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| | number = ML070851386 | | | number = ML070851386 |
| | issue date = 03/26/2007 | | | issue date = 03/26/2007 |
| | title = Three Mile Island Annual Assessment Slides for ROP 2006-07 Public Meeting on 4-11-07 | | | title = Annual Assessment Slides for ROP 2006-07 Public Meeting on 4-11-07 |
| | author name = | | | author name = |
| | author affiliation = NRC/RGN-I/DRP/PB6 | | | author affiliation = NRC/RGN-I/DRP/PB6 |
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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 07-015 | | | case reference number = MN 07-015 |
| | package number = ML070851327 | | | package number = ML070851327 |
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| {{#Wiki_filter:NRC Annual Performance Assessment NRC Annual Performance Assessment of of Three Mile Island Three Mile Island 2006 Reactor Oversight Program 2006 Reactor Oversight Program 2 2 Purpose of Today's MeetingNRC will address licensee performance as described NRC will address licensee performance as described in the annual assessment letterin the annual assessment letterAmerGenAmerGenwill be given the opportunity to respond to will be given the opportunity to respond to the information in the letter and inform the NRC of the information in the letter and inform the NRC of new or existing programs to maintain or improve new or existing programs to maintain or improve their performance their performance NRC will be available to engage interested NRC will be available to engage interested stakeholders on performance of the plant and our role stakeholders on performance of the plant and our role in ensuring safe plant operationsin ensuring safe plant operations 3 3 AgendaIntroduction and NRC OrganizationReview of NRC Reactor Oversight ProcessRegulatory Summary of National Plant PerformanceNRC Assessment of Plant Performance ResultsAmerGenResponse and RemarksNRC Closing RemarksBreakNRC available to address public questions 4 4Samuel J. Collins Regional AdministratorMarc L. DapasDeputy Regional AdministratorDavid C. LewDirector Division of Reactor ProjectsJames W. CliffordDeputy DirectorA. Randolph Blough Director Division of Reactor SafetyMarsha K. GamberoniDeputy DirectorDr Ronald BellamyBranch ChiefRegional SpecialistsThree Mile IslandResident InspectorsDavid Kern-SRIJavier Brand-RIProject EngineersScott Barber-Senior PE Andrew Rosebrook-PE Region I Organization 5 5 NRC Representatives NRC RepresentativesDavid C. Lew, Director, Division Reactor Projects | | {{#Wiki_filter:NRC Annual Performance Assessment of Three Mile Island 2006 Reactor Oversight Program |
| -(610) 337-5229James W. Clifford, Deputy Division Director, DRP
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| -(610) 337-5080Dr. Ronald Bellamy, Branch Chief
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| -(610) 337-5200Victor Nerses, Project Manager, NRR
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| -(301) 415-1484David Kern, Senior Resident Inspector
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| -(717) 948-8270Javier Brand, Resident Inspector
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| -(717) 948-1165Scott Barber, Senior Project Engineer
| |
| -(610) 337-5232 6 6NRC Performance GoalsSafety: Ensure protection of the public health and safety and the environmentSecurity: Ensure the secure use and management of
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| 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's strategic objective 7 7 Reactor Oversight ProcessSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance Areas 8 8 Examples of Baseline Inspection AreasEquipment Alignment Triennial Fire Protection Operator Response Emergency Preparedness Radiation Release Controls Worker Radiation Protection Corrective Action Program Corrective Action Case Reviews 9 9 Significance Threshold Performance Indicators Green:Only Baseline InspectionWhite:May increase NRC oversight Yellow:Requires more NRC oversight Red:Requires more NRC oversight Inspection Findings Green:Very Low safety issueWhite:Low to moderate safety issue Yellow:Substantial safety issue Red:High safety issue 10 10 Action Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.DegradedCornerstoneUnacceptablePerformance Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions 11 11 Regulatory Summary of National Plant Performance Status at End of 2006Licensee Response 70Regulatory Response 24Degraded Cornerstone 6Multiple/Repetitive Degraded Cornerstone3Unacceptable 0Total103 12 12 National SummaryPerformance Indicator Results (at end of 2006) | | Purpose of Todays Meeting |
