Similar Documents at Cook |
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Category:Inspection Report
MONTHYEARIR 05000315/20240032024-10-31031 October 2024 Integrated Inspection Report 05000315/2024003 05000316/2024003 07200072/2024001 and Exercise of Enforcement Discretion 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 IR 05000315/20243012024-09-0505 September 2024 NRC Initial License Examination Report 05000315/2024301 and 05000316/2024301 IR 05000315/20240112024-08-30030 August 2024 NRC Inspection Report 05000315/2024011 and 05000316/2024011 and Notice of Violation 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) IR 05000315/20240022024-07-24024 July 2024 Integrated Inspection Report 05000315/2024002 and 05000316/2024002 IR 05000315/20244012024-05-14014 May 2024 – Security Baseline Inspection Report 05000315/2024401 and 05000316/2024401 IR 05000315/20240012024-05-14014 May 2024 Integrated Inspection Report 05000315/2024001 and 05000316/2024001 IR 05000315/20230062024-02-28028 February 2024 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023006 and 05000316/2023006) IR 05000315/20230042024-01-31031 January 2024 Integrated Inspection Report 05000315/2023004 and 05000316/2023004 IR 05000315/20234032023-09-19019 September 2023 Security Baseline Inspection Report 05000315/2023403 and 05000316/2023403 IR 05000315/20230112023-08-31031 August 2023 Functional Engineering Inspection - Commercial Grade Dedication Report 05000315/2023011 and 05000316/2023011 IR 05000315/20230052023-08-24024 August 2023 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2023005 and 05000316/2023005) IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 IR 05000315/20230122023-06-22022 June 2023 Biennial Problem Identification and Resolution Inspection Report 05000315/2023012 and 05000316/2023012 IR 05000315/20235012023-06-21021 June 2023 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2023501 and 05000316/2023501 IR 05000315/20234042023-05-11011 May 2023 D.C. Cook Information Request for the Cyber-Security Baseline Inspection, Notification to Perform Inspection 05000315/2023404 and 05000316/2023404 IR 05000315/20230012023-05-0303 May 2023 Integrated Inspection Report 05000315/2023001 and 05000316/2023001 IR 05000315/20234012023-03-16016 March 2023 – Security Baseline Inspection Report 05000315/2023401 and 05000316/2023401 IR 05000315/20220062023-03-0101 March 2023 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022006 and 05000316/2022006) IR 05000315/20220042023-02-0101 February 2023 Integrated Inspection Report 05000315/2022004 and 05000316/2022004 and Exercise of Enforcement Discretion IR 05000315/20220112022-11-0404 November 2022 Design Basis Assurance Inspection (Teams) Inspection Report 05000315/2022011 and 05000316/2022011 IR 05000315/20220032022-10-28028 October 2022 Integrated Inspection Report 05000315/2022003 and 05000316/2022003 IR 05000315/20224202022-10-19019 October 2022 Cover Letter - Donald C. Cook Nuclear Plant Units 1 and 2 - Security Baseline Inspection Report 05000315/2022420 and 05000316/2022420 IR 05000315/20230102022-09-21021 September 2022 Notification of Post-Approval Site Inspection for License Renewal - Phase IV; IR 05000315/2023010; 05000316/2023010 and RFI IR 05000315/20224012022-09-21021 September 2022 Security Baseline Inspection Report 05000315 2022401 05000316 2022401 Independent Spent Fuel Storage Security Inspection Report 07200072 2022401 IR 05000315/20223012022-08-31031 August 2022 NRC Initial License Examination Report 05000315/2022301; 05000316/2022301 IR 05000315/20220052022-08-24024 August 2022 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2022005 and 05000316/2022005) IR 05000315/20220022022-08-0808 August 2022 Integrated Inspection Report 05000315/2022002 and 05000316/2022002 IR 05000315/20224022022-07-0505 July 2022 Material Control and Accounting Program Inspection Report 05000315/2022402 and 05000316/2022402 ML22165A2012022-06-14014 June 2022 Notification of NRC Baseline Inspection and Request for Information; Inspection Report 05000315/2022001 and 05000316/2022001 