ML17037C535: Difference between revisions

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| number = ML17037C535
| number = ML17037C535
| issue date = 05/21/1973
| issue date = 05/21/1973
| title = Nine Mile Point Nuclear Station, Unit 1 - Requests Description to Quality Assurance Program at It Applies to the Plant Operation and Maintenance in Light of Regulatory Guide No. 1.33
| title = Requests Description to Quality Assurance Program at It Applies to the Plant Operation and Maintenance in Light of Regulatory Guide No. 1.33
| author name = Ziemann D L
| author name = Ziemann D
| author affiliation = US Atomic Energy Commission (AEC)
| author affiliation = US Atomic Energy Commission (AEC)
| addressee name = Raymond P D
| addressee name = Raymond P
| addressee affiliation = Niagara Bottling Company
| addressee affiliation = Niagara Bottling Company
| docket = 05000220
| docket = 05000220
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:MAY811973DocketHo.50-220HiagaraHohawkPowerCorporationATTN:Hr.PhilipD.RaymondVicePresident-Engineering300ErieBoulevardHestSyracuse,HewYork13202Gentlemen:Ourletter,t'oyoudatedHarch26,1971.,requestedthatyousubmit,asasupplementtoyourTinalSafetyAnalysisReport(TSAR),adescriptionofyourqualityassuranceprogramfortheHineHilePoint,NuclearStationUnitHo.1(RP-1).AppendixBof10CFR50wasindicatedasthecriteriaforaqualityassuranceprogramfordesign>construction,endoperationofthe.structures,systems,andcomponentsofthefacility.inparticular,wewereinterestedindeterminingtowhatextentyourqualityassuranceprogramcoverssuchactivitiesasoperation,maintenance,repair,refueling,andmodifications.YourreplydatedJune21,l971,wassubmittedastheNinthSupplementtotheTSAR.Inaddition,youbrieflyaddressedthissub)ectin'yourapplicationdatedJuly5,1972,forconversionfromtheprovisionaloperatinglicensetoafull.-tennoperatinglicense.liehaveevaluatedthesesubmittalsagainstthecriteriaofAppendix3of10CTR50aseachappliestoqualityassuranceduringoperationofHHP-1.Asyoumaybeaware,RegulatoryGuideHo.1.33,QualityAssuranceProgramRequirements(Operation),wasissuedonNovember3,1972.TheGuidereferencesAHS3.2,StandardforAdministrativeControlsforHuclearPowerPlants,andANSIH452-1971,QualityAssuranceProgramRequirementsforNuclearPowerPlants.ConformancewiththesestandardswillprovideanadequatebasisforcomplyingwithAppendixBof10CTRPart50.Pleasereassessyourqualityassuranceprogramasitappliestotheplantoperationandmaintenance,inlightofRegulatoryGuideHo.'1.33andtheabovecomments,andresubmitadescriptionoftheprogramthat C1p'=IIEI~I4E64ElIEE4lE'1 NiagaraHohawkPowerCorporation-2-MAY8l]973isresponsivetotheguide.DeviationfromANS3.2orANSIN45.2-1971mustbedescxibedindets11andadequatelygusttified.Wherereferenceismadeinthediscussionthattherequixementissatisfiedbyastate-mentin,theTechnicalSpecifications,aspecificreferenceto'theappro-priatesubsectionoftheTechnicalSpecificationsshouldbemade.Theaboveinformationshouldbesubmittedwithin90daysofthedate,ofthisletterasasupplementtoyourapplicationfox'onversionfromaprovisionaloperatinglicensetoafull-termoperatinglicense.Thxeesignedandnotarizedoriginalsandthirty-sevenadditionalcopiesof..yoursubmittalshouldbeprovided.Sincerely,OriginalsignedbgD0nnisL.JiI'nIanngennisL.Ziemann,ChiefOperatingReactorsBranchP2ectorate.ofLicensingDircc:J.BruceHacDonald,EsquireDeputyComad.ssionerandCounselNew'orkStateDepartmentofCommerceandCounseltotheAtomicEnergyCouncil4AxvtnE.Upton,EsquireLeBoeuf,Lamb,Leiby6MacRaeDistributionacketPileAECPDRLocalPDRRPReadingBranchReadingJRBuchanan,OWLDJSkovholt,L:ORTJCarter,L:ORACRS(16).,RO(3)Bordenick,OGCHaflich',OGCDLZiemann,L:ORBf/2CJDeBevec,L:ORBI/2,RMDiggs,L:ORB//2RWHouston,L:OSBJRSears,L:OSBqOswegoCityLibraryDr.WilliamSeymourStaffCoordinatorNewYorkStateAtomicEnergyCouncilNewYorkStateDepartmentofCommerce'L:O>e/IZX74O3--~CJDeBEvdc:sjOFFICEDSURNAMEDDATE>5/17/73FormhEC-318(Rev.9-33)hECM0240L:ORB,82higgs5/17/73L:O//2DLZiemann54//73o~oe43-le-Sla05-1clM78 AAIIJrJIi.IIiIgftIIII~IjIIw-AIIIIIIIlI
{{#Wiki_filter:MAY 81  1973 Docket Ho. 50-220 Hiagara Hohawk Power Corporation ATTN:   Hr. Philip D. Raymond Vice President  Engineering 300 Erie Boulevard Hest Syracuse, Hew York 13202 Gentlemen:
}}
Our letter,t'o you dated Harch 26, 1971., requested that you submit, as a supplement to your Tinal Safety Analysis Report (TSAR), a description of your quality assurance program for the Hine Hile Point, Nuclear Station Unit Ho. 1 (RP-1). Appendix B of 10 CFR 50 was indicated as the criteria for a quality assurance program for design>
construction, end operation of the. structures, systems, and components of the facility. in particular, we were interested in determining to what extent your quality assurance program covers such activities as operation, maintenance, repair, refueling, and modifications.
Your reply dated June 21, l971, was submitted as the Ninth Supplement to the TSAR. In addition, you briefly addressed this sub)ect in 'your application dated July 5, 1972, for conversion from the provisional operating license to a full.-tenn operating license. lie have evaluated these submittals against the criteria of Appendix 3 of 10 CTR 50 as each applies to quality assurance during operation of HHP-1.
As you may be aware, Regulatory Guide Ho. 1.33, Quality Assurance Program Requirements (Operation), was issued on November 3, 1972. The Guide references  AHS 3.2, Standard for Administrative Controls for Huclear Power  Plants, and ANSI H45 2-1971, Quality Assurance Program Requirements for Nuclear Power Plants. Conformance with these standards will provide an adequate basis for complying with Appendix B of 10 CTR Part 50.
Please reassess  your quality assurance program as  it applies to the plant operation and maintenance, in light of Regulatory Guide Ho.'1.33 and the above comments, and resubmit a description of the program that
 
