ML21103A409
| ML21103A409 | |
| Person / Time | |
|---|---|
| Site: | Calvert Cliffs  |
| Issue date: | 04/12/2021 |
| From: | Dullinger J Exelon Generation Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML21103A409 (24) | |
Text
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i 2..o0,,,n.or Plant Manager Calvert Chffs Nuclear PowerPlant 1650Calvert Cliffs Parkway
- Lusby, MD 20657 410-495-520S Office 610-765-5881Mobile wwwexeloncorp.com joseph.dullinger@exeloncorpcom TS5.6.5 April 12,2021 U.S.Nuclear Regulatory Commission ATTN:Document Control Desk Mail StopP1-37 OneWhiteFlint North 11555Rockville Pike Rockville MD 20852-2738 Calvert Cliffs Nuclear PowerPlant, UnitNo.1 Renewed Facility Operating License No.DPR-69 NRCDocket No.50-318
Subject:
Pursuant toCalvert Cliffs Nuclear PowerPlant Technical Specification 5.6.5, the attached Core Operating Limits Report forUnit 2,Cycle 24,Revision 0(Attachment 1),
isprovided foryour records.
Please replace theUnit 2CoreOperating Limits Report initsentirety, withtheattached Revision 0.
There arenoregulatory commitments contained inthis correspondence.
Should youhavequestions regarding this
- matter, please contact Mr.Larry D.Smith at(410) 495-5219.
Respectfully, Joseph A.Dullin r
Plant Manager JAD/LDS/lmd
Attachment:
(1)CoreOperating Limits Report forUnit2,Cycle 24,Revision 0
ATTACHMENLLU COREOPERATING LIMITS REPORT FOR UNIT2,CYCLE 24,REVISION 0
Calvert Cliffs Nuclear PowerPlant April 12,2021
j-v i
r in ii COLR Unit2Cycle24 Revision 0
Effective Date: 03/03/2021 Digitally signed bySchearer, Timothy A
- Schearer, Timothy ADN:cn=Schearer, Timothy A
Date:
2021.02.16 12:43:05
-05'00' Responsible Engineer
/ Date Digitally signed byKelllher, Andrew P
DN:cn=Kelllher, Andrew P
Date:
2021.02.16 12:53:06
-05'00' Independent Reviewer/
Date Digitally signed byBroderick, Alexander J.
Broderick, Alexander J.DN:cn=8roderick, Alexander J.
Date:
2021.02.17 16:07:50-05'00' Station Qualified Reviewer/
Date Sr.Manager
- PWRCoreDesign/
Date Calvert Cliffs 2,Cycle 24COLR Page1of22 Rev.0
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COREOPERATINGLIMITSREPORT CALVERTCLIFFSUNIT2,CYCLE24 Thefollowing limits are included in thisCore Operating Limits Report:
SpjsiEcatioIl litle Pagg Introduction.=..,.,.........,,,--,,,,.......,....,,,..,,.,..,.
4 Definitions.,.<..--.-........,,-.,....,.,......,.............
5 Licensing Restrictions...--,,,.,,....,,,.......,,,.,........,.,
6 3.1.1 Shutdown Margin (SDM) 9 3.1.3 Moderator Temperature Coefficient (MTC).,-,......,.,..
9 3.1.4 Control Element Assembly (CEA)
Alignment
.....,=<<..
9 3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits
=,
,=-..,--<
9 3.2.1 Linear HeatRate(LHR).,,..,,,,-.
~.-,,,,,,.,,.,-.,,.,
9 3.2.3 Total Integrated Radial Peaking Factor (F7).-,,,.,,,,,,,,,,,,.,,..,
10 3.2.5 Axial Shape Index (ASI)..--..--,,,,-,.-,,.,=...,,,.-,......
10 3.3.1 Reactor Protective System (RPS)
Instrumentation
- Operating..,,,,-,.,,-.-
10 3.4.1 RCSPressure, Temperature, andFlowDNBLimits 10 3.9.1 Boron Concentration.-....-...-.-...,.,...........-=.....,.-....
11 List ofApproved Methodologies.---.,..,.,.,.......,....
20 Thefollowing figures areincluded inthis CoreOperating Limits Report:
Num.hg.r Iitl.e
.Page Figure 3.1.6CEAGroupInsertion Limits vs.Fraction ofRated Thermal Power..,..,,........
