ML20203C783

Forwards Proprietary WCAP-10835, Rept of DS-416 Reactor Trip Breaker... & WCAP-10852, Rept of DB-50 Reactor Trip Breaker..., in Response to Request for Info to Aid in Review Re Generic Ltr 83-28.W/o Encls

ML20203C783
Person / Time
Site:	McGuire
Issue date:	12/09/1985
From:	Butterfield L COMMONWEALTH EDISON CO., WESTINGHOUSE OPERATING PLANTS OWNERS GROUP
To:	Wright R Office of Nuclear Reactor Regulation
Shared Package
ML20203C770	List: ML20203C766 ML20203C783
References
GL-83-28, OG-167, NUDOCS 8604210239
Download: ML20203C783 (2)

Text

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Commonwealth Edison 4 72 West Adams Street. Chicago, ethnois

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• 3 Address Reply to: Post Office Box 767

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(,/ Chicago, Illinois 60690 OG-167 December 9,1985 Mr. Robert J. Wright Equipeont Qualification Branch, P-234 Nuclear Regulatory Commission 7920 Norfolk Avenue Bethesda, M 20014

Subject:

Westinghouse Owners Group (W0G)

Reactor Trip Breaker Programs Description and Submittal of RTB Trip Attachment Life Cycle Test Reports

Dear Mr. Wright:

In response to your request for information to aid in your review of Generic Letter 83-28 submittals from licensees who are members of the Westinghouse Owners Group, we are forwarding one copy each of the following topical reports covering recent reactor trip switchgear component testing conducted by the WOG:

WCAP-10835, " Report of the DS-416 Reactor Trip Breaker Undervoltage and Shunt Trip Attachments Life Cycle Tests" (Proprietary)

WCAP-10852, " Report of the 05-50 Reactor Trip Breaker Shunt and Under-voltage Trip Attachments Life Cycle Tests" (Proprietary)

Please note that these NCAP reports contain Westinghouse proprietary information - commercial and financial information which we consider privileged or confidential. It is of a type customarily held in confidence by Westinghouse and is customarily not disclosed to the general public.

This information is being furnished in accordance with your request and pursuant to the Commission's general powers under Section 161 of the Atomic Energy Act of 1954, as amended. Accordingly, it is requested that this Westinghouse proprietary information be handled on a confidential basis and be withheld from public disclosure.

This material is for your internal use only and may be used only for the purpose for which it is submitted. It should not be otherwise used, disclosed, duplicated or disseminated, in whole or in part, to any other person or organization outside the NRC without the prior written approval of Westinghouse and the Westinghouse Owners Group.

9604210239 060414 9 DR ADOCK 050 es.ne s a

0G-167

-( Mr. Robert J. Wright December 9,1985 Correspondence with respect to the application for withholding should reference AW-85-083, and should be addressed to R. A. Wiesemann, Manager of Regulatory and Legislative Affairs, Westinghouse Electric Corporation, P.

O. Fox 355, Pittsburgh, Pennsylvania 15230-0355.

As we have discussed previously with the Staff, it was intended, in undertaking the reactor trip breaker life cycle test program, to go beyond addressing the immediate issues of_ Generic Letter 83-28. At the same time, the WOG's Technical Specification Optimiration Program (WOG-TCPS),

WCAP-10271, included a treatment of unavailability of the reactor trip breakers as a basis for proposed technical specification changes.

However, as was agreed in our meeting of January 9,1985 (Refer: 0G-146, Feb. 27,1985) the reactor trip breakers were omitted from the SER for WOG-T0PS (Thomas to Sheppard, February 21, 1985) because of questlons stemming from the Salem incident.

Furthar work on the reactor trip breakers in regard to WOG-TOPS was deferred until the W0G could undertake a comprehensive program for that purpont. Such a program was mentioned in our letter of June 25, 1985, 0G-151, t,ritten in response to Generic Letter 85-09. Therein the WOG expressed the intention to develop a rigorous basis for reactor trip breaker technical specifications incorporating the life cycle test data, past reliability studies, and the WOG RTS maintenance programs.

The WOG elected to undertake such a program at their September 1985 meeting. The program that was approved will determine a basis for optimal reactor trip and bypass breaker test and maintenance intervals. The objectives of this program are to establish a reactor trip circuit breaker database and to develop a reliability model of the trip breaker which can be used to determine reliability-centered test and maintenance intervals.

This info would be used to support appropriate plant toch spec and maintenance program changes. It is scheduled to be completed by September j of 1986, and will be submitted to NRC for review and approval at that time, if you have any questions regarding this material please contact Mr. Tom Lordi on 412/236-6665, or Mr. Mark Burzynski 615/365-8863, who is Chairman of the Technical Specifications Subcommittee of the WOG. Thank you.

Very truly yours, I h I L. D. Butterfield, Chairman i

Westinghouse Owners Group Enclosure cc: WOG Rep Tech Spec S/C N. Thompson T. Spels

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