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{{#Wiki_filter: | {{#Wiki_filter:BRUCE H HAMILTON IDuke Vice President Energy Oconee Nuclear Station Duke Energy Corporation ONO0 VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax April 2, 2007 bhhamilton@duke-energy.com U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555 | ||
==Subject:== | ==Subject:== | ||
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Site Docket No. 50-2/s 3 'q-Core Operating Limits Report (COLR)Gentlemen: | Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Site Docket No. 50-2/s 3 'q-Core Operating Limits Report (COLR) | ||
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 23, Rev. 26.Very truly yours, Bruce H. Hamilton Site, Vice President Oconee Nuclear Site Attachment 4DC)(www. duke-energy. | 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 23, Rev. 26. | |||
Very truly yours, Bruce H. Hamilton Site, Vice President Oconee Nuclear Site Attachment 4DC)( | |||
003587 | www. duke-energy. corn | ||
& Civil) E] Inspected By/Date: RES (Electrical Only) L Inspected By/Date: RES (Reactor) | |||
LI Inspected By/Date: MOD LI Inspected By/Date: Other ( _]) -Inspected By/Date: OCONEE Inspection Waived MCE (Mechanical | NRC Document Control Desk April 2, 2007 Page 2 xc w/att: Mr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr. Dan Rich Senior Resident Inspector Oconee Nuclear Site | ||
& Civil) n] 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) LI Inspected By/Date: RES (Electrical Only) LI Inspected By/Date: RES (Reactor) | NRC Document Control Desk April 2, 2007 Page 3 bxc wo/att: NSRB - EC05P bxc w/att: ELL ONS Document Management | ||
LI Inspected By/Date: MOD El Inspected By/Date: Other ( ) [L Inspected By/Date: | |||
ONEI-0400-51 Rev 26 Page 3 of 33 Oconee 2 Cycle 23 Core Operating Limits Report Insertion Sheet for Revision 26 This revision is not valid until the end of operation for Oconee 2 Cycle 22.Remove these Revision 25 pages Insert these Revision 26 pages 1 -33 1 -33 Revision Log Effective | DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 03/27/07 OTHERWISE IDENTIFIED BELOW | ||
--32 17 Oct 2002 1-31 32 -32 lOconee 2 Cycle 19 revisions below -16 May 2001 1-31 --31 ONEI-0400-51 Rev 26 Page 4 of 33 Oconee 2 Cycle 23 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C23 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 02C23 by references 15 through 17. The 02C23 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.The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 02C23 reload core.1.1 References | : 1) 00620 DOC MGMT MICROFILM EC04T Document Transmittal #: DUK070860020 | ||
: 1. Nuclear Design Methodology Using CASMO-3 I SIMULATE-3P, DPC-NE-1 004-A, Revision 0, SER dated November 23, 1992.2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002-A, Revision 2, SER dated October 1, 1985.3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001 A, Revision 5, SER dated December 8, 2000.4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003-PA, Revision 1, SER dated June 23, 2000.5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, Revision 3, SER dated September 1, 2002.6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008-PA, Revision 0, SER dated April 3,1995.7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 2, SER dated September 24, 2003.8. Thermal Hydraulic Transient Analysis Methodology, DPC-NE-3000-PA, Rev. 3, SER dated September 24, 2003.9. BAW-1 0192-PA, BWNT LOCA -BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, Rev. 0, SER dated February 18, 1997.10. BAW-1 01 64P-A, Rev. 4, RELAP5/MOD2-B&W | : 2) 00813 DOC MGMT EC04T ORIGINAL i_2 Duke Energy QA CONDITION N Yes [] No | ||
-An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis, SER dated April 9, 2002.11. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, Rev. 1, June 2003 (SER to BAW-1 01 86P-A dated June 18, 2003).12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit, OSC-4048, Revision 4, January 2001.13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001.14. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.15. 02C23 Maneuvering Analysis, OSC-8974, Revision 1, March 2007.16. 02C23 Specific DNB Analysis, OSC-9001, Revision 0, October.2006. | : 3) 06358 ONS REGUL COMPLIANCE -ON03RC | ||
: 4) 06700 ONS MANUAL MASTER FILE ON03DM DOCUMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED FD Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE | |||
: 5) 06937 R R ST CLAIR ECO8G ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO: | |||
REFERENCE NUCLEAR GENERAL OFFICE Duke Energy OCONEE NUCLEAR STATION P.O. Box 1006 WORK ITEM: EXEMPTION M-5 Energy Center EC04T ve 0% 0- RESP GROUP: NE RECORD RETENTION: 003587 Charlotte, N.C. 28201-1006 OCONEE 2 CYCLE 23 CORE OPERATING LIMITS REPORT Rec'd By %I-) | |||
Page 1 of 1 Date mQlnuo I I DOCUMENT NO QACOND REV #/ DATE DISTR CODE 1 2 1'3' t 4 5 6 7 8 9 10 11 12 113 14 15 TOTAL ONEI-0400-051 1 026 03/27/07 1NOMD-27 V1 X Vik V1 4 REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM THOMAS C GEER NUCLEAR STATION ENGR MANAGER GS-SVP NUCLEAR SUPPORT BY: | |||
J W SIMMONS JWS/JAK EC08H | |||
ONEI-0400-51 Rev 26 Page 1 of 33 Duke Energy Oconee 2 Cycle 23 Core Operating Limits Report QA Condition 1 Prepared By: D.S. Orr d",etzl Date 3 -O7 Checked By: G.M. Presnell P1Y,~t~42 Date: P?/,2 4 20 0*da7 CDR By: A.W. Strange Date: 0 Approved By: R.R. St.Clair Date": 1 -- N6 - .,,.oo7 | |||
Document No. / Rev. ONEI-0400-51 Rev. 26 Date March 22, 2007 Page No. Page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Date: .3h G(D/*O*2. | |||
(Sponsor) | |||
CATAWBA Inspection Waived* | |||
MCE (Mechanical & Civil) E] Inspected By/Date: | |||
RES (Electrical Only) L Inspected By/Date: | |||
RES (Reactor) LI Inspected By/Date: | |||
MOD LI Inspected By/Date: | |||
Other ( _]) - Inspected By/Date: | |||
OCONEE Inspection Waived MCE (Mechanical & Civil) n] 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) LI Inspected By/Date: | |||
RES (Electrical Only) LI Inspected By/Date: | |||
RES (Reactor) LI Inspected By/Date: | |||
MOD El Inspected By/Date: | |||
Other ( ) [L Inspected By/Date: | |||
