ONS-2017-004, Submittal of Core Operating Limits Report
| ML17017A167 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 01/12/2017 |
| From: | Teresa Ray Duke Energy Carolinas |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| ONS-2017-004 | |
| Download: ML17017A167 (48) | |
Text
ef_~DUKE
~ ENERGY ONS-2017-004 January 12, 2017 ATTN: Document Control Desk U. S. Nuclear Regulatory Commission Washington, DC 20555-0001 Duke Energy Carolinas, LLC (Duke Energy)
Oconee Nuclear Station (ONS) Units 1 and 3 Docket Nos. 50-269 and 50-287 Renewed License Nos. DPR-38 and DPR-55
Subject:
Submittal of Core Operating Limits Report (COLR) for Units 1 and 3 Thomas D. Ray Vice President Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC 29672 o: 864.873.5016 f: 864.873. 4208 Tom.Ray@duke-energy.com Attached, pursuant to Oconee Technical Specification 5.6.5.d, is an information copy of the COLR for Oconee Unit 1, Cycle 30, and Oconee Unit 3, Cycle 29.
If you have any questions regarding this submittal, please contact Stephen C. Newman, Oconee Regulatory Affairs, at 864-873-4388.
Sincerely,
~-p~
Vice President, Oconee Nuclear Station : Oconee Unit 1 Cycle 30 COLR : Oconee Unit 3 Cycle 29 COLR
U. S. Nuclear Regulatory Commission January 12, 2017 Page 2 cc w/attachments :
Ms. Catherine. Haney Administrator Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, Georgia 30303-1257 Mr. James R. Hall, Project Manager (ONS)
(by electronic mail only)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-881 Rockville, MD 20852 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Oconee Unit 1 Cycle 30 COLR
Oconee 1 Cycle 30 ONEl-0400-470 Core Operating Limits Report Rev. 0 AD-EG-ALL-1176 (Rev. 0\\
Manual Certification Form Page 1
of 22 Plant:
Oconee Unit:
1 Quality Level:
1
Title:
Oconee 1 Cycle 30 Core Operating Limits Report Duke Energy File Number:
ONEl-0400-470 Revision Number:
0 Vendor:
N/A Vendor Document Number:
N/A Responsible Engineer:
(or vendor name & P.O. Number, if applicable)
N/A Prepared By:
Design Verified By:
Approved By:
Approved By Owner:
(N/A except when document revision is prepared, Design Verified, and approved above by a vendor)
L.C. James II (signed electronically)
J.D. Forster (signed electronically)
R.R. St.Clair (signed electronically)
Revision
Description:
ORIGINAL ISSUE (REVISION 0)
NOTES:
Date:
Date:
Date:
Date:
For Vendor Manuals Only The 01C30 COLR requires the reload 50.59 to be approved prior to implementation and fuel loading.
Revision 0 may become effective anytime during NO MODE between cycles 29 and 30, but it must become effective prior to entering MODE 6 at the onset of cycle 30.
The 01 C30 COLR will cease to be effective during NO MODE between cycles 30 and 31.
Material Removed from Manual Material Inserted into Manual Pages 1 through 22
Oconee 1 Cycle 30 Table Of Contents Section 1.0 Error Adjusted Core Operating Limits NRC Approved Methodology TS Number Technical Specification Reference#
2.1.1 Safety Limits 1, 2, 3, 4, 5, 6, 7, 8,9, 10 3.1.1 Shutdown Margin (SOM}
1, 3, 7,8 3.1.3 Moderator Temperature Coefficient (MTC) 1, 3, 7 3.1.4 Control Rod Group Alignment Limits 1,3, 7, 8 3.1.5 Safety Rod Position Limits 1,3, 4, 5, 7, 8, 9, 10 3.2.1 Regulating Rod Position Limits 1,3,4,5, 7,8,9, 10 3.2.2 Axial Power Imbalance Operating Limits 1, 2, 3, 4, 5, 7,8, 9, 10 3.2.3 Quadrant Power Tilt (QPT}
1, 3, 7, 9, 10 3.3.1 Reactor Protective System (RPS) 1, 2, 3, 4, 5, Instrumentation 6, 7,8,9, 10 3.4.1 RCS Pressure, Temperature, and Flow 4,5, 7,8 Departure from Nucleate Boiling Limits 3.5.1 Core Flood Tanks (CFTs) 1,3, 7,8 3.5.4 Borated Water Storage Tank (BWST) 1,3, 7,8 3.7.12 Spent Fuel Pool Boron Concentration 1,3, 7,8 3.9.1 Boron Concentration (RCS and 1,3, 7,8 Refueling Canal}
5.6.5 Core Operating Limits Report (COLR)
None NRC Approved Methodology SLC Number Reference#
16.5.13 High Pressure Injection and Chemical 1,3, 7,8 Addition Systems ONEl-0400-470 Rev 0 Page 2 of 22 COLR Parameter Maximum Allowed RPS Power Imbalance Limits Shutdown Margin MTC Misaligned, Dropped, or Inoperable Misaligned, Dropped, or Inoperable Withdrawal Sequence and Overlap 4-pump No Inoperable Rod CR Position Setpoints 3-pump No Inoperable Rod CR Position Setpoints 4-pump Operational Power Imbalance Setpoints 3-pump Operational Power Imbalance Setpoints QPT Setpoints Correlation Slope Variable Low RCS Pressure RPS Setpoints Maximum Allowed RPS Power Imbalance Limits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpoints RCS Pressure, Temperature, and Flow Boron Concentration Boron Concentration Boron Concentration Boron Concentration References COLR Parameter Volume and Boron Concentration of Concentrated Boric Acid Storage Tank (CBAST)
Section 2.0 Core Operating Limits - Not Error Adjusted (NOT FOR PLANT USE)
TS Number Technical Specification 2.1.1 Safety Limits 3.2.1 Regulating Rod Position Limits 3.2.3 Quadrant Power Tilt (QPT)
NRC Approved Methodology Reference #
COLR Parameter 1, 2, 3, 4, 5, Variable Low RCS Pressure 6, 7, 8, 9, 10 Protective Limits Axial Power Imbalance Protective Limits 1, 3, 4, 5, 7, 8, 9, 10 Rod Index Limits 1, 3, 7, 9, 10 Quadrant Power Tilt Limits
Oconee 1 Cycle 30 1.0 Error Adjusted Core Operating Limits ONEl-0400-470 Rev 0 Page 3 of22 The Core Operating Limits Report for 01 C30 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 01C30 by References 15 through 16. The 01C30 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, radial local peaking {E'ih) 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 01 C30 reload core.
