ONS-2014-068, Core Operating Limits Report (Colr), Cycle 28, ONEI-0400-70, Revision 36

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

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

Text

Scott L.Batson ENERGY, Vice President Oconee Nuclear Station Duke Energy ONO IVP 17800 RochesterHwy Seneca, SC 29672 o: 864.873.3274 ONS-2014-068 f 864,873. 4208 Scott.Batson@duke-energy.com May 15, 2014 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Site Docket Number 50-287 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 for Oconee Unit 3, Cycle 28, ONEI-0400-70, Revision 36.

If you have any questions, please direct them to Judy Smith at 864-873-4309.

Sincerely, Scott L. Batson Vice President Oconee Nuclear Station Attachment "Piz www.duke-energy.com

U.S. Nuclear Regulatory Commission May 15, 2014 Page 2 xc wlatt: Mr. Victor McCree, Regional Administrator U.S. Nuclear Regulatory Commission, Region II 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

DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO PRIORITY SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 04108/114 OTHERWISE IDENTIFIED BELOW ib ini nt 6rasittai # -"DUK140980068

1) 00813 DOC MGMT EC04T ORIGINAL

2) 00358 ONS REGUL COMPUANCE ON03RC Duke Energy QA CONDITION

• Yes [] No

3) 06700 ONS MANUAL MASTER FILE ON03DM DO(;UMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED LI Yes

4) 06937 R RST CLAIR EC08G IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

REFERENCE NUCLEAR GENERAL OFFICE Duke Energy OCONEE NUCLEAR STATION P.O. Box 1006 Energy Center RETENTION 421734 EC04T Charlotte, N.C. 28201-1006 OCONEE 3 CYCLE 28 CORE OPERATING LIMITS REPORT Recd By I'

Page 1 of 1 Date i4M~!IL(~

DOCUMENT NO 1ACOND REV #/DATE DISTR CODE 1 12'.. 3 4 5 16 7 a 9 10 ill 12 13 14 15 TOltK I 4 ONEI-0400-070 1 036 04/08/14 NOMD-27 X V1 V1i vi REMARKS: DUKE DAVID A BAXTER DOCUMENTS CREATED UNDER EDM-501 ARE EXCLUDED FROM THE EDM-601 PROCESS PER NSD-301, SECTION 2.4. THEREFORE, THE EXEMPTION CODE VICE PRESIDENT OR PIP NUMBER REQUIRED BY EDM-601 IS NOT REQUIRED FOR THIS NUCLEAR ENGINEERING DOCUMENT. BY:

D S ORR DSOfZLA EC08G

ONEI-0400-70 Rev 36 Page 1 of 24 Duke Energy Oconee 3 Cycle 28 Core Operating Limits Report QA Condition I Co-Prepared By. A.L. Lan Date: LU*, -- L/

Co-Prepared By: D.S. Orr Date: y-Reviewed By: L.D. McClain YQ4u1," 1G&W% Date:

Date: L/. '_/.,-/

CDR By: A.R. Bingham Approved By: R.R. St.Clair Date: V/- g-/d

Document No. ) Rev. ONIE[-0400-70 Rev. 36 Date April 2014 Page No. Patne 2 of 24 INSPECTION OF ENGLNEERING INSTRUCTIONS Inspection Waived By: R R St. Claw Date: .!V CATAWBA Inspection Waived MCE (Mechanical & Civil) 0 Inspected By/Date:

RES (Electrical Only) I] Inspected By/Date:

RES (Reactor) El Inspected By/Date:

MOD 0l Inspected By/Date:

Other ( ]

E) Inspected By/Date:

OCONEE Inspection Waived MCE (Mechanical & Civil) 19 Inspected By/Date:

RES (Electrical Only) Inspected By/Date:

RES (Reactor) [] Inspected By/Date:,,q MOD Inspected By/Date:

Other ( ) Inspected By/Date:

MCGUIRLE Inspection Waived MCE (Mechanical & Civil) 1] Inspected By/Date:

RES (Electrical Only) C] Inspected By/Date:

RES (Reactor) [] Inspected By/Date:

MOD E] Inspected By/Date:

Other ( ]

0) Inspected By/Date:

