ML21103A409

Core Operating Limits Report for Unit 2, Cycle 24, Revision 0

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

@

m.-

- i 2..o0,,,n.or Plant Manager Chffs Calvert Nuclear Power Plant 1650 CalvertCliffs Parkway MD 20657 Lusby, Office 410-495-520S 610-765-5881Mobile wwwexeloncorp.com joseph.dullinger@exeloncorpcom TS5.6.5 April 12,2021 U.S.NuclearRegulatory Commission ATTN:Document Control Desk MailStop P1-37 OneWhite Flint North 11555Rockville Pike MD 20852-2738 Rockville Cliffs Calvert Nuclear PowerPlant, Unit No.1 RenewedFacility Operating License No.DPR-69 NRCDocket No.50-318

Subject:

PursuanttoCalvert Cliffs Nuclear Plant Power Technical Specification the 5.6.5, attached Core Operating Limits Reportfor 2,Cycle Unit 24,Revision 1),

0 (Attachment for isprovided your records.

Please replacetheUnit 2 Core Limits Operating entirety, inits Report withtheattached Revision 0.

Therearenoregulatory commitmentscontained inthis correspondence.

Shouldyouhavequestions this regarding please matter, Mr.Larry contact D.Smith at(410) 495-5219.

Respectfully, JosephA.Dullinr Plant Manager JAD/LDS/lmd

Attachment:

(1)CoreOperating Limits for Report Unit2,Cycle 24,Revision 0

ATTACHMENLLU CORE OPERATING LIMITS REPORT FOR UNIT2,CYCLE 24,REVISION 0 Cliffs Calvert NuclearPowerPlant April 12,2021

j-v i r in ii COLR Unit 2 Cycle24 Revision0 Effective Date: 03/03/2021 Digitally signedbySchearer, A Timothy Schearer,Timothy A DN:

Date:

cn=Schearer, 2021.02.16 Timothy 12:43:05 A

-05'00' Responsible Engineer / Date Digitally byKelllher, signed Andrew P DN:cn=Kelllher, AndrewP Date: 2021.02.16 -05'00' 12:53:06 IndependentReviewer / Date Digitally byBroderick, signed Alexander J.

Alexander Broderick, J.DN:

Date:

Alexander cn=8roderick, J.

16:07:50-05'00' 2021.02.17 Qualified Station Reviewer/ Date ManagerPWRCore Sr. -

Design/ Date Cliffs Calvert 24COLR 2,Cycle Page1of22 Rev.0

W me

- i COREOPERATING LIMITS REPORT CALVERT CLIFFS UNIT2,CYCLE24 Thefollowing limits are included in thisCore Operating Limits Report:

litle SpjsiEcatioIl 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 Heat Rate (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, andFlow DNBLimits , -......,..... 10 3.9.1 Boron Concentration.-....-...-.-...,.,...........-=.....,.-.... 11 List ofApproved Methodologies.---.,..,.,.,.......,.... 20 figures Thefollowing are included inthis Core Operating Limits Report:

Num.hg.r Iitl.e .Page 3.1.6 CEAGroup Figure Insertion Limits vs.Fraction ofRated Thermal Power..,..,,........ 12 Figure 3.2.1-1 Allowable Peak Linear Heat Rate vs. TimeinCycle =.....,.........,....... 13 Figure Linear 3.2.1-2 Heat Rate Axial Flux Offset Control Limits =.=,,.- ,..... 14 3.2.3 Total Figure Allowable Integrated Fraction Radial ofRated Peaking Factor vs.

