ML042540171
| ML042540171 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 09/10/2004 |
| From: | Dan Collins NRC/NRR/DLPM/LPD1 |
| To: | Bakken A Public Service Enterprise Group |
| Collins D, NRR/DLPM, 415-1427 | |
| References | |
| BL-03-001, TAC MB9607, TAC MB9608 | |
| Download: ML042540171 (5) | |
Text
September 10, 2004 Mr. A. Christopher Bakken, III President & Chief Nuclear Officer PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION RE: BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MB9607 AND MB9608)
Dear Mr. Bakken:
By letter dated August 8, 2003, PSEG Nuclear, LLC (PSEG) provided their 60-day response to NRC Bulletin 2003-01 for the Salem Nuclear Generating Station, Unit 1 and 2. The Bulletin requested PSEG to either (1) state that the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions have been analyzed with respect to the potentially adverse post-accident debris blockage effects identified in the bulletin and are in compliance with all existing applicable regulatory requirements, or (2) describe any interim compensatory measures that have been or will be implemented to reduce the interim risk associated with potentially degraded or nonconforming ECCS and CSS recirculation functions until an evaluation to determine compliance is complete.
The Nuclear Regulatory Commission (NRC) staff is reviewing your response and has determined that the information request in the attachment to this letter is necessary for completion of the NRC staffs review. The required information was discussed with Mr. Michael Mosier of your staff on September 3, 2004. The NRC staff requests that you provide responses to the enclosed questions within 45 days in order for the NRC to complete its review in a timely manner. If you have any questions, please contact me at (301) 415-1427.
Sincerely,
/RA/
Daniel S. Collins, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-272 and 50-311
Enclosure:
As stated cc w/encl: See next page
September 10, 2004 Mr. A. Christopher Bakken, III President & Chief Nuclear Officer PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION RE: BULLETIN 2003-01, POTENTIAL IMPACT OF DEBRIS BLOCKAGE ON EMERGENCY SUMP RECIRCULATION AT PRESSURIZED-WATER REACTORS (TAC NOS. MB9607 AND MB9608)
Dear Mr. Bakken:
By letter dated August 8, 2003, PSEG Nuclear, LLC (PSEG) provided their 60-day response to NRC Bulletin 2003-01 for the Salem Nuclear Generating Station, Unit 1 and 2. The Bulletin requested PSEG to either (1) state that the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions have been analyzed with respect to the potentially adverse post-accident debris blockage effects identified in the bulletin and are in compliance with all existing applicable regulatory requirements, or (2) describe any interim compensatory measures that have been or will be implemented to reduce the interim risk associated with potentially degraded or nonconforming ECCS and CSS recirculation functions until an evaluation to determine compliance is complete.
The Nuclear Regulatory Commission (NRC) staff is reviewing your response and has determined that the information request in the attachment to this letter is necessary for completion of the NRC staffs review. The required information was discussed with Mr. Michael Mosier of your staff on September 3, 2004. The NRC staff requests that you provide responses to the enclosed questions within 45 days in order for the NRC to complete its review in a timely manner. If you have any questions, please contact me at (301) 415-1427.
Sincerely,
/RA/
Daniel S. Collins, Senior Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-272 and 50-311
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION PUBLIC JHannon AWang ECoby, RGN-I DSolorio ACRS DCollins RRodriguez GMiller MKowal OGC PDI-2 Reading LWhitney ADAMS Accession Number: ML042540171
- Input Provided by Memorandum, no major changes made OFFICE PDI-2/PE PDI-2/PM SPLB-BC PDI-2/SC NAME GMiller GWunder for DCollins JHannon*
DCollins for JClifford DATE 9/9/04 9/9/04 8/23/04 9/9/04 OFFICIAL RECORD COPY
Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. Michael H. Brothers Vice President - Site Operations PSEG Nuclear - X15 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John T. Carlin Vice President - Nuclear Assessments PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. David F. Garchow Vice President - Eng/Tech Support PSEG Nuclear - N28 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Steven Mannon Acting Manager - Licensing PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Jeffrie J. Keenan, Esquire PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038 Ms. R. A. Kankus Joint Owner Affairs PECO Energy Company Nuclear Group Headquarters KSA1-E 200 Exelon Way Kennett Square, PA 19348 Lower Alloways Creek Township c/o Mary O. Henderson, Clerk Municipal Building, P.O. Box 157 Hancocks Bridge, NJ 08038 Dr. Jill Lipoti, Asst. Director Radiation Protection Programs NJ Department of Environmental Protection and Energy CN 415 Trenton, NJ 08625-0415 Brian Beam Board of Public Utilities 2 Gateway Center, Tenth Floor Newark, NJ 07102 Regional Administrator, Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Senior Resident Inspector Salem Nuclear Generating Station U.S. Nuclear Regulatory Commission Drawer 0509 Hancocks Bridge, NJ 08038 Mr. Carl J. Fricker Plant Manager PSEG Nuclear - N21 P.O. Box 236 Hancocks Bridge, NJ 08038
REQUEST FOR ADDITIONAL INFORMATION REGARDING PROPOSED ALTERNATIVE TO BULLETIN 2003-01 SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated August 8, 2003, PSEG Nuclear, LLC (PSEG) provided their 60-day response to NRC Bulletin 2003-01 for the Salem Nuclear Generating Station, Unit 1 and 2. The bulletin requested PSEG to either (1) state that the emergency core cooling system (ECCS) and containment spray system (CSS) recirculation functions have been analyzed with respect to the potentially adverse post-accident debris blockage effects identified in the bulletin and are in compliance with all existing applicable regulatory requirements, or (2) describe any interim compensatory measures that have been will be implemented to reduce the interim risk associated with potentially degraded or nonconforming ECCS and CSS recirculation functions until an evaluation to determine compliance is complete. The Nuclear Regulatory Commission (NRC) staff has completed its preliminary review of your response and determined that responses to the following questions are necessary for completion of the NRC staffs review:
1.
On page 5 of Attachment 3 of your response to Bulletin 2003-01 you state that The [Westinghouse Owners Group] WOG has committed to evaluate and access (sic) actions to delay switchover to containment sump recirculation and provide generic recommendations to utilities by March 31, 2004. After the WOG recommendations are approved and issued, Salem will re-evaluate the need for changes to the EOPs and any supporting analysis or licensing changes that may be required.
The WOG has developed operational guidance in response to Bulletin 2003-01 for Westinghouse and CE type pressurized water reactors. Provide a discussion of your plans to consider implementing this new WOG guidance. Include a discussion of the WOG recommended compensatory measures that have been or will be implemented at your plant, and the evaluations or analyses performed to determine which of the WOG recommended changes are acceptable at your plant. Provide technical justification for those WOG recommended compensatory measures not being implemented by your plant. Also include a detailed discussion of the procedures being modified, the operator training being implemented, and your schedule for implementing these compensatory measures.
2.
NRC Bulletin 2003-01 provides possible interim compensatory measures licensees could consider to reduce risks associated with sump clogging. In addition to those compensatory measures listed in Bulletin 2003-01, licensees may also consider implementing unique or plant-specific compensatory measures, as applicable. On page 9 of Attachment 1 to your Bulletin 2003-01 response, you discussed the design, purpose, and cleaning routine for both the inner and outer annulus drain trenches.
Please discuss any other possible unique or plant-specific compensatory measures you considered for implementation at your plant. Include a basis for rejecting any of these additional considered measures.