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Category:Inservice/Preservice Inspection and Test Report
MONTHYEARCP-202300442, (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program2023-09-15015 September 2023 (CPNPP) - Request to Use Later Code Edition for Inservice Inspection (ISI) Program CP-202300411, (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20)2023-08-17017 August 2023 (Cpnpp), Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 2 Refueling Outage 20 (2RF20) 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-202200306, (CPNPP) - Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 22 (1RF22)2022-08-11011 August 2022 (CPNPP) - Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 22 (1RF22) CP-202200200, (CPNPP) Unit 2 Refueling Outage 19 (2RF19) Steam Generator 180 Day Report2022-05-0505 May 2022 (CPNPP) Unit 2 Refueling Outage 19 (2RF19) Steam Generator 180 Day Report TXX-2201, (CPNPP) - Inservice Inspection (ISI) Owner'S Activity Report (OAR-1 Form) for Unit 2 Refueling Outage 19 (2RF19)2022-02-0101 February 2022 (CPNPP) - Inservice Inspection (ISI) Owner'S Activity Report (OAR-1 Form) for Unit 2 Refueling Outage 19 (2RF19) CP-202100751, (CPNPP) - ASME OM Inservice Test Program Relief Request SNB-3, Snubber Inservice Program Third Internal Extension2022-01-0404 January 2022 (CPNPP) - ASME OM Inservice Test Program Relief Request SNB-3, Snubber Inservice Program Third Internal Extension CP-202100150, (CPNPP) Units 1 & 2 - Inservice Testing Plan for Pumps & Valves Third Interval, Revision 42021-03-23023 March 2021 (CPNPP) Units 1 & 2 - Inservice Testing Plan for Pumps & Valves Third Interval, Revision 4 CP-202100061, (CPNPP) - Inservice Inspection (Isi) Owner'S Activity Report (OAR-1 Form) for Unit 1 Refueling Outage 21 (1RF21)2021-01-27027 January 2021 (CPNPP) - Inservice Inspection (Isi) Owner'S Activity Report (OAR-1 Form) for Unit 1 Refueling Outage 21 (1RF21) ML20282A7342020-10-22022 October 2020 Proposed Alternative to the Requirements of the ASME Code to Extend the Inservice Inspection Interval (EPID L-2020-LLR-0059 (COVID-19)) CP-202000463, (CPNPP) - Inservice Test (IST) Program Request to Use Later Code Edition2020-08-31031 August 2020 (CPNPP) - Inservice Test (IST) Program Request to Use Later Code Edition CP-202000262, Snubber Testing and Snubber Visual Examinations Relief Request2020-04-10010 April 2020 Snubber Testing and Snubber Visual Examinations Relief Request CP-202000261, Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests2020-04-0707 April 2020 Inservice Inspection (ISI) and Inservice Testing (IST) Program Relief Requests CP-201900496, Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 20 (IRF20)2019-08-26026 August 2019 Inservice Inspection (ISI) Owner'S Activity Reports (OAR-1 Forms) for Unit 1 Refueling Outage 20 (IRF20) CP-201800215, Submittal of Nineteenth Refueling Outage (1RF19) Steam Generator 180 Day Report2018-04-19019 April 2018 Submittal of Nineteenth Refueling Outage (1RF19) Steam Generator 180 Day Report CP-201800086, Submittal of Unit 1 Nineteenth Refueling Outage (IRF19) Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda Unit 1 Third Interval Start Date: August 13, 2010 Unit 1 Third ..2018-02-0707 February 2018 Submittal of Unit 1 Nineteenth Refueling Outage (IRF19) Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda Unit 1 Third Interval Start Date: August 13, 2010 Unit 1 Third .. CP-201700623, Submittal of Sixteenth Refueling Outage (2RF16) Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval, Start Date: Aug. 3, 2014 Third Interval End Date: Aug. 2, 2023)2017-08-0101 August 2017 Submittal of Sixteenth Refueling Outage (2RF16) Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval, Start Date: Aug. 3, 2014 Third Interval End Date: Aug. 2, 2023) CP-201600869, Submittal of Eighteenth Refueling Outage (1RF18) Inservice Inspection Summary Report2016-08-31031 August 2016 Submittal of Eighteenth Refueling Outage (1RF18) Inservice Inspection Summary Report CP-201600148, Requesting Additional Information for Relief Request b-9 for Unit 2 Second Ten Year Inservice Inspection Interval2016-03-0202 March 2016 Requesting Additional Information for Relief Request b-9 for Unit 2 Second Ten Year Inservice Inspection Interval CP-201600117, Submittal of Fifteenth Refueling Outage (2RF15), Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda, Third Interval Start Date: August 3, 2014, Third Interval End Date: August 2, 2023)2016-02-0808 February 2016 Submittal of Fifteenth Refueling Outage (2RF15), Inservice Inspection (ISI) Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda, Third Interval Start Date: August 3, 2014, Third Interval End Date: August 2, 2023) CP-201500777, Relief Request B-10, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-10, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500775, Relief Request B-3, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-3, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500776, Relief Request B-9, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-9, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500778, Relief Request B-11, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-11, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500779, Relief Request B-15, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request B-15, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500780, Relief Request C-2, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request C-2, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500781, Relief Request C-4, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August..2015-08-0303 August 2015 Relief Request C-4, Second Ten Year Inservice Inspection Interval from 10CFR50.55a Inspection Requirements Due to Physical Interferences (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August.. CP-201500685, Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 & 2.2015-07-22022 July 2015 Response to Request for Additional Information for Relief Request 2A3-1, Unit 2, Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 & 2. CP-201500671, Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3.2015-06-30030 June 2015 Relief Request T-1 for Inservice Testing Program for Application of an Alternative to the ASME OM Code Frequency Specifications, (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date: August 3. CP-201500244, Relief Request 2A3-1 for Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 and 2 Piping Welds (2007 Edition of ASME Code.2015-03-0404 March 2015 Relief Request 2A3-1 for Inservice Inspection for Application of an Alternative to the ASME Boiler and Pressure Vessel Code Section XI Examination Requirements for Class 1 and 2 Piping Welds (2007 Edition of ASME Code. CP-201500157, Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023)2015-02-24024 February 2015 Relief Request No. 2C3-1 for the Reactor Pressure Vessel Leak-Off Flange (Third ISI Interval Start Date: August 3, 2014; Third ISI Interval End Date: August 2, 2023) CP-201500222, Submittal of Unit 1, Seventeenth Refueling Outage (1RF17) Inservice Inspection Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date August 13, 2010 Third Interval End Date: August 12, 2020)2015-02-18018 February 2015 Submittal of Unit 1, Seventeenth Refueling Outage (1RF17) Inservice Inspection Summary Report (2007 Edition of ASME Code, Section XI, 2008 Addenda Third Interval Start Date August 13, 2010 Third Interval End Date: August 12, 2020) ML14325A7592014-11-19019 November 2014 Transmittal of Inservice Testing Plan for Pumps and Valves Third Interval, Revision 1 CP-201401035, Relief Requests Nos. B-7, B-12 and B-13 for the Second 10-Year ISI Interval (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014)2014-08-27027 August 2014 Relief Requests Nos. B-7, B-12 and B-13 for the Second 10-Year ISI Interval (Second ISI Interval Start Date: August 3, 2004; Second ISI Interval End Date: August 2, 2014) CP-201400933, Submittal of Unit 2 Fourteenth Refueling Outage (2RF14) Inservice Inspection (ISI) Summary Report (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August 3, 2004 Second Interval End Date: August 2, 20142014-07-23023 July 2014 Submittal of Unit 2 Fourteenth Refueling Outage (2RF14) Inservice Inspection (ISI) Summary Report (1998 Edition of ASME Code, Section XI, 2000 Addenda Second Interval Start Date: August 3, 2004 Second Interval End Date: August 2, 2014 CP-201401379, Transmittal of Inservice Testing Plan for Pumps and Valves Third Interval, Revision 12014-02-24024 February 2014 Transmittal of Inservice Testing Plan for Pumps and Valves Third Interval, Revision 1 CP-201300143, Response to RAI for Unit 1 Relief Request No. B-22013-02-0707 February 