ML15040A080

Calvert Cliffs Nuclear Power Plant, Unit 2 - Core Operating Limits Report for Cycle 20

ML15040A080
Person / Time
Site:	Calvert Cliffs
Issue date:	02/04/2015
From:	Gellrich G H Exelon Generation Co
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
Download: ML15040A080 (24)

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AGeorge GellrichExelon Generation Site Vice PresidentCalvert Cliffs Nuclear Power Plant1650 Calvert Cliffs ParkwayLusby, MD 20657410 495 5200 Office717 497 3463 Mobilewww.exeloncorp.comgeorge~gellrich@exeloncorp.comTS 5.6.5February 4, 2015U. S. Nuclear Regulatory CommissionATTN: Document Control DeskWashington, DC 20555Calvert Cliffs Nuclear Power Plant, Unit No. 2Renewed Facility Operating License No. DPR-69NRC Docket No. 50-318

Subject:

Core Operatingq Limits Report for Unit 2, Cycle 20Pursuant to Calvert Cliffs Nuclear Power Plant Technical Specification 5.6.5, the attached CoreOperating Limits Report for Unit 2, Cycle 20, Revision 1 (Attachment 1), is provided for yourrecords.Please replace the Unit 2 Core Operating Limits Report in its entirety, with the attachedRevision 1.There are no regulatory commitments contained in this correspondence.Should you have questions regarding this matter, please contact Mr. Douglas E. Lauver at(410) 495-5219.Respectfully,George H. GellrichSite Vice PresidentGHG/PSF/bjm

Attachment:

(1) Core Operating Limits Report for Unit 2, Cycle 20, Revision 1 Document Control DeskFebruary 4, 2015Page 2cc: Resident Inspector, NRC(Without Attachment)NRC Project Manager, Calvert CliffsNRC Regional Administrator, Region IS. Gray, MD-DNR ATTACHMENT (1)CORE OPERATING LIMITS REPORTFORUNIT 2, CYCLE 20, REVISION 1Calvert Cliffs Nuclear Power PlantFebruary 4, 2015 Amw Exelon Generation.,JCalvert Cliffs Nuclear Power PlantCore Operating Limits ReportCOLRUnit 2 Cycle 20Revision IIEffective Date: lo,ý al 05mResponsible Engneer / DateStation Qualifiled Reviewer I DateIICalver! Cliffs 2, Cycle 20 COLR Page I of2l Rev. ICalvert Cliffs 2. Cycle 20 COLRPage I of 21Rev. I AO Exelon Generation.CORE OPERATING LIMITS REPORTCALVERT CLIFFS UNIT 2, CYCLE 20The following limits are included in this Core Operating Limits Report:Specification TitlePage3.1.13.1.33.1.43.1.63.2.13.2.33.2.53.3.13.4.13.9.1Introduction ........................................................................................................... 4Definitions ......................................................................................................... 5Licensing Restrictions ........................................................................................... 6Shutdown Margin (SDM) ...................................................................................... 8Moderator Temperature Coefficient (MTC) .......................................................... 8Control Element Assembly (CEA) Alignment ...................................................... 8Regulating Control Element Assembly (CEA) Insertion Limits ........................... 8Linear Heat Rate (LHR) ......................................................................................... 8Total Integrated Radial Peaking Factor (FrT) ........................................................... 9Axial Shape Index (ASI) ......................................................................................... 9Reactor Protective System (RPS) Instrumentation -Operating .............................. 9RCS Pressure, Temperature, and Flow DNB Limits .............................................. 9Boron Concentration ............................................................................................. 10List of Approved Methodologies .......................................................................... 