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#REDIRECT [[ONS-2015-111, Oconee, Unit 2 - Core Operating Limits Report, Cycle 28, ONEI-0400-450, Revision 00]]
| number = ML15310A043
| issue date = 10/30/2015
| title = Oconee, Unit 2 - Core Operating Limits Report, Cycle 28, ONEI-0400-450, Revision 00
| author name = Batson S L
| author affiliation = Duke Energy Carolinas, LLC
| addressee name =
| addressee affiliation = NRC/Document Control Desk, NRC/NRR
| docket = 05000270
| license number =
| contact person =
| case reference number = ONS-2015-111
| document report number = ONEI-0400-450, Rev. 00
| document type = Fuel Cycle Reload Report, Letter
| page count = 27
}}
 
=Text=
{{#Wiki_filter:~ENERGYScott L. BatsonVice President Oconee Nuclear StationDuke EnergyONOIVP I 7800 Rochester HwySeneca, SC 29672os 864.873.3274 fi 864.873.
4208Scott. Batson@duke-energy.cam ONS-201 5-111October 30, 2015U. S. Nuclear Regulatory Commission Document Control DeskWashington, D. C. 20555-0001
 
==Subject:==
Duke Energy Carolinas, LLCOconee Nuclear Site Docket Number 50-270Core Operating Limits Report (COLR)Attached, pursuant to Oconee Technical Specification 5.6.5.d, is an information copy ofthe Core Operating Limits Report (COLR) for Oconee Unit 2, Cycle 28, ONEI-0400-450, Revision 00.If you have any questions, please direct them to Judy Smith at 864-873-4309.
Sincerely, Scott L. BatsonVice President Oconee Nuclear StationAttachment H Y-www.duke-energy.com U. S. Nuclear Regulatory Commission October 30, 2015Page 2bc w/att: Mr. Leonard D. Wert, Jr.Administrator, Region II (Acting)U.S. Nuclear Regulatory Commission Marquis One Tower245 Peachtree Center Ave., NE, Suite 1200Atlanta, GA 30303-1257 Mr. James R. Hall(By electronic mail only)U.S. Nuclear Regulatory Commission One White Flint North, M/S O-8B111555 Rockville PikeRockville, MD 20852-2746 Mr. Eddy CroweSenior Resident Inspector Oconee Nuclear Site
~ENERGYFacility Code : ONApplicable Facilities
: ONDocument Number : ON EI-0400-450 Document Revision Number : 000Document EC Number :Change Reason : NO reason given per RR StClairDocument Title : OCONEE 2 CYCLE 28 CORE OPERATING LIMITS REPORTLang, Amanda L. Originator 9/24/2015
: Forster, Joy D Verifier 9/24/2015 Reed, James Cross Disciplinary Review 9/24/2015 St Clair, Robert R Approver 9/24/2015 Notes :
ONEI-0400-450 Rev 0Page 1 of 24Duke EnergyOconee 2 Cycle 28Core Operating Limits ReportQA Condition 1Prepared By: A.L. Lang / Signed Electronically Reviewed By: J.D. Forster/ISigned Electronically Date:Date:CDR By: J. A. Reed I Signed Electronically Date:Approved By: R.R. St.Clair
/Signed ElectronicallyDae Date:
ONEI-0400-450 Rev 0Page 2 of 24Engineering Instruction Inspection Waiver:This El Inspection has been waived by OS-105.00.
