ML19210D889

Approves of Revision 10 to CE-1-A, Comm Ed QA Program for Generating Stations W/Exception of Application to Byron/Braidwood Stations.Addl Info Required

ML19210D889
Person / Time
Site:	Dresden, Byron, Braidwood, Quad Cities, Zion, LaSalle
Issue date:	11/03/1979
From:	Haass W Office of Nuclear Reactor Regulation
To:	Naughton W COMMONWEALTH EDISON CO.
References
TASK-17, TASK-RR NUDOCS 7911280333
Download: ML19210D889 (2)

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e Mr. W. F. ::aughton Nuclear Licensing Administrator Boiling '.!ater Reactors Ccmmonwealth Edison Company P.O. Box 767 Chicago, IL 60690

SUBJECT:

NRC ACCEPTANCE OF REVISIONS TO QA TOPICAL REPORT By letter dated September 24, 1979, you submitted Revision 10 to the Ccmonwealth Edison Topical Report No. CE-1-A, " Commonwealth Edison Company Quality Assurance Program for Nuclear Generating Staticns." You indicated in your transmittal letter that the topical report and this revision are intended to be applicable to nuclear units identified by Docket Numbers 50-10, 50-237, 50-249, 50-254, 50-265, 50-295, 50-304, 50-373, 50-374, 50-454, 50-455, 50-456, and 50-457. The revision concerns general organizational changes.

We have evaluated the proposed changes against the acceptance criteria included in SRP Section 17.2 and find them acceptable with the following exception. Since the FSAR for the Byron /Braidwood Stations, Unit Nos.1 & 2, Docket Nos. 50-454, 50-455, 50-456, and 50-457, is still under review and evaluation against the acceptance criteria included in SRP Section 17.2, Revision 1, " Quality Assurance During the Operations Phase," the topical report is not considered acceptable for the Byron /Braidwood Stations. Accordingly, as a result of our review and evaluation of the Byron /Braidwood Stations, it is expected that either the QA Topical or Section 17.0 of the FSAR will require additional information to meet our present requirements for this FSAR application. With the exception just noted, your revised topical report meets the criteria of Appendix B to 10 CFR Part 50 and is therefore acceptable for use.

Should regulatory criteria or regulacions change such that our conclusions about this topical report are invalidated, we will notify you. You will be given the opportunity to revise and resubmit it should you so desire. As noted above, should you desire to reference this topical report in support of quality assurance programs for new nuclear plant projects, the basis of our evaluation will be the acceptance criteria included in SRP Sections 17.1 and 17.2, Revision 1.

Appropriate changes will, therefore, be necessary.

Programmatic changes by CECO to this topical report are to be submitted to the NRC for review prior to implementation. Organizational changes are to be submitted no later than 30 days after announcement.

Please reciace our letter of September ll,1979 with this letter, renumber the report as CE-1-A, Revision 10, and submit 36 copies to the NRC. Your transmittal letter should identify the nuclear units to which the report is applicable, as noted above.

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"r. W. F. ?l3ughton *1Cy 89979 Chculd you have any questions regarding our review or if we can provide assistance, i: lease feel free to contact me or Mr. !Jillir.m Belke at (301) 492-7741.,

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kalter P. Haass, Chief Quality Assurance Branch Division of Project Management i fi n 9 71,4