ML14142A216

Oconee, Unit 3 - Core Operating Limits Report (Colr), Cycle 28, ONEI-0400-70, Revision 36

ML14142A216
Person / Time
Site:	Oconee
Issue date:	05/15/2014
From:	Batson S L Duke Energy Carolinas
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
ONS-2014-068 ONEI-0400-70, Rev. 36
Download: ML14142A216 (27)

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ENERGY,Scott L. BatsonVice PresidentOconee Nuclear StationDuke EnergyONO I VP 1 7800 Rochester HwySeneca, SC 29672o: 864.873.3274f 864,873. 4208Scott.Batson@duke-energy.comONS-2014-068May 15, 2014U. S. Nuclear Regulatory CommissionDocument Control DeskWashington, D. C. 20555-0001

Subject:

Duke Energy Carolinas, LLCOconee Nuclear Site Docket Number 50-287Core Operating Limits Report (COLR)Attached, pursuant to Oconee Technical Specification 5.6.5.d, is an information copy of theCore Operating Limits Report for Oconee Unit 3, Cycle 28, ONEI-0400-70, Revision 36.If you have any questions, please direct them to Judy Smith at 864-873-4309.Sincerely,Scott L. BatsonVice PresidentOconee Nuclear StationAttachment"Pizwww.duke-energy.com U.S. Nuclear Regulatory CommissionMay 15, 2014Page 2xc wlatt: Mr. Victor McCree, Regional AdministratorU.S. Nuclear Regulatory Commission, Region IIMarquis One Tower245 Peachtree Center Ave., NE, Suite 1200Atlanta, GA 30303-1257Mr. James R. Hall(By electronic mail only)U.S. Nuclear Regulatory CommissionOne White Flint North, M/S O-8B111555 Rockville PikeRockville, MD 20852-2746Mr. Eddy CroweSenior Resident InspectorOconee Nuclear Site DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TOPRIORITY SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT ISOTHERWISE IDENTIFIED BELOW1) 00813 DOC MGMT EC04T ORIGINAL2) 00358 ONS REGUL COMPUANCE ON03RC3) 06700 ONS MANUAL MASTER FILE ON03DM DO(4) 06937 R R ST CLAIR EC08GDuke Energy;UMENT TRANSMITTAL FORMDate: 04108/114ib ini nt 6rasittai # -"DUK140980068QA CONDITION

• Yes [] NoOTHER ACKNOWLEDGEMENT REQUIRED LI YesIF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASEACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:REFERENCENUCLEAR GENERAL OFFICEOCONEE NUCLEAR STATIONRETENTION 421734OCONEE 3 CYCLE 28 CORE OPERATINGLIMITS REPORTPage 1 of 1Duke EnergyP.O. Box 1006Energy CenterEC04TCharlotte, N.C.28201-1006Recd ByDateI'i4M~!IL(~DOCUMENT NO1ACONDREV #/DATEDISTR CODE112'..345167a910 ill12131415TOltKI 4ONEI-0400-0701036 04/08/14NOMD-27XV1V1iviREMARKS:DUKEDOCUMENTS CREATED UNDER EDM-501 ARE EXCLUDED FROM THE EDM-601PROCESS PER NSD-301, SECTION 2.4. THEREFORE, THE EXEMPTION CODEOR PIP NUMBER REQUIRED BY EDM-601 IS NOT REQUIRED FOR THISDOCUMENT.DAVID A BAXTERVICE PRESIDENTNUCLEAR ENGINEERINGBY:D S ORR DSOfZLA EC08G ONEI-0400-70 Rev 36Page 1 of 24Duke EnergyOconee 3 Cycle 28Core Operating Limits ReportQA Condition ICo-Prepared By. A.L. LanCo-Prepared By: D.S. OrrReviewed By: L.D. McClain YQ4u1," 1 G&W%CDR By: A.R. BinghamApproved By: R.R. St.ClairDate: --L/Date: y-Date:Date: L/. '_/.,-/Date: V/- g-/d Document No. ) Rev. ONIE[-0400-70 Rev. 36Date April 2014Page No. Patne 2 of 24INSPECTION OF ENGLNEERING