5/31/06 Public Meeting with Entergy/Fitzpatrick, SlidesML061170003 |
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FitzPatrick |
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05/03/2006 |
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NRC Region 1 |
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Download: ML061170003 (22) |
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Category:Meeting Briefing Package/Handouts
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[Table view] Category:Slides and Viewgraphs
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FitzPatrick Annual Assessment Meeting ML0808400822008-03-0606 March 2008 ACRS Fitzparick Lr Presentation ML0808400482008-03-0606 March 2008 ACRS NRC, Fitzpatrick Lr SER ML0731902202007-11-0707 November 2007 Meeting Handout Fitzpatrick GNF2 Introduction at Entergy ML0725306142007-09-21021 September 2007 Public Meeting Summary on the Reactor Oversight Process ML0726905292007-09-0505 September 2007 ACRS License Renewal Subcommittee Presentation September 5, 2007 ML0726905372007-09-0505 September 2007 License Renewal Safety Evaluation Report Staff Presentation to the ACRS ML0722600232007-08-0101 August 2007 Slides for Public Meeting Regarding the Draft SEIS for FitzPatrick - Aug 01, 2007 ML0721405662007-06-21021 June 2007 License Renewal Exit Meeting Slides - June 21, 2007 ML0716603202007-06-15015 June 2007 2007 Entergy'S Slide Presentation, Journey to Excellence, from NRC Public Meeting to Discuss FitzPatrick Aam ML0716603032007-06-15015 June 2007 Aam Slides (NRC) ML0733409182007-05-31031 May 2007 05/31/2007 Presentation by J. 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[Table view] |
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James A. FitzPatrick Annual Assessment Meeting Reactor Oversight Program - CY 2005 Nuclear Regulatory Commission - Region 1 Fulton, New York May 31, 2006
Purpose of Todays Meeting A public forum for discussion of Entergys operational performance at the James A.
FitzPatrick Nuclear Power Plant The NRC will present its assessment of Entergys performance as described in the annual assessment letter Entergy will be given the opportunity to respond and describe new or existing programs to maintain or improve their performance.
2
Agenda Introduction Review of Reactor Oversight Process National Summary of Plant Performance Discussion of Plant Performance Results Entergy Response and Remarks NRC Closing Remarks Break NRC available to address public questions
Region I Organization NRC Region I Samuel J. Collins, Regional Administrator Marc L. Dapas, Deputy Regional Administrator Director Division of Reactor Projects Director Division of Reactor Safety Brian E. Holian, Director A. Randolph Blough, Director David C. Lew, Deputy Director Marsha K. Gamberoni, Deputy Director Projects Branch 2 Regional Specialist Branches Eugene W. Cobey, Chief J.A. FitzPatrick Project Engineers Resident Inspectors Donald E. Jackson Gordon K. Hunegs Christopher M. Long Douglas A. Dempsey Stacy M. Smith Odunayo A. Ayegbusi
NRC Representatives Eugene Cobey, Chief, Projects Branch 2, Region I
- (610) 337-5171 Gordon Hunegs, Senior Resident Inspector
- (315) 342-4907 Douglas Dempsey, Resident Inspector
- (315) 342-4907 John Boska, Project Manager, NRR
NRC Performance Goals Safety: Ensure protection of the public health and safety and the environment Security: Ensure the secure use and management of radioactive materials Openness: Ensure openness in our regulatory process Effectiveness: Ensure that NRC actions are effective, efficient, realistic, and timely Management: Ensure excellence in agency management to carry out the NRCs strategic objectives
Reactor Oversight Process Strategic Strategic PerformanceAreas Performance Areas Safety Safety Cornerstones Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold ActionMatrix Action Matrix Regulatory Response
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone L cen si R egto la u ry eD ed d
ra g ltiu M ple/R .U c lep a
n b ta c
R espn o eR esp n
o e e to rn o
C es n a sto g
eD rn o
C ed n r Perfo c n
a rm Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
Examples of Baseline Inspections 1 Equipment Alignment ~80 hrs/yr Triennial Fire Protection ~200 hrs/3 yrs Operator Response ~125 hrs/yr Emergency Preparedness ~80 hrs/yr Rad Release Controls ~110 hrs/2 yrs Engineering Design ~680 hrs/2 yrs Corrective Action Program ~250 hrs/2 yrs Corrective Action Case Reviews ~60 hrs/yr 1Baseline Inspections For A Single Unit Require Approximately ~5000
~5000 Hours Per Year
Significance Threshold Inspection Findings Green: Very low safety significance White: Low to moderate safety significance Yellow: Substantial safety significance Red: High safety significance Performance Indicators Green: Baseline Inspection White: Increased NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight
National Summary Status At End Of 2005 2004 Licensee Response 84 78 Regulatory Response 12 21 Degraded Cornerstone 4 0 Multiple/Repetitive Degraded Cornerstone 3 3 Unacceptable 0 0 Total 103 102*
- Davis-Davis-Besse was in Shutdown with Enhanced Oversight in 2004
National Summary Total Inspection Findings Total For Calendar Year 2005 2004 Green 849 778 White 10 11 Yellow 1 0 Red 0 0 Performance Indicator Results Status At End Of 2005 2004 Green 1850 1834 White 4 6 Yellow 0 0 Red 0 0
Assessment Results January 1, 2005 - December 31, 2005 Operated safely throughout the Assessment Period Licensee Response column of the Action Matrix for all of 2005 NRC will conduct baseline inspections during the remainder of the cycle
Assessment Bases January 1, 2005 - December 31, 2005 All Site Performance Indicators Green All Inspection Findings Green
- 8 findings of very low safety significance (Green)
James A. FitzPatrick Indicators Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html
James A. FitzPatrick Findings Available On The Web At: http://www.nrc.gov/reactors/operating/oversight.html
NRC Inspection Activities January 1, 2005 - December 31, 2005 6456 hours0.0747 days <br />1.793 hours <br />0.0107 weeks <br />0.00246 months <br /> of inspection related activities Baseline inspections and performance indicator reviews completed 2 resident inspectors assigned to the site conducting the Baseline Inspection Program 16 regional specialist inspector visits 3 team inspections conducted
J.A. FitzPatrick Team Inspection Activities A Special Inspection was conducted to inspect cracking in the primary containment torus shell A Triennial Fire Inspection was conducted An Emergency Plan Exercise Inspection was conducted
Entergy Response and Remarks Pete Dietrich J.A. FitzPatrick- Site Vice President Entergy Nuclear Northeast
Summary Of NRC Assessment Entergy operated James A.
FitzPatrick in a manner that preserved public health and safety All cornerstone objectives were met, the plant is in the Licensee Response Column of the NRCs Action Matrix NRC will conduct baseline inspections at JAF during the 2006 assessment period
Contacting the NRC To report an emergency (301) 816-5100 (call collect)
To report a safety concern (800) 695-7403 or Allegation@nrc.gov General information or questions www.nrc.gov Select What We Do for Public Affairs
Reference Sources Reactor Oversight Process http://www.nrc.gov/NRR/OVERSIGHT/ASSES S/index.html Public Electronic Reading Room http://www.nrc.gov/reading-rm.html Public Document Room 1-800-397-4209 (Toll Free)