ML20135A623

Responds to Generic Ltr 85-09.On-line Testing of Reactor Trip Breakers Not Permissible.Breakers Redundant in Series & Opening of Either Breaker Would Result in Scram.Discussion of Reactor Trip Sys Encl.Tech Spec Changes Unwarranted

ML20135A623
Person / Time
Site:	Yankee Rowe
Issue date:	09/04/1985
From:	Papanic G YANKEE ATOMIC ELECTRIC CO.
To:	Zwolinski J Office of Nuclear Reactor Regulation
References
FYR-85-94, GL-85-09, GL-85-9, NUDOCS 8509100220
Download: ML20135A623 (2)

Text

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Tepho"e (6 ") "- 'o YANKEE ATOMIC ELECTRIC COMPANY TWX 710-380-7619 y,- (

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1671 Worcester Road, Framingham, Massachusetts 01701 2.C.2.1 FYR 85-94

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September 4, 1985 United States Nuclear Regulatory Commission Washington, DC 20555 Attention: Mr. John A. Zwolinski, Chief Operating Reactors Branch No. 5 Division of Licensing

References:

(a) License No. DPR-3 (Docket No. 50-29)

(b) USNRC Letter to All Licensees, dated May 23, 1985 (Generic Letter 85-09) (NYR 85-92)

(c) YAEC Letter to USNRC, dated January 13, 1984 (FYR 84-09)

(d) YAEC Letter to USNRC, dated November 5, 1983 (FYR 83-04)

Subject:

Response to Generic Letter 85-09

Dear Sir:

Reference (b) requested licensees to submit proposed Technical Specification changes to require independent testing of the undervoltage and shunt trip attachments during power operations and independent testing of the Control Room manual switch contacts during each refueling outage. In response to Reference (b), on-line testing of the reactor trip breakers is not permissible at Yankee since the breakers are redundant in series and the opening of either breaker would result in a plant scram.

Reference (c) provides a detailed discussion of the Reactor Trip System.

This reference also included an evaluation of the existing maintenance and inspection programs for these breakers as well as a system reliability analysis based on PRA. These evaluations have led to the following conclusions: (1) that modifications to permit on-line testing would not enhance the excellent 25-year reliability of the Yankee Reactor Trip System, and (2) that the present Reactor Trip System and supportive maintenance and inspection programs are an acceptable alternative to on-line testing.

Based upon the above, it is Yankee's position that changes to the Technical Specifications as requested by Reference (b) are neither warranted no required for the Yankee plant.

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B509100220 850904 i PDR ADOCK 05000029 4 P PDR

7-e4e 9 United States Nuclear Regulatory Commission September 4, 1985 Attention: Mr. John A. Zwolinski Page 2 We trust this information is satisfactory; however, if you have any further questions, please contact us.

Very truly yours, YANKEE ATOMIC ELECTRIC COMPANY l d G. Papanic, Jr.

Senior Project Engineer - Licensing GP/dps.

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