ONS-2014-151, Cycle 29 Core Operating Limits Report
| ML14342B006 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 12/04/2014 |
| From: | Batson S Duke Energy Carolinas, Duke Energy Corp |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ONS-2014-151 | |
| Download: ML14342B006 (27) | |
Text
@DUKE
- ENERGY, Scott L. Batson Vice President Oconee Nuclear Station Duke Energy ONGlVP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.3274
- f. 864.873. 4208 Scott.Batson@duke-energy.com ONS-2014-151 December 4, 2014 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Site Docket Number 50-269 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 1, Cycle 29, ONEI-0400-50, Revision 35.
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 Aiýb www.duke-energy.com
U. S. Nuclear Regulatory Commission December 4, 2014 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 (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
PRIORITY SuperRush DISPOSION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMrrrAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW
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2 06M58 ONS REL (OU.ICE ON03RC.-
- 3) 06700 ONS MANUAL MASTER FILE ON03DM
- 4) 06937 R R ST CLAIR ECOSG LNFORMATION ONLN.
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REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION RETENTION 421734 OCONEE 1 CYCLE 29 CORE OPERATING LIMITS REPORT Page 1 of 1 Duke Energy P.O. Box 1006 Energy Center EC04T Charlotte, N.C.
Reed By 1
28201-1006 Date 4
DOCUMENT NO QACOND REV #/ DATE DISTR CODE 1
3 4
5 6
7 8
9 10 ill 12 13 14 15 TOTAL 4
1 4
ONEI-0400-050 1
035 10/07/14 NOMD-27 X
vi 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:
A L LANG ALG/ZLA EC08G
'ONEI-0400-50 Rev 35 Page 1 of 24 Duke Energy Oconee I Cycle 29 Core Operating Limits Report QA Condition I OJXY 1ý1 Prepared By: A.L. Lang
~C (~
Reviewed By: L.D. McClain CDR By: K. A. Hemker Approved By: R.R. St.Clair Date:
C0/*2/H q
Date:.2, Ocf2-f"lb Date:
0)L4-Date:
101A/lxoL-
ONEI-0400-50 Rev 35 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 35 Page 3 of 24 Oconee 1 Cycle 29 Core Operating Limits Report Insertion Sheet for Revision 35 This revision is not valid until the end of operation for Oconee 1 Cycle 28.
Remove these Revision 34 pages Insert these Revision 35 pages 1-33 1-24 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 1 Cycle 29 revisions below 35 Oct 2014 1-24 25-33 24 Oconee 1 Cycle 28 revisions below 34 Apr 2013 1-33 33 33 Oct 2012 1-33 33 IOconee 1 Cycle 27 revisions below 32 Mar 2011 1-33 33 Oconee I Cycle 26 revisions below 31 Nov 20b09 1 -33 33 30 Nov 2009 1-33 33 29 Nov 2009 1-33 33 28 Sep 2009 1-33 33 Oconee I Cycle 25 revisions below 27 Apr2008 1-33 33 Oconee 1 Cycle 24 revisions below 26 Oct2006 1-33 33 Oconee 1 Cycle 23 revisions below 25 Apr2005 1-33 33
ONEI-0400-50 Rev 35 Page 4 of 24 Oconee 1 Cycle 29 Table Of Contents Section 1.0 Error Adlusted Core Ooeratina 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 (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 Umits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpoints 3.4.1 RCS Pressure, Temperature, and Flow 4, 5, 7, 8 RCS Pressure, Temperature, Departure from Nucleate Boiling Limits and Flow 3.5.1 Core Flood Tanks (CFTs) 1, 3, 7,8 Boron Concentration 3.5.4 Borated Water Storage Tank (BWST) 1, 3, 7,8 Boron Concentration 3.7.12 Spent Fuel Pool Boron Concentration 1, 3, 7.8 Boron Concentration 3.9.1 Boron Concentration (RCS and 1,3, 7.8 Boron Concentration Refueling Canal) 5.6.5 Core Operating Limits Report (COLR)
None References NRC Approved Methodology SLC Number Reference #
COLR Parameter 16.5.13 High Pressure Injection and Chemical 1, 3, 7,8 Volume and Boron Concentration Addition Systems of Concentrated Boric Acid Storage Tank (CBAST)
Section 2.0 Core Operating Limits - Not Error Adiusted (NOT FOR PLANT USE)
NRC Approved Methodology TS Number Technical Specification Reference #
COLR Parameter 2.1.1 Safety Limits 1,2, 3,4, 5, Variable Low RCS Pressure 8, 7, 8, 9, 10 Protective Limits Axial Power Imbalance Protective Limits 3.2.1 Regulating Rod Position Limits 1, 3, 4, 57, 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 35 Page 5 of 24 Oconee 1 Cycle 29 1.0 Error Adjusted Core Operating Umits The Core Operating Limits Report for 01 C29 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 OIC29 by References 15 through 17. The O1C29 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 O1C29 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.
