Letter Sequence Supplement |
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EPID:L-2024-LLA-0040, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating (Approved, Closed) |
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MONTHYEARAEP-NRC-2024-10, Form OAR-1, Owners Activity Report2024-02-0707 February 2024 Form OAR-1, Owners Activity Report Project stage: Request AEP-NRC-2024-02, Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-04-0303 April 2024 Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating Project stage: Request ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 Project stage: Other AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report Project stage: Request AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating Project stage: Supplement ML24156A0052024-05-22022 May 2024 NRR E-mail Capture - D.C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Acceptance of License Amendment Request Regarding Reserve Feed Enclosure Project stage: Acceptance Review ML24156A0072024-05-30030 May 2024 NRR E-mail Capture - Final RAI - D.C. Cook Nuclear Plant, Unit Nos. 1 and 2 - License Amendment Request Regarding Reserve Feed Enclosure Project stage: RAI AEP-NRC-2024-48, Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-07-0202 July 2024 Response to Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating Project stage: Response to RAI ML24197A1262024-07-15015 July 2024 Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating Project stage: Request AEP-NRC-2024-76, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-08-28028 August 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating Project stage: Supplement ML24225A0022024-09-0303 September 2024 Issuance of Amendment Nos. 363 and 344 Revising Technical Specifications Section 3.8.1, AC Sources-Operating, for a One-Time Extension of a Completion Time Project stage: Approval 2024-05-30
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Category:Letter type:AEP
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[Table view] Category:Technical Specification
MONTHYEARML24159A2692024-05-30030 May 2024 Technical Specifications Bases, List of Effective Pages ML24159A2722024-05-30030 May 2024 Technical Specifications Bases, List of Effective Pages AEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System 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 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-2020-33, 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-2020-10, 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 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. 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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 2024-05-30
[Table view] Category:Amendment
MONTHYEARAEP-NRC-2024-40, Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating2024-05-16016 May 2024 Unit 2 - Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating AEP-NRC-2024-04, License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, Low Temperature Overpressure Protection (LTOP) System2024-03-0606 March 2024 License Amendment Request Regarding a Change to Unit 1 Technical Specification 3.4.12, 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 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 ML0627103092006-09-15015 September 2006 Technical Specification Change to Reactor Trip System Instrumentation and Engineered Safety Feature Actuation System Instrumentation ML0626905002006-09-15015 September 2006 Technical Specification Change for Reactor Trip on Low Turbine Oil Pressure 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 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 2024-05-16
[Table view] |
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Indiana Michigan Power INDIANA Cook Nuclear Plant MICHIGAN One Cook Place POWIR " Bridgman, Ml 49106 ind1anamichiganpower.com An AEP Company
BOUNDLESS ENERGY-
May 16, 2024 AEP-NRC-2024-40 10 CFR 50.90
Docket Nos.: 50-315 50-316
U.S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, D.C. 20555-0001
Donald C. Cook Nuclear Plant Unit 1 and Unit 2 Supplement to License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
References:
- 1. Letter from K. J. Ferneau, Indiana Michigan Power Company (l&M), to U.S. Nuclear Regulatory Commission (NRC), "Donald C. Cook Nuclear Plant Unit 1 and Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating,"
dated April 3, 2024, Agencywide Documents Access and Management System (ADAMS)
Accession No. ML24094A288.
- 2. Letter from S. P. Wall, NRC, to Q. S. Lies, l&M, "Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Supplemental Information Needed for Acceptance of License Amendment Request to Revise Technical Specification 3.8.1 (EPID No. L-2024-LLA-0040)," dated May 7, 2024, ADAMS Accession No. ML24115A215.
This letter provides Indiana Michigan Power Company's (l&M), licensee for Donald C. Cook Nuclear Plant (CNP) Unit 1 and Unit 2, response to Reference 2 by the U.S. Nuclear Regulatory Commission (NRC) regarding Reference 1.
Enclosure 1 to this letter provides an affirmation statement. Enclosure 2 to this letter provides l&M's response to Reference 2.
Enclosure 3 and Enclosure 4 provide Unit 1 and Unit 2 TS pages, respectively, marked to show the proposed changes. Enclosure 5 provides a list of Regulatory Commitments that l&M will be making to support approval and implementation of the License Amendment Request (LAR) made in Reference 1.
The changes proposed in this letter do not impact the conclusions provided in Reference 1 that a finding of "no significant hazards consideration" is justified. There are new regulatory commitments made in U.S Nuclear Regulatory Commission AEP-NRC-2024-40 Page 2
this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Director, at (269) 466-2649.
