ONS-2017-083, Core Operating Limits Report (COLR) for Cycle 29 ONEl-0400-491, Revision 0
ML17334A031 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 11/21/2017 |
From: | Grant H Duke Energy Carolinas |
To: | Document Control Desk, Office of Nuclear Reactor Regulation |
References | |
ONS-2017-083 | |
Download: ML17334A031 (25) | |
Text
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1
~-,DUKE H. Todd Grant G~neral Manager
~ ENERGY<< Nuclear Engineering Oconee Nuclear Station Duke Energy ON01 VP I 7800 Rochester Hwy Seneca, SC 29672
- 0. 864.873.6767 f: 864.873.5791 ToddGrant@duke-energy.com ONS-2017-083 November 21, 2017 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555-0001
Subject:
Duke Energy Carolinas, LLC Oconee Nuclear Station Unit 2, Docket Number 50-270 Core Operating Limits Report (COLR) for Unit 2 Cycle 29 Pursuant to Oconee Technical Specification* 5.6.5.d, attached is an information copy of the Core Operating Limits Report (COLR) for Oconee Unit 2, Cycle 29, ONEl-0400-491, Revision 0.
If you have any questions, please direct them to Stephen C. Newman, Lead Nuclear Engineer at 864-873-4388.
Sincerely, it~J1d H. Todd Grant General Manager Nuclear Engineering Oconee Nuclear Station Attachment
U. S. Nuclear Regulatory Commissi6n November 21, 2017 Page 2 cc:
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 0-08B1A Rockville, MD 20852-2738 Mr. Eddy Crowe NRC Senior Resident Inspector Oconee Nuclear Station
(_~DUKE
~ ENERGY..
Facility Code : ON Applicable Facilities : ON Document Number : ONEl-0400-491 Document Revision Number : 000 ,
Document EC Number :
Change Reason : No reason given per RR St.Clair Document Title : OCONEE 2 CYCLE29 CORE OPERATING LIMITS REPORT
(
REFERENCE:
OSC-11652, REVISION 001)
Scurlock, Alyse M. Originator 9/26/2017 Forster, Joy D Verifier 9/26/2017 Phelps, Timothy P Cross Disciplinary Reviewer 9/26/2017 Presnell, G Michael Approver 9/26/2017 Notes:
Oconee 2 Cycle 29 ONEl-0400-491 Core Operating Limits Report Rev. 0 AD-EG-ALL-1176 (Rev. 0)
Manual Certification Form Plant: Oconee Unit: 2 Quality Level:
Title:
Oconee 2 Cycle 29 Core Operating Limits Report Duke Energy File Number: ONEl-0400-491 Revision Number: 0 Vendor: N/A For Vendor Manuals Only Vendor Document Number: N/A Responsible Engineer:
N/A (or vendor name & P.O. Number, if applicable)
Prepared By: A.M. Scurlock (signed electronically) Date:
Design Verified By: J.D. Forster (signed electronically) Date:
Approved By: G.M. Presnell (signed electronically) Date:
Approved By Owner:
(N/A except when document revision Date:
is prepared, Design Verified, and approved above by a vendor)
Revision
Description:
ORIGINAL ISSUE (REVISION 0)
NOTES:
- The 02C29 COLR requires the reload 50.59 to be approved prior to implementation and fuel loading.
