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 Issue dateTitle
CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 44 October 2023Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4
ML23256A15011 September 2023Request for Additional Information Requests - Comanche Peak - Set 4
ML23172A1469 August 2023Aging Management Audit Report - Comanche Peak Units 1 and 2 - License Renewal Application
ML23172A1479 August 2023Breakout 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 327 July 2023Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3
CP-202300165, License Renewal Application Revision 0 - Supplement 224 April 2023License Renewal Application Revision 0 - Supplement 2
ML16179A40511 July 2016Relief Request Nos. B-9, B-3, B-10, and B-11 for Piping Welds, Second 10-year Inservice Inspection Interval
IR 05000445/201600129 April 2016NRC Integrated Inspection Report 05000445/2016001 and 05000446/2016001
ML16074A00114 March 2016Relief 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 2015Revision 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 - Operating14 July 2015Request 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 2015Relief 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 Frequency20 April 2015Relief 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
ML14084A2914 April 2014Relief 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 2011Transmittal 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 2007Transmittal 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)
ML06136008723 May 2006Bulletin 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 2005Transmittal 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 2005Day 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..
ML0434302122 December 2004Response 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 200460-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-03-0092 July 2004Day 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 Leakage18 December 200360 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
ML02275009017 September 2002Second 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 2002Day 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 Piping23 November 1994Microbiologically Influenced Corrosion of Emergency Diesel Generator Service Water Piping
ML19354D76731 December 1989Rev 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 1988Summary of Responses to NRC Bulletin 87-01, Thinning of Pipe Walls in Nuclear Power Plants.
ML20214J93231 May 1986Nonproprietary Shotpeening Licensing Rept for Comanche Peak Unit 1
NRC Generic Letter 1986-013 January 1986NRC Generic Letter 1986-001: Safety Concerns Associated with Pipe Breaks in the BWR Scram System