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| {{#Wiki_filter:CATEGORYj.REGULAT+INFORMATIONDISTRIBUTIONOZSTEM(RIDE)DISTRIBUTIONCODE:A001DCOPIESRECEIVED:LTRENCLSIZE:TITLE:ORSubmittal:GeneralDistributiontACCESS.:GN-NBR.:9603200113DOC.DATE:96/03/12NOTARIZED:YESDOCKETFACIL:50.-316DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATIONFITZPATRICK,E.IndianaMichiganPowerCo.(formerlyIndiana&Mi'chiganEleRECIP.NAMERECIPIENTAFFILIATIONDocumentControlBranch(DocumentControlDesk) | | {{#Wiki_filter:CATEGORYj.REGULAT+INFORMATION DISTRIBUTIONOZSTEM (RIDE)DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal: |
| | GeneralDistribution tACCESS.:GN |
| | -NBR.:9603200113 DOC.DATE: |
| | 96/03/12NOTARIZED: |
| | YESDOCKETFACIL:50.-316 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E. |
| | IndianaMichiganPowerCo.(formerly Indiana&Mi'chigan EleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk) |
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| ==SUBJECT:== | | ==SUBJECT:== |
| ApplicationforamendtolicenseDPR-74,removingTSsreshutdown6controlrodpositionindicationwhileinmodes3,4S5.NOTES:RECIPIENTIDCODE/NAMEPD3-1LAHICKMAN,JCOPIESLTTRENCL1111RECIPIENTIDCODE/NAMEPD3-1PDCOPIESLTTRENCL11INTERN.gCENTERCBNRR/DSSA/SRXBOGC/HDS2EXTERNAL:NOAC1111111011NRR/DE/EMCBNRR/DSSA/SPLBNUDOCS-ABSTRACTNRCPDR11111111NOTETOALL"RIDSNRECIPIENTS)PLEASEHELPUSTOREDUCEWASTElCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.415"20B3)TOELIMINATEYOURNAMEFROMDXSTRKBUTXONLXSTS"'FORDOCUMENTSYOUDON'TNEEDlTOTALNUMBEROFCOPIESREQUIRED:LTTR12ENCL.11 IndianaMichigan~PowerCompanyPOBox16631Columbus,OH43216INOlANANlCHIGANPOWERMarch12,1996AEP:NRC:1248DocketNos.:50-316U.S.NuclearRegulatoryCommissionATTN:DocumentControlDeskWashington,D.C.20555Gentlemen:DonaldC.CookNuclearPlantUnit2PROPOSEDAMENDMENTTOREMOVETECHNICALSPECIFICATIONS3.1.3.3AND3.10.5,"RODPOSITIONINDICATORCHANNELS-SHUTDOWN,"TOACHIEVECONSISTENCYWITHDONALDC.COOKNUCLEARPLANTUNIT1ANDNUREG-1431.Thisletteranditsattachmentsconstituteanapplicationforamendmenttothetechnicalspecifications(T/Ss)forDonaldC.CookNuclearPlantunit2.Specifically,weareproposingtoremovetheT/Ssrelatedtoshutdownandcontrolrodpositionindicationwhileinmodes3,4,and5.Thefollowingunit2T/Ssareaffected:3.1.3.3and3.10.5andassociatedsurveillancesandbases.TheexistingCookNuclearPlantunit2T/SsrequirethatrodpositionindicationbeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.IfOPERABILITYcannotbeassured,thenumberofcontrolorshutdownrodsthatcanbewithdrawnislimitedtoasinglebankwhileperformingroddroptests.Thisrequirementisoverlyrestrictivesince,duringshutdownmodes,theabilitytoensureadequateshutdownmargincanbecompensatedbyanincreaseintheboronconcentrationofthereactorcoolantsystem.Inadditiontothereductioninunnecessaryrequirements,theproposed,amendmentwouldalsoaligntheaffectedunit2T/Sswiththeunit1T/SsandtheimprovedstandardtechnicalspecificationsissuedbytheNRCasNUREG-1431,Revision1.Attachment1providesadetaileddescriptionoftheproposedchanges,thejustificationforthechanges,andourdeterminationofnosignificanthazardsconsiderationperformedpursuantto10CFR50.92.Attachment2containstheexistingT/Spagesmarked'76032001i39603i2PDRADQCK05000316PPDR00l~
| | Application foramendtolicenseDPR-74,removing TSsreshutdown6controlrodpositionindication whileinmodes3,4S5.NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL11INTERN.gCENTERCBNRR/DSSA/SRXB OGC/HDS2EXTERNAL: |
| U.S.NuclearRegulatoryCommissionPage2AEP:NRC:1248toreflecttheproposedchanges.Attachment3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificantchangeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificantincreaseinindividualorcumulativeoccupationalradiationexposure.TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommitteeandwillbereviewedatthenextregularlyscheduledNuclearSafetyandDesignReviewCommitteemeeting.ItisrequestedthattheproposedamendmentbeapprovedbyApril12,1996insupportoftheupcomingunit2refueling.Incompliancewiththerequirementsof10CFR50.91(b)(1),copiesofthisletteranditsattachmentshavebeentransmittedtotheMichiganPublicServiceCommissionandtotheMichiganDepartmentofPublicHealth.ca~E.E.Fitzpatrick,VicePresidentSWORNTOANDSUBSCRIBEDBEFOREMEotaryPublicpitAttachmentcc:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector-BridgmanJ.R.Padgett ATTACHMENT1TOAEP:NRC:1248DESCRIPTIONANDJUSTIFICATIONOFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDCDCOOKNUCLEARPLANTUNIT2TECHNICALSPECIFICATIONS