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| {{#Wiki_filter:CATEGORY1REGULATOINFORMATIONDISTRIBUTIONSYSTEM(RIDS)i"ACCESSIONNBR:960208007'8",DOC.DATE:96/02/01NOTARIZED:YESDOCKETFACIi".50-315DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM,.05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndianaSMichiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk) | | {{#Wiki_filter:CATEGORY1REGULATOINFORMATION DISTRIBUTION SYSTEM(RIDS)i"ACCESSION NBR:960208007'8", |
| | DOC.DATE: |
| | 96/02/01NOTARIZED: |
| | YESDOCKETFACIi".50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM,.05000316 AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E. |
| | IndianaMichiganPowerCo.(formerly IndianaSMichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| Respondsto950925RAIre941116ltrrequestingchangetomintimedelayrequiredaftershutdownformovementofspentfuelfromcoretostorageinspentfuelpool.DISTRIBUTIONCODE:00010COPIESRECEIVED:LTR!ENCLlSIZE:7+TITLE:ORSubmittal:GeneralDistributionNOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JINTERNL:FILECEN~ER~N01RRDRY/HICBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOACCOPIESLTTRENCL11111111111011RECIPIENTIDCODE/NAMEPD3-1PDNRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDRCOPIESLTTRENCL111111111.1NOTETOALL"RIDS"RECIPIENTS:PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESKiROOMOWFN5D-5(EXT.415-2083)TOELIMINATEYOURNAMEFROMDISTRIBUTIONLISTSFORDOCUMENTSYOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL11 0''i' IndianaMichiganPowerCompanyPOBox16631Columbus,OH43216February1,1996lNOIANAMICHlGANPWKRAEP:NRC:1202ADocketNos.:50-31550-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnits1and2REFUELINGOPERATIONSDECAYTIMEUPDATEDANALYSISANDRESPONSETOREQUESTFORADDITIONALINFORMATIONThisletteranditsattachmentsconstitutearesponsetotheSeptember25,1995,requestforadditionalinformationconcerningourNovember16,1994,submittal(AEP:NRC:1202).Ouroriginal,submittalrequestedachangetotheminimumtimedelayrequiredaftershutdownformovementofspentfuelfromthecoretostorageinthespentfuelpool.Attachment1containsourresponsetotherequestforinformation.Attachment2containsarevisedthermal-hydraulicanalysiswhichreflectschangesinoperationalstrategiestoincludelongerfuelcyclesonbothunits,andapotentialincreaseinlicensedpowerforDonaldC.CookNuclearPlantUnit2.Thethermal-hydraulicanalysissummarizedinattachment2superce'desthethermal-hydraulicanalysissubmittedinAEP:NRC:1202.TheclarificationstothespentnuclearfuelpoolstoragerackboralpoisonsurveillanceprogrampresentedinAEP:NRC:1202do,however,remainvalid.Theresultspresentedinattachment2demonstratethatthemaximumbulkspentfuelpoolwatertemperatureisboundedbythe155FpresentedinAEP:NRC:1202fornormaldischargescenerios.Theconclusionsofthenosignificanthazardsconsiderationperformedpursuantto10CFR50.92containedintheoriginalsubmittal,therefore,remainvalid.Incompliancewiththerequirementsof10CFR50.91(b)(l),copiesofthisletteranditsattachmentshavebeentransmittedtoMr.J.R.Padgett,oftheMichiganPublicServiceCommission,andtotheMichiganDepartmentofPublicHealth.0800349602080078'760201PDRADQCK05000315,PPDRpgiI