19The following figures are included in this Core Operating Limits Report:NumberTitlePageFigure 3.1.6Figure 3.2.1-1Figure 3.2.1-2Figure 3.2.3Figure 3.2.5Figure 3.3.1-1Figure 3.3.1-2Figure 3.3.1-3CEA Group Insertion Limits vs. Fraction of Rated Thermal Power ......................... I 1Allowable Peak Linear Heat Rate vs. Time in Cycle ............................................ 12Linear Heat Rate Axial Flux Offset Control Limits .............................................. 13TTotal Integrated Radial Peaking Factor (F, ) vs.Allowable Fraction of Rated Thermal Power ........................................................ 14DNB Axial Flux Offset Control Limits .............................................................. 15Axial Power Distribution -High Trip Setpoint Peripheral Axial ShapeIndex vs. Fraction of Rated Thermal Power ........................................................ 16Thermal Margin/Low Pressure Trip Setpoint -Part 1 ......................................... 17Thermal Margin/Low Pressure Trip Setpoint -Part 2 ......................................... 18Calvert Cliffs 2, Cycle 20 COLRPage 2 of 21Rev. I AO ExeLon GenerationUNIT 2CORE OPERATING LIMITS REPORTLIST OF EFFECTIVE PAGESPage No. Rev. No.1 12 13 14 15 16 17 18 19 110 1I1 I12 113 114 115 116 117 118 119 120 121 1Calvert Cliffs 2, Cycle 20 COLRPage 3 of 21Rev. I AO Exeton GenerationINTRODUCTIONThis report provides the cycle-specific limits for operation of Calvert Cliffs Unit 2, Cycle 20. Itcontains the limits for:Shutdown Margin (SDM)Moderator Temperature Coefficient (MTC)Control Element Assembly (CEA) AlignmentRegulating Control Element Assembly (CEA) Insertion LimitsLinear Heat Rate (LHR)Total Integrated Radial Peaking Factor (FrT)Axial Shape Index (ASI)Reactor Protective System (RPS) Instrumentation -OperatingRCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) LimitsBoron ConcentrationIn addition, this report contains a number of figures which give limits on the parameters listedabove. If any of the limits contained in this report are exceeded, corrective action will be taken asdefined in the Technical Specifications.This report has been prepared in accordance with the requirements of Technical Specifications.The cycle specific limits have been developed using the NRC-approved methodologies given inthe "List of Approved Methodologies" section of this report and in the Technical Specifications.COLR Revision 0Initial release of the Unit 2 Cycle 20 (U2C20) COLR per Safety Evaluation SE00522Revision 0. U2C20 may operate in all plant modes.COLR Revision 1Adds an end-of-cycle refueling boron concentration option per Safety Evaluation SE00522Revision 1 which will allow the core to be offloaded to the spent fuel pool during the 2015RFO. Changed corporation name from CENG to Exelon Generation. Added signature onCOLR cover page for a Station Qualified Reviewer. Updated the title for the approvalauthority.Calvert Cliffs 2, Cycle 20 COLR Page 4 of2I Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 4 of 21Rev. I rAO Exelon GenerationDEFINITIONSAxial Shape Index (ASI)ASI shall be the power generated in the lower half of the core less the power generated inthe upper half of the core, divided by the sum of the power generated in the lower andupper halves of the core.ASI = lower- upper = YElower + upperThe Axial Shape Index (YI) used for the trip and pretrip signals in the Reactor ProtectionSystem (RPS) is the above value (YE) modified by an appropriate multiplier (A) and aconstant (B) to determine the true core axial power distribution for that channel.Y= AYE + BTotal Integrated Radial Peaking Factor -FrTThe Total Integrated Radial Peaking Factor is the ratio of the peak pin power to theaverage pin power in an unrodded core.Calvert Cliffs 2, Cycle 20 COLR Page 5 of2I Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 5 of 21Rev. I AO Exelon Generation,LICENSING RESTRICTIONS1) For the Asymmetric Steam Generator