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Category:Meeting Briefing Package/Handouts
MONTHYEARML22222A1102022-07-21021 July 2022 KM Session Final ML22178A1952022-06-27027 June 2022 2021 Davis Besse Nuclear Power Station End-of-Cycle Meeting Presentation ML22028A3922022-02-0101 February 2022 Licensee Regulatory Conference Presentation ML22028A3972022-02-0101 February 2022 NRC Regulatory Conference Presentation ML21176A1992021-06-25025 June 2021 Slideshow Presentation for 2020 End -of-Cycle Public Meeting for Davis-Besse and Perry ML20210M0712020-07-27027 July 2020 Combined End-of-Cycle 2019 Public Meeting Slide Presentation ML19249D0212019-09-0606 September 2019 End-of-Cycle Summary Handout (2018) ML18310A3802018-11-0808 November 2018 Pre-Submittal Meeting Davis-Besse Nuclear Power Station (DB) Post-Shutdown Emergency Plan (PSEP) License Amendment Request ML18180A1962018-06-29029 June 2018 Slides for Davis Besse 2017 EOC Open House ML17229B3382017-08-17017 August 2017 Presentation for 2016 Davis-Besse EOC Open House ML16174A3152016-06-21021 June 2016 Annual Assessment Meeting Open House June 21, 2016 ML15156A6962015-06-11011 June 2015 Annual Assessment Meeting Open House Handout ML14224A1112014-08-25025 August 2014 Safety Culture Presentation for Brazil, U.S. Workshop on Safety and Security Culture - August 25, 2014 ML14218A0542014-08-0707 August 2014 Handout Davis-Besse EOC Mtg ML14050A4002014-02-20020 February 2014 NRC Presentation for Davis-Besse Steam Generator Replacement Webinar ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13294A5972013-10-21021 October 2013 FENOC Presentation Slides for Public Meeting September 24, 2013 ML13157A0642013-06-0606 June 2013 June 11, 2013 NRC Presentation ML13159A0092013-06-0404 June 2013 Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12227A4172012-08-15015 August 2012 NRC End-Of-Cycle Assessment 2011 Meeting Presentation ML12221A2642012-08-0909 August 2012 NRC Public Meeting NRC Presentation 8/9/12 ML12221A2682012-08-0909 August 2012 FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML1206901712012-02-29029 February 2012 Slides and View Graphs - Boric Acid Corrosion Testing Program: Industry Perspective ML12200A2402012-02-23023 February 2012 Presentation Slides on Davis-Besse Shield Building Crack ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML12004A0102012-01-0404 January 2012 Public Meeting NRC Slides ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML1117209902011-06-15015 June 2011 Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station. ML1021501182010-07-29029 July 2010 Licensee Slides for Davis-Besse Annual Assessment Meeting ML1021501112010-07-29029 July 2010 NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting L-02-002, G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse2010-04-15015 April 2010 G20100238/EDATS: OEDO-2010-0305 - Ltr. Tom Gurdziel, 2.206 - Firstenergy - Davis-Besse ML0920202972009-07-15015 July 2009 NRC Slides from EOC Meeting ML0920202872009-07-15015 July 2009 Meeting Slides, NRC Annual Assessment Meeting Davis-Besse Nuclear Power Station ML0725600562007-09-12012 September 2007 9/12/2007 Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) 9/12/2007 NRC Meeting Slides ML0725600462007-09-11011 September 2007 9/11/2007-Meeting to Discuss Davis-Besse License Amendment Request for Conversion to Improved Technical Specifications (ITS) - 9/11/2007 NRC Meeting Slides ML0722201892007-08-0808 August 2007 NRC EOC Public Meeting Slides ML0717905962007-06-27027 June 2007 Slides from Public Meeting Between NRC and FENOC Regarding Response to May 14, 2007, Demand for Information ML0702603952007-01-31031 January 2007 Summary of Conference Telephone Call