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{{Adams
#REDIRECT [[ONS-2015-111, Core Operating Limits Report, Cycle 28, ONEI-0400-450, Revision 00]]
| number = ML15310A043
| issue date = 10/30/2015
| title = 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. Batson Vice President Oconee Nuclear Station Duke Energy ONOIVP I 7800 Rochester Hwy Seneca, SC 29672 os 864.873.3274 fi 864.873. 4208 Scott. Batson@duke-energy.cam ONS-201 5-111 October 30, 2015 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
 
==Subject:==
Duke Energy Carolinas, LLC Oconee Nuclear Site Docket Number 50-270 Core Operating Limits Report (COLR)Attached, pursuant to Oconee Technical Specification 5.6.5.d, is an information copy of the 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. Batson Vice President Oconee Nuclear Station Attachment H Y-www.duke-energy.com U. S. Nuclear Regulatory Commission October 30, 2015 Page 2 bc w/att: Mr. Leonard D. Wert, Jr.Administrator, Region II (Acting)U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. James R. Hall (By electronic mail only)U.S. Nuclear Regulatory Commission One White Flint North, M/S O-8B1 11555 Rockville Pike Rockville, MD 20852-2746 Mr. Eddy Crowe Senior Resident Inspector Oconee Nuclear Site
~ENERGYFacility Code : ON Applicable Facilities
: ON Document Number : ON EI-0400-450 Document Revision Number : 000 Document EC Number : Change Reason : NO reason given per RR StClair Document Title : OCONEE 2 CYCLE 28 CORE OPERATING LIMITS REPORT Lang, 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 0 Page 1 of 24 Duke Energy Oconee 2 Cycle 28 Core Operating Limits Report QA Condition 1 Prepared 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 0 Page 2 of 24 Engineering Instruction Inspection Waiver: This El Inspection has been waived by OS-105.00.
ONEI-0400-450 Rev 0 Page 3 of 24 Oconee 2 Cycle 28 Core Operating Limits Report Insertion Sheet for Revision 0 Effective Revision Date Revision Log Pages Revised Pages Pages Total Effective Added Deleted Pages lOconee2 Cycle 28 revisions belOwsp211-244 ONEI-0400-450 Rev 0 Page 4 of 24 Oconee 2 Cycle 28 Table Of Contents Section 1.0 Error Adiusted Core Operating Limits NRC Approved Methodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Maximum Allowed RPS Power 6, 7, 8, 9, 10 Imbalance Limits 3.1.1 Shutdown Marg]in (SDM) 1, 3, 7 ,8 Shutdown Margin 3.1.3 Moderator Temperature Coefficient (MTC) 1, 3, 7 MTC 3.1.4 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 Overlap 4-pump No Inoperable Rod CR Position Setpoints 3-pump No Inoperable Rod CR Position Setpoints 3.2.2 Axial Power Imbalance Operating Limits 1, 2, 3, 4, 5, 4-pump Operational Power 7, 8, 9, 10 Imbalance Setpoints 3-pump Operational Power Imbalance 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 Slope Instrumentation 6, 7, 8, 9, 10 Variable Low RCS Pressure RPS Setpoints Maximum Allowed RPS Power Imbalance Limits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpoints 3.4.1 RCS Pressure, Temperature, and Flow 4, 5, 7, 8 RCS Pressure, Temperature, Departure from Nucleate Boiling Limits and Flow 3.5.1 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 Approved Methodology 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 Acid Storage Tank (CBAST)Section 2.0 Core Operating Limits -Not Error Adiusted (NOT FOR PLANT USE)NRC Approved Methodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Variable Low RCS Pressure 6, 7, 8, 9, 10 Protective Limits Axial Power Imbalance Protective Limits 3.2.1 Reglulatingl Rod Position Limits 1, 3, 4, 5, 7, 8, 9, 10 Rod Index Limits 3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 Quadrant Power Tilt Limits ONEI-0400-450 Rev 0 Page 5 of 24 Oconee 2 Cycle 28 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02028 has been prepared in accordance with the requirements of TS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology 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 by References 15 through 17. The O2C28 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, 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 569 0 F.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 for Once-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 Water Reactor 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 Pressure Safety Limit, OSC-4048, Revision 6, September 2010.13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, 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 0 Page 6 of 24 Oconee 2 Cycle 28 Miscellaneous 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 the CFT'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 10-4 Linear interpolation is valid within the table provided.
