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H. Todd GrantGeneral ManagerNuclear EngineeringOconee Nuclear StationDuke EnergyON01VP 7800 Rochester HwySeneca, SC 29672o. 864.873.6767f: 864.873.5791Todd.Grant@duke-energy.comRA-22-016610 CFR 50.36May 19, 2022U. S. Nuclear Regulatory CommissionDocument Control DeskWashington, D. C. 20555-0001Duke Energy Carolinas, LLCOconee Nuclear Station (ONS) Unit 3Docket Number 50-287Renewed License Number DPR-55Subject:Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 3 Cycle 32(Revision 0)Pursuant to Oconee Technical Specification 5.6.5.d, attached is an information copy of the CoreOperating Limits Report (COLR) for Oconee Unit 3, Cycle 32, ONEI-0400-578, Revision 0.Any inquiries on this submittal should be directed to Sam Adams, Oconee Regulatory Affairs, at864-873-3348.Sincerely,H. Todd GrantGeneral ManagerNuclear EngineeringOconee Nuclear StationAttachment:ONEI-0400-578 Revision 0 – Oconee Unit 3 Cycle 32 COLR

RA-22-0166May 19, 2022cc (w/attachment):Ms. Laura Dudes, Administrator, Region IIU.S. Nuclear Regulatory CommissionMarquis One Tower245 Peachtree Center Ave., NE, Suite 1200Atlanta, GA 30303-1257Mr. Shawn Williams, Project Manager(by electronic mail only)U.S. Nuclear Regulatory Commission11555 Rockville PikeMail Stop O-08B1ARockville, MD 20852-2738Mr. Jared NadelNRC Senior Resident InspectorOconee Nuclear StationPage 2

Facility Code :ONApplicable Facilities :ONDocument Number :ONEI-0400-578Document Revision Number :000Document EC Number :Change Reason :produced IAW AD-NF-ALL-0807Document Title :Oconee 3 Cycle 32 Core Operating Limits ReportOrr, David SOriginator3/22/2022Forster, Joy DDesign Verifier3/22/2022Reed, JamesCross Disciplinary Review3/22/2022Washburn, WalterEI Inspection - site3/22/2022Lambert, BradApprover3/22/2022Notes :

ONEI-0400-578 (Rev. 0)Page 1 of 22Oconee 3 Cycle 32 Core Operating Limits ReportONEI-0400-578Revision 0Reload 50.59 AR# 02418346Prepared By:D.S. OrrDesign Verified By:J.D. ForsterCross-Disciplinary Review By:James Reed, Safety AnalysisStakeholder Inspection By:Walter Washburn, ONS RESApproved By:B.J. LambertAll signatures were captured viaFusion E-signature. See theFusion cover sheet for signaturedates.The CDR was limited to pages 4,6 and 20 only.Revision SummaryRevisionPages RevisedPages AddedPages Deleted0--1 - 22--CommentsOriginal issue.NOTES: The O3C32 COLR will cease to be effective during NO MODE between cycles 32 and 33.

ONEI-0400-578 Rev 0Page 2 of 22Oconee 3 Cycle 32Table Of ContentsSection 1.0 Error Adjusted Core Operating Limits3.1.13.1.33.1.43.1.53.2.1NRC ApprovedMethodologyTechnical SpecificationReference #Safety Limits1, 2, 3, 4, 5,6, 7, 8, 9, 10Shutdown Margin (SDM)1, 3, 7 ,8Moderator Temperature Coefficient (MTC)1, 3, 7Control Rod Group Alignment Limits1, 3, 7, 8Safety Rod Position Limits1 ,3, 4, 5, 7, 8, 9, 10Regulating Rod Position Limits1, 3, 4, 5, 7, 8, 9, 103.2.2Axial Power Imbalance Operating Limits1, 2, 3, 4, 5,7, 8, 9, 103.2.33.3.1Quadrant Power Tilt (QPT)Reactor Protective System (RPS)Instrumentation1, 3, 7, 9, 101, 2, 3, 4, 5,6, 7, 8, 9, 103.4.1RCS Pressure, Temperature, and FlowDeparture from Nucleate Boiling LimitsCore Flood Tanks (CFTs)Borated Water Storage Tank (BWST)Spent Fuel Pool Boron ConcentrationBoron Concentration (RCS andRefueling Canal)Core Operating Limits Report (COLR)TS Number2.1.13.5.13.5.43.7.123.9.15.6.5SLC Number16.5.1316.13.10High Pressure Injection and ChemicalAddition Systems4, 5, 7, 81, 3, 7 ,81, 3, 7 ,81, 3, 7 ,81, 3, 7 ,8NoneNRC ApprovedMethodologyReference #1, 3, 7 ,8COLR ParameterMaximum Allowed RPS PowerImbalance LimitsShutdown MarginMTCMisaligned, Dropped, or InoperableMisaligned, Dropped, or InoperableWithdrawal Sequence and Overlap4-pump No Inoperable Rod CRPosition Setpoints3-pump No Inoperable Rod CRPosition Setpoints4-pump Operational PowerImbalance Setpoints3-pump Operational PowerImbalance SetpointsQPT SetpointsCorrelation SlopeVariable Low RCS PressureRPS SetpointsMaximum Allowed RPS PowerImbalance Limits4-pump RPS PowerImbalance Setpoints3-pump RPS PowerImbalance SetpointsRCS Pressure, Temperature,and FlowBoron ConcentrationBoron ConcentrationBoron ConcentrationBoron ConcentrationReferencesCOLR ParameterVolume and Boron Concentrationof Concentrated Boric AcidStorage Tank (CBAST)Section 2.0 Core Operating Limits - Not Error Adjusted (NOT FOR PLANT USE)TS Number2.1.13.2.13.2.3Technical SpecificationSafety LimitsRegulating Rod Position LimitsQuadrant Power Tilt (QPT)NRC ApprovedMethodologyReference #1, 2, 3, 4, 5,6, 7, 8, 9, 10COLR ParameterVariable Low RCS PressureProtective LimitsAxial Power ImbalanceProtective Limits1, 3, 4, 5, 7, 8, 9, 10 Rod Index Limits1, 3, 7, 9, 10Quadrant Power Tilt Limits

