RA-18-0069, Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 3 Cycle 30 (Revision 2)
| ML18190A180 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 06/26/2018 |
| From: | Grant H Duke Energy Carolinas |
| To: | Document Control Desk |
| References | |
| RA-18-0069 | |
| Download: ML18190A180 (26) | |
Text
(a DUKE..
~ ENERGY~
RA-18-0069 June 26, 2018 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001 Duke Energy Carolinas, LLC Oconee Nuclear Station (ONS) Unit 3 Docket Number 50-287 Renewed License Number DPR-55 10 CFR 50.36 H. Todd Grant General Manager Nuclear Engineering Oconee Nuclear Station Duke Energy ON01VP I 7800 Rochester Hwy Seneca, SC.29672
- o. 864.873.6767 f: 864.873.5791 Todd. Granl@duke-energy.com
Subject:
Transmittal of Core Operating Limits Report (COLR) for Oconee Unit 3 Cycle 30 (Revision 2)
Pursuant to Oconee Technical Specification 5.6.5.d, attached is an information copy of the revised Core Operating Limits Reports (COLR) for Oconee Unit 3. This is a mid-cycle revision made to the COLR to increase the incore power tilt setpoints.
Any inquiries on this submittal should be directed to Sam Adams, Oconee Regulatory Affairs, at 864-873-3348.
~4 H. Todd Grant General Manager Nuclear Engineering Oconee Nuclear Station
Attachment:
Oconee Unit 3, Cycle 30 COLR, ONEl-0400-503, Revision 2.
U. S. Nuclear Regulatory Commission June 26, 2018 cc (w/attachment):
Ms. Catherine Haney, Administrator, Region II U.S. Nuclear Regulatory Commission Marquis One Tower 245 Peachtree Center Ave., NE, Suite 1200 Atlanta, GA 30303-1257 Ms. Audrey L. Klett, Project Manager (by electronic mail only)
U.S. Nuclear Regulatory Commission 11555 Rockville Pike Mail Stop 0-0881A Rockville, MD 20852-2738 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station Page 2
(_~DUKE
~ ENERGY.
Facility Code :
Applicable Facilities :
Document Number :
Document Revision Number :
Document EC Number:
Change Reason :
Document Title :
Lang, Amanda L.
McClain, Dewain Reed, James Smith, Joshua R.
St. Clair, Robert R.
Notes:
1 ON ON ON El-0400-503 002 Not an EC - Change Process is AD-NF-ALL-0807 OCONEE 3 CYCLE *30 CORE OPERATING LIMITS REPORT Originator 6/12/2018 Verifier 6/12/2018 Cross Disciplinary Review 6/12/2018 Site Inspection 6/12/2018 Approver 6/12/2018
ONEl-0400-503 (Rev. 2)
Page 1 of 22 Oconee 3 Cycle 30 Core Operating Limits Report ON El-0400-503 Revision 2 Reload 50.59 AR# 02190144 Prepared By:
A. L. Lang All signatures were captured via Design Verified By:
L. D. McClain Fusion E-signature. See the Cross-Disciplinary Review By:
J.A. Reed Fusion cover sheet for signature (CDR of paQes 4, 6 and 20 only) dates.
Site Inspection By:
J.R. Smith, ONS RES Approved By:
R. R. St.Clair Revision Summary Revision Pages Revised Pages Added Pages Deleted Comments 0
1 - 22 Original issue.
1 1-22 Revised to increase incore tilt set points.
2 1-22 Revised to increase incore tilt setpoints.
NOTES:
Discard Attachment 1 (Design Verification Documents) of the El.
The 03C30 COLR will cease to be effective during NO MODE between cycles 30 and 31.
Oconee 3 Cycle 30 Table Of Contents 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 ONEl-0400-503 Rev 2 Page 2 of 22 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#
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, 1 O Quadrant Power Tilt Limits
Oconee 3 Cycle 30 1.0 Error Adjusted Core Operating Limits ONEl-0400-503 Rev 2 Page 3 of22 The Core Operating Limits Report for 03C30 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 03C30 by References 15 and 16. The 03C30 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, radial local peaking (F 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 03C30 reload core.