ML22129A2052022-05-10010 May 2022 Integrated Inspection Report 05000315/2022001 and 05000316/2022001 IR 05000315/20220012022-05-10010 May 2022 Integrated Inspection Report 05000315/2022001 and 05000316/2022001 IR 05000315/20220102022-04-0505 April 2022 Triennial Fire Protection Inspection Report 05000315/2022010 and 05000316/2022010 ML22084A5812022-03-25025 March 2022 Request for Information for an NRC Triennial Baseline Design Bases Assurance Inspection (Team): Inspection Report 05000315/2022011 05000316/2022011 IR 05000315/20210062022-03-0202 March 2022 Annual Assessment Letter for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2021006 and 05000316/2021006) IR 05000315/20210042022-02-0707 February 2022 Integrated Inspection Report 05000315/2021004 and 05000316/2021004 and Exercise of Enforcement Discretion IR 05000315/20214032021-11-17017 November 2021 Security Baseline Inspection Report 05000315/2021403 and 05000316/2021403 IR 05000315/20210112021-11-15015 November 2021 Design Basis Assurance Inspection (Programs) Inspection Report 05000315/2021011 and 05000316/2021011 IR 05000315/20210032021-10-26026 October 2021 Integrated Inspection Report 05000315/2021003; 05000316/2021003; and 07200072/2021001 IR 05000315/20215012021-10-0606 October 2021 Emergency Preparedness Biennial Exercise Inspection Report 05000315/2021501 and 05000316/2021501 IR 05000315/20210102021-09-0707 September 2021 Biennial Problem Identification and Resolution Inspection Report 05000315/2021010 and 05000316/2021010 IR 05000315/20210052021-09-0101 September 2021 Updated Inspection Plan for Donald C. Cook Nuclear Plant, Units 1 and 2 (Report 05000315/2021005 and 05000316/2021005) IR 05000315/20210132021-08-0303 August 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2021013; 05000316/2021013 IR 05000315/20210122021-08-0202 August 2021 Donald Cook Nuclear Plant - NRC Inspection Report 05000315/2021012 and 05000316/2021012 IR 05000315/20210022021-07-22022 July 2021 Integrated Inspection Report 05000315/2021002 and 05000316/2021002 IR 05000315/20214022021-06-0909 June 2021 Donald D. C. Cook Nuclear Plant - Security Baseline Inspection Report 05000315/2021402 and 05000316/2021402 ML21158A1732021-06-0909 June 2021 Review of the Fall 2017 Steam Generator Tube Inspections Report IR 05000315/20210012021-04-28028 April 2021 Integrated Inspection Report 05000315/2021001 and 05000316/2021001 2024-09-05
[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] Category:Request for Additional Information (RAI)
MONTHYEARML24178A0432024-06-26026 June 2024 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - License Amendment Request Regarding Neutron Flux Instrumentation 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 ML24141A2162024-05-20020 May 2024 —Information Request to Support the NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection ML23352A3502023-12-19019 December 2023 Dc. Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 IR 05000315/20230102022-09-21021 September 2022 Notification of Post-Approval Site Inspection for License Renewal - Phase IV; IR 05000315/2023010; 05000316/2023010 and RFI ML22230A4362022-08-19019 August 2022 Licensed Operator Positive Fitness-For-Duty Test ML22049B4532022-02-22022 February 2022 Notification of NRC Baseline Inspection and Request for Information Report 05000315/2022002 ML21307A3352021-11-0303 November 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Final RAI - License Amendment Request Regarding Containment Water Level Instrumentation IR 05000315/20210132021-08-0303 August 2021 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2021013; 05000316/2021013 ML21140A3052021-05-20020 May 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request ISIR-4-11, Impractical Examinations for the Fourth 10-Year ISI Interval ML21049A2682021-02-16016 February 2021 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit No. 2 - Final RAI - License Amendment Request for One-Time Extension Containment Type a ILRT ML21026A3472021-01-26026 January 2021 NRR E-mail Capture - Final RAI - D.C. Cook 1 & 2 - Relief Request REL-PP2 