1.1 References
- 1. Oconee Nuclear Design Methodology Using CASM0-4 / 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.
- 5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, SE dated October 29, 2008.
- 6. Fuel Mechanical Reload Analysis Methodology Using TAC03 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..'1Tc and EOC Reduced Tavg Operation, OSC-7265, Revision 1, June 2002.
- 15. 01C30 Maneuvering Analysis, OSC-11546, Revision 1.
- 16. 01 C30 Reload Safety Evaluation, OSC-11634, Revision 0.
ONEl-0400-470 Rev 0 Page 4 of 22 Oconee 1 Cycle 30 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 (SOM) shall be greater than 1%.1k/k.
Referred to by TS 3.1.1.
Moderator Temperature Coefficient (MTC) shall be less than:
Linear interpolation is valid within the table provided.
Referred to by TS 3.1.3:
MTC x 10-4
.1p I °F
+0.70
+0.525 0.00 0.00 0.00
%FP 0
20 80 100 120 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:
Referred to by TS 3.4.1.
The measured Tavg must be less than COLR limits minus instrument uncertainty..1Tc is the setpoint value selected by the operators.
Max Loop Tavg (Incl 2°F unc)
581.0 581.0 1
581.4 581.2 2
581.8 581.4 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:
Referred to by TS 3.4.1.
4RCP:
3RCP:
Measured ;:::: 109.5 %df 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).
Oconee 1 Cycle 30 Steady State Operating Band Rod Index APSR %WO EFPD Min Max Min Max 0 to 615 292 +/- 5 615 to EOG 292 +/- 5 300 300 30 100 40 100 Quadrant Power Tilt Setpoints Steady State Transient Core Power Level, %FP 0 - 30
> 30 0 - 30
> 30 Full lncore 7.61 3.50 9.40 7.11 Out of Core 6.09 2.35 7.72 5.63 Backup lncore 3.87 2.25 4.81 3.63 Referred to by TS 3.2.3 Correlation Slope (CS) 1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
ONEl-0400-470 Rev 0 Page 5 of 22 Maximum
>O 16.55 14.22 10.07
(.!)
Ci5 a..
a)
- I en en
~
a.. c tl3 Ci 0
(.)
0 t5 tl3 Q) a:
P = 2355 psig 2300 2200 2100 2000 1900 P = 1800 psig Oconee 1 Cycle 30 ONEl-0400-470 Rev 0 Page 6 of 22 Variable Low RCS Pressure RPS Setpoints Acceptable Operation Referred to by TS 3.3.1 P = 11.14
- Tout - 4 706
~
T = 584 °F Unacceptable Operation 1700 -l-~~~~~-+-~~~~~-+-~~~~~-i-~~~~~~
..... ~~~~---t 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, °F
Oconee 1 Cycle 30 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 ONEl-0400-470 Rev 0 Page 7 of 22
ONEl-0400-470 Rev 0 Page 8 of 22 Oconee 1 Cycle 30 Operational Power Imbalance Setpoints Referred to by TS 3.2.2 Full Backup Out of
%FP lncore lncore Core 4 Pumps 0.0
-28.0
-27.2
-27.5 80.0
-28.0
-27.2
-27.. 5 90.0
-28.0
-24.0
-24.3 100.0
-17.7
-17.5
-17.7 102.0
-15.6
-15.6
-15.6 102.0 15.6 11.0 11.6 100.0 17.7 13.1 13.7 90.0 28.0 24.0 24.5 80.0 28.0 28.0 28.0 0.0 28.0 28.0 28.0 3 Pumps 0.0
-28.0
-27.2
-27.5 63.1
-28.0 63.5
-27.5 63.8
-27.2 77.0
-13.2
-13.2
-13.2 77.0 13.2 13.2 13.2 63.1 28.0 28.0 28.0 0.0 28.0 28.0 28.0 Referred to by TS 3.2.2
%FP 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
% FP Oconee 1 Cycle 30 ONEl-0400-470 Rev 0 Page 9 of 22 RPS I Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOG Referred to by TS 3.2.2 and TS 3.3.1 RPS Trip Full lncore Alarm Out of Core Alarm
-14.4 14.4
-16.4 16.4
-17.5 17.5
-18.5 18.5
-19.6 19.6
-20.7 20.7
-15.6 15.6
-15.6 11.6
-21.7 21.7
-16.7 16.7
-16.7 12.7
-22.8 22.8
-17.7 17.7
-17.7 13.7
-23.9 23.9
-18.7 18.7
-18.4 14.8
-24.9 24.9
-19.8 19.8
-19.0 15.9
-26.0 26.0
-20.8 20.8
-19.7 16.9
-27.0 27.0
-21.8 21.8
-20.3 18.0
-28.1 28.1
-22.9 22.9
-21.0 19.1
-29.2 29.2
-23.9 23.9
-21.7 20.2
-30.2 30.2
-24.9 24.9
-22.3 21.3
-31.3 31.3
-25.9 25.9
-23.0 22.3
-32.3 32.3
-27.0 27.0
-23.6 23.4
-33.0 33.0
-27.6 27.6
-24.0 24.1
-33.0 33.0
-28.0 28.0
-24.3 24.5
-33.0 33.0
-28.0 28.0
-24.6 24.9
-33.0 33.0
-28.0 28.0
-24.9 25.2
-33.0 33.0
-28.0 28.0
-25.3 25.6
-33.0 33.0
-28.0 28.0
-25.6 25.9
-33.0 33.0
-28.0 28.0
-25.9 26.3
-33.0 33.0
-28.0 28.0
-26.2 26.6
-33.0 33.0