Transient analysis performed in accordance withthe methodology of Technical Specification 5.6.5.b.8, the methodology shall be revisedto capture the asymmetric core inlet temperature distribution and application of localpeaking augmentation factors. The revised methodology shall be applied to CalvertCliffs Unit 2 core reload designs starting with Cycle 19.2) For the Seized Rotor Event analysis performed in accordance with the methodology ofTechnical Specification 5.6.5.b.8, the methodology shall be revised to capture theasymmetric core inlet flow distribution. The revised methodology shall be applied toCalvert Cliffs Unit 2 core reload designs starting with Cycle 19.3) For the Control Element Assembly Ejection analysis performed in accordance with themethodology of Technical Specification 5.6.5.b.1 1, the cycle-specific hot zero powerpeak average radial fuel enthalpy is calculated based on a modified power dependentinsertion limit with Control Element Assembly Bank 3 assumed to be fully inserted (onlyin the analysis, not in actual plant operations). This revised methodology shall be appliedto Calvert Cliffs Unit 2 core reload designs starting with Cycle 19.4) The Small Break Loss of Coolant accident performed in accordance with themethodology of Technical Specification 5.6.5.b.9 shall be analyzed using a breakspectrum with augmented detail related to break size. This revised methodology shall beapplied to Calvert Cliffs Unit 2 core reload designs starting with Cycle 19.5) Core Operating Limits Report Figures 3.1.6, 3.2.3, and 3.2.5 shall not be changedwithout prior NRC review and approval until an NRC-accepted generic, or CalvertCliffs-specific, basis is developed for analyzing the Control Element Assembly RodBank Withdrawal Event, the Control Element Assembly Drop, and the Control ElementAssembly Ejection (power level-sensitive transients) at full power conditions only.6) Approval of the use of S-RELAP5 (Technical Specification 5.6.5.b.8) is restricted only tothose safety analyses that confirm acceptable transient performance relative to thespecified acceptable fuel design limits. Prior transient specific NRC approval is requiredto analyze transient performance relative to reactor coolant pressure boundary integrityuntil NRC-approval is obtained for a generic or Calvert Cliffs-specific basis for the useof the methodology in Technical Specification 5.6.5.b.8 to demonstrate reactor coolantpressure boundary integrity.Calvert Cliffs 2, Cycle 20 COLRPage 6 of 21Rev. I AO Exelon Generation.7) For the RODEX2-based fuel thermal-mechanical design analysis performed inaccordance with the methodology of Technical Specification 5.6.5.b.3, Calvert CliffsUnit 2 core reload designs (starting with Cycle 19) shall satisfy the following criteria:a. Predicted rod internal pressure shall remain below the steady state system pressure.b. The linear heat generation rate fuel centerline melting safety limit shall remain below21.0 KW/ft.8) For the Control Element Assembly Ejection analysis, Calvert Cliffs Unit 2 core reloads(starting with Cycle 19) shall satisfy the following criteria:a. Predicted peak radial average fuel enthalpy when calculated in accordance with themethodology of Technical Specification 5.6.5.b.1 I shall remain below 200 cal/g.b. For the purpose of evaluating radiological consequences, should the S-RELAP5 hotspot model predict fuel temperature above incipient centerline melt conditions whencalculated in accordance with the methodology of Technical Specification 5.6.5.b.8, aconservative radiological source term (in accordance with Regulatory Guide 1.183,Revision 0) shall be applied to the portion of fuel beyond incipient melt conditions(and combined with existing gap source term), and cladding failure shall bepresumed.9) The approval of the emergency core cooling system evaluation performed in accordancewith the methodology of Technical Specification 5.6.5.b.7 shall be valid only for CalvertCliffs Unit 2, Cycle 19. To remove this condition, Calvert Cliffs shall obtain NRCapproval of the analysis of once- and twice-burned fuel for core designs following Unit 2Cycle 19.NOTE: The revised methodology was submitted and received NRC approval in December2012. This license condition is satisfied; however since NRC approval wasobtained via letter and not LAR, this license condition is still listed in Appendix Cof the Tech. Specs. and has been retained here for consistency.

