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Issue date | Title | |
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ML22340A207 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 2) |
ML22340A170 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 3, Reactor (Unit 2) |
ML22340A186 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 6, Tables |
ML22340A173 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 14.A-G, Radiation Sources (Appendix 14A) (Unit 1) |
ML22340A183 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System |
ML22340A171 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 2, Tables |
ML22340A150 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 1.0, Introduction and Summary |
ML22340A136 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 14.4, Revision 29, Environmental Qualification Analyses (Unit 2) |
ML22340A192 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 5, Containment System |
ML22340A180 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 1) |
ML22340A210 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 2, Site and Environment |
ML22340A203 | 30 November 2022 | 1 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems |
ML22164A861 | 24 June 2022 | Closeout of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors |
ML22340A159 | 26 July 2021 | NFPA 805 Fire Protection Program Manual (Nfppm), Revision 5 |
AEP-NRC-2021-19, 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary |
ML21125A518 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 2, Figures |
ML21125A590 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 3, Tables (Unit 2) |
ML21125A562 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 5, Containment System |
ML21125A472 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 14.4, Environmental Qualification Analyses (Unit 2) |
ML21125A510 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 2, Tables |
ML21125A508 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 3, Reactor (Unit 2) |
ML21125A534 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System |
ML21125A540 | 19 April 2021 | Rev. 4 to NFPA 805 Fire Protection Program Manual |
ML21125A542 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 6, Tables |
ML21125A584 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary and Emergency Systems |
ML21125A599 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 2.0, Site and Environment |
ML21125A592 | 19 April 2021 | 0 to Updated Final Safety Analysis Report, Chapter 14, Section 14.A&G, Radiation Sources (Appendix 14A)(Unit 1) |
ML21125A600 | 19 April 2021 | 0 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 Methodology | 20 November 2018 | Request 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 Piping | 7 March 2018 | Request for Approval of Application of Proprietary Leak-Before-Break Methodology for Reactor Coolant System Small Diameter Piping |
ML18334A268 | 31 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) |
ML18072A013 | 31 January 2018 | WCAP-18295-NP, Revision 0, Technical Justification for Eliminating Accumulator Line Rupture as the Structural Design Basis, Using Leak-Before-Break Methodology. |
ML18072A014 | 31 January 2018 | WCAP-18302-NP, Revision 0, Technical Justification for Eliminating Residual Heat Removal Line Rupture as the Structural Design Basis, Using Leak-Before-Before Break Methodology. |
ML18072A015 | 31 January 2018 | WCAP-18309-NP, Revision 0, Technical Justification for Eliminating Safety Injection Line Rupture as the Structural Design Basis Using Leak-Before-Break Methodology. |
ML18334A269 | 31 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. |
ML16336A560 | 24 October 2016 | Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 3, Table 3.1-3 |
ML16336A405 | 24 October 2016 | Donald C. Cook Nuclear Plant, Units 1 & 2, Revision 27 to Updated Final Safety Analysis Report, Chapter 2, Table 2.9-1, Conditions/Effects Considered |
ML16336A323 | 24 October 2016 | Donald 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 |
ML16341B096 | 24 October 2016 | Donald 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 |
ML15264A851 | 9 November 2015 | Safety 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 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) |
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 2015 | 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) |
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 2014 | 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. |
ML14177A645 | 27 June 2014 | Applications and Amendments to Facility Operating Licenses and Combined Licenses Involving No Significant Hazards Considerations |
ML14073A759 | 31 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 |
ML14092A330 | 17 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 |
ML13337A325 | 24 January 2014 | Interim Staff Evaluation and Audit Report Relating to Overall Integrated Plan in Response to Order EA-12-049 (Mitigation Strategies) |
ML14035A352 | 13 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 |
ML13357A325 | 10 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 |
ML13331A540 | 9 December 2013 | 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 |