ML18041A042

Forwards Rev 14 to NMP Unit 1 Updated Fsar,Including Changes to QA Program Description & Annual 10CFR50.59 Safety Evaluation Summary Rept

ML18041A042
Person / Time
Site:	Nine Mile Point
Issue date:	06/28/1996
From:	SYLVIA B R NIAGARA MOHAWK POWER CORP.
To:	NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
Shared Package
ML18041A043	List: ML18041A042
References
NMP1L-1090, NUDOCS 9607020103
Download: ML18041A042 (256)

Text

REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9607020103DOC.DATE:96/06/28NOTARIZED:YESDOCKETFACIL:50-220NineMilePointNuclearStation,Unit1,Niagaraowe05000220AUTH.NAMEAUTHORAFFILIATIONSYLVIA,B.R.;NiagaraMohawkPowerCorp./ofpRECAP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk)

SUBJECT:

ForwardsRev14toNMPUnit1UpdatedFSAR,includingchangestoQAprogramdescription6annual10CFR50.59safetyeva1uationsummaryrept.DISTRIBDTIONCODE:A053DCOPIESRECEIVED!LTRIENCLJISIZE:TITLE:ORSubmittal:UpdatedFSAR(50.71)andAmendmentsNOTES:RECIPIENTIDCODE/NAMEPD1-1PDINTERNAL:AYERSFILECENTER01EXTERNAL:IHSNRCPDRCOPIESLTTRENCL1022'221111RECIPIENTIDCODE/NAMEHOOD,DAEOD/DOA/IRBRGN1NOACCOPIESLTTRENCL11111111DUNNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR11ENCLlo N

NIAGARAMOHAWKCENERATIONBUSINESSCROUPB.RALPHSYLVIAExecutiveVicePresidentGenerationBusinessGroupChiefNuclearOfficer300ERIEBOULEVARDWEST.SYRACUSE,NEWYORK13202/TELEPHONE(315)4284983June28,1996NMP1L1090U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,DC2055510C.F.R.550.71(e)10C.F.R.$50.54(a)(3)10C.F.R.$50.59(b)(2)RE:NineMilePointUnit1DocketNo.50-220

Subject:

SubmittalofRevision14totheNineMilePointNuclearStationUnit1FinalSafetyAnalysisReport(Updated),IncludingChangestotheQualityAssuranceProgramDescnption,andtheAnnual10C.F.R.5$0.$9SafetyEvaluationSummaryReportGentlemen:Pursuanttotherequirementsof10C.F.R.$50.71(e),10C.F.R.$50.54(a)(3),and10C.F.R.$50.59(b)(2),NiagaraMohawkPowerCorporationherebysubmitsRevision14totheNineMilePointNuclearStationUnit1FinalSafetyAnalysisReport(Updated),includingchangestotheNiagaraMohawkPowerCorporationQualityAssuranceTopicalReport,andtheannualSafetyEvaluationSummaryReport.One(1)signedoriginalandten(10)copiesoftheUnit1FSAR(Updated),Revision14,areenclosed.CopiesarealsobeingsentdirectlytotheRegionalAdministrator,RegionI,andtheSeniorResidentInspectoratNineMilePoint.TheUnit1FSAR(Updated)revisioncontainschangesmadesincethesubmittalofRevision13inJune1995.Inaddition,manyoftheUnit1FSAR(Updated)Sectionshavebeenreformattedintheirentiretytoeliminateblankpages,establishauniformleft-marginjustificationformat,andtoreorganizetheinformationinto"Text/Table/Figure"order.Thecertificationrequiredby10C.F.R.$50.71(e)isattached.EnclosureA'providestheidentification,reason,andbasisforeachchangetothequalityassuranceprogramdescription,Unit1FSAR(Updated)AppendixB,inaccordancewith10C.F.R.$50.54(a)(3)(ii).9607020i03960628PDRADQCK'5000220KPDR

Page2TheenclosedannualSafetyEvaluationSummaryReport(EnclosureB)containsbriefdescriptionsofchangestothefacilitydesign,procedures,tests,andexperiments.NoneoftheSafetyEvaluationsinvolvedanunreviewedsafetyquestionasdefinedin10C.F.R.$50.59(a)(2).Verytrulyyours,B.RalphSylviaChiefNuclearOfficerBRS/JJL/kapEnclosurespc:Mr.T.T.Martin,RegionalAdministrator,RegionIMr.D.S.Hood,SeniorProjectManager,NRRMr.B.S.Norris,SeniorResidentInspectorRecordsManagement l'.i'll NIACARAMOHAWKGENERATI0NBUSINESSGROUPB.RALPHSYLVIAExecutiveVicePresidentGenerationBusinessGroupChiefNuclearOfficer300ERIEBOULEVARDWEST.SYRACUSE,NEWYORK13202/TELEPHONE(315)428-6983June28,1996NMP1L1090U.S.NuclearRegulatoryCommissionAttn:DocumentControlDeskWashington,DC20555'0C.F.R.$50.71(e),10C.F.R.550.54(a)(3)10C.F.R.$50.59(b)(2)RE:NineMilePointUnit1DocketNo.50-220

Subject:

SubmittalofRevisionI4totheNineMilePointNuclearStationUnitIFinalSafetyAnalysisReport(Updated),IncludingChangestotheQualityAssuranceProgramDescription,andtheAnnual10C.F.R.550.59SafetyEvaluationSummaryReportGentlemen:Pursuanttotherequirementsof10C.F.R.$50.71(e),10C.F.R.$50.54(a)(3),and10C.F.R.$50.59(b)(2),NiagaraMohawkPowerCorporationherebysubmitsRevision14totheNineMilePointNuclearStationUnit1FinalSafetyAnalysisReport(Updated),includingchangestotheNiagaraMohawkPowerCorporationQualityAssuranceTopicalReport,andtheannualSafetyEvaluationSummaryReport.One(1)signedoriginalandten(10)copiesoftheUnit1FSAR(Updated),Revision14,areenclosed.CopiesarealsobeingsentdirectlytotheRegionalAdministrator,RegionI,andtheSeniorResidentInspectoratNineMilePoint.TheUnit1FSAR(Updated)revisioncontainschangesmadesincethesubmittalofRevision13inJune1995.Inaddition,manyoftheUnit1FSAR(Updated)Sectionshavebeenreformattedintheirentiretytoeliminateblankpages,establishauniformleft-marginjustificationformat,andtoreorganizetheinformationinto"Text/Table/Figure"order.Thecertificationrequiredby10C.F.R.$50.71(e)isattached.EnclosureAprovidestheidentification,reason,andbasisforeachchangetothequalityassuranceprogramdescription,Unit1FSAR(Updated)AppendixB,inaccordancewith10C.F.R.$50.54(a)(3)(ii).

Page2TheenclosedannualSafetyEvaluationSummaryReport(EnclosureB)containsbriefdescriptionsofchangestothefacilitydesign,procedures,tests,andexperiments.NoneoftheSafetyEvaluationsinvolvedanunreviewedsafetyquestionasdefinedin10C.F.R.$50.59(a)(2).Verytrulyyours,B.RalphSylviaChiefNuclearOfficerBRS/JJL/kapEnclosurespc:Mr.T.T.Martin,RegionalAdministrator,RegionIMr.D.S.Hood,SeniorProjectManager,NRRMr.B.S.Norris,SeniorResidentInspectorRecordsManagement J

UNITEDSTATESOFAMERICANUCLEARREGULATORYCOMMISSIONIntheMatterofNiagaraMohawkPowerCorporation(NineMlePointUnit1)DocketNo.50-220CERTIFICATIONB.RalphSylvia,beingdulysworn,statesthatheisChiefNuclearOfficerofNiagaraMohawkPowerCorporation;thatheisauthorizedonthepartofsaidCompanytosignandfilewiththeNuclearRegulatoryCommissionthiscertification;andthat,inaccordancewith10C.F.R.$50.71(e)(2),theinformationcontainedintheattachedletterandupdatedFinalSafetyAnalysisReportaccuratelypresentschangesmadesincetheprevioussubmittalnecessarytoreflectinformationandanalysessubmittedtotheCommissionorpreparedpursuanttoCommissionrequirementandcontainsanidentificationofchangesmadeundertheprovisionsof$50.59butnotpreviouslysubmittedtotheCommission.B.RalphylviaChiefNuclear0ficerSubscribedandsworntobeforeme,aNotaryPublicinandfortheStateofNewYorkandCountyof,this~~dayof,1996.NotaryPublicinandforCounty,NewYorkMyCommissionExpires:cLtNAM.'LANDERSNoteryPublic,StateofNewYohRegistrationNo.i908015QuahfiedfnjeffersonCoolnqConrrnissionExpiresOctober13,19r

ENCLOSE'IDENTIFICATIONOFCHANGES,REASONSAl'6)BASESFORN)PC-QATR-1(UFSARAPPENDIXB)

ENCLOSUREAIDENTIFICATIONOFCHANGES,REASONS,ANDBASESFORQAPROGRAMDESCRIPTIONCHANGES(UNITIUFSARAPPENDIXB)';:;":;-'.UFSARIA'ppe'ndh't::,B:,,:.".:';:.,',"::.;';;'::;::;:'Page'/SeetIon':.,-:':,,::::,::",,::.::-:,:l=,Si'ih:for,"Con'dttdlnj'.that,."the':Revised;Prigam::-",-"',".',Gi'ntin'iiesto'Stttis~fy)10CFRSO;'Appendh't'8iiid",::,+3","";::,Contitihn'en'::PreyIously,'.'.A'p'pr'o'y'ed;by":the':NRC::.'::',:";.',PageB.0-1,thirdparagraphChanged"ExecutiveVicePresidentNuclear"to"ChiefNuclearOf5cer"Reorganization.ReorganizationapprovedbytheNRCviaUnit1LicenseAmendment157andUnit2LicenseAmendment71,datedFebnuuy20,1996.PageB.1-1,SectionB.l.1,firstparagraphReplaced"contractorsandconsultants"with"suppliers"Editorial.NMPCusestheterm"suppliers"asasynonymof"contractors"and"consultants,"andpreferstheterm"suppliers."Theuseofanall~compassingterm(i.e.,using"suppliers"toincludeordescribecontractors,consultants,orvendors)doesnotaffectcompliancewith10CFR50AppendixB.PageB.1-1,SectionB.l.1,secondparagraphChanged"Eachorganizationaldepartment,includingNuclearGeneration,NuclearEngineering,andNuclearSafetyAssessmentandSupport(NSAS),isresponsibleforthequalityofitsownwork."toread"Eachorganizationaldepartmentisresponsibleforthequalityofitsownwork."Editorial.Editorial.N/APageB.1-1,SectionB.1.2.1a.Changed"isdelegatedbythePresidenttocorporateofflcers,asdescribedherein"toread"isdelegatedbythePresidenttocorporateoKcersandtheManagerQualityAssurance,asdescribedherein"EditoriaLToreflectthattheauthorityandresponsibilityoftheManagerQualityAssuranceisalsodescribed.a.Editorial.N/Ab.Changed"Figure13.1-1a"toread"Figure13.1-1"b.Editorial.b.Editorial.N/A

"',:::%.""UFSARAppendix':B;:.:,,';;::,:'":,;"-",".;;:Page/Section';:"';,':.;"::;"-PageB.1-2,SectionB.1.2.1.1,firstparagrapha.Changed"ExecutiveVicePresidentNuclear"to"ChiefNuclearOfficer"a.Reorganization.a.ReorganizationapprovedbyNRCviaUnit1LicenseAmendment157andUnit2LicenseAntendment71,datedFebnuuy20,1996.Changed"...includingallfunctionsperformedbyNuclearGeneration,NuclearEngineering,NuclearSafetyAssessmentandSupport,NuclearController,..."toread"...includingthePlantGenerationandEngineeringFunctionsundertheVicePresidentandGeneralManager-Nuclear,NuclearSafetyAssessmentandSupport(NSAS),BusinessManagement,..."b.Reorganization.SameasItema.PageB.1-2,SectionB.1.2.1.1,secondparagraphChanged"ControllerNuclearDivision"to"GeneralManagerBusinessManagement"Reorganization.Titlechange.Positiontitlechangetoreflectmanagementofbusinesscomputersandfiruume/accountingactivitiesunderthepositionofGeneralManagerBusinessManagement.ThisisanadministrativemanagementpositionwhichdoesnotperformQArelatedactivities.

".-;;:",.;UFSAR'"'Appendix8"':i,"".;:".':'-,".-"",:,:.'-::.,:,:PagelSectlon<'-',-'.-.',:l,-,:,l'..',;-';:::",",$'"',j'-"IderitIficatlon'oE;Cliaiige::.""i'."i!,;.'::;-':.':::-;::;,"",:.'.;:!'Reason'for,,Change':".'.::;i,"-:::--"'-:."'::.'-::"'.Bi'sls,for,'.,Co'n'eludingthat;thee':Revtsed,&iograiiii::.-':::;:>,,NConIlriues'hi,Satisfy.:10CFR50!AppendixB;and'";i.-;.:.,Cotniiiitd1entsPreviously',Approvedby'.theNRCg~:;PageB.1-2,SectionB.1.2.1.1,Item1Changed"TheVicePresidentNuclearGenerationreportstotheExecutiveVicePresidentNuclear,andisresponsibleforsafeandefficientoperation,maintenance,andmodificationoftheStationincompliancewithStationlicenses,applicableregulations,andtheQAProgram.TheVicePresidentNuclearGenerationdelegatestothePlantManagersandotherappropriatepersonnelauthorityforperfonnanceinaccordancewiththeQAProgram.SeeTableB-1forQAProgramelementresponsibilities.ActivitiesperformedundertheresponsibilityoftheVicePresidentNuclearGenerationinclude:"toread"TheVicePresidentandGeneralManager-NuclearreportstotheChiefNuclearOfficer,andhastheoveraHdivisionalresponsibilityforplantoperationandengineering.TheVicePresidentNuclearEngineering,PlantManagers,andtheGeneralSupervisorLaborRelationsreportdirectlytothisVicePresident.SeeTableB-1forQAProgramelementresponsibilities.ActivitiesperformedundertheresponsibilityoftheVicePresidentandGeneralManager-Nuclearinclude:"Corporatemanagementreorganization.ReorganizationapprovedbyNRCviaUnit1LicenseAmendment157andUnit2LicenseAmendment71,datedFebruary20,1996.

l i";":::::PUFSAR:'AppendhB.;:.;:$:;,"<'P<!:;.';:;::Ide'i'itHication'ofChang'e,"-,<:,.",::;"::::.,".,::'.,:",:,,,;':IBashfor".,'Co'ndudliigthat.the'.Revfsed,Program"'.",::".;.:;Contliities'to,'Sathfy,';.jOCFR50;Appendht.8:aiilq.';,:~Comntitm'ents',PrevIon'slyApproved,by',the'NRC!'-:::.v.,'ageB.1-3,Item2ChangedItem2toread:"ResponsibilitiesanddutiesoftheVicePresidentNuclearEngineeringandtheNuclearEngineeringorganizationaredescribedinUnit1UFSARSectionXIH.A.1andUnit2USARSection13.1.1.SeeTableB-1forQAProgramelementresponsibilities."Corporatemanagementreorganization.ReorganizationapprovedbyNRCviaUnit1LicenseAmendment157andUnit2LicenseAmendmettt71,datedFebrmuy20,1996.PageB.1-3,Item3ChangedItem3toread:"TheVicePresidentNuclearSafetyAssessmentandSupportreportstotheChiefNuclearOfficerandisresponsibleforQualityAssurance,Licensing,Training/EmergencyPreparedness,Security,andtheUnit2IndependentSafetyEngineeringChoupgSEO).SeeTableB-1forQAProgramelementresponsibilities.NuclearSafetyAssessmentandSupportresponsibilitiesaredescribedinUnit1UFSARSectionXIHandUnit2USARSection13."Corporatemanagementreorganization.ReorganizationapprovedbyNRCviaUnit1LicenseAmendment157andUnit2LicenseAmendment71,datedFebruary20,1996.PageB.1-3,Item4,firstparagraphChanged"ExecutiveVicePresidentNuclear"toread"ChiefNuclearOfficer"Corporatemanagementreorganization.ReorganizationapprovedbyNRCviaUnit1LicenseAmadment157andUnit2LicenseAugment71,datedFebruary20,1996.

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',:'~'~UFSAR'!Appendli,B.~,'-";,;:;=.j:",:~+:Page/Sectlon.:'..;,::;::.':;;,;'-:,',-,i,"::;;.:,';;";':;'.".,::,IdetItilici;:.Siishi'forConcludingtImt'thi"Revtse'dPiogrt'un'.'s,":...'.;:Con/biue's,,tYi:Sibsfy,'.10CFR50'AppendixB;ttnd"':g>:;:-'CotttrnItiiients'PievIottsly:Approv'edby'the'.NRC:,"'-'-':PageB.1-3,Item4,secondparagrapha.Changed"Tasksperformedtofulfilltheseresponsibilitiesinclude"toread"Tasksperformedtofulfilltheseresponsibilitiesaredelineatedinsiteproceduresandinclude"Editorial.a.Editorial.N/ACombinedInspectionsandNDEExaminationsasonetaskandremovedthefollowingidentifiedtasks:~CoordinatingandReportingInternalandExternalQAAssessments~OperationsExperienceA88essnlent~AdministeringtheEvaluationandCorrectiveActionProgramforDeviationEventReports(DERs)~DERTrendAnalysis~PreparingandProcessingQAOrganizationDocumentsb.Editorial.ManyofthesetasksarealsodescribedundertheresponsibilitiesofsupervisorsorinothersectionsoftheQATR.AdministeringtheEvaluationandCorrectiveActionProgramforDeviation/EventReports(DERs)istheresponsibilityofthePlantManagers.b.Editorial.N/AC,Addedthefollowingtasks:~RecordsManagement~DocumentControlc.Reorganization.c.ReorganizationapprovedbyNRCvialetterdatedJuly13,1995.

';':"':":jUFSAR'.Appeii'dbr'8-:.,:;:::::,';:.-,'::;:,.",IderiIdicaIIonofChange+~,;:;,:;:::~:,:.;-;,-.::,,".,",';-'Reisonfoi",Cliaiigi.",;";."..,:.","."..:':.;"',i:':,iBisls,t'or,'Coaduding'thatthe.Revtse'0Piogiasnt"-'"..'."'.'.-~Coritliiiies.,'to,Siibsfy.';10CFR50'Appendix:B,and':;:;"::::;>lCon'ti'nitntentsPk'vionsiy".Appr'ovedbytheNRC.":,=;";PageB.14,Item4.bChanged"...determiningapplicabilityofindustryandin-plantexperience"toread"~..assessmentsdeterminingapplicabilityofindustryandin-plantoperatingexperience"Editorialclarification.Incorporatestheterm"assessments"associatedwithoperationsexperienceassessmentsintosupervisorresponsibilities.Editorial.N/APageB.IQ,Item4.dChanged"...performingsourcesurveillancesofselectedprocurements"toread"...performingsupplierevaluationsandsourcesurveillancesofselectedprocurements"Editorialclarification.QualifiesthetypeofactivitiesthataredonebytheProcurementQualityAssuranceGroup.Editorial.N/APageB.14,Item4.eAddedItem4.etodescribetheresponsibilitiesoftheGeneralSupervisorQualityServicesReorganizationestablishednewpositionofSupervisorQualityServiceswhichwaslaterchangedtoGeneralSupervisorQualityServices.ReorganizationapprovedbyNRCvialetterdatedJuly13,1995.TitlechangeisadministrativeinnatureanddoesnotaffectpositionfunctionsorresponsibiTities.PageB.2-2,SectionB.2.2.3,firstparagraphChanged"ExecutiveVicePresidentNuclear"to'ChiefNuclearOKcer"Reorganizationtitlechange.ReorganizationreviewedandapprovedbyNRCviaUnit1LicenseAmendment157andUnit2LicenseAmendment71,datedFebruary'20,1996.

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';':".<<;.:-',',":'"',.Id4Basb"for',,Coiidiidbigthatthe.'Revfsed,Piog'ram'!"-.;,,",'--Continues'toSatbfy':,10CN50;Appen'dix'.B:arid:.'-',5$='CommitinentsPr'evIously,"Appi'ovedby,.theNRC:.;-.PageB.2-5,SectionB.2.2.15,Item1Changedwordingfrom"TheManagerQualityAssuranceisresponsibleforreportingonthestatus,adequacyandeffectivenessoftheNMPCQAProgramthroughtheNuclearDivisionInternalSALPTypeAssessmentReports"toread"TheChiefNuclearOfficerisresponsibleforreportingonthestatus,adequacyandeffectivenessoftheNMPCQAProgram"Clarificationandreorganizationtitlechange.AlthoughtheManagerQualityAssuranceisresponsibleforreportingonthestatus,adequacyandeffectivenessoftheQAProgramtotheChiefNuclearOfficer,itistheChiefNuclearOfficerthatreportstothePresidentorChiefExecutiveOfficer(CEO).TheChiefNuclearOKcerreportstothePresidentofNMPCasdescribedinUnit1LicenseAmendment157andUnit2LicenseAnieixlnient71,datedFebruary20,1996.PageB.2-5,SectionB.2.2.15,Item2Changed"ExecutiveVicePresidentNuclear"to"ChiefNuclearOfficer"Reorganizationtitlechange.ReorganizationofcorporatemanagementapprovedbyNRCviaUnit1LicenseAmendmerit157andUnit2LicenseAmendmeiit71,datedFebnuuy20,1996.PageB.24,SectionB.2.2.16Changedwordingfrom"TheSRABisastandingcommitteechairedbytheVicePresidentNuclearEngineeringandreportstotheExecutiveVicePresidentNuclearregardingdesignatedQAfunctionsattheNineMilePointNuclearStation"toread'TheSRABisastandingcommitteereportingtotheChiefNuclearOfficerregardingdesignatedQAfunctionsattheNineMilePointNuclearStation"Clarification.TomoreclearlyreflectPlantAdministrativeTechnicalSpecifications.ThechangemoreclearlyreflectsPlantTechnicalSpecifications,AdministrativeControlsSection,andalsoreflectscorporatemanagementpositiontitlechangesassociatedwithUnitILicenseAmendment157andUnit2LicenseAmendment71.PageB.24,SectionB.2.2.17Changedwordingfrom"TheSORCisanindependentreviewcommitteeresponsibletotheVicePresidentNuclearGenerationandtransmitsreportstotheSRAB"toread"TheSORCisanindependentreviewcommitteeresponsibletothePlantManagersandtransmitsreportstotheSRAB"Clarification.TomoreclearlyreflectPlantAdministrativeTechnicalSpecifications.ThechangemoreclearlyreflectsPlantTechnicalSpecifications,AdministrativeControlsSection,andalsoreflectscorporatemanagementpositiontitlechangesassociatedwithUnit1LicenseAmendment157andUnit2LicenseAmendnient71.

":;,j,:UFSAR;:Appe'adh'r",B::9'i::.".:I-'.,>,::::.-,;~,,',,",'.:.:.:'.,Ideiitific>>aIIon'of,Change;,',,~;-'.,"".,s'..",',':.:.,":,::i,;:,;'.:;:'-;,'..:':='."';.';;.Reasori;for,,:Changers,-;..-'":,';;;:-::>"::-,-.".',Cori(i'ues:,to',Satisfy,'10CPR50'Appeadh;B.'iiil"".4i>>CommitmentsPrevloiisly",.":A'jipx'ovedby,':the',NRC-">>."PagoB.24,SectionB.2.2.18Changedwordingfrom"...andactionsareverifiedbyQ1Ppersonnelpriortocloseout"toread"...andtheactionsareverifiedpriortocloseout"Clarification.WhileQ1Ppersonnelverifytheoverallclosureofallitems,othergroupsmaybeusedtodosomeoftheactualtechnicalverificationsforcompleteness.TheoverallindepeadenceandconfidentialityofQ1Phavenotchanged.ThetechnicalabiTityofotherdepartmeatsisusedtoreviewsomoofthoconcerns.PageB.4-2,SectionB.4.2.7PagoB.5-1,SectionB.5.2.6Chaagedwordingfrom"NQAorProcurementpersonnelotherthanthepersonwhogeneratedtheprocurementdociiment,butcpalifiodinQA,..."tored"Personnelotherthanthepersonwhogeneratedtheprocurementdocument,butwithadecpateuaderstaidingoftherecpirementsandintentoftheprocurementdocuments,..."AddedSectionB.5.2.6todescnboprocedurereviewprocessClarification.Asanalteraativetoperformingprocedurereviewsnolessfrequentlythaneverytwoyearstodetermineifchangesarenecessaryordesirable(ANS-3.2).NiagaraMohawkhasprogrammaticcontrolsinplacetocontinuallyidentifyprocedurerevisionswhichmayboneededtoensureproceduresareappropriateforthecircumstancesaadaremaintainedcurrenteThereisnospecificrepireaiontforanyparticulargrouptoperformthesereviews,onlythattheindividualsdoingthereviewadecpatolyunderstandthempirementsandintentofthoprocurementdocumeats.ThisisinaccordancewithNQA-l,4S-1,section3,whichisourstatedprogramformeeting10CFR50AppendixB.Thisdoesnotconstituteareductionofcommitmentsincewhoeverdoesthereviewfuactionisrequiredtobecpalified.ThisqualiT!cationisaccomplishedthroughtraining.NRCapprovalper10CFR50.54grantedvialetterdatedJanuary30,1996.PageB.7-1,SectionB.7.2.2Changedwordingfrom"WhencontractorsperformworkundertheirownQAprograms..."toread"WhensuppliersperformworkundertheirownQApfogfaiasEditorial.NMPCusestheterm"suppliers"asasynonymof"contractors,"aadpreferstbeterm"suppliers."Thouseofanall~passingtenn(i.o.,using"suppliers"toincludeordescnbecontractors,consultants,orvendors)doesnotaffectcompliancewith10CFR50AppendixB.

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UFSAR.:"Appiiidlx,B,"'.";'"-,'..~+~';':-',~IdeiitifiaitIo'iiof,Chaiige;;:,":;;'.-".:,;;.P,,;.,Contlniies,4i'SatlsfyiiOCH60,::Appendix'8'an'6=;,';.'"'~j(CoiniiiitinentsPit.vlo'iisly'!hpproved,by,that.NRC:;.'-:,:.'ageB.7-1,SectionB.7.2.3,Item1a.Changedwordingfrom"...resultinthesupplierbeingplacedontheQualiTiedContractorListDatabase(QCLD)asaqualifiedvendor"to"...resultinthesupplierbeingplacedontheQualifiedSupplierListDatabase(QSLD)"a.Editorialclarification.Toreflectuseoftheterm"supplier"ratherthan"contractor."a.Editorial.N/Ab.Changedwordingfrom"...byvirtueofthisability"toread"...byvirtueoftheirability"b.Editorial.b.EditoriaLN/AChangedwordingfrom"...characteristicsidentifiedbyNuclearEngineeringandNQA"toread"...CharacteristicsidentifiedbyNuclearEngineering"c.Clarification.TofullyreflectNuclearEngineeringresponsibilities.cNuclearEngineeringisresponsibleformaintainingthedesignbasisofsystems,structures,andcomporlentsandtfallslatesdesignrequirementstosupplierswhicharedeemedcriticalforaparticularitem/service.TheidentificationofcriticalmanufacturingandfunctionalprocessesandcharacteristicsbyNuclearEngineeringcontinuestosatisfy10CFR50AppendixB,Criterion7.Changedwordingfrom"...methodshavebeenidentifiedanddocumentedbywhichNQAwillverifyconformancetotheseiequlfelnentstoreadre@methodshavebeen$Ienttfiledanddocumentedwhichwillverifyconformancetotheserequirements"d.ClariTication.d.NQAisinvolvedwithverificationofsupplierprogramswithattentiontocriticalprocesses/characteristicsselected,unlesstheycanbeverifiedonsiteviatestand/orinspection.Theseresponsibilitieshavenotchangedand,therefore,continuetosatisfy10CFRSOhppendixB.

