ML033420944
| ML033420944 | |
| Person / Time | |
|---|---|
| Site: | Oconee  |
| Issue date: | 11/12/2003 |
| From: | Rosalyn Jones Duke Power Co |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| Download: ML033420944 (25) | |
Text
Duke P DPowere A Duke Energy Company R. A. JONES Vice President Duke Power 29672 / Oconee Nuclear Site 7800 Rochester Highway Seneca, SC 29672 864 885 3158 864 885 3564 fax November 12, 2003 U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Subject:
Oconee Nuclear Site Docket No. 50-270/50-287 Core Operating Limits Report (COLR)
Gentlemen:
Attached, pursuant to Oconee Technical Specifications 5.6.5, is an information copy of a revision to the Core Operating Limits Report for Oconee Unit 2, Cycle 20, Rev. 19 and Unit 3, Cycle 21, Rev 18.
Very k y yours, R. A ones Site, Vice President Oconee Nuclear Site Attachment An rD I www. duke-energy. corn
NRC Document Control Desk November 12, 2003 Page 2 xc w/att:
Mr. L. A. Reyes, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr. Mel Shannon Senior Resident Inspector Oconee Nuclear Site
PRIORITY SuperRush DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS OTHERWISE IDENTIFIED BELOW
- 1) 00620 DOC MGMT MICROFILM EC03C
- 2) 00813 DOC MGMT EC03C ORIGINAL
.3) 06358 ONS REGUL COMPUANCE ON03RC
- 4) 06700 ONS MANUAL MASTER FILE ON03DM
- 5) 06937 R R ST CLAIR ECo8G Duke Power Company DOCUMENT TRANSMITTAL FORM REFERENCE NUCLEAR GENERAL OFFICE OCONEE NUCLEAR STATION EXEMPTION CODE: M-5 CORE OPERATING LIMITS REPORT Page 1 of 1 Date:
11/10103 Document Transmittal #
DUK033140020 QACONDmON E Yes D No OTHER ACKNOWLEDGEMENT REQUIRED D1 Yes IF OA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:
Duke Power Company P.O. Box 1006 Energy Center EC03C Charlotte, N.C Rec'd By Date 1
DOCUMENT NO, QACOND REV #1 DATE DISTR CODE 1
2 3
4 5
6 7
8 9
10 Ill 12 1 13 14 115 TOTAL l
l l
l l
l I
l l
I I
ONEI-0400-051 ONEI-0400-070 SEE REMARKS
- 1 I
019 11/10/03 018 11/10103 11 11 NOMD-27 V1 K
VI 4
.F INI Tic N NdY
.~._
I l
REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM (NUCLEAR) MODIFICATION PROGRAM PLEASE UPDATE YOUR DOCUMENT WITH THE PAGES RECEIVED ON THIS TRANSMITTAL. THIS IS NOT THE ENTIRE DOCUMENT.
K S CANADY MANAGER NUCLEAR ENGINEERING BY:
J W SIMMONS JWS/AYB EC08H
ONEI-0400-51 Rev 19 Page 1 of 32 Duke Power Company Oconee 2 Cycle 20 Core Operating Limits ReporfOR INFORMATION ONLY QA Condition I R-Rv eEDNfDA ppoyEDoeebAAf
)
Prepared By: J. D. Forster f&.
Checked By: G. M. Presnell Date: -6 tY Date :
lk 6, ooy CDRBy: S. G. Siry tUW62 I.
1A Date: 1117103 Approved By: R. R. St. Clair Dat:
Date: /j/
747/W0~3
Document NoJ Rev. ONEI-0400-51 Rev. 19 Date November 6. 2003 Page No.
page I a of 32 INSPECTION OF ENGINEERING INSTRUCTIONS Date:
Jt/2(2t03 Inspection Waived By:
(Sponsr-),-
.)
CATAWBA Inspection Waived MCE (Mechanical & Civil)
D Inspected By/Date:
RES (Electrical Only)
[l Inspected By/Date:
RES (Reactor)
[7 Inspected By/Date:
[l Inspected By/Date:_
Other (
)
[
Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil)
[:
Inspected By/Date:
RES (Electrical Only)
[:
Inspected By/Date:
RES (Reactor)
Inspected By/Date:
MOD WI' Inspected By/Date:
Other (
)
[
Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil)
[7 Inspected By/Date:
RES (Electrical Only) a Inspected By/Date:
RES (Reactor)
[l Inspected By/Date:
[D Inspected By/Date:
Other (
l)
Inspected By/Date:
ONEI-0400-51 Rev 19 Page 2 of 32 Oconee 2 Cycle 20 Core Operating LimitsReport Insertion Sheet for Revision 19 This revision is not valid until the end of operation for Oconee 2 Cycle 19.