ATTACHMENTTOAEP:NRC:1248DESCRIPTIONOFCHANGESPage1Thefollowingunit2technicalspecifications(T/S)3.1.3.3and3.10.5andassociatedsurveillancesandbasesareaffectedbytheproposedchange.TS34133DeletetheReactivityControlSystems,PositionIndicatorChannels-Shutdown,LimitingConditionforOperation(3.1.3.3)andtheassociatedsurveillance(4.1.3.3)(page3/41-22).TS3410.5DeletetheSpecialTestException,PositionIndicatorChannelsShutdown,LimitingConditionforOperation(3.10.5)andtheassociatedsurveillances(4.10.5.1and4.10.5.2)(page3/410-5).Also,deletethebasesreferencetoT/S3/4.10.5,PositionIndicatorChannel-Shutdown(pageB3/410-1)IndexDeletereferenceto"PositionIndicatorChannels-Shutdown,"fromthetechnicalspecificationIndex(pageIV).II.JUSTIFICATIONFORCHANGESTheaxialpositionofshutdownrodsandcontrolrodsisdeterminedbytwoseparateandindependentsystems:thebankdemandpositionindicationsystemandtheanalogrodpositionindication(ARPI)system.Thecurrentunit2T/SsrequiretheARPIsystemtobeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.Tosatisfythisrequirement,twosetsofARPIcalibrationsmustbeperformed.OnecalibrationisperformedonanindividualrodbankbasistosatisfytheARPIrequirementsduringroddroptestinginaccordancewithT/S3/4.10.5.Thesecondcalibrationisperformedatthecompletionofthe"bank"calibrationsequencetoensurethattherodsarecalibratedcorrectlytoaddressbankoverlap.Thesecalibrationsareredundantandtimeintensive.Additionally,inmodes3,4,and5,theboronconcentrationinthereactorcoolantsystem(RCS)isincreasedtoensurethatadequateshutdownmargin(SDM)isachievedandmaintainedinaccordancewithexistingCookNuclearPlantT/Ss.Thecalculationusedtoobtain ATTACHMENTTOAEP:NRC:1248Page2therequiredboronconcentrationtakesintoaccounttherelativepositionofthecontrolandshutdownrods.StrictproceduralcontrolsareinplaceatCookNuclearPlanttoensurethatanallrodsoutshutdownmarginismaintainedduringrodpositionindicatorcalibration.Theadjustmentofboronconcentrationtoassureadequateshutdownmargininmodes3,4,and5isalsosupportedbytheImprovedStandardTechnicalSpecifications(ISTS)forWestinghousePlants(NUREG-1431).TheISTSdoesnotcontainaT/Sforrodpositionindicationinmodes3,4,and5;however,thebasespositionforthemodes1and2T/Ssaddresstheshutdownmodesinthefollowingmanner."InshutdownMODES,theOPERABILITYoftheshutdownandcontrolbankshasthepotentialtoaffecttherequiredSDM(shutdownmargin),butthiseffectcanbecompensatedforbyanincreaseintheboronconcentrationoftheReactorCoolantSystem."Therefore,theassurancethatadequateshutdownmarginexistsforanallrodsoutconditioninmodes3,4,and5negatestheneedforrodpositionindicationinthesemodes.Technicalspecification3.10,5isa"specialtestexception"directlytiedtoT/S3.1.3.3.Specifically,itprovidesanexemptionfromthe"positionindicatorchannel-shutdown"requirementsduringroddroptesting.Deletionofthisspecificationisnecessarysincetheprimaryspecification3.1.3.3isbeingdeleted.ItisconcludedthatthedeletionofT/S3.1.3.3,PositionIndicationChannels-Shutdown,doesnotresultinareductioninsafetyastheimpactonshutdownmarginisadequatelycompensatedforbyanincreaseinboronconcentrationthatisconsistentwiththeguidanceofNUREG-1431.III.10CFR5092CRITERIAPer10CFR50.92,thisproposedchangedoesnotinvolveasignificanthazardsconsiderationbecausethechangedoesnot:involveasignificantincreaseintheprobabilityorconsequencesofanaccidentpreviouslyevaluated,2.createthepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated,or3.involveasignificantreductioninamarginofsafety. | | NOAC1111111011NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR11111111NOTETOALL"RIDSNRECIPIENTS |
| Attachment1toAEP:NRC:1248Page3Criterion1TheboronconcentrationinthereactorcoolantsystemwillbehighenoughtoassureadequateSDMinmodes3,4,and5.Thecalculationtoobtaintherequiredboronconcentrationtakesintoaccountthepositionoftherods.Shutdownmarginisassumedasaninitialconditioninthesafetyanalysis.ThesafetyanalysisestablishesaSDMthatensuresspecifiedacceptablefueldesignlimitsarenotexceeded.AslongastheSDMissatisfied,nochangeintheprobabilityorconsequencesofanaccidentpreviouslyevaluatedwillresultfromtheproposeddeletionofthe"positionindicatorshutdown"specification.ItisnotedthatthischangeisconsistentwiththenewISTSapprovedbytheNRCasNUREG-1431,Rev.l.Criterion2TheabilitytoinsertthecontrolandshutdownrodsprovidedbytherodcontrolsystemisnotaffectedbytheOPERABILITYstatusoftheARPIsystem.Asmentionedpreviously,thereactorcoolantsystemboronconcentrationwillbehighenoughtoassureadequateSDMismaintained.Therefore,itisconcludedthattheproposedchangesdonotcreatethepossibilityofanewordifferentkindofaccidentfromanyaccidentpreviouslyevaluated.Criterion3Themarginofsafetyrequirements,arenotaffectedbytheremovalofthisT/S.TherequiredSDMwhichisaninitialconditioninthesafetyanalysis,isunaffectedsincethereactorcoolantsystemboronconcentrationisincreasedtoaddressthe.potential"allrodsout"configuration.Basedontheseconsiderations,itisconcludedthattheproposedchangesdonot'involveasignificantreductioninamarginofsafety.}}