Ap / 0 F % FP Referred to by TS 3.1.3. +0.70 0+0.525 20 0.00 80 0.00 100 0.00 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by TS 3.4.1. 4 RCP: measured hot leg pressure > 2125 psig 3 RCP: measured hot leg pressure > 2125 psig DNB 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 Op 0 581.0 581.0 *The measured Tavg must be less than COLR limits minus 1 581.4 581.2 instrument uncertainty.
ATc is the setpoint value selected by 2 581.8 581.4 the operators.
3 582.1 581.7 4 582.5 581.9 5 582.9 582.1* This limit is applied to the loop with the lowest ioop average temperature consistent with the 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 %df Referred to by TS 3.4.1. 3 RCP: Measured > 74.7 % of 4 RCP min flow Regulating 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 by TS 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 0 Page 7 of 24 Oconee 2 Cycle 28 EFPD 0 to 646 646 to EOC Core Power Level, %FP Full Incore Out of Core Backup Incore Steady State Operating Band Rod Index APSR %WD Min Max Min Max 292+/-+5 300 30 40 292 +/-5 300 100 100 Quadrant Power Tilt Setpoints Steady State Transient 0 -30 > 30 0 -30 > 30 7.61 3.50 9.40 7.11 6.09 2.35 7.72 5.63 3.87 2.25 4.81 3.63 Referred to by TS 3.2.3 Maximum>0 16.55 14.22 10.07 Correlation Slope (CS)1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
ONEI-0400-450 Rev 0 Page 8 of 24 Oconee 2 Cycle 28 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P = 2355 psig T = 618 0 F 2300 2200 09 a2100 Acceptable cnOperation 0)_P = 11.14" Tout-470 0 2000/ Unacceptable 1900 /Operation P = 1800 psig 1800 T = 584 0 F 1700 I I I 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, 0 F ONEI-0400-450 Rev 0 Page 9 of 24 Oconee 2 Cycle 28 Referred to by TS 2.1.1 and TS Table 3.3.1-1 Maximum Allowable RPS Power Imbalance Limits% FP % Imbalance 4 Pumps 0.0 -35.0 90.0 -35.0 Pmax => 109.4 -14.4 Pma.x=> 109.4 14.4 90.0 35.0 0.0 35.0 3 Pumps 0.0 -35.0 62.3 -35.0 Pmax => 81.7 -14.4 Pmax=> 81.7 14.4 62.3 35.0 0.0 35.0 ONE1-0400-450 Rev 0 Page 10 of 24 Oconee 2 Cycle 28 Operational Power Imbalance Setpoints Referred to by TS 3.2.2 Full Backup Out of%FP Incore Incore Core 4 Pumps 0.0 -28.0 -25.9 -26.4 80.0 -28.0 -25.9 -26.4 90.0 -28.0 -21.5 -21.9 100.0 -17.7 -15.9 -16.2 102.0 -15.6 -14.8 -15.1 102.0 15.6 11.7 12.1 100.0 17.7 13.5 13.9 90.0 28.0 22.4 22.7 80.0 28.0 27.5 28.0 0.0 28.0 27.5 28.0 3 Pumps 0.0 -28.0 -25.9 -26.4 63.1 -28.0 --64.6 -- -26.4 65.0 --25.9 -77.0 -13.2 -13.2 -13.2 77.0 13.2 13.2 13.2 63.5 -27.5 -63.1 28.0 -28.0 0.0 28.0 27.5 28.0 Referred to by TS 3.2.2 ONEI-0400-450 Rev 0 Page 11 of 24 Oconee 2 Cycle 28 RPS / Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1% FP RPS Trip ] Full Incore Alarm J Out of Core Alarm 107.9 106.0 105.0 104.0 103.0 102.0 101.0 100.0 99.0 98.0 97.0 96.0 95.0 94.0 93.0 92.0 91.0 90.4 90.0 89.0 88.0 87.0 86.0 85.0 84.0 83.0 82.0 81.0 80.0 0.0-14.4-16.4-17.5-18.5-19.6-20.7-21.7-22.8-23.9-24.9-26.0-27.0-28.1-29.2-30.2-31.3-32.3-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0 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 33.0-15.6-16.7-17.7-18.7-19.8-20.8-21.8-22.9-23.9-24.9-25.9-27.0-27.6-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0 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 28.0-15.1-15.7-16.2-16.8-17.3-17.9-18.5-19.1-19.6-20.2-20.8-21.3-21.7-21.9-22.4-22.8-23.3-23.7-24.2-24.6-25.1-25.5-26.0-26.4-26.4 12.1 13.0 13.9 14.8 15.7 16.5 17.4 18.3 19.2 20.1 20.9 21.8 22.4 22.7 23.2 23.8 24.3 24.8 25.4 25.9 26.4 26.9 27.5 28.0 28.0 28.0% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-450 Rev 0 Page 12 of 24 Oconee 2 Cycle 28 RPS / Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1% FP j RPS Trip Full Incore Alarm [Out of Core Alarm 80.6 80.0 79.0 78.0 77.0 76.0 75.0 74.0 73.0 72.0 71.0 70.0 69.0 68.0 67.0 66.0 65.0 64.6 64.0 63.1 63.0 62.0 61.0 60.0 0.0-14.4-15.0-16.1-17.1-18.2-19.3-20.3-21.4-22.4-23.5-24.6-25.6-26.7-27.8-28.8-29.9-30.9-31.4-32.0-33.0-33.0-33.0-33.0-33.0-33.0 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 33.