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

REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9607020103 DOC.DATE:

96/06/28NOTARIZED:

YESDOCKETFACIL:50-220 NineMilePointNuclearStation,Unit1,Niagaraowe05000220AUTH.NAMEAUTHORAFFILIATION SYLVIA,B.R.

NiagaraMohawkPowerCorp./ofpRECAP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)

SUBJECT:

ForwardsRev14toNMPUnit1UpdatedFSAR,including changestoQAprogramdescription 6annual10CFR50.59 safetyeva1uationsummaryrept.DISTRIBDTION CODE:A053DCOPIESRECEIVED!LTR IENCLJISIZE:TITLE:ORSubmittal:

UpdatedFSAR(50.71)andAmendments NOTES:RECIPIENT IDCODE/NAME PD1-1PDINTERNAL:

AYERSFILECENTER01EXTERNAL:

IHSNRCPDRCOPIESLTTRENCL1022'221111RECIPIENT IDCODE/NAME HOOD,DAEOD/DOA/IRB RGN1NOACCOPIESLTTRENCL11111111DUNNOTETOALL"RIDS"RECIPIENTS:

PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFNSD-5(EXT.

415-2083)

TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:

LTTR11ENCLlo N

NIAGARAMOHAWKCENERATIONBUSINESSCROUPB.RALPHSYLVIAExecutive VicePresident Generation BusinessGroupChiefNuclearOfficer300ERIEBOULEVARD WEST.SYRACUSE, NEWYORK13202/TELEPHONE (315)4284983June28,1996NMP1L1090U.S.NuclearRegulatory Commission Attn: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:

Submittal ofRevision14totheNineMilePointNuclearStationUnit1FinalSafetyAnalysisReport(Updated),

Including ChangestotheQualityAssurance ProgramDescnption, andtheAnnual10C.F.R.5$0.$9SafetyEvaluation SummaryReportGentlemen:

Pursuanttotherequirements of10C.F.R.$50.71(e),

10C.F.R.$50.54(a)(3),

and10C.F.R.$50.59(b)(2),

NiagaraMohawkPowerCorporation herebysubmitsRevision14totheNineMilePointNuclearStationUnit1FinalSafetyAnalysisReport(Updated),

including changestotheNiagaraMohawkPowerCorporation QualityAssurance TopicalReport,andtheannualSafetyEvaluation SummaryReport.One(1)signedoriginalandten(10)copiesoftheUnit1FSAR(Updated),

Revision14,areenclosed.

CopiesarealsobeingsentdirectlytotheRegionalAdministrator, RegionI,andtheSeniorResidentInspector atNineMilePoint.TheUnit1FSAR(Updated) revisioncontainschangesmadesincethesubmittal ofRevision13inJune1995.Inaddition, manyoftheUnit1FSAR(Updated)

Sectionshavebeenreformatted intheirentiretytoeliminate blankpages,establish auniformleft-margin justification format,andtoreorganize theinformation into"Text/Table/Figure" order.Thecertification requiredby10C.F.R.$50.71(e)isattached.

Enclosure A'provides theidentification, reason,andbasisforeachchangetothequalityassurance programdescription, Unit1FSAR(Updated)

AppendixB,inaccordance with10C.F.R.$50.54(a)(3)(ii).

9607020i03 960628PDRADQCK'5000220 KPDR

Page2TheenclosedannualSafetyEvaluation SummaryReport(Enclosure B)containsbriefdescriptions ofchangestothefacilitydesign,procedures, tests,andexperiments.

NoneoftheSafetyEvaluations involvedanunreviewed safetyquestionasdefinedin10C.F.R.$50.59(a)(2).

Verytrulyyours,B.RalphSylviaChiefNuclearOfficerBRS/JJL/kap Enclosures pc:Mr.T.T.Martin,RegionalAdministrator, RegionIMr.D.S.Hood,SeniorProjectManager,NRRMr.B.S.Norris,SeniorResidentInspector RecordsManagement l'.i'll NIACARAMOHAWKGENERATI0NBUSINESSGROUPB.RALPHSYLVIAExecutive VicePresident Generation BusinessGroupChiefNuclearOfficer300ERIEBOULEVARD WEST.SYRACUSE, NEWYORK13202/TELEPHONE (315)428-6983June28,1996NMP1L1090U.S.NuclearRegulatory Commission Attn: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:

Submittal ofRevisionI4totheNineMilePointNuclearStationUnitIFinalSafetyAnalysisReport(Updated),

Including ChangestotheQualityAssurance ProgramDescription, andtheAnnual10C.F.R.550.59SafetyEvaluation SummaryReportGentlemen:

Pursuanttotherequirements of10C.F.R.$50.71(e),

10C.F.R.$50.54(a)(3),

and10C.F.R.$50.59(b)(2),

NiagaraMohawkPowerCorporation herebysubmitsRevision14totheNineMilePointNuclearStationUnit1FinalSafetyAnalysisReport(Updated),

including changestotheNiagaraMohawkPowerCorporation QualityAssurance TopicalReport,andtheannualSafetyEvaluation SummaryReport.One(1)signedoriginalandten(10)copiesoftheUnit1FSAR(Updated),

Revision14,areenclosed.

CopiesarealsobeingsentdirectlytotheRegionalAdministrator, RegionI,andtheSeniorResidentInspector atNineMilePoint.TheUnit1FSAR(Updated) revisioncontainschangesmadesincethesubmittal ofRevision13inJune1995.Inaddition, manyoftheUnit1FSAR(Updated)

Sectionshavebeenreformatted intheirentiretytoeliminate blankpages,establish auniformleft-margin justification format,andtoreorganize theinformation into"Text/Table/Figure" order.Thecertification requiredby10C.F.R.$50.71(e)isattached.

Enclosure Aprovidestheidentification, reason,andbasisforeachchangetothequalityassurance programdescription, Unit1FSAR(Updated)

AppendixB,inaccordance with10C.F.R.$50.54(a)(3)(ii).

Page2TheenclosedannualSafetyEvaluation SummaryReport(Enclosure B)containsbriefdescriptions ofchangestothefacilitydesign,procedures, tests,andexperiments.

NoneoftheSafetyEvaluations involvedanunreviewed safetyquestionasdefinedin10C.F.R.$50.59(a)(2).

Verytrulyyours,B.RalphSylviaChiefNuclearOfficerBRS/JJL/kap Enclosures pc:Mr.T.T.Martin,RegionalAdministrator, RegionIMr.D.S.Hood,SeniorProjectManager,NRRMr.B.S.Norris,SeniorResidentInspector RecordsManagement J

UNITEDSTATESOFAMERICANUCLEARREGULATORY COMMISSION IntheMatterofNiagaraMohawkPowerCorporation (NineMlePointUnit1)DocketNo.50-220CERTIFICATION B.RalphSylvia,beingdulysworn,statesthatheisChiefNuclearOfficerofNiagaraMohawkPowerCorporation; thatheisauthorized onthepartofsaidCompanytosignandfilewiththeNuclearRegulatory Commission thiscertification; andthat,inaccordance with10C.F.R.$50.71(e)(2),

theinformation contained intheattachedletterandupdatedFinalSafetyAnalysisReportaccurately presentschangesmadesincetheprevioussubmittal necessary toreflectinformation andanalysessubmitted totheCommission orpreparedpursuanttoCommission requirement andcontainsanidentification ofchangesmadeundertheprovisions of$50.59butnotpreviously submitted totheCommission.

B.RalphylviaChiefNuclear0ficerSubscribed andsworntobeforeme,aNotaryPublicinandfortheStateofNewYorkandCountyof,this~~dayof,1996.NotaryPublicinandforCounty,NewYorkMyCommission Expires:cLtNAM.'LANDERS NoteryPublic,StateofNewYohRegistration No.i908015Quahfiedfnjefferson CoolnqConrrnission ExpiresOctober13,19r

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

ENCLOSURE AIDENTIFICATION OFCHANGES,REASONS,ANDBASESFORQAPROGRAMDESCRIPTION CHANGES(UNITIUFSARAPPENDIXB)';:;":;-'.UFSARIA'ppe'ndh't::,B:,,:.".

';:.,',"::.;';;'::;::;:'Page'/SeetIon':.,-:':,,::::,::",,::.::-:,:l

=,Si'ih:for,"Con'dttdlnj'.that,."the':Revised;Prigam::-",

-"',".',Gi'ntin'iies to'Stttis~fy)10CFRSO;'Appendh't'8iiid",::,+3","

";::,Contitihn'en'::PreyIously,'.'.A'p'pr'o'y'ed;by":

the':NRC::.'::',:";.',

PageB.0-1,thirdparagraph Changed"Executive VicePresident Nuclear"to"ChiefNuclearOf5cer"Reorganization.

Reorganization approvedbytheNRCviaUnit1LicenseAmendment 157andUnit2LicenseAmendment 71,datedFebnuuy20,1996.PageB.1-1,SectionB.l.1,firstparagraph Replaced"contractors andconsultants" with"suppliers" Editorial.

NMPCusestheterm"suppliers" asasynonymof"contractors" and"consultants,"

andpreferstheterm"suppliers."

Theuseofanall~compassing term(i.e.,using"suppliers" toincludeordescribecontractors, consultants, orvendors)doesnotaffectcompliance with10CFR50AppendixB.PageB.1-1,SectionB.l.1,secondparagraph Changed"Eachorganizational department, including NuclearGeneration, NuclearEngineering, andNuclearSafetyAssessment andSupport(NSAS),isresponsible forthequalityofitsownwork."toread"Eachorganizational department isresponsible forthequalityofitsownwork."Editorial.

Editorial.

N/APageB.1-1,SectionB.1.2.1a.Changed"isdelegated bythePresident tocorporate

offlcers, asdescribed herein"toread"isdelegated bythePresident tocorporate oKcersandtheManagerQualityAssurance, asdescribed herein"EditoriaL Toreflectthattheauthority andresponsibility oftheManagerQualityAssurance isalsodescribed.

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, firstparagraph a.Changed"Executive VicePresident Nuclear"to"ChiefNuclearOfficer"a.Reorganization.

a.Reorganization approvedbyNRCviaUnit1LicenseAmendment 157andUnit2LicenseAntendment 71,datedFebnuuy20,1996.Changed"...including allfunctions performed byNuclearGeneration, NuclearEngineering, NuclearSafetyAssessment andSupport,NuclearController,

..."toread"...including thePlantGeneration andEngineering Functions undertheVicePresident andGeneralManager-Nuclear,NuclearSafetyAssessment andSupport(NSAS),BusinessManagement,..."

b.Reorganization.

SameasItema.PageB.1-2,SectionB.1.2.1.1, secondparagraph Changed"Controller NuclearDivision" to"GeneralManagerBusinessManagement" Reorganization.

Titlechange.Positiontitlechangetoreflectmanagement ofbusinesscomputers andfiruume/accounting activities underthepositionofGeneralManagerBusinessManagement.

Thisisanadministrative management positionwhichdoesnotperformQArelatedactivities.

".-;;:",.;UFSAR'"'Appendix 8"':i,"".;:".':

'-,".-"",:,:.'-::.,:,:PagelSectlon<'-',-'.-.',:l,-,:,l

'..',;-';:::",",$

'"',j'-"IderitIficatlon'oE;Cliaiige::.

""i'."i!,;.'::;-':.':::-;::;,"",:.'.;:!'Reason'for,,Change':".'.::;i,"-:::--"'-:."'::.'-::"

'.Bi'sls, for,'.,Co'n'eluding that;thee':Revtsed,&iograiiii::.-':::;:>,,

NConIlriues'hi,Satisfy.:10CFR50!Appendix B;and'";i.-;.:.

,Cotniiiitd1ents Previously',Approved by'.theNRCg~:;PageB.1-2,SectionB.1.2.1.1, Item1Changed"TheVicePresident NuclearGeneration reportstotheExecutive VicePresident Nuclear,andisresponsible forsafeandefficient operation, maintenance, andmodification oftheStationincompliance withStationlicenses, applicable regulations, andtheQAProgram.TheVicePresident NuclearGeneration delegates tothePlantManagersandotherappropriate personnel authority forperfonnance inaccordance withtheQAProgram.SeeTableB-1forQAProgramelementresponsibilities.

Activities performed undertheresponsibility oftheVicePresident NuclearGeneration include:"

toread"TheVicePresident andGeneralManager-NuclearreportstotheChiefNuclearOfficer,andhastheoveraHdivisional responsibility forplantoperation andengineering.

TheVicePresident NuclearEngineering, PlantManagers, andtheGeneralSupervisor LaborRelations reportdirectlytothisVicePresident.

SeeTableB-1forQAProgramelementresponsibilities.

Activities performed undertheresponsibility oftheVicePresident andGeneralManager-Nuclearinclude:"

Corporate management reorganization.

Reorganization approvedbyNRCviaUnit1LicenseAmendment 157andUnit2LicenseAmendment 71,datedFebruary20,1996.

l i";":::::P UFSAR:'Appendh B.;:.;:$:;,"<'P<!:;.';:;::Ide'i'itHication'ofChang'e,"-,<:,.",::;"::::.,".,::'.,:",:,,,;':

IBashfor".,'Co'ndudliig that.the'.Revfsed,Program"'.

",::".;.:

Contliities'to,'Sathfy,';.jOCFR50;Appendht.8

aiilq.';,:

~Comntitm'ents',PrevIon'slyApproved,by',the'NRC!'-:::.v.,'age B.1-3,Item2ChangedItem2toread:"Responsibilities anddutiesoftheVicePresident NuclearEngineering andtheNuclearEngineering organization aredescribed inUnit1UFSARSectionXIH.A.1andUnit2USARSection13.1.1.SeeTableB-1forQAProgramelementresponsibilities."

Corporate management reorganization.

Reorganization approvedbyNRCviaUnit1LicenseAmendment 157andUnit2LicenseAmendmettt 71,datedFebrmuy20,1996.PageB.1-3,Item3ChangedItem3toread:"TheVicePresident NuclearSafetyAssessment andSupportreportstotheChiefNuclearOfficerandisresponsible forQualityAssurance, Licensing, Training/Emergency Preparedness,

Security, andtheUnit2Independent SafetyEngineering ChoupgSEO).SeeTableB-1forQAProgramelementresponsibilities.

NuclearSafetyAssessment andSupportresponsibilities aredescribed inUnit1UFSARSectionXIHandUnit2USARSection13."Corporate management reorganization.

Reorganization approvedbyNRCviaUnit1LicenseAmendment 157andUnit2LicenseAmendment 71,datedFebruary20,1996.PageB.1-3,Item4,firstparagraph Changed"Executive VicePresident Nuclear"toread"ChiefNuclearOfficer"Corporate management reorganization.

Reorganization approvedbyNRCviaUnit1LicenseAmadment157andUnit2LicenseAugment71,datedFebruary20,1996.

,I

',:'~'~UFSAR'!Appendli,B.~,'-";,;:;

=.j:",:~+:Page/Sectlon.:'..;,::;::.':;;,;'-:,',-,

i,"::;;.:,';;";':;'.".,::,IdetItilici

.Siishi'forConcluding tImt'thi"Revtse'd Piogrt'un'.'s,"

...'.;:Con/biue's,,tYi:Sibsfy,'.10CFR50'Appendix B;ttnd"':g>:;:-

'CotttrnItiiients'PievIottsly:Approv'ed by'the'.NRC:,"'-'-':

PageB.1-3,Item4,secondparagraph a.Changed"Tasksperformed tofulfilltheseresponsibilities include"toread"Tasksperformed tofulfilltheseresponsibilities aredelineated insiteprocedures andinclude"Editorial.

a.Editorial.

N/ACombinedInspections andNDEExaminations asonetaskandremovedthefollowing identified tasks:~Coordinating andReporting InternalandExternalQAAssessments

~Operations Experience A88essnlent

~Administering theEvaluation andCorrective ActionProgramforDeviation EventReports(DERs)~DERTrendAnalysis~Preparing andProcessing QAOrganization Documents b.Editorial.

Manyofthesetasksarealsodescribed undertheresponsibilities ofsupervisors orinothersectionsoftheQATR.Administering theEvaluation andCorrective ActionProgramforDeviation/Event Reports(DERs)istheresponsibility ofthePlantManagers.

b.Editorial.

N/AC,Addedthefollowing tasks:~RecordsManagement

~DocumentControlc.Reorganization.

c.Reorganization approvedbyNRCvialetterdatedJuly13,1995.

';':"':":jUFSAR'.Appeii'dbr'8-:.,:;::::

,';:.-,'::;:,.",IderiIdicaIIon ofChange+~,;:;,:;:::~:,:.;-;,-.::,

,".,",';-'Reison foi",Cliaiigi.",;";."..,:.","."..:':.;"',i:

':,iBisls,t'or,'Coaduding'that the.Revtse'0Piogiasnt"-'"..'."'.'.-

~Coritliiiies.,'to,Siibsfy.';10CFR50'Appendix:B,and

':;:;"::::;>

lCon'ti'nitntents Pk'vionsiy".Appr'oved bytheNRC.":,=;";

PageB.14,Item4.bChanged"...determining applicability ofindustryandin-plantexperience" toread"~..assessments determining applicability ofindustryandin-plantoperating experience" Editorial clarification.

Incorporates theterm"assessments" associated withoperations experience assessments intosupervisor responsibilities.

Editorial.

N/APageB.IQ,Item4.dChanged"...performing sourcesurveillances ofselectedprocurements" toread"...performing supplierevaluations andsourcesurveillances ofselectedprocurements" Editorial clarification.

Qualifies thetypeofactivities thataredonebytheProcurement QualityAssurance Group.Editorial.

N/APageB.14,Item4.eAddedItem4.etodescribetheresponsibilities oftheGeneralSupervisor QualityServicesReorganization established newpositionofSupervisor QualityServiceswhichwaslaterchangedtoGeneralSupervisor QualityServices.

Reorganization approvedbyNRCvialetterdatedJuly13,1995.Titlechangeisadministrative innatureanddoesnotaffectpositionfunctions orresponsibiTities.

PageB.2-2,SectionB.2.2.3,firstparagraph Changed"Executive VicePresident Nuclear"to'ChiefNuclearOKcer"Reorganization titlechange.Reorganization reviewedandapprovedbyNRCviaUnit1LicenseAmendment 157andUnit2LicenseAmendment 71,datedFebruary'20, 1996.

'JI

';':".<<;.:-',',":

'"',.Id4Basb"for',,Coiidiidbig thatthe.'Revfsed,Piog'ram'!"-.;,,",'--Continues'to Satbfy':,10CN50;Appen'dix'.B:arid:.'-',5$

='Commitinents Pr'evIously,"Appi'oved by,.theNRC:.;-.PageB.2-5,SectionB.2.2.15, Item1Changedwordingfrom"TheManagerQualityAssurance isresponsible forreporting onthestatus,adequacyandeffectiveness oftheNMPCQAProgramthroughtheNuclearDivisionInternalSALPTypeAssessment Reports"toread"TheChiefNuclearOfficerisresponsible forreporting onthestatus,adequacyandeffectiveness oftheNMPCQAProgram"Clarification andreorganization titlechange.AlthoughtheManagerQualityAssurance isresponsible forreporting onthestatus,adequacyandeffectiveness oftheQAProgramtotheChiefNuclearOfficer,itistheChiefNuclearOfficerthatreportstothePresident orChiefExecutive Officer(CEO).TheChiefNuclearOKcerreportstothePresident ofNMPCasdescribed inUnit1LicenseAmendment 157andUnit2LicenseAnieixlnient 71,datedFebruary20,1996.PageB.2-5,SectionB.2.2.15, Item2Changed"Executive VicePresident Nuclear"to"ChiefNuclearOfficer"Reorganization titlechange.Reorganization ofcorporate management approvedbyNRCviaUnit1LicenseAmendmerit 157andUnit2LicenseAmendmeiit 71,datedFebnuuy20,1996.PageB.24,SectionB.2.2.16Changedwordingfrom"TheSRABisastandingcommittee chairedbytheVicePresident NuclearEngineering andreportstotheExecutive VicePresident Nuclearregarding designated QAfunctions attheNineMilePointNuclearStation"toread'TheSRABisastandingcommittee reporting totheChiefNuclearOfficerregarding designated QAfunctions attheNineMilePointNuclearStation"Clarification.

TomoreclearlyreflectPlantAdministrative Technical Specifications.

ThechangemoreclearlyreflectsPlantTechnical Specifications, Administrative ControlsSection,andalsoreflectscorporate management positiontitlechangesassociated withUnitILicenseAmendment 157andUnit2LicenseAmendment 71.PageB.24,SectionB.2.2.17Changedwordingfrom"TheSORCisanindependent reviewcommittee responsible totheVicePresident NuclearGeneration andtransmits reportstotheSRAB"toread"TheSORCisanindependent reviewcommittee responsible tothePlantManagersandtransmits reportstotheSRAB"Clarification.

TomoreclearlyreflectPlantAdministrative Technical Specifications.

ThechangemoreclearlyreflectsPlantTechnical Specifications, Administrative ControlsSection,andalsoreflectscorporate management positiontitlechangesassociated withUnit1LicenseAmendment 157andUnit2LicenseAmendnient

71.

":;,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>

>Commitments Prevloiisly",.":A'jipx'oved by,':the',NRC-">>."

PagoB.24,SectionB.2.2.18Changedwordingfrom"...andactionsareverifiedbyQ1Ppersonnel priortocloseout" toread"...andtheactionsareverifiedpriortocloseout" Clarification.

WhileQ1Ppersonnel verifytheoverallclosureofallitems,othergroupsmaybeusedtodosomeoftheactualtechnical verifications forcompleteness.

Theoverallindepeadence andconfidentiality ofQ1Phavenotchanged.Thetechnical abiTityofotherdepartmeats isusedtoreviewsomoofthoconcerns.

PageB.4-2,SectionB.4.2.7PagoB.5-1,SectionB.5.2.6Chaagedwordingfrom"NQAorProcurement personnel otherthanthepersonwhogenerated theprocurement dociiment, butcpalifiod inQA,..."tored"Personnel otherthanthepersonwhogenerated theprocurement

document, butwithadecpateuaderstaiding oftherecpirements andintentoftheprocurement documents,..."

AddedSectionB.5.2.6todescnboprocedure reviewprocessClarification.

Asanalteraative toperforming procedure reviewsnolessfrequently thaneverytwoyearstodetermine ifchangesarenecessary ordesirable (ANS-3.2).

NiagaraMohawkhasprogrammatic controlsinplacetocontinually identifyprocedure revisions whichmayboneededtoensureprocedures areappropriate forthecircumstances aadaremaintained currenteThereisnospecificrepireaiont foranyparticular grouptoperformthesereviews,onlythattheindividuals doingthereviewadecpatoly understand thempirements andintentofthoprocurement documeats.

Thisisinaccordance withNQA-l,4S-1,section3,whichisourstatedprogramformeeting10CFR50AppendixB.Thisdoesnotconstitute areduction ofcommitment sincewhoeverdoesthereviewfuactionisrequiredtobecpalified.

ThisqualiT!cation isaccomplished throughtraining.

NRCapprovalper10CFR50.54 grantedvialetterdatedJanuary30,1996.PageB.7-1,SectionB.7.2.2Changedwordingfrom"Whencontractors performworkundertheirownQAprograms..."

toread"Whensuppliers performworkundertheirownQApfogfaias Editorial.

NMPCusestheterm"suppliers" asasynonymof"contractors,"

aadpreferstbeterm"suppliers."

Thouseofanall~passing tenn(i.o.,using"suppliers" toincludeordescnbecontractors, consultants, orvendors)doesnotaffectcompliance with10CFR50AppendixB.

I(

UFSAR.:"Appiiidlx,B,"'.";'"-,'..

~+~';':-',~IdeiitifiaitIo'ii of,Chaiige;;:,":;;'.-".:,;;.P,,

.,Contlniies,4i'SatlsfyiiOCH60,

:Appendix'8

'an'6=;,';.'"'~j (Coiniiiitinents Pit.vlo'iisly'!hpproved,by,that.

NRC:;.'-:,:.'age B.7-1,SectionB.7.2.3,Item1a.Changedwordingfrom"...result inthesupplierbeingplacedontheQualiTied Contractor ListDatabase(QCLD)asaqualified vendor"to"...result inthesupplierbeingplacedontheQualified SupplierListDatabase(QSLD)"a.Editorial clarification.

Toreflectuseoftheterm"supplier" ratherthan"contractor."

a.Editorial.

N/Ab.Changedwordingfrom"...byvirtueofthisability"toread"...byvirtueoftheirability"b.Editorial.

b.EditoriaL N/AChangedwordingfrom"...characteristics identified byNuclearEngineering andNQA"toread"...Characteristics identified byNuclearEngineering" c.Clarification.

TofullyreflectNuclearEngineering responsibilities.

cNuclearEngineering isresponsible formaintaining thedesignbasisofsystems,structures, andcomporlents andtfallslates designrequirements tosuppliers whicharedeemedcriticalforaparticular item/service.

Theidentification ofcriticalmanufacturing andfunctional processes andcharacteristics byNuclearEngineering continues tosatisfy10CFR50AppendixB,Criterion 7.Changedwordingfrom"...methods havebeenidentified anddocumented bywhichNQAwillverifyconformance totheseiequlfelnents toreadre@methods havebeen$Ienttfiledanddocumented whichwillverifyconformance totheserequirements" d.ClariTication.

d.NQAisinvolvedwithverification ofsupplierprogramswithattention tocriticalprocesses/characteristics

selected, unlesstheycanbeverifiedonsiteviatestand/orinspection.

Theseresponsibilities havenotchangedand,therefore, continuetosatisfy10CFRSOhppendixB.

';"~~":.="-'::::<

IdentIfimtloti':ot,.Change/!-"::.:-':;:.';';;:::::.::::,;;:,:.'.-'.::,'-.:."'%~Reasosn.for,Chatige,",':;:',;:,,:-:-',::,

'.,:::Bash for',Coiicliidlng thatthe':Revtsed,Prog'rain',-':;;~j,"

NConttriues.'to';Sahfy':10CFR50:App'endlx.:B:aciid'-.::""4':

-.Coi'iimitrneeriti':Prevto'tisly,::Approve'd by,'theNRC';-"PageB.7-2,SectionB.7.2.3,Item2a.Changedwordingfrom"NMPC-qualified suppliers involvedinactiveprocurement aresurveyedevery3yrtomaintain..."

toread"NMPC~ified suppliers involvedinactiveprocurement aresurveyedevery3years~tomaintain..."

Thechangefrom3yrto3yearsiseditorial.

Theadditionofanotetoreflectatolerance ofonequarterofayearisalsoeditorial asthisreflectsRegulatory Guide1.28,paragraph 3.2,asdescribed inQATRTableB-3,sheet1of8.a.Editorial.

