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Category:Fuel Cycle Reload Report
MONTHYEARNL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-22-0273, Core Operating Limits Report, Cycle 23, Version 12022-04-12012 April 2022 Core Operating Limits Report, Cycle 23, Version 1 NL-21-0962, Core Operating Limits Report, Cycle 24, Version 12021-10-26026 October 2021 Core Operating Limits Report, Cycle 24, Version 1 ML21046A0962021-02-15015 February 2021 Core Operating Limits Report, Cycle 1, Version 3 ND-21-0084, (VEGP) Unit 3 - Affidavits of Brian H. Whitley & Zachary S. Harper2020-12-11011 December 2020 (VEGP) Unit 3 - Affidavits of Brian H. Whitley & Zachary S. Harper NL-20-1130, Core Operating Limits Report, Cycle 22, Version 22020-09-29029 September 2020 Core Operating Limits Report, Cycle 22, Version 2 NL-20-0415, Vogle, Unit 1, Core Operating Limits Report Cycle 23 Version 32020-04-13013 April 2020 Vogle, Unit 1, Core Operating Limits Report Cycle 23 Version 3 NL-18-1356, Core Operating Limits Report, Cycle 22, Version 12018-10-30030 October 2018 Core Operating Limits Report, Cycle 22, Version 1 NL-17-1757, Core Operating Limits Report, Cycle 20, Version 12017-11-0202 November 2017 Core Operating Limits Report, Cycle 20, Version 1 NL-17-1063, Core Operating Limits Report, Cycle 21 Version 12017-06-0606 June 2017 Core Operating Limits Report, Cycle 21 Version 1 NL-16-0597, Cycle 19 Core Operating Limits Report, Version 22016-04-20020 April 2016 Cycle 19 Core Operating Limits Report, Version 2 NL-15-2014, Submittal of Core Operating Limits Reports2015-11-0202 November 2015 Submittal of Core Operating Limits Reports NL-15-1602, Cycle 19 Core Operating Limits Report Version 22015-08-21021 August 2015 Cycle 19 Core Operating Limits Report Version 2 NL-14-1719, Cycle 18 Core Operating Limits Report, Version 12014-10-30030 October 2014 Cycle 18 Core Operating Limits Report, Version 1 NL-14-0753, Vogtle, Unit 1 - Cycle 19 Core Operating Limits Report2014-05-13013 May 2014 Vogtle, Unit 1 - Cycle 19 Core Operating Limits Report NL-14-0753, Cycle 19 Core Operating Limits Report2014-05-13013 May 2014 Cycle 19 Core Operating Limits Report ML14133A6772014-05-13013 May 2014 Cycle 19 Core Operating Limits Report NL-13-0646, Cycle 17 Core Operating Limits Reports2013-04-0505 April 2013 Cycle 17 Core Operating Limits Reports NL-12-2622, Unit 1 Cycle 18 Core Operating Limits Report2012-12-19019 December 2012 Unit 1 Cycle 18 Core Operating Limits Report NL-11-2044, Cycle 16 Version 2 Core Operating Limits Report2011-10-26026 October 2011 Cycle 16 Version 2 Core Operating Limits Report NL-11-0919, Cycle 17 Core Operating Limits Report2011-05-16016 May 2011 Cycle 17 Core Operating Limits Report NL-10-1213, Cycle 15 Version 3 Core Operating Limits Report2010-06-28028 June 2010 Cycle 15 Version 3 Core Operating Limits Report NL-10-0662, Unit 2 Cycle 15 Version 2 Core Operating Limits Report2010-04-0202 April 2010 Unit 2 Cycle 15 Version 2 Core Operating Limits Report NL-10-0389, Cycle 15 Core Operating Limits Report2010-03-17017 March 2010 Cycle 15 Core Operating Limits Report NL-09-1588, Cycle 16 Core Operating Limits Report, Rev. 0, & Rev. 12009-10-26026 October 2009 Cycle 16 Core Operating Limits Report, Rev. 0, & Rev. 1 NL-08-1651, Supplement to Unit 2 Cycle 14 Core Operating Limits Report, Rev 02008-10-31031 October 2008 Supplement to Unit 2 Cycle 14 Core Operating Limits Report, Rev 0 NL-07-0744, Cycle 13 Core Operating Limits Report, Rev. 02007-04-11011 April 2007 Cycle 13 Core Operating Limits Report, Rev. 0 NL-07-0012, Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report2007-01-30030 January 2007 Revision 1 of Unit 1 Cycle 14 Core Operating Limits Report NL-06-2319, Cycle 14 and Unit 2 Cycle 12 - Core Operating Limits Reports2006-10-20020 October 2006 Cycle 14 and Unit 2 Cycle 12 - Core Operating Limits Reports NL-06-1092, Cycle 13 Core Operating Limits Report2006-05-31031 May 2006 Cycle 13 Core Operating Limits Report NL-06-0151, Cycle 13 Core Operating Limits Report2006-01-31031 January 2006 Cycle 13 Core Operating Limits Report NL-05-2061, Revision 1 of Unit 1 Cycle 13 Core Operating Limits Report2005-11-18018 November 2005 Revision 1 of Unit 1 Cycle 13 Core Operating Limits Report NL-05-1739, Cycle 12 Core Operating Limits Report2005-09-30030 September 2005 Cycle 12 Core Operating Limits Report NL-05-0533, Cycle 13 Core Operating Limits Report2005-03-21021 March 2005 Cycle 13 Core Operating Limits Report NL-04-0623, Cycle 11 Core Operating Limits Report2004-04-28028 April 2004 Cycle 11 Core Operating Limits Report NL-03-1078, Cycle 11 Core Operating Limits Report2003-05-13013 May 2003 Cycle 11 Core Operating Limits Report ML0230202852002-10-16016 October 2002 Cycle 10 Core Operating Limits Report ML0209301632002-03-28028 March 2002 Cycle 11 Core Operating Limits Report 2023-07-19