INSTRUCTIONSR R St. ClawInspection Waived By:Date: .!VCATAWBAInspectionWaivedMCE (Mechanical & Civil) 0 Inspected By/Date:RES (Electrical Only) I] Inspected By/Date:RES (Reactor) El Inspected By/Date:MOD 0l Inspected By/Date:Other ( E) ] Inspected By/Date:OCONEEInspectionWaivedMCE (Mechanical & Civil) 19 Inspected By/Date:RES (Electrical Only) Inspected By/Date:RES (Reactor) [] Inspected By/Date:,,qMOD Inspected By/Date:Other ( ) Inspected By/Date:MCGUIRLEInspectionWaivedMCE (Mechanical & Civil) 1] Inspected By/Date:RES (Electrical Only) C] Inspected By/Date:RES (Reactor) [] Inspected By/Date:MOD E] Inspected By/Date:Other ( 0) ] Inspected By/Date:

ONEI-0400-70 Rev 36Page 3 of 24Oconee 3 Cycle 28Core Operating Limits ReportInsertion Sheet for Revision 36This revision is not valid until the end of operation for Oconee 3 Cycle 27. 1Remove these Revision 35 pages Insert these Revision 36 pages1-33 1-24Revision LogEffective Pages Pages Pages Total EffectiveRevision Date Revised Added Deleted Pages1Oconee 3 Cycle 28 revisions below I36 Apr 2014 1-24 25-33 24Oconee 3 Cycle 27 revisions below35 Apr 2014 1-33 3334 Apr 2013 1-33 -3333 Oct 2012 1-33 -3332 May 2012 1-33 -33I conee 3 Cycle 26 revisions below31 Oct 2010 1-33 -33Oconee 3 Cycle 25 revisions below30 May 2009 1-33 3329 May 2009 1-33 3328 Apr2009 1-33 33Oconee 3 Cycle 24 revisions below27 Mar 2009 1 -33 3326 Nov 2007 1-33 3325 Nov 2007 1-33 33FOconee 3 Cycle 23 revisions below J24 May 2006 1-33 -33Oconee 3 Cycle 22 revisions below2223 No Mar ar20202006 1 -4, 6, 151 -" 16.33 21, 27, 31 -3333322 Mar 2005 1-5 -3321 Nov 2004 1-33 -33 ONEI-0400-70 Rev 36Page 4 of 24Oconee 3 Cycle 28Table Of ContentsSection 1.0Error Adlusted Core Operatina Limits..... m m mmNRC ApprovedMethodologyTS Number Technical Specification Reference X COLR Parameter2.1.1 Safety Limits 1, 2. 3,4, 5, Maximum Allowed RPS Power6, 7, 8, 9,10 Imbalance Limits3.1.1 Shutdown Margin (SDM) 1, 3, 7 ,8 Shutdown Margin3.1.3 Moderator Temperature Coefficient (MTC) 1, 3, 7 MTC3.1.4 Control Rod Group Alignment Limits 1, 3, 7, 8 Misaligned, Dropped, or Inoperable3.1.5 Safety Rod Position Limits 1.3, 4, 5, 7, 8, 9, 10 Misaligned, Dropped, or Inoperable3.2.1 Regulating Rod Position Limits 1, 3,4, 5, 7, 8, 9, 10 Withdrawal Sequence and Overlap4-pump No Inoperable Rod CRPosition Setpoints3-pump No Inoperable Rod CRPosition Setpoints3.2.2 Axial Power Imbalance Operating Limits 1.2, 3, 4, 5, 4-pump Operational Power7, 8, 9, 10 Imbalance Setpoints3-pump Operational PowerImbalance Setpoints3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 QPT Setpoints3.3.1 Reactor Protective System (RPS) 1,2, 3,4, 5, Correlation SlopeInstrumentation 6, 7, 8, 9, 10 Variable Low RCS PressureRPS SetpointsMaximum Allowed RPS PowerImbalance Limits4-pump RPS PowerImbalance Setpoints3-pump RPS PowerImbalance Setpoints3.4.1 RCS Pressure, Temperature, and Flow 4, 5, 7, 8 RCS Pressure, Temperature,Departure from Nucleate Boiling Limits and Flow3.5.1 Core Flood Tanks (CFTs) 1, 3, 7,8 Boron Concentration3.5.4 Borated Water Storage Tank (BWST) 1, 3, 7,8 Boron Concentration3.1.12 