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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 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: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 ML21259A0332021-09-16016 September 2021 Initial License Renewal Application - NRC Presubmittal Meeting Slides - Environmental ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report 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) 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 ML0204200522002-02-0505 February 2002 Regulatory Conference - January 23 2002 2023-08-07
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7/8/2009 NRC - CPNPP Public Meeting RAI 9 - Pool Fill Transport Comanche Peak Emergency Sump Performance July 9th 2009 N
CIENt ANDTEtHNOLOGY1 Updated: 7/6/09 Debris Transport During Pool Fill Phase
" Following the blowdown, as the pool starts filling, debris would tend to be washed out of the two RCS Loop Bay doors.
" During the initial high velocity sheeting phase of the fill-up period, the only directional flow outside the secondary shield wall would be toward the inactive reactor cavity.
- Therefore, debris would be scattered around outside the secondary shield wall and carried into the reactor cavity.
0 Water would not flow preferentially to the sump strainers until the water level rises above the top of the 12 inch debris interceptors (after the sheeting phase is over), and it would take less than a minute for the sump cavities to fill.
I
7/8/2009 Debris Distribution at Beginning of Recirculation Although, debris in the pool would be more likely to be concentrated in the vicinity of the reactor cavity entrance and around the full area *,
outside the secondary shield wall, the debris transport calculation conservatively assumed that the debris -i would be distributed along the shortest paths from the location of the break to the sump strainers.
Debris Distribution at Beginning of Recirculation Due to the high spray flow, most debris in the path of the sprays would be washed down from upper containment relatively quickly and would reach the pool before the initiation of recirculation.
2
7/8/2009 Debris Transport During Recirculation Phase Although it was not credited, the presence of RMI and other less transportable debris in the vicinity of the strainer would tend to trap more readily transportable debris reducing the overall recirculation transport.
3
,-Pu lic eetng ergency Sum PErformnest Coup-nche Peak Eme.rgency Sumtp Performance
, July th2009 A LION SCIENCE AND TECHNOLOGY Updated: 7/6/09
Erosio Te.
- 6. Please describe the testing performed to support the assumption of 10%
erosion of fibrous debris pieces in the containment pool. Please specifically include the following information:
- a. Please describe the test facility used and demonstrate the similarity of the flow conditions (velocity and turbulence), chemical conditions, and fibrous materialpresent in the erosion tests to the analogous conditions applicable to the plant condition.
- b. Please provide specific justification for any erosion tests conducted at a minimum tumbling velocity if debris settling was credited in the test flume for velocities in excess of this value.
- c. Please identify the duration of the erosion tests and how the results were extrapolated to the sump mission time.
RAI 6 - Erosion Testing Please describe the testing performed to support the assumption of 10% erosion of fibrous debris pieces in the containment pool.
oALION-PLN-LAB-2352-77, Rev 3 - Test Plan for the Erosion Testing of Low Density Fiberglass Insulation and High Density Fiberglass Insulation.
-ALION-REP-LAB-2352-77, Rev 3 - Test Report: Erosion Testing of Low Density Fiberglass Insulation.
-ALION-REP-TXU-4464-03, Comanche Peak Low Density Fiberglass Debris Erosion Testing Report" Alion issued ALION-PLN-LAB-2352-77 and ALION-REP-LAB-2352-77 to the NRC on 070/8/09 Please specifically include the following information:
RAI 6 - Erosion Testing RAI 6 - Erosion Testing RAI 6a: Please describe the test facility used and demonstrate the similarity of the flow conditions (velocity and turbulence), chemical conditions, and fibrous material present in the erosion tests to the analogous conditions applicable to the plant condition.
-Per Section 2.2 of "ALION-REP-TXU-4464-03, Comanche Peak Low Density Fiberglass Debris Erosion Testing Report", NUKON LDFG testing was performed in Alion's Hydraulic Test Lab Vertical Test Loop (VTL) and the lab's Transport Flume (TF). Details of these apparatuses can be found in "ALION-PLN-LAB-2352-77: Low Density Fiberglass Erosion Test Plan" which is Ref. 3 of ALION-REP-TXU-4464-03.
-The description of the Test is given in Section 3 of ALION-REP-TXU-4464-03 as well.
-Per Section 3.3 of ALION-REP-TXU-4464-03, since the incipient tumbling velocity is the velocity at which the debris would start moving, this velocity bounds the greatest velocity that a piece of insulation lying in the containment pool would experience without being carried to the sump strainer.
