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Category:Fuel Cycle Reload Report
MONTHYEAR0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN052401, Cycle 32 Core Operating Limits Report2024-05-0404 May 2024 Cycle 32 Core Operating Limits Report 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 2CAN102101, Cycle 29 Core Operating Limits Report (COLR)2021-10-15015 October 2021 Cycle 29 Core Operating Limits Report (COLR) 1CAN062102, Cycle 30 Core Operating Limits Report (COLR) Revision 12021-06-25025 June 2021 Cycle 30 Core Operating Limits Report (COLR) Revision 1 1CAN042101, Cycle 30 Core Operating Limits Report (COLR)2021-04-21021 April 2021 Cycle 30 Core Operating Limits Report (COLR) 2CAN032003, Cycle 28 COLR2020-03-30030 March 2020 Cycle 28 COLR 1CAN101905, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-4 Supplemental Examination Requirements ANO1-ISI-0332019-10-31031 October 2019 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-4 Supplemental Examination Requirements ANO1-ISI-033 1CAN101902, Cycle 29 Core Operating Limits Report (COLR)2019-10-18018 October 2019 Cycle 29 Core Operating Limits Report (COLR) 1CAN121804, Core Operating Limits Report (COLR) Cycle 28 COLR, Revision 22018-12-19019 December 2018 Core Operating Limits Report (COLR) Cycle 28 COLR, Revision 2 2CAN101802, Cycle 27 COLR2018-10-25025 October 2018 Cycle 27 COLR 1CAN041806, Cycle 28 COLR, Revision 12018-04-23023 April 2018 Cycle 28 COLR, Revision 1 2CAN051701, Cycle 26 Core Operating Limits Report2017-05-22022 May 2017 Cycle 26 Core Operating Limits Report ML16315A1672016-11-10010 November 2016 Core Operating Limits Report for Cycle 27 1CAN021601, Cycle 26 Core Operating Limits Report, Revision 12016-02-0303 February 2016 Cycle 26 Core Operating Limits Report, Revision 1 2CAN101502, Submittal of Cycle 25, Core Operating Limits Report (COLR)2015-10-19019 October 2015 Submittal of Cycle 25, Core Operating Limits Report (COLR) 1CAN081504, Cycle 26 Core Operating Limits Report (COLR)2015-08-27027 August 2015 Cycle 26 Core Operating Limits Report (COLR) 1CAN021501, Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report2015-02-0505 February 2015 Unit 1 - Submits Revision 0 of Cycle 26 Core Operating Limits Report 1CAN101408, Cycle 25 Core Operating Limits Report2014-10-28028 October 2014 Cycle 25 Core Operating Limits Report 1CAN081301, Unit 1, ANO-1 Cycle 25 COLR, Revision 12013-08-12012 August 2013 Unit 1, ANO-1 Cycle 25 COLR, Revision 1 1CAN061303, Cycle 25 Core Operating Limits Report2013-06-20020 June 2013 Cycle 25 Core Operating Limits Report 1CAN101202, Unit 1: Cycle 24 Core Operating Limits Report (Colr), Revision 52012-10-15015 October 2012 Unit 1: Cycle 24 Core Operating Limits Report (Colr), Revision 5 2CAN101202, Cycle 23, Core Operating Limits Report2012-10-0404 October 2012 Cycle 23, Core Operating Limits Report 2CAN101201, Cycle 23, Core Operating Limits Report2012-10-0303 October 2012 Cycle 23, Core Operating Limits Report 1CAN081203, Cycle 24 Core Operating Limits Report (Colr), Revision 42012-08-30030 August 2012 Cycle 24 Core Operating Limits Report (Colr), Revision 4 1CAN041201, Unit 1, ANO-1 Cycle 24 COLR, Revision 32012-04-0404 April 2012 Unit 1, ANO-1 Cycle 24 COLR, Revision 3 1CAN111104, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 22011-11-23023 November 2011 Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 2 1CAN111103, Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 12011-11-11011 November 2011 Unit 1, ANO-1 Cycle 24 Core Operating Limits Report (Colr), Revision 1 1CAN101101, Submittal of Cycle 24 Core Operating Limits Report (COLR)2011-10-31031 October 2011 Submittal of Cycle 24 Core Operating Limits Report (COLR) 2CAN031103, Cycle 22 COLR2011-03-10010 March 2011 Cycle 22 COLR 2CAN081005, Cycle 21 COLR, Revision 12010-08-20020 August 2010 Cycle 21 COLR, Revision 1 1CAN041005, Submittal of Rev. 1 to Cycle 23 Core Operating Limits Report2010-04-15015 April 2010 Submittal of Rev. 1 to Cycle 23 Core Operating Limits Report 1CAN041001, Cycle 23 Core Operating Limits Report2010-04-0606 