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MONTHYEARCP-201000890, Relief Request No. C-7 for the 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-7 for the Second 10 Year ISI Interval from 10 CFR 50.55a Inspection Requirements Due to Physical Interferences (Second Interval Start Date: August 13, 2000) Project stage: Request 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) Project stage: Request ML1101403932011-01-14014 January 2011 Acceptance Review Email for Relief Request (RR) C-7 for Containment Spray Heat Exchanger and RR C-6 for Excess Letdown Heat Exchanger, Second 10-Year Inservice Inspection Interval Project stage: Acceptance Review ML1109606982011-04-0606 April 2011 Email, Request for Additional Information, Relief Request (RR) C-6 & C-7 for Containment Spray Heat Exchanger and RR C-6 for Excess Letdown Heat Exchanger, Second 10-Year Inservice Inspection Interval Project stage: RAI CP-201100609, Response to Request for Additional Information, Relief Request No. C-6 and C-72011-04-21021 April 2011 Response to Request for Additional Information, Relief Request No. C-6 and C-7 Project stage: Response to RAI ML1121403322011-09-0202 September 2011 Relief Request C-7 for Containment Spray Heat Exchanger and RR C-6 for Excess Letdown Heat Exchanger, Second 10-Year Inservice Inspection Interval Project stage: Other 2011-04-21
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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:CP
MONTHYEARCP-202400030, License Renewal Application Revision 0 - Supplement 3, Revision 12024-01-31031 January 2024 License Renewal Application Revision 0 - Supplement 3, Revision 1 CP-202400034, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1)2024-01-29029 January 2024 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 1) CP-202300575, (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 22023-12-13013 December 2023 (Cpnpp), License Amendment Request to Adopt 10 CFR 50.69, Risk-Informed Categorization and Treatment of Structures, Systems and Components for Nuclear Power Reactors Supplement 2 CP-202300566, (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation2023-12-12012 December 2023 (Cpnpp), Special Report 1-SR-23-001-00, Inoperable Post Accident Monitoring Instrumentation CP-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-202300416, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-10-12012 October 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300432, Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 42023-10-0404 October 2023 Response to Request for Additional Information Regarding the Safety Review of the License Renewal Application - Set 4 CP-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-202300391, (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule2023-08-24024 August 2023 (CPNPP) - Request for Exemption from 10 CFR 50.71(e)(4) Final Safety Analysis Update Schedule 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-202300361, (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report2023-08-17017 August 2023 (CPNPP) - Unit 2 Refueling Outage 20 (2RF20) Steam Generator 180 Day Report CP-202300401, 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 0182023-08-15015 August 2023 10CFR50.59 Evaluation Summary Report 024, 10CFR72.48 Evaluation Summary Report 009, and Commitment Material Change Evaluation Report 018 CP-202300358, (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 1122023-08-0101 August 2023 (Cpnpp), Transmittal of Electronic Licensing Basis Documents Including Certified FSAR Amendment 112 CP-202300322, Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 32023-07-27027 July 2023 Response to Requests for Additional Information Regarding Review of the License Renewal Application Sets 2 and 3 CP-202300348, (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48)2023-07-18018 July 2023 (Cpnpp), Transmittal of Revised Emergency Plan (Revision 48) CP-202300285, Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 12023-07-12012 July 2023 Response to Request for Additional Information Regarding Review of the License Renewal Application - Set 1 CP-202300262, Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 22023-06-20020 June 2023 Response to Request for Confirmation of Information Regarding Review of the License Renewal Application - Set 2 CP-202300263, Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements2023-06-15015 June 2023 Supplemental Information to Facilitate Acceptance of Licensee Amendment Request 23-002, Application Regarding GDC-5 Shared System Requirements CP-202300248, Response to Request for Additional Information Regarding License Renewal Application - Set 12023-06-13013 June 2023 Response to Request for Additional Information Regarding License Renewal Application - Set 1 CP-202300209, Response to Request for Additional Information - License Renewal Application Environmental Review2023-06-0606 June 2023 Response to Request for Additional Information - License Renewal Application Environmental Review