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Category:Slides and Viewgraphs
MONTHYEARML24192A2262024-07-11011 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 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 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. 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 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) 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) 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) 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) 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 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) 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 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 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 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 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 ML0732413392007-09-19019 September 2007 Email from D. Decker, NRR to K. Cotton, NRR Et Al. Final Copy Farley Aitnrc Slides.Ppt ML0732413252007-09-18018 September 2007 Email from K. Cotton, NRR to S. Shaeffer, Rii on Final Farley Aitnrc Slides.Ppt 2024-07-08
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Text
Joseph M. Farley Nuclear Plant Appendix R Status and Elimination of Reliance on Kaowool Fire Barriers for the Service Water Intake Structure (SWIS)
Mike Stinson General Manager Farley Nuclear Support July 25, 2003 SOUTHERN COMPANY Energy to Serve Your World Enclosure 2
Agenda
- 1. Introduction & Purpose
- 2. Appendix R Overview
- Current exemption for the SWIS
- 3. Basis for the New SWIS Exemption
- Deterministic and risk-informed performance-based approaches
- Application of risk-informed performance-based methodology
- Change evaluation process
- 4. Summary 2
Introduction & Purpose
- Discuss status of Farley's Kaowool issues
- Discuss SNC's application of risk-informed performance-based methodology for the Farley SWIS Appendix R 10 CFR 50.12 exemption
- Receive feedback from the NRC on the proposed approach 3
Appendix R Overview Doug McKinney Farley Licensing Manager 4
Background Information
- Kaowool related Appendix R exemption requests for Plant Farley were approved by the NRC during 1985 and 1986
- The 1986 exemption for the SWIS relied on Kaowool for protection of several cables
- On August 26, 1999, the NRC informed Farley that qualification tests did not demonstrate that Kaowool met regulatory requirements 5
Background Information (cont.)
- SNC re-evaluated the Appendix R program
- SNC planned modifications to eliminate dependence on Kaowool
-5 modifications completed 27 modifications scheduled to be completed by the end of the spring 2006 outage
- SNC will change licensing documents 6
Background Information (cont.)
For the SWIS, three options were identified
- 1. Comply with the Current Licensing Basis
- 2. Install alternate seal injection pump and reroute cables
- 3. Determine whether a risk-informed performance-based evaluation would justify not relying on Kaowool 7
Background Information (cont.)
- A risk-informed performance-based pilot study was completed
- SNC discussed proposed risk-informed performance-based exemption approach in previous meeting with the NRC
- A confirming risk-informed performance-based analysis was completed
- SNC plans modifications and new SWIS exemption 8
SWIS Plan View- Existing t
N 72A Train B Racew ays Train A >
Racew ays Legend Strainer Pit Zone 72A - SW Purnp Deck and Strainer Pit Zone 72B - Sw itchgear Room - Train B Zone 72C - 5kV Disconnect Sw itch - Train B Zone 72D - 5kV Disconnect Sw itch - Train A Zone 72E- Sw itchgear Room - Train A Zone 73 - Battery Room - Train B Zone 74 - Battery Room - Train A Unit 2 SW Pumps Unit 1 SW Pumps Train A B B AB A 0
A A A AB 00 B B Train B 72B I 72C 72D I ~~72E Train B 7 Train A c )
9
Current Exemption for the SWIS Five of eleven specific configurations rely in part on Kaowool for exemptions from Section III.G.2 requirements:
- U1 Train A cables for Strainer Pit MOVs U2 Train A cables for Strainer Pit MOVs
- U2 Train A raceways for certain lube and cooling water pump cables
- Train A / Train B raceways in northeast corner 10
Basis for the New SWIS Exemption Doug McKinney Farley Licensing Manager 11
Deterministic Approach
- Deterministic reanalysis, confirming no spurious operation
- Creation of new fire areas
- One SW pump for fire scenario 12
Risk-Informed Performance-Based Approach
- Evaluated power cables to SW pumps
- Evaluated cable raceways in NE corner 13
Application of Risk-Informed Performance-Based Methodology
- Draft Section 8.3 of NEI Implementation Guide for NFPA 805 14
Change Evaluation Process The Change Evaluation Process consisted of four major parts:
x
- NflmItIon usmeut Yee E mt~
16
Preliminary Assessment - Initial Fire Modeling ~~~~~~~~..
Fire Scenario fr N 72A IE Train B Racew ays Train A Racew ays Legend Strainer Pit Zone 72A - SW Purrp Deck and Strainer Pit Zone 72B - Sw itchgear Room - Train B Zone 72C - 5kV Disconnect Sw itch - Train B Zone 72D - 5kV Disconnect Sw itch - Train A Zone 72E - Sw itchgear Room - Train A Fire Scenario Fire Scenariol Zone 73 - Battery Room - Train B Zone 74 - Battery Room - Train A Unit 2 SW Pumps Unit I SW Pumps Train A Train B B B AB A A A A AB B B I 72C 72D 72B 72E Train B 7 7 Train A 17
Preliminary Assessment - Initial Risk Assessment Determined that combined analysis was required for SW pumps 18
Combined Analysis
- One SW pump remains operable
- CDF determined for one SW pump
- RG 1.174 criteria met for SWIS
- Defense-In-Depth Elimination of dependence on Kaowool meets NFPA 805 criteria to
- Prevent fires from starting
- Detect fires quickly and suppressing those that occur
- Provide protection for systems and structures so that safe shutdown can be achieved
- NRC criteria met 19
Summary
- Continue modifications - complete in 2006
- SWIS Current licensing bases changes Exemption based on risk-informed performance-based methodology
- New exemption will be submitted to NRC