Regarding the Spring 2006 Steam Generator Inspections - Handouts ML0706502022007-01-23023 January 2007 Slides to Summary of Pre-Application Meeting with FENOC Proposed License Amendment Request for Measurement Uncertainty Recapture Power Uprate ML0632003672006-12-11011 December 2006 Slides, Improved Technical Specification Conversion from Category 1 Pre-submittal Meeting with Fenco to Discuss Davis-Besse's' Proposed Conversion to Improved Technical Specifications ML0612404142006-05-0202 May 2006 NRC Annual Assessment Meeting ML0601801602006-01-18018 January 2006 Industry Safety Culture Presentation for January 18, 2006 Public Meeting ML0603002272006-01-10010 January 2006 Multi-Regional NRC Public Meeting Licensee (FENOC) Slide Presentation ML0802205572005-09-12012 September 2005 NRC Commissioners Briefing by Firstenergy Nuclear Operating Co ML0525604472005-08-17017 August 2005 B&W Owners Group Reactor Vessel Working Group Summary of the Plans of the B&Wog Reactor Vessel Integrity Program ML0526600162005-08-16016 August 2005 Mantg Conference, 8/16/05 - Plenary - Keynote Speech by Samuel J. Collins, Regional Administrator, Region I, the Changing Roles of the Operators and Trainers 2022-07-21
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23152A2022023-06-0101 June 2023 2022 Davis-Besse End-of-Cycle Meeting Presentation ML22222A1102022-07-21021 July 2022 KM Session Final ML22178A1952022-06-27027 June 2022 2021 Davis Besse Nuclear Power Station End-of-Cycle Meeting Presentation ML22028A3922022-02-0101 February 2022 Licensee Regulatory Conference Presentation ML22028A3972022-02-0101 February 2022 NRC Regulatory Conference Presentation ML21176A1992021-06-25025 June 2021 Slideshow Presentation for 2020 End -of-Cycle Public Meeting for Davis-Besse and Perry ML20210M0712020-07-27027 July 2020 Combined End-of-Cycle 2019 Public Meeting Slide Presentation ML19249D0212019-09-0606 September 2019 End-of-Cycle Summary Handout (2018) ML18310A3802018-11-0808 November 2018 Pre-Submittal Meeting Davis-Besse Nuclear Power Station (DB) Post-Shutdown Emergency Plan (PSEP) License Amendment Request ML18180A1962018-06-29029 June 2018 Slides for Davis Besse 2017 EOC Open House ML17229B3382017-08-17017 August 2017 Presentation for 2016 Davis-Besse EOC Open House ML16174A3152016-06-21021 June 2016 Annual Assessment Meeting Open House June 21, 2016 ML16117A1822016-04-22022 April 2016 Industry Slides for the Spring 2016 Conference Call Regarding the Steam Generator Tube Inservice Inspections ML15156A6962015-06-11011 June 2015 Annual Assessment Meeting Open House Handout ML14224A1112014-08-25025 August 2014 Safety Culture Presentation for Brazil, U.S. Workshop on Safety and Security Culture - August 25, 2014 ML14218A0542014-08-0707 August 2014 Handout Davis-Besse EOC Mtg ML14050A4002014-02-20020 February 2014 NRC Presentation for Davis-Besse Steam Generator Replacement Webinar ML13322B3112013-11-13013 November 2013 NFPA 805 Transition - Meeting Slides, 11/13/2013 ML13294A5972013-10-21021 October 2013 FENOC Presentation Slides for Public Meeting September 24, 2013 ML13220A0632013-08-30030 August 2013 Dsd ED2013 3267 Presentation, Primary Water Stress Corrosion Cracking Tests and Metallurgical Analyses of Davis-Besse Control Rod Drive Mechanism Nozzle #4. ML13157A0642013-06-0606 June 2013 June 11, 2013 NRC Presentation ML13159A0092013-06-0404 June 2013 Notable Failures in Nondustructive Testing - June 4, 2013 Public Meeting ML13078A2492013-03-20020 March 2013 Project Overview-Public Mtg 3-20-13 Non Proprietary ML12269A0612012-09-26026 September 2012 FENOC Presentation for 2012-09-26 Public Meeting ML12227A4172012-08-15015 August 2012 NRC End-Of-Cycle Assessment 2011 Meeting Presentation