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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:Schedule and Calendars
[Table view] |
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Indiana Michigan Power One Cook Place Bridgman, MI 49106 A unit of American Electric Power IndianaMichiganPower.com July 19, 2010 AEP-NRC-2010-49 10 CFR 50.90 10 CFR 73.54 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 Approval of the Donald C. Cook Nuclear Plant Cyber Security Plan
Dear Sir or Madam:
By letter dated November 20, 2009, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP), submitted a request for an amendment to the Renewed Facility Operating Licenses (FOL) for CNP Unit 1 and Unit 2. This proposed amendment requested NRC approval of the CNP Cyber Security Plan, an implementation schedule for the Cyber Security Plan, and an addition to the existing FOL Physical Protection license condition requiring I&M to fully implement and maintain in effect all provisions of the approved Cyber Security Plan. By letter dated May 20, 2010, the NRC acknowledged receipt of I&M's letter and requested I&M to respond with either a revised submittal that addresses previously identified generic issues from use of NEI 08-09, Revision 3, or to respond by withdrawing the existing application and resubmitting a revised Cyber Security Plan consistent with Regulatory Guide 5.71 or NEI 08-09, Revision 6. In response to the NRC's request, I&M is withdrawing its previously submitted license amendment request dated November 20, 2009. Therefore, I&M is submitting a new license amendment request for approval of the CNP Cyber Security Plan consistent with NEI 08-09, Revision 6.
By letter dated April 28, 2010, the Nuclear Energy Institute (NEI) provided the Nuclear Regulatory Commission (NRC) a copy of NEI 08-09, "Cyber Security Plan for Nuclear Power Reactors,"
Revision 6, dated April 2010, for review and endorsement. By letter dated May 5, 2010, from the NRC to NEI, the NRC endorsed the use of NEI 08-09, Revision 6, as acceptable for use by licensees to comply with the requirements of 10 CFR 73.54 with the exception of the definition of "cyber attack." NEI responded with a new, proposed definition of "cyber attack" in a letter to the NRC, dated June 2, 2010. By letter dated June 7, 2010, from the NRC to NEI, the NRC accepted NEI's proposed definition for "cyber attack" and authorized licensees to incorporate this definition in cyber security plans based on NEI 08-09, Revision 6.
Enclosures 4 and 5 to this letter contain sensitive information Withhold from public disclosure under 10 CFR 2.390 Upon removal of Enclosures 4 and 5, this letter is decontrolled SECURITY-RELATED INFORMATION -WITHHOLD UNDER 10 CFR 2.390
U. S. Nuclear Regulatory Commission AEP-NRC-2010-49 Page 2 Pursuant to 10 CFR 50.90 and 10 CFR 73.54, Indiana Michigan Power Company, the licensee for CNP, is submitting a request for an amendment to the Renewed FOL for CNP Unit 1 and Unit 2.
This proposed amendment requests NRC approval of the CNP Cyber Security Plan, an implementation schedule for the Cyber Security Plan, and an addition to the existing FOL Physical Protection license condition requiring I&M to fully implement and maintain in effect all provisions of the approved Cyber Security Plan. to this letter provides an affirmation statement regarding the information in this letter. provides I&M's evaluation of the proposed change. Enclosure 3 provides the proposed implementation schedule required by 10 CFR 73.54 as regulatory commitments. Enclosure 4 provides the proposed CNP Cyber Security Plan which will be incorporated by reference into CNP's Physical Security Plan following NRC approval. Enclosure 5 provides the details of the deviations from NEI 08-09, Revision 6. Enclosure 6 to this letter provides the requested change to the FOL for CNP Unit 1 and Unit 2. Clean copies of the affected FOL pages with the proposed changes incorporated will be provided to the NRC Licensing Project Manager upon request. A&M requests that Enclosure 4 and Enclosure 5, which contain sensitive security related information, be withheld from public disclosure in accordance with 10 CFR 2.390.
I&M requests approval of the proposed amendment in accordance with the normal NRC review schedule. The proposed amendment will be implemented within 90 days of approval. The approved plan will be implemented in accordance with Enclosure 3.
