ML20079B128
| ML20079B128 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 03/14/1991 |
| From: | WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | |
| Shared Package | |
| ML20079B114 | List: |
| References | |
| REF-PROJ-M-32 OSR-IRTS-10-DRF, NUDOCS 9106130328 | |
| Download: ML20079B128 (9) | |
Text
._ -- - . . . .
West Valley Dec. Nurter OSR-!RTS-10 Demonstration Pro.'ect neunion N .r o Revision Date TITLE: CRITICA. .T CCNTROL DURING PROCESSING OF HIGH LEVEL WASTE THROUGH ION EXCHANGE COLOMNS CONTAININC TI-COATED IEOLITE PREPARED BY - /M-- -
J. J. Prowse Date I /
1: n ineer APPROVED BY W D. C. Meesu Date 3-Id-9I Cogniza system Design Manager APPROVED . .R. A. Humphrey Date / k/
Radiation E. Safety mmittee Chai .
APPROVED BY - F AAd D. L. Shugars Date Quality Assurpace r
\ / l APPROVED BY 'bM P. J. Valenti Date Facilities Manager [/
APPROVED BY D \_ k N1. M N D. J. Harward Date Radi(Eqon & Safety Department q*e West Valley Nuclear Services Co.,Inc.
P.O. Box 191 RLW4241:3RM West Valley, NY 14171-0191 WV-1816, Rev.1 J
9106130328 910610 PDR PROJ M-32 PDR
OSR-IRTS-10 Rov. O RECOP.D OF MEVTSICN P#CCID URE If there are changes to the procedu ', the revision number increases by one.
These changes are indicated in the lef t margin of the body by an arrow (>) at the beginning of the paragraph that contains a chcnge.
Exteele
> The arrow in the margin indicates a change.
Revision On Rev. No. Descrintion of Chances Pacefs) Dated 0 original Issus All
\
1 I
l l
WV-1807, Rev. 1 i RLW4241:3RM I
__. _ _ _ _ _ . _ . . _ _ _ _ . . -._. . ._..__.___._.._m..-__.-_ _ _ . _ _ _ . . . . _ _ _ . _ . . . _ . . _ . .
CSR-IR*S-10 Rev. O RECORD OLtg/ISION fCCN"INUATION SFEE?i F.4vitLon On tt av . No. Dese-intien of Chances , Puinfsi Dated I
W-1807, Rev. 1 11 RLW4241:3RM I. ,
- - _ ~ _ . _ _ . - - _
t TYPE: OSR TITLE: Criticality control During NWiBER: 05R-IRT3-lO Processing of High Lavel Waste OSR (%) Through Ion Exchange Columns Centaining Ti-Coated Zeolite Tech. Reqmn't. ( )
CRITERIA: Prevent criticality on an ion exchange column containing Ti-coated neolite.
UNACCEPTABLE EVENTS: Inadvertent criticality.
Safety Limit X Reporting Requirements: DOE-ID CCNTRCLLED LCO I UCR LCS Surveillance Reqmn't. I "echnleal Recuirement DCE-WVPO CCNTPOLLED Ceeratine Limit WOTS CCNTDCLLED e
IXPLZMINTING PRCCEDURES:
Aca-2701 ACM-Cross-1:Ol ACM-2703 Others under development-to be approved prior to CRR.
l l
l l
I RLW4241.3RM
. , . _ - . ._. ___ m - _ . . _ . . _ . . _ _ . _ _ _ _ _ - _ _ _ _ . _ ___ - ._ _ ... _.._ -.._._ m ___ __
l CSR-IRTS-10 Rev. O, Draft l
CPERATIONAL SAFETY REQUIREMENT Criticality Centrol Durino Processine of Hich Level Waste Threuch ten Exchance 4 Columns Centainino Ti-Cented !eolite APPLICABILITY This CSR applies to the processing of all liquid high-level waste (EW) !
through ion exchange columns containing Ti-coated zoollte in the STS.
