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Issue date | Title | |
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ML23086C101 | 27 March 2023 | NRC Staff'S Answer Opposing Cfur Hearing Request |
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 - Operating | 19 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 |
ML20314A342 | 12 November 2020 | NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating |
CP-202000305, (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water | 24 June 2020 | (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water |
ML17067A166 | 13 June 2017 | Staff Assessment of Response to 10 CFR 50.54(f) Information Request - Flood-Causing Mechanism Reevaluation |
ML16014A125 | 22 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 |
ML15320A100 | 13 November 2015 | IR 05000445/2015008 and 05000446/2015008, on 08/31/2015 - 10/01/2015, Comanche Peak Nuclear Power Plant, NRC Problem Identification and Resolution and Notice of Violation |
IR 05000445/2015007 | 2 September 2015 | IR 05000445/2015007 and 05000446/2015007), June 1, 2015 Through August 3, 2015, Comanche Peak, Units 1 and 2, NRC Component Design Bases |
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 Accident | 27 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 |
CP-201201129, License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation | 2 October 2012 | License Amendment Request (LAR) 12-005, Revision to Technical Specification 3.3.1, Reactor Trip System (RTS) Instrumentation and 3.3.2, Engineered Safety Feature Actuation System (ESFAS) Instrumentation |
ML12053A340 | 12 March 2012 | Request 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 |
ML12056A049 | 12 March 2012 | Enclosure 3 - Recommendation 2.3: Seismic |
ML12056A050 | 12 March 2012 | Enclosure 4 - Recommendation 2.3: Flooding |
ML12056A048 | 12 March 2012 | Enclosure 2 - Recommendation 2.1: Flooding |
ML12056A047 | 12 March 2012 | Enclosure 1 - Recommendation 2.1: Seismic |
ML090260039 | 23 January 2009 | NRC Response to GDC 2, 4, and 5 One-Pager |
ML081510173 | 27 June 2008 | Issuance of Amendment Nos. 146 and 146, Stretch Power Uprate, Revision to TS 1.0, Use and Application, to Revise Rated Thermal Power from 3458 to 3612 Mwt |
CPSES-200701127, Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times. | 15 November 2007 | Response to Request for Additional Information Related to License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times. |
ML072490358 | 31 August 2007 | WCAP-16840-NP, Rev. 0, Comanche Peak Nuclear Power Plant Stretch Power Uprate Licensing Report, Page 2.8.1-1 to End |
ML072490310 | 31 August 2007 | WCAP-16840-NP, Rev. 0, Comanche Peak Nuclear Power Plant Stretch Power Uprate Licensing Report, Cover to Page 2.7.7-5 |
ML070730037 | 26 March 2007 | Letter & License Pgs - Issuance of Amendment Nos. 136 & 136 - Changes to TSs Re Control Room Envelope Habitability in Accordance w/TSTF-448, Rev. 3, Using Consolidated Line Item Improvement Process |
CPSES-200700130, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators | 18 January 2007 | License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators |
CPSES-200601634, License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators | 13 October 2006 | License Amendment Request (LAR) 06-009, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Diesel Generators |
ML052380208 | 29 September 2005 | Issuance of Amendments Reactor Trip System and Engineered Safety Features Actuation System |
CPSES-200500155, License Amendment Request (LAR) 04-015 Revision to Technical Specification 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System Instrumentation (Esffas) | 24 March 2005 | License Amendment Request (LAR) 04-015 Revision to Technical Specification 3.3.1 Reactor Trip System Instrumentation and 3.3.2 Engineered Safety Feature Actuation System Instrumentation (Esffas) |
ML050460331 | 31 January 2005 | Issuance License Amendments 114 & 114 Plant Protection Plant Times, Completion Times and Surveillance Test Intervals |
CPSES-200402477, (CPSES) License Amendment Request (LAR) 04-013 Revision to Technical Specification (TS) 3.7.5 Auxiliary Feedwater (AFW) System | 24 January 2005 | (CPSES) License Amendment Request (LAR) 04-013 Revision to Technical Specification (TS) 3.7.5 Auxiliary Feedwater (AFW) System |
CPSES-200402431, License Amendment Request 04-011, Revision to Technical Specification (TS 3.3.3) Post Accident Monitoring Instrumentation and 3.6.8 Hydrogen Recombiners | 28 October 2004 | License Amendment Request 04-011, Revision to Technical Specification (TS 3.3.3) Post Accident Monitoring Instrumentation and 3.6.8 Hydrogen Recombiners |
