Category:E-Mail
MONTHYEARML24292A0282024-10-18018 October 2024 NRR E-mail Capture - Acceptance Review Comanche Peak Adoption of TSTF-51, TSTF-471, and TSTF-571 ML24262A1302024-09-18018 September 2024 NRR E-mail Capture - Acceptance Review Comanche Peak Multiple Relief Requests for Unit 2 Third Inservice Inspection Interval Due to Impracticality (EPID L-2024-LLR-0053 Through -0058) ML24205A2162024-07-23023 July 2024 September 2024 Emergency Preparedness Program Inspection - Request for Information ML24204A0022024-07-18018 July 2024 NRR E-mail Capture - Request for Additional Information Comanche Peak Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule ML24095A1532024-04-0404 April 2024 NRR E-mail Capture - Acceptance Review Comanche Peak Request to Revise Technical Specifications to Adopt TSTF-591, Revise Risk Informed Completion Time (RICT) Program (EPID 2024-LLA-0023) ML24095A2382024-04-0404 April 2024 NRR E-mail Capture - Acceptance Review Comanche Peak Request to Revise Technical Specifications to Adopt TSTF-589, Eliminate Automatic Diesel Generator Start During Shutdown ML24052A0122024-02-16016 February 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Request for Exemption from Enhanced Weapons, Firearms Background Checks, and Security Event Notifications ML24033A2642024-02-0202 February 2024 NRR E-mail Capture - Comanche Peak - Revised Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24036A0122024-02-0202 February 2024 NRR E-mail Capture - Comanche Peak - Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24025A0172024-01-22022 January 2024 NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment ML24019A0742024-01-19019 January 2024 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - License Amendment Request to Extend the Allowed Outage Time for an Inoperable Emergency Diesel Generator ML24008A2492023-12-18018 December 2023 Texas SHPO Response for Comanche Peak Deis Review and Comment ML23311A2202023-11-20020 November 2023 NRC to Fws, NRC Request for Concurrence with Endangered Species Act Determinations for Comanche Peak License Renewal, Issuance of Draft Supplemental Environmental Impact Statement, and Opportunity for Public Comment (Consultation Code: 2023 ML23255A2882023-09-12012 September 2023 NRR E-mail Capture - Comanche Peak - Acceptance of Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule ML23256A1492023-09-11011 September 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 4 ML23226A0072023-08-11011 August 2023 NRR E-mail Capture - Comanche Peak 1 and 2 – Audit Plan - License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23188A0442023-07-0707 July 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 3 ML23181A0722023-06-29029 June 2023 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors ML23181A0202023-06-29029 June 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Additional Information - Set 2 ML23172A0152023-06-20020 June 2023 NRR E-mail Capture - Re Comanche Peak - Acceptance of License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23167A0222023-06-14014 June 2023 Email: Request for Additional Information (RAI) Letter for the Review of the Comanche Peak Initial License Renewal Application, Set 1 ML23145A2332023-05-25025 May 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 2 ML23143A1382023-05-23023 May 2023 Email from Mark Yoo (NRC) to Ken Peters (Vistra) - Comanche Peak LRA - Request for Confirmation of Information - Set 1 ML23139A0802023-05-18018 May 2023 NRR E-mail Capture - Comanche Peak – Draft Supplemental Information Request - License Amendment Request Regarding General Design Criterion 5 of Appendix a to 10 CFR Part 50 and Regulatory Guide 1.81 ML23138A1522023-05-18018 May 2023 Lr Docs - (External_Sender) Comanche Peak Nuclear Power Plants ML23135A9132023-05-15015 May 2023 NRR E-mail Capture - Comanche Peak - Draft Supplemental Information Request - License Amendment Request to 10 CFR 50.69 ML23131A2932023-05-11011 May 2023 Lr Docs - License Renewal for Comanche Peak Nuclear Power Plant, Units 1 and 2 ML23128A1612023-05-0808 May 2023 NRR E-mail Capture - Comanche Peak Nuclear Power Plant, Units 1 and 2, Beaver Valley Power Station, Unit Nos. 1 and 2, Davis-Besse Nuclear Power Station, Unit 1, and Perry Nuclear Power Plant, Unit No. 1 - Acceptance of Requested Licensing ML23110A7122023-04-20020 April 2023 NRR E-mail Capture - Comanche Peak - Verbal Authorization of Proposed Alternative RV-1 (L-2023-LLR-0019) ML23103A4682023-04-11011 April 2023 NRR E-mail Capture - Comanche Peak – Request for Additional Information - License