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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 Summary
MONTHYEARML24037A1032024-03-0707 March 2024 – Summary of February 1, 2204 RAI Clarification Teleconference ML24051A1932024-02-29029 February 2024 Feb 13 Meeting Summary, Energy Solutions TMI-2 Decommissioning Overview with NRC ML24052A2572024-02-26026 February 2024 Summary of January 17, 2024, Partially Closed Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for Entergy Fleet Regarding Implementation of an Online Monitoring Methodology ML23257A2412023-09-19019 September 2023 Summary of August 15, 2023, Pre-submittal Teleconference with Entergy Operations, Inc. to Discuss Proposed License Amendment Request Concerning Pressurizer Heaters for Arkansas Nuclear One, Unit 1 ML23181A0342023-07-11011 July 2023 Summary of Classification Meeting with TMI-2 Solutions, LLC Regarding the Process for Consultation Under Section 106 of the National Historic Preservation Act of 1966 as Related to the Historic and Culture Resources Review License Amendment ML23047A3822023-03-21021 March 2023 Summary of December 15, 2022 Periodic Advanced Reactor Stakeholder Public Meeting ML22215A1912022-08-0909 August 2022 Summary of July 13, 2022, Teleconference Meeting with Entergy Operations, Inc. to Discuss Planned License Amendment Requests to Adopt Technical Specifications Task Force (TSTF) Traveler 505, Risk-Informed Extended Completion Times ML22147A0932022-06-0606 June 2022 2021 Annual Assessment Public Meeting Summary ML22151A1302022-06-0202 June 2022 May 10, 2022, Summary of Teleconference Meeting W/Entergy Operations, Inc. to Discuss a Planned Alternative for a One-Time Schedule Extension for the In-Service Examination of Control Rod Drive Mechanism Penetration No. 1 in the Reactor Ves ML22125A2452022-05-0909 May 2022 May 3, 2022, Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for ANO, Units 1 & 2 Regarding Proposed Revision to Emergency Plan and On-Shift Staff Analysis ML22003A0562022-01-10010 January 2022 Summary of December 16, 2021, Presubmittal Teleconference with Entergy Operations, Inc. to Discuss Proposed Amendment Request Concerning TS 3.4.4, RCS Loops, Modes 1 and 2, for Arkansas Nuclear One, Unit 1 ML21323A0472021-12-0606 December 2021 Summary of Public Meeting on November 5, 2021, with the National Organization of Test, Research, and Training Reactors on Operator Licensing for Research and Test Reactors ML21288A0392021-10-18018 October 2021 September 14, 2021, Summary of Public Workshop on Scale/Melcor Source Term Demonstration Project - Pebble-Bed Molten-Salt-Cooled Reactor ML21181A3352021-07-0101 July 2021 June 23, 2021, Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21158A2232021-06-0808 June 2021 Meeting Summary for Ticap Workshop 3 ML21140A3892021-05-24024 May 2021 Riv Column 1 EOC 2020 Public Meeting Summary ML21132A2952021-05-14014 May 2021 Summary of Public Meeting to Discuss Technology Inclusive Content of Application Project ML21117A0262021-05-0505 May 2021 Summary of Teleconference with Entergy Operations, Inc. to Discuss Forthcoming LAR Concerning Reactor Coolant System Primary Activity and Primary-to-Secondary Leak Rate ML20337A1572020-12-0808 December 2020 Summary of Teleconference Meeting with Entergy Operations, Inc. to Discuss the Forthcoming Supplemental Response Concerning Generic Letter 2004-02 for Arkansas Nuclear One, Units 1 and 2 ML20287A4012020-10-26026 October 2020 Summary of September 17, 2020, Meeting with Entergy to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Request to the Extend Allowable Outage Time for the Emergency Cooling Pond ML20260G9992020-09-16016 September 2020 Summary of August 4, 2020, Teleconference Meeting with Entergy Operations, Inc. to Discuss Proposed License Amendment Request for Arkansas Nuclear One, Units 1 and 2 Regarding Adoption of 10 CFR 50.69 ML20189A2832020-07-0707 July 2020 Summary of Region IV Annual Assessment Public Meeting ML20153A2252020-06-0404 June 2020 April 29, 2020, Summary of Meeting with Entergy Operations, Inc. to Discuss a Proposed Relief Request Use of Carbon Fiber Reinforced Polymer Piping for Underground Service Water Piping at Arkansas Nuclear One, Units 1 and 2 ML19326A3152019-12-0303 December 2019 Summary of November 18, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request for an Alternative to Supplemental Valve Position Indication Testing Requirements