ONEI-0400-51 Rev 26 Page 3 of 33 Oconee 2 Cycle 23 Core Operating Limits Report Insertion Sheet for Revision 26 This revision is not valid until the end of operation for Oconee 2 Cycle 22. | |||
Remove these Revision 25 pages Insert these Revision 26 pages 1 - 33 1 - 33 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages 1Oconee 2 Cycle 23 revisions below I 26 Mar 2007 1-33 33 Oconee 2 Cycle 22 revisions below I 25 Oct 2005 1-33 33 Oconee 2 Cycle 21 revisions below 24 Aug 2005 1-4,6 - 33 23 Mar2005 1-5 - 33 22 Dec 2004 1-3,30 - 33 21 Apr2004 1-33 - 33 Oconee 2 Cycle 20 revisions below 20 Feb 2004 1-3,5 - 33 19 Nov 2003 1-4,8-10,12-13,29 la - 33 18 Oct 2002 1-3,14,16,24,30 - - 32 17 Oct 2002 1-31 32 - 32 lOconee 2 Cycle 19 revisions below - | |||
16 May 2001 1-31 - - 31 | |||
ONEI-0400-51 Rev 26 Page 4 of 33 Oconee 2 Cycle 23 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C23 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 02C23 by references 15 through 17. The 02C23 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. | |||
The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 02C23 reload core. | |||
1.1 References | |||
: 1. Nuclear Design Methodology Using CASMO-3 I SIMULATE-3P, DPC-NE-1 004-A, Revision 0, SER dated November 23, 1992. | |||
: 2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002-A, Revision 2, SER dated October 1, 1985. | |||
: 3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001 A, Revision 5, SER dated December 8, 2000. | |||
: 4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003-PA, Revision 1, SER dated June 23, 2000. | |||
: 5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, Revision 3, SER dated September 1, 2002. | |||
: 6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008-PA, Revision 0, SER dated April 3,1995. | |||
: 7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 2, SER dated September 24, 2003. | |||
: 8. Thermal Hydraulic Transient Analysis Methodology, DPC-NE-3000-PA, Rev. 3, SER dated September 24, 2003. | |||
: 9. BAW-1 0192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, Rev. 0, SER dated February 18, 1997. | |||
: 10. BAW-1 01 64P-A, Rev. 4, RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis, SER dated April 9, 2002. | |||
: 11. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, Rev. 1, June 2003 (SER to BAW-1 01 86P-A dated June 18, 2003). | |||
: 12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit, OSC-4048, Revision 4, January 2001. | |||
: 13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001. | |||
: 14. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002. | |||
: 15. 02C23 Maneuvering Analysis, OSC-8974, Revision 1, March 2007. | |||
: 16. 02C23 Specific DNB Analysis, OSC-9001, Revision 0, October.2006. | |||
: 17. 02C23 Reload Safety Evaluation, OSC-9057, Revision 0, March 2007. | : 17. 02C23 Reload Safety Evaluation, OSC-9057, Revision 0, March 2007. | ||
ONEI-0400-51 Rev 26 Page 5 of 33 Oconee 2 Cycle 23 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm. | |||
Referred to by TS 3.5.4. | |||
Spent fuel pool boron concentration shall be greater than 2220 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 1874 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. | |||
Referred to by TS 3.9.1. | |||
Shutdown Margin (SDM) shall be greater |
Revision as of 08:34, 23 November 2019
ML071000160 | |
Person / Time | |
---|---|
Site: | Oconee ![]() |
Issue date: | 04/02/2007 |
From: | Brandi Hamilton Duke Energy Carolinas, Duke Power Co |
To: | Document Control Desk, NRC/NRR/ADRO |
References | |
Download: ML071000160 (37) | |
Text
BRUCE H HAMILTON IDuke Vice President Energy Oconee Nuclear Station Duke Energy Corporation ONO0 VP / 7800 Rochester Highway Seneca, SC 29672 864 885 3487 864 885 4208 fax April 2, 2007 bhhamilton@duke-energy.com U. S. Nuclear Regulatory Commission Document Control Desk Washington, D. C. 20555
Subject:
Duke Power Company LLC d/b/a Duke Energy Carolinas, LLC Oconee Nuclear Site Docket No. 50-2/s 3 'q-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 23, Rev. 26.
Very truly yours, Bruce H. Hamilton Site, Vice President Oconee Nuclear Site Attachment 4DC)(
www. duke-energy. corn
NRC Document Control Desk April 2, 2007 Page 2 xc w/att: Mr. W. D. Travers, Regional Administrator U. S. Nuclear Regulatory Commission, Region II Mr. L. N. Olshan, Project Manager Office of Nuclear Reactor Regulation Mr. Dan Rich Senior Resident Inspector Oconee Nuclear Site
NRC Document Control Desk April 2, 2007 Page 3 bxc wo/att: NSRB - EC05P bxc w/att: ELL ONS Document Management
DISPOSITION OF THE ORIGINAL DOCUMENT WILL BE TO SuperRush THE TRANSMITTAL SIGNATURE UNLESS RECIPIENT IS Date: 03/27/07 OTHERWISE IDENTIFIED BELOW
- 1) 00620 DOC MGMT MICROFILM EC04T Document Transmittal #: DUK070860020
- 3) 06358 ONS REGUL COMPLIANCE -ON03RC
- 4) 06700 ONS MANUAL MASTER FILE ON03DM DOCUMENT TRANSMITTAL FORM OTHER ACKNOWLEDGEMENT REQUIRED FD Yes IF QA OR OTHER ACKNOWLEDGEMENT REQUIRED, PLEASE
- 5) 06937 R R ST CLAIR ECO8G ACKNOWLEDGE RECEIPT BY RETURNING THIS FORM TO:
REFERENCE NUCLEAR GENERAL OFFICE Duke Energy OCONEE NUCLEAR STATION P.O. Box 1006 WORK ITEM: EXEMPTION M-5 Energy Center EC04T ve 0% 0- RESP GROUP: NE RECORD RETENTION: 003587 Charlotte, N.C. 28201-1006 OCONEE 2 CYCLE 23 CORE OPERATING LIMITS REPORT Rec'd By %I-)
Page 1 of 1 Date mQlnuo I I DOCUMENT NO QACOND REV #/ DATE DISTR CODE 1 2 1'3' t 4 5 6 7 8 9 10 11 12 113 14 15 TOTAL ONEI-0400-051 1 026 03/27/07 1NOMD-27 V1 X Vik V1 4 REMARKS: DUKE DOCUMENT RELEASE EXEMPT FROM NUCLEAR MODIFICATION PROGRAM THOMAS C GEER NUCLEAR STATION ENGR MANAGER GS-SVP NUCLEAR SUPPORT BY:
J W SIMMONS JWS/JAK EC08H
ONEI-0400-51 Rev 26 Page 1 of 33 Duke Energy Oconee 2 Cycle 23 Core Operating Limits Report QA Condition 1 Prepared By: D.S. Orr d",etzl Date 3 -O7 Checked By: G.M. Presnell P1Y,~t~42 Date: P?/,2 4 20 0*da7 CDR By: A.W. Strange Date: 0 Approved By: R.R. St.Clair Date": 1 -- N6 - .,,.oo7
Document No. / Rev. ONEI-0400-51 Rev. 26 Date March 22, 2007 Page No. Page 2 of 33 INSPECTION OF ENGINEERING INSTRUCTIONS Inspection Waived By: Date: .3h G(D/*O*2.