Amendment Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23086B9852023-03-27027 March 2023 NRR E-mail Capture - Comanche Peak – Draft Request for Additional Information - Request to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model ML23061A1612023-03-0202 March 2023 E-mail from David Griggs Regarding Submission to NRC Electronic Information Exchange on 03/01/2023 for Citizens for Fair Utility Regulation in Comanche Peak Proceeding ML23032A3842023-02-0101 February 2023 LRA On-Site Audit Needs List ML23214A0192023-01-30030 January 2023 (External_Sender) Request to Broaden Extended Deadline to the General Public (with Attachments) - C3 ML23214A0202023-01-29029 January 2023 (External_Sender) Requesting a Deadline Extension on NRC-2002-0183, Comanche Peak License Renewal - C2 ML23214A0182023-01-26026 January 2023 (External Sender) NRC-2022-0183-0003 (with Attachment) - C6 ML23214A0162023-01-24024 January 2023 (External Sender) EPA Scoping Comment Letter for the Comanche Peak Nuclear Power Plant License Renewal (with Attachment) - C8 ML23214A0142023-01-23023 January 2023 (External Sender) Docket NRC-2022-0183 Comanche Peak Nuclear Power Plant Renewal (with Attachment) - C1 ML23214A0172023-01-17017 January 2023 (External Sender) NRC License Extension? No! ML23214A0132023-01-17017 January 2023 (External Sender) Docket Id NRC-2022-0183, Request for Extension of License for Comanche Peak, Comment for Environmental Scoping - C9 ML23214A0122023-01-13013 January 2023 (External Sender) Correction to Comment Submitted 01-13-23 - C11 ML22362A0992022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Apply Westinghouse Fsloca Evaluation Model ML22362A0972022-12-28028 December 2022 NRR E-mail Capture - Comanche Peak - Acceptance of License Amendment Request to Adopt WCAP-17661-P-A, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications, ML22325A2742022-11-21021 November 2022 NRR E-mail Capture - Comanche Peak - Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22318A3102022-11-10010 November 2022 NRR E-mail Capture - Comanche Peak - Draft Request for Additional Information - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22237A2842022-08-25025 August 2022 CPNPP 2022 EP Program Inspection RFI Hjs 08252022 ML22229A0792022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak - Acceptance of Requested Licensing Action - Proposed Alternative P-1 Regarding IST of Safeguards Building Sump Pumps ML22230B1092022-08-17017 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22220A1942022-08-0808 August 2022 NRR E-mail Capture - Comanche Peak Unit 2 - Draft Request for Additional Information - 2RE19 Inspection Summary Report for Steam Generator Tubing ML22133A0472022-05-13013 May 2022 July 2022 Emergency Preparedness Exercise Inspection - Request for Information 2024-09-18
[Table view] Category:Graphics incl Charts and Tables
MONTHYEARCP-201900070, Commitment to Maintain Severe Accident Management Guidelines2019-02-0404 February 2019 Commitment to Maintain Severe Accident Management Guidelines ML16056A1392016-03-11011 March 2016 Correction to the U.S. Nuclear Regulatory Commission Analysis of Licensees' Decommissioning Funding Status Reports 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 Information2013-07-0303 July 2013 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 Information CP-200900283, Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request2009-02-17017 February 2009 Response to Request for Additional Information Regarding Spent Fuel Pool Criticality License Amendment Request ML0728203072007-10-11011 October 2007 Electronic Distribtion Initiative Letter, Licensee List, Electronic Distribution Input Information, Division Plant Mailing Lists ML0620500132006-07-17017 July 2006 Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 75 Through 216 ML0620500142006-07-17017 July 2006 Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 125 Through 168 ML0620500152006-07-17017 July 2006 Attachment 1 to TXX-0612 Response to Requests for Additional Information for the Replacement Steam Generator Supplement to Txu Power'S Large and Small Break Loss of Coolant Accident Analysis Methodologies, Pages 169 -End & Attachment 2 ML0612805802006-06-30030 June 2006 Memo with Enclosures 1 and 2, - Trip Report Regarding Staff Observations Regarding Flume Testing of a Prototype Portion of the Proposed Replacement Suction Screen Design for the Comanche Peak Steam Electric Station CPSES-200601160, Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power.2006-06-29029 June 2006 Revised Response to the 60-Day Response to NRC Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power. ML0702304002006-04-13013 April 2006 Default-Graph 001 ML0608701442005-09-13013 September 2005 CPSES-09-2005 - Draft Outline ML0512504782005-03-28028 March 2005 03-2005-Draft-Operating Exam ML0512504692005-03-28028 March 2005 03-2005-Draft-Written Outline ML0512504262005-03-28028 March 2005 03-2005-Draft-Operating Test Outline ML0512304372005-03-28028 March 2005 03-2005-Licensee Post-Exam Analysis ML0401305382003-04-17017 April 2003 Response to AIF Generator Survey 2019-02-04
