|
|
(3 intermediate revisions by the same user not shown) |
Line 2: |
Line 2: |
| | number = ML13059A181 | | | number = ML13059A181 |
| | issue date = 02/28/2013 | | | issue date = 02/28/2013 |
| | title = Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, (TAC Nos. MC4676 and MC4677) | | | title = Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, |
| | author name = Seawright J | | | author name = Seawright J |
| | author affiliation = Luminant Generation Co, LLC | | | author affiliation = Luminant Generation Co, LLC |
| | addressee name = Singal B K | | | addressee name = Singal B |
| | addressee affiliation = NRC/NRR/DORL/LPLIV | | | addressee affiliation = NRC/NRR/DORL/LPLIV |
| | docket = 05000445, 05000446 | | | docket = 05000445, 05000446 |
| | license number = NPF-087, NPF-089 | | | license number = NPF-087, NPF-089 |
| | contact person = Singal B K | | | contact person = Singal B |
| | case reference number = TAC MC4677, TAC MC4776 | | | case reference number = TAC MC4677, TAC MC4776 |
| | package number = ML13059A180 | | | package number = ML13059A180 |
| | document type = Slides and Viewgraphs, Meeting Briefing Package/Handouts | | | document type = Slides and Viewgraphs, Meeting Briefing Package/Handouts |
| | page count = 17 | | | page count = 17 |
| | project = TAC:MC4677, TAC:MC4776 | | | project = TAC:MC4676, TAC:MC4677, TAC:MC4776 |
| | stage = Meeting | | | stage = Meeting |
| }} | | }} |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:CPNPP GSI-191 ClosureFebruary 28, 20131 Purpose of the MeetingPurpose of the Meeting*To open plant specific discussions with the NRC regarding strainer testing "The licensee will discuss the Generic Safety Issue 191 (GSI-191) pump strainer test protocols for bypass and head loss testing and related topics for Comanche Peak Nuclear Power Plant, Units 1 d2Thliiidithdltttand 2. The licensee is considering a repeat head loss test to include newly identified debris source (fiberglass tape) and would like to discuss the data extrapolation methods from previous testing to determine if the additional testing is needed." gg2 BackgroundBackground*CPNPP Strainer Testing -Generic Letter 2004-02 Supplemental Response, ER-ESP-001, Rev. 2, October 13, 2009 | | {{#Wiki_filter:CPNPP GSI-191 Closure February 28, 2013 1 |
| [ML093080003/ML093080004]*AldenLabsPrototypeStrainerFlumeTestingMarch2006*Alden Labs Prototype Strainer Flume Testing, March 2006*Alion Science and Technology Debris Transport Testing, August 2006*Alden Labs Strainer Flume Testing, March 2008NRCLetterdatedApril192010[ML100950564]*NRC Letter dated April 19, 2010 [ML100950564]*"The NRC staff has no further questions for CPNPP, Units 1 and 2, at this timeregarding completion of corrective actions or GL 2004-02. This conclusion is based on the staff's evaluation of your submittals, with emphasis on your responses to an NRC staff request for additional information dated July 15, 2009."3 BackgroundBackground*NEI Debris Preparation Protocol (January 30, 2012) [ML120481052 and ML120481057] *PCI Strainer Test Protocol *SFSS-TD-2011-001 Rev. 0, SURE-FLOW SUCTION STRAINER | | |
| -LARGE FLUME TEST PROTOCOL (LFTP) ELEMENT ISSUES & RESOLUTION, February 13, 2012 | | Purpose of the Meeting |
| *Plant Specific Decisions and Hold Points*CPNPPisevaluatingbypasstestinginatankversusaflumeCPNPP is evaluating bypass testing in a tank versus a flume*Contingent on a suitable test protocol and appropriate precedent4 Comparison to Recent TestingComparison to Recent Testing*Strainer Bypass Test Protocol -Tank Test Precedents*MHI(minimalfiber,LDFG)MHI (minimal fiber, LDFG)*STP (high fiber, LDFG) | | * To open plant specific discussions with the NRC regarding strainer testing The licensee will discuss the Generic Safety Issue 191 (GSI-191) pump strainer test protocols for bypass and head loss testing and related topics for Comanche Peak Nuclear Power Plant, Units 1 andd 2. |
