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| {{#Wiki_filter:~CATEGORY1REGULATORYINFORMATIONDISTRIBUTIONSYSTEM(RIDS)ACCESSIONNBR:9802120302DOC.DATE:98/Ol/30NOTARIZED:YESDOCKETFACIL:50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-~16D'onaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.EIndianaMichiganPowerCo.RECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk) | | {{#Wiki_filter:~CATEGORY1REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9802120302 DOC.DATE: |
| | 98/Ol/30NOTARIZED: |
| | YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-~16D'onaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E IndianaMichiganPowerCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) |
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| SubmitsGL97-04,"AssuranceofSufficientNetPositiveSuctionHeadforECCEcContainmentHeatRemovalPumps."DISTRIBUTIONCODE:A076DCOPIESRECEIVED:L'VRENCLSIZE:TITLE:GL97-04AssuranceofSufficientNet>PositiveSuctionHeadForNOTES:Emerg~ERECIPIENTIDCODE/NAMEPD3-3PDCOPIESRECIPIENTLTTRENCLIDCODE/NAME11"HICKMAN,JCOPIESLTTRENCL110INTERNAL:LECENTENRRSSA/SRXBEXTERNAL:NOAC111.111NRR/DSSA/SCSBNRR/PD3-2NRCPDR112211D0UENNOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATIONREMOVEDFROMDISTRIBUTIONLISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION,CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION415-2083TOTALNUMBEROFCOPIESREQUIRED:LTTR9ENCL9 a~ft,~i'4f,pVI' IndianaMichiganPowerCompany500CircleDriveBuchanan,Ml491071395January30,1998AEP:NRC:1280ADocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555-0001Gentlemen:DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR-74REQUESTEDINFORMATION-GENERICLETTER(GL)97-04ASSURANCEOFSUFFICIENTNETPOSITIVESUCTIONHEADFOREMERGENCYCORECOOLINGANDCONTAINMENTHEATREMOVALPUMPSOnOctober7,1997,theNuclearRegulatoryCommission(NRC)issuedGL97-04,"AssuranceofSufficientNetPositiveSuctionHeadforEmergencyCoreCoolingandContainmentHeatRemovalPumps",indicatingthatadequatenetpositivesuctionheadmaynotbeavailabletotheemergencycorecoolingsystemandcontainmentspraypumpsunderalldesignbasisaccidentscenarios.TheattachmenttothislettercontainsourresponsetotheinformationrequestedinGL97-04."'.E.E.FitzpatrickVicePresident'rt,,SWORNTOANDSUBSCRIBEDBEFOREMEghTHIS~DAYOF~+~4,1998NotaryPublic//vlbAttachmentUNDAL8OEi.CKENotaryPublic,8errienCaunty,MlMyCommissionExpiresJanuary21,2001J.A.AbramsonA.B.BeachMDEQ-DW&RPDNRCResidentInspectorJ.R.Sampson9802i20302'st80i30PDRADQCK050003i5PPDRllllllllllllllllllllllllllllIlllllllll li"l ATTACHMENTTOAEP:NRC:1280AREQUESTEDINFORMATION-GENERICLETTER(97-04),ASSURANCEOFSUFFICIENTNETPOSITIVESUCTIONHEADFOREMERGENCYCORECOOLINGANDCONTAINMENTHEATREMOVALPUMPSa'pl%llh\' | | SubmitsGL97-04,"Assurance ofSufficient NetPositiveSuctionHeadforECCEcContainment HeatRemovalPumps."DISTRIBUTION CODE:A076DCOPIESRECEIVED:L'VR ENCLSIZE:TITLE:GL97-04Assurance ofSufficient Net>Positive SuctionHeadForNOTES:Emerg~ERECIPIENT IDCODE/NAME PD3-3PDCOPIESRECIPIENT LTTRENCLIDCODE/NAME 11"HICKMAN,J COPIESLTTRENCL110INTERNAL: |
| AttachmenttoAEP:NRC:1280APage1Followingisourresponsetotheinformationrequestedingenericletter(GL)97-04,"AssuranceofSufficientNetPositiveSuctionHeadforEmergencyCoreCoolingandContainmentHeatRemovalPumps",datedOctober7,1997.GL97-04REVESTNO.1"SpecifythegeneralmethodologyusedtocalculatetheheadlossassociatedwiththeECCSsuctionstrainers."OURRESPONSETOREVESTNO.1Theemergencycorecoolingsystem(ECCS)suctionstrainersatCookNuclearPlantconsistofgratingandscreensattheinlettothecontainmentrecirculationsump.Thesumpdesignincludestwolayersofcoarsegratingatthesumpentrancethatsandwichasinglelayerof1/4"finemeshscreen.Thenetpositivesuctionhead(NPSH)calculationfortheECCSandcontainmentspray(CTS)pumpsassumesaheadlossof1ft.acrossthecontainmentrecirculationsumpataflowof15,600gpm.Thisheadlossrepresentslossesfromupstreamoftheouterlayerofgrating,throughthesump,andintothepipesatthesumpexit.Theassumedheadlossisbasedonempiricaldatafromsumpmodeltesting,plusconservatism.Ourcontainmentrecirculationsumpdesignwasmodeltestedduringthelate1970satAldenResearchLaboratorytostudyvortexingandairentrainment.TheresultsfromthemodeltestingweresubmittedtotheNRCinourletterAEP:NRC:00112,datedDecember20,1978.Aby-productfromthemodeltesting,whichincludedtestingforvarious"plateblockage"schemesatthesumpentrance,wasempiricalheadlossdataacrosstheentiresumpatminimumwaterlevel,elevation602'-10".Sumpentryscreenblockageofupto50%wasmodeled.Losscoefficientsweredeterminedforvarioustestschemes,andarerepresentedbytheequation:h~Cq=".y'2gwhere:Cghvgdimensionlesslosscoefficienttheheadlossinft.fluidvelocityatthesumpexitpipes32.2ft./sec.'osscoefficientdatafromtable10oftheAldenLaboratorytestreport,whenusedwiththeaboveequation,indicatedthatthehighestobservedheadlossacrossthesumpwas0.77ft.Maximumflowduringsumpmodeltestingwas15,400gpm,7,700gpmpersumpoutletpipe,whichcompareswelltoamaximumexpectedflowof15,600gpmpercurrentcalculations.Thisdifferenceinflowwasconsideredinsignificantindeterminingheadlossacrossthesumpinletandthroughthesump.Theas-modeledsumpdesignincludedasinglecoarsegratingandasinglefinemeshscreen.AldenLaboratoryalsoprovidedheadlossdataforlossesacrossthegratingandscreen.Becausethecurrentsumpentranceincludestwolayersofcoarsegrating,oneupstreamandonedownstreamofthefinemeshscreen,theheadlossacrossthegratingandscreenwascountedtwicetoconservativelyaccountforthesecondgrating.