- 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.
- 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. 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-1 1268, Revision 0, July 2014.
- 16. 01C29 Specific DNB Evaluation, OSC-11277, Revision 0, July 2014.
- 17. 01 C29 Reload Safety Evaluation, OSC-11283, Revision 0, October 2014.
ONEI-0400-50 Rev 35 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% 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 I *F
+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 pslg 3 RCP:
measured hot leg pressure > 2125 psig DNB parameter for RCS loop average temperature shall be:
Max Loop Tavg (Incl 29F unc)
Referred to by TS 3.4.1.
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%
- 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-0400-50 Rev 35 Page 7 of 24 Oconee 1 Cycle 29 EFPD 0 to 615 615 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 +/- 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-0400-50 Rev 35 Page 8 of 24 Oconee 1 Cycle 29 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P = 2355 psig T =618 OF 2300 2200 M 2100 Acceptable Operation 0.
P= 11.14 *Tout - 4706 2000 (D
Unacceptable 1900 Operation P = 1800 psig 1800 T = 584 °F 1700 I
I i
q 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, OF
ONEI-0400-50 Rev 35 Page 9 of 24 Oconee 1 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 Pmax =>
109.4 14.4 90.0 35.0 0.0 35.0 3 Pumps 0.0
-35.0 62.3
-35.0 Pmax =>
81.7
-14.4 Pmax =>
81.7 14.4 62.3 35.0 0.0 35.0
ONEI-0400-50 Rev 35 Page 10 of 24 Oconee 1 Cycle 29 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
-26.6
-26.9 80.0
-28.0
-26.6
-26.9 90.0
-28.0
-26.6
-26.9 100.0
-17.7
-17.7
-17.7 102.0
-15.6
-15.6
-15.6 102.0 15.6 10.4 11.0 100.0 17.7 13.6 14.2 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
-26.6 63.1
-28.0 64.1 64.4
-26.6 77.0
-13.2
-13.2 77.0 13.2 13.2 63.1 28.0 28.0 0.0 28.0 28.0 Referred to by TS 3.2.2
-26.9
-26.9
-13.2 13.2 28.0 28.0
ONEI-0400-50 Rev 35 Page 11 of 24 Oconee 1 Cycle 29 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
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0 14.4 16.4 17.5 18.5 19.6 20.7 21.7 22.8 23.9 24.9 26.0 27.0 28.1 29.2 30.2 31.3 32.3 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0 33.0
-15.6
-16.7
-17.7
-18.7
-19.8
-20.8
-21.8
-22.9
-23.9
-24.9
-25.9
-27.0
-27.6
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0
-28.0 15.6 16.7 17.7 18.7 19.8 20.8 21.8 22.9 23.9 24.9 25.9 27.0 27.6 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0
-15.6
-16.7
-17.7
-18.6
-19.5
-20.5
-21.4
-22.3
-23.2
-24.1
-25.1
-26.0
-26.5
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9 11.0 12.6 14.2 15.6 17.0 18.3 19.7 21.1 22.5 23.9 25.2 26.6 27.5 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0 28.0
