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| | number = ML111650038 | | | number = ML111650038 |
| | issue date = 06/08/2011 | | | issue date = 06/08/2011 |
| | title = Seabrook Aam Slides, June 8, 2011 | | | title = Aam Slides, June 8, 2011 |
| | author name = Burritt A L | | | author name = Burritt A |
| | author affiliation = NRC/RGN-I/DRP/PB3 | | | author affiliation = NRC/RGN-I/DRP/PB3 |
| | addressee name = | | | addressee name = |
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| | page count = 19 | | | page count = 19 |
| }} | | }} |
| | |
| | =Text= |
| | {{#Wiki_filter:Seabrook Station Assessment Meeting Seabrook Station Safety Performance in 2010 U.S. Nuclear Plant Safety in light of Japan Events 2010 Reactor Oversight Process Nuclear Regulatory Commission - Region I 1 |
| | |
| | NRC Representatives |
| | * James Clifford- Deputy Director, Division of Reactor Projects |
| | * Arthur Burritt - Branch Chief |
| | * William Raymond - Senior Resident Inspector |
| | * Jonathan Johnson - Resident Inspector 2 |
| | |
| | Agenda |
| | * Introduction |
| | * Discussion of safety performance at Seabrook |
| | * Discussion of U.S. nuclear plant safety in light of Japan events |
| | * NRC to address public questions |
| | * Closing remarks 3 |
| | |
| | NRC Assessment Summary Seabrook |
| | * NextEra operated Seabrook safely and in a manner that preserved the public health and safety and protected the environment. |
| | * Licensee Response column of the Action Matrix |
| | * Baseline inspections planned for 2011 4 |
| | |
| | Inspection Activities 2010 Seabrook |
| | * 6753 hours of inspection and related activities |
| | * 2 resident inspectors on site - residents perform inspections daily and can respond to plant events at any time |
| | * 3 major team inspections |
| | * CDBI |
| | * Emergency Planning |
| | * PI&R 5 |
| | |
| | Performance Indicator and Inspection Results January 1 through December 31, 2010 Seabrook |
| | * All Green Performance Indicators |
| | * 3 Green inspection finding 6 |
| | |
| | NRC Action Matrix Licensee Regulatory Degraded Multiple Repetitive Unacceptable Response Response Cornerstone Degraded Performance Cornerstone All Inputs are 1 or 2 White 2 White or 1 Multiple Yellow Inputs Overall Green; Inputs; Yellow Input; or 1 Red Input; Unacceptable Cornerstone Cornerstone Cornerstone Cornerstone Performance; Plants Objectives Objectives Objectives Met w/ Objectives Met w/ not permitted to Fully Met Fully Met Moderate Significant Operate w/in this Degradation in Degradation in Safety Column; Safety Performance Unacceptable Performance Margin to Safety |
| | * Increasing safety significance |
| | * Increasing NRC inspection efforts |
| | * Increasing NRC/Licensee management involvement |
| | * Increasing regulatory actions |
| | |
| | 2010 Seabrook Assessment Summary |
| | * Seabrook was operated safely |
| | * Licensee Response column of the Action Matrix |
| | * Baseline inspections planned for 2011 8 |
| | |
| | Seabrook Assessment Meeting U.S. Nuclear Plant Safety in Light of Japan Events 9 |
| | |
| | U.S. Nuclear Plants Remain Safe |
| | * NRC requires plants to be designed to withstand external events |
| | * NRC requires a defense defense-in-depth in depth approach to safety |
| | * NRC performs independent safety inspections |
| | * NRC assesses new safety information and requires improvements 10 |
| | |
| | Designed for Site Specific Natural Events |
| | * Earthquakes |
| | * Tsunamis |
| | * Hurricanes |
| | * Floods |
| | * Tornadoes 11 |
| | |
| | The NRC Requires Defense-In-Depth |
| | * Redundant and diverse safety systems |
| | * Multiple physical barriers to contain radioactive material |
| | * Testing and inspection of systems important to safety |
| | * Emergency planning 12 |
| | |
| | NRC Independent Safety Inspections Reactor Oversight Program |
| | * NRC inspectors have unfettered access to all plant activities related to nuclear safety and security |
| | * At least two full-time NRC resident inspectors at each nuclear plant |
| | * NRC specialists conduct additional inspections at each nuclear plant 13 |
| | |
| | NRC Requires Safety Improvements NRC assesses new safety information, develops lessons learned, and requires safety enhancements: |
| | * NRC operating experience program |
| | * Rulemaking (Station Blackout) |
| | * Post TMI Actions |
| | * Post 9/11 Orders |
| | * Generic Safety Issues 14 |
| | |
| | NRC Response to Events in Japan |
| | * NRC conducting a methodical and systematic review |
| | * Near-term actions (<90 days) |
| | - conducting additional inspections |
| | - identifying near term operational issues |
| | * Longer-term actions 15 |
| | |
| | Directors Comments Jim Clifford Deputy Director Division of Reactor Projects Region I 16 |
| | |