QBJECTIVE Limit.the keff + 2a to less than 0.95 by limiting the mass of fissile Pu (Pu-239 plus Pu-241) that could accumulate on an STS ion exchange column containing Ti-coated zeolite to less than 1 kg during processing of liquid
. HIA.
i SAFETY LIMIT f SL_i_
- l. A maxirum of 1 kg (Pu-239 plus Pu-241) . accumulated on an ion exchange column containing T1-coated zeolite.
LIMT?ING CONDITIONS FOR OPERATION f !.CO )
- 1. ' No more than a calculated maximum of 750 g (Pu-239 plus Pu-241) er 250 ci alpha Pu, whichever is more restrictue, may be accumulated on an ion exchange column containing Ti-coated zeolite.
- 2. At least two independent methods of determining the t umulative volume of EW processed through the STS len exchange columns shall be operational during liquid EW processing. If failures occur during processing, such that only one method of process volume measurement is available, an additional method shall be placed in service within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. If this cannot be accomplished, a flush sequence shall be initiated.
t i
RLW4241:3RM 1 of 5
CSR- RTS-10 Rev. O, Draft S"RVETLI.MCE 9E00TREMENTS f $ 3J,
- 1. (Reference LCO No. 1) Method No. 1 to control accumulation of alpha Pu to less than or equal to 250 C1.
During processing for each ion exchange column containing Ti-coated zoolite, at least once every 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> a column inlet sample, and a column outlet sample shall be taken. The alpha Pu concentration of these samples shall be determined. The product of the difference in the inlet and outlet concentrations and the volume processed since the last samples were drawn shall be recorded as the activity of alpha Pu that has &ccumulated on the ion exchange column during that period. The concentration diff erence used for this calculation shall be the greater of that calculated for either the current samples or for the last samples. The total activity of alpha Pu accumulated on each Lon exchange column containing Ti-coated zeolite shall be documented at least once every 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> to ensure coopliance with LCO No.l.
- 2. (Reference LCO No. 1) Method No. 2 to control accumulation of fissile Pu
( (Pu-239 plus Pu-241) to less than or equal to 750 g.
Prior to initiating processing of liquid EW through an ion exchange column containing Ti-coated zoolite, a liquid EW feed sample shall be taken (at a sampling point different from that in SR No. 1) and the Pu-239 plut Pu-240 concentration shall be determined. This concentration value shall be used to determine the appropriate range (Column 1, Table 1) and the corresponding maximum allowable volume of EW which may be prccessed (Column 2, Table 1). Additional samples shall be taken every 7 to 10 days during processing. This ensures that the concentration has remained within the range established by the initial sample. ?! the concentration increases to within a higher range (Column 1, Table 1) corresponding to a lower volume of EW which may be processed (Column 2, Tsble 1), then the lower volume shall be considered to be the maximum allowable volu=e to be processed. If this new limiting volume has already been exceeded, a flush saquence shall be initiated.
RLW4241:3RM 2 of 5 '
i l
l
. -_. . _ . _ _ _ _ _ _ _ . _ _ _ - _ . _ . - _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ ~ . . . _ _
OSR-IRTS-10 Rev. O, Draft
- 3. (Reference LCO No. 1 and 2)
The volume processed through an ion exchange column containing Ti-coated zoollte shall be determined at least once every 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> and verified by a second independent measurement.
- 4. Quarterly, during KLW processing through ion exchange columns containing Ti-coated zeolite, the activity ratio of Pu-238 to the sum of Pu-239 plus Pu-240 shall be determined.
HASIS This CSR implements the double contingency principle for processing of liquid ELW through ion exchange columns containing Ti-coated zeolite, as required by
- DOE Order 5480.5 and IU 5480.5A, . " Safety of Nuclear Facilities."
The SI was based on criticality assessment calculations using a modified ona group and a combination of Monte Carlo neutron transport and discrete ordinates calculations for aqueous Pu-239 solutions (Yuan,1990; caldwell, 1990). These analyses are conservative for aqueous liquids since they constitute highly thermalized systems. There is no potential for criticality in an ion exchange column loaded with Ti-coatec zeolite for accumulations of less than 1 kg (Pu-239 plus Pu-241) .