-28.0 28.0
-26.5 27.0
-33.0 33.0
-28.0 28.0
-26.9 27.3
-33.0 33.0
-28.0 28.0
-27.2 27.7
-33.0 33.0
-28.0 28.0
-27.5 28.0
-33.0 33.0
-28.0 28.0
-27.5 28.0 RPS Trip Full lncore Alarm Out of Core Alarm
%FP 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 63.5 63.1 63.0 62.0 61.0 60.0 0.0
% FP Oconee 1 Cycle 30 ONEl-0400-470 Rev 0 Page 10 of 22 RPS I Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 RPS Trip Full lncore Alarm Out of Core Alarm
-14.4 14.4
-15.0 15.0
-16.1 16.1
-17.1 17.1
-18.2 18.2
-13.2 13.2
-13.2 13.2
-19.3 19.3
-14.3 14.3
-14.3 14.3
-20.3 20.3
-15.3 15.3
-15.3 15.3
-21.4 21.4
-16.4 16.4
-16.4 16.4
-22.4 22.4
-17.4 17.4
-17.4 17.4
-23.5 23.5
-18.5 18.5
-18.5 18.5
-24.6 24.6
-19.6 19.6
-19.6 19.6
-25.6 25.6
-20.6 20.6
-20.6 20.6
-26.7 26.7
-21.7 21.7
-21.7 21.7
-27.8 27.8
-22.8 22.8
-22.8 22.8
-28.8 28.8
-23.8 23.8
-23.8 23.8
-29.9 29.9
-24.9 24.9
-24.9 24.9
-30.9 30.9
-25.9 25.9
-25.9 25.9
-32.0 32.0
-27.0 27.0
-27.0 27.0
-32.5 32.5
-27.5 27.5
-27.5 27.5
-33.0 33.0
-28.0 28.0
-27.5 28.0
-33.0 33.0
-28.0 28.0
-27.5 28.0
-33.0 33.0
-28.0 28.0
-27.5 28.0
-33.0 33.0
-28.0 28.0
-27.5 28.0
-33.0 33.0
-28.0 28.0
-27.5 28.0
-33.0 33.0
-28.0 28.0
-27.5 28.0 RPS Trip Full lncore Alarm Out of Core Alarm
Oconee 1 Cycle 30 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0
(-14.4,107.9)
(14.4,107.9
- .A<-~~~~~--+--~~-'--'-~-?!(..
100.0 M1=0.942 r
Acceptable 4 Pump Operation
(-33.0,90.4) 60.0
(-33.0,63.1)
Acceptable 3 or 4 Pump Operation 40.0 20.0
-40.0
-30.0
-20.0
-10.0 0.0 10.0 Percent Power Imbalance ONEl-0400-470 Rev 0 Page 11of22 M2=-0.942~
(33.0,90.4)
(33.0,63.1) 20.0 30.0 40.0
Oconee 1 Cycle 30 Imbalance Setpoints for 4 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1
-14.4, 107.9
-15.6, 102.0
-17.5, 100.0 14.4, 107.9 11.0, 102.0 13.1,100.0 ONEl-0400-470 Rev 0 Page 12 of 22 RPS Trip Setpoint 33.0, 90.4 ~::::::
-24.0, 90.0 24.0, 90.0
-27.2, 80.0 28.0, 80.0 t=t::t=l=t:tl:::t=t=t::t:::t=tlll=t=t=t=t::t=l=t:tl:::I Labels Correspond to the Backup lncore Alarm Setpoints 20 10
- = -33.0, 0.0 0
-40
-35
-27.2, 0.0
-30
-25
-20
-15
-10
-5 0
5 Percent Axial Imbalance Backup lncore
-outcore
-lncore
_._RPS Trip 28.0, 0.0 33.0, 0.0==
10 15 20 25 30 35 40
110 100 90 80 RPS Trip Setpoint 70
~
. -33.0, 63.1 0 a..
60
-27.2, 63.8
- u.
0 c 50 Q)
~
Q) a..
40 30 20 10
~ -33. 0' 0. 0 ::t::l=t=t=t:=t=ll:ll: -2 7. 2, 0. 0 0
-40
-35
-30
-25
-20 Oconee 1 Cycle 30 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1
-14.4, 80.6 14.4, 80.6
-13.2, 77.0 13.2, 77.0 Labels Correspond to the Backup lncore Alarm Setpoints ONEl-0400-470 Rev 0 Page 13 of 22 RPS Trip Setpoint =t=i:::::t=:1=1==1=l=I 33.0, 63.1 = =
28.0, 63.1
~
Backup I ncore ::::t:::l=t=t=t:::t::l=l=:t::t:::!=l=t=t:=l=t=t:::t:=!=l=:t::::I
-outcore
-lncore
-RPS Trip 28.0, 0.0 33.0, 0.0 =~
-15
-10
-5 0
5 10 15 20 25 30 35 40 Percent Axial Imbalance
ONEl-0400-470 Rev 0 Page 14 of 22 Oconee 1 Cycle 30 Operational Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint RI Withdrawal
%FP No lnop Rod 1 lnop Rod Setpoint 4 Pumps 102.0 263.5 283.4 300 100.0 261.5 281.5 300 90.0 251.5 271.9 300 80.0 241.5 262.3 300 50.0 201.5 233.4 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 237.5 285.2 300 75.0 234.8 281.5 300 50.0 201.5 235.2 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300
ONEl-0400-470 Rev 0 Page 15 of 22 Oconee 1 Cycle 30 Shutdown Margin Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint RI Withdrawal
%FP No lnop Rod 1 lnop Rod Setpoint 4 Pumps 102.0 224.6 283.4 300 100.0 221.5 281.5 300 48.0 141.5 231.5 300 13.0 76.5 161.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 227.4 285.2 300 75.0 221.5 281.5 300 48.0 141.5 231.5 300 13.0 76.5 161.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300
105 100 95 90 85 80 75 70 65 a_
LL 60
..: 55 Q) 3:
0 50 a_
~ 45 co Q) 0:::
40 35 30 25 20 15 10 1.5, 3.0 5 0.0, 2.8 tm1 0 l!llO.O, 0.0 lo 10 Oconee 1 Cycle 30 1-llHtl-1*:( _,_....