| | )PLEASEHELPUSTOREDUCEWASTElCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT. |
| | 415"20B3) |
| | TOELIMINATE YOURNAMEFROMDXSTRKBUTXON LXSTS"'FORDOCUMENTS YOUDON'TNEEDlTOTALNUMBEROFCOPIESREQUIRED: |
| | LTTR12ENCL.11 IndianaMichigan~PowerCompanyPOBox16631Columbus, OH43216INOlANANlCHIGANPOWERMarch12,1996AEP:NRC:1248 DocketNos.:50-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen: |
| | DonaldC.CookNuclearPlantUnit2PROPOSEDAMENDMENT TOREMOVETECHNICAL SPECIFICATIONS 3.1.3.3AND3.10.5,"RODPOSITIONINDICATOR CHANNELS-SHUTDOWN," |
| | TOACHIEVECONSISTENCY WITHDONALDC.COOKNUCLEARPLANTUNIT1ANDNUREG-1431.Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantunit2.Specifically, weareproposing toremovetheT/Ssrelatedtoshutdownandcontrolrodpositionindication whileinmodes3,4,and5.Thefollowing unit2T/Ssareaffected: |
| | 3.1.3.3and3.10.5andassociated surveillances andbases.TheexistingCookNuclearPlantunit2T/Ssrequirethatrodpositionindication beOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.IfOPERABILITY cannotbeassured,thenumberofcontrolorshutdownrodsthatcanbewithdrawn islimitedtoasinglebankwhileperforming roddroptests.Thisrequirement isoverlyrestrictive since,duringshutdownmodes,theabilitytoensureadequateshutdownmargincanbecompensated byanincreaseintheboronconcentration ofthereactorcoolantsystem.Inadditiontothereduction inunnecessary requirements, theproposed, amendment wouldalsoaligntheaffectedunit2T/Sswiththeunit1T/Ssandtheimprovedstandardtechnical specifications issuedbytheNRCasNUREG-1431, Revision1.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarked'76032001i3 9603i2PDRADQCK05000316PPDR00l~ |
| | U.S.NuclearRegulatory Commission Page2AEP:NRC:1248 toreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure. |
| | TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedatthenextregularly scheduled NuclearSafetyandDesignReviewCommittee meeting.Itisrequested thattheproposedamendment beapprovedbyApril12,1996insupportoftheupcomingunit2refueling. |
| | Incompliance withtherequirements of10CFR50.91(b)(1), |
| | copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.ca~E.E.Fitzpatrick |
| | ,VicePresident SWORNTOANDSUBSCRIBED BEFOREMEotaryPublicpitAttachment cc:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector |
| | -BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC:1248 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDCDCOOKNUCLEARPLANTUNIT2TECHNICAL SPECIFICATIONS ATTACHMENT TOAEP:NRC:1248 DESCRIPTION OFCHANGESPage1Thefollowing unit2technical specifications (T/S)3.1.3.3and3.10.5andassociated surveillances andbasesareaffectedbytheproposedchange.TS34133DeletetheReactivity ControlSystems,PositionIndicator Channels-Shutdown, LimitingCondition forOperation (3.1.3.3) andtheassociated surveillance (4.1.3.3) |
| | (page3/41-22).TS3410.5DeletetheSpecialTestException, PositionIndicator ChannelsShutdown, LimitingCondition forOperation (3.10.5)andtheassociated surveillances (4.10.5.1 and4.10.5.2) |
| | (page3/410-5).Also,deletethebasesreference toT/S3/4.10.5, PositionIndicator Channel-Shutdown(pageB3/410-1)IndexDeletereference to"Position Indicator Channels-Shutdown," |
| | fromthetechnical specification Index(pageIV).II.JUSTIFICATION FORCHANGESTheaxialpositionofshutdownrodsandcontrolrodsisdetermined bytwoseparateandindependent systems:thebankdemandpositionindication systemandtheanalogrodpositionindication (ARPI)system.Thecurrentunit2T/SsrequiretheARPIsystemtobeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.Tosatisfythisrequirement, twosetsofARPIcalibrations mustbeperformed. |
| | Onecalibration isperformed onanindividual rodbankbasistosatisfytheARPIrequirements duringroddroptestinginaccordance withT/S3/4.10.5. |
| | Thesecondcalibration isperformed atthecompletion ofthe"bank"calibration sequencetoensurethattherodsarecalibrated correctly toaddressbankoverlap.Thesecalibrations areredundant andtimeintensive. |
| | Additionally, inmodes3,4,and5,theboronconcentration inthereactorcoolantsystem(RCS)isincreased toensurethatadequateshutdownmargin(SDM)isachievedandmaintained inaccordance withexistingCookNuclearPlantT/Ss.Thecalculation usedtoobtain ATTACHMENT TOAEP:NRC:1248 Page2therequiredboronconcentration takesintoaccounttherelativepositionofthecontrolandshutdownrods.Strictprocedural controlsareinplaceatCookNuclearPlanttoensurethatanallrodsoutshutdownmarginismaintained duringrodpositionindicator calibration. |