N/A"<<Withatolerance ofonequarterofayear"b.Changedwordingfrom"Supplier 3-yrsurveys..."

toread"Supplier 3-yearsurveys"b.Editorial.

b.Editorial.

N/APageB.7-2,SectionB.7.2.3,Item3AddedItem3toidentifysuppliers/organizations thatarenotrequiredtobeevaluated orlistedontheQualified SupplierListDatabase(QSLD).Clarification.

Thesestatements clarifytheuseoftheNationalInstitute ofShuxlards andTechnology andotherNRClicensedutilities thatmeettherequirements of10CFRSOAppendixB.PageB.7-3,SectionB.7.2.6Changedwordingfrom"...purchased inaccordance withNuclearEngineering Procedures thatprovide.otoread"purchased inaccordance withprocedures thatprovide..."

Clarification.

ThesecontrolsarenotlimitedtoNuclearEngineering paicedures.

Severaltypesofprocedures areusedtomakesurethatdesigncriteriaisincludedinpurchaserequirements.

AlthoughEngineering procedures providecontrolstoassurethatitemssatisfydesignrequirements, thesecontrolsmayalsobefoundinNuclearInterface Procedures ordepartment procedures otherthanEngineering.'hese procedural controlscontinuetosatisfyIOCFRSOAppendixBCriterion 7.PageB.9-2,SectionB.9.2.9Changedwordingfrom'...keptbyvendorsand/orforwarded toNMPC"toread"...keptbysuppliers and/orforwarded toNMPC"EditoriaL NMPCusestheterm"suppliers" asasynonymof"vendors,"

andpreferstheterm'suppliers."

Theuseofanall~conipassing term(i.e.,using'suppliers" toincludeordescribecontractors, consultants, orvendors)doesnotaffectcompliance with10CFR50AppendixB.10

-

;;.~".';UFSAR::Appendix 8;-g;.;g(~:A:,:;."::".-:."Identdici'tlon,of,:Cha'nge=;..:::;::";-.;.'".'-::c.-:.':j';::-

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4Sashy,;,10CFR50':Appendh;B aril;.';.':;..-,,

.ComnIitmeit9 Prevlou'sly'

Appr'oved.by.Ihe NRC<"-"-,

PageB.10-1,SectionB.10.1Replacedpolicystatement withwordingfromNQA-1Editorial clarification toreflectwordingprovidedinNQA-1.Therestructuring oftheparagraph toreflectNQA-1isconsistent with10CFR50AppendixB,Criterion 10.Allareascontinuetobereviewedexceptforthedeletionofwitnesspoints.Witnesspointshaveeitherbeenupgradedtoholdpointsordeletedbecausetheywerenotneeded.PageB.10-1,SectionB.10.2.2, Item4Changedfrom"Holdpointsand/orwitnesspoints"toread"Holdpoints"WitnesspointsarenolongerusedatNineMilePoint.Allwitnesspointshavebeenconverted toholdpointsordeletedfromNMPCprocedures.

Theremovalofwitnesspointscontinues tosatisfyAppendixB,Criterion 10,sincethosewitnesspointsthatwererequiredhavebeenupgradedtoholdliitsoPageB.10-2,SectionB.10.2.5B.10.2,6B.10.2.7B.10.2.8DeletedpreviousSectionB.10.2.5, whichstated"Witnesspointsrequiresufficient notification ofthespecifying organuation priortoperformance ofthespecified activity" andrenumbered reinaining sectionsaccordingly.

WitnesspointsarenolongerusedatNineMilePoint.Allwitnesspointshavebeenconverted toholdpointsordeletedfromNMPCprocedures.

Theremovalofwitnesspointscontinues tosatisfyAppendixB,Criterion 10,sincethosewitnesspointsthatwererequiredhavebeenupgradedtoholdpoints'age B.10-3,SectionB.10.2.9Changedwordingfrom"Aprogramforinspection andsurveillance ofactivities affecting fireprotection isestablished..."

toread"Aprogramforinspection andsurveillance, asrequired, foractivities affecting fireprotection isestablished..."

Editorial clarification foreaseofreadingaudsentencestructure.

Editorial.

N/APageB.11-2,SectionB.11.2.3, Item5PageB.18-1,SectionB.18.1Changedwonlingfrom"Anywitnessandholdpoints"toread"Anyholdpoints"Changedwonlingfrom"...including thoseelementsoftheprogramimplemented bysuppliers andcontractors" toread'including thoseelementsoftheprogramimplemented bysuppliers" WitnesspointsarenolongerusedatNineMilePoint.Allwitnesspointshavebeenconverted toholdpointsordeletedfromNMPCprocedures.

Editorial.

NMPCusestheterm'suppliers" asasynonymof"contractors,"

andprefersthetenn'suppliers."

Theremovalofwitnesspointscontinues tosatisfyAppendixB,Criterion 10,sincethosewitnesspointsthatwererequiredhavebeenupgradedtoholdpolrlts.Theuseofanallmicompassing term(i.e.,using"suppliers" toincludeordescribecontractors, consultants, orvendors)doesnotaffectcompliance with10CFR50AppendixB.11

,'"::i';:UFSAR A'p'peti'dlx.S,:;;".-.';.'-,.;

.,'.':;.'-:)-:.-,""-PIdeiitificatlon of,Ch'ange';:-,;,,:j,'=,:;:;g,'.<<'::.~;."'~"',",:".;,";.".,

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>,'.Conimsitinents:Prevlot'isly"'Approv'ed,by, theNRC-"-,";

PageB.18-1,SectionB.18.2.3Changedwordingfrom"onceevery2yr"toread"onceevery2years"Editorial.

Editorial N/ATableB-l,sheetIof2a.b.UnderProcedures column,identiTied QualityAssurance (QA),NuclearLicensing (NL),andNuclearTraining(N'I)undertheVicePresident NuclearSafetyAssessment andSupport(VP-NSAS),andidentified NuclearEngineering (NE)andNuclearGeneration (NG)undertheVicePresident andGeneralManager-Nuclear(VPGM-N).

RemovedNuclearProcurement (NP)fromtheNSASProcedures columntoreflecttransferoftheNuclearProcurement functiontoNuclearEngineering.

Identified NuclearEngineering asresponsible forQAProgramelementsassociated withCriterion IV,accordingly.

Editorial, toreflectcorporate management restmcturing.

b.Reorganization.

a.Editorial.

N/Ab.TheNuclearProcurement organization wastransferred fromNuclearSafetyAssessment andSupport(NSAS)toNuclearEngineering.

Theduties,functions, andresponsibilities ofNuclearProcurement havenotbeenaltered.c,RemovedTechnical Services(TS)andInformation Management (IM)fromtheNSASProcedures cotunm.coReorganization.

cTheduties,responsibilities, andfunctions performed byTechnical Services(TS)andInformation Management (IM)havebeenreassigned tootherbranches, asappropriate.

TheQAProgramelementsonceimplemented byTSandIMhavebeenintegrated intotheappropriate branchandareidentified ontheresnsibilimatrix.12 l,

+:,",,"..,'"'UFSAR'Ap'pend@

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',.::,.ContlntIes,to.Satisfy',:jKFR50,Appendfix 8;and:,,",:.'"":;;.';

jCommttmerits',Prevlou'sty'."Appr'oved by,thi".'RC:;""k TableB.l,sheet1of2(cont'd.)

Identified QualityAssurance responsibiTity forQAProgramelementsassociated withCriteriaVI(Document Control)toreflecttransferofresponsibility fromNuclearEngineering.

d.Reorganization.

d.Reorganization approvedbyNRCvialetterdatedJuly13,1995.TableB-l,sheet2of2RemovedNuclearProcurement (NP),Technical Services(TS),andInformation Management (IM),fromunderNSASProcedures columnandfromlistingofNMPCorganizations.

a.Reorganization.

a.ThefunctionofNuclearProcurement wastransferred fmmtheNuclearSafetyAssessment andSupportorganization toNuclearEngineering.

Thistransferdoesnotaffectdutiesorfunctional responsibilities and,therefore, continues tosatisfy10CFR50AppendixBcriteria.

Theduties,responsibilities andfunctions ofTechnical ServicesandInformation Management havebeentransferred tootherorganizations asappropriate.

b.Identified QualityAssurance responsibility forQAProgramelementsassociated withCriteriaXVH(QualityAssurance Records)toreflecttransferofresponsibility fromNuclearEngineering.

b.Reorganization.

b.Reorganization approvedbyNRCvialetterdatedJuly13,1995.TableB-3,sheet2of8ChangedDocumentcolumnrow"d"fromPara.4toread"Section4"EditoriaL Editorial.

N/A13 1

Enclosure BtoNMP1L1090NINEMILEPOINT-UNIT1SAFETYEVALUATION SUMMARYREPORT1996DocketNo.50-220LicenseNo.DPR-63

SafetyEvaluation SummaryReportPage1of60SafetyEvaluation No.:89-019Rev.0,1,28c3Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:Mod.N1-89-174 XI-14Low-Pressure ReactorFeedwater SystemLow-Pressure ReactorFeedwater SystemDesignPressureReduction

==

Description:==

Thepipewallthickness originally specified forthelow-pressure reactorfeedwater systemwasverymarginalforadesignpressureof600psig.Ifthestandardmanufacturing tolerance andareasonable corrosion allowance, wereconsidered, thesystempipingwasnotadequatefor600psig.For16"pipe,theavailable corrosion allowance forthe40-yearplantlifeisonly.013",assumingthepipewallthickness wassuppliedattheminimumofthemanufacturer's tolerance.

Theoriginalplantspecifications requiredacorrosion allowance of.088".Inordertoprovideadditional marginforcorrosion overtheremaining plantlife,thedesignpressurewasreducedfrom600psigto530psig.Thisincreased theavailable corrosion allowance from.013"to.050".SafetyEvaluation Summary:Thismodification willreducetheoriginaldesignpressureof600psigto530psig.Asaresultofthischange,pressuresafetyreliefvalvesinstalled onfeedwater pumpsuctionpipingandonthefeedwater sideofthefeedwater draincoolersmustberesettothecorresponding designpressure.

Resetting thereliefvalvestothecorresponding designpressurewillnotaffectsystemoperation becausethevalvesprovidenegligible pressurereliefduringnormaloperation oftheequipment/piping eachvalveprotects.

Todemonstrate thatthereliefvalvesprovidenegligible pressurerelieftotheequipment/piping theyprotectduringnormaloperation, thefield-corrected pumpcurveswerereviewed.

Areviewofthepumpcurvesindicates thatduringminimumflowconditions, areduction of150gpmofflowduetoallsixreliefvalvesliftingcorresponds toapproximately zeropressurereduction.

Thepurposeofthevalvesistopreventexcessive pressures inthesystemwhenthesectionofthesystembecomesisolatedbyvalvesandthatsectionmaybesubjected tounexpected sourcesofheat.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage2of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:91-019Mod.N1-88-052 N/ASpentFuelPoolInstallation ofPoisonHighDensitySpentFuelRacksintheSouthHalfoftheSpentFuelPoolDescription ofChange:Modification No.N1-82-013 andSafetyEvaluation 84-003Rev.1encompassed theanalysesdesignandinstallation ofeightpoisonspentfuelracks,or1710storagelocations, inthesouthhalfofthespentfuelpoolfora'totalinstalled capacityof2776locations.

ThiswasapprovedbytheNRCinAmendment 54totheNMP1Operating LicenseDPR-63.Theinstallation wasplannedinphasesasdescribed intheabovesafetyevaluation.

Sixoftheeightrackswereinstalled priortothisplannedmodification.

/Thismodification installed theseventh(216spaces)storagerackinthesouthwest cornerofthepool.Theeighthrack(198spaces)willbeheldinstoresascontingency storage.Thesouthwest workplatformwaspermanently removedandreplacedbyatemporary seismicstrutrestraint.

Theremovaloftheworkplatformuncovered thepoollinerwhichwasdeformedfromapriorinstallation.

Thedeformation (orbubble)wasmappedandlocatedtodetermine theextenttowhichoneoffourrackpedestalsupportshadtobemodifiedsoastoavoidthedeformation.

Following exactinformation obtainedfromthemapping,thepedestalwasreanalyzed andmodifiedaccordingly.

Following thepedestalmodification, thetemporary seismicrestraint wasremovedandtherackinstalled alongwithitsrestraints andseismicbeam.SafetyEvaluation Summary:Aseismiceventoccurring duringtheshortperiodinwhichtheracksareunrestrained isnotconsidered acredibleaccidentcondition.

Thiscondition was SafetyEvaluation SummaryReportPage3of60SafetyEvaluation No.:SafetyEvaluation Summary:91-019(cont'd.)

(cont'd.)

previously described intheJune1983submittal totheNRCandwassubsequently approvedinAmendment 54.Heavyloadswillnotbehandledoverspentfuel.duringreracking.

Priorcriticality, thermal-hydraulics, andpoolstructure analyseswillnotrequirereanalyses asaresultofthismodification.

Therackmechanical analysishas-beenrevisedtoaccountforthepedestalmodification andwillbereviewedfollowing thepoollinermapping.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage4of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:91-033Rev.25.3Gale.4.16KVAC-DG-ES, Rev.2IX-18,FigureIX-6Emergency DieselGenerator Emergency DieselGenerator Essential

.LoadingandLoadManagement Description ofChange:Thissafetyevaluation analyzedachangetotheUnit1UFSARthatresultedfromreconstitution ofthedieselgenerator designbasisloadinganalysis.

Information contained inSectionIXoftheUFSARpertaining todieselgenerator ratingsandaccidentloadingwaschangedtoshowmorecompleteandaccurateinformation.

SafetyEvaluation'ummary:

Maximumexpecteddieselgenerator loadhasbeendetermined bycalculation, comparedtoequipment capability, andfoundtobeacceptable.

Informa'tion previously providedintheUFSARshowsthatmaximumdieselgenerator loadiswithinthemachine's capability.

Thedieselgenerator loadanalysishasdefinedthemaximumallowable designloadbasedonvendorinformation andregulatory guidancedocuments.

TheproposedUFSARchangesareconsistent withtheanalysisanddemonstrate thatthedieselgenerators willbeoperatedwithintheirrating.Withappropriate manualactions,totalloadcanbemaintained withinthemaximumallowable designbasisloadlimit.Manualactionstobereflected inUFSARFigureIX-6agreewithcurrentoperating procedures andincludeshuttingdownacorespraytoppingpump,controlroddrivepumpandacontainment spraypumpunderappropriate plantconditions.

Theimpactonaffectedsystemshasbeenanalyzedanditisconcluded thatthesesystemscancontinuetoperformtheirintendedfunctions asdescribed intheUFSAR.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage5of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:93-056Rev.1,2&3SimpleDesignChangeSC2-0328-92 FigureIII-1~-TitleofChange:Construct aSpareTransformer FacilityDescription ofChange:Thesparetransformer facilitywasconstructed southwest oftheUnit2345-kVswitchyard.

Thisfacilitywillbeusedforthestorageoftheadditional sparetransformer forUnit2.SafetyEvaluation Summary:Theconstruction ofthesparetransformer facilitydoesnotimpactthepertinent licensing issuesthatareassociated withhydrological engineering; i.e.,flooding, localintenseprecipitation (probable maximumprecipitation),

andtheimpactontheairintakeaccidentX/0(Chi/0),theatmospheric dispersion coefficient.i Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage6of60SafetyEvaluation No.:Implementation DocumentNo.:94-004SimpleDesignChangeSC1-0281-91/

SC1-0158-93UFSARAffectedPages:Dwg.B-40143-C Overlay1-3System:CO2FireProtection, FireDetection andProtection (FDP)TitleofChange:RetireStyreneFireDetection ZonesD-8013,D-6053VP, andDA-6063HD Description ofChange:Thischangeretiredinplacethreefiredetection zones.ZoneD-8013islocatedintheStyrene(Binder)PumpHouse.Thepumphouseisitsown'building locatednorthoftheWasteBuilding.

Theflammable substance styrenehasbeenremovedandnootherflammables existatthatlocation.

Thepumpsarenolongeroperational andthebuildingisdesignedexplosion-proof.

ZoneD-6053VPisusedforstyrenevapordetection locatedinthePumpHouseandtheDOWSystem(Radioactive WasteSolidification) mixingareaoftheWasteBuilding.

Withstyreneremoved,thesearenotnecessary.

ZoneDA-6063HD islocatedinthemixinghoodoftheDOWmixingarea,rendering itunnecessary.

TheDOWSystemhasbeenretiredforyears,makingtheseselectedretirements possible.

SafetyEvaluation Summary:Thischangewillremovenuisancealarmspresently onthesystem.Withthealarmsandpanelengraving removed,thiswillaidoperations.

Thischangewillhavenoimpactonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage7of60SafetyEvaluation No.:Implementation DocumentNo.:94-007SimpleDesignChangeSC1-0156-92, SC1-0157-92, SC1-0158-92 UFSARAffectedPages:System:TitleofChange:TableVl-1,FigureVl-22;X-16Containment CuttingandCappingofUnusedContainment PipingDescription ofChange:Theheadspraypiping,reference vesselleakratepiping,andtheelectrochemical pipingareabandoned systemsthatpenetrate thedrywell.Sincethisunusedpipingcontainsvalvesorblindflanges,AppendixJTypeBoriCtestingisrequired.

Thesesimpledesignchangescutandcappedunusedpipingandrestoredthedrywellpenetrations toasparestatus.SafetyEvaluation Summary:/Thecuttingandcappingofunuseddrywellpipingalongwithremovalofvalvesorflangedendswillrestorethedrywellpenetrations toasparestatus.Cappingnearthepenetration andelimination ofisolation valveswilleliminate AppendixJTypeBorCtesting.Potential leakpathsthroughvalvesorflangeswillbeeliminated.

Thecappedlineswillbeconsidered sparesandwillbesubjecttoAppendixJTypeAtestingtoensureoverallcontainment integrity.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage8of60SafetyEvaluation No.:implementation DocumentNo.:UFSARAffectedPages:System:94-008Temporary Mod.94-019X-34ServiceAirTitleofChange:Installation ofaPortableHouseServiceAirCompressor Description ofChange:Thistemporary modification installed aportableaircompressor atvalveHSA-113locatedattheTurbineBuildingelevation 300'.Thistemporary modification willpreventdepressurization oftheserviceairsystemduringmaintenance ofcompressor 95-01.Theintertiebetweenserviceairandinstrument airwillbeclosed.Thiswillprovideassurance ofnoflowofairtotheinstrument airsystemwhilemaintenance isbeingperformed onserviceaircompressor 95-01,topreventpotential oilcontamination ofinstrument air.SafetyEvaluation Summary:Theserviceairsystemdoesnothaveabackupairsupply.Iftheserviceairsystemdropsbelow20psigfortheplantpreaction firesprinkler zonesand50psigforthedrypipesystems,therespective alarmwillcomeinandthedrypipefiresprinkler zoneswillfill.Theportableaircompressor willpreventthisfromoccurring.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage9of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-013Mod.N1-93-018 FigureIX-224VDCSystemReplace24VDCBatteryChargersThismodification replacedtheexisting24VDCbatterychargerswithnewbatterychargingunitsofmoderndesign.Thismodification alsoprovidedadisconnect switchtoisolatethe48VDC,center-tapped, groundedneutralbatteryfromthebatterychargersanditsconnected loads.SafetyEvaluation Summary:Thefailureof24VDCbatterychargersisnotaninitiating eventforanydesignbasisaccident.

Thereplacement oftheexisting24VDCbatterychargerswithsimilarequipment isfunctionally aone-for-one equipment substitution withequivalent electrical characteristics andgreaterreliability.

Consequently, thiswillnotincreasetheprobability orconsequences ofanaccident.

Nonewmalfunction orfailuremodehasbeencreatedthatcouldcauseanewunanalyzed event.Systemreliability, systemcharacteristics, equipment qualifications, andcompliance withfireprotection andAppendixRrequirements areunchanged orareimprovedbythismodification.

Installation willnotresultinareduction oftheplantsafetymargin.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage10of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:94-019Rev.0L1IVlod.N1-92-005 10A-96,10A-114,10A-1184160VAC,600VACand125VDCSystemsTitleofChange:Description ofChange:ImproveElectrical Coordination Theemergency dieselgenerator 51-Vrelayanditsmiscoordination withdownstream protective deviceswasresolvedbydefeating thetrippingfunctionofthe51-Vrelaywhenanautomatic coresprayinjection signalisinitiated.

/Analarmcircuitwasaddedsothatactuation ofthe51-Vrelayannunciates inthecontrolroom.Acommonannunciator windowisusedfor51-Vrelayslocatedatpowerboards(PB)102and103;however,aseparatecomputerpointisprovidedforeach51-Vrelay.iForcircuitsassociated withPB16and17,electrical protective devicecoordination wasimprovedasfollows:1.ForPB16B/PB17B mainsupplybreakers, thelongtimesettingsforexistingelectromechanical tripdeviceswererevised.2.Forthefeederbreakertolightingvoltageregulator 16,theexistingelectromechanical tripdeviceswerereplacedwithnewelectromechanical

'ripdevices.3.InPB161B/PB171B, onemotorcasecircuitbreaker(MCCB)wasreplacedwithanewMCCB.4,InPB16B/PB17B, forthefeederbreakerstoPB167,theexistingelectromechanical tripdeviceswerereplacedwithnewelectromechanical tripdevices.5.InPB167,twoMCCBswerereplacedwithtwonewMCCBs.

SafetyEvaluation SummaryReportPage11of60SafetyEvaluation No.:Description ofChange:94-019(cont'd.)

(cont'd.)

6.InPB16B/PB17B, forthefeederbreakerstoPB1671A/PB1671C, thelongtimeandshorttime(PB17Bonly)settingsfortheexistingelectromechanical tripdeviceswererevised.7.InPB1671A/PB'1671C, oneexistingMCCBwasreplacedwithanewMCCB.Forcircuitsassociated withbatteryboards(BB)11and12,electrical protective devicecoordination wasimprovedasfollows:1.InBB11/12batterysupplybreakers, theexistingelectromechanical tripdeviceswerereplacedwithnewelectromechanical tripdevices.2.InBB11/12,replacedselectedexistingMCCBswithfusesandfuseblocks.3.Forfuseslocatedatordownstream ofBB11/BB12, replacedselectedexistingfuseswithnewfuses.Forsomecircuits, fuseblockreplacement wasrequired.

/SafetyEvaluation Summary:Thereplacement ofelectrical protective deviceswithsimilarequipment isschematically aone-for-one substitution ofcomponents withfunctionally equivalent characteristics.

Themodification oftheemergency dieselgenerator's outputcircuitbreaker's trippingschemewillimprovetheavailability ofemergency powerwhenitismostneededbyreducingthepossibility ofaspuriousbreakertrip.Thismodification willalsoimprovetheavailability ofsafety-related equipment whenanelectrical faultoccurs.Consequently, thiswillnotincreasetheprobability orconsequences ofanaccident.

Nonewmalfunction orfailuremodehasbeencreatedthatcouldcauseanewunanalyzed event.Systemreliability, systemcharacteristics, equipment qualifications, andcompliance withfireprotection andAppendixRrequirements areunchanged orareimprovedbythismodification.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage12of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-037Rev.1Mod.N1-89-079 N/AEmergency CoolingSystemNo.39Emergency CoolingAppendixJModification Thismodification cutoutandreplacedexistingvalves39-03and39-04andmodifiedvalves39-05and39-06withthereactorinthecoldshutdowncondition andsinglereactorpressureboundaryisolation viasafety-related manualgatevalves39-01and39-02./SafetyEvaluation Summary:Thismodification effectively providesvalvereplacement andmodification.

Thiswillresultinenhancedcontainment integrity andtestability anddoesnotincreasetheprobability ofoccurrence ortheconsequences ofanaccidentormalfunction tosafetypreviously evaluated intheFSAR.Thereplacement andmodification ofthesevalvestoenhancetheirabilitytoisolatethecontainment doesnotcreatethepossibility foranaccidentormalfunction ofadifferent typethananyevaluated intheFSAR.ItalsodoesnotreducethemarginofsafetyasdefinedinthebasisfortheTechnical Specifications.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

glSafetyEvaluation SummaryReportPage13of60SafetyEvaluation No.:Implementation DocumentNo.:94-038Rev.1SimpleDesignChangeSC1-0151-93 Mod.N1-93-023 UFSARAffectedPages:~System:TitleofChange:Description ofChange:N/AMainSteamSystem4'SIVBrakeInstallation andPoppetUpgradeThismodification eliminated repeatedleakratetestfailuresonmainsteamisolation valves(MSIV)toenhancetheirtestability.

Themodification consisted ofinstalling vendorrecommended MSIVpoppetretrofitpackages, andelectricbrakesandnewmotorswithextendedshaftsfortheoperators onthemotor-operated valves.SafetyEvaluation Summary:Thismodification effectively provideschangestotheMSIVstoeliminate leakratetestfailuresandenhancetheirtestability.

Thechangehasbeendesignedtominimizestemsusceptibility tocracking, provideimprovedanti-rotation mechanism, poppetselfaligningfeaturesandadditional hardfacing.

Additionally, installation ofthenewmotorswithbrakesontheinboardMSIVmotoroperators willpreventexcessive slidingofthevalvesduringclosuretesting.Thiswillresultinenhancedcontainment integrity andtestability.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage14of60SafetyEvaluation No.:Implementation DocumentNo.:94-039Rev.0Bc1Mod.N1-88-052, PhaseIIAUFSARAffectedPages:N/ASystem:TitleofChange:SpentFuelPoolSouthwest CornerRackModifications andAdditionofRackTopPlatformDescription ofChange:Thischangeprovidedarepairsolutiontofacilitate theinstallation ofthespentfuelstorageracklocatedinthesouthwest cornerofthefuelpoolpriortorefueling outageRFO13.Thisrackwasoneoftworemaining tobeinstalled fromthererackcampaignduring1984.Anewworkplatformwasinstalled ontopofthisrack.SafetyEvaluation.

Summary:Revision0ofthissafetyevaluation requiredthatpreviously discharged fuel(i.e.,fuelwithlowdecayheatgeneration) beusedwhenloadingthisspentfuelrackanddidnotallowfortheloadingofnewlydischarged fuelfromRFO13.Thisrestriction wasestablished byNMPCtoprovideadditional thermalmarginwiththeracktopplatforminstalled.

Revision1ofthissafetyevaluation removesthisrestriction (allowing RFO13newlydischarged fueltobeloadedintotherack)andinsteadrequiresthattheracktopplatformnotbeinstalled foraminimumperiodof180daysaftertherackhashadirradiated fueltransferred toit.The180daysisboundedbytheUnit1UFSARFigureX-7,DecayHeatGeneration vs.DaysAfterReactorShutdownCurve,whichindicates that110daysfollowing afullcoredischarge, decayheatgeneration isstabilized.