for Pump and Valve IST Fifth 10-year Interval IR 05000315/20200112020-09-17017 September 2020 Information Request to Support Upcoming Temporary Instruction 2515/194 Inspection; Inspection Report 05000315/2020011; 05000316/2020011 ML20181A4122020-06-29029 June 2020 NRR E-mail Capture - Final RAI - D.C. Cook 1 - One-Time Extension, Containment Type a ILRT Frequency ML20232B4562020-04-27027 April 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Fragility Questions IR 05000315/20200202020-04-10010 April 2020 Units 1 and 2 - Information Request for NRC Triennial Evaluation of Changes, Tests, and Experiments (50.59) Baseline Inspection 05000315/2020020 and 05000316/2020020 ML20232B4432020-03-25025 March 2020 Request for Supporting Information for the D.C. Cook SPRA Audit Review - Plant Response Model Questions ML19267A1362019-09-24024 September 2019 NRC Information Request (September 23, 2019) - IP 71111.08 - DC Cook U2 - Documents Selected for Onsite Review (DRS-M.Holmberg) ML19204A0962019-07-23023 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 and 2 - Request for Additional Information Related to Unit 2 Leak Before Break Analysis and Deletion of Containment Humidity Monitors for Unit Nos. 1 and 2 ML19211C3032019-07-0303 July 2019 NRR E-mail Capture - D.C. Cook Nuclear Plant Unit Nos. 1 & 2 - Request for Additional Information Related to LAR to Address NSAL-15-1 ML19084A0002019-03-20020 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19072A1432019-03-12012 March 2019 NRR E-mail Capture - Resubmitted: Draft Request for Additional Information DC Cook Unit 1 - Leak-Before-Break LAR ML19011A3512019-01-11011 January 2019 NRR E-mail Capture - Request for Additional Information DC Cook Unit 1 Leak Before Break Amendment ML18313A0802018-11-0808 November 2018 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI for RPV Threads in Flange Alternative ML18263A1542018-09-14014 September 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18204A3722018-07-19019 July 2018 NRR E-mail Capture - D.C. Cook Unit No. 1 - RAI for Leak-Before-Break LAR ML18143B6292018-05-29029 May 2018 Dtf. RAI ML18142B5312018-05-29029 May 2018 Request for Additional Information Concerning 2017 Decommissioning Funding Status Report ML18060A0212018-02-28028 February 2018 Enclosurequest for Additional Information (Request for Additional Information Regarding Indiana Michigan Power Company'S Decommissioning Funding Update for Donald C Cook Nuclear Plant Units 1 and 2 ISFSI) ML18043A0092018-02-0909 February 2018 NRR E-mail Capture - DC Cook, Unit 2 - Request for Additional Information Regarding Reactor Vessel Internals Again Management Program ML17304A0102017-11-0101 November 2017 Unit Nos.1 and 2 - Request for Additional Information Regarding Generic Letter 2016-01, Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools (CAC Nos. MF9444 and MF9445; EPID L-2016-LRC-0001) ML17249A7492017-08-28028 August 2017 E-Mail Sent August 28, 2017, Request for Information for Donald C. Cook Nuclear Power Plant, Unit 1 (Part B); Inspection Report 05000315/2017004 (Msh) ML17108A7772017-04-18018 April 2017 17 Donald C. Cook Nuclear Power Plant, Unit 1 - Notification of NRC Baseline Inspection and Request for Information (05000315/2017003; 05000316/2017003) (Msh) ML17068A0652017-03-0808 March 2017 Ltr 03/08/17 Donald C. Cook Nuclear Power Plant, Unit 2 - Information Request for an NRC Post-Approval Site Inspection for License Renewal 05000316/2017009 (Bxj) ML17027A0192017-01-26026 January 2017 NRR E-mail Capture - D.C. Cook Units 1 and 2 - RAI Regarding LAR to Revise TS 5.5.14 (MF8483 and MF8484) ML16211A0152016-08-0101 August 2016 Follow-Up Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control IR 05000315/20160042016-07-11011 July 2016 Donald C. Cook Nuclear Power Plant, Unit 2 - Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16193A6542016-07-11011 July 2016 Notification of NRC Inspection and Request for Information; Inspection Report 05000315/2016004; 05000316/2016004 ML16154A1822016-06-0909 June 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control (CAC