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Category:Letter type:AEP
MONTHYEARAEP-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 AEP-NRC-2024-69, Core Operating Limits Report2024-09-0909 September 2024 Core Operating Limits Report 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 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 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 AEP-NRC-2024-47, Form OAR-1, Owners Activity Report2024-07-30030 July 2024 Form OAR-1, Owners Activity Report AEP-NRC-2024-52, Manual Reactor Trip Following Rapid Downpower for Steam Leak2024-07-15015 July 2024 Manual Reactor Trip Following Rapid Downpower for Steam Leak 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 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 AEP-NRC-2024-23, Core Operating Limits Report2024-05-23023 May 2024 Core Operating Limits Report AEP-NRC-2024-30, 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 AEP-NRC-2024-26, Transmittal of Donald C. 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Transmittal of Report of Changes to the Emergency Plan2022-10-12012 October 2022 Unit 2 - Transmittal of Report of Changes to the Emergency Plan 2024-09-09
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MICNIGAN Indiana Michigan Power One Cook Place Bridgman, MI 49106 A unit of American Electric Power IndianaMichiganPower.com July 3, 2012 AEP-NRC-2012-50 10 CFR 50.55a Docket Nos.: 50-316 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555-0001 Donald C. Cook Nuclear Plant Unit 2 Form OAR-i, Owner's Activity Report This letter provides a copy of Form OAR-i, Owner's Activity Report for inservice inspection activities' performed at Donald C. Cook Nuclear Plant (CNP) Unit 2 through the completion of the U2C20 refueling outage. This report meets the requirements of the American Society of Mechanical Engineers (ASME) Code Case N-532-4, "Repair/Replacement Activity Documentation Requirements and Inservice Summary Report Preparation and Submission, Section Xl, Division 1."
This code case is used as an alternative to the requirements of the ASME Boiler and Pressure Vessel Code,Section XI, Article IWA-6000 as approved by Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability, ASME Section Xl, Division 1, Revision 16."
The Authorized Code Inspection Company is One CIS Insurance Co., of Lynn, Massachusetts. The Authorized Nuclear Inspector is Reuel Schenck.
There are no new or revised commitments in this letter. Should you have any questions, please contact Mr. Michael K. Scarpello, Regulatory Affairs Manager, at (269) 466-2649.
Sincerely, Miq H Carlson Site Support Serlvices Vice President MCS/kmh Enclosure D.C. Cook Nuclear Unit 2, Form OAR-i, Owner's Activity Report r4~-V7
U.S. Nuclear Regulatory Commission AEP-NRC-2012-50 Page 2 c: C.A. Casto - NRC Region III 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 P. K. Tam - NRC Washington, DC
For O R-'--O, e'sActiv ityi R60r. ~.
Report Number 2-2012-4-1-02 Plant Donald C. Cook Nuclear Plant, One Cook Place, Bridgman, Michigan 49106 (Name and Address of Plant)
Unit No. 2 Commercial Service Date 71111978 Refueling Outage No. U2C20 Cifapplicable)
Current Inspection Interval 4th for Components and Supports (C&S) and 2nd for Containment IS[ (CISI) Program (1st, 2nd, 3rd, 4th, other)
Current Inspection Period 1st for C&S and 1st for CISI (1st, 2nd, 3rd)
Edition and Addenda of Section XI applicable to the inspection plans 2004 Edition/No Addenda Date and Revision of inspection plans 4/5/2011, Revision 2 for C&S, and 6/22/2011, Revision 1 for CISI Edition and Addenda of Section Xi applicable to repair/replacement activities, if different than the inspection plans Edition and Addenda same as the inspection plans Code Case used: N-460, N-532-4, N-552, N-566-2, N-624, N-716, N-722 and N-729-1 for C&S and N-649 for CISI (If applicable)
CERTIFICATE OF CONFORMANCE I certify that (a) the statements made in this report are correct; (b) the examinations and tests meet the Inspection Plan as required by the ASME Code,Section XI; and (c) the repair/replacement activities and evaluations supporting the completion of U2C20 conform to the requirements of Section XI. (Refueling Outage Number)
Signed wnesOwer DesieDateT -,AU) 21, vi Owners or Owner's Designee, Title CERTIFICATE OF INSERVICE INSPECTION I, the undersigned, holding a valid commission issued by the National Board of Boiler and Pressure Vessel Inspectors and the State or Province of Michigan and employed by One CIS Insurance Co. of Lynn, MA have inspected the items described in this Owner's ActivityReport, and state that, to the best of my knowledge and belief, the Owner has performed all activities represented by this report in accordance with the requirements of Section Xl.
By signing this certificate neither the Inspector nor his employer makes any warranty, expressed or implied, concerning the repair/replacement activities and evaluation described in this report. Furthermore, neither the Inspector nor his employer shall be liable in any manner for any personal injury or property damage or loss of any kind arising from or connected with this inspection.
T1 -6.04 5/.-_4t, iCommissions Michigan 300959, NB 11412, Endorsements: A I N NS Inst pector's Signature National Board, State, Province, and Endorsements Date G-ZI-Z- .
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D.C. Cook Nuc~lear Unit 2 Items with flaws or relevant conditions that required evaluation for continued service Examination Item Number Item Description Evaluation Description Category OM ISTD ISTD-4200 The common hydraulic fluid reservoir to Steam Generator snubbers 2-OME There was an Operational Readiness Test Evaluation performed in 1-HSD-3L and 2-OME-3-1-HSD-3U was found empty. accordance with ISTD-4240. The snubbers passed the functional tests. Leaks were repaired in the 3U snubber assembly and tubing fittings. The remaining snubbers were acceptable.
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fAUbL[dk;L VIj ~ ((J II~1 ~III required for continued service Code Class Item Description Description of Work Date Complete Repair/ Replacement Plan Number 1 Steam Generator 2-OME-3-2 Tube Plugging Mechanical tube plugging of 1 tube due to uninspectable 4/8/12 Work Order Task 55309882-22 I_ region due to probe restriction.
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