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| {{#Wiki_filter:0JUN3,91970DocketMo.50-220Attention:le.KnotH.PrattVicePresidentandExecutiveEngineerhEIIyletterdatedMarch13,1970,requestedappropriatexcpoxtimgofyourxcpairplansandthcsignificantresultsofyourinvestigationandevaluationofthcfurnace-sensitizedatcinleassteelsafeendspriortqtherezmptionofh"'Preactoroperations.Youhavesub>>mittedthisinformationalongwithyourplaneforfuturesurveillanceandtha,resumptionofoperationsinthefollowingdocuments:1.ReactorPrimarySystemInvestigationatNineIQ.lcPoint.NuclearStation"datedHay1,1970.DISTRIBUTIONDoolyDRR.,Engelken,CO(2)H.Shapar,OGC(2)N.Dube~DRL(5)J.R.Buchanan,ORNLT.WLaughlin,DTXE,W.D.Gilbert,GEDocumentRoomv5ocketFileDRReadingDRLReadingNiagaraMohawkPc~rexCorporationBranchRading300ErieBoulevardWestD.Thompson,DRL'yracuse,NcvYork13202D.J.Skuvholt,DRLR.H.Vollmex,DRLD.L.Ziemann,DRLC.J.DeBevec,,DRLR.M.Diggs,DRLACRS(3)Gentlemen:,F.Schroeder,DRLR.BoydR.DeYoungThislottcrauthoxi"csthereturntooperationoftheNineIiXXePointNuclearStation(KP)inaccordancewithyourdocumentedpxogxauforrestorationtoserviceandsubjecttootherconditionswhichaxcdefinedherein.2.'ReactorPximrySystemXnvcstigati.on,atNinaNilePointNuclearStation-ReportNo.2"datedofayll,1970.U3."'PxogramforRestorationtoServiceBasedonReportsofPximaxySystemInvestigation-Nine.HalePointNuclearStation"datedkwyll,1970,Wehavexcvicvedthesereportsincludingtheresultsoftheinves-tigativeprogramandtheevaluationofthemetallurgicalpxoblem,andhaveconcluded.thatyourplansforrepairofthesafeendsandforresumptionofoperationsareacceptableasoctforthinyourreport(Item3above).Inthisregard,Menotethatareinspectionoffurnace= | | {{#Wiki_filter:0JUN3,91970DocketMo.50-220Attention: |
| 1,>>I"'~J(.2a~~-..JL'~I"'k>>'i,8>>..>>il.~'i4>>>>>>>>4'I'J">gVg>>L(J~>>Cll~>>>>>>(I/J>><<4,~p3<<IK tNiagaraMohivkPovex'orporation4JUNie,i9Nsensitizedsafeendsvillbemadevithinoneyear.gefurthex'nder-standthateffortsvillbemadetoperformsomeofthissurveillanceduringtheyear,wheneverunscheduledshutdownsprovidetheoppor-tunityforsuchinspection.gerequestthatyouprovideareportoftheresultsofthissurveillanceprogram,includingevaluationoftheirsignificancepromptlyaftex'ompletion>TheAdvt.soryCommitteeonReactorSafeguards(ACRS)revievedthismatteratits122ndmeetingheldJunell-'l3,1970.AcopyofthereportoftheACRS,datedJune16,1970,isenclosed.Initsreport,theACRSmaderecommendatfons,concerning'resumptionandfutux'eopera-tionofthefacilftyiTheseitemsinclude:1,Atleastoneleak-detectionsysteminadditionto'heproposedsumpaccumulatfon"rateanddevpointsystemsshouldbeinstalledvithinafevmonths.2.Assuranceshouldbeprovfdedthat'thebiologicalshieldsuxroundfngthereactorvesselcanwithstandthepxessurethatcouldbedevelopedbylossofintegrftyofasafeendornozzle,orthatfailureoftheshieldvouldhavenointolerableconsequences.Pleaseinformusexpeditiouslyofyourplansregardingimplementationofitem1.Pith,regardtoitem2,verequestthatyousubmitananalysisofshieldintegrityandconsequencesoffailureundertheprescribedconditions.Pleaseadviseusofyourplannedscheduleforsubmittag.Inaddition,aprogramforsurveillanceofthesensitizedmatex'ialovex'helongtermshouldbedeveloped.Sincedeterminationoftheappropriateextentofsuchaprogramvilldependupontheresultsofthesurveillanceperfoxmedduringtheforthcomingyear,verequestthat,inyourreportofthissurveillanceeffort,youincludeyourplansforfurthersurveillanceofthismaterial.Sub)ecttotheaboveconsiderations,vehaveconcludedthatresumptionofoperationsoftheNineMilePointreactorwillnotendangerthehealthand,safetyofthepublic.Sincerely,PeterA,Morris,'ixectorDivisionofReactorlicensingRSReport-6OFFICE>cSURNAME>ArvinE.U......I.eBoeuf..LDATE>FormAL'C-318(Rcv.9-53)16/70.........D.PRL.CDeBe'lEFleu'rDZfemton,Esquire,Lefb.y..@.6/(tt/706/19/70VS.GOVERNNENTI'RtNIINGCfftCE<WOO304598kovhol.Pgchgqedeg.6/g/70~....1}.JL4e6//QQs.../70 k>>)aII"'('1EII'rIfI>>IIt>>II'Itk>>ukI'ltI>>'Ik7Pr~y/k*rI77M~1~\II,JlJt 00ADVISORYCOMMITTEEONREACTORSAFEGUARDSUNITEDSTATESATOMICENERGYCOMMISSIONWASHINGTON,D.C.205454CJune16,1970HonorableGlennT.SeaborgChairmanU.STAtomicEnergyCommissionWashington,D.C.20545 | | le.KnotH.PrattVicePresident andExecutive EngineerhEIIyletterdatedMarch13,1970,requested appropriate xcpoxtimg ofyourxcpairplansandthcsignificant resultsofyourinvestigation andevaluation ofthcfurnace-sensitized atcinleas steelsafeendspriortqtherezmption ofh"'Preactoroperations. |
| | Youhavesub>>mittedthisinformation alongwithyourplaneforfuturesurveillance andtha,resumption ofoperations inthefollowing documents: |
| | 1.ReactorPrimarySystemInvestigation atNineIQ.lcPoint.Nuclear Station"datedHay1,1970.DISTRIBUTION DoolyDRR.,Engelken, CO(2)H.Shapar,OGC(2)N.Dube~DRL(5)J.R.Buchanan, ORNLT.WLaughlin, DTXE,W.D.Gilbert,GEDocumentRoomv5ocketFileDRReadingDRLReadingNiagaraMohawkPc~rexCorporation BranchRading300ErieBoulevard WestD.Thompson, DRL'yracuse, NcvYork13202D.J.Skuvholt, DRLR.H.Vollmex,DRLD.L.Ziemann,DRLC.J.DeBevec,, |
| | DRLR.M.Diggs,DRLACRS(3)Gentlemen:, |
| | F.Schroeder, DRLR.BoydR.DeYoungThislottcrauthoxi"cs thereturntooperation oftheNineIiXXePointNuclearStation(KP)inaccordance withyourdocumented pxogxauforrestoration toserviceandsubjecttootherconditions whichaxcdefinedherein.2.'ReactorPximrySystemXnvcstigati.on, atNinaNilePointNuclearStation-ReportNo.2"datedofayll,1970.U3."'Pxogram forRestoration toServiceBasedonReportsofPximaxySystemInvestigation |
| | -Nine.HalePointNuclearStation"datedkwyll,1970,Wehavexcvicvedthesereportsincluding theresultsoftheinves-tigativeprogramandtheevaluation ofthemetallurgical pxoblem,andhaveconcluded. |
| | thatyourplansforrepairofthesafeendsandforresumption ofoperations areacceptable asoctforthinyourreport(Item3above).Inthisregard,Menotethatareinspection offurnace= |
| | 1,>>I"'~J(.2a~~-..JL'~I"'k>>'i,8>>..>>il.~'i4>>>>>>>>4'I'J">gVg>>L(J~>>Cll~>>>>>>(I/J>><<4,~p3<<IK tNiagaraMohivkPovex'orporation 4JUNie,i9Nsensitized safeendsvillbemadevithinoneyear.gefurthex'nder-standthateffortsvillbemadetoperformsomeofthissurveillance duringtheyear,wheneverunscheduled shutdowns providetheoppor-tunityforsuchinspection. |
| | gerequestthatyouprovideareportoftheresultsofthissurveillance program,including evaluation oftheirsignificance promptlyaftex'ompletion> |
| | TheAdvt.soryCommittee onReactorSafeguards (ACRS)revievedthismatteratits122ndmeetingheldJunell-'l3,1970.AcopyofthereportoftheACRS,datedJune16,1970,isenclosed. |
| | Initsreport,theACRSmaderecommendatfons, concerning |
