ML023470300
| ML023470300 | |
| Person / Time | |
|---|---|
| Site: | West Valley Demonstration Project, P00M-032 |
| Issue date: | 12/06/2002 |
| From: | Horton D US Dept of Energy, West Valley Demonstration Project |
| To: | Glenn C NRC/NMSS/DWM/HLWB |
| References | |
| +KBR1SISP20050613 | |
| Download: ML023470300 (11) | |
Text
RECORDS MANAGEMENT DEPARTMENT TO: C. GLENN --- NRC HEADQUARTERS DATE: 12/06/2002 FROM: D.L. HORTON AOC-21 TEL: 716 942-4300 PACE: I TRANSMITTAL HUM: 000018853 CONTROLLED COPY TRANSMITTAL / RECEIPT ACKNOWLEDGEMENT Attached is a CONTROLLED COPY of the following document(s) and its applicable index. Add or replace your existing copy with the attached.
CONTROLLED ISSUE COPY* PROC ID REV* FC* DATE PROCEDURE TITLE 006 PSR-l 2 12/06/2002 REQUIREMENTS FOR LIQUID TRANSFERS OF FISSILE MATERIAL Copies made from a controlled document MUST be marked UNCONTROLLED before distribution. Signature below signifies all previous revisions, if applicable, have bean destroyed or marked superseded.
I have complied with the above Instructions:
RETURN BY: 12/20/2002 Signature (BLACK INDELIBLE INK ONLY) Date FOR YOUR CONVENIENCE, A SELF-ADDRESSED, STAMPED ENVELOPE HAS BEEN INCLUDED.
sKi
DATE: 12/06/2002 PROCESS SAFETY REQUIREMENTS PAGE: I1 TIME: 08:57 WVDP-218 INDEX ISSUE PeOC In BE Fa PROCEDURE TITLE STATUS. hDATE COGNIZANT MANAGER WVDP-218 11 !PREFACE FOR PROCESS SAFETY REQUIREMENTS ACTIVE 06/12/2002 CHILSON,L.J.
PSR-2 2 MAIN PLANT STACK AIRBORNE EFFLUENT ACTIVE 09/12/2000 POTTS,W.J.
"SAMPLING SYSTEM REQUIREMENTS ACTIVE 12106/2002 POTTS.W.J.
PSR-I 2 REQUIREMENTS FOR LIQUID TRANSFERS OF
- FISSILE MATERIAL -T I BUILDING AND VESSEL VENTILATION SYSTEM ACTIVE 01/03/2001 POTTS,W.J.
PSR-3 2 I REQUIREMENTS 1 -, ,
BUILDING AND VESSEL VENTILATION SYSTEM ACTIVE 06129/2001 POTTS,W.J.
PSR-3 2 1
"-REQUIREMENTS C 3 SPENT FUEL CASK STAGING AND HANDLING ACTIVE 05/30/2002 POTTS,W.J.
PSR-4 REQUIREMENTS PSR-4 3 1 SPENT FUEL CASK STAGING AND HANDLING "ACTIVE 12/02/2002 POTTS,W.J.
REQUIREMENTS PSR-5 2 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 11/05/1999 POTTS,W.J.
ACTIVE 11/23/1999 POTTS.W.J.
PSR-5 2 1 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 02/17/2000 POTTSW.J.
PSR-5 2 2 STANDBY AND BACKUP POWER REQUIREMENTS PSR-5 2 3 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 06/29/2001 POTTS.W.J.
PSR-6 2 FISSILE MATERIAL PACKAGING AND STORAGE ACTIVE 06/12/2002 KOMASARA ,S .M.
REQUIREMENTS PSR-7 2 EMERGENCY PAGING SYSTEM AND SHELTERING ACTIVE 10/131/2000 POTTS.W.J.
ALARM REQUIREMENTS ACTIVE 07/20/2001 POTTSW.J.