CP-202300207, Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-052023-05-25025 May 2023 Revision to Comanche Peak Nuclear Power Plant'S Response to Notice of Violation (NOV) 05000445/2021011-05 CP-202300182, Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application2023-05-0808 May 2023 Response to Requests for Confirmation of Information Regarding the Environmental Review of the License Renewal Application CP-202300201, (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0)2023-05-0404 May 2023 (CPNPP) - Core Operating Limits Report (Colr), Unit 2 Cycle 21, (ERX-23-001, Revision 0) CP-202300160, (Cpnpp), 2022 Annual Radiological Environmental Operating Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Environmental Operating Report CP-202300159, (Cpnpp), 2022 Annual Radiological Effluent Release Report2023-04-27027 April 2023 (Cpnpp), 2022 Annual Radiological Effluent Release Report CP-202300165, License Renewal Application Revision 0 - Supplement 22023-04-24024 April 2023 License Renewal Application Revision 0 - Supplement 2 CP-202300175, Submittal of 2022 Annual Environmental Operating Report (Non-Radiological)2023-04-20020 April 2023 Submittal of 2022 Annual Environmental Operating Report (Non-Radiological) CP-202300181, ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments2023-04-20020 April 2023 ISFSI, Beaver Valley, Units 1 and 2, ISFSI, Davis-Besse, Unit 1, ISFSI, Perry, Unit 1, ISFSI, Corrected Affidavit for Application for Order Consenting to Transfer of Licenses and Conforming License Amendments 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-202300144, (CPNPP) - Decommissioning Report2023-03-30030 March 2023 (CPNPP) - Decommissioning Report CP-202300139, (CPNPP) - Property Damage Insurance2023-03-30030 March 2023 (CPNPP) - Property Damage Insurance CP-202300098, (Cpnpp), Annual Report of Changes in Peak Cladding Temperature2023-03-16016 March 2023 (Cpnpp), Annual Report of Changes in Peak Cladding Temperature CP-202200481, Response to Request for Additional Information - Relief Request Application P-1, Inservice Testing (IST)2022-12-0707 December 2022 Response to Request for Additional Information - Relief Request Application P-1, Inservice Testing (IST) CP-202200454, (Cpnpp), Reply to a Notice of Violation Transmitted Via NRC Letter from Gregory Werner to Ken Peters Dated 11/01/2022, Comanche Peak Nuclear Power Plant, Units 1 and 2 Integrated Inspection Report 05000445/2022003 .2022-12-0101 December 2022 (Cpnpp), Reply to a Notice of Violation Transmitted Via NRC Letter from Gregory Werner to Ken Peters Dated 11/01/2022, Comanche Peak Nuclear Power Plant, Units 1 and 2 Integrated Inspection Report 05000445/2022003 . 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-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-202200450, (CPNPP) - Registration of Dry Spent Fuel Storage Canisters2022-11-16016 November 2022 (CPNPP) - Registration of Dry Spent Fuel Storage Canisters CP-202200435, (Cpnpp), Registration of Dry Spent Fuel Storage Canisters2022-11-0808 November 2022 (Cpnpp), Registration of Dry Spent Fuel Storage Canisters 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-202200357, (CPNPP) Unit 2 - Response to Request for Additional Information, Fall 2021 (2RF19) Steam Generator Tube Inspection Report2022-09-14014 September 2022 (CPNPP) Unit 2 - Response to Request for Additional Information, Fall 2021 (2RF19) Steam Generator Tube Inspection Report CP-202200358, (CPNPP) - Transmittal of Revised Emergency Plan (Revision 46)2022-09-14014 September 2022 (CPNPP) - Transmittal of Revised Emergency Plan (Revision 46) CP-202200246, Evacuation Time Estimate Analysis2022-08-25025 August 2022 Evacuation Time Estimate Analysis 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-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-202200276, (CPNPP) - Relief Request Application P-1, Inservice Testing (IST)2022-07-20020 July 2022 (CPNPP) - Relief Request Application P-1, Inservice Testing (IST) CP-202200247, (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 0172022-06-30030 June 2022 (CPNPP) - 10CFR50.59 Evaluation Summary Report 023, 10CFR72.48 Evaluation Summary Report 008 and Commitment Material Change Evaluation Report 017 2024-01-31
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Rafael Flores Luminant Power Senior Vice President P 0 Box 1002 011 & Chief Nuclear Officer 6322 North FM 56 rafael.flores@Luminant.com Glen Rose, TX 76043 Luminant 2548975550 C 817 559 0403 F 254 897 6652 CP-201000889 Ref. # 10 CFR'50.55a(g)(5)(iii)
Log # TXX-10091 December 15, 2010 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NO. 50-445 RELIEF REQUEST NO. C-6 FOR THE 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)
Dear Sir or Madam:
Pursuant to 10 CFR 50.55a(g)(5)(iii), Luminant Generation Company, LLC (Luminant Power) is submitting Relief Request C-6 (see attachment) for Comanche Peak Unit 1 for the second ten year inservice inspection interval. Luminant Power has determined that certain inspection requirements of ASME Section XI are impractical due to physical interferences.