- Revision O 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 02C29 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
ONEl-0400-491 Rev 0 Page 2 of 22 Oconee 2 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 (SOM), 1, 3, 7 ,8 Shutdown Margin 3.1.3 Moderator Temperature Coefficient (MTC) 1, 3, 7 MTC 3.1.4 Control Rod Group Alignment Limits 1,3, 7,8 Misaligned, Dropped, or Inoperable 3.1.5 Safety Rod Position Limits 1 ,3, 4, 5, 7, 8, 9, 10 Misaligned, Dropped, or Inoperable 3.2.1 Regulating Rod Position Limits 1,3,4,5, 7,8,9, 10 Withdrawal Sequence and Overlap 4-pump No Inoperable Rod CR Position Setpoints 3-pump No Inoperable Rod CR Position Setpoints 3.2.2 Axial Power Imbalance Operating Limits 1, 2, 3, 4, 5, 4-pump Operational Power 7,8,9, 10 Imbalance Setpoints 3-pump Operational Power Imbalance Setpoints 3.2.3 Quadrant Power Tilt (QPT) 1,3, 7,9, 10 QPT Setpoints 3.3.1 Reactor Protective System (RPS) 1, 2, 3, 4, 5, Correlation Slope Instrumentation 6, 7,8,9, 10 Variable Low RCS Pressure RPS Setpoints Maximum Allowed RPS Power Imbalance Limits 4-pump RPS Power Imbalance Setpoints 3-pump RPS Power Imbalance Setpoints 3.4.1 RCS Pressure, Temperature, and Flow 4,5, 7,8 RCS Pressure, Temperature, Departure from Nucleate Boiling Limits and Flow 3.5.1 Core Flood Tanks (CFTs) 1,3, 7 ,8 Boron Concentration 3.5.4 Borated Water Storage Tank (BWST) 1,3, 7 ,8 Boron Concentration 3.7.12 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, 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, 1O Rod Index Limits 3.2.3 Quadrant Power Tilt (QPT) 1, 3, 7, 9, 10 Quadrant Power Tilt Limits
ONEl-0400-491 Rev 0 Page 3 of 22 Oconee 2 Cycle 29 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C29 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 02C29 by References 15 and 16. The 02C29 analyses assume a design flow of 108.5% of 88,000 gpm per RCS pump, radial local peaking (Ft.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 02C29 reload core.
1.1 References
- 1. DPC-NE-1006-PA, Oconee Nuclear Design Methodology Using CASM0-4 I 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.
- 5. DPC-NE-2005-PA, Thermal Hydraulic Statistical Core Design Methodology, SE dated October 29, 2008.
- 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 (M5) 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, t.Tc and EOC Reduced Tavg Operation.
- 15. OSC-11652, Revision 1, 02C29 Maneuvering Analysis.
- 16. OSC-11713, Revision 1, 02C29 Reload Safety Evaluation.
ONEl-0400-491 Rev 0 Page 4 of 22 Oconee 2 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 (SOM) 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. ~p I °F %FP Referred to by TS 3.1.3. +0.70 0
+0.525 20 0.00 80 0.00 100 0.00 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by TS 3.4.1. 4 RCP: measured hot leg pressure> 2125 psig 3 RCP: measured hot leg pressure> 2125 psig DNB parameter for RCS loop average temperature shall be: Max Loop Tavg (Incl 2°F unc)
Referred to by TS 3.4.1. ~Tc, °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. ~Tc 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: 4RCP: Measured :::: 108.5 %df Referred to by TS 3.4.1. 3 RCP: Measured:::: 74.7 % of 4 RCP min flow Regulating rod groups shall be withdrawn in sequence starting with group 5, group 6, and finally group 7.
Referred to by TS 3.2.1.
Regulating rod group overlap shall be 25% +/- 5% between two sequential groups.
Referred to by TS 3.2.1.
Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculations when determining if overlap requirements are met as these situations are explicitly addressed by TS 3.1.4 (Control Rod Group Alignment Limits), TS 3.1.5 (Safety Rod Position Limits), and TS 3.2.3 (Quadrant Power Tilt).
ONEl-0400-491 Rev 0 Page 5 of 22 Oconee 2 Cycle 29 Steady State Operating Band Rod Index APSR %WO EFPD Min Max Min Max 0 to 639 292 +/- 5 300 30 40 639 to EOC 292 +/- 5 300 100 100 Quadrant Power Tilt Setpoints Steady State Transient Maximum Core Power Level, %FP 0 - 30 > 30 0 - 30 > 30 >O Full lncore 7.61 3.50 9.40 7.11 16.55 Out of Core 6.09 2.35 7.72 5.63 14.22 Backup lncore 3.87 2.25 4.81 3.63 10.07 Referred to by TS 3.2.3 Correlation Slope (CS) 1.15 Referred to by TS 3.3.1 (SR 3.3.1.3).
