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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
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARML22055A0012022-06-0808 June 2022 Issuance of Amendment No. 341 Updating the Reactor Coolant System Pressure Temperature Limits 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-2021-28, 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System2021-06-15015 June 2021 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System AEP-NRC-2021-24, Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation2021-03-23023 March 2021 Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation AEP-NRC-2020-72, License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2020-12-14014 December 2020 License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency ML20164A0452020-06-0808 June 2020 License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency ML20126G4552020-04-30030 April 2020 Application to Revise Technical Specifications to Adopt Tstf-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-04-30030 April 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System2020-04-0707 April 2020 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System AEP-NRC-2020-09, Unit 2, Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam, Supply to Turbine Driven Afw/Efw Pump Inoperable2020-04-0707 April 2020 Unit 2, Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam, Supply to Turbine Driven Afw/Efw Pump Inoperable AEP-NRC-2020-14, License Amendment Requests and Exemption Requests Regarding Changes to the Routine Reporting Requirements Subject to Plant Technical Specifications and 10 CFR 50.71(e)2020-04-0707 April 2020 License Amendment Requests and Exemption Requests Regarding Changes to the Routine Reporting Requirements Subject to Plant Technical Specifications and 10 CFR 50.71(e) AEP-NRC-2019-33, Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-4212019-08-27027 August 2019 Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-421 ML19134A3552019-07-11011 July 2019 Issuance of Amendments Technical Specification Task Force (TSTF) Traveler 563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program AEP-NRC-2019-18, License Amendment Request to Delete Technical Specification Surveillance Requirement 3.8.1.20, Regarding Diesel Generator Operation When Connected to Its Load Test Resistor Bank2019-06-27027 June 2019 License Amendment Request to Delete Technical Specification Surveillance Requirement 3.8.1.20, Regarding Diesel Generator Operation When Connected to Its Load Test Resistor Bank AEP-NRC-2019-05, License Amendment Request to Address Issues Identified in Westinghouse Document NSAL-15-12019-02-26026 February 2019 License Amendment Request to Address Issues Identified in Westinghouse Document NSAL-15-1 AEP-NRC-2019-01, Application to Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2019-02-26026 February 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. AEP-NRC-2018-72, Donald C. Cook. Nuclear Plant, Units 1 and 2 - License Amendment Request to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environmental Protection Plan2018-12-11011 December 2018 Donald C. Cook. Nuclear Plant, Units 1 and 2 - License Amendment Request to Revise Operating Licenses DPR-58 and DPR-74, Appendix B, Environmental Technical Specifications, Part II, Non-Radiological Environmental Protection Plan AEP-NRC-2018-10, Request for Deviation from National Fire Protection Association (NFPA) 805 Requirements2018-06-11011 June 2018 Request for Deviation from National Fire Protection Association (NFPA) 805 Requirements AEP-NRC-2018-02, Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-03-0707 March 2018 Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping AEP-NRC-2018-04, Supplement to License Amendment Request Regarding Revision to the Emergency Plan for Technical Support Center Relocation2018-01-19019 January 2018 Supplement to License Amendment Request Regarding Revision to the Emergency Plan for Technical Support Center Relocation ML18024A4472018-01-19019 January 2018 Enclosure 2 - Technical Support Center Loss of Coolant Accident Radiological Analysis ML17317A4712017-11-0707 November 2017 Evaluation of Proposed Change Regarding Revision to the Emergency Plan for Technical Support Center Relocation & Revised Pages to Emergency Plan AEP-NRC-2017-10, Request for Deviation from National Fire Protection Association (NFPA) 805 Requirements2017-11-0707 November 2017 Request for Deviation from National Fire Protection Association (NFPA) 805 Requirements ML17146A0752017-05-23023 May 2017 Donald C. Cook, Unit 1 and 2, License Amendment Request to Revise Emergency Action Levels ML17146A0762017-05-23023 May 2017 Evaluation of License Amendment Request to Revise Emergency Action Levels AEP-NRC-2017-04, License Amendment Request to Revise Technical Specifications Section 3.7.2, Steam Generator Stop Valves.2017-03-24024 March 2017 License Amendment Request to Revise Technical Specifications Section 