ML20009B106

Forwards Equipment Qualification Branch Safety Evaluation for Environ Qualification of safety-related Electrical Equipment.Also Forwards Technical Evaluation of Revision 1 to Licensee Response to IE Bulletin 79-01B

ML20009B106
Person / Time
Site:	Beaver Valley
Issue date:	06/29/1981
From:	Varga S Office of Nuclear Reactor Regulation
To:	Carey J DUQUESNE LIGHT CO.
Shared Package
ML20009B107	List: ML20009B106 ML20009B112 ML20009B113
References
IEB-79-01B, IEB-79-1B, TAC-42459, NUDOCS 8107140797
Download: ML20009B106 (2)

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Docket No. 50-334 ORB #1 Rdg 6

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Mr. J. J. Carey, Vice President ACRS-l'0 bp M@

IE-3 Duquesne Light Company SVarga W

s Nuclear Division DChaney N

Post Office Box 4 CParrish Shippingport, Pennsylvania 15077 Gray File-4

SUBJECT:

EHYIROHMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT RE:

Facility Operating License No. DPR-66 for Beaver Valley Power Station, Unit No.1 Reference (a) - Order for Modification of License Concerning the Environmental Qualification of Safety-Related Electrical Equipment dated October 24, 1980

Dear Mr. Carey:

This letter transmits the Safety Evaluation for the Environmental Qualifi-cation of Safety-Related Electrical Equipment at your facilf ty. This evaluation was based on your submittals dated December 31, 1980 and March 12, 1981. Our letter of June 9,1981, which forwarded our prelimirary 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 (a). We request that you provide the information identified in sections 3 and 4 of this Safety Evaluation to us within 90 days.

This Safety Evaluation addresses only the safety-related electrical equipment exposed to a harsh environment resulting from an accident (i.e., the IEB 79-01B review). Reference (a) requires that all safety-related electrical equipment be qualified by June 30, 1982. The Hhr. review effort for the equipment in mild environments will be addressed by separate correspondence.

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

The staff will consider alternative approaches if these nethods are within the D0R 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 maneger for assistance in these matters, i -

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%g fir. J. J. Carey 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, Orie:inal signed by:

r. A. Varga Steven A. Varga, Chief Operating Reactors Branch #1 Division of Licensing

Enclosures:

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