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| | number = ML060820248 | | | number = ML060820248 |
| | issue date = 03/23/2006 | | | issue date = 03/23/2006 |
| | title = 03/30/2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance | | | title = NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance |
| | author name = Krohn P | | | author name = Krohn P |
| | author affiliation = NRC/RGN-I/DRP/PB6 | | | author affiliation = NRC/RGN-I/DRP/PB6 |
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| {{#Wiki_filter:Seabrook Seabrook Annual Assessment MeetingAnnual Assessment MeetingReactor Oversight Program Reactor Oversight Program | | {{#Wiki_filter:Seabrook Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 30, 2006 |
| --CY 2005CY 2005Nuclear Regulatory Commission Nuclear Regulatory Commission
| | |
| --Region IRegion IKing of Prussia, PennsylvaniaKing of Prussia, PennsylvaniaMarch 30, 2006March 30, 2006 Purpose of Today's MeetingPurpose of Today's MeetingA public forum for discussion of the licensee's A public forum for discussion of the licensee's performanceperformanceNRC will address the licensee performance issues NRC will address the licensee performance issues identified in the annual assessment letteridentified in the annual assessment letterLicensee will be given the opportunity to respond to Licensee 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 AgendaAgendaIntroduction Introduction Review of Reactor Oversight ProcessReview of Reactor Oversight ProcessNational Summary of Plant PerformanceNational Summary of Plant PerformanceDiscussion of Plant Performance ResultsDiscussion of Plant Performance ResultsLicensee Response and RemarksLicensee Response and RemarksNRC Closing RemarksNRC Closing RemarksBreakBreakNRC available to address public questionsNRC available to address public questions Region I OrganizationRegion 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 DirectorPaul G. KrohnBranch ChiefRegional SpecialistsSeabrookResident InspectorsGlenn DentelSteve ShafferSenior Project EngineersScott BarberBarry Norris NRC RepresentativesNRC RepresentativesGlenn Dentel, Senior Resident InspectorGlenn Dentel, Senior Resident InspectorSteve Shaffer, Resident InspectorSteve Shaffer, Resident Inspector
| | Purpose of Todays Meeting A public forum for discussion of the licensees performance NRC will address the licensee performance issues identified in the annual assessment letter Licensee 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 |
| --(603) 474 (603) 474--3589/35803589/3580Ed Miller, Project Manager, NRREd Miller, Project Manager, NRR
| | |
| --(301) 415 (301) 415--24812481Paul Krohn, Branch ChiefPaul Krohn, Branch Chief
| | 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 |
| --(610) 337 (610) 337--51205120Scott Barber, Senior Project EngineerScott Barber, Senior Project Engineer
| | |
| --(610) 337 (610) 337--52325232Barry Norris, Senior Project EngineerBarry Norris, Senior Project Engineer
| | 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 Paul G. Krohn Regional Specialists Branch Chief Seabrook Senior Project Engineers Resident Inspectors Scott Barber Glenn Dentel Barry Norris Steve Shaffer |
| --(610) 337 (610) 337--51115111 NRC Performance Goals NRC Performance GoalsSafety: Ensure protection of the public health and Safety: Ensure protection of the public health and safety and the environmentsafety and the environmentSecurity: Ensure the secure use and management of Security: Ensure the secure use and management of radioactive materialsradioactive materialsOpenness: Ensure openness in our regulatory processOpenness: Ensure openness in our regulatory processEffectiveness: Ensure that NRC actions are effective, Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timelyefficient, realistic, and timelyManagement: Ensure excellence in agency Management: Ensure excellence in agency management to carry out the NRC strategic objectivemanagement to carry out the NRC strategic objective Reactor Oversight ProcessReactor Oversight ProcessSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance Areas Examples of Baseline InspectionsExamples of Baseline InspectionsEquipment Alignment Equipment Alignment ~80 hrs/yr ~80 hrs/yr Triennial Fire