';"~~":.="-'::::<IdentIfimtloti':ot,.Change/!-"::.:-':;:.';';;:::::.::::,;;:,:.'.-'.::,'-.:."'%~Reasosn.for,Chatige,",':;:',;:,,:-:-',::,'.,:::Bashfor',Coiicliidlngthatthe':Revtsed,Prog'rain',-':;;~j,"NConttriues.'to';Sahfy':10CFR50:App'endlx.:B:aciid'-.::""4':-.Coi'iimitrneeriti':Prevto'tisly,::Approve'dby,'theNRC';-"PageB.7-2,SectionB.7.2.3,Item2a.Changedwordingfrom"NMPC-qualifiedsuppliersinvolvedinactiveprocurementaresurveyedevery3yrtomaintain..."toread"NMPC~ifiedsuppliersinvolvedinactiveprocurementaresurveyedevery3years~tomaintain..."Thechangefrom3yrto3yearsiseditorial.TheadditionofanotetoreflectatoleranceofonequarterofayearisalsoeditorialasthisreflectsRegulatoryGuide1.28,paragraph3.2,asdescribedinQATRTableB-3,sheet1of8.a.Editorial.N/A"<<Withatoleranceofonequarterofayear"b.Changedwordingfrom"Supplier3-yrsurveys..."toread"Supplier3-yearsurveys"b.Editorial.b.Editorial.N/APageB.7-2,SectionB.7.2.3,Item3AddedItem3toidentifysuppliers/organizationsthatarenotrequiredtobeevaluatedorlistedontheQualifiedSupplierListDatabase(QSLD).Clarification.ThesestatementsclarifytheuseoftheNationalInstituteofShuxlardsandTechnologyandotherNRClicensedutilitiesthatmeettherequirementsof10CFRSOAppendixB.PageB.7-3,SectionB.7.2.6Changedwordingfrom"...purchasedinaccordancewithNuclearEngineeringProceduresthatprovide.otoread"purchasedinaccordancewithproceduresthatprovide..."Clarification.ThesecontrolsarenotlimitedtoNuclearEngineeringpaicedures.Severaltypesofproceduresareusedtomakesurethatdesigncriteriaisincludedinpurchaserequirements.AlthoughEngineeringproceduresprovidecontrolstoassurethatitemssatisfydesignrequirements,thesecontrolsmayalsobefoundinNuclearInterfaceProceduresordepartmentproceduresotherthanEngineering.'heseproceduralcontrolscontinuetosatisfyIOCFRSOAppendixBCriterion7.PageB.9-2,SectionB.9.2.9Changedwordingfrom'...keptbyvendorsand/orforwardedtoNMPC"toread"...keptbysuppliersand/orforwardedtoNMPC"EditoriaLNMPCusestheterm"suppliers"asasynonymof"vendors,"andpreferstheterm'suppliers."Theuseofanall~conipassingterm(i.e.,using'suppliers"toincludeordescribecontractors,consultants,orvendors)doesnotaffectcompliancewith10CFR50AppendixB.10

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;;.~".';UFSAR::Appendix8;-g;.;g(~:A:,:;."::".-:."Identdici'tlon,of,:Cha'nge=;..:::;::";-.;.'".'-::c.-:.':j';::-;".Bashfor,Concludingthat,theReytsed,Prograni:"".:,'-',:;Coritliiites.4Sashy,;,10CFR50':Appendh;Baril;.';.':;..-,,;.ComnIitmeit9Prevlou'sly':Appr'oved.by.IheNRC<"-"-,PageB.10-1,SectionB.10.1ReplacedpolicystatementwithwordingfromNQA-1EditorialclarificationtoreflectwordingprovidedinNQA-1.TherestructuringoftheparagraphtoreflectNQA-1isconsistentwith10CFR50AppendixB,Criterion10.Allareascontinuetobereviewedexceptforthedeletionofwitnesspoints.Witnesspointshaveeitherbeenupgradedtoholdpointsordeletedbecausetheywerenotneeded.PageB.10-1,SectionB.10.2.2,Item4Changedfrom"Holdpointsand/orwitnesspoints"toread"Holdpoints"WitnesspointsarenolongerusedatNineMilePoint.AllwitnesspointshavebeenconvertedtoholdpointsordeletedfromNMPCprocedures.TheremovalofwitnesspointscontinuestosatisfyAppendixB,Criterion10,sincethosewitnesspointsthatwererequiredhavebeenupgradedtoholdliitsoPageB.10-2,SectionB.10.2.5B.10.2,6B.10.2.7B.10.2.8DeletedpreviousSectionB.10.2.5,whichstated"Witnesspointsrequiresufficientnotificationofthespecifyingorganuationpriortoperformanceofthespecifiedactivity"andrenumberedreinainingsectionsaccordingly.WitnesspointsarenolongerusedatNineMilePoint.AllwitnesspointshavebeenconvertedtoholdpointsordeletedfromNMPCprocedures.TheremovalofwitnesspointscontinuestosatisfyAppendixB,Criterion10,sincethosewitnesspointsthatwererequiredhavebeenupgradedtoholdpoints'ageB.10-3,SectionB.10.2.9Changedwordingfrom"Aprogramforinspectionandsurveillanceofactivitiesaffectingfireprotectionisestablished..."toread"Aprogramforinspectionandsurveillance,asrequired,foractivitiesaffectingfireprotectionisestablished..."Editorialclarificationforeaseofreadingaudsentencestructure.Editorial.N/APageB.11-2,SectionB.11.2.3,Item5PageB.18-1,SectionB.18.1Changedwonlingfrom"Anywitnessandholdpoints"toread"Anyholdpoints"Changedwonlingfrom"...includingthoseelementsoftheprogramimplementedbysuppliersandcontractors"toread'includingthoseelementsoftheprogramimplementedbysuppliers"WitnesspointsarenolongerusedatNineMilePoint.AllwitnesspointshavebeenconvertedtoholdpointsordeletedfromNMPCprocedures.Editorial.NMPCusestheterm'suppliers"asasynonymof"contractors,"andprefersthetenn'suppliers."TheremovalofwitnesspointscontinuestosatisfyAppendixB,Criterion10,sincethosewitnesspointsthatwererequiredhavebeenupgradedtoholdpolrlts.Theuseofanallmicompassingterm(i.e.,using"suppliers"toincludeordescribecontractors,consultants,orvendors)doesnotaffectcompliancewith10CFR50AppendixB.11

,'"::i';:UFSARA'p'peti'dlx.S,:;;".-.';.'-,.;.,'.':;.'-:)-:.-,""-PIdeiitificatlonof,Ch'ange';:-,;,,:j,'=,:;:;g,'.<<'::.~;."'~"',",:".;,";.".,Rea'sonfor;Change;..":j':'.;.':::.-',::@IBasIsfor,Coiicluding'that'theRevfsed.Prograii'i'...':::;;-Contlriue<<s'toSatisfy'10CFR50'App<<eindiIx'B'aiid'..';~";.~>,'.Conimsitinents:Prevlot'isly"'Approv'ed,by,theNRC-"-,";PageB.18-1,SectionB.18.2.3Changedwordingfrom"onceevery2yr"toread"onceevery2years"Editorial.EditorialN/ATableB-l,sheetIof2a.b.UnderProcedurescolumn,identiTiedQualityAssurance(QA),NuclearLicensing(NL),andNuclearTraining(N'I)undertheVicePresidentNuclearSafetyAssessmentandSupport(VP-NSAS),andidentifiedNuclearEngineering(NE)andNuclearGeneration(NG)undertheVicePresidentandGeneralManager-Nuclear(VPGM-N).RemovedNuclearProcurement(NP)fromtheNSASProcedurescolumntoreflecttransferoftheNuclearProcurementfunctiontoNuclearEngineering.IdentifiedNuclearEngineeringasresponsibleforQAProgramelementsassociatedwithCriterionIV,accordingly.Editorial,toreflectcorporatemanagementrestmcturing.b.Reorganization.a.Editorial.N/Ab.TheNuclearProcurementorganizationwastransferredfromNuclearSafetyAssessmentandSupport(NSAS)toNuclearEngineering.Theduties,functions,andresponsibilitiesofNuclearProcurementhavenotbeenaltered.c,RemovedTechnicalServices(TS)andInformationManagement(IM)fromtheNSASProcedurescotunm.coReorganization.cTheduties,responsibilities,andfunctionsperformedbyTechnicalServices(TS)andInformationManagement(IM)havebeenreassignedtootherbranches,asappropriate.TheQAProgramelementsonceimplementedbyTSandIMhavebeenintegratedintotheappropriatebranchandareidentifiedontheresnsibilimatrix.12 l,

+:,",,"..,'"'UFSAR'Ap'pend@8,:"..;;";"'.Bi'sh,'fot'.Con'du'din'g'that,'the".Revts'edPi'o'g'ram".,",;:.',:,",'~',.::,.ContlntIes,to.Satisfy',:jKFR50,Appendfix8;and:,,",:.'"":;;.';jCommttmerits',Prevlou'sty'."Appr'ovedby,thi".'RC:;""kTableB.l,sheet1of2(cont'd.)IdentifiedQualityAssuranceresponsibiTityforQAProgramelementsassociatedwithCriteriaVI(DocumentControl)toreflecttransferofresponsibilityfromNuclearEngineering.d.Reorganization.d.ReorganizationapprovedbyNRCvialetterdatedJuly13,1995.TableB-l,sheet2of2RemovedNuclearProcurement(NP),TechnicalServices(TS),andInformationManagement(IM),fromunderNSASProcedurescolumnandfromlistingofNMPCorganizations.a.Reorganization.a.ThefunctionofNuclearProcurementwastransferredfmmtheNuclearSafetyAssessmentandSupportorganizationtoNuclearEngineering.Thistransferdoesnotaffectdutiesorfunctionalresponsibilitiesand,therefore,continuestosatisfy10CFR50AppendixBcriteria.Theduties,responsibilitiesandfunctionsofTechnicalServicesandInformationManagementhavebeentransferredtootherorganizationsasappropriate.b.IdentifiedQualityAssuranceresponsibilityforQAProgramelementsassociatedwithCriteriaXVH(QualityAssuranceRecords)toreflecttransferofresponsibilityfromNuclearEngineering.b.Reorganization.b.ReorganizationapprovedbyNRCvialetterdatedJuly13,1995.TableB-3,sheet2of8ChangedDocumentcolumnrow"d"fromPara.4toread"Section4"EditoriaLEditorial.N/A13 1

EnclosureBtoNMP1L1090NINEMILEPOINT-UNIT1SAFETYEVALUATIONSUMMARYREPORT1996DocketNo.50-220LicenseNo.DPR-63

SafetyEvaluationSummaryReportPage1of60SafetyEvaluationNo.:89-019Rev.0,1,28c3ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:Mod.N1-89-174XI-14Low-PressureReactorFeedwaterSystemLow-PressureReactorFeedwaterSystemDesignPressureReductionDescription:Thepipewallthicknessoriginallyspecifiedforthelow-pressurereactorfeedwatersystemwasverymarginalforadesignpressureof600psig.Ifthestandardmanufacturingtoleranceandareasonablecorrosionallowance,wereconsidered,thesystempipingwasnotadequatefor600psig.For16"pipe,theavailablecorrosionallowanceforthe40-yearplantlifeisonly.013",assumingthepipewallthicknesswassuppliedattheminimumofthemanufacturer'stolerance.Theoriginalplantspecificationsrequiredacorrosionallowanceof.088".Inordertoprovideadditionalmarginforcorrosionovertheremainingplantlife,thedesignpressurewasreducedfrom600psigto530psig.Thisincreasedtheavailablecorrosionallowancefrom.013"to.050".SafetyEvaluationSummary:Thismodificationwillreducetheoriginaldesignpressureof600psigto530psig.Asaresultofthischange,pressuresafetyreliefvalvesinstalledonfeedwaterpumpsuctionpipingandonthefeedwatersideofthefeedwaterdraincoolersmustberesettothecorrespondingdesignpressure.Resettingthereliefvalvestothecorrespondingdesignpressurewillnotaffectsystemoperationbecausethevalvesprovidenegligiblepressurereliefduringnormaloperationoftheequipment/pipingeachvalveprotects.Todemonstratethatthereliefvalvesprovidenegligiblepressurerelieftotheequipment/pipingtheyprotectduringnormaloperation,thefield-correctedpumpcurveswerereviewed.Areviewofthepumpcurvesindicatesthatduringminimumflowconditions,areductionof150gpmofflowduetoallsixreliefvalvesliftingcorrespondstoapproximatelyzeropressurereduction.Thepurposeofthevalvesistopreventexcessivepressuresinthesystemwhenthesectionofthesystembecomesisolatedbyvalvesandthatsectionmaybesubjectedtounexpectedsourcesofheat.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage2of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:91-019Mod.N1-88-052N/ASpentFuelPoolInstallationofPoisonHighDensitySpentFuelRacksintheSouthHalfoftheSpentFuelPoolDescriptionofChange:ModificationNo.N1-82-013andSafetyEvaluation84-003Rev.1encompassedtheanalysesdesignandinstallationofeightpoisonspentfuelracks,or1710storagelocations,inthesouthhalfofthespentfuelpoolfora'totalinstalledcapacityof2776locations.ThiswasapprovedbytheNRCinAmendment54totheNMP1OperatingLicenseDPR-63.Theinstallationwasplannedinphasesasdescribedintheabovesafetyevaluation.Sixoftheeightrackswereinstalledpriortothisplannedmodification./Thismodificationinstalledtheseventh(216spaces)storagerackinthesouthwestcornerofthepool.Theeighthrack(198spaces)willbeheldinstoresascontingencystorage.Thesouthwestworkplatformwaspermanentlyremovedandreplacedbyatemporaryseismicstrutrestraint.Theremovaloftheworkplatformuncoveredthepoollinerwhichwasdeformedfromapriorinstallation.Thedeformation(orbubble)wasmappedandlocatedtodeterminetheextenttowhichoneoffourrackpedestalsupportshadtobemodifiedsoastoavoidthedeformation.Followingexactinformationobtainedfromthemapping,thepedestalwasreanalyzedandmodifiedaccordingly.Followingthepedestalmodification,thetemporaryseismicrestraintwasremovedandtherackinstalledalongwithitsrestraintsandseismicbeam.SafetyEvaluationSummary:Aseismiceventoccurringduringtheshortperiodinwhichtheracksareunrestrainedisnotconsideredacredibleaccidentcondition.Thisconditionwas SafetyEvaluationSummaryReportPage3of60SafetyEvaluationNo.:SafetyEvaluationSummary:91-019(cont'd.)(cont'd.)previouslydescribedintheJune1983submittaltotheNRCandwassubsequentlyapprovedinAmendment54.Heavyloadswillnotbehandledoverspentfuel.duringreracking.Priorcriticality,thermal-hydraulics,andpoolstructureanalyseswillnotrequirereanalysesasaresultofthismodification.Therackmechanicalanalysishas-beenrevisedtoaccountforthepedestalmodificationandwillbereviewedfollowingthepoollinermapping.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage4of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:91-033Rev.25.3Gale.4.16KVAC-DG-ES,Rev.2IX-18,FigureIX-6EmergencyDieselGeneratorEmergencyDieselGeneratorEssential.LoadingandLoadManagementDescriptionofChange:ThissafetyevaluationanalyzedachangetotheUnit1UFSARthatresultedfromreconstitutionofthedieselgeneratordesignbasisloadinganalysis.InformationcontainedinSectionIXoftheUFSARpertainingtodieselgeneratorratingsandaccidentloadingwaschangedtoshowmorecompleteandaccurateinformation.SafetyEvaluation'ummary:Maximumexpecteddieselgeneratorloadhasbeendeterminedbycalculation,comparedtoequipmentcapability,andfoundtobeacceptable.Informa'tionpreviouslyprovidedintheUFSARshowsthatmaximumdieselgeneratorloadiswithinthemachine'scapability.Thedieselgeneratorloadanalysishasdefinedthemaximumallowabledesignloadbasedonvendorinformationandregulatoryguidancedocuments.TheproposedUFSARchangesareconsistentwiththeanalysisanddemonstratethatthedieselgeneratorswillbeoperatedwithintheirrating.Withappropriatemanualactions,totalloadcanbemaintainedwithinthemaximumallowabledesignbasisloadlimit.ManualactionstobereflectedinUFSARFigureIX-6agreewithcurrentoperatingproceduresandincludeshuttingdownacorespraytoppingpump,controlroddrivepumpandacontainmentspraypumpunderappropriateplantconditions.TheimpactonaffectedsystemshasbeenanalyzedanditisconcludedthatthesesystemscancontinuetoperformtheirintendedfunctionsasdescribedintheUFSAR.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage5of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:93-056Rev.1,2&3SimpleDesignChangeSC2-0328-92FigureIII-1~-TitleofChange:ConstructaSpareTransformerFacilityDescriptionofChange:ThesparetransformerfacilitywasconstructedsouthwestoftheUnit2345-kVswitchyard.ThisfacilitywillbeusedforthestorageoftheadditionalsparetransformerforUnit2.SafetyEvaluationSummary:Theconstructionofthesparetransformerfacilitydoesnotimpactthepertinentlicensingissuesthatareassociatedwithhydrologicalengineering;i.e.,flooding,localintenseprecipitation(probablemaximumprecipitation),andtheimpactontheairintakeaccidentX/0(Chi/0),theatmosphericdispersioncoefficient.iBasedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage6of60SafetyEvaluationNo.:ImplementationDocumentNo.:94-004SimpleDesignChangeSC1-0281-91/SC1-0158-93UFSARAffectedPages:Dwg.B-40143-COverlay1-3System:CO2FireProtection,FireDetectionandProtection(FDP)TitleofChange:RetireStyreneFireDetectionZonesD-8013,D-6053VP,andDA-6063HDDescriptionofChange:Thischangeretiredinplacethreefiredetectionzones.ZoneD-8013islocatedintheStyrene(Binder)PumpHouse.Thepumphouseisitsown'buildinglocatednorthoftheWasteBuilding.Theflammablesubstancestyrenehasbeenremovedandnootherflammablesexistatthatlocation.Thepumpsarenolongeroperationalandthebuildingisdesignedexplosion-proof.ZoneD-6053VPisusedforstyrenevapordetectionlocatedinthePumpHouseandtheDOWSystem(RadioactiveWasteSolidification)mixingareaoftheWasteBuilding.Withstyreneremoved,thesearenotnecessary.ZoneDA-6063HDislocatedinthemixinghoodoftheDOWmixingarea,renderingitunnecessary.TheDOWSystemhasbeenretiredforyears,makingtheseselectedretirementspossible.SafetyEvaluationSummary:Thischangewillremovenuisancealarmspresentlyonthesystem.Withthealarmsandpanelengravingremoved,thiswillaidoperations.Thischangewillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage7of60SafetyEvaluationNo.:ImplementationDocumentNo.:94-007SimpleDesignChangeSC1-0156-92,SC1-0157-92,SC1-0158-92UFSARAffectedPages:System:TitleofChange:TableVl-1,FigureVl-22;X-16ContainmentCuttingandCappingofUnusedContainmentPipingDescriptionofChange:Theheadspraypiping,referencevesselleakratepiping,andtheelectrochemicalpipingareabandonedsystemsthatpenetratethedrywell.Sincethisunusedpipingcontainsvalvesorblindflanges,AppendixJTypeBoriCtestingisrequired.Thesesimpledesignchangescutandcappedunusedpipingandrestoredthedrywellpenetrationstoasparestatus.SafetyEvaluationSummary:/Thecuttingandcappingofunuseddrywellpipingalongwithremovalofvalvesorflangedendswillrestorethedrywellpenetrationstoasparestatus.CappingnearthepenetrationandeliminationofisolationvalveswilleliminateAppendixJTypeBorCtesting.Potentialleakpathsthroughvalvesorflangeswillbeeliminated.ThecappedlineswillbeconsideredsparesandwillbesubjecttoAppendixJTypeAtestingtoensureoverallcontainmentintegrity.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage8of60SafetyEvaluationNo.:implementationDocumentNo.:UFSARAffectedPages:System:94-008TemporaryMod.94-019X-34ServiceAirTitleofChange:InstallationofaPortableHouseServiceAirCompressorDescriptionofChange:ThistemporarymodificationinstalledaportableaircompressoratvalveHSA-113locatedattheTurbineBuildingelevation300'.Thistemporarymodificationwillpreventdepressurizationoftheserviceairsystemduringmaintenanceofcompressor95-01.Theintertiebetweenserviceairandinstrumentairwillbeclosed.Thiswillprovideassuranceofnoflowofairtotheinstrumentairsystemwhilemaintenanceisbeingperformedonserviceaircompressor95-01,topreventpotentialoilcontaminationofinstrumentair.SafetyEvaluationSummary:Theserviceairsystemdoesnothaveabackupairsupply.Iftheserviceairsystemdropsbelow20psigfortheplantpreactionfiresprinklerzonesand50psigforthedrypipesystems,therespectivealarmwillcomeinandthedrypipefiresprinklerzoneswillfill.Theportableaircompressorwillpreventthisfromoccurring.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage9of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-013Mod.N1-93-018FigureIX-224VDCSystemReplace24VDCBatteryChargersThismodificationreplacedtheexisting24VDCbatterychargerswithnewbatterychargingunitsofmoderndesign.Thismodificationalsoprovidedadisconnectswitchtoisolatethe48VDC,center-tapped,groundedneutralbatteryfromthebatterychargersanditsconnectedloads.SafetyEvaluationSummary:Thefailureof24VDCbatterychargersisnotaninitiatingeventforanydesignbasisaccident.Thereplacementoftheexisting24VDCbatterychargerswithsimilarequipmentisfunctionallyaone-for-oneequipmentsubstitutionwithequivalentelectricalcharacteristicsandgreaterreliability.Consequently,thiswillnotincreasetheprobabilityorconsequencesofanaccident.Nonewmalfunctionorfailuremodehasbeencreatedthatcouldcauseanewunanalyzedevent.Systemreliability,systemcharacteristics,equipmentqualifications,andcompliancewithfireprotectionandAppendixRrequirementsareunchangedorareimprovedbythismodification.Installationwillnotresultinareductionoftheplantsafetymargin.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage10of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:94-019Rev.0L1IVlod.N1-92-00510A-96,10A-114,10A-1184160VAC,600VACand125VDCSystemsTitleofChange:DescriptionofChange:ImproveElectricalCoordinationTheemergencydieselgenerator51-Vrelayanditsmiscoordinationwithdownstreamprotectivedeviceswasresolvedbydefeatingthetrippingfunctionofthe51-Vrelaywhenanautomaticcoresprayinjectionsignalisinitiated./Analarmcircuitwasaddedsothatactuationofthe51-Vrelayannunciatesinthecontrolroom.Acommonannunciatorwindowisusedfor51-Vrelayslocatedatpowerboards(PB)102and103;however,aseparatecomputerpointisprovidedforeach51-Vrelay.iForcircuitsassociatedwithPB16and17,electricalprotectivedevicecoordinationwasimprovedasfollows:1.ForPB16B/PB17Bmainsupplybreakers,thelongtimesettingsforexistingelectromechanicaltripdeviceswererevised.2.Forthefeederbreakertolightingvoltageregulator16,theexistingelectromechanicaltripdeviceswerereplacedwithnewelectromechanical'ripdevices.3.InPB161B/PB171B,onemotorcasecircuitbreaker(MCCB)wasreplacedwithanewMCCB.4,InPB16B/PB17B,forthefeederbreakerstoPB167,theexistingelectromechanicaltripdeviceswerereplacedwithnewelectromechanicaltripdevices.5.InPB167,twoMCCBswerereplacedwithtwonewMCCBs.

SafetyEvaluationSummaryReportPage11of60SafetyEvaluationNo.:DescriptionofChange:94-019(cont'd.)(cont'd.)6.InPB16B/PB17B,forthefeederbreakerstoPB1671A/PB1671C,thelongtimeandshorttime(PB17Bonly)settingsfortheexistingelectromechanicaltripdeviceswererevised.7.InPB1671A/PB'1671C,oneexistingMCCBwasreplacedwithanewMCCB.Forcircuitsassociatedwithbatteryboards(BB)11and12,electricalprotectivedevicecoordinationwasimprovedasfollows:1.InBB11/12batterysupplybreakers,theexistingelectromechanicaltripdeviceswerereplacedwithnewelectromechanicaltripdevices.2.InBB11/12,replacedselectedexistingMCCBswithfusesandfuseblocks.3.ForfuseslocatedatordownstreamofBB11/BB12,replacedselectedexistingfuseswithnewfuses.Forsomecircuits,fuseblockreplacementwasrequired./SafetyEvaluationSummary:Thereplacementofelectricalprotectivedeviceswithsimilarequipmentisschematicallyaone-for-onesubstitutionofcomponentswithfunctionallyequivalentcharacteristics.Themodificationoftheemergencydieselgenerator'soutputcircuitbreaker'strippingschemewillimprovetheavailabilityofemergencypowerwhenitismostneededbyreducingthepossibilityofaspuriousbreakertrip.Thismodificationwillalsoimprovetheavailabilityofsafety-relatedequipmentwhenanelectricalfaultoccurs.Consequently,thiswillnotincreasetheprobabilityorconsequencesofanaccident.Nonewmalfunctionorfailuremodehasbeencreatedthatcouldcauseanewunanalyzedevent.Systemreliability,systemcharacteristics,equipmentqualifications,andcompliancewithfireprotectionandAppendixRrequirementsareunchangedorareimprovedbythismodification.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage12of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-037Rev.1Mod.N1-89-079N/AEmergencyCoolingSystemNo.39EmergencyCoolingAppendixJModificationThismodificationcutoutandreplacedexistingvalves39-03and39-04andmodifiedvalves39-05and39-06withthereactorinthecoldshutdownconditionandsinglereactorpressureboundaryisolationviasafety-relatedmanualgatevalves39-01and39-02./SafetyEvaluationSummary:Thismodificationeffectivelyprovidesvalvereplacementandmodification.ThiswillresultinenhancedcontainmentintegrityandtestabilityanddoesnotincreasetheprobabilityofoccurrenceortheconsequencesofanaccidentormalfunctiontosafetypreviouslyevaluatedintheFSAR.ThereplacementandmodificationofthesevalvestoenhancetheirabilitytoisolatethecontainmentdoesnotcreatethepossibilityforanaccidentormalfunctionofadifferenttypethananyevaluatedintheFSAR.ItalsodoesnotreducethemarginofsafetyasdefinedinthebasisfortheTechnicalSpecifications.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

