Letter Sequence Meeting |
---|
|
|
MONTHYEARML1122119682011-08-26026 August 2011 Notice of Meeting with Luminant Generation Company LLC to Discuss Comanche Peak, Units 1 and 2, Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative 8a Project stage: Meeting ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... Project stage: Meeting ML1125904822011-10-14014 October 2011 Summary of Meeting with Luminant to Discuss Comanche Peak, Units 1 and 2, Proposed Request to Adopt Risk-Informed Technical Specification Task Force Initiative 8a, Relocate LCOs for RPS and ESFAS Instrumentation to Licensee Control Project stage: Meeting 2011-08-26
[Table View] |
|
---|
Category:Meeting Briefing Package/Handouts
MONTHYEARML23215A1922023-08-0707 August 2023 – August 7, 2023 Presubmittal Meeting Presentation - Relocation of Technical Specification 3.9.3 Nuclear Instrumentation to a Licensee Controlled Document (EPID: L?2023?LRM-0052) ML23215A1652023-08-0404 August 2023 – August 8, 2023 Presubmittal Meeting Presentation - Technical Specification 3.8.1 AC Sources - Operating Required Action B.4, 14-hour Completion Time (EPID: L?2023?LRM-0053) ML23094A2722023-04-0606 April 2023 – April 6, 2023 Presubmittal Meeting Presentation - Extension Request for Thermal Relief Valves (EPID: L?2023?LRM-0023) ML23081A0252023-03-22022 March 2023 – March 28, 2023 Pre-submittal Meeting Presentation - LAR for Exception to RG 1.81 (EPID L?2023?LRM-0015) ML23045A1552023-02-14014 February 2023 Public Meeting February 23, 2023 - Presentation Slides ML23011A0872023-01-10010 January 2023 License Renewal Scoping Meeting, Comanche Peak Nuclear Power Plant, Units 1 and 2 - Meeting Slides ML22140A1082022-05-31031 May 2022 (CPNPP) First License Renewal (60 Years) Application Pre-Application Submittal Meeting 2, Meeting Slides ML21259A0312021-09-30030 September 2021 Initial License Renewal Pre-Application Submittal Meeting Sept 2021 - Safety ML21259A0292021-09-16016 September 2021 Initial License Renewal - NRC Presubmittal Meeting Slides - Safety ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report ML21259A0332021-09-16016 September 2021 Initial License Renewal Application - NRC Presubmittal Meeting Slides - Environmental ML21097A0522021-04-0707 April 2021 NRC Talking Points - 4/7/2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for Comanche Peak ML21068A0292021-03-0909 March 2021 Presentation - 3/24/2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21007A2562021-01-12012 January 2021 Luminant-CPNPP License Renewal SAMA January 12 2021 Public Mtg ML20314A3422020-11-12012 November 2020 NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating ML20097B2852020-04-0606 April 2020 April 7, 2020, Presubmittal Teleconference Discussion Topics - Proposed Relief Requests for Deferral of Several Inspections and Tests from 2RF18 (Spring 2020) to 2RF19 (Fall 2021) ML20097C2662020-04-0606 April 2020 April 6, 2020, Presubmittal Teleconference Presentation - License Amendment Request Revise Technical Specification 5.5.9 ML20036D4102020-02-12012 February 2020 Pre-Submittal Meeting for: Comanche Peak Nuclear Power Plant Docket Nos. 50-445 and 50-446 February 12, 2020 - License Amendment Request for Changes to Certain Emergency Action Levels ML19296D5592019-10-24024 October 2019 Pre-Submittal Meeting with NRC for Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources - Operating, Presentation ML14077A2872014-03-18018 March 2014 Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317 ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, ML12328A1252012-11-20020 November 2012 Licensee Slides from 11/20/12 Pre-Submittal Meeting to Discuss LAR for Spent Fuel Criticality ML12229A5042012-09-19019 September 2012 8/6/2012 Summary of Conference Call with Luminant to Discuss Proposed License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 ML12236A3322012-08-23023 August 2012 Non-proprietary - Presentation for September 13, 2012, Proposed License Amendment Request for Spend Fuel Pool Criticality Analysis ML12188A6972012-07-18018 July 2012 6/26/12 Summary of Meeting with Luminant Generation Company LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME8 ML12156A2052012-05-31031 May 2012 Presentation to NRC for LAR 12 ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... ML1114003142011-05-19019 May 2011 Summary of Public Meeting with Luminant Generation Company on Comanche Peak Nuclear Power Plant, Units 1 and 2, to Discuss 2010 End of Cycle Performance Assessment ML0924401642009-09-14014 September 2009 Meeting Summary, Pre-Application Meeting on with Luminant Generation Company LLC to Dicuss Future Amendment Request to Revise Comanche Peak Units 1 and 2 Startup Transformer Completion Times ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues ML0919402772009-07-0909 July 2009 Luminant Holistic Overview: Presentation Will Cover Information Related to RAIs 1 - 5, 7, 12 - 14,16 - 19, 21, 25 - 36 and Overall Response to GL 2004-02 ML0919400832009-07-0909 July 2009 Pci RAI 8, Test Protocol, Erosion Issue, RAI 15, Test Protocol, Latent Fiber Issue, Areva RAI 20, Test Flume, Fiberglass Larges Question ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing ML0828204232008-10-0707 October 2008 Meeting Handout - Comanche Peak Col Application Public Orientation Meeting ML0817100272008-06-12012 June 2008 Second Handout for Comanche Peak Public Outreach Meeting on June 12, 2008 ML0816201432008-06-10010 June 2008 End-of-Cycle Meeting Summary 6/5/08 ML0729204682007-10-29029 October 2007 09/25/2007, Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and Strategic Teaming and Resource Sharing Representatives to Discuss License Renewal Activities ML0717200702007-06-20020 June 2007 Summary of Meeting with Txu Power Regarding Comanche Peak Steam Electric Stations End-of-Cycle Assessment for 2006 ML0720101702007-05-23023 May 2007 Enclosure 3 - 5/23/07 P.