Nos. MF7114 and MF7115) ML16127A0792016-05-11011 May 2016 Request for Additional Information Regarding License Amendment Request to Relocate Surveillance Frequencies to Licensee Control ML16025A0552016-01-22022 January 2016 Ltr. 01/22/16 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Pilot Design Bases Inspection on the Implementation of the Environmental Qualification Program Inspection Report 05000315/2016008; 05000316 ML15267A6832015-10-0505 October 2015 Second Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15231A5542015-08-18018 August 2015 Ltr. 08/18/15 Donald C. Cook Nuclear Power Plant, Units 1 and 2 - Request for Information for an NRC Triennial Pilot Baseline Component Design Bases Inspection (Inspection Report 05000315/2015008; 05000316/2015008) (Axd) ML15225A5772015-08-13013 August 2015 Information Request to Support Upcoming Problem Identification and Resolution Inspection at D.C. Cook, Units 1 and 2 ML15163A1672015-06-15015 June 2015 Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.8.1 ML15149A3832015-05-28028 May 2015 Information Request to Support NRC Annual Baseline Emergency Action Level and Emergency Plan Changes Inspection (Mxg) ML15119A3392015-05-0505 May 2015 Follow-up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program Submittal ML15055A5702015-02-24024 February 2015 Cyber Security RFI Temporary Instruction 2201/004 ML15022A1532015-01-21021 January 2015 Dccook ISI Request for Information 2024-06-26
[Table view] |
See also: IR 05000315/2017003
Text
UNITED STATES
NUCLEAR REGULATORY COMMISSION
REGION III
2443 WARRENVILLE RD. SUITE 210
LISLE, IL 60532-4352
April 18, 2017
Mr. Joel P. Gebbie
Senior VP and Chief Nuclear Officer
Indiana Michigan Power Company
Nuclear Generation Group
One Cook Place
Bridgman, MI 49106
SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNIT 1 - NOTIFICATION OF
NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION
(05000315/2017003; 05000316/2017003)
Dear Mr. Gebbie:
On September 18, 2017, the U. S. Nuclear Regulatory Commission (NRC) will begin the
Baseline Inservice Inspection (Procedure 71111.08). This onsite inspection is scheduled to be
performed September 18, 2017, through September 28, 2017.
Experience has shown that this inspection is resource intensive both for the NRC inspector and
your staff. In order to minimize the impact to your on-site resources, and to ensure a productive
inspection for both sides, we have enclosed a request for documents needed for this inspection.
These documents have been divided into two groups. The first group identifies information
necessary to ensure that the inspector is adequately prepared. The second group identifies the
information the inspector will need upon arrival at the site. It is important that all of these
documents are up-to-date, and complete, in order to minimize the number of additional
documents requested during the preparation and/or the onsite portions of the inspection.
We have discussed the schedule for inspection activities with your staff and understand that our
regulatory contact for this inspection will be Mr. M. Ellet, of your organization. If there are any
questions about this inspection or the material requested, please contact the lead inspector
Mr. M. Holmberg at 630-829-9748 or via e-mail at msh@nrc.gov.
This letter does not contain new or amended information collection requirements subject to
the Paperwork Reduction Act of 1995 (44 U.S.C. 3501 et seq.). Existing information collection
requirements were approved by the Office of Management and Budget, Control Number
3150-0011. The NRC may not conduct or sponsor, and a person is not required to respond to,
a request for information or an information collection requirement unless the requesting
document displays a currently valid Office of Management and Budget Control Number.
J. Gebbie -2-
This letter and its enclosure will be made available for public inspection and copying at
http://www.nrc.gov/reading-rm/adams.html and at the NRC Public Document Room in
accordance with 10 CFR 2.390, Public Inspections, Exemptions, Requests for Withholding.