| | LECENTENRRSSA/SRXBEXTERNAL: |
| IIAttachmenttoAEP:NRC:1280APage2Basedontheheadlossthroughthesumpof0.77ft.intheas-modeledconfiguration,andaheadlossof0.052ft.acrossthesecondgrating,thecurrentNPSHcalculationconservativelyassumesa1ft.headlossacrossthesump.Althoughthesumpheadlossdataaboveincludeslossesfromupstreamofthesumpentrancetoinsidethepipesatthesumpexit,entrancelossesatthesumpexitpipeswerealsocalculatedseparatelyandincludedintheNPSHcalculationsforconservatism.GL97-04REVESTNO.2"IdentifytherequiredNPSHandtheavailableNPSH."OURRESPONSETOREVESTNO.2Thenetpositivesuctionheadrequired(NPSHR)andnetpositivesuctionheadavailable(NPSHA)fortheresidualheatremoval(RHR)andCTSpumps,whichtakesuctiondirectlyfromthecontainmentrecirculationsump,areasfollows:~PumNPSHRNPSHARHRCTS20ft.abs9ft.abs29ft.abs31ft.absAsa"pointofinformation,theNPSHRandNPSHAforthesafetyinjection(SI)andcentrifugalcharging(CC)pumps,whichtakesuctionfromtheRHRpumpswhentheECCSisintherecirculationmodeofoperation,are:~PumSICCNPSHR13ft.abs17ft.absNPSHA122ft.abs48ft.absTheNPSHR,tabulatedabove,wasobtainedfromtheindividualECCSpumpperformancecurvesattheexpectedECCSpumpflow.AvailableNPSH,tabulatedabove,wascalculatedusingthegeneralmethodologydetai'led,below.Asindicated'in,ourresponsetoquestion.No.,l,,'head,lossof1'ft.'a'crossthesump'screhnwasas'sumedin,the.NPSH,calculationat15,600gpm.ThebasicequationforcalculatingNPSHis:NPSH=h,-h,+h-hfdfwhere:h,habsolutepressure,infeetoftheliquidbeingpumped,onthesurfaceoftherecirculationsumplevel,head,infeet,correspondingtothevaporpressureoftherecirculationsumpliquidatthetemperaturebeingpumped,staticheight,infeet,thattherecirculationsumpliquidlevelisaboveorbelowthepumpsuctioncenterlineorimpellereye,and AttachmenttoAEP:NRC:1280APage3h=allfrictionlosses,infeet,includingentrancelossesandfrictionlossesthroughpipe,valves,andfittings,etc.Additionaldetailsoneachoftheabovetermsareprovidedbelow.h,-Absolutepressureonthesurfaceoftherecirculationsumplevel.Thistermisthecontainmentpressureassumedintheanalysis.Becausenocreditistakenforcontainmentoverpressure,atmosphericpressureisusedastheliquid'sabsolutepressure.h,-Headcorrespondingtothevaporpressureoftherecirculationsumpliquidatthetemperaturebeingpumped.Thistermisafunctionofthetemperatureofthefluid.Themaximumexpectedrecirculationsumptemperatureof190'.isused.Thisconservativelyboundsbothunits.h-Staticheightthattherecirculationsumpliquidlevelisaboveorbelowthepumpsuctioncenterlineorimpellereye.Thistermistheminimumstaticheightoffluidabovethepumpcenterline.Aminimumsumpwaterlevelcorrespondingtoelevation602'-10"wasused,whichwasconfirmedviasumpmodeltestingtobealevelthatprecludesairentrainmentandvortexing.Sumpinventorycalculationsconfirmthatthislevelwillbesustainedforpostulatedaccidents.h-Allfrictionlossesincludingentrancelossesandfrictionlossesthroughpipe,valvesandfittings.ThisterminvolvessuctionlinelossesassociatedwiththeECCSpumpbeingevaluated.Theheadlossesconsideredinthistermarefrictionlossesbasedonpiperoughness,pipelength,velocityheadlosses,headlossassociatedwithsumpscreen,entrancelosses,andnumberortypeofvalvesandifittingsinthe,suctionpiping.i~w~,IiQL.97-04REVESTNO.'""Specifywhetherthecurrentdesign-basisNPSHanalysisdiffersfromthemostrecentanalysisreviewedandapprovedbytheNRCforwhichasafetyevaluationwasissued."OURRESPONSETOREVESTNO.3ThecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmittedtotheNRCinthemannerinwhichtheRHRsystemwasanalyzed.ThemostrecentNPSHanalysissubmittedtotheNRCwasprovidedinresponsetoFSARchapter6.3,question212.29(unit2,appendixQ;amendment78,October1977).Question212.29consistedofthreeparts,oneofwhichwasspecifictotheNPSHanalysesfortheECCSpumps.ThisquestionrequesteddetaileddescriptionsoftheNPSHcalculationsfortheECCSpumpsduringpostulatedpostloss-of-coolantaccidentconditions,includingpertinentelevations,limitingpumpandvalvealignmentthatwouldprovidethesmallestNPSHmargin,pumpNPSHrequirements,justificationofthesumpwatertemperature,suctionlinehydrauliclosses,andresultant AttachmenttoAEP:NRC:1280APage4NPSHmargininaccordancewithregulatoryguide1.1.Aspartoftheresponsetothisquestion,acopyoftheNPSHcalculationwasincludedasanattachment.AreviewofthatattachmentindicatesthattheNPSHwascalculatedbasedonthefollowing.Watertemperature,1904F.Containmentpressure,oneatmosphere(absolute)Pumpsoperatingatmaximumflowrateasdeterminedbysystemresistancecalculationsassumingreactorcoolantsystempressureequalto0psigandallaffectedvalvesconsideredwideopen.ThesinglefailurethatwillresultinthelowestNPSHmarginisthefailureofoneRHRpumptooperate.Inthisinstance,theremainingRHRpumpwilloperateatarunoutcondition.Noreactorcoolantwaternoricebedmeltdownisusedtoestablishactivecontainmentsumpwaterinventory.TheNPSHAcalculationsutilizeonlythatportionoftherefuelingwaterstoragetank(RWST)inventorythathasbeenpumpedintothecontainmentpriortotheswitchoverofthefirstECCStrainswitch-overfromRWSTtotheactivecontainmentsump.RHRpumpdischargecrosstievalves,IMO-314andIM0-324,areopenallowingRHRflowfromonepumptoflowthroughbothRHRheatexchangers.Containmentrecirculationsumpdesignincludescoarsegratingatthesumpentranceandfinegrating,perforatedplate,inthesumpbackchamberjustupstxeamofthesumpoutletpipes.ThecurrentdesignbasisNPSHcalculationisbasedonthefollowing.\2.3'.'atertemperature,1904F.Containmentpressure,one,atmosphere(absolute)..IPumpsoperatingasdeterminedbysystemresistancecalculationsassumingreactorcoolantsystempressureequalto0psig,andECCSSIandCCvalvessetasrequiredbytechnicalspecifications.ThesinglefailureappliedisthefailureofoneRHRpumptooperate.Inthisinstance,theremainingRHRpumpwillsupplytwoSIpumpsandtwoCCpumpsthroughasingleRHRheatexchanger(see6below).Reactorcoolantwaterandicebedmeltdownisusedtoestablishactivecontainmentsumpwaterinventory.Thischangewasdeterminedtobeanunreviewedsafetyquestion.AlicenseamendmenthasbeenissuedinresponsetooursubmittalAEP:NRC:0900K,datedOctober8,1997.RHRpumpdischargecrosstievalvesareclosedasrequiredbyourprocedureOHP4023.ES-1.3,"TransfertoColdLegRecirculation".TheRHRpumpdischargecrosstievalvesarenormallyclosedtoprecludedead-headingofaweakerRHRpump.
