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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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Category:Meeting Briefing Package/Handouts
MONTHYEARML24264A1592024-09-30030 September 2024 Adtf Exemption Request Pre-submittal Meeting Presentation ML24190A1452024-07-0808 July 2024 Public Meeting Slides for Arkansas Nuclear One 2023 Annual Assessment, Pope County Quorum Court ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML22193A0262022-07-12012 July 2022 (ANO) RICT License Amendment Request TSTF-505 NRC Pre-Submittal Meeting Presentation - July 13, 2022 ML21351A0282021-12-16016 December 2021 Preliminary Information of ANO-1 1R17 (2002) Findings on CRDM Nozzle 56, and Presentation Slides for PT Exam of Nozzle 56 ML21348A1262021-12-14014 December 2021 RCP TS LAR Pre-Submittal Meeting Slides, December 16, 2021 ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21242A2792021-08-30030 August 2021 ANO Slides Presentation for 9-1-21 Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20315A1582020-11-17017 November 2020 Presentation Meeting Slides for the 11/17/20 Teleconference ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20255A0242020-09-11011 September 2020 (Ano), Pre-Submittal Meeting with NRC - Request to Extend Allowable Outage Time (AOT) for the Emergency Cooling Pond (ECP) ML20211L7052020-08-0404 August 2020 (ANO) Units 1 & 2, Pre-Submittal Slide Presentation for August 4, 2020 Public Meeting ML20114E2752020-04-29029 April 2020 (ANO) Carbon Fiber Reinforced Polymer (Cfrp) Relief Request Pre-Submittal Meeting with NRC - April 29, 2020 ML19136A2512019-06-13013 June 2019 Handout for the June 13, 2019 Pre-submittal Public Meeting for Planned License Amendment Request Regarding Fuel Handling Accident Analysis ML18176A1312018-06-21021 June 2018 Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18081A1922018-03-20020 March 2018 Presentation at the PRA Workshop ML17328A3652017-11-30030 November 2017 Workshop on Sharing Operating Experience from Rigging, Lifting and Load Handling Events - Temporary Overhead Crane Failure at Arkansas Nuclear One Presented to IAEA ML16109A3642016-04-18018 April 2016 Summary of Meeting to Discuss Supplemental Inspection Results and Annual Assessment Meeting with Entergy Operations Inc. Regarding 2015 Performance of Arkansas Nuclear One ML16015A0622016-01-20020 January 2016 Briefing Notes for 95003 Inspection at Arkansas Nuclear One ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML14356A1852014-12-22022 December 2014 ANO2 Exit ML14329B2092014-11-25025 November 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Flood Protection Deficiencies ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML12332A1792012-11-26026 November 2012 Power Point Presentation by Entergy at the November 26, 2012 Meeting (TAC No. ME9706.) ML12306A2912012-11-0101 November 2012 Transmittal Email and WCAP-17128-NP, Revision 1, Flaw Evaluation of CE Design RCP Suction and Discharge Nozzle Dissimilar Metal Welds, Phase III Study, May 2010 ML12278A2552012-10-0909 October 2012 Licensee Slide Presentation, ANO-2 NFPA 805 Application, at the October 9, 2012, pre-submittal Meeting to Discuss the NFPA 805 Application ML12278A2532012-10-0909 October 2012 Licensee Handout, Design Input for Fire Risk Evaluation, at the 10/9/2012 Pre-submittal Meeting to Discuss the NFPA 805 Application ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML1218003412012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #4 ML1218003192012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #3 ML1218003122012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #2, Table W-2 ANO-2 Fire Area Risk Summary ML1218003102012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Item #1, Plant Modifications and Items to Be Completed ML1218003062012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Power Point Slides ML12166A5602012-06-12012 June 2012 