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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
Charles R. Pierce Southern Nuclear Regulatory Affairs Director Operating Company, Inc.
40 Inverness Center Parkway Post Office Box 1295 Birmingham, AL 35242 Tel 205.992.7872 Fax 205.992.7601 SOUTHERN << \
NUCLEAR A SOUTHERN COMPANY August 21, 2015 Docket Nos.: 50-424 NL-15-1602 U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D. C. 20555-0001 Vogtle Electric Generating Plant, Unit 1 Cycle 19 Core Operating Limits Report Version 2 Ladies and Gentlemen:
In accordance with Technical Specification 5.6.5.d, Southern Nuclear Operating Company (SNC) submits the enclosed Core Operating Limits Report (COLR) for the Vogtle Electric Generating Plant (VEGP) - Unit 1, Cycle 19, Version 2.
Version 2 includes an algorithm and figure for calculating the revised predicted near End of Life (EOL) moderator temperature coefficient {MTC). The Nuclear Regulatory Commission approved the use of this methodology with the issuance of Technical Specification amendment number 174 (Unit 1).
This letter contains no NRC commitments. If you have any questions, please contact Ken McElroy at {205) 992-7369 .
C. R. Pierce Regulatory Affairs Director CRP/RMJ
Enclosure:
Unit 1 Cycle 19 Core Operating Limits Report Version 2
U.S. Nuclear Regulatory Commission NL-15-1602 Page2 cc: Southern Nuclear Operating Company Mr. S. E. Kuczynski, Chairman, President & CEO Mr. D. G. Bast, Executive Vice President & Chief Nuclear Officer Mr. D. R. Madison, Vice President- Fleet Operations Mr. M. D. Meier, Vice President- Regulatory Affairs Mr. B. K. Taber, Vice President- Vogtle 1 & 2 Mr. B. J. Adams, Vice President- Engineering Mr. G.W. Gunn, Regulatory Affairs Manager- Vogtle 1 & 2 RType: CVC7000 U.S. Nuclear Regulatorv Commission Mr. V. M. McCree, Regional Administrator Mr. R. E. Martin, NRR Senior Project Manager- Vogtle 1 & 2 Mr. L. M. Cain, Senior Resident Inspector- Vogtle 1 & 2
Vogtle Electric Generating Plant, Unit 1 Cycle 19 Core Operating Limits Report Version 2 Enclosure Unit 1 Cycle 19 Core Operating Limits Report Version 2
VOGTLE ELECTRIC GENERATING PLANT (VEGP) UNIT 1 CYCLE 19 CORE OPERATING LIMITS REPORT Version 2 June 2015
CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE 2015 1.0 CORE OPERATING LIMITS REPORT This Core Operating Limits Report (COLR) for VEGP Unit 1 Cycle 19 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 - Fo(Z) 3.2.2 Nuclear Enthalpy Rise Hot Channnel Factor- FN m 3.2.3 Axial Flux Difference 3.9.1 Boron Concentration Page 1 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 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 &/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.
Page 2 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE 2015 2.3 Moderator Temperature Coefficient (Specification 3.1.3) 2.3.1 The Moderator Temperature Coefficient (MTC) limits are:
The BOLlARO/HZP-MTC shall be less positive than +0. 7 x 1O"" Aklk/°F for power levels up to 70% RTP with a linear ramp to 0 Aklk/°F at 100% RTP.
The EOLIARO/RTP-MTC shall be less negative than -5.50 x 10"" Aklk/°F. 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 10"" Aklk/°F. 1 The revised predicted near-EOL 300 ppm MTC shall be calculated using Figure 6 and the following algorithm:
Revised Predicted MTC Predicted MTC* + AFD Correction** + Predictive Correction***
where,
- Predicted MTC is calculated from Figure 6 at the burnup corresponding to the measurement of300 ppm at RTP conditions,
- AFD Correction is the more negative value of:
{0 pcm/°F or (b.AFD
where: D.AFD is the measured AFD minus the predicted AFD from an incore flux map taken at or near the burnup corresponding to 300ppm, AFD Sensitivity= 0.08 pcm/°F I D.AFD
- ..Predictive Correction is -3 pcmfDF.
The 60 ppm/ARO/RTP-MTC should be less negative than -5.35 x tO"" Aklk/°F. 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 I Applicable for full-power T-average of 584.1 to 587.1 °F.
Page3 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 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 rod banks shall be limited in physical insertion as shown in Figure 3.
2.6 Heat Flux Hot Channel Factor- F Q(Z) (Specification 3.2.1)
FRTP 2.6.1 FQ (Z) ~ _Q_
FRTP FQ (Z) ~ _Q_
- K(Z) for P ~ 0.5 0.5 THERMAL POWER where: P=----------
RATED THERMAL POWER 2.6.2 2.6.3 K(Z) is provided in Figure 4.
FRTP. K(Z) 2.6.4 F (Z) ~ Q for P > 0.5 Q P*W(Z)
FRTP. K(Z)
F (Z) < Q for P ~ 0.5 Q - 0.5 *W(Z) 2.6.5 W(Z) values are provided in Table 2.
