RA-23-0186, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)
| ML23199A296 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 07/18/2023 |
| From: | Grant H Duke Energy Carolinas |
| To: | Office of Nuclear Reactor Regulation, Document Control Desk |
| References | |
| RA-23-0186 | |
| Download: ML23199A296 (1) | |
Text
H. Todd Grant General Manager Nuclear Engineering Oconee Nuclear Station Duke Energy ON01VP l 7800 Rochester Hwy Seneca, SC 29672
- o. 864.873.6767 f: 864.873.5791 Todd.Grant@duke-energy.com RA-23-0186 10 CFR 50.36 July 18, 2023 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001 Duke Energy Carolinas, LLC Oconee Nuclear Station (ONS) Unit 2 Docket Number 50-270 Renewed License Number DPR-47
Subject:
Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 2 Cycle 31 (Revision 3)
Pursuant to Oconee Technical Specification 5.6.5.d, attached is an information copy of the Core Operating Limits Report (COLR) for Oconee Unit 2, Cycle 31, Revision 3. Revision 3 is a mid-cycle revision completed to address Revision 3 of the referenced Maneuvering Analysis calculation.
Any inquiries on this submittal should be directed to Sam Adams, Oconee Regulatory Affairs, at 864-873-3348.
Sincerely, H. Todd Grant General Manager Nuclear Engineering Oconee Nuclear Station Attachments: ONEI-0400-567 Revision 3 - Oconee Unit 2 Cycle 31 COLR
RA-23-0186 July 18, 2023 Page 2 cc (w/attachment):
Ms. Laura Dudes, Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Mr. Shawn Williams, Project Manager U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop O-08B1A Rockville, MD 20852-2738 Mr. Nick Smalley NRC Senior Resident Inspector (Acting)
Oconee Nuclear Station
Facility Code : ON Applicable Facilities : ON Document Number : ONEI-0400-567 Document Revision Number : 003 Document EC Number :
Change Reason : produced IAW AD-NF-ALL-0807 Document Title : Oconee 2 Cycle 31 Core Operating Limits Report Orr, David S Originator 7/3/2023 Forster, Joy D Design Verifier 7/6/2023 Washburn, Walter EI Inspection - site 7/5/2023 Pettyjohn, Jake Cross Disciplinary Review 7/5/2023 Lambert, Brad Approver 7/6/2023 Notes :
ONEI-0400-567 (Rev. 3)
Page 1 of 22 Oconee 2 Cycle 31 Core Operating Limits Report ONEI-0400-567 Revision 3 Reload 50.59 AR# 02415451 Prepared By: David S. Orr All signatures were captured via Fusion E-signature. See the Design Verified By: Joy D. Forster Fusion cover sheet for signature Cross-Disciplinary Review By: Jake Pettyjohn, Safety Analysis dates.
Stakeholder Inspection By: Walt Washburn, ONS RES The CDR was limited to pages 4, Approved By: Brad J. Lambert 6 and 20 only.
Revision Summary Revision Pages Revised Pages Added Pages Deleted Comments 0 -- 1 - 22 -- Original issue.
Revised for operation with Group 1 1-22 -- -- 8 fully inserted throughout the cycle.
Revised to add reference for 2 1-22 -- --
COPERNIC methodology.
Revised to address Revision 3 of the referenced MA calculation.
3 1-22 -- --
Affected limits are on pages 8-10, 12-13, and 21.
NOTES:
- The O2C31 COLR will cease to be effective during NO MODE between cycles 31 and 32.
ONEI-0400-567 Rev 3 Page 2 of 22 Oconee 2 Cycle 31 Table Of Contents Section 1.0 Error Adjusted 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, 13 Imbalance Limits 3.1.1 Shutdown Margin (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 Misaligned, 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, 13 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 16.13.10 Addition Systems of Concentrated Boric Acid Storage Tank (CBAST)
Section 2.0 Core Operating Limits - Not Error Adjusted (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, 13 Protective Limits Axial Power Imbalance Protective Limits 3.2.1 Regulating 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-0400-567 Rev 3 Page 3 of 22 Oconee 2 Cycle 31 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for O2C31 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 1 through 13. The RPS protective limits and maximum allowable setpoints are documented in References 14 through 16. These limits are validated for use in O2C31 by References 17 and 18. The O2C31 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, radial local peaking (Fh) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB)
Tavg reduction for up to 10°F provided 4 RCPs are in operation and Tavg does not decrease below 569°F.
