NRC-23-0079, Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22
| ML23348A164 | |
| Person / Time | |
|---|---|
| Site: | Fermi  |
| Issue date: | 12/14/2023 |
| From: | Frank E DTE Electric Company |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| NRC-23-0079 | |
| Download: ML23348A164 (1) | |
Text
DTE ElectricCompany 6400 N. Dixie Highway Newport, MI 48166 DTE
December 14, 2023 TS 5.6.5 NRC-23-0079
U.S. Nuclear Regulatory Commission Attention: Document Control Desk Washington, DC 20555-0001
Fermi 2 Power Plant NRC Docket No. 50-341 NRC License No. NPF-43
Subject:
Transmittal of Revision 1 of the Core Operating Limits Report for Cycle 22
In accordance with Fermi 2 Technical Specification 5.6.5, DTE Electric Company (DTE) hereby submits a copy of the Core Operating Limits Report (COLR) for Cycle 22, Revision 1. This COLR will be used during the remainder of the Fermi 2 twenty-second operating cycle.
No new commitments are being made in this submittal.
Should you have any questions or require additional information, please contact me at (734)586-4772.
Sincerely,
Eric Frank Manager - Nuclear Licensing
Enclosure:
Core Operating Limits Report (COLR), Cycle 22, Revision 1
cc: NRC Project Manager NRC Resident Office Regional Administrator, Region III Enclosure to NRC-23-0079
Fermi 2 NRC Docket No. 50-341 Operating License No. NPF-43
Core Operating Limits Report (COLR), Cycle 22, Revision 1 COLR - 22 Revision 1 Page 1 of30
FERMI2
CORE OPERATING LIMITS REPORT
CYCLE22
REVISION 1
Prepared by: 10/23/2023 Paul R. Kiel Date Principal Technical Expert, Reactor Engineering
Reviewed by: 10/24/23 Brian Lefevre Date Lead Engineer, Reactor Engineering
Approved by: /0,27.,~
Michael A. Lake Date Supervisor, Reactor Engineering
November 2023 COLR-22Revision1 Page2of30
TABLEOFCONTENTS
1.0INTRODUCTION
AND
SUMMARY
....................................................................................4 2.0SAFETYLIMITMINIMUMCRITICALPOWERRATIO..................................................5 2.1Definition........................................................................................................................5 2.2DeterminationofCycleSpecificSLMCPR....................................................................5 3.0AVERAGEPLANARLINEARHEATGENERATIONRATE............................................6 3.1Definition........................................................................................................................6 3.2DeterminationofMAPLHGRLimit...............................................................................6 3.2.1CalculationofMAPFAC(P).....................................................................................9 3.2.2CalculationofMAPFAC(F)...................................................................................11 4.0MINIMUMCRITICALPOWERRATIO.............................................................................12 4.1Definition......................................................................................................................12 4.2DeterminationofOperatingLimitMCPR....................................................................12 4.3CalculationofMCPR(P)...............................................................................................14 4.3.1CalculationofKP....................................................................................................14 4.3.2Calculationof 't.......................................................................................................17 4.4CalculationofMCPR(F)................................................................................................18 5.0LINEARHEATGENERATIONRATE...............................................................................19 5.1Definition......................................................................................................................19 5.2DeterminationofLHGRLimit......................................................................................19 5.2.1CalculationofLHGRFAC(P).................................................................................22 5.2.2CalculationofLHGRFAC(F).................................................................................24 6.0CONTROLRODBLOCKINSTRUMENTATION.............................................................25 6.1Definition......................................................................................................................25 7.0BACKUPSTABILITYPROTECTIONREGIONS.............................................................26 7.1Definition......................................................................................................................26
8.0REFERENCES
......................................................................................................................29 COLR-22Revision1 Page3of30
LISTOFTABLES
TABLE1FUELTYPE-DEPENDENTSTANDARDMAPLHGRLIMITS............................7
TABLE2FLOW-DEPENDENTMAPLHGRLIMITCOEFFICIENTS................................11
TABLE3OLMCPR100/105ASAFUNCTIONOFEXPOSUREAND................................13
't TABLE4FLOW-DEPENDENTMCPRLIMITCOEFFICIENTS........................................18
TABLE5STANDARDLHGRLIMITSFORVARIOUSFUELTYPES..............................20
TABLE6FLOW-DEPENDENTLHGRLIMITCOEFFICIENTS.........................................24
TABLE7CONTROLRODBLOCKINSTRUMENTATIONSETPOINTSWITHFILTER25
LISTOFFIGURES
FIGURE1BSPREGIONS(NOMINALFEEDWATERTEMPERATURE).........................27
FIGURE2BSPREGIONS(FEEDWATERTEMPERATUREREDUCTION).....................28 COLR-22Revision1 Page4of30
1.0INTRODUCTION
AND
SUMMARY
Thisreportprovidesthecyclespecificplantoperatinglimits,whicharelistedbelow,forFermi2, Cycle22,asrequiredbyTechnicalSpecification5.6.5.Theanalyticalmethodsusedtodetermine thesecoreoperatinglimitsarethosepreviouslyreviewedandapprovedbytheNuclearRegulatory CommissioninGESTARII(Reference7).
Thecyclespecificlimitscontainedwithinthisreportarevalidforthefullrangeofthelicensed operatingdomain.