Spent Fuel Pool Boron Concentration 1, 3, 7 ,8 Boron Concentration3.9.1 Boron Concentration (RCS and 1, 3, 7,8 Boron ConcentrationRefueling Canal)5.6.5 Core Operating Limits Report (COLR) None ReferencesNRC ApprovedMethodologySLC Number Reference # COLR Parameter16.5.13 High Pressure Injection and Chemical 1, 3, 7,8 Volume and Boron ConcentrationAddition Systems of Concentrated Boric AcidStorage Tank (CBAST)Section 2.0 Core Operatina Limits -Not Error Adlusted (NOT FOR PLANT USE)NRC ApprovedMethodologyTS Number Technical Specification Reference # COLR Parameter2.1.1 Safety Limits 1, 2, 3,4, 5, Variable Low RCS Pressure6, 7, 8, 9,10 Protective LimitsAxial Power ImbalanceProtective Limits3.2.1 Regulating Rod Position Limits 1, 3, 4, 5, 7, 8, 9, 10 Rod Index Limits3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 Quadrant Power Tilt Limits ONEI-0400-70 Rev 36Page 5 of 24Oconee 3 Cycle 281.0 Error Adjusted Core Operating LimitsThe Core Operating Limits Report for 03C28 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 11. The RPS protective limits and maximum allowablesetpoints are documented in References 12 through 14. These limits are validated for use in 03C28 byReferences 15 through 17. The 03C28 analyses assume a design flow of 108.5% of 88,000 gpm per RCSpump, radial local peaking (Fth) 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 5690F.The error adjusted core operating limits included in Section 1 of the report incorporate all necessaryuncertainties and margins required for operation of the 03C28 reload core.1.1 References1. Oconee Nuclear Design Methodology Using CASMO-4 / SIMULATE-3, DPC-NE-1006-PA,SE dated August 2, 2011.2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002-A, SE dated July 21, 2011.3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001-A, SE dated July 21, 2011.4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003-PA,SE dated July 21, 2011.5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, SE dated October 29, 2008.6. Fuel Mechanical Reload Analysis Methodology Using TACO3 and GDTACO, DPC-NE-2008-PA,SE dated July 21, 2011.7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, SE dated July 21, 2011.8. Thermal Hydraulic Transient Analysis Methodology, DPC-NE-3000-PA, SE dated July 21, 2011.9. BAW-1 01 92P-A, BWNT LOCA -BWNT Loss of Coolant Accident Evaluation Model forOnce-Through Steam Generator Plants, Revision 0, 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-10227P-A, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel,Rev. 1, June 2003 (SER to BAW-10186P-A dated June 18, 2003).12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low PressureSafety Limit, OSC-4048, Revision 6, September 2010.13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of1.094, OSC-5604, Revision 4, April 2011.14. ATc and EOC Reduced Tavg Operation, OSC-7265, Revision 1, June 2002.15. 03C28 Maneuvering Analysis, OSC-11093, Revision 2, April 2014.16. 03C28 Specific DNB Evaluation, OSC-1 1096, Revision 0, October 2013.17. 03C28 Reload Safety Evaluation, OSC-11123, Revision 0, April 2013.