3.7.2, Steam Generator Stop Valves. AEP-NRC-2016-65, License Amendment Request Regarding Technical Specification 3.9.3, Containment Penetrations2016-12-14014 December 2016 License Amendment Request Regarding Technical Specification 3.9.3, Containment Penetrations AEP-NRC-2016-93, DC Cook Nuclear Plant, Units 1 & 2, Supplement to License Amendment Request to Revise the Cyber Security Plan Implementation Schedule2016-10-28028 October 2016 DC Cook Nuclear Plant, Units 1 & 2, Supplement to License Amendment Request to Revise the Cyber Security Plan Implementation Schedule AEP-NRC-2016-64, License Amendment Request Regarding Containment Leakage Rate Testing Program2016-10-18018 October 2016 License Amendment Request Regarding Containment Leakage Rate Testing Program AEP-NRC-2016-83, Emergency License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2016-10-11011 October 2016 Emergency License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2016-78, Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and ..2016-09-15015 September 2016 Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and .. AEP-NRC-2016-19, License Amendment Request to Revise the Cyber Security Plan Implementation Schedule2016-03-14014 March 2016 License Amendment Request to Revise the Cyber Security Plan Implementation Schedule AEP-NRC-2016-07, License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation.2016-01-29029 January 2016 License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation. ML15328A4512015-11-19019 November 2015 Enclosures 1 - 5: Affirmation, Description of Proposed Changes, Probabilistic Risk Assessment Technical Adequacy, and CNP Units 1 & 2 TS Pages Marked to Show Proposed Changes ML15328A4522015-11-19019 November 2015 Enclosures 6 - 11: CNP Units 1 & 2 TS Bases, TSTF-425 Versus CNP TS Cross-Reference, Proposed No Significance Hazards Consideration, Proposed Inserts and Regulatory Commitments AEP-NRC-2015-46, License Amendment Request to Adopt TSTF-425-A, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5B2015-11-19019 November 2015 License Amendment Request to Adopt TSTF-425-A, Rev. 3, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 5B AEP-NRC-2015-85, License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2015-10-19019 October 2015 License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation AEP-NRC-2015-62, Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2015-06-29029 June 2015 Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation AEP-NRC-2015-49, Emergency License Amendment Request to Extend the Allowed Outage Time for an Emergency Diesel Generator2015-05-28028 May 2015 Emergency License Amendment Request to Extend the Allowed Outage Time for an Emergency Diesel Generator AEP-NRC-2014-70, License Amendment Request Regarding Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.152014-12-17017 December 2014 License Amendment Request Regarding Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15 AEP-NRC-2014-65, License Amendment Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification, and Implement Full-Scope Alternative Source Term2014-11-14014 November 2014 License Amendment Request to Adopt TSTF-490, Rev. 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification, and Implement Full-Scope Alternative Source Term AEP-NRC-2014-24, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits2014-04-0909 April 2014 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits AEP-NRC-2014-09, License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program2014-03-0707 March 2014 License Amendment Request to Revise Technical Specification Section 5.5.14, Containment Leakage Rate Testing Program AEP-NRC-2014-04, License Amendment Request to Revise the Cyber Security Implementation Schedule2014-01-10010 January 2014 License Amendment Request to Revise the Cyber Security Implementation Schedule AEP-NRC-2013-50, License Amendment Request Regarding Containment Divider Barrier Seal2013-11-0606 November 2013 License Amendment Request Regarding Containment Divider Barrier Seal AEP-NRC-2013-79, License Amendment Request Regarding Restoration of Normal Reactor Coolant System Operating Pressure and Temperature Consistent with Previously Licensed Conditions, with Enclosures 1 Through 52013-10-0808 October 2013 License Amendment Request Regarding Restoration of Normal Reactor Coolant System Operating Pressure and Temperature Consistent with Previously Licensed Conditions, with Enclosures 1 Through 5 AEP-NRC-2013-84, Emergency License Amendment Request Regarding Containment Distributed Ignition System2013-10-0707 October 2013 Emergency License Amendment Request Regarding Containment Distributed Ignition System ML13283A1222013-09-30030 September 2013 WCAP-17762-NP, Revision 1, D. C. Cook Unit 1 Return to Reactor Coolant System Normal Operating Pressure/Normal Operating Temperature Program - Licensing Report, and Enclosures 7 Through 9 ML12138A3982012-08-23023 August 2012 Issuance of Amendment No. 302 Regarding Optimized Zirlo Clad Fuel Rods ML11188A1452011-07-0101 July 2011 Request for License Amendment to Adopt National Fire Protection Association 805 Performance-Based Standard for Fire Protection for Light Water Reactor Generating Plants 2022-06-08