Copies of this letter and its enclosures are being transmitted to the Michigan Public Service Commission and Michigan Department of Environmental Quality in accordance with the requirements of 10 CFR 50.91. This letter contains regulatory commitments.
Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Joel P. Gebbie Site Vice President AMD/jmr Enclosures 4 and 5 to this letter contain sensitive information Withhold from public disclosure under 10 CFR 2.390 Upon removal of Enclosures 4 and 5, this letter is decontrolled SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390
U. S. Nuclear Regulatory Commission AEP-NRC-2010-49 Page 3
Enclosures:
- 1. Affirmation
- 2. Indiana Michigan Power Company's Evaluation
- 3. Implementation Schedule as Regulatory Commitments
- 4. Donald C, Cook Nuclear Plant Cyber Security Plan
- 5. Deviations from NEI 08-09, Revision 6
- 6. Proposed Facility Operating License Change c: J. T. King, MPSC S. M. Krawec, AEP Ft. Wayne, w/o enclosures MDNRE - WHMD/RPS NRC Resident Inspector M. A. Satorius, NRC Region III P. S. Tam, NRC Washington DC Enclosures 4 and 5 to this letter contain sensitive information Withhold from public disclosure under 10 CFR 2.390 Upon removal of Enclosures 4 and 5, this letter is decontrolled SECURITY-RELATED INFORMATION - WITHHOLD UNDER 10 CFR 2.390
Enclosure 1 to AEP-NRC-2010-49 AFFIRMATION I, Joel P. Gebbie, 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 Joel P. Gebbie Site Vice President SWORN TO AND SUBSCRIBED BEFORE ME THIS I-DAY OF Lt ,2010 My Commss14in Er P43--r ,.,,,
': y;Comrhission Expires o lo1 "Co I 1ClZ1
Enclosure 2 to AEP-NRC-2010-49 INDIANA MICHIGAN POWER COMPANY'S EVALUATION
Subject:
License Amendment Request for Approval of the Donald C. Cook Nuclear Plant Cyber Security Plan
1.0 DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY SAFETY ANALYSIS 5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria 5.3 Conclusion
6.0 ENVIRONMENTAL CONSIDERATION
S
7.0 REFERENCES
to AEP-NRC-2010-49 Page 2
1.0 DESCRIPTION
Pursuant to 10 CFR 50.90 and 10 CFR 73.54, Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP), is submitting a request for an amendment to the Renewed Facility Operating Licenses (FOL) for CNP Unit 1 and Unit 2. This proposed amendment requests Nuclear Regulatory Commission (NRC) approval of the CNP Cyber Security Plan, an implementation schedule for the Cyber Security Plan, and addition to the existing FOL Physical Protection license condition requiring I&M to fully implement and maintain in effect all provisions of the approved Cyber Security Plan.
2.0 PROPOSED CHANGE
I&M proposes to implement the Donald C. Cook Nuclear Plant Cyber Security Plan, described in to this letter, in accordance with the implementation schedule described in to this letter.
I&M proposes to add a condition to the Unit 1 and the Unit 2 FOL, as described in Enclosure 6 to this letter. The proposed license condition will require that I&M implement and maintain in effect the Cyber Security Plan.
3.0 BACKGROUND
This license amendment request (LAR) consists of three parts: the proposed Cyber Security Plan, a proposed Implementation Schedule, and a proposed addition to the existing FOL Physical Protection license condition to require I&M to fully implement and maintain in effect all provisions of the Commission-approved cyber security plan as required by 10CFR 73.54, "Protection of digital computer and communication systems and networks." The regulations in 10 CFR 73.54 establish the requirements for a cyber security program. These regulations require each licensee currently licensed to operate a nuclear power plant under 10 CFR 50 to submit a cyber security plan that satisfies the requirements of the rule. Each submittal must include a proposed implementation schedule and implementation of the licensee's cyber security program must be consistent with the approved schedule. The background for this application is addressed by the NRC Notice of Availability published on March 27, 2009, in Federal Register notice 74 FR 13926 (Reference 1).