2013 Response to RAI for Unit 1 Relief Request No. B-2 CP-201300005, Submittal of Inservice Inspection Summary Report for the 13th Refueling Outage2013-01-31031 January 2013 Submittal of Inservice Inspection Summary Report for the 13th Refueling Outage CP-201300003, Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010)2013-01-16016 January 2013 Submittal of Relief Request No. B-2, Third 10 Year ISI Interval from 10CFR50.55a Requirements for Reactor Vessel Hot Leg Nozzle Weld Examinations (Third ISI Interval Start Date August 13, 2010) CP-201200879, Relief Request No. V-1 for Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 2004 Edition, Through 2006 Addenda; Third Interval Start Date: August 3, 2013)2012-09-0606 September 2012 Relief Request No. V-1 for Unit 1 and Unit 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 2004 Edition, Through 2006 Addenda; Third Interval Start Date: August 3, 2013) CP-201200045, Submittal of Unit 1 Fifteenth Refueling Outage (1RF15) Inservice Inspection (ISI) Summary Report (Unit 1: 1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - August 13, 2010, Third Interval)2012-01-17017 January 2012 Submittal of Unit 1 Fifteenth Refueling Outage (1RF15) Inservice Inspection (ISI) Summary Report (Unit 1: 1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - August 13, 2010, Third Interval) CP-201101429, Twelfth Refueling Outage (2RF12) Steam Generator 180 Day Report2011-10-12012 October 2011 Twelfth Refueling Outage (2RF12) Steam Generator 180 Day Report CP-201101031, Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 0 (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2010, Third Interval)2011-08-0202 August 2011 Transmittal of Unit 1 Inservice Inspection Program Plan, Revision 0 (Unit 1: ASME Code XI 1998 Edition, 1999 and 2000 Addenda, Interval Start - August 13, 2010, Third Interval) CP-201100852, Submittal of 12th Refueling Outage (2RF12) Inservice Inspection (ISI) Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - August 4,2004, Second Interval)2011-07-21021 July 2011 Submittal of 12th Refueling Outage (2RF12) Inservice Inspection (ISI) Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - August 4,2004, Second Interval) CP-201001545, Relief Request No. B-10 for the Unit 1 Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. B-10 for the Unit 1 Second 10 Years ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) CP-201000889, Relief Request No. C-6 for Unit 1 Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000)2010-12-15015 December 2010 Relief Request No. C-6 for Unit 1 Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) CP-201000888, Submittal of Unit 1 Fourteenth Refueling Outage Inservice Inspection Summary Report (Unit 1: 1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - August 13, 2000, Second Interval)2010-07-22022 July 2010 Submittal of Unit 1 Fourteenth Refueling Outage Inservice Inspection Summary Report (Unit 1: 1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - August 13, 2000, Second Interval) CP-200900707, Revision to Relief Request No. P-2 for the Units 1 & 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval)2009-05-14014 May 2009 Revision to Relief Request No. P-2 for the Units 1 & 2 Inservice Testing Plan for Pumps and Valves (ASME OM Code 1998 Edition, Through 2000 Addenda; Interval Start Date: August 3, 2004, Second Interval) CP-200900009, Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses2009-03-0404 March 2009 Request for Relief to Extend the Unit 1 & 2 Inservice Inspection Interval for the Reactor Vessel Weld Examination and License Amendment Request 09-004 to Add License Condition for Submittal of ISI Information and Analyses CP-200900008, Submittal of Unit 1 Thirteenth Refueling Outage (1RF13) Inservice Inspection (ISI) Summary Report (Unit 1:1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/13/2000, Second Interval2009-01-0808 January 2009 Submittal of Unit 1 Thirteenth Refueling Outage (1RF13) Inservice Inspection (ISI) Summary Report (Unit 1:1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/13/2000, Second Interval 2023-09-15
[Table view] Category:Letter type:CPSES
MONTHYEARCPSES-201001000, Operator Licensing Examination Data, Form 5362010-07-28028 July 2010 Operator Licensing Examination Data, Form 536 CPSES-200901377, Operator Licensing Examination Data2009-09-29029 September 2009 Operator Licensing Examination Data 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.2007-11-15015 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. CPSES-200701495, Withdrawal of License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-10-22022 October 2007 Withdrawal of License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200701530, Additional Information in Connection with the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments2007-10-0909 October 2007 Additional Information in Connection with the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments CPSES-200701496, Information Required by Order Approving the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments2007-10-0202 October 2007 Information Required by Order Approving the Indirect Transfer of Facility Operating Licenses and Conforming License Amendments CPSES-200701351, Transmittal of First-Half 2007 Fitness-for-Duty Program Performance Data2007-08-29029 August 2007 Transmittal of First-Half 2007 Fitness-for-Duty Program Performance Data CPSES-200701076, Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt2007-08-28028 August 2007 Revision to the Operating License and Technical Specifications 1.0, Use and Application and 3.7.17, Spent Fuel Assembly Storage to Revise Rated Thermal Power from 3458 Mwt to 3612 Mwt CPSES-200701302, Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval)2007-08-22022 August 2007 Relief Request B-4 to the Unit 2 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date - August 03, 2004, Second Interval) CPSES-200701324, Supplement to License Amendment Request (LAR) 07-003 Revision to Technical Specification 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, and 5.6.5 B, Core Operating Limits2007-08-16016 August 2007 Supplement to License Amendment Request (LAR) 07-003 Revision to Technical Specification 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, and 5.6.5 B, Core Operating Limits CPSES-200701323, License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System..2007-08-16016 August 2007 License Amendment Request 07-006, Revision to Technical Specification 3.1.4, Rod Group Alignment Limits, Table 3.3.1-1, Reactor Trip System Instrumentation, Table 3.3.2-1, Engineered Safety Feature Actuation System.. CPSES-200701279, Mitigation of Alloy 82/182 Pressurizer Butt Welds in 20082007-08-0303 August 2007 Mitigation of Alloy 82/182 Pressurizer Butt Welds in 2008 CPSES-200701284, (Cpses), Operator Licensing Examination Data2007-08-0202 August 2007 (Cpses), Operator Licensing Examination Data 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-200701178, Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 72007-07-20020 July 2007 Supplement to Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change (TAC Nos. MD5289 and MD5280), Enclosures 1, 4, 5, 6 & 7 CPSES-200701126, Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-07-18018 July 2007 Response to Request for Additional Information to License Amendment Request (LAR) 06-007 Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits CPSES-200701174, Submittal of Twelfth Refueling Outage (1RF12) Inservice Inspection Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/03/2000, Second Interval)2007-07-17017 July 2007 Submittal of Twelfth Refueling Outage (1RF12) Inservice Inspection Summary Report (1998 Edition of ASME Code Section XI Through 2000 Addenda, Interval Start Date - 08/03/2000, Second Interval) CPSES-200701065, Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.2007-06-21021 June 2007 Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients. CPSES-200700951, (Cpses), Unit 1, Pressurizer Weld Overlay 60 Day Report and Update for Unit 1 Reactor Pressure Vessel Head Replacement Regarding Revised Order EA-03-0092007-06-19019 June 2007 (Cpses), Unit 1, Pressurizer Weld Overlay 60 Day Report and Update for Unit 1 Reactor Pressure Vessel Head Replacement Regarding Revised Order EA-03-009 CPSES-200701059, Submittal of Startup Report, Cycle 132007-06-13013 June 2007 Submittal of Startup Report, Cycle 13 CPSES-200700738, License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves2007-05-22022 May 2007 License Amendment Request (LAR) 07-001 Revision to Technical Requirements Surveillance 13.3.33.2 Frequency for the Turbine Stop and Control Valves CPSES-200700915, Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability2007-05-0707 