Reference:

Letter from Douglas V. Picket (NRC) to George H. Gellrich (CCNPP) dated February18, 2011, Calvert Cliffs Nuclear Power Plant, Unit Nos. I and 2 -Amendment Re: Transitionfrom Westinghouse Nuclear Fuel to AREVA Nuclear Fuel (TAC Nos. ME2831 and ME2832)Calvert Cliffs 2, Cycle 20 COLR Page 7 of2l Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 7 of 21Rev. I A Pr Exelon GenerationCYCLE SPECIFIC LIMITS FOR UNIT 2, CYCLE 203.1.1 Shutdown Margin (SDM) (SR 3.1.1.1)Tavg > 200 TF -Modes 3 and 4:The shutdown margin shall be > 3.5% Ap.Tavg 5200 'F -Mode 5:The shutdown margin shall be > 3.0% Ap.3.1.3 Moderator Temperature Coefficient (MTC) (SR 3.1.3.2)The Moderator Temperature Coefficient (MTC) shall be less negative than -3.0 x 10-4 Ap/0Fat rated thermal power.3.1.4 Control Element Assembly (CEA) Alignment (Action 3.1.4.B.1)The allowable time to realign a CEA is 120 minutes when the pre-misaligned FrT is < 1.65and zero (0) minutes when the pre-misaligned FrT is > 1.65.The pre-misaligned Fr T value used to determine the allowable time to realign the CEA shallbe the latest measurement taken within 5 days prior to the CEA misalignment. If nomeasurements have been taken within 5 days prior to the misalignment and the full corepower distribution monitoring system is unavailable then the time to realign is zero (0)minutes.3.1.6 Regulating Control Element Assembly (CEA) Insertion Limits(SR 3.1.6.1 and SR 3.1.6.2)The regulating CEA groups insertion limits are shown on COLR Figure 3.1.6.Figure 3.1.6 will not be changed unless the requirements in Licensing Restriction 5 are met.3.2.1 Linear Heat Rate (LHR) (SR 3.2.1.2 and SR 3.2.1.4)The linear heat rate shall not exceed the limits shown on COLR Figure 3.2.1-1.The axial shape index power dependent control limits are given in COLR Figure 3.2.1-2.When using the excore detector monitoring system (SR 3.2.1.2):The alarm setpoints are equal to or less than the ASI limits; therefore when the alarms areadjusted, they provide indication to the operator that ASI is not within the limits.The axial shape index alarm setpoints are shown as a function of fraction of thermal power onCOLR Figure 3.2.1-2.Calvert Cliffs 2, Cycle 20 COLRPage 8 of 21Rev. I AExeton Generation,When using the incore detector monitoring system (SR 3.2.1.4):The alarm setpoints are adjusted to protect the Linear Heat Rate limits shown on COLRFigure 3.2.1-1 and uncertainty factors are appropriately included in the setting of thesealarms.The uncertainty factors for the incore detector monitoring system are:I. A measurement-calculational uncertainty factor of 1.072. An engineering uncertainty factor of 1.03,3.a For measured thermal power less than or equal to 50 percent but greater than 20 percentof rated full core power a thermal power measurement uncertainty factor of 1.035.3.b For measured thermal power greater than 50 percent of rated full core power a thermalpower measurement uncertainty factor of 1.020.3.2.3 Total Integrated Radial Peaking Factor (FrT) (SR 3.2.3.1)The calculated value of FrT shall be limited to < 1.65.The allowable combinations of thermal power, CEA position, and FrT are shown on COLRFigure 3.2.3.Figure 3.2.3 will not be changed unless the requirements in Licensing Restriction 5 are met.3.2.5 Axial Shape Index (ASI) (SR 