| | 'resumption andfutux'eopera-tionofthefacilftyi Theseitemsinclude:1,Atleastoneleak-detection systeminadditionto'heproposedsumpaccumulatfon"rate anddevpointsystemsshouldbeinstalled vithinafevmonths.2.Assurance shouldbeprovfdedthat'thebiological shieldsuxroundfng thereactorvesselcanwithstand thepxessurethatcouldbedeveloped bylossofintegrfty ofasafeendornozzle,orthatfailureoftheshieldvouldhavenointolerable consequences. |
| | Pleaseinformusexpeditiously ofyourplansregarding implementation ofitem1.Pith,regardtoitem2,verequestthatyousubmitananalysisofshieldintegrity andconsequences offailureundertheprescribed conditions. |
| | Pleaseadviseusofyourplannedscheduleforsubmittag. |
| | Inaddition, aprogramforsurveillance ofthesensitized matex'ial ovex'helongtermshouldbedeveloped. |
| | Sincedetermination oftheappropriate extentofsuchaprogramvilldependupontheresultsofthesurveillance perfoxmed duringtheforthcoming year,verequestthat,inyourreportofthissurveillance effort,youincludeyourplansforfurthersurveillance ofthismaterial. |
| | Sub)ecttotheaboveconsiderations, vehaveconcluded thatresumption ofoperations oftheNineMilePointreactorwillnotendangerthehealthand,safetyofthepublic.Sincerely, PeterA,Morris,'ixector DivisionofReactorlicensing RSReport-6OFFICE>cSURNAME>ArvinE.U......I.eBoeuf |
| | ..LDATE>FormAL'C-318(Rcv.9-53)16/70.........D |
| | .PRL.CDeBe'lEFleu'rDZfemton,Esquire,Lefb.y..@. |
| | 6/(tt/706/19/70VS.GOVERNNENTI'RtNIINGCfftCE<WO O304598kovhol.Pgchgqedeg |
| | .6/g/70~....1}.JL4e6//QQs.../70 k>>)aII"'('1EII'rIfI>>IIt>>II'Itk>>ukI'ltI>>'Ik7Pr~y/k*rI77M~1~\II,JlJt 00ADVISORYCOMMITTEE ONREACTORSAFEGUARDS UNITEDSTATESATOMICENERGYCOMMISSION WASHINGTON, D.C.205454CJune16,1970Honorable GlennT.SeaborgChairmanU.STAtomicEnergyCommission Washington, D.C.20545 |
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| ==DearDr.Seaborg:== | | ==DearDr.Seaborg:== |
| Atits122ndmeeting,June11-13,1970,theAdvisoryCommittee.onReactorSafeguardsreviewedtheprogramproposedbytheNiagaraMohawkPowerCorporationforrestorationtoserviceoftheNineMilePointStationfollowingthediscoveryduringMarch,1970,ofcracksandleakageina"safeend"(stainlesssteelextensionofthereactorvesselnozzle).TheprogramwasalsoconsideredatSubcommitteemeetingsonMay5,1970,andJune1and2,1970.Duringitsreview,theCommitteehadthebenefitofdiscussionswithrepresentativesoftheapplicant,theGeneralElectricCompany,theAECRegulatoryStaff,andtheirconsultants,andofthedocumentslisted.TheCommitteepreviouslyreportedto;youonthispro)ectonApril17;,1969.\Normalproceduresformostreactorpressurevesselshavebeentojointheausteniticstainlesssteelsafeendstothenozzlespriorto,thestressrelievingheattreatment.Thisheattreat-ment'sensitizesthesafeends,whichmakesthesteellessresistanttocertaintypesofcorrosion.Sensitizedausteniticstainlesssteelsinthisconditionhavegivenreasonablysatis-factoryserviceovermanyreactoryearsofoperation.TheapplicantandtheGeneralElectricCompanyhaveconductedanextensiveinvestigationofthecrackinganditscauses,Anindependentstressanalysisoftheas-builtpipinghasrevealedthatstressesinthecrackedsafeend,andoneothersafeend,wereexcessive.Itisbelievedthatthisexcessivestress,possiblyincombinationwithahighconcentrationof | | Atits122ndmeeting,June11-13,1970,theAdvisoryCommittee. |
| | onReactorSafeguards reviewedtheprogramproposedbytheNiagaraMohawkPowerCorporation forrestoration toserviceoftheNineMilePointStationfollowing thediscovery duringMarch,1970,ofcracksandleakageina"safeend"(stainless steelextension ofthereactorvesselnozzle).Theprogramwasalsoconsidered atSubcommittee meetingsonMay5,1970,andJune1and2,1970.Duringitsreview,theCommittee hadthebenefitofdiscussions withrepresentatives oftheapplicant, theGeneralElectricCompany,theAECRegulatory Staff,andtheirconsultants, andofthedocuments listed.TheCommittee previously reportedto;youonthispro)ectonApril17;,1969.\Normalprocedures formostreactorpressurevesselshavebeentojointheaustenitic stainless steelsafeendstothenozzlespriorto,thestressrelieving heattreatment. |
| | Thisheattreat-ment'sensitizes thesafeends,whichmakesthesteellessresistant tocertaintypesofcorrosion. |
| | Sensitized austenitic stainless steelsinthiscondition havegivenreasonably satis-factoryserviceovermanyreactoryearsofoperation. |
| | Theapplicant andtheGeneralElectricCompanyhaveconducted anextensive investigation ofthecrackinganditscauses,Anindependent stressanalysisoftheas-builtpipinghasrevealedthatstressesinthecrackedsafeend,andoneothersafeend,wereexcessive. |
| | Itisbelievedthatthisexcessive stress,possiblyincombination withahighconcentration of |
| ~ebe~ | | ~ebe~ |
| CHon.GlennT.Seaborg'r~,oxygeninthenon-flowingfluidinthepipeconcerned,causedtheintergranularcrackingofthefurnace-sensitizedstainlesssteelsafeend.Both,oftheoverstressedsafeendshavebeenremovedandreplacedwithnewonesmadeofunsensitizedmaterial.Thethermalsleeveshavebeenslottedtoavoidthepossibilityofgasbubblesatthehighpoints.Thepipingsupportshavebeenrearranged,andtheentireprimarysystemre-analyzed,forbothhotandcoldconditions,togiveassurancethatstresseswillremainwithinallowablelimits.Oneothersafeendmadeofsensitizedmaterialhasbeenremovedandexamined,foundnottocontaincracks,andhasbeenreplacedwithanewoneofunsensitizedmaterial.Allothersafeendsmadeofsensitizedmaterialhavebeennon-destructivelytested.Theminordefectsfoundwillbegroundoutbeforethereactorisoperatedagain.Theapplicantstatedthatexpansionsofprimarypipingwillbemeasuredduringahotfunctionaltesttobeconductedpriortorestartingthereactor,tocheckthepipesupportsandtheseismicrestraints.Theapplicanthasproposedanaugmentedsurveillanceprogramforthesensitizedsafeendsremainingintheprimarysystem,',.includingnon-destructivetestingatleastonceayearandre-checkingpipingexpansionsforseveralfullthermalcycles.TheRegulatoryStaffshouldassureitselfthatthedetailsoftheproposedprogramareappropriate.Theapplicantisstudyingimprovedleak-detectionmethods.TheCommitteebelievesthatdetectionandlocationofsmallleaksisanessentialpartofthesurveillanceprogram.Theapplicantshouldexpeditiouslyinstallsuchleak-detectiondevicesasseemlikelytogiveimprovedsensitivityorspeed'I"ofleakdetection.TheCommitteerecommendsthatatleastoneleak-detectionsysteminadditiontotheproposedsumpaccumu-lationrateanddewpointsystemsbeinstalledwithinafewmonthsandwishestobekeptinformedofprogress,inthisregard. | | CHon.GlennT.Seaborg'r~,oxygeninthenon-flowing fluidinthepipeconcerned, causedtheintergranular crackingofthefurnace-sensitized stainless steelsafeend.Both,oftheoverstressed safeendshavebeenremovedandreplacedwithnewonesmadeofunsensitized material. |