ML19182A0332019-07-10010 July 2019 Summary of Teleconference with Entergy Operations, Inc. Regarding Proposed License Amendment Request Revised Fuel Handling Analysis and Adoption of Various TSTF Travelers for Arkansas Nuclear One, Unit 2 ML19191A1882019-07-0909 July 2019 Joint Annual Assessment Meeting (Webinar) for Pennsylvania Power Plants - Meeting Summary ML19162A0272019-06-21021 June 2019 Summary of June 4, 2019, Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Extend the Test Interval for Safety Relief Valves ML19036A8832019-02-0707 February 2019 Summary of Meeting with Exelon Generation Company, LLC Regarding a Planned Request to Use ASME Code Case N-879 ML18354B1712019-01-0202 January 2019 Summary of December 19, 2018, Meeting with Exelon Generation Company, LLC Regarding the Use of Boiling Water Reactor Vessel and Internals Project Guidelines ML18325A1712018-11-28028 November 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Planned Fleet License Amendment Request to Revise Technical Specifications for High Radiation Areas ML18176A1312018-06-21021 June 2018 Summary of Annual Assessment Meeting with Entergy Operations, Inc., Regarding 2017 Performance of Arkansas Nuclear One ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing ML18107A4972018-04-27027 April 2018 April 10, 2017, Summary of Public Meeting with Entergy Nuclear Operations, Inc. Regarding Upcoming License Amendment Request to Add Setpoint Verification Requirement to Technical Specification Surveillance Requirements ML18108A0652018-04-18018 April 2018 Annual Assessment Meeting Summary and Attendance List 2018 ML18099A0712018-04-16016 April 2018 March 20, 2018, Summary of Meeting with the Nuclear Energy Institute and Other Industry Representatives Regarding the Surveillance Frequency Control Program ML17353A1542017-12-22022 December 2017 Summary of Public Meeting with Entergy Operations, Inc., on Proposed Changes to Emergency Plans to Revise Emergency Action Levels for Arkansas; Grand Gulf; River Bend; and Waterford (EPID-L-2017-LRM-0060) ML17132A2592017-05-19019 May 2017 TMI Annual Assessment Meeting (4-20-17) Summary ML16228A0622016-08-15015 August 2016 Summary of July 26, 2016, Public Meeting on Status of Associated Effects Submittals Related to the Reevaluated Flood Hazards at Exelon Generation Company, LLC Sites as Part of the Response to Near-Term Task Force Recommendation 2.1, Floodin 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 ML16085A3292016-04-0606 April 2016 Summary of March 22, 2016, Meeting with Exelon Generation Company, LLC, on Proposed License Amendment Request to Adopt ANSI 3.1-2014 Operating Training Standards ML16091A0782016-03-31031 March 2016 Annual Assessment Meeting Summary on 03/23/2016 ML16040A2182016-02-11011 February 2016 January 21, 2016, Summary of Meeting with Exelon Generation Company, LLC Licensing Managers ML15348A1882016-01-0606 January 2016 Summary of October 28, 2015, Closed Meeting Between Representatives of the U.S. Army Corps of Engineers, U.S. Nuclear Regulatory Commission and Entergy Nuclear Operations, Inc. to Discuss Flood Analysis Associated with Arkansas Nuclear One, ML15350A1962015-12-30030 December 2015 Summary of the Conference Call Regarding Fall 2015 Steam Generator Tube Inservice Inspection ML15267A4182015-09-24024 September 2015 Summary of Meeting to Discuss Arkansas Nuclear One Performance Improvement ML15225A2542015-08-14014 August 2015 Summary of 4/20-23/2015 Audit in Support of Request to Adopt National Fire Protection Association NFPA 805, Performance-Based Standard for Fire Protection for LWR Generating Plants (2001 Edition) ML15132A1752015-05-21021 May 2015 Summary of Annual Assessment Meeting with Entergy Operations Inc., Regarding ANO 2014 Performance ML15089A1642015-04-27027 April 2015 Summary of February 25, 2015, Partially Closed Meeting with Industry Stakeholders Regarding the Babcock and Wilcox Loss of Coolant Accident Evaluation Model Analysis ML15104A6382015-04-14014 April 2015 Summary of Annual Assessment Meeting - Three Mile Island Nuclear Station, Unit 1 ML15007A4782015-01-15015 January 2015 Summary of July 15-18, 2013, Arkansas Nuclear One, Unit 2, Audit Associated with License Amendment Request to Transition to National Fire Protection Association Standard 805 2024-03-07
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- 1< February 13, 2012 LICENSEE: Exelon Generation Company, LLC (Exelon) and Entergy Operations, Inc.