(Sponsor)
CATAWBA Inspection Waived*
MCE (Mechanical & Civil) E] Inspected By/Date:
RES (Electrical Only) L Inspected By/Date:
RES (Reactor) LI Inspected By/Date:
Other ( _]) - Inspected By/Date:
OCONEE Inspection Waived MCE (Mechanical & Civil) n] 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) LI Inspected By/Date:
RES (Electrical Only) LI Inspected By/Date:
RES (Reactor) LI Inspected By/Date:
MOD El Inspected By/Date:
Other ( ) [L Inspected By/Date:
ONEI-0400-51 Rev 26 Page 3 of 33 Oconee 2 Cycle 23 Core Operating Limits Report Insertion Sheet for Revision 26 This revision is not valid until the end of operation for Oconee 2 Cycle 22.
Remove these Revision 25 pages Insert these Revision 26 pages 1 - 33 1 - 33 Revision Log Effective Pages Pages Pages Total Effective Revision Date Revised Added Deleted Pages 1Oconee 2 Cycle 23 revisions below I 26 Mar 2007 1-33 33 Oconee 2 Cycle 22 revisions below I 25 Oct 2005 1-33 33 Oconee 2 Cycle 21 revisions below 24 Aug 2005 1-4,6 - 33 23 Mar2005 1-5 - 33 22 Dec 2004 1-3,30 - 33 21 Apr2004 1-33 - 33 Oconee 2 Cycle 20 revisions below 20 Feb 2004 1-3,5 - 33 19 Nov 2003 1-4,8-10,12-13,29 la - 33 18 Oct 2002 1-3,14,16,24,30 - - 32 17 Oct 2002 1-31 32 - 32 lOconee 2 Cycle 19 revisions below -
16 May 2001 1-31 - - 31
ONEI-0400-51 Rev 26 Page 4 of 33 Oconee 2 Cycle 23 1.0 Error Adjusted Core Operating Limits The Core Operating Limits Report for 02C23 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 02C23 by references 15 through 17. The 02C23 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.
The error adjusted core operating limits included in section 1 of the report incorporate all necessary uncertainties and margins required for operation of the 02C23 reload core.
1.1 References
- 1. Nuclear Design Methodology Using CASMO-3 I SIMULATE-3P, DPC-NE-1 004-A, Revision 0, SER dated November 23, 1992.
- 2. Oconee Nuclear Station Reload Design Methodology II, DPC-NE-1 002-A, Revision 2, SER dated October 1, 1985.
- 3. Oconee Nuclear Station Reload Design Methodology, NFS-1 001 A, Revision 5, SER dated December 8, 2000.
- 4. ONS Core Thermal Hydraulic Methodology Using VIPRE-01, DPC-NE-2003-PA, Revision 1, SER dated June 23, 2000.
- 5. Thermal Hydraulic Statistical Core Design Methodology, DPC-NE-2005-PA, Revision 3, SER dated September 1, 2002.
- 6. Fuel Mechanical Reload Analysis Methodology Using TACO3, DPC-NE-2008-PA, Revision 0, SER dated April 3,1995.
- 7. UFSAR Chapter 15 Transient Analysis Methodology, DPC-NE-3005-PA, Revision 2, SER dated September 24, 2003.
- 8. Thermal Hydraulic Transient Analysis Methodology, DPC-NE-3000-PA, Rev. 3, SER dated September 24, 2003.
- 9. BAW-1 0192-PA, BWNT LOCA - BWNT Loss of Coolant Accident Evaluation Model for Once-Through Steam Generator Plants, Rev. 0, SER dated February 18, 1997.
- 10. BAW-1 01 64P-A, Rev. 4, RELAP5/MOD2-B&W - An Advanced Computer Program for Light Water Reactor LOCA and Non-LOCA Transient Analysis, SER dated April 9, 2002.
- 11. BAW-1 0227-PA, Evaluation of Advanced Cladding and Structural Material (M5) in PWR Reactor Fuel, Rev. 1, June 2003 (SER to BAW-1 01 86P-A dated June 18, 2003).
- 12. RPS RCS Pressure & Temperature Trip Function Uncertainty Analyses and Variable Low Pressure Safety Limit, OSC-4048, Revision 4, January 2001.
- 13. Power Imbalance Safety Limits and Tech Spec Setpoints Using Error Adjusted Flux-Flow Ratio of 1.094, OSC-5604, Revision 2, October 2001.
- 14. ATc and EOC Reduced Tavg Operation, OSC-7265, Rev. 1, Duke Power Co., June 2002.
- 15. 02C23 Maneuvering Analysis, OSC-8974, Revision 1, March 2007.
- 16. 02C23 Specific DNB Analysis, OSC-9001, Revision 0, October.2006.
- 17. 02C23 Reload Safety Evaluation, OSC-9057, Revision 0, March 2007.
ONEI-0400-51 Rev 26 Page 5 of 33 Oconee 2 Cycle 23 Miscellaneous Setpoints BWST boron concentration shall be greater than 2220 ppm and less than 3000 ppm.
Referred to by TS 3.5.4.
Spent fuel pool boron concentration shall be greater than 2220 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 1874 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.
Referred to by TS 3.9.1.
Shutdown Margin (SDM) shall be greater than 1% Ak/k.
Referred to by TS 3.1.1.
Moderator Temperature Coefficient (MTC) shall be less than: MTC x 10-4 Linear interpolation is valid within the table provided. Ap/ °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. ATc,°F 4RCPOp 3RCPOp 0 581.0 581.0 The measured Tavg must be less than COLR limits minus 1 581.4 581.2 instrument uncertainty. ATc is the setpoint value selected by 2 581.8 581.4 the operators. Values are expanded by linear interpolation on 3 582.1 581.7 page 33 of this document without instrument uncertainty. 4 582.5 581.9 5 582.9 582.1
- This limit is applied to the loop with the lowest loop average temperature consistent with the NOTE in SR 3.4.1.2. All other temperature limits apply to the maximum loop Tavg.
DNB parameter for RCS loop total flow shall be: 4 RCP: Measured > 107.5 %df Referred to by TS 3.4.1. 3 RCP: Measured > 74.7 % of 4 RCP min flow Regulating rod groups shall be withdrawn in sequence starting with group 5, group 6, and finally group 7.
Referred to by TS 3.2.1.
Regulating rod group overlap shall be 25% +/-5% between two sequential groups.
Referred to by TS 3.2.1.
Misaligned, dropped, or inoperable rods may be excluded from control rod group average calculations when determining if overlap requirements are met as these situations are explicitly addressed by TS 3.1.4 (Control Rod Group Alignment Limits), TS 3.1.5 (Safety Rod Position Limits), and TS 3.2.3 (Quadrant Power Tilt).