May 2007 Supplemental Response to Request for Information on Generic Letter 2003-01, Control Room Habitability CPSES-200700871, Transmittal of Year 2006 Radioactive Effluent Release Report2007-04-30030 April 2007 Transmittal of Year 2006 Radioactive Effluent Release Report CPSES-200700859, Submittal of the Annual Non-Radiological Environmental Operating Report for 20062007-04-27027 April 2007 Submittal of the Annual Non-Radiological Environmental Operating Report for 2006 CPSES-200700517, Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change2007-04-18018 April 2007 Application for Order Approving Indirect Transfer of Control of Licenses and License Amendments to Reflect Proposed Licensee Name Change CPSES-200700719, Nuclear Liability Insurance2007-04-10010 April 2007 Nuclear Liability Insurance CPSES-200700605, License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report2007-04-10010 April 2007 License Amendment Request (LAR) 07-003, Revision to Technical Specifications 3.1, Reactivity Control Systems, 3.2, Power Distribution Limits, 3.3, Instrumentation, & 5.6.5b, Core Operating Limits Report CPSES-200700708, Evaluation of Pressurizer Weld Overlay Confirmatory Analyses2007-04-0505 April 2007 Evaluation of Pressurizer Weld Overlay Confirmatory Analyses CPSES-200700691, Core Operating Limits Report, Cycle 132007-04-0404 April 2007 Core Operating Limits Report, Cycle 13 CPSES-200700663, Transmittal of the Annual Radiological Environmental Operating Report for 20062007-03-30030 March 2007 Transmittal of the Annual Radiological Environmental Operating Report for 2006 CPSES-200700607, Property Damage Insurance2007-03-29029 March 2007 Property Damage Insurance CPSES-200700606, Decommissioning Report2007-03-29029 March 2007 Decommissioning Report CPSES-200700573, Request to Withdraw Relief Request A-72007-03-22022 March 2007 Request to Withdraw Relief Request A-7 CPSES-200700571, Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186)2007-03-19019 March 2007 Supplement to License Amendment Request (LAR) 05-06; Revision to Technical Specification 5.6.5 Revise Listing of LOCA and Non-LOCA Analysis Methodologies (TAC Nos. MD0185/0186) CPSES-200700515, Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients.2007-03-0909 March 2007 Day Response to NRC Generic Letter 2007-01, Inaccessible or Underground Power Cable Failures That Disable Accident Mitigation Systems or Cause Plant Transients. CPSES-200700454, Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data2007-02-28028 February 2007 Transmittal of Second-Half 2006 Fitness-For-Duty Program Performance Data CPSES-200700451, Annual Operating Report for 20062007-02-28028 February 2007 Annual Operating Report for 2006 CPSES-200700422, Response to Request for Additional Information Related to Txu Power'S Request for Review of Previously Submitted Topical Reports2007-02-22022 February 2007 Response to Request for Additional Information Related to Txu Power'S Request for Review of Previously Submitted Topical Reports 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)2007-02-22022 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) CPSES-200700391, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds2007-02-20020 February 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds 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-200700229, Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date..2007-02-0202 February 2007 Comanche, Response to Request for Additional Information, Relief Request B-6 for the Unit 1 Inservice Inspection (ISI) Program Plan from the 1998 Edition of ASME Code, Section XI, Through 2000 Addenda (Interval Start Date.. CPSES-200700169, Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds2007-01-30030 January 2007 Inspection and Mitigation of Alloy 82/182 Pressurizer Butt Welds CPSES-200700147, Response to Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power2007-01-29029 January 2007 Response to Request for Additional Information Regarding Resolution of Generic Letter 2006-02, Grid Reliability and the Impact on Plant Risk and the Operability of Offsite Power CPSES-200700127, Submittal of Unit 2 Ninth Refueling Outage (2RF09) Inservice Inspection (ISI) Summary Report (Unit 2: 1998 Edition of ASME Code Section XI, Through 2000 Addenda, Interval Start Date - August 3, 2004, Second Interval)2007-01-24024 January 2007 Submittal of Unit 2 Ninth Refueling Outage (2RF09) Inservice Inspection (ISI) Summary Report (Unit 2: 1998 Edition of ASME Code Section XI, Through 2000 Addenda, Interval Start Date - August 3, 2004, Second Interval) CPSES-200700146, License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits2007-01-18018 January 2007 License Amendment Request (LAR) 06-007, Revision to Technical Specification (TS) 3.8.1, AC Sources - Operating, Extension of Completion Times for Offsite Circuits 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 Generators2007-01-18018 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-200700099, Annual Report of Changes in Peak Cladding Temperature2007-01-10010 January 2007 Annual Report of Changes in Peak Cladding Temperature CPSES-200602339, License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program.2006-12-19019 December 2006 License Amendment Request (LAR) 06-010, Revision to Technical Specification 5.5.16, Containment Leakage Rate Testing Program. CPSES-200602340, License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating.2006-12-19019 December 2006 License Amendment Request (LAR) 06-012, Revision to Technical Specification 3.7.5, Auxiliary Feedwater System, TS 3.8.1, AC Sources - Operating, & TS 3.8.9, Distribution Systems - Operating. 2010-07-28
[Table view] Category:License-Application for Facility Operating License (Amend/Renewal) DKT 50
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 ML24023A0242024-01-24024 January 2024 Correction to Amendment Nos. 185 and 185 Regarding Implementation of Full Spectrum Loss-of-Coolant Accident Methodology CP-202300494, License Renewal Application Revision 0, Supplement 32023-12-0606 December 2023 License Renewal Application Revision 0, Supplement 3 CP-202300349, License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation2023-11-20020 November 2023 License Amendment Request (Lar) 23-004 Technical Specifications (TS) 3.9.3, Nuclear Instrumentation 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 Days2023-09-14014 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 L-23-205, Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-09-12012 September 2023 Supplement to Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300096, License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements2023-04-20020 April 2023 License Amendment Request (LAR) 23-002 Application Regarding GDC-5 Shared Systems Requirements CP-202300140, Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-0012023-04-19019 April 2023 Application to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors. LAR 23-001 CP-202300157, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-14014 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, and ISFSI, Application for Order Consenting to Transfer of Licenses and Conforming License Amendments CP-202300135, License Renewal Application Revision 0 - Supplement 12023-04-0606 April 2023 License Renewal Application Revision 0 - Supplement 1 CP-202200380, (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications2022-11-21021 November 2022 (CPNPP) - Non-Voluntary License Amendment Request to Revise Technical Specifications 3.2.1, Fq(Z), to Implement Methodology from WCAP-17661, Revision 1, Improved RAOC and CAOC Fq Surveillance Technical Specifications CP-202200355, Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-0022022-11-21021 November 2022 Application to Revise Technical Specifications to Apply the Westinghouse Full Spectrum Loss of Coolant Accident Evaluation Model LAR 22-002 CP-202200350, Facility Operating License Numbers NPF-87 and NPF-89 - License Renewal Application - Appendix E, Environmental Report2022-10-0303 October 2022 Facility Operating License Numbers NPF-87 and NPF-89 - License Renewal Application - Appendix E, Environmental Report ML22192A0072022-08-22022 August 2022 Issuance of Amendment Nos. 183 and 183 Regarding the Adoption of Technical Specifications Task Force Traveler TSTF-505, Revision 2 CP-202200273, Third Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative2022-07-20020 July 2022 Third Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative CP-202200006, (CPNPP) - Second Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended.2022-02-17017 February 2022 (CPNPP) - Second Supplement to License Amendment Request (LAR) 20-006 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended. CP-202200075, Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2022-02-15015 February 2022 Third Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202100575, (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-08-31031 August 2021 (CPNPP) - Supplement to Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202100251, (CPNPP) - Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections2021-07-27027 July 2021 (CPNPP) - Application to Revise Technical Specifications to Adopt TSTF 577, Revised Frequencies for Steam Generator Tube Inspections CP-202100394, Supplement to License Amendment Request (LAR) 20-0062021-07-13013 July 2021 Supplement to License Amendment Request (LAR) 20-006 CP-202100065, Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b2021-05-11011 May 2021 Application to Revise Technical Specifications to Adopt Risk Informed Completion Times, TSTF-505, Revision 2, Provide Risk-Informed Extended Completion Times - RITSTF Initiative 4b CP-202000585, (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump2021-01-27027 January 2021 (CPNPP) - Supplement to License Amendment Request (LAR) 20-005, Revision to Technical Specification (TS) 3.6.8, Containment Sump CP-202000584, (CPNPP) - Supplement to License Amendment Request (LAR) 15-001, Revision to Technical Specification (TS) 3.8.l, AC SOURCES-OPERATING2020-12-0909 December 2020 (CPNPP) - Supplement to License Amendment Request (LAR) 15-001, Revision to Technical Specification (TS) 3.8.l, 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 - Operating2020-11-19019 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 CP-202000365, Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump2020-08-31031 August 2020 Luminant, Comamche Leak Nuclear Power Plant, License Amendment Request 20-005, New Technical Specification 3.6.8, Containment Sump CP-202000401, (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water2020-07-28028 July 2020 (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water CP-202000388, (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water2020-07-16016 July 2020 (CPNPP) - Supplement to Exigent License Amendment Request (LAR) 20-002, Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water CP-202000321, (CPNPP) - License Amendment Request (LAR) 20-001 Technical Specification (TS) 1.1, Definitions - ESP & RTS Response Time2020-07-0202 July 2020 (CPNPP) - License Amendment Request (LAR) 20-001 Technical Specification (TS) 1.1, Definitions - ESP & RTS Response Time CP-202000305, (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water2020-06-24024 June 2020 (CPNPP) - Exigent License Amendment Request (LAR) 20-002 Revision to Technical Specification (TS) 3.7.19, Safety Chilled Water TXX-2002, Exigent License Amendment Request (LAR) 20-003 Revision to Technical Specification (TS) 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Program2020-04-10010 April 2020 Exigent License Amendment Request (LAR) 20-003 Revision to Technical Specification (TS) 5.5.9, Unit 1 Model D76 and Unit 2 Model D5 Steam Generator Program CP-201900368, Revision to Technical Specifications 3.8.1, AC Sources - Operating2020-03-31031 March 2020 Revision to Technical Specifications 3.8.1, AC Sources - Operating CP-202000016, Editorial Correction to License Amendment Request (LAR) 19-002 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program.2020-01-16016 January 2020 Editorial Correction to License Amendment Request (LAR) 19-002 Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program. CP-201900393, License Amendment Request (LAR) 19-001, Application to Adopt TSTF-513-A, Revision 3, PWR Operability Requirements and Actions for RCS Leakage Instrumentation2019-11-0707 November 2019 License Amendment Request (LAR) 19-001, Application to Adopt TSTF-513-A, Revision 3, PWR Operability Requirements and Actions for RCS Leakage Instrumentation CP-201900415, License Amendment Request (LAR) 19-002, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program2019-11-0707 November 2019 License Amendment Request (LAR) 19-002, Application to Adopt TSTF-563, Revise Instrument Testing Definitions to Incorporate the Surveillance Frequency Control Program CP-201800115, License Amendment Request 17-001 Revision to Technical Specification 3.3.2. ESFAS Instrumentation2018-03-29029 March 2018 License Amendment Request 17-001 Revision to Technical Specification 3.3.2. ESFAS Instrumentation ML17074A4942017-04-13013 April 2017 Issuance of Amendment Nos. 168 and 168 Adoption of TSTF-545, Revision 3, TS Inservice Testing Program Removal & Clarify SR Usage Rule Application to Section 5.5 Testing ML16351A2002016-12-14014 December 2016 Submittal of License Amendment Request 16-003, Administrative Change to License Name CP-201600216, License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing.2016-04-27027 April 2016 License Amendment Request 16-001, Application to Revise Technical Specifications to Adopt TSF-545, Revision 3, TS Inservice Testing Program Removal and Clarify SR Usage Rule Application to Section 5.5 Testing. CP-201501062, ISFSI - Application for Order Approving Transfer of Licenses and Conforming License Amendments2015-11-12012 November 2015 ISFSI - Application for Order Approving Transfer of Licenses and Conforming License Amendments CP-201400165, (CPNPP) - Redacted Version of License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule2014-02-0404 February 2014 (CPNPP) - Redacted Version of License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule CP-201301322, License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule2013-11-21021 November 2013 License Amendment Request (LAR) 13-003, for Approval of the Revised CPNPP Cyber Security Plan Implementation Schedule CP-201301065, Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process2013-08-29029 August 2013 Revision to Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item Improvement Process CP-201300738, License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item..2013-07-10010 July 2013 License Amendment Request 13-002, Application to Revise Technical Specifications to Adopt TSTF-510, Revision to Steam Generator Program Inspection Frequencies and Tube Sample Selection, Using the Consolidated Line Item.. 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.2013-03-28028 March 2013 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. 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.2013-01-15015 January 2013 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. CP-201200518, License Amendment Request (LAR) 12-004, Revision to Technical Specification 3.8.1, Ac Sources - Operating, for Two, 14-Day Completion Times for Offsite Circuits2012-10-0202 October 2012 License Amendment Request (LAR) 12-004, Revision to Technical Specification 3.8.1, Ac Sources - Operating, for Two, 14-Day Completion Times for Offsite Circuits CP-201200552, License Amendment Request (LAR) 2012-001, Revision to Technical Specification 5.7, High Radiation Area and Technical Specifications Table 3.3.3-12012-07-12012 July 2012 License Amendment Request (LAR) 2012-001, Revision to Technical Specification 5.7, High Radiation Area and Technical Specifications Table 3.3.3-1 CP-201200012, (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent ....2012-03-28028 March 2012 (Cpnpp), Revision to Technical Specification (TS) 5.5.9, Unit 1 D76 and Unit 2 D5 Steam Generator (SG) Program, and TS 5.6.9, Unit 1 D76 and Unit 2 D5 Steam Generator Tube Inspection Report, for a Permanent .... CP-201101038, License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled2011-08-0101 August 2011 License Amendment Request (LAR) 11-001, Application for Technical Specification Change Regarding Risk-Informed Justification for the Relocation of Specific Surveillance Frequency Requirements to a Licensee Controlled 2024-01-31
[Table view] |
Text
TXU Power TXU Power Mike Blevins Comanche Peak Steam Senior V& & Reeside5t Elecric Statio Chief NuclearOffimr Ref. 10CFR50.90 P-O Box 1002 (E01)
Glen Rose, TX 76043 Tel: 254 897 5209 Fax: 254 897 6652 mtke.blevins@txu.com CPSES-200602339 Log# TXX-06191 File # 00236 December 19, 2006 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50-446 LICENSE AMENDMENT REQUEST (LAR) 06-0 10 REVISION TO TECHNICAL SPECIFICATION 5.5.16, "CONTAINMENT LEAKAGE RATE TESTING PROGRAM"
Dear Sir or Madam:
Pursuant to I OCFR50.90, TXU Generation Company LP (TXU Power) hereby requests an amendment to the CPSES Unit I Operating License (NPF-87) and CPSES Unit 2 Operating License (NPF-89) by incorporating the attached change into the CPSES Unit I and 2 Technical Specifications. This change request applies to both units.