| 'IV v+8sr+JI1fonorabl(.GlennT.S>>aborgJun(2',1970ThcCnmmitte(.believ>>sthatthcRegulatoryStaffshouldassur>>its(.lf:L'haLthebjologicalshieldsurroundingthereactorv>>ss(1canwithsL'and~th(.pressur>>thaLcouldbedevelopedbylossofintegrityofasafecndornozzle,orthatfailureoftheshieldwouldhavenointolerablecon-sQ(fu('nc>>seTh(,hCi<Sbelievesthat,iiducr>>gardisgiventothe'r(.commendationsaboveand,initspr>>viousreportLoyouofApril17,1969,thereisxeaso>>abl<<.aSsur(mccthattheNin>>HilePointNucl>>arStationcanbeoperiL(.'(1atpowerlev(:lsupto1>38MM(t)withouL'nduerisktothehealth<<ndsafetyof.thepublic.Sincerelyyours,JosephH.liendrieChaix'manRefer>>n'cesl.NiagaraHohawkPowerCorporationInvestigationatNineNilePoiht,2.NiagaraHohawkPowerCorporationInvestigaL'ionatNiiaeHilcPointdaLedHay11,1970.,report,"ReactorPrimarySystemNuclearStation,"datedHay1,1970.report,"ReactorPrimarySystemNuclearStation,ReportNo.2,"I3.'iagnaMohawkPowerCorporationrepox't,"ProgramforRestorationL'oS<<rviceBasedonRepoxtsofPrimarySystemInvestigationNine,NileI'ointNuclearStation,"datedMay11,1970. | | Thethermalsleeveshavebeenslottedtoavoidthepossibility ofgasbubblesatthehighpoints.Thepipingsupportshavebeenrearranged, andtheentireprimarysystemre-analyzed, forbothhotandcoldconditions, togiveassurance thatstresseswillremainwithinallowable limits.Oneothersafeendmadeofsensitized materialhasbeenremovedandexamined, foundnottocontaincracks,andhasbeenreplacedwithanewoneofunsensitized material. |
| WC'PADL04 Hon.GlennT.Seaborg%30~eCommitteebelievesthattheRegulatoryStaffshouldassureelfthatthebiologicalshieldsurroundingthereactorveselcanwithstandthepressurethatcouldbedevelopedbylossfintegrityofasafeendornozzle,orthatfailureofthesPeldwouldhavenointolerableconsequences.TheACRSlievesthat,ifdueregardisgiventotherecommendat'onsaboveandinitspreviousreporttoyouofApril17,19,thereisreasonableassurancethattheNineMilePointNucearStationcanbeoperatedatpowerlevelsupto1538MN(t)withoutunduerisktothehealthandsafetyofthepublic.,Sincerelyyours,JosephM.endrieChairmanReferences1~NiagaraMohawkPowerCorporatioreport,NEDM-10159,-"PreliminaryReport,CoreSprayNzleSafeEnd,NineMilePointPowerStation",datdMarch27,1970'.NiagaraMohawkPowerCorporationrepor,"ReactorPrimarySystemInvestigationatNineMiPointNuclearStation,ReportNo.2",datedMayll,19~3.NiagaraMohawkPowerCorporationreport,"PrgramforRestorationtoServiceBasedonReportsofPrarySystemInvestigation'NineMilePointNuclearStion",datedMayll,1970, | | Allothersafeendsmadeofsensitized materialhavebeennon-destructively tested.Theminordefectsfoundwillbegroundoutbeforethereactorisoperatedagain.Theapplicant statedthatexpansions ofprimarypipingwillbemeasuredduringahotfunctional testtobeconducted priortorestarting thereactor,tocheckthepipesupportsandtheseismicrestraints. |
| | Theapplicant hasproposedanaugmented surveillance programforthesensitized safeendsremaining intheprimarysystem,',.including non-destructive testingatleastonceayearandre-checkingpipingexpansions forseveralfullthermalcycles.TheRegulatory Staffshouldassureitselfthatthedetailsoftheproposedprogramareappropriate. |
| | Theapplicant isstudyingimprovedleak-detection methods.TheCommittee believesthatdetection andlocationofsmallleaksisanessential partofthesurveillance program.Theapplicant shouldexpeditiously installsuchleak-detection devicesasseemlikelytogiveimprovedsensitivity orspeed'I"ofleakdetection. |
| | TheCommittee recommends thatatleastoneleak-detection systeminadditiontotheproposedsumpaccumu-lationrateanddewpointsystemsbeinstalled withinafewmonthsandwishestobekeptinformedofprogress, inthisregard. |
| | 'IV v+8sr+JI1fonorabl(. |
| | GlennT.S>>aborgJun(2',1970ThcCnmmitte(. |
| | believ>>sthatthcRegulatory Staffshouldassur>>its(.lf:L'haLthebjological shieldsurrounding thereactorv>>ss(1canwithsL'and~th(.pressur>>thaLcouldbedeveloped bylossofintegrity ofasafecndornozzle,orthatfailureoftheshieldwouldhavenointolerable con-sQ(fu('nc>>s eTh(,hCi<Sbelievesthat,iiducr>>gardisgiventothe'r(.commendations aboveand,initspr>>viousreportLoyouofApril17,1969,thereisxeaso>>abl<<. |
| | aSsur(mcc thattheNin>>HilePointNucl>>arStationcanbeoperiL(.'(1atpowerlev(:lsupto1>38MM(t)withouL'ndue risktothehealth<<ndsafetyof.thepublic.Sincerely yours,JosephH.liendrieChaix'man Refer>>n'ces l.NiagaraHohawkPowerCorporation Investigation atNineNilePoiht,2.NiagaraHohawkPowerCorporation InvestigaL'ion atNiiaeHilcPointdaLedHay11,1970.,report,"ReactorPrimarySystemNuclearStation," |
| | datedHay1,1970.report,"ReactorPrimarySystemNuclearStation,ReportNo.2,"I3.'iagnaMohawkPowerCorporation repox't,"ProgramforRestoration L'oS<<rviceBasedonRepoxtsofPrimarySystemInvestigation Nine,NileI'ointNuclearStation," |
| | datedMay11,1970. |
| | WC'PADL04 Hon.GlennT.Seaborg%30~eCommittee believesthattheRegulatory Staffshouldassureelfthatthebiological shieldsurrounding thereactorveselcanwithstand thepressurethatcouldbedeveloped bylossfintegrity ofasafeendornozzle,orthatfailureofthesPeldwouldhavenointolerable consequences. |
| | TheACRSlievesthat,ifdueregardisgiventotherecommendat'ons aboveandinitspreviousreporttoyouofApril17,19,thereisreasonable assurance thattheNineMilePointNucearStationcanbeoperatedatpowerlevelsupto1538MN(t)withoutunduerisktothehealthandsafetyofthepublic.,Sincerely yours,JosephM.endrieChairmanReferences 1~NiagaraMohawkPowerCorporatio report,NEDM-10159, |
| | -"Preliminary Report,CoreSprayNzleSafeEnd,NineMilePointPowerStation", |
| | datdMarch27,1970'.NiagaraMohawkPowerCorporation repor,"ReactorPrimarySystemInvestigation atNineMiPointNuclearStation,ReportNo.2",datedMayll,19~3.NiagaraMohawkPowerCorporation report,"PrgramforRestoration toServiceBasedonReportsofPrarySystemInvestigation |
| | 'NineMilePointNuclearStion",datedMayll,1970, |
| ~\f~}} | | ~\f~}} |
|
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Category:ACRS Summary Report
MONTHYEARML17037C4771974-11-15015 November 1974
Letter Enclosing Supplement No. 1 to the Safety Evaluation Report for the Application for a Full-Term Operating License
ML17037C2071974-09-25025 September 1974
Letter Responding to a September 17, 1974 Letter Requesting a Response to Two ACRS Identified Items Concerning Main Steam Isolation Valve Leakage and Inservice Inspection of the Reactor Pressure Vessel and Advising That Inform.
