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Category:Annual Operating Report
MONTHYEARAEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report AEP-NRC-2021-50, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2021-08-25025 August 2021 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2021-27, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report AEP-NRC-2020-58, Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2020-08-26026 August 2020 Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2020-29, Submittal of Annual Radiological Environmental Operating Report2020-05-14014 May 2020 Submittal of Annual Radiological Environmental Operating Report AEP-NRC-2019-43, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2019-08-29029 August 2019 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2019-16, Annual Radiological Environmental Operating Report2019-04-29029 April 2019 Annual Radiological Environmental Operating Report AEP-NRC-2018-62, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2018-08-21021 August 2018 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes ML18123A3482018-04-30030 April 2018 Donald C. Cook, Units 1 and 2, Submittal of 2017 Annual Radioactive Effluent Release Report AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual2018-04-30030 April 2018 Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual AEP-NRC-2017-47, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2017-08-30030 August 2017 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes AEP-NRC-2016-73, Submittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2016-08-26026 August 2016 Submittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2013-32, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2013-08-30030 August 2013 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2012-69, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2012-08-31031 August 2012 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2012-22, Annual Radiological Environmental Operating Report for 20112012-05-0909 May 2012 Annual Radiological Environmental Operating Report for 2011 AEP-NRC-2011-32, Annual Radiological Environmental Operating Report2011-05-13013 May 2011 Annual Radiological Environmental Operating Report AEP-NRC-2011-27, Annual Radioactive Effluent Release Report, January 1, 2010, Through December 31, 20102011-04-29029 April 2011 Annual Radioactive Effluent Release Report, January 1, 2010, Through December 31, 2010 AEP-NRC-2010-37, Submittal of 2009 Annual Environmental Operating Report2010-04-30030 April 2010 Submittal of 2009 Annual Environmental Operating Report AEP-NRC-2009-54, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2009-08-28028 August 2009 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2009-29, Submittal of Annual Radioactive Effluent Release Report for 20082009-04-29029 April 2009 Submittal of Annual Radioactive Effluent Release Report for 2008 ML0913405232009-04-29029 April 2009 Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Cover Through Appendix Iv AEP-NRC-2009-32, Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Appendix V Through End2009-04-29029 April 2009 Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Appendix V Through End AEP-NRC-2008-27, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2008-08-29029 August 2008 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML0506302372005-02-25025 February 2005 2004 Annual Operating Report ML0425300392004-08-26026 August 2004 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML0407009102004-03-0101 March 2004 Transmittal of 2003 Annual Operating Report ML0313606492003-04-30030 April 2003 Annual Environmental Operating Report ML0312606062003-04-30030 April 2003 Annual Radiological Environmental Operating Report, Appendix D and E, Pages D-101 Through E-3 ML0312606482003-04-30030 April 2003 Annual Radiological Environmental Operating Report, Table of Contents Through Appendix D, Pages D-1 - 100 GNRO-2003/00026, South Mississippi Electric Power Association (Smep) Annual Report for 20022003-04-28028 April 2003 South Mississippi Electric Power Association (Smep) Annual Report for 2002 ML0307005302003-02-28028 February 2003 Annual Operating Report ML0214202912002-04-25025 April 2002 Part a - Donald C. Cook Nuclear Plant, Units 1 & 2 - Annual Environmental Operating Report ML0213002702002-04-25025 April 2002 Part B - Donald C. Cook Nuclear Plant, Units 1 & 2 - Annual Environmental Operating Report ML0206001322002-02-26026 February 2002 Annual Operating Report for Donald C. Cook Nuclear Plant, Units 1 & 2 for 2001 2023-08-29