Therefore, it is considered the velocity that would produce the most insulation fines that would travel to the sump strainer while the piece of insulation itself would remain stationary in the pool.
RAI 6 - Erosion Testing Per Section 3.4 of ALION-REP-TXU-4464-03, the increased post-LOCA water temperature at Comanche Peak would have no effect on the flow erosion of fiberglass since the higher water temperature does not affect the chemical or physical reaction of the fibers with respect to physical erosion taking place. Per Ref. I of ALION-REP-TXU-4464-03, i.e. "ALION-REP-LAB-2352-77, Test Report: Erosion Testing of Low Density Fiberglass Insulation", the tests were conducted in tap water and not buffered or borated water that would be present in containment. The use of tap water is considered appropriate because the lack of chemicals such as aluminum, boron, or pH buffers will not affect the amount of fibers that would erode off of a Nukon sample with respect to flow erosion. On the contrary, the presence of some chemicals such as aluminum would actually bond to the fibers and increase the mass of the Nukon sample instead of aiding its erosion.
Additionally, if turbulence is high enough to not allow settling, then the insulation debris will be transported to the sump strainers. In both cases, since the debris will be transported to the sump strainers, it will not be sitting in the containment pool and its flow erosion will not be taken into consideration as it will be irrelevant. The erosion factor is applied to the portion of the small and large pieces of fiber in the pool that are subjected to a low enough turbulence to allow settling and low enough velocity (i.e. a velocity lower than the corresponding incipient tumbling velocity) to avoid tumbling. A combination of the above two conditions applies to a portion of the pool that is calmer than the rest of the areas.
RAI 6 - Erosion Testing
" As discussed in Section 4.0 of ALION-REP-TXU-4464-03, it was observed that the term fiber "erosion" to describe the loss of weight is more aptly described as fiber "attrition." The fibers themselves that make up the samples do not actually erode down into fines as the water passes across them; the "erosion" is actually the release of loosely bound constituent fibers that are washed away by the flowing water. Alion's experience with fibrous debris during other types of tests is evident of this behavior. During testing, the following is usually observed that when the clumps of fiber subjected to a velocity such that an erosion factor is applicable (as discussed above) on the floor of a test pool:
- Individual fibers tend to clump which is evident by the measures taken by the Alion Hydraulics Laboratory to keep them apart during testing.
" Individual fibers released tend to re-clump or adhere to pieces of fiber present downstream.
No credit is taken for the above.
RAI 6 - Erosion Testing RAI 6b is: Please provide specific justification for any erosion tests conducted at a minimum tumbling velocity if debris settling was credited in the test flume for velocities in excess of this value.
-Per Section 3.3 of ALION-REP-TXU-4464-03, since the incipient tumbling velocity is the velocity at which the debris would start moving, this velocity bounds the greatest velocity that a piece of insulation lying in the containment pool would experience without being carried to the sump strainer.
Therefore, it is considered the velocity that would produce the most insulation fines that would travel to the sump strainer while the piece of insulation itself would remain stationary in the pool.
sio Testin RAI 6c is: Please identify the duration of the erosion tests and how the results were extrapolated to the sump mission time.
-The results for small Nukon erosion testing did not require extrapolation due to having performed 30 day tests.
-Twenty two (22) erosion tests were performed on small pieces of NUKONTM, each test consisting of 8-12 samples. Each such test is an average of the results obtained from the corresponding set of samples, i.e. each data point in Figure 3.2-I of Reference 3 of ALION-REP-TXU-4464-03. The results are used to represent the entire size distribution of'the insulation material that the erosion factor will be applied to. This is conservative because Alion testing has shown that smaller pieces that have a higher relative surface area (i.e. higher surface to mass ratio which means more expected erosion per gram) erode more than larger pieces; therefore, the larger pieces in containment would typically erode less than the bounding value that this report applies. Note that by the large amount of data represented by Figure 3.2-I, although a disparity of results is not expected, but because of the small size and mass of the samples, a substantial data scatter is expected.
RAI 6 - Erosion Testing
" The erosion factor is based on the pre-test and post-test mass differences of each sample, so any handling losses also are represented by the erosion factor, since there isn't a way of differentiating the handling losses from the actual erosion during testing. This results in an additional potential conservatism. But because of gained experience by the Alion testing team, the later testing resulted in more consistent data. So while the 30 day samples exhibit lower results then some of the earlier samples, they were in fact the last set of tests performed and due to the number of test performed and the experience of the test staff are considered the most consistent/accurate.