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Niagara Hohawk Power Corporation            - 2                   MAY 8 l ]973 is  responsive to the guide.       Deviation from ANS 3.2 or ANSI N45.2-1971 must be descxibed      in dets11 and adequately gusttified. Where reference is made in the discussion that the requixement is satisfied by a state-ment in,the Technical Specifications, a specific reference to 'the appro-priate subsection of the Technical Specifications should be made.
The above      information should be submitted within 90 days of the date, of this letter as a supplement to your application fox'onversion from a provisional operating license to a full-term operating license. Thxee signed and notarized originals and thirty-seven additional copies of                    .
            . your submittal should be provided.
Sincerely, Original signed bg D0nnis L.JiI'nIann gennis L. Ziemann, Chief Operating Reactors Branch          P2 Directorate.of Licensing cc:     J. Bruce HacDonald, Esquire                                    Distribution Deputy Comad.ssioner and Counsel New'ork State Department of acket    Pile AEC PDR Commerce and Counsel to the                                  Local PDR Atomic Energy Council                              q        RP Reading 4
Branch Reading Axvtn E. Upton, Esquire                                        JRBuchanan, OWL LeBoeuf, Lamb, Leiby 6 MacRae                                  DJSkovholt, L:OR TJCarter, L:OR Dr. William Seymour                                            ACRS  (16).,
Staff Coordinator                                              RO (3)
New York State Atomic Energy Council                            Bordenick,   OGC New York State Department of Commerce                          Haflich', OGC DLZiemann, L:ORB f/2 Oswego    City Library                                          CJDeBevec, L:ORB I/2 RMDiggs, L:ORB //2 RWHouston, L:OSB JRSears, L:OSB OFFICE D
                      'L:O>e /IZ        L: ORB,82    L:O        //2 X74O3--~
SURNAME D      CJDeBEvdc:sj      higgs        DLZiemann DATE >     5/17/73          5/17/73      54//73 Form hEC-318 (Rev. 9-33) hECM 0240                o~o  e43-le-Sla05-1 clM78
 