glSafetyEvaluationSummaryReportPage13of60SafetyEvaluationNo.:ImplementationDocumentNo.:94-038Rev.1SimpleDesignChangeSC1-0151-93Mod.N1-93-023UFSARAffectedPages:~System:TitleofChange:DescriptionofChange:N/AMainSteamSystem4'SIVBrakeInstallationandPoppetUpgradeThismodificationeliminatedrepeatedleakratetestfailuresonmainsteamisolationvalves(MSIV)toenhancetheirtestability.ThemodificationconsistedofinstallingvendorrecommendedMSIVpoppetretrofitpackages,andelectricbrakesandnewmotorswithextendedshaftsfortheoperatorsonthemotor-operatedvalves.SafetyEvaluationSummary:ThismodificationeffectivelyprovideschangestotheMSIVstoeliminateleakratetestfailuresandenhancetheirtestability.Thechangehasbeendesignedtominimizestemsusceptibilitytocracking,provideimprovedanti-rotationmechanism,poppetselfaligningfeaturesandadditionalhardfacing.Additionally,installationofthenewmotorswithbrakesontheinboardMSIVmotoroperatorswillpreventexcessiveslidingofthevalvesduringclosuretesting.Thiswillresultinenhancedcontainmentintegrityandtestability.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage14of60SafetyEvaluationNo.:ImplementationDocumentNo.:94-039Rev.0Bc1Mod.N1-88-052,PhaseIIAUFSARAffectedPages:N/ASystem:TitleofChange:SpentFuelPoolSouthwestCornerRackModificationsandAdditionofRackTopPlatformDescriptionofChange:ThischangeprovidedarepairsolutiontofacilitatetheinstallationofthespentfuelstorageracklocatedinthesouthwestcornerofthefuelpoolpriortorefuelingoutageRFO13.Thisrackwasoneoftworemainingtobeinstalledfromthererackcampaignduring1984.Anewworkplatformwasinstalledontopofthisrack.SafetyEvaluation.Summary:Revision0ofthissafetyevaluationrequiredthatpreviouslydischargedfuel(i.e.,fuelwithlowdecayheatgeneration)beusedwhenloadingthisspentfuelrackanddidnotallowfortheloadingofnewlydischargedfuelfromRFO13.ThisrestrictionwasestablishedbyNMPCtoprovideadditionalthermalmarginwiththeracktopplatforminstalled.Revision1ofthissafetyevaluationremovesthisrestriction(allowingRFO13newlydischargedfueltobeloadedintotherack)andinsteadrequiresthattheracktopplatformnotbeinstalledforaminimumperiodof180daysaftertherackhashadirradiatedfueltransferredtoit.The180daysisboundedbytheUnit1UFSARFigureX-7,DecayHeatGenerationvs.DaysAfterReactorShutdownCurve,whichindicatesthat110daysfollowingafullcoredischarge,decayheatgenerationisstabilized.Sincetheadditionofthe180-daywaitingperiodpriortoracktopplatforminstallationwillensurethattheintentoftheoriginalrestrictionismet(i.e.,theracktopplatformwillnotbeinstalledoverfuelwithahighdecayheatgenerationrate),thischangeisboundedbytheoriginalevaluationandhasnoimpactonthespentfuelpoolheatremovalcapability.ThismodificationinstallsoneofthetworemainingBoraflexdesignhigh-densityspentfuelstorageracksnecessarytofacilitateafullcoredischargecapabilityduringournextrefuelingoutage.Thismodificationwillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage15of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-051Mod.N1-91-02110A-118ReactorInstrumentReplaceACUREXThismodificationreplacedtheACUREXAutodataTen/5dataloggerslocatedininstrumentandcontrolcabinets1S10and1S69,withnewsafety-relatedprocessinghardwarelocatedininstrumentandcontrolcabinets1S16and1S17.Italsoreplacedtwoexistingrecorderswithone.LoggingoftorustemperatureindividualRTDvalueshasbeentransferredtotheprocesscomputer.RPScircuitsto1S16and1S17havebeenchangedforconsistencyofpowersources.TheLo-Lo-Loinputstothefuelzoneindicationwereremovedandthenormalizationconstant(kfactor)waseliminatedfromthecompensatedwaterlevelcalculation.SafetyEvaluationSummary:Nuclearsafetyisimprovedbythismodification.TheRPScircuitsarebetterbalanced,thusimprovingtheirloadcharacteristics.Theinstallationofmorereliableelectronichardwareimprovestheprobabilitythatthesystemwillbeavailableduringaneventwhereitisneeded,andtheinformationitprovideswillbemorereliable.Theremovalofthenormalizationconstantwillprovidemorereliableindicationthroughouttheentireinstrumentrange.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage16of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-052Mod.N1-87-042VIII-11;10A-118PlantProcessComputerRISIsolatorReplacementThismodificationinstalledasafety-relatedstate-of-the-artdataacquisitionsystem(DAS)toprovidesignalisolationforAPRM/LPRMandfeedwatersysteminputstotheplantprocesscomputer.IThemodificationreplacedtheexistingRochesterInstrumentisolatorsusedtoisolatesafety-relatedsignalsinputtotheplantprocesscomputer.TheisolatorswerereplacedwithanInput/Output(I/O)computersystemandinterfacedwiththeexistingplantprocesscomputersystemviaafiberopticcable.Thefiberopticcableisolatesallmaximumcrediblefaultsfromthesafety-relatedinputs.Thenew.I/Osystem,cabinets,I/Ocardsandcablesaresafetyrelatedandseismicallyqualified.SafetyEvaluationSummary:TheDASloadswillbeappropriatelyisolatedandprotectedtopreventmalfunctionsfromimpactingRPS.Also,thismodificationwillnotcauseachangetoanysysteminterfaceinawaythatwouldincreasethelikelihoodofanaccident.Allsafety-relatedequipmentandmaterialswillbeprocuredandinstalledtoapplicableregulatoryandindustrycodesandstandardstoensuresystemintegrity.ThenewDASperformsthesamedesignfunctionasthecurrentlyinstalledisolatorsandisbeingprocuredandinstalledtoequaltoorhigherdesignstandards.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage17of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:94-053Rev.051Mod.N1-94-002FigureVill-4ReactorRecirculationGEMACRecirculationPumpControlModificationDescriptionofChange:ThismodificationremovedfromservicefiveobsoleteandunreliableGEMACfunctiongenerators(FGs)usedinthereactorrecirculationpumpmotorgeneratorsetcontrolcircuits.TheFGsaidinlinearizingtherelationshipbetweenpumpspeedandreactorrecirculationpumpmotorgeneratorsetoutput.TheirsignalprocessingfunctionwillbereplacedbymodifyingthecamsineachBaileypneumaticpositioner.TheproposedmodificationisdefinedinGeneralElectric'sproposalforthereactorrecirculationcontrolsystemenhancements.SafetyEvaluationSummary:TheproposeddesignchangeisfunctionallyequivalenttothepresentFG/Baileyactuatorconfiguration.Thesystemresponseforeachreactorrecirculationcontrolloopwillremainlinear;theBaileypositioner,withtheAcharacterizercaminstalled,willperformtherequiredsignalprocessinginsteadoftheFGs.EliminationoftheFGsfromthecontrolloopswillprovideadditionalsystemreliabilityandrelieffromcalibrating,refurbishingorprocuringreplacementFGs.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage18of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:94-056Rev.0,1,53Mod.N1-88-153TableVl-3aSh2Bc3;Vll-5,FigureVll-1;X-2,FigureX-1System:TitleofChange:ShutdownCoolingandCoreSpraySystemsContainmentIsolationValve(AppendixJ)Modification-ShutdownCoolingWaterSealDescriptionofChange:Thismodificationprovidedaqualified,30-daywatersealfortheshutdowncoolingsystemisolationvalvesutilizinganominalflowof22gpmfrorrleitherloop11or12ofthecorespraysystem.ThisallowsUnit1toachievecompliancewith10CFR50AppendixJ,asrequiredbytheNRC,withoutthereplacementofisolationvalves38-01,38-13,and38-12.SafetyEvaluationSummary:/Thiswatersealwillresultinenhancedcontainmentintegrity.Theadditionofcheckvalves38-165,166,167,168,169,170,171,and172providesisolationbetweenthehigh-pressurereactorcoolant:systemandthelow-pressurecorespraysystem.Thesealwatersystemdesignuptothecheckvalvesmeetsthesamedesigncriteriaasthereactorcoolantsystemwithrespecttosafetyclassification,temperature,andpressure.LeaktestingforthesecheckvalveswillbeinaccordancewithSpecification3.2.7.1.Therefore,adequateassuranceisprovidedsuchthatthelow-pressurecorespraysystemwillnotbedamagedbyoverpressurizationandresultinpotentiallossofintegritywithsubsequentreleaseofradioactivity.TheacceptabilityofthedesignregardingsingleactivefailureundercertainscenarioswasfoundacceptablebasedonthePRAstudyandguidelinesprovidedbyNUREG-0800andGenericLetter88-20.IthasbeendeterminedthatnoexemptionisneededfromtheAppendixJcompliancestandpointduringthisscenariobasedonguidanceprovidedbyNUREG-0800andGenericLetter88-20.TheNRChasissuedaSafetyEvaluationReport(SER)ontheTechnicalSpecificationAmendmenttoaddthenewwatersealcheckvalvestothePressureIsolationValveTable3.2.7.1.ThisSERhasreviewedthenewdesignconfigurationforwater-sealingtheshutdowncoolingisolationvalvesusingthe SafetyEvaluationSummaryReportPage19of60SafetyEvaluationNo.:SafetyEvaluationSummary:94-056Rev.0,1,&3(cont'd.)(cont'd.)corespraywaterinordertomeet10CFR50AppendixJcriteria,includingthetwoscenariosunderwhichthesinglefailurecriteriaisnotbeingmet.Nosignificantadverseimpactonshutdowncoolingandcorespraysystemperformancewillresultasaconsequenceofthismodification.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage20of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:94-057Rev.1Mod.N1-91-009FigureVll-3;10B-58;TableXV-4,ContainmentSprayReplaceOperatorsonContainmentSprayIntertieValvesEPN80-40and80-45DescriptionofChange:Thismodificationreplacedthehandwheelsonvalves80-40and80-45withpneumaticoperatorsdesignedtofail-open.Theremovalofthehandwheelsgivesoperatorsgreaterflexibilitywhilethefail-opendesignensuresawatersealfor10CFR50AppendixJ.lSafetyEvaluation'Summary:Thedesignfunctionofintertievalves80-40and80-45istobeinthenormallyopenposition,ensuringinterconnectionoftheprimaryandsecondaryloopsofcontainmentsprayinordertoprovideawatersealinaccordancewith10CFR50AppendixJ.Theadditionofpneumaticoperatorsclassifiedassafety-relatedactive,anddesignedsothatonalossofmotivepowertheairwillbereleased,allowingthespringtoopenthevalve,willnotchangethedesignfunctionofthevalves.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage21of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-060SimpleDesignChangeSC1-0087-93N/AServiceWaterEmergencyServiceWaterSupportsThissimpledesignchangeaddednewsupportstotheservicewaterinletandoutletpipingtotheReactorBuildingclosedloopcoolingheatexchangers.Existingsupportswerereworkedandreplaced.SafetyEvaluationSummary:Thenewsupportarrangementwillbeinaccordancewiththeoriginaldesignbasiscriteria.AIIpipingstresswillbelessthantheallowablespecifiedinB31.1-55andallsupportswillhaveallowableloadslessthanthemanufacturer'sallowableorlessthanAISC8thEditionallowable.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage22of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-062Rev.05.1SimpleDesignChangeSC1-0059-94III-23;10B-69N/AFoamRoomWallReplacementThissimpledesignchangeremovedtheequipmentsupportsattachedtotheFoamRoomwestandsouthprecastconcreteexteriorwallpanelsandprovidednewsupports.Thesewallpanelswereremovedandreplacedwithatemporaryenclosureuntilamasonrywallwasconstructed.WeldswererepairedtoDCvalveboard¹11totheexistingembeddedfloorchannels.An8-inchreinforcedblockwallwithabrickveneerwasthenconstructed.SafetyEvaluationSummary:Thedesignoftheequipmentsupports,thetemporaryenclosure,theblockwallbarrier,andthemasonrywallconsiderstherequirementsdescribedintheUpdatedFinalSafetyAnalysisReport(UFSARj.ThedesignsatisfiesthelicensingbasisrequirementsdescribedintheUFSAR.TheweldrepairofthisvalveboardwillsatisfytherequirementsoftheSQUGGenericImplementationProcedure.Thischangewillhavenoimpactonthesafeoperationorshutdownoftheplant.Basedontheevaluationperformed,itisconcludedthatremovaloftheprecastconcretepanelsandreplacementwithareinforcedconcreteblockwalldoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage23of60SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:System:TitleofChange:94-068SimpleDesignChangeSC1-0062-9410A-118120VACDistribution'DCSC1-0062-94,InstallationofDataAcquisitionSystemDescription:ThismodificationinstalledapermanentDataAcquisitionSystem(DAS)toreplacetheindividualDAAScomputerspreviouslyinuseintheAuxiliaryControlRoom.ThescopeofthismodificationwaslimitedtotheinstallationofallcomputerequipmentassociatedwiththeDAS,alongwithanasynchronouscommunicationslinktobeutilizedfordatatransfertoaNetworkFileService.Thisincludedthemountingofthecomputercabinet,andprovidingapermanentpowersupplyforthesystemMGset167computerpanelboard.AnewcablewasroutedintheAuxiliaryControlRoombetweenMGset167computerpanelboardthroughexistingracewayandnewlyinstalledraceway./SafetyEvaluationSummary:ThefunctionoftheDAS,withoutinputsfromprocesscontrolinstrumentation,isnonsafetyrelatedanddoesnot.haveanelectricalinterfacewithanysafety-relatedsystemsorcomponents;therefore,anelectricalfailureofthesystemwillhavenoimpactonplantsafety.Inaddition,thesystemreceivesitspowerfromMGset167computerpanelboard,andsincetheloadsassociatedwiththispanelboardarenotrequiredforsafeplantshutdown,theDASisalsonotrequiredforplantshutdown.Structurally,theinstallationdetailsconformtotherequirementsofaseismicClassIarea.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage24of60SafetyEvaluationNo.:ImplementationDocumentNo.:USARAffectedPages:94-069SimpleDesignChangeSC1-0039-94TablesVl-1,Vl-3bSh2;Vll-34,FigureVll-13System:TitleofChange:Hydrogen/OxygenMonitoringH,/O~SampleLineReductionDescription:Thissafetyevaluationaddressesthereductioninthenumberofsamplepointsforthehydrogen/oxygenmonitoringsystem.Specifically,thissimpledesignchangeretiredonesampleline,streamAforH,/0,channel¹11andtwolines,streamsAandCforH,/0,channel¹12.Thiswasaccomplishedbycuttingandweldingacaponthesamplelinesoutsidethedrywellbeforethefirstisolationvalve.Theelectricalconnectionsweredisconnectedandtheisolationvalvesandpipingwereretiredinplace.ControlRoomindicationwasblankedanddeleted.Thisreducedthenumberofsamplepointsfromthedrywelltotwo,oneforeachchannel,andtwofromthetorus,oneforeachchannel.Sincethissafetyevaluation,isgenericwithrespecttothereductioninthenumberofsamplepointsforH~/0isolationvalveclosure,asdirectedbyOP-9,uptonolessthanonesamplefromthedrywellandtorusforeachchannelofH,/Owasevaluatedandjustifiedbythissafetyevaluation.SafetyEvaluationSummary:TheH,/0,monitoringsystemisclassifiedassafetyrelatedasaresultofRegulatoryGuide1.97.However,thesystemisapassivemonitoringsystemandisneithertheinitiatornorthecontributortoanyaccidentsevaluatedintheUFSAR.Thereductionofthenumberofsamplepointswillnotincreasetheprobabilityofoccurrenceofanyoftheseaccidents.Basedontheresultsofnumerouscontainmentmixingstudies,theresponsetothedesignbasiseventwillbeunchanged.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage25of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:94-070SimpleDesignChangeSC1-0070-9410A-118ReactorRecirculationControlSystem(RRCS)TitleofChange:InstallationofCable&TerminationsfortheDataAcquisitionSystem(DAS)DescriptionofChange:Thenewdataacquisitionsystem(DAS)consistsofaPC,videomonitor,printerandanenclosurewhichwillbelocatedintheAuxiliaryControlRoom.ThenewDASwillprovideinformationfortrendingandtroubleshooting:thatwillincreaseboththereliabilityandcapacityfactoratUnit1.Thissimpledesignchangeelectricallyconnectedthereactorrecirculationcontrolsystem(RRCS)totheDAS.Inaddition,severalcableswererunfromvariouscabinetstotheDASinpreparationforotherinstallations.Thesecables'werestoredintheexistingcabletraysuntilfinalinstallation.ThescopeofthischangeinvolvedroutingcablethroughouttheAuxiliaryControlRoomandterminatingcablesattheDASandtheRRCS.Theinstallationrequiredroutingcablethroughexistingcabletraysandterminatingtheseconductorsatvariouspointsinthelogic.Thecableismultiple-conductor,twisted,shieldedpair016.TheshieldsofeachpairweregroundedtopreventextraneousnoisefromenteringtheDAS.Allterminationsweremadeonterminalblockswithringtongueterminals.Asafety-relatedsignalisolatorwasinstalledtoisolatethesafety-relatedreactorrecirculationtotalflowsystemfromthenonsafety-relatedDAS.SafetyEvaluationSummary:ThelogicoftheRRCSwillbeunchangedbythismodification.ThecrediblefailuresthatthischangecanproduceareenvelopedinSectionXVoftheUpdatedFinalSafetyAnalysisReport.Crediblefailuresincludethelossorsuddenreductionofthecontrolsignalinoneormorereactorrecirculationloopsduetoashortedleadinthecontrolcircuit.TheriskofashortisminimalduetotheDASbeingapassivesystemthatwillmonitorsystemparametersonly.Thecontrolsystemwilloperateasdesignedwithnochangesinresponseorcontrol.

SafetyEvaluationSummaryReportPage26of60SafetyEvaluationNo.:SafetyEvaluationSummary:94-070(cont'd.)(cont'd.)Inaddition,theinstallationofthesafety-relatedisolationamplifierinthetotalreactorrecirculationflowcircuitwillhavenoeffectonthecircuit.Theinputresistanceoftheisolatorisgreatenoughsothatitwillnotadverselyaffectflowinputtotheaveragepowerrangemonitors.TheClass1Eisolatorisdesignedtoadequatelyisolatethesafety-relatedsignalfromanyfaultsortransientscausedbythenonsafety-relatedDAS.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage27of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:94-072Rev.08c1Mod.N1-90-041TableVl-3bSh2;Vll-2,Vll-3,Vll-4,Vll-7,FiguresVll-1,Vll-2;10A-108,10A-109,10A-110,10A-112,10A-113,10A-114,10A-118;10B-63;TableXV-9aSystem:TitleofChange:CoreSpraySystemCoreSprayMinimumFlowRecirculationLines/ThrottlingDescriptionofChange:Thismodificationinstalledseparateminimumflowrecirculationlinesforeachcore/spraypumpset.Inaddition,theinboardisolationvalveswerethrottledtoslowlyinjectcoresprayduringanticipatedtransientwithoutscramandsmallbreakloss-of-coolantaccidentevents.Toaccomplishthis,EOPjumperswereinstalledintheControlRoomwhichinhibitstheinitiationandinterlocksignalsfortheinboard,outboardandtestreturnvalves.Thetestreturnvalvesarerequiredtobeopenedtosupportextendedrecirculationflowandcorespraypumpsetoperationfortheshutdowncoolingwaterseal.SafetyEvaluationSummary:Theanalysissectionclearlydemonstratesthattheapplicabledesignandlicensingcriteriahavebeensatisfied.Thisincludesbothnormaldesignbasisfunctions,manualEOP-directedoperation,andshutdowncoolingsystemwatersealrequirements.Theimpactofseparateminimumflowrecirculationlinesandinboardvalvethrottlingonrequiredcoresprayinjectionflowshasbeencalculated.Basedonthecalculation,thecorespraysystemprovidesadequateflowtosatisfy10CFR50.46.Redundancy,separation,AppendixR,seismicqualificationandenvironmentalqualificationhavebeenincorporatedintothedesignandconfirmedbyanalysis.Thischangedoesnotincreasetheprobability,consequencesorcreateadifferenttypeofaccidentormalfunctionofequipmentimportanttosafety.Themarginofsafetyisnotdecreased.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage28of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:-System:94-074DER1-94-0224VI-32ContainmentSpray,CoreSpray,ContainmentSprayRawWater,NitrogenSupplySystem¹12,NitrogenSupplySystem¹11TitleofChange:LicensingDocumentChangeRequest1-93-IST-006totheNMP1ISTProgramPlanandLDCR1-94-UFS-056totheUFSARDescriptionofChange:I/ThissafetyevaluationevaluatedadditionstoanddeletionsfromtheIn-ServiceTesting(IST)ProgramPlan,basedontherecentdevelopmentand/orrevisionsofSafetyClassdeterminationswhichnecessitatechangestotestingrequirements.SafetyEvaluationSummary://Ithasbeendeterminedthatoverpressureofthecontainmentduetomalfunctionofpressurecontrolvalves(PCV)inthenitrogensupplysystemisnotadesignbasissafetyconcernasitwouldrequirethefailureof1)aPCVand2)afailureopenofanisolationvalve.Thiswouldconstitutetwoactivefailuresofsafety-relatedcomponentsandisbeyondthedesignbasisoftheplant.Therefore,thereliefvalvesdonotneedtobesafety-relatedactiveandinclusionofthereliefvalvesintheprogramisnotrequired.SectionVI-F.3oftheUpdatedFinalSafetyAnalysisReport,ContainmentVentilationSystem,containslanguagewhichisvagueandrequiresclarification.Thissectionstatesthatthereliefvalvesandoverpressureregulatorsinthenitrogenmakeupsupplyline"weretestedpriortoinitialstartupandperiodicallythereafterforoperabilityandsetpoint."Notethatthisstatementisinthepasttense(itdoesnotcommittocontinuoustesting),whileallothertestingdescribedinSectionVl-FandreferencestoISTforothersystemsinSectionVllareinthepresenttense.ThestatementistoberevisedpriortodeletingthereliefvalvesfromtheISTProgramPlan.Further,thePCVsarenottestedperiodicallyatthistime;PCVsareexemptfromtestinginaccordancewithASMEXIIWV-1200.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage29of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:94-075Mod.N1-93-013TableIX-1Sh1-3;X-18;10A-115ContainmentAtmosphereMonitoringSystem,H~/0,AnalyzerTitleofChange:DescriptionofChange:ReplaceH,/0,MonitoringSystemThismodificationreplacedthehydrogen/oxygen(H,/O~)monitoringsystem,cabinets,andanalyzers.TheprevioussystemwasproducedbyBeckmaninstrumentsandinstalledpriortoRegulatoryGuide1.97andNUREG-0737requirements.Duetoageandthereclassificationassafetyrelated,themaintenancehadbecomeextensive.AnewTeledyneAnalyticalInstrumentsH,/0,monitoringsystemwasinstalledinplaceoftheBeckman.Thecabinetsaremountedinthesamelocation,withthecontrolcabinetmountedonthecolumnacrosstheaisle.TheTeledynesystemwasprocuredsafetyrelatedandisfullyseismicallyandenvironmentallyqualified./SafetyEvaluationSummary:Theanalysisclearlydemonstratescompliancewithallapplicablecriteriaincludingsafetyclassification,seismicqualification,environmentalqualification,powerrequirementsandseparation.Calculationshavebeenperformedforthetransportationtime,responsetimeandaccuracyandassurecompliancewithdesignbasisfunctionsandlicensingcommitments.Specifically,therequirementsof10CFR50AppendixA,General,DesignCriterion41,AppendixB,QualityAssurancerequirements,IEEE-344,RegulatoryGuide1.97,NUREG-0737,FireProtectionprogramandISTprogramhavebeensatisfied.Thischangedoesnotincreasetheprobability,consequencesorcreateadifferenttypeofaccidentormalfunctionofequipmentimportanttosafety.Themarginofsafetyisnotdecreased.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage30of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:94-079DER1-93-0921VI-21,VI-26,TableVl-3bSh4TraversingIn-coreProbe(TIP)TIPSystemContainmentIsolation-LDCRThissafetyevaluationanalyzedamethodtomoreaccuratelyrepresenttheexisting'esignofTIPsystemcontainmentisolationfeaturesintheUnit1UFSAR.Valveconfiguration,isolationlogicandvalvemotivepowerareaddressed.WordingwasaddedtotheUFSARtodescribetheTIPballandshearvalvesandhowtheballvalvesarepreventedfromreopeningafteranisolationsignalclears.ISafetyEvaluationSummary:ApplicablecriteriahavebeenreviewedtoverifythattheTIPcontainmentisolationdoescomplywithplantlicensinganddesignbasisrequirements.TheabilityoftheTIPsystemtoremainisolatedfollowingacontainmentisolationisassuredbysystemdesign,normaloperatingconfigurationandproceduralcontrols.IntheunlikelyeventtheTIPguidetubesfailtoisolate,calculatedaccidentdosesarenotsignificantlyimpactedandarewellwithin10CFR100limits.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion..

SafetyEvaluationSummaryReportPage31of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:94-080Rev.0&1Mod.N1-94-003IV-27,IV-28,IV-29,FigureIV-9;XVI-5,XVI-12,XVI-21,XVI-122,TablesXVI-2Sh152,XVI-9a,FiguresXVI-12a,XVI-12bSystem:TitleofChange:DescriptionofChange:ReactorVesselReactorCoreShroudRepairTheshroudmodificationwasdesignedtoprovideanalternativeloadpathforallType304stainlesssteelcircumferentialwelds(weldsH1-H7).ThemodificationensuresthestructuralintegrityofthecoreshroudbyreplacingthefunctionofcoreshroudweldsH1throughH7withfourstabilizerassemblies.'Thestabilizerassembliesarecomprisedoffourtie-rodassembliesandfour'oreplatewedges.SafetyEvaluationSummary:Thisevaluationhasinvestigatedtheinstallationofcoreshroudstabilizer'satUnit1.Theevaluationoftheshroudmodificationhardwareincludeddesign,code,materials,fabrication,structural,systems,installationandinspectionconsiderations.TheevaluationconcludedthattheproposedmodificationisinaccordancewiththeBWRVIPCoreShroudRepairDesignCriteriaandtheNRCSafetyEvaluationReport(SER)ontheBWRVIPShroudRepairCriteria.TheUnit1repairmodificationofthecoreshroudistobeperformedasanalternativetoASMESectionXI,aspermittedby10CFR50.55a(a)(3).Consequently,NRCapprovalofthisrepairapproachisrequired.ThissafetyevaluationdocumentstheNIVIPCreviewoftherepairinaccordancewiththeprovisionsof10CFR50.59.Aseparatesafetyevaluation(95-013)wasperfoimedtoevaluatetheacceptabilityoftheinstallationofthecoreshroudstabilizerassembliespriortoNRCapproval.TheevaluationconcludedthattherearenounreviewedsafetyquestionsassociatedwithinstallingtherepairpriortoNRCapproval,providedthereactorremainsinthecoldshutdownconditionorthehotshutdownconditionforthe SafetyEvaluationSummaryReportPage32of60SafetyEvaluationNo.:94-080Rev.0&1(cont'd.)SafetyEvaluationSummary:(cont'd.)performanceofnoncriticalhydrotestingabove212'Fand/ortheperformanceofCRDscramtimetestinguntilNRCapprovaloftherepairisobtained.Additionally,SE95-007wasperformedtoreviewpotentialsafetyimpactsoftheinstallationactivitiesassociatedwiththerepair.Theevaluationconcludedthattherearenounreviewedsafetyquestionsrelativetotherepairinstallationactivities.TheNRCissuedaSER,datedMarch31,1995,entitled"SafetyEvaluationoftheRepairProposalfortheNMP1CoreShroud."TheNRCSERhasreviewedalloftherepairdesignaspectsandhasconcludedtherepairdesignisacceptable.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage33of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:95-002Rev.0L1SimpleDesignChangeSC1-0067-94FigureVll-1CoreSprayCoreSprayIVPressureBindingReliefThismodificationaddedapressurebindingreliefpathtocoresprayvalves40-01,40-09,40-10,40-11,andtestreturnvalves40-05and40-06,toensurethevalveswillopenunderallpostulatedconditions.Forthecoresprayvalves,aninstrumentlinewasconnectedtotheexisting1/4-inchtapforthelanternglandstuffingboxandconnectedtothereactorsidedrainvalves.Thedrainvalveswerelockedopentoprovidethereliefpathtothereactorsideprocesspiping.Thevalvepackingwasmodifiedtoallowpressureinthebonnettorelievethroughthe1/4-inchtap.Forthetestreturnvalves,asmallholewasdrilledintothediskonthereactorsideofthevalvetoprovidethereliefpath.Alsoincludedinthismodification,thedrainvalveconfigurationofvalve40-05wasrevisedtoprovidetwovalvesandathreadedcap.ThischangewasrequiredtoenabletheattachmentofDPmeasurementequipmentacrossthevalveduringGenericLetter(GLI89-10dynamicflowtesting.Thesedrainvalvesarelockedclosedduringnormalplantoperation.SafetyEvaluationSummary:Thecorespraysystemisrequiredtooperatetopreventoverheatingofthefuelfollowingapostulatedloss-of-coolantaccident.Theinsidevalvesarerequiredtoopenwhenreactorpressureis365psigorlessandthetestreturnvalveswillberequiredtoopentofacilitatethrottlingofthecoresprayflowtothereactortomaintainwaterlevel.Theadditionofapressurereliefpathtothesevalveswillpreventthepotentialforpressurelockingintheredundantcoresprayloops,andtheadditionofdoubleisolationdrainvalvestoonevalvewillenableGL89-10dynamictesting.ThismodificationwillhavenoeffectonaccidentsormalfunctionspreviouslyevaluatedintheUFSAR.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage34of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-003SimpleDesignChangeSC1-0089-94X-35,X-36,FigureX-9InstrumentAirSystemInstrumentAirUpgrade-Valve94-91LogicChangeDescriptionofChange:Thissimpledesignchangeaddedapressureswitchcontactinthecontrolcircuitofair-operatedvalve94-91sothatiflowpressureissenseddownstreamofthe'alve,thevalvewillclose.Thisenhancesavailabilityofthesafety-relatedportionoftheinstrumentairsystemshouldthenonsafety-relatedpipingdownstreamofvalve94-91fail.Additionally,apressureindicatorwasaddedtomonitorthesameprocesspressureasthepressureswitch.SafetyEvaluationSummary:TheapplicablecriteriafromtheUFSAR,ChapterX,XVand10A,havebeensatisfiedbythissimpledesignchange.SinglefailurecriteriahasbeenaddressedandsafetyclassdeterminationNo.93-084evaluatedforimpact.Thecomponentsaddedarenonsafetyrelatedandnotrequiredtoberedundant.Theaddedcableisinconduitand,therefore,thefireloadinthisareaisnotincreased.Thevalvewillperformitssafety-relatedfunctiontofailclose.Theavailabilityoftheinstrumentairsystemisenhancedbythischange.Thischangedoesnotincreasetheprobability,consequencesorcreateadifferenttypeofaccidentormalfunctionofequipmentimportanttosafety.Themarginofsafetyisnotdecreased.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage35of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:95-007Mod.N1-94-003N/ARXVECoreShroudRepairInstallationTheNRCissuedGenericLetter94-03duetoobservedcrackinginthecoreshroudsofseveralBWRs.Thisgenericletterrequiresinspectionoftheshroudand/orrepair,ifnecessary.NMPCwilleitherinspectandpossiblyperformarepairiftheweldinspectionnecessitatesitorperformapreemptiverepairoftheshroudduringRFO13.TheUnit1reactorcoreshroudrepairisdesignedtostructurallyreplaceshroudweldsH1throughH8.Theinstallationoftheentirerepairinvolveselectricaldischargemachining(EDM)oftheshroudsupportconeandshrouditself,whichwillgenerateveryfineparticlescalledswarf,theattachmentofatrolley/buggytotheRefuelBridge,theadditionofanauxiliarybridgeonReactorBuildingEl.340,andotherspecialconsiderationsfortheshroudrepair.,Thissafetyevaluation(SE)coverstheshroudrepairinstallationactivitiesandwillsupplementSE94-080,"CoreShroudRepair."SafetyEvaluationSummary:Theinstallationofthecoreshroudrepairrequiresthatspecialequipmentandprocessesbeusedtominimizethein-vesseldebrisgenerationandprovideminimalimpactonotherworkbeingperformedonReactorBuildingEl.340.Thedesignandfunctionofthespentfuelpoolcooling(SFP)andthereactorwatercleanupsystemsarenotbeingalteredduringtherepairinstallation.Bothsystemshavebeenevaluatedandwillcontinuetoperformasdesignedduringandaftertherepairinstallation.TheSFPsystemisdesignedtoremoveparticlesassmallas1micron.TheswarfparticlesfromtheEDMprocesswhichentertheskimmersfromthetankoverflowwillbealmostentirelyremovedinthefilters.Theremainingparticleswillbelessthan1microninsizeandwillnotaffectthefunctionoftheSFPsystem.