Thermal (F)

Power,.,.,,,..,,,,<,--.... 15 3.2.5DNBAxial Figure Flux Offset Control Limits.,,,,,,-....,,....,,,,,,,,,,.,..... 16 Figure Axial 3.3.1-1 Power Distribution -

High Trip Setpoint Peripheral Axial Shape Index vs. Fraction ofRated Thermal Power -,..................,............ 17 Figure Thermal 3.3.1-2 Margin/Low Pressure Trip Setpoint -

Part 1 ..............,=............... 18 Figure Thermal 3.3.1-3 Margin/Low Pressure Trip Setpoint -

Part 2 ................... 19 Calvert 2,Cycle Cliffs 24COLR Page 2of22 Rev.0

W m xx

- i UNIT2 COREOPERATING LIMITSREPORT LISTOFEFFECTIVEPAGES PageNo. Rev.No.

1 0 2 0 3 0 4 0 5 0 6 0 7 0 8 0 9 0 10 0 11 0 12 0 13 0 14 0 15 0 16 0 17 0 18 0 19 0 20 0 21 0 22 0 Cliffs Calvert 24COLR 2,Cycle Page3of22 Rev.0

W mg

- i INTRODUCTION This providesthe cycle-specific limits report for operation ofCalvert Cliffs Unit 2,Cycle 24.It contains thelimitsfor:

Shutdown Margin (SDM)

ModeratorTemperature Coefficient (MTC)

ControlElement Assembly (CEA) Alignment RegulatingControl Element Assembly (CEA) Insertion Limits LinearHeat Rate (LHR)

TotalIntegratedRadial Peaking Factor (F?)

AxialShape Index (ASI)

ReactorProtective System (RPS) Instrumentation -

Operating RCS Pressure, and Flow Temperature, Departure from Nucleate Boiling (DNB) Limits BoronConcentration this Inaddition, report contains anumber offigures whichgive limits onthe parameters listed Ifanyofthe above, limitscontained inthis report areexceeded, corrective action will betaken as defined intheTechnical Specifications.

This has report been prepared inaccordance with the requirements ofTechnical Specifications.

Thecyclespecific limits have been developed using the NRC-approved methodologies given in the ofApproved "List Methodologies" section ofthis report andinthe Technical Specifications.

COLRRevision 0 Initial ofthe release Unit 2 Cycle 24(U2C24) COLR.U2C24mayoperate inall plant modes.

Calvert 2,Cycle Cliffs 24COLR Page 4of22 Rev.0

W my

- i-DEFINITIONS Shape Axial Index(ASI)

ASIshall bethe power generated in the lower halfofthe core less the powergenerated in the half upper ofthe core, divided bythe sumofthe power generatedinthe and lower halves upper ofthe core.

lower upper ASI -

y lower+ upper TheAxial Shape Index (Y1) used for thetrip and pretripsignals inthe Protection Reactor System (RPS) isthe a bove value (YE) modified by an appropriate multiplier (A)anda (B) constant todetermine the true core axial power distribution forthat channel.

Y1=AYE+ B Total Integrated Radial Peaking Factor -

Frf TheTotal IntegratedRadial Peaking Factor istheratio ofthepeak pin powertothe pin average power inanunrodded core.

Calvert 2,Cycle Cliffs 24COLR Page 5of22 Rev.0

W mg

- i LICENSING RESTRICTIONS 1)FortheAsymmetric Steam Generator Transient analysis performed inaccordance with themethodologyof Technical Specification 5.6.5.b.8, the methodology shall berevised tocapturethe asymmetric core inlet temperature distribution andapplication oflocal peakingaugmentationfactors. Therevised methodology shall beapplied toCalvert Cliffs Unit 2core reload designs starting with Cycle 19.

2)Forthe Seized Rotor Event analysis performed in accordance with the methodology of TechnicalSpecification 5.6.5.b.8, the methodology shall berevised tocapture the asymmetric core inletflow distribution. The revised methodology shall beapplied to CalvertCliffsUnit 2core reload designsstarting with Cycle 19.

3)Forthe Control Element Assembly Ejection analysis performed inaccordance withthe methodology ofTechnical Specification 5.6.5.b.11, the cycle-specific hot zeropower peakaverage radial fuel enthalpy is calculated based on amodified power dependent limit insertion with Control Element Assembly Bank 3assumed tobefully inserted (only intheanalysis,notin actual plant operations). This revised methodology shall beapplied toCalvertCliffs Unit 2core reload designs starting with Cycle 19.