[Table view] Category:Technical Specification
MONTHYEARAEP-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 ML22340A1602022-11-30030 November 2022 Technical Specifications Bases, List of Effective Pages ML22340A2022022-11-30030 November 2022 Technical Specifications Bases, List of Effective Pages 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-2021-24, Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation2021-03-23023 March 2021 Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation AEP-NRC-2020-72, License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2020-12-14014 December 2020 License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2020-61, Unit 2, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable2020-10-27027 October 2020 Unit 2, Supplement to the Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam Supply to Turbine Driven Afw/Efw Pump Inoperable ML20164A0452020-06-0808 June 2020 License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2020-10, Unit 2, Application to Revise Technical Specification to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position2020-04-30030 April 2020 Unit 2, Application to Revise Technical Specification to Adopt TSTF-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-04-30030 April 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues ML20126G4552020-04-30030 April 2020 Application to Revise Technical Specifications to Adopt Tstf-541, Revision 2, Add Exceptions to Surveillance Requirements for Valves and Dampers Locked in the Actuated Position AEP-NRC-2020-09, Unit 2, Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam, Supply to Turbine Driven Afw/Efw Pump Inoperable2020-04-0707 April 2020 Unit 2, Application to Revise Technical Specifications to Adopt TSTF-412, Revision 3 Provide Actions for One Steam, Supply to Turbine Driven Afw/Efw Pump Inoperable AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System2020-04-0707 April 2020 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System AEP-NRC-2019-39, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition.2019-10-31031 October 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition. AEP-NRC-2019-33, Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-4212019-08-27027 August 2019 Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-421 AEP-NRC-2019-18, License Amendment Request to Delete Technical Specification Surveillance Requirement 3.8.1.20, Regarding Diesel Generator Operation When Connected to Its Load Test Resistor Bank2019-06-27027 June 2019 License Amendment Request to Delete Technical Specification Surveillance Requirement 3.8.1.20, Regarding Diesel Generator Operation When Connected to Its Load Test Resistor Bank AEP-NRC-2019-01, Application to Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2019-02-26026 February 2019 Application to Revise Technical Specifications to Adopt TSTF-563, Revision 0, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. AEP-NRC-2018-66, Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology2018-11-20020 November 2018 Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology AEP-NRC-2018-26, Application to Revise Technical Specifications to Adopt TFTF-529, Revision 4, Clarify and Use Application Rule2018-05-0404 May 2018 Application to Revise Technical Specifications to Adopt TFTF-529, Revision 4, Clarify and Use Application Rule ML16355A0992016-10-24024 October 2016 Donald C. Cook Nuclear Plant, Unit 1 - Technical Specification (TS) Bases Update Summary AEP-NRC-2016-78, Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and ..2016-09-15015 September 2016 Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and .. AEP-NRC-2016-29, Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 and to Request an Alternative to the ASME Code2016-07-21021 July 2016 Application to Revise Technical Specifications to Adopt TSTF-545, Revision 3 and to Request an Alternative to the ASME Code AEP-NRC-2016-07, License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation.2016-01-29029 January 2016 License Amendment Request to Revise Technical Specifications to Adopt Technical Specifications Task Force-523, Generic Letter 2008-01, Managing Gas Accumulation. AEP-NRC-2016-09, Correction of Technical Specification Typographical Error2016-01-15015 January 2016 Correction of Technical Specification Typographical Error ML15328A4522015-11-19019 November 2015 Enclosures 6 - 11: CNP Units 1 & 2 TS Bases, TSTF-425 Versus CNP TS Cross-Reference, Proposed No Significance Hazards Consideration, Proposed Inserts and Regulatory Commitments AEP-NRC-2014-70, License Amendment Request Regarding Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.152014-12-17017 December 2014 License Amendment Request Regarding Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.15 