ML20215N162

Forwards Rev 1 to Impell Corp 01-0300-1395, Leak-Before- Break Evaluation of Reactor Coolant Loop, Final Rept. Analysis Revised to Comply w/NUREG-1061,Vol 3

ML20215N162
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	10/31/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20215N163	List: ML20215N162 ML20215N167
References
RTR-NUREG-1061 TAC-06596, TAC-6596, NUDOCS 8611040383
Download: ML20215N162 (2)

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Bart D. Weers Vce Presdyt October 31, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation Attn Mr. Steven A. Varga, Director PWR Project Directorate 3 Division of PWR Licensing-A U. S. Nuclear Regulatory Commission Washington DC 20555

Dear Mr. Varga:

Revised Leak-Before-Break Evaluation for Trojan

Reference:

1.

Letter to B. D. Withers, PGE, from S. A. Varga, NRC,

" Request for Additional Information Concerning the Leak-Before-Break Evaluation for Trojan Nuclear Plant",

Dated December 20, 1985 2.

Letter to E. J. Butcher, NRC, from B. D. Withers, PGE,

" Leak-Before-Break Evaluation for Trojan", Dated October 25, 1985 Attached for your review are three (3) copies of a revised leak-before-break evaluation of the Trojan reactor coolant loop piping.

The purpose of this revised submittal is to address previous questions (Reference 1) on our earlier submittal (Reference 2) and to demonstrate the validity of the leak-beforo-break methodology foe Trojan.

Yhe 1.cevious NRC request for additional information (Reference 1) asked that the report address the specific criteria provided in NUREG-1061, Vsit.re 3.

Attachment I responds to this by summarizing where the criteria are discussed in the attached report.

In addition, the request for additional information asked for a discusnion of materials properties.

This is also included in Attachment 1.

The leak-before-break analysis (Attachment 2) has been revised to comply with the guidance of NUREG-1061, Volume 3.

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Mr. Steven A. Varga Trojan Nuclear Plant Ocotber 31, 1986 Docket 50-344 License NPF-1 Page 2 We request that you' review this revised submittal. Note that this analysis is submitted in lieu of addressing outstanding NRC questions on PGE Topical Report PGE-1014. " Reactor Vessel Support Analysis for the Trojan Nuclear Plant", as discussed in Reference 2.

Sincerely, hy Bart Withers Vice President Nuclear Attachment Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission i

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