ML12221A2642012-08-0909 August 2012 NRC Public Meeting NRC Presentation 8/9/12 ML12221A2682012-08-0909 August 2012 FENOC Shield Building Cracking Davis-Besse Public Meeting 8/9/12 ML12138A0732012-05-14014 May 2012 FENOC-Davis-Besse Nuclear Power Station, Unit 1 Docket No. 50-346, License No. NPF-3 Submittal of Contractor Root Cause Assessment Report-Section 5 ML12132A3442012-05-11011 May 2012 NRC-AERB Bilateral Meeting Slide Presentation (Nro/De), Aerb, India - May 16-17, 2012 ML1206901712012-02-29029 February 2012 Slides and View Graphs - Boric Acid Corrosion Testing Program: Industry Perspective ML12200A2402012-02-23023 February 2012 Presentation Slides on Davis-Besse Shield Building Crack ML1204402842012-02-16016 February 2012 Public Meeting Construction Experiences - Evaluate Impact of Concrete Degradation ML1200501462012-01-0505 January 2012 Public Meeting FENOC Slides ML12004A0102012-01-0404 January 2012 Public Meeting NRC Slides ML12200A2492011-12-22022 December 2011 Presentation Slides on Shield Building /Containment Delamination ML11220A2542011-08-0101 August 2011 DBNPS-Info Meeting Slides ML11221A3012011-08-0101 August 2011 521- R326C B&W Tech Cross Training - Chapter 16 Davis-Besse Loss of All Feedwater ML1117303602011-06-21021 June 2011 FENOC Licensee Slides for 6-21-11 All FENOC Meeting ML1116400632011-06-15015 June 2011 EOC NRC Slides for Public Meeting ML1117209902011-06-15015 June 2011 Meeting Presentation NRC Annual Assessment Meeting: Davis-Besse Nuclear Power Station. ML1032103472010-11-16016 November 2010 FENOC 11/16/10 Public Meeting Presentation Slides ML1025103462010-09-0909 September 2010 SIT Exit Meeting Presentation Slides ML1021501112010-07-29029 July 2010 NRC Slides for Davis-Besse; July 29, 2010; Annual Assessment Meeting ML1021501182010-07-29029 July 2010 Licensee Slides for Davis-Besse Annual Assessment Meeting ML1015400332010-06-0303 June 2010 Licensee Slides for June 3, 2010 Public Meeting Presentation ML1015400342010-06-0303 June 2010 NRC Slides for June 3, 2010 Public Meeting Presentation ML1009102662010-03-31031 March 2010 Slides FENOC and NRC Senior Management Briefing, 3-31-10 ML0920202872009-07-15015 July 2009 Meeting Slides, NRC Annual Assessment Meeting Davis-Besse Nuclear Power Station ML0920202972009-07-15015 July 2009 NRC Slides from EOC Meeting ML0814104322008-05-13013 May 2008 Meeting Slides, Davis-Besse Annual Assessment Meeting, Reactor Oversight Program - Cy 2007 2023-06-01
[Table view] |
Text
Briefing for Representative Kucinich's Staff on Activities at Davis-Besse Brian Sheron, Associate Director for Project Licensing and Technical Analysis, Office of Nuclear Reactor Regulation Michael Johnson, Deputy Director Division of Systems Safety and Analysis, Office of Nuclear Reactor Regulation Jack Grobe, Chairman, Davis-Besse Oversight Panel Laura Gerke, Office of Congressional Affairs November 11, 2003 1
.p RE3,
- .! , 1 Concerns Expressed by Representative Kucinich
_I
Topics of Discussion
- Overview of the Reactor Oversight Process (ROP)
- Evaluation of the Davis-Besse Degraded Reactor Head
- Discussion of NRC Oversight of Davis-Besse 3
NRC Reactor Oversight Process
- Reactor Oversight Process framework is structured and focuses on safety
- Action matrix integrates safety insights from SDPs and performance indicators resulting in consistent and predictable regulatory action 4
NRC Reactor Oversight
-I Process Framework REGULATORY FRAMEWORK Ccriersi
- HUMAN ---------- SAFETY CONSCIOUS WORIK--------------- 1'ROBLEM ---------
PERFORMANCE ENVIRONMENT IDENTIFICATION AND RESOLUTION 5
- A I -0 010 (A
I 1
11 I ..
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,..Reactor Oversight Process
-i 6
I -PA EGC0 CIV 4,;~q.