Protection Triennial Fire Protection ~200 hrs every 3 yrs~200 hrs every 3 yrsOperator Response Operator Response ~125 hrs/yr~125 hrs/yrEmergency Preparedness Emergency Preparedness ~80 hrs/yr~80 hrs/yrRad Release Controls Rad Release Controls ~110 hrs every 2 yrs~110 hrs every 2 yrsWorker Radiation Protection Worker Radiation Protection ~90 hrs/yr~90 hrs/yrCorrective Action Program Corrective Action Program ~250 hrs every 2 yrs~250 hrs every 2 yrsCorrective Action Case Reviews Corrective Action Case Reviews ~60 hrs/yr~60 hrs/yr Significance ThresholdSignificance ThresholdPerformance IndicatorsPerformance IndicatorsGreenGreen::Baseline InspectionBaseline Inspection White White::May increase NRC oversightMay increase NRC oversightYellowYellow::Requires more NRC oversightRequires more NRC oversight Red Red::Requires more NRC oversightRequires more NRC oversightInspection FindingsInspection FindingsGreenGreen::Very low safety issueVery low safety issue White White::Low to moderate safety issueLow to moderate safety issueYellowYellow::Substantial safety issueSubstantial safety issue Red Red::High safety issueHigh safety issue Action Matrix ConceptAction Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.DegradedCornerstoneUnacceptablePerformanceIncreasing Safety SignificanceIncreasing Safety SignificanceIncreasing NRC Inspection EffortsIncreasing NRC Inspection EffortsIncreasing NRC/Licensee Management InvolvementIncreasing NRC/Licensee Management InvolvementIncreasing Regulatory ActionsIncreasing Regulatory Actions National Summary of Plant PerformanceNational Summary of Plant PerformanceStatus at End of CY 2005Status at End of CY 2005Licensee Response Licensee Response 84 84Regulatory Response Regulatory Response 12 12Degraded Cornerstone Degraded Cornerstone 4 4Multiple/Repetitive Degraded CornerstoneMultiple/Repetitive Degraded Cornerstone 3 3Unacceptable Unacceptable 0 0TotalTotal 103 103 National Summary National SummaryPerformance Indicator Results (at end of CY 2005)Performance Indicator Results (at end of CY 2005)GreenGreen18501850 White White 4 4YellowYellow 0 0 Red Red 0 0Total Inspection Findings (CY 2005)Total Inspection Findings (CY 2005)GreenGreen849849 White White 10 10YellowYellow 1 1 Red Red 0 0 Seabrook Assessment Results Seabrook Assessment Results (Jan 1 (Jan 1 --Dec 31, 2005)Dec 31, 2005)Licensee Response ColumnLicensee Response ColumnNo safety significant findings or PIsNo safety significant findings or PIs Seabrook Inspection ActivitiesSeabrook Inspection Activities(Jan 1 (Jan 1 --Dec 31, 2005)
| | |
| Dec 31, 2005)6800 Hours of inspection related activities6800 Hours of inspection related activitiesTwo resident inspectors assigned to the siteTwo resident inspectors assigned to the siteSpecialist InspectionsSpecialist Inspections | | NRC Representatives z Glenn Dentel, Senior Resident Inspector Steve Shaffer, Resident Inspector |
| --9 regional inspections9 regional inspections | | - (603) 474-3589/3580 z Ed Miller, Project Manager, NRR |
| --2 team inspections 2 team inspections Seabrook Inspection ActivitiesSeabrook Inspection Activities(Jan 1 -Dec 31, 2005)Inspection findingsInspection findings | | - (301) 415-2481 z Paul Krohn, Branch Chief |
| --8 findings of very low safety significance (Green)8 findings of very low safety significance (Green)Refueling outage (April 2 Refueling outage (April 2
| | - (610) 337-5120 z Scott Barber, Senior Project Engineer |
| --April 30, 2005)April 30, 2005)
| | - (610) 337-5232 z Barry Norris, Senior Project Engineer |
| --no findings related to the outageno findings related to the outageSafety System Design team inspectionSafety System Design team inspection
| | - (610) 337-5111 |
| --1 finding of very low safety significance (Green)1 finding of very low safety significance (Green)Triennial Fire Protection team inspectionTriennial Fire Protection team inspection
| | |
| --1 finding of very low safety significance (Green)1 finding of very low safety significance (Green)
| | 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 |
| Seabrook SeabrookAnnual Assessment SummaryAnnual Assessment SummaryJanuary 1 January 1 | | |