| !Green 1843!White11!Yellow 0!Red 0Total Inspection Findings (2006)
| | NRC will address licensee performance as described in the annual assessment letter |
| !Green 676!White13!Yellow 0!Red 0 13 13 NRC Inspection Activities at Three Mile Island (Jan 1 (Jan 1 --Dec 31, 2006)
| | AmerGen will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance |
| Dec 31, 2006)5498 hours of inspection and related activities2 resident inspectors assigned to the site12 regional inspections3 team inspections 14 14 NRC Inspection Activities at Three Mile Island (Jan 1 (Jan 1 --Dec 31, 2006)
| | NRC will be available to engage interested stakeholders on performance of the plant and our role in ensuring safe plant operations 2 |
| Dec 31, 2006)Completed a Specialized Plant Security Review Completed a Problem Identification and Resolution Team (PI&R) Team InspectionCompleted a Plant Modifications Team InspectionResident Inspections 15 15 NRC Assessment of Three Mile Island(Jan 1 -Dec 31, 2006)The plant operated safely The plant operated safelyPlant was in regulatory response column of the Action Plant was in regulatory response column of the Action Matrix for the first quarter of 2006 Matrix for the first quarter of 2006NRC supplemental inspection during February 2006 closed NRC supplemental inspection during February 2006 closed out a white emergency preparedness inspection finding and out a white emergency preparedness inspection finding and the plant transitioned into the licensee response column of the plant transitioned into the licensee response column of the Action Matrix the Action Matrix Plant remained in the licensee response column of the Plant remained in the licensee response column of the Action Matrix for the second thru fourth quarters of 2006 Action Matrix for the second thru fourth quarters of 2006 (cornerstone objectives fully met)(cornerstone objectives fully met)NRC plans baseline inspections for the remainder of 2007 NRC plans baseline inspections for the remainder of 2007 16 16 Safety Significant Findings or PIsAll performance indicators were green (very low All performance indicators were green (very low safety significance) in 2006safety significance) in 2006Ten green inspection findings were identified during Ten green inspection findings were identified during the year the year 17 17 NRC Sample Inspection Findings / Issues at Three Mile IslandWorker Fatigue and Fitness for Duty (FFD)
| | |
| Worker Fatigue and Fitness for Duty (FFD)Shift Manager Inattentive to DutyShift Manager Inattentive to DutyOperators did not consider fatigue to be an FFD Issue Operators did not consider fatigue to be an FFD IssueSecurity guard working hours / awareness Security guard working hours / awarenessPrevious trend in Procedure Quality & AdherencePrevious trend in Procedure Quality & AdherenceImprovements have been notedImprovements have been notedCurrent trend in the Use of Industry Operating ExperienceCurrent trend in the Use of Industry Operating ExperienceIndustry and NRC Fitness for Duty issues Industry and NRC Fitness for Duty issues Monitoring for air voids in safety related systems.Monitoring for air voids in safety related systems. | | Agenda |
| 18 18 NRC Annual Assessment Summary at Three Mile Island (Jan 1 -Dec 31, 2006)AmerGen operated Three Mile Island in a manner that preserved public health and safety.All cornerstone objectives were met. NRC plans baseline inspections at Three Mile Island for the remainder of the assessment period.
