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MONTHYEARML0603903012006-02-0909 February 2006 GSI Letter RAI Response to GL 2004-02 (TAC Nos. MC4676 and 4677) Project stage: RAI ML0817601002008-06-27027 June 2008 Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized Water Reactors, Approval of Extension Request Project stage: Other ML0835004652008-11-26026 November 2008 Comanche Peak - Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors, Cover Letter Project stage: Request ML0916604102009-05-11011 May 2009 E-mail Draft Request for Additional Information, Licensee'S Supplemental Responses Dated February 29 and November 26, 2008, to GL 2004-02 Project stage: Draft RAI ML0916604222009-05-11011 May 2009 Request for Additional Information Supplemental Responses to Generic Letter (GL) 2004-02 Dated 02/29/2008 and 11/26/2008 Project stage: RAI 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 Project stage: Draft RAI ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing Project stage: Request ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues Project stage: Request 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 Project stage: Draft RAI 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 Project stage: Request 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 Project stage: Request ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing Project stage: Request ML0916707382009-07-15015 July 2009 Request for Additional Information Supplemental Responses to GL 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: RAI 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 Project stage: Draft RAI ML0919705782009-07-31031 July 2009 Summary of Category 1 Meeting with Luminant Generation Company LLC, Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Meeting ML0926107912009-09-10010 September 2009 Comanche Peak Supplement Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors. Project stage: Request CP-200901396, Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors.2009-10-12012 October 2009 Supplement to Response to NRC Generic Letter (GL) 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basic Accidents at Pressurized-water Reactors. Project stage: Supplement ML0930800032009-10-13013 October 2009 Comanche Peak - Supplement to Response to NRC Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors Project stage: Request ML1009505642010-04-19019 April 2010 Generic Letter 2004-02 Supplemental Response Project stage: Other 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 Project stage: Meeting ML13059A2022013-02-28028 February 2013 Email Licensee Slides for 2/28/13 Meeting Via Conference Call Project stage: Meeting ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, Project stage: Meeting ML13067A0292013-03-15015 March 2013 2/28/13 - Summary 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 Project stage: Meeting CP-201300670, Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance2013-05-16016 May 2013 Closure Options for Generic Safety Issue 191 (GSI-191), Assessment of Debris Accumulation on Pressurized Water Reactor Sump Performance Project stage: Other ML13267A1972013-09-30030 September 2013 Request for Additional Information, Closure of Option 2a to Address In-Vessel Mitigative Measures for Potential In-Vessel Blockage; Related to Generic Safety Issue 191 Project stage: RAI CP-201301214, Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 1912013-10-31031 October 2013 Response to Request for Additional Information Regarding Closure Options for Generic Safety Issue 191 Project stage: Response to RAI 2009-07-31
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Category:Meeting Summary
MONTHYEARML24019A0342024-01-30030 January 2024 Public Meeting Summary - 01-04-2024 - Comanche Peak LRA - Structures Monitoring Program ML23255A0622023-09-18018 September 2023 Summary of August 7, 2023, Presubmittal Meeting with Vistra Operations Company LLC to Discuss the Proposed LAR to Relocate Refueling Operations TS 3.9.3, Nuclear Instrumentation, to the Technical Requirements Manual ML23132A1572023-05-18018 May 2023 Summary of the License Renewal Environmental Audit (EPID Number: L-2022-LNE-004) (Docket Numbers 50-445 and 50-446) ML23103A3002023-04-14014 April 2023 Summary of March 28, 2023, Presubmittal Meeting with Vistra Operations Company LLC to Discuss Proposed LAR to Take Exception to RG 1.81, Rev. 1, Shared Emergency and Shutdown Electric Systems for Multi-Unit Nuclear Power Plants, ML23081A5232023-04-12012 April 2023 Public Scoping Meeting for Environmental Review of Comanche Peak Nuclear Power Plant (Cpnpp), Unit Nos. 1 and 2 License Renewal Application