(Entergy)
FACILITY: Three Mile Island, Unit 1 and Arkansas Nuclear One, Unit 1
SUBJECT:
SUMMARY
OF JANUARY 26,2012, MEETING WITH EXELON AND ENTERGY TO DISCUSS RECENT ONCE-THROUGH STEAM GENERATOR INSERVICE INSPECTION RESULTS (TAC NOS. ME7700 AND ME7701)
On January 26,2012, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of licensees Exelon Generation Company, LLC (Exelon), and Entergy Operations, Inc. (Entergy). Representatives from AREVA also participated in the meeting. The purpose of the meeting was to discuss recent inservice inspection results at Three Mile Island, Unit 1 (TMI-1) and Arkansas Nuclear One, Unit 1 (ANO-1). Specifically, the meeting was held to discuss tube-to-tube wear indications in the replacement once-through steam generators at TMI-1 and ANO-1 Both licensees assessed the significance of the wear indications and concluded their units could safely operate until the next scheduled inspection. Exelon presented the detailed inspection results from their most recent refueling outage in the fall of 2011, where the tube-to-tube degradation mechanism was first detected. This refueling outage was the first inspection opportunity after the replacement of the steam generators in the fall of 2009. Entergy presented an analysis of past tube inspection results at ANO-1, which were re-examined in light of the TMI-1 operating experience. The Entergy presentation included an explanation of why the tube to-tube wear was mischaracterized in previous refueling outages between 2007 and 2011.
AREVA presented the status of the root cause investigation, which has an estimated completion date of May 31, 2012. Detailed handout material from the meeting may be found at Agencywide Documents Access and Management System (ADAMS) Accession Nos. ML120250105 (TMI-1 slides), ML120250111 (ANO-1 slides) and ML120250116 (AREVA slides). The NRC staff plans to continue to monitor and evaluate this new wear mechanism, including the results of the root cause investigation.
More specifically, during the meeting, several items were discussed/clarified by the participants, including the following:
- No loose parts or potential loose part indications were detected during the TMI-1 outage.
- The conclusion at TMI-1 that the indications faced each other was based on examinations of six pairs of tubes.
- On slide 13 of the TMI-1 presentation, the presenter clarified that the difference between the number of tubes with indications identified by "either the Primary or Secondary" analyst and the total number of tubes with indications, is the number
- 2 of additional calls made by the resolution analyst as a result of a more detailed review of the data once an indication was identified (e.g., in the "A" steam generator, 33 additional tubes were identified by the resolution analysts that were
=
not identified by either the primary or secondary analysis (74 - 41 33)).
- The licensee for TMI-1 clarified that the +Point sizing method for flat wear was determined to be the correct technique for tube-to-tube wear in once-through steam generators based on the profiles and sizes of the indications.
- At TMI-1, there was one tube that had tube-to-tube wear between both the ]'h and 8th , and the 8th and 9th , tube support plate. The licensee clarified after the meeting that, including this tube, there were 5 tubes with wear between the 7th and 8th tube support plate, and 2 tubes with wear between the 4th and 5th tube support plate. All other tube-to-tube wear indications were between the 8th and 9th tube support plate.
- Regarding slide 18 of the ANO-1 presentation, the presenter clarified, in response to an NRC staff question, that similar plots had not been performed for the new indications identified in refueling outages '1 R20 and 1R21.
- The voltages reported on slide 19 of the ANO-1 presentation are bobbin voltages.
