Text

Submittal of Core Operating Limits Report (COLR)
	ML15026A739
Person / Time
Site:	Oconee
Issue date:	01/22/2015
From:	Batson S; Duke Energy Carolinas
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	ONS-2015-004
	Download: ML15026A739 (87)
	v • d • e

@DUKE ENERGY.

Scott L. Batson Vice President Oconee Nuclear Station Duke Energy ONOIVP 1 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3274 f 864.873.4208 Scott.Batson@duke-energy.com ONS-2015-004 January 22, 2015 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001

Subject:

Duke Energy Carolinas, LLC Oconee Nuclear Site Docket Number 50-269, 50-270 and 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 (COLR) for Oconee Unit 1, Cycle 29, ONEI-0400-50, Revision 36, COLR for Oconee Unit 2, Cycle 27, ONEI-0400-51 Revision 34, and COLR for Oconee Unit 3, Cycle 28, ONEI-0400-70, Revision 37.

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 4oo0(

www.duke-energy.com

U. S. Nuclear Regulatory Commission January 22, 2015 Page 2 bc w/att:

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, Senior Project Manager (ONS)

(By electronic mail only)

U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 11555 Rockville Pike Mail Stop O-8G9A Rockville, MD 20852 Mr. Jeffrey A. Whited, (Acting) Project Manager (ONS)

(By electronic mail only)

U. S. Nuclear Regulatory Commission Office of Nuclear Reactor Regulation 11555 Rockville Pike Mail Stop O-8B1A Rockville, MD 20852 Mr. Eddy Crowe Senior Resident Inspector Oconee Nuclear Site

PRIORITY SuperRush DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERW IDENTIFIED BELOW

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3) 0ON 1 1 MASTER LE ON3OM

4) 06W3"RRST

.AIREC08G FOR INFORMATION ONLY Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION RETENTION 421734 OCONEE 1 CYCLE 29 CORE OPERATING LIMITS REPORT Page 1 of I Date:

12119114 Document Transmittal #:

DUK143530013 QA CONDITION

I Yes [-]No OTHER ACKNOWLEDGEMENT REQUIRED [] Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

Duke Energy P.O. Box 1006 Energy Center EC04T Charlotte, N.C.

28201-1006

~OJ~O\\A~zJ Recd By Date

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I DOCUMENT NO QACOND REV #1 DATE DITR CODE 1 & 3 4

5 6

7 8

9 10 11 12 13 14 15 TOTAL 1

ONEI-0400-050 1

036 12/19/14 NOMD-27 X

W v1 V1 3

J.LLJ.ALLA1L REMARKS:

DUKE DOCUMENTS CREATED UNDER EDM-501 ARE EXCLUDED FROM THE EDM-601 PROCESS PER NSD-301, SECTION 2.4. THEREFORE, THE EXEMPTION CODE OR PIP NUMBER REQUIRED BY EDM-601 IS NOT REQUIRED FOR THIS DOCUMENT.

DAVID C. CULP GENERAL MANAGER NUCLEAR ENGINEERING BY:

D S ORR DSOZL.A EC08G

ONEI-0400-50 Rev 36 Page 1 of 24 Duke Energy Oconee I Cycle 29 Core Operating Limits Report QA Condition I lib Date:Iq Prepared By: D.S. Orr Reviewed By. L.C. James II

=,,

CDR By: N/A Approved By: R.R. St.Clair Date:-

Date:

l

) Cc2Oil

ONEI-0400-50 Rev 36 Page 2 of 24 Engineering Instruction Inspection Waiver:

In accordance with EDM 130, this El Inspection has been waived by OS-105.00.

ONEI-0400-50 Rev 36 Page 3 of 24 Oconee 1 Cycle 29 Core Operating Limits Report Insertion Sheet for Revision 36 Implement this COLR revision on or before January 9, 2015 Remove these Revision 35 pages 1 -24 Insert these Revision 36 pages 1 -24 Revision Log Pages Effective Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 1 Cyle 29 revisions below 36 Dec 2014 1-24 24 35 Oct 2014 1-24 25-33 24 Oconee 1 Cycle 28 revisions below I

34 Apr 2013 1-33 33 33 Oct 2012 1-33 33 1Oconee I Cycle 27 revisions below 1

32 Mar 2011 1 -33 33 I

Oconee I Cycle 26 revisions below i

31 Nov 2009 1-33 33 30 Nov 2009 1-33 33 29 Nov 2009 1-33 33 28 Sep 2009 1-33 33 1 27 Ap 2008 1-33 33 lOconee I Cycle 24 revisions below 26 Oct 2006 1-33 33 lOconee I Cycle 23 revisions below L

25 Apr2005 1-33 33

ONEI-0400-50 Rev 36 Page 4. of 24 Oconee 1 Cycle 29 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 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 Selpoints 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 (OPT) 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 Setpolnts 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 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, Variabte 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 (OPT) 1, 3, 7. 9,10 Quadrant Power Tilt Limits

ONEI-0400-50 Rev 36 Page 5 of 24 Oconee 1 Cycle 29 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for OIC29 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 O1C29 by References 15 through 17. The 01C29 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 10°F provided 4 RCPs are in operation and Tavg does not decrease below 5690F.

The error adjusted core operating limits included in Section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 01 C29 reload core.

1.1 References

1. Oconee Nuclear Design Methodology Using CASMO-4 / 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.

6. 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-1 01 64P-A, Rev. 4 and 6, RELAP5IMOD2-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. 01C29 Maneuvering Analysis, OSC-11268, Revision 2, December 2014.

16. OIC29 Specific DNB Evaluation, OSC-1 1277, Revision 0, July 2014.

.17. 01 C29 Reload Safety Evaluation, OSC-1 1283, Revision 1, December 2014.

ONEI-0400-50 Rev 36 Page 6 of 24 Oconee 1 Cycle 29 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%,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.

Ap / °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 20F unc)

Referred to by TS 3.4.1.

ATc, OF 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 > 109.5 %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% 15% 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-0400-50 Rev 36 Page 7 of 24 Oconee 1 Cycle 29 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 to 615 292 +/- 5 300 30 40 615 to EOC 292 +/- 5 300 100 100 Quadrant Power Tilt Setpoints Steady State Transient Core Power Level, %FP 0-30

> 30 0-30

> 30 Full Incore 7.61 3.50 9.40 7.11 Out of Core 6.09 2.35 7.72 5.63 Backup Incore 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 byTS 3.3.1 (SR 3.3.1.3).

ONEI-0400-50 Rev 36 Page 8 of 24 Oconee I Cycle 29 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P

2355 psig T 618F 2300 2200 2100 Acceptable Operation L.

P = 11.14 Tout - 4706 2000 0

Unacceptable 1900 Operation P = 1800 psig 1800 T:= 584 *F 1700 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, °F

ONEI-0400-50 Rev 36 Page 9 of 24 Oconee I Cycle 29 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 -->

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-0400-50 Rev 36 Page 10 of 24 Oconee 1 Cycle 29 Operational Power Imbalance Setpoints Referred to by TS 3.2.2

%FP 4 Pumps 0.0 80.0 90.0 100.0 102.0 102.0 100.0 90.0 80.0 0.0 3 Pumps 0.0 63.1 64.1.

64.6 77.0 77.0 64.5 63.8 63.1 0.0 Full Incore

-28.0

-17.7

-15.6 15.6 17.7 28.0 28.0 28.0

-28.0

-28.0 Backup Incore

-26.4

-25.0

-17.7

-15.6 11.6 13.6 23.7 26.5 26.5 Out of Core

-26.9

-25.3

-17.7

-15.6 12.2 14.2 24.2 27.2 27.2

-26.4

-26.9

-26.4

-13.2

-13.2 13.2 13.2 26.5

-13.2 13.2 27.2 28.0 28.0 26.5 27.2 Referred to by TS 3.2.2

ONEI-0400-50 Rev 36 Page 11 of 24 Oconee I Cycle 29 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 107.9 106.0 105.0 104.0 103.0 102.0 101.0 100.0 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 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 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

-18.5

-19.2

-20.0

-20.7

-21.5

-22.3

-23.0

-23.8

-24.5

-25.0

-25.3

-25.5

-25.6

-25.8

-25.9

-26.1

-26.3

-26.4

-26.6

-26.7

-26.9

-26.9 12.2 13.2 14.2 15.2 16.2 17.2 18.2 19.2 20.2 21.2 22.2 23.2 23.8 24.2 24.5 24.8 25.1 25.4 25.7 26.0 26.3 26.6 26.9 27.2 27.2

% FP RPS Trip 1

Full Incore Alarm Out of Core Alarm ONEI-0400-50 Rev 36 Page 12 of 24 Oconee 1 Cycle 29 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 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 64.1 64.0 63.8 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

-31.9

-32.0

-32.2

-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 31.9 32.0 32.2 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

-26.9

-27.0

-27.2

-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 26.9 27.0 27.2 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

-26.9

-26.9 13.2 14.2 15.2 16.2 17.2 18.2 19.2 20.2 21.2 22.2 23.2 24.2 25.3 26.2 26.3 27.2 27.2 27.2 27.2 27.2 27.2 27.2

-33.0 28.0

% FP I

RPS Trip Full Incore Alarm

_Out of Core Alarm ONEI-0400-50 Rev 36 Page 13 of 24 Oconee I Cycle 29 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP

-40.0

-30.0

-20.0

-10.0 0.0 10.0 20.0 30.0 Percent Power Imbalance 40.0

Oconee I Cycle 29 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 4.4 107.9 14.4, 107.9 110 100 1

1. -:

ONEI-0400-50 Rev 36 Page 14 of 24 RPS Trip Setpoint 33090.4 RPS Trip Setpoint:

-33.0.90.4

-17.7. 100.0 11.6.