12 Figure 3.2.1-1 Allowable PeakLinear HeatRate vs.TimeinCycle
=.....,.........,.......
13 Figure 3.2.1-2 Linear HeatRateAxial FluxOffset Control Limits
=.=,,.-
14 Figure 3.2.3Total Integrated Radial Peaking Factor(F) vs.
Allowable Fraction ofRated Thermal Power,.,.,,,..,,,,<,--....
15 Figure 3.2.5DNBAxial FluxOffset Control Limits.,,,,,,-....,,....,,,,,,,,,,.,.....
16 Figure 3.3.1-1 Axial PowerDistribution
- HighTrip Setpoint Peripheral Axial Shape Index vs.Fraction ofRated Thermal Power 17 Figure 3.3.1-2 Thermal Margin/Low Pressure Trip Setpoint
- Part1..............,=...............
18 Figure 3.3.1-3 Thermal Margin/Low Pressure Trip Setpoint
- Part 2
19 Calvert Cliffs 2,Cycle 24COLR Page2of22 Rev.0
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Calvert Cliffs 2,Cycle 24COLR Page3of22 Rev.0
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INTRODUCTION This report providesthe cycle-specific limits foroperation ofCalvert Cliffs Unit 2,Cycle 24.It contains thelimits for:
Moderator Temperature Coefficient (MTC)
Control Element Assembly (CEA) Alignment Regulating Control Element Assembly (CEA) Insertion Limits Linear HeatRate(LHR)
Total Integrated Radial Peaking Factor (F?)
Axial Shape Index (ASI)
Reactor Protective System (RPS)
Instrumentation Operating RCSPressure, Temperature, andFlow Departure from Nucleate Boiling (DNB)
Limits BoronConcentration Inaddition, this report contains anumber offigures whichgive limits ontheparameters listed above,Ifanyofthelimits contained inthis report areexceeded, corrective action will betaken as defined intheTechnical Specifications.
This report hasbeenprepared inaccordance with therequirements ofTechnical Specifications.
Thecycle specific limits havebeendeveloped using theNRC-approved methodologies given in the"List ofApproved Methodologies" section ofthis report andinthe Technical Specifications.
COLRRevision 0
Initial release oftheUnit 2Cycle 24(U2C24)
COLR.U2C24mayoperate inall plant modes.
Calvert Cliffs 2,Cycle 24COLR Page4of22 Rev.0
W my i-DEFINITIONS Axial Shape Index (ASI)
ASIshall bethe power generated inthelower half ofthecoreless thepowergenerated in theupper half ofthe
- core, divided bythesumofthepowergenerated inthelower and upper halves ofthecore.
ASI lower upper y
lower+ upper TheAxial Shape Index (Y1) usedfor thetrip and pretripsignals intheReactor Protection System (RPS) istheabove value (YE) modified byanappropriate multiplier (A) anda constant (B) todetermine the truecoreaxial power distribution forthat channel.
Y1=AYE+B Total Integrated Radial Peaking Factor
- Frf TheTotal Integrated Radial Peaking Factor istheratio ofthepeak pinpowertothe average pinpowerinanunrodded core.
Calvert Cliffs 2,Cycle 24COLR Page5of22 Rev.0
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LICENSING RESTRICTIONS 1)Forthe Asymmetric Steam GeneratorTransient analysis performed inaccordance with the methodologyof Technical Specification 5.6.5.b.8, themethodology shall berevised tocapture the asymmetric coreinlet temperaturedistribution andapplication oflocal peaking augmentationfactors.
Therevised methodology shall beapplied toCalvert Cliffs Unit 2core reload designs starting withCycle 19.
2)FortheSeized Rotor Event analysis performed inaccordance with themethodology of Technical Specification 5.6.5.b.8,the methodology shall berevised tocapture the asymmetric coreinlet flow distribution.
The revised methodologyshall beapplied to Calvert Cliffs Unit 2corereload designsstarting withCycle 19.
3)FortheControl Element Assembly Ejection analysis performed inaccordance with the methodology ofTechnical Specification 5.6.5.b.11, the cycle-specific hotzeropower peakaverage radial fuel enthalpy iscalculated based on amodified powerdependent insertion limit with Control Element Assembly Bank3assumed tobefully inserted (only intheanalysis, notinactual plant operations).
This revised methodology shall beapplied toCalvert Cliffs Unit 2corereload designs starting with Cycle 19.