| *Others ?StrainerBpassTestProtocolFlmeTestPrecedent*Strainer Bypass Test Protocol -Flume Test Precedent*Point Beach (Nukon, LDFG, Mineral wool, Cal-Sil, Asbestos)*CPNPP Plant specific debris issues (lead blanket covers and p(Glass 69 tape | | 2 The Th licensee li is i considering id i a repeatt h headd lloss ttestt tto include newly identified debris source (fiberglass tape) and would like to discuss the data extrapolation methods from previous testingg to determine if the additional testing g is needed. |
| *Lead blanket covers were included in previous testing*Glass 69 tape has not been tested (discovered after previous testing)*Similar to tapes and lead blanket cover materials previously 5tested | | 2 |
| *Quantity is much less than previously tested materials Fibrous DebrisFibrous Debris*Latent Fiber (surrogate -treated as Nukon)*Low Density Fiber Glass (surrogate -treated as Nukon)*Min-KFabric(surrogate-shreddedMin-Kfabric)MinK Fabric (surrogate shredded MinK fabric)*Lead Blanket Covers Gl69T*Glass 69 Tape ZOI Fibrous Debris Preparation: Processing, Storage and Handling, Rev. 1, January 2012 (aka NEI Debris Preparation g,,y(pProtocol) *Suitable for LDFG 6*Not suitable for lead blanket covers, Min-K or Glass 69 tape Typical-twoorthreelayersofBlanketCover:AlphaMaritexibly1'x4'Lancs40lbhightemperatureldFiberglassFabricimpregnatedwithsiliconeleadshieldingblanketsrubber7 WCAP-16727-NP Debris8 ProcessedthruProcessedthruchipper/shredder9 Headloss test -drain down without flow10Test 4 Headloss Headloss test -drain down completeSettled fines on top of interceptorinterceptor11Test 4 Headloss Tin powder and 1/64th inch paint chips can be seen on the debris interceptor. | | |
| Headloss test -drain down completeHeavier debris load on bottom half12Test 4 Headloss Test 4 Head Loss Extrapolation Curve Exponential -07497 ft0.7497 ft.Last 75 minutes of 10 hour test13 Head LossHead Loss*The extrapolated debris head loss for 30 days (T=2,592,000 sec) using the exponential curve fit is 0.7497 ft of water*The maximum total strainer head loss due to the design basis debrisloadextrapolatedto30daysat212°Fis155feetdebris load extrapolated to 30 days at 212 F is 1.55 feet. *This extrapolation showed a conservative minimum NPSHa margin of 5 feet at 30 days.*Transport testing of intact tapes and labels showed settling before the strainer.*Head loss testing assumed 200 sq. ft. of blocked strainer (approx. | | ===Background=== |
| 5%)14 Gl69TSth69GlGlass69TapeScotch 69 Glass Cloth Electrical Tape is a white glass tape with a high temperature thermosettingsiliconeadhesivethermosetting silicone adhesive 15 Glass 69 TapeGlass 69 Tape*There are similarities between the Glass 69 tape and the blanket covers (e.g. embedded fiber in chemical and temperature (gpresistance materials)*Comanche Peak is considering using the same debris preparation methodfortheGlass69tapeaswasusedfortheblanketcoversmethod for the Glass 69 tape as was used for the blanket covers*An alternative could be to use an equivalent quantity of Nulkonas a surrogate for the tape *Transport testing for blockage and head loss could be performed separately or as part of an integrated head loss test16 OptionsOptions*Perform Bypass Testing in a Tank*Plant specific debris issues*Limited precedent | | * CPNPP Strainer Testing - Generic Letter 2004-02 Supplemental Response, ER-ESP-001, Rev. 2, October 13, 2009 |
| *Protocols critical to acceptable results | | [ML093080003/ML093080004] |
| *SeparatetransporttestingrequiredforGlass69tapeSeparate transport testing required for Glass 69 tape *Perform Bypass Testing in a Flume*CFD requiredUdtdtliiiddd*Understood protocol, prior experience, issues addressed.*Prototypical | | * Alden Labs Prototype Strainer Flume Testing Testing, March 2006 |