4)TheSmall Break Loss ofCoolant accident performed inaccordance with the methodology ofTechnical Specification 5.6.5.b.9 shall beanalyzed using a break spectrumwith augmented detail related tobreak size. This revised methodology shall be appliedtoCalvert Cliffs Unit 2core reload designs starting with Cycle 19.

5)CoreOperating Limits Report Figures 3.I.6, 3.2.3, and 3.2.5 shallnotbechanged withoutpriorNRCreview andapproval until anNRC-accepted generic, orCalvert Cliffs-specific, basis is developed for analyzing the Control Element Assembly Rod Bank Withdrawal Event, the Control Element Assembly Drop, andthe Control Element Assembly Ejection (power level-sensitive transients) atfull power conditions only.

6)Approval ofthe useofS-RELAP5 (Technical Specification 5.6.5.b.8) isrestrictedonlyto thosesafetyanalyses that confirm acceptable transient performance relative tothe specified acceptable fuel design limits. Prior transient specific NRCapproval isrequired toanalyze transientperformance relative toreactor coolant pressure boundary integrity NRC-approval until is obtained for ageneric orCalvert Cliffs-specific basis fortheuse ofthemethodology inTechnical Specification 5.6.5.b.8 todemonstrate reactor coolant pressureboundary integrity.

NOTE: TheNRChas issueda letterthat allows S-RELAP5 tobeused forthetransient-application specific ofthe methodology toCCNPP onlyasdescribedinthe letter toPSVsetpoints.

pertaining Itis notageneric approval ofthe methodology.

Ref: Letter from Alexander N.Chereskin (NRC) toBryan C.Hanson (Exelon) dated December 30,2015, Calvert Cliffs Nuclear Power Plant, UnitNos.1and2 -

ofAmendment Issuance Re:Revision toPressurizer SafetyValve Technical (CAC Specifications Nos. MF3541 andMF3542)

Cliffs Calvert 2,Cycle 24COLR Page 6 of22 Rev.0

W me

- i 7)Forthe RODEX2-based fuel thermal-mechanical design analysis performed in accordancewith the methodology ofTechnical Specification 5.6.5.b.3, Calvert Cliffs Unit2 corereloaddesigns (starting with Cycle 19) shall satisfy the f ollowing criteria:

a. Predictedrod internal pressure shall remain below the steady state system pressure.

b.Thelinear heat generation rate fuelcenterline melting safety limitshall remain below 21.0 KW/ft.

8)FortheControl Element Assembly Ejection analysis, Calvert Cliffs Unit 2 corereloads (starting withCycle 19)shall satisfy thefollowing criteria:

a. Predictedpeak radial average fuel enthalpywhen calculated inaccordance with the methodology ofTechnical Specification 5.6.5.b.1 Ishall remain below 200cal/g.

b.For the purpose ofevaluating radiological consequences, should the S-RELAP5 hot spotmodel predict fuel temperature above incipient centerline melt conditionswhen calculatedinaccordance with the methodology ofTechnical Specification 5.6.5.b.8, a conservativeradiological source term(in accordance with Regulatory Guide 1.183, Revision0)shall beapplied tothe portion offuel beyond incipient melt conditions (and combined with existing gap source term), and cladding failure shall be presumed.

9)Theapproval ofthe emergency core cooling system evaluation performed inaccordance withthe methodology ofTechnical Specification 5.6.5.b.7 shall bevalid only forCalvert Cliffs Unit 2,Cycle 19. Toremove this condition, Calvert Cliffs shall obtain NRC approvalofthe analysis ofonce- andtwice-burned fuel for core designs following Unit2 Cycle19.