2.6.6 The F 0 (Z) penalty factors are provided in Table I.
Page 4 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE2015
- 2.7 Nuclear Enthalpy Rise Hot Channel Factor- pN Mi (Specification 3.2.2)
THERMAL POWER where: p =----------
RATED THERMAL POWER 2.7.2 F:JP = 1.65 2.7.3 PFMI =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 1880 ppm. 2 2
This concentration bounds the condition ofkerr~ 0.95 (all rods in less the most reactive rod) and subcriticality (ru! rods out) over the entire cycle. This concentration includes additional boron to address uncertainties and B 10 depletion.
Page 5 ofl3
CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE2015 Tablel FQ(Z) PENALTY FACTOR Cycle Burnup FQ(Z) Penalty Factor (MWDIMTU) 30 1.0348 150 1.0348 368 1.0391 585 1.0417 803 1.0423 1020 1.0410 1238 1.0366 1456 1.0308 1673 1.0248 1891 1.0200 6242 1.0200 6460 1.0204 6678 1.0260 6895 1.0262 7113 1.0261 7330 1.0244 7548 1.0214 7765 1.0200 Notes:
- 1. The Penalty Factor, to be applied to FQ(Z) in accordance with SR 3.2.1.2, is the maximum factor by which FQ(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 bum up at which the FQ(Z) was determined.
- 2. Linear interpolation is adequate for intermediate cycle bumups.
- 3. For all cycle burnups outside the range of the table, a penalty factor of 1.020 shall be used.
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CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE 2015 Table 2 RAOCW(Z)
Axial Elevation ISO 3000 12000 20000 Point (reet) MWD/MTU MWD/MTU MWD/MTU MWD/MTU 1-5 12.072- 11.267 1.0000 1.0000 1.0000 1.0000 6 11.066 1.3172 1.3495 1.3279 1.2728 7 10,865 1.3162 1.3440 1.3244 1.2665 8 10.664 1.3018 1.3350 1.3164 1.2561 9 10.462 1.2808 1.3167 1.3051 1.2430 10 10.261 1.2615 1.2912 1.2919 1.2294 11 10.060 1.2467 1.2683 1.2775 1.2189 12 9.859 1.2503 1.2431 1.2614 1.2150 13 9.658 1.2444 1.2130 1.2438 1.2096 14 9.456 1.2373 1.1979 1.2384 1.2144 15 9.255 1.2278 1.1893 1.2286 1.2272 16 9.054 1.2168 1.1763 1.2165 1.2359 17 8.853 1.2020 1.1662 1.2092 1.2397 18 8.652 1.1893 1.1670 1.2141 1.2426 19 8.450 1.1900 1.1724 l.llJO 1.2438 20 8.249 1.1889 1.1761 1.2290 1.2500 21 8.048 1.1918 1.1783 1.2332 1.2591 22 7.847 1.1940 1.1780 1.2344 1.2670 23 7.646 1.1935 1.1761 1.2336 1.2800 24 7.444 1.1914 1.1728 1.2315 1.2895 25 7.243 1.1867 1.1674 1.2259 1.2944 26 7.042 1.1802 1.1604 1.2178 1.2950 27 6.841 1.1724 1.1523 1.2083 1.2931 l8 6.640 1.1633 1.1459 1.1918 1.2890 29 6.438 1.1529 1.1393 1.1896 1.2819 30 6.237 1.1452 l.ln6 1.1101 1.2719 31 6,036 1.1401 1.1279 1.1696 1.2596 32 5.835 1.1344 1.1252 1.1608 1.2478 33 5.634 1.1321 1.1225 1.1560 1.2400 34 5.432 1.1309 1.1258 1.1590 1.2349 35 5.231 1.1317 1.1378 1.1648 1.2349 36 5.030 1.1386 1.1484 1.1706 1.2348 37 4.829 1.1477 1.1587 1.1753 1.2344 38 4.628 1.1561 1.1683 1.1790 1.2333 39 4.426 1.1640 1.1775 1.1815 1.2302 40 4.225 1.1710 1.1856 1.1829 1.2254 41 4.024 1.1770 1.1930 1.1133 1.2191 42 3,823 1.1826 1.1994 1.1822 1.2100 43 3.622 1.1872 1.2065 1.1795 1.1985 44 3.420 1.1925 1.2159 1.1763 1.1861 45 3.219 1.1985 1.2241 1.1722 1.1765 46 3.018 1.2057 1.2377 1.1765 1.1776 47 2.817 1.2190 1.2562 1.1889 1.1890 48 2.616 1.2337 1.2794 1.2020 1.2019 49 2.414 1.2476 1.3058 1.2149 1.2147 50 2.213 1.2616 1.3328 1.2279 1.2275 51 2.012 1.2755 1.3595 1.2399 1.2386 52 1.811 1.2893 1.3858 1.2514 1.2491 53 1.610 1.3024 1.4105 1.2627 1.2601 54 1.408 1.3149 1.4336 1.2737 1.2714 55 1.207 1.3269 1.4550 1.2843 1.2828 56 1.006 1.3380 1.4742 1.2943 1.2945 57-61 0.805 - 0.000 1.0000 1.0000 1.0000 1.0000 Top and Bottom 5 Points Excluded per Technical Specification B3.2.1.
