ML17213B127

Comprehensive Vibration Assessment Program,Final Summary Rept.

ML17213B127
Person / Time
Site:	Saint Lucie
Issue date:	02/28/1983
From:	UHRIG R E FLORIDA POWER & LIGHT CO.
To:
Shared Package
ML17213B125	List: ML17213B124 ML17213B127
References
RTR-NUREG-0843, RTR-NUREG-843 CEN-244(L), NUDOCS 8303150538
Download: ML17213B127 (15)

Text

FloridaPov!er5Ligh>>Co.,St.LuciePlantUnit-.":2DocketHn.50-389CVi-2ee(L}ComprehensiveVibrationAssessmentPrnoramFinalSummarReortFebruary1983Combustion"-ngineering,Inc.:NuclearPou,'erSystemsPowerSystemsGroup!!indsor,Connecticut060958303i50538830310PDRADOCK05000389EPDR

'L~llk>~til TAP>LEOFCO<'lTEl!TS1.ItlTRODUCTI0,'lSUtUQRYANDCO."iCLUSIOl'lS3.VIBRATIOilAiNLYSISPROGRAll4.VISUALIl(SPECTIOilPROGPAW2of9 FloridaPowerandLightCn.,St.LuciePlantUnit;-2ComprehensiveVibrationAssessmentProgramIHTROOUCTIOllTheComprehensiveVibrationAssessmentProgram(CVAP;occasionallyreferredtoasthePrecriticalVibration!lonitoringProgram,PV!1P)reportedhereinsatisfiestheHPCRegulatoryGuide1.20(Reference1),requirementsforverifyingthestructuralintegrityofthereactorintmalsforflowinducedvibrationspriortocommercialoperation.TheCVAPprnvidehconfirmation,baseduponprototypePVhPprograms,ananalyticalprogranandaninspectionprogram,thatthehydraulicexcitationsandstructuralresponsesoZtheFloridaPowerandLight,1St.LuciePlantUnit2reactorinternalsarewithindesignestimatesandareacceptableforallnormalsteadystateandtransientmodesofreactorcoolantpumpoperation.AsstatedinReference2,Section3.9.2.4,theilaineYankeandFortCalhounreactorsaredesignatedjointlyastheValidPrototypefortheSt.LuciePlantUni.2CVAP,withSt.LuciePlantUnit2designatedasa!ion-PrototypeCategory1reactor.Reference3{Section3.9.2.3)statesthatthe.'lRCstaffhasaccept-edtheSt.Lucie2programprovidedthat"theapplicantsubmitsacorrelationoftheSt.Lucie2observedvibrationalcharacteristicswiththeresultsfromtheprototypereactors".Reference1requiresthatanaralysisprogramandameasurementorinspectionprogrambeperformedfortheCVAPfor!!on-PrototypeCateqory1reactors.TheanalysisprogramforSt.LuciePlantUnit2CVAPwasreportedinReference2,Section3.9.2.6.AvisualinspectionprogramwithphotographicdocumentationwasperformedforSt.LuciePlantUnit2inlieuofameasurementprogram.ThisreportsummarizestheresultsoftheSt.LuciePlantUnit2CVAPandprovidesanevaluationofthoseresults.2.SUi!l'!ARYAi'l0CO!lCLUSIOl!STheSt.Lucie2CVAPwassuccessfullycompletedinaccordancewiththerequirementsof.'lRCRegulatoryGuile1.20,Revision2{Reference'1).3of9 Thevibrationanalysisprogram,performedinaccordancewithregulatorypositionC.3.1.1ofReference1,providedsufficientevidencetosupporttheclassificationofSt.Lucie2asNon-Prototype,Category1,withthoValidPrototypedesignatedjointlyasViaineYankeeandFortCalhoun.ComparisonoftheSt.Lucie2resultswiththos.fromtheprototypereactorswasfavorable,nocorrectiveactionwasrequiredandnoindicationswereobservedthatwouldnecessitatereactorintmalsmodificationsonSt.Lucie2.TheSt.Lucie2vibrationinspectionprogram,perfor.",edinaccordancewiththeguidelinesnfreoulatorypositionC.3.1.3andC.2.3ofReference1,includedinspectionsoftheSt.Lucie2reactorinternalsbothpriortoandfollowingpre-corehotfunctionaltesting.Thepre-corehotfunctionaltestingincludedallsteady-stateandtransientmodesofreactorcoolantpumpoperation.Heither,realnordurityfuelassemblieswereinpositionforthetesting.ItwasshownbyanalysisthatthoabsenceoffuelassemblieswouldyieldconservativeresultsfortheCVAP.ofreactorinternals.ThecriticalreactorinternalscomponentwiththelowestnaturalfrequencyistheCoreSupportBarrel(CSB).BasedupontheminimumsignificantresponsefrequencyoftheCSB,thecriticalreactorinternalsconponentswersubjectedtoapproximately8.6X106cycles.ofvibrationduringthepre-corehotfunctionaltesting.t(OTE:RegulatoryGuide1.20Revision2recommends,aminimumof1X196cycles.Theinspectionprogramwasperformedwithoutdeviationfromthespecifiedoperatingconditions.Hounanticipatedobservationsorinspectionanomolieswereencountered.Theinspctionsoft"..eSt.Lucie2reactorinternalsrevealednodefects;evidenceofunacceptablemotion,orexcessiveorunduewear.Theinteriorofthereactorvesselwasvisuallyinspectedafterthepre-corehotfunctionaltestingandfoundtobeabsentofanyloosepartsorforeignmaterial.Insummary,theSt.Lucie2CVAPinspectionprogramwasentirelyconsistentwiththeP'/llPoftheHaineYanf:ee.andFortCalhounreactorsandv)iththeSt.Lucie2CVAPanalysisprogram.EvaluationoftheresultsoftheSt.Lucie2CVAPconcludesthatasignificartmarginof.safetyforthestructulalintegrityoftheSt.Lucie2reactor4of9 V