ML23101A0432023-04-12012 April 2023 April 6, 2023, Summary of Meeting with Vistra Operations Company LLC to Discuss Proposed Alternative Regarding Inservice Testing of Various Thermal Relief Valves for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML22151A1842022-06-22022 June 2022 License Renewal Application May 26, 2022 Pre-submittal Public Meeting Summary ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22020A1782022-01-31031 January 2022 Summary of Conference Call Regarding the Fall 2021 Steam Generator Tube Inspections ML21259A1492021-10-26026 October 2021 CPNPP, Unit Nos. 1 and 2 - Meeting Summary for Environmental Pre Submittal Meeting for Initial License Renewal Application on September 21, 2021 ML21259A1402021-10-0505 October 2021 Meeting Summary for Safety Pre Submittal Meeting for Initial License Renewal Application on September 21, 2021 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21130A6832021-05-20020 May 2021 Summary of April 7, 2021, Presubmittal Meeting with Vistra Operations Company LLC Regarding the Proposed Exemption Request to Defer the Annual Force-On-Force Exercise for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21124A0072021-05-10010 May 2021 Meeting Summary for Environmental Pre-Submittal Meeting for Initial License Renewal Application ML21110A0602021-05-0707 May 2021 Summary of April 6, 2021, Meeting with Vistra Operations Company LLC to Defer the Biennial Emergency Planning Exercise for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21099A2752021-04-15015 April 2021 Summary of Teleconference with Vistra Operations Company LLC to Discuss Proposed LAR to Adopt TSTF-505, Rev. 2, to Provide Risk-Informed Extended Completion Times for Comanche Peak, Units 1 and 2 ML20351A2592021-01-0505 January 2021 Summary of November 12, 2020, Teleconference with Vistra Operations Company LLC Proposed License Amendment Request for One-Time TS Revision to Replace Station Service Water Pump ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML20115E3932020-04-30030 April 2020 Summary of April 6 and 7, 2020, COVID-19 Related Presubmittal Teleconferences with Vistra Operations Company LLC to Discuss Licensing Actions Supporting the Comanche Peak Unit No. 2 Spring 2020 Refueling Outage ML20044D3052020-02-26026 February 2020 Summary of Teleconference with Vistra Operations Company, LLC to Discuss a Proposed License Amendment Request for Changes to Certain Emergency Action Levels for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 (EPID L-2020-LRM-000 ML19352E3172020-01-0808 January 2020 Summary of Teleconference with Vistra Operations Company LLC to Discuss a Proposed License Amendment Request to Change TS 3.8.1, AC Sources - Operating for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML19311C2122019-11-13013 November 2019 Summary of November 5, 2019, Teleconference with Vistra Operations Company LLC to Discuss a Proposed License Amendment Request to Change TS 3.8.1, Ac Sources - Operating for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML18275A3142018-10-16016 October 2018 Summary of September 17, 2018, Public Teleconference with Vistra Operations Company, LLC, on Proposed Changes to the Emergency Plan for Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML17137A1742017-05-22022 May 2017 Summary of Conference Call Regarding the Spring 2017 Steam Generator Tube Inspections ML16194A4962016-07-12012 July 2016 Summary of Annual Performance Assessment Meeting and Public Open House Regarding Comanche Peak Nuclear Power Plant 2015 Performance ML15191A2282015-07-27027 July 2015 7/9/2015 Summary of Pre-submittal Meeting with Luminant Generation Company LLC to Discuss Submittal for License Amendment Request to Revise Technical Specification 3.8.1 for Comanche Peak Nuclear Power Plant, Units 1 and 2 (TACs MF6311 and ML15191A2512015-07-0909 July 2015 July 9, 2015 Public Meeting: Comanch Peak Pre- Application Meeting, Emergency Diesel Generator Voltage and Frequency Technical Specification Changes ML14188C4402014-07-22022 July 2014 6/3/2014 Summary of Meeting with Luminant Generation Company LLC to Discuss Proposed Modifications to Technical Specifications to Install Backup Transformer XST1A for Comanche Peak, Units 1 and 2 ML13067A0292013-03-15015 March 2013 2/28/13 - Summary 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 ML12341A0812012-12-18018 December 2012 Summary of 11/15/12 Meeting with Luminant Generation Company LLC to Discuss Indirect License Transfers for Comanche Peak Nuclear Power Plant, Units 1 and 2 ML12332A3652012-12-18018 December 2012 Summary of Meeting with Luminant Generation Company LLC, to Discuss License Amendment Request