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| | number = ML060750803 | | | number = ML060750803 |
| | issue date = 03/22/2006 | | | issue date = 03/22/2006 |
| | title = 04/05/2006 - NRC Slide Presentation for Public Meeting Ref: Three Mile Island, Unit 1 Annual Assessment Performance CY2005 | | | title = NRC Slide Presentation for Public Meeting Ref: Three Mile Island, Unit 1 Annual Assessment Performance CY2005 |
| | author name = Bellamy R R | | | author name = Bellamy R |
| | author affiliation = NRC/RGN-I/DRP/PB7 | | | author affiliation = NRC/RGN-I/DRP/PB7 |
| | addressee name = | | | addressee name = |
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| | docket = 05000289 | | | docket = 05000289 |
| | license number = DPR-050 | | | license number = DPR-050 |
| | contact person = Bellamy R R Rgn-I/DRP/Br7/610-337-5200 | | | contact person = Bellamy R Rgn-I/DRP/Br7/610-337-5200 |
| | case reference number = MN 06-011 | | | case reference number = MN 06-011 |
| | package number = ML060680618 | | | package number = ML060680618 |
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| {{#Wiki_filter:Three Mile Island Unit 1 Three Mile Island Unit 1 Annual Assessment MeetingAnnual Assessment MeetingReactor Oversight Program Reactor Oversight Program | | {{#Wiki_filter:Three Mile Island Unit 1 Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania April 5, 2006 |
| --CY 2005CY 2005Nuclear Regulatory Commission Nuclear Regulatory Commission
| | |
| --Region IRegion IKing of Prussia, PennsylvaniaKing of Prussia, PennsylvaniaApril 5, 2006April 5, 2006 Purpose of Today's MeetingA public forum for discussion of the licensee's A public forum for discussion of the licensee's performanceperformanceNRC will address licensee performance issues NRC will address licensee performance issues Licensee will be given the opportunity to respond Licensee will be given the opportunity to respond and inform the NRC of new or existing programs to and inform the NRC of new or existing programs to maintain or improve their performance maintain or improve their performance AgendaIntroduction Review of Reactor Oversight ProcessNational Summary of Plant PerformanceDiscussion of Plant Performance ResultsLicensee Response and RemarksNRC Closing Remarks BreakNRC available to address public questions Region I OrganizationSamuel J. CollinsRegional AdministratorMarc L. DapasDeputy Regional AdministratorBrian E. HolianDirector Division of Reactor ProjectsDavid C. LewDeputy DirectorA. Randolph BloughDirector Division of Reactor SafetyMarsha K. GamberoniDeputy DirectorDr. Ronald R. BellamyBranch ChiefRegional SpecialistsThree Mile IslandResident InspectorsDavid M. KernJavier M. BrandProject EngineersRoy L. FuhrmeisterAndrew A. RosebrookRonald E. Cureton NRC RepresentativesNRC RepresentativesA. Randolph Blough, Director, Division of Reactor Safety -(610) 337-5126David M. Kern, Senior Resident Inspector-(717) 948-1165Javier M. Brand, Resident Inspector-(717) 948-1165Roy L. Fuhrmeister, Senior Project Engineer-(610) 337-5059Dr. Ronald R. Bellamy, Branch Chief-(610) 337-5200 NRC Performance GoalsSafety:Ensure protection of the public health and safety and the environmentSecurity:Ensure the secure use and management of radioactive materialsOpenness:Ensure openness in our regulatory processEffectiveness:Ensure that NRC actions are effective, efficient, realistic, and timelyManagement:Ensure excellence in agency management to carry out the NRC' strategic objective Reactor Oversight ProcessSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance Areas Examples of Baseline InspectionsEquipment Alignment ~80 hrs/yr Triennial Fire Protection ~200 hrs every 3 yrsOperator Response ~125 hrs/yrEmergency Preparedness ~80 hrs/yrRad Release Controls ~110 hrs every 2 yrsWorker Radiation Protection ~90 hrs/yrCorrective Action Program ~250 hrs every 2 yrsCorrective Action Case Reviews ~60 hrs/yr Significance ThresholdPerformance IndicatorsGreen:Baseline Inspection White:Requires more NRC oversightYellow:Requires more NRC oversight Red:Requires more NRC oversightInspection FindingsGreen:Very Low safety issue White:Low to moderate safety issueYellow:Substantial safety