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Category:Meeting Briefing Package/Handouts
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 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 ML20217L4312020-08-13013 August 2020 Edwin I Hatch, Units 1 and 2; and Vogtle Electric Plant, Units 1, 2, 3, and 4 - Meeting Slides a License Amendment Request for the Emergency Plan (EPID Nos L-2020-LLA-0150 and L-2020-LLA-051 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 ML18311A1822018-11-0707 November 2018 November 13, 2018, Joseph M. Farley Nuclear Power Plant, Public Meeting Slides Regarding Spent Fuel Pool Criticality Analyses and Measurement Uncertainty Recovery (Mur) Pre-Application 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. ML18234A4712018-08-23023 August 2018 NRC-Pre Submittal Meeting TSTF-51 for Hatch and TSTF-51 and -471 for Farley - August 23, 2018 ML18136A8902018-05-16016 May 2018 May 21, 2018 Slides for Public Teleconference Regarding Changes to Hatch, Farley, and Vogtle TS 5.2.2.g ML18065A0202018-03-12012 March 2018 March 12, 2018, Public Meeting Presentation ML18065A0222018-03-0606 March 2018 March 12, 2018, Public Meeting - Draft 4b Application ML18065A0252018-03-0606 March 2018 Joseph M Farley March 12, 2018, Public Meeting - Draft 4b Application Enclosures NL-16-0388, September 22, 2016, Public Meeting Presentation Slides2016-09-22022 September 2016 September 22, 2016, Public Meeting Presentation Slides ML16260A1162016-09-22022 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. ML14135A1732014-02-26026 February 2014 May 16, 2014, J.M. Farley Category 1 Meeting Handout, Duration for Completion of the Flood Hazard Re-evaluation. ML13079A1502013-03-20020 March 2013 Summary of Public Meeting with Joseph M. Farley 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) 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) 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) 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) 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 ML0814900902008-05-22022 May 2008 List of Attendees - Joseph M. Farley Nuclear Plant, Annual Public Assessment Meeting 2024-09-23
[Table view] 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
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Joseph M. Farley Nuclear Plant Purpose of Todays Meeting Annual Assessment Meeting Reactor Oversight Program - CY 2008 A public forum for discussion of the licensee licensees performance NRC will address the licensee performance issues identified in the annual assessment letter Licensee will be given the opportunity to respond to the information in the letter and Nuclear Regulatory Commission - Region II inform the NRC of new or existing programs to Dothan, AL maintain or improve their performance March 19, 2009 Agenda Region II Organization Luis Reyes Regional Administrator
Victor McCree Introduction Deputy Regional Administrator Review of Reactor Oversight Process National Summary of Plant Performance Division of Reactor Projects Len Wert, Director Division of Reactor Safety Kriss Kennedy, Director Richard Croteau, Deputy Director Joel Munday, Acting Deputy Director Discussion of Plant Performance Results Harold Christensen, Deputy Director Licensee Response and Remarks NRC Closing Remarks Projects Branch 2 Scott Shaeffer, Chief (404)562-4521 Regional Specialist Inspectors Break NRC available to address public questions Resident Inspectors (RI)
Project Engineers (PE)
Eddy Crowe, Senior RI Curt Rapp, Senior PE Shane Sandal, RI Tonya Lighty, PE RI Office: (334)899-3386
Our Mission Some Nuclear Facts To license and More than 100 nuclear regulate the nation nations power plants supply about 20 percent of the civilian use of electricity in the U.S.
byproduct, source, and special nuclear Nuclear materials are used materials to ensure in medicine for diagnosis and cancer treatment.
adequate protection of public health and Nuclear materials are safety, promote the widely used in industry, common defense and such as in density gauges, security, and protect flow measurement devices, radiography devices, and the environment. irradiators.
The NRC Regulates What We Dont Do Nuclear reactors - commercial power reactors, Regulate nuclear weapons, military research and test reactors, new reactor designs reactors, or space vehicle reactors Nuclear materials - nuclear reactor fuel, radioactive materials for medical, industrial, and academic use Own or operate nuclear power plants Nuclear waste - transportation, storage and disposal of nuclear material and waste, Regulate some radioactive materials, decommissioning of nuclear facilities such as X-X-rays and naturally Nuclear security - physical security of nuclear occurring radon facilities and materials from sabotage or attacks
How We Regulate Assurance of Plant Safety Establish rules and regulations Require defense-defense-in-in-depth depth Issue licenses Provide oversight through inspection, Require long-long-term maintenance of enforcement, and evaluation of equipment operational experience Conduct research to provide support Require continual training of for regulatory decisions operators Respond to events and emergencies Verify compliance with regulations What We Do - Nuclear Waste What We Do - Nuclear Security The NRC regulates: NRC Requires:
- Well-Well-armed and well-well-
- Storage of spent trained security forces, reactor fuel in fuel
- Surveillance and pools or dry storage perimeter patrols, casks, and
- State-State-of-of-the-the-art site access equipment and controls,
- Physical barriers and fuel storage site--
site-- detection zones, and Yucca Mountain.