The error adjusted core operating limits included in Section 1 of the report incorporate all necessary uncertainties and margins required for operation of the O2C31 reload core.
1.1 References
- 1. DPC-NE-1006-PA, Oconee Nuclear Design Methodology Using CASMO-4 / SIMULATE-3, NRC SE issued August 2, 2011.
- 2. DPC-NE-1002-A, Oconee Nuclear Station Reload Design Methodology II, SE dated July 21, 2011.
- 3. NFS-1001-A, Oconee Nuclear Station Reload Design Methodology, SE dated July 21, 2011.
- 5. DPC-NE-2005-PA, Thermal Hydraulic Statistical Core Design Methodology, SE dated October 29, 2008.
- 6. DPC-NE-2008-PA, Fuel Mechanical Reload Analysis Methodology Using TACO3 and GDTACO, SE dated July 21, 2011.
- 9. BAW-10192P-A, Revision 0, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.
- 10. BAW-10164P-A, Rev. 4 and 6, RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis, SERs dated April 9, 2002 and June 25, 2007, respectively.
- 11. BAW-10192P-A, Supplement 1P-A, Revision 0, BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SE dated November 2, 2017.
- 12. BAW-10227P-A, Revision 1, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, June 2003 (SER to BAW-10186P-A dated June 18, 2003).
- 13. BAW-10231P-A, Rev. 1, COPERNIC Fuel Rod Design Computer Code, January 2004.
- 14. OSC-4048, Revision 6, RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit.
- 15. OSC-5604, Revision 5, Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094.
- 16. OSC-7265, Revision 1, Tc and EOC Reduced Tavg Operation.
- 17. OSC-11955, Revision 3, O2C31 Maneuvering Analysis.
- 18. OSC-11974, Revision 1, O2C31 Reload Safety Evaluation.
ONEI-0400-567 Rev 3 Page 4 of 22 Oconee 2 Cycle 31 Miscellaneous Setpoints 100% rated thermal power, or RTP, is 2568 MWth. See TS 1.1, "Definitions."
BWST boron concentration shall be greater than 2500 ppm and less than 3000 ppm.
Referred to by TS 3.5.4.
Spent fuel pool boron concentration shall be greater than 2500 ppm.
Referred to by TS 3.7.12.
The equivalent of at least 1100 cubic feet of 11,000 ppm boron shall be maintained in the CBAST.
Referred to by TS SLC 16.5.13 and SLC 16.13.10.
CFT boron concentration shall be greater than 2400 ppm. The average boron concentration in 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 2400 ppm and less than 3000 ppm.
Referred to by TS 3.9.1.
Shutdown Margin (SDM) shall be greater than 1% k/k.
Referred to by TS 3.1.1.
Moderator Temperature Coefficient (MTC) shall be less than: MTC x 10-4 Linear interpolation is valid within the table provided. / °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 loop average temperature shall be: Max Loop Tavg (Incl 2°F unc)
Referred to by TS 3.4.1. Tc, °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. Tc 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 loop average temperature consistent with the 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 %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% +/- 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-0400-567 Rev 3 Page 5 of 22 Oconee 2 Cycle 31 Quadrant Power Tilt Setpoints Steady State Transient Maximum Core Power Level, %FP 0 - 30 > 30 0 - 30 > 30 >0 Full Incore 7.93 4.50 9.72 7.43 16.87 Out of Core 6.09 2.96 7.71 5.63 14.22 Backup Incore 3.86 2.46 4.81 3.62 10.06 Referred to by TS 3.2.3 Correlation Slope (CS) 1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
