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| {{#Wiki_filter:NRC Annual Performance Assessment of Seabrook 2007 Reactor Oversight Program 2 Purpose of Today's MeetingDiscuss Seabrook Plant Performance for CY 2007 Provide FPL Energy the opportunity to respond to the NRC's Annual | | {{#Wiki_filter:NRC Annual Performance Assessment of Seabrook 2007 Reactor Oversight Program |
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| Performance Assessment and discuss new or existing programs to improve performance Provide the public an opportunity to discuss plant performance and the NRC'srole in ensuring safe plant | | Purpose of Todays Meeting |
| | * Discuss Seabrook Plant Performance for CY 2007 |
| | * Provide FPL Energy the opportunity to respond to the NRCs Annual Performance Assessment and discuss new or existing programs to improve performance |
| | * Provide the public an opportunity to discuss plant performance and the NRCs role in ensuring safe plant operations with the NRC staff 2 |
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| operations with the NRC staff 3 AgendaIntroductionNRC Organization and Performance GoalsReactor Oversight Process (ROP)National Summary of Plant PerformanceSeabrook's Plant Performance AssessmentFPL Energy's Response and RemarksNRC Closing RemarksBreakNRC available to address public questions 4Region I OrganizationSamuel J. CollinsRegional AdministratorMarc J. DapasDeputy Regional AdministratorDavid C. LewDirector Division of Reactor ProjectsJames W. CliffordDeputy DirectorMarsha K. GamberoniDirector Division of Reactor SafetyDarrell J. RobertsDeputy DirectorRegional SpecialistsArthur L. BurrittBranch ChiefProject EngineersLeonard Cline -Senior PEJoyce C. Tomlinson -PESeabrook Resident InspectorsWilliam Raymond -Senior RIPeter Presby-RI (acting) 5NRC RepresentativesArthur L. Burritt, Branch Chief (610) 337-5069William Raymond, SRI (603) 474-3589Peter Presby, RI (acting)
| | Agenda |
| (603) 474-3589Ross Moore, (in training) 6NRC Strategic Plan GoalsSafety: Ensure adequate protection of public health and safety and the environmentSecurity: Ensure adequate protection in the secure use and management of radioactive materials 7 Reactor Oversight Process 3 Strategic Areas & 7 CornerstonesReactorSafetyRadiationSafetySafeguardsInitiatingEventsMitigatingSystemsBarrierIntegrityEmergencyPreparedness OccupationalRadiationSafety PublicRadiationSafetyPhysicalProtection 8 Reactor Oversight ProcessSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance AreasSafetyCornerstonesBaseline Inspection ResultsSignificance ThresholdAction MatrixSignificance ThresholdPerformance IndicatorResultsRegulatory ResponseStrategicPerformance Areas 9 Typical Baseline Inspection Areas Equipment AlignmentFire ProtectionOperator ResponseEmergency PreparednessRadiation Release ControlsWorker Radiation ProtectionCorrective Action Program 10Significance Threshold Performance IndicatorsGreen Baseline InspectionWhiteMay increase NRC oversightYellow Requires more NRC oversightRed Requires the most NRC oversight Inspection FindingsGreenVery low safety issueWhiteLow to moderate safety issueYellowSubstantial safety issueRed High safety issue 11Action Matrix ConceptLicenseeResponseRegulatoryResponseDegradedCornerstoneMultiple/Rep.Degraded CornerstoneUnacceptablePerformanceIncreasing Safety SignificanceIncreasing NRC Inspection EffortsIncreasing NRC/Licensee Management InvolvementIncreasing Regulatory Actions 12National Summary (at end of 2007)Licensee Response 87Regulatory Response 8Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone1Unacceptable 0Total104 13National Summary (at end of 2007)
| | * Introduction |
| Performance Indicator ResultsGreen 1954White8Yellow2Red0 Total Inspection FindingsGreen918White9Yellow2Red0 14NRC 2007 Annual Assessment for SeabrookFPL Energy operated Seabrook in a manner that preserved public health and safety and protected the
| | * NRC Organization and Performance Goals |
| | * Reactor Oversight Process (ROP) |
| | * National Summary of Plant Performance |
