ML15266A273

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

ML15266A273
Person / Time
Site:	Vermont Yankee File:NorthStar Vermont Yankee icon.png
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
Download: ML15266A273 (153)

Text

Attachment1toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015

1.0INTRODUCTION

AND

SUMMARY

1.1 Modifiedsection1.1,Applicant,changedtitletoIntroduction,includedinformationregardingoriginandpurposeofDefueledSafetyAnalysisReport,combinedselectinformationapplicablein thedefueledstatefromsections1.1.1,Applicant,1.1.2,EngineerConstruction,1.1.3,NuclearSteamSupplySystemSupplier,and1.1.4,TurbineGeneratorSupplier,deletedhistoricaland obsoleteinformation.

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 1.2 FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therrefore,manyofthedefinitionsinthissectionarenolongerapplicable.

TheSSCclassificationprocessdescribedinUFSARsection1.4,ClassificationofBWRSystems,Criteria,andRequirementsisnotapplicableinthedefueledstateandhasbeendeleted.Manyof thedefinitionsprovidedinthissectiondefinetermsrelatedtotheSSCClassificationprocessandtherefore,arenolongerapplicable Additionally,manyofthedefinitionsprovidedinthissectionarealreadydefinedinmoreappropriatedocumentation,includingTechnicalSpecificationsandtheTechnicalRequiementsManual.

Finally,manyofthedefinitionsprovidedinthissectionarenotusedintheDSAR.Therefore,theinformationinthissectionishistorcalandobsoleteandmaybedeleted.

Table 1.2.1(A)

DeleteTable1.2.1(A).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1 allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanently defueledstation.Consequently,theinformationinTable1.2.1(A)isnolongerrequiredandisobsolete.

Table 1.2.1(B)

DeleteTable1.2.1(B).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1 allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanently defueledstation.Consequently,theinformationinTable1.2.1(B)isnolongerrequiredandisobsolete.

Table 1.2.1(C)

DeleteTable1.2.1(C).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1 allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanently defueledstation.Consequently,theinformationinTable1.2.1(C)isnolongerrequiredandisobsolete.

Table 1.2.1(D)

DeleteTable1.2.1(D).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1 allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanently defueledstation.Consequently,theinformationinTable1.2.1(D)isnolongerrequiredandisobsolete.

Table1.2.1(E)

DeleteTable1.2.1(E).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1 allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanently defueledstation.Consequently,theinformationinTable1.2.1(E)isnolongerrequiredandisobsolete.

Table1.2.1(F)

DeleteTable1.2.1(F).FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1 allowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanently defueledstation.Consequently,theinformationinTable1.2.1(F)isnolongerrequiredandisobsolete.

Figure1.2.1 DeleteFigure1.2.1.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowe classificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueled station.Consequently,theinformationinFigure1.2.1isnolongerrequiredandisobsolete.

1.0INTRODUCTION

AND

SUMMARY

Introduction NuclearSteamSupplySystemSupplier TurbineGeneratorSupplier DEFINITIONS VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary RelationshipBetweenSafetyActionand ProtectiveAction ActualPlantDesignandOperation,Safety Considerations ActualPlantDesignandOperation,Power GenerationConsiderations ActualPlantDesignandOperation,Safety Considerations ActualPlantDesignandOperation,Safety Considerations ActualPlantDesignandOperation,Safety Considerations ActualPlantDesignandOperation,Safety Considerations DSARSection PROJECTIDENTIFICATION Applicant EngineerConstruction VYDSAR Page1of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure1.2.2 DeleteFigure1.2.2.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowe classificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueled station.Consequently,theinformationinFigure1.2.2isnolongerrequiredandisobsolete.

Figure1.2.3 DeleteFigure1.2.3.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedinsection1.4.1allowe classificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoapermanentlydefueled station.Consequently,theinformationinFigure1.2.3isnolongerrequiredandisobsolete.

1.3 1.3.1 1.ModifiedParagraph1.3.1toreflectdefueledstateandassociatedchangeispurposeoftheSAR.

1.1 1.3.2 DeletedSection1.3.2,RadioactiveMaterialBarrierConcept,providedamethodologyforrankingSSCswithdepthofinformationpresentedregardingeachSSCdeterminedbasedon relationshipwiththeradioactivebarrierconcept.Althoughthisapproachwasusedforoperation,theapproachisnotapplicablefollowingcertificationofpermanentdefueling,isobsoletepost defueling,andwasnotusedinthedevelopmentoftheDSAR.

1.3.4 FormatOrganizationofSections InformationinthissectionwasdeletedsinceitoutlinedtheformatandpresentationfortheUFSAR.TheDSARformatandpresentationanddepthofmaterialpresentedwasbasedon predecessorDSARsandRegGuide1.184.

Deletesection1.3.3,OrganizationofContents,todeleteincorporationbyreferenceofthefollowingspecialreferencessincetheyarenolongerapplicablefollowingcertificationofcessationof operationsandpermanentdefueling.

APED5286DesignBasisforCriticalHeatFluxinBoilingWaterReactors(September1966).

APED5450,DesignProvisionsforInServiceInspection(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)

RadioactiveMaterialBarrierConcept 1.3.3 OrganizationofContents RelationshipBetweenProtectiveFunctionsand ProtectiveActions RelationshipsBetweenDifferentTypesof Systems,ActionsandObjectives METHODSOFTECHNICALPRESENTATION Purpose ThissectionwasdeletedsinceitoutlinedtheformatandpresentationfortheUFSAR.TheDSARformatandpresentationanddepthofmaterialpresentedwasbasedonpredecessorDSARsand RegGuide1.184.

Introduction Page2of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.3.5 Deletedsection1.3.5,PowerLevelBasisforAnalysisofAbnormalOperationalTransientsandAccidents.Informationinthissectionisnotapplicablefollowingcertificationofpermanent defueling.Sincethereactormaynolongerbeoperatedandnuclearfuelmaynolongerbeemplacedorretainedinthereactorvessel,informationregardingthepowerlevelbasisforanalysisof AOTsandaccidentsisnolongerapplicable.

Figure1.31 Delete,referencenolongerrequiredsinceentiresectionhasbeendeleted.

1.4 DeleteSection1.4,CLASSIFICATIONOFBWRSYSTEMS,CRITERIA,ANDREQUIREMENTS 1.4.1 DeleteSection1.4.1,Introduction.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theclassificationprocessdescribedin thissectionallowedclassificationofanyBWRaspectrelativetoeitherpersonnelhazardorthegenerationofelectricalpower.Thisprocessisnolongerrequiredandisnotapplicabletoa permanentlydefueledstation.

1.4.2 DeleteSection1.4.2,ClassificationBasis.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisnotapplicabletoa permanentlydefueledstation.

1.4.3 DeleteSection1.4.3,UseoftheClassificationBasis.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,thesectiondescribinguseoftheclassificationbasisisnolonger requiredandisnotapplicabletoapermanentlydefueledstation.

Table1.4.1 DeleteTable1.4.1,ConceptforClassificationofBWRSystems,CriteriaandRequirements.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,thetablelistingthesafet considerationsandpowergenerationconsiderationsforPlannedOperation,AbnormalOperatingTransientsandAccidentsisnolongerrequired.

1.5 1.Deletedparagraphinsection1.5whichstatedthatdesigncriteriaaregroupedaccordingtotheclassificationplangiveninTable1.2.1,sincetable1.2.1andtheclassificationplanarenot applicabletothedefueledstate.Obsoleteinformation 2.Consolidateddesigncriteriawhichremainapplicableinthedefueledstateintoappropriategeneralsections.

1.5.1 2.Section1.5.1,GeneralCriteria,General,deletedcriteriawhichstatesthatthestationshallbedesigned,fabricatedanderectedsothatitcanbeoperatedtoproduceelectricalpowerina safe,reliableandeffecientmanner.Obsoleteinformation 3.Section1.5.1,GeneralCriteria,Nuclear,deletedparagraph3pertainingtothecriteriaforthereactorcoreandreactivitycontrolsystems.Notapplicableinthedefueledstate,obsolete information 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.Followingcertificationofpermanentdefuelingthelicenseeisnolonger authorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelated designbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivity ControlDesignCriteriaarenolongerapplicable.

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.Fuelwillbestoredinthespent fuelpooluntiltransferredtothesiteISFSI,controlrodswillbestoredeitherinthespentfuelpoolorremaininstalledinthereactorvessel 1.3.2.1 1.6.1.4 Deletethissection,Notapplicableinthedefueledstate,obsoleteinformation DESIGNCRITERIA FACILITYDESCRIPTION General SITEANDENVIRONS FACILITYARRANGEMENT FuelStorageandHandling NuclearFuelandControlRods CLASSIFICATIONOFBWRSYSTEMS,CRITERIA,AND REQUIREMENTS Introduction ClassificationBasis UseoftheClassificationBasis ConceptforClassificationofBWRSystems, CriteriaandRequirements PRINCIPALDESIGNCRITERIA POWERCONVERSIONSYSTEMS PowerLevelBasisforAnalysisofAbnormal OperationalTransientsandAccidents PipingandInstrumentSymbols,G191155 SITEANDENVIRONS FACILITYARRANGEMENT NUCLEARSYSTEM NuclearSafetyDesignCriteria(Abnormal OperationalTransients)

NuclearSafetyDesignCriteria(Accidents)

SpecialSafetyDesignCriteria PLANTDESCRIPTION General GeneralCriteria PowerGenerationDesignCriteria(Planned Operation)

PowerGenerationDesignCriteria(Abnormal OperationalTransients)

NuclearSafetyDesignCriteria(Planned Operation) 1.2 Page3of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.6.1.5 ElectricalPowerSystems Modifytoremovereferencetopowergenerationatthestation,referencetothemaingeneratorandexcitationsystem,thestationmaintransformer,andthe345kVtransmissionlines.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,theequipmentmentionedaboveisnolongerrequiredandisobsolete.

1.3.5.1 1.6.1.6 Modifytoremovereferencetomethodsusedtocontrolreleaseofradioactivematerialtowithinapplicablelimits.Listingofthemethodsusedisexcessdetailandisnotreqired.

1.3.3 1.6.1.6.1 LiquidRadwasteSystem Modifytoremovereferencetodischargeofradioactiveprocessliquidwasatethroughthecirculatingwaterdischargecanalanddilutionwithcondensereffluentcirculatingwaterorriverwater Thestatement"inaccordancewithapplicablepermits"ensuresthatVYdischargeswillcomplywithallapplicablerequirements.Informationremovedisconsideredexcessivedetail.

1.3.3.2 1.6.1.6.2 SolidRadwasteSystem Modifytoremoveexcessivedetailregardingmethodsforpreparingandshippingsolidradioactivewaste.AllVYsolidradwasteshippedwillbeinaccordancewithapplicablerequirements.

1.3.3.3 1.6.1.6.3 GaseousRadwaste System 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)system andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperable onlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactiv decaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelinginJanuary2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,thesecondary containmentfunctionisnolongerrequired.

1.6.2.9 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.10 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation 1.6.2.11 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonge possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheCoreStandby CoolingSystemsarenolongerrequired.InformationregardingtheCoreStandbyCoolingSystemsisobsoletedandmaybedeleted.

1.6.2.12 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonge possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheResidualHeat RemovalSystem(ContainmentCooling)arenolongerrequired.InformationregardingtheResidualHeatRemovalSystem(ContainmentCooling)isobsoletedandmaybedeleted.

1.6.2.13 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactor vessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,thefunctionsprovidedbytheControlRodVelocityLimitersarenolongerapplicable.

1.6.2.14 Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactor vessel,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 NuclearSystemPressureRelief System ReactorCoreIsolationCooling System PrimaryContainment PrimaryContainmentandReactor VesselIsolationControlSystem RadioactiveWasteSystems NuclearSafetyandEngineeredSafeguards ReactorProtectionSystem ControlRodDriveHousingSupports StandbyGasTreatmentSystem Page4of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.6.2.16 ModifySection1.6.2.16,StationDieselGeneratorSystemtoremovereferencetooperatingandaccidentconditions,andreflectthatthedieselgeneratorsnowsupplybackuppoweronlyto ensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDieselGeneratorsareonlyrequiredtosupplybackuppower toensurethesafestorageofirradiatedfuel.

1.3.5.1 1.6.2.17 ModifySection1.6.2.17,125VoltBatterySystem,toremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensurethesafe storageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsofthe125VDCsystemarenolonger required.

1.3.5.1 1.6.2.18 ModifySection1.6.2.18StationServiceWaterSystem,toremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystemnowsuppliesonlycooling necessarytoensurethesafestorageandhandlingofirradiatedfuel.

1.3.5.2 1.6.2.19 Deletesection,Notapplicableinthedefueledstate,obsoleteinformation SeeSection10.9 1.6.2.20 Deletesection1.6.2.20,MainSteamLineRadiationMonitoringSystem.

TheMainSteamLineRadiationMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontain thereleasedfissionproducts.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLine RadiationMonitoringSystemarenolongerrequired.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 ReactorManualControl System Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.2 RecirculationFlow ControlSystem Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.3 NeutronMonitoring System Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.4 RefuelingInterlocks Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.5 RefuelingVessel Instrumentation Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.1.6 ProcessComputer System Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.2 DeleteSection1.6.4.2 1.6.4.2.1 PressureRegulatorand TurbineGenerator Control Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.2.2 FeedwaterSystem Control Deleted,Notapplicableinthedefueledstate,obsoleteinformation 1.6.4.3 1.3.4 ElectricalPowerSystems ElectricalPowerSystems ServiceWaterSystem ReactorBuildingVentilationRadiationMonitoring System ReactorBuildingVentilation RadiationMonitoringSystem SpecialSafetySystems StandbyLiquidControlSystem StationEquipmentOutsidetheMain ControlRoom ProcessControlandInstrumentation StationServiceWaterSystem ReactorBuildingClosedCooling WaterSystem MainSteamLineRadiation MonitoringSystem StationDieselGeneratorSystem StationBatterySystem RadiationMonitoringandControl NuclearSystemProcessControland Information PowerConversionSystemsProcess ControlandInstrumentation RadiationMonitoringandControl Page5of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.6.4.3.1 ProcessRadiation Monitoring DeletedreferencetoAOGSystemOffGas,PrimaryContainmentSystemPurgeVentilationSystemDischarge,StandbyGasTreatmentsystemdischarge,CirculatingWaterDischarge,Cooling Tower.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheaboveRadiation MonitoringSystemarenolongerrequired.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 LiquidRadwasteSystem Control 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 GaseousRadwaste SystemControl DeleteSection1.6.4.3.5,GaseousRadwasteSystemControl.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheGaseousRadwaste Systemarenolongerrequired.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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.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 LiquidRadwasteSystem SolidRadwasteSystem AuxiliarySystems ElectricalPowerSystems FireProtectionSystem NormalAuxiliaryACPower TurbineBuildingClosedCooling WaterSystem AlternateCoolingSystem AuxiliarySystems PotableandSanitaryWaterSystem EquipmentandFloorDrainage Systems ProcessSamplingSystem FuelPoolCoolingandCleanup System ServiceandInstrumentAirSystems MakeupWaterTreatmentSystem Heating,Ventilating,andAir ConditioningSystems NewandSpentFuelStorage Heating,Ventilating,andAirConditioningSystems IrradiatedFuelStorage StandbyFuelPoolCoolingandDemineralizerSystem ServiceandInstrumentAirSystems StationWaterPurification,TreatmentandStorage MakeupWaterTreatmentSystem PotableandSanitaryWaterSystem EquipmentandFloorDrainageSystems ProcessSamplingSystem StationCommunicationsSystem PostAccidentSamplingSystem StationCommunicationsSystem StationShielding,AccessControlandRP Procedures Shielding,AccessControlandRadiationProtectionProcedures Page6of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 1.6.6.1 Deletedreferencetotable1.6.1,shieldingincontainmentrequiredtomakeradiationlevelsonthestationconsistentwithoperationalrequirements 1.3.8.1 1.6.6.2 Sectionmodifiedtopresentsummarytoreflectconditionsinpermanentlydefueledstateandtoeliminateduplicationbetween1.6.6andsection12.3,RadiationShieldingand13.4Radiation Protection.Consolidatedsectionwithsection1.6.6.1.

1.6.6.3 Sectionmodifiedtopresentsummarytoreflectconditionsinpermanentlydefueledstateandtoeliminateduplicationbetween1.6.6andsection12.3,RadiationShieldingand13.4Radiation Protection.Consolidatedsectionwithsection1.6.6.1.

1.6.6.4 Sectionmodifiedtopresentsummarytoreflectconditionsinpermanentlydefueledstateandtoeliminateduplicationbetween1.6.6andsection12.3,RadiationShieldingand13.4Radiation Protection.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,VYC2423,UpdatedVitalAreaDoseforEPU,documentedareviewofplantshielding forvitalequipmentandpostaccidentproceduralcontrolsinresponsetoNUREG0737,ItemII.B.2.2.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedinreference3isnolongerapplicable andisobsolete.

Sincenoadditionalreferencesexist,thissectionmaybedeleted.

Table1.6.1 DeleteTable1.6.1,ShieldingDesignBasisLimitations.Referencetothistablehasbeendeletedfromsection1.6.6.1,nootherreferencestothistableexistinthissection.Therefore,thistable maybedeleted.

Figure1.61 DeleteFigure1.61,ReactorHeatBalance,RatedPower.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Theinformation providedbyfigure1.61,ReactorHeatBalance,RatedPower,isnolongerapplicable.Thisinformationisobsolete.

Figure1.62 DeleteFigure1.62,TurbineGeneratorHeatBalance,RatedPower.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.The informationprovidedbyfigure1.61,ReactorHeatBalance,RatedPower,isnolongerapplicable.Thisinformationisobsolete.

1.7 DeleteSection1.7,ComparisonofPrincipalDesignCharacteristics.ThissectionprimarilyliststhedesigncharacteristicsoftheVYstationatinitiallicensingandcomparesthemtosimilarplants inoperationatthetime.Thisinformationishistoricalinnatureandisnolongerapplicablefollowingpermanentdefueling.Whereapplicable,informationprovidedwasverifiedtoalsoexistin theappropriateSSCdescriptioninotherlocationsintheDSAR.Additionally,theinformationpresentedinTable1.7.7,AEC1967DraftGeneralDesignCriteriaIndexedtoapplicableUFSAR Section(s)ishistoricalinformationandisnolongerapplicable.

1.7.1 Delete,notapplicabletothedefueledstate,obsoleteinformation 1.7.2 Delete,notapplicabletothedefueledstate,obsoleteinformation 1.7.3 Delete,notapplicabletothedefueledstate,obsoleteinformation 1.7.4 Delete,notapplicabletothedefueledstate,obsoleteinformation 1.7.5 Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.1 Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.2 Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.3 Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.4 Delete,notapplicabletothedefueledstate,obsoleteinformation RPProcedures ImplementationofStructuralLoadingCriteria PlantDesignChanges General Shielding AccessControlProcedures General StructuralLoadingCriteria StructuralDesignCharacteristics ComparisonNuclearSystemDesign Characteristics ComparisonPowerConversionSystemDesign Characteristics ComparisonElectricalSystemDesign Characteristics ComparisonofContainmentDesign Characteristics COMPARISONOFPRINCIPALDESIGNCHARACTERISTICS NuclearSystemDesignCharacteristics PowerConversionSystemDesignCharacteristics ElectricalPowerSystemsDesignCharacteristics ContainmentDesignCharacteristics References ShieldingDesignBasisLimitations ReactorHeatBalance,RatedPower TurbineGeneratorHeatBalance,RatedPower(at 0.96PowerFactor)

Page7of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table1.7.5 Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.6 Delete,notapplicabletothedefueledstate,obsoleteinformation Table1.7.7 Delete,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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,fueldamagedueAbnormalOperationalTransientsarenolonger possible.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.DeletedreferencetoANSIN18.71976,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,notapplicablepostdefueling,Obsoleteinformation 1.11 Sectionrewordedtostate:"Basedonthedesignofthefacility,andtheanalysisofcredibleevents,thereisreasonableassurancethatthefacilitycansafelymanageirradiatedfueland radioactivewastewithoutendangeringthehealthandsafetyofthepublic."

1.5 2.0STATIONSITEANDENVIRONS 2.1 NoChanges,retainedassupportinghistoricalinformation 2.1 2.2 2.2 2.2.1 NoChanges 2.2.1 2.2.2 NoChanges 2.2.2 2.2.3 DeletedreferencetoHinsdaleRaceway,racewayhasbeendemolished.

2.2.3 2.2.4 Section3.0,ExclusionAreas,deleted"duringnormalplantoperation" 2.2.4 2.2.5 NoChanges 2.2.5 Table2.2.1 NoChanges Table2.2.1 Table2.2.2 NoChanges Table2.2.2 ComparisonofStructuralDesignCharacteristics Responsibilities Implementation ManagementEvaluation AbnormalOperationalTransients Accidents SummaryoftheMaximumOffsiteEffectsof DesignBasisAccidents QAPROGRAM Scope ComparisonofSystemDesignCharacteristics AEC1967DraftGeneralDesignCriteriaIndexed toApplicableUFSARSection(s)

SUMMARY

OFRADIATIONEFFECTS NormalOperations QAProgram Scope Responsibilities Implementation ManagementEvaluation

SUMMARY

OFRADIATIONEFFECTS FuelStorageandHandlingandWasteManagement AccidentsandEvents SiteAreaBoundaries,ExclusionArea,andLow PopulationZone Conclusions PopulationDensityComparision LocationandArea Population LandUse STATIONRESEARCHDEVELOPMENTANDFURTHER INFORMATION;REQUIREMENTSANDRESOLUTION

SUMMARY

GENERALCONCLUSIONS

SUMMARY

DESCRIPTION STATIONSITEANDENVIRONS GeneralConclusions 2.0STATIONSITEANDENVIRONS SummaryDescription SiteDescription LocationandArea Population LandUse SiteAreaBoundaries,ExclusionArea,andLowPopulationZone Conclusions PopulationDensityComparision 2000PopulationDistribution 2000PopulationDistribution Page8of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table2.2.3 NoChanges Table2.2.3 Table2.2.4 NoChanges Table2.2.4 Table2.2.5 NoChanges Table2.2.5 Table2.2.6 NoChanges Table2.2.6 Table2.2.7 NoChanges Table2.2.7 Figure2.21 NoChanges Figure2.21 Figure2.22 NoChanges Figure2.22 Figure2.23 NoChanges Figure2.23 Figure2.24 NoChanges Figure2.24 Figure2.25 NoChanges Figure2.25 Figure2.26 NoChanges Figure2.26 Figure2.27 NoChanges Figure2.27 Figure2.28 NoChanges Figure2.28 2.3 2.3 2.3.1 NoChanges 2.3.1 2.3.2 NoChanges 2.3.2 2.3.3 NoChanges 2.3.3 2.3.4 NoChanges 2.3.4 2.3.5 NoChanges 2.3.5 2.3.6 NoChanges 2.3.6 2.3.7 NoChanges 2.3.7 2.3.8 NoChanges 2.3.8 Table2.3.1 NoChanges Table2.3.1 Table2.3.2 NoChanges Table2.3.2 Table2.3.3 NoChanges Table2.3.3 Table2.3.4 NoChanges Table2.3.4 Table2.3.5 NoChanges Table2.3.5 LocationMap2MileRadius LocationMap10MileRadius LocationMap25MileRadius TableofLandUseSquareMiles AgriculturalStatisticsforCountiesWithin50 Miles AgriculturalStatisticsforCountiesWithin50 Miles ProjectedPopulationDistributionforYear2010 UrbanCentersWithin30MilesofSite ProjectedPopulationDistributionforYear2010 UrbanCentersWithin30MilesofSite TableofLandUseSquareMiles AgriculturalStatisticsforCountiesWithin50Miles AgriculturalStatisticsforCountiesWithin50Miles LocationMap2MileRadius LocationMap10MileRadius LocationMap25MileRadius General OnsiteMeteorologicalPrograms DiffusionClimatology StationSiteAreaPopulationDistribution10 MileRadiusYear2000 StationSiteAreaPopulationDistribution50 MileRadiusYear2000 METEOROLOGY G191142StationPlan 59206245PlanShowingExclusionAreaand RestrictedAreaBoundaries StationSiteAreaPopulationDistribution5Mile RadiusYear2000 G191142StationPlan 59206245PlanShowingExclusionAreaandRestrictedArea Boundaries StationSiteAreaPopulationDistribution5MileRadiusYear 2000 StationSiteAreaPopulationDistribution10MileRadiusYear 2000 StationSiteAreaPopulationDistribution50MileRadiusYear 2000 Meteorology General OnsiteMeteorologicalPrograms DiffusionClimatology PRECIPITATIONDATAFORTHEVERNONAREA WINDSDURINGTHUNDERSTORMS RAINFALLDATAFROMHURRICANECONNIE Conclusions MeteorologyRecord TEMPERATUREDATAFORTHEVERNONAREA WindsandWindLoading TemperatureandPrecipitation Storms References WindsandWindLoading TemperatureandPrecipitation Storms Conclusions References MeteorologyRecord TEMPERATUREDATAFORTHEVERNONAREA PRECIPITATIONDATAFORTHEVERNONAREA WINDSDURINGTHUNDERSTORMS RAINFALLDATAFROMHURRICANECONNIE Page9of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure2.31 NoChanges Figure2.31 Figure2.32 NoChanges Figure2.32 Figure2.33 NoChanges Figure2.33 2.4 NoChanges 2.4 2.4.1 NoChanges 2.4.1 2.4.2 NoChanges 2.4.2 2.4.3 Section2.4.3.4,Hydrology,Floods.Deleteinformationregardingequipmentrequiredtooperateduringamaximumprobablefloodsincethatequipmentwasnecessarytoensureadequate decayheatremovalfromarecentlyshutdownreactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sincepoweroperationscannotoccur andthereisnofuelinthereactorvessel,coredecayheatremovalduringaPMFfromarecentlyshutdownreactorisnolongeraconcern.Therefore,thisinformationisnolongerapplicable andmaybedeleted.

Section2.4.3.4,Hydrology,Floods.InsertthestatementregardingfuelpoolcoolingduringaPMF.Fuelpoolcoolingwillbemaintaineduntileitherservicewaterislostornormalelectrical powerislost.DGbackupsareavailableforpower.Alternatecoolingstrategiesexistintheeventservicewaterorelectricalpowerislost.

ReplaceddiscussionoffloodingandwaverunupwithdiscussiongeneratedduringFukushimaFloodingEvaluation.Informationinpreviousdiscussionwassupersededbytheinformationinthe FukushimaEvaluation.FukushimaEvaluationinformationwaslocatedintheconclusionsectionandwasmovedintothetextbody.

2.4.3 2.4.4 NoChanges 2.4.4 2.4.5 NoChanges 2.4.5 2.4.6 NoChanges 2.4.6 2.4.7 NoChanges 2.4.7 2.4.8 1.Section2.4.8,Conclusions,deletedstatement"Sincetheentrancestoallstructurescntainingequipmentnecessaryforreactorshutdownandcoolingareatelevation252.5feetMSL,theyare protectedagainstthePMF."Noequipmentisrequiredforreactorshutdownorcoolingpostdefueling.

2.4.8 2.4.9 NoChanges 2.4.9 Table2.4.1 NoChanges Table2.4.1 Table2.4.2 NoChanges Table2.4.2 Table2.4.3 NoChanges Table2.4.3 Table2.4.4 NoChanges Table2.4.4 Table2.4.5 NoChanges Table2.4.5 Table2.4.6 NoChanges Table2.4.6 Hydrology UsesOfRiver Biology HYDROLOGYANDBIOLOGY General LandAreaGroundHydrology StationSiteWestoverAFB,MassachusettsArea AnnualSurfaceWindrose StationSiteWestoverAFB,MassachusettsArea SeasonalSurfaceWindroses StationSiteConcordNewHampshireArea, PeriodsofRainfall(ForExtremelyShort Intervals)

General LandAreaGroundHydrology StationSiteWestoverAFB,MassachusettsAreaAnnualSurface Windrose StationSiteWestoverAFB,MassachusettsAreaSeasonal SurfaceWindroses StationSiteConcordNewHampshireArea,PeriodsofRainfall (ForExtremelyShortIntervals)

HydrologyandBiology Hydrology UsesOfRiver Biology MunicipalandIndustrialGroundwaterUsage Withina10MileRadiusoftheVernonSite PublicWaterSuppliesWithina10MileRadiusof theVernonSite WaterSuppliesWithinalMileRadiusoftheSite References AverageandExtremeValuesofStreamFlow ConnecticutRiverat Vernon,VermontWaterYears19451965 VermontYankeeNuclearPowerStation,Daily StreamFlowforOctober1964toSeptember 1965,ConnecticutRiveratVernon,Vermont ChemicalandBacteriologicalQualityofWater RiverFieldProgram Conclusions ChemicalandBacteriologicalQualityofWater RiverFieldProgram Conclusions References AverageandExtremeValuesofStreamFlowConnecticutRiverat Vernon,VermontWaterYears19451965 VermontYankeeNuclearPowerStation,DailyStreamFlowfor October1964toSeptember1965,ConnecticutRiveratVernon, Vermont MunicipalandIndustrialGroundwaterUsageWithina10Mile RadiusoftheVernonSite PublicWaterSuppliesWithina10MileRadiusoftheVernonSite WaterSuppliesWithinalMileRadiusoftheSite SixHourPMPandRunoffIncrements ConnecticutRiverBasinaboveVernon,Vermont SixHourPMPandRunoffIncrementsConnecticutRiverBasin aboveVernon,Vermont Page10of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table2.4.7 NoChanges Table2.4.7 Table2.4.8 NoChanges Table2.4.8 Table2.4.9 NoChanges Table2.4.9 Table2.4.10 NoChanges Table2.4.10 Table2.4.11 NoChanges Table2.4.11 Figure2.41 NoChanges Figure2.41 Figure2.42 NoChanges Figure2.42 Figure2.43 NoChanges Figure2.43 Figure2.44 NoChanges Figure2.44 Figure2.45 NoChanges Figure2.45 Figure2.46 NoChanges Figure2.46 Figure2.47 NoChanges Figure2.47 Figure2.48 NoChanges Figure2.48 Figure2.49 NoChanges Figure2.49 Figure2.410 NoChanges Figure2.410 Figure2.411 NoChanges Figure2.411 2.5 NoChanges 2.5 2.5.1 NoChanges 2.5.1 2.5.2 NoChanges 2.5.2 2.5.3 NoChanges 2.5.3 2.5.4 NoChanges 2.5.4 Table2.5.1 NoChanges Table2.5.1 StationSiteAreaPublicWaterSupplies10 MileRadius StationSiteAreaPrivateWaterSupplies1Mile Radius EnvelopingDepthDurationAreaValuesofPMP forSusquehannnaRiverBasin TimeVaryingModifiedPMFStageDischarge TableVermontYankeeNuclearPlantSite ChecklistofConnecticutRiverFishesFoundNear Vernon,Vermont FishesoftheConnecticutRiverintheVicinityof Vernon,VermontAllCollections,1980 MaximumAnnualFloodsonConnecticutRiverat Vernon,VermontArrangedinDescendingOrder (1927,1936,1938,19451973)

TimeVaryingPMFStageDischargeTable VermontYankeeNuclearPlantSite MaximumAnnualFloodsonConnecticutRiveratVernon, VermontArrangedinDescendingOrder(1927,1936,1938,1945 1973)

TimeVaryingPMFStageDischargeTableVermontYankee NuclearPlantSite TimeVaryingModifiedPMFStageDischargeTableVermont YankeeNuclearPlantSite ChecklistofConnecticutRiverFishesFoundNearVernon, Vermont FishesoftheConnecticutRiverintheVicinityofVernon,Vermont AllCollections,1980 StationSiteAreaPublicWaterSupplies10MileRadius StationSiteAreaPrivateWaterSupplies1MileRadius EnvelopingDepthDurationAreaValuesofPMPfor SusquehannnaRiverBasin CrossSectionoftheCriticalFetch VermontYankeeSampleStationsonConnecticut River GEOLOGYANDSEISMOLOGY ConnecticutRiverBasinFederalPower CommissionWaterResourceAppraisalsfor HydroelectricLicensingSummaryof PlanningStatus VermontYankeeNuclearPlantLocationofRiver CrossSections StageDischargeCurveattheVermontYankee NuclearPlant 6HourUnitHydrograph TotalSPFHydrograph TotalPMFHydrograph(NaturalandModified) 6HourUnitHydrograph TotalSPFHydrograph TotalPMFHydrograph(NaturalandModified)

ConnecticutRiverBasinFederalPowerCommissionWater ResourceAppraisalsforHydroelectricLicensingSummaryof PlanningStatus VermontYankeeNuclearPlantLocationofRiverCrossSections StageDischargeCurveattheVermontYankeeNuclearPlant CrossSectionoftheCriticalFetch VermontYankeeSampleStationsonConnecticutRiver GeologyandSeismology Conclusions AvailableInformationConcerningGeologyand SeismicActivityRelatedtotheVermontYankee General Geology Seismology General Geology Seismology Conclusions AvailableInformationConcerningGeologyandSeismicActivity RelatedtotheVermontYankeeNuclearPowerStationSite Page11of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table2.5.2 NoChanges Table2.5.2 Figure2.51 PreviouslyDeleted Figure2.52 NoChanges Figure2.52 Figure2.53 NoChanges Figure2.53 Figure2.54 NoChanges Figure2.54 Figure2.55 NoChanges Figure2.55 Figure2.56 NoChanges Figure2.56 Figure2.57 NoChanges Figure2.57 Figure2.58 NoChanges Figure2.58 Figure2.59 NoChanges Figure2.59 Figure2.510 NoChanges Figure2.510 Figure2.511 NoChanges Figure2.511 Figure2.512 NoChanges Figure2.512 Figure2.513 NoChanges Figure2.513 Figure2.514 NoChanges Figure2.514 Figure2.515 NoChanges Figure2.515 2.6 Section2.6.1,deletedthewordsafetyfromthesectiontitle.SincetheclassificationprocessdescribedintheUFSARsection1.4.1isnolongerused,theterm"Safety"objectiveisnolonger applicable.

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 StationSiteGeologicalSurveyGeneralPlan LocationofTestBorings StationSiteGeologicalSurveySubsurface ProfileLogofTestBorings(1A,2A,3A,4,5,8)

VernonPluton:EstimatedModeoftheOliverian MagmaSeries VernonPluton:EstimatedModeoftheOliverianMagmaSeries StationSiteGeologicalSurveyGeneralPlanLocationofTest Borings StationSiteGeologicalSurveySubsurfaceProfileLogofTest Borings(1A,2A,3A,4,5,8)

StationSiteGeologicalSurveySubsurface Profile(SectionCC)LogofTestBorings(2,2A,5, 7,7A,13,and15)

StationSiteGeologicalSurveySubsurface Profile(SectionDD)LogofTestBorings(3,3A, 4,8,8A,12,and16)

StationSiteTectonicMapNewEnglandArea StationSiteGeologicalSurveyAreaGeological Section StationSiteGeologicalSurveySubsurface Profile(SectionAA)LogofTestBorings(5,8,S9, 11,and21)

StationSiteGeologicalSurveySubsurface Profile(SectionBB)LogofTestBorings(2A,3A, ST61/2,andS9)

StationSiteTectonicMapStateofVermont StationSiteTectonicMapStateofNew Hampshire StationSiteGeologicalSurveyAreaBedrock Geology StationSiteTectonicMapStateofVermont StationSiteTectonicMapStateofNewHampshire StationSiteGeologicalSurveyAreaBedrockGeology StationSiteGeologicalSurveyAreaGeologicalSection StationSiteGeologicalSurveySubsurfaceProfile(SectionAA)

LogofTestBorings(5,8,S9,11,and21)

StationSiteGeologicalSurveySubsurfaceProfile(SectionBB)

LogofTestBorings(2A,3A,ST61/2,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 StationSiteCompilationofEarthquakesNew EnglandArea StationSiteEarthquakeIntensityModified MercalliandRossiForelScales StationSiteCompilationofEarthquakes CentralNewEnglandArea StationSiteCompilationofEarthquakesNewEnglandArea StationSiteEarthquakeIntensityModifiedMercalliandRossi ForelScales StationSiteCompilationofEarthquakesCentralNewEngland Area RadiologicalEnvironmentalMonitoringProgram Objectives MonitoringNetwork LandUseCensus EmergencySurveillance Reports Reports Reactor Page12of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.1 DeletetheinformationinSection3.1,SummaryDescription,renamethesection3.1,DesignCriteriatoprovideacentrallocationforSSCdesigninformationpertinentinthepermanently defueledstate.

Informationintheoldsummarydescriptionsectionsummmarizedaspectsofthedesignandoperationofthereactorwhicharenolongerapplicableinthepermanentlydefueledstate.

Section3.1,DesignCriteria,establishesacentrallocationfordesigninformationwhichremainsapplicableinthepermanentlydefueledstate.

3.1 3.2 3.3.1.1 3.2.1 ModifySection3.2.1,PowerGenerationObjectives,toreflectthefactthatfuelmaynolongerbeemplacedorretainedinthereactorvessel.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.Allfuelisstoredeitherinthespentfuelpool orattheISFSI.ThisobjectivehasbeenrewrittenandappliestothefuelstoredintheSpentFuelPool.

3.3.1.1.1 3.2.2 DeleteSection3.2.2,FuelMechDesignSafetyDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesse IAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheSafetyDesignBasisisnotapplicable.Portionsofthisobjectiveremainingapplicablehavebeenconsolidatedwiththe PowerGenerationObjectivetoformtheObjectivesection.

3.2.3 ModifySection3.2.3,FuelMechanicalDesignDescriptiontoremovealldiscussionsoecifictofuelemplacementinthereactorvessel.Followingcertificationofpermanentdefuelingthelicensee isnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.InformationprovidedintheFuelMechanicalDesign Descriptionsectionregardingnuclearfueloperationoremplacementinthereactorvesselisnolongerapplicable;allnuclearfuelhasbeenremovedfromthereactorvesselandisstoredinthe spentfuelpoolorattheISFSI.Informationregardingfueldesignapplicabletostorageinthespentfuelpoolhasbeenretained.

3.3.1.1.2 3.2.4 DeleteSection3.2.4,FuelMechDesignSafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheinformationprovidedintheFuelMechDesignSafetyEvaluationsectionisnolongerapplicable.

3.2.5 DeleteSection3.2.5,FuelMechDesignInspectionandtesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheinformationprovidedintheFuelMechDesignInspectionandTestingsectionisnolongerapplicable.

3.2.6 DeleteSection3.2.6,FuelMechDesignReferences.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Therefore,poweroperationscannotoccur.TheinformationprovidedintheFuelMechDesignReferencessectionisnolongerapplicable.

3.3 Deleteentiresection,Sections3.3.1through3.3.7arenolongerapplicable,noinformationremainsinthissection 3.3.1 Deletesection3.3.1,ReactorVesselInternalsMechDesign,PowerGenerationObjectives.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,the safetyobjectiveisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.

3.3.2 Deletesection3.3.2,ReactorVesselInternalsMechDesign,PowerGenerationDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,the powergenerationdesignbasesarenotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.

3.3.3 Deletesection3.3.3,ReactorVesselInternalsMechDesign,SafetyDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,thesafety designbasisisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.

3.3.4 Deletesection3.3.4,ReactorVesselInternalsMechDesign,Description.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,theinformation providedinthedescriptionsectionisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.

3.3.5 Deletesection3.3.5,ReactorVesselInternalsMechDesign,SafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,the informationprovidedinthesafetyevaluationsectionisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.

Objective Description DesignCriteria NuclearFuel PowerGenerationObjectives PowerGenerationDesignBases SafetyDesignBasis Description SafetyEvaluation Description SafetyEvaluation InspectionandTesting References REACTORVESSELINTERNALSMechDesign

SUMMARY

DESCRIPTION FuelMechDesign PowerGenerationObjectives SafetyDesignBasis Page13of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.3.6 Deletesection3.3.6,ReactorVesselInternalsMechDesign,InspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,the informationprovidedintheInspectionandTestingsectionisnotrequired.ReactorVesselInternalsMechDesigninformationisobsolete.

3.3.7 Deletesection3.3.7,ReactorVesselInternalsMechDesign,References.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,thereferences providednolongerapply.ReactorVesselInternalsMechDesigninformationisobsolete.

Table3.3.1 DeleteTable3.3.1,ReactorVesselInternalsDesignData.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctions performedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsMechDesigninformationisnolongerapplicable,theinformationprovidedno longerapplies.ReactorVesselInternalsMechDesigninformationisobsolete.

Figure3.3.1 DeleteFigure3.3.1,ReactorVesselInternals.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctions performedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.

ReactorVesselInternalsinformationisobsolete.

Figure3.3.2 DeleteFigure3.3.2,ReactorVesselInternalsFlowSchematic.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctions performedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.

ReactorVesselInternalsinformationisobsolete.

Figure3.3.3 DeleteFigure3.3.3,SteamSeparator.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactor vesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternals informationisobsolete.

Figure3.3.4 DeleteFigure3.3.4,FuelSupportPieces.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctions performedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.

ReactorVesselInternalsinformationisobsolete.

Figure3.3.5 DeleteFigure3.3.5,JetPumpIsometric.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctions performedbythereactorvesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.

ReactorVesselInternalsinformationisobsolete.

Figure3.3.6 DeleteFigure3.3.6,SteamDryer.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactor vesselinternalsarenolongerrequired.Consequently,theReactorVesselInternalsinformationisnolongerapplicable,theinformationprovidednolongerapplies.ReactorVesselInternals informationisobsolete.

Figure3.3.7 DeleteFigure3.3.7,LocationsofCalculatedPressureDifferentials.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.The functionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheLocationsofCalculatedPressureDifferentialsisnolongerapplicable,the informationprovidednolongerapplies.Thisinformationisobsolete.

Figure3.3.8A DeleteFigure3.3.8A,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisno longerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressure DifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure3.3.8B DeleteFigure3.3.8B,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisno longerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressure DifferentialsFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure3.3.8C DeleteFigure3.3.8C,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisno longerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressure DifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

InspectionandTesting JetPumpIsometric SteamDryer LocationsofCalculatedPressureDifferentials PressureDifferentialsFollowingSteamLineBreak InsidetheDrywell102%Power/107%CoreFlow PressureDifferentialsFollowingSteamLineBreak InsidetheDrywell102%Power/107%CoreFlow 3.38CPressureDifferentialsFollowingSteam LineBreakInsidetheDrywell16.7%Power/110%

CoreFlow References ReactorVesselInternalsDesignData ReactorVesselInternals ReactorVesselInternalFlowSchematic SteamSeparator FuelSupportPieces Page14of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure 3.3.8D DeleteFigure3.3.8D,PressureDifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisno longerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingthePressure DifferentialsFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure3.3.8E DeleteFigure3.3.8E,SteamDryerPressureDifferentialFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheSteam DryerPressureDifferentialFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationis obsolete.

Figure3.3.9 DeleteFigure3.3.9,ThermalShockTransientAnalysisZones.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thefunctions performedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheThermalShockTransientAnalysisZonesisnolongerapplicable,theinformation providednolongerapplies.Thisinformationisobsolete.

Figure3.3.10 DeleteFigure3.3.10,MaterialBehaviorGraphCyclesVersusStressforStainlessSteel.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheMaterialBehaviorGraphCyclesVersusStressforStainless Steelisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure3.3.11 PreviouslyDeleted Figure 3.3.12A DeleteFigure3.3.12A,VesselDomePressureFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisno longerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheVesselDome PressureFollowingSteamLineBreakInsidetheDrywell102%Power/107%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure 3.3.12B DeleteFigure3.3.12B,VesselDomePressureFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisno longerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheVesselDome PressureFollowingSteamLineBreakInsidetheDrywell16.7%Power/110%CoreFlowisnolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure 3.3.13A DeleteFigure3.3.13A,MSLBBundleLiftMarginat102%Power/107%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheMSLBBundleLiftMarginat102%Power/107%CoreFlowis nolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

Figure 3.3.13B DeleteFigure3.3.13B,MSLBBundleLiftMarginat16.7%Power/110%CoreFlow.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Thefunctionsperformedbythereactorvesselinternalsarenolongerrequired.Consequently,informationregardingtheMSLBBundleLiftMarginat16.7%Power/110%CoreFlowis nolongerapplicable,theinformationprovidednolongerapplies.Thisinformationisobsolete.

3.4 Deleteentiresection,Sections3.4.1through3.4.8arenolongerapplicable,noinformationremainsinthissection 3.4.1 Deletesection3.4.1,ReactivityControlMechDesign,PowerGenerationObjective.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisno longerapplicable,thePowerGenerationObjectiveprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.4.2 Deletesection3.4.2,ReactivityControlMechDesign,SafetyObjective.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolonger applicable,theSafetyObjectiveprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.

PressureDifferentialsFollowingSteamLineBreak InsidetheDrywell16.7%Power/110%CoreFlow SteamDryerPressureDifferentialFollowing SteamLineBreakInsidetheDrywell16.7%

Power/110%CoreFlow ThermalShockTransientAnalysisZones MaterialBehaviorGraphCyclesVersusStressfor StainlessSteel Deleted VesselDomePressureFollowingSteamLine BreakInsidetheDrywell102%Power/107%Core Flow SafetyObjectives VesselDomePressureFollowingSteamlineBreak InsidetheDrywell16.7%Power/110%CoreFlow MSLBBundleLiftMarginat102%Power/107%

CoreFlow MSLBBundleLiftMarginat16.7%Power/110%

CoreFlow REACTIVITYCONTROLMechDesign PowerGenerationObjective Page15of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.4.3 Deletesection3.4.3,ReactivityControlMechDesign,PowerGenerationDesignBasis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisno longerapplicable,thePowerGenerationDesignBasisprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.4.4 Deletesection3.4.4,ReactivityControlMechDesign,SafetyDesignBasis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolonger applicable,theSafetyDesignBasisprovidednolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.4.5 Deletesection3.4.5,ReactivityControlMechDesign,Description.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Since nuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolonger applicable,theinformationprovidedinthedescriptionsectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.4.6 Deletesection3.4.6,ReactivityControlMechDesign,SafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolonger applicable,theinformationprovidedinthesafetyevaluationsectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.4.7 Deletesection3.4.7,ReactivityControlMechDesign,InspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolonger applicable,theinformationprovidedintheInspectionandTestingsectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.4.8 Deletesection3.4.8,ReactivityControlMechDesign,References.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Since nuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,theReactivityControlMechDesigninformationisnolonger applicable,theinformationprovidedintheReferencessectionnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.41 DeleteFigure3.41,OriginalEquipmentControlRodIsometric.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclear fuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,OriginalEquipmentControlRodinformationisnolongerapplicable,the informationprovidedintheOriginalEquipmentControlRodIsometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.42 DeleteFigure3.42,TypicalControlRodtoControlRodDriveCouplingIsometric.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,TypicalControlRodtoControlRodDriveCoupling informationisnolongerapplicable,theinformationprovidedintheTypicalControlRodtoControlRodDriveCouplingIsometricnolongerapplies.ReactivityControlMechDesigninformation isobsolete.

Figure3.43 DeleteFigure3.43,TypicalControlRodVelocityLimiterIsometric.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Since nuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,TypicalControlRodVelocityLimiterinformationisnolonger applicable,theinformationprovidedintheTypicalControlRodVelocityLimiterIsometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.44 DeleteFigure3.44,ControlRodDrive,SimplifiedComponentIllustration.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDrive,SimplifiedComponentinformationisno longerapplicable,theinformationprovidedintheControlRodDrive,SimplifiedComponentIllustrationnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.45 DeleteFigure3.45,ControlRodDrive,SchematicDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincenuclear fuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDrive,informationisnolongerapplicable,theinformation providedintheControlRodDrive,SchematicDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

References OriginalEquipmentControlRodIsometric TypicalControlRodtoControlRodDriveCoupling Isometric TypicalControlRodVelocityLimiterIsometric ControlRodDrive,SimplifiedComponent Illustration ControlRodDrive,SchematicDiagram PowerGenerationDesignBases SafetyDesignBasis Description SafetyEvaluation InspectionandTesting Page16of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure3.46 DeleteFigure3.46,ControlRodDriveHydraulicControlSystemSimplifiedComponentIllustration.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDrive informationisnolongerapplicable,theinformationprovidedintheControlRodDriveHydraulicControlSystemSimplifiedComponentIllustrationnolongerapplies.ReactivityControlMech Designinformationisobsolete.

Figure3.47A DeleteFigure3.47A,ControlRodDriveHydraulicSystemPipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsare nolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolonger applicable,theinformationprovidedintheControlRodDriveHydraulicSystemPipingandInstrumentationDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.47B DeleteFigure3.47B,ControlRodDriveHydraulicSystemPipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsare nolongerpossible.Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolonger applicable,theinformationprovidedintheControlRodDriveHydraulicSystemPipingandInstrumentationDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.48 DeleteFigure3.48,ControlRodUnitDriveCutawayIllustration.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Since nuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,the informationprovidedintheControlRodUnitDriveCutawayIllustrationnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.49 DeleteFigure3.49,ControlRodDriveHydraulicSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Sincenuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,the informationprovidedintheControlRodDriveHydraulicSystem,ProcessDiagramnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

Figure3.410 DeleteFigure3.410,ControlRodHydraulicControlUnitIsometric.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Since nuclearfuelcannolongerbeplacedinthereactorvessel,reactivitycontrolfunctionsarenolongerrequired.Consequently,ControlRodDriveinformationisnolongerapplicable,the informationprovidedintheControlRodHydraulicControlUnitIsometricnolongerapplies.ReactivityControlMechDesigninformationisobsolete.

3.5 Deleteentiresection,Sections3.5.1through3.5.5arenolongerapplicable,noinformationremainsinthissection 3.5.1 Deletesection3.5.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthe ControlRodDriveHousingSupportsarenolongerrequired,thesafetyobjectiveisnolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.

3.5.2 Deletesection3.5.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheControlRodDriveHousingSupportsarenolongerrequired,thesafetydesignbasesarenolongerapplicable.ControlRodDriveHousingSupportSysteminformationisobsolete.

3.5.3 Deletesection3.5.3,CRDHousingSupportDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedinthedescriptionsectionisnolongerapplicable.ControlRodDriveHousingSupport Systeminformationisobsolete.

3.5.4 Deletesection3.5.4,CRDHousingSupportSafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently, thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedinthesafetyevaluationsectionisnolongerapplicable.ControlRodDriveHousing SupportSysteminformationisobsolete.

3.5.5 Deletesection3.5.5,CRDHousingSupportInspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedintheInspectionandTestingsectionisnolongerapplicable.Control RodDriveHousingSupportSysteminformationisobsolete.

Figure3.51 DeleteFigure3.51,ControlRodDriveHousingSupportIsometric.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheControlRodDriveHousingSupportsarenolongerrequired,theinformationprovidedintheControlRodDriveHousingSupportIsometricisnolonger applicable.ControlRodDriveHousingSupportSysteminformationisobsolete.

