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Category:Slides and Viewgraphs
MONTHYEARML23177A1142023-06-26026 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 ML13357A0412013-12-23023 December 2013 Public Meeting on Seabrook Station Testing Program ML13357A0432013-12-23023 December 2013 ASR at Seabrook Station Update on 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 ML0727106062006-06-0505 June 2006 Viewgraphs of Use of Ultrasonic Flow Measurement to Determine Reactor Power ML0608202482006-03-23023 March 2006 NRC Slides for Public Meeting with FPL Seabrook to Discuss Cy 2005 Performance ML0601300312005-12-16016 December 2005 Meeting Slides, Measurement Uncertainty Recapture Fple/Caldon - NRC Meeting December 16, 2005 2023-06-26
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U.S.NRC Seabrook United States Nuclear Commission Protecting People and the Environment A*pril 20, MEMO FOR THE NRC Slides for April 14,
U.S.NRC NRC Strategic Plan United States Nuclear Commission Protecting People and the Environment 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
U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment 2009 Assessment Summary NextEra operated Seabrook safely and in a manner that preserved the public health and safety and protected the environment . .. Regulatory Response column of the Action Matrix . .. Baseline inspections planned for 2010. " IP 95001 supplemental inspection planned for second quarter.
I nspection Activities at United States Nuclear Commission Protecting People and the Environment Seabt"ook in 2009 " 5618 hours0.065 days <br />1.561 hours <br />0.00929 weeks <br />0.00214 months <br /> of inspection and related activities
.. 2 resident inspectors on site .. 12 regional inspections
.. 1 team inspection Seabrook U.S.NRC United States Nuclear Commission Protecting People and the Environment Performance Indicator Inspection January 1 through December 31, " All Green Performance Indicators iii Identified 2 Green inspection findings " Identified 1 White inspection finding -failure of the B EDG in February 2009 U.S.NRC United States Nuclear Commission Insoection Protecting People and the Environment
- Report 2009-07 B EDG failed to run during February 25, 2009 test EDG shutdown when cooling water gasket failed Gasket was modified during overhaul in January 2009 Gasket design was not of adequate material, thickness
& configuration U.S.NRC United Slates NucJea.f Commission Protecting People and the Environment Inadequate Design Control Q suitability of gasket for flange conditions
.. flange performance history Q potential failure modes " impacts of vibrations on flange performance Inadequate Corrective Actions NextEra did not adequately tj. use internal operating experience " correct known flange vibrations Theme: Design Control & U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment Corrective Actions I<ey Point: EDG finding in the area of design control, with aspects of inadequate corrective actions Another finding in 2009, unrelated to the EDG, concerned inadequate design control for the failure to verify that service water isolation valve leakage was within design assumptions U.S.NRC United States Nuclear Regulatory Commission NRC Action Matrix Licensee l Regulatory 1\ Degraded Response , All Inputs a Cornerstor Fully Met, Response 1 or 2 White Inputs; Cornerstone Objectives Fully Met Cornerstone
\ 2 White or 1 Yellow Input; Cornerstone jectives Met wi j Moderate egradation in Safety Performance Multiple Multiple Inputs or 1 Input; Objectives Met Degradation Safety Protecting People and t-he Environment Unacceptable Performance Overall Unacceptable Performance; Plants not permitted to Operate wlin this Column; Unacceptable Margin to Safety
.. Increasing safety significance
.. Increasing NRC inspection efforts .. Increasing NRC/Licensee management involvement
.. Increasing regulatory actions 2010 Inspection U.S.NRC United States Nuclear Commission Protecting People atul the Environment for Seabrook Supplemental and Baseline Inspection Baseline inspections planned for 2010. IP 95001 supplemental inspection planned for the second quarter of 2010 U.S.NRC United States Nuclear Commission Protecting People ana the Environment NextEra Energy Response and Seabrook U.S.NRC United States Nuclear Regulatory Commission Protecting People and the Environment 2009 Assessment Summary "Seabrook was in the Regulatory Response column of the Action Matrix. " Baseline inspections are planned for " IP 95001 supplemental inspection is planned for the second quarter 2010.
U.S.NR C United States Nuclear Regulatory Commission Protecting People and the Environment Contacting the NRC Report a safety concern: -(800) 695-7403 -Allegation@nrc.gov General information or questions:
-Public Affairs Officers:
- Neil Sheehan 610-337-5331 NRC U.S.NRC United States Nuclear Commission Protecting People and the Envi1Onment Threshold Summary .. .. Performance Indicators (PI) Baseline Inspection " White Requires additional NRC oversight Requires more NRC oversight ill Red Requires most NRC oversight nspection Findings Very low safety issue " .. White Low to moderate safety issue Substantial safety issue " Red High safety issue I nspection Activities at United States Nuclear Regulatory Commission Protecting People and the Environment Seabrook in Baseline Inspection Performance Indicators (Pis) 5618 hrs inspection 16 Pis per operating unit 2 resident inspectors on site Significance Threshold Across the 7 Cornerstones 17 regional inspections Green Very low safety issue Inspector verified 1 major team inspection White Low to moderate safety issue Yellow Substantial safety issue Red High safety issue X-Cutting Themes 1 Greater-than-Green No Greater-than-Green None 2 Green / SL IV findings Performance Indicators Substantive X-cutting Issues Action Matrix None