ML18219E126
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ML18219E126 | |
Person / Time | |
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Site: | Cook ![]() |
Issue date: | 04/14/1975 |
From: | Tillinghast J Indiana Michigan Power Co, (Formerly Indiana & Michigan Power Co) |
To: | Kniel K Office of Nuclear Reactor Regulation |
References | |
Download: ML18219E126 (33) | |
Similar Documents at Cook | |
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Category:Letter
MONTHYEARAEP-NRC-2024-62, Unit 2 Independent Spent Fuel Storage Installation - Registration of Dry Spent Fuel Storage Cask2024-08-0808 August 2024
[Table view]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 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 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 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 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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Cook Nuclear Power Plant, Units 1 Biennial Licensed Operator Requalification Program Inspection and Request for Information ML23338A2642023-12-0505 December 2023 Confirmation of Initial License Examination AEP-NRC-2023-45, Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation2023-11-16016 November 2023 Unit 2 - Schedular Exemption for Enhanced Weapons, Firearms, Background Checks, and Security Event Notifications Implementation IR 05000315/20234042023-11-0606 November 2023 Cyber Security Inspection Report 05000315/2023404 and 05000316/2023404 ML23310A1152023-11-0606 November 2023 Notification of the NRC Baseline Inspection and Request for Information, Inspection Report 05000316/2024002 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 ML23242A1832023-08-30030 August 2023 Notification of NRC Baseline Inspection and Request for Information; Inspection Report05000315/2023004 AEP-NRC-2023-40, Annual Report of Loss-of-Coolant Accident Evaluation Model Changes2023-08-29029 August 2023 Annual Report of Loss-of-Coolant Accident Evaluation Model Changes IR 05000315/20234022023-08-11011 August 2023 Security Baseline Inspection Report 05000315/2023402 and 05000316/2023402 AEP-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 IR 05000315/20230022023-07-24024 July 2023 Integrated Inspection Report 05000315/2023002 and 05000316/2023002 ML23178A2422023-06-28028 June 2023 Reassignment of the U.S. Nuclear Regulatory Commission Branch Chief in the Division of Operating Reactor Licensing for Plant Licensing Branch III 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 AEP-NRC-2023-29, Core Operating Limits Report2023-06-19019 June 2023 Core Operating Limits Report ML23159A0192023-06-13013 June 2023 Information Meeting with a Question and Answer Session to Discuss NRC 2022 End-Of-Cycle Plant Performance Assessment of Donald C. Cook Nuclear Plant, Units 1 and 2 2024-08-08 Category:Report MONTHYEARML24183A0162024-07-25025 July 2024
[Table view]Review of Reactor Vessel Material Surveillance Program Capsule W Technical Report 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-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022 Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring AEP-NRC-2022-46, Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in2022-12-12012 December 2022 Notification of Deviation from Electric Power Research Institute (EPRI) Materials Reliability Program 2019-008, Interim Guidance for NEI 03-08 Needed Requirements for Us PWR Plants for Management of Thermal Fatigue in ML22340A1762022-11-30030 November 2022 Commitment Change Summary October 2020 to May 2022 ML22340A1992022-11-30030 November 2022 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2) ML22340A2132022-11-30030 November 2022 R1900-0024-001, Revision 13, NFPA 805 Nuclear Safety Capability Assessment AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2021-44, Form OAR-1, Owner'S Activity Report2021-08-12012 August 2021 Form OAR-1, Owner'S Activity Report ML21125A5582021-04-19019 April 2021 Report 2019, Commitment Change Summary, May 2019 to October 2020 ML21125A5392021-04-19019 April 2021 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2), Boration System Functionality Requirement Change in Mode 4 EA-21-024, Notice of Enforcement Discretion2021-03-0404 March 2021 Notice of Enforcement Discretion for Donald C. Cook Nuclear Plant, Units 1 and 2 AEP-NRC-2021-07, Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level2021-01-28028 January 2021 Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level AEP-NRC-2020-28, CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations2020-05-0606 May 2020 CFR 72.48(d)(2) Summary Report of Completed Changes, Tests, and Experiments 1O CFR 72.48 Evaluations AEP-NRC-2020-23, Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2020-04-30030 April 2020 Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML20108E9992020-03-0505 March 2020 Enclosure 7 - LTR-SCS-19-50, Revision 0, D.C. Cook Unit 1 Low Temperature Overpressure Protection System (Ltops) Analysis for 48 EFPY, Dated March 5, 2020, Attachment 2 Only (Non-Proprietary) ML20108F0002020-02-28028 February 2020 Enclosure 5 - WCAP-18455-NP, Revision 1, D.C. Cook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, Westinghouse Electric