4)TheSmall Break LossofCoolant accident performed inaccordance with the methodology ofTechnical Specification 5.6.5.b.9 shall beanalyzed using abreak spectrum with augmented detail related tobreak size.
This revised methodology shall be applied toCalvert Cliffs Unit 2corereload designs starting with Cycle 19.
5)CoreOperating Limits Report Figures 3.I.6, 3.2.3, and3.2.5 shall notbechanged without prior NRCreview andapproval until anNRC-accepted
- generic, orCalvert Cliffs-specific, basis isdeveloped foranalyzing theControl Element Assembly Rod BankWithdrawal
- Event, theControl Element Assembly
- Drop, andtheControl Element Assembly Ejection (power level-sensitive transients) atfull powerconditions only.
6)Approval oftheuseofS-RELAP5(Technical Specification 5.6.5.b.8) isrestricted only to those safety analyses that confirm acceptable transient performance relative tothe specified acceptable fuel design limits.
Prior transient specific NRCapproval isrequired toanalyze transient performance relative toreactor coolant pressure boundary integrity until NRC-approval isobtained for ageneric orCalvert Cliffs-specific basis fortheuse ofthemethodology inTechnical Specification 5.6.5.b.8 todemonstrate reactor coolant pressure boundary integrity.
NOTE:TheNRChasissued aletter that allows S-RELAP5 tobeusedforthetransient-specific application ofthemethodology toCCNPPonly asdescribed intheletter pertaining toPSVsetpoints.
Itisnotageneric approval ofthemethodology.
Ref: Letter fromAlexander N.Chereskin (NRC) toBryanC.Hanson(Exelon) dated December 30,2015,Calvert Cliffs Nuclear PowerPlant, Unit Nos.1and2 Issuance ofAmendment Re:Revision toPressurizer Safety Valve Technical Specifications (CAC Nos.MF3541andMF3542)
Calvert Cliffs 2,Cycle 24COLR Page6of22 Rev.0
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7)Forthe RODEX2-based fuel thermal-mechanical design analysis performed in accordance with the methodology ofTechnical Specification 5.6.5.b.3, Calvert Cliffs Unit 2core reloaddesigns (starting withCycle 19) shall satisfy thefollowing criteria:
a.Predicted rodinternal pressure shall remain below thesteady state systempressure.
b.Thelinear heat generationrate fuelcenterline melting safety limit shall remain below 21.0KW/ft.
8)FortheControl Element Assembly Ejection analysis, Calvert Cliffs Unit 2corereloads (starting withCycle19) shall satisfy thefollowing criteria:
a.Predicted peakradial average fuel enthalpywhen calculated inaccordance with the methodology ofTechnical Specification 5.6.5.b.1 Ishall remain below 200cal/g.
b.Forthepurpose ofevaluating radiological consequences, should theS-RELAP5 hot spotmodel predict fuel temperature above incipient centerline meltconditionswhen calculated inaccordance with themethodology ofTechnical Specification 5.6.5.b.8, a
conservative radiological source term(in accordance with Regulatory Guide1.183, Revision 0)shall beapplied totheportion offuel beyond incipient melt conditions (and combined withexisting gapsource term),
andcladding failure shall be presumed.
9)Theapproval oftheemergency corecooling systemevaluation performed inaccordance with themethodology ofTechnical Specification 5.6.5.b.7 shall bevalid only forCalvert Cliffs Unit 2,Cycle 19.Toremove this condition, Calvert Cliffs shall obtain NRC approval oftheanalysis ofonce-andtwice-burned fuel forcoredesigns following Unit2 Cycle 19.
JSOTE:
Therevised methodology wassubmitted andreceived NRCapproval inDecember 2012.Thislicense condition issatisfied; however since NRCapproval wasobtained vialetter andnotLAR,this license condition isstill listed inAppendix Cofthe Tech.
Specs.
andhasbeenretained here forconsistency.
Ref: Letter fromDouglas V.Pickett (NRC) toGeorge H.Gellrich (CCNPP) dated February 18,2011,Calvert Cliffs Nuclear PowerPlant, Unit Nos.1and2 Amendment Re:Transition fromWestinghouse Nuclear Fuel toAREVANuclear Fuel(TAC Nos.ME2831andME2832)
Calvert Cliffs 2,Cycle 24COLR Page7of22 Rev.0
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10)UptotwoFramatome PROtectTMLeadTestAssemblies utilizing Chromium-coated M5@cladding andchromia doped pellets maybeplaced inlimiting regions ofthecoreforupto3cycles commencing with the implementation ofAmendment 317.
