4 Building and Vessel Ventilation M.11.5.2.1. Systems Operability NFS 5.3, STS 1,1, 1.2, CSS 4.1, 4,2, SRF 8.2. LWTS 5.1 M.11.5.2.7. WDP 4.14 (] LWTS 5.2, (/ NFS 6.5, STS 1.2 CSS 4.2 M 11.5.2.8. i TVS 3.0 M.11.5.2.1 VF 2.2, 2.3 OSR GP-3 OSR/TR-CP-3 OSR/GP-4 2 Effluent and Environmental M ll.5 ;.1.B.X Monitoring (WDP 5.1) OSR GP-4 OSR/TR-CP-4 BLB0578:3RM DATED: 08-27-91 + (.

' /N WVDP Former kVDP, NFS (,,) Identifier Rev. Title / Contents __Identifiern OSR/GP-5 3 WVDP Emergency Power Requirements M.ll.5.4.3. NFS 6.4 M.11.5.2.1.D STS 1.3 M.ll.5.2.1.C CSS 4.4 OSR GP 5 OSR/TR CP-5 j TR/GP-6 2 Storage Requirements for M.11.5.2.1.J Low Level Waste LAG-1, LAG 2 j M.11.5.2.1.1 SRF 8.4 TR GP 6 l OSR/TR GP-6 OSR/GP-7 2 Criticality Safety for Liquid M.11.5.2.2. Iransfer WVDP 4.3 OSR CP 7. OSR/TR-CP 7 TR/GP-8 ? Water Activity Alarms M.11.5.4.1. NFS 6.9 TR GP 8 OSR/TR-GP a TR/GP-9 2 Control.:f Plant Equipment New Function and Configuration TR CP-9 OSR/TR-CP-9 OSR/GP.10 2 Airborne Effluent Monitoring M.ll.5.4.4 System Operability NFS 6,5 STS 1.1, 1.2 CSS 4.1 OSR CP-10 OSR/TR-CP-10 OSR/GP-ll 3 Storage Canister Loading and M.11.5,1.2.B Spacing AFM 6.0 STS 1.4, CSS 4.3, LWTS 5.3 OSR GP-ll OSR/TR-CP-ll f "N BLB0578:3RM DATED: 08-27-91 )

WDP Fortner WDP,. NFS Identifier Rev. Titic/ Contents Identifiers OSR/CP-12 2 Fissile Material Limits and M.11.5.1.1.B Requirements for k'aste Packages CPCRIT 9.1, 9.3, STS 1.4, TRU 9.1, 9.2, LAC-1, LAC 2 M.ll.5.1.1.J RER 1 1 M.11.5.4.1.J RER 1.3 M ll.5.6.1.J RER 1.2 OSR CP-12 OSR/TR CP-12 TR-CP-13 1 Evacuation Alarm and Emergency New Paging System Operability TR CP-13 OSR/TR-CP-13 TR-CP 14 1 WDP Meteorological System New Operability TR CP-14 OSR/TR-CP-14 TR CP-15 1 Fire Brigade and Emergency New Response Team Training TR CP-15 OSR/TR-CP-15 TR/GP-16 2 Plant Fire Protection Systems New TR CP-16 OSR/TR CP-16 OSR/GP-17 0 TN-BRP and TN-REG Shipping Cask NA Lid Installation OSR/CP 18 0 Type B Shipping Cask License NA Compliance Documentation TR/CP-19 0 Area Radiation Detector NA Requirements During Cask Fuel Loading BLB0578 : 3 P.}i DATED: 08-27-91

i /^)i UVDP Forner WVDP, NFS (,, Identifier Rev. Titic/ Contents Identi fiern i OSR/IRTS 1 3 Maintenance of Carbon Steel M.11.5.2.6. i High Level Vaste Tank Integrity NFS 4.12 i M.11.5.4.2. NFS 6.3 OSR IRTS-1 OSR/TR IRTS-1 'TR/IRTS 2 3 Control of CSS Recipe for M.11.5.2.2.G l Decontaminated Supernatant CSS 4.3 TR IRTS-2 j OSR/TR IRTS-2 OSR/IRTS-3 3 Maintenance of Spare HLW M.11.5.2.3. f Storage Capacity NFS 5.4 [ OSR IRTS-3 l OSR/TR IRTS 3 I f TR/IRTS 4 4 Depressurization of STS for M 11.5.6.1.D Maintenance TR IRTS-4 1 J-OSR/TR 1RTS-4 i TR/IRTS 5 6 STS Process 1.imits M.11.5.1.1.D l STS 1.4 I l TR IRTS-5 OSR/TR-IRTS-5 } TR IRTS-6 2 LWTS Manifold Control CANCELLED New l l TR IRTS-6 OSR/TR-IRTS-6 l t TR IRTS 7 5 Sampling and Analysis New Requirements for Tank 5D 15B M.11.5.1.1.H j LWTS 5.3 TR IRTS-7 OSR/TR-IRTS-7 l TR/IRTS-8 4 Sampling and Analysis New Requirements for Tanks 5-D-15 TR IRTS 8 Al and A2. OSR/TR-IRTS-8 l t I I L BLB0578:3RM DATED: 08-27-91 [' \\ I ?

. P% ib) - Doc. Numcer _0co/GP-1 Revision Numee. 2 Revision Date _- 08-27-91 Engineering Release #1430 P;r ECN #3353 West Va ley Jemonstration Dro'ect OPER ATICNAL S AFE*Y REDUIREMENTS - (~M.. r,' # s D. R. Stefres Cate PREFARED BY 7 Cognitan:, Enginee ' APPROVED,3Y b - -v C. J. Roberts Cate$/ Ef Cpgna: ant Manager APPROVED BY b R. A. Humphrey Date [/k4 b i. s Kiciat;on &{ Safety Q Ccp.m ' tee, Chairman Date N I AP.PRDVED BY ) W-v3 C. L. Shugars / Quality. Assurance APPROVED BY MM R. F. F.essner Date I E 8 LLW Trea* men Pr,Jel,gE lJ.L.Knabensenuh . / Date 67J.c/TT ,I .-se e _ m APPROVED BY d [.Actological & Enytronmental / S vety. Manager Cate i b L!o a -E U4E R. E. Lawrence, Jr. APPROVED SY Supernatant Treatment Project Manager West Vcliey Nuclear Services Co. P.O. B o x 191 West Valley, N.Y.14171-Cl91 RLC3242: SEA-65 DOE Approved: DW:91:0530 Wy. j f3 ! 6 ECB Concurrence: 08-10-91

. ~.. ~. - -. _ -. -. -. _ ~. -. - -l l OSR/GP 1 -l Rev, 2' - > ~ ~ ' ^ ~ p RECORD OF-REVIS10N PROCEDURE If there are changes to the procedure, the' revision number, increases by one, These changes are indicated in the left margin of the body by an arrow (>) at the beginning of the paragraph that contains a change. Example; The arrow in the margin indicates a change. l Revision On Dated Rev. No. Description of Changes Page(s). i 0 , Original-Issue All 1 Dated.5/20/88 All .9: J -1 Engineering Release'1430 N/A 8/88 -2' Per ECN 3353 Page 4 08/91 'f i

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4 i l .3 I j W.- 1807, Rev. I 1 f LLK0125:3PJi { i h h I e )

_,7...._ _._.._.._.._._....-.., -._. _ _.-.._ __- ---- - _.....- -.. _. _ _ _ _._ _-. ___ _ _...m._.._.... c. - OSR/GP 1-Rev. 2- -ii RECORD OF REVISION (CONTINUATION SHEET) Revision on Rev._No. Description of Changes Page(s)- n 4 1 I l F i I i 1 l J s R L n u y 'l r i ' 4 i W-1807, Rev. 1 it { LLK0125:3RM-1 7 t I 6 W I >i I 1 I 6 + +-em-" .-os 4-..... ,,-4.- <+ =e.e,+w. m.- -, .,.wv.._--.-mew,-,,.. ....,.-m ,vm--,- e, re.-,..---es-m,mn.-, e..- ww - +w-,

OSR/GP 1 Rev. 2 --- y O I I -TYPE: __ l TITLE: WDP Airborne Radioactive l NUMBER: GENPIRT 'OSR_[X] l Release-Limits l-1 1 I Tech. Reqmn'_t.-( )l l l l CRITERIA: l. Release of airborne radioactive effluents shall not exceed limits established by DOE orders, j i UNACCEPTABLE EVENTS: 'l. Releases of airborne radioactivity exceeding DOE limits. i-i l l I Safety Limit l X l Reporting Requirements: l DOE-ID CONTROLLED l LCO l X l UOR l

i. I LCS l

l l \\ Surveillance Reqmn't. l X l l I I I I I I f Tech. Requirement l I l DOE-WPO CONTROLLED l' I I I i Operating Limit 1 I IWNS CONTROLLED j- ~> IMPLEMENTING PROCEDURES: EM-ll .EM-101 -SOP 15-11 -SOP 70 30-l SOP'50 SOP 80 5 t-SOP 80-6 I i i LIX0125:3RM 1 o

OSR/GP 1 Rev. 2 OPDIATIONAL SAFETY RIX)UIRIMFNT /~3 (J 1 \\ WDP AIRBORNE RADIDACTIVITY RELFASE LIMITS APPLICABILITY This OSR applies to all airborne radioactive etnissions from WDP permitted process and ventilation stacks. OIOECTIVE This specification ensures that the off-site doses frota airborna radioactive releases frotn WDP operations are less thea the guideline valveu stipulated by 003 L Order 5480.1A, Chapter XI, and 40 CFR 61, fcr lad.fiduals in uncontrolled (of f site)

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SPECIFICATION -G L f SAFETY LIMIT OFF-SITE EXPOSURE TO THE MAXIMALLY EXP') SED INDIVIDUAL BY Tile AIRBORNE PATilWAY SilALL j BE LESS 'IriAN 25 MREM VHOLE BODY OR 75 MREM / YEAR DOSE TO ANY ORGAN.

1. LIMITING CONDITIONS QR OPERATION 6

? A. THE TOTAL PARTICUIATE RADIOACTIVITY RELEASE PATE FROM Tile WDP MAIN PLANT i STACK 5 HALL NOT EXCEED 0.04 MICR0 CURIES /SECOND FOR LONC LIVED CROSS BETA ACTIVITY AND 0.002 MICR0 CURIES /SECOND FOR LONC-LIVED CROSS ALPilA ACTIVITY AVERAGED OVER A CALENDAR QUARTER. I v l P n%/ P LLE0125:3RM-1 Page 1 of 4 i

OSR/GP 1 Rev 2 B. THE TOTAL PARTICULATE RADIOACTIVITY RELEASE RATE FROM EACH OF THE OTHER f3 ('~ [ -EXHAUST STACKS (01-14 BUILDING, STS, CONTACT SIZE REDUCTION FACILITY, SUPERCOMPACTOR, AND CTS) AND ANY FUTURE VENTS OR STACKS, SHALL NOT INDIVIDUALLY EXCEED 0.002 MICR0 CURIES /SECOND FOR LONG LIVED GROSS BETA ACTIVITY AND 20 PIC0 CURIES /SECOND FOR LONG LIVED CROSS ALPHA ACTIVITY AVERACED OVER A CALENDAR QUARTER.

2. - SURVEILI ANCE REQUIREMENT A.

THE COMBINED LONG LIVED PARTICULATE RADIOACTIVITY RELEASED FROM PERMITTED STACKS SHALL BE MEASURED TO ENSURE THAT THE AVERAGE AIRBORNE RADI0 ACTIVITY RELEASED DOES NOT EXCEED 70 MILLICURIES GROSS BETA ACTIVITY OR 3.0 MILLICURIES GROSS ALPHA ACTIVITY IN ANY ONE MONTH. 3, RECOVERY IF THE RELEASE RATES SPECIFIED IN THE S'URVEILIANCE REQUIREMENT ARE EXCEEDED, OPERATIONS SHALL BE CURTAILED-AND CONDITIONS EVALUATED AND CORRECTED TO ASSURE THAT THE QUARTERLY LIMITS CAN BE MET BEFORE FURTHER OPERATIONS ARE PERMITTED. .%) KASIS Per DOE Order 5480,1 requirements, the committed dose to any organ of the maximally exposed individual from the airborne pathway is limited to 75 arem/ year, with an administrative action level set at 37.5 mrem for this pathway. Annual average measurements of stack effluents show that the concentration of long-lived gross beta activity is typically on the order of 100 times the long-lived gross alpha component. Gross beta is assumed conservatively to be 100 percent Sr + Cs, and gross alpha is'100 percent Pu + Am. Given measured effluent ratios of Cs-137fto Sr 90 of approximately 1:1, and Am-241 to Pu-239 of 3:1, calculations were made using Table 1 values from WVDP-65, " Radiological Parameters," for long term stack releases. Dose predictions were also based on the EPA approved dose assessment code AIRDOS-EPA, version CAAC. O LLK0125:3RM 1 Page 2 of 4

1 1 OSR/GP 1 Rev. 2 Assuming that all stacks continuously discharge at the maximum rates npecified by g-) t the LCOs of this OSR and that these stack effluents account for 90 percent of all a radioactivity released from the site, the maximum total off-site organ dose commitment from air pathways would be less than 75 mrem / year. To maintain conservatism and to meet DOE reporting requirements the releases corresponding apprcximately to the action level of 37.5 mrem / year to any organ (or the 12.5 mrem / year action level for the whole body dose) are used as the monthly surveillance requirement to meet the requirement of DOE 19 Order 5480.1, Chapter XII. ATTACIMEffrS None REFERENCES DOE /EP-0096, A Guide for Effluent Radiological Measurements at DOE Installations, 7/83. V(N DOE /EP-0023, A Guide for Environmental Radiological Surveillance at U.S. Department of Energy Installations, 7/81. DOE EH Draft, Committed Dose Equivalent Tables for U.S. Department of Energy Population Dose Calculations, 8/85. Memo from D. E. Patterson to Heads of Field Organizations, Annual Site Environmental Monitoring Report, dated February 27, 1984 I I e [ \\ (_) LLK0125:3RM 1 Page 3 of 4 e e

r OSR/CP 1 Rev. 2 i Memo from-J. C. Tseng' to Heads of Field Organizations, Clarification of Applicable () Radiation Protection St'andards, dated November _4, 19C7. ~ + Radiological Parameters for Assessment of West Valley Demonstration Project j Activities, WVDP 65, 10/87. [ U.S. DOE Order $480.1, Chapter XI, " Requirements for Radiation Protection," 4/81. U.S. DOE Order 5484.1, " Environmental Protection, Safety, and Health-Protection i Information Reporting Requirements," 2/81, i DOE-ID Order 5480.1, Chapter XII, " Prevention, Control, and Abatement of f Environmental Pollution," 3/82. ~ I i \\ I t r t i ? l b I t t c w I LLK0125:3RM-1 Page 4 of 4 [ I F

1 t*c 000. Nuscer.OSR/GP-3 Revision Nu :er 4 Revision Ca:e os n_gi_ Enginee"ing Release #1430 Per ECV #2611 Per ECN #2770, 2770A, 2770B Per ECN #3353 a ei. e s \\ I.ee I a e -= C~l VUliCj 3G m OnSITGiiOn U FO[eCi CPIRAT:0 MAL SATI~'? RE UIR OENTS E/

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F.C. E c x 191 West Vctiey, N.Y.14171-CIS t VLA0321:EtiG-392 90E Approved: DW:91:0530 'N V - 1816 ECB Concurrence: 08-10-91

p_____. .___.-_______._..m_. 4 i si o .OSR/GP 3 (_ Rev,,. RECORD OF-REVISION PROCEDURE If there are changesLeo the procedure, the revision number increases by one, t. lT These_ changes are indicated in the left margin of the body'by an arrow (>) at is the beginning of the paragraph that contains a' change. l Example: l' l The arrow in the' margin indicates'a change; l t -Revision On_ l Rev. No. Description of Changes Page(s) Dated i !-I 01 OriB nal Issue 'All i l_ 1 Dated 5/20/88 All l 1 Engineering Release 1430-N/A 08/88 i 2 Per ECN n2611 2,6 12/88 l 3 Per ECN #2770, #2770A, a27708 -1,2,4,6,10,12 10/89 i 4 Per ECN 3353 4 08/91 l-l 4 o I - i i ) W VLA0321SAV:3RM-1.

..... > -.. _. _... -_-_ _ __ _._ _.......__.~_- m_...=--- OSR/GP.3' .Rev. 4 1 RECORD OF REVISION (CONTINUATION SHEET) Revisio" on n. Description of Changes Page(s) Rev. No. 1 l, i .i f I t I L E 3 i-(' i W-1807, Rev. 1 11 VIA0321:3RM-1

.0SR/GP 3 .Rev. 4 U l l TYPE: l TITLE: Building and Vessel' l NUMBER: - CENPLNT - OSR_[X) l Ventilation Systems Operability .l 3 I l Tech Reqm'nt. [ ]l l l I CRITERIA:

1. Release of airborne radioactivity effluent to the off site environs shall not exceed DOE guidelines.

2 Provide a barrier to release of airborne radioactivity to off site environs in the event of a SAR identified accident, i UNACCEPTABLE EVENTS: 1. Unplanned release of radioactivity to the l off-site L environs. F 4 E l l l Safety Limit -l l Reporting Requirements: l DOE-ID CONTROLLED LCO l X-l UOR l LCS l. l l Surveillance Reqm'nt. l X l l I f I l-I l L Tech. Requirement l l l DOE VVPO CONTROLLED

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-l I l-Operating Limit t l lWVNS CONTROLLED > IMPLEMENTING PROCEDURES: S0P 1-38 S0P 15-9 S0P 50-36 SOP 70-4 SOP 80 1 SOP 6-2 SOP 15-20 SDP 50-37 SOP 70 11 SOP 80-2 i SOP 6-5 SOP 15 21 SOP 50-44 SOP 70-14 SOP 80-4 SOP 6-6 -SOP 15-2G SOP 56-1 SOP 70-15 SOP 80-5 ' SOP 8-1 SOP 15 SOP 56-2 SOP 70 16 SOP 80 6 . SOP 9-5 SOP 15-48 SOP-56-3 SOP 70-30 i VLA0321:3RM-1 s O 1

OSR/CP 3 Rev. 4 OPERATIONAL SAFETY REQUIREMENTS y CENERAL PLANT 3 P,UILDING AND VESSEL VENTIIATION SYSTEM OPERABILITY APPLICABILITY E This OSR applies to the operability requirements of the permitted ventilation systems used at the VVDP for radionuclide removal. This includes systems dedicated to the Process Building, Liquid Waste Treatment System, Vitrification Facility, Supernatant Treatment System, Cement Solidification System, Size Reduction Facility and supercompactor. OBJECTIVE fs. To assure that ventilation equipment necessary for safety is operable _i ) . \\~~/ during all project operations and to assure that radionuclide particulates are properly filtered from air being discharged to the environment so that such releases are below the limits of DOE Order 5480.1A, Chapter XI, and are maintained ALARA. SPECIFICATION LIMITING CONDITIONS FOR OPERATION:

1. SITE WIDE A,

THE APPLICABLE PLANT, PROCESS, AND STORAGE AREAS (LISTED IN i APPLICABILITY ABOVE) WHERE THERE IS A POTENTIAL FOR LOOSE RADIOACTIVE SURFACE CONTAMINATION SHALL BE VENTILATED T'iROUGH HICH EFFICIENCY FILTER (HEPA) SYSTEMS OF APPROPRIATE DESIGN AT ALL { TIMES. HEPA FILTERS USED AT THE WVDP FOR RADIONUCLIDE REMOVAL SHALL HAVE BEEN PREVIOUSLY TESTED (PRIOR TO INSTALLATION) TO 99.97 PERCENT ( EFFICIENCY. t VLA0321:3RM-1 Page 1 of 13

OSR/GP-3 l Rev. 4 l O B. INSTRUMENTATION MONITORING THE DIFFERENTIAL PRESSURE ACROSS THE OPERATING FINAL HEPA FILTER (SEE CHART) IN ALL VENTIIATION SYSTEMS SHALL BE OPERABLE DURING OPERATION OF THE FILTER. THIS MAY BE ACCOMPLISHED BY LOW AND HICH PRESSURE DIFFERENTIAL RECORDERS FOR EACH FILTER BANK. IF THIS INSTRUMENTATION SHOULD BECOME INOPERABLE, OPERATION OF THE FILTER MAY CONTINUE FOR TEN DAYS, PROVIDED THAT THE INSTRUMENTATION MONITORING THE DIFFERENTIAL PRESSURE ACROSS THE FILTER TRAIN IS OPERABLE. FINAL HEPA FILTER AND FILTER BANK DIFFERENTIAL PRESSURE INSTRUMENTATION (SEE CHART) SHALL BE CALIBRATED AT LEAST ANNUALLY. C. THE SUSTAINED OPERATING PRESSURE DIFFERENTIAL ACRCSS ANY ABSOLUTE FILTER IN ANY OF THE EXHAUST VENTILATION SYSTEMS SHALL NOT EXCEED 85 PERCENT sI.E., 8.5 ANCHES W.C. ) 0F THE GREATEST PRESSURE DIFFERENTIAL AT WHICH THAT FILTER HAS BEEN QUALIFIED IN ACCORDANCE WITH SPECIFICATION MIL F-51068C. D. ALARMS SHALL BE PROVIDED TO ANNUNCIATE HIGH DIFFERENTIAL PRESSURE (SEE CHART) ACROSS THE FINAL OPERATING ABSOLUTE FILTERS IN ANY VENTIIATION OR OFF-CAS TREATMENT SYSTEM USED IN RADIOACTIVE SERVICE. THESE ALARMS SHALL BE SET TO ANNUNCIATE AT LEAST 75 PERCENT OF THE GREATEST DIFFERENTIAL PRESSURE FOR WHICH THAT FILTER HAS BEEN QUALIFIED IN ACCORDANCE WITH THE APPROPRIATE REQUIREMENTS OF SPECIFICATION MIL-F-5106BC. E. AN AIARM SHALL BE PROVIDED TO ANNUNCIATE LOW DIFFERENTIAL PRESSURE (SEE CHAPT) ON THE FINAL OPERATING ABSOLUTE FILTER IN ANY VENTIIATION OR OFF-CAS TREATMENT SYSTEM USED IN RADIOACTIVE SERVICES. AFTER THE OPERATING DIFFERENTIAL PRESSURE EXCEEDS FIVE INCHES W.C., THIS AIARM SHALL BE SET WITHIN THREE INCHES W.C. OF THE OPERATING DIFFERENTIAL PRESSURE AND SHALL BE ADJUSTED WEEKLY. VLA0321:3RM-1 Page 2 of 13 O

OSR/GP 3-Rev. 4 IV

2. MAIN PLANT V0G, HEAD VENT AND MAIN PLANT VENT A.

SHOULD EITHER A FTLTER (6T 2, 6T 2A, 6T 3 6T 3A) OR PRIMARY BLOWER (6K-2) 0F THE MAIN PIANT VESSEL OFF-GAS SYSTEM (V0G) BECOME UNUSABLE FOR ANY REASON, PIANT OPERATIONS MAY CONTINUE PROVIDED THAT IMMEDIATE AND CONTINUING ACTION ARE TAKEN TO RETURN THE FAILED EQUIPMENT TO SERVICE AND THE REDUNDANT TRAIN IS FULLY OPERATIONAL. + B. IF, FOR ANY REASON, THE REDUNDANCY IN FILTRATION (MVS 15T 49A) ) (HEV 15T 70A, 71A', 72A, 73A) CAPABILITY OR EXHAUST BLOWER (MVS-15K. 10A) (HEV 15K-21) AVAILABILITY OF EITHER THE HEAD END (HEV) OR MAIN PLANT VENTILATION SYSTEM IS LOST FOR A PERIOD OF TIME EXCEEDING TEN DAYS, ALL PLANT OPERATIONS EXCEPT THE AVAIIABLE VENTILATION SYSTEMS SHALL BE SHUTDOWN IN AN ORDERLY-FASHION. PIANT OPERATIONS MAY BE CONTINUED BEYOND THE TEN DAY PERIOD ONLY IF ON-GOING REPAIR 0F A MAJOR COMPONENT SUCH AS A BLOWER OR A DRIVE UNIT EXCEEDS THE TEN DAY TIME LIMIT AND PROVIDED; 1) THE RADIATION AND SAFETY COMMITTEE HAS APPROVED A PIAN FOR EXPEDIENT REPAIR OR REPIACEMENT Of THE FAILED UNIT; AND 2) THE MAIN PLANT STACK EFFLUENT MONITORING AND SAMPLING SYSTEMS ARE OPERABLE, C. IF EITHER' THE HEAD END OR MAIN PLANT EXHAUST VENTIIATION SYSTEM FAILS TO SUCH AN EXTENT THAT NORMAL FLOW OF FILTERED AIR IS NOT AVAILABLE IN THE PARTICULAR SYSTEM, ALL PIANT OPERATIONS EXCEPT VENTIIATION SYSTEM OPERATION SHALL BE SHUTDOWN IN AN ORDERLY MANNER. PIANT OPERATIONS MAY CONTINUE IF HEV OPERATION IS SUSPENDED BY APPROVED PROCEDURES. D. AT LEAST ONE V0G BACKUP FILTER (6T 3 OR 6T-3A) 3 HALL BE OPERABLE AT ALL TIMES. VIA0321: 3RM-1 Page 3 of 13 4