Company, February 2020. (Non-Proprietary) ML18334A2712018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D.C. Cook, Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break. ML18274A0952018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D. C. Cook Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break, September 2018 (Non-Proprietary) AEP-NRC-2018-36, Notification of Initial Renewable Operating Permit2018-05-0909 May 2018 Notification of Initial Renewable Operating Permit AEP-NRC-2018-21, 30-Day Report of Changes to or Errors in an Evaluation Model2018-05-0404 May 2018 30-Day Report of Changes to or Errors in an Evaluation Model ML18026A8822018-02-0505 February 2018 Staff Assessment of Flooding Focused Evaluation ML18334A2692018-01-31031 January 2018 WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology. ML18334A2682018-01-31031 January 2018 WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology (Non-Proprietary) ML18334A2702018-01-31031 January 2018 WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis for D.C. Cook, Units 1 and 2, Using Leak-Before-Break Methodology. ML17151A9672017-06-14014 June 2017 Flood Hazard Mitigation Strategies Assessment ML16313A1172016-10-10010 October 2016 1BTl1V001-RPT-01, Donald C. Cook Focused Scope Peer Review - Pre-Initiator Human Reliability Analysis. ML16127A3352016-05-0606 May 2016 Reactor Oversight Process Task Force FAQ Log-April 13, 2016 ML16113A1982016-04-20020 April 2016 Precursor Screening Analysis- Reject ML16169A1182016-03-31031 March 2016 RWA-1313-015, Rev. 1, AST Radiological Analysis Technical Report. ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. AEP-NRC-2015-83, Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)2015-10-0101 October 2015 Revision 1 of Final Integrated Plan Regarding March 12, 2012, NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049) ML15233A0242015-08-19019 August 2015 Transmittal of Annual Report of Loss-of-Coolant Accident Evaluation Model Changes ML14253A3172014-09-0404 September 2014 Enclosure 2: I&M CAP Document AR 2010-1804-10, Root Cause Evaluation Attachment, Rx Vessel Core Support Lug Bolting Anomalies ML14147A3292014-06-18018 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14181A5382014-06-0505 June 2014 Enclosure 5 to AEP-NRC-2014-42, Attachment #2 (NP-Attachment) of Westinghouse Letter, LTR-PL-14-22, Westinghouse Responses to NRC, Request for Additional Information on the Application for Amendment to Restore.. 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 ML14092A3302014-03-17017 March 2014 Document No. 13Q3208-RPT-003, Revion 1, Seismic Hazard and Screening Report for the Cook Nuclear Plant (Cnp), Enclosure 2 to AEP-NRC-2014-25 AEP-NRC-2014-15, 30 Day Report of Changes to or Errors in an Evaluation Model2014-02-27027 February 2014 30 Day Report of Changes to or Errors in an Evaluation Model ML13337A3252014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) AEP-NRC-2014-08, SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-4042014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-404 ML14035A3642014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-1 Through Page D-91 ML14035A3682014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-241 Through Page D-321 ML14035A3672014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-170 Through Page D-240 ML14035A3662014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-92 Through Page D-169 ML14035A3522014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Cover Through Page B-312 ML14035A3532014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-1 Through Page C-114 ML14035A3552014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-405 Through End ML14035A3562014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-115 Through Page C-231 ML14035A3572014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-232 Through Page C-353 2024-07-25 Category:Technical MONTHYEARAEP-NRC-2022-66, Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring2022-12-15015 December 2022
[Table view]Report Per Technical Specification 5.6.6 for Inoperability of Unit 2 Post Accident Monitoring Neutron Flux Monitoring ML22340A2132022-11-30030 November 2022 R1900-0024-001, Revision 13, NFPA 805 Nuclear Safety Capability Assessment ML22340A1992022-11-30030 November 2022 Report of Changes, Tests, Experiments Pursuant to 10 CFR 50.59(d)(2) ML22340A1762022-11-30030 November 2022 Commitment Change Summary October 2020 to May 2022 AEP-NRC-2022-58, U1C31 Steam Generator Tube Inspection Report2022-10-24024 October 2022 U1C31 Steam Generator Tube Inspection Report AEP-NRC-2021-07, Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level2021-01-28028 January 2021 Supplement to Report Per Technical Specification 5.6.6, Lnoperability of Unit 1, Post Accident Monitoring, Containment Water Level AEP-NRC-2020-23, Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography2020-04-30030 April 2020 Request for Use of Encoded Phased Array Ultrasonic Examination Techniques in Lieu of Radiography ML20108E9992020-03-0505 March 2020 Enclosure 7 - LTR-SCS-19-50, Revision 0, D.C. Cook Unit 1 Low Temperature Overpressure Protection System (Ltops) Analysis for 48 EFPY, Dated March 5, 2020, Attachment 2 Only (Non-Proprietary) ML20108F0002020-02-28028 