U.S.NuclearRegulatoryCommissionPage2AEP'NRC:1202AThisletterissubmittedpursuantto10CFR50.30(b)and,assuch,anoathstatementisattached.Sincerely,E.E.FitzatrickVicePresidentSWORNTOANDSUBSCRIBEDBEFOREMETHIS@~DAYOF~~1996NoaryPublid-dpitAttachmentsCC:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett ATTACHMENT1TOAEP:NRC1202ARESPONSETOREQUESTFORADDITIONALINFORMATION ATTACHMENT1TOAEP:NRC:1202APage1SWERSTORAIBYThissectioncontainsresponsestoquestionsposedbytheUSNRCinresponsetothepreviouslysubmittedHoltecReportHI-941183.Anyreferencetotablesorfiguresinthissectionrefertothecorrespondingarticlesineithertheoriginallicensingreport(datedJuly26,1991)orHoltecReportHI-941183.Ql.ItisassumedthatthecombinedSFPHxheatloadandevaporativeheatlosses(asshowninTable2.2ofHoltecReportHI-941183)areequivalenttothetotaldecayheatgenerationineachcase,e.g.,CaselASFPHxload30.84E6BTU/Hr.+evaporativelosses3.14E6BTU/Hr.,foratotalof33.98E6BTU/Hr.Ifthisisincorrect,explainwhatthecorrectdecayheatloadisineachcaseandjustifyanydifferences.A1.Yourassumptioniscorrectasstated.ThetotaldecayheatgenerationisequaltothesumoftheSPFHxheatloadandtheevaporativecoolingloss.Q2.Apreliminarycomparisonwasmadeofthedecayheatgeneratedbythe80fuelelementsdepositedinthespentfuelpoolincases1A,1Band2forthedecaytimesshowninTable2.2withsimilarcasesinTable5.5.1ofyourprevioussubmittaldatedJuly26,1991whereinthefuelwaspermittedtodecayfor168inlieuofthedecayperiodof100hourspresentlyrequested.Thatcomparisonshowsdifferencesof2.6to2.7E6BTU/Hr.inlieuofthedifferencesyoushowof0.71to0.86E6BTU/Hr.Justifyyourcalculations.A2.Thereductioninthereactorholdtimewillincreasethedecayheatofthefreshlydischargedfuelassembliesonly,thedecayheatfrompreviouslydischargedfuelsisnotaffectedbythechangeinholdtime.However,thefreshfueldecayheataccountsforlessthan508ofthetotalheatgeneration.Additionally,HoltecReportHI-941183incorporateschangestotherefuelingschedulewhichreducethedecayheatcontributionofthepreviouslydischargedfuel.Refuelingschedulechangesincludedusingactualrefuelingoutagedurationsandassemblydischargeburnups.Actualrefuelingoutagelengthswerelongerthanforecastedandactualassemblydischargeburnupswerelowerthatpreviouslyassumed.Thesefactorstendtodecreasethedecayheatcontributionofthepreviouslydischargedfuel.Thereductioninthedecayheatofthepreviouslydischargedfuelservestolimittheincreaseinthetotaldecayheatgenerationrate.Q3.ExplainwhetheryouhavedeviatedfromTable2.1ofHoltecreportHi-941183inusingthenumberofthosedischarged ATTACHMENT1TOAEP'NRC'1202APage2assembliesanddatesofdischargesincalculatingtheheatgenerationofthespentfuelassembliesstoredinthespentfuelpool.Forexample,youstatedthatyoucalculatedtheheatgenerationfor80fuelassembliesinanormaldischargebatchinlieuof76showninTable2.1.A3.ThedecayheatcalculationsinHoltecReportHI-941183aredevisedtoprovideanupperboundtoanyactualdischargescenarios.ThecalculationofthedecayheatgenerationfromallpreviouslydischargedfuelsisbasedontherefuelingscheduleofTable2.1.However,thenormaldischargebatchfromUnit1containsmoreassembliesthandoesUnit2.Toprovideananalysisthatboundsallnormaldischargescenarios,thefinaldischargebatchsizewasassumedtobetheUnit1batchsizeof80assemblies.Thisassumptionservestoincreasetheconservatismoftheanalysis.4.ProvidethedecayheatgenerationratefortheassembliesdepositedinthepoolforeachdischargecycleusedinyourcalculationsforCases3and4.Ifyoudonotusethedi'schargesandcycleEFPDshowninTable2.1explainthemethodusedand)ustifyitsapplication.A4.Thedecayheatgenerationratesforfuelfromeachpreviousdischargecyclearesummarizedbelow.ItwasconservativelyassumedthattheEFPDforallpreviouslydischargedfuelassemblieswas1260days.CycleUnit1DecayHeat(BTUr)182106184518Unit2DecayHeat(BTUHr)23939128582218934223215519718119899023215530692820441726170229366129788227315930511810287631300294311751325017335871358785 