ML021620160

West Valley Demonstration Project, Index & Rev 3 to PSR-4 - Spent Fuel Cask Staging & Handling Requirements

ML021620160
Person / Time
Site:	West Valley Demonstration Project, P00M-032
Issue date:	05/31/2002
From:	Ploetz D West Valley Nuclear Services Co, Westinghouse Government Services Co
To:	NRC/NMSS/DWM/HLWB
References
+KBR1SISP20050613, HLWB PSR-4 Rev 3
Download: ML021620160 (14)

Text

RECORDS MANAGEMENT DEPARTMENT c1 1

512 TO: C. GLENN NRC HEADQUARTERS DATE: 05/31/2002 FROM: D.L. HORTON AOC-21 TEL: 716 942-4300 PAGE: 1 TRANSMITTAL NUM: 000018308 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-4 3 05/30/2002 SPENT FUEL CASK STAGING AND HANDLING REQUIREMENTS Copies made from a controlled document MUST be marked UNCONTROLLED before distribution. Signature below signifies all previous revisions, if applicable, have been destroyed or marked superseded.

I have complied with the above instructions:

RETURN BY: 06/14/2002 Signature (BLACK INDELIBLE INK ONLY) Date C\

FOR YOUR CONVENIENCE, A SELF-ADDRESSED, STAMPED ENVELOPE HAS BEEN INCLUDED.

DATE: 05/31/2002 PROCESS SAFETY REQUIREMENTS PAGE:

TIME: 12:53 WVDP-218 INDEX ISSUE VROCID RE_ BE PROCEDURE TITLE STATUS DATE COGNIZANT MANAGER WVDP-218 10 PREFACE FOR PROCESS SAFETY REQUIREMENTS ACTIVE 12/11/2000 CHILSON,L.J.

WVDP-218 10 1 PREFACE FOR PROCESS SAFETY REQUIREMENTS ACTIVE 03/09/2001 CHILSON,L.J.

WVDP-218 10 2 PREFACE FOR PROCESS SAFETY REQUIREMENTS ACTIVE 06/05/2001 CHILSON,L.J.

WVDP-218 10 3 PREFACE FOR PROCESS SAFETY REQUIREMENTS ACTIVE 09/19/2001 CHILSONL,.J.

PSR-1 REQUIREMENTS FOR LIQUID TRANSFERS OF ACTIVE 03/15/1996 POTTS,W.J.

FISSILE MATERIAL PSR-1 1 REQUIREMENTS FOR LIQUID TRANSFERS OF ACTIVE 04/03/1997 POTTS,W.J.

FISSILE MATERIAL PSR-2 2 MAIN PLANT STACK AIRBORNE EFFLUENT ACTIVE 09/12/2000 POTTS,W.J.

SAMPLING SYSTEM REQUIREMENTS PSR-3 2 BUILDING AND VESSEL VENTILATION SYSTEM ACTIVE 01/03/2001 POTTS,W.J.

REQUIREMENTS PSR-3 2 1 BUILDING AND VESSEL VENTILATION SYSTEM ACTIVE 06/29/2001 POTTS,W.J.

REQUIREMENTS PSR-4 3 SPENT FUEL CASK STAGING AND HANDLING ACTIVE 05/30/2002 POTTS,W.J.

REQUIREMENTS PSR-5 2 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 11/05/1999 POTTS,W.J.

PSR-5 2 1 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 11/23/1999 POTTS,W.J.

PSR-5 2 2 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 02/17/2000 POTTS,N.J.

PSR-6 2 3 STANDBY AND BACKUP POWER REQUIREMENTS ACTIVE 06/29/2001 POTTS .W. J.

PSR-6 FISSILE MATERIAL PACKAGING AND STORAGE ACTIVE 07/10/1996 KOMASARA,S.M.

1 REQUIREMENTS PSR-6 1 FISSILE MATERIAL PACKAGING AND STORAGE ACTIVE 04/07/1997 KOMASARA,S.M.

REQUIREMENTS PSR-7 2 FISSILE MATERIAL PACKAGING AND STORAGE ACTIVE 07/02/1998 KOMASARAS.M.

REQUIREMENTS PSR-7 2 EMERGENCY PAGING SYSTEM AND SHELTERING ACTIVE 10/13/2000 POTTS,W.J.