Full Incore Alarm I
Out of Core Alarm ONEI-0400-50 Rev 35 Page 12 of 24 Oconee I 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 63.1 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
-33.0
-33.0
-33.0
-33.0
-33.0
-33.0 14.4 15.0 16.1 17.1 18.2 19.3 20.3 21.4 22.4 23.5 24.6 25.6 26.7 27.8 28.8 29.9 30.9 31.9 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
-26.9
-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 24.9 25.9 26.9 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
-24.9
-25.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9
-26.9 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 28.0 28.0 28.0 28.0 28.0 28.0
% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-50 Rev 35 Oconee 1 Cycle 29 Page 13 of 24 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0 9(14.4,107.9) 100.0 Acceptable 4 Pump Operation (33.0,90.4)
(14.4,80.6) 60.0 (33.0,63.1)
Acceptable 3 or 4 Pump Operation 40.0 20.0
-10.0 0.0 10.0 20.0 30.0 40.0
-40.0
-30.0
-20.0 Percent Power Imbalance
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 ONEI-0400-50 Rev 35 Page 14 of 24 110 100 90 80 70 60 L.
50 2
4O
- 0) a. 40 30 20 10 0 i
,-3.
40
-35
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 Percent Axial Imbalance
Oconee I Cycle 29 ONEI-0400-50 Rev 35 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 Page 15 of 24 110 100 90 8o 70 60 LL 0-50 40 30 20 10 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 35 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 35 Page 17 of 24 Oconee 1 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
I Oconee I Cycle 29 Referred to by TS 3.2.1 ONEI-0400-50 Rev 35 Page 18 of 24 105 102.0
.102.0 300.0,102.0:
IUD) 100 10C Control Rod Position Setpoints 221.5, 100.0..
0.
95 No Inoperable Rods, 4 Pump Flow, 2.1....
95 90 BOC to EOC 90 85 251.5,90.0 85 80 80 75 75 70 70 65 25067665 a.
60 Unacceptable 60
~HOpe tion Rsrce tý 55
........55 n50 Acceptable 50 141.5,4,8.0.
Operation H
t45 45 M 40 40
- 125.0. 39.1
- 75.0, 41.6 35 35 30 30 25 25 20 125..
20 15 7
15 10 10 5
0.0, 2
8 8
6,_"_*
5 15 25 35 45 55 65 75 85 9
0 10 20 30 40 50 60 70 80 90 100o I0 10 20 30 40 50 60 70 80 90 10oo 0
I Group 5 Control Rod Posifion, % WD
I Oconee I Cycle 29 1 Referred to by TS 3.2.1 ONEI-0400-50 Rev 35 Page 19 of 24 105 100 95 90 85 80 75 Control Rod Position Setpoints No Inoperable Rods, 3 Pump Flow, BOC to EOC 105 100 95 90 85 300.0. 77.0 80 75 70 227.4,77.1 i, 77.01
), 76.:
.5, 75.0 ý234.
75.:
70 0-LiL 50 65 60 55 50 45 40 I.1 99rn I Unacceptable Operation 175.0,.59.3 65 60 I
55 141.5,48.0 Restricted Operation 201.5, 50.0 jf+195.2,48.-09 125A 3AQ 175.0,41.1 35 30 25 20 Acceptable Operation 50 45 40 35 30 25 20 15
, &a.