ATTACHMENT1TOAEP:NRC:1202APage3121316171819202122232432441433707734853436119737325738592039978941426143416047214956682077304629818353587853708453847144003924221004679285981761078164Q5.Discussbriefly,youroperationofthespentfuelpooltrainsinanormalreload.A5.Thespentfuelpoolcoolingsystem(SFPCS)isnotdirectlyassociatedwitheitherplantstartup,normaloperation,orshutdown.Itisoperatedwhenthereisaneedtolowerthepoolwatertemperatureorwhenthereisaneedtoclarifyorpurifythepoolwater.Bothsituationsaredependentuponfuelloadingofthepoolandupontheelapsedtimethatthespentfuelhasbeeninthepool.TodateonlyoneSFPCStrainhasbeenneededatanypointintimetokeepthepooltemperaturebelowthehightemperaturealarmsetpointof125F.AnevaluationshallbeperformedpriortoeachfullcoreoffloadtoassurethatoneSFPCStrainissufficienttokeepthepoolbulkwatertemperaturebelowthatwhichisacceptable.
| | Respondsto950925RAIre941116ltrrequesting changetomintimedelayrequiredaftershutdownformovementofspentfuelfromcoretostorageinspentfuelpool.DISTRIBUTION CODE:00010COPIESRECEIVED:LTR |
| ATTACHMENT2TOAEP:NRC:1202AREVISEDSAFETYANALYSISPERFORMEDBYHOLTECINTERNATIONAL}}
| | !ENCLlSIZE:7+TITLE:ORSubmittal: |
| | GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNL:FILECEN~ER~N01 RRDRY/HICBNRR/DSSA/SRXB OGC/HDS2EXTERNAL: |
| | NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL111111111.1NOTETOALL"RIDS"RECIPIENTS: |
| | PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESKiROOMOWFN5D-5(EXT. |
| | 415-2083) |
| | TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR12ENCL11 0''i' IndianaMichiganPowerCompanyPOBox16631Columbus, OH43216February1,1996lNOIANAMICHlGANPWKRAEP:NRC:1202A DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen: |
| | DonaldC.CookNuclearPlantUnits1and2REFUELING OPERATIONS DECAYTIMEUPDATEDANALYSISANDRESPONSETOREQUESTFORADDITIONAL INFORMATION Thisletteranditsattachments constitute aresponsetotheSeptember 25,1995,requestforadditional information concerning ourNovember16,1994,submittal (AEP:NRC:1202). |
| | Ouroriginal, submittal requested achangetotheminimumtimedelayrequiredaftershutdownformovementofspentfuelfromthecoretostorageinthespentfuelpool.Attachment 1containsourresponsetotherequestforinformation. |
| | Attachment 2containsarevisedthermal-hydraulic analysiswhichreflectschangesinoperational strategies toincludelongerfuelcyclesonbothunits,andapotential increaseinlicensedpowerforDonaldC.CookNuclearPlantUnit2.Thethermal-hydraulic analysissummarized inattachment 2superce'des thethermal-hydraulic analysissubmitted inAEP:NRC:1202. |
| | Theclarifications tothespentnuclearfuelpoolstoragerackboralpoisonsurveillance programpresented inAEP:NRC:1202 do,however,remainvalid.Theresultspresented inattachment 2demonstrate thatthemaximumbulkspentfuelpoolwatertemperature isboundedbythe155Fpresented inAEP:NRC:1202 fornormaldischarge scenerios. |