| *Conservative | | * Alion Science and Technology Debris Transport Testing, August 2006 |
| *Would include transport and head loss testing of Glass 69 pgtape*. Questions and/or Comments?17 | | * Alden Labs Strainer Flume Testing, March 2008 |
| }} | | * NRC Letter dated April 1919, 2010 [ML100950564] |
| | * The NRC staff has no further questions for CPNPP, Units 1 and 2, at this time regarding completion of corrective actions or GL 2004-02. This conclusion is based on the staff's evaluation of your submittals, with emphasis on your responses to an NRC staff request for additional information dated July 15, 2009. |
| | 3 |
| | |
| | ===Background=== |
| | * NEI Debris Preparation Protocol (January 30, 2012) [ML120481052 and ML120481057] |
| | * PCI Strainer Test Protocol |
| | * SFSS-TD-2011-001 Rev. 0, SURE-FLOW SUCTION STRAINER |
| | - LARGE FLUME TEST PROTOCOL (LFTP) ELEMENT ISSUES & |
| | RESOLUTION, February 13, 2012 |
| | * Plant Specific Decisions and Hold Points |
| | * CPNPP is evaluating bypass testing in a tank versus a flume |
| | * Contingent on a suitable test protocol and appropriate precedent 4 |
| | |
| | Comparison to Recent Testing |
| | * Strainer Bypass Test Protocol - Tank Test Precedents |
| | * MHI (minimal fiber, LDFG) |
| | * STP (high fiber, LDFG) |
| | * Others ? |
| | * Strainer B Bypass pass Test Protocol - Flume Fl me Test Precedent |
| | * Point Beach (Nukon, LDFG, Mineral wool, Cal-Sil, Asbestos) |
| | * CPNPP Plant specific p debris issues ((lead blanket covers and Glass 69 tape |
| | * Lead blanket covers were included in previous testing |
| | * Glass 69 tape has not been tested (discovered after previous testing) |
| | * Similar to tapes and lead blanket cover materials previously tested |
| | * Quantity is much less than previously tested materials 5 |
| | |
| | Fibrous Debris |
| | * Latent Fiber (surrogate - treated as Nukon) |
| | * Low Density Fiber Glass (surrogate - treated as Nukon) |
| | * Min Min-KK Fabric (surrogate - shredded Min-K Min K fabric) |
| | * Lead Blanket Covers |
| | * Glass Gl 69 T Tape ZOI Fibrous Debris Preparation: Processing, Storage and Handling,g, Rev. 1,, Januaryy 2012 (aka |
| | ( NEI Debris Preparation p |
| | Protocol) |
| | * Suitable for LDFG |
| | * Not suitable for lead blanket covers, Min-K or Glass 69 tape 6 |
| | |
| | Typical - two Blanket Cover: |
| | or three AlphaMaritex layers y of Fiberglass ib l 1x4 Lancs Fabric 40 lb high impregnated temperature with silicone l d lead rubber shielding blankets 7 |
| | |
| | WCAP-16727-NP Debris 8 |
| | |
| | Processed thru chipper/shredder 9 |
| | |
| | Headloss test - drain down without flow Test 4 Headloss 10 |
| | |
| | Headloss test - drain down complete Settled fines on top of interceptor Test 4 Headloss Tin powder and 1/64th inch paint chips can be seen 11 on the debris interceptor. |
| | |
| | Headloss test - drain down complete Heavier debris load on bottom half Test 4 Headloss 12 |
| | |
| | Test 4 Head Loss Extrapolation Curve Exponential - |
| | 0 7497 ft 0.7497 ft. |
| | Last 75 minutes of 10 hour test 13 |
| | |
| | Head Loss |
| | * The extrapolated debris head loss for 30 days (T=2,592,000 sec) using the exponential curve fit is 0.7497 ft of water |
| | * The maximum total strainer head loss due to the design basis debris load extrapolated to 30 days at 212 °F F is 1.55 1 55 feet feet. |
| | * This extrapolation showed a conservative minimum NPSHa margin of 5 feet at 30 days. |
| | * Transport testing of intact tapes and labels showed settling before the strainer. |
| | * Head loss testing assumed 200 sq. ft. of blocked strainer (approx. |
| | 5%) |
| | 14 |
| | |
| | Gl Glass 69 Tape T Scotch S t h 69 Gl Glass Cloth Electrical Tape is a white glass tape with a high temperature thermosetting silicone adhesive 15 |
| | |
| | Glass 69 Tape |