Sincerely,
/RA/
Mel Holmberg
Engineering Branch 1
Division of Reactor Safety
Docket Nos. 50-315; 50-316
License Nos. DPR-58; DPR-74
Enclosure:
Inservice Inspection Document Request
cc: Distribution via LISTSERV
J. Gebbie -3-
Letter to Joel P. Gebbie from Mel Holmberg dated April 18, 2017
SUBJECT: DONALD C. COOK NUCLEAR POWER PLANT, UNIT 1 - NOTIFICATION OF
NRC BASELINE INSPECTION AND REQUEST FOR INFORMATION
(05000315/2017003; 05000316/2017003)
DISTRIBUTION:
Jeremy Bowen
RidsNrrDorlLpl3
RidsNrrPMDCCook Resource
RidsNrrDirsIrib Resource
Cynthia Pederson
Darrell Roberts
Richard Skokowski
Allan Barker
Carole Ariano
Linda Linn
DRPIII
DRSIII
ADAMS Accession Number ML17108A777
OFFICE RIII RIII RIII RIII
NAME MHolmberg:cl
DATE 04/18/17
OFFICIAL RECORD COPY
INSERVICE INSPECTION DOCUMENT REQUEST
Inspection Dates: September, 18 - 28, 2017
Inspection Procedures: IP 71111-08, Inservice Inspection
Lead Inspector: Mel Holmberg, DRS
630-829-9748
msh@nrc.gov
A. Information for the In-Office Preparation Week
The following information is requested as an (electronic copy CD ROM if possible) by
August, 23, 2017, to facilitate the selection of specific items that will be reviewed during
the on-site inspection week. The inspector will select specific items from the information
requested below and a list of additional documents needed on-site from your staff. We
request that the specific items selected from the lists be available and ready for review
on the first day of inspection. The following information is applicable to Unit 1 unless
otherwise indicated. If you have any questions regarding this information, please call the
inspector as soon as possible.
1. For the upcoming outage, a detailed schedule and description of:
a. non-destructive examinations (NDE) planned for Class 1 and 2 Systems and
containment, performed as part of your American Society of Mechanical
Engineers (ASME) Code Inservice Inspection (ISI) Program (include edition and
addenda of Code committed to), and NDEs planned for other systems performed
as part of a Risk-Informed ISI Program, or other augmented inspection programs
(e.g., ASME Code Case N-770-1 examination of dissimilar metal welds and
examinations to meet an industry initiative). For each weld examination, include
the weld identification number, description of weld (component name), category,
class, type of exam and procedure number, and date of examination;
b. reactor vessel upper head examinations required by Title 10 of the Code of
Federal Regulations (CFR), Part 50.55a(g)(6)(ii)(D) and Code Case N-729-1;
c. steam generator (SG) tube inspection and repair activities for the upcoming
outage or SG secondary side examinations 1;
d. welding on Code Class 1, 2, or 3 components; and
e. baffle former bolt examinations as identified in Westinghouse Nuclear Safety
Advisory Letter 16-1 Baffle-Former Bolts, Electric Power Research Institute
(EPRI) MRP 2017-009 Letter dated March 15, 2017 and MRP 2016-022 dated
July 27, 2016.
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Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
and no further information is required for the items identified above requesting SG related information.
Enclosure
INSERVICE INSPECTION DOCUMENT REQUEST
2. A copy of the NDE procedures and welding procedures used to perform the
activities identified in Item A.1 (including NDE calibration and flaw
characterization/sizing procedures and Welding Procedure Qualification Records).
For ultrasonic examination procedures qualified in accordance with Appendix VIII, of
Section XI of the ASME Code, provide documentation supporting the procedure
qualification (e.g., the EPRI performance demonstration qualification summary
sheets).
3. A copy of ASME Section XI, Code Relief Requests applicable to the examinations
identified in Item A.1. This would include the U.S. Nuclear Regulatory Commission
(NRC) approved Relief Request for implementing a risk-informed ISI Program (if
applicable).
4. A copy of the 10-year ISI Program showing those required exams scheduled to be
performed this outage, and those which have been completed.
5. A list identifying NDE reports (ultrasonic, radiography, magnetic particle, or dye
penetrant), which have identified relevant indications on Code Class 1 and 2
Systems since the beginning of the last refueling outage.
6. List with short description of the welds in Code Class 1 and 2 Systems, which have
been fabricated due to component repair/replacement activities since the beginning
of the last refueling outage and identify the system, weld number, and reference
applicable documentation (e.g., NIS-2 forms with definitions of system and
component acronyms).
7. If reactor vessel weld examinations required by the ASME Code are scheduled to
occur during the inspection period, provide a detailed description of the welds to be
examined, and the extent of the planned examination.