Sincerely,
~L~
Site Vice President
JMT/sjh
Enclosures:
1. Affirmation
- 2. Supplement to License Amendment Request Regarding One-Time Extension of Completion Time for Inoperable AC Source - Operating
- 3. Donald C. Cook Nuclear Plant Unit 1 Technical Specification Pages Marked to Show Proposed Changes
- 4. Donald C. Cook Nuclear Plant Unit 2 Technical Specification Pages Marked to Show Proposed Changes
- 5. Regulatory Commitments to Support License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating
c: EGLE - RMD/RPS J. B. Giessner-NRC Region Ill NRC Resident Inspector N. Quilico - MPSC R. M. Sistevaris -AEP Ft. Wayne, w/o enclosures S. P. Wall - NRC Washington, D.C.
A. J. Williamson - AEP Ft. Wayne, w/o enclosures Enclosure 1 to AEP-NRC-2024-40
AFFIRMATION
I, Kelly J. Ferneau, being duly sworn, state that I am the Site Vice President of Indiana Michigan Power Company (l&M), that I am authorized to sign and file this request with the U.S. Nuclear Regulatory Commission on behalf of l&M, and that the statements made and the matters set forth herein pertaining to l&M are true and correct to the best of my knowledge, information, and belief.
Indiana Michigan Power Company
~1"Site Vice President ~
SWORN TO AND SUBSCRIBED BEFORE ME
TH1s \\ Lo DAY oF Ho l J 2024
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My Commission Expires /-:)3) :lce,O Enclosure 2 to AEP-NRC-2024-40
Supplement to License Amendment Request Regarding One-Time Extension of Completion Time for Inoperable AC Source - Operating
By letter dated April 3, 2024 (Reference 1 ), Indiana Michigan Power Company (l&M, the licensee) submitted a license amendment request (LAR) for the Donald C. Cook Nuclear Plant (CNP), Units Nos. 1 and 2. The proposed LAR would revise Technical Specification (TS) 3.8.1, "AC Sources -
Operating," by adding a footnote for TS 3.8.1, Required Action A.3 to allow a one-time completion time (CT) extension from 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> to 288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br /> to support the replacement of the 12AB (Train B)
Loop Feed Enclosure (LFE) and associated bus for the Train B reserve feed preferred power source.
By letter dated May 7, 2024 (Reference 2) the NRC informed l&M that the proposed LAR (Reference
- 1) would need to be supplemented, to be accepted, to address several BTP-related items that were not found in the LAR.
This Enclosure 2 to this letter contains a supplement to Reference 1 to address the items that were identified by the NRC in Reference 2 from NUREG-0800, Revision 3, "Standard Review Plan for the Review of Safety Analysis Reports for Nuclear Power Plants, Branch Technical Position (BTP) 8-8, "Onsite (Emergency Diesel Generators) and Off site Power Sources Allowed Outage Time Extensions". Additionally, at the end of this Enclosure l&M is providing a change to a reference made in the Probabilistic Risk Assessment (PRA) discussion in Reference 1.
EEEB-1
'~ supplemental alternating current (AC) power source needed. This source should be available as a backup to the inoperable EOG or offsite power source, to maintain the defense-in-depth philosophy of the electrical system to meet its intended function.
The supplemental AC power source must have capacity to bring a unit to safe shutdown (cold shutdown) in case of a loss of offsite power (LOOP) concurrent with a single failure during plant operation (Mode 1) as supported by the risk-informed and deterministic evaluation.
Note: Multi-unit sites that have installed a single supplemental AC power source for station blackout (S80) cannot substitute it for the inoperable diesel when requesting CT extensions unless the supplemental AC power source has enough capacity to carry all LOOP loads to bring the unit to a cold shutdown as a substitute for the EOG in an extended CT and carry all SBO loads for the unit that has an S80 event without any load shedding"
l&M Response to EEEB-1
The supplemental alternating current power source for CNP are two Supplemental Diesel Generators (SDGs) which were permanently installed at CNP in 2005 in support of extending the Allowed Outage Time for the Emergency Diesel Generators (EDGs). In the event of a loss of 4kV voltage to the to AEP-NRC-2024-40 Page 2
Emergency Power (EP) system, the two SDGs automatically start, sync with each other, and automatically energize the EP Bus #1. The SDGs may then be manually aligned from EP Bus #1 to the safety-related 4kV busses through breakers T11 C2, T11 D1, T11 A 12, T11 B2 in Unit 1, or breakers T21C2, T21D1, T21A12, or T21 B2 in Unit 2. This allows for power to be supplied to whichever train is not affected by any single failure. The two SDGs are rated to a combined capacity of 4500kW, which is above the 3500kW rating of each EOG (CNP has 2 EDGs per Unit, one for Train A and one for Train B). This capability is verified in CNP Calculation 12-E-S-EPEDG-001, Allowable Outage Time (AOT) Diesel Generator ETAP Analysis. The two SDGs provide sufficient capacity to bring a Unit to safe shutdown in case of a LOOP event with a single failure during plant operation (Mode 1 ).