| | Introduction and NRC Organization |
| 19 19 Licensee Response and Remarks Mr. Rusty WestSite Vice President -Three Mile IslandAmerGen Energy LLC 20 20 Contacting the NRCReport an emergency
| | Review of NRC Reactor Oversight Process |
| !(301) 816-5100 (call collect)Report a safety concern:
| | Regulatory Summary of National Plant Performance |
| !(800) 695-7403
| | NRC Assessment of Plant Performance Results |
| !Allegation@nrc.govGeneral information or questions
| | AmerGen Response and Remarks |
| !www.nrc.gov
| | NRC Closing Remarks |
| !Select "What We Do"for Public Affairs 21 21 Reference SourcesReactor Oversight Process
| | Break |
| !http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.htmlPublic Electronic Reading Room
| | NRC available to address public questions 3 |
| !http://www.nrc.gov/reading-rm.htmlPublic Document Room
| | |
| !1-800-397-4209 (Toll Free)}}
| | Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator David C. Lew A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Marsha K. Gamberoni Deputy Director Deputy Director Dr Ronald Bellamy Branch Chief Regional Specialists Three Mile Island Project Engineers Resident Inspectors Scott Barber-Senior PE David Kern-SRI Andrew Rosebrook-PE Javier Brand-RI 4 |
| | |
| | NRC Representatives |
| | David C. Lew, Director, Division Reactor Projects |
| | - (610) 337-5229 |
| | James W. Clifford, Deputy Division Director, DRP |
| | - (610) 337-5080 |
| | Dr. Ronald Bellamy, Branch Chief |
| | - (610) 337-5200 |
| | Victor Nerses, Project Manager, NRR |
| | - (301) 415-1484 |
| | David Kern, Senior Resident Inspector |
| | - (717) 948-8270 |
| | Javier Brand, Resident Inspector |
| | - (717) 948-1165 |
| | Scott Barber, Senior Project Engineer |
| | - (610) 337-5232 5 |
| | |
| | NRC Performance Goals |
| | Safety: Ensure protection of the public health and safety and the environment |
| | Security: Ensure the secure use and management of radioactive materials |
| | Openness: Ensure openness in our regulatory process |
| | Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely |
| | Management: Ensure excellence in agency management to carry out the NRCs strategic objective 6 |
| | |
| | Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response 7 |
| | |
| | Examples of Baseline Inspection Areas |
| | Equipment Alignment |
| | Triennial Fire Protection |
| | Operator Response |
| | Emergency Preparedness |
| | Radiation Release Controls |
| | Worker Radiation Protection |
| | Corrective Action Program |
| | Corrective Action Case Reviews 8 |
| | |
| | Significance Threshold Performance Indicators Green: Only Baseline Inspection White: May increase 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 9 |
| | |
| | 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 10 |
| | |
| | Regulatory Summary of National Plant Performance Status at End of 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103 11 |
| | |
| | National Summary |
| | Performance Indicator Results (at end of 2006) |
| | Green 1843 White 11 Yellow 0 Red 0 |
| | Total Inspection Findings (2006) |
| | Green 676 White 13 Yellow 0 Red 0 12 |
| | |
| | NRC Inspection Activities at Three Mile Island (Jan 1 - Dec 31, 2006) |
| | 5498 hours of inspection and related activities |
| | 2 resident inspectors assigned to the site |
| | 12 regional inspections |
| | 3 team inspections 13 |
| | |
| | NRC Inspection Activities at Three Mile Island (Jan 1 - Dec 31, 2006) |
| | Completed a Specialized Plant Security Review |
| | Completed a Problem Identification and Resolution Team (PI&R) Team Inspection |
| | Completed a Plant Modifications Team Inspection |
| | Resident Inspections 14 |
| | |
| | NRC Assessment of Three Mile Island (Jan 1 - Dec 31, 2006) |
| | The plant operated safely |
| | Plant was in regulatory response column of the Action Matrix for the first quarter of 2006 |
| | NRC supplemental inspection during February 2006 closed out a white emergency preparedness inspection finding and the plant transitioned into the licensee response column of the Action Matrix |
| | Plant remained in the licensee response column of the Action Matrix for the second thru fourth quarters of 2006 (cornerstone objectives fully met) |
| | NRC plans baseline inspections for the remainder of 2007 15 |
| | |
| | Safety Significant Findings or PIs |
| | All performance indicators were green (very low safety significance) in 2006 |
| | Ten green inspection findings were identified during the year 16 |
| | |