3.2.5.1)The axial shape index and thermal power shall be maintained equal to or less than the limitsof COLR Figure 3.2.5 for CEA insertions specified by COLR Figure 3.1.6.Figure 3.2.5 will not be changed unless the requirements in Licensing Restriction 5 are met.3.3.1 Reactor Protective System (RPS) Instrumentation -Operating(Reactor Trip Setpoints) (TS Table 3.3.1-1)The Axial Power Distribution -High trip setpoint and allowable values are given in COLRFigure 3.3.1-1.The Thermal Margin/Low Pressure (TM/LP) trip setpoint is given in COLR Figures 3.3.1-2and 3.3.1-3. The allowable values are to be not less than the larger of (l) 1875 psia or (2) thevalue calculated from COLR Figures 3.3.1-2 and 3.3.1-3.3.4.1 RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling (DNB) LimitsThe RCS DNB parameters for pressurizer pressure, cold leg temperature, and RCS total flowrate shall be within the limits specified below:a. Pressurizer pressure > 2200 psia;b. RCS cold leg temperature (Tc) < 548°F; andc. RCS total flow rate > 370,000 gpm.Calvert Cliffs 2, Cycle 20 COLRCalvert Cliffs 2, Cycle 20 COLR Page 9 of2l Rev. IPage 9 of 21Rev. I AwExelon Generation,3.9.1 Boron Concentration (SR 3.9.1.1)The refueling boron concentration will maintain the keff at 0.95 or less (including a 1% Ak/kconservative allowance for uncertainties). The refueling boron concentration shall bemaintained uniform. For Mode 6 operation the RCS temperature must be maintained< 1400F.U2C20 Refueling Boron Concentration LimitsU2C20 Burnup > 16 GWD/MTU0 Credited CEAsPost-Refueling UGS or RV Head Lift Height No RestrictionRestrictions.Minimum Required Refueling BoronConcentration:This number includes:" Chemistry Sampling Uncertainty > 2554 ppm" Boron-lO Depletion Allowance" Margin for dilution of refueling pool (Note 1)between low and high level alarms" Unlimited number of temporary rotations offuel assemblies" Extra Conservatism for empty locationsduring refueling operations.Note: (1) The limit in the above table represents the minimum required refueling boronconcentration. It is acceptable for NEOP-23 to conservatively specify higher values.Calvert Cliffs 2, Cycle 20 COLR Page 10 of 21 Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 10 of 21Rev. I A Exelon Generation.I-U-00z-J1.0000.9000.8000.7000.6000.5000.4000.3000.2000.100AboveZPPD7LSEPOINT(1.00 FRTP Grou 5@ 5%In$6ertedg I I lSf(0.9) FRTP .Grou 5 @ 5%Inserted_ OP__RAlIlNGIC (0.75 FRlP, 3rou 5@50% Ins ered) --R,-G1IN-I- IK I I-.r_ -d (0.7,0FR ,Gro , p5@G 60% l,,serte )_ -Iis e --,T.5 F I.56 FRTP, roup- @ 59 % ed)gI*v i , -* -.--- -- --.---- ---------S !ES,0 , -0 Tranient Insertion LinsitSMV, I j =(0. 0 FRTP, Grobp3 6M61 iserteJ0- -" ------.(Abc ve Zer Pov(er PDIý Setp int,Groyp 3 q 60% Ihserte.GULAING GRUREUATN GRU 1I I I0% 20% 40%135" 108" 81"I I I I60% 8096 100%0%54" 27" 0" 135"I I I I I I20% 40% 60% 80% 100%0%108" 81" 54" 27" 0" 135"I I I I I20% 40% 60% 80% 100%108" 81" 54" 27" 0"[K GLTN GRUPi:EGULAT'_ G *U1 I I I I I I0% 20% 40% 60% 80% 100%0%135" 108" 81" 54" 27" 0" 135"I20%108"40% 60% 80% 100%81" 54" 27" 0"%CEA INSERTIONINCHES CEA WITHDRAWN(ARO is defined in NEOP-23)Note:Per Tech Spec Bases 3.1.5 and 3.1.6, CEAs are considered to befully withdrawn at 129 inches.Figure 3.1.6CEA Group Insertion Limits vs. Fraction of Rated Thermal PowerThis figure cannot be changed without prior NRC approval.Calvert Cliffs 2, Cycle 20 COLRCalvert Cliffs 2, Cycle 20 COLR Page 11 of2I Rev. 1Page I11 of 21Rev. I AdIIIIIIIIIIIIEWAdMMMWANIOMPFExelon GenerationD17.016.54 4 4 4! 