13.6, 100.0 90 80 5.0,90.0

.7, 90.0 8W.0 -A Labels Correspond to the Backup Incore Alarm Setpoints:

70 C-60 u.

50 a) 40

-*-Backup Incore

-mb-Outcore nwore

=RPS Urp 30 20 10 E.-ý3-9. 9-9

-26.4, 0.0 26.5.0.0 1

ý 31.o, o4o a

0 -40

-35

-30

-25

-20

-15

-10

-5 0

5 Percent Axial Imbalance 10 15 20 25 30 35 40

Oconee I Cycle 29 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 110 100 90 80 70 60 50 ONEI-0400-50 Rev 36 Page 15 of 24 RSTrip Setpoint

-14.4.80.6 RPS'Trip Setpoint

ý -13.2.77.0 3.2 l77.0 IL w,,

0 0'-

a)2 if I -33.0. 63.1.

63.1

t :1

==

-26.4. 64.8

. 64_A I LU LIIM 40 30 20 10 Backup Incore Alarm SetPo~i~n."

-,-e-Backup Incore H-!

,-17f-,I--

Outcor

,--Inxore RPS Tdp I

-33.0, 0.0

-26.4. 0.0 26.5,0.01 r33.0o..0o I 0

-40

-35

-30

-25

-20

-15

-10

-5 0

5 Percent Axial Imbalance 10 15 20 25 30 35 40

ONEI-0400-50 Rev 36 Page 16 of 24 Oconee I Cycle 29 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-0400-50 Rev 36 Page 17 of 24 Oconee I Cycle 29 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

0 I

Oconee I Cycle 29 1

ONEI-0400-50 Rev 36 Page 18 of 24 Referred to by TS 3.2.1 105 100 95 90 85 80 75 70 65 a."

60 L:*

55 50 35 o 45.

m

35 30 25 20 15 10 5

0J 224.6, 102.0263.5,.102..0.

0.

Control Rod Position Setpoints 221.5. 100.02 10.

No Inoperable Rods, 4 Pump Flow, BOC to EOC II A

251.5, 90.0 241.5,8.0 175.0. 69.8 Operation esrced 201.5, 50.0

141.5,.48.0 prto 195.2, 48.0

125.0, 39.1 175.0. 41.6 Itiif 125.0 25.7 5..C----

15 25 35 45 55 165 75 85 9

I" 105 100 95 90 85 80 75 70 65 60 55 so 45 40 35 30 25 20 15 10 5

U 1U zU 3U 4U b50 6U (U

5U 0U 1UUI

[U 1U 2U FGroup 5 CnrlRdPsto,%W I

Control Rod Position, % W D

.u 4qU ou Du I

u OU Fu IuuI

I Oconee I Cycle 29 1 Referred to by TS 3.2.1 ONEI-0400-50 Rev 36 Page 19 of 24 ic 1.

.4 10 0

3 2

2 81 1

m 351 30 1

Control Rod Position Setpoints, No Inoperable Rods, 3 Pump Flow, g

90 BOC to EOC 221.5.75.0 75.0 10 7

15 6

Unacceptable 175.059.3 E0Operation

)0 141.5. 480 015.5, 0.0 5

Restricted

$5 0prto 2 8.

4 440 125.0,3.1 4

.0,41.6 5

Acceptable 3

0 Operation 3

5 2

.0 25.7 2

0 11 5 0.0.2.8 Group 6 5..1MNM 0,.

5 15

.25 35 45 55 65 75 85 95 05 00

'5

'0

'5 0

5 0

10 10 20 30 40 50 60 70 80 90 100 1 10 10 20 30 40 50 60 70 80 90 1Q01 0.0. 0.0 I Group 5 Control Rod Position, % WD

[-Group-]

0 0

ONEI-0400-50 Rev 38 Page 20 of 24 I

I I

Oconee 1 Cycle 29 I

Referred to by TS 3.2.1 I1 IL m 4 0

4 3

2 2

0 6 M " U M M M I 4 3 0.0, 1 0 2.0 00 Control Rod Position Setpoints 281.5.100.0 95 1 Inoperable Rod,-4 Pump Flow, H: i BOC to EOC

)0 8U5 F5 70 15 Unacceptable 60 Operation 5

0 231.5. 48.0 Acceptable

5 Operation 10 5

30 0

175.0,19.8 5

74.8, 2.8 5

15 25 35 45 55 65 75 85 95 0._

105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

0 0

10 20 30 40 50 60 70 80 90 100 1

I0 10 20 30 40 50 60 70 80 90 1001 JGroup 5 Coto o osto.%W B

Control Rod Position, % WD GrouP 7

Oconee 1 Cycle Z9ý Referred to by TS 3.2.1 ONEI-0400-50 Rev 36 105 100 95 90 85 80 75 70 65 Q-u-60) 55 a

m* 45 (D

40 35 3

25 20 15 10 5

01 Control Rod Position Setpoints U

Inoperable Rod, 3 Pump Flow,n BOC to EOC 7.6 3 125

...0 8 2852. 77.0

-2 11;111111MI 75.0.275.0 Unacceptable Operation 225.07244.8 Acceptable Operation i 175.0, 19.81 31 161.51.0 76.5 3.0 125.0. &7

.1....

G ro u p 6

.... !.o:o~... 5 s

5 3 45 55 ss7 85 95 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

n 10 20 30 40 50 60 70 80 90 100 I Group 5 1 r,,,

0 10 20 30 40 50 60 70 80 90 100 trol Rod Position, % WD LGoup 7 1

ONEI-0400-50 Rev 36 Page 22 of 24 Oconee 1 Cycle 29 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 "a r A,

Core Power Level, Quadrant Power T Core Out 1

1 2

2 2

2

(

%FP C

lit, %

1 Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State T

1-30

> 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, OF Isia 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-0400-50 Rev 36 Page 23 of 24 Oconee I Cycle 29 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1 j Not for Plant Use 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

-14.4 14.4 35.0 35.0

-35.0

-14.4 14.4 35.0 35.0

-38.2

-36.9

-28.4 24.1 35.6 38.6 38.6

-38.2

-38.2 38.6 38.6

ONEI-0400-50 Rev 36 Page 24 of 24 Oconee I Cycle 29 Rod Index Limits Referred to by TS 3.2.1 Not P

I.".,,

Operational RI Shutdown Margin RI Insertion Limit

%FP Insertion Limit No Inop Rod I 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

280 230 160 75 280 230 160 75 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300

DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO SuperRush THE TRANSMITTN. SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW

1) 00613 DOC MGMT ECO4T ORIGINAL 3)N500ONS MANUIAL MASTER FILE ON030M

4) 06937 RIRST LAIRE08G FOR INFORMATION ONLY

. Duke Energy DOCUMENT TRANSMITTAL FORM REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION RETENTION 421734 OCONEE 2 CYCLE 27 CORE OPERATING LIMITS REPORT Page 1 of I Date:

12119114 Document Transmittal #:

DUK143530014 GA CONDITION I

Yes [I No OTHER ACKNXOLEDGlEENT REQUIRED

-I Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED. PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:

Duke Energy P.O. Box 1006 Energy Center EC04T Charlotte, N.C.

28201-1006 Reed By

)1<D%-ý "O4aj\\,'

Date I

I' t

I DOCUMENT NO QA COND REV

DATE DISrR CODE 1

& 13 4 15 16 7

a 9

10 11 12 113 114 115 1TOTAL I

+

ONEI-0400-051 I

034 12/19/14 NOMD-27 K

VI1 3

I ___________________ I _____________________

I I ___________________

REMARKS:

DUKE DOCUMENTS CREATED UNDER EDM-501 ARE EXCLUDED FROM THE EDM-601 PROCESS PER NSD-301, SECTION 2.4. THEREFORE, THE EXEMPTION CODE OR PIP NUMBER REQUIRED BY EDM-601 IS NOT REQUIRED FOR THIS DOCUMENT.

DAVID C. CULP GENERAL MANAGER NUCLEAR ENGINEERING BY:

D S ORR DSO/Z.A EC08G

ONEI-0400-51 Rev 34 Page 1 of 34 Duke Energy Oconee 2 Cycle 27 Core Operating Limits Report QA Condition I Prepared By: L. C. James II Reviewed By: L. D. McClain ý P,,wu 904 Date:,ZW2) 4.

Date:

Dec /o4 CDR By: N/A Approved By: R.R. St.Clair Date:

Date: 19 L) e o

/01

ONEI-0400-51 Rev 34 Page 2 of 34 Engineering Instruction Inspection Waiver, In accordance with EDM 130, this El Inspection has been waived by OS-105.00.