| | Meeting Ground Rules |
| | : 1. Please be respectful to the speaker - only one speaker at a time |
| | : 2. See NRC staff if you have procedural questions/concerns or still want to sign up. |
| | : 3. NRC staff members will be available after the meeting to talk to those interested 17 |
| | |
| | Questions 18 |
| | |
| | Contacting the NRC |
| | * Report a safety concern |
| | * 1-800-695-7403 |
| | * allegation@nrc.gov |
| | * General questions |
| | * www.nrc.gov |
| | * Region I Public Affairs |
| | * Diane Screnci, 610-332-5330 or diane.screnci@nrc.gov |
| | * Neil Sheehan, 610-332-5331 or neil.sheehan@nrc.gov 19}} |
|
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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
[Table view] Category:Meeting Briefing Package/Handouts
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 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 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 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 2023-06-26
[Table view] |
Text
Seabrook Station Assessment Meeting Seabrook Station Safety Performance in 2010 U.S. Nuclear Plant Safety in light of Japan Events 2010 Reactor Oversight Process Nuclear Regulatory Commission - Region I 1
NRC Representatives
- James Clifford- Deputy Director, Division of Reactor Projects
- William Raymond - Senior Resident Inspector
- Jonathan Johnson - Resident Inspector 2
Agenda
- Discussion of safety performance at Seabrook
- Discussion of U.S. nuclear plant safety in light of Japan events
- NRC to address public questions
NRC Assessment Summary Seabrook
- NextEra operated Seabrook safely and in a manner that preserved the public health and safety and protected the environment.
- Licensee Response column of the Action Matrix
- Baseline inspections planned for 2011 4
Inspection Activities 2010 Seabrook
- 6753 hours0.0782 days <br />1.876 hours <br />0.0112 weeks <br />0.00257 months <br /> of inspection and related activities
- 2 resident inspectors on site - residents perform inspections daily and can respond to plant events at any time
Performance Indicator and Inspection Results January 1 through December 31, 2010 Seabrook
- All Green Performance Indicators
- 3 Green inspection finding 6
NRC Action Matrix Licensee Regulatory Degraded Multiple Repetitive Unacceptable Response Response Cornerstone Degraded Performance Cornerstone All Inputs are 1 or 2 White 2 White or 1 Multiple Yellow Inputs Overall Green; Inputs; Yellow Input; or 1 Red Input; Unacceptable Cornerstone Cornerstone Cornerstone Cornerstone Performance; Plants Objectives Objectives Objectives Met w/ Objectives Met w/ not permitted to Fully Met Fully Met Moderate Significant Operate w/in this Degradation in Degradation in Safety Column; Safety Performance Unacceptable Performance Margin to Safety
- Increasing safety significance
- Increasing NRC inspection efforts
- Increasing NRC/Licensee management involvement
- Increasing regulatory actions
2010 Seabrook Assessment Summary
- Seabrook was operated safely
- Licensee Response column of the Action Matrix
- Baseline inspections planned for 2011 8
Seabrook Assessment Meeting U.S. Nuclear Plant Safety in Light of Japan Events 9
U.S. Nuclear Plants Remain Safe
- NRC requires plants to be designed to withstand external events
- NRC requires a defense defense-in-depth in depth approach to safety
- NRC performs independent safety inspections
- NRC assesses new safety information and requires improvements 10
Designed for Site Specific Natural Events
The NRC Requires Defense-In-Depth
- Redundant and diverse safety systems
- Multiple physical barriers to contain radioactive material
- Testing and inspection of systems important to safety
NRC Independent Safety Inspections Reactor Oversight Program
- NRC inspectors have unfettered access to all plant activities related to nuclear safety and security
- At least two full-time NRC resident inspectors at each nuclear plant
- NRC specialists conduct additional inspections at each nuclear plant 13
NRC Requires Safety Improvements NRC assesses new safety information, develops lessons learned, and requires safety enhancements:
- NRC operating experience program
- Rulemaking (Station Blackout)
NRC Response to Events in Japan
- NRC conducting a methodical and systematic review
- Near-term actions (<90 days)
- conducting additional inspections
- identifying near term operational issues
Directors Comments Jim Clifford Deputy Director Division of Reactor Projects Region I 16
Meeting Ground Rules
- 1. Please be respectful to the speaker - only one speaker at a time
- 2. See NRC staff if you have procedural questions/concerns or still want to sign up.
- 3. NRC staff members will be available after the meeting to talk to those interested 17
Questions 18
Contacting the NRC