Remove these revision 18 pages Insert these revision 19 pages 1-4, 8-10, 12-13, 29 1-4, 8-10, 12-13;29 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages Oconee 2 Cycle 20 revisions below
.19 Nov2003 1-4.8-10,12-13,29 32 198
.Ncov2002.
1-3.1,126,24,30 32 17 Oct 2002 1 - 31 32 32 lOconee 2 Cycle !19 revisions below
.16 FMay2001 1-31 31 Oconee 2 Cycle 18 revisions below 15 Apr2001 1-4 31 14 Feb 2000 1-4 31 13 Nov 1999 1-31 31 12 Sep. 1999 1-31 31 11 Apr 1999 1-4,6 31 10 Mar 1999 1-31 31
ONEI-0400-51 Rev 19 Page 3 of 32 Oconee 2 Cycle 20 1.0 Error Adjusted Core Operating Umits The Core Operating Limits Report for 02C20 has been prepared in accordance with the requirements of ITS 5.6.5. The core operating limits within this report have bedn developed using NRC approved methodology identified in references 1 through 10. The RPS protective limits and maximum allowable setpoints are documented In references 11 through 13. These limits are validated for use in 02C20 by references 14 through 16. The 02C20 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (F&h) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (< 100 ppmB) Tavg reduction of up to 10 OF provided 4 RCPs are in operation and Tavg does not decrease below 569 OF.
The error adjusted core operating limits included In section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 02C20 reload core.
1.1 References
- 1. Nuclear Design Methodology Using CASMO-3 i SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November 23,1992.
- 2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002A, Revision 1, SER dated October 1,1985.
- 3. Oconee NuclearStation Reload Design Methodology, NFS-1001A, Revision 5, SER dated December 8, 2000.
- 4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003P-A, Revision 1, SER dated June 23,2000.
- 5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005P-A, Revision 2, SER dated June 8,1999.
- 6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, SER dated April 3,1995.
- 7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 1, SER dated May 25,1999.
- 8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 2, SER dated October 14, 1998.
- 9. BAW-10192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.
- 10. BAW-10227-PA, Evaluation of Advanced Cladding and Structural Material (M5) In PWR Reactor Fuel, SER dated February 4, 2000.
- 11. Variable Low Pressure Safety Limit, OSC-4048, Revision 4, January 2001.
- 12. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001.
- 13. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.
- 14. 02C20 Maneuvering Analysis, OSC-8082, Revision 4, November 2003.
- 15. 02C20 Specific DNB Analysis, OSC-8103, Revision 0, June 2002.
- 16. 02C20 Reload Safety Evaluation, OSC-8182, Revision 1, November 2002.
ONEI-0400-51 Rev 19 Page 4 of 32 Oconee 2 Cycle 20 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm.
Referred to by ITS 3.5A.
Spent fuel pool boron concentration shall be greater than 2220.
Referred to by ITS 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 ITS SLC 16.5.13.
CFT boron concentration shall be greater than 1835 ppm. The average boron concentration in the CFT's shall be less than 4000 ppm.
Referred to by ITS 3.5.1.
RCS and Refueling canal boron concentration shall be greater than 2220 ppm.
Referred to by ITS 3.9.1.
Shutdown Margin (SDM) shall be greater than 1% Aktk.
Referred to by ITS 3.1.1.
Moderator Temperature Coefficient (MTC) shall be less than:
Linear Interpolation is valid within the table provided.
Referred to by ITS 3.1.3.
)
MTC x 10-4 Api°F
+0.70
+0.40 0.00
-0.125
-0.25
% FP 0
15 80 100 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by ITS 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 ITS 3.4.1.
The measured Tavg must be less than COLR limits minus instrument uncertainty. ATc Is the setpolnt value selected by the operators. Values are expanded by linear Interpolation on page 32 of this document without instrument uncertainty.
Max Loop Tavg (Incl 2 0F 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 ITS 3.4.1.
4 RCP:
Measured > 107.5 %df 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 ITS 3.2.1.
Regulating rod group overlap shall be 25% +/- 5% between two sequential groups.
Referred to by ITS 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 A (Control Rod Group Alignment Umits), TS 3.1.5 (Safety Rod Position Limits), and TS 32.3 (Quadrant Power Tilt).
