ML042370106
| ML042370106 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 08/24/2004 |
| From: | Dan Collins NRC/NRR/DLPM/LPD1 |
| To: | Bakken A Public Service Enterprise Group |
| Collins D S, NRR/DLPM, 415-1427 | |
| References | |
| TAC MC3094, TAC MC3095 | |
| Download: ML042370106 (5) | |
Text
August 24, 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: IMPLEMENTATION OF ALTERNATE SOURCE TERM (TAC NOS. MC3094 AND MC3095)
Dear Mr. Bakken:
By letter dated April 26, 2004, PSEG Nuclear, LLC submitted a request for changes to the Salem Nuclear Generating Station, Units No. 1 and 2, Technical Specifications. The proposed changes would revise the source term used for design basis radiological analysis. The proposed change would also revise certain requirements in the Technical Specifications and Updated Final Safety Analysis Report based on the radiological dose analysis margins obtained in the Alternate Source Term application.
The Nuclear Regulatory Commission (NRC) staff has determined that responses to the questions in the enclosure to this letter are necessary in order for the Materials and Chemical Engineering Branch to complete its review. Additional information needs, necessary for other branches to complete their review, will be communicated to you as they are identified. The staff requests that you provide responses to the enclosed questions within 30 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 by George F. Wunder for/
Daniel S. Collins, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
As stated cc w/encl: See next page
August 24, 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: IMPLEMENTATION OF ALTERNATE SOURCE TERM (TAC NOS. MC3094 AND MC3095)
Dear Mr. Bakken:
By letter dated April 26, 2004, PSEG Nuclear, LLC submitted a request for changes to the Salem Nuclear Generating Station, Units No. 1 and 2, Technical Specifications. The proposed changes would revise the source term used for design basis radiological analysis. The proposed change would also revise certain requirements in the Technical Specifications and Updated Final Safety Analysis Report based on the radiological dose analysis margins obtained in the Alternate Source Term application.
The Nuclear Regulatory Commission (NRC) staff has determined that responses to the questions in the enclosure to this letter are necessary in order for the Materials and Chemical Engineering Branch to complete its review. Additional information needs, necessary for other branches to complete their review, will be communicated to you as they are identified. The staff requests that you provide responses to the enclosed questions within 30 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 by George F. Wunder for/
Daniel S. Collins, Sr. Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket No. 50-354
Enclosure:
As stated cc w/encl: See next page DISTRIBUTION PUBLIC JClifford LLund ECoby, RGN-I ACRS DCollins RRodriguez GMiller OGC PDI-2 Reading ADAMS Accession Number: ML042370106
- See Previous Concurrence OFFICE PDI-2/PE PDI-2/PM EMCB-C/SC PDI-2/SC NAME GMiller DCollins LLund*
DCollins forJClifford DATE 8/23/04 8/23/04 8/23/04 8/23/04 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 UTILIZE A RISK INFORMED-INSERVICE INSPECTION PLAN SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 DOCKET NOS. 50-272 AND 50-311 By letter dated April 26, 2004, PSEG Nuclear, LLC submitted a request for changes to the Salem Nuclear Generating Station, Units No. 1 and 2, Technical Specifications. The proposed changes would revise the source term used for design basis radiological analysis. The proposed change would also revise certain requirements in the Technical Specifications and Updated Final Safety Analysis Report based on the radiological dose analysis margins obtained in the Alternate Source Term application. The Nuclear Regulatory Commission (NRC) staff has been reviewing your submittal and has determined that the following additional information is required to complete our review:
1.
Section 4.1, pages 12 and 16, in your submittal state that the containment sump water will remain at a pH greater than 7 following a loss of coolant accident (LOCA). Provide a discussion of the assumptions and calculations used to conclude that the pH will remain above 7 for at least 30 days following a LOCA. This discussion should be in sufficient detail for the NRC staff to perform independent calculations and verify the validity of this conclusion. If the calculations were performed manually, discuss the methodology used and provide sample calculations. If the calculations were performed using a computer code, provide a description of the code including input values and how they were determined. Provide the results at different time intervals and discuss the criteria for selecting the intervals.
2.
Provide information on the systems used to ensure that after a LOCA the pH of the sump water will stay basic. Your response should include a description of the methodology and the accompanying calculations used in determining the amounts of chemical agents needed to achieve this objective.