[Table view] Category:Letter type:NL
MONTHYEARNL-24-0031, Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R232024-01-29029 January 2024 Inservice Inspection Program Owner'S Activity Report (OAR-1) for Outage 2R23 NL-24-0020, Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report2024-01-22022 January 2024 Plan, Unit 1 Responses to NRC Request for Additional Information for Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0926, Correction of Technical Specification Typographical Error2024-01-12012 January 2024 Correction of Technical Specification Typographical Error NL-23-0878, Request for Exemption from Security Event Notification Implementation2023-11-29029 November 2023 Request for Exemption from Security Event Notification Implementation NL-23-0827, Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.142023-11-17017 November 2023 Response to Requests for Additional Information for a License Amendment Request and a Proposed Alternative Related to TS 3.4.14 NL-23-0750, Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr2023-10-0404 October 2023 Response to Second Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the Colr NL-23-0745, Refueling Outage 1R24 Steam Generator Tube Inspection Report2023-09-22022 September 2023 Refueling Outage 1R24 Steam Generator Tube Inspection Report NL-23-0695, Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2)2023-08-31031 August 2023 Response to Round 2 Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters Operating, Completion Time Extension (LAR-22-002S2) NL-23-0666, License Amendment Request: Remove Combined License Appendix C (LAR 23-008)2023-08-28028 August 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-008) NL-23-0670, Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-08-11011 August 2023 Response to Request for Additional Information Regarding License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0658, Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal2023-08-11011 August 2023 Southern Nuclear Operating Company - Response to Request for Additional Information Regarding Quality Assurance Topical Report Submittal NL-23-0672, Licensee Guarantees of Payment of Deferred Premiums2023-08-10010 August 2023 Licensee Guarantees of Payment of Deferred Premiums NL-23-0542, CFR 50.46 ECCS Evaluation Model Annual Report for 20222023-08-0909 August 2023 CFR 50.46 ECCS Evaluation Model Annual Report for 2022 NL-23-0624, Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis2023-08-0404 August 2023 Report of Changes to Emergency Plan and Summary of 50.54(q) Analysis NL-23-0611, Core Operating Limits Report, Cycle 11 Version 12023-07-19019 July 2023 Core Operating Limits Report, Cycle 11 Version 1 NL-23-0584, Preservice Inspection Program Owner'S Activity Report2023-07-10010 July 2023 Preservice Inspection Program Owner'S Activity Report NL-23-0555, Request for Exemption from Physical Barrier Requirement2023-07-0707 July 2023 Request for Exemption from Physical Barrier Requirement NL-23-0506, to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications2023-07-0505 July 2023 to Non-Voluntary License Amendment Request: Technical Specification Revision to Adopt WCAP-17661-P-A, Improved RAOC and CAOC Fq Surveillance Technical Specifications NL-23-0541, Inservice Inspection Program Owners Activity Report for Outage 1R242023-06-28028 June 2023 Inservice Inspection Program Owners Activity Report for Outage 1R24 NL-23-0444, Quality Assurance Topical Report Submittal2023-06-15015 June 2023 Quality Assurance Topical Report Submittal NL-23-0339, Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1)2023-06-13013 June 2023 Response to Request for Additional Information Regarding License Amendment Request for Technical Specification 3.8.3, Inverters - Operating, Completion Time Extension (LAR-22-002S1) NL-23-0455, Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report2023-06-12012 June 2023 Report of 10 CFR 50.59 Changes, Tests, and Experiments and 10 CFR 52 Appendix D Departure Report NL-23-0467, Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1)2023-06-0909 June 2023 Response to Request for Additional Information Regarding License Amendment Request: Timing of Unit 4 Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005S1) NL-23-0346, License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007)2023-05-25025 May 2023 License Amendment Request for Exception to Regulatory Guide 1.163 (LAR 23-007) NL-23-0383, SNC Response to Regulatory Issue Summary 2023-01:Preparation And.2023-05-19019 May 2023 SNC Response to Regulatory Issue Summary 2023-01:Preparation And. NL-23-0385, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1)2023-05-17017 May 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006R1) NL-23-0398, Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-05-16016 May 2023 Withdrawal of Request of License Amendment Request Regarding More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0372, Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 20222023-05-10010 May 2023 Units 1 & 2, Joseph M. Farley Nuclear Plant - Units 1 & 2, Vogtle Electric Generating Plant - Units 1 & 2, Annual Radiological Environmental Operating Reports for 2022 NL-23-0360, Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-05-0505 May 2023 Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel NL-23-0326, Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-1082023-05-0101 May 2023 Response to Apparent Violation in NRC Inspection Report 05000424, 425/2023090; EA-22-108 NL-23-0217, License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-022023-05-0101 May 2023 License Amendment Request to Revise Technical Specification Surveillance Requirement 3.4.14.1 and Proposed Inservice Testing Alternative ALT-VR-02 NL-23-0330, Core Operating Limits Report, Cycle 25, Version 12023-04-26026 April 2023 Core Operating Limits Report, Cycle 25, Version 1 NL-23-0310, Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 20222023-04-25025 April 2023 Annual Non-Radiological Environmental Operating Reports and Annual Radioactive Effluent Release Reports for 2022 NL-23-0135, License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005)2023-04-17017 April 2023 License Amendment Request: Timing of Technical Specifications Effectiveness Prior to Initial Criticality (LAR-23-005) NL-23-0019, GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI2023-04-12012 April 2023 GEN-ISI-ALT-2023-01, Request to Use Provision of a Later Edition of the ASME Boiler and Pressure Vessel Code, Section XI NL-23-0152, License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-144832023-04-11011 April 2023 License Amendment Request: Technical Specification Revision to Adopt TSTF-339-A, Relocate Technical Specification Parameters to the COLR Consistent with WCAP-14483 NL-23-0263, Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report2023-04-0505 April 2023 Southern Nuclear Company Submittal of Drug and Alcohol Testing Errors Identified 10 CFR 26.719(c) 30-Day Report NL-23-0136, License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006)2023-04-0505 April 2023 License Amendment Request: More Restrictive Action for Technical Specification 3.1.9 (LAR-23-006) NL-23-0132, License Amendment Request: Remove Combined License Appendix C (LAR 23-001)2023-04-0404 April 2023 License Amendment Request: Remove Combined License Appendix C (LAR 23-001) NL-23-0014, Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding2023-03-29029 March 2023 Southern Nuclear Operating Co Submittal of Report on Status of Decommissioning Funding NL-23-0208, Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update2023-03-29029 March 2023 Independent Spent Fuel Storage Installation ISFSI, Decommissioning Funding Plan Triennial Update NL-23-0193, Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003)2023-03-24024 March 2023 Request for License Amendment: Relocation of TS 3.7.9, Spent Fuel Pool Makeup Water Sources (LAR-23-003) NL-23-0196, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-03-24024 March 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0228, Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21)2023-03-20020 March 2023 