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MONTHYEARML0515204222005-06-0303 June 2005 TMI - RAI Potential Impact of Debris Blockage on Emergency Sump Recirculation at Pressurized-Water Reactors Project stage: RAI ML0603801532006-02-0909 February 2006 RAI Response to Generic Letter 2004-02, Potential Impact of Debris Blockage on Emergency Recirculation During Design-Basis Accidents at Pressurized Water Reactors Project stage: RAI ML0818306152008-07-0101 July 2008 Electronic Transmission, Draft Request for Additional Information Regarding Generic Letter, 2004-02 Supplemental Response Project stage: Draft RAI ML0820407552008-08-12012 August 2008 Request for Additional Information Regarding Generic Letter 2004-02, Supplemental Response Project stage: RAI ML0831703462008-11-10010 November 2008 Response to Request for Additional Information Related 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 ML0918908482009-07-23023 July 2009 Request for Additional Information Regarding Generic Letter 2004-02, Supplemental Response Project stage: RAI ML0922505512009-08-21021 August 2009 Summary of August 11, 2009, Meeting with Exelon to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML0922505802009-08-28028 August 2009 Forthcoming Conference Call with Exelon Generation Company, LLC, to Discuss Three Mile Island, Unit 1, Generic Letter 2004-02 Supplemental Response Project stage: Request ML0926504072009-09-23023 September 2009 Draft RAI Responses Provided in Support of Discussions with NRC on Sept. 23, 2009 Project stage: Request ML0926705032009-09-30030 September 2009 Summary of Meeting with Exelon to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML0927306232009-10-0606 October 2009 Notice of Conference Call with Exelon Generation Company, LLC, to Discuss Three Mile Island, Unit 1, Generic Letter 2004-02 Supplemental Response Project stage: Request ML0929501582009-11-0202 November 2009 Summary of Category 1 Public Meeting with Exelon to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information Project stage: RAI ML14300A5452014-10-30030 October 2014 10/30/2014, Meeting Slide with NRC Regarding GL 2004-02 Close Out for Three Mile Island, Unit 1 Project stage: Request 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 Project stage: Meeting 2009-11-02
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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 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 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 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 ML18120A1772018-05-0101 May 2018 Summary of Meeting with Exelon Generation Company, LLC Regarding Draft Guidance for Emergency Response Organization Staffing ML18108A0652018-04-18018 April 2018 Annual Assessment Meeting Summary and Attendance List 2018 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 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 ML15350A1962015-12-30030 December 2015 Summary of the Conference Call Regarding Fall 2015 Steam Generator Tube Inservice Inspection 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 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 ML14133A0592014-07-0101 July 2014 Summary of Closed Meeting Between Representatives of the Army Corps of Engineers, Nuclear Regulatory Commission, Federal Energy Regulatory Commission, Exelon Generation Co, LLC, and PPL Susquehanna, LLC, to Discuss Dam Failure Analysis.. ML14119A0292014-04-29029 April 2014 Annual Assessment Meeting Summary for April 17, 2014 ML14015A3562014-01-24024 January 2014 Summary of Conference Calls Regarding the Fall 2013 Steam Generator Tube Inservice Inspection ML13262A1632013-09-23023 September 2013 Meeting Report - Three Mile Island, Unit 2, Post-Shutdown Decommissioning Activities Report Public Meeting ML13179A0932013-07-17017 July 2013 6/17/2013 - Summary of Meeting with Exelon to Discuss Recent Once-Through Steam Generator Tube-to-Tube Wear at Three Mile Island, Unit 1 ML13141A6372013-05-21021 May 2013 5/7/2013 - Summary of Annual Assessment Meeting - Three Mile Island ML12110A3112012-05-0303 May 2012 4/10/2012 Summary of Public Meeting with Exelon Generation Company, LLC Regarding Its Future Submittal of Technical Specification Changes of Licensed Operator Eligibility Requirements ML12117A0022012-04-25025 April 2012 ROP-12 Annual Assessment Meeting Summary 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 ML1135501672011-12-28028 December 2011 Summary of