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-27.0-28.0-28.0-28.0-28.0-28.0-28.0 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 28.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-26.4-26.4-26.4-26.4-26.4-26.4-26.4 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 28.0% FP J RPS Trip j Full Incore Alarm jOut of Core Alarm ONEI-0400-450 Rev 0 Page 13 of 24 Oconee 2 Cycle 28 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0-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)
-40.0 60.0-Acceptable 3 or 4 Pump Operation 40.0-20.0--30.0-20.0-10.0 0.0 10.0 Percent Power Imbalance 20.0 30.0 b 40.0 Oconee 2 Cycle 28 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-450 Rev 0 Page 14 of 24 110 100 90 80 70 0 6 a- 6 00 50 2O 10 14.4, 107.9 0-40 30 20 10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance Oconee 2 Cycle 28 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-450 Rev 0 Page 15 of 24 o)0.a-P-'4-110 100 90 80 70 60 50 40 30 20 10.. .,44.O.6 -!- I !i -L- t- i-IRPS TriP 13.2, 77.0Trip setpoint 33.0,63.1-I It 7 -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--i 7-4-25.9, 27.5, 0.0 33.0, 0.0 J-~ i~-40-35-30-25-20-15-10 -5 0 5 Percent Axial Imbalance 10 15 20 25 30 35 40 ONEI-0400-450 Rev 0 Page 16 of 24 Oconee 2 Cycle 28 Operational Rod Index Setpoints Referred to by TS 3.2.1 4 Pumps 3 Pumps%FP 102.0 100.0 90.0 80.0 50.0 48.0 15.0 13.0 5.0 3.0 2.8 0.0 77.0 75.0 50.0 48.0 15.0 13.0 5.0 3.0 2.8 0.0 RI Insertion Setpoint No Inop Rod 1 Inop Rod 263.5 283.4 261.5 281.5 251.5 271.9 241.5 262.3 201.5 233.4 195.2 231.5 91.5 165.5 76.5 161.5 16.5 93.5 1.5 76.5 0.0 74.8 0.0 51.0 RI Withdrawal Setpoint 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 237.5 234.8 201.5 195.2 91.5 76.5 16.5 1.5 0.0 0.0 285.2 281.5 235.2 231.5 165.5 161.5 93.5 76.5 74.8 51.0 ONEI-0400-450 Rev 0 Page 17 of 24 Oconee 2 Cycle 28 Shutdown Margin Rod Index Setpoints 4 Pumps 3 Pumps%FP 102.0 100.0 48.0 13.0 3.0 2.8 0.0 77.0 75.0 48.0 13.0 3.0 2.8 0.0 Referred to by TS 3.2.1 RI Insertion Setpoint No Inop Rod 1 Inop Rod 224.6 283.4 221.5 281.5 141.5 231.5 76.5 161.5 1.5 76.5 0.0 74.8 0.0 51.0 RI Withdrawal Setpoint 300 300 300 300 300 300 300 300 300 300 300 300 300 300 227.4 221.5 141.5 76.5 1.5 0.0 0.0 285.2 281.5 231.5 161.5 76.5 74.8 51.0 SOconee 2 Cycle 28 0NE1-0400-450 Rev 0 Page 18 of 24 Referred to by TS 3.2.1 LIL O 0.0Y 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 ol 0.260.05,1502235 45 55.65 5185.9 F 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0 r m0 10 20 30 40 50 60 70 80 90 100ol 10 10 20 30 40 50 60 70 80 90 1001 I, Group 5 Control Rod Position, % WD Group 7 I Control Rod Position, % WD I Group 7J J SOconee 2 Cycle 28 Referred to by TS 3.2.1 0NE1-0400-450 Rev 0 Page 19 of 24 0 a-rY 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 SControl Rod Position Setpoints No Inoperable Rods, 3 Pump Flow, BOO to EOC H 221.5, 75.0 237.5, 77.0_LU 234.8, 75.0 Unacceptable Operation S175.0, 59.w 105 100 i195.2, 48.0 141.5, 48.75 70 65 755 50 45 40 355 30 25 20 15 10 25 Restricted Operation 125.0,_ 39.1 175.0, 41.Acceptable Operation 125.0, 25.71 76.5,1,3 191.5, 1 S0 10 20 30 40 50 61 0.0, 0.0Gru 5 75.0, 12.8 0 70 80 90 25 100C 354]5 6 Control Rod Position, % 75 85 95 (J 0O 10 20 30 40 50 60 70 80 90 100]'VD I Group 71 0 I I I Oconee 2 Cycle 28 I Referred to by TS 3.2.1 ONEI-0400-450 Rev 0 Page 20 of 24 10(9, 9(8, 8(7, 7(6, a-.41 4, 3(3 2 2 1 5 f300 0.0 ~~~Control Rod Position Setpoints21.,00 5 1 Inoperable Rod, 4 Pump Flow, 0 5 0 5 0 5 Unacceptable 0215480 Acceptable 5 0 5 0 5 050, 551oo0!5 15 25 35 45 55 65 75 85 95 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0 10 10 20 30 40 50 60 70 80 90 100 I S0 10 20 30 40 50 60 70 80 90 100 L Group 5 J Group 5 I ~Control Rod Position, % WD Gru7 I Group 7 J