ONEI-0400-51 Rev 34 Page 3 of 34 Oconee 2 Cycle 27 Core Operating Limits Report Insertion Sheet for Revision 34 Implement the COLR revision on or before January 9, 2015.

Remove these Revision 33 pages Insert these Revision 34 pages 1-34 1-34 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 2 Cycle 27 revisions below 34 Dec 2014 1-34 34 33 Oct 2013 1-33 34 34 Oconee 2 Cycle 26 revisions below 32 Apr 2013 1-33 33 31 Oct 2011 1-33 33 I conee 2 Cycle 25 revisions below 30 Apr 2010 1-33 33 Oconee 2 Cycle 24 revisions below 29 Feb 2010 1-33 33 28 Nov 2008 1-33 33

'Oconee 2 Cycle 23 revisions below 27 May 2008 1 -33 33 26 Mar 2007 1-33 33 10conee 2 Cycle 22 revisions below 1

25 Oct 2005 1 -33

-33 O~conee 2 Cycle 21 revisions below 24 Aug 2005 1-4,6 33 23 Mar 2005 1-5 33 22 Dec 2004 1-3,30 33 21 Apr2004 1-33 33 Oconee 2 Cycle 20 revisions below 20 Feb 2004 1-3,5 33 19 Nov 2003 1-4,8-10,12-13,29 la 33 18 Oct 2002 1-3,14,16,24,30 32 17 Oct 2002 1-31 32 32

ONEI-0400-51 Rev 34 Page 4 of 34 Oconee 2 Cycle 27 Technical Specification/NRC Approved Methodology Cross Reference Section 1.0 Error Adjusted Core Operatina 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 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 OPT 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 Operatina 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 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 (OPT) 1, 3, 7, 9, 10 Quadrant Power Tilt Limits

ONEI-0400-51 Rev 34 Page 5 of 34 Oconee 2 Cycle 27 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C27 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 02C27 by References 15 through 17. The 02C27 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 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 02C27 reload core.

1.1 References

1. Oconee Nuclear Design Methodology Using CASMO-41 SIMULATE-3, DPC-NE-1 006-PA, NRC SE dated August 2. 2011.

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

3. Oconee Nuclear Station Reload Design Methodology, NFS-1001-A, NRC SE dated July 21, 2011.

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

5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, Revision 4a, December 2008.

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

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

8. Thermal Hydraulic Transient Analysis Methodology, DPC-NE-3000-PA, NRC 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-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. Digital RPS RCS Pressure & Temperature Trip Function Uncertainties and Variable Low RCS Pressure Safety Limit, OSC-8828, Revision 4, November 2014.

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. 02C27 Maneuvering Analysis, OSC-10936, Revision 3, December 2014.

16. 02C27 Specific DNB Analysis, OSC-10938, Revision 0, May 2013.

17. 02C27 Reload Safety Evaluation, OSC-1 1004, Revision 2, December 2014.

ONEI-0400-51 Rev 34 Page 6 of 34 Oconee 2 Cycle 27 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% 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/ 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 2 2125 pslg DNB parameter for RCS loop average temperature shall be:

Max Loop Tavg (Incl 2°F unc)

Referred to by TS 3.4.1.

ATc, OF 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. Values are expanded by linear interpolation on 3

582.1 581.7 page 34 of this document without Instrument uncertainty.

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% 1 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-0400-51 Rev 34 Page 7 of 34 Oconee 2 Cycle 27 EFPD 0 to 622 622 to EOC Steady State Operating Band Rod Index APSR %WD Min Max Min Max 292 +/- 5 300 30 40 292:+/-15 300 100 100 Core Power Level, %FP Full Incore Out of Core Backup Incore 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-0400-51 Rev 34 Page 8 of 34 Oconee 2 Cycle 27 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P = 2355 psig T =618 °F 2300 2200 0.

al 2100 Acceptable Operation a,

_P

= 11.14"Tout-470 2000 0

a,,

Unacceptable 1900 Operation P = 1800 psig 1800 T = 584 °F 1700 I

I 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, °F

ONEI-0400-51 Rev 34 Page 9 of 34 Oconee 2 Cycle 27 Referred to by TS 2.1.1 and TS Table 3.3.1-1 RPS Power Imbalance Setpoints 4 Pumps

% FP 0.0 90.4 107.9 107.9 90.4 0.0 0.0 63.1 80.6 80.6 63.1 0.0

% Imbalance

-33.0

-14.4 14.4 33.0 33.0

-33.0

-14.4 14.4 33.0 33.0 3 Pumps Maximum Allowable RPS Power Imbalance Limits 4 Pumps 3 Pumps

% FP 0.0 90.0 Pmax =>

109.4 Pmax =>

109.4 90.0 0.0 0.0 62.3 Pmax =>

81.7 Pmax =>

81.7 62.3 0.0

% Imbalance

-35.0

-14.4 14.4 35.0 35.0

-35.0

-14.4 14.4 35.0 35.0

ONEI-0400-51 Rev 34 Page 10 of 34 Oconee 2 Cycle 27 Operational Power Imbalance Setpoints Referred to by TS 3.2.2 4 Pumps 3 Pumps

%FP 0.0 80.0 90.0 100.0 102.0 102.0 100.0 90.0 80.0 0.0 0.0 63.1 63.4 77.0 77.0 63.9 63.1 0.0 Full Incore

-28.0

-17.8

-15.7 15.7 17.8 28.0 28.0 28.0

-28.0

-13.2 13.2 28.0 28.0 Backup Incore

-27.7

-25.2

-17.8

-15.7 13.3 14.7 21.6 27.1 27.1

-27.7

-13.2 13.2 27.1 27.1 Out of Core

-28.0

-25.5

-17.8

-15.7 13.6 15.0 22.0 27.6 27.6

-28.0

-13.2 13.2 27.6 27.6

ONEI-0400-51 Rev 34 Page 11 of 34 Oconee 2 Cycle 27 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 107.9 107.0 106.0 105.0 104.0 103.0 102.0 101.0 100.0 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

-15.4

-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 14.4 15.4 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

-15.7

-16.7

-17.8

-18.8

-19.8

-20.9

-21.9

-22.9

-23.9

-24.9

-26.0

-27.0

-27.6

-28.0

-28.0 15.7 16.7 17.8 18.8 19.8 20.9 21.9 22.9 23.9 24.9 26.0 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

-15.7

-16.7

-17.8

-18.6

-19.3

-20.1

-20.9

-21.6

-22.4

-23.2

-24.0

-24.7

-25.2

-25.5

-25.7

-26.2

-26.5

-26.7

-27.0

-27.2

-27.5

-27.7

-28.0

-28.0 13.6 14.3 15.0 15.7 16.4 17.1 17.8 18.5 19.2 19.9 20.6 21.3 21.7 22.0 22.6 23.1 23.7 24.2 24.8 25.3 25.9 26.4 27.0 27.6 27.6

% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-51 Rev 34 Page 12 of 34 Oconee 2 Cycle 27 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 I

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 64.0 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

-32.0

-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 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

-27.0

-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 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

-24.6

-25.9

-27.0

-28.0

-28.0 13.2 14.2 15.3 16.3 17.3 18.4 19.4 20.4 21.4 22.5 23.5 24.5 25.6 26.6 27.6 27.6 27.6 27.6 27.6 27.6

% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-51 Rev 34 Page 13 of 34 Oconee 2 Cycle 27 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.g)

(14.4,107.9)

M 0M2= -0.942 1

Acceptable 4 Pump Operation

(_

,(33.0,90.4)

(-33.0,90.4) 14 A A CA a%

t* If.-tU.01

-40.0

-30.0

-20.0

-10.0 0.0 10.0 20.0 30.0 Percent Power Imbalance 40.0

Oconee 2 Cycle 27 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-51 Rev 34 Page 14 of 34 110.0 100.0 90.0 80.0 70.0 60.0 50.0 RPS Trip Setpoint RPS Trip Setpoint.

Outcore Alarm I

Full Incore &

Outcore Alarm 0

LL 0

IL U.a-a, Outcore Alarm Curve is inside or on Full Incore Alarm Curve 40.0 30.0 20.0 10.0 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 27 ONEI-0400-51 Rev 34 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Page 15 of 34 Referred to by TS 3.2.2 and TS 3.3.1 110 100 90 80 RPS Trip Setpoint WPS Trip Setpoint 0

L.

0-U.

I-,4) 0l.