ONEI-0400-51 Rev 19 Page 8 of 32 Oconee 2 Cycle 20 Operational Power Imbalance Setpoints Full Backup Out of
%FP Incore Incore Core 4 Pumps 0
-26.0
-25.5
-26.0 80
-26.0
-25.5
-26.0 90
-22.7
-22.3
-22.7 100
-13.5
-13.1
-13.5 102
-11.7
-11.3
-11.7 102 17.0 17.0 17.0 100 19.1 18.9 19.1 90 24.6 24.3 24.6 80 28.1 27.6 28.1 0
28.1 27.6 28.1 3 Pumps 0.0
-26.0
-25.5
-26.0 68.50
-26.0
-26.0 68.97
-25.5 77.0
-11.7
-11.3
-11.7 77.0 17.0 17.0 17.0 66.98 27.6 66.51 28.1 28.1 0.0 28.1 27.6 28.1
ONEI-0400-51 Rev 19 Page 9 of 32 Oconee 2 Cycle 20 Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC
_ _P I
RPS Trip I
Full Incore Alarm I
Out of Core Alarm
)
107.9 107 106 105 104 103 102 101 100 99 98 97 96 95 94 93 92 91 90.4 90 89 88 87 86 85 84 83-82 81 80 0
-14.40
-15.36
-16.42
-17.48
-18.55
-19.61
-20.67
-21.73
-22.80
-23.86
-24.92
-25.99
-27.05
-28.11
-29.17
-30.24
-31.30
-32.36
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00 14.40 15.36 16.42 17.48 18.55 19.61 20.67 21.73 22.80 23.86 24.92 25.99 27.05 28.11 29.17 30.24 31.30 32.36 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00
-11.70
-12.60
-13.50
-14.42
-15.34
-16.26
-17.18
-18.10
-19.02
-19.94
-20.86
-21.78
-22.33
-22.70
-23.03
-23.36
-23.69
-24.02
-24.35
-24.68
-25.01
-25.34
-25.67
-26.00
-26.00 17.00 18.05 19.10 19.65 20.20 20.75 21.30 21.85 22.40 22.95 23.50 24.05 24.38 24.60 24.95 25.30 25.65 26.00 26.35 26.70 27.05 27.40 27.75 28.10 28.10
-13.50
-14.42
-15.34
-16.26
-17.18
-18.10
-19.02
-19.94
-20.86
-21.78
-22.33
-22.70
-23.03
-23.36
-23.69
-24.02
-24.35
-24.68
-25.01
-25.34
-25.67
-26.00
-26.00
-11.70
-12.60 17.00 18.05 19.10 19.65 20.20 20.75 21.30 21.85 22.40 22.95 23.50 24.05 24.38 24.60 24.95 25.30 25.65 26.00 26.35 26.70 27.05 27A0 27.75 28.10 28.10
% FP 1~
RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-51 Rev 19 Page 10 of 32 Oconee 2 Cycle 20 Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOC
% FP I
RPS Trip I
Full Incore Alarm I
Out of Core Alarm
)
80.6 80 79 78 77.0 76 75 74 73 72 71 70 69 68.5 68 67 66.5 66 65 64 63.1 63 62 61 60 0
-14.40
-15.04
-16.10
-17.16
-18.23
-19.29
-20.35
-21.41
-22.48
-23.54
-24.60
-25.67
-26.73
-27.26
-27.79
-28.85
-29.37
-29.92
-30.98
-32.04
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00 14.40 15.04 16.10 17.16 18.23 19.29 20.35 21.41 22.48 23.54 24.60 25.67 26.73 27.26 27.79 28.85 29.37 29.92 30.98 32.04 33.00 33.00 33.00 33.00 33.00 33.00
-11.70
-13.38
-15.06
-16.75
-18.43
-20.11
-21.79
-23.47
-25.15
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00 17.00 18.06 19.12 20.18 21.23 22.29 23.35 24.41 25.47 26.00 26.53 27.58 28.10 28.10 28.10 28.10 28.10 28.10 28.10 28.10 28.10 28.10
-11.70
-13.38
-15.06
-16.75
-18.43
-20.11
-21.79
-23.47
-25.15
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00
-26.00 17.00 18.06 19.12 20.18 21.23 22.29 23.35 24.41 25.47 26.00 26.53 27.58 28.10 28.10 28.10 28.10 28.10 28.10 28.10 28.10 28.10 28.10
% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-51 R 9
Page 12 of 32 Oconee 2 Cycle 20 Imbalance Setpoints for 4 Pump Operation, BOC to EOC 110 RPS Trp Setpoint 100 Incore & Outcore Alarm RPS Trip Setpoint 90 80 70 L.
