ML15266A273

Rev. 0 to Defueled Safety Analysis Report, UFSAR to DSAR Conversion Matrix

ML15266A273
Person / Time
Site:	Vermont Yankee
Issue date:	09/01/2015
From:	Entergy Nuclear Operations
To:	Office of Nuclear Reactor Regulation
Shared Package
ML15266A267	List: BVY 15-046, Rev. 0 to Defueled Safety Analysis Report, Drawing G-200347, Circulating Water System Aerating Structure-MAS & Reinf. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report - List of Effective Pages BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, DSAR Changes BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, DSAR Drawing List BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing 5920-00526, Process Radiation Monitoring System BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing 5920-06245, Plan Showing Property Lines & Plan Site. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191142, Site Plot Plan. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191144, General Arrangement Turbine Building Ground Floor Plan. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191148, Rev. 23, General Arrangement Reactor Building Plans Sheet 1. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191149, Rev. 27, General Arrangement Reactor Building Plans Sheet 2. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191150, Rev. 20, General Arrangement Reactor Building Section. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191151, Rev 19, General Arrangement Radwaste Building Plans. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191152, Rev. 14, General Arrangement Radwaste Building Section. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 100, Flow Diagram Service Water System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191159, Rev. 92, Flow Diagram Service Water System. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 24, Flow Diagram Instrument Air System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 4 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 5 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 6 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 7 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 25, Flow Diagram Instrument Air System. Sheet 8 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 31, Flow Diagram Instrument Air System. Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191160, Rev. 37, Flow Diagram Instrument Air System. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191161, Rev. 22, Flow Diagram, Maxe-up Water Treatment System. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191163, Rev. 51, Flow Diagram Fire Protection System Inner Loop. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191164, Rev. 29, Flow Diagram Sampling System. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191165, Rev. 46, Flow Diagram Sampling System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191173, Rev. 12, Flow Diagram Fuel Pool Cooling & Clean Up System. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191173, Rev. 42, Flow Diagram Fuel Pool Cooling & Cleanup System. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191177, Rev. 23, Flow Diagram Radwaste Systems. Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191177, Rev. 44, Flow Diagram Radwaste Systems. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191177G, Rev. 28, Flow Diagram Radwaste Systems. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191238, Rev. 38, HVAC - Flow Diagram Reactor Building. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191254, Rev. 43, HVAC Heating Flow Diagram & Boiler Room Layout. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191298, Rev. 5, Main One Line Wiring Diagram. Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191299, Rev. 37, 4KV Auxiliary One Line Diagram. BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191300, Rev. 27, 480V Auxiliary One Line Wiring Diagram Swgr BUS-8 MCC-8A, 8C. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191300, Rev. 38, 480V, Auxiliary One Line Diagram MCC-8B, MCC-8E, MCC-89B. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 30, 480V Aux. One Line Diagram Swgr BUS-9, MCC-9A, 9C. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191301, Rev. 39, 480V Aux. One Line Diagram MCC-9B, 9D, 89A. Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 120/240V Vital AC and Instrument AC One Line Diagram, Sheet 4 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 125V DC One Line Diagram, Sheet 3 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, 24V DC Neutron Monitoring & 120V AC RPS One Line Diagram, Sheet 5 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191372, Rev. 72, 125VDC One Line Wiring Diagram. Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191451, Circulating Water System Intake Structure-M, Sheet 1 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191452, Circulating Water System Intake Structure-V, Sheet 2 BVY 15-046, Vermont Yankee Nuclear Power Station, Rev. 0 to Defueled Safety Analysis Report, Drawing G-191453, Circulating Water System Intake Structure-M, Sheet 3 ... further results
References
BVY 15-046
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Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015

1.0INTRODUCTION

AND

SUMMARY

1.1 Modifiedsection1.1,Applicant,changedtitletoIntroduction,includedinformationregardingoriginandpurposeofDefueledSafetyAnalysisReport,combinedselectinformationapplicableinthedefueledstatefromsections1.1.1,Applicant,1.1.2,Engineer Construction,1.1.3,NuclearSteamSupplySystemSupplier,and1.1.4,TurbineGeneratorSupplier,deletedhistoricalandobsoleteinformation.

1.1 1.1.1 Deletedsection1.1.1,Applicant,movedrelevantinformationtoSection1.1,Introduction 1.1.2 Deletedsection1.1.2,EngineerConstruction,movedrelevantinformationtoSection1.1,Introduction 1.1.3 Deletedsection1.1.3,NuclearSteamSupplySystemSupplier,movedrelevantinformationtoSection1.1,Introduction 1.1.4 Deletedsection1.1.4,TurbineGeneratorSupplier,movedrelevantinformationtoSection1.1,Introduction 1.2FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therrefore,manyofthedefinitionsinthissectionarenolongerapplicable.

TheSSCclassificationprocessdescribedinUFSARsection1.4,ClassificationofBWRSystems,Criteria,andRequirementsisnotapplicableinthedefueledstateandhasbeendeleted.ManyofthedefinitionsprovidedinthissectiondefinetermsrelatedtotheSSCClassificationprocessandtherefore,arenolongerapplicable Additionally,manyofthedefinitionsprovidedinthissectionarealreadydefinedinmoreappropriatedocumentation,includingTechnicalSpecificationsandtheTechnicalRequiementsManual.Finally,manyofthedefinitionsprovidedinthissectionarenotusedintheDSAR.Therefore,theinformationinthissectionishistorcalandobsoleteandmaybedeleted.Table1.2.1(A)DeleteTable1.2.1(A).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinTable1.2.1(A)isnolongerrequiredandisobsolete.Table1.2.1(B)DeleteTable1.2.1(B).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinTable1.2.1(B)isnolongerrequiredandisobsolete.Table1.2.1(C)DeleteTable1.2.1(C).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinTable1.2.1(C)isnolongerrequiredandisobsolete.Table1.2.1(D)DeleteTable1.2.1(D).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinTable1.2.1(D)isnolongerrequiredandisobsolete.Table1.2.1(E)DeleteTable1.2.1(E).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinTable1.2.1(E)isnolongerrequiredandisobsolete.Table1.2.1(F)DeleteTable1.2.1(F).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinTable1.2.1(F)isnolongerrequiredandisobsolete.Figure1.2.1 DeleteFigure1.2.1.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowe classificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinFigure1.2.1isnolongerrequiredandisobsolete.

1.0INTRODUCTION

AND

SUMMARY

Introduction NuclearSteamSupplySystemSupplier TurbineGeneratorSupplier DEFINITIONS VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary RelationshipBetweenSafetyActionandProtectiveAction ActualPlantDesignandOperation,SafetyConsiderations ActualPlantDesignandOperation,PowerGenerationConsiderations ActualPlantDesignandOperation,SafetyConsiderations ActualPlantDesignandOperation,SafetyConsiderations ActualPlantDesignandOperation,SafetyConsiderations ActualPlantDesignandOperation,SafetyConsiderations DSARSection PROJECTIDENTIFICATION Applicant EngineerConstruction VYDSAR Page1of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure1.2.2 DeleteFigure1.2.2.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowe classificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinFigure1.2.2isnolongerrequiredandisobsolete.Figure1.2.3 DeleteFigure1.2.3.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowe classificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Consequently,theinformationinFigure1.2.3isnolongerrequiredandisobsolete.1.3 1.3.1 1.ModifiedParagraph1.3.1toreflectdefueledstateandassociatedchangeispurposeoftheSAR.1.1 1.3.2 DeletedSection1.3.2,RadioactiveMaterialBarrierConcept,providedamethodologyforrankingSSCswithdepthofinformationpresentedregardingeachSSCdeterminedbasedonrelationshipwiththeradioactivebarrierconcept.Althoughthisapproachwasusedforoperation,theapproachisnotapplicablefollowingcertificationofpermanentdefueling,isobsoletepostdefueling,andwasnotusedinthedevelopmentoftheDSAR.1.3.4FormatOrganizationofSections InformationinthissectionwasdeletedsinceitoutlinedtheformatandpresentationfortheUFSAR.TheDSARformatandpresentationanddepthofmaterialpresentedwasbasedonpredecessorDSARsandRegGuide1.184.Deletesection1.3.3,OrganizationofContents,todeleteincorporationbyreferenceofthefollowingspecialreferencessincetheyarenolongerapplicablefollowingcertificationofcessationofoperationsandpermanentdefueling.

APED5286DesignBasisforCriticalHeatFluxinBoilingWaterReactors(September1966).

APED5450,DesignProvisionsforIn ServiceInspection(April1967)

APED5453VibrationAnalysisandTestingofReactorInternals(April1967).

APED5448AnalysisMethodsofHypotheticalSuperPromptCriticalReactivityTransientsinLargePowerReactors(April1968).

APED5458EffectivenessofCoreStandbyCoolingSystemsforGeneralElectricBoilingWaterReactors(March1968).

APED5460DesignandPerformanceofGeneralElectricBoilingWaterReactorJetPumps(September1968).

APED5454MetalWaterReactionsEffectsonCoreCoolingandContainment(March1968).

APED5654ConsiderationsPertainingtoContainmentInerting(August1968).

APED5706InCoreNeutronMonitoringSystemforGeneralElectricBoilingWaterReactors(November1968).

APED5698SummaryofResultsObtainedfromaTypicalGeneralElectricBoilingWaterReactorStartupandPowerTestProgram(February1969).

APED5736GuidelinesforDeterminingSafeTestIntervalsandRepairTimesforEngineeredSafeguards(April1969).

APED5750DesignandPerformanceofGeneralElectricBWRMainSteamIsolationValves(March1969).

APED5758QualitySystemSummaryforBWRNuclearSystemsProjects(July1969).

APED5703DesignandAnalysisofControlRodDriveReactorVesselPenetrations(November1968).

APED5652StabilityandDynamicPerformanceoftheGeneralElectricBoilingWaterReactor(April1969).

APED5446ControlRodVelocityLimiter(March1967).

APED5449ControlRodWorthMinimizer(March1967).

APED5447DepressurizationPerformanceofHPCI(June1969).

APED5455TheMechanicalEffectsofReactivityTransients(January1968).

APED5528NuclearExcursionTechnology(August1967).

APED5640XenonConsiderationsinDesignofLargeBoilingWaterReactors(June1968).

NEDO10017FieldTestingRequirementsforFuel,CurtainsandControlRods(June1969).

NEDO10029AnAnalyticalStudyofBrittleFractureofGEBWRVesselSubjecttotheDesignBasisAccident(July1969).

NEDO10045ConsequencesofaSteamLineBreakinaGeneralElectricBoilingWaterReactor(July1969).

NEDO10173CurrentStateofKnowledgeHighPerformanceBWRZircaloyCladUO2Fuel(May1970).

NEDO10179EffectsofCladdingTemperatureandMaterialonECCSPerformance(June1970).

NEDO10139ComplianceofProtectionSystemstoBWRIndustryCriteria;GeneralElectricNuclearSteamSupplySystem(June1970).

NEDO10174ConsequencesofaPostulatedFlowBlockageIncidentinaBoilingWaterReactor(May1970).

NEDO10208EffectsofFuelRodFailureonECCSPerformance(August1970).

NEDO10189AnAnalysisofFunctionalCommonModeFailuresinGEBWRProtectionandControlInstrumentation(July1970).

SafeShutdownCapabilityAnalysis(Section10.11.3)RadioactiveMaterialBarrierConcept1.3.3OrganizationofContents RelationshipBetweenProtectiveFunctionsandProtectiveActions RelationshipsBetweenDifferentTypesofSystems,ActionsandObjectives METHODSOFTECHNICALPRESENTATION Purpose ThissectionwasdeletedsinceitoutlinedtheformatandpresentationfortheUFSAR.TheDSARformatandpresentationanddepthofmaterialpresentedwasbasedonpredecessorDSARsandRegGuide1.184.Introduction Page2of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.3.5 Deletedsection1.3.5,PowerLevelBasisforAnalysisofAbnormalOperationalTransientsandAccidents.Informationinthissectionisnotapplicablefollowingcertificationofpermanentdefueling.Sincethereactormaynolongerbeoperatedandnuclearfuelmaynolongerbeemplacedorretainedinthereactorvessel,informationregardingthepowerlevelbasisforanalysisofAOTsandaccidentsisnolongerapplicable.

Figure1.31Delete,referencenolongerrequiredsinceentiresectionhasbeendeleted.1.4 DeleteSection1.4,CLASSIFICATIONOFBWRSYSTEMS,CRITERIA,ANDREQUIREMENTS 1.4.1 DeleteSection1.4.1,Introduction.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheclassificationprocessdescribedinthissectionallowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.1.4.2 DeleteSection1.4.2,ClassificationBasis.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.1.4.3 DeleteSection1.4.3,UseoftheClassificationBasis.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,thesectiondescribinguseoftheclassificationbasisisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Table1.4.1 DeleteTable1.4.1,ConceptforClassificationofBWRSystems,CriteriaandRequirements.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,thetablelistingthesafet considerationsandpowergenerationconsiderationsforPlannedOperation,AbnormalOperatingTransientsandAccidentsisnolongerrequired.1.5 1.Deletedparagraphinsection1.5whichstatedthatdesigncriteriaaregroupedaccordingtotheclassificationplangiveninTable1.2.1,sincetable1.2.1andtheclassificationplanarenotapplicabletothedefueledstate.Obsoleteinformation 2.Consolidateddesigncriteriawhichremainapplicableinthedefueledstateintoappropriategeneralsections.1.5.1 2.Section1.5.1,GeneralCriteria,General,deletedcriteriawhichstatesthatthestationshallbedesigned,fabricatedanderectedsothatitcanbeoperatedtoproduceelectricalpowerinasafe,reliableandeffecientmanner.Obsoleteinformation 3.Section1.5.1,GeneralCriteria,Nuclear,deletedparagraph3pertainingtothecriteriaforthereactorcoreandreactivitycontrolsystems.Notapplicableinthedefueledstate,obsoleteinformation

4.Consolidatedremaininginformationintoonesectiontitled"DesignCriteria"anddeletedsection1.5.1 1.5.2 4.Deletedsection1.5.2,PowerGenerationDesignCriteria,(PlannedOperations).Notapplicableinthedefueledstate,obsoleteinformation 1.5.3 5.Deletedsection1.5.3,PowerGenerationDesignCriteria,(AbnormalOperationalTransients.Notapplicableinthedefueledstate,obsoleteinformation.

1.5.4 6.Deletedsection1.5.4,NuclearSafetyDesignCriteria(PlannedOperation).Notapplicableinthedefueledstate,obsoleteinformation 1.5.5 7.Deletedsection1.5.5,NuclearSafetyDesignCriteria,(AbnormalOperationalTransients).Notapplicableinthedefueledstate,obsoleteinformation 1.5.6 8.DeletedSection1.5.6,NuclearSafetyDesignCriteria(Accidents).Notapplicableinthedefueledstate,obsoleteinformation 1.5.7 DeletedSection1.5.7,SpecialSafetyDesignCriteria.Thissectionliststhegeneraldesigncontrolforreactivitycontrol.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlDesignCriteriaarenolongerapplicable.

1.6 1.3 1.6.1 1.3.1 1.6.1.1 NoChange 1.3.1.1 1.6.1.2 NoChange 1.3.1.2 1.3.2 1.6.1.3 Deletesection1.6.1.3,Notapplicableinthedefueledstate,obsoleteinformationEXCEPTsection1.6.1.3.1,RenamedsectiontoNuclearFuelandControlRods.FuelwillbestoredinthespentfuelpooluntiltransferredtothesiteISFSI,controlrodswillbestoredeitherinthespentfuelpoolorremaininstalledinthereactorvessel 1.3.2.1 1.6.1.4 Deletethissection,Notapplicableinthedefueledstate,obsoleteinformation DESIGNCRITERIA FACILITYDESCRIPTION General SITEANDENVIRONS FACILITYARRANGEMENT FuelStorageandHandling NuclearFuelandControlRods CLASSIFICATIONOFBWRSYSTEMS,CRITERIA,ANDREQUIREMENTS Introduction ClassificationBasis UseoftheClassificationBasis ConceptforClassificationofBWRSystems,CriteriaandRequirements PRINCIPALDESIGNCRITERIA POWERCONVERSIONSYSTEMS PowerLevelBasisforAnalysisofAbnormalOperationalTransientsandAccidents PipingandInstrumentSymbols,G 191155 SITEANDENVIRONS FACILITYARRANGEMENT NUCLEARSYSTEM NuclearSafetyDesignCriteria(AbnormalOperationalTransients)

NuclearSafetyDesignCriteria(Accidents)

SpecialSafetyDesignCriteria PLANTDESCRIPTION General GeneralCriteria PowerGenerationDesignCriteria(PlannedOperation)

PowerGenerationDesignCriteria(AbnormalOperationalTransients)

NuclearSafetyDesignCriteria(PlannedOperation)

1.2 Page3of153

Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR1.6.1.5ElectricalPowerSystems Modifytoremovereferencetopowergenerationatthestation,referencetothemaingeneratorandexcitationsystem,thestationmaintransformer,andthe345kVtransmissionlines.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,theequipmentmentionedaboveisnolongerrequiredandisobsolete.1.3.5.1 1.6.1.6 Modifytoremovereferencetomethodsusedtocontrolreleaseofradioactivematerialtowithinapplicablelimits.Listingofthemethodsusedisexcessdetailandisnotreqired.1.3.31.6.1.6.1LiquidRadwasteSystem Modifytoremovereferencetodischargeofradioactiveprocessliquidwasatethroughthecirculatingwaterdischargecanalanddilutionwithcondensereffluentcirculatingwaterorriverwate r Thestatement"inaccordancewithapplicablepermits"ensuresthatVYdischargeswillcomplywithallapplicablerequirements.Informationremovedisconsideredexcessivedetail.1.3.3.21.6.1.6.2SolidRadwasteSystem Modifytoremoveexcessivedetailregardingmethodsforpreparingandshippingsolidradioactivewaste.AllVYsolidradwasteshippedwillbeinaccordancewithapplicablerequirements.

1.3.3.3 1.6.1.6.3 GaseousRadwasteSystem Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2 1.6.2.1 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.2 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.3 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.4 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.5 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.6 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.7 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.8 Deletethissection.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)syste m andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioacti v decaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,thesecondarycontainmentfunctionisnolongerrequired.1.6.2.9 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.10 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.11 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolong e possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheCoreStandbyCoolingSystemsarenolongerrequired.InformationregardingtheCoreStandbyCoolingSystemsisobsoletedandmaybedeleted.1.6.2.12 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolong e possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheResidualHeatRemovalSystem(ContainmentCooling)arenolongerrequired.InformationregardingtheResidualHeatRemovalSystem(ContainmentCooling)isobsoletedandmaybedeleted.1.6.2.13 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,thefunctionsprovidedbytheControlRodVelocityLimitersarenolongerapplicable.

1.6.2.14 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctions,inxludingthecontrolrods,arenolongerrequired.Consequently,thefunctionsprovidedbytheControlRodDriveHousingSupportsarenolongerapplicable.

1.6.2.15 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation ElectricalPowerSystems LiquidRadwasteSystem SolidRadwasteSystem RadioactiveWasteManagement SecondaryContainment MainSteamLineIsolationValves MainSteamLineFlowRestrictors CoreStandbyCoolingSystems ResidualHeatRemovalSystem(ContainmentCooling)ControlRodVelocityLimiter NeutronMonitoringSystem ControlRodDriveSystem NuclearSystemPressureReliefSystem ReactorCoreIsolationCoolingSystem PrimaryContainment PrimaryContainmentandReactorVesselIsolationControlSystem RadioactiveWasteSystems NuclearSafetyandEngineeredSafeguards ReactorProtectionSystem ControlRodDriveHousingSupports StandbyGasTreatmentSystem Page4of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.6.2.16 ModifySection1.6.2.16,StationDieselGeneratorSystemtoremovereferencetooperatingandaccidentconditions,andreflectthatthediesel generatorsnowsupplyback uppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDiesel Generatorsareonlyrequiredtosupplybackuppowertoensurethesafestorageofirradiatedfuel.1.3.5.1 1.6.2.17 ModifySection1.6.2.17,125VoltBatterySystem,toremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsofthe125VDCsystemarenolongerrequired.1.3.5.1 1.6.2.18 ModifySection1.6.2.18StationServiceWaterSystem,toremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystemnowsuppliesonlycoolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel.1.3.5.2 1.6.2.19 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation SeeSection10.9 1.6.2.20 Deletesection1.6.2.20,MainSteamLineRadiationMonitoringSystem.TheMainSteamLineRadiationMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLineRadiationMonitoringSystemarenolongerrequired.MainSteamLineRadiationMonitoringSysteminformationisobsolete.1.6.2.21 Modifyasindicatetoreflectdefueledstate 1.3.4.1 1.6.3 1.6.3.1 Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.3.2 Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4 1.6.4.1 Delete 1.6.4.1.1 ReactorManualControlSystem Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.2 RecirculationFlowControlSystem Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.3 NeutronMonitoringSystem Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.4 RefuelingInterlocks Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.5 RefuelingVesselInstrumentation Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.6 ProcessComputerSystem Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.2 DeleteSection1.6.4.2 1.6.4.2.1 PressureRegulatorandTurbineGeneratorControl Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.2.2 FeedwaterSystemControl Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.3 1.3.4 ElectricalPowerSystems ElectricalPowerSystems ServiceWaterSystem ReactorBuildingVentilationRadiationMonitoringSystem ReactorBuildingVentilationRadiationMonitoringSystem SpecialSafetySystems StandbyLiquidControlSystem StationEquipmentOutsidetheMainControlRoom ProcessControlandInstrumentation StationServiceWaterSystem ReactorBuildingClosedCoolingWaterSystem MainSteamLineRadiationMonitoringSystem StationDieselGeneratorSystem StationBatterySystem RadiationMonitoringandControl NuclearSystemProcessControlandInformation PowerConversionSystemsProcessControlandInstrumentation RadiationMonitoringandControl Page5of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.6.4.3.1 ProcessRadiationMonitoring DeletedreferencetoAOGSystemOffGas,PrimaryContainmentSystemPurgeVentilationSystemDischarge,StandbyGasTreatmentsystemdischarge,CirculatingWaterDischarge,CoolingTower.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheaboveRadiationMonitoringSystemarenolongerrequired.InformationprovidedregardingthoseRadiationMonitoringSystemsisobsolete.1.3.4.2 1.6.4.3.2 AreaRadiationMonitors Section1.6.4.3.2,AreaRadiationMonitorsmodifiedtoremoveexcessinformationregardinglocationsofarearadiationmonitorsintheReactorBuilding.1.3.4.3 1.6.4.3.3 LiquidRadwasteSystemControl Section1.6.4.3.3,LiquidRadwasteSystemcontroleditorialchangesonly.1.3.3.2 1.6.4.3.4 SolidRadwasteControl NochangestoSolidRadwasteControl,informationconsolidatedintoSolidRadwasteSystem.1.3.3.3 1.6.4.3.5 GaseousRadwasteSystemControl DeleteSection1.6.4.3.5,GaseousRadwasteSystemControl.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheGaseousRadwasteSystemarenolongerrequired.InformationprovidedregardingtheGaseousRadwasteSystemisobsolete.1.6.5 1.3.5 1.6.5.1 Modifiedtoreflectthatfacilitypowerissuppliedfrom115kVswydsviaSUtransformers 1.3.5.1 1.6.5.2 Deleted,Notapplicableinthedefueledstate,obsoleteinformation.SeeSection10.10 1.6.5.3 DeleteSection1.6.5.3,AlternateCoolingSystem.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,theinformationprovidedregardingtheAlternateCoolingSystemisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.1.6.5.4 Modifiedasindicatedtoremoveexcessspecificity 1.3.5.3 1.6.5.5 EditorialChangesonly 1.3.5.4 1.6.5.6 ModifiedtoaccommodatetransferofirradiatedfueltotheISFSI.RemovedstatementthatirradiatedfuelistransferredunderwatersincetransfertotheISFSIdoesnotoccurunderwater.SeeSection10.3 Removedthereferencetospentfuel,sincenotallirradiatedfuelis"spent".1.3.2.2 1.6.5.7 Editorialchangestoreflectchangestosection10.5 1.3.2.3 1.6.5.8 DeletedreferencetothePrimaryContainmentAtmospehericControlSystemsincethatsystemisnolongerrequired 1.3.5.5 1.3.7 1.6.5.9 EditorialChangesonly 1.3.7.1 1.6.5.10 EditorialChangesonly 1.3.7.2 1.6.5.11 EditorialChangesonly 1.3.3.1 1.6.5.12 EditorialChangesonly 1.3.5.6 1.6.5.13 Deleted,Notapplicableinthedefueledstate,obsoleteinformation SeeSection10.20 1.6.5.14 EditorialChangesonly 1.3.6 1.6.6 1.3.8 FireProtectionSystem ProcessRadiationMonitoring AreaRadiationMonitors LiquidRadwasteSystemSolidRadwasteSystem AuxiliarySystems ElectricalPowerSystems FireProtectionSystem NormalAuxiliaryACPower TurbineBuildingClosedCoolingWaterSystem AlternateCoolingSystem AuxiliarySystems PotableandSanitaryWaterSystem EquipmentandFloorDrainageSystems ProcessSamplingSystem FuelPoolCoolingandClean upSystem ServiceandInstrumentAirSystems MakeupWaterTreatmentSystem Heating,Ventilating,andAirConditioningSystems NewandSpentFuelStorage Heating,Ventilating,andAirConditioningSystems IrradiatedFuelStorage StandbyFuelPoolCoolingandDemineralizerSystem ServiceandInstrumentAirSystems StationWaterPurification,TreatmentandStorage MakeupWaterTreatmentSystem PotableandSanitaryWaterSystem EquipmentandFloorDrainageSystems ProcessSamplingSystem StationCommunicationsSystem Post AccidentSamplingSystem StationCommunicationsSystem StationShielding,AccessControlandRPProcedures Shielding,AccessControlandRadiationProtectionProcedures Page6of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR1.6.6.1Deletedreferencetotable1.6.1,shieldingincontainmentrequiredtomakeradiationlevelsonthestationconsistentwithoperationalrequirements1.3.8.1 1.6.6.2 Sectionmodifiedtopresentsummarytoreflectconditionsinpermanentlydefueledstateandtoeliminateduplicationbetween1.6.6andsection12.3,RadiationShieldingand13.4RadiationProtection.Consolidatedsectionwithsection1.6.6.1.1.6.6.3 Sectionmodifiedtopresentsummarytoreflectconditionsinpermanentlydefueledstateandtoeliminateduplicationbetween1.6.6andsection12.3,RadiationShieldingand13.4RadiationProtection.Consolidatedsectionwithsection1.6.6.1.1.6.6.4 Sectionmodifiedtopresentsummarytoreflectconditionsinpermanentlydefueledstateandtoeliminateduplicationbetween1.6.6andsection12.3,RadiationShieldingand13.4RadiationProtection.Consolidatedsectionwithsection1.6.6.1.1.6.7 NoChange 1.3.9 1.6.8 DeleteSection1.6.8.Thissectionisredundanttotheregulatoryrequirementtosubmitsummariesof50.59evaluations.

1.6.9 DeleteSection1.6.9,References.References1and2weredeletedinearlierUFSARrevisions,Reference3,VYC 2423,UpdatedVitalAreaDoseforEPU,documentedareviewofplantshieldingforvitalequipmentandpostaccidentproceduralcontrolsinresponsetoNUREG0737,ItemII.B.2.2.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedinreference3isnolongerapplicableandisobsolete.Sincenoadditionalreferencesexist,thissectionmaybedeleted.Table1.6.1 DeleteTable1.6.1,ShieldingDesignBasisLimitations.Referencetothistablehasbeendeletedfromsection1.6.6.1,nootherreferencestothistableexistinthissection.Therefore,thistablemaybedeleted.Figure1.6 1 DeleteFigure1.6 1,ReactorHeatBalance,RatedPower.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theinformationprovidedbyfigure1.6 1,ReactorHeatBalance,RatedPower,isnolongerapplicable.Thisinformationisobsolete.Figure1.6 2 DeleteFigure1.6 2,TurbineGeneratorHeatBalance,RatedPower.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theinformationprovidedbyfigure1.6 1,ReactorHeatBalance,RatedPower,isnolongerapplicable.Thisinformationisobsolete.1.7 DeleteSection1.7,ComparisonofPrincipalDesignCharacteristics.ThissectionprimarilyliststhedesigncharacteristicsoftheVYstationatinitiallicensingandcomparesthemtosimilarplantsinoperationatthetime.Thisinformationishistoricalinnatureandisnolongerapplicablefollowingpermanentdefueling.Whereapplicable,informationprovidedwasverifiedtoalsoexistintheappropriateSSCdescriptioninotherlocationsintheDSAR.Additionally,theinformationpresentedinTable1.7.7,AEC1967DraftGeneralDesignCriteriaIndexedtoapplicableUFSARSection(s)ishistoricalinformationandisnolongerapplicable.1.7.1Delete,notapplicabletothedefueledstate,obsoleteinformation1.7.2Delete,notapplicabletothedefueledstate,obsoleteinformation1.7.3Delete,notapplicabletothedefueledstate,obsoleteinformation1.7.4Delete,notapplicabletothedefueledstate,obsoleteinformation1.7.5Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.1Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.2Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.3Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.4Delete,notapplicabletothedefueledstate,obsoleteinformation RPProcedures ImplementationofStructuralLoadingCriteria PlantDesignChanges General Shielding AccessControlProcedures General StructuralLoadingCriteria StructuralDesignCharacteristics ComparisonNuclearSystemDesignCharacteristics ComparisonPowerConversionSystemDesignCharacteristics ComparisonElectricalSystemDesignCharacteristics ComparisonofContainmentDesignCharacteristics COMPARISONOFPRINCIPALDESIGNCHARACTERISTICS NuclearSystemDesignCharacteristics PowerConversionSystemDesignCharacteristics ElectricalPowerSystemsDesignCharacteristics ContainmentDesignCharacteristics References ShieldingDesignBasisLimitations ReactorHeatBalance,RatedPower TurbineGeneratorHeatBalance,RatedPower(at0.96PowerFactor)Page7of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table1.7.5Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.6Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.7Delete,notapplicabletothedefueledstate,obsoleteinformation 1.8 1.4 1.8.1 1.Changedsection1.8.1Titleto"FuelStorageandHandlingandWasteManagement" 2.Changed"Thestationwillbeoperated"to"Spentfuelstorageandhandlingandwastemanagementoperationswillbeconducted"-.

3.Deleted"basedonoperatingexperience",inserted"Duringfuelstorageandhandlingandwastemanagementoperations" 1.4.1 1.8.2 Deletedsection1.8.2,AbnormalOperatingTransients.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,fueldamagedueAbnormalOperationalTransientsarenolongerpossible.Consequently,theinformationprovidedinthissectionisobsoleteandmaybedeleted.1.8.3 6.RewordedFHAsectiontoreflectonly2accidents,aFHAinthepoolandaradwastetransfercaskdropaccident.1.4.2 Table1.8.1 7.Deletedtable1.8.1,SummaryofMaximumOffsiteEffectsofDesignBasisAccidents,notapplicableindefueledstate,obsoleteinformation 1.9 5.4 1.9.1 NoChanges 5.4.1 1.9.2 1.DeletedreferencetoANSIN18.7 1976,inserted"ascommittedtowithintheQAPM" 2.Deletedreferenceto"SectionA.2",inserted"TheOrganizationsectionoftheQAPM".5.4.2 1.9.3 3.Section1.9.3,Implementation,deleted"inTable1of".Removinginformationwhichistoospecific 5.4.3 1.9.4 4.Section1.9.4,ManagementEvaluation,substitutedDSARforUFSAR,deleted"Entergy's,inserted"applicable".Removinginformationwhichistoospecific 5.4.4 1.10 1.Deleteentiresection,notapplicablepost defueling,Obsoleteinformation 1.11 Sectionrewordedtostate:"Basedonthedesignofthefacility,andtheanalysisofcredibleevents,thereisreasonableassurancethatthefacilitycansafelymanageirradiatedfuelandradioactivewastewithoutendangeringthehealthandsafetyofthepublic." 1.5 2.0STATIONSITEANDENVIRONS 2.1 NoChanges,retainedassupportinghistoricalinformation 2.1 2.2 2.22.2.1NoChanges 2.2.12.2.2NoChanges 2.2.2 2.2.3DeletedreferencetoHinsdaleRaceway,racewayhasbeendemolished.

2.2.32.2.4Section3.0,ExclusionAreas,deleted"duringnormalplantoperation" 2.2.42.2.5NoChanges 2.2.5 Table2.2.1NoChanges Table2.2.1 Table2.2.2NoChanges Table2.2.2 ComparisonofStructuralDesignCharacteristics Responsibilities Implementation ManagementEvaluation AbnormalOperationalTransients Accidents SummaryoftheMaximumOffsiteEffectsofDesignBasisAccidents QAPROGRAM Scope ComparisonofSystemDesignCharacteristics AEC1967DraftGeneralDesignCriteriaIndexedtoApplicableUFSARSection(s)

SUMMARY

OFRADIATIONEFFECTS NormalOperations QAProgram Scope Responsibilities Implementation ManagementEvaluation

SUMMARY

OFRADIATIONEFFECTS FuelStorageandHandlingandWasteManagement AccidentsandEvents SiteAreaBoundaries,ExclusionArea,andLowPopulationZone Conclusions PopulationDensityComparision LocationandArea Population

LandUse STATIONRESEARCHDEVELOPMENTANDFURTHERINFORMATION;REQUIREMENTSANDRESOLUTION

SUMMARY

GENERALCONCLUSIONS

SUMMARY

DESCRIPTION STATIONSITEANDENVIRONS GeneralConclusions 2.0STATIONSITEANDENVIRONS SummaryDescription SiteDescription LocationandArea Population

LandUse SiteAreaBoundaries,ExclusionArea,andLowPopulationZone Conclusions PopulationDensityComparision 2000PopulationDistribution 2000PopulationDistribution Page8of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table2.2.3NoChanges Table2.2.3 Table2.2.4NoChanges Table2.2.4 Table2.2.5NoChanges Table2.2.5 Table2.2.6NoChanges Table2.2.6 Table2.2.7NoChanges Table2.2.7 Figure2.21NoChanges Figure2.2 1 Figure2.22NoChanges Figure2.2 2 Figure2.23NoChanges Figure2.2 3 Figure2.24NoChanges Figure2.2 4 Figure2.25NoChanges Figure2.2 5 Figure2.26NoChanges Figure2.2 6 Figure2.27NoChanges Figure2.2 7 Figure2.28NoChanges Figure2.2 8 2.3 2.32.3.1NoChanges 2.3.12.3.2NoChanges 2.3.22.3.3NoChanges 2.3.32.3.4NoChanges 2.3.42.3.5NoChanges 2.3.52.3.6NoChanges 2.3.62.3.7NoChanges 2.3.72.3.8NoChanges 2.3.8 Table2.3.1NoChanges Table2.3.1 Table2.3.2NoChanges Table2.3.2 Table2.3.3NoChanges Table2.3.3 Table2.3.4NoChanges Table2.3.4 Table2.3.5NoChanges Table2.3.5 LocationMap2MileRadius LocationMap10MileRadius LocationMap25MileRadius TableofLandUseSquareMiles AgriculturalStatisticsforCountiesWithin50Miles AgriculturalStatisticsforCountiesWithin50Miles ProjectedPopulationDistributionforYear2010 UrbanCentersWithin30MilesofSite ProjectedPopulationDistributionforYear2010 UrbanCentersWithin30MilesofSite TableofLandUseSquareMiles AgriculturalStatisticsforCountiesWithin50Miles AgriculturalStatisticsforCountiesWithin50Miles LocationMap2MileRadius LocationMap10MileRadius LocationMap25MileRadius General On siteMeteorologicalPrograms DiffusionClimatology StationSiteAreaPopulationDistribution10MileRadiusYear2000 StationSiteAreaPopulationDistribution50MileRadiusYear2000 METEOROLOGY G 191142StationPlan 5920 6245PlanShowingExclusionAreaandRestrictedAreaBoundaries StationSiteAreaPopulationDistribution5MileRadiusYear2000 G 191142StationPlan 5920 6245PlanShowingExclusionAreaandRestrictedAreaBoundaries StationSiteAreaPopulationDistribution5MileRadiusYear2000 StationSiteAreaPopulationDistribution10MileRadiusYear2000 StationSiteAreaPopulationDistribution50MileRadiusYear2000 Meteorology General On siteMeteorologicalPrograms DiffusionClimatology PRECIPITATIONDATAFORTHEVERNONAREA WINDSDURINGTHUNDERSTORMS RAINFALLDATAFROMHURRICANECONNIE Conclusions MeteorologyRecord TEMPERATUREDATAFORTHEVERNONAREA WindsandWindLoading TemperatureandPrecipitation Storms References WindsandWindLoading TemperatureandPrecipitation Storms Conclusions

References MeteorologyRecord TEMPERATUREDATAFORTHEVERNONAREA PRECIPITATIONDATAFORTHEVERNONAREA WINDSDURINGTHUNDERSTORMS RAINFALLDATAFROMHURRICANECONNIE Page9of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure2.31NoChanges Figure2.3 1 Figure2.32NoChanges Figure2.3 2 Figure2.33NoChanges Figure2.3 3 2.4 NoChanges 2.42.4.1NoChanges 2.4.12.4.2NoChanges 2.4.2 2.4.3 Section2.4.3.4,Hydrology,Floods.Deleteinformationregardingequipmentrequiredtooperateduringamaximumprobablefloodsincethatequipmentwasnecessarytoensureadequatedecayheatremovalfromarecentlyshutdownreactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sincepoweroperationscannotoccurandthereisnofuelinthereactorvessel,coredecayheatremovalduringaPMFfromarecentlyshutdownreactorisnolongeraconcern.Therefore,thisinformationisnolongerapplicableandmaybedeleted.Section2.4.3.4,Hydrology,Floods.InsertthestatementregardingfuelpoolcoolingduringaPMF.Fuelpoolcoolingwillbemaintaineduntileitherservicewaterislostornormalelectricalpowerislost.DGbackupsareavailableforpower.Alternatecoolingstrategiesexistintheeventservicewaterorelectricalpowerislost.ReplaceddiscussionoffloodingandwaverunupwithdiscussiongeneratedduringFukushimaFloodingEvaluation.InformationinpreviousdiscussionwassupersededbytheinformationintheFukushimaEvaluation.FukushimaEvaluationinformationwaslocatedintheconclusionsectionandwasmovedintothetextbody.2.4.32.4.4NoChanges 2.4.42.4.5NoChanges 2.4.52.4.6NoChanges 2.4.62.4.7NoChanges 2.4.7 2.4.8 1.Section2.4.8,Conclusions,deletedstatement"Sincetheentrancestoallstructurescntainingequipmentnecessaryforreactorshutdownandcoolingareatelevation252.5feetMSL,theyareprotectedagainstthePMF."Noequipmentisrequiredforreactorshutdownorcoolingpostdefueling.

2.4.82.4.9NoChanges 2.4.9 Table2.4.1NoChanges Table2.4.1 Table2.4.2NoChanges Table2.4.2 Table2.4.3NoChanges Table2.4.3 Table2.4.4NoChanges Table2.4.4 Table2.4.5NoChanges Table2.4.5 Table2.4.6NoChanges Table2.4.6 Hydrology UsesOfRiver Biology HYDROLOGYANDBIOLOGY General LandAreaGroundHydrology StationSiteWestoverAFB,MassachusettsAreaAnnualSurfaceWindrose StationSiteWestoverAFB,MassachusettsAreaSeasonalSurfaceWindroses StationSiteConcordNewHampshireArea,PeriodsofRainfall(ForExtremelyShortIntervals)

General LandAreaGroundHydrology StationSiteWestoverAFB,MassachusettsAreaAnnualSurfaceWindrose StationSiteWestoverAFB,MassachusettsAreaSeasonalSurfaceWindroses StationSiteConcordNewHampshireArea,PeriodsofRainfall(ForExtremelyShortIntervals)

HydrologyandBiology Hydrology UsesOfRiver Biology MunicipalandIndustrialGroundwaterUsageWithina10 MileRadiusoftheVernonSite PublicWaterSuppliesWithina10 MileRadiusoftheVernonSite WaterSuppliesWithinal MileRadiusoftheSite References AverageandExtremeValuesofStreamFlowConnecticutRiverat Vernon,VermontWaterYears1945 1965 VermontYankeeNuclearPowerStation,DailyStreamFlowforOctober1964toSeptember1965,ConnecticutRiveratVernon,Vermont ChemicalandBacteriologicalQualityofWater RiverFieldProgram Conclusions ChemicalandBacteriologicalQualityofWater RiverFieldProgram Conclusions References AverageandExtremeValuesofStreamFlowConnecticutRiverat Vernon,VermontWaterYears1945 1965 VermontYankeeNuclearPowerStation,DailyStreamFlowforOctober1964toSeptember1965,ConnecticutRiveratVernon,Vermont MunicipalandIndustrialGroundwaterUsageWithina10 MileRadiusoftheVernonSite PublicWaterSuppliesWithina10 MileRadiusoftheVernonSite WaterSuppliesWithinal MileRadiusoftheSite Six HourPMPandRunoffIncrementsConnecticutRiverBasinaboveVernon,Vermont Six HourPMPandRunoffIncrementsConnecticutRiverBasinaboveVernon,Vermont Page10of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table2.4.7NoChanges Table2.4.7 Table2.4.8NoChanges Table2.4.8 Table2.4.9NoChanges Table2.4.9 Table2.4.10NoChanges Table2.4.10 Table2.4.11NoChanges Table2.4.11 Figure2.41NoChanges Figure2.4 1 Figure2.42NoChanges Figure2.4 2 Figure2.43NoChanges Figure2.4 3 Figure2.44NoChanges Figure2.4 4 Figure2.45NoChanges Figure2.4 5 Figure2.46NoChanges Figure2.4 6 Figure2.47NoChanges Figure2.4 7 Figure2.48NoChanges Figure2.4 8 Figure2.49NoChanges Figure2.4 9 Figure2.410NoChanges Figure2.4 10 Figure2.411NoChanges Figure2.4 11 2.5 NoChanges 2.52.5.1NoChanges 2.5.12.5.2NoChanges 2.5.22.5.3NoChanges 2.5.32.5.4NoChanges 2.5.4 Table2.5.1 NoChanges Table2.5.1 StationSiteAreaPublicWaterSupplies10 MileRadius StationSiteAreaPrivateWaterSupplies1 MileRadius EnvelopingDepth Duration AreaValuesofPMPforSusquehannnaRiverBasin TimeVaryingModifiedPMFStageDischargeTableVermontYankeeNuclearPlantSite ChecklistofConnecticutRiverFishesFoundNearVernon,Vermont FishesoftheConnecticutRiverintheVicinityofVernon,VermontAllCollections,1980 MaximumAnnualFloodsonConnecticutRiveratVernon,VermontArrangedinDescendingOrder(1927,1936,1938,1945 1973)TimeVaryingPMFStageDischargeTableVermontYankeeNuclearPlantSite MaximumAnnualFloodsonConnecticutRiveratVernon,VermontArrangedinDescendingOrder(1927,1936,1938,1945 1973)TimeVaryingPMFStageDischargeTableVermontYankeeNuclearPlantSite TimeVaryingModifiedPMFStageDischargeTableVermontYankeeNuclearPlantSite ChecklistofConnecticutRiverFishesFoundNearVernon,Vermont FishesoftheConnecticutRiverintheVicinityofVernon,VermontAllCollections,1980 StationSiteAreaPublicWaterSupplies10 MileRadius StationSiteAreaPrivateWaterSupplies1 MileRadius EnvelopingDepth Duration AreaValuesofPMPforSusquehannnaRiverBasin CrossSectionoftheCriticalFetch VermontYankeeSampleStationsonConnecticutRiver GEOLOGYANDSEISMOLOGY ConnecticutRiverBasinFederalPowerCommissionWaterResourceAppraisalsforHydroelectricLicensingSummaryof PlanningStatus VermontYankeeNuclearPlantLocationofRiverCross Sections Stage DischargeCurveattheVermontYankeeNuclearPlant 6 HourUnitHydrograph TotalSPFHydrograph TotalPMFHydrograph(NaturalandModified)6 HourUnitHydrograph TotalSPFHydrograph TotalPMFHydrograph(NaturalandModified)ConnecticutRiverBasinFederalPowerCommissionWaterResourceAppraisalsforHydroelectricLicensingSummaryofPlanningStatus VermontYankeeNuclearPlantLocationofRiverCross Sections Stage DischargeCurveattheVermontYankeeNuclearPlant CrossSectionoftheCriticalFetch VermontYankeeSampleStationsonConnecticutRiver GeologyandSeismology Conclusions AvailableInformationConcerningGeologyandSeismicActivityRelatedtotheVermontYankeeGeneral Geology Seismology General Geology Seismology

Conclusions AvailableInformationConcerningGeologyandSeismicActivityRelatedtotheVermontYankeeNuclearPowerStationSite Page11of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table2.5.2 NoChanges Table2.5.2 Figure2.5 1 PreviouslyDeleted Figure2.5 2 NoChanges Figure2.5 2 Figure2.5 3 NoChanges Figure2.5 3 Figure2.5 4 NoChanges Figure2.5 4 Figure2.5 5 NoChanges Figure2.5 5 Figure2.5 6 NoChanges Figure2.5 6 Figure2.5 7 NoChanges Figure2.5 7 Figure2.5 8 NoChanges Figure2.5 8 Figure2.5 9 NoChanges Figure2.5 9 Figure2.5 10 NoChanges Figure2.5 10 Figure2.5 11 NoChanges Figure2.5 11 Figure2.5 12 NoChanges Figure2.5 12 Figure2.5 13 NoChanges Figure2.5 13 Figure2.5 14 NoChanges Figure2.5 14 Figure2.5 15 NoChanges Figure2.5 15 2.6 Section2.6.1,deletedthewordsafetyfromthesectiontitle.SincetheclassificationprocessdescribedintheUFSARsection1.4.1isnolongerused,theterm"Safety"objectiveisnolongerapplicable.2.6 2.6.1 NoChanges 2.6.1 2.6.2 NoChanges 2.6.2 2.6.3 NoChanges 2.6.3 2.6.4 NoChanges 2.6.4 2.6.5 NoChanges 2.6.5 3.0 Renamesection"FacilityDesignandOperation"toprovideacentrallocationforinformationpertinenttothedesignandoperationofVermontYankeeinthepermanentlydefueledstate.3.0 FacilityDesignandOperation Deleted StationSiteGeologicalSurveyGeneralPlanLocationofTestBorings StationSiteGeologicalSurveySubsurfaceProfileLogofTestBorings(1A,2A,3A,4,5,8)VernonPluton:EstimatedModeoftheOliverianMagmaSeries VernonPluton:EstimatedModeoftheOliverianMagmaSeries StationSiteGeologicalSurveyGeneralPlanLocationofTestBorings StationSiteGeologicalSurveySubsurfaceProfileLogofTestBorings(1A,2A,3A,4,5,8)StationSiteGeologicalSurveySubsurfaceProfile(SectionCC)LogofTestBorings(2,2A,5,7,7A,13,and15)StationSiteGeologicalSurveySubsurfaceProfile(SectionDD)LogofTestBorings(3,3A,4,8,8A,12,and16)StationSiteTectonicMapNewEnglandArea StationSiteGeologicalSurveyAreaGeologicalSectionStationSiteGeologicalSurveySubsurfaceProfile(SectionAA)LogofTestBorings(5,8,S9,11,and21)StationSiteGeologicalSurveySubsurfaceProfile(SectionBB)LogofTestBorings(2A,3A,ST6 1/2,andS9)StationSiteTectonicMapStateofVermont StationSiteTectonicMapStateofNewHampshire StationSiteGeologicalSurveyAreaBedrockGeology StationSiteTectonicMapStateofVermont StationSiteTectonicMapStateofNewHampshire StationSiteGeologicalSurveyAreaBedrockGeology StationSiteGeologicalSurveyAreaGeologicalSectionStationSiteGeologicalSurveySubsurfaceProfile(SectionAA)LogofTestBorings(5,8,S9,11,and21)StationSiteGeologicalSurveySubsurfaceProfile(SectionBB)LogofTestBorings(2A,3A,ST6 1/2,andS9)StationSiteGeologicalSurveySubsurfaceProfile(SectionCC)LogofTestBorings(2,2A,5,7,7A,13,and15)StationSiteGeologicalSurveySubsurfaceProfile(SectionDD)LogofTestBorings(3,3A,4,8,8A,12,and16)StationSiteTectonicMapNewEnglandArea RadiologicalEnvironmentalMonitoringProgram SafetyObjectives MonitoringNetwork LandUseCensus EmergencySurveillance StationSiteCompilationofEarthquakesNewEnglandArea StationSiteEarthquakeIntensityModifiedMercalliandRossiForelScales StationSiteCompilationofEarthquakesCentralNewEnglandArea StationSiteCompilationofEarthquakesNewEnglandArea StationSiteEarthquakeIntensityModifiedMercalliandRossiForelScales StationSiteCompilationofEarthquakesCentralNewEnglandArea RadiologicalEnvironmentalMonitoringProgram Objectives MonitoringNetwork LandUseCensus EmergencySurveillance Reports Reports Reactor Page12of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.1 DeletetheinformationinSection3.1,SummaryDescription,renamethesection3.1,DesignCriteriatoprovideacentrallocationforSSCdesigninformationpertinentinthepermanentlydefueledstate.Informationintheoldsummarydescriptionsectionsummmarizedaspectsofthedesignandoperationofthereactorwhicharenolongerapplicableinthepermanentlydefueledstate.Section3.1,DesignCriteria,establishesacentrallocationfordesigninformationwhichremainsapplicableinthepermanentlydefueledstate.3.1 3.2 3.3.1.1 3.2.1 ModifySection3.2.1,PowerGenerationObjectives,toreflectthefactthatfuelmaynolongerbeemplacedorretainedinthereactorvessel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.AllfuelisstoredeitherinthespentfuelpoolorattheISFSI.ThisobjectivehasbeenrewrittenandappliestothefuelstoredintheSpentFuelPool.3.3.1.1.1 3.2.2 DeleteSection3.2.2,FuelMechDesignSafetyDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvess e IAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheSafetyDesignBasisisnotapplicable.PortionsofthisobjectiveremainingapplicablehavebeenconsolidatedwiththePowerGenerationObjectivetoformtheObjectivesection.3.2.3 ModifySection3.2.3,FuelMechanicalDesignDescriptiontoremovealldiscussionsoecifictofuelemplacementinthereactorvessel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.InformationprovidedintheFuelMechanicalDesignDescriptionsectionregardingnuclearfueloperationoremplacementinthereactorvesselisnolongerapplicable;allnuclearfuelhasbeenremovedfromthereactorvesselandisstoredinthespentfuelpoolorattheISFSI.Informationregardingfueldesignapplicabletostorageinthespentfuelpoolhasbeenretained.3.3.1.1.2 3.2.4 DeleteSection3.2.4,FuelMechDesignSafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheinformationprovidedintheFuelMechDesignSafetyEvaluationsectionisnolongerapplicable.