| | Theconclusions ofthenosignificant hazardsconsideration performed pursuantto10CFR50.92contained intheoriginalsubmittal, therefore, remainvalid.Incompliance withtherequirements of10CFR50.91(b)(l), |
| | copiesofthisletteranditsattachments havebeentransmitted toMr.J.R.Padgett,oftheMichiganPublicServiceCommission, andtotheMichiganDepartment ofPublicHealth.0800349602080078 |
| | '760201PDRADQCK05000315, PPDRpgiI U.S.NuclearRegulatory Commission Page2AEP'NRC:1202A Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached. |
| | Sincerely, E.E.FitzatrickVicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS@~DAYOF~~1996NoaryPublid-dpitAttachments CC:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector |
| | -BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC1202ARESPONSETOREQUESTFORADDITIONAL INFORMATION ATTACHMENT 1TOAEP:NRC:1202A Page1SWERSTORAIBYThissectioncontainsresponses toquestions posedbytheUSNRCinresponsetothepreviously submitted HoltecReportHI-941183. |
| | Anyreference totablesorfiguresinthissectionrefertothecorresponding articlesineithertheoriginallicensing report(datedJuly26,1991)orHoltecReportHI-941183. |
| | Ql.ItisassumedthatthecombinedSFPHxheatloadandevaporative heatlosses(asshowninTable2.2ofHoltecReportHI-941183) areequivalent tothetotaldecayheatgeneration ineachcase,e.g.,CaselASFPHxload30.84E6BTU/Hr.+evaporative losses3.14E6BTU/Hr.,foratotalof33.98E6BTU/Hr.Ifthisisincorrect, explainwhatthecorrectdecayheatloadisineachcaseandjustifyanydifferences. |
| | A1.Yourassumption iscorrectasstated.Thetotaldecayheatgeneration isequaltothesumoftheSPFHxheatloadandtheevaporative coolingloss.Q2.Apreliminary comparison wasmadeofthedecayheatgenerated bythe80fuelelementsdeposited inthespentfuelpoolincases1A,1Band2forthedecaytimesshowninTable2.2withsimilarcasesinTable5.5.1ofyourprevioussubmittal datedJuly26,1991whereinthefuelwaspermitted todecayfor168inlieuofthedecayperiodof100hourspresently requested. |
| | Thatcomparison showsdifferences of2.6to2.7E6BTU/Hr.inlieuofthedifferences youshowof0.71to0.86E6BTU/Hr.Justifyyourcalculations. |
| | A2.Thereduction inthereactorholdtimewillincreasethedecayheatofthefreshlydischarged fuelassemblies only,thedecayheatfrompreviously discharged fuelsisnotaffectedbythechangeinholdtime.However,thefreshfueldecayheataccountsforlessthan508ofthetotalheatgeneration. |
| | Additionally, HoltecReportHI-941183 incorporates changestotherefueling schedulewhichreducethedecayheatcontribution ofthepreviously discharged fuel.Refueling schedulechangesincludedusingactualrefueling outagedurations andassemblydischarge burnups.Actualrefueling outagelengthswerelongerthanforecasted andactualassemblydischarge burnupswerelowerthatpreviously assumed.Thesefactorstendtodecreasethedecayheatcontribution ofthepreviously discharged fuel.Thereduction inthedecayheatofthepreviously discharged fuelservestolimittheincreaseinthetotaldecayheatgeneration rate.Q3.ExplainwhetheryouhavedeviatedfromTable2.1ofHoltecreportHi-941183 inusingthenumberofthosedischarged ATTACHMENT 1TOAEP'NRC'1202A Page2assemblies anddatesofdischarges incalculating theheatgeneration ofthespentfuelassemblies storedinthespentfuelpool.Forexample,youstatedthatyoucalculated theheatgeneration for80fuelassemblies inanormaldischarge batchinlieuof76showninTable2.1.A3.Thedecayheatcalculations inHoltecReportHI-941183 aredevisedtoprovideanupperboundtoanyactualdischarge scenarios. |