The geometry of the excess letdown heat exchanger makes the Code required examination coverage requirements impractical. Ultrasonic Testing (UT) of the subject weld was performed during the second interval to the maximum extent practical based on design configuration restrictions. Pressure test VT-2 visual examinations were also performed with no evidence of leakage identified for the subject component. No undue risk to the public health and safety is presented by this request.
This communication contains no new licensing basis commitments regarding Comanche Peak Unit 1.
Should you have any questions, please contact Mr. Jack Hicks at (254)897-6725.
Sincerely, Luminant Generation Company LLC Rafael Flores By:
BFred W. Madden Director, Oversight & Regulatory Affairs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak
- Diablo Canyon- PaloVerde. San Onofre. South Texas Project Wolf Creek
U. S. Nuclear Regulatory Commission TXX-10091 Page 2 12/15/2010 Attachments - 1. Relief Request C-6 for Unit 1 Relief Request for Weld Examination Coverage for the Excess Letdown Heat Exchanger
- 2. Drawing and Inspection Sheets for Excess Letdown Heat Exchanger c- E. E. Collins, Region IV B. K. Singal, NRR Resident Inspectors, Comanche Peak Brian Welch, ANII, Comanche Peak Anthony Jones, TDLR to TXX- 10091 Page 1 of 3 10CFR 50.55a Request Number C-6 Relief Requested In Accordance with 10CFR50.55a(g)(5)(iii)
- Inservice Inspection Impracticality -
- 1. ASME Code Component Affected:
Class 2 Excess Letdown Heat Exchanger (TBX-CSAHEL-01) Head Circumferential Weld Code Cat / Item No. Description Weld No.
C-A / C1.20 Excess Letdown HX Head to Flange Weld TBX-2-1 110-1
2. Applicable Code Edition and Addenda
The applicable ASME Boiler and Pressure Vessel Code (hereafter referred to as the "Code") edition and addenda is ASME Section XI, "Rules for Inservice Inspection of Nuclear Power Plant Components," 1998 Edition through 2000 Addenda.
3. Applicable Code Requirement
ASME Section XI, Figure IWC-2500-1 (a) 1998 Edition through 2000 Addenda, requires a minimum volumetric examination of the weld volume extending 1/2" into the base metal on the vessel and flange sides for the head circumferential weld (Code Item C1.20).
Comanche Peak Nuclear Power Plant (CPNPP) second ten-year interval Inservice Inspection Program Plan also implements Code Case N-460, which is endorsed by the NRC in revision 15 of Regulatory Guide 1.147, "Inservice Inspection Code Case Acceptability ASME Section XI, Division 1." Code Case N-460 states, in part, whe'n the entire examination volume or area cannot be examined due to interference by another component or part geometry, a reduction in examination coverage on any Class 1 or Class 2 weld may be accepted, provided the reduction coverage for that weld is less than 10 percent.
NRC Information Notice (IN) 98-42, "Implementation of 10CFR50.55a(g) Inservice Inspection Requirements," termed a reduction in coverage of less than 10 percent to be "essentiallyýi 00 percent." IN 98-42 states, in part, "The NRC has adopted and further refined the definition of "essentially 100 percent" to mean "greater than 90 percent"... has been applied to all examinations of welds or other areas required by ASME Section XI."
to TXX-10091 Page 2 of 3 10CFR50.55a Request Number C-6
- 4. Impracticality of Compliance:
The examination of the subject component weld is limited by the configuration of the flange design and the location of two-four inch and two-three inch nozzles on the tube side of the heat exchanger. As shown on the Attachment 2, the proximity of the nozzles limits the perpendicular scans on the tube side. Parallel scans were limited on the flange side of the weld. This yields a composite coverage of 50% of the required examination volume.
The examinations were conducted in accordance with procedure TX-ISI-214,"Ultrasonic Examination Procedure for Welds in Piping Systems and Vessels." Straight beam (00) and angle beams (450 shear and 600 longitudinal) scans were used to achieve the weld volume obtained.