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0720101742007-05-23023 May 2007 Enclosure 2 - 5/23/07 A.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0707202502006-12-12012 December 2006 12/12-13/2006 Slides, Txu Power Comanche Peak Site, NRC Onsite Review, Site Geotechnical Investigation Activities. ML0435101002004-11-10010 November 2004 Meeting Slides - Nrc/Stars Plant Aging Management Center of Business Meeting ML0330402882003-10-30030 October 2003 Meeting Handout Materials Regarding STARS-IRAG/NRC Meeting to Discuss Topics Taken from the June 10.11, 2003, Workshop ML0324812782003-09-10010 September 2003 Agenda and Handout for Public Meeting Between NRC and Firstenergy Nuclear Operating Company Davis-Besse Nuclear Power Station ML0319206482003-06-10010 June 2003 Meeting Handouts for STARS-IRAG/NRC Workshop to Discuss Selected Topics Listed in the Agenda Attached to Meeting Notice ML0234504632002-12-10010 December 2002 05000445; Txu Energy, Comanche Peak, Public Exit Meeting - December 10, 2002-Licensee Handouts ML0231200242002-11-0707 November 2002 Meeting Handouts - Meeting with Strategic Teaming and Resources Sharing - Integrated Regulatory Affairs Group ML0208705662002-04-15015 April 2002 Meetingsummary with Stars and the NRC to Inform the NRC About Current Stars Activities ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary 2023-08-07
[Table view] Category:Meeting Agenda
MONTHYEARPMNS20241399, Meeting to Discuss the Nuclear Regulatory Commissions (NRC) 2023 Annual Assessment of Safety Performance at Comanche Peak Nuclear Power Plant2024-11-0505 November 2024 Meeting to Discuss the Nuclear Regulatory Commissions (NRC) 2023 Annual Assessment of Safety Performance at Comanche Peak Nuclear Power Plant PMNS20231415, Notice of Meeting for the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application2023-12-22022 December 2023 Notice of Meeting for the Comanche Peak Nuclear Power Plant Units 1 and 2 License Renewal Application ML23345A2122023-12-11011 December 2023 Environmental Meeting Related to the Comanche Peak Nuclear Power Plant Draft Supplemental Environmental Impact Statement, Units 1 and 2, License Renewal Application ML23340A0902023-12-0606 December 2023 Environmental Meeting Related to the Comanche Peak Nuclear Power Plant Draft Supplemental Environmental Impact Statement, Units 1 and 2, License Renewal Application ML23340A2282023-12-0606 December 2023 Environmental Meeting Related to the Comanche Peak Nuclear Power Plant Draft Supplemental Environmental Impact Statement, Units 1 and 2, License Renewal Application ML23313A0622023-11-0909 November 2023 Environmental Meeting Related to the Comanche Peak Nuclear Power Plant Draft Supplemental Environmental Impact Statement, Units 1 and 2, License Renewal Application ML23296A1232023-10-23023 October 2023 Environmental Meeting Related to the Comanche Peak Nuclear Power Plant Draft Supplemental Environmental Impact Statement, Units 1 and 2, License Renewal Application ML23215A1922023-08-0707 August 2023 – August 7, 2023 Presubmittal Meeting Presentation - Relocation of Technical Specification 3.9.3 Nuclear Instrumentation to a Licensee Controlled Document (EPID: L?2023?LRM-0052) PMNS20230867, Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Extend the Diesel Generator Allowed Outage Time from 3 Days to 14 Days at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 22023-07-26026 July 2023 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Extend the Diesel Generator Allowed Outage Time from 3 Days to 14 Days at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 PMNS20230863, Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Relocate Refueling Operations Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual2023-07-26026 July 2023 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Relocate Refueling Operations Technical Specification 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual PMNS20230624, Meeting to Discuss the Nuclear Regulatory Commissions (NRC) 2022 Annual Assessment of Safety Performance at Comanche Peak Nuclear Power Plant, Units 1 and 22023-05-12012 May 2023 Meeting to Discuss the Nuclear Regulatory Commissions (NRC) 2022 Annual Assessment of Safety Performance at Comanche Peak Nuclear Power Plant, Units 1 and 2 PMNS20230363, Meeting with Vistra Operations Company LLC Proposed Alternative for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, for Inservice Testing of Component Cooling Water Heat Exchanger Relief Valves2023-04-0606 April 2023 Meeting with Vistra Operations Company LLC Proposed Alternative for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, for Inservice Testing of Component Cooling Water Heat Exchanger Relief Valves ML23094A2722023-04-0606 April 2023 – April 6, 2023 Presubmittal Meeting