3.2.5 DeleteSection3.2.5,FuelMechDesignInspectionandtesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheinformationprovidedintheFuelMechDesignInspectionandTestingsectionisnolongerapplicable.3.2.6 DeleteSection3.2.6,FuelMechDesignReferences.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheinformationprovidedintheFuelMechDesignReferencessectionisnolongerapplicable.3.3 Deleteentiresection,Sections3.3.1through3.3.7arenolongerapplicable,noinformationremainsinthissection 3.3.1 Deletesection3.3.1,ReactorVesselInternalsMechDesign,PowerGenerationObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,thesafetyobjectiveisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.3.3.2 Deletesection3.3.2,ReactorVesselInternalsMechDesign,PowerGenerationDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,thepowergenerationdesignbasesarenotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.3.3.3 Deletesection3.3.3,ReactorVesselInternalsMechDesign,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,thesafetydesignbasisisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.3.3.4 Deletesection3.3.4,ReactorVesselInternalsMechDesign,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,theinformationprovidedinthedescriptionsectionisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.3.3.5 Deletesection3.3.5,ReactorVesselInternalsMechDesign,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,theinformationprovidedinthesafetyevaluationsectionisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.Objective Description DesignCriteria NuclearFuel PowerGenerationObjectives PowerGenerationDesignBases SafetyDesignBasis Description

SafetyEvaluation Description SafetyEvaluation InspectionandTesting References REACTORVESSELINTERNALSMechDesign

SUMMARY

DESCRIPTION FuelMechDesign PowerGenerationObjectives SafetyDesignBasis Page13of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.3.6 Deletesection3.3.6,ReactorVesselInternalsMechDesign,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,theinformationprovidedintheInspectionandTestingsectionisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.3.3.7 Deletesection3.3.7,ReactorVesselInternalsMechDesign,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,thereferencesprovidednolongerapply.ReactorVesselInternalsMechDesigninformationisobsolete.Table3.3.1 DeleteTable3.3.1,ReactorVesselInternalsDesignData.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsMechDesigninformationisobsolete.Figure3.3.1 DeleteFigure3.3.1,ReactorVesselInternals.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsinformationisobsolete.Figure3.3.2 DeleteFigure3.3.2,ReactorVesselInternalsFlowSchematic.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsinformationisobsolete.Figure3.3.3 DeleteFigure3.3.3,SteamSeparator.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsinformationisobsolete.Figure3.3.4 DeleteFigure3.3.4,FuelSupportPieces.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsinformationisobsolete.Figure3.3.5 DeleteFigure3.3.5,JetPumpIsometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsinformationisobsolete.Figure3.3.6 DeleteFigure3.3.6,SteamDryer.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternalsinformationisobsolete.Figure3.3.7 DeleteFigure3.3.7,LocationsofCalculatedPressureDifferentials.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheLocationsofCalculatedPressureDifferentialsisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.8A DeleteFigure3.3.8A,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.8B DeleteFigure3.3.8B,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.8C DeleteFigure3.3.8C,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.InspectionandTesting JetPumpIsometric SteamDryer LocationsofCalculatedPressureDifferentials PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow 3.3 8CPressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow References ReactorVesselInternalsDesignData ReactorVesselInternals ReactorVesselInternalFlowSchematic SteamSeparator FuelSupportPieces Page14of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure3.3.8D DeleteFigure3.3.8D,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.8E DeleteFigure3.3.8E,SteamDryerPressureDifferentialFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheSteamDryerPressureDifferentialFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.9 DeleteFigure3.3.9,ThermalShockTransientAnalysisZones.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheThermalShockTransientAnalysisZonesisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.10 DeleteFigure3.3.10,MaterialBehaviorGraphCyclesVersusStressforStainlessSteel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheMaterialBehaviorGraphCyclesVersusStressforStainlessSteelisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.11PreviouslyDeleted Figure3.3.12A DeleteFigure3.3.12A,VesselDomePressureFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheVesselDomePressureFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.12B DeleteFigure3.3.12B,VesselDomePressureFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheVesselDomePressureFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.13A DeleteFigure3.3.13A,MSLBBundleLiftMarginat102%Power/107%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfueli n thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheMSLBBundleLiftMarginat102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.Figure3.3.13B DeleteFigure3.3.13B,MSLBBundleLiftMarginat16.7%Power/110%CoreFlow.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheMSLBBundleLiftMarginat16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.3.4 Deleteentiresection,Sections3.4.1through3.4.8arenolongerapplicable,noinformationremainsinthissection 3.4.1 Deletesection3.4.1,ReactivityControlMechDesign,PowerGenerationObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,thePowerGenerationObjectiveprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.4.2 Deletesection3.4.2,ReactivityControlMechDesign,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,theSafetyObjectiveprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowSteamDryerPressureDifferentialFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow ThermalShockTransientAnalysisZones MaterialBehaviorGraphCyclesVersusStressforStainlessSteel Deleted VesselDomePressureFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow SafetyObjectives VesselDomePressureFollowingSteamlineBreakInsidetheDrywell16.7%Power/110%CoreFlow MSLBBundleLiftMarginat102%Power/107%CoreFlow MSLBBundleLiftMarginat16.7%Power/110%CoreFlow REACTIVITYCONTROLMechDesign PowerGenerationObjective Page15of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.4.3 Deletesection3.4.3,ReactivityControlMechDesign,PowerGenerationDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,thePowerGenerationDesignBasisprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.4.4 Deletesection3.4.4,ReactivityControlMechDesign,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,theSafetyDesignBasisprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.4.5 Deletesection3.4.5,ReactivityControlMechDesign,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,theinformationprovidedinthedescriptionsectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.4.6 Deletesection3.4.6,ReactivityControlMechDesign,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,theinformationprovidedinthesafetyevaluationsectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.4.7 Deletesection3.4.7,ReactivityControlMechDesign,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,theinformationprovidedintheInspectionandTestingsectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.4.8 Deletesection3.4.8,ReactivityControlMechDesign,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolongerapplicable,theinformationprovidedintheReferencessectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 1 DeleteFigure3.4 1,OriginalEquipmentControlRodIsometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,OriginalEquipmentControlRodinformationisnolongerapplicable,theinformationprovidedintheOriginalEquipmentControlRodIsometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 2 DeleteFigure3.4 2,TypicalControlRodtoControlRodDriveCouplingIsometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,TypicalControlRodtoControlRodDriveCouplinginformationisnolongerapplicable,theinformationprovidedintheTypicalControlRodtoControlRodDriveCouplingIsometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 3 DeleteFigure3.4 3,TypicalControlRodVelocityLimiterIsometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,TypicalControlRodVelocityLimiterinformationisnolongerapplicable,theinformationprovidedintheTypicalControlRodVelocityLimiterIsometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 4 DeleteFigure3.4 4,ControlRodDrive,SimplifiedComponentIllustration.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDrive,SimplifiedComponentinformationisnolongerapplicable,theinformationprovidedintheControlRodDrive,SimplifiedComponentIllustrationnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 5 DeleteFigure3.4 5,ControlRodDrive,SchematicDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDrive,informationisnolongerapplicable,theinformationprovidedintheControlRodDrive,SchematicDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.References OriginalEquipmentControlRodIsometric TypicalControlRodtoControlRodDriveCouplingIsometric TypicalControlRodVelocityLimiterIsometric ControlRodDrive,SimplifiedComponentIllustration ControlRodDrive,SchematicDiagram PowerGenerationDesignBases SafetyDesignBasis Description

SafetyEvaluation InspectionandTesting Page16of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure3.4 6 DeleteFigure3.4 6,ControlRodDriveHydraulicControlSystemSimplifiedComponentIllustration.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,theinformationprovidedintheControlRodDriveHydraulicControlSystemSimplifiedComponentIllustrationnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 7A DeleteFigure3.4 7A,ControlRodDriveHydraulicSystemPipingandInstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,theinformationprovidedintheControlRodDriveHydraulicSystemPipingandInstrumentationDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 7B DeleteFigure3.4 7B,ControlRodDriveHydraulicSystemPipingandInstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,theinformationprovidedintheControlRodDriveHydraulicSystemPipingandInstrumentationDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 8 DeleteFigure3.4 8,ControlRodUnitDrive CutawayIllustration.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,theinformationprovidedintheControlRodUnitDrive CutawayIllustrationnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 9 DeleteFigure3.4 9,ControlRodDriveHydraulicSystem,ProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,theinformationprovidedintheControlRodDriveHydraulicSystem,ProcessDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.Figure3.4 10 DeleteFigure3.4 10,ControlRodHydraulicControlUnit Isometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,theinformationprovidedintheControlRodHydraulicControlUnit Isometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.3.5 Deleteentiresection,Sections3.5.1through3.5.5arenolongerapplicable,noinformationremainsinthissection 3.5.1 Deletesection3.5.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,thesafetyobjectiveisnolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.3.5.2 Deletesection3.5.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,thesafetydesignbasesarenolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.3.5.3 Deletesection3.5.3,CRDHousingSupportDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedinthedescriptionsectionisnolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.3.5.4 Deletesection3.5.4,CRDHousingSupportSafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedinthesafetyevaluationsectionisnolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.3.5.5 Deletesection3.5.5,CRDHousingSupportInspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedintheInspectionandTestingsectionisnolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.Figure3.5 1 DeleteFigure3.5 1,ControlRodDriveHousingSupportIsometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedintheControlRodDriveHousingSupportIsometricisnolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.InspectionandTesting ControlRodDriveHousingSupportIsometric CONTROLRODDRIVEHOUSINGSUPPORTS SafetyObjective SafetyDesignBasis Description

SafetyEvaluation G 191170ControlRodDriveHydraulicControlSystemSimplifiedComponentIllustration G 191170ControlRodDriveHydraulicSystemPipingandInstrumentationDiagram G 191170HydraulicControlUnit,PipingandInstrumentationDiagram ControlRodUnitDrive CutawayIllustration 5920 164ControlRodDriveHydraulicSystem,ProcessDiagram ControlRodHydraulicControlUnit Isometric Page17of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.6 3.6.1 Section3.6.1,PowerGenerationObjectives,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurandtheseobjectivesnolongerapply 3.6.2 Section3.6.2,PowerGenerationDesignBases,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurandthesedesignbasesnolongerapply 3.6.3 Section3.6.3,SafetyDesignBases,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefor e poweroperationscannotoccurandtheseSafetyDesignBasesnolongerapply 3.6.4Section3.6.4,NuclearRequirements,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel Therefore,poweroperationscannotoccurandthesenuclearrequirementsnolongerapply:Controlrodswillberemovedfromcore.ReactorManualcontrolsystemwillnolongerberequiredStandbyliquidcontrolsystemwillnolongerberequiredsincetherewillbenocore 3.6.5 Section3.6.5,FuelNuclearCharacteristics,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPoolandpooldesigncharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransientscannotoccur.3.6.6 Section3.6.6,NuclearEvaluations,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefor e poweroperationscannotoccurandthesenuclearevaluationsarenolongerrequired 3.6.7 Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurandtestingandverificationofnucleardesigncriteriaarenolongerrequired.3.6.8DeleteSection4.2.7,References.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistedreferencesnolongerapply.Figure3.6 1 DeleteFigure3.6 1,RelativeXenonStabilityWithNoFluxFlattening,Postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPoolandpooldesigncharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransientscannotoccur.Therefore,theinformationprovidedbyFigure3.6 1isnolongerapplicableandisobsolete.Figure3.6 2 DeleteFigure3.6 2,EffectofPowerDensityonAxialXenonStabilityIncludingVoidTransport.Postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPoolandpooldesigncharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransientscannotoccur.Therefore,theinformationprovidedbyFigure3.6 2isnolongerapplicableandisobsolete.Figure3.6 3 DeleteFigure3.6 3,AzimuthalXenonStability.Postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPoolandpooldesigncharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransientscannotoccur.Therefore,theinformationprovidedbyFigure3.6 3isnolongerapplicableandisobsolete.3.7 3.7.1 DeleteSection3.7.1,PowerGenerationObjective.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydraulicdesignisnolongerrequiredandpowergenerationobjectivesareobsoleteinformation.

3.7.2 DeleteSection3.7.2,PowerGenerationDesignBases.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydraulicdesignisnolongerrequiredandpowergenerationdesignbasesareobsoleteinformation.

3.7.3 DeleteSection3.7.3,SafetyDesignBases.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2)Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydraulicdesignisnolongerrequiredandsafetydesignbasesareobsoleteinformation.

3.7.4 DeleteSection3.7.4,ThermalandHydraulicLimits.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydrauliclimitsarenolongerrequiredandareobsoleteinformation.

3.7.5 DeleteSection3.7.5,ThermalandHydraulicCharacteristics.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydrauliccharacteristicsarenolongerrequiredandareobsoleteinformation NUCLEARDESIGN PowerGenerationObjectives PowerGenerationDesignBases PowerGenerationDesignBases SafetyDesignBasis ThermalandHydraulicLimits ThermalandHydraulicCharacteristics RelativeXenonStabilityWithNoFluxFlattening EffectofPowerDensityonAxialXenonStabilityIncludingVoidTransport AzimuthalXenonStability THERMALANDHYDRAULICDESIGN PowerGenerationObjective SafetyDesignBasis NuclearRequirements FuelNuclearCharacteristics NuclearEvaluations TestingandVerification References Page18of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.7.6DeleteSection3.7.6,ThermalandHydraulicEvaluation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thecorethermalandhydraulicevaluationisnolongerrequiredandisobsoleteinformation.ThedesignMCPRlimitnolongerapplies,fueldamageorwaterloggingcannotoccurduetoexceedinglimits,andflowblockagescannolongeroccur.3.7.7 DeleteSection3.7.7,TestingandVerification.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,testingandverificationthatoperationisoccurringwithinMCPRandLHGRlimitsisnolongerrequiredandisobsoleteinformation.3.7.8DeleteSection3.7.8,References.Sincethissectionisbeingdeletedcompletely,thesereferencesarenolongerrequiredandareobsoleteinformation.

3.8 3.8.1 DeleteSection3.8.1,SafetyObjective.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.Theseobjectivesareobsoleteinformation.

3.8.2 DeleteSection3.8.2,SafetyDesignBases.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA,sinceaLOCAcannolongeroccur.Thesedesignbasesareobsoleteinformation.

3.8.3 DeleteSection3.8.3,Description.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.3.8.4 DeleteSection3.8.4,SafetyEvaluation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Therefore,asafetyevaluationoftheSBLCsystemisnolongerrequiredandisobsoleteinformation.3.8.5 DeleteSection3.8.5,InspectionandTesting.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Therefore,inspectionandtestingoftheSBLCsystemisnolongerrequiredandisobsoleteinformation.TechnicalSpecificationsurveillancerequirementsweredeletedfromTechnicalSpecificationsinpermanentlydefueledtechnicalspecifications.

Figure3.8 1 DeleteFigure3.8 1,StandbyLiquidControlSystem,PipingandInstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformationprovidedonFigure3.8 1isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.Figure3.8 2 DeleteFigure3.8 2,StandbyLiquidControlSystem,ProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformationprovidedonFigure3.8 2isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.Figure3.8 3 DeleteFigure3.8 3,SaturationTemperatureofSodiumPentaborateSolution.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformationprovidedonFigure3.8 3isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.Figure3.8 4 DeleteFigure3.8 4,StandbyLiquidControlSystem,FunctionalControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformationprovidedonFigure3.8 4isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.Figure3.8 5 DeleteFigure3.8 5,SodiumPentaborateSolutionVolumeConcentrationRequirements.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformationprovidedonFigure3.8 5isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.4.0ReactorCoolantSystem ThermalandHydraulicEvaluation TestingandVerification SodiumPentaborateSolutionVolumeConcentrationRequirements SafetyEvaluation InspectionandTesting StandbyLiquidControlSystem,PipingandInstrumentationDiagramG191171 StandbyLiquidControlSystem,ProcessDiagram5920 717 SaturationTemperatureofSodiumPentaborateSolution StandbyLiquidControlSystem,FunctionalControlDiagram5920 40 References STANDBYLIQUIDCONTROLSYSTEM SafetyObjective SafetyDesignBases Description Page19of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.1 DeleteSection4.1,ReactorCoolantSystemSummaryDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequentlythestructures,systemsandcomponentsdiscussedinsection4.arenolongerrequiredandtheinformationprovidedisnolongerapplicable.

Table4.1.1 DeleteTable4.1.1,EquipmentWithinReactorCoolantPressureBoundaryComparisonWith10CFR50.55A.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequentlythestructures,systemsandcomponentsdiscussedinsection4.1arenolongerrequiredandtheinformationprovidedinTable4.1.1isnolongerapplicable.

4.2 4.2.1 Section4.2.1,PowerGenerationObjectives,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurandtheseobjectivesnolongerapply.4.2.2 Section4.2.2,PowerGenerationDesignBases,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurandthesereactorvesseldesignbasesnolongerapply.4.2.3 Section4.2.3,SafetyDesignBases,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurandtheseSafetyDesignBasesnolongerapply.4.2.4 4.2.4.1 DeleteSection4.2.4.1,ReactorVessel.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.4.2.4.2 DeleteSection4.2.4.2,ShroudSupport.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheshroudandshroudsupportarenolongerrequired.4.2.4.3DeleteSection4.2.4.3,ReactorVesselSupportAssembly.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheReactorVesselSupportAssemblyarenolongerrequired..4.2.4.4 DeleteSection4.2.4.4,VesselStabilizers.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheReactorVesselStabilizersarenolongerrequired.4.2.4.5 DeleteSection4.2.4.5,RefuelingBellows.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepermissibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheRefuelingBellowsarenolongerrequired.Therefore,theinformationprovidedregardingtherefuelingbellowsisnolongerrequiredandisconsideredobsolete.4.2.4.6 DeleteSection4.2.4.6,ControlRodDriveHousings.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Consequently,thefunctionsofareactorvessel,includingtheControlRodDriveHousingsarenolongerrequired.4.2.4.7 DeleteSection4.2.4.7,ControlRodDriveHousingSupports.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Consequently,thefunctionsofareactorvessel,includingtheControlRodDriveHousingsupportsarenolongerrequired.4.2.4.8 DeleteSection4.2.4.8,IncoreNeutronFluxMonitorHousings.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvessel,includingtheIncoreNeutronFluxMonitorHousingsarenolongerrequired.4.2.4.9 DeleteSection4.2.4.9,ReactorVesselInsulation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvessel,includingtheReactorVesselInsulationarenolongerrequired.4.2.5 DeleteSection4.2.5,SafetyEvaluation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,asafetyevaluationofthereactorpressurevesselisnolongerrequiredandisobsoleteinformation.

4.2.6 DeleteSection4.2.6,InspectionandTesting.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,inspectionandtestingoftheReactorPressureVesselisnolongerrequired.

SUMMARY

DESCRIPTION EquipmentWithinReactorCoolantPressureBoundaryComparisonWith10CFR50.55A REACTORVESSELANDAPPURTENANCESPowerGenerationObjectives PowerGenerationDesignBases InspectionandTesting RefuelingBellows ControlRodDriveHousings ControlRodDriveHousingSupports IncoreNeutronFluxMonitorHousings ReactorVesselInsulation SafetyEvaluation SafetyDesignBases Description ReactorVessel ShroudSupport ReactorVesseilSupportAssembly VesselStabilizers Page20of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.2.7 DeleteSection4.2.7,References.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistedreferencesnolongerapply.Table4.2.1 DeleteTable4.2.1,ReactorPressureVesselMaterials.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistofReactorPressureVesselMaterialsisobsoleteinformation.

Table4.2.2 DeleteTable4.2.2,ReactorVesselData.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistofReactorVesselDataisobsoleteinformation Table4.2.3 DeleteTable4.2.3,ReactorVesselAttachments.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistofReactorVesselAttachmentsisobsoleteinformation Table4.2.4 DeleteTable4.2.4,SurveillanceCapsuleRemovalSchedule.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,theSurveillanceCapsuleRemovalScheduleisobsoleteinformation.

Figure4.2 1 DeleteFigure4.2.1,ReactorVessel.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,theinformationprovidedonFigure4.2.1,ReactorVesselisnolongerapplicable.Informationregardingthereactorvesselisobsolete.Figure4.2 2 DeleteFigure4.2.2,ReactorVesselNozzlesandPenetrations.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,theinformationprovidedonFigure4.2.2,ReactorVesselnozzlesandpenetrationsisnolongerapplicable.Informationregardingthereactorvesselisobsolete.Figure4.2 3 DeleteFigure4.2.3,ChangeinNDTTVersusNeutronExposure.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,theinformationprovidedonFigure4.2.3,ChangeinNDTTVersusNeutronExposureisnolongerapplicable.Informationregardingthereactorvesselisobsolete.Figure4.24PreviouslyDeleted 4.3 TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.4.3.1 DeleteSection4.3.1,PowerGenerationObjectives.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.ReactorRecirculationSysteminformationisobsolete.4.3.2 DeleteSection4.3.2,PowerGenerationDesignBasis.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.ReactorRecirculationSysteminformationisobsolete.4.3.3 DeleteSection4.3.3,SafetyDesignBasis.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.ReactorRecirculationSysteminformationisobsolete.References ReactorPressureVesselMaterials ReactorVesselData ReactorVesselAttachments SurveillanceCapsuleRemovalSchedule PowerGenerationDesignBasisSafetyDesignBasis ReactorVessel ReactorVesselNozzlesandPenetrations ChangeinNDTTVersusNeutronExposure Deleted REACTORRECIRCULATIONSYSTEM PowerGenerationObjectives Page21of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.3.4 DeleteSection4.3.4,Description.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.ReactorRecirculationSysteminformationisobsolete.4.3.5 DeleteSection4.3.5,SafetyEvaluation.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,aReactorRecirculationSafetyEvaluationisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.4.3.6 DeleteSection4.3.6,InspectionandTesting.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,inspectionandtestingoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminspectionandtestinginformationisobsolete.4.3.7 DeleteSection4.3.7,SafetyEvaluation.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,ReactorRecirculationSystemreferencesarenolongerrequired.ReactorRecirculationSystemreferencesinformationisobsolete.Table4.3.1 DeleteTable4.3.1,ReactorRecirculationSystemDesignCharacteristics.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,ReactorRecirculationSystemDesignCharacteristicsinformationisobsolete.Figure4.3 1 DeleteFigure4.3 1,RecirculationSystemElevation,Isometric.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.3 1isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.Figure4.3 2 DeleteFigure4.3 2,NuclearBoiler,PipingandInstrumentationDiagram.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.3 2isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.ReactorRecirculationSystemDesignCharacteristics RecirculationSystemElevation,Isometric NuclearBoiler,PipingandInstrumentationDiagramG 191167 Description SafetyEvaluationInspectionandTestingSafetyEvaluation Page22of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure4.3 3 DeleteFigure4.3 3,RecirculationPumpPipingandInstrumentationDiagram.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.3 3isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.Figure4.3 4 DeleteFigure4.3 4,JetPumpOperatingPrinciple.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.3 4isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.Figure4.3 5 DeleteFigure4.3 5,RecirculationSystemCoreFloodingCapability.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.3 5isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.4.4 4.4.1 DeleteSection4.4.1,PowerGenerationObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.4.4.2 DeleteSection4.4.2,SafetyObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.4.4.3 DeleteSection4.4.3,PowerGenerationDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete 4.4.4 DeleteSection4.4.4,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Consequently,depressurizationisnotrequired Therefore,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.4.4.5 DeleteSection4.4.5,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.4.4.6 DeleteSection4.4.6,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.ANuclearSystemPressureReliefSystemsafetyevaluationisnotrequired,theNuclearSystemPressureReliefsysteminformationisobsolete.4.4.7 DeleteSection4.4.7,PowerGnerationEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.ANuclearSystemPressureReliefSystempowergenerationevaluationisnotrequired,theNuclearSystemPressureReliefsysteminformationisobsolete.4.4.8 DeleteSection4.4.8,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminspectionandtestingisnotrequired,theNuclearSystemPressureReliefsysteminformationisobsolete.RecirculationPumpPipingandInstrumentationDiagramG 191159,Sh5 JetPumpOperatingPrinciple RecirculationSystemCoreFloodingCapability SafetyEvaluation PowerGenerationEvaluation InspectionandTesting NuclearSystemPressureReliefSystem PowerGenerationObjectives SafetyObjectives PowerGenerationDesignBases SafetyDesignBases Description Page23of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.4.9 DeleteSection4.4.9,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofNuclearSystemPressureReliefSystemarenolongerrequired.ANuclearSystemPressureReliefSystemreferencesnolongerapply;theNuclearSystemPressureReliefsysteminformationisobsolete.Table4.4.1 DeleteTable4.4.1,NuclearSystemSafetyandReliefValves.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.TheNuclearSystemPressureReliefsysteminformationisobsolete.Figure4.4 1 DeleteFigure4.4 1,NuclearSystemPressureReliefSystem,PipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplac e orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired,theinformationprovidedonfigure4.4 1isnolongerapplicable.NuclearSystemPressureReliefSysteminformationisobsolete.Figure4.4 2 DeleteFigure4.4 2,NuclearSystemReliefValveClosedPosition.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired,theinformationprovidedonfigure4.4 2isnolongerapplicable.NuclearSystemPressureReliefSysteminformationisobsolete.Figure4.4 3 DeleteFigure4.4 3,NuclearSystemReliefValveOpenPosition.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired,theinformationprovidedonfigure4.4 3isnolongerapplicable.NuclearSystemPressureReliefSysteminformationisobsolete.Figure4.44PreviouslyDeleted 4.5 4.5.1 1.Deletesection4.5.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorinformationisobsolete.4.5.2 2.Deletesection4.5.2,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorinformationisobsolete.4.5.3 3.Deletesection4.5.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorinformationisobsolete.4.5.4 4.Deletesection4.5.4,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.AMainSteamLineFlowRestrictorSafetyEvaluationisnotrequired.MainSteamLineFlowRestrictorinformationisobsolete.4.5.5 5.Deletesection4.5.5,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorInspectionandTestingisnotrequired.MainSteamLineFlowRestrictorinformationisobsolete.Figure4.5 1 DeleteFigure4.5 1,MainSteamlineFlowRestrictorLocation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.Therefore,theinformationprovidedonfigure4.5 1isnolongerapplicable.MainSteamLineFlowRestrictorinformationisobsolete.4.6 4.6.1 1.DeleteSection4.6.1,SafetyObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thesafetyobjectivesoftheMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.InformationregardingtheMainSteamIsolationValvesisobsolete.4.6.2 2.DeleteSection4.6.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thesafetyDesignBasesoftheMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.InformationregardingtheMainSteamIsolationValvesisobsolete.NuclearSystemReliefValveClosedPosition NuclearSystemReliefValveOpenPosition PreviouslyDeleted MAINSTEAMLINEFLOWRESTRICTOR SafetyObjective SafetyDesignBases References NuclearSystemSafetyandReliefValves NuclearSystemPressureReliefSystem,PipingandInstrumentationDiagramG 191167 SafetyDesignBases Description SafetyDesignBases InspectionandTesting MainSteamlineFlowRestrictorLocation MAINSTEAMLINEISOLATIONVALVES SafetyObjectives Page24of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.6.3 3.DeleteSection4.6.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.InformationregardingtheMainSteamIsolationValvesisobsolete 4.6.4 4.DeleteSection4.6.4,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.AnMSIVsafetyevaluationisnotrequired.InformationregardingtheMainSteamIsolationValvesisobsolete.4.6.5 5.DeleteSection4.6.5,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.MSIVinspectionandtestingisnotrequired.InformationregardingtheMainSteamIsolationValvesisobsolete 4.6.6 6.DeleteSection4.6.6,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur;referencesnolongerapply.InformationregardingtheMainSteamIsolationValvesisobsolete.Figure4.6 1 DeleteFigure4.6 1,RockwellMainSteamIsolationValve CrossSection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.Therefore,theinformationprovidedonFigure4.6 1isnolongerapplicable.InformationregardingtheMainSteamIsolationValvesisobsolete Figure4.6 2 DeleteFigure4.6 2,MainSteamLineIsolationValve,SchematicControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesaren o requiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.Therefore,theinformationprovidedonFigure4.6 2isnolongerapplicable.InformationregardingtheMainSteamIsolationValvesisobsolete 4.7 4.7.1 Deletesection4.7.1,PowerGenerationObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.7.2 Deletesection4.7.2,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.7.3 Deletesection4.7.3,PowerGenerationDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.7.4 Deletesection4.7.4,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.7.5 Deletesection4.7.5,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired;aRCICsafetyevaluationisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.7.6 Deletesection4.7.6,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired;aRCICsafetyevaluationisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.7.7 Deletesection4.7.7,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired;RCICinspectionandtestingisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.MainSteamLineIsolationValve,SchematicControlDiagram5920 6766 REACTORCOREISOLATIONCOOLINGSYSTEM PowerGenerationObjectives SafetyObjective PowerGenerationDesignBasis SafetyDesignBases Description SafetyEvaluation InspectionandTesting References RockwellMainSteamIsolationValve CrossSection5920 2038,sh.5 Description SafetyEvaluation InspectionandTesting Page25of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table4.7.1 DeleteTable4.7.1,ReactorCoreIsolationCoolingSystemTurbinePumpDesignData.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.RCICsystemTurbinePumpDesignDataisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.Figure4.7 1a DeleteFigure4.7 1a,ReactorCoreIsolationCoolingSystem,PipingandInstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.7 1aisnolongerapplicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.Figure4.7 1b DeleteFigure4.7 1b,ReactorCoreIsolationCoolingSystem,PipingandInstrumentationDiagram,sheet2.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedt o emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.7 1bisnolongerapplicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.Figure4.7 2a DeleteFigure4.7 2a,ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.7 2aisnolongerapplicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.Figure4.7 2b DeleteFigure4.7 2b,ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.7 2bisnolongerapplicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.Figure4.7 2c DeleteFigure4.7 2c,ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.7 2bisnolongerapplicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.Figure4.7 3 DeleteFigure4.7 3,ReactorCoreIsolationCoolingSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinth e reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.7 2bisnolongerapplicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.4.8 TheRHRsystemremoveddecayheatandresidualheatfromthenuclearsystemsothatrefuelingandnuclearsystemservicingcanbeperformed,andsupplementedtheFuelPoolCoolingSystemwhennecessarytoprovideadditionalcoolingcapacity.4.8.1 Deletesection4.8.1,ResidualHeatRemovalSystem,PowerGenerationObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,removalofdecayandresidualheatisnolongerrequired.SinceaLOCAisnolongerpossible,postthepostLOCAfunctionsofRHRarealsonolongerrequired.Additionally,theirradiatedfueldecayheatloadinthefuelpooliswithinthecapacityoffuelpoolcooling,heatremovalsupplementationbytheRHRsystemisnolongerrequired.Therefore,thepowergenerationobjectivesarenolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.4.8.2 Deletesection4.8.2,ResidualHeatRemovalSystem,SafetyObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired.Therefore,thesafetyobjectivesarenolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.4.8.3 Deletesection4.8.3,ResidualHeatRemovalSystem,PowerGenerationDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,removalofdecayandresidualheatisnolongerrequired.Additionally,theirradiatedfueldecayheatloadinthefuelpooliswithinthecapacityoffuelpoolcooling,he a removalsupplementationbytheRHRsystemisnolongerrequired.Therefore,anadditionalsourceofwaterforcontainmentfloodingisnotrequired,theRHRpowergenerationdesignbasisisnolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.4.8.4 Deletesection4.8.2,ResidualHeatRemovalSystem,SafetyObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired.Therefore,thesafetydesignbasesarenolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.4.8.5 Deletesection4.8.5,ResidualHeatRemovalSystem,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheRHRsystemarenolongerrequired.Therefore,theinformationprovidedinthedescriptionsectionisnolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.PowerGenerationObjectives SafetyObjectives PowerGenerationDesignBasis ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram5920 25 ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram5920 26 ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram5920 490 ReactorCoreIsolationCoolingSystem,ProcessDiagram5920 605 RESIDUALHEATREMOVALSYSTEM ReactorCoreIsolationCoolingSystemTurbinePumpDesignData ReactorCoreIsolationCoolingSystem,PipingandInstrumentationDiagramG 191174,Sh1 ReactorCoreIsolationCoolingSystemPipingandInstrumentationDiagram,Sheet2G 191174,Sh2 SafetyDesignBases Description Page26of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.8.5.1 Deletesection4.8.5.1,DescriptionoftheShutdownCoolingmodeofoperationofRHR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequentlyareactorshutdownandcooldownwillnolongerbeconducted.Therefore,theShutdownCoolingfunctionsoftheRHRsystemarenolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.4.8.5.2 Deletesection4.8.5.2,DescriptionoftheContainmentCoolingmodeofoperationofRHR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,heatremovalfromthesuppressionpoolfollowingaLOCAisnolongerrequired.Therefore,theContainmentCoolingfunctionsoftheRHRsystemarenolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.4.8.5.3 Deletesection4.8.5.3,DescriptionoftheLowPressureCoolantInjectionmodeofoperationofRHR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,restorationand,maintenanceofthecoolantinventoryinthereactorvesselafteralossofcoolantaccidentisnolongerrequired.Therefore,theLowPressureCoolantInjectionfunctionsoftheRHRsystemarenolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.4.8.6 Deletesection4.8.6,ResidualHeatRemovalSystem,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SincethefunctionsoftheRHRsystemarenolongerrequiredasafetyevaluationisalsonolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.4.8.7 Deletesection4.8.7,ResidualHeatRemovalSystem,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRHRsystemarenolongerrequired,inspectionandtestingoftheRHRsystemisalsonolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.Table4.8.1 DeleteTable4.8.1,ResidualHeatRemovalSystemEquipmentDesignData.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRHRsystemarenolongerrequired.TheinformationprovidedinTable4.8.1isnolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.Figure4.8 1 DeleteFigure4.8 1,ResidualHeatRemovalSystemProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheRHRsystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.8 1isnolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.Figure4.8 2 DeleteFigure4.8 2,ResidualHeatRemovalSystem,Pipingand InstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheRHRsystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.8 2isnolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.4.9 4.9.1 Deletesection4.9.1,PowerGenerationObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.ReactorWaterCleanupSysteminformationisobsolete.4.9.2 Deletesection4.9.2,PowerGenerationDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.ReactorWaterCleanupSysteminformationisobsolete.4.9.3 Deletesection4.9.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.ReactorWaterCleanupSysteminformationisobsolete.4.9.4 Deletesection4.9.4,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired;inspectionandtestingoftheReactorWaterCleanupSystemisnotrequired.ReactorWaterCleanupSysteminformatio n isobsolete.Table4.9.1 5.DeleteTable4.9.1,ReactorWaterCleanupSystemEquipmentDesignData.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.ReactorWaterCleanupSysteminformationisobsolete.ResidualHeatRemovalSystemEquipmentDesignData ResidualHeatRemovalSystemProcess Diagram5920 725 ResidualHeatRemovalSystem,Pipingand InstrumentationDiagramG191172 REACTORWATERCLEANUPSYSTEM PowerGenerationObjectivesPowerGenerationDesignBases ContainmentCoolingSubsystem LowPressureCoolantInjectionSubsystem SafetyEvaluation InspectionandTesting ShutdownCoolingSubsystem Description InspectionandTesting ReactorWaterCleanupSystemEquipmentDesign Page27of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure4.9 1 DeleteFigure4.9 1,ReactorWaterCleanupSystemPipingandInstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.9 1isnolongerapplicable.ReactorWaterCleanupSysteminformationisobsolete.Figure4.9 2 DeleteFigure4.9 2,ReactorWaterCleanupSystemProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.9 2isnolongerapplicable.ReactorWaterCleanupSysteminformationisobsolete.Figure4.9 3 DeleteFigure4.9 3,ReactorWaterCleanupFilterDemineralizerSystem,PipingandInstrumentDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.9 3isnolongerapplicable.ReactorWaterCleanupSysteminformationisobsolete.Figure4.9 4 DeleteFigure4.9 4,ReactorWaterCleanupSystemFunctionalControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.9 4isnolongerapplicable.ReactorWaterCleanupSysteminformationisobsolete.4.10 4.10.1 Deletesection4.10.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.4.10.2 Deletesection4.10.2,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.4.10.3 Deletesection4.10.3,Description.Sections4.10.3.1,4.10.3.2,and4.10.3.3arenolongerapplicable.SincethereisnoinformationinSection4.10.3,ithasbeendeleted.4.10.3.1 Deletesection4.10.3.1,IdentifiedLeakageRate.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.DeterminationofIdentifiedLeakageratesisnolongerrequired.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.4.10.3.2 Deletesection4.10.3.2,UnidentifiedLeakageRate.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.DeterminationofIdentifiedLeakageratesisnolongerrequired.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.4.10.3.3 Deletesection4.10.3.3,TotalLeakageRate.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.DeterminationofTotalLeakageratesisnolongerrequired.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.4.10.4 Deletesection4.10.4,ActionsUponDiscoveryofaLeak.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.Therefore,noactionsarerequiredsincenoleakagewilloccur.AllleakagelimitshavebeenremovedfromPermanentlydefueledtechnicalspecifications.NuclearSystemLeakageDetectionSystemsinformationisobsolete.Table4.10.1 DeleteTable4.10.1,LeakageandDrainageInputstoDrywellsumps.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.Figure4.10 1Nochanges Figure4.5.2 4 DrywellSumpsDiagramG 191177,Sh1 UnidentifiedLeakageRate TotalLeakageRate ActionsUponDiscoveryofaLeakLeakageandDrainageInputstoDrywellsumps DrywellSumpsDiagramG 191177,Sh1 ReactorWaterCleanupSystemFunctionalControlDiagram5920 3867 NUCLEARSYSTEMLEAKAGERATELIMITSANDLEAKAGEDETECTIONSYSTEMS SafetyObjectiver SafetyDesignBases Description IdentifiedLeakageRate ReactorWaterCleanupSystemPipingandInstrumentationDiagramG 191178,Sh1 ReactorWaterCleanupSystemProcessDiagram5920 429 ReactorWaterCleanupFilterDemineralizerSystem,PipingandInstrumentDiagramG 191178,Sh2 Page28of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.0 5.1 5.1.1 Deletesection5.1.1,ContainmentSystem,Summary,General.ContainmentSystemsarenotrequiredfollowingcertificationofpermanentdefuelingandanalysisoffuelhandlingaccident.Seesections5.2,PrimaryContainmentandSection5.3,SecondaryContainment.

5.1.2 Deletesection5.1.2,PrimaryContainmentdescriptionhasbeendeletedfromtheSAR.Seesection5.2,PrimaryContainment 5.1.3 Deletesection5.1.3,SecondaryContainmentdescriptionhasbeendeletedfromtheSAR.Seesection5.3,SecondaryContainment 5.2 5.2.1 Deletesection5.2.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.PrimaryContainmentSysteminformationisobsolete.5.2.2 Deletesection5.2.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequiredandthesafetydesignbasesarenolongerapplicable.PrimaryContainmentSysteminformationisobsolete.5.2.3 Deletesection5.2.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.TheinformationprovidedintheDescriptionsectionisnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.5.2.4 Deletesection5.2.4,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Aprimarycontainmensafetyevaluaionisnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.5.2.5 Deletesection5.2.5,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.PrimaryContainmentInspectionandTestingisnotrequired.PrimaryContainmentSysteminformationisobsolete.5.2.6 DeleteSection5.2.6,ContainmentInerting.Subsections5.2.6.1,SafetyDesignBasis,5.2.6.2,SystemDescription,5.2.6.3,SafetyEvaluationand5.2.6.4,NitrogenSupplySystemInspectionandTestinghavebeendeleted.5.2.6.1 Deletesection5.2.6.1,PrimaryContainmentInertingSafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.PrimaryContainmentInertingSysteminformationisobsolete.5.2.6.2 Deletesection5.2.6.2,PrimaryContainmentInertingSystemDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.TheinformationprovidedinthePrimaryContainmentInertingSystemDescriptionsectionisnolongerapplicable.PrimaryContainmentInertingSysteminformationisobsolete.5.2.6.3 Deletesection5.2.6.3,PrimaryContainmentInertingSystemSafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.TheinformationprovidedinthePrimaryContainmentInertingSystemSafetyEvaluationsectionisnolongerapplicable.PrimaryContainmentInertingSysteminformationisobsolete.5.2.6.4 Deletesection5.2.6.4,NitrogenSupplySystemInspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.TheinformationprovidedintheNitrogenSupplySystemInspectionandTestingsectionisnolongerapplicable.PrimaryContainmentInertingSysteminformationisobsolete.5.2.7 DeleteSection5.2.7,ContainmentAtmosphericDilution(CAD)System.Subsections5.2.7.1,SafetyDesignBasis,5.2.7.2,SystemDescription,5.2.7.3,SystemOperation,5.2.7.4,SafetyEvaluationand5.2.7.5,ContainmentAtmosphericDilution(CAD)SystemInspectionandTestinghavebeendeleted.5.2.7.1 DeleteSection5.2.7.1,ContainmentAtmosphericDilution(CAD)SystemSafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSafetyDesignBasissectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.Containment SafetyEvaluation InspectionandTesting PrimaryContainmentInerting SafetyDesignBasis SystemDescription SafetyEvaluation SecondaryContainment PRIMARYCONTAINMENTSYSTEM SafetyObjective SafetyDesignBases Description

SUMMARY

DESCRIPTION General PrimaryContainment NSSInspectionandTesting ContainmentAtmosphereDilutionSystem SafetyDesignBasis Page29of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.2.7.2 DeleteSection5.2.7.2,ContainmentAtmosphericDilution(CAD)SystemDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSystemDescriptionsectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.5.2.7.3 DeleteSection5.2.7.3,ContainmentAtmosphericDilution(CAD)SystemOperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSystemOperationsectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.5.2.7.4 DeleteSection5.2.7.4,ContainmentAtmosphericDilution(CAD)SystemOperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSystemSafetyEvaluationsectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.5.2.7.5 DeleteSection5.2.7.5,ContainmentAtmosphericDilution(CAD)SystemInspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSystemInspectionandTestingsectionisnolongerapplicable.

5.2.8 DeleteSection5.2.8,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSystemReferencessectionisnolongerapplicable.Table5.2.1 DeleteTable5.2.1,PrincipalDesignParametersofPrimaryContainment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossibl e Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired;theinformationprovidedinTable5.2.1isnolongerapplicable.

Table5.2.2 DeleteTable5.2.2,PrimaryContainmentSystemPenetrationsandAssociatedContainmentIsolationValves.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired;theinformationprovidedinTable5.2.2isnolongerapplicable.