..I Oconee 2 Cycle 28 I Referred to byTIS 3.2.1 ONEI-0400-450 Rev 0 Paoe 21 of 24 10.1LL U)o 0.0 0Y 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0ontrol Rod Position Setpoints 1 Inoperable Rod, 3 Pump Flow, BOC to EOC 285.2, 77.0 In Em ui Ilium="300.0,7 281.5. 75.0 Operation 2231.0, 4.8, 105 100 95 90 85 175 70 65 60 55 50 45 40 35 Acceptable Operation 30 175.0, 19.8 161.5,13.0 H-",R &#xa3;  125.0, 8.7 25 20 15 10 5 0 1.-750 '282 lilt ~ ~ Ft-IT~&#xb6;T1fInmT I51-00 &deg;0 15 25 35 45 55 65 75 85 95U 0 O 10 20 o3 40 50 60 70 80 90 10 1 0 10 20 30 40 50 60 70 80 90 1001I 1 I Group 5 I Control Rod Position, % WD I ru onrlRdPsiin DGroup 7I ONEI-0400-450 Rev 0 Page 22 of 24 Oconee 2 Cycle 28 2.0 Core Operating Limits -Not Error Adjusted The data provided on the following pages satisfies a licensing commitment to identify specific parameters 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 Ti Core Outi F 1 1 2 2 2 2%FP C ilt, % 1 Quad rant Power Tilt Limits Referred to by TS 3.2.3 Steady State T)3- 30 > 30 0 -30 10.00 5.40 12.00"ransient>30 9.44 Maximum>0 20.00 Variable Low RCS Pressure Protective Limits Referred to by TS 2.1.1 let Pressure Reactor Coolant Outlet Temperature, 0 F 3sia 3 RCS Pumps 4 RCS Pumps 800 581.0 578.3 900 590.0 587.3 000 598.9 596.3 100 607.9 605.2 200 616.9 614.2 300 625.9 623.2 ONEI-0400-450 Rev 0 Page 23 of 24 Oconee 2 Cycle 28 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1 4 Pumps 3 Pumps%FP 0.0 80.0 90.0 100.0 109.4 109.4 100.0 90.0 80.0 0.0 0.0 62.3 77.0 81.7 81.7 77.0 62.3 0.0 RPS Operational
-35.0-35.0-14.4 14.4 35.0 35.0-35.0-35.0-1.-14.4 35.0 35.0-37.6-37.6-32.8-26.5 23.7 33.8 39.5 39.5-37.6-37.6 39.39.5 ONEI-0400-450 Rev 0 Page 24 of 24 Oconee 2 Cycle 28 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit%FP Insertion Limit No Inop Rod 1 Inop Rod 4 Pumps 3 Pumps 102 100 90 80 50 15 5 77 50 15 5 262 260 250 240 200 90 0 236 200 90 0 220 140 75 0 220 140 75 0 280 230 160 75 280 230 160 75 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300
~ENERGYScott L. Batson Vice President Oconee Nuclear Station Duke Energy ONOIVP I 7800 Rochester Hwy Seneca, SC 29672 os 864.873.3274 fi 864.873. 4208 Scott. Batson@duke-energy.cam ONS-201 5-111 October 30, 2015 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
 
==Subject:==
Duke Energy Carolinas, LLC Oconee Nuclear Site Docket Number 50-270 Core Operating Limits Report (COLR)Attached, pursuant to Oconee Technical Specification 5.6.5.d, is an information copy of the 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. Batson Vice President Oconee Nuclear Station Attachment H Y-www.duke-energy.com U. S. Nuclear Regulatory Commission October 30, 2015 Page 2 bc w/att: Mr. Leonard D. Wert, Jr.Administrator, Region II (Acting)U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. James R. Hall (By electronic mail only)U.S. Nuclear Regulatory Commission One White Flint North, M/S O-8B1 11555 Rockville Pike Rockville, MD 20852-2746 Mr. Eddy Crowe Senior Resident Inspector Oconee Nuclear Site
~ENERGYFacility Code : ON Applicable Facilities