| | Theadjustment ofboronconcentration toassureadequateshutdownmargininmodes3,4,and5isalsosupported bytheImprovedStandardTechnical Specifications (ISTS)forWestinghouse Plants(NUREG-1431). |
| | TheISTSdoesnotcontainaT/Sforrodpositionindication inmodes3,4,and5;however,thebasespositionforthemodes1and2T/Ssaddresstheshutdownmodesinthefollowing manner."InshutdownMODES,theOPERABILITY oftheshutdownandcontrolbankshasthepotential toaffecttherequiredSDM(shutdown margin),butthiseffectcanbecompensated forbyanincreaseintheboronconcentration oftheReactorCoolantSystem."Therefore, theassurance thatadequateshutdownmarginexistsforanallrodsoutcondition inmodes3,4,and5negatestheneedforrodpositionindication inthesemodes.Technical specification 3.10,5isa"specialtestexception" directlytiedtoT/S3.1.3.3.Specifically, itprovidesanexemption fromthe"position indicator channel-shutdown" requirements duringroddroptesting.Deletionofthisspecification isnecessary sincetheprimaryspecification 3.1.3.3isbeingdeleted.Itisconcluded thatthedeletionofT/S3.1.3.3,PositionIndication Channels-Shutdown, doesnotresultinareduction insafetyastheimpactonshutdownmarginisadequately compensated forbyanincreaseinboronconcentration thatisconsistent withtheguidanceofNUREG-1431.III.10CFR5092CRITERIAPer10CFR50.92,thisproposedchangedoesnotinvolveasignificant hazardsconsideration becausethechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety. |
| | Attachment 1toAEP:NRC:1248 Page3Criterion 1Theboronconcentration inthereactorcoolantsystemwillbehighenoughtoassureadequateSDMinmodes3,4,and5.Thecalculation toobtaintherequiredboronconcentration takesintoaccountthepositionoftherods.Shutdownmarginisassumedasaninitialcondition inthesafetyanalysis. |
| | Thesafetyanalysisestablishes aSDMthatensuresspecified acceptable fueldesignlimitsarenotexceeded. |
| | AslongastheSDMissatisfied, nochangeintheprobability orconsequences ofanaccidentpreviously evaluated willresultfromtheproposeddeletionofthe"position indicator shutdown" specification. |
| | Itisnotedthatthischangeisconsistent withthenewISTSapprovedbytheNRCasNUREG-1431, Rev.l.Criterion 2TheabilitytoinsertthecontrolandshutdownrodsprovidedbytherodcontrolsystemisnotaffectedbytheOPERABILITY statusoftheARPIsystem.Asmentioned previously, thereactorcoolantsystemboronconcentration willbehighenoughtoassureadequateSDMismaintained. |
| | Therefore, itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated. |
| | Criterion 3Themarginofsafetyrequirements, arenotaffectedbytheremovalofthisT/S.TherequiredSDMwhichisaninitialcondition inthesafetyanalysis, isunaffected sincethereactorcoolantsystemboronconcentration isincreased toaddressthe.potential "allrodsout"configuration. |
| | Basedontheseconsiderations, itisconcluded thattheproposedchangesdonot'involve asignificant reduction inamarginofsafety.}} |
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Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] Category:TEXT-LICENSE APPLICATIONS & PERMITS
MONTHYEARML17335A5551999-10-12012 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.6.2.2.d for Spray Additive Sys to Relocate Details Associated with Acceptance Criteria & Test Parameters to Associated TS Bases ML17335A5591999-10-11011 October 1999 Supplement to Application for Amends to Licenses DPR-58 & DPR-74,replacing Correct TS Pages Inadvertently Included in 990923 Submittal.Attached Pages Also Include Appropriate Administrative Changes ML17335A5411999-10-0101 October 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Containment Recirculation Sump Water Inventory.Calculation & non-proprietary WCAP-15302 Rept Also Encl ML17326A1571999-09-23023 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,involving Movement of Loads in Excess of Design Basis Seismic Capability of Auxiliary Bldg Load Handling Equipment & Structures ML17326A1421999-09-17017 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,to Allow Credit of Rod Cluster Control Assemblies for Cold Leg Large Break LOCA Subcriticality.Ts Pages & non-proprietary Versions of WCAP-15246 Encl.Proprietary Version Withheld ML17326A1161999-09-10010 September 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Surveillance Requirement 4.4.7,TS Tables 4.4-3,3.4-1 & TS Surveillance Requirement 4.11.2.2 Re RCS & Gas Storage Tank Sampling ML17326A0921999-08-17017 August 1999 Application for Amend to License DPR-58,to Change TS 3/4.4.5 & Bases for TS 3/4.4.5,3/4.4.6.2 & 3/4.4.8 to Remove voltage-based Repair Criteria,F* Repair Criteria & Sleeving Methodologies from Unit 1 TS & Clarify