ONEl-0400-491 Rev 0 Page 6 of 22 Oconee 2 Cycle 29 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 P = 2355 psig
~ - - - - - - - - - - - - - - - - - - - - - - T = 618 °F 2300 2200
~
(/)
a..
~ 2100 Acceptable
- J rn Operation rn
~
a..
0 C
ell P = 11.14
- Tout - 4706
~
0
~ 2000
.8
(..)
ell (I) 0::
Unacceptable 1900 Operation P = 1800 psig T = 584 °F 1700 ~~~~~~ .....~~~~~-+-~~~~~--+~~~~~~+--~~~~---,
540 560 580 600 620 640 Reactor Coolant Outlet Temperature, °F
ONEl-0400-491 Rev 0 Page 7 of 22 Oconee 2 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
?max=> 109.4 -14.4
?max=> 109.4 14.4 90.0 35.0 0.0 35.0 3 Pumps 0.0 -35.0 62.3 -35.0
?max=> 81.7 -14.4
?max=> 81.7 14.4 62.3 35.0 0.0 35.0
ONEl-0400-491 Rev 0 Page 8 of 22 Oconee 2 Cycle 29 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 -27.0 -27.3 80.0 -28.0 -27.0 -27.3 90.0 -28.0 -22.8 -23.1 100.0 -17.7 -16.8 -17.1 102.0 -15.6 -15.6 -15.6 102.0 15.6 11.7 12.1 100.0 17.7 13.4 13.8 90.0 28.0 21.9 22.3 80.0 28.0 25.6 25.9 0.0 28.0 25.6 25.9 3 Pumps 0.0 -28.0 -27.0 -27.3 63.1 -28.0 63.7 -27.3 64.0 -27.0 77.0 -13.2 -13.2 -13.2 77.0 13.2 13.2 13.2 65.3 25.6 65.0 25.9 63.1 28.0 0.0 28.0 25.6 25.9 Referred to by TS 3.2.2
ONEl-0400-491 Rev 0 Page 9 of 22 Oconee 2 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 lncore Alarm Out of Core Alarm 107.9 -14.4 14.4 106.0 -16.4 16.4 105.0 -17.5 17.5 104.0 -18.5 18.5 103.0 -19.6 19.6 102.0 -20.7 20.7 -15.6 15.6 -15.6 12.1 101.0 -21.7 21.7 -16.7 16.7 -16.4 13.0 100.0 -22.8 22.8 -17.7 17.7 -17.1 13.8 99.0 -23.9 23.9 -18.7 18.7 -17.7 14.7 98.0 -24.9 24.9 -19.8 19.8 -18.3 15.5 97.0 -26.0 26.0 -20.8 20.8 -18.9 16.4 96.0 -27.0 27.0 -21.8 21.8 -19.5 17.2 95.0 -28.1 28.1 -22.9 22.9 -20.1 18.1 94.0 -29.2 29.2 -23.9 23.9 -20.7 18.9 93.0 -30.2 30.2 -24.9 24.9 -21.3 19.8 92.0 -31.3 31.3 -25.9 25.9 -21.9 20.6 91.0 -32.3 32.3 -27.0 27.0 -22.5 21.5 90.4 -33.0 33.0 -27.6 27.6 -22.9 22.0 90.0 -33.0 33.0 -28.0 28.0 -23.1 22.3 89.0 -33.0 33.0 -28.0 28.0 -23.5 22.7 88.0 -33.0 33.0 -28.0 28.0 -23.9 23.0 87.0 -33.0 33.0 -28.0 28.0 -24.4 23.4 86.0 -33.0 33.0 -28.0 28.0 -24.8 23.7 85.0 -33.0 33.0 -28.0 28.0 -25.2 24.1 84.0 -33.0 33.0 -28.0 28.0 -25.6 24.5 83.0 -33.0 33.0 -28.0 28.0 -26.0 24.8 82.0 -33.0 33.0 -28.0 28.0 -26.5 25.2 81.0 -33.0 33.0 -28.0 28.0 -26.9 25.5 80.0 -33.0 33.0 -28.0 28.0 -27.3 25.9 0.0 -33.0 33.0 -28.0 28.0 -27.3 25.9