[Table view] Category:Report
MONTHYEARML24136A1352024-07-30030 July 2024 LRA - Record of Decision ML23355A2682023-12-21021 December 2023 NRC Comments - Comanche Peak LRA Supplement 3 (1) CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 L-23-188, Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-08-0707 August 2023 Energy Harbor Nuclear Corp., Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202200419, (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report2022-11-0303 November 2022 (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report CP-202200247, (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 0172022-06-30030 June 2022 (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 017 ML22020A1792021-11-0404 November 2021 Fall 2021 Steam Generator Tube Inspections Discussion Input CP-202100127, Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 62021-03-16016 March 2021 Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 6 CP-202000462, Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 0162020-09-29029 September 2020 Submittal of 10CFR50.59 Evaluation Summary Report 022, 007, and Commitment Material Change Evaluation Report 016 ML20153A7442020-06-0404 June 2020 Review of the Fall 2018 Steam Generator Tube Inspection Report CP-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings2019-08-14014 August 2019 (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings CP-201900378, Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report2019-06-10010 June 2019 Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report CP-201900126, Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report.2019-02-25025 February 2019 Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report. CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report2018-09-12012 September 2018 Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report ML18044A0982018-02-0808 February 2018 Solid Waste Registration Number: 33306; Texas Waste Code: 37043902; Reference Number: 15749 CP-201700805, Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report2017-10-30030 October 2017 Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report CP-201700223, Decommissioning Funding Status Report for Financial Assurance as of 12/31/20162017-03-30030 March 2017 Decommissioning Funding Status Report for Financial Assurance as of 12/31/2016 CP-201700033, Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path2017-02-0909 February 2017 Mitigating Strategies Assessment Flood Report, NEI 12-06, Appendix G, Revision 2, G.4.1 Path 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.2016-02-29029 February 2016 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. CP-201600093, Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 0132016-02-24024 February 2016 Transmittal of 10CFR50.59 Evaluation Summary Report 019, 10CFR72.48 Evaluation Summary Report 004, and Commitment Material Change Evaluation Report 013 ML16014A1252016-01-22022 January 2016 Staff 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 ML16047A3302016-01-20020 January 2016 NEI 12-01 Phase 2 Staffing Assessment, Revision 1 ML15062A0302015-02-25025 February 2015 Work Plan for Completing a Once Through Cooling Water Study for Total Dissolved Solids, Chlorides, and Sulfates CP-201401268, Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report2014-10-21021 October 2014 Fourteenth Refueling Outage (2RF14) Steam Generator 180 Day Report CP-201401027, 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 0122014-08-27027 August 2014 10CFR50.59 Evaluation Summary Report 018, 10CFR72.48 Evaluation Summary Report 003 and Commitment Material Change Evaluation Report 012 ML14189A5432014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request ML14189A5002014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5 ML14189A5312014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5 ML14189A5332014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5 ML14189A5372014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 RIS 2014-07, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 52014-06-19019 June 2014 Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 1 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 2 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 3 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 4 of 5, Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program- Vendor Information Request. Part 5 of 5 CP-201400335, . Pressure and Temperature Limits Report2014-04-0808 April 2014 . Pressure and Temperature Limits Report 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 Accident2014-03-27027 March 2014 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 Accident ML14036A0362014-03-0707 March 2014 Staff 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 ML13225A5752013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13338A6612013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Comanche Peak Nuclear Power Plant, TAC Nos.: MF0860 and MF0861 ML13309A0272013-10-31031 October 2013 WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis CP-201301238, Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report2013-10-15015 October 2013 Sixteenth Refueling Outage (1RF16) Steam Generator 180 Day Report ML12159A2882012-06-11011 June 2012 Review of 60-day Response to Request for Information Pursuant to 10 CFR 50.54(f) Regarding Recommendation 9.3 of the Near Term Task Force Related to Fukushima Dai-ichi Accident ML12080A1432012-03-0606 March 2012 CPNPP Systems Annual Operator Employment Notices ML12080A1502012-03-0606 March 2012 Submittal of Stc Annual Operator Employment Notices CP-201101257, Submittal of Operator Licensing Examination Data2011-09-21021 September 2011 Submittal of Operator Licensing Examination Data 2024-07-30
[Table view] Category:Technical
MONTHYEARML23355A2682023-12-21021 December 2023 NRC Comments - Comanche Peak LRA Supplement 3 (1) CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202200419, (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report2022-11-0303 November 2022 (CPNPP) - Unit 1 Refueling Outage 22 (1RF22) Steam Generator 180 Day Report CP-202100127, Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 62021-03-16016 March 2021 Transmittal of Pressure and Temperature Limits Report, ERX-07-003, Revision 6 CP-201900467, (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings2019-08-14014 August 2019 (CPNPP) - Biennial Review of Procedures and Station Operations Review Committee Meetings CP-201900378, Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report2019-06-10010 June 2019 Transmittal of Seventeenth Refueling Outage (2RF17) Steam Generator 180 Day Report CP-201900126, Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report.2019-02-25025 February 2019 Special Report 2-SR-19-001-00, Inoperable Post Accident Monitoring Instrumentation Report. CP-201800652, Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report2018-09-12012 September 2018 Special Report 1-SR-18-001-00, Inoperable Post Accident Monitoring Instrumentation Report ML18044A0982018-02-0808 February 2018 Solid Waste Registration Number: 33306; Texas Waste Code: 37043902; Reference Number: 15749 CP-201700805, Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report2017-10-30030 October 2017 Sixteenth Refueling Outage (2RF16) Steam Generator 180 Day Report 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.2016-02-29029 February 2016 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. ML16047A3302016-01-20020 January 2016 NEI 12-01 Phase 2 Staffing Assessment, Revision 1 ML14189A4982014-06-19019 June 2014 Stars Response to Nuclear Regulatory Commission (NRC) Regulatory Issue Summary (RIS) 2014-07, Enhancements to the Vendor Inspection Program - Vendor Information Request CP-201400335, . Pressure and Temperature Limits Report2014-04-0808 April 2014 . Pressure and Temperature Limits Report ML13225A5752013-12-19019 December 2013 Interim Staff Evaluation Relating to Overall Integrated Plan in Response to Order EA-12-049 - Mitigation Strategies ML13338A6612013-12-18018 December 2013 Mega-Tech Services, LLC, Technical Evaluation Report Regarding the Overall Integrated Plan for Comanche Peak Nuclear Power Plant, TAC Nos.: MF0860 and MF0861 ML13309A0272013-10-31031 October 2013 WCAP-17728-NP, Rev. 1, Comanche Peak Nuclear Power Plant Units 1 and 2 Spent Fuel Pool Criticality Safety Analysis ML1029201602010-09-30030 September 2010 WCAP-17269-NP, Revision 0, Analysis of Capsule W from the Comanche Peak Unit No. 2 Reactor Vessel Radiation Surveillance Program. ML0930800082009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 57 of 99 Through Page 89 of 99 ML0930800102009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment E, Page 23 of 49 Through Attachment F CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 452009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B2009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment C Through Attachment D, Page 20 of 992009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment C Through Attachment D, Page 20 of 99 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 21 of 99 Through Page 56 of 992009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 21 of 99 Through Page 56 of 99 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 57 of 99 Through Page 89 of 992009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 57 of 99 Through Page 89 of 99 CP-200901403, Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 492009-10-13013 October 2009 Comanche Peak - Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 49 ML0930800092009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 90 of 99 Through Attachment E, Page 22 of 49 ML0930800072009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment D, Page 21 of 99 Through Page 56 of 99 ML0930800062009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment C Through Attachment D, Page 20 of 99 ML0930800052009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Attachment a, Page 31 of 45, Through Attachment B CP-200901403, Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 452009-10-13013 October 2009 Engineering Report ER-ESP-001, Revision 2, Generic Letter 2004-02 Supplemental Response, Cover Page Through Attachment a, Page 30 of 45 CP-200801606, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a2008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a ML0835004682008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment B Through Attachment D, Page 20 ML0835004702008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 21 Through 57 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 58 Through 952008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 58 Through 95 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 21 Through 572008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 21 Through 57 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment B Through Attachment D, Page 202008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment B Through Attachment D, Page 20 CP-200801606, Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a2008-11-26026 November 2008 Comanche Peak, Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Introduction Through Attachment a ML0835004722008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment E ML0835004712008-11-26026 November 2008 Engineering Report, Generic Letter 2004-02 Supplemental Response ER-ESP-001, Revision 1, Attachment D, Page 58 Through 95 ML0815600282008-09-0909 September 2008 Generic Letter 2008-01, Managing Gas Accumulation in Emergency Core Cooling, Decay Heat Removal, and Containment Spray Systems, Proposed Alternative Course of Action ML0821900132008-08-0707 August 2008 Monthly Operating Reports Second Quarter 2008 ML0826102862008-06-30030 June 2008 WCAP-16827-NP, Addendum 1, Revision 0, Supplement to Comanche Peak, Units 1 and 2, Spent Fuel Pool Criticality Safety Analysis. CP-200800265, Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors2008-02-29029 February 2008 Transmittal of Supplemental Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0734401502007-12-0303 December 2007 Drill Report 11/06/2007, Final Report - Radiological Emergency Preparedness (REP) Program, 12/03/2007. Draft CPSES-200701238, Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses2007-07-31031 July 2007 Submittal of the CPSES Units 1 and 2 Large and Small Break LOCA Analyses CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses2007-04-0505 April 2007 Evaluation of Pressurizer Weld Overlay Confirmatory Analyses CPSES-200700346, Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 20062007-02-0808 February 2007 Guarantees of Payment of Deferred Premiums, Submits Form 10-Q for the Period Ending September 30, 2006 CPSES-200602196, WCAP-16610-NP, Rev. 0, Analysis of Capsule X from the Txu Energy Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program.2006-09-30030 September 2006 WCAP-16610-NP, Rev. 0, Analysis of Capsule X from the Txu Energy Company Comanche Peak Unit 1 Reactor Vessel Radiation Surveillance Program. CPSES-200600269, Eighth Refueling Outage (2RF08) Steam Generator Twelve Month Report2006-02-14014 February 2006 Eighth Refueling Outage (2RF08) Steam Generator Twelve Month Report 2023-07-12
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