ONEI-0400-567 Rev 3 Page 6 of 22 Oconee 2 Cycle 31 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P = 2355 psig T = 618 °F 2300 2200 Reactor Coolant Pressure, PSIG 2100 Acceptable Operation P = 11.14
- Tout - 4706 2000 Unacceptable 1900 Operation P = 1800 psig 1800 T = 584 °F 1700 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, °F
ONEI-0400-567 Rev 3 Page 7 of 22 Oconee 2 Cycle 31 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 Pmax => 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
ONEI-0400-567 Rev 3 Page 8 of 22 Oconee 2 Cycle 31 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 -27.8 -28.0 80.0 -28.0 -27.8 -28.0 90.0 -28.0 -22.1 -22.5 100.0 -17.7 -15.2 -15.6 102.0 -15.6 -13.9 -14.2 102.0 15.6 14.0 14.3 100.0 17.7 15.4 15.8 90.0 28.0 22.5 22.9 80.0 28.0 27.6 28.0 0.0 28.0 27.6 28.0 3 Pumps 0.0 -28.0 -27.8 -28.0 63.1 -28.0 - -28.0 63.2 - -27.8 -
77.0 -13.2 -13.2 -13.2 77.0 13.2 13.2 13.2 63.4 - 27.6 -
63.1 28.0 - 28.0 0.0 28.0 27.6 28.0 Referred to by TS 3.2.2
ONEI-0400-567 Rev 3 Page 9 of 22 Oconee 2 Cycle 31 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 Out of Core Alarm 107.9 -14.4 14.4 106.0 -16.4 16.4 105.0 -17.4 17.4 104.0 -18.5 18.5 103.0 -19.6 19.6 102.0 -20.6 20.6 -15.6 15.6 -14.2 14.3 101.0 -21.7 21.7 -16.6 16.6 -14.9 15.0 100.0 -22.7 22.7 -17.7 17.7 -15.6 15.8 99.0 -23.8 23.8 -18.7 18.7 -16.2 16.5 98.0 -24.9 24.9 -19.7 19.7 -16.9 17.2 97.0 -25.9 25.9 -20.7 20.7 -17.6 17.9 96.0 -27.0 27.0 -21.8 21.8 -18.3 18.6 95.0 -28.0 28.0 -22.8 22.8 -19.0 19.3 94.0 -29.1 29.1 -23.8 23.8 -19.7 20.0 93.0 -30.2 30.2 -24.9 24.9 -20.4 20.7 92.0 -31.2 31.2 -25.9 25.9 -21.1 21.4 91.0 -32.3 32.3 -26.9 26.9 -21.8 22.1 90.4 -33.0 33.0 -27.6 27.6 -22.2 22.6 90.0 -33.0 33.0 -28.0 28.0 -22.5 22.9 89.0 -33.0 33.0 -28.0 28.0 -23.0 23.4 88.0 -33.0 33.0 -28.0 28.0 -23.6 23.9 87.0 -33.0 33.0 -28.0 28.0 -24.1 24.4 86.0 -33.0 33.0 -28.0 28.0 -24.7 24.9 85.0 -33.0 33.0 -28.0 28.0 -25.2 25.4 84.0 -33.0 33.0 -28.0 28.0 -25.8 25.9 83.0 -33.0 33.0 -28.0 28.0 -26.3 26.4 82.0 -33.0 33.0 -28.0 28.0 -26.9 26.9 81.0 -33.0 33.0 -28.0 28.0 -27.4 27.4 80.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 0.0 -33.0 33.0 -28.0 28.0 -28.0 28.0
% FP RPS Trip Full Incore Alarm Out of Core Alarm
ONEI-0400-567 Rev 3 Page 10 of 22 Oconee 2 Cycle 31 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 RPS Trip Full Incore Alarm Out of Core Alarm 80.6 -14.4 14.4 80.0 -15.0 15.0 79.0 -16.0 16.0 78.0 -17.1 17.1 77.0 -18.2 18.2 -13.2 13.2 -13.2 13.2 76.0 -19.2 19.2 -14.2 14.2 -14.2 14.2 75.0 -20.3 20.3 -15.3 15.3 -15.3 15.3 74.0 -21.4 21.4 -16.3 16.3 -16.3 16.3 73.0 -22.4 22.4 -17.4 17.4 -17.4 17.4 72.0 -23.5 23.5 -18.5 18.5 -18.5 18.5 71.0 -24.5 24.5 -19.5 19.5 -19.5 19.5 70.0 -25.6 25.6 -20.6 20.6 -20.6 20.6 69.0 -26.7 26.7 -21.7 21.7 -21.7 21.7 68.0 -27.7 27.7 -22.7 22.7 -22.7 22.7 67.0 -28.8 28.8 -23.8 23.8 -23.8 23.8 66.0 -29.9 29.9 -24.9 24.9 -24.9 24.9 65.0 -30.9 30.9 -25.9 25.9 -25.9 25.9 64.0 -32.0 32.0 -27.0 27.0 -27.0 27.0 63.1 -33.0 33.0 -28.0 28.0 -28.0 28.0 63.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 62.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 61.0 -33.0 33.0 -28.0 28.0 -28.0 28.0