| | * Seabrooks Plant Performance Assessment |
| | * FPL Energys Response and Remarks |
| | * NRC Closing Remarks |
| | * Break |
| | * NRC available to address public questions 3 |
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| environmentAll cornerstone objectives were fully metSeabrook was in the Licensee Response column of the NRC's Action Matrix for all four quarters of 2007NRC plans baseline inspections at Seabrook for the remainder of CY 2008 15NRC Inspection Activities at Seabrook6000+ hours of inspection related activities2329 hours of direct inspection activities2 resident inspectors on-site13 Regional Specialist inspections 16NRC Inspection ActivitiesTeam Inspections
| | Region I Organization Samuel J. Collins Regional Administrator Marc J. Dapas Deputy Regional Administrator David C. Lew Marsha K. Gamberoni Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Darrell J. Roberts Deputy Director Deputy Director Arthur L. Burritt Regional Specialists Branch Chief Seabrook Resident Inspectors William Raymond - Senior RI Project Engineers Peter Presby - RI (acting) Leonard Cline - Senior PE Joyce C. Tomlinson - PE 4 |
| -Component Design Basis team inspectionSupplemental inspections | |
| -Emergency Diesel Generators 17Safety Significant PIs / FindingsAll Performance Indicators in the Reactor and Radiation Safety Areas at | |
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| Seabrook remained GREEN throughout
| | NRC Representatives |
| | * Arthur L. Burritt, Branch Chief (610) 337-5069 |
| | * William Raymond, SRI (603) 474-3589 |
| | * Peter Presby, RI (acting) |
| | (603) 474-3589 |
| | * Ross Moore, (in training) 5 |
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| 2007Inspectors documented six GREEN inspection findings in the Reactor and Radiation Safety Areas at Seabrook in
| | NRC Strategic Plan Goals |
| | Safety: Ensure adequate protection of public health and safety and the environment |
| | Security: Ensure adequate protection in the secure use and management of radioactive materials 6 |
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| 2007 18NRC Inspection FindingsGreen -Enclosure building air handling fan power supply cable connections not torqued per procedures. Green -Inadequate testing of the alternate cooling water supply resulted in failure of alternate cooling water to centrifugal charging pump lube oil coolersGreen -Inadequate corrective actions resulted in multiple voltage regulator failures of the B EDG 19NRC 2007 Assessment Summary for SeabrookFPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment.Seabrook was in the Licensee Response Column of the Action Matrix for all of 2007.NRC plans baseline inspections for the remainder of 2008. | | Reactor Oversight Process 3 Strategic Areas & 7 Cornerstones Reactor Radiation Safeguards Safety Safety Public Occupational Initiating Mitigating Barrier Emergency Physical Radiation Radiation Events Systems Integrity Preparedness Protection Safety Safety 7 |
| 20 Licensee Response and Remarks Mr. G. St. Pierre Site Vice President -Seabrook FPL Energy 21 Contacting the NRCReport an emergency:(301) 816-5100 (call collect)Report a safety concern:(800) 695-7403Allegation@nrc.govGeneral information or questions:www.nrc.govSelect "Public Meetings & Involvement"or "Contact Us" 22 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)
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| End of the PresentationNuclear Regulatory Commission -Region IKing of Prussia, Pennsylvania March 25, 2008 24NRC Performance IndicatorsInitiating Events PIsUnplanned ScramsUnplanned Scrams with Complications Unplanned Power ChangesMitigating Systems PIsEmergency AC Power System High Pressure Injection SystemResidual Heat Removal SystemCooling Water Support Systems Safety System Functional FailuresBarrier Integrity PIsReactor Coolant System Specific Activity Reactor Coolant System LeakageEmergency Planning PIsDrill / Exercise PerformanceEmergency Response Organization ParticipationAlert and