JSOTE: Therevised methodology wassubmitted and received NRCapproval inDecember 2012.This licensecondition issatisfied; however sinceNRCapproval wasobtained via letter andnotLAR,this license conditionis still listedinAppendix C ofthe Tech.

Specs. andhas been retained herefor consistency.

Ref: Letter from Douglas V.Pickett (NRC) toGeorge H.Gellrich (CCNPP) dated February18,2011, Calvert CliffsNuclear Power Plant,Unit Nos. 1and 2 Amendment Re:Transition from Westinghouse Nuclear Fuel toAREVANuclear (TAC Fuel Nos. ME2831 andME2832)

Cliffs Calvert 2,Cycle 24COLR Page 7of22 Rev.0

W mx

- i 10)UptotwoFramatome PROtectTM Lead Test Assemblies utilizing M5@cladding Chromium-coated andchromiadoped pellets maybe placed inlimiting regionsofthe core upto3cycles for commencingwith the implementation ofAmendment 317.

I1)Thesafety limitsspecified inTS 2.1.1.2 regardingfuel centerlinemelt for temperatureFramatome fuel,

<50810F,decreasing by580F per 10,000 MWD/MTUandadjusted for poison burnable XN-per NF-79-56(P)(A),Revision 1,Supplement 1is notapplicable forthe PROtectTM Framatome Lead Test Assemblies utilizingChromium-coated M5@ cladding and chromia dopedpelletsupto3cycles for commencingwith the implementation ofAmendment 317.

12)Therequirement thatthe RODEX2 predicted rod intemal pressure shall remain below thesteady state system is pressure notapplicable for the Framatome PROtectTM Lead TestAssemblies utilizing Chromiumcoated M5@cladding andchromia dopedpellets for upto3cycles with commencing the ofAmendment implementation 317.

• LicenseCondition #12supersedes License Condition #7a onlyfor Lead the TestAssembly.

Calvert Cliffs 24COLR 2,Cycle Page 8of22 Rev.0

W my

- i CYCLE SPECIFIC LIMITSFORUNIT2,CYCLE24 3.1.1 Shutdown Margin (SDM) (SR 3.1.1.1)

Tavg> 2000F Modes 3and4:

Theshutdown marginshall be2 3.5% Ap.

TavgS2000F Mode5:

Theshutdown marginshall be2 3.0% Ap.

3.1.3Moderator Temperature Coefficient (MTC) (SR 3.1.3.2)

TheModerator Temperature Coefficient(MTC) shall beless negative than x 104

-3.1 Ap/0F atrated thermal power.

3.1.4Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1)

Theallowable timetorealign aCEAis120 minutes when the pre-misaligned FrTis5 1.65 andzero(0)minutes when t he p re-misaligned FrTis > 1.65.

Thepre-misaligned FrTvalue used todetermine the allowable time torealign the CEAshall bethelatest measurement taken within 5days priortothe CEAmisalignment. If no measurements havebeen taken within 5days priortothe misalignment and thefullcore powerdistribution monitoring system isunavailablethen thetime torealign iszero(0) minutes.

3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits (SR andSR3.1.6.2) 3.1.6.1 Theregulating CEAgroups insertion limits areshown onCOLRFigure 3.1.6.

Figure 3.I.6will notbechanged unless therequirements inLicensing Restriction 5are met.

3.2.1Linear Heat Rate (LHR) (SR 3.2.1.2 andSR3.2.1.4)

Thelinear heat rateshallnotexceed thelimits shown onCOLRFigure 3.2.1-1.

Theaxial shape indexpower dependent limits control are given inCOLRFigure 3.2.1-2.

Thealarmsetpoints areequal toorless thanthe ASIlimits; therefore whenthe alarmsare adjusted, they provideindication tothe operatorthatASIis notwithin the limits.

Theaxial shape indexalarm setpoints areshown asafunction offraction ofthermal poweron COLRFigure 3.2.1-2.