SafetyEvaluationSummaryReportPage36of60SafetyEvaluationNo.:SafetyEvaluationSummary:95-007(cont'd.)(cont'd.)Thecleanupsystemisdesignedtomaintainhighreactorwaterpuritybycontinuouslypurifyingaportionoftherecirculationflow.Thedebrissizeexpectedfromtheshroudrepairis1to50micron;therefore,anyparticlesthatthecleanupsystemcannotremoveareassumedtobesmallenoughthataparticleofthatsize.couldcurrentlybeinthesystemandisnotaconcern.ThevolumeofparticlesexpectedtoremaininthevesselandSFPsystemfollowingtherepair,afterfiltering,isconsideredinsignificantwhencomparedtothetotalvolumeofwaterinthevessel.Theauxiliarybridgeandrefuelbridgebuggywillnotbeusedformovingfuel.The-auxiliarybridgehasbeenanalyzedandisacceptableforuseoverirradiatedfuel.Therefuelbridgebuggywillnotbemovedoverfuelunlessitistiedofftotherefuelbridge.TherequirementsofNUREG-0612willbemetthroughtheuseofN1-MMP-GEN-914,whichisreferencedintheGEshroudrepairprocedures.Thetoolingfor"heavyloads"hasbeendesignedandwillbeusedinaccordancewithNUREG-0612.Basedontheevaluationperformed,itisconcludedthatthespecialequipmentandprocessesrequiredfortheinstallationofthecoreshroudrepairdonotconstituteanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage37of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:95-009SimpleDesignChangeSC1-0102-93TableVl-3aSh1&3;VIII-1,Vill-2,Vill-9,VIII-32,FiguresVill-1,Vill-2;XV-48System:MainSteam(MSS),ReactorProtection(RPS),Offgas(OFG),PostaccidentSampling,EmergencyCoolingTitleofChange:RemovalofMainSteamLineHighRadiationScram/MSIVIsolationSignaltoImplementTechnicalSpecificationAmendment149DescriptionofChange:JThissafetyevaluationanalyzedplantchangesassociatedwithTechnicalSpecificationAmendment(TSA)149thatarenotexplicitlydescribedintheamendmentand,therefore,arenotcoveredbytheNRC'ssafetyevaluationfortheamendment.TSA149deletedtheautomaticreactorscramandmainsteamlineisolationfunctionsofthemainsteamlineradiationmonitors.TSA149onlystatesthatthemainsteamisolationvalves(MSIV)isolationfunctionwillberemoved;however,otherreactorvesselisolationvalvesarecoupledwiththeMSIVslogiccircuits.Therefore,whentheMSIVisolationsignalisremoved,theseothervalveswillalsonotisolateonhighradiation.SafetyEvaluationSummary:Thissafetyevaluationdemonstratesthatallnecessarysafeguardshavebeentakentoidentifyandaddressalllicensinganddesignbasisrequirementsforthedesignandoperationofthesystemsimpactedbythisdesignchange,andforinstallationofthedesignchange.BasedonreviewofNEDO31400A,varioussystemdesignsandsystemfailurecriteria,thechangewillnotresultinaradiologicalreleasebeyondexistinglimitsnoraffectoperationofsafety-relatedequipment.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvoiveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage38of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:95-010DER1-95-0133X-39FuelSpentFuelStorageThissafetyevaluationevaluatedaclarificationchangetotheUFSARwherea"maximumfuelenrichment"of3.75percentisspecifiedfortheboraflexracks.Ithasbeenestablishedthatthisvalueisthepeakdesignlatticeenrichment(nominalvalue).SafetyEvaluationSummary:1Storingfuelwithapeakdesignlatticeenrichmentof3.75percent(nominalvalue)intheboraflexracksisconsistentwithmaintainingtheK-effectivebelow0.95.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage39of60SafetyEvaluationNo.:ImplementationDocumentNo.:95-011NEDE-24011-P-A-10NEDE-24011-P-A-10-US(GESTARII)UFSARAffectedPages:I-9,I-10,I-15;IV-7,IV-12,IV-13,IV-30;V-20;XV-2,XV-3,XV-5,XV-6,XV-7,XV-15,XV-68,XV-79,TablesXV-2,XV-9Sh1h2,XV-9aSystem:TitleofChange:DescriptionofChange:VariousOperationofNMP1Reload13/Cycle12ThischangeconsistedoftheadditionofnewfuelbundlesandtheestablishmentofanewcoreloadingpatternforReload13/Cycle12operationofUnit1.TwoHundred(200)newfuelbundlesoftheGE11designwereloaded.All164ofthePSxSRbundlesfromCycle10,and36oftheGESx8EBbundlesfromCycle11,weredischargedtothespentfuelpool.Variousevaluationsandanalyseswereperformedtoestablishappropriateoperatinglimitsforthe.reloadcore.Thesecycle-specificlimitsweredocumentedintheCoreOperatingLimitsReport.SafetyEvaluationSummary:ThereloadanalysesandevaluationsareperformedbasedontheGeneralElectricStandardApplicationforReactorFuel,NEDE-24011-P-A-10andNEDE-24011-P-A-10-US(GESTARII).Thisdocumentdescribesthefuellicensingacceptancecriteria;thefuelthermal-mechanical,nuclear,andthermal-hydraulicanalysesbases;andthesafetyanalysismethodology.ForReload13,theevaluationsincludedtransientsandaccidentslikelytolimitoperationbecauseofminimumcriticalpowerratioconsiderations;overpressurizationevents;loss-of-coolantaccident;andstabilityanalysis.Appropriateconsiderationofequipment-out-of-servicewasincluded.Limitsonplantoperationwereestablishedtoassurethatapplicablefuelandreactorcoolantsystemsafetylimitsarenotexceeded.Basedontheevaluationperformed,itisconcludedthatUnit1canbesafelyoperatedduringReload13/Cycle12,andthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage40of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-013Rev.061Mod.N1-94-003N/AReactorVesselReactorCoreShroudRepairInstallationPriortoNRCApprovalofAdequacyUnder10CFR50.55a(a)(3)DescriptionofChange:ThismodificationinstalledthecoreshroudrepaircomponentspriortoNRCapprovaloftheadequacyofthesecomponentsasalternativerepairsforthecoreshroudhorizontalweldsH1throughH8./SafetyEvaluationSummary:TheseshroudrepaircomponentsarenotrequiredtoperformanydesignbasisfunctionduringthetimeperiodrequiredforNRCreviewoftheadequacyoftheproposedmodification.TheexistingshroudH1throughH8weldstructuralintegritywhichexistedpriortoplantshutdownismaintainedasdiscussedintheanalysis.Therestrictionthatthereactorremainincoldshutdownexceptforentryintothehotshutdownconditionforperformanceoftheportionofthenoncriticalhydrotestand/orCRDscramtimetestingabove212'F,inaccordancewithTechnicalSpecification3.2.2.e,untilNRCapprovalisobtainedguaranteesthatUnit1willremainincompliancewiththeNRCSafetyEvaluationReportdatedJanuary13,1995.Thisrestrictionplustherestrictiontomaintaintotalflowlessthanratedmassflow(67.5Mlb/hr)duringreactornoncriticalhydrotestingensuresthatnosignificantthermalorpressureloadsarecarriedbytheshroudortie-rodassemblies.Theanalysishasdemonstratedthatthetie-rodpreloaddoesnotincreasethestresssignificantlyinanyoftheshroudweldssuchthattheprobabilityoffailureisincreased.Theanalysishasdemonstratedthatthebypassleakageislessthan1'/oatratedrecirculationflowconditionswhichboundsthecoldandhotshutdownrequiredcorecoolingconditions.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage41of60SafetyEvaluationNo.:ImplementationDocumentNo.:95-014Rev.1TemporaryMod.95-009TemporaryMod.95-012UFSARAffectedPages:System:TitleofChange:N/AReactorCoreSprayRemovalofCoreSprayMinimumFlowReliefValvesDescriptionofChange:Thesetemporarymodificationsremovedtheminimumflowreliefvalvesforeachofthecorespraypumpsetsandreplacedthemwithblindflanges.Flangeswereinstalledattheexistingendconnectionsforeachreliefvalve./Thisdisabledtheminimumflowcapabilityforeachofthepumpsetsofthecorespraysystem.ThischangewasrequiredtosupportreloadactivitieswhiletheCoreSprayMinimumFlowModification,N1-90-041,wasbeingre-evaluatedforproblemsassociatedwiththereliefvalves.Thissafetyevaluationisonlyapplicablewhile/thereactorisdepressurized.SafetyEvaluationSummary:Removaloftheminimumflowreliefvalvesandreplacingthemwithblankflangesforrefuel/coldshutdownoperationdoesnotaffecttheabilityofthecorespraysystemtoperformitsfunctiontocoolthecore.Thischangedoesnotadverselyaffectthecorespraysystemperformanceinamannerwhichwouldincreasetheprobabilityofoccurrenceofanaccidentpreviouslyevaluatedinthesafetyanalysisreport.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage42of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:95-015N/AN/ASystem:N/ATitleofChange:CO,PelletDecontaminationFacilityat,OffGasBuilding-261DescriptionofChange:OperationoftheCO,(dryice)pelletcleaningfacilityisfordecontaminationofmiscellaneoustoolsandequipmentpost-RFO-13.TheactualCO,pelletblasterislocatedinsideofamodulardecontaminationbuilding(aportablekellybuilding)locatedintheOffgasBuildingonelevation261.ACO,storagetankandcompressorarelocatedoutdoorsattheeastsideoftheOffgasBuilding.\SafetyEvaluationSummary:TheuseandoperationoftheCO,cleaningfacilityatOffgasBuildingelevation261withaCO,storagetankandcompressorimmediatelyadjacenttotheeastsideoftheUnit1OffgasBuildingdoesnotcreatethepossibilityofanaccidentormalfunctionnotpreviouslyanalyzed,increasetheprobabilityofanaccidentormalfunctionalreadyanalyzed,reducethemarginofsafetyinanyTechnicalSpecifications,orincreasetheconsequencesofanyaccidentormalfunctionalreadyanalyzed.Inaddition,theproposedcontrolsandoperationofthefacilitywillnotcreateanewradioactiveeffluentpathwayorcreateanunmonitoredreleaseofradioactivity.Basedontheevaluationperformed,itisconcludedthatthetemporaryuseoftheCO~cleaningfacilitydoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage43of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:95-016LDCRNo.1-95-UFS-019X-47;10A-7,10A-8,10A-9,1)A-24,10A-32,10A-41,10A-44,10A-46a,10A-48,10A-52a,10A-55a,10A-57;10B-196;XIII-1thruXll!-6,Xlll-10,TableXlll-1,FiguresXIII-1thruXIII-4,System:TitleofChange:N/ADeletionofFireProtectionReportRequirementsintheFireHazardsAnalysisDescriptionofChange:/ThischangedeletedtherequirementforsendingfireprotectionprogramreportstotheNRCforinoperablefireprotectionsystemsandcomponentsasrequiredbytheFireHazardsAnalysis.SafetyEvaluationSummary:TheFireHazardsAnalysiscontainsreportingrequirementsforinoperablefireprotectionsystemsandcomponents.ThesereportsaremadeuponmeetingspecificcriteriadelineatedwithintheFireHazardsAnalysis.In1992,whenLicenseAmendment132wasissuedbytheNRC,anadditionalTechnicalSpecification(6.9.2)wasaddedtorequirethatfireprotectionprogramnoncompliancesbereviewedundertheprovisionsof10CFR50.72and10CFR50.73.Reportsarenowsubmittedundertheseprovisions,asdeterminedthroughtheplantproceduresgoverningDeviation/EventReporting.ThepreparationandsubmittaloffireprotectionreportsinadditiontothoserequiredunderTechnicalSpecification6.9.2isnolongerrequiredforlicenseeswhohaveremovedthefireprotectionprogramelementsfromtheTechnicalSpecificationspertheguidanceofNRCGenericLetters86-10and88-12.Unit1completedthisprocessthroughthegrantingofLicenseAmendment132.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage44of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:95-017Dwg.B-69007-CVI-2158;201.2LT58-05IsolationCapabilitiesLT58-05instrumentlinesdonotcontaintwomanualvalves.Instead,isolationisprovidedbyasinglemanualvalveanddiaphragmsealassemblies.SafetyEvaluationSummary:/Thediaphragmsealassemblyexceedsdesignratingsofthetorusundernormalandaccidentconditions.Thesealassemblyeffectivelyisolatesthetransmitterfromprocessfluid.Thesealassemblyislocatedclosetothetorusroompenetrationandthefirstmanualvalve.ThediaphragmsealassemblyisanAppendixJtestableconfiguration.Thevalve/sealassemblycombinationprovidessufficientisolationcapabilitytomitigatepotentialinstrumentlineleakage.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage45of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-018Gale.S7-RX340-W01XVI-70,TableXVI-31Sh1N/AUFSARChangesforPressureReliefPanelDiscrepanciesDescriptionofChange:UFSARSectionsIII.A.1.2andVI.C.1.2statedthatthepressurereliefpanelsintheTurbineandReactorBuildingsblowoutat45psf.UFSARTableXVI-31,pageXVI-185,andthediscussiononpa'geXVI-187,statedthatthepressurereliefpanelsblowoutat40psfinboththeReactorandTurbineBuildings.CalculationS7-RX340-W01andDCRN1-95001LG329,documentingexistingas-builtconditionsforfieldworkdonetothereliefpanelsinRefuelingOutage13,indicatethatthecorrectblowoutpressureis45psf.ThischangetotheUFSARcorrecteddiscrepanciesrelatingtotheblowoutpressuresforthepressurereliefpanelsintheReactorandTurbineBuildings.SafetyEvaluationSummary:Theabove-referenceddocumentsshowthatthecorrectblowoutpressureis45psfforthepressurereliefpanelsinbothbuildings.Thischangecorrectsstatedpressuresof40psfto45psfontheUFSARaffectedpages.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage46of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-019Gale.S15-72-F009X-25,FigureX-6ServiceWaterRevisiontoNMP1FSARChapterX,PagesX-31,X-32,andX-33DescriptionofChange:ThefollowingchangesweremadetoUFSARChapterXtoreconcileadiscrepancybetweentextandfigurepertainingtothepositionoftheblockingvalvesonthesupplyheader.1.TextinSectionX-2.0waschangedfrom:"Duringnormaloperationoftheturbinebuildingsystemonlyoneservicewatersupplyisused;theotherlineisvalvedoffasaspare.However,onthereactorbuildingsystembothservicewatersupplylinesareengagedatalltimesformaximumreliability."to:"DuringnormaloperationboththesupplyheadersontheRBCLCsideandTBCLCsideareengagedbykeepingtheblockingvalvesopen;however,toperformmaintenanceorotherplantactivitiesoneoftheRBCLCsideandoneoftheTBCLCsideblockingvalvescanbesecured."2.FigureX-6wasrevisedtoshowbothsetsofsupplyheaderblockingvalvestobeopeninthenormaloperatingconfiguration.SafetyEvaluationSummary:TheservicewatersystemcanadequatelymeetitsflowdemandinaconfigurationwherebothofthevalvesontheRBCLCsideandTBCLCsideareopenorinaconfigurationwhereoneofthetwovalvesontheRBCLCandTBCLCsidearesecured.Thissafetyevaluationanalyzesbothsetsofblockingvalvestobeopenundernormaloperatingcondition.Thiswillreducepotentialcloggingandcorrosionoftheportionsofthesupplyheaderwherestagnantflowconditionswouldoccuriftheblockingvalvewassecured.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage47of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-020DER1-94-0354lll-7,III-23,III-24N/ATurbineandAdministrationBuildingDescriptionChangesDescriptionofChange:ThissafetyevaluationevaluatedchangesintheconfigurationoftheAdministrationandTurbineBuildingsasfollows:1.Thenewpersonnelaccesscontrolisatel.248'-0"oftheAdministration/Building.2.TheAdministrationBuildingbasementhasanentrancetotheTurbineBuilding.3.jThepersonnellockerroomwasaddedtotheAdministrationBuildinggroundfloordescriptionintheUFSAR.Adescriptionoftheofficeforshopsandstoreswasdeleted,aswasthereferencetothemonitorroom,thepersonneldecontaminationroom,laundryroom,andlunchrooms.4.Thereceptionareaandthelocationofthelunchroom,lockerrooms,radiationprotectionoffices,andaccesstotheradiologically-controlledarea(RCA)weredeletedfromtheUFSAR.SafetyEvaluationSummary:ChangingthepersonnelRCAaccess,shopandradiationprotectionoffice,lunchrooms,laundryroom,anddeletingthereceptionareadoesnotcreatethepossibilityofaccidentormalfunctionnotpreviouslyanalyzed,affectplantequipmentorsystems,orreducethemarginofsafetyinanyTechnicalSpecification.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage48of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:95-021ProceduresGAP-POL-01,NSAS-POL-01X-47;10A-7,10A-8,10A-9;10B-196;XIII-1thruXlll-4,Xlll-8,Figures.XIII-1thru'III-4;B.1-2,B.1-3,TableB-1Sh1&2System:TitleofChange:N/AReorganization;ChangestoGAP-POL-01BcNSAS-POL-01toEstablishNuclearBusinessManagementOrganizationDescriptionofChange:ProceduresGAP-POL-01andNSAS-POL-01havebeenrevised'toreorganizethefunctionsofFinance,ComputerSoftwareDevelopment,BusinessPlanning,andNuclearProcurem'entunderaneworganizationtitled,"NuclearBusinessManagement,"reportingtotheVicePresidentNuclearGeneration.SafetyEvaluationSummary:Theseprocedurechangesestablishdepartmentalresponsibilitiesandlinesofauthority,responsibility,andcommunicationfortheNuclearBusinessManagementorganization.TheproposedorganizationstructuresatisfiesthecriteriaofSRP13.1.1andconformswiththerequirementsofSection6.1.2ofthePlantTechnicalSpecifications.Theproposedchangesdonotimpactaccidentormalfunctioninitiationorconsequences.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage49of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-022ProceduresGAP-POL-01,NSAS-POL-01XIII-3,XIII-7N/AReorganization;ChangestoGAP-POL-01&NSAS-POL-01toTransferManagementandOperationalResponsibilityfortheSiteSewageTreatmentFacilityfromTechnicalServices(Environmental)toUnit1ChemistryDescriptionofChange:!ProceduresGAP-POL-01andNSAS-POL-01havebeenrevisedtotransfermanagementand'operationalresponsibilityfortheSiteSewageTreatmentFacilityfromtheTechnicalServicesBranch(Environmental)oftheNuclearSafetyAssessment&SupportDepartmenttotheUnit1ChemistryBranchofNuclearGeneration.SafetyEvaluationSummary:Theseprocedurechangesestablishdepartmentalresponsibilitiesandlinesofauthority,responsibility,andcommunicationformanagementandoperationoftheSiteSewageTreatmentFacility.TheproposedorganizationalstructuresatisfiesthecriteriaofSRP13.1.1andconformswiththerequirementsofSection6.1.2ofthePlantTechnicalSpecifications.Theproposedchangesdonotimpactaccidentormalfunctioninitiationorconsequences.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage50of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-023ProcedureNSAS-POL-01Xlll-3,FigureXIII-4N/AReorganization;ChangestoNSAS-POL-01toTransferProcedureProgramCoordinationfromTechnicalServicestoQualityAssuranceDescriptionofChange:ProcedureNSAS-POL-01hasbeenrevisedtodeletetheresponsibilityassignedtotheManagerTechnicalServicestomanageimplementationof.theprocedureprogramincludingpublication.The"managing"functionassignedtotheManagerTechnicalServiceswastoprovideoverallcoordinationoftheprocedureprogram.ResponsibilityforoverallcoordinationoftheprocedureprogramhasbeentransferredtotheManagerQualityAssuranceasaQualityAssuranceadministrativeservicefunction./SafetyEvaluationSummary:Theseprocedurechangesestablishdepartmentalresponsibilitiesandlinesofauthority,responsibility,andcommunicationforimplementationoftheprocedureprogramincludingpublication.TheproposedorganizationalstructuresatisfiesthecriteriaofSRP13.1.1andconformswiththerequirementsofSection6.1.2ofthePlantTechnicalSpecifications.Theproposedchangesdonotimpactaccidentormalfunctioninitiationorconsequences.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage51of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-025ProcedureNSAS-POL-01Xlll-3,Xlll-4,FigureXIII-4N/AReorganization;ChangestoNSAS-POL-01toTransferEnvironmentalProtectionFunctionsfromTechnicalServicestoLicensingandEmergencyPreparednessDescriptionofChange:ProcedureNSAS-POL-01hasbeenrevisedtoreorganize(transfer)responsibilityforthefunctionalareasofenvironmentalmonitoring(includingcontrolofhazardousandindustrialwastes,andassessingeffectsofradioactiveeffluent)fromtheManagerTechnicalServicestotheManagerLicensing,andmeteorologicalmonitoringfromtheManagerTechnicalServicestotheDirectorEmergencyPreparedness./SafetyEvaluationSummary:Theseprocedurechangesestablishdepartmentalresponsibilitiesandlinesofauthority,responsibility,andcommunicationforimplementationoftheprocedureprogramincludingpublication.TheproposedorganizationalstructuresatisfiesthecriteriaofSRP13.1.1andconformswiththerequirementsofSection6.1.2ofthePlantTechnicalSpecifications.Theproposedchangesdonotimpactaccidentormalfunctioninitiationorconsequences.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage52of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-058GAP-POL-01N/AN/ADissolutionoftheUnit2TechnicalSupportBranchSupportSectionDescriptionofChange:TheNuclearDivisionisorganizedintodepartmentswithdepartmentsbeingsubdividedintobranchesandbranchesbeingsubdividedintosections.SectionscomposethelowestorganizationaltieroftheNuclearDivision.ThissafetyevaluationanalyzeschangestotheTechnicalSupportBranch.asaresultofdissolvingtheSupportSection.TheorganizationalchangeinvolvesdissolutionoftheUnit2TechnicalSupportBranch'sSupportSectionby:/~EliminatingthepositionofLeadSupportEngineer.~ConvertingtheAdministrativeTechnicianpositiontoasupervisorypositionwiththetitleofSupervisorAdministrativeSupport.~HavingtheSupervisorAdministrativeSupportreportdirectlytotheManagerTechnicalSupportandtoberesponsiblefor:1.AdministrationofStationOperationsReviewCommittee(SORC).2.Administrationoftheplanttechnicalreviewprogram.3.SupervisionoftheBranch'sclericalstaff.~Redistributingtheremainingpersonnelandfunctions(includingcoordinationofplantmodifications)oftheSupportSectiontotheSystemEngineeringSectionsunderthesupervisionoftheLeadSystemEngineers.

SafetyfvaluationSummaryReportPage53of60SafetyEvaluationNo.:SafetyEvaluationSummary:95-058(cont'd.)(cont'd.)DissolutionoftheUnit2TechnicalSupportBranch'sSupportSectiondoesnotinvolveachangetotheestablishedresponsibilitiesoftheTechnicalSupportBranchasdescribedintheUFSAR;onlythereportingstructurewithintheBranchisbeingaffected.Theorganizationcontinuestoprovidefortheintegratedmanagementofactivitiesthatsupporttheoperationofthefacilityandmaintainsclearmanagementcontrolandeffectivelinesofauthorityandcommunication;Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage54of60SafetyEvaluationNo.:ImplementationDocumentNo.:95-102Rev.051ProceduresNSAS-POL-01,GAP-POL-01,NEP-POL-0101,NIP-FPP-01,NIP-TQS-01,GAP-OPS-01UFSARAffectedPages:X-47,10A-7,10A-S,10A-9;10B-196;XIII-1throughXIII-6,Xlll-10,TableXlll-l,FiguresXIII-1throughXIII-4;B.1-3,TableB-1Sh1System:TitleofChange:N/ARestructuringofNuclearSBUinAccordancewithRevisedProceduresNSAS-POL-01,GAP-POL-01,NEP-POL-01,NIP-FPP-01,NIP-TQS-01andGAP-OPS-01DescriptionofChange:NSAS-POL-01,"CompositionandResponsibilityoftheNuclearSafetyAssessment8cSupportOrganization,"GAP-POL-01,"Compositionand'ResponsibilityoftheNuclearGenerationOrganization,"NEP-POL-01,"NuclearEngineeringDepartmentOrganization,"NIP-FPP-01,"FireProtectionProgram,"NIP-TQS-01,"QualificationandCertification,"andGAP-OPS-01,"AdministrationofOperations,"havebeenrevisedto:~TransferresponsibilityforOfficeAdministrationactivitiesfromNuclearSafetyAssessmentLSupport(NSAS)SiteServicestoBusinessManagement,-andremovetheBusinessManagementorganizationfromtheNuclearGenerationDepartment(theGeneralManagerBusinessManagementreportsdirectlytotheExecutiveVicePresidentNuclear).~TransferresponsibilityforProcurementandIntegratedPlanningfunctionsfromtheBusinessManagementOrganizationtotheEngineeringDepartment.~"Unitize"thecoordinationofcontractormaintenance/modificationactivitiespreviouslyperformedbyNSASSiteServicesandtransferresponsibilityforthefunctionstotheMaintenanceBranchateachunit.

SafetyEvaluationSummaryReportPage55of60SafetyEvaluationNo.:DescriptionofChange:95-102Rev.0&1(cont'd.)(cont'd.)Transferresponsibilityforadministrationandimplementationof.theFireProtectionProgramfromNSASTechnicalServicestoUnit1Operations.~TransferresponsibilityforadministrationofCentralMaintenanceactivities(asitefunctionthatincludesM&TEcalibration,securitysystemsupport,.materialtesting,andwarehousepreventivemaintenance)fromNSASTechnicalServicestoUnit2Maintenance.TransferresponsibilityforadministrationofBuildings&Grounds/FacilitiesPlanningactivities(asitefunction)fromtheNSASSiteServicestoUnit1Maintenance.AbolishthepositionsofManagerTechnicalServicesandManagerSiteServices.i~TransferresponsibilityforIn-serviceTestingatUnit1fromOperationstoMaintenance./~ConsolidatetheUnit1OperationsEngineeringandPlanningSectionsandcombinewiththeFireProtectionSection(currentlyinNSASTechnicalServices)intoanewOperationsSupportSectiontobeheadedbyanewposition,GeneralSupervisorOperationsSupport.AssignI&CTechnicianstoUnit2TechnicalSupportBranch-LeadPerformanceEngineer.ConsolidateUnit1andUnit2OperationsTrainingorganizationsintoonecommonsectionunderthesupervisionoftheGeneralSupervisorOperationsTraining.~AssignresponsibilityformanagementofSiteRelay&ControlTestingactivities(formerlyaCorporatesupportfunction)totheManagerMaintenanceUnit2.~TransferresponsibilityforMaintenancePlanningatUnit2fromMaintenancetoWorkControl/Outage.

SafetyEvaluationSummaryReportPage56of60SafetyEvaluationNo.:SafetyEvaluationSummary:95-102Rev.051(cont'd.)Theseprocedurechangesestablishdepartmentalresponsibilitiesandlinesofauthority,responsibility,andcommunicationwithintheNuclearSBU.TheproposedorganizationalstructuresatisfiesthecriteriaofSRPs9.5.1,13.1.1and13.1.2-13.1.3,andconformswiththerequirementsofSection6.2ofthePlantTechnicalSpecifications.Theproposedchangesdonotimpactaccidentormalfunctioninitiationorconsequences.Basedontheevaluationperformed,itisconcludedthatthesechangesdonotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage57of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-106N/AFigureIII-1-N/ADemolitionofTemporaryStructuresInsidetheProtectedArea,EastoftheUnit2StructuresDescriptionofChange:ThissafetyevaluationaddressesthedemolitionofthefollowingbuildingslocatedeastoftheUnit2plantstructures.1.2.3.4.5.Carpenter'sshopPaintshopElectricfabshopInsulatorsfabshopMaintenancestoragebuildingAllofthesebuildingswerebuiltforuseastemporarybuildingsduringtheconstructionofUnit2.Thesebuildingshavebeendemolishedandactivitiesconsolidatedwithintheremainingbuildings.SafetyEvaluationSummary:AllofthebuildingstobedemolishedarelocatedinanareathatwasnotusedasaflowchannelfortheProbableMaximumPrecipitationanalysis.Removalofthesebuildingsandtheconsequentreductionintherunoffcoefficientwouldmaketheanalysismoreconservative.Thesebuildingshavenoimpactonthepreviously.calculatedX/0values.Thedesignmarginsforthecontrolroomfreshairintakesarenotcompromised.Locationofdemolitionactivitiesareadequatelyseparatedfromsafety-relatedsystemsandstructurestoprecludeanyadverseimpactfromconstructionactivities.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage58of60SafetyEvaluationNo.:implementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-107NTP-TQS-102N/AN/ANTP-TQS-102,LicensedOperatorRequalificationTrainingChangestoReflecttheRequirementsoftheNRCApprovedSystemsApproachtoTrainingProgramDescriptionofChange:ThischangemoreclearlydefinesaSystemsApproachtoTraining(SAT)-basedRequalificationprogram./TheSAT-basedprogramallowsflexibilityinaddressingidentifiedweaknessesandcurrentissueswhilesatisfyingrequiredtrainingspecifiedin10CFR55.SafetyEvaluationSummary:Unit1and2LicensedOperatorTrainingProgramshavebeendevelopedusingaSystemsApproachtoTrainingandareaccreditedbytheNationalNuclearAccreditingBoard.BasedonthiscertificationandNRCapproval,thischangesatisfies10CFR55requirementsforLicensedOperatorRequalificationTraining.ChangingtheLicensedOperatorRequalificationTrainingprogramtomorecleariydefineaSAT-basedprogramdoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage59of60SafetyEvaluationNo.:implementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:DescriptionofChange:95-128N/AN/AN/AAerialRadiationSurveyofNMPSiteSection2.2.3.1.7oftheUnit2USARdiscussesaircraftcrashes,butthediscussionisonlyinreferencetoairplaneflightsassociatedwithnearbyairportsandhelicopterflightstoandfromthesite.TheNRCcontractedEG&GtoperformanaerialradiationsurveyoftheNineMilePointsite.Thissurveyinvolvedhelicopterflightsdirectlyoverthesiteand,asstatedabove,tlieUnit2USARonlyevaluatedflightstoandfromthesite.SafetyEvaluationSummary:Thehelicopterflightsdirectlyoverthesite,forthepurposeofperforminganaerialradiationsurvey,wereevaluatedandfoundtopresentaninsignificantriskofanaircraftcrashonsite.Thehelicopteraccidentrates,apreviousStone&WebsterEngineeringCorp.calculation,anArgonneNationalLaboratoryStudyofAircraftCrashHazards,andtheNRCStandardReviewPlan(SRP)wereusedtoassesstheriskassociatedwiththeSurveyPlandescribedbytheEG&Gpilot.Theassessmentresultedinacrashprobabilitybetween8AE-8and7E-7.PertheSRP,thisprobabilityissufficientlylowenoughthatcrashesneednotbeconsideredasdesignbasisevents.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

SafetyEvaluationSummaryReportPage60of60SafetyEvaluationNo.:ImplementationDocumentNo.:UFSARAffectedPages:System:TitleofChange:95-130NuclearDivisionPolicyPOLB.1-2N/AReorganization;ChangetoNuclearDivisionPolicytoReflectEstablishmentofthe'orporateOfficerPosition"ExecutiveVicePresident-GenerationBusinessGroup/ChiefNuclearOfficer"DescriptionofChange:TheNuclearDivisionPolicy"POL"hasbeenrevisedtoreflect.theestablishmentofthecorporateofficerpositionExecutiveVicePresident-GenerationBusinessGroup/ChiefNuclearOfficer.ThisExecutiveVicePresidentreportsdirectlytotheNiagaraMohawkPowerCorporationPresident.TheExecutiveVicePresident-NuclearissubordinatetotheExecutiveVicePresident-GenerationBusinessGroup/ChiefNuclearOfficerandcontinuestohaveoverallresponsibilityfortheadmjnistrationandoperationoftheNuclearSBU.SafetyEvaluationSummary:Theproposeduppermanagementorganizationalstructuresatisfiesapplicableacceptancecriteria,anddoesnotimpactaccidentormalfunctioninitiationorconsequences.Basedontheevaluationperformed,itisconcludedthatthischangedoesnotinvolveanunreviewedsafetyquestion.