[Table view] Category:Environmental Monitoring Report
MONTHYEARAEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report AEP-NRC-2022-35, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2022-08-18018 August 2022 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2022-29, Annual Radiological Environmental Operating Report for 20212022-05-13013 May 2022 Annual Radiological Environmental Operating Report for 2021 AEP-NRC-2022-28, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report AEP-NRC-2021-66, 2020 Annual Radioactive Effluent Release Report Correction2021-11-17017 November 2021 2020 Annual Radioactive Effluent Release Report Correction AEP-NRC-2021-50, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2021-08-25025 August 2021 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2021-32, Annual Radiological Environmental Operating Report2021-05-12012 May 2021 Annual Radiological Environmental Operating Report AEP-NRC-2021-27, Annual Radioactive Effluent Release Report2021-04-28028 April 2021 Annual Radioactive Effluent Release Report AEP-NRC-2020-29, Submittal of Annual Radiological Environmental Operating Report2020-05-14014 May 2020 Submittal of Annual Radiological Environmental Operating Report ML20132A2022020-04-29029 April 2020 Annual Radioactive Effluent Release Report Including Off-site Dose Calculation Manual Changes AEP-NRC-2020-35, Submittal of 2019 Annual Radioactive Effluent Release Report2020-04-29029 April 2020 Submittal of 2019 Annual Radioactive Effluent Release Report AEP-NRC-2019-16, Annual Radiological Environmental Operating Report2019-04-29029 April 2019 Annual Radiological Environmental Operating Report AEP-NRC-2019-19, 2018 Annual Radioactive Effluent Release Report2019-04-29029 April 2019 2018 Annual Radioactive Effluent Release Report ML18137A2032018-05-15015 May 2018 Annual Radiological Environmental Operating Report for 2017 AEP-NRC-2018-35, Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual2018-04-30030 April 2018 Annual Radioactive Effluent Release Report - Off-Site Dose Calculation Manual ML18123A3482018-04-30030 April 2018 Donald C. Cook, Units 1 and 2, Submittal of 2017 Annual Radioactive Effluent Release Report AEP-NRC-2017-24, Submittal of Annual Radiological Environmental Operating Report2017-05-0808 May 2017 Submittal of Annual Radiological Environmental Operating Report AEP-NRC-2017-23, Annual Radioactive Effluent Release Report2017-04-26026 April 2017 Annual Radioactive Effluent Release Report ML17146A0772017-03-22022 March 2017 EP-CALC-CNP-1601, Rev 2, Radiological Effluent EAL Threshold Values. AEP-NRC-2016-87, Unit 2 - Mitigating Strategies Flood Hazard Assessment2016-12-15015 December 2016 Unit 2 - Mitigating Strategies Flood Hazard Assessment AEP-NRC-2017-02, EP-CALC-CNP-1602, Rev. 0, Containment Radiation EAL Threshold Values.2016-10-0707 October 2016 EP-CALC-CNP-1602, Rev. 0, Containment Radiation EAL Threshold Values. AEP-NRC-2016-40, Annual Radiological Environmental Operating Report for 20152016-05-13013 May 2016 Annual Radiological Environmental Operating Report for 2015 AEP-NRC-2016-32, Annual Radioactive Effluent Release Report for 20152016-04-28028 April 2016 Annual Radioactive Effluent Release Report for 2015 AEP-NRC-2015-30, Annual Radiological Environmental Operating Report for Period January 1, 2014, Through December 31, 20142015-05-11011 May 2015 Annual Radiological Environmental Operating Report for Period January 1, 2014, Through December 31, 2014 AEP-NRC-2015-34, 2014 Annual Radioactive Effluent Release