| | Thecalculation ofthedecayheatgeneration fromallpreviously discharged fuelsisbasedontherefueling scheduleofTable2.1.However,thenormaldischarge batchfromUnit1containsmoreassemblies thandoesUnit2.Toprovideananalysisthatboundsallnormaldischarge scenarios, thefinaldischarge batchsizewasassumedtobetheUnit1batchsizeof80assemblies. |
| | Thisassumption servestoincreasetheconservatism oftheanalysis. |
| | 4.Providethedecayheatgeneration ratefortheassemblies deposited inthepoolforeachdischarge cycleusedinyourcalculations forCases3and4.Ifyoudonotusethedi'scharges andcycleEFPDshowninTable2.1explainthemethodusedand)ustifyitsapplication. |
| | A4.Thedecayheatgeneration ratesforfuelfromeachpreviousdischarge cyclearesummarized below.Itwasconservatively assumedthattheEFPDforallpreviously discharged fuelassemblies was1260days.CycleUnit1DecayHeat(BTUr)182106184518Unit2DecayHeat(BTUHr)23939128582218934223215519718119899023215530692820441726170229366129788227315930511810287631300294311751325017335871358785 ATTACHMENT 1TOAEP:NRC:1202A Page3121316171819202122232432441433707734853436119737325738592039978941426143416047214956682077304629818353587853708453847144003924221004679285981761078164Q5.Discussbriefly,youroperation ofthespentfuelpooltrainsinanormalreload.A5.Thespentfuelpoolcoolingsystem(SFPCS)isnotdirectlyassociated witheitherplantstartup,normaloperation, orshutdown. |
| | Itisoperatedwhenthereisaneedtolowerthepoolwatertemperature orwhenthereisaneedtoclarifyorpurifythepoolwater.Bothsituations aredependent uponfuelloadingofthepoolandupontheelapsedtimethatthespentfuelhasbeeninthepool.TodateonlyoneSFPCStrainhasbeenneededatanypointintimetokeepthepooltemperature belowthehightemperature alarmsetpointof125F.Anevaluation shallbeperformed priortoeachfullcoreoffloadtoassurethatoneSFPCStrainissufficient tokeepthepoolbulkwatertemperature belowthatwhichisacceptable. |
| | ATTACHMENT 2TOAEP:NRC:1202A REVISEDSAFETYANALYSISPERFORMED BYHOLTECINTERNATIONAL}} |
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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
CATEGORY1REGULATOINFORMATION DISTRIBUTION SYSTEM(RIDS)i"ACCESSION NBR:960208007'8",
DOC.DATE:
96/02/01NOTARIZED:
YESDOCKETFACIi".50-315 DonaldC.CookNuclearPowerPlant,Unit1,IndianaM0500031550-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM,.05000316 AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichiganPowerCo.(formerly IndianaSMichiganEleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
SUBJECT:
Respondsto950925RAIre941116ltrrequesting changetomintimedelayrequiredaftershutdownformovementofspentfuelfromcoretostorageinspentfuelpool.DISTRIBUTION CODE:00010COPIESRECEIVED:LTR
!ENCLlSIZE:7+TITLE:ORSubmittal:
GeneralDistribution NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J INTERNL:FILECEN~ER~N01 RRDRY/HICBNRR/DSSA/SRXB OGC/HDS2EXTERNAL:
NOACCOPIESLTTRENCL11111111111011RECIPIENT IDCODE/NAME PD3-1PDNRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDRCOPIESLTTRENCL111111111.1NOTETOALL"RIDS"RECIPIENTS:
PLEASEHELPUSTOREDUCEWASTE!CONTACTTHEDOCUMENTCONTROLDESKiROOMOWFN5D-5(EXT.