- 5. Burden caused by Compliance:
The design configuration restrictions of the of the subject component makes the Code required examination coverage requirements for the weld volume impractical. Plant modifications or replacements of components designed to allow for complete would be needed to meet the Code requirements. This would cause considerable burden to CPNPP.
- 6. Proposed Alternative and Basis for Use:
Proposed Alternative:
The following alternatives are proposed in lieu of the required examination coverage of essentially 100 percent:
- 1. Ultrasonic testing (UT) of the subject component weld was performed to the maximum extent practical during the second ten-year interval.
- 2. Pressure test VT-2 visual examinations were performed, as required by Code Category C-H, during the second ten-year interval. No evidence of leakage was identified for this component.
Basis for use: .
The basis for use of this alternative is that it provides the best examination coverage practical within the limitations of the current configuration. Based on the percentage of the examination volume completed and the lack of any indications identified, there is a high level of confidence in the continued structural integrity of the weld. CPNPP believes that there is no undue risk to the public health and safety presented by this request.
to TXX-10091 Page 3 of 3 10CFR50.55a Request Number C-6
- 7. Duration of Proposed Alternative:
The second ten-year ISI interval for Unit 1 began on August 13, 2000 and ended on August 12, 2010.
- 8. Precedents:
Relief Request C-9 was submitted in letter TXX-98170 from CPNPP to USNRC in July 22, 1998 for the first ten-year interval for Unit 1.
PDI Calibration Data Sheet CD 0)
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.~CP Plant / Unit COMANCHE PEAK UNIT I Data Sheet # 13 UT-23 so 80 Company WESDYNE Page I of <_ C)
Comp / System CHEM. & VOL. CONTROL 60 60 Procedure No. TX-ISI-214 Cal. Checks Time (0 Rev / Chng. No. 4/NA Initial Calib. 0900 40 0 2 4 6T 40 Cal. Block No. TBX-8 Initial Calib. Date 10/3/08 Cal. Block Temp 880 Comp. Temp 770 Intermediate N/A 20 20 Therm S/N: TU-2367 Intermediate NIA Size 8" Sch. 140/ .812 "T" Final Calib. 1120 W* Ferritic FiXlAustenitic Final Calib. Date 10/3/08 0 2 .4 6 a 2 4 6 a 10 CRT Div. 2.5" 10 CRT Div. =
Cal. Direction: X Axial Circ. Both Couplant Scan Area: _ to Weld Type: ULTRA GEL I1 Search Unit #1 Manufacturer:Search Unit #2 to Weld Batch: 06225 Manufacturer: KBA Serial No.: 01BXY3 Freq.: 2.25 MHz Serial No.: Freq.:
Recordable Size: .5" Shape: ROUND Size: Shape:
Access __Indications Exam Sens. Exam Angle: 00 Model: GAMMA Exam Angle: Model:
Examination Area / Weld Yes No Geom Measured Angle: 00 Measured Angle:
TBX-2-1110 1 CAP -SIDE _ 14.5 dB Wedge Style: N/A Wedge Style: N Search Unit Cable Search Unit C61e RG 174 Type:/
Type:
Remarks / Reason for Incomplete Scan(s) Length: 12' No. of Connectors: 0 Length: No. of onnectors:
Instrument Settings / Instrumen Settings 50% NOT EXAMINED Make / Model: KBA/USN 52R Make / Model:
Serial No.: SAP 101866 Serial No.: SAP SEE PREVIOUS DATA Dis.Delay: 0.000 ps Range: 2.5" Dis.Delay: / s Range:
Prb.Delay: 0.000 ps Pwidth: N/A Prb.Delay: s Pwidth:
M'tl Cal/Vel: .2256 ps Pulser: N/A M'tl Cal/Vel: s Pulser:
Damping: 1000 Q Reject: 0% Damping: 0 Reject:
Rep. Rate: AUTOHIGH Freq.: 2-8 MHz Rep. Rate. AUTOHIGH Freq.:
Filter: N/A Mode: FIXED Filter: / _" _ Mode:
Voltage: N/A Rectify: FULLWAVE Voltag: ' Rectify: FULLWAVE Examiner: JOE FUNYAK Level II Date 10/3/08 Reference Sensitivity (Sens.) Ref ence Sensitivity (Sens.)
