ML20058D090

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Forwards Safety Evaluation Re Degradation of RCS Thermal Sleeves.Resumption of Power Operation Scheduled for 820815. Timely Review of Info Requested
ML20058D090
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 07/22/1982
From: Withers B
PORTLAND GENERAL ELECTRIC CO.
To: Clark R
Office of Nuclear Reactor Regulation
Shared Package
ML20058D094 List:
References
TAC-48518, NUDOCS 8207270025
Download: ML20058D090 (1)


Text

.

s Portland General Electric ('ompany July 22, 1982 v e % rt Trojan Nuclect Plant r

wa,s Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation ATTN:

Mr. Robert A. Clark, Chief Operating Reactors Branch No. 3 Division of Licensing U. S. Nuclear Regulatory Commission Washington, DC 20555

Dear Mr. Clark:

Degradation of RCS Thermal Sleeves The Portland General Electric Company previously informed you of thermal sleeve degradation in certain piping nozzles of the Trojan Reactor Coolant System.

Mr. D. J. Broehl's letter of July 9,1982 described our experience with degraded thermal sleeves and our corrective action.

A safety evaluation justifying Trojan'c return to power operation was included.

This letter is to provide additional information in support of our safety evaluation as requested verbally by the NRC staff. Attachment A provides analytical details supplied by Westinghouse to support the conclusions contained in the safety evaluation. Attachment B describes the results of a baseline inspection of the RCS nozzles performed by ultrasonic testing methods.

We are proceeding toward our planned resumption of power operation on August 15, 1982. We request a timely review of the attached reports to support this schedule.

Sincerel,

f2' Bart D. Withers 8207270025 820722 Vice President PDR ADOCK 0",000344 Nuclear P

PDR Attachments 00I c:

Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. R. H. Engelken U. S. huclear Regulatory Commission Institute cf Nuclear Power Operations 121 SW syrmn Swt. Pomnt Orcgan 97204