|
|
(2 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 |
Line 19: |
Line 19: |
|
| |
|
| =Text= | | =Text= |
| {{#Wiki_filter:CPNPP GSI-191 ClosureFebruary 28, 2013 1 | | {{#Wiki_filter:CPNPP GSI-191 Closure February 28, 2013 1 |
| 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 d2Thliiidithdlttt an d 2. Th e li censee i s cons id er ing a repea t h ea d l oss t es t t o include newly identified debris source (fiberglass tape) and would like to discuss the data extrapolation methods from previous
| |
|
| |
|
| testin g to determine if the additional testin g is needed."
| | Purpose of the Meeting |
| gg 2 BackgroundBackground*CPNPP Strainer Testing -Generic Letter 2004-02 Supplemental Response, ER-ESP-001, Rev. 2, October 13, 2009
| | * 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=== |
| | * CPNPP Strainer Testing - Generic Letter 2004-02 Supplemental Response, ER-ESP-001, Rev. 2, October 13, 2009 |
| [ML093080003/ML093080004] | | [ML093080003/ML093080004] |
| *AldenLabsPrototypeStrainerFlumeTestingMarch2006
| | * Alden Labs Prototype Strainer Flume Testing Testing, March 2006 |
| *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] | | * Alion Science and Technology Debris Transport Testing, August 2006 |
| *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 | | * Alden Labs Strainer Flume Testing, March 2008 |
| -LARGE FLUME TEST PROTOCOL (LFTP) ELEMENT ISSUES & | | * 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 | | RESOLUTION, February 13, 2012 |
| *Plant Specific Decisions and Hold Points | | * Plant Specific Decisions and Hold Points |
| *CPNPPisevaluatingbypasstestinginatankversusaflume CPNPP is evaluating bypass testing in a tank versus a flume*Contingent on a suitable test protocol and appropriate precedent 4 | | * CPNPP is evaluating bypass testing in a tank versus a flume |
| Comparison to Recent TestingComparison to Recent Testing*Strainer Bypass Test Protocol -Tank Test Precedents | | * Contingent on a suitable test protocol and appropriate precedent 4 |
| *MHI(minimalfiber,LDFG) | | |
| MHI (minimal fiber, LDFG)*STP (high fiber, LDFG) | | Comparison to Recent Testing |
| *Others ?StrainerBpassTestProtocolFlmeTestPrecedent | | * Strainer Bypass Test Protocol - Tank Test Precedents |
| *Strainer B y pass Test Protocol -Fl u me Test Precedent*Point Beach (Nukon, LDFG, Mineral wool, Cal-Sil, Asbestos)*CPNPP Plant s p ecific debris issues (lead blanket covers and p(Glass 69 tape | | * MHI (minimal fiber, LDFG) |
| *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 5 tested | | * STP (high fiber, LDFG) |
| *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) | | * Others ? |
| *Min-KFabric(surrogate | | * Strainer B Bypass pass Test Protocol - Flume Fl me Test Precedent |
| -shreddedMin | | * Point Beach (Nukon, LDFG, Mineral wool, Cal-Sil, Asbestos) |
| -Kfabric)Min K Fabric (surrogate shredded Min K fabric)*Lead Blanket Covers Gl69T*Gl ass 69 T ape ZOI Fibrous Debris Preparation: Processing, Storage and Handlin g, Rev. 1 , Januar y 2012 (aka NEI Debris Pre p aration g,,y(p Protocol) *Suitable for LDFG 6*Not suitable for lead blanket covers, Min-K or Glass 69 tape Typical-twoorthreela yersofBlanketCover:AlphaMaritexibl y1'x4'Lancs40lbhightemperatureld F iberg l assFabricimpregnatedwithsiliconel ea dshieldingblankets rubber 7 WCAP-16727-NP Debris 8 | | * CPNPP Plant specific p debris issues ((lead blanket covers and Glass 69 tape |
| Processed thruProcessedthruchipper/shredder 9 | | * Lead blanket covers were included in previous testing |
| Headloss test -drain down without flow 10Test 4 Headloss Headloss test -drain down complete Settled fines on top of interceptor interceptor 11Test 4 Headloss Tin powder and 1/64th inch paint chips can be seen on the debris interceptor. | | * Glass 69 tape has not been tested (discovered after previous testing) |
| Headloss test -drain down complete Heavier debris load on bottom half 12Test 4 Headloss Test 4 Head Loss Extrapolation Curve Exponential -07497 ft 0.7497 ft.Last 75 minutes of 10 hour test 13 Head Loss 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 wate r*The maximum total strainer head loss due to the design basis debrisloadextrapolatedto30daysat212 | | * Similar to tapes and lead blanket cover materials previously tested |
| °Fis155feet debris 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.
| | * 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 |
|
| |
|
| 5%)14 Gl 69 TSth69Gl Gl ass69T ape S co t c h 69 Gl ass Cloth Electrical Tape is a white glass tape with a high temperature thermosettingsiliconeadhesive thermosetting 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 tem p erature (gp resistance materials)*Comanche Peak is considering using the same debris preparation methodfortheGlass69tapeaswasusedfortheblanket covers method 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 test 16 Options Options*Perform Bypass Testing in a Tank*Plant specific debris issues*Limited precedent
| | Glass 69 Tape |
| *Protocols critical to acceptable results
| | * 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 |
|
| |
|
| *SeparatetransporttestingrequiredforGlass69tape Separate transport testing required for Glass 69 tape *Perform Bypass Testing in a Flume*CFD requiredUdtdtliiiddd | | Options |
| *U n d ers t oo d pro t oco l , pr i or exper i ence, i ssues a dd resse d.*Prototypical | | * Perform Bypass Testing in a Tank |
| *Conservative | | * Plant specific debris issues |
| *Would include trans p ort and head loss testin g of Glass 69 pg tape*. Questions and/or Comments? | | * 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}} | | 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