1 ALARM REQUIREMENTS PSR-B 3 FIRE PROTECTION SYSTEMS REQUIREMENTS ACTIVE 07/20/2001 POTTS,W.J.

PSR-10 3 HIGH-LEVEL WASTE TANK LEAK DETECTION ACTIVE 02/12/2001 MEESS,D,C.

AND RECOVERY REQUIREMENTS PSR-11 2 HIGH-LEVEL WASTE TANK SPARE CAPACITY ACTIVE 03/15/1996 MEESS,D,C.

1 5 REQUIREMENTS PSR-12 1 HIGH-LEVEL WASTE TANK SPARE CAPACITY ACTIVE 03/26/1997 MEEES,D,TC.

REQUIREMENTS PSR-12 2 VITRIFICATION FACILITY VENTILATION AND ACTIVE 02/21/1997 KOCIALSKI,T.F.

OFF-GAS SYSTEMS REQUIREMENTS PSR- 12 1 VITRIFICATION FACILITY VENTILATION AND ACTIVE 11/03/1998 KOCIALSKI,T.F.

OFF-GAS SYSTEMS REQUIREMENTS PSR-12 3 2 VITRIFICATION FACILITY VENTILATION AND ACTIVE 03/05/1999 KOCIALSKI,T.F.

OFF-GAS SYSTEMS REQUIREMENTS PSR-12 3 5 VITRIFICATION FACILITY VENTILATION AND ACTIVE 05/20/1999 KOCIALSKI,T.F.

OFF-GAS SYSTEMS REQUIREMENTS PSR-13 2 VITRIFICATION FACILITY STANDBY POWER ACTIVE 03/28/1996 KOCIALSKI,T.F.

REQUIREMENTS PSR-13 2 1 VITRIFICATION FACILITY STANDBY POWER ACTIVE 05/24/1996 KOCIALSKI,T.F.

REQUIREMENTS PSR-13 2 2 VITRIFICATION FACILITY STANDBY POWER ACTIVE 07/11/1996 KOCIALSKI,T.F.

REQUIREMENTS 3 NOX MONITORING INSTRUMENTATION ACTIVE 09/30/1998 KOCIALSKI,T.F.

REQUIREMENTS PSR-15 3 1 NOX MONITORING INSTRUMENTATION ACTIVE 11/23/1999 KOCIALSKI,T.F.

REQUIREMENTS

DATE: 05/31/2002 PROCESS SAFETY REQUIREMENTS PAGE: 2 TIME: 12:53 WVDP-218 INDEX ISSUE PROC ID REV fC PROCEDURF TITLE STATUS COGNIZANT MANAGER PSR-16 6 ANHYDROUS AMMONIA MONITORING ACTIVE 11/12/1998 KOCIALSKI,T.F.

INSTRUMENTATION AND STORAGE REQUIREMENTS PSR-16 6 1 ANHYDROUS AMMONIA MONITORING ACTIVE 06/27/2000 KOCIALSKI,T.F.

INSTRUMENTATION AND STORAGE REQUIREMENTS PSR-17 4 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 09/24/1999 COVERT,B.C.

OPERATION PSR-17 4 1 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 05/11/2000 COVERT,B.C.

OPERATION PSR-17 4 2 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 10/13/2000 COVERTB.C, OPERATION PSR-17 4 3 MINIMUM STAFFING LEVELS FOR SAFE FACILITY ACTIVE 10/26/2000 COVERT,B.C.

OPERATION

Doc. ID Number PSR-4 West Valley Revision Number 3 Demonstration Project Revision Date 05/30/2002 PROCESS SAFETY REQUIREMENTS TITLE: SPENT FUEL CASK STAGING AND HANDLING REQUIREMENTS V

APPROVED BY:

Cognizant Manager Date APPROVED BY:

Ra r afety Committee, Date

• alrman AUTHORIZATION TO IMPLEMENT:

Process Plant Decontamination iate Project Manager Westinghouse Government Services Group West Valley Nuclear Services Co.

10282 Rock Springs Road West Valley, NY 14171-9799 W-1 816, Rev. 3

PSR-4 Rev. 3 Page 2 of 9 PROCESS SAFETY REQUIREMENT - 4 TITLE: Spent Fuel Cask Staging and Handling Requirements CRITERIA: Prevention of criticality during handling and storage of spent fuel assemblies. (PSR Criterion 3.a from WV-365, Preparation of WVDP Safety Documents, Attachment C, Process Safety Requirement Criteria.)

