ML20214K157

Advises That Rev 10/6A to WCAP-8370/7800, Water Reactor Div QA Plan, Meets Criteria of 10CFR50,App B & Acceptable. Organizational Changes Described in Should Be Issued to All Holders of Rept

ML20214K157
Person / Time
Site:	07007800
Issue date:	05/22/1987
From:	Miller H Office of Nuclear Reactor Regulation
To:	Johnson W WESTINGHOUSE ELECTRIC COMPANY, DIV OF CBS CORP.
References
REF-QA-99900404 NUDOCS 8705280343
Download: ML20214K157 (2)

Text

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NUCLEAR REGULATORY COMMISSION

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MAY 2 21987 Docket No. 99900404 Mr. W. J. Johnson, Manager Nuclear Safety, Power Systems Westinghouse Electric Corporation Box 855 Pittsburgh, PA 15230-0855

SUBJECT:

NRC ACCEPTANCE OF WESTINGHOUSE QA TOPICAL REPORT We have reviewed the reorganization information submitted in your letter of April 29, 1987, and its effect on the Westinghouse QA topical report. The letter indicates that Westinghouse nuclear efforts are now under the Energy Systems organization, and current organization charts are included. We y;1,l understand that the. topical report, WCAP-8370/7800, Revision 10/6A, " Water Reactor Division's Quality Assurance Plan," is being revised to reflect the responsibilities of the new organizations. We were told that the revised P !

report will be submitted before the end of 1987.

s In the interim, we find that the topical report continues to meet the I,,',~,G criteria of Appendix B to 10 CFR Part 50 and is, therefore, acceptable.

While the QA program is acceptably described, Westinghouse must ensure its effective implementation so that regulatory requirements continue to be met.

Important to determining the effectiveness of the QA program is the performance of significant, in-depth technical audits of work products..

Please issue the organizational changes described in your letter of April 29, 1987, together with this acceptance letter, to all holders of the topical

"" j report.

Future changes to the report should be reported to the NRC in accordance with the provisions for holders of construction permits as described in 10 CFR 50.55(f)(3).

Any questions on this subject should be addressed to the QA Branch reviewer, Jack Spraul, on (301) 492-4883.

Sincerely, s

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Hub t J. Miller, Acting Director Di sion of Licensee Performance and Quality Evaluation Office of Nuclear Reactor Regulation 870S280343 870522 PDR GA999 EMVWEST 99900404 PDR g

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