OSR/GP 3 Rev. 4 D'\\ b-3, SUPERNATANT TREATMENT SYSTEM THE STS PERMANENT VENTILATION SYSTEM SHALL BE FULLY OPERATIONAL DURING ANY-STS OPERATIONS OR WHEN THE PVS IS USED TO PROVIDE HLW TANK. VENTILATION DURING TANK ACCESS THROUGH TANK RISERS. TO BE FULLY OPERATIONAL THE PVS SHALL CONSIST OF TWO OPERATIONALLY INDEPENDENT AND PARALLEL AIR CLEANING TRAINS OF APPROVED DESIGN. BOTH ELECTRIC POWERED -BLOWERS (56K-201, 56K 201A) SHALL BE AVAILABLE AND BOTH COMPLETE AIR CLEANING TRAINS (56T-202/202A, 56T-203/303A 56T 204/204A) SHALL BE OPERATIONAL FOR STS STARTINC A PROCESS CAMPAIGN, THE CAPABILITY FOR AUTOMATIC SWITCHOVER FROM THE PRIMARY (56T-202, 56T-203, 56T-204) TO THE . BACKUP TRAIN (56T 202A, 56T-203A, 56T-204A) SHALL BE PROVIDED EXCEPT DURING FILTER CHANGE 0UT WHEN MANUAL SWITCH 0V5'.R WILL BE MADE TO ALLOW FOR CONTINUOUS FILTRATION. IF DURING PROCESSING, REDUNDANCY IN THE PVS TRAIN OR BLOWERS IS LOST, STS MAY CONTINUE TO OPERATE TO ALLOW COMPLETION OF THE PRESENT STS CAMPAIGN AND THUS PREVENT GENERATION OF I EXCESS ZEOLITE DUE TO THE NEED TO DUMP PARTIALLY USED IX COLUMNS ON SHUTDOWN OF STS, TO CONTINUE OPERATION FOLLOWING LOSS OF FILTER TRAIN REDUNDANCY, THE PVS STACK MONITORING AND SAMPLING MUST BE OPERATIONAL AND THE PRESENT CA"?AIGN MUST REQUIRE LESS THAN 10 DAYS TO COMPLETE, l

4. CEMENT SOLIDIFICATION SYSTEM

? THE ELECTRIC POWERED BLWER (475-100) AND A DIESEL POWERED BACKUP BLOWER 475-101 SHALL BE AVAILABLE AT THE START OF A CSS OPERATIONS CAMPAIGN. IN ADDITION, BOTH COMPLETE FILTER TRAINS IN THE OPERATING AISLE FILTER SYSTEM (479-113A/B AND 479-114A/B) AND THE SIX-FILTER BANKS I IN'THE PROCESS ROOM VENTILATION SYSTEM (479-115A/B AND 479-116A/B), .[ SHALL BE OPERATIONAL AT ALL TIMES DURING PROCESSING. IF DURING A CAMPAIGN THE PT.IMARY BLOWER (475-100) IS. LOST, THE BACKUP BIDWER i (475-101) SHALL BE USED TO PROVIDE VENTILATION WHILE REPAILS % THE PRIMARY BLOWER ARE COMPLETED. IF REPAIRS REQUIRE GREATER THAN 10 DAYS VLA0321:3RM-1 Page 4 of 13 D t i 5 e

i OSR/CP 3 _{ Rev 4 THE CSS SilALL BE SilVT DOWN UNTIL FULL SYSTEM REDUNDANCY IS REESTABLISHED. WASTE PROCESSING SilALI NOT BE RESTARTE) UNTIL ADEQUATE j f BACKUP BlDVER CAPACITY IS RESTORED. IF A FILTER BANK FOR THE OPERATING AISLE OR PROCESS ROOM SYSTEM PECOMES INOPERI.BLE, AND AFTER 10 DAYS REPAIRS ARE NOT COMPLETE. Tile CSS SHALL BE SHUT DOVN, AND V\\STE I PROCESSING SHALL NOT BE RESTARTED UNTIL ALL FILTERS ARE liACK ON LINE.

5. VASTE TANK FARM VENTILATION SYSTEM t

i FOR FILTEPS (87+1/87 1A), BIhVERS (8K+1/8K.1A) AND WASTE TANK FARM VENTILATION CONDENSERS (SE.1/8E.1A), EIT}lER UNIT MAY BE USED WITil THE l REMAINING UNIT IN STANDBY. IF Tile UNIT IN SERVICE FAILS, Tile WASTE TANK VENT SYSTEM SHALL BE SWITCllED TO THE STANDBY EQUIPMENT AND IMMEDIATE EFFORT.SilALL BE INSTITUTED TO RETURN THE FAILED EQUIPMENT TO SERVICE.

6. SIZE REDUCTION FACILITY NO PROCESSING OPERATIONS MAY PROCEED IN THE SIZE REDUCTION FACILITY V-($RF) VITHOUT BOTH Tile HF.AD END (llEV) AND SRF ROOM VENTILATION SYSTEMS FULLY FUNCTIONAL. SilOULD EITilER Tile SRF ROO!! VENTI 1ATION SYSTEM OR Tile llEV SYSTEM BECOME INOPERABLE OR LOSE ITS REDUNDANCY, ALL PROCESSING OPERATIOC IN Tile SRF SHALL BE STOPPED IN AN ORDERLY FASHION AND Tile AREA

$Ect; RED FROM FURTilER OPERATION.

7. SUPER COMPACTOR THE SUPER COMPACTOR VENTILATION SYSTEM SilALL BE IN OPERATION DURING SUPER COMPACTOR OPERATIONS.

SHOULD ANY COMPONENT IN Tills SYSTEM FAIL, OPERATIONS SHALL BE SECURED IN A SAFE AND ORDERLV MANNER AND DISCONTINUED UNTIL REPAIRS ARE EFFECTED. l J i O " ' ^ " ' ' " " ~ ' i +

OSR/CP 3 7 4 Rev. 4 0 SUR'?EILIANCE REQUIREMENTS

1. SITE VIDE A.

PRLSSURE DIFFERENTIAL INSTRUMENTS (SEE CilART) VILL BE CALIBRATED ANNUALLY. THE ALARMS AND SWITC110VER CAPABILITY WILL BE OPERATIONALLY TE$7ED QUARTERLY. 1 B. ALL llEPA FILTERS USED AT THE WDP FOR RADIONUCLIDE REMOVAL SilALL BE DOP TESTED ANNUALLY AND AFTER EACH FILTER CilANCE; FRIOR TO ROUTINE SERVICE. WITil PARTICULATES OF AN APPROPRIATE SIZE TO ESTABLISH TilAT f THE INSTALLED FILTERS PROVIDE A COLLECTION EFFICIENCY OF AT LEAST 99.95 PERCENT FOR PARTICULATES 0.3 MICRONS IN DIAMETER OR INtCER. i ANY llEPA VilICll RAS BEEN OPERATIONAL FOR ONE YEAR MUST BE DOP TESTED l VITdIN 30 DAYS. + C. FOLI4 WING RECEIPT OF A LOW DIFFERENTIAL PRESSURE AIARM (SEE CilART) O THE VENTI 1ATION SYSTEM VILL BE SVITCilED OVER TO THE BACKUP llEPA i FILTERS AND THE INTEGRITY OF THE IIEPA FILTERS SHALL BE VERIFIED AND THE HEPA FILTERS REPIACED IF FAILED. D. Tile DIFFERENTIAL PRESSURE ACROSS THE FINAL OPERATING HEPA FILTERS (OR HEPA PLUS ROUCHING VilERE THE FILTERS ARE VITHIN Tile SAME FRAME) .SHALL BE MONITORED BY INSTRUMENTATION (SEE CHART). PRESSURE DIFFERENTIAL INSTRUMENTATION SHALL BE OPERATIONAL ACROSS EACll FILTER BANK AT ALL TIMES. THIS MAY BE ACCOMPLISHED BY lhV AND HICil PRESSURE LIFFERENTIAL RECORDER FOR EACH FILTER BANK. IF PRESSURE INhTRUMENTATION IS INOPERABLE. THE ASSOCIATED FILTER TRAIN SilALL BE OPERATED IN ACCORDANCE WITH LIMITING CONDITION FOR OPERATIONS mI.B UNTIL REPAIRS ARE COMPLETED. VIA0321: 3RM.I Page 6 of 13 k

OSR/CP.3 l Rev. 4 O

2. MAIN PLANT VOC IlEAD END VENT AND MAIN PLANT VENT A.

ALL V0G AND PIANT VENTILATION llEPA FILTERS SilALL BE CllANCED VilEN THE j SUSTAINED OPERATING PRESSURE DIFFERENTIAL, ACROSS Tile FILTER OR FILTER PLUS ROUGHING FILTER IF ENCIASED IN A COMMON ll0USING, EQUALS i OR EXCEEDS 8.$ INCHES W.C. AN EXCEPTION TO THIS IS TilAT THE VENTI 1ATION FILTERS IN SERVICE FOR CSS OFF.CAS OR BUILDING 01 14 l VENTIIATION SilALL BE CHANCED WilEN THE PRESSURE DIFFERENTIAL ACROSS { THE FILTER IS 6 INCHES W.C. l [

3. SUPERNATANT 7REATHENT SYSTEM A.

OPERABILITY OF THE STS BACKUP BihWER (S6K 201A), AUTOMATIC SWITCHING REIAY, AND PRESSURE INSTRUMENTATION (56PDR.229, 56PDR 230, l 56PDR 231, 56PDR 232) SilALL BE TESTED QUARTERLY. Tills CllECK S11ALL TEST Tile AUTOMATIC SWITC110VER, STARTUP AND OPERATION OF Tile BACKUP [ BLOWER (56K 201A). O i

4. CEMENT SOLIDIFICATION SYSTEM A.

OPERABILITY OF Tile CSS (BUILDING 01 14) BACKUP BlDVER (475101) AND Tile AUTOMATIC SWITCllING RELAY (2KTI/01 PDC-17) SHALL BE TESTED f QUARTERLY. TilIS CHECK SHALL TEST THE AUTOMATIC SWITCil OVER, STARTUP r AND OPEPATION OF Tite CSS BACKUP B1/ 'R. Tile BACKUP BLDWER SHALL BE RUN FOR 30 MINUTES DURING EACH TE I i i

5. WA.iTE TANK FARM VENT 11ATION SYSTEM j

OPERABILITY OF WTF BACKUP BLOWER (8K 1A) MANUAL SWITCHING, AND PRESSURE f INSTRUMENTATION (8PDR 2) SHALL BE TESTED QUARTERLY. THIS CHECK SilALL -[ TEST THE SWITCHOVER, STARTUP AND-OPERATION OF BACKUP BIDWER. I r i VLA0321:3RM.1 Page 7 of 13 k -f 'I I

OSR/CP 3 Rev. 4

6. SIZE REDUCTION FACILITY THE FIRST BANK OF llEPA FILTERS SilALL BE CllANGED VilEN Tile DIFFERENTI AL PRESSURE IS $ INCllES W.C. AND THE SECOND BANK OF llEPA FILTERS SilALL BE CHANGED kTEN THE DIFFERENTIAL PRES $URE IS 2 INCllES W.C.

Tile SYSTEM VILL A1 ARM AND AUTOMATICALLY SlfUT DOWN kHEN Tile DIFFERENTIAL PRESSURES ARE 5.2 INCllES W.C. AND 2.2 INCHES W.C. ACROSS THE FIRST AND SECONS BANKS OP -HEPA FILTERS RESPECTIVELY.

7. DRUM COMPACTOR Tile VENTILATION SYSTEM HICil DIFFERENTIAL PRESSURE A1 ARM VILL ALARM VilEN.

THE DIFFERENTIAL PRESSURE ACROSS Tile HEPA FILTER REACllES 3 INCllES W.C. THIS DOES.NOT SHUT THE VENT!!ATION SYSTEM DOWN BUT IS USED TO INDICATE Tile NEED FOR A HEPA FILTER CHANCE 0UT. IF THE VENTILATION SYSTEM SilUTS DOWN, THE IlYDRAULIC PUMP AUTOMATICALLY SifUTS DOWN WHICH PREVENTS FURTilER DRUM COMPACTION UNTIL THE VENTILATION SYS'IEK IS RESTARTED. BASIS The primary control of airborne radioactivity in the plant is provided by ' three ventilation systems. This OSR has been designed to assure the availability of sufficient ventilation capacity to provide the proper pressure differentials between process cells and occupied areas so that p? ant personnel are protected frein airborne activity, and to maintain in operation essential treatment systems for the retaoval of radioactivity from the ventilation streams prior to their release-to the atmosphere. Vessel off-gas systems (V00) provide equipment for the treatment of the airborne effluents from radioactive process vessels throughout the project facilities. These vessel off gases are condensed, scrubbed, heated, and . filtered prior to blower discharge to a stack.. If a V0G filter fails, confinement is maintained by the V00 backup filter (6T3 and 6T3A) and the VLA0321: 3RM.1 Page 8 of 13 i i .,.,_._m._._,_ _ _ _. _.. _. _, -, _. _, _ _, _,..,.. _.., ~. ~. _. -. -, - -,,

I OSR/GP.3 j Rev. 4 j l t O main ventilation system. which exhausts the spaces where the vessels on the V00 system are located. Should either a VOC filter or blower fail, immediate and continuing action shall be taken to return the failed unit to service.- l t I A !! EPA filter and a parallel alternate are installed in the comreon i discharge line from the V00 exhausters to the stack. These filters provide in depch protection against releases from a failed filter in the V0G system. The V00 limiting conditions for operation requires that one of the backup filters must be operable, llence, the spare must be maintained in [ t readiness.- i The main ventilation system controls the passage of air through tle process areas beyond the CPC from clean areas to successively more contaminated-f areas and filters exhausted air prior to discharge up the stack. To provide for continuous operation a standby filter exhauster unit is [ provided. If one of the filter banks becomes inoperable, plant operations f may continua for a ten day period without a spare while the filter bank is f being returned to service. Ten days permit filter replaceinent without upsetting maintenance programs, yet entails minimal risk of being without a spare. If both filter exhauster systems are inoperative at the same time. an orderly shutdown must be initiated. I l 1 - The } lead End Ventilation (!!EV) system controls air flows for the mechanical j processing a, teas, the CPC and the manipulator repair and decontamination building. Like the main ventilation system, the head end ventilation l system includes independent filter systems and blowers as alternates. The llEV system has more flexibility since either. filter bank can be operated with either the electric driven or the propane-driven blower. The llEV system includes an even greater defense in depth since double llEPA j filtration is used. The operability requirements for !!EV are similar to - those established for the main ventilation system. Should the llEV system become totally inoperable, an orderly shutdown of the SRF must be i ini tia te d'. f i O VLA0321:3RM.1 Page 9 of 13 { I h 1 %g-- 4 ,t-4e m e

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OSR/GP 3 Rev. 4 f Filters are provided both in parallel and in series in the STS Permanent Ventilation System. This allows for redundancy should failure of a filter or a complete air cleaning train occur and to permit continuous filtration j f during filter changeout. Proper performance and operation of the Permanent Ventilation System and the stack effluent monitoring and sampling system is [ necessary to ensure radioactivity released in airborne effluents from the l STS is maintained within DOE limits and A1 ARA. -f v i in the event of loss of ventilation system redundancy during operation of ( STS and CSS. operation will continue provided immediate actions are taken to resolve the problem and the problem can be repaired before the start -of f the next campaign. Shutting down in less than ten days will impact 1RTS in I that more zeolite will be used, and thus more waste may be generated. PVS ventilates STS building which has low activity since WTFVS vents STS f process vessels, whfch contains the radioactive material, likewise the CSS [ ventilation of 0114 Building is a low activity source. The ten days } required to complete an STS campaign is based on processing 15,000 gallons -f t of supernatant, diluted with 30,000 gallons of water, at a 3 gpm flow [ ,O CSS is required to be available to process deconned supernatant from rate. STS and thus must also meet the ten day limit. Filters are provided both in parallel and in series in the 01 14 Building System. The cell ventilation air passes through the Procese Room t Wntilation System which includes one bank of filters, made up of six ilEPA j filters in parallel, followed by a second set of six HEPAs. Individual filters may be valved out to allow replacement, providing that no new filter is on line for 24 hours without passing a DOP test. However, under F normal operation all six sets of filters must be in operation, t 4 ? The filter room exhaust is filtered prior to di,scharge through two parallel trains consisting of a roughing filter and llEPA filter in series. Pressure j differential monitoring instrumentation is provided in several forms. f Pressure differential alarms (low) are installed across each filter. I i whereas pressure differential alarms (high) are installed across each bank i of filters. These instruments are backed up by pressure differential f O 1 VIA0321 : 3RJ1 1 Page 10 of 13 f I. . a.- ..,_..._,.,__.._u.a__.___._.___.__._______.___._.______________!

5 ~ OSR/CP.3 f Rev. 4 6 recorders. The Stack Monitor will provide an isokinetic sample ef ventilation discharge from-the 01 14 Building stack and will monitor to l assure that this discharge is within DOE limits. The alarm point is set l sufficiently low to assure that the system can be shutdown until the cause of elevated activity can be identified without violating the discharge limit. The SRF exhaust ventilation system provides positive control of airborne contamination in the SRF. Failure of this system would result in a i reduction of ventilation capacity with reliance on the HEV to maintain a } minimum airflow for contamination control. Failure of the.HEV would result 1 F -in a loss of ventilation capacity to the 1 ADS system, the MSM decon stall, and a loss of backup capacity for the cutting and decon areas. Loss of f either system results in a reduction of the ventilation capacity, below an f acceptable margin of safety to permit continued operation, j i i Safety Analysis Report, Volume IV, Rev. O of February 10, 1988, for _j ' Low Level Class. B and C Radioactive Waste Handling and Disposal Operations f for the Radwaste Treatment System Drum Cell" analyzed maximum potential f release of airborne radioactivity to the Drum Cell air during accident j conditions. Based on the results of these analyses it was shown that HEPA .{ filtered ventilation for the Low Level Class B and C Vaste Storage Drum l Cell was not required. Because of the potentially large inventories of radioactivity on the main l ventilation filters and the HEV futer, redundant instrumentation is [ provided. In addition to the stack monitor, performance of the operating i filter is monitorad by dual differential pressure recorders and high-- f differential pressure alarms. The primary set of instruments monitors the f HEPA filters which are the final barrier to radioactivity release and the l ~ alternate set monitors the entire filter stage. [ I V1A0321:3RM 1 Page 11 of 13 ,,--,.__..____.___.._,___,_.,__-;_._.,__,,.__-....__.,,,..._.,..,_.,._,-,,,..c

OSR/CP.3 Rev. 4 f (~ \\ The vaste tank off gas system condenses and filters gaseous ef fluents from the storage tanks during normal operations. 1he PVS is used to ventilate j HLW tanks when penetration such as tank risers are open to provide access to the tanks. In the VTFVS system independently spared equipment (i.e., condensers, filters and blowers) is provided. Failure of an in.line component will require a switch to the alternate standby component. Since a failure would decrease the defense in depth, high priority is given to the repair of a failed component, j A1*fACIMENTS Ventilation System blower, Filter and Instrument Chart j R EFERENCF.S NFS Tech Specs, Change No. 12 VVDP SAR 004, Volume III, Part D VVHS Hemo HE:86:0113, " Transmittal of SuR for the MSM Size Reduction / Decontamination Facility," J. P. Englert to P. J. Valenti, June 1986. OTHER APPL.1CAFLI.E OSRs OSR/CP.1, WDP Airborne Radioactivity Release Limits OSR/CP.10, Airborne Effluent Monitoring Syste.m Operability ,q VIA0321:3RM 1 Page 12 of 13 b

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.m. I 4 l I [ i r Nc. Numoer OSR/GP-4 f R6visien Numeer 2 i Revision Cate o g-2 7_m i Engineering Release #1430 } Per ECN #3353 l L West a ey ~ 36fnOnStrGiiOn U FO:ect l OPER ATICNAL SAFEM RE0f)IREVENTO (

0. R. Staffes Date PP.EPARED E Cognizan:, Enginee /

l Cata5,! If APPROVED.hk + C. J. R:berts Cpgni: ant Manager [ O d n0 A L l# #- 5 .O ( ArenUVLp 61. r u rt. L -- R. A. Mumphrey Ca t e j /?.4 /A"r Racl.ation & s [ ce,=mutee,hSafety Q air =n APPROVEDSYf W-m D. L. Shugars Cate E/b N / l -Quality As ura.%e APPROVED BY M P., F. Cessner Date [ 8 LL4 Trea =en* Pr Jgy# i APPROVED EY .m , WL ms. J. L. Knabensenuh Date 6%2c/TT i i /Raciological & Enytronmental S' ety. Manager bb' I'4 ck R. E. Lawrence, Jr. Cate i/ /" a f APPROVED BY Supernatant Tetatment Project Manager West Vcliey Nuclear Services Co. P.O. B o x 191 e West Valley, N.Y.14171-CISI RI43249: SEA-65 [ DOE Approved: DW:91:0530 [ W -1816 ECB Concurrence: 08-10-91 ? l [ t 9 i ... ~

OSR/CP 4 Rev. 2 RECORD OF REVISION FROCEDURE If there are changes to the procedure, the revisioni number increases by one. These changes are indicated in the left margin of the body by an arrow (>) at n the beginning of the paragraph that contains a change. ) i Example-i The arrow in the margin indicates a change. { i l I -Revision On-L Rev. No. Description of Changes Page(s) Dated 0 Original Issue All l! 1 Dated S/20/G8 All 1-Engineering Release 1430 N/A 08/88 2 Per ECN 3353 Page 4 08/91 3 i t b s t W 1807, Rev ' 1 i LLK0127:3RM-1 l i. 1

t j' OSR/GP 4 l Rev. 2 j RECORD OF REVISION (CONTINUATION SHEET) lO Revision on Rev. No. Description of Changes Page(s) i I i l l t i 9 + l I l- { l I i l f !~ l t: 1 l I t l' !t 1i I W 1807, Rev.1 11 - LIIK0127:3RM 1 t.. i i. , _ ~ -, - - -. ~,.