ML17037C4801974-09-13013 September 1974
Letter Transmitting ACRS Report Dated September 10, 1974, on the Application for Conversion of the Provisional Operating License to a Full-Term Operating License for the Nine Mile Point Nuclear Station Unit
ML17037C4901974-02-20020 February 1974
Letter Submitting Copy of Report of the Advisory Committee on Reactor Safeguards Dated February 12, 1974 on Expected Performance of General Electric 8x8 Fuel Design for Reload Use
ML17037C3691971-03-12012 March 1971
Letter Responding to a February 11, 1971 Forwarding an ACRS Report Pertaining to the Request for an Increase from 1538 to 1850 Thermal Megawatts in the Licensed Power Level
ML17037C3501970-06-19019 June 1970
Letter Authorizing the Return to Operation of Unit 1 in Accordance with Your Documented Program and Subject to Conditions Defined and Enclosing an ACRS Report Dated June 16, 1970
1974-09-25
[Table view]
Category:Letter
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Integrated Inspection Report 05000220/2023004 and 05000410/2023004
NMP1L3569, CFR 50.46 Annual Report2024-01-26026 January 2024
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IR 05000220/20234022023-11-28028 November 2023
Security Baseline Inspection Report 05000220/2023402 and 05000410/2023402
NMP1L3557, Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications Implementation2023-11-22022 November 2023
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Constellation Energy Generation, LLC - 2023 Annual Report - Guarantees of Payment of Deferred Premiums
IR 05000220/20234202023-11-0101 November 2023
Security Baseline Inspection Report 05000220/2023420 and 05000410/2023420
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IR 05000220/20230032023-10-25025 October 2023
Integrated Inspection Report 05000220/2023003 and 05000410/2023003
IR 05000220/20235012023-10-17017 October 2023
Emergency Preparedness Biennial Exercise Inspection Report 05000220/2023501 and 05000410/2023501
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Comprehensive Engineering Team Inspection Report 05000220/2023011 and 05000410/2023011
RS-23-097, Constellation Energy Generation, LLC, Advisement of Leadership Changes and Submittal of Updated Standard Practice Procedures Plans2023-10-12012 October 2023
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NMP1L3554, Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases2023-10-0606 October 2023
Submittal of Revision 28 to the Final Safety Analysis Report (Updated), Fire Protection Design Criteria Document, 10CFR50.59 Evaluation Summary Report, 10CFR54.37(b) Aging Management Review, and Technical Specifications with Revised Bases C
IR 05000220/20233032023-09-20020 September 2023
Retake Operator Licensing Examination Report 05000220/2023303
ML23250A0822023-09-19019 September 2023
Regulatory Audit Summary Regarding LARs to Adopt TSTF-505, Rev. 2, and 10 CFR 50.69
ML23257A1732023-09-14014 September 2023
Requalification Program Inspection
IR 05000220/20230052023-08-31031 August 2023
Updated Inspection Plan for Nine Mile Point Nuclear Station, Units 1 and 2 (Report 05000220/2023005 and 05000410/2023005)
RS-23-080, Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs2023-08-30030 August 2023
Constellation Energy Generation, LLC, Application to Revise Technical Specifications to Adopt TSTF-264-A, Revision 0, 3.3.9 and 3.3.10 - Delete Flux Monitors Specific Overlap Requirement SRs
NMP2L2851, Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations2023-08-25025 August 2023
Relief Request Associated with Successive Inspections for Generic Letter 88-01 / BWRVIP-75-A Augmented Examinations
ML23151A3472023-08-21021 August 2023
Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration
NMP1L3534, License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation2023-08-18018 August 2023
License Amendment Request - Revision to the Technical Specifications Design Features Sections to Remove the Nine Mile 3 Nuclear Project, LLC, Designation
ML23220A0262023-08-0808 August 2023
Licensed Operator Positive Fitness-for-Duty Test
IR 05000220/20234012023-08-0808 August 2023
Cyber Security Inspection Report 05000220/2023401 and 05000410/2023401 (Cover Letter Only)
NMP1L3545, Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .2023-08-0404 August 2023
Supplemental Information Letter to Adopt TSTF-505, Provide Risk- Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2 and 10 CFR 50.69, Risk-informed Categorization and Treatment of Structures, Systems .