Axial: 14.5 dB Circ: N//A Ax 'l: Circ:
Examiner: N/A Level N/A Date N/A SDH Sensitivity: N/A H Sensitivity:
Further Evaluation Required? E] Yes [] No Reviewer!I Date ICIe./'/OF Reviewer Date l FA $
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PDI Calibration Data Sheet C0 0)
CD Cn :3 Plant / Unit COMANCHE PEAK UNIT 1 Data Sheet # 13 UT-23-A 80 B0 Company WESDYNE Page 2 of e 0 60 Comp / System CHEM. & VOL. CONTROL C)
Procedure No. TX-ISI-214 Cal. Checks Time 0R Rev/ Chng. No. 4/NA Initial Calib. 0910 40 40 Cal. Block No. TBX-8 Initial Calib. Date 1013/08 Cal. Block Temp 85' Comp. Temp 770 Intermediate N/A 20 20 Therm S/N: TU-2367 Intermediate N/A Size 8" Sch. 140/ .812 "T" Final Calib. 1115 D- Ferritic F--]Austenitic Final Calib. Date 10/3/08 0 2 10 CRT Div.
4 6 3.5" 8 0 2 10 CRT Div.
4 6 8 Cal. Direction: Axial Circ. X Both Coupiant
/
Scan Area: -L to Weld Type: ULTRA GEL II Search Unit #1
=]to Weld Batch: 06225 Manufacturer: KBA Manufacturer:
Serial No.: 0096VP Freq.: 1.5 MHz Serial No.: _
Recordable Size: 5375" Shape: ROUND Size: Shape:
Access Indications Exam Sens. Exam Angle: 450 Model: COMP-G Exam Angle: Model:
Examination Area / Weld Yes No Geom Measured Angle: 450 Measured Angle:
TBX-2-1 110 1 CAP -SIDE X 35.3/40.6 dB Wedge Style: NON INTEGRAL Wedge Style: _
Search Unit Cable Search Unit CQ Type: RG 174 Type:
Length: 12" No. of Connectors: 0 Length:
Remarks / Reason for Incomplete Scan(s) Instrument Settings Instrumen Settin!
Model:
50% NOT EXAMINED Make / Model: KBA/USN 52R Make / I Serial No.: SAP 101866 Serial No.: / SAF SEE PREVIOUS DATA Dis.Delay: 0.000 ps Range: 3.50" Dis.Dela *y: ps Range Prb.Delay: 4.921 ps Pwidth: N/A Prb.Delz ay: / ps Pwidtv M'tl Cal/Vel: 1.253 ps Pulser: N/A M'tI Call VVel: s Pulser Damping: 1000 Q Reject: 0% Dampin( g: _ Q
.. Reject Rep. Rate: AUTOHIGH Freq.: 2-8 MHz Rep. Ra te .AUTOHIGH Freq.:
Filter: N/A Mode: FIXED Filter: / __-Mode:
Voltage: N/A Rectify: FULLWAVE Volta Rectifý Examiner: JOE FUNYAK Level II Date 10/3/08 Reference Sensitivity (Sens.) Ref enlce Sensitivity (Sens.)
Examiner:
Reviewer/Oate Reviewer I Dare ~
NIA Level
/a~/.,4 10Z':
/~ 1~ F N/A Date N/A Axial:
SDH Sensitivity:
25.3 dB Further Evaluation Required?
ReviewerlDate R-lewer I Dale Circ:
N/A Fl Yes 30.6 dB
£*. No
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Ax* :
Ii H Se nsitivity:t
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PDI Calibration Data Sheet CD 0 0 -CD Plant / Unit COMANCHE PEAK UNIT 1 Data Sheet# 13 UT-23-B 80 Company WESDYNE Page of -S 0 Comp / System CHEM. & VOL. CONTROL 60 Procedure No. TX-ISI-214 Cal. Checks Time C)
C0 Rev / Chng. No. 4/NA Initial Calib. 0920 40 Cal. Block No. TBX-8 Initial Calib. Date 10/3/08 Cal. Block Temp 850 Comp. Temp 77° Intermediate N/A 20 Therm SIN: TU-2367 Intermediate N/A I Size 8"' Sch. 140/.812 "T" Final Calib.