Notification SystemRadiation Protection PIsOccupational Exposure Control Effectiveness RETS / ODCM Radiological EffluentSecurity PIsare not Publicly Available 25Seabrook Performance IndicatorsUnplanned Scrams (G)Unplanned Scrams with Complications (G)Unplanned Power Changes (G)Emergency AC Power System (G)High Pressure Injection System (G)Residual Heat Removal System (G)Heat Removal System (G)Cooling Water Systems (G)Safety System Functional Failures (G)RCS Specific Activity (G)RCS Leakage (G)Alert and Notification System (G)ERO Drill Participation (G)Drill/Exercise Performance (G)RETS/ODCM Radiological Effluent (G)Occupational Exposure Control Effectiveness (G)Security (Not Public)}} | | Reactor Oversight Process S tra te g ic P e rfo r m a n c e A re a s S a fety C o rn e r s to n e s B a s e lin e In s p e c tio n P e r fo r m a n c e In d ic a to r R e s u lts R e s u lts S ig n ific a n c e S ig n ific a n c e T h r e s h o ld T h r e s h o ld A c tio n M a tr ix R e g u la to ry R e s p o n s e 8 |
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| | Typical Baseline Inspection Areas |
| | * Equipment Alignment |
| | * Fire Protection |
| | * Operator Response |
| | * Emergency Preparedness |
| | * Radiation Release Controls |
| | * Worker Radiation Protection |
| | * Corrective Action Program 9 |
| | |
| | Significance Threshold Performance Indicators |
| | Green Baseline Inspection |
| | White May increase NRC oversight |
| | Yellow Requires more NRC oversight |
| | Red Requires the most NRC oversight Inspection Findings |
| | Green Very low safety issue |
| | White Low to moderate safety issue |
| | Yellow Substantial safety issue |
| | Red High safety issue 10 |
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| | 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 11 |
| | |
| | National Summary (at end of 2007) |
| | Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 12 |
| | |
| | National Summary (at end of 2007) |
| | Performance Indicator Results |
| | Green 1954 |
| | White 8 |
| | Yellow 2 |
| | Red 0 Total Inspection Findings |
| | Green 918 |
| | White 9 |
| | Yellow 2 |
| | Red 0 13 |
| | |
| | NRC 2007 Annual Assessment for Seabrook |
| | * FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment |
| | * All cornerstone objectives were fully met |
| | * Seabrook was in the Licensee Response column of the NRCs Action Matrix for all four quarters of 2007 |
| | * NRC plans baseline inspections at Seabrook for the remainder of CY 2008 14 |
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| | NRC Inspection Activities at Seabrook |
| | * 6000+ hours of inspection related activities |
| | * 2329 hours of direct inspection activities |
| | * 2 resident inspectors on-site |
| | * 13 Regional Specialist inspections 15 |
| | |
| | NRC Inspection Activities |
| | * Team Inspections |
| | - Component Design Basis team inspection |
| | * Supplemental inspections |
| | - Emergency Diesel Generators 16 |
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| | Safety Significant PIs / Findings |
| | * All Performance Indicators in the Reactor and Radiation Safety Areas at Seabrook remained GREEN throughout 2007 |
| | * Inspectors documented six GREEN inspection findings in the Reactor and Radiation Safety Areas at Seabrook in 2007 17 |
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| | NRC Inspection Findings |
| | * Green - Enclosure building air handling fan power supply cable connections not torqued per procedures. |
| | * Green - Inadequate testing of the alternate cooling water supply resulted in failure of alternate cooling water to centrifugal charging pump lube oil coolers |
| | * Green - Inadequate corrective actions resulted in multiple voltage regulator failures of the B EDG 18 |
| | |
| | NRC 2007 Assessment Summary for Seabrook |
| | * FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment. |
| | * Seabrook was in the Licensee Response Column of the Action Matrix for all of 2007. |
| | * NRC plans baseline inspections for the remainder of 2008. |
