ML17037C337: Difference between revisions

From kanterella
Jump to navigation Jump to search
(Created page by program invented by StriderTol)
(Created page by program invented by StriderTol)
Line 15: Line 15:


=Text=
=Text=
{{#Wiki_filter:FROMI~~.Siagara-khhavtr.-PcwerCorPoration8~'gyrccccc,SccYork2320'~~ElcEcPgatt.TOI3r-Peter-Ac-NorrisLTR.XORIG.IMEMOiCCI0RTI0THERtDATEOFDOCUMENT'DATERECEIVED22++9is96'8.~5OTNERiACTIONNECESSARYQNOACTIONNECESSARYQCONCURRENCEQDATEANSWEREDCOMMENTCIBYICLASSIFiPOSTOFFICEREG.NOiFILECODE(gp-22O(Xmm)DESCRIPTIONI(MuStBOUnClaSSlfiad)Xtrtransthefollovfag:ENCLOSURESICHAI"EHWUE8PNO.2toTechSecsrequestingmc@ificationstosafetylimitonfue1cleMlina,integrity.sied.51conf'd.csrecsd)REMARKS(REFERREDTODATEDXS3RKBUTIOH:Rega2atoryfilAECPDRCompliance2)OGCamPO6AHPricekSkovholtDuhe/IevtneDThosoBoyCHSICBuchananZiemnn+~9vcsforACTXM2RECEIVEDBY9csadvDishVo(1cyea),DATE*U,B,OOVSRHIISNTrlllNTIHOOFFICSi$44WI~UWATOMICENERGYCOMMISSIONMQQtrPNTRPLFPRMFORMA<<->><<(860)  
{{#Wiki_filter:FROMI~~.Siagara-khhavtr.-Pcwer CorPoration 8~'gyrccccc, SccYork2320'~~ElcEcPgatt.TOI3r-Peter-Ac
*Mlh~Fq~.4,2"A'>>~ItI,A.i')p",..i"'TgfggQII NIAGARAMOHAWKPOWERCORPORATIONRegufatoryFifet:y.NIAGARA~~MOHAWK300ERIEBOUIEVAROWESTSYRACUSE,N,Y.13202December9,1969Dr;PeterA.Morris,DirectorDivisionofReactorLicensingUnitedStatesAtomicEnergyCommissionWashington,D.C.20545
-NorrisLTR.XORIG.IMEMOiCCI0RTI0THERtDATEOFDOCUMENT'DATERECEIVED22++9is96'8.~5OTNERiACTIONNECESSARY QNOACTIONNECESSARY QCONCURRENCE QDATEANSWEREDCOMMENTCIBYICLASSIFiPOSTOFFICEREG.NOiFILECODE(gp-22O(Xmm)DESCRIPTIONI (MuStBOUnClaSSlfiad)
Xtrtransthefollovfag:
ENCLOSURESI CHAI"EHWUE8PNO.2toTechSecsrequesting mc@ifications tosafetylimitonfue1cleMlina, integrity.
sied.51conf'd.csrecsd)REMARKS(REFERREDTODATEDXS3RKBUTIOH:
Rega2atory filAECPDRCompliance 2)OGCamPO6AHPricekSkovholtDuhe/Ievtne DThosoBoyCHSICBuchananZiemnn+~9vcsforACTXM 2RECEIVEDBY9csadvDishVo(1cyea),DATE*U,B,OOVSRHIISNT rlllNTIHO OFFICSi$44WI~UWATOMICENERGYCOMMISSION MQQtrPNTRPLFPRMFORMA<<->><<(860)  
*Mlh~Fq~.4,2"A'>>~ItI,A.i')p",..i"'Tgfg gQII NIAGARAMOHAWKPOWERCORPORATION Regufatory Fifet:y.NIAGARA~~MOHAWK300ERIEBOUIEVAROWESTSYRACUSE, N,Y.13202December9,1969Dr;PeterA.Morris,DirectorDivisionofReactorLicensing UnitedStatesAtomicEnergyCommission Washington, D.C.20545


