ML18102A908

Provides Notification of Change in Commitment Implementation Schedule Re Potential for Thermal Overpressurization of Containment Fan Coil Unit Piping Per LER 96-020

ML18102A908
Person / Time
Site:	Salem
Issue date:	03/07/1997
From:	Dawn Powell Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
GL-96-06, GL-96-6, LR-N97145, NUDOCS 9703190083
Download: ML18102A908 (2)

Text

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PuQlic Service Electric and Gas Company P.O. Box 236 Hancocks Bridge, New Jersey 08038-0236

• Nuclear Business Unit MAR 7 1997 LR-N97145 U.S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 NOTIFICATION OF CHANGE IN COMMITMENT IMPLEMENTATION SCHEDULE SALEM GENERATING STATION UNIT NO. 2 DOCKET NO. 50-311 Gentlemen:

Public Service Electric & Gas Company (PSE&G) notified the NRC of the potential for thermal overpressurization of the Salem Unit 2 Containment Fan Coil Unit (CFCU) piping in Licensee Event Report (LER) 272/96-020. To resolve this condition, PSE&G committed to install relief valves on the Service Water System (SWS) cooling lines that supply the CFCU's. Installation of the relief valves was to be accomplished prior to the unit entering Mode 4. Subsequent to PSE&G's LER, the NRC issued Generic Letter 96-06 which required a formal evaluation and response by all operating plants to this and other safety concerns relating to maintaining containment integrity and cooling following I

design basis accidents.

Salem Unit 2 will be entering Mode 4 while work is in progress on planned modifications to address the concerns identified in NRC Generic Letter 96-06. Two CFCU's will be available for normal containment cooling while the unit is in Mode 4. Prior to entry into Mode 4, relief valves will be installed on the operating CFCU's as committed. Non-operating CFCU' s will be drained to preclude overpressurization in the unlikely event that a LOCA should occur while the unit is in Mode 4. The closed system boundary inside containment will also be maintained for the non-operating CFCU piping loops. Relief valves will be installed on the remaining CFCU' s prior to their return to service or the next entry to Mode 4.

If you have any questions concerning this matter, please feel free to contact us.

Sincerely,

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-- - ...... , David R. Powell

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.* Document Control Desk 2 LR-N97145 C Mr. H. Miller, Administrator - Region I U. S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. N. Olshan, Licensing Project Manager - Salem U. S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. Marschall (X24)

USNRC Senior Resident Inspector Mr. K. Tosch, Manager, IV Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, NJ 08625 l_