ML20129H756

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Forwards Safety Evaluation Supporting Licensee 831107 & 841228 Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Re Reactor Trip Sys Reliability,Provided Corrective Action Taken If Higher than Normal Values Observed in Trip Force
ML20129H756
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 05/16/1985
From: John Miller
Office of Nuclear Reactor Regulation
To: Fay C
WISCONSIN ELECTRIC POWER CO.
Shared Package
ML20129H761 List:
References
GL-83-28, TAC-53140, TAC-53141, NUDOCS 8506070654
Download: ML20129H756 (1)


Text

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.7 May 16; 1985 DISTRIBUTION:

Docket Nos. 50-266 MET 7TEF ACRS+10 and 50-301 NRC PDR Gray File L PDR VNoonan A

ORB #3 RDG HThompson Mr. C. W. Fay, Vice President OELD Nuclear Power Department EJordan Wisconsin Electric Power Company BGrimes 231 West' Michigan Street Room 308 JPartlow Milwaukee, Wisconsin 53201 TColburn PMKreutzer

Dear Mr. Fay:

SUBJECT:

GENERIC LETTER 83-28 ITEMS 4.2.1 AND 4.2.2 - PREVENTATIVE MAINTENANCE PROGRAM FOR REACTOR TRIP BREAKERS / MAINTENANCE AND TRENDING (MPA B-81)

The staff has reviewed your responses of November 7,1983 and December 28, 1984 on the subject items. Based on our review, the staff finds that your program for preventative maintenance of the reactor trip breakers at Point Beach Units 1 and 2 is acceptable provided your maintenance interval does not exceed 12 months and your current practices with regard to measurement of undervoltage trip attachment dropout voltage, trip force, breaker response time and breaker insulation resistance are maintained. The details of our review are contained in the enclosed Safety Evaluation. Should you have any questions, please contact your NRC project manager, T. G. Colburn, at (301) 492-4709.

Sincerely, Original signed by:

James R. Miller, Chief Operating Reactors Branch #3 Division of Licensing

Enclosure:

Safety Evaluation cc w/ enclosure See next page 8506070654 850516 PDR ADOCK 05000266 P

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