Annual Assessment Meeting, Reactor Oversight Program - Cy 2003ML041050628 |
Person / Time |
---|
Site: |
Farley |
---|
Issue date: |
04/13/2004 |
---|
From: |
NRC/RGN-II |
---|
To: |
|
---|
References |
---|
Download: ML041050628 (17) |
|
|
---|
Category:Slides and Viewgraphs
MONTHYEARML24260A0792024-09-23023 September 2024 9/23/2024 Pre-Submittal Meeting - Joseph M. Farley Nuclear Plant, Units 1 and 2, LAR to Change UFSAR for Exception to RG 1.183, Revision 0, Table 3 - Footnote 11 (EPID L-2024-LRM-0108) - Meeting Slides ML24192A2262024-07-11011 July 2024 Mtg to Exchange Technical Information Regarding Farley, Units 1 & 2, Proposed License Amendment Request to Increase TS 3.6.5 Containment Temperature Limit Completion Using Risk-Informed Process for Evaluation (EPID L-2024-LRM-0086) - Slides ML24190A1082024-07-0808 July 2024 NRC Slides-07/11/2024 Mtg to Exchange Technical Information Regarding Joseph M. Farley Nuclear Plant, Units 1 & 2, Proposed License Amendment Request to Increase TS 3.6.5 Containment Temperature Limit Completion Using Risk-Informed Process ML24134A1062024-05-13013 May 2024 2023 Annual Assessment Meeting Presentation Slides ML24088A1662024-04-0303 April 2024 SNC Slides - Pre-Submittal Meeting on April 3, 2024 - Farley LAR Changing TS 3.6.5 Containment Air Temperature Using RIPE ML23361A0812024-01-0808 January 2024 SNC Slides - Pre-Submittal Public Meeting on January 8, 2024 Related to Fleet QATR ML23139A2462023-05-19019 May 2023 Annual Assessment Public Meeting Slides (May 23, 2023) ML22080A0192022-03-18018 March 2022 Annual Assessment Meeting Presentation ML21306A0242021-11-30030 November 2021 SNC Pre-Submittal Meeting for LAR to Relocate Augmented Piping Inspection Program Details from TSs to a Licensee Controlled Document for Farley Nuclear Plant, Units 1 & 2; and Vogtle Electric Generating Plant, Units 1 & 2 (EPID L-2021-LRM-0 ML21280A0012021-10-31031 October 2021 Pre-Submittal Meeting Presentation from SNC to Discuss a Future LAR Regarding Change TS to Increase Containment Peak Pressure to Address Several NSALs ML21173A0632021-06-24024 June 2021 Pre-Application SNC Presentation Slides - Removal of Encapsulations from Recirculation Suction Valves ML21083A2872021-03-24024 March 2021 Pre-Submittal Meeting - Quality Assurance Topical Report Revision to Allow Application of Remote Assessment Techniques During Exigent Conditions ML21057A0182021-02-26026 February 2021 Pre-Submittal Meeting Revise Technical Specification 3.2.1 Heat Flux Hot Channel Factor (Fq(Z)) (EPID L-2021-LRM-0023) (Slides) ML21036A1172021-02-0505 February 2021 SNC Slides - Pre-Submittal Meeting on February 16, 2021 - Beacon LAR ML20318A1032020-11-12012 November 2020 SNC ERO Staffing LAR RAI Responses ML20101K6582020-04-10010 April 2020 Annual Assessment ML20022A0262020-01-22022 January 2020 NEI Presentation Status Update for Ropte Short Term Action Plan: Removed Planned Unavailability for Mitigating Systems Performance Index ML19149A4222019-05-29029 May 2019 Summary of Public Meeting Concerning Annual Assessment of the Farley Nuclear Plant, Units 1 and 2, Docket Nos. 05000348 and 05000361 ML19057A4762019-03-0707 March 2019 Presentation Slides Related to Pre-Application Public Meeting Regarding to Technical Specification 3.3.1 and 3.3.2 (L-2019-LRM-0010) ML19025A0242019-01-25025 January 2019 SNC License Amendment Request for Proposed Changes to Emergency Response Organization Staffing and Augmentation NL-18-1412, Presentation Material for the Measurement Uncertainty Recovery and Spent Fuel Pool Criticality Analysis Pre-Submittal Meeting2018-11-0808 November 2018 Presentation Material for the Measurement Uncertainty Recovery and Spent Fuel Pool Criticality Analysis Pre-Submittal Meeting ML18290B0942018-10-16016 October 