.. _,.... -.. - _ _ _. _ _ _ _ _.. _ ~....... _ _ _. _ _.. _. OSR/CP 4 l Rev. 2

v m.m me s

= O i i l l l TYPE: } TITLE: Effluent a6vi Envirorumental l NUMllER: CENPLNT OSR [X) l Monitoring l 4 I I I Tech. Reqmn't. [ ]l-l 1 l CRITERIA: 1. Provide demonstration that project effluent release to off. site environs is trithin DOE limits. i UNACCEPTABLE INENTS: 1, Urnonttored radiological and nonradiological releases to the envirornent. l. I i Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED O LCO j' l UOR l LCS l l l Surveillance Riqmn't. l X l l l l l l I l -Tech. Requirement l l _1 DOE.WPO CONTR0!. LED._ l l I Operating Limii l i lWNS CONTROLLED IMPLEMENTING PROCEDURES: EM Procedures WDP Environmental Monitoring Program Plan - > S0P 15 1 > SOP 15 41 ene LLK0107:3RM 1 O

OSR/CP 4 Rev. 2 OPERAv10NAL SAFETY RrQUlHIMENT EFFIEENT AND ENVIRONMENTAL MON 11DRING APPL.ICA!Lil.1TY This OSR applies to the sampling and analysis of airborne and 11guld plant effluents sind to the routine environmental monitoring program. OluECTIVE To establish the requirement for an environmental monitoting and reporting program. SPECIFICATION SURVEILIANCE REQUIREMENT I EFFLUENT AND ENVIRONMENTAL MONITORING SHALL BE PERTORMED IN ACCORDANCE WITil THE DOE-APPROVED ENVIRONMENTAL MONITORING PROGRAM PLAN FOR VVDP. ILASIS DOE-ID Order 5484.1 requires that each DOE facility monitor liquid effluents and gaseous emissions from facility operation to determine compliance with the requirements of DOE.ID 5480.1, Chapters I, XI, and XII, evaluate the ef fectiveness of effluent treatment and control, to maintain radioactivity inventory and to determine compliance with all DOE, EPA, state agency imposed effluent limits and other environmental commitments, e.g., those published in environmental impact statements or other official documents. The order also requires that radioactivity released to on site waste treatment or disposal systems be monitored to assess the efficiency of treatment and control and to provide a quantitative and qualitativo annual summary of the radioactivity released on site, In addition, the order identifies monitoring [ guidelines and tionitoring data recorakeeping and reporting requirements. O LLK0127:3RM-1 Page 1 of 2 ) i e',,,,, _.., ,,,j,,,r ,,.,c. _%.p,,,,,,_,,,,,w_y,,, ,.-_.-..,__.7 ,,,,_gy-,

k t OSR/CP 4 Rev. 2 l An Environmental Monitoring Program is developed to assure that liquid effluents and () gaseous emissions from UVDP operations activities are monitored and comply with DOE. ID 5484.1 requirements and that environmental effects from the VVDP are minimized, e i ATTACIMENTS i None l _R_E_F7RENCES 7 the Environmental Monitoring Program is designed to assure compliance with f f i DOE Order Orders $484.1, Chapter III, " Safety Requirements for the Packaging of { Pissile and Other Radioactive Material" [ DOE ID order $484.1A, Chapter III, " Effluent and Environmental Monitori.,g Program { Requirements" DOE Order 5480.1A, Chapter XII " Prevention, Control, and Abatement of Environmental [ Pollution" { DOE ID Order 5480.1, Chapter X11 " Prevention. Control and Abatement of Environmental Pollution" f i DOE Order $480.4, " Environmental Protection Safety, and Health Protection Standards" i r DOE Order 5480,1A, Chapter XI, " Requirements for Radiation Protection" DOE Order 5480.14 " Comprehensive Environmental Response, i Compensat on, and Liability r Act (CERCLA) Program" l [ DOE ID $100,4B, " Quality Assurance" f 1986 WVDP Environmental Monitoring Plan [ i LlX0127:3mi 1 Page 2 of 2 ..~,_ ~.

m /*U Occ. Num:er OSR/GP-5 Revisien '!ue:er 3 Revi 1:n 04:e 08-27-91 Dgineering Rele3Se #1430 Per Ech 2832 Per ECN #3353 a, e yu v u l e_ y.. Jemonstration Pro lect L C.: r. $. 4'.. '..'.' t 'a' e. r..' *?..".'..*r*'.e'.'".' f-M/. T D.

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,) cg... : ar.: m v A???.07ED ET f F.. A. Mu=;n. ey O a t e./ 0 f _s a f'i:;10 :n 4 (lare ty Q l Cr..L:: s e. 8 \\ C.a L r:an i A??E0VI; !? ) th_. e D. L. Ehutar Ca : a / w Cg'e-- e c:- - e qua _ :y A: = u r a.~: e I i d .) / AP?E0vt: z: [5C&h/ ?.. F. C. :. e r ca:e.5/23.7 d' L:'., Tre u zer.- irv ept )f w J. L. Kr.2: e r.::nu. Ca:e c-A, /TT h :4, APPROVI: E: -%p 4 ha:::1 g:.:21 4 Ir.v '. re r.r e n t a ; Sa(4:7..".2.a s e r -Md.U ' !, R. E. Lr-.e.*:e, Jr. Ca:a ti' k!o 3 APPEOVEO &T superna:an: Tr e a::er.: Pr:Jee: P.ac.a ge r West Vciley Nuclecr S ervices Co. P.O. E c x 191 West Ve!!ey, N.Y.14171-Cl91 DOE Approved: 9W:91:0530 V) W'/ - 15 t $ ECB Concurrence: 08-10-91 i 3 I T I i n

OSR/GP.5 Rev. 3 f RECORD OF REVISION PROCEDJRE I If there are changes to the procedure, the revision number increases by one. These changes are indicated in the left margin of the body by su arrow (>) at the beginning of the paragraph that contains a change. Exarnple,: ( The arrow in the reargin indicates a change. Revision On Dated Rev. No. Description of Changos PaSe(s) 0-Original Issuo All 1 Dated 5/20/88 All 'l Engineering Release 1430

N/A 08/88

.l i 2 Per ECN 2832 Cover Page, 2 10/89 3 Per ECN 3353 Page 4 08/91 t i p I 4 l l l' } !~ i l l' l-i v-l l. b l 'W 180 7, R'ev. 1 i ~ -DLS0336:3RM 1 l i l. i: l -'. l I'

. _. _,~ - = --__ _ - -. _. _ __ _ = __. __ i i OSR/GP 5 Rev. 3 RECORD OF REVISION (CONTINUATION SHEET) O l Revision on li Rev. No. Description of Changes Page(s) i i I l \\ } a- !, O I l l I l l l l. l l-i i i f I W-1807, Rev. 1 - 11 l DLS0336:3PJi 1 I 9 1 i t

OSR/GP 5 i Rev. 3 { [ t O l l l TYPE: l TITLE: WDP Emergency Powet l NUMBER: GENPLNT I f OSR [X) l Requirements l 5 I l Tech, Reqmn't. [ ]l l I I f I CRITERIA: 1. Prevent the _ loss of critical systems during power outages or failures which could result in release of radioactivity to off site environs, j i } r UNACCEPTABLE EVENTS: 1. Loss of function of critical plant electrical loads durinh interruption of _ normal power. f i i ) t t { l l l Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED O. LCO l X l UOR l MS l l l Surveillance Reqmn't. l X l l l l l 1 j l l l Tech. Requirement I i l DOE WPO CONTROLLED i l i I -Operating Limit i ,, _j_,_ lWNS CONTROLLED E IMPLEMENTING PROCEDURES: f SOP 30 1 > SOP 50-36 i SOP 30 3 > SOP 50 37 [ SOP 30 5 > SOP 50 44 -SOP 50 26 > SOP 56-2_ SOP 70 19 > SOP 70 4 i > SOP 15 9 > S0P 70 11 l > SOP 15 11 > SOP 70 14 -> SOP 15 20 > S0P 70-15 l > SOP 31-2 > SOP 70 16 > S0P 50 35 > S0P 70 30 } s DLS0336:3RM l' O 1 I t i i t*

i i OSR/GP 5 i Rev. 3 I f OPERATIONAL SAFETY REQUIREMENTS VVDP ENERCENCY POVER RIX}UIREMENTS j APPL.1CABILITY l I This OSR applies to systems, instruments, and equipreent required to supply emergency services at the VVDP. I OluECTIVE I The OSR specifies items of equipment that shall be operable to prevent an unsafe plant or process condition upon interruption of normal electrical power, to assure l capability for a safe shutdown and to maintain vital services throughout the power f

outage, i

l SPECI FICATION O j

1. LIMITING CONDITIONS FOR OPERATION t

A. EQUIPMENT LISTED IN TABLE I SilALL BE CONNECTED TO AP EMERGENCY POWER SERVICE. f i l B. THE QUANTITY OF DIESEL FUEL IN Ti!E OIL STORAGE TANK (31D 2) SilALL, DURING I NORMAL OPERATIONS, BE MAINTAINED AT 8,000 CALLONS OR MORE OF DIESEL FUEL. ViiEN TliE GENERATOR IS IN OPERATION, A MINIMUM VOLUME OF 4,000 CALLONS OR I GREATER SilALL BE MAINTAINED, A VOLUME LESS TilAN Tills MINIMUM VALUE WILL REQUIRE Tile COMMENCEMENT OF PLANT SilUTDOWN WillCil SilA1.L CONTINUE UNLESS Tile PRIMARY FUEL (NATURAL CAS) SERVICE IS RESTORED OR Tile FUEL DIL SUPPLY IS i REPLENISilED. i r f e i t DLS0336:3RM 1 Page 1 of 6 f I L

OSR/GP 5 l Rev. 3 1 C. Tile QUANTITY OF PROPM'E FUEL IN THE L'ROPANE STORAGE TANK (15D.3) SilALL, DURING NORMAL OPERATIOFS, BE MAINTAINED AT 600 Gall.ONS OR MORE. IF USED DURING l ABNORMAL CONDITIONS, OPEFATIONS MAY CCNTINUE AS thNG AS A VOLUME OF 300 l CALLO!45 OR GREATER 13 MAINTAINED, A VOLUME 1.ESS THAN 300 GALLONS VILL REQUIRE COMMENCEMENT OF CliUTDOWN OF OPERATIONS VHICll SilALL CONTINUE UNLESS Tile PROPANE SUPPLY IS REPLFNItiHED. i D. AT LEAST 400 CALIDNS OF DIESEL FUEL DEDICATED TO STS SilALL BE AVAILABLE ON-SITE WITH A MINIMUM OF 200 CAL 10NS IN THE STS EMERGENCY DIESEL STORAGE TA!M, E. AT LEAST 24 CALIANS OF DIESEL FUEL DEDICATED TO CJS SilALL BE AVAI1ABLE ON-SITE.

2. SURVEILIANCE REOUIP.EMENTS t

A. Tile EHERGENCY GENERATOR (30T 1). AIR COMPRESSOR (31K 1) AND Tile COOLING VATER PUMP (32G.4B) SMALL BE OPEPATED AT LEAST ONCE EVERY CALENDAR QUAR'IER NOT TO EXCEED 120 DAYS TO DETERMINE Tile AUTOMATIC START CAPABILITY AND THE -FERFORKANCE FOR AT 1.E&ST ONF. HOUR UNDER AN OPERATING LOAD. i I B. Tile EQUIPMENT LISTED BELOW SHALL BE OPERATED AT LEAST ONCE EVERY CALENDER QUARTER TO DETERMINE PERFORMANCE FOR AT LEAST ONE HOUR UNDER AN OPERATING LOAD. l BOILER FEED PUMP 3 310 2 AND 31G.2A BOILER DRAFT FANS 31K 2 AND 31K.2A t PLANT WATER PUMPS 32G 2A AND 32G-2B f ll ) .I i ? ? .o DLS0336:3RM.1 Page 2 of 6 f { r i l,- l r l:..: u., -... --.-.-. ---a ~.----.---..- -.,-..-.----,-.a

OSR/CP 5 Rev. 3 C. THE AUXILIARY HEV B14WER (15R 21) AND HAIN PLANT SPARE EX1tAUST BthWER (15K. 10A) SHA1.L BE OPERATED AT LEAST ONCE EVERY THREE MONTHS TO DETERMIhE Tile AUTOMATIC START CAPABILITY AND Tile PERFORMANCE FOR AT LEAST ONE HOUR UNDER AN OPERATING LOAD. D. THE STS EMERGENCY POWER GENERATOR SOP 1 SilALL BE OPERATED AT LEAST ONCE OVER EACH CALENDAR QUARTER (NOT TO EXCEED 120 DAYS) WITHOUT ELECTRICAL 14AD FOR 30 MINUTES AND WITH ELECTRICAL LOAD FOR ONE HOUR. E. INSPECTIONS OF THE EMERGENCY CENERATORS, FUEL SUPPLIES, AND PROPER ALIGNMENT 0F SWITCHES, VALVES, ETC., REQUIRED FOR STANDBY OPERATION SHALL BE MADE, AND RESULTS RECORDED DAILY. F. THE CSS DIESEL POWERED BihWER (475 101) SPA 1*. 8E OPERATED AT LEAST ONCE OVER EACH CALENDAR QUARTER (NOT TO EXCEED 120 DAYS) FOR A PERIOD OF 30 MINUTES). C. THE PVS (56K 201A, 56K.201) AND WTF BIDWERS (8K 1, 8K 1A) SilALL BE TESTED EACH CALENDAR QUARTER (NOT TO EXCEED 120 DAYS) TO DETERMINE THE AUTOMATIC RESTART CAPABILITY OF THE BIDWER HOTORS. BASIS Auxiliary power must be provided to maintain vital services throughout a power outage. Continuous ventilation and effluent monitoring is required to assure the containment of airborne activity. This OSR assures that auxiliary power services are available to vital STS components. Emergency power is also required to safety shutdown the CSS process while maintaining the containment provided by the 01 14 Building IIV System. To shut down the CSS requires that the cement mixers be emptied and flushed. The above specification provides for this. DLS0336:3RM 1 Page 3 of 6 r 5

t OSR/CP 5 Rev. 3 Once the CSS is shutdown, ventilation will still be required to assure the containment of airborne activity. Backup ventilation is pro 'ided by a diesel driven blower. This specification assures an adequate fuel supply is on hand for this blower. The minimua fuel supply provides suf ficient time to restore power or obtain more iuel. Instrumentation and lighting will be required to monitor the system during its shutdown status. Backup power for these services is assure d by this specification. A17AC1MENTS Table 1 Charts REFERENCES None O k e i l O LLS0336:3Ph i PaSe 4 of 6 e ,.~...__c. ,,_,._._,,.r__,_,,.,.,m_,.,,,pwy..., ,m. y.

OSR/GP.5 Rev. 3 TABLE I: EQUIPMENT VilICll SilALL BE SUPPLIED WITil EMERCENCY POWER O Equipment Designation 1. Stack Monitoring Systems See Table 2 2. Electrically operated controls and relays See Table 2 utilized to switch-blowers or filter trains 3. liigh Shear Mixers (and associated 70.K.002, 70.K.004, hydraulic system); Hixer control Panel .llSCSS Panel 4 Building 01 14 Lighting LP.EE3 5. Ventilation Filter Instrumentation See Table 2 6. PVS Blower Motors (2) $6K 201, 56K 201A 7. WTF Blower Motors (2) 8K 1, 8K-1A O CLS033C:3RM 1 Page 5 of 6

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c. Num:er _ _ TR / GP-6 Revis1:n Nu :er 2

Revis ten Oate 28 H-g1 Engineering RelenJe #1430 Per E04 #3354 West a ey Demonstration a ro'ect CPERA*:0NAL SAFE 7! RE;UIRCME!!*$ M C. R. 31stfes Cate T "o PRE?ARE cosnt:an: Ensineerg C. J. Acterta Cate M W APPROVED,'k b b0 [ ~~ Cpgnt: ant Manager Date !"/kc APPROVED BY Y R. A. Hum;nrvy 2 8 F.i;1at;Cn & lfaf e ty Q % Cc,mmi, tee, dhairman APPROVEDBY/ ) W ~m D. L. Shugare Cate [ b $ b I Quailey A urE e APPROVED BY- / W M R. T. Cessner Oate I 7 APPROVED BY J. L. Knacensenuh Date f/ 6 / W /h4C1010g10a1 & EaVironmental / sv ety. Manager Cate i /1 /o a APPROVE 3 SY Lu.N l'i6 R. E. Lawrence. Jr. supernacant treataanc -Project Manager West Vcliey Nuclear Services Co. P.O. Eox 191 West Vciley, N.Y.14171-CISI DOE Approved: IM:90:0214 LLK0129: 3R+-1 ECB Concurrence: 08-10-91 WV-1816 ., M

1 1i' TR/CP.6 Rev, 2 RECORD OF REVISION 1-l PROCEDURE 1 If there are changes to the procedure, the revision number increases by one. These changes are indicated in the left. margin of the body by an arrow (>) at the beginning of the paragraph that contains a change, i.. l Example: i ( The arrow-in the margin indicates a change. i l l ) Revision On Rev. No. Description of Changes Page(s) Dated 1 0 Original Issue All l 1 Dated $/20/88 All 1. Engineering Release N/A 8/88-2 Per ECN 3354 Page 4 08/91 i I i i. l l O WV.1807, Rev. 1 i LLK0129:3RM 1

TR/GP 6 Rev. 2 RECORD OF REVISION (CONTINUATION SilEET) Revision on Rev. No. Description of Changes Page(s) O W 1807, Rev, 1 11 LLK0129:3RM 1

TR/CP 6 Rev. 2 i \\ I l-TYPE: - l TITLE: Storage Requirements for l NUMBER: CENPLNT - OSR [ } -l Low Level Vaste l 6 I I - Tech. Reqer.' t (X)l l .... s 1 - l CRITERIA: 1. Avoid spread of contamination to radiologically clean areas, i i. UNACCEPTABLE EVENTS: 1. Contamination of clean areas. l t -l l 1 Safety Limit l l Reporting Re.airements: l DOE-ID COFIF.. ' E! 'LCO l l l LCS .l l l [ .Surreillance Reqmn't.. l l l 1 1 I a Tecig. Requirement I X l Critique 1 DOE-WPO CONTu,. LED f I i i Oparating Limit l l IWNS CONTR01 LED } IMPLEMENTING PROCEDURES: l SOP 9-2 -[ > SOP 02 5 > SOP 9-5 l > SOP 9-7 i { > SOP 80 5 -t i ~ I LLK0l?,9:3RM 1 O t i i ---s-r m r a m-- 'Yw

.;p - TR/GP 6 Rev 2 TECHNICAL REQUIREMENT f STORACE ftEQUIRFMENTS EVR IDW LEVEL WASTE APPLICABILITY These requirements establish the limits for low level and transuranic was:e package types, contents, placement, external dose rates and surface contamination of radioactive low level wastes stored in the Lag Storage Facility and sprung structures. OBJECTIVE The objectives of these requirements are to assure that appropriate radiatior, protection measures are in effect for facility operation, and physically safe configurations are maintained. TECHNICAL REQUIREMENT (D

1. DOSE RATE AT THE SURFACE OF UNSHIIADED PACKAGES IN THE LAG STORAGE FACILITY SHALL BE LESS THAN 100 MREM /HR, IF THE SURFACE DOSE RAT' EXCEEDS 100 MREM /HR, THE PACKAGE SHALL BE COVERED WITH A SHIELD OVERPACK SUFFICIENT TO REDUCE THE DOSE RATE TO LESS THAN 100 MREM /HR.

2. DOSE RATE AT ANY POINT 18 INCHES FROM THE EXTERIOR SURFACE OF THE LAG STORAGE AREAS SHALL BE LESS T!iAN 2,5 MREM /HR.

3, SHEARABLE (REMOVABLE) SURFACE CONTAMINATION ON THE WASTE PACKAGES IN THE STORAGE FACILITIES SHALL BE LESS THAN 50 DPM C5' ALPHA AND 500 DPM OF BETA ACTIVITY PER 100 SQUARE CENTIMETERS. A. ONLY NONCOMBUSTIBLE CONTAINERS AND MATERIALS HANDLING FIXTURES (PALLETS, SKIDS, ETC.) ARE PERMITTED INSIDE THE BUILDING, 1 O l Q LLK0129:3RM 1 Page 1 of 2 ~

TR/GP 6 Rev, 2 THE LAG STORAGE BUILDING WILL BE PROVIDED WITH A FIRE DETECTION SYSTEM WITH LOCAL u!. AND REMOTE ALARMS, IN ADDITION TO PORTABLE FIRE EXTINGUISHERS REQUIRED FOR PERSONNEL PROTECTION. I

5. ALL STANDARD CONTAINERS SHALL BE SEALED AND SECURED,

6. DRUMS SHALL fE STACKED ONE ON TOP OF ANOTHER IN A PYRAMID CONFIGURATION TO A MAXIMUM OF TlREE HIGH, OR STACKED ON NONCOMBUSTIBLE SKIDS TO A MAXIMUM OF FOUR HIGH, WHEN STACKING DRUME IN THE PYRAMID CCNFIGURATION, EACH DRUM, FROM SUCCESSIVE LAYERS OF DRUMS, SHALL BE STACKED ON AT LEAST FOUR DRUMS.

7. STEEL BOXES SHALL BE STACKED ONLY ON STEEL BOXES AND ONLY TO A MAXIMUM OF FOUR v

HICH,

't hASIS Radiological control requirements arise from the Project Radiological Controls Manual (WVDP 10). l i Potential for off site dose as a result of fire in the Lag Storage (Butler) building i is as a result of TRU wastu storage in this facility. Since TRU waste is not stored ~ on-site except for in the Lag Storage (Butler) building, fire detection equipment is not addressed in other facilities. [ ATTACHHFRTS i i None REFERENCES " Low-level and Transuranic Waste Interim Storage Facility Safety Analysis"; Rev. O, HE:85:0021, February 8, 1984 Memo HF:84:0081, J. Goodman to R. E. Lawrence, " Response to the Radiation and Safety Committee Request for Drum Stacking Clarification", dated May 9, 1984, { LLK0129:3RM-1 Page 2 of 2

k Doc. Numoer OSR/GP-7 ,( Revision Nuncer 2 .% vision Date 08-27-91 Digineering Release #1430 Per #3353 a e 6o~f u'*' . c y' ' ^ Jemonstration o ro. ect OPER AT:CNAL SAFE'Y RE*:UIREv.E!!TS

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/* ~ PREPARED $! j. wl:[N ~/ f . M/.aT D. R. Steffes Cate T /A' 'M Cogna:an; Ing:. nee,/ ? APPROVE 3,k,k C. J. Roberts Date$/ Ef Cysit:an: Manager 'l APPROVED BY fb

n. A. Humpnrey Cate [b4 b

Rictatton &gSafety-Q t C:r~. L;:ee, Chairmau APPROVED SY v3 D. L. Shugars Da te E/ b Quality As.*ura e I r APPROVED SY M M R. F. Cessner Oate I d' LLW Teeaj / / p p'. Ic..AlJ. L. Knacenscnun

eny Pro

.m},S', Da:e.$b /TK APPROVE 3 SY .actolog::a1 & Environmental SMe ty. Manager APPROVED SY / bM.!M6 R. E. Lawrence,.lr. Ca te i /3. / > a Supernacanc Treatmen: Pro,!ect Manager West Vcliey Nuclear Services Co. P.O. Ec x 191 West Valley, N.Y.14171-CISI RIr3258: SEA-65 DOE Approved: DW:91:0530 ECB Concurrence: 08-10-91 g, ggg t t

OSR/GP 7 Rev. 2 } RECORD OF REVISION PROCEDURE If there are changes to the procedure, the revision number increases by one. These changes are indicated in the left margin of the body by an arrow (d) at the beginning of the paragraph that contains a change. Example: The arrow in the margin indicates a change. Revision On Dated Rev. No. Description of Changes Page(s) 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release 1430 N/A 8/88 2 Per ECN 3353 Page 4 8/91 WV-1807, Rev. 1 i LLK0130:3RM-1

t i -OSR/GP-7 n. Rev. 2 i RECORD OF REVISION-(CONTINUATION SHEET) c. Revision on . Rev, No. Description of Changes Page(s). T i I r r ( i i 5 !'t i i i 1 L i I 1 e i.t ? I ) ? r i r r i r i l W-1807, Rev, 1 it =. LLK0130:3RM 1 Ii

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OSR/GP 7 Rev. 2 o l l-TYPE: l TITLE: Criticality _ Safety for Liquid { NUMBER: '.a tLNT OSR [X) l Transfers j 7 I I Tech. Reqmn't.'[ ]l l-1 l CRITERIA: 1. Prevent criticality i UNACCEPTABLE EVENTS: 1. Inadvertent criticality. l l I Safety Litnit l-X l Reporting Requirements: l DOE ID CONTROLLED LCO l X ] UOR l .LCS l l l 3 \\ Surveillance Req m't. l X l l l 1 l l l l Tech. Requirement i l IDOE-WPO CONTROLLED i. 1 I I [ Operating Limit l l lWNS CONTROLLED >ItiPLEMENTING PROCEDURES: _EP 007 EP 008 EP 011-SOP 7-8 SOP 71-1 l. SOP 71 2 [- SOP 71 ! SOP 71-16 i LLK0130:3RM 1 LO 1 L t I ........ _ _. _. ~. _ _..... _, _... _.. ~.. _. _. _ _ _ _ _ _ _. _ _ _.. _ _... _ _

OSR/CP 7 Rev. 2 OPERATIONAL SAFETY REQUIREMDITS .r. CRITICALITY SAFETY IVR LIQUID TRANSFERS APPLICABILITY This requirement applies to all liquid transfers of fissile material at the VVDP except for transfers of decontaminated supernatant within the IRTS system. ORJECTIVE The objective of this requirement is to assure that all liquid transfers of fissile material are conducted in a manner which has no potential for an inadvertent criticality. SPECIFICATIONS SAFETY LIMIT NO LIQUID TRANSFERS SHALL BE MADE THAT WILL RESULT IN EXCEEDING A k,gg 0F GREATER THAN 0.95. LIMITING CONDITIONS FOR OPERATIONS

1. FOR UNRESTRICTED AND UNLIMITED LIQUID BATCH TRANSFERS, FISSILE MATERIAL CONCENTRATION SHALL NOT EXCEED THE VALUES LISTED IN TABLE 1.