| --December 31, 2005December 31, 2005FPL operated Seabrook Station in a manner that FPL operated Seabrook Station in a manner that preserved public health and safetypreserved public health and safetyAll cornerstone objectives were metAll cornerstone objectives were metNRC plans baseline inspections at Seabrook for the NRC plans baseline inspections at Seabrook for the remainder of the assessment periodremainder of the assessment period Licensee Response and RemarksLicensee Response and RemarksGene St. PierreGene St. PierreSite Vice PresidentSite Vice PresidentFPL Energy Seabrook, LLCFPL Energy Seabrook, LLC Contacting the NRCContacting the NRCReport an emergencyReport an emergency(301) 816(301) 816--5100 (call collect)5100 (call collect)Report a safety concern: Report a safety concern: (800) 695(800) 695--7403 7403 Allegation@nrc.govAllegation@nrc.govGeneral information or questionsGeneral information or questionswww.nrc.govwww.nrc.govSelect "What We Do" for Public AffairsSelect "What We Do" for Public Affairs Paul Paul KrohnKrohn, Branch Chief, Branch Chiefpgk1@nrc.govpgk1@nrc.gov Reference SourcesReference SourcesReactor Oversight ProcessReactor Oversight Processhttp://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.htmlhttp://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.htmlPublic Electronic Reading RoomPublic Electronic Reading Roomhttp://www.nrc.gov/readinghttp://www.nrc.gov/reading
| | Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response |
| --rm.htmlrm.htmlPublic Document RoomPublic Document Room 1 1--800 800--397 397--4209 (Toll Free)4209 (Toll Free)
| | |
| END OF THE PRESENTATIONEND OF THE PRESENTATIONNuclear Regulatory Commission Nuclear Regulatory Commission | | 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 |
| --Region IRegion IKing of Prussia, PennsylvaniaKing of Prussia, PennsylvaniaMarch 30, 2006March 30, 2006 Potential Public Interest IssuesPotential Public Interest IssuesSafety Concerns Brought to the NRCSafety Concerns Brought to the NRCNRC has a formal processNRC has a formal processConcerns are reviewed on an individual basis by NRC technical, Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and managementlegal, investigative staff and managementIssues of immediate concern receive prompt attention by NRC and Issues of immediate concern receive prompt attention by NRC and by nuclear power plant managementby nuclear power plant managementNRC'sNRC'sprocess requires reviews of all valid safety issues to ensure process requires reviews of all valid safety issues to ensure they are adequately addressedthey are adequately addressedNRC implements measures to protect the identity of allegers NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegatiincluding not commenting on the existence of a specific allegati on on Potential Public Interest IssuesPotential Public Interest IssuesRecent Press Articles on Security IssuesRecent Press Articles on Security IssuesCurrent NRC policy is to not discuss security matters in a Current NRC policy is to not discuss security matters in a public forumpublic forumNRC will not comment on existence of allegations in this NRC will not comment on existence of allegations in this area areaNotwithstanding these policies, we want to assure the Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take public that if safety issues did exist, the NRC would take prompt action to address themprompt action to address them}}
| | |
| | Significance Threshold Performance Indicators Green: 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 |
| | |
| | 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 |
| | |
| | Seabrook Assessment Results (Jan 1 - Dec 31, 2005) z Licensee Response Column z No safety significant findings or PIs |
| | |
| | Seabrook Inspection Activities (Jan 1 - Dec 31, 2005) 6800 Hours of inspection related activities Two resident inspectors assigned to the site Specialist Inspections |
| | - 9 regional inspections |
| | - 2 team inspections |
| | |
| | Seabrook Inspection Activities (Jan 1 - Dec 31, 2005) |
| | Inspection findings |
| | - 8 findings of very low safety significance (Green) |
| | Refueling outage (April 2 - April 30, 2005) |
| | - no findings related to the outage Safety System Design team inspection |
| | - 1 finding of very low safety significance (Green) |
| | Triennial Fire Protection team inspection |