0 C:
0) 0.
60 50 40 30 20 10 O I
-40
-35
-30
-25
-20
-15
-10
-5 0
5 Percent Axial Imbalance 10 15 20 25 30 35 40
ONEI-0400-51 Rev-,
Page 13 of 32 110 Oconee 2 Cycle 20 Imbalance Setpoints-for 3 Pump Operation, BOC to EOC RPS Trip Set p it.
100 90 80 r
ir lncore & Outcore Alarm:
70
.RPS Trip Setpoint F=I L-CD 0)
Q..
0) 0~
60 50 40 30 20 10 0 j;
-40
-35
-30
-25
-20
-15
-10
-5 0
5 Percent Axial Imbalance 10 1
i5 20 25 30 35 40
ONEI-0400-51 Rev 19 Page 29 of 32 Oconee 2 Cycle 20 Axial Power Imbalance Protective Limits Referred to by ITS 2.1.1 c$ r
%FP 4 Pumps
)
0 80 90 100 112.
112 100 90 80 0
0 74.6 77.0 86.6 86.6 77.0 74.6 0
-48.0
-48.0
-31.1 31.1 48.0 48.0
-48.0
-48.0
-31.1 31.1 48.0 48.0 Operational
-37.0
-37.0
- -33.7
-23.2 30.0 36.0 39.6 39.6
-37.0
-37.0 39.6 39.6 3 Pumps
ONEI-0400-70 Rev 18 Page 1 of 33 j
Duke Power Company Oconee 3 Cycle 21 FOR INFORMATION ONLY Core Operating Limits Report QA Condition I
.)
Noa t Re x.'
d orApproved by CFAM 3.13 ammDvpRO J. D. Forster Zb-A (
ot Prepared By:
Checked By:
kJ G. M. Presnell M' Date: 06 NN He Date:
It' 6-2zoo CDR By: S. G. Siry llaL!OJ-D. !Liz Date: 11/710 3 V
V Approved By: R. R. St. Clair An 4!
,D/7 Date: {/ /71--c300
Document No} Rev. ONEI-0400-70 Rev. 18 Date November 6. 2003 Page No.
page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By:
. /,<_
A7 Date:
17/ZO3 (Sponsor)
.)
CATAWBA Inspection Waived MCE (Mechanical & Civil)
[D Inspected By/Date:
RES (Electrical Only)
E Inspected By/Date:
RES (Reactor)
[
Inspected By/Date:
MOD 5
Inspected By/Date:
Other (
)
a Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil)
E Inspected By/Date:
RES (Electrical Only)
Inspected By/Date:
RES (Reactor)
Inspected By/Date:
MOD Inspected By/Date:
Other (
)
[
Inspected By/Date:
MCGUIRE Inspection Waived MCE (Mechanical & Civil)
E]
Inspected By/Date:
RES (Electrical Only)
D Inspected By/Date:
RES (Reactor) 5 Inspected By/Date:
[
Inspected By/Date:
Other (
)
[
Inspected By/Date:
I
ONEI-0400-70 Rev 18 Page 3 of 33 Oconee 3 Cycle 21 Core Operating Limits Report Insertion Sheet for Revision 18 This revision is not valid until the end of operation for Oconee 3 Cycle 20.
Remove these revision 17 pages Insert these revision 18 pages 1-5, 9-11, 13-14,30 1-5, 9-11, 13-14, 30
)
Revision Log Effective Pages Pages Revision Date Revised Added Pages Total Effective Deleted Pages IOconee 3 Cycle 21 revisions below
- 18 Nov. 2003 1-5,9-11,13-14,30 33 17 Apr.2003 1 - 31 32 - 33 33 Oconee 3 Cycle 20 revisions below 16 Oct.2002 1 -3,5 31 15 NoV.-2001 1-3 31 14 Nov.2001 1 - 31 31 Oconee 3 Cycle 19 revisions below l
1 3 Apr.2000 1'- 31 31
)
ONEI-0400-70 Rev 18 Page 4 of 33 Oconee 3 Cycle 21 1.0 ErrorAdjusted Core Operating Limits The Core Operating Limits Report for 03C21 has been prepared In accordance with the requirements of ITS 5.6.5. The core operating limits within this report have been developed using NRC approved methodology identified In references 1 through 10. The RPS protective limits and maximum allowable setpoints are documented In references 11 through 13. These limits are validated for use in 03C21 by references 14 through 16. The 03C21 analyses assume a design flow of 107.5% of 88,000 gpm per RCS pump, radial local peaking (FAh) of 1.714, and axial peaking factor (Fz) of 1.5, and an EOC (E 100 ppmB) Tavg reduction of up to 10 OF provided 4 RCPs are In operation and Tavg does not decrease below 569 OF.