Sincetheadditionofthe180-daywaitingperiodpriortoracktopplatforminstallation willensurethattheintentoftheoriginalrestriction ismet(i.e.,theracktopplatformwillnotbeinstalled overfuelwithahighdecayheatgeneration rate),thischangeisboundedbytheoriginalevaluation andhasnoimpactonthespentfuelpoolheatremovalcapability.

Thismodification installsoneofthetworemaining Boraflexdesignhigh-density spentfuelstorageracksnecessary tofacilitate afullcoredischarge capability duringournextrefueling outage.Thismodification willhavenoimpactonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage15of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-051Mod.N1-91-021 10A-118ReactorInstrument ReplaceACUREXThismodification replacedtheACUREXAutodataTen/5dataloggers locatedininstrument andcontrolcabinets1S10and1S69,withnewsafety-related processing hardwarelocatedininstrument andcontrolcabinets1S16and1S17.Italsoreplacedtwoexistingrecorders withone.Loggingoftorustemperature individual RTDvalueshasbeentransferred totheprocesscomputer.

RPScircuitsto1S16and1S17havebeenchangedforconsistency ofpowersources.TheLo-Lo-Loinputstothefuelzoneindication wereremovedandthenormalization constant(kfactor)waseliminated fromthecompensated waterlevelcalculation.

SafetyEvaluation Summary:Nuclearsafetyisimprovedbythismodification.

TheRPScircuitsarebetterbalanced, thusimproving theirloadcharacteristics.

Theinstallation ofmorereliableelectronic hardwareimprovestheprobability thatthesystemwillbeavailable duringaneventwhereitisneeded,andtheinformation itprovideswillbemorereliable.

Theremovalofthenormalization constantwillprovidemorereliableindication throughout theentireinstrument range.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage16of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-052Mod.N1-87-042 VIII-11;10A-118PlantProcessComputerRISIsolatorReplacement Thismodification installed asafety-related state-of-the-art dataacquisition system(DAS)toprovidesignalisolation forAPRM/LPRM andfeedwater systeminputstotheplantprocesscomputer.

IThemodification replacedtheexistingRochester Instrument isolators usedtoisolatesafety-related signalsinputtotheplantprocesscomputer.

Theisolators werereplacedwithanInput/Output (I/O)computersystemandinterfaced withtheexistingplantprocesscomputersystemviaafiberopticcable.Thefiberopticcableisolatesallmaximumcrediblefaultsfromthesafety-related inputs.Thenew.I/Osystem,cabinets, I/Ocardsandcablesaresafetyrelatedandseismically qualified.

SafetyEvaluation Summary:TheDASloadswillbeappropriately isolatedandprotected topreventmalfunctions fromimpacting RPS.Also,thismodification willnotcauseachangetoanysysteminterface inawaythatwouldincreasethelikelihood ofanaccident.

Allsafety-related equipment andmaterials willbeprocuredandinstalled toapplicable regulatory andindustrycodesandstandards toensuresystemintegrity.

ThenewDASperformsthesamedesignfunctionasthecurrently installed isolators andisbeingprocuredandinstalled toequaltoorhigherdesignstandards.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage17of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:94-053Rev.051Mod.N1-94-002 FigureVill-4ReactorRecirculation GEMACRecirculation PumpControlModification Description ofChange:Thismodification removedfromservicefiveobsoleteandunreliable GEMACfunctiongenerators (FGs)usedinthereactorrecirculation pumpmotorgenerator setcontrolcircuits.

TheFGsaidinlinearizing therelationship betweenpumpspeedandreactorrecirculation pumpmotorgenerator setoutput.Theirsignalprocessing functionwillbereplacedbymodifying thecamsineachBaileypneumatic positioner.

Theproposedmodification isdefinedinGeneralElectric's proposalforthereactorrecirculation controlsystemenhancements.

SafetyEvaluation Summary:Theproposeddesignchangeisfunctionally equivalent tothepresentFG/Bailey actuatorconfiguration.

Thesystemresponseforeachreactorrecirculation controlloopwillremainlinear;theBaileypositioner, withtheAcharacterizer caminstalled, willperformtherequiredsignalprocessing insteadoftheFGs.Elimination oftheFGsfromthecontrolloopswillprovideadditional systemreliability andrelieffromcalibrating, refurbishing orprocuring replacement FGs.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage18of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:94-056Rev.0,1,53Mod.N1-88-153 TableVl-3aSh2Bc3;Vll-5,FigureVll-1;X-2,FigureX-1System:TitleofChange:ShutdownCoolingandCoreSpraySystemsContainment Isolation Valve(Appendix J)Modification

-ShutdownCoolingWaterSealDescription ofChange:Thismodification providedaqualified, 30-daywatersealfortheshutdowncoolingsystemisolation valvesutilizing anominalflowof22gpmfrorrleitherloop11or12ofthecorespraysystem.ThisallowsUnit1toachievecompliance with10CFR50AppendixJ,asrequiredbytheNRC,withoutthereplacement ofisolation valves38-01,38-13,and38-12.SafetyEvaluation Summary:/Thiswatersealwillresultinenhancedcontainment integrity.

Theadditionofcheckvalves38-165,166,167,168,169,170,171,and172providesisolation betweenthehigh-pressure reactorcoolant:system andthelow-pressure corespraysystem.Thesealwatersystemdesignuptothecheckvalvesmeetsthesamedesigncriteriaasthereactorcoolantsystemwithrespecttosafetyclassification, temperature, andpressure.

Leaktestingforthesecheckvalveswillbeinaccordance withSpecification 3.2.7.1.Therefore, adequateassurance isprovidedsuchthatthelow-pressure corespraysystemwillnotbedamagedbyoverpressurization andresultinpotential lossofintegrity withsubsequent releaseofradioactivity.

Theacceptability ofthedesignregarding singleactivefailureundercertainscenarios wasfoundacceptable basedonthePRAstudyandguidelines providedbyNUREG-0800 andGenericLetter88-20.Ithasbeendetermined thatnoexemption isneededfromtheAppendixJcompliance standpoint duringthisscenariobasedonguidanceprovidedbyNUREG-0800 andGenericLetter88-20.TheNRChasissuedaSafetyEvaluation Report(SER)ontheTechnical Specification Amendment toaddthenewwatersealcheckvalvestothePressureIsolation ValveTable3.2.7.1.ThisSERhasreviewedthenewdesignconfiguration forwater-sealing theshutdowncoolingisolation valvesusingthe SafetyEvaluation SummaryReportPage19of60SafetyEvaluation No.:SafetyEvaluation Summary:94-056Rev.0,1,&3(cont'd.)

(cont'd.)

corespraywaterinordertomeet10CFR50AppendixJcriteria, including thetwoscenarios underwhichthesinglefailurecriteriaisnotbeingmet.Nosignificant adverseimpactonshutdowncoolingandcorespraysystemperformance willresultasaconsequence ofthismodification.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage20of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:94-057Rev.1Mod.N1-91-009 FigureVll-3;10B-58;TableXV-4,Containment SprayReplaceOperators onContainment SprayIntertieValvesEPN80-40and80-45Description ofChange:Thismodification replacedthehandwheels onvalves80-40and80-45withpneumatic operators designedtofail-open.

Theremovalofthehandwheels givesoperators greaterflexibility whilethefail-open designensuresawatersealfor10CFR50AppendixJ.lSafetyEvaluation'Summary:

Thedesignfunctionofintertievalves80-40and80-45istobeinthenormallyopenposition, ensuringinterconnection oftheprimaryandsecondary loopsofcontainment sprayinordertoprovideawatersealinaccordance with10CFR50AppendixJ.Theadditionofpneumatic operators classified assafety-related active,anddesignedsothatonalossofmotivepowertheairwillbereleased, allowingthespringtoopenthevalve,willnotchangethedesignfunctionofthevalves.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage21of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-060SimpleDesignChangeSC1-0087-93 N/AServiceWaterEmergency ServiceWaterSupportsThissimpledesignchangeaddednewsupportstotheservicewaterinletandoutletpipingtotheReactorBuildingclosedloopcoolingheatexchangers.

Existingsupportswerereworkedandreplaced.

SafetyEvaluation Summary:Thenewsupportarrangement willbeinaccordance withtheoriginaldesignbasiscriteria.

AIIpipingstresswillbelessthantheallowable specified inB31.1-55andallsupportswillhaveallowable loadslessthanthemanufacturer's allowable orlessthanAISC8thEditionallowable.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage22of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-062Rev.05.1SimpleDesignChangeSC1-0059-94 III-23;10B-69N/AFoamRoomWallReplacement Thissimpledesignchangeremovedtheequipment supportsattachedtotheFoamRoomwestandsouthprecastconcreteexteriorwallpanelsandprovidednewsupports.

Thesewallpanelswereremovedandreplacedwithatemporary enclosure untilamasonrywallwasconstructed.

WeldswererepairedtoDCvalveboard¹11totheexistingembeddedfloorchannels.

An8-inchreinforced blockwallwithabrickveneerwasthenconstructed.

SafetyEvaluation Summary:Thedesignoftheequipment

supports, thetemporary enclosure, theblockwallbarrier,andthemasonrywallconsiders therequirements described intheUpdatedFinalSafetyAnalysisReport(UFSARj.Thedesignsatisfies thelicensing basisrequirements described intheUFSAR.Theweldrepairofthisvalveboardwillsatisfytherequirements oftheSQUGGenericImplementation Procedure.

Thischangewillhavenoimpactonthesafeoperation orshutdownoftheplant.Basedontheevaluation performed, itisconcluded thatremovaloftheprecastconcretepanelsandreplacement withareinforced concreteblockwalldoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage23of60SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:System:TitleofChange:94-068SimpleDesignChangeSC1-0062-94 10A-118120VACDistribution

'DCSC1-0062-94, Installation ofDataAcquisition SystemDescription:

Thismodification installed apermanent DataAcquisition System(DAS)toreplacetheindividual DAAScomputers previously inuseintheAuxiliary ControlRoom.Thescopeofthismodification waslimitedtotheinstallation ofallcomputerequipment associated withtheDAS,alongwithanasynchronous communications linktobeutilizedfordatatransfertoaNetworkFileService.Thisincludedthemountingofthecomputercabinet,andproviding apermanent powersupplyforthesystemMGset167computerpanelboard.

AnewcablewasroutedintheAuxiliary ControlRoombetweenMGset167computerpanelboard throughexistingracewayandnewlyinstalled raceway./SafetyEvaluation Summary:ThefunctionoftheDAS,withoutinputsfromprocesscontrolinstrumentation, isnonsafety relatedanddoesnot.haveanelectrical interface withanysafety-related systemsorcomponents; therefore, anelectrical failureofthesystemwillhavenoimpactonplantsafety.Inaddition, thesystemreceivesitspowerfromMGset167computerpanelboard, andsincetheloadsassociated withthispanelboard arenotrequiredforsafeplantshutdown, theDASisalsonotrequiredforplantshutdown.

Structurally, theinstallation detailsconformtotherequirements ofaseismicClassIarea.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage24of60SafetyEvaluation No.:Implementation DocumentNo.:USARAffectedPages:94-069SimpleDesignChangeSC1-0039-94 TablesVl-1,Vl-3bSh2;Vll-34,FigureVll-13System:TitleofChange:Hydrogen/Oxygen Monitoring H,/O~SampleLineReduction

==

Description:==

Thissafetyevaluation addresses thereduction inthenumberofsamplepointsforthehydrogen/oxygen monitoring system.Specifically, thissimpledesignchangeretiredonesampleline,streamAforH,/0,channel¹11andtwolines,streamsAandCforH,/0,channel¹12.Thiswasaccomplished bycuttingandweldingacaponthesamplelinesoutsidethedrywellbeforethefirstisolation valve.Theelectrical connections weredisconnected andtheisolation valvesandpipingwereretiredinplace.ControlRoomindication wasblankedanddeleted.Thisreducedthenumberofsamplepointsfromthedrywelltotwo,oneforeachchannel,andtwofromthetorus,oneforeachchannel.Sincethissafetyevaluation, isgenericwithrespecttothereduction inthenumberofsamplepointsforH~/0isolation valveclosure,asdirectedbyOP-9,uptonolessthanonesamplefromthedrywellandtorusforeachchannelofH,/Owasevaluated andjustified bythissafetyevaluation.

SafetyEvaluation Summary:TheH,/0,monitoring systemisclassified assafetyrelatedasaresultofRegulatory Guide1.97.However,thesystemisapassivemonitoring systemandisneithertheinitiator northecontributor toanyaccidents evaluated intheUFSAR.Thereduction ofthenumberofsamplepointswillnotincreasetheprobability ofoccurrence ofanyoftheseaccidents.

Basedontheresultsofnumerouscontainment mixingstudies,theresponsetothedesignbasiseventwillbeunchanged.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage25of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:94-070SimpleDesignChangeSC1-0070-94 10A-118ReactorRecirculation ControlSystem(RRCS)TitleofChange:Installation ofCable&Terminations fortheDataAcquisition System(DAS)Description ofChange:Thenewdataacquisition system(DAS)consistsofaPC,videomonitor,printerandanenclosure whichwillbelocatedintheAuxiliary ControlRoom.ThenewDASwillprovideinformation fortrendingandtroubleshooting:that willincreaseboththereliability andcapacityfactoratUnit1.Thissimpledesignchangeelectrically connected thereactorrecirculation controlsystem(RRCS)totheDAS.Inaddition, severalcableswererunfromvariouscabinetstotheDASinpreparation forotherinstallations.

Thesecables'were storedintheexistingcabletraysuntilfinalinstallation.

Thescopeofthischangeinvolvedroutingcablethroughout theAuxiliary ControlRoomandterminating cablesattheDASandtheRRCS.Theinstallation requiredroutingcablethroughexistingcabletraysandterminating theseconductors atvariouspointsinthelogic.Thecableismultiple-conductor, twisted,shieldedpair016.Theshieldsofeachpairweregroundedtopreventextraneous noisefromenteringtheDAS.Allterminations weremadeonterminalblockswithringtongueterminals.

Asafety-relatedsignalisolatorwasinstalled toisolatethesafety-related reactorrecirculation totalflowsystemfromthenonsafety-related DAS.SafetyEvaluation Summary:ThelogicoftheRRCSwillbeunchanged bythismodification.

Thecrediblefailuresthatthischangecanproduceareenveloped inSectionXVoftheUpdatedFinalSafetyAnalysisReport.Crediblefailuresincludethelossorsuddenreduction ofthecontrolsignalinoneormorereactorrecirculation loopsduetoashortedleadinthecontrolcircuit.TheriskofashortisminimalduetotheDASbeingapassivesystemthatwillmonitorsystemparameters only.Thecontrolsystemwilloperateasdesignedwithnochangesinresponseorcontrol.

SafetyEvaluation SummaryReportPage26of60SafetyEvaluation No.:SafetyEvaluation Summary:94-070(cont'd.)

(cont'd.)

Inaddition, theinstallation ofthesafety-related isolation amplifier inthetotalreactorrecirculation flowcircuitwillhavenoeffectonthecircuit.Theinputresistance oftheisolatorisgreatenoughsothatitwillnotadversely affectflowinputtotheaveragepowerrangemonitors.

TheClass1Eisolatorisdesignedtoadequately isolatethesafety-related signalfromanyfaultsortransients causedbythenonsafety-related DAS.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage27of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:94-072Rev.08c1Mod.N1-90-041 TableVl-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:CoreSpraySystemCoreSprayMinimumFlowRecirculation Lines/Throttling Description ofChange:Thismodification installed separateminimumflowrecirculation linesforeachcore/spraypumpset.Inaddition, theinboardisolation valveswerethrottled toslowlyinjectcoresprayduringanticipated transient withoutscramandsmallbreakloss-of-coolant accidentevents.Toaccomplish this,EOPjumperswereinstalled intheControlRoomwhichinhibitstheinitiation andinterlock signalsfortheinboard,outboardandtestreturnvalves.Thetestreturnvalvesarerequiredtobeopenedtosupportextendedrecirculation flowandcorespraypumpsetoperation fortheshutdowncoolingwaterseal.SafetyEvaluation Summary:Theanalysissectionclearlydemonstrates thattheapplicable designandlicensing criteriahavebeensatisfied.

Thisincludesbothnormaldesignbasisfunctions, manualEOP-directed operation, andshutdowncoolingsystemwatersealrequirements.

Theimpactofseparateminimumflowrecirculation linesandinboardvalvethrottling onrequiredcoresprayinjection flowshasbeencalculated.

Basedonthecalculation, thecorespraysystemprovidesadequateflowtosatisfy10CFR50.46.

Redundancy, separation, AppendixR,seismicqualification andenvironmental qualification havebeenincorporated intothedesignandconfirmed byanalysis.

Thischangedoesnotincreasetheprobability, consequences orcreateadifferent typeofaccidentormalfunction ofequipment important tosafety.Themarginofsafetyisnotdecreased.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage28of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:-System:94-074DER1-94-0224 VI-32Containment Spray,CoreSpray,Containment SprayRawWater,NitrogenSupplySystem¹12,NitrogenSupplySystem¹11TitleofChange:Licensing DocumentChangeRequest1-93-IST-006 totheNMP1ISTProgramPlanandLDCR1-94-UFS-056 totheUFSARDescription ofChange:I/Thissafetyevaluation evaluated additions toanddeletions fromtheIn-Service Testing(IST)ProgramPlan,basedontherecentdevelopment and/orrevisions ofSafetyClassdeterminations whichnecessitate changestotestingrequirements.

SafetyEvaluation Summary://Ithasbeendetermined thatoverpressure ofthecontainment duetomalfunction ofpressurecontrolvalves(PCV)inthenitrogensupplysystemisnotadesignbasissafetyconcernasitwouldrequirethefailureof1)aPCVand2)afailureopenofanisolation valve.Thiswouldconstitute twoactivefailuresofsafety-related components andisbeyondthedesignbasisoftheplant.Therefore, thereliefvalvesdonotneedtobesafety-related activeandinclusion ofthereliefvalvesintheprogramisnotrequired.

SectionVI-F.3oftheUpdatedFinalSafetyAnalysisReport,Containment Ventilation System,containslanguagewhichisvagueandrequiresclarification.

Thissectionstatesthatthereliefvalvesandoverpressure regulators inthenitrogenmakeupsupplyline"weretestedpriortoinitialstartupandperiodically thereafter foroperability andsetpoint."

Notethatthisstatement isinthepasttense(itdoesnotcommittocontinuous testing),

whileallothertestingdescribed inSectionVl-Fandreferences toISTforothersystemsinSectionVllareinthepresenttense.Thestatement istoberevisedpriortodeletingthereliefvalvesfromtheISTProgramPlan.Further,thePCVsarenottestedperiodically atthistime;PCVsareexemptfromtestinginaccordance withASMEXIIWV-1200.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage29of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:94-075Mod.N1-93-013 TableIX-1Sh1-3;X-18;10A-115Containment Atmosphere Monitoring System,H~/0,AnalyzerTitleofChange:Description ofChange:ReplaceH,/0,Monitoring SystemThismodification replacedthehydrogen/oxygen (H,/O~)monitoring system,cabinets, andanalyzers.

TheprevioussystemwasproducedbyBeckmaninstruments andinstalled priortoRegulatory Guide1.97andNUREG-0737 requirements.

Duetoageandthereclassification assafetyrelated,themaintenance hadbecomeextensive.

AnewTeledyneAnalytical Instruments H,/0,monitoring systemwasinstalled inplaceoftheBeckman.Thecabinetsaremountedinthesamelocation, withthecontrolcabinetmountedonthecolumnacrosstheaisle.TheTeledynesystemwasprocuredsafetyrelatedandisfullyseismically andenvironmentally qualified.

/SafetyEvaluation Summary:Theanalysisclearlydemonstrates compliance withallapplicable criteriaincluding safetyclassification, seismicqualification, environmental qualification, powerrequirements andseparation.

Calculations havebeenperformed forthetransportation time,responsetimeandaccuracyandassurecompliance withdesignbasisfunctions andlicensing commitments.

Specifically, therequirements of10CFR50AppendixA,General,DesignCriterion 41,AppendixB,QualityAssurance requirements, IEEE-344, Regulatory Guide1.97,NUREG-0737, FireProtection programandISTprogramhavebeensatisfied.

Thischangedoesnotincreasetheprobability, consequences orcreateadifferent typeofaccidentormalfunction ofequipment important tosafety.Themarginofsafetyisnotdecreased.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage30of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:94-079DER1-93-0921 VI-21,VI-26,TableVl-3bSh4Traversing In-coreProbe(TIP)TIPSystemContainment Isolation

-LDCRThissafetyevaluation analyzedamethodtomoreaccurately represent theexisting'esignofTIPsystemcontainment isolation featuresintheUnit1UFSAR.Valveconfiguration, isolation logicandvalvemotivepowerareaddressed.

WordingwasaddedtotheUFSARtodescribetheTIPballandshearvalvesandhowtheballvalvesareprevented fromreopening afteranisolation signalclears.ISafetyEvaluation Summary:Applicable criteriahavebeenreviewedtoverifythattheTIPcontainment isolation doescomplywithplantlicensing anddesignbasisrequirements.

TheabilityoftheTIPsystemtoremainisolatedfollowing acontainment isolation isassuredbysystemdesign,normaloperating configuration andprocedural controls.

IntheunlikelyeventtheTIPguidetubesfailtoisolate,calculated accidentdosesarenotsignificantly impactedandarewellwithin10CFR100limits.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion..

SafetyEvaluation SummaryReportPage31of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:94-080Rev.0&1Mod.N1-94-003 IV-27,IV-28,IV-29,FigureIV-9;XVI-5,XVI-12,XVI-21,XVI-122,TablesXVI-2Sh152,XVI-9a,FiguresXVI-12a,XVI-12bSystem:TitleofChange:Description ofChange:ReactorVesselReactorCoreShroudRepairTheshroudmodification wasdesignedtoprovideanalternative loadpathforallType304stainless steelcircumferential welds(weldsH1-H7).Themodification ensuresthestructural integrity ofthecoreshroudbyreplacing thefunctionofcoreshroudweldsH1throughH7withfourstabilizer assemblies.

'Thestabilizer assemblies arecomprised offourtie-rodassemblies andfour'oreplatewedges.SafetyEvaluation Summary:Thisevaluation hasinvestigated theinstallation ofcoreshroudstabilizer's atUnit1.Theevaluation oftheshroudmodification hardwareincludeddesign,code,materials, fabrication, structural, systems,installation andinspection considerations.

Theevaluation concluded thattheproposedmodification isinaccordance withtheBWRVIPCoreShroudRepairDesignCriteriaandtheNRCSafetyEvaluation Report(SER)ontheBWRVIPShroudRepairCriteria.

TheUnit1repairmodification ofthecoreshroudistobeperformed asanalternative toASMESectionXI,aspermitted by10CFR50.55a(a)(3).

Consequently, NRCapprovalofthisrepairapproachisrequired.

Thissafetyevaluation documents theNIVIPCreviewoftherepairinaccordance withtheprovisions of10CFR50.59.

Aseparatesafetyevaluation (95-013)wasperfoimed toevaluatetheacceptability oftheinstallation ofthecoreshroudstabilizer assemblies priortoNRCapproval.

Theevaluation concluded thattherearenounreviewed safetyquestions associated withinstalling therepairpriortoNRCapproval, providedthereactorremainsinthecoldshutdowncondition orthehotshutdowncondition forthe SafetyEvaluation SummaryReportPage32of60SafetyEvaluation No.:94-080Rev.0&1(cont'd.)

SafetyEvaluation Summary:(cont'd.)

performance ofnoncritical hydrotestingabove212'Fand/ortheperformance ofCRDscramtimetestinguntilNRCapprovaloftherepairisobtained.

Additionally, SE95-007wasperformed toreviewpotential safetyimpactsoftheinstallation activities associated withtherepair.Theevaluation concluded thattherearenounreviewed safetyquestions relativetotherepairinstallation activities.

TheNRCissuedaSER,datedMarch31,1995,entitled"SafetyEvaluation oftheRepairProposalfortheNMP1CoreShroud."TheNRCSERhasreviewedalloftherepairdesignaspectsandhasconcluded therepairdesignisacceptable.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage33of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:95-002Rev.0L1SimpleDesignChangeSC1-0067-94 FigureVll-1CoreSprayCoreSprayIVPressureBindingReliefThismodification addedapressurebindingreliefpathtocoresprayvalves40-01,40-09,40-10,40-11,andtestreturnvalves40-05and40-06,toensurethevalveswillopenunderallpostulated conditions.

Forthecoresprayvalves,aninstrument linewasconnected totheexisting1/4-inchtapforthelanternglandstuffingboxandconnected tothereactorsidedrainvalves.Thedrainvalveswerelockedopentoprovidethereliefpathtothereactorsideprocesspiping.Thevalvepackingwasmodifiedtoallowpressureinthebonnettorelievethroughthe1/4-inchtap.Forthetestreturnvalves,asmallholewasdrilledintothediskonthereactorsideofthevalvetoprovidethereliefpath.Alsoincludedinthismodification, thedrainvalveconfiguration ofvalve40-05wasrevisedtoprovidetwovalvesandathreadedcap.Thischangewasrequiredtoenabletheattachment ofDPmeasurement equipment acrossthevalveduringGenericLetter(GLI89-10dynamicflowtesting.Thesedrainvalvesarelockedclosedduringnormalplantoperation.

SafetyEvaluation Summary:Thecorespraysystemisrequiredtooperatetopreventoverheating ofthefuelfollowing apostulated loss-of-coolant accident.

Theinsidevalvesarerequiredtoopenwhenreactorpressureis365psigorlessandthetestreturnvalveswillberequiredtoopentofacilitate throttling ofthecoresprayflowtothereactortomaintainwaterlevel.Theadditionofapressurereliefpathtothesevalveswillpreventthepotential forpressurelockingintheredundant coresprayloops,andtheadditionofdoubleisolation drainvalvestoonevalvewillenableGL89-10dynamictesting.Thismodification willhavenoeffectonaccidents ormalfunctions previously evaluated intheUFSAR.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage34of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-003SimpleDesignChangeSC1-0089-94 X-35,X-36,FigureX-9Instrument AirSystemInstrument AirUpgrade-Valve94-91LogicChangeDescription ofChange:Thissimpledesignchangeaddedapressureswitchcontactinthecontrolcircuitofair-operated valve94-91sothatiflowpressureissenseddownstream ofthe'alve,thevalvewillclose.Thisenhancesavailability ofthesafety-related portionoftheinstrument airsystemshouldthenonsafety-related pipingdownstream ofvalve94-91fail.Additionally, apressureindicator wasaddedtomonitorthesameprocesspressureasthepressureswitch.SafetyEvaluation Summary:Theapplicable criteriafromtheUFSAR,ChapterX,XVand10A,havebeensatisfied bythissimpledesignchange.Singlefailurecriteriahasbeenaddressed andsafetyclassdetermination No.93-084evaluated forimpact.Thecomponents addedarenonsafety relatedandnotrequiredtoberedundant.