I1)Thesafety limits specified inTS 2.1.1.2 regardingfuel centerline melt temperature forFramatome
- fuel,
<50810F, decreasing by580F per 10,000 MWD/MTUandadjusted forburnable poison perXN-NF-79-56 (P)(A),
Revision 1,Supplement 1isnotapplicable fortheFramatome PROtectTM LeadTest Assemblies utilizing Chromium-coated M5@
cladding andchromia doped pellets forupto3cycles commencing with theimplementation ofAmendment 317.
12)Therequirement that theRODEX2predicted rod intemal pressure shall remain below thesteady state systempressure isnotapplicable forthe Framatome PROtectTMLeadTestAssemblies utilizing Chromium coated M5@cladding andchromia dopedpellets forupto3cycles commencing with the implementation ofAmendment 317.
- License Condition
- 12supersedes License Condition #7a onlyfortheLeadTestAssembly.
Calvert Cliffs 2,Cycle 24COLR Page8of22 Rev.0
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CYCLE SPECIFIC LIMITSFORUNIT2,CYCLE24 3.1.1Shutdown Margin (SDM) (SR3.1.1.1)
Tavg> 2000F
- Modes 3and4:
Theshutdown marginshall be23.5%Ap.
TavgS2000F
- Mode5:
Theshutdown margin shall be2 3.0% Ap.
3.1.3Moderator Temperature Coefficient (MTC) (SR3.1.3.2)
TheModerator Temperature Coefficient(MTC) shallbeless negative than
-3.1 x104 Ap/0F atrated thermal power.
3.1.4Control Element Assembly (CEA)
Alignment (Action 3.1.4.B.1)
Theallowable time torealign aCEAis120minutes when thepre-misaligned FrT is51.65 andzero(0) minutes whenthepre-misaligned FrT is> 1.65.
Thepre-misaligned FrT value used todetermine the allowabletime torealign theCEAshall bethelatest measurement taken within 5days prior totheCEAmisalignment.
Ifno measurements havebeentaken within 5daysprior tothe misalignment and thefull core power distribution monitoring systemisunavailable thenthetime torealign iszero(0) minutes.
3.1.6Regulating Control Element Assembly (CEA)
Insertion Limits (SR3.1.6.1 andSR3.1.6.2)
Theregulating CEAgroups insertion limits areshown onCOLRFigure 3.1.6.
Figure 3.I.6 will notbechanged unless therequirements inLicensing Restriction 5aremet.
3.2.1Linear HeatRate(LHR)
(SR3.2.1.2 andSR3.2.1.4)
Thelinear heat rateshall notexceed thelimits shown onCOLRFigure 3.2.1-1.
Theaxial shape index powerdependent control limits aregiven inCOLRFigure 3.2.1-2.
Thealarm setpoints areequal toorless than theASIlimits; therefore whenthealarms are
- adjusted, they provide indication totheoperator that ASIisnotwithin thelimits.
Theaxial shape index alarm setpoints areshownasafunction offraction ofthermal power on COLRFigure 3.2.1-2.
Calvert Cliffs 2,Cycle 24COLR Page9of22 Rev.0
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Thealarm setpoints areadjustedtoprotect theLinear HeatRatelimits shown onCOLR Figure 3.2.1-1 and uncertainty factors areappropriately included inthesetting ofthese alarms.
Theuncertainty factorsfor the incoredetector monitoring system are:
- 1. A measurement-calculational uncertainty factor of1.07
- 2. Anengineering uncertaintyfactor of1.03, 3.aFormeasured thermal power less than orequalto50percent butgreater than 20percent ofrated full corepowerathermal power measurement uncertainty factor of1.035.
3.bFormeasured thermal power greater than 50 percent ofrated full corepower athermal power measurement uncertainty factor of1.020.
3.2.3Total Integrated Radial Peaking Factor (FJ)(SR 3.2.3.1)
Thecalculated value ofFrT Shall belimited to5 1.65.
Ifthecalculated FrT eXCeeds theabove
- limit, theallowable combinations ofthermal
- power, CEA
- position, andFrT areshownonCOLRFigure 3.2.3.
Figure 3.2.3 will notbechanged unless therequirements inLicensing Restriction 5aremet.