Conference Calls with Exelon Generation Company, LLC to Discuss 2011 Steam Generator Tube Inspections ML1116500712011-06-14014 June 2011 Summary of Three Mile Island Annual Assessment Meeting, June 7, 2011 ML1108109722011-03-25025 March 2011 Summary of March 14, 2011, Meeting with Exelon to Discuss Proposed Main Steam Safety Valve License Amendment Request ML1036305532011-01-0606 January 2011 Summary of Meeting (Teleconference) with Exelon to Discuss RAI Regarding the Implementation of an Emergency Action Level Scheme Based on NEI 99-01, Rev. 5 ML1031902892010-11-22022 November 2010 Summary of October 19, 2010 NRC Petition Board Meeting for 2.206 Petition Regarding TMI-2 Decommissioning Funding Financial Assurance ML1020700252010-07-27027 July 2010 Summary of Category 1 Meeting with Exelon to Discuss Re-Submittal of Its Cyber Security Plan ML1015301202010-05-27027 May 2010 Memo Annual Assessment Meeting Summary for Three Mile Island ML0930804802009-11-19019 November 2009 Meeting Summary of 10/22/2009 Meeting Regarding Its Power Uprate Project Plan ML0930104552009-11-0303 November 2009 Once-Through Steam Generator Tube Loads Under Conditions Resulting from Postulated Breaks in Reactor Coolant System Upper Hot-Leg Large-Bore Piping ML0929406112009-11-0202 November 2009 Summary of Category 1 Public Meeting with Exelon to Discuss Proposed Control Rod Drive Control System License Amendment Request ML0929501582009-11-0202 November 2009 Summary of Category 1 Public Meeting with Exelon to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information ML0926705032009-09-30030 September 2009 Summary of Meeting with Exelon to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information ML0922505512009-08-21021 August 2009 Summary of August 11, 2009, Meeting with Exelon to Discuss Generic Letter 2004-02 Supplemental Response Request for Additional Information ML0919803632009-08-20020 August 2009 Summary of Licensing Counterparts Meeting with Exelon Generation Company, to Discuss Licensing Practices and Processes ML0912801592009-05-0707 May 2009 TMI Annual Assessment Meeting 4/2/09 - Summary ML0906204192009-03-0909 March 2009 02/24/2009 Summary of Public Meetings on the Draft Supplemental Environmental Impact Statement Regarding the Three Mile Island Nuclear Station, Unit 1, License Renewal Review (TAC No. MD7702) Ltr ML0833100732008-11-26026 November 2008 Summary of Meeting with Exelon to Review the Results of Security Organization Safety Conscious Work Environment (SCWE) Surveys at Exelon Nuclear Operating Reactors ML0830900532008-11-17017 November 2008 License Renewal Application, Summary of Conference Call with Amergen Energy Company Regarding Responses to Request for Additional Information for Sections 2.3.3 and 2.3.4 ML0826821322008-10-10010 October 2008 Summary of Meeting with Amergen to Discuss Planned License Amendment Request Relating to Rod Control System Replacement ML0821207272008-08-0505 August 2008 07/17/2008 Summary of Telephone Conference Call Between the NRC and Amergen Energy Company, Llc., Concerning Follow-up Questions Pertaining to Three Mile Island, Unit 1 License Renewal Environmental Review and Site Audit ML0815606662008-06-12012 June 2008 Summary of Conference Call with Amergen Energy Company, LLC, to Discuss the Severe Accident Mitigation Alternatives Requests for Additional Information for Three Mile Island Nuclear Station, Unit 1 2024-03-07
[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
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Text
LICENSEE:
Exelon Generation Company, LLC FACILITY:
Three Mile Island Nuclear Station, Unit 1
SUBJECT:
PUBLIC MEETING WITH THE U.S. NUCLEAR REGULATORY COMMISSION AND EXELON GENERATION COMPANY, LLC REGARDING GENERIC LETTER 2004-02 (TAC NO. MC4724) On October 30, 2014, a Category 1 public meeting was held between the U.S. Nuclear Regulatory Commission (NRC) and representatives of Exelon Generation Company, LLC (Exelon) at NRC Headquarters, One White Flint North, 11555 Rockville Pike, Rockville, Maryland.
The purpose of the meeting was to discuss planned testing for Generic Letter (GL) 2004-02, "Potential Impact of Debris Blockage on Emergency Recirculation During Design Basis Accidents at Pressurized-Water Reactors," associated with Three Mile Island Nuclear Station, Unit 1 (TMI-1 ). The meeting notice and agenda, dated October 1, 2014, is available in the Agencywide Documents Access and Management System (ADAMS) under Accession No. ML 14301A322.