- Intrusion detection systems and alarm stations.
Reactor Oversight Process NRC Performance Goals Strategic Safety: Ensure adequate protection of Performance Areas Safety public health and safety and the Cornerstones environment. Baseline Inspection Performance Indicator Results Results Security: Ensure adequate Significance Threshold Significance Significance Threshold Threshold protection in the secure use and management of radioactive Action Matrix materials.
Regulatory Response Examples of Baseline Inspections Significance Threshold Inspection Findings & Performance Indicators Equipment Alignment ~80 hrs/yr Green: Very Low safety issue Triennial Fire Protection ~250 hrs triennially White: Low to moderate safety issue Yellow: Substantial safety issue Operator Response ~125 hrs/yr Red: High safety issue Emergency Preparedness ~80 hrs/yr Rad Release Controls ~110 hrs biennially NRC Response:
Worker Radiation Protection ~95 hrs/yr Green: Only Baseline Inspection Corrective Action Program ~250 hrs biennially White: May increase NRC oversight Corrective Action Case Reviews ~60 hrs/yr Yellow: Requires more NRC oversight Red: Requires more NRC oversight
Action Matrix Concept National Summary of Plant Performance Multiple/Rep Status at End of CY 2008 Licensee Regulatory Degraded Unacceptable Degraded Response Response Cornerstone Cornerstone Performance Licensee Response 86 Regulatory Response 14 Degraded Cornerstone 3 Increasing Safety Significance Multiple/Repetitive Degraded Cornerstone 1 Unacceptable 0 Increasing NRC Inspection Efforts Total 104 Increasing NRC/Licensee Management Involvement Increasing Regulatory Actions National Summary Inspection Activities 7400 hours0.0856 days <br />2.056 hours <br />0.0122 weeks <br />0.00282 months <br /> of inspection-related activities Performance Indicator Results (end of CY 2008) In-service Inspection Radiation Protection
- White 6 Biennial Problem Identification & Resolution (PI&R) Inspection
- Yellow 0 Biennial Licensed Operator Requalification Inspection Security
Total Inspection Findings (CY 2008) 95002 Supplemental Inspection for Breakers & Residual Heat Removal (RHR) valves
- Green 776 B.5.B Inspection (TI 171)
Heat Sink Performance Inspection
EDG TS Surveillance Requirements (Endurance/Margin) Inspection (TI 176)
2008 Assessment Results - Unit 1 Unit 1 Assessment Results (contd) nd rd th st nd rd th 2 Qtr 2007 3 Qtr 2007 4 Qtr 2007 1 Qtr 2008 2 Qtr 2008 3 Qtr 2008 4 Qtr 2008 Input 1 White Performance Input 1 White Performance Input 1 White Performance Input 1 White Performance 1st and 2nd quarters 2008 within the Degraded Indicator CCW Indicator CCW Indicator CCW ADDRESSED IN 95002 Indicator CCW Cornerstone column 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 Overall, Regulatory issues at Farley Unit 1 have been associated with:
White Breakers White Breakers White Breakers White Breakers ADDRESSED IN 95002 Repetitive 4160 volt breaker failures 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 ADDRESSED IN 95001 Run failures on the 1B EDG Input 4 White Input 4 White All Action Matrix inputs for these issues have Finding EDG Finding EDG Exhaust Exhaust ADDRESSED IN 95001 Licensee Degraded Degraded Degraded Degraded Regulatory Regulatory been successfully reviewed by the NRC via Supplemental 95002 and 95001 Inspections Response Cornerstone Cornerstone Cornerstone Cornerstone Response Response (Column 1) (Column 3) (Column 3) (Column 3) (Column 3) (Column 2) (Column 2)
Unit 1 Assessment Results (contd) Unit 1 Assessment Results (contd)
For the breaker issues, a Confirmatory Action Letter (CAL) NRC conducted Supplemental Inspection was issued November 2007 Procedure 95002 in June 2008 which CAL closed (January 25, 2008) based on inspection and encompassed::
review of licensee new multipoint breaker inspection
- multiple safety-safety-related circuit breaker failures process
- White MSPI MSPIs PI associated with these issues Marked improvement in breaker performance over the
- White PI parallel finding 2008 assessment period