15w 10 ill35I 3.0 0.0, 2.8 1.5, 15.0 Group 5 10 5
0 16.5, 5.01 1i5 15S 25 35 45 55 65 75 RS QS I 15 15 25 35 45 55 65 75 85 95 1 10 10 20 30 40 50 60 70 80 90 100 I 10 10 20 30 40 50 60 70 80 90 100j I
I 0.0, 0.0 Group 5 G
Control Rod Position, % WD F-G-rou-p 1
I I
Oconee I Cycle 29 I
Referred to by TS 3.2.1 105 100 95 90 85 80 75 70 65 60 55 50 45 7'
T Control Rod Position Setpoints I Inoperable Rod, 4 Pump Flow, ONEI-0400-50 Rev 35 Page 20 of 24 300.0. 102.0 f..283.4,102.0.
pi S8.5,0.0......
t10 100 95 90 85 80 75 (L
LL 0) 0~
0:
Unacceptable Operation 70 65 60 55 50 45 40 225.0,448~
KAcceptable Operation 40 35 30 25 20 15 10 5
175.
19*8 161.5,13.0 35 30 25 20 15 10 5
0 flfljf L'L1'LUL`LH
125.0. 8.7 7674 380 ;2 w8a nM Group 6 1 l 1.,0.
E 7C Occ f
f0 Ij11.1fffT I.1
- J lh YJ1FJ U
- 14.
U4J p7;j 10 10 20 30 40 50 60 70 80 90 100 1
I 0 10 20 30 40 50 60 70 80 90 100 I Group 5 Control Rod Position, % WD Group 7 I
Control Rod Position, % WD I Group 7
I Oconee I Cycle 29 I
Referred to by TS 3.2.1 105 100 95 90 85 80 75 70 ONEI-0400-50 Rev 35 Pae e21aof24 Control Rod Position Setpoints, I Inoperable Rod, 3 Pump Flow,.
BOC to EOC 105 100 95 90 85 80 75 70 65 300.0, 77.0
+?1""M M I i i. I.I.,
285.2, 77.0 281.5
,75.0 M
U-a-
n..
2 rU 65 60 55 50 45 40 35 30 25 20 15 10 5
Unacceptable Operation 231.5, 48.0 44M4&a4L1
....ff4-.
4 225.0,44.8
,I Acceptable Operation I
60 55 50 45 40 35 30 25 20 15 181 15.1 0 9.8 161-5.!3-0 I'I 5n
' ' 3 n 0
.. 125.0,8.7 A
vo I V.V 74.8, 2.82 fl-i*
5 15 25 35 45 55 65 51.0.0.0 11 7
A R
_sis I
10 5
0 0
75 85 95 t0 10 20 30 40 50 60 70 80 90 100 I
I 0 10 20 30 40 50 60 70 80 90 100 1 I Group 5 Control Rod Position, % WD I Group 7
ONEI-0400-50 Rev 35 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.
Core Power Level, Quadrant Power T Core Outl p
I 2(2 2
2:
%FP
(
ilt, %
1 Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State T
S-30
> 30 0-30 0.00 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 et Pressure Reactor Coolant Outlet Temperature, °F sia 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 35 Page 23 of 24 Oconee 1 Cycle 29 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1 4 Pumps 3 Pumps
%FP 0.0 80.0 90.0 100.0 109.4 109.4 100.0 90.0 80.0 0.0 0.0 62.3 77.0 81.7 81.7 77.0 62.3 0.0 RPS Operational
-35.0
-35.0
-14.4 14.4 35.0 35.0
-35.0
-35.0
-14.4 14.4 35.0 35.0
-38.2
-38.2
-38.2
-28.4 24.1 39.5 39.5 39.5
-38.2
-38.2 39.5 39.5
ONEI-0400-50 Rev 35 Page 24 of 24 Oconee 1 Cycle 29 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit
%FP Insertion Limit No Inop Rod I Inop Rod 4 Pumps 102 100 90 80 50 15 5
262 260 250 240 200 90 0
236 200 90 0
220 140 75 0
220 140 75 0
280 230 160 75 280 230 160 75 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300 3 Pumps 77 50 15 5