3.2.5Axial Shape Index(ASI)
Theaxial shape index andthermal powershall bemaintained equal toorless thanthe limits ofCOLRFigure 3.2.5 for CEAinsertions specified byCOLRFigure 3.1.6.
Figure 3.2.5 will notbechanged unless therequirements inLicensing Restriction 5are met.
3.3.1Reactor Protective System(RPS)
Instrumentation
- Operating (Reactor TripSetpoints)
(TSTable3.3.1-1)
TheAxial PowerDistribution
- Hightrip setpoint andallowable values aregiven inCOLR Figure 3.3.1-1.
TheThermal Margin/Low Pressure (TM/LP) trip setpoint isgiven inCOLRFigures 3.3.1-2 and3.3.1-3.
Theallowable values aretobenotless than thelarger of(1) 1875psia or(2) the value calculated fromCOLRFigures 3.3.1-2 and3.3.1-3.
3.4.1RCSPressure, Temperature, andFlowDeparture fromNucleate Boiling (DNB)
Limits TheRCSDNBparameters forpressurizer
- pressure, coldlegtemperature, andRCStotal flow rateshall bewithin thelimits specified below:
a.
Pressurizer pressure 2 2200psia; b.
RCScold legtemperature (Tc) 5 548F;and c.
RCStotal flow rate2 370,000 gpm.
Calvert Cliffs 2,Cycle 24COLR Page10of22 Rev.0
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3.9.1BoronConcentration (SR3.9.1.1)
Therefueling boron concentration will maintain thekerr at0.95 orless (including a1%Ak/k conservative allowance for uncertainties). Therefueling boron concentration shall be maintained uniform.
For Mode6operation theRCStemperature mustbemaintained
< 1400F.
U2C24Refueling Boron Concentration Limits UNIT2CYCLE24 U2C24Cycle Average Exposure 0GWD/MTU
> 16GWD/MTU NumberofCredited CEAs 0
0 Post-Refueling UGSorRVHeadLift Height NoRestriction NoRestriction Restrictions.
Minimum Required Refueling Boron Concentration:
Thisnumber includes:
= Chemistry Sampling Uncertainty
= Boron-10 Depletion Allowance 22560ppm 22560ppm
= Margin fordilution ofrefueling pool between lowandhigh level alarms
= Allowance for temporary rotations offuel assemblies
= Extra Conservatism forunlimited number ofemptylocations during refueling operations.
Calvert Cliffs 2,Cycle 24COLR PageI1of22 Rev.0
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i 1.000
,ll (1.06FRTP3Group5@35%lnsertedj 0900 i
UNACCEPAB
- I (0'.9()FRTP.,G roug$
5@35%lnserted j
ji OPERATING a[ 0.E jji (0.75 FRTP, Grougl5 @50%lnser ted):
REGION m
a 1 0.700
!l i (0.70 FR
, Gronp5 @60Volbserte d) 2
!2 g
(d.65FftTP, Group5 -@8502 Inserted) p 0.600
!lj3 i 2
i @
lj (0.56 FRTP, roup@50%1n@ed) 0.500 j
s
.n a
is l;
j"0.400
- =
a
- I g
l,8 lyg Trar$ient insertion Lirhit o 0.300 l
z
- a e I
0.200%
jj (0.20FRTP, Gro'up3 @60%lserte@
2
"- 0.100 Above (Above zero Power PDll
- Setpoint, 2PPDR.
Group3@60%inserted)
SEIPOINT l
0% 20% 40%60% 80% 100%0% 20% 40% 60%80%100%0% 20% 40% 60%
80%100%
135"108'81' 54' 27'O' 135"108'81' 54'27" 0" 135
108
81' 54' 27 0" 0% 20% 40% 60%80% 100%0% 20% 40% 60% 80% 100%
135'108'81' 54
" 27" O' 135 108
81' 54' 27 O'
%CEAINSERTION INCHESCEAWITHDRAWN (ARO isdefined inNEOP-23)
Note:
PerTechSpecBases3.1.5 and3.1.6, CEAsareconsidered tobe fully withdrawn at129inches.
Figure 3.1.6 CEAGroupInsertion Limits vs.Fraction ofRatedThermal Power Thisfigure cannotbechanged without prior NRCapproval.
