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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
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- Degradation of CRDM Nozzle and Other Vessel Closure 4/00 llead Penetrations" 12RFO video 1/93 9/RQ B& W issues "Safetv and visual Eialuation for 4/96 intspection of NRC audit of DI B& W Design Reactor IORFO visual 4/98 head boric acid corrosion inspection II RFO visual control program Vesselflead CRDM Nozzle of head inspection of per GL 89-05 I Cracking" head T
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"* Visual inspections since 1988
"* Commitment to start refueling outage early
"* Compensatory measures until start of refueling outage
"* Most comprehensive inspection of reactor head in industry to date
- Hairline axial cracks found in 5 nozzles
"* Formation of FENOC Investigation Team
" Complete weld repairs on 3 nozzles 11'!
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"* Special team formed to investigate root cause includes Framatome, EPRI, INPO, Oconee, MRP and other industry, experts
"* Team to create, repair plan
"* Safety Assessment submitted to NRC April 8 Plant operated safely during this condition
"* Repair plan to be submitted during April
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"* Probable Cause Through wall cracking of CRDM nozzle, resulting in boric acid corrosion of Reactor Pressure Vessel (RPV) head low-alloy steel.
"* Contributing Causes Failure to clean boric acid from RPV head Design of RPV service structure limited access for cleaning and inspections {)
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Deferral of modification to install portals to service structure to allow cleanings and inspections ,
- Deferral of head cleaning and inspecti,
FENOC Root Cause Summary (continued)
- Causal Factors Acceptance of boric acid accumulation on RPV head from CRDM flange leakage Failure to recognize symptoms of leakage collected from Containment Building monitors Harsh environmental conditions
-Boric acid corrosion control program targeted CRDM flange leakage