InspectionandTesting ControlRodDriveHousingSupportIsometric CONTROLRODDRIVEHOUSINGSUPPORTS SafetyObjective SafetyDesignBasis Description SafetyEvaluation G191170ControlRodDriveHydraulicControl SystemSimplifiedComponentIllustration G191170ControlRodDriveHydraulicSystem PipingandInstrumentationDiagram G191170HydraulicControlUnit,Pipingand InstrumentationDiagram ControlRodUnitDriveCutawayIllustration 5920164ControlRodDriveHydraulicSystem, ProcessDiagram ControlRodHydraulicControlUnitIsometric Page17of153 toPADandLBDCRforDSARRev0(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.Therefore poweroperationscannotoccurandtheseSafetyDesignBasesnolongerapply 3.6.4 Section3.6.4,NuclearRequirements,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel Therefore,poweroperationscannotoccurandthesenuclearrequirementsnolongerapply:

Controlrodswillberemovedfromcore.

ReactorManualcontrolsystemwillnolongerberequired Standbyliquidcontrolsystemwillnolongerberequiredsincetherewillbenocore 3.6.5 Section3.6.5,FuelNuclearCharacteristics,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.

Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPoolandpool designcharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransientscannot occur.

3.6.6 Section3.6.6,NuclearEvaluations,Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore poweroperationscannotoccurandthesenuclearevaluationsarenolongerrequired 3.6.7 Deletethissection,postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannotoccurand testingandverificationofnucleardesigncriteriaarenolongerrequired.

3.6.8 DeleteSection4.2.7,References.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Power operationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsof areactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistedreferencesnolongerapply.

Figure3.61 DeleteFigure3.61,RelativeXenonStabilityWithNoFluxFlattening,Postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactor vessel.Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPool andpooldesigncharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransients cannotoccur.Therefore,theinformationprovidedbyFigure3.61isnolongerapplicableandisobsolete.

Figure3.62 DeleteFigure3.62,EffectofPowerDensityonAxialXenonStabilityIncludingVoidTransport.Postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceor retainfuelinthereactorvessel.Therefore,thereactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.Reactivitycontrolwillbeprovidedbyfuelplacement intheSpentFuelPoolandpooldesigncharacteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicable andxenontransientscannotoccur.Therefore,theinformationprovidedbyFigure3.62isnolongerapplicableandisobsolete.

Figure3.63 DeleteFigure3.63,AzimuthalXenonStability.Postdefuelingthelicenseewillnolongerbeauthorizedtooperatethereactororemplaceorretainfuelinthereactorvessel.Therefore,the reactorwillnotbetakencriticaloroperated.FuelNuclearcharacteristicsnolongerapply.ReactivitycontrolwillbeprovidedbyfuelplacementintheSpentFuelPoolandpooldesign characteristics,controlrodworthisnolongerapplicablesincecontrolrodswillberemovedfromtheRPV,reactivitycoefficientsarenolongerapplicableandxenontransientscannotoccur.

Therefore,theinformationprovidedbyFigure3.63isnolongerapplicableandisobsolete.

3.7 3.7.1 DeleteSection3.7.1,PowerGenerationObjective.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydraulicdesignisnolongerrequiredandpower generationobjectivesareobsoleteinformation.

3.7.2 DeleteSection3.7.2,PowerGenerationDesignBases.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydraulicdesignisnolongerrequiredandpower generationdesignbasesareobsoleteinformation.

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

Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydraulicdesignisnolongerrequiredandsafetydesignbasesareobsolete information.

3.7.4 DeleteSection3.7.4,ThermalandHydraulicLimits.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydrauliclimitsarenolongerrequiredandareobsolete information.

3.7.5 DeleteSection3.7.5,ThermalandHydraulicCharacteristics.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,corethermalandhydrauliccharacteristicsarenolongerrequiredandare obsoleteinformation NUCLEARDESIGN PowerGenerationObjectives PowerGenerationDesignBases PowerGenerationDesignBases SafetyDesignBasis ThermalandHydraulicLimits ThermalandHydraulicCharacteristics RelativeXenonStabilityWithNoFluxFlattening EffectofPowerDensityonAxialXenonStability IncludingVoidTransport AzimuthalXenonStability THERMALANDHYDRAULICDESIGN PowerGenerationObjective SafetyDesignBasis NuclearRequirements FuelNuclearCharacteristics NuclearEvaluations TestingandVerification References Page18of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 3.7.6 DeleteSection3.7.6,ThermalandHydraulicEvaluation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thecorethermalandhydraulicevaluationisnolongerrequiredandis obsoleteinformation.ThedesignMCPRlimitnolongerapplies,fueldamageorwaterloggingcannotoccurduetoexceedinglimits,andflowblockagescannolongeroccur.

3.7.7 DeleteSection3.7.7,TestingandVerification.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,testingandverificationthatoperationisoccurringwithinMCPRandLHGR limitsisnolongerrequiredandisobsoleteinformation.

3.7.8 DeleteSection3.7.8,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,nor istoruspHcontrolrequiredfollowingaLOCA,sinceaLOCAcannolongeroccur.Thesedesignbasesareobsoleteinformation.

3.8.3 DeleteSection3.8.3,Description.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Power generationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired,noris toruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.

3.8.4 DeleteSection3.8.4,SafetyEvaluation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired, noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Therefore,asafetyevaluationoftheSBLCsystemisnolongerrequiredandis obsoleteinformation.

3.8.5 DeleteSection3.8.5,InspectionandTesting.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrolrodsisnolongerrequired, noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Therefore,inspectionandtestingoftheSBLCsystemisnolongerrequiredandis obsoleteinformation.

TechnicalSpecificationsurveillancerequirementsweredeletedfromTechnicalSpecificationsinpermanentlydefueledtechnicalspecifications.

Figure3.81 DeleteFigure3.81,StandbyLiquidControlSystem,PipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthe reactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,the informationprovidedonFigure3.81isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.

Figure3.82 DeleteFigure3.82,StandbyLiquidControlSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactorindependentofcontrol rodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformationprovidedonFigure3.82is nolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.

Figure3.83 DeleteFigure3.83,SaturationTemperatureofSodiumPentaborateSolution.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactor independentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformation providedonFigure3.83isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.

Figure3.84 DeleteFigure3.84,StandbyLiquidControlSystem,FunctionalControlDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthereactor independentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,theinformation providedonFigure3.84isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.

Figure3.85 DeleteFigure3.85,SodiumPentaborateSolutionVolumeConcentrationRequirements.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,amethodofshuttingdownthe reactorindependentofcontrolrodsisnolongerrequired,noristoruspHcontrolrequiredfollowingaLOCA.ThefunctionsoftheSBLCsystemarenolongerrequired.Consequently,the informationprovidedonFigure3.85isnolongerapplicable.InformationregardingtheStandbyLiquidControlSystemisobsolete.

4.0 ReactorCoolantSystem ThermalandHydraulicEvaluation TestingandVerification SodiumPentaborateSolutionVolume ConcentrationRequirements SafetyEvaluation InspectionandTesting StandbyLiquidControlSystem,Pipingand InstrumentationDiagramG191171 StandbyLiquidControlSystem,ProcessDiagram 5920717 SaturationTemperatureofSodiumPentaborate Solution StandbyLiquidControlSystem,Functional ControlDiagram592040 References STANDBYLIQUIDCONTROLSYSTEM SafetyObjective SafetyDesignBases Description Page19of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.1 DeleteSection4.1,ReactorCoolantSystemSummaryDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequentlythestructures,systemsandcomponentsdiscussedinsection4.

arenolongerrequiredandtheinformationprovidedisnolongerapplicable.

Table4.1.1 DeleteTable4.1.1,EquipmentWithinReactorCoolantPressureBoundaryComparisonWith10CFR50.55A.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorized toemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequentlythestructures,systems andcomponentsdiscussedinsection4.1arenolongerrequiredandtheinformationprovidedinTable4.1.1isnolongerapplicable.

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,includingtheshroudandshroudsupportarenolonger required.

4.2.4.3 DeleteSection4.2.4.3,ReactorVesselSupportAssembly.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheReactorVesselSupport Assemblyarenolongerrequired..

4.2.4.4 DeleteSection4.2.4.4,VesselStabilizers.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheReactorVesselStabilizersarenolonger required.

4.2.4.5 DeleteSection4.2.4.5,RefuelingBellows.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepermissibletoloadanuclearcore.Consequently,thefunctionsofareactorvessel,includingtheRefuelingBellowsareno longerrequired.Therefore,theinformationprovidedregardingtherefuelingbellowsisnolongerrequiredandisconsideredobsolete.

4.2.4.6 DeleteSection4.2.4.6,ControlRodDriveHousings.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Consequently,thefunctionsofareactorvessel, includingtheControlRodDriveHousingsarenolongerrequired.

4.2.4.7 DeleteSection4.2.4.7,ControlRodDriveHousingSupports.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Consequently,thefunctionsofareactorvessel, includingtheControlRodDriveHousingsupportsarenolongerrequired.

4.2.4.8 DeleteSection4.2.4.8,IncoreNeutronFluxMonitorHousings.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.

Consequently,thefunctionsofareactorvessel,includingtheIncoreNeutronFluxMonitorHousingsarenolongerrequired.

4.2.4.9 DeleteSection4.2.4.9,ReactorVesselInsulation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.

Consequently,thefunctionsofareactorvessel,includingtheReactorVesselInsulationarenolongerrequired.

4.2.5 DeleteSection4.2.5,SafetyEvaluation.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,the functionsofareactorvesselarenolongerrequired.Therefore,asafetyevaluationofthereactorpressurevesselisnolongerrequiredandisobsoleteinformation.

4.2.6 DeleteSection4.2.6,InspectionandTesting.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,the functionsofareactorvesselarenolongerrequired.Therefore,inspectionandtestingoftheReactorPressureVesselisnolongerrequired.

SUMMARY

DESCRIPTION EquipmentWithinReactorCoolantPressure BoundaryComparisonWith10CFR50.55A REACTORVESSELANDAPPURTENANCES PowerGenerationObjectives PowerGenerationDesignBases InspectionandTesting RefuelingBellows ControlRodDriveHousings ControlRodDriveHousingSupports IncoreNeutronFluxMonitor Housings ReactorVesselInsulation SafetyEvaluation SafetyDesignBases Description ReactorVessel ShroudSupport ReactorVesseilSupportAssembly VesselStabilizers Page20of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.2.7 DeleteSection4.2.7,References.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Power operationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,thefunctionsof areactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistedreferencesnolongerapply.

Table4.2.1 DeleteTable4.2.1,ReactorPressureVesselMaterials.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.

Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistofReactorPressureVessel Materialsisobsoleteinformation.

Table4.2.2 DeleteTable4.2.2,ReactorVesselData.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.Consequently,the functionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistofReactorVesselDataisobsolete information Table4.2.3 DeleteTable4.2.3,ReactorVesselAttachments.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.

Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,thelistofReactorVessel Attachmentsisobsoleteinformation Table4.2.4 DeleteTable4.2.4,SurveillanceCapsuleRemovalSchedule.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Poweroperationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Allcontrolrodshavebeenremoved.Allnuclearinstrumentationhasbeenremoved.

Consequently,thefunctionsofareactorvesselarenolongerrequired.InspectionandtestingoftheReactorPressureVesselisnolongerrequired.Therefore,theSurveillanceCapsuleRemoval Scheduleisobsoleteinformation.

Figure4.21 DeleteFigure4.2.1,ReactorVessel.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Power generationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,theinformationprovidedon Figure4.2.1,ReactorVesselisnolongerapplicable.Informationregardingthereactorvesselisobsolete.

Figure4.22 DeleteFigure4.2.2,ReactorVesselNozzlesandPenetrations.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,the informationprovidedonFigure4.2.2,ReactorVesselnozzlesandpenetrationsisnolongerapplicable.Informationregardingthereactorvesselisobsolete.

Figure4.23 DeleteFigure4.2.3,ChangeinNDTTVersusNeutronExposure.PostcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Powergenerationcannolongeroccurnorwillitbepossibletoloadanuclearcore.Consequently,thefunctionsofareactorvesselarenolongerrequired.Therefore,the informationprovidedonFigure4.2.3,ChangeinNDTTVersusNeutronExposureisnolongerapplicable.Informationregardingthereactorvesselisobsolete.

Figure4.24 PreviouslyDeleted 4.3 TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

4.3.1 DeleteSection4.3.1,PowerGenerationObjectives.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.ReactorRecirculationSysteminformationisobsolete.

4.3.2 DeleteSection4.3.2,PowerGenerationDesignBasis.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.ReactorRecirculationSysteminformationisobsolete.

4.3.3 DeleteSection4.3.3,SafetyDesignBasis.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.ReactorRecirculationSysteminformationisobsolete.

References ReactorPressureVesselMaterials ReactorVesselData ReactorVesselAttachments SurveillanceCapsuleRemovalSchedule PowerGenerationDesignBasis SafetyDesignBasis ReactorVessel ReactorVesselNozzlesandPenetrations ChangeinNDTTVersusNeutronExposure Deleted REACTORRECIRCULATIONSYSTEM PowerGenerationObjectives Page21of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.3.4 DeleteSection4.3.4,Description.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.ReactorRecirculationSysteminformationisobsolete.

4.3.5 DeleteSection4.3.5,SafetyEvaluation.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,aReactorRecirculationSafetyEvaluationisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.

4.3.6 DeleteSection4.3.6,InspectionandTesting.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,inspectionandtestingoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminspectionandtestinginformationisobsolete.

4.3.7 DeleteSection4.3.7,SafetyEvaluation.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,ReactorRecirculationSystemreferencesarenolongerrequired.ReactorRecirculationSystemreferencesinformationisobsolete.

Table4.3.1 DeleteTable4.3.1,ReactorRecirculationSystemDesignCharacteristics.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,ReactorRecirculationSystemDesignCharacteristicsinformationisobsolete.

Figure4.31 DeleteFigure4.31,RecirculationSystemElevation,Isometric.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,theinformationprovidedonFigure4.31isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.

Figure4.32 DeleteFigure4.32,NuclearBoiler,PipingandInstrumentationDiagram.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,theinformationprovidedonFigure4.32isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.

ReactorRecirculationSystemDesign Characteristics RecirculationSystemElevation,Isometric NuclearBoiler,PipingandInstrumentation DiagramG191167 Description SafetyEvaluation InspectionandTesting SafetyEvaluation Page22of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure4.33 DeleteFigure4.33,RecirculationPumpPipingandInstrumentationDiagram.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,theinformationprovidedonFigure4.33isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.

Figure4.34 DeleteFigure4.34,JetPumpOperatingPrinciple.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,theinformationprovidedonFigure4.34isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.

Figure4.35 DeleteFigure4.35,RecirculationSystemCoreFloodingCapability.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactorRecirculationSystemareno longerrequired.Therefore,theinformationprovidedonFigure4.35isnolongerapplicable.ReactorRecirculationSysteminformationisobsolete.

4.4 4.4.1 DeleteSection4.4.1,PowerGenerationObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.

4.4.2 DeleteSection4.4.2,SafetyObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofa NuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.

4.4.3 DeleteSection4.4.3,PowerGenerationDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete 4.4.4 DeleteSection4.4.4,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Consequently,depressurizationisnotrequired Therefore,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.

4.4.5 DeleteSection4.4.5,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsof NuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminformationisobsolete.

4.4.6 DeleteSection4.4.6,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,the functionsofaNuclearSystemPressureReliefSystemarenolongerrequired.ANuclearSystemPressureReliefSystemsafetyevaluationisnotrequired,theNuclearSystemPressureRelief systeminformationisobsolete.

4.4.7 DeleteSection4.4.7,PowerGnerationEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.

Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.ANuclearSystemPressureReliefSystempowergenerationevaluationisnotrequired,the NuclearSystemPressureReliefsysteminformationisobsolete.

4.4.8 DeleteSection4.4.8,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.

Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.NuclearSystemPressureReliefSysteminspectionandtestingisnotrequired,theNuclear SystemPressureReliefsysteminformationisobsolete.

RecirculationPumpPipingandInstrumentation DiagramG191159,Sh5 JetPumpOperatingPrinciple RecirculationSystemCoreFloodingCapability SafetyEvaluation PowerGenerationEvaluation InspectionandTesting NuclearSystemPressureReliefSystem PowerGenerationObjectives SafetyObjectives PowerGenerationDesignBases SafetyDesignBases Description Page23of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.4.9 DeleteSection4.4.9,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.Consequently,thefunctionsof NuclearSystemPressureReliefSystemarenolongerrequired.ANuclearSystemPressureReliefSystemreferencesnolongerapply;theNuclearSystemPressureReliefsysteminformationis obsolete.

Table4.4.1 DeleteTable4.4.1,NuclearSystemSafetyandReliefValves.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolongerrequired.

Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired.TheNuclearSystemPressureReliefsysteminformationisobsolete.

Figure4.41 DeleteFigure4.41,NuclearSystemPressureReliefSystem,PipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.

Depressurizationisnolongerrequired.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired,theinformationprovidedonfigure4.41isnolonger applicable.NuclearSystemPressureReliefSysteminformationisobsolete.

Figure4.42 DeleteFigure4.42,NuclearSystemReliefValveClosedPosition.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolonger required.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired,theinformationprovidedonfigure4.42isnolongerapplicable.NuclearSystem PressureReliefSysteminformationisobsolete.

Figure4.43 DeleteFigure4.43,NuclearSystemReliefValveOpenPosition.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandtheRPVcannotbepressurized.Depressurizationisnolonger required.Consequently,thefunctionsofaNuclearSystemPressureReliefSystemarenolongerrequired,theinformationprovidedonfigure4.43isnolongerapplicable.NuclearSystem PressureReliefSysteminformationisobsolete.

Figure4.44 PreviouslyDeleted 4.5 4.5.1 1.Deletesection4.5.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,the functionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorinformationisobsolete.

4.5.2 2.Deletesection4.5.2,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,the functionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorinformationisobsolete.

4.5.3 3.Deletesection4.5.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,thefunctionsofMain SteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorinformationisobsolete.

4.5.4 4.Deletesection4.5.4,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,the functionsofMainSteamLineFlowRestrictorsarenolongerrequired.AMainSteamLineFlowRestrictorSafetyEvaluationisnotrequired.MainSteamLineFlowRestrictorinformationis obsolete.

4.5.5 5.Deletesection4.5.5,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently,the functionsofMainSteamLineFlowRestrictorsarenolongerrequired.MainSteamLineFlowRestrictorInspectionandTestingisnotrequired.MainSteamLineFlowRestrictorinformationis obsolete.

Figure4.51 DeleteFigure4.51,MainSteamlineFlowRestrictorLocation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur,steamcannotbegenerated,asteamlinebreakcannotoccur.Consequently, thefunctionsofMainSteamLineFlowRestrictorsarenolongerrequired.Therefore,theinformationprovidedonfigure4.51isnolongerapplicable.MainSteamLineFlowRestrictor informationisobsolete.

4.6 4.6.1 1.DeleteSection4.6.1,SafetyObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thesafetyobjectivesoftheMainSteamIsolationValvesarenot requiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.InformationregardingtheMainSteamIsolationValvesisobsolete.

4.6.2 2.DeleteSection4.6.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thesafetyDesignBasesoftheMainSteamIsolationValvesare notrequiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.InformationregardingtheMainSteamIsolationValvesisobsolete.

NuclearSystemReliefValveClosedPosition NuclearSystemReliefValveOpenPosition PreviouslyDeleted MAINSTEAMLINEFLOWRESTRICTOR SafetyObjective SafetyDesignBases References NuclearSystemSafetyandReliefValves NuclearSystemPressureReliefSystem,Piping andInstrumentationDiagramG191167 SafetyDesignBases Description SafetyDesignBases InspectionandTesting MainSteamlineFlowRestrictorLocation MAINSTEAMLINEISOLATIONVALVES SafetyObjectives Page24of153 toPADandLBDCRforDSARRev0(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,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiring MainSteamIsolationValveactuationcannolongeroccur.InformationregardingtheMainSteamIsolationValvesisobsolete 4.6.4 4.DeleteSection4.6.4,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincethe conditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.AnMSIVsafetyevaluationisnotrequired.InformationregardingtheMainSteamIsolationValvesisobsolete.

4.6.5 5.DeleteSection4.6.5,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincethe conditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.MSIVinspectionandtestingisnotrequired.InformationregardingtheMainSteamIsolationValvesisobsolete 4.6.6 6.DeleteSection4.6.6,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenotrequiredsincetheconditionsrequiring MainSteamIsolationValveactuationcannolongeroccur;referencesnolongerapply.InformationregardingtheMainSteamIsolationValvesisobsolete.

Figure4.61 DeleteFigure4.61,RockwellMainSteamIsolationValveCrossSection.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesarenot requiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.Therefore,theinformationprovidedonFigure4.61isnolongerapplicable.Information regardingtheMainSteamIsolationValvesisobsolete Figure4.62 DeleteFigure4.62,MainSteamLineIsolationValve,SchematicControlDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,theMainSteamIsolationValvesareno requiredsincetheconditionsrequiringMainSteamIsolationValveactuationcannolongeroccur.Therefore,theinformationprovidedonFigure4.62isnolongerapplicable.Information regardingtheMainSteamIsolationValvesisobsolete 4.7 4.7.1 Deletesection4.7.1,PowerGenerationObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

4.7.2 Deletesection4.7.2,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthe ReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

4.7.3 Deletesection4.7.3,PowerGenerationDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

4.7.4 Deletesection4.7.4,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

4.7.5 Deletesection4.7.5,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthe ReactorCoreIsolationCoolingSystemarenolongerrequired;aRCICsafetyevaluationisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

4.7.6 Deletesection4.7.6,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthe ReactorCoreIsolationCoolingSystemarenolongerrequired;aRCICsafetyevaluationisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

4.7.7 Deletesection4.7.7,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired;RCICinspectionandtestingisnotrequired.ReactorCoreIsolationCoolingSysteminformationisobsolete.

MainSteamLineIsolationValve,Schematic ControlDiagram59206766 REACTORCOREISOLATIONCOOLINGSYSTEM PowerGenerationObjectives SafetyObjective PowerGenerationDesignBasis SafetyDesignBases Description SafetyEvaluation InspectionandTesting References RockwellMainSteamIsolationValveCross Section59202038,sh.5 Description SafetyEvaluation InspectionandTesting Page25of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table4.7.1 DeleteTable4.7.1,ReactorCoreIsolationCoolingSystemTurbinePumpDesignData.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.RCICsystemTurbinePumpDesignDataisnotrequired.ReactorCoreIsolation CoolingSysteminformationisobsolete.

Figure4.71a DeleteFigure4.71a,ReactorCoreIsolationCoolingSystem,PipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.71aisnolonger applicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.

Figure4.71b DeleteFigure4.71b,ReactorCoreIsolationCoolingSystem,PipingandInstrumentationDiagram,sheet2.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.71bisnolonger applicable.ReactorCoreIsolationCoolingSysteminformationisobsolete.

Figure4.72a DeleteFigure4.72a,ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.72aisnolongerapplicable.Reactor CoreIsolationCoolingSysteminformationisobsolete.

Figure4.72b DeleteFigure4.72b,ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.72bisnolongerapplicable.Reactor CoreIsolationCoolingSysteminformationisobsolete.

Figure4.72c DeleteFigure4.72c,ReactorCoreIsolationCoolingSystem,FunctionalControlDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.72bisnolongerapplicable.Reactor CoreIsolationCoolingSysteminformationisobsolete.

Figure4.73 DeleteFigure4.73,ReactorCoreIsolationCoolingSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheReactorCoreIsolationCoolingSystemarenolongerrequired.Theinformationprovidedonfigure4.72bisnolongerapplicable.ReactorCoreIsolation CoolingSysteminformationisobsolete.

4.8 TheRHRsystemremoveddecayheatandresidualheatfromthenuclearsystemsothatrefuelingandnuclearsystemservicingcanbeperformed,andsupplementedtheFuelPoolCooling Systemwhennecessarytoprovideadditionalcoolingcapacity.

4.8.1 Deletesection4.8.1,ResidualHeatRemovalSystem,PowerGenerationObjectives.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,removalofdecayandresidualheatisnolongerrequired.SinceaLOCAisnolongerpossible,postthepostLOCAfunctionsofRHRarealsonolongerrequired.

Additionally,theirradiatedfueldecayheatloadinthefuelpooliswithinthecapacityoffuelpoolcooling,heatremovalsupplementationbytheRHRsystemisnolongerrequired.Therefore, thepowergenerationobjectivesarenolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.

4.8.2 Deletesection4.8.2,ResidualHeatRemovalSystem,SafetyObjectives.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired.

Therefore,thesafetyobjectivesarenolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.

4.8.3 Deletesection4.8.3,ResidualHeatRemovalSystem,PowerGenerationDesignBasis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,removalofdecayandresidualheatisnolongerrequired.Additionally,theirradiatedfueldecayheatloadinthefuelpooliswithinthecapacityoffuelpoolcooling,hea removalsupplementationbytheRHRsystemisnolongerrequired.Therefore,anadditionalsourceofwaterforcontainmentfloodingisnotrequired,theRHRpowergenerationdesignbasisis nolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.

4.8.4 Deletesection4.8.2,ResidualHeatRemovalSystem,SafetyObjectives.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired.

Therefore,thesafetydesignbasesarenolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.

4.8.5 Deletesection4.8.5,ResidualHeatRemovalSystem,Description.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheRHRsystemarenolongerrequired.Therefore,theinformationprovidedinthedescriptionsectionisnolongerapplicable.ResidualHeatRemovalSystem informationisobsolete.

PowerGenerationObjectives SafetyObjectives PowerGenerationDesignBasis ReactorCoreIsolationCoolingSystem,Functional ControlDiagram592025 ReactorCoreIsolationCoolingSystem,Functional ControlDiagram592026 ReactorCoreIsolationCoolingSystem,Functional ControlDiagram5920490 ReactorCoreIsolationCoolingSystem,Process Diagram5920605 RESIDUALHEATREMOVALSYSTEM ReactorCoreIsolationCoolingSystemTurbine PumpDesignData ReactorCoreIsolationCoolingSystem,Pipingand InstrumentationDiagramG191174,Sh1 ReactorCoreIsolationCoolingSystemPipingand InstrumentationDiagram, Sheet2G191174,Sh2 SafetyDesignBases Description Page26of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 4.8.5.1 Deletesection4.8.5.1,DescriptionoftheShutdownCoolingmodeofoperationofRHR.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequentlyareactorshutdownandcooldownwillnolongerbeconducted.Therefore,theShutdownCoolingfunctionsoftheRHRsystemarenolongerrequired.ResidualHeat RemovalSysteminformationisobsolete.

4.8.5.2 Deletesection4.8.5.2,DescriptionoftheContainmentCoolingmodeofoperationofRHR.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,heatremovalfromthesuppressionpoolfollowingaLOCAisnolongerrequired.Therefore,theContainmentCoolingfunctionsoftheRHRsystemarenolonger required.ResidualHeatRemovalSysteminformationisobsolete.

4.8.5.3 Deletesection4.8.5.3,DescriptionoftheLowPressureCoolantInjectionmodeofoperationofRHR.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,restorationand,maintenanceofthecoolantinventoryinthereactorvesselafteralossofcoolantaccidentisnolongerrequired.Therefore,the LowPressureCoolantInjectionfunctionsoftheRHRsystemarenolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.

4.8.6 Deletesection4.8.6,ResidualHeatRemovalSystem,SafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

SincethefunctionsoftheRHRsystemarenolongerrequiredasafetyevaluationisalsonolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.

4.8.7 Deletesection4.8.7,ResidualHeatRemovalSystem,InspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Therefore,thefunctionsoftheRHRsystemarenolongerrequired,inspectionandtestingoftheRHRsystemisalsonolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.

Table4.8.1 DeleteTable4.8.1,ResidualHeatRemovalSystemEquipmentDesignData.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Therefore,thefunctionsoftheRHRsystemarenolongerrequired.TheinformationprovidedinTable4.8.1isnolongerrequired.ResidualHeatRemovalSysteminformationisobsolete.

Figure4.81 DeleteFigure4.81,ResidualHeatRemovalSystemProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheRHRsystemarenolongerrequired.Therefore,theinformationprovidedonFigure4.81isnolongerapplicable.ResidualHeatRemovalSysteminformation isobsolete.

Figure4.82 DeleteFigure4.82,ResidualHeatRemovalSystem,Pipingand InstrumentationDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheRHRsystemare nolongerrequired.Therefore,theinformationprovidedonFigure4.82isnolongerapplicable.ResidualHeatRemovalSysteminformationisobsolete.

4.9 4.9.1 Deletesection4.9.1,PowerGenerationObjectives.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorWaterCleanupSystemarenolongerrequired.ReactorWaterCleanupSysteminformationisobsolete.

4.9.2 Deletesection4.9.2,PowerGenerationDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorWaterCleanupSystemarenolongerrequired.ReactorWaterCleanupSysteminformationisobsolete.

4.9.3 Deletesection4.9.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsoftheReactor WaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigationMonitoringSystemdoesnotrequireflow fromthecleanupsystem.ReactorWaterCleanupSysteminformationisobsolete.

4.9.4 Deletesection4.9.4,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheReactorWaterCleanupSystemarenolongerrequired;inspectionandtestingoftheReactorWaterCleanupSystemisnotrequired.ReactorWaterCleanupSysteminformation isobsolete.

Table4.9.1 5.DeleteTable4.9.1,ReactorWaterCleanupSystemEquipmentDesignData.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.ReactorWaterCleanupSysteminformationisobsolete.

ResidualHeatRemovalSystemEquipmentDesign Data ResidualHeatRemovalSystemProcess Diagram5920725 ResidualHeatRemovalSystem,Pipingand InstrumentationDiagramG191172 REACTORWATERCLEANUPSYSTEM PowerGenerationObjectives PowerGenerationDesignBases ContainmentCoolingSubsystem LowPressureCoolantInjection Subsystem SafetyEvaluation InspectionandTesting ShutdownCoolingSubsystem Description InspectionandTesting ReactorWaterCleanupSystemEquipmentDesign Page27of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure4.91 DeleteFigure4.91,ReactorWaterCleanupSystemPipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenota concern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.91isnolongerapplicable.ReactorWaterCleanup Systeminformationisobsolete.

Figure4.92 DeleteFigure4.92,ReactorWaterCleanupSystemProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,theMitigation MonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.92isnolongerapplicable.ReactorWaterCleanupSysteminformationis obsolete.

Figure4.93 DeleteFigure4.93,ReactorWaterCleanupFilterDemineralizerSystem,PipingandInstrumentDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotential arenotaconcern,theMitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.93isnolongerapplicable.ReactorWater CleanupSysteminformationisobsolete.

Figure4.94 DeleteFigure4.94,ReactorWaterCleanupSystemFunctionalControlDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsoftheReactorWaterCleanupSystemarenolongerrequired.Sincenoblemetaldurabilityandelectrochemicalcorrosionpotentialarenotaconcern,the MitigationMonitoringSystemdoesnotrequireflowfromthecleanupsystem.Therefore,theinformationprovidedonFigure4.94isnolongerapplicable.ReactorWaterCleanupSystem informationisobsolete.

4.10 4.10.1 Deletesection4.10.1,SafetyObjective.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthe NuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.

4.10.2 Deletesection4.10.2,SafetyDesignBasis.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.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.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Determinationof IdentifiedLeakageratesisnolongerrequired.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetection Systemsinformationisobsolete.

4.10.3.2 Deletesection4.10.3.2,UnidentifiedLeakageRate.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Determinationof IdentifiedLeakageratesisnolongerrequired.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetection Systemsinformationisobsolete.

4.10.3.3 Deletesection4.10.3.3,TotalLeakageRate.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Determinationof TotalLeakageratesisnolongerrequired.Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystems informationisobsolete.

4.10.4 Deletesection4.10.4,ActionsUponDiscoveryofaLeak.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.Therefore,noactionsarerequiredsincenoleakagewilloccur.Allleakagelimitshavebeenremovedfrom Permanentlydefueledtechnicalspecifications.NuclearSystemLeakageDetectionSystemsinformationisobsolete.

Table4.10.1 DeleteTable4.10.1,LeakageandDrainageInputstoDrywellsumps.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsoftheNuclearSystemLeakageDetectionSystemsarenolongerrequired.NuclearSystemLeakageDetectionSystemsinformationisobsolete.

Figure4.101 Nochanges Figure4.5.2 4

DrywellSumpsDiagramG191177,Sh1 UnidentifiedLeakageRate TotalLeakageRate ActionsUponDiscoveryofaLeak LeakageandDrainageInputstoDrywellsumps DrywellSumpsDiagramG191177,Sh1 ReactorWaterCleanupSystemFunctional ControlDiagram59203867 NUCLEARSYSTEMLEAKAGERATELIMITSANDLEAKAGE DETECTIONSYSTEMS SafetyObjectiver SafetyDesignBases Description IdentifiedLeakageRate ReactorWaterCleanupSystemPipingand InstrumentationDiagramG191178,Sh1 ReactorWaterCleanupSystemProcessDiagram 5920429 ReactorWaterCleanupFilterDemineralizer System,PipingandInstrumentDiagramG 191178,Sh2 Page28of153 toPADandLBDCRforDSARRev0(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.See sections5.2,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,thefunctionsofthe PrimaryContainmentSystemarenolongerrequired.PrimaryContainmentSysteminformationisobsolete.

5.2.2 Deletesection5.2.2,SafetyDesignBases.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofthePrimaryContainmentSystemarenolongerrequiredandthesafetydesignbasesarenolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

5.2.3 Deletesection5.2.3,Description.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimary ContainmentSystemarenolongerrequired.TheinformationprovidedintheDescriptionsectionisnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

5.2.4 Deletesection5.2.4,SafetyEvaluation.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).

Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthe PrimaryContainmentSystemarenolongerrequired.Aprimarycontainmensafetyevaluaionisnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

5.2.5 Deletesection5.2.5,InspectionandTesting.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofthePrimaryContainmentSystemarenolongerrequired.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,NitrogenSupplySystemInspectionand Testinghavebeendeleted.

5.2.6.1 Deletesection5.2.6.1,PrimaryContainmentInertingSafetyDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.PrimaryContainment InertingSysteminformationisobsolete.

5.2.6.2 Deletesection5.2.6.2,PrimaryContainmentInertingSystemDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.Theinformation providedinthePrimaryContainmentInertingSystemDescriptionsectionisnolongerapplicable.PrimaryContainmentInertingSysteminformationisobsolete.

5.2.6.3 Deletesection5.2.6.3,PrimaryContainmentInertingSystemSafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.The informationprovidedinthePrimaryContainmentInertingSystemSafetyEvaluationsectionisnolongerapplicable.PrimaryContainmentInertingSysteminformationisobsolete.

5.2.6.4 Deletesection5.2.6.4,NitrogenSupplySystemInspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentInertingsystemisalsonolongerrequired.Theinformation providedintheNitrogenSupplySystemInspectionandTestingsectionisnolongerapplicable.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,Safety Evaluationand5.2.7.5,ContainmentAtmosphericDilution(CAD)SystemInspectionandTestinghavebeendeleted.

5.2.7.1 DeleteSection5.2.7.1,ContainmentAtmosphericDilution(CAD)SystemSafetyDesignBasis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolonger required.TheinformationprovidedintheContainmentAtmosphericDilutionSafetyDesignBasissectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationis obsolete.

Containment SafetyEvaluation InspectionandTesting PrimaryContainmentInerting SafetyDesignBasis SystemDescription SafetyEvaluation SecondaryContainment PRIMARYCONTAINMENTSYSTEM SafetyObjective SafetyDesignBases Description

SUMMARY

DESCRIPTION General PrimaryContainment NSSInspectionandTesting ContainmentAtmosphereDilutionSystem SafetyDesignBasis Page29of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.2.7.2 DeleteSection5.2.7.2,ContainmentAtmosphericDilution(CAD)SystemDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.

TheinformationprovidedintheContainmentAtmosphericDilutionSystemDescriptionsectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.

5.2.7.3 DeleteSection5.2.7.3,ContainmentAtmosphericDilution(CAD)SystemOperation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.

TheinformationprovidedintheContainmentAtmosphericDilutionSystemOperationsectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.

5.2.7.4 DeleteSection5.2.7.4,ContainmentAtmosphericDilution(CAD)SystemOperation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.

TheinformationprovidedintheContainmentAtmosphericDilutionSystemSafetyEvaluationsectionisnolongerapplicable.ContainmentAtmosphericDilutionSysteminformationisobsolete.

5.2.7.5 DeleteSection5.2.7.5,ContainmentAtmosphericDilution(CAD)SystemInspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsare nolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,thePrimaryContainmentAtmosphericDilutionsystemisalsonolonger required.TheinformationprovidedintheContainmentAtmosphericDilutionSystemInspectionandTestingsectionisnolongerapplicable.

5.2.8 DeleteSection5.2.8,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired,therefore,the PrimaryContainmentAtmosphericDilutionsystemisalsonolongerrequired.TheinformationprovidedintheContainmentAtmosphericDilutionSystemReferencessectionisnolonger applicable.

Table5.2.1 DeleteTable5.2.1,PrincipalDesignParametersofPrimaryContainment.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired;theinformationprovidedinTable5.2.1isnolongerapplicable.

Table5.2.2 DeleteTable5.2.2,PrimaryContainmentSystemPenetrationsandAssociatedContainmentIsolationValves.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorized toemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired;theinformationprovidedinTable5.2.2isnolongerapplicable.

Figure5.21 DeleteFigure5.21,PrimaryContainmentVessels.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationprovidedonfigure5.21isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

Figure5.22 DeleteFigure5.22,PrimaryContainmentSystemPipingandInstrumentationDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingprimarycontainmentsystempipingandinstrumentationprovided onfigure5.22isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

Figure5.23 DeleteFigure5.23,TypesofPenetrationsforProcessLines.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently, thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingtypesofprimarycontainmentpenetrationsforprocesslinesprovidedonfigure5.23isno longerapplicable.PrimaryContainmentSysteminformationisobsolete.

Figure5.24 DeleteFigure5.24,PenetrationAssemblyforProcessLines.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel IAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently, thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingpenetrationassembliesforprocesslinesprovidedonfigure5.24isnolongerapplicable.

PrimaryContainmentSysteminformationisobsolete.

Figure5.25 DeleteFigure5.25,ElectricalandControlPenetrations.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingelectricalandcontrolcontainmentpenetrationsprovidedonfigure5.25isnolonger applicable.PrimaryContainmentSysteminformationisobsolete.

TypesofPenetrationsforProcessLines PenetrationAssemblyforProcessLines ElectricalandControlPenetrations SystemInspectionandTesting References PrincipalDesignParametersofPrimary Containment PrimaryContainmentSystem PenetrationsandAssociatedContainment IsolationValves PrimaryContainmentVessels592045 PrimaryContainmentSystemPipingand InstrumentationDiagramG191175,Sh1 SystemDescription SystemOperation SafetyEvaluation Page30of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure5.26 DeleteFigure5.26,EnergyAbsorberDetailInstalledAgainstDrywell.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingenergyabsorberinstalledagainstthedrywell,providedonfigure5.26,isno longerapplicable.PrimaryContainmentSysteminformationisobsolete.

Figure5.27 DeleteFigure5.27,NitrogenSupplySubsystemPrimaryContainmentAtmosphereControlSystem.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingthecontainmentinertingnitrogensupply subsystem,providedonfigure5.27,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

Figure5.28 DeleteFigure5.28,EngineeringFlowDiagramContainmentAtmosphereDilutionSystem.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingthecontainmentcontainmentatmospheredilution subsystem,providedonfigure5.28,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

Figure5.29 DeleteFigure5.29,DrywellTemperatureResponsetoSmallSteamLineBreaks.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Consequently,thefunctionsofthePrimaryContainmentSystemarenolongerrequired.Theinformationregardingthetemperatureresponsetosmallsteamlinebreaksinthedrywel providedonfigure5.29,isnolongerapplicable.PrimaryContainmentSysteminformationisobsolete.

5.3 5.3.1 DeleteSection5.3.1,SecondaryContainmentSystemSafetyObjective.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015, eliminatedoperabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiation instrumentationwhenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesin secondarycontainmentandduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.Consequently,the SecondaryContainmentsafetyobjectiveisnotapplicable.SecondaryContainmentinformationisobsolete.

5.3.2 DeleteSection5.3.2,SecondaryContainmentSystemGeneral.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatsecondarycontainmentisnolonger requiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,theinformationprovidedintheSecondaryContainmentGeneralsection isnotapplicable.SecondaryContainmentinformationisobsolete.

5.3.3 5.3.3.1 DeleteSection5.3.3.1,ReactorBuildingSecondaryContainmentSafetyObjective.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdufuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theReactorBuildingSafetyObjectiveisnotapplicable.SecondaryContainmentinformationisobsolete.

EnergyAbsorberDetailInstalledAgainst Drywell NitrogenSupplySubsystemPrimary ContainmentAtmosphereControlSystemG 191175,Sh2 EngineeringFlowDiagramContainment AtmosphereDilutionSystem(CAD)VYE75002 DrywellTemperatureResponsetoSmall SteamLineBreaks SECONDARYCONTAINMENTSYSTEM SafetyObjective General ReactorBuilding SafetyObjective Page31of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.3.2 DeleteSection5.3.3.2,ReactorBuildingSecondaryContainmentSafetyDesignBasis.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdufuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theReactorBuildingSafetyDesignBasisisnotapplicable.SecondaryContainmentinformationis obsolete.

5.3.3.3 DeleteSection5.3.3.3,ReactorBuildingSecondaryContainmentDescription.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.Consequently,theinformationprovidedinthe ReactorBuildingDescriptionSectionisnotapplicable.SecondaryContainmentinformationisobsolete.

5.3.3.4 DeleteSection5.3.3.4,ReactorBuildingSecondaryContainmentSafetyEvaluation.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatthesecondarycontainmentfunctionofthe ReactorBuildingisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,asafetyevaluationoftheReactorBuilding SecondaryContainmentfunctionisnolongerrequired.SecondaryContainmentinformationisobsolete.

5.3.3.5 DeleteSection5.3.3.5,ReactorBuildingSecondaryContainmentInspectionandTesting.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatthesecondarycontainmentfunctionofthe ReactorBuildingisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,ainspectionandtestingoftheReactor BuildingSecondaryContainmentfunctionisnolongerrequired.SecondaryContainmentinformationisobsolete.

5.3.4 TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

5.3.4.1 DeleteSection5.3.4.1,StandbyGasTreatmentSystemSafetyObjective.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theStandbyGasTreatmentSystemSafetyObjectiveisnotapplicable.SecondaryContainment informationisobsolete.

SafetyDesignBasis Description SafetyEvaluation InspectionandTesting StandbyGasTreatmentSystem SafetyObjective Page32of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.4.2 DeleteSection5.3.4.2,StandbyGasTreatmentSystemSafetyDesignBasis.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theStandbyGasTreatmentSystemSafetyDesignBasisisnotapplicable.SecondaryContainment informationisobsolete.

5.3.4.3 DeleteSection5.3.4.3,StandbyGasTreatmentSystemDescription.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theinformationprovidedintheStandbyGasTreatmentDescriptionSectionisnolongerapplicable.

SecondaryContainmentinformationisobsolete.

5.3.4.4 DeleteSection5.3.4.4,StandbyGasTreatmentSystemSafetyEvaluation.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,asafetyevaluationoftheStandbyGasTreatmentSystemisno longerrequired.SecondaryContainmentinformationisobsolete.

5.3.4.5 DeleteSection5.3.4.5,StandbyGasTreatmentSystemInspectionandTesting.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,inspectionandtestingoftheStandbyGasTreatmentSystemisno longerrequired.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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,theRBHVACsafetydesignbasisisnolongerrequired.

5.3.5.4 ModifySection5.3.5.4,RBHVACDescriptiontoremovereferencetoplantoperation,accidentsandotherconditionswhicharenolongerapplicable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheRBHVACsystemto addressthoseconditionsarenolongerrequired.Informationmovedtosection10.12.3.1,RBNormalHVAC SafetyDesignBasis Description SafetyEvaluation InspectionandTesting ReactorBuildingNormalHVAC Description PowerGenerationObjective PowerGenerationDesignBasis Safety Design Basis Page33of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.5.5 DeleteSection5.3.5.5,RBHVACSafetyEvaluation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,asafetyevaluationoftheRBHVACsystemisnolongerrequired.

5.3.5.6 ModifySection5.3.5.4,RBHVACDescriptiontoremovereferencetoplantoperation,accidentsandotherconditionswhicharenolongerapplicable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheRBHVACsystemto addressthoseconditionsarenolongerrequired.InspectionandtestingoftheRBHVACsystemwillbeconductedasappropriateforthedefueledstate.Informationmovedtosection10.12.3.1 RBNormalHVAC 5.3.6 ReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasisaccident.

5.3.6.1 DeleteSection5.3.6.1,ReactorBuildingPenetrationsSafetyObjective.

TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasis accident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,thesafetyobjectiveoftheRBPenetrationsystemisnolongerapplicable.RBPenetrationSystem informationisobsolete.

5.3.6.2 DeleteSection5.3.6.2,ReactorBuildingPenetrationsSafetyDesignBasis TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasis accident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequired tomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,thesafetydesignbasisoftheRBPenetrationsystemisnolongerapplicable.RB PenetrationSysteminformationisobsolete.

5.3.6.3 DeleteSection5.3.6.3,ReactorBuildingPenetrationsDescription.

TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasis accident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequired tomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,theinformationprovidedintheRBPenetrationDescriptionsectionislonger applicable.RBPenetrationSysteminformationisobsolete.

5.3.6.4 DeleteSection5.3.6.4,ReactorBuildingPenetrationsSafetyEvaluation.

TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasis accident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequired tomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,asafetyevaluationoftheRBPenetrationsystemislongerrequired.RBPenetration Systeminformationisobsolete.

5.3.6.5 DeleteSection5.3.6.5,ReactorBuildingPenetrationsInspectionandTesting.

TheReactorBuildingpenetrationsprovidedarelativelytightsecondarycontainmentsuchthatgroundlevelreleaseofradioactivematerialswasminimizedintheeventofadesignbasis accident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheRBPenetrationsarenolongerrequired tomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,inspectionandtestingoftheRBPenetrationsystemislongerrequired.RB PenetrationSysteminformationisobsolete.

5.3.7 TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

ReactorBuildingPenetrations SafetyObjective SafetyDesignBasis Description SafetyEvaluation InspectionandTesting SafetyEvaluation InspectionandTesting MSIVAlternateLeakageTreatmentPath Page34of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.7.1 DeleteSection5.3.7.1,MSIVALTPath,Background.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.Therefore,ALTrelatedinformationisobsolete.

5.3.7.2 DeleteSection5.3.7.2,MSIVALTPath,SafetyObjective.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.TheALTsafetyobjectiveisnolongerapplicable.ALTrelatedinformationisobsolete.

5.3.7.3 DeleteSection5.3.7.3,MSIVALTPath,SafetyDesignBases TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.TheALTsafetydesignbasesarenolongerapplicable.ALTrelatedinformationisobsolete.

5.3.7.4 DeleteSection5.3.7.4,MSIVALTPath,Description.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.TheinformationprovidedintheALTdescriptionsectionisnolongerapplicable.ALTrelatedinformationisobsolete.

5.3.7.5 DeleteSection5.3.7.5,MSIVALTPath,SafetyEvaluation.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.Therefore,asafetyevaluationoftheALTpathisnolongerrequired.ALTpathrelatedinformationisobsolete.

5.3.7.6 DeleteSection5.3.7.6,MSIVALTPath,SeismicVerification.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.Therefore,thesystemsintheALTpathwayarenolongerrequiredtobeseismictosupporttheALTfunction.ALTpathrelated informationisobsolete.

5.3.7.7 DeleteSection5.3.7.7,MSIVALTPath,RadiologicalAnalysis.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.Therefore,aRadiologicalAnalysisoftheeffectivenessoftheALTpathduringaDBAisnolongerrequired.ALTpathrelated informationisobsolete.

5.3.7.8 DeleteSection5.3.7.8,MSIVALTPath,InspectionandTesting.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.Therefore,inspectionandtestingofthecomponentsintheALTpathisnolongerrequired.ALTpathrelatedinformationis obsolete.

SeismicVerification RadiologicalAnalysis InspectionandTesting

Background

SafetyObjective SafetyDesignBases Description SafetyEvaluation Page35of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 5.3.8 DeleteSection5.3.8,SecondaryContainmentSystemReferences.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationsarenolongerpossibleandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatsecondarycontainmentisnolonger requiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.consequently,theSecondaryContainmentreferencesarenolongerapplicable.

SecondaryContainmentinformationiaobsolete.

Table5.3.1 DeleteTable5.3.1,StandbyGasTreatmentSystem,ReactorBuildingVacuumDataWithOneSGTTrainOperating.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.consequently,theinformationprovidedintable5.3.1isnotapplicablesinceSBGT isnolongerreliedontomitigatetheconsequencesofafuelhandlingaccidentand.therefore,willnolongerbeoperated.SecondaryContainmentinformationisobsolete.

Figure5.31 DeleteFigure5.31,SecondaryContainmentSystem-ReactorBuilding-CalculatedExfiltrationRateVersusWindVelocity.

SecondaryContainmentminimizedthegroundlevelreleaseofairborneradioactivematerialsandprovidedameansforacontrolledreleaseofthebuildingatmosphereshouldadesignbasis accidentoccur.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatthesecondarycontainmentfunctionofthe ReactorBuildingisnolongerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,theinformationprovidedonFigure5.31is notapplicable.SecondaryContainmentinformationisobsolete.

Figure5.32 Movedtosection10.12 Figure5.33 DeleteFigure5.33,MainSteamIsolationValveAlternateLeakageTreatmentPath.

TheMSIVALTpathreducedPostLOCAdosestowithintheguidelinesof10CFR50.67andtheacceptancecriteriaofGDC19withaleakagerateof62scfhperMSIVwithatotalleakagerateof 124scfhthroughthemainsteampathways.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.TheadditionalMSIVleakageallowedbytheALTpathisnolongerapplicable sincetheconditionsaddressedbyALTarenolongerpossible.TheinformationprovidedonFigure5.33isnolongerapplicable.ALTrelatedinformationisobsolete.

6.0 CoreStandbyCoolingSystems 6.1 6.1.1 DeleteSection6.1.1,CoreStandbyCoolingSystemsSafetyObjective.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincea LOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theSafety Objectiveisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.

6.2 DeleteSection6.2,CoreStandbyCoolingSystemsSafetyDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore, theSafetyDesignBasesarenolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.

6.3 DeleteSection6.3,SummaryDescriptionCoreStandbyCoolingSystems.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,the informationprovidedintheCSCSsummarydescriptionsectionisnolongerapplicable.InformationregardingtheCSCSsisobsolete.

Table6.3.1 DeleteTable6.3.1,CoreStandbyCoolingSystemsEquipmentDesignDataSummary.SincetheCSCSsarenolongerrequiredandhavebeendeleted,theinformationprovidedinthistableis obsolete.