Report2015-04-28028 April 2015 2014 Annual Radioactive Effluent Release Report AEP-NRC-2014-34, Annual Radiological Environmental Operating Report2014-05-13013 May 2014 Annual Radiological Environmental Operating Report AEP-NRC-2014-30, Annual Radioactive Effluent Release Report for 20132014-04-29029 April 2014 Annual Radioactive Effluent Release Report for 2013 ML13135A0472013-05-10010 May 2013 Submittal of Annual Radiological Environmental Operating Report AEP-NRC-2013-25, Annual Radioactive Effluent Release Report2013-04-29029 April 2013 Annual Radioactive Effluent Release Report AEP-NRC-2012-22, Annual Radiological Environmental Operating Report for 20112012-05-0909 May 2012 Annual Radiological Environmental Operating Report for 2011 AEP-NRC-2011-32, Annual Radiological Environmental Operating Report2011-05-13013 May 2011 Annual Radiological Environmental Operating Report AEP-NRC-2010-40, Annual Radiological Environmental Operating Report2010-05-14014 May 2010 Annual Radiological Environmental Operating Report AEP-NRC-2010-37, Submittal of 2009 Annual Environmental Operating Report2010-04-30030 April 2010 Submittal of 2009 Annual Environmental Operating Report AEP-NRC-2010-38, Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 20092010-04-29029 April 2010 Annual Radioactive Effluent Release Report, January 1, 2009, Through December 31, 2009 AEP-NRC-2009-77, Submittal of Renewed National Pollutant Discharge Elimination System Permit, MI00058272009-10-29029 October 2009 Submittal of Renewed National Pollutant Discharge Elimination System Permit, MI0005827 AEP-NRC-2009-34, 2008 Annual Radiological Environmental Operating Report2009-05-15015 May 2009 2008 Annual Radiological Environmental Operating Report AEP-NRC-2009-41, Submittal of Retraction of Notification of National Pollutant Discharge Elimination System Permit MI0005827 Exceedence2009-05-0606 May 2009 Submittal of Retraction of Notification of National Pollutant Discharge Elimination System Permit MI0005827 Exceedence AEP-NRC-2009-29, Submittal of Annual Radioactive Effluent Release Report for 20082009-04-29029 April 2009 Submittal of Annual Radioactive Effluent Release Report for 2008 ML0913405232009-04-29029 April 2009 Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Cover Through Appendix Iv AEP-NRC-2009-32, Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Appendix V Through End2009-04-29029 April 2009 Enclosure to AEP-NRC-2009-32 - Donald C. Cook, Units 1 and 2 - 2008 Annual Environmental Operating Report, Appendix V Through End ML0903502102009-01-14014 January 2009 License Amendment Request to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environmental Protection Plan ML1017501492008-12-0101 December 2008 Indiana Michigan Power D. C. Cook Nuclear Plant Groundwater Discharge Authorization Application for the Disposal of Wastewater to the Ground or Groundwater ML1017501502008-12-0101 December 2008 Indiana Michigan Power D. C. Cook Nuclear Plant Groundwater Discharge Authorization Application for the Disposal of Wastewater to the Ground or Groundwater ML0814301012008-05-14014 May 2008 Annual Radiological Environmental Operating Report for the Period January 1, 2007 Though December 31, 2007 ML0814804212008-04-29029 April 2008 Annual Environmental Operating Report for the Period January 1, 2007 Through December 31, 2007 ML0809203912008-03-28028 March 2008 Submittal of Annual Radioactive Effluent Release Report, January 1, 2007, Through December 31, 2007. Cover Through A2.4-8 ML0809203932008-03-28028 March 2008 Submittal of Annual Radioactive Effluent Release Report, January 1, 2007, Through December 31, 2007. Pages A3.0-1, Off-Site Dose Calculation Manual, PMP-6010-OSD-001, Revision 22 Through End ML0714305092007-05-14014 May 2007 Annual Radiological Environmental Operating Report for Period from January 1, 2006 Through December 31, 2006 ML0614500412006-05-12012 May 2006 Annual Radiological Environmental Operating Report ML0613501282006-04-28028 April 2006 Annual Environmental Operating Report for 2005 2023-05-15
[Table view] Category:Letter type:AEP