February 2020 Enclosure 5 - WCAP-18455-NP, Revision 1, D.C. Cook Unit 1 Heatup and Cooldown Limit Curves for Normal Operation, Westinghouse Electric Company, February 2020. (Non-Proprietary) ML18334A2712018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D.C. Cook, Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break. ML18274A0952018-09-30030 September 2018 WCAP-18394-NP, Revision 1, Fatigue Crack Growth Evaluations of D. C. Cook Units 1 and 2 RHR, Accumulator, and Safety Injection Lines Supporting Expanded Scope Leak-Before-Break, September 2018 (Non-Proprietary) ML18334A2692018-01-31031 January 2018 WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology. ML18334A2682018-01-31031 January 2018 WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis for D.C. Cook Units 1 and 2, Using Leak-Before-Break Methodology (Non-Proprietary) ML18334A2702018-01-31031 January 2018 WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis for D.C. Cook, Units 1 and 2, Using Leak-Before-Break Methodology. ML16313A1172016-10-10010 October 2016 1BTl1V001-RPT-01, Donald C. Cook Focused Scope Peer Review - Pre-Initiator Human Reliability Analysis. ML16169A1182016-03-31031 March 2016 RWA-1313-015, Rev. 1, AST Radiological Analysis Technical Report. ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. ML14253A3172014-09-0404 September 2014 Enclosure 2: I&M CAP Document AR 2010-1804-10, Root Cause Evaluation Attachment, Rx Vessel Core Support Lug Bolting Anomalies ML14147A3292014-06-18018 June 2014 Staff Assessment of the Flooding Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-ichi Nuclear Power Plant Accident ML14092A3302014-03-17017 March 2014 Document No. 13Q3208-RPT-003, Revion 1, Seismic Hazard and Screening Report for the Cook Nuclear Plant (Cnp), Enclosure 2 to AEP-NRC-2014-25 ML13337A3252014-01-24024 January 2014 Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) ML14035A3642014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-1 Through Page D-91 AEP-NRC-2014-08, SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-4042014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-322 Through Page D-404 ML14035A3682014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-241 Through Page D-321 ML14035A3672014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-170 Through Page D-240 ML14035A3522014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Cover Through Page B-312 ML14035A3532014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-1 Through Page C-114 ML14035A3662014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-92 Through Page D-169 ML14035A3632014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-845 Through Page C-962 ML14035A3622014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-723 Through Page C-844 ML14035A3612014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-584 Through Page C-722 ML14035A3552014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page D-405 Through End ML14035A3602014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-469 Through Page C-583 ML14035A3592014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-354 Through Page C-468 ML14035A3572014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-232 Through Page C-353 ML14035A3562014-01-13013 January 2014 SD-121023-001, Rev. 2, in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic for the D. C. Cook Unit 1 and 2, Page C-115 Through Page C-231 ML13357A3252014-01-10010 January 2014 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Donald C. Cook Nuclear Plant, Units 1 and 2, TAC Nos.: MF0766 and MF0767 ML14253A3182013-12-31031 December 2013 Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 1 of 3 AEP-NRC-2014-59, Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 3 of 32013-12-31031 December 2013 Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 3 of 3 ML14253A3192013-12-31031 December 2013 Enclosure 3: Babcock & Wilcox Report, S-1473-002, Revision 0, Examination of Clevis Bolts Removed from D. C. Cook Nuclear Plant. Part 2 of 3 ML13267A3272013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-1 Through Page D-48 AEP-NRC-2013-07, SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-405 Through End2013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-405 Through End ML13267A3352013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-339 Through Page D-404 ML13267A3342013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-271 Through Page D-338 ML13267A3322013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-221 Through Page D-270 ML13267A3292013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-115 Through Page D-160 ML13267A3282013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page D-49 Through Page D-114 ML13267A3252013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-801 Through Page C-884 ML13267A3162013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Page B-312 ML13267A3172013-09-12012 September 2013 SD-121023-001, Rev. 1, Seismic Walkdown Report in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Page C-1 Through Page C-98 2022-12-15 Category:Response to Request for Additional Information (RAI) MONTHYEARML24197A1262024-07-15015 July 2024