Calvert Cliffs 2,Cycle 24COLR Page12of22 Rev.0
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i 17.0 j
16.5
j-------
16.0 E
2 E
@ 15.5 g
UNACCEPTABLE OPERATION g O 6)15.0 Eo5
< O3 14.5 55 SE aj 14.0 ACCEPTABLE OPERATION n5 13.0 BOC EOC TIMEINCYCLE Figure 3.2.1-1 Allowable PeakLinear HeatRatevs.TimeinCycle Calvert Cliffs 2,Cycle 24COLR Page13of22 Rev.0
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.x i
11 1
0.9 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION REGlON REGlON 0.8 e!
%0.7 E
0.6 OP 8
REGlON 11 E
u.0.5 0.4 0.3 0.2
-0.5
-0.4
-0.3
-0.2
-0.1 0
0.1 0.2 0.3 0.4 0.5 Perhipheral Axial Shapeindex(Yi)
Figure 3.2.1-2 Linear HeatRateAxial FluxOffset Control Limits (AXIAL SHAPEINDEXlimits forLinear HeatRatewhenusing Excore Detector Monitoring System)
(LCO Limits arenotneeded below 20%thermal powerperSE00433)
(See NEOP-23forOperational Limits)
Calvert Cliffs 2,Cycle 24COLR Page14of22 Rev.0
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c i
1.05 (1.65,1.00)
UNACCEPTABLE
@0.95 OPERATION B
REGloN O30.85 (1.7325,0.80)
E@0.75 z
FrT LIMITCURVE 0.65 a 0.55 O
0.45 ACCEPTABLE I-OPERATION O
REGloN 0.35 m 0.25 3
O (1.819,0.20)
-j0.15 0.05 1.60 1.65 1.70 1.75 1.80 1.85 p,T Figure3.2.3 Total Integrated Radial Peaking Factor(FrT) ys, Allowable Fraction ofRated Thermal Power Whileoperating withFrT greater than1.65, withdraw CEAstoorabovetheLongTermSteady State Insertion Limits (Figure 3.1.6)
This figure cannotbechanged without prior NRCapproval.
Calvert Cliffs 2,Cycle 24COLR Page15of22 Rev.0
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1.10 1.05 1.00
(-0.08,1.00)
(0.15, 1.00) d 0.95 UNACCEPTABLE UNACCEPTABLE OPERATION OPERATION I 0.90 REGION REGION Ej0.85 Oo 0.80 (0.3, 0.80)
LuD0.75 ACCEPTABLE 0.70
(-0.3, 0.70)
OPERATION O
REGION p0.65
@0.60 0.55
@0.50
(-0.3, 0.50) u.
O 0.45 0.40 O@0.35 u.0.30 0.25
(-0.42, 0.20)
(0.3, 0.20) 0.20
-0.60
-0.40
-0.20 0.00 0.20 0.40 0.60 PERIPHERAL AXIALSHAPEINDEX,Yi Figure 3.2.5 DNBAxial FluxOffset Control Limits (LCO Limits arenotneeded below 20%thermal powerperSE00433)
(See NEOP-23 forOperational Limits)
This figure cannotbechanged without prior NRCapproval.
Calvert Cliffs 2,Cycle 24COLR Page16of22 Rev.0
W my-i 1.300 1.250 (0.0, 1.17) 1.200 UNACCEPTABLE UNACCEPTABLE 1150 OPERATION OPERATION REGION REGION 1.100 1.050 1.000
(-0.2, 1.00)
(0.2, 1.00) g 0.950 D
O 0.900 aj 0.850 EE 0.800 a@0.750 m@ 0.700 8
p 0.650 SE 0.e00 ACCEPTABLE OPERATION 0.550 REGloN 0.500 0450 0.400
(-0.6, 040)
(0.6, 0.40) 0.350 0.300 0.250 0.200 0.150
-080
-0.60
-0.40
-0.20 0.00 0.20 0.40 0.60 0.80 PERIPHERAL AXIALSHAPEINDEX,Yi Figure3.3.1-1 Axial PowerDistribution
- HighTripSetpoint Peripheral Axial Shape Index vs.Fraction ofRatedThermal Power Calvert Cliffs 2,Cycle 24COLR Page17of22 Rev.0
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i 1.60 P var
= 2869.5 x(A1) x(QR1)
+ 17.98 xTin
- 10820 1.50 QogA1 x QR1 1.40
^
1.30 2
1.20 A1 +0.167 xA I+ 1.0
(+0.6, 1.1) 1.10 A1= 0.5x SI+ 1.
