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Issue date | Title | |
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CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 | 4 October 2023 | Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 |
ML23256A150 | 11 September 2023 | Request for Additional Information Requests - Comanche Peak - Set 4 |
ML23172A146 | 9 August 2023 | Aging Management Audit Report - Comanche Peak Units 1 and 2 - License Renewal Application |
ML23172A147 | 9 August 2023 | Breakout Questions - Aging Management Audit - Comanche Peak Units 1 and 2 - License Renewal Application |
CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3 | 27 July 2023 | Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3 |
CP-202300165, License Renewal Application Revision 0 - Supplement 2 | 24 April 2023 | License Renewal Application Revision 0 - Supplement 2 |
ML16179A405 | 11 July 2016 | Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval |
IR 05000445/2016001 | 29 April 2016 | NRC Integrated Inspection Report 05000445/2016001 and 05000446/2016001 |
ML16074A001 | 14 March 2016 | Relief Request 1B3-3, Alternative for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency from Not to Exceed 7 Years to 9 Years for the Third 10-Year Inservice Inspection Interval |
CP-201500999, Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection.. | 15 October 2015 | Revision to Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection.. |
CP-201500727, Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.5.2, ECCS - Operating | 14 July 2015 | Request for Enforcement Discretion Regarding Compliance with Technical Specification 3.5.2, ECCS - Operating |
CP-201500430, Relief Request lB3-4 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Head Penetration Weld Inspection.. | 22 April 2015 | Relief Request lB3-4 Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Head Penetration Weld Inspection.. |
CP-201500402, Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency | 20 April 2015 | Relief Request 1B3-3 Inservice Inspection for Application of an Alternative to ASME Boiler & Pressure Vessel Code Section XI Examination Requirements for Reactor Pressure Vessel Cold Leg Weld Inspection Frequency |
ML14084A291 | 4 April 2014 | Relief Request No. C-3 for Reactor Pressure Vessel Leak-Off Flange for the Second 10-Year Inservice Inspection Interval |
CP-201101030, Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 6, (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2000, Second Interval) | 2 August 2011 | Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 6, (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2000, Second Interval) |
CPSES-200700414, Transmittal of Inservice Inspection Program Plan, Revision 5 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - 08/13/200, Second Interval) | 22 February 2007 | Transmittal of Inservice Inspection Program Plan, Revision 5 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start Date - 08/13/200, Second Interval) |
ML061360087 | 23 May 2006 | Bulletin 2004-01, Inspections of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Comanche Peak Steam Electric Station, Units 1 and 2 |
CPSES-200501745, Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 4 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 200, Second Interval) | 23 August 2005 | Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 4 (Unit 1: ASME Code Section XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 200, Second Interval) |
CPSES-200500134, Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in Fabrication of Pressurizer Penetrations & Steam Space Piping Connections at Pressurized Water Reactors, Revision 1 of NRC Order EA-03-009.. | 27 June 2005 | Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in Fabrication of Pressurizer Penetrations & Steam Space Piping Connections at Pressurized Water Reactors, Revision 1 of NRC Order EA-03-009.. |
ML043430212 | 2 December 2004 | Response to NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity |
CPSES-200401808, 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors. | 27 July 2004 | 60-Day Response to NRC Bulletin 2004-01, Inspection of Alloy 82/182/600 Materials Used in the Fabrication of Pressurizer Penetrations and Steam Space Piping Connections at Pressurized Water Reactors. |
CPSES-200401627, Day Response Regarding NRC Bulletin 2003-02 and NRC Order EA-03-009 | 2 July 2004 | Day Response Regarding NRC Bulletin 2003-02 and NRC Order EA-03-009 |
CPSES-200302701, 60 Day Response Regarding NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity and Report on RCS Conoseal Leakage | 18 December 2003 | 60 Day Response Regarding NRC Bulletin 2003-02, Leakage from Reactor Pressure Vessel Lower Head Penetrations and Reactor Coolant Pressure Boundary Integrity and Report on RCS Conoseal Leakage |
ML022750090 | 17 September 2002 | Second Interval ASME Section XI Inservice Inspection Program Plan Revision 1 |
CPSES-200203264, Day Response to Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs. | 11 September 2002 | Day Response to Bulletin 2002-02, Reactor Pressure Vessel Head and Vessel Head Penetration Nozzle Inspection Programs. |
Information Notice 1994-79, Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping | 23 November 1994 | Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping |
ML19354D767 | 31 December 1989 | Rev 0 to Analytical Evaluation of Station Svc Water Sys, Comanche Peak Nuclear Power Station, Final Rept |
Information Notice 1988-17, Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. | 22 April 1988 | Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants. |
ML20214J932 | 31 May 1986 | Nonproprietary Shotpeening Licensing Rept for Comanche Peak Unit 1 |
NRC Generic Letter 1986-01 | 3 January 1986 | NRC Generic Letter 1986-001: Safety Concerns Associated with Pipe Breaks in the BWR Scram System |