| | NOAC111.111NRR/DSSA/SCSB NRR/PD3-2 NRCPDR112211D0UENNOTETOALL"RIDS"RECIPIENTS: |
| AttachmenttoAEP:NRC:1280APage5ContainmentrecirculationsumpdesignasmodifiedtoincorporaterecommendationsfromsumpmodeltestingbyAldenResearchLaboratory.Modifiedsumpdesignincludestwolayersofgratingthatsandwichasinglelayeroffinemeshscreen,atthesumpentrance.Finegratingandperforatedplateinthesumpbackchamberwereremoved.Therefore,thecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmittedtotheNRCasindicatedbythedifferencesbetweenitems3,4,5,6,and7above.GL97-04REVESTNO.4"Specifywhethercontainmentoverpressure(i.e.,containmentpressureabovethevaporpressureofthesumporsuppressionpoolfluid)wascreditedinthecalculationofavailableNPSH.Specifytheamountofoverpressureneededandtheminimumoverpressureavailable."OURRESPONSETOREVESTNO.4CreditwasnottakenforthecontainmentpressureindeterminingtheNPSHavailabletotheECCSpumps.ThecontainmentpressureusedindeterminingtheNPSHavailableisoneatmosphere,absolute.NooverpressureorminimumoverpressurewasusedindeterminingtheavailableNPSH.GL97-04REUESTNO.5"WhencontainmentoverpressureiscreditedinthecalculationofavailableNPSH,confirmthatanappropriatecontainmentpressureanalysiswasdonetoestablishtheminimumcontainmentpressure."OURRESPONSETOREVESTNO.5CreditisnottakenforcontainmentoverpressurepressureindeterminingtheNPSHavailabletotheECCSpumps.ThecontainmentpressureusedindeterminingtheNPSHavailableisoneatmosphere.'Itlll4}}
| | PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR9ENCL9 a~ft,~i'4f,pVI' IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071395 January30,1998AEP:NRC:1280ADocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555-0001 Gentlemen: |
| | DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR-74REQUESTED INFORMATION |
| | -GENERICLETTER(GL)97-04ASSURANCE OFSUFFICIENT NETPOSITIVESUCTIONHEADFOREMERGENCY CORECOOLINGANDCONTAINMENT HEATREMOVALPUMPSOnOctober7,1997,theNuclearRegulatory Commission (NRC)issuedGL97-04,"Assurance ofSufficient NetPositiveSuctionHeadforEmergency CoreCoolingandContainment HeatRemovalPumps",indicating thatadequatenetpositivesuctionheadmaynotbeavailable totheemergency corecoolingsystemandcontainment spraypumpsunderalldesignbasisaccidentscenarios. |
| | Theattachment tothislettercontainsourresponsetotheinformation requested inGL97-04."'.E.E.Fitzpatrick VicePresident |
| | 'rt,,SWORNTOANDSUBSCRIBED BEFOREMEghTHIS~DAYOF~+~4,1998NotaryPublic//vlbAttachment UNDAL8OEi.CKENotaryPublic,8errienCaunty,MlMyCommission ExpiresJanuary21,2001J.A.AbramsonA.B.BeachMDEQ-DW&RPDNRCResidentInspector J.R.Sampson9802i20302'st80i30 PDRADQCK050003i5PPDRllllllllllllllllllllllllllllIll lllllll li"l ATTACHMENT TOAEP:NRC:1280A REQUESTED INFORMATION |
| | -GENERICLETTER(97-04),ASSURANCE OFSUFFICIENT NETPOSITIVESUCTIONHEADFOREMERGENCY CORECOOLINGANDCONTAINMENT HEATREMOVALPUMPSa'pl%llh\' |
| | Attachment toAEP:NRC:1280A Page1Following isourresponsetotheinformation requested ingenericletter(GL)97-04,"Assurance ofSufficient NetPositiveSuctionHeadforEmergency CoreCoolingandContainment HeatRemovalPumps",datedOctober7,1997.GL97-04REVESTNO.1"Specifythegeneralmethodology usedtocalculate theheadlossassociated withtheECCSsuctionstrainers." |
| | OURRESPONSETOREVESTNO.1Theemergency corecoolingsystem(ECCS)suctionstrainers atCookNuclearPlantconsistofgratingandscreensattheinlettothecontainment recirculation sump.Thesumpdesignincludestwolayersofcoarsegratingatthesumpentrancethatsandwichasinglelayerof1/4"finemeshscreen.Thenetpositivesuctionhead(NPSH)calculation fortheECCSandcontainment spray(CTS)pumpsassumesaheadlossof1ft.acrossthecontainment recirculation sumpataflowof15,600gpm.Thisheadlossrepresents lossesfromupstreamoftheouterlayerofgrating,throughthesump,andintothepipesatthesumpexit.Theassumedheadlossisbasedonempirical datafromsumpmodeltesting,plusconservatism. |
| | Ourcontainment recirculation sumpdesignwasmodeltestedduringthelate1970satAldenResearchLaboratory tostudyvortexing andairentrainment. |
| | Theresultsfromthemodeltestingweresubmitted totheNRCinourletterAEP:NRC:00112, datedDecember20,1978.Aby-product fromthemodeltesting,whichincludedtestingforvarious"plateblockage" schemesatthesumpentrance, wasempirical headlossdataacrosstheentiresumpatminimumwaterlevel,elevation 602'-10". |
| | Sumpentryscreenblockageofupto50%wasmodeled.Losscoefficients weredetermined forvarioustestschemes,andarerepresented bytheequation: |
| | h~Cq=".y'2gwhere:Cghvgdimensionless losscoefficient theheadlossinft.fluidvelocityatthesumpexitpipes32.2ft./sec.'oss coefficient datafromtable10oftheAldenLaboratory testreport,whenusedwiththeaboveequation, indicated thatthehighestobservedheadlossacrossthesumpwas0.77ft.Maximumflowduringsumpmodeltestingwas15,400gpm,7,700gpmpersumpoutletpipe,whichcompareswelltoamaximumexpectedflowof15,600gpmpercurrentcalculations. |
| | Thisdifference inflowwasconsidered insignificant indetermining headlossacrossthesumpinletandthroughthesump.Theas-modeled sumpdesignincludedasinglecoarsegratingandasinglefinemeshscreen.AldenLaboratory alsoprovidedheadlossdataforlossesacrossthegratingandscreen.Becausethecurrentsumpentranceincludestwolayersofcoarsegrating,oneupstreamandonedownstream ofthefinemeshscreen,theheadlossacrossthegratingandscreenwascountedtwicetoconservatively accountforthesecondgrating. |
| | IIAttachment toAEP:NRC:1280A Page2Basedontheheadlossthroughthesumpof0.77ft.intheas-modeledconfiguration, andaheadlossof0.052ft.acrossthesecondgrating,thecurrentNPSHcalculation conservatively assumesa1ft.headlossacrossthesump.Althoughthesumpheadlossdataaboveincludeslossesfromupstreamofthesumpentrancetoinsidethepipesatthesumpexit,entrancelossesatthesumpexitpipeswerealsocalculated separately andincludedintheNPSHcalculations forconservatism. |
| | GL97-04REVESTNO.2"Identify therequiredNPSHandtheavailable NPSH."OURRESPONSETOREVESTNO.2Thenetpositivesuctionheadrequired(NPSHR)andnetpositivesuctionheadavailable (NPSHA)fortheresidualheatremoval(RHR)andCTSpumps,whichtakesuctiondirectlyfromthecontainment recirculation sump,areasfollows:~PumNPSHRNPSHARHRCTS20ft.abs9ft.abs29ft.abs31ft.absAsa"pointofinformation, theNPSHRandNPSHAforthesafetyinjection (SI)andcentrifugal charging(CC)pumps,whichtakesuctionfromtheRHRpumpswhentheECCSisintherecirculation modeofoperation, are:~PumSICCNPSHR13ft.abs17ft.absNPSHA122ft.abs48ft.absTheNPSHR,tabulated above,wasobtainedfromtheindividual ECCSpumpperformance curvesattheexpectedECCSpumpflow.Available NPSH,tabulated above,wascalculated usingthegeneralmethodology detai'led, below.Asindicated |