1.1 References
- 1. DPC-NE-1006-PA, Oconee Nuclear Design Methodology Using CASM0-4 / SIMULATE-3, NRC SE issued August 2, 2011.
- 2. DPC-NE-1002-A, Oconee Nuclear Station Reload Design Methodology II, SE dated July 21, 2011.
- 3. NFS-1001-A, Oconee Nuclear Station Reload Design Methodology, SE dated July 21, 2011.
- 4. DPC-NE-2003-PA, ONS Core Thermal Hydraulic Methodology Using VIPRE-01,
SE dated July 21, 2011.
- 5. DPC-NE-2005-PA, Thermal Hydraulic Statistical Core Design Methodology, SE dated March 2016.
- 6. DPC-NE-2008-PA, Fuel Mechanical Reload Analysis Methodology Using TAC03 and GDTACO, SE dated July 21, 2011.
- 9. BAW-10192P-A, Revision 0, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.
- 10. BAW-10164P-A, Rev. 4 and 6, RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis, SERs dated April 9, 2002 and June 25, 2007, respectively.
11. BAW-10227P-A, Revision 1, Evaluation of Advanced Cladding and Structural Material (MS) in PWR Reactor Fuel, June 2003 (SER to BAW-10186P-A dated June 18, 2003).
- 12. OSC-4048, Revision 6, RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit.
- 13. OSC-5604, Revision 4, Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094.
- 14. OSC-7265, Revision 1, Tc and EOC Reduced Tavg Operation.
- 15. OSC-11720, Revision 3, 03C30 Maneuvering Analysis.
- 16. OSC-11779, Revision 1, 03C30 Reload Safety Evaluation.
ONEl-0400-503 Rev 2 Page 4 of22 Oconee 3 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% l\\k/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 p / *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. ~Tc 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 2'. 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).
Core Power Level, %FP Full lncore Out of Core Backup lncore Oconee 3 Cycle 30 Quadrant Power Tilt Setpoints Steady State Transient 0-30
>30 0 - 30
. > 30 7.94 6.09 3.87 5.00 3.42 2.64 9.72 7.72 4.81 Referred to by TS 3.2.3 Correlation Slope (CS) 1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
7.43 5.63 3.63 ONEl-0400-503 Rev 2 Page 5 of 22 Maximum
>O 16.88 14.22 10.07
(9 Cl) a..
(I)
L..
U)
U)
(])
L..
a..
c ro 0
0 u L..
0....
u ro
(])
0::
2300 2200 2100 2000 1900 Oconee 3 Cycle 30 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 P = 2355 psig ONEl-0400-503 Rev 2 Page 6 of 22
T = 618 °F 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
. I
Oconee 3 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-0400-503 Rev 2 Page 7 of 22
ONEl-0400-503 Rev 2 Page 8 of 22 Oconee 3 Cycle 30 Operational Power Imbalance Setpoints Referred to by TS 3.2.2 Full Backup Out of
%FP lncore lncore Gore 4 Pumps 0.0
-28.0
-24.7
-25.1 80.0
-28.0
-24.7
~25.1 90.0
-28.0
-19.8
-20.2 100.0
-17.7
-13.1
-13.4 102.0
-15.6
-11. 7
-12.1 102.0 15.6 13.0 13.2 100.0 17.7 13.4 13.6 90.0 23.4 15.6 16.0 80.0 25.0 17.3 17.8 0.0 25.0 17.3 17.8 3 Pumps 0.0
-28.0
-24.7
-25.1 63.1
-28.0 65.8
-25.1 66.1
-24.7 77.0
-13.2
-13.2