ONEI-0400-70 Rev 36 Page 3 of 24 Oconee 3 Cycle 28 Core Operating Limits Report Insertion Sheet for Revision 36 This revision is not valid until the end of operation for Oconee 3 Cycle 27. 1 Remove these Revision 35 pages Insert these Revision 36 pages 1-33 1-24 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages 1Oconee 3 Cycle 28 revisions below I 36 Apr 2014 1-24 25-33 24 Oconee 3 Cycle 27 revisions below 35 Apr 2014 1-33 33 34 Apr 2013 1-33 - 33 33 Oct 2012 1-33 - 33 32 May 2012 1-33 - 33 I conee 3 Cycle 26 revisions below 31 Oct 2010 1-33 - 33 Oconee 3 Cycle 25 revisions below 30 May 2009 1-33 33 29 May 2009 1-33 33 28 Apr2009 1-33 33 Oconee 3 Cycle 24 revisions below 27 Mar 2009 1 -33 33 26 Nov 2007 1-33 33 25 Nov 2007 1-33 33 FOconee 3 Cycle 23 revisions below 24 May 2006 1-33 - 33 J

Oconee 3 Cycle 22 revisions below 2223 No Mar ar20202006 1 - 4, 6, 151 -"16.33 21, 27, 31 - 33333 22 Mar 2005 1-5 - 33 21 Nov 2004 1-33 - 33

ONEI-0400-70 Rev 36 Page 4 of 24 Oconee 3 Cycle 28 Table Of Contents Section

..... 1.0 Error Adlusted m Core Operatina m mmLimits NRC Approved Methodology TS Number Technical Specification Reference X 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 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 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 3.1.12 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 Operatina Limits - Not Error Adlusted (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 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-0400-70 Rev 36 Page 5 of 24 Oconee 3 Cycle 28 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 03C28 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 11. The RPS protective limits and maximum allowable setpoints are documented in References 12 through 14. These limits are validated for use in 03C28 by References 15 through 17. The 03C28 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, radial local peaking (Fth) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB)

Tavg reduction for up to 10°F provided 4 RCPs are in operation and Tavg does not decrease below 569 0F.

The error adjusted core operating limits included in Section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 03C28 reload core.

1.1 References

1. Oconee Nuclear Design Methodology Using CASMO-4 / SIMULATE-3, DPC-NE-1006-PA, SE dated August 2, 2011.

2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002-A, SE dated July 21, 2011.

3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001-A, SE dated July 21, 2011.

4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003-PA, SE dated July 21, 2011.

5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, SE dated October 29, 2008.

6. Fuel Mechanical Reload Analysis Methodology Using TACO3 and GDTACO, DPC-NE-2008-PA, SE dated July 21, 2011.

7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, SE dated July 21, 2011.

8. Thermal Hydraulic Transient Analysis Methodology, DPC-NE-3000-PA, SE dated July 21, 2011.

9. BAW-1 01 92P-A, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model 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-10227P-A, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, Rev. 1, June 2003 (SER to BAW-10186P-A dated June 18, 2003).

12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low 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. 03C28 Maneuvering Analysis, OSC-11093, Revision 2, April 2014.

16. 03C28 Specific DNB Evaluation, OSC-1 1096, Revision 0, October 2013.

17. 03C28 Reload Safety Evaluation, OSC-11123, Revision 0, April 2013.

ONEI-0400-70 Rev 36 Page 6 of 24 Oconee 3 Cycle 28 Miscellaneous Setpoints 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.

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% Al/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 I °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 20 F unc)

Referred to by TS 3.4.1. ATc, °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 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-0400-70 Rev 36 Page 7 of 24 Oconee 3 Cycle 28 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 to 644 292 +/-5 300 30 40 644 to EOC 292 15 300 100 100 Quadrant Power Tilt Setpoints Steady State Transient Maximum Core Power Level, %FP 0-30 > 30 0-30 > 30 >0 Full Incore 7.61 3.50 9.40 7.11 16.55 Out of Core 6.09 2.35 7.72 5.63 14.22 Backup Incore 3.87 2.25 4.81 3.63 10.07 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-0400-70 Rev 36 Page 8 of 24 Oconee 3 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 co

(/L

,d 2100 Acceptable VOperation P =11.14 *Tout - 4706 0

2000 Unacceptable 1900 Operation P = 1800 psig 1800 T = 584 °F 1700 1 I i 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, OF

