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ML22340A20730 November 20221 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 2)
ML22340A17030 November 20221 to Updated Final Safety Analysis Report, Chapter 3, Reactor (Unit 2)
ML22340A18630 November 20221 to Updated Final Safety Analysis Report, Chapter 6, Tables
ML22340A17330 November 20221 to Updated Final Safety Analysis Report, Chapter 14.A-G, Radiation Sources (Appendix 14A) (Unit 1)
ML22340A18330 November 20221 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
ML22340A17130 November 20221 to Updated Final Safety Analysis Report, Chapter 2, Tables
ML22340A15030 November 20221 to Updated Final Safety Analysis Report, Chapter 1.0, Introduction and Summary
ML22340A13630 November 20221 to Updated Final Safety Analysis Report, Chapter 14.4, Revision 29, Environmental Qualification Analyses (Unit 2)
ML22340A19230 November 20221 to Updated Final Safety Analysis Report, Chapter 5, Containment System
ML22340A18030 November 20221 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 1)
ML22340A21030 November 20221 to Updated Final Safety Analysis Report, Chapter 2, Site and Environment
ML22340A20330 November 20221 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems
ML22164A86124 June 2022Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors
ML22340A15926 July 2021NFPA 805 Fire Protection Program Manual (Nfppm), Revision 5
AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary19 April 20210 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary
ML21125A51819 April 20210 to Updated Final Safety Analysis Report, Chapter 2, Figures
ML21125A59019 April 20210 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 2)
ML21125A56219 April 20210 to Updated Final Safety Analysis Report, Chapter 5, Containment System
ML21125A47219 April 20210 to Updated Final Safety Analysis Report, Chapter 14.4, Environmental Qualification Analyses (Unit 2)
ML21125A51019 April 20210 to Updated Final Safety Analysis Report, Chapter 2, Tables
ML21125A50819 April 20210 to Updated Final Safety Analysis Report, Chapter 3, Reactor (Unit 2)
ML21125A53419 April 20210 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System
ML21125A54019 April 2021Rev. 4 to NFPA 805 Fire Protection Program Manual
ML21125A54219 April 20210 to Updated Final Safety Analysis Report, Chapter 6, Tables
ML21125A58419 April 20210 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems
ML21125A59919 April 20210 to Updated Final Safety Analysis Report, Chapter 2.0, Site and Environment
ML21125A59219 April 20210 to Updated Final Safety Analysis Report, Chapter 14, Section 14.A&G, Radiation Sources (Appendix 14A)(Unit 1)
ML21125A60019 April 20210 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 1)
AEP-NRC-2018-66, Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology20 November 2018Request for License Amendment to Technical Specification 3.4.15, RCS Leakage Detection Instrumentation, and Application of Leak-Before-Break Methodology
AEP-NRC-2018-02, Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping7 March 2018Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping
ML18334A26831 January 2018WCAP-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)
ML18072A01331 January 2018WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis, Using Leak-Before-Break Methodology.
ML18072A01431 January 2018WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis, Using Leak-Before-Before Break Methodology.
ML18072A01531 January 2018WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis Using Leak-Before-Break Methodology.
ML18334A26931 January 2018WCAP-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.
ML16336A56024 October 2016Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 3, Table 3.1-3
ML16336A40524 October 2016Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 2, Table 2.9-1, Conditions/Effects Considered
ML16336A32324 October 2016Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 2, Figure 2.5-3, Recommended Response Spectra Design Basis Earthquake
ML16341B09624 October 2016Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 6, Table: 6.2-10, Recirculation Sump Component Design Load Combinations
ML15264A8519 November 2015Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051
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)1 October 2015Revision 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)
AEP-NRC-2015-23, Final Integrated Plan Regarding March 12, 2012, U.S. NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)16 June 2015Final Integrated Plan Regarding March 12, 2012, U.S. NRC Order Regarding Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
AEP-NRC-2014-94, Expedited Seismic Evaluation Process Report - Response to U. S. Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force.18 December 2014Expedited Seismic Evaluation Process Report - Response to U. S. Nuclear Regulatory Commission Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 2.1 of the Near-Term Task Force.
ML14177A64527 June 2014Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations
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
ML14092A33017 March 2014Document No. 13Q3208-RPT-003, Revion 1, Seismic Hazard and Screening Report for the Cook Nuclear Plant (Cnp), Enclosure 2 to AEP-NRC-2014-25
ML13337A32524 January 2014Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies)
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
ML13357A32510 January 2014Mega-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
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