April 2010 Cycle 23 Core Operating Limits Report 2CAN110901, Response to Request for Additional Information Technical Specification 6.6.5, Core Operating Limits Report2009-11-10010 November 2009 Response to Request for Additional Information Technical Specification 6.6.5, Core Operating Limits Report 2CAN090902, Cycle 21 COLR2009-09-14014 September 2009 Cycle 21 COLR 1CAN110801, Cycle 22 Core Operating Limits Report (COLR)2008-11-13013 November 2008 Cycle 22 Core Operating Limits Report (COLR) 2CAN050802, Revision 1 to the ANO-2 Cycle 20 COLR2008-05-22022 May 2008 Revision 1 to the ANO-2 Cycle 20 COLR 2CAN030805, Cycle 20 Core Operating Limits Report (COLR)2008-03-27027 March 2008 Cycle 20 Core Operating Limits Report (COLR) 1CAN050701, Arkansas - Unit 1 - Cycle 21 Core Operating Limits Report2007-05-0101 May 2007 Arkansas - Unit 1 - Cycle 21 Core Operating Limits Report 2CAN110601, Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R182006-11-30030 November 2006 Day Report for ANO-2 Reactor Pressure Vessel Head Inspection for Refueling Outage 2R18 2CAN100601, Cycle 19 Core Operating Limits Report2006-10-13013 October 2006 Cycle 19 Core Operating Limits Report 1CAN120503, Unit 1, Cycle 20 Core Operating Limits Report (COLR) Per Technical Specification 5.6.52005-12-0101 December 2005 Unit 1, Cycle 20 Core Operating Limits Report (COLR) Per Technical Specification 5.6.5 2CAN060502, Cycle 18 Startup Report - Arkansas Nuclear One, Unit 22005-06-11011 June 2005 Cycle 18 Startup Report - Arkansas Nuclear One, Unit 2 2CAN030504, Cycle 18 Core Operating Limits Report2005-03-29029 March 2005 Cycle 18 Core Operating Limits Report 1CAN040401, Unit 1, ANO-1 Cycle 19 COLR2004-04-30030 April 2004 Unit 1, ANO-1 Cycle 19 COLR 2CAN100305, Cycle 17 Core Operating Limits Report2003-10-0404 October 2003 Cycle 17 Core Operating Limits Report 1CAN110202, Revision 1 to Cycle 18 Core Operating Limits Report Per Technical Specification 5.6.5.d2002-11-0707 November 2002 Revision 1 to Cycle 18 Core Operating Limits Report Per Technical Specification 5.6.5.d 1CAN100201, Cycle 18 COLR2002-10-10010 October 2002 Cycle 18 COLR 1CAN070203, Submittal of Revision to Arkansas Nuclear One, Unit 1 Core Operating Limits Report2002-07-0303 July 2002 Submittal of Revision to Arkansas Nuclear One, Unit 1 Core Operating Limits Report 2024-07-08
[Table view] Category:Letter type:
MONTHYEAR2CAN072401, Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02)2024-07-19019 July 2024 Proposed Alternative for Implementation of Extended Reactor Vessel In-Service Inspection Interval (ANO2-ISI-24-02) 0CAN072401, Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes2024-07-0808 July 2024 Annual 10 CFR 50.46 Report for Calendar Year 2023 Emergency Core Cooling System Evaluation Changes 1CAN072401, Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply2024-07-0202 July 2024 Request for Review and Approval of Changes to the Safety Analysis Report and to a Confirmatory Order Clarifying an Alternate Means of Compliance for Pressurizer Heaters Emergency Power Supply 0CAN062403, Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels2024-06-25025 June 2024 Groundwater Protection Initiative - Voluntary Special Report for Tritium Levels 0CAN062402, Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles2024-06-0606 June 2024 Proposed Alternatives ANO1-ISI-24-01 and ANO2-ISI-24-01 for Examinations of Steam Generator Pressure-Retaining Welds and Full Penetration Welded Nozzles 0CAN052401, – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 20232024-05-13013 May 2024 – Units 1 and 2, Submittal of Annual Radiological Environmental Operating Report for 2023 1CAN052401, Cycle 32 Core Operating Limits Report2024-05-0404 May 2024 Cycle 32 Core Operating Limits Report 2CAN042403, Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C2024-04-24024 April 2024 Response to the Request for Additional Information Regarding ANO-2 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended C 0CAN042402, Annual Occupational Radiation Exposure Report for 20232024-04-23023 April 2024 Annual Occupational