Figure5.2 1 DeleteFigure5.2 1,PrimaryContainmentVessels.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationprovidedonfigure5.2 1isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 2 DeleteFigure5.2 2,PrimaryContainmentSystemPipingandInstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingprimarycontainmentsystempipingandinstrumentationprovidedonfigure5.2 2isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 3 DeleteFigure5.2 3,TypesofPenetrationsforProcessLines.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingtypesofprimarycontainmentpenetrationsforprocesslinesprovidedonfigure5.2 3isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 4 DeleteFigure5.2 4,PenetrationAssemblyforProcessLines.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingpenetrationassembliesforprocesslinesprovidedonfigure5.2 4isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 5 DeleteFigure5.2 5,ElectricalandControlPenetrations.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingelectricalandcontrolcontainmentpenetrationsprovidedonfigure5.2 5isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.TypesofPenetrationsforProcessLines PenetrationAssemblyforProcessLines ElectricalandControlPenetrations SystemInspectionandTesting References PrincipalDesignParametersofPrimaryContainment PrimaryContainmentSystemPenetrationsandAssociatedContainmentIsolationValves PrimaryContainmentVessels5920 45 PrimaryContainmentSystemPipingand InstrumentationDiagramG 191175,Sh1 SystemDescription SystemOperation SafetyEvaluation Page30of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure5.2 6 DeleteFigure5.2 6,EnergyAbsorberDetailInstalledAgainstDrywell.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingenergyabsorberinstalledagainstthedrywell,providedonfigure5.2 6,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 7 DeleteFigure5.2 7,NitrogenSupplySubsystemPrimaryContainmentAtmosphereControlSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingthecontainmentinertingnitrogensupplysubsystem,providedonfigure5.2 7,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 8 DeleteFigure5.2 8,EngineeringFlowDiagramContainmentAtmosphereDilutionSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingthecontainmentcontainmentatmospheredilutionsubsystem,providedonfigure5.2 8,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.Figure5.2 9 DeleteFigure5.2 9,DrywellTemperatureResponsetoSmallSteamLineBreaks.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingthetemperatureresponsetosmallsteamlinebreaksinthedrywel providedonfigure5.2 9,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.5.3 5.3.1 DeleteSection5.3.1,SecondaryContainmentSystemSafetyObjective.SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.Consequently,theSecondaryContainmentsafetyobjectiveisnotapplicable.SecondaryContainmentinformationisobsolete.5.3.2 DeleteSection5.3.2,SecondaryContainmentSystemGeneral.SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatsecondarycontainmentisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,theinformationprovidedintheSecondaryContainmentGeneralsectionisnotapplicable.SecondaryContainmentinformationisobsolete.5.3.3 5.3.3.1 DeleteSection5.3.3.1,ReactorBuildingSecondaryContainmentSafetyObjective.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdufuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theReactorBuildingSafetyObjectiveisnotapplicable.SecondaryContainmentinformationisobsolete.EnergyAbsorberDetailInstalledAgainst Drywell NitrogenSupplySubsystemPrimary ContainmentAtmosphereControlSystemG 191175,Sh2 EngineeringFlowDiagramContainment AtmosphereDilutionSystem(CAD)VY E 75 002 DrywellTemperatureResponsetoSmall SteamLineBreaks SECONDARYCONTAINMENTSYSTEM SafetyObjective General ReactorBuilding SafetyObjective Page31of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.3.2 DeleteSection5.3.3.2,ReactorBuildingSecondaryContainmentSafetyDesignBasis.SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdufuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theReactorBuildingSafetyDesignBasisisnotapplicable.SecondaryContainmentinformationisobsolete.5.3.3.3 DeleteSection5.3.3.3,ReactorBuildingSecondaryContainmentDescription.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.Consequently,theinformationprovidedintheReactorBuildingDescriptionSectionisnotapplicable.SecondaryContainmentinformationisobsolete.5.3.3.4 DeleteSection5.3.3.4,ReactorBuildingSecondaryContainmentSafetyEvaluation.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthatthesecondarycontainmentfunctionoftheReactorBuildingisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,asafetyevaluationoftheReactorBuildingSecondaryContainmentfunctionisnolongerrequired.SecondaryContainmentinformationisobsolete.5.3.3.5 DeleteSection5.3.3.5,ReactorBuildingSecondaryContainmentInspectionandTesting.SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthatthesecondarycontainmentfunctionoftheReactorBuildingisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,ainspectionandtestingoftheReactorBuildingSecondaryContainmentfunctionisnolongerrequired.SecondaryContainmentinformationisobsolete.5.3.4 TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.5.3.4.1 DeleteSection5.3.4.1,StandbyGasTreatmentSystemSafetyObjective.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theStandbyGasTreatmentSystemSafetyObjectiveisnotapplicable.SecondaryContainmentinformationisobsolete.SafetyDesignBasis Description SafetyEvaluation InspectionandTesting StandbyGasTreatmentSystem SafetyObjective Page32of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.4.2 DeleteSection5.3.4.2,StandbyGasTreatmentSystemSafetyDesignBasis.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theStandbyGasTreatmentSystemSafetyDesignBasisisnotapplicable.SecondaryContainmentinformationisobsolete.5.3.4.3 DeleteSection5.3.4.3,StandbyGasTreatmentSystemDescription.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theinformationprovidedintheStandbyGasTreatmentDescriptionSectionisnolongerapplicable.SecondaryContainmentinformationisobsolete.5.3.4.4 DeleteSection5.3.4.4,StandbyGasTreatmentSystemSafetyEvaluation.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,asafetyevaluationoftheStandbyGasTreatmentSystemisnolongerrequired.SecondaryContainmentinformationisobsolete.5.3.4.5 DeleteSection5.3.4.5,StandbyGasTreatmentSystemInspectionandTesting.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,inspectionandtestingoftheStandbyGasTreatmentSystemisnolongerrequired.SecondaryContainmentinformationisobsolete.5.3.5 5.3.5.1 ModifySection5.3.5.1,RBHVACPowerGenerationObjectivetodelete"PowerGeneration",sincefollowingcertificationofpermanentdefuelingpoweroperationsarenolongerpermitted.Informationmovedtosection10.12.3.1,RBNormalHVAC 5.3.5.2 ModifySection5.3.5.2,RBHVACPowerGenerationDesignBasistodelete"PowerGeneration",sincefollowingcertificationofpermanentdefuelingpoweroperationsarenolongerpermitted,removereferencestostationoperations,refueling,shutdownandhotstandby.Informationmovedtosection10.12.3.1,RBNormalHVAC 5.3.5.3 DeleteSection5.3.5.3,RBHVACSafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theRBHVACsafetydesignbasisisnolongerrequired.5.3.5.4 ModifySection5.3.5.4,RBHVACDescriptiontoremovereferencetoplantoperation,accidentsandotherconditionswhicharenolongerapplicable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheRBHVACsystemtoaddressthoseconditionsarenolongerrequired.Informationmovedtosection10.12.3.1,RBNormalHVAC SafetyDesignBasis Description SafetyEvaluation InspectionandTesting ReactorBuildingNormalHVAC Description PowerGenerationObjective PowerGenerationDesignBasis Safety Design Basis Page33of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.5.5 DeleteSection5.3.5.5,RBHVACSafetyEvaluation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,asafetyevaluationoftheRBHVACsystemisnolongerrequired.5.3.5.6 ModifySection5.3.5.4,RBHVACDescriptiontoremovereferencetoplantoperation,accidentsandotherconditionswhicharenolongerapplicable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheRBHVACsystemtoaddressthoseconditionsarenolongerrequired.InspectionandtestingoftheRBHVACsystemwillbeconductedasappropriateforthedefueledstate.Informationmovedtosection10.12.3.1 RBNormalHVAC 5.3.6 ReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.5.3.6.1 DeleteSection5.3.6.1,ReactorBuildingPenetrationsSafetyObjective.TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,thesafetyobjectiveoftheRBPenetrationsystemisnolongerapplicable.RBPenetrationSysteminformationisobsolete.5.3.6.2 DeleteSection5.3.6.2,ReactorBuildingPenetrationsSafetyDesignBasisTheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,thesafetydesignbasisoftheRBPenetrationsystemisnolongerapplicable.RBPenetrationSysteminformationisobsolete.5.3.6.3 DeleteSection5.3.6.3,ReactorBuildingPenetrationsDescription.TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,theinformationprovidedintheRBPenetrationDescriptionsectionislongerapplicable.RBPenetrationSysteminformationisobsolete.5.3.6.4 DeleteSection5.3.6.4,ReactorBuildingPenetrationsSafetyEvaluation.TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,asafetyevaluationoftheRBPenetrationsystemislongerrequired.RBPenetrationSysteminformationisobsolete.5.3.6.5 DeleteSection5.3.6.5,ReactorBuildingPenetrationsInspectionandTesting.TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,inspectionandtestingoftheRBPenetrationsystemislongerrequired.RBPenetrationSysteminformationisobsolete.5.3.7 TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.ReactorBuildingPenetrations SafetyObjective SafetyDesignBasis Description

SafetyEvaluation InspectionandTesting SafetyEvaluation InspectionandTesting MSIVAlternateLeakageTreatmentPath Page34of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.7.1 DeleteSection5.3.7.1,MSIVALTPath,Background.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.Therefore,ALTrelatedinformationisobsolete.5.3.7.2 DeleteSection5.3.7.2,MSIVALTPath,SafetyObjective.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.TheALTsafetyobjectiveisnolongerapplicable.ALTrelatedinformationisobsolete.5.3.7.3 DeleteSection5.3.7.3,MSIVALTPath,SafetyDesignBasesTheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.TheALTsafetydesignbasesarenolongerapplicable.ALTrelatedinformationisobsolete.5.3.7.4 DeleteSection5.3.7.4,MSIVALTPath,Description.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.TheinformationprovidedintheALTdescriptionsectionisnolongerapplicable.ALTrelatedinformationisobsolete.5.3.7.5 DeleteSection5.3.7.5,MSIVALTPath,SafetyEvaluation.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.Therefore,asafetyevaluationoftheALTpathisnolongerrequired.ALTpathrelatedinformationisobsolete.5.3.7.6 DeleteSection5.3.7.6,MSIVALTPath,SeismicVerification.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.Therefore,thesystemsintheALTpathwayarenolongerrequiredtobeseismictosupporttheALTfunction.ALTpathrelatedinformationisobsolete.5.3.7.7 DeleteSection5.3.7.7,MSIVALTPath,RadiologicalAnalysis.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.Therefore,aRadiologicalAnalysisoftheeffectivenessoftheALTpathduringaDBAisnolongerrequired.ALTpathrelatedinformationisobsolete.5.3.7.8 DeleteSection5.3.7.8,MSIVALTPath,InspectionandTesting.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.Therefore,inspectionandtestingofthecomponentsintheALTpathisnolongerrequired.ALTpathrelatedinformationisobsolete.SeismicVerification RadiologicalAnalysis InspectionandTesting Background SafetyObjective SafetyDesignBases Description

SafetyEvaluation Page35of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.8DeleteSection5.3.8,SecondaryContainmentSystemReferences.SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatsecondarycontainmentisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.consequently,theSecondaryContainmentreferencesarenolongerapplicable.SecondaryContainmentinformationiaobsolete.Table5.3.1 DeleteTable5.3.1,StandbyGasTreatmentSystem,ReactorBuildingVacuumDataWithOneSGTTrainOperating.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.consequently,theinformationprovidedintable5.3.1isnotapplicablesinceSBGTisnolongerreliedontomitigatetheconsequencesofafuelhandlingaccidentand.therefore,willnolongerbeoperated.SecondaryContainmentinformationisobsolete.Figure5.3 1 DeleteFigure5.3 1,SecondaryContainmentSystem-ReactorBuilding-CalculatedExfiltrationRateVersusWindVelocity.SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasisaccidentoccur.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthatthesecondarycontainmentfunctionoftheReactorBuildingisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,theinformationprovidedonFigure5.3 1isnotapplicable.SecondaryContainmentinformationisobsolete.Figure5.32Movedtosection10.12 Figure5.3 3 DeleteFigure5.3 3,MainSteamIsolationValveAlternateLeakageTreatmentPath.TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC 19withaleakagerateof62scfhperMSIVwithatotalleakagerateof124scfhthroughthemainsteampathways.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicablesincetheconditionsaddressedbyALTarenolongerpossible.TheinformationprovidedonFigure5.3 3isnolongerapplicable.ALTrelatedinformationisobsolete.6.0CoreStandbyCoolingSystems 6.1 6.1.1 DeleteSection6.1.1,CoreStandbyCoolingSystemsSafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theSafetyObjectiveisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.6.2 DeleteSection6.2,CoreStandbyCoolingSystemsSafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theSafetyDesignBasesarenolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.6.3 DeleteSection6.3,SummaryDescriptionCoreStandbyCoolingSystems.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedintheCSCSsummarydescriptionsectionisnolongerapplicable.InformationregardingtheCSCSsisobsolete.Table6.3.1 DeleteTable6.3.1,CoreStandbyCoolingSystemsEquipmentDesignDataSummary.SincetheCSCSsarenolongerrequiredandhavebeendeleted,theinformationprovidedinthistableisobsolete.6.4 6.4.1 DeleteSection6.4.1,HighPressureCoolantInjectionSystemDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedintheHPCIdescriptionsectionisnolongerapplicable.InformationregardingtheHPCIsystemisobsolete.ReactorBuildingHeatingVentilationandAirConditioningG 191238 MainSteamIsolationValveAlternateLeakageTreatmentPath5920 13407 CoreStandbyCoolingSystems SafetyObjective SafetyDesignBases SummaryDescription References ReactorBuildingVacuumDataWithOneSGTTrainOperating SecondaryContainmentSystem-ReactorBuilding-CalculatedExfiltrationRateVersusWindVelocity CoreStandbyCoolingSystemsEquipmentDesignDataSummary DESCRIPTION HighPressureCoolantInjectionSystem Page36of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 6.4.2 DeleteSection6.4.2,AutomaticDepressurizationSystemDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theAutomaticDepressurizationSystemisnolongerrequiredtofunctiontoallowlowpressuresystemstoinjectt o coolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedintheADSdescriptionsectionisnolongerapplicable.InformationregardingtheADSisobsolete.6.4.3 DeleteSection6.4.3,CoreSpraySystemDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theCoreSpraySystemisnolongerrequiredtofunctiontocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedintheCoreSpraydescriptionsectionisnolongerapplicable.InformationregardingtheCoreSpraySystemisobsolete.6.4.4 DeleteSection6.4.4,descriptionoftheLowPressureCoolantInjectionfunctionoftheResidualHeatRemovalSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvironsisnolongerrequired.Therefore,theinformationprovidedintheLPCIdescriptionsectionisnolongerapplicable.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.6.4.5 DeleteSection6.4.5,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thefunctionsoftheCoreStandbyCoolingSystemsarenolongerrequired.TheinformationprovidedintheCoreStandbyCoolingSystemsReferencessectionisnolongerapplicable.

Figure6.4 1 DeleteFigure6.4 1,HighPressureCoolantInjectionSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinth e reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedonfigure6.4 1isnolongerapplicable.InformationregardingtheHPCIsystemisobsolete.Figure6.4 2 DeleteFigure6.4 2,CoreSpraySystem,ProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theCoreSpraySystemisnolongerrequiredtofunctiontocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedintheCoreSpraydescriptionsectionisnolongerapplicable.InformationregardingtheCoreSpraySystemisobsolete.Figure6.4 3 DeleteFigure6.4 3,ResidualHeatRemovalSystem,ProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvironsisnolongerrequired.Therefore,theinformationprovidedonFigure6.4 3isnolongerapplicable.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.6.5 6.5.1 DeleteSection6.5.1,CoreStandbyCoolingSystemsSafetyEvaluation,Summary.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,asafetyevaluationoftheCoreStandbyCoolingSysemsisnotrequired.TheinformationprovidedintheSafetyEvaluation,Summarysectionisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.6.5.2 DeleteSection6.5.2,SafetyEvaluationPerformanceAnalysis.Allsubsectionsofthissummarysectionhavebeenevaluatedanddeleted.Theinformationinthissectionisnotrequiredandisobsolete.6.5.2.1 DeleteSection6.5.1,CoreStandbyCoolingSystemsSafetyEvaluation,PerformanceAnalysis,LOCAAnalysisMethodsandResults.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,aLOCAAnalysisisnotrequired.TheinformationprovidedintheLOCAAnalysisMethodsandResultssectionisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.6.5.2.2 DeleteSection6.5.2.2,HighPressureCoolantInjectionSystemPerformanceAnalysis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,asafetyevaluationandperformanceanalysisoftheHPCISystemisnotrequired.InformationregardingtheHPCIsystemisobsolete.PerformanceAnalysis LOCAAnalysisMethodsandResults HighPressureCoolantInjection(HPCI)System References HighPressureCoolantInjectionSystem,ProcessDiagram5920 784 CoreSpraySystem,ProcessDiagram5920 718 ResidualHeatRemovalSystem,ProcessDiagram5920 725 SAFETYEVALUATION Summary AutomaticDepressurizationSystem CoreSpraySystem LowPressureCoolantInjection Page37of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 6.5.2.3 DeleteSection6.5.2.3,HighPressureCoolantInjectionSystemPerformanceAnalysis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theAutomaticDepressurizationSystemisnolongerrequiredtorapidlydepressurizethepressurevesseltoallowlowpressuresystemstocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,asafetyevaluationandperformanceanalysisoftheAutomaticDepressurizationSystemisnotrequired.InformationregardingADSisobsolete.6.5.2.4 DeleteSection6.5.2.4,CoreSpraySystemPerformanceAnalysis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreSpraySystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,asafetyevaluationandperformanceanalysisoftheCoreSpraySystemisnotrequired.InformationregardingtheCoreSpraysystemisobsolete.6.5.2.5 DeleteSection6.5.2.5,PerformanceAnalysisoftheLowPressureCoolantInjectionfunctionoftheResidualHeatRemovalSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvironsisnotrequired.Therefore,asafetyevaluationandperformanceanalysisoftheLowPressureCoolantInjectionfunctionofRHRisnotrequired.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.6.5.3 DeleteSection6.5.3,CoreStandbyCoolingSystemsSafetyEvaluation,Compliancewith10CFR50.46Requirements.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,demonstrationofcompliancewith10CFR50.46requirementsisnotrequired.TheinformationprovidedintheCompliancewith10CFR50.46Requirementssectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.6.5.4 DeleteSection6.5.4,CoreStandbyCoolingSystemsSafetyEvaluation,CoreStandbyCoolingSystemsRedundancy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,demonstrationofcompliancewith10CFR50.46requirements,includingredundancy,isnotrequired.TheinformationprovidedintheCoreStandbyCoolingSystemsRedundancysectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.6.5.5DeleteSection6.5.4,References.SinceallpartsofSection6.5havebeendeleted,Referencesarenolongerapplicable.

6.6 6.6.1 DeleteSection6.6.1,CoreStandbyCoolingSystemsInspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,thefunctionsoftheCoreStandbyCoolingSystemsarenotrequired.Consequently,demonstrationoftheabilityoftheCSCSstomeettheirfunctionthroughinspectionandtestingisnotrequired.TheinformationprovidedintheCoreStandbyCoolingSystemsInspectionandtestingsectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.6.6.2DeleteSection6.5.4,References.Sincesection6.6.1hasbeendeleted,Referencesarenolongerapplicable.

7.0 ControlandInstrumentation

Deletethisheading,remainingsectioninformationmovedtoothersections 7.1 Deletethisheading,remainingsectioninformationmovedtoothersections 7.1.1 DeleteSection7.1.1,ControlandInstrumentation,ProtectionSystems.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueledstatio n andthefunctionsofProtectionSystemsarenolongerapplicableinthepermanentlydefueledstate.7.1.2 DeleteSection7.1.2,ControlandInstrumentation,PowerGenerationSystems.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefuele d station,andthefunctionsofPowerGenerationSystemsarenolongerapplicableinthepermanentlydefueledstate.7.1.3 DeleteSection7.1.3,ControlandInstrumentation,SafetyFunctions.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueledstation,an d thefunctionsofSafetySystemsarenolongerapplicableinthepermanentlydefueledstate.7.1.4 DeleteSection7.1.4,ControlandInstrumentation,SafetyFunctions.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueledstation,an d thefunctionsofStationOperationalControlSystemsarenolongerapplicableinthepermanentlydefueledstate.AutomaticDepressurizationSystem(ADS)CoreSpraySystem(CSS)LowPressureCoolantInjection(LPCI)

SUMMARY

DESCRIPTION ProtectionSystems PowerGenerationSystems SafetyFunctions StationOperationalControl ComplianceWith10CFR50.46Requirements CoreStandbyCoolingSystemsRedundancy References INSPECTIONANDTESTING Summary References Page38of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.1.5DeleteSection7.1.5,Definitions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therrefore,manyofthedefinitionsinthissectionarenolongerapplicable.

TheSSCclassificationprocessdescribedinUFSARsection1.4,ClassificationofBWRSystems,Criteria,andRequirementsisnotapplicableinthedefueledstateandhasbeendeleted.ManyofthedefinitionsprovidedinthissectiondefinetermsrelatedtotheSSCClassificationprocessandtherefore,arenolongerapplicable Additionally,manyofthedefinitionsprovidedinthissectionarealreadydefinedinmoreappropriatedocumentation,includingTechnicalSpecificationsandtheTechnicalRequiementsManual.Finally,manyofthedefinitionsprovidedinthissectionarenolongerusedintheDSAR.Therefore,theinformationinthissectionishistorcalandobsoleteandmaybedeleted.7.1.6 DeleteSection7.1.6,ControlandInstrumentation,IdentificationofSafetySystems.Sincethefunctionsofsafetysystemsarenolongerrequiredfollowingpermanentdefueling,specificidentificationofthoseSSCsisalsonolongerrequired.7.1.7 DeleteSection7.1.7,ControlandInstrumentation,DetailedDesignReview.Thissectioncontainshistoricinformationwhichisnotapplicablefollowingcertificationofpermanentdefueling.

7.1.8 Deletesection7.1.8,EnvironmentalQualification.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIA W 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theassurancesprovidedbytheEnvironmentalQualificationProgramarenolongerrequired.7.1.9 Deletesection7.1.9,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thereferenescitedinthissectionarenolongerapplicable.Alltextcitingthesereferenceshasbeendeletedfromthissection.Figure7.1 1 DeleteFigure7.1 1,UseofProtectionSystemControlandInstrumentationDefinitions.Figureisnolongerrequiredsincetheentiresectionhasbeendeleted.7.2 7.2.1 DeleteSection7.2.1,ReactorProtectionSystemSafetyObjective.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theRPSSafetyObjectiveisnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.7.2.2 DeleteSection7.2.2,ReactorProtectionSystemSafetyDesignBases.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theRPSSafetyObjectiveisnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.7.2.3 DeleteSection7.2.3,ReactorProtectionSystemDescription.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSystemDescriptionprovidedisnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.7.2.4 DeleteSection7.2.4,ReactorProtectionSystemSafetyEvaluation.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;asafetyevaluationoftheReactorProtectionSystemisnotrequiredsincethefunctionsoftheReactorProtectionSystemarenotrequired.InformationregardingtheReactorProtectionSystemisobsolete.Definitions IdentificationofSafetySystems DetailedControlRoomDesignReview EnvironmentalQualification SafetyDesignBases Description SafetyEvaluation References UseofProtectionSystemControlandInstrumentationDefinitions REACTORPROTECTIONSYSTEM SafetyObjective Page39of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.2.5 DeleteSection7.2.5,ReactorProtectionSystemInspectionandTesting.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;inspectionandtestingoftheReactorProtectionSystemisnotrequiredsincethefunctionsoftheReactorProtectionSystemarenotrequired.TheReactorProtectionSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingtheReactorProtectionSystemisobsolete.Table7.2.1 DeleteTable7.2.1,ReactorProtectionSystemInstrumentation.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired.TheReactorProtectionSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingtheReactorProtectionSystemisobsolete.Table7.2.2 DeleteTable7.2.2,ReactorProtectionSystemInstrumentationEnvironmentalConditions.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 1 DeleteFigure7.2 1,ReactorProtectionSystemInstrumentElectricalDiagram.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 1isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 2 DeleteFigure7.2 2,ReactorProtectionSystem,ControlRoomPanelforOneTripSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 2isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 3 DeleteFigure7.2 3,ReactorProtectionSystem,FunctionControlDiagramforOneTripSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 3isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 4 DeleteFigure7.2 4,SchematicDiagramofLogicsinOneTripSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 4isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 5 DeleteFigure7.2 5,SchematicDiagramofActuatorandActuatorLogics.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelan d nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 5isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.ReactorProtectionSystemInstrumentElectricalDiagram5920 272 ReactorProtectionSystem,ControlRoomPanelforOneTripSystem ReactorProtectionSystem,FunctionControlDiagramforOneTripSystem5920 273 SchematicDiagramofLogicsinOneTripSystem SchematicDiagramofActuatorandActuatorLogics InspectionandTesting ReactorProtectionSystemInstrumentation ReactorProtectionSystemInstrumentationEnvironmentalConditions Page40of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.2 6 DeleteFigure7.2 6,ReactorProtectionSystem,ScramFunctions.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 6isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 7 DeleteFigure7.2 7,ReactorProtectionSystemInstrumentation.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnucle a systemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 7isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 8 DeleteFigure7.2 8,RelationshipBetweenNeutronMonitoringSystemandReactorProtectionSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 8isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 9 DeleteFigure7.2 9,FunctionalControlDiagramforNeutronMonitoringSystemLogics.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 9isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 10 DeleteFigure7.2 10,TypicalArrangementofChannelsandLogics.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 10isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 11 DeleteFigure7.2 11,TypicalConfigurationforTurbineStopValveClosureScram.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromth e fuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 11isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.2 12 DeleteFigure7.2 12,TypicalConfigurationforMainSteamlineIsolationScram.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformationprovidedonfigure7.2 12isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.Figure7.213PreviouslyDeleted Figure7.214PreviouslyDeleted Figure7.215PreviouslyDeleted ReactorProtectionSystem,ScramFunctions ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier Deleted Deleted Deleted 7.3 PRIMARYCONTAINMENTANDREACTORVESSELISOLATIONCONTROLSYSTEM ReactorProtectionSystemInstrumentation5920 274 RelationshipBetweenNeutronMonitoringSystemandReactorProtectionSystem FunctionalControlDiagramforNeutronMonitoringSystemLogics5920 1807 TypicalArrangementofChannelsandLogics TypicalConfigurationforTurbineStopValveClosureScram TypicalConfigurationforMainSteamlineIsolationScram Page41of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.3.1 DeleteSection7.3.1,PrimaryContainmentandReactorVesselIsolationControlSystemSafetyObjective.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.7.3.2 DeleteSection7.3.2,PrimaryContainmentandReactorVesselIsolationControlSystemDefinitions.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.7.3.3 DeleteSection7.3.3,PrimaryContainmentandReactorVesselIsolationControlSystemSafetyDesignBases ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.ThePrimaryContainmentandReactorVesselIsolationControlSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.7.3.4 DeleteSection7.3.4,PrimaryContainmentandReactorVesselIsolationControlSystemDescription.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.InformationprovidedintheDescriptionsectionisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.7.3.5 DeleteSection7.3.5,PrimaryContainmentandReactorVesselIsolationControlSystemSafetyEvaluation.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.AsafetyevaluationofthePrimaryContainmentandReactorVesselIsolationControlSystemisnolongerrequired.ThePrimaryContainmentandReactorVesselIsolationControlSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingthePrimaryContainmentandReactorVess e IsolationControlSystemisobsolete.7.3.6 DeleteSection7.3.6,PrimaryContainmentandReactorVesselIsolationControlSystemInspectionandTesting.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.InspectionandTestingofthePrimaryContainmentandReactorVesselIsolationControlSystemisnolongerrequired.ThePrimaryContainmentandReactorVesselIsolationControlSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingthePrimaryContainmentandReactorVess e IsolationControlSystemisobsolete.SafetyObjective Definitions InspectionandTesting SafetyDesignBases Description SafetyEvaluation Page42of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.3.7 DeleteSection7.3.7,PrimaryContainmentandReactorVesselIsolationControlSystemReferences.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Referencesarenolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Table7.3.1 DeleteTable7.3.1,PrimaryContainmentandReactorVesselIsolationActuation.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.TheinformationpresentedinTable7.3.1isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Table7.3.2 DeleteTable7.3.2,PrimaryContainmentandReactorVesselIsolationControlSystemInstrumentation.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.TheinformationpresentedinTable7.3.2isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 1 DeleteFigure7.3 1,NuclearSystem,PipingandInstrumentationDiagram.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 1isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 2 DeleteFigure7.3 2,TypicalIsolationControlSystemUsingMotorOperatedValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 2isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 3 DeleteFigure7.3 3,TypicalIsolationControlSystemforMainSteamlineIsolationValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 3isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.34aPreviouslyDeleted NuclearSystem,PipingandInstrumentationDiagramG 191167 TypicalIsolationControlSystemUsingMotorOperatedValves TypicalIsolationControlSystemforMainSteamlineIsolationValves Deleted References PrimaryContainmentandReactorVesselIsolationActuation PrimaryContainmentandReactorVesselIsolationControlSystemInstrumentation Page43of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.3 4b DeleteFigure7.3 4b,MainSteamLineIsolationValve,SchematicControlDiagram.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 4bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 5a DeleteFigure7.3 5a,NuclearBoilerMiscellaneousSystems,FunctionalControlDiagram.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 5aisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 5b DeleteFigure7.3 5b,PrimaryContainmentandReactorVesselIsolationControlSystem,FunctionalControlDiagram.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 5bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 6 DeleteFigure7.3 6,AreaandCompartmentLeakageDetectionbyTemperatureMeasurement.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 6isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 7A DeleteFigure7.3 7A,TypicalHighTemperatureChannels.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 7Aisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 7B DeleteFigure7.3 7B,RWCSHighFlowChannel.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 7Bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 8 DeleteFigure7.3 8,TypicalArrangementforMainSteamlineLeakDetectionbyFlowMeasurement.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 8isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.MainSteamLineIsolationValve,SchematicControlDiagram5920 6766 NuclearBoilerMiscellaneousSystems,FunctionalControlDiagram5920 612,Sh1 PrimaryContainmentandReactorVesselIsolationControlSystem,FunctionalControlDiagram AreaandCompartmentLeakageDetectionbyTemperatureMeasurement TypicalHighTemperatureChannels RWCSHighFlowChannel TypicalArrangementforMainSteamline LeakDetectionbyFlowMeasurement Page44of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.3 9 DeleteFigure7.3 9,MainSteamlineHighFlowChannels.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 9isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 10 DeleteFigure7.3 10,RCICElbowTapArrangementforGrossLeakDetection.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 10isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 11 DeleteFigure7.3 11,TypicalElbowTapArrangementforGrossLeakDetection.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 11isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12A DeleteFigure7.3 12A,IsolationControlSystem,TypicalTripSystem.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12Aisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12B DeleteFigure7.3 12B,IsolationControlSystem,TypicalTripSystem.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12Bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12c DeleteFigure7.3 12c,IsolationControlSystem,TypicalControlsforInboardMainSteamlineIsolationValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12cisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12d DeleteFigure7.3 12d,IsolationControlSystem,TypicalControlsforOutboardMainSteamlineIsolationValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12disnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.RCICElbowTapArrangementforGrossLeakDetection TypicalElbowTapArrangementforGrossLeakDetection IsolationControlSystem,TypicalTripSystemB5920 2093Sheet1&2 IsolationControlSystem,TypicalTripSystemA5920 2092Sheet1&2 IsolationControlSystem,TypicalControlsforInboardMainSteamlineIsolation Valves5920 20945920 2095IsolationControlSystem,TypicalControlsforOutboardMainSteamlineIsolationValves5920 2096 MainSteamlineHighFlowChannels Page45of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.3 12e DeleteFigure7.3 12e,IsolationControlSystem,TypicalControlsforRHRSandReactorWaterCleanupValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12eisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12F DeleteFigure7.3 12F,IsolationControlSystem,TypicalControlsforRHRSShutdownCoolingValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12Fisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12g DeleteFigure7.3 12g,IsolationControlSystem,TypicalControlsforReactorWaterCleanupSystemValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12gisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12h DeleteFigure7.3 12h,IsolationControlSystem,TypicalControlsforRHRSDischargetoRadwasteValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12hisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12i DeleteFigure7.3 12i,IsolationControlSystem,TypicalControlsforMainSteamlineDrainValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12iisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12j DeleteFigure7.3 12j,IsolationControlSystem,TypicalControlsforRecirculationLoopSampleValves.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12jisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.Figure7.3 12k DeleteFigure7.3 12k,IsolationControlSystem,TypicalControlsforTIPSystem.ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitoredvariablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuelandnuclearsystemprocessbarrier,FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactorVesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.3 12kisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.IsolationControlSystem,TypicalControlsforRHRSandReactorWaterCleanupValves5920 2098 IsolationControlSystem,TypicalControlsforRHRSShutdownCoolingValves 5920 2099 IsolationControlSystem,TypicalControlsforReactorWaterCleanupSystemValves5920 2101 IsolationControlSystem,TypicalControlsforRHRSDischargetoRadwasteValves 5920 2100 IsolationControlSystem,TypicalControlsforMainSteamlineDrainValves5920 2097 IsolationControlSystem,TypicalControlsforRecirculationLoopSampleValves5920 2094 IsolationControlSystem,TypicalControlsforTIPSystem5920 2094 Page46of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR7.4SeeSection6.0,CoreStandbyCoolingSystems 7.4.1 DeleteSection7.4.1,CoreStandbyCoolingSystems(CSCS)ControlandInstrumentationSafetyObjective.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsinitiatedappropriateresponsesfromthevariouscoolingsystemssothatthefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSarenolongerrequired;theCSCSSafetyObjectiveisnotapplicablesincethereisnocoretoprotect.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlandInstrumentationisobsolete.7.4.2 DeleteSection7.4.2,CoreStandbyCoolingSystems(CSCS)ControlandInstrumentationSafetyDesignBases.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsinitiatedappropriateresponsesfromthevariouscoolingsystemssothatthefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired;theCSCSSafetyDesignBasesarenotapplicablesincethereisnocoretoprotect.TheCSCSfunctionsoftheassociatedsystemshavebeencategorizedasabandonedinaccordancewiththeassociatedEngineeringChanges.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlandInstrumentationisobsolete.7.4.3 7.4.3.1 DeleteSection7.4.3.1,CoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationIdentification.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.7.4.3.2 DeleteSection7.4.3.2,HighPressureCoolantInjectionSystemControlsandInstrumentationDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactiv materialtotheenvirons.Therefore,theHPCISystemControlsandInstrumentationarealsonolongerrequired.InformationprovidedintheHPCIControlsandInstrumentationdescriptionsectionisnolongerapplicable.InformationregardingtheHPCIsystemisobsolete.7.4.3.3 DeleteSection7.4.3.3,AutomaticDepressurizationSystemControlandInstrumentationDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theAutomaticDepressurizationSystemisnolongerrequiredtofunctiontoallowlowpressuresystemstoinjecttocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theADSControlsandInstrumentationarealsonolongerrequired.TheinformationprovidedintheADSControlandInstrumentationDescriptionsectionisnolongerapplicable.InformationregardingtheADSisobsolete.7.4.3.4 DeleteSection7.4.3.4,CoreSpraySystemControlandInstrumentationDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theCoreSpraySystemisnolongerrequiredtofunctiontocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theCoreSpraySystemControlsandInstrumentationarealsonolongerrequired.TheinformationprovidedintheCoreSpraydescriptionsectionisnolongerapplicable.InformationregardingtheCoreSpraySystemisobsolete.7.4.3.5 DeleteSection7.4.3.5,descriptionoftheLowPressureCoolantInjectionControlandInstrumentationfunctionoftheResidualHeatRemovalSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvironsisnolongerrequired.Therefore,theLPCISystemControlsandInstrumentationarealsonolongerrequired.TheinformationprovidedintheLPCIdescriptionsectionisnolongerapplicable.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.HPCIControl&Instrumentation ADSControl&Instrumentation CoreSprayControl&Instrumentation LPCIControl&Instrumentation CORESTANDBYCOOLINGSYSTEMSCONTROLANDINSTRUMENTATION SafetyObjective SafetyDesignBases Description Identification Page47of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.4.4 DeleteSection7.4.4,CoreStandbyCoolingSystemsInstrumentationandControlsSafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theCSCSControlsandInstrumentationarealsonolongerrequired.AsafetyevaluationoftheCoreStandbyCoolingSysemsControlsandInstrumentationisnotrequired.TheinformationprovidedintheSafetyEvaluationsectionisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.7.4.5 DeleteSection7.4.5,CoreStandbyCoolingSystemsControlsandInstrumentationInspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,thefunctionsoftheCoreStandbyCoolingSystemsarenotrequired.Consequently,demonstrationoftheabilityoftheCSCSstomeettheirfunctionthroughinspectionandtestingoftheCSCSControlsandInstrumentationisnotrequired.TheinformationprovidedintheCoreStandbyCoolingSystemsControlsandInstrumentationInspectionandtestingsectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.7.4.6DeleteSection7.4.6,References.Sincesection7.4hasbeendeleted,Referencesarenolongerapplicable.

Table7.4.1 DeleteTable7.4.1,HPCIInstrumentation.Section7.4.3.2,HPCISystemControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingHPCISysteminstrumentationisnolongerrequired.Informationprovidedinthetableisobsolete.Table7.4.2 DeleteTable7.4.2,ADSInstrumentation.Section7.4.3.3,ADSControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingADSinstrumentationi s nolongerrequired.Informationprovidedinthetableisobsolete.Table7.4.3 DeleteTable7.4.3,CoreSpraySystemInstrumentation.Section7.4.3.4,CoreSpraySystemControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingCoreSpraySysteminstrumentationisnolongerrequired.Informationprovidedinthetableisobsolete.Table7.4.4 DeleteTable7.4.4,LPCISystemInstrumentation.Section7.4.3.5,LPCISystemControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingLPCISysteminstrumentationisnolongerrequired.Informationprovidedinthetableisobsolete.Figure7.4 1A DeleteFigure7.4 1A,HighPressureCoolantInjectionSystemArrangement.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 1Aisnolong e applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 1B DeleteFigure7.4 1B,HighPressureCoolantInjectionSystem,TurbineandPumpUnit.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 1Bisnolonge applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 2a DeleteFigure7.4 2a,HighPressureCoolantInjectionSystem,TurbineandPumpUnit.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 2aisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 2b DeleteFigure7.4 2b,HighPressureCoolantInjectionSystem,MiscellaneousComponents,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 2bisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.References HighPressureCoolantInjectionSystemInstrumentation AutomaticDepressurizationSystemInstrumentation CoreSpraySystemInstrumentation LowPressureCoolantInjectionInstrumentation HighPressureCoolantInjectionSystemArrangementG 191169 SafetyEvaluation InspectionandTesting G 191169,Sh2HighPressureCoolantInjectionSystem,TurbineandPumpUnit 5920 38HighPressureCoolantInjectionSystemValves,FunctionalControlDiagram 5920 39HighPressureCoolantInjectionSystem,MiscellaneousComponents,FunctionalControlDiagram Page48of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.4 2c DeleteFigure7.4 2c,HighPressureCoolantInjectionSystem,TurbineFunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolin g providedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 2cisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 3 DeleteFigure7.4 3,AutomaticDepressurizationSystem,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 3isnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 4 DeleteFigure7.4 4,CoreSpraySystemPipingandInstrumentDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 4isnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 5 DeleteFigure7.4 5,CoreSpraySystem,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 5isnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 6 DeleteFigure7.4 6,ResidualHeatRemovalSystem,PipingandInstrumentationDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolin g providedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 6isnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 7a DeleteFigure7.4 7a,ResidualHeatRemovalSystem,LPCIPumpandValves,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigu r 7.4 7aisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.5920 37CoreSpraySystem,FunctionalControlDiagram G 191172ResidualHeatRemovalSystem,PipingandInstrumentationDiagram 5920 27ResidualHeatRemovalSystem,LPCIPumpandValves,FunctionalControlDiagram 5920 441HighPressureCoolantInjectionSystem,TurbineFunctionalControlDiagram 5920 611AutomaticDepressurizationSystem,FunctionalControlDiagram G 191168CoreSpraySystemPipingandInstrumentDiagram Page49of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.4 7b DeleteFigure7.4 7b,ResidualHeatRemovalSystem,LPCIValves,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolin g providedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 7bisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 7c DeleteFigure7.4 7c,ResidualHeatRemovalSystem,LPCIMiscellaneousComponentsFunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsar e identifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 7cisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.Figure7.4 8 DeleteFigure7.4 8,RecirculationLoopValves,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.4 8isnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.7.5 7.5.1 DeleteSection7.5.1,NeutronMonitoringSystemSafetyObjective.ThesafetyobjectiveoftheNeutronMonitoringSystemwastodetectconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandtoprovidesignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired;theNeutronMonitoringSystemSafetyObjectiveisnotapplicablesincethereisnocoretoprotect.7.5.2 DeleteSection7.5.2,NeutronMonitoringSystemPowerGenerationObjective.ThepowergenerationobjectiveoftheNeutronMonitoringSystemwastoprovideinformationfortheefficient,expedientoperationandcontrolofthereactor.TwospecificpowergenerationobjectivesoftheNeutronMonitoringSystemweretodetectconditionsthatcouldleadtolocalfueldamageandtoprovidesignalsthatwereusedtopreventsuchdamage,sothatstationavailabilitywasnotreduced.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired;theNeutronMonitoringSystemPowerGenerationObjectiveisnotapplicablesincepoweroperationscannolongeroccur.7.5.3DeleteSection,providesonlyatitlelistingofthesixmajorsubsystemsincludedinNeutronMonitoring.7.5.4 7.5.4.1 DeleteSection7.5.4.1,SourceRangeMonitorSubsystem,PowerGenerationDesignBasis.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcoreneutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemarenolongerrequired;theSourceRangeMonitorSubsystemPowerGenerationObjectiveisnotapplicablesinceanuclearcorecannolongerbeloadedintotheRPV.7.5.4.2 DeleteSection7.5.4.2,SourceRangeMonitorSubsystem,Description.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcoreneutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemarenolongerrequired;theinformationprovidedintheSourceRangeMonitorSubsystemDescriptionSectionsnotapplicablesinceanuclearcorecannolongerbeloadedintotheRPV.NEUTRONMONITORINGSYSTEM SafetyObjective PowerGenerationObjective Identification SourceRangeMonitorSubsystem PowerGenerationDesignBasis 5920 28ResidualHeatRemovalSystem,LPCIValves,FunctionalControlDiagram 5920 29ResidualHeatRemovalSystem,LPCIMiscellaneousComponentsFunctionalControlDiagram 5920 1816RecirculationLoopValves,FunctionalControlDiagram Description Page50of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.4.3 DeleteSection7.5.4.3,SourceRangeMonitorSubsystem,PowerGenerationEvaluation.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcoreneutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemarenolongerrequired;theinformationprovidedintheSourceRangeMonitorSubsystemPowerGenerationEvaluationSectionsnotapplicablesinceanuclearcorecannolongerbeloadedintotheRPV.7.5.4.4 DeleteSection7.5.4.4,SourceRangeMonitorSubsystem,PowerGenerationEvaluation.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcoreneutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemarenolongerrequired;theinformationprovidedintheSourceRangeMonitorSubsystemPowerGenerationEvaluationSectionsnotapplicablesinceanuclearcorecannolongerbeloadedintotheRPV.7.5.5 7.5.5.1 DeleteSection7.5.5.1,IntermediateRangeMonitorSubsystemSafetyDesignBasis.ThesafetydesignbasisoftheIRMSwastogenerateatripsignaltopreventfueldamageresultingfromabnormaloperationaltransientsthatoccurredwhileoperatingintheintermediatepowerrangeFollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheIntermediateRangeMonitorSubsystemarenolongerrequired;theIntermediateRangeMonitorSubsystemSafetyDesignBasisisnotapplicablesincethereisnocoretoprotect.7.5.5.2 DeleteSection7.5.5.2,IntermediateRangeMonitorSubsystemPowerGenerationDesignBasis.ThepowergenerationdesignbasisoftheIRMSwastogenerateatripsignaltoblockrodwithdrawaliftheIRMSreadingexceededapresetvalueoriftheIRMSwasnotoperatingproperly.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheIntermediateRangeMonitorSubsystemarenolongerrequired;theIntermediateRangeMonitorSubsystemPowerGenerationDesignBasiswasnotapplicablesincethereisnocoretoprotect.7.5.5.3 DeleteSection7.5.5.3,IntermediateRangeMonitorSubsystemDescription.TheIRMSfunctionedtogenerateatripsignaltopreventfueldamageresultingfromabnormaloperationaltransientsthatoccurredwhileoperatingintheintermediatepowerrange.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheIRMSarenolongerrequired;theIRMSDescriptionprovidedisnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.7.5.5.4 DeleteSection7.5.5.4,IntermediateRangeMonitorSubsystemSafetyEvaluation.TheIRMSfunctionedtogenerateatripsignaltopreventfueldamageresultingfromabnormaloperationaltransientsthatoccurredwhileoperatingintheintermediatepowerrange.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheIRMSarenolongerrequired;asafetyevaluationoftheIRMSisnotrequiredsincethefunctionsoftheIRMSarenotrequired.InformationregardingtheIRMSisobsolete.7.5.5.5 DeleteSection7.5.5.5,IntermediateRangeMonitorSubsystemPowerGenerationEvaluation.ThepowergenerationfunctionoftheIRMSwastogenerateatripsignaltoblockrodwithdrawali theIRMSreadingexceededapresetvalueoriftheIRMSwasnotoperatingproperly FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,apowergenerationevaluationoftheIRMSisnotrequiredsincethefunctionsoftheIRMSarenotrequiredandtheIRMShasbeencategorizedasabandonedinaccordancewithEC48455.InformationregardingtheIRMSisobsolete.7.5.5.6 DeleteSection7.5.5.6,IntermediateRangeMonitorSubsystemInspectionandTesting.TheIRMSfunctionedtogenerateatripsignaltopreventfueldamageresultingfromabnormaloperationaltransientsthatoccurredwhileoperatingintheintermediatepowerrange.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheIRMSisnotrequiredsincethefunctionsoftheIRMSarenotrequired.TheIRMShasbeencategorizedasabandonedinaccordancewithEC48455.InformationregardingtheIRMSisobsolete.7.5.6 Description SafetyEvaluation PowerGenerationEvaluation InspectionandTesting LocalPowerRangeMonitorSubsystem PowerGenerationEvaluation InspectionandTesting IntermediateRangeMonitorSubsystem SafetyDesignBasis PowerGenerationDesignBasis Page51of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.6.1 DeleteSection7.5.6.1,LocalPowerRangeMonitorSubsystemPowerGenerationDesignBasis.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocationswithinthereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheLocalPowerRangeMonitorSubsystemarenolongerrequired.7.5.6.2 DeleteSection7.5.6.2,LocalPowerRangeMonitorSubsystemDescription.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocationswithinthereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheLPRMSarenolongerrequired;theLPRMSDescriptionprovidedisnotapplicable.InformationregardingtheLPRMSisobsolete.7.5.6.3 DeleteSection7.5.6.3,LocalPowerRangeMonitorSubsystemPowerGenerationEvaluation.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocationswithinthereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheLocalPowerRangeMonitorSubsystemarenolongerrequired;apowergenerationevaluationisnotapplicable.7.5.6.4 DeleteSection7.5.6.4,LocalPowerRangeMonitorSubsystemInspectionandTesting.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocationswithinthereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheLPRMSisnotrequiredsincethefunctionsoftheLPRMSarenotrequired.InformationregardingtheLPRMSisobsolete.7.5.7 7.5.7.1 DeleteSection7.5.7.1,AveragePowerRangeMonitorSubsystemSafetyDesignBasis.TheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresultingfromabnormaloperationaltransientsintimetopreventfueldamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAveragePowerRangeMonitorSubsystemarenolongerrequired;theAveragePowerRangeMonitorSubsystemSafetyDesignBasisisnotapplicable.7.5.7.2 DeleteSection7.5.7.2,AveragePowerRangeMonitorSubsystemSafetyDesignBasis.TheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAveragePowerRangeMonitorSubsystemarenolongerrequired.7.5.7.3 DeleteSection7.5.7.3,AveragePowerRangeMonitorSubsystemDescription.TheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAPRMSarenolongerrequired;theAPRMSDescriptionprovidedisnotapplicable.InformationregardingtheAPRMSisobsolete.7.5.7.4 DeleteSection7.5.7.4,AveragePowerRangeMonitorSubsystemSafetyEvaluationTheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAPRMSarenolongerrequired;asafetyevaluationoftheAPRMSisnotrequiredsincethefunctionsoftheAPRMSarenotrequired.InformationregardingtheAPRMSisobsolete.7.5.7.5 DeleteSection7.5.7.5,AveragePowerRangeMonitorSubsystemSafetyEvaluationTheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAveragePowerRangeMonitorSubsystemarenolongerrequired;apowergenerationevaluationisnotapplicable.Description PowerGenerationEvaluation InspectionandTesting AveragePowerRangeMonitorSubsystem SafetyDesignBasis PowerGenerationDesignBasis PowerGenerationDesignBasis Description SafetyEvaluation PowerGenerationEvaluation Page52of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.7.6 DeleteSection7.5.7.5,AveragePowerRangeMonitorSubsystemSafetyEvaluationTheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheAPRMSisnotrequiredsincethefunctionsoftheAPRMSarenotrequired.InformationregardingtheAPRMSisobsolete.7.5.8 7.5.8.1 DeleteSection7.5.8.1,RodBlockMonitorSubsystemPowerGenerationDesignBasis.TheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorundertheworstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRodBlockMonitorSubsystemarenolongerrequired.TheRBMShasbeencategorizedasabandonedinaccordancewithEC48455.7.5.8.2 DeleteSection7.5.8.2,RodBlockMonitorSubsystemPowerGenerationDescription.TheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorundertheworstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRBMSarenolongerrequired;theRBMSDescriptionprovidedisnotapplicable.TheRBMShasbeencategorizedasabandonedinaccordancewithEC48455.InformationregardingtheRBMSisobsolete.7.5.8.3 DeleteSection7.5.8.3,RodBlockMonitorSubsystemPowerGenerationEvaluationTheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorundertheworstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRodBlockMonitorSubsystemarenolongerrequired;apowergenerationevaluationisnotapplicable.7.5.8.4 DeleteSection7.5.8.4,RodBlockMonitorSubsystemInspectionandTesting.TheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorundertheworstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheRBMSisnotrequiredsincethefunctionsoftheRBMSarenotrequired.InformationregardingtheRBMSisobsolete.7.5.9 7.5.9.1 DeleteSection7.5.9.1,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutronfluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRMgains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheTIPSubsystemarenolongerrequired.7.5.9.2 DeleteSection7.5.9.2,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutronfluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRMgains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheTIPSarenolongerrequired;theTIPSDescriptionprovidedisnotapplicable.InformationregardingtheTIPSisobsolete.7.5.9.3 DeleteSection7.5.9.3,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutronfluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRMgains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheTraversingIncoreProbeSubsystemarenolongerrequired;apowergenerationevaluationisnotapplicable.PowerGenerationEvaluation Description PowerGenerationEvaluation InspectionandTesting TraversingIncoreProbeSubsystem PowerGenerationDesignBasis Description InspectionandTesting RodBlockMonitorSubsystem PowerGenerationDesignBasis Page53of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.9.4 DeleteSection7.5.9.4,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutronfluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRMgains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheTIPSisnotrequiredsincethefunctionsoftheTIPSarenotrequired.InformationregardingtheTIPSisobsolete.7.5.10DeleteSection7.5.10,References.Sincetheneutronmonitoringsubsystemshaveallbeenabandonedthesereferencesnolongerapply.Table7.5.1DeleteTable7.5.1,SRMTrips.SinceSection7.5.4,SRMSubsystemhasbeendeleted,atablelistingSRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.2DeleteTable7.5.2,IRMTrips.SinceSection7.5.5,IRMSubsystemhasbeendeleted,atablelistingIRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.3DeleteTable7.5.3LPRMTrips.SinceSection7.5.6,LPRMSubsystemhasbeendeleted,atablelistingLPRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.4DeleteTable7.5.4,APRMTrips.SinceSection7.5.7,APRMSubsystemhasbeendeleted,atablelistingAPRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.5DeleteTable7.5.5,RBMTrips.SinceSection7.5.8,RBMSubsystemhasbeendeleted,atablelistingRBMtripsisnolongerrequired.Thisinformationisobsolete Figure7.5 1 DeleteFigure7.5 1,StartupRangeNeutronMonitor,InstrumentElectricalDiagram.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 1isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 2 DeleteFigure7.5 2,SRM/IRMNeutronMonitoringUnit.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 2isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 3a DeleteFigure7.5 3a,DetectorDriveSystemSchematic.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 3aisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 3b DeleteFigure7.5 3b,SRM/IRMDetectorDriveSystem,FunctionalControlDiagram.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 3bisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.InspectionandTesting References SRMTrips IRMTrips LPRMTrips APRMTrips RBMTrips 5920 270StartupRangeNeutronMonitor,InstrumentElectricalDiagram 5920 495SRM/IRMNeutronMonitoringUnit DetectorDriveSystemSchematic 5920 1812SRM/IRMDetectorDriveSystem,FunctionalControlDiagram Page54of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.5 4 DeleteFigure7.5 4,FunctionalBlockDiagramofSRMChannel.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 4isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 5 DeleteFigure7.5 5,NeutronMonitoringSystem,FunctionalControlDiagram.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 5isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 6 DeleteFigure7.5 6,SourceRangeMonitoringSystemCoreLocations.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 6isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 7 DeleteFigure7.5 7,FunctionalBlockDiagramofIRMChannel.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 7isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 8 DeleteFigure7.5 8,IRMLocations.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 8isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.59PreviouslyDeleted Figure7.510PreviouslyDeleted Figure7.5 11 DeleteFigure7.5 11,PowerRangeNeutronMonitoring,InstrumentElectricalDiagram.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 11isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Deleted 5920 271PowerRangeNeutronMonitoring,InstrumentElectricalDiagram FunctionalBlockDiagramofSRMChannel 5920 1807NeutronMonitoringSystem,FunctionalControlDiagram SourceRangeMonitoringSystemCoreLocations FunctionalBlockDiagramofIRMChannel IRMLocations Deleted Page55of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.5 12 DeleteFigure7.5 12,LPRMLocations.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 12isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 13 DeleteFigure7.5 13,PowerRangeNeutronMonitoringUnit.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 13isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 14a DeleteFigure7.5 14a,LPRMtoAPRMAssignmentScheme(SystemA).TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 14aisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 14b DeleteFigure7.5 14b,LPRMtoAPRMAssignmentScheme(SystemB).TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 14bisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 15 DeleteFigure7.5 15,APRMTracking,ReductioninPowerByFlowControl.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 15isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 16 DeleteFigure7.5 16,APRMTrackingWithOnLimitsControlRodWithdrawal.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 16isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.LPRMLocations 5920 496PowerRangeNeutronMonitoringUnit LPRMtoAPRMAssignmentScheme(SystemA)LPRMtoAPRMAssignmentScheme(SystemB)APRMTracking,ReductioninPowerByFlowControl APRMTrackingWithOnLimitsControlRodWithdrawal Page56of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.5 17 DeleteFigure7.5 17,AssignmentofLPRMAssembliestoRBM's.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 17isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 18 DeleteFigure7.5 18,RBMChannelA+CResponsetoControlRodMotion.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 18isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 19 DeleteFigure7.5 19,RBMChannelB+DResponsetoControlRodMotion.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 19isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 20 DeleteFigure7.5 20,AssignmentofLPRMStringstoTIPMachines.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 20isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 21 DeleteFigure7.5 21,TraversingIncoreProbeSubsystemBlockDiagram.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 21isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 22 DeleteFigure7.5 22,GammaTraversingIncoreProbeAssembly.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 22isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.TraversingIncoreProbeSubsystemBlockDiagram 5920 9365GammaTraversingIncoreProbeAssembly AssignmentofLPRMAssembliestoRBM's RBMChannelA+CResponsetoControlRodMotion RBMChannelB+DResponsetoControlRodMotion AssignmentofLPRMStringstoTIPMachines Page57of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.5 23a DeleteFigure7.5 23a,NeutronMonitoringSystemArrangement.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 23aisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 23b DeleteFigure7.5 23b,NeutronMonitoringSystemArrangement.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 23bisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 24 DeleteFigure7.5 24,TraversingIncoreProbe,FunctionalControlDiagram.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 24isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 25 DeleteFigure7.5 25,RangesofNeutronMonitoringSystem.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 25isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 26 DeleteFigure7.5 26,IRMCircuitArrangementforReactorProtectionSystemInput.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 26isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.Figure7.5 27 DeleteFigure7.5 27,TypicalAPRMCircuitArrangementforReactorProtectionSystemInput.TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperationandcontrolofthereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolongerrequired,theinformationprovidedonFigure7.5 27isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.7.6 IRMCircuitArrangementforReactorProtectionSystemInput TypicalAPRMCircuitArrangementforReactorProtectionSystemInput REFUELINGINTERLOCKS 5920 426NeutronMonitoringSystemArrangement 5920 427NeutronMonitoringSystemArrangement 5920 1813TraversingIncoreProbe,FunctionalControlDiagram RangesofNeutronMonitoringSystem Page58of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.6.1 DeleteSection7.6.1,RefuelingInterlocksPowerGenerationObjective.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.RefuelingInterlocksinformationisobsolete.7.6.2 DeleteSection7.6.2,RefuelingInterlocksPowerGenerationDesignBases.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.RefuelingInterlocksinformationisobsolete.7.6.3 DeleteSection7.6.3,RefuelingInterlocksDescription.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedintheRefuelingInterlocksDescriptionSectionisnolongerapplicable.RefuelingInterlocksinformationisobsolete.7.6.4 DeleteSection7.6.4,RefuelingInterlocksInspectionandTesting.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired,Therefore,inspectionandtestingoftherefuelinginterlocksisnolongerrequired.RefuelingInterlocksinformationisobsolete.Table7.6.1 DeleteTable7.6.1,RefuelingInterlockEffectiveness.Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.Therefore,atablelistingtheeffectivenessoftherefuelinginterlocksisnolongerrequired.RefuelingInterlocksinformationisobsolete.Figure7.6 1 DeleteFigure7.6 1,RefuelingInterlocks.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedonFigure7.6 1isnolongerapplicable.RefuelingInterlocksinformationisobsolete.Figure7.6 2A DeleteFigure7.6 2A,ControlRodDriveHydraulicSystem,RefuelingInterlocks,FunctionalControlDiagram.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedonFigure7.6 2Aisnolongerapplicable.RefuelingInterlocksinformationisobsolete.Figure7.6 2B DeleteFigure7.6 2B,ControlRodDriveHydraulicSystem,RefuelingInterlocks,FunctionalControlDiagram.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedonFigure7.6 2Bisnolongerapplicable.RefuelingInterlocksinformationisobsolete.PowerGenerationObjective PowerGenerationDesignBases Description InspectionandTesting RefuelingIntelockEffectiveness RefuelingInterlocks ControlRodDriveHydraulicSystem, RefuelingInterlocks,FunctionalControl Diagram5920 1638 ControlRodDriveHydraulicSystem, RefuelingInterlocks,FunctionalControl Diagram5920 1639 Page59of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.7 TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.7.7.1 DeleteSection7.7.1,ReactorManualControlSystemPowerGenerationObjective.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,itisnolongerpossibletochangecorenuclearreactivityandcontrolrodmanipulationwillnolongeroccur.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.ReactorManualControlSysteminformationisobsolete.7.7.2 DeleteSection7.7.2,ReactorManualControlSystemSafetyDesignBases.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,itisnolongerpossibletochangecorenuclearreactivityandcontrolrodmanipulationwillnolongeroccur.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.SafetyDesignBasesfortheReactorManualControlSystemarenolongerapplicable.ReactorManualControlSysteminformationisobsolete.7.7.3 DeleteSection7.7.3,ReactorManualControlSystemPowerGenerationDesignBases.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,itisnolongerpossibletochangecorenuclearreactivityandcontrolrodmanipulationwillnolongeroccur.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.PowerGenerationDesignBasesfortheReactorManualControlSystemarenolongerapplicable.ReactorManualControlSysteminformationisobsolete.7.7.4 7.7.4.1 DeleteSection7.7.4.1,ReactorManualControlSystemDescription,Identification.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired;theinformationprovidedtoidentifythecomponentsoftheReactorManualControlSystemisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.7.7.4.2 DeleteSection7.7.4.2,ReactorManualControlSystemDescription,Operation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired;theinformationprovidedtodescribetheoperationoftheReactorManualControlSystemisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.7.7.4.3 DeleteSection7.7.4.3,ReactorManualControlSystemDescription,RodBlockInterlocks.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnucle a reactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystem,includingrodblocks,arenolongerrequired;theinformationprovidedtodescribethemanagementofcontrolrodblocksbytheReactorManualControlSystemisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.7.7.4.4 DeleteSection7.7.4.4,ReactorManualControlSystemDescription,Instrumentation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystem,includingrodblocks,arenolongerrequired;theinformationprovidedtodescribethemanagementofcontrolrodblocksbytheReactorManualControlSystemisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.RodBlockInterlocks Instrumentation PowerGenerationObjective SafetyDesignBases PowerGenerationDesignBases Description Identification Operation REACTORMANUALCONTROLSYSTEM Page60of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.7.5 DeleteSection7.7.5,ReactorManualControlSystemSafetyEvaluation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysoth a reactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheReactorManualControlSystemarenolongerrequired;asafetyevaluationoftheReactorManualControlSystemisnotrequiredsincethefunctionsoftheRMCSarenotrequired.InformationregardingtheRMCSisobsolete.7.7.6 DeleteSection7.7.6,ReactorManualControlSystemSafetyEvaluation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysoth a reactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.Therefore,inspectionandtestingoftheReactorManualControlSystemisnolongerrequired.ReactorManualControlSysteminformationisobsolete.Table7.7.1 DeleteTable7.7.1,ReactorManualControlSystemInstrumentation.Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.Therefore,atablelistingtheReactorManualControlSystemInstrumentationisnolongerrequired.ReactorManualControlSysteminformationisobsolete.Figure7.7 1a DeleteFigure7.7 1a,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 1aisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 1b DeleteFigure7.7 1b,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 1bisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 1c DeleteFigure7.7 1c,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 1cisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 1d DeleteFigure7.7 1d,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 1disnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 1e DeleteFigure7.7 1e,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 1eisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.SafetyEvaluation InspectionandTesting ReactorManualControlSystemInstrumentation 5920 307ControlRodDriveHydraulicSystem,FunctionalControlDiagram 5920 308ControlRodDriveHydraulicSystem,FunctionalControlDiagram 5920 1636ControlRodDriveHydraulicSystem,FunctionalControlDiagram 5920 1637ControlRodDriveHydraulicSystem,FunctionalControlDiagram 5920 1638ControlRodDriveHydraulicSystem,FunctionalControlDiagram Page61of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.7 2 DeleteFigure7.7 2,ReactorControlBoard.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 2isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 3 DeleteFigure7.7 3,RBMFlowVarianceCircuit,Schematic.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 3isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 4 DeleteFigure7.7 4,InputSignalstoFour RodDisplay.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 4isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.Figure7.7 5 DeleteFigure7.7 5,ControlRodPositionsDisplayTypicalProcessComputerPrintout.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.TheinformationprovidedonFigure7.7 5isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.7.8 Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.7.8.1 DeleteSection7.8.1,ReactorVesselInstrumentation,PowerGenerationObjective.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired;theRVIPowerGenerationObjectiveisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.2 DeleteSection7.8.2,ReactorVesselInstrumentation,SafetyObjective.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired;theRVISafetyObjectiveisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.InputSignalstoFour RodDisplay ControlRodPositionsDisplayTypicalProcessComputerPrintout REACTORVESSELINSTRUMENTATION PowerGenerationObjective SafetyObjective ReactorControlBoard RBMFlowVarianceCircuit,Schematic Page62of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.8.3 DeleteSection7.8.3,ReactorVesselInstrumentation,PowerGenerationDesignBases.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired;theRVIPowerGenerationDesignBasesarenolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.4 DeleteSection7.8.4,ReactorVesselInstrumentation,SafetyDesignBases.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired;theRVISafetyDesignBasesarenolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5 7.8.5.1 DeleteSection7.8.5.1,ReactorVesselInstrumentation,ReactorVesselSurfaceTemperature.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVesselSurfaceTemperatureInstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselSurfaceTemperatureInstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5.2 DeleteSection7.8.5.2,ReactorVesselInstrumentation,ReactorVesselWaterLevel.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVesselWaterLevelInstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselWaterLevelInstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5.3 DeleteSection7.8.5.3,ReactorVesselInstrumentation,ReactorVesselCoolantFlowRatesandDifferentialTemperatures.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVesselCoolantFlowRatesandDifferentialTemperaturesInstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselCoolantFlowRatesandDifferentialTemperaturesinstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5.4 DeleteSection7.8.5.4,ReactorVesselInstrumentation,ReactorVesselInternalPressure.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVesselInternalPressurearenolongerrequired;theinformationprovidedtodescribetheReactorVesselInternalPressureinstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.SafetyDesignBases Description ReactorVesselSurfaceTemperature ReactorVesselWaterLevel ReactorVesselCoolantFlowRatesandDifferentialTemperatures ReactorVesselInternalPressure PowerGenerationDesignBases Page63of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.8.5.5 DeleteSection7.8.5.5,ReactorVesselInstrumentation,ReactorVesselTopHeadFlangeLeakDetection.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVesselTopHeadFlangeLeakDetectioninstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselTopHeadFlangeLeakDetectioninstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5.6 DeleteSection7.8.5.6,ReactorVesselInstrumentation,ReferenceLegTemperatureMonitoring.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReferenceLegTemperatureMonitoringinstrumentationarenolongerrequired;theinformationprovidedtodescribetheReferenceLegTemperatureMonitoringinstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5.7 DeleteSection7.8.5.7,ReactorVesselInstrumentation,ReferenceLegBackFillSystem.TheBackFillSystemensuredthatthereactorwaterlevelreferencelegfluidforselectedcondensingchambersdidnotbecomesaturatedwithnoncondensiblegases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReferenceLegBackFillSystemarenolongerrequired;theinformationprovidedtodescribetheReferenceLegBackfillSystemisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.5.8 DeleteSection7.8.5.8,ReactorVesselInstrumentation,SafetyValveLeakDetection.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.Anacousticaccelerometerinstalledoneachofthereactorvesselsafetyvalvesprovidedindirectindicationofvalveposition.Leakagewasalsodetectedbytemperatureelementsmountedonthereliefvalvetailpipes.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheSafetyValveLeakDetectioninstrumentationarenolongerrequired;theinformationprovidedtodescribetheSafetyValveLeakDetectioninstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.8.6 DeleteSection7.8.6,ReactorVesselInstrumentation,SafetyEvaluation.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbyReactorVesselInstrumentationarenolongerrequired;asafetyevaluationoftheReactorVesselInstrumentationisnotrequiredsincethefunctionsandinformationprovidedbytheReactorVesselInstrumentationarenotrequired.InformationregardingReactorVesselInstrumentationisobsolete.7.8.7 DeleteSection7.8.7,ReactorVesselInstrumentation,InspectionandTesting.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.Therefore,inspectionandtestingoftheReactorManualControlSystemisnolongerrequired.ReactorManualControlSysteminformationisobsolete.Table7.8.1 DeleteTable7.8.1,ReactorVesselInstrumentation.Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsandinformationprovidedbyReactorVesselInstrumentationarenolongerrequired.Therefore,atablelistingtheReactorVesselInstrumentationisnolongerrequired.ReactorVesselInstrumentationinformationisobsolete.ReactorVesselInstrumentation ReactorVesselTopHeadFlangeLeakDetection ReferenceLegTemperatureMonitoring ReferenceLegBackFillSystem SafetyValveLeakDetection SafetyEvaluation InspectionandTesting Page64of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.8 1 DeleteFigure7.8 1,NuclearSystemPressureReliefSystem,PipingandInstrumentationDiagram.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired.TheReactorVesselIndicationinformationprovidedonFigure7.8 1isnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.Figure7.8 2a DeleteFigure7.8 2a,ReactorVesselInstrumentationPipingandInstrumentationDiagram.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired.TheReactorVesselIndicationinformationprovidedonFigure7.8 2aisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.Figure7.8 2b DeleteFigure7.8 2b,ReactorVesselInstrumentationPipingandInstrumentationDiagram.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired.TheReactorVesselIndicationinformationprovidedonFigure7.8 2bisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.Figure7.8 3 DeleteFigure7.8 3,ReactorVesselThermocoupleLocations.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationarenolongerrequired.TheReactorVesselthermocouplelocationinformationprovidedonFigure7.8 3isnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.7.9 TheRecirculationFlowControlSystemcontrolledreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.7.9.1 DeleteSection7.9.1,RecirculationFlowControlSystem,PowerGenerationObjective.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;theRecirculationFlowControlSystemPowerGenerationObjectiveisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.2 DeleteSection7.9.2,RecirculationFlowControlSystem,PowerGenerationDesignBases.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;theRecirculationFlowControlSystemPowerGenerationDesignBasesarenolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.PowerGenerationObjective PowerGenerationDesignBases G 191167NuclearSystemPressureReliefSystem,PipingandInstrumentationDiagram G 191267,Sh1ReactorVesselInstrumentationPipingandInstrumentationDiagram G 191267,Sh2ReactorVesselInstrumentationPipingandInstrumentationDiagram ReactorVesselThermocoupleLocations RECIRCULATIONFLOWCONTROLSYSTEM Page65of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.9.3 DeleteSection7.9.3,RecirculationFlowControlSystem,SafetyDesignBases.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;theRecirculationFlowControlSystemSafetyDesignBasesarenolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.4 7.9.4.1 DeleteSection7.9.4.1,RecirculationFlowControlSystem,GeneralDescription.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;theinformationprovidedintheGeneralDescriptionSectionoftheRecirculationFlowControlSystemisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.4.2 DeleteSection7.9.4.2,RecirculationFlowControlSystem,MotorGeneratorSet.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;thedescriptionoftheRecirculationFlowControlSystemMotorGeneratorSetsprovidedisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.4.3 DeleteSection7.9.4.3,RecirculationFlowControlSystem,SpeedControlComponents.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;thedescriptionoftheRecirculationFlowControlSystemSpeedControlComponentsprovidedisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.4.4 DeleteSection7.9.4.4,RecirculationFlowControlSystem,SystemOperation.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;thedescriptionoftheRecirculationFlowControlSystemOperationprovidedisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.5 DeleteSection7.9.5,RecirculationFlowControlSystem,SafetyEvaluation.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;asafetyevaluationoftheRecirculationFlowControlSystemSystemisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.7.9.6 DeleteSection7.9.6,RecirculationFlowControlSystem,InspectionandTesting.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired;InspectionandtestingoftheRecirculationFlowControlSystemSystemcomponentsisnolongerrequired.RecirculationFlowControlSysteminformationisobsolete.7.9.7DeleteSection7.9.7,References.SincethefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired,referencesarenolongerapplicable.