OPERATINGLIMITTECHNICALSPECIFICATION
SLMCPR95/952.1.1.2
APLHGR3.2.1
MCPR3.2.2
LHGR3.2.3
RBM3.3.2.1
BSPREGIONS3.3.1.1
SLMCPR=SAFETYLIMITMINIMUMCRITICALPOWERRATIO
APLHGR=AVERAGEPLANARLINEARHEATGENERATIONRATE
MCPR=MINIMUMCRITICALPOWERRATIO
LHGR=LINEARHEATGENERATIONRATE
RBM=RODBLOCKMONITOR
BSP=BACKUPSTABILITYPROTECTION COLR-22Revision1 Page5of30
2.0SAFETYLIMITMINIMUMCRITICALPOWERRATIO
2.1Definition
TECHSPECIDENTOPERATINGLIMIT
2.1.1.2SLMCPR95/95
TheTechnicalSpecificationSAFETYLIMITMINIMUMCRITICALPOWERRATIO (SLMCPR95/95)shallbethesmallestcriticalpowerratiothatexistsinthecoreforeachfuelproduct.
TheTechnicalSpecificationSafetyLimitvalueisdependentonthefuelproductlineandthe correspondingMCPRcorrelation,whichiscycleindependent.ThevalueisbasedontheCritical PowerRatiodatastatisticsanda95%probabilitywith95%confidencethatrodsarenotsusceptible toboilingtransition.(Reference14)
TheCycleSpecificSLMCPR99.9presentedhereisthatpowerinthebundlethatisstatistically calculatedbyapplicationoftheappropriatecorrelationsanduncertaintiestocausesomepointin thebundletoexperienceboilingtransition,dividedbytheactualbundleoperatingpower.
2.2DeterminationofCycleSpecificSLMCPR
TheCycleSpecificSLMCPR,whichisalsoknownasSLMCPR99.9,iscycledependentandensures 99.9%ofthefuelrodsinthecorearenotsusceptibletoboilingtransition.(Reference14)The OperatingLimitMCPRissetbyaddingtheSLMCPR99.9andthechangeinMCPRforthemost limitinganticipatedoperationaloccurrencesuchthatfuelcladdingwillnotsustaindamagebecause ofnormaloperationandanticipatedoperationaloccurrences.
TheSLMCPR99.9issetsuchthatnosignificantfueldamageiscalculatedtooccurifthelimitis notviolated.Sincetheparametersthatresultinfueldamagearenotdirectlyobservableduring reactoroperation,thethermalandhydraulicconditionsthatresultintheonsetoftransitionboiling areusedtomarkthebeginningoftheregioninwhichfueldamagecouldoccur.Althoughtheonset oftransitionboilingwouldnotresultindamagetoBWRfuelrods,thecriticalpoweratwhich boilingtransitioniscalculatedtooccurhasbeenadoptedasaconvenientlimit.
Forthiscycle,theTwoLoopandSingleLoopSLMCPR99.9values(Reference2)are:
TwoLoopSLMCPR=1.08
SingleLoopSLMCPR=1.11 COLR-22Revision1 Page6of30
3.0AVERAGEPLANARLINEARHEATGENERATIONRATE
3.1Definition
TECHSPECIDENTOPERATINGLIMIT
3.2.1APLHGR
TheAVERAGEPLANARLINEARHEATGENERATIONRATE(APLHGR)shallbe applicabletoaspecificplanarheightandisequaltothesumoftheLINEARHEAT GENERATIONRATEs(LHGRs)forallthefuelrodsinthespecifiedbundleatthespecified heightdividedbythenumberoffuelrodsinthebundleattheheight.
3.2DeterminationofMAPLHGRLimit
ThemaximumAPLHGR(MAPLHGR)limitisafunctionofreactorpower,coreflow,fueltype, andaverageplanarexposure.Thelimitisdeveloped,usingNRCapprovedmethodologydescribed inReferences7and8,toensuregrosscladdingfailurewillnotoccurfollowingalossofcoolant accident(LOCA).TheMAPLHGRlimitensuresthatthepeakcladtemperatureduringaLOCA willnotexceedthelimitsasspecifiedin10CFR50.46(b)(1)andthatthefueldesignanalysiscriteria definedinReferences7and8willbemet.
TheMAPLHGRlimitduringdualloopoperationiscalculatedbythefollowingequation:
MAPLHGRLIMIT=MIN(MAPLHGR(P),MAPLHGR(F))
where:
MAPLHGR(P)=MAPFAC(P)xMAPLHGRSTD
MAPLHGR(F)=MAPFAC(F)xMAPLHGRSTD
Withinfourhoursafterenteringsingleloopoperation,theMAPLHGRlimitiscalculatedbythe followingequation:
MAPLHGRLIMIT=MIN(MAPLHGR(P),MAPLHGR(F))
where:
MAPLHGR(P)=MAPFAC(P)xMAPLHGRSTD
MAPLHGR(F)=MAPFAC(F)xMAPLHGRSTD
MAPFAC(P)andMAPFAC(F)arelimitedto0.90
TheSingleLoopOperationmultiplieronMAPLHGRis0.90.(Reference2)
COLR-22Revision1 Page7of30
MAPLHGRSTD,thestandardMAPLHGRlimit,isdefinedatapowerof3486MWthandflowof 105Mlbs/hrforeachfueltypeasafunctionofaverageplanarexposureandispresentedinTable 1.(Reference2)Whenhandcalculationsarerequired,MAPLHGRSTDshallbedeterminedby interpolationfromTable1.MAPFAC(P),thecorepower-dependentMAPLHGRlimitadjustment factor,shallbecalculatedbyusingSection3.2.1.MAPFAC(F),thecoreflow-dependent MAPLHGRlimitadjustmentfactor,shallbecalculatedbyusingSection3.2.2.