Bases Sections ML17325B6041999-05-21021 May 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising Limitations of Positive Reactivity Additions in Several TS Action Statements ML17325B5511999-04-19019 April 1999 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3/4.8.1.2, Electrical Power Systems & Associated Bases to Provide one-time Extension of 18-month Surveillance Interval for Specific SRs ML17335A3661998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,adding TS for Distributed Ignition Sys ML17335A3631998-12-0303 December 1998 Application for Amend to License DPR-58,revising TS 3/4.7.7, Sealed Source Contamination & Associated Bases to Address Testing Requirements for Fission Detectors ML17335A3591998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,making Administrative Changes to Remove Obsolete Info,To Provide Consistency Between Units 1 & 2,to Provide Consistency with Std Tech Specs,To Provide Clarification & to Correct Typos ML17335A3561998-12-0303 December 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.6.5.1, Ice Condenser,Ice Bed & Associated Bases to Reflect Max Ice Condenser Flow Channel Blockage Assumed in Accident Analyses ML17335A2631998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS Containment Sys Bases 3/4.6.1.4 Re Internal Pressure & 3/4.6.1.5 Re Air Temp ML17335A2761998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,placing Tighter Restrictions on Amount of Time RWST Water Level Instrumentation Can Be Out of Svc Before Compensatory Actions Are Required ML17335A2671998-10-0808 October 1998 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 3.4.1.3, RCS - Shutdown & Associated Bases to Provide Separate Requirements for Modes 4 & 5 with Loops Filled & Mode 5 with Loops Not Filled ML17335A2311998-09-14014 September 1998 Application for Amends to Licenses DPR-58 & DPR-74,changing Runout Limits for Safety Injection Pump to 675 Gpm Unless Pump Is Specifically Tested to Higher Flow Rate Not Exceeding 700 Gpm ML17335A1901998-08-28028 August 1998 Application for Amend to License DPR-58,requesting Extension of SG Surveillance,Which TSs Require to Be Performed on or Before 990408,until End of Current Refuel Cycle Currently Scheduled for Mar 2000.W/assessment of SG Degradation & TSs ML17334A7471998-06-10010 June 1998 Application for Amends to Licenses DPR-54 & DPR-78,changing Implementation Date to Reduce Boric Acid Concentration in Boric Acid Storage Sys.Attachment 1 to Ltr Contains Description of Proposed Change & Justification for Change ML17334B7011998-03-0303 March 1998 Application for Amends to TS for Licenses DPR-58 & DPR-74, Removing Word Immediately from Unit 1 Hydrogen Recombiner Surveillance Requirement 4.6.4.2.b.4 & Revising Plants TS 3/4.6.4 Bases ML17334B6561997-10-0808 October 1997 Application for Amends to Licenses DPR-58 & DPR-78,changing TSs 3/4.6.5 & 3/4.5.5 to Increase Both Minimum Required Ice Mass Per Ice Basket & Total Minimum Required Ice Mass. Proprietary Summary of Sump Inventory Calculations,Encl ML17333B0431997-09-19019 September 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Requirement for Automatic Valve Closure Feature on RHR Sys Suction from RCS ML17333A9831997-08-11011 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,allowing Filling of ECCS Accumulators W/O Declaring ECCS Equipment Inoperable ML17335A2101997-08-0101 August 1997 Application for Amends to Licenses DPR-58 & DPR-74,deleting Wording When Secondary Steam Supply Pressure Is Greater than 310 Psig from TS ML17333A8281997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74, Modifying TS 4.7.5.1.e.2 Which Describes Control Room Ventilation Sys Autostart Functions ML17333A8311997-03-26026 March 1997 Application for Amends to Licenses DPR-58 & DPR-74,changing Grammatical Correction to Wording of Unit 2 TS 3.4.8,Action a for Modes 1,2 & 3 & Returning Frequency Requirement to TS 4.7.1.2.c & 4.7.1.2.d That Was Inadvertently Deleted ML17333A7121996-12-20020 December 1996 Application for Amends to Licenses DPR-58 & DPR-74, Requesting Rev of Reactor Coolant Pump Flywheel Insp Frequency ML17334B5941996-07-11011 July 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Support Operation of Unit 2 at Increased Core Rated Thermal Power of 3,588 Mwt.Rev 1 to WCAP-14489, ...Unit 2 3,600 Mwt Uprating Program Licensing Rept Encl ML17334B5901996-06-19019 June 1996 Application for Amend to License DPR-58,addressing Applicable Requirements of NRC GL 95-05, Voltage-Based Repair Criteria for Repair of Westinghouse SG Tubes Affected by Outside