8. List with description of ISI and SG related issues such as piping or SG tube
degradation or damage (e.g., cracks, wall thinning, wear, microbiologically induced
corrosion) or errors identified during piping/SG tube examinations that have been
entered into your corrective action system since the beginning of the last refueling
outage. Also, include a list of corrective action records associated with foreign
material introduced/identified in the reactor vessel, primary coolant system, steam
generator or feed systems since the beginning of the last refueling outage.
9. Copy of any 10 CFR Part 21 reports applicable to your structures, systems, or
components within the scope of Section XI of the ASME Code that have been
identified since the beginning of the last refueling outage.
10. Copy of SG history documentation given to vendors performing eddy current (ET)
testing of the SGs during the upcoming outage.1.
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
and no further information is required for the items identified above requesting SG related information.
2
11. Copy of procedure containing screening criteria used for selecting tubes for in-situ
pressure testing and the procedure to be used for in-situ pressure testing. 1
12. Copy of previous outage SG tube operational assessment completed following ET
of the SGs (provide this document even if no SG ET is planned for current outage).
13. Copy of most recent SG Degradation Assessment (provide this document even if no
SG ET is planned for current outage).
14. Copy of most recent SG Condition Monitoring Assessments.1
15. Copy of the document defining the planned SG ET scope (e.g., 100 percent of
unrepaired tubes with bobbin probe and 20 percent sample of hot leg expansion
transition regions with rotating probe) and identify the scope expansion criteria,
which will be applied. Also identify and describe any deviations in this scope or
expansion criteria from the EPRI Guidelines.1
16. Copy of the document describing the ET acquisition equipment to be applied
including ET probe types. Also identify the extent of planned tube examination
coverage with each probe type (e.g., rotating probe - 0.080 inches, 0.115 inches
pancake coils and mid-range + point coil applied at the top-of-tube-sheet plus
3 inches to minus 12 inches).
17. Provide procedures with guidance/instructions for identifying (e.g. physically locating
the tubes that require repair) and plugging SG tubes.1
18. Identify and quantify any SG tube leakage experienced during the previous
operating cycle. Also provide documentation identifying which SG was leaking and
corrective actions completed or planned for this condition.
19. Copy of current calculations for EDY, and RIY as defined in Code Case N-729-1
that establish the volumetric and visual examination frequency for the reactor vessel
head and J-groove welds.
20. Point of contact information (name and site number) for the following activities:
a. ISI - Site and vendor leads
b. Boric Acid Inspections and Evaluations
c. Reactor Vessel Head Inspection - Site and vendor leads
d. Baffle Former Bolt Inspection & Repairs - Site and vendor leads
e. SG Inspection - Site and vendor leads
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
and no further information is required for the items identified above requesting SG related information.
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B. Onsite Information to be Provided to the Inspector on the First Day of the
Inspection (e.g., Following the Entrance Meeting). Please Provide Hard Copies
(e.g., Paper Records) of the Following Documents.
1. For welds selected by the inspector from Item A.1.d and A.6 above, provide copies of
the following documents:
a. Document of the weld number and location (e.g., system, train, branch);
b. Document with a detail of the weld construction (e.g., drawing);
c. Applicable portions of the Design Specification and applicable Code of
construction for the weldment (e.g., B31.1 or ASME Section III);
d. Applicable Code Edition and Addenda for weld procedure qualification;
e. Applicable weld procedure specifications and weld data sheets used to fabricate
the welds;
f. Copies of procedure qualification records supporting the weld procedure
specifications;
g. Copies of welders performance qualification records;
h. Copies of mechanical test reports identified in the prodecure qualification records
above;
i. Copies of the nonconformance reports for the selected welds;
j. Access to radiographs and equipment to view radiographs of the selected welds;
k. ASME Code Section XI repair replacement plan and reconciliation for
replacement components/materials;
l. Certified Material Test Reports for replacement pressure boundary materials; and
m. Copies of the NDE required by the construction Code and the pre-service
examination records required by the ASME Code Section XI for the selected
welds.
2. For the ISI-related corrective action issues selected by the inspector from Item A.8
above, provide a copy of the corrective actions and supporting documentation.
