ML20126L208

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Forwards Safety Evaluation Re Environ Qualification of safety-related Electrical Equipment.Evaluation Based on Util 800307,0425,0519,0905 & 810113 Submittals
ML20126L208
Person / Time
Site: Trojan File:Portland General Electric icon.png
Issue date: 05/27/1981
From: Clark R
Office of Nuclear Reactor Regulation
To: Withers B
PORTLAND GENERAL ELECTRIC CO.
Shared Package
ML20126L210 List:
References
IEB-79-01B, IEB-79-1B, TAC-06325, TAC-42502, TAC-6325, NUDOCS 8106010749
Download: ML20126L208 (3)


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Ur4tTED STATES y

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,,,,3 Mr. Bart D. Withers 49I

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121 S. W. Salmon Street Portland, Oregon 97204

SUBJECT:

ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE: TROJAN NUCLEAR PLANT, LICENSE N0. NPF-1 Reference (a) - Order for Modification of License Concerning the Environmental Qualification of Safety-Related Electrical Equipment dated October 24, 1980.

Dear Mr. Withers:

This letter transmits the Safety Evaluation for the Environmental Qualification of Safety-Related Electrical Equipment at your facility. This evaluation was based on your submittals dated March 7, April 25, May 19, and September 5,1980 and January 13, 1981. Our letter of March 26, 1981, which forwarded

'our preliminary results, indicated that an item-by-item re-evaluation would be required at a later date.

This safety evaluation identifies the specific-information required by the staff and the actions, on your part, necessary to comply with Reference (ai. We request that you provide the information identified in sections 3 and 4 of this Safety Evaluation to us within 90 days.

This safety eval.uation addresses only the safety-related electrical equipment exposed to o harsh environment resulting from an accident (i.e., the IEB 79-01B review).

Reference (a) requires that all safety-related electrical equipnent t.9 qualified by June 30, 1982. The NRC review effort for the equipment in mild environments will be addressed by separate correspondence.

Your response My present alternatives to the staff positions in the evaluation.

The staff will censider alternative approaches if these methods are within the 00R. Guidelines or NUREG-0588, as appropriate. For example, an acceptable alternative to the NRC staff's temperature criterion used for the service conditions (i.e. Section 3.3) must base that service condition on the FSAR analysis or other NRC approved analysis, provided that the specific analysis, together with reference to the previous NRC acceptance of that analysis, accompanies the 90 day response.

In addition, some of the information in the Safety Evaluation may require clarification. Contact your project manager for assistance in these matters.

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.. -It remains your responsibility to assure that the qualification deadline is met for all safety-related electrical equipment. The staff's review of your response to this letter should not delay any action which is required in

order to meet the deadline.

Sincerely,

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Robert A. Clark, Chief Operating Reactors-Branch #3 Division of Licensing

Enclosures:

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' Portland l General Electric Company cc:

Mr. J. W. Durham,' Esquire Vice President and

. Corporate Counsel Portland General Electric Company

'121 S. W. Salmon Street

-Portland, Oregon 97204 Multnomah County Library Social Science and Science Department 801 S.W. 10th Avenue-Portland, Oregon ' 97205 Michael Malmros, LResident ' Inspector U. S. Nuclear Regulatory Commission i

Trojan Nuclear Plant:

P. O. Box 0 Rainier, Oregon 97048 Robert M. Hunt, Chairman

' Board of County Commissioners Columbia County St. Helens, Oregon 97501 Director, Criteria and Standards Division Of fice of Radiation Programs ( AHR-460)

V. S. Environmental Protection Agency Washington, D.1:.

20460 Donald W. Godard, Supervisor Siting and Regulation Oregon Department of Energy 4

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