: ON Document Number : ON EI-0400-450 Document Revision Number : 000 Document EC Number : Change Reason : NO reason given per RR StClair Document Title : OCONEE 2 CYCLE 28 CORE OPERATING LIMITS REPORT Lang, 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 0 Page 1 of 24 Duke Energy Oconee 2 Cycle 28 Core Operating Limits Report QA Condition 1 Prepared 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 0 Page 2 of 24 Engineering Instruction Inspection Waiver: This El Inspection has been waived by OS-105.00.
ONEI-0400-450 Rev 0 Page 3 of 24 Oconee 2 Cycle 28 Core Operating Limits Report Insertion Sheet for Revision 0 Effective Revision Date Revision Log Pages Revised Pages Pages Total Effective Added Deleted Pages lOconee2 Cycle 28 revisions belOwsp211-244 ONEI-0400-450 Rev 0 Page 4 of 24 Oconee 2 Cycle 28 Table Of Contents Section 1.0 Error Adiusted Core Operating Limits NRC Approved Methodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Maximum Allowed RPS Power 6, 7, 8, 9, 10 Imbalance Limits 3.1.1 Shutdown Marg]in (SDM) 1, 3, 7 ,8 Shutdown Margin 3.1.3 Moderator Temperature Coefficient (MTC) 1, 3, 7 MTC 3.1.4 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 Overlap 4-pump No Inoperable Rod CR Position Setpoints 3-pump No Inoperable Rod CR Position Setpoints 3.2.2 Axial Power Imbalance Operating Limits 1, 2, 3, 4, 5, 4-pump Operational Power 7, 8, 9, 10 Imbalance Setpoints 3-pump Operational Power Imbalance 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 Slope Instrumentation 6, 7, 8, 9, 10 Variable Low RCS Pressure RPS Setpoints Maximum Allowed RPS Power Imbalance Limits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpoints 3.4.1 RCS Pressure, Temperature, and Flow 4, 5, 7, 8 RCS Pressure, Temperature, Departure from Nucleate Boiling Limits and Flow 3.5.1 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 Approved Methodology 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 Acid Storage Tank (CBAST)Section 2.0 Core Operating Limits -Not Error Adiusted (NOT FOR PLANT USE)NRC Approved Methodology TS Number Technical Specification Reference
# COLR Parameter 2.1.1 Safety Limits 1, 2, 3, 4, 5, Variable Low RCS Pressure 6, 7, 8, 9, 10 Protective Limits Axial Power Imbalance Protective Limits 3.2.1 Reglulatingl Rod Position Limits 1, 3, 4, 5, 7, 8, 9, 10 Rod Index Limits 3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 Quadrant Power Tilt Limits ONEI-0400-450 Rev 0 Page 5 of 24 Oconee 2 Cycle 28 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02028 has been prepared in accordance with the requirements of TS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology 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 by References 15 through 17. The O2C28 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, 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 569 0 F.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 for Once-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 Water Reactor 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 Pressure Safety Limit, OSC-4048, Revision 6, September 2010.13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, 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 0 Page 6 of 24 Oconee 2 Cycle 28 Miscellaneous 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 the CFT'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 10-4 Linear interpolation is valid within the table provided.
Ap / 0 F % FP Referred to by TS 3.1.3. +0.70 0+0.525 20 0.00 80 0.00 100 0.00 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by TS 3.4.1. 4 RCP: measured hot leg pressure > 2125 psig 3 RCP: measured hot leg pressure > 2125 psig DNB 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 Op 0 581.0 581.0 *The measured Tavg must be less than COLR limits minus 1 581.4 581.2 instrument uncertainty.