RS-23-087, Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor2023-08-0404 August 2023
Revision to Approved Alternatives Associated with the Use of the BWRVIP Guidelines in Lieu of Specific ASME Code Requirements on Reactor
IR 05000220/20230022023-08-0101 August 2023
Integrated Inspection Report 05000220/2023002 and 05000410/2023002
ML23207A0762023-07-14014 July 2023
EN 56557 - Update to Part 21 Report Re Potential Defect with Trane External Auto/Stop Emergency Stop Relay Card Pn: XI2650728-06
NMP1L3544, Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations2023-07-14014 July 2023
Fifth Inservice Inspection Interval, First Inservice Inspection Period 2023 Owner'S Activity Report for RFO-27 Inservice Examinations
ML23186A1642023-07-0606 July 2023
Operator Licensing Retake Examination Approval
NMP2L2846, Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications2023-07-0505 July 2023
Nine Mire Point Nuclear Station, Units 1 and 2, General License 30-day Cask Registration Notifications
ML23192A0622023-06-30030 June 2023
Engine Systems, Inc., 10CFR21 Reporting of Defects and Non-Compliance, Report No. 10CFR21-0136, Rev. 0
IR 05000220/20230102023-06-29029 June 2023
Biennial Problem Identification and Resolution Inspection Report 05000220/2023010 and 05000410/2023010
ML23131A4242023-06-23023 June 2023
Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568
RS-23-077, Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations2023-06-16016 June 2023
Response to NRC Regulatory Issue Summary 2023-01, Preparation and Scheduling of Operator Licensing Examinations
NMP1L3539, Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)2023-06-0909 June 2023
Day Commitment Response - Relief Request I5R-11 Concerning the Installation of a Weld Overlay on Reactor Pressure Vessel Recirculation Inlet Nozzle N2E Safe End-to-Nozzle Dissimilar Metal Weld (32-WD-208)
ML23159A0052023-06-0505 June 2023
56557-EN 56557 - Paragon - Redlined
RS-23-042, Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling2023-05-25025 May 2023
Application to Revise Technical Specifications to Adopt TSTF-580, Provide Exception from Entering Mode 4 with No Operable RHR Shutdown Cooling
IR 05000410/20233022023-05-15015 May 2023
Initial Operator Licensing Examination Report 05000410/2023302
2024-02-01
[Table view]
Category:Request for Additional Information (RAI)
MONTHYEARML23264A7992023-09-21021 September 2023
NRR E-mail Capture - Final RAI - Constellation Energy Generation, LLC Fleet Request License Amendment Request to Adopt TSTF-580, Revision 1
ML23205A2432023-07-19019 July 2023
NRC Staff Follow-up Question on Audit Question 18 TSTF-505 and 50.69 Regulatory Audit (E-mail Dated 7/19/2023) (EPIDs L-2022-LLA-0185 and L-2022-LLA-0186)
ML23087A2912023-03-28028 March 2023
Request for Additional Information (3/28/2023 E-mail) - Proposed Emergent I5R-11 Alternative Associated with a Weld Overlay on RPV Recirculation Nozzle N2E DM Weld
ML23061A0522023-03-0202 March 2023
Request for Additional Information (3/2/2023 E-mail) - Proposed Alternative Associated with a Weld Overlay Repair to the Torus
ML23012A2002023-01-13013 January 2023
Information Request for the Cyber Security Baseline Inspection, Notification to Perform Inspection 05000220/2023401 and 05000410/2023401
ML22207A2162022-07-26026 July 2022
Information Request to Support Triennial Baseline Design-Basis Capability of Power-Operated Valves Inspection; Inspection Report 05000220/2022010 and 05000410/2022010
ML22194A9412022-07-13013 July 2022
Request for Additional Information Relief Request CS-PR-02 (7/13/2022 e-mail)
ML22041B5362022-02-10010 February 2022
NRR E-mail Capture - Constellation Energy Generation, LLC - Request for Additional Information Regarding Fleet License Amendment Request to Adopt TSTF-541
ML22020A0642022-01-13013 January 2022
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles
ML21320A3472021-11-16016 November 2021
Request for Additional Information LAR to Revise TSs to Adopt TSTF-582, Revision 0
ML21306A3312021-11-0202 November 2021
Request for Additional Information Alternative Request GV-RR-10 (11/2/2021 e-mail)
ML21256A1902021-09-10010 September 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21144A2132021-05-24024 May 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding License Transfer Application
ML21117A0342021-05-0505 May 2021
Request for Additional Information Regarding Proposed Alternative to Use ASME Code Case N-893
ML21125A1282021-05-0404 May 2021
OPC Document Request - Feb 2021
ML21110A5112021-04-20020 April 2021
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt TSTF-582
ML21088A2682021-03-30030 March 2021
Notification of Conduct of a Fire Protection Team Inspection
ML21062A0652021-03-0101 March 2021
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Proposed Fleet Alternative to Documentation Requirements for Pressure Retaining Bolting
ML21049A2572021-02-18018 February 2021
Request for Additional Information Byron/Dresden Proposed Changes to Site Emergency Plans to Support Post-Shutdown and Permanently Defueled Conditions (EPID-2020-LLA-0240 & EPID-2020-LLA-0237)
ML20365A0092020-12-30030 December 2020
Request for Additional Information Concerning Review of License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency (EPIDs L-2020-LLA-0188 and L-2020-LLR-0114)
ML20358A2602020-12-28028 December 2020
Changes to Draft Request for Additional Information Regarding License Amendment Request and Relief Request to Change Excess Flow Check Valve Testing Frequency
ML20272A2802020-09-28028 September 2020
Withdrawal and Replacement of Request for Additional Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times
ML20248H5192020-09-28028 September 2020
Changes to Draft Request for Additional Information Regarding Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times
ML20246G6362020-09-0202 September 2020
Request for Additonal Information to Support Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
NMP2L2739, Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 22020-08-28028 August 2020
Request for Additional Information for Nine Mile Point Nuclear Station, Unit 2, to Adopt TSTF-505, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b, Revision 2
ML20239A7982020-08-25025 August 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Fleet License Amendment Request to Adopt TSTF-568, Revision 2
ML20212L8702020-07-30030 July 2020
Request for Additonal Information Review of License Amendment Requests Regarding Riskinformed Categorization and Treatment of Structures, Systems and Components (L-2019-LLA-0290)
ML20213A9352020-07-30030 July 2020
Request for Additional Information Review of License Amendment Request to Revise Technical Specifications to Adopt Risk Informed Completion Times
ML20153A7042020-06-0101 June 2020
NRR E-mail Capture - Preliminary RAI for Fleet Request to Use Alternative OMN-26
ML20135H1972020-05-14014 May 2020
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Extend Safety Relief Valve Test Interval
ML20045E3582020-02-14014 February 2020
Draft Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates
ML19296A1862019-10-23023 October 2019
Request for Additional Information Regarding License Amendment Request to Increase Allowable MSIV Leakage Rates (L-2019-LLA-0115)
ML19275H1362019-10-0202 October 2019
NRR E-mail Capture - Exelon Generation Company, LLC - Request for Additional Information Regarding Request to Use ASME Code Case N-879
ML19179A0612019-07-19019 July 2019
Three Mile Point 1 - Supplemental Information Needed to Proposed Alternative to Use ASME Code Case N-879
ML19151A8132019-05-31031 May 2019
Licensed Operator Positive Fitness-For-Duty Test
ML19025A1572019-01-25025 January 2019
Request for Additional Information Regarding Primary Containment Oxygen Concentration License Amendment Request
ML19025A1202019-01-24024 January 2019
NRR E-mail Capture - Calvert Cliffs, Fitzpatrick, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Response Organization Staffing
ML18341A2212018-12-0707 December 2018
Request for Additional Information Regarding Emergency Tech Spec Change Re HPCS Completion Time (EPID -L-2018-LLA-0491)
ML18228A6932018-08-15015 August 2018
Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426)
ML18205A3922018-07-24024 July 2018
Request for Additional Information Regarding Reactor Pressure Vessel Water Inventory Control License Amendment Request (L-2017-LLA-0426)
ML18184A2882018-07-0303 July 2018
Request for Additional Information Regarding Removal of Boraflex Credit from Spent Fuel Pool License Amendment Request(L-2018-LLA-0039)
ML18102A2372018-04-12012 April 2018
NRR E-mail Capture - Calvert Cliffs, Ginna, and Nine Mile Point - Request for Additional Information Regarding License Amendment Request to Revise Emergency Action Level Schemes (EPID-L-2017-LLA-0237)
ML17331B1342017-12-12012 December 2017
2, and R.E. Ginna Nuclear Power Plant - Request for Additional Information - Regarding
ML17285B1962017-10-27027 October 2017
Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools.