Radiation Exposure Report for 2023 2CAN012401, U.S. Additional Protocol2024-01-17017 January 2024 U.S. Additional Protocol 2CAN012403, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42024-01-11011 January 2024 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN012401, Registration of Cask Use2024-01-10010 January 2024 Registration of Cask Use 1CAN122301, Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037)2023-12-14014 December 2023 Responses to Request for Additional Information for Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISl-037) 2CAN112302, Submittal of Amendment 31 to Safety Analysis Report2023-11-16016 November 2023 Submittal of Amendment 31 to Safety Analysis Report 0CAN102303, Registration of Cask Use2023-10-24024 October 2023 Registration of Cask Use 0CAN102302, (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 32023-10-11011 October 2023 (ANO) Emergency Plan Revision 49 and Emergency Plan On-Shift Staffing Analysis Revision 3 0CAN102301, Evacuation Time Estimate (ETE) Study2023-10-0404 October 2023 Evacuation Time Estimate (ETE) Study 1CAN092301, Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-09-21021 September 2023 Supplemental Information - Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN092302, Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2023-09-14014 September 2023 Supplement to Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 2CAN092301, Reply to a Notice of Violation2023-09-0808 September 2023 Reply to a Notice of Violation 0CAN092301, Emergency Plan Implementing Procedure Revision2023-09-0505 September 2023 Emergency Plan Implementing Procedure Revision 0CAN082301, Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 03412023-08-17017 August 2023 Units 1 and 2 - Changes to the Quality Assurance Program Approval Form for Radioactive Material Package No. 0341 2CAN082301, Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29)2023-08-10010 August 2023 Inservice Inspection Summary Report for the Arkansas Nuclear One, Unit 2, Twenty-Ninth Refueling Outage (2R29) 0CAN072301, Registration of Cask Use2023-07-18018 July 2023 Registration of Cask Use 1CAN062304, Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2023-06-29029 June 2023 Supplement Related to License Amendment Request to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 0CAN062301, Status of Actions to Return to Compliance2023-06-26026 June 2023 Status of Actions to Return to Compliance 0CAN062302, Submittal of Revision 22 of the ANO Fire Hazards Analysis2023-06-20020 June 2023 Submittal of Revision 22 of the ANO Fire Hazards Analysis 1CAN062301, Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037)2023-06-0808 June 2023 Request for Alternative for Implementation of Extended Reactor Vessel Inservice Inspection Interval (ANO1-ISI-037) 0CAN052303, Annual 10 CFR 50.46 Report for Calendar Year 20222023-05-24024 May 2023 Annual 10 CFR 50.46 Report for Calendar Year 2022 0CAN052302, Emergency Plan Rev. 482023-05-11011 May 2023 Emergency Plan Rev. 48 0CAN052301, Units 1 and 2 - Annual Radiological Environmental Operating Report for 20222023-05-0909 May 2023 Units 1 and 2 - Annual Radiological Environmental Operating Report for 2022 2CAN052301, Cycle 30 Core Operating Limits Report (COLR)2023-05-0303 May 2023 Cycle 30 Core Operating Limits Report (COLR) 0CAN042302, Annual Occupational Radiation Exposure Report for 20222023-04-27027 April 2023 Annual Occupational Radiation Exposure Report for 2022 0CAN042301, Radioactive Effluent Release Report for 20222023-04-14014 April 2023 Radioactive Effluent Release Report for 2022 2CAN042301, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42023-04-0505 April 2023 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 1CAN032301, License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure2023-03-30030 March 2023 License Amendment Request to Modify the Arkansas Nuclear One, Unit 1, Technical Specification 3.3.1, Reactor Protection System Instrumentation, Turbine Trip Function on Low Control Oil Pressure 2CAN032304, Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Supplement