|
|
Line 1: |
Line 1: |
| #REDIRECT [[AEP-NRC-2013-58, Donald C. Cook, Unit 1, Withdrawal of Licensee Event Report (LER) 12-002-00]] | | {{Adams |
| | | number = ML13211A315 |
| | | issue date = 07/25/2013 |
| | | title = Donald C. Cook, Unit 1, Withdrawal of Licensee Event Report (LER) 12-002-00 |
| | | author name = Gebbie J P |
| | | author affiliation = Indiana Michigan Power Co |
| | | addressee name = |
| | | addressee affiliation = NRC/Document Control Desk, NRC/NRR |
| | | docket = 05000315 |
| | | license number = |
| | | contact person = |
| | | case reference number = AEP-NRC-2013-58 |
| | | document report number = LER 12-002-00 |
| | | document type = Letter |
| | | page count = 2 |
| | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:INDIANA MICHIGAN POWER 0 A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, MI 49106 IndianaMichiganPower.com AEP-NRC-2013-58 10 CFR 50.73 July 25, 2013 Docket No.: 50-315 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 WITHDRAWAL OF LICENSEE EVENT REPORT 315/2012-002-00 In accordance with the criteria established by NUREG-1022, Revision 3, Section 5, Licensee Event Reports, the following Licensee Event Report (LER) is being withdrawn: |
| | LER 315/2012-002-00: "Unit 1 Exceeded Technical Specification Time Limit to Shutdown." By letter dated September 14, 2012, Indiana Michigan Power (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP), submitted LER 315/2012-002-00, "Unit 1 Exceeded Technical Specification Time Limit to Shutdown." At that time, CNP understood that the location of the wiring failure (failed wiring splice) affected the actuation function (Engineered Safety Features Actuation System) rather than the component (Steam Generator Stop Valve).Based on additional investigation, CNP has determined that the wiring failure instead affected the component rather than the actuating function. |
| | Consequently, the incorrect Technical Specification (TS) action statement for TS 3.3.2 was entered instead of TS 3.7.2. Repairs were completed in a time-frame such that Unit 1 would not have exceeded the TS 3.7.2 time limit to shutdown. |
| | As a result, I&M is withdrawing LER 315/2012-002-00. |
| | There are no commitments contained in this submittal. |
| | 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 RAW/db~.A. ~L-(L. |
| | U.S. Nuclear Regulatory Commission AEP-NRC-2013-58 Page 2 c: LEReventscinpo.orq (e-mail only)J. T. King -MPSC S. M. Krawec -AEP Ft. Wayne MDEQ -RMD/RPS NRC Resident Inspector C. A. Casto -NRC Region III T.J. Wengart -NRC Washington DC}} |
Similar Documents at Cook |
---|
Category:Letter
MONTHYEARAEP-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-2024-51, Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes2024-08-28028 August 2024 Annual Report of Loss-Of-Coolant Accident Evaluation Model Changes 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 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 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 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 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 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 ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection 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 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-2024-26, 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 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 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 AEP-NRC-2024-29, (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-072024-04-0303 April 2024 (CNP) Unit 2 - Request for Relief Related to American Society of Mechanical Engineers (ASME) Code Case N-729-6 Supplemental Examination Requirements, ISIR-5-07 AEP-NRC-2024-19, Annual Report of Property Insurance2024-04-0101 April 2024 Annual Report of Property Insurance 2024-09-09
[Table view] |
Text
INDIANA MICHIGAN POWER 0 A unit of American Electric Power Indiana Michigan Power Cook Nuclear Plant One Cook Place Bridgman, MI 49106 IndianaMichiganPower.com AEP-NRC-2013-58 10 CFR 50.73 July 25, 2013 Docket No.: 50-315 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 1 WITHDRAWAL OF LICENSEE EVENT REPORT 315/2012-002-00 In accordance with the criteria established by NUREG-1022, Revision 3, Section 5, Licensee Event Reports, the following Licensee Event Report (LER) is being withdrawn:
LER 315/2012-002-00: "Unit 1 Exceeded Technical Specification Time Limit to Shutdown." By letter dated September 14, 2012, Indiana Michigan Power (I&M), the licensee for Donald C. Cook Nuclear Plant (CNP), submitted LER 315/2012-002-00, "Unit 1 Exceeded Technical Specification Time Limit to Shutdown." At that time, CNP understood that the location of the wiring failure (failed wiring splice) affected the actuation function (Engineered Safety Features Actuation System) rather than the component (Steam Generator Stop Valve).Based on additional investigation, CNP has determined that the wiring failure instead affected the component rather than the actuating function.
Consequently, the incorrect Technical Specification (TS) action statement for TS 3.3.2 was entered instead of TS 3.7.2. Repairs were completed in a time-frame such that Unit 1 would not have exceeded the TS 3.7.2 time limit to shutdown.
As a result, I&M is withdrawing LER 315/2012-002-00.
There are no commitments contained in this submittal.
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 RAW/db~.A. ~L-(L.
U.S. Nuclear Regulatory Commission AEP-NRC-2013-58 Page 2 c: LEReventscinpo.orq (e-mail only)J. T. King -MPSC S. M. Krawec -AEP Ft. Wayne MDEQ -RMD/RPS NRC Resident Inspector C. A. Casto -NRC Region III T.J. Wengart -NRC Washington DC