issue Red:High safety issue Action Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.DegradedCornerstoneUnacceptablePerformanceIncreasing Safety SignificanceIncreasing NRC Inspection EffortsIncreasing NRC/Licensee Management InvolvementIncreasing Regulatory Actions National Summary of Plant PerformanceStatus at End of CY 2005Licensee Response 84Regulatory Response 12Degraded Cornerstone 4Multiple/Repetitive Degraded Cornerstone3 Unacceptable 0Total103 National SummaryPerformance Indicator Results (at end of CY 2005)Green1850 White 4Yellow 0 Red 0Total Inspection Findings (CY 2005)Green849 White 10Yellow1Red0 Three Mile Island Assessment Results(Jan 1 -Dec 31, 2005)Operated SafelyRegulatory response column of the Action Matrix for the fourth quarter of 2005 (cornerstone objectives fully met)NRC will conduct baseline inspections during the next cycleNRC conducted a supplemental inspection during the week of February 27, 2006 related to the emergency preparedness white inspection findingThe results of the supplemental inspection are not yet final White Finding in Emergency Preparedness CornerstoneRelates to untimely conduct of required annual Relates to untimely conduct of required annual classroom retraining for some members of the classroom retraining for some members of the emergency response organizationemergency response organizationSupplemental Inspection conducted the week of Supplemental Inspection conducted the week of February 27, 2006February 27, 2006The results of the inspection are not finalThe results of the inspection are not final Three Mile Island Inspection Activities (Jan 1 (Jan 1 --Dec 31, 2005)Dec 31, 2005)5818 hours of inspection related activities2 resident inspectors assigned to the site12 regional inspections5 team inspectionsInspection findings9 findings of very low safety significance (green)1 finding of low to moderate safety significance (white)1 Severity Level IV Violation (Traditional Enforcement)
| | Purpose of Todays Meeting z A public forum for discussion of the licensees performance z NRC will address licensee performance issues z Licensee will be given the opportunity to respond and inform the NRC of new or existing programs to maintain or improve their performance |
| Three Mile Island Annual Assessment Summary(Jan 1 -Dec 31, 2005)AmerGenoperated Three Mile Island Unit 1 in a manner that preserved public health and safetyRegulatory Response Column of the Action MatrixOne White finding identified (EP performance deficiency relating to annual classroom retraining)NRC plans baseline inspections at TMI for the remainder of the assessment period Licensee Response and Remarks Contacting the NRCReport an emergency(301) 816-5100 (call collect)Report a safety concern: (800) 695-7403 Allegation@nrc.govGeneral information or questionswww.nrc.govSelect "What We Do" for Public Affairs Reference SourcesReactor Oversight Processhttp://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.htmlPublic Electronic Reading Roomhttp://www.nrc.gov/reading-rm.htmlPublic Document Room1-800-397-4209 (Toll Free)}} | | |
| | Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions |
| | |
| | Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Brian E. Holian A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety David C. Lew Marsha K. Gamberoni Deputy Director Deputy Director Dr. Ronald R. Bellamy Regional Specialists Branch Chief Three Mile Island Project Engineers Resident Inspectors Roy L. Fuhrmeister David M. Kern Andrew A. Rosebrook Javier M. Brand Ronald E. Cureton |
| | |
| | NRC Representatives z A. Randolph Blough, Director, Division of Reactor Safety |
| | - (610) 337-5126 z David M. Kern, Senior Resident Inspector |
| | - (717) 948-1165 z Javier M. Brand, Resident Inspector |
| | - (717) 948-1165 z Roy L. Fuhrmeister, Senior Project Engineer |
| | - (610) 337-5059 z Dr. Ronald R. Bellamy, Branch Chief |
| | - (610) 337-5200 |
| | |
| | NRC Performance Goals z Safety: Ensure protection of the public health and safety and the environment z Security: Ensure the secure use and management of radioactive materials z Openness: Ensure openness in our regulatory process z Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely z Management: Ensure excellence in agency management to carry out the NRC strategic objective |
