ML18095A345

Forwards Addl Info Re License Change Request 89-03 Re Reactor Trip Sys Instrumentation

ML18095A345
Person / Time
Site:	Salem
Issue date:	07/10/1990
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NLR-N90122, NUDOCS 9007170186
Download: ML18095A345 (3)

Text

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, ' Public Service Electric and Gas Company Stanley LaBruna Public Service Electric and Gas Company P.O. Box 236, Hancocks Bridge, NJ 08038 609-339-4800 Vice President - Nuclear Operations JUL 1 0 1990 NLR-N90122 United States Nuclear Regulatory Commission Document Control Desk Washington, DC 20555 Gentlemen:

REACTOR TRIP SYSTEM INSTRUMENTATION REQUEST FOR ADDITIONAL INFORMATION SALEM GENERATING STATIONS UNITS 1 AND 2 DOCKET NOS. 50-272 AND 50-311 Public Service Electric and Gas (PSE&G) hereby provides the additional information requested in your letter of March 28, 1990, concerning LCR 89-03.

Attachment 1 addresses those items identified in your request for additional information.

Should you have any questions regarding this transmittal, please feel free to contact us.

sincerely, Attachment 9Cl071 70 l. :::::6 90071() _____________ \

• r-.1R ADOCK 05000272 P

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V-Document Control Desk 2 ~4Ut 1 0 1990 NLR-N90122 C Mr. J. C. Stone Licensing Project Manager Mr. T. Johnson Senior Resident Inspector Mr. T. Martin, Administrator Region I Mr. Kent Tosch, Chief New Jersey Department of Environmental Protection Division of Environmental Quality Bureau of Nuclear Engineering CN 415 Trenton, NJ 08625

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\I-NLR-N90122 ATTACHMENT This attachment addresses each specific item identified in NRC letter, dated March 28, 1990.

Item 1 - Reactor Trip System Instrumentation Table 3.3-1, Functional Units 16 and 17 A reduction from 4 to 3 in the minimum number of Reactor Coolant Pump Undervoltage and Underfrequency channels will not reduce the capability of the function to provide the required protection. Three channels are sufficient to ensure the following:

a. A reactor trip and all associated actions will be initiated when the specified parameter reaches its setpoint.

b. The specific coincidence logic is maintained.

c. Sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance.

This change is in agreement with Westinghouse Standard Technical Specifications (NUREG-0452).

Item 2 - Reactor Trip System Instrumentation -

Table 3.3-1, Functional Units 1, 5, and 6 Table 4.3-1, Functional Units 5, 21, and 22 PSE&G withdraws its request to change the mode requirements for the listed functional units. The submitted change will not provide any additional guidance to the operator.

Item 5 - Engineered Safety Feature Actuation System (ESFAS)

Table 3.3-3, Action 20 The proposed relaxation of the allowed outage time (AOT) for testing from one hour to two hours is bounded by the analysis of WCAP-10272-A, Supplement 2, Revision 1, "Evaluation of Surveillance Frequencies and Out of Service Times for the Engineered Safety Features Actuation System."

This WCAP provides the analysis and justification for increasing the AOT from two hours to four hours for testing.

Because the Salem proposal would increase the AOT to two hours, the increases in core damage frequency and man-rem exposure at Salem would be less than those stated in the WCAP.

This change is in agreement with Westinghouse Standard Technical Specifications (NUREG-0452).

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