-28.0 28.0 60.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 0.0 -33.0 33.0 -28.0 28.0 -28.0 28.0
% FP RPS Trip Full Incore Alarm Out of Core Alarm
ONEI-0400-567 Rev 3 Page 11 of 22 Oconee 2 Cycle 31 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0
(-14.4,107.9) (14.4,107.9) 100.0 M1 = 0.942 M2 = -0.942 Acceptable 4 Pump Operation
(-33.0,90.4) (33.0,90.4)
(-14.4,80.6) (14.4,80.6) 80.0 60.0
(-33.0,63.1) (33.0,63.1)
Acceptable 3 or 4 Pump Operation 40.0 20.0 0.0
-40.0 -30.0 -20.0 -10.0 0.0 10.0 20.0 30.0 40.0 Percent Power Imbalance
ONEI-0400-567 Rev 3 Oconee 2 Cycle 31 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Page 12 of 22 Referred to by TS 3.2.2 and TS 3.3.1 110 -14.4, 107.9 14.4, 107.9 RPS Trip Setpoint RPS Trip Setpoint 100 -13.9, 102.0 14.0, 102.0
-15.2, 100.0
-33.0, 90.4 15.4, 100.0 33.0, 90.4 90
-22.1, 90.0 22.5, 90.0 80 -27.8, 80.0 27.6, 80.0 Labels Correspond to the Backup Incore Alarm Setpoints 70 Percent of Full Power 60 Backup Incore 50 Outcore Incore RPS Trip 40 30 20 10
-33.0, 0.0 -27.8, 0.0 27.6, 0.0 33.0, 0.0 0
-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance
Oconee 2 Cycle 31 ONEI-0400-567 Rev 3 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 Page 13 of 22 110 100 90
-14.4, 80.6 14.4, 80.6 80 RPS Trip Setpoint -13.2, 77.0 RPS Trip Setpoint 13.2, 77.0 70
-33.0, 63.1 33.0, 63.1 Percent of Full Power 60 -27.8, 63.2 27.6, 63.4 Labels Correspond to the Backup Incore Alarm Setpoints 50 40 Backup Incore Outcore 30 Incore RPS Trip 20 10
-33.0, 0.0 -27.8, 0.0 27.6, 0.0 33.0, 0.0 0
-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance
ONEI-0400-567 Rev 3 Page 14 of 22 Oconee 2 Cycle 31 Operational Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint RI Withdrawal
%FP No Inop Rod 1 Inop Rod Setpoint 4 Pumps 102.0 263.5 283.4 300 100.0 261.5 281.5 300 90.0 251.5 271.9 300 80.0 241.5 262.3 300 50.0 201.5 233.4 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 237.5 285.2 300 75.0 234.8 281.5 300 50.0 201.5 235.2 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300
ONEI-0400-567 Rev 3 Page 15 of 22 Oconee 2 Cycle 31 Shutdown Margin Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint RI Withdrawal
%FP No Inop Rod 1 Inop Rod Setpoint 4 Pumps 102.0 224.6 283.4 300 100.0 221.5 281.5 300 48.0 141.5 231.5 300 13.0 76.5 161.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 227.4 285.2 300 75.0 221.5 281.5 300 48.0 141.5 231.5 300 13.0 76.5 161.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300
ONEI-0400-567 Rev 3 Oconee 2 Cycle 31 Referred to by TS 3.2.1 Page 16 of 22 105 263.5, 102.0 300.0, 102.0 105 224.6, 102.0 100 100 Control Rod Position Setpoints 221.5, 100.0 261.5, 100.0 95 No Inoperable Rods, 4 Pump Flow, 95 90 BOC to EOC 90 85 251.5, 90.0 85 80 80 241.5, 80.0 75 75 70 70 175.0, 69.8 65 225.0, 67.6 65 Reactor Power, % FP 60 Unacceptable 60 Operation Restricted 55 Operation 55 50 Acceptable 50 201.5, 50.0 141.5, 48.0 Operation 45 195.2, 48.0 45 40 40 125.0, 39.1 175.0, 41.6 35 35 30 30 25 25 125.0, 25.7 20 20 15 76.5, 13.0 15 91.5, 15.0 10 1.5, 3.0 10 75.0, 12.8 5 0.0, 2.8 Group 6 5 16.5, 5.0 0.0, 0.0 5 15 25 35 45 55 65 75 85 95 0 0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 Group 5 Control Rod Position, % WD Group 7