TABLE1 FUELTYPE-DEPENDENT STANDARDMAPLHGRLIMITS
GE14Exposure GE14MAPLHGR GWD/ST kW/ft
0.0 12.82 14.51 12.82 19.13 12.82 57.61 8.00 63.50 5.00
FuelTypes GE14-P10CNAB385-13G=-100T-150-T6-4571 GE14-P10CNAB384-15G=-100T-150-T6-4572 GE14-P10CNAB383-13G=-100T-150-T6-4573 GE14-P10CNAB377-15G=-100T-150-T6-4574 GE14-P10CNAB383-8G6.0/5G5.0-100T-150-T6-4478 GE14-P10CNAB383-8G6.0/7G5.0-100T-150-T6-4479 GE14-P10CNAB383-2G6.0/11G5.0-100T-150-T6-4480 GE14-P10CNAB383-10G6.0/5G5.0-100T-150-T6-4481 COLR-22Revision1 Page8of30
TABLE1(Continued)
FUELTYPE-DEPENDENT STANDARDMAPLHGRLIMITS
GNF3Exposure GNF3MAPLHGR GWD/ST kW/ft
0.0 14.36 9.07 13.78 21.22 13.01 40.82 10.75 57.60 8.00 63.50 6.00
FuelTypes GNF3-P10CG3B388-14GZ-83AV-150-T6-4661 GNF3-P10CG3B399-14GZ-83AV-150-T6-4662 GNF3-P10CG3B402-16GZ-83AV-150-T6-4663 GNF3-P10CG3B419-16GZ-83AV-150-T6-4664 GNF3-P10CG3B403-16GZ-83AV-150-T6-4888 GNF3-P10CG3B403-15GZ-83AV-150-T6-4889 GNF3-P10CG3B421-13GZ-83AV-150-T6-4890 GNF3-P10CG3B420-13GZ-83AV-150-T6-4891 GNF3-P10CG3B404-16GZ-83AV-150-T6-4892 GNF3-P10CG3B404-14GZ-83AV-150-T6-4893 COLR-22Revision1 Page9of30
3.2.1CalculationofMAPFAC(P)
Thecorepower-dependentMAPLHGRlimitadjustmentfactor,MAPFAC(P)(Reference2,3&
10),shallbecalculatedbyoneofthefollowingequations.
For 0 ::: P < 25 :
Nothermallimitsmonitoringisrequired.
For 25 ::: P ::: 29.5 :
WithAllEquipmentOPERABLE,orMSRINOPERABLE
Forcoreflow<50Mlbs/hr, MAPFAC(P)=0.568+0.00156(P-29.5)
For core flow ~ 50 Mlbs/hr,
MAPFAC(P)=0.568+0.00156(P-29.5)
WithTurbineBypassINOPERABLE,orTurbineBypassandMSRINOPERABLE
Forcoreflow<50Mlbs/hr, MAPFAC(P)=0.488+0.01067(P-29.5)
For core flow ~ 50 Mlbs/hr,
MAPFAC(P)=0.436+0.00511(P-29.5)
For 29.5 < P ::: 45 :
MAPFAC(P)=0.713+0.00529(P-45)
For 45 < P ::: 60 :
MAPFAC(P)=0.791+0.00520(P-60)
For 60 < P ::: 85 :
MAPFAC(P)=0.922+0.00524(P-85)
For 85 < P ::: 100 :
MAPFAC(P)=1.000+0.00520(P-100)
where:P=Corepower(fractionofratedpowertimes100).
COLR-22Revision1 Page10of30
MAPFAC(P)forPressureRegulatorOutofService(PROOS)Limits WithoneTurbinePressureRegulatorOutofServiceandReactorPowerGreaterThanorEqual to25%andbothTurbineBypassandMoistureSeparatorReheater(MSR)Operable:
For 25 ::; P ::; 29.5 :
Forcoreflow<50Mlbs/hr, MAPFAC(P)=0.568+0.00156(P-29.5)
For core flow ~ 50 Mlbs/hr,
MAPFAC(P)=0.568+0.00156(P-29.5)
For 29.5 < P ::; 45 :
MAPFAC(P)=0.680+0.00626(P-45)
For 45 < P ::; 60 :
MAPFAC(P)=0.758+0.00520(P-60)
For 60 < P ::; 85 :
MAPFAC(P)=0.831+0.00292(P-85)
For 85 < P ::; 100 :
MAPFAC(P)=1.000+0.00520(P-100)
where:P=Corepower(fractionofratedpowertimes100).
Note:Pressureregulatorinserviceandoutofservicelimitsareidenticalforpower>85%.
COLR-22Revision1 Page11of30
3.2.2CalculationofMAPFAC(F)
Thecoreflow-dependentMAPLHGRlimitadjustmentfactor,MAPFAC(F)(Reference2,3,&
10),shallbecalculatedbythefollowingequation:
MIN x--WTA(C,=MAPFAC(F)FF)B+100
where:
WT=Coreflow(Mlbs/hr).
AF=GiveninTable2.
BF=GiveninTable2.
C=1.0inDualLoopand0.90inSingleLoop.
TABLE2FLOW-DEPENDENTMAPLHGRLIMITCOEFFICIENTS
MaximumCoreFlow*
(Mlbs/hr)AFBF
1100.88890.2613
- AslimitedbytheRecirculationSystemMGSetmechanicalscooptubestopsetting.
COLR-22Revision1 Page12of30
4.0MINIMUMCRITICALPOWERRATIO
TECHSPECIDENTOPERATINGLIMIT
3.2.2MCPR
4.1Definition
TheMINIMUMCRITICALPOWERRATIO(MCPR)shallbethesmallestCriticalPowerRatio (CPR)thatexistsinthecoreforeachtypeoffuel.TheCPRisthatpowerinthebundlethatis calculatedbyapplicationoftheappropriatecorrelation(s)tocausesomepointinthebundleto experienceboilingtransition,dividedbytheactualbundleoperatingpower.