The meeting began at 9:00a.m. Eastern Daylight Time (EDT) with opening remarks by the NRC staff followed by introductions of the attendees.
A list of attendees is provided in Enclosure
- 1. Exelon presented information (See Enclosure 2 or ADAMS Accession No. ML 14300A545).
Exelon selected Option 2a to close-out GL 2004-02 for TMI-1. Option 2 is the "mitigative measures and alternative methods;" Option 2a is the "deterministic resolution path." By letter dated May 16, 2013 (ADAMS Accession No. ML 13137A309), TMI-1 stated it would complete modifications and pursue refinements to evaluation methods and acceptance criteria.
TMI-1 committed to:
- Replace the NUKON currently installed on the pressurizer with Metallic Reflective Insulation (MRI) in the fall 2015 refueling outage (RFO).
- Complete strainer head loss testing based on the reduced strainer debris load by December 31, 2015.
- Re-evaluate strainer bypass by July 31, 2016.
- Submit a final updated supplemental response to support closure of GL 2004-02 for TMI-1 by June 1, 2017. The current Exelon plan/schedule for TMI-1 is to:
- Conduct strainer head loss and bypass testing at Alden Research Laboratory (Holden, MA) in 2014.
- Based on strainer head loss test results, replace NUKON blanket insulation on the pressurizer with MRI during the fall 2015 RFO.
- Submit final updated supplemental response to the NRC in 2016 pending completion of the Pressurized-Water Reactor Owners' Group efforts. Exelon proposed the following strainer test sequence:
(1) single top hat bypass test in November 2014, (2) strainer head loss testing in December 2014, and (3) strainer bypass test in December 2014. The single top hat bypass test will evaluate the effect of debris concentration/mixture and water chemistry on the strainer bypass. The results of this "sensitivity" test will be factored into a large scale bypass test. The strainer head loss test sequence will consist of a thin bed test followed by one or two full load head loss tests, as required, to determine the limiting debris quantity.
A test plan has been developed to evaluate several options for insulation replacement on the pressurizer.
The final decision for the scope of the insulation replacement during the fall 2015 RFO will be determined by the test results. The information gained in the single top hat bypass test will be used to develop the test plan/procedures for the final strainer bypass test. The TMI-1 pressurizer is currently insulated entirely with NUKON blanket insulation.
Exelon is investigating two options for replacing NUKON with MRI:
- Option A: replace NUKON insulation above the support region with the exception of the upper head, and
- Option 8: replace NUKON insulation in all locations with the exception of the upper head and inside the support. Exelon will use the head loss test sequence results to determine which option will result in acceptable net positive suction head for the emergency core cooling system pumps and acceptable maximum strainer differential pressure.
Exelon has estimated the debris reduction for TMI-1:
- Option A results in approximately 46-percent reduction in the volume of blanket insulation on the pressurizer,
- Option B results in approximately 81-percent reduction in the volume of blanket insulation on the pressurizer, and
- If necessary, a further reduction in the volume of fiber debris at the strainer can be achieved by removing the insulation currently included in Option B as "margin" and crediting the pressurizer support as a robust barrier (Option C). TMI-1 is continuing to follow the PWROG efforts to establish the allowable debris limits for vessel effects. The Exelon current calculated TMI-1 bypass of 34 grams fiber per fuel assembly is based on bypass testing that was performed for another utility with an Enercon top hat strainer similar to TMI-1. Exelon expects that the TMI-1 specific bypass test will provide a lower bypass fraction.
Exelon has proposed debris preparation protocol for head loss and final bypass tests to include the following:
fine debris added to the tank first, insulation torn into 1 "-4" pieces by hand, torn insulation to be wetted using garden hose nozzle, wetted debris will be mixed using a paddle to ensure even moisture penetration, additional water spray applied to ensure small pieces are separated from each other, and preparation ends when it has been confirmed that the pieces readily separate within the slurry and no pieces remain floating.
The NRC staff queried the licensee and vendor about the strainer test, questioning if it will include multiple top hats and chemical effects. Exelon and Enercon responded that the strainer test would include 9 top hats in a 3 by 3 array and it would include chemical effects. The NRC staff questioned if insulation had been changed at TMI-1. Exelon stated that during the steam generator (SG) replacement in 2007, that NUKON insulation was replaced with MRI on the SGs and some hot leg piping NUKON insulation was replaced with MRI. The NRC staff queried Exelon regarding if velocity sensitivity was going to be performed for the testing. Exelon responded that velocity sensitivity would not be performed.