Nuclear Property Insurance Coverage as of April 1, 2023 and Licensee Guarantees of Payment of Deferred Premiums (10 CFR 140.21) NL-22-0977, License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing2023-02-0909 February 2023 License Amendment Request to Modify Technical Specification 5.5.11.c Acceptance Criteria for Charcoal Filter Testing NL-23-0010, Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-4902023-02-0606 February 2023 Response to Request for Additional Information Regarding License Amendment Request for Alternative Source Term, TSTF-51, TSTF-471, and TSTF-490 NL-23-0076, Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004)2023-01-31031 January 2023 Exigent License Amendment Request: Technical Specification Exceptions for In-containment Refueling Water Storage Tank Operability Prior to Initial Criticality (LAR-23-004) NL-23-0013, Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements2023-01-30030 January 2023 Response to Request for Additional Information Related to 10CFR 50.75 Decommissioning Funding Assurance Requirements NL-23-0068, Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report2023-01-27027 January 2023 Responses to NRC Request for Additional Information Related to the Refueling Outage 2R22 Steam Generator Tube Inspection Report NL-23-0012, Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel2023-01-20020 January 2023 Post-Audit Supplement to License Amendment Request and Exemptions to Allow Use of Lead Test Assemblies for Accident-Tolerant Fuel 2024-01-29
[Table view] |
Text
Jeffrey T.Gasser Southern Nuclear Vice President Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, Alabama 35201 Tel 205.992.7721 Fax 205.992.0403 SOUTHERN £A April 28, 2004 COMPANY Energy to Serve Your World' Docket Nos.: 50-424 NL-04-0623 50-425 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant Unit 2 Cycle 11 Core Operating Limits Report Ladies and Gentlemen:
Pursuant to the reporting requirements of Vogtle Electric Generating Plant (VEGP)
Technical Specification 5.6.5, Southern Nuclear Operating Company (SNC) is submitting Revision 0 of the Unit 2 Cycle 11 Core Operting Limits Report (COLR).
This letter contains no NRC commitments. If you have any questions, please advise.
Si IJTia4~-~--
Jeffrdy T. Gasser JTG/RJF/daj
Attachment:
Unit 2 Cycle 11 Core Operating Limits Report cc: Southern Nuclear Operating Company Mr. J. B. Beasley, Jr., Executive Vice President Mr. W. F. Kitchens, General Manager - Plant Vogtle Mr. M. Sheibani, Engineering Supervisor - Plant Vogtle RType: CVC7000 U. S. Nuclear Regulatorv Commission Mr. L. A. Reyes, Regional Administrator Mr. C. Gratton, NRR Project Manager - Vogtle Mr. J. Zeiler, Senior Resident Inspector - Vogtle
-AOD I
VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 2 CYCLE 11 CORE OPERATING LIMITS REPORT REVISION 0 APRIL 2004
COLR for VEGP UNIT 2 CYCLE 11 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP UNIT 2 CYCLE 11 has been prepared in accordance with the requirements of Technical Specification 5.6.5.
The Technical Requirement affected by this report is listed below:
13.1.1 SHUTDOWN MARGIN - MODES 1 and 2 The Technical Specifications affected by this report are listed below:
3.1.1 SHUTDOWN MARGIN - MODES 3,4 and 5 3.1.3 Moderator Temperature Coefficient 3.1.5 Shutdown Bank Insertion Limits 3.1.6 Control Bank Insertion Limits 3.2.1 Heat Flux Hot Channel Factor - F0(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channel Factor - FISH 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration PAGE 1 of 14
COLR for VEGP UNIT 2 CYCLE 11 2.0 OPERATING LIMITS The cycle-specific parameter limits for the specifications listed in Section 1.0 are presented in the following subsections. These limits have been developed using NRC-approved methodologies, including those specified in Technical Specification 5.6.5.
2.1 SHUTDOWN MARGIN - MODES 1 AND 2 (Technical Requirement 13.1.1) 2.1.1 The SHUTDOWN MARGIN shall be greater than or equal to 1.30 percent Ak/k.
2.2 SHUTDOWN MARGIN - MODES 3.4 AND 5 (Specification 3.1.1) 2.2.1 The SHUTDOWN MARGIN shall be greater than or equal to the limits shown in Figures 1 and 2.
2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOIJARO/HZP - MTC shall be less positive than +0.7 x 104 Ak/k/0F for power levels up to 70% RTP with a linear ramp to 0 Akk/I&F at 100% RTP.