The proposed change will revise TS 5.5.16 entitled "Containment Leakage Rate Testing Program". The proposed change revises TS 5.5.16, "Containment Leakage Rate Testing Program," for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC. This regulation requires licensees to update their containment inservice inspection requirements in accordance with Subsections IWE and IWL of Section XI, Division I of the ASME Boiler and Pressure Vessel Code as limited by 10 CFR 50.55a(b)(2)(vi) and modified by 10 CFR 50.55a(b)(2)(viii) and 10 CFR50.55a(b)(2)(ix).
A member of the STARS (Strategic Teaming and Resource Sharing) Alliance XO/
Callaway Comanche Peak Diablo Canyon Palo Verde South Texas Project Wolf Creek A047
TXX-06191 Page 2 of 3 provides a detailed description of the proposed changes, a technical analysis of the proposed changes, TXU Power's determination that the proposed changes do not involve a significant hazard consideration, a regulatory analysis of the proposed changes and an environmental evaluation. Attachment 2 provides the affected Technical Specifications (TS) pages marked-up to reflect the proposed changes. Attachment 3 provides proposed changes to the Technical Specification Bases for information only. These changes will be processed per CPSES site procedures. Attachment 4 provides retyped Technical Specifications pages which incorporate the requested changes. Attachment 5 provides retyped Technical Specifications Bases pages which incorporate the proposed changes (for information only).
TXU Power requests approval of the proposed License Amendment by December 31, 2007, to be implemented within 120 days of the issuance of the license amendment.
The approval date was administratively selected to allow for NRC review but the plant does not require this amendment to allow continued safe full power operations.
In accordance with IOCFR50.91 (b), TXU Power is providing the State of Texas with a copy of this proposed amendment.
This communication contains no new or revised commitments.
Should you have any questions, please contact Mr. Carl Corbin at (254) 897-0121.
TXX-06191 Page 3 of3 I state under penalty of perjury that the foregoing is true and correct.
Executed on December 19, 2006.
Sincerely, TXU Generation Company LP By: TXU Generation Management Company LLC Its General Partner Mike Blevins By: IL..
F *er'd . Madden Director, Oversight and Regulatory Affairs CBC Attachments I. Description and Assessment
- 2. Proposed Technical Specifications Changes (Mark-up)
- 3. Proposed Technical Specifications Bases Changes (Markup For Information Only)
- 4. Retyped Technical Specifications Pages
- 5. Retyped Technical Specifications Bases Pages (for information) c - B. S. Mallett, Region IV M. C. Thadani, NRR Resident Inspectors, CPSES Ms. Alice Rogers Bureau of Radiation Control Texas Department of Public Health 1100 West 49th Street Austin, Texas 78756-3189
ATTACHMENT 1 to TXX-06191 DESCRIPTION AND ASSESSMENT
Attachment I to TXX-06191 Page 1 of 9 LICENSEE'S EVALUATION
1.0 DESCRIPTION
2.0 PROPOSED CHANGE
3.0 BACKGROUND
4.0 TECHNICAL ANALYSIS
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration 5.2 Applicable Regulatory Requirements/Criteria
6.0 ENVIRONMENTAL CONSIDERATION
7.0 PRECEDENTS to TXX-06191 Page 2 of 9
1.0 DESCRIPTION
By this letter, TXU Generation Company LP (TXU Power) requests an amendment to the CPSES Unit I Operating License (NPF-87) and CPSES Unit 2 Operating License (NPF-
- 89) by incorporating the attached change into the CPSES Unit 1 and 2 Technical Specifications. Proposed change LAR 06-010 is a request to revise Technical Specifications (TS) 5.5.16, "Containment Leakage Rate Testing Program," for Comanche Peak Steam Electric Station (CPSES) Units I and 2.
The proposed changes are based on the NRC-approved Technical Specifications Task Force Improved Standard Technical Specifications Change Traveler 343, Rev. 1, "Revision to TS 5.5.16 and associated TS Bases for Containment Leakage Rate Testing Program" (TSTF-343). The proposed changes are consistent with the wording in section 5.5.16 of NUREG- 143 1, Revision 3.1, "Standard Technical Specifications, Westinghouse Plants" (STS), since STS has already incorporated TSTF-343. The proposed change revises TS 5.5.16, "Containment Leakage Rate Testing Program," for consistency with the requirements of 10 CFR 50.55a(g)(4) for components classified as Code Class CC.
This regulation requires licensees to update their containment inservice inspection requirements in accordance with Subsections IWE and IWL of Section XI, Division I of the ASME Boiler and Pressure Vessel Code as limited by 10 CFR 50.55a(b)(2)(vi) and modified by 10 CFR 50.55a(b)(2)(viii) and 10 CFR50.55a(b)(2)(ix). The proposed change also revises TS Bases Surveillance Requirements SR 3.6.1.1. The TS Bases for SR 3.6.1.1 is revised for consistency with the requirements of the ASME Code Section XI, Subsection IWL, and applicable addenda as required by 10 CFR 50.55a.
CPSES Final Safety Analysis Report Chapter 6 will be updated as a result of this License Amendment Request.
2.0 PROPOSED CHANGE
The proposed change would revise TS 5.5.16 by adding the following exceptions to Regulatory Guide 1.163, "Performance- Based Containment Leak-Testing Program,"
- 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.
- 2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by
Attachment I to TXX-06191 Page 3 of 9 ASME Section XI Code, Subsection IWE, except where relief has been authorized by the NRC."