ONEI-0400-51 Rev 26 Page 6 of 33 Oconee 2 Cycle 23 Steady State Operating Band Rod Index APSR %WD EFPD Min Max Min Max 0 to EOC 292 +/- 5 300 30 40 Quadrant Power Tilt Setpoints Steady State Transient Maximum Core Power Level, %FP 30-100 0-30 30-100 0-30 0 - 100 Full Incore 3.50 7.61 7.11 9.40 16.55 Out of Core 2.35 6.09 5.63 7.72 14.22 Backup Incore 2.25 3.87 3.63 4.81 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).
ONEI-0400-51 Rev 26 Page 7 of 33 Oconee 2 Cycle 23 Variable Low RCS Pressure RPS Setpoints Referred to by TS 3.3.1 2400 P = 2355 psig T = 618 'F 2300 2200 0_)
53_
Acceptable c2100 10 OOperation 0~
P= 11.14*Tout -47 0
0 2000
/f Unacceptable 1900 /Operation P = 1800 psig 1800 T = 584 °F 1700 i I 540 560 580 600 620 640 Reactor Coolant Outlet Temperature, OF
ONEI-0400-51 Rev 26 Page 8 of 33 Oconee 2 Cycle 23 RPS Power Imbalance Setpoints
% FP % Imbalance 4 Pumps 0.0 -33.0 88.4 -33.0 107.9 -12.3 107.9 14.4 90.4 33.0 0.0 33.0 3 Pumps 0.0 -33.0 61.1 -33.0 80.6 -12.3 80.6 14.4 63.1 33.0 0.0 33.0 Maximum Allowable RPS Power Imbalance Limits
% FP % Imbalance 4 Pumps 0.0 -35.0 88.0 -35.0 109.4 -12.3 109.4 14.4 90.0 35.0 0.0 35.0 3 Pumps 0.0 -35.0 60.3 -35.0 81.7 -12.3 81.7 14.4 62.3 35.0 0.0 35.0
ONEI-0400-51 Rev 26 Page 9 of 33 Oconee 2 Cycle 23 Operational Power Imbalance Setpoints Full Backup Out of
%FP Incore Incore Core 4 Pumps 0.0 -28.0 -28.0 -28.0 80.0 -28.0 -28.0 -28.0 90.0 -26.3 -26.3 -26.3 100.0 -15.7 -15.7 -15.7 102.0 -13.6 -13.6 -13.6 102.0 15.7 15.7 15.7 100.0 17.8 17.8 17.8 90.0 28.0 27.6 28.0 80.0 28.0 27.6 28.0 0.0 28.0 27.6 28.0 3 Pumps 0.0 -28.0 -28.0 -28.0 61.1 -28.0 - -28.0 61.1 - -28.0 77.0 -11.1 -11.1 -11.1 77.0 13.2 13.2 13.2 63.5 - 27.6 -
63.1 28.0 - 28.0 0.0 28.0 27.6 28.0
ONEI-0400-51 Rev 26 Page 10 of 33 Oconee 2 Cycle 23 Operational Power Imbalance Setpoints Operation with 4 RCS Pumps, BOC to EOC
% FP I RPS Trip Full Incore Alarm Out of Core Alarm 107.9 -12.3 14.4 107.0 -13.3 15.4 106.0 -14.3 16.4 105.0 -15.4 17.5 104.0 -16.4 18.5 103.0 -17.5 19.6 102.0 -18.6 20.7 -13.6 15.7 -13.6 15.7, 101.0 -19.6 21.7 -14.6 16.7 -14.6 16.7 100.0 -20.7 22.8 -15.7 17.8 -15.7 17.8 99.0 -21.8 23.9 -16.8 18.8 -16.8 18.8 98.0 -22.8 24.9 -17.8 19.8 -17.8 19.8 97.0 -23.9 26.0 -18.9 20.9 -18.9 20.9 96.0 -24.9 27.0 -19.9 21.9 -19.9 21.9 95.0 -26.0 28.1 -21.0 22.9 -21.0 22.9 94.0 -27.1 29.2 -22.1 23.9 -22.1 23.9 93.0 -28.1 30.2 -23.1 24.9 -23.1 24.9 92.0 -29.2 31.3 -24.2 26.0 -24.2 26.0 91.0 -30.2 32.3 -25.2 27.0 -25.2 27.0 90.4 -30.9 33.0 -25.9 27.6 -25.9 27.6 90.0 -31.3 33.0 -26.3 28.0 -26.3 28.0 89.0 -32.4 33.0 -26.5 28.0 -26.5 28.0 88.4 -33.0 33.0 -26.6 28.0 -26.6 28.0 88.0 -33.0 33.0 -26.6 28.0 -26.6 28.0 87.0 -33.0 33.0 -26.8 28.0 -26.8 28.0 86.0 -33.0 33.0 -27.0 28.0 -27.0 28.0 85.0 -33.0 33.0 -27.2 28.0 -27.2 28.0 84.0 -33.0 33.0 -27.3 28.0 -27.3 28.0 83.0 -33.0 33.0 -27.5 28.0 -27.5 28.0 82.0 -33.0 33.0 -27.7 28.0 -27:7 28.0 81.0 -33.0 33.0 -27.8 28.0 -27.8 28.0 80.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 0.0 -33.0 33.0 -28.0 28.0 -28.0 28.0
% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-51 Rev 26 Page 11 of 33 Oconee 2 Cycle 23 Operational Power Imbalance Setpoints Operation with 3 RCS Pumps, BOC to EOC
% FP RPS Trip Full Incore Alarm Out of Core Alarm 80.6 -12.3 14.4 80.0 -12.9 15.0 79.0 -14.0 16.1 78.0 -15.0 17.1 77.0 -16.1 18.2 -11.1 13.2 -11.1 13.2 76.0 -17.2 19.3 -12.2 14.3 -12.2 14.3 75.0 -18.2 20.3 -13.2 15.3 -13.2 15.3 74.0 -19.3 21.4 -14.3 16.4 -14.3 16.4 73.0 -20.3 22.4 -15.3 17.4 -15.3 17.4 72.0 -21.4 23.5 -16.4 18.5 -16.4 18.5 71.0 -22.5 24.6 -17.5 19.6 -17.5 19.6 70.0 -23.5 25.6 -18.5 20.6 -18.5 20.6 69.0 -24.6 26.7 -19.6 21.7 -19.6 21.7 68.0 -25.7 27.8 -20.7 22.8 -20.7 22.8 67.0 -26.7 28.8 -21.7 23.8 -21.7 23.8 66.0 -27.8 29.9 -22.8 24.9 -22.8 24.9 65.0 -28.8 30.9 -23.8 25.9 -23.8 25.9 64.0 -29.9 32.0 -24.9 27.0 -24.9 27.0 63.1 -30.9 33.0 -25.9 28.0 -25.9 28.0 63.0 -31.0 33.0 -26.0 28.0 -26.0 28.0 62.0 -32.0 33.0 -27.0 28.0 -27.0 28.0 61.1 -33.0 33.0 -28.0 28.0 -28.0 28.0 61.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 60.0 -33.0 33.0 -28.0 28.0 -28.0 28.0 0.0 -33.0 33.0 -28.0 28.0 -28.0 28.0
% FP RPS Trip Full Incore Alarm Out of Core Alarm ONEI-0400-51 Rev 26 Page 12 of 33 Oconee 2 Cycle 23 RPS Power Imbalance Setpoints Referred to by TS 3.3.1 Thermal Power Level, %FP 120.0
