ML111890413
| ML111890413 | |
| Person / Time | |
|---|---|
| Site: | South Texas |
| Issue date: | 07/06/2011 |
| From: | Wright S South Texas |
| To: | Balwant Singal Plant Licensing Branch IV |
| Singal, B K, NRR/DORL, 301-415-301 | |
| Shared Package | |
| ML111890371 | List: |
| References | |
| TAC ME5358, GSI-191, TAC ME5359 | |
| Download: ML111890413 (8) | |
Text
QuestionsonLOCAFrequencyAnalysis General:
- 1. Howarefailuresthatdontoccuratweldsconsidered?Theseinclude,forexample,ControlRod DriveMechanism(CRDM)failures,pressurizerheatersleevefailures,SteamGenerator(SG)tube ruptures,bottommountedinstrumentation(BMI)nozzlefailures,thermalfatiguefailuresat nozzles,componenttees,andothermixinglocations?
Response:Weplantoaddressnonpiperelatedfailuresandnonweldrelatedfailuresin2012sothe focusin2011istoconsiderpipebreaks.Basedonourunderstandingoftheprevailingdamage mechanismswebelievethatLOCAfrequencieswillbedominatedbyfailuresatweldlocations includingpipetosafeendandnozzlelocations.Howeverconsideringthefactthattherearemany weldsdistributedratheruniformlyoverthepiperunstheweldlocationswillprovideanopportunity toevaluatemanydetailedpipebreaklocations.Itisnotclearthatmovingtheassumedbreak locationsbetweenweldlocationswillhaveasignificantimpactbutifitdoesthenwemayneedto considersuchbreaklocationsintheLOCAfrequencyanalysis.Thisisanissuethatcanbebetter examinedonceanumberofbreaklocationshavebeenfullyanalyzed.Weacknowledgethatwewill eventuallyneedtoincludenonweldeffectsordemonstratewhyaddingthemwillnotberisk significant.AsfarasnonweldandnonpipelocationssuchasCRDMfailuresourapproachto addressingthemhasnotyetbeendefined.SGTRaremodeledinthePRAbutitisnotclearhow tubefailureswouldgenerateanydebris.Oursubmittalwillincludeajustificationofwhichlocations wereconsideredandthosethatwerescreenedoutandwhy.
- 2. HowareLosscoolantAccidents(LOCAs)causedbyoverpressurizationeventssuchaswater hammerorotherPToverpressurizationevents(whichmaycausevesselfailuredueto embrittlement)considered?
Response:ThepotentialforwaterhammerintheClass1pipingwasassessedintheRIISIevaluation anddeterminednotbeacrediblefailuremechanismforLOCAsensitivepiping.ThePRAmodel explicitlyconsidersoverpressurizationduringlossofmainFW+ATWSconditionsandcalculatesa probabilityofvesselfailure.WhilesuchfailuresareinfactmodeledinthePRA,theywillnot contributetotheCHANGEinCDForLERFfromdesignoroperationalchangestoaddressGSI191-coredamagewillbeassumedforthecurrentdesignaswellasthereviseddesignifthevesselfails.
- 3. HowareLOCAscausedbypressurizedthermalshock(PTS)consideredintheanalysis?
Response:ThePRAmodelincludesamodelforPTSinducedvesselfailurefromthermalshockbut again,nocreditistakentojustifycoredamagepreventionfollowingvesselfailure.Our understandingoftheNRCresearchonPTSindicatesthatPTSinducedvesselfailureisnotrisk significantbutevenifitwaswhenthevesselfails,theissueofdebrisformationismootasfarasthe PRAmodelisconcerned.
NOTE:ThemodelconsidersvesselintegrityfollowingoneclassofPTSevents,namelyexcesssteam flowinresponsetoatransient.Forexample,themodelquerieswhetherthevesselintegrityis maintainedfollowingaplanttripandfailurebothoftheturbinetotripandtheMSIVstoclose.PTS orthermaltransientimpactonthereactorvesselisnotincludedinthemediumorlargeLOCAevent models.NUREG1806wouldsuggestthatafutureupdateofthemodelsshouldincludethermal shockchallengesinresponsetomediumandlargeLOCAsorequivalent.
PleasenotethatvesselintegrityisalsoqueriedafteranATWSwithfailureoftheMSIVstoisolate,in whichcasethefailuremechanismofconcernisoverpressurization.Thislogicisincludedinthe generaltransientandsmallLOCAmodelsonly.
