Letter Sequence Request |
---|
|
|
MONTHYEARML13267A3152013-09-13013 September 2013 Donald C. Cook, Units 1 & 2, Revised Seismic Walkdown Report Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Dai-ichi Accident Project stage: Request ML13294A5432013-11-21021 November 2013 Audit Report Regarding Seismic Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident Project stage: Other ML14035A3512014-01-29029 January 2014 Donald C. Cook, Units 1 & 2, Final Seismic Walkdown Report Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident Project stage: Request ML14073A7592014-03-31031 March 2014 Staff Assessment of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident Project stage: Other 2013-09-13
[Table View] |
Similar Documents at Cook |
---|
Category:Legal-Affidavit
MONTHYEARAEP-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-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-2022-03, 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-2021-28, 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 AEP-NRC-2020-50, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2020-07-0909 July 2020 Response to Request for Additional Information Regarding 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-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-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-2017-52, Enclosure 3: Donald C. Cook Nuclear Plant Unit 2, Application for Withholding Proprietary Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program from Public Disclosure2017-12-0808 December 2017 Enclosure 3: Donald C. Cook Nuclear Plant Unit 2, Application for Withholding Proprietary Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program from Public Disclosure 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-2014-56, First Response to Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2014-07-30030 July 2014 First Response to Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML13267A3152013-09-13013 September 2013 Donald C. Cook, Units 1 & 2, Revised Seismic Walkdown Report Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Dai-ichi Accident AEP-NRC-2012-38, Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation2012-06-11011 June 2012 Response to Request for Information, 10 CFR 50.46 Report for Emergency Core Cooling System Model Change or Error Associated with Thermal Conductivity Degradation ML0519903592005-07-0505 July 2005 Correction of Administrative Error for Improved Technical Specifications ML0317506392003-06-20020 June 2003 Updated Affidavits for Withholding Proprietary Information ML0201704012002-01-14014 January 2002 License Amendment Request for Pressurizer Code Safety Valve Setpoint Tolerance ML18219D7921978-05-23023 May 1978 Letter from Exxon Nuclear Co, Inc. to NRC, Transmitting Copies of Supplement 4 (Report) to Document XN-76-51 for Staff Review 2023-08-02
[Table view] Category:Letter
MONTHYEAR05000316/LER-2024-004, AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications2024-11-11011 November 2024 AB Emergency Diesel Generator Inoperable for Longer than Allowed by Technical Specifications IR 05000315/20240032024-10-31031 October 2024 Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion AEP-NRC-2024-77, U2C28 Steam Generator Tube Inspection Report2024-10-21021 October 2024 U2C28 Steam Generator Tube Inspection Report AEP-NRC-2024-80, Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask2024-10-15015 October 2024 Independent Spent Fuel Storage Installation Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-79, Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask2024-09-26026 September 2024 Unit 2, Independent Spent Fuel Storage Installation - Registration of Dry Spent Storage Cask AEP-NRC-2024-78, Reply to a Notice of Violation: EA-24-0472024-09-23023 September 2024 Reply to a Notice of Violation: EA-24-047 05000316/LER-2024-002-01, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-09-12012 September 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak IR 05000315/20244022024-09-10010 September 2024 Security Baseline Inspection Report 05000315/2024402 and 05000316/2024402, Independent Spent Fuel Storage Installation Security Inspection Report 07200072/2024401 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 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 IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation 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 AEP-NRC-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes 05000316/LER-2024-003, Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage2024-08-22022 August 2024 Plant Shutdown Required by Technical Specifications Due to Reactor Coolant System Identified Leakage IR 05000315/20240052024-08-21021 August 2024 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2024005 and 05000316/2024005) AEP-NRC-2024-61, Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request2024-08-15015 August 2024 Unit 2 - Response to Request for Additional Information for Neutron Flux Instrumentation License Amendment Request ML24221A2702024-08-0808 August 2024 Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask AEP-NRC-2024-62, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-08-0707 August 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask ML24256A1482024-08-0202 August 2024 2024 Post Examination Submittal Letter AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report ML24183A0162024-07-25025 July 2024 Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report ML24169A2142024-07-25025 July 2024 Issuance of Amendment No. 362 Regarding Change to Technical Specification 3.4.12, Low Temperature Overpressure Protection System IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 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 05000316/LER-2024-002, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak ML24191A0692024-07-0909 July 2024 Operator Licensing Examination Approval - Donald C. Cook Nuclear Power Plant, July 2024 AEP-NRC-2024-56, Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask2024-07-0808 July 2024 Unit 2, Independent Spent Fuel Storage Installation, Registration of Dry Spent Fuel Storage Cask 