ONEI-0400-70 Rev 36Page 6 of 24Oconee 3 Cycle 28Miscellaneous SetpointsBWST 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.CFT boron concentration shall be greater than 2300 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 2220 ppm and less than 3000 ppm.Referred to by TS 3.9.1.Shutdown Margin (SDM) shall be greater than 1% Al/k.Referred to by TS 3.1.1.Moderator Temperature Coefficient (MTC) shall be less than: MTC x 10-4Linear interpolation is valid within the table provided. Ap I °F % FPReferred to by TS 3.1.3. +0.70 0+0.525 200.00 800.00 1000.00 120Departure 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: Max Loop Tavg (Incl 20F unc)Referred to by TS 3.4.1. ATc, °F 4 RCP Op 3 RCP Op0 581.0 581.0The measured Tavg must be less than COLR limits minus 1 581.4 581.2instrument uncertainty. ATc is the setpoint value selected by 2 581.8 581.4the operators. 3 582.1 581.74 582.5 581.95 582.9 582.1This 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: 4 RCP: Measured >_ 108.5 %dfReferred to by TS 3.4.1. 3 RCP: Measured > 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-0400-70 Rev 36Page 7 of 24Oconee 3 Cycle 28EFPD0 to 644644 to EOCSteady State Operating BandRod Index APSR %WDMin Max Min Max292 +/-5 300 30 40292 15 300 100 100Core Power Level, %FPFull IncoreOut of CoreBackup IncoreQuadrant Power Tilt SetpointsSteady State Transient0-30 > 30 0-30 > 307.61 3.50 9.40 7.116.09 2.35 7.72 5.633.87 2.25 4.81 3.63Referred to by TS 3.2.3Maximum>016.5514.2210.07Correlation Slope (CS)1.15Referred to by TS 3.3.1 (SR 3.3.1.3).

ONEI-0400-70 Rev 36Page 8 of 24Oconee 3 Cycle 28Variable Low RCS Pressure RPS SetpointsReferred to by TS 3.3.12400P =2355 psig T 6180F23002200co(/L,d 2100 AcceptableVOperationP =11.14 *Tout -470602000Unacceptable1900 OperationP = 1800 psig1800T = 584 °F1700 1 I i540 560 580 600 620 640Reactor Coolant Outlet Temperature, OF ONEI-0400-70 Rev 36Page 9 of 24SOconee 3 Cycle 28Referred to byTS 2.1.1 and TS Table 3.3.1-1Maximum Allowable RPS Power Imbalance Limits% FP % Imbalance4 Pumps 0.0 -35.090.0 -35.0Pmrax => 109.4 -14.4Pmax => 109.4 14A490.0 35.00.0 35.03 Pumps 0.0 -35.062.3 -35.0Pmax => 81.7 -14.4Pmax => 81.7 14.462.3 35.00.0 35.0 ONEI-0400-70 Rev 36Page 10 of 24Oconee 3 Cycle 28Operational Power Imbalance SetpointsReferred to by TS 3.2.2Full Backup Out of%FP Incore Incore Core4 Pumps 0.0 -28.0 -27.5 -27.880.0 -28.0 -27.5 -27.890.0 -28.0 -27.5 -27.8100.0 -17.7 -17.7 -17.7102.0 -15.6 -15.6 -15.6102.0 15.6 11.2 11.8100.0 17.7 14.2 14.790.0 28.0 28.0 28.080.0 28.0 28.0 28.00.0 28.0 28.0 28.03 Pumps 0.0 -28.0 -27.5 -27.863.1 -28.0 -63.3 ---27.863.5 --27.5 -77.0 -13.2 -13.2 -13.277.0 13.2 13.2 13.263.1 -28.0 -63.1 --28.063.1 28.0 --0.0 28.0 28.0 28.0Referred to by TS 3.2.2 ,