6.4 6.4.1 DeleteSection6.4.1,HighPressureCoolantInjectionSystemDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.

Therefore,theinformationprovidedintheHPCIdescriptionsectionisnolongerapplicable.InformationregardingtheHPCIsystemisobsolete.

ReactorBuildingHeatingVentilationandAir ConditioningG191238 MainSteamIsolationValveAlternateLeakage TreatmentPath592013407 CoreStandbyCoolingSystems SafetyObjective SafetyDesignBases SummaryDescription References ReactorBuildingVacuumDataWithOneSGT TrainOperating SecondaryContainmentSystem-Reactor Building-CalculatedExfiltrationRateVersus WindVelocity CoreStandbyCoolingSystemsEquipmentDesign DataSummary DESCRIPTION HighPressureCoolantInjectionSystem Page36of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 6.4.2 DeleteSection6.4.2,AutomaticDepressurizationSystemDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincea LOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theAutomaticDepressurizationSystemisnolongerrequiredtofunctiontoallowlowpressuresystemstoinjectto coolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theinformationprovidedintheADSdescriptionsectionisnolongerapplicable.Information regardingtheADSisobsolete.

6.4.3 DeleteSection6.4.3,CoreSpraySystemDescription.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcanno longeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theCoreSpraySystemisnolongerrequiredtofunctiontocoolthecorefollowingaLOCAtolimitthereleaseofradioactive materialtotheenvirons.Therefore,theinformationprovidedintheCoreSpraydescriptionsectionisnolongerapplicable.InformationregardingtheCoreSpraySystemisobsolete.

6.4.4 DeleteSection6.4.4,descriptionoftheLowPressureCoolantInjectionfunctionoftheResidualHeatRemovalSystem.Followingcertificationofpermanentdefuelingthelicenseeisnolonger authorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelated designbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowingaLOCAto limitthereleaseofradioactivematerialtotheenvironsisnolongerrequired.Therefore,theinformationprovidedintheLPCIdescriptionsectionisnolongerapplicable.Informationregarding theLPCIfunctionoftheRHRSystemisobsolete.

6.4.5 DeleteSection6.4.5,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationsarenolongerpossible.Consequently,thefunctionsoftheCoreStandbyCoolingSystemsarenolongerrequired.The informationprovidedintheCoreStandbyCoolingSystemsReferencessectionisnolongerapplicable.

Figure6.41 DeleteFigure6.41,HighPressureCoolantInjectionSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.

Therefore,theinformationprovidedonfigure6.41isnolongerapplicable.InformationregardingtheHPCIsystemisobsolete.

Figure6.42 DeleteFigure6.42,CoreSpraySystem,ProcessDiagram.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcanno longeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theCoreSpraySystemisnolongerrequiredtofunctiontocoolthecorefollowingaLOCAtolimitthereleaseofradioactive materialtotheenvirons.Therefore,theinformationprovidedintheCoreSpraydescriptionsectionisnolongerapplicable.InformationregardingtheCoreSpraySystemisobsolete.

Figure6.43 DeleteFigure6.43,ResidualHeatRemovalSystem,ProcessDiagram.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincea LOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtothe environsisnolongerrequired.Therefore,theinformationprovidedonFigure6.43isnolongerapplicable.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.

6.5 6.5.1 DeleteSection6.5.1,CoreStandbyCoolingSystemsSafetyEvaluation,Summary.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.

Therefore,asafetyevaluationoftheCoreStandbyCoolingSysemsisnotrequired.TheinformationprovidedintheSafetyEvaluation,Summarysectionisnolongerapplicable.Information regardingtheCoreStandbyCoolingSystemsisobsolete.

6.5.2 DeleteSection6.5.2,SafetyEvaluationPerformanceAnalysis.Allsubsectionsofthissummarysectionhavebeenevaluatedanddeleted.Theinformationinthissectionisnotrequiredandis obsolete.

6.5.2.1 DeleteSection6.5.1,CoreStandbyCoolingSystemsSafetyEvaluation,PerformanceAnalysis,LOCAAnalysisMethodsandResults.Followingcertificationofpermanentdefuelingthelicenseeis nolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimittherelease ofradioactivematerialtotheenvirons.Therefore,aLOCAAnalysisisnotrequired.TheinformationprovidedintheLOCAAnalysisMethodsandResultssectionisnolongerapplicable.

InformationregardingtheCoreStandbyCoolingSystemsisobsolete.

6.5.2.2 DeleteSection6.5.2.2,HighPressureCoolantInjectionSystemPerformanceAnalysis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtothe environs.Therefore,asafetyevaluationandperformanceanalysisoftheHPCISystemisnotrequired.InformationregardingtheHPCIsystemisobsolete.

PerformanceAnalysis LOCAAnalysisMethodsandResults HighPressureCoolantInjection (HPCI)System References HighPressureCoolantInjectionSystem,Process Diagram5920784 CoreSpraySystem,ProcessDiagram5920718 ResidualHeatRemovalSystem,ProcessDiagram 5920725 SAFETYEVALUATION Summary AutomaticDepressurizationSystem CoreSpraySystem LowPressureCoolantInjection Page37of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 6.5.2.3 DeleteSection6.5.2.3,HighPressureCoolantInjectionSystemPerformanceAnalysis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.SinceaLOCAcannolongeroccur,theAutomaticDepressurizationSystemisnolongerrequiredtorapidlydepressurizethepressurevesseltoallowlowpressuresystemstocoolor refloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,asafetyevaluationandperformanceanalysisoftheAutomaticDepressurizationSystemisnotrequired.

InformationregardingADSisobsolete.

6.5.2.4 DeleteSection6.5.2.4,CoreSpraySystemPerformanceAnalysis.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactor vesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincea LOCAcannolongeroccur,theCoreSpraySystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,asafetyevaluationand performanceanalysisoftheCoreSpraySystemisnotrequired.InformationregardingtheCoreSpraysystemisobsolete.

6.5.2.5 DeleteSection6.5.2.5,PerformanceAnalysisoftheLowPressureCoolantInjectionfunctionoftheResidualHeatRemovalSystem.Followingcertificationofpermanentdefuelingthelicenseeis nolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRtocoolthecorefollowinga LOCAtolimitthereleaseofradioactivematerialtotheenvironsisnotrequired.Therefore,asafetyevaluationandperformanceanalysisoftheLowPressureCoolantInjectionfunctionofRHR isnotrequired.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.

6.5.3 DeleteSection6.5.3,CoreStandbyCoolingSystemsSafetyEvaluation,Compliancewith10CFR50.46Requirements.Followingcertificationofpermanentdefuelingthelicenseeisnolonger authorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelated designbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,demonstrationofcompliancewith10CFR50.46requirementsisnotrequired.Theinformationprovidedinthe Compliancewith10CFR50.46Requirementssectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.

6.5.4 DeleteSection6.5.4,CoreStandbyCoolingSystemsSafetyEvaluation,CoreStandbyCoolingSystemsRedundancy.Followingcertificationofpermanentdefuelingthelicenseeisnolonger authorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelated designbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccur,demonstrationofcompliancewith10CFR50.46requirements,includingredundancy,isnotrequired.The informationprovidedintheCoreStandbyCoolingSystemsRedundancysectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.

6.5.5 DeleteSection6.5.4,References.SinceallpartsofSection6.5havebeendeleted,Referencesarenolongerapplicable.

6.6 6.6.1 DeleteSection6.6.1,CoreStandbyCoolingSystemsInspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthe reactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

SinceaLOCAcannolongeroccur,thefunctionsoftheCoreStandbyCoolingSystemsarenotrequired.Consequently,demonstrationoftheabilityoftheCSCSstomeettheirfunctionthrough inspectionandtestingisnotrequired.TheinformationprovidedintheCoreStandbyCoolingSystemsInspectionandtestingsectionisnolongerapplicable.Informationprovidedinthissection isobsolete.

6.6.2 DeleteSection6.5.4,References.Sincesection6.6.1hasbeendeleted,Referencesarenolongerapplicable.

7.0 ControlandInstrumentation Deletethisheading,remainingsectioninformationmovedtoothersections 7.1 Deletethisheading,remainingsectioninformationmovedtoothersections 7.1.1 DeleteSection7.1.1,ControlandInstrumentation,ProtectionSystems.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueledstation andthefunctionsofProtectionSystemsarenolongerapplicableinthepermanentlydefueledstate.

7.1.2 DeleteSection7.1.2,ControlandInstrumentation,PowerGenerationSystems.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueled station,andthefunctionsofPowerGenerationSystemsarenolongerapplicableinthepermanentlydefueledstate.

7.1.3 DeleteSection7.1.3,ControlandInstrumentation,SafetyFunctions.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueledstation,and thefunctionsofSafetySystemsarenolongerapplicableinthepermanentlydefueledstate.

7.1.4 DeleteSection7.1.4,ControlandInstrumentation,SafetyFunctions.TheBWRSSCclassificationprocessdescribedinUFSARsection1.4isnotapplicabletoapermanentlydefueledstation,and thefunctionsofStationOperationalControlSystemsarenolongerapplicableinthepermanentlydefueledstate.

AutomaticDepressurizationSystem (ADS)

CoreSpraySystem(CSS)

LowPressureCoolantInjection(LPCI)

SUMMARY

DESCRIPTION ProtectionSystems PowerGenerationSystems SafetyFunctions StationOperationalControl ComplianceWith10CFR50.46Requirements CoreStandbyCoolingSystemsRedundancy References INSPECTIONANDTESTING Summary References Page38of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.1.5 DeleteSection7.1.5,Definitions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therrefore,manyofthedefinitionsinthissectionarenolongerapplicable.

TheSSCclassificationprocessdescribedinUFSARsection1.4,ClassificationofBWRSystems,Criteria,andRequirementsisnotapplicableinthedefueledstateandhasbeendeleted.Manyof thedefinitionsprovidedinthissectiondefinetermsrelatedtotheSSCClassificationprocessandtherefore,arenolongerapplicable Additionally,manyofthedefinitionsprovidedinthissectionarealreadydefinedinmoreappropriatedocumentation,includingTechnicalSpecificationsandtheTechnicalRequiementsManual.

Finally,manyofthedefinitionsprovidedinthissectionarenolongerusedintheDSAR.

Therefore,theinformationinthissectionishistorcalandobsoleteandmaybedeleted.

7.1.6 DeleteSection7.1.6,ControlandInstrumentation,IdentificationofSafetySystems.Sincethefunctionsofsafetysystemsarenolongerrequiredfollowingpermanentdefueling,specific identificationofthoseSSCsisalsonolongerrequired.

7.1.7 DeleteSection7.1.7,ControlandInstrumentation,DetailedDesignReview.Thissectioncontainshistoricinformationwhichisnotapplicablefollowingcertificationofpermanentdefueling.

7.1.8 Deletesection7.1.8,EnvironmentalQualification.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,the assurancesprovidedbytheEnvironmentalQualificationProgramarenolongerrequired.

7.1.9 Deletesection7.1.9,References.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thereferenescitedinthissection arenolongerapplicable.Alltextcitingthesereferenceshasbeendeletedfromthissection.

Figure7.11 DeleteFigure7.11,UseofProtectionSystemControlandInstrumentationDefinitions.Figureisnolongerrequiredsincetheentiresectionhasbeendeleted.

7.2 7.2.1 DeleteSection7.2.1,ReactorProtectionSystemSafetyObjective.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theRPSSafetyObjectiveisnot applicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

7.2.2 DeleteSection7.2.2,ReactorProtectionSystemSafetyDesignBases.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theRPSSafetyObjectiveisnot applicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

7.2.3 DeleteSection7.2.3,ReactorProtectionSystemDescription.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclear systemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthelicenseeis nolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSystemDescription providedisnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

7.2.4 DeleteSection7.2.4,ReactorProtectionSystemSafetyEvaluation.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;asafetyevaluationoftheReactor ProtectionSystemisnotrequiredsincethefunctionsoftheReactorProtectionSystemarenotrequired.InformationregardingtheReactorProtectionSystemisobsolete.

Definitions IdentificationofSafetySystems DetailedControlRoomDesignReview EnvironmentalQualification SafetyDesignBases Description SafetyEvaluation References UseofProtectionSystemControland InstrumentationDefinitions REACTORPROTECTIONSYSTEM SafetyObjective Page39of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.2.5 DeleteSection7.2.5,ReactorProtectionSystemInspectionandTesting.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;inspectionandtestingoftheReactor ProtectionSystemisnotrequiredsincethefunctionsoftheReactorProtectionSystemarenotrequired.TheReactorProtectionSystemhasbeencategorizedasabandonedinaccordancewith EC48440.InformationregardingtheReactorProtectionSystemisobsolete.

Table7.2.1 DeleteTable7.2.1,ReactorProtectionSystemInstrumentation.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclear systemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthelicenseeis nolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired.TheReactorProtectionSystemhasbeen categorizedasabandonedinaccordancewithEC48440.InformationregardingtheReactorProtectionSystemisobsolete.

Table7.2.2 DeleteTable7.2.2,ReactorProtectionSystemInstrumentationEnvironmentalConditions.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactive materialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationof permanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,power operationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired.

InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.21 DeleteFigure7.21,ReactorProtectionSystemInstrumentElectricalDiagram.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthe fuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanent defuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscanno longeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtection Systeminformationprovidedonfigure7.21isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.22 DeleteFigure7.22,ReactorProtectionSystem,ControlRoomPanelforOneTripSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerial fromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationof permanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,power operationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;the ReactorProtectionSysteminformationprovidedonfigure7.22isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.23 DeleteFigure7.23,ReactorProtectionSystem,FunctionControlDiagramforOneTripSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactive materialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationof permanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,power operationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;the ReactorProtectionSysteminformationprovidedonfigure7.23isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.24 DeleteFigure7.24,SchematicDiagramofLogicsinOneTripSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSystem informationprovidedonfigure7.24isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.25 DeleteFigure7.25,SchematicDiagramofActuatorandActuatorLogics.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSystem informationprovidedonfigure7.25isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

ReactorProtectionSystemInstrumentElectrical Diagram5920272 ReactorProtectionSystem,ControlRoomPanel forOneTripSystem ReactorProtectionSystem,FunctionControl DiagramforOneTripSystem5920273 SchematicDiagramofLogicsinOneTripSystem SchematicDiagramofActuatorandActuator Logics InspectionandTesting ReactorProtectionSystemInstrumentation ReactorProtectionSystemInstrumentation EnvironmentalConditions Page40of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.26 DeleteFigure7.26,ReactorProtectionSystem,ScramFunctions.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSystem informationprovidedonfigure7.26isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.27 DeleteFigure7.27,ReactorProtectionSystemInstrumentation.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefuelandnuclea systemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthelicenseeis nolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcore relateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSysteminformation providedonfigure7.27isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.28 DeleteFigure7.28,RelationshipBetweenNeutronMonitoringSystemandReactorProtectionSystem.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseof radioactivematerialfromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Following certificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclear core,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolonger required;theReactorProtectionSysteminformationprovidedonfigure7.28isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemis obsolete.

Figure7.29 DeleteFigure7.29,FunctionalControlDiagramforNeutronMonitoringSystemLogics.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerial fromthefuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationof permanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,power operationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;the ReactorProtectionSysteminformationprovidedonfigure7.29isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.210 DeleteFigure7.210,TypicalArrangementofChannelsandLogics.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthefueland nuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanentdefuelingthe licenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur andcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtectionSystem informationprovidedonfigure7.210isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.211 DeleteFigure7.211,TypicalConfigurationforTurbineStopValveClosureScram.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthe fuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanent defuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscanno longeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtection Systeminformationprovidedonfigure7.211isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.212 DeleteFigure7.212,TypicalConfigurationforMainSteamlineIsolationScram.TheReactorProtectionSystemfunctionedtopreventtheuncontrolledreleaseofradioactivematerialfromthe fuelandnuclearsystemprocessbarrierbyterminatingexcessivetemperatureandpressureincreasesthroughtheinitiationofanautomaticscram.Followingcertificationofpermanent defuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscanno longeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheReactorProtectionSystemarenolongerrequired;theReactorProtection Systeminformationprovidedonfigure7.212isnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

Figure7.213 PreviouslyDeleted Figure7.214 PreviouslyDeleted Figure7.215 PreviouslyDeleted ReactorProtectionSystem,ScramFunctions ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier Deleted Deleted Deleted 7.3 PRIMARYCONTAINMENTANDREACTORVESSELISOLATION CONTROLSYSTEM ReactorProtectionSystemInstrumentation5920 274 RelationshipBetweenNeutronMonitoring SystemandReactorProtectionSystem FunctionalControlDiagramforNeutron MonitoringSystemLogics59201807 TypicalArrangementofChannelsandLogics TypicalConfigurationforTurbineStopValve ClosureScram TypicalConfigurationforMainSteamline IsolationScram Page41of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.3.1 DeleteSection7.3.1,PrimaryContainmentandReactorVesselIsolationControlSystemSafetyObjective.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthe fuelandnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.

7.3.2 DeleteSection7.3.2,PrimaryContainmentandReactorVesselIsolationControlSystemDefinitions.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.

7.3.3 DeleteSection7.3.3,PrimaryContainmentandReactorVesselIsolationControlSystemSafetyDesignBases ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.ThePrimaryContainmentandReactorVesselIsolationControlSystemhasbeencategorizedasabandonedinaccordancewithEC48440.

InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemisobsolete.

7.3.4 DeleteSection7.3.4,PrimaryContainmentandReactorVesselIsolationControlSystemDescription.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.InformationprovidedintheDescriptionsectionisnolongerapplicable.InformationregardingthePrimaryContainmentandReactor VesselIsolationControlSystemisobsolete.

7.3.5 DeleteSection7.3.5,PrimaryContainmentandReactorVesselIsolationControlSystemSafetyEvaluation.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.AsafetyevaluationofthePrimaryContainmentandReactorVesselIsolationControlSystemisnolongerrequired.ThePrimary ContainmentandReactorVesselIsolationControlSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingthePrimaryContainmentandReactorVesse IsolationControlSystemisobsolete.

7.3.6 DeleteSection7.3.6,PrimaryContainmentandReactorVesselIsolationControlSystemInspectionandTesting.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.InspectionandTestingofthePrimaryContainmentandReactorVesselIsolationControlSystemisnolongerrequired.ThePrimary ContainmentandReactorVesselIsolationControlSystemhasbeencategorizedasabandonedinaccordancewithEC48440.InformationregardingthePrimaryContainmentandReactorVesse IsolationControlSystemisobsolete.

SafetyObjective Definitions InspectionandTesting SafetyDesignBases Description SafetyEvaluation Page42of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.3.7 DeleteSection7.3.7,PrimaryContainmentandReactorVesselIsolationControlSystemReferences.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Referencesarenolongerapplicable.InformationregardingthePrimaryContainmentandReactorVesselIsolationControlSystemis obsolete.

Table7.3.1 DeleteTable7.3.1,PrimaryContainmentandReactorVesselIsolationActuation.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.TheinformationpresentedinTable7.3.1isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Table7.3.2 DeleteTable7.3.2,PrimaryContainmentandReactorVesselIsolationControlSystemInstrumentation.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceedpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.TheinformationpresentedinTable7.3.2isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.31 DeleteFigure7.31,NuclearSystem,PipingandInstrumentationDiagram.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.31isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.32 DeleteFigure7.32,TypicalIsolationControlSystemUsingMotorOperatedValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.32isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.33 DeleteFigure7.33,TypicalIsolationControlSystemforMainSteamlineIsolationValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.33isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.34a PreviouslyDeleted NuclearSystem,PipingandInstrumentation DiagramG191167 TypicalIsolationControlSystemUsingMotor OperatedValves TypicalIsolationControlSystemforMain SteamlineIsolationValves Deleted References PrimaryContainmentandReactorVessel IsolationActuation PrimaryContainmentandReactorVessel IsolationControlSystemInstrumentation Page43of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.34b DeleteFigure7.34b,MainSteamLineIsolationValve,SchematicControlDiagram.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.34bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.35a DeleteFigure7.35a,NuclearBoilerMiscellaneousSystems,FunctionalControlDiagram.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.35aisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.35b DeleteFigure7.35b,PrimaryContainmentandReactorVesselIsolationControlSystem,FunctionalControlDiagram.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.35bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.36 DeleteFigure7.36,AreaandCompartmentLeakageDetectionbyTemperatureMeasurement.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.36isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.37A DeleteFigure7.37A,TypicalHighTemperatureChannels.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.37Aisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.37B DeleteFigure7.37B,RWCSHighFlowChannel.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.37Bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.38 DeleteFigure7.38,TypicalArrangementforMainSteamlineLeakDetectionbyFlowMeasurement.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.38isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

MainSteamLineIsolationValve,Schematic ControlDiagram59206766 NuclearBoilerMiscellaneousSystems,Functional ControlDiagram5920612,Sh1 PrimaryContainmentandReactorVessel IsolationControlSystem,FunctionalControl Diagram AreaandCompartmentLeakageDetectionby TemperatureMeasurement TypicalHighTemperatureChannels RWCSHighFlowChannel TypicalArrangementforMainSteamlineLeak DetectionbyFlowMeasurement Page44of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.39 DeleteFigure7.39,MainSteamlineHighFlowChannels.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.39isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.310 DeleteFigure7.310,RCICElbowTapArrangementforGrossLeakDetection.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.310isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.311 DeleteFigure7.311,TypicalElbowTapArrangementforGrossLeakDetection.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.311isnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12A DeleteFigure7.312A,IsolationControlSystem,TypicalTripSystem.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312Aisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12B DeleteFigure7.312B,IsolationControlSystem,TypicalTripSystem.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312Bisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12c DeleteFigure7.312c,IsolationControlSystem,TypicalControlsforInboardMainSteamlineIsolationValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312cisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12d DeleteFigure7.312d,IsolationControlSystem,TypicalControlsforOutboardMainSteamlineIsolationValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312disnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

RCICElbowTapArrangementforGrossLeak Detection TypicalElbowTapArrangementforGrossLeak Detection IsolationControlSystem,TypicalTripSystemB 59202093Sheet1&2 IsolationControlSystem,TypicalTripSystemA 59202092Sheet1&2 IsolationControlSystem,TypicalControls forInboardMainSteamlineIsolationValves 5920209459202095 IsolationControlSystem,TypicalControlsfor OutboardMainSteamlineIsolationValves 59202096 MainSteamlineHighFlowChannels Page45of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.3 12e DeleteFigure7.312e,IsolationControlSystem,TypicalControlsforRHRSandReactorWaterCleanupValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312eisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12F DeleteFigure7.312F,IsolationControlSystem,TypicalControlsforRHRSShutdownCoolingValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312Fisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12g DeleteFigure7.312g,IsolationControlSystem,TypicalControlsforReactorWaterCleanupSystemValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312gisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12h DeleteFigure7.312h,IsolationControlSystem,TypicalControlsforRHRSDischargetoRadwasteValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312hisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12i DeleteFigure7.312i,IsolationControlSystem,TypicalControlsforMainSteamlineDrainValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312iisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12j DeleteFigure7.312j,IsolationControlSystem,TypicalControlsforRecirculationLoopSampleValves.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312jisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

Figure7.3 12k DeleteFigure7.312k,IsolationControlSystem,TypicalControlsforTIPSystem.

ThePrimaryContainmentandReactorVesselIsolationControlSysteminitiatedautomaticisolationofappropriatepipelineswhichpenetratetheprimarycontainmentwhenevermonitored variablesexceededpreselectedoperationallimitstoprovidetimelyprotectionagainsttheonsetandconsequencesofaccidentsinvolvingthegrossreleaseofradioactivematerialsfromthefuel andnuclearsystemprocessbarrier, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsofthePrimaryContainmentandReactor VesselIsolationControlSystemarenolongerrequired.Informationprovidedonfigure7.312kisnolongerapplicable.InformationregardingthePrimaryContainmentandReactorVessel IsolationControlSystemisobsolete.

IsolationControlSystem,TypicalControlsfor RHRSandReactorWaterCleanupValves5920 2098 IsolationControlSystem,TypicalControlsfor RHRSShutdownCoolingValves5920 2099 IsolationControlSystem,TypicalControlsfor ReactorWaterCleanupSystemValves5920 2101 IsolationControlSystem,TypicalControlsfor RHRSDischargetoRadwasteValves59202100 IsolationControlSystem,TypicalControlsfor MainSteamlineDrainValves 59202097 IsolationControlSystem,TypicalControlsfor RecirculationLoopSampleValves 59202094 IsolationControlSystem,TypicalControlsforTIP System59202094 Page46of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.4 SeeSection6.0,CoreStandbyCoolingSystems 7.4.1 DeleteSection7.4.1,CoreStandbyCoolingSystems(CSCS)ControlandInstrumentationSafetyObjective.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsinitiated appropriateresponsesfromthevariouscoolingsystemssothatthefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthe releaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.Followingcertificationof permanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,power operationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSarenolongerrequired;theCSCSSafetyObjectiveisnot applicablesincethereisnocoretoprotect.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlandInstrumentationisobsolete.

7.4.2 DeleteSection7.4.2,CoreStandbyCoolingSystems(CSCS)ControlandInstrumentationSafetyDesignBases.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsinitiated appropriateresponsesfromthevariouscoolingsystemssothatthefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystemsrestrictedthe releaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.Followingcertificationof permanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,power operationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired;theCSCSSafetyDesignBasesare notapplicablesincethereisnocoretoprotect.TheCSCSfunctionsoftheassociatedsystemshavebeencategorizedasabandonedinaccordancewiththeassociatedEngineeringChanges.

InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlandInstrumentationisobsolete.

7.4.3 7.4.3.1 DeleteSection7.4.3.1,CoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationIdentification.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentified asthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.The coolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthe nuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolonger required.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.InformationregardingtheCoreStandby CoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

7.4.3.2 DeleteSection7.4.3.2,HighPressureCoolantInjectionSystemControlsandInstrumentationDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theHighPressureCoolantInjectionSystemisnolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactiv materialtotheenvirons.Therefore,theHPCISystemControlsandInstrumentationarealsonolongerrequired.InformationprovidedintheHPCIControlsandInstrumentationdescription sectionisnolongerapplicable.InformationregardingtheHPCIsystemisobsolete.

7.4.3.3 DeleteSection7.4.3.3,AutomaticDepressurizationSystemControlandInstrumentationDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theAutomaticDepressurizationSystemisnolongerrequiredtofunction toallowlowpressuresystemstoinjecttocoolorrefloodthecoretolimitthereleaseofradioactivematerialtotheenvirons.Therefore,theADSControlsandInstrumentationarealsono longerrequired.TheinformationprovidedintheADSControlandInstrumentationDescriptionsectionisnolongerapplicable.InformationregardingtheADSisobsolete.

7.4.3.4 DeleteSection7.4.3.4,CoreSpraySystemControlandInstrumentationDescription.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuel inthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theCoreSpraySystemisnolongerrequiredtofunctiontocoolthecorefollowingaLOCAtolimit thereleaseofradioactivematerialtotheenvirons.Therefore,theCoreSpraySystemControlsandInstrumentationarealsonolongerrequired.TheinformationprovidedintheCoreSpray descriptionsectionisnolongerapplicable.InformationregardingtheCoreSpraySystemisobsolete.

7.4.3.5 DeleteSection7.4.3.5,descriptionoftheLowPressureCoolantInjectionControlandInstrumentationfunctionoftheResidualHeatRemovalSystem.Followingcertificationofpermanent defuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscanno longeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceaLOCAcannolongeroccurandallfuelisstoredinthefuelpoolorontheISFSI,theLPCIfunctionofRHRto coolthecorefollowingaLOCAtolimitthereleaseofradioactivematerialtotheenvironsisnolongerrequired.Therefore,theLPCISystemControlsandInstrumentationarealsonolonger required.TheinformationprovidedintheLPCIdescriptionsectionisnolongerapplicable.InformationregardingtheLPCIfunctionoftheRHRSystemisobsolete.

HPCIControl&Instrumentation ADSControl&Instrumentation CoreSprayControl&

Instrumentation LPCIControl&Instrumentation CORESTANDBYCOOLINGSYSTEMSCONTROLAND INSTRUMENTATION SafetyObjective SafetyDesignBases Description Identification Page47of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.4.4 DeleteSection7.4.4,CoreStandbyCoolingSystemsInstrumentationandControlsSafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.SinceaLOCAcannolongeroccur,theCoreStandbyCoolingSystemsarenolongerrequiredtocoolorrefloodthecoretolimitthereleaseofradioactive materialtotheenvirons.Therefore,theCSCSControlsandInstrumentationarealsonolongerrequired.AsafetyevaluationoftheCoreStandbyCoolingSysemsControlsandInstrumentationis notrequired.TheinformationprovidedintheSafetyEvaluationsectionisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystemsisobsolete.

7.4.5 DeleteSection7.4.5,CoreStandbyCoolingSystemsControlsandInstrumentationInspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.SinceaLOCAcannolongeroccur,thefunctionsoftheCoreStandbyCoolingSystemsarenotrequired.Consequently,demonstrationoftheabilityoftheCSCSs tomeettheirfunctionthroughinspectionandtestingoftheCSCSControlsandInstrumentationisnotrequired.TheinformationprovidedintheCoreStandbyCoolingSystemsControlsand InstrumentationInspectionandtestingsectionisnolongerapplicable.Informationprovidedinthissectionisobsolete.

7.4.6 DeleteSection7.4.6,References.Sincesection7.4hasbeendeleted,Referencesarenolongerapplicable.

Table7.4.1 DeleteTable7.4.1,HPCIInstrumentation.Section7.4.3.2,HPCISystemControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingHPCISystem instrumentationisnolongerrequired.Informationprovidedinthetableisobsolete.

Table7.4.2 DeleteTable7.4.2,ADSInstrumentation.Section7.4.3.3,ADSControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingADSinstrumentationis nolongerrequired.Informationprovidedinthetableisobsolete.

Table7.4.3 DeleteTable7.4.3,CoreSpraySystemInstrumentation.Section7.4.3.4,CoreSpraySystemControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetable listingCoreSpraySysteminstrumentationisnolongerrequired.Informationprovidedinthetableisobsolete.

Table7.4.4 DeleteTable7.4.4,LPCISystemInstrumentation.Section7.4.3.5,LPCISystemControlsandInstrumentationhasbeendeletedsinceitisnolongerapplicable.Therefore,thetablelistingLPCI Systeminstrumentationisnolongerrequired.Informationprovidedinthetableisobsolete.

Figure7.41A DeleteFigure7.41A,HighPressureCoolantInjectionSystemArrangement.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequired fortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythe systemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.41Aisnolonge applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.41B DeleteFigure7.41B,HighPressureCoolantInjectionSystem,TurbineandPumpUnit.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipment requiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovided bythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.41Bisnolonge applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.42a DeleteFigure7.42a,HighPressureCoolantInjectionSystem,TurbineandPumpUnit.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipment requiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovided bythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.42aisnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.42b DeleteFigure7.42b,HighPressureCoolantInjectionSystem,MiscellaneousComponents,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystems areidentifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccident conditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolant waslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsareno longerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovided onFigure7.42bisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

References HighPressureCoolantInjectionSystem Instrumentation AutomaticDepressurizationSystem Instrumentation CoreSpraySystem Instrumentation LowPressureCoolantInjection Instrumentation HighPressureCoolantInjectionSystem ArrangementG191169 SafetyEvaluation InspectionandTesting G191169,Sh2HighPressureCoolantInjection System,TurbineandPumpUnit 592038HighPressureCoolantInjectionSystem Valves,FunctionalControlDiagram 592039HighPressureCoolantInjectionSystem, MiscellaneousComponents,FunctionalControl Diagram Page48of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.42c DeleteFigure7.42c,HighPressureCoolantInjectionSystem,TurbineFunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthat equipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecooling providedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclear system.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibleto loadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.42cisnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.43 DeleteFigure7.43,AutomaticDepressurizationSystem,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipment requiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovided bythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.43isnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.44 DeleteFigure7.44,CoreSpraySystemPipingandInstrumentDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredfor theinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythe systemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.44isnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.45 DeleteFigure7.45,CoreSpraySystem,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequiredforthe initiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythesystems restrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.Following certificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclear core,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethefunctionsof theCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.45isnolongerapplicable.

InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.46 DeleteFigure7.46,ResidualHeatRemovalSystem,PipingandInstrumentationDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthat equipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecooling providedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclear system.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibleto loadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.46isnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.47a DeleteFigure7.47a,ResidualHeatRemovalSystem,LPCIPumpandValves,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentified asthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.The coolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthe nuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolonger required.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigur 7.47aisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

592037CoreSpraySystem,FunctionalControl Diagram G191172ResidualHeatRemovalSystem,Piping andInstrumentationDiagram 592027ResidualHeatRemovalSystem,LPCI PumpandValves,FunctionalControlDiagram 5920441HighPressureCoolantInjection System,TurbineFunctionalControlDiagram 5920611AutomaticDepressurizationSystem, FunctionalControlDiagram G191168CoreSpraySystemPipingand InstrumentDiagram Page49of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.47b DeleteFigure7.47b,ResidualHeatRemovalSystem,LPCIValves,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthat equipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecooling providedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclear system.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibleto loadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.47bisnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.47c DeleteFigure7.47c,ResidualHeatRemovalSystem,LPCIMiscellaneousComponentsFunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsare identifiedasthatequipmentrequiredfortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccident conditions.Thecoolingprovidedbythesystemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolant waslostfromthenuclearsystem.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Since itisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsareno longerrequired.SincethefunctionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovided onFigure7.47cisnolongerapplicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

Figure7.48 DeleteFigure7.48,RecirculationLoopValves,FunctionalControlDiagram.ThecontrolsandinstrumentationfortheCoreStandbyCoolingSystemsareidentifiedasthatequipmentrequired fortheinitiationandcontrolofHPCIS,ADS,CSS,andtheLPCIfunctionofRHRtoensurethefuelwasadequatelycooledunderabnormaloraccidentconditions.Thecoolingprovidedbythe systemsrestrictedthereleaseofradioactivematerialsfromthefuelbylimitingtheextentoffueldamagefollowingsituationsinwhichreactorcoolantwaslostfromthenuclearsystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheCSCSsarenolongerrequired.Sincethe functionsoftheCSCSsarenolongerrequired,theinstrumentationandControlsforthosesystemsarealsonolongerrequired.Therefore,theinformationprovidedonFigure7.48isnolonger applicable.InformationregardingtheCoreStandbyCoolingSystems(CSCS)ControlsandInstrumentationisobsolete.

7.5 7.5.1 DeleteSection7.5.1,NeutronMonitoringSystemSafetyObjective.ThesafetyobjectiveoftheNeutronMonitoringSystemwastodetectconditionsinthecorethatthreatenedtheoverall integrityofthefuelbarrierduetoexcessivepowergenerationandtoprovidesignalstotheReactorProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwas limited.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required;theNeutronMonitoringSystemSafetyObjectiveisnotapplicablesincethereisnocoretoprotect.

7.5.2 DeleteSection7.5.2,NeutronMonitoringSystemPowerGenerationObjective.ThepowergenerationobjectiveoftheNeutronMonitoringSystemwastoprovideinformationfortheefficient, expedientoperationandcontrolofthereactor.TwospecificpowergenerationobjectivesoftheNeutronMonitoringSystemweretodetectconditionsthatcouldleadtolocalfueldamageand toprovidesignalsthatwereusedtopreventsuchdamage,sothatstationavailabilitywasnotreduced.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required;theNeutronMonitoringSystemPowerGenerationObjectiveisnotapplicablesincepoweroperationscannolongeroccur.

7.5.3 DeleteSection,providesonlyatitlelistingofthesixmajorsubsystemsincludedinNeutronMonitoring.

7.5.4 7.5.4.1 DeleteSection7.5.4.1,SourceRangeMonitorSubsystem,PowerGenerationDesignBasis.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcore neutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemareno longerrequired;theSourceRangeMonitorSubsystemPowerGenerationObjectiveisnotapplicablesinceanuclearcorecannolongerbeloadedintotheRPV.

7.5.4.2 DeleteSection7.5.4.2,SourceRangeMonitorSubsystem,Description.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcoreneutronfluxlevel informationandprotectiveactionsassociatedwithcertainconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemareno longerrequired;theinformationprovidedintheSourceRangeMonitorSubsystemDescriptionSectionsnotapplicablesinceanuclearcorecannolongerbeloadedintotheRPV.

NEUTRONMONITORINGSYSTEM SafetyObjective PowerGenerationObjective Identification SourceRangeMonitorSubsystem PowerGenerationDesignBasis 592028ResidualHeatRemovalSystem,LPCI Valves,FunctionalControlDiagram 592029ResidualHeatRemovalSystem,LPCI MiscellaneousComponentsFunctionalControl Diagram 59201816RecirculationLoopValves,Functional ControlDiagram Description Page50of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.4.3 DeleteSection7.5.4.3,SourceRangeMonitorSubsystem,PowerGenerationEvaluation.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcore neutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemareno longerrequired;theinformationprovidedintheSourceRangeMonitorSubsystemPowerGenerationEvaluationSectionsnotapplicablesinceanuclearcorecannolongerbeloadedintothe RPV.

7.5.4.4 DeleteSection7.5.4.4,SourceRangeMonitorSubsystem,PowerGenerationEvaluation.TheSourceRangeMonitorSubsystemoftheNeutronMonitoringSystemprovidednuclearcore neutronfluxlevelinformationandprotectiveactionsassociatedwithcertainconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheSourceRangeMonitorSubsystemareno longerrequired;theinformationprovidedintheSourceRangeMonitorSubsystemPowerGenerationEvaluationSectionsnotapplicablesinceanuclearcorecannolongerbeloadedintothe RPV.

7.5.5 7.5.5.1 DeleteSection7.5.5.1,IntermediateRangeMonitorSubsystemSafetyDesignBasis.ThesafetydesignbasisoftheIRMSwastogenerateatripsignaltopreventfueldamageresultingfrom abnormaloperationaltransientsthatoccurredwhileoperatingintheintermediatepowerrange FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheIntermediateRangeMonitorSubsystemare nolongerrequired;theIntermediateRangeMonitorSubsystemSafetyDesignBasisisnotapplicablesincethereisnocoretoprotect.

7.5.5.2 DeleteSection7.5.5.2,IntermediateRangeMonitorSubsystemPowerGenerationDesignBasis.ThepowergenerationdesignbasisoftheIRMSwastogenerateatripsignaltoblockrod withdrawaliftheIRMSreadingexceededapresetvalueoriftheIRMSwasnotoperatingproperly.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheIntermediateRangeMonitorSubsystemare nolongerrequired;theIntermediateRangeMonitorSubsystemPowerGenerationDesignBasiswasnotapplicablesincethereisnocoretoprotect.

7.5.5.3 DeleteSection7.5.5.3,IntermediateRangeMonitorSubsystemDescription.TheIRMSfunctionedtogenerateatripsignaltopreventfueldamageresultingfromabnormaloperational transientsthatoccurredwhileoperatingintheintermediatepowerrange.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprotectivefunctionsoftheIRMSarenolongerrequired;the IRMSDescriptionprovidedisnotapplicablesincethereisnocoretoprotect.InformationregardingtheReactorProtectionSystemisobsolete.

7.5.5.4 DeleteSection7.5.5.4,IntermediateRangeMonitorSubsystemSafetyEvaluation.TheIRMSfunctionedtogenerateatripsignaltopreventfueldamageresultingfromabnormaloperational transientsthatoccurredwhileoperatingintheintermediatepowerrange.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheIRMSarenolongerrequired;asafety evaluationoftheIRMSisnotrequiredsincethefunctionsoftheIRMSarenotrequired.InformationregardingtheIRMSisobsolete.

7.5.5.5 DeleteSection7.5.5.5,IntermediateRangeMonitorSubsystemPowerGenerationEvaluation.ThepowergenerationfunctionoftheIRMSwastogenerateatripsignaltoblockrodwithdrawali theIRMSreadingexceededapresetvalueoriftheIRMSwasnotoperatingproperly FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,apowergenerationevaluationoftheIRMSisnotrequiredsince thefunctionsoftheIRMSarenotrequiredandtheIRMShasbeencategorizedasabandonedinaccordancewithEC48455.InformationregardingtheIRMSisobsolete.

7.5.5.6 DeleteSection7.5.5.6,IntermediateRangeMonitorSubsystemInspectionandTesting.TheIRMSfunctionedtogenerateatripsignaltopreventfueldamageresultingfromabnormal operationaltransientsthatoccurredwhileoperatingintheintermediatepowerrange.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheIRMSisnotrequiredsincethe functionsoftheIRMSarenotrequired.TheIRMShasbeencategorizedasabandonedinaccordancewithEC48455.InformationregardingtheIRMSisobsolete.

7.5.6 Description SafetyEvaluation PowerGenerationEvaluation InspectionandTesting LocalPowerRangeMonitorSubsystem PowerGenerationEvaluation InspectionandTesting IntermediateRangeMonitorSubsystem SafetyDesignBasis PowerGenerationDesignBasis Page51of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.6.1 DeleteSection7.5.6.1,LocalPowerRangeMonitorSubsystemPowerGenerationDesignBasis.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvarious locationswithinthereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheLocalPowerRangeMonitorSubsystemare nolongerrequired.

7.5.6.2 DeleteSection7.5.6.2,LocalPowerRangeMonitorSubsystemDescription.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocationswithinthereactor coretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheLPRMSarenolongerrequired;theLPRMS Descriptionprovidedisnotapplicable.InformationregardingtheLPRMSisobsolete.

7.5.6.3 DeleteSection7.5.6.3,LocalPowerRangeMonitorSubsystemPowerGenerationEvaluation.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocations withinthereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheLocalPowerRangeMonitorSubsystemare nolongerrequired;apowergenerationevaluationisnotapplicable.

7.5.6.4 DeleteSection7.5.6.4,LocalPowerRangeMonitorSubsystemInspectionandTesting.TheLPRMSfunctionedtoprovidesignalsproportionaltothelocalneutronfluxatvariouslocationswithin thereactorcoretotheAveragePowerRangeMonitorSubsystem(APRMS),theRodBlockMonitorSubsystem,alarms,theprocesscomputerandlocalpowerindications.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheLPRMSisnotrequiredsincethe functionsoftheLPRMSarenotrequired.InformationregardingtheLPRMSisobsolete.

7.5.7 7.5.7.1 DeleteSection7.5.7.1,AveragePowerRangeMonitorSubsystemSafetyDesignBasis.TheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreases resultingfromabnormaloperationaltransientsintimetopreventfueldamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAveragePowerRangeMonitorSubsystem arenolongerrequired;theAveragePowerRangeMonitorSubsystemSafetyDesignBasisisnotapplicable.

7.5.7.2 DeleteSection7.5.7.2,AveragePowerRangeMonitorSubsystemSafetyDesignBasis.TheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreases resultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAveragePowerRangeMonitorSubsystem arenolongerrequired.

7.5.7.3 DeleteSection7.5.7.3,AveragePowerRangeMonitorSubsystemDescription.TheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreasesresulting fromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAPRMSarenolongerrequired;theAPRMS Descriptionprovidedisnotapplicable.InformationregardingtheAPRMSisobsolete.

7.5.7.4 DeleteSection7.5.7.4,AveragePowerRangeMonitorSubsystemSafetyEvaluationTheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreases resultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAPRMSarenolongerrequired;asafety evaluationoftheAPRMSisnotrequiredsincethefunctionsoftheAPRMSarenotrequired.InformationregardingtheAPRMSisobsolete.

7.5.7.5 DeleteSection7.5.7.5,AveragePowerRangeMonitorSubsystemSafetyEvaluationTheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreases resultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheAveragePowerRangeMonitorSubsystem arenolongerrequired;apowergenerationevaluationisnotapplicable.

Description PowerGenerationEvaluation InspectionandTesting AveragePowerRangeMonitorSubsystem SafetyDesignBasis PowerGenerationDesignBasis PowerGenerationDesignBasis Description SafetyEvaluation PowerGenerationEvaluation Page52of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.7.6 DeleteSection7.5.7.5,AveragePowerRangeMonitorSubsystemSafetyEvaluationTheAPRMSfunctionedtogenerateascramtripsignalinresponsetoaverageneutronfluxincreases resultingfromabnormaloperationaltransientsintimetopreventfueldamage,providedacontinuousindicationofaveragereactorpowerandprovidedtripsignalforblockingrodwithdrawal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheAPRMSisnotrequiredsincethe functionsoftheAPRMSarenotrequired.InformationregardingtheAPRMSisobsolete.

7.5.8 7.5.8.1 DeleteSection7.5.8.1,RodBlockMonitorSubsystemPowerGenerationDesignBasis.TheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorunderthe worstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRodBlockMonitorSubsystemarenolonger required.TheRBMShasbeencategorizedasabandonedinaccordancewithEC48455.

7.5.8.2 DeleteSection7.5.8.2,RodBlockMonitorSubsystemPowerGenerationDescription.TheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorunderthe worstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRBMSarenolongerrequired;theRBMS Descriptionprovidedisnotapplicable.TheRBMShasbeencategorizedasabandonedinaccordancewithEC48455.InformationregardingtheRBMSisobsolete.

7.5.8.3 DeleteSection7.5.8.3,RodBlockMonitorSubsystemPowerGenerationEvaluationTheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorunderthe worstpermittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheRodBlockMonitorSubsystemarenolonger required;apowergenerationevaluationisnotapplicable.

7.5.8.4 DeleteSection7.5.8.4,RodBlockMonitorSubsystemInspectionandTesting.TheRBMSfunctionedtopreventlocalfueldamageasaresultofasinglerodwithdrawalerrorundertheworst permittedconditionofRBMbypass.RBMSalsoprovidedasignaltopermitoperatorevaluationofthechangeinthelocalrelativepowerlevelduringcontrolrodmovement.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheRBMSisnotrequiredsincethe functionsoftheRBMSarenotrequired.InformationregardingtheRBMSisobsolete.

7.5.9 7.5.9.1 DeleteSection7.5.9.1,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutron fluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRM gains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheTIPSubsystemarenolongerrequired.

7.5.9.2 DeleteSection7.5.9.2,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutron fluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRM gains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheTIPSarenolongerrequired;theTIPS Descriptionprovidedisnotapplicable.InformationregardingtheTIPSisobsolete.

7.5.9.3 DeleteSection7.5.9.3,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutron fluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRM gains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheTraversingIncoreProbeSubsystemareno longerrequired;apowergenerationevaluationisnotapplicable.

PowerGenerationEvaluation Description PowerGenerationEvaluation InspectionandTesting TraversingIncoreProbeSubsystem PowerGenerationDesignBasis Description InspectionandTesting RodBlockMonitorSubsystem PowerGenerationDesignBasis Page53of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.5.9.4 DeleteSection7.5.9.4,TraversingIncoreProbeSubsystemPowerGenerationDesignBasis.TheTIPSprovidedasignalproportionaltothegammaflux,whichwasrelatedtotheaxialneutron fluxdistributionatselectedsmallaxialintervalsovertheregionsofthecorewhereLPRMdetectorassemblieswerelocated.ThissignalwashighprecisiontoallowreliablecalibrationofLPRM gains.TheTIPSalsoprovidedaccurateindicationofthepositionofthefluxmeasurementwhichallowedapointwiseorcontinuousmeasurementoftheaxialgammafluxdistribution.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,inspectionandtestingoftheTIPSisnotrequiredsincethe functionsoftheTIPSarenotrequired.InformationregardingtheTIPSisobsolete.

7.5.10 DeleteSection7.5.10,References.Sincetheneutronmonitoringsubsystemshaveallbeenabandonedthesereferencesnolongerapply.

Table7.5.1 DeleteTable7.5.1,SRMTrips.SinceSection7.5.4,SRMSubsystemhasbeendeleted,atablelistingSRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.2 DeleteTable7.5.2,IRMTrips.SinceSection7.5.5,IRMSubsystemhasbeendeleted,atablelistingIRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.3 DeleteTable7.5.3LPRMTrips.SinceSection7.5.6,LPRMSubsystemhasbeendeleted,atablelistingLPRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.4 DeleteTable7.5.4,APRMTrips.SinceSection7.5.7,APRMSubsystemhasbeendeleted,atablelistingAPRMtripsisnolongerrequired.Thisinformationisobsolete Table7.5.5 DeleteTable7.5.5,RBMTrips.SinceSection7.5.8,RBMSubsystemhasbeendeleted,atablelistingRBMtripsisnolongerrequired.Thisinformationisobsolete Figure7.51 DeleteFigure7.51,StartupRangeNeutronMonitor,InstrumentElectricalDiagram.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.51isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.52 DeleteFigure7.52,SRM/IRMNeutronMonitoringUnit.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.52isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.53a DeleteFigure7.53a,DetectorDriveSystemSchematic.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.53aisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.53b DeleteFigure7.53b,SRM/IRMDetectorDriveSystem,FunctionalControlDiagram.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.53bisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

InspectionandTesting References SRMTrips IRMTrips LPRMTrips APRMTrips RBMTrips 5920270StartupRangeNeutronMonitor, InstrumentElectricalDiagram 5920495SRM/IRMNeutronMonitoringUnit DetectorDriveSystemSchematic 59201812SRM/IRMDetectorDriveSystem, FunctionalControlDiagram Page54of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.54 DeleteFigure7.54,FunctionalBlockDiagramofSRMChannel.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.54isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.55 DeleteFigure7.55,NeutronMonitoringSystem,FunctionalControlDiagram.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.55isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.56 DeleteFigure7.56,SourceRangeMonitoringSystemCoreLocations.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.56isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.57 DeleteFigure7.57,FunctionalBlockDiagramofIRMChannel.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.57isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.58 DeleteFigure7.58,IRMLocations.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.58isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.59 PreviouslyDeleted Figure7.510 PreviouslyDeleted Figure7.511 DeleteFigure7.511,PowerRangeNeutronMonitoring,InstrumentElectricalDiagram.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.511isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Deleted 5920271PowerRangeNeutronMonitoring, InstrumentElectricalDiagram FunctionalBlockDiagramofSRMChannel 59201807NeutronMonitoringSystem, FunctionalControlDiagram SourceRangeMonitoringSystemCoreLocations FunctionalBlockDiagramofIRMChannel IRMLocations Deleted Page55of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.512 DeleteFigure7.512,LPRMLocations.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.512isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.513 DeleteFigure7.513,PowerRangeNeutronMonitoringUnit.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.513isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.5 14a DeleteFigure7.514a,LPRMtoAPRMAssignmentScheme(SystemA).

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.514aisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.5 14b DeleteFigure7.514b,LPRMtoAPRMAssignmentScheme(SystemB).