AEP-NRC-2010-12, Exigent License Amendment Request Regarding Containment Distributed Ignition System2010-01-24024 January 2010 Exigent License Amendment Request Regarding Containment Distributed Ignition System AEP-NRC-2009-45, License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System2009-07-17017 July 2009 License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System AEP-NRC-2009-18, License Amendment Request for Adoption TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-19019 March 2009 License Amendment Request for Adoption TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. ML0805303952008-02-13013 February 2008 Response to Request for Additional Information Regarding Proposed Amendment to Reduce Maximum Ventilation System Filter Pressure Drop ML0719103542007-06-27027 June 2007 Donald C. Cook, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Associated with Generic Letter 2004-02 ML0717300472007-06-13013 June 2007 License Amendment Request to Reduce Maximum Ventilation System Hepa/Charcoal Pressure Drop Allowed by Technical Specifications ML0630500862006-10-30030 October 2006 Tech Spec Pages for Amendments 297 and 278 Regarding Reactor Trip System Instrumentation ML0626905002006-09-15015 September 2006 Technical Specification Change for Reactor Trip on Low Turbine Oil Pressure ML0627103092006-09-15015 September 2006 Technical Specification Change to Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation ML0615701572006-05-26026 May 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0607605322006-03-0707 March 2006 Technical Specification Change of Interlock for a Reactor Trip on Turbine Trip ML0522803072005-08-0505 August 2005 Correction of Administrative Error for Improved Technical Specifications ML0405505362004-02-14014 February 2004 Application for Amendment to Delete Surveillance Requirements for Power Range, Intermediate Range, and Source Range Neutron Flux Monitors ML0405505612004-02-14014 February 2004 Application for Amendment to Technical Specifications Regarding Containment Requirements During Movement of Recently Irradiated Fuel Assemblies ML0325108672003-08-27027 August 2003 License Amendment Request to Revise Technical Specification 4.0.3: Missed Surveillance Time Allowance ML0319704522003-07-0202 July 2003 Supplement to License Amendment Request for Removal of Obsolete And/Or Expired License Conditions from the Unit 1 and Unit 2 Operating Licenses, Editorial Changes to the Unit 1 and Unit 2 Operating Licenses, and Administrative Changes.... ML0234604582002-12-10010 December 2002 License Amendment Request for Unit 1 Reactor Coolant System Pressure - Temperature Curves, & Request for Exemption from Requirements in 10 CFR 50.60(a) & 10 CFR 50, Appendix G ML0224901272002-08-30030 August 2002 License Amendment Request to Extend Reactor Trip System & Engineered Safety Features Actuation System Surveillance Time Requirements as Evaluated in WCAP-15376 ML0201702612002-01-16016 January 2002 Technical Specifications Amendments 261 & 244 Deleting TS 6.8.3 Requiring a Program for Post Accident Sampling ML0726900832001-09-21021 September 2001 Tech Spec Page for Amendment 281 Regarding Reactor Trip on Low Turbine Oil Pressure 2023-01-26
[Table view] Category:Amendment
MONTHYEARAEP-NRC-2021-24, Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation2021-03-23023 March 2021 Unit 2 - Request for Approval of Change Regarding Containment Water Level Instrumentation AEP-NRC-2020-72, License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2020-12-14014 December 2020 License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency ML20164A0452020-06-0808 June 2020 License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency AEP-NRC-2020-33, Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues2020-04-30030 April 2020 Application to Revise Technical Specifications to Adopt TSTF-567, Add Containment Sump TS to Address GSl-191 Issues AEP-NRC-2019-39, Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition.2019-10-31031 October 2019 Application to Revise Technical Specifications to Adopt TSTF-569, Revise Response Time Testing Definition. AEP-NRC-2019-33, Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-4212019-08-27027 August 2019 Application to Revise Technical Specification 5.5.5, Reactor Coolant Pump Flywheel Inspection Program, in Accordance with TSTF-421 AEP-NRC-2018-66, Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology2018-11-20020 November 2018 Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology AEP-NRC-2018-26, Application to Revise Technical Specifications to Adopt TFTF-529, Revision 4, Clarify and Use Application Rule2018-05-0404 May 2018 Application to Revise Technical Specifications to Adopt TFTF-529, Revision 4, Clarify and Use Application Rule AEP-NRC-2016-78, Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and ..2016-09-15015 September 2016 Unit 2 - Supplement to the License Amendment Request to Adopt TSTF-490, Revision 0, Deletion of E Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and .. AEP-NRC-2010-12, Exigent License Amendment Request Regarding Containment Distributed Ignition System2010-01-24024 January 2010 Exigent License Amendment Request Regarding Containment Distributed Ignition System AEP-NRC-2009-45, License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System2009-07-17017 July 2009 License Amendment Request for One-Time Extension of Technical Specification Completion Times for Inoperable Train of Reactor Trip System and Engineered Safety Feature Actuation System AEP-NRC-2009-18, License Amendment Request for Adoption TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26.2009-03-19019 March 2009 License Amendment Request for Adoption TSTF-511, Revision 0, Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26. ML0805303952008-02-13013 February 2008 Response to Request for Additional Information Regarding Proposed Amendment to Reduce Maximum Ventilation System Filter Pressure Drop ML0719103542007-06-27027 June 2007 Donald C. Cook, Units 1 and 2 - License Amendment Request to Revise Technical Specifications Associated with Generic Letter 2004-02 ML0630500862006-10-30030 October 2006 Tech Spec Pages for Amendments 297 and 278 Regarding Reactor Trip System Instrumentation ML0626905002006-09-15015 September 2006 Technical Specification Change for Reactor Trip on Low Turbine Oil Pressure ML0627103092006-09-15015 September 2006 Technical Specification Change to Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation ML0615701572006-05-26026 May 2006 Application for Technical Specification Improvement Regarding Steam Generator Tube Integrity ML0522803072005-08-0505 August 2005 Correction of Administrative Error for Improved Technical Specifications ML0405505612004-02-14014 February 2004 Application for Amendment to Technical Specifications Regarding Containment Requirements During Movement of Recently Irradiated Fuel Assemblies ML0405505362004-02-14014 February 2004 Application for Amendment to Delete Surveillance Requirements for Power Range, Intermediate Range, and Source Range Neutron Flux Monitors ML0325108672003-08-27027 August 2003 License Amendment Request to Revise Technical Specification 4.0.3: Missed Surveillance Time Allowance ML0319704522003-07-0202 July 2003 Supplement to License Amendment Request for Removal of Obsolete And/Or Expired License Conditions from the Unit 1 and Unit 2 Operating Licenses, Editorial Changes to the Unit 1 and Unit 2 Operating Licenses, and Administrative Changes.... ML0234604582002-12-10010 December 2002 License Amendment Request for Unit 1 Reactor Coolant System Pressure - Temperature Curves, & Request for Exemption from Requirements in 10 CFR 50.60(a) & 10 CFR 50, Appendix G ML0224901272002-08-30030 August 2002 License Amendment Request to Extend Reactor Trip System & Engineered Safety Features Actuation System Surveillance Time Requirements as Evaluated in WCAP-15376 ML0201702612002-01-16016 January 2002 Technical Specifications Amendments 261 & 244 Deleting TS 6.8.3 Requiring a Program for Post Accident Sampling ML0726900832001-09-21021 September 2001 Tech Spec Page for Amendment 281 Regarding Reactor Trip on Low Turbine Oil Pressure 2021-03-23
[Table view] |
Text
Indiana Michigan Power Company Nuclear Generation Group INDIANA MICHIGAN One Cook Place Bridgman, MI 49106 POWER. aep.com March 19, 2009 AEP-NRC-2009-18 10 CFR 50.90 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555-0001
Subject:
Donald C. Cook Nuclear Plant Units 1 and 2 Docket Nos. 50-315 and 50-316 License Amendment Request for Adoption of TSTF-51 1, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26."
Dear Sir or Madam:
In accordance with the provisions of Section 50.90 of Title 10 of the Code of Federal Regulations (10CFR), Indiana Michigan Power Company (I&M) is submitting a request for an amendment to the Technical Specifications (TS) for Donald C. Cook Nuclear Plant, Units 1 and 2.
The proposed amendment would delete those portions of TS superseded by 10 CFR Part 26, Subpart I. This change is consistent with Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR 26," Revision 0. The availability of this TS improvement was announced in the Federal Register on December 30, 2008, (73 FR 79923) as part of the consolidated line item improvement process. provides an evaluation of the proposed change. Attachment 2 provides the existing TS pages marked up to show the proposed change. New clean Unit 1 and Unit 2 TS pages with proposed changes incorporated will be provided to the NRC Licensing Project Manager when requested. Attachment 3 provides the regulatory commitment.
I&M requests approval of the proposed license amendment by September 1, 2009, to support implementation of TS changes concurrent with implementation of the 10 CFR 26, Subpart I requirement by October 1, 2009.
This letter contains one regulatory commitment identified in Attachment 3. Should you have any questions, please contact John A. Zwolinski, Manager of Regulatory Affairs, at (269) 466-2478.