Licensee Presentation on June 12 & 13, 2012, Meeting License Amendment Request on NFPA 805 Adoption ML1202501112012-01-25025 January 2012 Licensee Slides Arkansas Nuclear One, Unit 1 - Steam Generators Tube to Tube Wear ML1126502692011-09-22022 September 2011 Licensee Handouts for 10/05/2011 Presubmittal Meeting ML1117906392011-06-28028 June 2011 Summary of Meeting with Entergy Operations Inc ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1107504262011-03-15015 March 2011 Licensee Slides from 3/15/11 Pre-Sumittal Meeting SWS Room Cooling Required Action ML1107504162011-03-15015 March 2011 Licensee Slides from 3/15/11 Meeting with Entergy Operations on Technical Specification Change - Testing of Idle RCS Cooling Loop ML1016705012010-06-17017 June 2010 Discussion of Screening Criteria - Arkansas Nuclear One (ANO) ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0935005652009-12-15015 December 2009 NRC Handouts Current Status of Arkansas Nuclear One Unit Steam Generators, December 2009 ML0913104172009-05-11011 May 2009 Summary of Meeting with Entergy to Discuss Arkansas Nuclear One 2008 Performance 2024-09-30
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24264A1592024-09-30030 September 2024 Adtf Exemption Request Pre-submittal Meeting Presentation ML24190A1452024-07-0808 July 2024 Public Meeting Slides for Arkansas Nuclear One 2023 Annual Assessment, Pope County Quorum Court ML23348A3572023-12-14014 December 2023 Application to Revise Technical Specifications to Use Online Monitoring Methodology – Slides and Affidavit for Pre-Submittal Meeting ML23296A1002023-10-24024 October 2023 Entergy Presentation Slides for Pre-Submittal Meeting on 10/24/23, Mtc LAR ML23223A2032023-08-11011 August 2023 (ANO) Unit 1 Licensees Slide Presentation for 8/15/23 Public Meeting Pressurizer Heaters ML22193A0262022-07-12012 July 2022 (ANO) RICT License Amendment Request TSTF-505 NRC Pre-Submittal Meeting Presentation - July 13, 2022 ML22164A8012022-06-13013 June 2022 Entergy Fleet (GGNS, RBS, and WF-3) - Code Case N-752 RR 6-14-22 Pre-Submittal Public Meeting Presentation Slides ML22124A0692022-05-10010 May 2022 RVCH Penetration No. 1 Relief Request Public Meeting May 10, 2022 (EPID L-2022-LRM-0036) (Slides) ML21351A0282021-12-16016 December 2021 Preliminary Information of ANO-1 1R17 (2002) Findings on CRDM Nozzle 56, and Presentation Slides for PT Exam of Nozzle 56 ML21348A1262021-12-14014 December 2021 RCP TS LAR Pre-Submittal Meeting Slides, December 16, 2021 ML21319A2452021-11-15015 November 2021 Natrium Energy Island Decoupling Strategy - 11-17-2021 ML21309A0622021-11-0909 November 2021 NRC Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21306A3162021-11-0909 November 2021 Digital IC Presentation 11/09/2021 ML21312A0342021-11-0909 November 2021 Combined Slides for November 9, 2021, Technology Inclusive Content of Application Project Public Meeting ML21200A1792021-07-31031 July 2021 Scale/Melcor Non-LWR Source Term Demonstration Project - High Temperature Gas-Cooled Reactor 0CAN062101, Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling2021-06-15015 June 2021 Presentation Information for Pre-Submittal Meeting Regarding the Response to Request for Additional Information - Proposed Alternative to ASME Section XI Requirements for Repair/Replacement of Emergency Cooling ML21095A2122021-04-0808 April 2021 Pre-Submittal Meeting - ANO-1 LAR Related to RCS Primary Activity and Primary-to-Secondary Leak Rate ML20344A0572020-12-10010 December 2020 Combined Industry and NRC Slides for the December 10, 2020, Public Meeting on Technology Inclusive Content of Application Project, Advanced Reactor Content of Application Project and Applicability of Regulations to Non-Light Water Reactors ML20315A1582020-11-17017 November 2020 Presentation Meeting Slides for the 11/17/20 Teleconference ML20269A3452020-09-28028 September 2020 Pre-submittal Meeting for Request for One-Time Exemption from 10 CFR Part 50, Appendix