(-12.3,1( (14.4,107.9)
K 4-100.0-M2 = -0.942 M1 = 0.942 Operation
(-33.0,88.4) (33.0,90.4)
(-12.3,80.6 (14.4,80.6) 1
(-33.0,61.1) 60.0 (33.0,63.1)
Acceptable 3 or, I Pump Operation 40.0-20.0-I
- p I I
I
,;-40.0 -30.0 -20.0 -10.0 '0.0 10.0 20.0 30.0 40.0 Percent*Power Imbalance
0 ONEI-0400#v 26 Page 13 of 33 Oconee 2 Cycle 23 Imbalance Setpoints for 4 Pump Operation, BOC to EOC 110.0 RPS Trip Setpoint 100.0 Incore & Outcore Alarm RPS Trip Setpoint 90.0 80.0 70.0 0
- a. 60.0 U-
- 0) 50.0 40.0 30.0 20.0 t
I 10.0 0.0 F a 35 -30 -25 -20 -15 -10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance
0 ONEl-O4O0-51 ev 26 Oconee 2 Cycle 23 Page 14 of 33 Imbalance Setpoints for 3 Pump Operation, BOC to EOC 110 100 I
90 RPS Trip Setpoint RPS Trip Setpoint'-
80 Incore & Outcore Alarm 70 (D
0~ 60 LL 50 I0 40 30 20 10 0-35 -30 -25 -20 U
-15 5j U Li I
-10 -5 0 5 10 15 20 25 30 35 40 Percent Axial Imbalance
ONEI-0400-51 Rev 26 Page 15 of 33 Oconee 2 Cycle 23 Operational Rod Index Setpoints RI Insertion Setpoint RI Withdrawal
%FP No Inop Rod 1 Inop 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 80.0 251.5 262.3 300 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 77.0 246.5 285.2 300 75.0 243.2 281.5 300 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
ONEI-0400-51 Rev 26 Page 16 of 33 Oconee 2 Cycle 23 Shutdown Margin Rod Index Setpoints RI Insertion Setpoint RI Withdrawal
%FP No nop Rod 1 Inop 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
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 17 of 33 4 Pump Operation, No Inoperable Rods, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP6 CRGP7 102 100 99.8 24.8 100 100 63.5 101 100 99.0 24.0 100 100 62.5 100 100 98.2 23.2 100 100 61.5 99 100 97.5 22.5 100 100 60.5 98 100 96.7 21.7. 100 100 59.5 97 100 95.9 20.9 100 100 58.5 96 100 95.2 20.2 100 100 57.5 95 100 94.4 19.4 100 100 56.5 94 100 93.6 18.6 100 100 55.5 93 100 92.9 17.9 100 100 54.5 92 100 92.1 17.1 100 100 53.5 91 100 91.3 16.3 100 100 52.5 90 100 90.6 15.6 100 100 51.5 89 100 89.8 14.8 100 100 51.5 88 100 89.0 14.0 100 100 51.5 87 100 88.2 13.2 100 100 51.5 86 100 87.5 12.5 100 100 51.5 85 100 86.7 11.7 100 100 51.5 84 100 85.9 10.9 100 100 51.5 83 100 85.2 10.2 100 100 51.5 82 100 84.4 9.4 100 100 51.5 81 100 83.6 8.6 100 100 51.5 80 100 82.9 7.9 100 100 51.5 79 100 82.1 7.1 100 100 49.8 78 100 81.3 6.3 100 100 48.2 77 100 80.6 5.6 100 100 46.5 76 100 79.8 4.8 100 100 44.8 75 100 79.0 4.0 100 100 43.2 74 100 78.2 3.2 100 100 41.5 73 100 77.5 2.5 100 100 39.8 72 100 76.7 1.7 100 100 38.2 71 100 75.9 0.9 100 100 36.5 70 100 75.2 0.2 100 100 34.8 69.8 100 75.0 0. 100 100 34.5 69 100 73.8 0 100 100 33.2 68 100 72.3 0 100 100 31.5 67 100 70.7 0 100 100 29.8 66 100 69.2 0 100 100 28.2 65 100 67.7 0 100 100 26.5 64.1 100 66.3 0 100 100 25.0 63 100 64.6 0 100 99 24.1 62 100 63.0 0 100 98 23.2 61 100 61.5 0 100 97 22.4 60 100 60.0 0 100 96.6 21.6 59 100 58.4 0 100 95.8 20.8 58 100 56.9 0 100 94.9 19.9 57 100 55.3 0 100 94.1 19.1 56 100 53.8 0 100 93.2 18.2 55 100 52.3 0 100 92.4 17.4 54 100 50.7 0 100 91.6 16.6 53 100 49.2 0 100 90.8 15.8 52 100 47.7 0 100 89.9 14.9 51 100 46.1 0 100 89.1 14.1 50 100 1 44.6 0 100 88.2 13.2
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels. Continued on next page.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 18 of 33 4 Pump Operation, No Inoperable Rods, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 49 100 43.0 0 100 86.7 11.7 48 100 41.5 0 100 85.1 10.1 47 100 39.6 0 100 83.5 8.5 46 100 37.8 0 100 82.0 '7.0 45 100 35.9 0 100 80.4 5.4 44 100 34.1 0 100 78.8 3.8 43 100 32.2 0 100 77.2 .2.2 42 100 30.4 0 100 75.7 0.7 41.6 100 29.6 0 100 75.0 0 41 100 28.5 0 100 73.2 0 40 100 26.6 0 100 70.1 0 39.1 100 25.0 0 100 67.3 0 39 99.9 24.9 0 100 66.9 0 38 99.0 24.0 0 100 63.8 0 37 98.0 23.0 0 100 60.6 0 36 97.1 22.1 0 100 57.5 0 35 96.2 21.2 0 100 54.3 0 34 95.2 20.2 0 100 51.2 0 33 94.3 19.3 0 100 48.1 0 32 93.4 18.4 0 100 44.9 0 31 92.5 17.5 0 100 41.8 0 30 91.5 16.5 0 100 38.6 0 29 90.6 15.6 0 100 35.5 0 28 89.7 14.7 0 100 32.4 0 27 88.8 13.8 0 100 29.2 0 26 87.8 12.8 0 100 26.1 0 25.7 87.5 12.5 0 100 25.0 0 25 86.9 11.9 0 99.0 24.0 0 24 86.0 11.0 0 97.4 22.4 0 23 85.0 10.0 0 95.8 20.8 0 22 84.1 9.1 0 94.2 19.2 0 21 83.2 8.2 0 92.7 17.7 0 20 82.2 7.2 0 