PSR-B 3 FIRE PROTECTION SYSTEMS REQUIREMENTS PSR-10 3 HIGH-LEVEL WASTE TANK LEAK DETECTION ACTIVE 02/12/2001 MEESS,D,C.
AND RECOVERY REQUIREMENTS ACTIVE 03/15/1996 MEESS,D,C.
PSR-11 1 HIGH-LEVEL WASTE TANK SPARE CAPACITY REQUIREMENTS PSR-11 1 1 HIGH-LEVEL WASTE TANK SPARE CAPACITY ACTIVE 03/26/1997 MEESS,DC.
REQUIREMENTS PSR -12 3 VITRIFICATION FACILITY VENTILATION AND ACTIVE 02/21/1997 POTTS.W.J.
OFF-GAS SYSTEMS REQUIREMENTS PSR-12 3 1 VITRIFICATION FACILITY VENTILATION AND ACTIVE 11/03/1998 POTTS,W.J.
OFF-GAS SYSTEMS REQUIREMENTS PSR -12 3 2 VITRIFICATION FACILITY VENTILATION AND ACTIVE 03/03/1999 POTTS,W.J.
OFF-GAS SYSTEMS REQUIREMENTS PSR-12 3 3 VITRIFICATION FACILITY VENTILATION AND ACTIVE 05/20/1999 POTTS,W.J.
OFF-GAS SYSTEMS REQUIREMENTS PSR-13 2 VITRIFICATION FACILITY STANDBY POWER ACTIVE 03/28/1996 POTTSW.J.
REQUIREMENTS PSR-13 2 1 VITRIFICATION FACILITY STANDBY POWER ACTIVE 05/24/1996 POTTS,W.J.
REQUIREMENTS PSR-13 2 2 VITRIFICATION FACILITY STANDBY POWER ACTIVE 07/11/1996 POTTS,W.J.
REQUIREMENTS PSR-15 3 NOX MONITORING INSTRUMENTATION ACTIVE 09/30/1998 POTTS,W.J.
REQUIREMENTS PSR-15 3 1 NOX MONITORING INSTRUMENTATION ACTIVE 11/23/1999 POTTS,W.J.
REQUIREMENTS ACTIVE 11/12/1998 POTTS,W.J.
PSR-16 6 ANHYDROUS AMMONIA MONITORING INSTRUMENTATION AND STORAGE REQUIREMENTS PSR-16 5 1 ANHYDROUS AMMONIA MONITORING ACTIVE 06/27/2000 POTTSW.J.
INSTRUMENTATION AND STORAGE REQUIREMENTS
DATE: 12/06/2002 PROCESS SAFETY REQUIREMENTS PAGEt 2 TIME: 08:57 WYDP-218 INDEX K
ISSUE PRoCin REVM M PROCEDURF TITLF DATE SATIUS COGNIZANT MANAGER PSR-17 4 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 09/24/1999 CURCIO,J.P.
OPERATION PSR-17 4 1 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 05/11/200D CURCIOJ.P.
OPERATION PSR-17 4 2 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 10/13/2000 CURCIOJ.P.
OPERATION PSR-17 4 3 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 10/26/2000 CURCIO,J.P.
OPERATION PSR-18 0 COLLECTION, PROCESSING, AND STORAGE ACTIVE 0611212002 COVERT,B.C.
REQUIREMENTS FOR FISSILE-BEARING DEBRIS PSR-18 0 1 COLLECTION, PROCESSING, AND STORAGE ACTIVE 11/14/2002 COVERT,H .C.