4- ~ '
~4' LEVEL OF SIGNIFICANCE ASSOCIATED I-
< 0 WITH INSPECTION FINDINGS
-I o.--Da
- Green - very low risk ,;;.mre~lh~aniF,00N0;!ears>ofp, significance ' W~~~~~~~~
- White - low to moderate One Core Damage Event per 1,000,000 Years of Operation risk significance White
- Yellow - substantive risk :;One'.Core.Damage, Event per, significance -100,000 Years :of Operation:
ll ,,'
7J.......Ye
.,0 2%'ow';
- Red - high risk significance 7
& 0:Reactor Safety Significance Determination Process SI)P - Used to evaluate the safety significance of individual inspection findings for input to the action matrix.
- Uses Pre-established tools
- Findings must represent a deficiency in licensee performance
- SDP's for the Initiating Event, Mitigating Systems, and Barrier Integrity cornerstones are quantitative in nature, based on use of Probabilistic Risk Assessment techniques
- Other cornerstones are qualitative in nature 8
Reactor Safety Significance Determination Process Three Phases:
- Phase 1 -Screens issues to quickly identify those of very low safety significance (Green)
- Phase 2 - Simplified PRA tool to allow inspectors to evaluate findings. This tool tends to produce a conservative estimate of the risk.
- Phase 3 - Full analysis by a risk analyst utilizing refined modeling assumptions. It uses best available methods to establish the risk significance.
9
Reactor Safety Significance I
Determination Process Review process
- A Significance and Enforcement Review Panel is convened to review each evaluation that is greater than very low safety significance (Green). The panel is comprised of managers from headquarters and the regions.
- A "preliminary determination" is transmitted to the licensee and the licensee is offered an opportunity to meet in public with the NRC or provide a written response
- Final Determination is issued 10
NRC Action Matrix Am
- Receives input from NRC inspections and plant performance indicators to determine appropriate NRC response
- NRC response is structured and provides a graded approach to agency actions depending on level of licensee performance during the 12 month assessment window
- NRC regulatory responses range from continued baseline inspections to regulatory orders to modify, suspend, or revoke operating license
- Results are shared with licensee and public on the NRC web page and at annual public meetings in the vicinity of the plant 11
0~
9(
0 NRCReactor Oversight Process i Reactor Oversight Process framework is structured and focuses on safety
- Action matrix integrates safety insights from performance deficiencies and performance indicators resulting in consistent and predictable regulatory action 12
NRC Oversight at Davis-Besse
-I
- NRC implementing special oversight at Davis-Besse due to significant performance deficiencies
- Significance Determination of reactor head wastage followed NRC Policies and Procedures e NRC Providing effective oversight of Davis-Besse 13
NRC Oversight at Davis-Besse
- NRC Davis-Besse Oversight Panel chartered April 2002
- Oversight Panel coordinates NRC activities and provides NRC oversight utilizing existing regulatory tools
- SDP utilized to evaluate significance of performance deficiencies at Davis-Besse 14
"Red" Significance Determination at Davis-Besse
- Performance deficiency involved the failure to effectively implement the corrective action program and boric acid corrosion management program
- The performance deficiency resulted in Reactor Head Wastage which was a challenge to Barrier Integrity
Significance Determination of W-0Head Wastage
- Phase 1 SDP revealed finding was greater than "Green"
- Phase 2 SDP evaluation resulted in a "Red" finding
- Phase 3 analysis uniquely challenging and evolved over time
- Preliminary Phase 3 analysis assuming plate stainless steel behavior revealed "Green" risk significance
- Cladding was not plate stainless steel
- Corrosion mechanism and rate not well understood
- Because Phase 3 analysis contained significant uncertainties, the Phase 2 analysis was utilized to determine the significance. This is consistent with SDP procedures.
- Evaluation continues into cladding behavior and corrosion mechanisms 16
tN" REI,34 Current Status of NRC Oversight at Davis-Besse
- NRC approval needed for plant restart
- NRC Restart Checklist established-22 of 31 items completed
- Extensive NRC assessment of Safety-Significant Systems and Programs, and Management and Human Performance
- Approximately 70 public meetings conducted
- Davis-Besse will not be permitted to restart until the NRC is convinced it can be safely operated
- Oversight Panel will continue after restart 17
Conclusions
- ROP provides a predictable and consistent safety focused regulatory response to licensee performance
- Significance assessment of the Davis-Besse head degradation was performed in accordance with NRC policies and procedures
- NRC instituted special oversight processes at Davis-Besse. The Facility will not be permitted to restart unless NRC is convinced it can be operated safely 18