16.0LU.9- 15.5www÷ +15.0z_.UJ+L -J 14.5LL- 14.30.J 14.0._14 4 4 4UNACCEPTABLE OPERATIONACCEPTABLE OPERATION13.513.0BOCEOCTIME IN CYCLEFigure 3.2.1-1Allowable Peak Linear Heat Rate vs. Time in CycleCalvert Cliffs 2, Cycle 20 COLRPage 12 of 21Rev. I AWExelon GenerationIx0a.u.II-IL0z0I-01.101.051.000.950.900.850.800.750.700.650.600.550.500.450.400.350.300.250.20 4--0.60-0.40 -0.20 0.00 0.20 0.400.60PERIPHERAL AXIAL SHAPE INDEX, YiFigure 3.2.1-2Linear Heat Rate Axial Flux Offset Control Limits(AXIAL SHAPE INDEX limits for Linear Heat Rate when using Excore Detector MonitoringSystem)(LCO Limits are not needed below 20% thermal power per SE00433)(See NEOP-23 for Operational Limits)Calvert Cliffs 2, Cycle 20 COLR Page 13 of2l Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 13 of 21Rev. I AMWExelon Generation,1.05w 0.9500.850.75<'I-0.65wLL 0.550zo 0.45I-S0.350.250-- 0.150.05 4-1.601.65 1.70 1.75 1.80FrT1.85Figure 3.2.3Total Integrated Radial Peaking Factor (FrT) VS.Allowable Fraction of Rated Thermal PowerWhile operating with FrT greater than 1.65, withdraw CEAs to or above the Long Term SteadyState Insertion Limits (Figure 3.1.6)This figure cannot be changed without prior NRC approval.Calvert Cliffs 2, Cycle 20 COLRPage 14 of 21Rev. I Exelon Generation-jWW00~0U--z0._11.101.051.000.950.900.850.800.750.700.650.600.550.500.450.400.350.300.250.20-0.60-0.40 -0.20 0.00 0.20 0.40PERIPHERAL AXIAL SHAPE INDEX, Y1Figure 3.2.5DNB Axial Flux Offset Control Limits(LCO Limits are not needed below 20% thermal power per SE00433)(See NEOP-23 for Operational Limits)This figure cannot be changed without prior NRC approval.0.60Calvert Cliffs 2, Cycle 20 COLR Page 15 of2l Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 15 of 21Rev. I Exelon Generation1.3001.2501.2001.1501.1 001.0501.000, 0.9500 0.9000.850M 0.800a= 0.750W 0.700I,-0.650L-0 0.600zo_0.550I-0.500LI.L0.4500.4000.3500.3000.2500.2000.150 --0.80-0.60 -0.40 -0.20 0.00 0.20 0.40PERIPHERAL AXIAL SHAPE INDEX, Yi0.60 0.80Figure 3.3.1-1Axial Power Distribution -High Trip SetpointPeripheral Axial Shape Index vs. Fraction of Rated Thermal PowerCalvert Cliffs 2, Cycle 20 COLRPage 16 of 21Rev. I AOExelon Generation,1.601.501.401.301.201.101.000.901 i 4-0.60 -0.50 -0.40 -0.30 -0.20 -0.10 0.00 0.10 0.20 0.30 0.40 0.50ASI0.60Figure 3.3.1-2Thermal Margin/Low Pressure Trip Setpoint -Part 1(ASI vs. A1)Calvert Cliffs 2, Cycle 20 COLRCalvert Cliffs 2, Cycle 20 COLR Page 17 of2l Rev. IPage 17 of 21Rev. I A w Exelon GenerationpTrip-2var 869.5x(AI)x(QRI)+17.98x"QDNB = Al x QR11.211.1 QR1 = (RTP) + 0.01.0__ _0.90.8 __(0 , 0.8QR1 = 0.3710.7IX 0.6,, _ ICYO0.5 --_ __0.4 F QR,= 0.9167 x (RTP) + 00.3(0. 30.30.20.10.0 --in -10820(1.2, 1.2)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 1.3FRACTION OF RATED THERMAL POWER (RTP)Figure 3.3.1-3Thermal Margin/Low Pressure Trip Setpoint -Part 2(Fraction of Rated Thermal Power vs. QR1)Calvert Cliffs 2, Cycle 20 COLR Page 18 of2l Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 18 of 21Rev. I Exelon Generation,LIST OF APPROVED METHODOLOGIES1. ANF-88-133 (P)(A) and Supplement 1, "Qualification of Advanced Nuclear Fuels' PWR DesignMethodology for Rod Bumups of 62 GWd/MTU" Advanced Nuclear Fuels Corporation,December 19912. BAW- 10240(P)(A), Revision 0, "Incorporation of M5 Properties in Framatome ANP ApprovedMethods" Framatome ANP, May 20043. EMF-92-116(P)(A), Revision 0, "Generic Mechanical Design Criteria for PWR Fuel Designs"Siemens Power Corporation, February 1999 [Licensing Restriction 7]4. EMF-92-153(P)(A), Revision 1, "HTP: Departure from Nucleate Boiling Correlation for HighThermal Performance Fuel," Siemens Power Corporation, January 20055. EMF-96-029(P)(A) Volumes 1 and 2, "Reactor Analysis System for PWRs Volume I -Methodology Description, Volume 2 -Benchmarking Results," Siemens Power Corporation,January 19976. EMF-1961 (P)(A), Revision 0, "Statistical Setpoint/Transient Methodology for CombustionEngineering Type Reactors," Siemens Power Corporation, July 20007. EMF-2103 (P)(A), Revision 0, "Realistic Large Break LOCA Methodology for PressurizedWater Reactors" Framatome ANP, April 2003 [Licensing Restriction 9]8. EMF-23 1 O(P)(A), Revision 1, "SRP