MONTHYEARAEP-NRC-2024-01, Emergency Plan Revision 482024-01-0808 January 2024 Emergency Plan Revision 48 AEP-NRC-2023-56, Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor2023-12-20020 December 2023 Report Per Technical Specification 5.6.6 for Inoperability of Unit 1 Post Accident Monitoring Reactor Coolant (Loop 3 Cold Leg) Wide Range Temperature Recorder Thermal Sensor AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2023-34, Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation2023-08-0202 August 2023 Supplement to Request for Approval of Change Regarding Neutron Flux Instrumentation AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report AEP-NRC-2023-32, Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations2023-06-0606 June 2023 Response to NRC Regulatory Issue Summary 2023-1 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2023-33, Renewable Operating Permit2023-06-0505 June 2023 Renewable Operating Permit AEP-NRC-2023-30, Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump2023-06-0101 June 2023 Follow-Up Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-27, Annual Radiological Environmental Operating Report2023-05-15015 May 2023 Annual Radiological Environmental Operating Report AEP-NRC-2023-19, Annual Radioactive Effluent Release Report2023-04-30030 April 2023 Annual Radioactive Effluent Release Report AEP-NRC-2023-23, Annual Report of Individual Monitoring for 20222023-04-24024 April 2023 Annual Report of Individual Monitoring for 2022 AEP-NRC-2023-24, Notification of Ph Non-Compliance for Turbine Room Sump2023-04-12012 April 2023 Notification of Ph Non-Compliance for Turbine Room Sump AEP-NRC-2023-20, Annual Report of Property Insurance2023-04-0303 April 2023 Annual Report of Property Insurance AEP-NRC-2023-15, Decommissioning Funding Status Report2023-03-28028 March 2023 Decommissioning Funding Status Report AEP-NRC-2023-11, Form OAR-1, Owner'S Activity Report2023-01-31031 January 2023 Form OAR-1, Owner'S Activity Report AEP-NRC-2023-02, Request for Approval of Change Regarding Neutron Flux Instrumentation2023-01-26026 January 2023 Request for Approval of Change Regarding Neutron Flux Instrumentation AEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in AEP-NRC-2022-61, Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-062022-10-24024 October 2022 Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-06 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2022-56, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2022-10-12012 October 2022 Unit 2 - Transmittal of Report of Changes to the Emergency Plan AEP-NRC-2022-30, Core Operating Limits Report2022-10-0606 October 2022 Core Operating Limits Report AEP-NRC-2022-51, Evacuation Time Estimate Analysis2022-08-31031 August 2022 Evacuation Time Estimate Analysis AEP-NRC-2022-50, Form OAR-1, Owner'S Activity Report2022-08-25025 August 2022 Form OAR-1, Owner'S Activity Report AEP-NRC-2022-35, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2022-08-18018 August 2022 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2022-47, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan, Revision 472022-08-0202 August 2022 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan, Revision 47 AEP-NRC-2022-42, Unit 2 Updated Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements2022-07-18018 July 2022 Unit 2 Updated Steam Generator Tube Inspection Report to Reflect TSTF-577 Reporting Requirements AEP-NRC-2022-29, Annual Radiological Environmental Operating Report for 20212022-05-13013 May 2022 Annual Radiological Environmental Operating Report for 2021 AEP-NRC-2022-15, CFR 72.48(d)(2) Summary Report of 10 CFR 72.48 Evaluations2022-05-0404 May 2022 CFR 72.48(d)(2) Summary Report of 10 CFR 72.48 Evaluations AEP-NRC-2022-28, 2021 Annual Radioactive Effluent Release Report2022-04-29029 April 2022 2021 Annual Radioactive Effluent Release Report AEP-NRC-2022-27, Annual Report of Individual Monitoring2022-04-27027 April 2022 Annual Report of Individual Monitoring AEP-NRC-2022-05, Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements2022-04-0707 