The NRC staff questioned what temperature and range would the testing be performed.
Exelon responded that the testing would be performed at 120 degrees Fahrenheit CF) with a range of plus or minus 5°F. The NRC queried whether the testing included bypass eliminators, and Exelon responded that it does. The NRC questioned Exelon and Enercon if the fines are made according to the Nuclear Energy Institute (NEI) protocol, and the licensee responded yes. The NRC staff queried Exelon and Enercon if settling would be allowed during the testing, and Enercon responded that settling would not be allowed. The NRC staff asked Exelon to provide the exact dates for the testing, so the NRC staff could witness the testing, if desired. The NRC staff stated that they would look at the guidance for making small debris for the testing. No members of the public were in attendance.
Public Meeting Feedback forms were not received.
At this meeting, the NRC staff made no regulatory decisions regarding the merits of the proposed close-out of GL 2004-02 at TMI-1. The meeting was adjourned at 9:54a.m. EDT. Please direct any inquiries to me at 301-415-3100, Docket No.: 50-289
Enclosures:
1 . List of Meeting Attendees
- 2. Exelon Presentation Slides cc w/encls: Distribution via Listserv . Lamb, Senior Project Manager nt Licensing Branch 1-2 Di is"on of Operating Reactor Licensing Of
- e of Nuclear Reactor Regulation LIST OF ATTENDEES PUBLIC MEETING BETWEEN EXELON GENERATION COMPANY LLC (EXELON) AND THE U.S. NUCLEAR REGULATORY COMMISSION (NRC) STAFF THURSDAY, OCTOBER 30, 2014 9:00 a.m. -11:00 a.m. ONE WHITE FLINT NORTH, ROOM 0-8B6 NAME ORGANIZATION John Stang NRC Paul Klein NRC Steve Smith NRC John Lamb NRC Matt Yoder NRC Andrea Russell NRC Ashley Guzzetta NRC Robert Gladney NRC Dave Werkheiser NRC Frank Mascitelli Exelon Dave Reese Exelon Richard Sievers Exelon Pat Bennett Exelon Mike Fitzwater Exelon Caitlin Keane Exelon Kip Walker Enercon Tim Sande Enercon Ludwig Haber Alden Lab Enclosure 1
Enclosure 2
G) -f ::1: 1\) :::c 0 m o m z s: 6 --csl\l -1 r--""m 0 -r-0 )> en z m c 0 c: -1 GL 2004-02 Close Out for TMI Purpose of Meeting:
- Provide updated schedule of activities related to closure of GL 2004-02 for TMI.
- Identify any areas of concern that can be addressed during the TMI strainer testing program.
- Identify areas where additional discussion/review may be required to ensure successful closure of GL 2004-02 for Three Mile Island Unit 1. 2 £!!!' Exelon GL 2004-02 Close Out for TMI In July, 2012, NRC provided three options for closure of GSI-191*: Option 1: Compliance based on approved models o Plants must meet "clean plant criteria" or o Have sufficiently low strainer bypass and o Meet the 15 gram per fuel assembly limit Option 2: Mitigative measures and alternative methods 2a -Deterministic Resolution Path 2b -Full Risk-Informed Resolution Path Option 3: Different regulatory treatments for strainer and in-vessel effects o Use deterministic approach for strainer and a risk-informed approach to in-vessel.
only conceptually defined in 2012 and is still under development.
- SECY-12-0093 GL 2004-02 Close Out for TMI TMI selected Option 2a -complete additional modifications and pursue refinements to evaluation methods and acceptance criteria.*
{TMI previously applied a 70 ZOI for Nukon insulation.
The updated analyses and testing will apply the 170 ZOI.} TMI committed to:
- Replace the NUKON insulation currently installed on the pressurizer with Metallic Reflective Insulation (MRI) in T1 R21 (Fall 2015).
- Complete strainer head loss testing based on the reduced strainer debris load by 12/31/15
- Re-evaluate strainer bypass by 7/31/16
- Submit a final updated supplemental response to support closure of GL 2004-02 for TMI Unit 1 by 6/1/17. *TMI Letter (TMI-12-148) to USNRC dated May 16, 2013. 4 GL 2004-02 Close Out for TMI Current TMI plan/schedule:
- Conduct strainer head loss and bypass testing @ Alden Research Laboratory (Holden, MA) in 2014
- Based on strainer head loss test results, replace Nukon blanket insulation on the pressurizer with MRI in fall 2015 refueling outage (T1 R21 ).