| | 'in,ourresponsetoquestion. |
| | No.,l,,'head,lossof1'ft.'a'cross thesump'screhnwasas'sumedin,the.NPSH,calculation at15,600gpm.Thebasicequationforcalculating NPSHis:NPSH=h,-h,+h-hfdfwhere:h,habsolutepressure, infeetoftheliquidbeingpumped,onthesurfaceoftherecirculation sumplevel,head,infeet,corresponding tothevaporpressureoftherecirculation sumpliquidatthetemperature beingpumped,staticheight,infeet,thattherecirculation sumpliquidlevelisaboveorbelowthepumpsuctioncenterline orimpellereye,and Attachment toAEP:NRC:1280A Page3h=allfrictionlosses,infeet,including entrancelossesandfrictionlossesthroughpipe,valves,andfittings, etc.Additional detailsoneachoftheabovetermsareprovidedbelow.h,-Absolutepressureonthesurfaceoftherecirculation sumplevel.Thistermisthecontainment pressureassumedintheanalysis. |
| | Becausenocreditistakenforcontainment overpressure, atmospheric pressureisusedastheliquid'sabsolutepressure. |
| | h,-Headcorresponding tothevaporpressureoftherecirculation sumpliquidatthetemperature beingpumped.Thistermisafunctionofthetemperature ofthefluid.Themaximumexpectedrecirculation sumptemperature of190'.isused.Thisconservatively boundsbothunits.h-Staticheightthattherecirculation sumpliquidlevelisaboveorbelowthepumpsuctioncenterline orimpellereye.Thistermistheminimumstaticheightoffluidabovethepumpcenterline. |
| | Aminimumsumpwaterlevelcorresponding toelevation 602'-10"wasused,whichwasconfirmed viasumpmodeltestingtobealevelthatprecludes airentrainment andvortexing. |
| | Sumpinventory calculations confirmthatthislevelwillbesustained forpostulated accidents. |
| | h-Allfrictionlossesincluding entrancelossesandfrictionlossesthroughpipe,valvesandfittings. |
| | Thisterminvolvessuctionlinelossesassociated withtheECCSpumpbeingevaluated. |
| | Theheadlossesconsidered inthistermarefrictionlossesbasedonpiperoughness, pipelength,velocityheadlosses,headlossassociated withsumpscreen,entrancelosses,andnumberortypeofvalvesandifittings inthe,suctionpiping.i~w~,IiQL.97-04REVESTNO.'""Specifywhetherthecurrentdesign-basis NPSHanalysisdiffersfromthemostrecentanalysisreviewedandapprovedbytheNRCforwhichasafetyevaluation wasissued."OURRESPONSETOREVESTNO.3ThecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmitted totheNRCinthemannerinwhichtheRHRsystemwasanalyzed. |
| | ThemostrecentNPSHanalysissubmitted totheNRCwasprovidedinresponsetoFSARchapter6.3,question212.29(unit2,appendixQ;amendment 78,October1977).Question212.29consisted ofthreeparts,oneofwhichwasspecifictotheNPSHanalysesfortheECCSpumps.Thisquestionrequested detaileddescriptions oftheNPSHcalculations fortheECCSpumpsduringpostulated postloss-of-coolantaccidentconditions, including pertinent elevations, limitingpumpandvalvealignment thatwouldprovidethesmallestNPSHmargin,pumpNPSHrequirements, justificationofthesumpwatertemperature, suctionlinehydraulic losses,andresultant Attachment toAEP:NRC:1280A Page4NPSHmargininaccordance withregulatory guide1.1.Aspartoftheresponsetothisquestion, acopyoftheNPSHcalculation wasincludedasanattachment. |
| | Areviewofthatattachment indicates thattheNPSHwascalculated basedonthefollowing. |
| | Watertemperature, 1904F.Containment |
| | : pressure, oneatmosphere (absolute) |
| | Pumpsoperating atmaximumflowrateasdetermined bysystemresistance calculations assumingreactorcoolantsystempressureequalto0psigandallaffectedvalvesconsidered wideopen.ThesinglefailurethatwillresultinthelowestNPSHmarginisthefailureofoneRHRpumptooperate.Inthisinstance, theremaining RHRpumpwilloperateatarunoutcondition. |
| | Noreactorcoolantwaternoricebedmeltdownisusedtoestablish activecontainment sumpwaterinventory. |
| | TheNPSHAcalculations utilizeonlythatportionoftherefueling waterstoragetank(RWST)inventory thathasbeenpumpedintothecontainment priortotheswitchover ofthefirstECCStrainswitch-over fromRWSTtotheactivecontainment sump.RHRpumpdischarge crosstievalves,IMO-314andIM0-324,areopenallowingRHRflowfromonepumptoflowthroughbothRHRheatexchangers. |
| | Containment recirculation sumpdesignincludescoarsegratingatthesumpentranceandfinegrating,perforated plate,inthesumpbackchamberjustupstxeamofthesumpoutletpipes.ThecurrentdesignbasisNPSHcalculation isbasedonthefollowing.\2.3'.'atertemperature, 1904F.Containment |
| | : pressure, one,atmosphere (absolute).. |
| | IPumpsoperating asdetermined bysystemresistance calculations assumingreactorcoolantsystempressureequalto0psig,andECCSSIandCCvalvessetasrequiredbytechnical specifications. |
| | ThesinglefailureappliedisthefailureofoneRHRpumptooperate.Inthisinstance, theremaining RHRpumpwillsupplytwoSIpumpsandtwoCCpumpsthroughasingleRHRheatexchanger (see6below).Reactorcoolantwaterandicebedmeltdownisusedtoestablish activecontainment sumpwaterinventory. |
| | Thischangewasdetermined tobeanunreviewed safetyquestion. |
| | Alicenseamendment hasbeenissuedinresponsetooursubmittal AEP:NRC:0900K, datedOctober8,1997.RHRpumpdischarge crosstievalvesareclosedasrequiredbyourprocedure OHP4023.ES-1.3, "Transfer toColdLegRecirculation". |
| | TheRHRpumpdischarge crosstievalvesarenormallyclosedtoprecludedead-heading ofaweakerRHRpump. |
| | Attachment toAEP:NRC:1280A Page5Containment recirculation sumpdesignasmodifiedtoincorporate recommendations fromsumpmodeltestingbyAldenResearchLaboratory. |
| | Modifiedsumpdesignincludestwolayersofgratingthatsandwichasinglelayeroffinemeshscreen,atthesumpentrance. |
| | Finegratingandperforated plateinthesumpbackchamberwereremoved.Therefore, thecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmitted totheNRCasindicated bythedifferences betweenitems3,4,5,6,and7above.GL97-04REVESTNO.4"Specifywhethercontainment overpressure (i.e.,containment pressureabovethevaporpressureofthesumporsuppression poolfluid)wascreditedinthecalculation ofavailable NPSH.Specifytheamountofoverpressure neededandtheminimumoverpressure available." |
| | OURRESPONSETOREVESTNO.4Creditwasnottakenforthecontainment pressureindetermining theNPSHavailable totheECCSpumps.Thecontainment pressureusedindetermining theNPSHavailable isoneatmosphere, absolute. |
| | Nooverpressure orminimumoverpressure wasusedindetermining theavailable NPSH.GL97-04REUESTNO.5"Whencontainment overpressure iscreditedinthecalculation ofavailable NPSH,confirmthatanappropriate containment pressureanalysiswasdonetoestablish theminimumcontainment pressure." |