1.00 (0.0, 10) 0.90
-0.60-0.50-0.40-0.30-0.20-0.100.000.100.200.300.400.50 0.60 ASI Figure 3.3.1-2 Thermal Margin/Low Pressure TripSetpoint
- Part1 (ASI vs.A1)
Calvert Cliffs 2,Cycle 24COLR Page18of22 Rev.0
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i PTpr= 2869.5 x(A1) x(QR1)
+ 17.98 xTin
- 10820 Q DNB
= A1xQR1 1.2 (1.2, 1.2) 1.1 QR1= (RTP) +0.0 1.0 (1,
, 1.0 0.9 (0.
, 0.8)
OE QR1= 0.375 x(RTP) + 0.625 2 0.6 O
0.5 QR1= 0.9167 x(RTP)
+0.3 0.4 0.3 (0.
, 0.3 0.2 0.1 0.0 0.0 0.1 0.2 0.3 0.4 0.5 0.6 0.7 0.8 0.9 1.0 1.1 1.2 1.3 FRACTION OFRATEDTHERMALPOWER(RTP)
Figure 3.3.1-3 Thermal Margin/Low Pressure TripSetpoint
- Part2 (Fraction ofRatedThermal Powervs.QR1)
Calvert Cliffs 2,Cycle 24COLR Page19of22 Rev.0
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LISTOFAPPROVEDMETHODOLOGIES l.ANF-88-133 (P)(A) andSupplement1,"Qualification ofAdvanced Nuclear Fuels' PWRDesign Methodology for Rod Burnupsof62GWd/MTU"Advanced Nuclear Fuels Corporation, December 1991
- 2. BAW-10240(P)(A),Revision 0,"Incorporation ofM5Properties inFramatome ANPApproved Methods" Framatome
- ANP, May 2004 3.EMF-92-116(P)(A),
Revision0, Supplement l(P)(A),
Revision 0,"Generic Mechanical Design Criteria forPWRFuel Designs"AREVA Inc.
, February 2015[Licensing Restriction 7) 4.EMF-92-153(P)(A),
Revision 1,"HTP: Departure fromNucleate Boiling Correlation forHigh Thermal Performance Fuel,"
Siemens Power Corporation
, January 2005 5.EMF-96-029(P)(A)
Volumes 1and2,"ReactorAnalysis SystemforPWRsVolume1-Methodology Description, Volume 2-Benchmarking Results,"
Siemens PowerCorporation, January 1997 6.EMF-1961 (P)(A),
Revision 0,"Statistical Setpoint/Transient Methodology forCombustion Engineering TypeReactors,"
Siemens Power Corporation, July 2000 7.EMF-2103 (P)(A),
Revision 0,"Realistic LargeBreak LOCAMethodology for Pressurized WaterReactors" Framatome ANP,April 2003[Licensing Restriction 9) 8.EMF-2310(P)(A),
Revision 1,"SRPChapter 15Non-LOCAMethodology for Pressurized Water Reactors" Framatome ANP,May2004[Licensing Restrictions 1,2,6,and8b) 9.EMF-2328(P)(A),
Revision 0,Supplement 1(P)(A),
Revision 0,"PWRSmall BreakLOCA Evaluation
- Model, S-RELAP5Based" AREVA,December 2016[Licensing Restriction 4) 10.XN-NF-75-32(P)(A),
Supplements 1,2,3& 4,"Computational Procedure forEvaluating Fuel RodBowing" ExxonNuclear Company Inc.,
February 1983 1l XN-NF-78-44(NP)(A),
"AGeneric Analysis oftheControl RodEjection Transient for Pressurized Water Reactors" ExxonNuclear Company Inc.,
October 1983[Licensing Restrictions 3and8a) 12.XN-NF-79-56(P)(A),
Revision 1andSupplement 1,"Gadolinia FuelProperties forLWRFuel Safety Evaluation" Siemens PowerCorporation, October 1981 13.XN-NF-82-06(P)(A),
Revision 1& Supplements 2,4,and5,"Qualification ofExxonNuclear FuelforExtended Burnup" ExxonNuclear Company Inc.,
October 1986 14.XN-NF-82-21(P)(A),
Revision 1,"Application ofExxonNuclear Company PWRThermal Margin Methodology toMixedCoreConfigurations" ExxonNuclear Company Inc.,
August 1983 Calvert Cliffs 2,Cycle 24COLR Page20of22 Rev.0
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15.