70 60 50 40 30 20 10 FU Incore & Outcore Alarm Outcore Alarm Curve is inside or on Full Incore Alarm Curve 0

-40

-35

-30

-25

-20

-15

-10

-5 0

5 Percent Axial Imbalance 10 15 20 25 30 35 40

ONEI-0400-51 Rev 34 Page 16 of 34 Oconee 2 Cycle 27 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 3 Pumps 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 0.0 263.5 261.5 251.5 241.5 201.5 195.2 91.5 76.5 16.5 1.5 0.0 0.0 237.5 234.8 201.5 195.2 91.5 76.5 16.5 1.5 0.0 0.0 283.4 281.5 271.9 262.3 233.4 231.5 165.5 161.5 93.5 76.5 74.8 51.0 285.2 281.5 235.2 231.5 165.5 161.5 93.5 76.5 74.8 51.0 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300 300

ONEI-0400-51 Rev 34 Page 17 of 34 Oconee 2 Cycle 27 4 Pumps 3 Pumps Shutdown Margin Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint R

%FP No Inop Rod 1 Inop Rod 102.0 224.6 283.4 100.0 221.5 281.5 48.0 141.5 231.5 13.0 76.5 161.5 3.0 1.5 76.5 2.8 0.0 74.8 0.0 0.0 51.0 77.0 75.0 48.0 13.0 3.0 2.8 0.0 227.4 221.5 141.5 76.5 1.5 0.0 0.0 285.2 281.5 231.5 161.5 76.5 74.8 51.0 I Withdrawal Setpoint 300 300 300 300 300 300 300 300 300 300 300 300 300 300

Oconee 2 Cycle 27 Rod Index Setpoints 4 Pump Operation, No Inoperable Rods, BOC to EOC Referred to bv TS 3.2.1 ONEI-0400-51 Rev 34 Page 18 of 34 Shutdown Margin Setpoint Opetional Alarm Setpoint

% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 102 100 99.8 24.8 100 100 63.5 101 100 99.0 24.0 100 100 62.5 100 100 98.2 23.2 100 100 61.5 99 100 97.5 22.5 100 100 60.5 98 100 96.7 21.7 100 100 59.5 97 100 95.9 20.9 100 100 58.5 96 100 95.2 20.2 100 100 57.5 95 100 94.4 19.4 100 100 56.5 94 100 93.6 18.6 100 100 55.5 93 100 92.9 17.9 100 100 54.5 92 100 92.1 17.1 100 100 53.5 91 100 91.3 16.3 100 100 52.5 90 100 90.6 15.6 100 100 51.5 89 100 89.8 14.8 100 100 50.5 88 100 89.0 14.0 100 100 49.5 87 100 88.2 13.2 100 100 48.5 86 100 87.5 12.5 100 100 47.5 85 100 86.7 11.7 100 100 46.5 84 100 85.9 10.9 100 100 45.5 83 100 85.2 10.2 100 100 44.5 82 100 84.4 9.4 100 100 43.5 81 100 83.6 8.6 100 100 42.5 80 100 82.9 7.9 100 100 41.5 79 100 82.1 7.1 100 100 40.2 78 100 81.3 6.3 100 100 38.8 77 100 80.6 5.6 100 100 37.5 76 100 79.8 4.8 100 100 36.2 75 100 79.0 4.0 100 100 34.8 74 100 78.2 3.2 100 100 33.5 73 100 77.5 2.5 100 100 32.2 72 100 76.7 1.7 100 100 30.8 71 100 75.9 0.9 100 100 29.5 70 100 75.2 0.2 100 100 28.2 69.8 100 75.0 0

100 100 27.9 69 100 73.8 0

100 100 26.8 68 100 72.3 0

100 100 25.5 67.6 100 71.7 0

100 100 25.0 67 100 70.7 0

100 99.6 24.6 66 100 69.2 0

100 98.9 23.9 65 100 67.7 0

100 98.2 23.2 64 100 66.1 0

100 97.6 22.6 63 100 64.6 0

100 96.9 21.9 62 100 63.0 0

100 96.2 21.2 61 100 61.5 0

100 95.6 20.6 60 100 60.0 0

100 94.9 19.9 59 100 58.4 0

100 94.2 19.2 58 100 56.9 0

100 93.6 18.6 57 100 55.3 0

100 92.9 17.9 56 100 53.8 0

100 92.2 17.2 55 100 52.3 0

100 91.6 16.6 54 100 50.7 0

100 90.9 15.9 53 100 49.2 0

100 90.2 15.2 52 100 47.7 0

100 89.6 14.6 51 100 46.1 0

100 88.9 13.9 50 100 44.6 0

100 88.2 13.2

% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP?

Shutdown Margin Setpoint Operational Alarm Setpolnt RI = 300 is withdrawal limit at all power levels.

Continued on next page.

Oconee 2 Cycle 27 Rod Index Setpoints 4 Pump Operation, No Inoperable Rods, BOC to EOC Referred to by TS.2.1 ONEI-0400-51 Rev 34 Page 19 of 34 Shutdown Margin Setpoint Operational Alarm Setpoint

% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 49 100 43.0 0

100 86.7 11.7 48 100 41.5 0

100 85.1 10.1 47 100 39.6 0

100 83.5 8.5 46 100 37.8 0

100 82.0 7.0 45 100 35.9 0

100 80.4 5.4 44 100 34.1 0

100 78.8 3.8 43 100 32.2 0

100 77.2 2.2 42 100 30.4 0

100 75.7 0.7 41.6 100 29.6 0

100 75.0 0

41 100 28.5 0

100 73.2 0

40 100 26.6 0

100 70.1 0

39.1 100 25.0 0

100 67.3 0

39 99.9 24.9 0

100 66.9 0

38 99.0 24.0 0

100 63.8 0

37 98.0 23.0 0

100 60.6 0

36 97.1 22.1 0

100 57.5 0

35 96.2 21.2 0

100 54.3 0

34 95.2 20.2 0

100 51.2 0

33 94.3 19.3 0

100 48.1 0

32 93.4 18.4 0

100 44.9 0

31 92.5 17.5 0

100 41.8 0

30 91.5 16.5 0

100 38.6 0

29 90.6 15.6 0

100 35.5 0

28 89.7 14.7 0

100 32.4 0

27 88.8 13.8 0

100 29.2 0

26 87.8 12.8 0

100 26.1 0

25.7 87.5 12.5 0

100 25.0 0

25 86.9 11.9 0

99.0 24.0 0

24 86.0 11.0 0

97.4 22.4 0

23 85.0 10.0 0

95.8 20.8 0

22 84.1 9.1 0

94.2 19.2 0

21 83.2 8.2 0

92.7 17.7 0

20 82.2 7.2 0

91.1 16.1 0

19 81.3 6.3 0

89.5 14.5 0

18 80.4 5.4 0

88.0 13.0 0

17 79.5 4.5 0

86.4 11.4 0

16 78.5 3.5 0

84.8 9.8 0

15 77.6 2.6 0

83.2 8.2 0

14 76.7 1.7 0

79.5 4.5 0

13 75.8 0.8 0

75.8 0.8 0

12.8 75.0 0

0 75.0 0

0 12 69.0 0

0 69.0 0

0 11 61.5 0

0 61.5 0

0 10 54.0 0

0 54.0 0

0 9

46.5 0

0 46.5 0

0 8

39.0 0

0 39.0 0

0 7

31.5 0

0 31.5 0

0 6

24.0 0

0 24.0 0

0 5

16.5 0

0 16.5 0

0 4

9.0 0

0 9.0 0

0 3

1.5 0

0 1.5 0

0 2.8 0

0 0

0 2

0 0

1 0

0 0

%FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP 6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels.

Oconee 2 Cycle 27 Rod Index Setpoints 3 Pump Operation, No Inoperable Rods, BOC to EOC Referred tn by TS.2.1 ONEI-0400-51 Rev 34 Page 20 of 34 Shutdown Margin Setpoint Operational Alarm Setpoint

% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 77 100 100 27.4 100 100 37.5 76.2 100 100 25.0 100 100 36.4 76 100 99.7 24.7 100 100 36.1 75 100 98.2 23.2 100 100 34.8 74 100 96.8 21.8 100 100 33.5 73 100 95.3 20.3 100 100 32.1 72 100 93.8 18.8 100 100 30.8 71 100 92.3 17.3 100 100 29.5 70 100 90.8 15.8 100 100 28.1 69 100 89.4 14.4 100 100 26.8 68 100 87.9 12.9 100 100 25.5 67.6 100 87.4 12.4 100 100 25.0 67 100 86.4 11.4 100 99.6 24.6 66 100 84.9 9.9 100 98.9 23.9 65 100 83.4 8.4 100 98.2 23.2 64 100 82.0 7.0 100 97.6 22.6 63 100 80.5 5.5 100 96.9 21.9 62 100 79.0 4.0 100 96.2 21.2 61 100 77.5 2.5 100 95.6 20.6 60 100 76.0 1.0 100 94.9 19.9 59.3 100 75.0 0

100 94.4 19.4 59 100 74.1 0

100 94.2 19.2 58 100 71.1 0

100 93.6 18.6 57 100 68.2 0

100 92.9 17.9 56 100 65.2 0

100 92.2 17.2 55 100 62.2 0

100 91.6 16.6 54 100 59.3 0

100 90.9 15.9 53 100 56.3 0

100 90.2 15.2 52 100 53.4 0

100 89.6 14.6 51 100 50.4 0

100 88.9 13.9 50 100 47.4 0

100 88.2 13.2 49 100 44.5 0

100 86.7 11.7 48 100 41.5 0

100 85.1 10.1 47 100 39.6 0

100 83.5 8.5 46 100-...