to the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032303, Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-03-29029 March 2023 Responses to Request for Additional Information Concerning the Request for Alternative Regarding the Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 2CAN032305, 03 Post Examination Analysis2023-03-23023 March 2023 03 Post Examination Analysis 1CAN032302, Inspection Summary Report for the Thirtieth Refueling Outage (1R30)2023-03-20020 March 2023 Inspection Summary Report for the Thirtieth Refueling Outage (1R30) 1CAN012301, Responses to Request for Additional Information for Request for Relief ANO1-ISI-0352023-01-30030 January 2023 Responses to Request for Additional Information for Request for Relief ANO1-ISI-035 2CAN012303, U.S. Additional Protocol2023-01-23023 January 2023 U.S. Additional Protocol 2CAN012302, Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 462023-01-20020 January 2023 Relief Request ANO2-RR-23-001, Half-Nozzle Repair of Reactor Vessel Closure Head Penetration 46 1CAN122201, License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 42022-12-22022 December 2022 License Amendment Request to Revise Technical Specifications to Adopt Risk-Informed Completion Times TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4 0CAN122202, Registration of Cask Use2022-12-21021 December 2022 Registration of Cask Use 0CAN122201, Reply to a Notice of Violation; EA-22-0992022-12-0808 December 2022 Reply to a Notice of Violation; EA-22-099 0CAN112201, Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002)2022-11-10010 November 2022 Request for Alternative Frequency to Containment Unbonded Post-Tensioning System Inservice Inspection (ANO-CISI-002) 1CAN102202, Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation2022-10-31031 October 2022 Application to Remove Technical Specification Condition Allowing Two Reactor Coolant Pump Operation 1CAN102203, Cycle 31 Core Operating Limits Report2022-10-24024 October 2022 Cycle 31 Core Operating Limits Report 1CAN102201, Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations2022-10-13013 October 2022 Supplement to Proposed Technical Specifications 3.4.12 and 3.4.13 Revised Dose Calculations 2024-07-08
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Text
Entergy Operations, Inc.
1448 S.R. 333 Russellville, AR 72802 Tel 479-858-4619 Dale E. James Manager, Licensing Arkansas Nuclear One 2CAN030805 March 27, 2008 U. S. Nuclear Regulatory Commission Attn.: Document Control Desk Washington, DC 20555-0001
SUBJECT:
ANO-2 Cycle 20 COLR Arkansas Nuclear One, Unit 2 Docket No. 50-368 License No. NPF-6
Dear Sir or Madam:
Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 requires the submittal of the Core Operating Limits Report (COLR) for each reload cycle. Attached is Revision 0 of the ANO-2 Cycle 20 COLR. This completes the reporting requirement for the referenced specification.
This submittal contains no commitments.
If you have any questions or require additional information, please contact David Bice at 479-858-5338.
Sincerely, DEJ/dbb
Attachment:
ANO-2 Cycle 20 Core Operating Limits Report (COLR)
2CAN030805 Page 2 of 2 cc: Mr. Elmo E. Collins Regional Administrator U. S. Nuclear Regulatory Commission Region IV 611 Ryan Plaza Drive, Suite 400 Arlington, TX 76011-8064 NRC Senior Resident Inspector Arkansas Nuclear One P.O. Box 310 London, AR 72847 U.S. Nuclear Regulatory Commission Attn: Mr. Alan B. Wang MS O-7 D1 Washington, DC 20555-0001 Mr. Bernard R. Bevill Director Division of Radiation Control and Emergency Management Arkansas Department of Health & Human Services P.O. Box 1437 Slot H-30 Little Rock, AR 72203-1437
ATTACHMENT 2CAN030805 ANO-2 CYCLE 20 CORE OPERATING LIMITS REPORT (COLR)
ANO2-NE-08-00002 Revision 0 ENTERGY OPERATIONS ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 20 1
ANO2-NE-08-00002 Revision 0 CORE OPERATING LIMITS REPORT FOR CYCLE 20 INDEX PAGE I. INTRODUCTION ........................................................................................................ 3 II.