% FP RPS Trip Full lncore Alarm Out of Core Alarm
ONEl-0400-491 Rev 0 Page 10 of 22 Oconee 2 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 Trio Full lncore Alarm Out of Core Alarm 80.6 -14.4 14.4 80.0 -15.0 15.0 79.0 -16.1 16.1 78.0 -17.1 17.1 77.0 -18.2 18.2 -13.2 13.2 -13.2 13.2 76.0 -19.3 19.3 -14.3 14.3 -14.3 14.3 75.0 -20.3 20.3 -15.3 15.3 -15.3 15.3 74.0 -21.4 21.4 -16.4 16.4 . -16.4 16.4 73.0 -22.5 22.5 -17.5 17.5 -17.4 17.4 72.0 -23.5 23.5 -18.5 18.5 -18.5 18.5 71.0 -24.6 24.6 -19.6 19.6 -19.6 19.6 70.0 -25.7 25.7 -20.7 20.7 -20.6 20.6 69.0 -26.7 26.7 -21.7 21.7 -21.7 21.7 68.0 -27.8 27.8 -22.8 22.8 -22.7 22.7 67.0 -28.8 28.8 -23.8 23.8 -23.8 23.8 66.0 -29.9 29.9 -24.9 24.9 -24.9 24.8 65.0 -31.0 31.0 -26.0 26.0 -25.9 25.9 64.0 -32.0 32.0 -27.0 27.0 -27.0 25.9 63.7 -32.4 32.4 -27.4 27.4 -27.3 25.9 63.1 -33.0 33.0 -28.0 28.0 -27.3 25.9 63.0 -33.0 33.0 -28.0 28.0 -27.3 25.9 62.0 -33.0 33.0 -28.0 28.0 -27.3 25.9 61.0 -33.0 33.0 -28.0 28.0 -27.3 25.9 60.0 -33.0 33.0 -28.0 28.0 -27.3 25.9 0.0 -33.0 33.0 -28.0 28.0 -27.3 25.9
%FP RPS Trip Full lncore Alarm Out of Core Alarm
ONEl-0400-491 Rev 0 Page 11 of 22 Oconee 2 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.Q
~-------1----"--_..;..-.....ll[
100.0 M1 = 0.942 M2*-0.942~
( Acceptable 4 Pump Operation
(-33.0,90.4) (33.0,90.4)
(- 14 .4,ao. 6 ) .-----~~r+---(1_4_.4_,a_o._6~)
- 60.0
(-33.0,63.1) (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 20.0 30.0 40.0 Percent Power Imbalance
ONEl-0400-491 Rev 0 Oconee 2 Cycle 29 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 14.4, 107 9
-14.4, 107.9 t= RPS Trip Setpoint -- ---l@ RPS Trip Setpoint 100 ;:: -15.6, 102.0
~
11.7, 102.0 -
-16.8, 100.0
- -33.0, 90.4 13.4, 100.0 - - 33.0, 90.4 =~~
90
-22.8, 90.0 21.9, 90.0 I- 1--1-- -"'I 80 -27.0, 80.0 25.6, 80.0 Labels Correspond to the Backup lncore Alarm Setpoints 70 L..
Q)
- s:0
- n. 60
- i
-c LL 0
Q) 50
- Backup lncore
-outcore t.l L..