Sincerely, Lawrence J. Weber Site Vice President DD(
RP/rdw
U. S. Nuclear Regulatory Commission AEP-NRC-2009-18 Page 2
Enclosure:
Affirmation Attachments:
- 1. Evaluation of Proposed Change 2a. Unit 1 Proposed Technical Specification Change (Mark-Up) 2b. Unit 2 Proposed Technical Specification Change (Mark-Up)
- 3. List of Regulatory Commitments c: T. A. Beltz - NRC Washington, DC K. D. Curry - AEP Ft. Wayne, w/o enclosure/attachments J. T. King - MPSC, w/o enclosure/attachments MDEQ - WHMD/RPS, w/o enclosure/attachments NRC Resident Inspector M. A. Satorius - NRC Region III
Enclosure to AEP-NRC-2009-18 AFFIRMATION I, Lawrence J. Weber, being duly sworn, state that I am Site Vice President of Indiana Michigan Power Company (I&M), that I am authorized to sign and file this request with the Nuclear Regulatory Commission on behalf of I&M, and that the statements made and the matters set forth herein pertaining to I&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company Lawrence J. Weber Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS OCL'DAYOF W'(Afcfh ,2009 Cojire __blic My Commission Expires u* jilov7oI
Attachment 1 to AEP-NRC-2009-18 Evaluation of Proposed Change License Amendment Request for Adoption of TSTF-51 1, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26" 1.0 Description 2.0 Proposed Change 3.0 Background 4.0 Technical Analysis 5.0 Regulatory Safety Analysis 5.1 No Significant Hazards Determination 5.2 Applicable Regulatory Requirements/Criteria 6.0 Environmental Consideration 7.0 References to AEP-NRC-2009-18 Page 2
1.0 DESCRIPTION
The proposed amendment would delete those portions of Technical Specifications (TS) superseded by 10 Code of Federal Regulations (CFR) Part 26, Subpart I per Reference 1. This change is consistent with Nuclear Regulatory Commission (NRC)-approved Technical Specification Task Force (TSTF) Improved Standard Technical Specification Change Traveler, TSTF-511 (Reference 2). There are no differences between the proposed plant-specific TS changes, and the changes proposed by Reference 2. The availability of this TS improvement was announced in the Federal Register (Reference 3) as part of the consolidated line item improvement process (CLIIP).
2.0 PROPOSED CHANGE
Consistent with Reference 2, the proposed TS changes delete those portions of TS superseded by 10 CFR Part 26, Subpart I.
This application is being made in accordance with the CLIIP. Indiana Michigan Power Company (I&M) is not proposing variations or deviations from the TS changes described in Reference 2, or the NRC staff's model safety evaluation (SE) published in Reference 3, as part of the CLIIP Notice'of Availability.
3.0 BACKGROUND
The NRC issued Reference 1 to provide notice of the issuance of a final rule that amended 10 CFR Part 26. The revised regulations in 10 CFR Part 26, Subpart I, supersede working hour restrictions contained in Paragraph d of TS 5.2.2. The background for this application is adequately addressed by the NRC Notice of Availability published in Reference 3.
4.0 TECHNICAL ANALYSIS
I&M has reviewed the SE published in Reference 3 as part of the CLIIP Notice of Availability.
I&M has concluded that the technical justifications presented in the SE prepared by the NRC staff are applicable to Donald C. Cook Nuclear Plants (CNP), Units 1 and 2.
10 CFR Part 26, Subpart I, supersedes existing worker fatigue guidance. 10 CFR Part 26, Subpart I, distinguishes between work hour controls and fatigue management and strengthens the requirements for both. Under the new rule, work hour restrictions include not only work hour limitations for rolling 24-hour, 48-hour, and 7-day periods, but also include a required minimum break between work periods and varying required minimum days off.
Additionally, Subpart I confines the use of waivers (deviations from restrictions) to situations where overtime is necessary to mitigate or prevent a condition adverse to safety or necessary to maintain the security of the facility. Subpart I also strengthens reporting requirements. Finally, the new rule's work hour control scope includes certain operating and maintenance personnel, as well as individuals directing those operating and maintenance personnel, health physics and chemistry personnel who are a part of the on-site emergency response organization minimum shift complement, the fire brigade member who is responsible for understanding the effects of fire and fire suppressants on safe shutdown capability, and certain security personnel.
to AEP-NRC-2009-18 Page 3 The proposed change removes working hour limits imposed in the TS in order to support compliance with 10 CFR Part 26, Subpart I. Work hour controls and fatigue management requirements have been incorporated into the. NRC's regulations; therefore, it is unnecessary to have work hour control requirements in the TS.