ONEI-0400-450 Rev 0Page 3 of 24Oconee 2 Cycle 28Core Operating Limits ReportInsertion Sheet for Revision 0Effective Revision DateRevision LogPagesRevisedPages Pages Total Effective Added Deleted PageslOconee2 Cycle 28 revisions belOwsp211-244 ONEI-0400-450 Rev 0Page 4 of 24Oconee 2 Cycle 28Table Of ContentsSection 1.0 Error Adiusted Core Operating LimitsNRC ApprovedMethodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Maximum Allowed RPS Power6, 7, 8, 9, 10 Imbalance Limits3.1.1 Shutdown Marg]in (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 Misaliglned,
: Dropped, or Inoperable 3.1.5 Safety Rod Position Limits 1 ,3, 4, 5, 7, 8, 9, 10 Misaligned,
: Dropped, or Inoperable 3.2.1 Regulating Rod Position Limits 1, 3, 4, 5, 7, 8, 9, 10 Withdrawal Sequence and Overlap4-pump No Inoperable Rod CRPosition Setpoints 3-pump No Inoperable Rod CRPosition Setpoints 3.2.2 Axial Power Imbalance Operating Limits 1, 2, 3, 4, 5, 4-pump Operational Power7, 8, 9, 10 Imbalance Setpoints 3-pump Operational PowerImbalance Setpoints 3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 QPT Setpoints 3.3.1 Reactor Protective System (RPS) 1, 2, 3, 4, 5, Correlation SlopeInstrumentation 6, 7, 8, 9, 10 Variable Low RCS PressureRPS Setpoints Maximum Allowed RPS PowerImbalance Limits4-pump RPS PowerImbalance Setpoints 3-pump RPS PowerImbalance Setpoints 3.4.1 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 Concentration 3.5.4 Borated Water Storage Tank (BWST) 1, 3, 7,8 Boron Concentration 3.7.12 Spent Fuel Pool Boron Concentration 1, 3, 7 ,8 Boron Concentration 3.9.1 Boron Concentration (RCS and 1, 3, 7 ,8 Boron Concentration Refueling Canal)5.6.5 Core Operating Limits Report (COLR) None References NRC ApprovedMethodology SLC Number Reference
# COLR Parameter 16.5.13 High Pressure Injection and Chemical 1, 3, 7 ,8 Volume and Boron Concentration Addition Systems of Concentrated Boric AcidStorage Tank (CBAST)Section 2.0 Core Operating Limits -Not Error Adiusted (NOT FOR PLANT USE)NRC ApprovedMethodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Variable Low RCS Pressure6, 7, 8, 9, 10 Protective LimitsAxial Power Imbalance Protective Limits3.2.1 Reglulatingl 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-0400-450 Rev 0Page 5 of 24Oconee 2 Cycle 281.0 Error Adjusted Core Operating LimitsThe Core Operating Limits Report for 02028 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 I through 11. The RPS protective limits and maximum allowable setpoints are documented in References 12 through 14. These limits are validated for use in O2C28 byReferences 15 through 17. The O2C28 analyses assume a design flow of 108.5% of 88,000 gpm per RCSpump, radial local peaking (FAh) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB)Tavg reduction for up to 1 0&deg;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 necessary uncertainties and margins required for operation of the 02028 reload core.1.1 References
: 1. Oconee Nuclear Design Methodology Using CASMO-4 I SIMULATE-3, DPC-NE-1 006-PA,-SE dated August 2, 2011.2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002-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-10192P-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-1 0227P-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. 02028 Maneuvering
: Analysis, OSC-11319, Revision 2, September 2015.16. O2C28 Specific DNB Evaluation, OSC-11450, Revision 0, May 2015.17. 02C28 Reload Safety Evaluation, 0SC-1 1465, Revision 0, September 2015.
ONEI-0400-450 Rev 0Page 6 of 24Oconee 2 Cycle 28Miscellaneous Setpoints BWST boron concentration shahi be greater than 2500 ppm and iess 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% Ak/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 / 0F % 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 ioop average temperature shall be: Max Loop Tavg (Incl 2&deg;F unc)Referred to by TS 3.4.1. ATc, &deg;F 4 RCP Op 3 RCP Op0 581.0 581.0 *The 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.
3 582.1 581.74 582.5 581.95 582.9 582.1* This limit is applied to the loop with the lowest ioop average temperature consistent withthe NOTE in SR 3.4.1.2.