Control Rod Position Setpoints No Inoperable Rods, 4 Pump Flow, BOC to EOC Referred to by TS 3.2.1 224.6, 102.0 221.5, 100.0 175.0, 69.8 ONEl-0400-470 Rev 0 Page 16 of 22 263.5, 10~"0H 300.0, 102.0 :
261.5, 100.0 251.5, 90.0
+HJI 241.5, 80.0 1
105 00 95 90 225.0, 67.6 85 80 75 70 65 60 55 50 45 40 35 30 Unacceptable Operation Restricted Operation 201.5, 50.0
-- 141.5, 48.0
-- - mmura11 195.2, 48.0 125.0, 39.1 175.0, 41.6 125.0, 25.7 76.5, 13.0 91.5, 15.0 75.0, 12.8 Group 6 16.5, 5.0 5
15 25 35 45 55 65 75 85 95 20 30 40 50 60 70 80 90 100 I lo 10 20 30 I Group 5 I Control Rod Position, % WO Acceptable Operation 40 50 60 70 Group 7 80 90 2
2 1
1 5
0 1001 5
0 5
0
105 100 95 90 85 80 75 70 65 a..
LL 60
~
0 55 Q)
~
0 50 a..
L.
~ 45 Cll Q) 0:::
40 35 30 25 20 15 10 5
0 Oconee 1 Cycle 30 Referred to by TS 3.2.1 Control Rod Position Setpoints No Inoperable Rods, 3 Pump Flow, BOC to EOC Unacceptable 175.0, 59.3 Operation 141.5, 48.0 Restricted Operation 125.0, 39.1 125.0, 25.7 76.5. 13.og 91.5, 15.0 1.5, 3.0 75.0, 12.8 0.0, 2.8 Group 6 227.4, 77.0 225.0, 76.2 221.5, 75.0 237.5, 77.0 234.8, 75.0
+1::
ONEl-0400-470 Rev 0 Page 17 of 22 300.0, 77.0.
225.0, 67.6 201.5, 50.0 195.2, 48.0 175.0, 41.6 Acceptable Operation 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5
16.5, 5.0 5
15 25 35 45 55 65 75 85 95 Io 10 20 30 40 50 60 70 80 90 100 I 10 0.0, 0.0 I Group 5 I Control Rod Position, % WD 10 20 30 40 50 60 I Group 7 I 70 80 0
90 100 I
ONEI 0400 470 Rev 0 105 Oconee 1 Cycle 30 Referred to by TS 3.2.1 Page 18 of 22 10
~
300.0, 102.0 5
283.4, 102.0 100 10 Control Rod Position Setpoints 281.5, 100.0 0
95 1 Inoperable Rod, 4 Pump Flow, 95 BOC to EOC 90 90 85 85 80 80 75 75 70 70 65 Cl..
LL 60
~
0 Unacceptable 65 Operation 60
...: 55 Q)
~
55 0
Cl..
50 0
t5 45 co Q) 231.5, 48.0 Acceptable 50 Operation 225.0, 44.8 45 n:::
40 40 35 35 30 30 25 25 20 175.0, 19.8 20 15 -
161.5, 13.0 15 10 125.0, 8.7 76.5, 3.0 10 5
75.0, 2.82 ll "'
Group 6 5
u 51.0, 0.0 74.8, 2.8 "
5 15 25 35 45 55 65 75 85 95 u
0 -
0 lo 10 20 30 40 50 60 70 80 90 100 I I o 10 20 30 40 50 60 70 80 90 100 I I Group 5 I Control Rod Position, % WO I Group 7 I
I 105 100 95 90 85 80 75 70 65 a..
LL 60 cf:.
~ 55 0
a..
50
..... £ Cll 45 Q) 0::
40 35 30 25 20 15 10 5
0 lo L_
I I
I 10 20 Oconee 1 Cycle 30 Referred to by TS 3.2.1 Il l Ill 11 11 Control Rod Position Setpoints 1 Inoperable Rod, 3 Pump Flow, BOC to EOC Unacceptable Operation 231.5, 48.0 I
225.0, 44.8 175.0, 19.8 I
I 161.5, 13.0 76.5, 3.0 125.0, 8.7 75.0, 2.82..
... ~
Group 6 74.8, 2.8 51.0, 0.0
"'""'"""'" ::r-5 15 25 35 45 55 65 75 85 95 30 40 50 60 70 80 90 100 I o 10 20 I Group 5 I Control Rod Position, % WO ONEl-0400-470 Rev 0 p
19 f 22 a e 0
- 10 5 10 0 95 90 85 300.0, 77.0 80 285.2, 77.0 281.5, 75.0 75 70 65 60 55
. 50 45 Acceptable Operation 40 35 30 25 20 15 10 5
0 30 40 50 60 70 80 90 100 I Group 7 I
Oconee 1 Cycle 30 2.0 Core Operating Limits -- Not Error Adjusted ONEl-0400-470 Rev 0 Page 20 of 22 The data provided on the following pages satisfies a licensing commitment to identify specific parameters before instrumentation uncertainties are incorporated.