ONEI-0400-567 Rev 3 Oconee 2 Cycle 31 Referred to by TS 3.2.1 Page 17 of 22 105 105 100 100 Control Rod Position Setpoints 95 No Inoperable Rods, 3 Pump Flow, 95 90 BOC to EOC 90 85 85 227.4, 77.0 80 237.5, 77.0 300.0, 77.0 80 225.0, 76.2 75 75 221.5, 75.0 234.8, 75.0 70 70 65 225.0, 67.6 65 Unacceptable Reactor Power, % FP 175.0, 59.3 60 Operation 60 55 55 50 141.5, 48.0 50 201.5, 50.0 Restricted 45 Operation 195.2, 48.0 45 40 125.0, 39.1 40 175.0, 41.6 35 Acceptable 35 Operation 30 30 25 25 125.0, 25.7 20 20 15 76.5, 13.0 15 91.5, 15.0 10 1.5, 3.0 75.0, 12.8 10 0.0, 2.8 Group 6 5 5 16.5, 5.0 5 15 25 35 45 55 65 75 85 95 0 0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 0.0, 0.0 Group 5 Group 7 Control Rod Position, % WD
ONEI-0400-567 Rev 3 Oconee 2 Cycle 31 Page 18 of 22 105 300.0, 102.0 105 283.4, 102.0 100 100 Control Rod Position Setpoints 281.5, 100.0 95 1 Inoperable Rod, 4 Pump Flow, 95 BOC to EOC 90 90 85 85 80 80 75 75 70 70 65 65 Unacceptable Reactor Power, % FP 60 Operation 60 55 55 50 231.5, 48.0 50 Acceptable Operation 45 225.0, 44.8 45 40 40 35 35 30 30 25 25 20 175.0, 19.8 20 15 161.5, 13.0 15 125.0, 8.7 10 76.5, 3.0 10 75.0, 2.82 5 74.8, 2.8 Group 6 5 51.0, 0.0 5 15 25 35 45 55 65 75 85 95 0 0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 Group 5 Control Rod Position, % WD Group 7
ONEI-0400-567 Rev 3 Oconee 2 Cycle 31 Page 19 of 22 105 105 100 100 Control Rod Position Setpoints 95 1 Inoperable Rod, 3 Pump Flow, 95 BOC to EOC 90 90 85 85 80 300.0, 77.0 80 285.2, 77.0 75 281.5, 75.0 75 70 Unacceptable 70 Operation 65 65 Reactor Power, % FP 60 60 55 55 50 231.5, 48.0 50 45 225.0, 44.8 45 Acceptable 40 Operation 40 35 35 30 30 25 25 20 175.0, 19.8 20 15 161.5, 13.0 15 125.0, 8.7 10 76.5, 3.0 10 75.0, 2.82 5 Group 6 5 74.8, 2.8 51.0, 0.0 5 15 25 35 45 55 65 75 85 95 0 0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 Group 5 Group 7 Control Rod Position, % WD
ONEI-0400-567 Rev 3 Page 20 of 22 Oconee 2 Cycle 31 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.
Information provided in this section should not be used in plant procedures.
Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State Transient Maximum Core Power Level, %FP 0 - 30 > 30 0 - 30 > 30 >0 Quadrant Power Tilt, % 10.00 6.16 12.00 9.44 20.00 Variable Low RCS Pressure Protective Limits Referred to by TS 2.1.1 Core Outlet Pressure Reactor Coolant Outlet Temperature, °F psia 3 RCS Pumps 4 RCS Pumps 1800 581.0 578.3 1900 590.0 587.3 2000 598.9 596.3 2100 607.9 605.2 2200 616.9 614.2 2300 625.9 623.2
ONEI-0400-567 Rev 3 Page 21 of 22 Oconee 2 Cycle 31 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1 Not for Plant Use
%FP RPS Operational 4 Pumps 0.0 -35.0 -39.5 80.0 - -39.5 90.0 -35.0 -33.5 100.0 - -25.7 109.4 -14.4 -
109.4 14.4 -
100.0 - 25.9 90.0 35.0 34.0 80.0 - 39.5 0.0 35.0 39.5 3 Pumps 0.0 -35.0 -39.5 62.3 -35.0 -
77.0 - -39.5 81.7 -14.4 -
81.7 14.4 -
77.0 - 39.5 62.3 35.0 -
0.0 35.0 39.5
ONEI-0400-567 Rev 3 Page 22 of 22 Oconee 2 Cycle 31 Rod Index Limits Referred to by TS 3.2.1 Not for Plant Use Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal
%FP Insertion Limit No Inop Rod 1 Inop Rod Limit 4 Pumps 102 262 220 280 300 100 260 - - 300 90 250 - - 300 80 240 - - 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300 3 Pumps 77 236 220 280 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300