| | NRC Sample Inspection Findings / Issues at Three Mile Island |
| | Worker Fatigue and Fitness for Duty (FFD) |
| | Shift Manager Inattentive to Duty |
| | Operators did not consider fatigue to be an FFD Issue |
| | Security guard working hours / awareness |
| | Previous trend in Procedure Quality & Adherence |
| | Improvements have been noted |
| | Current trend in the Use of Industry Operating Experience |
| | Industry and NRC Fitness for Duty issues |
| | Monitoring for air voids in safety related systems. |
| | 17 |
| | |
| | NRC Annual Assessment Summary at Three Mile Island (Jan 1 - Dec 31, 2006) |
| | AmerGen operated Three Mile Island in a manner that preserved public health and safety. |
| | All cornerstone objectives were met. |
| | NRC plans baseline inspections at Three Mile Island for the remainder of the assessment period. |
| | 18 |
| | |
| | Licensee Response and Remarks Mr. Rusty West Site Vice President - Three Mile Island AmerGen Energy LLC 19 |
| | |
| | Contacting the NRC |
| | Report an emergency (301) 816-5100 (call collect) |
| | Report a safety concern: |
| | (800) 695-7403 Allegation@nrc.gov |
| | General information or questions www.nrc.gov Select What We Do for Public Affairs 20 |
| | |
| | Reference Sources |
| | Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html |
| | Public Electronic Reading Room http://www.nrc.gov/reading-rm.html |
| | Public Document Room 1-800-397-4209 (Toll Free) 21}} |
|
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Category:Meeting Agenda
MONTHYEARPMNS20241304, Notice of Meeting with Constellation Energy Generation, LLC2024-10-24024 October 2024 Notice of Meeting with Constellation Energy Generation, LLC PMNS20240138, Energysolutions Presentation to NRC on Decommissioning Activities at Three Mile Island Station, Unit 2 (TMI-2)2024-02-0909 February 2024 Energysolutions Presentation to NRC on Decommissioning Activities at Three Mile Island Station, Unit 2 (TMI-2) PMNS20230054, Test Meeting PMNS-1702023-01-13013 January 2023 Test Meeting PMNS-170 ML20178A4282020-06-30030 June 2020 NEI Questions for June 30, 2020 Public Meeting ML19151A6602019-05-31031 May 2019 BWR Fleet Mssv/Srv Testing Frequency Relief Request NRC Pre-Application Meeting June 4, 2019 ML14112A2392014-04-22022 April 2014 Notice of Forthcoming Closed Meeting to Discuss Dam Failure Analysis for Peach Bottom Atomic Power Station Units 2 and 3, Susquehanna Steam Electric Station Units 1 and 2, and Three Mile Island Nuclear Station Unit 1 ML14055A0042014-03-11011 March 2014 Meeting Notice with Exelon Generation Company, LLC (Exelon) Regarding Emergency Response Organization Annual Training ML13262A1632013-09-23023 September 2013 Meeting Report - Three Mile Island, Unit 2, Post-Shutdown Decommissioning Activities Report Public Meeting ML13256A2982013-09-12012 September 2013 09/25/2013 Notice of Meeting with the U.S. Department of Energy to Discuss the Three Mile Island Unit 2 License Renewal ML13221A4462013-08-12012 August 2013 Meeting Notice: to Discuss the Three Mile Island, Unit 2, Post-Shutdown Decommissioning Activities Report Submittal and Obtain Public Comments ML13190A3522013-07-10010 July 2013 Notice of Forthcoming Teleconference with Exelon Generation Company, LLC ML13136A2032013-05-20020 May 2013 Meeting Notice with Exelon Generation Company, LLC, to Discuss Once Through Steam Generator Tube-to-Tube Wear at Three Mile Island, Unit 1 ML12348A6962012-12-17017 December 2012 1/3/2013 - Notice of Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Requests for Additional Information Regarding Exelon Physical Security Plans ML1208602902012-03-26026 March 2012 Notice of Forthcoming Public Meeting with Exelon Generation to Discuss Future Fleet Submittal Regarding Licensed Operator Eligibility Requirements ML1200500362012-01-0909 January 2012 Forthcoming Meeting with Exelon Generation Company, LLC, and Entergy Operations, Inc., to Discuss Steam Generator Inspection Results at Three Mile Island, Unit 1, and Arkansas Nuclear One, Unit 1 ML1134801002011-12-19019 December 2011 Notice of Forthcoming Meeting with Exelon Generation Company, LLC, and Entergy Operations, Inc., to Discuss Steam Generator Inspection Results at Three Mile Island, Unit 1, and Arkansas Nuclear One, Unit 1 ML1105509182011-02-25025 February 2011 Notice of Meeting with Exelon Generation Company, LLC, to Discuss Three Mile Island, Unit 1, Main Steam Safety Valve License Amendment Request 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 