for Approval of Revised Spent Fuel Criticality Analysis to Update Comanche Peak, Units 1 and 2, Technical Specifications (TAC Nos. ME8896-ME8897) ML12283A3502012-10-25025 October 2012 Summary of 9/13/12 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 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 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 ML12072A3432012-03-12012 March 2012 3/6/2012 Summary of Meeting with Luminant Generation Company, LLC Regarding Planned Modifications to Resolve Fire Protection Circuit Interactions 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 ML1114001482011-05-23023 May 2011 Summary of Conference Call on 4/14/2011 with Nrr/Dci/Csgb Regarding the Spring 2011 Steam Generator Tube Inspections 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 ML1108004622011-03-28028 March 2011 3/17/11 Summary of Closed Meeting with Luminant Generation Company Via Conference Call to Discuss Generic Request for Additional Information Pertaining to Its Cyber Security Submittal ML1101908002011-01-18018 January 2011 Summary of Meeting with Luminant Generation Company LLC Regarding a Preliminary Finding with Moderate Safety Significance ML1034205662010-12-22022 December 2010 Memo Summary of the November 3, 2010, Public Meeting with the United States - Advanced Pressurized Water Reactor Design Centered Working Group to Discuss Inspections, Test, Analyses, and Acceptance Criteria, Conceptual Design Information. ML1016501752010-06-21021 June 2010 6/10/10 Summary of Closed Meeting with Luminant Generation Company, LLC to Discuss Comanche Peak Nuclear Power Plant, Units 1 and 2 Implementation Plan/Information Pertaining to Defensive Strategy for Cyber Security Submittal ML1013906402010-05-19019 May 2010 Summary of Public Meeting with Luminant Generation Company on Comanche Peak Nuclear Power Plant, Units 1 and 2, 2009 Performance 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 ML0919705782009-07-31031 July 2009 Summary of Category 1 Meeting with Luminant Generation Company LLC, Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors ML0918303012009-07-0202 July 2009 Summary of Annual Performance Assessment Meeting for Comanche Peak Steam Electric Stations 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 ML0720005052007-07-31031 July 2007 Summary of Meeting with Txu Generation Company LP to Discussed Regarding the Plans for Methodology Transition and Power Uprate ML0717200702007-06-20020 June 2007 Summary of Meeting with Txu Power Regarding Comanche Peak Steam Electric Stations End-of-Cycle Assessment for 2006 ML0612204362006-05-18018 May 2006 Attachment 3 to Comanche Peak Conference Call 2024-01-30
[Table view] Category:Memoranda
MONTHYEARML24019A0342024-01-30030 January 2024 Public Meeting Summary - 01-04-2024 - Comanche Peak LRA - Structures Monitoring Program ML23279A1052023-10-0606 October 2023 Memorandum from the Secretary to the Board and Parties ML22304A1912022-11-23023 November 2022 Aging Management Audit Plan Regarding the License Renewal Application Review ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML21259A1492021-10-26026 October 2021 CPNPP, Unit Nos. 1 and 2 - Meeting Summary for Environmental Pre Submittal Meeting for Initial License Renewal Application on September 21, 2021 ML21259A1402021-10-0505 October 2021 Meeting Summary for Safety Pre Submittal Meeting for Initial License Renewal Application on September 21, 2021 ML21176A1292021-06-25025 June 2021 CPNPP FFD Inspection Doc Request 2021 ML21174A0942021-06-23023 June 2021 Reactor Trip on June 7, 2021 - Management Directive 8.3 Screening ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21124A0052021-05-10010 May 2021 Memo for Environmental Pre-Submittal Meeting for Initial License Renewal Application ML19120A3382019-04-26026 April 2019 Memo to File Environmental Assessment and Finding of No Significant Impact for Luminant Generation Company, Llc'S Decommissioning Funding Plan Submitted in Accordance with 10 CFR 72.30(b) and 10 CFR 72.30(c) for Comanche Peak ISFSI ML18346A1832019-01-0606 January 2019 FO Closure Audit Summary ML18221A6322018-08-15015 August 2018 Eicb Safety Evaluation - Comanche Peak Nuclear Power Plant, Units 1 and 2, License Amendment Request to Revise Technical Specification 3.3.2 Engineered Safety Feature Actuation System Instrumentation Docket/Epid 000976/05000446/L-2018-LLA-0 ML18173A0082018-06-20020 June 2018 Cancelling Numerous Inspection Report Numbers ML16088A2042016-03-28028 March 2016 Memo T Bowers from s Ruffin, Technical Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations W/ Encl 2 (Template) ML16088A2052016-03-28028 March 2016 Enclosure 1 - (72.30 