Assurance that actions required to comply with Nuclear Regulatory Commission (NRC) spent fuel shipping cask Certificates of Compliance are properly incorporated into IMPLEMENTING PROCEDURES and, upon execution, are witnessed and verified. (PSR Criterion 4 from WV-365, Preparation of WVDP Safety Documents, Attachment C, Process Safety Requirement Criteria.)

UNACCEPTABLE EVENTS: Inadvertent criticality during handling and storage of spent fuel assemblies.

Failure to include in an approved IMPLEMENTING PROCEDURE actions required to comply with Nuclear Regulatory Commission spent fuel shipping cask Certificates of Compliance.

Failure to perform, witness, or verify actions required to comply with Nuclear Regulatory Commission spent fuel shipping cask Certificates of Compliance.

Process Safety Requirement - 4 Page No.

APPLICABILITY ................................ ................................... 3 OBJECTIVES ................................. .................................... 3 SPECIFICATIONS ............................... .................................. 3 BASIS .................................... ....................................... 8 ATTACHMENT ................................. .................................... 9 REFERENCES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 9

PSR-4 Rev. 3 Page 3 of 9 PROCESS SAFETY REQUIREMENT SPENT FUEL CASK STAGING AND HANDLING REQUIREMENTS APPLICABILITY This Process Safety Requirement (PSR) applies to fuel assembly storage and handling in the Cask Unloading Pool (CUP) section of the Fuel Receiving and Storage (FRS) facility and fuel assemblies staged for shipment in Nuclear Regulatory Commission (NRC)-licensed shipping casks anywhere on the WVDP site.

In addition, this PSR applies to actions required to comply with the NRC spent fuel shipping cask Certificates of Compliance.

OBJECTIVES The objectives of this PSR are to ensure that fuel assemblies are maintained in a subcritical configuration and to ensure that actions required to comply with Nuclear Regulatory Commission spent fuel shipping cask Certificates of Compliance are conducted per the requirements of an approved IMPLEMENTING PROCEDURE and, upon execution, are witnessed and verified.

SPECIFICATIONS

1. Deleted

2. Deleted

3. Deleted

4. Deleted

5. LIMITING CONDITION FOR OPERATION At least four bolts shall be installed to secure a cask lid before handling (moving or raising or lowering) of a shipping cask containing one or more fuel assemblies. This condition applies only to handling the cask while it is suspended from the FRS 100-ton crane for emplacement or removal from the CUP.

PSR-4 Rev. 3 Page 4 of 9 ACTION If it is determined that a loaded cas.k is being handled (moved or raised or lowered) into or out of the CUP without the lid being secured with at least four bolts, the cask shall IMMEDIATELY be placed in a safe resting position and the condition shall be reported IMMEDIATELY to the Spent Fuel Project Manager and the Radiation and Safety Committee Chairman. Written permission from the Radiation and Safety Committee shall be obtained to resume cask-handling (cask-moving or -raising or

-lowering) operations.

SURVEILLANCE REQUIREMENT PRIOR to any handling (moving or raising or lowering) activities involving a shipping cask into or out of the CUP in which at least one fuel assembly has been placed, verification shall be made per the requirements of an approved IMPLEMENTING PROCEDURE that at least four bolts have been properly installed to secure the cask lid.

6. Deleted

7. LIMITING CONDITION FOR OPERATION Operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-REG shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures, shall be conducted and, upon execution, witnessed and verified by the Quality Assurance Department per the requirements of an approved IMPLEMENTING PROCEDURE.

ACTION

a. If operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-REG shipping cask or underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures, are being conducted without the requirements being stated in an approved IMPLEMENTING PROCEDURE, all further operational steps shall be stopped IMMEDIATELY. The Spent Fuel Project Manager and the Radiation and Safety Committee Chairman shall be notified IMMEDIATELY. Resumption of operations shall be in accordance with a written plan that is approved by OH/WVDP.

PSR-4 Rev. 3 Page 5 of 9

b. If operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-REG shipping cask or underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures, are being conducted per the requirements of an approved IMPLEMENTING PROCEDURE but, upon execution, are not witnessed and verified by the Quality Assurance Department, all further operational steps shall be stopped IMMEDIATELY. The Spent Fuel Project Manager and the Radiation and Safety Committee Chairman shall be notified IMMEDIATELY. Resumption of operations shall be in accordance with a written plan that is approved by OH/WVDP.