Figure7.9 1 DeleteFigure7.9 1,RecirculationFlowControl.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlarenolongerrequired.TheinformationprovidedonFigure7.9 1regardingRecirculationFlowControlisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.Figure7.92PreviouslyDeleted SafetyDesignBases Description General MotorGeneratorSet Deleted SpeedControlComponents SystemOperation SafetyEvaluation InspectionandTesting References RecirculationFlowControl Page66of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.9 3 DeleteFigure7.9 3,RecirculationFlowControlSystem,InstrumentElectricalDiagram.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlarenolongerrequired.TheinformationprovidedonFigure7.9 3regardingRecirculationFlowControlisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.Figure7.9 4 DeleteFigure7.9 4,RecirculationFlowControlSystem,SpeedControlSystemInstrumentElectricalDiagram.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlarenolongerrequired.TheinformationprovidedonFigure7.9 4regardingRecirculationFlowControlisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.Figure7.95PreviouslyDeleted 7.10 TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

7.10.1 DeleteSection7.10.1,FeedwaterControlSystemPowerGenerationObjective.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheFeedwaterControlSystemarenolongerrequired;TheFeedwaterControlSystempowergenerationobjectiveisnolongerapplicable.FeedwaterControlSysteminformationisobsolete.7.10.2 DeleteSection7.10.2,FeedwaterControlSystemPowerGenerationDesignBases.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheFeedwaterControlSystemarenolongerrequired;TheFeedwaterControlSystempowergenerationdesignbasesarenolongerapplicable.FeedwaterControlSysteminformationisobsolete.7.10.3 7.10.3.1 DeleteSection7.10.3.1,FeedwaterControlSystemDescriptionofReactorVesselWaterLevelMeasurement.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;ReactorVesselWaterLevelMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.7.10.3.2 DeleteSection7.10.3.2,FeedwaterControlSystemDescriptionofSteamFlowMeasurement.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;SteamFlowMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.7.10.3.3 DeleteSection7.10.3.3,FeedwaterControlSystemDescriptionofFeedwaterFlowMeasurement.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;FeedwaterFlowMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.7.10.3.4 DeleteSection7.10.3.4,FeedwaterControlSystemDescriptionoftheFeedwaterFlowControlSignal.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;thedescriptionoftheFeedwaterControlSignalforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.PowerGenerationDesignBases Description ReactorVesselWaterLevelMeasurement SteamFlowMeasurement FeedwaterFlowMeasurement FeedwaterControlSignal 5920 279RecirculationFlowControlSystem,InstrumentElectricalDiagram 5920 1034RecirculationFlowControlSystem,SpeedControlSystemInstrumentElectricalDiagram Deleted FEEDWATERCONTROLSYSTEM PowerGenerationObjective Page67of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.10.3.5 DeleteSection7.10.3.5,FeedwaterControlSystemDescriptionofFeedwaterValveControl.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;thedescriptionofFeedwaterValveControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.7.10.3.6 DeleteSection7.10.3.6,FeedwaterControlSystemDescriptionofReactorVesselPressureMeasurement.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;ReactorVesselPressureMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.7.10.4 DeleteSection7.10.4,FeedwaterControlSystemInspectionandTesting.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControlSystemarenolongerrequired;FeedwaterControlSystemInspectionandTestingisnolongerrequired.FeedwaterControlSysteminformationisobsolete.Figure7.10 1 DeleteFigure7.10 1,FeedwaterControlSystem,InstrumentElectricalDiagram.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheFeedwaterControlSystemarenolongerrequired.TheFeedwaterControlSystemrelatedinformationprovidedonFigure7.10 1isnolongerapplicable.FeedwaterControlSysteminformationisobsolete.7.11 ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.7.11.1 Deletesection7.11.1,PressureRegulatorandTurbineGeneratorControlSystemPowerGenerationObjective.ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;thePressureRegulatorandTurbineGeneratorControlSystempowergenerationobjectiveisnolongerapplicable.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.7.11.2 Deletesection7.11.2,PressureRegulatorandTurbineGeneratorControlSystemPowerGenerationDesignBasesThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;thePressureRegulatorandTurbineGeneratorControlSystempowergenerationdesignbasesarenolongerapplicable.ThePressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.7.11.3 7.11.3.1 Deletesection7.11.3.1,PressureRegulatorandTurbineGeneratorControlSystemGeneralDescription.ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedinthePressureRegulatorandTurbineGeneratorControlSystemGeneralDescriptionisnolongerapplicable.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.7.11.3.2 Deletesection7.11.3.2,PressureRegulatorandTurbineGeneratorControlSystemPressureRegulatorDescription.ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedinthePressureRegulatorDescriptionsectionisnolongerapplicable.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.PowerGenerationDesignBases Description General PressureRegulator FeedwaterValveControl ReactorVesselPressureMeasurement InspectionandTesting 5920 204FeedwaterControlSystem,InstrumentElectricalDiagram PRESSUREREGULATORANDTURBINEGENERATORCONTROL PowerGenerationObjective Page68of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.11.3.3 Deletesection7.11.3.3,PressureRegulatorandTurbineGeneratorControlSystemPressureRegulatorDescription.ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedinthePressureRegulatorDescriptionsectionisnolongerapplicable.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.7.11.3.4 Deletesection7.11.3.4,PressureRegulatorandTurbineBypassSystemControl.ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedintheTurbineBypassSystemControlDescriptionsectionisnolongerapplicable.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.7.11.4 Deletesection7.11.4,PressureRegulatorandTurbineGeneratorControlSystemInspectionandTesting.ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed,withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulatorandTurbineGeneratorControlSystemarenolongerrequired;testingofthePressureRegulatorandTurbineGeneratorControlSystemcomponentsisnolongerrequired.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.7.12 4.7.1 7.12.1 TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.7.12.1.1 Deletesection7.12.1.1,MainSteamLineRadiationMonitoringSystem,SafetyObjective.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLineRadiationMonitoringSystemarenolongerrequired;theMainSteamLineRadiationMonitoringSystemSafetyObjectiveisnolongerapplicable.MainSteamLineRadiationMonitoringSysteminformationisobsolete.7.12.1.2 Deletesection7.12.1.2,MainSteamLineRadiationMonitoringSystem,SafetyDesignBasis.TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLineRadiationMonitoringSystemarenolongerrequired;theMainSteamLineRadiationMonitoringSystemSafetyDesignBasisisnolongerapplicable.MainSteamLineRadiationMonitoringSysteminformationisobsolete.7.12.1.3 Deletesection7.12.1.3,MainSteamLineRadiationMonitoringSystem,Description.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theMainSteamLineRadiationMonitoringSystemfunctionsandinformationoutlinedintheDescriptionsectionarenolongerapplicable.MainSteamLineRadiationMonitoringSysteminformationisobsolete.7.12.1.4 Deletesection7.12.1.4,MainSteamLineRadiationMonitoringSystem,SafetyDesignBasis.TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLineRadiationMonitoringSystemarenolongerrequired;theMainSteamLineRadiationMonitoringSystemSafetyEvaluationisnolongerapplicable.MainSteamLineRadiationMonitoringSyste m informationisobsolete.PROCESSRADIATIONMONITORINGSYSTEM InspectionandTesting PROCESSRADIATIONMONITORINGSYSTEM MainSteamLineRadiationMonitoringSystem SafetyObjective SafetyDesignBasis TurbineGeneratorControls TurbineBypassSystemControl Description SafetyEvaluation Page69of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.12.1.5 Deletesection7.12.1.5,MainSteamLineRadiationMonitoringSystem,SafetyDesignBasis.TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthereleasedfissionproducts.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLineRadiationMonitoringSystemarenolongerrequired;InspectionandtestingofthetheMainSteamLineRadiationMonitoringSystemcomponentsisnolongerrequired.MainSteamLineRadiationMonitoringSysteminformationisobsolete.7.12.2 TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthelimitswerenotexceeded.7.12.2.1 DeleteSection7.12.2.1,OffGasRadiationMonitoringSystemPowerGenerationObjective.TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthelimitswerenotexceeded.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiationMonitoringSystemarenolongerrequired;theOffGasRadiationMonitoringSystemPowerGenerationObjectiveisnolongerapplicable.OffGasRadiationMonitoringSysteminformationisobsolete.7.12.2.2 DeleteSection7.12.2.2,OffGasRadiationMonitoringSystemPowerGenerationDesignBasis.TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthelimitswerenotexceeded.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiationMonitoringSystemarenolongerrequired;theOffGasRadiationMonitoringSystemPowerGenerationDesignBasisisnolongerapplicable.OffGasRadiationMonitoringSysteminformationisobsolete.7.12.2.3 DeleteSection7.12.2.3,OffGasRadiationMonitoringSystemPowerGenerationDescription.

TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthelimitswerenotexceeded.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiationMonitoringSystemarenolongerrequired;InformationregardingtheOffGasRadiationMonitoringSystemprovidedintheDescriptionsectionisnolongerapplicable.OffGasRadiationMonitoringSysteminformationisobsolete.7.12.2.4 DeleteSection7.12.2.2,OffGasRadiationMonitoringSystemInspectionandTesting.TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthelimitswerenotexceeded.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiationMonitoringSystemarenolongerrequired;InspectionandtestingoftheOffGasRadiationMonitoringSystemisnotrequired.OffGasRadiationMonitoringSysteminformationisobsolete.7.12.3 4.7.1.1 7.12.3.1 ModifySection7.12.3.1,PlantStackRadiationMonitorSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.4.7.1.1.1 7.12.3.2 ModifySection7.12.3.1,PlantStackRadiationMonitorSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,releaseratevaluesaboveoperationalreleaseratelimitsdowntothereleaseratesnormallyencounteredduringhighpoweroperationcannolongeroccur.4.7.1.1.2 7.12.3.3 Nochanges 4.7.1.1.3 7.12.3.4 ModifySection7.12.3.4,PlantStackRadiationMonitorSystem,InspectionandTestingtoremovereferencetotestingrequiredbyTechnicalSpecifications.AllPlantStackRadiationMonitoringSystemtestingrequirementshavebeenremovedfromtheTechnicalSpecifications.

4.7.1.1.4 7.12.4 4.7.1.27.12.4.1ModifySection7.12.4.1,ProcessLiquidRadiationMonitorSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions.4.7.1.2.17.12.4.2ModifySection7.12.4.2,ProcessLiquidRadiationMonitorSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions.4.7.1.2.2 PlantStackRadiationMonitorSystem Objective DesignBasis ProcessLiquidRadiationMonitoringSystem PowerGenerationObjective PowerGenerationDesignBasis PowerGenerationDesignBasis Description InspectionandTesting Description InspectionandTesting PlantStackRadiationMonitorSystem PowerGenerationObjective InspectionandTesting OffGasRadiationMonitoringSystem PowerGenerationObjective PowerGenerationDesignBasis Description InspectionandTesting ProcessLiquidRadiationMonitoringSystem Objective DesignBasis Page70of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.12.4.3 ModifySection7.12.4.3,ProcessLiquidRadiationMonitorSystem,Descriptiontoremovereferencetooperatingandaccidentconditions,theReactorBuildingClosedCoolingWaterSysteman d theRHRServiceWaterSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbyRBCCWandRHRServiceWaterarenolongerrequired.Consequently,processradiationmonitoringofthosesystemsisnolongerrequiredandhasbeenremoved.InformationregardingtheRBCCWandRHRprocessradiationmonitorsisobsolete.4.7.1.2.3 7.12.4.4 NoChanges 4.7.1.2.4 7.12.5 4.7.1.3 7.12.5.1 Modifiedsection7.12.5.1todelete"Safety"fromthesectiontitle,andtoremovereferencetoinitiationofisolationandtripsignalsbasedonRBVhighradiation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed..Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolongerrequired.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

4.7.1.3.1 7.12.5.2 Modifiedsection7.12.5.2todelete"Safety"fromthesectiontitle,andtoremovereferencetoinitiationofisolationandtripsignalsbasedonRBVhighradiation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed..Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolongerrequired.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

4.7.1.3.2 7.12.5.3 Modifiedsection7.12.5.3toremovereferencetoinitiationofisolationandtripsignalsbasedonRBVhighradiation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolongerrequired.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

4.7.1.3.3 7.12.5.4 Modifiedsection7.12.5.4todelete"Safety"fromthesectiontitle,andtoremovereferencetoinitiationofisolationandtripsignalsbasedonRBVhighradiation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatsecondarycontainmentisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolongerrequired.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

4.7.1.3.47.12.5.5ModifiedSection7.12.5.5todeletereferencetoTechnicalSpecificationssinceVYwillneverbeinamodeinwhichthesurveillancerequirementswillapply.4.7.1.3.57.12.6TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

7.12.6.1 DeleteSection7.12.6.1,ContainmentHighRangeRadiationMonitoringSystem,SafetyObjective.

TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHighRangeRadiationMonitoringSystemarenolongerrequired;theContainmentHighRangeRadiationMonitoringSystemSafetyObjectiveisnolongerapplicable.ContainmentHighRangeRadiationMonitoringSysteminformationisobsolete.ReactorBuildingVentilationRadiationMonitoringSystem Description InspectionandTesting ReactorBuildingVentilationRadiationMonitoring System SafetyEvaluation InspectionandTesting ContainmentHighRangeRadiationMonitoringSystem SafetyObjective SafetyObjective SafetyDesignBasis Description Description InspectionandTesting Objective DesignBasis Description Evaluation InspectionandTesting Page71of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.12.6.2 DeleteSection7.12.6.2,ContainmentHighRangeRadiationMonitoringSystem,SafetyDesignBasis.TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHighRangeRadiationMonitoringSystemarenolongerrequired;theContainmentHighRangeRadiationMonitoringSystemSafetyDesignBasisisnolongerapplicable.ContainmentHighRangeRadiationMonitoringSysteminformationisobsolete.7.12.6.3 DeleteSection7.12.6.3,ContainmentHighRangeRadiationMonitoringSystem,Description.

TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHighRangeRadiationMonitoringSystemarenolongerrequired;theinformationregardingtheContainmentHighRangeRadiationMonitoringSystemprovidedintheDescriptionsectionisnolongerapplicable.ContainmentHighRangeRadiationMonitoringSysteminformationisobsolete.7.12.6.4 DeleteSection7.12.6.4,ContainmentHighRangeRadiationMonitoringSystem,SafetyDesignBasis.TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHighRangeRadiationMonitoringSystemarenolongerrequired;aContainmentHighRangeRadiationMonitoringSystemSafetyevaluationisnolongerrequired.ContainmentHighRangeRadiationMonitoringSysteminformationisobsolete.7.12.6.5 DeleteSection7.12.6.5,ContainmentHighRangeRadiationMonitoringSystem,InspectionandTesting.TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHighRangeRadiationMonitoringSystemarenolongerrequired;InspectionandTestingoftheContainmentHighRangeRadiationMonitoringSystemisnolongerrequired.ContainmentHighRangeRadiationMonitoringSysteminformationisobsolete.Table7.12.1 ModifiedtodeleteMainSteamLine,MainCondenserAEOffgas,AugmentedOffgas,andContainmentHighRangeRadmonitors.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythelistedradiationmonitorsarenolongerrequired.ModifyTable7.12.1todeletesensitivitycolumn.Pertechnicalreview,informationprovidedinthiscolumnisnotmeaningfulandisnotrequired.Table4.7.1.1 Table7.12.2Nochanges Table4.7.1.2 Table7.12.3Nochanges Table4.7.1.3 Figure7.12 1 ModifytodeleteMainSteamLine,MainCondenserAEOffgas,AugmentedOffgas,andContainmentHighRangeRadmonitors.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythelistedradiationmonitorsarenolongerrequired.Figure4.7.1 1 Figure7.122Nochanges Figure4.7.1 2 7.13 4.7.2 7.13.1 ModifiedSection7.13.1todeletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.4.7.2.1 7.13.2 ModifiedSection7.13.2todeletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Sectionwordingmodifiedtoremoveexcessspecificity.

4.7.2.2 7.13.3 4.7.2.3 7.13.3.1 ModifySection7.13.3.1,Monitors,Paragraph2,AreaAirborneRadiationMonitoringSystemstodeleteallreferencetotheReactorContainmentAirborneRadiationMonitoringSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.ThereforethefunctionsandinformationprovidedbytheReactorContainmentAirborneRadiationMonitoringSystemarenolongerapplicableandareobsolete.4.7.2.3.17.13.3.2NoChanges 4.7.2.3.2 ProcessRadiationMonitoringEnvironmentalandPowerSupplyDesignConditions PlantStackRadiationMonitorSystemCharacteristics 5920 00526ProcessRadiationMonitoringSystemInstrumentationDiagram 5920 03994PlantStackRadiationMonitoringSystemDiagram AREARADIATIONMONITORINGSYSTEM Objective DesignBases Description ProcessRadiationMonitoringEnvironmentatalandPowerSupplyDesignConditions PlantStackRadiationMonitorSystemCharacteristics 5920 00526ProcessRadiationMonitoringSystemInstrumentationDiagram SafetyDesignBasis Description SafetyEvaluation InspectionandTesting ProcessRadiationMonitoringSystemCharacteristics Locations PowerGenerationDesignBases Description Monitors 5920 3994PlantStackRadiationMonitoringSystemDiagram AREARADIATIONMONITORINGSYSTEM PowerGenerationObjective ProcessRadiationMonitoringSystemCharacteristics Monitors Locations Page72of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.13.4 ModifySection7.13.4,InspectionandTesting,todeleteallreferencetotheReactorContainmentAirborneRadiationMonitoringSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.ThereforethefunctionsandinformationprovidedbytheReactorContainmentAirborneRadiationMonitoringSystemarenolongerapplicableandareobsolete.4.7.2.4 Table7.13.1 ModifyTable7.13.1,todeletereferencetotheVermontYankeeEnvironmentalQualificationProgram.FollowingcertificationofpermanentdefuelingtheprotectionprovidedbytheVYEQprogramisnolongerrequiredandisobsolete.Table4.7.2.1 Table7.13.2NoChanges Table4.7.2.2 Table7.13.3 ModifyTable7.13.3todeleteallreferencetotheReactorContainmentAirborneRadiationMonitoringSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.ThereforethefunctionsandinformationprovidedbytheReactorContainmentAirborneRadiationMonitoringSystemarenolongerapplicableandareobsolete.Table4.7.2.3 Table7.13.4NoChanges Table4.7.2.4 Figure7.131NoChanges Figure4.7.2 1 Figure7.132NoChanges Figure4.7.2 2 Figure7.133DeleteFigure7.13 3.AllreferencetotheReactoContainmentAirborneRadiationMonitoringSystemhasbeendeleted.Systemfunctionsarenolongerrequired.7.14 Editorialandsectiontitlechangeonly 4.37.14.1Editorialandsectiontitlechangeonly 4.3.17.14.2Editorialandsectiontitlechangeonly 4.3.27.14.2.1Editorialandsectiontitlechangeonly 4.3.27.14.2.2Editorialandsectiontitlechangeonly 4.3.2 7.15 3.3.11 7.15.1 ModifySection7.15.1,ProcessComputerSystem,PowerGenerationObjectivetoremovereferencetocorethermalhydraulicconditiondetermination.DeletereferencetoERDS.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corethermal hydraulicconditionsnolongerexist.Additionally,ERDSisnolongerrequired,refertoFCR27/017.3.3.11.1 7.15.2 ModifySection7.15.2,ProcessComputerSystem,PowerGenerationDesignBasestoremovereferencetocorepowerandthermalhydraulicconditiondetermination,EOPentryconditiondetermination,marginanddisplayplotdetermination,criticalplantparametersandERDS.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepower,thermal hydraulicconditions,EOPentryconditions,andcriticalplantparametersnolongerexist.Additionally,ERDSisnolongerrequired,refertoFCR27/017.3.3.11.2 7.15.3 3.3.11.3 7.15.3.1 Nochanges 3.3.11.3.1 ComputerSystemComponents TechnicalSupportCenterAreaAirborneRadiationMonitoringSystem ObjectivesDesignBases Description LocationsofAreaRadiationMonitors ReactorBuildingAreaAirborneRadiationMonitoringSystem InspectionandTesting LocationsofAreaRadiationMonitors ReactorContainmentandReactorBuildingAreaAirborneRadiationMonitoringSystem InspectionandTesting AreaRadiationMonitoringSystem,EnvironmentalandPowerSupplyDesignConditions PortableInstrumentation FixedandLaboratoryInstrumentation PROCESSCOMPUTERSYSTEM HEALTHPHYSICSINSTRUMENTATION PowerGenerationObjective Description 5920 430Sheet1AreaRadiationMonitoringSystem,FunctionalBlockDiagram ReactorBuildingAreaAirborneRadiationMonitoringSystem ReactorContainmentAreaAirborneRadiationMonitoringSystem 5920 430Sheet1AreaRadiationMonitoringSystem,FunctionalBlockDiagram ReactorBuildingAreaAirborneRadiationMonitoringSystem Objective Description HEALTHPHYSICSINSTRUMENTATION PortableInstrumentation FixedandLaboratoryInstrumentation TechnicalSupportCenterAreaAirborneRadiationMonitoringSystem PROCESSCOMPUTERSYSTEM ComputerSystemComponents PowerGenerationObjective PowerGenerationDesignBases Description AreaRadiationMonitoringSystem,EnvironmentalandPowerSupplyDesignConditions Page73of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.15.3.2 Deletesection7.15.3.2,ReactorCorePerformanceFunction.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,reactorcoreperformancecannolongerbedeterminedandtheperformancedeteminationfunctionoftheProcessComputerisnolongerrequired.7.15.3.3 Deletesection7.15.3.3,RodWorthMinimizerFunction.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRodWorthMinimizerarenolongerrequired.RodWorthMinimizerinformationisobsolete.7.15.3.4 ModifySection7.15.3.4,MonitorAlarmandLoggingFunctionstodeletereferencetoPost MortemLoggingSinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionandinformationprovidedbythepost mortemloggingfeaturearenolongerrequired.3.3.11.3.2 MonitorAlarmandLoggingFunctions 7.15.4 NoChanges 3.3.11.4 7.15.5 NoChanges 3.3.11.5 AddedtodescribeProcessComputerDatafeedstothePlantDataServer.3.3.11.6 Table7.15.1 DeleteTable7.15.1,PPCInstrumentationInputSummary.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thePPCinputslistedinthetablearenolongervalid.Table7.15.2 DeleteTable7.15.2,INSTRUMENTATIONOUTPUT

SUMMARY

SIGNALOUTPUTDESCRIPTION.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theTIP,RPISandRWMoutputslistedintable7.15.2arenolongervalid.Theremainingfouroutputsarenotsignificantanddonotwarrantlistingonatable.Figure7.15 1 DeleteFigure7.15 1,RodWorthMinimizerFunctionalControlDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRodWorthMinimizerarenolongerrequired.TheinformationprovidedonFigure7.15 1isnotapplicable.RodWorthMinimizerinformationisobsolete.7.16 TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.7.16.1 DeleteSection7.16.1,NuclearSystemStabilityAnalysis,SafetyObjective.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsandinformationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theNuclearSystemStabilityAnalysisSafetyObjectiveisnolongerapplicable.NuclearSystemStabilityAnalysisinformationisobsolete.7.16.2 DeleteSection7.16.2,NuclearSystemStabilityAnalysis,SafetyDesignBasis TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsandinformationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theNuclearSystemStabilityAnalysisSafetyDesignBasisisnolongerapplicable.NuclearSystemStabilityAnalysisinformationisobsolete.7.16.3 DeleteSection7.16.3,NuclearSystemStabilityAnalysis,PowerGenerationDesignBasis TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsandinformationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theNuclearSystemStabilityAnalysisPowerGenerationDesignBasisisnolongerapplicable.NuclearSystemStabilityAnalysisinformationisobsolete.InspectionandTesting CyberSecurity ProcessComputerDataFeedtothePlantDataServer(PDS)MonitorAlarmandLoggingFunctions InspectionandTesting CyberSecurity ReactorCorePerformanceFunction RodWorthMinimizerFunction SafetyDesignBasis PowerGenerationDesignBasis InstrumentationInputSummary INSTRUMENTATIONOUTPUT

SUMMARY

SIGNALOUTPUTDESCRIPTION 5920 1640RodWorthMinimizer,FunctionalControlDiagram NuclearSystemStabilityAnalysis SafetyObjective Page74of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.16.4 DeleteSection7.16.4,NuclearSystemStabilityAnalysis,ConformanceWithSafetyandPowerGenerationDesignBasis.TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;demonstrationofConformanceWiththeSafetyandPowerGenerationDesignBasisoftheNuclearSystemStabilityAnalysisisnolongerrequired.NuclearSystemStabilityAnalysisinformationisobsolete.7.16.5 DeleteSection7.16.5,NuclearSystemStabilityAnalysis,DescriptionandPerformanceAnalysis.TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;adescriptionofcoreoscillationsandaperformanceanalysisdemonstratingadequacyofpreventionanddetectionofcoreoscillationsatVermontYankeeisnolongerrequired.NuclearSystemStabilityAnalysisinformationisobsolete.7.16.6 DeleteSection7.16.6,NuclearSystemStabilityAnalysis,Conclusions.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;aconclusionwhichstatesthatVYisadequatelyprotectedfromcoreoscillationsandtheirconsequencesisnolongerrequired.NuclearSystemStabilityAnalysisinformationisobsolete.7.16.7 DeleteSection7.16.5,NuclearSystemStabilityAnalysis,DescriptionandPerformanceAnalysis.Sincecorepoweroscillationscannolongeroccur,thereferencesprovidedinsection7.16.7arenolongerapplicable.

Figure7.16 1 DeleteFigure7.16 1,BWROGStabilityCriteriaMap.TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefueldesignlimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsandinformationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theinformationprovidedonFigure7.16 1isnolongerapplicable.NuclearSystemStabilityAnalysisinformationisobsolete.7.17 7.17.1 DeleteSection7.17.1,StandbyGasTreatmentSystemControlandInstrumentationSafetyObjective.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theStandbyGasTreatmentSystemControlsandInstrumentationSafetyObjectiveisnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.7.17.2 DeleteSection7.17.2,StandbyGasTreatmentSystemControlandInstrumentationSafetyDesignBasis ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theStandbyGasTreatmentSystemControlsandInstrumentationSafetyDesignBasisisnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.BWROGStabilityCriteriaMap STANDBYGASTREATMENTSYSTEMCONTROLANDINSTRUMENTATION SafetyObjective SafetyDesignBasis ConformanceWithSafetyandPowerGenerationDesignBasis DescriptionandPerformanceAnalysis Conclusions References Page75of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.17.3 DeleteSection7.17.3,StandbyGasTreatmentSystemControlandInstrumentationSafetyDesignBasis ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theinformationprovidedintheStandbyGasTreatmentSystemControlsandInstrumentationDescriptionsectionisnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.7.17.4 DeleteSection7.17.4,StandbyGasTreatmentSystemControlandInstrumentationSafetyEvaluation.ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,asafetyevaluationoftheStandbyGasTreatmentSystemControlsandInstrumentationisnotrequired.SBGTControlsandInstrumentationinformationisobsolete.7.17.5 DeleteSection7.17.5,StandbyGasTreatmentSystemControlandInstrumentationInspectionandTesting.ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,InspectionandTestingoftheStandbyGasTreatmentSystemControlsandInstrumentationisnotrequired.SBGTControlsandInstrumentationinformationisobsolete.Table7.17.1 DeleteTable7.17.1,StandbyGasTreatmentSystemInstrumentation.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,atableofStandbyGasTreatmentSystemInstrumentationisnotrequired.SBGTControlsandInstrumentationinformationisobsolete.Figure7.17 1 DeleteFigure7.17 1,StandbyGasTreatmentSystemFlowDiagram.ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theinformationprovidedonFigure7.17 1isnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.Description SafetyEvaluation InspectionandTesting StandbyGasTreatmentSystemInstrumentation G 191646StandbyGasTreatmentSystemFlowDiagram Page76of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.17 2 DeleteFigure7.17 2,StandbyGasTreatmentSystemLogicDiagram.ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafetyrequirementsintheReactorBuildingcouldbemet.TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactorBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsandinformationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theinformationprovidedonFigure7.17 2isnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.7.18 TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.7.18.1 DeleteSection7.18.1,AnticipatedTransientWithoutScramPrevention/MitigationSystem,SafetyObjective.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired;theAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyObjectiveisnolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.7.18.2 DeleteSection7.18.2,AnticipatedTransientWithoutScramPrevention/MitigationSystem,SafetyDesignBases.TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired;theAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyDesignBasesarenolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.7.18.3 DeleteSection7.18.3,AnticipatedTransientWithoutScramPrevention/MitigationSystem,Description.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired;thedescriptionoftheAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyDesignBasesisnolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.7.18.4 DeleteSection7.18.4,AnticipatedTransientWithoutScramPrevention/MitigationSystem,SafetyEvaluation.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired;asafetyevaluationoftheAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyDesignBasesisnolongerrequired.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.7.18.5 DeleteSection7.18.5,AnticipatedTransientWithoutScramPrevention/MitigationSystem,InspectionandTesting.TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired;InspectionandTestingoftheAnticipatedTransientWithoutScramPrevention/MitigationSystemisnolongerrequired.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.Table7.18.1 DeleteTable7.18.1,AnticipatedTransientWithoutScramPrevention/MitigationSystemInstrumentation.SinceTherefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired;atablelistingtheATWSPrevention/MitigationSystemInstrumentationisnolongerrequired.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.SafetyDesignBases Description

SafetyEvaluation InspectionandTesting AnticipatedTransientWithoutScramPrevention/MitigationSystemInstrumentation G 191646StandbyGasTreatmentSystemLogicDiagram ANTICIPATEDTRANSIENTWITHOUTSCRAMPREVENTION/MITIGATIONSYSTEM SafetyObjective Page77of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.18 1a DeleteFigure7.18 1a,RPTandARITripLogic.TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired.TheinformationprovidedonFigure7.18 1aregardingtheAnticipatedTransientWithoutScramPrevention/MitigationSystemisnolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.Figure7.18 1b DeleteFigure7.18 1b,RPTandARITripActuators.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransientoccuredandcontrolrodsfailedtoinsert.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipatedTransientWithoutScramPrevention/MitigationSystemarenolongerrequired.TheinformationprovidedonFigure7.18 1bregardingtheAnticipatedTransientWithoutScramPrevention/MitigationSystemisnolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.8.0 StationElectricalPowerSystems Placeholdersectioncontainingnoinformation 3.3.3 8.1 ModifySection8.1,StationElectricalSystemsSummaryDescriptiontoeliminatestartup,operationalandaccidentreferences.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,electricalalignmentsforthoseconditionsarenolongerrequired.ThissummarylevelinformationwasconsolidatedwithUFSARPlantSummarySection1.6 1.3.5.1 Figure8.1 1 NoChange Figure3.3.3 1 Figure8.1 2 NoChange Figure3.3.3 2 8.2 8.2.1 Deletesection8.2.1,StationMainGeneratorPowerGenerationObjective.

Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbytheMainGeneratorarenolongerrequired.TheMainGeneratorPowerGenerationobjectiveisnotapplicable.MainGeneratorinformationisobsolete.8.2.2 Deletesection8.2.2,StationMainGeneratorPowerGenerationDesignBasis, Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbytheMainGeneratorarenolongerrequired.TheMainGeneratorPowerGenerationdesignbasisisn o applicable.MainGeneratorinformationisobsolete.8.2.3 Deletesection8.2.3,StationMainGeneratorDescription, Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,theinformationprovidedbytheMainGeneratordescriptionsectionisnolongerapplicable.MainGeneratorinformationisobsolete.8.2.4 Deletesection8.2.4,StationMainGeneratorInspectionandTesting Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,theinspectionandtestingoftheMainGeneratorisnolongerrequired.MainGeneratorinformationisobsolete.8.3 3.3.3.1 8.3.1 ModifySection8.3.1,StationTransmissionSystemPowerGenerationObjectivetoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115k V startuptransformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfromthe345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.3.3.3.1.1 TransmissionSystem Objective RPTandARITripActuators StationElectricalSystems G 191298,Sh.3MainOne LineDiagram G 1912994160and480VoltAuxiliaryOne LineDiagram RPTandARITripLogic ElectricalPowerSystems ElectricalPowerSystems G 191298,Sh.3MainOne LineDiagram G 1912994160and480VoltAuxiliaryOne LineDiagram PowerGenerationObjective STATIONMAINGENERATORUNIT PowerGenerationObjective PowerGenerationDesignBasis Description

InspectionandTesting STATIONTRANSMISSIONSYSTEM Page78of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.3.2 ModifySection8.3.2,StationTransmissionSystemPowerGenerationDesignBasistoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe11 5 kVstartuptransformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfromthe345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.3.3.3.1.2 8.3.3 ModifySection8.3.3,StationTransmissionSystemDescriptiontoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115kVstartu p transformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfromthe345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.3.3.3.1.3 8.3.4 ModifySection8.3.4,StationTransmissionSystemDescriptiontoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115kVstartu p transformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfromthe345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.3.3.3.1.4 8.3.5 DeleteSection8.3.5,StationTransmissionSystemTechnicalSpecification FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfromthe345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.Figure8.3 1 DeleteFigure8.3 1,TransmissionLinesRiverCrossing.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfromthe345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.Figure8.3 2 NoChanges Figure3.3.3 1 8.4 3.3.3.2 8.4.1 ModifySection8.4.1,StationAuxiliaryPowerSystem,PowerGenerationObjective.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,themaingeneratorwillnolongerbeoperated,thestationauxiliarypowersystemwillbepoweredfromthestartuptransformers.Allreferencetooperationalconditionshasbeendeleted.ThepowergenerationObjectivesectionhasbeenmodifiedtoremovetheterm"PowerGeneration",andtheobjectivehasbeenrewordedtoreflectthesafestorageandhandlingofirradiatedfuel.3.3.3.2.1 8.4.2 ModifySection8.4.2,StationAuxiliaryPowerSystem,PowerGenerationDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,themaingeneratorwillnolongerbeoperated,thestationauxiliarypowersystemwillbepoweredfromthestartuptransformers.Allreferencetooperationalconditionshasbeendeleted.ThepowergenerationDesignBasissectionhasbeenmodifiedtoremovetheterm"PowerGeneration",andthedesignbasissectionhasbeenrewordedtoreflectthesafestorageandhandlingofirradiatedfuel.3.3.3.2.2 8.4.3 Deletesection8.4.3,StationAuxiliaryPowerSystem,SafetyObjective FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theStationAuxiliaryPowerSystemSafetyObjectiveisnolongerapplicable.

8.4.4 Deletesection8.4.4,StationAuxiliaryPowerSystem,SafetyDesignBasis FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theStationAuxiliaryPowerSystemSafetyDesignBasisisnolongerapplicable.