37.8 0

100 82.0 7.0 45 100 35.9 0

100 80.4 5.4 44 100 34.1 0

100 78.8 3.8 43 100 32.2 0

100 77.2 2.2 42 100 30.4 0

100 75.7 0.7 41.6 100 29.6 0

100 75.0 0

41 100 28.5 0

100 73.2 0

40 100 26.6 0

100 70.1 0

39.1 100 25.0 0

100 67.3 0

39 99.9 24.9 0

100 66.9 0

38 99 24.0 0

100 63.8 0

37 98 23.0 0

100 60.6 0

36 97.1 22.1 0

100 57.5 0

35 96.2 21.2 0

100 54.3 0

34 95.2 20.2 0

100 51.2 0

33 94.3 19.3 0

100 48.1 0

32 93.4 18.4 0

100 44.9 0

31 92.5 17.5 0

100 41.8 0

30 91.5 16.5 0

100 38.6 0

29 90.6 15.6 0

100 35.5 0

28 89.7 14.7 0

100 32.4 0

%FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 Is withdrawal limit at all power levels.

Continued on next page.

Oconee 2 Cycle 27 Rod Index Setpoints 3 Pump Operation, No Inoperable Rods, BOC to EOC Referred to bv TS 3.2.1 ONEI-0400-51 Rev 34 Page 21 of 34 Shutdown Margin Setpoint Operational Alarm Setpoint

% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 27 88.8 13.8 0

100 29.2 0

26 87.8 12.8 0

100 26.1 0

25.7 87.5 12.5 0

100 25.0 0

25 86.9 11.9 0

99.0 24.0 0

24 86.0 11.0 0

97.4 22.4 0

23 85.0 10.0 0

95.8 20.8 0

22 84.1 9.1 0

94.2 19.2 0

21 83.2 8.2 0

92.7 17.7 0

20 82.2 7.2 0

91.1 16.1 0

19 81.3 6.3 0

89.5 14.5 0

18 80.4 5.4 0

88.0 13.0 0

17 79.5 4.5 0

86.4 11.4 0

16 78.5 3.5 0

84.8 9.8 0

15 77.6 2.6 0

83.2 8.2 0

14 76.7 1.7 0

79.5 4.5 0

13 75.8 0.8 0

75.8 0.8 0

12.8 75.0 0

0 75.0 0

0 12 69.0 0

0 69.0 0

0 11 61.5 0

0 61.5 0

0 10 54.0 0

0 54.0 0

0 9

46.5 0

0 46.5 0

0 8

39.0 0

0 39.0 0

0 7

31.5 0

0 31.5 0

0 6

24.0 0

0 24.0 0

0 5

16.5 0

0 16.5 0

0 4

9.0 0

0 9.0 0

0 3

1.5 0

0 1.5 0

0 2.8 0

0 0

0 2

0 0

1 0

0 0

% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels.

Oconee 2 Cycle 27 Rod Index Setpoints 4 Pump Operation, I Inoperable Rod, BOC to EOC Referred to by TS 3.2.1 ONEI-0400-51 Rev 34 Page 22 of 34 Shutdown Marain Setpoint Operational Alarm Setpoint

% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 102 100 100 83.4 100 100 83.4 101 100 100 82.5 100 100 82.5 100 100 100 81.5 100 100 81.5 99 100 100 80.5 100 100 80.5 98 100 100 79.6 100 100 79.6 97 100 100 78.6 100 100 78.6 96 100 100 77.7 100 100 77.7 95 100 100 76.7 100 100 76.7 94 100 100 75.7 100 100 75.7 93 100 100 74.8 100 100 74.8 92 100 100 73.8 100 100 73.8 91 100 100 72.8 100 100 72.9 90 100 100 71.9 100 100 71.9 89 100 100 70.9 100 100 70.9 88 100 100 70.0 100 100 70.0 87 100 100 69.0 100 100 69.0 86 100 100 68.0 100 100 68.1 85 100 100 67.1 100 100 67.1 84 100 100 66.1 100 100 66.1 83 100 100 65.2 100 100 65.2 82 100 100 64.2 100 100 64.2 81 100 100 63.2 100 100 63.3 80 100 100 62.3 100 100 62.3 79 100 100 61.3 100 100 61.3 78 100 100 60.3 100 100 60.4 77 100 100 59.4 100 100 59.4 76 100 100 58.4 100 100 58.4 75 100 100 57.5 100 100 57.5 74 100 100 56.5 100 100 56.5 73 100 100 55.5 100 100 55.6 72 100 100 54.6 100 100 54.6 71 100 100 53.6 100 100 53.6 70 100 100 52.7 100 100 52.7 69 100 100 51.7 100 100 51.7 68 100 100 50.7 100 100 50.7 67 100 100 49.8 100 100 49.8 66 100 100 48.8 100 100 48.8 65 100 100 47.8 100 100 47.8 64 100 100 46.9 100 100 46.9 63 100 100 45.9 100 100 45.9 62 100 100 45.0 100 100 45.0 61 100 100 44.0 100 100 44.0 60 100 100 43.0 100 100 43.0 59 100 100 42.1 100 100 42.1 58 100 100 41.1 100 100 41.1 57 100 100 40.2 100 100 40.2 56 100 100 39.2 100 100 39.2 55 100 100 38.2 100 100 38.2 54 100 100 37.3 100 100 37.3 53 100 100 36.3 100 100 36.3 52 100 100 35.3 100 100 35.3 51 100 100 34.4 100 100 34.4 50 100 100 33.4 100 100 33.4 49 100 100 32.5 100 100 32.5 48 100 100 31.5 100 100 31.5

% FP CRGP5 CRGP6 CRGP 7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels.

Continued on next page.

Oconee 2 Cycle 27 Rod Index Setpoints 4 Pump Operation, 1 Inoperable Rod, BOC to EOC Referrn=d to bv TS 3.2 1 ONEI-0400-51 Rev 34 Page 23 of 34 Shutdown Margin Setpoint Operational Alarm Setpoint

% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 47 100 100 29.5 100 100 29.5 46 100 100 27.5 100 100 27.5 45 100 100 25.5 100 100 25.5 44.8 100 100 25.0 100 100 25.0 44 100 99.2 24.2 100 99.2 24.2 43 100 98.2 23.2 100 98.2 23.2 42 100 97.2 22.2 100 97.2 22.2 41 100 96.2 21.2 100 96.2 21.2 40 100 95.2 20.2 100 95.2 20.2 39 100 94.2 19.2 100 94.2 19.2 38 100 93.2 18.2 100 93.2 18.2 37 100 92.2 17.2 100 92.2 17.2 36 100 91.2 16.2 100 91.2 16.2 35 100 90.2 15.2 100 90.2 15.2 34 100 89.2 14.2 100 89.2 14.2 33 100 88.2 13.2 100 88.2 13.2 32 100 87.2 12.2 100 87.2 12.2 31 100 86.2 11.2 100 86.2 11.2 30 100 85.2 10.2 100 85.2 10.2 29 100 84.2 9.2 100 84.2 9.2 28 100 83.2 8.2 100 83.2 8.2 27 100 82.2 7.2 100 82.2 7.2 26 100 81.2 6.2 100 81.2 6.2 25 100 80.2 5.2 100 80.2 5.2 24 100 79.2 4.2 100 79.2 4.2 23 100 78.2 3.2 100 78.2 3.2 22 100 77.2 2.2 100 77.2 2.2 21 100 76.2 1.2 100 76.2 1.2 20 100 75.2 0.2 100 75.2 0.2 19.8 100 75.0 0

100 75.0 0

19 100 73.5 0

100 73.5 0

18 100 71.5 0

100 71.5 0

17 100 69.5 0

100 69.5 0

16 100 67.5 0

100 67.5 0

15 100 65.5 0

100 65.5 0

14 100 63.5 0

100 63.5 0

13 100 61.5 0

100 61.5 0

12 100 53.0 0

100 53.0 0

11 100

-44.5 0

100 44.5 0

10 100 36.0 0

100 36.0 0

9 100 27.5 0

100 27.5 0

8.7 100 25.0 0

100 25.0 0

8 97.0 22.0 0

97.0 22.0 0

7 92.8 17.8 0

92.8 17.8 0

6 88.5 13.5 0

88.5 13.5 0

5 84.2 9.2 0

84.2 9.2 0

4 80.0 5.0 0

80.0 5.0 0

3 75.8 0.8 0

75.8 0.8 0

2.8 75 0

0 75 0

0 2

68 0

0 68 0

0 1

59.5 0

0 59.5 0

0 0

51 0

0 51 0

0

%FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 Is withdrawal limit at all power levels.