- 4. HowarenonpassivesystemLOCAfrequencies(e.g.,InterfacingSystemLOCAs(ISLOCAs),seal LOCAs,activesystemLOCAs)considered?
Response:InterfacingLOCAsareexplicitlymodeledinthePRA.Whentheyoccurthepressure boundaryfailuresareoutsidethecontainmentandnotrelevanttocausingdebrisinducedcore damageinsidethecontainment.ForISLOCAsthecoredamageisduetothediversionofcoolant outsidethecontainment,bypassingthesumps,andinabilitytoestablishrecirculationflow.Seal LOCAsduetoactivefailuresareincludedinthePRAmodelandtheGSI191evaluationwillevaluate thedegreetowhichsuchfailurescangeneratedebris.Iftheyareshowntohavethecapabilityto generatedebris,theywillbeexplicitlyincludedintheanalysis.
- 5. Whenandhowisprobabilisticfracturemechanism(PFM)beingusedtohelpdetermineLOCA frequencyestimates(slide6)?
Response:WehavenoplanstoperformanynewPFManalysisin2011butareleavingopento performsuchcalculationsifneededbasedontheresultsthisyear.Thefocusin2011istoevaluatea widespectrumofcasesthatspantheentireClass1pressureboundary.PFManalysesaremore appropriateformorefocusedevaluationsatspecificandlimitednumberoflocations.Astheproject proceedsandwhenandifitisdeterminedthatsomespecificlocationsareespeciallyimportantand wouldbenefitfromaPFMwewillincludethatbutatthisstageitistooearlytotellwhetherthiswill benecessary.
Uncertainties:
- 1. Howarealeatoryandepistemicuncertaintiesconsideredandseparated(slide5)?
Response:ThealeatoryuncertaintiesarereflectedintheassumptionthatLOCAsoccurasaPoission processsothefrequencyofaLOCAisametricforthealeatoryuncertaintyaboutwhetheraLOCA willoccurornot.TheuncertaintydistributionswedeveloparoundtheLOCAfrequenciesrepresent primarilyepistemicuncertainties.Howeverwerecognizethatseparatingsourcesofuncertaintyinto thesebinsissubjecttoitsownformofuncertaintyandcanbedebated.OurLOCAfrequencymodel ofuncertaintyassumesthattheLOCAfrequencyisametricofaleatoryuncertaintyandthe
uncertaintydistributionwedevelopthatisaroundthatistheepistemictype.Werealizethisisjust amodel.
- 2. luncertaintiesdiscussedinslidesarecharacterizedasepistemicuncertainties.Whatisthebasis forthischaracterization?
Response:Seeaboveresponsetoitem1.
- 3. HowisPIPExpdatabaseusedtoresolveuncertainties(slide6)?Itsunclearfromtheslides.
Response:Wemeantosaythatinformationcontainedinthedatabaseandinsightsdevelopedover manyyearsincollectingandanalyzingthedatahelpstoreducethelevelofuncertaintythatwe expertsinputsinNUREG1829.Inadditionanearlierversionofthesamedatabaseprovideduseful inputtothelastNRCsponsoredprojectonLOCAfrequencies,NUREG/CR5750.Beforesuchdata wascollected,forexamplebackinWash1400,verylittledataonnuclearpipingsystemswaseither generatedoranalyzed.TheentireefforttoimplementRIISIprogramswassupportedbyinsights fromtheservicedata.Anearlyexampleofthekindofapplicationthatthisdatabasehasinreducing uncertaintiesistoguidethejudgmentsonhowtodefinehomogeneousweldpopulationsinto groupsforfailurerateestimation.Knowledgeofthedamagemechanismresponsibleforthe experiencedpipefailuresisessentialforguidingthesejudgments(e.g.needtoseparatebimetallic weldssubjecttoPWSCCfromotherweldsnotsubjecttothisdamagemechanism)
- 4. HowareNUREGs1829andCR5750beingusedtoquantifyepistemicuncertainties(slide6)?
WearepreparingaslidepresentationtouseduringourJuly7conferencecalltowalkthrough examplesofhowweplantousethesereferencestoincorporateepistemicuncertaintiesintothe STPspecificLOCAfrequencies.Tobrieflysummarizeweplantoincorporateinformationfrom NUREG1829toestablishtheuncertaintydistributionparametersofourmodelfortheconditional probabilityofLOCAvs.LOCAcategory.
- 5. WhydoesNihaveuncertainty?Isntthenumberofweldsknown?
