ML19329D681
| ML19329D681 | |
| Person / Time | |
|---|---|
| Site: | Crystal River, Rancho Seco  |
| Issue date: | 05/12/1976 |
| From: | Skovholt D Office of Nuclear Reactor Regulation |
| To: | Goller K Office of Nuclear Reactor Regulation |
| References | |
| NUDOCS 8003160302 | |
| Download: ML19329D681 (4) | |
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CRYSTAL R1YER UNIT NO. 3 A:D RANCID SECO - REQUEST FOR ADDITIONAL QUALITY ASSURANCE INFORMATION Tao guidelines relating to QA for plant operations, which are contained i
in the HASH documents 1233-Rhy.1,1234 and 1309, have 'recently been i,
incorporater into ANSI N13.7-1976 (Ecvision of NIS.7-1972), "AP nistrative 1!
Controls and Quality Asnrance for the Operational Phase of Nuclear Pwer Plan ts." ANSI h13.7-1976, which will be issued an the near futura, will be enJorced by a revision to Rei;ulator*/ Guido l.33 In C:c d cr 1974, th NRC requested be': Florida Power Corperation (*2FC) and S'icramnto 9&ipal ULI.li.ty District M,D) to :upen t.he decreted O progr.as for Q:tal Ricc. 'f.it 16. 3 and Ranche t
, respectir217, to include the gulduco in tb above L".Sh docuc;cnts.
Since botn FPC's and SiU3's responses (latters dated January 2S and 2, D75) Jo not satisfy the NRC reests, the enclosed letter las been pro".ared ta ;2 ist you'in
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which endorse the ANS! r,tandard; Icferemd in N16.7-1976. T.da alternative approach t:ill ::atisfy the N'10's slidelines for jue.ing the acenptability of the operational QA progran at Crystal RiYer Unit No. 3 and R1.Cho S?co.
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Picase include the QE en distribution of n11 correspondence related n this subject.
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T MAY I 2 l970 Do cke t No. :
50-302 (50-312) 1 Addressee
.3 Gentlemen:
This letter is in reference to our generic review of quality assurance programs at all operating nuclear power stations and to our efforts to 1 -
assure that the information in the docket contains a current description of the measures, which reflect how the require =ents of Appendix 3 are being satisfied, used to carry out the QA program activities.
In A. Schwencer's December 4,1974 lette r to you, Flcrida Power Corporation (Sacramento Municipal Utility District) was requested to augment the docketed quality assurance (QA) program for Crystal River Unit No. 3 (Rancho Seco)
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to include the guidance in the 'a'AS'd doce=ents No. 1283, " Guidance on Quality Assurance Requirements During Design and Procurement Phase of Nuclear Pcwer Plants - Revision'1," dated May 24,19 74,, No.1309, " Guidance on Quality Assurance Requirements During the Construction Phase of Nuclear Power Plants,"
dated May 10,1974, and No.1284, " Guidance on Quality Assurance Requirements During the Operations Phase of Nuclear Power Plants," dated October 26, 1973.
Florida Power Corporation's (Sacramento Municipal Utility District's) response as-contained in your January 28,1975 (January 31, 1975) letter does not satisfactorily resolve our previous concern nor adequately address our reques t.
Since that time, ANSI standard N18.7-1976 (Revision of N18.7-1972)
' "AA=4nistrative Controls and Quality Assurance for the Operational Phase of Nuclear Power Plants" has become available. ' Our review of this most I
recent-industry standard indicates that it does provide for the necessary
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p MAY I 21976 controls to provide adequate confidence that, if properly i=ple= anted, the resulting QA program would be acceptable.
Consequently, this ANSI standard will be endorsed by a revision to Regulatory Guide 1.33.
Accordingly, in lieu of complying with the guidance contained in the WASH documents as we previously requested, we would find acceptable a QA program consistent with ANSI N18.7-1976 and the Regulatory Guides (Nos. 1.8, 1.30, 1.37, 1.38, 1.39-, 1.54, 1.64-Rev. 1, 1.74, 1.88, and 1.94) which endorse the ANSI standards referenced in N18.7-1976. For your infor:ation and use, a copy of ANSI N18.7-1976 (latest draft dated September.ll,1975) is attached. We are advised that the docu=ent is being printed and will be available in May 1976.
l We believe you share our view that quality assurance is not a static issue.
The criteria in Appendix 5 reflect broad requirements, and a nu=ber of different methods can be used to attain conformance with these criteria. A considerable body of guidance, as reflected in the docu=ents centioned above, has been deve;, ped defining acceptable ways to assure conformance with Appendix B criteria. We consider it essential that quality assurance programs at all operating nuclear power stations be in conformance with Appendix B raquirements and that the docketed program description provides sufficient. details on how these requirements are satisfied with equivalent controls to thosa described above. On this latter point, we believe you also share the view that the public should have access to a QA program description which reflects this level of detail.
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s MAY 121975 3-Although nonconfornance with Appendix B criteria has not been identified in the Crystal River Unit No. 3 (Rancho Seco) QA program, we are not able to perform an evaluation regarding the adequacy of the QA activities in effect since many elements necessary to make this judgenent are not addressed in the program description that was previously filed. Accordingly, we request that you file a revised QA program description for the Crystal River Unit No. 3 (Rancho Seco) which conforms to the.2bove guidance. Please file this description within 90 days.
We shall be happy to meet and discuss this subject with you if you desire.
Sincerely, Robert W. Reid, Chief Cperating Reactors 3 ranch No. 4 Division of Operating Reactors
Enclosure:
ANSI N13. 7-19 76 4
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