ONEI-0400-578 Rev 0Page 3 of 22Oconee 3 Cycle 321.0 Error Adjusted Core Operating LimitsThe Core Operating Limits Report for O3C32 has been prepared in accordance with the requirements ofTS 5.6.5. The core operating limits within this report have been developed using NRC approvedmethodology identified in References 1 through 13. The RPS protective limits and maximum allowablesetpoints are documented in References 14 through 16. These limits are validated for use in O3C32 byReferences 17 and 18. The O3C32 analyses assume a design flow of 108.5% of 88,000 gpm per RCSpump, radial local peaking (F h) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC ( 100 ppmB)Tavg reduction for up to 10 F provided 4 RCPs are in operation and Tavg does not decrease below 569 F.The error adjusted core operating limits included in Section 1 of the report incorporate all necessaryuncertainties and margins required for operation of the O3C32 reload core.1.1 References1. DPC-NE-1006-PA, Oconee Nuclear Design Methodology Using CASMO-4 / SIMULATE-3,NRC SE issued August 2, 2011.2. DPC-NE-1002-A, Oconee Nuclear Station Reload Design Methodology II, SE dated July 21, 2011.3. NFS-1001-A, Oconee Nuclear Station Reload Design Methodology, SE dated July 21, 2011.4. DPC-NE-2003-PA, ONS Core Thermal Hydraulic Methodology Using VIPRE-01,SE dated July 21, 2011.5. DPC-NE-2005-PA, Thermal Hydraulic Statistical Core Design Methodology, SE dated October 29, 2008.6. DPC-NE-2008-PA, Fuel Mechanical Reload Analysis Methodology Using TACO3 and GDTACO,SE dated July 21, 2011.7. DPC-NE-3005-PA, UFSAR Chapter 15 Transient Analysis Methodology, SE dated January 26, 2021.8. DPC-NE-3000-PA, Thermal Hydraulic Transient Analysis Methodology, SE dated July 21, 2011.9. BAW-10192P-A, Revision 0, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model forOnce-Through Steam Generator Plants, SER dated February 18, 1997.10. BAW-10164P-A, Rev. 4 and 6, RELAP5/MOD2-B&W - An Advanced Computer Program for Light WaterReactor LOCA and Non-LOCA Transient Analysis, SERs dated April 9, 2002 and June 25, 2007, respectively.11. BAW-10192P-A, Supplement 1P-A, Revision 0, BWNT Loss of Coolant Accident Evaluation Model forOnce-Through Steam Generator Plants, SE dated November 2, 2017.12. BAW-10227P-A, Revision 1, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel,June 2003 (SER to BAW-10186P-A dated June 18, 2003).13. BAW-10231P-A, Rev. 1, COPERNIC Fuel Rod Design Computer Code, January 2004.14. OSC-4048, Revision 6, RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and VariableLow Pressure Safety Limit.15. OSC-5604, Revision 5, Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted FluxFlow Ratio of 1.094.16. OSC-7265, Revision 1, Tc and EOC Reduced Tavg Operation.17. OSC-11978, Revision 1, O3C32 Maneuvering Analysis.18. OSC-11993, Revision 0, O3C32 Reload Safety Evaluation.