| | 19 |
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| | Licensee Response and Remarks Mr. G. St. Pierre Site Vice President - Seabrook FPL Energy 20 |
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| | 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 Public Meetings & Involvement or Contact Us 21 |
| | |
| | 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) 22 |
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| | End of the Presentation Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 25, 2008 |
| | |
| | NRC Performance Indicators Initiating Events PIs |
| | * Unplanned Scrams |
| | * Unplanned Scrams with Complications |
| | * Unplanned Power Changes Mitigating Systems PIs |
| | * Emergency AC Power System |
| | * High Pressure Injection System |
| | * Residual Heat Removal System |
| | * Cooling Water Support Systems |
| | * Safety System Functional Failures Barrier Integrity PIs |
| | * Reactor Coolant System Specific Activity |
| | * Reactor Coolant System Leakage Emergency Planning PIs |
| | * Drill / Exercise Performance |
| | * Emergency Response Organization Participation |
| | * Alert and Notification System Radiation Protection PIs |
| | * Occupational Exposure Control Effectiveness |
| | * RETS / ODCM Radiological Effluent Security PIs are not Publicly Available 24 |
| | |
| | Seabrook Performance Indicators Occupational RETS/ODCM Unplanned Emergency AC RCS Specific Drill/Exercise Security Exposure Control Radiological Scrams (G) Power System (G) Activity (G) Performance (G) (Not Public) |
| | Effectiveness (G) Effluent (G) |
| | Unplanned High Pressure ERO Drill Scrams with Injection System RCS Leakage (G) |
| | Participation (G) |
| | Complications (G) (G) |
| | Residual Heat Alert and Unplanned Power Removal System Notification Changes (G) |
| | (G) System (G) |
| | Heat Removal System (G) |
| | Cooling Water Systems (G) |
| | Safety System Functional Failures (G) 25}} |
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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
NRC Annual Performance Assessment of Seabrook 2007 Reactor Oversight Program
Purpose of Todays Meeting
- Discuss Seabrook Plant Performance for CY 2007
- Provide FPL Energy the opportunity to respond to the NRCs Annual Performance Assessment and discuss new or existing programs to improve performance
- Provide the public an opportunity to discuss plant performance and the NRCs role in ensuring safe plant operations with the NRC staff 2
Agenda
- NRC Organization and Performance Goals
- Reactor Oversight Process (ROP)
- National Summary of Plant Performance
- Seabrooks Plant Performance Assessment
- FPL Energys Response and Remarks
- NRC available to address public questions 3
Region I Organization Samuel J. Collins Regional Administrator Marc J. Dapas Deputy Regional Administrator David C. Lew Marsha K. Gamberoni Director Division of Reactor Projects Director Division of Reactor Safety James W. Clifford Darrell J. Roberts Deputy Director Deputy Director Arthur L. Burritt Regional Specialists Branch Chief Seabrook Resident Inspectors William Raymond - Senior RI Project Engineers Peter Presby - RI (acting) Leonard Cline - Senior PE Joyce C. Tomlinson - PE 4
NRC Representatives
- Arthur L. Burritt, Branch Chief (610) 337-5069
- William Raymond, SRI (603) 474-3589
(603) 474-3589
- Ross Moore, (in training) 5
NRC Strategic Plan Goals
Safety: Ensure adequate protection of public health and safety and the environment
Security: Ensure adequate protection in the secure use and management of radioactive materials 6
Reactor Oversight Process 3 Strategic Areas & 7 Cornerstones Reactor Radiation Safeguards Safety Safety Public Occupational Initiating Mitigating Barrier Emergency Physical Radiation Radiation Events Systems Integrity Preparedness Protection Safety Safety 7
Reactor Oversight Process S tra te g ic P e rfo r m a n c e A re a s S a fety C o rn e r s to n e s B a s e lin e In s p e c tio n P e r fo r m a n c e In d ic a to r R e s u lts R e s u lts S ig n ific a n c e S ig n ific a n c e T h r e s h o ld T h r e s h o ld A c tio n M a tr ix R e g u la to ry R e s p o n s e 8