| | * There are similarities between the Glass 69 tape and the blanket covers ((e.g. |
| | g embedded fiber in chemical and temperature p |
| | resistance materials) |
| | * Comanche Peak is considering using the same debris preparation method for the Glass 69 tape as was used for the blanket covers |
| | * An alternative could be to use an equivalent quantity of Nulkon as a surrogate for the tape |
| | * Transport testing for blockage and head loss could be performed separately or as part of an integrated head loss test 16 |
| | |
| | Options |
| | * Perform Bypass Testing in a Tank |
| | * Plant specific debris issues |
| | * Limited precedent |
| | * Protocols critical to acceptable results |
| | * Separate transport testing required for Glass 69 tape |
| | * Perform Bypass Testing in a Flume |
| | * CFD required |
| | * Understood U d t d protocol,t l prior i experience, i iissues addressed. |
| | dd d |
| | * Prototypical |
| | * Conservative |
| | * Would include transport p and head loss testing g of Glass 69 tape |
| | *. Questions and/or Comments? |
| | 17}} |
Letter Sequence Meeting |
---|
|
|
MONTHYEARRS-04-148, Amergen/Exelon Nuclear, Summary of Teleconference Regarding Implementation of Revised Emergency Action Levels2004-10-0101 October 2004 Amergen/Exelon Nuclear, Summary of Teleconference Regarding Implementation of Revised Emergency Action Levels Project stage: Request ML0429402292004-10-26026 October 2004 Untis 2 & 3, LaSalle Units 1& 2, Limerick Units 1 & 2, Oyster Creek, Peach Bottom Units 2 & 3, Quad Cities Units 1 & 2, Three Mile Island - Staff Comments on Summary of Conference Call Project stage: Other ML0603903012006-02-0909 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 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 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 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 ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing 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 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 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 ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, Project stage: Meeting ML13059A2022013-02-28028 February 2013 Email Licensee Slides for 2/28/13 Meeting Via Conference Call 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 2009-07-22
[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
[Table view] Category:Meeting Briefing Package/Handouts
MONTHYEARML23215A1922023-08-0707 August 2023 August 7, 2023 Presubmittal Meeting Presentation - Relocation of Technical Specification 3.9.3 Nuclear Instrumentation to a Licensee Controlled Document (EPID: L?2023?LRM-0052) ML23215A1652023-08-0404 August 2023 August 8, 2023 Presubmittal Meeting Presentation - Technical Specification 3.8.1 AC Sources - Operating Required Action B.4, 14-hour Completion Time (EPID: L?2023?LRM-0053) ML23094A2722023-04-0606 April 2023 April 6, 2023 Presubmittal Meeting Presentation - Extension Request for Thermal Relief Valves (EPID: L?2023?LRM-0023) ML23081A0252023-03-22022 March 2023 March 28, 2023 Pre-submittal Meeting Presentation - LAR for Exception to RG 1.81 (EPID L?2023?LRM-0015) ML23045A1552023-02-14014 February 2023 Public Meeting February 23, 2023 - Presentation Slides ML23011A0872023-01-10010 January 2023 License Renewal Scoping Meeting, Comanche Peak Nuclear Power Plant, Units 1 and 2 - Meeting Slides ML22140A1082022-05-31031 May 2022 (CPNPP) First License Renewal (60 Years) Application Pre-Application Submittal Meeting 2, Meeting Slides ML21259A0312021-09-30030 September 2021 Initial License Renewal Pre-Application Submittal Meeting Sept 2021 - Safety ML21259A0292021-09-16016 September 2021 Initial License Renewal - NRC Presubmittal Meeting Slides - Safety ML21259A0352021-09-16016 September 2021 License Renewal Pre-Application