- Regarding slide 19 of the ANO-1 presentation, the presenter clarified that the "Total Present" column represents the results of the re-analysis while the other values represent the results of the original analysis. Looking at the data from refueling outage 1R23 in the "A" steam generator, it was explained that there are a total of 48 tube-to-tube wear indications. Of those 48 indications, 25 were not reported by the analysts (23 had voltages less than or equal to 0.49 volts and 2 had voltages greater than or equal to 0.50 volts). As a result, 23 indications were not reported by either the primary or secondary data analysts (Le., 48 - 25 23). =
Since only 17 indications were retained by the resolution analysts, this means that the resolution analysts eliminated 6 of the indications during their review of the data (23 - 17 = 6).
- Regarding slide 36 of the ANO-1 presentation, the experience cited is with the X-probe.
- The licensee for ANO-1 (Entergy) indicated it would consider performing more bobbin probe inspections within the area where tube-to-tube wear has been observed to provide confidence that the conditions are bounded.
- The voltage normalization for the eddy current probes is slightly different at ANO-1 than at TMI-1. At ANO-1, the absolute channel (channel 6) is set to 5 volts whereas at TIVII-1 it is set to 4 volts.
- Both ANO-1 and TMI-1 have tubing fabricated by Sumitomo.
- 3 No proprietary information was discussed at the meeting. Several members of the public were in attendance, including two representatives from the Bureau of Radiation Protection, Nuclear Safety Division, Pennsylvania Department of Environmental Protection (PADEP). The PADEP made two comments: (1) international operating experience should be considered in the investigation of this issue, and (2) the root cause should explain why it appears that the "B" steam generator at both sites appears to have more wear indications attributed to this mechanism than the "A" steam generator. The NRC staff responded that there would not likely be any relevant international operating experience because, to the staffs knowledge, the once through steam generator design is not used outside of the U.S. The NRC and AREVA acknowledged the comment about the "B" versus "AI) steam generator, and AREVA indicated that it would be addressed in the root cause investigation. No other comments from members of the public were received. A list of attendees is provided in the Enclosure.
Please direct any inquiries to me at 301-415-2833 or peter.bamford@nrc.gov.
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Peter Bamford Plant licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation Docket Nos. 50-289 and 50-313
Enclosure:
List of Attendees cc w/encl: Distribution via ListServ
LIST OF ATTENDEES JANUARY 26,2012, MEETING WITH EXELON GENERATION COMPANY. LLC AND ENTERGY OPERATIONS COMPANY, INC ONCE-THROUGH STEAM GENERATOR INSERVICE INSPECTION RESULTS AT THREE MILE ISLAND, UNIT 1 AND ARKANSAS NUCLEAR ONE, UNIT 1 Exelon Entergy Mark T orborg Jamie McCoy Jay Smith Danny Hughes Greg Ciraula Dan Meatheany William Carsky Bob Clark Steven Queen Steve Brown Wendi Croft Ralph DeSantis David Atherholt (via teleconference)
Peter Bamford, NRR AREVA Kenneth Karwoski, NRR Andrew Johnson, NRR Jeff Fleck Emmett Murphy, NRR Jim Begley Kaly Kalyanam, NRR Jeff Grigsby Michael Markley, NRR Mike Boudreaux Meena Khanna, NRR John Remark Jeffrey Whited, NRR Michael Street Charles Harris, RES Kendall Johnson James Drake, RIV (via teleconference)
Jeff Brown (via teleconference) Thomas Burns, RI (via teleconference)
Abin Fairbanks, RIV (via teleconference)
PUBLIC (via teleconference) Scott Bussey, HRTD (via teleconference)
Dennis Dyckman, PA state Public (in-person)
Rich Janati, PA State Eric Epstein, TMI Alert Dan Mays, Duke Energy David Goetcheus, TVA Tim Thulien, Duke Energy Dan Gilliland, Patriot-News Jeff Millman, B&W Peter King, B&W Richard Klarner, B&W Revi Kizhatil, B&W Daniel Gammage, B&W Steve Fluit, B&W Dave Garren, FENOC
Package ML120270400; Meeting Notice ML120050036; Meeting Handouts ML1120250105, ML120250111, ML120250116; Meeting Summary ML120270416 IloFFICE DORULPLI-2/PM DE/SLS DORULPL4/PM DORLILPLI-2/LA DORLILPLI-2/BC INAME P8amford KKarwoski KKalyanam ABaxter MKhanna ilDATE ! 01 131 112 02 101/12 02102/12 02/09/12 02/13/12