2018 October 16, 2018, Public Meeting Presentation Slides Related to July 27, 2018, License Amendment Request to Implement NEI 06-09, Revision 0-A, Risk-Informed Technical Specifications Initiative 4b. ML18065A0202018-03-12012 March 2018 March 12, 2018, Public Meeting Presentation ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application ML16260A1162016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides NL-16-0388, September 22, 2016, Public Meeting Presentation Slides2016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides ML15106A2042015-04-22022 April 2015 April 22, 2015, Meeting with Southern Nuclear Company, Slide Presentation ML14115A4052014-04-25025 April 2014 2013 End of Cycle Farley Public Meeting Summary Memo ML14108A0052014-04-23023 April 2014 April 23, 2014, Public Meeting Presentation Slides, Southern Nuclear Company, SNC Degraded Grid Design Criteria. ML14120A2252014-04-23023 April 2014 April 23, 2014, Category 1 Public Meeting, J.M. Farley Presentation Slides, Residual Heat Removal Autoclosure Interlock Deletion. ML14108A0042014-04-18018 April 2014 April 23, 2014, Category 1 Public Meeting, J.M. Farley Presentation Slides, Residual Heat Removal Autoclosure Interlock Deletion ML13079A1502013-03-20020 March 2013 Summary of Public Meeting with Joseph M. Farley ML13078A2462013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 2 (3/19) ML13078A2552013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 10 ML13078A2542013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 9 ML13078A2532013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 8 ML13078A2522013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 6 ML13078A2512013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 5 (3/19) ML13078A2502013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 4 ML13078A2482013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 3 (3/19) ML13078A2452013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 1 (3/19) ML13078A2472013-03-19019 March 2013 03/21/2013 Licensee Meeting Slides Re Joseph M. Farley Nuclear Plant NFPA 805 Fire Modeling LAR Submittal - Session 2 (3/20) IR 05000348/20110122011-07-15015 July 2011 Summary of Public Meeting with Joseph M. Farley Nuclear Plant, to Discuss Safety Significance of Preliminary White Finding Associated with One Apparent Violation Documented in NRC Inspection Report 05000348-11-012 and 05000364-11-012 ML1016705482010-06-0808 June 2010 Farley Nuclear Plant, NRC Screening Criteria Response ML1009805922010-04-0808 April 2010 Summary of Public Meeting to Discuss Nrc'S Reactor Oversight Process and Nrc'S Annual Assessment of Plant Safety Performance for Period of January 1, 2009 - December 31, 2009 - Joseph M. Farley Nuclear Plant ML0909210352009-03-19019 March 2009 Annual Assessment Meeting Presentation ML0819603642008-07-10010 July 2008 07/102008-Joseph M. Farley Regulatory Performance Meeting, Results of the NRC 95002 Supplemental Inspection ML0814901062008-05-22022 May 2008 Slides - Joseph M. Farley Nuclear Plant, Annual Public Assessment Meeting, ML0729806702007-10-24024 October 2007 Meeting Presentation on GEH Chemical Effects Testing Update 2024-09-23
[Table view] |
Text
Joseph M. Farley Nuclear Plant Annual Assessment Meeting Reactor Oversight Program - CY 2003 Nuclear Regulatory Commission - Region II Dothan, AL April 13, 2004
Purpose of Todays Meeting
! A public forum for discussion of Farleys performance
! NRC will address any performance issues identified in the annual assessment letter
! Licensee response to the information in the letter
Agenda
! Introduction
! Review of Reactor Oversight Process
! National Summary of Plant Performance
! Discussion of Plant Performance Results
! Licensee Response and Remarks
! NRC Closing Remarks
