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MONTHYEARML1202501052012-01-25025 January 2012 Licensee Slides for 1/26/12 Meeting Three Mile Island, Unit 1 - Summary of Tube to Tube Wear Identified During T1R19 (Fall 2011) Project stage: Request ML1202501112012-01-25025 January 2012 Licensee Slides Arkansas Nuclear One, Unit 1 - Steam Generators Tube to Tube Wear Project stage: Request ML1202704162012-02-13013 February 2012 1/26/2012 - Summary of Meeting with Entergy and Exelon to Discuss Recent Once-Through Steam Generator Inservice Inspection Results Project stage: Meeting 2012-01-25
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MONTHYEARML24040A0722024-02-13013 February 2024 – Energy Solution Feb 13 Pubic Meeting Slides on TMI-2 Decommissioning ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML19161A2572019-06-0404 June 2019 BWR Fleet Msv/Srv - Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML19022A2002019-01-23023 January 2019 Request for Use of ASME Code Case N-879 for Exelon Nuclear Power Plants ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML17142A2382017-05-25025 May 2017 OEDO-17-00280 - Briefing Package for Drop-In Visit on June 9, 2017, by Senior Management of Exelon Generation Company, LLC with Chairman Svinicki, Commissioner Baran, and Commissioner Burns ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16075A3292016-03-16016 March 2016 OEDO-16-00165 - Briefing Package for Drop-In Visit on March 23, 2016, by Senior Management of Exelon Generation Company, LLC with the NRC Executive Director for Operations ML15327A0812015-11-0909 November 2015 Fall 2015 Outage Call Regarding the Steam Generator Tube Inservice Inspections - Slides ML15238B6272015-08-26026 August 2015 Case Study Overview ML14300A5452014-10-30030 October 2014 10/30/2014, Meeting Slide with NRC Regarding GL 2004-02 Close Out for Three Mile Island, Unit 1 ML13262A1492013-09-19019 September 2013 Enclosure 3- NRC Presentation Handout ML13262A1172013-08-28028 August 2013 Enclosure 4 - Scott Portzline Presentation ML12262A3352012-09-13013 September 2012 9.13.2012 TMI Alert Presentation Nreg 0654 Public Mtg ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1202501052012-01-25025 January 2012 Licensee Slides for 1/26/12 Meeting Three Mile Island, Unit 1 - Summary of Tube to Tube Wear Identified During T1R19 (Fall 2011) ML1115901302011-06-0808 June 2011 NRC Slides - TMI Public Meeting, June 7, 2011 ML11090A0872011-04-0505 April 2011 Fire (a)(4) Tabletop Pilot Method and Results ML1007802632010-01-25025 January 2010 Presentation - Health Physics Society Mid-Year Meeting ML1007805052009-12-23023 December 2009 Executive Team Daily Brief ML1007805442009-12-0202 December 2009 Executive Team Daily Brief ML1007805412009-11-27027 November 2009 Executive Team Daily Brief ML1007805402009-11-25025 November 2009 Executive Team Daily Brief ML1007805062009-11-24024 November 2009 Executive Team Daily Brief ML0929406112009-11-0202 November 2009 Summary of Category 1 Public Meeting with Exelon to Discuss Proposed Control Rod Drive Control System License Amendment Request ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0910702242009-04-17017 April 2009 Riv Regional Administrator Presentation at Texas A&M University March 30, 2009, Three Mile Island - Impact on Safety Perspectives and Safety Belief ML0907508342009-03-16016 March 2009 Meeting Slides, Three Mile Island Annual Assessment Meeting 2008 Reactor Oversight Process ML0906302662009-02-24024 February 2009 02/24/2009 Three Mile Island Nuclear Station, Unit 1, Dseis Meeting Presentation Slides Preliminary Results of the Three Mile Island Nuclear Station, Unit 1 License Renewal Environmental Review. 