8.4.5 3.3.3.2.3 8.4.5.1 ModifySection8.4.5.1,StationAuxiliaryPowerSystem,4260VSwitchgeartoremovereferencetooperatingandaccidentconditions,reflectthattheauxiliarypowersystemcannolongerbesuppliedbytheunitauxiliarytransformer,andnotethestationauxiliarypowersystemfunctionisnowtosupplypowerforthesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.3.3.3.2.3.14160VSwitchgear 8.4.5.2 ModifySection8.4.5.2,StationAuxiliaryPowerSystem,480VBussestoremovereferencetooperatingandaccidentconditions,reflectthattheauxiliarypowersystemcannolongerbesuppliedbytheunitauxiliarytransformer,andnotethestationauxiliarypowersystemfunctionisnowtosupplypowerforthesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.3.3.3.2.3.2480VBuses DesignBasis Description

EvaluationofSystemProtection G 191298sheet3,MAINONELINEWIRINGDIAGRAM AuxiliaryPowerSystems Objective DesignBasis Description PowerGenerationDesignBasis SafetyObjective SafetyDesignBasis Description EvaluationofSystemProtection TechnicalSpecifications TransmissionLinesRiverCrossing STATIONAUXILIARYPOWERSYSTEMS PowerGenerationObjective PowerGenerationDesignBasis Description G 191298sheet3,MAINONELINEWIRINGDIAGRAM 4160VSwitchgear 480VBuses Page79of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.4.5.3 ModifySection8.4.5.3,StationAuxiliaryPowerSystem,120/240VInstrumentationDistributionSystemtoremovereferencetoelectricalloadswhicharenolongerrequiredandremovereferencetotheMGset.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,manyoftheloadssuppliedbythe120/240InstrumentationSystemarenolongerrequired.Additionally,thefunctionsprovidedbytheMGsetarenolongerrequired.Thatinformationishistoricalandobsoletedandmaybedeleted.3.3.3.2.3.3 120/240VInstrumentationDistributionSystem 8.4.6 ModifySection8.4.6,StationAuxiliaryPowerSystem,CableInstallationandSeparationCriteriatoremovereferencetocableseparationcriteriaforredundantsafetysystems.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorProtectionSystem,thePrimaryContainmentIsolationSystem,theEngineeredSafetyFeatureandECCS,PrimaryContainmentElectricalPenetrations,andDrywellSeparationcriteriaarenolongerapplicable.Therefore,theCableInstallationandSeparationCriteriasectionhasbeenmodifiedtoremovereferencetothoseareas,aswellasreferencetooperatingconditions.

3.3.3.2.4 8.4.7 DeleteSection8.4.7,StationAuxiliaryPowerSystem,SafetyEvaluation FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,asafetyevaluationoftheStationAuxiliaryPowerSystemisnotrequired.8.4.8 ModifySection8.4.8,StationAuxiliaryPowerSystem,InspectionandTestingtoremovereferencetooperatingcondition s FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.3.3.3.2.5 8.4.9 DeleteSection8.4.9,StationAuxiliaryPowerSystem,TechnicalSpecifications.AllTSsurveillancesrelatedtotheStationAuxiliaryPowerSystemhavebeendeletedintheDefueledTSsubmitt a totheNRC Figure8.41Nochanges Figure3.3.3 2 Figure8.4 2 Nochanges Figure3.3.3 2 Figure8.43Nochanges Figure3.3.3 3 Figure8.44Nochanges Figure3.3.3 4 Figure8.45Nochanges Figure3.3.3 5 Figure8.46Nochanges Figure3.3.3 6 Figure8.47DeleteFigure8.4 7,Duplicatesotherfiguresinthissection Figure8.4 8 Nochanges Figure3.3.3 10 Figure8.4 8 Nochanges Figure3.3.3 11 8.5 3.3.3.3 8.5.1 ModifySection8.5.1,StationStandbyDiesel GeneratorSystemsSafetyObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthatthediesel generatorsnowsupplyback uppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDiesel Generatorsareonlyrequiredtosupplybackuppowertoensurethesafestorageofirradiatedfuel.3.3.3.3.1 8.5.2 ModifySection8.5.2,StationStandbyDiesel GeneratorSystemsSafetyDesignBasestoremovereferencetooperatingandaccidentconditions,andreflectthatthediesel generatorsnowsupplyback uppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDiesel Generatorsareonlyrequiredtosupplybackuppowertoensurethesafestorageofirradiatedfuel.3.3.3.3.2 G 191299BalanceofPlant4160VoltAuxiliaryOne LineDiagram G 191300,Sh1Emergency480VoltAuxiliaryOne LineDiagram(SI)G 191300,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SI)G 191301,Sh1Emergency480VoltAuxiliaryOne LineDiagram(SII)G 191301,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SII)SafetyEvaluation InspectionandTesting TechnicalSpecifications G 191299Emergency4160VoltAuxiliaryOne LineDiagram 120/240VInstrumentationDistributionSystem CableInstallationandSeparationCriteria CableInstallationandSeparationCriteria InspectionandTesting G 191299BalanceofPlant4160VoltAuxiliaryOne LineDiagram G 191299BalanceofPlant4160VoltAuxiliaryOne LineDiagram G 191300,Sh1Emergency480VoltAuxiliaryOne LineDiagram(SI)G 191300,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SI)G 191301,Sh1Emergency480VoltAuxiliaryOne LineDiagram(SII)G 191301,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SII)SafetyDesignBases G 191300,Sh2G 191301,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SI&SII)G 191372,Sh4G 191372,Sh5120/240VoltInstrumentationOne LineDiagram STATIONSTANDBYDIESELGENERATORSYSTEMS SafetyObjective G 191372,Sh4G 191372,Sh5120/240VoltInstrumentationOne LineDiagram STANDBYDIESELGENERATORSYSTEMS G 191372,Sh4120/240VoltInstrumentationOne LineDiagramG 191372,Sh5OneLineDiagram,+24VoltDCPowerSystem Objective DesignBases Page80of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.5.3 ModifySection8.5.3,StationStandbyDiesel GeneratorSystemsDescriptiontoremovereferencetooperatingandaccidentconditions,andreflectthatthediesel generatorsnowsupplyback uppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDiesel Generatorsareonlyrequiredtosupplybackuppowertoensurethesafestorageofirradiatedfuel.3.3.3.3.3 8.5.4 DeleteSection8.5.4,StationStandbyDiesel GeneratorSystemsSafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsoftheStandbyDiesel Generatorsarenolongerrequired.Consequently,asafetyevaluationoftheStandbyDiesel GeneratorSystemsisnolongerreqired.8.5.5 DeleteSection8.5.5,LossofDieselGenerators.Availibilityofanalternatepowersupplyalignmenttobusses3and4isaddressedinsection8.4.5.1,4160VACBusses.Therearenosafetyconsequencesassociatewiththelossofabackupdiesel generatorinthepermanentlydefueledcondition.Adequatemitigationstrategiesexisttoensurespentfueltemperatureandinventoryaremaintained.

8.5.6 ModifySection8.5.4,StationStandbyDiesel GeneratorSystemsInspectionandTestingtoremovereferencetooperatingandaccidentconditions,andreflectthatthediesel generatorsnowsupplyback uppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDiesel Generatorsareonlyrequiredtosupplybackuppowertoensurethesafestorageofirradiatedfuel.StandbyDiesel GeneratorInspectionandTestingwillbecommeasuratewiththefunctionoftheDiesels.3.3.3.3.4 8.5.7 DeleteSection8.5.7,StandbyDiesel GeneratorSystemsTechnicalSpecifications.VYwillneverbeinamodewhichwillrequirethestandbydiesel generatorstobeoperablebytheTechnic a Specifications.

Table8.5.1A DeleteTable8.5.1A,DieselGeneratorDG 1 1ALoadingLossofACandMaximumHypotheticalAccident.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprojecteddieselgeneratorloadinginthistableisnolongerrequiredsincethemaximumhypotheticalaccidentisnolongerpossible.Table8.5.1B DeleteTable8.5.1B,DieselGeneratorDG 1 1BLoadingLossofACandMaximumHypotheticalAccident.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprojecteddieselgeneratorloadinginthistableisnolongerrequiredsincethemaximumhypotheticalaccidentisnolongerpossible.Table8.5.2A Deletetable8.5.2A.Thetableprovidedalistingofloadswhichwouldautomaticallystartandloadoneachdieselgeneratorfollowingspecificplantinitiatingconditions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,whenrequired,theDiesel Generatorswillsupplysufficientbackuppowerrequiredtoensurethesafestorageofirradiatedfuel.ThatloadingisasmallpercentageoftheDieselGeneratorloadingwhichwasrequiredfollowingalossofoff sitepowerandalossofcoolantorotherdesignbasisaccident.Consequently,theinformationprovideontable8.5.2Aishistoricalandobsolete.Assuch,thistablemaybedeleted.Table8.5.2B Deletetable8.5.2B.Thetableprovidedalistingofloadswhichwouldautomaticallystartandloadoneachdieselgeneratorfollowingspecificplantinitiatingconditions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,whenrequired,theDiesel Generatorswillsupplysufficientbackuppowerrequiredtoensurethesafestorageofirradiatedfuel.ThatloadingisasmallpercentageoftheDieselGeneratorloadingwhichwasrequiredfollowingalossofoff sitepowerandalossofcoolantorotherdesignbasisaccident.Consequently,theinformationprovideontable8.5.2Bishistoricalandobsolete.Assuch,thistablemaybedeleted.Table8.5.3A DeleteTable8.5.3A,DieselGeneratorDG 1 1ALoadingLossofACandVernonPond.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceSWwaslostduringalossoftheVernonPond,DGcoolingwasprovide d byRHRSW.RHRSWisnotrequiredinthepermanentlydefueledstate,therefore,coolingtotheDGsisnotavailableduringalossoftheVernonPond.OtherpowersourcesareavailableandstrategieshavebeendevelopedtomaintainSFPinventoryandcooling.Therefore,theprojecteddieselgeneratorloadingduringalossoftheVernonPondisnolongerrequired.DieselGeneratorDG 1 1ALoadingLossofACandMaximumHypotheticalAccident DieselGeneratorDG 1 1BLoadingLossofACandMaximumHypotheticalAccident DieselGeneratorDG 1 1ALoadingLossofACDieselGeneratorDG 1 1BLoadingLossofAC LossofDieselGenerator InspectionandTesting TechnicalSpecifications Description SafetyEvaluation Description InspectionandTesting DieselGeneratorDG 1 1ALoadingLossofACandVernonPond Page81of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table8.5.3B DeleteTable8.5.3B,DieselGeneratorDG 1 1BLoadingLossofACandVernonPond.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceSWwaslostduringalossoftheVernonPond,DGcoolingwasprovide d byRHRSW.RHRSWisnotrequiredinthepermanentlydefueledstate,therefore,coolingtotheDGsisnotavailableduringalossoftheVernonPond.OtherpowersourcesareavailableandstrategieshavebeendevelopedtomaintainSFPinventoryandcooling.Therefore,theprojecteddieselgeneratorloadingduringalossoftheVernonPondisnolongerrequired.Figure8.5 1 DeleteFigure8.5 1,FuelOilSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDiesel Generatorsareonlyrequiredtosupplybackuppowerasnecessarytoensurethesafestorageofirradiatedfuel.Therefore,adrawingofthefueloilsystemisnolongerrequiredtodemonstratethattheDiesel Generatorsarecapableofperformingtheirintendedfunction.8.6 3.3.3.4 8.6.1 ModifySection8.6.1,125VoltBatterySystem,SafetyObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsofthe125VDCsystemisnolongerrequired Consequently,theword"Safety"hasbeendeletedfromthetitleandthetextandtheword"emergency"hasbeendeletedfromthetext.3.3.3.4.1 8.6.2 ModifySection8.6.2,125VoltBatterySystem,SafetyDesignBasistoremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetydesignbasesofthe125VDCsystemisnolongerapplicable.Consequently,theword"Safety"hasbeendeletedfromthetitleandreferencetoredundancy,independenceandsinglefailurecriteriahavebeendeletedfromthetext.3.3.3.4.2 8.6.3 ModifySection8.6.3,125VoltBatterySystem,Descriptiontoremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theperformancerequirementsofthe125VDCsystemhavechangedtoessentiallyprovidingcontrolpowerforvariousstationcomponents.Consequently,referencetosafetyrelatedclassificationanddischargeratesandtimeshavebeendeletedfromthetext.Additionally,thefunctionsprovidedbystationbatteryAS 1arenolongerrequired.Therefore,referencestostationbatteryAS 1havebeendeleted.3.3.3.4.3 8.6.4 ModifySection8.6.4,125VoltBatterySystem,SafetyEvaluation,toremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsofthe125VDCsystemisnolongerrequired Consequently,theword"Safety"hasbeendeletedfromthetitle.Additionally,referencetosafetyrelatedclassificationanddischargeratesandtimeshavebeendeletedfromthetext.Also,thefunctionsprovidedbystationbatteryAS 1arenolongerrequired.Therefore,referencestostationbatteryAS 1havebeendeleted.3.3.3.4.48.6.5NoChanges 3.3.3.4.58.6.6NoChanges 3.3.3.4.6 8.6.7 DeleteSection8.6.7,125VoltBatterySystem,TechnicalSpecifications.VYwillneverbeinamodewhichwillrequirethebatterysystemtobeoperablebytheTechnicalSpecifications.

Figure8.6 1 NoChanges Figure3.3.3 7 3.3.3 8 3.3.3 9 8.7 3.3.3.5 8.7.1 ModifySection8.7.1,+24VoltDCPowerSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthatthe+24VoltDCPowerSystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincethereisnocoretoprotect,theneutronmonitoringsystemsarenolongerrequired.Therefore,powertotheneutronmonitoringsystemsfromthe+24VDCsystemisnolongerrequired.Referencetopowersuppliedtotheneutronmonitoringsystemshasbeendeletedfromthissection.3.3.3.5.1 InspectionandTesting 125VOLTBATTERYSYSTEM G 191372,Shs1,2,3125VDCOne LineDiagram+24VDCPowerSystem Objective Objective DesignBasis Description Evaluation AdditionalDCSystems G 191372,Shs1,2,3125VDCOne LineDiagram+24VDCPowerSustem PowerGenerationObjective AdditionalDCSystems InspectionandTesting TechnicalSpecifications SafetyDesignBasis Description SafetyEvaluation DieselGeneratorDG 1 1BLoadingLossofACandVernonPond FuelOilSystem 125VOLTBATTERYSYSTEM SafetyObjective Page82of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.7.2 ModifySection8.7.2,+24VoltDCPowerSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions,andreflectthatthe+24VoltDCPowerSystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.3.3.3.5.2 8.7.3 ModifySection8.7.3,+24VoltDCPowerSystem,Description,toremovereferencetooperatingandaccidentconditions,andreflectthatthe+24VoltDCPowerSystemnowsuppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincethereisnocoretoprotect,theneutronmonitoringsystemsarenolongerrequired.Therefore,powertotheneutronmonitoringsystemsfromthe+24VDCsystemisnolongerrequired.Referencetopowersuppliedtotheneutronmonitoringsystemshasbeendeletedfromthissection.Additionally,referencetodischargeratesandtimeshavebeendeletedfromthetext.3.3.3.5.38.7.4Nochanges 3.3.3.5.4 8.7.5 DeleteSection8.7.5,125VoltBatterySystem,TechnicalSpecifications.VYwillneverbeinamodewhichwillrequirethebatterysystemtobeoperablebytheTechnicalSpecifications.

Figure8.7 1 Nochanges Figure3.3.3 11 8.8 8.8.1 DeleteSection8.8.1,ECCS24VoltDCPowerSystemSafetyObjective.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemarenolongerrequired.Thesafetyobjectiveisnolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.8.8.2 DeleteSection8.8.2,ECCS24VoltDCPowerSystemSafetyDesignBases.TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemarenolongerrequired.Thesafetydesignbasesarenolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.8.8.3 DeleteSection8.8.3,ECCS24VoltDCPowerSystemDescription.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemarenolongerrequired.Theinformationprovidedinthedescriptionsectionisnolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.8.8.4 DeleteSection8.8.4,ECCS24VoltDCPowerSystemSafetyEvaluation.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemarenolongerrequired.AsafetyevaluaionoftheECCS24VoltDCPowrSystemisnolongerrequired.ECCS24VDCPowerSysteminformationisobsolete.8.8.5 DeleteSection8.8.5,ECCS24VoltDCPowerSystemSafetyEvaluation.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thererfore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemarenolongerrequired.InspectionandTestingoftheECCS24VoltDCPowerSystemisnolongerrequired.ECCS24VDCPowerSysteminformationisobsolete.Figure8.8 1 DeleteSection8.8 1,OneLineDiagramECCS24VoltDCPowerSystem.TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemarenolongerrequired.Theinformationprovidedonfigure8.8 1isnolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.9.0 RadioactiveWasteSystems DesignBasis Description InspectionandTesting G 191372,Sh5OneLineDiagram,+24VoltDCPowerSystem PowerGenerationDesignBasis Description InspectionandTesting Description SafetyEvaluation InspectionandTesting OneLineDiagramECCS24VoltDCPowerSystemG 191297 TechnicalSpecifications G 191372,Sh5OneLineDiagram,+24VoltDCPowerSystem ECCS24VOLTDCPOWERSYSTEM SafetyObjective SafetyDesignBasis Page83of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 9.1 ModifiedSection9.1,RadwasteSummaryDescriptionasfollows: 1.Deleted"StationOperation",inserted"safestorageandhandlingofirradiatedfuel"toreflectthepostdefuelingfunction.2.Removedunnecessaryspecifityfromthefirstparagraph.

3.Changed"Station"to"Facility"toreflectpostdefuelingfunction 4.DeletedreferencetotheGaseousRadwasteSystem.Followingpermanentdefueling,theairejectors,vacuumpump,glandsealcondenserandtheStandbyGasTreatmentSystemwillnolongerbeoperated.Ventilationsysteminformationisprovidedintheappropriateventilationsystemsections.5.Removedstatementregardingcontinuedcompliancewithannualdoselimitswith1912MWthrating,nolongerapplicablepostdefueling.

1.3.3 9.2 4.5.2 9.2.1 De l ete d" PowerGeneration "f romt h esectiontit l e.Sincet h ec l assi f icationprocessd escri b e dinsection1.4.1isnol ongeruse d ,t h ec l assi f icationb asisisnol ongerrequire dan disnotapp l ica bl toapermanentlydefueledstation.4.5.2.1 9.2.2 Deleted"PowerGeneration"fromthesectiontitle.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisnotapplicabl toapermanentlydefueledstation.4.5.2.2 9.2.3 DeletedSection9.2.3,SafetyDesignbasis,movedinformationtoSection9.2.2,DesignBases.9.2.4 4.5.2.39.2.4.1EditorialChangesonly 4.5.2.3.19.2.4.2EditorialChangesonly 4.5.2.3.29.2.4.3EditorialChangesonly 4.5.2.3.39.2.4.4EditorialChangesonly 4.5.2.3.49.2.5EditorialChangesonly 4.5.2.49.2.6NoChanges 4.5.2.5 Table9.2.1 NoChanges Table4.5.2.1 Table9.2.2 NoChanges Table4.5.2.2 Table9.2.3 NoChanges Table4.5.2.3 Table9.2.4 NoChanges Table4.5.2.4 Table9.2.5 NoChanges Table4.5.2.5 Figure9.2 1a NoChanges Figure4.5.2 1 Figure9.2 1b NoChanges Figure4.5.2 2 Figure9.2 2 NoChanges Figure4.5.2 3 Figure9.2 3 NoChanges Figure4.5.2 4 Figure9.2 4 NoChanges Figure4.5.2 5 Figure9.2 5 NoChanges Figure4.5.2 6 Figure9.2 6 NoChanges Figure4.5.2 7 Figure9.2 7 NoChanges Figure4.5.2 8 9.3 4.6.1 9.3.1 Deleted"PowerGeneration"fromthesectiontitle.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisnotapplicabl toapermanentlydefueledstation.4.6.1.1 9.3.2 Deleted"PowerGeneration"fromthesectiontitle.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisnotapplicabl toapermanentlydefueledstation.4.6.1.2 9.3.3 4.6.1.3 9.3.3.1 Nochange 4.6.1.2.1 RadioactiveWasteManagement LiquidRadwasteSystem Objective LIQUIDRADWASTESYSTEM PowerGenerationObjective PowerGenerationDesignBasis SafetyDesignBasis

SUMMARY

DESCRIPTION DesignBasis InspectionandTesting VermontYankeeRadioactiveLiquidWasteProcessingParameters VermontYankeeLiquidRadwasteSystemTankCapacities ChemicalWastes DetergentWastes SafetyEvaluation Description HighPurityWastes LowPurityWastes G 191177,Sh1LiquidRadwasteSystem G 191177,Sh2LiquidRadwasteSystem Description HighPurityWastes LowPurityWastes ChemicalWastes DetergentWastes Evaluation

InspectionandTesting VermontYankeeRadioactiveLiquidWasteProcessingParameters VermontYankeeLiquidRadwasteSystemTankCapacities VermontYankeeLiquidEffluents ActivityInputtoLiquidRadwasteSystem(Ci/yr)RadionuclideDischargeConcentrations G 191151RadioactiveWasteBuildingGeneralArrangement G 191152RadioactiveWasteBuildingGeneralArrangement G 191177,Sh3LiquidRadwasteSystem G 191151RadioactiveWasteBuildingGeneralArrangement G 191152RadioactiveWasteBuildingGeneralArrangement 5920 644,Sh2RadwasteSystem,ProcessDiagram VermontYankeeLiquidEffluents ActivityInputtoLiquidRadwasteSystem(Ci/yr)RadionuclideDischargeConcentrations General 5920 644,Sh2RadwasteSystem,ProcessDiagram G 191177,Sh1LiquidRadwasteSystem G 191177,Sh2LiquidRadwasteSystem G 191177,Sh3LiquidRadwasteSystem G 191177,Sh4LiquidRadwasteSystem RadwasteAreaPlanView Objective DesignBasis SOLIDRADWASTESYSTEM Description General PowerGenerationObjective PowerGenerationDesignBasis Description G 191177,Sh4LiquidRadwasteSystem RadwasteAreaPlanView SOLIDRADWASTESYSTEM Page84of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 9.3.3.2 Nochange 4.6.1.2.2 9.3.3.3 Nochange 4.6.1.2.3 9.3.3.4 StatementregardingtemporarystorageoflowlevelwastemodifiedtodeletereferencetoNorthWarehousetoaccommodateEC47799.Referencetoweathertightshippingcontainer s deletedtoremoveexcessdetail.SectiondeletedinaccordancewithEC54271.Wastestoragefacilityhasbeendemolished.

9.3.4 Nochange

4.6.1.4 Table9.3.1 Nochange Table4.6.1 9.4 9.4.1 DeleteSection9.4.1,GaseousRadwasteSystemPowerGenerationObjective.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystempowergenerationobjectiveisnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.9.4.2 DeleteSection9.4.2,GaseousRadwasteSystemSafetyObjective.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystemsafetyobjectiveisnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.9.4.3 DeleteSection9.4.3,GaseousRadwasteSystemPowerGenerationDesignBases.TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystempowergenerationdesignbasesarenolongerapplicable.GaseousRadwasteSysteminformationisobsolete.9.4.4 DeleteSection9.4.4,GaseousRadwasteSystemSafetyDesignBases.TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystemSafetyDesignBasesarenolongerapplicable.GaseousRadwasteSysteminformationisobsolete.9.4.5 DeleteSection9.4.5,GaseousRadwasteSystemDescription.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Further,theincinerationofslightlyradioactiveoilwillnolongerbeperformed.Therefore,informationprovidedintheGaseousRadwasteSystemDescriptionSectionisnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.DryWastes InspectionandTesting SolidRadwasteAnnualDisposalHistory WetWastes WetWastes DryWastes GASEOUSRADWASTESYSTEM PowerGenerationObjective SafetyObjective PowerGenerationDesignBasis SafetyDesignBasis Description WasteStorageFacility InspectionandTesting SolidRadwasteAnnualDisposalHistory Page85of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 9.4.6 DeleteSection9.4.6,GaseousRadwasteSystemSafetyEvaluation.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,asafetyevaluationoftheGaseousRadwasteSystemisnolongerrequired.GaseousRadwasteSysteminformationisobsolete.9.4.7 DeleteSection9.4.7,GaseousRadwasteSystemInspectionandTesting TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,inspectionandtestingoftheGaseousRadwasteSystemisnolongerrequired.GaseousRadwasteSysteminformationisobsolete.9.4.8 DeleteSection9.4.8,GaseousRadwasteSystemReferences.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,GaseousRadwasteSystemreferencesarenolongerapplicable.GaseousRadwasteSysteminformationisobsolete.Table9.4.1 DeleteTable9.4.1,AirEjectorIsotopeandSiteBoundaryReleaseRates.TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theinformationprovidedinTable9.4.1,AirEjectorIsotopeandSiteBoundaryReleaseRatesisnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.Figure9.4 1 DeleteFigure9.4 1,AdvancedOffGasSystemPipingandInstrumentationDiagram.TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Further,theincinerationofslightlyradioactiveoilwillnolongerbeperformed.

Therefore,informationprovidedonfigure9.4 1isnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.Figure9.4 2 DeleteFigure9.4 2,OffGasSystem.TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeitherstationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Further,theincinerationofslightlyradioactiveoilwillnolongerbeperformed.Therefore,informationprovidedonfigure9.4 2isnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.SafetyEvaluation InspectionandTesting REFERENCESAirEjectorIsotopeandSiteBoundaryReleaseRates VY E 75 001AdvancedOffGasSystemPipingandInstrumentationDiagram G 191162,Sh3OffGasSystemPage86of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.0 StationAuxiliarySystems 10.1 DeleteSection10.1.AnintroductiontoauxiliarysystemsisnotrequiredintheDSAR.Nomeaningfulinformationisprovidedinthissection.10.2 10.2.1 DeleteSection10.2.1,NewFuelStorageRacks,PowerGenerationObjective.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,thefunctionsprovidedbythenewfuelstorageracksarenolongerrequired.TheNewFuelStorageRackPowerGenerationObjectiveisnolongerapplicable.NewFuelStorageRackinformationisobsolete.10.2.2 DeleteSection10.2.2,NewFuelStorageRacks,PowerGenerationDesignBases.Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,thefunctionsprovidedbythenewfuelstorageracksarenolongerrequired.TheNewFuelStorageRackPowerGenerationDesignBasesarenolongerapplicable.NewFuelStorageRackinformationisobsolete.10.2.3 DeleteSection10.2.3,NewFuelStorageRacks,SafetyDesignBasis.Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,thefunctionsprovidedbythenewfuelstorageracksarenolongerrequired.TheNewFuelStorageRackSafetyDesignBasisisnolongerapplicable.NewFuelStorageRackinformationisobsolete.10.2.4 DeleteSection10.2.4,NewFuelStorageRacks,Description.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,theinformationprovidedbythenewfuelstorageracksdescriptionsectionisnolongerapplicable.NewFuelStorageRackinformationisobsolete.10.2.5 DeleteSection10.2.5,NewFuelStorageRacks,SafetyEvaluation.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,asafetyevaluationofthenewfuelstorageracksisnolongerrequired.NewFuelStorageRackinformationisobsolete.10.2.6 DeleteSection10.2.6,NewFuelStorageRacks,InspectionandTesting.Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,inspectionandtestingofthenewfuelstorageracksisnolongerrequired.NewFuelStorageRackinformationisobsolete.Figure10.2 1 DeleteFigure10.2 1,NewFuelStorageRack.Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently,theinformationprovidedonfigure10.2 1isnolongerapplicable.NewFuelStorageRackinformationisobsolete.10.3 3.3.1.210.3.1Rewordtitleto"Objective"delete"PowerGeneration"sincepowergenerationcannolongeroccurfollowingcertificationofpermanentdefueling.

3.3.1.2.1 10.3.2 Rewordtitleto"DesignBasis",delete"PowerGeneration"sincepowergenerationcannolongeroccurfollowingcertificationofpermanentdefueling.Includedesignbasesfromsection10.3.3 SafetyDesignBasis.3.3.1.2.210.3.3MoveSafetyDesignBasisinformationintosection10.3.2,DesignBasis,Deletethissection.10.3.4NumberingChangesonly 3.3.1.2.3 10.3.5 DeletedreferencetoananalysiswhichwasperformedtoverifythattheNFPCS,augmentedbyRHRasrequired,canmaintainSFPtemperatureinrequiredrangeunderalloperatingconditions.NFPCSabandonedunderEC50085followingpermanentdefueling.FPwillbecooledbySBFPCS.NumberingChangesasaconsequenceofcombiningdesignbasissections.InformationaddedtodocumentcompliancewithNUREG1738IDCsandSDAs 3.3.1.2.4 PowerGenerationObjective PowerGenerationDesignBasis SafetyDesignBasis SafetyDesignBasis Description

SafetyEvaluation InspectionandTesting NewFuelStorageRack SPENTFUELSTORAGE

SUMMARY

DESCRIPTION NEWFUELSTORAGERACKS PowerGenerationObjective PowerGenerationDesignBases SPENTFUELSTORAGE Objective DesignBasis Description SafetyEvaluation Description SafetyEvaluation Page87of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.3.6 NumberingChangesasaconsequenceofcombiningdesignbasissections.3.3.1.2.5 ReferencessectionaddedtopointtoNUREG1738,RegGuide1,174,andBVY14 009,CompliancewithIDCsandSDAs 3.3.1.5 Figure10.3 1 NoChanges Figure3.3.1 1 Figure10.3 2 NoChanges Figure3.3.1 2 Figure10.3 3 NoChanges Figure3.3.1 3 Figure10.3 4A NoChanges Figure3.3.1 4 Figure10.3 4B NoChanges Figure3.3.1 5 10.4 3.3.1.4 10.4.1 DeleteSection10.4.1,PowerGenerationObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingofreactorsystemswillnolongerberequired.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.10.4.2 Rewordtitleto"Objective",delete"Safety".NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.1 10.4.3 Rewordtitleto"DesignBasis",delete"Safety".Changed"refuelingaccident"to"fuelhandlingaccident".FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Consequently,arefuelingaccidentcannolongeroccur.NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.210.4.4NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3 10.4.4.1 Deletedreferencestoreactorgeneralservicingrequirements.Servicingofreactorsystemswillnolongerberequired.Anyreactorrelatedactivitieswilloccuraspartofdecommissionin g activitiesasoutlinedinthePSDAR.Deletedreferencetoflowchartoutliningactivitiesinanormalrefuelingoutage,sincepostdefueling,refuelingoutageswillnolongeroccur.NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3.1Introduction 10.4.4.2 Editorialcommentstoimprovegrammar.Removedthereferenceto"operating"personnel.

Removedreferencestothenewfuelinspectionstandfunctions,sincenewfuelwillnolongerbereceivedatthestation.Removedthedescriptionoftypicalchannelingproceureforswappinganirradiatedfuelchanneltoanewfuelbundle,sincenewfuelwillnolongerbereceivedatthestation.Additionally,channelingactivitesareprocedurallycoveredandshouldnotbedescribedintheFSARorDSAR.NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3.2 FuelServicingEquipment 10.4.4.3 Deletedreferencetoreasonsforusingaportableunderwatertelevisioncameraandmonitor.ThisisdetailedinformationnotrequiredtobeintheDSA R NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection3.3.1.4.3.3ServicingAids 10.4.4.4 Deletesection10.4.4.4,ReactorVesselServicingEquipment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingofreactorsystemswillnolongerberequired.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.10.4.4.5 Deletesection10.4.4.5,In VesselServicingEquipment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingofreactorsystemswillnolongerberequired.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.10.4.4.6 Re titled"RefuelingEquipment"to"FuelHandlingEquipment"sincefollowingcertificationofpermanentdefueling,refuelingoperationswillnolongeoccu r Rewordedsectiontoremoveallreferencetofuelhandlinginthereactorvesselandfueltransferfromthevesseltothepool.NumberingChangesasaresultofdeletingsections.3.3.1.4.3.4 FuelHandlingEquipment 10.4.4.7 Deletedreferencetonewfuelstorageracks.NumberingChangesasaresultofdeletingsections.3.3.1.4.3.5StorageEquipment NESFuelStorageRackAssembly(Partial)InspectionandTesting References FuelStorageArrangement 5920 6893PlanFuelStorageRackArrangement 5920 6893SpentFuelStorageRackSchematic NESFuelStorageRackAssembly(Partial)FuelStorageArrangement 5920 6893PlanFuelStorageRackArrangement 5920 6893SpentFuelStorageRackSchematic InspectionandTesting ServicingAids ReactorVesselServicingEquipment In VesselServicingEquipment Description Introduction FuelServicingEquipment PowerGenerationObjective SafetyObjective SafetyDesignBasis HoltecFuelStorageRackAssembly (Partial)TOOLSANDSERVICINGEQUIPMENT Objective DesignBasis Description RefuelingEquipment StorageEquipment HoltecFuelStorageRackAssembly (Partial)TOOLSANDSERVICINGEQUIPMENT Page88of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.4.4.8 Deletesection10.4.4.8,UnderReactorVesselServicingEquipment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingunderreactorvesselsystemswillnolongerberequired.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.10.4.4.9 Deletesection10.4.4.9,StoragePit.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbythestoragepitwillnolongerberequired.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.NumberingChangesasaresultofdeletingsections.10.4.5 Changed"refuelingaccident"to"fuelhandlingaccident".FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIA W 10CFR50.82(a)(2).Consequently,arefuelingaccidentcannolongeroccur.NumberingChangesasaresultofdeletingsections.3.3.1.4.410.4.6Deletethissection,singlereferenceincorporatedintotextbody Table10.4.1 ModifyTable10.4.1,ToolsandServicingEquipment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.Additionally,sinceallfuelhasbeenmovedtothespentfuelpool,thecattlechutewillalsonolongerberequired.Table10.4 1hasbeenmodifiedtoreflectthesechanges.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.Contentsofthetablepertinenttothepermanentlydefueledconditionhavebeenmovedintothebodyofthetext,tablehasbeendeleted Figure10.4 1 DeleteFigure10.4 1,Typ.PlantRefuelingOutageFlowDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,plantrefuelingoutageswillnolongeroccur.TheinformationprovidedinFigure10.4 1isnotapplicable.Plantrefuelingoutageflowdiagraminformationisobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.Figure10.4 2 DeleteFigure10.4 2,ChannelGaugingFixture.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,Fuelchannelingoperationsandactivitieswhichrequireuseofthechannelgaugingfixturewillnolongerbeconducted.Informationregardingthechannelgaugingfixtureprovidedonfigure10.4 2isnotapplicableandisobsolete.Figure10.4 3 DeleteFigure10.4 3,IncoreGuideTube.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.Informationregardingincoreguidetubetoolsprovidedonfigure10.4 3isnotapplicableandisobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.Figure10.4 4 DeleteFigure10.4 4,IncoreHousing.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.Informationregardingincorehousingtoolsprovidedonfigure10.4 4isnotapplicableandisobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.Figure10.4 5 DeleteFigure10.4 5,In CoreGuideTubeSeal.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingIncoreGuideTubeSealtoolsprovidedonfigure10.4 5isnotapplicableandisobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.Figure10.4 6 DeleteFigure10.4 6,In CoreFlangeSealTestPlug.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingIn CoreFlangeSealTestPlugtoolsprovidedonfigure10.4 6isnotapplicableandisobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.ToolsandServicingEquipment Typ.PlantRefuelingOutageFlowDiagram 5920 2429ChannelGaugingFixture 5920 2417IncoreGuideTube StoragePit SafetyEvaluation REFERENCESUnderReactorVesselServicingEquipment Evaluation IncoreHousing 5920 2422In CoreGuideTubeSeal In CoreFlangeSealTestPlug Page89of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure10.4 7 DeleteFigure10.4 7,FuelBailCleaner.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,operationsandactivitieswhichrequireuseofthefuelbailcleanerwillnolongerbeconducted.Informationregardingthefuelbailcleanerprovidedonfigure10.4 7isnotapplicableandisobsolete.Figure10.4 8 DeleteFigure10.4 8,ThermalSleeveInstallationTool.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingThermalSleeveInstallationToolsprovidedonfigure10.4 8isnotapplicableandisobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.Figure10.4 9 DeleteFigure10.4 9,ThermalSleeve.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,in vesselservicing,undervesselservicingandcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingtheThermalSleeveprovidedonfigure10.4 9isnotapplicableandisobsolete.An reactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.10.5 3.3.1.3 10.5.1 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisn o applicabletoapermanentlydefueledstation.Sectionwordinghasbeenmodifiedtoreflectalignmentchangesinthefuelpoolcoolingsystem;theNormalFuelPoolCoolingsystemhasbeenabandoned,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenabandoned,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.3.3.1.3.1 10.5.2 Deletesection10.5.2,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theneedtomaintaintheReactorBuildingenvironmentwithi theboundinglimitsoftheenvironmentalqualificationprogramforelectricalequipmentnolongerexists.Therefore,thesafetyobjectiveisnolongerapplicable.

10.5.3 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisn o applicabletoapermanentlydefueledstation.Sectionwordinghasbeenmodifiedtoreflectalignmentchangesinthefuelpoolcoolingsystem;theNormalFuelPoolCoolingsystemhasbeenabandoned,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenabandoned,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.3.3.1.3.2 10.5.4 Deletesection10.5.4,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theneedtomaintaintheReactorBuildingenvironmentwithi theboundinglimitsoftheenvironmentalqualificationprogramforelectricalequipmentnolongerexists.Therefore,thesafetydesignbasisisnolongerapplicable.

10.5.5 Section10.5.5,Description,wordinghasbeenmodifiedtoreflectalignmentchangesinthefuelpoolcoolingsystem;theNormalFuelPoolCoolingsystemhasbeenabandoned,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.TheSFPCShasbeenreclassifiedtonon safetyrelated,butremainsseismicclass1.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenabandoned,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.3.3.1.3.3 10.5.6 ModifySection10.5.6toremovetheterm"safety"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolong e requiredandisnotapplicabletoapermanentlydefueledstation.WordingwasaddedtothesectiontoreflectthattheSFPheatloadhasdecayedtowithinthecapacityofonetrainofSFPCS40daysaftershutdownwiththecoredischargedintothepoolandallfuelremaininginthepoolwhichwaspresentjustpriortoshutdown.3.3.1.3.4 10.5.7 ModifySection10.5.7,InspectionandTesting.TherearenoSFPCStestingrequirementsintheTechnicalSpecifications.Additionally,atleastonetrainoftheSFPCSwillbeinoperationata l times.Therefore,nospecialtestingorinspectionisrequired.3.3.1.3.5 Table10.5.1 DeletedTable10.5.1,HeatRemovalCapacities.ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.Consequently,theinformationregardingheatremovalcapacitiesprovidedbytable10.5.1isnolongerapplicable.

Table10.5.2 PreviouslyDeleted PowerGenerationDesignBasis SafetyDesignBasis Description 5920 2407ThermalSleeve FUELPOOLCOOLINGANDDEMINERALIZERSYSTEM PowerGenerationObjective SafetyObjective 5920 2419FuelBailCleaner 5920 2424ThermalSleeveInstallationTool Objective DesignBasis Description SafetyEvaluation InspectionandTesting HeatRemovalCapacities Deleted Evaluation InspectionandTesting STANDBYFUELPOOLCOOLINGANDDEMINERALIZERSYSTEM Page90of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table10.5.3 DeletedTable10.5.3,ComparisonofHeatLoadstoHeatRemovalCapacitieswithSFPatCapacity.ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.Consequently,theinformationregardingheatremovalcapacitiesprovidedbytable10.5.3isnolongerapplicable.

Table10.5.4 DeletedTable10.5.4,FuelPoolCoolingandDemineralizerSystemSystemSpecifications.ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.Consequently,theinformationregardingsystemspecificationsprovidedbytable10.5.4isnolongerapplicable.

Figure10.5 1a NoChanges Figure3.3.1 6 Figure10.5 1b NoChanges Figure3.3.1 7 Figure10.5 2 DeletedFigure10.5 2,FuelPoolFilterDemineralizerSystem.ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedbytheStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.Consequently,theinformationregardingsystemspecificationsprovidedbyFigure10.5 2isnolongerapplicable.

10.6 3.3.2 10.6.1 ModifySection10.6.1,StationServiceWaterSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystemnowsuppliesonlycoolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel.3.3.2.1 10.6.2 DeleteSection10.6.2,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thetheStationSWSisnolongerrequiredtoprovidecoolingwatertosystemsandequipmentrequiredtooperateunderaccidentconditions.

10.6.3 ModifySection10.6.3,StationServiceWaterSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystemnowsuppliesonlycoolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel.3.3.2.2 10.6.4 DeleteSection10.6.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thetheStationSWSisnolongerrequiredtoprovidecoolingwatertosystemsandequipmentrequiredtooperateunderaccidentconditions.TheStationSWSSafetyDesignBasesarenolongerapplicable.10.6.5 ModifySection10.6.5,StationServiceWaterSystem,Descriptiontoremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystemnowsuppliesonlycoolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel,removereferencetocertainautomaticfeaturesnolongerapplicable,reflectthatStationSWSdischargeisalignedt thecoolingtowerdeepbasin,andnotethatStationSWSpipingwhichsuppliesspentfuelpoolcoolingisseismicclass1.3.3.2.3 10.6.6 ModifySection10.6.6,SafetyEvaluationtodeletethetermsafetyfromthesectiontitleandrewordthesectiontodemonstratethattheobjectivesappropriatetothedefueledcondtionaremet, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theStationSWSisnolongerrequiredtoprovidecoolingwatertosystemsandequipmentrequiredtooperateunderaccidentconditions.AStationSWSSafetyEvaluationisnolongerrequired.3.3.2.4 10.6.7 ModifySection10.6.7,StationServiceWaterSystem,InspectionandTesting,toremovereferencetooperatingandaccidentconditions,andreflectthatsincetheStationServiceWaterSystemisinconstantoperation,specialtestingandinspectionsarenotrequired.3.3.2.5 Figure10.6 1a NoChange Figure3.3.2 1 Figure10.6 1b NoChange Figure3.3.2 2 10.7 TheRHRServiceWater(RHRSW)SystemprovidedadynamicheatsinkfortheResidualHeatRemoval(RHR)Systemduringnormaloperation.

10.7.1 Deletesection10.7.1,ResidualHeatRemovalServiceWaterSystem,PowerGenerationObjectives.TheRHRServiceWater(RHRSW)SystemprovidedadynamicheatsinkfortheResidualHeatRemoval(RHR)Systemduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheatisnolongerrequired,operationoftheRHRsystemandRHRSWsystemsisnolongerrequired.Therefore,theRHRSWpowergenerationobjectivesarenolongerapplicable.ResidualHeatRemovalServiceWaterSysteminformationisobsolete.G 191177,Sh4FuelPoolFilterDemineralizerSystem STATIONSERVICEWATERSYSTEM PowerGenerationObjective ComparisonofHeatLoadstoHeatRemovalCapacitieswithSFPatCapacity FuelPoolCoolingandDemineralizerSystemSystemSpecifications G 191173,Sh1FuelPoolCoolingSystem G 191173,Sh2FuelPoolCoolingSystem Objective G 191173,Sh1FuelPoolCoolingSystem G 191173,Sh2FuelPoolCoolingSystem SERVICEWATERSYSTEM RESIDUALHEATREMOVAL(RHR)SERVICEWATERSYSTEM PowerGenerationObjective SafetyEvaluation InspectionandTesting G 191159,Sh1FlowDiagramServiceWater(Part1)G 191159,Sh2FlowDiagramServiceWater(Part2)SafetyObjective PowerGenerationDesignBasis SafetyDesignBasis Description DesignBasis Description Evaluation InspectionandTesting G 191159,Sh1FlowDiagramServiceWater(Part1)G 191159,Sh2FlowDiagramServiceWater(Part2)Page91of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.7.2 Deletesection10.7.2,ResidualHeatRemovalServiceWaterSystem,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SincerestorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequire d thefunctionsofRHRSWarealsonolongerrequired.Therefore,theRHRSWsafetyobjectiveisnolongerapplicable.ResidualHeatRemovalSWSysteminformationisobsolete.10.7.3 Deletesection10.7.3ResidualHeatRemovalServiceWaterSystem,PowerGenerationDesignBasesTheRHRServiceWater(RHRSW)SystemprovidedadynamicheatsinkfortheResidualHeatRemoval(RHR)Systemduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheatisnolongerrequired,operationoftheRHRsystemandRHRSWsystemsisnolongerrequired.Therefore,theRHRSWpowergenerationdesignbasesarenolongerapplicable.ResidualHeatRemovalServiceWaterSysteminformationisobsolete.10.7.4 Deletesection10.7.4,ResidualHeatRemovalServiceWaterSystem,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SincerestorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,theRHRSWsafetyobjectiveisnolongerapplicable.ResidualHeatRemovalSWSysteminformationisobsolete.10.7.5 Deletesection10.7.5,ResidualHeatRemovalServiceWaterSystem,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheat,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,theinformationprovidedintheRHRSWdescriptionsectionisnolongerapplicable.ResidualHeatRemovalSWSysteminformationisobsolete.10.7.6 Deletesection10.7.6,ResidualHeatRemovalServiceWaterSystem,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheat,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,aRHRSWSystemsafetyevaluationisnolongerrequired.ResidualHeatRemovalSWSysteminformationisobsolete.10.7.7 Deletesection10.7.7,ResidualHeatRemovalServiceWaterSystem,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheat,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,InspectionandTestingoftheRHRSWsystemisnolongerrequired.ResidualHeatRemovalSWSysteminformationisobsolete.10.8 TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

10.8.1 DeleteSection10.8.1,AlternateCoolingSystemSafetyObjective.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,theAlternateCoolingSystemsafetyobjectiveisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.10.8.2 DeleteSection10.8.2,AlternateCoolingSystemSafetyDesignBases.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,theAlternateCoolingSystemsafetydesignbasesarenolongerapplicable.AlternateCoolingSysteminformationisobsolete.10.8.3 DeleteSection10.8.3,AlternateCoolingSystemDescription.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,theinformationprovidedintheAlternateCoolingSystemdescriptionisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.SafetyObjective PowerGenerationDesignBases SafetyDesignBases Description SafetyEvaluation InspectionandTesting ALTERNATECOOLINGSYSTEM SafetyObjective SafetyDesignBases Description Page92of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.8.4 DeleteSection10.8.4,AlternateCoolingSystemSafetyEvaluation.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,asafetyevaluationoftheAlternateCoolingSystemdescriptionisnolongerrequired.AlternateCoolingSysteminformationisobsolete.10.8.5 DeleteSection10.8.5,AlternateCoolingSystemInspectionandTesting.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,inspectionandtestingoftheAlternateCoolingSystemisnolongerrequired.AlternateCoolingSysteminformationisobsolete.10.8.6 DeleteSection10.8.6,References.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,CalculationVYC 1279J,"SWFlowAnalysis DeepBasinBackFlowDuetoSeismicLineBreaksinTurbineBuilding&MinimumEDGFlowratesAfterCommonDischargeHeaderBreak"isnolongerapplicable.AlternateCoolingSysteminformationisobsolete.Table10.8.1 DeleteTable10.8.1,RHRSWPumpOperatingModesfortheAlternateCoolingSystem.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,Table10.8.1isnolongerapplicable.AlternateCoolingSysteminformationisobsolete.Figure10.8 1 DeleteFigure10.8.1,AlternateCoolingSystem.TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisnolongerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.Consequently,theinformationprovidedonFigure10.8 1concerningtheAlternateCoolingSystemisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.10.9 TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

10.9.1 DeleteSection10.9.1,RBCCWSafetyObjective.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWSafetyObjectiveisnolongerapplicable.RBCCWinformationisobsolete.10.0.2 DeleteSection10.9.2,RBCCWPowerGenerationObjective.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWPowerGenerationObjectiveisnolongerapplicable.RBCCWinformationisobsolete.10.9.3 DeleteSection10.9.3,RBCCWSafetyDesignBases.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWSafetyDesignBasesarenolongerapplicable.RBCCWinformationisobsolete.SafetyObjective PowerGenerationObjective SafetyDesignBases SafetyEvaluation InspectionandTesting References RHRSWPumpOperatingModesfortheAlternateCoolingSystem AlternateCoolingSystem REACTORBUILDINGCLOSEDCOOLINGWATERSYSTEM Page93of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.9.4 DeleteSection10.9.4,RBCCWPowerGenerationDesignBases.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWPowerGenerationDesignBasesarenolongerapplicable.RBCCWinformationisobsolete.10.9.5 DeleteSection10.9.5,RBCCWDescription.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheinformationprovidedintheRBCCWDescriptionSectionisnolongerapplicable.RBCCWinformationisobsolete.10.9.6 DeleteSection10.9.6,RBCCWSafetyEvaluation.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.AnRBCCWSafetyEvaluationisnolongerrequired.RBCCWinformationisobsolete.10.9.7 DeleteSection10.9.7,RBCCWInspectionandTesting.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.RBCCWInspectionandTestingisnolongerrequired.RBCCWinformationisobsolete.Figure10.9 1 DeleteFigure10.9 1,RCWCoolingWaterSystem.TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheinformationprovidedregardingtheRBCCWCoolingWaterSystemonfigure10.9 1isnolongerapplicable.RBCCWinformationisobsolete.10.10 TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.10.10.1 DeleteSection10.10.1,TBCCWPowerGenerationObjective.TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystemarenolongerrequired.TheTBCCWPowerGenerationObjectiveisnolongerapplicable.TBCCWinformationisobsolete.10.10.2 DeleteSection10.10.2,TBCCWPowerGenerationDesignBasesTheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystemarenolongerrequired.TheTBCCWPowerGenerationDesignBasesarenolongerapplicable.TBCCWinformationisobsolete.10.10.3 DeleteSection10.10.3,TBCCWDescription.TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystemarenolongerrequired.TheinformationprovidedintheTBCCWDescriptionSectionisnolongerapplicable.TBCCWinformationisobsolete.PowerGenerationDesignBases Description

SafetyEvaluation InspectionandTesting G 191159,Sh3RCWCoolingWaterSystem TURBINEBUILDINGCLOSEDCOOLINGWATERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Description Page94of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.10.4 DeleteSection10.10.4,TBCCWInspectionandTesting.TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystemarenolongerrequired.TestingandInspectionoftheTBCCWSystemisnolongerrequired.TBCCWinformationisobsolete.Figure10.10 1 DeleteFigure10.10 1,TurbineBuildingClosedCoolingWaterSystem.TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystemarenolongerrequired.TheinformationprovidedonFigure10.10 1isnolongerapplicable.TBCCWinformationisobsolete.10.11 3.3.4 10.11.1 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisn o applicabletoapermanentlydefueledstation.3.3.4.1 10.11.2 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisn o applicabletoapermanentlydefueledstation.3.3.4.2 10.11.3 DeletedreferencetotheAppendix"R"Programandthesafeshutdowncapabilityanalysissincetheprogramnolongerappliespostcertificationofpermanentdefueling.