April 2022 Application to Revise Technical Specifications to Adopt TSTF-554, Revision 1, Revise Reactor Coolant Leakage Requirements AEP-NRC-2022-18, Annual Report of Property Insurance2022-03-28028 March 2022 Annual Report of Property Insurance AEP-NRC-2022-20, Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations2022-03-14014 March 2022 Response to NRC Regulatory Issue Summary 2022-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2022-12, Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source2022-03-0202 March 2022 Commitment Schedule Change Related to Seismic PRA Distributed Ignition Backup Power Source AEP-NRC-2022-02, Unit 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-5, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2022-02-0101 February 2022 Unit 2 - Supplement to Application to Revise Technical Specifications to Adopt TSTF-5, Revision 1, Revised Frequencies for Steam Generator Tube Inspections AEP-NRC-2022-01, Quality Assurance Program Change Request for Internal Audit Frequency2022-02-0101 February 2022 Quality Assurance Program Change Request for Internal Audit Frequency AEP-NRC-2022-03, Final Supplemental Response to NRC Generic Letter 2004-022022-01-20020 January 2022 Final Supplemental Response to NRC Generic Letter 2004-02 AEP-NRC-2021-68, Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation2021-12-16016 December 2021 Response to Request for Additional Information on Requested Change Regarding Containment Water Level Instrumentation AEP-NRC-2021-67, Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation2021-12-0909 December 2021 Unit 2 - Decommissioning Funding Plan for Independent Spent Fuel Storage Installation AEP-NRC-2021-66, 2020 Annual Radioactive Effluent Release Report Correction2021-11-17017 November 2021 2020 Annual Radioactive Effluent Release Report Correction AEP-NRC-2021-65, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2021-11-0808 November 2021 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-47, Unit 2 - Application to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections2021-11-0808 November 2021 Unit 2 - Application to Revise Technical Specifications to Adopt TSTF-577, Revision 1, Revised Frequencies for Steam Generator Tube Inspections AEP-NRC-2021-60, Registration of Dry Spent Fuel Storage Cask2021-10-12012 October 2021 Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-55, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2021-09-20020 September 2021 Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-48, Cycle 26 Core Operating Limits Report, Revision 02021-09-14014 September 2021 Cycle 26 Core Operating Limits Report, Revision 0 AEP-NRC-2021-53, Registration of Dry Spent Fuel Storage Cask2021-08-26026 August 2021 Registration of Dry Spent Fuel Storage Cask AEP-NRC-2021-50, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2021-08-25025 August 2021 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report2021-08-12012 August 2021 Form OAR-1, Owner'S Activity Report 2024-01-08
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t:m INDIANA Indiana Michigan Power MICHIGAN Cook Nuclear Plant POWER* One Cook Place Bridgman, Ml 49106 A unit ofAmerican Electric Power lndianaMichiganPower.com August 25, 2021 AEP-NRC-2021-50 10 CFR 50.46 Docket Nos.: 50-315 50-316 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001 Donald C. Cook Nuclear Plant Units 1 and 2 ANNUAL REPORT OF LOSS-OF-COOLANT ACCIDENT EVALUATION MODEL CHANGES Pursuant to 10 CFR 50.46, Indiana Michigan Power Company (l&M), the licensee for Donald C. Cook Nuclear Plant (CNP), is transmitting an annual report of loss-of-coolant accident (LOCA) evaluation model changes affecting the peak cladding temperature (PCT) for CNP Units 1 and 2. l&M is providing, as Enclosure to this letter, the Units 1 and 2 Large Break and Small Break LOCA Analyses-of-Record PCT values and error assessments for calendar year 2020.
There are no new or revised commitments in this letter. Should you have any questions, please contact me at (269) 466-2649.
