ML20059D097

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Forwards SER Accepting Util 880311,0401 & 1223 & 900319 & 0622 Responses to NRC Bulletin 88-002, Rapidly Propagating Fatigue Cracks in Steam Generator Tubes
ML20059D097
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 08/30/1990
From: Bevan R
Office of Nuclear Reactor Regulation
To: Cross J
PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20059D100 List:
References
IEB-88-002, IEB-88-2, TAC-67328, NUDOCS 9009060086
Download: ML20059D097 (2)


Text

.

August ~ 30, 1990 s.,

Docket No. 50-344' J

1 Mr. James E. Cross

.Vice President, Nuclear

- Portland General Electric Company 121 S.W. Salmon Street i

Portland, Oregon 97204

Dear Mr. Cross:

SUBJECT:

SAFETY EVALUATION OF LICENSEE RESPONSE TO NRC BULLETIN 88-02, l

" RAPIDLY PROPAGATING FATIGUE CRACKS IN STEAM GENERATOR TUBES" FORTROJAN(TAC-NO.67328) j 1.

L

.The NRC staff has u mpleted its evaluation of the Portland Genert Electric j

l Company (PGE) response to NRC Bulletin 88-02 for Trojan Nuclear P. ant. Our l'

evaluation included a review of your letters dated March 11, April 1, and '

I December 23, 1988, and letters dated March 19 and June 22, 1990, in response to the Bulletin. We find that the actions taken by PGE for Trojan fully-resolve:the issues' identified in the Bulletin, and are acceptable, A copy of the NRC staff Safety Evaluation on this issue is enclosed.

This o

L finding is subject to the adoption of administrative controls as described in the conclusion of the enclosed Safety Evaluation..This completes our review of activities performed in response to Bu11etin 88-02.

Sincerely, OriginalSigned By:

Roby B. Bevan, Project Manager Project Directorate V Division of Reactor Projects - III, IV, V and Special Projects Office of Nuclear Reactor Regulation

Enclosure:

As stated cc w/ enclosure:

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