References provided in section 1 of this COLR identify the sources for the data which follows.
Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State
- Transient Core Power Level, %FP 0 - 30
> 30 0 - 30
> 30 Quadrant Power Tilt, %
10.00 5.40 12.00 9.44 Variable Low RCS Pressure Protective Limits Core Outlet Pressure psia 1800 1900 2000 2100 2200 2300 Referred to by TS 2.1.1 Reactor Coolant Outlet Temperature, °F 3 RCS Pumps 4 RCS Pumps 581.0 590.0 598.9 607.9 616.9 625.9 578.3 587.3 596.3 605.2 614.2 623.2 Maximum
>O 20.00
Oconee 1 Cycle 30 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1
%FP RPS Operational 4 Pumps 0.0
-35.0
-39.0 80.0
-39.0 90.0
-35.0
-35.8 100.0
-28.4 109.4
-14.4 109.4 14.4 100.0 23.5 90.0 35.0 36.0 80.0 39.5 0.0 35.0 39.5 3 Pumps 0.0
-35.0
-39.0 62.3
-35.0 77.0
-39.0 81.7
-14.4 81.7 14.4 77.0 39.5 62.3 35.0 0.0 35.0 39.5 ONEl-0400-470 Rev 0 Page 21of22
4 Pumps 3 Pumps
%FP 102 100 90 80 50 15 5
77 50 15 5
Oconee 1 Cycle 30 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit Insertion Limit 262 260 250 240 200 90 0
236 200 90 0
No lnop Rod 220 140 75 0
220 140 75 0
1 lnop Rod 280 230 160 75 280 230 160 75 ONEl-0400-470 Rev 0 Page 22 of 22 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300 Oconee Unit 3 Cycle 29 COLR
Oconee 3 Cycle 29 Core Operating Limits Report AD-EG-ALL-1176 (Rev. Ol Manual Certification Form Plant:
Oconee Unit:
3 Quality Level:
Title:
Oconee 3 Cycle 29 Core Operating Limits Report Duke Energy File Number:
ONEl-0400-459 Revision Number:
0
- ~ection.. 2 Vendor:
N/A Vendor Document Number:
N/A SeCtion 3 (Only re(Juired when routing a.1)1anual.for hardcopy s(gnaturejt Responsible Engineer:
(or vendor name & P.O. Number, if applicable)
N/A Prepared By:
Design Verified By:
Approved By:
Approved By Owner:
(N/A except when document revision is prepared, Design Verified, and approved above by a vendor)
D.S. Orr (signed electronically)
A.L. Lang (signed electronically)
R.R. St.Clair (signed electronically)
Revision
Description:
ORIGINAL ISSUE (REVISION 0)
NOTES:
Date:
Date:
Date:
Date:
ONEl-0400-459 Rev.a For Vendor Manuals Only The 03C29 COLR requires the reload 50.59 to be approved prior to implementation and fuel loading.
Revision 0 may become effective anytime during NO MODE between cycles 28 and 29, but it must become effective prior to entering MODE 6 at the onset of cycle 29.
The 03C29 COLR will cease to be effective during NO MODE between cycles 29 and 30.
Material Removed from Manual Material Inserted into Manual Pages 1 through 22
Oconee 3 Cycle 29 Table Of Contents ONEl-0400-459 Rev 0 Page 2 of 22 Section 1.0 Error Adjusted Core Operating Limits TS Number 2.1.1 3.1.1 3.1.3 3.1.4 3.1.5 3.2.1 3.2.2 3.2.3 3.3.1 3.4.1 3.5.1 3.5.4 3.7.12 3.9.1 5.6.5 SLC Number 16.5.13 Technical Specification Safety Limits Shutdown Margin (SOM)
Moderator Temperature Coefficient (MTC)
Control Rod Group Alignment Limits Safety Rod Position Limits Regulating Rod Position Limits Axial Power Imbalance Operating Limits Quadrant Power Tilt (QPT)
Reactor Protective System (RPS)
Instrumentation RCS Pressure, Temperature, and Flow Departure from Nucleate Boiling Limits Core Flood Tanks (CFTs)
Borated Water Storage Tank (BWST)
Spent Fuel Pool Boron Concentration Boron Concentration (RCS and Refueling Canal)
Core Operating Limits Report (COLR)
High Pressure Injection and Chemical Addition Systems NRC Approved Methodology Reference#
1, 2, 3, 4, 5, 6, 7,8,9, 10 1, 3, 7,8
- 1. 3, 7 1,3, 7, 8 1,3, 4, 5, 7, 8, 9, 10 1, 3,4,5, 7,8, 9, 10 1, 2, 3, 4, 5, 7,8, 9, 10 1,3,7,9,10 1, 2, 3, 4, 5, 6, 7,8,9, 10 4,5, 7, 8 1, 3, 7,8 1, 3, 7,8 1, 3, 7,8 1,3, 7,8 None NRC Approved Methodology Reference#
1,3, 7,8 COLR Parameter Maximum Allowed RPS Power Imbalance Limits Shutdown Margin MTC Misaligned, Dropped, or Inoperable Misaligned, Dropped, or Inoperable Withdrawal Sequence and Overlap 4-pump No Inoperable Rod CR Position Setpoints 3-pump No Inoperable Rod CR Position Setpoints 4-pump Operational Power Imbalance Setpoints 3-pump Operational Power Imbalance Setpoints QPT Setpoints Correlation Slope Variable Low RCS Pressure RPS Setpoints Maximum Allowed RPS Power Imbalance Limits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpoints RCS Pressure, Temperature, and Flow Boron Concentration Boron Concentration Boron Concentration Boron Concentration References COLR Parameter Volume and Boron Concentration of Concentrated Boric Acid Storage Tank (CBASD Section 2.0 Core Operating Limits - Not Error Adjusted (NOT FOR PLANT USE)
TS Number Technical Specification 2.1.1 Safety Limits 3.2.1 Regulating Rod Position Limits 3.2.3 Quadrant Power Tilt (QPT)
NRC Approved Methodology Reference#
1, 2, 3, 4, 5, 6, 7, 8,9, 10 COLR Parameter Variable Low RCS Pressure Protective Limits Axial Power Imbalance Protective Limits 1, 3, 4, 5, 7, 8, 9, 10 Rod Index Limits 1, 3, 7, 9, 10 Quadrant Power Tilt Limits
Oconee 3 Cycle 29 1.0 Error Adjusted Core Operating Limits ONEl-0400-459 Rev 0 Page 3 of 22 The Core Operating Limits Report for 03C29 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 03C29 by References 15 through 17. The 03C29 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, radial local peaking (FD.h) 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 03C29 reload core.