Submittal Meeting Sept 2021 Environmental Report ML21259A0332021-09-16016 September 2021 Initial License Renewal Application - NRC Presubmittal Meeting Slides - Environmental ML21097A0522021-04-0707 April 2021 NRC Talking Points - 4/7/2021 Meeting with Vistra Operations Company LLC Proposed COVID-19 Related Exemption Request to Defer the Annual Force-on-Force Exercise for Comanche Peak ML21068A0292021-03-0909 March 2021 Presentation - 3/24/2021 Meeting with Vistra Operations Company LLC Proposed License Amendment Request to Adopt TSTF-505, Revision 2, to Provide Risk-Informed Extended Completion Times at Comanche Peak Nuclear Power Plant, Unit Nos. 1 and 2 ML21007A2562021-01-12012 January 2021 Luminant-CPNPP License Renewal SAMA January 12 2021 Public Mtg ML20314A3422020-11-12012 November 2020 NRC Teleconference with Comanche Peak Regarding a Proposed Exigent License Amendment Request (LAR) 20-007 TS 3.7.8 Station Service Water System TS 3.8.1 AC Sources - Operating ML20097B2852020-04-0606 April 2020 April 7, 2020, Presubmittal Teleconference Discussion Topics - Proposed Relief Requests for Deferral of Several Inspections and Tests from 2RF18 (Spring 2020) to 2RF19 (Fall 2021) ML20097C2662020-04-0606 April 2020 April 6, 2020, Presubmittal Teleconference Presentation - License Amendment Request Revise Technical Specification 5.5.9 ML20036D4102020-02-12012 February 2020 Pre-Submittal Meeting for: Comanche Peak Nuclear Power Plant Docket Nos. 50-445 and 50-446 February 12, 2020 - License Amendment Request for Changes to Certain Emergency Action Levels ML19296D5592019-10-24024 October 2019 Pre-Submittal Meeting with NRC for Proposed License Amendment Request (LAR) 15-001 TS 3.8.1, AC Sources - Operating, Presentation ML14077A2872014-03-18018 March 2014 Transcript of the 612th ACRS Meeting, March 6, 2014 (Open) Pages 1-317 ML13059A1812013-02-28028 February 2013 Licensee Slides for 2/28/13 Meeting Via Conference Call with Luminant Generation Company, LLC, ML12328A1252012-11-20020 November 2012 Licensee Slides from 11/20/12 Pre-Submittal Meeting to Discuss LAR for Spent Fuel Criticality ML12229A5042012-09-19019 September 2012 8/6/2012 Summary of Conference Call with Luminant to Discuss Proposed License Amendment Request to Revise Technical Specification 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 ML12236A3322012-08-23023 August 2012 Non-proprietary - Presentation for September 13, 2012, Proposed License Amendment Request for Spend Fuel Pool Criticality Analysis ML12188A6972012-07-18018 July 2012 6/26/12 Summary of Meeting with Luminant Generation Company LLC to Discuss Proposed License Amendment Request to Revise TS 3.8.1, AC Sources - Operating, to Support Installation of Backup Transformer at Comanche Peak, Units 1 and 2 (TAC ME8 ML12156A2052012-05-31031 May 2012 Presentation to NRC for LAR 12 ML1125702582011-09-13013 September 2011 Licensee Slides from 9/13/11 Meeting with Luminant Generation Company, LLC Regarding Proposed License Amendment Request for Risk-Informed Technical Specification Task Force Initiative... ML1114003142011-05-19019 May 2011 Summary of Public Meeting with Luminant Generation Company on Comanche Peak Nuclear Power Plant, Units 1 and 2, to Discuss 2010 End of Cycle Performance Assessment ML0924401642009-09-14014 September 2009 Meeting Summary, Pre-Application Meeting on with Luminant Generation Company LLC to Dicuss Future Amendment Request to Revise Comanche Peak Units 1 and 2 Startup Transformer Completion Times ML0919400842009-07-0909 July 2009 Luminant RAI 22 and 23 SBLOCA, Vortex, Air Ingestion, Void Fraction and Flashing Issues ML0919402772009-07-0909 July 2009 Luminant Holistic Overview: Presentation Will Cover Information Related to RAIs 1 - 5, 7, 12 - 14,16 - 19, 21, 25 - 36 and Overall Response to GL 2004-02 ML0919400832009-07-0909 July 2009 Pci