Calvert 2,Cycle Cliffs 24COLR Page 9of22 Rev.0

W my

- i Thealarmsetpoints are adjusted toprotect the Linear Heat Rate limits shown onCOLR 3.2.1-1 Figure and uncertainty factorsare appropriately included inthe setting 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 orequal to50percent but greater than20percent ofratedfull core power athermal power measurement uncertainty factor of1.035.

3.bFormeasured thermal power greater than 50 percent of rated fullcore power athermal powermeasurement uncertainty factor of1.020.

3.2.3TotalIntegrated Radial Peaking Factor (FJ)(SR 3.2.3.1)

Thecalculatedvalue ofFrT Shall belimited to5 1.65.

calculated Ifthe FrTeXCeeds the above limit, the allowable combinations ofthermal power, CEA andFrT position, areshown onCOLRFigure 3.2.3.

Figure 3.2.3will notbechanged unless the requirements inLicensing Restriction 5aremet.

3.2.5AxialShape Index (ASI) (SR 3.2.5.1)

Theaxial shape index andthermal power shall bemaintained equal toorless thanthe limits ofCOLRFigure 3.2.5for CEAinsertions specified byCOLRFigure 3.1.6.

Figure 3.2.5will notbechanged unless the requirements inLicensing Restriction 5are met.

3.3.1Reactor Protective System (RPS) Instrumentation -

Operating (Reactor Trip Setpoints) (TS Table 3.3.1-1)

TheAxialPower Distribution -

High trip setpoint andallowable values are given inCOLR Figure 3.3.1-1.

TheThermal Margin/Low Pressure (TM/LP) tripsetpoint isgiven inCOLRFigures 3.3.1-2 and3.3.1-3.

Theallowable values are tobenotless than the larger of(1) 1875 psiaor(2) the calculated value from COLRFigures 3.3.1-2 and3.3.1-3.

3.4.1 RCSPressure, Temperature, andFlow Departure from Nucleate Boiling (DNB) Limits TheRCSDNBparameters for pressurizer pressure, cold leg temperature, andRCStotal flow shall rate bewithin thelimits specified below:

a. Pressurizer pressure 2 2200 psia;

b. RCScold leg temperature (Tc) 5 548F;and

c. RCStotal flow rate 2 370,000 gpm.

Cliffs Calvert 2,Cycle24COLR Page 10of22 Rev.0

W m x

- i 3.9.1BoronConcentration (SR 3.9.1.1)

Therefueling boron concentration will maintainthe at0.95 kerr orless a 1%Ak/k (including conservativeallowance for uncertainties). Therefueling boron concentration shall be maintaineduniform. For Mode6operation RCStemperature the mustbemaintained

< 1400F.

U2C24Refueling Boron Concentration Limits UNIT2 CYCLE24 U2C24Cycle Average Exposure 0 GWD/MTU > 16GWD/MTU Number ofCredited CEAs 0 0 Post-RefuelingUGSorRVHead LiftHeight Restrictions. No Restriction No Restriction Minimum Required Refueling Boron Concentration:

This numberincludes:

= Chemistry Sampling Uncertainty

= Boron-10 Depletion Allowance 2 2560ppm 2 2560ppm

= Margin for dilution ofrefueling pool betweenlowandhigh level alarms

= Allowance for temporary rotations offuel assemblies

= ExtraConservatism forunlimited number ofempty locations during refueling operations.

Calvert Cliffs 2,Cycle 24COLR Page I1of22 Rev.0

W m.

- i 1.000

,l lnsertedj l (1.06FRTP3 Group5 @35%

0900 i

I (0'.9()FRTP.,G roug$

5 @35%lnserted j UNACCEPAB a 0.E ji jj OPERATING

[

m ai1 (0.75 FRTP, Grougl5 @50%lnser ted): REGION 0.700 !l i (0.70 FR .

, Gronp5 @60Vo lbserted) 2 p 0.600

!2 g (d.65 FftTP, Group5 -@8502 Inserted)

!lj3 i  !