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.514bisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.515 DeleteFigure7.515,APRMTracking,ReductioninPowerByFlowControl.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.515isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.516 DeleteFigure7.516,APRMTrackingWithOnLimitsControlRodWithdrawal.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.516isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

LPRMLocations 5920496PowerRangeNeutronMonitoringUnit LPRMtoAPRMAssignmentScheme(SystemA)

LPRMtoAPRMAssignmentScheme(SystemB)

APRMTracking,ReductioninPowerByFlow Control APRMTrackingWithOnLimitsControlRod Withdrawal Page56of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.517 DeleteFigure7.517,AssignmentofLPRMAssembliestoRBM's.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.517isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.518 DeleteFigure7.518,RBMChannelA+CResponsetoControlRodMotion.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.518isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.519 DeleteFigure7.519,RBMChannelB+DResponsetoControlRodMotion.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.519isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.520 DeleteFigure7.520,AssignmentofLPRMStringstoTIPMachines.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.520isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.521 DeleteFigure7.521,TraversingIncoreProbeSubsystemBlockDiagram.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.521isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.522 DeleteFigure7.522,GammaTraversingIncoreProbeAssembly.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.522isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

TraversingIncoreProbeSubsystemBlock Diagram 59209365GammaTraversingIncoreProbe Assembly AssignmentofLPRMAssembliestoRBM's RBMChannelA+CResponsetoControlRod Motion RBMChannelB+DResponsetoControlRod Motion AssignmentofLPRMStringstoTIPMachines Page57of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.5 23a DeleteFigure7.523a,NeutronMonitoringSystemArrangement.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.523aisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.5 23b DeleteFigure7.523b,NeutronMonitoringSystemArrangement.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.523bisnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.524 DeleteFigure7.524,TraversingIncoreProbe,FunctionalControlDiagram.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.524isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.525 DeleteFigure7.525,RangesofNeutronMonitoringSystem.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.525isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.526 DeleteFigure7.526,IRMCircuitArrangementforReactorProtectionSystemInput.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.526isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

Figure7.527 DeleteFigure7.527,TypicalAPRMCircuitArrangementforReactorProtectionSystemInput.

TheNeutronMonitoringSystemdetectedconditionsinthecorethatthreatenedtheoverallintegrityofthefuelbarrierduetoexcessivepowergenerationandprovidedsignalstotheReactor ProtectionSystem,sothatthereleaseofradioactivematerialfromthefuelbarrierwaslimited.TheNeutronMonitoringSystemalsoprovidedinformationfortheefficient,expedientoperation andcontrolofthereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheNeutronMonitoringSystemarenolonger required,theinformationprovidedonFigure7.527isnolongerapplicable.InformationregardingtheNeutronMonitoringSystemisobsoletesincethereisnocoretooperateandprotect.

7.6 IRMCircuitArrangementforReactorProtection SystemInput TypicalAPRMCircuitArrangementforReactor ProtectionSystemInput REFUELINGINTERLOCKS 5920426NeutronMonitoringSystem Arrangement 5920427NeutronMonitoringSystem Arrangement 59201813TraversingIncoreProbe,Functional ControlDiagram RangesofNeutronMonitoringSystem Page58of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.6.1 DeleteSection7.6.1,RefuelingInterlocksPowerGenerationObjective.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperational proceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationof refuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.RefuelingInterlocksinformationisobsolete.

7.6.2 DeleteSection7.6.2,RefuelingInterlocksPowerGenerationDesignBases.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperational proceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationof refuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.RefuelingInterlocksinformationisobsolete.

7.6.3 DeleteSection7.6.3,RefuelingInterlocksDescription.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthat prohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedintheRefuelingInterlocksDescriptionSectionisnolongerapplicable.Refueling Interlocksinformationisobsolete.

7.6.4 DeleteSection7.6.4,RefuelingInterlocksInspectionandTesting.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalprocedures thatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefueling equipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired,Therefore,inspectionandtestingoftherefuelinginterlocksisnolongerrequired.RefuelingInterlocks informationisobsolete.

Table7.6.1 DeleteTable7.6.1,RefuelingInterlockEffectiveness.Sinceitisnolongerpossibletoloadanuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventan inadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,thepreventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.Therefore,a tablelistingtheeffectivenessoftherefuelinginterlocksisnolongerrequired.RefuelingInterlocksinformationisobsolete.

Figure7.61 DeleteFigure7.61,RefuelingInterlocks.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefuelingoperationsbyreinforcingoperationalproceduresthatprohibitedtaking thereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementofcontrolrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedonFigure7.61isnolongerapplicable.RefuelingInterlocksinformationis obsolete.

Figure7.62A DeleteFigure7.62A,ControlRodDriveHydraulicSystem,RefuelingInterlocks,FunctionalControlDiagram.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefueling operationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementof controlrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedonFigure7.62Aisnolongerapplicable.RefuelingInterlocksinformationis obsolete.

Figure7.62B DeleteFigure7.62B,ControlRodDriveHydraulicSystem,RefuelingInterlocks,FunctionalControlDiagram.Therefuelinginterlockspreventedaninadvertentcriticalityduringrefueling operationsbyreinforcingoperationalproceduresthatprohibitedtakingthereactorcriticalundercertainsituationsencounteredduringrefuelingoperationsbyrestrictingthemovementof controlrodsandtheoperationofrefuelingequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,refuelingoperationswillnolongeroccurandprotectivefunctionstopreventaninadvertentcriticalityduringrefuelingoperationsarenolongerrequired.Consequently,the preventativefunctionsprovidedbytheRefuelingInterlocksarenolongerrequired.TheinformationprovidedonFigure7.62Bisnolongerapplicable.RefuelingInterlocksinformationis obsolete.

PowerGenerationObjective PowerGenerationDesignBases Description InspectionandTesting RefuelingIntelockEffectiveness RefuelingInterlocks ControlRodDriveHydraulicSystem, RefuelingInterlocks,FunctionalControl Diagram59201638 ControlRodDriveHydraulicSystem, RefuelingInterlocks,FunctionalControl Diagram59201639 Page59of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.7 TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

7.7.1 DeleteSection7.7.1,ReactorManualControlSystemPowerGenerationObjective.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclear reactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur,itisnolongerpossibletochangecorenuclearreactivityandcontrolrodmanipulationwillnolongeroccur.Consequently,thefunctions providedbytheReactorManualControlSystemarenolongerrequired.ReactorManualControlSysteminformationisobsolete.

7.7.2 DeleteSection7.7.2,ReactorManualControlSystemSafetyDesignBases.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivityso thatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur,itisnolongerpossibletochangecorenuclearreactivityandcontrolrodmanipulationwillnolongeroccur.Consequently,thefunctions providedbytheReactorManualControlSystemarenolongerrequired.SafetyDesignBasesfortheReactorManualControlSystemarenolongerapplicable.ReactorManualControlSystem informationisobsolete.

7.7.3 DeleteSection7.7.3,ReactorManualControlSystemPowerGenerationDesignBases.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclear reactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur,itisnolongerpossibletochangecorenuclearreactivityandcontrolrodmanipulationwillnolongeroccur.Consequently,thefunctions providedbytheReactorManualControlSystemarenolongerrequired.PowerGenerationDesignBasesfortheReactorManualControlSystemarenolongerapplicable.ReactorManual ControlSysteminformationisobsolete.

7.7.4 7.7.4.1 DeleteSection7.7.4.1,ReactorManualControlSystemDescription,Identification.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclear reactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired;theinformationprovidedtoidentifythecomponentsoftheReactorManualControlSystemisnolongerapplicable.ReactorManualControlSysteminformationis obsolete.

7.7.4.2 DeleteSection7.7.4.2,ReactorManualControlSystemDescription,Operation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivity sothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired;theinformationprovidedtodescribetheoperationoftheReactorManualControlSystemisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

7.7.4.3 DeleteSection7.7.4.3,ReactorManualControlSystemDescription,RodBlockInterlocks.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclea reactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystem, includingrodblocks,arenolongerrequired;theinformationprovidedtodescribethemanagementofcontrolrodblocksbytheReactorManualControlSystemisnolongerapplicable.Reactor ManualControlSysteminformationisobsolete.

7.7.4.4 DeleteSection7.7.4.4,ReactorManualControlSystemDescription,Instrumentation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclear reactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystem, includingrodblocks,arenolongerrequired;theinformationprovidedtodescribethemanagementofcontrolrodblocksbytheReactorManualControlSystemisnolongerapplicable.Reactor ManualControlSysteminformationisobsolete.

RodBlockInterlocks Instrumentation PowerGenerationObjective SafetyDesignBases PowerGenerationDesignBases Description Identification Operation REACTORMANUALCONTROLSYSTEM Page60of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.7.5 DeleteSection7.7.5,ReactorManualControlSystemSafetyEvaluation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysotha reactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsoftheReactorManualControlSystemarenolonger required;asafetyevaluationoftheReactorManualControlSystemisnotrequiredsincethefunctionsoftheRMCSarenotrequired.InformationregardingtheRMCSisobsolete.

7.7.6 DeleteSection7.7.6,ReactorManualControlSystemSafetyEvaluation.TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysotha reactorpowerlevelandpowerdistributioncouldbecontrolled.Thesystemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorManualControlSystem arenolongerrequired.Therefore,inspectionandtestingoftheReactorManualControlSystemisnolongerrequired.ReactorManualControlSysteminformationisobsolete.

Table7.7.1 DeleteTable7.7.1,ReactorManualControlSystemInstrumentation.Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorManualControlSystemarenolongerrequired.Therefore,atablelistingtheReactorManualControl SystemInstrumentationisnolongerrequired.ReactorManualControlSysteminformationisobsolete.

Figure7.71a DeleteFigure7.71a,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.71aisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.71b DeleteFigure7.71b,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.71bisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.71c DeleteFigure7.71c,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.71cisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.71d DeleteFigure7.71d,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.71disnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.71e DeleteFigure7.71e,ControlRodDriveHydraulicSystem,FunctionalControlDiagram.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.71eisnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

SafetyEvaluation InspectionandTesting ReactorManualControlSystemInstrumentation 5920307ControlRodDriveHydraulicSystem, FunctionalControlDiagram 5920308ControlRodDriveHydraulicSystem, FunctionalControlDiagram 59201636ControlRodDriveHydraulicSystem, FunctionalControlDiagram 59201637ControlRodDriveHydraulicSystem, FunctionalControlDiagram 59201638ControlRodDriveHydraulicSystem, FunctionalControlDiagram Page61of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.72 DeleteFigure7.72,ReactorControlBoard.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.72isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.73 DeleteFigure7.73,RBMFlowVarianceCircuit,Schematic.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.73isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.74 DeleteFigure7.74,InputSignalstoFourRodDisplay.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.74isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

Figure7.75 DeleteFigure7.75,ControlRodPositionsDisplayTypicalProcessComputerPrintout.

TheReactorManualControlSystemprovidedtheoperatorwiththemeanstomakechangesinnuclearreactivitysothatreactorpowerlevelandpowerdistributioncouldbecontrolled.The systemallowedtheoperatortomanipulatecontrolrods.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorManualControlSystemare nolongerrequired.TheinformationprovidedonFigure7.75isnolongerapplicable.ReactorManualControlSysteminformationisobsolete.

7.8 Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontrolofthese parameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowed byapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

7.8.1 DeleteSection7.8.1,ReactorVesselInstrumentation,PowerGenerationObjective.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvessel operatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthat thelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafety analyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired;theRVIPowerGenerationObjectiveisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

7.8.2 DeleteSection7.8.2,ReactorVesselInstrumentation,SafetyObjective.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperating parametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired;theRVISafetyObjectiveisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

InputSignalstoFourRodDisplay ControlRodPositionsDisplayTypicalProcess ComputerPrintout REACTORVESSELINSTRUMENTATION PowerGenerationObjective SafetyObjective ReactorControlBoard RBMFlowVarianceCircuit,Schematic Page62of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.8.3 DeleteSection7.8.3,ReactorVesselInstrumentation,PowerGenerationDesignBases.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvessel operatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthat thelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafety analyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired;theRVIPowerGenerationDesignBasesarenolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

7.8.4 DeleteSection7.8.4,ReactorVesselInstrumentation,SafetyDesignBases.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperating parametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired;theRVISafetyDesignBasesarenolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

7.8.5 7.8.5.1 DeleteSection7.8.5.1,ReactorVesselInstrumentation,ReactorVesselSurfaceTemperature.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactor vesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuch thatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystation safetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVessel SurfaceTemperatureInstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselSurfaceTemperatureInstrumentationisnolongerapplicable.Reactor VesselInstrumentationinformationisobsolete.

7.8.5.2 DeleteSection7.8.5.2,ReactorVesselInstrumentation,ReactorVesselWaterLevel.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvessel operatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthat thelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafety analyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVessel WaterLevelInstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselWaterLevelInstrumentationisnolongerapplicable.ReactorVessel Instrumentationinformationisobsolete.

7.8.5.3 DeleteSection7.8.5.3,ReactorVesselInstrumentation,ReactorVesselCoolantFlowRatesandDifferentialTemperatures.Reactorvesselinstrumentationmonitoredandtransmitted informationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseof radioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperating conditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactor VesselCoolantFlowRatesandDifferentialTemperaturesInstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselCoolantFlowRatesandDifferential Temperaturesinstrumentationisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

7.8.5.4 DeleteSection7.8.5.4,ReactorVesselInstrumentation,ReactorVesselInternalPressure.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvessel operatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthat thelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafety analyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVessel InternalPressurearenolongerrequired;theinformationprovidedtodescribetheReactorVesselInternalPressureinstrumentationisnolongerapplicable.ReactorVesselInstrumentation informationisobsolete.

SafetyDesignBases Description ReactorVesselSurfaceTemperature ReactorVesselWaterLevel ReactorVesselCoolantFlowRates andDifferentialTemperatures ReactorVesselInternalPressure PowerGenerationDesignBases Page63of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.8.5.5 DeleteSection7.8.5.5,ReactorVesselInstrumentation,ReactorVesselTopHeadFlangeLeakDetection.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkey reactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtothe environssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsidered bystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReactorVesselTop HeadFlangeLeakDetectioninstrumentationarenolongerrequired;theinformationprovidedtodescribetheReactorVesselTopHeadFlangeLeakDetectioninstrumentationisnolonger applicable.ReactorVesselInstrumentationinformationisobsolete.

7.8.5.6 DeleteSection7.8.5.6,ReactorVesselInstrumentation,ReferenceLegTemperatureMonitoring.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactor vesseloperatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuch thatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystation safetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheReferenceLeg TemperatureMonitoringinstrumentationarenolongerrequired;theinformationprovidedtodescribetheReferenceLegTemperatureMonitoringinstrumentationisnolongerapplicable.

ReactorVesselInstrumentationinformationisobsolete.

7.8.5.7 DeleteSection7.8.5.7,ReactorVesselInstrumentation,ReferenceLegBackFillSystem.TheBackFillSystemensuredthatthereactorwaterlevelreferencelegfluidforselectedcondensing chambersdidnotbecomesaturatedwithnoncondensiblegases.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReferenceLegBackFillSystemare nolongerrequired;theinformationprovidedtodescribetheReferenceLegBackfillSystemisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

7.8.5.8 DeleteSection7.8.5.8,ReactorVesselInstrumentation,SafetyValveLeakDetection.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvessel operatingparametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthat thelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafety analyses.

Anacousticaccelerometerinstalledoneachofthereactorvesselsafetyvalvesprovidedindirectindicationofvalveposition.Leakagewasalsodetectedbytemperatureelementsmountedon thereliefvalvetailpipes.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheSafetyValveLeak Detectioninstrumentationarenolongerrequired;theinformationprovidedtodescribetheSafetyValveLeakDetectioninstrumentationisnolongerapplicable.ReactorVesselInstrumentation informationisobsolete.

7.8.6 DeleteSection7.8.6,ReactorVesselInstrumentation,SafetyEvaluation.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperating parametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbyReactorVessel Instrumentationarenolongerrequired;asafetyevaluationoftheReactorVesselInstrumentationisnotrequiredsincethefunctionsandinformationprovidedbytheReactorVessel Instrumentationarenotrequired.InformationregardingReactorVesselInstrumentationisobsolete.

7.8.7 DeleteSection7.8.7,ReactorVesselInstrumentation,InspectionandTesting.Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperating parametersduringplannedoperationstoensurethatsufficientcontroloftheseparameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitst 10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowedbyapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorManualControlSystem arenolongerrequired.Therefore,inspectionandtestingoftheReactorManualControlSystemisnolongerrequired.ReactorManualControlSysteminformationisobsolete.

Table7.8.1 DeleteTable7.8.1,ReactorVesselInstrumentation.Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Consequently,thefunctionsandinformationprovidedbyReactorVesselInstrumentationarenolongerrequired.Therefore,atablelistingtheReactorVesselInstrumentationis nolongerrequired.ReactorVesselInstrumentationinformationisobsolete.

ReactorVesselInstrumentation ReactorVesselTopHeadFlangeLeak Detection ReferenceLegTemperature Monitoring ReferenceLegBackFillSystem SafetyValveLeakDetection SafetyEvaluation InspectionandTesting Page64of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.81 DeleteFigure7.81,NuclearSystemPressureReliefSystem,PipingandInstrumentationDiagram.

Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontrolofthese parameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowed byapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired.TheReactorVesselIndicationinformationprovidedonFigure7.81isnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

Figure7.82a DeleteFigure7.82a,ReactorVesselInstrumentationPipingandInstrumentationDiagram.

Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontrolofthese parameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowed byapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired.TheReactorVesselIndicationinformationprovidedonFigure7.82aisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

Figure7.82b DeleteFigure7.82b,ReactorVesselInstrumentationPipingandInstrumentationDiagram.

Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontrolofthese parameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowed byapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired.TheReactorVesselIndicationinformationprovidedonFigure7.82bisnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

Figure7.83 DeleteFigure7.83,ReactorVesselThermocoupleLocations.

Reactorvesselinstrumentationmonitoredandtransmittedinformationconcerningkeyreactorvesseloperatingparametersduringplannedoperationstoensurethatsufficientcontrolofthese parameterswaspossibleinordertoavoidareleaseofradioactivematerialtotheenvironssuchthatthelimitsto10CFR20wereexceeded,avoidnuclearsystemstressinexcessofthatallowed byapplicableindustrycodes,andavoidanyoperatingconditionsnotconsideredbystationsafetyanalyses.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheReactorVesselInstrumentationare nolongerrequired.TheReactorVesselthermocouplelocationinformationprovidedonFigure7.83isnolongerapplicable.ReactorVesselInstrumentationinformationisobsolete.

7.9 TheRecirculationFlowControlSystemcontrolledreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.

7.9.1 DeleteSection7.9.1,RecirculationFlowControlSystem,PowerGenerationObjective.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;theRecirculationFlowControlSystemPowerGenerationObjectiveisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

7.9.2 DeleteSection7.9.2,RecirculationFlowControlSystem,PowerGenerationDesignBases.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrange bycontrollingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;theRecirculationFlowControlSystemPowerGenerationDesignBasesarenolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

PowerGenerationObjective PowerGenerationDesignBases G191167NuclearSystemPressureRelief System,PipingandInstrumentationDiagram G191267,Sh1ReactorVesselInstrumentation PipingandInstrumentationDiagram G191267,Sh2ReactorVesselInstrumentation PipingandInstrumentationDiagram ReactorVesselThermocoupleLocations RECIRCULATIONFLOWCONTROLSYSTEM Page65of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.9.3 DeleteSection7.9.3,RecirculationFlowControlSystem,SafetyDesignBases.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;theRecirculationFlowControlSystemSafetyDesignBasesarenolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

7.9.4 7.9.4.1 DeleteSection7.9.4.1,RecirculationFlowControlSystem,GeneralDescription.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;theinformationprovidedintheGeneralDescriptionSectionoftheRecirculationFlowControlSystemisnolongerapplicable.RecirculationFlowControlSystem informationisobsolete.

7.9.4.2 DeleteSection7.9.4.2,RecirculationFlowControlSystem,MotorGeneratorSet.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;thedescriptionoftheRecirculationFlowControlSystemMotorGeneratorSetsprovidedisnolongerapplicable.RecirculationFlowControlSysteminformationis obsolete.

7.9.4.3 DeleteSection7.9.4.3,RecirculationFlowControlSystem,SpeedControlComponents.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;thedescriptionoftheRecirculationFlowControlSystemSpeedControlComponentsprovidedisnolongerapplicable.RecirculationFlowControlSysteminformationis obsolete.

7.9.4.4 DeleteSection7.9.4.4,RecirculationFlowControlSystem,SystemOperation.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;thedescriptionoftheRecirculationFlowControlSystemOperationprovidedisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

7.9.5 DeleteSection7.9.5,RecirculationFlowControlSystem,SafetyEvaluation.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrolling theflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;asafetyevaluationoftheRecirculationFlowControlSystemSystemisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

7.9.6 DeleteSection7.9.6,RecirculationFlowControlSystem,InspectionandTesting.TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangeby controllingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlSystem arenolongerrequired;InspectionandtestingoftheRecirculationFlowControlSystemSystemcomponentsisnolongerrequired.RecirculationFlowControlSysteminformationisobsolete.

7.9.7 DeleteSection7.9.7,References.SincethefunctionsprovidedbytheRecirculationFlowControlSystemarenolongerrequired,referencesarenolongerapplicable.

Figure7.91 DeleteFigure7.91,RecirculationFlowControl.

TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlareno longerrequired.TheinformationprovidedonFigure7.91regardingRecirculationFlowControlisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

Figure7.92 PreviouslyDeleted SafetyDesignBases Description General MotorGeneratorSet Deleted SpeedControlComponents SystemOperation SafetyEvaluation InspectionandTesting References RecirculationFlowControl Page66of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.93 DeleteFigure7.93,RecirculationFlowControlSystem,InstrumentElectricalDiagram.

TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlareno longerrequired.TheinformationprovidedonFigure7.93regardingRecirculationFlowControlisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

Figure7.94 DeleteFigure7.94,RecirculationFlowControlSystem,SpeedControlSystemInstrumentElectricalDiagram.

TheRecirculationFlowControlSystemfunctionedtocontrolreactorpowerleveloveralimitedrangebycontrollingtheflowrateofthereactorrecirculatingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRecirculationFlowControlareno longerrequired.TheinformationprovidedonFigure7.94regardingRecirculationFlowControlisnolongerapplicable.RecirculationFlowControlSysteminformationisobsolete.

Figure7.95 PreviouslyDeleted 7.10 TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

7.10.1 DeleteSection7.10.1,FeedwaterControlSystemPowerGenerationObjective.TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduring plannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheFeedwaterControlSystemareno longerrequired;TheFeedwaterControlSystempowergenerationobjectiveisnolongerapplicable.FeedwaterControlSysteminformationisobsolete.

7.10.2 DeleteSection7.10.2,FeedwaterControlSystemPowerGenerationDesignBases.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheFeedwaterControlSystemareno longerrequired;TheFeedwaterControlSystempowergenerationdesignbasesarenolongerapplicable.FeedwaterControlSysteminformationisobsolete.

7.10.3 7.10.3.1 DeleteSection7.10.3.1,FeedwaterControlSystemDescriptionofReactorVesselWaterLevelMeasurement.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;ReactorVesselWaterLevelMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

7.10.3.2 DeleteSection7.10.3.2,FeedwaterControlSystemDescriptionofSteamFlowMeasurement.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;SteamFlowMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

7.10.3.3 DeleteSection7.10.3.3,FeedwaterControlSystemDescriptionofFeedwaterFlowMeasurement.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;FeedwaterFlowMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

7.10.3.4 DeleteSection7.10.3.4,FeedwaterControlSystemDescriptionoftheFeedwaterFlowControlSignal.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;thedescriptionoftheFeedwaterControlSignalforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

PowerGenerationDesignBases Description ReactorVesselWaterLevel Measurement SteamFlowMeasurement FeedwaterFlowMeasurement FeedwaterControlSignal 5920279RecirculationFlowControlSystem, InstrumentElectricalDiagram 59201034RecirculationFlowControlSystem, SpeedControlSystemInstrumentElectrical Diagram Deleted FEEDWATERCONTROLSYSTEM PowerGenerationObjective Page67of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;thedescriptionofFeedwaterValveControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

7.10.3.6 DeleteSection7.10.3.6,FeedwaterControlSystemDescriptionofReactorVesselPressureMeasurement.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;ReactorVesselPressureMeasurementforFeedwaterControlisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

7.10.4 DeleteSection7.10.4,FeedwaterControlSystemInspectionandTesting.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheFeedwaterControl Systemarenolongerrequired;FeedwaterControlSystemInspectionandTestingisnolongerrequired.FeedwaterControlSysteminformationisobsolete.

Figure7.101 DeleteFigure7.101,FeedwaterControlSystem,InstrumentElectricalDiagram.

TheFeedwaterControlSystemfunctionedtomaintainapreestablishedwaterlevelinthereactorvesselduringplannedoperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheFeedwaterControlSystemareno longerrequired.TheFeedwaterControlSystemrelatedinformationprovidedonFigure7.101isnolongerapplicable.FeedwaterControlSysteminformationisobsolete.

7.11 ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

7.11.1 Deletesection7.11.1,PressureRegulatorandTurbineGeneratorControlSystemPowerGenerationObjective.

ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;thePressureRegulatorandTurbineGeneratorControlSystempowergenerationobjectiveisnolongerapplicable.Pressure RegulatorandTurbineGeneratorControlSysteminformationisobsolete.

7.11.2 Deletesection7.11.2,PressureRegulatorandTurbineGeneratorControlSystemPowerGenerationDesignBases ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;thePressureRegulatorandTurbineGeneratorControlSystempowergenerationdesignbasesarenolongerapplicable.The PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.

7.11.3 7.11.3.1 Deletesection7.11.3.1,PressureRegulatorandTurbineGeneratorControlSystemGeneralDescription.

ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedinthePressureRegulatorandTurbineGeneratorControlSystemGeneralDescriptionisnolonger applicable.PressureRegulatorandTurbineGeneratorControlSysteminformationisobsolete.

7.11.3.2 Deletesection7.11.3.2,PressureRegulatorandTurbineGeneratorControlSystemPressureRegulatorDescription.

ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedinthePressureRegulatorDescriptionsectionisnolongerapplicable.PressureRegulatorandTurbine GeneratorControlSysteminformationisobsolete.

PowerGenerationDesignBases Description General PressureRegulator FeedwaterValveControl ReactorVesselPressure Measurement InspectionandTesting 5920204FeedwaterControlSystem,Instrument ElectricalDiagram PRESSUREREGULATORANDTURBINEGENERATORCONTROL PowerGenerationObjective Page68of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedinthePressureRegulatorDescriptionsectionisnolongerapplicable.PressureRegulatorandTurbine GeneratorControlSysteminformationisobsolete.

7.11.3.4 Deletesection7.11.3.4,PressureRegulatorandTurbineBypassSystemControl.

ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;theinformationprovidedintheTurbineBypassSystemControlDescriptionsectionisnolongerapplicable.PressureRegulator andTurbineGeneratorControlSysteminformationisobsolete.

7.11.4 Deletesection7.11.4,PressureRegulatorandTurbineGeneratorControlSystemInspectionandTesting.

ThePressureRegulatorandTurbineGeneratorControlSystemfunctionedtocontrolsteamflowandpressuretotheturbineandtoprotecttheturbinefromoverpressureorexcessivespeed, withcontrolsintegratedwiththoseofthenuclearsystemsforanefficient,reliablepowergenerationunit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythePressureRegulator andTurbineGeneratorControlSystemarenolongerrequired;testingofthePressureRegulatorandTurbineGeneratorControlSystemcomponentsisnolongerrequired.PressureRegulator andTurbineGeneratorControlSysteminformationisobsolete.

7.12 4.7.1 7.12.1 TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthe releasedfissionproducts.

7.12.1.1 Deletesection7.12.1.1,MainSteamLineRadiationMonitoringSystem,SafetyObjective.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthe releasedfissionproducts.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLine RadiationMonitoringSystemarenolongerrequired;theMainSteamLineRadiationMonitoringSystemSafetyObjectiveisnolongerapplicable.MainSteamLineRadiationMonitoringSystem informationisobsolete.

7.12.1.2 Deletesection7.12.1.2,MainSteamLineRadiationMonitoringSystem,SafetyDesignBasis.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthe releasedfissionproducts.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLine RadiationMonitoringSystemarenolongerrequired;theMainSteamLineRadiationMonitoringSystemSafetyDesignBasisisnolongerapplicable.MainSteamLineRadiationMonitoring Systeminformationisobsolete.

7.12.1.3 Deletesection7.12.1.3,MainSteamLineRadiationMonitoringSystem,Description.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthe releasedfissionproducts.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theMainSteamLineRadiationMonitoringSystemfunctionsand informationoutlinedintheDescriptionsectionarenolongerapplicable.MainSteamLineRadiationMonitoringSysteminformationisobsolete.

7.12.1.4 Deletesection7.12.1.4,MainSteamLineRadiationMonitoringSystem,SafetyDesignBasis.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthe releasedfissionproducts.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLine RadiationMonitoringSystemarenolongerrequired;theMainSteamLineRadiationMonitoringSystemSafetyEvaluationisnolongerapplicable.MainSteamLineRadiationMonitoringSystem informationisobsolete.

PROCESSRADIATIONMONITORINGSYSTEM InspectionandTesting PROCESSRADIATIONMONITORINGSYSTEM MainSteamLineRadiationMonitoringSystem SafetyObjective SafetyDesignBasis TurbineGeneratorControls TurbineBypassSystemControl Description SafetyEvaluation Page69of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.12.1.5 Deletesection7.12.1.5,MainSteamLineRadiationMonitoringSystem,SafetyDesignBasis.

TheMainSteamLineMonitoringSystemmonitoredforthegrossreleaseoffissionproductsfromthefueland,uponindicationofsuchfailure,initiatedappropriateactiontocontainthe releasedfissionproducts.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheMainSteamLine RadiationMonitoringSystemarenolongerrequired;InspectionandtestingofthetheMainSteamLineRadiationMonitoringSystemcomponentsisnolongerrequired.MainSteamLine RadiationMonitoringSysteminformationisobsolete.

7.12.2 TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthe limitswerenotexceeded.

7.12.2.1 DeleteSection7.12.2.1,OffGasRadiationMonitoringSystemPowerGenerationObjective.

TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthe limitswerenotexceeded.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiation MonitoringSystemarenolongerrequired;theOffGasRadiationMonitoringSystemPowerGenerationObjectiveisnolongerapplicable.OffGasRadiationMonitoringSysteminformationis obsolete.

7.12.2.2 DeleteSection7.12.2.2,OffGasRadiationMonitoringSystemPowerGenerationDesignBasis.

TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthe limitswerenotexceeded.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiation MonitoringSystemarenolongerrequired;theOffGasRadiationMonitoringSystemPowerGenerationDesignBasisisnolongerapplicable.OffGasRadiationMonitoringSysteminformationis obsolete.

7.12.2.3 DeleteSection7.12.2.3,OffGasRadiationMonitoringSystemPowerGenerationDescription.

TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthe limitswerenotexceeded.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiation MonitoringSystemarenolongerrequired;InformationregardingtheOffGasRadiationMonitoringSystemprovidedintheDescriptionsectionisnolongerapplicable.OffGasRadiation MonitoringSysteminformationisobsolete.

7.12.2.4 DeleteSection7.12.2.2,OffGasRadiationMonitoringSystemInspectionandTesting.

TheOffGasRadiationMonitoringSystemindicatedwhenlimitsforthereleaseofradioactivematerialtotheenvironswereapproachedandinitiatedappropriatecontrolofoffgassothatthe limitswerenotexceeded.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheOffGasRadiation MonitoringSystemarenolongerrequired;InspectionandtestingoftheOffGasRadiationMonitoringSystemisnotrequired.OffGasRadiationMonitoringSysteminformationisobsolete.

7.12.3 4.7.1.1 7.12.3.1 ModifySection7.12.3.1,PlantStackRadiationMonitorSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

4.7.1.1.1 7.12.3.2 ModifySection7.12.3.1,PlantStackRadiationMonitorSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,releaseratevaluesaboveoperationalreleaseratelimitsdownto thereleaseratesnormallyencounteredduringhighpoweroperationcannolongeroccur.

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.AllPlantStackRadiationMonitoring SystemtestingrequirementshavebeenremovedfromtheTechnicalSpecifications.

4.7.1.1.4 7.12.4 4.7.1.2 7.12.4.1 ModifySection7.12.4.1,ProcessLiquidRadiationMonitorSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions.

4.7.1.2.1 7.12.4.2 ModifySection7.12.4.2,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 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.12.4.3 ModifySection7.12.4.3,ProcessLiquidRadiationMonitorSystem,Descriptiontoremovereferencetooperatingandaccidentconditions,theReactorBuildingClosedCoolingWaterSystemand theRHRServiceWaterSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbyRBCCWandRHRServiceWaterareno longerrequired.Consequently,processradiationmonitoringofthosesystemsisnolongerrequiredandhasbeenremoved.InformationregardingtheRBCCWandRHRprocessradiation monitorsisobsolete.

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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed..Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolonger required.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

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

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed..Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolonger required.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

4.7.1.3.2 7.12.5.3 Modifiedsection7.12.5.3toremovereferencetoinitiationofisolationandtripsignalsbasedonRBVhighradiation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.LicenseAmendment262,approvedbytheNRCinFebruary2015,eliminated operabilityrequirementsforsecondarycontainment,theStandbyGasTreatment(SGT)system,andthereactorbuildingventilationisolationandtheSGTsysteminitiationinstrumentation whenhandlingirradiatedfuelorafuelcask.Thechangesrequirethesubjectsystemstobeoperableonlyduringmovementof"recently"irradiatedfuelassembliesinsecondarycontainment andduringoperationswiththepotentialtodrainthereactorvessel.Theperiodofsufficientradioactivedecaywasdeterminedtobe13days.SinceVYNPScertifiedpermanentdefuelingin January2015,allfuelinthefuelpoolisconsideredsufficientlydecayed.Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiationLevelsarenolonger required.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

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

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Analysishasdemonstratedthatsecondarycontainmentisnolongerrequired tomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Consequently,automaticprotectiveactionsbasedonReactorBuildingVentilationRadiation Levelsarenolongerrequired.ReactorBuildingVentRadmonitoringwillprovideonlyalarmfunctions.

4.7.1.3.4 7.12.5.5 ModifiedSection7.12.5.5todeletereferencetoTechnicalSpecificationssinceVYwillneverbeinamodeinwhichthesurveillancerequirementswillapply.

4.7.1.3.5 7.12.6 TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

7.12.6.1 DeleteSection7.12.6.1,ContainmentHighRangeRadiationMonitoringSystem,SafetyObjective.

TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHigh RangeRadiationMonitoringSystemarenolongerrequired;theContainmentHighRangeRadiationMonitoringSystemSafetyObjectiveisnolongerapplicable.ContainmentHighRange RadiationMonitoringSysteminformationisobsolete.

ReactorBuildingVentilationRadiationMonitoring System Description InspectionandTesting ReactorBuildingVentilationRadiationMonitoring System SafetyEvaluation InspectionandTesting ContainmentHighRangeRadiationMonitoring System SafetyObjective SafetyObjective SafetyDesignBasis Description Description InspectionandTesting Objective DesignBasis Description Evaluation InspectionandTesting Page71of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHigh RangeRadiationMonitoringSystemarenolongerrequired;theContainmentHighRangeRadiationMonitoringSystemSafetyDesignBasisisnolongerapplicable.ContainmentHighRange RadiationMonitoringSysteminformationisobsolete.

7.12.6.3 DeleteSection7.12.6.3,ContainmentHighRangeRadiationMonitoringSystem,Description.

TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHigh RangeRadiationMonitoringSystemarenolongerrequired;theinformationregardingtheContainmentHighRangeRadiationMonitoringSystemprovidedintheDescriptionsectionisno longerapplicable.ContainmentHighRangeRadiationMonitoringSysteminformationisobsolete.

7.12.6.4 DeleteSection7.12.6.4,ContainmentHighRangeRadiationMonitoringSystem,SafetyDesignBasis.

TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHigh RangeRadiationMonitoringSystemarenolongerrequired;aContainmentHighRangeRadiationMonitoringSystemSafetyevaluationisnolongerrequired.ContainmentHighRangeRadiation MonitoringSysteminformationisobsolete.

7.12.6.5 DeleteSection7.12.6.5,ContainmentHighRangeRadiationMonitoringSystem,InspectionandTesting.

TheContainmentHighRangeRadiationMonitoringSystemmonitoredthecontainmentatmosphereforthegrossreleaseoffissionproductsduringaLOCA/HELB.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheContainmentHigh RangeRadiationMonitoringSystemarenolongerrequired;InspectionandTestingoftheContainmentHighRangeRadiationMonitoringSystemisnolongerrequired.ContainmentHighRange RadiationMonitoringSysteminformationisobsolete.

Table7.12.1 ModifiedtodeleteMainSteamLine,MainCondenserAEOffgas,AugmentedOffgas,andContainmentHighRangeRadmonitors.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythelistedradiation monitorsarenolongerrequired.

ModifyTable7.12.1todeletesensitivitycolumn.Pertechnicalreview,informationprovidedinthiscolumnisnotmeaningfulandisnotrequired.

Table4.7.1.1 Table7.12.2 Nochanges Table4.7.1.2 Table7.12.3 Nochanges Table4.7.1.3 Figure7.121 ModifytodeleteMainSteamLine,MainCondenserAEOffgas,AugmentedOffgas,andContainmentHighRangeRadmonitors.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbythelistedradiation monitorsarenolongerrequired.

Figure4.7.1 1

Figure7.122 Nochanges Figure4.7.1 2

7.13 4.7.2 7.13.1 ModifiedSection7.13.1todeletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1which isnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

4.7.2.1 7.13.2 ModifiedSection7.13.2todeletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1which isnolongerused,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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemareno longerrequired.ThereforethefunctionsandinformationprovidedbytheReactorContainmentAirborneRadiationMonitoringSystemarenolongerapplicableandareobsolete.

4.7.2.3.1 7.13.3.2 NoChanges 4.7.2.3.2 ProcessRadiationMonitoringEnvironmentalandPowerSupply DesignConditions PlantStackRadiationMonitorSystemCharacteristics 592000526ProcessRadiationMonitoringSystem InstrumentationDiagram 592003994PlantStackRadiationMonitoringSystemDiagram AREARADIATIONMONITORINGSYSTEM Objective DesignBases Description ProcessRadiationMonitoringEnvironmentatal andPowerSupplyDesignConditions PlantStackRadiationMonitorSystem Characteristics 592000526ProcessRadiationMonitoring SystemInstrumentationDiagram SafetyDesignBasis Description SafetyEvaluation InspectionandTesting ProcessRadiationMonitoringSystem Characteristics Locations PowerGenerationDesignBases Description Monitors 59203994PlantStackRadiationMonitoring SystemDiagram AREARADIATIONMONITORINGSYSTEM PowerGenerationObjective ProcessRadiationMonitoringSystemCharacteristics Monitors Locations Page72of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.13.4 ModifySection7.13.4,InspectionandTesting,todeleteallreferencetotheReactorContainmentAirborneRadiationMonitoringSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemareno longerrequired.ThereforethefunctionsandinformationprovidedbytheReactorContainmentAirborneRadiationMonitoringSystemarenolongerapplicableandareobsolete.

4.7.2.4 Table7.13.1 ModifyTable7.13.1,todeletereferencetotheVermontYankeeEnvironmentalQualificationProgram.FollowingcertificationofpermanentdefuelingtheprotectionprovidedbytheVYEQ programisnolongerrequiredandisobsolete.

Table4.7.2.1 Table7.13.2 NoChanges Table4.7.2.2 Table7.13.3 ModifyTable7.13.3todeleteallreferencetotheReactorContainmentAirborneRadiationMonitoringSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsofthePrimaryContainmentSystemareno longerrequired.ThereforethefunctionsandinformationprovidedbytheReactorContainmentAirborneRadiationMonitoringSystemarenolongerapplicableandareobsolete.

Table4.7.2.3 Table7.13.4 NoChanges Table4.7.2.4 Figure7.131 NoChanges Figure4.7.2 1

Figure7.132 NoChanges Figure4.7.2 2

Figure7.133 DeleteFigure7.133.AllreferencetotheReactoContainmentAirborneRadiationMonitoringSystemhasbeendeleted.Systemfunctionsarenolongerrequired.

7.14 Editorialandsectiontitlechangeonly 4.3 7.14.1 Editorialandsectiontitlechangeonly 4.3.1 7.14.2 Editorialandsectiontitlechangeonly 4.3.2 7.14.2.1 Editorialandsectiontitlechangeonly 4.3.2 7.14.2.2 Editorialandsectiontitlechangeonly 4.3.2 7.15 3.3.11 7.15.1 ModifySection7.15.1,ProcessComputerSystem,PowerGenerationObjectivetoremovereferencetocorethermalhydraulicconditiondetermination.DeletereferencetoERDS.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corethermalhydraulicconditionsnolongerexist.Additionally, ERDSisnolongerrequired,refertoFCR27/017.

3.3.11.1 7.15.2 ModifySection7.15.2,ProcessComputerSystem,PowerGenerationDesignBasestoremovereferencetocorepowerandthermalhydraulicconditiondetermination,EOPentrycondition determination,marginanddisplayplotdetermination,criticalplantparametersandERDS.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepower,thermalhydraulicconditions,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 ComputerSystem Components TechnicalSupportCenterAreaAirborneRadiationMonitoring System Objectives DesignBases Description LocationsofAreaRadiationMonitors ReactorBuildingAreaAirborneRadiationMonitoringSystem InspectionandTesting LocationsofAreaRadiationMonitors ReactorContainmentandReactorBuildingArea AirborneRadiationMonitoringSystem InspectionandTesting AreaRadiationMonitoringSystem, EnvironmentalandPowerSupplyDesign Conditions PortableInstrumentation FixedandLaboratory Instrumentation PROCESSCOMPUTERSYSTEM HEALTHPHYSICSINSTRUMENTATION PowerGenerationObjective Description 5920430Sheet1AreaRadiationMonitoring System,FunctionalBlockDiagram ReactorBuildingAreaAirborneRadiation MonitoringSystem ReactorContainmentAreaAirborneRadiation MonitoringSystem 5920430Sheet1AreaRadiationMonitoringSystem,Functional BlockDiagram ReactorBuildingAreaAirborneRadiationMonitoringSystem Objective Description HEALTHPHYSICSINSTRUMENTATION PortableInstrumentation FixedandLaboratoryInstrumentation TechnicalSupportCenterAreaAirborne RadiationMonitoringSystem PROCESSCOMPUTERSYSTEM ComputerSystemComponents PowerGenerationObjective PowerGenerationDesignBases Description AreaRadiationMonitoringSystem,EnvironmentalandPower SupplyDesignConditions Page73of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.15.3.2 Deletesection7.15.3.2,ReactorCorePerformanceFunction.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,reactorcoreperformancecannolongerbedeterminedandthe performancedeteminationfunctionoftheProcessComputerisnolongerrequired.

7.15.3.3 Deletesection7.15.3.3,RodWorthMinimizerFunction.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRodWorthMinimizerarenolonger required.RodWorthMinimizerinformationisobsolete.

7.15.3.4 ModifySection7.15.3.4,MonitorAlarmandLoggingFunctionstodeletereferencetoPostMortemLogging Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionand informationprovidedbythepostmortemloggingfeaturearenolongerrequired.

3.3.11.3.2 MonitorAlarmand LoggingFunctions 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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thePPCinputslistedinthetablearenolongervalid.

Table7.15.2 DeleteTable7.15.2,INSTRUMENTATIONOUTPUT

SUMMARY

SIGNALOUTPUTDESCRIPTION.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theTIP,RPISandRWMoutputslistedintable7.15.2arenolonger valid.Theremainingfouroutputsarenotsignificantanddonotwarrantlistingonatable.

Figure7.151 DeleteFigure7.151,RodWorthMinimizerFunctionalControlDiagram.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheRodWorthMinimizerarenolonger required.TheinformationprovidedonFigure7.151isnotapplicable.RodWorthMinimizerinformationisobsolete.

7.16 TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

7.16.1 DeleteSection7.16.1,NuclearSystemStabilityAnalysis,SafetyObjective.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsand informationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theNuclearSystemStabilityAnalysisSafetyObjectiveisnolongerapplicable.NuclearSystem StabilityAnalysisinformationisobsolete.

7.16.2 DeleteSection7.16.2,NuclearSystemStabilityAnalysis,SafetyDesignBasis TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsand informationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theNuclearSystemStabilityAnalysisSafetyDesignBasisisnolongerapplicable.Nuclear SystemStabilityAnalysisinformationisobsolete.

7.16.3 DeleteSection7.16.3,NuclearSystemStabilityAnalysis,PowerGenerationDesignBasis TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsand informationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theNuclearSystemStabilityAnalysisPowerGenerationDesignBasisisnolongerapplicable.

NuclearSystemStabilityAnalysisinformationisobsolete.

InspectionandTesting CyberSecurity ProcessComputerDataFeedtothePlant DataServer(PDS)

MonitorAlarmandLogging Functions InspectionandTesting CyberSecurity ReactorCorePerformanceFunction RodWorthMinimizerFunction SafetyDesignBasis PowerGenerationDesignBasis InstrumentationInputSummary INSTRUMENTATIONOUTPUT

SUMMARY

SIGNALOUTPUTDESCRIPTION 59201640RodWorthMinimizer,Functional ControlDiagram NuclearSystemStabilityAnalysis SafetyObjective Page74of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.16.4 DeleteSection7.16.4,NuclearSystemStabilityAnalysis,ConformanceWithSafetyandPowerGenerationDesignBasis.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;demonstrationof ConformanceWiththeSafetyandPowerGenerationDesignBasisoftheNuclearSystemStabilityAnalysisisnolongerrequired.NuclearSystemStabilityAnalysisinformationisobsolete.

7.16.5 DeleteSection7.16.5,NuclearSystemStabilityAnalysis,DescriptionandPerformanceAnalysis.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;adescriptionofcore oscillationsandaperformanceanalysisdemonstratingadequacyofpreventionanddetectionofcoreoscillationsatVermontYankeeisnolongerrequired.NuclearSystemStabilityAnalysis informationisobsolete.

7.16.6 DeleteSection7.16.6,NuclearSystemStabilityAnalysis,Conclusions.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;aconclusionwhichstates thatVYisadequatelyprotectedfromcoreoscillationsandtheirconsequencesisnolongerrequired.NuclearSystemStabilityAnalysisinformationisobsolete.

7.16.7 DeleteSection7.16.5,NuclearSystemStabilityAnalysis,DescriptionandPerformanceAnalysis.

Sincecorepoweroscillationscannolongeroccur,thereferencesprovidedinsection7.16.7arenolongerapplicable.

Figure7.161 DeleteFigure7.161,BWROGStabilityCriteriaMap.

TheNuclearSystemStabilityAnalysisdemonstratedthatstabilityrelatedneutronfluxoscillationswillbepreventedordetectedandsuppressedpriortoexceedingspecifiedacceptablefuel designlimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,corepoweroscillationscannotoccur;thefunctionsand informationprovidedbytheNuclearSystemStabilityAnalysisarenolongerrequired.Therefore,theinformationprovidedonFigure7.161isnolongerapplicable.NuclearSystemStability Analysisinformationisobsolete.

7.17 7.17.1 DeleteSection7.17.1,StandbyGasTreatmentSystemControlandInstrumentationSafetyObjective.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theStandbyGasTreatmentSystemControlsandInstrumentationSafetyObjectiveis notapplicable.SBGTControlsandInstrumentationinformationisobsolete.

7.17.2 DeleteSection7.17.2,StandbyGasTreatmentSystemControlandInstrumentationSafetyDesignBasis ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theStandbyGasTreatmentSystemControlsandInstrumentationSafetyDesign Basisisnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.

BWROGStabilityCriteriaMap STANDBYGASTREATMENTSYSTEMCONTROLAND INSTRUMENTATION SafetyObjective SafetyDesignBasis ConformanceWithSafetyandPowerGeneration DesignBasis DescriptionandPerformanceAnalysis Conclusions References Page75of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 7.17.3 DeleteSection7.17.3,StandbyGasTreatmentSystemControlandInstrumentationSafetyDesignBasis ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theinformationprovidedintheStandbyGasTreatmentSystemControlsand InstrumentationDescriptionsectionisnotapplicable.SBGTControlsandInstrumentationinformationisobsolete.

7.17.4 DeleteSection7.17.4,StandbyGasTreatmentSystemControlandInstrumentationSafetyEvaluation.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,asafetyevaluationoftheStandbyGasTreatmentSystemControlsand Instrumentationisnotrequired.SBGTControlsandInstrumentationinformationisobsolete.

7.17.5 DeleteSection7.17.5,StandbyGasTreatmentSystemControlandInstrumentationInspectionandTesting.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,InspectionandTestingoftheStandbyGasTreatmentSystemControlsand Instrumentationisnotrequired.SBGTControlsandInstrumentationinformationisobsolete.

Table7.17.1 DeleteTable7.17.1,StandbyGasTreatmentSystemInstrumentation.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,atableofStandbyGasTreatmentSystemInstrumentationisnotrequired.SBGT ControlsandInstrumentationinformationisobsolete.

Figure7.171 DeleteFigure7.171,StandbyGasTreatmentSystemFlowDiagram.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theinformationprovidedonFigure7.171isnotapplicable.SBGTControlsand Instrumentationinformationisobsolete.

Description SafetyEvaluation InspectionandTesting StandbyGasTreatmentSystemInstrumentation G191646StandbyGasTreatmentSystemFlow Diagram Page76of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.172 DeleteFigure7.172,StandbyGasTreatmentSystemLogicDiagram.

ThecontrolsandinstrumentationfortheStandbyGasTreatmentSystem(SGTS)initiatedappropriateresponsesfromtheSGTSandassociatedventilatingsystemsothattheminimumsafety requirementsintheReactorBuildingcouldbemet.

TheStandbyGasTreatmentSystemlimitedairbornefissionproductreleasetotheenvironmentbytheuseofhighefficiencyfiltersandbythemaintenanceofanegativepressureintheReactor Building.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.AnalysishasdemonstratedthattheStandbyGasTreatmentSystemisno longerrequiredtomitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.SincetheStandbyGasTreatmentSystemisnolongerrequired,thefunctionsand informationprovidedbytheSBGTControlsandInstrumentationarealsonolongerrequired.Consequently,theinformationprovidedonFigure7.172isnotapplicable.SBGTControlsand Instrumentationinformationisobsolete.

7.18 TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

7.18.1 DeleteSection7.18.1,AnticipatedTransientWithoutScramPrevention/MitigationSystem,SafetyObjective.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired;theAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyObjectiveisnolongerapplicable.

AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

7.18.2 DeleteSection7.18.2,AnticipatedTransientWithoutScramPrevention/MitigationSystem,SafetyDesignBases.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired;theAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyDesignBasesarenolonger applicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

7.18.3 DeleteSection7.18.3,AnticipatedTransientWithoutScramPrevention/MitigationSystem,Description.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired;thedescriptionoftheAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyDesignBasesis nolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

7.18.4 DeleteSection7.18.4,AnticipatedTransientWithoutScramPrevention/MitigationSystem,SafetyEvaluation.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired;asafetyevaluationoftheAnticipatedTransientWithoutScramPrevention/MitigationSystemSafetyDesign Basesisnolongerrequired.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

7.18.5 DeleteSection7.18.5,AnticipatedTransientWithoutScramPrevention/MitigationSystem,InspectionandTesting.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired;InspectionandTestingoftheAnticipatedTransientWithoutScramPrevention/MitigationSystemisnolonger required.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

Table7.18.1 DeleteTable7.18.1,AnticipatedTransientWithoutScramPrevention/MitigationSystemInstrumentation.SinceTherefore,thefunctionsandinformationprovidedbytheAnticipatedTransient WithoutScramPrevention/MitigationSystemarenolongerrequired;atablelistingtheATWSPrevention/MitigationSystemInstrumentationisnolongerrequired.AnticipatedTransient WithoutScramPrevention/MitigationSysteminformationisobsolete.

