ML20085K954
| ML20085K954 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project |
| Issue date: | 08/09/1991 |
| From: | Lindbergh B, Meess D, Prowse J WEST VALLEY NUCLEAR SERVICES CO., INC. |
| To: | |
| References | |
| REF-PROJ-M-32 HF:91:1257, OSR-IRTS-10, NUDOCS 9111010159 | |
| Download: ML20085K954 (16) | |
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Records Management Ext. 4433, !!S-52 g
HF:91:1257
'd October 23, 1991 l
Canttolled Distribution of Revisions to the Operational Safety Requirements / Technical Requirements, Volume VI Distribution ec:
Original, MS 50B Attached are tha following revisions to the Operational Sa ety Requirements / Technical Requirements, Volume VI, which has een assigned to you under controlled distribution:
o Latest Table of Contents o OSR-IRTS 10, Rev. 0
" Criticality Control During Processing of High Level Vaste through lon Exchange Columns Containing Ti-Treated Zeolite" Replace the current table ot contents in your manual with the attached; also, place OSR IRTS 10 Rev. O, in your manual accordingly.
Copies made from a con 6 ti scument are to be marked UNCONTR0il.ED before distribution.
To acknowledge receipt of this document sign, date, and return the e.ttached controlled distribution receipt acknowledgement to the undersigned by November 6, 1991.
For your convenience, a stan. pod (ori st;e recipients only) return address has been placed on the reverse side of the contcolled listribution receipt acknowledgement; please fold, staple, and place in the mail.
1 t.N-t B. E. LindbargET~ Records Procesadr Records Management West Valley Nuclear Services Co.,
Inc.
BEL I
Approved:
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C.M.Schifbuer, Supervisor
Attachment:
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9111010159 910309 FDR PROJ V
M-32 PLR
OPERATIONAL SAFL'I'Y REQUIRIXENTS/TECllNICAL RFQUIRFMENTS
.O VEST VALLEY LEMONSTRATION PROJECT V
WVDP Former VVDP, NF3 Iden_tifier Rev.
Titic/ Contents identifiers OSR/GP-1 2
WVDP Airborne Radioactivity M.11 5.2.4.
Release Limits VVDP 4.1 OSR CP 1 OSR/TR-CP 1 OSR-GP-2 1
Radioactivity Content of Liquid M.11.5,2.5.
Effluents Released from the WVDP WVDP 4.2 OSR-CP-2 OSR/TR CP 2 OSR/GP-3 4
Building and Vessel Venc11ation M.11.5.2.1.
Sjstems Operability NFS 5.3, STS 1.1, 1.2, CSS 4.1, 4.2, SRF 8.2, LVTS 5.1 M.11.5.2.7.
WVDP A.14 LWTS 5.2,
)
I NFS 6.5, STS 1.2, CSS 4.2 M.11.5.2.8.
TVS 3.0 M.11.5*.2.1 VF 2.2, 2.3 OSR GP-3 OSR/TR GP-3 OSR/CP 4 2
Effluent and Environmental M.11.5.2.1.B.X Monitoring (WVDP 5,1)
OSR GP-4 OSR/TR-CP-4 ELB0578:3RM DATED:
10-23-91 i
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WDP Foneer WDP, NFS g
Identiflor_
Rev.
Title / Contents Identiftern OSR/GP 5 3
WDP Emergency Power Requirements M.11.5.4.3.
NFS 6.4 M.11.5.2.1.D STS 1,3 M.11.5.2.1.G CSS 4.4 OSR GP 5 OSR/TR GP-5 i
TR/GP 6 2
Storage Requirements for M 11.5.2.1.J Low Level Vaste IAG 1, LAC 2 M.11,5.2.1.1 SRF 8.4 TR GP 6 1
OSR/TR GP 6 OSR/GP 7 2
Criticality Safety for Liquid M.11.5.2.2.
Transfer WDP 4.3 OSR GP 7 F.
OSR/TR GP-7 TR/GP-3 2
Water Activity Alarms M.11.5.4.1.
NFS 6.9 TR GP-8 OSP./TR CP-8 TR/GP-9 2
Control of Plant Equipment New i
Function and Configuration TR GP 9 OSR/TR-GP-9 6
OSR/GP-10 2
Airborne Effluent Monitoring M.11.5.4.4.
System Operability NFS 6.5 STS 1.1, 1.2 CSS 4.1 OSR GP-10 OSR/TR-GP 10 OSP./GP-11 3
Storage Canister Loading and M.11.5.1.2.B i
Spacing AFM 6.0 STS 1.4 CSS 4.3 1RTS 5.3 OSR GP ll OSR/TR CP-11 i
BLB0578:3RM 2-DATED:
10-23-91 1
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b WDP Fonner WDP, NFS Identi fier.
