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| {{#Wiki_filter:Joseph M. Farley Nuclear Plant Risk-Informed Technical Specifications Risk-Informed Initiative 4bPre-submittal MeetingMarch 12, 2018 OverviewFarley 4b License Amendment Request (LAR) | | {{#Wiki_filter:Joseph M. Farley Nuclear Plant Risk-Informed Technical Specifications Risk-Informed Initiative 4b Pre-submittal Meeting March 12, 2018 |
| *Plant specific application based on the approved Vogtle Safety Evaluation(SE) | | |
| *Implementation plans | | Overview Farley 4b License Amendment Request (LAR) |
| *Probabilistic Risk Assessment (PRA) models | | * Plant specific application based on the approved Vogtle Safety Evaluation(SE) |
| *LAR Enclosures | | * Implementation plans |
| *SNC RequestsKey Dates*Vogtle Application approved June 2017 | | * Probabilistic Risk Assessment (PRA) models |
| *Farley LAR submittal planned for early 2Q | | * LAR Enclosures |
| -2018 3 FNP Identical to Vogtle Application | | * SNC Requests Key Dates |
| *Identical to approved Vogtle Risk | | * Vogtle Application approved June 2017 |
| -Informed Technical Specifications (RITF) | | * Farley LAR submittal planned for early 2Q-2018 3 |
| -"Methods" license condition identical to Vogtle | | |
| -Tech Spec Section 3.3, Instrumentation, not in scope | | FNP Identical to Vogtle Application |
| -Use of either Common Cause Failure (CCF) Risk Managed Actions (RMAs) or modify CCF factors as required when applying an emergent Risk | | * Identical to approved Vogtle Risk-Informed Technical Specifications (RITF) |
| -Informed Completion Time (RICT) | | - Methods license condition identical to Vogtle |
| -Use of 24 hour backstop and design | | - Tech Spec Section 3.3, Instrumentation, not in scope |
| -basis parameter success criteria for Loss of Function (LOF) RICT | | - Use of either Common Cause Failure (CCF) Risk Managed Actions (RMAs) or modify CCF factors as required when applying an emergent Risk-Informed Completion Time (RICT) |
| -Providing examples of RMAs planned during RICTs related to TS inoperability of electrical equipment, like Diesel Generators (DGs), Inverters and offsite sources. | | - Use of 24 hour backstop and design-basis parameter success criteria for Loss of Function (LOF) RICT |
| -Vogtle Requests for Additional Information (RAI) incorporated and explicitly described in Attachment 1. | | - Providing examples of RMAs planned during RICTs related to TS inoperability of electrical equipment, like Diesel Generators (DGs), |
| 4 Implementation Plans | | Inverters and offsite sources. |
| *Implementing procedures are based on | | - Vogtle Requests for Additional Information (RAI) incorporated and explicitly described in Attachment 1. |
| -NEI 06-09 guidance | | 4 |
| -NRC Vogtle 4b audit inputs | | |
| -Vogtle RAI responses | | Implementation Plans |
| -Vogtle 4b LAR NRC SE. | | * Implementing procedures are based on |
| *FNP site is planning for a 4b implementation by the middle to end of 2019 by focusing on: | | - NEI 06-09 guidance |
| -Change management | | - NRC Vogtle 4b audit inputs |
| -Procedures changes to make fleet procedures applicable to Farley | | - Vogtle RAI responses |
| -Training to be delivered to Operations , Work Management and Supervision; as it was for Plant Vogtle. | | - Vogtle 4b LAR NRC SE. |
| 5 Farley PRA Models | | * FNP site is planning for a 4b implementation by the middle to end of 2019 by focusing on: |
| *Appendix X not utilized | | - Change management |
| *F&O resolutions reviewed in previous submittals | | - Procedures changes to make fleet procedures applicable to Farley |
| -NFPA 805 *Original SE | | - Training to be delivered to Operations , Work Management and Supervision; as it was for Plant Vogtle. |
| -March 10,2015 | | 5 |
| -ML14308A048 | | |
| *Final SE -November 1, 2017 | | Farley PRA Models |
| -ML17269A166 | | * Appendix X not utilized |
| -ILRT (SE -ML17261A087) | | * F&O resolutions reviewed in previous submittals |
| -5b, Surveillance frequency control program(SE ML11167A226) | | - NFPA 805 |