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MONTHYEARML24296B2132024-10-22022 October 2024 Slides for October 25, 2024, Meeting on Crane Clean Energy Center Regulatory Path to Restoring the Operating Reactor License Basis ML24040A0722024-02-13013 February 2024 – Energy Solution Feb 13 Pubic Meeting Slides on TMI-2 Decommissioning ML22301A1402022-10-28028 October 2022 1993 TMI Event - Jure Kutlesa, Security Specialist ML20178A4202020-06-30030 June 2020 NEI Slides for June 30, 2020, Public Meeting on COVID-19 Response ML20170B0212020-06-23023 June 2020 NRC Pre-Submittal Meeting Byron Unit 2 One-Time Deferral of Reactor Pressure Vessel Head Penetration Nozzle (Rpvhpn) Inspections ML20163A6552020-06-16016 June 2020 6-16-20 Byron Unit 2 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections ML20169A5592020-06-16016 June 2020 Steam Generator License Amendment Request Pre-Submittal Meeting (NRC) - Byron Unit 2 LAR for One-Time Deferral of Steam Generator Inspections (Rev 1) ML20050H0232020-02-20020 February 2020 Presentation Slides for Meeting to Discuss Environmental Regulatory Approach to TMI-2 Decommissioning ML19157A0542019-06-0606 June 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - NRC Presentation Slides ML18347B3142018-12-19019 December 2018 Bwrvip/Asme Relief Request Discussion December 19, 2018 ML18334A2162018-11-30030 November 2018 Presentation Slides: Exelon BWR MSIV (Boiling-Water Reactor - Main Steam Isolation Valve) Leakage Optimization for NRC Pre-Submittal Meeting of December 6, 2018 ML18319A1272018-11-19019 November 2018 Slides for 11/19/18 Public Meeting - Exelon Fleet LAR for Common Language for TS 5.7 High Radiation Areas ML16077A1562016-03-22022 March 2016 Fleet: Pre-application Teleconference with Exelon to Discuss a Potential License Amendment Request Regarding Operating Training Standards ML16070A1152016-03-11011 March 2016 Efforts to Improve Rulemaking Tracking and Reporting ML16006A2882016-01-0606 January 2016 Significant Operational Experience: 7 Major Industry Events with Regulatory Implications ML15327A0812015-11-0909 November 2015 Fall 2015 Outage Call Regarding the Steam Generator Tube Inservice Inspections - Slides ML14304A7832014-11-14014 November 2014 Public Meeting with the U.S. Nuclear Regulatory Commission and Exelon Generation Company, LLC Regarding Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Wate ML14300A5452014-10-30030 October 2014 10/30/2014, Meeting Slide with NRC Regarding GL 2004-02 Close Out for Three Mile Island, Unit 1 ML13262A1492013-09-19019 September 2013 Enclosure 3- NRC Presentation Handout ML13262A1172013-08-28028 August 2013 Enclosure 4 - Scott Portzline Presentation ML12262A3352012-09-13013 September 2012 9.13.2012 TMI Alert Presentation Nreg 0654 Public Mtg ML12116A0482012-04-25025 April 2012 Aam ROP-12 Slides ML1208701402012-03-27027 March 2012 Licensee Slides for Exelon Fleet Pre-Submittal Public Meeting 4-10-12 Licensed Operator Eligibility Requirements LAR ML12262A4762012-02-22022 February 2012 TMI Alert Portzline Presentation NUREG-0654 Public Mtg ML1202501052012-01-25025 January 2012 Licensee Slides for 1/26/12 Meeting Three Mile Island, Unit 1 - Summary of Tube to Tube Wear Identified During T1R19 (Fall 2011) ML11221A3262011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 18 Three Mile Island ML1115901302011-06-0808 June 2011 NRC Slides - TMI Public Meeting, June 7, 2011 ML13197A0522011-04-19019 April 2011 FOIA/PA-2011-0118, FOIA/PA-2011-0119, FOIA/PA-2011-0120 - Resp 111 - Partial, Group Letter Bt. Part 5 of 7 ML1007802632010-01-25025 January 2010 Presentation - Health Physics Society Mid-Year Meeting ML1007703672009-12-0707 December 2009 E-mail from J. White of USNRC to D. Screnci and J. Hawkins of USNRC, Regarding TMI NRC Slides.Ppt ML0929400522009-10-22022 October 2009 Meeting Power Uprate Meeting Slides ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - June 4, 2009, Slides ML0910702242009-04-17017 April 2009 Riv Regional Administrator Presentation at Texas A&M University March 30, 2009, Three Mile Island - Impact on Safety Perspectives and Safety Belief ML0907508342009-03-16016 March 2009 Meeting Slides, Three Mile Island Annual Assessment Meeting 2008 Reactor Oversight Process ML11216A2452008-12-0202 December 2008 0523 - R504P - Westinghouse Advanced Technology - 07.4 - Core Damaging Events ML0828805412008-10-14014 October 2008 Herbaceous Wetlands ML0826712092008-09-23023 September 2008 TMI Pre-Application Meeting - Control Rod Drive Control System Upgrade and Elimination of Axial Power Shaping Rods ML0812007842008-06-0202 June 2008 Meeting Slides, Nrc/Exelon Licensing Counterparts Meeting. 