2 0.500 i @ lj j

(0.56 FRTP, roup@50%

1n@ed) a is s .n l;I j" 0.400  :*=

l,8 a -

g lyg Trar$ient insertion Lirhit o 0.300 z l *a e I 0.200 % jj 2

. (0.20 FRTP, Gro'up3 @60%l serte@

"- 0.100  :

Above (Above zero Power PDll Setpoint, 2PPDR. Group 3@60%inserted)

SEIPOINT 0% 20% 40%60% 80% 100%0% 20% 40% 60% 80% 100%0% 20% 40% 60%

l 80%100%

108'81' 54' 27' O' 135"108'81' 54' 27" 0" 135

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 INCHES CEAWITHDRAWN (ARO isdefined inNEOP-23)

Note:

Per Tech Spec Bases 3.1.5 and3.1.6, CEAsare considered tobe fully withdrawn at129 inches.

Figure 3.1.6 CEAGroupInsertion Limits vs. Fraction ofRated Thermal Power This figure cannot bechanged without priorNRCapproval.

CalvertCliffs2,Cycle24COLR Page 12of22 Rev.0

W m

- i -

17.0 j

16.5 ----j-------

16.0 E

2 E

@ 15.5 g UNACCEPTABLE OPERATION gO

)

6 15.0 Eo

<O 5

3 14.5 55 SE a

j 14.0 -

ACCEPTABLE OPERATION n5 13.0 BOC EOC TIMEINCYCLE Figure 3.2.1-1 Allowable PeakLinear HeatRate vs. TimeinCycle Calvert Cliffs 24COLR 2,Cycle Page13of22 Rev.0

W m .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 Axial Perhipheral (Yi) index Shape Figure3.2.1-2 Linear Axial HeatRate FluxOffset Control Limits (AXIAL SHAPEINDEXlimitsLinear for HeatRate whenusing Excore Monitoring Detector System)

Limits (LCO notneeded are below20%thermal power SE00433) per (See NEOP-23forOperational Limits)

Calvert Cliffs 24COLR 2,Cycle Page14of22 Rev.0

W

m. c

- i 1.05 (1.65,1.00)

UNACCEPTABLE B

0.95 OPERATION REGloN O

3 0.85 (1.7325,0.80)

E z

0.75 FrT LIMITCURVE 0.65 a 0.55 O

0.45 ACCEPTABLE I-O OPERATION 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 RadialPeaking Factor (FrT) ys, Allowable ofRated Fraction Thermal Power While FrT with operating greater withdraw than1.65, CEAstoorabove theLongTermSteady State Insertion Limits(Figure3.1.6)

Thisfigure cannot bechangedwithout prior NRCapproval.

Calvert Cliffs 24COLR 2,Cycle Page15of22 Rev.0

mt W '

- i 1.10 1.05 1.00 (-0.08,1.00) 1.00)

(0.15, d 0.95 UNACCEPTABLE UNACCEPTABLE

@ I 0.90 OPERATION REGION OPERATION REGION E

j O

0.85 o 0.80 0.80)

(0.3, Lu D0.75 ACCEPTABLE 0.70 (-0.3, 0.70) OPERATION O REGION p 0.65

@ 0.60

@ 0.55 u.

0.50 0.50)

(-0.3, O 0.45 O

0.40 u.

0.35 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 AXIALSHAPE INDEX,Yi Figure 3.2.5 DNBAxial Flux Offset ControlLimits (LCO Limits arenotneeded below 20%thermal powerperSE00433)

(See NEOP-23 forOperational Limits)

This figure cannot bechanged without NRCapproval.

prior Calvert 2,Cycle Cliffs 24COLR Page 16of22 Rev.0

my W

- 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 a

j 0.850 E

E 0.800 a

m 0.750

@ 0.700 8

p 0.650 S

E 0.e00 ACCEPTABLE 0.550 OPERATION REGloN 0.500 0450 0.400 (-0.6, 0 40) (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 PERIPHERALAXIAL SHAPEINDEX, Yi Figure3.3.1-1 Axial Power Distribution -

HighTripSetpoint PeripheralAxial Shape Index vs. Fraction ofRated Thermal Power Calvert Cliffs 24COLR 2,Cycle Page 17of22 Rev.0

m.