All other temperature limits apply to the maximum ioop T'avg.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% :t 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 calculations when 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-0400-450 Rev 0Page 7 of 24Oconee 2 Cycle 28EFPD0 to 646646 to EOCCore Power Level, %FPFull IncoreOut of CoreBackup IncoreSteady State Operating BandRod Index APSR %WDMin Max Min Max292+/-+5 300 30 40292 +/-5 300 100 100Quadrant Power Tilt Setpoints Steady State Transient 0 -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-0400-450 Rev 0Page 8 of 24Oconee 2 Cycle 28Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.12400P = 2355 psigT = 618 0F2300220009a2100 Acceptable cnOperation 0)_P = 11.14" Tout-4700 2000/ Unacceptable 1900 /Operation P = 1800 psig1800T = 584 0F1700 I I I540 560 580 600 620 640Reactor Coolant Outlet Temperature, 0F ONEI-0400-450 Rev 0Page 9 of 24Oconee 2 Cycle 28Referred to by TS 2.1.1 and TS Table 3.3.1-1Maximum Allowable RPS Power Imbalance Limits% FP % Imbalance 4 Pumps 0.0 -35.090.0 -35.0Pmax => 109.4 -14.4Pma.x=> 109.4 14.490.0 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 ONE1-0400-450 Rev 0Page 10 of 24Oconee 2 Cycle 28Operational Power Imbalance Setpoints Referred to by TS 3.2.2Full Backup Out of%FP Incore Incore Core4 Pumps 0.0 -28.0 -25.9 -26.480.0 -28.0 -25.9 -26.490.0 -28.0 -21.5 -21.9100.0 -17.7 -15.9 -16.2102.0 -15.6 -14.8 -15.1102.0 15.6 11.7 12.1100.0 17.7 13.5 13.990.0 28.0 22.4 22.780.0 28.0 27.5 28.00.0 28.0 27.5 28.03 Pumps 0.0 -28.0 -25.9 -26.463.1 -28.0 --64.6 -- -26.465.0 --25.9 -77.0 -13.2 -13.2 -13.277.0 13.2 13.2 13.263.5 -27.5 -63.1 28.0 -28.00.0 28.0 27.5 28.0Referred to by TS 3.2.2 ONEI-0400-450 Rev 0Page 11 of 24Oconee 2 Cycle 28RPS / Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FP RPS Trip ] Full Incore Alarm J 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 .231.332.333.033.033.033.033.033.033.033.033.033.033.033.033.0-15.6-16.7-17.7-18.7-19.8-20.8-21.8-22.9-23.9-24.9-25.9-27.0-27.6-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.015.616.717.718.719.820.821.822.923.924.925.927.027.628.028.028.028.028.028.028.028.028.028.028.0-15.1-15.7-16.2-16.8-17.3-17.9-18.5-19.1-19.6-20.2-20.8-21.3-21.7-21.9-22.4-22.8-23.3-23.7-24.2-24.6-25.1-25.5-26.0-26.4-26.412.113.013.914.815.716.517.418.319.220.120.921.822.422.723.223.824.324.825.425.926.426.927.528.028.028.0% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-450 Rev 0Page 12 of 24Oconee 2 Cycle 28RPS / Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FP j RPS Trip Full Incore Alarm [Out of Core Alarm80.680.079.078.077.076.075.074.073.072.071.070.069.068.067.066.065.064.664.063.163.062.061.060.00.0-14.4-15.0-16.1-17.1-18.2-19.3-20.3-21.4-22.4-23.5-24.6-25.6-26.7-27.8-28.8-29.9-30.9-31.4-32.0-33.0-33.0-33.0-33.0-33.0-33.014.415.016.117.118.219.320.321.422.423.524.625.626.727.828.829.930.931.432.033.033.033.033.033.033.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-27.0-28.0-28.0-28.0-28.0-28.0-28.013.214.315.316.417.418.519.620.621.722.823.824.925.926.427.028.028.028.028.028.028.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-26.4-26.4-26.4-26.4-26.4-26.4-26.413.214.315.316.417.418.519.620.621.722.823.824.925.926.427.028.028.028.028.028.028.0% FP J RPS Trip j Full Incore Alarm jOut of Core Alarm ONEI-0400-450 Rev 0Page 13 of 24Oconee 2 Cycle 28RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1Thermal Power Level, %FP120.0-M1 0.942(14.4,107.91)
;. " " X,=100.0-Acceptable 4 Pump Operation
(-33.0,90.4)
(14.4,80.6)
(-14.4,80.6)
M2 = -0.942(33.0,90.4)
(33.0,63.1)
.- .. 4..OUl U(-33.0,63.1)