The error adjusted core operating limits Included In section 1 of the report Incorporate all necessary uncertainties and margins required for operation of the 03C21 reload core.
1.1 References
- 1. Nuclear Design Methodology Using CASMO-3 I SIMULATE-3P, DPC-NE-1004P-A, Revision 0, SER dated November 23, 1992.
- 2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1002A. Revision 1, SER dated October 1,1985.
- 3. Oconee Nuclear Station Reload Design Methodology, NFS-1001A, Revision 5,
)
SER dated December 8,2000.
- 4. ONS Core Thermal Hydraulic Methodology Using VIPRE-O1, DPC-NE-2003P-A, Revision 1, SER dated June 23,2000.
- 5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005P-A, Revision 2, SER dated June 8,1999.
- 6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008P-A, SER dated April 3,1995.
- 7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA. Revision 1, SER dated May 25, 1999.
- 8. DPC-NE-3000P-A, Thermal Hydraulic Transient Analysis Methodology, Rev. 2, SER dated October14,1998.
- 9. BAW-10192-PA. BWNT LOCA-BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, SER dated February 18, 1997.
- 10. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, SER dated February 4, 2000.
- 11. Variable Low Pressure Safety Limit, 0SC-4048, Revision 4, January 2001.
- 12. Power Imbalance Safety Umits and Tech Spec SetpoInts Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October2001.
- 13. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.
- 14. 03C21 Maneuvering Analysis, OSC-8178, Revision 3, November2003.
- 15. 03C21 Specific DNB Analysis, OSC-8220. Revision 0, October2002.
- 16. 03C21 Reload Safety Evaluation, OSC-8400, Revision 1, November2003.
ONEI-0400-70 Rev 18 Page 5 of 33 Oconee 3 Cycle 21 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm.
Referred to by ITS 3.5.4.
Spent fuel pool boron concentration shall be greater than 2220 ppm.
Referred to by ITS 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 ITS SLC 16.5.13.
CIFT boron concentration shall be greater than 1835 ppm. The average boron concentration In the CFT's shall be less than 4000 ppm.
Referred to by ITS 3.5.1.
RCS and Refueling canal boron concentration shall be greater than 2220 ppm.
Referred to by ITS 3.9.1.
Shutdown Margin (SDM) shall be greater than 1% Ak/k.
Referred to by ITS 3.1.1.
Moderator Temperature Coefficient (MTC) shall be less than:
Unear Interpolation is valid within the table provided.
Referred to by ITS 3.1.3.
)
MTC x 10-4 Ap/4 F
+0.70
+0.40.
0.00
-0.125
-0.25
% FP 0
15 80 100 120 Departure from Nucleate Boiling (DNB) parameter for RCS loop pressure shall be Referred to by ITS 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 ITS 3.4.1.
The measured Tavg must be less than COLR limits minus instrument uncertainty. ATc Is the setpoint value selected by the operators. Values are expanded by linear interpolation on page 33 of this document without instrument uncertainty.
Max Loop Tavg (Inci 20F 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 ITS 3.4.1.
4 RCP:
Measured > 107.5 %df 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 ITS 3.2.1.
Regulating rod group overlap shall be 25% +/- 5% between two sequential groups.
Referred to by ITS 3.2.1.
Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculations when determining if overlap requirements are met as these situations are explicitly addressed by TS 3.1.4 (Control Rod Group Alignment Limits), TS 3.1.5 (Safety Rod Position Limits), and TS 3.2.3 (Quadrant Power Tilt).
