ML18101B145

Transmits Response to NRC RAI Re Util 941011 Proposed Change to LCO 3.4.4.4, Pressurizer. Marked-up TS Pages Encl

ML18101B145
Person / Time
Site:	Salem
Issue date:	12/28/1995
From:	Dawn Powell Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18101B146	List: ML18101B145 ML18101B147
References
LCR-93-28, LR-N95250, NUDOCS 9601020235
Download: ML18101B145 (3)

Text

• PS~G Public Service Electric and Gas Company P.O. Box 236 . Hancocks Bridge, New Jersey 08038~0236 Nuclear Business Unit DEC 2 81995 LR-N95250 LCR 93-28 United States Nuclear Regulatory Commission Document Control Desk Washington, D.C. 20555 Gentlemen:

REQUEST FOR ADDITIONAL INFORMATION SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS. DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 This letter transmits Public Service Electric and Gas (PSE&G)

Company's response to the verbal request for additional information from Mr. L. Olshan, Licensing Project Manager .

. In our original submittal (Ref: NLR-N94149, dated October 11, 1994), PSE&G proposed a change to Limiting Condition for Operation (LCO) 3.4.4.4, "Pressurizer," for both Salem Units.

The submitted change read:

"The pressurizer shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (92% indicated level),

and at least two groups of pressurizer heaters each having a capacity of 150 KW and capable of being powered from an emergency power supply~"

As discussed with Mr. L. Olshan, Licensing Project Manager, the word "minimum" was inadvertently omitted from the submittal received by NRC. The proposed change should have read:

"The pressurizer shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (92% indicated level),

and at least two groups of pressurizer heaters each having a minimum capacity of 150 KW and capable of being powered from an emergency power supply."

Although our discussion of the proposed changes (Section II.A of our October 11, 1994 submittal) did not specifically describe the addition of the word "minimum", it stated, in part, "* .. The proposed change is consistent with NUREG 1431, Standard Technical Specifications Westinghouse Plants, issued in September 1992."

9601020235-95i228 PDR ADOCK 05000272 P PDR

.The power is in your hands. ~\\I 95-2168 REV. 6/94

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Document Control Desk

• DEC 2 8 1995 LR-N95250 NUREG 1431 - LCO 3.4.9 states, in part, that: " ... the pressurizer heaters be OPERABLE with a capacity equal to or greater than ... " The bases for this wording (and value) is to establish the minimum heater capacity required to maintain Reactor Coolant System (RCS) pressure (without Reactor Coolant Pumps (RCP) running) when accounting for heat losses through the pressurizer insulation. Accordingly, it was PSE&G's intent to use the word "minimum" to reflect the bases requirements.

As discussed with Mr. L. Olshan and within the context of this LCO, the word minimum and the equal to or greater than sign (~)

are equivalent terms. Therefore, to be truly consistent with NUREG 1431, PSE&G requests to substitute the equal to or greater than sign for the word minimum, such that the LCO should read:

"The pressurizer shall be OPERABLE with a water volume of less than or equal to 1650 cubic feet (92% indicated level), and at least two groups of pressurizer heaters each having a capacity of ~ 150 KW and capable of being powered from an emergency power supply."

New marked-up Technical Specification pages are enclosed. PSE&G believes that the original Determination of No Significant Hazards Consideration is still valid.

Should you have any additional questions, please do not hesitate to contact me.

Sincerely, David R. Powell Manager - Licensing & Regulation

• -r .

Document Control Desk

• DEC 2 8 1995 LR-N95250 C Mr. L. Olshan, Licensing Project Manager U.S. Nuclear Regulatory Commission One White Flint North 11555 Rockville Pike Mail Stop 14E21 Rockville, MD 20852 Mr. C. S. Marschall (S09)

USNRC Senior Resident Inspector Mr. T. T. Martin, Administrator - Region I U.S. Nuclear Regulatory Commission 475 Allendale Road King of Prussia, PA 19406 Mr. Kent Tosch, Manager, VI Bureau of Nuclear Engineering 33 Arctic Parkway CN 415 Trenton, New Jersey 08625