NRCFORM35(11-93)NRCMD3.53Page1ofU.S.NUCLEARREGULATORYCOMMISSION'comsT~NSFERggyyyS'gS'1.JOBNUMBER39114.VOLUMEINCUBICFEET5I.P2.FRCACCESSIONNUMBER5.LOCATIONNUMBER(S)17127-1713173.3.DATEJOBRECEIVED08/13/19976.DATEELIGIBLEFORDESTRUCTION10/01/20297.DATEELIGIBLEFORTRANSFERTONARA10.COMMENTSLICENSEEXPIRES08/22/20098.ORIGINATINGOFFICECODEFC/NRR/[X]AFQAF-V39.FACILITYCODEQAF-V5QFRCG0<T<'e'8-Z11.ORIGINATINGOFFICE(Office/Division/Rranch)FC/NRR/12.FILECUSTODIAN(Name/Telephone)TyroneGreene(301)415-628113.LOCATIONOFRECORDS(ffuffdfng/Room)TSC314.T(TLRAFRFCARDSFREFS(RefertoNUREG0910)(Completeaseparateformforeachserfes)NuclearPowerPlantDocketFiles(E)15.RFCARDSCHFA11LENUMBER(RefertoNUREG.0910)NRCS02-20.09E16.CLASSIFICATIONOFRECORDS[X]UNCLASSIFIEDQOTHER(Specifybelow)HIGHESTCLASSIFICATION[X]PAPERQMICROFORMo*PROVIDESPECIFICMEDIUM17.RECORDMEDIUMQAUDIOVISUAL+QMACEHNEREADABLEo18.TOTALNUMBEROFCONTAINERS19.TYPEOFCONTAINER(S)(NOTEtPaperreconfsmustberetiredlnfwubfefootrecordcenterboxes)[X]RECORDCENTERBOXQOTHER(Specify)20GENERALDESCRIPTIONOFRECORDS(Prorhfcagenera(dcserfptfonoftherecordsusingitemscommonlyusedbythestofffamfNarwiththcrecords.)50-220NIAGRAMOHAWKPOWERCORP.NINEMILEPOINTUNIT1NRCFORM35(11-93)s 1'I Page2ofDETAILEDINVENTORYOFRECORDSBEINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.lfmorespaceisrequired,useNRCfor35A,'RecordsTransferContinuation'.21.CONTAINERNUMBER~m:M23.RECORDSDESCRIPTION50-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)24.DATESPAN(Month/Yrnrs)10/1996-10/199650-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)09/1996-09/199650-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)08/1996-08/199650-220NINEMILEPT1REVISIONTOEPIPS(SECONDCOPY)06/1996-06/199650-220NINEMILEPI'IREVISIONTOEPIPS(SECONDCOPY)04/1996-04/199650-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)03/1996-03/199650-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)02/1996-02/199625.RECORDSLIAISONOFFICFR-Qprg/rrnneandSigna/urnTyroneGreene27.REVIEWINGANALYST..S/gna/nrcLatravettaLee26.DATE08/13/199728.DATE08/13/199729.DATETRANSFERREDTOFRCQ30.DATEDESTROYED31.DATETRANSFERREDTONARANRCFORM35(11.93)

~5 NRCPORN35II1-93INRCMD3.53Page3ofU.S.NUCLEARREGULATORYCOMMISSIONRECORDSTRANSFERContinuationDETAILEDINVENTORYOFRECORDSMINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminatedOI/3I/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAINERNUAIBERW~@M23.RECORDSDESCRIPTION24.DATESPAN(Month/Years)50-220NINEMILEPT1REVISIONTOEPIPS(SECONDCOPY)12/1995-12/199550-220NINEMILEPTIREVISION35TOSITEEMERGENCYPLANANDEPIPS(SECONDCOPY)01/1997-01/199750-220NINEMILEPT1REVISION34TOSITEEMERGENCYPLANANDEPIPS(SECONDCOPY)05/1996-05/199650-220NINEMILEPT1REVISION33TOSITEEMERGENCYPLANANDEPIPS(SECONDCOPY)04/1996-04/199650-220NINEMILEPTIEVACUATIONTRAVELTIMEESTIMATESFORTHENINEMILEPOINTEMERGENCYPLANNINGZONE06/1992-06/199250-220NINEMILEPTIREVISION14TOUFSAR(SECONDCOPY)06/1996-06/1996250-220NINEMILEPT1REPORTTOACRS03/1969-03/1969.NRCFORM35(11-93)

NRCFORM35/1I931NRCMD3.53Page4ofU.S.NUCLEARREGULATORYCOMMISSION'ECORDSTRANSFERCOntinuatiOnDETAILEDINVENTORYOFRECORDSBEINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/9G,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAlNERNUSIBER23.RECORDSDESCRIP1'lON24.DATESPAN(Month/Yenrs)50-220NINEMILEPTIANNUALFINANCIALREPORT1992RG&EC05/1993-05/199350-220NINEMILEPT1ANNUALFINANCIALREPORT1992LILCO05/1993-05/199350-220NINEMILEPTIANNUALFINANCIALREPORT1992NYSE&GC05/1993-05/199350-220NINEMILEPT1ANNUALFINANCIALREPORT1992CHG&EC05/1993-05/199350-220NINEMILEPT1ANNUALFINANCIALREPORT1992NMPC05/1993-05/199350-220NINEMILEPT1ANNUALFINANCIALREPORT1991NMPCIV1992-11/199250.220NINEMILEPT1ANNUALFINANCIALREPORT1991RG&EC05/1992-05/199250-220NINEMILEPTIANNUALFINANCIALREPORT1991LILCO05/1992-05/1992NRCFORM35(11-93)t I

NRCFORM35/I1.9.QNRCMD3.53Page5ofU.S.NUCLEARREGULATORYCOMMISSIONRECORDSTRANSFERContinuationDETAILEDINVENTORYOFRECORDSBEINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAINERNUSIBER~%;;M23.RECORDSDESCRIPI'ION24.DATESPAN(Month/Y<<nrs)50-220NINEMILEPTIANNUALFINANCIALREPORT1991NYSE&GC05/1992-05/199250-220NINEMILEPTIANNUALFINANCIALREPORT1991CHG&EC05/1992-05/199250-220NINEMILEPTISAFETYEVALUATIONOFTHREETMIACTIONPLANITEMS(NUREG-0737)>H.F.'1.4,H.F.1.5ANDH.F.1.6,BYCONTAINMENT06/198206/198250-220NINEMILEPT1SAFETYEVALUATIONREPORT06/1981-06/198150-220NINEMILEPTISAFETYEVALUATIONREPORTREGARDINGFIREPROTECTION07/1979-07/197950-220NINEMILEPT1PROPOSEDCHANGETOTECHNICALSPECIFICATIONSREGARDINGADMINISTRATIVECHANGES06/1993-06/199350-220NINEMILEPT1PROPOSEDCHANGETOTECHNICALSPECIFICATIONSCONSISTINGOFADMINISTRATIVECHANGES05/1993-05/1993NRCFORM35(11-93)

II NRCFORM35(11-931NRCMD3.53Pape6ofU.S.NUCLEARREGULATORYCOMMISSION'ECORDSTRANSFERContinuationDETAILEDINVENTORYOFRECORDSBEINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAINERNUMBERMXM23.RECORDSDESCRIPTION24.DATESPAN(Monrh/Years)50-220NINEMILEPTIPROPOSEDCHANGETOTECHNICALSPECIFICATIONSTOINCREASESURVEILLANCETESTINTERVALSANDADDALLOIVABLEOUT-OFS12/1992-12/199250-220NINEMILEPTIPROPOSEDCHANGETOTECHNICALSPECIFICATIONSREGARDINGCOOLANTSYSTEM02/1992-02/199250-220NINEMILEPT1DRAFTTECHNICALSPECIFICATIONS(FSAR)(REVISED)03/1969-03/196950-220NINEMILEPTISAMPLETECHNICALSPECIFICATIONS12/1965-12/196550-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)06/1997-06/199750-220NINEMILEPTIREVISIONTOEPIPS(SECONDCOPY)05/1997-05/199750-220NINEMILEPT1REVISIONTOEPIPS(SECONDCOPY)04/1997-04/199750-220NINEMILEPT1REVISIONTOEPIPS(SECONDCOPY)03/1997-03/1997NRCFORM35(11-93)

I NRCFORM35/I1-931NRCMD3.53Page7ofU.S.NUCLEARREGULATORYCOMMISSION'ECORDSTRANSFERContinuationDETAILEDINVENTORYOFRECORDSBEINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAINERNUi%1BERW>A~M23.RECORDSDESCRIPTION24.DATESPAN(Month/Years)50-220NINEMILEPf1REVISIONTOEPIPS(SECONDCOPY)10/1996-10/199650-220NINEMILEPTIREACTORCONTAINMENTBUILDINGINTEGRATEDLEAKAGERATETESTFINALREPORT04/1993-04/199350-220NINEMILEPTISAFETYEVALUATIONSUMMARYREPORT,199206/1992-06/199250-220NINEMILEPT1SAFETYEVALUATIONSUMMARYREPORT1990SUBMITTEDWITHUPDATEDFSAR,REVISION8ANDAMENDMENTS06/1990-06/1990350-220NINEMILEPT1APPROVEDPROCEDURESPOWERASCENSIONPROGRAM01/1990-01/1990W50-220NINEMILEPT1CONTAINMENTLEAKTEST05/1984-05/198450-220NINEMILEPI'1EQUIPMENTQUALIFICATIONPROGRAM05/1984-05/1984NRCFORM35(11.93)

~h NRCFORM35/11-9:41NRCMD3.53Page8ofU.S.NUCLEARREGULATORYCOMMISSION'ECORDSTRANSFERContinuationDETAILEDINVENTORYOFRECORDSMINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideailidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAINERNUMBER23.RECORDSDESCRIPTION24.DATESPAN(Month/Yeats)50.220NINEMILEPT1TECHNICALSUPPLEMENTTOPETITIONFORCONVERSIONFROMPROVISIONALOPERATINGLICENSETOFULL-TERMOPERATINGLICE07/1972-07/197250-220NINEMILEPTIFIFTHADDENDUMTOTECHNICALSUPPLEMENTTOPETITIONTOINCREASEPOWERLEVELOV1971-OV197150-220NINEMILEPT1FOURTHADDENDUMTOTECHNICALSUPPLEMENTTOPETITIONTOINCREASEPOWERLEVEL12/1970-12/197050-220NINEMILEPT1THIRDADDENDUMTOTECHNICALSUPPLEMENTTOPETITIONTOINCREASEPOWERLEVEL12/1970-12/19700-220NINEMILEPT1SECONDADDENDUMTOTECHNICALSUPPLEMENTTOPETITIONTOINCREASEPOWERLEVEL10/1970-10/197050-220NINEMILEPTIFIRSTADDENDUMTOTECHNICALSUPPLEMENTTOPETITIONTOINCREASEPOWERLEVEL10/1970-10/197050-220NINEMILEPT1RESPONSETOB.L.RIDINGSOFKINSTON,TN'SLETTEROFOCTOBER13,199311/1993-11/199350-22009/1993-09/1993NRCFORM35(11-93)

WRCFORM35(11-931NRCMD3.53PageilofU.S.NUCLEARREGULATORYCOMMISSIONRECORDSTRANSFERContinuationDETAILEDINVENTORYOFRECORDSBEINGTRANSFERREDForeachindividualfolder,binder,report,tape,etc.,sufficientdescriptiontopermitretrieval.Provideallidentifyingnumbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedispositioninstructions(e.g.licenseterminated01/31/90,caseclosed01/31/90,etc.).Doublespacebetweenitemsinthesamecontainer.Triplespacewhenbeginninganewcontainer.21.CONTAINERNUMBER23.RECORDSDESCRIPTION24.DATESPAN(MonthA'ears)50-220NINEMILEPTISUPERSEDEDPAGESPERREVISIONTOEPP10/1996-10/199650-220NINEMILEPTISUPERSEDEDPAGESPERREVISIONTOEPP10/1996-10/199650-220NINEMILEPT1SUPERSEDEDPAGESPERREVISIONTOEPP09/1996-09/199650-220NINEMILEFf1SUPERSEDEDPAGESPERREVISIONTOEPP11/1995-11/199550-220NINEMILEPTISUPERSEDEDPAGESPERREVISIONTOSITEEMERGENCYPLAN01/1997-01/199150-220NINEMILEPI'1SUPERSEDEDPAGESPERREVISION13TOUFSAR06/1995-06/1995~,NRCFORM35(11.93) l NINEMILEPOINTUN3Z1FSAR-(UPDATED)LISTOFEFFECTIVEPAGESGENERALTABLEOFCONTENTSPAGENUMBER1liilliVVViViiV3.3.'1ViiiaViiib3.XXXlX3.iXiiiX3.VXVXVlXVl1XVlilXiXXXXXiXX3.1XXiiiXXiVXXVXXViXXVll,XXV3.1iXX3.XXXXXXXiXXxiiXXX3.3.3.XXX3.VXXXVXXXVl.XXXV3.iXXXViiiXXXiXxlXlixiiixliiiT=TABLEF=FIGURENUMBERREVISIONNUMBER121212121312121313131312131213131312121312~121213-c)13121212121212PAGENUMBERxlivXlvxlvixlviixlviiiillT=TABLEF=FIGURENUMBERREVISIONNUMBER1212~13121212.12UFSARRevision13EPiJune1995&

0 NINEMILEPOINTUNIT1FSAR(UPDATED)LISTOFEFFECTIVEPAGESGENERALTABLEOFCONTENTSPAGENUMBERI-1I-2I-3I-4I-5I-6I-7I-8I-9I-10I-11I-12I-13I-14I-15I-16I-17T=TABLEF=FIGURENUMBERFI-1REVISIONNUMBER0990110000131313120003PAGENUMBERT=TABLEF=FIGUREREVISIONNUMBERNUMBERUFSARRevision13EP1-1June1995