CNP has adopted the AC Independent approach for coping with an SBO event as delineated in Regulatory Guide 1.155 (CNP UFSAR 8.7.2). CNP does not credit the SDGs in the SBO analysis, and therefore the SDGs are not required to be able to supply loads in the event of a SBO. By extension, the SDGs would not be required to supply SBO loads while supplying safe-shutdown loads in the event of a LOOP. The "Note" above does not apply to CNP.
EEEB-2
"The time to make the supplemental AC power source available, including accomplishing the cross-connection, should be approximately one hour to enable restoration of battery chargers and control reactor coolant system inventory.
Note: To support the one-hour time for making this power source available, plants must assess their ability to cope with loss of all AC power (S80) for one hour independent of a supplemental AC power source. The plant should have formal engineering calculations for equipment sizing and protection and have approved procedures for connecting the supplemental AC power source to the safety buses."
l&M Response to EEEB-2
CNP can sustain the SBO event for the coping duration of 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> (CNP UFSAR 8.7.2), which exceeds the required one-hour time to make the supplemental AC power source available.
The SDGs are permanently installed plant equipment and automatically start upon a sustained loss of voltage on the 4.16 kV EP system. As discussed above the SDGs automatically load to the EP Bus
- 1, which is then available for the operator to manually load to any of the safety related 4.16 kV Buses (CNP UFSAR 8.3.1). CNP emergency operating procedure 1(2)-OHP-4023-ECA-0-0, Loss of All AC Power, Step 9, directs restoration of power to AC emergency buses via the SDGs in the event that reserve power is not available. This action has been demonstrated by plant operators, when performed in the CNP simulator, to be completed in less than 30 minutes.
As discussed above, SDG load capabilities are demonstrated in CNP Calculation 12-E-S-EPEDG-001, Allowable Outage Time (AOT) Diesel Generator ETAP Analysis. Relay settings are validated in CNP design document 12-E-S-EPEDG-002, Supplemental Diesel Generator System Relay Settings. to AEP-NRC-2024-40 Page 3
EEEB-3
"The availability of supplemental AC power source should be verified within the last 30 days before entering extended CT by operating or bringing the power source to its rated voltage and frequency for 5 minutes and ensuring all its auxiliary support systems are available or operational."
l&M Response to EEEB-3
CNP's Technical Requirements Manual (TRM) Surveillance Requirement (SR) 8.8.3.2 requires:
"Exercise the SDGs by running each one unloaded for>= 5 minutes," with a Frequency of 14 days.
At a Frequency of 14 days, both of CNPs Supplemental Diesel Generators will be tested in accordance with the normal TRM surveillance frequency prior to entering the extended Completion Time period per CNP procedure 12-OHP-4030-033-001, Supplemental Diesel Generator Testing,, which requires checking that each SDG runs for at least 5 minutes unloaded and stabilizes at the rated voltage and frequency. Completion of this TRM SR 8.8.3.2 ensures all auxiliary support systems are available or operational.
As 14 days is within the required 30 days, it is assured this check will occur within the 30 day period prior to entering the extended Completion Time.
EEEB-4
"The availability of supplemental AC power source shall be checked every 8-12 hours (once per shift). If the supplemental AC power source becomes unavailable any time during extended CT, the unit shall enter the LCO and start shutting down within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />. This 24-hour period will be allowed only once within any given extended CT for the restoration of the offsite power. "
l&M Response to EEEB-4
In order to address this statement, l&M is changing the proposed wording of the footnote discussed in Section "2.4 Description of the Proposed Change" in Reference 1. This footnote is being replaced in its entirety with the revised footnote below.