Michael K. Scarpello Regulatory Affairs Director JMT/mll
Enclosure:
Donald C. Cook Nuclear Plant Units 1 and 2, Large and Small Break Loss-of-Coolant Accident Peak Clad Temperature Summary
U.S. Nuclear Regulatory Commission AEP-NRC-2021-50 Page 2 c: R. J. Ancona - MPSC EGLE - RMD/RPS J.B. Giessner- NRC Region Ill NRC Resident Inspector R. M. Sistevaris - AEP Ft. Wayne J.E. Walcutt-AEP Ft. Wayne S. P. Wall - NRC Washington, D.C.
A. J. Williamson-AEP Ft. Wayne, w/o enclosures
ENCLOSURE TO AEP-NRC-2021-50 DONALD C. COOK NUCLEAR PLANT UNITS 1 AND 2 LARGE AND SMALL BREAK LOSS-OF-COOLANT ACCIDENT PEAK CLAD TEMPERATURE
SUMMARY
Abbreviations:
10CFR Title 10 of the Code of Federal Regulations ADAMS Agencywide Documents Access and Management System CNP Donald C. Cook Nuclear Plant OF degrees Fahrenheit ECCS emergency core cooling system EM evaluation methodology FdH nuclear enthalpy rise hot channel factor Fa heat flux hot channel factor HHSI high head safety injection (Safety Injection System at CNP) l&M Indiana Michigan Power Company LB large break LOCA loss of coolant accident NOP/NOT normal operating pressure/normal operating temperature NRC Nuclear Regulatory Commission PBOT/PMID power integrals in the bottom-third/middle-third PCT peak cladding temperature RHR residual heat removal SGTP steam generator tube plugging SB small break TCD thermal conductivity degradation Summary:
By letter dated March 19, 2012, (ADAMS Accession No. ML12088A104), and supplemented by letter dated June 11, 2012, (ADAMS Accession No. ML12173A025), l&M, the licensee for CNP Units 1 and 2, submitted a report describing the impact of fuel pellet TCD on the LB LOCA ECCS evaluation model, and an estimate of the effect on the predicted PCT for CNP Units 1 and 2. This report was submitted pursuant to 10 CFR Part 50, Section 50.46, Paragraph (a)(3),
and referred to a letter from Westinghouse Electric Company dated March 7, 2012, (ADAMS Accession No. ML12072A035). The report was subsequently found to be acceptable by NRC letter dated March 7, 2013, (ADAMS Accession No. ML13077A137).
By Westinghouse letter LTR-LIS-13-360, "D. C. Cook Units 1 and 2 10 CFR 50.46 Report for Revised Heat Transfer Multiplier Distributions," dated July 31, 2013, Westinghouse Electric Company notified l&M of significant errors in the EM for the LB LOCA analysis of record for CNP Unit 1. In a subsequent letter, LTR-LIS-13-406, "Additional Information on the Evaluation of Revised Heat Transfer Multiplier Distributions," dated August 14, 2013, Westinghouse Electric Company provided l&M additional detail on the nature of the errors and the corrections
Enclosure to AEP-NRC-2021-50 Page2 made. Pursuant to 10 CFR Part 50, Section 50.46, Paragraph (a)(3), by letter dated August 30, 2013, l&M submitted a report to the NRC describing the impact of Revised Heat Transfer Multiplier Distributions on the predicted PCT for CNP Unit 1 (ADAMS Accession No. ML13247A174). As documented in the subsequent rack-up sheets, the error results in a benefit to the calculated PCT.
By Westinghouse letter LTR-LIS-14-44, "D. C. Cook Units 1 and 2 10 CFR 50.46 Report for the HOTSPOT Burst Strain Error Correction," dated January 29, 2014, Westinghouse Electric Company notified l&M of significant errors in the EM for the LB LOCA analysis of record for CNP Unit 1. Pursuant to 10 CFR Part 50, Section 50.46, Paragraph (a)(3), by letter dated February 27, 2014, l&M submitted a report to the NRC describing the impact of an Error in Burst Strain Application on the predicted PCT for CNP Unit 1 (ADAMS Accession No. ML14063A043).
