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CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 213 December 2023(Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2
CP-202300293, (CPNPP) - License Amendment Request Proposing Changes to Technical Specifications to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days14 September 2023(CPNPP) - License Amendment Request Proposing Changes to Technical Specifications to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator from 72 Hours to 14 Days
CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 112 July 2023Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1
ML23158A2767 June 2023Memorandum and Order (Denying Intervention Petition and Terminating Proceeding) (LBP-23-06)
CP-202300165, License Renewal Application Revision 0 - Supplement 224 April 2023License Renewal Application Revision 0 - Supplement 2
ML23086C08627 March 2023Vistra Operations Company Llc'S Answer Opposing the Petition for Leave to Intervene and Request for Hearing of Citizens for Fair Utility Regulation
ML22038A1641 February 2022Technical Specification Bases, Revision 83
ML22038A1731 February 2022FSAR Certified Amendment 111, Chapters 6 Through 8, Figures
ML21015A21212 February 2021Issuance of Amendment Nos. 178 and 178 Regarding One-Time Revision to Technical Specifications 3.7.8 Station Service Water System (Ssws) and 3.8.1 AC Sources - Operating
CP-202000575, (CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating19 November 2020(CPNPP) - Exigent License Amendment Request (LAR) 20-007 Revision to Technical Specification (TS) 3.7.8, Station Service Water System and TS 3.8.1, AC Sources - Operating
ML20226A4263 August 2020Amendment No. 110 to Final Safety Analysis Report, Chapters 6 Thru 8, Figures
ML20226A4293 August 2020Technical Specifications Bases, Revision 78
CP-202000401, (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water28 July 2020(CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water
CP-202000305, (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water24 June 2020(CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water
ML17226A0611 August 2017FSAR Amendment 108, Figures - Chapter 06 Thru 08
CP-201600329, Summary of Compliance with EA-12-049, NRC Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond Design-Basis External Events28 July 2016Summary of Compliance with EA-12-049, NRC Order Modifying Licenses with Regard to Requirements for Mitigating Strategies for Beyond Design-Basis External Events
ML16137A05614 June 2016Issuance of Amendment Nos. 166 and 166, Request to Revise Emergency Action Levels Based on Nuclear Energy Institute (NEI) 99-01, Revision 6
CP-201600097, Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.29 February 2016Westinghouse LTR-PAFM-16-2-NP, Technical Justification to Support Extended Volumetric Examination Interval for Comanche Peak Unit 1 Reactor Vessel Inlet Nozzle to Safe End Dissimilar Metal Welds.
ML16057A31012 February 2016Westinghouse LTR-PAFM-16-8 Attachment B - Responses to the NRC RAIs Re Comanche Peak Unit 1 Extension of Required Inspection Frequency for Reactor Vessel Inlet Nozzle Dissimilar Metal Welds from 7 to 9 Calendar Years
ML16180A4301 February 2016FSAR Amendment 107, Text - Chapter 15
ML16180A4311 February 2016FSAR Amendment 107, Text - Chapters 1 and 2
ML16180A4431 February 2016FSAR Amendment 107, Figures - Chapters 3, 4, and 5, Part 3 of 4
ML16180A4261 February 2016FSAR Amendment 107, Figures - Chapters 6, 7, and 8
CP-201600048, Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels27 January 2016Response to Request for Additional Information Regarding License Amendment Request 15-003 for Revision to Emergency Action Levels
ML16014A12522 January 2016Staff Assessment of Information Provided Pursuant to Title 10 of the Code of Federal Regulations Part 50 Section 50.54(f) Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force
ML15309A07330 December 2015Issuance of Amendment Nos. 165 and 165, Revise Technical Specification 5.5.16, Containment Leakage Rate Testing Program, to Increase ILRT Test Interval from 10 to 15 Years and Type C Tests from 60 to 75 Mos
ML15180A2615 August 2015Report for the Audit Regarding Implementation of Mitigating Strategies Related to Order EA-12-049
ML15191A16424 June 2015Emergency Action Level Technical Bases (Redline and Strikeout Version)
ML15191A16324 June 2015EPP-201, Emergency Action Level Technical Bases Document(Clean Version)
ML15167A5465 June 20152015-06 Final Written Exam
CP-201500034, Licence Amendment Request 14-002, Extension of Containment Leakage Rate Testing Program28 January 2015Licence Amendment Request 14-002, Extension of Containment Leakage Rate Testing Program
ML14111A1479 May 2014Seismic Screening and Prioritization Results Regarding Information Pursuant to Title 10 of the Code of Federal Regulations 50.54(f) Regarding Seismic Hazard Reevaluations for Recommendation 2.1 of the Near-Term Task Force Review of Insights
CP-201400324, Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident27 March 2014Seismic Hazard and Screening Report (CEUS Sites), Response to NRC Request for Information Pursuant to 10 CFR 50.54(0 Regarding Recommendation 2.1 of the Near-Term Task Force Review of Insights from the Fukushima Dai-ichi Accident
ML14036A0367 March 2014Staff Assessments of the Seismic Walkdown Report Supporting Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-Ichi Nuclear Power Plant Accident
CP-201400244, Second Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)27 February 2014Second Six-Month Status Report in Response to March 12, 2012, Commission Order Modifying Licenses with Regard to Requirements for Mitigation Strategies for Beyond-Design-Basis External Events (Order Number EA-12-049)
ML13225A57519 December 2013Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies
ML13338A66118 December 2013Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Comanche Peak Nuclear Power Plant, TAC Nos.: MF0860 and MF0861
ML13295A6744 November 2013Interim Staff Evaluation and Request for Additional Information Regarding the Overall Integrated Plan for Implementation of Order EA-12-051, Reliable Spent Fuel Pool Instrumentation
CP-201300982, 446 Submittal of Requested Information Identified During Regulatory Audit Regarding Seismic Walkdowns at CPNPP, Units 1 & 2, to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-ichi Nuclear12 September 2013446 Submittal of Requested Information Identified During Regulatory Audit Regarding Seismic Walkdowns at CPNPP, Units 1 & 2, to Support Implementation of Near-Term Task Force Recommendation 2.3 Related to Fukushima Dai-ichi Nuclear
CP-201300788, Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), Response to Request for Additional Information3 July 2013Overall Integrated Plan in Response to March 12, 2012 Commission Order Modifying Licenses with Regard to Reliable Spent Fuel Pool Instrumentation (Order No. EA-12-051), Response to Request for Additional Information
ML13108A2058 April 20132013-04 Final Written Exam
CP-201300257, License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals.28 March 2013License Amendment Request (LAR) 13-01, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage, 4.3, Fuel Storage, and 5.5 Programs & Manuals.
ML13071A39121 February 2013Technical Specifications Bases
ML13043A0394 February 2013Technical Specification Bases, Revision 67
CP-201300130, Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 674 February 2013Comanche Peak, Units 1 & 2, Technical Specification Bases, Revision 67
CP-201300083, License Amendment Request 12-06, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage and 5.5 Programs and Manuals.15 January 2013License Amendment Request 12-06, Revision to Technical Specifications 3.7.16, Fuel Storage Pool Boron Concentration, 3.7.17, Spent Fuel Assembly Storage and 5.5 Programs and Manuals.
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
ML12056A04712 March 2012Enclosure 1 - Recommendation 2.1: Seismic
ML12056A04912 March 2012Enclosure 3 - Recommendation 2.3: Seismic
IR 05000445/201101121 October 2011NRC Inspection Report 50-445/2011-11, 50-446/2011-11, and 72-74/2011-01
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