1.1 References
- 1. Oconee Nuclear Design Methodology Using CASM0-4 /SIMULA TE-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 TAC03 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. D.Tc and EOC Reduced Tavg Operation, OSC-7265, Revision 1, June 2002. *
- 15. 03C29 Maneuvering Analysis, OSC-1147 4, Revision 1.
- 16. 03C29 Specific DNB Evaluation, DPND-1553.63-0742, Revision 0.
- 17. 03C29 Reload Safety Evaluation, OSC-11539, Revision 0.
Oconee 3 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.
ONEl-0400-459 Rev 0 Page 4 of 22 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 (SOM) shall be greater than 1% Ak/k.
Referred to by TS 3.1.1.
Moderator Temperature Coefficient (MTC) shall be less than:
Linear interpolation is valid within the table provided.
Referred to by TS 3.1.3.
MTG x 10-4 L\\p I °F
+0.70
+0.525 0.00 0.00 0.00
%FP 0
20 80 100 120 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:
Referred to by TS 3.4.1.
The measured Tavg must be less than COLR limits minus instrument uncertainty. ATc is the setpoint value selected by the operators.
Max Loop Tavg (Incl 2°F unc)
581.0 581.0 1
581.4 581.2 2
581.8 581.4 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:
Referred to by TS 3.4.1.
4 RCP:
3 RCP:
Measured~ 108.5 %df Measured 2'. 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).
Oconee 3 Cycle 29 Steady State Operating Band Rod Index APSR%WD EFPD Min Max Min Max 0 to 635 292 +/- 5 635 to EOC 292 +/- 5 300 300 30 100 40 100 Quadrant Power Tilt Setpoints Steady State Transient Core Power Level, %FP 0 - 30
> 30 0 - 30
> 30 Full lncore 7.61 3.50 9.40 7.11 Out of Core 6.09 2.35 7.72 5.63 Backup lncore 3.87 2.25 4.81 3.63 Referred to by TS 3.2.3 Correlation Slope (CS) 1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
ONEl-0400-459 Rev 0 Page 5 of 22 Maximum
>O 16.55 14.22 10.07
CJ
(/)
0...
Q).
- l en en Q) a: c ro 0 a u
.._ a u ro Q) a:::
P = 2355 psig Oconee 3 Cycle 29 ONEl-0400-459 Rev 0 Page 6 of 22 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 1-----------------------... T = 618 °F 2300.
2200.
2100.
2000.
1900 P = 1800 psig Acceptable Operation P = 11.14 *Tout - 4706
~
T = 584 °F Unacceptable Operation 1700...--~~~~~-+-~~~~~--t~~~~~~-;-~~~~~-;-~~~~~--t 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, °F
Oconee 3 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 Pm(L"C =>
81.7 14.4 62.3 35.0 0.0 35.0 ONEl-0400-459 Rev 0 Page 7 of 22
64;2 63~8 63.1*
o~o 28.0 28.0 26.T**
. 26.7 RefE;?rred to by TS.3;2.2.*.
-13.2 132*..
27.2 21:2 *.