-40.060.0-Acceptable 3 or 4 Pump Operation 40.0-20.0--30.0-20.0-10.0 0.0 10.0Percent Power Imbalance 20.030.0b40.0 Oconee 2 Cycle 28Imbalance Setpoints for 4 Pump Operation, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1ONEI-0400-450 Rev 0Page 14 of 241101009080700 6a- 600502O1014.4, 107.90-40 30 20 10 -50 5 10 15 20 25 30 35 40Percent Axial Imbalance Oconee 2 Cycle 28Imbalance Setpoints for 3 Pump Operation, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1ONEI-0400-450 Rev 0Page 15 of 24o)0.a-P-'4-110100908070605040302010.. .,44.O.6 -!- I !i -L- t- i-IRPS TriP 13.2, 77.0Trip setpoint 33.0,63.1-IIt7 -25.9, 65.0* = -I-T-I-27.5, 63.5-Labels Correspond to the Backup Incore Alarm-,,e--Backup Incore :Outcore---II-- RPS Trip !t--i7-4-25.9, 27.5, 0.033.0, 0.0J-~ i~-40-35-30-25-20-15-10 -5 0 5Percent Axial Imbalance 10 15202530 35 40 ONEI-0400-450 Rev 0Page 16 of 24Oconee 2 Cycle 28Operational Rod Index Setpoints Referred 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 Withdrawal Setpoint300300300300300300300300300300300300300300300300300300300300300300237.5234.8201.5195.291.576.516.51.50.00.0285.2281.5235.2231.5165.5161.593.576.574.851.0 ONEI-0400-450 Rev 0Page 17 of 24Oconee 2 Cycle 28Shutdown Margin Rod Index Setpoints 4 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 Withdrawal Setpoint300300300300300300300300300300300300300300227.4221.5141.576.51.50.00.0285.2281.5231.5161.576.574.851.0 SOconee 2 Cycle 280NE1-0400-450 Rev 0Page 18 of 24Referred to by TS 3.2.1LILO0.0Y1051009590858075706560555045403530252015105ol0.260.05,1502235 45 55.65 5185.9F10510095908580757065605550454035302520151050rm0 10 20 30 40 50 60 70 80 90100ol10 10 20 30 40 50 60 70 80 90 1001I,Group 5 Control Rod Position,
% WD Group 7IControl Rod Position,
% WDI Group 7J J SOconee 2 Cycle 28Referred to by TS 3.2.10NE1-0400-450 Rev 0Page 19 of 240a-rY1051009590858075706560555045403530252015SControl Rod Position Setpoints No Inoperable Rods, 3 Pump Flow,BOO to EOCH221.5, 75.0237.5, 77.0_LU234.8, 75.0Unacceptable Operation S175.0, 59.w105100i195.2, 48.0141.5, 48.757065755504540355302520151025Restricted Operation 125.0,_ 39.1175.0, 41.Acceptable Operation 125.0, 25.7176.5,1,3191.5,1S0 10 20 30 40 50 610.0, 0.0Gru 575.0, 12.80 70 80 9025100C354]5 6Control Rod Position,
% 75 85 95 (J0O 10 20 30 40 50 60 70 80 90 100]'VD I Group 710 I II Oconee 2 Cycle 28IReferred to by TS 3.2.1ONEI-0400-450 Rev 0Page 20 of 2410(9,9(8,8(7,7(6,a-.414,3(32215 f300 0.0 ~~~Control Rod Position Setpoints21.,00 5 1 Inoperable Rod, 4 Pump Flow,050505 Unacceptable 0215480 Acceptable 50505050,551oo0!5 15 25 35 45 55 65 75 85 951051009590858075706560555045403530252015105010 10 20 30 40 50 60 70 80 90 100 IS0 10 20 30 40 50 60 70 80 90 100L Group 5 JGroup 5 I ~Control Rod Position,
% WD Gru7I Group 7 J
..I Oconee 2 Cycle 28IReferred to byTIS 3.2.1ONEI-0400-450 Rev 0Paoe 21 of 2410.1LLU)o0.00Y10510095908580757065605550454035302520151050ontrol Rod Position Setpoints 1 Inoperable Rod, 3 Pump Flow,BOC to EOC285.2, 77.0In Em ui Ilium="300.0,7 281.5. 75.0Operation 2231.0, 4.8,1051009590851757065605550454035Acceptable Operation 30175.0, 19.8161.5,13.0 H-",R &#xa3; 125.0, 8.725201510501.-750 '282lilt ~ ~ Ft-IT~&#xb6;T1fInmT I51-00 &deg;015 25 35 45 5565 75 85 95U0 O 10 20 o3 40 50 60 70 80 90 101 0 10 20 30 40 50 60 70 80 90 1001I1I Group 5 IControl Rod Position,
% WDI ru onrlRdPsiin DGroup 7I ONEI-0400-450 Rev 0Page 22 of 24Oconee 2 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.Core Power Level,Quadrant Power TiCore OutiF112222%FP Cilt, % 1Quad rant Power Tilt LimitsReferred to by TS 3.2.3Steady State T)3- 30 > 30 0 -3010.00 5.40 12.00"ransient
>309.44Maximum>020.00Variable Low RCS Pressure Protective LimitsReferred to by TS 2.1.1let Pressure Reactor Coolant Outlet Temperature, 0F3sia 3 RCS Pumps 4 RCS Pumps800 581.0 578.3900 590.0 587.3000 598.9 596.3100 607.9 605.2200 616.9 614.2300 625.9 623.2 ONEI-0400-450 Rev 0Page 23 of 24Oconee 2 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
-35.0-35.0-14.414.435.035.0-35.0-35.0-1.-14.435.035.0-37.6-37.6-32.8-26.523.733.839.539.5-37.6-37.639.39.5 ONEI-0400-450 Rev 0Page 24 of 24Oconee 2 Cycle 28Rod Index LimitsReferred to by TS 3.2.1Operational RI Shutdown Margin RI Insertion Limit%FP Insertion Limit No Inop Rod 1 Inop Rod4 Pumps3 Pumps10210090805015577501552622602502402009002362009002201407502201407502802301607528023016075RI Withdrawal Limit300300300300300300300300300300300
~ENERGYScott L. BatsonVice President Oconee Nuclear StationDuke EnergyONOIVP I 7800 Rochester HwySeneca, SC 29672os 864.873.3274 fi 864.873.