ONEI-0400-70 Rev 36Page 11 of 24Oconee 3 Cycle 28RPS / Operational Power Imbalance SetpointsOperation with 4 RCS Pumps, BOC to EOCReferred to byTS 3.2.2 and TS 3.3.1% FP RPS Trip Full Incore Alarm Out of Core Alarm107.9106.0105.0104.0103.0102.0101.0100.099.098.097.096.095.094.093.092.091.090.490.089.088.087.086.085.084.083.082.081.080.00.0-14.4-16.4-17.5-18.5-19.6-20.7-21.7-22.8-23.9-24.9-26.0-27.0-28.1-29.2-30.2-31.3-32.3-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.014.416.417.518.519.620.721.722.823.924.926.027.028.129.230.231.332.333.033.033.033.033.033.033.033.033.033.033.033.033.0-15.6-16.7-17.7-18.7-19.8-20.8-21.8-22.9-23.9-24.9-25.9-27.0-27.6-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.015.616.717.718.719.820.821.822.923.924.925.927.027.628.028.028.028.028.028.028.028.028.028.028.028.0-15.6-16.7-17.7-18.7-19.7-20.7-21.7-22.8-23.8-24.8-25.8-26.8-27.4-27.8-27.8-27.8-27.8-27.8-27.8-27.8-27.8-27.8-27.8-27.8-27.811.813.314.716.017.418.720.021.422.724.025.326.727.528.028.028.028.028.028.028.028.028.028.028.028.0% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-70 Rev 36Page 12 of 24Oconee 3 Cycle 28RPS I Operational Power Imbalance SetpointsOperation with 3 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FP RPS Trip Full Incore Alarm Out of Core Alarm80.680.079.078.077.076.075.074.073.072.071.070.069.068.067.066.065.064.063.363.163.062.061.060.00.0-14.4-15.0-16.1-17.1-18.2-19.3-20.3-21.4-22.4-23.5-24.6-25.6-26.7-27.8-28.8-29.9-30.9-32.0-32.8-33.0-33.0-33.0-33.0-33.0-33.014.415.016.117.118.219.320.321.422.423.524.625.626.727.828.829.930.932.032.833.033.033.033.033.033.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-27.0-27.8-28.0-28.0-28.0-28.0-28.0-28.013.214.315.316.417.418.519.620.621.722.823.824.925.927.027.828.028.028.028.028.028.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-27.0-27.8-27.8-27.8-27.8-27.8-27.8-27.813.214.315.316.417.418.519.620.621.722.823.824.925.927.027.828.028.028.028.028.028.0% FP I RPS Trip Full Incore Alarm I Out of Core Alarm :

ONEI-0400-70 Rev 36Page 13 of 24Oconee 3 Cycle 28RPS Power Imbalance SetpointsReferred to by TS 3.3.1 and TS Table 3.3.1-1Thermal Power Level, %FP120.0(-14.4,107.9)M1 = 0.942(14.4,107.9,1100.0Acceptable 4 Pump Operation(-33.0,90.4)(14.4,80.6)(A 4.4,80.6M2 =-0.942(33.0,90.4)I, (33.0,63.1)OU.U(-33.0,63.1)60.0Acceptable 3 or 4 Pump Operation140.020.0L% I , I I-40.0-30.0-20.0-10.0 0.0 10.0Percent Power Imbalance20.0= , L ff30.040.0 Oconee 3 Cycle 28Imbalance Setpoints for 4 Pump Operation, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1-14.4, 107.9144.107.9ONEI-0400-70 Rev 36Page 14 of 2411010090RP ri ýp Seipoint'wr I a I T I I -I IRPS Trip Setpoint102.0--17.7. 100.O E Eii2AQ20M-33.0, 90.414.2. 100.0 -liii 0.iiILZi-27.5,90.0-27.5. 80.028.0. 