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Latest revision as of 19:53, 4 February 2020

Requests Description to Quality Assurance Program at It Applies to the Plant Operation and Maintenance in Light of Regulatory Guide No. 1.33
ML17037C535
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 05/21/1973
From: Ziemann D
US Atomic Energy Commission (AEC)
To: Raymond P
Niagara Bottling Company
References
Download: ML17037C535 (4)


Text

MAY 81 1973 Docket Ho. 50-220 Hiagara Hohawk Power Corporation ATTN: Hr. Philip D. Raymond Vice President Engineering 300 Erie Boulevard Hest Syracuse, Hew York 13202 Gentlemen:

Our letter,t'o you dated Harch 26, 1971., requested that you submit, as a supplement to your Tinal Safety Analysis Report (TSAR), a description of your quality assurance program for the Hine Hile Point, Nuclear Station Unit Ho. 1 (RP-1). Appendix B of 10 CFR 50 was indicated as the criteria for a quality assurance program for design>

construction, end operation of the. structures, systems, and components of the facility. in particular, we were interested in determining to what extent your quality assurance program covers such activities as operation, maintenance, repair, refueling, and modifications.

Your reply dated June 21, l971, was submitted as the Ninth Supplement to the TSAR. In addition, you briefly addressed this sub)ect in 'your application dated July 5, 1972, for conversion from the provisional operating license to a full.-tenn operating license. lie have evaluated these submittals against the criteria of Appendix 3 of 10 CTR 50 as each applies to quality assurance during operation of HHP-1.

As you may be aware, Regulatory Guide Ho. 1.33, Quality Assurance Program Requirements (Operation), was issued on November 3, 1972. The Guide references AHS 3.2, Standard for Administrative Controls for Huclear Power Plants, and ANSI H45 2-1971, Quality Assurance Program Requirements for Nuclear Power Plants. Conformance with these standards will provide an adequate basis for complying with Appendix B of 10 CTR Part 50.

Please reassess your quality assurance program as it applies to the plant operation and maintenance, in light of Regulatory Guide Ho.'1.33 and the above comments, and resubmit a description of the program that

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Niagara Hohawk Power Corporation - 2 MAY 8 l ]973 is responsive to the guide. Deviation from ANS 3.2 or ANSI N45.2-1971 must be descxibed in dets11 and adequately gusttified. Where reference is made in the discussion that the requixement is satisfied by a state-ment in,the Technical Specifications, a specific reference to 'the appro-priate subsection of the Technical Specifications should be made.

The above information should be submitted within 90 days of the date, of this letter as a supplement to your application fox'onversion from a provisional operating license to a full-term operating license. Thxee signed and notarized originals and thirty-seven additional copies of .

. your submittal should be provided.

Sincerely, Original signed bg D0nnis L.JiI'nIann gennis L. Ziemann, Chief Operating Reactors Branch P2 Directorate.of Licensing cc: J. Bruce HacDonald, Esquire Distribution Deputy Comad.ssioner and Counsel New'ork State Department of acket Pile AEC PDR Commerce and Counsel to the Local PDR Atomic Energy Council q RP Reading 4

Branch Reading Axvtn E. Upton, Esquire JRBuchanan, OWL LeBoeuf, Lamb, Leiby 6 MacRae DJSkovholt, L:OR TJCarter, L:OR Dr. William Seymour ACRS (16).,

Staff Coordinator RO (3)

New York State Atomic Energy Council Bordenick, OGC New York State Department of Commerce Haflich', OGC DLZiemann, L:ORB f/2 Oswego City Library CJDeBevec, L:ORB I/2 RMDiggs, L:ORB //2 RWHouston, L:OSB JRSears, L:OSB OFFICE D

'L:O>e /IZ L: ORB,82 L:O //2 X74O3--~

SURNAME D CJDeBEvdc:sj higgs DLZiemann DATE > 5/17/73 5/17/73 54//73 Form hEC-318 (Rev. 9-33) hECM 0240 o~o e43-le-Sla05-1 clM78

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