[Table view]Unit 2 - Request for Additional Information (RAI) for License Amendment Request for One-Time Extension of Completion Time for Inoperable AC Source - Operating 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-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-2021-43, Response to Request for Additional Information Regarding Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval2021-07-21021 July 2021 Response to Request for Additional Information Regarding Relief Request for Limited Coverage Examinations Performed in the Fourth 10-Year Inspection Interval AEP-NRC-2021-16, Unit 2 - Response to Request for Additional Information Regarding CFR 50.55a Request Associated with the Fifth Ten-Year Inservice Testing Interval2021-02-25025 February 2021 Unit 2 - Response to Request for Additional Information Regarding CFR 50.55a Request Associated with the Fifth Ten-Year Inservice Testing Interval AEP-NRC-2021-18, Response to Request for Additional Information Regarding License Amendment Request for One-Time Extension of the Containment Type a Leak Rate Testing Frequency2021-02-18018 February 2021 Response to Request for Additional Information Regarding 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 AEP-NRC-2019-56, Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic2019-11-0404 November 2019 Seismic Probabilistic Risk Assessment in Response to Near Term Task Force Recommendation 2.1: Seismic AEP-NRC-2019-32, Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 22019-08-22022 August 2019 Unit 2 - Response to Request for Additional Information Regarding Unit 2 Leak-Before-Break Analysis and Deletion of Containment Humidity Monitors for Unit 1 and Unit 2 AEP-NRC-2019-40, Response to Request for Additional Information Regarding License Amendment Request to Address NSAL-15-1, Rev. 02019-07-30030 July 2019 Response to Request for Additional Information Regarding License Amendment Request to Address NSAL-15-1, Rev. 0 AEP-NRC-2018-81, Supplement to Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-11-27027 November 2018 Supplement to Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping AEP-NRC-2018-82, Response to Request for Additional Information Regarding the Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination2018-11-20020 November 2018 Response to Request for Additional Information Regarding the Alternative Request for Elimination of the Reactor Pressure Vessel Threads in Flange Examination AEP-NRC-2018-64, Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping2018-09-27027 September 2018 Response to Request for Additional Information Regarding License Amendment Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping ML18334A2722018-09-18018 September 2018 LTR-SDA-II-18-41-NP, Revision 1, Responses to NRC Questions on the Expanded Scope Leak-Before-Break Evaluations for D.C. Cook, Units 1 and 2. AEP-NRC-2018-45, Response to Request for Additional Information Concerning 2017 Decommissioning Funding Status Report2018-08-0909 August 2018 Response to Request for Additional Information Concerning 2017 Decommissioning Funding Status Report AEP-NRC-2018-01, Response to Request for Additional Information Regarding Generic Letter 2016-012018-05-25025 May 2018 Response to Request for Additional Information Regarding Generic Letter 2016-01 AEP-NRC-2018-23, Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plan2018-04-11011 April 2018 Response to Request for Additional Information Regarding Independent Spent Fuel Storage Installation Decommissioning Funding Plan ML18092A0842018-03-28028 March 2018 Donald C. Cook Nuclear Plant Unit 2, Response to Request for Additional Information Regarding Supplemental Information Regarding the Reactor Vessel Internals Aging Management Program ML17346A7662017-12-0808 December 2017 Enclosures 2 & 3 to AEP-NRC-2017-56 - Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels and EAL Technical Basis Manual AEP-NRC-2017-56, Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels2017-12-0808 December 2017 Response to Request for Additional Information Regarding the License Amendment Request to Revise Emergency Action Levels AEP-NRC-2017-30, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations2017-05-26026 May 2017 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.9.3, Containment Penetrations AEP-NRC-2017-16, Submittal of Focused Evaluation in Response to March 12, 2012, Request for Information Regarding Near- Term Task Force Recommendation 2.1: Flooding2017-05-11011 May 2017 Submittal of Focused Evaluation in Response to March 12, 2012, Request for Information Regarding Near- Term Task Force Recommendation 2.1: Flooding AEP-NRC-2017-09, Response to Request for Additional Information Regarding the License Amendment Request for the Containment Leakage Rate Testing Program2017-02-27027 February 2017 Response to Request for Additional Information Regarding the License Amendment Request for the Containment Leakage Rate Testing Program AEP-NRC-2016-81, Unit 2 - Supplemental Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTP-425, Relocate Surveillance Frequencies Program to Licensee Control-Risk Informed ...2016-11-0303 November 2016 Unit 2 - Supplemental Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTP-425, Relocate Surveillance Frequencies Program