Theaddedcableisinconduitand,therefore, thefireloadinthisareaisnotincreased.

Thevalvewillperformitssafety-related functiontofailclose.Theavailability oftheinstrument airsystemisenhancedbythischange.Thischangedoesnotincreasetheprobability, consequences orcreateadifferent typeofaccidentormalfunction ofequipment important tosafety.Themarginofsafetyisnotdecreased.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage35of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:95-007Mod.N1-94-003 N/ARXVECoreShroudRepairInstallation TheNRCissuedGenericLetter94-03duetoobservedcrackinginthecoreshroudsofseveralBWRs.Thisgenericletterrequiresinspection oftheshroudand/orrepair,ifnecessary.

NMPCwilleitherinspectandpossiblyperformarepairiftheweldinspection necessitates itorperformapreemptive repairoftheshroudduringRFO13.TheUnit1reactorcoreshroudrepairisdesignedtostructurally replaceshroudweldsH1throughH8.Theinstallation oftheentirerepairinvolveselectrical discharge machining (EDM)oftheshroudsupportconeandshrouditself,whichwillgenerateveryfineparticles calledswarf,theattachment ofatrolley/buggy totheRefuelBridge,theadditionofanauxiliary bridgeonReactorBuildingEl.340,andotherspecialconsiderations fortheshroudrepair.,This safetyevaluation (SE)coverstheshroudrepairinstallation activities andwillsupplement SE94-080,"CoreShroudRepair."SafetyEvaluation Summary:Theinstallation ofthecoreshroudrepairrequiresthatspecialequipment andprocesses beusedtominimizethein-vessel debrisgeneration andprovideminimalimpactonotherworkbeingperformed onReactorBuildingEl.340.Thedesignandfunctionofthespentfuelpoolcooling(SFP)andthereactorwatercleanupsystemsarenotbeingalteredduringtherepairinstallation.

Bothsystemshavebeenevaluated andwillcontinuetoperformasdesignedduringandaftertherepairinstallation.

TheSFPsystemisdesignedtoremoveparticles assmallas1micron.Theswarfparticles fromtheEDMprocesswhichentertheskimmersfromthetankoverflowwillbealmostentirelyremovedinthefilters.Theremaining particles willbelessthan1microninsizeandwillnotaffectthefunctionoftheSFPsystem.

SafetyEvaluation SummaryReportPage36of60SafetyEvaluation No.:SafetyEvaluation Summary:95-007(cont'd.)

(cont'd.)

Thecleanupsystemisdesignedtomaintainhighreactorwaterpuritybycontinuously purifying aportionoftherecirculation flow.Thedebrissizeexpectedfromtheshroudrepairis1to50micron;therefore, anyparticles thatthecleanupsystemcannotremoveareassumedtobesmallenoughthataparticleofthatsize.couldcurrently beinthesystemandisnotaconcern.Thevolumeofparticles expectedtoremaininthevesselandSFPsystemfollowing therepair,afterfiltering, isconsidered insignificant whencomparedtothetotalvolumeofwaterinthevessel.Theauxiliary bridgeandrefuelbridgebuggywillnotbeusedformovingfuel.The-auxiliary bridgehasbeenanalyzedandisacceptable foruseoverirradiated fuel.Therefuelbridgebuggywillnotbemovedoverfuelunlessitistiedofftotherefuelbridge.Therequirements ofNUREG-0612 willbemetthroughtheuseofN1-MMP-GEN-914, whichisreferenced intheGEshroudrepairprocedures.

Thetoolingfor"heavyloads"hasbeendesignedandwillbeusedinaccordance withNUREG-061 2.Basedontheevaluation performed, itisconcluded thatthespecialequipment andprocesses requiredfortheinstallation ofthecoreshroudrepairdonotconstitute anunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage37of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:95-009SimpleDesignChangeSC1-0102-93 TableVl-3aSh1&3;VIII-1,Vill-2,Vill-9,VIII-32,FiguresVill-1,Vill-2;XV-48System:MainSteam(MSS),ReactorProtection (RPS),Offgas(OFG),Postaccident

Sampling, Emergency CoolingTitleofChange:RemovalofMainSteamLineHighRadiation Scram/MSIV Isolation SignaltoImplement Technical Specification Amendment 149Description ofChange:JThissafetyevaluation analyzedplantchangesassociated withTechnical Specification Amendment (TSA)149thatarenotexplicitly described intheamendment and,therefore, arenotcoveredbytheNRC'ssafetyevaluation fortheamendment.

TSA149deletedtheautomatic reactorscramandmainsteamlineisolation functions ofthemainsteamlineradiation monitors.

TSA149onlystatesthatthemainsteamisolation valves(MSIV)isolation functionwillberemoved;however,otherreactorvesselisolation valvesarecoupledwiththeMSIVslogiccircuits.

Therefore, whentheMSIVisolation signalisremoved,theseothervalveswillalsonotisolateonhighradiation.

SafetyEvaluation Summary:Thissafetyevaluation demonstrates thatallnecessary safeguards havebeentakentoidentifyandaddressalllicensing anddesignbasisrequirements forthedesignandoperation ofthesystemsimpactedbythisdesignchange,andforinstallation ofthedesignchange.BasedonreviewofNEDO31400A,varioussystemdesignsandsystemfailurecriteria, thechangewillnotresultinaradiological releasebeyondexistinglimitsnoraffectoperation ofsafety-related equipment.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvoiveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage38of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:95-010DER1-95-0133 X-39FuelSpentFuelStorageThissafetyevaluation evaluated aclarification changetotheUFSARwherea"maximumfuelenrichment" of3.75percentisspecified fortheboraflexracks.Ithasbeenestablished thatthisvalueisthepeakdesignlatticeenrichment (nominalvalue).SafetyEvaluation Summary:1Storingfuelwithapeakdesignlatticeenrichment of3.75percent(nominalvalue)intheboraflexracksisconsistent withmaintaining theK-effective below0.95.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage39of60SafetyEvaluation No.:Implementation DocumentNo.:95-011NEDE-24011-P-A-10 NEDE-2401 1-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:Description ofChange:VariousOperation ofNMP1Reload13/Cycle12Thischangeconsisted oftheadditionofnewfuelbundlesandtheestablishment ofanewcoreloadingpatternforReload13/Cycle12operation ofUnit1.TwoHundred(200)newfuelbundlesoftheGE11designwereloaded.All164ofthePSxSRbundlesfromCycle10,and36oftheGESx8EBbundlesfromCycle11,weredischarged tothespentfuelpool.Variousevaluations andanalyseswereperformed toestablish appropriate operating limitsforthe.reloadcore.Thesecycle-specific limitsweredocumented intheCoreOperating LimitsReport.SafetyEvaluation Summary:Thereloadanalysesandevaluations areperformed basedontheGeneralElectricStandardApplication forReactorFuel,NEDE-24011-P-A-10 andNEDE-24011-P-A-10-US(GESTARII).Thisdocumentdescribes thefuellicensing acceptance criteria; thefuelthermal-mechanical, nuclear,andthermal-hydraulic analysesbases;andthesafetyanalysismethodology.

ForReload13,theevaluations includedtransients andaccidents likelytolimitoperation becauseofminimumcriticalpowerratioconsiderations; overpressurization events;loss-of-coolant accident; andstability analysis.

Appropriate consideration ofequipment-out-of-servicewasincluded.

Limitsonplantoperation wereestablished toassurethatapplicable fuelandreactorcoolantsystemsafetylimitsarenotexceeded.

Basedontheevaluation performed, itisconcluded thatUnit1canbesafelyoperatedduringReload13/Cycle12,andthatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage40of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-013Rev.061Mod.N1-94-003 N/AReactorVesselReactorCoreShroudRepairInstallation PriortoNRCApprovalofAdequacyUnder10CFR50.55a(a)

(3)Description ofChange:Thismodification installed thecoreshroudrepaircomponents priortoNRCapprovaloftheadequacyofthesecomponents asalternative repairsforthecoreshroudhorizontal weldsH1throughH8./SafetyEvaluation Summary:Theseshroudrepaircomponents arenotrequiredtoperformanydesignbasisfunctionduringthetimeperiodrequiredforNRCreviewoftheadequacyoftheproposedmodification.

TheexistingshroudH1throughH8weldstructural integrity whichexistedpriortoplantshutdownismaintained asdiscussed intheanalysis.

Therestriction thatthereactorremainincoldshutdownexceptforentryintothehotshutdowncondition forperformance oftheportionofthenoncritical hydrotest and/orCRDscramtimetestingabove212'F,inaccordance withTechnical Specification 3.2.2.e,untilNRCapprovalisobtainedguarantees thatUnit1willremainincompliance withtheNRCSafetyEvaluation ReportdatedJanuary13,1995.Thisrestriction plustherestriction tomaintaintotalflowlessthanratedmassflow(67.5Mlb/hr)duringreactornoncritical hydrotesting ensuresthatnosignificant thermalorpressureloadsarecarriedbytheshroudortie-rodassemblies.

Theanalysishasdemonstrated thatthetie-rodpreloaddoesnotincreasethestresssignificantly inanyoftheshroudweldssuchthattheprobability offailureisincreased.

Theanalysishasdemonstrated thatthebypassleakageislessthan1'/oatratedrecirculation flowconditions whichboundsthecoldandhotshutdownrequiredcorecoolingconditions.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage41of60SafetyEvaluation No.:Implementation DocumentNo.:95-014Rev.1Temporary Mod.95-009Temporary Mod.95-012UFSARAffectedPages:System:TitleofChange:N/AReactorCoreSprayRemovalofCoreSprayMinimumFlowReliefValvesDescription ofChange:Thesetemporary modifications removedtheminimumflowreliefvalvesforeachofthecorespraypumpsetsandreplacedthemwithblindflanges.Flangeswereinstalled attheexistingendconnections foreachreliefvalve./Thisdisabledtheminimumflowcapability foreachofthepumpsetsofthecorespraysystem.Thischangewasrequiredtosupportreloadactivities whiletheCoreSprayMinimumFlowModification, N1-90-041, wasbeingre-evaluated forproblemsassociated withthereliefvalves.Thissafetyevaluation isonlyapplicable while/thereactorisdepressurized.

SafetyEvaluation Summary:Removaloftheminimumflowreliefvalvesandreplacing themwithblankflangesforrefuel/cold shutdownoperation doesnotaffecttheabilityofthecorespraysystemtoperformitsfunctiontocoolthecore.Thischangedoesnotadversely affectthecorespraysystemperformance inamannerwhichwouldincreasetheprobability ofoccurrence ofanaccidentpreviously evaluated inthesafetyanalysisreport.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage42of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:95-015N/AN/ASystem:N/ATitleofChange:CO,PelletDecontamination Facilityat,OffGasBuilding-261Description ofChange:Operation oftheCO,(dryice)pelletcleaningfacilityisfordecontamination ofmiscellaneous toolsandequipment post-RFO-13.

TheactualCO,pelletblasterislocatedinsideofamodulardecontamination building(aportablekellybuilding) locatedintheOffgasBuildingonelevation 261.ACO,storagetankandcompressor arelocatedoutdoorsattheeastsideoftheOffgasBuilding.

\SafetyEvaluation Summary:Theuseandoperation oftheCO,cleaningfacilityatOffgasBuildingelevation 261withaCO,storagetankandcompressor immediately adjacenttotheeastsideoftheUnit1OffgasBuildingdoesnotcreatethepossibility ofanaccidentormalfunction notpreviously

analyzed, increasetheprobability ofanaccidentormalfunction alreadyanalyzed, reducethemarginofsafetyinanyTechnical Specifications, orincreasetheconsequences ofanyaccidentormalfunction alreadyanalyzed.

Inaddition, theproposedcontrolsandoperation ofthefacilitywillnotcreateanewradioactive effluentpathwayorcreateanunmonitored releaseofradioactivity.

Basedontheevaluation performed, itisconcluded thatthetemporary useoftheCO~cleaningfacilitydoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage43of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:95-016LDCRNo.1-95-UFS-019 X-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/ADeletionofFireProtection ReportRequirements intheFireHazardsAnalysisDescription ofChange:/Thischangedeletedtherequirement forsendingfireprotection programreportstotheNRCforinoperable fireprotection systemsandcomponents asrequiredbytheFireHazardsAnalysis.

SafetyEvaluation Summary:TheFireHazardsAnalysiscontainsreporting requirements forinoperable fireprotection systemsandcomponents.

Thesereportsaremadeuponmeetingspecificcriteriadelineated withintheFireHazardsAnalysis.

In1992,whenLicenseAmendment 132wasissuedbytheNRC,anadditional Technical Specification (6.9.2)wasaddedtorequirethatfireprotection programnoncompliances bereviewedundertheprovisions of10CFR50.72 and10CFR50.73.

Reportsarenowsubmitted undertheseprovisions, asdetermined throughtheplantprocedures governing Deviation/Event Reporting.

Thepreparation andsubmittal offireprotection reportsinadditiontothoserequiredunderTechnical Specification 6.9.2isnolongerrequiredforlicensees whohaveremovedthefireprotection programelementsfromtheTechnical Specifications pertheguidanceofNRCGenericLetters86-10and88-12.Unit1completed thisprocessthroughthegrantingofLicenseAmendment 132.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage44of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:95-017Dwg.B-69007-C VI-2158;201.2LT58-05Isolation Capabilities LT58-05instrument linesdonotcontaintwomanualvalves.Instead,isolation isprovidedbyasinglemanualvalveanddiaphragm sealassemblies.

SafetyEvaluation Summary:/Thediaphragm sealassemblyexceedsdesignratingsofthetorusundernormalandaccidentconditions.

Thesealassemblyeffectively isolatesthetransmitter fromprocessfluid.Thesealassemblyislocatedclosetothetorusroompenetration andthefirstmanualvalve.Thediaphragm sealassemblyisanAppendixJtestableconfiguration.

Thevalve/seal assemblycombination providessufficient isolation capability tomitigatepotential instrument lineleakage.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage45of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-018Gale.S7-RX340-W01 XVI-70,TableXVI-31Sh1N/AUFSARChangesforPressureReliefPanelDiscrepancies Description ofChange:UFSARSectionsIII.A.1.2 andVI.C.1.2statedthatthepressurereliefpanelsintheTurbineandReactorBuildings blowoutat45psf.UFSARTableXVI-31,pageXVI-185,andthediscussion onpa'geXVI-187,statedthatthepressurereliefpanelsblowoutat40psfinboththeReactorandTurbineBuildings.

Calculation S7-RX340-W01 andDCRN1-95001LG329, documenting existingas-builtconditions forfieldworkdonetothereliefpanelsinRefueling Outage13,indicatethatthecorrectblowoutpressureis45psf.ThischangetotheUFSARcorrected discrepancies relatingtotheblowoutpressures forthepressurereliefpanelsintheReactorandTurbineBuildings.

SafetyEvaluation Summary:Theabove-referenced documents showthatthecorrectblowoutpressureis45psfforthepressurereliefpanelsinbothbuildings.

Thischangecorrectsstatedpressures of40psfto45psfontheUFSARaffectedpages.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage46of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-019Gale.S15-72-F009 X-25,FigureX-6ServiceWaterRevisiontoNMP1FSARChapterX,PagesX-31,X-32,andX-33Description ofChange:Thefollowing changesweremadetoUFSARChapterXtoreconcile adiscrepancy betweentextandfigurepertaining tothepositionoftheblockingvalvesonthesupplyheader.1.TextinSectionX-2.0waschangedfrom:"Duringnormaloperation oftheturbinebuildingsystemonlyoneservicewatersupplyisused;theotherlineisvalvedoffasaspare.However,onthereactorbuildingsystembothservicewatersupplylinesareengagedatalltimesformaximumreliability."

to:"Duringnormaloperation boththesupplyheadersontheRBCLCsideandTBCLCsideareengagedbykeepingtheblockingvalvesopen;however,toperformmaintenance orotherplantactivities oneoftheRBCLCsideandoneoftheTBCLCsideblockingvalvescanbesecured."

2.FigureX-6wasrevisedtoshowbothsetsofsupplyheaderblockingvalvestobeopeninthenormaloperating configuration.

SafetyEvaluation Summary:Theservicewatersystemcanadequately meetitsflowdemandinaconfiguration wherebothofthevalvesontheRBCLCsideandTBCLCsideareopenorinaconfiguration whereoneofthetwovalvesontheRBCLCandTBCLCsidearesecured.Thissafetyevaluation analyzesbothsetsofblockingvalvestobeopenundernormaloperating condition.

Thiswillreducepotential cloggingandcorrosion oftheportionsofthesupplyheaderwherestagnantflowconditions wouldoccuriftheblockingvalvewassecured.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage47of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-020DER1-94-0354 lll-7,III-23,III-24N/ATurbineandAdministration BuildingDescription ChangesDescription ofChange:Thissafetyevaluation evaluated changesintheconfiguration oftheAdministration andTurbineBuildings asfollows:1.Thenewpersonnel accesscontrolisatel.248'-0"oftheAdministration

/Building.

2.TheAdministration BuildingbasementhasanentrancetotheTurbineBuilding.

3.jThepersonnel lockerroomwasaddedtotheAdministration Buildinggroundfloordescription intheUFSAR.Adescription oftheofficeforshopsandstoreswasdeleted,aswasthereference tothemonitorroom,thepersonnel decontamination room,laundryroom,andlunchrooms.4.Thereception areaandthelocationofthelunchroom,lockerrooms,radiation protection offices,andaccesstotheradiologically-controlled area(RCA)weredeletedfromtheUFSAR.SafetyEvaluation Summary:Changingthepersonnel RCAaccess,shopandradiation protection office,lunchrooms,laundryroom,anddeletingthereception areadoesnotcreatethepossibility ofaccidentormalfunction notpreviously

analyzed, affectplantequipment orsystems,orreducethemarginofsafetyinanyTechnical Specification.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage48of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:95-021Procedures GAP-POL-01, NSAS-POL-01 X-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-01 BcNSAS-POL-01 toEstablish NuclearBusinessManagement Organization Description ofChange:Procedures GAP-POL-01 andNSAS-POL-01 havebeenrevised'to reorganize thefunctions ofFinance,ComputerSoftwareDevelopment, BusinessPlanning, andNuclearProcurem'ent underaneworganization titled,"NuclearBusinessManagement,"

reporting totheVicePresident NuclearGeneration.

SafetyEvaluation Summary:Theseprocedure changesestablish departmental responsibilities andlinesofauthority, responsibility, andcommunication fortheNuclearBusinessManagement organization.

Theproposedorganization structure satisfies thecriteriaofSRP13.1.1andconformswiththerequirements ofSection6.1.2ofthePlantTechnical Specifications.

Theproposedchangesdonotimpactaccidentormalfunction initiation orconsequences.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage49of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-022Procedures GAP-POL-01, NSAS-POL-01 XIII-3,XIII-7N/AReorganization; ChangestoGAP-POL-01

&NSAS-POL-01 toTransferManagement andOperational Responsibility fortheSiteSewageTreatment FacilityfromTechnical Services(Environmental) toUnit1Chemistry Description ofChange:!Procedures GAP-POL-01 andNSAS-POL-01 havebeenrevisedtotransfermanagement and'operational responsibility fortheSiteSewageTreatment FacilityfromtheTechnical ServicesBranch(Environmental) oftheNuclearSafetyAssessment

&SupportDepartment totheUnit1Chemistry BranchofNuclearGeneration.

SafetyEvaluation Summary:Theseprocedure changesestablish departmental responsibilities andlinesofauthority, responsibility, andcommunication formanagement andoperation oftheSiteSewageTreatment Facility.

Theproposedorganizational structure satisfies thecriteriaofSRP13.1.1andconformswiththerequirements ofSection6.1.2ofthePlantTechnical Specifications.

Theproposedchangesdonotimpactaccidentormalfunction initiation orconsequences.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage50of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-023Procedure NSAS-POL-01 Xlll-3,FigureXIII-4N/AReorganization; ChangestoNSAS-POL-01 toTransferProcedure ProgramCoordination fromTechnical ServicestoQualityAssurance Description ofChange:Procedure NSAS-POL-01 hasbeenrevisedtodeletetheresponsibility assignedtotheManagerTechnical Servicestomanageimplementation of.theprocedure programincluding publication.

The"managing" functionassignedtotheManagerTechnical Serviceswastoprovideoverallcoordination oftheprocedure program.Responsibility foroverallcoordination oftheprocedure programhasbeentransferred totheManagerQualityAssurance asaQualityAssurance administrative servicefunction.

/SafetyEvaluation Summary:Theseprocedure changesestablish departmental responsibilities andlinesofauthority, responsibility, andcommunication forimplementation oftheprocedure programincluding publication.

Theproposedorganizational structure satisfies thecriteriaofSRP13.1.1andconformswiththerequirements ofSection6.1.2ofthePlantTechnical Specifications.

Theproposedchangesdonotimpactaccidentormalfunction initiation orconsequences.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage51of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-025Procedure NSAS-POL-01 Xlll-3,Xlll-4,FigureXIII-4N/AReorganization; ChangestoNSAS-POL-01 toTransferEnvironmental Protection Functions fromTechnical ServicestoLicensing andEmergency Preparedness Description ofChange:Procedure NSAS-POL-01 hasbeenrevisedtoreorganize (transfer) responsibility forthefunctional areasofenvironmental monitoring (including controlofhazardous andindustrial wastes,andassessing effectsofradioactive effluent) fromtheManagerTechnical ServicestotheManagerLicensing, andmeteorological monitoring fromtheManagerTechnical ServicestotheDirectorEmergency Preparedness.

/SafetyEvaluation Summary:Theseprocedure changesestablish departmental responsibilities andlinesofauthority, responsibility, andcommunication forimplementation oftheprocedure programincluding publication.

Theproposedorganizational structure satisfies thecriteriaofSRP13.1.1andconformswiththerequirements ofSection6.1.2ofthePlantTechnical Specifications.

Theproposedchangesdonotimpactaccidentormalfunction initiation orconsequences.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage52of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-058GAP-POL-01 N/AN/ADissolution oftheUnit2Technical SupportBranchSupportSectionDescription ofChange:TheNuclearDivisionisorganized intodepartments withdepartments beingsubdivided intobranchesandbranchesbeingsubdivided intosections.

Sectionscomposethelowestorganizational tieroftheNuclearDivision.

Thissafetyevaluation analyzeschangestotheTechnical SupportBranch.asaresultofdissolving theSupportSection.Theorganizational changeinvolvesdissolution oftheUnit2Technical SupportBranch'sSupportSectionby:/~Eliminating thepositionofLeadSupportEngineer.

~Converting theAdministrative Technician positiontoasupervisory positionwiththetitleofSupervisor Administrative Support.~HavingtheSupervisor Administrative SupportreportdirectlytotheManagerTechnical Supportandtoberesponsible for:1.Administration ofStationOperations ReviewCommittee (SORC).2.Administration oftheplanttechnical reviewprogram.3.Supervision oftheBranch'sclericalstaff.~Redistributing theremaining personnel andfunctions (including coordination ofplantmodifications) oftheSupportSectiontotheSystemEngineering Sectionsunderthesupervision oftheLeadSystemEngineers.

Safetyfvaluation SummaryReportPage53of60SafetyEvaluation No.:SafetyEvaluation Summary:95-058(cont'd.)

(cont'd.)

Dissolution oftheUnit2Technical SupportBranch'sSupportSectiondoesnotinvolveachangetotheestablished responsibilities oftheTechnical SupportBranchasdescribed intheUFSAR;onlythereporting structure withintheBranchisbeingaffected.

Theorganization continues toprovidefortheintegrated management ofactivities thatsupporttheoperation ofthefacilityandmaintains clearmanagement controlandeffective linesofauthority andcommunication; Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage54of60SafetyEvaluation No.:Implementation DocumentNo.:95-102Rev.051Procedures NSAS-POL-01, GAP-POL-01, NEP-POL-0101, NIP-FPP-01, NIP-TQS-01, GAP-OPS-01 UFSARAffectedPages: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/ARestructuring ofNuclearSBUinAccordance withRevisedProcedures NSAS-POL-01, GAP-POL-01, NEP-POL-01, NIP-FPP-01, NIP-TQS-01 andGAP-OPS-01 Description ofChange:NSAS-POL-01, "Composition andResponsibility oftheNuclearSafetyAssessment 8cSupportOrganization,"

GAP-POL-01, "Composition and'Responsibility oftheNuclearGeneration Organization,"

NEP-POL-01, "NuclearEngineering Department Organization,"

NIP-FPP-01, "FireProtection Program,"

NIP-TQS-01, "Qualification andCertification,"

andGAP-OPS-01, "Administration ofOperations,"

havebeenrevisedto:~Transferresponsibility forOfficeAdministration activities fromNuclearSafetyAssessment LSupport(NSAS)SiteServicestoBusinessManagement,-and removetheBusinessManagement organization fromtheNuclearGeneration Department (theGeneralManagerBusinessManagement reportsdirectlytotheExecutive VicePresident Nuclear).

~Transferresponsibility forProcurement andIntegrated Planningfunctions fromtheBusinessManagement Organization totheEngineering Department.

~"Unitize" thecoordination ofcontractor maintenance/modification activities previously performed byNSASSiteServicesandtransferresponsibility forthefunctions totheMaintenance Branchateachunit.

SafetyEvaluation SummaryReportPage55of60SafetyEvaluation No.:Description ofChange:95-102Rev.0&1(cont'd.)

(cont'd.)

Transferresponsibility foradministration andimplementation of.theFireProtection ProgramfromNSASTechnical ServicestoUnit1Operations.

~Transferresponsibility foradministration ofCentralMaintenance activities (asitefunctionthatincludesM&TEcalibration, securitysystemsupport,.

materialtesting,andwarehouse preventive maintenance) fromNSASTechnical ServicestoUnit2Maintenance.

Transferresponsibility foradministration ofBuildings

&Grounds/Facilities Planningactivities (asitefunction) fromtheNSASSiteServicestoUnit1Maintenance.

Abolishthepositions ofManagerTechnical ServicesandManagerSiteServices.

i~Transferresponsibility forIn-service TestingatUnit1fromOperations toMaintenance.

/~Consolidate theUnit1Operations Engineering andPlanningSectionsandcombinewiththeFireProtection Section(currently inNSASTechnical Services) intoanewOperations SupportSectiontobeheadedbyanewposition, GeneralSupervisor Operations Support.AssignI&CTechnicians toUnit2Technical SupportBranch-Lead Performance Engineer.