W

- i 1.60 P var = 2869.5 x(A1)x(Q + 17.98 R1) xTin10820 1.50 QogA1 x QR1 1.40

^ ' '

1.30 2

1.20 A1 +0.167 x A I+ 1.0 1.1)

(+0.6, 1.10 A1= 0.5 x SI+ 1.

1.00 10)

(0.0, 0.90

-0.60-0.50 -0.40 -0.30 -0.10

-0.20 0.000.100.200.300.400.50 0.60 ASI Figure3.3.1-2 Thermal Pressure Margin/Low TripSetpoint 1

Part (ASIvs.A1)

Calvert Cliffs 2,Cycle 24COLR Page 18of22 Rev.0

m, W

- i PTpr = 2869.5 x (A1) x (Q R1) + 17.98xTin10820 Q DNB = A1xQR1 1.2 1.2)

(1.2, 1.1 QR1= (RTP) + 0.0 1.0 (1,1.0 0.9 OE (0.0.8)

QR1= 0.375 x (RTP) + 0.625 2

O 0.6 0.5 0.4 QR1= 0.9167 x (RTP) + 0.3 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 OFRATEDTHERMAL POWER (RTP) 3.3.1-3 Figure Thermal Margin/Low Trip Pressure Setpoint Part2 (Fraction ofRatedThermalPowerv s.QR1)

Calvert 2,Cycle Cliffs 24COLR Page19of22 Rev.0

m-W y

- i LISTOFAPPROVED METHODOLOGIES l.ANF-88-133 (P)(A) andSupplement 1,"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 from Nucleate BoilingCorrelation forHigh Thermal Performance Fuel," Siemens Power Corporation , January 2005

5. EMF-96-029(P)(A) Volumes 1and 2,"ReactorAnalysis Systemfor PWRsVolume 1 -

Methodology Description,Volume 2 Benchmarking Results," Siemens Power Corporation, January1997

6. EMF-1961 (P)(A), Revision0,"Statistical Setpoint/Transient Methodology forCombustion EngineeringType Reactors," Siemens Power Corporation, July 2000

7. EMF-2103 (P)(A), Revision0,"Realistic Large Break LOCAMethodology for Pressurized Water Reactors" Framatome ANP,April 2003[Licensing Restriction 9)

8. EMF-2310(P)(A), Revision 1,"SRPChapter 15Non-LOCA Methodology 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 EvaluationModel, S-RELAP5 Based" AREVA,December 2016[Licensing Restriction 4) 10.XN-NF-75-32(P)(A), Supplements 1,2,3& 4,"Computational Procedurefor Evaluating Fuel RodBowing" Exxon Nuclear Company Inc.,February 1983 1l XN-NF-78-44(NP)(A), "AGeneric Analysis ofthe Control RodEjection Transient for PressurizedWater Reactors" Exxon Nuclear Company Inc.,October 1983[Licensing Restrictions3and8a) 12.XN-NF-79-56(P)(A), Revision 1andSupplement 1,"Gadolinia Fuel Properties forLWRFuel SafetyEvaluation" Siemens Power Corporation, October 1981 13.XN-NF-82-06(P)(A), Revision 1& Supplements 2,4,and5,"Qualification ofExxon Nuclear Fuel Extended for Burnup" Exxon Nuclear Company Inc., October 1986 14.XN-NF-82-21(P)(A), Revision 1,"Application ofExxon Nuclear Company PWRThermal Margin Methodology toMixed Core Configurations" Exxon Nuclear Company Inc., August 1983 Calvert Cliffs2,Cycle 24COLR Page 20of22 Rev.0