SUMMARY
OF CHANGES......................................................................................... 3 III. AFFECTED TECHNICAL SPECIFICATIONS ............................................................ 3 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS ........................... 4 V. CORE OPERATING LIMITS....................................................................................... 6 VI. LIST OF FIGURES ..................................................................................................... 7 2
ANO2-NE-08-00002 Revision 0 ARKANSAS NUCLEAR ONE - UNIT 2 CORE OPERATING LIMITS REPORT FOR CYCLE 20 I. INTRODUCTION This CORE OPERATING LIMITS REPORT (COLR) has been prepared in accordance with the requirements of Arkansas Nuclear One - Unit 2 (ANO-2) Technical Specification 6.6.5 for ANO-2's Cycle 20. This is Revision 0 of the Cycle 20 COLR.
II.
SUMMARY
OF CHANGES Listed below are the changes to the COLR from the latest revision of the Cycle 19 COLR.
- Figures 4 and 5, DNBR Margin Operating Limit Based on Core Protection Calculators, Minimum 1 CEAC Operable and Both CEACs Inoperable, respectively, were revised to remove the adjustment made in Cycle 19 to account for crediting ABB-NV CHF correlation for CPC DNBR calculations since this credit is not being taken in Cycle 20.
- Linear Heat Rate has been changed from 14.4 kW/ft to 13.7 kW/ft.
- References 21 through 25 have been added to Section IV.
III. AFFECTED TECHNICAL SPECIFICATIONS
- 1) 3.1.1.1 Shutdown Margin - Tavg > 200°F
- 2) 3.1.1.2 Shutdown Margin - Tavg 200°F
- 3) 3.1.1.4 Moderator Temperature Coefficient
- 4) 3.1.3.1 CEA Position
- 5) 3.1.3.6 Regulating and Group P CEA Insertion Limits
- 6) 3.2.1 Linear Heat Rate
- 7) 3.2.3 Azimuthal Power Tilt - Tq
- 8) 3.2.4 DNBR Margin
- 9) 3.2.7 Axial Shape Index 3
ANO2-NE-08-00002 Revision 0 IV. APPROVED METHODOLOGIES USED TO DETERMINE LIMITS Provided below are the analytical methods used to determine the core operating limits addressed by the individual Technical Specifications. These methods have been reviewed and approved by the NRC.
- 1) Qualification of the PHOENIX-P / ANC Nuclear Design System for Pressurized Water Reactor Cores, (WCAP-11596-P-A), June 1988, ANC: A Westinghouse Advanced Nodal Computer Code (WCAP-10965-P-A), September 1986, and ANC: A Westinghouse Advanced Nodal Computer Code: Enhancements to ANC Rod Power Recovery (WCAP-10965-P-A, Addendum 1), April 1989 (Methodology for Specification 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.6; and 3.2.4.b)
- 2) CE Method for Control Element Assembly Ejection Analysis, CENPD-0190-A, January 1976 (Methodology for Specification 3.1.3.6 and 3.2.3)
- 3) Modified Statistical Combination of Uncertainties, CEN-356(V)-P-A, Revision 01-P-A, May 1988 (Methodology for 3.2.4.c, 3.2.4.d and 3.2.7)
- 4) Calculative Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, August 1974 (Methodology for 3.1.1.4, 3.2.1, 3.2.3 and 3.2.7)
- 5) Calculational Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 1, February 1975 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
- 6) Calculational Methods for the CE Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 2-P, July 1975 (Methodology for 3.1.1.4, 3.2.1, 3.2.3 and 3.2.7)
- 7) Calculative Methods for the CE Large Break LOCA Evaluation Model for the Analysis of CE and W Designed NSSS, CEN-132, Supplement 3-P-A, June 1985 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
- 8) Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model, CENPD-132-P, Supplement 4-P-A, Revision 1, December 2000 (Methodology for 3.1.1.4, 3.2.1; 3.2.3 and 3.2.7)
- 9) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137-P, August 1974 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