91.1 16.1 0 19 81.3 6.3 0 89.5 14.5 0 18 80.4 5.4 0 88.0 13.0 0 17 79.5 4.5 0 86.4 11.4 0 16 78.5 3.5 0 84.8 9.8 0 15 77.6 2.6 0 83.2 8.2 0 14 76.7 1.7 0 79.5 4.5 0 13 75.8 0.8 0 75.8 0.8 0 12.8 75.0 0 0 75.0 0 0 12 69.0 0 0 69.0 0 0 11 61.5 0 0 61.5 0 0 10 54.0 0 0 54.0 0 0 9 46.5 0 0 46.5 0 0 8 39.0 0 0 39.0 0 0 7 31.5 0 0 31.5 0 0 6 24.0 0 0 24.0 0 0 5 16.5 0 0 16.5 0 0 4 9.0 0 0 9.0 0 0 3 1.5 0 0 1.5 0 0 2.8 0 0 0 0 0 0 2 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 19 of 33 3 Pump Operation, No Inoperable Rods, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 77 100 100 27.4 100 100 46.5 76.2 100 100 25.0 100 100 45.2 76 100 99.7 24.7 100 100 44.9 75 100 98.2 23.2 100 100 43.2 74 100 96.8 21.8 100 100 41.5 73 100 95.3 20.3 100 100 39.9 72 100 93.8 18.8 100 100 38.2 71 100 92.3 17.3 100 100 36.5 70 100 90.8 15.8 100 100 34.9 69 100 89.4 14.4 100 100 33.2 68 100 87.9 12.9 100 100 31.5 67 100 86.4 11.4 100 100 29.9 66 100 84.9 9.9 100 100 28.2 65 100 83.4 8.4 100 100 26.5 64.1 100 82.1 7.1 100 100 25.0 63 100 80.5 5.5 100 99 24.1 62 100 79.0 4.0 100 98 23.3 61 100 77.5 2.5 100 97 22.4 60 100 76.0 1.0 100 96.6 21.6 59.3 100 75.0 0.0 100 96.0 21.0 59 100 74.1 0 100 95.8 20.8 58 100 71.1 0 100 94.9 19.9 57 100 68.2 0 100 94.1 19.1 56 100 65.2 0 100 93.3 18.3 55 100 62.2 0 100 92.4 17.4 54 100 59.3 0 100 91.6 16.6 53 100 56.3 0 100 90.8 15.8 52 100 53.4 0 100 89.9 14.9 51 100 50.4 0 100 89.1 14.1 50 100 47.4 0 100 88.2 13.2 49 100 44.5 0 100 86.7 11.7 48 100 41.5 0 100 85.1 10.1 47 100 39.6 0 100 83.5 8.5 46 100 37.8 0 100 82.0 7.0 45 100 35.9 0 100 80.4 5.4 44 100 34.1 0 100 78.8 3.8 43 100 32.2 0 100 77.2 2.2 42 100 30.4 0 100 75.7 0.7 41.6 100 29.6 0 100 75.0 0.0 41 100 28.5 0 100 73.2 0 40 100 26.6 0 100 70.1 0 39.1 100 25.0 0 100 67.3 0 39 99.9 24.9 0 100 66.9 0 38 99 24.0 0 100 63.8 0 37 98 23.0 0 100 60.6 0 36 97.1 22.1 0 100 57.5 0 35 96.2 21.2 0 100 54.3 0 34 95.2 20.2 0 100 51.2 0 33 94.3 19.3 0 100 48.1 0 32 93.4 18.4 0 100 44.9 0 31 92.5 17.5 0 100 41.8 0 30 91.5 16.5 0 100 38.6 0 29 90.6 15.6 0 100 35.5 0 28 89.7 14.7 0 100 32.4 0
% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels. Continued on next page.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 20 of 33 3 Pump Operation, No Inoperable Rods, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP 5 CRGP 6 CRGP 7 ,CRGP 5 CRGP 6 CRGP 7 27 88.8 13.8 0 100 29.2 0 26 87.8 12.8 0 100 26.1 0 25.7 87.5 12.5 0 100 25.0 0 25 86.9 11.9 0 99.0 24.0 0 24 86.0 11.0 0 97.4 22.4 0 23 85.0 10.0 0 95.8 20.8 0 22 84.1 9.1 0 94.2 19.2 0 21 83.2 8.2 0 92.7 17.7 0 20 82.2 7.2 0 91.1 16.1 0 19 81.3 6.3 0 89.5 14.5 0 18 80.4 5.4 0 88.0 13.0 0 17 79.5 4.5 0 86.4 11.4 0 16 78.5 3.5 0 84.8 9.8 0 15 77.6 2.6 0 83.2 8.2 0 14 76.7 1.7 0 79.5 4.5 0 13 75.8 0.8 0 75.8 0.8 0 12.8 75.0 0 0 75.0 0 0 12 69.0 0 0 69.0 0 0 11 61.5 0 0 61.5 0 0 10 54.0 0 0 54.0 0 0 9 46.5 0 0 46.5 0 0 8 39.0 0 0 39.0 0 0 7 31.5 0 0 31.5 0 0 6 24.0 0 0 24.0 0 0 5 16.5 0 0 16.5 0 0 4 9.0 0 0 9.0 0 0 3 1.5 0 0 1.5 0 0 2.8 0 0 0 0 0 0 2 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0
% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP 7 1_ Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 21 of 33 4 Pump Operation, 1 Inoperable Rod, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 102 100 100 83.4 100 100 83.4 101 100 100 82.5 100 100 82.5 100 100 100 81.5 100 100 81.5 99 100 100 80.5 100 100 80.5 98 100 100 79.6 100 100 79.6 97 100 100 78.6 100 100 78.6 96 100 100 77.7 100 100 77.7 95 100 100 76.7 100 100 76.7 94 100 100 75.7 100 100 75.7 93 100 100 74.8 100 100 74.8 92 100 100 73.8 100 100 73.8 91 100 100 72.8 100 100 72.9 90 100 100 71.9 100 100 71.9 89 100 100 70.9 100 100 70.9 88 100 100 70.0 100 100 70.0 87 100 100 69.0 100 100 69.0 86 100 100 68.0 100 100 68.1 85 100 100 67.1 100 100 67.1 84 100 100 66.1 100 100 66.1 83 100 100 65.2 100 100 65.2 82 100 100 64.2 100 100 64.2 81 100 100 63.2 100 100 63.3 80 100 100 62.3 100 100 62.3 79 100 100 61.3 100 100 61.3
,78 100 100 60.3 100 1 100 60.4 77 100 100 59.4 100 100 59.4 76 100 100 58.4 100 100 58.4 75 100 100 57.5 100 100 57.5 74 100 100 56.5 100 100 56.5 73 100 100 55.5 100 100 55.6 72 100 100 54.6 100 100 54.6