The EOL/ARO/RTP-MTC shall be less negative than -5.50 x 104 Ak/kPF.1 2.3.2 The MTC Surveillance limits are:
The 300 ppm/ARO/RTP-MTC should be less negative than or equal to
-4.75 x 104 Ak/kf1F.'
The 60 ppm/ARO/RTP-MTC should be less negative than
-5.35 x 104 Ak/k/0F.1 where: BOL stands for Beginning of Cycle Life ARO stands for All Rods Out HZP stands for Hot Zero THERMAL POWER EOL stands for End of Cycle Life RTP stands for RATED THERMAL POWER 2.4 Shutdown Bank Insertion Limits (Specification 3.1.5) 2.4.1 The shutdown banks shall be withdrawn to a position greater than or equal to 225 steps.
2.5 Control Bank Insertion Limits (Specification 3.1.6) 2.5.1 The control banks shall be limited in physical insertion as shown in Figure 3.
Applicable for full-power T-average of 586.40F to 587.40F.
PAGE 2 OF 14
COLR for VEGP UNIT 2 CYCLE 11 2.6 Heat Flux Hot Channel Factor - Fa(Z) (Specification 3.2.1)
RTP FQ 2.6.1 Fa(Z) S
RTP Fo FQ(Z) s
0.5 where
P =THERMAL POWER RATED THERMAL POWER RTP 2.6.2 Fa = 2.50 2.6.3 K(Z) is provided in Figure 4.
RTP 2.6.4 Fo(Z) S FQ K(Z) for P > 0.5 P *W(Z)
RTP Fa(Z) S Fn
- W(Z) 2.6.5 W(Z) values are provided in Figures 6 through 9.
2.6.6 The Fa(Z) penalty factors are provided in Table 1.
PAGE 3 of 14
COLR for VEGP UNIT 2 CYCLE 11 2.7 Nuclear Enthalpy Rise Hot Channel Factor - FISH (Specification 3.2.2) 2.7.1 FISH S F *H(1 + PFAH* (1-P))
THERMAL POWER where: P =
RATED THERMAL POWER 2.7.2 FRHT = 1.65 2.7.3 PFAH = 0.3 2.8 Axial Flux Difference (Specification 3.2.3) 2.8.1 The Axial Flux Difference (AFD) Acceptable Operation Limits are provided in Figure 5.
2.9 Boron Concentration (Specification 3.9.1) 2.9.1 The boron concentration shall be greater than or equal to 1900 ppm.1
'This concentration bounds the condition of ken < 0.95 (all rods in less the most reactive rod) and subcriticality (I rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B10 depletion.
PAGE 4 of 14
COLR for VEGP UNIT 2 CYCLE 11 TABLE 1 Fa(Z) PENALTY FACTOR Cycle Fa(Z)
Burnup Penalty (MWD/MTU) Factor 4201 1.020 4414 1.021 4628 1.025 4841 1.025 5054 1.025 5267 1.023 5480 1.021 5694 1.020 Notes:
- 1. The Penalty Factor, to be applied to Fo(Z) in accordance with SR 3.2.1.2, is the maximum factor by which Fa(Z) is expected to increase over a 39 EFPD interval (surveillance interval of 31 EFPD plus the maximum allowable extension not to exceed 25% of the surveillance interval per SR 3.0.2) starting from the burnup at which the Fo(Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle burnups.
- 3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.
PAGE 5 of 14
COLR for VEGP UNIT 2 CYCLE 11 5.00 S 4.00 I- 4 4 4-
0 OPERATING a)
REGION z (2500, 3.1L e5 3.00 c:
z (1600,2.
0 c:]
t- 2.00 C, UNACCEPTABLE w
a5 OPERATING (950, 1.30) REGION wa cc A Ion . I ., .
0 500 . 1000 1500 2000 2500 2175-1
. RCS BORON CONCENTRATION (ppm)
FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING)
PAGE 6 of 14
COLR for VEGP UNIT 2 CYCLE 11 Ax 5.1 WVliii U
(250074.90)
'A
?4.00 ACCEPTABLE L.1 0.
2 z
j5 3.00 1 4 OPERATING REGION
- 4. -
7, 4.