3. For the NDE reports with relevant indications on Code Class 1 and 2 Systems
selected by the inspector from Item A.5 above, provide a copy of the examination
records and associated corrective action documents. Updated schedules for Item
A.1 (including schedule showing contingency repair plans if available).
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4. Copy of the procedures which govern the scope, equipment used, and
implementation of the inspections required to identify boric acid leakage from
systems and components above the vessel head.
5. Copy of:
a. Engineering evaluations/assessments of boric acid related deposits and
associated wastage or corrosion for safety significant components; and
b. Corrective action records for coolant leakage including boric acid deposits on
safety-related components identified since the beginning of the last refueling
outage.
6. Copy of the plant procedures used to perform inspections to identify reactor coolant
system leaks or boric acid deposits and the procedures for resolution of leaks or
boric acid deposits.
7. Fabrication Drawings (D size) of the reactor vessel welds (including vessel head
J-groove welds) if any are to be examined during the outage. Also provide any
drawings used by NDE vendors to locate these welds.
8. Copy of the documents which demonstrate that the procedures to be used for
volumetric examination of the reactor vessel head penetration J-groove welds were
qualified by a blind demonstration test in accordance with 10 CFR 50.55a(g)(6)(ii)(D).
9. Copy of volumetric, surface and visual examination records for the prior inspection of
the reactor vessel head and head penetration J-groove welds.
10. Provide a copy of the EPRI Examination Technique Specification Sheets and vendor
Examination Technique Specification Sheets related documents, which support
qualification of the ET probes to be used during the upcoming SG tube inspections.1
11. Provide a copy of the guidance to be followed if a loose part or foreign material is
identified in the SGs. 1
12. Identify the types of SG tube repair processes which will be implemented for
defective SG tubes (including any NRC reviews/evaluation/approval of this repair
process). Provide the flaw depth sizing criteria to be applied for ET indications
identified in the SG tubes. 1
13. Copy of document describing actions to be taken if a new SG tube degradation
mechanism is identified. 1
1 Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
and no further information is required for the items identified above requesting SG related information.
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14. Provide document which defines the scope of SG secondary side examinations (if
any are planned) and identify site specific operational history related to degradation
of SG secondary side components (if any).
15. Provide procedures with guidance/instructions for identifying (e.g., physically locating
the tubes that require repair) and plugging SG tubes.1
16. Provide a copy of the document that identifies the scope of the Unit 1 baffle former
bolt inspection.
17. Provide a copy of the engineering change, work order and procedures used for baffle
former bolt replacement.
18. Provide a copy of license basis analysis (and NRC acceptance review for this
analysis) for the Unit 1 baffle former assembly and provide a copy of applicable
vendor analysis completed to support inspections and/or anticipated repairs to baffle
former bolts.
19. Provide copies of the following standards at the on-site NRC inspection location for
the duration of the inspection:
a. Sections V, IX, and XI of the ASME Code with Editions applicable to the ISI
Program and the Repair/Replacement Program;
b. Copy of the performance demonstration initiative (PDI) generic procedures
with the latest applicable revisions that support site qualified ultrasonic
examination of piping welds and components (e.g., PDI-UT-1, PDI-UT-2,
PDI-UT-3, PDI-UT-10 etc.);
c. EPRI and industry standards referenced in the site procedures used to
perform the SG tube ET examination, which includes EPRI documents:
TR 107621-R1, Steam Generator Integrity Assessment Guidelines,
TR-107620-R1, Steam Generator In-Situ Pressure Test Guidelines, Steam
Generator Management Program: Steam Generator Integrity Assessment
Guidelines, Part 10, and 1003138, Pressurized1 Water Reactor Steam
Generator Examination Guidelines1; and
d. Boric Acid Corrosion Guidebook Revision 1 - EPRI Technical Report 1000975.
20. Provide training (e.g., Scaffolding, Fall Protection, Foreign Material Exclusion) if
required to access the NDEs selected by the inspector for observation.
If you have questions regarding the information requested, please contact the lead inspector.
1
Note 1- If no SG examinations are planned for this outage, please confirm when the next SG examination will occur
and no further information is required for the items identified above requesting SG related information.
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