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NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionB.1.01.12.02.12.22.3TitleDESCRIPTIONOFAREAADJ'ACENTTOTHESITEGeneralPopulationAgricultural,IndustrialandRecreationalUseAgriculturalUseIndustrialUseRecreationalUsePacaeII-6II-6ZZ-6XI-9II-9IZ-11ZZ-17C.D.E.F.SECTIONIXIMETEOROLOGYLIMNOLOGYEARTHSCIENCESENVIRONMENTALRADIOLOGYBUILDINGSANDSTRUCTURESII-22XX-23II-24II-25IIZ-1A.1.01.11.21.31.41.52.02.12.22.32.43.0B.1.01.11.21.31.41.52.02.12.22.32.43.0TURBINEBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilationShieldingandAccessControlStructureDesignGeneralStructuralFeaturesHeatingandVentilationSystemSmokeandHeatRemovalShieldingandAccessControlSafetyAnalysisCONTROLROOMDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilationShieldingandAccessControlStructureDesignGeneralStructuralFeaturesHeating,VentilationandAirConditioningSystemSmokeandHeat.RemovalShieldingandAccessControlSafetyAnalysisIII-4IZZ-4IIZ-4XII-4IXZ-4III-6ZZZ-6IIZ-6II1-6III-17IZX-21III-21III-21IZI-23ZII-23III-23III-23XIZ-23III-23III-23aIII-24ZZZ-24ZIZ-25ZZZ-27IXI-27ZZZ-28UFSARRevision0'une1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionC.1.01.11.21.31.41.52.02.12.22.33.0D.1.01.11.21.31.41.52.02.12.22.33.0E.1.01.11.1.11.1.21.1.31.1.41.1.51.21.2.11.2.21.2.31.32.02.12.1.12.1.22.1.32.1.42.1.52.1.62.1.7TitleWASTEDISPOSALBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilationShieldingandAccessControlStructureDesignGeneralStructuralFeaturesHeatingandVentilationSystemShieldingandAccessControlSafetyAnalysisOFFGASBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilationShieldingandAccessControlStructureDesignGeneralStructuralFeaturesHeatingandVentilationSystemShieldingandAccessControlSafetyAnalysisNONCONTROLLEDBUILDINGSAdministrationBuildingDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeating,CoolingandVentilationShieldingandAccessControlStructureDesignGeneralStructuralFeaturesHeating,VentilationandAirConditioningAccessControlSafetyAnalysisSewageTreatmentBuildingDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsElectricalDesignFireandExplosiveGasDetectionHeatingandVentilationShieldingandAccessControlPacaeIII-29IIZ-29ZI1-29IZZ-29III-29III-30ZZI-30III-30ZII-30IIZ-32III-34IIZ-36ZII-38ZII-38III-38III-38ZII-38ZZI-38III-38III-38III-39ZII-39ZII-41III-41ZII-42III-42IIZ-42IZI-42III-42III-42ZII-43IIZ-43IZZ-43III-43ZII-45IZI-45IIZ-47III-47IZZ-47aIII-47aIZI-47aIZZ-47aZII-47aZII-47aIII-48ZZI-48UFSARRevision12June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section2.22.2.12.2.22.2.33.03.13.1.13.1.23.1.33.1.43.1.53.23.2.13.2.23.2.3TitleStructureDesignGeneralStructuralFeaturesVentilationSystemAccessControlEnergyInformationCenterDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilationShieldingandAccessControlStructureDesignGeneralStructuralFeaturesHeatingandVentilationSystemAccessControlPacaeIII-48IZX-48ZII-49III-49III-49IZI-49IXI-49III-50XII-50ZZI-50III-50III-51ZII-51II1-51Zll-52F.1.01.11.1.11.1.21.1.31.1.41.1.51.22.02.12.23.0G.1.01.11.21.31.42.03.03.13.23.2.13.2.23.2.3H.SCREENHOUSE~INTAKEANDDISCHARGETUNNELSScreenhouseDesignBasisWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilationShieldingandAccessControlStructureDesignIntakeandDischargeTunnelsDesignBasesStructureDesignSafetyAnalysisSTACKDesignBasesGeneralWindLoadingSeismicDesignShieldingandAccessControlStructureDesignSafetyAnalysisRadiologyStackFailureAnalysisReactorBuildingDiesel-GeneratorBuildingScreenandPumpHouseSECURITYBUILDINGANDSECURITYBUILDINGANNEXII1-53ZII-53III-53ZIZ-53ZZZ-53III-53IIZ-53III-53III-53IIZ-57XII-57III-57III-59III-61ZZZ-61III-61ZZZ-61ZZI-61ZIZ-61ZZZ-61IZX-64ZII-64ZII-64ZIX-66ZZZ-66ZZZ-67III-68UFSARRevision12June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)~Sectio1~01.11.21.31.41~52'2~12~22'3.04'SECTIONIVA.1.02.03.0B.1.02'2.12'2.2.12.2'2.33.03.13.1~13.1.23.23.2.13.2.23.34.04.14'5'5.15RADWASTESOLIDIFICATIONANDSTORAGEBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeating,VentilationandAirConditioningShieldingandAccessControlStructureandDesignGeneralStructuralFeaturesHeating,VentilationandAirConditioningShieldingandAccessControlUseReferencesREACTORDESIGNBASESGeneralPerformanceOb)ecti.vesDesignLimitsandTargetsREACTORDESIGNGeneralNuclearDesignTechniqueReferenceLoadingPatternFinalLoadingPatternAcceptableDeviationFromReferenceLoadingPatternReexaminationofLicensingBasisRefuelingCycleReactivityBalanceThermalandHydraulicCharacteristicsThermalandHydraulicDesignRecirculationFlowControlCoreThermalLimitsThermalandHydraulicAnalysesHydraulicAnalysisThermalAnalysis'eactorTransientsStabilityAnalysisDesignBasesStabilityAnalysisMethodMechanicalDesignandEvaluationFuelMechanicalDesignDesignBasesPacaeIII-69III-69XII-69III-69III-69XXI-69III-70III-70III-70III-71III-73III-73III-75IV-1IV-1IV-1IV-1IV-2IV-3IV-3IV-5XV-6IV-6IV-6IV-7IV-8IV-8IV-8IV-8IV-9IV-15IV-15IV-17IV-23IV-23IV-23IV-24IV-25IV-25IV-25UFSARRevision13June1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section5.1.25.1.35.1.45.1.55.1.65.1.76.06.16.1.16.1.26.26.2.16.2.26.36.47.07.17.1.17.1.27.1.37.1.47.1.57.1.67.1.77.1.87.27.3SECTIONVTitle'LFuelRodsWaterRodsFuelAssembliesMechanicalDesignLimitsandStressAnalysisRelationshipBetweenFuelDesignLimitsandFuelDamageLimitsSurveillanceandTestingControlRodMechanicalDesignandEvaluationDesignControlRodsandDrivesStandbyLiquidPoisonSystemControlSystemEvaluationRodWithdrawalErrorsEvaluationOverallControlSystemEvaluationLimitingConditionsforOperationandSurveillanceControlRodLifetimeReactorVesselInternalStructureDesignBasesCoreShroudCoreSupportTopGridControlRodGuideTubesFeedwaterSpargerCoreSpraySpargersLiquidPoisonSpargerSteamSeparatorandDryerDesignEvaluationSurveillanceandTestingREACTORCOOLANTSYSTEMPacaeIV-27ZV-29IV-29IV-30ZV-31IV-31ZV-32IV-32ZV-32ZV-40ZV-40IV-40ZV-41ZV-45IV-45ZV-46IV-46IV-47IV-49IV-49ZV-49IV-50ZV-50IV-50ZV-50IV-51IV-52A.1.02.03.04.05;0B.1.01.11.21.31.41.5DESIGNBASESGeneralPerformanceObjectivesDesignPressureCyclicLoads(MechanicalandThermal)CodesSYSTEMDESIGNANDOPERATIONGeneralDrawingsMaterialsofConstructionThermalStressesPrimaryCoolantLeakageCoolantChemistryV-1V-1V-1V-6V-6V-8v-10V-10V-10V-10V-10V-12V-12aUFSARRevision12ViJune1994 NineMilePointUnit,1FSARTABLEOFCONTENTS(Cont'.)Section2.03.04.05.0C.1.02.03.04.04.14.24.34.44.55.05.15.25.36.0D.1.0.2.02.12.2TitleReactorVesselReactorRecirculationLoopsReactorSteamandAuxiliarySystemsPipingReliefDevicesSYSTEMDESIGNEVALUATIONGeneralPressureDesignHeatupandCooldownRatesMaterialsRadiationExposurePressure-TemperatureLimitCurvesTemperatureLimitsforBoltupTemperatureLimitsforIn-ServiceSystemPressureTestsOperatingLimitsDuringHeatup,Cooldown,andCoreOperationPredictedShiftinRT~~MechanicalConsiderationsJetReactionForcesSeismicForcesPipingFailureStudiesSafetyLimits,LimitingSafetySettingsandMinimumConditionsforOperationTESTSANDINSPECTIONSPrestartupTestingInspectionandTestingFollowingStartupHydroPressurePressureVesselIrradiationPBceeV-12aV-14V-16V-16V-19V-19V-19V-21V-21V-21V-22V-22V-23aV-23aV-23aV-23aV-23bv-26V-26V-27V-27V-27V-27V-27E.1.02.03.03.13.23.33.44.04.14.2SECTIONVIEMERGENCYCOOLINGSYSTEMDesignBasesSystemDesignandOperationDesignEvaluationRedundancyMakeupWaterSystemLeaksContainmentIsolationTestsandInspectionsPrestartupTestSubsequentInspectionsandTestsCONTAXNMENTSYSTEMPRXMARYCONTAINMENT-MARKICONTAXNMENTPROGRAMV-28V-28V-28v-30V-30v-30V-30V-31V-31V-31V-31VI-1VI-2UFSARRevision12ViiJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)~Sectic1~02.02.12.22.33.0B.1.01~11~21'1'1.51.61.72.02.12.22.32.42.52.6,2.7C.1~01~11'1.31.42~02.1T~iteGeneralStructurePressureSuppressionHydrodynamicLoadsSafety/ReliefValveDischargeLoss-of-CoolantAccidentSummaryofLoadingPhenomenaPlantUniqueModificationsPRIMARYCONTAINMENT-PRESSURESUPPRESSIONSYSTEMDesignBasesGeneralDesignBasisAccidentContainmentHeatRemovalIsolationCriteriaVacuumReliefCriteriaFloodingCriteriaShieldingStructureDesign-GeneralPenetrationsandAccessOpeningsJetandMissileProtectionMaterialsShieldingVacuumReliefContainmentFloodingSECONDARYCONTAINMENT-REACTORBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignShieldingStructureDesignGeneralStructuralFeatures~acaeVI-2VI-2VI-3VI-3VI-5VI-6VI-8VI-8VI-8VI-8VI-11VI-11VI-11VI-12VI-12VI-13VI-13VI-15VI-21VI-22VI-22a,-VI-22aVI-23VI-24VI-24VI-24VI-24VI-25VI-25VI-25VI-26D.1.01.12.03.0E.,1.0111.22.0CONTAINMENTISOLATIONSYSTEMDesignBasesContainmentSprayAppendixJWaterSealRequirementsSystemDesignTestsandInspectionsCONTAINMENTVENTILATIONSYSTEMPri'maryContainment,DesignBasesSystemDesignSecondaryContainmentVI-43VI-43VI-56aVI-57VI-59VI-60VI-60VI-60VI-60VI-62UFSARRevision13viiiJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)~Sectio2~12'DesignBasesSystemDesign~aeVI-62VX-62UFSARRevision13viiiaJune1995 NineMilePointUnit1FSARTHISPAGEINTENTIONALLYBLANKUFSARRevision13viiibJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)~SecticF.1.01.11.22.02.12'3.04.05.05.1'5~25.3SECTIONVIITESTANDINSPECTIONSDrywellandSuppressionChamberPreoperationalTestingPostoperationalTestingContainmentPenetrationsandIsolationValvesPenetrationandValveLeakageValveOperabilityTestContainmentVentilationSystemOtherContainmentTestsReactorBuildingReactorBuildingNormalVentilationSystemReactorBuildingIsolationValvesEmergencyVentilationSystemENGINEEREDSAFEGUARDS~aeVI-65VI-65VI-65VI-65VI-66VI-66VI-67VI-67VI-67VI-68VI-68VI-68VI-68VII-1A.1.02.02.12.23.04.0B.1.02.02'3.04.0C.1.02.02~13.04.05.0D.1.02.03.03.13.23.34.0CORESPRAYSYSTEMDesignBasesSystemDesignGeneralOperatorAssessmentDesignEvaluationTestsandInspectionsCONTAINMENTSPRAYSYSTEMDesignBasesSystemDesignOperatorAssessmentDesignEvaluationTestsandInspectionsLIQUIDPOISONINJECTIONSYSTEMDesignBasesSystemDesignOperatorAssessmentDesignEvaluationTestsandInspectionsAlternateBoronInjectionCONTROLRODVELOCITYLIMITERDesignBasesSystemDesignDesignEvaluationGeneralDesignSensitivityNormalOperationTestsandInspectionsVII-2VII-2VII-2VII-2VII-7VII-8VII-9VII-11VII-11VII-11aVII-17VII-18VII-19VII-21VII-21VII-21aVII-27VII-28VII-29VII-30VII-31VII-31VII-31VII-34VII-34VII-34VII-35VII-36UFSARRevision13iXJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionE.1.02.02.13.04.0F.1.02.03.04.0G.1.02.02.12.23.'3.13.24.0H.1.02.02.13.04.0I.1.02.03.04.0SECTIONA.1.01.11.22.02.1"2.23.0VIIITitleCONTROLRODHOUSINGSUPPORTDesignBasesSystemDesignLoadsandDeflectionsDesignEvaluationTestsandInspectionsFLOWRESTRICTORSDesignBasesSystemDesignDesignEvaluationTestsandInspectionsCOMBUSTIBLEGASCONTROLSYSTEMDesignBasesContainmentInertingSystemSystemDesignDesignEvaluationContainmentAtmosphericDilutionSystemSystemDesignDesignEvaluationTestsandInspectionsEMERGENCYVENTILATIONSYSTEMDesignBasesSystemDesignOperatorAssessmentDesignEvaluationTestsandInspectionsHXGH-PRESSURECOOLANTZNJECTXONDesignBasesSystemDesignDesignEvaluationTestsandXnspectionsINSTRUMENTATZONANDCONTROLPROTECTIVESYSTEMSDesignBasesReactorProtectionSystemAnticipatedTransientsWithoutScramMitigationSystemSystemDesignReactorProtectionSystemAnticipatedTransientsWithoutScramMitigationSystemSystemEvaluationPacaeVZI-37VZI-37VI1-38VZZ-40VII-41VII-41VZZ-42VZI-42VIZ-42VII-42VZZ-43VZZ-44VZZ-44VII-44VZZ-44VZZ-46aVZZ-48VZZ-48VIX-49VZI-53VZI-55VII-55VII-55aVZI-58vZZ-58VII-59VII-61VZZ-61VII-61VZI-61aVZZ-62aVIXX-1VIIZ-1VIII-1VXII-1VIII-6VIZ1-6VZZZ-6VXXI-14VXII-15UFSARRevision12June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionB.1.02~02~12.22.32.43.03'3.23'3.4REGULATINGSYSTEMSDesignBasesSystemDesignControlRodAdjustmentControlRecirculationFlowControlPressureandTurbineControlReactorFeedwaterControlSystemEvaluationControlRodAdjustmentControlRecirculationFlowControlPressureandTurbineControlReactorFeedwaterControl~aeVIII-18VIII-18VIII-18VIII-18VIII-18VIII-20VIII-21VIII-21VIII-21VIII-22VIII-22VIII-22C.1.01.11~1~11.1~21.1~31.1~41.1.51.21.2.11.2.21.2.31.2.42.02.12.1.12.1.22.1.32'2'.12.2.22'.33.03'3~1~13.1.23.24.04.1INSTRUMENTATIONSYSTEMSNuclearInstrumentationDesignSourceRangeMonitorsIntermediateRangeMonitorsLocalPowerRangeMonitorsAveragePowerRangeMonitorsTraversingIn-CoreProbeSystemEvaluationSourceRangeMonitorsIntermediateRangeMonitorsLocalPowerRangeMonitorsAveragePowerRangeMonitorsNon-NuclearProcessInstrumentationDesignBasesNon-NuclearProcessInstrumentsin-ProtectiveSystemNonnuclearProcessInstrumentsinRegulatingSystemsOtherNonnuclearProcessInstrumentsEvaluationNonnuclearProcessInstrumentsinProtectiveSystemNonnuclearProcessInstrumentsinRegulatingSystemsOtherNonnuclearProcessInstrumentsRadioactivityInstrumentationDesignBasesRadiationMonitorsinProtectiveSystemsOtherRadiationMonitorsEvaluationOtherInstrumentationRodWorthMinimizerVIII-23VIII-23VIII-23VIII-25VIII-28VIII-32VIII-32VIII-40VIII-40VIII-42VIII-43VIII-50VIII-50VIII-54VIII-54VIII-54VIII-58VIII-60VIII-62VIII-62VIII-62VIII-62aVIII-62aVIII-62aVIII-62aVIII-68VIII-76VIII-76VIII-76UFSARRevision13June1995 NineMilePointUnit1FSARSTABLEOFCONTENTS(Cont'd.)Section4.1.14.1.25.05.15.25.35.45.4.15.4.25.4.35.4.45.55.65.6.15.6.25.6.35.6.45.6.55.6.6I55.6.9TitleDesignBasesEvaluationRegulatoryGuide1.97(Revision2)InstrumentationLicensingActivities-BackgroundDefinitionofRG1.97VariableTypesandInstrumentCategoriesDeterminationofRG1.97TypeAVariablesforNMP1Determinationof"EOPKeyParameters"forNMP1"DeterminationBasis/ApproachDefinitionofPrimarySafetyFunctionsAssociationofEOPstoPrimarySafetyFunctionsIdentificationofEOPKeyParametersNMP1RG1.97Variables,VariableType,andAssociatedInstrumentCategoryDesignationsSummaryoftheRG1.97InstrumentDesignandImplementationCriteriathatwereEstablishedforNMP1asPartoftheUnit11990RestartActivitiesNoTypeAVariablesEOPKeyParametersSingleTapfortheFuelZoneRPVWaterLevelInstrumentNonredundantWide-RangeRPVWaterLevelIndicationUpgradingEOPKeyParameterCategory1InstrumentLoopComponentstoSafetyRelatedClassificationSafetyRelatedClassificationofInstrumentationforRG1.97VariableTypesOtherthantheEOPKeyParametersRoutingandSeparationofChannelizedCategory1InstrumentLoopCablesElectricalIsolationofCategory1InstrumentLoopsfromAssociatedComponentsthatarenotSafetyRelatedPowerSourceInformationforCategory1InstrumentsPRCReVIXI-76VIXI-80VIXI-80VZ1Z-81VIII-81VIII-82aVIII-82bVIIX-82bVZII-82cVIII-82dVIII-84VIII-86VIII-99VIXI-99VI1I-100VIII-101VIXI-102VIIZ-104VIIX-105VIII-105VIII-106VIII-107UFSARRevision12XiiJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section5.6.105.6.115.6.125.7SECTIONIXA.B.1.01.11.22.02.12.22.32.42.53.03.13'3.33.43.4.13.4.23.4.33.53.5.13.5.24.04.14.24.35.05.15.25.36.06.1MarkingofInstrumentsofControlRoomPanels"Alternate"InstrumentsforMonitoringEOPKeyParametersIndicatingRangesofMonitoringInstrumentsReferencesELECTRICALSYSTEMSDESIGNBASESELECTRICALSYSTEMDESIGNNetworkInterconnections345-kVSystem115-kVSystemStationDistributionSystemTwof24-VoltDCSystemsTwo120-V,60-Hz,Single-Phase,UninterruptiblePowerSupplySystemsTwo120-V,57-60Hz,One-Phase,ReactorTripPowerSuppliesOne120/208-V,60-Hz,InstrumentandControlTransformerOne120/240-V,60-Hz,Three-Phase,ComputerPowerSupplyCablesandCableTraysCableSeparationCablePenetrationsProtectioninHazardousAreasTypesofCablesPowerCableControlCableSpecialCableDesignandSpacingofCableTraysTrayDesignSpecificationsTraySpacingEmergencyPowerDieselGeneratorSystemStationBatteriesNonsafetyBatterySystemTestsandInspectionsDiesel-GeneratorStationBatteriesNonsafetyBatteriesConformancewith10CFR50.63,StationBlackoutRuleStationBlackoutDuration~aeVZIZ-108VIIZ-108VIII-109VIII-110IX-1IX-1IX-2IX-2IX-2IX-3IX-8aIX-13IX-15IX-16IX-16IX-16aIX-16aIX-'16aIX-17IX-17ZX-18IX-18IX-18IX-19IX-19IX-19IX-20IX-20IX-20IX-26IX-31IX-34IX-34IX-35IX-35IX-35IX-35UFSARRevision13xiiiJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section6.26.36.46.56.6StationBlackoutCopingCapabilityProceduresandTrainingQualityAssuranceEDGReliabilityProgramReferences~aeIX-36IX-38IX-39IX-39IX-40SECTIONXA.1'2.03.04.0B.1.02.03.04.0C.1.02.02~12.22.32.42.52.62.72.82.92.102'12.122.132.143.03.13.2'.33.43.54.05.0REACTORAUXILIARYANDEMERGENCYSYSTEMSREACTORSHUTDOWNCOOLINGSYSTEMDesignBasesSystemDesignSystemEvaluationTestsandInspections1REACTORCLEANUPSYSTEMDesignBasesSystemDesignSystemEvaluationTestsandInspectionsCONTROLRODDRIVEHYDRAULICSYSTEMDesignBasesSystemDesignPumpsFiltersFirstPressureStageSecondPressureStageThirdPressureStageExhaustHeaderAccumulatorScramPilotValvesScramValvesScramDumpVolumeControlRodDriveCoolingSystemDirectionalControlandSpeedControlValvesRodInsertionandWithdrawalScramActuationSystemEvaluationNormalWithdrawalSpeedAccidentalMultipleOperationScramReliabilityOperationalReliabilityAlternateRodInjection(ARI)ReactorVesselLevelInstrumentationReferenceLegBackfillTestsandInspectionsX-1X-1X-1X-1X-3X-3X-4X-4X-4X-7X-7X-8X-8X-8X-10X-10X-11X-11X-12X-13X-13X-14X-14X-15X-16X-16X-17X-17X-18X-18X-19X-19X-20X-21X-21X-21UFSARRevision13xivJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectoD.1'2.03.04.0E.1.02'3.04.0F.1.02.03.04.0G.1.02'3.04.0H.1'2.03.04.01.02.03.04.01~02.02.12.1.12.23.04.0REACTORBUILDINGCLOSEDLOOPCOOLINGWATERSYSTEMDesignBasesSystemDesignDesignEvaluationTestsandInspectionsTURBINEBUILDINGCLOSEDLOOPCOOLINGWATERSYSTEMDesignBasesSystemDesignDesignEvaluationTestsandInspectionsSERVICEWATERSYSTEMDesignBasesSystemDesignDesignEvaluationTestsandInspectionsMAKEUPWATERSYSTEMDesignBasesSystemDesignSystemEvaluationTestsandInspectionsSPENTFUELSTORAGEPOOLFILTERINGANDCOOLINGSYSTEMDesignBasesSystemDesignDesignEvaluationTestsandInspectionsBREATHING,INSTRUMENTANDSERVICEAIRSYSTEMDesignBasesSystemDesignDesignEvaluationTestsandInspectionsFUELANDREACTORCOMPONENTSHANDLINGSYSTEMDesignBasesSystemDesignDescriptionofFacilityCaskDropProtectionSystemOperationoftheFacilityDesignEvaluationTestsandInspectionsX-22X-22X-22X-25X-26X-27X-27X-27X-29X-30X-31X-31X-31X-33X-34X-35X-35X-35X-37X-38X-39X-39X-39aX-43X-44X-45X-45X-45X-48X-49X-50X-50X-50X-50X-54X-55X-57X-58UFSARRevision13xvJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionK.1.01.11.21.31.41.51.62.02.12.22.32.43.03.13.24.0TitleFIREPROTECTIONPROGRAMProgramBasesNuclearDivisionDirective-FireProtectionProgramNuclearDivisionInterfaceProcedure-FixeProtectionProgramFireHazardsAnalysis(FHA)AppendixRReviewSafeShutdownAnalysis(SSA)FireProtectionandAppendixRRelatedPortionsofOperationsProcedures(OPs,SOPs,andEOPs)andDamageRepairProceduresFireProtectionPortionsoftheEmergencyPlanProgramImplementationandDesignAspectsFireProtectionImplementingProceduresFireProtectionAdministrativeControlsFireProtectionSystemDrawingsandCalculationsFireProtectionEngineeringEvaluations(FPEEs)MonitoringandEvaluatingProgramImplementationFireProtectionQualityAssuranceProgram(FPQAP)FireBrigadeManning,Training,DrillsandResponsibilitiesSurveillanceandTestsPacaeX-59X-59X-59X-59X-59X-60X-60X-60X-60X-60X-61X-61X-61X-62x-62X-62x-62L.1.02.03.04.0M.1.02.03.04.0IAPPENDIX1OAIAPPENDIX10BREMOTESHUTDOWNSYSTEMDesignBasesSystemDesignSystemEvaluationTestsandInspectionsSAFETYPARAMETERDISPLAYSYSTEMDesignBasesSystemDesignSystemEvaluationTestsandInspectionsFIREHAZARDSANALYSISSAFESHUTDOWNANALYSISX-76X-76X-76X-76X-77X-78X-78X-78X-78X-79UFSARRevision12XviJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionSECTIONXZA.Ti.tieSTEAMTOPOWERCONVERSIONSYSTEMDESIGNBASESPRcRBXZ-,1XI-1,B.1.02.03.04.05.06.07.08.09.010.0SYSTEMDESIGNANDOPERATIONTurbine-GeneratorTurbineCondenserCondenserAirRemovalandOffgasSystemCirculatingWaterSystemCondensatePumpsCondensateDemineralirerSystemCondensateTransferSystemFeedwaterBoosterPumpsFeedwaterPumpsFeedwaterHeatersXI-9XZ-9XI-11XI-12XI-17XZ-17XI-18XI-19XI-20XI-20XZ-20C.D.SECTIONXZZSYSTEMANALYSISTESTSANDINSPECTIONSRADIOLOGICALCONTROLSXZ-22XZ-25XII-11.01.11.21.2.11.2.21.2.32.02.12.1.12.1.22.1.32.1.42.22.2.12.2.22.2.32.2.42~32.3.12.3.23.04.04.1RAD10ACTZVEWASTESDesignBasesObjectivesTypesofRadioactiveWastesGaseousWastesLiquidWastesSolidWastesSystemDesignandEvaluationGaseousWasteSystemOffgasSystem,SteamPackingExhausterSystemBuildupVentilationSystemsStackLiquidWasteSystemLiquidWasteHandlingProcessesSamplingandMonitoringLiquidWastesLiquidWasteEquipment.ArrangementLiquidRadioactiveWasteSystemControlSolidWasteSystemSolidWasteHandlingProcessesSolidWasteSystemEquipmentSafetyLimitsTestsandInspectionsWasteProcessSystemsXZI-1XII-1XZZ-1XIZ-1XZZ-1XZI-2XZZ-3XII-3XII-3XII-7XII-7XZZ-7XII-8XII-8XZI-8XII-12XII-13XII-13XII-15XZZ-15XIZ-17XII-17XZI-18XIZ-18UFSARRevision12XV3.iUJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)~sectic4.24.34.3.14.3.2B.1.01.11.21.2.111.'2.31'2.02.12.1.12.1.22.1~32.22.2.12.2.222'3.03~13.1.13.1.23.1.33.1.43'3.2.13.2.23.33.3.13.3'3.3.33.43.4.13.53.5.13.5.23.5.33.5'3.5.54.0FiltersEffluentMonitorsOffgasandStackMonitorsLiquidWasteEffluentMonitorRADIATIONPROTECTIONPrimaryandSecondaryShieldingDesignBasesDesignReactorShieldWallBiologicalShieldMiscellaneousEvaluationAreaRadioactivityMonitoringSystemsAreaRadiationMonitoringSystemDesignBasesDesignEvaluationAreaAirContaminationMonitoringSystemDesignBasesDesignEvaluationRadiationProtectionFacilitiesLaboratory,CountingRoomandCalibrationFacilitiesChangeRoomandLaundryFacilitiesPersonnelDecontaminationFacilityToolandEquipmentDecontaminationFacilityRadiation,ControlShieldingAccessControlContaminationControlFacilityContaminationControlPersonnelContaminationControlAirborneContaminationControlPersonnel.DoseDeterminationsRadiationDoseRadiationProtectionInstrumentationCountingRoomInstrumentationPortableRadiationInstrumentationAirSamplingInstrumentationPersonnelMonitoringInstrumentsEmergencyInstrumentationTestsandInspections~aeXII-18XII-19XII-19XII-19XII-20XII-20XII-20XII-22XII-22XII-23XII-23XII-23XII-24XII-24XII-24XII-25XII-30XII-31XII-31XII-31XII-31XII-32XII-32aXII-32aXII-33XII-34XII-34XII-35XII-35XII-36XII-37XII-38XII-38XII-39XII-41XII-41XII-41aXII-41aXII-42XII-42XII-43XII-43XII-44UFSARRevision13xvi11June1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section4.14.24.34'4.4'4.4.24.5ShieldingAreaRadiationMonitorsAreaAirContaminationMonitorsRadiationProtectionFacilitiesVentilationAirFlowsInstrumentCalibrationWellShieldingRadiationProtectionInstrumentationA.1.01.1.31.1~41.1.51'.61.22.02.13.04.0ORGANIZATIONANDRESPONSIBILITYManagementandTechnicalSupportOrganizationNuclearDivisionVicePresidentNuclearGenerationVicePresidentNuclearEngineeringVicePresidentNuclearSafetyAssessmentandSupportDirectorNuclearCommunicationsandPublicAffairsDirectorHumanResourceDevelopmentControllerNuclearDivisionCorporateSupportDepartmentsOperatingOrganizationPlantManagerQualityAssuranceFacilityStaffQualificationsSECTIONXIIICONDUCTOFOPERATIONSPacaeXII-44XII-44XII-45XII-45XII-45'XII-45XII-45XIII-1XIII-1XIII-1XIII-1XIII-1XIII-2'III-3XIII-6XIII-7XIII-7XIII-7XIII-8XIII-8XIII-11XIII-12B.1.02.03.04.04.14.24.34.3.14.3.24.3.34.3.444.3.64.3.7QUALIFICATIONSANDTRAININGOFPERSONNEL,ThisSectionDeletedThisSectionDeletedThisSectionDeletedTrainingofPersonnel=GeneralResponsibilityImplementationQualityForOperatorTrainingForMaintenanceForTechniciansForGeneralEmployeeTraining/RadiationProtectionandEmergencyPlanForIndustrialSafetyForNuclearQualityAssuranceForFireBrigadeXIII-13XIII-13XIII-13XIII-13XIII-13XIII-13XIII-13XIII-13XIII-13XZZZ-14XIII-14XIII-14XIII-14XIII-14XIII-14UFSARRevision13XiXJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section5.0C.D.E.F.1.01.11.21.31.42.03.03.13.23.33.43.54.05.06.07.0G.1..01'2.02.13.0SECTIONXZVTitleTrainingofLicensedOperatorCandidates/LicensedNRCOperatorRetrainingCooperativeTrainingwithLocal,StateandFederalOfficialsOPERATINGPROCEDURESEMERGENCYPLANANDPROCEDURESSECURITYRECORDSOperations.ControlRoomLogBookStationShiftSupervisor'sBookRadwasteLogBookWasteQuantityLevelShippedMaintenanceRadiationProtectionPersonnelExposureBy-ProductMaterialasRequiredby10CFR30MeterCalibrationsStationRadiologicalConditionsin-AccessibleAreasAdministrationoftheRadiationProtectionProgramandProceduresChemistryandRadiochemistrySpecialNuclearMaterialsCalibrationofInstrumentsAdministrativeRecordsandReportsREVIEWANDAUDITOFOPERATIONSStationOperationsReviewCommitteeFunctionSafetyReviewandAuditBoardFunctionReviewofOperatingExperienceINITIALTESTINGANDOPERATIONSPacaeXIII-14XIII-15XIII-16XIII-17XIII-19XIII-20XIII-20XIII-20XIII-20XZZI-20XIII-20XIII-21XIII-21XIII-21XIII-21XIII-21XIII-21XTII-21XIII-21XIII-21XZII-22XIII-22XIII-23XIII-23XZZZ-23XIII-23XIII-23XIII-24XZV-1A.TESTSPRIORTOINITIALREACTORFUELINGXIV-1B.1.0INITIALCRITICALITYANDPOSTCRITICALZTYTESTSInitialFuelLoadingandNear-ZeroPowerTestsat:AtmosphericPressureXIV-5XZV-5UFSARRevision12XXJune1994 NineMilePointUnit1FSAR'LTABLEOFCONTENTS(Cont'd.)Section1.11.21.32.02.12.23.04.05.06.0SECTIONXVA.B.1.02.03.03.13.23.33.43.53.63.73.83.93.103.113.123'.12.13.12.23.12.33.12.43.133.14TitleGeneralRecpxirementsGeneralProceduresCoreLoadingandCriticalTestProgramHeatupfromAmbienttoRatedTemperatureGeneralTestsConductedFromZeroto100PercentInitialReactorRatingFull-PowerDemonstrationRunComparisonofBaseConditionsAdditionalTestsatDesignRatingSAFETYANALYSISINTRODUCTIONBOUNDARYPROTECTIONSYSTEMSTransientsConsideredMethodsandAssumptionsTransientAnalysisTurbineTripWithoutBypassLossof100'FFeedwaterHeatingFeedwaterControllerFailure-MaximumDemandControlRodWithdrawalErrorMainSteamLineIsolationValveClosure(WithScram)InadvertentStartupofColdRecirculationLoopRecirculationPumpTripsRecirculationPumpStallRecirculationFlowControllerMalfunction-IncreasingFlowFlowControllerMalfunction-DecreaseFlowInadvertentActuationofOneSolenoidReliefValveSafetyValveActuationObjectivesAssumptionsandInitialConditionsCommentsResultsFeedwaterControllerMalfunction(ZeroDemand)TurbineTripwithPartialBypass(LowPower)PacaeXZV-5XIV-5XZV-8XIV-10XZV-10XIV-10XIV-12XIV-14XZV-14XIV-14XV-1XV-1XV-2XV-2XV-5aXV-6XV-6XV-7aXV-9XV-11aXV-18XV-20XV-24XV-27XV-28XV-32XV-34XV-36XV-36XV-36XV-37XV-37XV-41XV-43UFSARRevision12xx1June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section3.153.163,173.183.193.203.213.223.233.243.25C.1.01.11.21.2.11.2.21.2.31.2.41.2.51.2.61.2.71.2.81.31.3.11.3.21.3.32.02.1I2.22.2.12.2.22.2.32.2.42.32.4TitleTurbineTripwithPartialBypass(FullPower)InadvertentActuationofOneBypassValveOneFeedwaterPumpTripandRestartLossofMainCondenserVacuumLossofElectricalLoad(GeneratorTrip)LossofAuxiliaryPowerPressureRegulatorMalfunctionInstrumentAirFailureD-CPowerInterruptionsFailureofOneDiesel-GeneratortoStartPowerBusLossofVoltageSTANDBYSAFEGUARDSANALYSISMainSteamLineBreakOutsidetheDrywellIdentificationofCausesAccidentAnalysisValveClosureInitiationFeedwaterFlowCoreShutdownMixtureLevelSubcooledLiquidSystemPressureandSteam-WaterMassMixtureImpactForcesCoreInternalForcesRadiologicalEffectsRadioactivityReleasesMeteorologyandDoseRatesComparisonwithRegulatoryGuide1.5Loss-of-CoolantAccidentIntroductionInputtoAnalysisOperationalandECCSInputParametersSingleFailureStudyonECCSManually-ControlledElectrically-OperatedValvesSingleFailureBasisPipeWhipBasisAppendixKLOCAPerformanceAnalysisforP8DNB277AppendixKLOCAPerformanceAnalysisPacaeXV-44XV-48xv-50xv-50XV-52XV-54XV-56XV-57XV-66XV-67xv-68XV-70XV-70XV-70XV-70XV-71XV-71XV-72XV-72XV-72XV-72XV-73XV-75XV-75XV-75XV-77XV-78XV-81XV-81xv-81aXV-81axv-81axV-96xv-96XV-96XV-134UFSARRevision12June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section2.4.12.4.22.4.32.4.42.53.03.13.23.33.3.13.3.23.3.34.04.14.24'4.44,54.5.14.5.25.05.15.1.15.1.25.1.35.1.45.1.55.1.65.1.75.1.85.25.2.15.2.25.2.35.2.45.2.55.2.65.35.3.15.3.2Ti.tieComputerCodesDescriptionofModelChangesAnalysisProcedureAnalysisResultsAppendixKLOCAMAPLHGREvaluationwithCoreSprayFlowThroughOneSpargerRefuelingAccidentIdentificationofCausesAccidentAnalysisRadiologicalEffectsFissionProductReleasesMeteorologyandDoseRatesComparisontoRegulatoryGuide1.25ControlRodDropAccidentIdentificationofCausesAccidentAnalysisDesignedSafeguardsProceduralSafeguardsRadiologicalEffectsFissionProductReleasesMeteorologyandDoseRatesContainmentDesignBasisAccidentOriginalRecirculationLineRuptureAnalysis-WithCoreSprayPurposeAnalysisMethodandAssumptionsCoreHeatBuildupCoreSpraySystemContainmentPressureImmediatelyFollowingBlowdownContainmentSprayBlowdownEffectsonCoreComponentsRadiologicalEffectsOriginalContainmentDesignBasisAccidentAnalysis-WithoutCoreSprayPurposeCoreHeatupContainmentResponseFissionProductReleasefromtheFuelFissionProductReleasefromtheReactorandContainmentMeteorologyandDoseRatesDesignBasisReconstitution(DBR)SuppressionChamberHeatupAnalysisIntroductionInputtoAnalysisPRcRBXV-137aXV-137aXV-137bXV-137dXV-137dXV-137d2XV-137d2XV-139XV-142XV-142XV-145XV-145XV-146XV-146XV-149XV-152XV-153XV-154XV-154XV-159XV-159XV-159aXV-159aXV-159aXV-159bXV-159cXV-159fXV-159iXV-159kXV-159mXV-160XV-160XV-160XV-164XV-164aXV-167XV-169XV-169XV-169XV-169bUFSARRevision12June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section5.3.35.3.46.06.16.26.37.07~17.27.37.47.57.67.7SECTIONXVZA.1.02.02.12.22.2.12.32.42.52.62.6.12.6.22.6.32.6.42.6.52.72.7.12.7.22.7.33.03.13.2TitleDBRSuppressionChamberHeatupAnalysisConclusionsNewFuelBundleLoadingErroxAnalysisIdentificationofCausesAccidentAnalysisSafetyRequirementsMeteorologicalModelsUsedinAccidentAnalysesGroundReleasesStackReleasesVariabilityExfiltrationGroundDepositionThyroidDoseWholeBodyDoseSPECIALTOPICALREPORTSREACTORVESSELApplicabilityofFormalCodesandPertinentCertificationsDesignAnalysisCodeApprovalAnalysisSteady-StateAnalysisBasisforDeterminingStressesPipeReactionCalculationsEarthquakeLoadingCriteriaandAnalysisReactorVesselSupportStressDesignCriteriaandAnalysisStrainSafetyMarginforReactorVesselsIntroductionStrainMarginFailureProbabilityResultsofProbabilityAnalysisConclusionsComponentsRequiredforSafeReactorShutdownDesignBasisLoadCombinationsExpectedStressandDeformationStressesandDeformationsatWhichtheComponentisUnabletoFunctionandMarginofSafetyInspectionandTestReportSummaryMaterialsFabricationandInspectionPacaeXV-169bXV-169gXV-169kXV-169kXV-169kXV-171XV-171XV-171XV-171XV-173XV-175XV-197XV-198'V-199XVZ-1XVZ-1XVI-1XVZ-3XVI-3XVI-3XVZ-3XVI-10XVI-10XVZ-14XVI-24XVZ-24XVZ-26XVI-27XVI-31XVI-31XVZ-36XVI-36XVI-36XVI-41XVI-47XVZ-47XVI-47UFSARRevision12xxivJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section4.04.14.2B.1.02.02.12.22.32.42.52'.12.62.72.82'.12.8.22.8.32.8.42.8.52.8.62.8.72.8.82.93.03.13.23.33.3.13.3.2C.1.01.11.21.31.3.1TitleSurveillanceProvisionsCouponSurveillanceProgramPeriodicInspectionPRESSURESUPPRESSIONCONTAINMENTApplicabilityofFormalCodesandPertinentCertificationsDesignAnalysisCodeApprovalCalculationsUnderRatedConditionsUltimateCapabilityUnderAccidentConditionsCapabilitytoWithstandInternalMissilesandJetForcesFloodingCapabilitiesoftheContainmentDrywellAirGapTestsandInspectionsBiologicalShieldWallCompatibilityofDynamicDeformationsOccurringintheDrywell,Torus,andConnectingVentPipesContainmentPenetrationsClassificationofPenetrationsDesignBasesMethodofStressAnalysisLeakTestCapabilityFatigueDesignMaterialSpecificationApplicableCodesJetandReactionLoadsDrywellShearResistanceCapabilityandSupportSkirtJunctionStressesInspectionandTestReportSummaryFabricationandInspectionTestsConductedDiscussionofResultsResultsEffectofVariousTransientsENGINEEREDSAFEGUARDSSeismicAnalysisandStressReportIntroductionMathematicalModelMethodofAnalysisFlexibilityor.InfluenceCoefficientMatrixPacaeXVI-51XVI-51XVI-51XVI-52XVI-52XVI-53XVI-53XVI-53XVI-53XVZ-57XVZ-61XVI-63XVZ-65XVI-69XVI-74XVI-74XVZ-74XVZ-76XVI-76XVZ-77XVI-77XVI-77XVI-78XVI-79XVI-83XVZ-83XVZ-83XVI-85XVI-85XVI-87XVZ-92XVI-92XVI-92XVZ-93XVI-94XVZ-95UFSARRevision12xxvJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionTitlePacae1.3.21.3.31.3.41.3.51.3.61.3.71.42.02.12.1.12.1.22.1.32.1.42.22.2.1D.1.01.11.1.11.1.21.21.32.02.1IF1-12.1.22.1.32.23.04.0NormalModeFrequenciesandModeShapesTheSeismicSpectrumValuesDynamicModalLoadsModalResponseQuantitiesTheCombinedResponseQuantitiesBasicCriteriaforAnalysisDiscussionofResultsContainmentSpraySystemDesignAdequacyatRatedConditionsGeneralCondensationandHeatRemovalMechanismsMechanicalDesignLoss-of-CoolantAccidentSummaryofTestResultsSprayTestsConductedDESIGNOFSTRUCTURES,COMPONENTS/EQUIPMENTANDSY'STEMSClassificationandSeismicCriteriaDesignTechniquesStructuresSystemsandComponentsPipeSupportsSeismicExposureAssumptionsPlantDesignforProtectionAgainstPostulatedPipingFailuresinHighEnergyLinesInsidePrimaryContainmentContainmentIntegrityAnalysisSystemsAffectedbyLineBreakEngineeredSafeguardsProtectionOutsidePrimaryContainmentBuildingSeparationAnalysisTornadoProtectionXVZ-96XVI-96XVI-97XVZ-98XVI-98XVZ-99XVI-99XVI-104XVZ-104XVI-104XVI-104XVI-113XVI-113XVZ-116XVI-116XVI-123XVI-123XVI-126XVZ-126XVI-146XVZ-153XVI-154XVI-155XVZ-155XVI-155aXVZ-158XVI-163XVI-165XVZ-168XVZ-168E.G.EXHIBITSCONTAINMENTDESIGNREVIEWUSAGEOFCODES/STANDARDSFORSTRUCTURALSTEELANDCONCRETESECTIONXVIIORIGINALENVIRONMENTALSTUDIESXVI-189XVI-227XVZ-238XVII-1A.1.02.0METEOROLOGXGeneralSynopticMeteorologicalFactorsXVII-1XVII-1XVII-2UFSARRevision12xxviJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section3.03.13.1.13.1~23.1.33.23.33.43.4.14.04.14.24.34.3.14.44.4.14.4.24.54.64.6.14.6;24.6.34.75.0B.1.02.03.03.13.23.2.13.2.23.2.33.3TitleMicrometeorologyWindPatterns200-FootWindRosesEstimatesofWindsatthe350-FootLevelComparisonBetweenTowerandSatelliteWindsLapseRateDistributionsTurbulenceClassesDispersionParametersChangesinDispersionParametersApplicationstoReleaseProblemsConcentrationsfromaGround-LevelSourceConcentrationsfromanElevatedSourceRadialConcentrationsMonthlyandAnnualSectorConcentrationsLeastFavorableConcentrationsOveranExtendedPeriodGround-LevelReleaseElevatedReleaseMeanAnnualSectorDepositionDoseRatesfromaPlumeofGammaEmittersRADOSProgramCenterlineDoseRatesSectorDoseRatesConcentrationsfromaMajorSteamLineBreakConclusionsLIMNOLOGYIntroductionSummaryReportofCruisesDilutionofStationEffluentinSelectedAreasDilutionofEffluentattheLakeSurfaceAbovetheDischargeDilutionofEffluentattheSiteBoundariesGeneralDilutionofEffluentattheEasternSiteBoundaryDilutionofEffluentWestoftheStationSiteDilutionofEffluentattheCityofOswegoIntakePacaeXVII-2XVII-2XVII-2XVII-2XVII-16XVII-19XVIZ-19XVII-19XVII-39XVIZ-45XVZZ-46XVZZ-53XVZZ-55XVZZ-55XVII-83XVZZ-83XVIZ-86XVI1-87XVII-90XVIZ-90XVII-91XVZZ-100XVII-103XVZZ-106XVZZ-107XVZZ-107XVII-107XVZZ-109XVII-109XVZZ-114XVIZ-114XVZI-116XVII-122XVZZ-123UFSARRevision12XxviiJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section3.3.13.3.23.3.33.3.43.3.53.3.63.43.54.04.14.1.14.1.24.25.0TitleTiltingoftheIsothermalPlanesandSubsequentDilutionDilutionasaFunctionofCurrentVelocityPercentofTimeEffluentWillBeCarriedtotheOswegoAreaMixingwithDistanceOswegoRiverWaterasaBuffertoPreventEffluentFromPassingOvertheIntakeSummaryofAnnualDilutionFactorsfortheCityofOswegoIntakeDilutionofEffluentattheNineMilePointIntakeSummaryofDilutionintheNineMilePointAreaPreliminaryStudyofLakeBiotaOffNineMilePointBiologicalStudiesPlanktonStudyBottomStudySummaryofBiologicalStudiesConclusionsPacaeXVZI-123XVII-124XVII-127XVII-127XVII-127XVII-127XVZI-128XVII-128XVII-129XVII-129XVII-129XVII-129XVII-130XVZZ-130C.1.02.03.03.13.24.04.14.24.34.44.5SECTIONXVZZIEARTHSCIENCESIntroductionAdditionalSubsurfaceStudiesConstructionExperienceStationAreaIntakeandDischargeTunnelsCorrelationWithPreviousStudiesGeneralGeologicalConditionsHydrologicalConditionsSeismologicalConditionsConclusionHUMANFACTORSENGINEERING/SAFETYPARAMETERDISPLAYSYSTEMXVZI-132XVII-132XVII-132XVII-138XVII-138XVII-139XVII-140XVII-140XVII-140XVII-142XVZI-142XVZZ-142XVZZZ-1A.1.02.03.03.13.23.33.43.5DETAILEDCONTROLROOMDESIGNREVIEWGeneralPlanningRequirementsfortheDCRDRDCRDRReviewProcessOperatorSurveyHistoricalReviewTask'nalysisControlRoomInventoryControlRoomSurveyXVIIZ-1XVIII-1XVIII-2XVIII-2XVIII-2XVIII-2XVIII-3XVIZZ-3XVIII-4UFSARRevision12XXV'.3.3.June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)SectionTitle~acae3.63.73.84.04.14.24.2.14.2.2.5.06.06.16.26.36.47.0VerificationofTaskPerformanceCapabilitiesValidationofControlRoomFunctions~CompilationofDiscrepancyFindingsAssessmentandImplementationAssessmentImplementationIntegratedCosmeticPackageFunctionalFixesReportingContinuingHumanFactorsProgramFixVerificationsMultidisciplinaryReviewTeamAssessmentsHumanFactorsManualforFutureDesignChangeOutstandingHumanFactorsItemsReferencesXVIII-4XVIII-4XVIZZ-5XVZII-5XVIII-5XVIZI-5XVIZ1-6XVIII-7XVIII-7XVIII-8XVIII-8XVZII-8XVIII-8XVIII-8XVIII-9B.1.02.03.04.05.05.15.1.15.1.25.1.35.1.45.25.2.15.2.25.35.3.15.3.25.4SAFETYPARAMETERDISPLAYSYSTEMIntroductiontotheSafetyParameterDisplaySystemSystemDescriptionRoleoftheSPDSHumanFactorsEngineeringGuidelinesHumanFactorsEngineeringPrinciplesAppliedtotheSPDSDesignNUREG-0737,Supplement1,Section4.1.aConciseDisplayCriteriaPlantVariablesRapidandReliableDeterminationofSafetyStatusAidtoControlRoomPersonnelNUREG-0737,Supplement1,Section4.1.bConvenientLocationContinuousDisplayNUREG-0737,'Supplement1,Section4.1.cProceduresandTrainingIsolationofSPDSfromSafety-RelatedSystemsNUREG-0737,Supplement1,Section4.1.eXVZII-11XVIII-11XVIII-11XVIII-12XVIII-13XVIII-13XVIZZ-13XVIII-13XVIII-13XVIIZ-14XVIII-14XVIII-14XVIII-14XVZII-15XVIII-15XVIII-15XVIII-15XVIII-16UFSARRevision12xxixJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)Section5.4.15.4.25.56.06.16.27.0TitleIncorporationofAcceptedHumanFactorsEngineeringPrinciplesInformationCanbeReadilyPerceivedandComprehendedNUREG-0737,Supplement1,Section4.1.f,SufficientInformationProceduresOperatingProceduresSurveillanceProceduresReferencesPacaeXVIII-16XVIII-17XVIII-17XVIII-17XVIII-17XVIII-18XVIII-19APPENDIXAAPPENDIXBUnusedNIAGARAMOHAWKPOWERCORPORATIONQUALITYASSURANCEPROGRAMTOPICALREPORT(NMPC-QATR-1)~NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONSPHASEUFSARRevision12XXZJune1994 NineMilePointUnit1FSARLISTOFFIGURESFigureNumberII-1ZI-2II-3II-4ZI-5XI-6ZZI-1III-2IIX-3IXI-4Xjj-5Ijj-6IXZ-7ZZI-8IIX-9XXX-10IZI-11III-12IIX-13IIZ-14IIX-15IIZ-16IIX-17IZI-18III-19TitlePiping,InstrumentandEquipmentSymbolsStationLocationAreaMapSiteTopographyPopulationDistributionWithinaTwelveMileRadiusoftheStationCountiesandTownsWithinTwelveMilesoftheStation1980PopulationDistributionWithinaFiftyMileRadiusoftheStationPlotPlanStationFloorPlan-Elevation225-6StationFloorPlan-Elevations237and250StationFloorPlan-Elevation261StationFloorPlan-Elevations277and281StationFloorPlan-Elevations281and291StationFloorPlan-Elevations298and300StationFloorPlan--Elevations317-6and318StationFloorPlan-Elevations320,333-8,340and369SectionBetweenColumnRows7'and8SectionBetweenColumnRows12and14TurbineBuildingVentilationSystemLaboratoryandRadiationProtectionFacilityVentilationSystemControlRoomVentilationSystemWasteDisposalBuildingVentilationSystemWasteDisposalBuildingExtensionVentilationSystemOffgasBuildingVentilationSystemTechnicalSupportCenterVentilationSystemCirculatingWaterChannelsUnderScreenandPumpHouse-NormalOperationPacaeI-17II-2IZ-3XZ-4ZI-7IZ-8IZ-10III-3IZZ-7ZZI-8III-9III-10XIZ-11ZII-12XIZ-13XII-14Ijj-15XII-16Xlj-18XIX-20IZI-26ZII-33XXX-35Ijj-40IZI-46IXI-55UFSARRevisionXXXiJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)Figure~umberIII-20III-21III-22III-23IV-1IV-2IV-3IV-3aIV-4IIV-5IV-5aIV-5bIV-6IV-7IV-8IV-9V-1V-2V-3V-4V-5V-6V-7V-8VI-1VI-2VI-3VI-4VI-5VI-6xMt1RCirculatingWaterChannelsUnderScreenandPumpHouse-SpecialOperationsIntakeandDischargeTunnelsPlanandProfileStack-PlanandElevationStackFailure-CriticalDirections/LimitingPower/FlowLineFigureDeletedFigureDeletedGE11FuelAssemblyDesignTypicalControlRod-IsometricFigureDeletedControlRodPositioningWithinCoreCellGE8X8EBControlRodPositioningWithinCoreCellWithTypicalGE11FuelAssemblyControlRodDriveandHydraulicSystemControlRodDriveAssemblyTypicalControlRodtoDriveCoupling-IsometricReactorVesselIsometricReactorEmergencyCoolantSystemReactorVesselNozzleLocation.ReactorVesselSupportFigureDeletedPressureVesselEmbrittlementTrendFigureDeletedFigureDeletedEmergencyCondenserSupplyIsolationValves(Typicalof2)DrywellandSuppressionChamberElectricalPenetrations-HighVoltageElectricalPenetrations-LowVoltagePipePenetrations-HotTypicalPenetrationForInstrumentLinesReactorBuildingDynamicAnalysis-AccelerationEast-WestDirection~aeIII-56III-58III-62III-65IV-10IV-26IV-28IV-28aIV-33IV-34IV-34aIV-34bIV-37IV-38IV-39IV-48V-11V-13V-15V-18V-23V-24V-25V-32VI-14'I-17VI-18VI-19VI-20VI-28UFSARRevision13XXXiiJune1995 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberVI-7vz-8VI-9VX-10VZ-11VI-12Vz-13VZ-14VI-15VI-16VZ-17VI-18VI-19vz-20VZ-21VX-22VI-23VI-24VII-1VIX-2VXI-3VII-4VII-4aVIZ-5vzz-6VII-7vzx-8TitleReactorBuildingDynamicAnalysisDeflectionsEast-WestDirectionReactorBuildingDynamicAnalysis-Elevationvs.BuildingShearEast-WestDirectionReactorBuildingDynamicAnalysisElevationvs.BuildingMomentEast-WestDirectionReactorBuildingDynamicAnalysis-AccelerationNorth-SouthDirectionReactorBuildingDynamicAnalysis-DeflectionsNorth-SouthDirectionReactorBuildingDynamicAnalysis-Elevationvs.BuildingShear-North-SouthDirectionReactorBuildingDynamicAnalysis'-Elevationvs.BuildingMoment-North-SouthDirectionReactorSupportDynamicAnalysisElevationvs.AccelerationReactorSupportDynamicAnalysis-Elevationvs.DeflectionReactorSupportDynamicAnalysis-Elevationvs.ShearReactorSupportDynamicAnalysis-Elevationvs.MomentTypicalDoorSealsDetailsofReactorBuildingAirLocksInstrumentLineIsolationValveArrangementTypicalFlowCheckValveIsolationValveSystemDrywellCoolingSystemReactorBuildingVentilationSystemCoreSpraySystemCoreSpraySpargerFlow,PerSparger,forOneCoreSprayPumpandOneToppingPumpContainmentSpraySystemFigureDeletedFigureDeletedFigureDeletedLiquidPoisonSystemMinimumAllowableSolutionTemperatureFigureDeletedPacaevx-29VI-30VI-31VI-32VI-33VI-34VX-35Vz-36VZ-37vz-38VI-39VZ-41VX-42vz-53VI-54vz-58VI-61vz-63VII-3VXI-5VIZ-12VII-13VZZ-13aVzz-14VII-22VII-24VII-25UFSARRevision12ZXXiiiJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberVII-9VZI-10VZI-11VZI-12VII-13VXI-14VZI-15VII-16VII-17VIIZ-1VIII-2VIII-3VXII-4VIII-5VIII-6VIII-7VXII-8VIII-9VIIX-10VXII-11VIII-12VXII-13VIXI-14VIII-15VIII-16VIIZ-17VIXX-18VIII-19TitleTypicalControlRodVelocityLimiterControlRodHousingSupportHydrogenFlammabilityLimitsCombustibleGasControlSystemH,-O,SamplingSystemH,-O,ConcentrationsinContainmentFollowingLOCAN,AddedbyCADOperationFollowingLOCAContainmentPressurewithCADOperation-ZeroContainmentLeakageFeedwaterDeliveryCapability(ShaftDrivenPump)ProtectiveSystemFunctionReactorProtectionSystemElementaryDiagramProtectiveSystemTypicalSensorArrangementRecirculationFlowandTurbineControlNeutronMonitoringInstrumentRangesSourceRangeMonitor(SRM)SRMDetectorLocationIntermediateRangeMonitor(IRM)IRMCoreLocationLPRMLocationWithinCoreLatticeLPRMandAPRMCoreLocationLocalPowerRangeMonitor(LPRM)andAveragePowerRangeMonitors(APRM)APRMSystem-TypicalTripLogicf'rAPRMScramandRodBlockTraversingIn-CoreProbeRodPatternDuringStartupRadialPowerDistributionforControlRodPatternShowninFigureVXII-16DistancefromWorstControlRodtoNearestActiveIRMMonitorMeasuredResponseTimeofIntermediateRangeSafetyInstrumentationPacaeVII-32VI1-39VII-45VII-47VII-50VZZ-51VII-52VII-54VII-63VIII-2VIII-8VIII-16VXIZ-19VII1-24VIII-26VIII-27VIII-29VIII-30VIIX-33VIII-34VIXI-35VIXI-37VIII-38VIXI-41VIII-45VIII-46VIIZ-47VIXI-49UFSARRevision12XXX'.VJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberVIXI-20VIIZ-21VIIZ-22VIII-23VIII-24VIXI-25VIIZ-26VIII-27VIII-28VIII-29IX-1IX-2IX-3IX-4IX-5IX-6Ix-7X-1X-2-X-3X-4X-6X-7X-8X-10X-11TitleEnvelopeofMaximumAPRMDeviationbyFlowControlReductioninPowerEnvelopeofMaximumAPRMDeviationforAPRMTrackingWithOnUnitsControlRodWithdrawalMainSteamLineRadiationMonitorReactorBuildingVentilationRadiationMonitorOffgasSystemRadiationMonitorEmergencyCondenserVentRadiationMonitorStackEffluentandLiquidEffluentRadiationMonitorsContainmentSprayHeatExchangerRawWaterEffluentRadiationMonitorContainmentAtmosphericMonitoringSystemRodWorthMinimizerA.C.StationPowerDistributionControlandInstrumentPowerTraysBelowElevation261TraysBelowElevation277TraysBelowElevation300DieselGeneratorLoadingFollowingLoss-of-CoolantAccidentDieselGeneratorLoadingforOrderlyShutdownReactorShutdownCoolingSystemReactorCleanupSystemControlRodDriveHydraulicSystemReactorBuildingClosedLoopCoolingSystemTurbineBuildingClosedLoopCoolingSystemServiceWaterSystemDecayHeatGenerationvs.DaysAfterReactorShutdownSpentFuelStoragePoolFilteringandCoolingSystemBreathing,Instrument,andServiceAirReactorRefuelingSystemPictorialCaskDropProtectionSystemPacaeVIIX-52VXZZ-53VIII-63VIII-65VXII-66VXIZ-69VXII-70VXIX-73VIXI-75VIIZ-78Ix-9XX-14IX-21Ix-22Ix-23Zx-27Ix-28X-2x-5X-9X-23x-28X-32X-40X-41X-46X-51x-56UFSARRevision12XXXVJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberXI-1XI-2XI-3XI-4XI-5XI-6XI-7XII-1XIII-1IXIII-2XIII-3XIII-4XIII-5XV-1IXV2XV-2aXV-2bXV-3XV-4XV-4aXV-4bXV-5XV-6XV-6aXV-7XV-8XV-9XV-10XV-11~T'teSteamFlowandReheaterVentilationSystemExtractionSteamFlowMainCondenserAirRemovalandOffgasSystemCirculatingWaterSystemCondensateFlowCondensateTransferSystemFeedwaterFlowSystemRadioactiveWasteDisposalSystemNMPCUpperManagementNuclearOrganizationNineMilePointNuclearSiteOrganizationNuclearEngineeringOrganizationNuclearSafetyAssessmentandSupportOrganizationSafetyOrganizationStationTransientDiagramFigureDeletedFigureDeletedFigureDeletedPlantResponsetoLossof100FFeedwaterHeatingFigureDeletedPlantResponsetoFeedwaterControllerFailure(GE11atEOC)PlantResponsetoFeedwaterControllerFailure(GE11atEOCExtendedLoadLineLimit)FigureDeletedFigureDeletedFigureDeletedFigureDeletedStartupofColdRecirculationLoop-PartialPowerRecirculationPumpTrips(1Pump)RecirculationPumpTrips(5Pumps)RecirculationPumpStall~aeXI-2XI-3XI-4XI-5XI-6XI-7XI-8XII-9XV-3XV-8XV-8aXV-8bXV-10XV-12XV-12aXV-12bXV-16XV-17XV-17aXV-19XV-23XV-25XV-26XV-29UFSARRevision13xxxviJune1995 NineMilePointUnit1FSAR1LISTOFFIGURES(Cont,'d.)FigureNumberXV-12XV-13XV-14XV-15XV-16XV-17XV-18XV-19XV-20XV-21XV-22XV-23XV-24XV-25XV-26XV-27XV-28XV-29XV-30XV-31XV-32XV-33XV-33aXV-34XV-35XV-36XV-37XV-38XV-39XV-40XV-41XV-42XV-43XV-44XV-45XV-46XV-47XV-48XV-49XV-50TitleFlowControllerMalfunction(IncreasedFlow)FlowControllerMalfunctionDecreasingFlowInadvertentActuationofOneSolenoidReliefValveFigureDeletedFigureDeletedFeedwaterControllerMalfunction-ZeroFlowTurbineTripWithPartialBypassIntermediatePowerTurbineTripWithPartialBypassInadvertentActuationofOneBypassValveOneFeedwaterPumpTripandRestartLossofElectricalLoadLossofAuxiliaryPowerPressureRegulatorMalfunctionMainSteamLineBreak-CoolantLossFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeleted~aeXV-31XV-33XV-35XV-39XV-40XV-42XV-45XV-47XV-49XV-51XV-53XV-55XV-58XV-74XV-85XV-86XV-89XV-90XV-91XV-92XV-93XV-94XV-94aXV-103XV-104XV-105XV-106XV-107XV-108XV-109XV-110XV-111XV-112XV-113XV-114XV-115XV-116XV-117XV-118XV-119UFSARRevision13xxxviiJune1995 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberXV-51XV-52XV-53XV-54XV-55xv-56XV-56A!XV-56BXV-56CXV-56DXV-56EXV-56FXV-56Gxv-56HXV-57XV-58XV-59XV-60xv-60aXV-60bXV-61XV-62xv-63XV-64XV-65XV-66XV-67TitleFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedFigureDeletedLoss-of-CoolantAccident-WithCoreSprayCladdingTemperatureLoss-of-CoolantAccidentDrywellPressureLoss-of-CoolantAccidentSuppressionChamberPressureLoss-of-CoolantAccidentContainmentTemperature-WithCoreSprayLoss-of-CoolantAccidentCladPerforationWithCoreSprayContainmentDesignBasisCladTemperatureResponse-WithoutCoreSprayContainmentDesignBasisMetal-WaterReactionContainmentDesignBasisCladPerforationWithoutCoreSprayContainmentDesignBasisContainmentTemperature-WithoutCoreSprayDBRAnalysisSuppressionPoolandWetwellAirspaceTemperatureResponse-ContainmentSprayDesignBasisAssumptionDBRAnalysisSuppressionPoolandWetwellAirspaceTemperatureResponse-EOPOperationAssumptionsReactorBuildingModelExfiltrationvs.WindSpeed-NortherlyWindReactorBuildingDifferentialPressureExfiltrationvs.WindSpeed-SoutherlyWindReactorBuilding-IsometricReactorBuilding-CornerSectionsReact.orBuilding-RoofSectionsPacaeXV-120XV-121XV-122XV-123XV-126XV-127XV-137iXV-137jXV-137kXV-159eXV-159g,,XV-159hXV-159LXV-159nXV-161XV-163XV-165XV-166XV-169Lxv-169mXV-178'v-184xv-185.XV-186XV-188XV-189XV-190O.UFSARRevision12XXXViiiJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberTitlePacaeXV-68XV-69XV-70XV-71XV-72ReactorBuilding-PaneltoConcreteSectionsReactorBuilding-ExpansionJointSectionsReactorBuildingExfiltration-NortherlyWindReactorBuildingExfiltration-SoutherlyWindReactorBuildingDifferentialPressureXV-191XV-192XV-193XV-194XV-196O.XVI-1XVZ-2XVI-3XVI-4XVI-6XVI-7XVI-8XVZ-9XVI-10XVI-11XVI-12XVZ-13XVI-14XVI-15XVZ-16XVI-17XVI-18XVI-19XVI-20XVI-21SeismicAnalysisofReactorVesselGeometricandLumpedMassRepresentationReactorSupportDynamicAnalysis-Elevationvs.MomentReactorSupportDynamicAnalysisElevationvs.ShearReactorSupportDynamicAnalysis-Elevationvs.DeflectionReactorSupportDynamicAnalysisElevationvs.AccelerationFigureDeletedFigureDeletedFigureDeletedReactorVesselSupportStructureStressSummaryThermalAnalysisFailureProbabilityDensityFunctionAdditionStrainsPast4%RequiredtoExceedDefinedSafetyMarginLossofCoolantAccident-ContainmentPressureNoCoreorContainment.SpraysFigureDeletedDrywelltoConcreteAirGapTypicalPenetrationsBiologicalShieldWallConstructionDetailsVentPipeandSuppressionChamberPrimaryContainmentSupportandAnchorage.SealDetails-DrywellShellSteelandAdjacentConcreteDrywellSliding-Acceleration,Shear,andMomentXVI-12XVI-13XVI-15XVI-16XVI-17XV1-18XVZ-19XVZ-20XVI-21XVI-22XVI-28XVI-32XVI-54XVZ-60XVI-62XVZ-64XVI-66XVI-70XVI-71XVI-73XVI-75UFSARRevision12XxxixJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberXVZ-22XVI-23XVZ-24XVI-25xvI-26XVZ-27XVZ-28XVI-29XVZ-30XVI-31XVI-32XVZ-33XVZ-34XVZ-35xvz-36XVI-37xvI-38XVZ-39XVI-40XVZ-41XVI-42XVZ-43XVI-44xvI-45XVI-46XVI-47XVI-48XVZ-49TitleShearResistanceCapability-InsideDrywellShearResistanceCapability-OutsideDrywellDrywell-SupportSkirtJunctionStressesPointLocationforContainmentSpraySystemPipingHeatExchangertoDrywellComparisonofStaticandDynamicStresses(PSI)SeismicConditions-ContainmentSpraySystemHeatExchangertoDrywellConductioninaDropletLossofCoolantAccident-ContainmentPressureLossofCoolantAccident-ContainmentPressureNozzleSprayTest-PressureDropof80psigNozzleSprayTest-PressureDropof80psigNozzleSprayTest-PressureDropof30psigNozzleSprayTest-PressureDropof30psigSeismicAnalysis-ReactorBuildingDynamicAnalysis-DrywellReactorSupportStructure-SeismicSeismicAnalysis-WasteBuildingSeismicAnalysis-ScreenhouseSeismicAnalysis-TurbineBuilding(NorthofRowC)SeismicAnalysis-TurbineBuilding(SouthofRowC)SeismicAnalysis-ConcreteVentilationStackReactorBuildingMathematicalModel(North-South)ReactorSupportStructure-SeismicReactorSupportStructure-ReactorBuildingReactorSupportStructure-ReactorBuildingandSeismicPlanofBuildingWallSection1WallSection1-Detail"A"WallSection1-Detail"B"PRcRBXVI-80XVI-81xvI-82XVZ-100XVI-103XVI-109XVI-115XVZ-117XVI-118XVI-119XVZ-120XVI-121XVI-134XVI-135XVI-136XVI-137XVI-138XVI-139XVI-140XVI-141XVI-144XVI-147XVZ-148XVI-149XVZ-169XVI-170XVZ-171XVI-172UFSARRevision12xlJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberTitlePacaeXVI-50XVI-51XVI-52XVI-53XVI-54XVI-55XVI-56XVI-57XVZ-58XVZ-59XVI-60XVI61WallWallWallWallWallWallWallWallWallWallWallWallSectionSectionSectionSectionSectionSectionSectionSectionSectionSectionSectionSection1-Detail1-Detail"D"1-Detail"E"233A-Details44-Detail14-Detail2567XVI-173XVI-174XVI-175XVI-176XVI-177XVI-178XVZ-179XVI-180XVI-181XVI-182XVI-183XVI-184XVZI-1XVII-2XVII-3XVII-4XVII-5XVII-6XVII-7XVII-8XVZI-9XVZI-10XVIZ-11XVII-12XVII-13XVII-14XVII-15XVII-16XVZZ-17XVII-18XVZZ-19Average'3-'4Average'3-'4Average'3-'4Average'3-'4AverageAverageAverageAverage'3-'4Average'3-'4Average'3-'4Average'3-'4Average'3-'4AverageAverage'3-'4Average'3-'4Average'3-'4Average'3-'4AverageSeptembAverage'3-'4WindRosesforJanuaryWindRosesforFebruaryWindRosesforMarchWindRosesforAprilWindRosesforMay'3-'4WindRosesforJune'3-'4WindRosesforJuly'63-'64WindRosesforAugustWindRosesforSeptemberWindRosesforOctoberWindRosesforNovemberWindRosesforDecemberWindRosesfor'63-'64DiurnalLapseRateJanuaryFebruary'3-'4DiurnalLapseRateMarchApril'3-'4DiurnalLapseRateMayJune'3-'4DiurnalLapseRateJulyAugust'3-'4DiurnalLapseRateer'3-'4,October'3-'4DiurnalLapseRateNovemberDecember'2-'3XVII-3XVII-4XVZI-5XVII-6XVII-7XVZI-8XVII-9XVII-10XVII-11XVII-12XVIZ-13XVII-14XVII-15XVII-20XVIZ-21XVIZ-22XVII-23XVIZ-24XVII-25UFSARRevisionxliJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberXVII-20XVII-21XVII-22XVIZ-23XVII-24XVII-25XVII-26XVII-27XVZZ-28XVIZ-29XVII-30XVII-31XVIZ-32XVII-33XVII-34XVZI-35XVII-36XVIZ-37XVII-38TitleLapseRatesbyWindSpeedandTurbulenceClassesforJanuary'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforFebruary'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforMarch'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforApril'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforMay'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforJune'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforJuly'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforAugust'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforSeptember'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforOctober'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforNovember'3-'4LapseRatesbyWindSpeedandTurbulenceClassesforDecember'3-'4SectorMapCenterlineConcentrationsTurbulenceClassICenterlineConcentrations-TurbulenceClassIICenterlineConcentrations-TurbulenceClassIIICenterlineConcentrations-TurbulenceClassIVCenterlineConcentrationsTurbulenceClassIZBecomingClassIVat2kmandClassIIat23kmCenterlineConcentrations-TurbulenceClassIVBecomingClassIIat16km~acaeXVZI-27XVZI-28XVZI-29XVII-30XVII-31XVII-32XVII-33XVII-34XVZZ-35XVII-36XVZI-37XVIZ-38XVZI-44XVII-47XVII-48XVZI-49XVII-50XVIZ-51XVZI-52UFSARRevisionxiiiJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberTitlePacaexvzz-39XVII-40XVII-41XVII-42XVII-43XVII-44XVII-45XVZI-46XVII-47XVII-48XVII-49XVII-50XVII-51XVII-52XVII-53XVIZ-54XVII-55XVZI-56XVII-57XVZI-58XVII-59CenterlineConcentrations-TurbulenceClassIVBecomingClassIIat2kmRadialConcentrations-TurbulenceClassIRadialConcentrations-TurbulenceClassIIRadialConcentrations-TurbulenceClassIllRadialConcentrations-TurbulenceClassIVRadialConcentrations-TurbulenceClassIIBecomingClassZVat2kmandClassIIat23kmRadialConcentrations-TurbulenceClassZVBecomingClassIzat16kmRadialConcentrations-TurbulenceClassZVBecomingClassZZat2kmCenterlineGammaDoseRates-TurbulenceClassICenterlineGammaDoseRates-TurbulenceClassZZCenterlineGammaDoseRatesTurbulenceClassIZICenterlineGammaDoseRates-TurbulenceClassIVCenterlineGammaDoseRatesTurbulenceClassIzBecomingClassZVat2kmandClassIzat23kmCenterlineGammaDoseRatesTurbulenceClassIVBecomingClassIIat16kmCenterlineGammaDoseRates-TurbulenceClassIVBecomingClassIIat2kmAssumedConcentrationandDoseRateDistributionsClosetotheElevatedSourceGammaDoseRateasaFunctionofGyat1kmFromtheSourceSoutheasternLakeOntarioDilutionofRisingPlumeEstimatedLakeCurrentsatCoolingWaterDischargeTemperatureProfilesinanEastwardCurrentattheOswegoCityWaterIntakeXVZI-54XVZI-57XVII-58XVII-59XVII-60XVZI-61XVII-62xvzZ-63XVIZ-93XVIZ-94XVIZ-95XVZI-96XVII-97XVZZ-98XVII-99Xvzz-101XVII-102XVII-108XVII-112XVIZ-113XVII-125UFSARRevision12xliiiJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)FigureNumberXVZI-60XVII-61XVZI-62XVIZ-63XVII-64XVII-65TitleSubsurfaceSectionPlotPlanLogofBoring(BoringCB-1)LogofBoring(BoringCB-2)LogofBoring(BoringCB-3)LogofBoring(BoringCB-4)AttenuationCurvesPacaeXVII-133XVZI-134XVII-135XVII-136XVZI-137XVII-141UFSARRevision12xlivJune1994 NineMilePointUnit1FSARLISTOFTABLESTableNumberXI-1ZI-2ZI-3IZ-4II-5xx-6IX-7II-8V-1V-2V-3V-4V-5VI-1VI-2VI-3aVZ-3bVI-3cVI-4VZ-5VII-1VIXI-1VIXI-2VIII-3Title1980PopulationandPopulationDensityforTownsandCitiesWithin12MilesofNineMile.Point-Unit1CitiesWithina50-mileRadiusoftheStationWithPopulationsover10,000RegionalAgriculturalUseRegionalAgriculturalStatistics-CattleandMilkProductionIndustrialFirmsWithin8km(5mi)ofUnit1PublicUtilitiesinOswegoCountyPublicWaterSupplyDataforLocationsWithinanApproximate30-MileRadiusRecreationalAreasintheRegionReactorCoolantSystemDataOperatingCyclesandTransientAnalysisResultsFatigueResistanceAnalysisCodesforSystemsConnectedtotheReactorCoolantSystemTimetoAutomaticBlowdownDrywellPenetrationsSuppressionChamberPenetrationsReactorCoolantSystemIsolationValvesPrimaryContainmentIsolationValves-LinesEnteringFreeSpaceoftheContainmentTableDeletedSeismicDesignCriteriaforIsolationValvesXnitialTestsPriortoStationOperationPerformanceTestsAssociationBetweenPrimarySafetyFunctionsandEmergencyOperatingProceduresListofEOPKeyParametersTypeandInstrumentCategoryforNMP1RG1.97'VariablesPacaeIx-6Ix-9ZX-11II-12IX-13II-17IZ-18II-19"V-3V-7V-9V-9V-12aVX-44Vx-46Vx-47VZ-49VZ-51VI-56vx-69VZI-35VXXI-83VIII-85VIIZ-87UFSARRevision12xlvJune1994 NineMilePointUnit1FSARLISTOFTABLES(Cont'd.)TableNumberIX-1XII-1XII-2XII-3XII-4XII-5XII-6XII-7XII-8~iceMagnitudeandDutyCycleofMajorStationBatteryLoadsFlowsandActivitiesofMajorSourcesofGaseousActivityQuantitiesandActivitiesofLiquidRadioactiveWastesAnnualSolidWasteAccumulationandActivityLiquidWasteDisposalSystem-MajorComponentsSolidWasteDisposalSystem-MajorComponentsOccupancyTimesGammaEnergyGroupsAreaRadiationMonitorDetectorLocationsPacaeIX-32XII-2XII-4XII-6XII-14XII-18XII-21XII-22XII-26XIII-1XV-1XV-2XV-4XV-5XV-6XV-7XV-8XV-9XV-9AXV-10XV-11XV-12XV-13XV-14XV-15XV-16XV-17XV-18XV-19ANSIStandardCross-ReferenceUnit1TransientsConsideredTripPointsforProtectiveFunctionsTableDeletedInstrumentAirFailureBlowdownRates'odineConcentrationsFractionalConcentrationsinCloudsMainSteamLineBreakAccidentDosesSignificantInputParameterstotheLoss-of-CoolantAccidentAnalysisCoreSpraySystemFlowPerformanceAssumedinLOCAAnalysisECCSSingleValveFailureAnalysisSingleFailuresConsideredinLOCAAnalysisTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedXV-6XV-14XV-60XV-73XV-76XV-77XV-78XV-82XV-82bXV-97XV-98XV-101XV-102XV-124XV-125XV-131XV-134XV-134XV-136UFSARRevision13xlviJune1995 NineMilePointUnit1FSARLISTOFTABLES(Cont'd.)TableNumberXV-20XV-21XV-21AXV-21BXV-21CXV-21DXV-21EXV-22XV-23XV-24XV-25XV-26XV-27XV-28XV-29XV-29aXV-29bXV-29cXV-29dXV-30XV-32XV-32aXV-33XV-34XV-35XV-36XVI-1XVI-2TitleTableDeletedTableDeletedAnalysisAssumptionsForNineMilePoint-1CalculationsTableDeletedTableDeletedTableDeletedTableDeletedReactorBuildingAirborneFissionProductInventoryStackDischargeRatesFuelHandlingAccidentDoses(REM)FissionProductReleaseAssumptionsAtmosphericDispersionandDoseConversionFactorsEffectonDoseofFactorsUsedintheCalculationsNobleGasReleaseHalogenReleaseWettingofFuelCladdingbyCoreSprayAirborneDrywellFissionProductInventoryReactorBuildingAirborneFissionProductInventoryStackDischargeRatesAirborneDrywellFissionProductInventoryReactorBuildingAirborneFissionProductInventoryStackDischargeRatesSignificantInputParameterstotheDBRContainmentSuppressionChamberHeatupAnalysisDownwindGroundConcentrationsMaximumGroundConcentrationsDiversityFactorsfor"LeastFavorable"GroundConcentrationsfromStackRelease,forGroundRelease,forMaximumGroundConcentrationsReactorBuildingLeakagePathsCodeCalculationSummarySteadyState-(100%FullPowerNormalOperation)PertinentStressesorStressIntensitiesPacaeXV-136XV-136XV-137eXV-137fXV-137gXV-137hXV-137hXV-144XV-145XV-146XV-147XV-148XV-148XV-158XV-159XV-159f'V-159sXV-159uXV-159xXV-167XV-168XV-168XV-169iXV-172XV-173XV-176XV-195XVI-4XVI-6UFSARRevision12xlviiJune1994 NineMilePointUnit1FSARLISTOFTABLES(Cont'd.)TableNumberXVI-3XVI-4XVI-5XVI-6XVI-7XVZ-8XVZ-9xvz-10XVl-11XVI-12XVZ-13XVI-14XVI-15XVI-16XVI-17XVI-18XVZ-19XVZ-20XVI-21XVI-22XVI-23XVI-24XVI-25xvz-26XVI-27XVI-28TitleListofReactionsforReactorVesselNozzlesEffectofValueofInitialFailureProbabilitySingleTransientEventforReactorPressureVessel.PostulatedEventsMaximumStrainsfromPostulatedEventsCoreStructureAnalysisRecirculationLineBreakCoreStructureAnalysis-SteamLineBreakDrywellJetandMissileHazardAnalysisDataDrywellJetandMissileHazardAnalysisResultsStressDuetoDrywellFloodingAllowableWeldShearStressLeakRateTestResultsOverpressureTest-PlateStressesStressSummaryHeatTransferCoefficientsasaFunctionofDropDiameterHeatTransferCoefficientsasaFunctionofPressureRelationshipBetweenParticleSizeandTypeofSprayPatternAllowableStressesforFloorSlabs,Beams,Columns,Walls,Foundations,etc.AllowableStressesforStructuralSteelAllowableStresses-ReactorVesselConcretePedestalDrywell-AnalyzedDesignLoadCombinationsSuppressionChamber-AnalyzedDesignLoadCombinationsACICode505AllowableStressesandActualStressesforConcreteVentilationStackAllowableStressesforConcreteSlabs,Walls,Beams,StructuralSteel,andConcreteBlockWallsSystemLoadCombinationsHighEnergySystems-InsideContainmentPacaeXVI-11XVI-31XVI-33XVI-34xvz-35XVI-37XVI-40xvz-55xvz-56XVI-59xvz-65xvz-86xvz-91xvz-101XVI-110XVI-111XVI-122XVI-127XVI-128xvz-129xvz-130XVI-131XVZ-132XVI-133XVZ-151xvz-155aUFSARRevision12xlviiitune1994 NineMilePointUnit1FSARLISTOFTABLES(Cont'd.)TableNumberXVI-29XVZ-30XVZ-31TitleHighEnergySystems-OutsideContainmentSystemsWhichMayBeAffectedbyPipeWhipCapabilitytoResistWindPressureandWindVelocityPacaeXVI-166XVI-167XVI-185XVZI-1XVZI-2XVZI-3XVZI-4XVII-5XVII-6XVII-7XVII-8XVII-9XVIZ-10XVZI-11XVII-12XVII-13XVZI-14XVII-15XVII-16XVIZ-17XVII-18XVZI-19XVII-20XVII-21DispersionandAssociatedMeteorologicalParametersRelationofSatelliteandNineMPointWindsFrequencyofOccurrenceofLapseRates-1963and1964RelationBetweenWindDirectionRangeandTurbulenceClassesStackCharacteristicsDistributionofTurbulenceClassBySectorsSectorConcentrations-1963-64SectorAElev.350SectorConcentrations-1963-64SectorBElev.350SectorConcentrations-1963-64SectorCElev.350SectorConcentrations-1963-64SectorD,Elev.350SectorConcentrations-1963-64SectorD,Elev.350SectorConcentrations-1963-64SectorEElev.350SectorConcentrations-1963-64SectorFElev.350SectorConcentrations-1963-64SectorGElev.350SectorConcentrations-1963-64SectorAGroundHeightSectorConcentrations-1963-64SectorBGroundHeightSectorConcentrations-1963-64SectorCGroundHeightSectorConcentrations-1963-64SectorD,GroundHeightSectorConcentrations-1963-64SectorD~GroundHeightSectorConcentrations-1963-64SectorEGroundHeightSectorConcentrations-1963-64SectorFGroundHeightileesXVII-17XVZI-18XVII-26XVII-40XVZI-56XVII-64XVII-66XVII-67XVII-68XVII-69XVII-70XVZI-71XVII-72XVII-73XVII-75XVII-76XVII-77XVII-78XVIZ-79XVIZ-80XVZI-81UFSARRevision12June1994 NineMilePointUnit1FSARLISTOFTABLES(Cont'd.)TableNumberXVII-22XVII-23XVII-24XVII-25XVII-26XVII-27XVII-28XVII-29XVII-30XVIII-1TitleSectorConcentrations-1963-64SectorGGroundHeightEstimatesoftheLeastFavorable30Daysin100Y'earsConcentrationsintheLeastFavorableCalendarMonth-1963-64AnnualAverageSectorDepositionRates(Vg=0.5cm/sec)AnnualAverageSectorDepositionRates(Vg=2.5cm/sec)PrincipalRadionuclidesinGaseousWasteReleaseCorrectionFactorstoObtainAdjustedCenterlineDoseRatesforSectorEstimatesAnnualAverageGammaDoseRatesDilutionCalculationforEastwardCurrentsBasedonWaterAvailabilitySPDSParameterSetPacaeXVII-82xvII-84XVII-85XVII-88xvII-89XVII-92XVII-104XVII-105XVII-119XVIII-20UFSARRevision12June1994 SECTIONIINTRODUCTIONANDSUMMARYThisreportissubmittedinaccordancewith10CFRPart50.71(e)entitled"PeriodicUpdatingofFinalSafetyAnalysisReports"forNiagaraMohawkPowerCorporation'sNineMilePointUnit1NuclearStation.TheStationislocatedonthesoutheastshoreofLakeOntario,inOswegoCounty,NewYork,7milesnortheastofthecityofOswego.