SafetyDesignBases Description SafetyEvaluation InspectionandTesting AnticipatedTransientWithoutScram Prevention/MitigationSystemInstrumentation G191646StandbyGasTreatmentSystemLogic Diagram ANTICIPATEDTRANSIENTWITHOUTSCRAM PREVENTION/MITIGATIONSYSTEM SafetyObjective Page77of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure7.18 1a DeleteFigure7.181a,RPTandARITripLogic.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired.TheinformationprovidedonFigure7.181aregardingtheAnticipatedTransientWithoutScram Prevention/MitigationSystemisnolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

Figure7.18 1b DeleteFigure7.181b,RPTandARITripActuators.

TheATWSPrevention/MitigationSystemprovidedameanstoreducetheprobabilityofafailuretoscramormitigatedtheconsequencesintheunlikelyeventthatananticipatedtransient occuredandcontrolrodsfailedtoinsert.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsandinformationprovidedbytheAnticipated TransientWithoutScramPrevention/MitigationSystemarenolongerrequired.TheinformationprovidedonFigure7.181bregardingtheAnticipatedTransientWithoutScram Prevention/MitigationSystemisnolongerapplicable.AnticipatedTransientWithoutScramPrevention/MitigationSysteminformationisobsolete.

8.0 StationElectricalPowerSystems Placeholdersectioncontainingnoinformation 3.3.3 8.1 ModifySection8.1,StationElectricalSystemsSummaryDescriptiontoeliminatestartup,operationalandaccidentreferences.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,electricalalignmentsforthoseconditionsarenolongerrequired.

ThissummarylevelinformationwasconsolidatedwithUFSARPlantSummarySection1.6 1.3.5.1 Figure8.11 NoChange Figure3.3.3 1

Figure8.12 NoChange Figure3.3.3 2

8.2 8.2.1 Deletesection8.2.1,StationMainGeneratorPowerGenerationObjective.

Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbytheMainGeneratorarenolongerrequired.TheMainGeneratorPowerGenerationobjectiveisnot applicable.MainGeneratorinformationisobsolete.

8.2.2 Deletesection8.2.2,StationMainGeneratorPowerGenerationDesignBasis, Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbytheMainGeneratorarenolongerrequired.TheMainGeneratorPowerGenerationdesignbasisisno applicable.MainGeneratorinformationisobsolete.

8.2.3 Deletesection8.2.3,StationMainGeneratorDescription, Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,theinformationprovidedbytheMainGeneratordescriptionsectionisnolongerapplicable.MainGeneratorinformationis obsolete.

8.2.4 Deletesection8.2.4,StationMainGeneratorInspectionandTesting Thestationmaingeneratorprovidedareliablesourceofelectricalpowertothe345kVgridandthestationAuxiliaryPowerSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,theinspectionandtestingoftheMainGeneratorisnolongerrequired.MainGeneratorinformationisobsolete.

8.3 3.3.3.1 8.3.1 ModifySection8.3.1,StationTransmissionSystemPowerGenerationObjectivetoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115kV startuptransformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfrom the345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.

3.3.3.1.1 TransmissionSystem Objective RPTandARITripActuators StationElectricalSystems G191298,Sh.3MainOneLineDiagram G1912994160and480VoltAuxiliaryOneLine Diagram RPTandARITripLogic ElectricalPowerSystems ElectricalPowerSystems G191298,Sh.3MainOneLineDiagram G1912994160and480VoltAuxiliaryOneLineDiagram PowerGenerationObjective STATIONMAINGENERATORUNIT PowerGenerationObjective PowerGenerationDesignBasis Description InspectionandTesting STATIONTRANSMISSIONSYSTEM Page78of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.3.2 ModifySection8.3.2,StationTransmissionSystemPowerGenerationDesignBasistoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115 kVstartuptransformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfrom the345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.

3.3.3.1.2 8.3.3 ModifySection8.3.3,StationTransmissionSystemDescriptiontoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115kVstartup transformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfrom the345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.

3.3.3.1.3 8.3.4 ModifySection8.3.4,StationTransmissionSystemDescriptiontoremovediscussionsof345kVtransmissionlines,andrewordtodescribestationpowersupplyviathe115kVstartup transformers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfrom the345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.

3.3.3.1.4 8.3.5 DeleteSection8.3.5,StationTransmissionSystemTechnicalSpecification FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfrom the345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.

Figure8.31 DeleteFigure8.31,TransmissionLinesRiverCrossing.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thestationwillnolongerbegeneratingandsupplyingpowertothe345kVtransmissionsystem.Thestationisisolatedfrom the345kVtransmissionsystem,StationPowerissuppliedviathe115kVsystem.

Figure8.32 NoChanges Figure3.3.3 1

8.4 3.3.3.2 8.4.1 ModifySection8.4.1,StationAuxiliaryPowerSystem,PowerGenerationObjective.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,themaingeneratorwillnolongerbeoperated,thestationauxiliarypowersystemwillbepoweredfromthestartup transformers.Allreferencetooperationalconditionshasbeendeleted.ThepowergenerationObjectivesectionhasbeenmodifiedtoremovetheterm"PowerGeneration",andtheobjective hasbeenrewordedtoreflectthesafestorageandhandlingofirradiatedfuel.

3.3.3.2.1 8.4.2 ModifySection8.4.2,StationAuxiliaryPowerSystem,PowerGenerationDesignBasis.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,themaingeneratorwillnolongerbeoperated,thestationauxiliarypowersystemwillbepoweredfromthestartup transformers.Allreferencetooperationalconditionshasbeendeleted.ThepowergenerationDesignBasissectionhasbeenmodifiedtoremovetheterm"PowerGeneration",andthedesign basissectionhasbeenrewordedtoreflectthesafestorageandhandlingofirradiatedfuel.

3.3.3.2.2 8.4.3 Deletesection8.4.3,StationAuxiliaryPowerSystem,SafetyObjective FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theStationAuxiliaryPowerSystemSafetyObjectiveisno longerapplicable.

8.4.4 Deletesection8.4.4,StationAuxiliaryPowerSystem,SafetyDesignBasis FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theStationAuxiliaryPowerSystemSafetyDesignBasisisno longerapplicable.

8.4.5 3.3.3.2.3 8.4.5.1 ModifySection8.4.5.1,StationAuxiliaryPowerSystem,4260VSwitchgeartoremovereferencetooperatingandaccidentconditions,reflectthattheauxiliarypowersystemcannolongerbe suppliedbytheunitauxiliarytransformer,andnotethestationauxiliarypowersystemfunctionisnowtosupplypowerforthesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

3.3.3.2.3.1 4160VSwitchgear 8.4.5.2 ModifySection8.4.5.2,StationAuxiliaryPowerSystem,480VBussestoremovereferencetooperatingandaccidentconditions,reflectthattheauxiliarypowersystemcannolongerbe suppliedbytheunitauxiliarytransformer,andnotethestationauxiliarypowersystemfunctionisnowtosupplypowerforthesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

3.3.3.2.3.2 480VBuses DesignBasis Description EvaluationofSystemProtection G191298sheet3,MAINONELINEWIRINGDIAGRAM AuxiliaryPowerSystems Objective DesignBasis Description PowerGenerationDesignBasis SafetyObjective SafetyDesignBasis Description EvaluationofSystemProtection TechnicalSpecifications TransmissionLinesRiverCrossing STATIONAUXILIARYPOWERSYSTEMS PowerGenerationObjective PowerGenerationDesignBasis Description G191298sheet3,MAINONELINEWIRING DIAGRAM 4160VSwitchgear 480VBuses Page79of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.4.5.3 ModifySection8.4.5.3,StationAuxiliaryPowerSystem,120/240VInstrumentationDistributionSystemtoremovereferencetoelectricalloadswhicharenolongerrequiredandremove referencetotheMGset.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,manyoftheloadssuppliedbythe120/240Instrumentation Systemarenolongerrequired.Additionally,thefunctionsprovidedbytheMGsetarenolongerrequired.Thatinformationishistoricalandobsoletedandmaybedeleted.

3.3.3.2.3.3 120/240V Instrumentation DistributionSystem 8.4.6 ModifySection8.4.6,StationAuxiliaryPowerSystem,CableInstallationandSeparationCriteriatoremovereferencetocableseparationcriteriaforredundantsafetysystems.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheReactorProtectionSystem,the PrimaryContainmentIsolationSystem,theEngineeredSafetyFeatureandECCS,PrimaryContainmentElectricalPenetrations,andDrywellSeparationcriteriaarenolongerapplicable.

Therefore,theCableInstallationandSeparationCriteriasectionhasbeenmodifiedtoremovereferencetothoseareas,aswellasreferencetooperatingconditions.

3.3.3.2.4 8.4.7 DeleteSection8.4.7,StationAuxiliaryPowerSystem,SafetyEvaluation FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,asafetyevaluationoftheStationAuxiliaryPowerSystemis notrequired.

8.4.8 ModifySection8.4.8,StationAuxiliaryPowerSystem,InspectionandTestingtoremovereferencetooperatingconditions FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

3.3.3.2.5 8.4.9 DeleteSection8.4.9,StationAuxiliaryPowerSystem,TechnicalSpecifications.AllTSsurveillancesrelatedtotheStationAuxiliaryPowerSystemhavebeendeletedintheDefueledTSsubmitta totheNRC Figure8.41 Nochanges Figure3.3.3 2

Figure8.42 Nochanges Figure3.3.3 2

Figure8.43 Nochanges Figure3.3.3 3

Figure8.44 Nochanges Figure3.3.3 4

Figure8.45 Nochanges Figure3.3.3 5

Figure8.46 Nochanges Figure3.3.3 6

Figure8.47 DeleteFigure8.47,Duplicatesotherfiguresinthissection Figure8.48 Nochanges Figure3.3.3 10 Figure8.48 Nochanges Figure3.3.3 11 8.5 3.3.3.3 8.5.1 ModifySection8.5.1,StationStandbyDieselGeneratorSystemsSafetyObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthatthedieselgeneratorsnowsupply backuppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDieselGeneratorsareonlyrequiredtosupplybackuppower toensurethesafestorageofirradiatedfuel.

3.3.3.3.1 8.5.2 ModifySection8.5.2,StationStandbyDieselGeneratorSystemsSafetyDesignBasestoremovereferencetooperatingandaccidentconditions,andreflectthatthedieselgeneratorsnow supplybackuppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDieselGeneratorsareonlyrequiredtosupplybackuppower toensurethesafestorageofirradiatedfuel.

3.3.3.3.2 G191299BalanceofPlant4160VoltAuxiliary OneLineDiagram G191300,Sh1Emergency480VoltAuxiliaryOne LineDiagram(SI)

G191300,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SI)

G191301,Sh1Emergency480VoltAuxiliaryOne LineDiagram(SII)

G191301,Sh2Emergency480VoltAuxiliaryOne LineDiagram(SII)

SafetyEvaluation InspectionandTesting TechnicalSpecifications G191299Emergency4160VoltAuxiliaryOne LineDiagram 120/240VInstrumentation DistributionSystem CableInstallationandSeparationCriteria CableInstallationandSeparationCriteria InspectionandTesting G191299BalanceofPlant4160VoltAuxiliaryOneLineDiagram G191299BalanceofPlant4160VoltAuxiliaryOneLineDiagram G191300,Sh1Emergency480VoltAuxiliaryOneLineDiagram (SI)

G191300,Sh2Emergency480VoltAuxiliaryOneLineDiagram (SI)

G191301,Sh1Emergency480VoltAuxiliaryOneLineDiagram (SII)

G191301,Sh2Emergency480VoltAuxiliaryOneLineDiagram (SII)

SafetyDesignBases G191300,Sh2G191301,Sh2Emergency480 VoltAuxiliaryOneLineDiagram(SI&SII)

G191372,Sh4G191372,Sh5120/240Volt InstrumentationOneLineDiagram STATIONSTANDBYDIESELGENERATORSYSTEMS SafetyObjective G191372,Sh4G191372,Sh5120/240Volt InstrumentationOneLineDiagram STANDBYDIESELGENERATORSYSTEMS G191372,Sh4120/240VoltInstrumentationOneLineDiagram G191372,Sh5OneLineDiagram,+24VoltDCPowerSystem Objective DesignBases Page80of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.5.3 ModifySection8.5.3,StationStandbyDieselGeneratorSystemsDescriptiontoremovereferencetooperatingandaccidentconditions,andreflectthatthedieselgeneratorsnowsupplyback uppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDieselGeneratorsareonlyrequiredtosupplybackuppower toensurethesafestorageofirradiatedfuel.

3.3.3.3.3 8.5.4 DeleteSection8.5.4,StationStandbyDieselGeneratorSystemsSafetyEvaluation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsoftheStandbyDieselGeneratorsareno longerrequired.Consequently,asafetyevaluationoftheStandbyDieselGeneratorSystemsisnolongerreqired.

8.5.5 DeleteSection8.5.5,LossofDieselGenerators.Availibilityofanalternatepowersupplyalignmenttobusses3and4isaddressedinsection8.4.5.1,4160VACBusses.Therearenosafety consequencesassociatewiththelossofabackupdieselgeneratorinthepermanentlydefueledcondition.Adequatemitigationstrategiesexisttoensurespentfueltemperatureandinventory aremaintained.

8.5.6 ModifySection8.5.4,StationStandbyDieselGeneratorSystemsInspectionandTestingtoremovereferencetooperatingandaccidentconditions,andreflectthatthedieselgeneratorsnow supplybackuppoweronlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDieselGeneratorsareonlyrequiredtosupplybackuppower toensurethesafestorageofirradiatedfuel.StandbyDieselGeneratorInspectionandTestingwillbecommeasuratewiththefunctionoftheDiesels.

3.3.3.3.4 8.5.7 DeleteSection8.5.7,StandbyDieselGeneratorSystemsTechnicalSpecifications.VYwillneverbeinamodewhichwillrequirethestandbydieselgeneratorstobeoperablebytheTechnica Specifications.

Table8.5.1A DeleteTable8.5.1A,DieselGeneratorDG11ALoadingLossofACandMaximumHypotheticalAccident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprojecteddieselgeneratorloadinginthistableisnolonger requiredsincethemaximumhypotheticalaccidentisnolongerpossible.

Table8.5.1B DeleteTable8.5.1B,DieselGeneratorDG11BLoadingLossofACandMaximumHypotheticalAccident.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theprojecteddieselgeneratorloadinginthistableisnolonger requiredsincethemaximumhypotheticalaccidentisnolongerpossible.

Table8.5.2A Deletetable8.5.2A.Thetableprovidedalistingofloadswhichwouldautomaticallystartandloadoneachdieselgeneratorfollowingspecificplantinitiatingconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,whenrequired,theDieselGeneratorswillsupplysufficient backuppowerrequiredtoensurethesafestorageofirradiatedfuel.ThatloadingisasmallpercentageoftheDieselGeneratorloadingwhichwasrequiredfollowingalossofoffsitepowerand alossofcoolantorotherdesignbasisaccident.

Consequently,theinformationprovideontable8.5.2Aishistoricalandobsolete.Assuch,thistablemaybedeleted.

Table8.5.2B Deletetable8.5.2B.Thetableprovidedalistingofloadswhichwouldautomaticallystartandloadoneachdieselgeneratorfollowingspecificplantinitiatingconditions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,whenrequired,theDieselGeneratorswillsupplysufficient backuppowerrequiredtoensurethesafestorageofirradiatedfuel.ThatloadingisasmallpercentageoftheDieselGeneratorloadingwhichwasrequiredfollowingalossofoffsitepowerand alossofcoolantorotherdesignbasisaccident.

Consequently,theinformationprovideontable8.5.2Bishistoricalandobsolete.Assuch,thistablemaybedeleted.

Table8.5.3A DeleteTable8.5.3A,DieselGeneratorDG11ALoadingLossofACandVernonPond.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceSWwaslostduringalossoftheVernonPond,DGcoolingwasprovided byRHRSW.RHRSWisnotrequiredinthepermanentlydefueledstate,therefore,coolingtotheDGsisnotavailableduringalossoftheVernonPond.Otherpowersourcesareavailableand strategieshavebeendevelopedtomaintainSFPinventoryandcooling.Therefore,theprojecteddieselgeneratorloadingduringalossoftheVernonPondisnolongerrequired.

DieselGeneratorDG11ALoadingLossofAC andMaximumHypotheticalAccident DieselGeneratorDG11BLoadingLossofAC andMaximumHypotheticalAccident DieselGeneratorDG11ALoadingLossofAC DieselGeneratorDG11BLoadingLossofAC LossofDieselGenerator InspectionandTesting TechnicalSpecifications Description SafetyEvaluation Description InspectionandTesting DieselGeneratorDG11ALoadingLossofAC andVernonPond Page81of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table8.5.3B DeleteTable8.5.3B,DieselGeneratorDG11BLoadingLossofACandVernonPond.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.SinceSWwaslostduringalossoftheVernonPond,DGcoolingwasprovided byRHRSW.RHRSWisnotrequiredinthepermanentlydefueledstate,therefore,coolingtotheDGsisnotavailableduringalossoftheVernonPond.Otherpowersourcesareavailableand strategieshavebeendevelopedtomaintainSFPinventoryandcooling.Therefore,theprojecteddieselgeneratorloadingduringalossoftheVernonPondisnolongerrequired.

Figure8.51 DeleteFigure8.51,FuelOilSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theDieselGeneratorsareonlyrequiredtosupplybackuppower asnecessarytoensurethesafestorageofirradiatedfuel.Therefore,adrawingofthefueloilsystemisnolongerrequiredtodemonstratethattheDieselGeneratorsarecapableofperforming theirintendedfunction.

8.6 3.3.3.4 8.6.1 ModifySection8.6.1,125VoltBatterySystem,SafetyObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlyto ensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsofthe125VDCsystemisnolongerrequired Consequently,theword"Safety"hasbeendeletedfromthetitleandthetextandtheword"emergency"hasbeendeletedfromthetext.

3.3.3.4.1 8.6.2 ModifySection8.6.2,125VoltBatterySystem,SafetyDesignBasistoremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlyto ensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetydesignbasesofthe125VDCsystemisnolonger applicable.Consequently,theword"Safety"hasbeendeletedfromthetitleandreferencetoredundancy,independenceandsinglefailurecriteriahavebeendeletedfromthetext.

3.3.3.4.2 8.6.3 ModifySection8.6.3,125VoltBatterySystem,Descriptiontoremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlytoensure thesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theperformancerequirementsofthe125VDCsystemhave changedtoessentiallyprovidingcontrolpowerforvariousstationcomponents.Consequently,referencetosafetyrelatedclassificationanddischargeratesandtimeshavebeendeletedfrom thetext.Additionally,thefunctionsprovidedbystationbatteryAS1arenolongerrequired.Therefore,referencestostationbatteryAS1havebeendeleted.

3.3.3.4.3 8.6.4 ModifySection8.6.4,125VoltBatterySystem,SafetyEvaluation,toremovereferencetooperatingandaccidentconditions,andreflectthatthe125VDCsystemnowsuppliespoweronlyto ensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyfunctionsofthe125VDCsystemisnolongerrequired Consequently,theword"Safety"hasbeendeletedfromthetitle.Additionally,referencetosafetyrelatedclassificationanddischargeratesandtimeshavebeendeletedfromthetext.Also, thefunctionsprovidedbystationbatteryAS1arenolongerrequired.Therefore,referencestostationbatteryAS1havebeendeleted.

3.3.3.4.4 8.6.5 NoChanges 3.3.3.4.5 8.6.6 NoChanges 3.3.3.4.6 8.6.7 DeleteSection8.6.7,125VoltBatterySystem,TechnicalSpecifications.VYwillneverbeinamodewhichwillrequirethebatterysystemtobeoperablebytheTechnicalSpecifications.

Figure8.61 NoChanges Figure3.3.3 7

3.3.38 3.3.39 8.7 3.3.3.5 8.7.1 ModifySection8.7.1,+24VoltDCPowerSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthatthe+24VoltDCPowerSystemnow suppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincethereisnocoretoprotect,theneutronmonitoringsystemsareno longerrequired.Therefore,powertotheneutronmonitoringsystemsfromthe+24VDCsystemisnolongerrequired.Referencetopowersuppliedtotheneutronmonitoringsystemshas beendeletedfromthissection.

3.3.3.5.1 InspectionandTesting 125VOLTBATTERYSYSTEM G191372,Shs1,2,3125VDCOneLineDiagram

+24VDCPowerSystem Objective Objective DesignBasis Description Evaluation AdditionalDCSystems G191372,Shs1,2,3125VDCOneLineDiagram

+24VDCPowerSustem PowerGenerationObjective AdditionalDCSystems InspectionandTesting TechnicalSpecifications SafetyDesignBasis Description SafetyEvaluation DieselGeneratorDG11BLoadingLossofAC andVernonPond FuelOilSystem 125VOLTBATTERYSYSTEM SafetyObjective Page82of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 8.7.2 ModifySection8.7.2,+24VoltDCPowerSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions,andreflectthatthe+24VoltDCPowerSystemnow suppliespoweronlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

3.3.3.5.2 8.7.3 ModifySection8.7.3,+24VoltDCPowerSystem,Description,toremovereferencetooperatingandaccidentconditions,andreflectthatthe+24VoltDCPowerSystemnowsuppliespower onlytoensurethesafestorageandhandlingofirradiatedfuel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sincethereisnocoretoprotect,theneutronmonitoringsystemsareno longerrequired.Therefore,powertotheneutronmonitoringsystemsfromthe+24VDCsystemisnolongerrequired.Referencetopowersuppliedtotheneutronmonitoringsystemshas beendeletedfromthissection.Additionally,referencetodischargeratesandtimeshavebeendeletedfromthetext.

3.3.3.5.3 8.7.4 Nochanges 3.3.3.5.4 8.7.5 DeleteSection8.7.5,125VoltBatterySystem,TechnicalSpecifications.VYwillneverbeinamodewhichwillrequirethebatterysystemtobeoperablebytheTechnicalSpecifications.

Figure8.71 Nochanges Figure3.3.3 11 8.8 8.8.1 DeleteSection8.8.1,ECCS24VoltDCPowerSystemSafetyObjective.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemare nolongerrequired.Thesafetyobjectiveisnolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.

8.8.2 DeleteSection8.8.2,ECCS24VoltDCPowerSystemSafetyDesignBases.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemare nolongerrequired.Thesafetydesignbasesarenolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.

8.8.3 DeleteSection8.8.3,ECCS24VoltDCPowerSystemDescription.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemare nolongerrequired.Theinformationprovidedinthedescriptionsectionisnolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.

8.8.4 DeleteSection8.8.4,ECCS24VoltDCPowerSystemSafetyEvaluation.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemare nolongerrequired.AsafetyevaluaionoftheECCS24VoltDCPowrSystemisnolongerrequired.ECCS24VDCPowerSysteminformationisobsolete.

8.8.5 DeleteSection8.8.5,ECCS24VoltDCPowerSystemSafetyEvaluation.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Thererfore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemare nolongerrequired.InspectionandTestingoftheECCS24VoltDCPowerSystemisnolongerrequired.ECCS24VDCPowerSysteminformationisobsolete.

Figure8.81 DeleteSection8.81,OneLineDiagramECCS24VoltDCPowerSystem.

TheECCS24VDCPowerSystemprovidedasupplyof24VdcpowerfortheoperationoftheECCSAnalogTripSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbytheECCS24VoltDCPowerSystemare nolongerrequired.Theinformationprovidedonfigure8.81isnolongerapplicable.ECCS24VDCPowerSysteminformationisobsolete.

9.0 RadioactiveWasteSystems DesignBasis Description InspectionandTesting G191372,Sh5OneLineDiagram,+24VoltDCPowerSystem PowerGenerationDesignBasis Description InspectionandTesting Description SafetyEvaluation InspectionandTesting OneLineDiagramECCS24VoltDCPowerSystem G191297 TechnicalSpecifications G191372,Sh5OneLineDiagram,+24VoltDC PowerSystem ECCS24VOLTDCPOWERSYSTEM SafetyObjective SafetyDesignBasis Page83of153 toPADandLBDCRforDSARRev0(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,glandsealcondenserandtheStandbyGasTreatmentSystemwillno longerbeoperated.Ventilationsysteminformationisprovidedintheappropriateventilationsystemsections.

5.Removedstatementregardingcontinuedcompliancewithannualdoselimitswith1912MWthrating,nolongerapplicablepostdefueling.

1.3.3 9.2 4.5.2 9.2.1 Deleted"PowerGeneration"fromthesectiontitle.Sincetheclassificationprocessdescribedinsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisnotapplicabl 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 4.5.2.3 9.2.4.1 EditorialChangesonly 4.5.2.3.1 9.2.4.2 EditorialChangesonly 4.5.2.3.2 9.2.4.3 EditorialChangesonly 4.5.2.3.3 9.2.4.4 EditorialChangesonly 4.5.2.3.4 9.2.5 EditorialChangesonly 4.5.2.4 9.2.6 NoChanges 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 Figure9.21a NoChanges Figure4.5.2 1

Figure9.21b NoChanges Figure4.5.2 2

Figure9.22 NoChanges Figure4.5.2 3

Figure9.23 NoChanges Figure4.5.2 4

Figure9.24 NoChanges Figure4.5.2 5

Figure9.25 NoChanges Figure4.5.2 6

Figure9.26 NoChanges Figure4.5.2 7

Figure9.27 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 VermontYankeeRadioactiveLiquidWaste ProcessingParameters VermontYankeeLiquidRadwasteSystemTank Capacities ChemicalWastes DetergentWastes SafetyEvaluation Description HighPurityWastes LowPurityWastes G191177,Sh1LiquidRadwasteSystem G191177,Sh2LiquidRadwasteSystem Description HighPurityWastes LowPurityWastes ChemicalWastes DetergentWastes Evaluation InspectionandTesting VermontYankeeRadioactiveLiquidWasteProcessingParameters VermontYankeeLiquidRadwasteSystemTankCapacities VermontYankeeLiquidEffluents ActivityInputtoLiquidRadwasteSystem(Ci/yr)

RadionuclideDischargeConcentrations G191151RadioactiveWasteBuildingGeneralArrangement G191152RadioactiveWasteBuildingGeneralArrangement G191177,Sh3LiquidRadwasteSystem G191151RadioactiveWasteBuildingGeneral Arrangement G191152RadioactiveWasteBuildingGeneral Arrangement 5920644,Sh2RadwasteSystem,Process Diagram VermontYankeeLiquidEffluents ActivityInputtoLiquidRadwasteSystem(Ci/yr)

RadionuclideDischargeConcentrations General 5920644,Sh2RadwasteSystem,ProcessDiagram G191177,Sh1LiquidRadwasteSystem G191177,Sh2LiquidRadwasteSystem G191177,Sh3LiquidRadwasteSystem G191177,Sh4LiquidRadwasteSystem RadwasteAreaPlanView Objective DesignBasis SOLIDRADWASTESYSTEM Description General PowerGenerationObjective PowerGenerationDesignBasis Description G191177,Sh4LiquidRadwasteSystem RadwasteAreaPlanView SOLIDRADWASTESYSTEM Page84of153 toPADandLBDCRforDSARRev0(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.Referencetoweathertightshippingcontainers 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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystempowergenerationobjectiveisnolongerapplicable.

GaseousRadwasteSysteminformationisobsolete.

9.4.2 DeleteSection9.4.2,GaseousRadwasteSystemSafetyObjective.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemisnolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystemsafetyobjectiveisnolongerapplicable.Gaseous RadwasteSysteminformationisobsolete.

9.4.3 DeleteSection9.4.3,GaseousRadwasteSystemPowerGenerationDesignBases.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystempowergenerationdesignbasesarenolongerapplicable.

GaseousRadwasteSysteminformationisobsolete.

9.4.4 DeleteSection9.4.4,GaseousRadwasteSystemSafetyDesignBases.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theGaseousRadwasteSystemSafetyDesignBasesarenolongerapplicable.Gaseous RadwasteSysteminformationisobsolete.

9.4.5 DeleteSection9.4.5,GaseousRadwasteSystemDescription.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Further,theincinerationofslightlyradioactiveoilwillnolongerbeperformed.Therefore, informationprovidedintheGaseousRadwasteSystemDescriptionSectionisnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.

DryWastes InspectionandTesting SolidRadwasteAnnualDisposalHistory WetWastes WetWastes DryWastes GASEOUSRADWASTESYSTEM PowerGenerationObjective SafetyObjective PowerGenerationDesignBasis SafetyDesignBasis Description WasteStorageFacility InspectionandTesting SolidRadwasteAnnualDisposalHistory Page85of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.

Therefore,asafetyevaluationoftheGaseousRadwasteSystemisnolongerrequired.GaseousRadwasteSysteminformationisobsolete.

9.4.7 DeleteSection9.4.7,GaseousRadwasteSystemInspectionandTesting TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,inspectionandtestingoftheGaseousRadwasteSystemisnolongerrequired.Gaseous RadwasteSysteminformationisobsolete.

9.4.8 DeleteSection9.4.8,GaseousRadwasteSystemReferences.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,GaseousRadwasteSystemreferencesarenolongerapplicable.GaseousRadwaste Systeminformationisobsolete.

Table9.4.1 DeleteTable9.4.1,AirEjectorIsotopeandSiteBoundaryReleaseRates.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Therefore,theinformationprovidedinTable9.4.1,AirEjectorIsotopeandSiteBoundaryRelease Ratesisnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.

Figure9.41 DeleteFigure9.41,AdvancedOffGasSystemPipingandInstrumentationDiagram.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Further,theincinerationofslightlyradioactiveoilwillnolongerbeperformed.

Therefore,informationprovidedonfigure9.41isnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.

Figure9.42 DeleteFigure9.42,OffGasSystem.

TheGaseousRadwasteSystemcollected,processed,anddischargedradioactivegaseouswastestotheatmospherethroughtheplantstackduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,radioactivegaseouswastewillnolongerbeproducedfromeither stationoperationorcorerelateddesignbasisaccidents.Additionally,analysishasdemonstratedthatsecondarycontainmentandtheStandbyGasTreatmentSystemarenolongerrequiredto mitigatetheconsequencesoftheremainingdesignbasisaccident,afuelhandlingaccident.Further,theincinerationofslightlyradioactiveoilwillnolongerbeperformed.Therefore, informationprovidedonfigure9.42isnolongerapplicable.GaseousRadwasteSysteminformationisobsolete.

SafetyEvaluation InspectionandTesting REFERENCES AirEjectorIsotopeandSiteBoundaryRelease Rates VYE75001AdvancedOffGasSystemPipingand InstrumentationDiagram G191162,Sh3OffGasSystem Page86of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, thefunctionsprovidedbythenewfuelstorageracksarenolongerrequired.TheNewFuelStorageRackPowerGenerationObjectiveisnolongerapplicable.NewFuelStorageRackinformation isobsolete.

10.2.2 DeleteSection10.2.2,NewFuelStorageRacks,PowerGenerationDesignBases.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, thefunctionsprovidedbythenewfuelstorageracksarenolongerrequired.TheNewFuelStorageRackPowerGenerationDesignBasesarenolongerapplicable.NewFuelStorageRack informationisobsolete.

10.2.3 DeleteSection10.2.3,NewFuelStorageRacks,SafetyDesignBasis.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, thefunctionsprovidedbythenewfuelstorageracksarenolongerrequired.TheNewFuelStorageRackSafetyDesignBasisisnolongerapplicable.NewFuelStorageRackinformationis obsolete.

10.2.4 DeleteSection10.2.4,NewFuelStorageRacks,Description.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, theinformationprovidedbythenewfuelstorageracksdescriptionsectionisnolongerapplicable.NewFuelStorageRackinformationisobsolete.

10.2.5 DeleteSection10.2.5,NewFuelStorageRacks,SafetyEvaluation.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, asafetyevaluationofthenewfuelstorageracksisnolongerrequired.NewFuelStorageRackinformationisobsolete.

10.2.6 DeleteSection10.2.6,NewFuelStorageRacks,InspectionandTesting.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, inspectionandtestingofthenewfuelstorageracksisnolongerrequired.NewFuelStorageRackinformationisobsolete.

Figure10.21 DeleteFigure10.21,NewFuelStorageRack.

Thenewfuelstorageracksprovidedasafe,speciallydesignedstorageplacefornewfuelassembliesorbundles.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,newfuelwillnolongerbereceivedonthestation.Consequently, theinformationprovidedonfigure10.21isnolongerapplicable.NewFuelStorageRackinformationisobsolete.

10.3 3.3.1.2 10.3.1 Rewordtitleto"Objective"delete"PowerGeneration"sincepowergenerationcannolongeroccurfollowingcertificationofpermanentdefueling.

3.3.1.2.1 10.3.2 Rewordtitleto"DesignBasis",delete"PowerGeneration"sincepowergenerationcannolongeroccurfollowingcertificationofpermanentdefueling.Includedesignbasesfromsection10.3.3 SafetyDesignBasis.

3.3.1.2.2 10.3.3 MoveSafetyDesignBasisinformationintosection10.3.2,DesignBasis,Deletethissection.

10.3.4 NumberingChangesonly 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 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.3.6 NumberingChangesasaconsequenceofcombiningdesignbasissections.

3.3.1.2.5 ReferencessectionaddedtopointtoNUREG1738,RegGuide1,174,andBVY14009,CompliancewithIDCsandSDAs 3.3.1.5 Figure10.31 NoChanges Figure3.3.1 1

Figure10.32 NoChanges Figure3.3.1 2

Figure10.33 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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingofreactorsystemswillnolongerberequired.Any reactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

10.4.2 Rewordtitleto"Objective",delete"Safety".

NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.1 10.4.3 Rewordtitleto"DesignBasis",delete"Safety".

Changed"refuelingaccident"to"fuelhandlingaccident".FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Consequently,arefuelingaccidentcannolongeroccur.

NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.2 10.4.4 NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3 10.4.4.1 Deletedreferencestoreactorgeneralservicingrequirements.Servicingofreactorsystemswillnolongerberequired.Anyreactorrelatedactivitieswilloccuraspartofdecommissioning activitiesasoutlinedinthePSDAR.

Deletedreferencetoflowchartoutliningactivitiesinanormalrefuelingoutage,sincepostdefueling,refuelingoutageswillnolongeroccur.

NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3.1 Introduction 10.4.4.2 Editorialcommentstoimprovegrammar.

Removedthereferenceto"operating"personnel.

Removedreferencestothenewfuelinspectionstandfunctions,sincenewfuelwillnolongerbereceivedatthestation.

Removedthedescriptionoftypicalchannelingproceureforswappinganirradiatedfuelchanneltoanewfuelbundle,sincenewfuelwillnolongerbereceivedatthestation.Additionally, channelingactivitesareprocedurallycoveredandshouldnotbedescribedintheFSARorDSAR.

NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3.2 FuelServicing Equipment 10.4.4.3 Deletedreferencetoreasonsforusingaportableunderwatertelevisioncameraandmonitor.ThisisdetailedinformationnotrequiredtobeintheDSAR NumberingChangesasaresultofdeletingPowerGenerationObjectiveSection 3.3.1.4.3.3 ServicingAids 10.4.4.4 Deletesection10.4.4.4,ReactorVesselServicingEquipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingofreactorsystemswillnolongerberequired.Any reactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

10.4.4.5 Deletesection10.4.4.5,InVesselServicingEquipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingofreactorsystemswillnolongerberequired.Any reactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

10.4.4.6 Retitled"RefuelingEquipment"to"FuelHandlingEquipment"sincefollowingcertificationofpermanentdefueling,refuelingoperationswillnolongeoccur Rewordedsectiontoremoveallreferencetofuelhandlinginthereactorvesselandfueltransferfromthevesseltothepool.

NumberingChangesasaresultofdeletingsections.

3.3.1.4.3.4 FuelHandling Equipment 10.4.4.7 Deletedreferencetonewfuelstorageracks.

NumberingChangesasaresultofdeletingsections.

3.3.1.4.3.5 StorageEquipment NESFuelStorageRackAssembly(Partial)

InspectionandTesting References FuelStorageArrangement 59206893PlanFuelStorageRackArrangement 59206893SpentFuelStorageRackSchematic NESFuelStorageRackAssembly(Partial)

FuelStorageArrangement 59206893PlanFuelStorageRackArrangement 59206893SpentFuelStorageRackSchematic InspectionandTesting ServicingAids ReactorVesselServicingEquipment InVesselServicingEquipment Description Introduction FuelServicingEquipment PowerGenerationObjective SafetyObjective SafetyDesignBasis HoltecFuelStorageRackAssembly (Partial)

TOOLSANDSERVICINGEQUIPMENT Objective DesignBasis Description RefuelingEquipment StorageEquipment HoltecFuelStorageRackAssembly (Partial)

TOOLSANDSERVICINGEQUIPMENT Page88of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.4.4.8 Deletesection10.4.4.8,UnderReactorVesselServicingEquipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,servicingunderreactorvesselsystemswillnolongerberequired.

AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

10.4.4.9 Deletesection10.4.4.9,StoragePit.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thefunctionsprovidedbythestoragepitwillnolongerbe required.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

NumberingChangesasaresultofdeletingsections.

10.4.5 Changed"refuelingaccident"to"fuelhandlingaccident".FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Consequently,arefuelingaccidentcannolongeroccur.

NumberingChangesasaresultofdeletingsections.

3.3.1.4.4 10.4.6 Deletethissection,singlereferenceincorporatedintotextbody Table10.4.1 ModifyTable10.4.1,ToolsandServicingEquipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.Additionally,sinceallfuelhasbeenmovedtothespentfuelpool,thecattlechutewillalsonolongerbe required.Table10.41hasbeenmodifiedtoreflectthesechanges.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

Contentsofthetablepertinenttothepermanentlydefueledconditionhavebeenmovedintothebodyofthetext,tablehasbeendeleted Figure10.41 DeleteFigure10.41,Typ.PlantRefuelingOutageFlowDiagram.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,plantrefuelingoutageswillnolongeroccur.Theinformation providedinFigure10.41isnotapplicable.Plantrefuelingoutageflowdiagraminformationisobsolete.Anyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesas outlinedinthePSDAR.

Figure10.42 DeleteFigure10.42,ChannelGaugingFixture.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,Fuelchannelingoperationsandactivitieswhichrequireuseofthe channelgaugingfixturewillnolongerbeconducted.Informationregardingthechannelgaugingfixtureprovidedonfigure10.42isnotapplicableandisobsolete.

Figure10.43 DeleteFigure10.43,IncoreGuideTube.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.Informationregardingincoreguidetubetoolsprovidedonfigure10.43isnotapplicableandisobsolete.

AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

Figure10.44 DeleteFigure10.44,IncoreHousing.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.Informationregardingincorehousingtoolsprovidedonfigure10.44isnotapplicableandisobsolete.

AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

Figure10.45 DeleteFigure10.45,InCoreGuideTubeSeal.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingIncoreGuideTubeSealtoolsprovidedonfigure10.45isnotapplicableandis obsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

Figure10.46 DeleteFigure10.46,InCoreFlangeSealTestPlug.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingInCoreFlangeSealTestPlugtoolsprovidedonfigure10.46isnotapplicableand isobsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

ToolsandServicingEquipment Typ.PlantRefuelingOutageFlowDiagram 59202429ChannelGaugingFixture 59202417IncoreGuideTube StoragePit SafetyEvaluation REFERENCES UnderReactorVesselServicing Equipment Evaluation IncoreHousing 59202422InCoreGuideTubeSeal InCoreFlangeSealTestPlug Page89of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure10.47 DeleteFigure10.47,FuelBailCleaner.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,operationsandactivitieswhichrequireuseofthefuelbailcleaner willnolongerbeconducted.Informationregardingthefuelbailcleanerprovidedonfigure10.47isnotapplicableandisobsolete.

Figure10.48 DeleteFigure10.48,ThermalSleeveInstallationTool.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingThermalSleeveInstallationToolsprovidedonfigure10.48isnotapplicableandis obsolete.AnyreactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

Figure10.49 DeleteFigure10.49,ThermalSleeve.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,ReactorVesselServicing,invesselservicing,undervesselservicing andcontrolroddrivehydraulicsystemservicingactivitieswillnolongerbeconducted.InformationregardingtheThermalSleeveprovidedonfigure10.49isnotapplicableandisobsolete.An reactorrelatedactivitieswilloccuraspartofdecommissioningactivitiesasoutlinedinthePSDAR.

10.5 3.3.1.3 10.5.1 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisno applicabletoapermanentlydefueledstation.

Sectionwordinghasbeenmodifiedtoreflectalignmentchangesinthefuelpoolcoolingsystem;theNormalFuelPoolCoolingsystemhasbeenabandoned,allfuelpoolcoolingisperformedby theStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenabandoned,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalled inthepool.

3.3.1.3.1 10.5.2 Deletesection10.5.2,SafetyObjective.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theneedtomaintaintheReactorBuildingenvironmentwithi theboundinglimitsoftheenvironmentalqualificationprogramforelectricalequipmentnolongerexists.Therefore,thesafetyobjectiveisnolongerapplicable.

10.5.3 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisno applicabletoapermanentlydefueledstation.

Sectionwordinghasbeenmodifiedtoreflectalignmentchangesinthefuelpoolcoolingsystem;theNormalFuelPoolCoolingsystemhasbeenabandoned,allfuelpoolcoolingisperformedby theStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenabandoned,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalled inthepool.

3.3.1.3.2 10.5.4 Deletesection10.5.4,SafetyDesignBasis.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theneedtomaintaintheReactorBuildingenvironmentwithi theboundinglimitsoftheenvironmentalqualificationprogramforelectricalequipmentnolongerexists.Therefore,thesafetydesignbasisisnolongerapplicable.

10.5.5 Section10.5.5,Description,wordinghasbeenmodifiedtoreflectalignmentchangesinthefuelpoolcoolingsystem;theNormalFuelPoolCoolingsystemhasbeenabandoned,allfuelpool coolingisperformedbytheStandbyFuelPoolCoolingsystem.TheSFPCShasbeenreclassifiedtononsafetyrelated,butremainsseismicclass1.Demineralizerswhicharepartoftheinstalled FPCsystemhavebeenabandoned,poolclarityismaintainedbyfiltrationanddemineralizerunitsinstalledinthepool.

3.3.1.3.3 10.5.6 ModifySection10.5.6toremovetheterm"safety"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolonge requiredandisnotapplicabletoapermanentlydefueledstation.

WordingwasaddedtothesectiontoreflectthattheSFPheatloadhasdecayedtowithinthecapacityofonetrainofSFPCS40daysaftershutdownwiththecoredischargedintothepooland allfuelremaininginthepoolwhichwaspresentjustpriortoshutdown.

3.3.1.3.4 10.5.7 ModifySection10.5.7,InspectionandTesting.TherearenoSFPCStestingrequirementsintheTechnicalSpecifications.Additionally,atleastonetrainoftheSFPCSwillbeinoperationatal times.Therefore,nospecialtestingorinspectionisrequired.

3.3.1.3.5 Table10.5.1 DeletedTable10.5.1,HeatRemovalCapacities.

ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedby theStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationand demineralizerunitsinstalledinthepool.Consequently,theinformationregardingheatremovalcapacitiesprovidedbytable10.5.1isnolongerapplicable.

Table10.5.2 PreviouslyDeleted PowerGenerationDesignBasis SafetyDesignBasis Description 59202407ThermalSleeve FUELPOOLCOOLINGANDDEMINERALIZERSYSTEM PowerGenerationObjective SafetyObjective 59202419FuelBailCleaner 59202424ThermalSleeveInstallationTool Objective DesignBasis Description SafetyEvaluation InspectionandTesting HeatRemovalCapacities Deleted Evaluation InspectionandTesting STANDBYFUELPOOLCOOLINGANDDEMINERALIZER SYSTEM Page90of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table10.5.3 DeletedTable10.5.3,ComparisonofHeatLoadstoHeatRemovalCapacitieswithSFPatCapacity.

ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedby theStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationand demineralizerunitsinstalledinthepool.Consequently,theinformationregardingheatremovalcapacitiesprovidedbytable10.5.3isnolongerapplicable.

Table10.5.4 DeletedTable10.5.4,FuelPoolCoolingandDemineralizerSystemSystemSpecifications.

ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedby theStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationand demineralizerunitsinstalledinthepool.Consequently,theinformationregardingsystemspecificationsprovidedbytable10.5.4isnolongerapplicable.

Figure10.5 1a NoChanges Figure3.3.1 6

Figure10.5 1b NoChanges Figure3.3.1 7

Figure10.52 DeletedFigure10.52,FuelPoolFilterDemineralizerSystem.

ThefollowingchangeshaveoccurredintheFuelPoolCoolingalignment:theNormalFuelPoolCoolingsystemhasbeenpermanentlyremovedfromservice,allfuelpoolcoolingisperformedby theStandbyFuelPoolCoolingsystem.DemineralizerswhicharepartoftheinstalledFPCsystemhavebeenpermanentlyremovedfromservice,poolclarityismaintainedbyfiltrationand demineralizerunitsinstalledinthepool.Consequently,theinformationregardingsystemspecificationsprovidedbyFigure10.52isnolongerapplicable.

10.6 3.3.2 10.6.1 ModifySection10.6.1,StationServiceWaterSystem,PowerGenerationObjectivetoremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystem nowsuppliesonlycoolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel.

3.3.2.1 10.6.2 DeleteSection10.6.2,SafetyObjective.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thetheStationSWSisnolongerrequiredtoprovidecooling watertosystemsandequipmentrequiredtooperateunderaccidentconditions.

10.6.3 ModifySection10.6.3,StationServiceWaterSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWater Systemnowsuppliesonlycoolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel.

3.3.2.2 10.6.4 DeleteSection10.6.2,SafetyDesignBases.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thetheStationSWSisnolongerrequiredtoprovidecooling watertosystemsandequipmentrequiredtooperateunderaccidentconditions.TheStationSWSSafetyDesignBasesarenolongerapplicable.

10.6.5 ModifySection10.6.5,StationServiceWaterSystem,Descriptiontoremovereferencetooperatingandaccidentconditions,andreflectthattheStationServiceWaterSystemnowsuppliesonly coolingnecessarytoensurethesafestorageandhandlingofirradiatedfuel,removereferencetocertainautomaticfeaturesnolongerapplicable,reflectthatStationSWSdischargeisalignedt thecoolingtowerdeepbasin,andnotethatStationSWSpipingwhichsuppliesspentfuelpoolcoolingisseismicclass1.

3.3.2.3 10.6.6 ModifySection10.6.6,SafetyEvaluationtodeletethetermsafetyfromthesectiontitleandrewordthesectiontodemonstratethattheobjectivesappropriatetothedefueledcondtionare

met, FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theStationSWSisnolongerrequiredtoprovidecoolingwater tosystemsandequipmentrequiredtooperateunderaccidentconditions.AStationSWSSafetyEvaluationisnolongerrequired.

3.3.2.4 10.6.7 ModifySection10.6.7,StationServiceWaterSystem,InspectionandTesting,toremovereferencetooperatingandaccidentconditions,andreflectthatsincetheStationServiceWaterSystem isinconstantoperation,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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheatisnolongerrequired,operationof theRHRsystemandRHRSWsystemsisnolongerrequired.Therefore,theRHRSWpowergenerationobjectivesarenolongerapplicable.ResidualHeatRemovalServiceWaterSystem informationisobsolete.

G191177,Sh4FuelPoolFilterDemineralizer System STATIONSERVICEWATERSYSTEM PowerGenerationObjective ComparisonofHeatLoadstoHeatRemoval CapacitieswithSFPatCapacity FuelPoolCoolingandDemineralizerSystem SystemSpecifications G191173,Sh1FuelPoolCoolingSystem G191173,Sh2FuelPoolCoolingSystem Objective G191173,Sh1FuelPoolCoolingSystem G191173,Sh2FuelPoolCoolingSystem SERVICEWATERSYSTEM RESIDUALHEATREMOVAL(RHR)SERVICEWATERSYSTEM PowerGenerationObjective SafetyEvaluation InspectionandTesting G191159,Sh1FlowDiagramServiceWater(Part 1)

G191159,Sh2FlowDiagramServiceWater(Part 2)

SafetyObjective PowerGenerationDesignBasis SafetyDesignBasis Description DesignBasis Description Evaluation InspectionandTesting G191159,Sh1FlowDiagramServiceWater(Part1)

G191159,Sh2FlowDiagramServiceWater(Part2)

Page91of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.7.2 Deletesection10.7.2,ResidualHeatRemovalServiceWaterSystem,SafetyObjective.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.SincerestorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolongerrequired thefunctionsofRHRSWarealsonolongerrequired.Therefore,theRHRSWsafetyobjectiveisnolongerapplicable.ResidualHeatRemovalSWSysteminformationisobsolete.

10.7.3 Deletesection10.7.3ResidualHeatRemovalServiceWaterSystem,PowerGenerationDesignBases TheRHRServiceWater(RHRSW)SystemprovidedadynamicheatsinkfortheResidualHeatRemoval(RHR)Systemduringnormaloperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceremovalofdecayandresidualheatisnolongerrequired,operationof theRHRsystemandRHRSWsystemsisnolongerrequired.Therefore,theRHRSWpowergenerationdesignbasesarenolongerapplicable.ResidualHeatRemovalServiceWaterSystem informationisobsolete.

10.7.4 Deletesection10.7.4,ResidualHeatRemovalServiceWaterSystem,SafetyDesignBases.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.SincerestorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCoolingfollowingaLOCAarenolonger required,thefunctionsofRHRSWarealsonolongerrequired.Therefore,theRHRSWsafetyobjectiveisnolongerapplicable.ResidualHeatRemovalSWSysteminformationisobsolete.

10.7.5 Deletesection10.7.5,ResidualHeatRemovalServiceWaterSystem,Description.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Sinceremovalofdecayandresidualheat,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCooling followingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,theinformationprovidedintheRHRSWdescriptionsectionisnolongerapplicable.

ResidualHeatRemovalSWSysteminformationisobsolete.

10.7.6 Deletesection10.7.6,ResidualHeatRemovalServiceWaterSystem,SafetyEvaluation.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretain fuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolonger possible.Sinceremovalofdecayandresidualheat,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainmentCooling followingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,aRHRSWSystemsafetyevaluationisnolongerrequired.ResidualHeatRemovalSW Systeminformationisobsolete.

10.7.7 Deletesection10.7.7,ResidualHeatRemovalServiceWaterSystem,InspectionandTesting.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceor retainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsareno longerpossible.Sinceremovalofdecayandresidualheat,restorationandmaintenanceofRPVwaterlevelfollowingaLOCA,SuppressionPoolCoolingfollowingaLOCA,andContainment CoolingfollowingaLOCAarenolongerrequired,thefunctionsofRHRSWarealsonolongerrequired.Therefore,InspectionandTestingoftheRHRSWsystemisnolongerrequired.Residual HeatRemovalSWSysteminformationisobsolete.

