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Issue date | Title | |
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ML22144A132 | 18 May 2022 | 6 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging |
ML22144A131 | 18 May 2022 | 6 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Featres |
ML22144A133 | 18 May 2022 | 6 to Updated Final Safety Analysis Report, Chapter 8, Electric Power |
ML21334A025 | 22 November 2021 | 3 to Updated Final Safety Analysis Report, Chapter 16, Managing the Effects of Component Aging |
ML21334A023 | 22 November 2021 | 3 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System |
ML21334A027 | 22 November 2021 | 3 to Updated Final Safety Analysis Report, Appendix B, Seismic Design |
ML21334A031 | 22 November 2021 | 3 to Updated Final Safety Analysis Report, Chapter 3, Reactor |
ML21334A039 | 22 November 2021 | 3 to Updated Final Safety Analysis Report, Chapter 8, Electrical Systems |
ML21334A026 | 22 November 2021 | 3 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary |
ML20335A140 | 23 November 2020 | 5 to Updated Final Safety Analysis Report, Chapter 19, Managing the Effects of Component Aging |
ML20335A141 | 23 November 2020 | 5 to Updated Final Safety Analysis Report, Chapter 8, Electric Power |
ML20335A139 | 23 November 2020 | 5 to Updated Final Safety Analysis Report, Chapter 6, Engineered Safety Features |
ML20160A063 | 20 May 2020 | 2 to Updated Final Safety Analysis Report, Chapter 4, Reactor Coolant System |
ML20160A060 | 20 May 2020 | 2 to Updated Final Safety Analysis Report, Chapter 1, Introduction and Summary |
ML20160A062 | 20 May 2020 | 2 to Updated Final Safety Analysis Report, Chapter 3, Reactor |
ML20160A075 | 20 May 2020 | 2 to Updated Final Safety Analysis Report, Chapter 16, Managing the Effects of Component Aging |
ML20160A077 | 20 May 2020 | 2 to Updated Final Safety Analysis Report, Appendix B, Seismic Design |
ML17095A276 | 18 May 2017 | Safety Evaluation Regarding Implementation of Mitigating Strategies and Reliable Spent Fuel Pool Instrumentation Related to Orders EA-12-049 and EA-12-051 |
ML17213A016 | 11 May 2017 | Enclosure a: Beaver Valley, Units 1, Seismic Probabilistic Risk Assessment in Response to 50.54(f) Letter with Regard to NTTF 2.1 |
ML17213A017 | 11 May 2017 | Enclosure B: Beaver Valley, Unit 2, Seismic Probabilistic Risk Assessment in Response to 50.54(0 Letter with Regard to NTTF 2.1 |
ML17117A457 | 21 April 2017 | Revision 30 to Updated Final Safety Analysis Report, Appendix B, Seismic Design |
ML17117A439 | 21 April 2017 | Revision 30 to Updated Final Safety Analysis Report, Section 1, Introduction and Summary |
ML17117A445 | 21 April 2017 | Revision 30 to Updated Final Safety Analysis Report, Section 7, Instrumentation and Controls |
ML17117A441 | 21 April 2017 | Revision 30 to Updated Final Safety Analysis Report, Section 3, Reactor |
ML17244A912 | 21 April 2017 | Redacted - Beaver Valley Power Station, Unit 1, Revision 30 to Updated Final Safety Analysis Report, Section 2, Site |
L-17-029, Redacted - Beaver Valley Power Station, Unit 1, Revision 30 to Updated Final Safety Analysis Report, Section 8, Electrical Systems | 21 April 2017 | Redacted - Beaver Valley Power Station, Unit 1, Revision 30 to Updated Final Safety Analysis Report, Section 8, Electrical Systems |
ML16034A193 | 10 December 2015 | Final Written Examination with Answer Key (401-5 Format)(Folder 2) |
ML15355A243 | 30 November 2015 | Draft Written Exam (Folder 2) |
IR 05000412/2014007 | 15 January 2015 | IR 05000334/20114007 and 05000412/2014007, November 3, 2014 to December 4, 2014, Beaver Valley Power Station - NRC Component Design Bases |