Therearetworeasonsforthisuncertainty.Oneisplanttoplantvariability.Eachplanthasa differentnumberofweldsforagivencomponent,therearedifferentnumbersofcoolantloopsin thePWRpopulation(2,3,and4),differentnumberofinterfacingsystemconnectionslikeECCS,etc.
etc.Thesecondreasonisthateventhoughthesenumbersareknownwitheachplants organization,thereareonlypublicallyavailablecountsforsomespecificplants.Basedonalimited samplewhichwillbedocumentedinoursubmittal,planttoplantvariabilityisresponsiblefora factorof2aboveandbelowthebestestimateformanypipeweldcategories.
- 6. Whyistherelittleuncertaintyassociatedwiththenumberoffailures(nikinslide9)?Doesnt littleuncertaintyinthisparameterassumethatdatabasehascompletecoverageofallevents andthatnootherfailureshaveoccurred?
Basedonourexperience,thereisverylittleuncertaintyinpipefailurecountsfortheClass1 pressureboundarybasedonthePIPExpdataandcertainlymuchlessthantheuncertaintyweare assigningtothecomponentexposure.AlsothewholeideaofusingaBayesmethodforestimating failureratesisbasedontheideaofstartingwithapriordistributionthatmodelsaverylarge uncertainty.Inourapproachthepriorsareassumedtobelognormalwithrangefactorsof100.
CalculationofLOCAestimates:
- 1. Howistheintegritymanagementfactor(Iik)calculated(slide8)?IstheMarkovmodelusedto determineIik?
Response:Yes,theMarkovmodelisusedtocalculatethisfactor.Thiscalculationapproachwas workedoutfortheEPRIRIISIandisextensivelydocumentedintheattachedreferences.Thefirst reportontheMarkovmodelisReference[1]andtheinitialpipefailuredatadevelopedforuseof thismodelinReference[2].EPRIsponsoredreviewsofthisworkaredocumentedinReference[3]
whichisincludedasanappendixtoReference[1].Thismodelanddataweredevelopedinitiallyin ordertosupportestimatesinthechangeinCDFandLERFduetochangesinweldselectionsforNDE aspartoftheEPRIRIISIprogram.TheuseoftheMarkovmodeltocalculateinspectionfactorswas firstdocumentedintheEPRIRIISITopicalReportinReference[4].TheNRCsafetyevaluationofthe EPRITopicalReportincludesfindingsthatapprovetheuseofthemodelandthesupportingdatafor theEPRIRIISIevaluations.ThisreviewwassupportedbyanNRCsponsoredreviewoftheMarkov modelandtheBayesfailureratemethodverysimilartowhatweplantouseinthisprojectdoneby LANLinReference[5].Apeerreviewedjournalarticlewithmanyofthemathematicaldetailsofthis methodarefoundinReference[6].
TosummarizetheMarkovmodelisusedtoformulateordinarydifferentialequationswhichare solvedanalyticallyforthetimedependentstateprobabilities.Theinputparametersformodel whicharethecoefficientsoftheODEaredefinedintermsofpipefailuremechanismsthatproduce flaws,leaksandruptures,aswellasparametersforthefrequencyandreliabilityofprogramsto detectleaksandinspectforflaws.Thenfromthesesolutions,analyticalexpressionsareobtained forthehazardrate,whichiskindofatimedependentrateofrupture.Duetotheboundary conditionsoftheequations,thehazardrateincreaseswithplantage(asseeninAppendixDof NUREG1829).Theinspectionfactoristhehazardrateat40years(or60yearsdependingonthe application)duetosomespecificintegritymanagementprogram(combinationofleakinspection andNDE)dividedbythehazardrateatthesametimefortheaveragecomponentwithaverage integritymanagement.
- 2. Therelationshipbetweentheflowchart(slide12)andequations(1)-(3)(slides8and9)is unclear.Pleaseidentifywhichspecifictermsintheequationsarecalculatedbyspecificstepsin theflowchart.
WeplantowalkthroughanexampleinourJuly7presentationwhichwillclarifyeachstepin quantifyingtheLOCAfrequencies.
- 3. Therearemanyquestionsrelatedtotheflowchart(slide12).
- a. Whydoesthenumberofleaksprovideinputtoboththefailurefrequencyand conditionalruptureprobability?
Thenumberofleakscontributestothenumeratorofthefailurerateestimate.Thenumber ofleaksalsocontributestothedenominatoroftheconditionalprobabilityofrupture estimate.