The TS Bases for SR 3.6.1.1 is revised for consistency with the requirements of the ASME Code Section XI, Subsection IWL, and applicable addenda as required by 10 CFR 50.55a. The TS Bases changes are provided for information only.
3.0 BACKGROUND
On January 7, 1994, the Nuclear Regulatory Commission (NRC) published a proposed amendment to the regulations to incorporate by reference the 1992 Edition with the 1992 Addenda of Subsections IWE and IWL of Section XI, Division I of the ASME Boiler and Pressure Vessel Code (the Code). The final rule, Subpart 50.55a(g)(6)(ii)(B) of Title 10 of the Code of Federal Regulations (10 CFR), became effective on September 9, 1996, and requires licensees to implement Subsections IWE and IWL, with specified modifications and limitations, by September 9, 2001.
The containment structure is a fully continuous, steel-lined, reinforced concrete structure.
It consists of a vertical cylinder and a hemispherical dome.
4.0 TECHNICAL ANALYSIS
The Technical Specification requirements for the Containment Leakage Rate Testing Program specify that the program shall be in accordance with the guidelines contained in Regulatory Guide 1.163. Regulatory Position C.3 of the regulatory guide states that "Section 9.2.1, 'Pretest Inspection and Test Methodology,' of NEI 94-01 provides guidance for the visual examination of accessible interior and exterior surfaces of the containment system for structural problems. These examinations should be conducted prior to initiating a Type A test, and during two other refueling outages before the next Type A test if the interval for the Type A test has been extended to 10 years, in order to allow for early uncovering of evidence of structural deterioration." There are no specific requirements in NEI 94-01 for the visual examination except that it is to be a general visual examination of accessible interior and exterior surfaces of the primary containment components.
In addition to the requirements of Regulatory Guide 1.163 and NEI 94-01, the concrete surfaces of the containment must be visually examined in accordance with the ASME Section XI Code, Subsection IWL, and the liner plate inside containment must be visually examined in accordance with Subsection IWE. The frequency of visual examination of the concrete surfaces per Subsection IWL is once every five years, and the frequency of visual examination of the liner plate per Subsection IWE is, in general, three visual examinations over a 10-year period. The visual examinations performed
Attachment I to TXX-06191 Page 4 of 9 pursuant to Subsection IWL may be performed at any time during power operation or during shutdown, and the visual examinations performed pursuant to Subsection IWE are performed during refueling outages since this in the only time that the liner plate is fully accessible.
The visual examinations performed pursuant to Subsections IWL and IWE are more rigorous than those performed pursuant to Regulatory Guide 1.163 and NEI 94-01. For example, Subarticle IWE-2320 requires the general visual examination to be the responsibility of an individual who is knowledgeable in the requirements for design, inservice inspection, and testing of Class MC and metallic liners of Class CC components. Subsection IWE, Subarticle-2330 requires the examination to be performed either directly or remotely, by an examiner with visual acuity sufficient to detect evidence of degradation.
Similarly, Subarticle IWL-2320 states that:
"The Responsible Engineer shall be a Registered Professional Engineer experienced in evaluating the inservice condition of structural concrete. The Responsible Engineer shall have knowledge of the design and Construction Codes and other criteria use in design and construction of concrete containments in nuclear power plants.
The Responsible Engineer shall be responsible for the following:
(a) development of plans and procedures for examination of concrete surfaces; (b) approval, instruction, and training of concrete examination personnel; (c) evaluation of examination results; (d) preparation or review of Repair/Replacement Plans and procedures; (e) review of procedures for pressure tests following repair/replacement procedures; (f) submittal of report to the Owner documenting results of examinations and repairs."
Based on the above, the Responsible Engineer will ensure that a comprehensive visual examination of the concrete is performed in accordance with Code requirements except where relief has been granted by the NRC. Furthermore, with respect to examinations performed pursuant to both Subsections IWL and IWE, visual examinations of both the concrete surfaces and the liner plate must be reviewed by an Inspector employed by a State or municipality of the United States or an Inspector regularly employed by an insurance company authorized to write boiler and pressure vessel insurance, in accordance with IWA-21 10 and IWA-2120. The combination of the Code requirements for the rigor of the visual examinations plus the third party review will more than offset the fact that one fewer visual examination of the concrete will be performed during a 10-to TXX-06191 Page 5 of 9 year interval. The fact that the concrete visual examination pursuant to Subsection IWL may be performed during power operation as opposed to during a refueling outage will have no effect on the quality of the examination and will provide flexibility in scheduling of the visual examinations.
5.0 REGULATORY ANALYSIS
5.1 No Significant Hazards Consideration TXU Power has evaluated whether or not a significant hazards consideration is involved with the proposed amendment(s) by focusing on the three standards set forth in IOCFR50.92, "Issuance of amendment," as discussed below:
I. Do the proposed changes involve a significant increase in the probability or consequences of an accident previously evaluated?
Response: No The proposed change revises the TS administrative controls programs for consistency with the requirements of 10 CFR 50, paragraph 55a(g)(4) for components classified as Code Class CC.
The proposed change affects the frequency of visual examinations that will be performed for the concrete surfaces of the containment for the purpose of the Containment Leakage Rate Testing Program. In addition, the proposed change allows those examinations to be performed during power operation as opposed to during a refueling outage. The frequency of visual examinations of the concrete surfaces of the containment and the mode of operation during which those examinations are performed has no relationship to or adverse impact on the probability of any of the initiating events assumed in the accident analyses. The proposed change would allow visual examinations that are performed pursuant to NRC approved ASME Section XI Code requirements (except where relief has been granted by the NRC) to meet the intent of visual examinations required by Regulatory Guide 1.163, without requiring additional visual examinations pursuant to the Regulatory Guide. The intent of early detection of deterioration will continue to be met by the more rigorous requirements of the Code required visual examinations. As such, the safety function of the containment as a fission product barrier is maintained.
Attachment I to TXX-06191 Page 6 of 9 The proposed change does not impact any accident initiators or analyzed events or assumed mitigation of accident or transient events. It does not involve the addition or removal of any equipment, or any design changes to the facility.
Therefore, the proposed change does not involve a significant increase in the probability or consequences of an accident previously evaluated.
- 2. Do the proposed changes create the possibility of a new or different kind of accident from any accident previously evaluated?
Response: No The proposed change revises the TS administrative controls programs for consistency with the requirements of 10 CFR 50, paragraph 55a(g)(4) for components classified as Code Class CC.
The change affects the frequency of visual examinations that will be performed for the concrete surfaces containments. In addition, the proposed change allows those examinations to be performed during power operation as opposed to during a refueling outage. The proposed change does not involve a modification to the physical configuration of the plant (i.e., no new equipment will be installed) or change in the methods governing normal plant operation. The proposed change will not impose any new or different requirements or introduce a new accident initiator, accident precursor, or malfunction mechanism. Additionally, there is no change in the types or increases in the amounts of any effluent that may be released off-site and there is no increase in individual or cumulative occupational exposure.
Therefore, the proposed change does not create the possibility of a new or different kind of accident from any accident previously evaluated.
- 3. Do the proposed changes involve a significant reduction in a margin of safety?
Response: No The proposed change revises the Improved Standard Technical Specification Administrative Controls program requirements for consistency with the requirements of 10 CFR 50, paragraph 55a(g)(4) for components classified as Code Class CC.