Addedthewords"Thefireprotectionprogramforthepermanentlydefueledstatehasbeendevelopedbasedontheapplicablerequirementsof10CFR50.48andBTPAPCSB9.51,AppendixA.TheFireHazardsAnalysis(FHA)documentsexistingplantconfigurationsanddefinestheresourcesavailableforthepreventionandlimitationofdamagefromfire(Reference1).Inadditiontoplansandphysicalconfigurationsforfireprotection,firedetection,firesuppressionandlimitationoffiredamage,theFHAalsoprovidesanoveralldescriptionofthefireprotectionprogram."toreflectthefacilitystatepost defueling.

Removedthewords"ThefollowingdocumentsformthebasisoftheFireProtectionProgramandareincorporatedbyreferenceintotheDSAR:

• FireProtectionProgram

• FireHazardAnalysis toremovetheIBRsinceitisnolongerrequired.3.3.4.310.11.4Nochanges 3.3.4.4 10.11.5 Deletesection10.11.5,References.Onlyreferenceinthissection,referencetotheSafeShutdownCapabilityAnalysis,wasdeletedsincetheanalysisnolongerappliespostcertificationofpermanentdefueling.

Re addedVYFireHazardsAnalysisasareference.

3.3.4.5 Figure10.11 1A NoChanges Figure3.3.4 1 Figure10.11 1b NoChanges Figure3.3.4 2 10.12 3.3.5 10.12.1 ModifySection10.12.1toeliminatereferencetotheterm"Station"andreplacewith"facility"whereappropriat e Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.5.1 10.12.2 ModifySection10.12.2toeliminatereferencetopurgingtheprimarycontainment.

Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.Removereferencetopurgingprimarycontainment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequiredandthesafetydesignbasesarenolongerapplicable.PrimaryContainmentSysteminformationisobsolete.3.3.5.2 10.12.3 3.3.5.3 10.12.3.1 RBHVACinformationmovedintothissectionfromSection5.3 3.3.5.3.1 ReactorBuilding Description InspectionandTesting References TestingandInspection G 191159,Sh4TurbineBuildingClosedCoolingWaterSystem FireProtectionSystem PowerGenerationObjective PowerGenerationDesignBasis FIREPROTECTIONSYSTEM Objective DesignBasis Description InspectionandTesting References PowerGenerationDesignBasis Description ReactorBuilding G 191163,Sh1FireProtectionSystem G 191163,Sh2FireProtectionSystem(OuterLoop)STATIONHEATING,VENTILATING,ANDAIRCONDITIONINGSYSTEMS PowerGenerationObjective G 191163,Sh1FireProtectionSystem G 191163,Sh2FireProtectionSystem(OuterLoop)Heating,VentilatingandAirConditioningSystems Objective DesignBasis Description Page95of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.12.3.2 ModifySection10.12.3.2todeletereferencetothemodularfacilitylocatedontheturbinedeckwithaventilationsystemindependentoftheturbinebuildingventilationsystem.Thefacilitywasastagingareaforpersonnelengagedinmainturbineandgeneratorworkduringrefuelingoutages.Sincerefuelingoutages,includingturbineandgeneratoroverhauls,willnolongerbeconducted,thefunctionsprovidedbythemodularfacilityarenolongerrequired.Thereforethesefunctionsareobsoleteandmaybedeleted.3.3.5.3.2TurbineBuilding 10.12.3.3 ModifySection10.12.3.3todeletereferencetomanualoperationofcontrolroomventilationdampersduringaLOCA,includingreferencetomanualoperationofdamperswithin3hoursaftertheevent.Followingcertificationofpermanentdefueling,thelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannolongeroccurandaLOCAisnotpossible.Additionally,thethreehourrequirementoriginatedinanAppendixRscenario.The3hourlimitintendedtoensurecontrolroomtemperatureremainedbelow120Ftopreventchallengingequipmentoperatinglimits.Postdefueling,AppendixRisnolongerapplicable.3.3.5.3.3MainControlRoom 10.12.3.4 NoChanges3.3.5.3.4ServiceBuilding 10.12.3.5 NoChanges3.3.5.3.5RadwasteBuilding 10.12.3.6 NoChanges 3.3.5.3.6 HeatingBoilerSystem 10.12.3.7 NoChanges 3.3.5.3.7 AdvancedOff GasBuildingHVAC 10.12.4 NoChanges 3.3.5.4 Figure10.12 1 NoChanges Figure3.3.5 1 Figure10.12 2 NoChanges Figure3.3.5 2 Figure10.12 3 NoChanges Figure3.3.5 3 Figure10.12 4 NoChanges Figure3.3.5 4 Thisfiguremovedinfromsection5.3,SecondaryContainment Fi gure3.3.5 5 10.13 3.3.8.1 10.13.1 ModifySection10.13.1,StationMakeupWaterSystem,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheStationMakeupWate Systemnowsuppliesonlymakeupwaternecessarytoensurethesafestorageandhandlingofirradiatedfuel.Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.8.1.1 10.13.2 ModifySection10.13.2,StationMakeupWaterSystem,PowerGenerationDesignBasis,toremovereferencetooperatingandaccidentconditionsandreflectthattheStationMakeupWate Systemnowsuppliesonlymakeupwaternecessarytoensurethesafestorageandhandlingofirradiatedfuel.Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.8.1.210.13.3ModifiedSection10.13.3,Description,toremovereferenceto"potable"watertoaccommodatechangesduetoEC45613,trackedbyFCR27 003 3.3.8.1.3 10.13.3.1 EditorialChangesonly.3.3.8.1.3.1General 10.13.3.2 Nochanges 3.3.8.1.3.2 PretreatmentSystem 10.13.3.3 Nochanges 3.3.8.1.3.3 DemineralizerSystem10.13.4Nochanges 3.3.8.1.4 Figure10.13 1 Nochanges Figure3.3.8 1 10.14 3.3.6 10.14.1 ModifySection10.14.1,StationInstrumentandServiceAirSystems,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheStatio n InstrumentandServiceAirSystemsnowsupplyonlypressurizedairnecessarytoensurethesafestorageandhandlingofirradiatedfuel.Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.6.1 TurbineBuilding MainControlRoom ServiceBuilding InspectionandTesting STATIONMAKEUPWATERSYSTEM PowerGenerationObjective G 191237,Sh2HVACFlowDiagramTurbine,Service,and ControlRoomBuildings G 191236HVACFlowDiagramRadwasteBuilding G 191254StationHeatingBoilerSystem G 191237,Sh2HVACFlowDiagramTurbine,Service,andControlRoomBuildings G 191236HVACFlowDiagramRadwasteBuilding G 191254StationHeatingBoilerSystem ReactorBuildingHeatingVentilationandAirConditioningG 191238 MAKEUPWATERSYSTEM Objective DesignBasis Description RadwasteBuilding StationHeatingBoilerSystem AdvancedOff GasBuildingHVAC InspectionandTesting G 191237,Sh1HVACFlowDiagramTurbine,Service,and ControlRoomBuildings G 191237,Sh1HVACFlowDiagramTurbine,Service,andControlRoomBuildings G 191161Make UpWaterTreatmentSystem STATIONINSTRUMENTANDSERVICEAIRSYSTEMS PowerGenerationObjective PretreatmentSystem DemineralizerSystem InspectionandTesting InspectionandTesting G 191161Make UpWaterTreatmentSystem INSTRUMENTANDSERVICEAIRSYSTEMS Objective PowerGenerationDesignBasis Description General Page96of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.14.2 ModifySection10.14.2,StationInstrumentandServiceAirSystems,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheStationInstrumentandServiceAirSystemsnowsupplyonlypressurizedairnecessarytoensurethesafestorageandhandlingofirradiatedfuel.Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.6.2 10.14.3 ModifySection10.14.3,StationInstrumentandServiceAirSystems,Descriptiontoremovereferencetooperatingandaccidentconditions,theCompressednitrogensystemandreflectthattheStationInstrumentandServiceAirSystemsnowsupplyonlypressurizedairnecessarytoensurethesafestorageandhandlingofirradiatedfuel.TheCompressednitrogenSystemsuppliedcompressednitrogenforpneumaticinstrumentsandcontrolslocatedintheprimarycontainmentwhencontainmentwasinerted.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceprimarycontainmentisnolongerrequiredandcontainmentinertingwillnolongeroccur,compressednitrogenforpneumaticsinthedrywellisnolongerrequired.3.3.6.310.14.4Editorialchangesonly 3.3.6.4 Figure10.14 1 Nochanges Figure3.3.6 1 Figure10.14 2 Nochanges Figure3.3.6 2 Figure10.14 3 Nochanges Figure3.3.6 3 Figure10.14 4 Nochanges Figure3.3.6 4 Figure10.14 5 Nochanges Figure3.3.6 5 Figure10.14 6 Nochanges Figure3.3.6 6 Figure10.14 7 Nochanges Figure3.3.6 7 Figure10.14 8 Nochanges Fi gure3.3.6 8 10.15 3.3.8.2 10.15.1 ModifySection10.15.1,StationPotableandSanitaryWaterSystem,PowerGenerationObjective,toremovereferencetooperatingandaccidentcondition s Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.8.2.1 10.15.2 ModifySection10.15.2,StationPotableandSanitaryWaterSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentcondition s Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.3.3.8.2.2 10.15.3 Mo d i f ie dSection10.15.3,Description,toremovere f erenceto" pota bl e"wateran dc h angenum b ero fwe ll sf romf ourtotwoan dremoveover l yd etai l e din f ormation,toaccommo d atec h ange s duetoEC45613,trackedbyFCR27 003.3.3.8.2.3 10.16 4.5.1 10.16.1 ModifySection10.16.1,StationEquipmentandFloorDrainageSystems,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimar y stationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.1 10.16.2 ModifySection10.16.2,StationEquipmentandFloorDrainageSystems,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheprimar y stationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.2 10.16.3 4.5.1.310.16.3.1NoChanges 4.5.1.3.1 10.16.3.2 ModifySection10.16.3.2,RadioactiveEquipmentDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.3.2 10.16.3.3 ModifySection10.16.3.3,RadioactiveFloorDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.3.3 10.16.3.4 ModifySection10.16.3.4,RadioactiveLiquidChemicalDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.3.4 PowerGenerationDesignBasis Description InspectionandTesting DesignBasis Description InspectionandTesting G 191160,Sh7FlowDiagramDieselGeneratorStartingAirSystem G 191160,Sh8FlowDiagramServiceAirSystem STATIONPOTABLEANDSANITARYWATERSYSTEM G 191160,Sh4InstrumentAirSystemFlowDiagram G 191160,Sh5FlowDiagramServiceAirSystem G 191160,Sh6FlowDiagramServiceAirSystem G 191160,Sh1FlowDiagramInstrumentAirSystem G 191160,Sh2ServiceandInstrumentAirSystem(Reactor G 191160,Sh3InstrumentAirSystemFlowDiagram POTABLEANDSANITARYWATERSYSTEM G 191160,Sh1FlowDiagramInstrumentAirSystem G 191160,Sh2ServiceandInstrumentAirSystem(Reactor G 191160,Sh3InstrumentAirSystemFlowDiagram G 191160,Sh4InstrumentAirSystemFlowDiagram G 191160,Sh5FlowDiagramServiceAirSystem G 191160,Sh6FlowDiagramServiceAirSystem G 191160,Sh7FlowDiagramDieselGeneratorStartingAirSystem G 191160,Sh8FlowDiagramServiceAirSystem Description General RadioactiveEquipmentDrainageSystems STATIONEQUIPMENTANDFLOORDRAINAGESYSTEMS PowerGenerationObjective PowerGenerationDesignBasis PowerGenerationObjective PowerGenerationDesignBasis Description Objective DesignBasis Description EQUIPMENTANDFLOORDRAINAGESYSTEMS Objective DesignBasis Description General RadioactiveEquipmentDrainageSystems RadioactiveFloorDrainageSystems RadioactiveLiquidChemicalDrainageSystems RadioactiveFloorDrainageSystems RadioactiveLiquidChemicalDrainageSystems Page97of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.16.3.5 ModifySection10.16.3.5,OilDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingo irradiatedfuel.Editorialmodificationaddedtoremovethepotentialimpressionthatanoil watermixturemaybedrainedtotheenvironment.

4.5.1.3.5 10.16.3.6 ModifySection10.16.3.6,NonradioactiveWaterDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.3.6 10.16.3.7 ModifySection10.16.3.7,SanitaryDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingofirradiatedfuel.4.5.1.3.7 10.16.4 Modifysection10.16.4,StationEquipmentandFloorDrainageSystems,InspectionandTestingtoreflectthatthefacilityEquipmentandFloorDrainageSystemsareinconstantoperation,specialtestingandinspectionisnotrequired.Deleteexistingtestingandinspectionrequirementssincethoseareconstructionandinstallationrequirmentsandarenolongerapplicable.

4.5.1.4 10.17 3.3.7 10.17.1 Delete"PowerGeneration"fromsectiontitle.Modifysectiontoreflectdefueledstate 3.3.7.1 10.17.2 Delete"PowerGeneration"fromsectiontitle.Modifysectiontoreflectdefueledstate 3.3.7.2 10.17.3 3.3.7.3 10.17.3.1 Modifiedtoreflectdefueledstat e DeletedpointertoProcessRadMonitoring,notrequired 3.3.7.3.110.17.3.2Deletethissection,notrequiredpostdefueling,allsamplepointfromabandonedsystems 10.17.3.3 Deletethissection,notrequiredpostdefueling,allsamplepointfromabandonedsystems 10.17.3.4 NoChanges 3.3.7.3.2 10.17.3.5 EditorialchangetoremovereferencetoaUFSARsectionwhichnolongerexists,otherwise,nochanges 3.3.7.3.3 Table10.17.1 ModifiedTable10.17.1,FluidSamplestoremovefluidsamplepointsnolongerusedpostdefueling.TheReactorwater,cleanup,mainsteamline,StandbyLiquidControl,Feedwater,closedcoolingloop,condensateandCirculatingwatersystemsarenolongerrequiredfollowingpermanentdefueling.Therefore,samplingofthosesystemsisnolongerrequired.TheinformationdeletedfromTable10.17.1isobsolete.Remaininginformationinthetablehasbeenrelocatedintothetextbodyofthissection Table10.17.2 ModifiedTable10.17.2,GasSamplestoremovegaseoussamplepointsnolongerusedpostdefueling.TheAirEjectoroffgas,OffGasFiltersamplesandStandbyGasTreatmentSystemsaren o longerrequiredfollowingpermanentdefueling.Therefore,samplingofthosesystemsisnolongerrequired.TheinformationdeletedfromTable10.17.2isobsolete.Remaininginformationinthetablehasbeenrelocatedintothetextbodyofthissection Figure10.17 1 Nochanges Figure3.3.7 1 Figure10.17 2 Nochanges Fi gure3.3.7 2 10.18 3.3.10 10.18.1 ModifySection10.18.1,StationCommunicationsSystem,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctioni nowthesafestorageandhandlingofirradiatedfuel.3.3.10.1 10.18.2 ModifySection10.18.2,StationCommunicationsSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctio n isnowthesafestorageandhandlingofirradiatedfuel.3.3.10.2 10.18.3 ModifySection10.18.3,StationCommunicationsSystem,Descriptiontoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesaf e storageandhandlingofirradiatedfuel.3.3.10.3 10.18.4 NoChanges 3.3.10 4 10.19 3.3.9 10.19.1 ModifySection10.19.1,StationLightingSystem,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowth e safestorageandhandlingofirradiatedfuel.3.3.9.1 10.19.2 ModifySection10.19.2,StationLightingSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisno w thesafestorageandhandlingofirradiatedfuel.3.3.9.2 10.19.3 ModifySection10.19.3,StationLightingSystem,Descriptiontoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestoragean d handlingofirradiatedfuel.3.3.9.310.19.4Nochanges 3.3.9.4 General TurbineBuildingSamplingPanel ReactorBuildingSamplingPanel PowerGenerationObjective PowerGenerationDesignBasis Description NonradioactiveWaterDrainageSystems SanitaryDrainageSystems InspectionandTesting STATIONPROCESSSAMPLINGSYSTEMS OilDrainageSystems OilDrainageSystems NonradioactiveWaterDrainageSystems SanitaryDrainageSystems InspectionandTesting PROCESSSAMPLINGSYSTEMS Objective PowerGenerationObjective PowerGenerationDesignBasis Description Description InspectionandTesting STATIONLIGHTINGSYSTEMS STATIONCOMMUNICATIONSSYSTEM PowerGenerationObjective PowerGenerationDesignBasis GasSamples G 191164StationProcessSamplingSystem G 191165StationProcessSamplingSystem RadwasteBuildingSamplingPanel GasSamplingandMonitoring FluidSamples G 191164StationProcessSamplingSystem G 191165StationProcessSamplingSystem Objective DesignBasis Description InspectionandTesting COMMUNICATIONSSYSTEM LIGHTINGSYSTEMS Objective DesignBasis Description InspectionandTesting InspectionandTesting DesignBasis Description General RadwasteBuildingSamplingPanel GasSamplingandMonitoring Page98of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table10.19.1 Mo d i f yTa bl e10.19.1,AreasRequiringStan db yLig h ting,toremovere f erencetooperatingan dacci d entcon d itionsan dre fl ectt h att h eprimarystationf unctionisnowt h esa f estoragean d handlingofirradiatedfuel.Remaininginformationinthetablehasbeenrelocatedintothetextbodyinthissection.10.20 Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.10.20.1 Deletesection10.20.1,PostAccidentSamplingSystemSafetyObjective.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystemarenolongerrequired.ThePostAccidentSamplingSystemSafetyObjectiveisnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.10.20.2 Deletesection10.20.2,PostAccidentSamplingSystemSafetyDesignBasis.Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystemarenolongerrequired.ThePostAccidentSamplingSystemSafetyDesignBasisisnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.10.20.3 Deletesection10.20.3,PostAccidentSamplingSystemDescription.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystemarenolongerrequired.TheinformationprovidedinthePostAccidentSamplingSystemDescriptionsectionisnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.10.20.4 Deletesection10.20.4,PostAccidentSamplingSystemSafetyEvaluation.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystemarenolongerrequired.APostAccidentSamplingSystemSafetyEvaluationnolongerrequired.PostAccidentSamplingSysteminformationisobsolete.10.20.5 Deletesection10.20.5,PostAccidentSamplingSystemInspectionandTesting.Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystemarenolongerrequired.InspectionandTestingofthePostAccidentSamplingSystemisnolongerrequired.PostAccidentSamplingSysteminformationisobsolete.Figure10.20 1 DeleteFigure10.20 1,FundamentalFlowDiagramPostAccidentSamplingSystem.Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystemarenolongerrequired.Theinformationprovidedonfigure10.20 1isnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.10.21 TheAdvancedOff GasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycol watercoolingtoauxiliaryequipmentintheadvancedoff gasbuilding.10.21.1 Deletesection10.21.1,AdvancedOff GasCoolingWaterSystemPowerGenerationObjective.

TheAdvancedOff GasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycol watercoolingtoauxiliaryequipmentintheadvancedoff gasbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOff GasClosedCoolingWaterSystemarenolongerrequired.TheAdvancedOff GasClosedCoolingWaterSystemPowerGenerationObjectiveisnolongerapplicable.AdvancedOff GasClosedCoolingWaterSysteminformationisobsolete.PowerGenerationObjective SafetyDesignBasis Description

SafetyEvaluation InspectionandTesting G 191165FundamentalFlowDiagramPostAccidentSamplingSystem ADVANCEDOFFGASCLOSEDCOOLINGWATERSYSTEM AreasRequiringStandbyLighting POSTACCIDENTSAMPLINGSYSTEM SafetyObjective Page99of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.21.2 Deletesection10.21.2,AdvancedOff GasCoolingWaterSystemPowerGenerationDesignBasis.TheAdvancedOff GasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycol watercoolingtoauxiliaryequipmentintheadvancedoff gasbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOff GasClosedCoolingWaterSystemarenolongerrequired.TheAdvancedOff GasClosedCoolingWaterSystemPowerGenerationDesignBasisisnolongerapplicable.AdvancedOff GasClosedCoolingWaterSysteminformationisobsolete.10.21.3 Deletesection10.21.3,AdvancedOff GasCoolingWaterSystemDescription.

TheAdvancedOff GasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycol watercoolingtoauxiliaryequipmentintheadvancedoff gasbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOff GasClosedCoolingWaterSystemarenolongerrequired.TheinformationprovidedintheAdvancedOff GasClosedCoolingWaterSystemDescriptionisnolongerapplicable.AdvancedOff GasClosedCoolingWaterSysteminformationisobsolete.10.21.4 Deletesection10.21.4,AdvancedOff GasCoolingWaterSystemInspectionandTesting.TheAdvancedOff GasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycol watercoolingtoauxiliaryequipmentintheadvancedoff gasbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOff GasClosedCoolingWaterSystemarenolongerrequired.InspectionandtestingoftheAdvancedOff GasClosedCoolingWaterSystemisnolongerrequired.AdvancedOff GasClosedCoolingWaterSysteminformationisobsolete.Figure10.21 1 DeleteFigure10.21 1,AOGCWFlowDiagram.TheAdvancedOff GasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycol watercoolingtoauxiliaryequipmentintheadvancedoff gasbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOff GasClosedCoolingWaterSystemarenolongerrequired.TheinformationprovidedonFigure10.21 1isnolongerapplicable.AdvancedOff GasClosedCoolingWaterSysteminformationisobsolete.11.0 StationPowerConversionSystems 11.1 DeleteSection11.1,SummaryDescriptionoftheStationPowerConversionSystems.Thestationpowerconversionsystemswerethosesystemswhichwererequiredtoconverttheenergyofnuclearsteamtoelectricalenergy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformationprovidedbytheStationPowerConversionSystemsarenolongerrequired.StationPowerConversionSystemsinformationisobsolete.11.2 TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.11.2.1 DeleteSection11.2.1,MainTurbineGeneratorPowerGenerationObjective.

TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformationprovidedbytheMainTurbineGeneratorarenolongerrequired.TheMainTurbineGeneratorPowerGenerationObjectiveisnolongerapplicable.MainTurbineGeneratorinformationisobsolete.11.2.2 DeleteSection11.2.2,MainTurbineGeneratorPowerGenerationDesignBasis TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformationprovidedbytheMainTurbineGeneratorarenolongerrequired.TheMainTurbineGeneratorPowerGenerationDesignBasisisnolongerapplicable.MainTurbineGeneratorinformationi obsolete.11.2.3 DeleteSection11.2.3,MainTurbineGenerator,Description.

TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformationprovidedbytheMainTurbineGeneratorarenolongerrequired.TheinformationprovidedintheMainTurbineGeneratordescriptionsectionisnolongerapplicable.MainTurbineGeneratorinformationisobsolete.11.2.4 DeleteSection11.2.4,MainTurbineGenerator,InspectionandTesting.TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformationprovidedbytheMainTurbineGeneratorarenolongerrequired.InspectionandTestingoftheMainTurbineGeneratorisnolongerrequired.MainTurbineGeneratorinformationisobsolete.PowerGenerationDesignBasis Description

TestingandInspection G 191159,Sh6AOGCWFlowDiagram

SUMMARY

DESCRIPTION MAINTURBINEGENERATOR PowerGenerationObjective PowerGenerationDesignBasis Description TestingandInspection Page100of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure11.2 1 DeleteFigure11.2 1,TurbineGenerator,MainSteamandExtractionSteamSystems.TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformationprovidedbytheMainTurbineGeneratorarenolongerrequired.TheinformationprovidedonFigure11.2 1isnolongerapplicable.MainTurbineGeneratorinformationisobsolete.11.3 TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationofcondensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.11.3.1 DeleteSection11.3.1,MainCondenserSystem,PowerGenerationObjective.TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationofcondensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired,condensatepumpNPSHisnotrequiredandnosteamcyclemakeupisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.TheMainCondenserSystemPowerGenerationObjectiveisnolongerapplicable.MainCondenserinformationisobsolete.11.3.2 DeleteSection11.3.2,MainCondenserSystem,PowerGenerationDesignBasisTheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationofcondensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired,condensatepumpNPSHisnotrequiredandnosteamcyclemakeupisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.TheMainCondenserSystemPowerGenerationDesignBasesarenolongerapplicable.MainCondenserinformationisobsolete.11.3.3 DeleteSection11.3.3,MainCondenserSystem,PowerGenerationDesignBasisTheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationofcondensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired,condensatepumpNPSHisnotrequiredandnosteamcyclemakeupwastisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.TheMainCondenserSystemPowerGenerationDesignBasesarenolongerapplicable.MainCondenserinformationisobsolete.11.3.4 DeleteSection11.3.4,MainCondenserSystem,PowerGenerationDesignBasisTheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationofcondensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired,condensatepumpNPSHisnotrequiredandnosteamcyclemakeupwastisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.InspectionandTestingoftheMainCondenserSystemisnolongerrequired.MainCondenserinformationisobsolete.11.4 Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

11.4.1 DeleteSection11.4.1,MainCondenserGasRemovalandTurbineSealingSystems,PowerGenerationObjective.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewillnolongeroperate,turbinesealingisnotrequired.ThefunctionsandinformationprovidedbytheMainCondenserGasRemovalandTurbineSealingSystemsarenolongerrequired.TheMainCondenserGasRemovalandTurbineSealingSystemsPowerGenerationObjectiveisnolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.PowerGenerationObjective MAINCONDENSERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Description TestingandInspection MAINCONDENSERGASREMOVALANDTURBINESEALINGSYSTEMS G 191156TurbineGenerator,MainSteamandExtractionSteamSystems Page101of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.4.2 DeleteSection11.4.2,MainCondenserGasRemovalandTurbineSealingSystems,PowerGenerationObjective.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewillnolongeroperate,turbinesealingisnotrequired.ThefunctionsandinformationprovidedbytheMainCondenserGasRemovalandTurbineSealingSystemsarenolongerrequired.TheMainCondenserGasRemovalandTurbineSealingSystemsPowerGenerationDesignBasesarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.11.4.3 11.4.3.1 DeleteSection11.4.3.1,MainCondenserGasRemovalandTurbineSealingSystems,GeneralDescription.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewillnolongeroperate,turbinesealingisnotrequired.ThefunctionsandinformationdescribedintheMainCondenserGasRemovalandTurbineSealingSystemsGeneralDescriptionSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.11.4.3.2 DeleteSection11.4.3.2,MainCondenserGasRemovalandTurbineSealingSystems,CondenserHoggingPump.Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.AmechanicalacmotordrivenremotemanuallyoperatedVBeltrotarytypepumpremovednon condensiblegassesduringstartup.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.ThefunctionsandinformationdescribedintheCondenserHoggingPumpSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.11.4.3.3 DeleteSection11.4.3.3,MainCondenserGasRemovalandTurbineSealingSystems,SteamJetAirEjectors.Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Duringoperation,steamjetairejectorsremovedgasesandvaporsfromthemaincondensersusingmainsteam,reducedinpressure,asthedrivingmedium..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.ThefunctionsandinformationdescribedintheSteamJetAirEjectorsSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.11.4.3.4 DeleteSection11.4.3.4,MainCondenserGasRemovalandTurbineSealingSystems,SteamPackingExhausterUnit.Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Duringoperation,onesteampackingexhausterunitcollectedandcondensedsealingsteamanddischargedairleakagetotheoffgassystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.ThefunctionsandinformationdescribedintheSteamPackingExhausterUnitSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.11.4.3.5 DeleteSection11.4.3.5,MainCondenserGasRemovalandTurbineSealingSystems,SteamSealRegulator.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Duringoperation,thesteamsealregulatormaintainedthesamepreselectedsteampressureinthepackingheaderregardlessofthesteamturbineload..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.ThefunctionsandinformationdescribedintheSteamSealRegulatorSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.PowerGenerationDesignBases Description General CondenserHoggingPump SteamJetAirEjectors SteamPackingExhausterUnit SteamSealRegulator Page102of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.4.4 DeleteSection11.4.4,MainCondenserGasRemovalandTurbineSealingSystems,InspectionandTesting.Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewillnolongeroperate,turbinesealingisnotrequired.InspectionandTestingoftheMainCondenserGasRemovalandTurbineSealingSystemsGeneralDescriptionSectionisnotrequired.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.Figure11.4 1 DeleteFigure11.4 1,TurbineSteamSealSystem.Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewillnolongeroperate,turbinesealingisnotrequired.TheinformationprovidedonFigure11.4 1isnolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.11.5 Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.11.5.1 DeleteSection11.5.1,SteamSystems,PowerGenerationObjective.Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsPowerGenerationObjectiveisnolongerapplicable.SteamSystemsinformationisobsolete.11.5.2 DeleteSection11.5.2,SteamSystems,PowerGenerationDesignBasesThesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsPowerGenerationDesignBasesarenolongerapplicable.SteamSystemsinformationisobsolete.11.5.3 DeleteSection11.5.3,SteamSystems,SafetyDesignBasesThesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsSafetyDesignBasesarenolongerapplicable.SteamSystemsinformationisobsolete.11.5.4 11.5.4.1 DeleteSection11.5.4.1,MainSteamSystemDescription Themainsteamsystemconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbine.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,themainsteamsystemisnolongerrequired.ThedescriptionoftheMainSteamSystemisnolongerapplicable.SteamSystemsinformationisobsolete.11.5.4.2 DeleteSection11.5.4.2,MainSteamTurbineBypassSystemDescription TheMainTurbineBypasssystemopenedwheneverthepermittedadmissionofsteamintotheturbinewaslessthantheamountofsteamgeneratedbythereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,themainturbinebypasssystemisnolongerrequired.Thedescriptionofthemainturbinebypasssystemisnolongerapplicable.SteamSystemsinformationisobsolete.PowerGenerationDesignBases SafetyDesignBases Description MainSteamSystem MainTurbineBypassSystem InspectionandTesting 5920 12598TurbineSteamSealSystem STEAMSYSTEMS PowerGenerationObjective Page103of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.5.4.3 DeleteSection11.5.4.3,ExtractionSteamSystemDescription.ExtractionSteamprovidedsteamforfeedwaterpre heating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,theExtractionSteamsystemisnolongerrequired.ThedescriptionoftheExtractionSteamSystemisnolongerapplicable.SteamSystemsinformationisobsolete.11.5.5 DeleteSection11.5.5,SteamSystems,SafetyEvaluationThesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsSafetyEvaluationisarenolongerapplicable.SteamSystemsinformationisobsolete.11.5.6 DeleteSection11.5.6SteamSystems,TestsandInspections.

Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TestsandInspectionoftheSteamSystemsarenolongerrequired.SteamSystemsinformationisobsolete.Figure11.5 1 DeleteFigure11.5 1,PrimarySteamPipingArrangement.Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectlytothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,andduringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheinformationprovidedonFigure11.5 1isnolongerapplicable.SteamSystemsinformationisobsolete.11.6 TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersforsteamcondensationandheatremovalinthecondensers.

11.6.1 DeleteSection11.6.1,CirculatingWaterSystems,PowerGenerationObjective.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersforsteamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.TheCirculatingWaterSystemsPowerGenerationObjectiveisnolongerapplicable.CirculatingWaterSystemsinformationisobsolete.11.6.2 DeleteSection11.6.2,CirculatingWaterSystems,PowerGenerationDesignBases.TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersforsteamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.TheCirculatingWaterSystemsPowerGenerationDesignBasesarenolongerapplicable.CirculatingWaterSystemsinformationisobsolete.11.6.3 DeleteSection11.6.3,CirculatingWaterSystems,Description.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersforsteamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.ThefunctionsandinformationprovidedbytheCirculatingWaterSystemarenolongerrequired.InformationprovidedintheCirculatingWaterSystemDesriptionsectionisnolongerapplicable.MainCondenserinformationisobsolete.SafetyEvaluation TestsandInspections 5920 569PrimarySteamPipingArrangement CIRCULATINGWATERSYSTEMS PowerGenerationObjective PowerGenerationDesignBases ExtractionSteam Description Page104of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.6.4 DeleteSection11.6.4,CirculatingWaterSystems,InspectionandTesting.TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersforsteamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.InspectionandTestingoftheCirculatingWaterSystemisnolongerrequired.InformationprovidedintheCirculatingWaterSystemInspectionandTestingsectionisnolongerapplicable.MainCondenserinformationisobsolete.Figure11.6 1 DeleteFigure11.6 1,CirculatingWaterSystems.TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersforsteamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.ThefunctionsandinformationprovidedbytheCirculatingWaterSystemarenolongerrequired.InformationprovidedonFigure11.6 1isnolongerapplicable.CirculatingWaterinformationisobsolete.11.7 Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.11.7.1 DeleteSection11.7.1,CondensateDemineralizerSystem,PowerGenerationObjective.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thecondensatedemineralizersystemisnolongerrequired.TheCondensateDemineralizerSystemPowerGenerationObjectiveisnolongerapplicable.InformationprovidedintheCondensateDemineralizerPowerGenerationObjectivesectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.11.7.2 DeleteSection11.7.2,CondensateDemineralizerSystem,PowerGenerationDesignBases.Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thecondensatedemineralizersystemisnolongerrequired.TheCondensateDemineralizerSystemPowerGenerationDesignBasesarenolongerapplicable.InformationprovidedintheCondensateDemineralizerPowerGenerationDesignBasessectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.11.7.3 11.7.3.1 DeleteSection11.7.3.1,CondensateDemineralizerSystem,GeneralDescription.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerGeneralDescriptionsectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.11.7.3.2 DeleteSection11.7.3.2,CondensateDemineralizerSystem,EquipmentDescription.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerEquipmentDescriptionsectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.11.7.3.3 DeleteSection11.7.3.3,CondensateDemineralizerSystem,ControlandInstrumentation.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerControlandInstrumentationdescriptionsectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.Description General Equipment ControlandInstrumentation InspectionandTesting G 191166CirculatingWaterSystems CONDENSATEDEMINERALIZERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Page105of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.7.3.4 DeleteSection11.7.3.4,CondensateDemineralizerSystem,Specifications.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerSpecificationssectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.11.7.4 DeleteSection11.7.4,CondensateDemineralizerSystem,InspectionandTesting.Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InspectionandTestingoftheCondensateDemineralizerSystemisnolongerrequired.CondensateDemineralizerSysteminformationisobsolete.Figure11.7 1 DeleteFigure11.7 1,CondensateDemineralizerSystem.Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedonFigure11.7 1isnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.11.8.1 DeleteSection11.8.1,CondensateandReactorFeedwaterSystems,PowerGenerationObjective.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.TheCondensateandReactorFeedwaterSystemsPowerGenerationObjectiveisnolongerapplicable.InformationprovidedintheCondensateandReactorFeedwaterSystemsPowerGenerationObjectivesectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.2 DeleteSection11.8.2,CondensateandReactorFeedwaterSystems,PowerGenerationObjective.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.TheCondensateandReactorFeedwaterSystemsPowerGenerationDesignBasesarenolongerapplicable.InformationprovidedintheCondensateandReactorFeedwaterSystemsPowerGenerationDesignBasessectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3 11.8.3.1 DeleteSection11.8.3.1,CondensateandReactorFeedwaterPumps.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheCondensateandReactorFeedwaterPumpsarenolongerrequired.InformationprovidedintheCondensateandReactorFeedwaterPumpssectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.2 DeleteSection11.8.3.2,ReactorFeedwaterHeaters.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheReactorFeedwaterHeatersarenolongerrequired.InformationprovidedintheReactorFeedwaterHeaterssectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.G 191274CondensateDemineralizerSystem 11.8 CONDENSATEANDREACTORFEEDWATERSYSTEMS Specifications InspectionandTesting CondensateandReactorFeedwaterPumps ReactorFeedwaterHeaters PowerGenerationObjective PowerGenerationDesignBases Description TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.Page106of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.8.3.3 DeleteSection11.8.3.3,CondensateDemineralizerSystem.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerSystemsectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.4 DeleteSection11.8.3.4,SteamJetAirEjector(SJAE)Intercondensers.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheSteamJetAirEjector(SJAE)Intercondensersarenolongerrequired.InformationprovidedintheSteamJetAirEjector(SJAE)Intercondenserssectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.5 DeleteSection11.8.3.5,SteamPackingExhauster.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheSteamPackingExhausterarenolongerrequired.InformationprovidedintheSteamJetAirEjector(SJAE)Intercondenserssectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.6 DeleteSection11.8.3.6,FeedwaterControlStation.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheFeedwaterControlStationarenolongerrequired.InformationprovidedintheFeedwaterControlStationsectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.7 DeleteSection11.8.3.7,CondensateandFeedwaterSystemMinimumFlowBypasses.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheCondensateandFeedwaterSystemMinimumFlowBypassesarenolongerrequired.InformationprovidedintheCondensateandFeedwaterSystemMinimumFlowBypassessectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.8 DeleteSection11.8.3.8,CondensateandFeedwaterSystemKeepFillPressurizingLine.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheKeepFillPressurizingLinearenolongerrequired.InformationprovidedintheKeepFillPressurizingLinesectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.3.9 DeleteSection11.8.3.9,CondensateandFeedwaterSystemCondensateMakeupandRejectSystems.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheCondensateMakeupandRejectSystemsarenolongerrequired.InformationprovidedintheCondensateMakeupandRejectSystemssectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.CondensateandFeedwaterSystemMinimumFlowBypasses KeepFillPressurizingLine CondensateMakeupandRejectSystems CondensateDemineralizerSystem SteamJetAirEjector(SJAE)Intercondensers SteamPackingExhauster FeedwaterControlStation Page107of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.8.3.10 DeleteSection11.8.3.10,CondensateandFeedwaterPiping TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.ThefunctionsandinformationprovidedbytheCondensateandFeedwaterPipingarenolongerrequired.InformationprovidedintheCondensateandFeedwaterPipingsectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.11.8.4 DeleteSection11.8.4,CondensateandReactorFeedwaterSystems,PowerGenerationObjective.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.InspectionandTestingoftheCondensateandReactorFeedwaterSystemsisnolongerrequired.InformationprovidedintheCondensateandReactorFeedwaterSystemsInspectionandTestingsectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.Figure11.8 1 DeleteFigure11.8 1,CondensateFeedwaterandGasRemovalSystems.TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.TheCondensateandReactorFeedwaterSystemsPowerGenerationObjectiveisnolongerapplicable.InformationprovidedonFigure11.8 1isnolongerapplicable.CondensateandReactorFeedwaterSystemsinformatio n isobsolete.11.9 TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.ThecoolingtowerstransferredheatfromthecirculatingwatertotheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.11.9.1 DeleteSection11.9.1,StationCoolingTowerWaterSystem,PowerGenerationObjective.

TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.ThecoolingtowerstransferredheatfromthecirculatingwatertotheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStationCoolingTowerWaterSystemisnolongerrequired.TheStationCoolingTowerWaterSystemPowerGenerationObjectiveisnolongerapplicable.StationCoolingTowerWaterSysteminformationisobsolete.11.9.2 DeleteSection11.9.2,StationCoolingTowerWaterSystem,PowerGenerationDesignBases.TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.ThecoolingtowerstransferredheatfromthecirculatingwatertotheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStationCoolingTowerWaterSystemisnolongerrequired.TheStationCoolingTowerWaterSystemPowerGenerationDesignBasesarenolongerapplicable.StationCoolingTowerWaterSysteminformationisobsolete.11.9.3 DeleteSection11.9.3,StationCoolingTowerWaterSystemDescription.

TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.ThecoolingtowerstransferredheatfromthecirculatingwatertotheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStationCoolingTowerWaterSystemisnolongerrequired.InformationprovidedintheStationCoolingTowerWaterSystemdescriptionsectionisnolongerapplicable.StationCoolingTowerWaterSysteminformationisobsolete.11.9.4 DeleteSection11.9.4,StationCoolingTowerWaterSystemInspectionandTesting.TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.ThecoolingtowerstransferredheatfromthecirculatingwatertotheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStationCoolingTowerWaterSystemisnolongerrequired.InspectionandtestingoftheStationCoolingTowerWaterSystemisnolongerrequired.StationCoolingTowerWaterSysteminformationisobsolete.CondensateandFeedwaterPiping InspectionandTesting G 191157,Sh1CondensateFeedwaterandGasRemovalSystems STATIONCOOLINGTOWERWATERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Description InspectionandTesting Page108of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.0 3.2 12.1 Modifysection12.1,StationStructures,SummaryDescription,todeletereferencetoprimarycontainment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.PrimaryContainmentSysteminformationisobsolete.1.3.1.2 12.2 Headingdeleted,redundant 12.2.1 Section12.2.1,LoadingConsiderationsforStructures,Foundations,EquipmentandSystems,deleteinternalreference,notrequired,excessivedetail Section12.2.1,LoadingConsiderationsforStructures,Foundations,EquipmentandSystems,deleteinternalreference,notrequired,excessivedetail.Section12.2.1,LoadingConsiderationsforStructures,Foundations,EquipmentandSystems,deleteinternalreference,notrequired,excessivedetail,section5.2hasbeendeleted.Section12.2.1,LoadingConsiderationsforStructures,Foundations,EquipmentandSystems,Deleteinformationregardingturbinebuildingdampers,HELBnolongerpossible,steamtunnelpressurizationduetosteamleaknolongerpossible,damperfunctionnolongerrequired.3.1.3 12.2.1.1 Section12.2.1.1,SeismicClassification,deletereferencetoamainsteamlinebreakoutsidethedrywell.Followingcertificationofpermanentdefueling,amainsteamlinebreakoutsidethedrywellisnotpossible.3.1.3.112.2.1.1.1ClassIStructures Section12.2.1.1.1,ClassIStructures,DeleteAlternatecoolingcellandcoolingtowercellfromlistofclassIstructures.Thefunctionsprovidedbythosestructuresarenolongerrequiredfollowingpermanentdefueling,thosestructuresnolongermeetthedefinitionofclassIstructures,therefore,thereisnorequirementtomaintainthosestructuresasClassI.3.1.3.1.112.2.1.1.2ClassIEquipment Section12.2.1.1.2,ClassIEquipment,DeletethebelowlistedequipmentfromtheclassIequipmentlist.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythebelowsystemsarenolongerrequiredandthatequipmentnolongermeetsthedefinitionofclassIequipment.

• ControlRodsandDriveSystem*ControlRodDriveHousingSupports*CoreShroud*CoreSupports*RecirculationPiping,includingvalves,pumpsandsuspensionsystem*PrimaryContainmentIsolationDampers*ReactorBuildingIsolationDampers*AllPipingConnectionsfromtheReactorPrimaryVesseluptoandincludingtheFirstIsolationValveExternaltotheDrywell*PrimaryContainmentisolationvalves*ReactorBuildingIsolationDampers*ReactorCoreHighPressureCoolantInjectionSystem*ReactorCoreIsolationCoolingSystem*StandbyLiquidControlSystem*ReactorCoreSprayCoolingSystem*ReactorBuildingClosedCoolingWaterSystem,alternatecoolingandprimarycontainmentisolationportionsonly*ReactorCoreResidualHeatRemovalSystemanditsassociatedServiceWaterSystem*AlternateCoolingSystem*StationStandbyGasTreatmentSystem*StationBatterySystem*EmergencyBussesandOtherElectricalGearandPowertoSafetyEquipment*Instrumentationandcontrolsystems:ADSbackupnitrogensupply,reactorwaterlevel,standbyliquidcontrolsystems,CRDI&CScramportions,corestandbycoolingsystems,primarycontainmentisolationsystems,controlrodpositionindicationsystems,reactorprotectionsystems,nuclearinstrumentationsystems*CondensateStorageTankandCondensateTransferSystem(linestiedtoEngineeringSafetySystems)3.1.3.1.212.2.1.1.3ClassIIStructures Section12.2.1.1.3,ClassIIStructures,DeletethebelowlistedstructuresfromtheclassIIstructurelist.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythebelowstructuresarenolongerrequiredandthatequipmentnolongermeetsthedefinitionofclassIIstructures.

• AOGBuilding*Coolingtower 3.1.3.1.3 FacilityStructures PRINCIPALSTATIONSTRUCTURESANDFOUNDATIONS LoadingConsiderationsforStructures,Foundations,EquipmentandSystems SeismicClassification

SUMMARY

DESCRIPTION StationStructures SeismicClassification LoadingConsiderationsforStructures,Foundations,EquipmentandSystems ClassIIStructures

SUMMARY

DESCRIPTION ClassIEquipment ClassIStructures Page109of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR12.2.1.1.4ClassIIEquipment Section12.2.1.1.4,ClassIIEquipment,DeletethebelowlistedequipmentfromtheclassIIequipmentlist.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythebelowsystemsarenolongerrequiredandthatequipmentnolongermeetsthedefinitionofclassIIequipment.

• AdvancedOff GasSystem*TurbineGeneratorSystem*MainCondenserSystem*ReactorFeedwaterandCondensateSystems*ReactorClean UpDemineralizerSystem*TurbineSystemMoistureSeparators

• CondensateDemineralizerSystem*SteamSeparatorsandDriers 3.1.3.1.4 12.2.1.2 3.1.3.212.2.1.2.1ClassIStructures Modifysection12.2.1.2.1todeletereferencetothealternatecoolingcell.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythealternatecoolingcellarenolongerrequired.Informationregardingthealternatecoolingcellisobsoleteandmaybedeleted.3.1.3.2.112.2.1.2.2ClassIIStructuresNochanges 3.1.3.2.2 12.2.1.2.3 EquipmentSeismicDesign Section12.2.1.2.3,EquipmentSeismicDesign,deletethestatementregardingsnubberoperabilityforthereactorcoolantandothersafetyrelatedsystems.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbytheReactorCoolantsystemarenolongerrequiredandassuranceofstructuralintegrityoftheReactorcoolantsystemduringanearthquakeisnotrequired.Followingcertificationofpermanentdefueling,onlythefuelpoolstructure,liner,racksandfuelareconsideredsafetyrelated.Thosecomponentsandstructuresdonotrequirefunctionalsnubberstomeetrequirementsduringanearthquake.

3.1.3.2.3 12.2.2 3.2.1 12.2.2.1 Section12.2.2.1,Function,ModifythestatementregardingtheSSCsenclosedbythereactorbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequentlythefunctionsprovidedbytheprimaryreactorsystem,primarycontainment,reactorauxiliaryandcoolingsystemsandreactorwellpoolarenolongerrequired.Followingcertificationofpermanentdefueling,thereactorbuildingfunctionsonlytohouseandsupportthespentfuelpool 3.2.1.1 12.2.2.2 Section12.2.2.2,Description,*addtheword"structure"followingprimarycontainmenttoreflectthefactthatfollowingpermanentdefuelingthereisnoprimarycontainmentfunction,onlytheconcretestructure.

• Deletereferencetothesystemandsupportfacilitiesforthereactor,includingReactorWaterCleanup,SupplementalCoolingSystems,ReactorControlRodDriveHydraulicSystems,aswella refuelingfunctions.ThefunctionsprovidedbythoseSSCsarenotrequiredfollowingpermanentdefueling.Section12.2.2.2,Description:

• Deleteallreferencetocorrosionofthelowerpartofthesteeldrywellliner.Followingpermanentdefueling,thefunctionprovidedbythesteellinerisnolongerrequired.Therefore,corrosionofthesteellinerisnotaconcern.Section12.2.2.2,Description:

• DeletereferencetoHELBinthereactorbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequentlyahighenergylinebreakisnolongerpossibleinthereactorbuilding.3.2.1.212.2.2.3NoChanges 3.2.1.3 12.2.3 3.2.2 ReactorBuilding Function Description SeismicAnalysis TurbineBuilding Description SeismicAnalysis TurbineBuilding SesmicDesign ReactorBuilding Function ClassIIEquipment SesmicDesign ClassIStructures ClassIIStructures EquipmentSeismicDesign Page110of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.2.3.1 Section12.2.3.1,TurbineBuildingFunction:*Paragraphmodifiedtoreflectfacilityconditionfollowingcessationofcommercialoperationsandcertificationofpermanentdefueling.Thefunctionsprovidedbytheturbinegenerator,condensate,feedwaterandwatertreatmentsystemsarenolongerrequired.Theturbinebuildingnowprovidesmiscellaneousspaceforauxiliaryequipment.

3.2.2.1 12.2.3.2 Section12.2.3.2,TurbineBuildingDescription:

• DeleteportionofturbinebuildingdescriptionstatingthattheTBhousedpowergenerationandrelatedequipment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,powergenerationwillnolongeroccur.Section12.2.3.2,TurbineBuildingDescription:

• DeleteportionofturbinebuildingdescriptionstatingthatblowoutpanelsventtheTBduringcertainhighenergylinebreaks..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,highenergylinebreaksintheturbinebuildingcannolongeroccur.3.2.2.212.2.3.3NoChanges 3.2.2.3 12.2.4 3.2.3 12.2.4.1 Section12.2.4.1,PlantStackDescription:

• Grammaticalchangesonly.3.2.3.112.2.4.2NoChanges 3.2.3.2 12.2.5 3.2.4 12.2.5.1 Section12.2.5.1,ControlRoomBuilding,Description:

• Removedreferencetostationoperation,sincestationoperationwillnotoccurfollowingcertificationofpermanentdefueling.

3.2.4.112.2.5.2NoChanges 3.2.4.2 12.2.6 3.2.5 12.2.6.1 12.2.6.1,CirculatingWaterIntakeandDischargeStructures,General.*Deletethissection.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceo retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythecirculatingwatersystemarenolongerrequiredandareobsolete.Theintakeanddischarge aeratingstructuresareaddressedinsubsequentsectionsandarenotrequiredinthissection.12.2.6.2 3.2.5.112.2.6.2.1Description 12.2.6.2.1,IntakeStructure,Description.

• Sectionrewordedtoremoveexcessdetail*Deletedreferencestothefunctionsprovidedbythecirculatingwatersystem.Followingcertificationofpermanentdefuelingpoweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecirculatingwatersystemarenolongerrequiredandmaybedeleted.CirculatingWaterSysteminformationisobsolete.3.2.5.1.112.2.6.2.2SeismicAnalysisNoChanges 3.2.5.1.2 12.2.6.3 Section12.2.6.3,DischargeandAeratingStructure.

