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| {{#Wiki_filter:il5 , a NRC -Luminant Power Public Meeting Comanche Peak Nuclear Power Plant Secondary Line Breaks July 9th 2009 Secondary Line Breaks* Containment Spray provides containment heat removal -maximum 10 hour mission time for equipment qualification. | | {{#Wiki_filter:a il5 , |
| Decay heat removal is by the secondary systems (not by ECCS, i.e., 50.46)* GDC-38 and GDC-41 do not apply Containment Spray is not credited for Part 100 RG 1.82 R3" "Some PWRs may require recirculation from the sump for licensing basis events other than LOCAs. Therefore, plants should review the licensing basis and include potential break locations in the main steam and main feedwater lines as well in determining the most limiting conditions for sump operation."* GDC-4 is the Comanche Peak licensing basis for secondary line breaks* CPNPP elected to evaluate sump performance using the same break selection criteria as for LOCA.Comparison of Fiber Load Fibrous MSLB (lbs) Prototype (lbs) LOCA (lbs) Bounded Latent Fiber 24 30 24 Yes LDFG Fines 42.6 53.8 Yes LDFG Smalls 160 540.75 183 Yes LDFG Large 18.4 LDFG Intact 18.6 Kaowool 353.6 448.8 Prototype Sil-temp 52.4 71.4 Prototype Min-K 12.96 8 1.6 No Covers 27.2 Total 645.6 1099 218.8 Prototype Comparison of Particulate Load MSLB (lbs) Prototype (lbs) LOCA (lbs) Bounded Dirt/Dust 136 170 136 Yes Min-K Fines 52.16 34.3 lbs 6.72 No Acceptable Epoxy 217.5 3860.9 262.9 Yes Acceptable IOZt 366.9 267.5 376 Yes Unqualified Epoxy 2838 (6 mil) 12920 lbs as 2838 (6 mil) Yes.(outside ZOI) particulate fines (walnut shells)Unqualified IOZ Yes (outside ZOI) 16834 25634 16834 Unqualified Alkyd Yes (outside ZOI) 104 992 104 Total 20, 549 43,879 20,557.6 Yes Prototype (small flume) Testing* Ultra-Conservative test temperature | | NRC - Luminant Power Public Meeting Comanche Peak Nuclear Power Plant Secondary Line Breaks July 9th 2009 Secondary Line Breaks |
| -< 50 F" Fiberglass fibers settle in 20 to 60 minutes in 50 F water versus 20 to 30 seconds in 120 F water[NUREG/CR-2982, "...water temperature has a paramount effect on buoyancy..."] | | *Containment Spray provides containment heat removal - maximum 10 hour mission time for equipment qualification. |
| * Tests conducted at 128 F and 169 F confirmed the effect on settling of fiberglass | | Decay heat removal is by the secondary systems (not by ECCS, i.e., 50.46) |
| [Test Report No. ITR-92-03N]* MSLB Head Loss -Small Flume 0.005 ft. (0.0044 fps)* LOCA Head Loss -Small Flume 0.4682 ft. (0.0073 fps)* LOCA Head Loss -Large Flume 0.6 ft. (0.0073 fps)RAI 13 Conclusion | | * GDC-38 and GDC-41 do not apply Containment Spray is not credited for Part 100 |
| * Debris Generation and Transport analyses were performed consistent with the SER for NEI 04-07" Prototype testing showed that LOCA debris loads and conditions bounded the secondary break head loss" Large flume testing under the March 2008 protocol confirmed the the small flume test protocol was conservative for this case" CPNPP has provided reasonable asurrance, that the Containment Spray System wil perform its design function for secondary line breaks}} | | |
| | RG 1.82 R3 |
| | " "Some PWRs may require recirculation from the sump for licensing basis events other than LOCAs. Therefore, plants should review the licensing basis and include potential break locations in the main steam and main feedwater lines as well in determining the most limiting conditions for sump operation." |
| | * GDC-4 is the Comanche Peak licensing basis for secondary line breaks |
| | * CPNPP elected to evaluate sump performance using the same break selection criteria as for LOCA. |
| | Comparison of Fiber Load Fibrous MSLB (lbs) Prototype (lbs) LOCA (lbs) Bounded Latent Fiber 24 30 24 Yes LDFG Fines 42.6 53.8 Yes LDFG Smalls 160 540.75 183 Yes LDFG Large 18.4 LDFG Intact 18.6 Kaowool 353.6 448.8 Prototype Sil-temp 52.4 71.4 Prototype Min-K 12.96 8 1.6 No Covers 27.2 Total 645.6 1099 218.8 Prototype |
| | |
| | Comparison of Particulate Load MSLB (lbs) Prototype (lbs) LOCA (lbs) Bounded Dirt/Dust 136 170 136 Yes Min-K Fines 52.16 34.3 lbs 6.72 No Acceptable Epoxy 217.5 3860.9 262.9 Yes Acceptable IOZt 366.9 267.5 376 Yes Unqualified Epoxy 2838 (6 mil) 12920 lbs as 2838 (6 mil) Yes. |