4208Scott. Batson@duke-energy.cam ONS-201 5-111October 30, 2015U. S. Nuclear Regulatory Commission Document Control DeskWashington, D. C. 20555-0001
 
==Subject:==
Duke Energy Carolinas, LLCOconee Nuclear Site Docket Number 50-270Core Operating Limits Report (COLR)Attached, pursuant to Oconee Technical Specification 5.6.5.d, is an information copy ofthe Core Operating Limits Report (COLR) for Oconee Unit 2, Cycle 28, ONEI-0400-450, Revision 00.If you have any questions, please direct them to Judy Smith at 864-873-4309.
Sincerely, Scott L. BatsonVice President Oconee Nuclear StationAttachment H Y-www.duke-energy.com U. S. Nuclear Regulatory Commission October 30, 2015Page 2bc w/att: Mr. Leonard D. Wert, Jr.Administrator, Region II (Acting)U.S. Nuclear Regulatory Commission Marquis One Tower245 Peachtree Center Ave., NE, Suite 1200Atlanta, GA 30303-1257 Mr. James R. Hall(By electronic mail only)U.S. Nuclear Regulatory Commission One White Flint North, M/S O-8B111555 Rockville PikeRockville, MD 20852-2746 Mr. Eddy CroweSenior Resident Inspector Oconee Nuclear Site
~ENERGYFacility Code : ONApplicable Facilities
: ONDocument Number : ON EI-0400-450 Document Revision Number : 000Document EC Number :Change Reason : NO reason given per RR StClairDocument Title : OCONEE 2 CYCLE 28 CORE OPERATING LIMITS REPORTLang, Amanda L. Originator 9/24/2015
: Forster, Joy D Verifier 9/24/2015 Reed, James Cross Disciplinary Review 9/24/2015 St Clair, Robert R Approver 9/24/2015 Notes :
ONEI-0400-450 Rev 0Page 1 of 24Duke EnergyOconee 2 Cycle 28Core Operating Limits ReportQA Condition 1Prepared By: A.L. Lang / Signed Electronically Reviewed By: J.D. Forster/ISigned Electronically Date:Date:CDR By: J. A. Reed I Signed Electronically Date:Approved By: R.R. St.Clair
/Signed ElectronicallyDae Date:
ONEI-0400-450 Rev 0Page 2 of 24Engineering Instruction Inspection Waiver:This El Inspection has been waived by OS-105.00.
ONEI-0400-450 Rev 0Page 3 of 24Oconee 2 Cycle 28Core Operating Limits ReportInsertion Sheet for Revision 0Effective Revision DateRevision LogPagesRevisedPages Pages Total Effective Added Deleted PageslOconee2 Cycle 28 revisions belOwsp211-244 ONEI-0400-450 Rev 0Page 4 of 24Oconee 2 Cycle 28Table Of ContentsSection 1.0 Error Adiusted Core Operating LimitsNRC ApprovedMethodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Maximum Allowed RPS Power6, 7, 8, 9, 10 Imbalance Limits3.1.1 Shutdown Marg]in (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 Misaliglned,
: Dropped, or Inoperable 3.1.5 Safety Rod Position Limits 1 ,3, 4, 5, 7, 8, 9, 10 Misaligned,
: Dropped, or Inoperable 3.2.1 Regulating Rod Position Limits 1, 3, 4, 5, 7, 8, 9, 10 Withdrawal Sequence and Overlap4-pump No Inoperable Rod CRPosition Setpoints 3-pump No Inoperable Rod CRPosition Setpoints 3.2.2 Axial Power Imbalance Operating Limits 1, 2, 3, 4, 5, 4-pump Operational Power7, 8, 9, 10 Imbalance Setpoints 3-pump Operational PowerImbalance Setpoints 3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 QPT Setpoints 3.3.1 Reactor Protective System (RPS) 1, 2, 3, 4, 5, Correlation SlopeInstrumentation 6, 7, 8, 9, 10 Variable Low RCS PressureRPS Setpoints Maximum Allowed RPS PowerImbalance Limits4-pump RPS PowerImbalance Setpoints 3-pump RPS PowerImbalance Setpoints 3.4.1 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 Concentration 3.5.4 Borated Water Storage Tank (BWST) 1, 3, 7,8 Boron Concentration 3.7.12 Spent Fuel Pool Boron Concentration 1, 3, 7 ,8 Boron Concentration 3.9.1 Boron Concentration (RCS and 1, 3, 7 ,8 Boron Concentration Refueling Canal)5.6.5 Core Operating Limits Report (COLR) None References NRC ApprovedMethodology SLC Number Reference