415-2083)
TOELIMINATE YOURNAMEFROMDISTRIBUTION LISTSFORDOCUMENTS YOUDON'TNEED!TOTALNUMBEROFCOPIESREQUIRED:
LTTR12ENCL11 0i' IndianaMichiganPowerCompanyPOBox16631Columbus, OH43216February1,1996lNOIANAMICHlGANPWKRAEP:NRC:1202A DocketNos.:50-31550-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
DonaldC.CookNuclearPlantUnits1and2REFUELING OPERATIONS DECAYTIMEUPDATEDANALYSISANDRESPONSETOREQUESTFORADDITIONAL INFORMATION Thisletteranditsattachments constitute aresponsetotheSeptember 25,1995,requestforadditional information concerning ourNovember16,1994,submittal (AEP:NRC:1202).
Ouroriginal, submittal requested achangetotheminimumtimedelayrequiredaftershutdownformovementofspentfuelfromthecoretostorageinthespentfuelpool.Attachment 1containsourresponsetotherequestforinformation.
Attachment 2containsarevisedthermal-hydraulic analysiswhichreflectschangesinoperational strategies toincludelongerfuelcyclesonbothunits,andapotential increaseinlicensedpowerforDonaldC.CookNuclearPlantUnit2.Thethermal-hydraulic analysissummarized inattachment 2superce'des thethermal-hydraulic analysissubmitted inAEP:NRC:1202.
Theclarifications tothespentnuclearfuelpoolstoragerackboralpoisonsurveillance programpresented inAEP:NRC:1202 do,however,remainvalid.Theresultspresented inattachment 2demonstrate thatthemaximumbulkspentfuelpoolwatertemperature isboundedbythe155Fpresented inAEP:NRC:1202 fornormaldischarge scenerios.
Theconclusions ofthenosignificant hazardsconsideration performed pursuantto10CFR50.92contained intheoriginalsubmittal, therefore, remainvalid.Incompliance withtherequirements of10CFR50.91(b)(l),
copiesofthisletteranditsattachments havebeentransmitted toMr.J.R.Padgett,oftheMichiganPublicServiceCommission, andtotheMichiganDepartment ofPublicHealth.0800349602080078
'760201PDRADQCK05000315, PPDRpgiI U.S.NuclearRegulatory Commission Page2AEP'NRC:1202A Thisletterissubmitted pursuantto10CFR50.30(b)and,assuch,anoathstatement isattached.
Sincerely, E.E.FitzatrickVicePresident SWORNTOANDSUBSCRIBED BEFOREMETHIS@~DAYOF~~1996NoaryPublid-dpitAttachments CC:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC1202ARESPONSETOREQUESTFORADDITIONAL INFORMATION ATTACHMENT 1TOAEP:NRC:1202A Page1SWERSTORAIBYThissectioncontainsresponses toquestions posedbytheUSNRCinresponsetothepreviously submitted HoltecReportHI-941183.
Anyreference totablesorfiguresinthissectionrefertothecorresponding articlesineithertheoriginallicensing report(datedJuly26,1991)orHoltecReportHI-941183.
Ql.ItisassumedthatthecombinedSFPHxheatloadandevaporative heatlosses(asshowninTable2.2ofHoltecReportHI-941183) areequivalent tothetotaldecayheatgeneration ineachcase,e.g.,CaselASFPHxload30.84E6BTU/Hr.+evaporative losses3.14E6BTU/Hr.,foratotalof33.98E6BTU/Hr.Ifthisisincorrect, explainwhatthecorrectdecayheatloadisineachcaseandjustifyanydifferences.
A1.Yourassumption iscorrectasstated.Thetotaldecayheatgeneration isequaltothesumoftheSPFHxheatloadandtheevaporative coolingloss.Q2.Apreliminary comparison wasmadeofthedecayheatgenerated bythe80fuelelementsdeposited inthespentfuelpoolincases1A,1Band2forthedecaytimesshowninTable2.2withsimilarcasesinTable5.5.1ofyourprevioussubmittal datedJuly26,1991whereinthefuelwaspermitted todecayfor168inlieuofthedecayperiodof100hourspresently requested.
