ML20080Q925

Forwards Containment post-accident Profiles Utilized in 10CFR50.49 Qualification Program & Extended Drywell Temp Analysis.Drywell Temp Analysis Withheld (Ref 10CFR2.790)

ML20080Q925
Person / Time
Site:	Hatch
Issue date:	02/24/1984
From:	Gucwa L GEORGIA POWER CO.
To:	Stolz J Office of Nuclear Reactor Regulation
Shared Package
ML19292C421	List: ML20080Q925 ML20080Q937
References
NED-84-079, NED-84-79, TAC-42505, TAC-42506, NUDOCS 8402270215
Download: ML20080Q925 (2)

Text

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Manager fLclear Engmeer ng aN Ch et ruciear Engmer NED-84-079 February 24, 1984 Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Division of Licensing U. S. Nuclear Regulatory Commission Washirigton, D. C.

20555 NRC DOCKETS 50-321, 50-366 OPERATING LICENSES DPR-57, NPF-5 EIMIN I. HATCH NUCLEAR PLANT UNITS 1, 2 TRANSMITTAL OF CONTAINMENT ACCIDENT PROFILES UTILIZED IN 10 CFR 50.49 QUALIFICATION PROGRAM Gentlemen:

On Feburary 14, 1984 Georgia Power Company (GPC) met with members of the NRC staff to discuss the program developed for the qualification of electrical equipment at Plant Hatch under 10 CFR 50.49.

GPC committed to submit the minutes of that meeting, which would include details on the Hatch qualificaton program, as well as a schedule for its completion, by March 30, 1984.

In addition, GPC committed to a submittal of the post-accident drywell pressure / temperature profiles used in qualifying plant equipment, includirig details on the development by General Electric Company (GE) of the profiles for small and intermediate high energy line breaks, by February 24, 1984. This submittal fulfills the second of these two commitments.

During the above mentioned meeting of February 14, 1984, members of the NRR Containment Systems Branch staff stated that the NRC Safety Evaluation i

Report on the Hatch qualification program could not be completed until all of the drywell accident environment profiles had been reviewed by the NRC.

GE just recently completed their analysis of drywell conditions af ter a small or intermediate steam line break; therefore, GPC has not yet had a chance to submit these curves for NRC review as part of the normal revision process to the Final Safety Analysis Reports (FSAR) for Plant Hatch.

Therefore, as attachments to this letter GPC is submitting the methodology and conclusions of the GE analysis, along with the other drywell environmental profiles used in the qualification program, in order to help expedite review of the Hatch program.

Please note that some information has been marked " proprietary" in order to protect the commercial interests of the vendor.

In accordance with 10 CFR 2.790, an affidavit is included which requests that certain information be withheld from the public domain.

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o GeorgiaPower d Director of Nuclear Reactor Regulation Attention: Mr. John F. Stolz, Chief Operating Reactors Branch No. 4 Page Two Febmary 24, 1984 GPC forsees no problem in meeting the committment for submittal of the meeting minutes by March 30, 1984.

This report will be transmitted to NRR in a seperate submittal.

Sincerely yours;

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L. T. Gucwa CBS Enclosures xc:

H. C. Nix, Jr.

G. Rivenbark J. R. Jordan l

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