ML17272A0112017-10-10010 October 2017
Request for Additional Information Regarding License Amendment Concerning Reactor Pressure Vessel Water Inventory Control
ML17234A3592017-08-30030 August 2017
Request for Additional Information Regarding Relief Request NMP-RR-001 to Utilize Code Case N-702
ML17241A2752017-08-29029 August 2017
Request for Additional Information Response MSA (MF7946,7) and FE (MG0087,8) E-mail Attachment
ML17240A3102017-08-15015 August 2017
NRR E-mail Capture - Nine Mile Point MSA and FE RAI
ML17172A0842017-06-27027 June 2017
Request for Additional Information Regarding Relief Request to Utilize ASME Code Case N-702
ML17065A1622017-03-14014 March 2017
Request for Additional Information Regarding Proposed Alternative to Perform Pressure Isolation Valve Leakage Testing at Frequencies Consistent with 10 CFR Part 50, Appendix J
2023-09-21
[Table view]
Category:Safety Evaluation
MONTHYEARML23305A1402023-12-13013 December 2023
Units 1 & 2; Nine Mile Point, Unit 2; Peach Bottom, Units 2 & 3; and Quad Cities, Units 1 and 2 - Issuance of Amendments to Adopt Traveler TSTF-580
ML23291A4642023-12-0707 December 2023
Issuance of Amendment No. 251 Regarding the Adoption of Title 10 the Code of Federal Regulations Section 50.69, Risk-Informed Categorization and Treatment of SSC for Nuclear Power Plants
ML23289A0122023-12-0606 December 2023
Issuance of Amendment No. 250 Regarding the Revision to Technical Specifications to Adopt TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b
ML23151A3472023-08-21021 August 2023
Issuance of Amendments to Adopt TSTF-295-A, Modify Note 2 to Actions of PAM Table to Allow Separate Condition Entry for Each Penetration
ML23131A4242023-06-23023 June 2023
Issuance of Amendment No. 249 Regarding the Revision to Technical Specification 3.3.1 to Adopt Technical Specifications Task Force Traveler TSTF-568
ML23156A6832023-06-22022 June 2023
Authorization and Safety Evaluation of Alternative Relief Request I5R-14
ML23156A6822023-06-22022 June 2023
Authorization and Safety Evaluation of Alternative Relief Request I5R-11
ML23114A2522023-04-28028 April 2023
Request to Use a Provision of a Later Edition of the ASME Boiler & Pressure Vessel Code, Section XI
ML23081A0382023-04-25025 April 2023
County, 1 & 2; Nine Mile Point, 2; and Quad Cities, 1 & 2 - Issuance of Amendments to Adopt TSTF-306, Rev. 2, Add Action to LCO 3.3.6.1 to Give Option to Isolate the Penetration
ML23103A1912023-04-20020 April 2023
Request for Threshold Determination Under 10 CFR 50.80
ML23082A3502023-04-17017 April 2023
Issuance of Amendment No. 192, Revision of Surveillance Requirements Associated with Emergency Diesel Generator Testing
ML23094A1422023-04-0505 April 2023
Approval of Alternative Request I5R-13 to Utilize Specific Provisions of Code Case N-716-3
ML23025A4122023-02-28028 February 2023
Issuance of Amendment No. 248 to Revise Alternative Source Term Calculation for Main Steam Isolation Valve Leakage and Non-MSIV Leakage
ML22339A0582022-12-21021 December 2022
Relief Request Associated with Pump Periodic Verification Tests of Core Spray System Pumps
ML22293B8052022-11-30030 November 2022
Constellation Energy Generation, Llc_Fleet - Request to Authorize Use Honeywell Mururoa V4F1 R Supplied Air Suits
ML22090A0862022-04-29029 April 2022
Amendments to Adopt TSTF-541,Rev.2,Add Exceptions to Surveillance Requirements for Valves,Dampers Locked in Actuated Position
ML22094A0012022-04-15015 April 2022
Constellation Energy Generation, LLC - Proposed Alternative for Repair of Water Level Instrumentation Partial Penetration Nozzles (Epids L-2021-LLR-0057 and L-2021-LLR-0058)
ML22061A0402022-03-11011 March 2022
Relief Request Associated with Excess Flow Check Valves
ML22033A3102022-03-0404 March 2022
Issuance of Amendment No. 190, Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements
ML21347A0382022-01-13013 January 2022
Issuance of Amendments to Revise Reactor Coolant Leakage Requirements
ML21277A2482021-11-16016 November 2021
Letter with Enclosure 4, Safety Evaluation for Transfer of Licenses and Draft Conforming License Amendments (Public Version)
ML21295A7342021-11-15015 November 2021
Issuance of Amendment No. 187 Adoption of Technical Specification Task Force (TSTF) Traveler TSTF-501, Revision 1, Relocate Stored Fuel Oil and Lube Oil Volume Values to Licensee Control
ML21256A1792021-11-0202 November 2021
Issuance of Amendment No. 246 Changes to Reactor Pressure Vessel Water Inventory Control Technical Specification Requirements
ML21280A0782021-10-27027 October 2021
Proposed Alternative to Use of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Case N-893 (Epids L-2020-LLR-0147 and L-2020-LLR-0148)
ML21230A2062021-09-0303 September 2021
Proposed Alternative to Use ASME OM Code Case OMN-28
ML21216A2202021-08-0505 August 2021
Proposed Alternative to Eliminate Certain Documentation Requirements for Pressure Retaining Bolting
ML21166A1682021-06-25025 June 2021
ML21140A1532021-06-0303 June 2021
Correction to April 22, 2021 Safety Evaluation for Requests for Alternative to the Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Program Interval
ML21082A2212021-04-29029 April 2021
Issuance of Amendment No. 186, Adoption of TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4B
ML21109A2162021-04-22022 April 2021
Proposed Alternative to Inservice Testing Requirements of the ASME OM Code for the Fifth 10-Year Interval
ML21105A3382021-04-22022 April 2021
Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code Concerning Examination Coverage of Certain Class 1 and 2 Component Welds
ML21033A5302021-04-0101 April 2021
Issuance of Amendments to Adopt Technical Specifications Task Force TSTF-566, Revise Actions for Inoperable RHR Shutdown Cooling Subsystems
ML21049A0062021-03-16016 March 2021
Issuance of Amendment No. 245 for Relaxation of Surveillance Frequency for Instrument-Line Flow Check Valve
ML21049A0242021-02-23023 February 2021
Alternative Request to the Requirements of the ASME OM Code for the Testing Intervals for the Instrument-Line Flow Check Valves
ML21013A0052021-02-0404 February 2021
Issuance of Amendments to Adopt Technical Specifications Task Traveler TSTF-568, Revise Applicability of BWR/4 TS 3.6.2.5 and TS 3.6.3.2
ML21028A6732021-02-0303 February 2021
Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L-2020-LLR-011
ML20332A1152021-01-29029 January 2021
Issuance of Amendment No. 183 Regarding Risk-Informed Categorization and Treatment of Structures, Systems, and Components
ML21005A0612021-01-14014 January 2021
Proposed Alternatives to Extend the Safety Relief Valve Testing Interval (EPID L-2020-LLR-0014 Through L-2020-LLR-0018)
ML20287A1302020-11-0505 November 2020
Review of Quality Assurance Program Changes
ML20241A1902020-10-20020 October 2020
Issuance of Amendment No. 182 to Change Allowable Main Steam Isolation Valve Leak Rates
ML20269A2002020-09-30030 September 2020
Request to Use a Provision of Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI (EPID L2020-LLR-0117
ML20232A1712020-09-0101 September 2020
Request to Use Alternative Code Case OMN-26
ML20141L6362020-07-10010 July 2020
Issuance of Amendments Based on TSTF-427,Allowance for Nontechnical Specification Barrier Degradation on Supported System Operability,Rev 2
ML20134H9402020-07-0808 July 2020
Issuance of Amendments Revising the High Radiation Area Administrative Controls
ML20141L0532020-06-0202 June 2020
Relief from the Requirements of the American Society of Mechanical Engineers Boiler and Pressure Vessel Code
ML20113F0412020-04-30030 April 2020
Proposed Alternative to the Submittal Schedule for Certain Reports (COVID-19)
ML20021A0702020-04-0606 April 2020
Issuance of Amendments to Delete License Conditions for Decommissioning Trusts
ML20028E3992020-02-0404 February 2020
Proposed Alternative to Use ASME Code Case N-879
ML19301B0052019-11-25025 November 2019
Issuance of Amendment No. 239 Administrative Edits to the Technical Specifications
ML19269C5342019-09-27027 September 2019
Proposed Alternative to Use Encoded Phased Array Ultrasonic Examination Techniques
2023-08-21
[Table view]
Category:Test/Inspection/Operating Procedure
MONTHYEARML18018A9612018-01-18018 January 2018
Preservice Inspection Plan
ML18018B0521999-09-27027 September 1999
Third Inservice Inspection Interval
ML17037C4711975-05-30030 May 1975
Letter Regarding the General Electric Development of a New Calculational Method for Determining Void Coefficients and Requesting That Niagara Mohawk Inform the Commission as to How the New Void Coefficients Will Be ..