RAI 8, Test Protocol, Erosion Issue, RAI 15, Test Protocol, Latent Fiber Issue, Areva RAI 20, Test Flume, Fiberglass Larges Question ML0919400852009-07-0909 July 2009 Luminant RAI 24 and 37, Secondary Line Breaks, Debris Load and Testing ML0919604492009-07-0808 July 2009 Alion Meeting Presentations on RAI 9 - Pool Fill Transport, & RAI 6 - Fiber Erosion Testing ML0828204232008-10-0707 October 2008 Meeting Handout - Comanche Peak Col Application Public Orientation Meeting ML0817100272008-06-12012 June 2008 Second Handout for Comanche Peak Public Outreach Meeting on June 12, 2008 ML0816201432008-06-10010 June 2008 End-of-Cycle Meeting Summary 6/5/08 ML0729204682007-10-29029 October 2007 09/25/2007, Summary of Meeting Between the U.S. Nuclear Regulatory Commission Staff and Strategic Teaming and Resource Sharing Representatives to Discuss License Renewal Activities ML0717200702007-06-20020 June 2007 Summary of Meeting with Txu Power Regarding Comanche Peak Steam Electric Stations End-of-Cycle Assessment for 2006 ML0720101702007-05-23023 May 2007 Enclosure 3 - 5/23/07 P.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0720101742007-05-23023 May 2007 Enclosure 2 - 5/23/07 A.M. Meeting Slides - Comanche Peak Steam Electric Station, Units 1 and 2 - Summary of Meeting Held on 5/23/07 with Txu Generation Company LP to Discuss the Plans for Methodology Transition and Power Uprate ML0707202502006-12-12012 December 2006 12/12-13/2006 Slides, Txu Power Comanche Peak Site, NRC Onsite Review, Site Geotechnical Investigation Activities. ML0435101002004-11-10010 November 2004 Meeting Slides - Nrc/Stars Plant Aging Management Center of Business Meeting ML0330402882003-10-30030 October 2003 Meeting Handout Materials Regarding STARS-IRAG/NRC Meeting to Discuss Topics Taken from the June 10.11, 2003, Workshop ML0324812782003-09-10010 September 2003 Agenda and Handout for Public Meeting Between NRC and Firstenergy Nuclear Operating Company Davis-Besse Nuclear Power Station ML0319206482003-06-10010 June 2003 Meeting Handouts for STARS-IRAG/NRC Workshop to Discuss Selected Topics Listed in the Agenda Attached to Meeting Notice ML0234504632002-12-10010 December 2002 05000445; Txu Energy, Comanche Peak, Public Exit Meeting - December 10, 2002-Licensee Handouts ML0231200242002-11-0707 November 2002 Meeting Handouts - Meeting with Strategic Teaming and Resources Sharing - Integrated Regulatory Affairs Group ML0208705662002-04-15015 April 2002 Meetingsummary with Stars and the NRC to Inform the NRC About Current Stars Activities ML0208107562002-03-19019 March 2002 Operator Licensing Workshop Meeting Summary 2023-08-07
[Table view] |
Text
CPNPP GSI-191 Closure February 28, 2013 1
Purpose of the Meeting
- To open plant specific discussions with the NRC regarding strainer testing The licensee will discuss the Generic Safety Issue 191 (GSI-191) pump strainer test protocols for bypass and head loss testing and related topics for Comanche Peak Nuclear Power Plant, Units 1 andd 2.
2 The Th licensee li is i considering id i a repeatt h headd lloss ttestt tto include newly identified debris source (fiberglass tape) and would like to discuss the data extrapolation methods from previous testingg to determine if the additional testing g is needed.
2
Background
[ML093080003/ML093080004]
- Alden Labs Prototype Strainer Flume Testing Testing, March 2006
- Alion Science and Technology Debris Transport Testing, August 2006
- Alden Labs Strainer Flume Testing, March 2008
- NRC Letter dated April 1919, 2010 [ML100950564]
- The NRC staff has no further questions for CPNPP, Units 1 and 2, at this time regarding completion of corrective actions or GL 2004-02. This conclusion is based on the staff's evaluation of your submittals, with emphasis on your responses to an NRC staff request for additional information dated July 15, 2009.
