ML20030C855

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Advises That Info Requested in NRC Re Safety Evaluation for Environ Qualification of safety-related Electrical Equipment Will Be Submitted by 811008.Delay Due to Expansion of Requested Info at 810707-10 Meeting W/Nrc
ML20030C855
Person / Time
Site: Point Beach  NextEra Energy icon.png
Issue date: 08/21/1981
From: Fay C
WISCONSIN ELECTRIC POWER CO.
To: Clark R, Harold Denton
Office of Nuclear Reactor Regulation
References
NUDOCS 8108280244
Download: ML20030C855 (1)


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Wisconsin Electnc mcome eT *2$ b 231 WEST MICHIGAN, MILWAUKEE, WISCONSIN 53201

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\\ "g I w gust 21, 1981 Mr. H.

R. Denton, Director Office of Nuclear Reactor Regulation U.

S. NUCLEAR REGULATORY COMMISSION Washington, D.

C.

20555 Attention:

Mr. Robert A. Clark, Chief Operating Reactors Branch 3 Gentlemen:

DOCKET NOS. 50-266 AND 50-301 SAFETY EVALUATION FOR THE ENVIRONMENTAL QUALIFICATION OF SAFETY-RELATED ELECTRICAL EQUIPMENT POINT BEACH NUCLEAR PLANT, UNITS 1 AND 2 Mr. Clark's letter of May 21, 1981 transmitted the Safety Evaluation for the Environmental Qualification of Safety-Related Electrical Equipment at Point Beach Nuclear Plant, Units 1 and 2.

It was requested that the information identified in Sections 3 and 4 of the Safety Evaluation be provided to you within 90 days of receipt.

The NRC/ Utility meeting on environmental qualification held in Bethesda, Maryland on July 7-10, 1981, however, considerably expanded the scope of information requested from licensees.

Much more detailed information is now requested for justification of qualification for high energy line break (HELB) temperature, chemical sprays, radiation, aging, and submergence.

As a result, Wisconsin Electric has not been able to gather all of the information requested as of this date.

We will continue to work to gather the information requested and will submit on or before October 8, 1981 (90 days following the NRC/ Utility meeting) that information which is then available.

Our reviews to date have not identified any safety-related electrical equipment which requires immediate corrective action.

Therefore, the conclusion of my April 9, 1981 10 CFR 50.54 (f) letter to you "that Point Beach Units 1 and 2 may continue to operate in a safe manner" remains valid.

We would be pleased to respond to any questions you may have in this matter.

Very truly yours,

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8108280244 810821 C. W.

ay, Director PDR ADOCK 05000266 Nuclear Power Department

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