==DearDr.Morris:==
==DearDr.Morris:==
Re:ChangeRequestNo.2ProvisionalOperatingLicenseDPR-17Docket50-220EnclosedarethreesignedcopiesandnineteenreproducedsignaturecopiesofChangeRequestNo.2requestingamodificationtothesafetylimitonfuelcladdingintegrity.InaccordancewithTechnicalSpecificationrequirement6.1.C.2,thischangehasbeenreviewedbytheStationOperationsReviewCommitteeandtheSafetyReviewandAuditBoard,respec-tively,andbearstheapprovalofbothbodies.WeaskthattheCommissiongivepromptconsiderationtothisrequestforchange.VerytrulyyoursMHP/jclEnclosures,fI]o)/rPCKpEprU31ffCOECg1969k,-REGUIA)pRy'@L~CCffpe/KBCLERK/H.PratVicePresidentandExecutiveEngineer3815~
Re:ChangeRequestNo.2Provisional Operating LicenseDPR-17Docket50-220Enclosedarethreesignedcopiesandnineteenreproduced signature copiesofChangeRequestNo.2requesting amodification tothesafetylimitonfuelcladdingintegrity.
1l'aLTlP.f,CC Kl',/''PP,<jCRINGEREVESTNO.2Qygg~gfg)gyj+,,gOJgPROVISIONALOPERATINGLICENSEDPR-17(DOCKET50-220)ApplicantherebyrequeststheCommissiontochangetheTechnical.Specification(AppendixAoftheabovecaptionedlicense)asfollows:1.SecificationToBeChangedSafetyLimit-FuelCladdingIntegrity,Figure2.1.1andSpecification2.1.1.b2.ExtentofChanea.Figure2.1.1-Extendthe1250psiaand1015psiasafetylimitcurvesfrom20percentrecirculationflowto5percentrecirculationflow.b.Specification2.l.l.b-h1odifyspecificationtopermitreactoroperationinaccordancewiththeadditionaldatathatisapplicablefrom5percentto20percentrecircu-lationflowasshownontheattachedfigure.3.ChaneReuesteda.Figure2.1.1-SupersedetheexistingTechnicalSpecificationFigure2.1.1withtheattachedfigure.b.Specification2.l.l.b-ftodifystatementtoread:"Whenthereactorpressureislessthan585psigorreactorrecirculationflowislessthan5percentofdesign,thereactorthermalpowershallnotexceed307h/Wt."c.References,Page8-AddReference(6)ChangeRequestNo.2-Discussion.
Inaccordance withTechnical Specification requirement 6.1.C.2,thischangehasbeenreviewedbytheStationOperations ReviewCommittee andtheSafetyReviewandAuditBoard,respec-tively,andbearstheapprovalofbothbodies.WeaskthattheCommission givepromptconsideration tothisrequestforchange.VerytrulyyoursMHP/jclEnclosures
eh 4.DiscussionTheextensionofthefuelcladdingintegritysafetylimitcurves,Figure2.1.1,toflowsaslowas".percentofdesignwasperformedusingthesameassumptionsandinitialconditions~aswereemployedi.nthecurvespresentlyintheTechnicalSpeci-fications.ThedesignbasiscriticalheatfluxcorrelationgiveninAPED-3892wasused.ThepowershapewasbasedonaMCHFRof1.5at120percentoverpower,andresultsinatotalpeakingfactorof3.13.Maximumfeedwaterter;peraturewasassumedforthevariouspressuresandflowsandthecoreinletenthalpywasbasedonthesubcoolingres<<lt~ngfromequilibriumoperation.(EEvaluationofthefuelcladdingintegritysafetylimitinthelowflowregionwasperformedusingthedesignbasiscriti-calheatfluxcorrelationatthelowmass-'lowlimit.Thisevaluationisconservativeduetotheinverserelationshipbetweenmassflowandcriticalheatfluxinthehighqualityregionofthecorrelation.Cri.ticalheatfluxformassflowslowerthanthelowlimitofthedesignbasiscriticalheatfluxcorrelationaregreatertha'nthatpredictedbythecorre-lation.TheproposedchangeofSafetyLimit".l.l.bandFigure2.1.1doesnotreducethe.marginot'afetylimitprotectionsinceneutronmonitoringsystemrodblockandscramtripsmain-tainadequatemargintoproposedsafetylimitlinesonFigureE.JanssenandS.Levy,"BurnoutLimitCurvesforBoilingWaterReactors"APED-3892,April1,1962.
,fI]o)/rPCKpEprU31ffCOECg1969k,-REGUIA)pRy
0F4,  4.Discussion(Continued)forallregionsofpossibleoperation.Thecorenaturalcircu-lationcharacteristic,thelowerlimitofcoreflowforpoweroperation,precludesoperationuptothesafetylimitwithouthavingfirstreachedtherodblocktripandthescramtrip.PriorsubmittaltotheFDSAR,AppendixE,hasshownthatthereactorisadequatelyprotectedbythe'pressurescramandfixed120percentfluxscramforalltransientsconsideredsuchasthecontinuousrodwithdrawalandturbinetripwithoutbypassoriginatingfromallnormaloperating.conditionsinclud-'ngthelowpowerandflowlevelsconsistent>>ithnaturalcirculation.NIAGARAM01(NOKP()I('ER.CORPORATIONbypinotfl.PrattVicePresidentExecutiveEngineer v~  