| | (outside ZOI) particulate fines (walnut shells) |
| | Unqualified IOZ Yes (outside ZOI) 16834 25634 16834 Unqualified Alkyd Yes (outside ZOI) 104 992 104 Total 20, 549 43,879 20,557.6 Yes Prototype (small flume) Testing |
| | * Ultra-Conservative test temperature - < 50 F |
| | " Fiberglass fibers settle in 20 to 60 minutes in 50 F water versus 20 to 30 seconds in 120 F water |
| | [NUREG/CR-2982, "...water temperature has a paramount effect on buoyancy..."] |
| | * Tests conducted at 128 F and 169 F confirmed the effect on settling of fiberglass [Test Report No. ITR-92-03N] |
| | * MSLB Head Loss - Small Flume 0.005 ft. (0.0044 fps) |
| | * LOCA Head Loss - Small Flume 0.4682 ft. (0.0073 fps) |
| | * LOCA Head Loss - Large Flume 0.6 ft. (0.0073 fps) |
| | |
| | ===RAI 13=== |
| | |
| | Conclusion |
| | * Debris Generation and Transport analyses were performed consistent with the SER for NEI 04-07 |
| | " Prototype testing showed that LOCA debris loads and conditions bounded the secondary break head loss |
| | " Large flume testing under the March 2008 protocol confirmed the the small flume test protocol was conservative for this case |
| | " CPNPP has provided reasonable asurrance, that the Containment Spray System wil perform its design function for secondary line breaks}} |
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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] |
Text
a il5 ,
NRC - Luminant Power Public Meeting Comanche Peak Nuclear Power Plant Secondary Line Breaks July 9th 2009 Secondary Line Breaks
- Containment Spray provides containment heat removal - maximum 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> mission time for equipment qualification.
Decay heat removal is by the secondary systems (not by ECCS, i.e., 50.46)
RG 1.82 R3
" "Some PWRs may require recirculation from the sump for licensing basis events other than LOCAs. Therefore, plants should review the licensing basis and include potential break locations in the main steam and main feedwater lines as well in determining the most limiting conditions for sump operation."
- GDC-4 is the Comanche Peak licensing basis for secondary line breaks
- CPNPP elected to evaluate sump performance using the same break selection criteria as for LOCA.
Comparison of Fiber Load Fibrous MSLB (lbs) Prototype (lbs) LOCA (lbs) Bounded Latent Fiber 24 30 24 Yes LDFG Fines 42.6 53.8 Yes LDFG Smalls 160 540.75 183 Yes LDFG Large 18.4 LDFG Intact 18.6 Kaowool 353.6 448.8 Prototype Sil-temp 52.4 71.4 Prototype Min-K 12.96 8 1.6 No Covers 27.2 Total 645.6 1099 218.8 Prototype
Comparison of Particulate Load MSLB (lbs) Prototype (lbs) LOCA (lbs) Bounded Dirt/Dust 136 170 136 Yes Min-K Fines 52.16 34.3 lbs 6.72 No Acceptable Epoxy 217.5 3860.9 262.9 Yes Acceptable IOZt 366.9 267.5 376 Yes Unqualified Epoxy 2838 (6 mil) 12920 lbs as 2838 (6 mil) Yes.
(outside ZOI) particulate fines (walnut shells)
Unqualified IOZ Yes (outside ZOI) 16834 25634 16834 Unqualified Alkyd Yes (outside ZOI) 104 992 104 Total 20, 549 43,879 20,557.6 Yes Prototype (small flume) Testing
- Ultra-Conservative test temperature - < 50 F
" Fiberglass fibers settle in 20 to 60 minutes in 50 F water versus 20 to 30 seconds in 120 F water
[NUREG/CR-2982, "...water temperature has a paramount effect on buoyancy..."]
- Tests conducted at 128 F and 169 F confirmed the effect on settling of fiberglass [Test Report No. ITR-92-03N]
- MSLB Head Loss - Small Flume 0.005 ft. (0.0044 fps)
- LOCA Head Loss - Small Flume 0.4682 ft. (0.0073 fps)
- LOCA Head Loss - Large Flume 0.6 ft. (0.0073 fps)
RAI 13
Conclusion
- Debris Generation and Transport analyses were performed consistent with the SER for NEI 04-07
" Prototype testing showed that LOCA debris loads and conditions bounded the secondary break head loss
" Large flume testing under the March 2008 protocol confirmed the the small flume test protocol was conservative for this case
" CPNPP has provided reasonable asurrance, that the Containment Spray System wil perform its design function for secondary line breaks