4.2DeterminationofOperatingLimitMCPR
TherequiredOperatingLimitMCPR(OLMCPR)(Reference2)atsteady-stateratedpowerand flowoperatingconditionsisderivedfromtheestablishedfuelcladdingintegritySafetyLimit MCPRandananalysisofabnormaloperationaltransients.ToensurethattheSafetyLimitMCPR isnotexceededduringanyanticipatedabnormaloperationaltransient,themostlimitingtransients havebeenanalyzedtodeterminewhicheventwillcausethelargestreductioninCPR.Three differentcoreaverageexposureconditionsareevaluated.TheresultisanOperatingLimitMCPR whichisafunctionofexposureand. isameasureofscramspeedandisdefinedinSection
4.3.2. ThelimitingOLMCPRshallberepresentedbythefollowingequation
OLMCPR = MA; (MCPR(P),MCPR(F))
TheprocesstocalculateMCPR(P),thecorepower-dependentMCPRoperatinglimit,isillustrated inSection4.3.
TheprocesstocalculateMCPR(F),thecoreflow-dependentMCPRoperatinglimit,isillustrated inSection4.4.
IncaseofSingleLoopOperation,theSafetyLimitMCPRisincreasedtoaccountforincreased uncertaintiesincoreflowmeasurementandTIPmeasurement.ForSingleLoopOperation,the OLMCPRisincreasedby0.03(Reference2)fromtheTwoLoopOLMCPR.
COLR-22Revision1 Page13of30
IncaseofoperationwithoneTurbinePressureRegulatoroutofservice,OLMCPRlimitsare boundingwhenreactorpowerislessthan29.5%orgreaterthan85%.Whenreactorpoweris greaterthanorequalto29.5%andlessthanorequalto85%,thenoperationwithoneTurbine PressureRegulatoroutofserviceispermittedifbothTurbineBypassValvesandtheMoisture SeparatorReheaterareoperable.(Reference2,3,and19)
TABLE3OLMCPR100/105ASAFUNCTIONOFEXPOSUREAND
EXPOSURE CONDITION (MWD/ST) OLMCPR100/105
BOTHTurbineBypassValves ANDMoistureSeparatorReheater TwoLoopSingleLoop OPERABLE BOCto3133 =0 1.44 1.47
=1 1.44 1.47 3133to EOR-5491 =0 1.29 1.32
=1 1.38 1.41 EOR-5491to EOR-3991 =0 1.30 1.33
=1 1.40 1.43 EOR-3991to EOC =0 1.33 1.36
=1 1.43 1.46 ONETurbinePressureRegulatorOutofService ANDReactorPowerbetween29.5%and85%
AND BOTHTurbineBypassValvesandMoistureSeparatorReheaterOperable
BOCto3133 =0 1.44 1.47
=1 1.44 1.47 3133toEOC =0 1.37 1.40
=1 1.48 1.51 MoistureSeparatorReheater INOPERABLEBOCto 3133 =0 1.44 1.47
=1 1.48 1.51 3133toEOC =0 1.37 1.40
=1 1.48 1.51
BOC=BeginningofCycleEOC=EndofCycleEOR=EndofRatedConditions.
EORisdefinedas100%power,100%coreflow,andallcontrolrodsfullywithdrawn.
EOR-5491means5491MWD/STbeforeEndofRatedConditions.
COLR-22Revision1 Page14of30
TABLE3(continued)OLMCPR100/105ASAFUNCTIONOFEXPOSUREAND
EXPOSURE CONDITION (MWD/ST) OLMCPR100/105
TurbineBypassValve INOPERABLEBOCto 3133 't =0 1.44 1.47
't =1 1.47 1.50 3133toEOC 't =0 1.38 1.41
't =1 1.50 1.53 BOTHTurbineBypassValve ANDMoistureSeparatorReheater INOPERABLEBOCto 3133 't =0 1.44 1.47
't =1 1.50 1.53 INOPERABLE 3133toEOC 't =0 1.38 1.41
't =1 1.50 1.53
4.3CalculationofMCPR(P)
MCPR(P),thecorepower-dependentMCPRoperatinglimit,shallbecalculatedbythefollowing equation:
MCPR P ()=Kp OLMCPR100 x/10s
KP,thecorepower-dependentMCPROperatingLimitadjustmentfactor,shallbecalculatedby usingSection4.3.1.OLMCPR100/105shallbedeterminedbyinterpolationon't fromTable3,and
't shallbecalculatedbyusingSection4.3.2.
4.3.1CalculationofKP
Thecorepower-dependentMCPRoperatinglimitadjustmentfactor,KP(Reference2,3,10,&
19),shallbecalculatedbyusingoneofthefollowingequations:
Note:P=Corepower(fractionofratedpowertimes100)forallcalculationofKP.
For0<P<25:
Nothermallimitsmonitoringisrequired.
COLR-22Revision1 Page15of30
For25<P<29.5:
WhenAllEquipmentisOPERABLE,
Forcoreflow<50Mlbs/hr,
( KBYP + ( 0 0067 29 5 - P.x(.)) )
= OLMCPR 100
/10 5
where:KBYP=1.95fortwoloopoperation
=1.98forsingleloopoperation
For core flow 2: 50 Mlbs/hr,
( KBYP + ( 0 0156 29 5 - P.x(.)) )
= OLMCPR 100
/10 5
where:KBYP=2.13fortwoloopoperation
=2.16forsingleloopoperation
For25<P<29.5:(continued)
WhenMoistureSeparatorReheaterisINOPERABLE,
Forcoreflow<50Mlbs/hr,
( KBYP + ( 0 0067 29 5 - P.x(.)) )
= OLMCPR 100 10 5
/
where:KBYP=1.95fortwoloopoperation
=1.98forsingleloopoperation
For core flow 2: 50 Mlbs/hr,
( KBYP + ( 0 0156 29 5 - P.x(.)) )
= OLMCPR 100 10 5
/
where:KBYP=2.13fortwoloopoperation
=2.16forsingleloopoperation
WhenTurbineBypassisINOPERABLE,
( KBYP + ( 0 0244 29 5 - P.x(.)) )
= OLMCPR 100 10 5
/
For core flow 2: or< 50 Mlbs/hr, where: K BYP=2.35fortwoloopoperation
=2.38forsingleloopoperation COLR-22Revision1 Page16of30
WhenTurbineBypassandMoistureSeparatorHeaterareINOPERABLE,
Forcoreflow<50Mlbs/hr,
( KBYP + ( 0 0244 29 5 - P.x(.)) )
= OLMCPR 100
/10 5
where:KBYP=2.35fortwoloopoperation
=2.38forsingleloopoperation
For core flow 2: 50 Mlbs/hr, (KBYP + (o 0178 29 5 -P.x(.)))
