ML20238F272

Forwards SER Approving 980723 Proposed Rev 20 to Northeast Utilities Quality Assurance Program Topical Rept

ML20238F272
Person / Time
Site:	Millstone
Issue date:	08/27/1998
From:	Bill Dean NRC (Affiliation Not Assigned)
To:	Bowling M, Loftus P NORTHEAST NUCLEAR ENERGY CO.
Shared Package
ML20238F274	List: ML20238F272 ML20238F278
References
TAC-MA2393, TAC-MA2394, TAC-MA2395, NUDOCS 9809030239
Download: ML20238F272 (3)

Text

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50-g2'S yp" "%,i UNITED STATES

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NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 2066tHm01

'% August 27, 1998

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i Mc. Martin L. Bowling, Jr.

} Recovery Officer - Technical Services Northeast Nuclear Energy Company c/o Ms. Patricia A. Loius Director- Regulatory Affairs P. O. Box 128 Waterford, Connecticut 06385

SUBJECT:

APPROVAL OF PROPOSED REVISION 20 OF THE NORTHEAST UTILITIES QUALITY ASSURANCE PROGRAM TOPICAL REPORT (TAC NOS. MA2393, MA2394, AND MA2395) 3

Dear Mr. Bowling:

On July 23,1998, Northeast Nuclear Energy Company (NNECO) transmitted proposed Revision 20 to the Northeast Utilities QuMty Assurance Program (NUQAP) Topical Report for NRC review and approval in accordan',e with 10 CFR 50.54(a)(3).

' in its proposed Revision 20 to the NL QAP, NNECO identified several organizational and editorial r

changes. However, only one minor change (associated with the removal of certain consumables from Appendix A, " Category i Structuras, Systems, and Components," to the NUQAP) was identified by the licensee as a reduction in commitment in the NUQAP and thus, subject to NRC approval pursuant to 10 CFR 50.54(a)(3). The enclosed safety evaluation documents the bases for our conclusion that the reduction in commitments identified by the licensee in Revision 20 to the NUQAP are consistent with the guidance in NUREG-0800, the " Standard Review Plan," and, therefore, continue to satisfy the requirements of Appendix B to 10 CFR Part 50. However, this conclusion does not establish the technical validity of the Material Equipment and Parts List (MEPL) evaluation performed by NNECO which forms the basis for the licensee's decision to exclude these consumables from the provisions of Appendix B to 10 CFR Part 50. Section 50.59 and Criterion lll of Appendix B to 10 CFR Part 50 requirements govem the process under which the MEPL evaluation was performed and its bases and conclusions are subject to NRC inspection accordingly.

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Maitin L. Bowhng  ;,

August 27, 1998 If you have any questions regarding this issue, please call James Andersen of my staff at (301) 415-1437.

Sincerely, Original signed by D. Mcdonald for:

William M. Dean, Director Millstone Project Directorate Division of Reactor Projects - 1/11 Office of Nuclear Reactor Regulation Docket Nos. 50-245,50-336, and 50-423

Enclosure:

Safety Evaluation cc w/ encl: See next page DISTRIBUTION:

'Becket Fue25 PUBLIC MSPD Reading JAndersen WDean SDembek DMcDonald LBerry OGC ACRS THarris (e-mail SE)

JDurr, RI DScrenci, RI DOCUMENT NAME: G:%NDERSENW2395.WPD To receive a cop 7 of this documeest, ledcate let the bom! *C' = Copy wipfwenattachment/enclosu G* = Copy with attachment / enclosure

• N" = No copy OFFICE MSPD:PM ,// l MSPD:LA I )OWs MSPD:D i, l l NAME JAndersen /f) LBerry (/[{ > W dear @ )

DATE 080/98 08/l /98 \ 08ffl98 Ud 08/ /98 08/ /98 y OFFICIAL RECORD COPY

e i Madin L. Bowling l If you have any questions regarding this issue, please call James Andersen of my staff at (301) 415-1437.

Sincerely, N William fd. Dean, Director Millstone Project Directorate Division of Reactor Projects - t/II Office of Nuclear Reactor Regulation Docket Nos. 50-245, 50-336, and 50-423

Enclosure:

Safety Evaluation cc w/ encl: See next page l

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