Rev.
Title / Contents identi fle rs L)
OSR/GP-17 2
Fissile Material Limits and M.11.5.1.1.B Requirements for Vaste Packages CPCRIT 9.1, 9.3, STS 1.4, TRU 9.1, 9.2, IAC 1 IAC-2 M.11.5.1.1.J RER 1.1 M.11.5.4.1.J RER 1.3 M.11.5.6.1.J RER 1.2 OSR GP 12 OSR/TR-CP 12 TR GP 13 1
Evacuation Alann 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 Responso Team Training TR CP-15 OSR/TR GP-15 TR/CP-16 2
Plant Fire Protection Systems New TR CP 16 OSR/TR-CP-16 l
OSR/GP-17 0
TN BRP and TN REG Shipping Cask New Lid Installation OSR/GP-18 0
Type B Shipping Cask License New Compliance Documentation l
l TR/GP-19 0
Area Radiation Detector New l
Requirements During Cask Fuel Loading l-l [
BLB0578:3RM 3-DATED:
10-23 91 l
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__Ident ifie r Rev.
Title / Contents Identifiers OSR/IRTS-1 3
Maintenance of Carbon Steel M.11.5.2.6.
High Level Waste Tank Integrity NFS 4.12 M.ll.5.4.2.
NFS 6.3 OSR IRTS 1 OSR/TR IRIS i TR/IRTS 2 3
Control of CSS Recipe for M.ll.5.2.2 G Decontaminated Supernatant CSS 4.3 TR IRTS-2 OSR/TR-IRTS-2 OSR/IRTS 3 3
Maintenance of Spare HLW M.11.5.2.3.
Storage Capacity NFS 5.4 OSR IRTS-3 OSR/TR-IRTS-3 TR/IRTS-4 4
Depressurization of STS for M.11.5.6.1.D Maintenance TR IRTS-4 OSR/TR IRTS-4 s
TR/IRTS-5 7
STS Process Limits M.11.5.1.1.D STS 1.4 TR IRTS-5 OSR/TR-IRTS-5 TR IRTS-6 2
LWTS Manifold Control - CANCELJEl)
New TR IRTS-6 OSR/TR-IRTS-6 TR-IRTS-7 5
Sampling and Analysis New Requirements for Tank SD-15B M.11.5.1.1.H LWTS 5.3 TR IRTS-7 OSR/TR-IRTS-7 TR/IRTS-8 4
Sampling and Analysis New Requirements for Tanks 5-D-15 TR IRTS-8 Al and A2.
OSR/TR IRTS-8 BLB0578:3RM DATED:
10-23-91 l
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Identifier,
,Rev.
Titic/ Contents Identifiers OSR-IRTS-10 0
Criticality Control During New ProcessinE of High Level Waste Through Ion Exchange Columns Containing Ti Treated Zeolite TR IRTS 11 0
Fissile Material Mass Balance New Across the Lk'TS Evaporator u
y O
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r West Valley Doc. Number OSR-IRTS-10 Demonstration Project Re.isiee Nueer o
Revision Date 10/11/91 Engineering Release #2203 TITLE:
CRITICALITY CONTFOL DURING PROCESSING OF UIGH LEVEL WASTE *1HROUGH ION EXCHANGE COLUMNS CONTAINING TI-TREATED ZEOLITE
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PE.vARED BY Vl*
J. J. Prowse Date t
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(cv[uizant;/ En'q eer APPROVED BY b/rf D.
C. Meess Dato Cogniaant System Tenign Manager APPROVED BY. /
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A. Humphrey Date
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Radiation & Safety ComEtiN;ee Chairman APPROVED BY AAM (LAO D.
L.
Shugara Date
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l~l Quality Assurfnce APPROVED BY P.
J. Valenti Date Fa'cilities Manager APPROVED BY
%d bWD D.
J.
Harward Date Radlajion& Eafety Department Manager West Valley Nuclear Services Co., Inc.
P.O. Box 191 O
RLW4241:R3 DOE Approved DW: 91:0909 West Valley, NY 14171-0191 Dated 10/11/91 VN-1816, Rev.1
OSR-IRTS-10 Rev. 0 RECORD OF REVISIOrt 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.
Exampigt
> The arrow in the margin indicates a change.
Revision on Rev. No.
Description of Chance; Paceis)
Dated O
Original Issue All 10/11/91 0
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9 WV-1807, Rev. 1 i
RLW4241.R3 i
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OSR-IRTS-10 Rev. O P&pORD OF REVISION fCONTINUATION SHEET)
Revision On-Rev. No.