% FP 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
%FP Oconee 3 Cycle 29 ONEl-0400-459 Rev 0 Page 9 of 22 RPS I Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 RPS Trip Full lncore Alarm Out of Core Alarm
-14.4 14.4
-16.4 16.4
-17.5 17.5
-18.5 18.5
-19.6 19.6
-20.7 20.7
-15.6 15.6
-15.6 13.3
-21.7 21.7
-16.7 16.7
-16.7 14.0
-22.8 22.8
-17.7 17.7
-17.7 14.7
-23.9 23.9
-18.7 18.7
-18.5 15.4
-24.9 24.9
-19.8 19.8
-19.3 16.1
-26.0 26.0
-20.8 20.8
-20.1 16.8
-27.0 27.0
-21.8 21.8
-20.9 17.5
-28.1 28.1
-22.9 22.9
-21.8 18.3
-29.2 29.2
-23.9 23.9
-22.6 19.0
-30.2 30.2
-24.9 24.9
-23.4 19.7
-31.3 31.3
-25.9 25.9
-24.2 20.4
-32.3 32.3
-27.0 27.0
-25.0 21.1
-33.0 33.0
-27.6 27.6
-25.5 21.5
-33.0 33.0
-28.0 28.0
-25.8 21.8
-33.0 33.0
-28.0 28.0
-26.0 22.3
-33.0 33.0
-28.0 28.0
-26.2 22.9
-33.0 33.0
-28.0 28.0
-26.4 23.4
-33.0 33.0
-28.0 28.0
-26.6 24.0
-33.0 33.0
-28.0 28.0
-26.8 24.5
-33.0 33.0
-28.0 28.0
-26.9 25.1
-33.0 33.0
-28.0 28.0
-27.1 25.6
-33.0 33.0
-28.0 28.0
-27.3 26.1
-33.0 33.0
-28.0 28.0
-27.5 26.7
-33.0 33.0
-28.0 28.0
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2 RPS Trip Full lncore Alarm Out of Core Alarm
%FP 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 63.8 63.3 63.1 63.0 62.0 61.0 60.0 0.0
% FP Oconee 3 Cycle 29 ONEl-0400-459 Rev 0 Page 10 of 22 RPS I Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOG Referred to by TS 3.2.2 and TS 3.3.1 RPS Trip Full lncore Alarm Out of Core Alarm
-14.4 14.4
-15.0 15.0
-16.1 16.1
-17.1 17.1
-18.2 18.2
-13.2 13.2
-13.2 13.2
-19.3 19.3
-14.3 14.3
-14.3 14.3
-20.3 20.3
-15.3 15.3
-15.3 15.3
-21.4 21.4
-16.4 16.4
-16.4 16.4
-22.4 22.4
-17.4 17.4
-17.4 17.4
-23.5 23.5
-18.5 18.5
-18.5 18.5
-24.6 24.6
-19.6 19.6
-19.6 19.6
-25.6 25.6
-20.6 20.6
-20.6 20.6
-26.7 26.7
-21.7 21.7
-21.7 21.7
-27.8 27.8
-22.8 22.8
-22.8 22.8
-28.8 28.8
-23.8 23.8
-23.8 23.8
-29.9 29.9
-24.9 24.9
-24.9 24.9
-30.9 30.9
-25.9 25.9
-25.9 25.9
-32.0 32.0
-27.0 27.0
-27.0 27.0
-32.2 32.2
-27.2 27.2
-27.2 27.2
-32.7 32.7
-27.7 27.7
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2
-33.0 33.0
-28.0 28.0
-27.7 27.2 RPS Trip Full lncore Alarm Out of Core Alarm
Oconee 3 Cycle 29 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0
(-14.4,107.9)
{14.4,107.9
~~~~~~-;-~~-'----'~--ll:..
100.0 M1=0.942
(
Acceptable 4 Pump Operation
(-33.0,90.4)
(-33.0,63.1) 60.0 1 Acceptable 3 or 4 Pump Operation 40.0 20.0
-40.0
-30.0
-20.0
-10.0 0.0 10.0 Percent Power Imbalance ONEl-<1400-459 Rev 0 Page 11 of 22 M2 = --0.942 ~
(33.0,90.4)
(33.0,63.1) 20.0 30.0 40.0
0 3 C I 29 ONEl-0400-459 Rev 0 conee..
ye e Imbalance Setpoints for 4 Pump Operation, BOC to EOC Page 12 of 22 Referred to by TS 3.2.2 and TS 3.3.1 110 100 90 80 70 Q)
~
60
- a.
- u.
0 50 c:
~
Q)
- a.
40 30 20 10 0
-40
-35
-30
-25
-20
-15
-10
-5 0
5 10 15 20 25 30 35 40 Percent Axial Imbalance
Qi 3
0 a..
110 100
=-=-*:..--
f-* 1---
-f--- :---
-r-1----- -
- =t--~=--
- -t--
. 1--
Oconee 3 Cycle 29 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 ONEl-0400-459 Rev 0 r------ --- -,-
Page 13 of 22
--1--1---
90 f-~--=
1-,__
-- -r-1--
1--
- I--
,.~-
1-t-t-t-r-*1* __ i-*:- ~-.. -t-i
...-.-._-t_-_t-,_-r_-r._-i--r--i--i-- r-1 80 70 60 50 40 30 20 10 RPS Trip Setpoint :,:.::::::::- -
- w=w
-33.0, 63.1
-27.4, 63.6 -
~~
l=t-t-t-t-~:-:t~ a.::t-=t=*==1~-~::::= lll+-
f.- *- -- --
'--~----
-r---- - --
--=I--
. - ~-~-
-f--
1---*
t-*
, ___ -y- --
--1---
.1-. _,_:
_- -33.0. 0.0 +-
- j: -27.4, 0.0 - - -
0
-40
~ -l 1-- -35 1
I 1*-* -30
-25
-20
..
- _.., ~1--- -
--4*
-- RPS Trip Setpoint ::=J==:.j::--::j:*::j* =!=:R=I
-13.2, 77.0
~ ~ -
13.2, 77.0 ~ ~...
...._= *-
-~~
t-.. -- -- =~ *- *--
~
r-
-* -l!!!oo -** 33.0, 63.1 ::-t-:
-- ~
1- ~ :- --- -...-
.,-+-
26.7, 64.2
- Labels Correspond to the Backup lncore Alarm Setpoints --
- ~=--
-...---...--.---. - ~-
- i-----
i-1-
i-- r--
1-i----
-f--1--
-- --r--1---
- - f--
Backup lncore -~--I*-~-~--l*g~j:~l:t-l~'~g~tttJ
- ~--l-~--~--~-~-§13 o utcore
- - f-1-1-f-
-lncore 1---
1-- --
,..-= ~ RPS Trip t--i.---
l : - =,=f:=;.::
-f--f- --
f---
1
~ *
- _~ 7, 0. 0 33.0, 0.0 =:::
.---...,~*-
-15
-10
-5 0
5 10 15 20 25 30 35 40 Percent Axial Imbalance
ONEl-0400-459 Rev 0 Page 14 of 22 Oconee 3 Cycle 29 Operational Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint RI Withdrawal
%FP No lnop Rod 1 lnop Rod Setpoint 4 Pumps 102.0 263.5 283.4 300 100.0 261.5 281.5 300 90.0 251.5 271.9 300 80.0 241.5 262.3 300 50.0 201.5 233.4 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 237.5 285.2 300 75.0 234.8 281.5 300 50.0 201.5 235.2 300 48.0 195.2 231.5 300 15.0 91.5 165.5 300 13.0 76.5 161.5 300 5.0 16.5 93.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300
ONEl-0400-459 Rev 0 Page 15 of 22 Oconee 3 Cycle 29 Shutdown Margin Rod Index Setpoints Referred to by TS 3.2.1 RI Insertion Setpoint RI Withdrawal
%FP No lnop Rod 1 lnop Rod Setpoint 4 Pumps 102.0 224.6 283.4 300 100.0 221.5 281.5 300 48.0 141.5 231.5 300 13.0 76.5 161.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300 3 Pumps 77.0 227.4 285.2 300 75.0 221.5 281.5 300 48.0 141.5 231.5 300 13.0 76.5 161.5 300 3.0 1.5 76.5 300 2.8 0.0 74.8 300 0.0 0.0 51.0 300
ONEl-0400-459 Rev 0 Referred to by TS 3.2.1 Page 16 of 22 105.