2. SAMPLING AND ANALYSIS IS THE PREFERRED METHOD TO VERIFY FISSILE CONCENTRATION.

HOWEVER, VERIFICATION MAY BE BY USE OF PREVIOUS DOCUMENTATION kHICH IS TRACEABLE TO SAMPLE ANALYSIS. IF THE FISSILE MATERIAL CONCENTRATION OF A TANK IS VERIFIED BY MEANS OTHER THAN DIRECT SAMPLING AND THE TANK IS PART OF A SYSTEM INTO WHICH FISSILE MATERIAL HAD BEEN TRANSFERRED OR THE TANK IS PART OF AN ACTIVE WASTE SYSTEM IN WHICH FISSILE MATERIAL IS SUSPECTED PRESENT, WRITTEN CONCURRENCE AND/0 AUTHORIZATION OF THE RADIATION AND SAFETY MANAGER SHALL BE REQUIRED PRIOR TO TRANSFER. IN ADDITION, THE SYSTEM MUST BE ANALYZED TO ENSURE THAT PROCESSING WILL NOT CONCENTRATE FISSILE MATERIAL BEYOND THE LIMITS SPECIFIED IN TABLE 1 AND THAT SAMPLES DRAWN ARE REPRESENTATIVE OF THE ENTIRE VESSEL CONTENTS. V LLK0130:3RM-1 Page 1 of 5

OSR/GP 7 Rev. 2 SURVEILLANCE REQUIREMENT: \\ FISSILE CONCENTRATION SHALL BE VERIFIED BEFORE EACH TRANSFER AND SHALL INCLUDE, AS MINIMUM, DETERMINATION OF THE FISSILE MATERIAL CONCENTRATIONS OF BOTH THE " SENDING" l AND " RECEIVING" TANKS WHICH COULD POTENTIALLY CONTAIN FISSILE MATERIAL. FOR UNINTERRUPTED BATCH TRANSFERS OR OTHER ROUTINE TRANSFERS VHERE THE FISSILE CONCENTRATION IN EACH INTERMEDIATE AND RECEIVING TANK HAS BEEN PREVIOUSLY VERIFIED TO MEET TABLE 1 REQUIREMENTS, ONLY THE SENDING TANK MUST BE SAMPLED AS A CONDITION FOR FUTURE TRANSFERS. IN ADDITION, THE SYSTEM MUST BE ANALYZED TO ENSURE THAT PROCESSING WILL NOT PRECIPITATE FISSILE MATERIAL OUT OF SOLUTION, RECOVERY: IF SAMPLE ANALYSIS RESULTS OR OTHER DOCUMENTATION SHOW FISSILE MATERIAL CONCENTRATIONS THAT EQUAL OR EXCEED THOSE SPECIFIED IN TABLE 1, THE TRANSFER SHALL NOT PROCEEt; BAS 7S A modified one group (thermal neutron system approximation with correction for slowing down, Fermi Age Theory) was used in the calculation for conservative results. The critical solution concentration of Pu-239 was determined as e functio of U-235 concentration. This eliminates the need for determining the U-235 concentration as a function of uranium solution enrichment, which is more difficult since the solution stream concentration will have to be known or estimated. For th purpose of these calculations, the U-235 concentration was allowed to vary from zer t to 4.0 g/L, U-235. I. A O LLK0130:3RM-1 Page 2 of 5

4 I l OSR/GP 7 Rev. 2 This analysis is conservative for aqueous liquids since they constitute highly j ,_,\\ / ( ) thermalized systems. The gevmetry of all available vessels and sumps in the plant (including those planned for STS, i.VTS, and CSS) was analyzed, and the most limitin 4 1 safe concentration values were determined. These are listed in rabic 1. ' Analysis of potential criticality in the SAR for STS indicaten no identified concentrating factors exist and thus no potential for criticality from liquid transfers within ST ] '1 or between STS and LWT5 exists. No potential for criticality within Tank 8D 2. No j l potential for criticality as a result of tank to tank transfers wit' tin IRTS, No potential for criticality in STS as a result of concentration in Prefilter or IX columns (reference memo K. O'Ahoofe). No potential for criticality within LWTS a j a result of concentration in evaporator (reference SAR Volume IV, Part H). No potential for concentration identified for CSS (reference SAR V, Volume IV, Part G), All sumps, drains, collection points were analyzed. ATTACIMEN~S Table 1 - Criteria for Determining the Allowable Fissile Solution Concentrations fo Plant Solution Transfers - Taken from Table 5.3 of FB:85:0150. 6 I h R./ REFERENCES FB:85:0072 " CSS Criticality Safety Evaluation" K. A. O' Ahoofe memo to J, C, cuynar, dated March 26, 1985. FB:85:0150 " Allowable Fissile Material Solution Concentration for Liquid Transfers, Revision 1, dated July 2,1985. VVDP SAR, Vol. IV, Part H, Liquid Waste Treatment System WVDP SAR, Vol. III, Part D, Supernatant Treatment System WVDP SAR, Vol. IV, Part G, Cement Solidification System OV 11K0130:3RM-1 Page 3 of 5

.....a OSR/GP-7 P.ev. 2 OTitER APPL.ICABLE OSRS O OSR CP-12 Fissile Material Limits and Requirements for Radioactive Waste Packages OSR GP 11 Storage Canister Loading and Spacing .O O LLK0130:3RM-1 Page 4 of 5

OSR/CP 7 Rev. 2 TABLE 1 CRITERIA FOR DETERMINING THE ALLO'JABLE FISSILE SOLUTION CONCENTRATIONS FOR PIANT SOLUTION TRANSFERS (1) Column 1 Column 2 Concentration of Uranium Corresponding Maximum Plutonium (U-233 + U-235) Concentration (Pu-239 + Pu-241) grams / litre grams / litre Greater But Less Than Than Greater than 1.85(2) 0. 0.049 1.85 0.05 0.499 1.63 0.5 0.99 1.39 1.0 1.99 0.90 2.0 2.49 0.68 2.5 2.99 0.44 0.19 3.0 3.4{2) 3.5 Greater Than (1) Column 1 is the total concentration of fissile uranium and Column 2 is the corresponding allowable total fissile plutonium ccacentration. For a sample containing a combined U-235 plus U-233 concentration in the range shown in O Column 1, the corresponding value in Column 2 is the limiting and allowable combined Pu-239 plus P..-241 concentration for safe processing. (2) Not authorized for processing. Special written authorization of the Radiation and Safety Committee is required. O LLK0130:3RM 1 Page 5 of 5

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. Nue:er-TR/GP-8 F.evis1:n Muerer 2'-

I Revisi:n O&:e 08-27-91 Engineering Release #1430 i t Per ECN #3354-Wa 65 i u. le., vu y 3 ern O n STTGilO n 3 TO ect ? 0 ? EK A* *!! A'. S ATI- RI:'J:E E'd.E'.'~5 i fa P I:-ARED EY NT D. E. Stafras Ca:a 'T ' < * ' # C;in:.:sn*, ir.5:nes / .O - A??E VID,h5 b f C. J. E:te.- a CA:e $/ i ( w...:a.: unate.- Oa:e[/kC!EI-APPROVID !! fNb . __, b- - A R. A. Hu=parey [ Ric:a: cn & (Sate:y Q C0.214:ae. Chatr:an I \\} /c

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APPROVE 3 SY-t R. T. Cessner Cate - t LL'.i tr ea *:e.a - -- F ra j eg A??ECVE0 SY N M J. L. Kna: ens;nuh Oa:a [A'b/TT getoi:g::a. & Env:rennencai ss(4:y. Manager -]f J ca:e i /2 ; /.>.'. . L '14.eW cL k i R. E. Lawrence, Jr. APPacvt: er su;: err.a:an: trea::en-P.-ej ec : Manager West Vcliey Nuclecr S ervices Co. [ P.C. Ec x 191 West Vcitey, N.Y.14t71-Clst j LLK0126: 3R4-1 ~~ DOE Approved: DW:90:0214 l ECB Concurrence: 08-10-9L f \\ W V - ! 516 i ? L P i c........-. .~..

._._._._~.- b JTR/CP-8= Revi 2 t f RECORD OF REVISION 4 J PROCEDURE I If-there.are changer to the proc ~edure,- the-revision number: increases by one. These. changes are indicated in the lett margin of the body by an arrow'(>)-at the be5 inning of the paragraph that contains a change. [ } i y Example: [ The arrow in-the margin indicates a' change; i i t t l !-) -Revision On Rev. No. Description of Changes Page(s) Dated v 0 Original Issue All 1 -Dated 5/20/88 All 1.- Engineering Release N/A 8/88 2 Per ECN 3354 -Page 4 08/91 t t + v l - l i 4 ) i i l t i ~ ~ W-1807, Rev. 1 i LLK0126:3RM 1

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f 1 TR/GP 8 Rev. 2 RECORD OF' REVISION (CONTINUATION SHEET) Revision en Rev. No. Description of Changes Page(s) i 'I i -) -l 6 r ? i i k k 6 .L i .t I I t i !t

5 E

i i t i .i I =! i .. t 5 t e i D f-t 1 i W-1807, Rev. 1 11 LIX0126 : 3RM-1 t I l t ? I k

. ~. TR/GP 8 Rev. 2 O l I. TYPE: -l TITLE: Water Activity Alarms -{ NUMBER: GENPUit OSR-[ ] l l 8 I l-Tech. Reqmn't. [X)l l l l CRITERIA:

1. Prevent contamination of-radiologically clean facilities or transfer of-radioactive liquids to radiologically clean systems.

2. Maintain existing NFS requirements of existing systems.

UNACCEPTABLE EVENTS: 1. Spread of contamination to clean systems. I I I Safety Limit-l l Reporting Requitements: l DOE-ID CONTROLLED tc0 l l l Os 'LCS l l [ Surveillance Reqmn't. l l l 1 l l I I I Tech. Requirement i X l Critique IDOE-WPO CONTROLLED 1 1 i Operating Limit i l lWNS CONTROLLED -IMPLEMENTING PROCEDURES: > SOP 31-2 > SOP 8-1 LIX0126 : 3RM-1 =

v TR/CP.B Rev. 2 TECllNICAL RFaUIREMENT O VATER ACTIVITY AIARMS APPLICABILITY This requirement provides for periodic verification of the operability of the alerms used to detect excessive radioactivity in cooling water or steam condensate roturned frotn the coils or jackets used to control temperature of vessels containing radioactivity. O!UECTIVE To provide added assurance of prompt detection of excessive radioactivity in steam condensate and cooling water. REQUIREMFST O AIARMS ON MONITORS FOR DETECTION OF RADIOACTIVITY IN C00LINC VATER AND STEAM CONDENSATE SHALL BE SET TO CORRESPOND TO A CONCENTRATION OF 1E-5 pCi/mL. SURVEILLANCE THE OPERABILITY OF EACH RADIATION ALARM SYSTEM MONITORING RETURNED CONDENSATE OR COOLING WATER SHALL BE TESTED AT LEAST ONCE EVERY THIRTY DAYS (DURING PERIODS WHEN THE SYSTEM IS IN USE) EY TrlE APPLICATION OF A RADIATION SOURCE. THESE SYSTEMS ARE SHOWN BELOW. EFFORT SHALL BE DIRECTED TO REPAIR ANY SYSTEM FOUND INOPERABLE WITHIN FOUR HOURS OF DISCOVERING THAT IT IS OUT OF SERVICE. IF REPAIR CANNOT BE COMPLETED WITHIN THE 4 HOUR PERIOD, SAMPLES WILL BE COLLECTED AND ANALYZED ONCE EACH SHIFT (8 HOURS). LLK0126:3RM 1 Page 1 of 2

TR/CP 8 Rev. 2 ) ALARM SYSTEM LOCATION STEAM CONDENSATE RETURN - UTILITY ROOM MAIN COOLING VATER RETURN - UTILITY ROOM 8D 3, BD 4 COOLING WATER OUTLET - CON ED SHELTER BASIS Steam and cooling water are used for heating and cooling of process solutions. The pressures of these heat transfer fluids are higher than those of the process solution in nrder to minimize leakage of radioactivity if a passage should develop between a process solution and a heat transfer fluid. In addition, radiation monitors are incorporated into the piping where the steam condensate and cooling water returns to the utility room. These monitors alarm in occupied areas when excessive radioactivity is detected. Further assurance is provided by the batchwis collection and analysis of returned condensate and a radiation monitor at the outle ( from the cooling coils of high level, stainless steel waste storage tanks. Since the radiation instruments are read at least once per shift, testing of the radiation alarms once per month is sufficient to verify alarm functionability. ATTACitMFETS None REFERENCES None O LLE0126:3RM-1 Page 2 of 2

} / 4 h i Doc. Num er TR/GP-9 i Revision Nun er 2 l Revision Cate J8-27-91 Engineerdag Release #1430 [ Per ECN #3354 l West VaHey Demonstration Dro.ect t OPER ATIONAL SAFE *Y REOUIRE".ENTS [ PREPARE M D. R. Steffes Date '7 / ~d ' Coganan;. Eng nee / APPROVED,h C. J. Roberts-Cate I ( ) Cpgnizant Manager fO , _b - 2 R. A. Humphrey Cate[/b4, I APPROVED BY l Ristation & Safety Q J Ccy.s tee. . airman Cate E/k b APPROVEDBYf N-w D. L. Shugars Quality Assurance -' APPROVED BY .J / M M R. F. Cessner Date [ 8 LLW Tre. =en* Pr jef APPROVED SY x J. L. Knabensenun Cate 6/b/TW /Ractoicgical & Environmental / -S= <ty. Manager APPROVED BY A u d !'4 b R. E. Lawrence, Jr. Catei!I,/oi Supernatant Treatment Project Manager West VcIley Nuclear Services Co. l P.O. ea x 191 West Va!!ey, N.Y.14171-C191 LLK0128: 3fe4-1 DOE Approved: EM 90:0214 ECB Concurrence: 08-10-91 wv-ieis .a i I . _. ~ _ _ _

~. _. _ _ _ _ _ _.. _. - _ _. _ - _.. TR/GP 9 Rev. 2 7g-RECORD OF REVISION PROCEDURE I'f there are changes to,the procedure, the revision number increases by one. These changes are indicated in the left margin of the body by an arrow (>) at the beginning of the paragraph that contains a change. Example: The arrow in the margin indicates a change. j; i Revision On Dated 4 .Rev.-No.- Description of Changes Page(s) i l 0 Original Issue All } (O; l' Dated-5/20/88 All l 1 Engineering Release 1430 N/A 8/88 i . 2 Per ECN 3354 Page 4 08/91-4. 4 T 4 -d W-1807, Rev, 1 1 - LLK0128:3RM-1 .r-,-.--.-...~.,...e .-.~.,--.......i....----..-.--.....,w.. .... -. -.... - ~.. -.... - ~. - .,.--,m.,...,-. e.r.-r.,--..

i -1 TR/GP 9 l Rev. 2 ' RECORD OF REVISION (CONTINUATION SHEET) Revision on Rev, No. Description of Changes Pa!,a ( s). I t i. i -l ~. 1 l l l l. I 1.- i. I -i i i l-i i l i W-1807, Rev. 1 11 LLK0128:3RM 1 ) f l-i l h .) 1 .~.-.__..-.c_._-~,.___._______ i

TR/GP 9 Rev. 2-t( l l TYPE: l TITLE: Control of Plant Equipment l NUMBER: GENPLNT OSR I ] l Funccion and Configuration l 9 I i Tech. Reqmn't. [X)l l l l CRITERIA: 1. Safety system function must re:nain in as designed configuration. UNACCEPTABLE EVENTS: 1. Failure of function of plant safety systems. 2. Incorrect replacement of components. 3. Loss af configuration control. 4. Failwre of safety systems results from loss of configuration control. 1 1 1 Safety Limit l l Reporting Requirements: l DOE-ID CONTROLLED 1C0 l j. l LCS l l l Surveillance Reqmn't. l t l I h. I I I I Tech. Requirement i X -1 Critique IDOE WPO CONTROLLED l l l 1 - Operating Limit l l IVVNS CONTROLLED IMPLEMENTING PROCEDURES: [ I W 906 [ EP 3-01 EP 3 02 E EP 3 07 -t EM 11 > SOP 15 { 4 i I k LLK0128:3RM-1 i i u v

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TR/GP 9 I Rev. 2 TEClINICAL REQUIREMENT CONTROL OF PIANT EQUllMENT RINCTION AND CONFICURATION APPI.ICABILITY This requirement applies to all VVDI process and fuel handling and storage equipment whose function and/or configuration is importatit to safety. OfLTECTIVE This requirement cescribcs the control of functional and physical changes to plant equipment. REQUIREMENTS

1. ALL FUNCTIONAL AND PHYSICAL CilANGES TO PIANT EQUIPMENT VilICH EFFECT SAFETY SilALL BE TROPERLY APPROVED IN ACCORDANCE VITH THE REFERENCED PROCEDURES.

2, CHANCES Ol'TSIDE THE ENVEIDPE OF THE EXISTING DOE-ID APPROVED SAFETY ANALYSIS REPORT AND/OR DESIGN CRITERIA SilA?1 BE APPROVED BY DOE ID. PHYSICAL CllANCES REQUIRING DOE APPROVAL SHALL BE APPROVED BY DOE ID PRIOR TO THE START OF INSTALLATION, A CHANGE IS DEEMED TO BE OUTSIDE THE ENVELOPE OF THE SAFETY ANALYSIS REPORT IF ANY OF THE FOLLOWING CONDITIONS ARE MET: A. ANY FUNCTIONAL CHANGES TO ACTIVE AND PASSIVE BARRIEES FOR VHICH CREDIT IS TAKEN IN THE SAFETY ANALYSIS REPORT. THIS IS INTENDED TO INCLUDE INSTRtHENTS, SHIELDING, VENTILATION, FILTRATION, ETC., FOR WHICH QUALITATIVE OR QUANTITATIVE CREDIT IS TAKEN OR IDENTIFIED IN SAFETY ANALYSIS DOCUMENTATION FOR PROVIDING MITIGATIVE OR PREVENTIVE FUNCTIONS. B. ANY PHYSICAL, FUNCTIONAL, OR SOFTWARE CHANGE THAT MAY SIGNIFICANTLY REDUCE THE MARCIN OF SAFETY (CONSERVATISM) FOR THAT STATED IN Tile SAFETY ANALYSIS REPORT. O LLK0128:3RM 1 Page 1 of 3

TR/GP 9 Rev. 2 l C. ANY PHYSICAL, FUNCTIONAL, OF SOFWARE CHJCE TilAT MAY RESULT IN SIGNIFICANT SAFETY CONSEQUENCES FROM A CREDIBLE ACCIDENT OR ORIGINAL DESIGN MALFUNCTION OF A DIFFERENT TYPE THAN THAT CONSIDERED IN THE ORIGINAL DESIGN. IMSIS Plant equipnent whose function and configuration is controlled by review of changes both within WNS and DOE-ID is categorized in this standard. The WDP review requirements (Part 1 of the requirements) reflect company philosophy that safety is a line responsibflity of the operating managers. The DCE ID review requirements (Part 2 of the requirements) are based on DOE-ID's interpretation of its responsibilities under DOE Order 5480.1.\\, Chapter V and DOE ID Order 5480.1, Chapter V. Plant equipment covered by this TR includes WDP process equipment and peripheral support equipment covered by approved safety analyses. Configuration changes requiring DOE approval must be approsed by DOE-ID prior to installation. Maj or procurements for plant configuration changes will still require prior approval by O DOE. ATTACIMENTS None O LI.K0128:3RM-1 Page 2 of 3

TR/GP-9 Rev. 2 REFERFNCES DOE Order 5480.1A, Chapter, V, " Safety of Nuclear Facilities" a i DOE ID Order 5480.1, Chapter V. " Safety of Nuclear Facilities h I L l l t i i i s I r I t h I l l t i LLK0128:3RM 1 Page 3 of 3 l b i I

'l 7 --Dl 'A) Occ. Number OSR/GP-10 Revisim Num er ? Revision Date 08-27-91 Engineering Release #1430 Per ECN #3353 S t e 1 p, A tj 1b Y d.- A*e U ; , Cy O1 Jemonstration o ro'ect CPER ATIONAL SATET! REOUIREMENTS 4 D. R, Sterres Date T PREPARE CcEnl:4n; Er.Ethee / APPROVE 3h.h -- v ' C. J. Rceerts Cate N Cygnt:an Manager APPROVED SY O R. A. Humphrey Date M 4 b ,s factacten & Safety Q d C- =L::ee,.airnan W D. L. Shugars Ce b A? PROVE 3SYf_) Quality As)urance / APPROVED BY I # M R. F. Cessner Ca:e I A LLW Trea sen* Pr jeg / APPROVED SY ,f /e-A J. L. Knacense?.un Oa:e M r /T W w riacloicgical & F.nvironmental Safety. Manager Y d bi.vK!'c/ )'r, Ca:e ! II +l" ' _ .t R. E. Lawrence. Jr. APPROVE 3 BY Supernatant Trea.=en: Project Manager West Vcliey Nuclear Services Co. P.O. Ec x 191 West Valley, N.Y.14171-C191 RLC3262: SEA-65 DOE Approved: DW:91:0530 WV-1816 ECB Concurrence: 08-10 . -.. ~ _ -. -.,. -, -.... - -. - ~.... - - - - 'OSR/GP 10 Rev. 2 I l RECORD OF REVISION PROCEDURE If there are changes'to the procedure, the-revision number increases ty one. ' ~ These changes are indicated in the lef:: margin of_the body by an arrow (>) at the beginning of the paragraph that contains a change. b ' Exarnple : l-The. arrow in the margin indicates a change. l Revision On Dated Rev. No, Description of Changes Page(s) .j .O' original Issue-All 1 Dated All ~1 Engineering Release 'N/A' 8/88 I 2 -Per ECN 3353 Pege 4 8/91 -l l I 1 ii .q. l e-a 1 -i F 1 .[ i l 1 f.y I f W-1807, Rev. 1 1 l 1.LK0132 : 3PJi-1 f ? l h l i k r

r 8 i!- t OSR/CP-10 j.~ Rev. 2. l RECORD OF REVISION (CONTINUATION SHEET) Revision on j: Description of Changes .Page(s) l Rev. No. 4 I l! l-l t I~ l -- W-180/, Rev, 1 it LLK0132:3RM 1

l OSR/CP 10 Rev. 2 '~ j j i TYPE: l TITLE: Airborne Effluent Monitoring l NUMBER: CENPIRT 0% [X) l Syrtem Operability l 10 l l Teci. Reqmn't. [ }l l 1 l CRITERIA: 1. Release of otrborne effluents to the off site environ shall not exceed limits as set by toe orders. UNACCEPTABLE EVENTS: 1. D.ceeding DOL limits Safety Limit l l Peporting Requirements: l DOE ID CONTROLLED LCO l X l UOR l ?CS l l l Surveillance Regan' t. l X l l O _L I I t i i Tech. Requi renient l 1 l DOE WPO CONTR01.1.ED I I I Operat192 Limit l l [WNS CONTROLLED > IMPLEMENTING PROCEDURES: EM 11 50P 70 30 D1 101 SOP BO 6 SOP 15 11 SOP 30 3 SOP 50 33 SOP 50 35 SDP 56 2 SOP 70 4 LLK0132:3RM 1 0