Presentation - Extension Request for Thermal Relief Valves (EPID: L?2023?LRM-0023) PMNS20230232, Meeting with Vistra Operations Company LLC Proposed License Amendment Request for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, to Take Exception to Regulatory Guide 1.81, Revision 1, Position C.32023-03-0909 March 2023 Meeting with Vistra Operations Company LLC Proposed License Amendment Request for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2, to Take Exception to Regulatory Guide 1.81, Revision 1, Position C.3 PMNS20230133, Environmental Scoping Meeting Related to the Comanche Peak Nuclear Power Plant, Units 1 and 2, License Renewal Application2023-02-15015 February 2023 Environmental Scoping Meeting Related to the Comanche Peak Nuclear Power Plant, Units 1 and 2, License Renewal Application PMNS20221254, Environmental Scoping Meeting Related to the Comanche Peak Nuclear Power Plant, Units 1 and 2, License Renewal Application2023-01-0909 January 2023 Environmental Scoping Meeting Related to the Comanche Peak Nuclear Power Plant, Units 1 and 2, License Renewal Application ML22140A1082022-05-31031 May 2022 (CPNPP) First License Renewal (60 Years) Application Pre-Application Submittal Meeting 2, Meeting Slides PMNS20220522, Second Pre-Submittal Meeting for License Renewal Application for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP) - Safety2022-05-23023 May 2022 Second Pre-Submittal Meeting for License Renewal Application for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP) - Safety PMNS20220467, Public Webinar to Discuss the Nuclear Regulatory Commissions 2021 Annual Assessment of Safety Performance at Region IV Plants2022-05-0303 May 2022 Public Webinar to Discuss the Nuclear Regulatory Commissions 2021 Annual Assessment of Safety Performance at Region IV Plants ML21259A0312021-09-30030 September 2021 Initial License Renewal Pre-Application Submittal Meeting Sept 2021 - Safety ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report PMNS20211050, Pre-Submittal Meeting for License Renewal Application for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP) - Environmental2021-08-13013 August 2021 Pre-Submittal Meeting for License Renewal Application for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP) - Environmental PMNS20211053, Pre-Submittal Meeting for License Renewal Application for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP) - Safety2021-08-0909 August 2021 Pre-Submittal Meeting for License Renewal Application for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (CPNPP) - Safety PMNS20210563, Public Webinar to Discuss the NRCs 2020 Annual Assessment of Safety Performance at Arkansas Nuclear One, Columbia, Comanche Peak, Cooper, Diablo Canyon, Palo Verde, River Bend Station, South Texas Project, Waterford, and Wolf Creek2021-04-29029 April 2021 Public Webinar to Discuss the NRCs 2020 Annual Assessment of Safety Performance at Arkansas Nuclear One, Columbia, Comanche Peak, Cooper, Diablo Canyon, Palo Verde, River Bend Station, South Texas Project, Waterford, and Wolf Creek PMNS20210373, Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 22021-03-25025 March 2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for the Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 PMNS20210370, Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Biennial Emergency Planning Exercise for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 22021-03-25025 March 2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Biennial Emergency Planning Exercise for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 PMNS20210249, Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 22021-03-0909 March 2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21068A0292021-03-0909 March 2021 Presentation - 3/24/2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 PMNS20201387, Initial License Renewal pre-application Meeting2020-12-16016 December 2020 Initial License Renewal pre-application Meeting ML20314A3422020-11-12012 November 2020 NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating ML20302A2692020-10-28028 October 2020 Teleconference with Vistra Operations Company LLC Regarding a Proposed License Amendment Request to Make a One-Time TS Change to Replace a Station Service Water Pump at Comanche Peak Nuclear Power Plant, Unit No. 2 ML20170B1872020-06-19019 June 2020 Public Webinar to Discuss the Nrc'S Assessment of Safety Performance at Region IV Plants for 2019 ML15191A2512015-07-0909 July 2015 July 9, 2015 Public Meeting: Comanch Peak Pre- Application Meeting, Emergency Diesel Generator Voltage and Frequency Technical Specification Changes ML14043A2032014-02-19019 February 2014 Federal Register Notice Regarding the 612th ACRS Meeting, March 6-8, 2014 ML13045A4102013-02-15015 February 2013 2/28/13 Notice of Meeting Via Conference Call with Luminant to Discuss Generic Safety Issue 191, Assessment of Debris Accumulation on PWR (Pressurized-Water Reactor) Sump Performance, for Comanche Peak, Units 1 and 2 ML12328A1252012-11-20020 November 2012 Licensee Slides from 11/20/12 Pre-Submittal Meeting to Discuss LAR for Spent Fuel Criticality ML12306A3242012-11-0505 November 2012 Notice of Meeting with Luminant Generation Company LLC to Discuss Indirect License Transfers for Comanche Peak Nuclear Power Plant, Units 1 and 2 