9.8028.0.80.01700a. 60U-u.4504)n40Labels Correspond to the Backup Incore Alar StpontsBackup Incom--, Outcore-incoreRPS Trip302010-ý3390-oo-27.5, 0.028.0.0.033.0, 0.00II*E i*U-~Minkno-6 M --40 30 20 10 -5 0 5Percent Axial Imbalance10 15 20 25 30 35 40 Oconee 3 Cycle 28Imbalance Setpoints for 3 Pump Operation, BOC to EOCONE'40-70 Rev 36Referred to by TS 3.2.2 and TS 3.3.1 Page 15 of 241101009014.4, 80.6-0.0.LL.0CDQ.8070605040302010-RPS Trip Setpoint I_ -132;77.0.13 77.0t-33.0. 63.1; RPS Trip Setpoint ýý.1I1-27.5, 63.128.0.63.1ibels Correspond to the Backup Incore Alarm Setpoints-a-Backup Iiicore-Incore-oRPS TripI-33.0, 0.0I-27.5, 0.028.0. 0.0 :-33.0,0.0 -T-:I0-40 30 20 10 -5 0 5Percent Axial Imbalance10 15 20 25 30 35 40 ONEI-0400-70 Rev 36Page 16 of 24Oconee 3 Cycle 28Operational Rod Index SetpointsReferred to by TS 3.2.14 Pumps3 Pumps%FP102.0100.090.080.050.048.015.013.05.03.02.80.077.075.050.048.015.013.05.03.02.80.0RI Insertion SetpointNo Inop Rod 1 Inop Rod263.5 283.4261.5 281.5251.5 271.9241.5 262.3201.5 233.4195.2 231.591.5 165.576.5 161.516.5 93.51.5 76.50.0 74.80.0 51.0RI WithdrawalSetpoint300300300300300300300300300300300300300300300300300300300300300300237.5234.8201.5195.291.576.516.51.50.00.0285.2281.5235.2231.5165.5161.593.576.574.851.0 ONEI-0400-70 Rev 36Page 17 of 24Oconee 3 Cycle 28Shutdown Margin Rod Index Setpoints4 Pumps3 Pumps%FP102.0100.048.013.03.02.80.077.075.048.013.03.02.80.0Referred to by TS 3.2.1RI Insertion SetpointNo Inop Rod 1 Inop Rod224.6 283.4221.5 281.5141.5 231.576.5 161.51.5 76.50.0 74.80.0 51.0RI WithdrawalSetpoint300300300300300300300300300300300300300300227.4221.5141.576.51.50.00.0285.2281.5231.5161.576.574.851.0 I Oconee 3 Cycle 28 1ONEI-0400-70 Rev 36Page 18 of 24Referred to by TS 3.2.1(LU-L:0LL.I-(Dw10510095908580757065605550454035302520151050HI il lit 224.6, 102.0 263.5, 102.0 .300.0,10.Control Rod Position Setpoints s r: 221.5,100.0.......No Inoperable Rods, 4 Pump Flow, ..10...oBOC to EOCMilI1 ,251.5,.90.0loo oll",241.5. 80.0.1 :175.0. 69.8 1 1 i..Operation RestrictedOperationOeraio48.02 48.0125.0, 39.1 175.0,.41.60.0 ,... ...8 .... ... ....u.15 2 5 .. .. ..... 5 5 .. 7 5 ... ..:12 5 ., .. .......r105100959085807570656055504540353025201510590 "..V' 20 30 40 50 60 70 8090 100o110 10 20 30 40 50 60 70 80 90 1001I Group 5 1Control Rod Position, % WDI Grup I ontrl Rd Psitin, WDGroup 7 I Oconee 3 Cycle 28 1Referred to by TS 3.2.1ONEI-0400-70 Rev 36Page 19 of 241051009590858075IUControl Rod Position SetpointsNo Inoperable Rods, 3 Pump Flow,I BOC to EOC227.4, 77.4225.0.47.1.5. 75.0237.5. 77.0234~8. 75.0Ja-00ccc706560555045403530252015105225.0.67.6UnacceptableOperation105100959085, 77.o 80757065605550454035302520175.0. 59.3I141.5.48.RestrictedOperation1111201.5. 50.0195.2,.48.0175.0,41.6125.0.AcceptableOoerationI125.0,25.7If..' .' " ....1.5, 1 3 *.... 16.5. 5.07 .5,13.0 ..........WNW75.0,12.8...........roup 6MZ5 ::'l 5 25 35 45 55 65 75 85 951510UII50!010 10 20 30 40 50 60 70 80 90100110 1020 30 40 50 60 70 80 90 1001I* l0.0,.0.0I Group 5Control Rod Position, % WDI Group 7j.

