ML20198S019

Forwards Documentation from Bechtel Corp Re Review & Evaluation of Final Results of RCS Thermal Expansion Analysis & Hot Leg Shell Analysis Performed by Impell Corp. Encl Info Should Close Out Concerns in

ML20198S019
Person / Time
Site:	Trojan File:Portland General Electric icon.png
Issue date:	06/06/1986
From:	Withers B PORTLAND GENERAL ELECTRIC CO.
To:	Varga S Office of Nuclear Reactor Regulation
Shared Package
ML20198S025	List: ML20198S019 ML20198S051
References
TAC-61405, NUDOCS 8606100295
Download: ML20198S019 (3)

Text

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-E [htt D WWirs Vce Presad June 6, 1986 Trojan Nuclear Plant Docket 50-344 License NPF-1 Director of Nuclear Reactor Regulation Attn: Mr. Steven A. Varga Director PWR-A Project Directorate No. 3 U.S. Nuclear Regulatory Commission Washington DC 20555

Dear Sir:

Reactor Coolant System (RCS) Thermal Expansion Issue In response to your letter of June 5, 1986, attached is documentation from the Bechtel Corporation discussing their review and evaluation of the final results of the RCS thermal expansion analysis and hot les shell analysis performed by our consultant, the Impell Corporation. In addition, the documents provide affirmation by Bechtel of the general conclusions of the analysis. This information is considered to be sufficient to permit your review of this issue and permit the Trojan Nuclear Plant to return to power operation.

Attachment A to this letter is a copy of the May 23, 1986 interim report by Bechtel Corporation. It describes their evaluation of the Impell analysis as of that date. It should be noted that several questions were raised in that report that subsequently have been resolved and incorporated by Impell in their analyses. The resolution of these concerns is addressed in the letter from Bechtel Corporation provided as Attachment B.

Attachment C is a letter from Bechtel documenting their review and conclusions concerning the Temporary Plant Test, TPT 166, describing the RCS heat-up monitoring program.

Bechtel has been requested by PCE to look into several additional areas other than just the analyses performed by Impell Corporation. These areas include results of the monitoring program, pipe whip restraint operability, 8606100295 860606 PDR ADOCKOSOOg4 121 S W Sirrcn St eet. Paar>J Oreyn 97204 VP*b I

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Mr. Steven A. Varga June 6, 1986 Page 2 and snubber reliability. A final Bechtel report addressing all of these areas is not expected for some time. However, the information provided in this letter should be adequate to close out the concerns raised in your June 5 latter and permit the Trojan Nuclear Plant to return to power operation.

Sincerely, e a-_;

Bart D. Withers Vice President Nuclear

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Attachments c: Mr. John B. Martin Regional Administrator, Region V U.S. Nuclear Regulatory Commission Mr. Lynn Frank, Director State of Oregon Department of Energy 4

P k'TrojanNuclearPlant Mr. Steven A. Varga June 6, 1986 4 Docket 50-344 License NPF-1 Attachment A

. Bechtel Power Corporation Engr 5ee'5-Con 11'ucto 1 Fdiv Bese Street San Franersco. Californe Ma# A00ress- P O Bos 3965 San 8rancesco CA W119 In reply please reference:

Doc. Control No. IC24570 BP- 12476 Mr. R. L. Steele Manager, Nuclear Plant Engineering Portland General Electric Company 121 S. W. Salmon Street Portland, Oregon 97204 Attention: R. J. Wehage-

Subject:

Portland General Electric Company Trojan Nuclear Plant - Job 11760-176 Peer Review of Reactor Coolant Loop Movements

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Gentlemen:

Attached are 10 copies of the Interim Report of the Independent Review of Trojan Nuclear Plant Reactor Coolant Loop Evaluation Program. This version covers the technical aspects of the situation to date. We intend to finalize the report after review of the Impell detailed evaluation report and after implementation of corrective actions by PGE. .

If there are questions on the report, please do not hesitate to call me.

Very truly yours, R. W. r osse Project Engineer

Attachment:

Interim Report cc: G. Zi=mer=an - PGr W. Sak - I=pell TLS/47

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