ML17037C2351974-06-26026 June 1974
Letter Referring to October 26, 1973 Letter Concerning the HPCI System Status and Advising That the Off-Site Power Test Utilizing Energy from Other than the Normal Off-Site Supply Has Been Completed During the Spring 1974 Outage
ML17037C2391974-05-0808 May 1974
Letter Responding to a March 6, 1974 Letter Regarding Inspections and Submittal of Positive Reports When Defective Units Are Found
ML17037C2401974-05-0606 May 1974
Letter Responding to the April 11, 1974 Letter Concerning a Change to the Facility Pursuant to Section 50.59 of the Commission'S Regulations and Advising Niagara Mohawk That a Description of the Change Including a Summary ...
ML17037C2471974-01-25025 January 1974
Letter Responding to a December 5, 1973 Letter Requesting Certain Information Concerning the Reload Fuel and Advising That Niagara Mohawk Plans to Submit the Remaining Information by February 19, 1974 Except for the Second ...
ML17037C3601972-08-0101 August 1972
Letter Informing the Commission That on Mary 21, 1972, During the Poison Curtain Removal Outage, the Main Steam Line Isolation Valves Were Leak Tested and Advising That Details of Tests, Calculations, and Procedures Are on File
ML17037C1361971-12-15015 December 1971
Letter Advising That the Power Level of 1850 Mw(T) Was Achieved and Testing Was Performed During the Week of December 5, 1971 and That Comprehensive Reports Are in Preparation and Will Be Available for Review
ML17037C3451971-09-0808 September 1971
Letter Requesting That Niagara Mohawk Obtain Measurements of Primary Coolant Samples Taken at a Frequency Consistent with Changing Operating Parameters and That a Representative Attend the Meeting on September 23, 1971
ML17037C3691971-03-12012 March 1971
Letter Responding to a February 11, 1971 Forwarding an ACRS Report Pertaining to the Request for an Increase from 1538 to 1850 Thermal Megawatts in the Licensed Power Level
ML17037C3501970-06-19019 June 1970
Letter Authorizing the Return to Operation of Unit 1 in Accordance with Your Documented Program and Subject to Conditions Defined and Enclosing an ACRS Report Dated June 16, 1970
ML17037C1471969-08-0101 August 1969
Letter Regarding the Matter of Examination and Assurance of Adequate Quality for the Specific Service Application of Certain Components
ML17037C1481968-12-31031 December 1968
Letter Concerning Stub Tube Post Hydro Inspection and Advising That Agreement on the Dye Test Procedures to Be Used with the Division of Compliance Has Been Reached
2018-01-18
[Table view] |
Text
0JUN3,91970DocketMo.50-220Attention:
le.KnotH.PrattVicePresident andExecutive EngineerhEIIyletterdatedMarch13,1970,requested appropriate xcpoxtimg ofyourxcpairplansandthcsignificant resultsofyourinvestigation andevaluation ofthcfurnace-sensitized atcinleas steelsafeendspriortqtherezmption ofh"'Preactoroperations.
Youhavesub>>mittedthisinformation alongwithyourplaneforfuturesurveillance andtha,resumption ofoperations inthefollowing documents:
1.ReactorPrimarySystemInvestigation atNineIQ.lcPoint.Nuclear Station"datedHay1,1970.DISTRIBUTION DoolyDRR.,Engelken, CO(2)H.Shapar,OGC(2)N.Dube~DRL(5)J.R.Buchanan, ORNLT.WLaughlin, DTXE,W.D.Gilbert,GEDocumentRoomv5ocketFileDRReadingDRLReadingNiagaraMohawkPc~rexCorporation BranchRading300ErieBoulevard WestD.Thompson, DRL'yracuse, NcvYork13202D.J.Skuvholt, DRLR.H.Vollmex,DRLD.L.Ziemann,DRLC.J.DeBevec,,
DRLR.M.Diggs,DRLACRS(3)Gentlemen:,
F.Schroeder, DRLR.BoydR.DeYoungThislottcrauthoxi"cs thereturntooperation oftheNineIiXXePointNuclearStation(KP)inaccordance withyourdocumented pxogxauforrestoration toserviceandsubjecttootherconditions whichaxcdefinedherein.2.'ReactorPximrySystemXnvcstigati.on, atNinaNilePointNuclearStation-ReportNo.2"datedofayll,1970.U3."'Pxogram forRestoration toServiceBasedonReportsofPximaxySystemInvestigation
-Nine.HalePointNuclearStation"datedkwyll,1970,Wehavexcvicvedthesereportsincluding theresultsoftheinves-tigativeprogramandtheevaluation ofthemetallurgical pxoblem,andhaveconcluded.
thatyourplansforrepairofthesafeendsandforresumption ofoperations areacceptable asoctforthinyourreport(Item3above).Inthisregard,Menotethatareinspection offurnace=
1,>>I"'~J(.2a~~-..JL'~I"'k>>'i,8>>..>>il.~'i4>>>>>>>>4'I'J">gVg>>L(J~>>Cll~>>>>>>(I/J>><<4,~p3<<IK tNiagaraMohivkPovex'orporation 4JUNie,i9Nsensitized safeendsvillbemadevithinoneyear.gefurthex'nder-standthateffortsvillbemadetoperformsomeofthissurveillance duringtheyear,wheneverunscheduled shutdowns providetheoppor-tunityforsuchinspection.
gerequestthatyouprovideareportoftheresultsofthissurveillance program,including evaluation oftheirsignificance promptlyaftex'ompletion>
TheAdvt.soryCommittee onReactorSafeguards (ACRS)revievedthismatteratits122ndmeetingheldJunell-'l3,1970.AcopyofthereportoftheACRS,datedJune16,1970,isenclosed.
Initsreport,theACRSmaderecommendatfons, concerning
'resumption andfutux'eopera-tionofthefacilftyi Theseitemsinclude:1,Atleastoneleak-detection systeminadditionto'heproposedsumpaccumulatfon"rate anddevpointsystemsshouldbeinstalled vithinafevmonths.2.Assurance shouldbeprovfdedthat'thebiological shieldsuxroundfng thereactorvesselcanwithstand thepxessurethatcouldbedeveloped bylossofintegrfty ofasafeendornozzle,orthatfailureoftheshieldvouldhavenointolerable consequences.
Pleaseinformusexpeditiously ofyourplansregarding implementation ofitem1.Pith,regardtoitem2,verequestthatyousubmitananalysisofshieldintegrity andconsequences offailureundertheprescribed conditions.
Pleaseadviseusofyourplannedscheduleforsubmittag.
Inaddition, aprogramforsurveillance ofthesensitized matex'ial ovex'helongtermshouldbedeveloped.
Sincedetermination oftheappropriate extentofsuchaprogramvilldependupontheresultsofthesurveillance perfoxmed duringtheforthcoming year,verequestthat,inyourreportofthissurveillance effort,youincludeyourplansforfurthersurveillance ofthismaterial.