DFP Reviews to Be Completed 2015) - Memo T Bowers from s Ruffin, Technial Assistance Requests - Review 2015 Tri-Annual Decommissioning Funding Plans for Multiple Independent Spent Fuel Storage Installations 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 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 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 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) 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 ML1117302232011-06-29029 June 2011 Staff Review of the Comanche Peak Independent Spent Fuel Storage Installation Physical Security Plan and Verification of Additional Security Measures Incorporation 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 ML1009105332010-04-0505 April 2010 U.S. Nuclear Regulatory Commission Staff Review of the Department of Homeland Security Consultation Reports ML1006010322010-03-0101 March 2010 Cy 2009 Baseline Inspection Completion ML0925404602009-09-10010 September 2009 Summary of Phone Call with Industry to Issues Related to Eccentricity of the Steam Generator Tube-to-Tubesheet Joints in the Finite Element Model Used for the Technical Basis of the Permanent Alternate Repair Criteria License Amendment Requ ML0919705782009-07-31031 July 2009 Summary of Category 1 Meeting with Luminant Generation Company LLC, Resolution of Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors 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 ML0807400842008-03-14014 March 2008 Draft Regulatory Guide for Comment ML0724904812007-09-11011 September 2007 Notice of Meeting with Strategic Teaming and Resource Sharing (Stars) for Licensees of Comanche Peak, Diablo Canyon, Palo Verde, South Texas, and Wolf Creek Plants ML0720800042007-07-31031 July 2007 Memo to File Request for Additional Information Application for Order Approving Indirect Transfer of Control of Licenses & License Amendments to Reflect Proposed Licensee'S Name Change ML0713003582007-05-11011 May 2007 Notice of Meeting with Txu Generation Company LP, Regarding Proposed Transition to Westinghouse Methodology and Other Methodologies Specific to Comanche Peak Steam Electric Station (CPSES) and Power Uprate Application ML0630400142006-10-31031 October 2006 Notice of Forthcoming Meeting with Txu Generation Company, LP Re Radiological Consequences of Design-Basis Accidents for Comanche Peak Steam Electric Station ML0627202212006-10-13013 October 2006 Staff'S Review of the Revision to Technical Specification Surveillance Requirements 3.3.1.2 & 3.3.1.3, Reactor Trip System Instrumentation (RTS) ML0612805802006-06-30030 June 2006 Memo with Enclosures 1 and 2, - Trip Report Regarding Staff Observations Regarding Flume Testing of a Prototype Portion of the Proposed Replacement Suction Screen Design for the Comanche Peak Steam Electric Station ML0607302642006-03-0707 March 2006 Closure Memorandum: Issue for Resolution 2005-083: Evaluation: Part 21 - Engine Systems - Governor Drive Coupling Element ML0527802152005-10-0505 October 2005 Forthcoming Meeting with Txu Analytical Methodologies Supporting the Comanche Peak, Unit 1, Steam Generators Replacement Project ML0525803232005-09-15015 September 2005 Meeting with Strategic Teaming and Resource Sharing (Stars) for Licensees of Comanche Peak, Diablo Canyon, Palo Verde, South Texas, and Wolf Creek Plants ML0519301632005-07-14014 July 2005 Unit 2 - Closeout Letter for Bulletin 2003-01, Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors. ML0516003452005-06-14014 June 2005 Draft Information Memo - May 6 - May 27, 2005 ML0506104872005-03-23023 March 2005 Draft Information Memo - May 1, 2005 Thru May 27, 2005 ML0435701632005-01-24024 January 2005 Draft Information Memo - Inputs from March 2, 2004 Through March 31, 2004 ML0429402412004-10-25025 October 2004 Draft Information for June 1, 2004 to June 30, 2004 ML0426400682004-09-21021 September 2004 Draft Information Report from January 14 Thru February 26, 2004 ML0421103022004-08-19019 August 2004 Draft Information Memo for April, 2004 - Shirley ML0422602762004-08-12012 August 2004 Meeting Summary of the August 8, 2004 Public Workshop - Region IV Operator Licensing Feedback 2024-01-30
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UNITED STATES NUCLEAR REGULATORY COMMISSION WASHINGTON, D.C. 20555-0001 July 31, 2009 LICENSEE: LUMINANT GENERATION COMPANY LLC FACILITY: COMANCHE PEAK STEAM ELECTRIC STATION, UNITS 1 AND 2
SUBJECT:
SUMMARY
OF JULY 9,2009, CATEGORY 1 MEETING WITH LUMINANT GENERATION COMPANY LLC ON RESOLUTION OF GENERIC LETTER 2004-02 (TAC NOS. MC4676 AND MC4677)
From 8:00 AM to 12:00 PM on July 9, 2009, a public meeting was held between the U.S.