Removal of the TS requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I, requirements, even if the TS change is implemented prior to the October 1, 2009, deadline. Along with this license amendment request, I&M has submitted a commitment to comply with 10 CFR Part 26, Subpart I, concurrently with the implementation of the TS change.
5.0 REGULATORY SAFETY ANALYSIS 5.1 NO SIGNIFICANT HAZARDS DETERMINATION Indiana Michigan Power Company (I&M) has reviewed the no significant hazards determination published in Reference 3 as part of the consolidated line item improvement process (CLIIP)
Notice of Availability. I&M has concluded that the determination presented in the notice is applicable to Donald C. Cook Nuclear Plant (CNP), Units 1 and 2. I&M has evaluated the proposed changes to the Technical Specifications (TS) using the criteria in 10 Code of Federal Regulations (CFR) Part 50.92 and has determined that the proposed changes do not involve a significant hazards consideration. An analysis of the issue of no significant hazards consideration is presented below:
Criterion 1: The proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
The proposed change removes TS restrictions on working hours for personnel who perform safety-related functions. The TS restrictions are superseded by the worker fatigue requirements in 10 CFR Part 26. Removal of the TS requirements will be performed concurrently with the implementation of the 10 CFR Part 26, Subpart I, requirements. The proposed change does not impact the physical configuration or function of plant structures, systems, or components (SSCs) or the manner in which SCCs are operated, maintained, modified, tested, or inspected.
Worker fatigue is not an initiator of any accident, previously evaluated. Worker fatigue is not an assumption in the consequence mitigation of any accident previously evaluated.
Therefore, it is concluded that this change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
Criterion 2: The proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change removes TS restrictions on working hours for personnel who perform safety-related functions. The TS restrictions are superseded by the worker fatigue requirements in 10 CFR Part 26. Working hours will continue to be controlled in accordance with Nuclear Regulatory Commission (NRC) requirements. The new rule allows for deviations from controls to mitigate or prevent a condition adverse to safety or as necessary to maintain the security of the facility. This ensures that the new rule will not unnecessarily restrict working hours and to AEP-NRC-2009-18 Page 4 thereby create the possibility of a new or different kind of accident from any accident previously evaluated.
The proposed change does not alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, or affect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
Criteria 3: The proposed change does not involve a significant reduction in a margin of safety.
The proposed change removes TS restrictions on working hours for personnel who perform safety-related functions. The TS restrictions are superseded by the worker fatigue requirements in 10 CFR Part 26. The proposed change does not involve any physical changes to the plant or alter the manner in which plant systems are operated, maintained, modified, tested, or inspected. The proposed change does not alter the manner in which safety limits, limiting safety system settings or limiting conditions for operation are determined. The safety analysis acceptance criteria are not affected by this change. The proposed change will not result in plant operation in a configuration outside the design basis. The proposed change does not adversely affect systems that respond to safely shutdown the plant and to maintain the plant in a safe shutdown condition.
Removal of plant-specific TS administrative requirements will not reduce a margin of safety because the requirements in 10 CFR Part 26 are adequate to ensure that worker fatigue is managed.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above, I&M concludes that the proposed change presents no significant hazards consideration under the standards set forth in 10 CFR 50.92c, and, accordingly, a finding of "no significant hazards consideration" is justified.
5.2 APPLICABLE REGULATORY REQUIREMENTS/CRITERIA A description of the proposed TS change and its relationship to applicable regulatory requirements was provided in Reference 3, I&M has reviewed the NRC staff's model safety evaluation published in Reference 3 as part of the CLIIP Notice of Availability and concluded that the regulatory evaluation section is applicable to CNP, Units 1 and 2.
The proposed change eliminates the plant-specific TS administrative controls on working hours.
The TS guidance has been superseded by Reference 1.
10 CFR Part 26, Subpart I, "Managing Fatigue," contains requirements for managing worker fatigue at operating nuclear power plants.
10 CFR 50.36 provides, among other things, the regulatory requirements for the content in the Administrative Controls section of the TS. The inclusion of requirements to control working to AEP-NRC-2009-18 Page 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> and manage fatigue is not required to be in the Administrative Controls by 10 CFR Part 50.36. Because the requirement to control working hours and manage fatigue is provided in Reference 1, it is unnecessary for the TS to contain similar controls.
