ML19210D026

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Notifies That Eddy Current Testing of Row 1 Tubes in All Four Steam Generators Will Be Completed & All Leaks Plugged During Outage.Tube Samples from Steam Generator D Will Be Removed During Next Refueling Outage
ML19210D026
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 11/16/1979
From: Broehl D
PORTLAND GENERAL ELECTRIC CO.
To: Engelken R
NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V)
References
NUDOCS 7911200435
Download: ML19210D026 (2)


Text

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Portland General BectricCompany Oc9ataJ Ercent Ass: star.t V.ce P'es; cent November 16, 1979 Trojan Nuclear Plant Docket 50-344 License NPF-1 Mr. R. H. Engelken, Director Nuclear Regulatory Commission Region V Suite 202, Walnut Creek Plaza 1990 N. California Blvd.

Walnut Creek, CA 94596

Dear Mr. Engelken:

Pursuant to discussions with the Nuclear Reactor Regulation Staff (Division of Operating Reactors), the following information supple-ments our letter of November 4, 1979 concerning leaking tubes it "A" and "D" steam generators at the Trojan Nuclear Plant. We will com-plete eddy current testing of row one tubes in all four steam gener-ators and plug all indications and/or identified lenkers during this outage.

If at any time, prior to removing tube samples as committed below, the steam generator tube leakage exceeds 150 gpd, the Trojan Nuclear Plant will be shut down and the steam generator tubes inspected. Should the location of the leaks be determined to be in the same area as the leaks presently identified in steam generators "A" and "D",

samples of tubes will be removed for further inspection and analysis prior to resumption of power. If the source of leakage is in locations other than near those presently identified, an evaluation will be made based on the particular circumstances. In any case, tube samples will be removed from steam generator "D" at the next refueling outage.

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Mr. R. H. Engelken November 16, 1979 Page Two This approach will allow us to resume operation of the Trojan Nuclear Plant with no compromise in safety and no relaxation in the conserva-tisms developed in our Plant accident analyses. The interest of the public can best be served by the above course of acticn.

Sincerely, m

,/ e c:

Mr. Lynn Frank, Director State of Oregon Department of Energy Mr. A. Schwencer, Chief Operating Reactors Branch #1 Division of Operating Reactors U. S. Nuclear Regulatory Commission

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