= OLMCPR 100 10 5
/
where:KBYP=2.42fortwoloopoperation
=2.45forsingleloopoperation
For29.5<P<45:
=1.150+ ( 45-P) 0.0021x()
For45<P<60:
=1.150
For60<P<85:
=1.056+ ( 85-P) 0.0038x()
For85<P<100:
=1.000+ ( 100 -P) 0.0037x()
KPforPressureRegulatorOutofServiceLimits WithoneTurbinePressureRegulatorOutofService,ReactorPowergreaterthan29.5%,and bothTurbineBypassandMoistureSeparatorReheaterOperable:
For29.5<P<45:
=1.303+ ( 45-P) 0.0081x()
For45<P<60:
=1.241+ ( 60-P) 0.0041x()
For60<P<85:
=1.159+ ( 85-P) 0.0033x()
ForReactorPower<29.5%andReactorPower>85%,thePressureRegulatorOutofService conditionisnotlimiting(Reference2and19).
COLR-22Revision1 Page17of30
4.3.2Calculationof 't
Thevalueof 't,whichisameasureoftheconformanceoftheactualcontrolrodscramtimestothe assumedaveragecontrolrodscramtimeinthereloadlicensinganalysis(References4&16),shall becalculatedbyusingthefollowingequation:
T -r Bave)(=
't T -T AB
where: A=1.096seconds
B=0.830+0.019x1.65 N 1seconds n
Jf Ni i1
n N ii ave= i1 n
Ni i1
n=numberofsurveillancetestsperformedtodateincycle,
Ni=numberofactivecontrolrodsmeasuredintheithsurveillancetest,
i=averagescramtimetonotch36ofallrodsmeasuredinthe ithsurveillancetest,and
N1=totalnumberofactiverodsmeasuredintheinitialcontrolrodscramtime testforthecycle(TechnicalSpecificationSurveillanceRequirement 3.1.4.4).
Thevalueof shallbecalculatedandusedtodeterminetheapplicableOLMCPR100/105valuefrom Table3within72hoursoftheconclusionofeachcontrolrodscramtimesurveillancetestrequired byTechnicalSpecificationSurveillanceRequirements3.1.4.1,3.1.4.2,and3.1.4.4.
COLR-22Revision1 Page18of30
4.4CalculationofMCPR(F)
MCPR(F),thecoreflow-dependentMCPRoperatinglimit(Reference2&3),shallbecalculated byusingthefollowingequation:
ForTwoLoopOperation 211MAXx--WTA(,.(=MCPR(F)FF))B+100
ForSingleLoopOperation 241MAXx--WTA(,.(=MCPR(F)FF))B+100
where:
WT=Coreflow(Mlbs/hr).
AF=GiveninTable4.
BF=GiveninTable4.
TABLE4FLOW-DEPENDENTMCPRLIMITCOEFFICIENTS
MaximumCoreFlow*
(Mlbs/hr)AFBF
TwoLoopOperation110-0.5961.739
SingleLoopOperation110-0.5961.769
- AslimitedbytheRecirculationSystemMGSetmechanicalscooptubestopsetting.
COLR-22Revision1 Page19of30
5.0LINEARHEATGENERATIONRATE
TECHSPECIDENTOPERATINGLIMIT
3.2.3LHGR
5.1Definition
TheLINEARHEATGENERATIONRATE(LHGR)shallbetheheatgenerationrateperunit lengthoffuelrod.Itistheintegraloftheheatfluxovertheheattransferareaassociatedwiththe unitlength.BymaintainingtheoperatingLHGRbelowtheapplicableLHGRlimit,itisassured thatallthermal-mechanicaldesignbasesandlicensinglimitsforthefuelwillbesatisfied.
5.2DeterminationofLHGRLimit
ThemaximumLHGRlimitisafunctionofreactorpower,coreflow,fuelandrodtype,andfuel rodnodalexposure.Thelimitisdeveloped,usingNRCapprovedmethodologydescribedin Reference7,toensurethecladdingwillnotexceeditsyieldstressandthatfuelthermal-mechanical designcriteriawillnotbeviolatedduringanypostulatedtransientevents.TheLHGRlimitensures thefuelmechanicaldesignrequirementsasdefinedinReferences1,15,&17willbemet.
TheLHGRlimitduringdualloopoperationiscalculatedbythefollowingequation:
LHGRLIMIT=MIN(LHGR(P),LHGR(F))
where:
LHGR(P)=LHGRFAC(P)xLHGRSTD
LHGR(F)=LHGRFAC(F)xLHGRSTD
Withinfourhoursafterenteringsingleloopoperation,theLHGRlimitiscalculatedbythe followingequation:
LHGRLIMIT=MIN(LHGR(P),LHGR(F))
where:
LHGR(P)=LHGRFAC(P)xLHGRSTD
LHGR(F)=LHGRFAC(F)xLHGRSTD
LHGRFAC(P)andLHGRFAC(F)arelimitedto0.90
TheSingleLoopOperationmultiplieronLHGRis0.90.(Reference2)
COLR-22Revision1 Page20of30
LHGRSTD,thestandardLHGRlimit,isdefinedatapowerof3486MWthandflowof105Mlbs/hr foreachfuelandrodtypeasafunctionoffuelrodnodalexposure.LHGRSTDisfoundinthe referencecitedinTable5.Whenhandcalculationsarerequired,LHGRSTDshallbedetermined byinterpolationofthelimitsprovidedintheTable5reference.LHGRFAC(P),thecorepower-dependentLHGRlimitadjustmentfactor,shallbecalculatedbyusingSection5.2.1.