OSR/GP 10 Rev. 2 OPERATIONAL SAITTY REX}UIRIMENT O AIRBORNE EIT111ENT HONITORING SYSTlMS OPERABILITY APPL.ICAB11.ITY This OSR is applicable to the WDP airborne waste ef fluent monitoring systems for all process activities. OlLIECTIVE This OSR states the operability re mirements for the VVDP airborne waste effluent monitoring systems. S Yr.ClYIrAT10N 1. LIMITING CONDITION FOR OPERATION: A, ONE AIRBORNE EFFLUENT MONITORING SYSTEM LISTED IN TABLE 1 SilALL ltE OPERA!5LE AT ALL TIMES, STAND!\\7 CAPABILITIES SilALL BE PROVIDED AS SPECIFIED IN TA15LE 1. B. STANDPY INSTRUMENTATION / EQUIPMENT SilALL BE UTILIZED AT ANY TIME Tile PRIMARY UNIT IS TAKEN OFFLINE. Sil0ULD EITilER UNIT BECOME INOPERABLE IT WILL BE RETURNED TO SERVICE.READINE 'S WITilIN 72 Il0URS. IF TilIS CANNOT BE ACCOMPLISHED, Tile INOPERABLE OFF LINE UNIT SilALL BE REllACED BY A COMPARABLE, OPERABLE UNIT, OR Tile PROCESS SilALL BE SilUT DOWN. 2. SURVEILIANCE REQU,IREMENT A, ALL OPERATING STACK MONITORING SYSTEMS SilALL BE SOURCE CllECKED VEERLY. B, ALL UNITS SilALL BE CALIBRATED SEMIANNUALLY, C. ALL UNITS SilALL BE CllECKED FOR OPERABILITY OF A1 ARMS AND AUTOMATIC BACKUP SYSTEMS AT LEAST SfdIANNUALLY O LLK0132:3RM 1 Page 1 of 5

OSR/Gp.10 Rev. 2 i r I i RASIS \\ Standards for radiation detection instrument calibration require at least ari annual i calibration of operational oquipment. A semiannual system component calibration f assures that both online and standby instruments (radiation detection and air flow f measurement) will be operationally satisfactory during any point in the calibration f cycle. Tha standby units are equivalent instruments and equipment which replicate the capabilities of the on line units. In the event that one requires repair, a [ third synte s, (the sample unit) serves as backup for the on line monitor. Loss of i all on line monitors requires cement system shutdown since the sampler does not [ provide radioactive release indication although it provides an accurate measure of l integrated releases. The weekly source check assures basic systets response to known input: this test will coincide with the weekly filter changeout necessitating placing the monitor offline for a period of less than 15 minutes during testing. ATTACIDOWTS P None t t P t t i i I \\ [ 1.120132:3PA 1 Page 2 of 5 t [

OSR/GP 10 Rev 2 REFERENCES t( ANSI N42,18 1974 (R 1980) Specification for Performance of On site Instrumentation for Continuously Monitoring Radioactivity in Effluents. ANSI N320 1979 Perfornance Specifications for Reactor Emergency RadioloC cal Monitoring Instrumentation l i ANSI N323 1978 radiation protection instrumentation test and calibration l t DOE $484.1A Chapter III [ c DOE /EP 0096 A Guide for Effluent Radiological Hensurements at DOE l Installations [ t t I t -s f I h i i I t i h l ( LLK0132:3RM 1 Page 3 of $ a

w ki i 4 OSR/GP-lO i Rev. 2 i TABLE 1: ESSENTIAL AIREORNE EFFIEENT MONITORING EQUIPMENT i 4 i Primary Method of 4 Process Equipment Designation Standby (Backup) Designation Actuation Main Plant Alpha Cam On-line SA Alpha Cam Standby 5B Automatic upon Beta Cam On-line 3A Beta Cam Standby 3B on-line monitor J. i. i-failure i-Monitor vacuum On-Line.M-1 Standby Monitor Standby SM-1 Automatic upon low Pump On-line M-2 Vaccuus Pump-flow rate i Sample Vacuum On-line S-1 Standby Sample Standby SS-1 Automatic upon low s {- Pump Vac Pump flow rate i f CSS Alpha Cam On-line Alpha Cam Standby Manual changeout 4 i (01-14 Building). Beta Cam On-line Beta Cam Standby upon operating unit faila m i System Vacuum On-line F-1 System Vacuum Standby SP-1 Automatic upon Pump Pump low flow rate i j LLK0132:3RM 1 6 of 5 i ___---,,-,...-_,....--_.-.._..~,_,.-,-..--,.-_-,.--,-,..m-,-----..,.--.__,,-,,--_

M: a i i 1 l [ OSR/GP-10 i Rev.'2 4 { TABLE 1:. ESSENTIAL AIRBORNE EFE1UENT MONITORING EQUIIMENT (CC INUED) i Primarv Method of Process Equipment Designation -. Standby (Backup) Designation Actuation j CSRF (MSM Roof) Alpha Cam On-line Alpha Can SMndby Manual changeout Beta Cam On-line Beta Cam Standby upon operating j ' unit failure t i I System vacuum On-line System vacuum Standby Automatic upon i { Pump Pump low f1cw rate i 4 PVS (STS) Alpha Cam, On-line Alpha Cam, Standby Manual switchover Beta' Cam. Skid 1 Beta Cam, - Skid 2 upon operating unit j Two Vacuum Pumps Two Vacuum Pumps failure. Low flow i sill activate the standby pump in operating skid i l automatical~y. l Sample Vacuum On-line Sample Vacuum Standby Automatic upon low Pump Pump flow rate 4 i LLK0132:3RM-1 5 of.5

{ ( Occ. Num:er OSR/CP-11 Revisten Num:er 1 Revision Cate 08-27-91 _ Engineering Release #1430 Per ECN'#2605A Per ECN #3353 West Va ey 36 m O7ST'a":On,iO,eCT CP E* A!!ON AL ! Art'"! R E*U:# E?E!!T! PREPARE M D. R. 3: artes' Cate 'T Cognl: ant, E..g;neer// [' APPRCVED,,h O. J. Accerta Date W \\ Cygni:an Manager P.. A. Hum;r. rey Cate [k4 k fN APPROVE 3 BY faciatten & Satsty Q i Cr.r.m L::e e.. airman APPROVED BY l' W D. L. Shugars Cate b QuaLL:7 As urnere i / / APPROVED BY,,, ./ R. F. Cessner Cate IA 2/7d~ LLW Trea men

• P

/. L. Knacenser.un APPROVEDBY__.j- _ - __ I-J Oate M5MT _+s f.actoicgacal.&,s.avtecnmental i f S&fety. Manager APPROVE 0 SY k O' t'I L R. E. Lawres.ce, Jr. Cateibt/oa Supernatant Treatment Project Manager h West Valley Nuclecr Services Co. P.O. Ec x 191 West Valley, N.Y,14171-CISI O MSS 0654 DG-392 DOE Approved: DW191:0530 WV - lE16 ECB Concurrence 1 08-10-91 L

I i OSR/CP 11 Rev. 3 , RECORD OF REVISION n if there are changes to the procedure, the revision nuniber increases by one. j These changes are indicated in the left margin of the body by an arrow (>) at the beginning of the paragraph that contains a change, f r.xample : The arrow in the margin indicates a change. j. Rev. Revision On 4 Dated f-No. Description of Changes Page(s) i. O Original Issue All 1 Dated $/20/89 All i 4 1 Engineering R& lease a1430 All 08/88 2 Per ECN m2605A Page 3,5 12/88 3 Per ECH 3353 Page 4 08/91 i l [ f I i W 1807. Rev. I 1 MSS 0654: 3PJ4 1 O 'h -I l I* ~

._. -..___. _ ___. _.~.__..._ _ __ _ _. _ _ _ - 5 F OSR/CP 11 k Rev. 3 4 I RECORD OF REVISION (CONTINUATION SHEET) I e-i Revision on- [ t 1 Rev. No. Description of Changes Page(s) [ i ? i h i r e I f; I L [ I r -t I W-1807, Rev.1 11 MSS 0654:3RM 1 i 8r t -.w _~_l..-___._,____n-. _.____+.______._._-.._.-__.__.._~~+.n..e_-~,,_.~., ,J ,cm-+.+_n,.,---_..-._

0$R/GP 11 l Rev. 3 l t i l I TYPE:. l TITLE: Storage Canister Loading and l NUMBER: GENPLNT E OSR (X) l Spacing l 11 l l Tech. Regan't, [ ]l l 1 l l CRITERIA: 1. Prevent criticality l t I UNACCEPTABLE EVENTS: 1. Criticality. i i I I I l -Safety Limit l X l Reporting Requirements: jDOE ID CONTROLLED O LCO l l UOR [ i Lc5 l l l [ Surveillance Reqmn't. l X l l I I l l l 1 I i Tech Requirement l l l DOE WPO CONTROLLED I I I i Operatinc. Lirnit l l lWNS CONTROLLED i i i > IMPLEMENTING PROCEDURES: t SOP 1 9 SOP 1 49 SOP 1 10 SDP 1-57 SOP 1 11 SOP 1 16 SOP 143 i SOP 146 l SOP 148 [ I f i I MSS 0654:3RM.I j I t i O I I I i

OSR/CP 11 Rev. 3 /"') OPERATIONAL SAFETY REQUIREMENTS V CENERAL PLANT 11 STORACE CANISTER IDADING AND SPACING i APPLICABILITY l 1 These requirements establish limits governing fuel distribution and handling in the Fuel Storage Pool (FSP) and the Cask Unloading / Loading Pool (CUP) { section of the Fuel Receiving and Storage (FRS) Area. OnJECTIVE To assure that individual fuel bearing units and arrays of units are maintained in suberitical configuration. SPECIFICATION LIMITING CONDITIONS FOR Ol'ERATION 1. IRRADIATED NUCLEAR FUEL ASSEMBLIES IN Tile ITEL STORACE POOL (FSP) AND THE CASK UNLOADING /1DADING POOL (CUP) SHALL BE STORED IN CANISTERS ON Tile ~ STORAGE RACK. AND/OR THE LIIT RACK. 2. CRITICALITY ALARMS SilALL BE OPERATIONAL k'llENEVER FUEL IS BEING STORED, HANDLED OR TRANSFERRED IN Tile FRS. 3. NO MORE THAN ONE ITEL TYPE IS PERMITTED TO BE PRESENT IN Tile CUP AT ANY TIME. 9 4. A FUEL ASSEMBLY IS NOT PERMITTED IN THE CUP k' HEN THE FUEL STORAGE POOL FLOOR DEBRIS CONTAINER (S), FILLED OR PARTIALLY FILLED, IS IN Tile CUP. MSS 0654: 3PJi 1 Page 1 of 5

09R/GP Il Rev. 3 O 5. ITEL CANISTERS SHALL NOT CONTAIN MORE TilAN Tilt F01. LOVING hTMBER OF ASSEMBLIES: A. ONE PVR ASSEMBLY B. '1VO BVR ASSEMBLIES 6. CANISTERS SilALL BE SPACED TO PROVIDE A MINIMUM OF TWELVE (12) INCllES OF WATER BETWEEN ITEL CONTAINED IN ADJACENT CANISTERS AND/OR ANY FSP/ CUP FLOOR DEBRIS CONTAINERS. 7. ONLY ONE CANISTER (VilETilER OR NOT IT CONTAINS ITEL ASSEMBLIES) MAY BE liANDLED AT A TIME OUT OF STORACE LOCATIONS IN Tile FSP AND/OR Tile CUP. SIMULTANEOUS IIANDLING OPERATIONS IN THE FSP AND Tile CUP ARE PEPJilTTED. 8. NO FUEL IS PERMITTED IN Tile LIFT RACK VilEN Tile POOL CATE IS to BE M;,VED OR A SHIPPING CONTAINER IS TO BE TRANSFERRED INTO OR OUT OF Tile CUP. O 9. NO MORE TilAN ONE FUEL ASSDtLLY OF ANY TYPE MAY B5.' IIANDLED OUTSIDE OF ITS CANISI.'.R OR LICENSED SHIPPING CONTAINER AT A TIME IN Tile CUP. Tile FOLLOWING MAXIMUM NUMBER OF CANISTERS ARE PERMITTED To BE PRESENT IN THE CUP: A. ONE CANISTER OF PWR FUEL, OR B. FOUR CANISTERS OF BWR ITEL, OR C. ONE FSP/ CUP FLOOR DEBRIS CONTAINER VilICil IS AT LEAST PARTIALLY FILLED. (ITEL ASSEMBLIES MAYBE BROUGHT NEAR EMPTY FSP/ CUP FLOOR DEBRIS CONTAINERS). 10. THE "AXIMUM NUMBER OF FUEL ASSEMBLIES PERMITTED IN A SHIPPING CASK AT A TT.ME IN THE CUP WILL BE LIMITED TO TilAT QUANTITY PERMITTED BY Tile LICENSE FOR THAT CONTAINER. MSS 0654: 3RM 1 Page 2 of 5 i

OSR/CP Il Rev. 3 V 11. FUEL llANDLING SilALL BE STOPPED IMMEDIATELY UPON ANY OF Tile FOLLOVING OCCURRENCES AND SilALL REMAIN SilVTDOVN UNTIL VRITTEN PERMISSION TO RESTART llAS BEEN GRANTED BY Tile RADIATION AND SAFETY MANAGER. A. ANY TIME A FUEL ASSDIBLY IS DROPPED. B. ANY TIME A CANISTER CONTAINER IS DROPPED. C. ANY TIME A ITEL ASSEMBLY IS STUCK IN A CANISTER AND CANNOT BE FREED IN ACCORDANCE WITil Tile OPEPATING PROCEDURE. D. IN Tile EVENT TilAT ITEL RODS, OR STRUCTURAL llARDWARE NECESSARY TO RETAIN FUEL RODS, SEPARATE FROM A ITEL ASSEMBLY OR ITEL RODS AND/OR PIECES SEPARATE FROM ITEL ASSEMBLIES. E. ANY CRITICALITY ALARM OTilER TilAN PIANNED TESTS. - F. FAILURE OF ANY CRITICALITY AIARM SYSTEM. C. IN THE EVENT A ITEL ASSEMBLY IS BROUGitT INTO Tile CUP AND TilERE IS A FILLED OR PARTIALLY FILLED ITEL STORAGE POOL FLOOR DEBRIS CONTAINFR IN Tile CUP. SURVE11.IANCE LIMITING CONDITIONS FOR OPERATION NO. 2, LUDLUM MODEL 2368 CRITICALITY MONITORS WITil DESIGNATED LOCATIONS NORTHEAST, SOUTH, NORTilVEST ARE OPERATIONALLY CHECKED BI VEEKLY, ALARMED CllECKED QUARTERLY, AND CALIBRATED SEMI ANNUALLY VliEN P.EQUIRED TO BE OPELATIONAL, BASIS The Fuel Receiving and Storage Area (FRS) has been designed to permit the handling of fuel assemblies such that geometry and administrative control prevena the interaction of one fuel assembly with another. These precautions are necessary since the FRS may contain fuel in excess of that necessary to produce criticality if placed in optimum array. O MSS 0654:3RM.I Page 3 of 5 V

i I OSR/GP.11 Hev. 3 ) L i I The storage racks and canisters provide a ininimura edge to edge spacing of 7.5 inches between adjacent canistors and a miniinum edge to edge spacing of ) twelve inches between.the fuel contained in adjacent canisters. Canisters a { containing fuel'are also separated by at least 12 inches from TSP / CUP floor i debris. canisters. This separation of twelve inches of water prevents l significant interaction of neutrons and provides a safe array. l l .t A k,gg less than 0.9$ (k,gg + 2=a f,0.95) provides a reasonable margin to J eritical. The fuel assumed for the analysis is unirradiated. This provides j an additional safety margin since the stored fuel is irradiated. By comparing I } the calculational ~ method with known critical'systerns containing similar fuel g material, uncertainties in the method have been determined. r i 4 Individual fuel elements or packages previously stored under water have been demonstrated'as safe and, theref ore, no further calculations are deemed i necessary provided that twelve inches is maintained between fuel in adjacent canisters in storage. j. FSP/ CUP floor-debris containers have not been evaluated for neutron interaction with fuel presently in storage. Therefore, a neutron isolation j (i.e., 12 inches of water) requirement is necessitated for maintenance of the i margin of. safety.. Adrainistrative procedures are established to assure correct.... ster loadings. l Calculations performed in 1983 and revised in 1987 have shown that the k,gg [ 11mit of-0.9$ will not be' exceeded for intended operations and postulated i accident scenarios as long as-this OSR is complied with, i The consequence of exceeding these require:nents would be to decrease the margin of safety for the prevention of criticality, j-1- U ) MS50654:3RM 1 Page 4 of 5 r r

u.....

.~.. .2.

OSR/GP 11 Rev. 3 (d3 The surveillance conditions provide actions necessary to assure criticality monitors are installed and operational when fuel is stored, handled, or transferred as per the original NFS Technical Specifications and Safety Analysis Report Volume II, ATTACIMENTS None RFEERENCES, NFS SAR NRC Docket 50 201 " Safety Assessment Document for the West Valley Demonstration Project Fuel Receiving and Storage Area", Rev. 1, dated September 23, 1983. " Revised OSRs for the Collection and Storage of TSP / CUP Floor Debris," Q FA:87:0059, dated May 28, 1987. OT1tER APPLICARLE OSRs OSR/TR GP Fissile Material Limits and Requirements for Radioactive Waste Packages Liquid Transfers of Fissile Material OSR/TR.CP.7 MSS 0654:3RM 1 Page 5 of 5

E i i i f, Doc. Num:er OSR/CP-12_ j Revision Nue ea Revisfon Date 08-27-91. f Engbeering Release #1430 Per ECN #3353 West a ey l i Demonstration Dro.ect 5 OPERA *!ONAL SAFE *? REOUIREFENTS N D. R. Staries Date '. (* PRE?ARE Ccgnt:an Engines / W C. J. R0certs Oate( P APPROVED,h Cpgnt: ant Manager Cate[/k0 b APPRCVED SY fb - _. b. R. A. Humpnrey A n10tation atSafety Q } I C:.p.mLt ee. Chairman [ CateN 5b f APPROVEDBYf) WN~v., D. L. Shugars / i Quality Assurance APPROVED BY .J / R. T. Cessner Cate I [ [ LLW tres men Prjeg APPROVED BY ___ /f Mw - e x _ J. L. Kna:entenun Oate M.o/TT l i 21 i Enytronmental /Ractol:gt: l Safety. Manager Cate5/I',/a3 Lud t *42., b R. E. Lawrence. Jr. APPROVED BY Supernacant Treatment Project Manager l West Valley Nuclear Services Co. P.O. Bo x 191 l l i. West Vcitey, N.Y.14171-CISI { t; Appr n : 2 0D0 RLC3260 SEA-65 ECB Concurrence: 08-10-91 V - 1816 W l r __,,.,...m...

OSR/CP 12 Rev. 2 RFCORD OF REVISION M EDURE If there are chang.es to the procedare, the revision nwr.ber increases by one. These changes are indicated in the left margin of the body by an arrow (>) at the beginning of the paragraph that contains a change. Exartple : The arrow in the reargin indicates a change. Revision un Dated Rev. No. Description of Changes Page(s) 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release N/A 8/88 2 Per ECN 33$3 Page 4 08/91 W-1807. Rev. 1 i LLK0131 : 3Pfi-1

i l OSR/GP 12 l Rev, 2 RECORD OF REVISION (CONTINUATION SilEET) Revision on Rev. No. Description of Changes Page(s) A t I I i O I i; f f ) f t.i; f at t t ) [ l i Ii l i i -r i i W.1807. Rev, 1 it LII0131:3RM 1 h I ,.,...,. _.,..,,.4-..._,..._,_._

p _ _.., _ _ _ _, _ _ _. _. _ _. _.m.._. - _ _ _._____.-.. _._.. _. _. _._ _. _ _ _ -.-._ _ _ _._ OSR/CP.12 Rev. 2 1 l - TYPE: l _ TITLE: Fissile Material Limits and l NUMBER: CENPLNT f OSR (X) l Requirements of Waste Packages l 12 I I i Tech. Reqmn't. [ ll l j l I t i CRITERIA: 1. Prevent Criticality f -i + t f UNACCEPTABLE EVENTS: 1. Criticality. { i i I I I Safety Limit l X l Reporting Requirements: l DOE.1D CONTR0l'.ED ~ LCO l X l l f LCS l l l Surveillance Reqmn't. l l UOR l l l I I I Tech. Requirement l l l DOE.WPO CONTROLLED _ I I I l Operatinr. Limit l l lWNS CONTROLLED I IMPLEMENTING PROCEDURES: SOP 9 2 I > SOP 9 14 i > SOP 9 7 i > SOP 9 8 I t t e I LLK0131:3RM l' i .g I I i .,_..__..,....._____.,...--,.._.__________...______._...___,..___,.._.__.__..________t _- ~. _, _.

OSR/GP 12 Rev. 2 } f OPERATIONAL SA} TTY RFIJUIRINFXT FISSIII MATERIAL LIMITS AND REQUIREMENTS }UR WASTE PACKACES APPLICARILITY This OSR applies to the packaging and storage of radioactive material and debris comprising significant quantities of fissile material. Storage areas include, but [ are not limited to, the LAC Storage Building, the RAM Equipment Room (RER), the General Purpose Cell (CPC), OfLIECTIVE l i T's cbjective of this OSR is to assure that operations involving the packaging and stor:gs of radioactive waste comprised of fissile material are controlled to f rs.ciude the formation of a critical array of containers. Specific package, storage a'er, and storage array limits are derived to assure suberiticality for all credible storage configurations and accident scenarios. [ SPECIFICATION f l A. IAC STORAGE BUILDING SAFETY LIMITS 1. STORAGE CONTAINER LIMITS SHALL NOT EXCEED THE SAFETY LIMIT VALUES GIVEN IN j TABLE 1. i i LIMITING CONDITIONS FOR OPERATION E 1. CONTAINER CLOSURES (LIDS, LOCKS, SEA 1.5, ETC.) SHALL BE IN PLACE PRIOR TO STORAGE IN THE LAG STORAGE BUILDING. t r i LLE0131:3RM 1 Page 1 of 7 i i i 5 ..,.w. .,..-n._.__-.-_

t t OSR/CP 12 Rev. 2

2. -DRUM ARRAYS SilALL BE LIMITED TO FOUR TIERS OR LESS.

(THERE IS NO LIMIT FOR -HORIZONTAL ARRAY SIZE,) 3. CONTAINERS SHALL NOT BE INTENTIONALLY OPENED IN T}lE STORACE FACILITY. 4. DAMACED CONTAINERS VHOSE VOLUHE ilAS EEEN SIGNIFICANTLY REDUCED (BY IMPACT. j-ETC.) SHALL BE REPLACED. (EXCEPTION: CONTAIPERS PROCESSED TilROUCil THE l SUPERCOMPACTOR.) f a s !e B. RA,M EQUIPMENT ROOM f i SAFETY LIMITS l t 1. YllE TOTAL MASS OF FISSILE MATERIAL SHALL BE LIMITE: TJ 803 CRAMS IN Tile FACILITY. I I t 2. DRUMS SHALL BE LIMITED TO 200' CRAMS OR LESS OF FISSILE MATERIAL. i LIMITING CONDITIONS FOR OPERATION 1. TRU WASTE SHALL BE CONTAINED ONLY IN V} LITE TRU WASTE DRUMS (DOT SPECIFICATION 17C). t 2. ONLY TRU WASTE IN THE CHEMICAL FORM OF NITRATL SALTS (URANYL HITRATE AND/OR i PLUTONIUM NITRATE) SHALL BE STORED IN THE FACILITY, EXCEPTION: UP T0-FOUR CRAMS OF PLUTONIUM OXIDE MAY BE STORED. (VERIFICATION OF Tile NITRATE MAY BE-- SURMISED OR INFERRED FROM THE PLANT SOURCE OR PROCESS FLOW SitEETS AND l CHEMICAL ANALYSIS IS NOT REQUIRED.) j i 3. DRUMS SHALL NOT BE INTENTIONALLY OPENED IN Tile STORAGE FACILITY. i [ i i f i 4 [ -L LLK0131:3RM 1 Page 2 of 7 f i i __,,,_--m.,,,,.__ .. _ _ ~, ~ _ _. _. -. _ - - _ _ - - _ -. -.., -. ~..