-13.2 77.0 13.2 13.2 13.2 73.1 17.3 72.6 17.8 65.9 25.0 0.0 25.0 17.3 17.8 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 3 Cycle 30 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
- oNEl-0400-503 Rev 2 Page 9 of 22 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
-12.1 13.2
-21.7 21.7
-16.7 16.7
-12.8 13.4
-22.8 22.8
-17.7 17.7
-13.4 13.6
-23.9 23.9
-18.7 18.3
-14.1 13.8
-24.9 24.9
-19.8 18.8
-14.8 14.1
-26.0 26.0
-20.8 19.4
-15.4 14.3
-27.0 27.0
-21.8 20.0
-16.1 14.6
-28.1 28.1
-22.9 20.6
-16.8 14.8
-29.2 29.2
-23.9 21.1
-17.5 15.0
-30.2 30.2
-24.9 21.7
-18.2 15.3
-31.3 31.3
-25.9 22.3
-18.8 15.5
-32.3 32.3
-27.0 22.8
-19.5 15.8
-33.0 33.0
-27.6 23.2
-19.9 15.9
-33.0 33.0
-28.0 23.4
-20.2 16.0
-33.0 33.0
-28.0
- 23.6
-20.7 16.2
-33.0 33.0
-28.0 23.7
-21.2 16.4
-33.0 33.0
-28.0 23.9
-21.7 16.5
-33.0 33.0
-28.0 24.0
-22.2 16.7
-33.0 33.0
-28.0 24.2
-22.7 16.9
-33.0 33.0
-28.0 24.4
-23.1 17.1
-33.0 33.0
-28.0 24.5
-23.6 17.3
-33.0 33.0
-28.0 24.7
-24.1 17.4
-33.0 33.0
-28.0 24.8
-24.6 17.6
-33.0 33.0
-28.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8 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 72.6 72.0 71.0 70.0 69.0 68.0 67.0 66.0 65.9 65.8 64.0 63.1 63.0 62.0 61.0 60.0 0.0
% FP Oconee 3 Cycle 30 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 ONEl-0400-503 Rev 2 Page 10 of 22 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 14.2
-20.3 20.3
-15.3 15.3
-15.3 15.3
-21.4 21.4
-16.4 16.4
-16.4 16.3
-22.5 22.5
-17.5 17.5
-17.5 17.4
-22.9 22.9
-17.9 17.9
-17.9 17.8
-23.5 23.5
-18.5 18.5
-18.5 17.8
-24.6 24.6
-19.6 19.6
-19.6 17.8
-25.7 25.7
-20.7 20.6
-20.6 17.8
-26.7 26.7
-21.7 21.7
-21.7 17.8
-27.8 27.8
-22.8 22.8
-22.8 17.8
-28.8 28.8
-23.8 23.8
-23.8 17.8
-29.9 29.9
-24.9 24.9
-24.9 17.8
-30.0
- 30.0
-25.0 25.0
-25.0 17.8 *
-30.1 30.1
-25.1 25.0
-25.1 17.8
-32.0 32.0
-27.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8
-33.0 33.0
-28.0 25.0
-25.1 17.8 RPS Trip Full lncore Alarm Out of Core Alarm
M1 = 0.942 r
(-33.0,90.4)
Oconee 3 Cycle 30 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 and TS Table 3.3.1-1 Thermal Power Level, %FP 120.0 100.0 Acceptable 4 Pump Operation
, _14.4,80_6) r--------+---(1_4_.4_,a_o_.6_)~
(-33.0,63.1) 60.0 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-0400-503 Rev-2 Page 11 of 22 M2=-0.942~
(33.0,90.4)
(33.0,63.1) 20.0 30.0 40.0
110 100 :: RPS Trip Setpoint
-33.0, 90.4 90 80 70 CL 60 "3
LJ.. -
0 -
C:
Q) e Q)
CL 50 40 30 20 10
- -33.0, 0.0 0
-40
-35
-30 Oconee 3 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
-11.7, 102.0 :
-13.1, 100.0
-19.8, 90.0
-24.7, 80.0 13.0, 102.0 -- -
13.4, 100.0 14.4, 1*07.9 15.6, 90.0 -
17.3, 80.0,_.,_.
Labels Correspond to the Backup lncore Alarm Setpoints
-24.7, 0.0
-25
-20
-15
-10
-5 0
5 Percent Axial Imbalance
..,._Backup lncore
...... autcore lncore
-RPS Trip 17.3, 0.0 10 15 20 ONEl-0400-503 Rev 2 Page 12 of 22 RPS Trip Setpoint
-.... ~
33.0, 90.4 : f::::
- 33.0, 0.0 =:::
25 30 35 40
Q) 3:
0 a.