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 ML24176A1012024-06-21021 June 2024 57143-EN 57143 - Paragon Energy Solutions - Update 1 (Final) - 10CFR Part 21 Final Notification: P21-05242024-FN, Rev. 0 AEP-NRC-2024-45, Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring2024-06-13013 June 2024 Report Per Technical Specification 5.6.6 for Inoperability of Post Accident Monitoring Neutron Flux Monitoring ML24163A0132024-06-12012 June 2024 Request for Information for the NRC Age-Related Degradation Inspection: Inspection Report 05000315/2024012 and 05000316/2024012 ML24159A2522024-05-30030 May 2024 10 CFR 50.71(e) Update and Related Site Change Reports AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 05000316/LER-2024-001, Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip2024-05-20020 May 2024 Reactor Trip Due to Main Turbine Trip from a High-High Thrust Bearing Position Trip 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-2024-41, Annual Radiological Environmental Operating Report2024-05-15015 May 2024 Annual Radiological Environmental Operating Report IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 AEP-NRC-2024-26, Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 492024-05-14014 May 2024 Transmittal of Donald C. Cook Nuclear Plant, Emergency Plan Revision 49 AEP-NRC-2024-07, Unit 2 - Transmittal of Report of Changes to the Emergency Plan2024-05-14014 May 2024 Unit 2 - Transmittal of Report of Changes to the Emergency Plan AEP-NRC-2024-24, Form OAR-1, Owners Activity Report2024-05-0707 May 2024 Form OAR-1, Owners Activity Report ML24115A2152024-05-0707 May 2024 LTR: CNP Non-Acceptance with Opportunity TS 3-8-1 ML24256A1472024-05-0606 May 2024 DC Cook 2024 NRC Examination Submittal Letter: Submittal ML24116A0002024-05-0202 May 2024 – Regulatory Audit in Support of Review of the Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors AEP-NRC-2024-35, Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations2024-04-30030 April 2024 Response to NRC Regulatory Issue Summary 2024-01 Preparation and Scheduling of Operator Licensing Examinations AEP-NRC-2024-28, 2023 Annual Radioactive Effluent Release Report2024-04-29029 April 2024 2023 Annual Radioactive Effluent Release Report AEP-NRC-2024-31, Annual Report of Individual Monitoring2024-04-24024 April 2024 Annual Report of Individual Monitoring 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 2024-09-09
[Table view] |
Text
INDIANA MICHIGAN POWERO A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, MI 49106 Indiana Michiga nPower.com September 13, 2013 AEP-NRC-2013-74 10 CFR 50.54(f)U.S. Nuclear Regulatory Commission ATTN: Document Control Desk 11555 Rockville Pike, Rockville, MD 20852
Subject:
Donald C. Cook Nuclear Plant Unit 1 and Unit 2 Revised Seismic Walkdown Report Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
References:
- 1. Letter from the U. S. Nuclear Regulatory Commission, "Donald C. Cook Nuclear Plant Unit 1 and Unit 2 Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated March 12, 2012, ADAMS Accession Number ML 12045A046.
- 2. Letter from J. P. Gebbie, Indiana Michigan Power Company to U. S. Nuclear Regulatory Commission document Control Desk, "Donald C. Cook Nuclear Plant Units 1 and 2 180-Day Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident," dated November 26, 2012, ADAMS Accession Number ML 12340A442.
- 3. Letter from the U. S. Nuclear Regulatory Commission to L. J. Weber, Indiana Michigan Power Company, "Plan for the Regulatory Audit Regarding Seismic Walkdowns at the Donald C. Cook Nuclear Plant, Units 1 and 2, to Support Implementation of Near-Term Task Force Recommendation
2.3 Related
to the Fukushima Dai-ichi Nuclear Power Plant Accident (TAC Nos. MF1648 and MF1649)," dated June 12, 2013, ADAMS Accession Number ML 13143A439.
By Reference 1, the U. S. Nuclear Regulatory Commission (NRC) requested Indiana Michigan Power Company (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP), to provide further information to support the NRC staff's evaluation of regulatory actions to be taken in response to lessons learned from Japan's Fukushima Dai-ichi Nuclear Power Plant accident.
The request addressed the methods and procedures for plants to conduct seismic and flooding hazards walkdowns to identify and address degraded, nonconforming, A4oo U. S. Nuclear Regulatory Commission AEP-NRC-2013-74 Page 2 or unanalyzed conditions through the corrective action program, and to verify the adequacy of the monitoring and maintenance procedures.
By Reference 2, I&M, submitted the Seismic Walkdown Report as requested per Enclosure 3 of Reference 1, "Recommendation 2.3: Seismic" for CNP Units 1 and 2 to the Nuclear Regulatory Commission (NRC). Reference 3 notified I&M of the NRC staff plans to conduct a regulatory audit on July 17-19, 2013, to verify information and gain a better understanding of I&M's conduct of the seismic walkdowns at CNP.Based on the results of this regulatory audit, I&M has revised CNP's Seismic Walkdown Report. Enclosure 1 to this letter provides an affirmation.
Enclosure 2 provides CNP's revised Seismic Walkdown Report.This letter contains no new regulatory commitments.
Should you have any questions concerning the content of this letter, please contact Mr. Michael K. Scarpello, Manager, Nuclear Regulatory Affairs, at (269) 466-2649.Sincerely, Q Shane Lies Vice President, Indiana Michigan Power DB/amp
Enclosures:
- 1. Affirmation
- 2. Seismic Walkdown Report, Revision 1 c: J. T. King, MPSC, w/o enclosures S. M. Krawec, AEP Ft. Wayne, w/o enclosures MDEQ -RMD/RPS, w/o enclosures NRC Resident Inspector, (Enclosure 2 on CD)C. D. Pederson, NRC Region III, (Enclosure 2 on CD)T. J. Wengert, NRC Washington, DC, (Enclosure 2 on CD)
Enclosure 1 to AEP-NRC-2013-74 AFFIRMATION I, Q. Shane Lies, being duly sworn, state that I am a 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 Q. Shane Lies Vice President, Indiana Michigan Power SWORN TO AND SUBSCRIBED BEFORE ME THIS \, DAY OF ,2013 y CNary tQZbF \My Commission Expires Z,-%- DANIELLE BURGOYNE Notary Public. State of Michigan County of Berrien My Commission Expires O0O-4-2O18 Acting In the County of k