10.8 TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

10.8.1 DeleteSection10.8.1,AlternateCoolingSystemSafetyObjective.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,theAlternateCoolingSystemsafetyobjectiveisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.

10.8.2 DeleteSection10.8.2,AlternateCoolingSystemSafetyDesignBases.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,theAlternateCoolingSystemsafetydesignbasesarenolongerapplicable.AlternateCoolingSysteminformationisobsolete.

10.8.3 DeleteSection10.8.3,AlternateCoolingSystemDescription.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,theinformationprovidedintheAlternateCoolingSystemdescriptionisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.

SafetyObjective PowerGenerationDesignBases SafetyDesignBases Description SafetyEvaluation InspectionandTesting ALTERNATECOOLINGSYSTEM SafetyObjective SafetyDesignBases Description Page92of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,asafetyevaluationoftheAlternateCoolingSystemdescriptionisnolongerrequired.AlternateCoolingSysteminformationisobsolete.

10.8.5 DeleteSection10.8.5,AlternateCoolingSystemInspectionandTesting.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,inspectionandtestingoftheAlternateCoolingSystemisnolongerrequired.AlternateCoolingSysteminformationisobsolete.

10.8.6 DeleteSection10.8.6,References.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,CalculationVYC1279J,"SWFlowAnalysisDeepBasinBackFlowDuetoSeismicLineBreaksinTurbineBuilding&MinimumEDGFlowratesAfterCommonDischargeHeader Break"isnolongerapplicable.AlternateCoolingSysteminformationisobsolete.

Table10.8.1 DeleteTable10.8.1,RHRSWPumpOperatingModesfortheAlternateCoolingSystem.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,Table10.8.1isnolongerapplicable.AlternateCoolingSysteminformationisobsolete.

Figure10.81 DeleteFigure10.8.1,AlternateCoolingSystem.

TheAlternateCoolingSystem(ACS)providedanalternatemeansofheatremovalintheeventthattheservicewaterpumpsbecomeinoperable.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,decayandsensibleheatremovalfromtheprimarysystemisno longerrequired.AbackupsystemforheatremovalfromtheFuelPoolisnolongerrequired,otherstrategiesareinplacetomaintaincoolingandinventoryinthespentfuelpool.

Consequently,theinformationprovidedonFigure10.81concerningtheAlternateCoolingSystemisnolongerapplicable.AlternateCoolingSysteminformationisobsolete.

10.9 TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

10.9.1 DeleteSection10.9.1,RBCCWSafetyObjective.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWSafetyObjectiveisnolongerapplicable.RBCCWinformationisobsolete.

10.0.2 DeleteSection10.9.2,RBCCWPowerGenerationObjective.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWPowerGenerationObjectiveisnolongerapplicable.RBCCWinformationisobsolete.

10.9.3 DeleteSection10.9.3,RBCCWSafetyDesignBases.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWSafetyDesignBasesarenolongerapplicable.RBCCWinformationisobsolete.

SafetyObjective PowerGenerationObjective SafetyDesignBases SafetyEvaluation InspectionandTesting References RHRSWPumpOperatingModesfortheAlternate CoolingSystem AlternateCoolingSystem REACTORBUILDINGCLOSEDCOOLINGWATERSYSTEM Page93of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheRBCCWPowerGenerationDesignBasesarenolongerapplicable.RBCCWinformationisobsolete.

10.9.5 DeleteSection10.9.5,RBCCWDescription.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheinformationprovidedintheRBCCWDescriptionSectionisnolongerapplicable.RBCCWinformationis obsolete.

10.9.6 DeleteSection10.9.6,RBCCWSafetyEvaluation.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.AnRBCCWSafetyEvaluationisnolongerrequired.RBCCWinformationisobsolete.

10.9.7 DeleteSection10.9.7,RBCCWInspectionandTesting.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.RBCCWInspectionandTestingisnolongerrequired.RBCCWinformationisobsolete.

Figure10.91 DeleteFigure10.91,RCWCoolingWaterSystem.

TheReactorBuildingClosedCoolingWater(RBCCW)Systemprovidedinhibiteddemineralizedwatertocoolreactorauxiliaryequipment.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Reactorauxiliarysystemsoperationwillnolongerberequired.

Consequently,thefunctionsprovidedbytheRBCCWsystemarenolongerrequired.TheinformationprovidedregardingtheRBCCWCoolingWaterSystemonfigure10.91isnolonger applicable.RBCCWinformationisobsolete.

10.10 TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.

10.10.1 DeleteSection10.10.1,TBCCWPowerGenerationObjective.

TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystem arenolongerrequired.TheTBCCWPowerGenerationObjectiveisnolongerapplicable.TBCCWinformationisobsolete.

10.10.2 DeleteSection10.10.2,TBCCWPowerGenerationDesignBases TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystem arenolongerrequired.TheTBCCWPowerGenerationDesignBasesarenolongerapplicable.TBCCWinformationisobsolete.

10.10.3 DeleteSection10.10.3,TBCCWDescription.

TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystem arenolongerrequired.TheinformationprovidedintheTBCCWDescriptionSectionisnolongerapplicable.TBCCWinformationisobsolete.

PowerGenerationDesignBases Description SafetyEvaluation InspectionandTesting G191159,Sh3RCWCoolingWaterSystem TURBINEBUILDINGCLOSEDCOOLINGWATERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Description Page94of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystem arenolongerrequired.TestingandInspectionoftheTBCCWSystemisnolongerrequired.TBCCWinformationisobsolete.

Figure10.10 1

DeleteFigure10.101,TurbineBuildingClosedCoolingWaterSystem.

TheTurbineBuildingClosedCoolingWater(TBCCW)SystemprovidedinhibiteddemineralizedcoolingwatertoauxiliaryequipmentintheTurbineBuildingrequiringcoolingwater.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Auxiliarysystemsoperationintheturbinebuildingwillnolongerberequired.Consequently,thefunctionsprovidedbytheTBCCWsystem arenolongerrequired.TheinformationprovidedonFigure10.101isnolongerapplicable.TBCCWinformationisobsolete.

10.11 3.3.4 10.11.1 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisno applicabletoapermanentlydefueledstation.

3.3.4.1 10.11.2 Deleted"PowerGeneration"fromthesectiontitle.SincetheclassificationprocessdescribedinUFSARsection1.4.1isnolongerused,theclassificationbasisisnolongerrequiredandisno applicabletoapermanentlydefueledstation.

3.3.4.2 10.11.3 DeletedreferencetotheAppendix"R"Programandthesafeshutdowncapabilityanalysissincetheprogramnolongerappliespostcertificationofpermanentdefueling.

Addedthewords"Thefireprotectionprogramforthepermanentlydefueledstatehasbeendevelopedbasedontheapplicablerequirementsof10CFR50.48andBTPAPCSB9.51,AppendixA.

TheFireHazardsAnalysis(FHA)documentsexistingplantconfigurationsanddefinestheresourcesavailableforthepreventionandlimitationofdamagefromfire(Reference1).Inadditionto plansandphysicalconfigurationsforfireprotection,firedetection,firesuppressionandlimitationoffiredamage,theFHAalsoprovidesanoveralldescriptionofthefireprotectionprogram."

toreflectthefacilitystatepostdefueling.

Removedthewords"ThefollowingdocumentsformthebasisoftheFireProtectionProgramandareincorporatedbyreferenceintotheDSAR:

• FireProtectionProgram

• FireHazardAnalysis toremovetheIBRsinceitisnolongerrequired.

3.3.4.3 10.11.4 Nochanges 3.3.4.4 10.11.5 Deletesection10.11.5,References.Onlyreferenceinthissection,referencetotheSafeShutdownCapabilityAnalysis,wasdeletedsincetheanalysisnolongerappliespostcertificationof permanentdefueling.

ReaddedVYFireHazardsAnalysisasareference.

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"whereappropriate Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.5.1 10.12.2 ModifySection10.12.2toeliminatereferencetopurgingtheprimarycontainment.

Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

Removereferencetopurgingprimarycontainment.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,the functionsofthePrimaryContainmentSystemarenolongerrequiredandthesafetydesignbasesarenolongerapplicable.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 G191159,Sh4TurbineBuildingClosedCooling WaterSystem FireProtectionSystem PowerGenerationObjective PowerGenerationDesignBasis FIREPROTECTIONSYSTEM Objective DesignBasis Description InspectionandTesting References PowerGenerationDesignBasis Description ReactorBuilding G191163,Sh1FireProtectionSystem G191163,Sh2FireProtectionSystem(Outer Loop)

STATIONHEATING,VENTILATING,ANDAIRCONDITIONING SYSTEMS PowerGenerationObjective G191163,Sh1FireProtectionSystem G191163,Sh2FireProtectionSystem(OuterLoop)

Heating,VentilatingandAirConditioningSystems Objective DesignBasis Description Page95of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.12.3.2 ModifySection10.12.3.2todeletereferencetothemodularfacilitylocatedontheturbinedeckwithaventilationsystemindependentoftheturbinebuildingventilationsystem.Thefacility wasastagingareaforpersonnelengagedinmainturbineandgeneratorworkduringrefuelingoutages.Sincerefuelingoutages,includingturbineandgeneratoroverhauls,willnolongerbe conducted,thefunctionsprovidedbythemodularfacilityarenolongerrequired.Thereforethesefunctionsareobsoleteandmaybedeleted.

3.3.5.3.2 TurbineBuilding 10.12.3.3 ModifySection10.12.3.3todeletereferencetomanualoperationofcontrolroomventilationdampersduringaLOCA,includingreferencetomanualoperationofdamperswithin3hoursafter theevent.Followingcertificationofpermanentdefueling,thelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvessel.Therefore,poweroperationscannolongeroccur andaLOCAisnotpossible.Additionally,thethreehourrequirementoriginatedinanAppendixRscenario.The3hourlimitintendedtoensurecontrolroomtemperatureremainedbelow120F topreventchallengingequipmentoperatinglimits.Postdefueling,AppendixRisnolongerapplicable.

3.3.5.3.3 MainControlRoom 10.12.3.4 NoChanges 3.3.5.3.4 ServiceBuilding 10.12.3.5 NoChanges 3.3.5.3.5 RadwasteBuilding 10.12.3.6 NoChanges 3.3.5.3.6 HeatingBoiler System 10.12.3.7 NoChanges 3.3.5.3.7 AdvancedOffGas BuildingHVAC 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 Figure3.3.5 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,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.8.1.1 10.13.2 ModifySection10.13.2,StationMakeupWaterSystem,PowerGenerationDesignBasis,toremovereferencetooperatingandaccidentconditionsandreflectthattheStationMakeupWate Systemnowsuppliesonlymakeupwaternecessarytoensurethesafestorageandhandlingofirradiatedfuel.

Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.8.1.2 10.13.3 ModifiedSection10.13.3,Description,toremovereferenceto"potable"watertoaccommodatechangesduetoEC45613,trackedbyFCR27003 3.3.8.1.3 10.13.3.1 EditorialChangesonly.

3.3.8.1.3.1 General 10.13.3.2 Nochanges 3.3.8.1.3.2 Pretreatment System 10.13.3.3 Nochanges 3.3.8.1.3.3 Demineralizer System 10.13.4 Nochanges 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,toremovereferencetooperatingandaccidentconditionsandreflectthattheStation InstrumentandServiceAirSystemsnowsupplyonlypressurizedairnecessarytoensurethesafestorageandhandlingofirradiatedfuel.

Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.6.1 TurbineBuilding MainControlRoom ServiceBuilding InspectionandTesting STATIONMAKEUPWATERSYSTEM PowerGenerationObjective G191237,Sh2HVACFlowDiagramTurbine, Service,and ControlRoomBuildings G191236HVACFlowDiagramRadwaste Building G191254StationHeatingBoilerSystem G191237,Sh2HVACFlowDiagramTurbine,Service,and ControlRoomBuildings G191236HVACFlowDiagramRadwasteBuilding G191254StationHeatingBoilerSystem ReactorBuildingHeatingVentilationandAirConditioningG 191238 MAKEUPWATERSYSTEM Objective DesignBasis Description RadwasteBuilding StationHeatingBoilerSystem AdvancedOffGasBuildingHVAC InspectionandTesting G191237,Sh1HVACFlowDiagramTurbine, Service,and ControlRoomBuildings G191237,Sh1HVACFlowDiagramTurbine,Service,and ControlRoomBuildings G191161MakeUpWaterTreatmentSystem STATIONINSTRUMENTANDSERVICEAIRSYSTEMS PowerGenerationObjective PretreatmentSystem DemineralizerSystem InspectionandTesting InspectionandTesting G191161MakeUpWaterTreatmentSystem INSTRUMENTANDSERVICEAIRSYSTEMS Objective PowerGenerationDesignBasis Description General Page96of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.14.2 ModifySection10.14.2,StationInstrumentandServiceAirSystems,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheStation InstrumentandServiceAirSystemsnowsupplyonlypressurizedairnecessarytoensurethesafestorageandhandlingofirradiatedfuel.

Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.6.2 10.14.3 ModifySection10.14.3,StationInstrumentandServiceAirSystems,Descriptiontoremovereferencetooperatingandaccidentconditions,theCompressednitrogensystemandreflectthatthe StationInstrumentandServiceAirSystemsnowsupplyonlypressurizedairnecessarytoensurethesafestorageandhandlingofirradiatedfuel.

TheCompressednitrogenSystemsuppliedcompressednitrogenforpneumaticinstrumentsandcontrolslocatedintheprimarycontainmentwhencontainmentwasinerted.Following certificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclear core,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Sinceprimarycontainmentisnolongerrequiredandcontainmentinertingwillno longeroccur,compressednitrogenforpneumaticsinthedrywellisnolongerrequired.

3.3.6.3 10.14.4 Editorialchangesonly 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 Figure3.3.6 8

10.15 3.3.8.2 10.15.1 ModifySection10.15.1,StationPotableandSanitaryWaterSystem,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditions Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.8.2.1 10.15.2 ModifySection10.15.2,StationPotableandSanitaryWaterSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditions Deletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,theterm isnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

3.3.8.2.2 10.15.3 ModifiedSection10.15.3,Description,toremovereferenceto"potable"waterandchangenumberofwellsfromfourtotwoandremoveoverlydetailedinformation,toaccommodatechanges duetoEC45613,trackedbyFCR27003.

3.3.8.2.3 10.16 4.5.1 10.16.1 ModifySection10.16.1,StationEquipmentandFloorDrainageSystems,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimary stationfunctionisnowthesafestorageandhandlingofirradiatedfuel.

4.5.1.1 10.16.2 ModifySection10.16.2,StationEquipmentandFloorDrainageSystems,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheprimary stationfunctionisnowthesafestorageandhandlingofirradiatedfuel.

4.5.1.2 10.16.3 4.5.1.3 10.16.3.1 NoChanges 4.5.1.3.1 10.16.3.2 ModifySection10.16.3.2,RadioactiveEquipmentDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafe storageandhandlingofirradiatedfuel.

4.5.1.3.2 10.16.3.3 ModifySection10.16.3.3,RadioactiveFloorDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorage andhandlingofirradiatedfuel.

4.5.1.3.3 10.16.3.4 ModifySection10.16.3.4,RadioactiveLiquidChemicalDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafe storageandhandlingofirradiatedfuel.

4.5.1.3.4 PowerGenerationDesignBasis Description InspectionandTesting DesignBasis Description InspectionandTesting G191160,Sh7FlowDiagramDieselGenerator StartingAirSystem G191160,Sh8FlowDiagramServiceAirSystem STATIONPOTABLEANDSANITARYWATERSYSTEM G191160,Sh4InstrumentAirSystemFlow Diagram G191160,Sh5FlowDiagramServiceAirSystem G191160,Sh6FlowDiagramServiceAirSystem G191160,Sh1FlowDiagramInstrumentAir System G191160,Sh2ServiceandInstrumentAirSystem (Reactor G191160,Sh3InstrumentAirSystemFlow Diagram POTABLEANDSANITARYWATERSYSTEM G191160,Sh1FlowDiagramInstrumentAirSystem G191160,Sh2ServiceandInstrumentAirSystem(Reactor G191160,Sh3InstrumentAirSystemFlowDiagram G191160,Sh4InstrumentAirSystemFlowDiagram G191160,Sh5FlowDiagramServiceAirSystem G191160,Sh6FlowDiagramServiceAirSystem G191160,Sh7FlowDiagramDieselGeneratorStartingAirSystem G191160,Sh8FlowDiagramServiceAirSystem Description General RadioactiveEquipmentDrainage Systems STATIONEQUIPMENTANDFLOORDRAINAGESYSTEMS PowerGenerationObjective PowerGenerationDesignBasis PowerGenerationObjective PowerGenerationDesignBasis Description Objective DesignBasis Description EQUIPMENTANDFLOORDRAINAGESYSTEMS Objective DesignBasis Description General RadioactiveEquipmentDrainage Systems RadioactiveFloorDrainageSystems RadioactiveLiquidChemicalDrainage Systems RadioactiveFloorDrainageSystems RadioactiveLiquidChemicalDrainage Systems Page97of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.16.3.5 ModifySection10.16.3.5,OilDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageandhandlingo irradiatedfuel.

Editorialmodificationaddedtoremovethepotentialimpressionthatanoilwatermixturemaybedrainedtotheenvironment.

4.5.1.3.5 10.16.3.6 ModifySection10.16.3.6,NonradioactiveWaterDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafe storageandhandlingofirradiatedfuel.

4.5.1.3.6 10.16.3.7 ModifySection10.16.3.7,SanitaryDrainageSystems,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageand handlingofirradiatedfuel.

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 Modifiedtoreflectdefueledstate DeletedpointertoProcessRadMonitoring,notrequired 3.3.7.3.1 10.17.3.2 Deletethissection,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,closed coolingloop,condensateandCirculatingwatersystemsarenolongerrequiredfollowingpermanentdefueling.Therefore,samplingofthosesystemsisnolongerrequired.Theinformation deletedfromTable10.17.1isobsolete.Remaininginformationinthetablehasbeenrelocatedintothetextbodyofthissection Table10.17.2 ModifiedTable10.17.2,GasSamplestoremovegaseoussamplepointsnolongerusedpostdefueling.TheAirEjectoroffgas,OffGasFiltersamplesandStandbyGasTreatmentSystemsareno longerrequiredfollowingpermanentdefueling.Therefore,samplingofthosesystemsisnolongerrequired.TheinformationdeletedfromTable10.17.2isobsolete.Remaininginformationin thetablehasbeenrelocatedintothetextbodyofthissection Figure10.17 1

Nochanges Figure3.3.7 1

Figure10.17 2

Nochanges Figure3.3.7 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,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunction isnowthesafestorageandhandlingofirradiatedfuel.

3.3.10.2 10.18.3 ModifySection10.18.3,StationCommunicationsSystem,Descriptiontoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafe storageandhandlingofirradiatedfuel.

3.3.10.3 10.18.4 NoChanges 3.3.104 10.19 3.3.9 10.19.1 ModifySection10.19.1,StationLightingSystem,PowerGenerationObjective,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthe safestorageandhandlingofirradiatedfuel.

3.3.9.1 10.19.2 ModifySection10.19.2,StationLightingSystem,PowerGenerationDesignBasistoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnow thesafestorageandhandlingofirradiatedfuel.

3.3.9.2 10.19.3 ModifySection10.19.3,StationLightingSystem,Descriptiontoremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageand handlingofirradiatedfuel.

3.3.9.3 10.19.4 Nochanges 3.3.9.4 General TurbineBuildingSamplingPanel ReactorBuildingSamplingPanel PowerGenerationObjective PowerGenerationDesignBasis Description NonradioactiveWaterDrainage Systems SanitaryDrainageSystems InspectionandTesting STATIONPROCESSSAMPLINGSYSTEMS OilDrainageSystems OilDrainageSystems NonradioactiveWaterDrainageSystems SanitaryDrainageSystems InspectionandTesting PROCESSSAMPLINGSYSTEMS Objective PowerGenerationObjective PowerGenerationDesignBasis Description Description InspectionandTesting STATIONLIGHTINGSYSTEMS STATIONCOMMUNICATIONSSYSTEM PowerGenerationObjective PowerGenerationDesignBasis GasSamples G191164StationProcessSamplingSystem G191165StationProcessSamplingSystem RadwasteBuildingSamplingPanel GasSamplingandMonitoring FluidSamples G191164StationProcessSamplingSystem G191165StationProcessSamplingSystem Objective DesignBasis Description InspectionandTesting COMMUNICATIONSSYSTEM LIGHTINGSYSTEMS Objective DesignBasis Description InspectionandTesting InspectionandTesting DesignBasis Description General RadwasteBuildingSamplingPanel GasSamplingandMonitoring Page98of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table10.19.1 ModifyTable10.19.1,AreasRequiringStandbyLighting,toremovereferencetooperatingandaccidentconditionsandreflectthattheprimarystationfunctionisnowthesafestorageand handlingofirradiatedfuel.Remaininginformationinthetablehasbeenrelocatedintothetextbodyinthissection.

10.20 Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

10.20.1 Deletesection10.20.1,PostAccidentSamplingSystemSafetyObjective.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystem arenolongerrequired.ThePostAccidentSamplingSystemSafetyObjectiveisnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.

10.20.2 Deletesection10.20.2,PostAccidentSamplingSystemSafetyDesignBasis.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystem arenolongerrequired.ThePostAccidentSamplingSystemSafetyDesignBasisisnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.

10.20.3 Deletesection10.20.3,PostAccidentSamplingSystemDescription.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystem arenolongerrequired.TheinformationprovidedinthePostAccidentSamplingSystemDescriptionsectionisnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.

10.20.4 Deletesection10.20.4,PostAccidentSamplingSystemSafetyEvaluation.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystem arenolongerrequired.APostAccidentSamplingSystemSafetyEvaluationnolongerrequired.PostAccidentSamplingSysteminformationisobsolete.

10.20.5 Deletesection10.20.5,PostAccidentSamplingSystemInspectionandTesting.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystem arenolongerrequired.InspectionandTestingofthePostAccidentSamplingSystemisnolongerrequired.PostAccidentSamplingSysteminformationisobsolete.

Figure10.20 1

DeleteFigure10.201,FundamentalFlowDiagramPostAccidentSamplingSystem.

Thepostaccidentsamplingsystemprovidedrepresentativesamplesofreactorcoolantforanalysiswhichwouldbeindicativeoftheextentanddevelopmentofcoredamage.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbythePostAccidentSamplingSystem arenolongerrequired.Theinformationprovidedonfigure10.201isnolongerapplicable.PostAccidentSamplingSysteminformationisobsolete.

10.21 TheAdvancedOffGasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycolwatercoolingtoauxiliaryequipmentintheadvancedoffgasbuilding.

10.21.1 Deletesection10.21.1,AdvancedOffGasCoolingWaterSystemPowerGenerationObjective.

TheAdvancedOffGasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycolwatercoolingtoauxiliaryequipmentintheadvancedoffgasbuilding.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOffGasClosed CoolingWaterSystemarenolongerrequired.TheAdvancedOffGasClosedCoolingWaterSystemPowerGenerationObjectiveisnolongerapplicable.AdvancedOffGasClosedCoolingWater Systeminformationisobsolete.

PowerGenerationObjective SafetyDesignBasis Description SafetyEvaluation InspectionandTesting G191165FundamentalFlowDiagramPost AccidentSamplingSystem ADVANCEDOFFGASCLOSEDCOOLINGWATERSYSTEM AreasRequiringStandbyLighting POSTACCIDENTSAMPLINGSYSTEM SafetyObjective Page99of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 10.21.2 Deletesection10.21.2,AdvancedOffGasCoolingWaterSystemPowerGenerationDesignBasis.

TheAdvancedOffGasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycolwatercoolingtoauxiliaryequipmentintheadvancedoffgasbuilding.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOffGasClosed CoolingWaterSystemarenolongerrequired.TheAdvancedOffGasClosedCoolingWaterSystemPowerGenerationDesignBasisisnolongerapplicable.AdvancedOffGasClosedCooling WaterSysteminformationisobsolete.

10.21.3 Deletesection10.21.3,AdvancedOffGasCoolingWaterSystemDescription.

TheAdvancedOffGasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycolwatercoolingtoauxiliaryequipmentintheadvancedoffgasbuilding.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOffGasClosed CoolingWaterSystemarenolongerrequired.TheinformationprovidedintheAdvancedOffGasClosedCoolingWaterSystemDescriptionisnolongerapplicable.AdvancedOffGasClosed CoolingWaterSysteminformationisobsolete.

10.21.4 Deletesection10.21.4,AdvancedOffGasCoolingWaterSystemInspectionandTesting.

TheAdvancedOffGasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycolwatercoolingtoauxiliaryequipmentintheadvancedoffgasbuilding.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOffGasClosed CoolingWaterSystemarenolongerrequired.InspectionandtestingoftheAdvancedOffGasClosedCoolingWaterSystemisnolongerrequired.AdvancedOffGasClosedCoolingWater Systeminformationisobsolete.

Figure10.21 1

DeleteFigure10.211,AOGCWFlowDiagram.

TheAdvancedOffGasClosedCoolingWaterSystem(AOGCCW)providedinhibitedglycolwatercoolingtoauxiliaryequipmentintheadvancedoffgasbuilding.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAdvancedOffGasClosed CoolingWaterSystemarenolongerrequired.TheinformationprovidedonFigure10.211isnolongerapplicable.AdvancedOffGasClosedCoolingWaterSysteminformationisobsolete.

11.0 StationPowerConversionSystems 11.1 DeleteSection11.1,SummaryDescriptionoftheStationPowerConversionSystems.

Thestationpowerconversionsystemswerethosesystemswhichwererequiredtoconverttheenergyofnuclearsteamtoelectricalenergy.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformation providedbytheStationPowerConversionSystemsarenolongerrequired.StationPowerConversionSystemsinformationisobsolete.

11.2 TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.

11.2.1 DeleteSection11.2.1,MainTurbineGeneratorPowerGenerationObjective.

TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformation providedbytheMainTurbineGeneratorarenolongerrequired.TheMainTurbineGeneratorPowerGenerationObjectiveisnolongerapplicable.MainTurbineGeneratorinformationis obsolete.

11.2.2 DeleteSection11.2.2,MainTurbineGeneratorPowerGenerationDesignBasis TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformation providedbytheMainTurbineGeneratorarenolongerrequired.TheMainTurbineGeneratorPowerGenerationDesignBasisisnolongerapplicable.MainTurbineGeneratorinformationi obsolete.

11.2.3 DeleteSection11.2.3,MainTurbineGenerator,Description.

TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformation providedbytheMainTurbineGeneratorarenolongerrequired.TheinformationprovidedintheMainTurbineGeneratordescriptionsectionisnolongerapplicable.MainTurbine Generatorinformationisobsolete.

11.2.4 DeleteSection11.2.4,MainTurbineGenerator,InspectionandTesting.

TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformation providedbytheMainTurbineGeneratorarenolongerrequired.InspectionandTestingoftheMainTurbineGeneratorisnolongerrequired.MainTurbineGeneratorinformationis obsolete.

PowerGenerationDesignBasis Description TestingandInspection G191159,Sh6AOGCWFlowDiagram

SUMMARY

DESCRIPTION MAINTURBINEGENERATOR PowerGenerationObjective PowerGenerationDesignBasis Description TestingandInspection Page100of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure11.21 DeleteFigure11.21,TurbineGenerator,MainSteamandExtractionSteamSystems.

TheMainTurbineGeneratorSystemconvertedthethermodynamicenergyofthesteamintoelectricalenergy.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandelectricalpowercannotbegenerated.Consequently,thefunctionsandinformation providedbytheMainTurbineGeneratorarenolongerrequired.TheinformationprovidedonFigure11.21isnolongerapplicable.MainTurbineGeneratorinformationisobsolete.

11.3 TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationof condensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.

11.3.1 DeleteSection11.3.1,MainCondenserSystem,PowerGenerationObjective.

TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationof condensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired, condensatepumpNPSHisnotrequiredandnosteamcyclemakeupisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.TheMain CondenserSystemPowerGenerationObjectiveisnolongerapplicable.MainCondenserinformationisobsolete.

11.3.2 DeleteSection11.3.2,MainCondenserSystem,PowerGenerationDesignBasis TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationof condensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired, condensatepumpNPSHisnotrequiredandnosteamcyclemakeupisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.TheMain CondenserSystemPowerGenerationDesignBasesarenolongerapplicable.MainCondenserinformationisobsolete.

11.3.3 DeleteSection11.3.3,MainCondenserSystem,PowerGenerationDesignBasis TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationof condensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired, condensatepumpNPSHisnotrequiredandnosteamcyclemakeupwastisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.TheMain CondenserSystemPowerGenerationDesignBasesarenolongerapplicable.MainCondenserinformationisobsolete.

11.3.4 DeleteSection11.3.4,MainCondenserSystem,PowerGenerationDesignBasis TheMainCondenserSystemprovidedaheatsinkforsteamcondensationduringnormaloperationorsteambypassvalveoperation.Themaincondenseralsoprovidedforthedeaerationof condensate,providedNPSHforthecondensatepumps,andservedasamakeuppointforwaterusedinthesteamcycle.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamcondensationisnotrequired,condensatedeaerationisnotrequired, condensatepumpNPSHisnotrequiredandnosteamcyclemakeupwastisrequired.ThefunctionsandinformationprovidedbytheMainCondenserSystemarenolongerrequired.Inspection andTestingoftheMainCondenserSystemisnolongerrequired.MainCondenserinformationisobsolete.

11.4 Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

11.4.1 DeleteSection11.4.1,MainCondenserGasRemovalandTurbineSealingSystems,PowerGenerationObjective.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewill nolongeroperate,turbinesealingisnotrequired.ThefunctionsandinformationprovidedbytheMainCondenserGasRemovalandTurbineSealingSystemsarenolongerrequired.TheMain CondenserGasRemovalandTurbineSealingSystemsPowerGenerationObjectiveisnolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

PowerGenerationObjective MAINCONDENSERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Description TestingandInspection MAINCONDENSERGASREMOVALANDTURBINESEALING SYSTEMS G191156TurbineGenerator,MainSteamand ExtractionSteamSystems Page101of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewill nolongeroperate,turbinesealingisnotrequired.ThefunctionsandinformationprovidedbytheMainCondenserGasRemovalandTurbineSealingSystemsarenolongerrequired.TheMain CondenserGasRemovalandTurbineSealingSystemsPowerGenerationDesignBasesarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationis obsolete.

11.4.3 11.4.3.1 DeleteSection11.4.3.1,MainCondenserGasRemovalandTurbineSealingSystems,GeneralDescription.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewill nolongeroperate,turbinesealingisnotrequired.ThefunctionsandinformationdescribedintheMainCondenserGasRemovalandTurbineSealingSystemsGeneralDescriptionSectionareno longerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

11.4.3.2 DeleteSection11.4.3.2,MainCondenserGasRemovalandTurbineSealingSystems,CondenserHoggingPump.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

AmechanicalacmotordrivenremotemanuallyoperatedVBeltrotarytypepumpremovednoncondensiblegassesduringstartup.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.Thefunctionsandinformation describedintheCondenserHoggingPumpSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

11.4.3.3 DeleteSection11.4.3.3,MainCondenserGasRemovalandTurbineSealingSystems,SteamJetAirEjectors.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Duringoperation,steamjetairejectorsremovedgasesandvaporsfromthemaincondensersusingmainsteam,reducedinpressure,asthedrivingmedium..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.Thefunctionsandinformation describedintheSteamJetAirEjectorsSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

11.4.3.4 DeleteSection11.4.3.4,MainCondenserGasRemovalandTurbineSealingSystems,SteamPackingExhausterUnit.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Duringoperation,onesteampackingexhausterunitcollectedandcondensedsealingsteamanddischargedairleakagetotheoffgassystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.Thefunctionsandinformation describedintheSteamPackingExhausterUnitSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

11.4.3.5 DeleteSection11.4.3.5,MainCondenserGasRemovalandTurbineSealingSystems,SteamSealRegulator.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Duringoperation,thesteamsealregulatormaintainedthesamepreselectedsteampressureinthepackingheaderregardlessofthesteamturbineload..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired.Thefunctionsandinformation describedintheSteamSealRegulatorSectionarenolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

PowerGenerationDesignBases Description General CondenserHoggingPump SteamJetAirEjectors SteamPackingExhausterUnit SteamSealRegulator Page102of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewill nolongeroperate,turbinesealingisnotrequired.InspectionandTestingoftheMainCondenserGasRemovalandTurbineSealingSystemsGeneralDescriptionSectionisnotrequired.Main CondenserGasRemovalandTurbineSealingSystemsinformationisobsolete.

Figure11.41 DeleteFigure11.41,TurbineSteamSealSystem.

Themaincondensergasremovalsystemevacuatedgasesfromthemainturbineandmaincondenserduringstartupandmaintainedthesystemfreeofnoncondensiblegasesduringoperation.

Theturbinesealingsystemactedinconjunctionwiththegasremovalsystemtopreventairfromenteringintothesystemduringstartupandoperationandtopreventsteamfromleakingtoth atmosphere.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,maincondensergasremovalisnotrequired,and,sincethemainturbinewill nolongeroperate,turbinesealingisnotrequired.TheinformationprovidedonFigure11.41isnolongerapplicable.MainCondenserGasRemovalandTurbineSealingSystemsinformationis obsolete.

11.5 Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

11.5.1 DeleteSection11.5.1,SteamSystems,PowerGenerationObjective.

Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsPowerGeneration Objectiveisnolongerapplicable.SteamSystemsinformationisobsolete.

11.5.2 DeleteSection11.5.2,SteamSystems,PowerGenerationDesignBases Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsPowerGeneration DesignBasesarenolongerapplicable.SteamSystemsinformationisobsolete.

11.5.3 DeleteSection11.5.3,SteamSystems,SafetyDesignBases Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsSafetyDesignBasesare nolongerapplicable.SteamSystemsinformationisobsolete.

11.5.4 11.5.4.1 DeleteSection11.5.4.1,MainSteamSystemDescription Themainsteamsystemconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbine.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,themainsteamsystemisnolongerrequired.ThedescriptionoftheMain SteamSystemisnolongerapplicable.SteamSystemsinformationisobsolete.

11.5.4.2 DeleteSection11.5.4.2,MainSteamTurbineBypassSystemDescription TheMainTurbineBypasssystemopenedwheneverthepermittedadmissionofsteamintotheturbinewaslessthantheamountofsteamgeneratedbythereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,themainturbinebypasssystemisnolongerrequired.Thedescriptionofthe mainturbinebypasssystemisnolongerapplicable.SteamSystemsinformationisobsolete.

PowerGenerationDesignBases SafetyDesignBases Description MainSteamSystem MainTurbineBypassSystem InspectionandTesting 592012598TurbineSteamSealSystem STEAMSYSTEMS PowerGenerationObjective Page103of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.5.4.3 DeleteSection11.5.4.3,ExtractionSteamSystemDescription.ExtractionSteamprovidedsteamforfeedwaterpreheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,theExtractionSteamsystemisnolongerrequired.Thedescriptionofthe ExtractionSteamSystemisnolongerapplicable.SteamSystemsinformationisobsolete.

11.5.5 DeleteSection11.5.5,SteamSystems,SafetyEvaluation Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheSteamSystemsSafetyEvaluationisare nolongerapplicable.SteamSystemsinformationisobsolete.

11.5.6 DeleteSection11.5.6SteamSystems,TestsandInspections.

Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TestsandInspectionoftheSteamSystems arenolongerrequired.SteamSystemsinformationisobsolete.

Figure11.51 DeleteFigure11.51,PrimarySteamPipingArrangement.

Thesteamsystemsconductedsteamfromthereactorvesselthroughtheprimarycontainmenttothesteamturbineatacontrolledpressureduringnormaloperation,bypassedsteamdirectly tothemaincondensertocontrolpressureduringreactorvesselheatupandastheturbinewasbroughtonlineandwhenreactorsteamgenerationexceededtheturbinerequirements,and duringreactorcooldown.Steamsystemsalsoprovidedturbineextractionsteamforcondensateandreactorfeedwaterheating.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,steamsystemsarenotrequired.TheinformationprovidedonFigure11.51 isnolongerapplicable.SteamSystemsinformationisobsolete.

11.6 TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersfor steamcondensationandheatremovalinthecondensers.

11.6.1 DeleteSection11.6.1,CirculatingWaterSystems,PowerGenerationObjective.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersfor steamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.TheCirculatingWaterSystems PowerGenerationObjectiveisnolongerapplicable.CirculatingWaterSystemsinformationisobsolete.

11.6.2 DeleteSection11.6.2,CirculatingWaterSystems,PowerGenerationDesignBases.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersfor steamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.TheCirculatingWaterSystems PowerGenerationDesignBasesarenolongerapplicable.CirculatingWaterSystemsinformationisobsolete.

11.6.3 DeleteSection11.6.3,CirculatingWaterSystems,Description.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersfor steamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Thefunctionsandinformation providedbytheCirculatingWaterSystemarenolongerrequired.InformationprovidedintheCirculatingWaterSystemDesriptionsectionisnolongerapplicable.MainCondenserinformation isobsolete.

SafetyEvaluation TestsandInspections 5920569PrimarySteamPipingArrangement CIRCULATINGWATERSYSTEMS PowerGenerationObjective PowerGenerationDesignBases ExtractionSteam Description Page104of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 11.6.4 DeleteSection11.6.4,CirculatingWaterSystems,InspectionandTesting.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersfor steamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.InspectionandTestingofthe CirculatingWaterSystemisnolongerrequired.InformationprovidedintheCirculatingWaterSystemInspectionandTestingsectionisnolongerapplicable.MainCondenserinformationis obsolete.

Figure11.61 DeleteFigure11.61,CirculatingWaterSystems.

TheCirculatingWaterSystemprovidedacontinuoussupplyofcoolingwaterpumpedfromandreturnedtotheConnecticutRiverorbyrecirculationflowpumpedthroughcoolingtowersfor steamcondensationandheatremovalinthecondensers.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Thefunctionsandinformation providedbytheCirculatingWaterSystemarenolongerrequired.InformationprovidedonFigure11.61isnolongerapplicable.CirculatingWaterinformationisobsolete.

11.7 Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

11.7.1 DeleteSection11.7.1,CondensateDemineralizerSystem,PowerGenerationObjective.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thecondensate demineralizersystemisnolongerrequired.TheCondensateDemineralizerSystemPowerGenerationObjectiveisnolongerapplicable.InformationprovidedintheCondensateDemineralizer PowerGenerationObjectivesectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.

11.7.2 DeleteSection11.7.2,CondensateDemineralizerSystem,PowerGenerationDesignBases.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thecondensate demineralizersystemisnolongerrequired.TheCondensateDemineralizerSystemPowerGenerationDesignBasesarenolongerapplicable.InformationprovidedintheCondensate DemineralizerPowerGenerationDesignBasessectionisnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.

11.7.3 11.7.3.1 DeleteSection11.7.3.1,CondensateDemineralizerSystem,GeneralDescription.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsand informationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerGeneralDescriptionsectionisnolonger applicable.CondensateDemineralizerSysteminformationisobsolete.

11.7.3.2 DeleteSection11.7.3.2,CondensateDemineralizerSystem,EquipmentDescription.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsand informationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerEquipmentDescriptionsectionisnolonger applicable.CondensateDemineralizerSysteminformationisobsolete.

11.7.3.3 DeleteSection11.7.3.3,CondensateDemineralizerSystem,ControlandInstrumentation.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsand informationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerControlandInstrumentationdescriptionsection isnolongerapplicable.CondensateDemineralizerSysteminformationisobsolete.

Description General Equipment ControlandInstrumentation InspectionandTesting G191166CirculatingWaterSystems CONDENSATEDEMINERALIZERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Page105of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsand informationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerSpecificationssectionisnolongerapplicable.

CondensateDemineralizerSysteminformationisobsolete.

11.7.4 DeleteSection11.7.4,CondensateDemineralizerSystem,InspectionandTesting.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsand informationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InspectionandTestingoftheCondensateDemineralizerSystemisnolongerrequired.Condensate DemineralizerSysteminformationisobsolete.

Figure11.71 DeleteFigure11.71,CondensateDemineralizerSystem.

Thecondensatedemineralizersystemmaintainedtherequiredpurityoffeedwatersuppliedtothereactor.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Consequently,thefunctionsand informationprovidedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedonFigure11.71isnolongerapplicable.CondensateDemineralizerSystem informationisobsolete.

11.8.1 DeleteSection11.8.1,CondensateandReactorFeedwaterSystems,PowerGenerationObjective.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.TheCondensateandReactor FeedwaterSystemsPowerGenerationObjectiveisnolongerapplicable.InformationprovidedintheCondensateandReactorFeedwaterSystemsPowerGenerationObjectivesectionisno longerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.

11.8.2 DeleteSection11.8.2,CondensateandReactorFeedwaterSystems,PowerGenerationObjective.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.TheCondensateandReactor FeedwaterSystemsPowerGenerationDesignBasesarenolongerapplicable.InformationprovidedintheCondensateandReactorFeedwaterSystemsPowerGenerationDesignBasessection isnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.

11.8.3 11.8.3.1 DeleteSection11.8.3.1,CondensateandReactorFeedwaterPumps.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheCondensateandReactorFeedwaterPumpsarenolongerrequired.InformationprovidedintheCondensateandReactorFeedwaterPumpssectionisnolonger applicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.

11.8.3.2 DeleteSection11.8.3.2,ReactorFeedwaterHeaters.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheReactorFeedwaterHeatersarenolongerrequired.InformationprovidedintheReactorFeedwaterHeaterssectionisnolongerapplicable.CondensateandReactorFeedwater Systemsinformationisobsolete.

G191274CondensateDemineralizerSystem 11.8 CONDENSATEANDREACTORFEEDWATERSYSTEMS Specifications InspectionandTesting CondensateandReactorFeedwater Pumps ReactorFeedwaterHeaters PowerGenerationObjective PowerGenerationDesignBases Description TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

Page106of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheCondensateDemineralizerSystemarenolongerrequired.InformationprovidedintheCondensateDemineralizerSystemsectionisnolongerapplicable.Condensateand ReactorFeedwaterSystemsinformationisobsolete.

11.8.3.4 DeleteSection11.8.3.4,SteamJetAirEjector(SJAE)Intercondensers.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheSteamJetAirEjector(SJAE)Intercondensersarenolongerrequired.InformationprovidedintheSteamJetAirEjector(SJAE)Intercondenserssectionisnolongerapplicable.

CondensateandReactorFeedwaterSystemsinformationisobsolete.

11.8.3.5 DeleteSection11.8.3.5,SteamPackingExhauster.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheSteamPackingExhausterarenolongerrequired.InformationprovidedintheSteamJetAirEjector(SJAE)Intercondenserssectionisnolongerapplicable.Condensateand ReactorFeedwaterSystemsinformationisobsolete.

11.8.3.6 DeleteSection11.8.3.6,FeedwaterControlStation.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheFeedwaterControlStationarenolongerrequired.InformationprovidedintheFeedwaterControlStationsectionisnolongerapplicable.CondensateandReactorFeedwater Systemsinformationisobsolete.

11.8.3.7 DeleteSection11.8.3.7,CondensateandFeedwaterSystemMinimumFlowBypasses.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheCondensateandFeedwaterSystemMinimumFlowBypassesarenolongerrequired.InformationprovidedintheCondensateandFeedwaterSystemMinimumFlowBypasses sectionisnolongerapplicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.

11.8.3.8 DeleteSection11.8.3.8,CondensateandFeedwaterSystemKeepFillPressurizingLine.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheKeepFillPressurizingLinearenolongerrequired.InformationprovidedintheKeepFillPressurizingLinesectionisnolongerapplicable.CondensateandReactorFeedwater Systemsinformationisobsolete.

11.8.3.9 DeleteSection11.8.3.9,CondensateandFeedwaterSystemCondensateMakeupandRejectSystems.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheCondensateMakeupandRejectSystemsarenolongerrequired.InformationprovidedintheCondensateMakeupandRejectSystemssectionisnolongerapplicable.

CondensateandReactorFeedwaterSystemsinformationisobsolete.

CondensateandFeedwaterSystem MinimumFlowBypasses KeepFillPressurizingLine CondensateMakeupandReject Systems CondensateDemineralizerSystem SteamJetAirEjector(SJAE)

Intercondensers SteamPackingExhauster FeedwaterControlStation Page107of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.Thefunctionsandinformation providedbytheCondensateandFeedwaterPipingarenolongerrequired.InformationprovidedintheCondensateandFeedwaterPipingsectionisnolongerapplicable.Condensateand ReactorFeedwaterSystemsinformationisobsolete.

11.8.4 DeleteSection11.8.4,CondensateandReactorFeedwaterSystems,PowerGenerationObjective.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.InspectionandTestingofthe CondensateandReactorFeedwaterSystemsisnolongerrequired.InformationprovidedintheCondensateandReactorFeedwaterSystemsInspectionandTestingsectionisnolonger applicable.CondensateandReactorFeedwaterSystemsinformationisobsolete.

Figure11.81 DeleteFigure11.81,CondensateFeedwaterandGasRemovalSystems.

TheCondensateandReactorFeedwaterSystemsprovideddemineralizedwatertothereactorvesselataratesufficienttomaintainadequatereactorvesselwaterlevel.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedandCondensateandFeedwatersystemsarenotrequired.TheCondensateandReactor FeedwaterSystemsPowerGenerationObjectiveisnolongerapplicable.InformationprovidedonFigure11.81isnolongerapplicable.CondensateandReactorFeedwaterSystemsinformation isobsolete.

11.9 TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.Thecoolingtowerstransferredheatfromthecirculatingwater totheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.

11.9.1 DeleteSection11.9.1,StationCoolingTowerWaterSystem,PowerGenerationObjective.

TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.Thecoolingtowerstransferredheatfromthecirculatingwater totheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStation CoolingTowerWaterSystemisnolongerrequired.TheStationCoolingTowerWaterSystemPowerGenerationObjectiveisnolongerapplicable.StationCoolingTowerWaterSystem informationisobsolete.

11.9.2 DeleteSection11.9.2,StationCoolingTowerWaterSystem,PowerGenerationDesignBases.

TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.Thecoolingtowerstransferredheatfromthecirculatingwater totheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStation CoolingTowerWaterSystemisnolongerrequired.TheStationCoolingTowerWaterSystemPowerGenerationDesignBasesarenolongerapplicable.StationCoolingTowerWaterSystem informationisobsolete.

11.9.3 DeleteSection11.9.3,StationCoolingTowerWaterSystemDescription.

TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.Thecoolingtowerstransferredheatfromthecirculatingwater totheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStation CoolingTowerWaterSystemisnolongerrequired.InformationprovidedintheStationCoolingTowerWaterSystemdescriptionsectionisnolongerapplicable.StationCoolingTowerWater Systeminformationisobsolete.

11.9.4 DeleteSection11.9.4,StationCoolingTowerWaterSystemInspectionandTesting.

TheStationCoolingTowerWaterSystemprovidedanalternatemeansofcoolingheatedcondensercirculatingwaterdischarge.Thecoolingtowerstransferredheatfromthecirculatingwater totheatmosphereandreturnthecooledcirculatingwatertotheriverorrecirculateditthroughtheCirculatingWaterSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Therefore,nuclearsteamcannotbeproducedand,asaresult,CirculatingWaterSystemsarenotrequired.Consequently,theStation CoolingTowerWaterSystemisnolongerrequired.InspectionandtestingoftheStationCoolingTowerWaterSystemisnolongerrequired.StationCoolingTowerWaterSysteminformationis obsolete.

CondensateandFeedwaterPiping InspectionandTesting G191157,Sh1CondensateFeedwaterandGas RemovalSystems STATIONCOOLINGTOWERWATERSYSTEM PowerGenerationObjective PowerGenerationDesignBases Description InspectionandTesting Page108of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.0 3.2 12.1 Modifysection12.1,StationStructures,SummaryDescription,todeletereferencetoprimarycontainment.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorized toemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasis accidentsarenolongerpossible.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,steamtunnel pressurizationduetosteamleaknolongerpossible,damperfunctionnolongerrequired.

3.1.3 12.2.1.1 Section12.2.1.1,SeismicClassification,deletereferencetoamainsteamlinebreakoutsidethedrywell.Followingcertificationofpermanentdefueling,amainsteamlinebreakoutsidethe drywellisnotpossible.

3.1.3.1 12.2.1.1.1 ClassIStructures Section12.2.1.1.1,ClassIStructures,DeleteAlternatecoolingcellandcoolingtowercellfromlistofclassIstructures.Thefunctionsprovidedbythosestructuresarenolongerrequired followingpermanentdefueling,thosestructuresnolongermeetthedefinitionofclassIstructures,therefore,thereisnorequirementtomaintainthosestructuresasClassI.

3.1.3.1.1 12.2.1.1.2 ClassIEquipment Section12.2.1.1.2,ClassIEquipment,DeletethebelowlistedequipmentfromtheclassIequipmentlist.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctions providedbythebelowsystemsarenolongerrequiredandthatequipmentnolongermeetsthedefinitionofclassIequipment.

• 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,primary containmentisolationsystems,controlrodpositionindicationsystems,reactorprotectionsystems,nuclearinstrumentationsystems

• CondensateStorageTankandCondensateTransferSystem(linestiedtoEngineeringSafetySystems) 3.1.3.1.2 12.2.1.1.3 ClassIIStructures Section12.2.1.1.3,ClassIIStructures,DeletethebelowlistedstructuresfromtheclassIIstructurelist.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctions providedbythebelowstructuresarenolongerrequiredandthatequipmentnolongermeetsthedefinitionofclassIIstructures.

• AOGBuilding

• Coolingtower 3.1.3.1.3 FacilityStructures PRINCIPALSTATIONSTRUCTURESANDFOUNDATIONS LoadingConsiderationsforStructures, Foundations,EquipmentandSystems SeismicClassification

SUMMARY

DESCRIPTION StationStructures SeismicClassification LoadingConsiderationsforStructures,Foundations,Equipment andSystems ClassIIStructures

SUMMARY

DESCRIPTION ClassIEquipment ClassIStructures Page109of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.2.1.1.4 ClassIIEquipment Section12.2.1.1.4,ClassIIEquipment,DeletethebelowlistedequipmentfromtheclassIIequipmentlist.Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedto emplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctions providedbythebelowsystemsarenolongerrequiredandthatequipmentnolongermeetsthedefinitionofclassIIequipment.

• AdvancedOffGasSystem

• TurbineGeneratorSystem

• MainCondenserSystem

• ReactorFeedwaterandCondensateSystems

• ReactorCleanUpDemineralizerSystem

• TurbineSystemMoistureSeparators

• CondensateDemineralizerSystem

• SteamSeparatorsandDriers 3.1.3.1.4 12.2.1.2 3.1.3.2 12.2.1.2.1 ClassIStructures Modifysection12.2.1.2.1todeletereferencetothealternatecoolingcell.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythealternatecoolingcellarenolongerrequired.Informationregardingthealternatecoolingcellis obsoleteandmaybedeleted.