- 5 u.. -
0 c Q) f2 Q) a.
110 100 90 80 RPS Trip Setpoint 70
-33.0, 63.1 60 50 40 30 20 10
- -33.0, 0.0 0
-40
-35
- -24.7, 66.1
-24.7, 0.0
-30
-25
-20 Oconee 3 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
-13.2, 77.0 14.4, 80.6 13.2, 77.0,_ _
17.3, 73.1
- Labels Correspond to the Backup lncore Alarm Setpoints
-15
-10
-5 0
5 Percent Axial Imbalance
...,_Backup lncore
....... autcore lncore
-RPS Trip 17.3, 0.0 10 15 20 ONEl-0400-503 Rev 2 Page 13 of 22
,._ RPS Trip Setpoint 33.0, 63.1 :::§ 33.0, 0.0==
25 30 35 40
ONEl-0400-503 Rev 2 Page 14 of 22 Oconee 3 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-0400-503 Rev 2 Page 15 of22 Oconee 3 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
- a.
u..
~
0
~
0 a.
0 -
(..)
co Q) 0::
ONEl-0400-503 Rev 2 Oconee 3 Cycle 30 Referred to by TS 3.2.1 Page 16 of 22 mmmmm~f4'6* 102*0
'!Tffiii'i'ffi'ii'l'!ii'ffii', 263.5: *. 102.0 l'l+mrn 300.0. 102.0 105 100 105 100 tf:li f1j1 If fill I H*111ttt1*l l+I H I 11-ttttJ lll:t:l:l:tl.1111-t+l 11-t-tt I 1*11*tt1-t11.111-tl11 H+!+lllli:l:m I.LI 111.uu 11.1-1111 t~Hl+l l~ll ~H H~
- 1 l+IHHH-1 IHHJ 1~-11~-l.f.f.l+l.f.1,H I IIJ.LWlU I 95 90 85 80 75 -
70 -
Control Rod Position Setpoints 1+1-Hi-1-1-1 i 1+i~-1-1-1-1-!111No Inoperable Rods, 4 Pump Flow, BOC to EOC b 175.0, 69.8 221.5, 100.0 ilitttlitltli-11*1111 261.5, 100.0..
251.5, 90.0 l+ttl llH<** +1+111+.1f++filt
- H'!:ll 1*
1 *
- LI.
241.5, 80.0 65 225.0, 67.6 60 55 50 45 40 35 30 25 Unacceptable Operation 11111111111 1 I"
141.5, 48.0 t1 1+1,wnu.-,..,...
125.0, 39.1 20 125.0, 25.7 15 -++++l+++++t+++++++++t++l-++++lioit++-l++++++t+++++++++tH++++++ 76. 5, 13. 0 91.5, 15.0 10 1.5, 3.0 11 11111 11111*
5 0.0, 2.8 /'!'FI i
.imw;-*..,..,
16.5, 5.0 *1+1 ~ilUl+l-1*1~
O ~
-0, 0.0 :*
75.0, 12.8 Group 6 25 35 45 55 100 I
- 11-l+l*
- . :,.:::~. 5 15 I o 1 o 20 30 40 50 60 10 80 90 Restricted Operation
- 201.5, 50.0
,11 11111 111 11 1 195.2, 48.0 175.0, 41.6 65 75 85 95 10 10 20 30 i Group 5 i Control Rod Position, % WD 40 I
50 Acceptable Operation 60 70 Group 7 I 80 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5
0 90 1 oo I
105 100 95 90 85 80 75 70 65 c..
LI..
60
~
0
..: 55
~
0 50 c.....