Oconee 2 Cycle 27 Rod Index Setpoints 3 Pump Operation, 1 Inoperable Rod, BOC to EOC Referred to bv TS 3.2.1 ONEI-0400-51 Rev 34 Page 24 of 34 Shutdown Margin Setpoint Operational Alarm Setpolnt

% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 77 100 100 85.2 100 100 85.2 76 100 100 83.4 100 100 83.4 75 100 100 81.5 100 100 81.5 74 100 100 79.6 100 100 79.6 73 100 100 77.8 100 100 77.8 72 100 100 75.9 100 100 75.9 71 100 100 74.1 100 100 74.1 70 100 100 72.2 100 100 72.2 69 100

.100 70.4 100 100 70.4 68 100 100 68.5 100 100 68.5 67 100 100 66.7 100 100 66.7 66 100 100 64.8 100 100 64.8 65 100 100 63.0 100 100 63.0 64 100 100 61.1 100 100 61.1 63 100 100 59.3 100 100 59.3 62 100 100 57.4 100 100 57.4 61 100 100 55.6 100 100 55.6 60 100 100 53.7 100 100 53.7 59 100 100 51.9 100 100 51.9 58 100 100 50.0 100 100 50.0 57 100 100 48.2 100 100 48.2 56 100 100 46.3 100 100 46.3 55 100 100 44.5 100 100 44.5 54 100 100 42.6 100 100 42.6 53 100 100 40.8 100 100 40.8 52 100 100 38.9

'100 100 38.9 51 100 100 37.1 100 100 37.1 50 100 100 35.2 100 100 35.2 49 100 100 33.4 100 100 33.4 48 100 100 31.5 100 100 31.5 47 100 100 29.5 100 100 29.5 46 100 100 27.5 100 100 27.5 45 100 100 25.5 100 100 25.5 44.8 100 100 25.0 100 100 25.0 44 100 99.2 24.2 100 99.2 24.2 43 100 98.2 23.2 100 98.2 23.2 42 100 97.2 22.2 100 97.2 22.2 41 100 96.2 21.2 100 96.2 21.2 40 100 95.2 20.2 100 95.2 20.2 39 100 94.2 19.2 100 94.2 19.2 38 100 93.2 18.2 100 93.2 18.2 37 100 92.2 17.2 100 92.2 17.2 36 100 91.2 16.2 100 91.2 16.2 35 100 90.2 15.2 100 90.2 15.2 34 100 89.2 14.2 100 89.2 14.2 33 100 88.2 13.2 100 88.2 13.2 32 100 87.2 12.2 100 87.2 12.2 31 100 86.2 11.2 100 86.2 11.2 30 100 85.2 10.2 100 85.2 10.2 29 100 84.2 9.2 100 84.2 9.2 28 100 83.2 8.2 100 83.2 8.2 27 100 82.2 7.2 100 82.2 7.2 26 100 81.2 6.2 100 81.2 6.2 25 100 80.2 5.2 100 80.2 5.2 24 100 79.2 4.2 100 79.2 4.2

%FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 Is withdrawal limit at all power levels.

Continued on next page.

Oconee 2 Cycle 27 Rod Index Setpoints 3 Pump Operation, 1 Inoperable Rod, BOC to EOC Referred to by TS 3.2.1 ONEI-0400-51 Rev 34 Page 25 of 34 Shutdown Margin Setpoint Operational Alarm Setpoint

% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 23 100 78.2 3.2 100 78.2 3.2 22 100 77.2 2.2 100 77.2 2.2 21 100 76.2 1.2 100 76.2 1.2 20 100 75.2 0.2 100 75.2 0.2 19.8 100 75.0 0

100 75.0 0

19 100 73.5 0

100 73.5 0

18 100 71.5 0

100 71.5 0

17 100 69.5 0

100 69.5 0

16 100 67.5 0

100 67.5 0

15 100 65.5 0

100 65.5 0

14 100 63.5 0

100 63.5 0

13 100 61.5 0

100 61.5 0

12 100 53.0 0

100 53.0 0

11 100 44.5 0

100 44.5 0

10 100 36.0 0

100 36.0 0

9 100 27.5 0

100 27.5 0

8.7 100 25.0 0

100 25.0 0

8 97.0 22.0 0

97.0 22.0 0

7 92.8 17.8 0

92.8 17.8 0

6 88.5 13.5 0

88.5 13.5 0

5 84.2 9.2 0

84.2 9.2 0

4 80.0 5.0 0

80.0 5.0 0

3 75.8 0.8 0

75.8 0.8 0

2.8 75.0 0

0 75.0 0

0 2

68 0

0 68 0

0 1

59.5 0

0 59.5 0

0 0

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Shutdown Margin Setpoint Operational Alarm Setooint RI = 300 is withdrawal limit at all power levels.

I Oconee 2 Cycle 27 I

ONEI-0400-51 Rev 34 Page 26 of 34 Referred to by TS 3.2.1 105 100 95 90 85 80 75 70 65 LL 6o 50 O 45 40 35 30 25 20 45 10 5

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0 10 10 20 30 40 50 60 70 80 90 100 IGroup 5I Con 1 0 10 20 30 40 50 60

'70 80 90 100 trol Rod Position. % WD Group 7

ONEI-0400-51 Rev 34 Oconee 2 Cycle 27 Referred to by TS 3.2.1 Page 27 of 34 105 105 100 Control Rod Position Setpoints 100 95 1No Inoperable Rods, 3 Pump Flow, 95 BOC to EOC 95 90 90 85 85 80 80 75 75 70 70 65 Unacceptable 65

a.

Operation

-60 60 55 55 50 50 cc 45 45 It Restricted 40 Operation 40

35.

35 30 Acceptable 30 fill Operation 25 25 20 20 15 15 10 I10 WI Group 6 5

5 15 25 35 45 55-63585 9

0 I..

...I....

I..,.