Nuclear Regulatory Commission (NRC), and representatives of Luminant Generation Company LLC (Luminant, the licensee), at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, MD. The purpose of the meeting was to discuss the resolution the draft NRC request for additional information (RAI) regarding Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation during Design Basis Accidents at Pressurized-Water Reactors," for Comanche Peak Steam Electric Station (CPSES), Units 1 and 2.
A list of meeting attendees and the Nuclear Energy Institute (NEI) bridge line participants is enclosed. During this meeting, representatives from Luminant, AREVA NP Inc. (AREVA), Alion Science and Technology Corporation (Alion), Alden Research Laboratory, Inc. (Alden), and Performance Contracting, Inc. (PCI), presented slides discussing the common understanding and proposed path forward regarding the draft GL 2004-02 RAI.
Presentations The following meeting slides are located in the Agencywide Documents Access and Management System (ADAMS):
Results of Discussion RAI #2: The licensee discussed the potential for destruction of lead blankets during a loss-of coolant accident (LOCA) and the expected characteristics of the lead blanket debris. The NRC
-2 staff was able to determine that the debris usec;! during head loss testing likely provided a conservative representation of the debris that would be created in the plant during a LOCA.
This item should be able to be satisfactorily addressed.
RAI #9: The licensee discussed the analytical pool-fill transport model for CPSES, Units 1 and
- 2. The NRC staff stated that the discussion was not sufficient to resolve the issue, in part, because the issue actually concerned the modeling of pool-fill transport in the test flume, which did not appear to have been performed prototypically. The licensee agreed to provide additional explanation and justification for its analysis methods, physics, and modeling conservatisms during the pool-fill phase.
RAI #6: The licensee discussed the testing that formed the basis for the assumption that 10 percent fiberglass materials settled in the containment pool will be eroded to fines. The NRC staff is currently reviewing the erosion test report to determine whether this assumption is justified.
RAI #8: The licensee stated that adding fine debris to the test flume to account for the erosion of settled debris pieces in the flume is unnecessary and that fines are released from small and large pieces of debris added to the test flume. The NRC staff stated that the information presented by the licensee to provide sufficient confidence that a representative quantity of fine debris is released to account for erosion. The licensee agreed to provide additional information on this subject, explaining and documenting known conservatisms in this area.
RAI #15: The licensee discussed the basis for the addition of approximately two-thirds of the latent fibrous debris prior to starting the test flume recirculation pump. The NRC staff stated that this practice appears inconsistent with the head loss testing review guidance but agreed that a video taken of latent debris transport in the small flume at Alden would be helpful in assessing the significance of the issue. The licensee stated that it plans to provide additional information, including the video discussed.
RAI #20: The licensee stated that the transport of large debris pieces in the test flume was not affected adversely by its narrowness. The NRC staff stated that it is likely that the addition of large pieces adversely affected debris transport in the flume, but noted that the significance of the issue may be limited if the licensee could demonstrate that the debris pile on the flume floor was relatively non-porous. The licensee informed the staff that it plans to provide additional supporting information, including a description of fiber preparation and supporting photos.
RAls #22 and 23: The licensee stated that the minimum submergence of the strainer had been recalculated and determined to be significantly greater than previously determined. The licensee also stated that the strainer would be fully submerged within 5 to 15 minutes of the initiation of emergency core cooling system recirculation and that, for full recirculation, the strainer would be fully submerged. The licensee agreed to provide the NRC staff with supplemental analysis of revised small-break LOCA analysis which revised the minimum sump water level. Based on the information provided, or expected to be provided, the NRC staff expressed the belief that the licensee is likely to be able to demonstrate adequate strainer performance in the areas of air ingestion, voiding, vortex formation, and flashing.
-3 RAI #37: The licensee stated that strainer testing had been performed conservatively for the limiting secondary line break location, even though the licensing basis does not require consideration of this break location. The NRC staff expressed the view that the test methodology used for the strainer test for this break does not appear conservative and that the licensee's argument concerning the exclusion of this break location from the licensing basis had not been sufficiently justified. NRC Regulatory Guide 1.82, "Water Sources for Long-Term Recirculation Cooling Following a Loss-of-Coolant Accident," dated November 2003, and the NRC staff's safety evaluation dated December 6, 2004 (ADAMS Accession No. ML043280641),
on NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology," dated May 28, 2004 (ADAMS Accession No. ML041550661), indicate that the limiting secondary line break locations for strainer performance should be considered, and General Design Criterion 4, "Environmental and dynamic effects design bases," in Appendix A to Part 50 of Title 10 of the Code of Federal Regulations, does not address the generation of debris by high-energy line breaks. The licensee stated that it planned to provide NRC staff with an improved basis regarding the acceptability of test design and results.