0 t5 45 t'O a.>
0:::
40 35 30 25 20 15 10 5
0 11 Oconee 3 Cycle 30 Referred to by TS 3.2.1 Control Rod Position Setpoints No Inoperable Rods, 3 Pump Flow, BOC to EOC i
227.4, 77.0 237.5, 77.0 ONEl-0400-503 Rev 2 Page 17 of 22 300.0, 77.0 105 100 95 90 85 80 l++l+'+tttlltt,-l-ttttittttl:+tt-ltttttt-+ttlttt-tttti+l,+t-tttti-li+lttl ttt1 11tt+Hctttttltcj-ttttittttt-ttttiltttt1-ttttirtffrHtrtttl""-ttttitttli-tttti-tttl*ltt"Tt1ttl t1tt 225. 0' 76 '2 I
/I ll 11111 111 11 I 75
, 1.5, 3.0 0.0, 2.8 I
16.5, 5.0 10 10 20 30 0.0, 0.0 Unacceptable Operation
-t I 125.0, 39.1 1111 141.5, 48.0 125.0, 25.7 1
175.0, 59.3 Restricted Operation 76.5, 13.0. I!
91.5, 15.0 75.0, 12.8 11 11 1111 j
Group 6 5
15 25 35 45 55 65 75 40 50 60 70 80 90 100 I 10 I Group 5 I Control Rod Position, % WO 221.5, 75.0 -ln+l+!-l+l+l-i,\\+!-l+. 234.8, 75.0 225.0, 67.6 201.5, 50.0 195.2, 48.0 11111 H 175.0, 41.6 I
85 95 10 20 30 40 I
Acceptable Operation 50 60 Group 7 I 70 65 60 55 50 45 40 35 30 25 20 15 10 5
0 70 80 90 100 I
ONEl-0400-503 Rev 2 Page 18 of 22 105 "1"1'1'!'P"'ffl'l'lll"!"l'!'ffl'l'i'll'!"l"l"!"l!"Tffl'!'!'!'"!'~~~~!iiffllili=m:i=!l\\l!!!!Ff~Flllffihiffi~~fflffl~~fflTT'l'fiTl"l'l'l"ffli!"l"!"!'m'!'l'i'l'!"l'fflm"ffffl"FF'!'ffl"iiff'l'l"l'!'ffl'ffl~i'l"l'ffll"l""ffil'!"l"l"!"l'l'lffl'l"!"l"l"l'l'r,'i"l'!'l'ffl' 11 lllllllllll lllllll.1111111111111111111111111111111111111111 It ltlltt 11 11111111111 1 111111 300.0, 102.0 Oconee 3 Cycle 30 Referred to by TS 3.2.1 105 100 95 90 85 80 75 70 65 60 '
55 50 45 40 35 30 25 20 15 10 a..
100 -
95 90 85 80 75 70 65 u..
60
~
~ 55 0
a..
50 0
t3 ro 45 Q) 0::
40 35 -
30 25 20 15 10 5
0 10
µ 283.4, 102.0 Control Rod Position Setpoints 1 Inoperable Rod, 4 Pump Flow, BOC to EOC I
I!
1 t
Unacceptable 281.5, 100.0 I
11 t
t
~
Operation i
,I 76.5, 3.0 -
t 75.0, 2.82
+
10 11 I I
IT 74.8, 2.8 '"'
51.0, 0.0 5
10 20 30 40 50 60 70 80 Group 5 I 125.0, 8.7 231.5, 48.0 225.0, 44.8 175.0, 19.8 161.5, 13.0 Acceptable Operation 11 Group 6 5
15 25 35 45 55 65 75 85 95
,---------------------0 I o 1 o 20 30 40 50 60 10 80 90 1 oo I **
'------------.======.---------
1 Group 7 l 90 1 oo I Control Rod Position, % WD
Oconee 3 Cycle 30 Referred to by TS 3.2.1 ONEl-0400-503 Rev 2 105 lffl'r"Tfflffl"T'l'TTfflll'ffl'!'~~~;;;:;;;:;:;:;;;;:;:r=mi:;:;:;:;;;;;:;;;;;:;;;;:;;;;;;~~l'!'i'ffl"ffl'l'ffl"'l'l'ffl'i'!'!nffl'!"'!'!'T'iii'!'l""l~'l'll"'!'!'l'!"T,.,,,,.,.,"'!"l'il'"""""ffi'i'l'"""""'l'ffl'F!'!'!'Fi'i'l'P'l'Pffl'Fni!'!'l'Fi~P~a~e;.l!19~of~2~2,.....,..,._.