LHGRFAC(F),thecoreflow-dependentLHGRlimitadjustmentfactor,shallbecalculatedby usingSection5.2.2.
TABLE5 STANDARDLHGRLIMITSFORVARIOUSFUEL TYPES
ForGE14fuellistedbelow,themostlimitingLHGRfor UraniumOnlyfuelrodisfoundinNEDC-32868PRevision6 TableD-2(References1&15).
ForGE14fuellistedbelow,themostlimitingLHGRfor GadoliniaBearingfuelrodsisfoundinNEDC-32868P Revision6TableD-4(References1&15).Utilizetherowfor 6%Rod/Sectionwt-%Gd2O3.
FuelTypes GE14-P10CNAB385-13G=-100T-150-T6-4571 GE14-P10CNAB384-15G=-100T-150-T6-4572 GE14-P10CNAB383-13G=-100T-150-T6-4573 GE14-P10CNAB377-15G=-100T-150-T6-4574 GE14-P10CNAB383-8G6.0/5G5.0-100T-150-T6-4478 GE14-P10CNAB383-8G6.0/7G5.0-100T-150-T6-4479 GE14-P10CNAB383-2G6.0/11G5.0-100T-150-T6-4480 GE14-P10CNAB383-10G6.0/5G5.0-100T-150-T6-4481 COLR-22Revision1 Page21of30
TABLE5(CONT.)
STANDARDLHGRLIMITSFORVARIOUSFUEL TYPES
ForGNF3fuellistedbelow,themostlimitingLHGRfor UraniumOnlyfuelrodisfoundinNEDC-33879PRevision2 TableA-1(References1&17).
ForGNF3fuellistedbelow,themostlimitingLHGRfor GadoliniaBearingfuelrodsisfoundinNEDC-33879P Revision2TableA-2(References1&17).Utilizetherowfor 6%Rod/Sectionwt-%Gd2O3.
FuelTypes GNF3-P10CG3B388-14G=-83AV-150-T6-4661 GNF3-P10CG3B399-14G=-83AV-150-T6-4662 GNF3-P10CG3B402-16G=-83AV-150-T6-4663 GNF3-P10CG3B419-16G=-83AV-150-T6-4664 GNF3-P10CG3B403-16G=-83AV-150-T6-4888 GNF3-P10CG3B403-15G=-83AV-150-T6-4889 GNF3-P10CG3B421-13G=-83AV-150-T6-4890 GNF3-P10CG3B420-13G=-83AV-150-T6-4891 GNF3-P10CG3B404-16G=-83AV-150-T6-4892 GNF3-P10CG3B404-14G=-83AV-150-T6-4893 COLR-22Revision1 Page22of30
5.2.1CalculationofLHGRFAC(P)
Thecorepower-dependentLHGRlimitadjustmentfactor,LHGRFAC(P)(Reference2,3,&10),
shallbecalculatedbyoneofthefollowingequations:
For 0 ::: P < 25 :
Nothermallimitsmonitoringisrequired.
For 25 ::: P ::: 29.5 :
WithAllEquipmentOPERABLE,orMSRINOPERABLE
Forcoreflow<50Mlbs/hr, LHGRFAC(P)=0.568+0.00156(P-29.5)
For core flow ~ 50 Mlbs/hr,
LHGRFAC(P)=0.568+0.00156(P-29.5)
WithTurbineBypassINOPERABLE,orTurbineBypassandMSRINOPERABLE
Forcoreflow<50Mlbs/hr, LHGRFAC(P)=0.488+0.01067(P-29.5)
For core flow ~ 50 Mlbs/hr,
LHGRFAC(P)=0.436+0.00511(P-29.5)
For 29.5 < P ::: 45 :
LHGRFAC(P)=0.713+0.00529(P-45)
For 45 < P ::: 60 :
LHGRFAC(P)=0.791+0.00520(P-60)
For 60 < P ::: 85 :
LHGRFAC(P)=0.922+0.00524(P-85)
For 85 < P ::: 100 :
LHGRFAC(P)=1.000+0.00520(P-100)
where:P=Corepower(fractionofratedpowertimes100).
COLR-22Revision1 Page23of30
LHGRFAC(P)forPressureRegulatorOutofServiceLimits WithoneTurbinePressureRegulatorOutofServiceandReactorPowerGreaterThanorEqual to25%andbothTurbineBypassandMoistureSeparatorReheaterOperable:
For 25 ::; P ::; 29.5 :
Forcoreflow<50Mlbs/hr, LHGRFAC(P)=0.568+0.00156(P-29.5)
For core flow ~ 50 Mlbs/hr,
LHGRFAC(P)=0.568+0.00156(P-29.5)
For 29.5 < P ::; 45 :
LHGRFAC(P)=0.680+0.00626(P-45)
For 45 < P ::; 60 :
LHGRFAC(P)=0.758+0.00520(P-60)
For 60 < P ::; 85 :
LHGRFAC(P)=0.831+0.00292(P-85)
For 85 < P ::; 100 :
LHGRFAC(P)=1.000+0.00520(P-100)
where:P=Corepower(fractionofratedpowertimes100).
COLR-22Revision1 Page24of30
5.2.2CalculationofLHGRFAC(F)
Thecoreflow-dependentLHGRlimitadjustmentfactor,LHGRFAC(F)(Reference2,3,&10),
shallbecalculatedbythefollowingequation:
MIN x--WTA(C,=LHGRFAC(F)FF)B+100
where:
WT=Coreflow(Mlbs/hr).