SURVEILLANCE REQUIREMENT

a. Before obtaining gas samples from the TN-REG shipping cask, performing helium leak testing, or changing out primary boundary seals, operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-REG shipping cask and applicable underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures, it shall be determined and documented that requirements contained in the NRC Certificate of Compliance for the TN-REG shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures are contained in approved IMPLEMENTING PROCEDURES. This determination and documentation shall be performed per the requirements of an approved IMPLEMENTING PROCEDURE.

b. Before obtaining gas samples from the TN-REG shipping cask, performing helium leak testing, or changing out primary boundary seals on the TN-REG shipping cask by conducting operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-REG shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures, it shall be determined and documented that the approved IMPLEMENTING PROCEDURES require witnessing and verification by the Quality Assurance Department upon completion of each of the designated procedural steps. This determination and documentation shall be performed per the requirements of an approved IMPLEMENTING PROCEDURE.

PSR-4 Rev. 3 Page 6 of 9

c. Upon completion of operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-REG shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR, Chapter Seven, Operating Procedures, it shall be determined and documented that the operational steps have been completed. This determination and documentation shall be performed per the requirements of an approved IMPLEMENTING PROCEDURE.

8. LIMITING CONDITION FOR OPERATION Operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-BRP shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Procedures, shall be conducted and, upon execution, witnessed and verified by the Quality Assurance Department per the requirements of an approved IMPLEMENTING PROCEDURE.

ACTION

a. If operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-BRP shipping cask or underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Procedures, are being conducted without the requirements being stated in an approved IMPLEMENTING PROCEDURE, all further operational steps shall be stopped IMMEDIATELY. The Spent Fuel Project Manager and the Radiation and Safety Committee Chairman shall be notified IMMEDIATELY. Resumption of operations shall be in accordance with a written plan that is approved by OH/WVDP.

b. If operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-BRP shipping cask or underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Procedures, are being conducted per the requirements of an approved IMPLEMENTING PROCEDURE but, upon execution, are not witnessed and verified by the Quality Assurance Department, all further operational steps shall be stopped IMMEDIATELY. The Spent Fuel Project Manager and the Radiation and Safety Committee Chairman shall be notified IMMEDIATELY. Resumption of operations shall be in accordance with a written plan that is approved by OH/WVDP.

PSR-4 Rev. 3 Page 7 of 9 SURVEILLANCE REQUIREMENT

a. Before obtaining gas samples from the TN-BRP shipping cask, performing helium leak testing, or changing out primary boundary seals, operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-BRP shipping cask and applicable underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Procedures, it shall be determined and documented that requirements contained in the NRC Certificate of Compliance for the TN-BRP shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Procedures are contained in approved IMPLEMENTING PROCEDURES. This determination and documentation shall be performed per the requirements of an approved IMPLEMENTING PROCEDURE.

b. Before obtaining gas samples from the TN-BRP shipping cask, performing helium leak testing, or changing out primary boundary seals on the TN-BRP shipping cask by conducting operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-BRP shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Procedures, it shall be determined and documented that the approved IMPLEMENTING PROCEDURES require witnessing and verification by the Quality Assurance Department upon completion of each of the designated procedural steps. This determination and documentation shall be performed per the requirements of an approved IMPLEMENTING PROCEDURE.

c. Upon completion of operational steps that are required to satisfy the NRC Certificate of Compliance for the TN-BRP shipping cask and underlined procedural steps in the latest revision of the NRC-approved TN-BRP SAR, Chapter Seven, Operating Proceduresi it shall be determined and documented that the operational steps have been completed. This determination and documentation shall be performed per the requirements of an approved IMPLEMENTING PROCEDURE.

PSR-4 Rev. 3 Page 8 of 9 BASIS PWR and BWR fuel assemblies are designed to sustain nuclear criticality when placed in a suitable configuration with other fuel assemblies. Consequently, engineered and administrative controls are required to protect against an inadvertent criticality.

The NRC-licensed shipping casks are designed to reduce the neutronic interaction between fuel assemblies to an acceptable level.

Handling of a loaded spent fuel shipping cask represents the only activity in which more -than one fuel assembly is handled outside of a storage canister. Dropping of a full shipping cask in which the lid has not been secured could result in the release of one or more fuel assemblies from the shipping cask, resulting in an unanalyzed condition and possibly an inadvertent criticality. Consequently, it is required that the lid be secured with at least four lid bolts PRIOR to cask handling activities into or out of the CUP using a crane to mitigate the potential for an inadvertent criticality. A cask would be lowered into the CUP if the lid O-ring seals required replacement. The lid will be secured with 48 bolts during all other movements.