| | OURRESPONSETOREVESTNO.5Creditisnottakenforcontainment overpressure pressureindetermining theNPSHavailable totheECCSpumps.Thecontainment pressureusedindetermining theNPSHavailable isoneatmosphere. |
| | 'Itlll4}} |
Similar Documents at Cook |
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Category:CORRESPONDENCE-LETTERS
MONTHYEARML20217J4721999-10-15015 October 1999
Forwards NRC Physical Security Insp Repts 50-315/99-27 & 50-316/99-27 on 990920-24.Two Violations Noted & Being Treated as Ncvs,Consistent with App C of Enforcement Policy. Areas Examined Exempt from Disclosure,Per 10CFR73.21
IA-99-379, First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety1999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
ML20217D9241999-10-0808 October 1999
First Final Response to FOIA Request for Documents.Documents Listed in App a Being Released in Entirety
ML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML20196K5961999-06-30030 June 1999
Ltr Contract:Task Order 40, DC Cook Extended Sys Regulatory Review Oversight Insp, Under Contract NRC-03-98-021
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML20207A9201999-05-21021 May 1999
Ack Receipt of 990319 Response to Notice of Violation & Proposed Imposition of Civil Penalty .On 981124, Licensee Remitted Check for Payment of Civil Penalties. Licensee Requests for Extension for Response,Granted
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML20205P0591999-04-14014 April 1999
Ninth Partial Response to FOIA Request for Documents.App Records Already Available in Pdr.Records in App T Encl & Being Made Available in Pdr.App U Records Being Released in Part (Ref FOIA Exemption 7).App V Records Withheld Entirely
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
1999-09-30
[Table view]
Category:INCOMING CORRESPONDENCE
MONTHYEARML17335A5511999-10-0707 October 1999
Forwards LER 99-023-00, Inadequate TS Surveillance Testing of ESW Pump ESF Response Time. Commitments Identified in LER Listed
ML20217D9361999-09-30030 September 1999
FOIA Request for Document Re Section 9.7 of SE by Directorate of Licensing,Us Ae Commission in Matter of Indiana & Michigan Electric Co & Indiana & Michigan Power Co,Dc Cook Nuclear Plan,Units 1 & 2
ML17326A1541999-09-20020 September 1999
Provides Notification of Change in Senior Licensed Operator Status.Operating Licenses for CR Smith,License SOP-30159-4 & Tw Welch,License SOP-30654-2 Are No Longer Required & Should Be Withdrawn
ML17326A1261999-09-17017 September 1999
Forwards LER 99-022-00 Re Electrical Bus Degraded Voltage Setpoints Too Low for Safety Related Loads.Listed Commitment Identified in Submittal
ML17326A1441999-09-17017 September 1999
Submits Trace on Second Shipment of Two Plant,Unit 2 Steam Generators.Info Re Shipment Submitted
ML17326A1531999-09-16016 September 1999
Submits Info Pertaining to Plant Proposed Operator Licensing Exam Requirements Through Yr 2003.NRC Form 536, Operator Licensing Exam Data, Which Provides Required Info Encl
ML17326A1101999-08-27027 August 1999
Forwards LER 99-021-00, GL 96-01 Test Requirements Not Met in Surveillance Tests. List of Commitments Identified in LER Provided
ML17326A0991999-08-26026 August 1999
Forwards LER 99-020-00,re EDGs Being Declared Inoperable. Commitments Made by Util Are Listed
ML17326A1221999-08-23023 August 1999
Forwards Revised Page 2 to 1998 Annual Environ Operating Rept, for DC Cook Nuclear Plant,Correcting Omission to App I
ML17326A0981999-08-23023 August 1999
Forwards fitness-for-duty Program Performance Data for Period of 990101-0630 for DC Cook Nuclear Plants,Units 1 & 2,per 10CFR26.71(d)
ML17326A0891999-08-16016 August 1999
Forwards LER 99-019-00,re Victoreen Containment High Range Monitors Not Beign Environmentally Qualified to Withstand post-LOCA Conditions.Commitments Made by Util Are Listed
ML17326A0811999-08-10010 August 1999
Notifies NRC of Changes in Commitments Made in Response to GL 98-01,supplement 1, Yr 2000 Readiness of Computer Sys Ar Npps, Dtd 990623
ML17326A0821999-08-0606 August 1999
Informs That Util Is Submitting Encl Scope & Objectives for 991026 DC Cook Nuclear Plant Emergency Plan Exercise to G Shear of NRC Plant Support Branch.Exercise Will Include Full State & County Participation
ML17326A1451999-08-0404 August 1999
Requests Withholding of WCAP-15246, Control Rod Insertion Following Cold Leg Lbloca.
ML17326A0751999-08-0404 August 1999
Forwards LER 98-029-01, Fuel Handling Area Ventilation Sys Inoperable Due to Original Design Deficiency. Supplemental Rept Represents Extensive Rev to Original LER & Replaces Rept in Entirely.Commitment Listed
ML17326A0721999-07-29029 July 1999
Forwards LER 99-018-00 Re Refueling Water Storage Tank Suction Motor Operated Valves Inoperable,Due to Inadequate Design.Listed Commitments Were Identified in LER
ML17326A0711999-07-27027 July 1999
Responds to 980123 RAI Re NRC GL 87-02, Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors,Unresolved Safety Issue (USI) A-46.
ML17326A0601999-07-22022 July 1999
Forwards UFSAR, IAW 10CFR50.71(e) & Rept of Changes,Tests & Experiments as Required by 10CFR50.59(b)(2) for DC Cook Nuclear Plant,Units 1 & 2.Without UFSAR
ML17326A0631999-07-22022 July 1999
Forwards LER 98-014-03, Response to High-High Containment Pressure Procedure Not Consistent with Analysis of Record. Revised Info Marked by Sidebars in Right Hand Margin. Commitments Made by Util,Listed
ML17326A0311999-07-0101 July 1999
Forwards LER 99-004-01 Re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitments Made by Util Are Listed
ML17326A0281999-06-28028 June 1999
Provides Response to 981116 & 960228 RAIs Re GL 92-01. Revised Pressurized Thermal Shock Evaluation Based on New Weld Chemistry Info & Copy of W Rept WCAP-15074, Evaluation of 1P3571 Weld Metal from Surveillance Programs... Encl
ML17326A0241999-06-23023 June 1999
Responds to GL 98-01,Suppl 1, Y2K Readiness of Computer Sys at Nuclear Power Plants. Y2K Readiness Disclosure for Plant & List of Commitments Encl
ML17326A0121999-06-18018 June 1999
Forwards LER 99-014-00 Re Requirement of TS 4.0.5 Not Met for Boron Injection Tank Bolting.Commitments Identified in Submittal Listed
ML17326A0111999-06-11011 June 1999
Provides Response to NRC RAI Re GL 97-01, Degradation of Crdm/Cedm Nozzle & Other Vessel Closure Head Penetrations.