! Break
! NRC available to address public questions
Region II Organization Luis Reyes Regional Administrator Loren Plisco Deputy Regional Administrator Victor McCree Charles Casto Director Division of Reactor Projects Director Division of Reactor Safety Lenoard Wert Harold Christensen Deputy Director Deputy Director Brian Bonser Branch Chief Farley Resident Inspectors Project Engineers Charles Patterson - SRI Curt Rapp Rodney Fanner - RI James Baptist
NRC Performance Goals
! NRC PRIMARY GOAL - Maintain safety and protect the environment
! Enhance public confidence
! Improve effectiveness, efficiency, and realism of processes and decision making
! Reduce unnecessary regulatory burden
Reactor Oversight Process Strategic Performance Areas Safety Cornerstones Baseline Inspection Performance Indicator Results Results Significance Significance Threshold Threshold Action Matrix Regulatory Response
Examples of Baseline Inspections
! Equipment Alignment ~92 hrs/yr
! Triennial Fire Protection ~200 hrs every 3 yrs
! Operator Response ~125 hrs/yr
! Emergency Preparedness ~80 hrs/yr
! Rad Release Controls ~100 hrs every 2 yrs
! Worker Radiation Protection ~100 hrs/yr
! Corrective Action Program ~200 hrs every 2 yrs
! Corrective Action Case Reviews ~60 hrs/yr
Performance Thresholds Safety Significance Green: Very Low safety issue White: Low to Moderate safety issue Yellow: Substantial safety issue Red: High safety issue NRC Inspection Efforts Green: Only Baseline Inspection White: May increase NRC oversight Yellow: Requires more NRC oversight Red: Requires more NRC oversight
National Summary
! Performance Indicator Results (at end of CY 2003)
< Green 1825
< White 15
< Yellow 0
< Red 0
! Total Inspection Findings (at the end of CY 2003)
< Green 748
< White 19
< Yellow 2
< Red 4
Action Matrix Concept Licensee Regulatory Degraded Multiple/Rep. Unacceptable Response Response Cornerstone Degraded Performance Cornerstone Increasing Safety Significance Increasing NRC Inspection Efforts Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions
National Summary of Plant Performance Status at End of CY 2003 Licensee Response 75 Regulatory Response 22 Degraded Cornerstone 2 Multiple/Repetitive Degraded Cornerstone 3 Unacceptable 0 Total Units 102*
- Davis-Besse - Shutdown Operating Reactor with Performance Problems
Farley 2003 Inspection Activities
! 3155 hours0.0365 days <br />0.876 hours <br />0.00522 weeks <br />0.0012 months <br /> of inspection related activities
< Reactor Vessel Upper Head
< Reactor Operator Licensing Examinations
< Biennial Problem Identification and Resolution
< Emergency Preparedness
< Security
< Radiation Protection
< Engineering
Farley 2003 Assessment Results
! Plant performance was within the Licensee Response Column of the NRCs Action Matrix
! All inspection findings were classified as very low safety significance (Green)
! All Performance Indicators were Green
Farley Annual Assessment Summary
! Southern Nuclear Operating Company operated the Farley Nuclear Plant in a manner that preserved public health and safety
! All cornerstone objectives were met.
! NRC plans baseline inspections at Farley for the 2004 assessment period
Farley 2004 Inspection Activities
! Reactor Vessel Upper and Lower Head
! Spent Fuel Material Control and Accounting
! Containment Sump Blockage
! Emergency Exercise
! License Renewal
! Independent Spent Fuel Storage Installation Construction
! Reactor Head Replacement
Contacting the NRC
! Report an emergency
< (301) 816-5100 (call collect)
! Report a safety concern:
< (800) 695-7403
< 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/ASSESS/index.html
! Public Electronic Reading Room
< http://www.nrc.gov/reading-rm.html
! Public Document Room
< 1-800-397-4209 (Toll Free)