Letter Sequence Request |
---|
|
|
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
[Table View] |
|
---|
Category:Meeting Briefing Package/Handouts
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. ML0906302652009-02-24024 February 2009 Dseis Meeting Handouts 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. ML0813301852008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Handouts and Slides ML0813301832008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Written Comments ML0807906742008-03-19019 March 2008 Slides, NRC Annual Performance Assessment of Three Mile Island - 2007 Reactor Oversight Program. ML0806700982008-03-0404 March 2008 License Renewal Process Overview Three Mile Island Unit 1 Public Meeting Handout 03/04/2008 ML0735507162007-12-21021 December 2007 TMI Refueling Outage Performance Summary 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 2024-02-13
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24040A0722024-02-13013 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. ML0813301852008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Handouts and Slides ML0813301832008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Written Comments ML0807906742008-03-19019 March 2008 Slides, NRC Annual Performance Assessment of Three Mile Island - 2007 Reactor Oversight Program. 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 ML0607508032006-03-22022 March 2006 NRC Slide Presentation for Public Meeting Ref: Three Mile Island, Unit 1 Annual Assessment Performance CY2005 2024-02-13
[Table view] |
Text
Three Mile Island, Unit 1 Summary of Tube-to-Tube Wear Identified During T1R19 (Fall 2011)
January 26, 2012 NRC Headquarters
Introduction 2 Introductions and Opening Remarks Bill Carsky, TMI-1 Site Engineering Director
- Greg Ciraula, TMI-1 Engineering Programs Manager
- Steve Queen, Director Corporate Engineering Programs
- Jay Smith, Corporate SG Program Manager
- Wendi Croft, Senior Licensing Engineer
Purpose 3 9 Provide information on tube-to-tube (T-T) wear
- How the indications were identified
- Primary and secondary analysis
- Ho the indications were How ere si sized ed
- Basis for sizing techniques
Background 4 9 TMI-1 installed AREVA, Enhanced Once Through Steam Generators (EOTSGs) during T1R18
- Operated January 2010 - October 2011 9 General design features of EOTSGs
- 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 tubes S
Spacing i b between t TSP TSPs varies i from f 35 - 46.4 46 4 Aspirating ports are in 10 span th
- Nominal gap between tubes is 0.25 9 First inservice inspection performed in October 2011
- 1.72 effective full power years (EFPY) on EOTSGs
- Maintained hot conditions throughout operating cycle
T1R19 Inspection Overview 5 9 100% full length bobbin coil inspections in each EOTSG 9 X-Probe inspections of peripheral tubes (two tubes deep) in each EOTSG (Evaluated 1st span for loose parts) 9 Tube damage mechanisms found in each EOTSG
- T Tube-to-tube b t t b supportt plate l t wear (T-TSP)
(T TSP) (expected)
( t d)
- Tube-to-tube wear (T-T) (not expected) 9 No evidence of tie rod bowing 9 No tie rod to tube contact or proximity
EOTSG A, T-T Wear Map 6 EOTSG B, T-T Wear Map 7 T1R19 T-T Wear Identification 8 9 Reported as absolute drift indications (ADIs) during bobbin coil inspection with most indications located:
- In a radial pattern 30 - 45
- In adjacent tubes (two or three) 9 Performed X-Probe and +Point on ADI signals
- Verified indications in adjacent tubes face each other
- Symmetrically tapered to maximum depth in center
- In adjacent j tubes the indications are at same elevation and are same length/depth g p
- Length and depth have a correlation that is consistent with wear
- Good correlation of phase angles and voltages between channels 9 Analysts, Exelon Engineering, and AREVA Engineering consensus is that these indications are T-T wear
Process for Screening T-T Wear 9 9 Indications 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
Example TMI-1 T-T Wear Bobbin Data 10 Example TMI-1 T-T Wear Bobbin Data 11 Example TMI-1 MBM Screened as ADI 12 Summary of ADI Indications (T-T Wear) 13 9 ADI Indications 0.5 volt
- A - 9 Tubes Primary = 9, Secondary = 7, Both = 7
- B - 19 Tubes Primary = 19, Secondary = 18, Both = 18 9 All ADIs including review for paired tubes
- A A - 74 Tubes with ADIs (0.08(0 08 - 1.62 1 62 volts)
Primary = 20, Secondary = 34, Both = 13 o Either Primary or Secondary = 41 o 74 of 74 confirmed by +Point or X-Probe
- B - 202* Tubes with ADIs (0.07 - 1.25 volts)
Primary = 145, Secondary = 95, Both = 71 o Either Primary or Secondary = 169 o *183 of 202 confirmed by X-Probe