ML1019000152010-07-0909 July 2010 Forthcoming Meeting with Exelon Generation Company, LLC to Discuss Revisions to the Cyber Security Plan Submittal for Braidwood, Byron, Clinton, Dresden, LaSalle, Limerick, Oyster Creek, Peach Bottom, Quad Cities and Three Mile Island ML0928706732009-10-19019 October 2009 Forthcoming Meeting with Exelon Generation Company, LLC, to Discuss Proposed Three Mile Island, Unit 1, License Amendment Request Concerning Control Rod Drive Control System 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 ML0926801972009-09-29029 September 2009 Notice of Pre-application Meeting to Discuss Egc'S Plants to Submit Power Uprate Requests for Various Units in Its Reactor Fleet 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 ML0914901422009-06-0909 June 2009 Notice of Meeting with Exelon Generation Company on Licensing Practices and Processes ML0913906312009-06-0404 June 2009 ACRS Meeting with the U.S. Nuclear Regulatory Commission, - 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Forthcoming Public Information Sessions for the U.S. Nuclear Regulatory Commission Staff to Discuss the License Renewal Process for the Three Mile Island Nuclear Station, Unit 1, License Renewal Application Review ML0802501172008-01-15015 January 2008 1/15/2008 Slides from Drop-in Visit Exelon/Amergen ML0726404852007-08-14014 August 2007 TMI ACNW Agenda ML0726404902007-08-14014 August 2007 TMI Intro ML0710901582007-04-19019 April 2007 Aam Final Slides for Reactor Oversight Program 2006-07 Public Meeting 04/11/07 ML0709601652007-04-10010 April 2007 Notice of Meeting with Amergen Energy Company, LLC to Discuss the Content of the Three Mile Island, Unit 1 License Amendment Request (LAR) Re High Thermal Performance Fuel Type Change ML0708513862007-03-26026 March 2007 Annual Assessment Slides for ROP 2006-07 Public Meeting on 4-11-07 ML0708514682007-03-26026 March 2007 Notice of Meeting with Amergen Energy Co., LLC, to Discuss the Nrc'S Assessment of the Safety Performance of the Three Mile Island Nuclear Power Station, Unit 1 for Calendar Year 2006 as Described in the Annual Assessment Letter 03/02/2007 ML0707503812007-03-16016 March 2007 Cancellation of Notice of Meeting with Amergen Energy Company, LLC Regarding Technical Aspects of the Licensee'S Scheduled Activities for the Upcoming Refueling Outage ML0706003912007-02-27027 February 2007 Revised Notice of Meeting with Exelon Generation Co., LLC to Discuss Licensing Issues and Schedule of Upcoming Licensing Activities with the Exelon Fleet of Nuclear Power Plants (Braidwood, Units 1 and 2, Byron, Unit Nos. 1 and 2; Clinton.. ML0703605402007-02-15015 February 2007 Forthcoming Meeting with Exelon Generation Company to Discuss Licensing Activities ML0607507992006-03-21021 March 2006 Public Meeting Notice for Three Mile Island (Amergen) and NRC Ref: Annual Assessment Performance CY2005 ML0524103052005-09-0606 September 2005 08/18/05 - Summary of Public Meeting on Mspi/Rop Topics for August 17/18, 2005 ML0503401822005-02-0303 February 2005 02/16-17/2005 Revised Notice of Meeting with Amergen Energy Company, LLC, Regarding TMI-1, Steam Generator Kinetic Expansion Inspection Acceptance Criteria ML0502403962005-02-0101 February 2005 02/16-17/05 - Forthcoming Meeting with Amergen Energy Company, LLC Regarding the Three Mile Island Nuclear Station, Unit 1, Steam Generator Kinetic Expansion Inspection Acceptance Criteria 2024-02-09
[Table view] 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
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NRC Annual Performance Assessment of Three Mile Island 2006 Reactor Oversight Program
Purpose of Todays Meeting
NRC will address licensee performance as described in the annual assessment letter
AmerGen will be given the opportunity to respond to the information in the letter and inform the NRC of new or existing programs to maintain or improve their performance
NRC will be available to engage interested stakeholders on performance of the plant and our role in ensuring safe plant operations 2
Agenda
Introduction and NRC Organization
Review of NRC Reactor Oversight Process
Regulatory Summary of National Plant Performance
NRC Assessment of Plant Performance Results
AmerGen Response and Remarks
NRC Closing Remarks
Break
NRC available to address public questions 3