Consolidate Unit1andUnit2Operations Trainingorganizations intoonecommonsectionunderthesupervision oftheGeneralSupervisor Operations Training.

~Assignresponsibility formanagement ofSiteRelay&ControlTestingactivities (formerly aCorporate supportfunction) totheManagerMaintenance Unit2.~Transferresponsibility forMaintenance PlanningatUnit2fromMaintenance toWorkControl/Outage.

SafetyEvaluation SummaryReportPage56of60SafetyEvaluation No.:SafetyEvaluation Summary:95-102Rev.051(cont'd.)

Theseprocedure changesestablish departmental responsibilities andlinesofauthority, responsibility, andcommunication withintheNuclearSBU.Theproposedorganizational structure satisfies thecriteriaofSRPs9.5.1,13.1.1and13.1.2-13.1.3, andconformswiththerequirements ofSection6.2ofthePlantTechnical Specifications.

Theproposedchangesdonotimpactaccidentormalfunction initiation orconsequences.

Basedontheevaluation performed, itisconcluded thatthesechangesdonotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage57of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-106N/AFigureIII-1-N/ADemolition ofTemporary Structures InsidetheProtected Area,EastoftheUnit2Structures Description ofChange:Thissafetyevaluation addresses thedemolition ofthefollowing buildings locatedeastoftheUnit2plantstructures.

1.2.3.4.5.Carpenter's shopPaintshopElectricfabshopInsulators fabshopMaintenance storagebuildingAllofthesebuildings werebuiltforuseastemporary buildings duringtheconstruction ofUnit2.Thesebuildings havebeendemolished andactivities consolidated withintheremaining buildings.

SafetyEvaluation Summary:Allofthebuildings tobedemolished arelocatedinanareathatwasnotusedasaflowchannelfortheProbableMaximumPrecipitation analysis.

Removalofthesebuildings andtheconsequent reduction intherunoffcoefficient wouldmaketheanalysismoreconservative.

Thesebuildings havenoimpactonthepreviously

.calculated X/0values.Thedesignmarginsforthecontrolroomfreshairintakesarenotcompromised.

Locationofdemolition activities areadequately separated fromsafety-related systemsandstructures toprecludeanyadverseimpactfromconstruction activities.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage58of60SafetyEvaluation No.:implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-107NTP-TQS-102 N/AN/ANTP-TQS-102, LicensedOperatorRequalification TrainingChangestoReflecttheRequirements oftheNRCApprovedSystemsApproachtoTrainingProgramDescription ofChange:ThischangemoreclearlydefinesaSystemsApproachtoTraining(SAT)-based Requalification program./TheSAT-based programallowsflexibility inaddressing identified weaknesses andcurrentissueswhilesatisfying requiredtrainingspecified in10CFR55.SafetyEvaluation Summary:Unit1and2LicensedOperatorTrainingProgramshavebeendeveloped usingaSystemsApproachtoTrainingandareaccredited bytheNationalNuclearAccrediting Board.Basedonthiscertification andNRCapproval, thischangesatisfies 10CFR55requirements forLicensedOperatorRequalification Training.

ChangingtheLicensedOperatorRequalification TrainingprogramtomorecleariydefineaSAT-based programdoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage59of60SafetyEvaluation No.:implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:Description ofChange:95-128N/AN/AN/AAerialRadiation SurveyofNMPSiteSection2.2.3.1.7 oftheUnit2USARdiscusses aircraftcrashes,butthediscussion isonlyinreference toairplaneflightsassociated withnearbyairportsandhelicopter flightstoandfromthesite.TheNRCcontracted EG&Gtoperformanaerialradiation surveyoftheNineMilePointsite.Thissurveyinvolvedhelicopter flightsdirectlyoverthesiteand,asstatedabove,tlieUnit2USARonlyevaluated flightstoandfromthesite.SafetyEvaluation Summary:Thehelicopter flightsdirectlyoverthesite,forthepurposeofperforming anaerialradiation survey,wereevaluated andfoundtopresentaninsignificant riskofanaircraftcrashonsite.Thehelicopter accidentrates,apreviousStone&WebsterEngineering Corp.calculation, anArgonneNationalLaboratory StudyofAircraftCrashHazards,andtheNRCStandardReviewPlan(SRP)wereusedtoassesstheriskassociated withtheSurveyPlandescribed bytheEG&Gpilot.Theassessment resultedinacrashprobability between8AE-8and7E-7.PertheSRP,thisprobability issufficiently lowenoughthatcrashesneednotbeconsidered asdesignbasisevents.Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

SafetyEvaluation SummaryReportPage60of60SafetyEvaluation No.:Implementation DocumentNo.:UFSARAffectedPages:System:TitleofChange:95-130NuclearDivisionPolicyPOLB.1-2N/AReorganization; ChangetoNuclearDivisionPolicytoReflectEstablishment ofthe'orporate OfficerPosition"Executive VicePresident-Generation BusinessGroup/Chief NuclearOfficer"Description ofChange:TheNuclearDivisionPolicy"POL"hasbeenrevisedtoreflect.theestablishment ofthecorporate officerpositionExecutive VicePresident-Generation BusinessGroup/ChiefNuclearOfficer.ThisExecutive VicePresident reportsdirectlytotheNiagaraMohawkPowerCorporation President.

TheExecutive VicePresident-Nuclear issubordinate totheExecutive VicePresident-Generation BusinessGroup/Chief NuclearOfficerandcontinues tohaveoverallresponsibility fortheadmjnistration andoperation oftheNuclearSBU.SafetyEvaluation Summary:Theproposeduppermanagement organizational structure satisfies applicable acceptance

criteria, anddoesnotimpactaccidentormalfunction initiation orconsequences.

Basedontheevaluation performed, itisconcluded thatthischangedoesnotinvolveanunreviewed safetyquestion.

NRCFORM35(11-93)NRCMD3.53Page1ofU.S.NUCLEARREGULATORY COMMISSION

'comsT~NSFERggyyyS'gS'1.JOBNUMBER39114.VOLUMEINCUBICFEET5I.P2.FRCACCESSION NUMBER5.LOCATIONNUMBER(S) 17127-1713173.3.DATEJOBRECEIVED08/13/1997 6.DATEELIGIBLEFORDESTRUCTION 10/01/2029 7.DATEELIGIBLEFORTRANSFERTONARA10.COMMENTSLICENSEEXPIRES08/22/2009 8.ORIGINATING OFFICECODEFC/NRR/[X]AFQAF-V39.FACILITYCODEQAF-V5QFRCG0<T<'e'8-Z11.ORIGINATING OFFICE(Office/Division/Rranch)

FC/NRR/12.FILECUSTODIAN (Name/Telephone)

TyroneGreene(301)415-6281 13.LOCATIONOFRECORDS(ffuffdfng/Room)

TSC314.T(TLRAFRFCARDSFREFS (RefertoNUREG0910)

(Complete aseparateformforeachserfes)NuclearPowerPlantDocketFiles(E)15.RFCARDSCHFA11LENUMBER (RefertoNUREG.0910)

NRCS02-20.09E 16.CLASSIFICATION OFRECORDS[X]UNCLASSIFIED QOTHER(Specify below)HIGHESTCLASSIFICATION

[X]PAPERQMICROFORMo

• PROVIDESPECIFICMEDIUM17.RECORDMEDIUMQAUDIOVISUAL+

QMACEHNEREADABLEo 18.TOTALNUMBEROFCONTAINERS 19.TYPEOFCONTAINER(S)

(NOTEtPaperreconfsmustberetiredlnfwubfefootrecordcenterboxes)[X]RECORDCENTERBOXQOTHER(Specify) 20GENERALDESCRIPTION OFRECORDS(Prorhfcagenera(dcserfptfon oftherecordsusingitemscommonlyusedbythestofffamfNarwiththcrecords.)

50-220NIAGRAMOHAWKPOWERCORP.NINEMILEPOINTUNIT1NRCFORM35(11-93)s 1'I Page2ofDETAILEDINVENTORY OFRECORDSBEINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

lfmorespaceisrequired, useNRCfor35A,'RecordsTransferContinuation'.

21.CONTAINER NUMBER~m:M23.RECORDSDESCRIPTION 50-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)24.DATESPAN(Month/Yrnrs) 10/1996-10/199650-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)09/1996-09/199650-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)08/1996-08/199650-220NINEMILEPT1 REVISIONTOEPIPS(SECONDCOPY)06/1996-06/199650-220NINEMILEPI'I REVISIONTOEPIPS(SECONDCOPY)04/1996-04/199650-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)03/1996-03/199650-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)02/1996-02/199625.RECORDSLIAISONOFFICFR-Qprg/rrnne andSigna/urn TyroneGreene27.REVIEWING ANALYST..S/gna/nrc Latravetta Lee26.DATE08/13/1997 28.DATE08/13/1997 29.DATETRANSFERRED TOFRCQ30.DATEDESTROYED 31.DATETRANSFERRED TONARANRCFORM35(11.93)

~5 NRCPORN35II1-93INRCMD3.53Page3ofU.S.NUCLEARREGULATORY COMMISSION RECORDSTRANSFERContinuation DETAILEDINVENTORY OFRECORDSMINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated OI/3I/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAINER NUAIBERW~@M23.RECORDSDESCRIPTION 24.DATESPAN(Month/Years) 50-220NINEMILEPT1 REVISIONTOEPIPS(SECONDCOPY)12/1995-12/199550-220NINEMILEPTI REVISION35TOSITEEMERGENCY PLANANDEPIPS(SECONDCOPY)01/1997-01/199750-220NINEMILEPT1 REVISION34TOSITEEMERGENCY PLANANDEPIPS(SECONDCOPY)05/1996-05/199650-220NINEMILEPT1 REVISION33TOSITEEMERGENCY PLANANDEPIPS(SECONDCOPY)04/1996-04/199650-220NINEMILEPTI EVACUATION TRAVELTIMEESTIMATES FORTHENINEMILEPOINTEMERGENCY PLANNINGZONE06/1992-06/199250-220NINEMILEPTI REVISION14TOUFSAR(SECONDCOPY)06/1996-06/1996250-220NINEMILEPT1 REPORTTOACRS03/1969-03/1969.NRCFORM35(11-93)

NRCFORM35/1I931NRCMD3.53Page4ofU.S.NUCLEARREGULATORY COMMISSION'ECORDS TRANSFERCOntinuatiOn DETAILEDINVENTORY OFRECORDSBEINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/9G, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAlNER NUSIBER23.RECORDSDESCRIP1'lON 24.DATESPAN(Month/Yenrs) 50-220NINEMILEPTI ANNUALFINANCIAL REPORT1992RG&EC05/1993-05/199350-220NINEMILEPT1 ANNUALFINANCIAL REPORT1992LILCO05/1993-05/199350-220NINEMILEPTI ANNUALFINANCIAL REPORT1992NYSE&GC05/1993-05/199350-220NINEMILEPT1 ANNUALFINANCIAL REPORT1992CHG&EC05/1993-05/199350-220NINEMILEPT1 ANNUALFINANCIAL REPORT1992NMPC05/1993-05/199350-220NINEMILEPT1 ANNUALFINANCIAL REPORT1991NMPCIV1992-11/199250.220NINEMILEPT1 ANNUALFINANCIAL REPORT1991RG&EC05/1992-05/199250-220NINEMILEPTI ANNUALFINANCIAL REPORT1991LILCO05/1992-05/1992NRCFORM35(11-93)t I

NRCFORM35/I1.9.QNRCMD3.53Page5ofU.S.NUCLEARREGULATORY COMMISSION RECORDSTRANSFERContinuation DETAILEDINVENTORY OFRECORDSBEINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAINER NUSIBER~%;;M23.RECORDSDESCRIPI'ION 24.DATESPAN(Month/Y<<nrs) 50-220NINEMILEPTI ANNUALFINANCIAL REPORT1991NYSE&GC05/1992-05/199250-220NINEMILEPTI ANNUALFINANCIAL REPORT1991CHG&EC05/1992-05/199250-220NINEMILEPTI SAFETYEVALUATION OFTHREETMIACTIONPLANITEMS(NUREG-0737)>

H.F.'1.4, H.F.1.5ANDH.F.1.6,BYCONTAINMENT 06/198206/198250-220NINEMILEPT1 SAFETYEVALUATIONREPORT 06/1981-06/198150-220NINEMILEPTISAFETYEVALUATION REPORTREGARDING FIREPROTECTION 07/1979-07/197950-220NINEMILEPT1 PROPOSEDCHANGETOTECHNICAL SPECIFICATIONS REGARDING ADMINISTRATIVE CHANGES06/1993-06/199350-220NINEMILEPT1 PROPOSEDCHANGETOTECHNICAL SPECIFICATIONS CONSISTING OFADMINISTRATIVE CHANGES05/1993-05/1993NRCFORM35(11-93)

II NRCFORM35(11-931NRCMD3.53Pape6ofU.S.NUCLEARREGULATORY COMMISSION'ECORDS TRANSFERContinuation DETAILEDINVENTORY OFRECORDSBEINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAINER NUMBERMXM23.RECORDSDESCRIPTION 24.DATESPAN (Monrh/Years) 50-220NINEMILEPTI PROPOSEDCHANGETOTECHNICAL SPECIFICATIONS TOINCREASESURVEILLANCE TESTINTERVALS ANDADDALLOIVABLE OUT-OFS12/1992-12/199250-220NINEMILEPTI PROPOSEDCHANGETOTECHNICAL SPECIFICATIONS REGARDING COOLANTSYSTEM02/1992-02/199250-220NINEMILEPT1 DRAFTTECHNICAL SPECIFICATIONS (FSAR)(REVISED) 03/1969-03/196950-220NINEMILEPTI SAMPLETECHNICAL SPECIFICATIONS 12/1965-12/196550-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)06/1997-06/199750-220NINEMILEPTI REVISIONTOEPIPS(SECONDCOPY)05/1997-05/199750-220NINEMILEPT1 REVISIONTOEPIPS(SECONDCOPY)04/1997-04/199750-220NINEMILEPT1 REVISIONTOEPIPS(SECONDCOPY)03/1997-03/1997NRCFORM35(11-93)

I NRCFORM35/I1-931NRCMD3.53Page7ofU.S.NUCLEARREGULATORY COMMISSION'ECORDS TRANSFERContinuation DETAILEDINVENTORY OFRECORDSBEINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAINER NUi%1BERW>A~M23.RECORDSDESCRIPTION 24.DATESPAN(Month/Years) 50-220NINEMILEPf1 REVISIONTOEPIPS(SECONDCOPY)10/1996-10/199650-220NINEMILEPTI REACTORCONTAINMENT BUILDINGINTEGRATED LEAKAGERATETESTFINALREPORT04/1993-04/199350-220NINEMILEPTI SAFETYEVALUATION SUMMARYREPORT,199206/1992-06/199250-220NINEMILEPT1 SAFETYEVALUATION SUMMARYREPORT1990SUBMITTED WITHUPDATEDFSAR,REVISION8ANDAMENDMENTS 06/1990-06/1990350-220NINEMILEPT1 APPROVEDPROCEDURES POWERASCENSION PROGRAM01/1990-01/1990W50-220NINEMILEPT1 CONTAINMENT LEAKTEST05/1984-05/198450-220NINEMILEPI'1 EQUIPMENT QUALIFICATION PROGRAM05/1984-05/1984NRCFORM35(11.93)

~h NRCFORM35/11-9:41NRCMD3.53Page8ofU.S.NUCLEARREGULATORY COMMISSION'ECORDS TRANSFERContinuation DETAILEDINVENTORY OFRECORDSMINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideailidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAINER NUMBER23.RECORDSDESCRIPTION 24.DATESPAN(Month/Yeats) 50.220NINEMILEPT1 TECHNICAL SUPPLEMENT TOPETITIONFORCONVERSION FROMPROVISIONAL OPERATING LICENSETOFULL-TERM OPERATING LICE07/1972-07/197250-220NINEMILEPTI FIFTHADDENDUMTOTECHNICAL SUPPLEMENT TOPETITIONTOINCREASEPOWERLEVELOV1971-OV197150-220NINEMILEPT1 FOURTHADDENDUMTOTECHNICAL SUPPLEMENT TOPETITIONTOINCREASEPOWERLEVEL12/1970-12/197050-220NINEMILEPT1 THIRDADDENDUMTOTECHNICAL SUPPLEMENT TOPETITIONTOINCREASEPOWERLEVEL12/1970-12/19700-220NINEMILEPT1 SECONDADDENDUMTOTECHNICAL SUPPLEMENT TOPETITIONTOINCREASEPOWERLEVEL10/1970-10/197050-220NINEMILEPTI FIRSTADDENDUMTOTECHNICAL SUPPLEMENT TOPETITIONTOINCREASEPOWERLEVEL10/1970-10/197050-220NINEMILEPT1 RESPONSETOB.L.RIDINGSOFKINSTON,TN'SLETTEROFOCTOBER13,199311/1993-11/199350-22009/1993-09/1993NRCFORM35(11-93)

WRCFORM35(11-931NRCMD3.53PageilofU.S.NUCLEARREGULATORY COMMISSION RECORDSTRANSFERContinuation DETAILEDINVENTORY OFRECORDSBEINGTRANSFERRED Foreachindividual folder,binder,report,tape,etc.,sufficient description topermitretrieval.

Provideallidentifying numbersthatapplytothematerial(e.g.docketnumber,casenumber,contractnumber,formnumber,etc.).Providethedatespanofeachitemaswellasanydateneededtoapplythedisposition instructions (e.g.licenseterminated 01/31/90, caseclosed01/31/90, etc.).Doublespacebetweenitemsinthesamecontainer.

Triplespacewhenbeginning anewcontainer.

21.CONTAINER NUMBER23.RECORDSDESCRIPTION 24.DATESPAN(MonthA'ears) 50-220NINEMILEPTI SUPERSEDED PAGESPERREVISIONTOEPP10/1996-10/199650-220NINEMILEPTI SUPERSEDED PAGESPERREVISIONTOEPP10/1996-10/199650-220NINEMILEPT1 SUPERSEDED PAGESPERREVISIONTOEPP09/1996-09/199650-220NINEMILEFf1 SUPERSEDED PAGESPERREVISIONTOEPP11/1995-11/199550-220NINEMILEPTI SUPERSEDED PAGESPERREVISIONTOSITEEMERGENCY PLAN01/1997-01/199150-220NINEMILEPI'1 SUPERSEDED PAGESPERREVISION13TOUFSAR06/1995-06/1995~,NRCFORM35(11.93) l NINEMILEPOINTUN3Z1FSAR-(UPDATED)

LISTOFEFFECTIVE PAGESGENERALTABLEOFCONTENTSPAGENUMBER1liilliVVViViiV3.3.'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)

LISTOFEFFECTIVE PAGESGENERALTABLEOFCONTENTSPAGENUMBERI-1I-2I-3I-4I-5I-6I-7I-8I-9I-10I-11I-12I-13I-14I-15I-16I-17T=TABLEF=FIGURENUMBERFI-1REVISIONNUMBER0990110000131313120003PAGENUMBERT=TABLEF=FIGUREREVISIONNUMBERNUMBERUFSARRevision13EP1-1June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESGENERALTABLEOFCONTENTST=TABLE.PAGEF=FIGURENUMBERNUMBERREVISIONNUMBERT=TABLEPAGEF=FIGUREREVISIONNUMBERNUMBERNUMBERII-1II-2II-3II-4II-5II-6II-7II-8II-9II-10II-11II-12-II-13II-14II-15II-16II-17II-18II-19II-20II-21II-22II-23II-24II-25FII-1FII-2FII-3TII-1FII-4FII-5TII-2FII-6TII-3TII-4TII-5TII-6TII-7TII-8TII-8TII-8130061300000130136661000093304UFSARRevision13EP2-1June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONIIIPAGENUMBERIII-1III-2III-3III-4III-5III-6III-7III-8III-9III-10.III-11III-12III-13III-14III-15III-16III-17III-18III-19III-20III-21III-22III-23III-23aIII-23bIII-24III-25III-26III-27III-28III-29III-30III-31III-32III-33III-34III-35III-36III-37III-38III-39III-40III-41III-42III-43T=TABLE'=FIGURENUMBERFIII-1FIII-2FIII-3FIII-4~FIII-5FIII-6FIII-7FIII-8FIII-9FIII-10FIII-11FIII-12FIII-13FIII-14FIII-15FIII-16"FIII-17REVISIONNUMBER901319061212121266622511311313121212,110111210000020i2011000009PAGENUMBERIII-44III-45III-46III-47III-47aIII-48III-48aIII-48bIII-49III-50III-51III-52III-53III-54III-54aIII-54bIII-55III-56III-57III-58III-59III-60III-61III-62III-63III-64III-65III-66III-67III-68III-69III-70III-71III-72III-73III-74III-75T=TABLEF=FIGURENUMBERFIII-18FIII-19FIII-20FIII-21FIII-22FIII-23REVISIONNUMBER91312123121010100000121212001200121001300000121212'2121212UFSARRevision13EP3-1June1995 0h NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONIVPAGENUMBERIV-1IV-2IV-3IV-4IV-5IV-6IV-7IV-8IV-9IV-10IV-11IV-12IV-13IV-14IV-15IV-16IV-17IV-18IV-19IV-19aIV-20IV-21IV-22IV-23IV-24IV-25IV-26IV-27IV-28IV-29IV-30IV-31IV-32IV-33IV-34IV-35IV-35aIV-35bIV-36IV-37IV-38IV-39IV-40IV-40aIV-40bT=TABLEF=FIGURENUMBERFIV-1FIV-2FIV-3FIV-4FIV-5FIV-6FIV-7FIV-8REVISIONNUMBER12136613120130131313131212000i13808131312136131313131313101311'1110000101312,12PAGENUMBERIV-41IV-42IV-43IV-44IV-45IV-46IV-46aIV-46bIV-47IV-48IV-49IV-50IV-51IV-52T=TABLEF=FIGURENUMBERFIV-9REVISIONNUMBER01000101010000000UFSARRevision13EP4-1June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONVT=TABLEPAGEF=FIGURENUMBERNUMBERREVISIONNUMBERT=TABLEPAGEF=FIGUREREVISIONNUMBERNUMBERNUMBERV-1V-2V-3V-4V=5V-6V-7V-8V-9V-10V-11V-12V-12aV-13.V-14V-15V-16V-17V-18V-19V-20V-21V-22V-23V-23aV-23bV-24V-25V-26V-27V-28V-29V-30V-30aV-31V-31aV-31bV-32V-33TV-1TV-1TV-1TV-2TV-3,TV-4FV-1TV-5FV-2FV-3FV-4FV-5FV-6'FV-7FV-800118100000011118900131310011111111111111001294412121203UFSARRevision13EP5-1June1995

/

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONVIPAGENUMBERVI-1VI-2VI-3VI-4VI-5VI-6VI-7VI-8VI-9V.I-10VI-11VI-12VI-13VI-14VI-15-VZ-16VI-17VI-18VI-19VI-19aVI-20VI-21VI-22VI-22aVI-22bVI-23VI-24VI-25VI-26VI-27VI-28VI-29VI-30VI-31VI-32VI-33VI-34VI-35VI-36VI-37VI-38VI-39VI-40VI-41VI-42T=TABLEF=FIGURENUMBERFVI-1FVI-2FVI-3FVI-4FVI-4aFVI-5FVI-6FVI-7FVI-8FVI-9FVI-10FVI-11FVI-12FVI-13FVI-14FVI-15FVI-16FVI-17FVI-18FVI-19REVISIONNUMBER0411111100901000.0000.PAGENUMBERVI-43VI-43aVI-43bVI-44VI-45VI-46VI-47VI-48VI-48aVI-49VI-50VI-50aVI-50bVI-51VI-52VI-53VI-54VI-55VI-56VI-56aVI-56bVI-57VI-58VI-59VI-60VI-61VI-62VI-63VI-64VI-65VI-66VI-67VI-68VI-69VI-70T=TABLEF=FIGURENUMBERTVI-1TVI-1TVI-2TVI-3aTVI-3aTVI-3aTVI-3bTVI-3bTVI-3bTVI-3bTVI-3cFVI-20FVI-21TVI-4FVI-22FVI-23FVI-24TVI-5TVI-5REVISIONNUMBER1111111111111313131111131111000121113133111200011121313'31300UFSARRevision13EP6-1June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONVIIPAGENUMBERT=TABLEF=FIGURENUMBERREVISIONNUMBERPAGENUMBERT=TABLEF=FIGURENUMBERREVISIONNUMBERVII-1VII-2VII-3VII-4VII-5VZI-,6VII-6aVII-7VII-8VII-9VII-10VII-11VII-11aVII-11bVII-12VII-13VIZ-13aVII-14VII-15VII-16VII-17VII-18VII-18aVII-18bVII-19VII-20VII-21VII-21aVII-21bVII-22VII-23VII-24VII-25VII-26VII-26aVII-26bVII-27VII-28VII-29VII-30VII-30aVII-30bVII-31VII-32VII-33'VII-1FVZI-2FVII-3FVII-4FVII-4aFVII-5FVII-6FVIZ-7FVII-8.FVII-99101089810688013131011910991091210101313111111107071110100110101010101010VZI-33aVIZ-33bVII-34VII-35VII-36VZI-37VZI-38VII-39VII-40VII-41VII-42VII-43VII-44VII-45VII-46VZI-46aVII-46bVII-47VII-48VII-49VII-53VII-54VIZ-55VII-55aVZI-55bVZI-56VII-57VZZ-58VZI-59VII-60VII-61VII-61aVII-62VII-62aVII-63TVII-1FVII-10FVIZ-11FVII-12FVII-16FVII-17VII-50FVII-13VII-51FVII-14VII-52FVII-15101000000090300012121212039000012121200000129889UFSARRevision13EP7-1June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONVIIIPAGENUMBERVIII-1VIIX-2VIII-3VIII-4VIII-5VIII-6VIII-7VIIZ-8VIII-9VIII-10VIII-11VIII-12VIII-13VIII-14VIII-15VIIZ-16VIII-17VIII-18VIII-19VIII;20VIII-21VIII-22VIII-23VIII-24VIII-25VIII-26VIII-27VIII-28VIII-29VIII-30VIII-31VIII-32VIII-33VIII-34VIII-35VIII-36VIII-37VIII-38VIII-39VIII-40VIII-40aVIII-41VIII-42VIII-43VIII-44T=TABLEF=FIGURENUMBERFVIII-1FVIII-2FVIXI-3FVIII-4FVIXI-5FVIII-6FVIIZ-7FVIII-8FVIIZ-9FVIII-10FVIII-11FVIII-12FVIXI-13FVIII-14FVIII-15REVISIONNUMBER121259570.131301171374500004000080'81000000100012'1880000PAGENUMBERVIII-45VIII-46VIII-47VIII-48VIII-49VIII-50VIII-51VIII-52VIII-53VIII-54VIII-55VIII-56VIII-57VIII-58'III-59VIIX-60VIII-61VIII-62VIII-62aVIII-62bVIII-63VIII-64VIII-65VIII-66VIII-67VIII-68VIII-69,VIII-70VIII-71VIII-71aVIII-71bVIII-72VIII-72aVIII-72bVIII-73VIII-74VIII-75VIII-76VIII-77VIIZ-78VIIZ-79VIIX-80'III-81 VIII-81aVIII-81bT=TABLEF=FIGURENUMBERFVIII-16FVIII-17FVIII-18FVIII-19FVIII-20FVIII-21FVIII-22FVIII-23FVIII-24FVIII-25FVIII-26FVIII-27FVIII-28FVIII-29REVISIONNUMBER0000011000001313131313131313130010100~4310121212101010100300009121212UFSARRevision13EP8-1June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