- Submit final updated supplemental response to the NRC in 2016 pending completion of the PWROG efforts. 5 :Exelon GL 2004-02 Close Out for TMI Strainer test sequence:
Single Top Hat Bypass Test-November 2014 This testwill evaluate the effect of debris concentration/mixture and water chemistry on strainer bypass. The results of this 'sensitivity' test will be factored into a large scale bypass test. Strainer Head Loss Testing-December 2014 This test sequence will consist of a thin bed test followed by one or two full load head loss tests as required to determine the limiting debris quantity.
A test plan has been developed to evaluate several options for insulation replacement on the pressurizer.
The final decision for the scope of insulation replacement in T1 R21 will be determined by the test results. Strainer Bypass Test-December 2014 The information gained in the single top hat bypass test will be used to develop the test plan/procedures for the final bypass test. Test plans and procedures are currently being developed.
6 1 & ¥J GL 2004-02 Close Out for .......------
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7 TMI TMI pressurizer is currently insulated entirely with Nukon blanket insulation.
Two options for replacing Nukon with MRI will be investigated:
Option A: replace Nukon insulation above the support region with the exception of the upper head. Option B: replace Nukon insulation in all locations except upper head and inside the support. The head loss test sequence will determine which option will result in acceptable NPSH for the ECCS pumps and acceptable maximum strainer DP. =--:-Exelon GL 2004-02 Close Out for TMI 8 Estimated debris reduction:
- Option A results in approximately 46°/o reduction in the volume of blanket insulation on the pressurizer
- Option B results in approximately 81 o/o reduction in the volume of blanket insulation on the pressurizer
- If necessary, a further reduction in the volume of fiber debris at the strainer can be achieved by removing the insulation currently included in Option B as 'margin' and crediting the pressurizer support as a robust barrier (Option C). {Following insulation replacement on the pressurizer, some small amounts of blanket insulation will remain on piping and components within the ZOI.} S"Exelon GL 2004-02 Close Out for TMI TMI is continuing to follow PWROG efforts to establish the allowable debris limits for in-vessel effects. The current calculated TMI bypass of 34 grams fiber/fuel assembly is based on bypass testing that was performed for another utility with an Enercon top hat strainer similar to TMI's. The TM I specific bypass test is expected to provide a lower bypass fraction.
' < 9 GL 2004-02 Close Out for TMI Proposed Debris Preparation Protocol for Head Loss and Final Bypass Tests*
- Debris categorized as small or large pieces and intact blankets will be prepared as follows: -Insulation torn into 1 "-4" pieces by hand -Torn insulation will be wetted using garden hose nozzle -Wetted debris will be mixed using a paddle to ensure even moisture penetration
-Additional water spray applied to ensure small pieces are separated from each other -Preparation ends when it has been confirmed that the pieces readily separate within the slurry and no pieces remain floating
- Fine debris will be added to the tank first *Fiber will be prepared only as 'fines' for the single top hat bypass test. 10 :Exelon Please direct any inquiries to me at 301-415-3100, or John.Lamb@nrc.gov.
Docket No.: 50-289
Enclosures:
- 1. List of Meeting Attendees
- 2. Exelon Presentation Slides cc w/encls: Distribution via Listserv DISTRIBUTION:
Public RidsNrrDoriLpi1-2Resource JStang, NRR PKiein, NRR SSmith, NRR IRA/ John G. Lamb, Senior Project Manager Plant Licensing Branch 1-2 Division of Operating Reactor Licensing Office of Nuclear Reactor Regulation MYoder, NRR RidsOpaMail Resource DWerkheiser, R-1 SKennedy, R-1 MDudek, EDO RidsNrrThreeMilelsland RidsNrrLAABaxter
RidsAcrsAcnw_MaiiCTR ADAMS Accession No.: Package: ML 14304A784, Summary: ML 14304A783, Slides: ML 14300A545 OFFICE LPL 1-2/PM LPL 1-2/LA LPL 1-2/BC LPL 1-2/PM NAME JLamb A Baxter MKhanna JLamb DATE 10/30/14 11/10/14 11/12/14 11/14/14 .. Off1c1al Agency Record