- Quality of root cause evaluations remained a The licensee completed modifications to their component focus area during inspection cooling water (CCW) system during 2nd quarter 2008 which Inspection indicated improvement in root reduced their risk profile for the CCW system cause evaluation process and noted The modification resulted in the licensee returning a key improvements in breaker reliability CCW Mitigating System Performance Index (MSPI) performance indictor (PI) to Green status
Unit 1 Assessment Results (contd) 2008 Assessment Results - Unit 2 NRC conducted 95001 supplemental inspection 3rd 1st Qtr 2007 2nd Qtr 2007 3rd Qtr 2007 4th Qtr 2007 1st Qtr 2008 2nd Qtr 2008 3rd Qtr 2008 4th Qtr 2008 quarter 2008 which encompassed: Input 1 White Input 1 White Input 1 White Input 1 White
- White MSPI Emergency AC Power system PI for 1B EDG Performance Performance Performance Performance failures Indicator RHR Indicator RHR Indicator RHR ADDRESSED IN 95002 Indicator RHR
- White Finding for inadequate work instructions to install the Input 2 White Input 2 White Input 2 White Input 2 White 1B EDG exhaust header Inspection Finding Inspection Finding Inspection Finding Inspection Finding Open Parallel Open Parallel Open Parallel Open Parallel NRC conducted an additional Problem PI&R White Breakers White Breakers White Breakers White Breakers inspection (Dec. 2008) ADDRESSED IN 95002
- Noted improved rigor and scope of root cause evaluations Input 3 Yellow Input 3 Yellow Input 3 Yellow Input 3 Yellow Inspection Finding Inspection Finding Inspection Finding Inspection Finding
- Incorporated improvements in the Corrective Action Program RHR Sump RHR Sump RHR Sump RHR Sump (CAP) ADDRESSED IN 95002 At end of assessment period, approximately 348 of 438 95002 Action Items were complete (80%) Licensee
Response
Regulatory
Response
Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Degraded Cornerstone Licensee
Response
Licensee
Response
The licensee entered the Regulatory Response (Column 1) (Column 2) (Column 3) (Column 3) (Column 3) (Column 3) (Column 1) (Column 1) column 3rd quarter 2008 based on:
- White finding for inadequate work instructions (Not counted in the NRC NRCs Action Matrix to prevent double counting)
Unit 2 Assessment Results (contd) Unit 2 Assessment Results (contd) 1st and 2nd quarters 2008 within the The licensee entered the Licensee Response Degraded Cornerstone column:
column 3rd quarter 2008 Yellow Inspection finding in the Mitigating Systems Cornerstone (RHR valve failures )
White Performance indicator Parallel Finding White MSPI RHR system PI NRC conducted Supplemental Inspection Procedure 95002 in June 2008 which encompassed all of the issues noted above
2008 Assessment Summary Overall Assessment Impact Overall, Farley Farleys performance has improved over the assessment period Southern Nuclear operated Farley in a manner that preserved public health and Both units improved their standing on the NRC NRCs Action Matrix safety with moderate degradation in safety All NRC Supplemental inspections conducted during 2008 were successfully completed with no new significant regulatory issues being performance identified.
All cornerstone objectives were met Specific corrective actions associated with breakers, EDGs and RHR sump valves have been effective For the remainder of 2009: Programmatic corrective actions in the area of root cause evaluations evaluations NRC plans baseline inspections and corrective action program improvements have been implemented.
implemented.
Although all effectiveness reviews have not been completed, the NRC will be looking for sustained performance in the areas noted above.
above.
Contacting the NRC Reference Sources Report an emergency Reactor Oversight Process (301) 816-5100 (call collect) http://www.nrc.gov/NRR/OVERSIGHT/ASSESS/index.html Report a safety concern:
(800) 695-7403 Public Electronic Reading Room http://www.nrc.gov/reading-rm.html Allegation@nrc.gov General information or questions Public Document Room www.nrc.gov 1-800-397-4209 (Toll Free)
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