3.1.3.2.1 12.2.1.2.2 ClassIIStructures Nochanges 3.1.3.2.2 12.2.1.2.3 EquipmentSeismic Design Section12.2.1.2.3,EquipmentSeismicDesign,deletethestatementregardingsnubberoperabilityforthereactorcoolantandothersafetyrelatedsystems.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbytheReactorCoolantsystemarenolongerrequiredandassuranceofstructuralintegrityofthe Reactorcoolantsystemduringanearthquakeisnotrequired.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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccur.Consequentlythefunctionsprovidedbytheprimaryreactorsystem,primarycontainment,reactorauxiliaryandcoolingsystemsand reactorwellpoolarenolongerrequired.Followingcertificationofpermanentdefueling,thereactorbuildingfunctionsonlytohouseandsupportthespentfuelpool 3.2.1.1 12.2.2.2 Section12.2.2.2,Description,

• addthewordstructurefollowingprimarycontainmenttoreflectthefactthatfollowingpermanentdefuelingthereisnoprimarycontainmentfunction,onlytheconcretestructure.

• Deletereferencetothesystemandsupportfacilitiesforthereactor,includingReactorWaterCleanup,SupplementalCoolingSystems,ReactorControlRodDriveHydraulicSystems,aswella refuelingfunctions.ThefunctionsprovidedbythoseSSCsarenotrequiredfollowingpermanentdefueling.

Section12.2.2.2,Description:

• Deleteallreferencetocorrosionofthelowerpartofthesteeldrywellliner.Followingpermanentdefueling,thefunctionprovidedbythesteellinerisnolongerrequired.Therefore, corrosionofthesteellinerisnotaconcern.

Section12.2.2.2,Description:

• DeletereferencetoHELBinthereactorbuilding.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW 10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequentlyahighenergylinebreakisnolongerpossibleinthereactorbuilding.

3.2.1.2 12.2.2.3 NoChanges 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 toPADandLBDCRforDSARRev0(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.Followingcertificationofpermanentdefuelingthelicenseeisnolonger authorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,power generationwillnolongeroccur.

Section12.2.3.2,TurbineBuildingDescription:

• DeleteportionofturbinebuildingdescriptionstatingthatblowoutpanelsventtheTBduringcertainhighenergylinebreaks..Followingcertificationofpermanentdefuelingthelicenseeis nolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore, highenergylinebreaksintheturbinebuildingcannolongeroccur.

3.2.2.2 12.2.3.3 NoChanges 3.2.2.3 12.2.4 3.2.3 12.2.4.1 Section12.2.4.1,PlantStackDescription:

• Grammaticalchangesonly.

3.2.3.1 12.2.4.2 NoChanges 3.2.3.2 12.2.5 3.2.4 12.2.5.1 Section12.2.5.1,ControlRoomBuilding,Description:

• Removedreferencetostationoperation,sincestationoperationwillnotoccurfollowingcertificationofpermanentdefueling.

3.2.4.1 12.2.5.2 NoChanges 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,thefunctionsprovidedbythe circulatingwatersystemarenolongerrequiredandareobsolete.Theintakeanddischargeaeratingstructuresareaddressedinsubsequentsectionsandarenotrequiredinthissection.

12.2.6.2 3.2.5.1 12.2.6.2.1 Description 12.2.6.2.1,IntakeStructure,Description.

• Sectionrewordedtoremoveexcessdetail

• Deletedreferencestothefunctionsprovidedbythecirculatingwatersystem.Followingcertificationofpermanentdefuelingpoweroperationscannolongeroccur.Consequently,the functionsprovidedbythecirculatingwatersystemarenolongerrequiredandmaybedeleted.CirculatingWaterSysteminformationisobsolete.

3.2.5.1.1 12.2.6.2.2 SeismicAnalysis NoChanges 3.2.5.1.2 12.2.6.3 Section12.2.6.3,DischargeandAeratingStructure.

• Sectionrewordedtoremoveexcessdetail.

• Deletedreferencetothefunctionsprovidedbythecirculatingwatersystem

• Deletedreferencetothepumpslocatedinthedischargestructurewhichsupplywatertothecoolingtowers.Followingcertificationofpermanentdefuelingthelicenseeisnolonger authorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,the functionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.

3.2.5.2 12.2.6.4 12.2.6.4.1 Description Section12.2.6.4.1,CoolingTowerRecirculationWaterSystem,Description.

Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelatedinformationis obsoleteandmaybedeleted.

12.2.6.4.2 SeismicAnalysis Section12.2.6.4.2,CoolingTowerRecirculationWaterSystem,SeismicAnalysis.

Deletethissection.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolonger possibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Sincethefunctionsprovidedbythe coolingtowersarenolongerrequired,aseismicanalysisofthecoolingtowersisalsonotrequired.Coolingtowerrelatedinformationisobsoleteandmaybedeleted.

Function Description SeismicAnalysis Description SeismicAnalysis Description SeismicAnalysis IntakeStructure DischargeandAeratingStructure Description SeismicAnalysis PlantStack ControlRoomBuilding CirculatingWaterIntakeandDischargeStructures Function Description SeismicAnalysis CirculatingWaterIntakeandDischarge Structures General IntakeStructure DischargeandAeratingStructure CoolingTowerRecirculatingWater System PlantStack Description SeismicAnalysis ControlRoomBuilding Description SeismicAnalysis Page111of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,themakeupfunctionoftheDeepBasinisnolongerrequired.

3.2.6 12.2.7 NoChanges 3.2.7 12.2.7.1 NoChanges 3.2.7.1 12.2.7.2 NoChanges 3.2.7.2 12.2.8 NoChanges 3.1.4 3.2.8 Table12.2.1 NoChanges Table3.1.1 Table12.2.2 NoChanges Table3.1.2 Figure12.21 NoChanges Figure3.21 Figure12.22 NoChanges Figure3.21 Figure12.23 NoChanges Figure3.22 Figure12.24 NoChanges Figure3.22 Figure12.25 NoChanges Figure3.22 Figure12.26 NoChanges Figure3.22 Figure12.27 NoChanges Figure3.23 Figure12.28 NoChanges Figure3.23 Figure12.29 NoChanges Figure3.24 Figure12.2 10 NoChanges Figure3.25 Figure12.2 11 NoChanges Figure3.26 Figure12.2 12 NoChanges Figure3.27 Figure12.2 13 NoChanges Figure3.27 Figure12.2 14 NoChanges Figure3.28 Figure12.2 15 NoChanges Figure3.28 Figure12.2 16 NoChanges Figure3.218 Drawingaddedsinceitisreferencedinthetextbody.

Figure3.29 Figure12.2 17 NoChanges Figure3.210 Figure12.2 18 NoChanges Figure3.211 Figure12.2 19 NoChanges Figure3.211 G191147TurbineBuildingSectionDD MainStackGeometry G191146TurbineBuildingSectionBB G191147TurbineBuildingSectionCC G191592ControlRoomBuildingPlanView(Typical)

G191595ControlRoomElevation(EasternWall)

G191595ControlRoomBuildingElevation(WestWall)

CoolingTowerDeepBasin InterimSpentFuelStorageInstallation G191142PLOTPLAN References AllowableStressesforClassIStructures SafetyMarginsforSeveralCriticalPortionsofMajorClassI Structures G191148ReactorBuildingPlanEL.213'9 G191148ReactorBuildingPlanEL.252'6 G191149ReactorBuildingPlanEL.280' G191149ReactorBuildingPlanEL.303' G191149ReactorBuildingPlanEL.318'8 G191149ReactorBuildingPlanEL.345'2 G191150ReactorBuildingSectionAA G191150ReactorBuildingSectionBB G191143TurbineBuildingBasementPlan G191144TurbineBuildingGroundFloorPlan G191145TurbineBuildingOperatingFloorPlan G191146TurbineBuildingSectionAA Description SeismicAnalysis InterimSpentFuelStorageInstallation Description SeismicAnalysis References AllowableStressesforClassIStructures SafetyMarginsforSeveralCriticalPortionsof MajorClassIStructures CoolingTowerDeepBasin G191146TurbineBuildingSectionBB G191147TurbineBuildingSectionCC G191147TurbineBuildingSectionDD MainStackGeometry G191592ControlRoomBuildingPlanView (Typical)

G191595ControlRoomElevation(EasternWall)

G191150ReactorBuildingSectionAA G191150ReactorBuildingSectionBB G191143TurbineBuildingBasementPlan G191144TurbineBuildingGroundFloorPlan G191145TurbineBuildingOperatingFloorPlan G191146TurbineBuildingSectionAA G191148ReactorBuildingPlanEL.213'9 G191148ReactorBuildingPlanEL.252'6 G191149ReactorBuildingPlanEL.280' G191149ReactorBuildingPlanEL.303' G191149ReactorBuildingPlanEL.318'8 G191149ReactorBuildingPlanEL.345'2 G191595ControlRoomBuildingElevation(West Wall)

Page112of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Figure12.2 20 NoChanges Figure3.211 Figure12.2 21 NoChanges Figure3.211 Figure12.2 22 NoChanges Figure3.212 Figure12.2 23 NoChanges Figure3.213 Figure12.2 24 NoChanges Figure3.214 Figure12.2 25 NoChanges Figure3.215 Figure12.2 26 NoChanges Figure3.216 Figure12.2 27 NoChanges Figure3.217 Figure12.2 28 DeleteFigure12.228.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythe circulatingwatersystemarenolongerrequiredandareobsolete.Theinformationshownonthisfigureisnolongerapplicableandisobsolete.

Figure12.2 29 DeleteFigure12.229.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythe circulatingwatersystemarenolongerrequiredandareobsolete.Theinformationshownonthisfigureisnolongerapplicableandisobsolete.

Figure12.2 30 DeleteFigure12.230.Thegeneraldescriptionofthecirculatingwatersystemisnotrequired..Followingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplace orretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Therefore,thefunctionsprovidedbythe circulatingwatersystemarenolongerrequiredandareobsolete.Theinformationshownonthisfigureisnolongerapplicableandisobsolete.

Figure12.2 31 DeleteFigure12.231.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelated informationisobsoleteandmaybedeleted.

Figure12.2 32 DeleteFigure12.232.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelated informationisobsoleteandmaybedeleted.

Figure12.2 33 DeleteFigure12.233.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelated informationisobsoleteandmaybedeleted.

Figure12.2 34 DeleteFigure12.234.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelated informationisobsoleteandmaybedeleted.

Figure12.2 35 DeleteFigure12.235.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelated informationisobsoleteandmaybedeleted.

Figure12.2 36 DeleteFigure12.236.FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisno longerpossibletoloadanuclearcore,poweroperationscannolongeroccur.Consequently,thefunctionsprovidedbythecoolingtowersarenolongerrequired.Coolingtowerrelated informationisobsoleteandmaybedeleted.

Figure12.2 37 NoChanges Figure3.11 Figure12.2 38 NoChanges Figure3.12 Figure12.2 39 DeleteFigure12.239.ThefigureisnotreferencedinUFSARSection12.2.ThisinformationisadequatelyaddressedintheISFSISAR.

Figure12.2 40 DeleteFigure12.240.ThefigureisnotreferencedinUFSARSection12.2.ThisinformationisadequatelyaddressedintheISFSISAR.

12.3 4.2 G191595ControlRoomBuildingElevation(NorthWall)

G191595ControlRoomBuildingElevation(SouthWall)

G191451IntakeStructureMasonry G191452IntakeStructureMasonry G191453IntakeStructureMasonry G191463DischargeStructureMasonry G191461,sh1DischargeStructureMasonry G200347AeratingStructureMasonryandReinforcing G191529ReactorBuildingReactorVesselPedestalMatM+R G191483ReactorBuildingFoundationMatPlanM+R G200353CoolingTowerNo.1BasinPlan CoolingTowerNo.1BasinElevationView G191463DischargeStructureMasonry G191461,sh1DischargeStructureMasonry G200347AeratingStructureMasonryand Reinforcing G200349CirculatingWaterSystemPartialPlan andProfile G191448CirculatingWaterSystemGeneralPlan andProfile G200350CirculatingWaterSystemCooling TowerPipingSectionsandDetails G191595ControlRoomBuildingElevation (NorthWall)

G191595ControlRoomBuildingElevation (SouthWall)

G191451IntakeStructureMasonry G191452IntakeStructureMasonry G191453IntakeStructureMasonry 59203324CoolingTowerTypicalPlan 59203326CoolingTowerTypicalSectionandFan DeckPlan G200357CoolingTowerNo.2BasinPlanView G200357CoolingTowerNo.2BasinElevation View G191529ReactorBuildingReactorVessel PedestalMatM+R G191483ReactorBuildingFoundationMatPlan M+R 592013400ISFSIConcreteStoragePad-LocationSitePlan 592013402ISFSIConcreteStoragePad-Plan, Sections,andDetails RADIATIONSHIELDING RadiationShielding Page113of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 12.3.1 ModifySection12.3.1,RadiationShielding,PowerGenerationObjective,todeletetheterm"PowerGeneration"fromthesectiontitle.Sincetheterm"PowerGeneration"isbasedinthe classificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

CombinedthepowergenerationobjectiveandsafetyobjectiveintoonesectionstatingtheobjectiveofRadiationShieldinginthepermanentlydefueledstate.

4.2.1 12.3.2 DeleteSection12.3.2,RadiationShielding,SafetyObjective.Sincetheterm"Safety"isbasedintheclassificationprocessdescribedinsection1.4.1whichisnolongerused,thetermisno longerrequiredandisnotapplicabletoapermanentlydefueledstation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,thesafetyobjectionofradiation 12.3.3 DeleteSection12.3.3,RadiationShielding,PowerGenerationDesignBasis.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelated 12.3.4 ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletetheterm"Safety"fromthesectiontitle.Sincetheterm"Safety"isbasedintheclassificationprocessdescribedin UFSARsection1.4.1whichisnolongerused,thetermisnolongerrequiredandisnotapplicabletoapermanentlydefueledstation.

ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingoftypicalareas.Thisinformationisexcessivedetailwhichisnotrequiredandisnolongerapplicableinthe defueledstate.

ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingoftypicalareaswithinthecontrolledboundaryareas.Thisinformationisexcessivedetailwhichisnotrequire andmaynolongerbeapplicable.

ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingoftypicalzoneIVareaswithinthecontrolledboundaryareas.Thisinformationisexcessivedetailwhichisnot requiredandmaynolongerbeapplicable.

ModifySection12.3.4,RadiationShielding,SafetyDesignBasis,todeletelistingofareaswhichwillbeequippedwithlocalmonitoringdevices.Thisinformationisexcessivedetailwhichisnot requiredandmaynolongerbeapplicable.

Deleteinternalreferencetosection7.Internalreferencenotrequired.

4.2.2 12.3.5 4.2.3 12.3.5.1 ModifySection12.3.5.1,materialsdescriptiontoremovereferencetotheshieldingsafetydesignbasis.Informationisnolongerapplicable.

4.2.3.1 12.3.5.2 ModifySection12.3.5.2,ReactorBuilding,toremovethediscussionregardingsacrificialshieldingprovidedinthedrywell.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationregardingthefunctionsprovidedbythe sacrificialshieldingdescribedinthisparagraphisnolongerapplicableandisobsolete.

ModifySection12.3.5.2,ReactorBuilding,toremovethediscussionregardingsacrificialshieldingprovidedinthedrywell.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationregardingthefunctionsprovidedbythe sacrificialshieldingdescribedinthisparagraphisnolongerapplicableandisobsolete.

ModifySection12.3.5.2,ReactorBuilding,toremovethediscussionregardingbiologicalshieldprovidedinthedrywell.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationregardingthefunctionsprovidedbythe biologicalshielddescribedinthisparagraphisnolongerapplicableandisobsolete.

4.2.3.2 12.3.5.3 DeleteSection12.3.5.3,RadiationShielding,TurbineBuilding.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,generationofNitrogen16gammaradiationisnotaconcern anddoesnotcontributetotheneedforshieldingintheturbinebuilding.Therefore,theareaslisteddonotrequireshieldingastheresultofpoweroperations.Residualradiationastheresult ofremainingradioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.

12.3.5.4 ModifySection12.3.5.4,MainControlRoomandTechnicalSupportCenter(TSC)toremovethestatementregardingadditionalshieldingtothefloorabovetheTSCtolimitdirectgammadose topersonnelintheTSCduringadesignbasisLOCA.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,adesignbasisLOCAisnolongerpossibleandreferencetotheDBA LOCAmaybedeleted.

ModifySection12.3.5.4,MainControlRoomandTechnicalSupportCenter(TSC)toremovethestatementregardingTEDEduringthe30daysfollowingadesignbasisaccident.Following permanentdefuelingadesignbasisaccidentisnolongerpossible.

ModifySection12.3.5.4todeletereferencetooperationat100%powersinceVYhasceasedpoweroperations.

4.2.3.3 12.3.5.5 DeleteSection12.3.5.5,RadiationShielding,ResidualHeatRemovalSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsprovidedbytheResidualHeatRemovalSystemarenolongerrequired,thesystemwillnotbeplacedinoperation.Residualradiationastheresultofremaining radioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.

TurbineBuilding MainControlRoomandTechnical SupportCenter(TSC)

ResidualHeatRemovalSystem SafetyObjective PowerGenerationDesignBasis SafetyDesignBasis Description MaterialsDescription ReactorBuilding PowerGenerationObjective Objective DesignBasis Description MaterialsDescription ReactorBuilding MainControlRoomandTechnicalSupportCenter (TSC)

Page114of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsprovidedbytheDemineralizerSystemarenolongerrequired,thesystemwillnotbeplacedinoperation.Residualradiationastheresultofremainingradioactive materialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.

12.3.5.7 DeleteSection12.3.5.5,RadiationShielding,AdvancedOffGasSystem.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thefunctionsprovidedbytheAdvancedOffGasSystemarenolongerrequired,thesystemwillnotbeplacedinoperation.Residualradiationastheresultofremaining radioactivematerialwillbeshieldedonacasebasisasrequiredforpersonnelprotection.

12.3.6 DeleteSection12.3.6,RadiationShielding,InspectionandTesting.

Thissectionprovideshistoricalinformationregardingshieldinginspectionsconductedduringtheconstructionphase.Thisinformationishistoricalandmaybedeleted.Additionally,thissection commitstoradiationsurveysconducteduponinitiationofreactoroperation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thereactoroperationswillnotbeconducted.Theinformationprovidedregardingradiationsurveysconductedduringpoweroperationsisnolongerapplicable,andisobsolete.

12.3.7 ModifySection12.3.7,RadiationShielding,SurveillanceandTesting,todeletereferencetonormalstationoperationsandresponseofsafeguardscomponentstoaccidentormechanicalfailure.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Therefore,normalstationoperationsarenolongerpossible,andsafeguardcomponentswillnolongerbeoperated.

4.2.4 12.3.8 DeleteSection12.3.8,References.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

Consequently,thereferenceslistedinsection12.3.8arenolongerapplicableandareobsolete Table12.3.1 Deletetable12.3.1,thisinformationduplicatesandismoreappropriatelycontainedinfacilityprocedures Table12.3.2 DeleteTable12.3.2Designandexpectedradiationlevelsinvariousbuildings.Radiationlevelsprovidedontable12.3.2whichareboundingforoperationat100%powerarenolongeraccurate orapplicablesinceVYhasceasedpoweroperations.

13.0 ConductofOperations 5

13.1 Deletedsection13.1,ConductofOperations,SummaryDescription,todeletethehistoryofownershipoftheVYNPS.Thisinformationisnotrequiredinthissectionandisredundanttosection 1.1 Deletedsection13.1,ConductofOperations,SummaryDescription,ThereportingrelationshipbetweentheplantmanagerandtheSiteVPisredundanttoTechnicalSpecifications DeleteSection13.1.ThediscussiononproceduresisredundanttoTechnicalSpecificationsSection6.4 Deletedreferencetothepreoperational,startupandpowertestprograms,nolongerapplicablefollowingpermanentdefueling.

DeletedreferencetoEmergencyOperatingProcedures;nolongerrequiredfollowingpermanentdefueling.

Theremaininginformationinthissectioniseitherobsoleteorredundanttootherchapter13sections.

13.1.1 DeletedSection13.1.1References.Onlyreferencenolongercitedinbodyoftext.

13.2 ModifiedSection13.2,ConductofOperations,OrganizationandResponsibility,toremovereferenceto"operating"organizationandstaffsincethestationwillnolongerbeoperatingfollowing certificationofpermanentdefueling.

ModifiedtheQAprogrammanualtoinclude"VermontYankee"inthetitletoreflectQAprogrammanualseparationfromcorporate.

5.1 13.3 5.2 13.3.1 ModifiedSection13.3.1,TrainingProgramDescription,Generaltoreflectthestationchangefromoperationtothesafestorageandhandlingofirradiatedfuelfollowingcertificationo permanentdefueling,DeletedreferencetoINPO,sinceVYisnolongerassociatedwiththenationalacademyfornucleartrainingand.assuch.INPOdoesnotaccredittrainingprogramsfornon operatingnuclearsites.

5.2.1 13.3.2 Nochanges 5.2.2 13.3.2.1 Nochanges 5.2.2.1 13.3.3 Modifysection13.3.3,ConductofOperations,FireBrigadeTrainingtoremovereferencetoAppendixR,sinceappendixRdoesnotapplytopermanentlydefueledstations.

5.2.3 13.3.4 ModifySection13.3.4,ConductofOperations,OperationsTraining,toremovereferenetooperationspositionswhichdonotexistfollowingpermanentdefueling,deletereerencetothe NationalAcademyforNuclearTraining,anddeletereferencetotheVYplantspecificsimulator,sincethesimulatorhasbeenremovedfromservice.

5.2.4 DemineralizerSystem AdvancedOffGasSystem InspectionandTesting ProgramDescription(General)

SurveillanceandTesting ConductofOperations ORGANIZATIONANDRESPONSIBILITY TRAINING ProgramDescription(General)

GeneralEmployeeTraining AccesstoPlant References ORGANIZATIONANDRESPONSIBILITY TRAINING SurveillanceandTesting References GeneralOccupancyRequirementsand CorrespondingRadiationLevels ShieldingDescriptionatVariousAreas

SUMMARY

DESCRIPTIONS GeneralEmployeeTraining FireBrigadeTraining OperationsTraining AccesstoPlant FireBrigadeTraining OperationsTraining Page115of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 13.3.5 Modifysection13.3.5,Craft,TechnicianandTechnicalStaffTraining,toremovereferencetoprogramaccreditationbythenationalacademyfornucleartraining,sincetheINPOdoesnotoffer accreditationfornonoperatingnuclearsitestrainingprograms.

5.2.5 13.3.6 Deletesection13.3.6,ConductofOperations,PlantCertificationProgram.Since,followingcertificationofpermanentdefueling,thelicenseeisnolongerauthorizedtoemplaceorretainfuelin thereactorvessel,poweroperationscannolongeroccur.SincethePlantCertificationProgramprovidedselectedstaffwithadvancedknowledgeofplantoperation,theprogranisnolonger applicable.

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,toreflectorganizationalandresponsibilitychangespos defueling.Deletedreferencestotrainingprogramsnolongerapplicable,includedapplicableresponsibilitiesformerlytheroleoftheSuperintendent,NuclearTraining,sincethosepositions werecombinedaspartofthepostdefuelingorganization.

5.2.8.1 13.3.9.2 DeleteSecyion13.3.9.2,Responsibility,SuperintendentNuclearTraining.TheapplicableresponsibilitiesoftheSuperintendent,NuclearTrainingweretransitionedtotheSuperintendent Trainingposition,andtheSuperintendentNuclearTrainingpostionwaseliminated.

13.4 4.4 13.4.1 Nochange 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 4.4.1.3 13.4.1.4 Nochange 4.4.1.4 13.4.1.5 Nochange 4.4.1.5 13.4.1.6 Nochange 4.4.1.6 13.4.1.7 Nochange 4.4.1.7 13.4.2 Nochange 4.4.2 13.4.2.1 Nochange 4.4.2.1 13.4.2.2 Nochange 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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram GeneralObjectivessectionisnolongerapplicable.

13.5.2 DeleteSection13.5.2StartupandPowerTestProgram,InitialFuelLoadingandTestsatAtmosphericPressure.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram, InitialFuelLoadingandTestsatAtmosphericPressuresectionisnolongerapplicable.

13.5.3 DeleteSection13.5.3,StartupandPowerTestProgram,InitialCoreHeatupfromAmbienttoRatedTemperatureandPressure.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTestProgram, InitialCoreHeatupfromAmbienttoRatedTemperatureandPressuresectionisnolongerapplicable.

13.5.4 DeleteSection13.5.4,StartupandPowerTestProgram,InitialCoreTestsFromRatedTemperatureto100%Power.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTest Program,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 InitialFuelLoadingandTestsatAtmospheric Pressure InitialCoreHeatupfromAmbienttoRated TemperatureandPressure InitialCoreTestsFromRatedTemperatureto 100%Power FacilitiesandEquipment PersonnelandProcedures RequiredMaterials FacilitiesandEquipment PersonnelandProcedures RequiredMaterials Page116of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 13.5.5 DeleteSection13.5.5,StartupandPowerTestProgram,ReloadCoreStartupTesting.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,theinformationprovidedintheStartupandPowerTest Program,ReloadCoreStartupTestingsectionisnolongerapplicable.

13.6 NoChanges 5.3 13.7 DeleteSection13.7.TheinformationcontainedinthissectionisredundanttotheinformationcontainedintheVYQAPM.SincetheUFSAR/DSARcommittoimplementationoftheVYQAPM, thereisnoneedtorepeatthatinformationintheUFSAR/DSAR.

13.7.1 Deletethissection,See13.7above 13.7.2 Deletethissection,See13.7above 13.7.3 Deletethissection,See13.7above 13.7.4 Deletethissection,See13.7above 13.8 5.5 13.8.1 NoChange 5.5.1 13.8.2 NoChange 5.5.2 13.8.3 NoChange 5.5.3 13.9 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.The informationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.

13.9.1 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.The informationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.

13.9.2 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.The informationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.

13.9.3 DeleteSection13.9,RefuelingOperations.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Therefore,refuelingoperationswillnolongerbeconducted.The informationprovidedintherefuelingoperationssectionisnolongerapplicableandisobsolete.

13.10 DiscussionmodifiedtoreflectchangestoTSandtheTRMastheresultofcertificationofpermanentdefueling.

Deletedthewords:

TheTRMisincorporatedbyreferenceintotheDSAR,ismaintainedinaccordancewithVermontYankeeadministrativeprocesses.

SincethereisnoregulatoryrequirementtomaintainaTRMatthesite,ortosubmitTRMchangestotheNRConaperiodicbasis,theTRMisnotrequiredtobeincorporatedbyreferenceinto theDSAR.

5.6 14.0 StationSafetyAnalysis 6.0 14.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.1.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.4.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

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 SAFETYDESIGNLIMITSFORABNORMALOPERATIONAL TRANSIENTS SAFETYDESIGNLIMITSFORACCIDENTS Page117of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.4.4.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.4.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.4.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.1.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.1.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.1.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.2.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.2.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.2.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.3.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.3.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.3.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.3.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.4.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.4.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.4.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.4.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.5.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.5.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.5.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.5.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.6 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.6.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.6.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.7 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.7.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.8 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

NuclearSystemProcessBarrier Damage ContainmentDamage References ANALYSISOFABNORMALOPERATIONALTRANSIENTS EventsResultinginaNuclearSystemPressure Increase GeneratorTrip(TurbineControl ValveFastClosure)

TripofOneRecirculationPump TripofTwoRecirculationPumps RecirculationPumpSeizure EventsResultinginaCoreCoolantFlowIncrease RecirculationFlowControllerFailure IncreasingFlow StartupofIdleRecirculationPump LossofAuxiliaryPower EventsResultinginaCoreCoolantFlowDecrease RecirculationFlowControlFailure DecreasingFlow EventsResultinginaPositiveReactivityInsertion ContinuousRodWithdrawalDuring PowerRangeOperation ContinuousRodWithdrawalDuring ReactorStartup ControlRodRemovalErrorDuring Refueling FuelAssemblyInsertionErrorDuring Refueling EventsResultinginaReactorVesselCoolant InventoryDecrease TurbineTrip(TurbineStopValve Closure)

MainSteamLineIsolationValve Closure EventsResultinginaReactorVesselWater TemperatureDecrease LossofaFeedwaterHeater ShutdownCooling(RHRS)

MalfunctionDecreasing InadvertentPumpStart PressureRegulatorFailure InadvertentOpeningofaSafety ReliefValveorSafetyValve LossofFeedwaterFlow EventResultinginaCoreCoolantTemperature Increase LossofRHRServiceWaterFlow EventResultinginExcessofCoolantInventory Page118of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.5.8.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.9 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.9.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.9.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.9.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.9.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.9.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.5.10 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.2.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.2.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.2.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.2.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.2.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.3.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.3.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.3.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.3.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.3.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.4.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.4.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.4.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.4.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.4.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.5.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.5.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.5.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.6.6 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

EvaluationAchievementofHot ShutdownCondition EvaluationAchievementoftheCold ShutdownCondition References 14.6 ANALYSISOFDESIGNBASISACCIDENTS FeedwaterControllerFailure MaximumDemand LossofHabitabilityoftheMainControlRoom CriteriaforLossofHabitabilityofthe ControlRoom Conditions Assumptions RadiologicalConsequences RefuelingAccident IdentificationofCauses Methods,Assumptions,and Conditions ResultsandConsequences FissionProductReleasetoEnvirons ResultsandConsequences LossofCoolantAccident(LOCA)

PeakContainmentPressure (Reference52)

LongTermPrimaryContainment

Response

OverPressureRequiredforCSand RHRPumpNPSH MetalWaterReactionEffectsonthe PrimaryContainment Introduction ControlRodDropAccident IdentificationofCauses StartingConditionsandAssumptions AccidentDescription MethodofAnalysis RadiologicalEffects MainSteamLineBreakAccident NuclearSystemTransientEffects Deleted RadiologicalEffects References Page119of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.7 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.8.6 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.1 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.4 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.5 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.6 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.1.7 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.2 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.9.3 Deleted,SeeFCR27006andFCR27020forjustificationandexplanationofchanges.

14.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.1 14.2 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.2 14.2.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.2.1 14.2.2 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.2.2 14.3 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3 14.3.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1 14.3.1.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.1 14.3.1.2 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.2 Introduction AcceptanceCriteria DBAAcceptanceCriteria SiteEventAcceptanceCriteria AccidentsEvaluated FuelHandlingAccident AnalyticalMethodology AssemblyDropinSFPwithOpen ContainmentScenario AnalyticalMethodsforEvaluatingRadiological Effects References RADIOLOGICALCONSEQUENCESFORNONDESIGNBASIS ACCIDENTSWITHATID-14844SOURCETERM EvaluationofStationSystemsUsingTID14844 SourceTerm SourceTermAssumptions StandbyGasTreatmentSystem CONCLUSIONS ANALYTICALMETHODS NuclearExcursionAnalysis ReactorVesselDepressurizationAnalysis ReactorHeatupAnalysis ContainmentResponseAnalysis References ECCSComponents ElectricalPenetrations ControlRoomHabitabilityPerformed inResponsetoNUREG0737 MaterialsWithintheContainment Conclusion RadiologicalConsequencesofAccidentswitha TID1488SourceTerm Introduction AcceptanceCriteria DBAAcceptanceCriteria SiteEventAcceptanceCriteria AccidentsEvaluated FuelHandlingAccident AnalyticalMethodology AssemblyDropinSFPwithOpenContainment Scenario Page120of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 14.3.1.3 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.3 14.3.1.4 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.4 14.3.1.5 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.5 14.3.1.6 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.6 14.3.1.7 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.7 14.3.1.8 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.8 14.3.1.9 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.3.1.9 14.4 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.4 14.4.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.4.1 14.4.1.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.4.1.1 14.4.1.2 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.4.1.2 14.4.1.3 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.4.1.3 14.4.1.4 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

6.4.1.4 14.5 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.Reference9changedfromNUMARC9301toNUMARC9106,GuidelinesforIndustryActionstoAssessShutdownManagement,intheReferences Section.9106isthecorrectreferenceandagreeswiththetextbody.

6.5 14.6 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Section6.6-AppendixA,Methodology-Step2,deletedthesentence:

"Giventhecomplexitiesofthefuelbundlesystemanditsresponseimpactevent,itisnotpossibletojudgethelevelofconservatisminthissetofassumptions,however,thehighlevelsof conservatisminotherareasofthiscalculationshouldmorethatmakeupforanynonconservatismintroducedhere."

Thisstatementisanengineeringjudgementestimationofconservatismwhichisnotquantifiable.Thestatementisnotrequiredsinceadequateconservatismalreadyexistsinthecalculation.

Therefore,sincethestatementisnotquantifiabeandisnotrequired,ishasbeendeleted.

6.6 Table14.3.1 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.1 AssemblyDropinSFPwithClosed ContainmentScenario Software Assumptions Inputs ImpactofWaterDepthonIodine DecontaminationFactor FuelDamagefromAssemblyDrop ontoSFPFuelRacks RadiologicalConsequences/Results SiteEventsEvaluated HighIntegrityContainer(HIC)DropEv AnalyticalMethodology Assumptions Inputs RadiologicalConsequences/Results References Appendices AnalyticalMethodology Assumptions Inputs RadiologicalConsequences/Results FHAScenariosAnalyzed References Appendices FHAScenariosAnalyzed AssemblyDropinSFPwithClosedContainment Scenario Software Assumptions Inputs ImpactofWaterDepthonIodineDecontamination Factor FuelDamagefromAssemblyDropontoSFPFuel Racks RadiologicalConsequences/Results SiteEventsEvaluated HighIntegrityContainer(HIC)DropEvent Page121of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table14.3.2 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.2 Table14.3.3 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.3 Table14.3.4 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.4 Table14.3.5 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.5 Table14.3.6 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.6 Table14.3.7 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Table6.3.7 Figure14.31 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Figure6.31 Figure14.32 SeeFCR27006andFCR27020forjustificationandexplanationofchanges.TheVYaccidentandtransientanalyseswerereplacedwithnewanalysesofaccidentsandeventswhichare applicableinthepermanentlydefueledstatewithirradiatedfuelstoredinthespentfuelpool.Thenewanalysisaddressafuelhandlingaccidentoverthespentfuelpoolandadropofahigh integrityradioactivematerialcontainer.

Figure6.32 15.0 AgingManagementProgram 7.0 15.1 Modifysection15.1,SupplementforRenewedOperatingLicense,todeletereferencetotheevaluationoftimelimitedaginganalysesfortheperiodofexendedoperation.

OnJanuary12,2015,EntergyNuclearOperations(ENO)certifiedtotheNuclearRegulatoryCommission(NRC)thatadeterminationtopermanentlyceaseoperationattheVermontYankee NuclearPowerStation(VYNPS)wasmadeonDecember29,2014whichwasthedateonwhichoperationceasedatVYNPS.ENOalsocertifiedthatthefuelhasbeenpermanentlyremovedfrom theVYNPSreactorvesselandplacedinthespentfuelpool.ENOacknowledgedthat,followingdocketing,theVYNPSlicensenolongerauthorizedoperationofthereactororemplacementor retentionoffuelintothereactorvessel.Consequently,theperiodofextendedoperationhasceasedandtheevaluationoftimelimitedaginganalysisisnolongerrequired.

7.1 15.2 OnJanuary12,2015,EntergyNuclearOperations(ENO)certifiedtotheNuclearRegulatoryCommission(NRC)thatadeterminationtopermanentlyceaseoperationattheVermontYankee NuclearPowerStation(VYNPS)wasmadeonDecember29,2014whichwasthedateonwhichoperationceasedatVYNPS.ENOalsocertifiedthatthefuelhasbeenpermanentlyremovedfrom theVYNPSreactorvesselandplacedinthespentfuelpool.ENOacknowledgedthat,followingdocketing,theVYNPSlicensenolongerauthorizedoperationofthereactororemplacementor retentionoffuelintothereactorvessel.

Cosequently,thefollowingchangesweremadetoSection15.2oftheVYNPSUFSAR:

1)EliminatediscussionsofLicenseRenewalagingmanagementprograms,analyses,andcommitmentsthatarenolongerrequiredtobemaintainedtosupportthecurrentconditionofthe plant; 2)Modifythescopesofprogramsandcommitmentstoreflectthepermanentlyshutdownanddefueledcondition;and 3)MakeadministrativechangesincludingtherenumberingandrestructuringoftheChapteranditssubsections.RefertoFCR27014.

SpecificchangestoSection15.2,AgingManagementProgramsandActivitiesinclude:

change"periodofextendedoperation"to"periodofwetfuelstorage",since,asdescribedinchangesummaryforsection15.1,theperiodofextendedoperationceasedfollowingcessation ofoperations.

Change"EntergyQualityAssuranceProgram"to"QualityAssuranceProgram"perFCR2713 7.2 15.2.1 NoChanges 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 UndecayedCoreInventoryforRadionuclides ImportantintheRadiologicalEvaluationofDBAs UndecayedGapActivityAvailableforRelease fromFuelAssemblyDropintheSFP TypicalIodineDecontaminationFactorsand IodineSpeciationvsWaterDepthaboveDropped Assembly AtmosphericDispersionFactorsforthe PostulatedFHA InputConditionsforFHA UndecayedCoreInventoryforRadionuclidesImportantinthe RadiologicalEvaluationofDBAs UndecayedGapActivityAvailableforReleasefromFuelAssembly DropintheSFP TypicalIodineDecontaminationFactorsandIodineSpeciationvs WaterDepthaboveDroppedAssembly AtmosphericDispersionFactorsforthePostulatedFHA EABTEDEDosevsLongDecayTime VYFHA-EABTEDEDosevsDecayTime VYFHA-MCRTEDEDosevsDecayTime Page122of153 toPADandLBDCRforDSARRev0(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.

15.2.9 NoChanges 7.2.2 15.2.10 DeleteSection15.2.10,EnvironmentalQualification(EQ)ofElectricComponentsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2Summaryo ChangesandFCR27010.

15.2.11 DeleteSection15.2.11,FatigueMonitoringProgram 15.2.12 NoChanges 7.2.3 15.2.13 NoChanges 7.2.4 15.2.14 DeleteSection15.2.14,FlowAcceleratedCorrosiongProgram,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.

15.2.18 NoChanges 7.2.5 15.2.19 ModifySection15.2.19,NonEQInaccessibleMediumVoltageCableProgram,toremoverequirementrelatedtofirsttestbeingperformedpriortotheperiodofextendedoperationwiththe exceptionofthe4.16kVcablesbetweentheUATsandBus1and2.

7.2.6 15.2.20 DeleteSection15.2.20,NonEQInstrumentationCircuitsTestReviewProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.

15.2.21 DeleteSection15.2.21,NonEQInsulatedCablesandConnectionsProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.

15.2.22 ModifySection15.2.22,OilAnalysisProgram,tochangetheword"plant"to"facility".

7.2.7 15.2.23 DeleteSection15.2.23,OnetimeInspectionProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2SummaryofChanges.

15.2.24 ModifySection15.2.24,PeriodicSurveillanceandPreventiveMaintenanceProgram,to changetheword"plant"to"facility".

removetheHPCIglandsealexhausterfanhousingandpiping,hydrogenanalyzerprecooler,housingsintheRHRcornerroom,EECS(stet)cornerroomrecirculationunitsandcirculating waterfromtheinspectionlist.

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:

deletereferencetoGL8913 change"periodofextendedoperation"to"periodofwetfuelstorage",since,asdescribedinchangesummaryforsection15.1,theperiodofextendedoperationceasedfollowingcessationo operations.

Inserttheword"opportunistic"todescribecomponentinspections Insertthewords"andnonsafetyrelated"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 NonEQInaccessibleMediumVoltageCableProgram OilAnalysisProgram PeriodicSurveillanceandPreventiveMaintenanceProgram BRWVesselIDAttachmentWeldsProgram BWRVesselInternalsProgram ContainmentLeakRateProgram DieselFuelMonitoringProgram InserviceInspectionContainmentInservice Inspection(CII)Program StructuresMonitoring-VernonDamFERC Program OilAnalysisProgram OneTimeInspectionProgram PeriodicSurveillanceandPreventive MaintenanceProgram ReactorHeadClosureStudsProgram ReactorVesselSurveillanceProgram SelectiveLeachingProgram InserviceInspection-InserviceInspection(ISI)

Program InstrumentAirQualityProgram NonEQInaccessibleMediumVoltageCable Program NonEQInstrumentationCircuitsTestReview Program NonEQInsulatedCablesandConnections Program EnvironmentalQualification(EQ)ofElectric ComponentsProgram FatigueMonitoringProgram FireProtectionProgram FireWaterSystemProgram FlowAcceleratedCorrosionProgram HeatExchangerMonitoringProgram ServiceWaterIntegrityProgram StructuresMonitoring-MasonryWallProgram StructuresMonitoring-StructuresMonitoring Program Page123of153 toPADandLBDCRforDSARRev0(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,programisnotrequiredfollowingcertificationofpermanent defueling.SeeSection15.2SummaryofChanges.

15.2.34 ModifySection15.2.34,WaterChemistryControl-AuxiliarySystemsProgram,to:

deletereferencetotheStatorCoolingWaterSystem changetheword"plant"to"facility".

deletereferencetotheOneTimeInspectionProgram,sincethatprogramhasbeendeleted.

7.2.13 15.2.35 ModifySection15.2.35,WaterChemistryControl-BWRProgram,to:

deletereferencetotheEPRIReport1008192BWRVIP130 insertreferencetoBWRWaterChemistryGuidlines,2008Revision,BWRVIP190 deletereferencetoprimarywaterchemistryandhydrogenwaterchemistry deletereferencetotheOneTimeInspectionProgram,sincethatprogramhasbeendeleted.

7.2.14 15.2.36 ModifySection15.2.36,WaterChemistryControl-ClosedCoolingProgram,to:

deletereferencetotheTBCCWsystem,AOGClosedCoolingWatersystem,andAOGRefrigerantskidwatersystem.

deletereferencetotheOneTimeInspectionProgram,sincethatprogramhasbeendeleted.

7.2.15 15.2.37 NoChanges 7.2.16 15.2.38 NoChanges 7.2.17 15.2.39 NoChanges 7.2.18 15.2.40 NoChanges 7.2.19 15.2.41 DeleteSection15.2.41,ProtectiveCoatingMonitoringandMaintenanceProgram,programisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.2Summaryof Changes.

15.3 Deletesection15.3,EvaluationofTimelLimitedAgingAnalyses.

OnJanuary12,2015,EntergyNuclearOperations(ENO)certifiedtotheNuclearRegulatoryCommission(NRC)thatadeterminationtopermanentlyceaseoperationattheVermontYankee NuclearPowerStation(VYNPS)wasmadeonDecember29,2014whichwasthedateonwhichoperationceasedatVYNPS.ENOalsocertifiedthatthefuelhasbeenpermanentlyremovedfrom theVYNPSreactorvesselandplacedinthespentfuelpool.ENOacknowledgedthat,followingdocketing,theVYNPSlicensenolongerauthorizedoperationofthereactororemplacementor retentionoffuelintothereactorvessel.Consequently,theperiodofextendedoperationhasceasedandtheevaluationoftimelimitedaginganalysisisnolongerrequired.

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,PressureTemperatureLimits,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.

15.3.1.3 Deletesection15.3.1.3,CharpyUpperShelfEnergy,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.SeeSection15.3Summaryof Changes.

15.3.1.6 Deletesection15.3.1.6,ReactorVesselAxialWeldFailureProbability 15.3.2 Deletesection15.3.2,MetalFatigue,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.

15.3.2.1 Deletesection15.3.2.1,Class1MetalFatigue,informationisnotrequiredfollowingcertificationofpermanentdefueling.SeeSection15.3SummaryofChanges.

15.3.2.2 Deletesection15.3.2.2,NonClass1MetalFatigue,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 NonClass1MetalFatigue EnvironmentalEffectsonFatigue EnvironmentalQualificationofElectrical Components FatigueofPrimaryContainment,AttachedPiping, andComponents CharpyUpperShelfEnergy AdjustedReferenceTemperature ReactorVesselCircumferentialWeld InspectionRelief ReactorVesselAxialWeldFailure Probability MetalFatigue Class1MetalFatigue SystemWalkdownProgram ThermalAgingandNeutronIrradiation EmbrittlementofCastAusteniticStainlessSteel (CASS)Program WaterChemistryControl-AuxiliarySystems Program WaterChemistryControl-BWRProgram NeutronAbsorberMonitoringProgram ProtectiveCoatingMonitoringandMaintenance Program EVALUATIONOFTIMELIMITEDAGINGANALYSES ReactorVesselNeutronEmbrittlement ReactorVesselFluence PressureTemperatureLimits WaterChemistryControl-ClosedCooling Program BoltingIntegrityProgram MetalEnclosedBusInspectionProgram BoltedCableConnectionsProgram Page124of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 15.3.5 Deletesection15.3.5,CorePlateRimHoldDownBoltLossofPreload,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 CommitmentEliminatedbyFCR27/014 7

CommitmentEliminatedbyFCR27/014 8

NoChanges 8

9 NoChanges 9

10 NoChanges 10 11 NoChanges 11 12 CommitmentEliminatedbyFCR27/014 13 NoChanges 13 14 CommitmentEliminatedbyFCR27/014 15 CommitmentEliminatedbyFCR27/014 EnhanceTheDieselFuelMonitoringProgramUTTankbottom every10yrs EnhanceFireWaterSystemProgamProcedurestospecifythata representativesampleofsprinklerswhichhavebeeninservicefor 50yearswillbetested.

LISTOFLICENSERENEWALCOMMITMENTS Guidanceforperformingexaminationsofburiedpiping CommitmentEliminatedbyFCR27/014 16 ImplementtheOneTimeInspectionProgram TheOneTimeInspectionProgramwasperformed;thus,thecommitmentwasmetandclosedbyFCR27/014.

Guidanceforperformingexaminationsofburied piping InspectFifteen(15)percentofthetopguide locations EnhanceTheDieselFuelMonitoringProgramUT Tankbottomevery10yrs EnhanceTheDieselFuelMonitoringProgram modifytankbottomacceptancecriteria ModifyFatigueMonitoringProgram Establishallowablenumberofeffective transients Enhanceprocedurestospecifythatfiredamper framesinfirebarrierswillbeinspectedfor corrosion Enhanceprocedurestostatethatthediesel enginesubsystems(includingthefuelsupply line)willbeobservedwhilethepumpisrunning EnhanceFireWaterSystemProgamProcedures tospecifythatarepresentativesampleof sprinklerswhichhavebeeninservicefor50years willbetested.

EnhancetheFireWaterSystemProgramto specifythatwallthicknessevaluationsoffire protectionpipingwillbeperformedonsystem componentsusingnonintrusivetechniquesto identifyevidenceoflossofmaterialdueto corrosion.

ImplementHeatExchangerMonitoringProgram ImplementtheNonEQInaccessibleMedium VoltageCableProgram ImplementtheNonEQInstrumentationCircuits TestReviewProgram ImplementtheNonEQInsulatedCablesand ConnectionsProgram LISTOFLICENSERENEWALCOMMITMENTS Usemanualcyclecountingtotrackandcompare accumulatedcycles Enhanceprocedurestostatethatthedieselenginesubsystems (includingthefuelsupplyline)willbeobservedwhilethepumpis running Enhanceprocedurestospecifythatfiredamperframesinfire barrierswillbeinspectedforcorrosion EnhanceTheDieselFuelMonitoringProgrammodifytankbottom acceptancecriteria EnhancetheFireWaterSystemProgramtospecifythatwall thicknessevaluationsoffireprotectionpipingwillbeperformed onsystemcomponentsusingnonintrusivetechniquestoidentify evidenceoflossofmaterialduetocorrosion.

ImplementtheNonEQInaccessibleMediumVoltageCable Program 15.5 Textmodifiedtoadd"commitmentsremainingapplicablefollowingpermanentcessationofoperationsandcertificationofpermanentdefueling.ModifySection15.4,References,toremove thosereferencesnolongercitedinthebodyofthetext.

15.4 CorePlateRimHoldDownBoltLossofPreload LowerPlenumFatigueAnalysis REFERENCES REFERENCES 6

Page125of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 17 NoChanges 17 18 CommitmentEliminatedbyFCR27/014 20 NoChanges 20 21 CommitmentEliminatedbyFCR27/014 22 NoChanges 22 23 CommitmentEliminatedbyFCR27/014 24 NoChanges 24 25 CommitmentEliminatedbyFCR27/014 26 NoChanges 26 EnhancethePeriodicSurveillanceandPreventiveMaintenance Programtoassurethattheeffectsofagingwillbemanaged EnhancetheStructuresMonitoringProgramtospecifythat processfacilitycranerailsandgirders,condensatestoragetank (CST)enclosure,CO2tankenclosure,nitrogentankenclosureand restrainingwall,CSTpipetrench,dieselgeneratorcabletrench, fueloilpumphouse,servicewaterpipetrench,manwayseals andgaskets,andhatchsealsandgasketsareincludedinthe program.

EnhanceGuidanceforperformingstructuralexaminationsof elastomerstoidentifycrackingandchangeinmaterialproperties intheStructuresMonitoringProgramprocedure Systemwalkdownguidancedocumentswillbeenhancedto performperiodicsystemengineerinspectionsofsystemsinscope andsubjecttoagingmanagementreview.

ProcedureswillbeenhancedtoflushtheJohnDeereDiesel Generatorcoolingwatersystemandreplacethecoolantand coolantconditionereverythreeyears.

TheSelectiveLeachingProgramwasperformed;thus,thecommitmentwasmetandclosedbyFCR27/014.

EnhancetheStructuresMonitoringProgramto specifythatprocessfacilitycranerailsand girders,condensatestoragetank(CST)enclosure, CO2tankenclosure,nitrogentankenclosureand restrainingwall,CSTpipetrench,dieselgenerator cabletrench,fueloilpumphouse,servicewater pipetrench,manwaysealsandgaskets,and hatchsealsandgasketsareincludedinthe program.

Addguidanceforperformingstructural examinationsofwoodtoidentifylossofmaterial, cracking,andchangeinmaterialpropertiestothe StructuresMonitoringProgram.

EnhanceGuidanceforperformingstructural examinationsofelastomerstoidentifycracking andchangeinmaterialpropertiesinthe StructuresMonitoringProgramprocedure AddGuidanceforperformingstructural examinationsofPVCcoolingtowerfilltoidentify crackingandchangeinmaterialpropertiestothe StructuresMonitoringProgramprocedure.

Systemwalkdownguidancedocumentswillbe enhancedtoperformperiodicsystemengineer inspectionsofsystemsinscopeandsubjectto agingmanagementreview.

ImplementtheThermalAgingandNeutron IrradiationEmbrittlementofCastAustenitic StainlessSteel(CASS)Program ProcedureswillbeenhancedtoflushtheJohn DeereDieselGeneratorcoolingwatersystemand replacethecoolantandcoolantconditionerevery threeyears.