XN-NF-85-92(P)(A),
Revision 0,"Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination andThermalConductivity Results" ExxonNuclear Company Inc.,
September 1986 16.CEN-124(B)-P,"Statistical Combination ofUncertainties Methodology Part2:Combination ofSystem Parameter Uncertainties inThermal Margin Analyses forCalvert Cliffs Units 1and 2,"January 1980[Notused forthis fuel cycle) 17.CEN-191(B)-P, "CETOP-D Code Structure andModeling Methods forCalvert Cliffs Units 1
and2,"December 1981[Not used for this fuel cycle) 18.Letter fromMr.D.H.Jaffe (NRC)to Mr. A.E.Lundvall,Jr.(BG&E),
dated June24,1982, Unit 1Cycle 6License Approval (Amendment No.71toDPR-53 andSER)
[Approval to CEN-124(B)-P (three parts) andCEN-191(B)-P))[Not usedfor this fuel cycle) 19.CENPD-161-P-A, "TORCCode, A ComputerCode for Determining theThermal Margin ofa Reactor Core,"
April 1986[Not usedfor this fuelcycle) 20.CENPD-206-P-A, "TORCCode,Verification andSimplified Modeling Methods,"
June1981
[Not usedfor this fuel cycle) 21.CENPD-225-P-A, "Fuel andPoison RodBowing,"
June1983[Not used for this fuel cyclej 22.CENPD-382-P-A, "Methodology forCoreDesigns Containing Erbium Burnable Absorbers,"
August 1993[Not usedfor this fuel cycle) 23.CENPD-139P-A, "C-EFuel Evaluation ModelTopical Report,"
July 1974[Not used for this fuel cycle) 24.CEN-161-(B)-P-A, "Improvements toFuel Evaluation Model,"
August 1989[Not used for this fuel cycle) 25.CEN-161-(B)-P, Supplement 1-P,"Improvements toFuelEvaluation Model,"
April 1986
[Not usedfor this fuel cycle) 26.Letter fromMr.S.A.McNeil, Jr.(NRC) toMr.J.A.Tiernan (BG&E),
dated February 4,
- 1987, Docket Nos.50-317 and50-318, "Safety Evaluation ofTopical Report CEN-161-(B)-P, Supplement 1-P,Improvements toFuelEvaluation Model" (Approval ofCEN-161(B),
Supplement 1-P)
[Not usedfor this fuel cycle) 27.CEN-372-P-A, "Fuel RodMaximumAllowable GasPressure,"
May1990[Not usedfor this fuel cycle) 28.CENPD-135, Supplement 5-P,"STRIKIN-II, A Cylindrical Geometry FuelRodHeatTransfer Program,"
April 1977[Not usedfor this fuel cycle) 29.CENPD-387-P-A, Latest Approved
- Revision, "ABBCritical HeatFluxCorrelations forPWR Fuel"
[Not usedfor this fuel cycle) 30.CENPD-404-P-A, Latest Approved
- Revision, "Implementation ofzIRLOTM Cladding Material inCENuclear PowerFuelAssembly Designs"
[Not usedfor this fuel cycle)
Calvert Cliffs 2,Cycle 24COLR Page21of22 Rev.0
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31.WCAP-1 1596-P-A, "Qualification ofthePHOENIX-P, ANCNuclear Design System for Pressurized Water ReactorCores,"
June1988.[Notusedfor this fuel cycle) 32.
WCAP-10965-P-A, "ANC:
A WestinghouseAdvanced NodalComputer Code,"
September 1986.
[Not used for this fuelcycle) 33.WCAP-10965-P-A Addendum 1,"ANC:A Westinghouse Advanced NodalComputer Code; Enhancements toANCRod Power Recovery,"
April 1989.
[Not usedfor this fuel cycle) 34.WCAP-16072-P-A, "Implementation ofzirconium Diboride Burnable Absorber Coatings inCENuclear Power Fuel Assembly Designs,"August 2004.[Not usedfor this fuel cycle) 35.WCAP-16045-P-A, "Qualification ofthe Two-Dimensional Transport Code PARAGON,"August 2004.[Not usedfor thisfuel cycle)
Calvert Cliffs 2,Cycle 24COLR Page22of22 Rev.0