OSR/CP 12 Rev. 2 i 4. DAMAGED OR PARTIALLY COLLAPSED DRUMS VillCil-NO LONGER PROVIDE Tile VOLUME DISPLACEMENT EQUIVALENT TO UNDAMAGED DRUMS SllALL BE REMOVED FROM Tite RER AND REPACl%CED AS NECESSARY. 5. EACll DRUM OF Tile STORAGE ARRAY SilALL BE CONFIGURED SO TilAT IT STANDS VITil I i Tile LID AND IhCK ON Tile TOP OF Tile ARRAY (RIGilt SIDE UP). 6. THE ARRAY OF DRUMS TRU VASTE SHALL BE LIMITED TO THREE TIERS, PP.0VIDED: A. AN ENGINEERING EVALUATION IS PERFORMED Vit!Cll DEMONSTRATED TilAT ALL DRUMS VILL MAINTAIN TilEIR STRUCTURAL INTEGRITY UNDER ALL ANTICIPATED STACKINO l CONFICURATIONS. f f f B. DRUMS WHICll FORM THE SECOND AND Til!RD TIERS SHALL BE STACKED USING NONCOMB'JSTIBLE PALLETS. I f C. GENERAL PURPOSE CELL i SAFETY _J.IMIT t 1. HI.VAC COLLECTION CONTAINERS SilALL BE LIMITED TO 680 CRAMS OR LESS OF i i FISSILE MATERIAL AS CHEMICAL PROCESS CELL TIDOR DEBRIS. f LIMITING CONDITIONS FOR OPERATION { i f 1. HI VAC COLLECTION CONTAINERS SHALL BE STORED ONLY IN A SINGLE TIER ARRAY AND - ONLY ON THE ENGINEERED STORAGE PLATFORM. l f f 2. ONLY ONE HI-VAC COLLECTION CONTAINER SilALL BE HANDLED AT A TIME, AND HANDLING SHAll BE LIMITED TO Tile AREA DIRECTLY OVER TiiE ENGINEERED STORACE PLATFORM OR Tile CllEMICAL PROCESS CELL. f 3. HI VAC COLLECTION CONTAINERS SilALL NOT BE OPENED IN Tile CENERAL PURPOSE i CELL. [ f I O L LLK0131:3RM 1 Page 3 of 7 f L i ,...-_ _,.,-- _- __..,,_,.._._,-__,,.,_ _, _.,_ _,., _,~ _- _- __ _ _ _ ___- __ __.. _. _ ______ _ _ _ _ __ ___ _ _ __ _ _.

OSR/Cp.12 Rev. 2 M SI S, Fissile material mass limits are required to assure that a criticality cannot occur under routine waste packaging and storage operations and all credible off nortaal and accident scenarios. Effective neutron multiplication factors generated for a large drurs array predicted an adequate margin of safety for uranium and plutonturn contaminated wastes limited to 200 grains fissile per drum (Reference RitO SA 183). The margin of safety is significantly reduced for arrays of drums comprising hi h6 concentrations of fissile material which occupy less than 20 percent of the drum volurce. Separate 11: nits are generated for the RER to support storage of these wastes. The package limits presented in Table 1 were developed in criticality safety analyses identified in the reference column of the table. These cv.luations were checked by an independent reviewer and approved by the Radiation and Safety Conuut t tee, Methods for coinplying with these limits may vary. In some instances the material to be packaged inay be sampled and subjected to radiothenical analysis for specific nuclide deterinination. In other cases, survey data may be correlated to fissile content using scaling factora based on radiochemical data and appropriate and conservative assumptions. In any case, the sampling and analysis procedura proposed for dennonstrating compliance with this OSR will have to be approved by the Radiation and Safety Cottunittee. The limit on total fissile material to be stored in the RER provides the necessary controls to ensure the safe storage and handling of TRU waste drums containing high concentrations of fissile material in the RER. Some of the TRU waste drums to be stored each contain 100 200 grams fissile material in a configuration in which the fissile material is not radially centered in the drums. Drums containing fissile material in that mass range and in the off centered configuration have not been evaluated for large arrays without a total area inventory limit. As a consequence, the area limit is imposed. The fissile material masses from all drums were evaluated at the minimum separation to envelop the off centered configuration. Therefore, the inadvertent stacking or rearrangement of drums, including collapsed druins, vill not reduce the margin of safety, i.e., the effective rnultiplication 1.150131:3RM 1 page 4 of 7

t OSR/CP 12 Rev. 2 factor is less than 0.95 when all of the fissile material is contained in drums but is not necessarily centered inside of the drums. Optimum moderator / reflector conditions were modeled for this analysis. I l Por the GPC, the til.VAC collection containers are evaluated for storage on an r engineered storage platform to enable retrieval via the CPC crane through the P CPC/CPC hatchway. The containers are evaluated for the accidetit scenario in which they fall to the cell floor and breach while the the fissile material /modarator composition is optimum. Ilowever. due to the distribution of fissile material on the t cell floor, the margin of safety would be substantially reduced if this accident [ scenario should occur at the southeast end of the cell where the chopped fuel I loading station and most of the fuel residues are most likely concentrated. Therefore, llI.VAC collection containers are limited to the southwest end of the GPC and the CPC. L The OSR provides the necessary controls to facilitate the safe packaging and storage l of fissile contaminated waste and high concentrations of fissile material in TRU f waste drums and fissile material / debris particulate. O A1TACllMENTS Table 1 L f i t O i LLK0131:3RM 1 Page 5 of 7 P ~- ,-w-# . ~. -.m

e OSR/GP 12 Rev. 2 REFERENCES ~' -{a) (1) " Low-Level and Transuranic Waste Interim Storage Facility Safety Analysis;" Rev. O, HE:86:0021, February 8, 1984. (2) Hemo HF:84:0081, J. Goodman to R. E. Lawrence, " Response to the Radiation and Safety Committee Request for Drum Stacking Clarification," dated May 9, 1984 (3) " Criticality Safety Analysis Report - Packaging and Storage of VVNS TRU Wasto Containers," FB:84:0249, December 1984. (4) " Criticality Parameters of 55 callon Waste Drum Arrays," Rito SA 183 U. A. Blyckert and R. D. Carter of Rockwell Hanford Operations, Nover c ar 7,1980. (5) " Radiation and Safety Committee Minutes, Fissile Material Limits for LAC StoraSe Facility," Letter AB:86:A314, July 25, 1986. (6) Specification VVNS EQ 122, Revision 1 Specification for 55 Callon TRU Drums, r'~ 03/23/84. t (7) Specification VVNS EQ 119, Revision 0. Type A Container, 05/08/84 (8) " Criticality Safety Evaluation and Operational Safety Requirements for Consolidation of TRU Waste Drums Containing Process Solutes," J. A. Eggert, VV 365:87:0001, February 1987. (9) " Criticality Safety Evaluation, Operational Safety Requirements, Hazards Classification for Storage of CPC Debris Canisters in GPC." HB:86:0155, October 23, 1986. V.O L1K0131:3RM 1 Page 6 of 7

i -( OSR/GP-12 2 l Rev. 2 TABLE 1 l i. FISS7LE MATERIAL LIMITS AND CONTAINER SFECIFICATIONS FOR IAC STORAGE FACILITY i Fissile Material i Operational Safety Mass Mass i Container Description ' Limit Limit Container Specification Contents References i Uhite 55-Callon Drum 125 g* 200 g WNS-EQ-187, DOT Specification 17C TRU Vaste-1-6 White Rectangular Box 200 g* 350 g WNS-EQ-119, DOT Specification 7A TRU Vaste 1-5, 7 l 1 i s 4 i ' l I i [

• These limits may be increased to 200 grams per drum and 3 rams per TRU waste box with the approval of the Radiation and Safety Manager i

1 j l 4 j LLK0131:31J1-1 Fage 7 of 7 1 r oc -s-v~

e. - - + w

______,---___----_--------_--1---

000. Nuecer TR/GP-16 Revisten Numcer 2 Revision Oate 08-27-91 Digineering Release #1430 Per ECt4 #3354 West cey Jemonstration ?ro'ect CPEP ATION AL S AFE*"f REOUIRE"ENTS /b' O D. R. Steffes Oate PREPARE C:gnl:an: Enginee Cate$/ ff APPROVED,?Y _(# W C. J. Rcberts Cp$nt: Ant Manager Oate_dc!Pb f O t. ~ R. A. Humphrey APPROVED BY 4 81014 tion & parety Q C-.nLttee Chairman Oa t e Ch. 27 b APPROVED BY.- ^~W D. L. Shugars ~ f Quality As'ura e Oate [/ 2 8 e M M M M R. F. Cessner APPROVED BY t LLWTrepme Prje/pr' f.. ,4 /.M,. e _m J. L. Knabensenuh Oate $ /T'T APPROVID BY _ M0101Cgical & Environmental / yety. Manager / S Oa te 3 /~, /.i a 4 \\i, t v2., R. E. Lawrence. Jr. APPROVED BY, supernacant Treatment Project Manager West Vciley Nuclear Services Co. P.O. Bo x 191 West Volley, N.Y. 14171- 0191 LLK0134 : 3R4-1 DOE Approved: EW:90:0214 O' - ECB Concurrence: 08-10-91 WV - 1816 l

an - I TR/GP.16 Rev, 2 } RECORD Ol' REVISION PROCEDURE If there are changes to the Procedure, the revision nwt.ber increases by one. These changes are indicated in the left margin of the body by an arrow (>) at the beginning of the paragraph that contains a change, Example: The arrow in the margin indicaten a change Revisiu On Dated Rev. No. Description of Changes Page(s) 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release 1430 N/A 8/88 2 Per ECN 3354 Page 4 08/91 k'V-1807, Rev. 1 i LLK0134:3RM 1

TR/GP 16 Rev. 2 RECORD OF RENISION (CONTINUATION SHEET) 9 Revision on Rev No. Description of Charifs Page(s) ey 9 W-1807, Rev. 1 11 LLKG134:3RM-1 0

TR/GP-16 Rev. 2 O l l TYPE: l TITLF I'*.it F1re Protection Systems l NLHBER: GENPuiT OSR ! ) l l 16 i I Tech. Reqmn't. [X)l l l l CRITERIA:

1. Limit spread of contamination to clean areas.

UNACCEPTABLE EVENTS: 1. Spread of contamination. 1 I I Safety Limit l l Reporting Requirements: l DOE-ID CONTROLLED I40 I i I LCS l l l Surveillance Reqmn't. l 1 l l 1 I l I i Tech. Requirement l X l Critique _,j DOE-WPO CONTROLLED Operating Liatit 1 i IWNS CONTROLLED IMPLEMENTING PROCEDURES: > SOP 33-1 LLK0134:3RM-1 O l

TR/GP 16 Rev. 2 TECHNICAL REQU1REMENT i.g)- b PLANT FIRE PROTECTICN SYSTFtB l APPL.1CABILITY i This OSR applies to the operability requirements of the fire protection systems used at the WVDP for process areas of the plant. This includes systems dedicated to the Main Process Building, Liquid Waste Treatment System. Vitrification Facility, Supernatant Treatment System, Cement Solidification System. Size Reduction Facility and supercompactor. ORJECTIVE To assure that appropriate fire protection is available during various operations, sufficient to ensure life safety, prevent property damage and possible airborne release of radioactive contamination. ~- SPECIFICATION 1, PLANT VIDE A THE APPLICABLE PLANT, PROCESS, AND STORAGE AREAS (LISTED IN APPLICABILITY [ ABOVE) SHALL HAVE ' ABLE FIRE PROTECTION SYSTEMS, (AS APPROPRIATE), CONSISTING OFf '- .or.E OF THE FOLLOWING: 1. PORTABLE FIRE EXTINGUISHERS; 2. FIRE DETECTORS AND A1 ARMS; 3. F'RE HOSE STATIONS; .t 4. SELF CONTAINED FIRE EXTINGUISHING SYSTEMS (HALON OR DRY CHEMICAL); 5. COMPUTER / CONTROL ROOM HALON SUPRESSION SYSTEMS; OO L1.0134:3RM-1 Page 1 of 6 l

i TR/GP 16 Rev. 2 f 6. AREA WATER SPRINKLER SYSTEMS; AND 7. SUPPORTING WATER SUPPLY, PUMPING AND DISTRIBUTION SYSTEMS. UTILIZATION OF THESE SYSTEMS IS DETAILED IN TABLE NO. 1, [ REQUIREMENTS: I l t

1. FIRE EXTINGUISHERS f

FIRE EXTINGUISHERS, STATIONED THROUGHOUT THE PIANT, ARE INTENDED FOR USE ON j INCIPIENT STAGE FIRES BY AREA OCCUPANTS OR Tile VVNS FIRE BRIGADE. UPON j DISCOVERING _ DEFICIENCIES (MISSING, BLOCKED, OR UNINSPECTED, UNITS) IMMEDIATE AND CONTINUING ACTION SHALL BE TAKEN TO REPIACE OR RESTORE THE NORMAL ACCESS TO TilIS. ESSENTIAL LEVEL OF FIRE PROTECTION.

2. FIRE DETECTORS-AND ALARMS

[ t THESE SYSTEMS ARE INTENDED-TO PROVIDE EARLY WARNING OF FIRE' FOR PARTICULARLY O VULNERABLE OR SENSITIVE AREAS. WHENEVER A FIRE ALARM SYSTEM IS OUT OF SERVICE, f 'U. AREA SURVEILLANCE SHALL BE PROVIDED AS FOLLOWS: A. DAY SHIFT - AREA OCCUPANTS SHALL BE NOTIFIED OF THE DEFICIENCY AND INSTRUCTED TO BE ON THE ALERT FOR FIRE. _ SHOKING IN THE AREA SHALL BE PROHIBITED DURING PERIODS OF A " FIRE WATCH." s 1 B. OFF SHIFT SECURITY PERSONNEL SI ALL BE UTILIZED FOR HOURLY " FIRE WATCH" 0F i AFFECTED AREAS. 3, FIRE !!OSE STATIONS [ [ THESE INSTALLED FIRE FICHTING HOSES ARE INTENDED FOR USE BY THE FIRE BRIGADE AND - 1 VEST VALLEY VFD. RESPONSE FOR DEFICIENCIES ARE THE SAME AS FOR FIRE EXTINGUISHERS. L i c ',G. j U LLK0134:3RM-1 Page 2 of 6 ? [ n ,-mer., v,y y- ,e.~.----,---r m-..,-.- ..,we-. -r w .-m e u

r TR/GP-16 f Rev. 2

4. SELF CONTAINED FIRE-EXTINCUISHING SYSTEM LO VVDP HAS. TWO TYPES OF SYSTEMS, DRY CHEMICAL FOR THE ANALYTICAL CELLS AND MAINTENANCE LUBE ROOM, AND HALON FOR VARIOUS PROCESS CONTROL CONSOLES -THROUGHOUT l

THE PIANT. THESE SYSTEMS ARE INTENDED TO PROVIDE EARLY RESPONSE TO POSSIBLE FIRES IN EQUIPMENT OR AREAS OF SPECIAL INTEREST. OPERATIONAL DEFICIENCIES IN ANY 0F THESE SYSTEMS REQUIRES IMMEDIATE AND CONTINUING REMEDIAL ACTION. i -5. COMPUTER / CONTROL ROOM HALON SUPRESSION SYSTEMS i-THESE SYSTEMS ARE YN1 ENDED TO PROVIDE LOCAL COVERACE FOR SENSITIVE EQUIPMENT. IN-ADDITION TO CONTINUING ACTION TO RESTORE THESE SYSTEMS TO FULL OPERATION AS S0ON [ AS POSSIBLE, AN = INCREASED " FIRE WATCH" WILL BE ESTABLISHED DURING PERIODS VHEN L -f THESE AREAS ARE UNOCCUPIED. i

6. AREA VATER SPRINKLER SYSTEMS PRIMARY Ih 'NDED TO PROVIDE PROPERTY PROTECTION AND LIFE SAFETY, DEFICIENCIES

{ RENDERING Th. . SYSTEMS INOPERABLE SHALL RECEIVE IMMEDIATE AND CONTINUING ACTION-4 TO RESTORE FIRE PROTECTION. IN ADDITION THE ESTABLISHMENT OF AN INCREASED " FIRE r WATCH" UTILIZING AREA PERSONNEL OR-SECURITY RESOURCES SHALL BE IMPLEMENTED. 7.' SUPPORTING WATER SUPPLY. PUMPING, AND DISTRIBUTION SYSTEMS. THE " FIRE VATER" SYSTEMS OF WVDP ARE ESSENTIAL TO EXTENDED FIRE FIGHTING CAPABILITIES AT THIS PROJECT k i ? i i L l f O i l I l LLK0134:3RM-1 Page 3 of 6 l. f

2 TR/GP.16 Rev. 2 I TWO FIRE PUMPS,-AN ELECTRIC PRIMARY AND DIESEL DRIVEN BACKUP MUST BE.0PERATIONAL 10R." NORMAL" PLANT PROCESSING. ONE PUMP MAY BE OUT OF SERVICE FOR OCCASIONAL MAINTENANCE, ETC. --FOR NO MORE THAN EIGHT HOURS AT A TIME. LONCER INTERRUPTIONS REQUIRE PROVISION OF AN ALTERNATE PUMPER. l INTERRUPTION OF THE WATER SUPPLY FROM THE MAIN TANK REQUIRES VALVING IN THE BACKUP LAKE PUMPS TO SUPPLY RAW WATER DIRECTLY TO THE FIRE MAINS. IF SUCH A f CONDITION IS EXPECTED TO IAST IN EXCESS OF 24 HOURS PROVISION OF A FIRE DEPARTMENT PUMPER AND WATER SUPPLY IS REQUIRED. P l SURVEILIANCE REQUIREMENTS t

1. PORTABLE FIRE EXTINGUISHER ON SITE ARE INSPECTED MONTHLY BY OUTSIDE CONTRACTOR f

AND RECORDS ARE KEPT IN SAFETY OFFICE.

2. FIRE DETECTORS AND AIARMS ARE INSPECTED EVERY SIX MONTHS BY AN OUTSIDE' CONTRACTOR.

3. FIRE HOSE STATIONS ARE INSPECTED MONTHLY BY THE SAFETY TECHNICIAN AND RECORDS ARE KEPT IN SAFETY OFFICE.

4. SELF CONTAINED FIRE AND EXTINCUISHER SYSTEMS BOTH HALON AND DRY CHEMICAL ARE INSPECTED MONTHLY BY OUTSIDE CONTRACTOR AND RECORDS ARE KEPT IN THE SAFETY 0FFICE.

i 5, COMPUTER / CONTROL ROOM, HALON SUPRESSION SYSTEMS ARE INSPECTED EVERY SIX MONTHS BY I AN OUTSIDE CONTRACTOR. f

6. FIDW INSPECTION OF SPRINKLER SYSTEMS ARE INSPECTED ONCE PER YEAR.

7. SUPPORTING WATER SUPPLY, PUMPING AND DISTRIBUTION SYSTEMS ARE TESTED ONCE A WEEK k

BY PLANT OPERATIONS PERSONNEL AND RECORDED IN THE UTILITY ROOM LOG BOOK. 8 I e O LIX0134 : 3RM-1 Page 4 of 6 b

t TR/GP-16 Rev. 2 BASIS O %-) Fire protection systems are required to provide early detection and prompt control of fires occurring at WDP, Limits on combustible materials in waste storage areas and low activity levels in on site waste preclude off site impacts from all on site accidents involving fires as analyzed in the Safety Aalysis Reports, L ATTAQMDfrS f Y REFERENCES r i O U l t f p i i P [ .U 1.LK0134:3RM-1 Page 5 of 6 l m..,

O D O TR/CP-16 Rev. 2 Sb1f Water j Contained Computer / Supply l Fire Fire Fire Control Area Pumping & Fire Detectors Hose Extinguisher Room Water Distribution Extinguishers & Alarms Stations Systems Systems Sprinklers Systems I 1 l' 1 Plant X X X i i l CSS X X X X X f LWS X X X X X l t l STS X X X X I CTS X X X X X X i k i i i i i i l j LLK0134:3RM-1 Page 6 of 6 i

i O Coc. Num:er OSR/IRTS!1 Revision Num er 3 Revision Date 08-27-91 Engineering Release #1430 Per ECNs 2607, 2607A i Per ECN #3353 \\ esi u- :ic y 1 ~. Jemonstration Pro lect OPER AT'ONAL SAFETf REOUIRD'EMTS ~ O

0. R. Stetfes Cate 7 c '

PREPARE ~ C gnt:an; Enginee Cats $/ APPROVE 0'3 / C. J. Roberts [ C.or. :an: Manager Ca:a [/b4 I fY - _., _~ R. A. Hus;:nrey APPROVED BY fa:tation & (Sats;y Q Cr;::st :ee, 6.. air:an E'k $b APPROVEDSYf.) W~m D. L. Shugars Ca a / Quality Assura.we APPROVED SY / M M R. F. Cessner Oate I [ LLW Tre men-Pr japt f ) ,F M '4 xb Oate 6~/4 m /TT J. L. Kna ensenun APPROVED SY my d /'P.acacicgical&F.nvironmental SMe ty. Manager V ? .,j g /} 4.u 'u' ! V d Y \\, Ca:e /1 '. / 6 a ~ f-R. E. Lawrenc e. Jr. APPROVE 0 BY Su;;ernacant Treatment Project Manager West Vcliey Nuclear S ervices Co. P.O. B o x 191 West Volley, N.Y.14171-CISI DLS0316:ENG-392 DOE Approved: DW:91:0530 w WV-lE16 ECB Concurrence: 08-10-91

OSR/IRTS 1-Rev. 3~. RECORD OF REVISION If there-are changes to the= procedure, the revision number increases by-one. T These changes'are. indicated in the left margin of the body by an arrow-(>)'at the beginning of the paragraph'that contains a change. Example: The: arrow in the margin indicates a chan5e- ~ Revision On .Rev..No. Description of Changes Page(s) Dated-0 Original Issue All .1 Dated 5/20/88 All ~' 1 Engineering Release 1430 N/A 08/88 .2 Per ECN 2607 & 2607A All 12/88 3' Per.ECN 3353 Page 3 08/91 W-1807, Rev. I 1 =.- DLS0316 : 3PJi-1 ~

.m._ OSR/1RTS 1 Rev. 3 -RECORD OF REVISION (CONTINUATION SHEET) -j i,..e 1 3 Revision on Rev. No. Description of Changes Page(s) -i 1 1 i I i l-i i' 1 -i i-e ) I V 1 l t i 1 l; i-L 1 I !i i W-1807, Rev. 1 11 l_ l DLs0316:3RM-1 O I I

-t t OSR/IRTS l' -l Rev. 2 l.i i -RECORD OF REVISION (CONTINUATION SilEET) i Revision on -I Rev. No.-- Description of Changes Page(s) f f 4 1 i i ? ? I s t i ^; .i l ? c + 9 i t I r s ? ii e t I !i f . I I i v h t r t W 1807, Rev. 1 11 i 1 -DLS0316:3RM-1 e k P h b f h ._.,_..._...-.,__.,......._..._____.-._________._.____..___..____....._.___._._______._..___..-._..I