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ML0806700982008-03-0404 March 2008 License Renewal Process Overview Three Mile Island Unit 1 Public Meeting Handout 03/04/2008 ML0802501172008-01-15015 January 2008 1/15/2008 Slides from Drop-in Visit Exelon/Amergen ML0726404902007-08-14014 August 2007 TMI Intro ML0726404922007-08-14014 August 2007 TMI Tritium Update 08/07 - Slide Presentation ML0713701672007-04-30030 April 2007 Enclosure 2 (Slides) - 04/30/2007 Summary of Meeting with Amergen Energy Co., LLC, Regarding License Amendment Request Relating to the Insertion of New Area High Thermal Performance Fuel in the TMI-1 Reactor ML0710901582007-04-19019 April 2007 Aam Final Slides for Reactor Oversight Program 2006-07 Public Meeting 04/11/07 ML0726404942007-03-28028 March 2007 Unit 2 Accident - Presentation Slides ML0708513862007-03-26026 March 2007 Annual Assessment Slides for ROP 2006-07 Public Meeting on 4-11-07 ML0716601022007-03-20020 March 2007 Slides to Counterparts Meeting with Exelon to Discuss Current and Planned Licensing Activities and Process - Correction 2024-02-13
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Text
Three Mile Island, Unit 1Summary of Tube-to-Tube
Wear Identified During
T1R19 (Fall 2011)
January 26, 2012 NRC Headquarters 2 IntroductionIntroductions and Opening RemarksBill Carsky, TMI-1 Site Engineering Director*Greg Ciraula, TMI-1 Engineering Programs Manager*Mark Torborg, TMI-1 Steam Generator (SG) Program Engineer*SteveQueen,DirectorCorporateEngineeringPrograms Steve Queen, Director Corporate Engineering Programs*Jay Smith, Corpor ate SG Program Manager*Wendi Croft, Senior Licensing Engineer 3 PurposeProvide information on tube-to-tube (T-T) wear*Inspection results*How the indications were identified
- Primary and secondary analysisHotheindicationseresied
- Ho w the indications w ere si z ed*Basis for sizing techniques
- Future planned actions 4 BackgroundTMI-1 installed AREVA, Enhanced Once Through Steam Generators (EOTSGs) during T1R18*Operated January 2010 -October 2011General design features of EOTSGs*15,597 tubes per EOTSG*Full depth hydraulic expansions in tubesheets
- 15 stainless steel tube support plates (TSP)
Trefoil broached holes, 1.18" thick Numbered 01S (bottom) -15S (top) 15S TSP has 1470 drill holes in peripheral tubesSibtTSPif35"464"S pac i ng b e tween TSPs var i es f rom 35" -46.4"Aspirating ports are in 10 th span *Nominal gap between tubes is 0.25"First inservice inspection performed in October 2011*24-month fuel cycles*1.72 effective full power years (EFPY) on EOTSGs
- Maintained hot conditions throughout operating cycle 5 T1R19 Inspection Overview100% full length bobbin coil inspections in each EOTSGX-Probe inspections of peripheral tubes (two tubes deep) in each EOTSG (Evaluated 1 st span for loose parts)Tube damage mechanisms found in each EOTSG Tb ttbtlt(TTSP)(td)*T u b e-t o-t u b e suppor t p l a t e wear (T-TSP) (expec t e d)*Tube-to-tube wear (T-T) (not expected)No evidence of tie rod bowing No tie rod to tube c ontact or proximity 6 EOTSG A, T-T Wear Map 7 EOTSG B, T-T Wear Map 8 T1R19 T-T Wear IdentificationReported as absolute drift indications (ADIs) during bobbin coil inspection with most indications located:*In mid-span*In the 9 th span*In a radial pattern 30" -45"
- In adjacent tubes (two or three)Performed X-Probe and +Point on ADI signals*Verified indications in adjacent tubes face each other *Symmetrically tapered to maximum depth in center
- In ad jacent tubes the indications are at same elevation and are same len g th/de p thjgp*Length and depth have a correlation that is consistent with wear*Good correlation of phase angles and voltages between channelsAnalysts, Exelon Engineering, and AREVA Engineering consensus is that these indications are T-T wear*Notified Steam Generator Management Program (SGMP) per the requirements of Nuclear Energy Institute (NEI) 97-06 *Notified NRC 9Process for Screening T-T WearIndications reported as ADIs Industry standard is to use I-Codes to identify (possible) flaw signals where no qualified sizing technique exists and supplemental testing is required.