3
Background
- NEI Debris Preparation Protocol (January 30, 2012) [ML120481052 and ML120481057]
- PCI Strainer Test Protocol
- SFSS-TD-2011-001 Rev. 0, SURE-FLOW SUCTION STRAINER
- LARGE FLUME TEST PROTOCOL (LFTP) ELEMENT ISSUES &
RESOLUTION, February 13, 2012
- Plant Specific Decisions and Hold Points
- CPNPP is evaluating bypass testing in a tank versus a flume
- Contingent on a suitable test protocol and appropriate precedent 4
Comparison to Recent Testing
- Strainer Bypass Test Protocol - Tank Test Precedents
- MHI (minimal fiber, LDFG)
- Strainer B Bypass pass Test Protocol - Flume Fl me Test Precedent
- Point Beach (Nukon, LDFG, Mineral wool, Cal-Sil, Asbestos)
- CPNPP Plant specific p debris issues ((lead blanket covers and Glass 69 tape
- Lead blanket covers were included in previous testing
- Glass 69 tape has not been tested (discovered after previous testing)
- Similar to tapes and lead blanket cover materials previously tested
- Quantity is much less than previously tested materials 5
Fibrous Debris
- Latent Fiber (surrogate - treated as Nukon)
- Low Density Fiber Glass (surrogate - treated as Nukon)
- Min Min-KK Fabric (surrogate - shredded Min-K Min K fabric)
- Glass Gl 69 T Tape ZOI Fibrous Debris Preparation: Processing, Storage and Handling,g, Rev. 1,, Januaryy 2012 (aka
( NEI Debris Preparation p
Protocol)
- Not suitable for lead blanket covers, Min-K or Glass 69 tape 6
Typical - two Blanket Cover:
or three AlphaMaritex layers y of Fiberglass ib l 1x4 Lancs Fabric 40 lb high impregnated temperature with silicone l d lead rubber shielding blankets 7
WCAP-16727-NP Debris 8
Processed thru chipper/shredder 9
Headloss test - drain down without flow Test 4 Headloss 10
Headloss test - drain down complete Settled fines on top of interceptor Test 4 Headloss Tin powder and 1/64th inch paint chips can be seen 11 on the debris interceptor.
Headloss test - drain down complete Heavier debris load on bottom half Test 4 Headloss 12
Test 4 Head Loss Extrapolation Curve Exponential -
0 7497 ft 0.7497 ft.
Last 75 minutes of 10 hour1.157407e-4 days <br />0.00278 hours <br />1.653439e-5 weeks <br />3.805e-6 months <br /> test 13
Head Loss
- The extrapolated debris head loss for 30 days (T=2,592,000 sec) using the exponential curve fit is 0.7497 ft of water
- The maximum total strainer head loss due to the design basis debris load extrapolated to 30 days at 212 °F F is 1.55 1 55 feet feet.
- This extrapolation showed a conservative minimum NPSHa margin of 5 feet at 30 days.
- Transport testing of intact tapes and labels showed settling before the strainer.
- Head loss testing assumed 200 sq. ft. of blocked strainer (approx.
5%)
14
Gl Glass 69 Tape T Scotch S t h 69 Gl Glass Cloth Electrical Tape is a white glass tape with a high temperature thermosetting silicone adhesive 15
Glass 69 Tape
- There are similarities between the Glass 69 tape and the blanket covers ((e.g.
g embedded fiber in chemical and temperature p
resistance materials)
- Comanche Peak is considering using the same debris preparation method for the Glass 69 tape as was used for the blanket covers
- An alternative could be to use an equivalent quantity of Nulkon as a surrogate for the tape
- Transport testing for blockage and head loss could be performed separately or as part of an integrated head loss test 16
Options
- Perform Bypass Testing in a Tank
- Plant specific debris issues
- Protocols critical to acceptable results
- Separate transport testing required for Glass 69 tape
- Perform Bypass Testing in a Flume
- Understood U d t d protocol,t l prior i experience, i iissues addressed.
dd d
- Would include transport p and head loss testing g of Glass 69 tape
- . Questions and/or Comments?
17