ML20134M984

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Forwards Safety Evaluation Re Util 831105,850118 & 0719 Responses to Generic Ltr 83-28,Items 4.2.1 & 4.2.2 Concerning Reactor Trip Sys Reliability.Responses Acceptable
ML20134M984
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 08/27/1985
From: Butcher E
Office of Nuclear Reactor Regulation
To: Withers B
PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20134M987 List:
References
GL-83-28, T6AC-53159, TAC-53159, NUDOCS 8509040366
Download: ML20134M984 (2)


Text

_.

August 27, 1985 Docket No. 50-344 Mr. Bart D. Withers Vice President Nuclear Portland General Electric Company 121 S.W. Salmon Street Portland, Oregon 97204

Dear Mr. Withers:

SUBJECT:

GENERIC LETTER 83-28 ITEMS 4.2.1 AND 4.2.2 SAFETY EVALUATION The staff has completed its review of your response to Generic Letter 83-28, items 4.2.1 and 4.2.2, Preventative Maintenance Program for Reactor Trip Breakers / Maintenance and Trending. The staff's safety evaluation (SE) is enclosed.

The staff finds that PGE's revised preventative maintenance program for reactor trip breakers contains all the necessary items recommended for maintenance by the manufacturer and the IEEE Standard 279-1971. PGE has also committed to performing the appropriate trend analysis. Based on our review, the staff concludes that PGE's positions on items 4.2.1 and 4.2.2 are acceptable.

The NRC staff was assisted in its evaluation of these issues by Idaho National Engineering Laboratory under contract to the NRC.

Sincerely, Edward J. Butcher, Acting Chief Operating Reactors Branch No. 3 Division of Licensing

Enclosure:

Safety Evaluation cc w/ enclosure:

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. William T. Dixon Oregon Department of Energy Labor and Industries Building Room 111

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