(125c 2..85J 0 .
a 4 4 .4.
t- 2.00 V I a:
Lu 1.00 I _
Ai /
(460,1.00) .,
UNACCEPTABLE OPERATING REGION I
At U rIFlI__
.uu 0 500 1000 1500 2000 2500 217SI RCS BORON CONCENTRATION (ppm)
FIGURE 2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE)
PAGE 7 of 14
COLR for VEGP UNIT 2 CYCLE 11 (Fully Withdrawn *)
225 220 i /80 '225)' (718.0%,
. 225)-
PI, ll lll r-uu -
ornn^lk asBANK B 180 0% ,~'1 61) I_ I_ (100%,
160 _ _ _
161)
I I.BAN C ts
~0 3: 140 I 7F I en a I' =c BAN =Ca U) z 1I "itI
&.W F -
0 F'
'A A 0 100 _I ZI -I1I flZ~iI z
7' A 80 0 BANK D acr 60 'd (0%,) ___6 __
4 0
2 (30.2%, 0) n - --
0 20 -40 60 80 100 (Fully Inserted) 2175-1 POWER (percent of rated thermal power)
Fully withdrawn shall be the condition where control rods are at a position within the interval >225 and 231 steps withdrawn.
Note: The Rod Bank Insertion Umits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 115 steps.
FIGURE 3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER PAGE 8 of 14
COLR for VEGP UNIT 2 CYCLE 11 1.40 1.20 30 1.00 cc zas:
w a- 0.80 0
w N
0.60 a: F0 = 2.50 0
z CORE -
0.40 HEIGHT K(Z) -
0.000 1.000 6.000 1.000 0.20 12.000 0.925 0
0 2.0 4.0 6.0 8.0 10.0 12.0 CORE HEIGHT (ft)
-FIGURE 4 K(Z) - NORMALIZED F0 (Z) AS A FUNCTION OF CORE HEIGHT PAGE 9 of 14
COLR for VEGP UNIT 2 CYCLE 11 120 - . - S- SS U S * - S- S- S- U -
(-15, 100) (+10,100) l _ll IOC UNACCEPTABLE UNACCEPTABLE 0)
- 8C
- 0) ACCEPTABLE v 6C co a)
(-3 0, 50) (+26,5 0) 0 r-4C w
0 aJ 0~
2t C _ _
-50 -40 -3C) -20 -10 0 10 20 30 40 50 AXIAL FLUX DIFFERENCE (percent AI)
-FIGURE 5 AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF % OF RATED THERMAL POWER FOR RAOC PAGE 10 of 14
COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation BOL Point (feet) W(Z) 1.b 1 12.00 1.0000
- 4 11.40 1.0000 5 11.20 1.0000
' 6 11.00 1.0000 7 10.80 1.0000 C.. ' 8 10.60 1.0000
- 1.
- 10 10.20 1.0000 11 10.00 1.3225 12 9.80 1.3149 13 9.60 1.3104 14 9.40 1.3001 15 9.20 1.2895 16 .9.00 1.2718
- 1. 4 17 8.80 1.2592 18 8.60 - .1.2532 A
19 8.40 1.2499 20 8.20 1.2485 A 21 8.00 1.2439 A 22 - 7.80 1.2463 23 7.60 1.2513 N 24 7.40 1.2517 1.
A 25 7.20 1.2498 A 26 7.00 1.2456 AAA A 27 6.80 1.2031
A-- - 28 6.60 1.1953 A 29 6.40 1.1857 A 30 6.20 1.1746 A - 31 6.00 1.1677
- 1. 2 -- -- -- --
32 5.80 1.1660 A A 33 5.60 1.1676 A A 34 5.40 1.1772 35 5.20 1.1913 36 5.00 1.2049 37 4.80 1.2174 38 4.60 1.2292 39 4.40 1.2399
- 1. 1-- -
40 4.20 1.2496 41 4.00 1.2581 42 3.80 1.2614 43 3.60 1.2630 44 3.40 1.2641 45 3.20 1.2731 46 3.00 1.2876 47 2.80 1.3052 I. 0I 48 2.60 1.3240 0.0 2.0 4.0 6.0 8.0 10.0 1, 49 2.40 1.3423 50 2.20 1.3603 Core Height - feet 51 2.00 1.3787
- 52 1.80 1.0000 53 1.60 1.0000
- 56 1.00 1.0000
- 57 0.80 1.0000 This figure Isreferred to by Specification B3.2.1
- 59 0.40 1.0000 These WV(Z) values are consistent with Figure 5,and arc valid
- 60 0.20 1.0000 over the IIF T 815 temperature range from 586.4 to 587A40 F. 61 0.00 1.0000
COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation MOL-1 Point (feet) W(Z) 1.i 5 1 12.00 1.0000 1
4 5
6 11.80 11.60 11.40 11.20 11.00 1.0000 1.0000 1.0000 1.0000 1.0000 7 10.80 1.0000 8 10.60 1.0000
- 1. 9 10.40 1.0000 10 10.20 1.0000 11 10.00 1.3366 12 9.80 1.3278 13 9.60 1.3167 14 9.40 1.3020 15 9.20 1.2869 16 9.00 1.2695
- 1. 17 8.80 1.2590 18 8.60 1.2566 19 8.40 1.2557 20 8.20 1.2527 21 8.00 1.2537 22 7.80 1.2533
.4---iWs~S-r _ 23 7.60 1.2496 N 24 7.40 1.2436
- 1.
