ML18096A656

Commits to Submitting Request for Amend to TSs 3/4.1.1.1 & 3/4.1.1.2,shutdown Margin & Tables 3.3-4,ESFAS Instrumentation Setpoints & 3.3-5,ESFs Response Times,Per Corrective Actions Described in LERs91-036 & 92-002-00

ML18096A656
Person / Time
Site:	Salem
Issue date:	04/22/1992
From:	Miltenberger S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N92052, NUDOCS 9205010201
Download: ML18096A656 (3)

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• Public Service Electric and Gas Company Steven E. Miltenberger Public Service Electric and Gas Company P.o: Box 236, Hancocks Bridge, NJ 08038 609-339-1100 Vice President and Chief Nuclear Officer APR 2 i i99Z N*LR-N9"2 052 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

SCHEDULE FOR SUBMITTING REQUEST FOR AMENDMENT SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSES DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Ref: 1) Licensee' Event Report 272/91-036, January 9, 1992, "Discovery of Nonconservative Auxiliary Feedwater Flow Rates For Steam Line Break Analyses. " '

2) LER 272/92-002-00, February 18, 1992, "Containment Spray Fluid Travel Time Greater Than Originally Assumed."

PSE&G hereby commits to submitting a request for amendment to the

.Salem Technical Specifications, consistent with the corrective actions described in the referenced LER's, within 30 days.

The request for amendment will affect the following Salem Unit L

No. 1 and 2 Technical Specifications:

3/4.1.1.1 and 3/4.1.1.2. SHUTDOWN MARGIN The minimum allowable shutdown margin will be increased to be consistent with Salem 1, Cycle 11 and Salem 2, Cycle 7 safety analyses. SHUTDOWN MARGIN in excess of the present Technical Specification limits has been credited in the Main steam Line Break (MSLB) safety analyses, to offset the effects of the increased auxiliary feedwater flow reported in reference 1.

Table 3.3-4, ESFAS Instrumentation Setpoints The containment pressure, high-high minimum setpoint and allowable value will be lowered. In order to help offset the effects of increased AFW flow (reference 1) and increased containment spray fluid travel time (reference 2), the setpoint was lowered during the Unit 2, sixth refueling outage. A design change package has been developed to lower the setpoint during the Unit 1, tenth refueling outage.

Docum2nt Control Desk _£\PR 2 2 1992 NLR-N92052 Table 3.3-5, Engineered Safety Features Response Times The maximum allowable containment spray response time will be lowered to account for the increased fluid travel time reported in reference 2. Service water response time from the containment pressure - high signal, with loss of offsite power, will be decreased to be consistent with containment fan cooler (CFC) response time requirements. The CFC response time will be moved from the containment pressure, high-high to the containment pressure, high signal, which is the CFC actuation signal. The maximum allowable CFC response time may be increased (Technical Specification response time is lower than the value assumed in the safety analyses).

The proposed Technical Specifications will reflect changes which have been implemented or are in progress. The changed parameters are under administrative control to ensure they are maintained consistent with the safety analysis assumptions. The containment pressure, high-high setpoint is controlled via the design change process. The response times and shutdown margin requirements are controlled via the procedure revision process. In each case, the change is conservative relative to the Technical Specification limits, and may therefore be implemented without prior NRC approval, in accordance with 10CFR50.59.

While the changes to shutdown margin and the containment pressure setpoint presently yield acceptable safety analysis results, PSE&G is in the process of evaluating design changes to reduce AFW flow, or other methods of improving containment pressure and temperature response following a postulated steam line break accident.

Sincerely,

Document Control Desk NLR-N92052

• _APR 2 z 199Z c Mr. J. c. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. K. Tosch, Chief Bureau of Nuclear Engineering Department of Environmental Protection CN 415 Trenton, New Jersey 08625