Rev 36 24 Page 9 of ONEI-0400-70 3 Cycle 28 S Oconee byTS 2.1.1 and TS Table 3.3.1-1 to Referred Limits Imbalance RPS Power Allowable  % Imbalance Maximum

% FP

-35.0 0.0 -35.0 90.0 -14.4 4 Pumps 14A4 109.4 Pmrax => 109.4 35.0 Pmax => 90.0 35.0 0.0

-35.0 0.0 -35.0 62.3 -14.4 3 Pumps 14.4 81.7 Pmax => 81.7 35.0 Pmax => 62.3 35.0 0.0

ONEI-0400-70 Rev 36 Page 10 of 24 Oconee 3 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 -27.5 -27.8 80.0 -28.0 -27.5 -27.8 90.0 -28.0 -27.5 -27.8 100.0 -17.7 -17.7 -17.7 102.0 -15.6 -15.6 -15.6 102.0 15.6 11.2 11.8 100.0 17.7 14.2 14.7 90.0 28.0 28.0 28.0 80.0 28.0 28.0 28.0 0.0 28.0 28.0 28.0 3 Pumps 0.0 -28.0 -27.5 -27.8 63.1 -28.0 -

63.3 - - -27.8 63.5 - -27.5 -

77.0 -13.2 -13.2 -13.2 77.0 13.2 13.2 13.2 63.1 - 28.0 -

63.1 - - 28.0 63.1 28.0 - -

0.0 28.0 28.0 28.0 Referred to by TS 3.2.2 ,

ONEI-0400-70 Rev 36 Page 11 of 24 Oconee 3 Cycle 28 RPS / Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC Referred to byTS 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 -17.5 17.5 104.0 -18.5 18.5 103.0 -19.6 19.6 102.0 -20.7 20.7 -15.6 15.6 -15.6 11.8 101.0 -21.7 21.7 -16.7 16.7 -16.7 13.3 100.0 -22.8 22.8 -17.7 17.7 -17.7 14.7 99.0 -23.9 23.9 -18.7 18.7 -18.7 16.0 98.0 -24.9 24.9 -19.8 19.8 -19.7 17.4 97.0 -26.0 26.0 -20.8 20.8 -20.7 18.7 96.0 -27.0 27.0 -21.8 21.8 -21.7 20.0 95.0 -28.1 28.1 -22.9 22.9 -22.8 21.4 94.0 -29.2 29.2 -23.9 23.9 -23.8 22.7 93.0 -30.2 30.2 -24.9 24.9 -24.8 24.0

-25.8 92.0 -31.3 31.3 -25.9 25.9 25.3 91.0 -32.3 32.3 -27.0 27.0 -26.8 26.7 90.4 -33.0 33.0 -27.6 27.6 -27.4 27.5 90.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 89.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 88.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 87.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 86.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 85.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 84.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 83.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 82.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 81.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 80.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 0.0 -33.0 33.0 -28.0 28.0 -27.8 28.0

% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-70 Rev 36 Page 12 of 24 Oconee 3 Cycle 28 RPS I 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 -16.1 16.1 78.0 -17.1 17.1 77.0 -18.2 18.2 -13.2 13.2 -13.2 13.2 76.0 -19.3 19.3 -14.3 14.3 -14.3 14.3 75.0 -20.3 20.3 -15.3 15.3 -15.3 15.3 74.0 -21.4 21.4 -16.4 16.4 -16.4 16.4 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 -24.6 24.6 -19.6 19.6 -19.6 19.6 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 -27.8 27.8 -22.8 22.8 -22.8 22.8 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 63.3 -32.8 32.8 -27.8 27.8 -27.8 27.8 63.1 -33.0 33.0 -28.0 28.0 -27.8 28.0 63.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 62.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 61.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 60.0 -33.0 33.0 -28.0 28.0 -27.8 28.0 0.0 -33.0 33.0 -28.0 28.0 -27.8 28.0

% FP I RPS Trip Full Incore Alarm I Out of Core Alarm :

ONEI-0400-70 Rev 36 Page 13 of 24 Oconee 3 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

(-14.4,107.9) (14.4,107.9,1 100.0 M1 = 0.942 M2 =-0.942 Acceptable 4 Pump Operation