IR 05000334/2014007 | 15 January 2015 | IR 05000334/20114007 and 05000412/2014007, November 3, 2014 to December 4, 2014, Beaver Valley Power Station - NRC Component Design Bases |
IR 05000334/2011400 | 15 January 2015 | IR 05000334/20114007 and 05000412/2014007, November 3, 2014 to December 4, 2014, Beaver Valley Power Station - NRC Component Design Bases |
ML14339A431 | 24 November 2014 | Updated Final Safety Analysis Report, Revision 21, Section 8, Electric Power |
ML14339A454 | 24 November 2014 | Updated Final Safety Analysis Report, Revision 21, Section 19, Managing the Effects of Component Aging |
ML13008A041 | 31 October 2012 | Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report. Cover Through A-40 |
ML13008A030 | 23 October 2012 | Near-Term Task Force Recommendation 2.3 Seismic Walkdown Report. Cover Through Appendix a, Resumes and Qualifications A-37 |
ML12111A222 | 20 April 2012 | Final Written Examination with Answer Key (401-5 Format) (Folder 2) |
ML12111A204 | 15 February 2012 | Draft Written Exam (Folder 2) |
IR 05000334/2011008 | 13 May 2011 | IR 05000334/2011008 and 05000412/2011008; 03/31/2011 - 04/29/2011; Beaver Valley Power Station, Units 1 and 2; Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event |
ML111310328 | 13 May 2011 | IR 05000334/2011008 and 05000412/2011008; 03/31/2011 - 04/29/2011; Beaver Valley Power Station, Units 1 and 2; Temporary Instruction 2515/183 - Followup to the Fukushima Daiichi Nuclear Station Fuel Damage Event |
L-10-151, Response to Request for Additional Information Related to Spent Fuel Pool Rerack License Amendment Request | 21 May 2010 | Response to Request for Additional Information Related to Spent Fuel Pool Rerack License Amendment Request |
ML093000278 | 31 October 2009 | NUREG-1929, Vol. 2, Safety Evaluation Report Related to the License Renewal of Beaver Valley Power Station, Units 1 and 2. |
L-09-152, Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. | 30 June 2009 | Supplemental Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. |
L-09-162, Additional Technical Information Pertaining to License Amendment Request No. 08-027 | 15 June 2009 | Additional Technical Information Pertaining to License Amendment Request No. 08-027 |
ML090500815 | 4 February 2009 | Transcript of the ACRS Plant License Renewal Subcommittee Meeting (Beaver Valley) on February 4, 2009, Pages 1-146 |
ML083010249 | 13 November 2008 | Summary of Telephone Conference Call Held on 10/8/08, Between the NRC and Firstenergy Nuclear Operating Company, Concerning Open Items Pertaining to the BVPS, Units 1 and 2, License Renewal SER |
L-08-332, Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 30 | 5 November 2008 | Supplemental Information for the Review of the Beaver Valley Power Station, Units 1 and 2. License Renewal Application (TAC Nos. MD6593 and MD6594) and License Renewal Application Amendment No. 30 |
ML082900209 | 31 August 2008 | WCAP-16158-NP, Revision 0, Technical Basis for Repair Options for Reactor Vessel Head Penetration Nozzles and Attachment Welds: Beaver Valley Unit 2 |
L-08-081, Reply to Request for Additional Information Regarding Severe Accident Mitigation Alternatives License Renewal | 7 March 2008 | Reply to Request for Additional Information Regarding Severe Accident Mitigation Alternatives License Renewal |
L-06-153, Report of Facility Changes, Tests and Experiments | 12 December 2006 | Report of Facility Changes, Tests and Experiments |
L-05-177, Responses to a Request for Additional Information (RAI Dated November 1, 2005) in Support of License Amendment Request Nos. 302 and 173 | 2 December 2005 | Responses to a Request for Additional Information (RAI Dated November 1, 2005) in Support of License Amendment Request Nos. 302 and 173 |