REQUIREMENTS FOR FISSILE-BEARING DEBRIS
Doc. ID Number PSR-1 West Valley I Revision Number 2 Demonstration Project dr Revision Date 12/06/2002 dr PROCESS SAFETY REQUIREMENTS REQUIREMENTS FOR LIQUID TRANSFERS OF FISSILE MATERIAL APPROVED BY: IX4ýýI aý5ý drl Cogniz 't Manager Date I_______
APPROVED BY: Date IIta .14r)1 APPROVED BY: Date /A2---Z WVNSCO W*cst Valley Nuclear Services Company 10282 Rock Springs Road West Valley, New York USA 14171-9799 I WV-1816, Rev. 5
PSR-1 Rev. 2 Page 2 of 7 PROCESS SAFETY REQUIREMENT - 1 TITLE: Requirements for Liquid Transfers of Fissile Material CRITERIA: Prevention of inadvertent criticality due to liquid transfers.
(PSR Criterion 3.a.)
UNACCEPTABLE EVENTS: Combination of process streams resulting in an inadvertent criticality.
Process Safety Requirement - 1 Page No.
APPLICABILITY ................................ ................................... 2 OBJECTIVE .................................. ..................................... 2 SPECIFICATIONS ............................... .................................. 2 I BASES .................................... ....................................... 3 ATTACHMENT ................................. .................................... 4 REFERENCES ................................. .................................... 4 TABLE 1 - Criteria for Determining the Allowable FISSILE URANIUM and FISSILE PLUTONIUM Concentrations for Liquid Transfers ......... ............ 6
PSR-I Rev. 2 Page 3 of 7 PROCESS SAFETY REQUIREMENT REQUIREMENTS FOR LIQUID TRANSFERS OF FISSILE MATERIALS APPLICABILITY This Process Safety Requirement (PSR) applies to tank-to-tank transfers of liquids containing greaterthan 1 gram total uranium or 0.06 Ci (Pu-239 + Pu-240).
This PSR does not apply to transfers of liquids between tanks 7D-2 and 3D-2 for the purpose of sampling tank 7D-2. This PSR does not apply to transfers of liquids within or between any of the following tanks or components within the Integrated Radwaste Treatment System (IRTS): 8D-1, 8D-2, 50D7001, STS Ion Exchange Columns, 8D-3, 5D-15B, 31017 (LWTS evaporator), 5D-15A1, 5D-15A2, .the Distillate Surge Tank (71-D-005), and the Waste Dispensing Vessel (70-D-001). This PSR does not apply to transfers of liquids within or between any of the following tanks or components within the Waste Tank Farm and Vitrification Facility (VF): 8D-1, 8D-2, 8D-3, 8D-4, Concentrator Feed Makeup Tank, Melter Feed Hold Tank, Slurry Fed Ceramic Melter, Submerged Bed Scrubber, Neutralizing Tank, and the Decontamination Tank.
OBJECTIVE The objective of this PSR is to ensure that all liquid transfers of FISSILE URANIUM and FISSILE PLUTONIUM are conducted in a manner such that a subcritical-condition exists at all times.
SPECIFICATIONS .
- 1. LIMITING CONDITION FOR OPERATION The FISSILE URANIUM and FISSILE PLUTONIUM concentrations in liquids in both_
the "sending tank" and "receiving tank" involved in a liquid transfer shall -be in compliance with the limits listed in Table 1.
ACTION If-sample analysis or documented process knowledge indicates that the FISSILE URANIUM and-FISSILE PLUTONIUM concentrations of either the sending tank or receiving tank are not in compliance with the limits specified inTable 1, the transfer shall not proceed, the tank(s) shall be left in its as discovered, state, and the Radiation and Safety Committee Chairman shall be notified.
PSR-l Rev. 2 Page 4 of 7 Disposition of the tank contents shall be in accordance with a written plan that is approved by the Radiation and Safety Committee.
SURVEILLANCE REQUIREMENT Before initiating tank-to-tank transfers of liquids containing FISSILE URANIUM and FISSILE PLUTONIUM, the FISSILE URANIUM and FISSILE PLUTONIUM concentrations in both the sending tank and the receiving tank shall be determined in accordance with the requirements of an approved IMPLEMENTING PROCEDURE.