0II Oconee 3 Cycle 28IReferred to byTS 3.2.1ONEI-0400-70 Rev 36Page 20 of 241010988776a.m 4322111300.0 102.0 10!......... .... 2 3.4 102.0'0 Control Rod Position Setpoints 2-1.5 .105 1 Inoperable Rod, 4 Pump Flow, 95BOC to EOC........0 905 85-0 80.'5 75'0 7015 6535 ~Unacceptable 610 Operation 6055 55*10 50SO I 231.5, 48.0 Acceptable 5~Operation225.044.8 ..... 45I0 4015 35.0 305 25lailillillini181.5 1113.01111105.0, 205 74., 150 .65 .0 .. ..f.i .10.82 551.o,5o 15 25 30 65 75 85O [i l ii t ' ii i n ..... .... ..., .... ..'. ... .... ...... .. ...... ............. 05-10 10 20 30 40 50 60 70 80 90 1001 0 10 20 30 40 50 60 70 80 90 100 1SIGroup 5 rumIControl Rod Position, % WDroup "7 II Oconee 3 Cycle 28IReferred to byTS 3.2.1ONEI-0400-70 Rev 36Panp 91 nf 2410510095908580757065a.UL605550C 4540105100IControl Rod Position SetpointsI Inoperable Rod, 3 Pump Flow,BOC to EOCSI I I I IN r= 300.0. 77.0285.2, 77.0 tJ I11111 1 i 1 J 11 +HI24I444f1m281.55,75.0-UnacceptableOperation2315 48.0959085807570656055504540353025201510:zr ~ raw22.U.44.8 5AcceptableOperationI3530252015105n175.0,113.0125.0,8.776.5. 3.075.0,2.8251.00.0 1HH _U111111 11'194 Group 625 35 45 5565 7585 95r5-010 10 20 30 40 50 60 70 80 90 1001 0 10 20 30 40 50 60 70 80 90 100 II Group 5 1Control Rod Position, % WDI Group 71 ONEI-0400-70 Rev 36Page 22 of 24Oconee 3 Cycle 282.0 Core Operating Limits -Not Error AdjustedThe data provided on the following pages satisfies a licensing commitment to identify specificparameters before instrumentation uncertainties are incorporated.References provided in section 1 of this COLR identify the sources for the data which follows.Quadrant Power Tilt LimitsReferred to by TS 3.2.3Steady StateTransientMaximumCore Power Level, %FPQuadrant Power Tilt, %0 -3010.00> 305.400-3012.00> 309.44>020.00Variable Low RCS Pressure Protective LimitsReferred to by TS 2.1.1Core Outlet Pressurepsla180019002000210022002300Reactor Coolant Outlet Temperature, OF3 RCS Pumps 4 RCS Pumps581.0590.0598.9607.9616.9625.9578.3587.3596.3605.2614.2623.2 ONEI-0400-70 Rev 36Page 23 of 24Oconee 3 Cycle 28Axial Power Imbalance Protective LimitsReferred to by TS 2.1.14 Pumps3 Pumps%FP0.080.090.0100.0109.4109.4100.090.080.00.00.062.377.081.781.777.062.30.0RPS Operational-35.0-35.0-14.414.435.035.0-35.0-35.0-14.414.435.035.0-39.3-39.3-39.3-28.424.739.539.539.5-39.3-39.339.539.5 ONEI-0400-70 Rev 36Page 24 of 24Oconee 3 Cycle 28Rod Index LimitsReferred to by TS 3.2.1I' ~Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal%FP Insertion Limit No Inop Rod I Inop Rod Limit4 Pumps3 Pumps10210090805015526226025024020090022014075022014075028023016075280230160753003003003003003003003003003003007750155236200900