ML19340E462

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Advises That Analysis Re Asymmetric LOCA Loadings Described in Revisions 1 to WCAP-9558 & WCAP-9570 Is Applicable to Facility.Util Will Participate in Fracture Mechanics Evaluation Sponsored by Westinghouse Owners Group
ML19340E462
Person / Time
Site: Fort Calhoun Omaha Public Power District icon.png
Issue date: 12/19/1980
From: Anderson T
WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
To: Eisenhut D
Office of Nuclear Reactor Regulation
References
NS-TMA-2349, NUDOCS 8101140569
Download: ML19340E462 (1)


Text

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300R ORIGINAL s s Westinghouse Water Reactor umecx:cMa Electric Corporation Divisions  :. e e~ wen Pennsman,a tur NS-TMA-2349 December 19,1980 Ref: a. NS-TMA-2265 Darrall G. Eisenhut, Director Division of Licensing Office of Nuclear Reactor Regulation U.S. Nuclear Regulatory Commission Washington, D.C. 20555

Dear Mr. Eisenhut:

Westinghouse has previously submitted information to the Staff in Reference (a) for the Westinghouse Owners Group of Operating Plants addressing asymmetric LOCA loadings (NRC Task Action Plan NRC-T AP-T CPIC- A-2). This information deals with a mechanistic fracture mechanics evaluation of stainless steel reactor coolant pipe to demonstrate that a postulated through-wall circumferential crack will not lead to a double ended guillotine break. Details of this evaluation are contained in WCAP 9558 Revision 1(proprietary) and WCAP 9570 Revision 1(non-proprietary).

At the request of the Omaha Public Power District (OPPD) and the Westinghouse Owners Group of Operating Plants Westinghouse has evaluated the applicability of the fracture mechanics eva'uation to the Fort Calhoun Nuclear Plant. As a result of this evaluation Westinghouse ? as concluded that the analysis and testing described in WCAP 9558 Revision 1 and J/ CAP 9570 Revision 1 a:e applicable to the Fort Calhoun Nuclear Plant.

Subsequently, t 'e Westinghouse Owners Group of Operating Utilities for Asymmetric LOCA Loads has accepted the Omaha Public Power District (OPPD) as a member for this issue. OPPO will participate in this fracture mechanics evaluation being sponsored by

! the Owners Group. As a result, the information in Reference (a) and additional analysis and testing performed by Westinghouse as part of this fracture mechanics evaluation may be referenced for the Fort Calhoun Nuclear Plant.

If you have any questions or if I can be of any further assistance, please do not hesitate to contact me.

Since l

/ y yours

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T. M. Anderson, Manager Nuclear Safety Department cc: S. Hosford, NRC Bethesda JJM/ keg

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