- 2. LIMITING CONDITION FOR OPERATION FISSILE URANIUM and FISSILE PLUTONIUM in solution shall not be precipitated.
ACTION If it is determined that conditions exist such that the precipitation of FISSILE URANIUM and FISSILE PLUTONIUM is possible, the transfer shall not proceed and the Radiation and Safety Committee Chairman shall be notified.
Disposition of the tank contents shall be in accordance with a written plan that is approved by the Radiation and Safety Committee.
SURVEILLANCE REQUIREMENT Before initiating tank-to-tank transfers of liquids containing FISSILE URANIUM and FISSILE PLUTONIUM and before neutralization of solutions containing FISSILE URANIUM and FISSILE PLUTONIUM, analyses shall be performed to ensure that FISSILE URANIUM and FISSILE PLUTONIUM will not precipitate.
BASES I Basis of Applicability This PSR has been prepared to control the transfer of liquids containing FISSILE URANIUM and FISSILE PLUTONIUM between tanks in facilities at the WVDP. Due to the I nature of activities at the WVDP, many waste streams, including streams meeting I environmental discharge requirements, contain some quantity of FISSILE URANIUM and I FISSILE PLUTONIUM. The thresholds specified in the Applicability of this PSR (i.e.,
PSR-l Rev. 2
. Page 5 of 7 K 1 gram TOTAL URANIUM, or 0.06 Ci Pu-239 + lPu-240) have been selected to exclude waste streams containing very low.masses of FISSILE URANIUM.and ýFISSILE PLUTONIUM. This threshold is consistent with DOE Order 420.1, .DOE G 421.1-1, ANSI/ANS-8.1-1983, and ANSI/ANS-8.10-1983. DOE:G 421.1-1 specifically addresses the-concept of "Exempt quantities of fissionable materials" in section'5.6.2.12.e- This concept allows for
,each facility to document the quantities-of-fissionable-material~s thatdo not require Nuclear Criticality Safety Evaluations and do not require'criticality safety controls. Based upon process knowledge and sampling history, the tanks to which this PSR applies are not expected to contain quantities of FISSILE URANIUM and FISSILE : I PLUTONIUM such that the 'exempt quantity would result in a meaningful 'increase'in the Keff of any of the tanks. :Further, this-practice is also-applied at Savannah River and Hanford.
The analysis documented in Reference 1 has-determined-that the tanks-to which this
,PSR applies (i.e4: Tanks°13D-8, 7D-2, 3D-2-[except when sampling 7D-2], 7D-8, 7D-14, 4D-10, 7D-1, 4D-2) are critically safe when the limits of Table 1 are met. The criticality safety of-operations within theJIRTS-and Vitrification-Facility are I k.-> documented in References 2 and 3. These systems process waste streams-with inherently safe FISSILE URANIUM and FISSILE PLUTONIUM concentrations. Therefore, liquid transfers of FISSILE URANIUM and FISSILE PLUTONIUM-in the -IRTS and Vitrification Facility need not be addressed in this PSR..- . - - - .
Bases of Limiting Conditions for Operation
- 1. Reference 1 calculates the safe concentration of Pu-239 corresponding to a given concentration of U-235.- The analysis in Reference 1-assumed a moderated, unreflected system containing-only U-235. and Pu-239.- Other fissile nuclides at the WVDP include U-233 and Pu-241. Although the analysis in
-Reference 1 considered these nuclides,'.it concluded that thes-e nuclides would' not contribute significantly to the reactivity of systems in which they are present due to the relatively small fraction (less than 5%) of the total fissile mass that these nuclides represent.ý Table 1 of this PSR ha'sbeen k
adapted, and independently reviewed, from Table.5.3,of Reference 1'to present limits in units provided by Analytical and Process Chemistry.