LCO'No. 1 allows 750 g (Pu-239 plus Pu-241) to be accumulated on an ion cxchange column loaded with Ti-coated zeolite. This value provides an edequate margin of safety such that exceeding the SL of 1 kg (Pu-239 plus 241) will be incredible. Additionally, it is recognired that the concentration determined for SR No. 2 could increase during the period of ELW processing, such that the new value falls into the next higher range. If this occurs, the calculated LCO of 750 g (Pu-239 plus Pu-241) will not be violated as long as the processed volume has not exceeded the original maximum allowable volume.
SR No. 2, which ensures that LCO No.1 is adhered to, is based upon Pu mass
( . isotopic ratios as reported in WVSP 89/011. Usi.tg this information, the conversion f actor of 9.6 g (Pu-239 + Pu-241) per CL (Pu-239 + Pu-24Q) was calculated (Prowse, 1992). The activity of Pu-239 plus Pu-240 is used based l
1 upon characteristic alpha energies and the methods of analyses used in the laboratory for reporting Pu concentration.
Similarly, the conversion factor of 2.86 g (Pu-239 plus Pu-241) per Ci alpna Pu was calculated, where alpha Pu activity is the sum of the alpha activities l cf Pu-238, Pu-239, Pu-240, and Pu-242. (Note Pu-242 activity is negligible) .
l RLW4241: 3 RM 3 of 5 l
- , - , , _ _ . _ , , - - , - - - - _ . _ , .r--- , -
OSR-IRTS-10 Rov. O, Draft Thus, limiting the activity on an ion exchange column containing Ti-coated zeolite to less than 262 Ci alpha Pu (750+2.86) ensures that less than 730 grams of (Pu-239 plus Pu-241) are aceumulated. Allowing for small variations in the mass isotopic ratios and additional conservatism, Lco No. I w s chosen to be 250 Ci alpha Pu. Hence, provided new mass isotopic ratios do not increase the conversion factor of 2.86 to greater than 3.0 (assured by SR No. 4), the amount of Pu-239 plus Pu-241 will not exceed 750 grams provided no more than 250 Ci alpha Pu is accumulated per ion exchange column.
LCO No. 2 requires redundant volume measurement and thereby reduces the probability of an incorrect process volume determination.
ATTACHMENTS Table 1 - Criteria for Determining the Maximum Allowable Volume of High Level Waste to be Processed through Ion Exchange Columns containing Ti-Coated Zeolite REFERENCTS
" Criticality Safety Analysis for WVNS Sludge Tanks and Related Processing E7uipment
- J. T. Caldwell, Octcber 1990 FB:91:0012, " criticality Evaluation: Sludge Wash and Mobilization System -
Zeolite Column," Y. Yuan, cctabe- 1990 FB:91:0060, " Criticality ' Control of an Ion Exchange Column Loaded with T1-coated ealite," J. J. Prowse memo to D. J. Fauth, March 1991.
WVSP 89/011, " Receipt, Analysis and Blending of Actual West Valley Vitrification Feed Components," L. A. Bray, Pacific Northwest Laboratory, October 1988 NUREG/75/014, " Reactor Safety Study - An Assessment of Accident Risks in U. S. Commarcial Nuclear Power Plants," October 1975 RLW4241:3RM 4 of 5
CSR-IRTs-10 Rev. O, Draft TABLZ 1 Criteria for Determining the Maximum Allowable Volume of High Lavol Waste to be Processed Through Ion Exchange Columna Containing Ti-Coated Zeolite Column 1 Column 2 Concentration of Correspo: ting Maximum Pu-239 plus Pu-240 Allowable Voluee (yC1/rk) of HLW to be Processed Greater But (Gallons) than or less equal to than 0.000 0.005 ................... 1,000,000 0.005 0.020 400,000 0.020 0.050 ................... 200,000 0.050 0.100 130,000 0.100 0.150 ................... 100,000 0.150 0.200 80,000 0.200 0.250 ................... 65,000 0.250 0.300 55,000 0.J00 0.350 ................... 50,000 0.350 0.400 45,000 0.400 0.450 ................... 40,000 0.450 May not be processed I
I RLW4241:3RM 5 of 5 i
_ - _ _ _ _