This footnote was included in the Unit 1 and Unit 2 Technical Specification marked up page, Enclosures 3 and 4, respectively, of Reference 1. These Enclosures 3 and 4 of Reference 1 are being replaced in their entirety by Enclosures 3 and 4 of this letter.
Enclosure 2 to AEP-NRC-2024-40 Page 4
Revisions to Footnote stated in Section 2.4, Enclosure 3 and Enclosure 4 of Reference 1
Original footnote in Reference 1 :
(a) For Train B only, the Completion Time that Train B can be inoperable as specified by Required Action A.3 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" up to "288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br />," to support modification of the Train B Reserve Feed 12AB Loop Feed Enclosure. Upon completion of the modification and restoration this footnote is no longer applicable. Compensatory measures described within CNP letter AEP-NRC-2024-02, dated April 3, 2024 will remain in effect during the extended period. The one-time extension shall expire upon completion of the modification and restoration of operability for Train B.
Revised footnote:
(a) For Train B only, the Completion Time that Train B can be inoperable as specified by Required Action A.3 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" up to "288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br />," to support modification of the Train B Reserve Feed 12AB Loop Feed Enclosure. Upon completion of the modification and restoration this footnote is no longer applicable. Prior to entry into the 288-hour extended Completion Time, the Supplemental Diesel Generators (SDGs) shall be verified as available.
During the 288-hour extended Completion Time, the SDGs shall be verified as available once per shift. If the SDGs becomes unavailable after the initial 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while in the extended 288-hour Completion Time period, it shall be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the unit shall be brought to MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This 24-hour period will be allowed only once within the single extended Completion Time. Compensatory measures described within CNP letter AEP-NRC-2024-02, dated April 3, 2024, and supplemented by AEP-NRC-2024-40, dated May 16th, will remain in effect during the extended period. The one-time extension shall expire upon completion of the modification and restoration of operability for Train B.
EEEB-5
"The six regulatory commitments listed on page 8-8-5 of BTP 8-8"
l&M Response to EEEB-5
l&M has included all six of the regulatory commitments listed on page 8-8-5 of BTP 8-8 into the list of Regulatory Commitments in Enclosure 5 of this letter.
Clarification on Technical Acceptability of Seismic PRA Peer Review in Section 3.3.1.1 Peer Review History
The wording in the original license amendment request (Reference 1) was copied from the original Peer Review Report (PWROG-18062-P) that was performed for the seismic PRA. To ensure consistency with the source document, historical description of the status of the Code Case was included. In Reference 1, this description is confusing given the current status of the Code Case in 2020. RG 1.200 Revision 3 provides endorsement of ASME/ANS RA-S Case 1 for seismic PRA, and therefore provides the current basis for acceptability of the Seismic PRA peer review, despite the discussion in the original peer review report. To ensure clarity on the basis for acceptability of CNP's SPRA peer review, the excerpt from PWROG-18062-P should be removed from Reference 1, and to AEP-NRC-2024-40 Page 5
instead a simple reference to RG 1.200 Revision 3 and its endorsement of ASME/ANS RA-S Case 1 should be provided for that section. This recommended replacement wording is presented below.
Current Wording:
"Seismic PRA (SPRA) model
"The seismic PRA model was peer reviewed in November 2018 (Reference 19). This peer review was conducted against the technical elements in PRA Standard Code Case for Part 5 (Reference 20). For supporting requirements in the Code Case that referred back to requirements in Part 2, Addendum B, of the PRA Standard (ANSE/ANS RA-Sb-2013) was utilized.
"Per PWROG-18062-P (Reference 19):
"This standard, ASME/ANS RA-Sb-2013 (Addendum B), was approved by ANSI in 2013, but has not been formally endorsed by the NRG through a revision to RG 1.200 (Reference 1).
However, Part 5 (Requirements for Seismic Events At-Power PRA) of Addendum B of the PRA Standard is referenced in the Electric Power Research Institute (EPRI) report "Screening, Prioritization and Implementation Details (SPID) for the Resolution of Fukushima Near-Term Task Force Recommendation 2.1: Seismic". NRG has endorsed this EPRI report as "one acceptable method for responding to the information requested in Enclosure 1 of the 50. 54(f) letter" pertaining to Post-Fukushima Near Term Task Force (NTTF) Recommendation 2.1 on seismic hazard re-evaluation. This effectively provides NRG endorsement of Part 5 of Addendum B of the PRA Standard, ASME/ANS RA-Sb-2013. In 2017, the Joint Committee on Nuclear Risk Management (JCNRM) released the Code Case as an acceptable alternative to Part 5 of Addendum B. By letter dated, March 7, 2018, the NRG stated the following:
"The NRG staff has determined that the alternative approach described in the Code Case is consistent with Part 5 of the ASMEIANS PRA standard which the staff has reviewed and endorsed in Regulatory Guide 1.200.