Sub)ecttotheaboveconsiderations, vehaveconcluded thatresumption ofoperations oftheNineMilePointreactorwillnotendangerthehealthand,safetyofthepublic.Sincerely, PeterA,Morris,'ixector DivisionofReactorlicensing RSReport-6OFFICE>cSURNAME>ArvinE.U......I.eBoeuf
..LDATE>FormAL'C-318(Rcv.9-53)16/70.........D
.PRL.CDeBe'lEFleu'rDZfemton,Esquire,Lefb.y..@.
6/(tt/706/19/70VS.GOVERNNENTI'RtNIINGCfftCE<WO O304598kovhol.Pgchgqedeg
.6/g/70~....1}.JL4e6//QQs.../70 k>>)aII"'('1EII'rIfI>>IIt>>II'Itk>>ukI'ltI>>'Ik7Pr~y/k*rI77M~1~\II,JlJt 00ADVISORYCOMMITTEE ONREACTORSAFEGUARDS UNITEDSTATESATOMICENERGYCOMMISSION WASHINGTON, D.C.205454CJune16,1970Honorable GlennT.SeaborgChairmanU.STAtomicEnergyCommission Washington, D.C.20545
Subject:
REPORTONNINEMILEPOINTNUCLEARSTATION
DearDr.Seaborg:
Atits122ndmeeting,June11-13,1970,theAdvisoryCommittee.
onReactorSafeguards reviewedtheprogramproposedbytheNiagaraMohawkPowerCorporation forrestoration toserviceoftheNineMilePointStationfollowing thediscovery duringMarch,1970,ofcracksandleakageina"safeend"(stainless steelextension ofthereactorvesselnozzle).Theprogramwasalsoconsidered atSubcommittee meetingsonMay5,1970,andJune1and2,1970.Duringitsreview,theCommittee hadthebenefitofdiscussions withrepresentatives oftheapplicant, theGeneralElectricCompany,theAECRegulatory Staff,andtheirconsultants, andofthedocuments listed.TheCommittee previously reportedto;youonthispro)ectonApril17;,1969.\Normalprocedures formostreactorpressurevesselshavebeentojointheaustenitic stainless steelsafeendstothenozzlespriorto,thestressrelieving heattreatment.
Thisheattreat-ment'sensitizes thesafeends,whichmakesthesteellessresistant tocertaintypesofcorrosion.
Sensitized austenitic stainless steelsinthiscondition havegivenreasonably satis-factoryserviceovermanyreactoryearsofoperation.
Theapplicant andtheGeneralElectricCompanyhaveconducted anextensive investigation ofthecrackinganditscauses,Anindependent stressanalysisoftheas-builtpipinghasrevealedthatstressesinthecrackedsafeend,andoneothersafeend,wereexcessive.
Itisbelievedthatthisexcessive stress,possiblyincombination withahighconcentration of
~ebe~
CHon.GlennT.Seaborg'r~,oxygeninthenon-flowing fluidinthepipeconcerned, causedtheintergranular crackingofthefurnace-sensitized stainless steelsafeend.Both,oftheoverstressed safeendshavebeenremovedandreplacedwithnewonesmadeofunsensitized material.
Thethermalsleeveshavebeenslottedtoavoidthepossibility ofgasbubblesatthehighpoints.Thepipingsupportshavebeenrearranged, andtheentireprimarysystemre-analyzed, forbothhotandcoldconditions, togiveassurance thatstresseswillremainwithinallowable limits.Oneothersafeendmadeofsensitized materialhasbeenremovedandexamined, foundnottocontaincracks,andhasbeenreplacedwithanewoneofunsensitized material.
Allothersafeendsmadeofsensitized materialhavebeennon-destructively tested.Theminordefectsfoundwillbegroundoutbeforethereactorisoperatedagain.Theapplicant statedthatexpansions ofprimarypipingwillbemeasuredduringahotfunctional testtobeconducted priortorestarting thereactor,tocheckthepipesupportsandtheseismicrestraints.
Theapplicant hasproposedanaugmented surveillance programforthesensitized safeendsremaining intheprimarysystem,',.including non-destructive testingatleastonceayearandre-checkingpipingexpansions forseveralfullthermalcycles.TheRegulatory Staffshouldassureitselfthatthedetailsoftheproposedprogramareappropriate.
Theapplicant isstudyingimprovedleak-detection methods.TheCommittee believesthatdetection andlocationofsmallleaksisanessential partofthesurveillance program.Theapplicant shouldexpeditiously installsuchleak-detection devicesasseemlikelytogiveimprovedsensitivity orspeed'I"ofleakdetection.
TheCommittee recommends thatatleastoneleak-detection systeminadditiontotheproposedsumpaccumu-lationrateanddewpointsystemsbeinstalled withinafewmonthsandwishestobekeptinformedofprogress, inthisregard.
'IV v+8sr+JI1fonorabl(.
GlennT.S>>aborgJun(2',1970ThcCnmmitte(.
believ>>sthatthcRegulatory Staffshouldassur>>its(.lf:L'haLthebjological shieldsurrounding thereactorv>>ss(1canwithsL'and~th(.pressur>>thaLcouldbedeveloped bylossofintegrity ofasafecndornozzle,orthatfailureoftheshieldwouldhavenointolerable con-sQ(fu('nc>>s eTh(,hCi<Sbelievesthat,iiducr>>gardisgiventothe'r(.commendations aboveand,initspr>>viousreportLoyouofApril17,1969,thereisxeaso>>abl<<.
aSsur(mcc thattheNin>>HilePointNucl>>arStationcanbeoperiL(.'(1atpowerlev(:lsupto1>38MM(t)withouL'ndue risktothehealth<<ndsafetyof.thepublic.Sincerely yours,JosephH.liendrieChaix'man Refer>>n'ces l.NiagaraHohawkPowerCorporation Investigation atNineNilePoiht,2.NiagaraHohawkPowerCorporation InvestigaL'ion atNiiaeHilcPointdaLedHay11,1970.,report,"ReactorPrimarySystemNuclearStation,"
datedHay1,1970.report,"ReactorPrimarySystemNuclearStation,ReportNo.2,"I3.'iagnaMohawkPowerCorporation repox't,"ProgramforRestoration L'oS<<rviceBasedonRepoxtsofPrimarySystemInvestigation Nine,NileI'ointNuclearStation,"
datedMay11,1970.
WC'PADL04 Hon.GlennT.Seaborg%30~eCommittee believesthattheRegulatory Staffshouldassureelfthatthebiological shieldsurrounding thereactorveselcanwithstand thepressurethatcouldbedeveloped bylossfintegrity ofasafeendornozzle,orthatfailureofthesPeldwouldhavenointolerable consequences.
TheACRSlievesthat,ifdueregardisgiventotherecommendat'ons aboveandinitspreviousreporttoyouofApril17,19,thereisreasonable assurance thattheNineMilePointNucearStationcanbeoperatedatpowerlevelsupto1538MN(t)withoutunduerisktothehealthandsafetyofthepublic.,Sincerely yours,JosephM.endrieChairmanReferences 1~NiagaraMohawkPowerCorporatio report,NEDM-10159,
-"Preliminary Report,CoreSprayNzleSafeEnd,NineMilePointPowerStation",
datdMarch27,1970'.NiagaraMohawkPowerCorporation repor,"ReactorPrimarySystemInvestigation atNineMiPointNuclearStation,ReportNo.2",datedMayll,19~3.NiagaraMohawkPowerCorporation report,"PrgramforRestoration toServiceBasedonReportsofPrarySystemInvestigation
'NineMilePointNuclearStion",datedMayll,1970,
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