ML20079B124
| ML20079B124 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 01/31/1990 |
| From: | WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | |
| Shared Package | |
| ML20079B114 | List: |
| References | |
| REF-PROJ-M-32 OSR-GP-7, NUDOCS 9106130321 | |
| Download: ML20079B124 (8) | |
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OSR/CP.7 Aev. 2 RECORD OF REVISION I
PROCEDURE If there are changes to the procedure, the revision nun.ber increases by one.
These changes are indicated in the left rnargin of the body by an arrow (>) at the beginning of the paragraph that contains a change.
Exarnph:
> The arrow in the margin indicates a change. ** *
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Revision On Page(s) D"t'd Rev. No. Description of Changes 0 Original Issue All 1 Dated 5/20/88 All 1 Engineering Release 1430 N/A 8/88 2 For ECN 3353 Page 4 1/90 W 1807, Rev. 1 i LLK0130:3RM 1 e,,1061 1:0 3 2 3 91061('.'
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OSR/GP 7 Rev. 2 RECORD OF REVISION (CONTI! NATION SHEET)
Revision on Rev. No. Description of Changes Page(s) i l
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IN-1807, Rev, 1 11 LLK0130:3RM-1 l.
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b', M.: . OSR/GP 7
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I I TYPE: l TITLE: Criticality Safety for Liqui! l NUMBER: CENPLNT OSR [X] l Transfers l 7 I I Tech. Reqmn't. [ ]l l l _
l CRITERIA: 1. P avent Criticality UNACCEPTABLE EVENTS: 1. Inadvertent criticality.
I- 1 I Safety Limic l X l Reporting Requirements: [ DOE ID CONTROLLED 1 LCO l X l UOR l I
LCS l l l Surveillance Reqmn't. l X l l 1 l l
' l l 1 Tech. Requirement l 1 l DOE WPO CONTROLLED I i i Operatink Limit l l lWNS CONTROLLED l
> IMPLEMENTING PROCEDURES:
l' l EP 007 l EP 008 EP 011 SUP 7 8 SOP 71-1 S0P 71 2 SOP 71 6 SOP 71-16 LLK0130:3RM-1 l
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T OSR/GP 7 Rev. 2 OPERATIONAL SAFL'? 4.WQUIREMENTS
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CRITICALITY SAFETY FT)R LIQUID TRANSFERS T 2 l 4% ,f,*/"'yN
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APPLICABILITY This requirement applies to all liquid transfers of fissile material st the VVD?
except for tran.afera of decontaminated supernatant within the IRTS system.
01UECTIVR 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.
i SPECIFICATIONS SAFETY LIMIT NO LIQUID TRANSFERS SHALL BE MADE THAT WILL RESULT IN EXCEEDING A k,gf 0F CREATER THAN 0.95.
I LIMITING CONDITIONS FOR OPERATIONS
- 1. FOR UNRESTRICTED AND UNLIMITED LIQUID BATCH TRANSFERS, FISSILE MATERIAL COPCENTRATION SHALL NOT EXCEED THE VALUES LISTED IN TABLE 1,
- 2. SAMPLING AND ANALYSIS IS THE PREFERRED METHOD TO VERIFY FISSILE CONCENTPATION.
HOWEVER, VERIFICATION .%Y BE BY USE Or' PREVIOUS DOCUMENTATION WHICH IS TRACEABLE TO SAMPLE ANALYSIS. IF THE FISSILE MATERIAL CONCENTRATION OF A TA1R IS VERIFIED BY MEANS OTHER THAN DIRECT SAMPLING AND THE TANK IS PART OF A ShIEM 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 SAFE' 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 TF.AT SAMPLES DRAWN ARE REPRESENTATIVE OF THE ENTIRE VESSEL CONTENTS.
LLK0130:3RM 1 Page 1 of 5
OSR/CP 7 Rev. 2 SURVEILLANCE REQUIREMENT:
FISSILE CONCENTRATION SHALL BE VERIFIED BEFORE EACll TRANSFER AND SilALL INCLUDE, AS HINIMUM, DETERMINATION OF Tile FISSILE MATERIAL CONCENTRATIONS OF BOTil Tile "SENDINC" AND "RECEIVINt l'ANKS WHICil COULD POTENTIALLY CONTAIN FISSILE MATERIAL, FOR UNINTERRUPTED BATCH TRANSFERS OR OTHER ROUTINE TRANSFERS VllERE THE FISSILE CONCENTRATION IN EACH INTERMEDIATE AND RECEIVING TANK HAS BEEN PREVIOUSLY VERIFIED TO MEET TABLE 1 REQUIREMENTS, ONLY TiiE SENDING TANK MUST BE SAMPLED AS A CONDITION FOR FUTURE TRANSFERS. IN ADDITION, THF SYSTEM MUST BE ANALYZED TO ENSURE TilAT PROCESSING WILL NOT PRECIPITATE FISSILE MATERIAL OUT OF SOLUTION.
