ML20211D374
| ML20211D374 | |
| Person / Time | |
|---|---|
| Site: | McGuire, Mcguire  |
| Issue date: | 06/10/1986 |
| From: | Youngblood B Office of Nuclear Reactor Regulation |
| To: | Tucker H DUKE POWER CO. |
| References | |
| GL-85-09, GL-85-9, NUDOCS 8606120832 | |
| Download: ML20211D374 (4) | |
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10 JUN 1985 4
Docket Nos.: 50-369 and 50-370 Mr. H. B. Tucker Vice President Nuclear Production Department Duke Power Comnany 422 South Church Street f,harlotte, Ncrth Carolina 28242
Dear Mr. Tucker:
SUBJECT:
TECHNICAL SPEC!FICATIONS REGARDING REACTOR TRIP BYPASS BREAKER -
MCGUIRE NUCLEAR STATION, UNITS 1 AND 2 i
By letter dated Decernbar 7,1905, you proposed changes to the McGuire Technica'l Specificaticns pertaining to Rebctor Trip System Instrumentation and Surveillance in response to Generic l.etter 85-09. Generic Letter 85-09 concludsd that TGchnical Specification changes should be proposed by licensees to e'/plicitly require independent testing of the undervoltage and shunt trip attachtaelts of the reactor trip treakers tJuring power operation, testing of bypass breakert prior t:3 use,, and independent testing of the control room manual twitch contacte rid wiring during each refueling outage.
We have reviewed your proposed chah$es and find them to be incomplete, and, thtrofore, unacceptable. Your preposal includes no provision for (1) testing of the Reactor Trip Bypass Brea'xer prior to each time it is put into service, and (2) verifying the operability of the Bypass Breaker trip circuits each refuelin; outage.
Your letter states that you hae declined to provide Technical Specifications l
for these items on the basis that there is no significant benefit to be expected from inclusion of Bypass Trip Braaker testing in the Technical l
l Specifications. We find this tasis unacceptable. When a reactor trip breaker is tested, the reactor trip bypass breaker is put into service as a backup.
l The Generic Letter E5-09 Technical Specifications specify a manual test of the l
bypass breaker prior to putting it into service. This testing is a simple procedure and it is prudent to do this test before relying on this breaker as a backup to the remaining reactor trip breaker, Although you state that i
probabilistic risk analyses show that te_ sting of the breaker has an l
insignificant effect en the overall reliability, no claim is made that the reliability is decreased or that the bypass breaker is not safety related.
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.$ Accordingly, we find that' these tests should be made as specified in Generic Letter 85-09, and request that you submit for staff review proposed Technical Specifications for this purpose in accordance with Generic Letter 85-09.
Sincerely,
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W fri B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A cc: See Next Page T
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Mr. H. B. Tucker Duke Power Company McGuire Nuclear Station cc:
Mr. A. Carr Dr. John M. Barry Duke Power Company Department of Environmental Health P. O. Box 33189 Mecklenburg County 422 South Church Street 1200 Blythe Boulevard Charlotte, North Carolina 28242 Charlotte, North Carolina 28203 s
Mr. F. J. Twogood County Manager of Mecklenburg County Power Systems Division 720 East Fourth Street Westinghouse Electric Corp.
Charlotte, North Carolina 28202 P. O. Box 355 Pittsburgh, Pennsylvania 15230 Chairman, North Carolina Utilities Comission Mr. Robert Gill Dobbs Building Duke Power Company 430 North Salisbury Street Nuclear Production Department Raleigh, North Carolina 27602 P. O. Box 33189 Charlotte, North Carolina 28242 Mr. Dayne H. Brown, Chief Radiation Protection Branch J. Michael McGarry, III, Esq.
Division of Facility Services I
Bishop, Liberman, Cook, Purcell Department of Human Resources and Reynolds P.O. Box 12200 1200 Seventeenth Street, N.W.
Raleigh, North Carolina 27605 Washington, D. C.
20036 Senior Resident Inspector c/o U.S. Nuclear Regulatory Comission Route 4, Box 529 l
Hunterville, North Carolina 28078 t
Regional Administrator, Region II U.S. Nuclear Regulatory Commission, 101 Marietta Street, N.W., Suite 2900 Atlanta, Georgia 30323 L. L. Williams Operating Plants Projects Regional Manager Westinghouse Electric Corporation - R&D 701 P. O. Box.'728 Pittsburgh, Pennsylvania 15230 v
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m 10 JUN 1966 Accordingly, we find that these tests should be made as specified in Generic Letter 85-09, and request that you submit for staff review proposed Technical Specifications for this purpose in accordance with Generic Letter 85-09.
Sincerely,\\6\\
B. J. Youngblood, Director PWR Project Directorate #4 Division of PWR Licensing-A cc: See Next Page DISTRIBUTION:
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