- 2. The analysis of Reference 1 assumes that the FISSILE URANIUM and FISSILE I
PSR-I Rev. 2 Page 6 of 7 PLUTONIUM is homogeneously distributed within the solution. Precipitation of FISSILE-URANIUM and FISSILE PLUTONIUM in a plant tank could result in an unanalyzed condition. Standard criticality safety references such as Reference 4 indicate that heterogenous moderated systems are more reactive than similar homogeneous systems. It is therefore necessary to identify and evaluate conditions that could result in the precipitation of FISSILE URANIUM and FISSILE PLUTONIUM.
ATTACHMENT I Table 1 - Criteria for Determining the Allowable FISSILE URANIUM and FISSILE PLUTONIUM Concentrations for Liquid Transfers REFERENCES
- 1) FB:85:0150, Allowable Fissile Material Solution Concentration for Liquid Transfers, Revision 1, K. A. O'Ahoofe memo to C.J. Roberts dated July 2, 1985.
- 2) WVNS-SAR-001, Safety Analysis Report for Waste Processing and Support Activities.
I 3) Paxton, H. C., and N. L. Pruvost. July, 1987. Critical Dimensions of Systems Containing 235 U, 2 39 Pu, and 133U (1986 Revision). Los Alamos National Laboratory. Report No. LA-10860-MS.
- 4) DOE Order 420.1. "Facility Safety."
- 5) DOE G 421.1-1. "DOE Good Practices Guide: Criticality Safety Good Practices I Program Guide for DOE Nonreactor Nuclear Facilities."
- 6) ANSI/ANS-8.1-1983. "Nuclear Criticality Safety in Operations with Fissionable Materials Outside Reactors." 1983.
- 7) ANSI/ANS-8.10-1983. "Criteria for Nuclear Criticality Safety Controls in Operations with Shielding and Confinement." 1983.
PSR-1 Rev. 2 Page 7 of 7 TABLE 1 CRITERIA FOR DETERMINING THE ALLOWABLE FISSILE URANIUM and FISSILE PLUTONIUM I CONCENTRATIONS FOR LIQUID TRANSFERS '
Column 1'l CThm :.
'Concentration of Corresponding'
' Maximum lI Total Uranium 2 'Plutonium Concentration l
- - - ,--.P-239 Thi-20 Greater Than -or But less Thahn.
Equalt Greater than 190 3 50 190 3 0.
50 500 170 500 1,000 140 1,000 2,000 94 2,000 2,500 71 2,500 3,000 46 3,000 3,500 20 3,500 3
- 1. Column 1 is the concentration of total FISSILE URANIUM and Column 2 is the corresponding allowable concentration of FISSILE PLUTONIUM. For a sample containing total uranium in the range shown in Column 1, the corresponding value in Column 2 provides the concentration limit for Pu-239 plus Pu-240.
- 2. The total uranium limits in Table 1 correspond to 100 weight percent (w/o)
U-233 + U-235 enriched solutions. Although such streams do not exist at the WVDP, laboratory analyses for specific uranium isotopes are typically not provided. However, if isotopic data are available, the values for U-233 +
U-235 may be compared to the values of Table 1.
- 3. Written authorization of the Radiation and Safety Committee is required for processing liquids at these concentrations.
PSR-l Rev. 2 WVNS RECORD OF REVISION Revision On Rev. No. Description of Changes Paqe(s) Dated 2 This revision of the PSR has been prepared to All 12/06/02 clarify the applicability of the PSR and to limit its applicability to transfers of liquids containing greater than 1 gram of total FISSILE URANIUM and FISSILE PLUTONIUM. The revision also introduces a new Limiting Condition for Operation to address FISSILE URANIUM and FISSILE PLUTONIUM precipitation. Table I has been modified to present the limits in terms of units received from the analytical laboratory.
PSO and the A&PC Lab. are affected by these changes.
DOE approval contained in-Letter DW:2000:0026, dated January 14, 2000.
WV-1807, Rev. 8 i