| | - 1 finding of very low safety significance (Green) |
| | |
| | Seabrook Annual Assessment Summary January 1 - December 31, 2005 z FPL operated Seabrook Station in a manner that preserved public health and safety z All cornerstone objectives were met z NRC plans baseline inspections at Seabrook for the remainder of the assessment period |
| | |
| | Licensee Response and Remarks Gene St. Pierre Site Vice President FPL Energy Seabrook, LLC |
| | |
| | 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 z Paul Krohn, Branch Chief pgk1@nrc.gov |
| | |
| | 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) |
| | |
| | END OF THE PRESENTATION Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 30, 2006 |
| | |
| | Potential Public Interest Issues Safety Concerns Brought to the NRC z NRC has a formal process z Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and management z Issues of immediate concern receive prompt attention by NRC and by nuclear power plant management z NRCs process requires reviews of all valid safety issues to ensure they are adequately addressed z NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegation |
| | |
| | Potential Public Interest Issues Recent Press Articles on Security Issues z Current NRC policy is to not discuss security matters in a public forum z NRC will not comment on existence of allegations in this area z Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take prompt action to address them}} |
|
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Category:Meeting Briefing Package/Handouts
MONTHYEARML24145A0012024-05-24024 May 2024 5/29/2024, Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML24121A1512024-04-30030 April 2024 Pre-Submittal Meeting to Discuss Upcoming NextEra Energy License Amendment Request for a One-Time Extension to TS 3.8.1.1.a Completion Time ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process – 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19050A4602019-02-13013 February 2019 Handouts from the Public at the February 13, 2019, Seabrook ASR Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML17129A3942017-05-0909 May 2017 Status of Safety Review of Seabrook License Renewal for May 9, 2017, Public Meeting on ASR in Seabrook LRA ML17129A3842017-05-0909 May 2017 NextEra Presentation at May 9, 2017, Public Meeting Re ASR in License Renewal ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML15176A5012015-06-18018 June 2015 Aam Attendance List for June 18, 2015 ML13357A0462013-12-23023 December 2013 Update on ASR ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML14023A7212013-12-18018 December 2013 No More Fukushima Statement for NRC Public Meeting on Dec 18, 2013 ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0608202482006-03-23023 March 2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance ML0603805612006-02-0606 February 2006 Meeting with FLP, Meeting Handouts, Proposed Submittal to Adopt Quality Assurance Topical Report ML0727105482005-12-16016 December 2005 Measurement Uncertainty Recapture Fple/Caldon - NRC Meeting ML0512201092005-04-22022 April 2005 Slides & Handouts from Meeting with FPL Energy Seabrook, LLC, Regarding Implementation of Technical Specification 3/4.8.1.1 ML0507302062005-03-14014 March 2005 NRC Slides for Public Meeting of Seabrook Station Annual Assessment ML0414201102004-05-20020 May 2004 Public Meeting Handouts Re Power Uprate License Amendment Request for Seabrook Station Unit No. 1 ML0406304312004-03-0303 March 2004 Powerpoint Presentation Slides for Meeting with Florida Power & Light Company Regarding Planned Power Uprate Request for Seabrook Station, Unit No. 1 ML0317404312003-06-12012 June 2003 Sign in Sheet ML0232601592002-11-14014 November 2002 Meeting Handout, Seabrook Steam Generator Tube Assessment Project 2024-05-24
[Table view] Category:Slides and Viewgraphs