ML12299A4102012-11-0505 November 2012 Notice of Meeting with Luminant Generation Company, LLC, to Discuss Proposed License Request for Approval of Revised Spent Fuel Criticality Analysis to Update Comanche Peak, Units 1 and 2, Technical Specifications ML12286A2792012-10-18018 October 2012 Notice of Meeting with Luminant Generating Company LLC to Discuss Indirect License Transfers for Comanche Peak Nuclear Power Plant, Units 1 and 2 ML12216A2992012-08-27027 August 2012 9/13/12 Notice of Meeting with Luminant Generation Company LLC to Discuss Proposed License Request for Approval of Revised Spent Fuel Criticality Analysis to Update Comanche Peak, Units 1 and 2, Technical Specifications ML12191A1472012-07-11011 July 2012 8/6/12 Notice of Conference Call with Luminant to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME8615-ME8616) ML12159A1182012-06-11011 June 2012 Notice of 6/26/12 Meeting with Luminant Generation Company LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME86 ML12171A1842012-06-11011 June 2012 6/26/12 Revised Notice of Meeting with Luminant Generation Company, LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... ML1122119682011-08-26026 August 2011 Notice of Meeting with Luminant Generation Company LLC to Discuss Comanche Peak, Units 1 and 2, Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative 8a ML1107401282011-03-15015 March 2011 3/17/11 Notice of Forthcoming Closed Meeting with Luminant Generation Company Via Conference Call to Discuss Generic Request for Additional Information Pertaining to Its Cyber Security Submittal ML0921000502009-07-31031 July 2009 Notice of Pre-Application Meeting with Luminant Generation Company LLC to Discuss Future Amendment Request to Revise Comanche Peak Units 1 and 2 Startup Transformer Completion Times ML0920203432009-07-22022 July 2009 Revised Conference Call with Luminant Generation Company, LLC, to Discuss Draft Request for Additional Information Re Generic Letter 2004-02, Dated May 11, 2009 ML0918207102009-07-0202 July 2009 Revised Notice of Meeting with Representatives of Luminant Generation Co., LLC, Comanche Peak to Discuss Draft Request for Information for Generic Letter 2004-02 Response ML0814400962008-05-23023 May 2008 Meeting Agenda for Closed Security Meeting with Luminant Generating Corporation, LLC to Discuss Security Related Issues and Inspection Results at Comanche Peak Steam Electric Station, Units 1 and 2 2024-11-05
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23332A2772023-11-0707 November 2023 CPNPP Dseis Slide for 12/7/23 Public Meetings_112223 ML23215A1922023-08-0707 August 2023 – August 7, 2023 Presubmittal Meeting Presentation - Relocation of Technical Specification 3.9.3 Nuclear Instrumentation to a Licensee Controlled Document (EPID: L?2023?LRM-0052) ML23215A1652023-08-0404 August 2023 – August 8, 2023 Presubmittal Meeting Presentation - Technical Specification 3.8.1 AC Sources - Operating Required Action B.4, 14-hour Completion Time (EPID: L?2023?LRM-0053) ML23094A2722023-04-0606 April 2023 – April 6, 2023 Presubmittal Meeting Presentation - Extension Request for Thermal Relief Valves (EPID: L?2023?LRM-0023) ML23081A0252023-03-22022 March 2023 – March 28, 2023 Pre-submittal Meeting Presentation - LAR for Exception to RG 1.81 (EPID L?2023?LRM-0015) ML23045A1552023-02-14014 February 2023 Public Meeting February 23, 2023 - Presentation Slides ML23011A0872023-01-10010 January 2023 License Renewal Scoping Meeting, Comanche Peak Nuclear Power Plant, Units 1 and 2 - Meeting Slides ML22140A1082022-05-31031 May 2022 (CPNPP) First License Renewal (60 Years) Application Pre-Application Submittal Meeting 2, Meeting Slides ML21259A0312021-09-30030 September 2021 Initial License Renewal Pre-Application Submittal Meeting Sept 2021 - Safety ML21259A0292021-09-16016 September 2021 Initial License Renewal - NRC Presubmittal Meeting Slides - Safety ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report ML21259A0332021-09-16016 September 2021 Initial License Renewal Application - NRC Presubmittal Meeting Slides - Environmental ML21095A3052021-04-0707 April 2021 4/7/2021 Presubmittal Meeting Presentation - Comanche Peak, Units 1 and 2 - Request for a Temporary Exemption from 10 CFR 73, Appendix B, Section VI, Subsection A.7 and Subsection C.3(l)(1) (L-2021-LRM-0039) ML21097A0522021-04-0707 April 2021 NRC Talking Points - 4/7/2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for Comanche Peak ML21068A0292021-03-0909 March 2021 Presentation - 3/24/2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21007A2562021-01-12012 January 2021 Luminant-CPNPP License Renewal SAMA January 12 2021 Public Mtg ML20314A3422020-11-12012 November 2020 NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating ML20036D4102020-02-12012 February 2020 Pre-Submittal Meeting for: Comanche Peak Nuclear Power Plant Docket Nos. 50-445 and 50-446 February 12, 2020 - License Amendment Request for Changes to Certain Emergency Action Levels ML19337A6622019-12-0303 December 2019 Revised Comanche Peak Pre-Submittal Meeting with NRC for Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources -- Operating ML19324D3482019-11-0505 November 2019 December 3, 2019 Pre-Submittal Meeting Presentation - Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources - Operating (L-2019-LRM-0072) ML17333A0772017-11-0707 