By letter dated May 20, 2016, (ADAMS Accession No. ML16145A291), l&M submitted a report of significant changes to the ECCS EM as a result of CNP Unit 1 returning to NOP/NOT. This report was submitted pursuant to 10 CFR Part 50, Section 50.46.
By letter dated May 4, 2018, (ADAMS Accession No.ML18130A580), l&M submitted a report of a significant change in calculated PCT for the CNP Unit 2 SB LOCA analysis as a result of the reactor vessel upflow conversion modification. This report was submitted pursuant to 10 CFR Part 50, Section 50.46 within 30-days of reactor start-up.
By letter dated May 9, 2019, (ADAMS Accession No.ML19133A060), l&M submitted a report of a significant change in calculated PCT for the CNP Unit 1 SB LOCA analysis as a result of the reactor vessel upflow conversion modification. This report was submitted pursuant to 10 CFR Part 50, Section 50.46 within 30-days of reactor start-up.
The following pages summarize the impact of TCD, peaking factor burndown, heat transfer multiplier distribution revisions, error in burst strain application, decay group uncertainty factors errors, changes to grid blockage ratio and porosity (Unit 2 only), and plant modification evaluations on the CNP Units 1 and 2 LB LOCA analyses of record. Pages are included that also summarize the SB LOCA PCT analyses of record for CNP Units 1 and 2. In addition, the impact on the SB and LB LOCA PCT analyses of record from the upflow conversion in Units 1 and 2 is addressed.
Enclosure to AEP-NRC-2021-50 Page 3 CNP UNIT 1 LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Applicable to U1C29 Evaluation Model: ASTRUM (2004)
Fa=2.15 FdH = 1.55 SGTP = 10% Break Size: Split Analysis Date: November 2008 Notes: Post-Analysis evaluation for Fa of 2.09 and FdH of 1.53 LICENSING BASIS Analysis-of-Record PCT= 2128°F MARGIN ALLOCATIONS (Delta PCT)
A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. Return to NOP/NOT Including Pellet Thermal 404°F(a)
Conductivity Degradation and Peaking Factor Burndown
- 2. Revised Heat Transfer Multiplier Distributions for -91°F NOP/NOT Conditions
- 3. Error in Burst Strain Application 85°F
- 4. Decay Group Uncertainty Factors Errors -29°F B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Design Input Changes with Respect to Plant Operation -489°F(a) for Return to NOP/NOT Evaluation
- 2. Upflow Conversion 14°F C. NEW 10 CFR 50.46 ASSESSMENTS D. OTHER LICENSING BASIS PCT+ MARGIN ALLOCATIONS PCT= 2022°F Notes:
- a. These assessments are coupled via an evaluation of burnup effects which include thermal conductivity degradation, peaking factor burndown and design input changes.
Enclosure to AEP-NRC-2021-50 Page 4 CNP UNIT 1 LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Applicable to U1C30 Evaluation Model: ASTRUM (2004)
Fa=2.15 FdH = 1.55 SGTP = 10% Break Size: Split Analysis Date: November 2008 Notes: Post-Analysis evaluation for Fa of 2.09 and FdH of 1.53 LICENSING BASIS Analysis-of-Record PCT= 2128°F MARGIN ALLOCATIONS (Delta PCT)
A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. Return to NOP/NOT Including Pellet Thermal 404°F{a)
Conductivity Degradation and Peaking Factor Burndown
- 2. Revised Heat Transfer Multiplier Distributions for -91°F NOP/NOT Conditions
- 3. Error in Burst Strain Application 85°F
- 4. Decay Group Uncertainty Factors Errors -29°F B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Design Input Changes with Respect to Plant Operation -489°F{a) for Return to NOP/NOT Evaluation
- 2. Upflow Conversion 14°F
- 3. PBOT/PMID Evaluation for Cycle 30 0°F(b)
C. NEW 10 CFR 50.46 ASSESSMENTS D. OTHER LICENSING BASIS PCT+ MARGIN ALLOCATIONS PCT= 2022°F
Enclosure to AEP-NRC-2021-50 Page 5 Notes:
- a. These assessments are coupled via an evaluation of burnup effects which include thermal conductivity degradation, peaking factor burndown and design input changes.