2: 25 7.20 1.2354 26 7.00 1.2254 27 6.80 1.1954 28 6.60 1.1830 29 6.40 1.1705 30 6.20 1.1568
___ _ _ _ 31 6.00 1.1634
- 1. 32 5.80 1.1557 33 5.60 1.1542 34 5.40 1.1611
_ _ _ _ _ _A 35 5.20 1.1694 36 5.00 1.1772 37 4.80 1.1841 38 4.60 1.1902 39 4.40 1.1955
- 1. 40 4.20 1.1997 41 4.00 1.2028 42 3.80 1.2074 43 3.60 1.2110 44 3.40 1.2138 45 3.20 1.2176 46 3.00 1.2312 47 2.80 1.2532
- 1. 48 2.60 1.2777 0.0 2.0 4.0 6.0 8.0 10.0 12.0 49 2.40 1.3017 50 2.20 1.3255 Core Height - feet 51 2.00 1.3492 52 1.80 1.0000 53 1.60 1.0000 54 1.40 1.0000
- 56 1.00 1.0000 57 0.80 1.0000 This figure Isreferred to by Specification B3.2.1 58 - 0.60 1.0000
- 59 0.40 1.0000 These W(Z) values are consistent with Figure 5, and are valid
- 60 0.20 1.0000 over the 1IFP Tayg temperature range from 586.4 to 587A°F.
- Top and Bottom 15% Excluded per Tecdnical Specification B3.2.1 FIGURE 7 PAGE 12 of 14 RAOC W (Z) AT 4000 MWD/MTU
COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation MOL-2
. . . . Point (feet) W(Z)
Of . . . . . . 1 12.00 1.0000
- 1. .
- 2 11.80 1.0000 3 11.60 1.0000 4 11.40 1.0000
- 1.
- 10 10.20 1.0000 11 10.00 1.2922 12 9.80 1.2803 13 9.60 1.2711 14 9.40 1.2604 15 9.20 1.2500 16 9.00 1.2425
- 1. 17 8.80 1.2355 18 8.60 1.2340 19 8.40 1.2383 20 8.20 1.2386 4-_ __ _, 21 8.00 1.2365 22 7.80 1.2352 23 7.60 1.2316 N 24 7.40 1.2259
-* 1. 25 7.20 1.2181 26 7.00 1.2085 27 6.80 1.1980 28 6.60 1.1877 X . . NS~sA 29 6.40 1.1777 z ~~~~ad . __- 30 6.20 1.1676 31 6.00 1.1575
_ __ _ . __ _ 32 5.80 1.1519
- 1. 33 5.60 1.1523 34 5.40 1.1563 35 5.20 1.1614
.- . _' . 36 5.00 1.1655 37 4.80 1.1683 38 4.60 1.1701
_ _A ~~~A _ _ _ 39 4.40 1.1706
- 1. 40 4.20 1.1703 41 4.00 1.1700 42 3.80 1.1688 43 3.60 1.1667 44 3.40 1.1655 45 3.20 1.1655 46 3.00 1.1672 47 2.80 1.1729
- 1. . 48 2.60 1.1817 0.0 2.0 4.0 6.0 8.0 10.0 12.0 49 2.40 1.1895 50 2.20 1.1971 Core Height - feet 51 2.00 1.2057
- 54 1.40 1.0000 55 1.20 1.0000
- 57 0.80 1.0000 This figure is referred to by Specification 133.2.1
- 59 0.40 1.0000 These W(Z) values are consistent with Figure 5, and are valid 60 0.20 1.0000 over the IIFP Tang temperature range from 586.4 to 587.4WF.