November 2017 Infogram 14-1 November 7, 2017 Meeting ML14077A2872014-03-18018 March 2014 Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317 ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, ML12229A5042012-09-19019 September 2012 8/6/2012 Summary of Conference Call with Luminant to Discuss Proposed License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 ML12236A3322012-08-23023 August 2012 Non-proprietary - Presentation for September 13, 2012, Proposed License Amendment Request for Spend Fuel Pool Criticality Analysis ML12188A6972012-07-18018 July 2012 6/26/12 Summary of Meeting with Luminant Generation Company LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME8 ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... ML1114003142011-05-19019 May 2011 Summary of Public Meeting with Luminant Generation Company on Comanche Peak Nuclear Power Plant, Units 1 and 2, to Discuss 2010 End of Cycle Performance Assessment ML1101908002011-01-18018 January 2011 Summary of Meeting with Luminant Generation Company LLC Regarding a Preliminary Finding with Moderate Safety Significance ML11161A1552009-11-30030 November 2009 Enclosure 4 to TXX-11056, Jp Morgan'S Long-Term Capital Market Returns ML0924401642009-09-14014 September 2009 Meeting Summary, Pre-Application Meeting on with Luminant Generation Company LLC to Dicuss Future Amendment Request to Revise Comanche Peak Units 1 and 2 Startup Transformer Completion Times ML0919402762009-07-0909 July 2009 NRC Opening Remarks Discuss the Draft Us Nuclear Regulatory Commission Request for Additional Information for Generic Letter GL-2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressur ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing ML0918303012009-07-0202 July 2009 Summary of Annual Performance Assessment Meeting for Comanche Peak Steam Electric Stations ML0828204232008-10-0707 October 2008 Meeting Handout - Comanche Peak Col Application Public Orientation Meeting ML0720101742007-05-23023 May 2007 Enclosure 2 - 5/23/07 A.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0720101702007-05-23023 May 2007 Enclosure 3 - 5/23/07 P.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0707202502006-12-12012 December 2006 12/12-13/2006 Slides, Txu Power Comanche Peak Site, NRC Onsite Review, Site Geotechnical Investigation Activities. ML0702304012006-10-20020 October 2006 Pre-DBA and Post DBA Pictures ML0530801972005-10-18018 October 2005 Slides 46 Pages - Comanche Peak -Summary of Meeting with Txu Generation Company, LP, to Discuss Application of Accident Analysis Methodologies ML0435101002004-11-10010 November 2004 Meeting Slides - Nrc/Stars Plant Aging Management Center of Business Meeting ML0429905152004-10-19019 October 2004 Presentation by Txu on 10/19/04 - Comanche Peak Steam Electric Station, Unit 1 - Steam Generator Replacement Project ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback ML0404104602004-02-10010 February 2004 2/4/2004 Meeting Summary with Txu for Comanche Peak, Units 1 and 2 to Discuss Plans for Digital Modifications ML0316806212003-07-17017 July 2003 Licensee'S Handouts, Slides and Viewgraphs, 53 Pages, S107210 ML0316806062003-07-17017 July 2003 NRC Handout, Slides and Viewgraphs, 103 Pages, S107211 ML0234504632002-12-10010 December 2002 05000445; Txu Energy, Comanche Peak, Public Exit Meeting - December 10, 2002-Licensee Handouts ML0234504962002-12-10010 December 2002 05000445-TXU Energy-Comanche Peak; Public Exit Meeting Slides (Nrc); December 10, 2002 ML0211400792002-04-22022 April 2002 Attachment 15, E-Mailed on April 22, 2002 (Docket Nos. 50-445 and 50-446). Slides for Zirlo Meeting ML0210801292002-03-0505 March 2002 March 5, 2002 - RIC 2002 Presentation - T3 Lance Terry - Policy Focus Safeguards/Security Issues 2023-08-07
[Table view] |
Text
Luminant Power-NRC Meeting Comanche Peak Lead Plant LAR to Relocate Tech Spec 3.3.1 and 3.3.2 LCOs that do not Satisfy Any of the Criteria of 10CFR50.36(c)(2)(ii)
September 13, 2011 Slide 1
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Agenda
- Purpose of the PWROG Program
- Summary of the March 2, 2011 NRC/PWROG Meeting
- Comments and Open Discussion Slide 2
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Purpose of the Meeting
- Discuss with the NRC Staff the Comanche Peak Units 1 and 2 lead plant License Amendment Request (LAR) that will propose to relocate the LCOs in Technical Specifications (TS) 3.3.1, RTS Instrumentation, and 3.3.2, ESFSA Instrumentation, that do not satisfy any of the Criteria of 10CFR50 10CFR50.36(c)(2)(ii) 36(c)(2)(ii) out of the TS to a licensee controlled document
- Obtain Staff feedback Slide 3
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Purpose of the PWROG program
- Identify the LCOs in TS 3.3.1 and 3.3.2 of the Comanche Peak TS that satisfy Criterion 3 of 10CFR50.36(c)(2)(ii) by reviewing Chapters 6 and 15 of the Comanche Peak safety analyses
- Identify the LCOs in TS 3.3.1 and 3.3.2 of the Comanche Peak TS that satisfy Criterion 4 of 10CFR50.36(c)(2)(ii) by reviewing the PRA and other Risk-Informed TS changes that have been implemented
- Determine the LCOs in TS 3.3.1 and 3.3.2 of the Comanche Peak TS that satisfy the Criteria of 10CFR50.36(c)(2)(ii) as discussed above Slide 4
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Purpose of the PWROG program (cont.)