Due to time constraints, the NRC staff and the licensee agreed to have a wrap-up phone call within 2 weeks of the meeting.
As a Category 1 meeting, the public was invited to observe and was given an opportunity to communicate with the NRC staff after the business portion, but before the meeting was adjourned. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at (301) 415-3016, or Balwant.Singal@nrc.gov.
Sincerely,
~~, u-..} \c..b l ~~
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
List of Attendees and NEI Bridge Line Participants cc w/encl: Distribution via Listserv
ENCLOSURE LIST OF MEETING ATTENDEES AND NEI BRIDGE LINE PARTICIPANTS JULY 9, 2009, PUBLIC MEETING WITH LUMINANT GENERATION COMPANY LLC
LIST OF ATIENDEES FOR JULY 9, 2009 PUBLIC MEETING WITH LUMINANT GENERATION COMPANY LLC NAME ORGANIZATION M~ES W CA/o(
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th Meeting on July 9 , 2009 between Luminant and the NRC NEI Bridge Line Participants Russ Lytton McGuire Nuclear Station, Duke Energy 980-875-5421 Russell. Lytton@duke-energy.com Andrew Kaufman Continuum Dynamics, Inc 609-538-0444 x 111 andy@continuum-dynamics.com Mark Harriman Ginna Station, Constellation Energy 585-771-3251 Mark.Harriman@constellation.com Paul Leonard Cook Station, AEP 269-697-5668 pwleonard@aep.com Wendi Croft Three Mile Island, Exelon Nuclear 610-765-5726 Wendi.Croft@exeloncorp.com Rich Sievers Three Mile Island, Exelon Nuclear 717-948-8398 Richard.sievers@exeloncorp.com Pete Wilkens Southern California Nuclear 949-368-2234 peter.wilkens@sce.com Ed Kimoto Southern California Nuclear 949-368-2114 edwin.kimoto@sce.com
ML043280641),
on NEI 04-07, "Pressurized Water Reactor Sump Performance Evaluation Methodology," dated May 28, 2004 (ADAMS Accession No. ML041550661), indicate that the limiting secondary line break locations for strainer performance should be considered, and General Design Criterion 4, "Environmental and dynamic effects design bases," in Appendix A to Part 50 of Title 10 of the Code of Federal Regulations, does not address the generation of debris by high-energy line breaks. The licensee stated that it planned to provide NRC staff with an improved basis regarding the acceptability of test design and results.
Due to time constraints, the NRC staff and the licensee agreed to have a wrap-up phone call within 2 weeks of the meeting.
As a Category 1 meeting, the public was invited to observe and was given an opportunity to communicate with the NRC staff after the business portion, but before the meeting was adjourned. Public Meeting Feedback forms were not received.
Please direct any inquiries to me at (301) 415-3016, or Balwant.Singal@nrc.gov.
Sincerely, IRA!
Balwant K. Singal, Senior Project Manager Plant Licensing Branch IV Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-445 and 50-446
Enclosure:
List of Attendees and NEI Bridge Line Participants cc w/encl: Distribution via Listserv DISTRIBUTION:
PUBLIC RidsNrrDssSsib Resource LPLIV rtf RidsNrrPMWolfCreek Resource RidsAcrsAcnw_MailCTR Resource RidsNrrLAJBurkhardt Resource RidsNroDsraSpcv Resource RidsOgcRp Resource RidsNrrDciCsgb Resource RidsRgn4MailCenter Resource RidsNrrDorlLpl4 Resource CTucci, NRR RidsNrrDrpPgcb Resource LTrocine, EDO Region IV ADAMS A ccesslon No. ML091970578 t d J uly
- e-mal'1 d ae I 16 , 2009 OFFICE NRRlLPL4/PM NRRlLPL4/LA NRRlSSIB/BC NRR/LPL4/BC NRRlLPL4/PM NAME BSingal JBurkhardt MScott* MMarkley BSingal DATE 7/27/09 7/24/09 7/16/09 7/31/09 7/31/09