# COLR Parameter 16.5.13 High Pressure Injection and Chemical 1, 3, 7 ,8 Volume and Boron Concentration Addition Systems of Concentrated Boric AcidStorage Tank (CBAST)Section 2.0 Core Operating Limits -Not Error Adiusted (NOT FOR PLANT USE)NRC ApprovedMethodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Variable Low RCS Pressure6, 7, 8, 9, 10 Protective LimitsAxial Power Imbalance Protective Limits3.2.1 Reglulatingl 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-0400-450 Rev 0Page 5 of 24Oconee 2 Cycle 281.0 Error Adjusted Core Operating LimitsThe Core Operating Limits Report for 02028 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 I through 11. The RPS protective limits and maximum allowable setpoints are documented in References 12 through 14. These limits are validated for use in O2C28 byReferences 15 through 17. The O2C28 analyses assume a design flow of 108.5% of 88,000 gpm per RCSpump, radial local peaking (FAh) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB)Tavg reduction for up to 1 0&deg;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 necessary uncertainties and margins required for operation of the 02028 reload core.1.1 References
: 1. Oconee Nuclear Design Methodology Using CASMO-4 I SIMULATE-3, DPC-NE-1 006-PA,-SE dated August 2, 2011.2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002-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-10192P-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-1 0227P-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. 02028 Maneuvering
: Analysis, OSC-11319, Revision 2, September 2015.16. O2C28 Specific DNB Evaluation, OSC-11450, Revision 0, May 2015.17. 02C28 Reload Safety Evaluation, 0SC-1 1465, Revision 0, September 2015.
ONEI-0400-450 Rev 0Page 6 of 24Oconee 2 Cycle 28Miscellaneous Setpoints BWST boron concentration shahi be greater than 2500 ppm and iess 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% Ak/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 / 0F % 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 ioop average temperature shall be: Max Loop Tavg (Incl 2&deg;F unc)Referred to by TS 3.4.1. ATc, &deg;F 4 RCP Op 3 RCP Op0 581.0 581.0 *The 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.
3 582.1 581.74 582.5 581.95 582.9 582.1* This limit is applied to the loop with the lowest ioop average temperature consistent withthe NOTE in SR 3.4.1.2.
All other temperature limits apply to the maximum ioop T'avg.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% :t 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 calculations when 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-0400-450 Rev 0Page 7 of 24Oconee 2 Cycle 28EFPD0 to 646646 to EOCCore Power Level, %FPFull IncoreOut of CoreBackup IncoreSteady State Operating BandRod Index APSR %WDMin Max Min Max292+/-+5 300 30 40292 +/-5 300 100 100Quadrant Power Tilt Setpoints Steady State Transient 0 -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-0400-450 Rev 0Page 8 of 24Oconee 2 Cycle 28Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.12400P = 2355 psigT = 618 0F2300220009a2100 Acceptable cnOperation 0)_P = 11.14" Tout-4700 2000/ Unacceptable 1900 /Operation P = 1800 psig1800T = 584 0F1700 I I I540 560 580 600 620 640Reactor Coolant Outlet Temperature, 0F ONEI-0400-450 Rev 0Page 9 of 24Oconee 2 Cycle 28Referred to by TS 2.1.1 and TS Table 3.3.1-1Maximum Allowable RPS Power Imbalance