- 10) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137, Supplement 1-P, January 1977 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
- 11) Calculative Methods for the CE Small Break LOCA Evaluation Model, CENPD-137, Supplement 2-P-A, April 1998 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
- 12) CESEC-Digital Simulation of a Combustion Engineering Nuclear Steam Supply System, December 1981 (Methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.1, 3.1.3.6, and 3.2.4.b)
- 13) Technical Manual for the CENTS Code, CENPD 282-P-A, February 1991 (Methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.1, 3.1.3.6, 3.2.4.b) 4
ANO2-NE-08-00002 Revision 0
- 14) Implementation of ZIRLO Material Cladding in CE Nuclear Power Fuel Assembly Designs, CENPD-404-P-A, November 2001 (Modifies CENPD-132-P and CENPD-137-P as methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
- 15) Qualification of the Two-Dimensional Transport Code PARAGON, WCAP-16045-P-A, August 2004 (May be used as a replacement for the PHOENIX-P lattice code as methodology for 3.1.1.1, 3.1.1.2, 3.1.1.4, 3.1.3.6, and 3.2.4.b)
- 16) Implementation of Zirconium Diboride Burnable Absorber Coatings in CE Nuclear Power Fuel Assembly Designs, WCAP-16072-P-A, August 2004 (Methodology for 3.1.1.4, 3.2.1, 3.2.3, and 3.2.7)
- 17) Letter: O.D. Parr (NRC) to F.M. Stern (CE) dated June 13, 1975 (NRC Staff Review of Combustion Engineering ECCS Evaluation Model). NRC approval for items 4, 5 and 9 methodologies
- 18) Letter: O. D. Parr (NRC) to A.E. Scherer (CE), dated December 9, 1975 (NRC Staff Review of the Proposed Combustion Engineering ECCS Evaluation Model changes). NRC approval for item 6 methodology
- 19) Letter: K.Kniel (NRC) to A. E. Scherer (CE), dated September 27, 1977 (Evaluation of Topical Reports CENPD-133, Supplement 3-P and CENPD-137, Supplement 1-P). NRC approval for item 10 methodology
- 20) Letter: 2CNA038403, dated March 20, 1984, J.R. Miller (NRC) to J.M. Griffin (AP&L),
CESEC Code Verification. NRC approval for item 12 methodology
- 21) CE 16 x 16 Next Generation Fuel Core Reference Report, WCAP-16500-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR)
WCAP-16500-P, Revision 0, CE [Combustion Engineering] 16 x 16 Next Generation
[(NGF)] Core Reference Report, (Methodology for Specification 3.1.1.4 Moderator Temperature Coefficient (MTC), 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin, and 3.2.7 for ASI)
- 22) Optimized ZIRLOTM, WCAP-12610-P-A and CENPD-404-P-A Addendum 1-A, (Methodology for Specification 3.1.1.4 for MTC, 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Tilt, and 3.2.7 for ASI)
- 23) Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, WCAP-16523-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR), WCAP-16523-P, Westinghouse Correlations WSSV and WSSV-T for Predicting Critical Heat Flux in Rod Bundles with Side-Supported Mixing Vanes, (Methodology for 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI)
- 24) ABB Critical Heat Flux Correlations for PWR Fuel, CENPD-387-P-A (Methodology for Specifications 3.2.4.b, 3.2.4.c, and 3.2.4.d for DNBR Margin and 3.2.7 for ASI) 5
ANO2-NE-08-00002 Revision 0
- 25) Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model -
Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood, CENPD-132, Supplement 4-P-A, Addendum 1-P and Final Safety Evaluation for Westinghouse Electric Company (Westinghouse) Topical Report (TR)
CENPD-132, Supplement 4-P-A, Addendum 1-P, Calculative Methods for the CE Nuclear Power Large Break LOCA Evaluation Model - Improvement to 1999 Large Break LOCA EM Steam Cooling Model for Less Than 1 in/sec Core Reflood, (Methodology for Specification 3.1.1.4 Moderator Temperature Coefficient (MTC), 3.2.1 for Linear Heat Rate, 3.2.3 for Azimuthal Power Tilt, and 3.2.7 for ASI)