mx W

- i 15.XN-NF-85-92(P)(A), Revision 0,"Exxon Nuclear Uranium Dioxide/Gadolinia Irradiation Examination andThermalConductivity Results"Exxon Nuclear Company Inc.,September 1986 16.CEN-124(B)-P,"Statistical Combination ofUncertainties Methodology Part 2:Combination ofSystem Parameter Uncertainties inThermal Margin Analyses forCalvert CliffsUnits 1and 2,"January 1980 [Not used this for fuel cycle) 17.CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert CliffsUnits 1 and2," December 1981 [Notused for thisfuelcycle) 18.Letterfrom Mr.D.H.Jaffe (NRC)to Mr. A.E.Lundvall, Jr.(BG&E), dated June 24,1982, Unit 1Cycle 6License Approval (Amendment No. 71toDPR-53 andSER) [Approval to CEN-124(B)-P (three parts) andCEN-191(B)-P))[Not usedfor thisfuel cycle) 19.CENPD-161-P-A, "TORCCode, A ComputerCode for Determining the Thermal Margin ofa Reactor Core," April 1986 [Not usedfor this fuelc ycle) 20.CENPD-206-P-A, "TORCCode, andSimplified Verification Modeling Methods," June 1981

[Not usedfor this fuelcycle) 21.CENPD-225-P-A, "Fuel andPoison RodBowing," June1983[Not used for thisfuel cyclej 22.CENPD-382-P-A, "Methodology for Designs Core Containing Erbium Burnable Absorbers,"

August 1993 [Not usedfor thisfuelcycle) 23.CENPD-139P-A, "C-E Fuel EvaluationModel Topical 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 toFuel Evaluation Model," April1986 [Not usedfor thisfuel cycle) 26.Letterfrom Mr.S.A.McNeil, (NRC)

Jr. toMr.J. A.Tiernan (BG&E), dated February 4, 1987, Docket Nos. 50-317 and50-318, "SafetyEvaluation ofTopical Report CEN-161-(B)-P, Supplement 1-P, Improvements toFuel Evaluation Model" (Approval ofCEN-161(B),

Supplement 1-P) [Notusedfor fuel this cycle) 27.CEN-372-P-A, "Fuel RodMaximum Allowable GasPressure," May1990 [Not usedfor this fuel cycle) 28.CENPD-135, Supplement 5-P, "STRIKIN-II, A Cylindrical Geometry Fuel RodHeat Transfer Program," April 1977 [Not usedfor thisfuelcycle) 29.CENPD-387-P-A, Latest Approved "ABBCritical Revision, Heat Flux Correlations for PWR Fuel" [Not usedfor thisfuel cycle) 30.CENPD-404-P-A, Latest Approved Revision,"Implementation ofzIRLOTM Cladding Material inCENuclear Power FuelAssembly Designs" [Not used for thisfuel cycle)

Calvert Cliffs 2,Cycle 24COLR Page 21of22 Rev.0

m W x

- i 31.WCAP-1 1596-P-A, "Qualification ofthe PHOENIX-P, ANCNuclearDesign for System Pressurized Water ReactorCores," June 1988. Notused

[ for fuel this cycle) 32.WCAP-10965-P-A, "ANC: A WestinghouseAdvanced Nodal September Code,"

Computer 1986. [Not used for this fuelcycle) 33.WCAP-10965-P-A Addendum 1,"ANC:A Westinghouse Advanced Computer Nodal Code; Enhancements toANCRod Power Recovery," April 1989. [Not for used fuel this cycle) 34.WCAP-16072-P-A, "Implementation ofzirconium Diboride Burnable Absorber Coatings inCENuclear Power Fuel Assembly Designs," 2004.

August used

[Not this for fuel cycle) 35.WCAP-16045-P-A, "Qualification ofthe Two-Dimensional Code Transport PARAGON," August 2004. [Not used for this fuel cycle)

Calvert Cliffs 2,Cycle 24COLR Page 22of22 Rev.0