Diameter Stress Corrosion Cracking. ML17334B5891996-06-11011 June 1996 Application for Amends to Licenses DPR-58 & DPR-74,removing TSs Certain Requirements for Administrative Controls,Related to QA Requirements,Per Administrative Ltr 96-05 ML17333A4201996-04-0808 April 1996 Application for Amends to Licenses DPR-58 & DPR-74,moving TS 4.0.4 Exemption Statement for MSSVs Into Section 4.7.1.1 ML17333A3551996-03-12012 March 1996 Application for Amend to License DPR-74,removing TSs Re Shutdown & Control Rod Position Indication While in Modes 3, 4 & 5 ML17334B5751996-02-29029 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,revising TS to Reduce Boric Acid Concentration in Boric Acid Storage Sys from Approx 12 Percent to Approx 4 Percent by Weight. Technical Rept Presenting Justificaion for Changes Encl ML17334B5741996-02-26026 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.6.2 to Increase Current Limit on Nominal Fuel Assembly Enrichment for New,Westinghouse - Fabricated Fuel Stored in New Fuel Storage Racks ML17333A3201996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Remove Requirement That Operations Superintendent Must Hold or Have Held Sol at Plant or Similar Reactor ML17333A3151996-02-22022 February 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying Table 4.8-1,DG Test Schedule by Ref Rg 1.9,Rev 3 Rather than Rg 1.108,Rev 1 Criteria for Determination of Valid DG Test ML17333A2641996-01-12012 January 1996 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Section 4.4.11 to Eliminate SR Demonstrating Operability of Emergency Power Supply for Pressurizer PORVs & Block Valves ML17333A2391995-12-19019 December 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 3/4.6.1.2,3/4.6.1.3,3/4.6.1.6 & 3/4.6.1.6 to Require Types A,B & C Tests (Overall Integrated & Local Containment Leakage Rate) to Be Performed Per 10CFR50,App J Option B ML17332B0111995-11-10010 November 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising Ts,By Modifying Surveillance Testing of EDG During Refueling & Normal Operations ML17332A9971995-10-20020 October 1995 Application for Amends to Licenses DPR-58 & DPR-74,proposing to Add Exemption to TS 4.0.4 in Surveillance Requirements for MSIV ML17332A9111995-08-0606 August 1995 Application for Amends to Licenses DPR-58 & DPR-74,informing That Licensee Has 45 Days from Date of Issuance to Implement Amend Unless Otherwise Specified ML17334B5561995-08-0404 August 1995 Application for Exigent Amend to License DPR-58,modifying TS 4.4.5.4 & 4.4.5.5 for Repair of Hybrid Expansion Joint Sleeved SG Tubes.Proprietary W Rept WCAP-14446, Repair...Of Hybrid Expansion Joint...Tubes Encl.W Rept Withheld ML17332A8271995-06-30030 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,changing TS Section 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02, Suppl 1 ML17334B5501995-06-20020 June 1995 License Amend Request to Licenses DPR-58 & DPR-74,to Remove Requirements for Fire Protection Systems from Licenses & Guidance in GL 86-10,GL 88-12 & GL 93-07 ML17332A7991995-06-15015 June 1995 Application for Amends to Licenses DPR-58 & DPR-74,revising TS 4.8.1.1.2.e.7 to Reduce Duration of Surveillance Testing for EDGs During Refueling Operations from 24 H to 8 H ML17334B5481995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Support Operation of Unit 1 at SG Tube Plugging Levels Up to 30%,make One Unit 1 TS More Nearly Like Corresponding Unit 2 TS & Maintain Consistency of Unit 2 Criteria ML17334B5461995-05-26026 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying Tech Specs 3/4.3.1 (Reactor Trip Sys Instrumentation) & 3/4.3.2 (ESFAS Instrumentation) & Bases to Relocate Tables of Response Time Limits to Ufsar,Per GL 93-08 ML17332A7661995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74.Amends Would Incorporate Cycle & Burnup Dependent Peaking Factor Penalty ML17332A7741995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS 5.3.1 to Allow Fuel Reconstitution,Per GL 90-02,Suppl 1 ML17332A7771995-05-25025 May 1995 Application for Amends to Licenses DPR-58 & DPR-74,modifying TS Table 4.3-2 to Change Main Steam Line Isolation Valve Manual Actuation Sys Surveillance Frequency from Monthly to Quarterly 1999-09-23
[Table view] |
Text
CATEGORYj.REGULAT+INFORMATION DISTRIBUTIONOZSTEM (RIDE)DISTRIBUTION CODE:A001DCOPIESRECEIVED:LTR ENCLSIZE:TITLE:ORSubmittal:
GeneralDistribution tACCESS.:GN
-NBR.:9603200113 DOC.DATE:
96/03/12NOTARIZED:
YESDOCKETFACIL:50.-316 DonaldC.CookNuclearPowerPlant,Unit2,IndianaM05000316AUTH.NAMEAUTHORAFFILIATION FITZPATRICK,E.