105 100 95 95 90.
90 85.
85 80 80 75 75 70 70 65.
65
- a.
- u.
60.
. 60
~
0 i
55 55 0
50.
50
- a.
0 -
45 45 u ro Q) a::
40 40 35 35 30 30 25 25 20 20 15 15 10 10 5
5 0
90 100 10 20 Group 5 Control Rod Position, % WO 105 100 95 90 85 80 75 70 65 a..
u...
60
";:f!.
0
..: 55 Q) ;:
0 50 a..
L..
0 t5 45 ro Q) 0:::
40 35 30 25 20 15 10 5
0 Oconee 3 Cycle 29 Referred to by TS 3.2.l
' llHlf I l!tW:J:tl
-ti tml:tl:l~ 1t-t*......
- I.I\\
r T
Control Rod Position Setpoints No Inoperable Rods, 3 Pump Flow, BOC to EOC t
i I I
1 1
~
1 227.4, 77.0
. I 237.5, 77.0 225.0, 76.2
.,.,.~itt1*
- m ONEl-0400-459 Rev 0 Page 17 of 22 1'
- l
-1 300.0, 77.0 rr*
- r.
1 105 00 95 90 85 80 75 221.5, 75.0 234.8, 75.0 I
I r
r 1 H 1
Unacceptable 1 175.0, 59.3 '
I Operation 1
1 I ~
I llH I
141.5, 48.0 '
?
r l r Restricted Operation r
125.0, 39.1 4
1
)i
)
t
\\,
I
- t.
l 1 125.0, 25.7 r
T 1
r 76.5, 13.0 -
91.5, 15.0
=
1.5, 3.0 I
t 75.0, 12.8 0.0, 2.8 Group 6 r
I L,.j;
I 16.5, 5.0 t
5 15 25 35 45 55 65 75 I o 10 20 30 40 50 60 70 80 90 100 I lo 0.0, 0.0 I Group 5 I Control Rod Position, % WO 225.0, 67.6 201.5, 50.0 195.2, 48.0 I !1 t
175.0, 41.6 I
Acceptable Operation t
85 95 10 20 30 40 50 60 I Group 7 I 1
1 70 80
- t l i t l I
j 70 65 60 55 50 45 40 35 30 25 20 1 5 1 0 5
0 90 100 I
105 95 90 85 80 70 pS 40 35 25 20 15 90 100 Group 5 ONEl-0400-459 Rev 0 Control Rod Position, % WO Group 7 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5
Referred to by TS 3.2.l ONEl-0400-459 Rev 0 22 105 105 100 100 95 95 90 85 80 80 75 70 60 55 50 40 35 30 25 20 15 10 90 100 lo 10 Groups Control Rod Position, % WO Group 7
Oconee 3 Cycle 29 2.0 Core Operating Limits -
Not Error Adjusted ONEl-0400-459 Rev 0 Page 20 of 22 The data provided on the following pages satisfies a licensing commitment to identify specific parameters before instrumentation uncertainties are incorporated.
References provided in section 1 of this COLR identify the sources for the data which follows.
Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State Transient Core Power Level, %FP 0- 30
> 30 0 -30
> 30 Quadrant Power Tilt, %
10.00 5.40 12.00 9.44 Variable Low RCS Pressure Protective Limits Core Outlet Pressure psi a 1800 1900 2000 2100 2200 2300 Referred to by TS 2.1.1 Reactor Coolant Outlet Temperature, °F 3 RCS Pumps 4 RCS Pumps 581.0 578.3 590.0 587.3 598.9 596.3 607.9 605.2 616.9 614.2 625.9 623.2 Maximum
>O 20.00
Oconee 3 Cycle 29 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1
%FP RPS Operational 4 Pumps 0.0
-35.0
-39.2 80.0
-39.2 90.0
-35.0
-37.6 100.0
-28.4 109.4
-14.4 109.4 14.4 100.0 24.7 90.0 35.0 32.7 80.0 38.6 0.0 35.0 38.6 3 Pumps 0.0
-35.0
-39.2 62.3
-35.0 77.0
-39.2 81.7
-14.4 81.7 14.4 77.0 38.6 62.3 35.0 0.0 35.0 38.6 ONEl-0400-459 Rev O Page 21of22
4 Pumps 3 Pumps
%FP 102 100 90 80 50 15 5
77 50 15 5
Oconee 3 Cycle 29 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit Insertion Limit 262 260 250 240 200 90 0
236 200 90 0
No lnop Rod 220 140 75 0
220 140 75 0
1 lnop Rod 280 230 160 75 280 230 160 75 ONEl-0400-459 Rev 0 Page 22 of22 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300