ONEI-0400-578 Rev 0Page 4 of 22Oconee 3 Cycle 32Miscellaneous Setpoints100% rated thermal power, or RTP, is 2568 MWth. See TS 1.1, "Definitions."BWST boron concentration shall be greater than 2500 ppm and less than 3000 ppm.Referred to by TS 3.5.4.Spent fuel pool boron concentration shall be greater than 2500 ppm.Referred to by TS 3.7.12.The equivalent of at least 1100 cubic feet of 11,000 ppm boron shall be maintained in the CBAST.Referred to by TS SLC 16.5.13 and SLC 16.13.10.CFT boron concentration shall be greater than 2400 ppm. The average boron concentration in theCFT's shall be less than 4000 ppm.Referred to by TS 3.5.1.RCS and Refueling canal boron concentration shall be greater than 2400 ppm and less than 3000 ppm.Referred to by TS 3.9.1.Shutdown Margin (SDM) shall be greater than 1% k/k.Referred to by TS 3.1.1.Moderator Temperature Coefficient (MTC) shall be less than:Linear interpolation is valid within the table provided.Referred to by TS 3.1.3.MTC x 10-4 ρ / F 0.70 0.5250.000.000.00% FP02080100120Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall beReferred to by TS 3.4.1.4 RCP: measured hot leg pressure 2125 psig3 RCP: measured hot leg pressure 2125 psigDNB parameter for RCS loop average temperature shall be:Referred to by TS 3.4.1.The measured Tavg must be less than COLR limits minusinstrument uncertainty. Tc is the setpoint value selected bythe operators.Max Loop Tavg (Incl 2 F unc) Tc, F4 RCP Op 3 RCP 2.5581.95582.9582.1* This limit is applied to the loop with the lowest loop average temperature consistent withthe NOTE in SR 3.4.1.2. All other temperature limits apply to the maximum loop Tavg.DNB parameter for RCS loop total flow shall be:Referred to by TS 3.4.1.4 RCP:3 RCP:Measured 108.5 %dfMeasured 74.7 % of 4 RCP min flowRegulating rod groups shall be withdrawn in sequence starting with group 5, group 6, and finally group 7.Referred to by TS 3.2.1.Regulating rod group overlap shall be 25% 5% between two sequential groups.Referred to by TS 3.2.1.Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculationswhen determining if overlap requirements are met as these situations are explicitly addressed byTS 3.1.4 (Control Rod Group Alignment Limits), TS 3.1.5 (Safety Rod Position Limits), and TS 3.2.3(Quadrant Power Tilt).

ONEI-0400-578 Rev 0Page 5 of 22Oconee 3 Cycle 32Quadrant Power Tilt SetpointsCore Power Level, %FPSteady State0 - 30 30Transient0 - 30 30Maximum 0Full Incore8.054.509.847.5516.99Out of Core6.092.857.715.6314.22Backup Incore3.862.424.813.6210.06Referred to by TS 3.2.3Correlation Slope (CS)1.15Referred to by TS 3.3.1 (SR 3.3.1.3).

ONEI-0400-578 Rev 0Page 6 of 22Oconee 3 Cycle 32Variable Low RCS Pressure RPS SetpointsReferred to by TS 3.3.12400P 2355 psigT 618 F2300Reactor Coolant Pressure, PSIG22002100AcceptableOperationP 11.14 * Tout - 47062000UnacceptableOperation1900P 1800 psig18001700T 584 F540560580600Reactor Coolant Outlet Temperature, F620640

ONEI-0400-578 Rev 0Page 7 of 22Oconee 3 Cycle 32Referred to by TS 2.1.1 and TS Table 3.3.1-1Maximum Allowable RPS Power Imbalance Limits% FP% ImbalancePmax Pmax 0Pmax Pmax 0.062.381.781.762.30.0-35.0-35.0-14.414.435.035.04 Pumps3 Pumps

ONEI-0400-578 Rev 0Page 8 of 22Oconee 3 Cycle 32Operational Power Imbalance SetpointsReferred to by TS 3.2.24 Pumps3 Pumps%FPFullIncoreBackupIncoreOut 13.263.128.028.028.00.028.028.028.0Referred to by TS 3.2.2

ONEI-0400-578 Rev 0Page 9 of 22Oconee 3 Cycle 32RPS / Operational Power Imbalance SetpointsOperation with 4 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FPRPS TripFull Incore AlarmOut of Core .0% FPRPS TripFull Incore AlarmOut of Core Alarm

ONEI-0400-578 Rev 0Page 10 of 22Oconee 3 Cycle 32RPS / Operational Power Imbalance SetpointsOperation with 3 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FPRPS TripFull Incore AlarmOut of Core 028.00.0-33.033.0-28.028.0-28.028.0% FPRPS TripFull Incore AlarmOut of Core Alarm

ONEI-0400-578 Rev 0Page 11 of 22Oconee 3 Cycle 32RPS Power Imbalance SetpointsReferred to by TS 3.3.1 and TS Table 3.3.1-1Thermal Power Level, %FP120.0(-14.4,107.9)(14.4,107.9)100.0M2 -0.942M1 0.942Acceptable 4 Pump 80.6)80.060.0(-33.0,63.1)(33.0,63.1)Acceptable 3 or 4 Pump cent Power Imbalance20.030.040.0