Attachment I to TXX-06191 Page 7 of 9 The change affects the frequency of visual examinations that will be performed for the concrete surfaces containments. In addition, the proposed change allows those examinations to be performed during power operation as opposed to during a refueling outage. The safety function of the containment as a fission product barrier will be maintained.
Therefore, the proposed change does not involve a significant reduction in a margin of safety.
Based on the above evaluations, TXU Power concludes that the proposed amendment(s) present no significant hazards under the standards set forth in 10CFR50.92(c) and, accordingly, a finding of no significant hazards consideration is justified.
5.2 Applicable Regulatory Requirements/Criteria The regulatory basis for PWR ISTS 3.6.1, "Containment," is to ensure that the containment is capable of remaining leak-tight following a loss of coolant accident.
This ensures that offsite radiation exposures are maintained within the limits of 10 CFR 100.
10 CFR 50, Appendix A, General Design Criterion 16, "Design," requires that reactor containment and associated systems shall be provided to establish an essentially leak-tight barrier against the uncontrolled release of radioactivity to the environment and to assure that the containment design conditions important to safety are not exceeded for as long as the postulated accident conditions require.
This Technical Specification change will not reduce the leak-tightness of the containment. Therefore, based on the considerations discussed above:
- 1) There is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner;
- 2) Such activities will be conducted in compliance with the Commission's regulations; and
- 3) Issuance of the amendment will not be inimical to the common defense and security or to the health and safety of the public.
In conclusion, based on the considerations discussed above, (1) there is reasonable assurance that the health and safety of the public will not be endangered by operation in the proposed manner, (2) such activities will be conducted in compliance with the Commission's regulations, and (3) the issuance of the amendment will not be inimical to
Attachment I to TXX-06191 Page 8 of 9 the common defense and security or to the health and safety of the public.
6.0 ENVIRONMENTAL CONSIDERATION
TXU Power has determined that the proposed amendment would change requirements with respect to the installation or use of a facility component located within the restricted area, as defined in I OCFR20, or would change an inspection or surveillance requirement.
TXU Power has evaluated the proposed changes and has determined that the changes do not involve (i) a significant hazards consideration, (ii) a significant change in the types or significant increase in the amount of effluent that may be released offsite, or (iii) a significant increase in the individual or cumulative occupational radiation exposure.
Accordingly, the proposed change meets the eligibility criterion for categorical exclusion set forth in I OCFR51.22 (c)(9). Therefore, pursuant to IOCFR51.22 (b), an environmental assessment of the proposed change is not required.
7.0. PRECEDENTS 7.1 10 CFR 50.55a, "Codes and Standards."
7.2 Regulatory Guide 1.163, "Performance-Based Containment Leak-Testing Program."
7.3 Letter dated January 18, 2000, to W. R. McCollum, Jr., Duke Energy Corporation, "Oconee Nuclear Station Units 1, 2, and 3 RE: Issuance of Amendments (TAC Nos. MA6568, MA6569, and MA6570)." Amendment Nos.
310 7.4 Letter dated June 6, 2001, to J. B. Beasley, Jr., Southern Nuclear Operating Company, Inc, "Vogtle Electric Generating Plant, Units 1 and 2 RE: Issuance of Amendments (TAC Nos. MB 1097 and MB 1098)." Amendment Nos. 122 and 100.
7.5 Letter dated January 30, 2001, to C. H. Cruse, Constellation Nuclear, "Calvert Cliffs Nuclear Power Plant, Unit Nos. 1 and 2 RE: Containment Tendon Surveillance Program - Amendment (TAC Nos. MBOOl I and MBOO 12)."
Amendment Nos. 240 and 214.
7.6 Letter dated January 31, 2001, to T. F. Plunkett, Florida Power and Light Company, "Turkey Point Units 3 and 4 - Issuance of Amendments Regarding Changes to Containment Structural Integrity Technical Specifications (TAC Nos.
MA9047 and MA9048)." Amendment Nos. 210 and 204.
Attachment I to TXX-06191 Page 9 of 9 7.7 Letter dated March 19, 2004, to G. R. Overbeck, Arizona Public Service Company, "Palo Verde Nuclear Generating Station, Units 1, 2, and 3 - Issuance of Amendment on Containment Tendon Surveillance Program and Containment Leakage Rate Testing Program (TAC Nos. MC 1069, MC 1070, and MC 1071)."
Amendment Nos. 151.
7.8 Letter dated March 17, 2004, to R. A. Muench, Wolf Creek Nuclear Operating Corporation, "Wolf Creek Generating Station - Issuance of Amendment Re:
Containment Tendon Surveillance Program and Containment Leakage Rate Testing Program." Amendment No. 152.
to TXX-06 191 Page 1 of 3 ATTACHMENT 2 to TXX-06191 PROPOSED TECHNICAL SPECIFICATIONS CHANGES (MARK-UP)
Pages 5.0-27 to TXX-06191 Page 2 of 3 Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16. Containment Leakage Rate Testing Program
- a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program, dated September, 1995" as modified by the following e: 98
/ S i" J,. / NEI 94-01 -1995, Section 9.2.3: The first Type A Test performed 3 after the December 7, 1993 Type A Test (Unit 1) and the December 1, 1997 Type A Test (Unit 2) shall be performed no later than December 15, 2008 (Unit 1) and December 9, 2012 (Unit 2)."
- b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 48.3 psig.
- c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.
- d. Leakage rate acceptance criteria are:
- 1. Containment leakage rate acceptance criteria is - 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests and < 0.75 La for Type A tests;
- 2. Air lock testing acceptance criteria are:
a) Overall air lock leakage rate is - 0.05 La when tested at --
Pa.
b) For each door, leakage rate is < 0.01 La when pressurized to ->Pa.
- e. The provision of SR 3.0.2 do not apply to the test frequencies specified in 66 the Containment Leakage Rate Testing Program, with the exception of the containment ventilation isolation valves.
- f. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
(continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-27 Amendment No.-R&-
to TXX-06191 Page 3 of 3 INSERT I FOR TECHINCAL SPECIFICATIONS PAGE 5.0-27 exceptions:
- 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.
- 2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWE, except where relief has been authorized by the NRC.
to TXX-06191 Page 1 of3 ATTACHMENT 3 to TXX-06191 PROPOSED TECHNICAL SPECIFICATIONS BASES CHANGES (Markup For Information Only)
Pages B 3.6-4 to TXX-06191 Page 2 of 3 Containment B 3.6.1 BASES ACTIONS B.1 and B.2 (continued)
If containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.1.1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing ProgramsFailure to meet air lock and purge valve with resilient seal leakage limits specified in LCO 3.6.2 j
.. A '" 7 and LCO 3.6.3 does not invalidate the acceptability of these overall leakage determinations unless their contribution to overall Type A, B, and C leakage causes that to exceed limits. As left leakage prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test is required to be < 0.6 La for combined Type B and C leakage, and < 0.75 La for overall Type A leakage. At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of < 1.0 La. At < 1.0 La the offsite dose consequences are bounded by the assumptions of the safety analysis. SR Frequencies are as required by the Containment Leakage Rate Testing Program. These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis.
REFERENCES 1. 10 CFR 50, Appendix J, Option B.
- 2. FSAR, Chapter 15.
- 3. FSAR, Section 6.2.