-lncore Q)
- n. -II-RPS Trip 40 30 20 10 i= -33.0, 0.0
-27.0, 0.0 25.6, 0.0 =tl;r=t:::t=t::t:::t=!=t:- 33.0, 0.0 ==
0 -
-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance
l Oconee 2 Cycle 29 ONEl-0400-491 Rev 0 Imbalance Setpoints for 3 Pump Operation, BOC to EOC Referred to by TS 3.2.2 and TS 3.3.1 Page 13 of 22 110 100 90
-14.4, 80.6 14.4, 80.6 80 1:::t::::t=t= RPS Trip Setpoint -13.2, 77.0 RPS Trip Setpoint 13.2, 77.0 70
....Q) s:0
-33.0, 63.1 25.6, 65.3 ~ ~~
33.0, 63.1 ==
-27.0, 64.0 a.. 60
- i u...
0
+-'
C Q) 50 Labels Correspond to the Backup lncore Alarm Setpoints
....Q) t.) I-a.. 40 --
-Backup lncore
-.-outcore I-30 -lncore
-II-RPS Trip 20
,_ ~~
10 0
E-33.o, o.o -27.0, 0.0 25.6, 0.0 33.0, 0.0 ~=
-40 -35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance
ONEl-0400-491 Rev 0 Page 14 of 22 Oconee 2 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-0400-491 Rev 0 Page 15 of 22 Oconee 2 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-0400-491 Rev 0 Oconee 2 Cycle 29 Referred to by TS 3.2.1 Page 16 of 22 105 ....... .... "' ""' = ,,, .... "' ,. 105 224.6, 102.0 263.5, 102.0 !mHI 300.0, 102.0 :
100 ""' ""' """' ""' ',_, s 100 221.5, 100.0 ""' ""
Control Rod Position Setpoints 261.5, 100.0 95 No Inoperable Rods, 4 Pump Flow, 95 90 BOC to EOC 90 85 ...
251.5, 90.0 85 80 80 241.5, 80.0 75 75 70 175.o; 69.8 70 65 225.0, 67.6 65 a..
LL 60 Unacceptable 60
- g 0
Operation Restricted Q)
~
55 ....
.... Operation 55 0 .... .. Acceptable 50
....0 50 a.. 201.5, 50.0 111111 1111 141.5, 48.0 Operation t) 45 45
<II Q) ..195.2, 48.0 0:: 40 40 125.0, 39.1 175.0, 41.6 35 35 30 30 25 25 125.0, 25.7 20 20 15 76.5, 13.0 - 15 91.5, 15.0 10 1.5, 3.0 10 5
.... *-.. 75.0, 12.8
... Group 6 5 0.0, 2.8 lffll 0 Jtilt 0.0, 0.0 ..16.5, 5.0
""' 5 15 25 35 45 55 65 75 85 95 0
lo 10 20 30 40 50 60 70 80 90 100 I lo 10 20 30 40 50 60 70 80 90 100 I I Group 5 I Control Rod Position, % WO Group 7
ONEl-0400-491 Rev 0 Oconee 2 Cycle 29 Referred to by TS 3.2.1 Page 17 of 22 105 105 100 100 Control Rod Position Setpoints 95 95 No Inoperable Rods, 3 Pump Flow, 90 BOC to EOC 90 85 85 227.4, 77.0 80 80 237.5, 77.0 300.0, 77.0 225.0, 76.2 75 ~ 75 221.5, 75.0 234.8, 75.0 70 ..::*- 70 65 225.0, 67.6 65 c.. Unacceptable 175.0, 59.3 -
LL - 60 60 Operation
~
0
..: 55 55 Q)
~ 50 c.. 50 141.5, 48.0 0 Restricted 201.5, 50.0
+-'
u 45 Operation 195.2, 48.0 45
('(l Q) er: 40 125.0, 39.1 40 175.0, 41.6 35 Acceptable 35 Operation
' 30 30 25 25 125.0, 25.7 20 20
- 15 15 76.5, 13.0 91.5, 15.0 10 1.5, 3.0 10 75.0, 12.8 0.0, 2.8 Group 6 5 5 16.5, 5.0 5 15 25 35 45 55 65 75 85 95 Io-0 '"' 0 10 20 30 40 50 60 70 80 90 100 I 10 10 20 30 40 50 60 70 80 90 100 I 0.0, 0.0 I Group 5 I Control Rod Position,% WD Group 7
ONEl-0400-491 Rev 0 Oconee 2 Cycle 29 Referred to by TS 3.2.1 Page 18 of 22 105 '
300.0, 102.0 105 II
'"' 283.4, 102.0 .,
II '"' "'
100 '"'
100 Control Rod Position Setpoints 281.5, 100.0
' 1 Inoperable Rod, 4 Pump Flow, ' ' 95 95 BOC to EOC 90 ' 90 85 ' 85 80 '
80 75 75 70 '
70 65 65 Unacceptable 0...