V. CORE OPERATING LIMITS The cycle-specific operating limits for the specifications listed are presented below.
- 1) 3/4.1.1.1 - SHUTDOWN MARGIN- Tavg > 200°F The SHUTDOWN MARGIN shall be greater than or equal to 5.0 % k/k in Modes 1, 2, 3, and 4.
- 2) 3/4.1.1.2 - SHUTDOWN MARGIN - Tavg 200°F The SHUTDOWN MARGIN shall be greater than or equal to 5.0% k/k in Mode 5.
- 3) 3.1.1.4 - MODERATOR TEMPERATURE COEFFICIENT The Moderator Temperature Coefficient (MTC) shall be in accordance with Figure 1. The Beginning of Cycle (BOC) positive COLR MTC limit line of Figure 1 is from BOC to 140.0 EFPD. From 400.0 EFPD to End of Cycle (EOC) the positive COLR MTC limit line is linear from an MTC of 0.0 E-4 k/k/°F at 0% power to an MTC of -1.0 E-4 k/k/°F at 100% power, which is bounded by the BOC positive MTC limit. Between 140.0 EFPD and 400.0 EFPD the positive MTC limit may be interpolated linearly with burnup.
- 4) 3.1.3.1 - CEA POSITION With one or more CEAs trippable but misaligned from any other CEAs in its group by more than the Technical Specification 3.1.3.1 allowed value, the minimum required core power reduction for Modes 1 and 2 is specified in Figure 2.
- 5) 3.1.3.6 - REGULATING CEA INSERTION LIMITS The regulating CEA groups and Group P shall be limited to the withdrawal and insertion limits shown on Figure 3. Figure 3 assumes that Groups 1 through 5 are maintained at or above the Programmed Insertion Limit.
- 6) 3/4.2.1 - LINEAR HEAT RATE With COLSS out of service, the linear heat rate shall be maintained 13.7 kW/ft.
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ANO2-NE-08-00002 Revision 0
- 7) 3.2.3 - AZIMUTHAL POWER TILT- Tq The measured AZIMUTHAL POWER TILT shall be maintained 0.03.
- 8) 3/4.2.4 - DNBR MARGIN The DNBR limit shall be maintained by one of the following methods:
a) With COLSS in service and neither CEAC operable - Maintain COLSS calculated core power less than or equal to COLSS calculated core power operating limit based on DNBR decreased by 10%.
b) With COLSS out of service and at least one CEAC operable - Operate within the Region of Acceptable Operation shown on Figure 4, using any operable CPC channel.
c) With COLSS out of service and neither CEAC operable - Operate within the Region of Acceptable Operation shown on Figure 5, using any operable CPC channel.
- 9) 3.2.7 - AXIAL SHAPE INDEX The core average AXIAL SHAPE INDEX (ASI) shall be maintained within the following limits:
a) COLSS IN SERVICE
- 0.27 ASI + 0.27 b) COLSS OUT OF SERVICE (CPC)
- 0.20 ASI + 0.20 VI. LIST OF FIGURES Figure 1 Moderator Temperature Coefficient Figure 2 Required Power Reduction After Inward CEA Deviation Figure 3 CEA Insertion Limits Versus Thermal Power Figure 4 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, CEAC Operable)
Figure 5 DNBR Margin Operating Limit Based on Core Protection Calculators (COLSS Out of Service, Both CEACs Inoperable) 7
ANO2-NE-08-00002 Revision 0 FIGURE 1 Moderator Temperature Coefficient 5.00E-05 (0, 0.50)
Unacceptable Operating Region 0.00E+00 (20, 0.32)
(50, 0.05)
(60, 0.00)
(100, -0.20)
-5.00E-05
-1.00E-04 MTC (Delta K/K/Degree F)
-1.50E-04 Acceptable Operating Region
-2.00E-04
-2.50E-04
-3.00E-04
-3.50E-04
-3.80 E-04 Unacceptable Operating Region
-4.00E-04 0 10 20 30 40 50 60 70 80 90 100 Core Power (% of Rated Thermal Power)
Note:
Per Technical Specification 3.1.1.4.a. and b., the Moderator Temperature Coefficient (MTC) maximum upper design limit shall be less positive than +0.5 x 10-4 k/k/°F whenever THERMAL POWER is 70% of RATED THERMAL POWER and less positive than 0.0 x 10-4 k/k/°F whenever THERMAL POWER is > 70% of RATED THERMAL POWER. Therefore, the actual MTC must be less than the COLR upper limit at zero power. At all other powers, the actual MTC may be equal to the COLR upper limit.