internalswillbemaintaineddurinoallnormalsteady-stateandtransientconditionsofreactorcoolantpumooperation.VIBRATIO!IAHALYSISPROGR,"JlThef1aineYankeeandFortCalhounreactorstogetherconstituteaValidPrototypeforthepurposeoftheSt.Lucie2CVAP.TheSt.Lucie2Plantreactorin-ternalsconfigurationhassubstantiallythesamearrangement,design,size'ndoperationconditionsastheValidPrototype.Hominaldifferencesinarrangement,design,sizeandoperatingconditionshavebeenshnv!nbytestoranalysistohavenosignificanteffectonthevibratoryresponseandex-citationofthosereactorinternalsimportantto,safety;forthesereasons,theSt.Lucie2reactorisdesignatedWon-Prototype,Category1,fortheCVAP.AsmentionedinReference2,Section3.9.2.4,theoreticalpredictionanalyseswereperformedfor,ilaineYankeo(Reference5)andFortCalhoun(Reference6)toestimatetheamplitude,time,andspatialdependencyofthesteady-stateandtransienthydraulicandstructuralresponsestobeencounteredduringprecriticaltesting.ThePVl/Pforf)aineYankeeandFortCalhoundemonstratethatthetheoreticalpredicationmethodsusedprovidedaccurateestimates1ofthesteady-stateresponseofthecoresupportbarrelsystem,whenrasonablebestestimatevaluesforthemagnitudeoftheinletpressurefluctuationsareused.Itwasconcludedfromtheseprogramsthatflov!,inducedvibrationsofthe!laineYankeeandFortCalhounreactorinternalsarewellwithindesignallowablesandareacceptableforallnormalsteady-state,andtransientflowmodesofreactorcoolantpumpoperation.Reference2,Table3.9-4,presentsasugaryofthesignificanthydraulicandstructuraldesignparametersfortheSt.Lucie2,HaineYankeeandFortCalhounreactordesigns.Theeffectsofthesestructuralandhydraulicparametersontheflov!-inducedvibratoryresponseofthereactorinternalsarepresentedinReference2,Section3.9.2.6,whereitisshownthatthenominaldifferenceshavenosignificanteffectsonthestress1vels.Ingeneral,theanalysisoftheSt.Lucie2Unitdemonstratsthat:A.ThepredictedstructuralresponsesoftheSt.Lucie2reactorinternalsarewellwithindesignallowablesandareacceptableforallnormalsteaRy-stateandtransientflov!modesofprimarycoolantpumpoperation.5of9 Lr