4.0 TECHNICAL ANALYSIS
Reference 1 issued the final rule that amended 10 CFR Part 73. The cyber security requirements codified as 10 CFR 73.54 are designed to provide high assurance that digital computer and communication systems and networks are adequately protected against cyber attacks up to and including the design basis threat established by 10 CFR 73.1 (a)(1)(v). These requirements are substantial improvements upon the requirements imposed by the NRC's Order Modifying License, EA-02-026 (Reference 2).
to AEP-NRC-2010-49 Page 3 By letter dated April 28, 2010 (Reference 3), the Nuclear Energy Institute (NEI) provided NEI 08-09, Revision 6, to the NRC for review and endorsement. NEI 08-09, Revision 6, provides a template for use by licensees in development of their own cyber security plans.
This LAR includes the proposed plan (Enclosure 4) that conforms to the template provided in NEI 08-09 with deviations documented in Enclosure 5. In addition, the LAR includes the proposed change to the existing FOL license condition for "Physical Protection" (Enclosure 6).
Finally, the LAR contains the proposed Implementation Schedule (Enclosure 3) as required by 10 CFR 73.54.
5.0 REGULATORY SAFETY ANALYSIS 5.1 Applicable Regulatory Requirements /Criteria This LAR is submitted pursuant to 10 CFR 73.54 which requires licensees currently licensed to operate a nuclear power plant under 10 CFR Part 50 to submit a Cyber Security Plan in accordance with 10 CFR 50.4 and 50.90.
5.2 No Significant Hazards Consideration I&M has evaluated whether a significant hazards consideration is involved with the-proposed amendment by focusing on the three standards set forth in 10 CFR 50.92, "Issuance of amendment," as discussed below:
- 1. Does the proposed change involve a significant increase in the probability of occurrence or consequences of an accident previously evaluated?
Response: No The proposed change is required by 10 CFR 73.54 and includes three parts. The first part is the submittal of the Donald C. Cook Nuclear Plant (CNP) Cyber Security Plan for Nuclear Regulatory Commission (NRC) review and approval. The plan provides a description of how the requirements of the rule will be implemented at CNP. The plan establishes the licensing basis for the Indiana Michigan Power Company (I&M) Cyber Security Program for CNP.
The plan establishes how to achieve high assurance that nuclear power plant digital computer and communication systems and networks associated with the following are adequately protected against cyber attacks up to and including the design basis threat:
- 1. Safety-related and important-to safety functions,
- 2. Security functions,
- 3. Emergency preparedness functions including offsite communications, and
.4. Support systems and equipment which, if compromised, Would adversely impact safety, security, or emergency preparedness functions.
to AEP-NRC-2010-49 Page 4 The plan is designed to provide high assurance that the systems and networks are protected from cyber attacks.. The plan, itself, does not require any plant modifications.
However, implementation of the plan is expected to require plant configuration changes.
The plan describes how plant modifications that -involve digital computers and communication systems and networks will be reviewed to provide high assurance of adequate protection against cyber attacks, up to and including the design basis threat as defined in 10 CFR 73.54. Changes to the systems and networks will be evaluated per 10 CFR 50.59 to determine if a License Amendment is required. Changes to the systems and networks will be evaluated per 10 CFR 50.54(q) to determine if the effectiveness of the site Emergency Plan is reduced. Changes to the systems and networks will be evaluated per 10 CFR 50.54(p) to determine if the effectiveness of the site Security Plan is reduced.
Prior NRC approval will be obtained if required by these evaluations.
The plan, itself, does not alter the plant configuration, require new plant equipment to be installed, alter accident analysis assumptions, add any initiators, or effect the function of plant systems or the manner in which systems are operated, maintained, modified, tested, or inspected. The plan has no impact on the probability or consequences of an accident previously evaluated.
The second part of the proposed change is an implementation schedule. The third part adds a sentence to the existing Renewed Facility Operating Licenses (FOL). license condition for physical protection. Both of these changes are administrative and have no impact on the probability or consequences of an accident previously evaluated.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Does the proposed change create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The first part of the proposed change is the submittal of the Cyber Security Plan for NRC review and approval. The plan provides a description of how the requirements of 10 CFR 73.54 will be implemented at CNP.