Exelon guidelines require analysts to report all indications of suspected tube wall degradation.
Primary Analysis (manual)0.5 volts & 90º channel 6 or%TW >0 on channels 4 & 6 *Secondary Analysis (auto) 0.5 volts & 30º -95º on channel 6
%TW >0 on channels 4 & 6 and 0.16 volts on channel 6 0.25 volts & 60º -120º on channel 6 10 Example TMI-1 T-T Wear Bobbin Data 11 Example TMI-1 T-T Wear Bobbin Data 12Example TMI-1 MBM Screened as ADI 13Summary of ADI Indications (T-T Wear) ADI Indications 0.5 volt*"A" -9 Tubes Primary = 9, Secondary = 7, Both = 7*"B" -19 Tubes Primary = 19, Secondary = 18, Both = 18All ADIs including review for paired tubes
- "A"74TubeswithADIs(008162volts)*A -74 Tubes with ADIs (0.08 -1.62 volts)Primary = 20, Secondary = 34, Both = 13oEither Primary or Secondary = 41o74 of 74 confirmed by +Point or X-Probe *"B" -202* Tubes with ADIs (0.07 -1.25 volts)
Primary = 145, Secondary = 95, Both = 71oEither Primary or Secondary = 169o*183 of 202 confirmed by X-Probe 14Process for Screening T-T Wear Per Exelon & SGMP PWR Steam Generator Examinations Guidelines, I-Code indications are "Category III: Supplemental Test Required"*Prior to T1R19, +Point and X-Probe identified as probes to be used for supplemental examinations X-Pr obe qua lifi ed f o r s izin g T-T S P w ea r (EPRI ET SS 11 956.3)obequaedosgSea(SS9563)
+Point qualified for sizing T-TSP wear (EPRI ETSS 96910.1)
+Point qualified for sizing various shapes of wear (EPRI ETSS 27901 -27907)oEPRI ETSS 27905.3 "Flat Wear" was determined to be the correct technique for T-T wear in EOTSGs 15 Example TMI-1 T-T Wear +Point DataNOTE: Graphic shows partial indication 16 Example TMI-1 T-T Wear X-Probe Data 17 Example Depth Profiles in Paired TubesT-T Wear Depth ProfilesEOTSG A , Tubes R26-T36 AND R26-T37 12 14 16 18 20 22%TW)R26 - T36R26 - T37 0 2 4 6 8 10 12131415161718192021222324AXIAL LOCATION ABOVE TSP 08S (INCHES)DEPTH (%
18T-T Wear Length-Depth CorrelationEOTSG A/B T-T WEAR LENGTH/DEPTH CORRELATIONy = -0.0098x 2 + 0.509x + 1.8162 5 6 7 8 9 NCHES)0 1 2 3 40510152025DEPTH (%TW)LENGTH (I N 19 Site Qualified Sizi ng Technique for T-T WearX-Probe T-T wear sizing technique developed in cooperation with EPRI*Used two of the same samples used to develop ETSS 27905.3 (+Point Flat Wear)*Developed "Power" trend line/regression curve using methodology used for other EPRI X-Probe techniques ETSS 11956.1
-11956.4, Broached TSP Wea r*"Power" trend line/regression scatter plot based on multiple examinations of 16 wear scars Wear scars ranged from 8% -60% TW*Analysis of standards performed by multiple analysts from three different vendor organizations*Accuracy validated through comparison of +Point and X-Probe results for EOTSG A 20 Graphic of Flat Wear Standard X-Probe 21 Graphic of Flat Wear Standard +Point 22 X-Probe Calibration CurveX-Probe Amplitude - Depth Calibration Curvey = 13.151x0.613 R 2= 0.991 40 50 60 70%TW 0 10 20 3002468101214Amplitude (Voltage Vmx)MET %
23 X-Probe Calibration Curve ValidationX-Probe 300 kHz Axial 40 50 60 70 iable (%TW)Sy.x = 2.09N = 32y = 0.9603x + 1.4017 R 2 = 0.9831r= 0.9915 0 10 20 30010203040506070NDE %TWStructural Var i
24 Comparison of +Point and X-ProbeEOTSG AX-Probe vs. +Point - %TW Correlation 20 25 30%TW)y = 0.9832x + 0.3458 R 2 = 0.932N = 41 0 5 10 15051015202530+Point (%TW)X-Probe (%