E, Biennial EP Exercise (Offsite) Due to COVID-19- Entergy Presentation Slides ML20255A0242020-09-11011 September 2020 (Ano), Pre-Submittal Meeting with NRC - Request to Extend Allowable Outage Time (AOT) for the Emergency Cooling Pond (ECP) ML20211L7052020-08-0404 August 2020 (ANO) Units 1 & 2, Pre-Submittal Slide Presentation for August 4, 2020 Public Meeting ML20114E2752020-04-29029 April 2020 (ANO) Carbon Fiber Reinforced Polymer (Cfrp) Relief Request Pre-Submittal Meeting with NRC - April 29, 2020 ML18107A3342018-04-10010 April 2018 Tech Spec 3.3.5.2a Change Pre-Submittal Meeting Presentation Slides ML18075A1232018-03-20020 March 2018 Entergy Nuclear Operations - March 20, 2018, Presentation Slides for Surveillance Frequency Control Program, UFSAR Change Considerations ML18081A1922018-03-20020 March 2018 Presentation at the PRA Workshop ML17328A3652017-11-30030 November 2017 Workshop on Sharing Operating Experience from Rigging, Lifting and Load Handling Events - Temporary Overhead Crane Failure at Arkansas Nuclear One Presented to IAEA ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML15014A0842015-01-14014 January 2015 NRC ANO Unit 1 Stator Drop SDP Evaluation ML14329B2092014-11-25025 November 2014 Summary of Regulatory Conference to Discuss Safety Significance of Arkansas Nuclear One Flood Protection Deficiencies ML14259A5972014-09-16016 September 2014 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One Performance ML14169A0722014-06-19019 June 2014 Entergy Public Meeting Presentation Slides ML13142A2272013-05-22022 May 2013 Summary of Public Meeting to Discuss Results of Augmented Inspection at Arkansas Nuclear One ML12332A1792012-11-26026 November 2012 Power Point Presentation by Entergy at the November 26, 2012 Meeting (TAC No. ME9706.) ML12275A5492012-10-0101 October 2012 Summary of Meeting with Entergy Operations, Inc., to Discuss the Performance of the Subject Facilities, Recent Organizational Changes, and Current Regulatory Issues ML1218003062012-06-28028 June 2012 Handouts at the June 29, 2012 NFPA 805 Meeting at the Hq - Power Point Slides ML1202501112012-01-25025 January 2012 Licensee Slides Arkansas Nuclear One, Unit 1 - Steam Generators Tube to Tube Wear ML1126502692011-09-22022 September 2011 Licensee Handouts for 10/05/2011 Presubmittal Meeting ML11221A3212011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 17 ANO-1 Seal Failure ML1110401532011-04-13013 April 2011 Licensee Slides from 4/13/11 Meeting with Entergy Operations, Inc., to Discuss Proposed National Fire Protection Programs Standards 805 License Amendment Submittal for Arkansas Nuclear One, Units 1 & 2 ML1107504262011-03-15015 March 2011 Licensee Slides from 3/15/11 Pre-Sumittal Meeting SWS Room Cooling Required Action ML1107504162011-03-15015 March 2011 Licensee Slides from 3/15/11 Meeting with Entergy Operations on Technical Specification Change - Testing of Idle RCS Cooling Loop ML1016705012010-06-17017 June 2010 Discussion of Screening Criteria - Arkansas Nuclear One (ANO) ML0935201272009-12-18018 December 2009 Nrc/Entergy Operations, Inc., Management Meeting ML0913104172009-05-11011 May 2009 Summary of Meeting with Entergy to Discuss Arkansas Nuclear One 2008 Performance ML0831102062008-11-0606 November 2008 Summary of Meeting with Entergy to Discuss an Open Substantive Crosscutting Issue at Arkansas Nuclear One ML0828000612008-10-0101 October 2008 Enclosure 3-Technical Papers 2 - Plant Application of Weld Onlay for Butt Weld Mitigation ML0828300322008-08-31031 August 2008 NRC Presentation Arkansas Nuclear One - Unit One ML0814306742008-05-22022 May 2008 Summary of Annual Performance Assessment Meeting for Arkansas Nuclear One ML0718004262007-06-29029 June 2007 Summary of Arkansas Nuclear One End-Of-Cycle Public Meeting 2024-09-30
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ANO1 Steam Generators NRC Presentation Arkansas Nuclear One Unit One Steam Generators Tube to Tube Wear Entergy/AREVA INC.