-.. = i t OSR/IRTS-1 ~! Rev. 3 l 1 -[ TYPE: l TITLE: Maintenance of Carbon Steel High l NUMBER: IRTS 1 l OSR-[X) l-Level Vaste Tank Integrity l-I l Tech, Reqmn't. [-ll l l-1 i CRITERIA: Protection of the carbon steel high level waste. i r UNACCEPTABLE EVENTS: 1. Failure of a carbon steel tank. t I I I Safety Limit l l Reporting Requirements: l DOE ID. CONTROLLED l LCO l X l UOR l 5 LCS l l l [ f Surveillance Reqmn't. l X l l I I l l I I Tech. Requirement i I lDOE-WPO CONTROLLED I I i Oyerating Limit l l lWNS CONTROLLED r > IMPLEMENTING PROCEDURES: l ) SOP 8-1 SOP 50-42 SOP 50-23 i I i DLS0316:3RM-1 O I I ) +

OSR/1RTS 1 Rev. 3 OPERATIONAL SAFETY RIMU11TMDIT fm u-MAINTENANCE OF CARBON STEEL WASTE TANK INTEGRITY APPLICABILITY This requirement applies to the concentration of caustic in the carbon steel waste storage tanks (8D-1 and 8D 2) and the operability of instruments for detecting the presence of leaking high level liquid waste in the pans that contain the tanks. OBJECTIVE To assure that the HLW in the carbon steel vaste storaga tanks 8D 1 and 8D 2 is maintained in alkaline conditiens at all times to prevent excessive corrosion of the t;nks, and to assure that any accumulation of HLW in the outer pan will be detected. ' SPECIFICATION LIMITING CONDITION FOR OPERATION EXCESS CA'JSTIC SHALL ALVAYS BE PRESENT IN TANK 8D-2 IN CONCENTRATIONS OF: A) AT LEAST 10 PERCENT BASED ON THE WASTE VOLUME UNTIL THE TOTAL VOLUME OF CONTAINED WASTE EXCEEDS 10,000 CALLONS, B) AT LEAST 5 PERCENT ON THE SAME BASIT UNTIL THE TOTAL VOLUME OF CONTAINED WASTE EXCEEDS 100,000 CALLONS; AND C) AT LEAST 1 PERCENT ON THE SAME BASIS AFTER THE VOLUME OF CONTAINED WASTE EXCEEDS 100,000 CALLONS. CAUSTIC SHALL BE ADDED TO TANK 8D-1 IN CONCENTRATIONS SUFFICIENT TO MAINTAIN THE TANK CONTENTS CREATER THAN A pH OF 11. IN THE EVENT THE PH IS DETERMINED TO BE LESS THAN 11, CAUSTIC SHALL BE ADDED WITHIN 48 HOURS. N DLS0316:3RM-1 Page 1 of 3 e -~v

l OSR/IRTS 1 Rev. 3 SURVEILLANCE ltEQUIREMENTS . -y V' 1. THE FH OF THE CONTENTS OF TANK 8D 1 SHALL.BE VERIFIED AS BEING GREATER THAN. [ 11 BY SAMPLING AT LEAST EVERY MONTH, f 2. THE PRESENCE OF EXCESS CAUSTIC IN TANK 8D 2 SHALL BE' ASSURED BY SAMPLING EACH EATCH ADDITION PRIOR TO TRANSFER TO THAT TANK. l 3. INSTRUMENTATION FOR MONITORING THE ACCUMULATIONS OF LIQUID IN THE PANS BENEATH LIQUID WASTE _ STORAGE TANKS 8D 1 AND BD 2 SHALL BE CHECKED FOR OPERABILITY AT LEAST_0NCE PER MONTH. THIS INSTRUMENTATION INCLUDES: f A. LEVEL INDICATORS 8LR 1, 8LR-5 B. LEVEL ALARM 8LAH 1, 8LAH-7 [ 5 BASIS The carbon steel HLW storage Tank 8D 2 is not suitable for storage of acidic wastes due to the potential for corrosion of the tank under acidic conditions, t f-~ i To prevent introduction of acidic wastes, normally acidic wastes must be [ s neutralized. prior to transfer into storage Tank 8D 2. Additionally, during waste i processing and mobilization activities (supernatant treatment, sludge / zeolite transfer, etc.), the addition of caustic to Tank 8D-1 must be considered to ensure that the above concentration requirements are complied with regarding residual wastes in the tanks and wastes-tra.isferred into this tank. The amount of excess caustic added to Tank 8D-1 raust be kept to a minimum to f minimize the migration of cesium from the cesium-loaded zeolite stored there and i to minimize the reaction of zeolite with the caustic. [ A lower limit can be placed on the amount of excess caustic in Tank 8D 1 because i the tank contents can be sampled directly on a routine basis. Tank 8D-2 on the other hand is sampled infrequently. Therefore, monitoring of excess caustic in Tank 8D-1 is easier. Furthermore, only two types of vastes will be transferred into Tank 8D-1, and none of them are acidic. These are cesium loaded zeolite and dilute supernatant from Tank 8D 2, which is already caustic. Tank 8D-2 on the j A(,) DLS0316 : 3RM-1 Page 2 of 3 f D ,- =- + .,..e ,7 ,_,~ p. -y

t OSR/1RTS 1-Rev. 3 other hand is used to receive and collect waste from almost anywhere in the ,,~ (_ j) f General Plant. Finally, corrosion coupons will be installed in Tank 8D 1 to monitor. corrosion. The addition of caustic, as well as possibly sodium nitrite, t to control corrosion in Tank 8D-1 will be based on periodic examination of these coupons. Sufficient caustic must be added to Tank 8D-1 to keep corrosion to a minimum. A pH of 11 was selected becaisse it is conservative with tespect to minimizing corrosion. The pH in Tank 8D-1 will tend to drift downward, over a period of f time because the zeolite has a bufferring affect. The pH, however, is not expected to drop below 9.5, which corresponds to a caustic concentration that is j still sufficient to minimize corrosion. If the pH in Tank 8D-1 is ever determined to be less than 11, response within a 48-hour time frame to add f additional caustic will be sufficient to maintenanc'e of the integrity of Tank SD 1 at all times. [ i Pans are provided'in the SD-1 and 8D-2 waste tank vaults to enhance detection of tank leakage. Vault inleakage reaching a level above the rim of the pan would l /T also be accumulated in the pan. Level indicators with a high-level alarm are { .V provided to annunciate any major leakage so that remedial measures may be promptly instituted, s Since vault leakage is not expected to develop at a high rate and the silty till in which the vaults are buried is expected to inhibit migration of liquids for i many years, a monthly surveillance frequency of the functioning of leak detection alarms will assure that the public will be protected from nadetected tank leakage. ATTACIIMENTS None i REFERENCES i i NFS Tech Specs, Change No. 18 t i h (" + s. DLS0316 : 3RM-1 Page 3 of 3 l

v Occ. Nue:er TR/ IRI'S-2 Revisten Nu=:er 3 Revision Oa:e 08-27-91 Engineering Release #1430 Per ECN #2842 Per ECN #3354 \\$/G S 1. /-] I ie i uiley Jemonstration Pro'ect CCER AY!CNAL S AFE7? RE':UIRC4ErS }:f< s tKm e / +1 D. R. Stefres Cate ' T /'A ' W PRE?ARED BY < t - --, Cogni:an.Enginee// Cat e 5,! Y C. J. Roberts ~ APPROVD,3Y @ n;:an: Manager s. APPROVOEY__fb R. A. Hu=;hrey Ca:e [ibC Ric.;a:10n 1(Saf e:y Q i Ccr.=1,0:ee, Cha te.an i wg/ Oa:e D~/c 2. b-APPROVC BY ( )

• he D. L. Shugars r

qual;;y Assurance APP'CVED EY t Ms R. F. Cessne.- Cate I M 7., Fra LLWTrea=en*Y,,:eg'f f 2f APPROVED BY I. %' , %ee. J. L. Knacensenuh Date 6~# r /T T 4 s r.acacieg;021 & Envircnmental S24ety. Manager ._ j y ? APPP.CVE0 BY '1 b di,l '-4.6 'I R. E. Lawrence. Jr. Oate */./>a Su;crnatan: Treatmen; Project Manager West Vcliey Nuclecr Services Co. P.O. Sox 191 West Vctiey, N.'f 14171-CISI DOE Approved: LM 90:0214 MSS 0808: 3R4-1 ECB Concurrencet 08-10-91 W V - 1816

~ TR/IRTS 2: Rev. 3' i i RECORD OF-REVISION l PROCEDURE r =If there are changes to the procedure, the revision number-increases by one. .These changes are indicated in the left margin of the body by an arrow-(>) at i the beginning:of the paragraph that contains a change. [ s l -I L f Example 2: The arrow in the margin indicates a change, l l 1 i Revision On Dated Rev.-No. Description of Changes Page(s) r s O-Original Issue All ~ i 11: Dated 5/20/88 All-- l t t 1 Engineering Release 1430 N/A 08/88 2 Per ECN #2842 All; 03/89 3. Per ECN #3354 Page 4 08/91 s i i y i i L i

W-1807, - Rev; 1 i

. MSS 0808:3RM-1. g i l r

TR/IRTS 2

f Rev -3

-l RECORD OF REVISION'(CONTINUATION SilEET) f g j Revision on. i -Rev.-No. Description of Changes Page(s)- i f f I e-! II !.t + 1 t ? 1 . i, t e f 1 e i ~k 't i I t i i i 41 7 6 t i W-1807, Rev. 1 11 1 -MSS 0808:3RM ! I ? [ . ~. - -,

TR/IRTS.2 Rev. 3 O-1 I . (,j TYPE: l TITLE: Control of CSS Recipe for l NUMBER:- IRTS 2 [ OSR [ ] l Decontaminated Supernatant l I I Tech Reqmn't. [X)l l I I CRITERIA: 1. Vaste produced shall meet the requirement of the Process Control Plan. UNACCEPTABLE EVENTS: 1. Production of solidifie:1 waste outside the approved recipe range. p 8 a W I I I i Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED LCO l l l r LCS' l. l ] p Surveillance Reqmn't. l l l 1 (' l I l i l I l Tech. Requirement I X l Critique l DOE-WPO CONTROLLED j i i I Operating Limit l l lWNS CONTROLLED l IMPLEMENTING PROCEDURES: I WNS PCP-001, Process Control Plan for " Decontaminated Supernatant Cement [ Solidification" > SOP 70 1 > SOP 00-13 > SOP 70 40 > S0P 70 45 [ i> t i i [ MSS 0808:3RM-1

TR/IRTS 2 Rev. 3 TECIINICAL REQUIREMENT CONTROL OF CSS RECIPE IUR DECONTAMINATED SUPERMATE APPLICARILITY This requirement applies to control of the quality of cement produced by the C3S process. OlUECTIVE To provide assurance that the recipe used in CSS to solidify decontaminated supernatant produces a product for storage that roeets the reference 1. REQUIREMENTS 1. ONLY DOE-APPROVED RECIPES (THOSE DOCUMENTED IN THE APPROVED '.SS O DECONTAMINATED SUPERNATANT PROCESS CONTROL PIAN) SHALL BE USED IN SOLIDIFICATION OPERATIONS. 2. THE IINAL CEMENT PRODUCT SHALL MEET THE FOLLOWINC QUALITY STANDARDS: A. WATER-TO-CEMENT RATIO OF BETWEEN 0.54 AND 0.70 B. COMPRESSIVE STRENCTH GREATER THAN 186 PSI C. FREE WATER CONTENT LESS THAN 0.5 PERCENT BY VOLUME. D. DRUM FILL FACTOR MUST BE CREATER THAN OR EQUAL TO 85 PERCENT. O MSS 0808:3RM-1 Page 1 of 2

i TR/IRTS 2 Rev. 3 (,) ' ~ - SURVEll3ANCE TESTS FOR THE PARAMETERS LISTED IN GEQUIREMENT NO 2 ABOVE SHALL BE PERFORMED ON ONE RANDOMLY SELECTED DRUM FROM EACH BATCH OF WASTE IN TANKS 5D.15A1 OR SD 15A2, EASIS In order to meet the waste form performance criteria stated in the NRC f Branch Technical Position, the CSS product must be in conformance with the approved recipe. The key performance indicator with respect to recipe compliance is the water to cement ratio of the final product. This ratio must be maintained between 0.54 and 0.70, Other key indicators of acceptable performance are the compressive strength, free water content, and percent fill, The NRC requirements must be met in order to provide a range of acceptab1'e options for permanent disposal of the cemented q decontaminated supernate. U The change in the cube compressive strength requirement from 60 psi to 186 psi is based on updated statistical evaluation of compressive strength test data documented in reference letter WD:89:0053 (FH:89:0006). ATTACIMENTS None REFERENCES l 1. Process Control Plan for Decontaminated Supernatant Cement Solidification (WNS-PCP-001). P b I (V MSS 0808:3RM-1 Page 2 of 2

i O f e (a) Doc. Nu:::er OSR /TRTS-3 Revision Num0er 3 Revision Date 08-27-91 Engineering Release #1430 Per ECN #3122 Por ECN #3353 West aJey 3emOnSITGIIOn ?rO ect 1 OPERATIONAL SAFE *"? REOUIREMENTS PREPARE M D. R. Steffes Oate "C Cognizan Engineer // !W II -APPROVED JY C. J. Roberts Oate [, C9snt: Ant Manager \\ 9 0 09 -- _IL cat. 5-ha /PP APPROVED E!. R. A. aumpneey Alciation &{Safecy Q l CrgmLttee, Chair:an Cate T/k U b APPROVED BY f ) hm D. L. Shugars Quality Assurance M M R. F. Cessne.- Cate 7 APPROVED BY .LLW Tr,e men Prjeg/ APPROVED BY .x J. L. Knabensenuh Cate E/4.c /T W ..~7 A.aciological & Enytronmental 8 /' S e.ty. Manager f 4M,lt41 R. E. Lawre nc e, Jr. Date i /2 /. 3 APPROVED BY, Supernatant Treatment Project Manager West Valley Nuclear-Services Co. P.0, Ec x 191 West Vcliey, N.Y.14171-Clet RLC3243: SEA-65 DOE Approved: DW:91:0530 i WV-1816 ECB Concu m nce: 08-10-M

'OSR/IRTS 3 Rev? 3

I{

RECORD OF REVISION f PROCEDURE-If there are changes to the procedure; the revision number increases by-one. l These changes are indicated in.the left margin of.the body by an arrow (>) at j! the beginning of the paragraph that contains a change, -l Example:- i 1 The arrow in the margin' indicates a change. } Revision On i Dated Rev. No; Description of Changes Page(s) -0 . Original Issue All [ I 1 -Dated 5/20/88-All -f -1 Engineering Release N/A-08/88 2-Eliminate Ambiguous k'ording per All 09/89 1 ECN #3122 3' Per ECN #3353 Page 4 08/91 i k .[t i I f i i r f i; i t i b I W 1807, Rev. 1 1 LED 0835:3RM 1 1

i i OSR/1RTS-3 .I Rev,' 3 RECORD OF Rr31SION (CONTINUATION SilEET) I f f Revision on i Rev. No. Description of Changes Page(s) f LI a -- e i i i t i i .i I I i@ 1 f i i r h i l 4 - n f l 1 I I t ? I i 6 I .) !i i W-1807, Rev. 1 it LED 0835:3RM 1 ,e 1 t

OSR/IRTS 3 Rev. 3 ,d 1 I . V TYPE: .[ TITLE:- Maintenance'of Spare HLW l NUMBER: IRTS 3 OSR [X) l Storage Capacity l l 1 Tech, Reqmn't. [.]l l-1 I CRITERIA; 1. Carryover Technical Specification from the NRC licensed NFS operations shall be maintained, !I 4 i UNACCEPTABLE EVENTS:. Tank failure without spare capacity to accommodate the waste volume stored in the leaking Tank, 1 I I Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED' LCO 1 X l UOR l l LCS l l l + Surveillance Reqmn't. l X l l 1 l l {v%l i l I 4 Tech. Requirement l l l DOE WPO CONTROL. LED I I i Operating Limit i i IWNS CONTROLL,ED > IMPLEMENTING PROCEDURES: a ' SOP 50 44 SOP'8 1 r 6 LED 0835:3RM 1 4 O i l l l . ~

OSR/IRTS-3 Rev. 3 OPERATIONAL SAFETY RF4UIREMENT O MAINTFNANCE OF SPARE HIR STORACE CAPACITY APPLICABILITY This requirement establishes the minimum provisions to be maintained in order to accommodate stored HLW in the event of failure of storage tanks in use. OILIECTIVE To ensure confinement of HLW. SPECIFICATION LIMITING CONDITIONS FOR OPERATION 1. SPARE TANKS OF SUITABLE CORROSION RESISTANT MATERI AL SHALL BE MAINTAINED WITil SUFFICIENT CAPACITY AND APPROPRIATE COOLING PROVISIONS TO ACCOMMODATE Tile CONTENTS OF THE LARGEST TANK IN WilICll HIGH-LEVEL RADIOACTIVE LIQUID WASTE, OF EACH CORROSIVE CHARACTERISTIC, IS STORED. 2. WHEN STORAGE OF HICH LEVEL RADIOAC11VE LIQUID WASTE HAS BEEN INITIATED IN ANY SPARE TANK REQUIRED BY ITEM 1 ABOVE, OR SUCH A TANK llAS BEEN FOUND TO BE UNSUITABLE FOR SPARE SERVICE, ACTION SHALL BE INITIATED WITHIN 24 HOURS TO REPLACE THE SPARE CAPAw1TY, 3. RADIOACTIVE LIQUID MAY RESIDE IN SPARE TANKS, WITHOUT COMPROMISING Tile AVAILABILITY OF THE SPARE CAPACITY, PROVIDED THE FOLLOWING CONDITION EXISTS: THE RADIOACTIVE LIQUID WASTE CAN BE REMOVED OR ITS VOLUME REDUCED SO THAT THE TOTAL LIQUID INVENTORY OF RADICACTIVE WASTE CAN BE CONTAINED IN THE SPARE TANK. O LED 0835:3RM-1 Page I of 3

OSR/IRTS-3 Rev. 3 SURVEILLANCE REQUIREMENT INSTALLED EQUIPMENT (PUMP NO C 001) AND EMERGENCY SPARE PUMP (WELDON PUMP) FOR TRANSFERRING Tile RADIOACTIVE FLUID STORED IN ANY HLW TANK TO THE SPARE TANKAGE SHALL BE INVENT 0RIED FOR AVAILABILITY AT LEAST EACll SIX MONTHS AND TESTED FOR OPERABILTTY AT LEAST ONCE PER YEAR. THE VOLUME OF WASTE IN llICH LEVEL WASTE TANKS SHALL BE CALCU1ATED EACH MONTH. AT NO TIME SHALL THE VOLUME IN 8D-2 BE GREATER THAN 720,000 CALLONS AT A DENSITY OF 1,22 gr/mL OR BD 4 BE GREATER THAN 13,410 CALLONS AT A DENSITY OF 1.66 gr/mL. PAN AND VAULT LEVEL DETECTION EQUIPMENT SHALL BE MONITORED DAILY. R BASIS Although waste tank life expectancy is half a century, the time when a tank will fail is not accurately known. Rather than explotting the confinement provided by the vaults in which tanks are buried during the construction of replacement tanks, this specification requires the maintenance of spare tanks, to which stored wastes could be transferred. The 8D-1 AND 8D-2 tanks sit on an engineered pan in a " cup and saucer" arrangement. Both the vault and the pan are equipped with leak detection level monitors. The vaults are equipped with jets to pump liquid to the pan and the pan is equipped such that_ leaks may be pumped b.ek to the tank. The 8D-3 and 8D-4 tanks are contained in a vault that is stainless steel lined. The vault is equipped with jets to pump liquid to either tank. Water head in the soil located around the vault is monitored and water is added as necessary to maintain a super saturated condition so as to assure inward leakage should a crack in the vault develop. A second safety feature of this system is the margin of confinement assured by the low permeability and high lon exchange capacity of the native silty till which surrounds the vault excavation. O LED 0835:3RM-1 Page 2 of 3

OSR/IRTS 3 i Rev. 3 Therefore, spart tanks do not require replacement until they no longer serve as f spares (i.e., it is not necessary to have spare tanks for spare tanks). All of the above factors provide 0,e necesssry time for response to an identified tank

leak, i

i 'iPe use of 80 1 for housing the STS cankage/ columns, storage of spent zeolite, and f r co!lection of 80 2 condensate and STS process water (e.g., sluice vater) does not compromise the requirement to maintain adequate spare tankage for the liquid llLV which have been stored in 8D 2. The 8D 1 contents can be processed through STS t and/or transferred to LWTS in a period of approximately 20 days. This time period is based upon historical STS processing data which showed that the largest 8D.1 volume which required volume reduction was 207,800 gallons and an assumed LVTS process rate of 8 gallons / minute. l I This OSR requires squipment to be available on site, to permit taking advantage of I the provision of spare tanks. j The use of Tank 8D.3 for vaste processing activities does not compromise the requirement to maintain adequate spare tankage for the thorex wastes which have - \\s / been stored in Tank 8D 4, because the 8D 3 contents can be transferred to 8D.2 or LVTS in parallel with installation of temporary transfer equipment in 8D 4. [ f The surveillance requirements for pan, tank, and vault level provide assurance i that significanc changes in tank lavel and corresponding changes in pan and vault t levels will not go undetected and thur assures the protection of public health and f safety. i ATTACHMENTS None i RFSERENCES i b NFS Tech Specs, Change No. 8 1 i ) 5 LEDo"'5:3RM-1 Page 3 of 3 P ---,-..m._ _,_.. -...--_-..-, _ _ _ _, ~. _ - -m.- -, -... -. -.. -

Coc. Nu=cer TR/1RTS-4 Revisien Nu= er 4 s Revision Cate 08-27 41 Engineering Release #1430 Per ECN #2779 Per ECN #3000 Per ECN #3354 West a ey 3GTIO1STTGT:On Pro. ecT CPt.8. AT 0N AL S ATIN R f 0'J!MIEM*2 PP.E7 ARE M

0. R. 2:s tf e's sate

'T Cogna:an: Lt.itnee ATPROVED Y / C. J. Rocerts 04:e II ~ Cctsni: ant Manager APPRCVED BY_ N _[_ R. A. Hum;hrey Cate b f.10.;stien & Q 8 C p :ee, kEstacy atr=an APPROVED BYI ) h e_ D. L. Shugars Cate b Gua1L;y As urance / APPROVE 3 BY / M R. f. Ce gr.or Cate I [ ~ LLW ires een Pr J ept APPROVED BY e J. L. Knac er.s cr.un Cate $ b / M i f?.actoics L:21 & Iny;ronmental / Safety Manage.- Wl, ! t *.6 R. E. Lawrence. Jr.

