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| {{#Wiki_filter:AMERICANELECTRICPOWERSERVICECORPORATIONDESIGNDIVISIONMECHANICALDESIGNSECTION~Scb'ctInterimAcceptanceCriteriaforSafetyRelatedPipingSystemsPlantAlicabilitDonaldC.CookNuclearPlantUnits1&2OriinatorMech.es.g.EnDate~ArcvalMech.Des.Sec.gr.8812130083881205'DRADGCK05000315PPDC | | {{#Wiki_filter:AMERICANELECTRICPOWERSERVICECORPORATION DESIGNDIVISIONMECHANICAL DESIGNSECTION~Scb'ctInterimAcceptance CriteriaforSafetyRelatedPipingSystemsPlantAlicabilit DonaldC.CookNuclearPlantUnits1&2OriinatorMech.es.g.EnDate~ArcvalMech.Des.Sec.gr.8812130083 881205'DR ADGCK05000315PPDC |
| ~~ | | ~~ |
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| ==1.0INTRODUCTION== | | ==1.0INTRODUCTION== |
| :Donald,",C.CookFSAR(hereinaftercalledFSAR,Ref..4)defines-designbasesforvariousseismiccategorypipingsystem.Thesebasesprovidesufficientsafetymarginforcontinuedplantoperationsuchthattheplantsafetyisnotcompromised.However,duringanevaluationofaspecificplantcondition,identifiedviaaproblemreport,ifthelimitsofthedesignbasesforpipinganditssupportsystemsareexceeded,operabilityofthepipingsystemduringaDBEwillbeassuredbymeetingthelimitsofthese'nterimcriteria(Note:ExpeditiousprocessingandreportabilityrequirementsaredefinedinAEPSCProcedureGP15.1).Thesecriteriawillprovidejustificationsforcontinuedplantoperation.Modificationsrequiredtoreturnthepipingandsupportsystemwithinthedesignbaseslimitsshallbemadebythenextrefuelingoutageorsooner.2.0SCOPE:Thesecriteriaareapplicabletcallsafetyre.latedpipingandassociatedsupportsystemsoftheDonaldC.CookNuclearPlant.3.0CRITERIA:3.1PiinSstemAccetanceCriteriaAnanalysisoftheaffectedpipingsystemshallbeperformedinaccordancewithASMESectionIIINC-3600ServiceLevelDlimits(Equation9)forloading.conditionassociatedwithDesignBasisEarthquake(DBE).IncreaseddampingvaluesaspermittedbyCodeCaseN-411shallbeusedforDBEanalysis.S+S+SD<2.4S(Ref.1,AppendixF)WhereS=LongitudinalPressureStressS=Deadwt.stressplusstressesduetowotherMechanicalloadsSD=DesignBasisEarthquakeStressS=MaterialYieldStressatDesignTemp.NOTE:Forpipesizes2.5inchesandlarger,useanallowablestressof2.0Sintheaboveequation.3.2PieSuortAccetanceCriteria3.2.1Inadditiontothesupportloadsdevelopedin3.1,thermalloadsandotherapplicabledisplacementinducedloads(e.g.seismicanchormovements)shallbeincludedtodefinedesignloadsforeachcomponentsupportassociatedwith | | : |
| ~J4 thepipingsystem.ThesesupportswillthenbeevaluatedinaccordancewiththelimitsprescribedinAppendixF(Ref.1)subsubarticleF-1370.3''32'Foranchorbolts,useafactorofsafetyof2againstultimateshearandtensionvalues,insteadofthevaluesgiveninStructuralDesignStandardSDS-88whichhaslargefactorofsafety.Forcatalogitems,prorateloadcapacitiesbasedonafactorofsafetyof2.Manufacture'sonetimeloadcapacityshallbeusedforhydraulicsnubbers. | | Donald,",C. |
| | CookFSAR(hereinafter calledFSAR,Ref..4)defines-designbasesforvariousseismiccategorypipingsystem.Thesebasesprovidesufficient safetymarginforcontinued plantoperation suchthattheplantsafetyisnotcompromised. |
| | However,duringanevaluation ofaspecificplantcondition, identified viaaproblemreport,ifthelimitsofthedesignbasesforpipinganditssupportsystemsareexceeded, operability ofthepipingsystemduringaDBEwillbeassuredbymeetingthelimitsofthese'nterimcriteria(Note:Expeditious processing andreportability requirements aredefinedinAEPSCProcedure GP15.1).Thesecriteriawillprovidejustifications forcontinued plantoperation. |
| | Modifications requiredtoreturnthepipingandsupportsystemwithinthedesignbaseslimitsshallbemadebythenextrefueling outageorsooner.2.0SCOPE:Thesecriteriaareapplicable tcallsafetyre.latedpipingandassociated supportsystemsoftheDonaldC.CookNuclearPlant.3.0CRITERIA: |
| | 3.1PiinSstemAccetanceCriteriaAnanalysisoftheaffectedpipingsystemshallbeperformed inaccordance withASMESectionIIINC-3600ServiceLevelDlimits(Equation 9)forloading.condition associated withDesignBasisEarthquake (DBE).Increased dampingvaluesaspermitted byCodeCaseN-411shallbeusedforDBEanalysis. |
| | S+S+SD<2.4S(Ref.1,AppendixF)WhereS=Longitudinal PressureStressS=Deadwt.stressplusstressesduetowotherMechanical loadsSD=DesignBasisEarthquake StressS=MaterialYieldStressatDesignTemp.NOTE:Forpipesizes2.5inchesandlarger,useanallowable stressof2.0Sintheaboveequation. |
| | 3.2PieSuortAccetanceCriteria3.2.1Inadditiontothesupportloadsdeveloped in3.1,thermalloadsandotherapplicable displacement inducedloads(e.g.seismicanchormovements) shallbeincludedtodefinedesignloadsforeachcomponent supportassociated with |