(-33.0,90.4) (33.0,90.4)

(14.4,80.6)

(A 4.4,80.6 OU.U

(-33.0,63.1) 60.0 I, (33.0,63.1) 1 Acceptable 3 or 4 Pump Operation 40.0 20.0 L% 4*,

I , I I = , L ff

-40.0 -30.0 -20.0 -10.0 0.0 10.0 20.0 30.0 40.0 Percent Power Imbalance

ONEI-0400-70 Rev 36 Oconee 3 Cycle 28 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Page 14 of 24 Referred to by TS 3.2.2 and TS 3.3.1 110 -14.4, 107.9144.107.9 wr I a I T I I -I I RPýpri Seipoint' RPS Trip Setpoint 100 102.0 ii2AQ20M

-- 17.7. 100.O E E 14.2. 100.0 - liii 0.

-33.0, 90.4 iiILZi 90

-27.5,90.0 28.0. 9.

80 -27.5. 80.0 28.0.80.01 Labels Correspond to the Backup Incore Alar Stponts 70 0

a. 60 U-u.4 i*-_e- Backup Incom 50

-- , Outcore

4) - incore n

40 RPS Trip 30 20 10

-ý3390-oo 0

-40 I*E

-35 i*U-~

-30

-27.5, 0.0

-25 -20 -15 -10 -5 0 5 10 15 20 28.0.0.0 Minkno-6 25 30 33.0, 0.0 M -

35 I

40 Percent Axial Imbalance

Oconee 3 Cycle 28 Rev 36 Imbalance Setpoints for 3 Pump Operation, BOC to EOCONE'40-70 Referred to by TS 3.2.2 and TS 3.3.1 Page 15 of 24 110 100 90 14.4, 80.6-80

- RPS Trip Setpoint I _-132;77.0

RPS Trip Setpoint ý

.13 77.0 70

0. t -33.0. 63.1 ý.1 I

0. 60 1-27.5, 63.1 28.0.63.1 LL. ibels Correspond to the Backup Incore Alarm Setpoints 0

50 CD Q.

40

-a-Backup Iiicore 30 -Incore

-oRPS Trip 20 10 0 I

-40

-33.0, 0.0I

-35 -30

-27.5, 0.0

-25 -20 -15 -10 -5 0 5 10 15 20 28.0. 0.0 :

25 30 35 I

- 33.0,0.0 -T-:

40 Percent Axial Imbalance

ONEI-0400-70 Rev 36 Page 16 of 24 Oconee 3 Cycle 28 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-0400-70 Rev 36 Page 17 of 24 Oconee 3 Cycle 28 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-0400-70 Rev 36 I Oconee 3 Cycle 28 1 Referred to by TS 3.2.1 Page 18 of 24 105 r 105 HI il lit 224.6, 102.0 263.5, 102.0 .300.0,10.

100 Control Rod Position Setpoints s r: 221.5,100.0 100

....... No Inoperable Rods, 4 Pump Flow,.. 10...o 95 95 BOC to EOCMilI1 ,

90 90 251.5,.90.0 85 85 80 80 loo oll",241.5. 80.0 75 75 70 .1:175.0. 69.8 1 1 i.. 70 65 65 (L

U- 60 60 Operation Restricted L: 55 55 OperationOeraio 0L 50 L. 50 I-48.02 48.0 (D 45 45 w

40 125.0, 39.1 175.0,.41.6 40 35 35 30 30 25 25 20 20 0.0 ,... . .. .... u 8 ... ....

15 . ..... .... 15 25 55 75 .. ... .. 15 10 :12 5 ., ..

10 5 5 0

9 0 "..V' 20 30 40 50 60 70 80 90 100o1 10 10 20 30 40 50 60 70 80 90 1001 I Group 5 1 Control Rod Position, % WD I Grup I ontrl Rd Psitin, WDGroup 7

ONEI-0400-70 Rev 36 I Oconee 3 Cycle 28 1 Referred to by TS 3.2.1 Page 19 of 24 105 105 100 100 IU Control Rod Position Setpoints 95 No Inoperable Rods, 3 Pump Flow, 95 90 I BOC to EOC 90 85 85 80 227.4, 77.4 , 77.o 80 237.5. 77.0 225.0.47.

