ML19329D750
| ML19329D750 | |
| Person / Time | |
|---|---|
| Site: | Crystal River  |
| Issue date: | 06/25/1976 |
| From: | Stolz J Office of Nuclear Reactor Regulation |
| To: | Rodgers J FLORIDA POWER CORP. |
| References | |
| NUDOCS 8003170691 | |
| Download: ML19329D750 (2) | |
Text
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c JUN 2 5 1976 Distribution: w/o enclosure Docket File /
Local PDR C. J. Heltemes LWR #1 File R. C. DeYoung h f.
ams Docket No. 50-302' g
L. Engle bec:
J. Buchanan, NSIC F16rida Power Corporation fbR ATTH: Mr. J. T. Rodgers Assistant Vice President and Nuclear Project Manager P. O. Box 14042 St. Petersburg, Florida 33733 Gentlemen:
This letter is in reference to our generic review of operational quality assurance programs at all nuclear power stations and to our efforts to assure that the information in the docket contains a current description of the measures, which reflect how the requirements of Appendix B are being satisfied, used to carry out the QA program activities.
In A. Schwencer's December 4,1974 letter to Florida Power Corporation (FPC) you were requested to augment your docketed operational quality assurance (QA) program for Crystal River'llnit, No. 3 (CR-3) to include the guidance in the WASH documents No.1283, " Guidance on Duality Assurance Requirements During Design and Procurement Phase of Nuclear Power Plants -
Revision 1 " dated May 24,1974; No.1309, " Guidance on Quality Assurance Requirements During the Construction Phase of Nuclear Power Plants,"
dated May 10,1974; and No.1284, " Guidance on Ouality Assurance Requirements During the Operations Phase of Nuclear Power Plants," dated October 26, 1973. Your response as contained in your January 28, 1975 letter does not satisfactorily resolve our previous concern nor adequately address our request.
- Since that time, ANSI standard N18.7-1976 (Revision of N18.7-1972)
" Administrative Controls and Quality Assurance for the Operational Phase of Huclear Power Plants" has become available. Our review of this nost rec;nt industry standard indicates that it does provide for the necessary -
controls to previde adequate confidence that, if nroperly inplemented, the resulting Qt program would be acceptable. Consequently, this ANSI standard will be endorsed by a revision to Regulatory Guide 1.33.
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Accordingly, in lieu of complying with the guidance contained in the WASH documents as we pmviously requested, we would find acceptable an operational QA progran consistent with ANSI N18.7-1976 r.nd the Regulatory Guides (Nos. 1. 8, 1. 30, 1. 37, 1. 38, 1.39, 1. 54, 1. 58, 1. 64-Rev. 1 1.74,1.88, and 1.94) which endorse the ANSI standards referenced in Nia.7-1976 (latest draft dated September 11,1975) is attached. We are advised that this doctsnent is now being printed and will be available in the near future.
We know you share our view that operational quality assurance is not a static issue. The criteria in Appendix B reflect broad requirements.
and a number of different methods can be used to attain confomance with these criteria. A considerable body of guidance, as reflected in the documents mentioned above, has been developed defining acceptable ways N
to assure confomance with Appendix B criteria. We consider it essential N.,"
that operational quality assurance pmgrans at all nuclear power stations
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be in confomance with Appendix B requirements and that the docketed j
program description provides sufficient details on how these requirements are satisfied with equivalent controls to those described above. On this latter point, we believe you also share the view that the public.
should have access to an operational QA program description which reflects this level of detail.
i Although nonconfomance with Appendix B criteria has not been identified in the CR-3 operational QA program, we are not able to perfom an evaluation regarding the adequacy of the QA activities in effect since many elements necessary to make this judgement are not addmssed in the progran description that was previously filed. Accordingly, we request that you file a revised operational QA program description for CR-3 which confoms to the above guidance. Please file this description within 90 days, and notify us within 30 days of your intent regarding these matters.
We shall be happy to meet and discuss this subject with you if you desire.
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(.sCA John F. Stolz7 Chief Light Water Reactors Branch P'o.1 Division of Project Manage-ent j
Enclosure:
MISI NlR.7-1976 cc: Mr. S. A. Brandinore "ic: Prc;i t '. cr.d b cral Cour.;;l P. 0. Box 1@42 L1 1
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