- Four (4) of the samples exhibited greater than 10% erosion which is attributed to some expected randomness and since the erosion factor will be applied to many randomly sized pieces of fiberglass one would expect some to exhibit greater and others lower amounts. Note that for thirteen (I 3) of the twenty two (22) samples (more than half of the samples) showed an erosion factor of less than 5% (half of the erosion factor that will be applied) which introduces an additional conservatism.
7/8/2009 NRC - CPNPP Public Meeting Preliminary Assessment of Containment Pool with respect to Erosion Testing Comanche Peak Emergency Sump Performance July 9th 2009 ASLION AND TECHNOLOGY SCIENCE Updated:7/6/09 Erosion Testing - Flume Turbulence vs. Plant Turbulence
" Velocity in flume tests set to approximately 0. 12 ftls, which is the tumbling velocity for small pieces of fiberglass
" Flume turbulence levels during erosion testing were not directly measured, but can be estimated using CFD I Comanche Peak Loop 4 break, two train operation: 100%
transport of small fiberglass debris (small piece fiberglass erosion is not applicable for this case)
Comanche Peak Loop 4 break, single train Sump B: partial transport of small fiberglass debris I
7/8/2009 TKE and velocity with limits set at suspension/tumbling of small pieces of fiberglass (Loop 4 LBLOCA Single Train Sump B)
-V'e-octy' 0.12 ftls Area where small fiberglass in lower containment would transport (Loop 4 LBLOCA Single Train Sump B)
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7/8/2009 Preliminary Average Velocity and Turbulence for Small Pieces of Fiberglass Debris in Lower Containment that do not Transport (2% of Small Fiberglass Debris Generated) 2 2 o040 Average Turbulence = 0.00068 ft /s AverageVelocity 0.056 ft/s Area where small fiberglass washed down to lower containment inside the RCS loop bays would transport (Loop 4 LBLOCA Single Train Sump B) 11bewasheddown would=V mto swv.ma 1,31Bft0 3
7/8/2009
..aAk Area where small fiberglass washed down to lower containment outside the secondary shield wall would transport (Loop 4 LBLOCA Single Train Sump B)
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7/8/2009 Preliminary Average Velocity and Turbulence for Small Pieces of Fiberglass Debris Washed Down Outside Secondary Shield Wall that do not Transport (5% of Small Fiberglass Debris 0O 20 80 Average Turbulence 0.00 12 ft2/s2 0 040 0 000 O0034
&5 CFDri/Ar M5 M3-el oln AverageVelocity =0.055 ft/s CFD Model of Flume Small Fiberglass Erosion Test 75 gpm sink 5
7/8/2009 Preliminary Flume Velocity and Turbulence 0.12 ft/s = 1.4 in/s 2 2 2 2 0.001 ft /s = 0.14 in /s Velocity Plan View TKE Plan View Ioty mentude Contours tuotoiend enely contours (in/s) (ins2) am am 0....3 M9 120 1. aim0 Q=02 0.00 *AM2 a=4 0.107 4.140 15.0 00.0 y
410.0
-3.0 02.2 47.4 72.0 9i.8 123.0 -. ,0 20.2 47.4 72J.0 070 120.0 Velocity Section View TKE Section View volcOty nogniude modtou0 0ojbilui0 energy 00000um (inls) 0 0 (in 1s )
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A.0 3.0 22.2 47.4 72.6 7.08 123A *0.0 222 47.4 7ITS 00 123J X X Preliminary Comparison of Comanche Peak Pool Velocity/Turbulence to Flume Velocity/Turbulence Comanche Peak Pool Alion Test Flume
- Average Velocity for Small
- Velocity:Approximately 0. 12 Pieces that do not Transport ft/s at sample basket
- Lower Containment: 0.056 ft/s
- Turbulence: Slightly less than
- Washed to Loop Bays: 0.075 ft/s 0.001 ft 2/s 2 at sample basket
- Washed outside Loop Bays: 0.055 ft/s
- Average Turbulence for Small Pieces that do not Transport 2 2
" Lower Containment 0.00068 ft /s 2 2
- Washed to Loop Bays: 0.00023 ft /s
- Washed outside Loop Bays: 0.0012 ft2/s2 6
7/8/2009 Conclusions
- The velocity in the flume during the erosion tests was approximately double the average velocity for which non-transporting pieces of small fiberglass in the Comanche Peak pool would be exposed.
- The turbulence in the flume during the erosion tests was approximately equal to the average turbulence for which non-transporting pieces of small fiberglass in the Comanche Peak pool would be exposed.
7