6.0 ENVIRONMENTAL CONSIDERATION
I&M has reviewed the environmental evaluation included in the SE published in Reference 3 as part of the CLIIP Notice of Availability. I&M has concluded that the staff's findings presented in that evaluation' are applicable to CNP, Units 1 and 2. The proposed amendment changes recordkeeping, reporting, or administrative procedures. Accordingly, the amendment meets the eligibility criteria for categorical exclusion set forth in 10 CFR 51.22(c)(10). Pursuant to 10 CFR 51.22(b) no environmental impact statement or environmental assessment need be prepared in connection with the issuance of the amendment.
7.0 REFERENCES
- 1. Federal Register Notice, Final Rule 10 CFR Part 26, published on March 31, 2008 (73 FR 17224).
- 2. TSTF-51 1, Revision 0, "Eliminate Working Hour Restrictions from TS 5.2.2 to Support Compliance with 10 CFR Part 26."
- 3. Federal Register Notice, Notice of Availability, published on December 30, 2008 (73 FR 79923).
Attachment 2a to AEP-NRC-2009-18 Proposed Technical Specification Change (Mark-Up)
Revised Page Unit 1 5.2-2
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements;
- c. A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;
- d. The amoun~t of overtime worked by unit staff members pe~ferming safety related func~tions must be Ifimnitcd in accordance with the NRC Polficy Statement on working hours (Gen*eri Letter 82 ) Deleted
- e. The operations manager must hold or have held a Senior Operator license at Cook Nuclear Plant or a similar reactor, or have been certified for equivalent Senior Operator knowledge. If the operations manager does not hold an Senior Operator license, then a line operations middle manager shall hold a Senior Operator license for the purposes of directing operational activities; and
- f. In MODE 1, 2, 3, or 4, an individual (shared with Unit 2) shall provide advisory technical support to the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Cook Nuclear Plant Unit 1 5.2-2
Attachment 2b to AEP-NRC-2009-18 Proposed Technical Specification Change (Mark-Up)
Revised Page Unit 2 5.2-2
Organization 5.2 5.2 Organization 5.2.2 Unit Staff (continued)
- b. Shift crew composition may be less than the minimum requirement of 10 CFR 50.54(m)(2)(i) and Specifications 5.2.2.a and 5.2.2.f for a period of time not to exceed 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br /> in order to accommodate unexpected absence of on-duty shift crew members provided immediate action is taken to restore the shift crew composition to within the minimum requirements;
- c. A radiation protection technician shall be on site when fuel is in the reactor.
The position may be vacant for not more than 2 hours2.314815e-5 days <br />5.555556e-4 hours <br />3.306878e-6 weeks <br />7.61e-7 months <br />, in order to provide for unexpected absence, provided immediate action is taken to fill the required position;
- d. The amount of overtimne workcd by unRit staff members pcrferming safety related functionS must be limited in acr'IdaRne With the NRC Policy Statement on wor.king hours (Generi Letter 82 12); Deete
- e. The operations manager must hold or have held a Senior Operator license at Cook Nuclear Plant or a similar reactor, or have been certified for equivalent Senior Operator knowledge. If the operations manager does not hold an Senior Operator license, then a line operations middle manager shall hold a Senior Operator license for the purposes of directing operational activities; and
- f. In MODE 1, 2, 3, or 4, an individual (shared with Unit 1) shall provide advisory technical supportto the unit operations shift crew in the areas of thermal hydraulics, reactor engineering, and plant analysis with regard to the safe operation of the unit. This individual shall meet the qualifications specified by the Commission Policy Statement on Engineering Expertise on Shift.
Cook Nuclear Plant Unit 2 5.2-2 Amendment No. 2&9
Attachment 3 to AEP-NRC-2009-18 List of Regulatory Commitments The following table identifies those actions committed to by Indiana Michigan Power Company (I&M) in this document. Any other actions discussed in this submittal represent intended or planned actions by .I&M. They are described to the Nuclear Regulatory Commission (NRC) for the NRC's information and are not regulatory commitments.
Commitment Due Date Removal of the plant-specific Technical Specification This commitment will be requirements will be performed concurrently with the completed no later than implementation of the 10 CFR Part 26, Subpart I requirements. October 1, 2009