Process for Screening T-T Wear 14 9 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-Probe obe qua qualified ed for o ssizingg T-TSP S wear ea ((EPRI ETSS SS 11956.3) 956 3)
+Point qualified for sizing T-TSP wear (EPRI ETSS 96910.1)
+Point qualified for sizing various shapes of wear (EPRI ETSS 27901 - 27907) o EPRI ETSS 27905.3 Flat Wear was determined to be the correct technique for T-T wear in EOTSGs
Example TMI-1 T-T Wear +Point Data 15 NOTE: Graphic shows partial indication
Example TMI-1 T-T Wear X-Probe Data 16 Example Depth Profiles in Paired Tubes 17 T-T Wear Depth Profiles EOTSG A , Tubes R26-T36 AND R26-T37 22 20 18 R26 - T36 R26 - T37 16 14 DEPTH (%
%TW) 12 10 8
6 4
2 0
13 14 15 16 17 18 19 20 21 22 23 24 AXIAL LOCATION ABOVE TSP 08S (INCHES)
T-T Wear Length-Depth Correlation 18 EOTSG A/B T-T WEAR LENGTH/DEPTH CORRELATION 9
8 7
LENGTH (IN NCHES) 6 y = -0.0098x2 + 0.509x + 1.8162 5
4 3
2 1
0 0 5 10 15 20 25 DEPTH (%TW)
Site Qualified Sizing Technique for T-T Wear 19 9 X-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 Wear
- 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
Graphic of Flat Wear Standard X-Probe 20 Graphic of Flat Wear Standard +Point 21 X-Probe Calibration Curve 22 X-Probe Amplitude - Depth Calibration Curve 70 60 50 0.613 y = 13.151x MET %
%TW 40 2 R = 0.991 30 20 10 0
0 2 4 6 8 10 12 14 Amplitude (Voltage Vmx)
X-Probe Calibration Curve Validation 23 X-Probe 300 kHz Axial Sy.x = 2.09 70 N = 32 60 Structural Variiable (%TW) 50 40 30 y = 0.9603x + 1.4017 2
R = 0.9831 20 r= 0.9915 10 0
0 10 20 30 40 50 60 70 NDE %TW
Comparison of +Point and X-Probe 24 EOTSG A X-Probe vs. +Point - %TW Correlation 30 25 20 X-Probe (%
%TW) 15 y = 0.9832x + 0.3458 2
R = 0.932 10 N = 41 5
0 0 5 10 15 20 25 30
+Point (% TW)
T1R19 T-T Wear Summary 25 9 A total of 257 tubes were identified with T-T wear
- EOTSG A: 89 indications in 74 tubes
- EOTSG B: 206 indications in 183 tubes 9 Wear depths range from 1% to 21% through wall (TW) 9 Wear axial lengths range from 2 to 8 9 No proximity or tube contact detected
- TTubes b are in i tension t i att cold ld conditions diti and d iin compression i att h hott conditions 9 Sizing performed by +Point Technique 27905.3 and a site qualified X-Probe Technique
- Good correlation between Bobbin, +Point, and X-Probe techniques 9 All tubes met condition monitoring limits and in-situ pressure testing was not required
T-T Wear Depth Distribution 26 30 25 EOTSG A 20 No. INDICATIONS 15 10 5
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 DEPTH (%TW) 45 40 35 30 EOTSG B No. INDICATIONS 25 20 15 10 5
0 1 2 3 4 5 6 7 8 9 10 11 12 13 14 15 16 17 18 19 20 21 22 DEPTH (%TW)
T1R19 T-T Wear Summary 27 EOTSG A EOTSG B Total number of In-Service Tubes 15597 15597 Number of T-T Wear Indications 89 206 Number of Tubes T-T Wear 74 183 Average Depth of T-T Wear 5.8% 7.4%
Maximum Depth of T-T Wear 21% 19%
Number of T-T Wear Indications >40% TW 0 0 Average Growth Rate T-T Wear 3.4%/EFPY 4.3%/EFPY 95 th Percentile Growth Rate T-T Wear 9.3%/EFPY 7.6%/EFPY Maximum Growth Rate T-T Wear 12.2%/EFPY 11.1%/EFPY Number of Tubes Plugged for T-T Wear 4 3
Condition Monitoring Summary for T-T Wear 28 9 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
Condition Monitoring Assessment for T-T Wear 29 CM Results for Tube-to-Tube Wear for Both Array Coil and +Point Sizing 100 CM Limit for X-probe sizing 90 SGA X-probe Depths SGB X-probe Depths 80 CM Limit for +Point Sizing SGA +Point Depths Structural Depth in Percen nt Throughwall 70 60 Conservatively 50 Assumed Wear Scar Length was entire span 40 between TSPs (39")
Actual lengths < 9" 30 20 10 0
0 5 10 15 20 25 30 35 40 45 Structural Length in Inches
Operational Assessment for T-T Wear 30 9 Mixed arithmetic/Monte Carlo method utilized
- Addressed indications sized with +Point and X-Probe separately
- End of cycle (EOC) length conservatively assumed 39
- Used maximum growth over previous cycle Conservative relative to ANO experience 9 Significant margin to leakage and burst at EOC
- Margin ~17% for worst case flaw at EOC 9 LBLOCA evaluation also demonstrates significant margin
Planned Future Actions 31 9 Update Site Specific Performance Demonstration (SSPD) training to include T-T wear 9 Convert TMI-1, X-Probe site qualification to EPRI Appendix H, Qualified Technique 9 Provide raw data to EPRI 9 Perform 100% eddy current examinations during T1R20 (Fall 2013) 9 Support AREVA root cause analysis 9 Implement appropriate actions based on the results of the root cause
TMI-1 Tube-to-Tube Wear Conclusions 32 9 T-T wear was identified during the first inservice inspection of the TMI-1 EOTSGs 9 All T-T wear indications meet Condition Monitoring and Operational Assessment performance criteria 9 T-T wear does not impact inspection interval length for Cycle 19