LISTOFEFFECTIVE PAGESSECTIONVIIIPAGENUMBERT=TABLEF=FIGUREREVISIONNUMBERiNUMBERT=TABLEPAGEF=FIGUREREVISIONNUMBERNUMBERNUMBERVIII-82VIII-82aVIII-82bVIII-82cVIII-826VIII-83VIII-84VIII-85VIII-86VIII-87VIII-88VIII-89VIII-90VIII-91VIII-92VIII-93VIII-94VIII-95VIII-96VIII-97VIII-98VIII-98aVIII-98bVIII-99VIII-100VIII-101VIII-102VIII-103VIII-104VIII-105VIII-106VIII-107VIII-108VIII-109VIII-110VIII-111VIII-112TVIII-1TVIII-2TVIII-3TVIII-3TVIII-3TVIII-3TVIII-3TVIII-3TVIII-3TVIII-3TVIII-3TVIII-3TVIII-39912121212121212131212121212129121212131313'1212121212121212121212121213UFSARRevision13EP8-2June1995

NINEMILEPOINTUNIT1FSAR(UPDATED)

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SYRACUSE, NEWYORK 0

NineMilePointUnit1FSARTABLEOFCONTENTSSectionTitlePacaeSECTIONITABLEOFCONTENTSLISTOFFIGURESLISTOFTABLESINTRODUCTION ANDSUMMARYXXXxiiiA.1.02.03.04.05.06.07.08.09.010.0B.1.02.03.04.05.06.07.08.09.010.011.012.013.014.015.016.0C.D.SECTIONIIPRINCIPAL DESIGNCRITERIAGeneralBuildings andStructures ReactorReactorVesselContainment ControlandInstrumentation Electrical PowerRadioactive WasteDisposalShielding andAccessControlFuelHandlingandStorageCHARACTERISTICS SiteReactorCoreFuelAssemblyControlSystemCoreDesignandOperating Conditions DesignPowerPeakingFactorNuclearDesignDataReactorVesselCoolantRecirculation LoopsPrimaryContainment Secondary Containment Structural DesignStationElectrical SystemReactorInstrumentation SystemReactorProtection SystemIDENTIFICATION OFCONTRACTORS GENERALCONCLUSIONS STATIONSITEANDENVIRONMENT I-2I-2I-2I-3I-4I-5Z-7I-8I-8I-9I-9I-10I-10I-10I-10I-10.I-11I-11I-11I-12I-12I-12I-12I-13I-13I-13I-13I-14I-15X-16IX-1A.1.02.03.0SITEDESCRIPTION GeneralPhysicalFeaturesPropertyUseandDevelopment II-1II-1XI-1II-5UFSARRevision12June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)

SectionB.1.01.12.02.12.22.3TitleDESCRIPTION OFAREAADJ'ACENT TOTHESITEGeneralPopulation Agricultural, Industrial andRecreational UseAgricultural UseIndustrial UseRecreational UsePacaeII-6II-6ZZ-6XI-9II-9IZ-11ZZ-17C.D.E.F.SECTIONIXIMETEOROLOGY LIMNOLOGY EARTHSCIENCESENVIRONMENTAL RADIOLOGY BUILDINGS ANDSTRUCTURES II-22XX-23II-24II-25IIZ-1A.1.01.11.21.31.41.52.02.12.22.32.43.0B.1.01.11.21.31.41.52.02.12.22.32.43.0TURBINEBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilation Shielding andAccessControlStructure DesignGeneralStructural FeaturesHeatingandVentilation SystemSmokeandHeatRemovalShielding andAccessControlSafetyAnalysisCONTROLROOMDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilation Shielding andAccessControlStructure DesignGeneralStructural FeaturesHeating,Ventilation andAirConditioning SystemSmokeandHeat.RemovalShielding andAccessControlSafetyAnalysisIII-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.1.01.11.1.11.1.21.1.31.1.41.1.51.21.2.11.2.21.2.31.32.02.12.1.12.1.22.1.32.1.42.1.52.1.62.1.7TitleWASTEDISPOSALBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilation Shielding andAccessControlStructure DesignGeneralStructural FeaturesHeatingandVentilation SystemShielding andAccessControlSafetyAnalysisOFFGASBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilation Shielding andAccessControlStructure DesignGeneralStructural FeaturesHeatingandVentilation SystemShielding andAccessControlSafetyAnalysisNONCONTROLLED BUILDINGS Administration BuildingDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeating,CoolingandVentilation Shielding andAccessControlStructure DesignGeneralStructural FeaturesHeating,Ventilation andAirConditioning AccessControlSafetyAnalysisSewageTreatment BuildingDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsElectrical DesignFireandExplosive GasDetection HeatingandVentilation Shielding andAccessControlPacaeIII-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.)

Section2.22.2.12.2.22.2.33.03.13.1.13.1.23.1.33.1.43.1.53.23.2.13.2.23.2.3TitleStructure DesignGeneralStructural FeaturesVentilation SystemAccessControlEnergyInformation CenterDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilation Shielding andAccessControlStructure DesignGeneralStructural FeaturesHeatingandVentilation SystemAccessControlPacaeIII-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~

INTAKEANDDISCHARGE TUNNELSScreenhouse DesignBasisWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeatingandVentilation Shielding andAccessControlStructure DesignIntakeandDischarge TunnelsDesignBasesStructure DesignSafetyAnalysisSTACKDesignBasesGeneralWindLoadingSeismicDesignShielding andAccessControlStructure DesignSafetyAnalysisRadiology StackFailureAnalysisReactorBuildingDiesel-Generator BuildingScreenandPumpHouseSECURITYBUILDINGANDSECURITYBUILDINGANNEXII1-53ZII-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.1.02'2.12'2.2.12.2'2.33.03.13.1~13.1.23.23.2.13.2.23.34.04.14'5'5.15RADWASTESOLIDIFICATION ANDSTORAGEBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignandInternalLoadingsHeating,Ventilation andAirConditioning Shielding andAccessControlStructure andDesignGeneralStructural FeaturesHeating,Ventilation andAirConditioning Shielding andAccessControlUseReferences REACTORDESIGNBASESGeneralPerformance Ob)ecti.ves DesignLimitsandTargetsREACTORDESIGNGeneralNuclearDesignTechnique Reference LoadingPatternFinalLoadingPatternAcceptable Deviation FromReference LoadingPatternReexamination ofLicensing BasisRefueling CycleReactivity BalanceThermalandHydraulic Characteristics ThermalandHydraulic DesignRecirculation FlowControlCoreThermalLimitsThermalandHydraulic AnalysesHydraulic AnalysisThermalAnalysis'eactor Transients Stability AnalysisDesignBasesStability AnalysisMethodMechanical DesignandEvaluation FuelMechanical DesignDesignBasesPacaeIII-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'LFuelRodsWaterRodsFuelAssemblies Mechanical DesignLimitsandStressAnalysisRelationship BetweenFuelDesignLimitsandFuelDamageLimitsSurveillance andTestingControlRodMechanical DesignandEvaluation DesignControlRodsandDrivesStandbyLiquidPoisonSystemControlSystemEvaluation RodWithdrawal ErrorsEvaluation OverallControlSystemEvaluation LimitingConditions forOperation andSurveillance ControlRodLifetimeReactorVesselInternalStructure DesignBasesCoreShroudCoreSupportTopGridControlRodGuideTubesFeedwater SpargerCoreSpraySpargersLiquidPoisonSpargerSteamSeparator andDryerDesignEvaluation Surveillance andTestingREACTORCOOLANTSYSTEMPacaeIV-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.1.01.11.21.31.41.5DESIGNBASESGeneralPerformance Objectives DesignPressureCyclicLoads(Mechanical andThermal)CodesSYSTEMDESIGNANDOPERATION GeneralDrawingsMaterials ofConstruction ThermalStressesPrimaryCoolantLeakageCoolantChemistry V-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.1.0.2.02.12.2TitleReactorVesselReactorRecirculation LoopsReactorSteamandAuxiliary SystemsPipingReliefDevicesSYSTEMDESIGNEVALUATION GeneralPressureDesignHeatupandCooldownRatesMaterials Radiation ExposurePressure-Temperature LimitCurvesTemperature LimitsforBoltupTemperature LimitsforIn-Service SystemPressureTestsOperating LimitsDuringHeatup,Cooldown, andCoreOperation Predicted ShiftinRT~~Mechanical Considerations JetReactionForcesSeismicForcesPipingFailureStudiesSafetyLimits,LimitingSafetySettingsandMinimumConditions forOperation TESTSANDINSPECTIONS Prestartup TestingInspection andTestingFollowing StartupHydroPressurePressureVesselIrradiation PBceeV-12aV-14V-16V-16V-19V-19V-19V-21V-21V-21V-22V-22V-23aV-23aV-23aV-23aV-23bv-26V-26V-27V-27V-27V-27V-27E.1.02.03.03.13.23.33.44.04.14.2SECTIONVIEMERGENCY COOLINGSYSTEMDesignBasesSystemDesignandOperation DesignEvaluation Redundancy MakeupWaterSystemLeaksContainment Isolation TestsandInspections Prestartup TestSubsequent Inspections andTestsCONTAXNMENT SYSTEMPRXMARYCONTAINMENT-MARK ICONTAXNMENT PROGRAMV-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~iteGeneralStructure PressureSuppression Hydrodynamic LoadsSafety/Relief ValveDischarge Loss-of-Coolant AccidentSummaryofLoadingPhenomena PlantUniqueModifications PRIMARYCONTAINMENT

-PRESSURESUPPRESSION SYSTEMDesignBasesGeneralDesignBasisAccidentContainment HeatRemovalIsolation CriteriaVacuumReliefCriteriaFloodingCriteriaShielding Structure Design-GeneralPenetrations andAccessOpeningsJetandMissileProtection Materials Shielding VacuumReliefContainment FloodingSECONDARY CONTAINMENT

-REACTORBUILDINGDesignBasesWindandSnowLoadingsPressureReliefDesignSeismicDesignShielding Structure DesignGeneralStructural Features~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.,1.0111.22.0CONTAINMENT ISOLATION SYSTEMDesignBasesContainment SprayAppendixJWaterSealRequirements SystemDesignTestsandInspections CONTAINMENT VENTILATION SYSTEMPri'maryContainment

,DesignBasesSystemDesignSecondary Containment VI-43VI-43VI-56aVI-57VI-59VI-60VI-60VI-60VI-60VI-62UFSARRevision13viiiJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)

~Sectio2~12'DesignBasesSystemDesign~aeVI-62VX-62UFSARRevision13viiiaJune1995 NineMilePointUnit1FSARTHISPAGEINTENTIONALLY BLANKUFSARRevision13viiibJune1995 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)

~SecticF.1.01.11.22.02.12'3.04.05.05.1'5~25.3SECTIONVIITESTANDINSPECTIONS DrywellandSuppression ChamberPreoperational TestingPostoperational TestingContainment Penetrations andIsolation ValvesPenetration andValveLeakageValveOperability TestContainment Ventilation SystemOtherContainment TestsReactorBuildingReactorBuildingNormalVentilation SystemReactorBuildingIsolation ValvesEmergency Ventilation SystemENGINEERED SAFEGUARDS

~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.1.02.03.03.13.23.34.0CORESPRAYSYSTEMDesignBasesSystemDesignGeneralOperatorAssessment DesignEvaluation TestsandInspections CONTAINMENT SPRAYSYSTEMDesignBasesSystemDesignOperatorAssessment DesignEvaluation TestsandInspections LIQUIDPOISONINJECTION SYSTEMDesignBasesSystemDesignOperatorAssessment DesignEvaluation TestsandInspections Alternate BoronInjection CONTROLRODVELOCITYLIMITERDesignBasesSystemDesignDesignEvaluation GeneralDesignSensitivity NormalOperation TestsandInspections VII-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"2.23.0VIIITitleCONTROLRODHOUSINGSUPPORTDesignBasesSystemDesignLoadsandDeflections DesignEvaluation TestsandInspections FLOWRESTRICTORS DesignBasesSystemDesignDesignEvaluation TestsandInspections COMBUSTIBLE GASCONTROLSYSTEMDesignBasesContainment InertingSystemSystemDesignDesignEvaluation Containment Atmospheric DilutionSystemSystemDesignDesignEvaluation TestsandInspections EMERGENCY VENTILATION SYSTEMDesignBasesSystemDesignOperatorAssessment DesignEvaluation TestsandInspections HXGH-PRESSURE COOLANTZNJECTXONDesignBasesSystemDesignDesignEvaluation TestsandXnspections INSTRUMENTATZON ANDCONTROLPROTECTIVE SYSTEMSDesignBasesReactorProtection SystemAnticipated Transients WithoutScramMitigation SystemSystemDesignReactorProtection SystemAnticipated Transients WithoutScramMitigation SystemSystemEvaluation PacaeVZI-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.1.02~02~12.22.32.43.03'3.23'3.4REGULATING SYSTEMSDesignBasesSystemDesignControlRodAdjustment ControlRecirculation FlowControlPressureandTurbineControlReactorFeedwater ControlSystemEvaluation ControlRodAdjustment ControlRecirculation FlowControlPressureandTurbineControlReactorFeedwater Control~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'.33.03'3~1~13.1.23.24.04.1INSTRUMENTATION SYSTEMSNuclearInstrumentation DesignSourceRangeMonitorsIntermediate RangeMonitorsLocalPowerRangeMonitorsAveragePowerRangeMonitorsTraversing In-CoreProbeSystemEvaluation SourceRangeMonitorsIntermediate RangeMonitorsLocalPowerRangeMonitorsAveragePowerRangeMonitorsNon-Nuclear ProcessInstrumentation DesignBasesNon-Nuclear ProcessInstruments in-Protective SystemNonnuclear ProcessInstruments inRegulating SystemsOtherNonnuclear ProcessInstruments Evaluation Nonnuclear ProcessInstruments inProtective SystemNonnuclear ProcessInstruments inRegulating SystemsOtherNonnuclear ProcessInstruments Radioactivity Instrumentation DesignBasesRadiation MonitorsinProtective SystemsOtherRadiation MonitorsEvaluation OtherInstrumentation RodWorthMinimizer VIII-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.)

Section4.1.14.1.25.05.15.25.35.45.4.15.4.25.4.35.4.45.55.65.6.15.6.25.6.35.6.45.6.55.6.6I55.6.9TitleDesignBasesEvaluation Regulatory Guide1.97(Revision 2)Instrumentation Licensing Activities

-Background Definition ofRG1.97VariableTypesandInstrument Categories Determination ofRG1.97TypeAVariables forNMP1Determination of"EOPKeyParameters" forNMP1"Determination Basis/Approach Definition ofPrimarySafetyFunctions Association ofEOPstoPrimarySafetyFunctions Identification ofEOPKeyParameters NMP1RG1.97Variables, VariableType,andAssociated Instrument CategoryDesignations SummaryoftheRG1.97Instrument DesignandImplementation CriteriathatwereEstablished forNMP1asPartoftheUnit11990RestartActivities NoTypeAVariables EOPKeyParameters SingleTapfortheFuelZoneRPVWaterLevelInstrument Nonredundant Wide-Range RPVWaterLevelIndication Upgrading EOPKeyParameter Category1Instrument LoopComponents toSafetyRelatedClassification SafetyRelatedClassification ofInstrumentation forRG1.97VariableTypesOtherthantheEOPKeyParameters RoutingandSeparation ofChannelized Category1Instrument LoopCablesElectrical Isolation ofCategory1Instrument LoopsfromAssociated Components thatarenotSafetyRelatedPowerSourceInformation forCategory1Instruments PRCReVIXI-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.1.01.11.22.02.12.22.32.42.53.03.13'3.33.43.4.13.4.23.4.33.53.5.13.5.24.04.14.24.35.05.15.25.36.06.1MarkingofInstruments ofControlRoomPanels"Alternate" Instruments forMonitoring EOPKeyParameters Indicating RangesofMonitoring Instruments References ELECTRICAL SYSTEMSDESIGNBASESELECTRICAL SYSTEMDESIGNNetworkInterconnections 345-kVSystem115-kVSystemStationDistribution SystemTwof24-VoltDCSystemsTwo120-V,60-Hz,Single-Phase, Uninterruptible PowerSupplySystemsTwo120-V,57-60Hz,One-Phase, ReactorTripPowerSuppliesOne120/208-V, 60-Hz,Instrument andControlTransformer One120/240-V, 60-Hz,Three-Phase, ComputerPowerSupplyCablesandCableTraysCableSeparation CablePenetrations Protection inHazardous AreasTypesofCablesPowerCableControlCableSpecialCableDesignandSpacingofCableTraysTrayDesignSpecifications TraySpacingEmergency PowerDieselGenerator SystemStationBatteries Nonsafety BatterySystemTestsandInspections Diesel-Generator StationBatteries Nonsafety Batteries Conformance with10CFR50.63, 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.)

Section6.26.36.46.56.6StationBlackoutCopingCapability Procedures andTrainingQualityAssurance EDGReliability ProgramReferences

~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'.33.43.54.05.0REACTORAUXILIARY ANDEMERGENCY SYSTEMSREACTORSHUTDOWNCOOLINGSYSTEMDesignBasesSystemDesignSystemEvaluation TestsandInspections 1REACTORCLEANUPSYSTEMDesignBasesSystemDesignSystemEvaluation TestsandInspections CONTROLRODDRIVEHYDRAULIC SYSTEMDesignBasesSystemDesignPumpsFiltersFirstPressureStageSecondPressureStageThirdPressureStageExhaustHeaderAccumulator ScramPilotValvesScramValvesScramDumpVolumeControlRodDriveCoolingSystemDirectional ControlandSpeedControlValvesRodInsertion andWithdrawal ScramActuation SystemEvaluation NormalWithdrawal SpeedAccidental MultipleOperation ScramReliability Operational Reliability Alternate RodInjection (ARI)ReactorVesselLevelInstrumentation Reference LegBackfillTestsandInspections X-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.1'2.03.04.01.02.03.04.01~02.02.12.1.12.23.04.0REACTORBUILDINGCLOSEDLOOPCOOLINGWATERSYSTEMDesignBasesSystemDesignDesignEvaluation TestsandInspections TURBINEBUILDINGCLOSEDLOOPCOOLINGWATERSYSTEMDesignBasesSystemDesignDesignEvaluation TestsandInspections SERVICEWATERSYSTEMDesignBasesSystemDesignDesignEvaluation TestsandInspections MAKEUPWATERSYSTEMDesignBasesSystemDesignSystemEvaluation TestsandInspections SPENTFUELSTORAGEPOOLFILTERING ANDCOOLINGSYSTEMDesignBasesSystemDesignDesignEvaluation TestsandInspections BREATHING, INSTRUMENT ANDSERVICEAIRSYSTEMDesignBasesSystemDesignDesignEvaluation TestsandInspections FUELANDREACTORCOMPONENTS HANDLINGSYSTEMDesignBasesSystemDesignDescription ofFacilityCaskDropProtection SystemOperation oftheFacilityDesignEvaluation TestsandInspections X-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.1.01.11.21.31.41.51.62.02.12.22.32.43.03.13.24.0TitleFIREPROTECTION PROGRAMProgramBasesNuclearDivisionDirective

-FireProtection ProgramNuclearDivisionInterface Procedure

-FixeProtection ProgramFireHazardsAnalysis(FHA)AppendixRReviewSafeShutdownAnalysis(SSA)FireProtection andAppendixRRelatedPortionsofOperations Procedures (OPs,SOPs,andEOPs)andDamageRepairProcedures FireProtection PortionsoftheEmergency PlanProgramImplementation andDesignAspectsFireProtection Implementing Procedures FireProtection Administrative ControlsFireProtection SystemDrawingsandCalculations FireProtection Engineering Evaluations (FPEEs)Monitoring andEvaluating ProgramImplementation FireProtection QualityAssurance Program(FPQAP)FireBrigadeManning,Training, DrillsandResponsibilities Surveillance andTestsPacaeX-59X-59X-59X-59X-59X-60X-60X-60X-60X-60X-61X-61X-61X-62x-62X-62x-62L.1.02.03.04.0M.1.02.03.04.0IAPPENDIX1OAIAPPENDIX10BREMOTESHUTDOWNSYSTEMDesignBasesSystemDesignSystemEvaluation TestsandInspections SAFETYPARAMETER DISPLAYSYSTEMDesignBasesSystemDesignSystemEvaluation TestsandInspections FIREHAZARDSANALYSISSAFESHUTDOWNANALYSISX-76X-76X-76X-76X-77X-78X-78X-78X-78X-79UFSARRevision12XviJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)

SectionSECTIONXZA.Ti.tieSTEAMTOPOWERCONVERSION SYSTEMDESIGNBASESPRcRBXZ-,1XI-1,B.1.02.03.04.05.06.07.08.09.010.0SYSTEMDESIGNANDOPERATION Turbine-Generator TurbineCondenser Condenser AirRemovalandOffgasSystemCirculating WaterSystemCondensate PumpsCondensate Demineralirer SystemCondensate TransferSystemFeedwater BoosterPumpsFeedwater PumpsFeedwater HeatersXI-9XZ-9XI-11XI-12XI-17XZ-17XI-18XI-19XI-20XI-20XZ-20C.D.SECTIONXZZSYSTEMANALYSISTESTSANDINSPECTIONS RADIOLOGICAL CONTROLSXZ-22XZ-25XII-11.01.11.21.2.11.2.21.2.32.02.12.1.12.1.22.1.32.1.42.22.2.12.2.22.2.32.2.42~32.3.12.3.23.04.04.1RAD10ACTZVE WASTESDesignBasesObjectives TypesofRadioactive WastesGaseousWastesLiquidWastesSolidWastesSystemDesignandEvaluation GaseousWasteSystemOffgasSystem,SteamPackingExhauster SystemBuildupVentilation SystemsStackLiquidWasteSystemLiquidWasteHandlingProcesses SamplingandMonitoring LiquidWastesLiquidWasteEquipment.

Arrangement LiquidRadioactive WasteSystemControlSolidWasteSystemSolidWasteHandlingProcesses SolidWasteSystemEquipment SafetyLimitsTestsandInspections WasteProcessSystemsXZI-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.'2.31'2.02.12.1.12.1.22.1~32.22.2.12.2.222'3.03~13.1.13.1.23.1.33.1.43'3.2.13.2.23.33.3.13.3'3.3.33.43.4.13.53.5.13.5.23.5.33.5'3.5.54.0FiltersEffluentMonitorsOffgasandStackMonitorsLiquidWasteEffluentMonitorRADIATION PROTECTION PrimaryandSecondary Shielding DesignBasesDesignReactorShieldWallBiological ShieldMiscellaneous Evaluation AreaRadioactivity Monitoring SystemsAreaRadiation Monitoring SystemDesignBasesDesignEvaluation AreaAirContamination Monitoring SystemDesignBasesDesignEvaluation Radiation Protection Facilities Laboratory, CountingRoomandCalibration Facilities ChangeRoomandLaundryFacilities Personnel Decontamination FacilityToolandEquipment Decontamination FacilityRadiation, ControlShielding AccessControlContamination ControlFacilityContamination ControlPersonnel Contamination ControlAirborneContamination ControlPersonnel.

DoseDeterminations Radiation DoseRadiation Protection Instrumentation CountingRoomInstrumentation PortableRadiation Instrumentation AirSamplingInstrumentation Personnel Monitoring Instruments Emergency Instrumentation TestsandInspections

~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.)