• Sectionrewordedtoremoveexcessdetail.*Deletedreferencetothefunctionsprovidedbythecirculatingwatersystem*Deletedreferencetothepumpslocatedinthedischargestructurewhichsupplywatertothecoolingtowers.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.3.2.5.2 12.2.6.412.2.6.4.1Description Section12.2.6.4.1,CoolingTowerRecirculationWaterSystem,Description.

Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.12.2.6.4.2SeismicAnalysis Section12.2.6.4.2,CoolingTowerRecirculationWaterSystem,SeismicAnalysis.Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Sincethefunctionsprovidedbythecoolingtowersarenolongerrequired,aseismicanalysisofthecoolingtowersisalsonotrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Function Description SeismicAnalysis Description SeismicAnalysis Description SeismicAnalysis IntakeStructure DischargeandAeratingStructure Description SeismicAnalysis PlantStack ControlRoomBuilding CirculatingWaterIntakeandDischargeStructures Function Description SeismicAnalysis CirculatingWaterIntakeandDischargeStructures General IntakeStructure DischargeandAeratingStructure CoolingTowerRecirculatingWaterSystem PlantStack Description

SeismicAnalysis ControlRoomBuilding Description

SeismicAnalysis Page111of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.2.6.5 Section12.2.6.5,CoolingTowerDeepBasin.ThissectionhasbeenrewordedtoreflectthatthefunctionofthedeepbasinisnolongertoprovidealternatecoolingcellmakeupintheeventofalossoftheVernonDam.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,themakeupfunctionoftheDeepBasinisnolongerrequired.3.2.612.2.7NoChanges 3.2.712.2.7.1NoChanges 3.2.7.112.2.7.2NoChanges 3.2.7.212.2.8NoChanges 3.1.4 3.2.8 Table12.2.1NoChanges Table3.1.1 Table12.2.2NoChanges Table3.1.2 Figure12.21NoChanges Figure3.2 1 Figure12.22NoChanges Figure3.2 1 Figure12.23NoChanges Figure3.2 2 Figure12.24NoChanges Figure3.2 2 Figure12.25NoChanges Figure3.2 2 Figure12.26NoChanges Figure3.2 2 Figure12.27NoChanges Figure3.2 3 Figure12.28NoChanges Figure3.2 3 Figure12.29NoChanges Figure3.2 4 Figure12.2 10 NoChanges Figure3.2 5 Figure12.2 11 NoChanges Figure3.2 6 Figure12.2 12 NoChanges Figure3.2 7 Figure12.2 13 NoChanges Figure3.2 7 Figure12.2 14 NoChanges Figure3.2 8 Figure12.2 15 NoChanges Figure3.2 8 Figure12.2 16 NoChanges Figure3.2 18 Drawingaddedsinceitisreferencedinthetextbody.Figure3.2 9 Figure12.2 17 NoChanges Figure3.2 10 Figure12.2 18 NoChanges Figure3.2 11 Figure12.2 19 NoChanges Figure3.2 11 G 191147TurbineBuildingSectionD D MainStackGeometry G 191146TurbineBuildingSectionB B G 191147TurbineBuildingSectionC C G 191592ControlRoomBuildingPlanView(Typical)G 191595ControlRoomElevation(EasternWall)G 191595ControlRoomBuildingElevation(WestWall)CoolingTowerDeepBasin InterimSpentFuelStorageInstallation G 191142PLOTPLAN References AllowableStressesforClassIStructures SafetyMarginsforSeveralCriticalPortionsofMajorClassIStructures G 191148ReactorBuildingPlanEL.213' 9 G 191148ReactorBuildingPlanEL.252' 6 G 191149ReactorBuildingPlanEL.280'G 191149ReactorBuildingPlanEL.303'G 191149ReactorBuildingPlanEL.318' 8 G 191149ReactorBuildingPlanEL.345' 2 G 191150ReactorBuildingSectionA A G 191150ReactorBuildingSectionB B G 191143TurbineBuildingBasementPlan G 191144TurbineBuildingGroundFloorPlan G 191145TurbineBuildingOperatingFloorPlan G 191146TurbineBuildingSectionA A Description SeismicAnalysis InterimSpentFuelStorageInstallation Description SeismicAnalysis References AllowableStressesforClassIStructures SafetyMarginsforSeveralCriticalPortionsofMajorClassIStructures CoolingTowerDeepBasin G 191146TurbineBuildingSectionB B G 191147TurbineBuildingSectionC C G 191147TurbineBuildingSectionD D MainStackGeometry G 191592ControlRoomBuildingPlanView(Typical)G 191595ControlRoomElevation(EasternWall)G 191150ReactorBuildingSectionA A G 191150ReactorBuildingSectionB B G 191143TurbineBuildingBasementPlan G 191144TurbineBuildingGroundFloorPlan G 191145TurbineBuildingOperatingFloorPlan G 191146TurbineBuildingSectionA A G 191148ReactorBuildingPlanEL.213' 9 G 191148ReactorBuildingPlanEL.252' 6 G 191149ReactorBuildingPlanEL.280'G 191149ReactorBuildingPlanEL.303'G 191149ReactorBuildingPlanEL.318' 8 G 191149ReactorBuildingPlanEL.345' 2 G 191595ControlRoomBuildingElevation(WestWall)Page112of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure12.2 20 NoChanges Figure3.2 11 Figure12.2 21 NoChanges Figure3.2 11 Figure12.2 22 NoChanges Figure3.2 12 Figure12.2 23 NoChanges Figure3.2 13 Figure12.2 24 NoChanges Figure3.2 14 Figure12.2 25 NoChanges Figure3.2 15 Figure12.2 26 NoChanges Figure3.2 16 Figure12.2 27 NoChanges Figure3.2 17 Figure12.2 28 DeleteFigure12.2 28.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythecirculatingwatersystemarenolongerrequiredandareobsolete.Theinformationshownonthisfigureisnolongerapplicableandisobsolete.Figure12.2 29 DeleteFigure12.2 29.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythecirculatingwatersystemarenolongerrequiredandareobsolete.Theinformationshownonthisfigureisnolongerapplicableandisobsolete.Figure12.2 30 DeleteFigure12.2 30.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythecirculatingwatersystemarenolongerrequiredandareobsolete.Theinformationshownonthisfigureisnolongerapplicableandisobsolete.Figure12.2 31 DeleteFigure12.2 31.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Figure12.2 32 DeleteFigure12.2 32.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Figure12.2 33 DeleteFigure12.2 33.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Figure12.2 34 DeleteFigure12.2 34.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Figure12.2 35 DeleteFigure12.2 35.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Figure12.2 36 DeleteFigure12.2 36.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.Figure12.2 37 NoChanges Figure3.1 1 Figure12.2 38 NoChanges Figure3.1 2 Figure12.2 39 DeleteFigure12.2 39.ThefigureisnotreferencedinUFSARSection12.2.ThisinformationisadequatelyaddressedintheISFSISAR.Figure12.2 40 DeleteFigure12.2 40.ThefigureisnotreferencedinUFSARSection12.2.ThisinformationisadequatelyaddressedintheISFSISAR.12.3 4.2 G 191595ControlRoomBuildingElevation(NorthWall)G 191595ControlRoomBuildingElevation(SouthWall)G 191451IntakeStructureMasonry G 191452IntakeStructureMasonry G 191453IntakeStructureMasonry G 191463DischargeStructureMasonry G 191461,sh1DischargeStructureMasonry G 200347AeratingStructureMasonryandReinforcing G 191529ReactorBuildingReactorVesselPedestalMatM+R G 191483ReactorBuildingFoundationMatPlan M+R G 200353CoolingTowerNo.1BasinPlan CoolingTowerNo.1BasinElevationView G 191463DischargeStructureMasonry G 191461,sh1DischargeStructureMasonry G 200347AeratingStructureMasonryandReinforcing G 200349CirculatingWaterSystemPartialPlanandProfile G 191448CirculatingWaterSystemGeneralPlanandProfile G 200350CirculatingWaterSystemCoolingTowerPipingSectionsandDetails G 191595ControlRoomBuildingElevation(NorthWall)G 191595ControlRoomBuildingElevation(SouthWall)G 191451IntakeStructureMasonry G 191452IntakeStructureMasonry G 191453IntakeStructureMasonry 5920 3324CoolingTowerTypicalPlan 5920 3326CoolingTowerTypicalSectionandFanDeckPlan G 200357CoolingTowerNo.2BasinPlanView G 200357CoolingTowerNo.2BasinElevationView G 191529ReactorBuildingReactorVesselPedestalMatM+R G 191483ReactorBuildingFoundationMatPlan M+R 5920 13400ISFSIConcreteStoragePad-LocationSitePlan 5920 13402ISFSIConcreteStoragePad-Plan,Sections,andDetails RADIATIONSHIELDING RadiationShielding Page113of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.3.1 ModifySection12.3.1,RadiationShielding,PowerGenerationObjective,todeletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.CombinedthepowergenerationobjectiveandsafetyobjectiveintoonesectionstatingtheobjectiveofRadiationShieldinginthepermanentlydefueledstate.4.2.1 12.3.2 DeleteSection12.3.2,RadiationShielding,SafetyObjective.Sincetheterm"Safety"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyobjectionofradiation 12.3.3 DeleteSection12.3.3,RadiationShielding,PowerGenerationDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelated12.3.4 ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletetheterm"Safety"fromthesectiontitle.Sincetheterm"Safety"isbasedintheclassificationprocessdescribedinUFSARsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingof"typical"areas.Thisinformationisexcessivedetailwhichisnotrequiredandisnolongerapplicableinthedefueledstate.ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingof"typical"areaswithinthecontrolledboundaryareas.Thisinformationisexcessivedetailwhichisnotrequire andmaynolongerbeapplicable.

ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingof"typical"zoneIVareaswithinthecontrolledboundaryareas.Thisinformationisexcessivedetailwhichisnotrequiredandmaynolongerbeapplicable.

ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingofareaswhichwillbeequippedwithlocalmonitoringdevices.Thisinformationisexcessivedetailwhichisnotrequiredandmaynolongerbeapplicable.

Deleteinternalreferencetosection7.Internalreferencenotrequired.4.2.2 12.3.5 4.2.312.3.5.1ModifySection12.3.5.1,materialsdescriptiontoremovereferencetotheshieldingsafetydesignbasis.Informationisnolongerapplicable.

4.2.3.1 12.3.5.2 ModifySection12.3.5.2,ReactorBuilding,toremovethediscussionregardingsacrificialshieldingprovidedinthedrywell.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationregardingthefunctionsprovidedbythesacrificialshieldingdescribedinthisparagraphisnolongerapplicableandisobsolete.ModifySection12.3.5.2,ReactorBuilding,toremovethediscussionregardingsacrificialshieldingprovidedinthedrywell.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationregardingthefunctionsprovidedbythesacrificialshieldingdescribedinthisparagraphisnolongerapplicableandisobsolete.ModifySection12.3.5.2,ReactorBuilding,toremovethediscussionregardingbiologicalshieldprovidedinthedrywell.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationregardingthefunctionsprovidedbythebiologicalshielddescribedinthisparagraphisnolongerapplicableandisobsolete.4.2.3.2 12.3.5.3 DeleteSection12.3.5.3,RadiationShielding,TurbineBuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,generationofNitrogen 16gammaradiationisnotaconcernanddoesnotcontributetotheneedforshieldingintheturbinebuilding.Therefore,theareaslisteddonotrequireshieldingastheresultofpoweroperations.Residualradiationastheresultofremainingradioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.12.3.5.4 ModifySection12.3.5.4,MainControlRoomandTechnicalSupportCenter(TSC)toremovethestatementregardingadditionalshieldingtothefloorabovetheTSCtolimitdirectgammadosetopersonnelintheTSCduringadesignbasisLOCA.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,adesignbasisLOCAisnolongerpossibleandreferencetotheDB A LOCAmaybedeleted.ModifySection12.3.5.4,MainControlRoomandTechnicalSupportCenter(TSC)toremovethestatementregardingTEDEduringthe30daysfollowingadesignbasisaccident.Followingpermanentdefuelingadesignbasisaccidentisnolongerpossible.ModifySection12.3.5.4todeletereferencetooperationat100%powersinceVYhasceasedpoweroperations.

4.2.3.3 12.3.5.5 DeleteSection12.3.5.5,RadiationShielding,ResidualHeatRemovalSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheResidualHeatRemovalSystemarenolongerrequired,thesystemwillnotbeplacedinoperation.Residualradiationastheresultofremainingradioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.TurbineBuilding MainControlRoomandTechnicalSupportCenter(TSC)ResidualHeatRemovalSystem SafetyObjective PowerGenerationDesignBasis SafetyDesignBasis Description MaterialsDescription ReactorBuilding PowerGenerationObjective Objective DesignBasis Description MaterialsDescription ReactorBuilding MainControlRoomandTechnicalSupportCenter(TSC)Page114of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.3.5.6 DeleteSection12.3.5.6,RadiationShielding,DemineralizerSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheDemineralizerSystemarenolongerrequired,thesystemwillnotbeplacedinoperation.Residualradiationastheresultofremainingradioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.12.3.5.7 DeleteSection12.3.5.5,RadiationShielding,AdvancedOff GasSystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOff GasSystemarenolongerrequired,thesystemwillnotbeplacedinoperation.Residualradiationastheresultofremainingradioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.12.3.6 DeleteSection12.3.6,RadiationShielding,InspectionandTesting.Thissectionprovideshistoricalinformationregardingshieldinginspectionsconductedduringtheconstructionphase.Thisinformationishistoricalandmaybedeleted.Additionally,thissectioncommitstoradiationsurveysconducteduponinitiationofreactoroperation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thereactoroperationswillnotbeconducted.Theinformationprovidedregardingradiationsurveysconductedduringpoweroperationsisnolongerapplicable,andisobsolete.12.3.7 ModifySection12.3.7,RadiationShielding,SurveillanceandTesting,todeletereferencetonormalstationoperationsandresponseofsafeguardscomponentstoaccidentormechanicalfailure.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,normalstationoperationsarenolongerpossible,andsafeguardcomponentswillnolongerbeoperated.4.2.4 12.3.8 DeleteSection12.3.8,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thereferenceslistedinsection12.3.8arenolongerapplicableandareobsolete Table12.3.1Deletetable12.3.1,thisinformationduplicatesandismoreappropriatelycontainedinfacilityprocedures Table12.3.2 DeleteTable12.3.2Designandexpectedradiationlevelsinvariousbuildings.Radiationlevelsprovidedontable12.3.2whichareboundingforoperationat100%powerarenolongeraccurateorapplicablesinceVYhasceasedpoweroperations.13.0 ConductofOperations 5 13.1 Deletedsection13.1,ConductofOperations,SummaryDescription,todeletethehistoryofownershipoftheVYNPS.Thisinformationisnotrequiredinthissectionandisredundanttosection1.1 Deletedsection13.1,ConductofOperations,SummaryDescription,ThereportingrelationshipbetweentheplantmanagerandtheSiteVPisredundanttoTechnicalSpecifications DeleteSection13.1.ThediscussiononproceduresisredundanttoTechnicalSpecificationsSection6.4 Deletedreferencetothepre operational,startupandpowertestprograms,nolongerapplicablefollowingpermanentdefueling.

DeletedreferencetoEmergencyOperatingProcedures;nolongerrequiredfollowingpermanentdefueling.Theremaininginformationinthissectioniseitherobsoleteorredundanttootherchapter13sections.13.1.1DeletedSection13.1.1References.Onlyreferencenolongercitedinbodyoftext.13.2 ModifiedSection13.2,ConductofOperations,OrganizationandResponsibility,toremovereferenceto"operating"organizationandstaffsincethestationwillnolongerbeoperatingfollowin g certificationofpermanentdefueling.

ModifiedtheQAprogrammanualtoinclude"VermontYankee"inthetitletoreflectQAprogrammanualseparationfromcorporate.

5.1 13.3 5.2 13.3.1 ModifiedSection13.3.1,TrainingProgramDescription,Generaltoreflectthestationchangefromoperationtothesafestorageandhandlingofirradiatedfuelfollowingcertificationo permanentdefueling,DeletedreferencetoINPO,sinceVYisnolongerassociatedwiththenationalacademyfornucleartrainingand.assuch.INPOdoesnotaccredittrainingprogramsforno n operatingnuclearsites.5.2.113.3.2Nochanges 5.2.213.3.2.1Nochanges 5.2.2.113.3.3Modifysection13.3.3,ConductofOperations,FireBrigadeTrainingtoremovereferencetoAppendixR,sinceappendixRdoesnotapplytopermanentlydefueledstations.5.2.3 13.3.4 ModifySection13.3.4,ConductofOperations,OperationsTraining,toremovereferenetooperationspositionswhichdonotexistfollowingpermanentdefueling,deletereerencetotheNationalAcademyforNuclearTraining,anddeletereferencetotheVYplantspecificsimulator,sincethesimulatorhasbeenremovedfromservice.5.2.4 DemineralizerSystem AdvancedOffGasSystem InspectionandTesting ProgramDescription(General)SurveillanceandTesting ConductofOperations ORGANIZATIONANDRESPONSIBILITY TRAINING ProgramDescription(General)GeneralEmployeeTraining AccesstoPlant References ORGANIZATIONANDRESPONSIBILITY TRAINING SurveillanceandTesting References GeneralOccupancyRequirementsandCorrespondingRadiationLevels ShieldingDescriptionatVariousAreas

SUMMARY

DESCRIPTIONS GeneralEmployeeTraining FireBrigadeTraining OperationsTraining AccesstoPlant FireBrigadeTraining OperationsTraining Page115of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 13.3.5 Modifysection13.3.5,Craft,TechnicianandTechnicalStaffTraining,toremovereferencetoprogramaccreditationbythenationalacademyfornucleartraining,sincetheINPOdoesnotofferaccreditationfornon operatingnuclearsitestrainingprograms.5.2.5 13.3.6 Deletesection13.3.6,ConductofOperations,PlantCertificationProgram.Since,followingcertificationofpermanentdefueling,thelicenseeisnolongerauthorizedtoemplaceorretainfueli n thereactorvessel,poweroperationscannolongeroccur.SincethePlantCertificationProgramprovidedselectedstaffwithadvancedknowledgeofplantoperation,theprogranisnolongerapplicable.

13.3.7 Modifiedsection13.3.7,ConductofOperations,TrainingRecordstoreflectthefactthatappropriatetrainingrecordswillbemaintainedinaccordancewithVYrecordsretentionpolicies.5.2.6 13.3.8 ModifiedSection13.3.8toremovereferencttoEntergyFleetTrainingProceduresandreflecttheappropriatestationorganizationalresponsibilitiespostdefueling.

5.2.7 13.3.9 5.2.8 13.3.9.1 ModifiedSection13.3.9.1,Responsibility,SuperintendentOperationsTraining,tochangethetitletoSuperintendent,Training,toreflectorganizationalandresponsibilitychangespo s defueling.Deletedreferencestotrainingprogramsnolongerapplicable,includedapplicableresponsibilitiesformerlytheroleoftheSuperintendent,NuclearTraining,sincethosepositionswerecombinedaspartofthepostdefuelingorganization.

5.2.8.1 13.3.9.2 DeleteSecyion13.3.9.2,Responsibility,SuperintendentNuclearTraining.TheapplicableresponsibilitiesoftheSuperintendent,NuclearTrainingweretransitionedtotheSuperintenden t Trainingposition,andtheSuperintendentNuclearTrainingpostionwaseliminated.

13.4 4.413.4.1Nochange 4.4.1 13.4.1.1 Nochange 4.4.1.1 13.4.1.2 Nochange 4.4.1.2 13.4.1.3 Nochange 4.4.1.313.4.1.4Nochange 4.4.1.413.4.1.5Nochange 4.4.1.5 13.4.1.6 Nochange 4.4.1.613.4.1.7Nochange 4.4.1.7 13.4.2 Nochange 4.4.213.4.2.1Nochange 4.4.2.113.4.2.2Nochange 4.4.2.2 13.4.2.3 Modifiedsection13.4.2.3,RadioactiveMaterialsSafetyProgram,RequiredMaterialstoreflectplantconditionsfollowingcertificationofpermanentdefueling, 4.4.2.3 13.5 13.5.1 DeleteSection13.5.1,StartupandPowerTestProgram,GeneralObjectives.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgramGeneralObjectivessectionisnolongerapplicable.

13.5.2 DeleteSection13.5.2StartupandPowerTestProgram,InitialFuelLoadingandTestsatAtmosphericPressure.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram,InitialFuelLoadingandTestsatAtmosphericPressuresectionisnolongerapplicable.

13.5.3 DeleteSection13.5.3,StartupandPowerTestProgram,InitialCoreHeatupfromAmbienttoRatedTemperatureandPressure.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram,InitialCoreHeatupfromAmbienttoRatedTemperatureandPressuresectionisnolongerapplicable.

13.5.4 DeleteSection13.5.4,StartupandPowerTestProgram,InitialCoreTestsFromRatedTemperatureto100%Power.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram,InitialCoreTestsFromRatedTemperatureto100%Powersectionisnolongerapplicable.

Responsibility Craft,Technician,andTechnicalStaffTraining TrainingRecords TrainingProgramApprovalandEvaluation Responsibility Superintendent,OperationsTraining Superintendent,NuclearTraining RadiationProtection PlantCertificationProgram TrainingRecords TrainingProgramApprovalandEvaluation Craft,Technician,andTechnicalStaffTraining Superintendent,Training RadiationProtection HealthPhysicsInstrumentation BioassayProgram RadioactiveMaterialsSafetyProgram ChangeAreaandShowerFacilities AccessControl LaboratoryFacilities HealthPhysics PersonnelMonitoringSystems PersonnelProtectiveEquipment HealthPhysics RadioactiveMaterialsSafetyProgram PersonnelMonitoringSystems PersonnelProtectiveEquipment ChangeAreaandShowerFacilities AccessControl LaboratoryFacilities HealthPhysicsInstrumentation BioassayProgram STARTUPANDPOWERTESTPROGRAM GeneralObjectives InitialFuelLoadingandTestsatAtmosphericPressure InitialCoreHeatupfromAmbienttoRatedTemperatureandPressure InitialCoreTestsFromRatedTemperatureto100%Power FacilitiesandEquipment PersonnelandProcedures RequiredMaterials FacilitiesandEquipment PersonnelandProcedures RequiredMaterials Page116of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 13.5.5 DeleteSection13.5.5,StartupandPowerTestProgram,ReloadCoreStartupTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram,ReloadCoreStartupTestingsectionisnolongerapplicable.

13.6 NoChanges 5.3 13.7 DeleteSection13.7.TheinformationcontainedinthissectionisredundanttotheinformationcontainedintheVYQAPM.SincetheUFSAR/DSARcommittoimplementationoftheVYQAPM,thereisnoneedtorepeatthatinformationintheUFSAR/DSAR.13.7.1Deletethissection,See13.7above13.7.2Deletethissection,See13.7above13.7.3Deletethissection,See13.7above13.7.4Deletethissection,See13.7above 13.8 5.513.8.1NoChange 5.5.113.8.2NoChange 5.5.213.8.3NoChange 5.5.3 13.9DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.Theinformationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.13.9.1 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.Theinformationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.13.9.2 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.Theinformationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.13.9.3 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.Theinformationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.13.10DiscussionmodifiedtoreflectchangestoTSandtheTRMastheresultofcertificationofpermanentdefueling.

Deletedthewords:TheTRMisincorporatedbyreferenceintotheDSAR,ismaintainedinaccordancewithVermontYankeeadministrativeprocesses.

SincethereisnoregulatoryrequirementtomaintainaTRMatthesite,ortosubmitTRMchangestotheNRConaperiodicbasis,theTRMisnotrequiredtobeincorporatedbyreferenceintotheDSAR.5.6 14.0 StationSafetyAnalysis 6.0 14.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.1.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.3 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.4.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.SafetyAnalysis TechnicalRequirementsManual General OnSiteSafetyReviewCommittee IndependentSafetyReview REVIEWANDAUDITOFOPERATIONS EMERGENCYPLAN STATIONRECORDS Standards ReloadCoreStartupTesting EMERGENCYPLAN SafetyReviewCommittee REFUELINGOPERATIONS RegularlyScheduledRefuelingOperations Authority RefuelingProcedures REVIEWANDAUDITOFOPERATIONS General OnSiteSafetyReviewCommittee Definitions RetentionTime CompletedRecords APPROACHTOSAFETYANALYSES General AbnormalOperationalTransients Accidents BarrierDamageEvaluations FuelDamage TechnicalRequirementsManual StationSafetyAnalysis OBJECTIVE SAFETYDESIGNLIMITSFORABNORMALOPERATIONALTRANSIENTS SAFETYDESIGNLIMITSFORACCIDENTS Page117of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR14.4.4.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.4.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.4.5Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.1.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.1.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.1.3 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.2.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.2.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.2.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.3 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.3.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.3.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.3.3 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.3.4 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.4 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.4.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.4.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.4.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.4.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.5 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.5.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.5.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.5.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.5.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.6 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.6.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.6.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.7 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.7.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.8 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.NuclearSystemProcessBarrierDamage ContainmentDamage References ANALYSISOFABNORMALOPERATIONALTRANSIENTS EventsResultinginaNuclearSystemPressureIncrease GeneratorTrip(TurbineControlValveFastClosure)TripofOneRecirculationPump TripofTwoRecirculationPumps RecirculationPumpSeizure EventsResultinginaCoreCoolantFlowIncrease RecirculationFlowControllerFailureIncreasingFlow StartupofIdleRecirculationPump LossofAuxiliaryPower EventsResultinginaCoreCoolantFlowDecrease RecirculationFlowControlFailureDecreasingFlow EventsResultinginaPositiveReactivityInsertion ContinuousRodWithdrawalDuringPowerRangeOperation ContinuousRodWithdrawalDuringReactorStartup ControlRodRemovalErrorDuringRefueling FuelAssemblyInsertionErrorDuringRefueling EventsResultinginaReactorVesselCoolantInventoryDecrease TurbineTrip(TurbineStopValveClosure)MainSteamLineIsolationValveClosure EventsResultinginaReactorVesselWaterTemperatureDecrease LossofaFeedwaterHeater ShutdownCooling(RHRS)MalfunctionDecreasingInadvertentPumpStart PressureRegulatorFailure InadvertentOpeningofaSafetyReliefValveorSafetyValve LossofFeedwaterFlow EventResultinginaCoreCoolantTemperatureIncrease LossofRHRServiceWaterFlow EventResultinginExcessofCoolantInventory Page118of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.5.8.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.9 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.9.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.9.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.9.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.9.4 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.9.5 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.5.10Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.2.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.2.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.2.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.2.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.2.5Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.3.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.3.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.3.3 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.3.4 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.3.5Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.4.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.4.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.4.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.4.4 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.4.5Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.5Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.5.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.5.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.5.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.6.6Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.EvaluationAchievementofHotShutdownCondition EvaluationAchievementoftheColdShutdownCondition References 14.6 ANALYSISOFDESIGNBASISACCIDENTS FeedwaterControllerFailureMaximumDemand LossofHabitabilityoftheMainControlRoom CriteriaforLossofHabitabilityoftheControlRoom Conditions Assumptions RadiologicalConsequences RefuelingAccident IdentificationofCauses Methods,Assumptions,andConditions ResultsandConsequences FissionProductReleasetoEnvirons ResultsandConsequences LossofCoolantAccident(LOCA)PeakContainmentPressure(Reference52)Long TermPrimaryContainmentResponse Over PressureRequiredforCSandRHRPumpNPSH MetalWaterReactionEffectsonthePrimaryContainment Introduction ControlRodDropAccident IdentificationofCauses StartingConditionsandAssumptions AccidentDescription MethodofAnalysis RadiologicalEffects MainSteamLineBreakAccident NuclearSystemTransientEffects Deleted RadiologicalEffects References Page119of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.7 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8.2Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8.5 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.8.6Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.1Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.4Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.5 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.6 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.1.7Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.2 Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.9.3Deleted,SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.14.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.1 14.2 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.2 14.2.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.2.1 14.2.2 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.2.2 14.3 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3 14.3.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1 14.3.1.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.1 14.3.1.2 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.2 Introduction AcceptanceCriteria DBAAcceptanceCriteria SiteEventAcceptanceCriteria AccidentsEvaluated FuelHandlingAccident AnalyticalMethodology AssemblyDropinSFPwithOpenContainmentScenario AnalyticalMethodsforEvaluatingRadiologicalEffects References RADIOLOGICALCONSEQUENCESFORNONDESIGNBASISACCIDENTSWITHATID-14844SOURCETERMEvaluationofStationSystemsUsingTID14844SourceTerm SourceTermAssumptions StandbyGasTreatmentSystem CONCLUSIONS ANALYTICALMETHODS NuclearExcursionAnalysis ReactorVesselDepressurizationAnalysis ReactorHeatupAnalysis ContainmentResponseAnalysis References ECCSComponents ElectricalPenetrations ControlRoomHabitabilityPerformedinResponsetoNUREG 0737 MaterialsWithintheContainment Conclusion RadiologicalConsequencesofAccidentswithaTID 1488SourceTerm Introduction AcceptanceCriteria DBAAcceptanceCriteria SiteEventAcceptanceCriteria AccidentsEvaluated FuelHandlingAccident AnalyticalMethodology AssemblyDropinSFPwithOpenContainmentScenario Page120of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.3.1.3 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.3 14.3.1.4 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.4 14.3.1.5 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.5 14.3.1.6 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.6 14.3.1.7 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.7 14.3.1.8 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.8 14.3.1.9 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.3.1.9 14.4 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.4 14.4.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.4.1 14.4.1.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.4.1.1 14.4.1.2 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.4.1.2 14.4.1.3 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.4.1.3 14.4.1.4 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

6.4.1.4 14.5 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichareapplicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.Reference9changedfromNUMARC93 01toNUMARC91 06,GuidelinesforIndustryActionstoAssessShutdownManagement,intheReferencesSection.91 06isthecorrectreferenceandagreeswiththetextbody.6.5 14.6 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Section6.6-AppendixA,Methodology-Step2,deletedthesentence: "Giventhecomplexitiesofthefuelbundlesystemanditsresponseimpactevent,itisnotpossibletojudgethelevelofconservatisminthissetofassumptions,however,thehighlevelsofconservatisminotherareasofthiscalculationshouldmorethatmakeupforanynon conservatismintroducedhere." Thisstatementisanengineeringjudgementestimationofconservatismwhichisnotquantifiable.Thestatementisnotrequiredsinceadequateconservatismalreadyexistsinthecalculation.Therefore,sincethestatementisnotquantifiabeandisnotrequired,ishasbeendeleted.6.6 Table14.3.1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.1 AssemblyDropinSFPwithClosedContainmentScenario Software Assumptions

Inputs ImpactofWaterDepthonIodineDecontaminationFactor FuelDamagefromAssemblyDropontoSFPFuelRacks RadiologicalConsequences/Results SiteEventsEvaluated HighIntegrityContainer(HIC)DropE v AnalyticalMethodology Assumptions

Inputs RadiologicalConsequences/Results References Appendices AnalyticalMethodology Assumptions

Inputs RadiologicalConsequences/Results FHAScenariosAnalyzed References Appendices FHAScenariosAnalyzed AssemblyDropinSFPwithClosedContainmentScenario Software Assumptions

Inputs ImpactofWaterDepthonIodineDecontaminationFactor FuelDamagefromAssemblyDropontoSFPFuelRacks RadiologicalConsequences/Results SiteEventsEvaluated HighIntegrityContainer(HIC)DropEvent Page121of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table14.3.2 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.2 Table14.3.3 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.3 Table14.3.4 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.4 Table14.3.5 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.5 Table14.3.6 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.6 Table14.3.7 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Table6.3.7 Figure14.3 1 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Figure6.3 1 Figure14.3 2 SeeFCR27 006andFCR27 020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichar e applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahighintegrityradioactivematerialcontainer.

Figure6.3 2 15.0 AgingManagementProgram 7.0 15.1 Modifysection15.1,SupplementforRenewedOperatingLicense,todeletereferencetotheevaluationoftime limitedaginganalysesfortheperiodofexendedoperation.

OnJanuary12,2015,EntergyNuclearOperations(ENO)certifiedtotheNuclearRegulatoryCommission(NRC)thatadeterminationtopermanentlyceaseoperationattheVermontYankeeNuclearPowerStation(VYNPS)wasmadeonDecember29,2014whichwasthedateonwhichoperationceasedatVYNPS.ENOalsocertifiedthatthefuelhasbeenpermanentlyremovedfromtheVYNPSreactorvesselandplacedinthespentfuelpool.ENOacknowledgedthat,followingdocketing,theVYNPSlicensenolongerauthorizedoperationofthereactororemplacementorretentionoffuelintothereactorvessel.Consequently,theperiodofextendedoperationhasceasedandtheevaluationoftime limitedaginganalysisisnolongerrequired.7.1 15.2 OnJanuary12,2015,EntergyNuclearOperations(ENO)certifiedtotheNuclearRegulatoryCommission(NRC)thatadeterminationtopermanentlyceaseoperationattheVermontYankeeNuclearPowerStation(VYNPS)wasmadeonDecember29,2014whichwasthedateonwhichoperationceasedatVYNPS.ENOalsocertifiedthatthefuelhasbeenpermanentlyremovedfromtheVYNPSreactorvesselandplacedinthespentfuelpool.ENOacknowledgedthat,followingdocketing,theVYNPSlicensenolongerauthorizedoperationofthereactororemplacementorretentionoffuelintothereactorvessel.Cosequently,thefollowingchangesweremadetoSection15.2oftheVYNPSUFSAR:1)EliminatediscussionsofLicenseRenewalagingmanagementprograms,analyses,andcommitmentsthatarenolongerrequiredtobemaintainedtosupportthecurrentconditionoftheplant;2)Modifythescopesofprogramsandcommitmentstoreflectthepermanentlyshutdownanddefueledcondition;and3)MakeadministrativechangesincludingtherenumberingandrestructuringoftheChapteranditssubsections.RefertoFCR27 014.SpecificchangestoSection15.2,AgingManagementProgramsandActivitiesinclude:change"periodofextendedoperation"to"periodofwetfuelstorage",since,asdescribedinchangesummaryforsection15.1,theperiodofextendedoperationceasedfollowingcessationofoperations.Change"EntergyQualityAssuranceProgram"to"QualityAssuranceProgram"perFCR27 13 7.215.2.1NoChanges 7.2.1 15.2.2 DeleteSection15.2.2,BWRCRDReturnLineNozzleProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.3 DeleteSection15.2.3,BWRFeedwaterNozzleProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.4 DeleeteSection15.2.4,BWRPenetrationsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.5 DeleteSection15.2.5,BWRStressCorrosionCrackingProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.EABTEDEDosevsLongDecayTime VYFHA-EABTEDEDosevsDecayTime VYFHA-MCRTEDEDosevsDecayTime SupplementforRenewedOperatingLicense AGINGMANAGEMENTPROGRAMSANDACTIVITIES BuriedPipingInspectionProgram AgingManagementProgram BWRPenetrationsProgram BWRStressCorrosionCrackingProgram SUPPLEMENTFORRENEWEDOPERATINGLICENSE AGINGMANAGEMENTPROGRAMSANDACTIVITIES BuriedPipingInspectionProgram BWRCRDReturnLineNozzleProgram BWRFeedwaterNozzleProgram InputConditionsforFHA UndecayedCoreInventoryforRadionuclidesImportantintheRadiologicalEvaluationofDBAs UndecayedGapActivityAvailableforReleasefromFuelAssemblyDropintheSFP TypicalIodineDecontaminationFactorsandIodineSpeciationvsWaterDepthaboveDroppedAssembly AtmosphericDispersionFactorsforthePostulatedFHA InputConditionsforFHA UndecayedCoreInventoryforRadionuclidesImportantintheRadiologicalEvaluationofDBAs UndecayedGapActivityAvailableforReleasefromFuelAssemblyDropintheSFP TypicalIodineDecontaminationFactorsandIodineSpeciationvsWaterDepthaboveDroppedAssembly AtmosphericDispersionFactorsforthePostulatedFHA EABTEDEDosevsLongDecayTime VYFHA-EABTEDEDosevsDecayTime VYFHA-MCRTEDEDosevsDecayTime Page122of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 15.2.6 DeleteSection15.2.6,BRWVesselIDAttachmentWeldsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.7 DeleteSection15.2.7,BWRVesselInternalsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.8 DeleteSection15.2.8,ContainmentLeakRateProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.9NoChanges 7.2.2 15.2.10 DeleteSection15.2.10,EnvironmentalQualification(EQ)ofElectricComponentsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2Summaryo ChangesandFCR27 010.15.2.11DeleteSection15.2.11,FatigueMonitoringProgram15.2.12NoChanges 7.2.315.2.13NoChanges 7.2.4 15.2.14 DeleteSection15.2.14,Flow AcceleratedCorrosiongProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.15 DeleteSection15.2.15,HeatExchangerMonitoringProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.16 DeleteSection15.2.16,InserviceInspectionContainmentInserviceInspection(CII)Program,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2 SummaryofChanges.15.2.17 DeleteSection15.2.17,InserviceInspection-InserviceInspection(ISI)Program,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.18NoChanges 7.2.5 15.2.19 ModifySection15.2.19,Non EQInaccessibleMedium VoltageCableProgram,toremoverequirementrelatedtofirsttestbeingperformedpriortotheperiodofextendedoperationwiththeexceptionofthe4.16kVcablesbetweentheUATsandBus1and2.7.2.6 15.2.20 DeleteSection15.2.20,Non EQInstrumentationCircuitsTestReviewProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.21 DeleteSection15.2.21,Non EQInsulatedCablesandConnectionsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.22ModifySection15.2.22,OilAnalysisProgram,tochangetheword"plant"to"facility".

7.2.7 15.2.23 DeleteSection15.2.23,One timeInspectionProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.24 ModifySection15.2.24,PeriodicSurveillanceandPreventiveMaintenanceProgram,tochangetheword"plant"to"facility".removetheHPCIglandsealexhausterfanhousingandpiping,hydrogenanalyzerpre cooler,housingsintheRHRcornerroom,EECS(stet)cornerroomrecirculationunitsandcirculatingwaterfromtheinspectionlist.7.2.8 15.2.25 DeleteSection15.2.25,ReactorHeadClosureStudsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.26 DeleteSection15.2.26,ReactorVesselSurveillanceProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.27 DeleteSection15.2.27,SelectiveLeachingProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.28 ModifySection15.2.28,ServiceWaterIntegrityProgram,to:deletereferencetoGL89 13change"periodofextendedoperation"to"periodofwetfuelstorage",since,asdescribedinchangesummaryforsection15.1,theperiodofextendedoperationceasedfollowingcessationo operations.Inserttheword"opportunistic"todescribecomponentinspectionsInsertthewords"andnon safetyrelated"tofurtherdescribetheheatexchangerstobeinspectedasapartofthisprogram 7.2.9 15.2.29 ModifySection15.2.29,StructuresMonitoring-MasonryWallProgram,to:change"periodofextendedoperation"to"periodofwetfuelstorage",since,asdescribedinchangesummaryforsection15.1,theperiodofextendedoperationceasedfollowingcessationo operations.

7.2.10 15.2.30 NoChanges 7.2.11 15.2.31 DeleteSection15.2.31,StructuresMonitoring-VernonDamFERCProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.ServiceWaterIntegrityProgram StructuresMonitoring-MasonryWallProgram StructuresMonitoring-StructuresMonitoringProgram DieselFuelMonitoringProgram FireProtectionProgram FireWaterSystemProgram InstrumentAirQualityProgram Non EQInaccessibleMedium VoltageCableProgram OilAnalysisProgram PeriodicSurveillanceandPreventiveMaintenanceProgram BRWVesselIDAttachmentWeldsProgram BWRVesselInternalsProgram ContainmentLeakRateProgram DieselFuelMonitoringProgram InserviceInspectionContainmentInserviceInspection(CII)Program StructuresMonitoring-VernonDamFERCProgram OilAnalysisProgram One TimeInspectionProgram PeriodicSurveillanceandPreventiveMaintenanceProgram ReactorHeadClosureStudsProgram ReactorVesselSurveillanceProgram SelectiveLeachingProgram InserviceInspection-InserviceInspection(ISI)Program InstrumentAirQualityProgram Non EQInaccessibleMedium VoltageCableProgram Non EQInstrumentationCircuitsTestReviewProgram Non EQInsulatedCablesandConnectionsProgram EnvironmentalQualification(EQ)ofElectricComponentsProgram FatigueMonitoringProgram FireProtectionProgram FireWaterSystemProgram Flow AcceleratedCorrosionProgram HeatExchangerMonitoringProgram ServiceWaterIntegrityProgram StructuresMonitoring-MasonryWallProgram StructuresMonitoring-StructuresMonitoringProgram Page123of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 15.2.32 ModifySection15.2.32,SystemWalkdownProgram,to:change"periodofextendedoperation"to"periodofwetfuelstorage",since,asdescribedinchangesummaryforsection15.1,theperiodofextendedoperationceasedfollowingcessationo operations.

7.2.12 15.2.33 DeleteSection15.2.33,ThermalAgingandNeutronIrradiationEmbrittlementofCastAusteniticStainlessSteel(CASS)Program,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.15.2.34 ModifySection15.2.34,WaterChemistryControl-AuxiliarySystemsProgram,to:deletereferencetotheStatorCoolingWaterSystemchangetheword"plant"to"facility".deletereferencetotheOne TimeInspectionProgram,sincethatprogramhasbeendeleted.7.2.13 15.2.35 ModifySection15.2.35,WaterChemistryControl-BWRProgram,to:deletereferencetotheEPRIReport1008192BWRVIP 130insertreferencetoBWRWaterChemistryGuidlines,2008Revision,BWRVIP 190deletereferencetoprimarywaterchemistryandhydrogenwaterchemistrydeletereferencetotheOne TimeInspectionProgram,sincethatprogramhasbeendeleted.7.2.14 15.2.36 ModifySection15.2.36,WaterChemistryControl-ClosedCoolingProgram,to:deletereferencetotheTBCCWsystem,AOGClosedCoolingWatersystem,andAOGRefrigerantskidwatersystem.deletereferencetotheOne TimeInspectionProgram,sincethatprogramhasbeendeleted.7.2.1515.2.37NoChanges 7.2.1615.2.38NoChanges 7.2.1715.2.39NoChanges 7.2.1815.2.40NoChanges 7.2.19 15.2.41 DeleteSection15.2.41,ProtectiveCoatingMonitoringandMaintenanceProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2Summaryo f Changes.15.3 Deletesection15.3,EvaluationofTimel LimitedAgingAnalyses.OnJanuary12,2015,EntergyNuclearOperations(ENO)certifiedtotheNuclearRegulatoryCommission(NRC)thatadeterminationtopermanentlyceaseoperationattheVermontYankeeNuclearPowerStation(VYNPS)wasmadeonDecember29,2014whichwasthedateonwhichoperationceasedatVYNPS.ENOalsocertifiedthatthefuelhasbeenpermanentlyremovedfromtheVYNPSreactorvesselandplacedinthespentfuelpool.ENOacknowledgedthat,followingdocketing,theVYNPSlicensenolongerauthorizedoperationofthereactororemplacementorretentionoffuelintothereactorvessel.Consequently,theperiodofextendedoperationhasceasedandtheevaluationoftime limitedaginganalysisisnolongerrequired.15.3.1 Deletesection15.3.1,ReactorVesselNeutronEmbrittlement,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.1.1 Deletesection15.3.1.1,ReactorVesselFluence,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.1.2 Deletesection15.3.1.2,Pressure TemperatureLimits,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.1.3 Deletesection15.3.1.3,CharpyUpper ShelfEnergy,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.1.4 Deletesection15.3.1.4,AdjustedReferenceTemperature,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.1.5 Deletesection15.3.1.5,ReactorVesselCircumferentialWeldInspectionRelief,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.1.6 Deletesection15.3.1.6,ReactorVesselAxialWeldFailureProbability15.3.2Deletesection15.3.2,MetalFatigue,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.2.1 Deletesection15.3.2.1,Class1MetalFatigue,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.2.2 Deletesection15.3.2.2,Non Class1MetalFatigue,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.2.3 Deletesection15.3.2.3,EnvironmentalEffectsonFatigue,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.3 Deletesection15.3.3,EnvironmentalQualificationofElectricalComponents,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.4 Deletesection15.3.4,FatigueofPrimaryContainment,AttachedPiping,andComponents,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3 SummaryofChanges.BoltedCableConnectionsProgram NeutronAbsorberMonitoringProgram WaterChemistryControl-AuxiliarySystemsProgram WaterChemistryControl-BWRProgram WaterChemistryControl-ClosedCoolingProgram BoltingIntegrityProgram MetalEnclosedBusInspectionProgram SystemWalkdownProgram Non Class1MetalFatigue EnvironmentalEffectsonFatigue EnvironmentalQualificationofElectricalComponents FatigueofPrimaryContainment,AttachedPiping,andComponents CharpyUpper ShelfEnergy AdjustedReferenceTemperature ReactorVesselCircumferentialWeldInspectionRelief ReactorVesselAxialWeldFailureProbability MetalFatigue Class1MetalFatigue SystemWalkdownProgram ThermalAgingandNeutronIrradiationEmbrittlementofCastAusteniticStainlessSteel(CASS)Program WaterChemistryControl-AuxiliarySystemsProgram WaterChemistryControl-BWRProgram NeutronAbsorberMonitoringProgram ProtectiveCoatingMonitoringandMaintenanceProgram EVALUATIONOFTIME LIMITEDAGINGANALYSES ReactorVesselNeutronEmbrittlement ReactorVesselFluence Pressure TemperatureLimits WaterChemistryControl-ClosedCoolingProgram BoltingIntegrityProgram MetalEnclosedBusInspectionProgram BoltedCableConnectionsProgram Page124of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 15.3.5 Deletesection15.3.5,CorePlateRimHold DownBoltLossofPreload,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.15.3.6 Deletesection15.3.6,LowerPlenumFatigueAnalysis 15.4 ModifySection15.4,Referenes,toremovethosereferencesnolongercitedinthebodyofthetext.15.3 1 NoChanges 1 2 CommitmentEliminatedbyFCR27/014 3 NoChanges 3 4 NoChanges 4 5 CommitmentEliminatedbyFCR27/0147CommitmentEliminatedbyFCR27/014 8 NoChanges 8 9 NoChanges 9 10 NoChanges 10 11 NoChanges 1112CommitmentEliminatedbyFCR27/014 13 NoChanges 1314CommitmentEliminatedbyFCR27/01415CommitmentEliminatedbyFCR27/014 EnhanceTheDieselFuelMonitoringProgramUTTankbottomevery10yrs EnhanceFireWaterSystemProgamProcedurestospecifythatarepresentativesampleofsprinklerswhichhavebeeninservicefor50yearswillbetested.LISTOFLICENSERENEWALCOMMITMENTSGuidanceforperformingexaminationsofburiedpipingCommitmentEliminatedbyFCR27/01416ImplementtheOne TimeInspectionProgramTheOne TimeInspectionProgramwasperformed;thus,thecommitmentwasmetandclosedbyFCR27/014.GuidanceforperformingexaminationsofburiedpipingInspectFifteen(15)percentofthetopguidelocationsEnhanceTheDieselFuelMonitoringProgramUTTankbottomevery10yrs EnhanceTheDieselFuelMonitoringProgrammodifytankbottomacceptancecriteria ModifyFatigueMonitoringProgram Establishallowablenumberofeffectivetransients Enhanceprocedurestospecifythatfiredamperframesinfirebarrierswillbeinspectedforcorrosion Enhanceprocedurestostatethatthedieselenginesub systems(includingthefuelsupplyline)willbeobservedwhilethepumpisrunning EnhanceFireWaterSystemProgamProcedurestospecifythatarepresentativesampleofsprinklerswhichhavebeeninservicefor50yearswillbetested.EnhancetheFireWaterSystemProgramtospecifythatwallthicknessevaluationsoffireprotectionpipingwillbeperformedonsystemcomponentsusingnon intrusivetechniquestoidentifyevidenceoflossofmaterialduetocorrosion.

ImplementHeatExchangerMonitoringProgram ImplementtheNon EQInaccessibleMedium VoltageCableProgramImplementtheNon EQInstrumentationCircuitsTestReviewProgram ImplementtheNon EQInsulatedCablesandConnectionsProgramLISTOFLICENSERENEWALCOMMITMENTSUsemanualcyclecountingtotrackandcompareaccumulatedcycles Enhanceprocedurestostatethatthedieselenginesub systems(includingthefuelsupplyline)willbeobservedwhilethepumpisrunning Enhanceprocedurestospecifythatfiredamperframesinfirebarrierswillbeinspectedforcorrosion EnhanceTheDieselFuelMonitoringProgrammodifytankbottomacceptancecriteria EnhancetheFireWaterSystemProgramtospecifythatwallthicknessevaluationsoffireprotectionpipingwillbeperformedonsystemcomponentsusingnon intrusivetechniquestoidentifyevidenceoflossofmaterialduetocorrosion.