'@L~CCffpe/KBCLERK/H.PratVicePresident andExecutive Engineer3815~
~~~~~-AI~160NOTESFIGURE2.1.1FUELCLADDINGINTEGRITYSAFETYLIMIT140120I-C?U'0100UJI-C)I~w80Cl060II-C3W4020I.Ratedpowerisl538Mwt2.Designflowis67.5xIOIb/hr3.Totalpeakingfactoris<3.134.Corepressureis>585psig5.WaterlevelshallnotbemorethanI'-7II/16"belowmin.normallevel(El.302'-9").FORPEAKINGFACTORS>3.13SL=3.13XSLOPFWHERE:SL=SAFETYLIMITFORPEAKINGFACTORS>3.13PF=PEAKINGFACTOR>3.13SLO=SAFETYLIMITSHOWNABOVE1000PSIG1235PSIG001020304050607080RECIRCULATIONFLOW(%OFOESIGN)90'10011012010 0:+Egg~~}}
1l'aLTlP.f,CC Kl',/''PP,
<jCRINGEREVESTNO.2Qygg~gfg)gyj+,,gOJgPROVISIONAL OPERATING LICENSEDPR-17(DOCKET50-220)Applicant herebyrequeststheCommission tochangetheTechnical
.Specification (Appendix Aoftheabovecaptioned license)asfollows:1.Secification ToBeChangedSafetyLimit-FuelCladdingIntegrity, Figure2.1.1andSpecification 2.1.1.b2.ExtentofChanea.Figure2.1.1-Extendthe1250psiaand1015psiasafetylimitcurvesfrom20percentrecirculation flowto5percentrecirculation flow.b.Specification 2.l.l.b-h1odifyspecification topermitreactoroperation inaccordance withtheadditional datathatisapplicable from5percentto20percentrecircu-lationflowasshownontheattachedfigure.3.ChaneReuesteda.Figure2.1.1-Supersede theexistingTechnical Specification Figure2.1.1withtheattachedfigure.b.Specification 2.l.l.b-ftodifystatement toread:"Whenthereactorpressureislessthan585psigorreactorrecirculation flowislessthan5percentofdesign,thereactorthermalpowershallnotexceed307h/Wt."c.References, Page8-AddReference (6)ChangeRequestNo.2-Discussion.
eh 4.Discussion Theextension ofthefuelcladdingintegrity safetylimitcurves,Figure2.1.1,toflowsaslowas".percentofdesignwasperformed usingthesameassumptions andinitialconditions
~aswereemployedi.nthecurvespresently intheTechnical Speci-fications.
Thedesignbasiscriticalheatfluxcorrelation giveninAPED-3892 wasused.ThepowershapewasbasedonaMCHFRof1.5at120percentoverpower,and resultsinatotalpeakingfactorof3.13.Maximumfeedwater ter;perature wasassumedforthevariouspressures andflowsandthecoreinletenthalpywasbasedonthesubcooling res<<lt~ng fromequilibrium operation.
(EEvaluation ofthefuelcladdingintegrity safetylimitinthelowflowregionwasperformed usingthedesignbasiscriti-calheatfluxcorrelation atthelowmass-'lowlimit.Thisevaluation isconservative duetotheinverserelationship betweenmassflowandcriticalheatfluxinthehighqualityregionofthecorrelation.
Cri.tical heatfluxformassflowslowerthanthelowlimitofthedesignbasiscriticalheatfluxcorrelation aregreatertha'nthatpredicted bythecorre-lation.TheproposedchangeofSafetyLimit".l.l.bandFigure2.1.1doesnotreducethe.marginot'afetylimitprotection sinceneutronmonitoring systemrodblockandscramtripsmain-tainadequatemargintoproposedsafetylimitlinesonFigureE.JanssenandS.Levy,"BurnoutLimitCurvesforBoilingWaterReactors" APED-3892, April1,1962.
0F4,  4.Discussion (Continued) forallregionsofpossibleoperation.
Thecorenaturalcircu-lationcharacteristic, thelowerlimitofcoreflowforpoweroperation, precludes operation uptothesafetylimitwithouthavingfirstreachedtherodblocktripandthescramtrip.Priorsubmittal totheFDSAR,AppendixE,hasshownthatthereactorisadequately protected bythe'pressure scramandfixed120percentfluxscramforalltransients considered suchasthecontinuous rodwithdrawal andturbinetripwithoutbypassoriginating fromallnormaloperating
.conditions includ-'ng thelowpowerandflowlevelsconsistent
>>ithnaturalcirculation.
NIAGARAM01(NOKP()I('ER.
CORPORATION bypinotfl.PrattVicePresident Executive Engineer v~  
~~~~~-AI~160NOTESFIGURE2.1.1FUELCLADDINGINTEGRITY SAFETYLIMIT140120I-C?U'0100UJI-C)I~w80Cl060II-C3W4020I.Ratedpowerisl538Mwt2.Designflowis67.5xIOIb/hr3.Totalpeakingfactoris<3.134.Corepressureis>585psig5.WaterlevelshallnotbemorethanI'-7II/16"belowmin.normallevel(El.302'-9").
FORPEAKINGFACTORS>3.13 SL=3.13XSLOPFWHERE:SL=SAFETYLIMITFORPEAKINGFACTORS>3.13PF=PEAKINGFACTOR>3.13 SLO=SAFETYLIMITSHOWNABOVE1000PSIG1235PSIG001020304050607080RECIRCULATION FLOW(%OFOESIGN)90'10011012010 0:+Egg~~}}