to Licensee Control-Risk Informed ... AEP-NRC-2016-80, Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools2016-10-31031 October 2016 Response to NRC Generic Letter 2016-01: Monitoring of Neutron-Absorbing Materials in Spent Fuel Pools AEP-NRC-2016-79, Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident2016-10-12012 October 2016 Spent Fuel Pool Evaluation Supplemental Report, Response to NRC Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from Fukushima Dai-ichi Accident AEP-NRC-2016-69, Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force.2016-09-0909 September 2016 Follow-up Response to Request for Additional Information Regarding License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to License Control-Risk Informed Technical Specification Task Force. AEP-NRC-2016-56, Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2016-07-12012 July 2016 Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-48, Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control...2016-06-16016 June 2016 Unit 2 - Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies Program to Licensee-Control... AEP-NRC-2016-54, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 582016-06-16016 June 2016 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-425, Relocate Surveillance Frequencies to Licensee Control - Risk Informed Technical Specification Task Force Initiative 58 ML16169A1152016-05-0606 May 2016 Donald C. Cook Nuclear Plant Units 1 and 2 - Response to Sixth Request for Additional Information the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-24, Response to Fifth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2016-02-19019 February 2016 Response to Fifth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2016-14, Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2016-01-21021 January 2016 Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation AEP-NRC-2015-11, Response (Part 2) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-12-17017 December 2015 Response (Part 2) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term ML15323A4342015-11-16016 November 2015 Response (Part 1) to Fourth Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term ML15323A4332015-11-16016 November 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent with Previously Licensed Conditions. AEP-NRC-2015-98, Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-10-30030 October 2015 Supplemental Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program AEP-NRC-2015-99, Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.152015-10-30030 October 2015 Response to Request for Additional Information Re License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11 and 3.8.1.15 ML15308A0932015-10-15015 October 2015 Pressurized Water Reactor Owners Group (Pwrog), 15066-NP, Revision 1, Responses to Follow-Up NRC RAI 2 on the D.C. Cook, Units 1 and 2, Reactor Internals Aging Management Program. AEP-NRC-2015-86, Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions.2015-09-18018 September 2015 Supplemental Response to Request for Additional Information on the Application for Amendment to Restore Normal Reactor Coolant System Pressure and Temperature Consistent With. Previously Licensed Conditions. AEP-NRC-2015-80, Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-28028 August 2015 Response to Third Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-75, Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-08-24024 August 2015 Response to Second Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-88, Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements2015-08-24024 August 2015 Response to Request for Additional Information Regarding Proposed Alternative to the American Society of Mechanical Engineers Code, Section XI Repair Requirements AEP-NRC-2015-69, Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program2015-08-0606 August 2015 Response to Follow-Up Request for Additional Information Concerning the Reactor Vessel Internals Aging Management Program ML15223A4362015-07-28028 July 2015 PWROG-15066-NP, Revision 0, Responses to Follow-Up NRC RAI 2 on the DC Cook Units 1 and 2 Reactor Internals Aging Management Program. AEP-NRC-2015-63, Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection2015-07-17017 July 2015 Response to Request for Additional Information Regarding 2014 Unit 1 Steam Generator Tube Inspection AEP-NRC-2015-64, Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term2015-07-17017 July 2015 Response to Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term AEP-NRC-2015-60, Response to a Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification Section 3.8.1, AC Sources - Operating, Surveillance Requirements 3.8.1.10, 3.8.1.11, and 3.8.1.152015-07-0909 July 2015 Response to a Request for Additional Information Regarding the License Amendment Request to Revise 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-2015-66, Response to Request for Additional Information Regarding Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation2015-07-0202 July 2015 Response to Request for Additional Information Regarding Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation 2024-07-02 |
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