I-2A.PRINCIPALDESIGNCRITERIAThefollowingparagraphsdescribingtheprincipaldesigncriteriaareorientedtowardthetwenty-sevencriteriaissuedbytheUSAEC.1.0GeneralTheStationisintendedasahighloadfactorgeneratingfacilitytobeoperatedasanintegralpartoftheNiagaraMohawksystem.TherecirculationflowcontrolsystemdescribedinSectionVIIIcontributestothisobjectivebyprovidingarelativelyfastmeansforadjustingtheStationoutputoverapreselectedpowerrange.Overallreliability,routineandperiodictestrequirements,andotherdesignconsiderationsmustalsobecompatiblewiththisobjective.Carefulattentionhasbeengiven.tofabricationproceduresandadherencetocoderequirements.Therigidrequirementsofspecificportionsofvariouscodeshavebeenarbitrarilyappliedtosomesafety-relatedsystemstoensurequalityconstructioninsuchcaseswherethecompletecodedoesnotapply.Forpiping,theASAB31.1-1955Codewasusedandwhereexceptionsweretaken,safetyevaluationswereperformedtodocumentthatanadequatemarginofsafetywasmaintained.WPeriodictestprogramshavebeendevelopedforrequiredengineeredsafeguardsequipment.Thesetestscovercomponenttestingsuchaspumpsandvalvesandfullsystemtests,duplicatingascloselyaspossibletheaccidentconditionsunderwhichagivensystemmustperform.2.0BuildinsandStructuresTheStationplotplan,designandarrangementofthevariousbuildingsandstructuresaredescribedinSectionIII.Principalstructuresandequipmentwhichmayserveeithertopreventaccidentsortomitigatetheirconsequencesaredesigned,fabricatedanderectedinaccordancewithapplicablecodestowithstandthemostsevereearthquake,floodingcondition,windstorm,icecondition,temperatureandotherdeleteriousnaturalphenomenawhichcanbeexpectedtooccuratthesite.'SAECPressRelease8-252,"GeneralDesignCriteriaforNuclearPowerPlantConstructionPermits,"November22,1965.Revision9June1991 I-33.0ReactorAdirect-cycleboilingwatersystemreactor,describedinSectionIV,isemployedtoproducesteam(1030psiginreactorvessel,956psigturbineinlet)foruseinasteam-driventurbine-generator.Theratedthermaloutputofthereactoris1850Mw(t).b.ThereactorisfueledwithslightlyenricheduraniumdioxidecontainedinZircaloy-cladfuelrodsdescribedinSectionIV.Selectedfuelrodsalsoincorporatesmallamountsofgadoliniumasburnablepoison.C~Toavoidfueldamage,theMinimumCriticalPowerRatioismaintainedgreaterthantheSafetyLimitCriticalPowerRatio.d.ThefuelrodcladdingisdesignedtomaintainitsintegritythroughouttheanticipatedfuellifeasdescribedinSectionIV.Fissiongasreleasewithintherodsandotherfactorsaffectingdesignlifeareconsideredforthemaximumexpectedburnup.e.Thereactorandassociatedsystemsaredesignedsothatthereisnoinherenttendencyforundampedoscillations.AstabilityanalysisevaluationisgiveninSectionIV.Heatremovalsystemsareprovidedwhicharecapableofsafelyaccommodatingcoredecayheatunderallcrediblecircumstances,includingisolationfromthemaincondenserandloss-of-coolant,fromthereactor.Eachdifferentsystemsoprovidedhasappropriateredundantfeatures.Independentauxiliarycoolingmeansareprovidedtocoolthereactorunderavarietyofconditions.ThenormalauxiliarycoolingmeansduringshutdownandrefuelingistheshutdowncoolingsystemdescribedinSectionX-A.Aredundantemergencycoolingsystem,describedinSectionV-E,isprovidedtoremovedecayheatintheeventthereactorisisolatedfromthemaincondenserwhilestillunderpressure.Additionalcoolingcapabilityisalsoavailablefromthehigh-pressurecoolantinjectionsystemandthefireprotectionsystem.Revision9June1991 g,h.Redundantandindependentcorespraysystemsareprovidedtocoolthecoreintheeventofaloss-of-coolantaccident.Automaticdepressurizationisincludedtorapidlyreducepressuretoassistwithcoresprayoperation(seeSectionVII-A).Operationofthecorespraysystemassuresthatanymetal-waterreactionfollowingapostulatedloss-of-coolantaccidentwillbelimitedtolessthan1percentoftheZircaloyclad.Reactivityshutdowncapabilityisprovidedtomakeandholdthecoreadequatelysubcritical,bycontrolrodaction,fromanypointintheoperatingcycleandatanytemperaturedowntoroomtemperature,assumingthatanyonecontrolrodisfullywithdrawnandunavailableforuse.ThiscapabilityisdemonstratedinSectionIV-B.AphysicaldescriptionofthemovablecontrolrodsisgiveninSectionIV-B.ThecontrolroddrivehydraulicsystemisdescribedinSectionX-C.Theforceavailabletoscramacontrolrodisapproximately3000poundsatthebeginningofascramstroke.Thisiswellinexcessofthe440-poundforcerequiredintheeventoffuelchannelpinchingofthecontrolrodbladeduringaloss-of-coolantaccidentasdiscussedinSectionXV.Evenwithscramaccumulatorfailureaforceofatleast1100poundsfromreactorpressureactingaloneisavailablewithreactorpressuresinexcessof800psig.Redundantreactivityshutdowncapabilityisprovidedindependentofnormalreactivitycontrolprovisions.Thissystemhasthecapability,asshowninSectionVII-C,tobringthereactortoacoldshutdowncondition,Kf<0.97,atanytimeinthecorelife,independenAfthecontrolrodsystemcapabilities-.Aflowrestrictorinthemainsteamlinelimitscoolantlossfromthereactorvesselintheeventofamainsteamlinebreak(SectionVII-F).4.0ReactorVessela0Thereactorcoreandvesselaredesignedtoaccommodatetrippingoftheturbinegenerator,lossofpowertothereactorrecirculationsystemandothertransientsandmaneuverswhichcanbeexpectedwithoutcompromisingsafetyandwithoutfueldamage.