January 2012 1
ANO1 Steam Generators 3/4 Entergy Jaime McCoy - Engineering Director Danny Hughes - EP&C Supervisor Dan Meatheany - SG Program Owner Steve Brown - Corporate SG Program Owner Bob Clark - Licensing 3/4 AREVA INC.
Jeff Fleck Jim Begley Jeff Grigsby Mike Boudreaux John Remark 2
ANO1 Steam Generators 3/4 Agenda Opening Remarks - Jaime McCoy Outage Results - Dan Meatheany Damage History - Mike Boudreaux Outage Plans for 1R24 - Dan Meatheany Questions Closing Comments - Jaime McCoy Root Cause - John Remark 3
ANO1 Steam Generators Opening Comments Jaime McCoy Engineering Director 4
ANO1 Steam Generators EOTSG Description 9 15 Tube Support Plates 9 External FW and EFW Rings 9 Floating TSP/Tie Rod 9 TSP are Trefoil Broach SS 9 Aspirating Port in 10th Span 9 Upper and Lower Shroud 9 Orifice Plate in Downcomer 9 FW into Downcomer 9 EFW Penetrates Shroud 9 52 Tie Rods Concentric Circles 5
ANO1 Steam Generators ANO1 EOTSG Inspections 3/4 Generators replaced in fall of 2005 (1R19) 3/4 First ISI was spring 2007 (1R20) 3/4 Second ISI was fall 2008 (1R21) 3/4 Third ISI was spring 2010 (1R22) 3/4 Fourth ISI was fall of 2011 (1R23) 6
ANO1 Steam Generators Inspection Scope 3/4 IR23 Inspection Scope 100% bobbin full length of tubes X-Probe of affected tubes around tie rods X-Probe off special interest (SI)
(S ) locations 3/4 A similar scope of 100% Bobbin and X-Probe SI was conducted in 1R20 and 1R21 3/4 Outage 1R22 was a limited scope of tubes surrounding tie rods for tie rod bowing 3/4 All special interest has been performed with the X-Probe 7
ANO1 Steam Generators Time Line for Identification of Tube-to-Tube Wear 3/4 Started ANO1 inspection on 10/20/2011 3/4 Analysis and repair complete on 10/26/2011 3/4 Notified by Exelon and AREVA on 11/07/2011 about Tube-to-Tube wear 3/4 Re-analyzed 100% of the 1R23 data using auto analysis and performed a review of historical data 3/4 Revised CMOA - acceptable to operate for 3 cycles 3/4 Initiated root cause effort 8
ANO1 Steam Generators Attributes of Tube-to-Tube Wear 3/4 Located in the middle of the 9th span which is also the middle of the entire tube and some (far fewer) indications in the middle of the 8th span 3/4 Typically located in a radial pattern 30- 45 from the center of the tubesheet 3/4 Present in adjacent tubes (groups of two or three) unless near the detection threshold 3/4 In adjacent tubes the indications face one another at the same elevation and are the same length and depth range 3/4 Indications occurring in a triangular pattern show two indications in one tube and one indication in each of the other two tubes 3/4 Symmetrically tapered to a maximum depth in the center 9
ANO1 Steam Generators Reanalysis for Tube-to-Tube Wear 3/4 Diagnosis of this condition at TMI led to an immediate notification and reanalysis of the ANO inspection data 3/4 The reanalysis was conducted with an automated algorithm with a reporting threshold of 0.35 volts, which equates to 6% TW (0.50 volts equates to 8% TW) 3/4 All identified indications were further reviewed for the attributes defined for Tube-to-Tube wear 10
ANO1 Steam Generators Reanalysis for Tube-to-Tube Wear 3/4 Identified tube-to-tube wear indications were reviewed in all prior inspections to concisely define history and develop growth data 3/4 Using the correlation between bobbin and
+Point voltages for TMI Tube-to-Tube wear, a calibration curve was developed for the ANO1 bobbin data to estimate depth based upon
+Point voltage from EPRI 27905.3 3/4 Depths were assigned to all indications in 1R20, 1R21 and 1R23 inspections 11
ANO1 Steam Generators Tube-to-Tube Wear Inspection Findings 3/4 A total of 126 indications in 122 tubes were identified with tube-to-tube wear EOTSG A: 48 indications in 48 tubes EOTSG B: 78 indications in 74 tubes 3/4 Wear depths range from 5% to 26% through wall 3/4 Indications have initiated with time None were present in the preservice inspection and none have disappeared since initiation 79 were present in the first inspection 11 new indications were in the second inspection 36 new indications were in the fourth inspection 12
