07/102008-Joseph M. Farley Regulatory Performance Meeting, Results of the NRC 95002 Supplemental InspectionML081960364 |
Person / Time |
---|
Site: |
Farley |
---|
Issue date: |
07/10/2008 |
---|
From: |
NRC/RGN-II |
---|
To: |
|
---|
References |
---|
Download: ML081960364 (16) |
|
|
---|
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 Regulatory Performance Meeting Results of the NRC 95002 Supplemental Inspection July 10, 2008
Meeting Purpose
- Public Exit Meeting for 95002 inspection (Inspection for One Degraded Cornerstone or any Three White Inputs in a Strategic Performance Area) conducted June 2 - 13
- Regulatory Performance Meeting to discuss corrective actions for the above issues.
Unit 1 Degraded Cornerstone Issues 3/4 Cooling Water MSPI (3Q 2007) 3/4 Parallel White Finding regarding Safety Related Breakers (3Q 2007)
Unit 2 Degraded Cornerstone Issues 3/4Parallel White Finding regarding Safety Related Breakers (3Q 2007) 3/4Yellow Finding for RHR suction valves (3Q 2007) 3/4White MSPI for RHR system (3Q 2007)
History - Unit 1 1st Qtr 2007 2nd Qtr 2007 3rd Qtr 2007 4th Qtr 2007 1st Qtr 2008 2nd Qtr 2008 Input 1 White Input 1 White Input 1 White Input 1 White Performance Performance Performance Performance Indicator CCW Indicator CCW Indicator CCW Indicator CCW Input 2 White Input 2 White Input 2 White Input 2 White Inspection Finding Inspection Finding Inspection Finding Inspection Finding Open Parallel Open Parallel Open Parallel Open Parallel White Breakers White Breakers White Breakers White Breakers Input 3 White Input 3 White Performance Performance Indicator AC Indicator AC Power Power Licensee Licensee Degraded Degraded Degraded Degraded Response Response Cornerstone Cornerstone Cornerstone Cornerstone (Column 1) (Column 1) (Column 3) (Column 3) (Column 3) (Column 3)
History - Farley Unit 2 1st Qtr 2007 2nd Qtr 2007 3rd Qtr 2007 4th Qtr 2007 1st Qtr 2008 2nd Qtr 2008 Input 1 White Input 1 White Input 1 White Input 1 White Input 1 White Performance Performance Performance Performance Performance Indicator RHR Indicator RHR Indicator RHR Indicator RHR Indicator RHR Input 2 White Input 2 White Input 2 White Input 2 White Inspection Inspection Inspection Inspection Finding Open Finding Open Finding Open Finding Open Parallel White Parallel White Parallel White Parallel White Breakers Breakers Breakers Breakers Input 3 Yellow Input 3 Yellow Input 3 Yellow Input 3 Yellow Inspection Inspection Inspection Inspection Finding RHR Finding RHR Finding RHR Finding RHR Sump Sump Sump Sump Licensee Regulatory Degraded Degraded Degraded Degraded Response Response Cornerstone Cornerstone Cornerstone Cornerstone (Column 1) (Column 2) (Column 3) (Column 3) (Column 3) (Column 3)
Licensee Actions 3/4Conducted Root Cause Evaluations for identified issues.
3/4Developed a Common Cause Report 3/4Developed Corrective Actions for the identified deficiencies.
IP 95002 Objectives
- To provide assurance that the root causes and contributing causes are understood for individual and collective (multiple white inputs) risk significant performance issues.
- To independently assess the extent of condition and the extent of cause for individual and collective (multiple white inputs) risk significant performance issues.
- To independently determine if safety culture components caused or significantly contributed to the individual or collective (multiple white inputs) risk significant performance issues.
- To provide assurance that licensee corrective actions to risk significant performance issues are sufficient to address the root causes and contributing causes, and to prevent recurrence.
Inspection Team
- Mike Ernstes, Branch Chief DRS
- Norm Merriweather, Senior Reactor Inspector
- Rob Berryman, Senior Reactor Inspector
- Mike Pribish, Watts Bar Resident Inspector
- Tonya Lighty, DRP Project Engineer (Trainee)
Inspection Scope 95002 Inspection U1 Cooling Water U1 Parallel finding U2 RHR Yellow Collective Requirements MSPI on S/R breakers finding & White Issues MSPI Problem Identification Root Cause Extent of Condition Extent of Cause Corrective Actions Independent assessment Safety Culture Section Lead Pribish / Hall Merriweather Berryman Hagar / Ernstes
Conclusions
- No new findings were identified by the inspection team.
- The NRC inspectors verified that the licensee used systematic methods to evaluate the issues and that they adequately determined causes for the events.
Conclusions
- The licensees evaluation of the problems with the Corrective Action Program accurately reflected the problem areas and they have proposed long term actions to improve performance.
- The licensees evaluations adequately considered Safety Culture aspects which contributed to the events. They have identified several actions to reinforce a strong safety culture.
Conclusions
- The NRC inspectors determined that the licensee has specified appropriate corrective actions for the root and contributing causes which led to the events.
Reactor Oversite Assessment Process
NRC Action Matrix Farley Unit 1 1 st Qtr 2007 2 nd Qtr 2007 3 rd Qtr 2007 4 th Qtr 2007 1st Qtr 2008 2 nd Qtr 2008 3rd Qtr 2008 4 th Qtr 2008 Input 1 White Input 1 White Input 1 White Input 1 White Input 1 White Input 1 White Performance Performance Performance Performance Performance Performance Indicator CCW Indicator CCW Indicator CCW Indicator CCW Indicator CCW Indicator CCW ADDRESSED IN 95002 Input 2 White Input 2 White Input 2 White Input 2 White Inspection Inspection Finding Inspection Finding Inspection Finding Open Open Parallel Open Parallel Finding Open Parallel White White Breakers White Breakers Parallel White Breakers Breakers ADDRESSED IN 95002 Input 3 White Input 3 White Input 3 White Input 3 White Performance Performance Performance Performance Indicator AC Indicator AC Indicator AC Indicator AC Power Power Power Power Licensee Lice nse e De grade d De grade d De grade d De grade d Re sponse Response Corne rstone Cornerstone Corne rstone Corne rstone (Column 1) (Column 1) (Column 3) (Column 3) (Column 3) (Column 3)
NRC Action Matrix Farley Unit 2 1 st Qtr 2007 2 nd Qtr 2007 3rd Qtr 2007 4th Qtr 2007 1st Qtr 2008 2 nd Qtr 2008 3rd Qtr 2008 4 th Qtr 2008 Input 1 White Input 1 White Input 1 White Input 1 White Input 1 White Input 1 White Input 1 White Performance Performance Performance Performance Performance Performance Performance Indicator RHR Indicator RHR Indicator RHR Indicator RHR Indicator RHR Indicator RHR Indicator RHR ADDRESSED IN 95002 Input 2 White Input 2 White Input 2 White Input 2 White Inspection Inspection Finding Inspection Finding Inspection Finding Finding Open Open Parallel Open Parallel Open Parallel Parallel White White Breakers White Breakers White Breakers Breakers ADDRESSED IN 95002 Input 3 Yellow Input 3 Yellow Input 3 Yellow Input 3 Yellow Inspection Inspection Finding Inspection Finding Inspection Finding Finding RHR RHR Sump RHR Sump RHR Sump Sump ADDRESSED IN 95002 Licensee Regulatory De grade d Degraded Degraded De grade d Re sponse Re sponse Corne rstone Cornerstone Cornerstone Cornerstone (Column 1) (Column 2) (Column 3) (Column 3) (Column 3) (Column 3)