~~B.Theprototypeprecriticalvibrationmonitoringprograms.or)/aineYankeeandFortCalhounadequatelyaccountforthespecificdesignfeaturesoftheSt.Lucie2UnitwhicharesharedbytheValidPrototypereactordesigns.VISUALIl(SPECTIOllPROGRAMTheSt.Lucie2CVAPinspectionprogramwasperformedpertheprocedureofReference4,whichmeetstheintentofregulatorypositionsC.3.1.3andC.2.3ofReference1.Theinspectionprogramincludesphotographicdocument-ationoftheconditionoftheSt.Lucie2reactorin.ernals,bothpriortoandafterpre-corehotfunctionaltesting.Theinspectionwasconductedintwophases.Thefirstphase(baselineinspect-ion)wascompletedonApril22,1982.Thesecondphase(post-hotfunctional,pre-core,inspection)wascompletedonJanuary10,1983.Peference1requiresthatthereactorinternalscriticalcomponentsbesub-jectedtoatleast10cyclesofvibrationpriortotheCVAPfinalinspec,ion,baseduponthecomponent'scomputedminimumsignificantresponsefrequency.TheSt.Lucie2CoreSupportBarrel(CSB)wascalculatedtohavethelowestnaturalfrequencyofthecriticalreactorinternalscomponents.Duringpre-corehotfunctionaltesting,theSt.Lucie2reactorinternalsweresubjectedto1.19X10sec.ofcol'dflow(below350'F)and1.61X106sec,ofhotflow(above350'F).BasedupontheminimumsigniicantresponsefrequencyoftheCSB,theinternalscriticalcomponentsweresubjecttoapproximately8.6X10cyclesofvibration..")eitherrealnorRummyfuelassemblies!vereincludedinthe.hotfunctionaltesting.Thelackoffuelservestoprovidegreaterflowvelocitiesandforcesonreactorinternalscomponentsand,therefore,yieldsconservativeresultsfortheCVAP.Thedetailedinspectionproceduropreparedinaccordancewith'Reference4requiresphotographicdocumentationand'descriptionsofconditionsobservedduringbothphases,inadditiontocommentaryonchangesfromthebaselineinspection.Theinspectionswereperormedandqualityassuredbyqualifiedinspectors.Theinspectionproceduresprovidethetabulationafallreactorinternalscomponentsandlocalareasinspected,whichincludes:6of9 A.Allmajorload-bearingelementsofthereactorinternalsreliedupontnretainthecoresupportstructureinposition.B.Thelateral,vertical,andtorsionalrestraintsprovidedwithinthevessel.C.Thoselockingandboltingcomponentswhosefailurecouldadverselyaffectthes.tructuralintegrityofthereactorinternals.0.Thosesurfacesthatareknowntobenrmaybecomecontactsurfacesduringoperation.E.Thosecriticallocationsnnthereactorinternalcomponentsasidentifiedbythevibrationanalysis.F.Theinteriorofthereactorvesselforevidenceofloosepartsorforeignmatter.Theanalysisprogram(Peference2,Section3.9.2.5)identifiedthecoresupportbarrelupperflangeregiontohavethemaximunstressintensity.Thisregionwas,includedintheSt.Lucie2inspectionstovrifytheresultsofthevib-raionanalysis,thatthemaximumstressintensitiesarebelowallowablestresscriteria.Acomparisonofthebaselinesuraceconditionswiththoseofthepost-hotfunctionalinspec.ionindicatedthatnoabnormallow-inducedvibrationhadoccurredandthatnoreductioninthestructuralintegrityoftheinternalscomponents,closureheadorreactorvesselhadoccurred.Therewereindicat-ionsofnormalamountsofrelativethermalgrowthbetweenthestainlesssteelinternalsandthecarbonsteelvessel.Atareaswherecontactoccurredbetweencoresupportbarrel(CSB)snubbers,guidelugs,andalignmentkeys,littleornowearwasindicated,butclosefi;swereevidentbydiscolorationandsomesurfaceburnishing.Contactbetweenthereactorvessel,upperguidestructureflange,CSBflange,andclosureheadappearedunifnmwithnowear.Allstructuralthreadedfastenersandlockbarsappearedsecureandshowednoindicationsofloading.ThegirthweldsontheCSBallappearedsoundasdidthecoreshroudwelds.Duetolackofindicationofabnormalmovementandcalculationalresultsbasedonpost-hotfunctionaldimensions,itisconcluderlthattheinternalswereprovidedwithadequatelateralan4axialsupport.Inoeneral,allin-ternalscomponentswerefoundtobeinverygoodcondition,theircontact'of9 II areasallappearednormalandasexpectedfollowinghotfUnctional4testingandcomparedfavorablywiththeprototypeinspections.Bof9

QEFEREHCES1."ComprehensiveVibrationAssessmentPrograr.forReactorVesselInternalsDuringPreoperationalandInitialStartupTesting.",IIRCReoulatoryGuide1.20,Revision2,datedhay1976.'I2."FinalSafetyAnalysisReport,St.LuciePlantUnit2",DocketI'!o.50-389.3."SafetyEvaluationReportbytheOfficeof!uclearReactorRegulation,U.S.HuclearRegulatoryCornission,RelatedtotheOperationofSt.LuciePlantUnit2",DocketHo,50-389andHUREG-0843.4."PrecriticalVibrationt'ionitoringProgramStandardProcedureforVisualIn-spectionofReactorVesselInternalsfor3410iypePlants",SpecificationHn.00000-RCE-413,Revision00,dated6/12/805."AnalysisofFlow-InducedVibrations:ilaineYankePrecriticalVibration11onitoringProgramPredictions",CombustionEngineering,Inc.CEHPD-55,.iiay30,1972.6."AnalysisofFlow-InducedVibrations:FortCalhounPrecriticalVibrationI/onitoringProgram",CombustionEngineering,Inc.,CE~!PD-85,January1973.e7."'!aineYankeePrecriticalVibrationilonitoringProgram,FinalReport",CombustionEnginering,Inc.,CE.'IPD-93,February1973.8."OmahaPrecriticalVibrationlionitoringProgram,FinalReport",CombustionEngineering,,Inc.,"0~CEil-70,Iiey1974.9of9 0V(