10 10 20 30 40 50 60 70 80 90 100

.I 10 10 20 30 40 50 60 70 80 90 100 I Group 5 1 Control Rod Position, % WD

ONEI-0400-51 Rev 34 105 Oconee 2 Cycle 27 Referred to byTS 3.2.1 Page 28 of 34 105 105 105 100 Control Rod Position Setpoints 100 95 1 Inoperable Rod, 4 Pump Flow, 95 90

~~~~~BOC to EOC....

9 90 90 85 85 80 80 75 75 70 70 65 65 6511fi Unacceptable6 LL 60 Operation 60

.55 55 o

i50 Acceptable 50 0 45 Operation 45 G) 40 40 35 35 30 25 25 20 20 15 15 10 10 5

5 5 15 25 351 45 5

6 5

85 95 FO 10_2_3040_0_6070_0_9_160._I_10_10 20_0_4_50_0_7 80 go 0

j0 10 20 30 40 50 60 70 80 90o100 I

I 0 10 20 30 40 50 60 70 80 90 1001 FG-r o- -up -5 1 l

Control Rod Position. % WD I Group 7 1

I Ocnee Cyle 2

I efered t byS 3..1ONEI-0400-51 Rev 34 105

~ocneeCycl 27Refrre to y T 3.. 1Paue 29 of 34 100 100 100

~Control Rod Position Setpoints10 95 1 Inoperable Rod, 3 Pump Flow, 95 BOC to EOC 90 90 85 8

80 80 75 75 70 Unacceptable fl mil70 Operation 6 5 65 a-

,u. 60 6D

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5050 cc 45 45 IIM HI Acceptables 40 Operation 4

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5 8

10 10 20 30 40 50 60 70 80 90 100 I,[0 10 20 30 40 50 60 70 80

-90 100j I Group 5 Control Rod Position,, % WD I G~rou 7

%I

ONEI-0400-51 Rev 34 Page 30 of 34 Oconee 2 Cycle 27 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.

Core Power Level, Quadrant Power T Core Outl r

1 2

2 22 2

%FP C

ilt, %

1 Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State T

)-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, OF asia 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-0400-51 Rev 34 Page 31 of 34 Oconee 2 Cycle 27 Axial Power Imbalance Protective Limits Referred to byTS 2.1.1 Not for Plant Use 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

-14.4 14.4 35.0 35.0

-35.0

-14.4 14.4 35.0 35.0

-39.5

-37.1

-28.4 25.0 32.9 39.0 39.0

-39.5

-39.5 39.0 39.0

ONEI-0400-51 Rev 34 Page 32 of 34 Oconee 2 Cycle 27 Rod Index Limits Referred to by TS 3.2.1 I

Not for Plant Use I

Operational RI

%FP Insertion Limit Shutdown Margin RI Insertion Limit RI Withdrawal No Inop Rod 1 Inop Rod Limit 4 Pumps 3 Pumps 102 100 90 80 50 15 5

77 50 15 5

262 260 250 240 200 90 0

236 200 go 0

220 140 75 0

280 230 160 75 280 230 160 75 300 300 300 300 300 300 300 300 300 300 300

ONEI-0400-51 Rev 34 Page 33 of 34 Oconee 2 Cycle 27 LOCA Limits Not for Plant Use Core Elevation LOCA LHR kwlft Limit Versus Bumup Feet Mk-B-HTP w1O% Gad rods 0 GWd/mtU 34 GWd/mtU 62 GWdImIU 0

16.9 14.9 11.7 2.506 17.8 15.8 12.3 4.264 17.8 15.8 12.3 6.021 17.8 15.8 12.3 7.779 17.8 15.8 12.3 9.536 17.3 15.3 12.3 12 16.4 14.4 11.7 Core Elevation LOCA LHR kwlft Limit Versus Bumup Feet Mk-B-HTP w/2% Gad rods 0 GWd/mtU 34 GWd/mtU 62 GWdImtU 0

16.0 14.0 11.0 2.506 16.9 14.9 11.6 4.264 16.9 14.9 11.6 6.021 16.9 14.9 11.6 7.779 16.9 14.9 11.6 9.536 16.4 14.4 11.6 12 15.5 13.5 11.0 Core Elevation LOCA LHR kw/ft Limit Versus Bumup Feet Mk-B-HTP w/4% Gad rods 0 GWd/mtU 34 GWdlmtU 62 GWd/mtU 0

15.2 13.2 10.5 2.506 16.1 14.1 11.1 4.264 16.1 14.1 11.1 6.021 16.1 14.1 11.1 7.779 16.1 14.1 11.1 9.536 15.7 13.7 11.1 12 14.9 12.9 10.5 Core Elevation LOCA LHR kwlft Limit Versus Bumup Feet Mk-B-HTP w16% Gad rods 0 GWdImtU 34 GWdlmtU 62 GWd/mtU 0

14.8 12.8 10.2 2.506 15.6 13.6 10.8 4.264 15.6 13.6 10.8 6.021 15.6 13.6 10.8 7.779 15.6 13.6 10.8 9.536 15.2 13.2 10.8 12 14.4 12.4 10.2 Core Elevation LOCA LHR kwlft Limit Versus Bumup Feet Mk-B-HTP w/8% Gad rods 0

2.506 4.264 6.021 7.779 9.536 12 0 GWdlmtU 34 GWdlmtU 62 GWd/mtU 14.3 12.3 9.9 15.1 13.1 10.4 15.1 13.1 10.4 15.1 13.1 10.4 15.1 13.1 10.4 14.7 12.7 10.4 13.9 11.9 9.9

ONEI-0400-51 Rev 34 Page 34 of 34 Oconee 2 Cycle 27 Referred to by TS 3.4.1.

Not for Plant Use Instrument uncertainties are not included in the values shown.

4 RcP Opertion - Loop Avemge Temp", F 3 RCP Opemtion-Loop Avemge Temp., F

&Tcold, OF Tav& (Analytical)

Tav6 (Analyflical) 0.U

<581 I.0

<.55' L U 0.1

-081.0

<581.0 0.2

<581.1

<'581.0 0.3

<581.1

<581.1 0.4

<581.2

<581.1 0.5

<58-1.2

<58 3.1 0.6

<381.2

.58 1.1 0.7

<581.3

<581.2 0.8

<581.3

<58 1.2 0.9

<581.3

<581.2 1.0

<581.4

<81.2 1.1

<581.4

<581.2 1.2

<581.5

<581.3

<581.5

<581.3 1.4

<581.5

<581.3 1.5

<8 1.6

<581.3 L6

<581.6

<581.4

[.7_

<581.6

<581.4 1.8

'5-81.7

<581.4 1.9

<581.7

<581.4 2.0

<581.8

<581.4

<581.8

<581.5 2.2

<581.8

<581.5 2.3

<581.9

<581.5 2.4

<581.9

<581.5 2.5

<582.0

<581.6 2.6

<582.0

<581.6 2.7

<582.0

<581.6 2.8

<582.1

<581.6 2.9

<'582.1

<581.6 3.0

<582.1

<581.7

'.1 <582.2

<581.7 3.2

<582.2

<581.7 3.3

<582.3

<581.7 3.4

<582.3

<581.7

'.5

<582.3

<581.8 3.6

<582.4

<581.8 3.7

<582.4

<58 1.8 3.8

<582.4

<581J8 3.9

<582.5

<58 1.9 4.0

<582.5

<581.9 4.1

<582.6

<581.9 4.2

<582.6

'58 1.9 4.3

<582.6

<581.9 4.4

<582.7

<582.0 4.5

<582.7

<582.0 4.6

<582.7

<582.0 4.7

<582.8

<582.0 4.8

<582.8

<582.1 4.9 11

<582.9

<582.1 5.0 5<82.9

<582.1

PRmORflY Supermush DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRAN4SMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW

1) 00813 DOG }MGMT ECO4T (OR:GtNAL

3) 067"0 ONS MANUAL MASTER FIE 0N0312M

4) 0U937 R RSTCAI.R EC08G FOR INFORMATION ONLY Duke Energy D)OCUMENT TRANSMITTAL FORM Date:

12119114 Document Transmittal #:

DUK1,13530015 QA CONDITION

Yes [-] No OERACKNOWLEDGEMIENT REQUIRED L'I Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED. PLEASE ACKNWLDE RECEIPT BY RETURNING THIS FORM TO:

Duke Energy P.O. Box 1006 Energy Center EC04T Chardotte, N.C.

28201-1006 REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION RETENTION 421734 OCONEE 3 CYCLE 28 CORE OPERATING UMITS REPORT Page 1 of 1 Rec'd By I

I Date 4

r DOCUMENT NO QA COND REV #/DATE DIST"R CODE 1 Ia 3

4 1 6

7 8

10 11 12 13 14 15 TOTAL I

.3.

ONEI-0400-070 1

037 12/19/14 NOMD-27 X II V1 V1 3

REMARKS:

DUKE DOCUMENTS CREATED UNDER EDM-501 ARE EXCLUDED FROM THE EDM-601 PROCESS PER NSD-301,* SECTION 2.4. THEREFORE, THE EXEMPTION CODE OR PIP NUMBER REQUIRED BY EDM-601 IS NOT REQUIRED FOR THIS DOCUMENT.

DAVID C. CULP GENERAL MANAGER NUCLEAR ENGINEERING BY:

D S ORR DSOIZLA EC08G

ONEI-0400-70 Rev 37 Page I of 24 Duke Energy Oconee 3 Cycle 28 Core Operating Limits Report QA Condition I

~fflsCQn Prepared By: L. D. McClain Date: IS Der O.,oIL--

W122 Date:

/ý I

Reviewed By: D. S. Orr CDR By: N/A Approved By: R.R. St.Clair Date:

N/A Date:

/.:,-e

-1 A

ONEI-0400-70 Rev 37 Page 2 of 24 Engineering Instruction Inspection Waiver:

In accordance with EDM 130, this El Inspection has been waived by OS-105.00.

0

ONEI-0400-70 Rev 37 Page 3 of 24 Oconee 3 Cycle 28 Core Operating Limits Report Insertion Sheet for Revision 37 I

implement this COLR revision on or before Januar 9, 2015 Remove these Revision 36 pages Insert these Revision 37 pages 1-24 1 -24 Effective Revision Date Revision Log Pages Revised Pages Pages Total Effective Added Deleted Pages I

Oconee 3 Cycle 28 revisions below 37 Dec 2014 1 -24 24 36 Apr 2014 1-24 25-33 24 Oconee 3 Cycle 27 revisions below 35 Apr 2014 1-33 333 34 Apr 2013 1-33 33 33 Oct 2012 1-33 33 32 May 2012 1-33 33 Oconee 3 Cycle 26 revisions below 1

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 Mar2009 1-33 33 28 Nov 2007 1-33 33 25 Nov 2007 1-33 33 oconee 3 Cy7cle 23 revisions below 24 May 2006 1-33 33 Oconee 3 Cycle 22 revisions below 23 Mar 2006 1 - 4, 6,15 - 16, 21,27, 31 33 22 Mar2005 1-5 33 21 Nov 2004 1-33 33

ONEI-0400-70 Rev 37 Page 4 of 24 Oconee 3 Cycle 28 Table Of Contents Section 1.0 Error Adlusted Core Oporatinn 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 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 Umits 1, 3. 7,_8 Misaligned, Dropped, or Inoperable 3.1.5 Safety Rod Position Umlts 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 Setpolnts 3.2.3 Quadrant Power Tilt (OPT) 1, 3, 7, 9,10 OPT 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 Setpolnts Maximum Allowed RPS Power Imbalance Limits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpolnts 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 a8 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 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 37 Page 5 of 24 Oconee 3 Cycle 28 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for O3C28 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 (FAh) of 1.714, an axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB)

