IR 05000344/1987025
| ML20215B702 | |
| Person / Time | |
|---|---|
| Site: | Trojan File:Portland General Electric icon.png |
| Issue date: | 06/11/1987 |
| From: | Kirsch D NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION V) |
| To: | Cockfield D PORTLAND GENERAL ELECTRIC CO. |
| References | |
| NUDOCS 8706170413 | |
| Download: ML20215B702 (2) | |
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June 11, 1987
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Docket Number'50-344 Portland General _ Electric Company 121 S.~W. Salmon Street-
Portland, Oregon 97204 Attention: Mr. D. W. Cockfield Vice ~ President Nuclear Gentlemen:
Subject: Management Meeting This refers to the management meeting held with Mr. Cockfield and members of your staff at the. Region V office on June 5, 1987. A number of topics were discussed in the meeting as summarized in the enclosed inspection report. The discussed topics-included your root cause analyses of several engineering problems-and.related operational safety concerns.
To summarize, your root cause. analyses appear generally to be thorough and technically sound. However, the fact that the feedwater restraint failure has _not been linked to a definite cause is a significant concern.- We understand that you are consulting. experts in the field of water hammer and
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feed / steam systems to assist in your identification of the root cause. We
'also understand.that you are doing examinations of feedwater and auxiliary feedwater check valves.in response to our meeting.
In the-area related to operational safety, the failure of operators to stop sluicing activities in the face of many indications that something was wrong is a significant. concern. Specifically, the operator performance at this juncture seriously draws into question their understanding of i
fundamentals of nuclear plant operations. We understand that you have been
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discussing this issue with plant personnel to instill appropriate understandings.
We encourage you to examine closely and place priority on these concerns.
Additionally, we. understand that you will provide us with your actions and analyses in regard to these topics on Friday, June 12, 1987. If you have any questions, do not hesitate to contact us.
i Dennis F. Kirsch, Director
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Division of Reactor Safety and Projects Enclosure:
Inspection Report Number 50-344/87-25 cc w/ enclosure:
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