"The NRG acceptance letter of the Code Case included limited clarifications.
"Sections 1-6 and 5-3 of the ASME/ANS PRA Standard include explicit requirements for a peer review of SPRAs against the requirements of Part 5 in the PRA Standard using a written process. The industry has developed the PRA peer review process as defined in NE/ 12-13 to perform the peer reviews for SPRAs and other external hazards PRAs. This was accepted with limited amendments by the NRG in the letter dated March 7, 2018.
"The findings from the Seismic PRA peer review have been addressed in the Seismic PRA model. In August 2019 (AEPDCC-0058-REPT-001), an F&O Closure Review was conducted for CNP. Finding level F&Os for the SPRA model are discussed in Attachment 1 of this enclosure." to AEP-NRC-2024-40 Page 6
Replacement Wording:
"Seismic PRA (SPRA) model
"The seismic PRA model was peer reviewed in November 2018 (Reference 19). This peer review was conducted against the technical elements in PRA Standard Code Case for Part 5 (Reference 20). For supporting requirements in the Code Case that referred back to requirements in Part 2, Addendum B, of the PRA Standard (ANSE/ANS RA-Sb-2013) was utilized. Code Case ASME/ANS RA-S Case 1 was endorsed, with staff exceptions and clarifications, by the NRG in Revision 3 of Regulatory Guide 1.200.
"The findings from the Seismic PRA peer review have been addressed in the Seismic PRA model. In August 2019 (AEPDCC-0058-REPT-001), an F&O Closure Review was conducted for CNP. Finding level F&Os for the SPRA model are discussed in Attachment 1 of this enclosure."
References:
- 1. Letter from K. J. Ferneau, Indiana Michigan Power Company (l&M), to U.S. Nuclear Regulatory Commission (NRC), "Donald C. Cook Nuclear Plant Unit 1 and Unit 2 License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating,"
dated April 3, 2024, Agencywide Documents Access and Management System (ADAMS)
Accession No. ML24094A288.
- 2. Letter from S. P. Wall, NRC, to Q. S. Lies, l&M, "Donald C. Cook Nuclear Plant, Unit Nos. 1 and 2 - Supplemental Information Needed for Acceptance of License Amendment Request to Revise Technical Specification 3.8.1 (EPID No. L-2024-LLA-0040)," dated May 7, 2024, ADAMS Accession No. ML24115A215.
Enclosure 3 to AEP-NRC-2024-40
Donald C. Cook Nuclear Plant Unit 1 Technical Specification Pages Marked to Show Proposed Changes AC Sources - Operating 3.8.1
ACTIONS
NO TE-----------------------------------------------
L CO 3.0.4.b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME
A. One required offsite A.1 ---------------NOTE-----------
circuit inoperable. Not applicable if a required Unit 2 offsite circuit is inoperable.
Perform SR 3.8.1.1 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required OPERABLE offsite circuit. AND
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter
AND
A.2 Declare required feature(s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from with no offsite power discovery of no offsite available inoperable when power to one train its redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)
AND
A.3 Restore required offsite 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s<a>
circuit to OPERABLE status. AND
17 days from discovery of failure to meet LCO 3.8.1.a orb (a) For Train B only, the Completion Time that Train B can be inoperable as specified by Required Action A.3 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" up to "288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br />," to support modification of the Train B Reserve Feed 12AB Loop Feed Enclosure. Upon completion of the modification and restoration this footnote is no longer applicable. Prior to entry into the 288-hour extended Completion Time, the Supplemental Diesel Generators (SDGs) shall be verified as available. During the 288-hour extended Completion Time, the SDGs shall be verified as available once per shift. If the SDGs becomes unavailable after the initial 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while in the extended 288-hour Completion Time period, it shall be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the unit shall be brought to MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This 24-hour period will be allowed only once within the single extended Completion Time. Compensatory measures described within CNP letter AEP-NRC-2024-02, dated April 3, 2024, and supplemented by AEP-NRC-2024-40, dated May 16th, will remain in effect during the extended period. The one-time extension shall expire upon completion of the modification and restoration of operability for Train B.
