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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 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
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GL 2004-02 C LOSE O UT FOR T HREE M ILE I SLAND U NIT 1 MEETINGWITH NRC OCTOBER 30, 2014 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMI Purpose of Meeting:
- Communicate current TMI plan for closure of GL 2004 02 2004-02 .*Provide updated schedule of activities related to closureofGL2004
-02forTMI.closure of GL 2004 02 for TMI. *Identify any areas of concern that can be addressed durin g the TMI strainer testin g p ro g ram.ggpg*Identify areas where additional discussion/review may be required to ensure successful closure of GL 200402fThMilIldUi1 2004-02 f or Th ree Mil e I s l an d U n i t 1.2 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMIIn July, 2012, NRC provided three options for closure of GSI-191*: Option1:Compliancebasedonapprovedmodels Option 1: Compliance based on approved models oPlants must meet "clean plant criteria" or oHave sufficiently low strainer bypass and oMeetthe15gramperfuelassemblylimit o Meet the 15 gram per fuel assembly limitOption 2: Mitigative measures and alternative methods2a -Deterministic Resolution Path2b -Full Risk-Informed Resolution Path O ption 3: Different re g ulator y treatments for strainer pgyand in-vessel effects oUse deterministic approach for strainer and a risk-informed approach to in-vessel.
oThis option only conceptually defined in 2012 and is still under development.
GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMITMI selected Option 2a -complete additional modifications and pursue refinements to evaluation methods and acceptance criteria.*{TMIpreioslapplieda7DZOIforNkoninslationThepdated
{TMI pre v io u sl y applied a 7D ZOI for N u kon ins u lation. The u pdated analyses and testing will apply the 17D ZOI.}TMIcommittedto:
TMI committed to:*Replace the NUKON insulation currently installed on the pressurizer with Metallic Reflective Insulation (MRI) in T1R21 (Fall2015).(Fall 2015). *Complete strainer head loss testing based on the reduced strainer debris load by 12/31/15
- Re-evaluatestrainerbypassby7/31/16 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.
- TMILetter(TMI 12148)toUSNRCdatedMay162013 TMI Letter (TMI-12-148) to USNRC dated May 16 , 2013.4 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMICurrent 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 blanketinsulationonthepressurizerwithMRIinfall blanket insulation on the pressurizer with MRI in fall 2015 refueling outage (T1R21).*Submit final u pdated su pp lemental res ponse to the ppppNRC in 2016 pending completion of the PWROG efforts.5 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMI Strainer test sequence:Single Top Hat Bypass Test -November 2014This 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 2014This 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 replacementonthepressurizer.Thefinaldecisionforthescopeofinsulation replacement on the pressurizer.
The final decision for the scope of insulation replacement in T1R21 will be determined by the test results.Strainer Bypass Test -December 2014 Th e inf o rm at i o n ga in ed in t h e s in g l e top h at bypass test will be used to eoatogaedtesgetopatbypasstestbeusedtodevelop the test plan/procedures for the final bypass test.Test plans and procedures are currently being developed.
6 GL 2004 GL 2004--02 Cl ose O u t f or 02 Cl ose O u t f or TMI TMITMI pressurizer is currently insulated entirely with Nukon blanket insulation. TtifliNkith B A Two op ti ons for rep l ac i ng N u k on w ith MRI will be investigated:Option A: replace Nukon insulation abovethesupportregionwiththe Pi above the support region with the exception of the upper head.Option B: replace Nukon insulation in alllocationsexceptupperheadand P ressur i zer Support Region all locations except upper head and inside the support.The head loss test se q uence will B qdetermine which option will result in acceptable NPSH for the ECCS pumps and acceptable maximum strainer DP.
7 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMIEstimated debris reduction:*Option A results in approximately 46% reduction in the lfblktiltithi vo l ume o f bl an k e t i nsu l a tion on th e pressur i ze r*Option B results in approximately 81% 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' dditithitbt an d cre diti ng th e pressur i zer suppor t as a ro b us t barrier (Option C).
{Following insulation replacement on the pressurizer, some small amounts of blanket insulation will remain on piping and components within the ZOI
.}8 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMITMI 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 blibdbttithtfdf assem bl y i s b ase d on b ypass t es ti ng th a t was per f orme d f or another utility with an Enercon top hat strainer similar to TMI's.The TMI specific bypass test is expected to provide a lower bypass fraction.
9 GL 2004 GL 2004--02 Close Out for TMI 02 Close Out for TMI Proposed Debris Preparation Protocol for Head Loss and Final Bypass Tests*
- Debriscategorizedassmallorlargepiecesandintact
- Debris categorized as small or large pieces and intact blankets will be prepared as follows:
Insulation torn into 1"-4" pieces by hand Torninsulationwillbewettedusinggardenhosenozzle Torn insulation will be wetted using garden hose nozzleWetted debris will be mixed using a paddle to ensure even moisture penetration Additional water spray applied to ensure small pieces are separated from eachother each otherPreparation ends when it has been confirmed that the pieces readily separate within the slurry and no pieces remain floating Fidbiillbdddhkfi
- Fi ne d e b r i s w ill b e a dd e d to t h e tan k fi rst*Fiber will be prepared only as 'fines' for the single top hat bypass test.
10