MONTHYEARML24145A0012024-05-24024 May 2024 5/29/2024, Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML24121A1512024-04-30030 April 2024 Pre-Submittal Meeting to Discuss Upcoming NextEra Energy License Amendment Request for a One-Time Extension to TS 3.8.1.1.a Completion Time ML24073A3372024-03-13013 March 2024 NextEra - NRC Slides for the Public Meeting on March 19, 2024 Regarding Emergency Plan Licensing Amendment ML23177A1142023-06-26026 June 2023 Annual Assessment Meeting Reactor Oversight Process – 2023 ML23066A2472023-03-0707 March 2023 Presubmittal Meeting Slides for March 7, 2023, Public Meeting ML22130A1282022-05-10010 May 2022 Annual Assessment Meeting for Seabrook Station - NRC Presentation Slides ML22146A3472022-02-23023 February 2022 Slides - Pre-Submittal Meeting for February 23 with Nextera Energy Seabrook, LLC Regarding Planned Submittal of License Amendment Request to Update Pressure-Temperature Limits Curves Period of Applicability ML21168A1452021-06-22022 June 2021 Annual Assessment Meeting Slides ML20161A0812020-06-0303 June 2020 Annual Assessment Meeting June 3, 2020 Slides ML19042A1102019-02-13013 February 2019 Presentation Slides - 2019 Seabrook Public Meeting ML18136A4822018-05-0202 May 2018 Annual Assessment Meeting 05-02-2018 Presentation ML18086A7742018-02-21021 February 2018 LOR Program Biennial Inspection 71111.11B Exam Overlap Issues ML17341A0622017-11-17017 November 2017 NextEra Energy Seabrook Presentation Slides - Seabrook Station ASR Methodology LAR: Structural Deformation - LAR 16-03, Methodology and Responses to Rais D2-D8 - for November 17, 2017, Public Meeting ML17310B2322017-11-0707 November 2017 Presentation Slides - NextEra Energy/Fpl - GSI-191 Issue Resolution, Pre-submittal Meeting, September 20, 2017 ML17278A7482017-10-13013 October 2017 Summary of August 24, 2017, Meeting with NextEra Energy Regarding License Amendment Request on Alkali Silica Reaction (CAC No. MF8260; EPID L-2016-LLA-0007) ML17283A0402017-10-10010 October 2017 Enclosure 2 - Nrc'S Presentation Slides-Seabrook Station, License Amendment Request, Stage 3 Methodology ML17283A0412017-08-24024 August 2017 Enclosure 3 - Licensee'S Presentation-Seabrook Station, License Amendment Request 16-03 ASR Structural Evaluation Methodology ML17164A2712017-06-0707 June 2017 Presentation Slides for Annual Assessment Meeting 2017 ML16176A0542016-06-21021 June 2016 6/21/2016 - Seabrook Station Annual Assessment Meeting - NRC Presentation Slides (Assessment and ASR Update) ML16168A4122016-06-15015 June 2016 Slides for Public Meeting with NextEra Energy Regarding Seabrook Station ASR License Amendment ML16146A2002016-04-28028 April 2016 License Renewal Application, April 28, 2016, Public Meeting NextEra Presentation ML14190B0432014-07-0909 July 2014 Annual Assessment Meeting Performance Slides - June 24 2014 ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on Testing Program ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML13357A0462013-12-23023 December 2013 Update on ASR ML13133A2492013-05-29029 May 2013 Slides from May 9, 2013, Meeting with NextEra Energy Seabrook, LLC on Pre-Submittal of a Fixed Incore Detector License Amendment Request ML13066A4882013-03-21021 March 2013 Summary of Meeting Held on February 21, 2013, Between the NRC and NextEra Energy Seabrook, LLS Regarding License Renewal Application, Seabrook Station ML12356A0432012-12-11011 December 2012 Safety Implications and Status of ASR Condition - Public Meeting on 12/11/2012 ML12236A3852012-08-23023 August 2012 Memo Summary of NextEra Energy Seabrook Drop in Visit and Slides, August 22, 2012 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML12131A4312012-05-10010 May 2012 Aam ROP-12 Slides-Safety Performance & Alkali-Silica Reaction - r9 Revised Format ML1211604142012-04-23023 April 2012 Structural Assessment of Seabrook Station - Role of Concrete Material Testing ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12026A4592012-01-26026 January 2012 EDG Ifr ML11343A4482011-12-0909 December 2011 NextEra Drop in Meeting Summary and Slides from 11-14-2011 Meeting with Region-I SBK-L-11190, Supplement to Request for Closed Meeting to Discuss Proprietary Test2011-09-19019 September 2011 Supplement to Request for Closed Meeting to Discuss Proprietary Test ML11259A0022011-09-15015 September 2011 Meeting Slides Preliminary Site-Specific Results of the License Renewal Environmental Review for Seabrook Station. ML1116500382011-06-0808 June 2011 Aam Slides, June 8, 2011 ML12054A6412011-05-24024 May 2011 Concrete Degradation - Alkali Silica Reaction, W/Handwritten Notes ML1108206992011-03-22022 