| | ~J4 thepipingsystem.Thesesupportswillthenbeevaluated inaccordance withthelimitsprescribed inAppendixF(Ref.1)subsubarticle F-1370.3''32'Foranchorbolts,useafactorofsafetyof2againstultimateshearandtensionvalues,insteadofthevaluesgiveninStructural DesignStandardSDS-88whichhaslargefactorofsafety.Forcatalogitems,prorateloadcapacities basedonafactorofsafetyof2.Manufacture's onetimeloadcapacityshallbeusedforhydraulic snubbers. |
|
| |
|
| ==4.0CONCLUSION== | | ==4.0CONCLUSION== |
| :ThesecriteriaprovideallowablevaluesgreaterthantheFSAR,however,thesevaluesarebasedonthecurrentcodes,standardsandpracticesapplicabletothedesignofNuclearPowerPlants. | | : |
| | Thesecriteriaprovideallowable valuesgreaterthantheFSAR,however,thesevaluesarebasedonthecurrentcodes,standards andpractices applicable tothedesignofNuclearPowerPlants. |
|
| |
|
| ==5.0REFERENCES== | | ==5.0REFERENCES== |
| :1.AmericanSocietyofMechanicalEngineers(ASME),BoilerandPressureVesselCodes,SectionIII,1983edition.2.ASMEcodecaseN-411(ApprovaldateFebruary20,1986)3.~"SteelConstructionManual",AmericanInstituteofSteelConstruction4.DonaldC.CookNuclearPlant,updatedFinalSafetyAnalysisReport(FSAR)}} | | : |
| | 1.AmericanSocietyofMechanical Engineers (ASME),BoilerandPressureVesselCodes,SectionIII,1983edition.2.ASMEcodecaseN-411(Approval dateFebruary20,1986)3.~"SteelConstruction Manual",AmericanInstitute ofSteelConstruction 4.DonaldC.CookNuclearPlant,updatedFinalSafetyAnalysisReport(FSAR)}} |
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Text
AMERICANELECTRICPOWERSERVICECORPORATION DESIGNDIVISIONMECHANICAL DESIGNSECTION~Scb'ctInterimAcceptance CriteriaforSafetyRelatedPipingSystemsPlantAlicabilit DonaldC.CookNuclearPlantUnits1&2OriinatorMech.es.g.EnDate~ArcvalMech.Des.Sec.gr.8812130083 881205'DR ADGCK05000315PPDC
~~
1.0INTRODUCTION
Donald,",C.
CookFSAR(hereinafter calledFSAR,Ref..4)defines-designbasesforvariousseismiccategorypipingsystem.Thesebasesprovidesufficient safetymarginforcontinued plantoperation suchthattheplantsafetyisnotcompromised.
However,duringanevaluation ofaspecificplantcondition, identified viaaproblemreport,ifthelimitsofthedesignbasesforpipinganditssupportsystemsareexceeded, operability ofthepipingsystemduringaDBEwillbeassuredbymeetingthelimitsofthese'nterimcriteria(Note:Expeditious processing andreportability requirements aredefinedinAEPSCProcedure GP15.1).Thesecriteriawillprovidejustifications forcontinued plantoperation.
Modifications requiredtoreturnthepipingandsupportsystemwithinthedesignbaseslimitsshallbemadebythenextrefueling outageorsooner.2.0SCOPE:Thesecriteriaareapplicable tcallsafetyre.latedpipingandassociated supportsystemsoftheDonaldC.CookNuclearPlant.3.0CRITERIA:
3.1PiinSstemAccetanceCriteriaAnanalysisoftheaffectedpipingsystemshallbeperformed inaccordance withASMESectionIIINC-3600ServiceLevelDlimits(Equation 9)forloading.condition associated withDesignBasisEarthquake (DBE).Increased dampingvaluesaspermitted byCodeCaseN-411shallbeusedforDBEanalysis.
S+S+SD<2.4S(Ref.1,AppendixF)WhereS=Longitudinal PressureStressS=Deadwt.stressplusstressesduetowotherMechanical loadsSD=DesignBasisEarthquake StressS=MaterialYieldStressatDesignTemp.NOTE:Forpipesizes2.5inchesandlarger,useanallowable stressof2.0Sintheaboveequation.
3.2PieSuortAccetanceCriteria3.2.1Inadditiontothesupportloadsdeveloped in3.1,thermalloadsandotherapplicable displacement inducedloads(e.g.seismicanchormovements) shallbeincludedtodefinedesignloadsforeachcomponent supportassociated with
~J4 thepipingsystem.Thesesupportswillthenbeevaluated inaccordance withthelimitsprescribed inAppendixF(Ref.1)subsubarticle F-1370.332'Foranchorbolts,useafactorofsafetyof2againstultimateshearandtensionvalues,insteadofthevaluesgiveninStructural DesignStandardSDS-88whichhaslargefactorofsafety.Forcatalogitems,prorateloadcapacities basedonafactorofsafetyof2.Manufacture's onetimeloadcapacityshallbeusedforhydraulic snubbers.
4.0CONCLUSION
Thesecriteriaprovideallowable valuesgreaterthantheFSAR,however,thesevaluesarebasedonthecurrentcodes,standards andpractices applicable tothedesignofNuclearPowerPlants.
5.0REFERENCES
1.AmericanSocietyofMechanical Engineers (ASME),BoilerandPressureVesselCodes,SectionIII,1983edition.2.ASMEcodecaseN-411(Approval dateFebruary20,1986)3.~"SteelConstruction Manual",AmericanInstitute ofSteelConstruction 4.DonaldC.CookNuclearPlant,updatedFinalSafetyAnalysisReport(FSAR)
