ML20039D457

Forwards WCAP-10019, Summary Rept on Reactor Vessel Integrity for Westinghouse Operating Plants. Rept Addresses Item II.K.2.13 of NUREG-0737 & Small LOCA Including Repressurization & Small Steam Line Break

ML20039D457
Person / Time
Site:	Beaver Valley, Salem, Indian Point, Kewaunee, Point Beach, Sequoyah, Summer, Prairie Island, Surry, North Anna, Turkey Point, Haddam Neck, Ginna, Diablo Canyon, Farley, Robinson, San Onofre, Cook, Yankee Rowe, Zion, McGuire, 05000000, Trojan
Issue date:	12/30/1981
From:	Kingsley O ALABAMA POWER CO.
To:	Harold Denton Office of Nuclear Reactor Regulation
Shared Package
ML20039D458	List: ML20039D457 ML20039D462
References
RTR-NUREG-0737, RTR-NUREG-737, TASK-2.K.2.13, TASK-TM OG-66, NUDOCS 8201040111
Download: ML20039D457 (2)

Text

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Alabama Power Company o

600 North 18th street L/

Post Office Box 2641

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Sirmingham, Alabama 35291 Telephone 205 250-1000 L

Alabama Power the Southern electnc System December 30, 1981 k'$$Lli n x.m.. _ >

y Mr. Harold R. Denton, Director g

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i Office of Nuclear Reactor Regulation d

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U.S. Nuclear Regulatory Commission y

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Phillips Building b'k M G [#

7920 Norfolk Avenue Bethesda, Maryland 20014

Dear Mr. Denton:

REACTOR VESSEL INTEGRITY Enclosed are forty '40) copies of WCAP-10019, " Summary Report on Reactor Vessel Integrity for Westinghouse Operating Plants".

This document details the generic analysis on reactor vessel integrity that was performed for the Westinghouse Owners Group.

This report provides a conservative assessment of reactor vessel integrity for all operating Westinghouse reactors. The report also provides each utility with a basis for determining the actions that need to be taken in both the short and long term.

The report addresses the requirements of Item II.K.2.13 of NUREG-0737 as well as the general subject of small loss-of-coolant accident including repressurization, the Rancho Seco event, small steam line break, and large loss-of-coolant accident. The analyses provide a thorough assessment of reactor vessel integrity, including very low probability events.

A number of conservatisms are present in the analyses, and thus in the analysis results. These conservatisms include the use of generic plant transients and material property categories.

In response to NRC concerns on several reactors, plant specific analyses have been initiated which include a review of the available remedial actions.

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Mr. Harold R. Denton December 30, 1981 OG-66 We will be happy to meet with your staff, and provide any additional information or answer questions on this report.

4 Very truly yours,

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0. D. Kings 1 hairman Westinghouse Owners Group

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