These W(Z) values are consistent with Figure 5, and are valid over the HFP T avg temperature range from 584.1 to 587 .I °F.
Page 7 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 FIGURE 1 REQUIRED SHUTDOWN MARGIN FOR MODES 3 AND 4 (FOUR LOOPS FILLED AND VENTED AND AT LEAST ONE REACTOR COOLANT PUMP RUNNING) 5.0 4.0 ACCEPTABLE OPERATING REGION (2 00, .1 b>
L/
vv SHUTDOWN MARGIN!
vv RE~UIRED (1 00 , .2 5)
/
v
/
/
/
/
/
/
!UNACCEPTABLE OPERATING REGION I
(~SC, . 0) 1.0 0.0 0 SOD 1000 1500 2000 2500 RCS BORON CONCBNTRATION (ppm)
Page 8 ofl3
CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE 2015 FIGURE2 REQUIRED SHUTDOWN MARGIN FOR MODES 4 AND 5 (MODE 4 WHEN FIGURE 1 NOT APPLICABLE) 5.0 (2 00 I '
.9
~
v vv
.~v 4.0 vv
!ACCEPTABLE OPERATING REGION I v
vv /
- i
....... v v
.II! /
<] 3.0 rJP
!REQUIRED SHUTDOWN MARGIN~ (1 50 I * .8 ~)
~
v H
a
! v 2.0 v
m v v
11.1 I UNACCEPTABLE OPERATING REGION 1.0
( 11:6( 1
- c0) 0.0 0 500 1000 1500 2000 2500 RCS BORON CONCENTRATION (ppm)
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CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE2015 FIGURE3 ROD BANK INSERTION LIMITS VERSUS % OF RATED THERMAL POWER (Fully Withdrawn*)
V I( .Oils 225 / 18. I) 220 v /
200
..... BANK B
~ 180 I/
w / v
- 8 v
/
1:115 .61 v
/
ll I ( 115 ~61
- 160
~
Ill PI
!J140 til BANK C I§ 120 /
/
/
H E-1 / k" H
til
'/
v v
/
~ 100 a 80
§
~ 1.1' BANK D I/ .1' 60 v .1' v /
'/
I Olli 4161) 40 20 i l .::.n 0) .1' 0 1.1' 0 10 20 30 40 50 60 70 80 90 1 0 POWER (\ of Rated Thermal Power}
- Fully withdrawn shall be the condition where control rods are at a position within the interval ~ 225 and ~ 23 I steps withdrawn.
NOTE: The Rod Bank Insertion Limits are based on the control bank withdrawal sequence A, B, C, D and a control bank tip-to-tip distance of 115 steps.
Page 10 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE 2015 FIGURE4 K(Z)- NORMALIZED F o(Z) AS A FUNCTION OF CORE HEIGHT 1.4 1.2
~ ~
Eo!
~ 1.0
~ -
a p.. 0. 8 FQ = 2.50
&I CORE ig N
HT. K(Z) 0.00 1.00
- 0. 6 6.00 1. 00 12.0 .925
~
N Ill:
0.4 0.2 0.0 0 2 4 6 8 10 12 CORE HEIGHT (feet)
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CORE OPERATING LIMITS REPORT. VEGP UNIT I CYCLE 19 JUNE 2015 FIGURES AXIAL FLUX DIFFERENCE LIMITS AS A FUNCTION OF %RATED THERMAL POWER FORRAOC 120 110
{-15, 100) {+10, 100) 100 I \
~
90 u ~AC ~EP' ABI E I \ UN CCI PTJl BLE
~
Po II \
80 \
a I \
I \
Ql
.r:l A~CE ~TAl LE E-4 70 "Cj ~
Ql Ill 60 I \
I \
ll!i 0
so 1/ 1\
rJP ll!i I { -30, 50) I (+26, SO)
~
Po 40 30 20 10 0
-so -40 -30 -20 -10 0 10 20 30 40 so AXIAL FLUX DIFFERENCE {percent ~I)
Page 12 of13
CORE OPERATING LIMITS REPORT. VEGP UNIT 1 CYCLE 19 JUNE2015 FIGURE6 PREDICTED HFP 300 PPM MTC VS CYCLE BURNUP
-f-L
-28.0 I I I r; - -
0 I I
' i 1
I
~I I I
' ...... I I
~ -28.5 I I
~ I I l
~ I
~0 I ~
u .......
Gl -29.0 I I I I I II ...... I B
-='-- "' -...,,I I
Ill I I T!
' I...... i'o-It 1--- -
E-1 -29.5 I I .......
1-1 I -- ----
llIll -I-
~ I I I
- i I -I
-30.0 I ' I i I I 17000 18000 19000 20000 21000 Cycle Burnup (MHD/MTU)
CycleBumup Moderator Temperature (MWD/MTU) Coefficient (pcm/°F) 17000 -28.33 18000 -28.65 19000 -28.93 20000 -29.23 21000 -2954 Page 13 of13