The plan does not require any plant modifications. The plan describes how plant modifications involving digital computer systems will be reviewed to provide high assurance of adequate protection against cyber attacks, up to and including the design basis threat defined in 10 CFR 73.54. The plan 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. The plan is designed to provide high assurance that the systems within the scope of the rule are protected from cyber attacks and does not create the possibility of a new or different kind of accident from any previously evaluated.
The second part of the proposed change is an implementation schedule. The third part adds a sentence to the existing FOL license condition for physical protection. Both of these to AEP-NRC-2010-49 Page 5 changes are administrative and do not create the possibility of a new or different kind of accident from any previously evaluated.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any previously evaluated.
- 3. Does the proposed change involve a significant reduction in a margin of safety?
Response: No The first part of the proposed change is the submittal of the plan for NRC review and approval. The plan is designed to provide high assurance that the systems within the scope of the rule are protected from cyber attacks. Plant safety margins are established through Limiting Conditions for Operation, Limiting Safety System Settings, and Safety Limits specified in the Technical Specifications. Because there is no change to these established safety margins, the proposed change does not involve a significant reduction in a margin of safety.
The second part of the proposed change is an implementation schedule. The third part adds a sentence to the existing FOL license condition for physical protection. Both of these changes are administrative and do not involve a significant reduction in a margin of safety.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
5.3 Conclusion In conclusion, based on the considerations discussed above: (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner; (2) such activities will be conducted in compliance with the Commission's regulations; and (3) the issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public. I&M concludes that the proposed amendment presents no significant hazards consideration under the standards set forth in 10 CFR 50.92(c), and, accordingly, a finding of "no significant hazards consideration" is justified.
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6.0 ENVIRONMENTAL CONSIDERATION
S A review has determined that the proposed amendment would change a requirement with respect to installation or use of a facility component located within the restricted area, as defined in 10 CFR 20, or would change an inspection or surveillance requirement. However, the proposed amendment does not involve (i) a significant hazards consideration, (ii) a significant change in the types of or significant increase in the amounts of any effluent that may be released offsite, or (iii) a significant increase in individual or cumulative occupational radiation exposure. Accordingly, the proposed amendment meets the eligibility criterion for categorical exclusion set forth in 10 CFR 51.22(c)(12). Therefore, pursuant to 10 CFR 51.22(b), no environmental impact statement or environmental assessment need be prepared in connection with the proposed amendment.
7.0 REFERENCES
- 1. Federal Register Notice, Final Rule 10 CFR Part 73, Power Reactor Security Requirements, published on March 27, 2009, 74 FR 13926.
- 2. EA-02-026, Order Modifying Licenses, Safeguards and Security Plan Requirements, issued February 25, 2002. (ADAMS Accession No. ML020500059)
- 3. Letter from J. W. Roe, Nuclear Energy Institute (NEI), to S. A. Morris, Nuclear Regulatory Commission (NRC), "NEI 08-09, Revision 6, Cyber Security Plan for Nuclear Power Reactors, April 2010," dated April 28, 2010. (ADAMS Accession No. ML101180434)
Enclosure 3 to AEP-NRC-2010-49 DONALD C. COOK NUCLEAR PLANT CYBER SECURITY PLAN IMPLEMENTATION SCHEDULE to AEP-NRC-2010-49 Page 1 Donald C. Cook Nuclear Plant Cyber Security Plan Implementation Schedule as Regulatory Commitments The following table identifies those actions committed to by Indiana Michigan Power Company (I&M) for implementation of the Donald C. Cook Nuclear Plant (CNP) Cyber Security PElan. 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 Completion Date Train and qualify Cyber Security Assessment Team. June 30, 2011 Identify Critical Systems and Critical Digital Assets. June 30, 2011 Develop Cyber Security Defensive Strategy. June 30, 2011 Implement cyber security defense-in-depth architecture for June 30, 2012 isolation boundaries.
Implement cyber security defense-in-depth architecture for June 30, 2013 all other non-isolation boundaries.
Establish Cyber Security Program policies/procedures. December 31, 2013 Perform and document the cyber security assessment December 31, 2013 described in the Cyber Security Plan.
Implement Security Controls not requiring a plant 48 months after NRC approval modification. of Cyber Security Plan The Cyber Security Program is implemented and the 48 months after NRC approval Program has entered maintenance phase. of Cyber Security Plan