CPSES-200400179, Comanche Peak - 1OCFR50.59 Evaluation Summary Report 0011 | 2 February 2004 | Comanche Peak - 1OCFR50.59 Evaluation Summary Report 0011 |
CPSES-200400149, License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals | 21 January 2004 | License Amendment Request (LAR) 03-08 Common Stars License Amendment Implementation of WCAP-14333 and WCAP-15376 RTS and ESFAS Test Times, Completion Times, and Surveillance Test Intervals |
TXX-9642, Forwards Detailed Description of Amend 94 to Updated FSAR for Cpses.Replacement of FSAR Figures W/Plant Process Flow Diagrams Meets Intent & Requirements of Reg Guide 1.70,rev 2 | 1 August 1996 | Forwards Detailed Description of Amend 94 to Updated FSAR for Cpses.Replacement of FSAR Figures W/Plant Process Flow Diagrams Meets Intent & Requirements of Reg Guide 1.70,rev 2 |
ML20097H712 | 31 January 1996 | Nonproprietary Bypass Test Instrumentation for Comanche Peak Units 1 & 2 |
ML20127M070 | 21 January 1993 | Forwards Advance FSAR Change to Reclassify Portion of Eight Inch Heater Drain Piping & One Pipe Support in Turbine Bldg from non-seismic to Seismic Category Ii.Change Permits One Seismic Pipe Support to Be Located 13 Inches Inside TB |
ML19354D665 | 15 December 1989 | Forwards Advance FSAR Changes of Tables 6.1B-4 & 6.5-3 Re Revs to Boron Concentration in Refueling Water Storage Tank & RCS & Quantity of Borated Water Used for Calculating Containment Sump Solution Mixing |
ML20246L279 | 31 August 1989 | Provides Advance Changes to Be Included in Future FSAR Amend Re Deletion of Tornado Door Schedule,Replacing Two Roll Up Doors w/blow-out Doors & Deleting Discussion of Venting of Cable Spreading Rooms |
ML20246L467 | 31 August 1989 | Provides Advance Changes to Be Included in Future FSAR Amend Re Removal of Automatic Safety Sys Inoperable Indication for Diesel Generator Room Fans |
ML20246M570 | 31 August 1989 | Forwards Advance FSAR Submittal Re Loadings & Stresses for Category I Structures |
ML20246L141 | 31 August 1989 | Provides Advance Changes to Be Included in Future FSAR Amend Re Component Cooling Water Sys Design Pressure |
ML20246L254 | 28 August 1989 | Provides Advance Changes to Be Included in Future FSAR Amend Re HVAC Gravity Damper Upgrade for FSAR Section 9.4 |
ML20246L160 | 28 August 1989 | Provides Advance Changes to Be Included in Future FSAR Amend.Changes Revise Main Steam Safety Valve Blowdown from 5% to Less than or Equal to 12% of Set Pressure for Safety Valve |
ML20246K916 | 28 August 1989 | Forwards Change to Be Included in Future FSAR Amend Re High Silica Concentration Alarm Function |
ML20246B271 | 16 August 1989 | Forwards Response to 890731 Request for Addl Info Re FSAR Sections 3.7 & 3.8.FSAR Advance Submittal Re Temp Ranges Inside & Outside Containment Also Encl |
ML20151A627 | 13 July 1988 | Memorandum & Order (Dismissing Proceedings).* Documents That Parties in Joint Stipulation Agreed to Tender Admitted to Record at 880713 Prehearing Conference.Served on 880715 |
ML20154Q216 | 1 June 1988 | Forwards Detailed Listing & Description of Every Change to FSAR That Causes Document to Differ from Version Reviewed & Accepted by NRC Through Sser 12 |
IR 05000445/1987037 | 4 February 1988 | Design Validation Packages Insp Repts 50-445/87-37 & 50-446/87-28 on 871026-1204.No Violations Noted.Major Areas Inspected:Mechanical Sys,Civil/Structural,Electrical & Instrumentation/Controls |
ML20195H911 | 15 January 1988 | Discusses Amend 66 to FSAR Including Updates,Clarifications, Revs,Corrections,Additions & Editorial Changes as Well as Revised Effective Page Listing for Affected Portions of Rept.Summary of Changes Encl |
TXX-6844, Informs That Field Verification Method (Fvm) for Unit 2 Sys Will Be Issued to Support Completion of Walkdowns,Generation of DCAs & Installation of Cable Grips by 881231,in Response to Notice of Violation.Draft FSAR Encl | 12 October 1987 | Informs That Field Verification Method (Fvm) for Unit 2 Sys Will Be Issued to Support Completion of Walkdowns,Generation of DCAs & Installation of Cable Grips by 881231,in Response to Notice of Violation.Draft FSAR Encl |
NRC Generic Letter 1987-02 | 19 February 1987 | NRC Generic Letter 1987-002: Verification of Seismic Adequacy of Mechanical & Electrical Equipment in Operating Reactors, Unresolved Safety Issue A-46 |
ML20207K707 | 29 December 1986 | Rev 0 to Generic Technical Issue Rept - Evaluation & Resolution of Tera Equipment Qualification Issue Resolution Repts DAP-E-EIC-503 (Environ) & DAP-E-M-500 (Seismic) |
TXX-6020, Forwards Revised Procedure Manuals Re Comanche Peak Response Team Checklists.Future Revs Will Be Sent Periodically. Related Documentation Encl | 10 October 1986 | Forwards Revised Procedure Manuals Re Comanche Peak Response Team Checklists.Future Revs Will Be Sent Periodically. Related Documentation Encl |