- b. Normalized PBOT/PMID of the core were slightly exceeding limits used in the best estimate LB LOCA analysis of record. It was determined that expanding the PBOT/PMID box to include the Cycle 30 values is acceptable and the violations have a 0°F peak cladding temperature impact on the best estimate LB LOCA analysis of record.
Enclosure to AEP-NRC-2021-50 Page6 CNP UNIT 1 LOCA Peak Clad Temperature Summary for Appendix K Small Break Applicable to U1C29 and U1C30 Evaluation Model: NOTRUMP Fa=2.32 FdH=1.55 SGTP=10% 3.25 inch cold leg break Analysis Date: January 26, 2012 LICENSING BASIS Analysis-of-Record PCT= 1725°F MARGIN ALLOCATIONS (Delta PCT)
A. PREVIOUS 10 CFR 50.46 ASSESSMENTS B. PLANNED PLANT MODIFICATION EVALUATIONS 0°F
- 1. Upflow Conversion 107°F (a)
C. NEW 10 CFR 50.46 ASSESSMENTS D. OTHER LICENSING BASIS PCT+ MARGIN ALLOCATIONS PCT= 1832°F Notes:
- a. The evaluation resulted in a minor shift in limiting break size from 3.25 inches to 3.00 inches.
Enclosure to AEP-NRC-2021-50 Page 7 CNP UNIT 2 LOCA Peak Clad Temperature Summary for ASTRUM Best Estimate Large Break Evaluation Model: ASTRUM (2004)
Fa= 2.335 FdH = 1.644 SGTP = 10% Break Size: Split Analysis Date: February 11, 2009 Notes: Post-Analysis evaluation of 1.5% SGTP and FdH of 1.61 LICENSING BASIS Analysis-of-Record PCT= 2107°F MARGIN ALLOCATIONS (Delta PCT)
A. PREVIOUS 10 CFR 50.46 ASSESSMENTS
- 1. Evaluation of TCD and Peaking Factor Burndown 73°F(a)
- 2. Changes to Grid Blockage Ratio and Porosity 16°F
- 3. Revised Heat Transfer Multiplier Distributions -3°F
- 4. Error in Burst Strain Application 13°F B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Plant Evaluations associated with TCD -239°F(a)
- 2. Upflow Conversion 37°F
- c. NEW 10 CFR 50.46 ASSESSMENTS 0°F D. OTHER LICENSING BASIS PCT+ MARGIN ALLOCATIONS PCT= 2004°F Notes:
- a. These assessments are coupled via an evaluation of burnup effects which include thermal conductivity degradation, peaking factor burndown and design input changes.
Enclosure to AEP-NRC-2021-50 Page 8 CNP UNIT 2 LOCA Peak Clad Temperature Summary for Appendix K Small Break Evaluation Model: NOTRUMP Fa= 2.32 FdH = 1.62 SGTP = 10% 4 inch cold leg break Analysis Date: June 28, 2011 LICENSING BASIS Analysis-of-Record PCT= 1274°F (a)
MARGIN ALLOCATIONS (Delta PCT)
A. PREVIOUS 10 CFR 50.46 ASSESSMENTS B. PLANNED PLANT MODIFICATION EVALUATIONS
- 1. Upflow Conversion 75°F C. NEW 10 CFR 50.46 ASSESSMENTS 0°F D. OTHER LICENSING BASIS PCT+ MARGIN ALLOCATIONS PCT= 1349°F Notes:
- a. Analysis models RHR injection flow diversion to RHR spray and HHSI cross-tie valves open during cold leg recirculation.