Region I Organization Samuel J. Collins Regional Administrator Marc L. Dapas Deputy Regional Administrator David C. Lew A. Randolph Blough Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Marsha K. Gamberoni Deputy Director Deputy Director Dr Ronald Bellamy Branch Chief Regional Specialists Three Mile Island Project Engineers Resident Inspectors Scott Barber-Senior PE David Kern-SRI Andrew Rosebrook-PE Javier Brand-RI 4
NRC Representatives
David C. Lew, Director, Division Reactor Projects
- (610) 337-5229
James W. Clifford, Deputy Division Director, DRP
- (610) 337-5080
Dr. Ronald Bellamy, Branch Chief
- (610) 337-5200
Victor Nerses, Project Manager, NRR
- (301) 415-1484
David Kern, Senior Resident Inspector
- (717) 948-8270
Javier Brand, Resident Inspector
- (717) 948-1165
Scott Barber, Senior Project Engineer
- (610) 337-5232 5
NRC Performance Goals
Safety: Ensure protection of the public health and safety and the environment
Security: Ensure the secure use and management of radioactive materials
Openness: Ensure openness in our regulatory process
Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely
Management: Ensure excellence in agency management to carry out the NRCs strategic objective 6
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response 7
Examples of Baseline Inspection Areas
Equipment Alignment
Triennial Fire Protection
Operator Response
Emergency Preparedness
Radiation Release Controls
Worker Radiation Protection
Corrective Action Program
Corrective Action Case Reviews 8
Significance Threshold Performance Indicators Green: Only Baseline Inspection White: May increase 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 9
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 10
Regulatory Summary of National Plant Performance Status at End of 2006 Licensee Response 70 Regulatory Response 24 Degraded Cornerstone 6 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total 103 11
National Summary
Performance Indicator Results (at end of 2006)
Green 1843 White 11 Yellow 0 Red 0
Total Inspection Findings (2006)
Green 676 White 13 Yellow 0 Red 0 12
NRC Inspection Activities at Three Mile Island (Jan 1 - Dec 31, 2006)
5498 hours0.0636 days <br />1.527 hours <br />0.00909 weeks <br />0.00209 months <br /> of inspection and related activities
2 resident inspectors assigned to the site
12 regional inspections
3 team inspections 13
NRC Inspection Activities at Three Mile Island (Jan 1 - Dec 31, 2006)
Completed a Specialized Plant Security Review
Completed a Problem Identification and Resolution Team (PI&R) Team Inspection
Completed a Plant Modifications Team Inspection
Resident Inspections 14
NRC Assessment of Three Mile Island (Jan 1 - Dec 31, 2006)
The plant operated safely
Plant was in regulatory response column of the Action Matrix for the first quarter of 2006
NRC supplemental inspection during February 2006 closed out a white emergency preparedness inspection finding and the plant transitioned into the licensee response column of the Action Matrix
Plant remained in the licensee response column of the Action Matrix for the second thru fourth quarters of 2006 (cornerstone objectives fully met)
NRC plans baseline inspections for the remainder of 2007 15
Safety Significant Findings or PIs
All performance indicators were green (very low safety significance) in 2006
Ten green inspection findings were identified during the year 16
NRC Sample Inspection Findings / Issues at Three Mile Island
Worker Fatigue and Fitness for Duty (FFD)
Shift Manager Inattentive to Duty
Operators did not consider fatigue to be an FFD Issue
Security guard working hours / awareness
Previous trend in Procedure Quality & Adherence
Improvements have been noted
Current trend in the Use of Industry Operating Experience
Industry and NRC Fitness for Duty issues
Monitoring for air voids in safety related systems.
17
NRC Annual Assessment Summary at Three Mile Island (Jan 1 - Dec 31, 2006)
AmerGen operated Three Mile Island in a manner that preserved public health and safety.
All cornerstone objectives were met.
NRC plans baseline inspections at Three Mile Island for the remainder of the assessment period.
18
Licensee Response and Remarks Mr. Rusty West Site Vice President - Three Mile Island AmerGen Energy LLC 19
Contacting the NRC
Report an emergency (301) 816-5100 (call collect)
Report a safety concern:
(800) 695-7403 Allegation@nrc.gov
General information or questions www.nrc.gov Select What We Do for Public Affairs 20
Reference Sources
Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html
Public Electronic Reading Room http://www.nrc.gov/reading-rm.html
Public Document Room 1-800-397-4209 (Toll Free) 21