IndianaMichiganPowerCo.(formerly Indiana&Mi'chigan EleRECIP.NAME RECIPIENT AFFILIATION DocumentControlBranch(Document ControlDesk)
SUBJECT:
Application foramendtolicenseDPR-74,removing TSsreshutdown6controlrodpositionindication whileinmodes3,4S5.NOTES:RECIPIENT IDCODE/NAME PD3-1LAHICKMAN,J COPIESLTTRENCL1111RECIPIENT IDCODE/NAME PD3-1PDCOPIESLTTRENCL11INTERN.gCENTERCBNRR/DSSA/SRXB OGC/HDS2EXTERNAL:
NOAC1111111011NRR/DE/EMCB NRR/DSSA/SPLB NUDOCS-ABSTRACT NRCPDR11111111NOTETOALL"RIDSNRECIPIENTS
)PLEASEHELPUSTOREDUCEWASTElCONTACTTHEDOCUMENTCONTROLDESK,ROOMOWFN5D-5(EXT.
415"20B3)
TOELIMINATE YOURNAMEFROMDXSTRKBUTXON LXSTS"'FORDOCUMENTS YOUDON'TNEEDlTOTALNUMBEROFCOPIESREQUIRED:
LTTR12ENCL.11 IndianaMichigan~PowerCompanyPOBox16631Columbus, OH43216INOlANANlCHIGANPOWERMarch12,1996AEP:NRC:1248 DocketNos.:50-316U.S.NuclearRegulatory Commission ATTN:DocumentControlDeskWashington, D.C.20555Gentlemen:
DonaldC.CookNuclearPlantUnit2PROPOSEDAMENDMENT TOREMOVETECHNICAL SPECIFICATIONS 3.1.3.3AND3.10.5,"RODPOSITIONINDICATOR CHANNELS-SHUTDOWN,"
TOACHIEVECONSISTENCY WITHDONALDC.COOKNUCLEARPLANTUNIT1ANDNUREG-1431.Thisletteranditsattachments constitute anapplication foramendment tothetechnical specifications (T/Ss)forDonaldC.CookNuclearPlantunit2.Specifically, weareproposing toremovetheT/Ssrelatedtoshutdownandcontrolrodpositionindication whileinmodes3,4,and5.Thefollowing unit2T/Ssareaffected:
3.1.3.3and3.10.5andassociated surveillances andbases.TheexistingCookNuclearPlantunit2T/Ssrequirethatrodpositionindication beOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.IfOPERABILITY cannotbeassured,thenumberofcontrolorshutdownrodsthatcanbewithdrawn islimitedtoasinglebankwhileperforming roddroptests.Thisrequirement isoverlyrestrictive since,duringshutdownmodes,theabilitytoensureadequateshutdownmargincanbecompensated byanincreaseintheboronconcentration ofthereactorcoolantsystem.Inadditiontothereduction inunnecessary requirements, theproposed, amendment wouldalsoaligntheaffectedunit2T/Sswiththeunit1T/Ssandtheimprovedstandardtechnical specifications issuedbytheNRCasNUREG-1431, Revision1.Attachment 1providesadetaileddescription oftheproposedchanges,thejustification forthechanges,andourdetermination ofnosignificant hazardsconsideration performed pursuantto10CFR50.92.Attachment 2containstheexistingT/Spagesmarked'76032001i3 9603i2PDRADQCK05000316PPDR00l~
U.S.NuclearRegulatory Commission Page2AEP:NRC:1248 toreflecttheproposedchanges.Attachment 3containstheproposedT/Spages.Webelievetheproposedchangeswillnotresultin(1)asignificant changeinthetypesofanyeffluentthatmaybereleasedoffsite,or(2)asignificant increaseinindividual orcumulative occupational radiation exposure.
TheseproposedchangeshavebeenreviewedbythePlantNuclearSafetyReviewCommittee andwillbereviewedatthenextregularly scheduled NuclearSafetyandDesignReviewCommittee meeting.Itisrequested thattheproposedamendment beapprovedbyApril12,1996insupportoftheupcomingunit2refueling.
Incompliance withtherequirements of10CFR50.91(b)(1),
copiesofthisletteranditsattachments havebeentransmitted totheMichiganPublicServiceCommission andtotheMichiganDepartment ofPublicHealth.ca~E.E.Fitzpatrick
,VicePresident SWORNTOANDSUBSCRIBED BEFOREMEotaryPublicpitAttachment cc:A.A.BlindG.CharnoffH.J.MillerNFEMSectionChiefNRCResidentInspector
-BridgmanJ.R.Padgett ATTACHMENT 1TOAEP:NRC:1248 DESCRIPTION ANDJUSTIFICATION OFCHANGES10CFR50.92ANALYSISFORCHANGESTOTHEDONALDCDCOOKNUCLEARPLANTUNIT2TECHNICAL SPECIFICATIONS ATTACHMENT TOAEP:NRC:1248 DESCRIPTION OFCHANGESPage1Thefollowing unit2technical specifications (T/S)3.1.3.3and3.10.5andassociated surveillances andbasesareaffectedbytheproposedchange.TS34133DeletetheReactivity ControlSystems,PositionIndicator Channels-Shutdown, LimitingCondition forOperation (3.1.3.3) andtheassociated surveillance (4.1.3.3)
(page3/41-22).TS3410.5DeletetheSpecialTestException, PositionIndicator ChannelsShutdown, LimitingCondition forOperation (3.10.5)andtheassociated surveillances (4.10.5.1 and4.10.5.2)
(page3/410-5).Also,deletethebasesreference toT/S3/4.10.5, PositionIndicator Channel-Shutdown(pageB3/410-1)IndexDeletereference to"Position Indicator Channels-Shutdown,"
fromthetechnical specification Index(pageIV).II.JUSTIFICATION FORCHANGESTheaxialpositionofshutdownrodsandcontrolrodsisdetermined bytwoseparateandindependent systems:thebankdemandpositionindication systemandtheanalogrodpositionindication (ARPI)system.Thecurrentunit2T/SsrequiretheARPIsystemtobeOPERABLEforeachshutdownandcontrolrodnotfullyinsertedinmodes3,4,and5.Tosatisfythisrequirement, twosetsofARPIcalibrations mustbeperformed.