- b. Whereisdegradationmechanism(DM)susceptibilityinEquations(1)-(3)?Howdoesit factorintothoseequations?
Response:Weknowfromtheserviceexperiencethatsomefailuresoccurduetosome specificdamagemechanisms.Wecancalculatetheunconditionalfailureratefromany damagemechanismsimplydividingthenumberoffailuresbythetotalcomponentyearsin theservicedata.ButafterwehaveacompletedRIISIprogramsuchasthecasewithSTP weknowonaweldbyweldbasiswhichweldsaresusceptibletoeachdamagemechanism.
Nowweneedtocalculatetheconditionalfailuregivenweknowtheapplicabledamage mechanism.Forthisweneedanestimateofthefractionofweldsinthedatabasethat producedsomayfailuresduetoeachDMhowmanyaresusceptibletoeachDM.Hencethe fractionfinthedenominatorofEquationmustbeappliedtoestimatetheconditionalfailure rate.Leavingitoutwouldyieldtheunconditionalfailurerate.
WeshallalsoaddressthisquestionintheJuly7meeting.
- c. Whatexpertsarebeingusedtoprovidevariousestimates?Aresameexpertsusedto provideeachdistributionindicatedinfigure?
Response:InthecaseofinformationwebringinfromNUREG1829,itistheexpertpanel fromthatproject.Wemayalsoneedtoincorporateexpertjudgmentsfromourteamthat willbeclearlydocumentedinthesubmittal.
- d. WhydotheDMsusceptibilityestimatesprovideinputtoboththegenericprior distributionandintheBayesupdatedistributions?
Response:Theestimatesofthefractionofweldsinthegenericpopulationthatare susceptibletothedamagemechanismareusedtodeterminetheparametersofthe likelihoodfunctionsfortheBayesupdateofpriordistributionswhichareintendedto representthefailureratesforcomponentssusceptibletothosemechanisms.Theyneedto beconsistent.OurJuly7presentationwillaimtoclarifythis.
- e. How,specifically,istheBayesianupdateofthepriordistributionperformedusingthe threedistributionsgeneratedtoinformtheprior?
Response:Thepriorareassumedtobelognormal.WeuseaPoissonlikelihoodfunctionto update these with one set of data for each hypothesis of weld population and weld
susceptibilityfraction.Thisyieldsseveraldifferentposteriorsthatarecombinedusingwhat isreferredtoasBayesposteriorweighting.WewillexplainthismoreclearlyduringJuly7 presentation.
- f.
HowistheBeliczySchultzcorrelationusedtocreatetheP(RlF)priordistribution?
Response:Asyouknow,thiscorrelationwasusedbyBengtLydellasinputtothis distributionforthebasecaseanalysesinAppendixDofNUREG1829.IntheSTPweplanto basethepriorsforthisdistributionusinginformationfromNUREG1829whichwillbe explainedduringtheJuly7meeting.
- g. HowistheP(RlF)priorupdatedusingBayes?
Response:WeperformaBayesupdateforeachdiscreteLOCAcategory,whichis associatedtoabreaksize.Weuseatruncatedlognormaldistributiontorepresentthe uncertaintyintheconditionalprobabilityofLOCAateachCategoryseparately.Weupdate itwithevidenceofnormally0LOCAsandNfailureswhereNisthenumberoffailuresused tocalculatethecorrespondingfailurerates.WewillshowthisintheJuly7meeting.
- 1. ThecalculationprocedureandtheapplicationoftheMarkovmodelinboththeflowchartand equationsisunclear.Also,information/documentationontheusedofthismodelforotherNRC approvedapplicationsandothernuclearapplicationsshouldbeprovided.Aretheredifferences betweenthemodelbeingusedfortheseestimatesandwhathasbeenapprovedandusedin otherapplications?
Response:Pleaseseetheabovequestionresponseontheinspectionfactorandprovided references.Anydeviationsfrompreviouslyreviewedapplicationswillbefullydocumentedinthe submittalandsupportingreports.
- 2. HowistheMarkovmodeldifferentthanP(RlF)?IsthismodelusedtodetermineP(RlF)?
Response:P(RF)isusedtocalculaterupturefrequencies.Failureratesforflaws,leaks,and rupturesareinputtotheMarkovmodeltodeveloptheintegritymanagementfactors.
- 3. IntheMarkovmodelthereisnoprobabilityofrupturegivennodetectibledamage.Whyisthis termneglected?DoesntthispresumethatISIisperfect?