Typical Baseline Inspection Areas
- Radiation Release Controls
- Worker Radiation Protection
- Corrective Action Program 9
Significance Threshold Performance Indicators
Green Baseline Inspection
White May increase NRC oversight
Yellow Requires more NRC oversight
Red Requires the most NRC oversight Inspection Findings
Green Very low safety issue
White Low to moderate safety issue
Yellow Substantial safety issue
Red High safety issue 10
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 11
National Summary (at end of 2007)
Licensee Response 87 Regulatory Response 8 Degraded Cornerstone 8 Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Total 104 12
National Summary (at end of 2007)
Performance Indicator Results
Green 1954
White 8
Yellow 2
Red 0 Total Inspection Findings
Green 918
White 9
Yellow 2
Red 0 13
NRC 2007 Annual Assessment for Seabrook
- FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment
- All cornerstone objectives were fully met
- Seabrook was in the Licensee Response column of the NRCs Action Matrix for all four quarters of 2007
- NRC plans baseline inspections at Seabrook for the remainder of CY 2008 14
NRC Inspection Activities at Seabrook
- 6000+ hours of inspection related activities
- 2329 hours0.027 days <br />0.647 hours <br />0.00385 weeks <br />8.861845e-4 months <br /> of direct inspection activities
- 2 resident inspectors on-site
- 13 Regional Specialist inspections 15
NRC Inspection Activities
- Component Design Basis team inspection
- Emergency Diesel Generators 16
Safety Significant PIs / Findings
- All Performance Indicators in the Reactor and Radiation Safety Areas at Seabrook remained GREEN throughout 2007
- Inspectors documented six GREEN inspection findings in the Reactor and Radiation Safety Areas at Seabrook in 2007 17
NRC Inspection Findings
- Green - Enclosure building air handling fan power supply cable connections not torqued per procedures.
- Green - Inadequate testing of the alternate cooling water supply resulted in failure of alternate cooling water to centrifugal charging pump lube oil coolers
- Green - Inadequate corrective actions resulted in multiple voltage regulator failures of the B EDG 18
NRC 2007 Assessment Summary for Seabrook
- FPL Energy operated Seabrook in a manner that preserved public health and safety and protected the environment.
- Seabrook was in the Licensee Response Column of the Action Matrix for all of 2007.
- NRC plans baseline inspections for the remainder of 2008.
19
Licensee Response and Remarks Mr. G. St. Pierre Site Vice President - Seabrook FPL Energy 20
Contacting the NRC
(301) 816-5100 (call collect)
(800) 695-7403
Allegation@nrc.gov
- General information or questions:
www.nrc.gov
Select Public Meetings & Involvement or Contact Us 21
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) 22
End of the Presentation Nuclear Regulatory Commission - Region I King of Prussia, Pennsylvania March 25, 2008
NRC Performance Indicators Initiating Events PIs
- Unplanned Scrams with Complications
- Emergency AC Power System
- High Pressure Injection System
- Cooling Water Support Systems
- Drill / Exercise Performance
- Emergency Response Organization Participation
- Alert and Notification System Radiation Protection PIs
- Occupational Exposure Control Effectiveness
- RETS / ODCM Radiological Effluent Security PIs are not Publicly Available 24
Seabrook Performance Indicators Occupational RETS/ODCM Unplanned Emergency AC RCS Specific Drill/Exercise Security Exposure Control Radiological Scrams (G) Power System (G) Activity (G) Performance (G) (Not Public)
Effectiveness (G) Effluent (G)
Unplanned High Pressure ERO Drill Scrams with Injection System RCS Leakage (G)
Participation (G)
Complications (G) (G)
Residual Heat Alert and Unplanned Power Removal System Notification Changes (G)
(G) System (G)
Heat Removal System (G)
Cooling Water Systems (G)
Safety System Functional Failures (G) 25