Descriotion of Chances Pacefsi Dated
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W-1807, Rev. 1 11 RLW4241.R3
i OSR-IRTS-10 Rev. O O
OPERATIONAL SAFETY R1'QUIREEENT IRTS-10 TITLE: Criticality Control During Processing of High avel Waste Through Ion Exchange Colvmns containing Ti-Treated Zeolite GIT *RIA:
Prevent critic 61ty on an ion exchange column containing TL-treated zeolite UNACCEPTABLE EVENTS:
Inadvertent criticality REPORTING REQUIREMENTS:
For Operational Safety Requirement (OSR) violations, Wi'-9 8 7 " Initial Investigation, Oral Reporting, and Written Crit ique of Occurrences at WVNS" shall be followed.
Operational Safety Re;. trement OSR-IRTS-10 Page No.
Applicability.
2 Objective.
2 Definitions.
2 Safety Limit (SL) 2 Limiting conditior.s for Operation (LCOs) 2 Surveillance Requirements (SRs) 3 Basis.
4 Attachments 6
References 6
Table 1.
7 1MPIEEEATING PROCEDURES ACM-2701 ACM-Cross-1201 ACM-2703 Othere under development-to be approved prior to the Operational Readiness Review.
RLW4241.R3 1 of 7
OSR-IRTS-10 Rev. O OPERATIONLL SAFETY REQUIREMENT O)
I IIILI:
Criticality Control During Processing of High Level Waste Through Ion Exchange Columns containing Ti-Treated Zeolite APPLICABILITY This Operational Safety Requirement (CSR) applies to the processing of all liquid high-level waste (HLW) through ion exchange columns containing Ti-treated reolite in the Supernatant Treatment System (STS).
OBJECTIVE Limit the k,gg + 20 to less than 0.95 by lintting the mass of fissile Pu (Pu-239 plus Pu-241) that could accumulate on an STS ion exchange column containing Ti-treated zeolite to less than 1 kg during processing of liquid HLW.
DEPTNITIONS Alpha Plutonium - Pu-233 plus Pu-239 pluu Pu-240 plus Pu-242 Decontamination Factor - inlet concentration divided by the outlet concentration Fissile Plutonium - Pu-239 plus Pu-241 lbFETY LIMIT (SL)
I The maximum mass of fissile plutonium accumulated on an ion exchange column containing Ti-treated zeolite shall be 1 kg.
l LIMITING CONDITIONS FOR OPERATION (TqQgl 1.
No more than a calculated maximum of 750 g of fiscile plutonium or 250 Ci alpha plutonium, whichever le more restrictive, may be accumulated on an ion exchange column containing Ti-treated zeolite.
2.
At least two independent methods of determining the cumulative volume of HLW processed through the STS ion exchange columns shall be operational during liquid HLW 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 f-~
cannot be accomplished, a flush eequence shall be initiated, and further
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processing prohibited until two independent methods are operational.
RLW4241.R3 2 of 7
OSR-IRTS-10 '
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Rev. 0-SURVEILLANCE REOUIREMENTS (SRei 1.
(Reference LCO No. 1) Control accumulat!On of alpha Pu to less than or gaual to 250 C1.
I During processing for each ion exchange co)umn containing Ti-treated zeolite, 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 columcs inlet sample, and a column outlot 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 accumulated on the ion exchange column during that period.
The concentration ditference used for this calculation shall be the greater of that calculated for either the current samples or for the last samplos.
The total activity of alpha Pu accumulated on each ion exchange column containing Ti-treated 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 compliance with LCO No.1, 2.
(heference LCO No. 1) Control accumulation of fissile Pu (Pa-23? olus_Pu-2411 t o less than or caual to 750 c.
Prior to initiating processing of liquid HLW through an ion exchange column containing Ti-treated zeolite, a liquid HLW feed sample shall be h
taken (at a sampling point different from that in SR No. 1) and the Pu-239 plus 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 HLh which may be processed (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.
If the concentration increases to within a higher range (Column 1, Table 1) corresponding to a lower volume of HLW wnich may be processed (Column 2, Table 1), then the lower volume shall be considered to be the maximum allowable volume to be processed.
If this new limiting volume has already been exceeded, a flush sequence shall be initiated and further processing prohiLited until two independent methods are operational.
3.
(Reference LCO No. 1 and 2)
The volume processed through an ion exchange column containing Ti-treated zeolite 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.
O RLW4241.R3 3 of 7 l'
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OSR-IRTS-10 l
Rev. 0 4.
Quarterly, during HLW processing through io'.. exchange columns containing
[N Ti-treated zeolite, the activity ratio of Pu-238 to the sum of Pu-239 plus
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Pu-240 shall be determined.
5.
(Reference SL)
Following any column discharge and after resumption of HLW processing, if the Pu-239 plus Pu-240 feen concentration, as determined in SR No. 2 is greater than 0.1 pci/mL, the zeolite type (IE-96 or Ti-treated IE-96) in each of the columns in use shall be verified within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />.