ATc is the setpoint value selected by 2 581.8 581.4 the operators.
3 582.1 581.7 4 582.5 581.9 5 582.9 582.1* This limit is applied to the loop with the lowest ioop average temperature consistent with the 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 %df Referred to by TS 3.4.1. 3 RCP: Measured > 74.7 % of 4 RCP min flow Regulating 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 by TS 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 0 Page 7 of 24 Oconee 2 Cycle 28 EFPD 0 to 646 646 to EOC Core Power Level, %FP Full Incore Out of Core Backup Incore Steady State Operating Band Rod Index APSR %WD Min Max Min Max 292+/-+5 300 30 40 292 +/-5 300 100 100 Quadrant Power Tilt Setpoints Steady State Transient 0 -30 > 30 0 -30 > 30 7.61 3.50 9.40 7.11 6.09 2.35 7.72 5.63 3.87 2.25 4.81 3.63 Referred to by TS 3.2.3 Maximum>0 16.55 14.22 10.07 Correlation Slope (CS)1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
ONEI-0400-450 Rev 0 Page 8 of 24 Oconee 2 Cycle 28 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P = 2355 psig T = 618 0 F 2300 2200 09 a2100 Acceptable cnOperation 0)_P = 11.14" Tout-470 0 2000/ Unacceptable 1900 /Operation P = 1800 psig 1800 T = 584 0 F 1700 I I I 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, 0 F ONEI-0400-450 Rev 0 Page 9 of 24 Oconee 2 Cycle 28 Referred to by TS 2.1.1 and TS Table 3.3.1-1 Maximum Allowable RPS Power Imbalance Limits% FP % Imbalance 4 Pumps 0.0 -35.0 90.0 -35.0 Pmax => 109.4 -14.4 Pma.x=> 109.4 14.4 90.0 35.0 0.0 35.0 3 Pumps 0.0 -35.0 62.3 -35.0 Pmax => 81.7 -14.4 Pmax=> 81.7 14.4 62.3 35.0 0.0 35.0 ONE1-0400-450 Rev 0 Page 10 of 24 Oconee 2 Cycle 28 Operational Power Imbalance Setpoints Referred to by TS 3.2.2 Full Backup Out of%FP Incore Incore Core 4 Pumps 0.0 -28.0 -25.9 -26.4 80.0 -28.0 -25.9 -26.4 90.0 -28.0 -21.5 -21.9 100.0 -17.7 -15.9 -16.2 102.0 -15.6 -14.8 -15.1 102.0 15.6 11.7 12.1 100.0 17.7 13.5 13.9 90.0 28.0 22.4 22.7 80.0 28.0 27.5 28.0 0.0 28.0 27.5 28.0 3 Pumps 0.0 -28.0 -25.9 -26.4 63.1 -28.0 --64.6 -- -26.4 65.0 --25.9 -77.0 -13.2 -13.2 -13.2 77.0 13.2 13.2 13.2 63.5 -27.5 -63.1 28.0 -28.0 0.0 28.0 27.5 28.0 Referred to by TS 3.2.2 ONEI-0400-450 Rev 0 Page 11 of 24 Oconee 2 Cycle 28 RPS / Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1% FP RPS Trip ] Full Incore Alarm J Out of Core Alarm 107.9 106.0 105.0 104.0 103.0 102.0 101.0 100.0 99.0 98.0 97.0 96.0 95.0 94.0 93.0 92.0 91.0 90.4 90.0 89.0 88.0 87.0 86.0 85.0 84.0 83.0 82.0 81.0 80.0 0.0-14.4-16.4-17.5-18.5-19.6-20.7-21.7-22.8-23.9-24.9-26.0-27.0-28.1-29.2-30.2-31.3-32.3-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0-33.0 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 33.0-15.6-16.7-17.7-18.7-19.8-20.8-21.8-22.9-23.9-24.9-25.9-27.0-27.6-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0-28.0 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 28.0-15.1-15.7-16.2-16.8-17.3-17.9-18.5-19.1-19.6-20.2-20.8-21.3-21.7-21.9-22.4-22.8-23.3-23.7-24.2-24.6-25.1-25.5-26.0-26.4-26.4 12.1 13.0 13.9 14.8 15.7 16.5 17.4 18.3 19.2 20.1 20.9 21.8 22.4 22.7 23.2 23.8 24.3 24.8 25.4 25.9 26.4 26.9 27.5 28.0 28.0 28.0% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-450 Rev 0 Page 12 of 24 Oconee 2 Cycle 28 RPS / Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1% FP j RPS Trip Full Incore Alarm [Out of Core Alarm 80.6 80.0 79.0 78.0 77.0 76.0 75.0 74.0 73.0 72.0 71.0 70.0 69.0 68.0 67.0 66.0 65.0 64.6 64.0 63.1 63.0 62.0 61.0 60.0 0.0-14.4-15.0-16.1-17.1-18.2-19.3-20.3-21.4-22.4-23.5-24.6-25.6-26.7-27.8-28.8-29.9-30.9-31.4-32.0-33.0-33.0-33.0-33.0-33.0-33.0 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 33.