Onecalibration isperformed onanindividual rodbankbasistosatisfytheARPIrequirements duringroddroptestinginaccordance withT/S3/4.10.5.
Thesecondcalibration isperformed atthecompletion ofthe"bank"calibration sequencetoensurethattherodsarecalibrated correctly toaddressbankoverlap.Thesecalibrations areredundant andtimeintensive.
Additionally, inmodes3,4,and5,theboronconcentration inthereactorcoolantsystem(RCS)isincreased toensurethatadequateshutdownmargin(SDM)isachievedandmaintained inaccordance withexistingCookNuclearPlantT/Ss.Thecalculation usedtoobtain ATTACHMENT TOAEP:NRC:1248 Page2therequiredboronconcentration takesintoaccounttherelativepositionofthecontrolandshutdownrods.Strictprocedural controlsareinplaceatCookNuclearPlanttoensurethatanallrodsoutshutdownmarginismaintained duringrodpositionindicator calibration.
Theadjustment ofboronconcentration toassureadequateshutdownmargininmodes3,4,and5isalsosupported bytheImprovedStandardTechnical Specifications (ISTS)forWestinghouse Plants(NUREG-1431).
TheISTSdoesnotcontainaT/Sforrodpositionindication inmodes3,4,and5;however,thebasespositionforthemodes1and2T/Ssaddresstheshutdownmodesinthefollowing manner."InshutdownMODES,theOPERABILITY oftheshutdownandcontrolbankshasthepotential toaffecttherequiredSDM(shutdown margin),butthiseffectcanbecompensated forbyanincreaseintheboronconcentration oftheReactorCoolantSystem."Therefore, theassurance thatadequateshutdownmarginexistsforanallrodsoutcondition inmodes3,4,and5negatestheneedforrodpositionindication inthesemodes.Technical specification 3.10,5isa"specialtestexception" directlytiedtoT/S3.1.3.3.Specifically, itprovidesanexemption fromthe"position indicator channel-shutdown" requirements duringroddroptesting.Deletionofthisspecification isnecessary sincetheprimaryspecification 3.1.3.3isbeingdeleted.Itisconcluded thatthedeletionofT/S3.1.3.3,PositionIndication Channels-Shutdown, doesnotresultinareduction insafetyastheimpactonshutdownmarginisadequately compensated forbyanincreaseinboronconcentration thatisconsistent withtheguidanceofNUREG-1431.III.10CFR5092CRITERIAPer10CFR50.92,thisproposedchangedoesnotinvolveasignificant hazardsconsideration becausethechangedoesnot:involveasignificant increaseintheprobability orconsequences ofanaccidentpreviously evaluated, 2.createthepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated, or3.involveasignificant reduction inamarginofsafety.
Attachment 1toAEP:NRC:1248 Page3Criterion 1Theboronconcentration inthereactorcoolantsystemwillbehighenoughtoassureadequateSDMinmodes3,4,and5.Thecalculation toobtaintherequiredboronconcentration takesintoaccountthepositionoftherods.Shutdownmarginisassumedasaninitialcondition inthesafetyanalysis.
Thesafetyanalysisestablishes aSDMthatensuresspecified acceptable fueldesignlimitsarenotexceeded.
AslongastheSDMissatisfied, nochangeintheprobability orconsequences ofanaccidentpreviously evaluated willresultfromtheproposeddeletionofthe"position indicator shutdown" specification.
Itisnotedthatthischangeisconsistent withthenewISTSapprovedbytheNRCasNUREG-1431, Rev.l.Criterion 2TheabilitytoinsertthecontrolandshutdownrodsprovidedbytherodcontrolsystemisnotaffectedbytheOPERABILITY statusoftheARPIsystem.Asmentioned previously, thereactorcoolantsystemboronconcentration willbehighenoughtoassureadequateSDMismaintained.
Therefore, itisconcluded thattheproposedchangesdonotcreatethepossibility ofanewordifferent kindofaccidentfromanyaccidentpreviously evaluated.
Criterion 3Themarginofsafetyrequirements, arenotaffectedbytheremovalofthisT/S.TherequiredSDMwhichisaninitialcondition inthesafetyanalysis, isunaffected sincethereactorcoolantsystemboronconcentration isincreased toaddressthe.potential "allrodsout"configuration.
Basedontheseconsiderations, itisconcluded thattheproposedchangesdonot'involve asignificant reduction inamarginofsafety.