Response:Thismodelisonlyusedandwillonlybeappliedforrupturesduetodegradation mechanisms.ThereisanotherversionofthemodeldevelopedinReference[1]thatincludes additionaltransitionsforleaksandrupturesabsentadetectableflaw.Thereasonfornotincluding thosetransitionsisthatpipefailuresduetosevereloadingconditionsaremodeledexplicitlybynon LOCAtypeinitiatorsinthePRAmodel.
- 4. Thereareanumberofquestionsrelatedtoslide33
- a. Whatisthebasisofthehazardrate{h(t)}equation?
Response:Thisisstandardreliabilityengineeringtheory.Thehazardrateisdefinedasthe negativeoftherateofchangeofthereliabilityfunction(probabilityofnorupture)divided bythereliabilityfunction.InthisMarkovmodel,thereliabilityisthesumofthestate probabilitiesforsuccess,flaw,andleak.SeeReference[7]forthemathematicaldetails.
- b. Whatisr(t)?
Response:Thisisthereliabilityfunctionreferredtoinitema.
- c. Howish(t)normalized?
Response:Seetheabovequestion/responseontheIntegrityManagementfactor
- d. Whatsensitivityanalysesonh(t)areperformed??
Response:Thisreferstochangingtheassumptionsabout:whetherornotthereisaleak detectionprogramandifthereis,howoftenitisdoneandwhatistheeffectiveprobability ofdetection;andwhetherornotthereisanNDEprogram,andifthereishowoftenitis performedandwhatistheeffectiveprobabilityofdetection.Foreachcombinationofleak detectionandNDEinspectionparameters,adifferentresultisobtained.
Questionsonspecificslides:
- 1. Slide17:WhatisWH(waterhammer)?Yes
- 2. Slide19:
- a. Howareunconditionalfailureratesdetermined?Byleavingfoutofthedenominatorin Equation(3)
- b. Aretheconditionalestimateddeterminedthroughexpertelicitationtodetermine bumpupfactorsfortheunconditionalestimates(i.e.,bumpupofapp.5forthermal fatigue)?Ifnot,howweretheconditionalestimatesdeterminedandwhatdothey mean?NotheresultsoftheRIISIDMevaluationareusedtoresolvedeterministically whichweldsaresubjecttoeachDM
- 3. Slide22:WhatareexcessiveLOCAs?VesselfailuresandmultiplepipebreaksandanyLOCA thatisbeyondthecapabilitiesoftheECCSaccordingtothePRAsuccesscriteria.
- 4. Slide38:WhydoesinspectionstillyyieldapositiveCDFforreactorcoolantpump(RCP)?
Whileitsalowernumberthanifnoinspectionisperformedwhydoesitstilladdrisktothe plant?RCPstandsforreactorcoolantsystempiping.Thereisanincreasebecauseofthefact thatmanyweldswereremovedfromtheRIISIprogram.ThisistypicalinallRIISIprograms.
References
[1] PipingSystemReliabilityandFailureRateEstimationModelsforUseinRiskInformedInService InspectionApplications.EPRI,PaloAlto,CA:1998.TR110161.
[2] PipingSystemFailureRatesandRuptureFrequenciesforUseinRiskInformedInService InspectionApplications.EPRI,PaloAlto,CA:1999.TR111880.
[3] Mosleh,A.andF.Groen,TechnicalReviewoftheMethodologyofEPRITR110161,University ofMarylandreportforEPRI,publishedasanAppendixtoEPRITR110161(Reference[6])
[4] RevisedRiskInformedInServiceInspectionProcedure.EPRI,PaloAlto,CA:1999.TR112657, Rev.BA.
[5] U.S.NuclearRegulatoryCommission,SafetyEvaluationReportRelatedtoRevisedRiskInformed InServiceInspectionEvaluationProcedure:EPRITR112657,Rev.B,July1999,Washington, D.C.,1999.(publishedasaforwardtoTR112657(Reference[9])
[6] Martz,H.,TSA1/99164:Final(Revised)ReviewoftheEPRIProposedMarkov Modeling/BayesianUpdatingMethodologyforUseinRiskInformedInServiceInspectionof PipinginCommercialNuclearPowerPlants,LosAlamosNationalLaboratory,June1999.
[7] Fleming,K.N.,MarkovModelsforEvaluatingRiskInformedInServiceInspectionStrategiesfor NuclearPowerPlantPipingSystems,ReliabilityEngineeringandSystemSafety,Vol.83,No.1, pp.27-45,2004.