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-27.0-28.0-28.0-28.0-28.0-28.0-28.0 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 28.0-13.2-14.3-15.3-16.4-17.4-18.5-19.6-20.6-21.7-22.8-23.8-24.9-25.9-26.4-26.4-26.4-26.4-26.4-26.4-26.4-26.4 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 28.0% FP J RPS Trip j Full Incore Alarm jOut of Core Alarm ONEI-0400-450 Rev 0 Page 13 of 24 Oconee 2 Cycle 28 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0-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)
-40.0 60.0-Acceptable 3 or 4 Pump Operation 40.0-20.0--30.0-20.0-10.0 0.0 10.0 Percent Power Imbalance 20.0 30.0 b 40.0 Oconee 2 Cycle 28 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-450 Rev 0 Page 14 of 24 110 100 90 80 70 0 6 a- 6 00 50 2O 10 14.4, 107.9 0-40 30 20 10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance Oconee 2 Cycle 28 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-450 Rev 0 Page 15 of 24 o)0.a-P-'4-110 100 90 80 70 60 50 40 30 20 10.. .,44.O.6 -!- I !i -L- t- i-IRPS TriP 13.2, 77.0Trip setpoint 33.0,63.1-I It 7 -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--i 7-4-25.9, 27.5, 0.0 33.0, 0.0 J-~ i~-40-35-30-25-20-15-10 -5 0 5 Percent Axial Imbalance 10 15 20 25 30 35 40 ONEI-0400-450 Rev 0 Page 16 of 24 Oconee 2 Cycle 28 Operational Rod Index Setpoints Referred to by TS 3.2.1 4 Pumps 3 Pumps%FP 102.0 100.0 90.0 80.0 50.0 48.0 15.0 13.0 5.0 3.0 2.8 0.0 77.0 75.0 50.0 48.0 15.0 13.0 5.0 3.0 2.8 0.0 RI Insertion Setpoint No Inop Rod 1 Inop Rod 263.5 283.4 261.5 281.5 251.5 271.9 241.5 262.3 201.5 233.4 195.2 231.5 91.5 165.5 76.5 161.5 16.5 93.5 1.5 76.5 0.0 74.8 0.0 51.0 RI Withdrawal Setpoint 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 237.5 234.8 201.5 195.2 91.5 76.5 16.5 1.5 0.0 0.0 285.2 281.5 235.2 231.5 165.5 161.5 93.5 76.5 74.8 51.0 ONEI-0400-450 Rev 0 Page 17 of 24 Oconee 2 Cycle 28 Shutdown Margin Rod Index Setpoints 4 Pumps 3 Pumps%FP 102.0 100.0 48.0 13.0 3.0 2.8 0.0 77.0 75.0 48.0 13.0 3.0 2.8 0.0 Referred to by TS 3.2.1 RI Insertion Setpoint No Inop Rod 1 Inop Rod 224.6 283.4 221.5 281.5 141.5 231.5 76.5 161.5 1.5 76.5 0.0 74.8 0.0 51.0 RI Withdrawal Setpoint 300 300 300 300 300 300 300 300 300 300 300 300 300 300 227.4 221.5 141.5 76.5 1.5 0.0 0.0 285.2 281.5 231.5 161.5 76.5 74.8 51.0 SOconee 2 Cycle 28 0NE1-0400-450 Rev 0 Page 18 of 24 Referred to by TS 3.2.1 LIL O 0.0Y 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 ol 0.260.05,1502235 45 55.65 5185.9 F 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0 r m0 10 20 30 40 50 60 70 80 90 100ol 10 10 20 30 40 50 60 70 80 90 1001 I, Group 5 Control Rod Position, % WD Group 7 I Control Rod Position, % WD I Group 7J J SOconee 2 Cycle 28 