& e i N '. / " ^

APPP.0VED BY supernacan: Treat:ent Project V.anager West Vciley Nuclear Services Cc. P.C. Ecx 191 West Valley, N.Y.14171-CISI DOE Approved: IM:90:0214 LED 0703: 3RM-1 ECB Concurrence: 08-10-91 wy.lgls .--w--. 4.--...._., ,,---.-_,_.,-~,,_.,,-.,-....u.,.-..ww,,-..+,..,,,.y.w-- ,,,,,,.r, y.,,.-...-,.,, 3yw,-e,--,

TR/IRTS 4 Rev. 4 RECORD OF REVISION PROCEDURE If there are changes to the procedure, the revision nun.ber increases by one. These changes are indicated in the left margin of the body by an arrow (>) at the beginning of the paragraph that contains a change. Example: The arrow in the rtargin indicates a change. Revision On Dated Rev. No. Description of Changes Page(s) 0 Original Issue All 1 Dated 05/20/88 All 1 Engineering Release 1430 N/A 08/88 2 Per ECN No. 2779 All 02/89 3 Per ECN No. 3000 All 07/89 4 PER ECN NO. 3354 Page 4 08/91 W-1807. Rev. 1 i LED 0703 : 3PJi-1

TR/1RTS 4 Rev. 4 RECORD OF REVISIOli (CONTINUATION SilEET) O Revision on Rev. No. Description of Changes Page(s) Dated O W 1807, Rev.1 11 LED 0703:3RM 1 O

TR/1RTS 4 Rev. 4 I I TYPE: l TITLE: Depressurization of STS for l NUMBER! IRTS-4 OSR ( ) l Maintenanco l 1 i Tech. Reqmn't. [X)l l ~l I i CRITERIA: 1. Protection of workers against unnecessary radiation exposure. 2. Protection of noncontaminated facilities from inadvertent surface contamination. P I i UNACCEPTABLE EVENTS: 1. Unplanned radiation exposure of operators. 2. Contamination of clean facilities. 1 I I l Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED l I - LCO l l l l LCs l l l q Surveillance Reqmn't. l l l l I l l l l l Tech. Requirement l' X l Critique IDOE WPO CONTROLLED a r i l I Operatinr. Limit l l lVVNS CONTROLLED IMPLEMENTING PROCEDURES: SOP $0 36 SOP 41 34 - SOP 50 37 SOP 50 24 SOP 50 44

TR/IRTS 4 i Rev. 4 t TEcllNICAL RFQUIREMENT DEPRESSURIZATION OF SUPERNATANT TREATMENT SYSTIM tVR MAINTENANCE APPLICARILITY h This requirement is applicable for all maintenance work to bo done on STS. On tECTIVE The objective cf this requirement is to prevent backup of high level waste (llLV) into the STS operations area by removing the driving head necessary to cause back flow during all occasions that inadvertent depressurization of instrument air systems could occur. RfX)UIREMFNTS PROCEDURES FOR SHUTDOWN OF STS SHALL REQUIRE DEPRESSURIZATION OF TANKS D 001, (SUPERNATANT MAKEUP TEED TANK), AND D 004 (SLUICE WATER LIFT TANK) IMMEDIATELY UPON SECURING Ti1E ASSOCIATED PUMPS (G 002 AND G.003). 2. ACCESS TO T$iE LEVEL / DENSITY INDICATOR CABINETS SilALL BE UNDER Tile CONTROL OF TliE SHIFT SUPERVISOR. 3. NO MAINTENANCE SilALL BE STARTED ON D 001 OR D 004 BUBBLERS OR VESSEL PRESSURIZATION SYSTEMS AND TiiE ASSOCIATED PIPING, TUBING, INSTRUMENTATION AIR SUPPLY, ELECTRICAL POWER SUPPLY, OR ANY WORK TO BE DONE IN Tile LEVEL / DENSITY CABINET, UNTIL D 001 AND D 004 ARE DEPRESSURIZED. A. DELETED B. DELETED C. DELETED D. MOVED TO 6. E. DELETED O 1.ED0703:3RM-1 Page 1 of 4

l TR/IRTS.4 [ Rev. 4 i i 4. DURING WATER RECIRCUIATION ANY MAINTENANCE ITEMS, NOT INCLUDED IN REQUIREMENT #3 CAN BE PERFORMED WilILE D 001 AND/OR D 004 ARE PRESSURIZED WITil [ Tile AUTil0RIZATION OF THE SHIIT FUPERVISOR AND THE PROCESS CONTROL ENGINEER ON Tile WORK CONTROL DOCUMENT, E.G.. WORK ORDER OR OPDR. l 5. IN SITUATIONS WilERE MAINTEN/NCE ON OPERATING SYSTEMS TS REQUIRED VilILE Tile SYSTEM IS PRESSURIZED AND PROCESSII;G f t'PERNATANT, MAINTENANCE CAN BE PERFORMED WITH Tile EXCLUSION OF THE ITEMS IN REQUIREMENT m3, WITH Tile l EXPLICIT APPROVAL OF Tile OPERATIONS MANAGER AND Tile RADIATION AND SAFETY [ MANAGER OR THEIR DESIGNATE ON Tile WORK CONTROL DOCUMENT, E.C., WORK ORDER OR - OPDR. [ 6. ANY MAINTENANCE ON OFFICE OR BUILDING SYSTEMS DURING SUPERNATANT PROCESSING REQUIRES ONLY Tile AUTil0RIZATION OF Tile SilIFT SUPERVISOR AND PROCESS CONTROL ENGINEER TO ASSUPE THERE IS NO IMPACT IN SAFE OPERATION OF Tile PROCESSING SYSTEM. I e SURVEILLANCE REQUIREMENTS 1. READ AND RECORD PRESSURE ON 50 PI.703 OR 50 PI 710 AND VERIFY AT ZERO PSIG WHEN PUMPS G 002 OR G.003 ARE SHUTDOWN, RECORD IN SHIIT SUPERVISORS LOG BOOK. [ i i 2. VERIFY THAT' BYPASS VENT VALVES 50.lN 719 OR 50 IIV 718 ARE OPEN TO I DEPRESSURIZE TANKS, RECORD IN Sil!FT SUPEkVISORS LOG BOOK. i 3. PRESSURE INDICATORS TO BE CALIBRATED ANNUALLY. i I I 4. CllECK AUTOMATIC SHUT OFF VALVES TilAT PREVENT BACKUP OF HLW INTO OPERATING j AISLE ON A SEMIANNUAL BASIS. ? i LED 0703:3RM 1 Page 2 of 4 1 [ w _. _, ~. _ _ ~.

TR/1RTS.4 7 Rev. 4 i RASIS O Due to the driving force available from the pressurized tanks D 001 and D 004 the bubbler and vessel pressurization systems on these tanks shall not have j maintenance done unless the vessels are depressurized. This requirement is needed because the equipment associated with the bubbler and vessel pressurization systems is located in the STS operating aisle. Without l depressurization of the vessels prior to maintenance work there is potential to have HLU backup into the operating aisle. t Maintenance on all equipment within the level / density cabinet shall also require depressurization of tanks D 001 and D 004. This is due to the possibility, in the confined space of the cabinet, of inadvertantly causing loss of the bubbler system (s). The access to this cabinet shall be under the control of the Shift Supervisor per Requirement a2, I [ During water recirculation of the STS lon exchange columns it is technically 1 t f^ important to maintain flow, to prevent spiking of column effluents when flow is [ resumed. Maintenance can be performed during water recirculation, with the exception of the above mentioned items, with the approval of the Shift Super"isor 7 [ and the process Control Engineer on the Work Control Document, e.g., Work Order [ or OPDR. In situations where maintenance is required while the system is pressurized and [ processing supernatant maintenance can be performed, with the exclusion of items k i in Requirement a3, with the explicit approval of the Operations Manager and the Radiation and Safety Manager or their designate on the Work Control Document, e.g., Vork Order or OPDR. f I i LED 0703:3RM 1 Page 3 of 4 i

TR/1RTS 4 Rev, 4 ^ " ^ " " " " " O None RE}TRPWCES

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TR/1RTS 5 Rev. 6 RECORD OF REVISION PP.0C EDl'RE If there are changes to the procedure, the revision number increases by one. These changes are indicated in the left trargin of the body by an arrow (>) at the beginning of the paragraph that contains a change. Example: The arrow in the niargin indicates a change. Revision on Dated Rev. No. Description of changes Page(s) 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release N/A 08/88 2 Per ECN No. 2607 & 2607A All 09/88 3 Per ECN No. 2845 All 02/89 4 Per ECN No. 2978 All 06/89 5 Per ECN No. 3174 1-3 11/89 6 Per ECN No. 3354 Page 3 08/91 W-1807. Rev. 1 i MSS 0678:3PJ1

TR/1RTS 5 Rev, 6 RECORD OF REVISION (CONTINUATION SilEET) Revision on Rev. No. Description of Changes Page(s) O W 1807, Rev. 1 11 MSS 0678:3RM-1 O

TR/IRTS.5 j Rev, 6 I l l TYPE: l TITLE: STS Process Limits l NUMBER: IRTS 5 OSR [ }- l l I I i Tech. Regan't. [X)l l l l l ( ) CRITERIA:

1. Vaste produced shall meet the qualification of the Process Control Plan.

2. STS shall meet the design criteria of a Decontamination Factor greater

} than 1,000 for Cs.137 if the waste is to be solidified in the CSS. }

3. STS may transfer liquid from 8D 1 to LVTS for volume reduction if the

{ volume reduced liquid is returned to the waste tank farm (8D.2). l t { UNACCEPTABLE EVENTS: 1. Failure of the STS to produce a decontamination factor of i 1000 for Cs.137. i 5 I I I i Safety Limit l l Reporting Requirements: l DOE.!D CONTROLLED LCO l-l l t LCS l l l Surveillance Reqmn't. l l l l l l l Tech, Requirement I X l Critique (DOE.WPO CONTROLLED I I I i Operatirp. Limit i l lWNS CONTROLLED l f > IMPLEMENTING PROCEDURES: SOP 50 23 So t' 50 36 SOP 50 42 l [ -SOP 50 33 SOP-00 13 SOP 50 32 SOP-50 44 i t HSS0678:3P& 1 ) i { t t O 1 r I [ b l t l.... - -... -.

TR/IRTS 5 Rev. 6 TECIINICAL KV)UIREMlWT SUPERNATANT TREA1HDrr SYS14*M PROCESS _ LIMl_TS_ APPLICABILITY i Requirement No. 1 applies to the maximum concentration of Cs 137 permitted in the discharge of the final ion exchange column in the STS. l.oquirement No. 2 applies to the maximum Cs 137 concentration permitted in the transfer of decontaminated i supernatant from BD 3 to the INTS, Requirement No. 4 applies to liquid that is sent to INTS for volume reduction and is ultimately returned to the VTF. OILIECTIVE I To provide a means to monitor the decontamination factor for Cs 137 provided by the STS system and to assure that supernatant transferred eventually to CSS is [ decontaminated by a factor of at least 1,000 for Cs 137. ? DEFINITIONS STS processes three kinds of liquid. 1. Decontaminated Supernatant - liquid from Tank 8D-2 (either diluted or i undiluted) that has passed through the STS ion exchange system. t 2. Decontaminated Supernatant plus Flush - a final process step for STS operaticn which uses liquid from Tank 8D 1, or water, to push residual supernatant through the ion exchange columns. Typically 10,000 gallons of I I Tank 8D-1 liquid or 6,000 gallons of water is used to flush the colwnns. 3. Liquid from Tank 8D 1 - water condensed from vapor generated in Tank 8D 2 and [ water generated from various STS operations. This liquid has a relatively l t low salt concentration and a constantly increasing cesium concentration (as loaded zeolite is dumpfd to Tank 8D 1), tG l MSS 0678:3RM-1 Page 1 of 4 i

i TR/IRTS 5 Rev. 6 REQUIREMENTS 1. LIQUID RADIATION MONITOR 50RE034 SHALL BE OPERAT1 sNAL AT ALL TIMES TO ANALYZE f CONCENTRATIONS OF RADIOACTIVE MATERIALS IN DECONTAMINATED SUPERNATANT PRODUCT TRANSFERRED TO TANK 8D 3. THIS MONITOR SHALL BE CAPABLE OF BEING CALIBRATED TO A LEVEL CORRESPONDING TO 10 PERCENT (OR LESS) 0F THE Cs 137 TRANSFER LIMIT t (1. E., s 0. 55 pCI/ML). THE MONITOR AIARM POINT SHALL BE SET SUFFICIENTLY LOW ~ TO ASSURE THAT CONCENTRATIONS OF Cs 137 IN EXCESS OF 5.5 pCi/ int BEING TRANSFERRED TO TANK 8D 3 WILL cal'SE AN AIARM. AUDIBLE AND VISUAL AIARMS r SHALL BE PROVIDED IN THE STS CONTROL ROOM. 2. TRANSFERS OF DECONTAMINATED SUPERNATANT AND FLUSH WATER FROM TANK 8D 3 TO THE LUTS SHALL BE LIMITED TO A MAXIMUM CONCENTRATION OF Cs 137 CORRESPONDING TO A DF OF 1,000 AS DETERMINED FROM TABLE 1. 3. RESPONSES TO A1 ARMS SHALL BE ACCORDANCE WITH SOP $0 33. r 4. ' TANK 8D 1 LIQUID", AFTER PROCESSING THROUCH STS, MAY BE ROUTED FROM TANK 8D-3 TO THE LVTS FOR VOLUME REDUCTION. THE VOLUME REDUCED LIQUID WILL BE RETURNED TO TANK 8D 2. ADMINISTRATIVE CONTROLS SHALL BE USED TO ENSURE THAT p THIS LIQUID IS NOT TRANSFERRED TO CSS. AT NO TIME MAY THE ACTIVITY CONCENTRATION IN THE VOLUME REDUCED LIQUID EXCEED 50 pCI/ML. A j DECONTAMINATION FACTOR IN STS SHALL NOT LIMIT TRANSFERS OF " TANK 8D 1 LIQUID" [ FROM 8D 3 TO LWTS (REQUIREMENT NO. 2 0F THIS TR). TR/IRTS-7 DOES NOT APPLY TO TANK 8D 1 LIQUID PROCESSING. TANK SD-15B SHALL BE SAMPLED AND THE j ANALYTICAL RESULTS USED TO CALCULATE THE MAXIMUM VOLUME REDUCTION THAT CAN BE ACHIEVED. l SURVEILIANCE REQUIREMENTS 1. SAMPLING AND ANALYSIS SHALL BE IN ACCORDANCE WITH THE STS SAMPLE PLAN CONTAINED IN SOP 50 42. 2. CALIBRATION FOR RAD MONITORS SHALL BE PERFORMED EVERY SIX MONTHS. O MSS 0678:3RM 1 Page 2 of 4 [ ~ t 4 s

TR/IRTS-5 Rev. 6 3. WHEN TANK 8D 1 LIQUID IS BEING VOLUME REDUCED, TANK SD 15A1 OR TANK SD 15A2, 5 AS NECUSARY SilALL BE SAMPLED TO ENSURE AN ACTIVITY CONCENTRATION OF b $0 pCI/HL IS NOT EXCEEDED. KASIS i The STS was designed to provide a supernatant decontamination factor of at least i 1,000 for Cs 137. Technical requirement No 2 gives the maximum acceptable Cesium concentration in Tank 8D 3 based on a DF of 1,000 from Tank 8D 2 l supernatant. This requirement sets STS product quality by placing a cesium limit, which is based on the weight fraction of the product, therefore ensuring an acceptable final product at CSS. DF calculations for supernatant shall be based on samples of Tank 8D 3 and tank D 001, and are used to verify STS system DF, Decontaminated supernatant with a decontamination factor less than 1,000 as i measured at Tank 8D 3 will be recycled to Tank 8D 2 for rework. Transfers from l t Tank 8D 3 to LWTS containing flush water shall meet the conditions of requirement No. 2 of this Technical Requirement, but the system DF calculation, as described above, is not used for the transfer. Due to the changing feed concentrations, it is not possible to get a representative system DF whilo using flush water. Os Volume reduction of Tank 8D 1 liquid may be required as an emergency response to a leak in the waste tank farm. LVTS is capablo of performing this volume reduction, to an activity limit of 50 pCi/mL (LVTS Design Criteria, VVNS DC 02',, parsgraph 2.2.1). VVNS vLlt work to the design criteria limit because of the l emergency nature of this action. Decontamination factor calculations and process centrol calculations designed to limit the activity concentration of waste sent to the CSS should not be applied to liquid that will be returned to the high-t level waste storage tanks. ATTACHMFNTS None REFERENCES None l s MS50678:3RM 1 Page 3 of 4 3

i TABLE 1 TR/IRTS 5 l .Rev. 6 l TABLES OF CESIUM CONCENTRATION FOR VARIOUS SALT FRACTIONS SALT FRACTION MAXIMUM ALLOWABLE CESIUM CONCENTRATION O.01 0.05 0.02 0.10 0.03 0.15 0.04 0.20 0.05 0.25 0.06 0.30 0.07 0.35 0.08 0.41 0.09 0.46 0.10 0.52 .0.11 0.57 0.12 0.63 0.13 0.69 0 '14 0.74 0.15 0.80 0.16 0.86 0.17 0.92 0.18 0.98 0.19 1.05 0.20 1.11 0.21 1.17 0.22 1.24 0.23 1.30 0.24-1.37 /~ 0.25 1.44 0.26 1.50 O.27 1 57 0.28 1.54 0.29 1.71 0.30 1.78 0.31 1.85 0.32 1.93 0.33 2.00 0.34 2,07 0.35 2.15 0.36 2.22 0.37 2.30 0.38 2.38 0.39 2.46 0.40 2.53 C, (1 + 0.829 f,) + f, , C 0.452 . Basis: DF Where: C - Cs 137 concentration (pCi/mL) DF - Cs Decontamination Factor f, - Salt Fraction (g salt /g solution) C, - BD 2 Supernatant Cs-137 concentration (2150 pCi/mL)

Reference:

Letter _ER Faillace to P-. J. Valenti, FB:89iOO74 " Transmittal of O Calculations to Estimate CS 137 Activity in LVTS Concentrates", dated 04/10/89 ' MSS 0678:3RM-1 Page 4 of 4

coe. Num:er TR/IRTS-8 Revision Mt::er 4 Pavis ten ca:e __08-27-91 Engineering Release #1430 Per ECN #2626 Per EQf #2841 Per E04 #3354 West a 'ey Demonstration PTO,9Ci CP ER A'l*::N AL ! A TE""! R E:'J:?.EYEN*t3 /b' PREPAP.E O 0. P.. S:affes Ca:a C g..1:an:, it.ganeer / APPRCVED 5, ( C..'. Ac c e r :4 Oats 5 IY cfsnt:an: unager R. A. Hus;:nrey Oat e [b.". .b APPRCVEDEY._f__O Aas;at;:n a(Safety Q r Cr unL::ee. Chair:an APPROVEDBYI) hvt D. L. Shugars Ca:a Eb $b Guaa;;7 assurancs APPRCVED BY MN# R. F. Cessner Oaca I [ L.',i irna sen* Frajeg APPP.6VE3 BY ).t..Kr.acensenun Date 6~/h /TT a A.actoicg;caa & Cavtecn:entai / Sde:7. Manager APPROVE 3 !Y ' b dl., l '4 6 R. E. L.s'-etace. Jr. CA:eib'.,!>3 Supernatant irtatsent Project Manager West Vcliey Nuclecr Services Co.. P.O. Ec x 191 West Valley, N.Y.14171-C191 MSS 0655:3fN-1 DDE Approved: CH:90:0214 O.'"' ECB Concurrence: 08-10-91 WV-lEls

i TR/IRTS 8 Rev. 4 i RECORD OF REVISloN 4 PROCEDURE 3 If there are changes to the procedure, the revision r. umber increases by one. j These changes are indicated in the left margin of the body by an arrow (>) at l the beginning of the paragraph that contains a change. e , Example: The arrow it.- the margin indicates a change. 4 Revision on Dated j Rev. No. Description of Changes Page(s). 0 Original Issue All 1 Dated 5/20/88 All 1 ' Engineering Release 1430 N/A 08/08 t -2 Per ECN =2626 All 09/88 2 3 Per.ECN #2841 All 03/89 s \\ 4 Per ECN #3354 Page 4 08/91 I .i 'I l i ) d~ t

i W-1807, Rev, 1 i

MSS 0655:3RM 1 1 i-f

TR/IRTS 8 Rev, 4 RECORD OF REVISION (CONTINW. TION SHEET) O Revisio(n)on Rev. No. Description of Changes Page s Dated f l O t t Li I-; 'k I i ?q i li [ t ti i l WV-1807, Rev. 1 11 4 MSS 0655:3RM 1 ? e i ('.m-u--. _.__,__-._-_.,_--.-.,--.-~.---..;

TR/IRTS 8 Rev. 4 O l l TYPE: 1 TITLE: Sattpling and Analysis l NUMBER: IRTS 8 OSR [ } l Requirements for Tanks 5 D 15 Al l l and A2 l Tech. Re gtnn ' t. [X]l l 1 l CPITiRIA: 1. Waste produced shall meet the qualifications of the Process control Plan. UNACCEPTABLE EVENTS: 1. Production of greater than Class C cement waste. O i i i Safety Limit l l Reporting Requirements: l DOE ID CONTROLLED LCO l l l LCS l l l Surveillance Reqmn't. l l l 1 I _l l i I Tech. Requirement I X l Critique IDOE WPO CONTROLLF.D I I I Operating Limit l l (WVNS CONTROLLED IMPLEMENTING PROCEDURES: SOP 00 13 SOP 71 10 SOP 71 11 WNS PCP-001 > SOP 71 2 > S0P 71-16 > SOP 70 45 > SOP 71-1 MSS 0655:3RM 1 O l

i TR/1RTS 8 Rev. 4 TECHNICAL REQUIREMENT SD-15A1 AND $D-15A2 SAMPLING AND ANALYSIS RulUIREMENTS, APPLICABI LITY i This technical requirement is applicable to the sampling and analysis of Tanks 5D 15A1 and SD-15A2 prior to transfer to CSS where it will be mixed with cement to generate a stabilized waste form. OEJECTIVE To control the concentration and composition of concentrates in Tanks SD 15A1 and SD 15A2 such that solidification of concentrates in CSS will meet approved recipe criteria and the final waste form will be in [ compliance with the Process control Plan. Additionally, a sample cercrete f cube made from the contents of SD 15A1 and/or SD 15A2 will be tested for compressive strength performance. s REQUIEMFXTS PRIOR TO TRANSFER TO C$S: 1. TOTAL DISSOLVED SOLIDS IN SD-15A1 AND SD-15A2 IS BETWEEN 37 AND + 41 WEIGHT PERCENT.- i 2. SAMPLE CONCRE1E CUBE MADE FROM CONTENTS OF SD-15A1 OR $D 15A2 WASTE STREAMS HAVE BEEN TESTED AND MEETS OR EXCEEDS THE 186 PSI COMPRESSIVE STRENGTH. 3. A SMiPLE OF WASTE IN SD 15A1 OR SD 15A2 SHALL BE TAKEN SO THAT I RADIONUCLIDE ANALYSES CAN BE PERFORMED TO VERIFY THAT IT MEETS THE 10 CFR 61 CRITERIA FOR CLASS "C" UASTE OR LOWER. THE TRANSFER AND PROCESSING CAN PROCEED VHILE THE ANALYSES ARE BEING PERFORMED. 5 i 1-MSS 0655:3RM 1 .n-..-

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TR/IRTS 8 Rev. 4 A SURVETIJANCE FOR EACH BATCH OF EVAPORATED CONCENTRATES IN SD 15A1 AND/OR SD 15A2, ANALYSIS VILL BE PERFORMED TO VERIFY TOTAL DISSOLVED SOLIDS IS BETWEEN 37 AND 41 VEIGHT PERCENT. SAMPLES VILL BE TAKEN TO VERIFY THAT THE FINAL VASTE FORM MEETS THE 10 CFR 61 CLASS "C" REQUIREMENTS. ONE PROCESS CUBE 2 x 2 x 2 PER 5,000 CALLONS (MINIMUM) OF WASTE WILL BE HANUFACTURED, CURED, AND TESTED FOR PENETRATION RESISTANCE VITHIN 24 TO 48 HOURS OF MANUFACTURE. t RASIS Recipe qualification in CSS has been established for a range of 37 to 41 weight percent of total dissolved solids in compliance with the CSS Process Control Plan. Also, the compressive strength performance of waste streams in $D 15A1 and SD 15A2 need to be verified prior to solidification. i t I The cure time is being changed from 48 hours to 24 to 48 hours. Test i _ 5 results on a 2 x 2 x 2 cube after 24 hours cure time show no change in penetration resistance values (both were >700 PSI) when compared to 48 hour cure specimens. The range will allow needed flexibility in scheduling process operations and laboratory personnel and sets an upper and lower limit for the total cure time. Radionuclide concentratione need to be determined for waste classification verification to Class "C" limits of 10CFR61 low level waste criteria. The [ required radionuclide analyses are confirmatory only and require 30 days 7 to complete; therefore, they cannot be used as an in process control analysis. Processing from 5D 15A1 and/or $D 15A2 may proceed in parallel with the confirmatory analyses. [ The change in the cube conpressive strength requirement from 60 psi to 186 psi is based on updated statistical evaluation of compressive test data documented in reference letter VD:89:0053 (FH:89:0006). m t MSS 0655:3RM 1 2-I s r--. ..,..-..,.r-, n.,.

TR/IRTS-8 Rev. 4 ATTACIMDfTS t NONE [ 1 REFERDICES f i i SOP 00 13 IRTS Integrated Run Plan SOP 71 11 LVTS Sampling Plan WNS PCP 001, CSS Process Control Plan and Run Plan i ,i 10 CFR 61.55 Tables 1 & 2 L i l O r i f f 1 9 I h l -v r i l MSS 0655:3RM 1 ; i . - -.. -,. - -, _., _ _ _..- -}}