ML17325B6401999-06-0101 June 1999
Forwards LER 99-013-00 Re Safety Injection & Centrifugal Charging Throttle Valve Cavitation During LOCA Could Lead to ECCS Pump Failure.Listed Commitments Identified in Submittal
ML17325B6281999-06-0101 June 1999
Forwards LER 99-S03-00,re Nonconforming Vital Area Barriers.Commitments Made by Util Are Listed
ML17325B6331999-05-28028 May 1999
Forwards LER 99-S02-00,re Vulnerability in Safeguard Sys That Could Allow Unauthorized or Undetected Access to Protected Area.Commitments Made by Util Are Listed
ML17265A8201999-05-24024 May 1999
Forwards LER 98-037-01,representing Extensive Rev to Original LER & Replacing Rept in Entirety.Listed Commitments Identified in Submittal
ML17325B6111999-05-21021 May 1999
Forwards Annual Radioactive Effluent Release Rept for 980101-1231 for DC Cook Nuclear Plant,Units 1 & 2. Transmittal of Submittal Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17325B6031999-05-21021 May 1999
Provides Response to NRC GL 98-04, Potential for Degradation of ECCS & Containment Spray Sys After LOCA Because of Const & Protective Coating Deficiencies & Foreign Matl in Containment.
ML17325B5971999-05-20020 May 1999
Forwards LER 99-012-00,re Auxiliary Building ESF Ventilation Sys Not Being Capable of Maintaining ESF Room Temps post-accident.Commitment,listed
ML17335A5281999-05-12012 May 1999
Forwards DC Cook Nuclear Plant Fitness for Duty Program Performance Dtd for six-month Period of 980701-1231,IAW 10CFR26.71(d).Info Was Delayed Due to Administrative Error in Regulatory Affairs Dept
ML17335A5271999-05-11011 May 1999
Forwards Details Re Sources & Levels of Insurance Maintained for DC Cook,Units 1 & 2,as of 990401,per 10CFR50.54(w)(3). Info Was Delayed Beyond Required Date Due to Internal Oversight
ML17325B5841999-05-10010 May 1999
Forwards LER 99-002-00 Re TS 4.0.5 Requirements Not Being Met Due to Improperly Performed Test.Commitments Identified in Ler,Listed
ML17325B5871999-05-0707 May 1999
Forwards Current Revs of Expanded Sys Readiness Review (Essr) Implementing Procedures,For Info Purposes to Support Current NRC Insps.Current Esrr Schedule Provided for Info Purposes,Reflecting Revised Target Dates
ML17325B5821999-05-0404 May 1999
Provides Addl Background,Description & Clarification of Previous & Revised Commitments Re UFSAR Revalidation Effort. Commitment Change Involved Alignment of UFSAR Revalidation Program Methodology to Strategy Contained in Current Plan
ML17325B5791999-05-0404 May 1999
Forwards LER 99-011-00,concerning Air Sys for EDG Not Supporting Long Term Operability.Commitments Made by Util Listed
ML17325B5741999-05-0303 May 1999
Forwards LER 99-010-00 Re RCS Leak Detection Sys Sensitivity Not in Accoradnce with Design Requirements.Listed Commitments Identified in Submittal
ML17325B5631999-04-22022 April 1999
Forwards Results of Independent Chemical Evaluations Performed from Sept 1997 Through Feb 1999,re Resolution of Issues Related to License Amend 227
ML17325B5561999-04-16016 April 1999
Forwards LER 99-006-00, Fuel Crane Loads Lifted Over SFP Could Impact Energies Greater than TS Limits, IAW 10CFR50.73.Submittal Was Delayed to Allow for Resolution of Questions.Commitment Made by Licensee,Listed
ML17325B5451999-04-12012 April 1999
Forwards LER 99-009-00 Re as-found RHR Safety Relief Valve Lift Setpoint Greater than TS Limit.Commitments Identified in Submittal Listed
ML17325B5301999-04-0707 April 1999
Forwards LER 99-S01-01, Vulnerability in Locking Mechanism of Four Vital Area Gates, Per 10CFR50.73.Commitments Made by Util,Listed
ML17325B5241999-04-0505 April 1999
Forwards Revs 0 & 1 to Cook Nuclear Plant Restart Plan, Dtd 980307 & 0407.Rev 5 Is Current Cook Nuclear Plant Restart & Supercedes Previous Revs in All Respects
ML17325B5121999-04-0101 April 1999
Forwards LER 99-007-00, Calculations Show That Divider Barrier Between Upper & Lower Containment Vols May Be Overstressed. Commitments Made by Util Are Listed
ML17325B5141999-03-30030 March 1999
Forwards Rept on Status of Decommissioning Funding.Attached Rept Includes Amount of Decommissioning Funds Estimated to Be Required Pursuant to 10CFR50.75(b) & (C)
ML17325B5191999-03-29029 March 1999
Forwards LER 99-001-00,re Degraded Component Cw Flow to Containment Main Steam Line Penetrations.Commitment, Listed
ML20204F6401999-03-19019 March 1999
Responds to NRC 981013 NOV & Proposed Imposition of Civil Penalty.Violations Cited in Subject NOV Were Initially Identified in Referenced Five Insp Repts.Corrective Actions: Ice Condensers Have Been Completely Thawed of Any Blockage
ML17325B4751999-03-18018 March 1999
Forwards LER 99-004-00,re Failure to Perform TS Surveillance Analyses of Reactor Coolant Chemistry with Fuel Removed. Commitment Made by Util,Listed
ML17325B4721999-03-18018 March 1999
Forwards LER 99-005-00,re Reactor Trip Breaker Manual Actuations During Rod Drop Testing Not Previously Reported. Listed Commitments Identified in Submittal
ML17325B4641999-03-17017 March 1999
Withdraws Response to Issue 1 of NRC Cal,Dtd 970919. Comprehensive Design Review Effort in Progress to Validate Resolution of Issue for Future Operation
1999-09-30
[Table view] |
Text
~CATEGORY1REGULATORY INFORMATION DISTRIBUTION SYSTEM(RIDS)ACCESSION NBR:9802120302 DOC.DATE:
98/Ol/30NOTARIZED:
YESDOCKETFACIL:50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-~16D'onaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.E IndianaMichiganPowerCo.RECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
SUBJECT:
SubmitsGL97-04,"Assurance ofSufficient NetPositiveSuctionHeadforECCEcContainment HeatRemovalPumps."DISTRIBUTION CODE:A076DCOPIESRECEIVED:L'VR ENCLSIZE:TITLE:GL97-04Assurance ofSufficient Net>Positive SuctionHeadForNOTES:Emerg~ERECIPIENT IDCODE/NAME PD3-3PDCOPIESRECIPIENT LTTRENCLIDCODE/NAME 11"HICKMAN,J COPIESLTTRENCL110INTERNAL:
LECENTENRRSSA/SRXBEXTERNAL:
NOAC111.111NRR/DSSA/SCSB NRR/PD3-2 NRCPDR112211D0UENNOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE.TOHAVEYOURNAMEORORGANIZATION REMOVEDFROMDISTRIBUTION LISTSORREDUCETHENUMBEROFCOPIESRECEIVEDBYYOUORYOURORGANIZATION, CONTACTTHEDOCUMENTCONTROLDESK(DCD)ONEXTENSION 415-2083TOTALNUMBEROFCOPIESREQUIRED:
LTTR9ENCL9 a~ft,~i'4f,pVI' IndianaMichiganPowerCompany500CircleDriveBuchanan, Ml491071395 January30,1998AEP:NRC:1280ADocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555-0001 Gentlemen:
DonaldC.CookNuclearPlantUnits1and2LICENSENOS.DPR-58ANDDPR-74REQUESTED INFORMATION
-GENERICLETTER(GL)97-04ASSURANCE OFSUFFICIENT NETPOSITIVESUCTIONHEADFOREMERGENCY CORECOOLINGANDCONTAINMENT HEATREMOVALPUMPSOnOctober7,1997,theNuclearRegulatory Commission (NRC)issuedGL97-04,"Assurance ofSufficient NetPositiveSuctionHeadforEmergency CoreCoolingandContainment HeatRemovalPumps",indicating thatadequatenetpositivesuctionheadmaynotbeavailable totheemergency corecoolingsystemandcontainment spraypumpsunderalldesignbasisaccidentscenarios.