Revision as of 00:13, 30 June 2018

Nine Mile Point Unit 1 - Letter Enclosing Change Request No. 2 Requesting a Modification to the Safety Limit on Fuel Cladding Integrity and Advising That the Change Has Been Reviewed and Bears the Approval of the Station Operations Review C
ML17037C337
Person / Time
Site: Nine Mile Point Constellation icon.png
Issue date: 12/09/1969
From: Pratt M H
Niagara Mohawk Power Corp
To: Morris P A
US Atomic Energy Commission (AEC)
References
Download: ML17037C337 (12)
v • d • e


Text

FROMI~~.Siagara-khhavtr.-Pcwer CorPoration 8~'gyrccccc, SccYork2320'~~ElcEcPgatt.TOI3r-Peter-Ac

-NorrisLTR.XORIG.IMEMOiCCI0RTI0THERtDATEOFDOCUMENT'DATERECEIVED22++9is96'8.~5OTNERiACTIONNECESSARY QNOACTIONNECESSARY QCONCURRENCE QDATEANSWEREDCOMMENTCIBYICLASSIFiPOSTOFFICEREG.NOiFILECODE(gp-22O(Xmm)DESCRIPTIONI (MuStBOUnClaSSlfiad)

Xtrtransthefollovfag:

ENCLOSURESI CHAI"EHWUE8PNO.2toTechSecsrequesting mc@ifications tosafetylimitonfue1cleMlina, integrity.

sied.51conf'd.csrecsd)REMARKS(REFERREDTODATEDXS3RKBUTIOH:

Rega2atory filAECPDRCompliance 2)OGCamPO6AHPricekSkovholtDuhe/Ievtne DThosoBoyCHSICBuchananZiemnn+~9vcsforACTXM 2RECEIVEDBY9csadvDishVo(1cyea),DATE*U,B,OOVSRHIISNT rlllNTIHO OFFICSi$44WI~UWATOMICENERGYCOMMISSION MQQtrPNTRPLFPRMFORMA<<->><<(860)

  • Mlh~Fq~.4,2"A'>>~ItI,A.i')p",..i"'Tgfg gQII NIAGARAMOHAWKPOWERCORPORATION Regufatory Fifet:y.NIAGARA~~MOHAWK300ERIEBOUIEVAROWESTSYRACUSE, N,Y.13202December9,1969Dr;PeterA.Morris,DirectorDivisionofReactorLicensing UnitedStatesAtomicEnergyCommission Washington, D.C.20545

DearDr.Morris:

Re:ChangeRequestNo.2Provisional Operating LicenseDPR-17Docket50-220Enclosedarethreesignedcopiesandnineteenreproduced signature copiesofChangeRequestNo.2requesting amodification tothesafetylimitonfuelcladdingintegrity.

