ML072400530
| ML072400530 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/28/2007 |
| From: | Richard Ennis NRC/NRR/ADRO/DORL/LPLI-2 |
| To: | Chernoff H K Plant Licensing Branch III-2 |
| Ennis R B, NRR/DORL, 415-1420 | |
| References | |
| GL-04-002, TAC MD6353, TAC MD6354 | |
| Download: ML072400530 (3) | |
Text
August 28, 2007MEMORANDUM TO:Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Richard B. Ennis, Senior Project Manager Plant Licensing Branch I-2/RA/Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2,DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD6353 AND MD6354)The attached draft request for information (RAI) was transmitted on August 28, 2007, toMr. Jamie Mallon of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee's amendment request for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, dated August 15, 2007. The proposed amendment would revise the licensing basis, as described in Appendix 3A of the Salem Updated Final Safety Analysis Report, regarding the method of calculating the net positive suction head available for the emergency core cooling system and containment heat removal system pumps. The proposed change relates to issues associated with Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." This memorandum and the attachment do not convey or represent an NRC staff positionregarding the licensee's request.Docket Nos. 50-272 and 50-311
Attachment:
Draft RAI August 28, 2007MEMORANDUM TO:Harold K. Chernoff, ChiefPlant Licensing Branch I-2 Division of Operating Reactor Licensing Office of Nuclear Reactor RegulationFROM:Richard B. Ennis, Senior Project ManagerPlant Licensing Branch I-2Division of Operating Reactor Licensing/RA/Office of Nuclear Reactor Regulation
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2,DRAFT REQUEST FOR ADDITIONAL INFORMATION (TAC NOS. MD6353 AND MD6354)The attached draft request for information (RAI) was transmitted on August 28, 2007, toMr. Jamie Mallon of PSEG Nuclear LLC (the licensee). This information was transmitted to facilitate an upcoming conference call in order to clarify the licensee's amendment request for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2, dated August 15, 2007. The proposed amendment would revise the licensing basis, as described in Appendix 3A of the Salem Updated Final Safety Analysis Report, regarding the method of calculating the net positive suction head available for the emergency core cooling system and containment heat removal system pumps. The proposed change relates to issues associated with Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." This memorandum and the attachment do not convey or represent an NRC staff positionregarding the licensee's request.Docket Nos. 50-272 and 50-311
Attachment:
Draft RAIDISTRIBUTIONPUBLICRidsNrrDorlLpl1-2WLyonPDI-2 ReadingRidsNrrPMREnnis RidsNrrDorlDprRLobelACCESSION NO.: ML072400530OFFICEPDI-2/PMNAMEREnnis DATE08/28/07OFFICIAL RECORD COPY 1Letter from E. C. Simpson, Public Service Electric and Gas Company, to NRC, 90 Day Response toGeneric Letter 97-04, January 5, 1998AttachmentDRAFT REQUEST FOR ADDITIONAL INFORMATIONREGARDING PROPOSED LICENSE AMENDMENTREVISION TO LICENSING BASIS - NET POSTIVE SUCTION HEAD METHODOLGYFOR EMERGENCY CORE COOLING SYSTEM PUMPSSALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2DOCKET NOS. 50-272 AND 50-311By letter dated August 15, 2007, PSEG Nuclear LLC (PSEG or the licensee) submitted anamendment request for Salem Nuclear Generating Station (Salem), Unit Nos. 1 and 2. The proposed amendment would revise the licensing basis, as described in Appendix 3A of the Salem Updated Final Safety Analysis Report (UFSAR), regarding the method of calculating the net positive suction head (NPSH) available for the emergency core cooling system and containment heat removal system pumps. The proposed change relates to issues associated with Generic Letter 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors." The NRC staff has reviewed the information the licensee provided that supports the proposedamendment and would like to discuss the following issues to clarify the submittal.1.Please confirm that the pressure to be credited in determining the available NPSH of theresidual heat removal pumps during a loss-of-coolant accident is the pre-accident partial air pressure in containment.2.The August 15, 2007, letter proposes to delete a statement from the UFSAR(Appendix 3A) which states:Added conservatism is introduced into the NPSH calculation by calculating thestatic head from the elevation of the top of the sump instead of the available water level above the sump.The reason for the deletion appears to be that the water level is determined, since 1997 1, as a minimum calculated value rather than the top of the sump. However, this isnot clarified by the proposed change to the UFSAR. Please propose wording to add to the UFSAR that will describe how the water level is determined (such as that on page 9 of Attachment 1 of the August 15, 2007, letter).