ML18102A394

Provides Suppl to Request for Change to Tech Specs Table 3.3-3 Pertaining to ESFAS Instrumentation

ML18102A394
Person / Time
Site:	Salem
Issue date:	09/12/1996
From:	Storz L Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18102A395	List: ML18102A394 ML18102A398
References
LR-N96244, NUDOCS 9609190188
Download: ML18102A394 (3)

Text

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Public Service Electric and Gas Company Louis F. Storz Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-5700 Senior Vice President - Nuclear Operations SEP 1 2 1996 LR-N96244 United states Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 SUPPLEMENT TO REQUEST FOR CHANGE TO TECHNICAL SPECIFICATIONS ENGINEERED SAFETY FEATURES INTERLOCK P-12 SALEM GENERATING STATION NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Gentlemen:

By letter LR-N96188, dated July 12, 1996, Public Service Electric

& Gas Company (PSE&G) submitted a request to amend Technical Specification (TS) Table 3.3-3 pertaining to Salem Generating Station's Engineered Safety Feature Actuation System (ESFAS)

Instrumentation. This letter provides a supplement to that request.

The requested change revises the setpoints for the interlock designated P-12 to provide consistency between the various instrumentation TSs, the system design basis, and the ESFAS channel setpoints in the plants. In the submittal, PSE&G requested that the TS be revised to reflect a setpoint of 543°F.

The words "increasing from" and "decreasing from" that value were also added to denote that the number of channels needed to meet the trip and reset condition of P-12 was dependent upon the direction of Reactor Coolant system average temperature (Tavg).

PSE&G has revised the proposed TS wording, (refer to the attached TS pages), to more clearly denote the setpoint of P-12. The revised wording will alleviate potential misinterpretation between the setpoint and the Tavg direction.

A review of the previously submitted evaluation in accordance with the three standards set forth in 10CFRS0.92 has been performed and concluded that no change is necessary as a result of the revised pages and the conclusion of no significant hazards ,

consideration remains valid.  :\Q\

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SEP 12 1996 Document control Desk 2 LR-N96244 Should you have any questions regarding this supplement, we will be pleased to discuss them with you.

Sincerely, Attachment c Mr. H. J. Miller, Administrator - Region I U. s. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. L. 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

REF: LR-N96244 STATE OF NEW JERSEY )

) SS.

COUNTY OF SALEM )

L. F. Storz, being duly sworn according to law deposes and says:

I am Senior Vice President - Nuclear Operations of Public Service Electric and Gas Company, and as such, I find the matters set forth in the above referenced le~ter, concerning Salem Generating station, Units 1 and 2, are true to the best of my knowledge, information and belief.

KIMBfRl y JO BROWN NOTARY. P~BLIC OF NEW JERSEY My Commission expires on ~~~~~My~C~o1~nn~11s~s1~on~E~xpwire~s~ap~iihl2~1 .~1~88~81--~-