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 Issue dateTitle
ML22340A13230 November 2022Technical Requirements Manual and Technical Requirements Manual Bases, List of Effective Pages (Unit 2)
ML22340A16030 November 2022Technical Specifications Bases, List of Effective Pages
ML22340A16530 November 2022Technical Requirements Manual and Technical Requirements Manual Bases, List of Effective Pages (Unit 1)
ML22340A20230 November 2022Technical Specifications Bases, List of Effective Pages
IR 05000315/20220028 August 2022Integrated Inspection Report 05000315/2022002 and 05000316/2022002
AEP-NRC-2021-28, 10 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System15 June 202110 CFR 50.90 License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
ML21125A49819 April 20217 to Technical Requirements Manual and Technical Manual Bases, List of Effective Pages (Unit 1)
ML21125A54819 April 20212 to Technical Specifications Bases, List of Effective Pages (Unit 1)
ML21125A57619 April 20219 Technical Specification Bases, List of Effective Pages (Unit 2)
ML21125A59519 April 20217 to Technical Requirements Manual and Technical Manual Bases, List of Effective Pages (Unit 2)
ML20352A17123 December 2020Documentation of the Completion of Required Actions Taken in Response to the Lessons Learned from the Fukushima Dai-ichi Accident
IR 05000315/202000113 May 2020Integrated Inspection Report 05000315/2020001 and 05000316/2020001
ML20112F48612 May 2020Final ASP Analysis - D.C. Cook 2 (LER 316-98-005)
AEP-NRC-2020-01, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System7 April 2020License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits and Low Temperature Overpressure Protection (LTOP) System
ML16327A11028 December 2016Cover Letter for Revised Safety Evaluation for Amendment Nos. 332 and 314 Adoption of TSTF-490, Rev. 0, and Implementation of Full-Scope Alternative Source Term
ML16242A11120 October 2016DC Cook, Units 1 and 2 - Issuance of Amendments Adoption of TSTF-490,REV.0,Deletion of E-Bar Definition and Revision to Reactor Coolant System Specific Activity Technical Specification and Implementation of Full-Scope Alternative Source Ter
AEP-NRC-2016-56, Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term12 July 2016Response to Seventh Request for Additional Information Regarding the License Amendment Request to Adopt TSTF-490 and Implement Alternative Source Term
ML16166A12714 June 2016NRR E-mail Capture - D.C. Cook Units 1 and 2 - Arcb RAI Concerning LAR to Adopt TSTF-490 and Implement FULL-SCOPE AST (CAC Nos. MF5184 and MF5185)
AEP-NRC-2016-31, Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation18 April 2016Supplement to the Response to Request for Additional Information Regarding License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
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) Instrumentation21 January 2016Response to Request for Additional Information Regarding the License Amendment Request to Revise Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML15344A35010 December 2015NRR E-mail Capture - D.C. Cook Nuclear Plant, Unit 2 - Sbpb Request for Additional Information Concerning ESFAS LAR
AEP-NRC-2015-85, License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation19 October 2015License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
AEP-NRC-2015-87, Proposed Alternative to the American Society of Mechanical Engineers Code, Section Xl Repair Requirements23 August 2015Proposed Alternative to the American Society of Mechanical Engineers Code, Section Xl Repair Requirements
AEP-NRC-2015-62, Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation29 June 2015Exigent License Amendment Request Regarding Technical Specification 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation
ML15105A34623 March 2015NSAL-15-2 - Impact of a Break in the Reactor Coolant Pump No. 1 Seal Leak-off Line Piping on Seal Leakage During a Loss of Seal Cooling Event
ML14147A32918 June 2014Staff 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
AEP-NRC-2014-24, License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits9 April 2014License Amendment Request Regarding a Change to the Reactor Coolant System Pressure and Temperature Limits
ML14073A75931 March 2014Staff 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
ML14035A35213 January 2014SD-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
ML13325A89123 December 2013Request for Additional Information Associated with Near-Term Task Force Recommendation 2.3, Flooding Walkdowns
ML13331A5409 December 2013Staff 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
ML13294A54321 November 2013Audit Report Regarding Seismic Walkdowns to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to the Fukushima Dai-Ichi Nuclear Power Plant Accident
ML13267A31513 September 2013Donald C. Cook, Units 1 & 2, Revised Seismic Walkdown Report Regarding the Seismic Aspects of Recommendation 2.3 of the Near-Term Task Force Review of Insights from the Dai-ichi Accident
ML13267A31612 September 2013SD-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
ML13143A43912 June 2013Plan for the Regulatory Audit Regarding Seismic Walkdowns at the Donald C. Cook Nuclear Plant, Units 1 and 2, to Support Implementation of Near-Term Task Force Recommendation 2.3, Related to the Fukushima Dai-Ichi Nuclear Power Plant Accide
AEP-NRC-2012-86, Flooding Walkdown Report in Response to the 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding for the D.C. Cook Nuclear Power Plant13 November 2012Flooding Walkdown Report in Response to the 50.54(F) Information Request Regarding Near-Term Task Force Recommendation 2.3: Flooding for the D.C. Cook Nuclear Power Plant
ML12362A0715 November 2012Donald C. Cook, Units 1 & 2, Seismic Walkdown Report SD-121023-001, Rev. 0 in Response to the 50.54(f) Information Request Regarding Fukushima Near-Term Task Force Recommendation 2.3: Seismic, Cover Through Appendix C, Page C-46
ML12056A05012 March 2012Enclosure 4 - Recommendation 2.3: Flooding
ML12053A34012 March 2012Request for Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Recommendations 2.1, 2.3, and 9.3, of the Near-Term Task Force Review of Insights from the Fukushima Dai-Ichi Accident
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
AEP-NRC-2008-17, Final Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors and Associated Request for Additional Information29 August 2008Final Response to NRC Generic Letter 2004-02: Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors and Associated Request for Additional Information
IR 05000315/200601010 August 2006
ML0607606733 April 2006Relief Request REL-PP6 Regarding the West Essential Service Water Pump Test Frequency
ML06088027810 March 2006Proposed Alternative to American Society of Mechanical Engineers Code for In-Service Test Requirements
ML06006011028 December 2005Fourth 10-Year Interval Pump and Valve Inservice Testing Program
ML05089034522 March 2005LER 99-001-01 Donald C. Cook Nuclear Plant Unit 2, Regarding Supplemental LER for Degraded Component Cooling Water Flow to Containment Main Steam Line Penetrations
ML0412003826 April 2004CNP Units 1 and 2 Improved Technical Specifications Conversion, Volume 12, Rev 0, ITS Section 3.7 Plant Systems.
ML03028072627 January 2003IR 05000315-02-009 (DRP) & IR 05000316-02-009 (Drp), on 10/01/2002-12/28/2002, Indiana Michigan Power Company. Non-Cited Violations Noted
ML99340024129 November 1999LER 315/99-027-00, Underrated Fuses Used in 250 Vdc System Could Result in Lack of Protective Coordination
ML20112F42022 October 1999Final ASP Analysis - D.C. Cook 1 and 2 (LER 315-99-026-01)
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