Limits% FP % Imbalance 4 Pumps 0.0 -35.090.0 -35.0Pmax => 109.4 -14.4Pma.x=> 109.4 14.490.0 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 ONE1-0400-450 Rev 0Page 10 of 24Oconee 2 Cycle 28Operational Power Imbalance Setpoints Referred to by TS 3.2.2Full Backup Out of%FP Incore Incore Core4 Pumps 0.0 -28.0 -25.9 -26.480.0 -28.0 -25.9 -26.490.0 -28.0 -21.5 -21.9100.0 -17.7 -15.9 -16.2102.0 -15.6 -14.8 -15.1102.0 15.6 11.7 12.1100.0 17.7 13.5 13.990.0 28.0 22.4 22.780.0 28.0 27.5 28.00.0 28.0 27.5 28.03 Pumps 0.0 -28.0 -25.9 -26.463.1 -28.0 --64.6 -- -26.465.0 --25.9 -77.0 -13.2 -13.2 -13.277.0 13.2 13.2 13.263.5 -27.5 -63.1 28.0 -28.00.0 28.0 27.5 28.0Referred to by TS 3.2.2 ONEI-0400-450 Rev 0Page 11 of 24Oconee 2 Cycle 28RPS / Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FP RPS Trip ] Full Incore Alarm J 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 .231.332.333.033.033.033.033.033.033.033.033.033.033.033.033.0-15.6-16.7-17.7-18.7-19.8-20.8-21.8-22.9-23.9-24.9-25.9-27.0-27.6-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.015.616.717.718.719.820.821.822.923.924.925.927.027.628.028.028.028.028.028.028.028.028.028.028.0-15.1-15.7-16.2-16.8-17.3-17.9-18.5-19.1-19.6-20.2-20.8-21.3-21.7-21.9-22.4-22.8-23.3-23.7-24.2-24.6-25.1-25.5-26.0-26.4-26.412.113.013.914.815.716.517.418.319.220.120.921.822.422.723.223.824.324.825.425.926.426.927.528.028.028.0% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-450 Rev 0Page 12 of 24Oconee 2 Cycle 28RPS / Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1% FP j RPS Trip Full Incore Alarm [Out of Core Alarm80.680.079.078.077.076.075.074.073.072.071.070.069.068.067.066.065.064.664.063.163.062.061.060.00.0-14.4-15.0-16.1-17.1-18.2-19.3-20.3-21.4-22.4-23.5-24.6-25.6-26.7-27.8-28.8-29.9-30.9-31.4-32.0-33.0-33.0-33.0-33.0-33.0-33.014.415.016.117.118.219.320.321.422.423.524.625.626.727.828.829.930.931.432.033.033.033.033.033.033.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-27.0-28.0-28.0-28.0-28.0-28.0-28.013.214.315.316.417.418.519.620.621.722.823.824.925.926.427.028.028.028.028.028.028.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-26.4-26.4-26.4-26.4-26.4-26.4-26.413.214.315.316.417.418.519.620.621.722.823.824.925.926.427.028.028.028.028.028.028.0% FP J RPS Trip j Full Incore Alarm jOut of Core Alarm ONEI-0400-450 Rev 0Page 13 of 24Oconee 2 Cycle 28RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1Thermal Power Level, %FP120.0-M1 0.942(14.4,107.91)
;. " " X,=100.0-Acceptable 4 Pump Operation
(-33.0,90.4)
(14.4,80.6)
(-14.4,80.6)
M2 = -0.942(33.0,90.4)
(33.0,63.1)
.- .. 4..OUl U(-33.0,63.1)
-40.060.0-Acceptable 3 or 4 Pump Operation 40.0-20.0--30.0-20.0-10.0 0.0 10.0Percent Power Imbalance 20.030.0b40.0 Oconee 2 Cycle 28Imbalance Setpoints for 4 Pump Operation, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1ONEI-0400-450 Rev 0Page 14 of 241101009080700 6a- 600502O1014.4, 107.90-40 30 20 10 -50 5 10 15 20 25 30 35 40Percent Axial Imbalance Oconee 2 Cycle 28Imbalance Setpoints for 3 Pump Operation, BOC to EOCReferred to by TS 3.2.2 and TS 3.3.1ONEI-0400-450 Rev 0Page 15 of 24o)0.a-P-'4-110100908070605040302010.. .,44.O.6 -!