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ANO2-NE-08-00002 Revision 0 FIGURE 2 REQUIRED POWER REDUCTION AFTER INWARD CEA DEVIATION*
30 (28% @ 120 min.)
25 Minimum Required Power Reduction (% of Rated Power) 20 15 10 5
0 0 15 30 45 60 75 90 105 120 Time After Deviation (minutes)
- When core power is reduced to 60% of rated power per this limit curve, further reduction is not required 9
ANO2-NE-08-00002 Revision 0 FIGURE 3 CEA INSERTION LIMITS VERSUS THERMAL POWER 150 150 GROUP P PDIL GROUP 6 PDIL 135 135 (74, 135)
Transient Insertion Limit Transient Insertion Limit 120 120 (100, 112.5)
Group P CEA Position, Inches Withdrawn Group 6 CEA Position, Inches Withdrawn (65, 112.5) 105 105 Long Term Long Term 90 Steady State SHUTDOWN 90 Steady State Actions Apply MARGIN NOT Actions Apply SATISFIED 75 75 60 (44, 60) 60 (82.5, 60)
Short Term Steady State Short Term 45 Actions Apply 45 Steady State Actions Apply 30 30 SHUTDOWN SHUTDOWN 15 MARGIN NOT 15 MARGIN NOT SATISFIED SATISFIED (20, 0) (62.5, 0) 0 0 0 10 20 30 40 50 60 70 80 90 100 0 10 20 30 40 50 60 70 80 90 100 Power (%) Power (%)
Note: Regulating Groups 1 through 5 at or above Programmed Insertion Limit 10
ANO2-NE-08-00002 Revision 0 FIGURE 4 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Lines Minimum One CEAC Operable 3.0 ACCEPTABLE OPERATION 2.9 Any Power Level (0.04, 2.83)
(0.20, 2.83) 2.8 2.7 2.6 ACCEPTABLE OPERATION
(-0.20, 2.58) Power at or above 80%
2.5
(-0.09, 2.41) 2.4 (0.20, 2.41)
D N (-0.20, 2.31)
B 2.3 R ACCEPTABLE OPERATION 2.2 Power at or above 90%
2.1
(-0.10, 1.99) 2.0 (0.20, 1.99)
(-0.20, 1.94) 1.9 1.8 UNACCEPTABLE OPERATION 1.7 Any Power Level 1.6
-0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 CPC Indicated ASI NOTE: DNBR greater than that indicated at the top of the figure is acceptable, provided the indicated ASI limits remain between the bounds that are shown for lower DNBR.
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ANO2-NE-08-00002 Revision 0 FIGURE 5 DNBR MARGIN OPERATING LIMIT BASED ON CORE PROTECTION CALCULATORS ANO-2 Cycle Independent COLSS OOS Limit Both CEACs Inoperable 4.2 4.1 4.0 ACCEPTABLE OPERATION Any Power Level 3.9 3.8 3.7 3.6 D
N (0.00, 3.48)
B 3.5 (0.20, 3.48)
R 3.4 3.3 UNACCEPTABLE OPERATION Any Power Level 3.2
(-0.20, 3.20) 3.1 3.0
-0.3 -0.2 -0.1 0.0 0.1 0.2 0.3 CPC Indicated ASI NOTE: DNBR greater than that indicated at the top of the figure is acceptable, provided the indicated ASI limits remain between the bounds that are shown for lower DNBR.
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