Chapter 15 Non-LOCA Methodology for Pressurized WaterReactors" Framatome ANP, May 2004 [Licensing Restrictions 1, 2, 6, and 8b]9. EMF-2328(P)(A), Revision 0, "PWR Small Break LOCA Evaluation Model, S-RELAP5 Based"Framatome ANP, March 2001 [Licensing Restriction 4]10. XN-NF-75-32(P)(A), Supplements 1, 2, 3 & 4, "Computational Procedure for Evaluating FuelRod Bowing" Exxon Nuclear Company Inc., February 198311. XN-NF-78-44(NP)(A), "A Generic Analysis of the Control Rod Ejection Transient forPressurized Water Reactors" Exxon Nuclear Company Inc., October 1983 [LicensingRestrictions 3 and 8a]12. XN-NF-79-56(P)(A), Revision 1 and Supplement 1, "Gadolinia Fuel Properties for LWR FuelSafety Evaluation" Siemens Power Corporation, October 198113. XN-NF-82-06(P)(A), Revision I & Supplements 2, 4, and 5, "Qualification of Exxon NuclearFuel for Extended Burnup" Exxon Nuclear Company Inc., October 198614. XN-NF-82-21(P)(A), Revision 1, "Application of Exxon Nuclear Company PWR ThermalMargin Methodology to Mixed Core Configurations" Exxon Nuclear Company Inc., August1983Calvert Cliffs 2, Cycle 20 COLRPage 19 of 21Rev. I AwExelon Generation15. XN-NF-85-92(P)(A), Revision 0, "Exxon Nuclear Uranium Dioxide/Gadolinia IrradiationExamination and Thermal Conductivity Results" Exxon Nuclear Company Inc., September 198616. CEN-124(B)-P, "Statistical Combination of Uncertainties Methodology Part 2: Combination ofSystem Parameter Uncertainties in Thermal Margin Analyses for Calvert Cliffs Units 1 and 2,"January 198017. CEN-191(B)-P, "CETOP-D Code Structure and Modeling Methods for Calvert Cliffs Units I and 2,"December 198118. Letter from Mr. D. H. Jaffe (NRC) to Mr. A. E. Lundvall, Jr. (BG&E), dated June 24, 1982, Unit ICycle 6 License Approval (Amendment No. 71 to DPR-53 and SER) [Approval to CEN-124(B)-P(three parts) and CEN- 191 (B)-P)]19. CENPD-I 61 -P-A, "TORC Code, A Computer Code for Determining the Thermal Margin of aReactor Core," April 198620. CENPD-206-P-A, "TORC Code, Verification and Simplified Modeling Methods," June 198121. CENPD-225-P-A, "Fuel and Poison Rod Bowing," June 198322. CENPD-382-P-A, "Methodology for Core Designs Containing Erbium Burnable Absorbers," August199323. CENPD-139-P-A, "C-E Fuel Evaluation Model Topical Report," July 197424. CEN-1 61 -(B)-P-A, "Improvements to Fuel Evaluation Model," August 198925. CEN- 161 -(B)-P, Supplement l-P, "Improvements to Fuel Evaluation Model," April 198626. Letter from Mr. S. A. McNeil, Jr. (NRC) to Mr. J. A. Tiernan (BG&E), dated February 4, 1987,Docket Nos. 50-317 and 50-3 18, "Safety Evaluation of Topical Report CEN-161-(B)-P, SupplementI-P, Improvements to Fuel Evaluation Model" (Approval of CEN-161 (B), Supplement I-P)27. CEN-372-P-A, "Fuel Rod Maximum Allowable Gas Pressure," May 199028. CENPD-135, Supplement 5-P, "STRIKIN-Il, A Cylindrical Geometry Fuel Rod Heat TransferProgram," April 197729. CENPD-387-P-A, Latest Approved Revision, "ABB Critical Heat Flux Correlations for PWR Fuel"30. CENPD-404-P-A, Latest Approved Revision, "Implementation of ZIRLOTM Cladding Material inCE Nuclear Power Fuel Assembly Designs".31. WCAP-1 1596-P-A, "Qualification of the PHOENIX-P, ANC Nuclear Design System forPressurized Water Reactor Cores," June 1988.32. WCAP-10965-P-A, "ANC: A Westinghouse Advanced Nodal Computer Code," September1986.33. WCAP-10965-P-A Addendum 1, "ANC: A Westinghouse Advanced Nodal Computer Code;Enhancements to ANC Rod Power Recovery," April 1989.Calvert Cliffs 2, Cycle 20 COLRPage 20 of 21Rev. I M"' Exelon Generation34. WCAP-16072-P-A, "Implementation of Zirconium Diboride Burnable Absorber Coatings in CENuclear Power Fuel Assembly Designs," August 2004.35. WCAP-16045-P-A, "Qualification of the Two-Dimensional Transport Code PARAGON,"August 2004.Calvert Cliffs 2, Cycle 20 COLR Page 21 of2l Rev. ICalvert Cliffs 2, Cycle 20 COLRPage 21 of 21Rev. I