LL Operation 60
- R 60 0
Q) 55 55
~
0 0...
L...
50 231.5, 48.0 Acceptable 50
~co 45 225.0, 44.8
- = Operation 45 Q) 0::
40 40 35 35 30 30 25 25 20 175.0, 19.8 20 I I 161.5, 13.0 15 15 125.0, 8.7 10 76.5, 3.0
- . ::: 10 11-Ill 75.0, 2.82 ""
1-ffl Group 6 5 74.8, 2.8 5 Ill 51.0, 0.0 '"' 5 15 25 35 45 55 65 75 85 95 0 0 lo 10 20 30 40 50 60 70 80 90 100 I I 0 10 20 30 40 50 60 70 80 90 10 a I I Group 5 I Control Rod Position, % WD Group 7
Referred to by TS 3.2.1 ONEl-0400-491 Rev 0 Oconee 2 Cycle 29 Pa e 19 of 22 10 5 105
~
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100 10 0 Control Rod Position Setpoints 95 1 Inoperable Rod, 3 Pump Flow, 95 BOC to EOC 90 90 85 ' 85 80 300.0, 77.0 80 285.2, 77.0 75 281.5, 75.0 75 70 Unacceptable 70 Operation I 65 65 a...
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15 I 225.0, 44.8 45 aJ 45 Acceptable a:: Operation 40 40 35 35 30 ' 30 25 25 20 175.0, 19.8 - 20
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' I 161.5, 13.0 15 15 125.0, 8.7 76.5, 3.0 10 10 75.0, 2.82 '"' ,. '
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15 25 35 45 55 65 75 85 95 0 0 Jo 10 20 30 40 50 60 70 80 90 100 I I 0 10 20 30 40 50 60 70 80 90 100 I I Group 5 I Control Rod Position ' 0YcoWD I Group 7 I
ONEl-0400-491 Rev 0 Page 20 of 22 Oconee 2 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.
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Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State Transient Maximum Core Power Level, %FP 0 - 30 > 30 0 - 30 > 30 >O Quadrant Power Tilt, % 10.00 5.40 12.00 9.44 20.00 Variable Low RCS Pressure Protective Limits Referred to by TS 2.1.1 Core Outlet Pressure Reactor Coolant Outlet Temperature, °F psia 3 RCS Pumps 4 RCS Pumps 1800 581.0 578.3 1900 590.0 587.3 2000 598.9 596.3 2100 607.9 605.2 2200 616.9 614.2 2300 625.9 623.2
ONEl-0400-491 Rev 0 Page 21 of 22 Oconee 2 Cycle 29 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1
%FP RPS Operational 4 Pumps 0.0 -35.0 -38.6 80.0 -38.6 90.0 -35.0 -34.3 100.0 -27.6 109.4 -14.4 109.4 14.4 100.0 23.6 90.0 35.0 33.2 80.0 37.0 0.0 35.0 37.0 3 Pumps 0.0 -35.0 -38.6 62.3 -35.0 77.0 -38.6 81.7 -14.4 81.7 14.4 77.0 37.0 62.3 35.0 0.0 35.0 37.0
ONEl-0400-491 Rev 0 Page 22 of 22 Oconee 2 Cycle 29 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal
%FP Insertion Limit No lnop Rod 1 lnop Rod Limit 4 Pumps 102 262 220 280 300 100 260 300 90 250 300 80 240 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300 3 Pumps 77 236 220 280 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300