- 71. 100 100 53.6 100 100 53.6 70 100 100 52.7 100 ,100 52.7 69 100 100 51.7 100 100 51.7 68 100 100 50.7 100 100 50.7 67 100 100 49.8 100 100 49.8 66 100 100 48.8 100 100 48.8 65 100 100 47.8 100 100 47.8 64 100 100 46.9 100 100 46.9 63 100 100 45.9 100 100 45.9 62 100 100 45.0 100 100 45.0 61 100 100 44.0 100 100 44.0 60 100 100 43.0 100 100 43.0 59 100 100 42.1 100 100 42.1 58 100 100 41.1 100 100 41.1 57 100 100 40.2 100 100 40.2 56 100 100 39.2 100 100 39.2 55 100 100 38.2 100 100 38.2 54 100 100 37.3 100 100 37.3 53 100 100 36.3 100 100 36.3 52 100 100 35.3 100 100 35.3 51 100 100 34.4 100 100 34.4 50 100 100 33.4 100 100 33.4 49 100 100 32.5 100 100 32.5 48 100 100 31.5 100 100 31.5
%FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7
_ _Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels. Continued on next page.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 22 of 33 4 Pump Operation, 1 Inoperable Rod, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 47 100 100 29.5 100 100 29.5 46 100 100 27.5 100 100 27.5 45 100 100 25.5 100 100 25.5 44.8 100 100 25.0 100 100 25.0
- 44. 100 99.2 24.2 100 99.2 24.2 43 100 98.2 23.2 100 98.2 23.2 42 100 97.2 22.2 100 97.2 22.2 41 100 96.2 21.2 100 96.2 21.2 40 100 95.2 20.2 100 95.2 20.2 39 100 94.2 19.2 100 94.2 19.2 38 100 93.2 18.2 100 93.2 18.2 37 100 92.2 17.2 100 92.2 17.2 36 100 91.2 '16.2 100 91.2 16.2 35 100 90.2 15.2 100 90.2 15.2 34 100 89.2 14.2 100 89.2 14.2 33 100 88.2 13.2 100 88.2 13.2 32 100 87.2 12.2 100 87.2 12.2 31 100 86.2 11.2 100 86.2 11.2 30 100 85.2 10.2 100 85.2 10.2 29 100 84.2 9.2 100 84.2 9.2 28 100 83.2 8.2 100 83.2 8.2 27 100 82.2 7.2 100 82.2 7.2 26 100 81.2 6.2 100 81.2 6.2 25 100 80.2 .5.2 100 80.2 5.2 24 100 79.2 4.2 100 79.2 4.2 23 100 78.2 3.2 100 78.2 3.2 22 100 77.2 2.2 100 77.2 2.2 21 100 76.2 1.2 100 76.2 1.2 20 100 75.2 0.2 100 - 75.2 0.2 19.8 100 75.0 0 100 75.0 0 19 100 73.5 0 100 73.5 0 18 100 71.5 0 100 71.5 0 17 100 69.5 0 100 69.5 0 16 100 67.5 0 100 67.5 0 15 100 65.5 0 100 65.5 0 14 100 63.5 0 100 63.5 0 13 100 61.5 0 100 61.5 0 12 100 53.0 0 100 53.0 0 11 100 44.5 0 100 44.5 0 10 100 36.0 0 100 36.0 0 9 100 27.5 0 100 27.5 0 8.7 100 25.0 0 100 25.0 0 8 97.0 22.0 0 97.0 22.0 0 7 92.8 17.8 0 92.8 17.8 0 6 88.5 13.5 0 88.5 13.5 0 5 84.2 9.2 0 84.2 9.2 0 4 80.0 5.0 0 80.0 5.0 0 3 75.8 0.8 0 75.8 0.8 0 2.8 75 0 0 75 0 0 2 68 0 0 68 0 0 1 59.5 0 0 59.5 0 0 0 51 0 0 51 0 0
% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limitat all power levels.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 23 of 33 3 Pump Operation, 1 Inoperable Rod, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 77 100 100 85.2 100 100 85.2 76 100 100 83.4 100 100 83.4 75 100 100 81.5 100 100 81.5 74 100 100 79.6 100 100 79.6 73 100 100 77.8 100 100 77.8 72 100 100 75.9 100 100 75.9 71 100 100 74.1 100 100 74.1 70 100 100 72.2 100 100 72.2 69 100 100 70.4 100 100 70.4 68 100 100 68.5 100 100 68.5 67 100 100 66.7 100 100 66.7 66 100 100 64.8 100 100 64.8 65 100 100 63.0 100 100 63.0 64 100 100 61.1 100 100 61.1 63 100 100 59.3 100 100 59.3 62 100 100 57.4 100 100 57.4 61 100 100 55.6 100 100 55.6 60 100 100 53.7 100 100 53.7 59 100 100 51.9 100 100 51.9 58 100 100 50.0 100 100 50.0 57 100 100 48.2 100 100 48.2 56 100 100 46.3 100 100 46.3 55 100 100 44.5 100 100 44.5 54 100 100 42.6 100 100 42.6 53 100 100 40.8 100 100 40.8 52 100 100 38.9 100 100 38.9 51 100 100 37.1 100 100 37.1 50 100 100 35.2 100 100 35.2 49 100 100 33.4 100 100 33.4 48 100 100 31.5 100 100 31.5 47 100 100 29.5 100 100 29.5 46 100 100 27.5 100 100 27.5 45 100 100 25.5 100 100 25.5 44.8 100 100 25.0 100 100 25.0 44 100 99.2 24.2 100 99.2 24.2 43 100 98.2 23.2 100 98.2 23.2 42 100 97.2 22.2 100 97.2 22.2 41 100 96.2 21.2 100 96.2 21.2 40 100 95.2 20.2 100 95.2 20.2 39 100 94.2 19.2 100 94.2 19.2 38 100 93.2 18.2 100 93.2 18.2 37 100 92.2 17.2 100 92.2 17.2 36 100 91.2 16.2 100 91.2 16.2 35 100 90.2 15.2 100 90.2 15.2 34 100 89.2 14.2 100 89.2 14.2 33 100 88.2 13.2 100 88.2 13.2 32 100 87.2 12.2 100 87.2 12.2 31 100 86.2 11.2 100 86.2 11.2 30 100 85.2 10.2 100 85.2 10.2 29 100 84.2 9.2 100 84.2 9.2 28 1.00 83.2 8.2 100 83.2 8.2 27 100 82.2 7.2 100 82.2 7.2 26 100 81.2 6.2 100 81.2 6.2 25 100 80.2 5.2 100 80.2 5.2 24 100 79.2 4.2 100 79.2 4.2
%FP CRGP 5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7
_ Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels. Continued on next page.