Inaccordance withTechnical Specification requirement 6.1.C.2,thischangehasbeenreviewedbytheStationOperations ReviewCommittee andtheSafetyReviewandAuditBoard,respec-tively,andbearstheapprovalofbothbodies.WeaskthattheCommission givepromptconsideration tothisrequestforchange.VerytrulyyoursMHP/jclEnclosures

,fI]o)/rPCKpEprU31ffCOECg1969k,-REGUIA)pRy

'@L~CCffpe/KBCLERK/H.PratVicePresident andExecutive Engineer3815~

1l'aLTlP.f,CC Kl',/PP,

<jCRINGEREVESTNO.2Qygg~gfg)gyj+,,gOJgPROVISIONAL OPERATING LICENSEDPR-17(DOCKET50-220)Applicant herebyrequeststheCommission tochangetheTechnical

.Specification (Appendix Aoftheabovecaptioned license)asfollows:1.Secification ToBeChangedSafetyLimit-FuelCladdingIntegrity, Figure2.1.1andSpecification 2.1.1.b2.ExtentofChanea.Figure2.1.1-Extendthe1250psiaand1015psiasafetylimitcurvesfrom20percentrecirculation flowto5percentrecirculation flow.b.Specification 2.l.l.b-h1odifyspecification topermitreactoroperation inaccordance withtheadditional datathatisapplicable from5percentto20percentrecircu-lationflowasshownontheattachedfigure.3.ChaneReuesteda.Figure2.1.1-Supersede theexistingTechnical Specification Figure2.1.1withtheattachedfigure.b.Specification 2.l.l.b-ftodifystatement toread:"Whenthereactorpressureislessthan585psigorreactorrecirculation flowislessthan5percentofdesign,thereactorthermalpowershallnotexceed307h/Wt."c.References, Page8-AddReference (6)ChangeRequestNo.2-Discussion.

eh 4.Discussion Theextension ofthefuelcladdingintegrity safetylimitcurves,Figure2.1.1,toflowsaslowas".percentofdesignwasperformed usingthesameassumptions andinitialconditions

~aswereemployedi.nthecurvespresently intheTechnical Speci-fications.

Thedesignbasiscriticalheatfluxcorrelation giveninAPED-3892 wasused.ThepowershapewasbasedonaMCHFRof1.5at120percentoverpower,and resultsinatotalpeakingfactorof3.13.Maximumfeedwater ter;perature wasassumedforthevariouspressures andflowsandthecoreinletenthalpywasbasedonthesubcooling res<<lt~ng fromequilibrium operation.

(EEvaluation ofthefuelcladdingintegrity safetylimitinthelowflowregionwasperformed usingthedesignbasiscriti-calheatfluxcorrelation atthelowmass-'lowlimit.Thisevaluation isconservative duetotheinverserelationship betweenmassflowandcriticalheatfluxinthehighqualityregionofthecorrelation.

Cri.tical heatfluxformassflowslowerthanthelowlimitofthedesignbasiscriticalheatfluxcorrelation aregreatertha'nthatpredicted bythecorre-lation.TheproposedchangeofSafetyLimit".l.l.bandFigure2.1.1doesnotreducethe.marginot'afetylimitprotection sinceneutronmonitoring systemrodblockandscramtripsmain-tainadequatemargintoproposedsafetylimitlinesonFigureE.JanssenandS.Levy,"BurnoutLimitCurvesforBoilingWaterReactors" APED-3892, April1,1962.

0F4, 4.Discussion (Continued) forallregionsofpossibleoperation.

Thecorenaturalcircu-lationcharacteristic, thelowerlimitofcoreflowforpoweroperation, precludes operation uptothesafetylimitwithouthavingfirstreachedtherodblocktripandthescramtrip.Priorsubmittal totheFDSAR,AppendixE,hasshownthatthereactorisadequately protected bythe'pressure scramandfixed120percentfluxscramforalltransients considered suchasthecontinuous rodwithdrawal andturbinetripwithoutbypassoriginating fromallnormaloperating

.conditions includ-'ng thelowpowerandflowlevelsconsistent

>>ithnaturalcirculation.

NIAGARAM01(NOKP()I('ER.

CORPORATION bypinotfl.PrattVicePresident Executive Engineer v~

~~~~~-AI~160NOTESFIGURE2.1.1FUELCLADDINGINTEGRITY SAFETYLIMIT140120I-C?U'0100UJI-C)I~w80Cl060II-C3W4020I.Ratedpowerisl538Mwt2.Designflowis67.5xIOIb/hr3.Totalpeakingfactoris<3.134.Corepressureis>585psig5.WaterlevelshallnotbemorethanI'-7II/16"belowmin.normallevel(El.302'-9").

FORPEAKINGFACTORS>3.13 SL=3.13XSLOPFWHERE:SL=SAFETYLIMITFORPEAKINGFACTORS>3.13PF=PEAKINGFACTOR>3.13 SLO=SAFETYLIMITSHOWNABOVE1000PSIG1235PSIG001020304050607080RECIRCULATION FLOW(%OFOESIGN)90'10011012010 0:+Egg~~

Retrieved from "https://kanterella.com/w/index.php?title=ML17037C337&oldid=756942"