AF=GiveninTable6.
BF=GiveninTable6.
C=1.0inDualLoopand0.90inSingleLoop.
TABLE6FLOW-DEPENDENTLHGRLIMITCOEFFICIENTS
MaximumCoreFlow*
(Mlbs/hr)AFBF
1100.88890.2613
- AslimitedbytheRecirculationSystemMGSetmechanicalscooptubestopsetting.
COLR-22Revision1 Page25of30
6.0CONTROLRODBLOCKINSTRUMENTATION
TECHSPECIDENTSETPOINT
3.3.2.1RBM
6.1Definition
Thenominaltripsetpointsandallowablevaluesofthecontrolrodwithdrawalblock instrumentationareshowninTable7.ThesevaluesareconsistentwiththebasesoftheAPRM RodBlockTechnicalSpecificationImprovementProgram(ARTS)andtheMCPRoperating limits.(References2,5,&9)
TABLE7CONTROLRODBLOCKINSTRUMENTATIONSETPOINTSWITH FILTER
Setpoint TripSetpoint AllowableValue
Lowpowersetpoint 27.028.4 Intermediatepowersetpoint 62.063.4 Highpowersetpoint 82.083.4
Lowtripsetpoint 117.0118.9 Intermediatetripsetpoint 112.2114.1 Hightripsetpoint 107.2109.1
Downscaletripsetpoint 94.092.3
Forthiscycle,theanalyzedhightripsetpointof111%boundsthesetpointsinTable7.The OLMCPRassociatedwiththeRBMsetpointof111%is1.44fordualloopoperationfrom beginningofcycleto3133MWd/stand1.29from3133MWd/sttotheendofcycle.(Reference 2)
COLR-22Revision1 Page26of30
7.0BACKUPSTABILITYPROTECTIONREGIONS
TECHSPECREFERENCEOPERATINGLIMIT 3.3.1.1ActionConditionJAlternatemethodtodetect andsuppressthermalhydraulic instabilityoscillations
TRMREFERENCEOPERATINGLIMIT 3.4.1.1Scram,Exit,andStability AwarenessRegions
7.1Definition
TheBackupStabilityProtection(BSP)RegionsareanintegralpartoftheTechSpecrequired alternativemethodtodetectandsuppressthermalhydraulicinstabilityoscillationsinthatthey identifyareasofthepower/flowmapwherethereisanincreasedprobabilitythatthereactorcore couldexperienceathermalhydraulicinstability.TheBSPRegionsarerequirediftheOscillation PowerRangeMonitorsareinoperable.Regionsareidentifiedthatareeitherexcludedfrom plannedentry(ScramRegion),orwherespecificactionsarerequiredtobetakentoimmediately leavetheregion(ExitRegion).Aregionisalsoidentifiedwhereoperationisallowedprovidedthat additionalmonitoringisperformedtoverifythatthereactorcoreisnotexhibitingsignsofcore thermalhydraulicinstability(StabilityAwarenessRegion).(Reference2)
TheboundariesoftheScramandExitregionsareestablishedonacyclespecificbasisbasedupon coredecayratiocalculationsperformedusingNRCapprovedmethodology.
BSPboundariesforthiscycledefinedinFigure1areapplicablewhenfinalfeedwatertemperature isneartheoptimumrangeasillustratedin20.107.02,LossofFeedwaterHeatingAbnormal OperatingInstructionEnclosureA.Figure2isapplicabletooperationwithFeedwaterHeaters Out-Of-Service(FWHOOS)orwithFinalFeedwaterTemperatureReduction(FFWTR)orwhen finalfeedwatertemperatureis15ºFto55ºFbelowtheoptimumrange.
80 COLR -22 Revision 1 Page 27 of 30 FIGURE 1: BSP REGIONS (NOMINAL FEEDWATER TEMPERATURE)
Cycle 22. 'BSP Regions (Nominal FeedwaterTemperature) 100% CLTP = 3486 MWt Rated Core Flow= 100.0Mlb/hr M LLlA Rod Une OPRM Enabled Region 30 +----+----'- -___.;...---:::ill',-r-- +----- ----:----- +--'------- ----:----+-:F:-o-ru-,-*s-ed'u--:ri-ng--=o=-p-er---:at*io-n*in-:-:th;--1e Nominal FW Temperature Region of 20.107.02 Enclosure 20 ------------------------------------------
30 40 50 60 70 Percent{3/4) of Rated Core Flow Nominal feedwater heating exists with all feedwater heaters in service, the moisture separator reheaters in service, and reactor water cleanup in or out of service. Nominal feedwater temperature is determined with the Loss ofFeedwater Heating Abnormal Operating Procedure, 20.107.02. Iffeedwater temperature is less than 15 degrees Fahrenheit below the Optimum Line of the Feedwater Inlet Temperature vs. Reactor Power graph provided in Enclosure A of 20.107.02, then Figure 1 can be used.
COLR -22 Revision 1 Page 28 of 30 FIGURE 2: BSP REGIONS (FEEDWATER TEMPERATURE REDUCTION)
Cycle 22 BSP Regions (SSF Temperature Reduc tion),
100% CL TP = 3486 MWt Rated Core Flow= 100.0 Mlb/hr 70,..__N -at-Lira_l _____________ _______ _ __ __ 1--- -------+---- -<
3 0 a.
_! 60 4-- -f. --.,,,,.,-:_ __ 4-___,; _ ____,,__ ___ _:.,. -.-- -.JE. :._ __..JL- ____ _______ ___ -I
'tl
'o g: so..i.-- - -- ---- - "'1"-- -----..-::-- ---+--- - ---- --- ----------- --1
... C GI GI Cl.
