ML18095A578

Forwards Addl Info Re 900710 Amend to License Change Request 89-03

ML18095A578
Person / Time
Site:	Salem
Issue date:	11/06/1990
From:	Labruna S Public Service Enterprise Group
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
NUDOCS 9011150122
Download: ML18095A578 (4)

Text

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

.~.NOV O6 1990

. NLR-N90208 United states Nuclea~ Re~i~#ory Commission Document control Desk Washington; DC 20555 Gentlemen:

ADDITIONAL INFORMATION LCR 89-03 SALEM GENERATING STATION UNIT NOS. 1 AND 2 FACILITY OPERATING LICENSE NOS DPR-70 AND DPR-75 DOCKET NOS. 50-272 AND 50-311 Public Service Electric & Gas Company (PSE&G) hereby submits additional information requested concerning License Change Request (LCR) 89-03, submitted September 13, 1989, amended by letter dated July 10, 1990.

This letter addresses the Significant Hazards Considerations for those changes instituted by the July 10, 1990 letter.

Attachment 1 is a copy of the changes submitted in the July 10, 1990 letter. Attachment 2 contains the revised sections of the Significant Hazards Consideration.

Should there be any questions with regard to this submittal, please do not hesitate to contact us.

Sincerely, p;{;~

Attachments

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Document Control Desk 2 NOV o 6 1990 NLR-N90208 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

NLR-N90208 ATTACHMENT 1 This attachment contains the changes submitted in the letter dated July 10, 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:

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a; . A reactor trip and .a1i:.-.. associated actions will. be initiated when the specific 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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NLR-N90208

. *ATTACHMENT 2 This attachment addresses the Significant Hazards Consideration for those items that have been changed by Attachment 1.

The proposed changes to the Technical Specifications do not involve a significant hazards consideration because operation of Salem Units 1 and 2 in accordance with these changes would not:

A. Involve a significant increase in the probability or consequences of an accident previously evaluated.

Item 1** Changing the required number of operable channels from four to three provides necessary flexibility in operations. Three channels are sufficient to ensure the following: 1) a reactor trip and all associated actions will be initiated when required, 2) specific coincidence logic is maintained, and 3) sufficient redundancy is maintained to permit a channel to be out of service for testing or maintenance. Operation with a minimum of three channels has been previously reviewed and approved for a four loop plant via the Westinghouse Standard Technical Specifications, Rev. 4 (NUREG-0452). This change will not increase the probability or consequences of a previously evaluated accident.

Item 2 This change is being withdrawn and therefore will not increase the probability or consequences of a previously evaluated accident.

Item 5 Extending the Allowed Outage Time (AOT) from one 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. Operation with an AOT of two hours has been previously reviewed and approved for a four loop plant via the Westinghouse Standard Technical Specifications, Rev. 4 (NUREG-0452).

This change will not increase the probability or consequences of a previously evaluated accident.

There are no other changes to the Significant Hazards Consideration as a result of the PSE&G letter, dated July 10, 1990.