IT ii i!lfi!iilil fl i!fi!ti.li! tlii!i!li!iii!i!ili lii!i!ilii!tllii!lildi II 100 95 90 85 80 75 70 65 -
0..
LL 60
?J. r 55 _
o..
50
~
ro 45 Q) er:
40 35 30 25 20 15 10 5
l:ttltmtll:tm!:ifflttmt:1:lUltltl Control Rod Position Setpoints 1 Inoperable Rod, 3 Pump Flow, BOC to EOC 1
1,1 76.5, 3.0 125.0, 8.7 75.0, 2.82 SI I
51.0, 0.0 Ii; 74.8, 2.8
" *=-:-:: 5 15 25 35 I
175.0, 19.8 T
T U T f,-
161.5, 13.0 Unacceptable Operation 231.5, 48.0 225.0, 44.8 Group 6 45 55 65 75 85 95 f
I i 285.2, 77.0 II " OIi I II" 111 " I 281.5, 75.0 II Acceptable Operation 300.0, 77.0 105 100 95 90 85 80 75 70 65 60 55 50 45 40 35 30 25 20 15 10 5
0 0
Jo 10 20 30 40 50 60 70 80
! Group 5 j 90 100 I o 10 20 30
-40 50 60 70 80 90 100 Control Rod Position, %. WD j Group 7 j
Oconee 3 Cycle 30 2.0 Core Operating Limits -- Not Error Adjusted ONEl-0400-503 Rev 2 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.
Information provided in this section should not be used in plant procedures.
Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State Transient Core Power Level, %FP Quadrant Power Tilt, %
0 - 30 10.00
>30 6.72 0 - 30 12.00
> 30 9.44 Variable Low RCS Pressure Protective Limits Referred to by TS 2.1.1 Core Outlet Pressure psia 1800 1900 2000 2100 2200 2300 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 30 Axial Power Imbalance Protective Limits Referred to by TS 2. 1.1 Not for Plant Use
%FP RPS Operational 4 Pumps 0.0
-35.0
-36.0 80.0
-36.0 90.0
-35.0
-30.7 100.0
-23.1 109.4
-14.4 109.4 14.4 100.0 23.4 90.0 35.0 25.6 80.0 27.1 0.0 35.0 27.1 3 Pumps 0.0
-35.0
-36.0 62.3
-35.0 77.0
-36.0 81.7
-14.4 81.7 14.4 77.0 27.1 62.3 35.0 0.0 35.0 27.1 ONEl-0400-503 Rev 2 Page 21 of22
4 Pumps 3 Pumps
%FP 102 100 90 80 50 15 5
77 50 15 5
Oconee 3 Cycle 30 Rod Index Limits Referred to by TS 3.2.1 Not for Plant Use 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-0400-503 Rev 2 Page 22 of 22 RI Withdrawal Limit 300 300 300 300 300 300 300 300 300 300 300
Oconee 3 Cycle 30 Core Operating Limits Report ONEl-0400-503 - Reviewer Forms and Comments Rev. 2 AD-EG-ALL-1110(Rev. 5) - Page 1 Record of Review Document:
ONEl-0400-503 Revision:
2 The signature of the Design Verification Reviewer confirms:
The type of verification method perfe>rmed Technical errors have been resolved and the records have been included, if applicable r:81 Reviewer or D Concurrent Reviewer Design Verification Review Method
~ Design Review D Alternate Calculation Other Records: D Attached D Qualification Testing Note:
This Record of Review form may be used to document other reviews, but is only required for Design Verification Reviews.
l.D. McClain/ Signed Electronically Nuclear Dated Electronically Reviewer(Print/Sign)
Discipline Date Item Technical Error Resolution No.
One power on page 10 (3 RCP Power 72.6 was moved to correct position and 1
RPS/Operational Power Imbalance Setpoints) was out-of-order.
Excel formulas were corrected.