Region For use during Operation om 15F 30 +----f--_;_ __ --::io.-::;...-+--..;-----.;..--1--- --- ----1-----=to_S_S_Fb_e_lo_w--::th,_e_O-':::-pt-:""'.im,,_.u,...,,-1::-F
-=-W::-*----1 Temperature line of 20.10.02 Enclosure A 20 --+----<---+ - - - ---+- - -+-----f - -- - --- - ---11---+- - -+--- - -- - +---- - --i--- - -+----+ --'
30 40 50 60 70 Percent (%} of Rated Core Flow Reduced feedwater temperature is analyzed for a 55 degree Fahrenheit reduction in feedwater temperature. If feedwater temperature is between 15 degrees Fahrenheit to 55 degrees Fahrenheit below the Optimum Line of the Feedwater Inlet Temperature vs. Reactor Power graph provided in Enclosure A of 20.107.02, then Figure 2 should be used.
COLR-22Revision1 Page29of30
8.0REFERENCES
CoreOperatingLimitsReportreferencesarecitedfortwopurposes.Manyreferencesareused asthebasisforinformation,numbers,andequationsfoundinCOLR.Thesereferencestendto befueltypeorcyclespecific.Otherreferencesarelistedasbasisinformationforthecontentand structureofCOLRbutarenotCyclespecific.
1.FuelBundleInformationReportforFermi2Reload21Cycle22,GlobalNuclearFuel, DRF006N0352,Revision0,July2021(LHGRLimits),DTC:TRVEND,DSN:Cycle22 FBIR
2.SupplementalReloadLicensingReportforFermi2Reload21Cycle22,GlobalNuclear Fuel,DRF:006N0351,Revision1,August2023(MAPLHGRLimits,SLOMultiplier, MCPRLimits,SLMCPR,Off-RatedLimits,BackupStabilityRegions,OPRMsetpoints, RBMsetpoint,PROOS),DTC:TRVEND,DSN:Cycle22SRLR
3.GNF3FuelDesignCycle-IndependentAnalysesforFermi2PowerPlant,GE-Hitachi, 004N7423,Revision0,November2019.(GNF3andGE14ARTSLimits,RRPumpSeizure, PROOS),EdisonFileNumber:T19-158
4.LetterfromGregPortertoB.L.Myers,ScramTimesforImprovedTechSpecs.GP-99014,October22,1999,containingDRFA12-00038-3,Vol.4informationfromG.A.
Watford,GE,toDistribution,
Subject:
ScramTimesversusNotchPosition(TAU Calculation),EdisonFileNumber:R1-7242
5.NUMACPowerRangeNeutronMonitoringSystem(PRNM)SurveillanceValidation, DesignCalculationDC-4608Volume1,RevisionG(RBMAandBSetpoints),DTC:
TDPINC,DSN:DC-4608VOLI
6.DetroitEdisonFermi-2ThermalPowerOptimizationTaskT0201:OperatingPower/Flow Map,EdisonFileNumber:T13-050(P-FMapforBSPfigures)
7.GeneralElectricStandardApplicationforReactorFuel(GESTARII),NEDE-24011-P-A, Revision31withamendments,EdisonFileNumber:R1-8103
8.TRACGApplicationforEmergencyCoreCoolingSystems/Loss-of-Coolant-Accident AnalysesforBWR/2-6,GE-Hitachi,NEDE-33005P-A,Revision2,May2018,DTC:
TRVEND,DSN:NEDE33005PA,EdisonFileNumber:R1-8509
9.MaximumExtendedOperatingDomainAnalysisforDetroitEdisonCompanyEnrico FermiEnergyCenterUnit2,GENuclearEnergy,NEDC-31843P,July1990(RBM Setpoints),EdisonFileNumber:R1-7177 COLR-22Revision1 Page30of30
10.Fermi2TRACGImplementationforReloadLicensingTransientAnalysis,Revision1, 0000-0128-8831-R1,June2014,(GE14ARTSLimits),EdisonFileNumber:R1-8124
11.MethodologyandUncertaintiesforSafetyLimitMCPREvaluations,NEDC-32601P-A, August1999,EdisonFileNumber:R1-7239
12.PowerDistributionUncertaintiesforSafetyLimitMCPREvaluations,NEDC-32694P-A, August1999,EdisonFileNumber:R1-7240
13.R-FactorCalculationMethodforGE11,GE12,andGE13Fuel,NEDC-32505P-A, Revision1,July1999,EdisonFileNumber:R1-7238
14.Fermi2-IssuanceofAmendmentNo.214Re:TechnicalSpecificationsTaskForce (TSTF)TSTF-564,"SafetyLimitMinimumCriticalPowerRatio"(EPIDL-2019-LLA-0028)LetterfromSujataGoetz,NRC,toPeterDietrich,DTEElectricdatedNovember5, 2019(SLMCPR) 15.GE14CompliancewithAmendment22ofNEDE-24011-P-A(GESTARII),NEDC-32868P,Revision6,March2016(LHGRLimits),EdisonFileNumber:R1-7307 16.LetterfromG.G.JonestoA.D.Smart,Fermi2TechnicalSpecificationChanges, February17,1989(Tau) 17.GNF3GenericCompliancewithNEDE-24011-P-A(GESTARII),NEDC-33879P, Revision2,March2018(LHGRLimits),EdisonFileNumber:R1-8483 18.DTEEnergyEnricoFermiUnit2TRACGECCSLoss-of-CoolantAccident(LOCA)
Analysis,GE-Hitachi,005N1475,Revision1,November2019,EdisonFileNumber:T19-137 19.008N0291Revision0,FermiCycle22MSRSteamFlowThermalLimitsValidation,August 18,2023(MSRISLimits)EdisonFileNumber:R1-8664