ANO1 Steam Generators 13
ANO1 Steam Generators 14
ANO1 Steam Generators Tube-to-Tube Wear Inspection Findings Average Depth Average Largest Largest of New Depth 1R23 New 1R23 Indications at Repeat Indication Indication 1R23 Indications Depth Depth at 1R23 SG A 9%TW 8%TW 16%TW 16%TW SG B 8%TW 10%TW 11%TW 26%TW 15
ANO1 Steam Generators 16
ANO1 Steam Generators 17
ANO1 Steam Generators 18
ANO1 Steam Generators Growth History for Two Largest Indications 19
ANO1 Steam Generators Condition Monitoring Satisfied 3/4 Utilized maximum depth and conservative length for 3 delta P conditions 3/4 Substantial margin against accident leakage and structural limits (>20%TW) 3/4 LBLOCA loading conditions evaluated and also satisfied, conservatively assuming 180 degree circumferential extent of wear 20
ANO1 Steam Generators 21
ANO1 Steam Generators Operational Assessment Summary 3/4 Mixed arithmetic/monte carlo method utilized 3/4 Cycle length 4.13 EFPY (three fuel cycles) 3/4 Used maximum growth over previous cycle 3/4 Significant margin to leakage and burst
(>10%TW margin) 3/4 LBLOCA evaluation also demonstrates significant margin 22
ANO1 Steam Generators ANO Unit 1 Inspection History Analysis of ADIs Mike Boudreaux 23
ANO1 Steam Generators Absolute Drift Indications 3/4 Absolute Drift Indications (ADI) are eddy current signals from the bobbin probe which have only an absolute channel response and are caused by numerous variables variables, most commonly; flaws flaws, MBMs and material property changes 3/4 Historically service related degradation in PWR Steam Generators have produced both differential and absolute channel responses and MBMs and material property changes have produced only an absolute channel response 24
ANO1 Steam Generators 25
ANO1 Steam Generators 26
ANO1 Steam Generators ADI Reporting Process (Bobbin Probe) 3/4 The reporting process for ADIs has been consistent since 1R20 to support historical review 3/4 The reporting criteria for absolute indications is 0 50 volts and > 0.50 0.50 0 50 inches in length to address the most common source - MBMs 3/4 The analysis rules allow reporting below this threshold if the indication is flaw-like 3/4 Resolution analysts review the production calls as well as evaluate the indications for change using a criteria of 10 degree phase shift and > 0.50 volt increase in amplitude 27
ANO1 Steam Generators Reporting Process (X-Probe) 3/4 The reporting process has been consistent since 1R20 3/4 The analysis requirements are prescriptive 3/4 The Th reporting ti criteria it i iinvolves l no particular ti l thresholds and there are reporting codes for linear and volumetric indications - otherwise No Degradation Found (NDF) 3/4 Resolution analysts review the production calls and assign a final call as they deem appropriate with concurrence 28
ANO1 Steam Generators Reporting History for Tube-to-Tube Wear SG A Tube-to-Tube Wear Indications Reported by Outage Category 1R20 1R21 1R23 Not available Primary 4 17 Not available Secondary 3 22 Resolution 1 1 17 Total Present 15 23 48 Not Reported 0.49 volts 11 18 23 0.50 volts 3 0 2 SG B Tube-to-Tube Wear Indications Reported by Outage Category 1R20 1R21 1R23 Not available Primary 26 27 Not available Secondary 25 41 Resolution 15 18 23 Total Present 64 67 78 Not Reported 0.49 volts 40 31 28 0.50 volts 9 7 6 29
ANO1 Steam Generators Analysis Process Review 3/4 An average of 21% of the Tube-to-Tube wear indications have been reported over the past inspections 3/4 An average of 57% of the Tube-to-Tube wear indications were e e be below o tthee ADI reporting epo t g tthreshold es o d o over e tthe e past inspections 3/4 This total of 78% means that, on the average, 20% of the reportable ADIs were not reported over the past inspections 3/4 The absence of a differential channel response, to indicate a flaw-like condition, coupled with a reporting threshold of 0.50 volts are the primary contributing factors to the percentage of indications reported 30