Theattachment tothislettercontainsourresponsetotheinformation requested inGL97-04."'.E.E.Fitzpatrick VicePresident
'rt,,SWORNTOANDSUBSCRIBED BEFOREMEghTHIS~DAYOF~+~4,1998NotaryPublic//vlbAttachment UNDAL8OEi.CKENotaryPublic,8errienCaunty,MlMyCommission ExpiresJanuary21,2001J.A.AbramsonA.B.BeachMDEQ-DW&RPDNRCResidentInspector J.R.Sampson9802i20302'st80i30 PDRADQCK050003i5PPDRllllllllllllllllllllllllllllIll lllllll li"l ATTACHMENT TOAEP:NRC:1280A REQUESTED INFORMATION
-GENERICLETTER(97-04),ASSURANCE OFSUFFICIENT NETPOSITIVESUCTIONHEADFOREMERGENCY CORECOOLINGANDCONTAINMENT HEATREMOVALPUMPSa'pl%llh\'
Attachment toAEP:NRC:1280A Page1Following isourresponsetotheinformation requested ingenericletter(GL)97-04,"Assurance ofSufficient NetPositiveSuctionHeadforEmergency CoreCoolingandContainment HeatRemovalPumps",datedOctober7,1997.GL97-04REVESTNO.1"Specifythegeneralmethodology usedtocalculate theheadlossassociated withtheECCSsuctionstrainers."
OURRESPONSETOREVESTNO.1Theemergency corecoolingsystem(ECCS)suctionstrainers atCookNuclearPlantconsistofgratingandscreensattheinlettothecontainment recirculation sump.Thesumpdesignincludestwolayersofcoarsegratingatthesumpentrancethatsandwichasinglelayerof1/4"finemeshscreen.Thenetpositivesuctionhead(NPSH)calculation fortheECCSandcontainment spray(CTS)pumpsassumesaheadlossof1ft.acrossthecontainment recirculation sumpataflowof15,600gpm.Thisheadlossrepresents lossesfromupstreamoftheouterlayerofgrating,throughthesump,andintothepipesatthesumpexit.Theassumedheadlossisbasedonempirical datafromsumpmodeltesting,plusconservatism.
Ourcontainment recirculation sumpdesignwasmodeltestedduringthelate1970satAldenResearchLaboratory tostudyvortexing andairentrainment.
Theresultsfromthemodeltestingweresubmitted totheNRCinourletterAEP:NRC:00112, datedDecember20,1978.Aby-product fromthemodeltesting,whichincludedtestingforvarious"plateblockage" schemesatthesumpentrance, wasempirical headlossdataacrosstheentiresumpatminimumwaterlevel,elevation 602'-10".
Sumpentryscreenblockageofupto50%wasmodeled.Losscoefficients weredetermined forvarioustestschemes,andarerepresented bytheequation:
h~Cq=".y'2gwhere:Cghvgdimensionless losscoefficient theheadlossinft.fluidvelocityatthesumpexitpipes32.2ft./sec.'oss coefficient datafromtable10oftheAldenLaboratory testreport,whenusedwiththeaboveequation, indicated thatthehighestobservedheadlossacrossthesumpwas0.77ft.Maximumflowduringsumpmodeltestingwas15,400gpm,7,700gpmpersumpoutletpipe,whichcompareswelltoamaximumexpectedflowof15,600gpmpercurrentcalculations.
Thisdifference inflowwasconsidered insignificant indetermining headlossacrossthesumpinletandthroughthesump.Theas-modeled sumpdesignincludedasinglecoarsegratingandasinglefinemeshscreen.AldenLaboratory alsoprovidedheadlossdataforlossesacrossthegratingandscreen.Becausethecurrentsumpentranceincludestwolayersofcoarsegrating,oneupstreamandonedownstream ofthefinemeshscreen,theheadlossacrossthegratingandscreenwascountedtwicetoconservatively accountforthesecondgrating.
IIAttachment toAEP:NRC:1280A Page2Basedontheheadlossthroughthesumpof0.77ft.intheas-modeledconfiguration, andaheadlossof0.052ft.acrossthesecondgrating,thecurrentNPSHcalculation conservatively assumesa1ft.headlossacrossthesump.Althoughthesumpheadlossdataaboveincludeslossesfromupstreamofthesumpentrancetoinsidethepipesatthesumpexit,entrancelossesatthesumpexitpipeswerealsocalculated separately andincludedintheNPSHcalculations forconservatism.
GL97-04REVESTNO.2"Identify therequiredNPSHandtheavailable NPSH."OURRESPONSETOREVESTNO.2Thenetpositivesuctionheadrequired(NPSHR)andnetpositivesuctionheadavailable (NPSHA)fortheresidualheatremoval(RHR)andCTSpumps,whichtakesuctiondirectlyfromthecontainment recirculation sump,areasfollows:~PumNPSHRNPSHARHRCTS20ft.abs9ft.abs29ft.abs31ft.absAsa"pointofinformation, theNPSHRandNPSHAforthesafetyinjection (SI)andcentrifugal charging(CC)pumps,whichtakesuctionfromtheRHRpumpswhentheECCSisintherecirculation modeofoperation, are:~PumSICCNPSHR13ft.abs17ft.absNPSHA122ft.abs48ft.absTheNPSHR,tabulated above,wasobtainedfromtheindividual ECCSpumpperformance curvesattheexpectedECCSpumpflow.Available NPSH,tabulated above,wascalculated usingthegeneralmethodology detai'led, below.Asindicated
'in,ourresponsetoquestion.