- RTS and ESFAS instrumentation does not satisfy Criteria 1 and 2 of 10CFR50.36(c)(2)(ii), since it does not detect RCS leakage and is not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis y
- Prepare and submit a lead plant LAR that proposes to relocate the LCOs in TS 3.3.1 and 3.3.2 of the Comanche Peak Units 1 and 2 TS that do not satisfy any of the Criteria of 10CFR50.36(c)(2)(ii)
Slide 5
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background
- WCAP-11618 (Methodically Engineered, Restructured, and Improved Technical Specifications, Merits Program - Phase II Task 5, Criteria Application, November 1987) proposed relocating a number of LCOs, including g RTS,, ESFAS,, and Interlock functions
- Generic application must be confirmed on a plant specific basis when converting to the Improved Standard Technical Specifications (ITS)
- NRC review of WCAP-11618 concluded that the majority of the LCOs could be relocated out of the TS, with some exceptions , such as RTS, ESFAS, and Interlock Functions, which should be retained in the TS Slide 6
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background (cont.)
- The NRC stated The Policy Statement criteria should not be used as the basis for relocating specific trip functions, channels, or instruments within these LCOs
- The TS LCOs that are relocated out of the TS to licensee control are relocated as is without any changes
- Therefore the plant design is not changed by relocating TS LCOs out of the TS
- The TS LCOs that are relocated out of the TS to licensee control must be changed in accordance with 10CFR50.59 to determine whether prior NRC review and approval of the change is required Slide 7
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background (cont.)
- NRC Final Policy Statement on TS Improvements issued on July 23, 1993
- Lack of well defined criteria for what should be included in the TS resulted in several fold increase in the number of LARs
- In the Commission's view, this has diverted both NRC staff and licensee attention from the more important requirements in these documents to the extent that it has resulted in an adverse but unquantifiable impact on safety.
Slide 8
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background (cont.)
- NRC Final Policy Statement on TS Improvements issued on July 23, 1993 (cont.)
- LCOs which do not meet any of the criteria below may be proposed for p
removal from the Technical Specifications and relocation to licensee-controlled documents, such as the FSAR.
- The following criteria delineate those constraints on design and operation of nuclear power plants that are derived from the plant safety analysis report or PSA information and that belong in the Technical Specifications in accordance with 10 CFR 50.36 and the purpose of Technical Specifications stated above.
Slide 9
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background (cont.)
TS LCO criteria contained in 10CFR50.36(c)(2)(ii):
Criterion 1. Installed instrumentation that is used to detect, and indicate in the control room,, a significant g abnormal degradation g
of the reactor coolant pressure boundary.
Criterion 2. A process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Slide 10
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background (cont.)
TS LCO Criteria contained in 10CFR50.36(c)(2)(ii):
Criterion 3. A SSC that is part of the primary success path and which functions or actuates to mitigate g a DBA or transient that either assumes the failure of or presents a challenge to the integrity of a fission product barrier.
Criterion 4. A SSC which operating experience or probabilistic risk assessment has shown to be significant to public health and safety.
Slide 11
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Background (cont.)
- During the development of the ITS (NUREG-1431), several LCOs were created from other LCOs contained in NUREG-0452:
- LCO 3.3.5, Loss of Power (LOP) Diesel Generator (DG) Start Instrumentation, was contained in LCO 3/4.3.2, ESFAS Instrumentation
- LCO 3.3.6, Containment Purge and Exhaust Isolation Instrumentation, LCO 3.3.7, Control Room Emergency Filtration System Actuation Instrumentation, and LCO 3.3.8, Fuel Building Air Cleanup System Actuation Instrumentation, were previously contained in LCO 3/4.3.3.1, Radiation Monitoring Instrumentation for Plant Operations Slide 12
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Precedent
- WCAP-11394-P-A, Methodology for the Analysis of the Dropped Rod Event, was approved by the Staff on October 23, 1989
- The WCAP contains Th t i a methodology th d l that th t demonstrates d t t that th t the th DNB design basis is met following a dropped RCCA event without crediting a reactor trip associated with the dropped RCCA or for automatic power reduction associated with the dropped RCCA
- The methodology supported the elimination of the Power Range Neutron Flux- High Negative Rate reactor trip function
- Several Westinghouse NSSS plants have implemented this methodology and eliminated this reactor trip function from the TS Slide 13
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Precedent (cont.)
- Amendment No. 45 was approved for a licensee on November 29, 1995 that relocated Function Unit 6.b, Feedwater Isolation -
Low RCS Tavgg Coincident with a Reactor Trip, from TS 3.3.2, ESFAS Instrumentation, to a licensee controlled document
- The NRC safety evaluation stated, in part:
- The staff has concluded that the instrumentation utilized to cause feedwater isolation on low RCS Tavg coincident with reactor trip does not serve a primary protective function so as to warrant inclusion in the TS in accordance with the criteria of 10 CFR 50.36.
Slide 14
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Precedent (cont.)
- The WCAP contains Th t i a methodology th d l th thatt was applied li d to t the th LCOs LCO in TS 3.3.3, PAM Instrumentation, of NUREG-1431
- The WCAP methodology determined which PAM LCOs satisfied Criterion 3 and/or 4 of 10CFR50.36(c)(2)(ii)
- PAM instrumentation does not satisfy Criteria 1 and 2 of 10CFR50.36(c)(2)(ii), since it does not detect RCS leakage and is not a process variable, design feature, or operating restriction that is an initial condition of a DBA or transient analysis
- The application of the Criteria of 10CFR50.36(c)(2)(ii) resulted in the relocation of PAM LCOs from TS 3.3.3 in NUREG-1431 Slide 15
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Need for the Change
- The NRC approved Amendments for several licensees that revise the TS for the ESFAS Function that Starts AFW on the Trip of all MFW Pumps
- Amendment NosNos. 312 and 319 were approved for a licensee on August 29, 2008
- Amendment No. 75 was approved for a licensee on March 4, 2009
- Emergency Amendment No. 187 was approved for a licensee on March 5, 2010 Slide 16
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Need for the Change (cont.)