RECOVERY:
IF SAMPLE ANALYSIS RESULTS OR OTilER DOCUMENTATION SHOV FISSILE MATERIAL CONCENTRATIONS TilAT EQUAL OR EXCEED THOSE SPECIFIED IN TABLE 1. THE TRANSFER SHALL NOT PROCEED.
IMSIS A modified one group (thermal neutron system approximation with correction for
- slowing down, Fermi Age Theory) was used in the calculatim for conservative resulta. The critical solution concentration of Pu-239 was determined as a funct lo of U 235 concentration. This eliminates the need for determining t!a U 235 concentration as a function of urani'.un 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
- er to 4.0 g/L, U-235.
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OSR/GP 7 Rev. 2 This analysis is conservative for aqueous liquids since they constitute highly thermalized systems. The geometry of all available vessels and sumps in the plant (including those planned for STS, LWTS, and CSS) was analyred, and the most limitin safe concentration values were determined. These are liste " . . Tab'e 1. Analysis of potential criticality in the SAR for STS fndicates no identified concentrating factors exist and thus no potential for criticality from liquid transfers within ST or between STS and LWTS exists. No potential for criticality within Tank 8D 2. No potential for criticality as a result of tank to tank transfers within IRTS. No potential for criticality in STS as a result of concentration in Prefilter or IX columns (reference mcmo K. O' Ahoofe) . No potential for criticality wichtn LWTS a a result of concentration in evaporator (reference SAR Voluma IV, Part No potential for concentration identified for CSS (reference SAR V Volum Part G). All sumps, drains, collection points were analyted.
ATTACHMuiTS Table 1 Criteria for Determining the Allcwable Fissile Solution Concentrationt lo Plant Solution Transfers - Taken from Table 5.3 of FB:85:0150.
P
- REFERENCES i
FB:85:0072 " CSS Criticality Safety Evaluation" K. A. O'Ahoofe momo to J. C. Cwynar, dated March 26, 1985.
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FB:85:0150 " Allowable Fissile Material Solution Concentration for Liquid Transfers, Revision 1, dated July 2,1985.
WVDP SAR, Vol. IV, Part H, Liquid Waste Treatm.ent System WVDP SAR, Vol. III, Part D, Supernatant 'i entment System WVDP SAR, Vol. IV, Part G, Cement Solidification System 1
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OSR/GP 7 Rev. 2 OTIIER APPI.ICABII OSRS OSR GP-12 Fissile Material Limits and Requirements for Ladioactive Waste Packages .
OSR GP 11 Storage Canister Loading and Spacing l
LLK0130:3RM-1 Page 4 of 5
OSR/GP 1 Rev. 2 TABLE 1 CRITERIA FOR DETERMINING THE AL14'JABLE FISSILE SOLUTION CONCENTRATIONS FOR PLANT SOLUTION TRANSFERS ('-)
Column 1 Column 2 Concentration of Uranium Corresponding Maximum Plutonima (U.233 + U 235) Concentration (Pu 239 + Pu 241) grams / litre grams / litre Greater But Less Than Than Greater than 1.85(2) f 0, 0.049 1.85 0.05 0.499 1.63 i 0.5 0.99 1,39 1.0 1.99 U.90 l 2.0 2.49 0.68 2.5 2.99 0,44 3.0 0.19 Greater Than 3.4{2) 3.5 (1) Column 1 is the total concentration of fissile uranium and Column 2 is the corresponding allowable total fissile plutonium concentration. For a sample containinh a combined U 235 plus U.233 concentration in the range shown in Coltunn 1, the ccrresponding value in Column 2 is the limiting and allowable combined Pu-239 plus Pu-241 concentration for safe processing.
(2) Not authorized for processing. Special written authorization of the Radiatic n and Safety Committee is required.
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