Cook Nuclear Plant Unit 1 Amendment No. ~. 291 Enclosure 4 to AEP-NRC-2024-40
Donald C. Cook Nuclear Plant Unit 2 Technical Specification Pages Marked to Show Proposed Changes AC Sources - Operating 3.8.1 ACTIONS
NOTE---------------------------------------------------
LCO 3.0.4.b is not applicable to DGs.
CONDITION REQUIRED ACTION COMPLETION TIME
A. One required offsite A.1 ---------------NOTE--------------
circuit inoperable. Not applicable if a required Unit 1 offsite circuit is inoperable.
Perform SR 3.8.1.1 for 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> required OPERABLE offsite circuit. AND
Once per 8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> thereafter AND
A.2 Declare required feature(s) 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> from with no offsite power discovery of no offsite available inoperable when power to one train its redundant required concurrent with feature(s) is inoperable. inoperability of redundant required feature(s)
AND
A.3 Restore required offsite 72 hour8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />s<a>
circuit to OPERABLE status. AND
17 days from discovery of failure to meet LCO 3.8.1.a orb (a) For Train B only, the Completion Time that Train B can be inoperable as specified by Required Action A.3 may be extended beyond the "72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br />" up to "288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br />," to support modification of the Train B Reserve Feed 12AB Loop Feed Enclosure. Upon completion of the modification and restoration this footnote is no longer applicable. Prior to entry into the 288-hour extended Completion Time, the Supplemental Diesel Generators (SDGs) shall be verified as available. During the 288-hour extended Completion Time, the SDGs shall be verified as available once per shift. If the SDGs becomes unavailable after the initial 72 hours8.333333e-4 days <br />0.02 hours <br />1.190476e-4 weeks <br />2.7396e-5 months <br /> while in the extended 288-hour Completion Time period, it shall be made available within 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br />, or the unit shall be brought to MODE 3 within the next 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and MODE 4 within the following 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />. This 24-hour period will be allowed only once within the single extended Completion Time. Compensatory measures described within CNP letter AEP-NRC-2024-02, dated April 3, 2024 and supplemented by AEP-NRC-2024-40, dated May 16th, will remain in effect during the extended period. The one-time extension shall expire upon completion of the modification and restoration of operability for Train B.
Cook Nuclear Plant Unit 2 3.8.1-2 Amendment No. ~. 273 Enclosure 5 to AEP-NRC-2024-40
Regulatory Commitments to Support License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating REGULATORY COMMITMENTS
The following table identifies actions committed to by Indiana Michigan Power Company (l&M) in this document. Any other actions discussed in this submittal represent intended or planned actions by l&M. They are described to the U. S. Nuclear Regulatory Commission (NRC) for the NRC's information and are not regulatory commitments. All commitments discussed in this table are one-time commitments.
Commitment Scheduled Completion Date (if applicable):
The extended AOT will be used no more than once in a 24-month For the duration of the use period ( or refueling interval) on a per diesel basis to perform of the extended one-time EOG maintenance activities, or any major maintenance on offsite Completion Time of 288 power transformer and bus. hours for modification of Train AB Reserve Feed.
For the duration of the use The preplanned maintenance will not be scheduled if severe of the extended one-time weather conditions are anticipated. Completion Time of 288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br /> for modification of Train AB Reserve Feed.
The system load dispatcher will be contacted once per day to For the duration of the use ensure no significant grid perturbations (high grid loading unable of the extended one-time to withstand a single contingency of line or generation outage) are Completion Time of 288 expected during the extended AOT hours for modification of Train AB Reserve Feed.
Component testing or maintenance of safety systems and For the duration of the use important non safety equipment in the offsite power systems that of the extended one-time can increase the likelihood of a plant transient (unit trip) or LOOP Completion Time of 288 will be avoided. In addition, no discretionary switchyard hours for modification of maintenance will be performed. Train AB Reserve Feed.
TS required systems, subsystems, trains, components, and For the duration of the use devices that depend on the remaining power sources will be of the extended one-time verified to be operable and positive measures will be provided to Completion Time of 288 preclude subsequent testing or maintenance activities on these hours for modification of systems, subsystems, trains, components, and devices. Train AB Reserve Feed.
For the duration of the use Steam-driven emergency feed water pump(s), will be controlled of the extended one-time as "guarded equipment." Completion Time of 288 hours0.00333 days <br />0.08 hours <br />4.761905e-4 weeks <br />1.09584e-4 months <br /> for modification of Train AB Reserve Feed.