- The NRC SE for Emergency Amendment No. 187 stated:
- The auto-start of AFW on loss of MFW is an anticipatory safety function needed to mitigate the operational impact of loss-of-feedwater events. The AFW start from the loss of MFW pumps is not a requirement in the licensee's design basis event analyses. The design basis events that impose AFW safety function requirements are loss of normal feedwater, main feed line or main steam line break, LOOP, and small break loss-of-coolant accident. These design basis events assume auto-start of the AFW system in the event of a LOOP, a safety-injection (SI) signal, or low-low SG water level. Therefore, even though the auto-start of MDAFW pumps upon an MFW pump trip is an ESFAS function in TS Table 3.3.2-1, Function 6.g, the function is an anticipatory start signal and no credit is taken in any of the licensee's safety analysis described in its USAR.
Slide 17
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Need for the Change (cont.)
- The NRC approved Amendment No.194 for a licensee on March 30, 2011 that revised the TS for ESFAS Interlock; Reactor Trip, P-4
- The NRC SE for Amendment No. No 194 stated:
- The proposed footnote (m) to Function 8.a in TS Table 3.3.2-1 includes removing out of the TSs the following functions (referred as the "Subject functions"): (1) the P-4 function of transfer of the steam dump system to the plant trip controller in MODES 1, 2, and 3, (2) the P-4 turbine trip function in MODE 3, and (3) the P-4 feedwater isolation function in MODE 3. Based on the above, the NRC staff concludes that the existing LCO and related surveillance requirement associated with the "subject functions" do not satisfy any of the criteria in 10CFR50.36(c)(2)(ii). Therefore, the proposed removal of the "subject functions" out of the TSs does not violate the 10 CFR 50.36(c)(2)(ii) requirements and is acceptable.
Slide 18
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Benefits of the Change
- Reductions in the number of LARs submitted
- Reduce the burden on licensees in the preparation of LARs
- Reduce the burden on the Staff to review the LARs
- Reductions R d ti iin potential t ti l TS violations i l ti
- Elimination of potential plant shutdowns required by the TS
Slide 19
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Summary of the March 2, 2011 PWROG/NRC Meeting
- The Staff stated that Criterion 3 also includes issues such as defense-in-depth and is not solely limited to the FSAR Chapter 6 and 15 analyses assumptions, and that they expected to see defense-in-depth defense in depth addressed in the submittal
- The Staff stated that Criterion 4 also includes Operating Experience and is not limited to PRA. The Staff also stated that Criterion 4 did not add any functions to TS 3.3.1 or TS 3.3.2.
- The Staff stated that either of the two proposed PRA approaches to address Criterion 4 as discussed on Slides 26 and 27 would be acceptable to address Criterion 4 Slide 20
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Summary of the March 2, 2011 PWROG/NRC Meeting (cont.)
- The Staff recommended that Luminant Power have a meeting with the Comanche Peak NRC Project Manager prior to submitting b itti the th LAR tot obtain bt i feedback f db k on hihis expectationst ti and d
also so that Staff review resources can be identified
- The Staff needs to resolve the potential Policy Issue related to relocating individual RTS and ESFAS instrumentation functions from the TS Slide 21
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Overall Approach
- Step 1: Meet with the NRC to discuss the program.
- Step 2a: Review plant safety analysis to identify the RTS and ESFAS functions that satisfy Criterion 3.
- Step 2b: Review the plant PRA model to identify which RTS and ESFAS functions are credited that satisfy Criterion 4.
- Step 2c: Review RI applications that have resulted in changes to the plants licensing basis that credited RTS and ESFAS functions that satisfy Criterion 4.
- Step 3: Identify the RTS and ESFAS functions that do not satisfy Criteria 3 & 4.
- Step 4: Prepare a LAR to propose the relocation of the RTS and ESFAS functions that do not satisfy Criteria 3 & 4.
- Step 5: NRC Review Activities Slide 22
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Overall Approach (cont.)
- Comanche Peak is the Lead Plant to facilitate the NRCs review
- Multi-step process - discussed on the following slides
- Initially apply the process to a W NSSS plant.
plant Then apply it to CE and B&W NSSS lead plant
- Plant specific applications of the Criterion of 10 CFR 50.36(c)(2)(ii) following this approach will be submitted after NRC approval of the Lead Plant LAR Slide 23
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 2a: Review the Safety Analyses
- Review the Comanche Peak Chapter 6 and 15 safety analyses
- Identify the primary RTS and ESFAS functions credited
- Any function that is not a primary function that is credited in the Chapter 6 and 15 safety analyses is a backup function, which does not satisfy Criterion 3 Slide 24
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 2b: Assess PRA Model Requirements
- Review the Comanche Peak PRA model
- Typically plant PRA models do not model specific RTS/ESFAS functions for each event, but use representative functions
- Quantitative function information (risk related) is not available
- Therefore two qualitative approaches will be used Slide 25
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 2b: Assess PRA Model Requirements (cont.)