| | |
| | Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response |
| | |
| | Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~200 hrs every 3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr |
| | |
| | Significance Threshold Performance Indicators Green: Baseline Inspection White: Requires more NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green: Very Low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue |
| | |
| | Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions |
| | |
| | National Summary of Plant Performance Status at End of CY 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103 |
| | |
| | National Summary z Performance Indicator Results (at end of CY 2005) |
| | Green 1850 White 4 Yellow 0 Red 0 z Total Inspection Findings (CY 2005) |
| | Green 849 White 10 Yellow 1 Red 0 |
| | |
| | Three Mile Island Assessment Results (Jan 1 - Dec 31, 2005) z Operated Safely z Regulatory response column of the Action Matrix for the fourth quarter of 2005 (cornerstone objectives fully met) z NRC will conduct baseline inspections during the next cycle z NRC conducted a supplemental inspection during the week of February 27, 2006 related to the emergency preparedness white inspection finding z The results of the supplemental inspection are not yet final |
| | |
| | White Finding in Emergency Preparedness Cornerstone z Relates to untimely conduct of required annual classroom retraining for some members of the emergency response organization z Supplemental Inspection conducted the week of February 27, 2006 z The results of the inspection are not final |
| | |
| | Three Mile Island Inspection Activities (Jan 1 - Dec 31, 2005) z 5818 hours of inspection related activities z 2 resident inspectors assigned to the site z 12 regional inspections z 5 team inspections z Inspection findings 3/4 9 findings of very low safety significance (green) 3/4 1 finding of low to moderate safety significance (white) 3/4 1 Severity Level IV Violation (Traditional Enforcement) |
| | |
| | Three Mile Island Annual Assessment Summary (Jan 1 - Dec 31, 2005) z AmerGen operated Three Mile Island Unit 1 in a manner that preserved public health and safety z Regulatory Response Column of the Action Matrix z One White finding identified (EP performance deficiency relating to annual classroom retraining) z NRC plans baseline inspections at TMI for the remainder of the assessment period |
| | |
| | Licensee Response and Remarks Contacting the NRC z Report an emergency (301) 816-5100 (call collect) z Report a safety concern: |
| | (800) 695-7403 Allegation@nrc.gov z General information or questions www.nrc.gov Select What We Do for Public Affairs |
| | |
| | Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)}} |
|
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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
MONTHYEARML24296B2132024-10-22022 October 2024 Slides for October 25, 2024, Meeting on Crane Clean Energy Center Regulatory Path to Restoring the Operating Reactor License Basis ML24040A0722024-02-13013 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. ML0813301832008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Written Comments ML0813301852008-05-0101 May 2008 License Renewal Environmental Scoping Meeting Handouts and Slides 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 2024-02-13
[Table view] |
Text
Three Mile Island Unit 1 Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania April 5, 2006
Purpose of Todays Meeting z A public forum for discussion of the licensees performance z NRC will address licensee performance issues z Licensee will be given the opportunity to respond and inform the NRC of new or existing programs to maintain or improve their performance
Agenda z Introduction z Review of Reactor Oversight Process z National Summary of Plant Performance z Discussion of Plant Performance Results z Licensee Response and Remarks z NRC Closing Remarks z Break z NRC available to address public questions
Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator Brian E. Holian A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety David C. Lew Marsha K. Gamberoni Deputy Director Deputy Director Dr. Ronald R. Bellamy Regional Specialists Branch Chief Three Mile Island Project Engineers Resident Inspectors Roy L. Fuhrmeister David M. Kern Andrew A. Rosebrook Javier M. Brand Ronald E. Cureton
NRC Representatives z A. Randolph Blough, Director, Division of Reactor Safety
- (610) 337-5126 z David M. Kern, Senior Resident Inspector
- (717) 948-1165 z Javier M. Brand, Resident Inspector
- (717) 948-1165 z Roy L. Fuhrmeister, Senior Project Engineer
- (610) 337-5059 z Dr. Ronald R. Bellamy, Branch Chief
- (610) 337-5200
NRC Performance Goals z Safety: Ensure protection of the public health and safety and the environment z Security: Ensure the secure use and management of radioactive materials z Openness: Ensure openness in our regulatory process z Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely z Management: Ensure excellence in agency management to carry out the NRC strategic objective
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Examples of Baseline Inspections z Equipment Alignment ~80 hrs/yr z Triennial Fire Protection ~200 hrs every 3 yrs z Operator Response ~125 hrs/yr z Emergency Preparedness ~80 hrs/yr z Rad Release Controls ~110 hrs every 2 yrs z Worker Radiation Protection ~90 hrs/yr z Corrective Action Program ~250 hrs every 2 yrs z Corrective Action Case Reviews ~60 hrs/yr
Significance Threshold Performance Indicators Green: Baseline Inspection White: Requires more NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight Inspection Findings Green: Very Low safety issue White: Low to moderate safety issue Yellow: Substantial safety issue Red: High safety issue
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
National Summary of Plant Performance Status at End of CY 2005 Licensee Response 84 Regulatory Response 12 Degraded Cornerstone 4 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103
National Summary z Performance Indicator Results (at end of CY 2005)
Green 1850 White 4 Yellow 0 Red 0 z Total Inspection Findings (CY 2005)
Green 849 White 10 Yellow 1 Red 0
Three Mile Island Assessment Results (Jan 1 - Dec 31, 2005) z Operated Safely z Regulatory response column of the Action Matrix for the fourth quarter of 2005 (cornerstone objectives fully met) z NRC will conduct baseline inspections during the next cycle z NRC conducted a supplemental inspection during the week of February 27, 2006 related to the emergency preparedness white inspection finding z The results of the supplemental inspection are not yet final
White Finding in Emergency Preparedness Cornerstone z Relates to untimely conduct of required annual classroom retraining for some members of the emergency response organization z Supplemental Inspection conducted the week of February 27, 2006 z The results of the inspection are not final
Three Mile Island Inspection Activities (Jan 1 - Dec 31, 2005) z 5818 hours0.0673 days <br />1.616 hours <br />0.00962 weeks <br />0.00221 months <br /> of inspection related activities z 2 resident inspectors assigned to the site z 12 regional inspections z 5 team inspections z Inspection findings 3/4 9 findings of very low safety significance (green) 3/4 1 finding of low to moderate safety significance (white) 3/4 1 Severity Level IV Violation (Traditional Enforcement)
Three Mile Island Annual Assessment Summary (Jan 1 - Dec 31, 2005) z AmerGen operated Three Mile Island Unit 1 in a manner that preserved public health and safety z Regulatory Response Column of the Action Matrix z One White finding identified (EP performance deficiency relating to annual classroom retraining) z NRC plans baseline inspections at TMI for the remainder of the assessment period
Licensee Response and Remarks Contacting the NRC z Report an emergency (301) 816-5100 (call collect) z Report a safety concern:
(800) 695-7403 Allegation@nrc.gov z General information or questions www.nrc.gov Select What We Do for Public Affairs
Reference Sources z Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html z Public Electronic Reading Room http://www.nrc.gov/reading-rm.html z Public Document Room 1-800-397-4209 (Toll Free)