Thatcomparison showsdifferences of2.6to2.7E6BTU/Hr.inlieuofthedifferences youshowof0.71to0.86E6BTU/Hr.Justifyyourcalculations.
A2.Thereduction inthereactorholdtimewillincreasethedecayheatofthefreshlydischarged fuelassemblies only,thedecayheatfrompreviously discharged fuelsisnotaffectedbythechangeinholdtime.However,thefreshfueldecayheataccountsforlessthan508ofthetotalheatgeneration.
Additionally, HoltecReportHI-941183 incorporates changestotherefueling schedulewhichreducethedecayheatcontribution ofthepreviously discharged fuel.Refueling schedulechangesincludedusingactualrefueling outagedurations andassemblydischarge burnups.Actualrefueling outagelengthswerelongerthanforecasted andactualassemblydischarge burnupswerelowerthatpreviously assumed.Thesefactorstendtodecreasethedecayheatcontribution ofthepreviously discharged fuel.Thereduction inthedecayheatofthepreviously discharged fuelservestolimittheincreaseinthetotaldecayheatgeneration rate.Q3.ExplainwhetheryouhavedeviatedfromTable2.1ofHoltecreportHi-941183 inusingthenumberofthosedischarged ATTACHMENT 1TOAEP'NRC'1202A Page2assemblies anddatesofdischarges incalculating theheatgeneration ofthespentfuelassemblies storedinthespentfuelpool.Forexample,youstatedthatyoucalculated theheatgeneration for80fuelassemblies inanormaldischarge batchinlieuof76showninTable2.1.A3.Thedecayheatcalculations inHoltecReportHI-941183 aredevisedtoprovideanupperboundtoanyactualdischarge scenarios.
Thecalculation ofthedecayheatgeneration fromallpreviously discharged fuelsisbasedontherefueling scheduleofTable2.1.However,thenormaldischarge batchfromUnit1containsmoreassemblies thandoesUnit2.Toprovideananalysisthatboundsallnormaldischarge scenarios, thefinaldischarge batchsizewasassumedtobetheUnit1batchsizeof80assemblies.
Thisassumption servestoincreasetheconservatism oftheanalysis.
4.Providethedecayheatgeneration ratefortheassemblies deposited inthepoolforeachdischarge cycleusedinyourcalculations forCases3and4.Ifyoudonotusethedi'scharges andcycleEFPDshowninTable2.1explainthemethodusedand)ustifyitsapplication.
A4.Thedecayheatgeneration ratesforfuelfromeachpreviousdischarge cyclearesummarized below.Itwasconservatively assumedthattheEFPDforallpreviously discharged fuelassemblies was1260days.CycleUnit1DecayHeat(BTUr)182106184518Unit2DecayHeat(BTUHr)23939128582218934223215519718119899023215530692820441726170229366129788227315930511810287631300294311751325017335871358785 ATTACHMENT 1TOAEP:NRC:1202A Page3121316171819202122232432441433707734853436119737325738592039978941426143416047214956682077304629818353587853708453847144003924221004679285981761078164Q5.Discussbriefly,youroperation ofthespentfuelpooltrainsinanormalreload.A5.Thespentfuelpoolcoolingsystem(SFPCS)isnotdirectlyassociated witheitherplantstartup,normaloperation, orshutdown.
Itisoperatedwhenthereisaneedtolowerthepoolwatertemperature orwhenthereisaneedtoclarifyorpurifythepoolwater.Bothsituations aredependent uponfuelloadingofthepoolandupontheelapsedtimethatthespentfuelhasbeeninthepool.TodateonlyoneSFPCStrainhasbeenneededatanypointintimetokeepthepooltemperature belowthehightemperature alarmsetpointof125F.Anevaluation shallbeperformed priortoeachfullcoreoffloadtoassurethatoneSFPCStrainissufficient tokeepthepoolbulkwatertemperature belowthatwhichisacceptable.
ATTACHMENT 2TOAEP:NRC:1202A REVISEDSAFETYANALYSISPERFORMED BYHOLTECINTERNATIONAL