- Identify the RTS and ESFAS functions credited explicitly or implicitly for each event considered in the PRA model
- Identify those events that credit a backup function for RT and ESF actuation and the backup function
- Primary and backup RTS and ESFAS functions identified satisfy Criterion 4
- Any functions that are not credited as a primary or backup function do not satisfy Criterion 4 Slide 26
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 2b: Assess PRA Model Requirements (cont.)
- Applicable to primarily RT signals and ATWS risk
- Consider a product of IE frequency and signal unavailability
- For higher frequency events, diverse signals and OA backup are required
- For low frequency events, diverse signals or OA backup may not be necessary Slide 27
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 2c: Assess PRA Applications Requirements
- Review the implementation of plant specific and generic Risk-Informed applications that are included in the Comanche Peak Licensing Basis
- Are the functions that were credited important to the results?
- Are backup functions credited to obtain acceptable results?
- Identify the RTS and ESFAS primary and backup functions credited for each event considered in the Risk-Informed application implemented
- Key Risk-Informed applications are those that resulted in changes to TS 3.3.1 and 3.3.2 Slide 28
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 2c: Assess PRA Applications Requirements (cont.)
- Primary and backup RTS and ESFAS functions satisfy Criterion 4
- Any RTS or ESFAS functions that are not credited as primary or backup do not satisfy Criterion 4 Slide 29
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 3: Identify RTS and ESFAS Functions that do not Satisfy Criteria 3 or 4
- Summarize the information obtained from Steps 2a, 2b, and 2c
- For each TS 3.3.1 and 3.3.2 function, identify if it is credited for eventt mitigation iti ti
- Primary RTS and ESFAS functions credited in the safety analyses satisfy Criterion 3
- Primary and backup RTS and ESFAS functions credited in the PRA and Risk-Informed applications satisfy Criteria 4
- Primary and backup RTS and ESFAS functions not credited in the PRA or Risk-Informed applications are candidates for re-location out of the TS Slide 30
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 4: Prepare Comanche Peak License Amendment Request
- Propose to relocate TS 3.3.1 and 3.3.2 functions that do not satisfy Criteria 3 or 4 out of the TS to licensee control
- Include technical justification that concludes the identified RTS and ESFAS functions can be re-located out of the TS to licensee control Slide 31
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 4: Prepare Comanche Peak License Amendment Request (cont.)
- Preliminary unverified RTS and ESFAS Functions to be relocated out of the TS to licensee control:
- RTS Function 16. a., Turbine Trip on Low Fluid Oil Pressure
- RTS Function 16. b., Turbine Trip on Turbine Stop Valve Closure
- ESFAS Function 6. e., AFW Start on Loss of Offsite Power
- ESFAS Function 6. g., AFW Start on Trip of all Main Feedwater Pumps
- Application of the Criteria of 10CFR50.36(c)(2)(ii) to the RTS and ESFAS Interlocks is being finalized Slide 32
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Step 5: NRC Review of Lead Plant LAR
- Respond to NRCs Requests for Additional Information
- Interface with the NRC Slide 33
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Project Schedule Task Start End Kickoff meeting with Luminant 10/26/2010 Meeting with the NRC 3/02/2011 Review RTS and ESFAS Functions and Identify those Functions 1/01/2011 12/31/11 that do not Satisfy Criterion 3 or 4 Prepare Comanche Peak LAR 1/2/2012 3/31/12 NRC Review Activities 4/1/2012 3/31/13 Slide 34
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Other Options Considered
- RITSTF Initiative 4b; Extend the Completion Time out to a Maximum Backstop of 30 Days
- Only addresses the Completion Time for one inoperable channel, LCO 3.0.3 must be entered for more than one inoperable channel, requires a power reduction or unit shutdown, and does not address reportability
- RITSTF Initiative 5b; Relocate Surveillance Frequencies to a SFCP
- Only addresses changes to the Surveillance Frequency, a power reduction or unit shutdown is still required, and does not address reportability Slide 35
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Other Options Considered (cont.)
- Only addresses changes to the Setpoints, not all plants will adopt Option B, a power reduction or unit shutdown is still required, and does not address reportability
- Relocating the TS 3.3.1 and 3.3.2 Functions that do not satisfy any of the Criteria of 10CFR50.36(c)(2)(ii) out of the TS to licensee control is consistent with the Regulations and the above changes could be made in accordance with 10CFR50.59 instead of 10CFR50.90 Slide 36
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Summary and Conclusions
- The Staff has reviewed and approved previous applications of the Criteria to LCOs (Functions) in TS 3.3.1 and 3.3.2
- The proposed TS changes are consistent with the NRCs Final Policy Statement on TS Improvements
- The proposed changes will result in a burden reduction on both licensee and Staff resources Slide 37
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Summary and Conclusions (cont.)
- The TS LCOs that are relocated out of the TS to licensee control are relocated as is without any changes
- Therefore the plant design is not changed by relocating TS LCOs out of the TS
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Summary and Conclusions (cont.)
- Diversity and Defense-in-Depth are not impacted by relocating the RTS and ESFAS Functions out of the TS to licensee control
- The TS LCOs that are relocated out of the TS to licensee control must be changed in accordance with 10CFR50.59 to determine whether prior NRC review and approval of the change is required Slide 39
Luminant Power-NRC Meeting: Relocate CPSES TS 3.3.1 and 3.3.2 LCOs that do not Satisfy the Criteria of 10CFR50.36(c)(2)(ii)
Comments and Open Discussion Slide 40