ImplementtheNon EQInaccessibleMedium VoltageCableProgram15.5 Textmodifiedtoadd"commitmentsremainingapplicablefollowingpermanentcessationofoperationsandcertificationofpermanentdefueling.ModifySection15.4,References,toremovethosereferencesnolongercitedinthebodyofthetext.15.4 CorePlateRimHold DownBoltLossofPreload LowerPlenumFatigueAnalysis REFERENCESREFERENCES6 Page125of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 17 NoChanges 1718CommitmentEliminatedbyFCR27/01420NoChanges 2021CommitmentEliminatedbyFCR27/01422NoChanges 2223CommitmentEliminatedbyFCR27/01424NoChanges 2425CommitmentEliminatedbyFCR27/01426NoChanges 26 EnhancethePeriodicSurveillanceandPreventiveMaintenanceProgramtoassurethattheeffectsofagingwillbemanaged EnhancetheStructuresMonitoringProgramtospecifythatprocessfacilitycranerailsandgirders,condensatestoragetank(CST)enclosure,CO2tankenclosure,nitrogentankenclosureandrestrainingwall,CSTpipetrench,dieselgeneratorcabletrench,fueloilpumphouse,servicewaterpipetrench,man waysealsandgaskets,andhatchsealsandgasketsareincludedintheprogram.EnhanceGuidanceforperformingstructuralexaminationsofelastomerstoidentifycrackingandchangeinmaterialpropertiesintheStructuresMonitoringProgramprocedure Systemwalkdownguidancedocumentswillbeenhancedtoperformperiodicsystemengineerinspectionsofsystemsinscopeandsubjecttoagingmanagementreview.ProcedureswillbeenhancedtoflushtheJohnDeereDieselGeneratorcoolingwatersystemandreplacethecoolantandcoolantconditionereverythreeyears.TheSelectiveLeachingProgramwasperformed;thus,thecommitmentwasmetandclosedbyFCR27/014.EnhancetheStructuresMonitoringProgramtospecifythatprocessfacilitycranerailsandgirders,condensatestoragetank(CST)enclosure,CO2tankenclosure,nitrogentankenclosureandrestrainingwall,CSTpipetrench,dieselgeneratorcabletrench,fueloilpumphouse,servicewaterpipetrench,man waysealsandgaskets,andhatchsealsandgasketsareincludedintheprogram.Addguidanceforperformingstructuralexaminationsofwoodtoidentifylossofmaterial,cracking,andchangeinmaterialpropertiestotheStructuresMonitoringProgram.EnhanceGuidanceforperformingstructuralexaminationsofelastomerstoidentifycrackingandchangeinmaterialpropertiesintheStructuresMonitoringProgramprocedure AddGuidanceforperformingstructuralexaminationsofPVCcoolingtowerfilltoidentifycrackingandchangeinmaterialpropertiestotheStructuresMonitoringProgramprocedure.Systemwalkdownguidancedocumentswillbeenhancedtoperformperiodicsystemengineerinspectionsofsystemsinscopeandsubjecttoagingmanagementreview.ImplementtheThermalAgingandNeutronIrradiationEmbrittlementofCastAusteniticStainlessSteel(CASS)Program ProcedureswillbeenhancedtoflushtheJohnDeereDieselGeneratorcoolingwatersystemandreplacethecoolantandcoolantconditionerever y threeyears.19ImplementtheSelectiveLeachingProgramEnhancethePeriodicSurveillanceandPreventiveMaintenanceProgramtoassurethattheeffectsofagingwillbemanaged EnhancetheReactorVesselSurveillanceProgramtoproceduralizethedataanalysis,acceptancecriteria,andcorrectiveactionsdescribedintheprogramdescriptionPage126of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR27CommitmentEliminatedbyFCR27/01428NoChanges 28 29 Theplant specificanalysistodeterminetheacceptancecriteriaforthecontinuedinspectionofcoreplateholddownboltingwasperformed.Thus,thecommitmentwasmetandclosedbyFCR27/014.30NoChanges 3031NoChanges 3132NoChanges 3233NoChanges 3334NoChanges 3435NoChanges 3536CommitmentEliminatedbyFCR27/01437CommitmentSuperseded.PlaceholderdeletedbyFCR27/014.ReviseprogramprocedurestoindicatethattheInstrumentAirProgramwillmaintaininstrumentairqualityinaccordancewithISAS7.3 ReviseSystemWalkdownProgramtospecifyCO2systeminspectionsevery6months.ReviseFireWaterSystemProgramtospecifyannualfirehydrantgasketinspectionsandflowtests.ImplementtheMetalEnclosedBusProgram IncludewithintheStructuresMonitoringProgramprovisionsthatwillensureanengineeringevaluationismadeonaperiodicbasis(atleastonceeveryfiveyears)ofgroundwatersamplestoassessaggressivenessofgroundwatertoconcrete.ImplementtheBoltingIntegrityProgram.ProvidewithintheSystemWalkdownTrainingProgramaprocesstodocumentbiennialrefreshertrainingofEngineerstodemonstrateinclusionofthemethodologyforagingmanagementofplantequipmentAtleast2yearspriortoenteringtheperiodofextendedoperation,forthelocationsidentifiedinNUREG/CR 6260forBWRsoftheVYvintage,VYwillrefineourcurrentfatigueanalysestoincludetheeffectsofreactorwaterenvironmentandverifythatthecumulativeusagefactors(CUFs)arelessthan1.ReviseprogramprocedurestoindicatethattheInstrumentAirProgramwillmaintaininstrumentairqualityinaccordancewithISAS7.3 VYNPSwillperformoneofthefollowing:

1.Installcoreplatewedges,or, 2.Completeaplant specificanalysistodetermineacceptancecriteriaforcontinuedinspectionofcoreplateholddownbolting ImplementtheBoltingIntegrityProgram.ProvidewithintheSystemWalkdownTrainingProgramaprocesstodocumentbiennialrefreshertrainingofEngineerstodemonstrateinclusionofthemethodologyforagingmanagementofplantequipmentIftechnologytoinspectthehiddenjetpumpthermalsleeveandcorespraythermalsleeveweldshasnotbeendevelopedandapprovedbytheNRCatleasttwoyearspriortotheperiodofextendedoperation,VYNPSwillinitiateplant specificaction toresolvethisissue.ThisCommitmentsupersededbysteamdryerlicensecondition3.S.ReviseSystemWalkdownProgramtospecifyCO2systeminspectionsevery6months.ReviseFireWaterSystemProgramtospecifyannualfirehydrantgasketinspectionsandflowtests.ImplementtheMetalEnclosedBusProgram IncludewithintheStructuresMonitoringProgramprovisionsthatwillensureanengineeringevaluationismadeonaperiodicbasis(atleastonceeveryfiveyears)ofgroundwatersamplestoassessaggressivenessofgroundwatertoconcrete.Page127of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR38CommitmentEliminatedbyFCR27/01439CommitmentEliminatedbyFCR27/01440CommitmentDeleted.PlaceholderdeletedbyFCR27/014.41CommitmentDeleted.PlaceholderdeletedbyFCR27/014.42NoChanges 4243CommitmentEliminatedbyFCR26/01144CommitmentSuperseded.PlaceholderdeletedbyFCR27/014.45CommitmentEliminatedbyFCR27/01446NoChanges 4647NoChanges 4748TheinternalinspectionoftheundergroundServiceWaterpipingwasperformed;thus,thecommitmentwasmetandclosed.PlaceholdereliminatedbyFCR27/014.49NoChanges 49 ImplementtheBoltedCableConnectionsProgram.EnhancetheDieselFuelMonitoringProgramtospecifythatfueloilinthefirepumpdieselstorage(day)tankandtheJohnDeeredieselstoragetankwillbeanalyzedaccordingtoASTMD975andforparticulatesperASTMD2276.EnhancetheDieselFuelMonitoringProgramtospecifythatfueloilinthecommonportablefueloilstoragetankwillbeanalyzedaccordingtoASTMD975,perASTMD2276forparticulates,andperASTMD2709forwaterandsediment.Revisestationprocedurestospecifyfirehydranthosetesting,inspection,andreplacement,ifnecessary,inaccordancewithNFPAcodespecificationsforfirehydranthoses ThisCommitmenthasbeendeletedandreplacedwithCommitment43.ImplementtheBoltedCableConnectionsProgram.Establishandimplementaprogramthatwillrequiretestingofthetwo13.8kVcablesfromthetwoVernonHydroStation13.8kVswitchgearbusestothe13.8kV/69kVstepuptransformers ThisCommitmenthasbeendeletedandreplacedwithCommitment54.EnhancetheServiceWaterIntegrityProgramtorequireaperiodicvisualinspectionoftheRHRSWpumpmotorcoolingcoilinternalsurfaceforlossofmaterial.EnhancetheDieselFuelMonitoringProgramtospecifythatfueloilinthefirepumpdieselstorage(day)tankandtheJohnDeeredieselstoragetankwillbeanalyzedaccordingtoASTMD975andforparticulatesperASTMD2276.EnhancetheDieselFuelMonitoringProgramtospecifythatfueloilinthecommonportablefueloilstoragetankwillbeanalyzedaccordingtoASTMD975,perASTMD2276forparticulates,andperASTMD2709forwaterandsediment.PerformaninternalinspectionoftheundergroundServiceWaterpipingbeforeenteringtheperiodofextendedoperation.

Revisestationprocedurestospecifyfirehydranthosetesting,inspection,andreplacement,ifnecessary,inaccordancewithNFPAcodespecificationsforfirehydranthoses TheBWRVIP 116reportwhichwasapprovedbytheStaffwillbeimplementedatVYNPSwiththeconditionsdocumentedinSections3and4oftheStaff'sfinalSEdatedMarch1,2006,fortheBWRVIP 116report.IftheVYNPSstandbycapsuleisremovedformthereactorvesselwithouttheintenttotestit,thecapsulewillbestoredinamannerwhichmaintainsitinaconditionwhichwouldpermititsfutureuse,includingduringtheperiodofextendedoperation,ifnecessary.ThisCommitmenthasbeendeletedandreplacedwithCommitment43.Page128of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR50CommitmentEliminatedbyFCR27/01451Theevaluationofoperatingexperienceatextendedpowerupratelevelswasperformed;thus,thecommitmentwasmetandclosed.PlaceholdereliminatedbyFCR27/014.52NoChanges 5253CommitmentEliminatedbyFCR27/01454NoChanges 5455CommitmentEliminatedbyFCR27/014 A A.1 Editorialchanges.Deletionstoremoveexcessdetail.A.1A.2NoChanges.ThisisanindependentreportbyH.J.SextonEngineering A.2 A.3 Editorialchangesonly.TurbineBuildinganalysisshouldremainatleastwhiletheDieselGeneratorsarerelieduponasastandbypowersource.A.3 FigureA.31NoChanges FigureA.3 1 FigureA.32NoChanges FigureA.3 2 A.4 NoChanges A.4 FigureA.4 1 NoChanges FigureA.4 1 FigureA.4 2 NoChanges FigureA.4 2 FigureA.4 3 NoChanges FigureA.4 3 SummaryDescription SPECIFICDESIGNANALYSISFORTHEDRYWELL,SUPPRESSIONCHAMBERANDREACTORBUILDING TurbineBuilding PlantStack Appendices TurbineBuildingBent TurbineBuildingBent TurbineBuildingBent TurbineBuildingBent VentilationStackMathematicalModel VentilationStackMaximumShear VentilationStackMaximumMovement VentilationStackMaximumShear VentilationStackMaximumMovement ImplementtheNeutronAbsorberMonitoringProgramPriortothePEO,VYNPSwillinspectportionsofthestandbygastreatmentsystemburiedpiping.DuringthePEO,inspectionsoftwocarbonsteelpipingsegmentsinthestandbygastreatmentsystemandfourcarbonsteel pipingsegmentsintheservicewatersystemwillbeperformedevery10yearsImplementtheNeutronAbsorberMonitoringProgramDuringtheperiodofextendedoperation,VYNPSwillperformperiodicvolumetricexaminationsofsmall boreClass1socketandbuttwelds.PriortothePEO,VYNPSwillinspectportionsofthestandbygastreatmentsystemburiedpiping.DuringthePEO,inspectionsoftwocarbonsteelpipingsegmentsinthestandbygastreatmentsystemandfourcarbonsteel pipingsegmentsintheservicewatersystemwillbeperformedevery10yearsPlantStack SEISMICANALYSES SummaryDescription SPECIFICDESIGNANALYSISFORTHEDRYWELL,SUPPRESSIONCHAMBERANDREACTORBUILDING TurbineBuilding Duringtheperiodofextendedoperation,reviewtheVernonDamownerFERCrequiredreport(s)ataminimumofeveryfiveyearstoconfirmthattheVernonDamownerisperformingtherequiredFERCinspections.Performanevaluationofoperatingexperienceatextendedpoweruprate(EPU)levelspriortotheperiodofextendedoperationtoensurethatoperatingexperienceatEPUlevelsisproperlyaddressedbytheagingmanagementprograms.VentilationStackMathematicalModel Enhancesafety relatedcoatingsprogramsandprocedurestobeconsistentwiththerecommendationsofNUREG 1801,SectionXI.S8,ProtectiveCoatingMonitoringandMaintenanceProgram.Page129of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureA.4 4 NoChanges FigureA.4 4 A.5 Nochanges,thisisanindependentreportbyEBASCOServices A.5 A.6 Nochanges.SeismicanalysisremainswhileportionoftheIntakeStructureremainsCat1.A.6 FigureA.6 1 NoChanges FigureA.6 1 FigureA.6 2 NoChanges FigureA.6 2 FigureA.6 3 NoChanges FigureA.6 3 FigureA.6 4 NoChanges FigureA.6 4 FigureA.6 5 NoChanges FigureA.6 5 FigureA.6 6 NoChanges FigureA.6 6 FigureA.6 7 NoChanges FigureA.6 7 A.7 DeleteAppendixA,SectionA.7AlternateCoolingCellSeismicAnalysis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAlternateCoolingCellarenolongerrequired.TheinformationprovidedintheAlternateCoolingCellSeismicAnalysisisnolongerapplicable,andisconsidereobsolete.A.8 DeleteAppendixA,SectionA.8,VERMONTYANKEENUCLEARPOWERSTATIONADDITIONALINFORMATIONCONCERNINGSEISMICANALYSISOFCLASSIPIPING.Theone timeanalysisdocumentedinA.8hasbeensupersededbyanynumberofanalysesperformedsincethattimeasfurtherdiscussedin,primarily,AppA.9.A.9 A.9 A.9.1 NoChanges A.9.1 A.9.2 ModifySectionA.9.2to:incorporateeditorialchangesDeletesectionA.9.2.8,Method7,sinceitappliedonlytothereactorrecirculationsystem,andthefunctionsprovidedbythatsystemarenotrequiredpostcertificationofpermanentdefueling.

A.9.2 PLANATEL230.00'SECTIONS INTAKESTRUCTURESERVICEWATERBAYAREAMATHEMATICALMODELS(N S)INTAKESTRUCTURESERVICEWATERBAYAREA MAXIMUMACCELERATIONS(N S)EarthquakeAnalysisoftheControlBuilding IntakeStructure Introduction DescriptionofAnalysisMethodology DESCRIPTION,SCOPE,ANDDESIGNMETHODOLOGYUSEDFORTHEREANALYSISOFSEISMICCLASSIPIPINGSUBSEQUENTTOINITIALOPERATION Introduction DescriptionofAnalysisMethodology VentilationStackMaximumDeflectionDiagram IntakeStructure-ServiceWaterBayArea,MaximumMoments(N S)SECTIONS INTAKESTRUCTURESERVICEWATERBAYAREAMATHEMATICALMODELS(N S)INTAKESTRUCTURESERVICEWATERBAYAREA MAXIMUMACCELERATIONS(N S)ServiceWaterBayArea,MaximumDisplacements(N S)IntakeStructure-ServiceWaterBayArea,MaximumShears(N S)IntakeStructure-ServiceWaterBayArea,MaximumMoments(N S)VentilationStackMaximumDeflectionDiagram PLANATEL230.00'ServiceWaterBayArea,MaximumDisplacements(N S)IntakeStructure-ServiceWaterBayArea,MaximumShears(N S)EarthquakeAnalysisoftheControlBuilding IntakeStructure AlternateCoolingCell VERMONTYANKEENUCLEARPOWERSTATIONADDITIONALINFORMATIONCONCERNINGSEISMICANALYSISOFCLASSIPIPING DESCRIPTION,SCOPE,ANDDESIGNMETHODOLOGYUSEDFORTHEREANALYSISOFSEISMICCLASSIPIPINGSUBSEQUENTTOINITIALOPERATION Page130of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR A.9.3 ModifiedSectionA.9.3todeletereferencetothefollowingSSCs,sincethefunctionsprovidedbythoseSSCsarenolongerrequiredfollowingcertificationofpermanentdefueling:RBCCW RHR SBGT Feedwater HPCI RCIC SBLC CS Clean UpWaterDemineralizerSystem MainSteamDrains ContainmentInerting CRD InstrumentairtoAdS,MSIVs SamplingSystem MiscSmallborepiping ContainmentatmosphereControl A.9.3 A.9.4 NoChanges A.9.4 A.9.5 NoChanges A.9.5 A.10 NoChanges A.10 TableA.10.2 1a NoChanges TableA.10.2 1a TableA.10.2 2a NoChanges TableA.10.2 2a TableA.10.2 2b NoChanges TableA.10.2 2b TableA.10.2 2c NoChanges TableA.10.2 2c TableA.10.2 2d NoChanges TableA.10.2 2d TableA.10.2 3a NoChanges TableA.10.2 3a TableA.10.2 3b NoChanges TableA.10.2 3b TableA.10.2 4a NoChanges TableA.10.2 4a TableA.10.2 4b NoChanges TableA.10.2 4b TableA.10.2 4c NoChanges TableA.10.2 4c TableA.10.2 5a NoChanges TableA.10.2 5a TableA.10.2 5b NoChanges TableA.10.2 5b TableA.10.2 5c NoChanges TableA.10.2 5c TableA.10.2 5d NoChanges TableA.10.2 5d TableA.10.2 6a NoChanges TableA.10.2 6a ScopeofSeismicClassIPipingSystemsModifiedandMethodologyUsed DescriptionofFloorAmplifiedResponseSpectraUsedforSeismicReanalysisofPiping SummaryandConclusions ScopeofSeismicClassIPipingSystemsModifiedandMethodologyUsed DescriptionofFloorAmplifiedResponseSpectraUsedforSeismicReanalysisofPiping SummaryandConclusions PRIMARYSTRUCTURESEISMICANALYSIS PRIMARYSTRUCTURESEISMICANALYSIS SummaryofNodalHydrodynamicMassesforHorizontalDirection HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations HorizontalModelBeamElementPropertiesNorthSouthDirection HorizontalModelBeamElementPropertiesNorthSouthDirection HorizontalModelBeamElementPropertiesNorthSouthDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection VerticalModelBeamElementProperties SummaryofNodalHydrodynamicMassesforHorizontalDirection HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations HorizontalModelBeamElementPropertiesNorthSouthDirection HorizontalModelBeamElementPropertiesNorthSouthDirection HorizontalModelBeamElementPropertiesNorthSouthDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection VerticalModelBeamElementProperties Page131of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableA.10.2 6b NoChanges TableA.10.2 6b TableA.10.2 6c NoChanges TableA.10.2 6c TableA.10.2 7a NoChanges TableA.10.2 7a TableA.10.2 8a NoChanges TableA.10.2 8a TableA.10.2 9a NoChanges TableA.10.2 9a TableA.10.2 10a NoChanges TableA.10.2 10a TableA.10.2 11a NoChanges TableA.10.2 11a FigureA.10.2 1 NoChanges FigureA.10.2 1 FigureA.10.2 2 NoChanges FigureA.10.2 2 FigureA.10.2 3 NoChanges FigureA.10.2 3 FigureA.10.2 4 NoChanges FigureA.10.2 4 FigureA.10.2 5 NoChanges FigureA.10.2 5 FigureA.10.3 1 NoChanges FigureA.10.3 1 FigureA.10.3 2 NoChanges FigureA.10.3 2 FigureA.10.3 3 NoChanges FigureA.10.3 3 FigureA.10.3 4 NoChanges FigureA.10.3 4 FigureA.10.3 5 NoChanges FigureA.10.3 5 FigureA.10.3 6 NoChanges FigureA.10.3 6 B B.1 DeleteAppendixB,SectionB.1,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,SummaryDescription.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.1isnolongerapplicableandisconsideredobsolete.B.2 DeleteAppendixB,SectionB.2,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedintheVermontYankeeAEC ACRSConstructionPermitLetters.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.2regardingresolutiono theelevenconcernitemspriortoinitialoperationofthefacilityisnolongerapplicableandisconsideredobsolete.B.3 DeleteAppendixB,SectionB.3,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedintheVermontYankeeAEC ACRSConstructionPermitSafetyEvaluationReport FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.3regardingresolutiono itemsofconcernpriortoinitialoperationofthefacilityisnolongerapplicableandisconsideredobsolete.SpringElementStiffnessesHorizontalModel SpringElementStiffnessesVerticalModel NaturalFrequenciesoftheN SModel NaturalFrequenciesoftheE WModel NaturalFrequenciesoftheVerticalModel ReactorBuildingComplexLongitudinalSection ReactorBuildingComplexSeismicHorizontalModel ReactorBuildingComplexSeismicVerticalModel StabilizerSystem DrywellGeometricFigure AccelerationTimeHistory(0.14G),H1Motion,DT=.01Sec.NPT=2049 A.10.34GESSARIIvs.NRCARS AccelerationTimeHistory.(0.14G),VMotion,DT=.01Sec.NPT=2201 STATIONRESEARCHDEVELOPMENTANDFURTHERINFORMATION,REQUIREMENTSANDRESOLUTIONS

SUMMARY

DESCRIPTION AREASSPECIFIEDINTHEVERMONTYANKEEAEC ACRSCONSTRUCTIONPERMITLETTERS AREASSPECIFIEDINTHEVERMONTYANKEEAECACRSCONSTRUCTIONPERMITSAFETYEVALUATIONREPORT(RefertoTable1.10.3)SpringElementStiffnessesHorizontalModel SpringElementStiffnessesVerticalModel NaturalFrequenciesoftheN SModel NaturalFrequenciesoftheE WModel NaturalFrequenciesoftheVerticalModel ReactorBuildingComplexLongitudinalSection ReactorBuildingComplexSeismicHorizontalModel ReactorBuildingComplexSeismicVerticalModel A.10.34GESSARIIvs.NRCARS AccelerationTimeHistory.(0.14G),VMotion,DT=.01Sec.NPT=2201 VerticalModelBeamElementProperties VerticalModelBeamElementProperties GESSARIIvs.NRCARS GESSARIIvs.NRCARS GESSARIIvs.NRCARS GESSARIIvs.NRCARS GESSARIIvs.NRCARS GESSARIIvs.NRCARS VerticalModelBeamElementProperties VerticalModelBeamElementProperties StabilizerSystem DrywellGeometricFigure AccelerationTimeHistory(0.14G),H1Motion,DT=.01Sec.NPT=2049 Page132of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR B.4 DeleteAppendixB,SectionB.4,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedinOtherRelatedAECACRSConstructionandOperatingPermitLetters.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.4regardingresolutiono itemsofconcernrelatedtooperationofthefacilityisnolongerapplicableandisconsideredobsolete.B.5 DeleteAppendixB,SectionB.5,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedinOtherAECStaffConstructionorOperatingPermitSafetyEvaluationReports.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.5regardingresolutiono itemsofconcernrelatedtooperationofthefacilityisnolongerapplicableandisconsideredobsolete.Additionally,informationregardingTornadoandMissileProtectionrelatedtoGETopicalReport"TornadoProtectionForTheSpentStoragePool,"APED5696,November,1968wasrelocatedtosection10.2,SpentFuelStorage.B.6 DeleteAppendixB,SectionB.6,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,SummaryConclusions.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theconclusionsprovidedinSectionB.6regardingresolutionofitemsofconcernrelatedtooperationofthefacilityisnolongerapplicableandareconsideredobsolete.C DeleteAppendixC,StructuralLoadingCriteria.Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximumhypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.TheinformationinthisappendixisthereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.Therefore,theinformationinAppendixCisaone timesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCswouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.C.1 DeleteAppendixC.1,StructuralLoadingCriteria.Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximumhypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.TheinformationinthisappendixisthereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.Therefore,theinformationinAppendixCisaone timesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCswouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.C.1.1 DeleteAppendixC.1.1,SummaryDescription.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximumhypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.TheinformationinthisappendixisthereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.Therefore,theinformationinAppendixCisaone timesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCswouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.C.2 C.2.1 C.2.2 C.2.3 C.2.4 C.2.5 C.2.6 C.2.7 AREASSPECIFIEDINOTHERRELATEDAECACRSCONSTRUCTIONANDOPERATINGPERMITLETTERS(RefertoTable1.10.4)IntentandScope LoadingConditionsandAllowableLimits GoverningLoadingConditionsandCriteria ReactorPressureVessel ReactorVesselInternals PipingSystems AREASSPECIFIEDINOTHERRELATEDAECSTAFFCONSTRUCTIONOROPERATINGPERMITSAFETYEVALUATIONREPORTS

SUMMARY

CONCLUSIONS STRUCTURALLOADINGCRITERIA StructuralLoadingCriteria SummaryDescription LOADINGCRITERIAFORGENERALELECTRIC(GE)SUPPLIEDCLASSICOMPONENTS Equipment DeleteAppendixC.2,LoadingCriteriaforGeneralElectric(GE)SuppliedClassIComponents.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximumhypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.TheinformationinthisappendixisthereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.Therefore,theinformationinAppendixCisaone timesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCswouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.Page133of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR C.2.8 C.3 DeleteAppendixC.3,LoadingCriteriaforClassIPiping.Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximumhypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.TheinformationinthisappendixisthereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.Therefore,theinformationinAppendixCisaone timesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCswouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.C.4 DeleteAppendixC.4,LoadingCriteriaforEBASCOSuppliedClassIComponents.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximumhypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.TheinformationinthisappendixisthereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.Therefore,theinformationinAppendixCisaone timesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCswouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.D DeleteAppendixD,QAProgram.Section1.9,QualityAssuranceProgram,establishesthecriteriatobeappliedtosystemsrequiringQualityAssurancewhichpreventormitigatetheconsequencesofpostulatedaccidentswhichcouldcauseunduerisktothehealthandsafetyofthepublic.TheQualityAssuranceProgramManual(QAPM)implementstherequirementsof10CFR50AppendixB.AppendixDfunctionedasaplacekeeperandisnolongerrequiredsincetheUFSARisbeingwhollyrewrittentotheDSARtoreflectthepermanentlydefueledstate.D.0 DeleteSectionD.0,QualityAssurance(QA)ProgramDuringtheOperationsPhase.Section1.9,QualityAssuranceProgram,establishesthecriteriatobeappliedtosystemsrequiringQualityAssurancewhichpreventormitigatetheconsequencesofpostulatedaccidentswhichcouldcauseunduerisktothehealthandsafetyofthepublic.TheQualityAssuranceProgramManual(QAPM)implementstherequirementsof10CFR50AppendixB.AppendixDfunctionedasaplacekeeperandisnolongerrequiredsincetheUFSARisbeingwhollyrewrittentotheDSARtoreflectthepermanentlydefueledstate.E DeleteAppendixE,StackReleaseLimitCalculations.AppendixEtotheVermontYankeeFinalSafetyAnalysisReport(FSAR)waspreviouslyeliminatedfromtheFSARbecauseitcontainedinformationwhichhadbeensupersededbytheimplementationoftheVermontYankeeOffSiteDoseCalculationManual(ODCM).InformationonreleasecalculationalmethodscanbefoundintheODCM.TheODCMalsoincludesreportingrequirementsforactualpublicdosesresultingfromthereleasecalculations.TheseresultsarepublishedintheAnnualRadioactiveEffluentReleaseReport.ThissectionfunctionedasaplacekeeperandisnolongerrequiredsincetheUFSARisbeingwhollyrewrittentotheDSARtoreflectthepermanentlydefueledstate.F InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.Theinformationishistorical,hasnotbeenupdated,isnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinAppendixFdoesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.InformationregardingcompliancewiththeintentoftheGDCsdeterminedtobeapplicableinthedefueledconditionhasbeenrelocatedtosection3.1.1.Allotherinformationinthissectionhasbeendeleted.3.1.1 Conformancewith10CFR50AppendixA,GeneralDesignCriteria Instrumentation LoadingCriteriaforClassIPiping LOADINGCRITERIAFOREBASCOSUPPLIEDCLASSICOMPONENTS QAPROGRAM QA(QA)ProgramDuringtheOperationsPhase STACKRELEASELIMITCALCULATIONS CONFORMANCEWITHAECDESIGNCRITERIA Page134of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR F.1 DeleteAppendixF.1,SummaryDescription.

InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinAppendixF.1,SummaryDescriptionishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinAppendixF.1,SummaryDescription,doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2 F.2.1 DeleteSectionF.2.1,GroupI OverallPlantRequirements(Criteria1 5).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.1ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.1doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2.2 DeleteSectionF.2.2,GroupII ProtectionbyMultipleFissionBarriers(Criteria6 10).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.2ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.2doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.

SUMMARY

DESCRIPTION CRITERIONCONFORMANCE GroupI OverallPlantRequirements(Criteria1 5)GroupII ProtectionbyMultipleFissionBarriers(Criteria6 10)Page135of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR F.2.3 DeleteSectionF.2.3,GroupIII NuclearandRadiationControls(Criteria11 18).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.3ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.3doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2.4 DeleteSectionF.2.4,GroupIV ReliabilityandTestabilityofProtectionSystems(Criteria19 26).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.4ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.4doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2.5 DeleteSectionF.2.5,GroupV ReactivityControl(Criteria27 32).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.5ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.5doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2.6 DeleteSectionF.2.6,GroupVI ReactorCoolantPressureBoundary(Criteria33 36).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.6ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.6doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.GroupIII NuclearandRadiationControls(Criteria11 18)GroupIV ReliabilityandTestabilityofProtectionSystems(Criteria19 26)GroupV ReactivityControl(Criteria27 32)GroupVI ReactorCoolantPressureBoundary(Criteria33 36)Page136of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR F.2.7 DeleteSectionF.2.7,GroupVII EngineeredSafetyFeatures(Criteria37 65).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.7ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.7doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2.8 DeleteSectionF.2.8,GroupVIII FuelandWasteStorageSystems(Criteria66 69).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.8ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.8doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.F.2.9 DeleteSectionF.2.9,GroupIX PlantEffluents(Criterion70).InaStaffRequirementsMemorandumonSECY 92 223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenotlicensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingoftheserequirementstoolderplantswouldprovidelittleornosafetybenefit.ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionoftheVermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludedaconsolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenotnewrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.9ishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.9doesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.G G.1 TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.Consequently,theinformationprovidedinSectionG.1isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.GroupIX PlantEffluents(Criterion70)STATIONMETEOROLOGY INITIALONSITEMETEOROLOGICALPROGRAM GroupVII EngineeredSafetyFeatures(Criteria37 65)GroupVIII FuelandWasteStorageSystems(Criteria66 69)Page137of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR G.1.1 DeleteSectionG.1.1,Introduction.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.1isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.G.1.2 DeleteSectionG.1.2,DescriptionoftheMonitoringProgram.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.2isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.G.1.3 DeleteSectionG.1.3,Results.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.3isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.G.1.4 DeleteSectionG.1.4,ComparisonwithPDARDiffusionModel.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.4isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.G.1.5 DeleteSectionG.1.5,Conclusions.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.5isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.Introduction DescriptionoftheMonitoringProgram Results ComparisonwithPDARDiffusionModel Conclusions Page138of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableG.1.1 DeleteTableG.1.1,MonthlyWindSummaryAugust1967.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.1isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.2 DeleteTableG.1.2,MonthlyWindSummarySeptember1967.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.2isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.3 DeleteTableG.1.3,MonthlyWindSummaryOctober1967.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.3isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.4 DeleteTableG.1.4,MonthlyWindSummaryNovember1967.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.4isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.5 DeleteTableG.1.5,MonthlyWindSummaryDecember1967.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.5isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.MonthlyWindSummaryAugust1967 MonthlyWindSummarySeptember1967 MonthlyWindSummaryOctober1967 MonthlyWindSummaryNovember1967 MonthlyWindSummaryDecember1967 Page139of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableG.1.6 DeleteTableG.1.6,MonthlyWindSummaryJanuary1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.6isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.7 DeleteTableG.1.7,MonthlyWindSummaryFebruary1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.7isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.8 DeleteTableG.1.8,MonthlyWindSummaryMarch1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.8isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.9 DeleteTableG.1.9,MonthlyWindSummaryApril1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.9isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.10 DeleteTableG.1.10,MonthlyWindSummaryMay1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.10isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.MonthlyWindSummaryMay1968 MonthlyWindSummaryJanuary1968 MonthlyWindSummaryFebruary1968 MonthlyWindSummaryMarch1968 MonthlyWindSummaryApril1968 Page140of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableG.1.11 DeleteTableG.1.11,MonthlyWindSummaryJune1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.11isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.12 DeleteTableG.1.12,MonthlyWindSummaryJuly1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.12isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.13 DeleteTableG.1.13,SeasonalWindSummarySummer;August1967,JuneJuly1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.13isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.14 DeleteTableG.1.14,SeasonalWindSummaryFall;SeptemberNovember1967.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.14isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.15 DeleteTableG.1.15,SeasonalWindSummaryWinter;December1967February1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.15isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.MonthlyWindSummaryJune1968 MonthlyWindSummaryJuly1968 SeasonalWindSummarySummer;August1967,JuneJuly1968 SeasonalWindSummaryFall;SeptemberNovember1967 SeasonalWindSummaryWinter;December1967February1968 Page141of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableG.1.16 DeleteTableG.1.16,SeasonalWindSummarySpring;MarchMay1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.16isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.17 DeleteTableG.1.17,AnnualWindSummaryAugust1967July1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.17isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.TableG.1.18 DeleteTableG.1.18,WindDirectionPersistenceSummaryin22.5DegreeSectorsAllClassesofStabilityCombined.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.18isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 1 DeleteFigureG.1 1,AnnualWindRose,AllStabilityClassesCombined.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 1isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 2 DeleteFigureG.1 2,FallWindRose,AllStabilityClassesCombined.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 2isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.SeasonalWindSummarySpring;MarchMay1968 AnnualWindSummaryAugust1967July1968 WindDirectionPersistenceSummaryin22.5DegreeSectorsAllClassesofStabilityCombined AnnualWindRose,AllStabilityClassesCombined FallWindRose,AllStabilityClassesCombined Page142of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.1 3 DeleteFigureG.1 3,WinterWindRose,AllStabilityClassesCombined.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 3isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 4 DeleteFigureG.1 4,SpringWindRose,AllStabilityClassesCombined.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 4isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 5 DeleteFigureG.1 5,SummerWindRose,AllStabilityClassesCombined.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 5isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 6 DeleteFigureG.1 6,AnnualWindRose,ModeratelyandSlightlyStableConditions.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 6isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 7 DeleteFigureG.1 7,AnnualWindRosewithPrecipitationOccurrence.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 7isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.WinterWindRose,AllStabilityClassesCombined SpringWindRose,AllStabilityClassesCombined SummerWindRose,AllStabilityClassesCombined AnnualWindRose,ModeratelyandSlightlyStableConditions AnnualWindRosewithPrecipitationOccurrence Page143of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.1 8 DeleteFigureG.1 8,AnnualWindRosewithNoPrecipitationOccurrence.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 8isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 9 DeleteFigureG.1 9,MonthlyInversionFrequencyandAverageWindSpeedDuringInversions.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 9isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 10 DeleteFigureG.1 10,NumberofHoursforEachWindSpeedGroupfor32HourDecember1967Inversion.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 10isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 11 DeleteFigureG.1 11,WindDirectionDistributionDuring32HourDecemberInversion.

TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 11isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.FigureG.1 12 DeleteFigureG.1 12,DurationofLongestInversioninEachMonthBetweenAugust1967andJuly1968.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 12isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.MonthlyInversionFrequencyandAverageWindSpeedDuringInversions NumberofHoursforEachWindSpeedGroupfor32HourDecember1967Inversion WindDirectionDistributionDuring32HourDecemberInversion DurationofLongestInversioninEachMonthBetweenAugust1967andJuly1968 AnnualWindRosewithNoPrecipitationOccurrence Page144of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.1 13 DeleteFigureG.1 13,CumulativeFrequencyofOccurrenceof.TheInitialOn SiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginalVYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVYPlantDesignandAnalysisReport.TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummariesandacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.TheinformationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.1 13isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.G.2 SectionG.2describesthecurrentonsitemeteorologicalmonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.Adiscussionofthedatasummariesisincluded,andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December1980).Resultsfrombothmonitoringprogramswerecompatible,andbothprogramsproduceddatabaseswhichwererepresentativeofsitemeteorology.

SectionG.2supportsthemeteorologysectionoftheSAR.SectionG.2supportsmeetingtherequirementsofRegGuide1.23,Rev.0.Nochangesarerequired.G.2G.2.1NoChanges G.2.1G.2.2NoChanges G.2.2G.2.3NoChanges G.2.3 TableG.2.1 NoChanges TableG.2.1 TableG.2.2 NoChanges TableG.2.2 TableG.2.3 NoChanges TableG.2.3 TableG.2.4 NoChanges TableG.2.4 TableG.2.5 NoChanges TableG.2.5 TableG.2.6 NoChanges TableG.2.6 TableG.2.7 NoChanges TableG.2.7 FigureG.2 1 NoChanges FigureG.2 1 FigureG.2 2 NoChanges FigureG.2 2 FigureG.2 3 NoChanges FigureG.2 3 FigureG.2 4 NoChanges FigureG.2 4 FigureG.2 5 NoChanges FigureG.2 5 FigureG.2 6 NoChanges FigureG.2 6 CURRENTONSITEMETEOROLOGICALPROGRAM Introduction DescriptionoftheMonitoringProgram Results MeteorologicalDataRecoveryRatesfor1980 JointFrequencyDistributionofWindSpeed,WindDirection,andJointFrequencyDistributionofWindSpeed,WindDirection,andWindDirectionPersistenceSummary(35footlevel)WindDirectionPersistenceSummary(297footlevel)InversionPersistenceSummary(198 33footDeltaT)InversionPersistenceSummary(295 33footDeltaT)LocationofPrimaryandBackupMeteorologicalTowers SpringWindRose(35footlevel)March1980May1980 SummerWindRose(35footlevel)June1980August1980 AutumnWindRose(35footlevel)September1980November1980 WinterWindRose(35footlevel)January1980February1980;December1980 AnnualWindRose(35footlevel)January1980December1980 SummerWindRose(35footlevel)June1980August1980 AutumnWindRose(35footlevel)September1980November1980 WinterWindRose(35footlevel)January1980February1980;December1980 AnnualWindRose(35footlevel)January1980December1980 CumulativeFrequencyofOccurrenceofIntroduction DescriptionoftheMonitoringProgram Results MeteorologicalDataRecoveryRatesfor1980 JointFrequencyDistributionofWindSpeed,WindDirection,andStabilityJointFrequencyDistributionofWindSpeed,WindDirection,andStabilityWindDirectionPersistenceSummary(35footlevel)WindDirectionPersistenceSummary(297footlevel)InversionPersistenceSummary(198 33footDeltaT)InversionPersistenceSummary(295 33footDeltaT)LocationofPrimaryandBackupMeteorologicalTowers SpringWindRose(35footlevel)March1980May1980 CURRENTONSITEMETEOROLOGICALPROGRAM Page145of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.2 7 NoChanges FigureG.2 7 FigureG.2 8 NoChanges FigureG.2 8 FigureG.2 9 NoChanges FigureG.2 9 FigureG.2 10 NoChanges FigureG.2 10 FigureG.2 11 NoChanges FigureG.2 11 H H.1 DeleteSectionH.1,ThermalHydraulicDesign,SummaryDescription.

Thematerialpresentedinthisappendixdescribestheanalyticalmethodologyusedintheinitialreactorcoredesign.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally,sinceSectionsH.2andH.3aredeletedfromtheDSAR,thesummaryofthosesectionspresentedinSectionH.1isnolongerapplicableandisobsolete.H.2 SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatethermalmargins.ThethermaloperatinglimitsfortheVermontYankeeNuclearPowerStationwereevaluatedforeachcycleofoperation.ThesewerepresentedinthecurrentcycleCorePerformanceAnalysisReportaswellasintheTechnicalSpecifications.

SectionH.2alsosupplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.H.2.1 DeleteSectionH.2.1,Introduction.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally,UFSARSection3.7hasbeendeleted.H.2.2 DeleteSectionH.2.2,ReactorCoreDesignBasesLimits.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally,UFSARSection3.7hasbeendeleted.H.2.3 DeleteSectionH.2.3,TypicalInitialCorePerformance.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.SectionH.2.3presentedexpectedinitialcoreperformancecharacteristics.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Initialcoreperformancecharacteristicsarehistoricalandarenolongerapplicable.

Additionally,UFSARSection3.7hasbeendeleted.AnnualWindRose(297footlevel)January1980December1980 SummerWindRose(297footlevel)June1980August1980 AutumnWindRose(297footlevel)September1980November1980 WinterWindRose(297footlevel)January1980February1980;December1980 SpringWindRose(297footlevel)March1980May1980SummerWindRose(297footlevel)June1980August1980 AutumnWindRose(297footlevel)September1980November1980 WinterWindRose(297footlevel)January1980February1980;December1980 AnnualWindRose(297footlevel)January1980December1980 THERMALHYDRAULICDESIGN SummaryDescription CORETHERMALDESIGN Introduction ReactorCoreDesignBasesLimits TypicalInitialCorePerformance SpringWindRose(297footlevel)March1980May1980Page146of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR H.2.4 DeleteSectionH.2.4,ThermalMargins.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.SectionH.2.4discussedthethermalmarginbetweentheproposedreactordesignlimitsandtheandfueldamagelimits.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally,UFSARSection3.7hasbeendeleted H.2.5 DeleteSectionH.2.5,TransientOperation.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally,UFSARSection3.7hasbeendeleted.H.2.6 DeleteSectionH.2.6,Summary.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally,UFSARSection3.7hasbeendeleted.H.2.7 DeleteSectionH.2.7,Conclusions.SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Theconclusionsdrawninthissectionarenolongerapplicable.

Additionally,UFSARSection3.7hasbeendeleted.H.2.8 DeleteSectionH.2.8,ReferencesSectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Thedocumentsreferencedinthissectionarenolongerapplicable.

Additionally,UFSARSection3.7hasbeendeleted.TableH.2.1 DeleteTableH.2.1,PeakLinearHeatGenerationRate(InitialReactorCoreDesignBases)SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.TheinformationprovidedinTableH.2.1ishistorical,isnolongerapplicableandisobsolete.Additionally,UFSARSection3.7hasbeendeleted.TableH.2.2 DeleteTableH.2.2,ResultsofTransients(InitialReactorCoreDesignBases).SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.TheinformationprovidedinTableH.2.2ishistorical,isnolongerapplicableandisobsolete.Additionally,UFSARSection3.7hasbeendeleted.RESULTSOFTRANSIENTS(INITIALREACTORCOREDESIGNBASES)ThermalMargin TransientOperation Summary Conclusions

REFERENCES PEAKLINEARHEATGENERATIONRATE(INITIALREACTORCOREDESIGNBASES)Page147of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableH.2.3 DeleteTableH.2.3,LimitComparisons(InitialReactorCoreDesignBases).SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.TheinformationprovidedinTableH.2.3ishistorical,isnolongerapplicableandisobsolete.Additionally,UFSARSection3.7hasbeendeleted.H.3 SectionH.3summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio.H.3.1 DeleteSectionH.3.1,IntroductionandSummary SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,informationregardingcriticalheatfluxmarginuncertaintiesishistorical,nolongerapplicableandisobsolete.H.3.2 DeleteSectionH.3.2,DefinitionsandObjectivesoftheAnalysis.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,informationregardingcriticalheatfluxmarginuncertaintiesishistorical,nolongerapplicableandisobsolete.H.3.3 DeleteSectionH.3.3,AnalyticalProceduresandResults.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,informationregardingcriticalheatfluxmarginuncertaintiesishistorical,nolongerapplicableandisobsolete.H.3.4 DeleteSectionH.3.4,ReactorModel.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,informationregardingthereactormodelusedincriticalheatfluxmarginuncertaintiesandanalysisishistorical,nolongerapplicableandisobsolete.H.3.5 DeleteSectionH.3.5,TheCalculationalProcess.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,informationregardingthecalculationalprocessusedincriticalheatfluxmarginuncertaintiesandanalysisishistorical,nolongerapplicableandisobsolete.LIMITCOMPARISONS(INITIALREACTORCOREDESIGNBASES)IntroductionandSummary DefinitionsandObjectivesoftheAnalysis AnalyticalProceduresandResults ReactorModel TheCalculationalProcess EFFECTOFUNCERTAINTIESONCRITICALHEATFLUXMARGIN Page148of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR H.3.6 DeleteSectionH.3.6,Results.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,informationregardingtheresultsoftheanalysisusedincriticalheatfluxmarginuncertaintiesarehistorical,nolongerapplicableandobsolete.H.3.7 DeleteSectionH.3.7,Conclusions.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,conclusionsregardingtheresultsoftheanalysisusedincriticalheatfluxmarginuncertaintiesarehistorical,nolongerapplicableandareobsolete.H.3.8 DeleteSectionH.3.7,References SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,documentslistedinthereferencessectionarenolongerapplicableandareobsolete.TableH.3.1 DeleteTableH.3.1,UncertaintyIncorePowerDetermination SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,theinformationprovidedinTableH.3.1isnolongerapplicableandisobsolete.TableH.3.2 DeleteTableH.3.2,OverpowerOccurrences.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,theinformationprovidedinTableH.3.2isnolongerapplicableandisobsolete.TableH.3.3 DeleteTableH.3.3,ManufacturingToleranceAffectingLocalPower.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,theinformationprovidedinTableH.3.3isnolongerapplicableandisobsolete.Results Conclusions References UncertaintyIncorePowerDetermination OverpowerOccurrences ManufacturingToleranceAffectingLocalPower Page149of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR TableH.3.4 DeleteTableH.3.4,BaseOperatingState.SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Consequently,theinformationprovidedinTableH.3.4isnolongerapplicableandisobsolete.I TheEstimateofProbabilitiesofaPipeBreakpresentedinAppendixI,attemptedtopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplantforeachpipingsystemandcomponent.I.1 DeleteSectionI.1,ProbabilityofLeakingFailures AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.1regardingtheprobabilityofleakingfailuresisnolongerapplicable.Thisinformationishistoricalandisobsolete.I.2 DeleteSectionI.2,CriticalCrackSize.AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.2regardingcriticalcracksizeisnolongerapplicable.Thisinformationishistoricalandisobsolete.I.3 DeleteSectionI.3,LeakageFlowFromCircumferentialCracks.AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.3regardingleakageflowfromcircumferentialcracksisnolongerapplicable.Thisinformationishistoricalandisobsolete.I.4 DeleteSectionI.4,ProbabilityofaLineBreak.AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.4regardinglinebreakprobabilityisnolongerapplicable.Thisinformationishistoricalandisobsolete.I.5 DeleteSectionI.5,References.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,thedocumentsreferencedinsectionI.5arenolongerapplicable.Thisinformationishistoricalandisobsolete.BaseOperatingState CRITICALCRACKSIZE LEAKAGEFLOWFROMCIRCUMFERENTIALCRACKS PROBABILITYOFLINEBREAK References ESTIMATEOFPROBABILITIESOFPIPEBREAK PROBABILITYOFLEAKINGFAILURES Page150of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureI 1 DeleteFigureI 1,SummaryofFractureDateforPipingMaterials AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,thesummaryinformationprovidedonFigureI 1regardingfracturedataforpipingmaterialsisnolongerapplicable.Thisinformationishistoricalandisobsolete.FigureI 2 DeleteFigureI 2,RelationshipofLeakRatetoStressIntensityFactor.AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedonFigureI 2regardingtherelationshipbetweenleakrateandstressintensityfactorisnolongerapplicable.Thisinformationishistoricalandisobsolete.FigureI 3 DeleteFigureI 3,ProbabilitythataLineBreakResultsfromaLeakingCrack.AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.PredictionoftheoccurrenceofthroughwallcracksforthoseSSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamageorthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedonFigureI 3showingtheprobabilitythatalinebreakwillresultfromaleakingcrackisnolongerapplicable.Thisinformationishistoricalandisobsolete.J J.1 DeleteSectionJ.1,StructuralEvaluationofReactorRecirculationSystem,ScopeandIntent.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesignbasisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.J.2 DeleteSectionJ.2,StructuralEvaluationofReactorRecirculationSystem,LoadingCondtions.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesignbasisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.J.3 DeleteSectionJ.3,StructuralEvaluationofReactorRecirculationSystem,AllowableLimits.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesignbasisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.SummaryofFractureDataforPipingMaterials RelationshipofLeakRatetoStressIntensityFactor ProbabilitythataLineBreakResultsfromaLeakingCrack STRUCTURALEVALUATIONOFREACTORRECIRCULATIONSYSTEM ScopeandIntent LoadingConditions AllowableLimits Page151of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR J.4 DeleteSectionJ.4,StructuralEvaluationofReactorRecirculationSystem,DiscussionofResults.TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesignbasisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.J.5 DeleteSectionJ.5,StructuralEvaluationofReactorRecirculationSystem,References.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesignbasisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.Referencesarenolongerapplicable.ReactorRecirculationSysteminformationisobsolete.TABLEJ.3 1 DeleteTableJ.3 1,RHRandRecirculationSystemsPipingLoadCombinations.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.ThesystemwasdesignedtoassureadequatefuelbarrierthermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintainarefloodablevolume.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesignbasisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.TheinformationprovidedontableJ.3 1isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.K K.1 DeletesectionK.1,CoreShroudRepair,IntroductionandSummary.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.K.2 DeletesectionK.2,CoreShroudRepair,Background.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.K.3 DeletesectionK.3,CoreShroudRepair,DescriptionofRepair.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.K.4 DeletesectionK.4,CoreShroudRepair,StructuralandDesignEvaluation.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.INTRODUCTIONAND

SUMMARY

BACKGROUND

DESCRIPTIONOFREPAIR STRUCTURALANDDESIGNEVALUATION CORESHROUDREPAIR RHRandRecirculationSystemsPipingLoadCombinations DiscussionofResults References Page152of153 Attachment1toPADandLBDCRforDSARRev0(FCR27/027)VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR K.5 DeletesectionK.5,CoreShroudRepair,SeismicAnalysis.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,theseismicanalysisprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.K.6 DeletesectionK.6,CoreShroudRepair,SystemsEvaluation.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,theSystemsevaluationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.K.7 DeletesectionK.7,MaterialsandFabrication.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,thedescriptionofthematerialsandfabricationprocessusedisnolongerapplicableandisconsideredobsolete.K.8 DeletesectionK.8,References.AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals,includingthecoreshroud,arenolongerrequired.Consequently,thereferenceslistedinSectionK.8arelongerapplicableandareconsideredobsolete.MATERIALSANDFABRICATION REFERENCES SEISMICANALYSES SYSTEMSEVALUATION Page153of153