75 75 1.5. 75.0 234~8. 75.0 J 70 70 65 225.0.67.6 65 Unacceptable 175.0. 59.3 a- 60 Operation 60 0

0c 55 50 45 I 141.5.48.

Restricted Operation 1111201.5. 50.0 195.2,.48.0 55 50 45 cc 40 125.0. 40 175.0,41.6 35 Acceptable 35 30 Ooeration I 30 25 25 125.0,25.7 20 20 15 7 .5,13.0 .......... 15

'* WNW 10 If 75.0,12.8 10 1.5,1 3 * ...........

5 roup 6 5

.... 16.5. 5.0 UII MZ5 ::'l 5 25 35 45 55 65 75 85 95 0 0 10 10 20 30 40 50 60 70 80 90 1001 I 10 10 20 30 40 50 60 70 80 90 1001l 0.0,.0.0 I Group 7j.

I Group 5 Control Rod Position, % WD

0 I ONEI-0400-70 Rev 36 10 I Oconee 3 Cycle 28 I Referred to byTS 3.2.1 1300.0 Page 20 of 24 102.0 10!5-

......... .... 2 3.4 102.0 10'0 Control Rod Position Setpoints 2-1.5 . 10 95 1 Inoperable Rod, 4 Pump Flow, 95 BOC to EOC........

0 90 8

5 85 8 -0 80 7 .'5 75 7'0 70 615 35 ~Unacceptable 6 65 10 Operation 60

a. 55 55

• 10 SO I 231.5, 48.0 Acceptable 50 5

~Operation m 4 225.044.8 ..... 45 I0 40 3

15 35

.0 30 25 25 lailillillini181.5 1113.011111 2 05.0, 20 15 74., 15 10 . 65 .0 .. .. f.i .10

.82 5 Ol ii

[i t ' ii i n 51.o,5o 15

. . . .. . 25

. .. . . 30

. , . . .. . . '. . .. . . .. . .65

. .....75

. . . . ..85

. . . .......... 0 10 10 20 30 40 50 60 70 80 90 100 10 10 20 30 40 50 60 70 80 90 100 1 SIGroup 5 m I ru Control Rod Position, % WD roup "7

I ONEI-0400-70 Rev 36 I Oconee 3 Cycle 28 I Referred to byTS 3.2.1 Panp 91 nf 24 105 105 I

100 100 Control Rod Position Setpoints 95 I Inoperable Rod, 3 Pump Flow, 95 BOC to EOC 90 90 85 85 80 SII I I IN*r= 300.0. 77.0 80 JI 285.2, 77.0 t 11111 1 i1 11 J +HI24I444f1m 75 281.55,75.0- 75 70 Unacceptable 70 Operation 65 65 a.

UL60 60 55 55 50 2315 48.0 50 45 :zr ~ raw C 22. U.44.8 5 45 40 Acceptable Operation I 40 35 35 30 30 25 25 20 20 175.0,113.0 15 15 125.0,8.7 10 76.5. 3.0 10 75.0,2.82 5 HH 11 11'194

_U1111 Group 6 r5 51.00.0 1 25 35 45 55 65 75 85 95 n

-0 Illl[llllWI]lllllllW*lIllllrJLL, 10 10 20 30 40 50 60 70 80 90 100 10 10 20 30 40 50 60 70 80 90 100 I I Group 5 1 Control Rod Position, % WD I Group 71

ONEI-0400-70 Rev 36 Page 22 of 24 Oconee 3 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.

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 5.40 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, OF psla 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-0400-70 Rev 36 Page 23 of 24 Oconee 3 Cycle 28 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1

%FP RPS Operational 4 Pumps 0.0 -35.0 -39.3 80.0 -39.3 90.0 -35.0 -39.3 100.0 -28.4 109.4 -14.4 109.4 14.4 100.0 24.7 90.0 35.0 39.5 80.0 39.5 0.0 35.0 39.5 3 Pumps 0.0 -35.0 -39.3 62.3 -35.0 77.0 -39.3 81.7 -14.4 81.7 14.4 77.0 39.5 62.3 35.0 0.0 35.0 39.5

ONEI-0400-70 Rev 36 Page 24 of 24 Oconee 3 Cycle 28 Rod Index Limits Referred to by TS 3.2.1 I' ~

Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal

%FP Insertion Limit No Inop Rod I 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