COLR for VEGP UNIT 2 CYCLE 11 Axial Elevation EOL 1.i LII I
2 3
4 5
6 (feet) 12.00 11.80 11.60 11.40 11.20 11.00 W(Z) 1.0000 1.0000 1.0000 1.0000 1.0000 1.0000
- 8 10.60 1.0000 1.5 9 10.40 1.0000
- 10 10.20 1.0000 11 10.00 1.2488 12 9.80 1.2565 13 9.60 1.2619 14 9.40 1.2649 15 9.20 1.2G79 16 9.00 1.2666
- 1. 17 8.80 1.2617 18 8.60 1.2613 19 8.40 1.2678 20 8.20 1.2760 21 8.00 1.2874 22 7.80 1.2852 23 7.60 1.2916 N 24 7.40 1.2949
- 1. 25 7.20 1.2951 A A __ _ 26 7.00 1.2923 27 6.80 1.2868 A AAA AA 28 6.60 1.2785 29 6.40 1.2681 AAA 30 6.20 1.2570 31 6.00 1.2444 32 5.80 1.2337
- 1. 33 5.60 1.2292
__A ~~~~a A& A__t K____
__ "^^ In^A 34 5.40 1.2290 35 5.20 1.2329 36 5.00 1.2353 37 4.80 1.2354 38 4.60 1.2336 39 4.40 1.2296 40 4.20 1.2236
- 1. 41 4.00 1.2156 42 3.80 1.2057 43 3.60 1.1944 44 3.40 1.1816 45 3.20 1.1695 46 3.00 1.1829 47 2.80 1.1900
- 1. i 48 2.60 1.1954 0.0 2.0 4.0 6.0 8.0 .10.0 12.( ) 49 2.40 1.2050 50 2.20 1.2159
-Core Height - feet 51 2.00 1.2268
- 52 1.80 1.0000 53 1.60 1.0000 54 1.40 1.0000
' 56 1.00 1.0000 57 0.80 1.0000 This figure is referred to by Specification 1D3.2.1 58 0.60 1.0000
' 59 0.40 1.0000 These W(Z) values are consistent with Figure 5, and are valid
- 60 0.20 1.0000 over the JIFP Tayg temperature range from 586.4 to 587AF.4
A SNC - Nuclear Licensing NRC Correspondence Routing and Information Sheet Applicable to: 10 CFR 50 Docket No. 10 CFR 72 No.
NRC Due Date: 4/ /0t Hatch Ul-321 U2-366 72-36 Author: R. J. Florian Farley UI-348 U2-364 LC #__ 72-42 Lic Letter No. NL-04-0623 Vogtle UI-424 U2-425 N/A Subject of Letter: Plant Vogtle Unit 2 Cycle 11 Core Operating Limits Report Response to: NRC Review I Concurrence Person Initials/Date Person InitialslDate 1 Site Mgmt. Concurrence 1J/A l 3 SRB Sub. Concurrence zJIf4 2 PRB Concurrence zJ1 4 Other WA Nuclear Licensing / Management Routing General Distributions:
O All extra copies to be issued via email in PDFMWORD format If possible (Except for NRC or State, issue hard copy)
O Allegation letters to JB Beasley in Confidential envelope O All letters to Executive: JB Beasley. Corp Licensing: BJ George, BD McKinney, RD Baker, NJ Stringfellow. Site NSACILicensing: GP Crone, M Sheibani, SB Tipps. TA Ruckman, TE Webb, WL Marlar, Submittals Review - FNP only.
o OPC (HNP & VNP only) - Laurence Bergen, Ken Rosanski and Bob Massey.
O All LERs to the respective LER Book, and LEReventseinpo.org as a WORD doc.
o NRR Project Managers: All TS Changes, RAI Responses and other items that require a response from the NRC.
Farlev: Sean Peters (sep~nrc.gov) Hatch & Vogtle: Christopher Gratton (cxg1 nrc.gov)
Other Distributions and comments: (List all distribution NOT shown in General Distributions above)