March 2011 3/22/11 Revised Pre-application Meeting Slides Regarding NFPA 805 License Amendment Request ML1022205712010-08-10010 August 2010 License Renewal Process Overview and Scoping Public Meeting Slides ML1019703702010-07-19019 July 2010 License Renewal Process Overview ML1013901282010-05-17017 May 2010 License Renewal Overview Presentation for Seabrook Station ML1011004582010-04-20020 April 2010 NRC Slides for Seabrook Annual Assessment Meeting, April 14, 2010 ML0927403042009-09-22022 September 2009 NextEra Letter and Slide Presentation to NRC Seabrook Regulatory Conference, Dated 9/22/09 ML0910604982009-04-30030 April 2009 NRC Slides for Annual Assement Meeting, 4/30/09 ML0809300252008-04-0202 April 2008 NRC Slides - Seabrook Aam 2008 ML0710002082007-03-29029 March 2007 Aam Slides for EOC 2006-07 ML0708001192007-03-21021 March 2007 Slides, End of the Presentation, from Seabrook Station Annual Assessment Meeting for EOC 2006-07 ML0727105992006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power 2024-05-24
[Table view] |
Text
Seabrook Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 30, 2006
Purpose of Todays Meeting A public forum for discussion of the licensees performance NRC will address the licensee performance issues identified in the annual assessment letter Licensee 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
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 Paul G. Krohn Regional Specialists Branch Chief Seabrook Senior Project Engineers Resident Inspectors Scott Barber Glenn Dentel Barry Norris Steve Shaffer
NRC Representatives z Glenn Dentel, Senior Resident Inspector Steve Shaffer, Resident Inspector
- (603) 474-3589/3580 z Ed Miller, Project Manager, NRR
- (301) 415-2481 z Paul Krohn, Branch Chief
- (610) 337-5120 z Scott Barber, Senior Project Engineer
- (610) 337-5232 z Barry Norris, Senior Project Engineer
- (610) 337-5111
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: 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
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
Seabrook Assessment Results (Jan 1 - Dec 31, 2005) z Licensee Response Column z No safety significant findings or PIs
Seabrook Inspection Activities (Jan 1 - Dec 31, 2005) 6800 Hours of inspection related activities Two resident inspectors assigned to the site Specialist Inspections
- 9 regional inspections
- 2 team inspections
Seabrook Inspection Activities (Jan 1 - Dec 31, 2005)
Inspection findings
- 8 findings of very low safety significance (Green)
Refueling outage (April 2 - April 30, 2005)
- no findings related to the outage Safety System Design team inspection
- 1 finding of very low safety significance (Green)
Triennial Fire Protection team inspection
- 1 finding of very low safety significance (Green)
Seabrook Annual Assessment Summary January 1 - December 31, 2005 z FPL operated Seabrook Station in a manner that preserved public health and safety z All cornerstone objectives were met z NRC plans baseline inspections at Seabrook for the remainder of the assessment period
Licensee Response and Remarks Gene St. Pierre Site Vice President FPL Energy Seabrook, LLC
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 z Paul Krohn, Branch Chief pgk1@nrc.gov
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)
END OF THE PRESENTATION Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 30, 2006
Potential Public Interest Issues Safety Concerns Brought to the NRC z NRC has a formal process z Concerns are reviewed on an individual basis by NRC technical, legal, investigative staff and management z Issues of immediate concern receive prompt attention by NRC and by nuclear power plant management z NRCs process requires reviews of all valid safety issues to ensure they are adequately addressed z NRC implements measures to protect the identity of allegers including not commenting on the existence of a specific allegation
Potential Public Interest Issues Recent Press Articles on Security Issues z Current NRC policy is to not discuss security matters in a public forum z NRC will not comment on existence of allegations in this area z Notwithstanding these policies, we want to assure the public that if safety issues did exist, the NRC would take prompt action to address them