COMANCHE PEAK - UNITS 1 AND 2 B 3.6-4 Amendment No. -&ý to TXX-06191 Page 3 of 3 INSERT 2 FOR TECHINCAL SPECIFICATIONS BASES PAGE 3.6-4 The containment concrete visual examinations may be performed during either power operation, e.g., performed concurrently with other containment inspection-related activities, or during a maintenance or refueling outage. The visual examinations of the steel liner plate inside containment are performed during maintenance or refueling outages since this is the only time the liner plate is fully accessible.
to TXX-06191 Page 1 of 4 ATTACHMENT 4 to TXX-06191 RETYPED TECHNICAL SPECIFICATIONS PAGES Pages 5.0-27 5.0-28 5.0-28a to TXX-06191 Page 2 of 4 Programs and Manuals 5.5 5.5 Programs and Manuals (continued) 5.5.16. Containment Leakage Rate Testing Program
- a. A program shall be established to implement the leakage rate testing of the containment as required by 10 CFR 50.54(o) and 10 CFR 50, Appendix J, Option B, as modified by approved exemptions. This program shall be in accordance with the guidelines contained in Regulatory Guide 1.163, "Performance-Based Containment Leak-Test Program, dated September, 1995" as modified by the following exceptions:
- 1. The visual examination of containment concrete surfaces intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B testing, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWL, except where relief has been authorized by the NRC.
- 2. The visual examination of the steel liner plate inside containment intended to fulfill the requirements of 10 CFR 50, Appendix J, Option B, will be performed in accordance with the requirements of and frequency specified by the ASME Section XI Code, Subsection IWE, except where relief has been authorized by the NRC.
- 3. NEI 94 1995, Section 9.2.3: The first Type A Test performed after the December 7, 1993 Type A Test (Unit 1) and the December 1, 1997 Type A Test (Unit 2) shall be performed no later than December 15, 2008 (Unit 1) and December 9, 2012 (Unit 2)."
- b. The peak calculated containment internal pressure for the design basis loss of coolant accident, Pa, is 48.3 psig.
- c. The maximum allowable containment leakage rate, La, at Pa, shall be 0.10% of containment air weight per day.
- d. Leakage rate acceptance criteria are:
- 1. Containment leakage rate acceptance criteria is - 1.0 La. During the first unit startup following testing in accordance with this program, the leakage rate acceptance criteria are < 0.60 La for the Type B and Type C tests and :- 0.75 La for Type A tests; (continued)
COMANCHE PEAK - UNITS 1 AND 2 5.0-27 Amendment No. 99, to TXX-06191 Page 3 of 4 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.16. Containment Leakage Rate Testing Program (continued)
- 2. Air lock testing acceptance criteria are:
a) Overall air lock leakage rate is S 0.05 La when tested at Z:
Pa.
b) For each door, leakage rate is < 0.01 La when pressurized to ->Pa.
- e. The provision of SR 3.0.2 do not apply to the test frequencies specified in the Containment Leakage Rate Testing Program, with the exception of the containment ventilation isolation valves.
- f. The provisions of SR 3.0.3 are applicable to the Containment Leakage Rate Testing Program.
5.5.17 Technical Requirements Manual (TRM)
The TRM contains selected requirements which do not meet the criteria for inclusion in the Technical Specification but are important to the operation of CPSES. Much of the information in the TRM was relocated from the TS.
Changes to the TRM shall be made under appropriate administrative controls and reviews. Changes may be made to the TRM without prior NRC approval provided the changes do not require either a change to the TS or NRC approval pursuant to 10 CFR 50.59. TRM changes require approval of the Plant Manager*.
5.5.18 Configuration Risk Management Program (CRMP)
The Configuration Risk Management Program (CRMP) provides a proceduralized risk-informed assessment to manage the risk associated with equipment inoperability. The program applies to technical specification structures, systems, or components for which a risk-informed Completion Time has been granted. The program shall include the following elements:
- a. Provisions for the control and implementation of a Level 1, at-power, internal events PRA-informed methodology. The assessment shall be capable of evaluating the applicable plant configuration.
(continued)
Duties may be performed by the Vice President of Nuclear Operations if that organizational position is assigned.
COMANCHE PEAK - UNITS 1 AND 2 5.0-28 Amendment No. 84, to TXX-06191 Page 4 of 4 Programs and Manuals 5.5 5.5 Programs and Manuals 5.5.18 Configuration Risk Management Program (CRMP) (continued)
- b. Provisions for performing an assessment prior to entering the LCO Action for preplanned activities.
- c. Provisions for performing an assessment after entering the LCO Action for unplanned entry into the LCO Action.
- d. Provisions for assessing the need for additional actions after the discovery of additional equipment out of service conditions while in the LCO Action.
- e. Provisions for considering other applicable risk significant contributors such as Level 2 issues, and external events, qualitatively or quantitatively.
5.5.19 Battery Monitoring and Maintenance Program This Program provides for restoration and maintenance, based on the recommendations of IEEE Standard 450, "IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications," or of the battery manufacturer for the following:
- a. Actions to restore battery cells with float voltage < 2.13 V, and
- b. Actions to equalize and test battery cells that had been discovered with electrolyte level below the top of the plates.
COMANCHE PEAK - UNITS 1 AND 2 5.0-28a Amendment No. 4-4-3, to TXX-06191 Page 1 of 2 ATTACHMENT 5 to TXX-06191 RETYPED TECHNICAL SPECIFICATIONS BASES PAGES Pages B 3.6-4 to TXX-06191 Page 2 of 2 Containment B 3.6.1 BASES ACTIONS B.1 and B.2 (continued)
If containment cannot be restored to OPERABLE status within the required Completion Time, the plant must be brought to a MODE in which the LCO does not apply. To achieve this status, the plant must be brought to at least MODE 3 within 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> and to MODE 5 within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br />. The allowed Completion Times are reasonable, based on operating experience, to reach the required plant conditions from full power conditions in an orderly manner and without challenging plant systems.
SURVEILLANCE SR 3.6.1.1 REQUIREMENTS Maintaining the containment OPERABLE requires compliance with the visual examinations and leakage rate test requirements of the Containment Leakage Rate Testing Program. The containment concrete visual examinations may be performed during either power operation, e.g., performed concurrently with other containment inspection-related activities, or during a maintenance or refueling outage. The visual examinations of the steel liner plate inside containment are performed during maintenance or refueling outages since this is the only time the liner plate is fully accessible. Failure to meet air lock and purge valve with resilient seal leakage limits specified in LCO 3.6.2 and LCO 3.6.3 does not invalidate the acceptability of these overall leakage determinations unless their contribution to overall Type A, B, and C leakage causes that to exceed limits. As left leakage prior to the first startup after performing a required Containment Leakage Rate Testing Program leakage test is required to be < 0.6 La for combined Type B and C leakage, and < 0.75 La for overall Type A leakage. At all other times between required leakage rate tests, the acceptance criteria is based on an overall Type A leakage limit of < 1.0 La. At -<1.0 La the offsite dose consequences are bounded by the assumptions of the safety analysis.
SR Frequencies are as required by the Containment Leakage Rate Testing Program. These periodic testing requirements verify that the containment leakage rate does not exceed the leakage rate assumed in the safety analysis.
REFERENCES 1. 10 CFR 50, Appendix J, Option B.
- 2. FSAR, Chapter 15.
- 3. FSAR, Section 6.2.
COMANCHE PEAK - UNITS 1 AND 2 B 3.6-4 Revision