Referred to by TS 3.2.1 0NE1-0400-450 Rev 0 Page 19 of 24 0 a-rY 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 SControl Rod Position Setpoints No Inoperable Rods, 3 Pump Flow, BOO to EOC H 221.5, 75.0 237.5, 77.0_LU 234.8, 75.0 Unacceptable Operation S175.0, 59.w 105 100 i195.2, 48.0 141.5, 48.75 70 65 755 50 45 40 355 30 25 20 15 10 25 Restricted Operation 125.0,_ 39.1 175.0, 41.Acceptable Operation 125.0, 25.71 76.5,1,3 191.5, 1 S0 10 20 30 40 50 61 0.0, 0.0Gru 5 75.0, 12.8 0 70 80 90 25 100C 354]5 6 Control Rod Position, % 75 85 95 (J 0O 10 20 30 40 50 60 70 80 90 100]'VD I Group 71 0 I I I Oconee 2 Cycle 28 I Referred to by TS 3.2.1 ONEI-0400-450 Rev 0 Page 20 of 24 10(9, 9(8, 8(7, 7(6, a-.41 4, 3(3 2 2 1 5 f300 0.0 ~~~Control Rod Position Setpoints21.,00 5 1 Inoperable Rod, 4 Pump Flow, 0 5 0 5 0 5 Unacceptable 0215480 Acceptable 5 0 5 0 5 050, 551oo0!5 15 25 35 45 55 65 75 85 95 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0 10 10 20 30 40 50 60 70 80 90 100 I S0 10 20 30 40 50 60 70 80 90 100 L Group 5 J Group 5 I ~Control Rod Position, % WD Gru7 I Group 7 J
..I Oconee 2 Cycle 28 I Referred to byTIS 3.2.1 ONEI-0400-450 Rev 0 Paoe 21 of 24 10.1LL U)o 0.0 0Y 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5 0ontrol Rod Position Setpoints 1 Inoperable Rod, 3 Pump Flow, BOC to EOC 285.2, 77.0 In Em ui Ilium="300.0,7 281.5. 75.0 Operation 2231.0, 4.8, 105 100 95 90 85 175 70 65 60 55 50 45 40 35 Acceptable Operation 30 175.0, 19.8 161.5,13.0 H-",R &#xa3;  125.0, 8.7 25 20 15 10 5 0 1.-750 '282 lilt ~ ~ Ft-IT~&#xb6;T1fInmT I51-00 &deg;0 15 25 35 45 55 65 75 85 95U 0 O 10 20 o3 40 50 60 70 80 90 10 1 0 10 20 30 40 50 60 70 80 90 1001I 1 I Group 5 I Control Rod Position, % WD I ru onrlRdPsiin DGroup 7I ONEI-0400-450 Rev 0 Page 22 of 24 Oconee 2 Cycle 28 2.0 Core Operating Limits -Not Error Adjusted The data provided on the following pages satisfies a licensing commitment to identify specific parameters 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 Ti Core Outi F 1 1 2 2 2 2%FP C ilt, % 1 Quad rant Power Tilt Limits Referred to by TS 3.2.3 Steady State T)3- 30 > 30 0 -30 10.00 5.40 12.00"ransient>30 9.44 Maximum>0 20.00 Variable Low RCS Pressure Protective Limits Referred to by TS 2.1.1 let Pressure Reactor Coolant Outlet Temperature, 0 F 3sia 3 RCS Pumps 4 RCS Pumps 800 581.0 578.3 900 590.0 587.3 000 598.9 596.3 100 607.9 605.2 200 616.9 614.2 300 625.9 623.2 ONEI-0400-450 Rev 0 Page 23 of 24 Oconee 2 Cycle 28 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1 4 Pumps 3 Pumps%FP 0.0 80.0 90.0 100.0 109.4 109.4 100.0 90.0 80.0 0.0 0.0 62.3 77.0 81.7 81.7 77.0 62.3 0.0 RPS Operational
-35.0-35.0-14.4 14.4 35.0 35.0-35.0-35.0-1.-14.4 35.0 35.0-37.6-37.6-32.8-26.5 23.7 33.8 39.5 39.5-37.6-37.6 39.39.5 ONEI-0400-450 Rev 0 Page 24 of 24 Oconee 2 Cycle 28 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit%FP Insertion Limit No Inop Rod 1 Inop Rod 4 Pumps 3 Pumps 102 100 90 80 50 15 5 77 50 15 5 262 260 250 240 200 90 0 236 200 90 0 220 140 75 0 220 140 75 0 280 230 160 75 280 230 160 75 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300}}

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