Section4.14.24.34'4.4'4.4.24.5Shielding AreaRadiation MonitorsAreaAirContamination MonitorsRadiation Protection Facilities Ventilation AirFlowsInstrument Calibration WellShielding Radiation Protection Instrumentation A.1.01.1.31.1~41.1.51'.61.22.02.13.04.0ORGANIZATION ANDRESPONSIBILITY Management andTechnical SupportOrganization NuclearDivisionVicePresident NuclearGeneration VicePresident NuclearEngineering VicePresident NuclearSafetyAssessment andSupportDirectorNuclearCommunications andPublicAffairsDirectorHumanResourceDevelopment Controller NuclearDivisionCorporate SupportDepartments Operating Organization PlantManagerQualityAssurance FacilityStaffQualifications SECTIONXIIICONDUCTOFOPERATIONS PacaeXII-44XII-44XII-45XII-45XII-45'XII-45XII-45XIII-1XIII-1XIII-1XIII-1XIII-1XIII-2'III-3 XIII-6XIII-7XIII-7XIII-7XIII-8XIII-8XIII-11XIII-12B.1.02.03.04.04.14.24.34.3.14.3.24.3.34.3.444.3.64.3.7QUALIFICATIONS ANDTRAININGOFPERSONNEL, ThisSectionDeletedThisSectionDeletedThisSectionDeletedTrainingofPersonnel=

GeneralResponsibility Implementation QualityForOperatorTrainingForMaintenance ForTechnicians ForGeneralEmployeeTraining/Radiation Protection andEmergency PlanForIndustrial SafetyForNuclearQualityAssurance ForFireBrigadeXIII-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/Licensed NRCOperatorRetraining Cooperative TrainingwithLocal,StateandFederalOfficials OPERATING PROCEDURES EMERGENCY PLANANDPROCEDURES SECURITYRECORDSOperations

.ControlRoomLogBookStationShiftSupervisor's BookRadwasteLogBookWasteQuantityLevelShippedMaintenance Radiation Protection Personnel ExposureBy-Product MaterialasRequiredby10CFR30MeterCalibrations StationRadiological Conditions in-Accessible AreasAdministration oftheRadiation Protection ProgramandProcedures Chemistry andRadiochemistry SpecialNuclearMaterials Calibration ofInstruments Administrative RecordsandReportsREVIEWANDAUDITOFOPERATIONS StationOperations ReviewCommittee FunctionSafetyReviewandAuditBoardFunctionReviewofOperating Experience INITIALTESTINGANDOPERATIONS PacaeXIII-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.1.0INITIALCRITICALITY ANDPOSTCRITICALZTY TESTSInitialFuelLoadingandNear-Zero PowerTestsat:Atmospheric PressureXIV-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'.12.13.12.23.12.33.12.43.133.14TitleGeneralRecpxirements GeneralProcedures CoreLoadingandCriticalTestProgramHeatupfromAmbienttoRatedTemperature GeneralTestsConducted FromZeroto100PercentInitialReactorRatingFull-Power Demonstration RunComparison ofBaseConditions Additional TestsatDesignRatingSAFETYANALYSISINTRODUCTION BOUNDARYPROTECTION SYSTEMSTransients Considered MethodsandAssumptions Transient AnalysisTurbineTripWithoutBypassLossof100'FFeedwater HeatingFeedwater Controller Failure-MaximumDemandControlRodWithdrawal ErrorMainSteamLineIsolation ValveClosure(WithScram)Inadvertent StartupofColdRecirculation LoopRecirculation PumpTripsRecirculation PumpStallRecirculation FlowController Malfunction

-Increasing FlowFlowController Malfunction-DecreaseFlowInadvertent Actuation ofOneSolenoidReliefValveSafetyValveActuation Objectives Assumptions andInitialConditions CommentsResultsFeedwater Controller Malfunction (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)Inadvertent Actuation ofOneBypassValveOneFeedwater PumpTripandRestartLossofMainCondenser VacuumLossofElectrical Load(Generator Trip)LossofAuxiliary PowerPressureRegulator Malfunction Instrument AirFailureD-CPowerInterruptions FailureofOneDiesel-Generator toStartPowerBusLossofVoltageSTANDBYSAFEGUARDS ANALYSISMainSteamLineBreakOutsidetheDrywellIdentification ofCausesAccidentAnalysisValveClosureInitiation Feedwater FlowCoreShutdownMixtureLevelSubcooled LiquidSystemPressureandSteam-Water MassMixtureImpactForcesCoreInternalForcesRadiological EffectsRadioactivity ReleasesMeteorology andDoseRatesComparison withRegulatory Guide1.5Loss-of-Coolant AccidentIntroduction InputtoAnalysisOperational andECCSInputParameters SingleFailureStudyonECCSManually-Controlled Electrically-Operated ValvesSingleFailureBasisPipeWhipBasisAppendixKLOCAPerformance AnalysisforP8DNB277AppendixKLOCAPerformance AnalysisPacaeXV-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.tieComputerCodesDescription ofModelChangesAnalysisProcedure AnalysisResultsAppendixKLOCAMAPLHGREvaluation withCoreSprayFlowThroughOneSpargerRefueling AccidentIdentification ofCausesAccidentAnalysisRadiological EffectsFissionProductReleasesMeteorology andDoseRatesComparison toRegulatory Guide1.25ControlRodDropAccidentIdentification ofCausesAccidentAnalysisDesignedSafeguards Procedural Safeguards Radiological EffectsFissionProductReleasesMeteorology andDoseRatesContainment DesignBasisAccidentOriginalRecirculation LineRuptureAnalysis-WithCoreSprayPurposeAnalysisMethodandAssumptions CoreHeatBuildupCoreSpraySystemContainment PressureImmediately Following BlowdownContainment SprayBlowdownEffectsonCoreComponents Radiological EffectsOriginalContainment DesignBasisAccidentAnalysis-WithoutCoreSprayPurposeCoreHeatupContainment ResponseFissionProductReleasefromtheFuelFissionProductReleasefromtheReactorandContainment Meteorology andDoseRatesDesignBasisReconstitution (DBR)Suppression ChamberHeatupAnalysisIntroduction InputtoAnalysisPRcRBXV-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.1.02.02.12.22.2.12.32.42.52.62.6.12.6.22.6.32.6.42.6.52.72.7.12.7.22.7.33.03.13.2TitleDBRSuppression ChamberHeatupAnalysisConclusions NewFuelBundleLoadingErroxAnalysisIdentification ofCausesAccidentAnalysisSafetyRequirements Meteorological ModelsUsedinAccidentAnalysesGroundReleasesStackReleasesVariability Exfiltration GroundDeposition ThyroidDoseWholeBodyDoseSPECIALTOPICALREPORTSREACTORVESSELApplicability ofFormalCodesandPertinent Certifications DesignAnalysisCodeApprovalAnalysisSteady-State AnalysisBasisforDetermining StressesPipeReactionCalculations Earthquake LoadingCriteriaandAnalysisReactorVesselSupportStressDesignCriteriaandAnalysisStrainSafetyMarginforReactorVesselsIntroduction StrainMarginFailureProbability ResultsofProbability AnalysisConclusions Components RequiredforSafeReactorShutdownDesignBasisLoadCombinations ExpectedStressandDeformation StressesandDeformations atWhichtheComponent isUnabletoFunctionandMarginofSafetyInspection andTestReportSummaryMaterials Fabrication andInspection PacaeXV-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.1.01.11.21.31.3.1TitleSurveillance Provisions CouponSurveillance ProgramPeriodicInspection PRESSURESUPPRESSION CONTAINMENT Applicability ofFormalCodesandPertinent Certifications DesignAnalysisCodeApprovalCalculations UnderRatedConditions UltimateCapability UnderAccidentConditions Capability toWithstand InternalMissilesandJetForcesFloodingCapabilities oftheContainment DrywellAirGapTestsandInspections Biological ShieldWallCompatibility ofDynamicDeformations Occurring intheDrywell,Torus,andConnecting VentPipesContainment Penetrations Classification ofPenetrations DesignBasesMethodofStressAnalysisLeakTestCapability FatigueDesignMaterialSpecification Applicable CodesJetandReactionLoadsDrywellShearResistance Capability andSupportSkirtJunctionStressesInspection andTestReportSummaryFabrication andInspection TestsConducted Discussion ofResultsResultsEffectofVariousTransients ENGINEERED SAFEGUARDS SeismicAnalysisandStressReportIntroduction Mathematical ModelMethodofAnalysisFlexibility or.Influence Coefficient MatrixPacaeXVI-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.1.01.11.1.11.1.21.21.32.02.1IF1-12.1.22.1.32.23.04.0NormalModeFrequencies andModeShapesTheSeismicSpectrumValuesDynamicModalLoadsModalResponseQuantities TheCombinedResponseQuantities BasicCriteriaforAnalysisDiscussion ofResultsContainment SpraySystemDesignAdequacyatRatedConditions GeneralCondensation andHeatRemovalMechanisms Mechanical DesignLoss-of-Coolant AccidentSummaryofTestResultsSprayTestsConducted DESIGNOFSTRUCTURES, COMPONENTS/

EQUIPMENT ANDSY'STEMSClassification andSeismicCriteriaDesignTechniques Structures SystemsandComponents PipeSupportsSeismicExposureAssumptions PlantDesignforProtection AgainstPostulated PipingFailuresinHighEnergyLinesInsidePrimaryContainment Containment Integrity AnalysisSystemsAffectedbyLineBreakEngineered Safeguards Protection OutsidePrimaryContainment BuildingSeparation AnalysisTornadoProtection XVZ-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.EXHIBITSCONTAINMENT DESIGNREVIEWUSAGEOFCODES/STANDARDS FORSTRUCTURAL STEELANDCONCRETESECTIONXVIIORIGINALENVIRONMENTAL STUDIESXVI-189XVI-227XVZ-238XVII-1A.1.02.0METEOROLOGX GeneralSynopticMeteorological FactorsXVII-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.1.02.03.03.13.23.2.13.2.23.2.33.3TitleMicrometeoro logyWindPatterns200-FootWindRosesEstimates ofWindsatthe350-FootLevelComparison BetweenTowerandSatellite WindsLapseRateDistributions Turbulence ClassesDispersion Parameters ChangesinDispersion Parameters Applications toReleaseProblemsConcentrations fromaGround-Level SourceConcentrations fromanElevatedSourceRadialConcentrations MonthlyandAnnualSectorConcentrations LeastFavorable Concentrations OveranExtendedPeriodGround-Level ReleaseElevatedReleaseMeanAnnualSectorDeposition DoseRatesfromaPlumeofGammaEmittersRADOSProgramCenterline DoseRatesSectorDoseRatesConcentrations fromaMajorSteamLineBreakConclusions LIMNOLOGYIntroduction SummaryReportofCruisesDilutionofStationEffluentinSelectedAreasDilutionofEffluentattheLakeSurfaceAbovetheDischarge DilutionofEffluentattheSiteBoundaries GeneralDilutionofEffluentattheEasternSiteBoundaryDilutionofEffluentWestoftheStationSiteDilutionofEffluentattheCityofOswegoIntakePacaeXVII-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.)

Section3.3.13.3.23.3.33.3.43.3.53.3.63.43.54.04.14.1.14.1.24.25.0TitleTiltingoftheIsothermal PlanesandSubsequent DilutionDilutionasaFunctionofCurrentVelocityPercentofTimeEffluentWillBeCarriedtotheOswegoAreaMixingwithDistanceOswegoRiverWaterasaBuffertoPreventEffluentFromPassingOvertheIntakeSummaryofAnnualDilutionFactorsfortheCityofOswegoIntakeDilutionofEffluentattheNineMilePointIntakeSummaryofDilutionintheNineMilePointAreaPreliminary StudyofLakeBiotaOffNineMilePointBiological StudiesPlanktonStudyBottomStudySummaryofBiological StudiesConclusions PacaeXVZI-123XVII-124XVII-127XVII-127XVII-127XVII-127XVZI-128XVII-128XVII-129XVII-129XVII-129XVII-129XVII-130XVZZ-130C.1.02.03.03.13.24.04.14.24.34.44.5SECTIONXVZZIEARTHSCIENCESIntroduction Additional Subsurface StudiesConstruction Experience StationAreaIntakeandDischarge TunnelsCorrelation WithPreviousStudiesGeneralGeological Conditions Hydrological Conditions Seismological Conditions Conclusion HUMANFACTORSENGINEERING/SAFETY PARAMETER DISPLAYSYSTEMXVZI-132XVII-132XVII-132XVII-138XVII-138XVII-139XVII-140XVII-140XVII-140XVII-142XVZI-142XVZZ-142XVZZZ-1A.1.02.03.03.13.23.33.43.5DETAILEDCONTROLROOMDESIGNREVIEWGeneralPlanningRequirements fortheDCRDRDCRDRReviewProcessOperatorSurveyHistorical ReviewTask'nalysis ControlRoomInventory ControlRoomSurveyXVIIZ-1XVIII-1XVIII-2XVIII-2XVIII-2XVIII-2XVIII-3XVIZZ-3XVIII-4UFSARRevision12XXV'.3.3.

June1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)

SectionTitle~acae3.63.73.84.04.14.24.2.14.2.2.5.06.06.16.26.36.47.0Verification ofTaskPerformance Capabilities Validation ofControlRoomFunctions

~Compilation ofDiscrepancy FindingsAssessment andImplementation Assessment Implementation Integrated CosmeticPackageFunctional FixesReporting Continuing HumanFactorsProgramFixVerifications Multidisciplinary ReviewTeamAssessments HumanFactorsManualforFutureDesignChangeOutstanding HumanFactorsItemsReferences XVIII-4XVIII-4XVIZZ-5XVZII-5XVIII-5XVIZI-5XVIZ1-6XVIII-7XVIII-7XVIII-8XVIII-8XVZII-8XVIII-8XVIII-8XVIII-9B.1.02.03.04.05.05.15.1.15.1.25.1.35.1.45.25.2.15.2.25.35.3.15.3.25.4SAFETYPARAMETER DISPLAYSYSTEMIntroduction totheSafetyParameter DisplaySystemSystemDescription RoleoftheSPDSHumanFactorsEngineering Guidelines HumanFactorsEngineering Principles AppliedtotheSPDSDesignNUREG-0737, Supplement 1,Section4.1.aConciseDisplayCriteriaPlantVariables RapidandReliableDetermination ofSafetyStatusAidtoControlRoomPersonnel NUREG-0737, Supplement 1,Section4.1.bConvenient LocationContinuous DisplayNUREG-0737,

'Supplement 1,Section4.1.cProcedures andTrainingIsolation ofSPDSfromSafety-Related SystemsNUREG-0737, Supplement 1,Section4.1.eXVZII-11XVIII-11XVIII-11XVIII-12XVIII-13XVIII-13XVIZZ-13XVIII-13XVIII-13XVIIZ-14XVIII-14XVIII-14XVIII-14XVZII-15XVIII-15XVIII-15XVIII-15XVIII-16UFSARRevision12xxixJune1994 NineMilePointUnit1FSARTABLEOFCONTENTS(Cont'd.)

Section5.4.15.4.25.56.06.16.27.0TitleIncorporation ofAcceptedHumanFactorsEngineering Principles Information CanbeReadilyPerceived andComprehended NUREG-0737, Supplement 1,Section4.1.f,Sufficient Information Procedures Operating Procedures Surveillance Procedures References PacaeXVIII-16XVIII-17XVIII-17XVIII-17XVIII-17XVIII-18XVIII-19APPENDIXAAPPENDIXBUnusedNIAGARAMOHAWKPOWERCORPORATION QUALITYASSURANCE PROGRAMTOPICALREPORT(NMPC-QATR-1)

~NINEMILEPOINTNUCLEARSTATIONUNITS1AND2OPERATIONS PHASEUFSARRevision12XXZJune1994 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,Instrument andEquipment SymbolsStationLocationAreaMapSiteTopography Population Distribution WithinaTwelveMileRadiusoftheStationCountiesandTownsWithinTwelveMilesoftheStation1980Population Distribution WithinaFiftyMileRadiusoftheStationPlotPlanStationFloorPlan-Elevation 225-6StationFloorPlan-Elevations 237and250StationFloorPlan-Elevation 261StationFloorPlan-Elevations 277and281StationFloorPlan-Elevations 281and291StationFloorPlan-Elevations 298and300StationFloorPlan--Elevations 317-6and318StationFloorPlan-Elevations 320,333-8,340and369SectionBetweenColumnRows7'and8SectionBetweenColumnRows12and14TurbineBuildingVentilation SystemLaboratory andRadiation Protection FacilityVentilation SystemControlRoomVentilation SystemWasteDisposalBuildingVentilation SystemWasteDisposalBuildingExtension Ventilation SystemOffgasBuildingVentilation SystemTechnical SupportCenterVentilation SystemCirculating WaterChannelsUnderScreenandPumpHouse-NormalOperation PacaeI-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-6xMt1RCirculating WaterChannelsUnderScreenandPumpHouse-SpecialOperations IntakeandDischarge TunnelsPlanandProfileStack-PlanandElevation StackFailure-CriticalDirections

/LimitingPower/Flow LineFigureDeletedFigureDeletedGE11FuelAssemblyDesignTypicalControlRod-Isometric FigureDeletedControlRodPositioning WithinCoreCellGE8X8EBControlRodPositioning WithinCoreCellWithTypicalGE11FuelAssemblyControlRodDriveandHydraulic SystemControlRodDriveAssemblyTypicalControlRodtoDriveCoupling-Isometric ReactorVesselIsometric ReactorEmergency CoolantSystemReactorVesselNozzleLocation.ReactorVesselSupportFigureDeletedPressureVesselEmbrittlement TrendFigureDeletedFigureDeletedEmergency Condenser SupplyIsolation Valves(Typicalof2)DrywellandSuppression ChamberElectrical Penetrations

-HighVoltageElectrical Penetrations

-LowVoltagePipePenetrations

-HotTypicalPenetration ForInstrument LinesReactorBuildingDynamicAnalysis-Acceleration East-West Direction

~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-17 VI-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-8TitleReactorBuildingDynamicAnalysisDeflections East-West Direction ReactorBuildingDynamicAnalysis-Elevation vs.BuildingShearEast-West Direction ReactorBuildingDynamicAnalysisElevation vs.BuildingMomentEast-West Direction ReactorBuildingDynamicAnalysis-Acceleration North-South Direction ReactorBuildingDynamicAnalysis-Deflections North-South Direction ReactorBuildingDynamicAnalysis-Elevation vs.BuildingShear-North-South Direction ReactorBuildingDynamicAnalysis'-

Elevation vs.BuildingMoment-North-South Direction ReactorSupportDynamicAnalysisElevation vs.Acceleration ReactorSupportDynamicAnalysis-Elevation vs.Deflection ReactorSupportDynamicAnalysis-Elevation vs.ShearReactorSupportDynamicAnalysis-Elevation vs.MomentTypicalDoorSealsDetailsofReactorBuildingAirLocksInstrument LineIsolation ValveArrangement TypicalFlowCheckValveIsolation ValveSystemDrywellCoolingSystemReactorBuildingVentilation SystemCoreSpraySystemCoreSpraySpargerFlow,PerSparger,forOneCoreSprayPumpandOneToppingPumpContainment SpraySystemFigureDeletedFigureDeletedFigureDeletedLiquidPoisonSystemMinimumAllowable SolutionTemperature FigureDeletedPacaevx-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-19TitleTypicalControlRodVelocityLimiterControlRodHousingSupportHydrogenFlammability LimitsCombustible GasControlSystemH,-O,SamplingSystemH,-O,Concentrations inContainment Following LOCAN,AddedbyCADOperation Following LOCAContainment PressurewithCADOperation

-ZeroContainment LeakageFeedwater DeliveryCapability (ShaftDrivenPump)Protective SystemFunctionReactorProtection SystemElementary DiagramProtective SystemTypicalSensorArrangement Recirculation FlowandTurbineControlNeutronMonitoring Instrument RangesSourceRangeMonitor(SRM)SRMDetectorLocationIntermediate RangeMonitor(IRM)IRMCoreLocationLPRMLocationWithinCoreLatticeLPRMandAPRMCoreLocationLocalPowerRangeMonitor(LPRM)andAveragePowerRangeMonitors(APRM)APRMSystem-TypicalTripLogicf'rAPRMScramandRodBlockTraversing In-CoreProbeRodPatternDuringStartupRadialPowerDistribution forControlRodPatternShowninFigureVXII-16DistancefromWorstControlRodtoNearestActiveIRMMonitorMeasuredResponseTimeofIntermediate RangeSafetyInstrumentation PacaeVII-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-11TitleEnvelopeofMaximumAPRMDeviation byFlowControlReduction inPowerEnvelopeofMaximumAPRMDeviation forAPRMTrackingWithOnUnitsControlRodWithdrawal MainSteamLineRadiation MonitorReactorBuildingVentilation Radiation MonitorOffgasSystemRadiation MonitorEmergency Condenser VentRadiation MonitorStackEffluentandLiquidEffluentRadiation MonitorsContainment SprayHeatExchanger RawWaterEffluentRadiation MonitorContainment Atmospheric Monitoring SystemRodWorthMinimizer A.C.StationPowerDistribution ControlandInstrument PowerTraysBelowElevation 261TraysBelowElevation 277TraysBelowElevation 300DieselGenerator LoadingFollowing Loss-of-Coolant AccidentDieselGenerator LoadingforOrderlyShutdownReactorShutdownCoolingSystemReactorCleanupSystemControlRodDriveHydraulic SystemReactorBuildingClosedLoopCoolingSystemTurbineBuildingClosedLoopCoolingSystemServiceWaterSystemDecayHeatGeneration vs.DaysAfterReactorShutdownSpentFuelStoragePoolFiltering andCoolingSystemBreathing, Instrument, andServiceAirReactorRefueling SystemPictorial CaskDropProtection SystemPacaeVIIX-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'teSteamFlowandReheaterVentilation SystemExtraction SteamFlowMainCondenser AirRemovalandOffgasSystemCirculating WaterSystemCondensate FlowCondensate TransferSystemFeedwater FlowSystemRadioactive WasteDisposalSystemNMPCUpperManagement NuclearOrganization NineMilePointNuclearSiteOrganization NuclearEngineering Organization NuclearSafetyAssessment andSupportOrganization SafetyOrganization StationTransient DiagramFigureDeletedFigureDeletedFigureDeletedPlantResponsetoLossof100FFeedwater HeatingFigureDeletedPlantResponsetoFeedwater Controller Failure(GE11atEOC)PlantResponsetoFeedwater Controller Failure(GE11atEOCExtendedLoadLineLimit)FigureDeletedFigureDeletedFigureDeletedFigureDeletedStartupofColdRecirculation Loop-PartialPowerRecirculation PumpTrips(1Pump)Recirculation PumpTrips(5Pumps)Recirculation PumpStall~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-50TitleFlowController Malfunction (Increased Flow)FlowController Malfunction Decreasing FlowInadvertent Actuation ofOneSolenoidReliefValveFigureDeletedFigureDeletedFeedwater Controller Malfunction-ZeroFlowTurbineTripWithPartialBypassIntermediate PowerTurbineTripWithPartialBypassInadvertent Actuation ofOneBypassValveOneFeedwater PumpTripandRestartLossofElectrical LoadLossofAuxiliary PowerPressureRegulator Malfunction MainSteamLineBreak-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-Coolant Accident-WithCoreSprayCladdingTemperature Loss-of-Coolant AccidentDrywellPressureLoss-of-Coolant AccidentSuppression ChamberPressureLoss-of-Coolant AccidentContainment Temperature

-WithCoreSprayLoss-of-Coolant AccidentCladPerforation WithCoreSprayContainment DesignBasisCladTemperature Response-WithoutCoreSprayContainment DesignBasisMetal-Water ReactionContainment DesignBasisCladPerforation WithoutCoreSprayContainment DesignBasisContainment Temperature

-WithoutCoreSprayDBRAnalysisSuppression PoolandWetwellAirspaceTemperature Response-Containment SprayDesignBasisAssumption DBRAnalysisSuppression PoolandWetwellAirspaceTemperature Response-EOPOperation Assumptions ReactorBuildingModelExfiltration vs.WindSpeed-Northerly WindReactorBuildingDifferential PressureExfiltration vs.WindSpeed-Southerly WindReactorBuilding-Isometric ReactorBuilding-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-184 xv-185.XV-186XV-188XV-189XV-190O.UFSARRevision12XXXViiiJune1994 NineMilePointUnit1FSARLISTOFFIGURES(Cont'd.)

FigureNumberTitlePacaeXV-68XV-69XV-70XV-71XV-72ReactorBuilding-PaneltoConcreteSectionsReactorBuilding-Expansion JointSectionsReactorBuildingExfiltration-Northerly WindReactorBuildingExfiltration-Southerly WindReactorBuildingDifferential PressureXV-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-21SeismicAnalysisofReactorVesselGeometric andLumpedMassRepresentation ReactorSupportDynamicAnalysis-Elevation vs.MomentReactorSupportDynamicAnalysisElevation vs.ShearReactorSupportDynamicAnalysis-Elevation vs.Deflection ReactorSupportDynamicAnalysisElevation vs.Acceleration FigureDeletedFigureDeletedFigureDeletedReactorVesselSupportStructure StressSummaryThermalAnalysisFailureProbability DensityFunctionAdditionStrainsPast4%RequiredtoExceedDefinedSafetyMarginLossofCoolantAccident-Containment PressureNoCoreorContainment

.SpraysFigureDeletedDrywelltoConcreteAirGapTypicalPenetrations Biological ShieldWallConstruction DetailsVentPipeandSuppression ChamberPrimaryContainment SupportandAnchorage

.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-49TitleShearResistance Capability-InsideDrywellShearResistance Capability-OutsideDrywellDrywell-SupportSkirtJunctionStressesPointLocationforContainment SpraySystemPipingHeatExchanger toDrywellComparison ofStaticandDynamicStresses(PSI)SeismicConditions-Containment SpraySystemHeatExchanger toDrywellConduction inaDropletLossofCoolantAccident-Containment PressureLossofCoolantAccident-Containment PressureNozzleSprayTest-PressureDropof80psigNozzleSprayTest-PressureDropof80psigNozzleSprayTest-PressureDropof30psigNozzleSprayTest-PressureDropof30psigSeismicAnalysis-ReactorBuildingDynamicAnalysis-DrywellReactorSupportStructure

-SeismicSeismicAnalysis-WasteBuildingSeismicAnalysis-Screenhouse SeismicAnalysis-TurbineBuilding(NorthofRowC)SeismicAnalysis-TurbineBuilding(SouthofRowC)SeismicAnalysis-ConcreteVentilation StackReactorBuildingMathematical Model(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-'64WindRosesforAugustWindRosesforSeptember WindRosesforOctoberWindRosesforNovemberWindRosesforDecemberWindRosesfor'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-38TitleLapseRatesbyWindSpeedandTurbulence ClassesforJanuary'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforFebruary'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforMarch'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforApril'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforMay'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforJune'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforJuly'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforAugust'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforSeptember

'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforOctober'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforNovember'3-'4LapseRatesbyWindSpeedandTurbulence ClassesforDecember'3-'4SectorMapCenterline Concentrations Turbulence ClassICenterline Concentrations-Turbulence ClassIICenterline Concentrations-Turbulence ClassIIICenterline Concentrations-Turbulence ClassIVCenterline Concentrations Turbulence ClassIZBecomingClassIVat2kmandClassIIat23kmCenterline Concentrations-Turbulence ClassIVBecomingClassIIat16km~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-59Centerline Concentrations-Turbulence ClassIVBecomingClassIIat2kmRadialConcentrations

-Turbulence ClassIRadialConcentrations

-Turbulence ClassIIRadialConcentrations

-Turbulence ClassIllRadialConcentrations

-Turbulence ClassIVRadialConcentrations

-Turbulence ClassIIBecomingClassZVat2kmandClassIIat23kmRadialConcentrations

-Turbulence ClassZVBecomingClassIzat16kmRadialConcentrations

-Turbulence ClassZVBecomingClassZZat2kmCenterline GammaDoseRates-Turbulence ClassICenterline GammaDoseRates-Turbulence ClassZZCenterline GammaDoseRatesTurbulence ClassIZICenterline GammaDoseRates-Turbulence ClassIVCenterline GammaDoseRatesTurbulence ClassIzBecomingClassZVat2kmandClassIzat23kmCenterline GammaDoseRatesTurbulence ClassIVBecomingClassIIat16kmCenterline GammaDoseRates-Turbulence ClassIVBecomingClassIIat2kmAssumedConcentration andDoseRateDistributions ClosetotheElevatedSourceGammaDoseRateasaFunctionofGyat1kmFromtheSourceSoutheastern LakeOntarioDilutionofRisingPlumeEstimated LakeCurrentsatCoolingWaterDischarge Temperature ProfilesinanEastwardCurrentattheOswegoCityWaterIntakeXVZI-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)Attenuation CurvesPacaeXVII-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-3Title1980Population andPopulation DensityforTownsandCitiesWithin12MilesofNineMile.Point-Unit1CitiesWithina50-mileRadiusoftheStationWithPopulations over10,000RegionalAgricultural UseRegionalAgricultural Statistics