NineMilePointUnit1FSARAbypasssystemhavingacapacityofapproximately40percentofturbinesteamflowforthethrottlevalveswideopenconditionpartiallymitigatestheeffectsofsuddenloadrejection.ThisandothertransientsandmaneuverswhichhavebeenanalyzedaredetailedinSectionXV.b.Separatesystemstopreventseriousreactorcoolantsystemoverpressureareincorporatedinthedesign.Theseincludeanoverpressurescram,solenoid-actuatedreliefvalves,safetyvalvesandtheturbinebypasssystem.Ananalysisoftheadequacyofreactorcoolant.systempressurereliefdevicesisincludedinSectionV-C.c~Powerexcursionswhichcouldresultfromanycrediblereactivityadditionaccidentwillnotcausedamage,eitherbymotionorrupture,tothepressurevesselorimpairoperationofrequiredsafeguardssystems.Themagnitudeofcrediblereactivityadditionaccidentsiscurtailedbycontrolrodvelocitylimiters(SectionVII-D),byacontrolrodhousingsupportstructure(SectionVII-E),andbyproceduralcontrolssupplementedbyarodworthminimizer(SectionVIII-C).PowerexcursionanalysesforcontrolroddropoutaccidentsareincludedinSectionXV.d.Thereactorvessel=willnotbesubstantiallypressurizeduntilthevesselwalltemperatureisinexcessofNDTT+60'F.TheinitialNDTTofthereactorvesselmaterialisnogreaterthan.40'F.ThechangeofNDTTwithradiationexposurehasbeenevaluatedinaccordancewithRegulatoryGuide1.99,Revision2.Vesselmaterialsurveillancesamplesarelocatedwithinthereactorvesseltopermitperiodicverificationofmaterialpropertieswithexposure.5.0Containmenta~Theprimarycontainment,includingthedrywell,pressuresuppressionchamber,associatedaccessopeningsandpenetrations,isdesigned,.fabricatedanderectedtoaccommodate,withoutfailure,thepressuresandtemperaturesresultingfromorsubsequenttothedouble-endedruptureorequivalentfailureofanycoolantpipewithinthedrywell.UFSARRevisionI-5June1993 I-6Theprimarycontainmentisdesignedtoaccommodatethepressuresfollowingaloss-of-coolantaccidentincludingthegenerationofhydrogenfromametal-waterreaction.PressuretransientsincludinghydrogeneffectsarepresentedinsectionXV.TheinitialNDTTforthe.primarycontainmentsystemisabout-20FandisnotexpectedtoincreaseduringthelifetimeoftheStation.ThesestructuresaredescribedinSectionVI-A,BandC.Additionaldetails,particularlythoserelatedtodesignandfabricationareincludedinSectionXVI.Provisionsaremadefortheremovalofheatfromwithintheprimarycontainment,forreasonableprotectionofthecontainmentfromfluidjetsormissilesandsuchothermeasuresasmaybenecessarytomaintaintheintegrityofthecontainmentsystemaslongasnecessaryfollowingaloss-of-coolantaccident.I<Redundantcontainmentspraysystems,describedinSectionVII,pumpwaterfromthesuppressionchamberthroughindependentheatexchangerstospraynozzleswhichdischargeintothedrywellandsuppressionchamber.Watersprayedintothedrywellisreturnedbygravitytothesuppressionchambertocompletethecoolingcycle.Studiesperformedtoverifythecapabilityof=thecontainmentsystemtowithstandpotentialfluidjetsandmissilesaresummarizedinSectionXVI.Provisionismadeforperiodicintegratedleakagerateteststobeperformedduringeachrefuelingandmaintenanceoutage.Provisionisalsomadeforleaktestingpenetrationsandaccessopeningsandforperiodicallydemonstratingtheintegrityofthereactorbuilding.Theseprovisionsarealldescribejl.in.SectionVI-F.Thecontainmentsystemandallothernecessaryengineeredsafeguardsaredesignedandmaintainedsuchthatoff-sitedosesresultingfrompostulated.accidentsarebelowthevaluesstatedin10CFR100.ThcanalysisresultsaredetailedinSectionXV.Doubleisolationvalvesareprovidedonalllinesdirectlyenteringtheprimarycontainmentfreespaceorpenetratingtheprimarycontainmentandconnectedtothereactorcoolantsystem.Periodictestingofthesevalveswillassuretheircapabilitytoisola':catalltimes.TheisolationvalvesystemisdiscussedindetailinSectionVI-D.

I-7Thereactorbuildingprovidessecondarycontainmentwhenthepressuresuppressionsystemisinserviceandservesastheprimarycontainmentbarrierduringperiodswhenthepressuresuppressionsystem.,isopen,suchasduringrefueling.ThisstructureisdescribedinSectionVI-C.Anemergencyventilationsystem(SectionVII-H)providesameansforcontrolledreleaseofhalogensandparticulatesviafiltersfromthereactorbuildingtothestackunderaccidentconditions.6.0ControlandInstrumentationa~b.TheStationisprovidedwithacontrolroom(SectionIII-B)whichhasadequateshieldingandotheremergencyfeaturestopermitoccupancyduringallcredibleaccidentsituations.Interlocksorotherprotectivefeaturesareprovidedtoaugmentthereliabilityofproceduralcontrolsinpreventingseriousaccidents.Interlocksystemsareprovidedwhichblockorpreventrodwithdrawalfromamultitudeofabnormalconditions.The-controlrodblocklogicisshowninFiguresVIII-6andVIII-S,respectively,fortheSRMandIRMneutroninstrumentation.Inthepowerrange,APRMinstrumentationprovidesbothcontrolrodandrecirculationflowcontrolblocks,asshowninFigureVIII-14.Reactivityexcursionsinvolvingthecontrolrodsareeitherpreventedortheirconsequencessubstantiallymitigatedbyacontrolrodworthminimizer(SectionVIII-C.4.0)whichsupplementsproceduralcontrolsinavoidingpatternsofhighrodworths,anLPRMneutronmonitoringandalarmsystem(SectionVIII-C.1.1.3)andacontrolrodpositionindicatingsystem(SectionIV-B.6.0)bothofwhichenabletheoperatortoobserverodmovement,thusverifyinghisactions.Acontrolrodovertravelpositionlightverifiesthatthebladeiscoupledtoawithdrawncontrolroddrive.ArefuelingplatformoperationinterlockisdiscussedinSectionXV,RefuelingAccident,which,alongwithotherproceduresandsupplementedbyautomaticinterlocks,servestopreventcriticalityaccidentsintherefuelingmode.

cAcoldwateradditionreactivityexcursionispreventedbytheproceduresandinterlocksdescribedinSectionXV,StartupofColdRecirculationLoop(TransientAnalysis).Security(keycardandalarms)andproceduralcontrolsforthedrywellandreactorbuildingairlocksareprovidedtoensurethatcontainmentintegrityismaintained.Areliable,duallogicchannelreactorprotectionsystemdescribedinSectionVIII-Aisprovidedtoautomaticallyinitiateappropriateactionwhenevervariousparametersexceedpresetlimits.Eachlogicchannelcontainstwosubchannelswithcompletelyindependentsensors,eachcapableoftrippingthelogicchannel.Atripofone-of-twosubchannelsineachlogicchannelresultsinareactorscram.Thetripineachlogicchannelmayoccurfromunrelatedparameters,i.e.,highneutronfluxinonelogicchannelcoupledwithhigh-pressureintheotherlogicchannelwillresultinascram.Thereactorprotectivesystemcircuitryfailsinadirectiontocauseareactorscramintheeventoflossofpowerorlossofairsupplytothescramsolenoidvalves.Periodictestingandcalibrationofindividualsubchannelsisperformedtoassuresystemreliability.TheabilityofthereactorprotectionsystemtosafelyterminateavarietyofStationmalfunctionsisdemonstratedinSectionXV.d.Redundantsensorsandcircuitryareprovidedfortheactuationofallequipmentrequiredtofunctionunderpost-accidentconditions.Thisredundancyisdescribedinthevarioussectionsofthetextdiscussingsystemdesign.,7.0ElectricalPowerSufficientnormalandstandbyauxiliarysources.ofelectricalpowerareprovidedtoassureacapabilityforpromptshutdownandcontinuedmaintenanceoftheStationinasafeconditionunderallcrediblecircumstances.ThesefeaturesarediscussedinSectionIX.8.0RadioactiveWasteDisosala~Gaseous,liquidandsolidwastedisposalfacilitiesaredesignedsothatdischargeofeffluentsareinaccordancewith10CFR20and1QCFR50,AppendixI.ThefacilitydescriptionsaregiveninSectionXII-AwhilethedevelopmentofappropriatelimitsiscoveredinSectionII.

I-99.0b.Gaseousdischax'gefromtheStationisappropriatelymonitored,asdiscussedinSectionVIIIandautomaticisolationfeaturesareincorporatedtomaintainreleasesbelowthelimitsof10CFR20and10CFR50,AppendixI.ShieldinandAccessContxolRadiationshieldingandaccesscontrolpatternsaresuchthatdoseswillbelessthanthosespecifiedin10CFR20.ThesefeaturesaredescribedinSectionXII-B.10.0FuelHandlinandStoraeAppropriatefuelhandlingandstoragefacilitieswhichprecludeaccidentalcriticalityandprovideadequatecoolingforspentfuelaredescribedinSectionX.

NineMilePointUnit1FSARB.CHARACTERISTICSThefollowingisasummaryofdesignandoperatingcharacteristics.1.0SiteLocationSizeofSiteSiteandStationOwnershipNetElectricalOutput2.0ReactorOswegoCounty,NewYorkState900AcresNiagaraMohawkPowerCorp.615MW(Maximum)ReferenceRatedThermalOutputDomePressureTurbineInletPressureTotalCoreCoolantFlowRateSteamFlowRate3.0CoreCircumscribedCoreDiameterActiveCoreHeight+Assembly4.0FuelAssembl1850MW1030psig956psig67.5x10~lb/hr7.29x10'lb/hr167.16in171.125inNumberofFuelAssembliesFuelRodArrayFuelRodPitchCladdingMaterialFuelMaterialActiveFuelLengthCladdingOutsideDiameterCladdingThicknessFuelChannelMaterial532SRLR('iReference3Reference3UO~andUO~-Gdz03Reference3>Reference3Reference3Reference3(4)GEFuelBundleDesigns,GeneralElectricCompanyProprietary,NEDE-31152P,February1993.GENE23A7170,Revision3,"SupplementalReloadLicensingReportforNMP1,Reload12,Cycle11,"May1994.UFSARRevision13I-10June1995 NineMilePointUnit1FSAR5.0ControlSstemNumberofMovableControlRodsShapeofMovableControlRodsPitchofMovableControlRodsControlMaterialinMovableControlRodsTypeofControlDrivesControlofReactorOutput129Cruciform12.0inB4C-70%TheoreticalDensity;HafniumBottomEntry,HydraulicActuatedMovementofControlRodsandVariationofCoolantFlowRate6.0CoreDesinand0eratinConditios7.0MaximumLinearHeatGenerationRateHeatTransferSurfaceAreaAverageHeatFlux-RatedPowerXnitialCriticalPowerRatioforMostLimitingTransientsCoreAverageVoidFraction-CoolantwithinAssembliesCoreAverageExitQuality-CoolantwithinAssembliesDesinPowerPeakinCoreOperatingLimitsReport50I496119,830Btu/hr-ft~CoreOperatingLimitsReport0.28010.715%FactorTotalPeakingFactorP8x8R-3.00GE8x8EB-2.90GE11-2.94(')-2.62+Maximumtotalpeakingfactorfortheportionofthebundlecontainingpartlengthrods(latticetypes1522,1519and1520perReference3).Maximumtotalpeakingfactorfortheregionabovethepartlengthrods(latticetypes1521,1523and1524perReference3).UFSARRevision13I-11June1995 NineMilePointUnit1FSAR8.0NuclearDesinDataAverageInitialVolumeMetricEnrichmentBeginningofCycle11-CoreEffectiveMultiplicationandControlSystemWorth-NoVoids,20C<4>UncontrolledFullyControlledStrongestControlRodOutReference31.0980.9580.981StandbyLiquidControlSystemCapability:ShutdownMargin(cR)20CXeonFreeSRLR~~SRLR~~9.0eactorVesselInsideDiameterInternalHeightDesignPressure17ft-9in63ft-10in1250psigat575F10.0CoolantRecirculationLoosLocationofRecircu-lationLoopsNumberofRecircula-tionLoopsandPumpsPipeSize11.0PrimarContainmentContainment'rywe1128inTypeDesignPressureofDrywellVesselDesignPressureofSuppressionChamberVesselDesignLeakageRatePressureSuppression62psig35psig0.5weightpercentperdayat35psigUFSARRevision13I-,12June1995 NineMilePointUnit1FSAR12.0SecondarContainmentTypeInternalDesignPressureDesignLeakageRateReinforcedconcreteandsteelsuperstructurewithmetalsiding40lb/ft'00%freevolumeperdaydischargedviastackwhilemaintaining0.25-inwaternegativepressureinthereactorbuildingrelativetoatmosphere13.0StructuralDesinSeismicGroundAccelerationSustainedWindLoadingControlRoomShielding0.11g125mph,300ftabovegroundlevelDosenottoexceedhourlyequivalent(basedon40-hrweek)ofmaximumpermissiblecgxarterlydosespecifiedin10CFR2014.0StationElectricalSstemIncomingPowerSourcesOutgoingPowerLinesOnsitePowerSourcesProvidedTwo115-kVtransmissionlinesTwo345-kVtransmissionlinesTwodieselgeneratorsTwosafety-relatedStationIbatteriesOnenonsafety125-Vdcbatterysystem15.0ReactorInstrumentationSstemLocationofNeutronMonitorSensorsIn-coreRangesofNuclearInstrumentation:FourStartupRangeMonitorsEightIntermediateRangeMonitors120PowerRangeMonitorsSourceto0.01%ratedpowerandto10%withchamberretraction0.0003%to10%ratedpower1%to125%ratedpowerUFSARRevision12I-13June1994 16.0ReactorProtectionSstemNumberofChannelsinReactorProtectionSpstemNumberofChannelsReguiredtoScramorEffectOtherProtectiveFunctionsNumberofSensorsperMonitoredVariableineachChannel(Minimumforscramfunction)

IDENTIFICATIONOFCONTRACTORSTheGeneralElectricCompanywasengagedtodesign,fabricateanddeliverthenuclearsteamsupplysystem,turbine-generatorandothermajorelementsandsystems.GeneralElectricalsofurnishedthecompletecoredesignandnuclearfuelsupplyfortheinitialcoreandiscurrentlyfurnishingreplacementcores.NiagaraMohawkPowerCorporation,actingasitsownarchitectengineer,specifiedandprocuredtheremainingsystemsandcomponentsincludingthepressuresuppressioncontainmentsystem,andcoordinatedthecompleteintegratedStation.StoneandWebsterEngineeringCorporationwasengagedbyNiagaraMohawktomanagefieldconstruction.Currently,NiagaraMohawkutilizesvariouscontractorstoassistincontinuousstationmodifications.

GENERALCONCLUSIONSThefavorablesitecharacteristics,criteriaanddesignrequirementsofallthesystemsrelatedtosafety,thepotentialconsequencesofpostulatedaccidentsandthetechnicalcompetenceoftheapplicantanditscontractorsassurethattheNineMilePointUnit1NuclearStationcanbeoperatedwithoutendangeringthehealthandsafetyofthepublic.