19 ImplementtheSelectiveLeachingProgram EnhancethePeriodicSurveillanceandPreventive MaintenanceProgramtoassurethattheeffects ofagingwillbemanaged EnhancetheReactorVesselSurveillanceProgram toproceduralizethedataanalysis,acceptance criteria,andcorrectiveactionsdescribedinthe programdescription Page126of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 27 CommitmentEliminatedbyFCR27/014 28 NoChanges 28 29 Theplantspecificanalysistodeterminetheacceptancecriteriaforthecontinuedinspectionofcoreplateholddownboltingwasperformed.Thus,thecommitmentwasmetandclosedbyFCR 27/014.

30 NoChanges 30 31 NoChanges 31 32 NoChanges 32 33 NoChanges 33 34 NoChanges 34 35 NoChanges 35 36 CommitmentEliminatedbyFCR27/014 37 CommitmentSuperseded.PlaceholderdeletedbyFCR27/014.

ReviseprogramprocedurestoindicatethattheInstrumentAir Programwillmaintaininstrumentairqualityinaccordancewith ISAS7.3 ReviseSystemWalkdownProgramtospecifyCO2system inspectionsevery6months.

ReviseFireWaterSystemProgramtospecifyannualfirehydrant gasketinspectionsandflowtests.

ImplementtheMetalEnclosedBusProgram IncludewithintheStructuresMonitoringProgramprovisionsthat willensureanengineeringevaluationismadeonaperiodicbasis (atleastonceeveryfiveyears)ofgroundwatersamplestoassess aggressivenessofgroundwatertoconcrete.

ImplementtheBoltingIntegrityProgram.

ProvidewithintheSystemWalkdownTrainingProgramaprocess todocumentbiennialrefreshertrainingofEngineersto demonstrateinclusionofthemethodologyforagingmanagement ofplantequipment Atleast2yearspriortoenteringtheperiodof extendedoperation,forthelocationsidentified inNUREG/CR6260forBWRsoftheVYvintage, VYwillrefineourcurrentfatigueanalysesto includetheeffectsofreactorwaterenvironment andverifythatthecumulativeusagefactors (CUFs)arelessthan1.

Reviseprogramprocedurestoindicatethatthe InstrumentAirProgramwillmaintaininstrument airqualityinaccordancewithISAS7.3 VYNPSwillperformoneofthefollowing:

1.Installcoreplatewedges,or, 2.Completeaplantspecificanalysisto determineacceptancecriteriaforcontinued inspectionofcoreplateholddownbolting ImplementtheBoltingIntegrityProgram.

ProvidewithintheSystemWalkdownTraining Programaprocesstodocumentbiennial refreshertrainingofEngineerstodemonstrate inclusionofthemethodologyforaging managementofplantequipment Iftechnologytoinspectthehiddenjetpump thermalsleeveandcorespraythermalsleeve weldshasnotbeendevelopedandapprovedby theNRCatleasttwoyearspriortotheperiodof extendedoperation,VYNPSwillinitiateplant specificaction toresolvethisissue.

ThisCommitmentsupersededbysteamdryer licensecondition3.S.

ReviseSystemWalkdownProgramtospecifyCO2 systeminspectionsevery6months.

ReviseFireWaterSystemProgramtospecify annualfirehydrantgasketinspectionsandflow tests.

ImplementtheMetalEnclosedBusProgram IncludewithintheStructuresMonitoring Programprovisionsthatwillensurean engineeringevaluationismadeonaperiodic basis(atleastonceeveryfiveyears)of groundwatersamplestoassessaggressivenessof groundwatertoconcrete.

Page127of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 38 CommitmentEliminatedbyFCR27/014 39 CommitmentEliminatedbyFCR27/014 40 CommitmentDeleted.PlaceholderdeletedbyFCR27/014.

41 CommitmentDeleted.PlaceholderdeletedbyFCR27/014.

42 NoChanges 42 43 CommitmentEliminatedbyFCR26/011 44 CommitmentSuperseded.PlaceholderdeletedbyFCR27/014.

45 CommitmentEliminatedbyFCR27/014 46 NoChanges 46 47 NoChanges 47 48 TheinternalinspectionoftheundergroundServiceWaterpipingwasperformed;thus,thecommitmentwasmetandclosed.PlaceholdereliminatedbyFCR27/014.

49 NoChanges 49 ImplementtheBoltedCableConnectionsProgram.

EnhancetheDieselFuelMonitoringProgramtospecifythatfuel oilinthefirepumpdieselstorage(day)tankandtheJohnDeere dieselstoragetankwillbeanalyzedaccordingtoASTMD975and forparticulatesperASTMD2276.

EnhancetheDieselFuelMonitoringProgramtospecifythatfuel oilinthecommonportablefueloilstoragetankwillbeanalyzed accordingtoASTMD975,perASTMD2276forparticulates,and perASTMD2709forwaterandsediment.

Revisestationprocedurestospecifyfirehydranthosetesting, inspection,andreplacement,ifnecessary,inaccordancewith NFPAcodespecificationsforfirehydranthoses ThisCommitmenthasbeendeletedandreplaced withCommitment43.

ImplementtheBoltedCableConnections Program.

Establishandimplementaprogramthatwill requiretestingofthetwo13.8kVcablesfromthe twoVernonHydroStation13.8kVswitchgear busestothe13.8kV/69kVstepuptransformers ThisCommitmenthasbeendeletedandreplaced withCommitment54.

EnhancetheServiceWaterIntegrityProgramto requireaperiodicvisualinspectionoftheRHRSW pumpmotorcoolingcoilinternalsurfaceforloss ofmaterial.

EnhancetheDieselFuelMonitoringProgramto specifythatfueloilinthefirepumpdiesel storage(day)tankandtheJohnDeerediesel storagetankwillbeanalyzedaccordingtoASTM D975andforparticulatesperASTMD2276.

EnhancetheDieselFuelMonitoringProgramto specifythatfueloilinthecommonportablefuel oilstoragetankwillbeanalyzedaccordingto ASTMD975,perASTMD2276forparticulates, andperASTMD2709forwaterandsediment.

Performaninternalinspectionofthe undergroundServiceWaterpipingbefore enteringtheperiodofextendedoperation.

Revisestationprocedurestospecifyfirehydrant hosetesting,inspection,andreplacement,if necessary,inaccordancewithNFPAcode specificationsforfirehydranthoses TheBWRVIP116reportwhichwasapprovedby theStaffwillbeimplementedatVYNPSwiththe conditionsdocumentedinSections3and4ofthe StaffsfinalSEdatedMarch1,2006,forthe BWRVIP116report.

IftheVYNPSstandbycapsuleisremovedform thereactorvesselwithouttheintenttotestit, thecapsulewillbestoredinamannerwhich maintainsitinaconditionwhichwouldpermitits futureuse,includingduringtheperiodof extendedoperation,ifnecessary.

ThisCommitmenthasbeendeletedandreplaced withCommitment43.

Page128of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR 50 CommitmentEliminatedbyFCR27/014 51 Theevaluationofoperatingexperienceatextendedpowerupratelevelswasperformed;thus,thecommitmentwasmetandclosed.PlaceholdereliminatedbyFCR27/014.

52 NoChanges 52 53 CommitmentEliminatedbyFCR27/014 54 NoChanges 54 55 CommitmentEliminatedbyFCR27/014 A

A.1 Editorialchanges.

Deletionstoremoveexcessdetail.

A.1 A.2 NoChanges.ThisisanindependentreportbyH.J.SextonEngineering A.2 A.3 Editorialchangesonly.TurbineBuildinganalysisshouldremainatleastwhiletheDieselGeneratorsarerelieduponasastandbypowersource.

A.3 FigureA.31 NoChanges Figure A.31 FigureA.32 NoChanges Figure A.32 A.4 NoChanges A.4 FigureA.41 NoChanges Figure A.41 FigureA.42 NoChanges Figure A.42 FigureA.43 NoChanges Figure A.43 SummaryDescription SPECIFICDESIGNANALYSISFORTHEDRYWELL,SUPPRESSIONCHAMBERAND REACTORBUILDING TurbineBuilding PlantStack Appendices TurbineBuildingBent TurbineBuildingBent TurbineBuildingBent TurbineBuildingBent VentilationStackMathematicalModel VentilationStackMaximumShear VentilationStackMaximumMovement VentilationStackMaximumShear VentilationStackMaximumMovement ImplementtheNeutronAbsorberMonitoringProgram PriortothePEO,VYNPSwillinspectportionsofthestandbygas treatmentsystemburiedpiping.

DuringthePEO,inspectionsoftwocarbonsteelpipingsegments inthestandbygastreatmentsystemandfourcarbonsteel pipingsegmentsintheservicewatersystemwillbeperformed every10years ImplementtheNeutronAbsorberMonitoring Program Duringtheperiodofextendedoperation,VYNPS willperformperiodicvolumetricexaminationsof smallboreClass1socketandbuttwelds.

PriortothePEO,VYNPSwillinspectportionsof thestandbygastreatmentsystemburiedpiping.

DuringthePEO,inspectionsoftwocarbonsteel pipingsegmentsinthestandbygastreatment systemandfourcarbonsteel pipingsegmentsintheservicewatersystemwill beperformedevery10years PlantStack SEISMICANALYSES SummaryDescription SPECIFICDESIGNANALYSISFORTHEDRYWELL, SUPPRESSIONCHAMBERANDREACTOR BUILDING TurbineBuilding Duringtheperiodofextendedoperation,review theVernonDamownerFERCrequiredreport(s) ataminimumofeveryfiveyearstoconfirmthat theVernonDamownerisperformingthe requiredFERCinspections.

Performanevaluationofoperatingexperienceat extendedpoweruprate(EPU)levelspriortothe periodofextendedoperationtoensurethat operatingexperienceatEPUlevelsisproperly addressedbytheagingmanagementprograms.

VentilationStackMathematicalModel Enhancesafetyrelatedcoatingsprogramsand procedurestobeconsistentwiththe recommendationsofNUREG1801,SectionXI.S8, ProtectiveCoatingMonitoringandMaintenance Program.

Page129of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureA.44 NoChanges Figure A.44 A.5 Nochanges,thisisanindependentreportbyEBASCOServices A.5 A.6 Nochanges.SeismicanalysisremainswhileportionoftheIntakeStructureremainsCat1.

A.6 FigureA.61 NoChanges Figure A.61 FigureA.62 NoChanges Figure A.62 FigureA.63 NoChanges Figure A.63 FigureA.64 NoChanges Figure A.64 FigureA.65 NoChanges Figure A.65 FigureA.66 NoChanges Figure A.66 FigureA.67 NoChanges Figure A.67 A.7 DeleteAppendixA,SectionA.7AlternateCoolingCellSeismicAnalysis.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,thefunctionsprovidedbytheAlternateCoolingCellareno longerrequired.TheinformationprovidedintheAlternateCoolingCellSeismicAnalysisisnolongerapplicable,andisconsidereobsolete.

A.8 DeleteAppendixA,SectionA.8,VERMONTYANKEENUCLEARPOWERSTATIONADDITIONALINFORMATIONCONCERNINGSEISMICANALYSISOFCLASSIPIPING.

TheonetimeanalysisdocumentedinA.8hasbeensupersededbyanynumberofanalysesperformedsincethattimeasfurtherdiscussedin,primarily,AppA.9.

A.9 A.9 A.9.1 NoChanges A.9.1 A.9.2 ModifySectionA.9.2to:

incorporateeditorialchanges DeletesectionA.9.2.8,Method7,sinceitappliedonlytothereactorrecirculationsystem,andthefunctionsprovidedbythatsystemarenotrequiredpostcertificationofpermanentdefueling.

A.9.2 PLANATEL230.00' SECTIONS INTAKESTRUCTURESERVICEWATERBAYAREA MATHEMATICALMODELS(NS)

INTAKESTRUCTURESERVICEWATERBAYAREA MAXIMUMACCELERATIONS(NS)

EarthquakeAnalysisoftheControlBuilding IntakeStructure Introduction DescriptionofAnalysisMethodology DESCRIPTION,SCOPE,ANDDESIGNMETHODOLOGYUSEDFORTHEREANALYSIS OFSEISMICCLASSIPIPINGSUBSEQUENTTOINITIALOPERATION Introduction DescriptionofAnalysisMethodology VentilationStackMaximumDeflectionDiagram IntakeStructure-ServiceWaterBayArea, MaximumMoments(NS)

SECTIONS INTAKESTRUCTURESERVICEWATERBAYAREAMATHEMATICALMODELS(NS)

INTAKESTRUCTURESERVICEWATERBAYAREAMAXIMUMACCELERATIONS (NS)

ServiceWaterBayArea,MaximumDisplacements(NS)

IntakeStructure-ServiceWaterBayArea,MaximumShears(NS)

IntakeStructure-ServiceWaterBayArea,MaximumMoments(NS)

VentilationStackMaximumDeflectionDiagram PLANATEL230.00' ServiceWaterBayArea,Maximum Displacements(NS)

IntakeStructure-ServiceWaterBayArea, MaximumShears(NS)

EarthquakeAnalysisoftheControlBuilding IntakeStructure AlternateCoolingCell VERMONTYANKEENUCLEARPOWERSTATION ADDITIONALINFORMATIONCONCERNING SEISMICANALYSISOFCLASSIPIPING DESCRIPTION,SCOPE,ANDDESIGN METHODOLOGYUSEDFORTHEREANALYSISOF SEISMICCLASSIPIPINGSUBSEQUENTTOINITIAL OPERATION Page130of153 toPADandLBDCRforDSARRev0(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 CleanUpWaterDemineralizerSystem 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 ScopeofSeismicClassIPiping SystemsModifiedandMethodology Used DescriptionofFloorAmplified ResponseSpectraUsedforSeismic ReanalysisofPiping SummaryandConclusions ScopeofSeismicClassIPipingSystemsModifiedand MethodologyUsed DescriptionofFloorAmplifiedResponseSpectraUsedforSeismic ReanalysisofPiping SummaryandConclusions PRIMARYSTRUCTURESEISMICANALYSIS PRIMARYSTRUCTURESEISMICANALYSIS SummaryofNodalHydrodynamicMassesforHorizontalDirection HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations HorizontalModelBeamElementPropertiesNorthSouth Direction HorizontalModelBeamElementPropertiesNorthSouth Direction HorizontalModelBeamElementPropertiesNorthSouth Direction HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection HorizontalModelBeamElementPropertiesEastWestDirection VerticalModelBeamElementProperties SummaryofNodalHydrodynamicMassesfor HorizontalDirection HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations HorizontalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations VerticalModelNodalMasses/Elevations HorizontalModelBeamElementProperties NorthSouthDirection HorizontalModelBeamElementProperties NorthSouthDirection HorizontalModelBeamElementProperties NorthSouthDirection HorizontalModelBeamElementPropertiesEast WestDirection HorizontalModelBeamElementPropertiesEast WestDirection HorizontalModelBeamElementPropertiesEast WestDirection HorizontalModelBeamElementPropertiesEast WestDirection VerticalModelBeamElementProperties Page131of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.1isnolongerapplicable andisconsideredobsolete.

B.2 DeleteAppendixB,SectionB.2,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedintheVermontYankeeAECACRSConstructionPermit Letters.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.2regardingresolutiono theelevenconcernitemspriortoinitialoperationofthefacilityisnolongerapplicableandisconsideredobsolete.

B.3 DeleteAppendixB,SectionB.3,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedintheVermontYankeeAECACRSConstructionPermit SafetyEvaluationReport FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.3regardingresolutiono itemsofconcernpriortoinitialoperationofthefacilityisnolongerapplicableandisconsideredobsolete.

SpringElementStiffnessesHorizontalModel SpringElementStiffnessesVerticalModel NaturalFrequenciesoftheNSModel NaturalFrequenciesoftheEWModel 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 STATIONRESEARCHDEVELOPMENTANDFURTHER INFORMATION,REQUIREMENTSANDRESOLUTIONS

SUMMARY

DESCRIPTION AREASSPECIFIEDINTHEVERMONTYANKEEAEC ACRSCONSTRUCTIONPERMITLETTERS AREASSPECIFIEDINTHEVERMONTYANKEEAEC ACRSCONSTRUCTIONPERMITSAFETY EVALUATIONREPORT(RefertoTable1.10.3)

SpringElementStiffnessesHorizontalModel SpringElementStiffnessesVerticalModel NaturalFrequenciesoftheNSModel NaturalFrequenciesoftheEWModel NaturalFrequenciesoftheVerticalModel ReactorBuildingComplexLongitudinalSection ReactorBuildingComplexSeismicHorizontal Model 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 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR B.4 DeleteAppendixB,SectionB.4,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedinOtherRelatedAECACRSConstructionandOperating PermitLetters.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.4regardingresolutiono itemsofconcernrelatedtooperationofthefacilityisnolongerapplicableandisconsideredobsolete.

B.5 DeleteAppendixB,SectionB.5,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,AreasSpecifiedinOtherAECStaffConstructionorOperatingPermit SafetyEvaluationReports.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theinformationprovidedinSectionB.5regardingresolutiono itemsofconcernrelatedtooperationofthefacilityisnolongerapplicableandisconsideredobsolete.Additionally,informationregardingTornadoandMissileProtectionrelatedtoGETopical Report"TornadoProtectionForTheSpentStoragePool,"APED5696,November,1968wasrelocatedtosection10.2,SpentFuelStorage.

B.6 DeleteAppendixB,SectionB.6,StationResearch,DevelopmentandFurtherInformation,RequirementsandResolutions,SummaryConclusions.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,theconclusionsprovidedinSectionB.6regardingresolutionof itemsofconcernrelatedtooperationofthefacilityisnolongerapplicableandareconsideredobsolete.

C DeleteAppendixC,StructuralLoadingCriteria.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximum hypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.Theinformationinthisappendixis thereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.

ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.

Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.

Therefore,theinformationinAppendixCisaonetimesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCs wouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.

C.1 DeleteAppendixC.1,StructuralLoadingCriteria.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximum hypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.Theinformationinthisappendixis thereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.

ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.

Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.

Therefore,theinformationinAppendixCisaonetimesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCs wouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.

C.1.1 DeleteAppendixC.1.1,SummaryDescription.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximum hypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.Theinformationinthisappendixis thereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.

ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.

Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.

Therefore,theinformationinAppendixCisaonetimesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCs wouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.

C.2 C.2.1 C.2.2 C.2.3 C.2.4 C.2.5 C.2.6 C.2.7 AREASSPECIFIEDINOTHERRELATEDAECACRS CONSTRUCTIONANDOPERATINGPERMIT LETTERS(RefertoTable1.10.4)

IntentandScope LoadingConditionsandAllowable Limits GoverningLoadingConditionsand Criteria ReactorPressureVessel ReactorVesselInternals PipingSystems AREASSPECIFIEDINOTHERRELATEDAECSTAFF CONSTRUCTIONOROPERATINGPERMITSAFETY EVALUATIONREPORTS

SUMMARY

CONCLUSIONS STRUCTURALLOADINGCRITERIA StructuralLoadingCriteria SummaryDescription LOADINGCRITERIAFORGENERALELECTRIC(GE)

SUPPLIEDCLASSICOMPONENTS Equipment DeleteAppendixC.2,LoadingCriteriaforGeneralElectric(GE)SuppliedClassIComponents.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximum hypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.Theinformationinthisappendixis thereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.

ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.

Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.

Therefore,theinformationinAppendixCisaonetimesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCs wouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.

Page133of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR C.2.8 C.3 DeleteAppendixC.3,LoadingCriteriaforClassIPiping.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximum hypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.Theinformationinthisappendixis thereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.

ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.

Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.

Therefore,theinformationinAppendixCisaonetimesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCs wouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.

C.4 DeleteAppendixC.4,LoadingCriteriaforEBASCOSuppliedClassIComponents.

Thecapacitythatthestationstructures,systems,equipment,andcomponentsshouldwithstandtheforcesofthesimultaneousoccurrenceofadesignbasisaccident(DBA)andamaximum hypotheticalearthquake(MHE)eventwasnotspecifiedasastationdesignrequirementwhentheVYconstructionpermitwasissuedinDecember1967.Theinformationinthisappendixis thereforeanidentificationandsummaryofthecapabilityoftheasbuiltVYNPSdesigntoconformtothenewAECrequirementofApril1968mentionedabove.

ThematerialinAppendixCwaspreparedatthetimeofinitialplantlicensingandwasbasedontheplantdesignatthattime.

Plantdesignchanges,subsequenttothattime,haveresultedinsituationsthatmayalterthemagnitudeofstressesreportedinAppendixC.

Therefore,theinformationinAppendixCisaonetimesnapshotanalysisoftheVYseismicdesigntodemonstratethatthedesignwasrobustenoughtomeettherequirementthatclassISSCs wouldsurviveaconcurrentDBAandMHE.Theinformationishistoricalandmaybedeleted.

D DeleteAppendixD,QAProgram.

Section1.9,QualityAssuranceProgram,establishesthecriteriatobeappliedtosystemsrequiringQualityAssurancewhichpreventormitigatetheconsequencesofpostulatedaccidentswhich couldcauseunduerisktothehealthandsafetyofthepublic.

TheQualityAssuranceProgramManual(QAPM)implementstherequirementsof10CFR50AppendixB.

AppendixDfunctionedasaplacekeeperandisnolongerrequiredsincetheUFSARisbeingwhollyrewrittentotheDSARtoreflectthepermanentlydefueledstate.

D.0 DeleteSectionD.0,QualityAssurance(QA)ProgramDuringtheOperationsPhase.

Section1.9,QualityAssuranceProgram,establishesthecriteriatobeappliedtosystemsrequiringQualityAssurancewhichpreventormitigatetheconsequencesofpostulatedaccidentswhich couldcauseunduerisktothehealthandsafetyofthepublic.

TheQualityAssuranceProgramManual(QAPM)implementstherequirementsof10CFR50AppendixB.

AppendixDfunctionedasaplacekeeperandisnolongerrequiredsincetheUFSARisbeingwhollyrewrittentotheDSARtoreflectthepermanentlydefueledstate.

E DeleteAppendixE,StackReleaseLimitCalculations.

AppendixEtotheVermontYankeeFinalSafetyAnalysisReport(FSAR)waspreviouslyeliminatedfromtheFSARbecauseitcontainedinformationwhichhadbeensupersededbythe implementationoftheVermontYankeeOffSiteDoseCalculationManual(ODCM).InformationonreleasecalculationalmethodscanbefoundintheODCM.TheODCMalsoincludesreporting requirementsforactualpublicdosesresultingfromthereleasecalculations.TheseresultsarepublishedintheAnnualRadioactiveEffluentReleaseReport.

ThissectionfunctionedasaplacekeeperandisnolongerrequiredsincetheUFSARisbeingwhollyrewrittentotheDSARtoreflectthepermanentlydefueledstate.

F InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.Theinformationishistorical,hasnotbeen updated,isnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinAppendixFdoesnotreflectthepermanentlydefueledstate.Thisinformationisobsoleteand maybedeleted.

InformationregardingcompliancewiththeintentoftheGDCsdeterminedtobeapplicableinthedefueledconditionhasbeenrelocatedtosection3.1.1.Allotherinformationinthissection hasbeendeleted.

3.1.1 Conformancewith10CFR50AppendixA, GeneralDesignCriteria Instrumentation LoadingCriteriaforClassIPiping LOADINGCRITERIAFOREBASCOSUPPLIEDCLASS ICOMPONENTS QAPROGRAM QA(QA)ProgramDuringtheOperationsPhase STACKRELEASELIMITCALCULATIONS CONFORMANCEWITHAECDESIGNCRITERIA Page134of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR F.1 DeleteAppendixF.1,SummaryDescription.

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinAppendixF.1, SummaryDescriptionishistorical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinAppendixF.1,SummaryDescription,does notreflectthepermanentlydefueledstate.Thisinformationisobsoleteandmaybedeleted.

F.2 F.2.1 DeleteSectionF.2.1,GroupIOverallPlantRequirements(Criteria15).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.1is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.1doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

F.2.2 DeleteSectionF.2.2,GroupIIProtectionbyMultipleFissionBarriers(Criteria610).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.2is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.2doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

SUMMARY

DESCRIPTION CRITERIONCONFORMANCE GroupIOverallPlantRequirements (Criteria15)

GroupIIProtectionbyMultiple FissionBarriers(Criteria610)

Page135of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR F.2.3 DeleteSectionF.2.3,GroupIIINuclearandRadiationControls(Criteria1118).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.3is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.3doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

F.2.4 DeleteSectionF.2.4,GroupIVReliabilityandTestabilityofProtectionSystems(Criteria1926).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.4is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.4doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

F.2.5 DeleteSectionF.2.5,GroupVReactivityControl(Criteria2732).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.5is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.5doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

F.2.6 DeleteSectionF.2.6,GroupVIReactorCoolantPressureBoundary(Criteria3336).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.6is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.6doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

GroupIIINuclearandRadiation Controls(Criteria1118)

GroupIVReliabilityandTestability ofProtectionSystems(Criteria1926)

GroupVReactivityControl(Criteria 2732)

GroupVIReactorCoolantPressure Boundary(Criteria3336)

Page136of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR F.2.7 DeleteSectionF.2.7,GroupVIIEngineeredSafetyFeatures(Criteria3765).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.7is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.7doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

F.2.8 DeleteSectionF.2.8,GroupVIIIFuelandWasteStorageSystems(Criteria6669).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.8is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.8doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

F.2.9 DeleteSectionF.2.9,GroupIXPlantEffluents(Criterion70).

InaStaffRequirementsMemorandumonSECY92223,theNRCapprovedaproposalinwhichitwasrecognizedthatplantswithconstructionpermitsissuedbeforeMay21,1971werenot licensedtomeetthefinalGeneralDesignCriteria.ThememorecognizedthatwhilecompliancewiththeintentofthefinalGeneralDesignCriteriawasimportant,backfittingofthese requirementstoolderplantswouldprovidelittleornosafetybenefit.

ThepurposeofAppendixF,asoriginallysubmittedwastodemonstratethat,althoughVYwasnotrequiredtocomplywiththeGeneralDesignCriteria,thedesignandconstructionofthe VermontYankeeNuclearPowerStationhadbeenperformedinaccordancewiththeGeneralDesignCriteriaproposedinJuly,1967.

ThefinalversionoftheGeneralDesignCriteriawaspublishedinFebruary,1971as10CFR50AppendixA.Differencesbetweentheproposedandfinalversionsofthecriteriaincludeda consolidationfrom70to64criteriaandgeneralelaborationofdesignrequirementdetails.Since,atthetimeofissuance,theCommissionstressedthatthefinalversionofthecriteriawerenot newrequirementsandwerepromulgatedtomoreclearlyarticulatethelicensingrequirementsandpracticesineffectatthetime,AppendixFwasnotupdatedtothefinalGDCs.

Consequently,theinformationprovidedinAppendixFisalate1960'ssnapshotofhowVYdesignandconstructionmettheintentoftheGDCs.TheinformationprovidedinSectionF.2.9is historical,hasnotbeenupdated,andisnotrequiredsinceVYisnotrequiredtomeettheGDCs.TheinformationprovidedinSectionF.2.9doesnotreflectthepermanentlydefueledstate.This informationisobsoleteandmaybedeleted.

G G.1 TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.Consequently, theinformationprovidedinSectionG.1isconsideredhistorical,isobsoleteandmaybedeletedfromtheDSAR.

GroupIXPlantEffluents(Criterion 70)

STATIONMETEOROLOGY INITIALONSITEMETEOROLOGICALPROGRAM GroupVIIEngineeredSafety Features(Criteria3765)

GroupVIIIFuelandWasteStorage Systems(Criteria6669)

Page137of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR G.1.1 DeleteSectionG.1.1,Introduction.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.1isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

G.1.2 DeleteSectionG.1.2,DescriptionoftheMonitoringProgram.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.2isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

G.1.3 DeleteSectionG.1.3,Results.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.3isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

G.1.4 DeleteSectionG.1.4,ComparisonwithPDARDiffusionModel.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.4isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

G.1.5 DeleteSectionG.1.5,Conclusions.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercedestheinformationinsectionG.1.Consequently,theinformationprovidedinSectionG.1.5isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Introduction DescriptionoftheMonitoring Program Results ComparisonwithPDARDiffusion Model Conclusions Page138of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table G.1.1 DeleteTableG.1.1,MonthlyWindSummaryAugust1967.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.1isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.2 DeleteTableG.1.2,MonthlyWindSummarySeptember1967.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.2isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.3 DeleteTableG.1.3,MonthlyWindSummaryOctober1967.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.3isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.4 DeleteTableG.1.4,MonthlyWindSummaryNovember1967.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.4isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.5 DeleteTableG.1.5,MonthlyWindSummaryDecember1967.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.5isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

MonthlyWindSummaryAugust 1967 MonthlyWindSummarySeptember 1967 MonthlyWindSummaryOctober 1967 MonthlyWindSummaryNovember 1967 MonthlyWindSummaryDecember 1967 Page139of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table G.1.6 DeleteTableG.1.6,MonthlyWindSummaryJanuary1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.6isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.7 DeleteTableG.1.7,MonthlyWindSummaryFebruary1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.7isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.8 DeleteTableG.1.8,MonthlyWindSummaryMarch1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.8isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.9 DeleteTableG.1.9,MonthlyWindSummaryApril1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.9isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.10 DeleteTableG.1.10,MonthlyWindSummaryMay1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.10isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

MonthlyWindSummaryMay1968 MonthlyWindSummaryJanuary 1968 MonthlyWindSummaryFebruary 1968 MonthlyWindSummaryMarch 1968 MonthlyWindSummaryApril1968 Page140of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table G.1.11 DeleteTableG.1.11,MonthlyWindSummaryJune1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.11isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.12 DeleteTableG.1.12,MonthlyWindSummaryJuly1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.12isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.13 DeleteTableG.1.13,SeasonalWindSummarySummer;August1967,JuneJuly1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.13isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.14 DeleteTableG.1.14,SeasonalWindSummaryFall;SeptemberNovember1967.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.14isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.15 DeleteTableG.1.15,SeasonalWindSummaryWinter;December1967February1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.15isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

MonthlyWindSummaryJune1968 MonthlyWindSummaryJuly1968 SeasonalWindSummarySummer; August1967,JuneJuly1968 SeasonalWindSummaryFall; SeptemberNovember1967 SeasonalWindSummaryWinter; December1967February1968 Page141of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table G.1.16 DeleteTableG.1.16,SeasonalWindSummarySpring;MarchMay1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.16isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.17 DeleteTableG.1.17,AnnualWindSummaryAugust1967July1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.17isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

Table G.1.18 DeleteTableG.1.18,WindDirectionPersistenceSummaryin22.5DegreeSectorsAllClassesofStabilityCombined.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinTableG.1.18isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 1

DeleteFigureG.11,AnnualWindRose,AllStabilityClassesCombined.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.11isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 2

DeleteFigureG.12,FallWindRose,AllStabilityClassesCombined.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.12isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

SeasonalWindSummarySpring; MarchMay1968 AnnualWindSummaryAugust1967 July1968 WindDirectionPersistenceSummary in22.5DegreeSectorsAllClassesof StabilityCombined AnnualWindRose,AllStability ClassesCombined FallWindRose,AllStabilityClasses Combined Page142of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.1 3

DeleteFigureG.13,WinterWindRose,AllStabilityClassesCombined.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.13isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 4

DeleteFigureG.14,SpringWindRose,AllStabilityClassesCombined.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.14isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 5

DeleteFigureG.15,SummerWindRose,AllStabilityClassesCombined.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.15isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 6

DeleteFigureG.16,AnnualWindRose,ModeratelyandSlightlyStableConditions.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.16isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 7

DeleteFigureG.17,AnnualWindRosewithPrecipitationOccurrence.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.17isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

WinterWindRose,AllStability ClassesCombined SpringWindRose,AllStability ClassesCombined SummerWindRose,AllStability ClassesCombined AnnualWindRose,Moderatelyand SlightlyStableConditions AnnualWindRosewithPrecipitation Occurrence Page143of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.1 8

DeleteFigureG.18,AnnualWindRosewithNoPrecipitationOccurrence.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.18isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 9

DeleteFigureG.19,MonthlyInversionFrequencyandAverageWindSpeed DuringInversions.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.19isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 10 DeleteFigureG.110,NumberofHoursforEachWindSpeedGroupfor32HourDecember1967Inversion.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.110isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 11 DeleteFigureG.111,WindDirectionDistributionDuring32HourDecemberInversion.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.111isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

FigureG.1 12 DeleteFigureG.112,DurationofLongestInversioninEachMonthBetweenAugust1967andJuly1968.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.112isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

MonthlyInversionFrequencyand AverageWindSpeed DuringInversions NumberofHoursforEachWind SpeedGroupfor32HourDecember 1967Inversion WindDirectionDistributionDuring 32HourDecemberInversion DurationofLongestInversioninEach MonthBetweenAugust1967and July1968 AnnualWindRosewithNo PrecipitationOccurrence Page144of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureG.1 13 DeleteFigureG.113,CumulativeFrequencyofOccurrenceof.

TheInitialOnSiteMeteorologicalProgramcollectedmeteorologicaldatafromAugust,1967toJuly,1968,foranalysisasthebasisforselectionofasuitablesitediffusionmodelfortheoriginal VYPlantDesignandAnalysisReport.SectionG.1containsadiscussionoftheresultsofthatmonitoringprogramandthemeteorologicalmodelusedfordosecalculationsintheoriginalVY PlantDesignandAnalysisReport.

TheOnSiteMeteorologicalDataCollectionProgramwasupgradedinearly1976tomeettheintentofRevision0ofRegulatoryGuide1.23.SectionG.2describesthecurrentonsitemonitoring programandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember31,1980.SectionG.2includesadiscussionofthedatasummaries andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedbythecurrentmonitoringprogram(January1980December 1980).Itwasconcludedthatresultsfrombothmonitoringprogramsarecompatible,andthatbothprogramsproduceddatabaseswhicharerepresentativeofsitemeteorology.The informationprovidedinsectionG.2supercededtheinformationinsectionG.1.Consequently,theinformationprovidedinFigureG.113isconsideredhistorical,isobsoleteandmaybedeleted fromtheDSAR.

G.2 SectionG.2describesthecurrentonsitemeteorologicalmonitoringprogramandpresentswindandstabilitydatasummariesforonefullyearofoperation;January1,1980throughDecember 31,1980.Adiscussionofthedatasummariesisincluded,andacomparisonismadebetweendatacollectedbytheinitialmonitoringprogram(August1967July1968)anddatacollectedby thecurrentmonitoringprogram(January1980December1980).Resultsfrombothmonitoringprogramswerecompatible,andbothprogramsproduceddatabaseswhichwere representativeofsitemeteorology.

SectionG.2supportsthemeteorologysectionoftheSAR.

SectionG.2supportsmeetingtherequirementsofRegGuide1.23,Rev.0.

Nochangesarerequired.

G.2 G.2.1 NoChanges G.2.1 G.2.2 NoChanges G.2.2 G.2.3 NoChanges G.2.3 Table G.2.1 NoChanges Table G.2.1 Table G.2.2 NoChanges Table G.2.2 Table G.2.3 NoChanges Table G.2.3 Table G.2.4 NoChanges Table G.2.4 Table G.2.5 NoChanges Table G.2.5 Table G.2.6 NoChanges Table G.2.6 Table G.2.7 NoChanges Table G.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

CURRENTONSITEMETEOROLOGICAL PROGRAM Introduction DescriptionoftheMonitoring Program Results MeteorologicalDataRecovery Ratesfor1980 JointFrequencyDistributionof WindSpeed,WindDirection,and JointFrequencyDistributionof WindSpeed,WindDirection,and WindDirectionPersistence Summary(35footlevel)

WindDirectionPersistence Summary(297footlevel)

InversionPersistenceSummary (19833footDeltaT)

InversionPersistenceSummary (29533footDeltaT)

LocationofPrimaryandBackup MeteorologicalTowers SpringWindRose(35footlevel)

March1980May1980 SummerWindRose(35foot level)June1980August1980 AutumnWindRose(35foot level)September1980 November1980 WinterWindRose(35footlevel)

January1980February1980; December1980 AnnualWindRose(35footlevel)

January1980December1980 SummerWindRose(35footlevel)

June1980August1980 AutumnWindRose(35footlevel)

September1980November1980 WinterWindRose(35footlevel)

January1980February1980; December1980 AnnualWindRose(35footlevel)

January1980December1980 CumulativeFrequencyofOccurrence of Introduction DescriptionoftheMonitoring Program Results MeteorologicalDataRecoveryRates for1980 JointFrequencyDistributionofWind Speed,WindDirection,andStability JointFrequencyDistributionofWind Speed,WindDirection,andStability WindDirectionPersistenceSummary (35footlevel)

WindDirectionPersistenceSummary (297footlevel)

InversionPersistenceSummary(198 33footDeltaT)

InversionPersistenceSummary(295 33footDeltaT)

LocationofPrimaryandBackup MeteorologicalTowers SpringWindRose(35footlevel)

March1980May1980 CURRENTONSITEMETEOROLOGICALPROGRAM Page145of153 toPADandLBDCRforDSARRev0(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).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Additionally, sinceSectionsH.2andH.3aredeletedfromtheDSAR,thesummaryofthosesectionspresentedinSectionH.1isnolongerapplicableandisobsolete.

H.2 SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatethermalmargins.Thethermal operatinglimitsfortheVermontYankeeNuclearPowerStationwereevaluatedforeachcycleofoperation.ThesewerepresentedinthecurrentcycleCorePerformanceAnalysisReportaswell asintheTechnicalSpecifications.

SectionH.2alsosupplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

H.2.1 DeleteSectionH.2.1,Introduction.

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

H.2.2 DeleteSectionH.2.2,ReactorCoreDesignBasesLimits.

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

H.2.3 DeleteSectionH.2.3,TypicalInitialCorePerformance.

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

SectionH.2.3presentedexpectedinitialcoreperformancecharacteristics.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.Initialcore performancecharacteristicsarehistoricalandarenolongerapplicable.

Additionally,UFSARSection3.7hasbeendeleted.

AnnualWindRose(297foot level)January1980December 1980 SummerWindRose(297foot level)June1980August1980 AutumnWindRose(297foot level)September1980 November1980 WinterWindRose(297foot level)January1980February 1980;December1980 SpringWindRose(297footlevel)

March1980May1980 SummerWindRose(297footlevel)

June1980August1980 AutumnWindRose(297footlevel)

September1980November1980 WinterWindRose(297footlevel)

January1980February1980; December1980 AnnualWindRose(297footlevel)

January1980December1980 THERMALHYDRAULICDESIGN SummaryDescription CORETHERMALDESIGN Introduction ReactorCoreDesignBasesLimits TypicalInitialCorePerformance SpringWindRose(297footlevel)

March1980May1980 Page146of153 toPADandLBDCRforDSARRev0(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.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

SectionH.2.4discussedthethermalmarginbetweentheproposedreactordesignlimitsandtheandfueldamagelimits.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Additionally,UFSARSection3.7hasbeendeleted H.2.5 DeleteSectionH.2.5,TransientOperation.

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

H.2.6 DeleteSectionH.2.6,Summary.

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

H.2.7 DeleteSectionH.2.7,Conclusions.

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.Theconclusionsdrawninthissectionarenolongerapplicable.

Additionally,UFSARSection3.7hasbeendeleted.

H.2.8 DeleteSectionH.2.8,References SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.Thedocumentsreferencedinthissectionarenolongerapplicable.

Additionally,UFSARSection3.7hasbeendeleted.

Table H.2.1 DeleteTableH.2.1,PeakLinearHeatGenerationRate(InitialReactorCoreDesignBases)

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.TheinformationprovidedinTableH.2.1ishistorical,isnolongerapplicableandisobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

Table H.2.2 DeleteTableH.2.2,ResultsofTransients(InitialReactorCoreDesignBases).

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.TheinformationprovidedinTableH.2.2ishistorical,isnolongerapplicableandisobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

RESULTSOFTRANSIENTS (INITIALREACTORCOREDESIGN BASES)

ThermalMargin TransientOperation Summary Conclusions REFERENCES PEAKLINEARHEATGENERATION RATE (INITIALREACTORCOREDESIGN BASES)

Page147of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table H.2.3 DeleteTableH.2.3,LimitComparisons(InitialReactorCoreDesignBases).

SectionH.2,CoreThermalDesign,reviewedinitialreactorcoredesigncriteriaand,bypresentationofanalyticaldata,showedtheexistenceofadequatecorethermalmargins.SectionH.2 supplementedthecorethermaldesigninformationgiveninSection3.7oftheUFSAR.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,transientoperationscannolongeroccur,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolonger applicableandareobsolete.TheinformationprovidedinTableH.2.3ishistorical,isnolongerapplicableandisobsolete.

Additionally,UFSARSection3.7hasbeendeleted.

H.3 SectionH.3summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectandresolutionofuncertaintiesinkeyareasoftheinitial reactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio.

H.3.1 DeleteSectionH.3.1,IntroductionandSummary SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,informationregardingcriticalheatfluxmarginuncertaintiesishistorical,nolongerapplicableandisobsolete.

H.3.2 DeleteSectionH.3.2,DefinitionsandObjectivesoftheAnalysis.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,informationregardingcriticalheatfluxmarginuncertaintiesishistorical,nolongerapplicableandisobsolete.

H.3.3 DeleteSectionH.3.3,AnalyticalProceduresandResults.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,informationregardingcriticalheatfluxmarginuncertaintiesishistorical,nolongerapplicableandisobsolete.

H.3.4 DeleteSectionH.3.4,ReactorModel.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,informationregardingthereactormodelusedincriticalheatfluxmarginuncertaintiesandanalysisishistorical,nolongerapplicableandisobsolete.

H.3.5 DeleteSectionH.3.5,TheCalculationalProcess.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,informationregardingthecalculationalprocessusedincriticalheatfluxmarginuncertaintiesandanalysisishistorical,nolongerapplicableandisobsolete.

LIMITCOMPARISONS (INITIALREACTORCOREDESIGN BASES)

IntroductionandSummary DefinitionsandObjectivesofthe Analysis AnalyticalProceduresandResults ReactorModel TheCalculationalProcess EFFECTOFUNCERTAINTIESONCRITICALHEAT FLUXMARGIN Page148of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR H.3.6 DeleteSectionH.3.6,Results.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,informationregardingtheresultsoftheanalysisusedincriticalheatfluxmarginuncertaintiesarehistorical,nolongerapplicableandobsolete.

H.3.7 DeleteSectionH.3.7,Conclusions.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,conclusionsregardingtheresultsoftheanalysisusedincriticalheatfluxmarginuncertaintiesarehistorical,nolongerapplicableandareobsolete.

H.3.8 DeleteSectionH.3.7,References SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,documentslistedinthereferencessectionarenolongerapplicableandareobsolete.

Table H.3.1 DeleteTableH.3.1,UncertaintyIncorePowerDetermination SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,theinformationprovidedinTableH.3.1isnolongerapplicableandisobsolete.

Table H.3.2 DeleteTableH.3.2,OverpowerOccurrences.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,theinformationprovidedinTableH.3.2isnolongerapplicableandisobsolete.

Table H.3.3 DeleteTableH.3.3,ManufacturingToleranceAffectingLocalPower.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,theinformationprovidedinTableH.3.3isnolongerapplicableandisobsolete.

Results Conclusions References UncertaintyIncorePower Determination OverpowerOccurrences ManufacturingToleranceAffecting LocalPower Page149of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR Table H.3.4 DeleteTableH.3.4,BaseOperatingState.

SectionH.3,EffectsofUncertaintiesonCriticalHeatFluxMargin,summarizedthecorethermalhydraulicuncertaintyanalysisandpresentedadditionalinformationregardingtheeffectand resolutionofuncertaintiesinkeyareasoftheinitialreactorcoredesign,e.g.,thecalculationsofflowinasinglechannelandthecalculationsoftheminimumcriticalheatfluxratio..

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsarenolongerpossible.

Sinceareactorcorecannolongerbeloadedintothereactorvessel,reactorcoredesigncriteria,thermalmarginsandthermallimitsarenolongerapplicableandareobsolete.

Consequently,theinformationprovidedinTableH.3.4isnolongerapplicableandisobsolete.

I TheEstimateofProbabilitiesofaPipeBreakpresentedinAppendixI,attemptedtopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplantforeachpipingsystemand component.

I.1 DeleteSectionI.1,ProbabilityofLeakingFailures AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.1regardingtheprobabilityofleakingfailuresisnolongerapplicable.Thisinformationis historicalandisobsolete.

I.2 DeleteSectionI.2,CriticalCrackSize.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.2regardingcriticalcracksizeisnolongerapplicable.Thisinformationishistoricalandis obsolete.

I.3 DeleteSectionI.3,LeakageFlowFromCircumferentialCracks.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.3regardingleakageflowfromcircumferentialcracksisnolongerapplicable.Thisinformationis historicalandisobsolete.

I.4 DeleteSectionI.4,ProbabilityofaLineBreak.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedinSectionI.4regardinglinebreakprobabilityisnolongerapplicable.Thisinformationishistoricalandis obsolete.

I.5 DeleteSectionI.5,References.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,thedocumentsreferencedinsectionI.5arenolongerapplicable.Thisinformationishistoricalandisobsolete.

BaseOperatingState CRITICALCRACKSIZE LEAKAGEFLOWFROMCIRCUMFERENTIAL CRACKS PROBABILITYOFLINEBREAK References ESTIMATEOFPROBABILITIESOFPIPEBREAK PROBABILITYOFLEAKINGFAILURES Page150of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR FigureI1 DeleteFigureI1,SummaryofFractureDateforPipingMaterials AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,thesummaryinformationprovidedonFigureI1regardingfracturedataforpipingmaterialsisnolongerapplicable.This informationishistoricalandisobsolete.

FigureI2 DeleteFigureI2,RelationshipofLeakRatetoStressIntensityFactor.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedonFigureI2regardingtherelationshipbetweenleakrateandstressintensityfactorisnolonger applicable.Thisinformationishistoricalandisobsolete.

FigureI3 DeleteFigureI3,ProbabilitythataLineBreakResultsfromaLeakingCrack.

AppendixI,EstimateofProbabilitiesofPipeBreak,attemptedtoassignaprobabilitytopredicttherateofoccurrenceofthroughwallcracksduringthelifeoftheplant.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelatedtransientsanddesignbasisaccidentsarenolongerpossible.Predictionoftheoccurrenceofthroughwallcracksforthose SSCswhichremaininoperationfollowingpermanentdefuelingisnotrequiredsinceafailureofthoseSSCswhichremaininservicewillnotinitiateadesignbasisaccident,resultinfueldamage orthreatenthehealthandsafetyofthepublic.Therefore,theinformationprovidedonFigureI3showingtheprobabilitythatalinebreakwillresultfromaleakingcrackisnolonger applicable.Thisinformationishistoricalandisobsolete.

J J.1 DeleteSectionJ.1,StructuralEvaluationofReactorRecirculationSystem,ScopeandIntent.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesign basisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.

J.2 DeleteSectionJ.2,StructuralEvaluationofReactorRecirculationSystem,LoadingCondtions.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesign basisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.

J.3 DeleteSectionJ.3,StructuralEvaluationofReactorRecirculationSystem,AllowableLimits.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesign basisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.

SummaryofFractureDataforPipingMaterials RelationshipofLeakRatetoStressIntensity Factor ProbabilitythataLineBreakResultsfroma LeakingCrack STRUCTURALEVALUATIONOFREACTORRECIRCULATION SYSTEM ScopeandIntent LoadingConditions AllowableLimits Page151of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR J.4 DeleteSectionJ.4,StructuralEvaluationofReactorRecirculationSystem,DiscussionofResults.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesign basisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.ReactorRecirculationSysteminformationisobsolete.

J.5 DeleteSectionJ.5,StructuralEvaluationofReactorRecirculationSystem,References.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesign basisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.Referencesarenolongerapplicable.ReactorRecirculation Systeminformationisobsolete.

TABLEJ.31 DeleteTableJ.31,RHRandRecirculationSystemsPipingLoadCombinations.

TheReactorRecirculationSystemprovidedavariablemoderator(coolant)flowtothereactorcoretoadjustreactorpowerlevel.Thesystemwasdesignedtoassureadequatefuelbarrier thermalmarginremainedfollowingRecirculationPumpSystemmalfunctionsandthatfailureofpipingintegritydidnotcompromisetheabilityofthereactorvesselinternalstomaintaina refloodablevolume.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.Consequently,fuelbarrierthermalmarginandcorerefloodfollowingdesign basisaccidentsisnolongerapplicable.Asaresult,astructuralevaluationoftheReactorRecirculationSystemisnolongerrequired.TheinformationprovidedontableJ.31isnolonger applicable.ReactorRecirculationSysteminformationisobsolete.

K K.1 DeletesectionK.1,CoreShroudRepair,IntroductionandSummary.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsidered obsolete.

K.2 DeletesectionK.2,CoreShroudRepair,Background.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsidered obsolete.

K.3 DeletesectionK.3,CoreShroudRepair,DescriptionofRepair.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsidered obsolete.

K.4 DeletesectionK.4,CoreShroudRepair,StructuralandDesignEvaluation.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,thehistoricalinformationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsidered obsolete.

INTRODUCTIONAND

SUMMARY

BACKGROUND DESCRIPTIONOFREPAIR STRUCTURALANDDESIGNEVALUATION CORESHROUDREPAIR RHRandRecirculationSystemsPipingLoad Combinations DiscussionofResults References Page152of153 toPADandLBDCRforDSARRev0(FCR27/027)

VermontYankeeUFSARtoDSARConversionProject 7/15/2015 VYUFSAR UFSARSection FSARConversiontoDSARChangeSummary DSARSection VYDSAR K.5 DeletesectionK.5,CoreShroudRepair,SeismicAnalysis.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,theseismicanalysisprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsideredobsolete.

K.6 DeletesectionK.6,CoreShroudRepair,SystemsEvaluation.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,theSystemsevaluationprovidedinthissectionregardingcoreshroudrepairsisnolongerapplicableandisconsidered obsolete.

K.7 DeletesectionK.7,MaterialsandFabrication.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,thedescriptionofthematerialsandfabricationprocessusedisnolongerapplicableandisconsideredobsolete.

K.8 DeletesectionK.8,References.

AppendixKsummarizesthedesignofthecoreshroudrepairfortheVermontYankeeNuclearPowerStation.

FollowingcertificationofpermanentdefuelingthelicenseeisnolongerauthorizedtoemplaceorretainfuelinthereactorvesselIAW10CFR50.82(a)(2).Sinceitisnolongerpossibletoloada nuclearcore,poweroperationscannolongeroccurandcorerelateddesignbasisaccidentsarenolongerpossible.

AsdescribedinthejustificationforeliminationoftheReactorVesselandAppurtenances(UFSARSection4.2)fromtheDSAR,thefunctionsprovidedbytheReactorVesselandinternals, includingthecoreshroud,arenolongerrequired.Consequently,thereferenceslistedinSectionK.8arelongerapplicableandareconsideredobsolete.

MATERIALSANDFABRICATION REFERENCES SEISMICANALYSES SYSTEMSEVALUATION Page153of153