-CattleandMilkProduction Industrial FirmsWithin8km(5mi)ofUnit1PublicUtilities inOswegoCountyPublicWaterSupplyDataforLocations WithinanApproximate 30-MileRadiusRecreational AreasintheRegionReactorCoolantSystemDataOperating CyclesandTransient AnalysisResultsFatigueResistance AnalysisCodesforSystemsConnected totheReactorCoolantSystemTimetoAutomatic BlowdownDrywellPenetrations Suppression ChamberPenetrations ReactorCoolantSystemIsolation ValvesPrimaryContainment Isolation Valves-LinesEnteringFreeSpaceoftheContainment TableDeletedSeismicDesignCriteriaforIsolation ValvesXnitialTestsPriortoStationOperation Performance TestsAssociation BetweenPrimarySafetyFunctions andEmergency Operating Procedures ListofEOPKeyParameters TypeandInstrument CategoryforNMP1RG1.97'Variables PacaeIx-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~iceMagnitude andDutyCycleofMajorStationBatteryLoadsFlowsandActivities ofMajorSourcesofGaseousActivityQuantities andActivities ofLiquidRadioactive WastesAnnualSolidWasteAccumulation andActivityLiquidWasteDisposalSystem-MajorComponents SolidWasteDisposalSystem-MajorComponents Occupancy TimesGammaEnergyGroupsAreaRadiation MonitorDetectorLocations PacaeIX-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-Reference Unit1Transients Considered TripPointsforProtective Functions TableDeletedInstrument AirFailureBlowdownRates'odineConcentrations Fractional Concentrations inCloudsMainSteamLineBreakAccidentDosesSignificant InputParameters totheLoss-of-Coolant AccidentAnalysisCoreSpraySystemFlowPerformance AssumedinLOCAAnalysisECCSSingleValveFailureAnalysisSingleFailuresConsidered inLOCAAnalysisTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedTableDeletedXV-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-2TitleTableDeletedTableDeletedAnalysisAssumptions ForNineMilePoint-1Calculations TableDeletedTableDeletedTableDeletedTableDeletedReactorBuildingAirborneFissionProductInventory StackDischarge RatesFuelHandlingAccidentDoses(REM)FissionProductReleaseAssumptions Atmospheric Dispersion andDoseConversion FactorsEffectonDoseofFactorsUsedintheCalculations NobleGasReleaseHalogenReleaseWettingofFuelCladdingbyCoreSprayAirborneDrywellFissionProductInventory ReactorBuildingAirborneFissionProductInventory StackDischarge RatesAirborneDrywellFissionProductInventory ReactorBuildingAirborneFissionProductInventory StackDischarge RatesSignificant InputParameters totheDBRContainment Suppression ChamberHeatupAnalysisDownwindGroundConcentrations MaximumGroundConcentrations Diversity Factorsfor"LeastFavorable" GroundConcentrations fromStackRelease,forGroundRelease,forMaximumGroundConcentrations ReactorBuildingLeakagePathsCodeCalculation SummarySteadyState-(100%FullPowerNormalOperation)

Pertinent StressesorStressIntensities PacaeXV-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-28TitleListofReactions forReactorVesselNozzlesEffectofValueofInitialFailureProbability SingleTransient EventforReactorPressureVessel.Postulated EventsMaximumStrainsfromPostulated EventsCoreStructure AnalysisRecirculation LineBreakCoreStructure Analysis-SteamLineBreakDrywellJetandMissileHazardAnalysisDataDrywellJetandMissileHazardAnalysisResultsStressDuetoDrywellFloodingAllowable WeldShearStressLeakRateTestResultsOverpressure Test-PlateStressesStressSummaryHeatTransferCoefficients asaFunctionofDropDiameterHeatTransferCoefficients asaFunctionofPressureRelationship BetweenParticleSizeandTypeofSprayPatternAllowable StressesforFloorSlabs,Beams,Columns,Walls,Foundations, etc.Allowable StressesforStructural SteelAllowable Stresses-ReactorVesselConcretePedestalDrywell-AnalyzedDesignLoadCombinations Suppression Chamber-AnalyzedDesignLoadCombinations ACICode505Allowable StressesandActualStressesforConcreteVentilation StackAllowable StressesforConcreteSlabs,Walls,Beams,Structural Steel,andConcreteBlockWallsSystemLoadCombinations HighEnergySystems-InsideContainment PacaeXVI-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-OutsideContainment SystemsWhichMayBeAffectedbyPipeWhipCapability toResistWindPressureandWindVelocityPacaeXVI-166XVI-167XVI-185XVZI-1XVZI-2XVZI-3XVZI-4XVII-5XVII-6XVII-7XVII-8XVII-9XVIZ-10XVZI-11XVII-12XVII-13XVZI-14XVII-15XVII-16XVIZ-17XVII-18XVZI-19XVII-20XVII-21Dispersion andAssociated Meteorological Parameters RelationofSatellite andNineMPointWindsFrequency ofOccurrence ofLapseRates-1963and1964RelationBetweenWindDirection RangeandTurbulence ClassesStackCharacteristics Distribution ofTurbulence ClassBySectorsSectorConcentrations

-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

-1963-64SectorGGroundHeightEstimates oftheLeastFavorable 30Daysin100Y'earsConcentrations intheLeastFavorable CalendarMonth-1963-64AnnualAverageSectorDeposition Rates(Vg=0.5cm/sec)AnnualAverageSectorDeposition Rates(Vg=2.5cm/sec)Principal Radionuclides inGaseousWasteReleaseCorrection FactorstoObtainAdjustedCenterline DoseRatesforSectorEstimates AnnualAverageGammaDoseRatesDilutionCalculation forEastwardCurrentsBasedonWaterAvailability SPDSParameter SetPacaeXVII-82xvII-84XVII-85XVII-88xvII-89XVII-92XVII-104XVII-105XVII-119XVIII-20UFSARRevision12June1994 SECTIONIINTRODUCTION ANDSUMMARYThisreportissubmitted inaccordance with10CFRPart50.71(e)entitled"Periodic UpdatingofFinalSafetyAnalysisReports"forNiagaraMohawkPowerCorporation's NineMilePointUnit1NuclearStation.TheStationislocatedonthesoutheast shoreofLakeOntario,inOswegoCounty,NewYork,7milesnortheast ofthecityofOswego.

I-2A.PRINCIPAL DESIGNCRITERIAThefollowing paragraphs describing theprincipal designcriteriaareorientedtowardthetwenty-seven criteriaissuedbytheUSAEC.1.0GeneralTheStationisintendedasahighloadfactorgenerating facilitytobeoperatedasanintegralpartoftheNiagaraMohawksystem.Therecirculation flowcontrolsystemdescribed inSectionVIIIcontributes tothisobjective byproviding arelatively fastmeansforadjusting theStationoutputoverapreselected powerrange.Overallreliability, routineandperiodictestrequirements, andotherdesignconsiderations mustalsobecompatible withthisobjective.

Carefulattention hasbeengiven.tofabrication procedures andadherence tocoderequirements.

Therigidrequirements ofspecificportionsofvariouscodeshavebeenarbitrarily appliedtosomesafety-related systemstoensurequalityconstruction insuchcaseswherethecompletecodedoesnotapply.Forpiping,theASAB31.1-1955 Codewasusedandwhereexceptions weretaken,safetyevaluations wereperformed todocumentthatanadequatemarginofsafetywasmaintained.

WPeriodictestprogramshavebeendeveloped forrequiredengineered safeguards equipment.

Thesetestscovercomponent testingsuchaspumpsandvalvesandfullsystemtests,duplicating ascloselyaspossibletheaccidentconditions underwhichagivensystemmustperform.2.0BuildinsandStructures TheStationplotplan,designandarrangement ofthevariousbuildings andstructures aredescribed inSectionIII.Principal structures andequipment whichmayserveeithertopreventaccidents ortomitigatetheirconsequences aredesigned, fabricated anderectedinaccordance withapplicable codestowithstand themostsevereearthquake, floodingcondition, windstorm, icecondition, temperature andotherdeleterious naturalphenomena whichcanbeexpectedtooccuratthesite.'SAECPressRelease8-252,"GeneralDesignCriteriaforNuclearPowerPlantConstruction Permits,"

November22,1965.Revision9June1991 I-33.0ReactorAdirect-cycle boilingwatersystemreactor,described inSectionIV,isemployedtoproducesteam(1030psiginreactorvessel,956psigturbineinlet)foruseinasteam-driven turbine-generator.

Theratedthermaloutputofthereactoris1850Mw(t).b.Thereactorisfueledwithslightlyenricheduraniumdioxidecontained inZircaloy-clad fuelrodsdescribed inSectionIV.Selectedfuelrodsalsoincorporate smallamountsofgadolinium asburnablepoison.C~Toavoidfueldamage,theMinimumCriticalPowerRatioismaintained greaterthantheSafetyLimitCriticalPowerRatio.d.Thefuelrodcladdingisdesignedtomaintainitsintegrity throughout theanticipated fuellifeasdescribed inSectionIV.Fissiongasreleasewithintherodsandotherfactorsaffecting designlifeareconsidered forthemaximumexpectedburnup.e.Thereactorandassociated systemsaredesignedsothatthereisnoinherenttendencyforundampedoscillations.

Astability analysisevaluation isgiveninSectionIV.Heatremovalsystemsareprovidedwhicharecapableofsafelyaccommodating coredecayheatunderallcrediblecircumstances, including isolation fromthemaincondenser andloss-of-coolant, fromthereactor.Eachdifferent systemsoprovidedhasappropriate redundant features.

Independent auxiliary coolingmeansareprovidedtocoolthereactorunderavarietyofconditions.

Thenormalauxiliary coolingmeansduringshutdownandrefueling istheshutdowncoolingsystemdescribed inSectionX-A.Aredundant emergency coolingsystem,described inSectionV-E,isprovidedtoremovedecayheatintheeventthereactorisisolatedfromthemaincondenser whilestillunderpressure.

Additional coolingcapability isalsoavailable fromthehigh-pressure coolantinjection systemandthefireprotection system.Revision9June1991 g,h.Redundant andindependent corespraysystemsareprovidedtocoolthecoreintheeventofaloss-of-coolant accident.

Automatic depressurization isincludedtorapidlyreducepressuretoassistwithcoresprayoperation (seeSectionVII-A).Operation ofthecorespraysystemassuresthatanymetal-water reactionfollowing apostulated loss-of-coolant accidentwillbelimitedtolessthan1percentoftheZircaloyclad.Reactivity shutdowncapability isprovidedtomakeandholdthecoreadequately subcritical, bycontrolrodaction,fromanypointintheoperating cycleandatanytemperature downtoroomtemperature, assumingthatanyonecontrolrodisfullywithdrawn andunavailable foruse.Thiscapability isdemonstrated inSectionIV-B.Aphysicaldescription ofthemovablecontrolrodsisgiveninSectionIV-B.Thecontrolroddrivehydraulic systemisdescribed inSectionX-C.Theforceavailable toscramacontrolrodisapproximately 3000poundsatthebeginning ofascramstroke.Thisiswellinexcessofthe440-pound forcerequiredintheeventoffuelchannelpinchingofthecontrolrodbladeduringaloss-of-coolant accidentasdiscussed inSectionXV.Evenwithscramaccumulator failureaforceofatleast1100poundsfromreactorpressureactingaloneisavailable withreactorpressures inexcessof800psig.Redundant reactivity shutdowncapability isprovidedindependent ofnormalreactivity controlprovisions.

Thissystemhasthecapability, asshowninSectionVII-C,tobringthereactortoacoldshutdowncondition, Kf<0.97,atanytimeinthecorelife,independenAf thecontrolrodsystemcapabilities-.

Aflowrestrictor inthemainsteamlinelimitscoolantlossfromthereactorvesselintheeventofamainsteamlinebreak(SectionVII-F).4.0ReactorVessela0Thereactorcoreandvesselaredesignedtoaccommodate trippingoftheturbinegenerator, lossofpowertothereactorrecirculation systemandothertransients andmaneuvers whichcanbeexpectedwithoutcompromising safetyandwithoutfueldamage.

NineMilePointUnit1FSARAbypasssystemhavingacapacityofapproximately 40percentofturbinesteamflowforthethrottlevalveswideopencondition partially mitigates theeffectsofsuddenloadrejection.

Thisandothertransients andmaneuvers whichhavebeenanalyzedaredetailedinSectionXV.b.Separatesystemstopreventseriousreactorcoolantsystemoverpressure areincorporated inthedesign.Theseincludeanoverpressure scram,solenoid-actuated reliefvalves,safetyvalvesandtheturbinebypasssystem.Ananalysisoftheadequacyofreactorcoolant.systempressurereliefdevicesisincludedinSectionV-C.c~Powerexcursions whichcouldresultfromanycrediblereactivity additionaccidentwillnotcausedamage,eitherbymotionorrupture,tothepressurevesselorimpairoperation ofrequiredsafeguards systems.Themagnitude ofcrediblereactivity additionaccidents iscurtailed bycontrolrodvelocitylimiters(SectionVII-D),byacontrolrodhousingsupportstructure (SectionVII-E),andbyprocedural controlssupplemented byarodworthminimizer (SectionVIII-C).Powerexcursion analysesforcontrolroddropoutaccidents areincludedinSectionXV.d.Thereactorvessel=willnotbesubstantially pressurized untilthevesselwalltemperature isinexcessofNDTT+60'F.TheinitialNDTTofthereactorvesselmaterialisnogreaterthan.40'F.

ThechangeofNDTTwithradiation exposurehasbeenevaluated inaccordance withRegulatory Guide1.99,Revision2.Vesselmaterialsurveillance samplesarelocatedwithinthereactorvesseltopermitperiodicverification ofmaterialproperties withexposure.

5.0 Containment

a~Theprimarycontainment, including thedrywell,pressuresuppression chamber,associated accessopeningsandpenetrations, isdesigned,

.fabricated anderectedtoaccommodate, withoutfailure,thepressures andtemperatures resulting fromorsubsequent tothedouble-ended ruptureorequivalent failureofanycoolantpipewithinthedrywell.UFSARRevisionI-5June1993 I-6Theprimarycontainment isdesignedtoaccommodate thepressures following aloss-of-coolant accidentincluding thegeneration ofhydrogenfromametal-water reaction.

Pressuretransients including hydrogeneffectsarepresented insectionXV.TheinitialNDTTforthe.primarycontainment systemisabout-20FandisnotexpectedtoincreaseduringthelifetimeoftheStation.Thesestructures aredescribed inSectionVI-A,BandC.Additional details,particularly thoserelatedtodesignandfabrication areincludedinSectionXVI.Provisions aremadefortheremovalofheatfromwithintheprimarycontainment, forreasonable protection ofthecontainment fromfluidjetsormissilesandsuchothermeasuresasmaybenecessary tomaintaintheintegrity ofthecontainment systemaslongasnecessary following aloss-of-coolant accident.

I<Redundant containment spraysystems,described inSectionVII,pumpwaterfromthesuppression chamberthroughindependent heatexchangers tospraynozzleswhichdischarge intothedrywellandsuppression chamber.Watersprayedintothedrywellisreturnedbygravitytothesuppression chambertocompletethecoolingcycle.Studiesperformed toverifythecapability of=thecontainment systemtowithstand potential fluidjetsandmissilesaresummarized inSectionXVI.Provision ismadeforperiodicintegrated leakagerateteststobeperformed duringeachrefueling andmaintenance outage.Provision isalsomadeforleaktestingpenetrations andaccessopeningsandforperiodically demonstrating theintegrity ofthereactorbuilding.

Theseprovisions arealldescribejl.

in.SectionVI-F.Thecontainment systemandallothernecessary engineered safeguards aredesignedandmaintained suchthatoff-sitedosesresulting frompostulated

.accidents arebelowthevaluesstatedin10CFR100.ThcanalysisresultsaredetailedinSectionXV.Doubleisolation valvesareprovidedonalllinesdirectlyenteringtheprimarycontainment freespace orpenetrating theprimarycontainment andconnected tothereactorcoolantsystem.Periodictestingofthesevalveswillassuretheircapability toisola':catalltimes.Theisolation valvesystemisdiscussed indetailinSectionVI-D.

I-7Thereactorbuildingprovidessecondary containment whenthepressuresuppression systemisinserviceandservesastheprimarycontainment barrierduringperiodswhenthepressuresuppression system.,isopen,suchasduringrefueling.

Thisstructure isdescribed inSectionVI-C.Anemergency ventilation system(SectionVII-H)providesameansforcontrolled releaseofhalogensandparticulates viafiltersfromthereactorbuildingtothestackunderaccidentconditions.

6.0 ControlandInstrumentation

a~b.TheStationisprovidedwithacontrolroom(SectionIII-B)whichhasadequateshielding andotheremergency featurestopermitoccupancy duringallcredibleaccidentsituations.

Interlocks orotherprotective featuresareprovidedtoaugmentthereliability ofprocedural controlsinpreventing seriousaccidents.

Interlock systemsareprovidedwhichblockorpreventrodwithdrawal fromamultitude ofabnormalconditions.

The-control rodblocklogicisshowninFiguresVIII-6andVIII-S,respectively, fortheSRMandIRMneutroninstrumentation.

Inthepowerrange,APRMinstrumentation providesbothcontrolrodandrecirculation flowcontrolblocks,asshowninFigureVIII-14.Reactivity excursions involving thecontrolrodsareeitherprevented ortheirconsequences substantially mitigated byacontrolrodworthminimizer (SectionVIII-C.4.0) whichsupplements procedural controlsinavoidingpatternsofhighrodworths,anLPRMneutronmonitoring andalarmsystem(SectionVIII-C.1.1.3) andacontrolrodpositionindicating system(SectionIV-B.6.0) bothofwhichenabletheoperatortoobserverodmovement, thusverifying hisactions.Acontrolrodovertravel positionlightverifiesthatthebladeiscoupledtoawithdrawn controlroddrive.Arefueling platformoperation interlock isdiscussed inSectionXV,Refueling

Accident, which,alongwithotherprocedures andsupplemented byautomatic interlocks, servestopreventcriticality accidents intherefueling mode.

cAcoldwateradditionreactivity excursion isprevented bytheprocedures andinterlocks described inSectionXV,StartupofColdRecirculation Loop(Transient Analysis).

Security(keycardandalarms)andprocedural controlsforthedrywellandreactorbuildingairlocksareprovidedtoensurethatcontainment integrity ismaintained.

Areliable, duallogicchannelreactorprotection systemdescribed inSectionVIII-Aisprovidedtoautomatically initiateappropriate actionwhenevervariousparameters exceedpresetlimits.Eachlogicchannelcontainstwosubchannels withcompletely independent sensors,eachcapableoftrippingthelogicchannel.Atripofone-of-two subchannels ineachlogicchannelresultsinareactorscram.Thetripineachlogicchannelmayoccurfromunrelated parameters, i.e.,highneutronfluxinonelogicchannelcoupledwithhigh-pressure intheotherlogicchannelwillresultinascram.Thereactorprotective systemcircuitry failsinadirection tocauseareactorscramintheeventoflossofpowerorlossofairsupplytothescramsolenoidvalves.Periodictestingandcalibration ofindividual subchannels isperformed toassuresystemreliability.

Theabilityofthereactorprotection systemtosafelyterminate avarietyofStationmalfunctions isdemonstrated inSectionXV.d.Redundant sensorsandcircuitry areprovidedfortheactuation ofallequipment requiredtofunctionunderpost-accident conditions.

Thisredundancy isdescribed inthevarioussectionsofthetextdiscussing systemdesign.,7.0Electrical PowerSufficient normalandstandbyauxiliary sources.ofelectrical powerareprovidedtoassureacapability forpromptshutdownandcontinued maintenance oftheStationinasafecondition underallcrediblecircumstances.

Thesefeaturesarediscussed inSectionIX.8.0Radioactive WasteDisosala~Gaseous,liquidandsolidwastedisposalfacilities aredesignedsothatdischarge ofeffluents areinaccordance with10CFR20and1QCFR50,AppendixI.Thefacilitydescriptions aregiveninSectionXII-Awhilethedevelopment ofappropriate limitsiscoveredinSectionII.

I-99.0b.Gaseousdischax'ge fromtheStationisappropriately monitored, asdiscussed inSectionVIIIandautomatic isolation featuresareincorporated tomaintainreleasesbelowthelimitsof10CFR20and10CFR50,AppendixI.ShieldinandAccessContxolRadiation shielding andaccesscontrolpatternsaresuchthatdoseswillbelessthanthosespecified in10CFR20.Thesefeaturesaredescribed inSectionXII-B.10.0FuelHandlinandStoraeAppropriate fuelhandlingandstoragefacilities whichprecludeaccidental criticality andprovideadequatecoolingforspentfuelaredescribed inSectionX.

NineMilePointUnit1FSARB.CHARACTERISTICS Thefollowing isasummaryofdesignandoperating characteristics.

1.0SiteLocationSizeofSiteSiteandStationOwnership NetElectrical Output2.0ReactorOswegoCounty,NewYorkState900AcresNiagaraMohawkPowerCorp.615MW(Maximum)

Reference RatedThermalOutputDomePressureTurbineInletPressureTotalCoreCoolantFlowRateSteamFlowRate3.0CoreCircumscribed CoreDiameterActiveCoreHeight+Assembly4.0FuelAssembl1850MW1030psig956psig67.5x10~lb/hr7.29x10'lb/hr167.16in171.125inNumberofFuelAssemblies FuelRodArrayFuelRodPitchCladdingMaterialFuelMaterialActiveFuelLengthCladdingOutsideDiameterCladdingThickness FuelChannelMaterial532SRLR('iReference 3Reference 3UO~andUO~-Gdz03 Reference 3>Reference 3Reference 3Reference 3(4)GEFuelBundleDesigns,GeneralElectricCompanyProprietary, NEDE-31152P, February1993.GENE23A7170,Revision3,"Supplemental ReloadLicensing ReportforNMP1,Reload12,Cycle11,"May1994.UFSARRevision13I-10June1995 NineMilePointUnit1FSAR5.0ControlSstemNumberofMovableControlRodsShapeofMovableControlRodsPitchofMovableControlRodsControlMaterialinMovableControlRodsTypeofControlDrivesControlofReactorOutput129Cruciform 12.0inB4C-70%Theoretical Density;HafniumBottomEntry,Hydraulic ActuatedMovementofControlRodsandVariation ofCoolantFlowRate6.0CoreDesinand0eratinConditios7.0MaximumLinearHeatGeneration RateHeatTransferSurfaceAreaAverageHeatFlux-RatedPowerXnitialCriticalPowerRatioforMostLimitingTransients CoreAverageVoidFraction-CoolantwithinAssemblies CoreAverageExitQuality-CoolantwithinAssemblies DesinPowerPeakinCoreOperating LimitsReport50I496119,830Btu/hr-ft~

CoreOperating LimitsReport0.28010.715%FactorTotalPeakingFactorP8x8R-3.00GE8x8EB-2.90GE11-2.94(')-2.62+Maximumtotalpeakingfactorfortheportionofthebundlecontaining partlengthrods(latticetypes1522,1519and1520perReference 3).Maximumtotalpeakingfactorfortheregionabovethepartlengthrods(latticetypes1521,1523and1524perReference 3).UFSARRevision13I-11June1995 NineMilePointUnit1FSAR8.0NuclearDesinDataAverageInitialVolumeMetricEnrichment Beginning ofCycle11-CoreEffective Multiplication andControlSystemWorth-NoVoids,20C<4>Uncontrolled FullyControlled Strongest ControlRodOutReference 31.0980.9580.981StandbyLiquidControlSystemCapability:

ShutdownMargin(cR)20CXeonFreeSRLR~~SRLR~~9.0eactorVesselInsideDiameterInternalHeightDesignPressure17ft-9in63ft-10in1250psigat575F10.0CoolantRecirculation LoosLocationofRecircu-lationLoopsNumberofRecircula-tionLoopsandPumpsPipeSize11.0PrimarContainment Containment'rywe11 28inTypeDesignPressureofDrywellVesselDesignPressureofSuppression ChamberVesselDesignLeakageRatePressureSuppression 62psig35psig0.5weightpercentperdayat35psigUFSARRevision13I-,12June1995 NineMilePointUnit1FSAR12.0SecondarContainment TypeInternalDesignPressureDesignLeakageRateReinforced concreteandsteelsuperstructure withmetalsiding40lb/ft'00%

freevolumeperdaydischarged viastackwhilemaintaining 0.25-inwaternegativepressureinthereactorbuildingrelativetoatmosphere 13.0Structural DesinSeismicGroundAcceleration Sustained WindLoadingControlRoomShielding 0.11g125mph,300ftabovegroundlevelDosenottoexceedhourlyequivalent (basedon40-hrweek)ofmaximumpermissible cgxarterly dosespecified in10CFR2014.0StationElectrical SstemIncomingPowerSourcesOutgoingPowerLinesOnsitePowerSourcesProvidedTwo115-kVtransmission linesTwo345-kVtransmission linesTwodieselgenerators Twosafety-related StationIbatteries Onenonsafety 125-Vdcbatterysystem15.0ReactorInstrumentation SstemLocationofNeutronMonitorSensorsIn-coreRangesofNuclearInstrumentation:

FourStartupRangeMonitorsEightIntermediate RangeMonitors120PowerRangeMonitorsSourceto0.01%ratedpowerandto10%withchamberretraction 0.0003%to10%ratedpower1%to125%ratedpowerUFSARRevision12I-13June1994 16.0ReactorProtection SstemNumberofChannelsinReactorProtection SpstemNumberofChannelsReguiredtoScramorEffectOtherProtective Functions NumberofSensorsperMonitored VariableineachChannel(Minimumforscramfunction)

IDENTIFICATION OFCONTRACTORS TheGeneralElectricCompanywasengagedtodesign,fabricate anddeliverthenuclearsteamsupplysystem,turbine-generator andothermajorelementsandsystems.GeneralElectricalsofurnished thecompletecoredesignandnuclearfuelsupplyfortheinitialcoreandiscurrently furnishing replacement cores.NiagaraMohawkPowerCorporation, actingasitsownarchitect

engineer, specified andprocuredtheremaining systemsandcomponents including thepressuresuppression containment system,andcoordinated thecompleteintegrated Station.StoneandWebsterEngineering Corporation wasengagedbyNiagaraMohawktomanagefieldconstruction.

Currently, NiagaraMohawkutilizesvariouscontractors toassistincontinuous stationmodifications.

GENERALCONCLUSIONS Thefavorable sitecharacteristics, criteriaanddesignrequirements ofallthesystemsrelatedtosafety,thepotential consequences ofpostulated accidents andthetechnical competence oftheapplicant anditscontractors assurethattheNineMilePointUnit1NuclearStationcanbeoperatedwithoutendangering thehealthandsafetyofthepublic.