Tavg reduction for up to 1 0F 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 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-1001-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-101 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. BAWA10164P-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 8, September 2010.

13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Retio 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-1 1093, Revision 3, December 2014.

16. 03C28 Specific DNB Evaluation, OSC-11096, Revision 0, October 2013.

17. 03C28 Reload Safety Evaluation, OSC-1 1123, Revision 1, December 2014.

ONEI-0400-70 Rev 37 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% &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.

Ap / °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 pslg DNB parameter for RCS loop average temperature shall be:

Max Loop Tavg (Inel 20F 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 a 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 37 Page 7 of 24 Oconee 3 Cycle 28 EFPD 0 to 644 644 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 15 300 30 40 292 t 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-0400-70. Rev 37 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 "F 2300 2200 V,

0.

,i 2100 Acceptable Operation P= 11.14 Tout-4706 2000 V

Unacceptable 1900 Operation P =1800 psig 1800 T

584 OF 1700 640 560 580 600 620 640 Reactor Coolant Outlet Temperature, OF

ONEI-0400-70 Rev 37 Page 9 of 24 Oconee 3 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 Pmax =>

109.4 14.4 90.0 35.0 0.0 35.0 3 Pumps 0.0

-35.0 62.3

-35.0 Pma =>

81.7

-14.4 Pmax*=>

81.7 14.4 62.3 35.0 0.0 35.0

ONEI-0400-70 Rev 37 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

-23.1

-23.6 100.0

-17.7

-15.9

-18.2 102.0

-15.6

-14.4

-14.7 102.0 15.6 12.5 12.9 100.0 17.7 14.4 14.7 90.0 28.0 23.4 23.7 80.0 28.0 27.7 28.0 0.0 28.0 27.7 28.0 3 Pumps 0.0

-28.0

-27.5 63.1

-28.0 63.3 63.5

-27.5 77.0

-13.2

-13.2 77.0 13.2 13.2 63.3 27.7 63.1 63.1 28.0 0.0 28.0 27.7 Referred to by TS 3.2.2

-27.8

-13.2 13.2 28.0 28.0

ONEI-0400-70 Rev 37 Page 11 of 24 Oconee 3 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 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 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 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

-14.7

-15.5

-16.2

-16.9

-17.7

-18.4

-19.1

-19.9

-20.6

-21.3

-22.0

-22.8

-23.2

-23.5

-23.9

-24.4

-24.8

-25.2

-25.7

-26.1

-26.5

-26.9

-27.4

-27.8

-27.8 12.9 13.8 14.7 15.6 16.5 17.4 18.3 19.2 20.1 21.0 21.9 22.8 23.4 23.7 24.1 24.6 25.0 25.4 25.9 26.3 26.7 27.1 27.6 28.0 28.0

% FP RPS Trip Full Incore Alarm.

Out of Core Alarm ONEI-0400-70 Rev 37 Page 12 of 24 Oconee 3 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 RPS Tria Full Inoore Alarm Out of Core Alarm I

U I

I 4

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 64.0 63.3 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

-24.8

-25.6

-26.7

-27.8

-28.8

-29.9

-30.9

-32.0

-32.8

-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 32.0 32.8 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

-27.0

-27.8

-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 27.0 27.8 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

-27.0

-27.8

-27.8 13.2 14.3 15.3 18.4 17.4 18.5 19.6 20.6 21.7 22.8 23.8 24.9 25.9 27.0 27.8 28.0 28.0 28.0 28.0 28.0 28.0

% FP RPS Trip

" Full Incore Alarm 1

Out of Core Alarm ONEI-0400-70 Rev 37 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 -

(-33.0,90.4)

(-33.0,63.1)

-40.0

(-14.4,107.9)

M1 =0.942

(-14.4,80.6) 100.0 Acceptable 4 Pump Operation (14.4,80.6) on" (14.4,107.9.)

M2 = -0.942 (33.0,90.4)

(33.0,63.1)

I.

60.0 Acceptable 3 or 4 Pump Operatlor 40.0 20.0 PP 1 _____________

-30.0

-20.0

-10.0 0.0 10.0 Percent Power Imbalance 20.0 30.0 40.0

Oconee 3 Cycle 28 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-70 Rev 37 Page 14 of 24 110 1

....4,

.r.

1 RPS Trip Set..int g

M.0 90-3..0.

90 80 Labels Correspond to the Backup Incore A 70 0-60 LL IL 40 30 20 10

--33.0, 0.o 30

-40

-35

-30

-25

-20

-15

-10

-5 0

5 Percent Axial Imbalance 10 15 20 25 30 35 40

Oconee 3 Cycle 28 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEI-0400-70 Rev 37 Page 15 of 24 110 100 90

-14.4. 80.6 14.4, 80.6 IL 0

IL 80 70 60 50 40 30 20 10 J=RPS Trip Setpoint

13.*:n.i 13.2,77.01 1, 63.1:

NzRPSTrip Setpoint~

13.1 #

-27.5, 6.ý I -,,L,--

9-"

nd to the Backup Incore Alarm Setpoints a&W4 macre

-"i C%&it I f

-B*RPS Trip I

-33.0, o.o1

-27.5. 0.0 7.7. 0.0 [

i 4

" 33.o0o. I 0

-40

-35

-30

-25

-20

-15

-10

-5 0

5 Percent Axial Imbalance 10 15 20 25 30 35 40

ONEI-0400-70 Rev 37 Page 18 of 24 Oconee 3 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 283.5 283.4 261.5 281.5 251.5 271.9 241.5 262.3 201.5 233.4 195.2 231.5 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-0400-70 Rev 37 Page 17 of 24 Oconee 3 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 76.0 48.0 13.0 3.0 2.8 0.0 Referred to by TS 3.2.1 RI Insertion Setpoint No Inop Rod I 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

IOconee 3 Cycle 28 1 Referred to by TS 3.2.1 ONEI-0400-70 Rev 37 Page 18 of 24 105 100 95 90 85 80 75 70 65 60 S55 50 ao 45 m

40 35 30 25 20 15 10 5 0.0.2.1 Control Rod Pos o Inoperable Rod Rlnrt M

4 Pump Flow, Mrv Unacceptable Operation Restricted Ooeration

,tmmmmm 105 M0.O0,102,01 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5

90 1001 Acceptable innaratinn 1.0. 0)

'nlll ilium 16.5. 5.0

=

2.0-- 30 40 50 6

SG- -upsI5 70 80 lOO0 O0 Control Rod Position, % WD 0

50 60 70 80 SGroup 71

l ONEI-0400-70 Rev 37 Oconee 3 Cycle 28 Referred to by TS 3.2.1 Page 1t Page 19 of 24 105-105 100 100 Control Rod Position Setpoints 95-No Inoperable Rods, 3 Pump Flow, 95 90 BOC to EOC 90 85 85 80 0.300.0.

77.0" 80 75 75 22*1.5,.75.0 i234.8.

75.0:

70 -

70 65 65225.0,67.6 6

Unacceptable 15.05.3 LL 60 6Operation

%z55 -55 50 50 Restricted i015:5..

45 Operation 195.2,480 45 40 125.0.

40 17&0.0 41.6 35 -

35 30

~Operation 3

30 J3 25 25 FAI 125.0. 25.7 20 -......

20 15 15 10

.10 5

1,,8*

ru 6 5

0 15 25 35 45 55 65 75 85 95 r0 10 20 30 40 50 60 70 80 90 100 I0 10 20 30 40 50 60 70 80 90 1001 0...0 FIGru5 Control Rod Position, % WD Gru7I

I Oconee 3 Cycle 28 T

I Referred to byTS 3.2.1 ONEI-0400-70 Rev 37 Page 20 of 24 105 100 95 90 85 80 75 70 65 1L60 55 0

50 45 40 35 30 25 20 15 10 MI 334.02.0.

0 Control Rod Position Setpoints 2a~. 10.....

1 Inoperable Rod, 4 Pump Flow, BOC to EOC:

Unacceptable Opperation 111111"1l161"5" fill 16,5 3.112..

IUD 100 95 90 85 8o 75 70 65 60 55 so 45 40 35 30 25 20 15 10 5

0 5

0~

I.

I

[0 10 20 30 40 50 60 70 80 90 100 I

[ 0 10 20 30 40 50 60 70 80 90 100 1

SGr=p 5oo W

Coftol Rod Poshion, % WD

I Oconee 3 Cycle Referred to by TS 3.2.1 ONEI-0400-70 Rev 37 105~Pa 21 of 124 111 10 105 105 100 Control Rod Position Setpoints 100 95 1 Inoperable Rod, 3 Pump Flow, 95 BOC to EOC 90 90 85 85

80.

300.0.77.0 80 75 75 70 Unaceptable 70 Operation 65 65

o.

6 60 60 -6 "55 55

'500 50 n°,. 50 231.5.48.0 5

S45 225.0. 44.8 SAcceptable45 U,

40 Operation 40 35 35 30 30 25 25 20 -75.0.19.8 20 I15 161.5. 13.0 5

5 0

10 20 30 40 50 60 70 80 90 100 10 20 30 40 50 60 70 80 90 100

! Gmupi JcontroRod posito.. %wD Group 7

ONEI-0400-70 Rev 37 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 I of this COLR Identify the sources for the data which follows.

Information provIded'n this section should.not'be u4Ad In plant procedures..

I I

I

[

I I I Core Power Level, Quadrant Power T Core Outl p

2 2

22

%FP C

ilt. %

Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State 1

0-30

> 30 0-30 10.00 5.40 12.00 ranslent

> 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, OF isla 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-0400-70 Rev 37 Page 23 of 24 Oconee 3 Cycle 28 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1 I'....

.~

.o

.P ntU e

I ".-

" **?."'

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

-14.4 14.4 35.0 35.0

-35.0

-14.4 14.4 35.0 35.0

-39.3

-34.7

-26.5 24.7 35.0 39.5 39.5

-39.3

-39.3 39.5 39.5

ONEI-0400-70 Rev 37 Page 24 of 24 Oconee 3 Cycle 28 Rod Index Limits Referred to by TS 3.2.1 Nbt fo~OTPla US jj Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal

%FP Insertion Umht No Inop Rod 1 Inop Rod Limit 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

280 230 160 75 280 230 160 75 300 300 300 300 300 300 300 300 300 300 300

ONS-2015-004, Submittal of Core Operating Limits Report (COLR)

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