Nuclear Regulatory Commission (NRC) spent fuel shipping cask Certificates of Compliance specify or reference actions that must be carried out in order to ensure the validity of the latest revision of the NRC-approved TN-REG SAR and TN-BRP SAR.

These actions must be conducted per the requirements of an approved IMPLEMENTING PROCEDURE. Further, upon execution of these actions, witnessing and verification must be performed. A final verification must be performed to establish that the actions have been completed.

The operational steps required to maintain the validity of TN-REG and TN-BRP shipping cask transport safety analysis conclusions are specifically identified by underlined procedural steps in the latest revision of the NRC-approved TN-REG SAR and TN-BRP SAR, Chapter Seven, Operating Procedures and the NRC Certificates of Compliance for the TN-REG and TN-BRP shipping casks. These designated operational steps must be conducted per the requirements of an approved IMPLEMENTING PROCEDURE. Further, upon execution of underlined procedural steps, witnessing and verification must be performed. A final verification must be performed to establish that underlined procedural steps have been completed.

PSR-4 Rev. 3 Page 9 of 9 The latest revision of the NRC-approved TN-REG SAR and TN-BRP SAR, Chapter 8.0, Acceptance and Maintenance Programs, statc that Chapter 8.0 describes activities that ensure that the cask conforms to the requirements of the respective SAR and remains in conformance following fuel loading. The requirements of Chapter 8.0 of latest revision of each SAR were reviewed and were found either to have been previously completed or to be carried out as a subset of the requirements of underlined procedural steps in Chapter 7.0 of the latest revision of each SAR. Thus, no additional PSR SPECIFICATIONS are needed to fulfill the requirements of the latest revision of the NRC-approved TN-REG SAR and TN-BRP SAR, Chapter 8.0, Acceptance and Maintenance Programs.

ATTACHMENT None REFERENCES TN-BRP SAR. TN-BRP Spent Fuel Package Safety Analysis Report for Transport.

TN-REG SAR. TN-REG Spent Fuel Package Safety Analysis Report for Transport.

WVNS-SAR-012 1 . Safety Analysis Report for Fuel Receiving and Storage Facility.

NOTE 1: WVNS-SAR-012 IS IN THE PROCESS OF BEING CONSOLIDATED IN WVNS-SAR-002.

PSR-4 Rev. 3 WVNS RECORD OF REVISION Revision On Rev. No. Descriotion of Changes Page(s) Dated 3 General Revision All 05/30/02 REVISED cover sheet with approval signatures 1 Changed PSR title to reflect current requirements 1,2,3 MODIFIED the section on APPLICABILITY 3 DELETED Specifications 1, 2, 3, and 4 3 These four specifications, which applied to the fuel canisters, racks and lift racks, are now obsolete as the fuel assemblies are no longer handled or stored in the Fuel Storage Pool or CUP.

The fuel assemblies have been removed from the Fuel Storage Pool and are now staged in two NRC licensed shipping casks.

CLARIFIED Specification 5 3 This LCO applies only to handling the cask while it is suspended from the FRS 100-ton crane for emplacement or removal from the CUP.

DELETED Specification 6 4 This specification, which required maintaining the conductivity of the water in the Fuel Storage Pool below 4 gmho/cm to minimize corrosion of the canisters and racks, is no longer required. The purpose of this specification was to prevent reduction in the spacing between fuel assemblies due to failure of the racks or canisters caused by corrosion. The fuel assemblies have been removed from the Fuel Storage Pool and are staged dry in two NRC-Licenced shipping casks.

CLARIFIED Specifications 7 and 8 4 and 6 This specification was changed to address only activities to maintain the casks since all other actions have been completed loading the casks.

Certain SAR Chapter 7 underlined steps must be repeated while performing the listed maintenance actions.

CHANGED references the Spent Fuel Shipping Manager to the Spent Fuel Project Manager throughout.

CHANGED the BASIS to reflect the above changes.

WV-1807, Rev. 8 i

PSR-4 Rev. 3 WVNS RECORD OF REVISION CONTINUATION FORM Revision On Rev. No. Description of Changes Page(s) Dated 3 cont. ADDED a footnote to the REFERENCES that WVNS 9 SAR-012 is in the process of being consolidated into WVNS SAR-002.

DOE approval obtained in letter DW:2002:0177 dated, 04/11/02.

WV-1807, Rev. 8