ONEI-0400-70 Rev 18 Page 9 of 33 Oconee 3 Cycle 21 Operational Power Imbalance Setpoints 4 Pumps 3 Pumps
%FP 0
80 90 100 102 102 100 90 80 0
0.0 70.10 70.58 77.0 77.0 68.12 67.65 0.0 Full Incore
-24.3
-24.3
-21.1
-12.3
-10.5 17.0 18.6 23.7 26.9 26.9
-24.3
-24.3
-10.5 17.0 26.9 26.9 Backup Incore
-23.8
-23.8
-20.7
-11.9
-10.1 17.0 18.3 23.4 26.4 26.4
-23.8
-23.8
-10.1 17.0 26.4 26.4 Out of Core
-24.3
-24.3
-21.1
-12.3
-10.5 17.0 18.6 23.7 26.9 26.9
-24.3
-24.3
-10.5 17.0 26.9 26.9
ONEI-0400-70 Rev 18 Page 10 of 33 Oconee 3 Cycle 21 Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC
Full Incore Alarm Out of Core Alarmr
-14.40 107.9 107 106 105 104 1 03 102 101 100 99 98 97 96 95 94 93 92
.91 90.4 90 89 88 87 86 85 84 83.
82 81 80 0
-15.36
-16.42
-17.48
-18.55
-19.61
-20.67
-21.73
-22.80
-23.86
-24.92
-25.99
-27.05
-28.11
-29.17
-30.24
-31.30
-32.36
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00 14.40 15.36 16.42 17.48 18.55 19.61 20.67 21.73 22.80 23.86 24.92 25.99 27.05 28.11 29.17 30.24 31.30 32.36 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00 33.00
-10.50
-11.40
-12.30
-13.18
-14.06
-14.94
-15.82
-16.70
-17.58
-18.46
-19.34
-20.22
-20.75
-21.10
-21.42
-21.74
-22.06
-22.38
-22.70
-23.02
-23.34
-23.66
-23.98
-24.30
-24.30 17.00 17.80 18.60 19.11 19.62 20.13 20.64 21.15 21.66 22.17 22.68 23.19 23.50 23.70 24.02 24.34 24.66 24.98 25.30 25.62 25.94 26.26 26.58 26.90 26.90
-10.50
-11.40
-12.30
-13.18
-14.06
-14.94
- -15.82
-16.70
- - -17.58
-18.46
-19.34
-20.22
-20.75
-21.10
-21.42
-21.74
-22.06
-22.38
-22.70
-23.02
-23.34
-23.66
-23.98
-24.30
-24.30 17.00 17.80 18.60 19.11 19.62 20.13 20.64 21.15 21.66 22.17 22.68 23.19 23.50 23.70 24.02 24.34 24.66 24.98 25.30 25.62 25.94 26.26 26.58 26.90 26.90
% FP RPS Trip Full Incore Alarm Out of Core Alarm
A ONEI-0400-70 Rev 18 Page 11 of 33 i
Oconee 3 Cycle 21 Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOC
% FPI RPS Trip Full'Incore Alarm Out of Core Alarm -
,)
80.6 80 79 78 77.0 76 75 74 73
.72 71 70.1 70 69 68 67.65 67 66 65
- 64 63.1 63 62 61 60 0
-14.40
-15.04
-16.10
-17.16
-18.23.
-19.29
-20.35
-21.41
-22.48
-23.54
- -24.60
-25.56
-25.67
-26.73
-27.79
-28.17
-28.85
-29.92
-30.98
-32.04
-33.00
-33.00
-33.00
-33.00
-33.00
-33.00 14.40 15.04 16.10 17.16 18.23 19.29 20.35 21.41 22.48 23.54 24.60 25.56 25.67 26.73 27.79 28.17 28.85 29.92 30.98 32.04 33.00 33.00 33.00 33.00
.33.00 33.00
-10.50
-12.50
-14.50
-16.50
-18.50
-20.50
-22.50
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30 17.00 18.06 19.12 20.18 21.23 22.29 23.35 24.30 24.41 25.47 26.53 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90
-10.50
-12.50
-14.50
-16.50
-18.50
-20.50
-22.50
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30
-24.30 17.00 18.06 19.12 20.18 21.23 22.29 23.35 24.30 24.41 25.47 26.53 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90 26.90
% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-7(
/ 18 Page 13 of 33 Oconee 3 Cycle 21 Imbalance Setpoints. for 4 Pump Operation, BOC to EOC f.
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ONEI-0400-70 RbV 18 Page 14 of 33 110 Oconee 3 Cycle 21 Imbalance Setpoints for 3 Pump Operation, BOC to EOC
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ONEI-0400-70 Rev 18 Page 30 of 33 Oconee 3 Cycle 21 Axial Power Imbalance Protective Limits Referred to by ITS 2.1.1 Not 1 1
%FP RPS Operational 4 Pumps I
0 80 90 100.
112 112 100 90 80 0
0 74.6 77.0 86.6 86.6 77.0 74.6 0
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-31.1 31.1 48.0 48.0
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-35.0
-35.0 38.2 J 38.2 3 Pumps