- I !i -L- t- i-IRPS TriP 13.2, 77.0Trip setpoint 33.0,63.1-IIt7 -25.9, 65.0* = -I-T-I-27.5, 63.5-Labels Correspond to the Backup Incore Alarm-,,e--Backup Incore :Outcore---II-- RPS Trip !t--i7-4-25.9, 27.5, 0.033.0, 0.0J-~ i~-40-35-30-25-20-15-10 -5 0 5Percent Axial Imbalance 10 15202530 35 40 ONEI-0400-450 Rev 0Page 16 of 24Oconee 2 Cycle 28Operational Rod Index Setpoints Referred 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 Withdrawal Setpoint300300300300300300300300300300300300300300300300300300300300300300237.5234.8201.5195.291.576.516.51.50.00.0285.2281.5235.2231.5165.5161.593.576.574.851.0 ONEI-0400-450 Rev 0Page 17 of 24Oconee 2 Cycle 28Shutdown Margin Rod Index Setpoints 4 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 Withdrawal Setpoint300300300300300300300300300300300300300300227.4221.5141.576.51.50.00.0285.2281.5231.5161.576.574.851.0 SOconee 2 Cycle 280NE1-0400-450 Rev 0Page 18 of 24Referred to by TS 3.2.1LILO0.0Y1051009590858075706560555045403530252015105ol0.260.05,1502235 45 55.65 5185.9F10510095908580757065605550454035302520151050rm0 10 20 30 40 50 60 70 80 90100ol10 10 20 30 40 50 60 70 80 90 1001I,Group 5 Control Rod Position,
% WD Group 7IControl Rod Position,
% WDI Group 7J J SOconee 2 Cycle 28Referred to by TS 3.2.10NE1-0400-450 Rev 0Page 19 of 240a-rY1051009590858075706560555045403530252015SControl Rod Position Setpoints No Inoperable Rods, 3 Pump Flow,BOO to EOCH221.5, 75.0237.5, 77.0_LU234.8, 75.0Unacceptable Operation S175.0, 59.w105100i195.2, 48.0141.5, 48.757065755504540355302520151025Restricted Operation 125.0,_ 39.1175.0, 41.Acceptable Operation 125.0, 25.7176.5,1,3191.5,1S0 10 20 30 40 50 610.0, 0.0Gru 575.0, 12.80 70 80 9025100C354]5 6Control Rod Position,
% 75 85 95 (J0O 10 20 30 40 50 60 70 80 90 100]'VD I Group 710 I II Oconee 2 Cycle 28IReferred to by TS 3.2.1ONEI-0400-450 Rev 0Page 20 of 2410(9,9(8,8(7,7(6,a-.414,3(32215 f300 0.0 ~~~Control Rod Position Setpoints21.,00 5 1 Inoperable Rod, 4 Pump Flow,050505 Unacceptable 0215480 Acceptable 50505050,551oo0!5 15 25 35 45 55 65 75 85 951051009590858075706560555045403530252015105010 10 20 30 40 50 60 70 80 90 100 IS0 10 20 30 40 50 60 70 80 90 100L Group 5 JGroup 5 I ~Control Rod Position,
% WD Gru7I Group 7 J
..I Oconee 2 Cycle 28IReferred to byTIS 3.2.1ONEI-0400-450 Rev 0Paoe 21 of 2410.1LLU)o0.00Y10510095908580757065605550454035302520151050ontrol Rod Position Setpoints 1 Inoperable Rod, 3 Pump Flow,BOC to EOC285.2, 77.0In Em ui Ilium="300.0,7 281.5. 75.0Operation 2231.0, 4.8,1051009590851757065605550454035Acceptable Operation 30175.0, 19.8161.5,13.0 H-",R &#xa3; 125.0, 8.725201510501.-750 '282lilt ~ ~ Ft-IT~&#xb6;T1fInmT I51-00 &deg;015 25 35 45 5565 75 85 95U0 O 10 20 o3 40 50 60 70 80 90 101 0 10 20 30 40 50 60 70 80 90 1001I1I Group 5 IControl Rod Position,
% WDI ru onrlRdPsiin DGroup 7I ONEI-0400-450 Rev 0Page 22 of 24Oconee 2 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.Core Power Level,Quadrant Power TiCore OutiF112222%FP Cilt, % 1Quad rant Power Tilt LimitsReferred to by TS 3.2.3Steady State T)3- 30 > 30 0 -3010.00 5.40 12.00"ransient
>309.44Maximum>020.00Variable Low RCS Pressure Protective LimitsReferred to by TS 2.1.1let Pressure Reactor Coolant Outlet Temperature, 0F3sia 3 RCS Pumps 4 RCS Pumps800 581.0 578.3900 590.0 587.3000 598.9 596.3100 607.9 605.2200 616.9 614.2300 625.9 623.2 ONEI-0400-450 Rev 0Page 23 of 24Oconee 2 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
-35.0-35.0-14.414.435.035.0-35.0-35.0-1.-14.435.035.0-37.6-37.6-32.8-26.523.733.839.539.5-37.6-37.639.39.5 ONEI-0400-450 Rev 0Page 24 of 24Oconee 2 Cycle 28Rod Index LimitsReferred to by TS 3.2.1Operational RI Shutdown Margin RI Insertion Limit%FP Insertion Limit No Inop Rod 1 Inop Rod4 Pumps3 Pumps10210090805015577501552622602502402009002362009002201407502201407502802301607528023016075RI Withdrawal Limit300300300300300300300300300300300}}

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