Final Calib. Date 1112 10/3/08 0 I
2
-I Li 6
[-] Ferritic F-]Austenitic 0 2 4 6 8 4 8 10 CRT Div.= 2.903" 10 CRT Div. =
Cal. Direction: X Axial Circ. Both Couplant Scan Area: - to Weld Type: ULTRA GEL II Search Unit #1 Search Unit #2 Manufacturer:" //
= to Weld Batch: 06225 Manufacturer: RTD Serial No.: 08-374 Freq.: 2.0 MHz Serial No.: Freq.:_/
Size: 2 (7X10) Shape: RECT. Size: - Sh-ape:
Exam Sens. Exam Angle: 600 Model: TRLA Exam Angle: Model:
Measured Angle: 600 Measured Angle:
73.1 dB Wedge Style: INTEGRAL Wedge Style: NA Search Unit Cable Search Unit CilAe Type: RG 174 Type:
Length: 12" No. of Connectors: 0 Length: No. of onnectors:
Instrument Settings *InstrumenISettings 50% r*4OT EXAMINED Make / Model: KBAIUSN 52R Make / Model.:
Serial No.: SAP 101866 Serial No.: SAP SEE PREVIOUS DATA Dis.Delay: 0.000 ps Range: 2.903" Dis.Delay: s Range:
ID ROLL AT 30% SCREEN HEIGHT AT REF. dB Prb.Delay: 7.78 ps Pwidth: N/A Prb.Delay: s Pwidth:
M'tl Cal/Veh .2306 ps Pulser: N/A M'tl CalNel: s Pulser:
Damping: 1000 Q) Reject: 0% Damping: 0) Reject:
Rep. Rate: AUTOHIGH Freq.: 2-8 MHz Rep. Rate. AUTOHIGH Freq.:
Filter: . __"-- - Mode:
Filter: N/A Mode: FIXED Voltage: N/A Rectify: FULLWAVE Volta : _-- - Rectify: FULLWAVE Examiner: JOE FUNYAK Level 11 Da te 10/3/08 Reference Sensitivity (Sens.) Ref ence Sensitivity (Sens.)
Axial: 73.1 dB Circ: N/A Ax' : _Circ:
Examiner: N/A Level N/A Da te N/A SDH Sensitivity: N/A H Sensitivity:-
Further Evaluation Required? E] Yes .X No Reviewer IDate
-, Dale o.,.
Reviewer.,
Ii.~
to TXX-10091 Page 4 of 5 i WESTINGHOUSE NUCLEAR SERVICES DIVISION REPORT NO. UT-98-129 INSPECTION SERVICES PAGE OF 3 PROFILE OF THE EMAMINATION V Eý,ý y 5-PLANT Comanche Peak UNIT I SKETCH TBX-2-1110 Rev, 1 SYST/COMP CHEMICAL & VOLUME CONTROL PROCEDURE TX4SI-214 Rev. 2 FC N/A EXAMINER Morini, George LEVEL II DATE 4110198 EXAMINER NIA LEVEL NIA DATE COMPONENT ID TBX-2-1110-1 COMMENTSISKETCH/DETAILS
(,6'LI S-TDE S F) A j C, D:C)9P
.. 0 0 Iroj I.
TU ELECTRIC REVIEW I DATE DeBonis, John to TXX-10091 Page 5 of 5 m.m REPORT NO. 'UT-98-129
- - WESTINGHOUSE NUCLEAR SERVICES DIVISION *PAGE ..- OF .
~ oe 4 LIMITATION TO EXAMINATION PLANT Conaanche Peak UNIT 1 SKETCH TBX-2-111O Rev. 1 SYST/COMP CHE* AICAL & VOLU ME CONTROL PROCEDURE TX-tSI-214 Rev. 2 FC NfA EXAMINER Mort ni, George , LEVEL I1 DATE 4t198 EXAMINER - N/A LEVEL NIA DATE COMPONENT ID TBX-2-1110.1 RELATED TO Q MT Q PT UT 0 VT PROVIDE SUFFICIENT INFORMATION TO DESCRIBE SIZE, LOCATION AND TYPE OF LIMITATION.
COMMENTS/SKETCHIDETAILS Four nozzles located as shown below. Two 3- nozzles and two 4' nozzles on side 2. 50% not examined.
4
+/-
T S%' 0.15 TU ELECTRIC REVIEW I DATE TU ELECTRIC LEVEL IIIREVEW / DATE ANII REVIEW I DATE DeBonis, John R a /alt, Joe-C. li, if.j
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