No.,l,,'head,lossof1'ft.'a'cross thesump'screhnwasas'sumedin,the.NPSH,calculation at15,600gpm.Thebasicequationforcalculating NPSHis:NPSH=h,-h,+h-hfdfwhere:h,habsolutepressure, infeetoftheliquidbeingpumped,onthesurfaceoftherecirculation sumplevel,head,infeet,corresponding tothevaporpressureoftherecirculation sumpliquidatthetemperature beingpumped,staticheight,infeet,thattherecirculation sumpliquidlevelisaboveorbelowthepumpsuctioncenterline orimpellereye,and Attachment toAEP:NRC:1280A Page3h=allfrictionlosses,infeet,including entrancelossesandfrictionlossesthroughpipe,valves,andfittings, etc.Additional detailsoneachoftheabovetermsareprovidedbelow.h,-Absolutepressureonthesurfaceoftherecirculation sumplevel.Thistermisthecontainment pressureassumedintheanalysis.
Becausenocreditistakenforcontainment overpressure, atmospheric pressureisusedastheliquid'sabsolutepressure.
h,-Headcorresponding tothevaporpressureoftherecirculation sumpliquidatthetemperature beingpumped.Thistermisafunctionofthetemperature ofthefluid.Themaximumexpectedrecirculation sumptemperature of190'.isused.Thisconservatively boundsbothunits.h-Staticheightthattherecirculation sumpliquidlevelisaboveorbelowthepumpsuctioncenterline orimpellereye.Thistermistheminimumstaticheightoffluidabovethepumpcenterline.
Aminimumsumpwaterlevelcorresponding toelevation 602'-10"wasused,whichwasconfirmed viasumpmodeltestingtobealevelthatprecludes airentrainment andvortexing.
Sumpinventory calculations confirmthatthislevelwillbesustained forpostulated accidents.
h-Allfrictionlossesincluding entrancelossesandfrictionlossesthroughpipe,valvesandfittings.
Thisterminvolvessuctionlinelossesassociated withtheECCSpumpbeingevaluated.
Theheadlossesconsidered inthistermarefrictionlossesbasedonpiperoughness, pipelength,velocityheadlosses,headlossassociated withsumpscreen,entrancelosses,andnumberortypeofvalvesandifittings inthe,suctionpiping.i~w~,IiQL.97-04REVESTNO.'""Specifywhetherthecurrentdesign-basis NPSHanalysisdiffersfromthemostrecentanalysisreviewedandapprovedbytheNRCforwhichasafetyevaluation wasissued."OURRESPONSETOREVESTNO.3ThecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmitted totheNRCinthemannerinwhichtheRHRsystemwasanalyzed.
ThemostrecentNPSHanalysissubmitted totheNRCwasprovidedinresponsetoFSARchapter6.3,question212.29(unit2,appendixQ;amendment 78,October1977).Question212.29consisted ofthreeparts,oneofwhichwasspecifictotheNPSHanalysesfortheECCSpumps.Thisquestionrequested detaileddescriptions oftheNPSHcalculations fortheECCSpumpsduringpostulated postloss-of-coolantaccidentconditions, including pertinent elevations, limitingpumpandvalvealignment thatwouldprovidethesmallestNPSHmargin,pumpNPSHrequirements, justificationofthesumpwatertemperature, suctionlinehydraulic losses,andresultant Attachment toAEP:NRC:1280A Page4NPSHmargininaccordance withregulatory guide1.1.Aspartoftheresponsetothisquestion, acopyoftheNPSHcalculation wasincludedasanattachment.
Areviewofthatattachment indicates thattheNPSHwascalculated basedonthefollowing.
Watertemperature, 1904F.Containment
- pressure, oneatmosphere (absolute)
Pumpsoperating atmaximumflowrateasdetermined bysystemresistance calculations assumingreactorcoolantsystempressureequalto0psigandallaffectedvalvesconsidered wideopen.ThesinglefailurethatwillresultinthelowestNPSHmarginisthefailureofoneRHRpumptooperate.Inthisinstance, theremaining RHRpumpwilloperateatarunoutcondition.
Noreactorcoolantwaternoricebedmeltdownisusedtoestablish activecontainment sumpwaterinventory.
TheNPSHAcalculations utilizeonlythatportionoftherefueling waterstoragetank(RWST)inventory thathasbeenpumpedintothecontainment priortotheswitchover ofthefirstECCStrainswitch-over fromRWSTtotheactivecontainment sump.RHRpumpdischarge crosstievalves,IMO-314andIM0-324,areopenallowingRHRflowfromonepumptoflowthroughbothRHRheatexchangers.
Containment recirculation sumpdesignincludescoarsegratingatthesumpentranceandfinegrating,perforated plate,inthesumpbackchamberjustupstxeamofthesumpoutletpipes.ThecurrentdesignbasisNPSHcalculation isbasedonthefollowing.\2.3'.'atertemperature, 1904F.Containment
- pressure, one,atmosphere (absolute)..
IPumpsoperating asdetermined bysystemresistance calculations assumingreactorcoolantsystempressureequalto0psig,andECCSSIandCCvalvessetasrequiredbytechnical specifications.
ThesinglefailureappliedisthefailureofoneRHRpumptooperate.Inthisinstance, theremaining RHRpumpwillsupplytwoSIpumpsandtwoCCpumpsthroughasingleRHRheatexchanger (see6below).Reactorcoolantwaterandicebedmeltdownisusedtoestablish activecontainment sumpwaterinventory.
Thischangewasdetermined tobeanunreviewed safetyquestion.
Alicenseamendment hasbeenissuedinresponsetooursubmittal AEP:NRC:0900K, datedOctober8,1997.RHRpumpdischarge crosstievalvesareclosedasrequiredbyourprocedure OHP4023.ES-1.3, "Transfer toColdLegRecirculation".
TheRHRpumpdischarge crosstievalvesarenormallyclosedtoprecludedead-heading ofaweakerRHRpump.
Attachment toAEP:NRC:1280A Page5Containment recirculation sumpdesignasmodifiedtoincorporate recommendations fromsumpmodeltestingbyAldenResearchLaboratory.
Modifiedsumpdesignincludestwolayersofgratingthatsandwichasinglelayeroffinemeshscreen,atthesumpentrance.
Finegratingandperforated plateinthesumpbackchamberwereremoved.Therefore, thecurrentdesignbasisNPSHanalysisdiffersfromthemostrecentanalysissubmitted totheNRCasindicated bythedifferences betweenitems3,4,5,6,and7above.GL97-04REVESTNO.4"Specifywhethercontainment overpressure (i.e.,containment pressureabovethevaporpressureofthesumporsuppression poolfluid)wascreditedinthecalculation ofavailable NPSH.Specifytheamountofoverpressure neededandtheminimumoverpressure available."
OURRESPONSETOREVESTNO.4Creditwasnottakenforthecontainment pressureindetermining theNPSHavailable totheECCSpumps.Thecontainment pressureusedindetermining theNPSHavailable isoneatmosphere, absolute.
Nooverpressure orminimumoverpressure wasusedindetermining theavailable NPSH.GL97-04REUESTNO.5"Whencontainment overpressure iscreditedinthecalculation ofavailable NPSH,confirmthatanappropriate containment pressureanalysiswasdonetoestablish theminimumcontainment pressure."
OURRESPONSETOREVESTNO.5Creditisnottakenforcontainment overpressure pressureindetermining theNPSHavailable totheECCSpumps.Thecontainment pressureusedindetermining theNPSHavailable isoneatmosphere.
'Itlll4