Verification as to whether a column contains IE-96 or Ti-treated IE-96 shall be established by determining the plutonium decontamination factor (DF) across each column based on inlet and outlet concentrations of plutonium. A DF greater than two indicates Ti-treated IE-96.
If the zeolite type in a given column is different from that recorded in the operational records, the column in questior shril be discharged following a flush sequence.
BASIS This OSR implements the double contingency principle for processing of liquid f' g MLW through ion exchange columns containing Ti-treated zeolite, as required by
$,)
DOE Order 5480.5 **1 ID 5480.5A, " Safety of Nuclear Facilities."
s The SL was based on criticality assessment calculations using a modified one group and a combination of Monte Carlo neutron transport and discrete ordinates calculations for aqueous Pu-239 solutions (Yuan, 1990; Caldwell, 1990). These analyres are conservative for aqueous liquida since they constitute highly thermalized systems. There is no potential for criticality in an ion exchange column loaded with Ti-treated zeolite for accumulations of less than 1 kg (Pu-239 plus Pu-241).
1 LCO No. 1 allows 750 g (Pu-239 plus Pu-241) to be accumulated on an ion exchange column loaded with Ti-treated zeolite.
This value provides an adequate margin of safety such that exceeding the SL of 1 kg (Pu-239 plus 241) will be incredible. Additionally, it is recognized that the concentration determined for SR No. 2 could increase during the period of HLW processing, such that the new value falls into the next higher range.
If this occurs, the calculated Lc0 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 mcas f
isotopic ratios as reported in WVSP 89/011.
Using this information, the
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conversion factor of 9.6 g (Pu-239 + Pu-241) per C1 (Pu-239 + Pu-24Q) was s_s r
calculated (Prowse, 1991). The activity of Pu-239 plus Pu-240 is used based RLW4241.R3 4 of 7
OSR-IRTS-10 l
Rev. O I
upon characteristic alpha energies and the methods of analysos used in the laboratory for reporting Pu concentration.
Similarly, the conversion factor of 2.86 g (Pu-239 plus Pu-241) per Ci alpha Pu was calculated, where alpha Pu activity is the sum of the alpha activities of Pu-236, Pu-239, Pu-240, and Pu-242.
(Notes Pu-247 activity is negligible).
Thus, limiting the activity on an ton exchange column containing Ti-treated zoollte to less than 262 C1 alpha Pu (750+2.86) ensures that less than 750 grams of (Pu-239 plus Pu-241) are accumulated.
Allowing for small variationi in the mase isotopic ratios and additicnal conservatism, LCO No. I was choses to be 250 C1 alpha Pu.
Hence, provided new mass isotopic ration 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 provided no more than 250 Ci alpha Pu is accumulated per ton exchange column.
LCO No. 2 requires redundant volume measurement and thereby reduces the probability of an incorrect process volume determination.
SR No. 5 confirms the type of zeolite in each of the process columns to minimize the potential for discharging the incorrect ion exchange column and unintentionally exceeding the SL.
The concentration threshold of 0.1 pCi Pu-239 plus Pu-240/mL was choven because this would result in processing approximately 480 g of Pu-239 plue Pu-241 at the volume limit of 130,000 gallons of sludge wash solution.
Therefore, processing of one complete wash cycle from Tank BD-2, below the concentration threshold would not result in exceeding the SL.
O RLW4241.R3 5 of 7
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OSR-IRTS-10 Rev. O ATTACRMENTS O
Table 1 - Criteria for Determining the Maximum Allowable Volume of High Level Waste to be Processed Through Ion Exchange Columns containing Ti-Treated Zeolite REFERENCES F3:91:0129 " Criticality Safety Analysis for WVNS Sludge Tanks and Related Processing Equipment," J.
T. Caldwell, October 1990 FB:91:0012, " Criticality Evaluations Sludge Wash and Mobilization Slstem -
Eeolite Column," Y. Yuan, October 1990 FB 91:0060, " Criticality Control of an Ion Exchange Column Loaded with T1-coated Zeolite," 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, Commercial Nuclear Power Plants," October 1975 O
O RLW4241.R3 6 of 7
OSR-IRTS-10 Rev. 0 TABLE 1 Criteria for Determining the Maximum Allowable Volume of High Level Waste to be Processed Through Ion Exchuge Columns Containing Ti-Treated Zeolite Column 1 Column 2
+b Concentration of Corresponding Maximum Pu-239 plus Pu-240 Allowable Volume (pCi/mL) of HLW to be Processed creater But (Gallons) than or leen 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 4
0.300 0.350...................
50,000 0.350 0.400 45,000 0.400 0.450...................
40,000 0.450 May not be processed O
RLW4241.R3 7 of 7