ML030770044
| ML030770044 | |
| Person / Time | |
|---|---|
| Site: | Salem  |
| Issue date: | 03/18/2003 |
| From: | Robert Fretz NRC/NRR/DLPM/LPD1 |
| To: | Keiser H Public Service Enterprise Group |
| Fretz, R, NRR/DLPM, 415-1324 | |
| References | |
| TAC MB5710, TAC MB5711 | |
| Download: ML030770044 (5) | |
Text
March 18, 2003 Mr. Harold W. Keiser Chief Nuclear Officer & President PSEG Nuclear LLC - X04 Post Office Box 236 Hancocks Bridge, NJ 08038
SUBJECT:
SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2, REQUEST FOR ADDITIONAL INFORMATION (RAI) RE: REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS RELATING TO CONTAINMENT CLOSURE AND FUEL HANDLING AREA VENTILATION REQUIREMENTS (TAC NOS.
MB5710 AND MB5711)
Dear Mr. Keiser:
By letter dated July 29, 2002, PSEG Nuclear LLC submitted a request for a revision to Technical Specifications associated with containment closure and Fuel Handling Area ventilation requirements at the Salem Nuclear Generating Station, Unit Nos. 1 and 2. The request was submitted in order to provide flexibility in scheduling certain refueling outage activities.
The U.S. Nuclear Regulatory Commission staff is reviewing your request and has determined that additional information is necessary in order to complete its evaluation. We discussed the enclosed RAI with your staff during a telephone call on February 27, 2003. During the call, you agreed to respond to the enclosed RAI within 45 days from the date of this letter. If circumstances result in the need to revise the target date, please contact me at (301) 415-1324.
Sincerely,
/RA/
Robert J. Fretz, Project Manager, Section 2 Project Directorate I Division of Licensing Project Management Office of Nuclear Reactor Regulation Docket Nos. 50-272 and 50-311
Enclosure:
RAI cc w/encl: See next page
ML030770044 OFFICE PDI-2/PM PDI-2/LA PDI-2/SC NAME RFretz CRaynor JBoska for JClifford DATE 03/13/03 03-13-03 3-14-03 Enclosure REQUEST FOR ADDITIONAL INFORMATION REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS CONTAINMENT CLOSURE AND FUEL HANDLING AREA VENTILATION REQUIREMENTS SALEM NUCLEAR GENERATING STATION, UNIT NOS. 1 AND 2 By letter dated July 29, 2002, PSEG Nuclear LLC submitted a request for a revision to Technical Specifications (TSs) associated with containment closure and Fuel Handling Area ventilation requirements at the Salem Nuclear Generating Station, Unit Nos. 1 and 2 (Salem).
The U.S. Nuclear Regulatory Commission (NRC) staff is reviewing your request and has determined that additional information is necessary in order to complete its evaluation.
Questions:
1.
As a result of the adoption of the alternate source term (AST), some licensees are requesting that certain requirements, including ventilation systems no longer credited in the accident dose analysis, be removed from TSs. After a careful review of some of these requests, the NRC staff concluded that certain requests may be granted provided that other applicable regulations and requirements continue to be met. These regulations may include, where applicable, Title 10 of the Code of Federal Regulations (10 CFR) Section 50.36, General Design Criterion (GDC) 61, GDC 64, and rules on ALARA. Other requirements would include: (1) following the principles of risk-informed regulations, (2) maintaining defense-in-depth and existing safety margins, (3) ensuring that increases in risk do not result in violation of core damage frequency (CDF) and large early release frequency (LERF) goals, and (4) performance based implementation and monitoring address uncertainties and include corrective actions.
Accordingly, because PSEG is requesting to remove or downgrade ventilation systems required by TSs by adopting AST, the licensee needs to address, in writing, how 10 CFR 50.34a; 10 CFR 50.36, Criterion 2; and GDCs 61, 63, and 64 continue to be met as a result of the requested change.
2.
According to the submittal, the containment purge system and the auxiliary building ventilation systems can draw a negative pressure on the containment with the equipment hatch open. Describe the analyses that were performed to verify that these systems can draw down the containment with the equipment hatch open.
3.
If the Fuel Handling Area Ventilation system is not operating when moving loads over the spent fuel pool, how will radiological releases due to a dropped load be monitored?
4.
In paragraph 5. of Containment Building Closure on page 5 of the submittal, the licensee states that, if containment closure would be hampered by an outage activity, compensatory actions will be developed. Briefly describe any expected outage activities that could prevent the establishment of containment closure and the compensatory actions that would need to be taken.
5.
In paragraph 3 of Fuel Handling Building Closure on page 6 of the submittal, PSEG states that, if fuel handling building closure would be hampered by an outage activity, compensatory actions will be developed. Briefly describe any expected outage activities that could prevent the establishment of fuel handling building closure and the compensatory actions that would need to be taken.
PSEG Nuclear LLC Salem Nuclear Generating Station, Unit Nos. 1 and 2 cc:
Mr. David F. Garchow Vice President - Operations PSEG Nuclear - X04 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. John T. Carlin Vice President - Nuclear Reliability and Technical Support PSEG Nuclear - N10 P.O. Box 236 Hancocks Bridge, NJ 08038 Mr. Gabor Salamon Manager - Nuclear Safety and 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