25 T1R19 T-T Wear SummaryA total of 257 tubes were identified with T-T wear*EOTSG A: 89 indications in 74 tubes*EOTSG B: 206 indications in 183 tubesWear depths range from 1% to 21% through wall (TW)Wear axial lengths range from 2" to 8" No proximity or t ube contact detectedTbititldditidiitht
- T u bes are i n t ens i on a t co ld con ditions an d i n compress i on a t h o t conditionsSizing performed by +Point Technique 27905.3 and a site qualified X-Probe Technique*Good correlation between Bobbin, +Point, and X-Probe techniquesAll tubes met condition monitori ng limits and in-situ pressure testing was not required 26 T-T Wear Depth Distribution 0 5 10 15 20 25 30No. INDICATION SEOTSG A 012345678910111213141516171819202122DEPTH (%TW) 0 5 10 15 20 25 30 35 40 4512345678910111213141516171819202122DEPTH (%TW)No. INDICATION SEOTSG B 27 T1R19 T-T Wear SummaryEOTSG AEOTSG BTotal number of In-Service Tubes1559715597Number of T-T Wear Indications89206Number of Tubes T-T Wear74183 Average Depth of T-T Wear5.8%7.4%Maximum Depth of T-T Wear21%19%Number of T-T Wear Indications >40% TW00 Average Growth Rate T-T Wear3.4%/EFPY4.3%/EFPY
95 thPercentile Growth Rate T-T Wear9.3%/EFPY7.6%/EFPYMaximum Growth Rate T-T Wear12.2%/EFPY11.1%/EFPYNumber of Tubes Plugged for T-T Wear43 28Condition Monitoring Su mmary for T-T Wear Condition Monitoring Satisfied*Utilized maximum depth and bounding length of 39" for 3 X normal operating pressure differential conditions
(3P)*Substantial margin against accident leakage and structural limits*Large break loss of coolant accident (LBLOCA) loading conditions evaluated and satisfied Assumed 180 degree circumferential extent of wear 29Condition Monitoring Assessment for T-T Wear CM Results for Tube-to-Tube Wear for Both Array Coil and +Point Sizing 60 70 80 90 100 nt ThroughwallCM Limit for X-probe sizingSGA X-probe DepthsSGB X-probe DepthsCM Limit for +Point SizingSGA +Point Depths 0 10 20 30 40 50051015202530354045Structural Length in InchesStructural Depth in Perce nConservatively Assumed Wear Scar Length was entire span between TSPs (39")
Actual lengths < 9" 30 Operational Assessment for T-T Wear Mixed arithmetic/Monte Carlo method utilized*Cycle length 1.927 EFPY*Addressed indications siz ed with +Point and X-Probe separately*End of cycle (EOC) length conservatively assumed 39"
- Usedmaximumgrowthoverpreviouscycle
- Used maximum growth over previous cycleConservative relative to ANO experienceSignificant margin to leakage and burst at EOC*Margin ~17% for worst case flaw at EOCLBLOCA evaluation also demonstrates significant margin 31 Planned Future Actions Update Site Specific Performance Demonstration (SSPD) training to include T-T wearConvert TMI-1, X-Probe site qualification to EPRI "Appendix H, Qualified Technique"Provide raw data to EPRI Perform 100% eddy current examinations during T1R20 (Fall 2013)Support AREVA root cause analysisImplement appropriate actions based on the results of the root cause 32TMI-1 Tube-to-Tube Wear Conclusions T-T wear was identified during the first inservice inspection of the TMI-1 EOTSGsAll T-T wear indications meet Condition Monitoring and Operational Assessment
performance criteria T-T wear does not impact inspection interval
length for Cycle 19