ANO1 Steam Generators Analysis Process Review 3/4 A review of the indications shows that both the production, resolution and IQDA analysts have mischaracterized the indications in one fashion or another over the past inspections Production - either by not reporting them or mischaracterizing them Resolution - either by deleting them or mischaracterizing them IQDA - either by not questioning deleted indications or agreeing with the mischaracterization 31
ANO1 Steam Generators Review of Tube R116-T029 Reporting History 3/4 1R20 Reported as an NQI on bobbin and VOL on X-Probe 3/4 1R21 Reported R t db by production d ti as ADI on b bobbin bbi and d SVI and d
MBM on X-Probe Resolution stated it was anomaly or geometry and changed call to NDF with IQDA agreement 3/4 1R23 Reported by production as ADI on bobbin and changed to NQS based on history and did not receive an X-Probe test 32
ANO1 Steam Generators Review of Tube R117-T029 Reporting History 3/4 1R20 Not reported on bobbin though signal was present 3/4 1R21 Reported R t dbby production d ti as ADI on b bobbin bbi and d SVI and d
MBM on X-Probe Resolution stated it was anomaly or geometry and changed call to NDF with IQDA agreement 3/4 1R23 Reported by production as ADI on bobbin and changed to NQS based on history and did not receive an X-Probe test 33
ANO1 Steam Generators Summary for R116-T029 and R117-T029 3/4 Hindsight review would indicate that these indications should have been investigated further The tubes are side by side The indications are at the same elevation The bobbin voltage was > 2 volts The X-Probe signal was volumetric in nature Voltage change was > 0.5 volts from 1R20 outage 34
ANO1 Steam Generators Resolution Analysis Team Structure (1R23) 3/4 The primary and secondary resolution teams were from different companies 3/4 The IQDA was from the secondary analysis company 3/4 There were 5 primary & 6 secondary resolution analysts and 2 IQDA - all certified Level III QDA 3/4 The resolution process requires a minimum of two resolution and one IQDA analysts to delete degradation 35
ANO1 Steam Generators Resolution Analysis Team Experience (1R23)
Experience Position
(# Jobs)
Primary Resolution 1 16 Primary Resolution 2 5 Primary Resolution 3 25 Primary Resolution 4 11 Primary Resolution 5 9 Secondary Resolution 1 2 Secondary Resolution 2 4 Secondary Resolution 3 7 Secondary Resolution 4 5 Secondary Resolution 5 9 Secondary Resolution 6 3 Independent QDA 1 8 Independent QDA 2 14 36
ANO1 Steam Generators Potential to Mask Other Degradation 3/4 As the steam generators age there is a possibility for another form of degradation to initiate at a Tube-to-Tube wear site 3/4 Itt iss unlikely u e y tthat at the t e absolute abso ute ssignal g a from o tthe e wear ea sca scar will mask other degradation since that degradation is likely to produce a differential signal and differential channels are unaffected by Tube-to-Tube wear signals 3/4 New degradation will result in a change in the signal which will require the indication to be further tested 3/4 No other attributes of the Tube-to-Tube wear scar are likely to affect eddy current signal response for bobbin, X-Probe or RPC 37
ANO1 Steam Generators ANO Unit 1 1R24 Inspection Plan Dan Meatheany 38
ANO1 Steam Generators Purpose of Inspections 3/4 Confirm apparent cause and analysis inputs 3/4 Determine magnitude of tie rod bow 3/4 Determine if free-span wear exists on tubes around tie rods 3/4 Determine if denting exists on tubes around tie rods 3/4 Evaluate the Tube-to-Tube wear 39
ANO1 Steam Generators Current Scope of 1R24 Inspection Plans 3/4 Bobbin test of surrounding tubes for all 52 tie rods in both steam generators 3/4 Inspect all previously identified Tube-to-Tube wear > 00.35 35 volts 40
ANO1 Steam Generators Questions ?
41
ANO1 Steam Generators Closing Comments - Jaime McCoy 42