Oconee 2 Cycle 23 ONEI-0400-51 Rev 26 Rod Index Setpoints Page 24 of 33 3 Pump Operation, 1 Inoperable Rod, BOC to EOC Shutdown Margin Setpoint Operational Alarm Setpoint
\
% FP CRGP 5 CRGP 6 CRGP 7 CRGP 5 CRGP 6 CRGP 7 23 100 78.2 3.2 100 78,2 3.2 22 100 77.2 2.2 100 77.2 2.2 21 100 76.2 1.2 100 76.2 1.2 20 100 75.2 0.2 100 75,2 0.2 19.8 100 75.0 0 100 75.0 0 19 100 73.5 0 100 73,5 0 18 100 71.5 0 100 71.5 0 17 100 69.5 0 100 69.5 0 16 100 67.5 0 100 67.5 0 15 100 65.5 0 100 65.5 0 14 100 63.5 0 100 63.5 0 13 100 61.5 0 100 61.5 0 12 100 53.0 0 100 53.0 0 11 100 44.5 0 100 44.5 0 10 100 36.0 0 100 36.0 0 9 100 27.5 0 100 27.5 0 8.7 100 25.0 0 100 25.0 0 8 97.0 22.0 0 97.0 22,0 0 7 92.8 17.8 0 92.8 17.8 0 6 88.5 13.5 0 88.5 13.5 0 5 84.2 9.2 0 84.2 9.2 0 4 80.0 5.0 0 80.0 5.0 0 3 75.8 0.8 0 75.8 0.8 0 2.8 75.0 0 0 75.0 0 0 2 68 0 0 68 0 0 1 59.5 0 0 59.5 0 0 0 51 0 0 51 0 0
% FP CRGP5 CRGP6 CRGP7 CRGP5 CRGP6 CRGP7 Shutdown Margin Setpoint Operational Alarm Setpoint RI = 300 is withdrawal limit at all power levels.
_
I il Oconee 2 Cycle 23 ill _
I 0 ONEI-0400-511026 Page 25 of 33 105 105 100 100 95 95 90 90 85 85 80 80 75 75 70 70 65 65 60 60 55 55 50 50 45 45 40 40 35 35 30 30 25 25 20 .20 15 15 10 10 5
75 ,85 95 01gl.Ii 0
0 10 20 30 40 50 60 70 80 90 1007 I Group 7
Control Rod Position, % WD
Oconee 2 Cycle 23 ONEI-0400-5026 2 Page 26 of 33 105 I I 105 100 Control Rod Position Setpoints T 100 H H H4~
95 No Inoperable Rods, 3 Pump Flow mil 95 a It 90 ,'if, 90 85 85 H+H iIj i
80 80 75 75 70 i +
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.Oconee 2 Cycle 23 ONEI-0400-50 26 Page 27 of 33 105 105 100 Control Rod Position Setpoints 100 95 1 Inoperable Rod, 4 Pump Flow 95 90 90 85 85 80 80 75 75 70 70 65 65 a..
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ONEI-0400-51 Rev 26 Page 29 of 33 Oconee 2 Cycle 23 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.
Quadrant Power Tilt Limits Referred to by TS 3.2.3 Steady State T ransient Maximum Core Power Level, %FP, 340-100 0-30 30-10(0 0-30 0- 100 Quadrant Power Ti it, % 5.40 10.00 9.44 12.00 20.00 Variable Low RCS Pressure Protective Limits Referred to by TS 2.1.1 Core Outl et Pressure Reactor Coolant Outlet Temperature, OF psia 3 RCS Pumps 4 RCS Pumps 800 581.0 578.3 11900 590.0 587.3 2(000 598.9 596.3 2 100 607.9 605.2 22200 616.9 614.2 300 625.9 623.2
ONEI-0400-51 Rev 26 Page 30 of 33 Oconee 2 Cycle 23 Axial Power Imbalance Protective Limits Referred to by TS 2.1.1
%FP RPS Operational 4 Pumps 0.0 -35.0 -39.5 80.0 -39.5 88.0 -35.0 90.0 -38.1 100.0 -25.8
-12.3 109.4 109.4 14.4 100.0 28.4 90.0 35.0 39.5 80.0 39.5 0.0 35.0 39.5 3 Pumps 0.0 -35.0 -39.5 60.3 -35.0 77.0 -39.5 81.7 -12.3 81.7 14.4 77.0 39.5 62.3 35.0 0.0 35.0 39.5
ONEI-0400-51 Rev 26 Page 31 of 33 Oconee 2 Cycle 23 Rod Index Limits Referred to by TS 3.2.1 Operational RI Shutdown Margin RI Insertion Limit RI Withdrawal
%FP Insertion Limit No Inop Rod 1 Inop Rod Limit 4 Pumps 102 262 220 280 300 100 260 300 90 250 300 80 250 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300 3 Pumps 77 245 220 280 300 50 200 140 230 300 15 90 75 160 300 5 0 0 75 300
ONEI-0400-51 Rev 26 Page 32 of 33 Oconee 2 Cycle 23 LOCA Limits Core Elevation Feet LOCA LHR kw/ft Limit Versus Burnup Mk-B1 1 Fuel 0 GWd/mtU 40 GWd/mtU 62 GWd/mtU 0.000 16.6 16.6 12.2 2.506 17.5 17.5 12.2 4.264 17.6 17.6 12.2 6.021 17.7 17.7 12.2 7.779 17.6 17.6 12.2 9.536 17.5 17.5 12.2 12.00 16.6 16.6 12.2
ONEI-0400-51 Rev 26 Page 33 of 33 Oconee 2 Cycle 23 4 RCP Operation - Loop Average Temp., *F 3 RCP Operation - Loop Average Temp., TF ATcold, 0F Tavg (Analytical) Tavg (Analytical) 0.0 <581.0 <581.0 0.1 <581.0 <581.0 0.2 <581.1 <581.0 0.3 <581.1 <581.1 0.4 <581.2 <581.1 0.5 <581.2 <581.1 0.6 <581.2 <581.1 0.7 <581.3 <581.2 0.8 <581.3 <581.2 0.9 <581.3 <581.2 1.0 <581.4 <581.2 1.1 <581.4 <581.2 1.2 <581.5 <581.3 1.3 <581.5 <581.3 1.4 <581.5 <581.3 1.5 <581.6 <581.3 1.6 <581.6 <581.4 1.7 <581.6 <581.4 1.8 <581.7 <581.4 1.9 <581.7 <581.4 2.0 <581.8 <581.4 2.1. <581.8 <581.5 2.2 <581.8 <581.5 2.3 <581.9 <581.5 2.4 <581.9 <581.5 2.5 <582.0 <581.6 2.6 <582.0 <581.6 2.7 <582.0 <581.6 2.8 <582.1 <581.6 2.9 <582.1 <581.6 3.0 <582.1 <581.7 3.1 <582.2 <581.7 3.2 <582.2 <581.7 3.3 <582.3 <581.7 3.4 <582.3 <581.7 3.5 <582.3 <581.8 3.6 <582.4 <581.8 3.7 <582.4 <581.8 3.8 <582.4 <581.8 3.9 <582.5 <581.9 4.0 <582.5 <581.9 4.1 <582.6 <581.9 4.2 <582.6 <581.9 4.3 <582.6 <581.9 4.4 <582.7 <582.0 4.5 <582.7 <582.0 4.6 <582.7 <582.0 4.7 <582.8 <582.0 4.8 <582.8 <582.1 4.9 <582.9 <582.1 5.0 <582.9 <582.1