| *Fire model data updates | | * Original SE - March 10,2015 - ML14308A048 |
| -Incipient Detection | | * Final SE - November 1, 2017 - ML17269A166 |
| *FAQ-08-046 to NUREG 2180 | | - ILRT (SE - ML17261A087) |
| -Reactor Coolant Pump Shutdown Seal model credit | | - 5b, Surveillance frequency control program(SE ML11167A226) |
| *(Verification of approval version: ML17200C865) | | * Fire model data updates |
| -Fire Ignition Frequencies (NUREG 2169) | | - Incipient Detection |
| -Heat Release Rates (NUREG 2178) 6 LAR EnclosuresEnclosure 1: List of Revised Required Actions to Corresponding PRA Functions. | | * FAQ-08-046 to NUREG 2180 |
| -Similar to VEGP LAR in content | | - Reactor Coolant Pump Shutdown Seal model credit |
| -RICT calculations based on PEER Reviewed frozen models (previous version of the model) | | * (Verification of approval version: ML17200C865) |
| *Example calculations of RICTs | | - Fire Ignition Frequencies (NUREG 2169) |
| *Actual RICTs may vary based on plant configuration | | - Heat Release Rates (NUREG 2178) 6 |
| *Review of Vogtle RAI for DC subsystemsEnclosure 2: Information Supporting Consistency with Reg. Guide 1.200, Revision 2. | | |
| -Documents resolution of F&Os for Internal, Internal Flooding and Internal Fire PRAsEnclosure 3: Information Supporting Justification of Bounding Analysis or Excluding Sources of Risk Not Addressed by the PRA Models | | LAR Enclosures : List of Revised Required Actions to Corresponding PRA Functions. |
| -Documents use of Seismic bounding value based on convolution of FNP IPEEE and EPRI 2014 hazard Enclosure 4: Baseline CDF and LERF | | - Similar to VEGP LAR in content |
| -Total CDF/LERF meet 1E | | - RICT calculations based on PEER Reviewed frozen models (previous version of the model) |
| -04/1E-05 RG 1.1.74 risk thresholds based on latest version FNP modelsEnclosure 5: PRA Model Update ProcessEnclosure 6: Attributes of the CRMP ModelEnclosure 7: Key Assumptions and Sources of UncertaintyEnclosure 8: Program ImplementationEnclosure 9: Cumulative Risk and Performance Monitoring ProgramEnclosure 10: Risk Management Action Example 7 | | * Example calculations of RICTs |
| SNC Requests 8*Alignment on plant specific applications | | * Actual RICTs may vary based on plant configuration |
| -Identical to Vogtle | | * Review of Vogtle RAI for DC subsystems : Information Supporting Consistency with Reg. Guide 1.200, Revision 2. |
| -Any issues with NRC approval of Vogtle 4b | | - Documents resolution of F&Os for Internal, Internal Flooding and Internal Fire PRAs : Information Supporting Justification of Bounding Analysis or Excluding Sources of Risk Not Addressed by the PRA Models |
| *Use of previously approved models and recent changes | | - Documents use of Seismic bounding value based on convolution of FNP IPEEE and EPRI 2014 hazard : Baseline CDF and LERF |
| *NRC Staff feedback on SNC approach to Enclosure 1}} | | - Total CDF/LERF meet 1E-04/1E-05 RG 1.1.74 risk thresholds based on latest version FNP models : PRA Model Update Process : Attributes of the CRMP Model : Key Assumptions and Sources of Uncertainty : Program Implementation : Cumulative Risk and Performance Monitoring Program 0: Risk Management Action Example 7 |
| | |
| | SNC Requests |
| | * Alignment on plant specific applications |
| | - Identical to Vogtle |
| | - Any issues with NRC approval of Vogtle 4b |
| | * Use of previously approved models and recent changes |
| | * NRC Staff feedback on SNC approach to Enclosure 1 8}} |
|
|---|
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
[Table view] |
Text
Joseph M. Farley Nuclear Plant Risk-Informed Technical Specifications Risk-Informed Initiative 4b Pre-submittal Meeting March 12, 2018
Overview Farley 4b License Amendment Request (LAR)
- Plant specific application based on the approved Vogtle Safety Evaluation(SE)
- Vogtle Application approved June 2017
FNP Identical to Vogtle Application
- Identical to approved Vogtle Risk-Informed Technical Specifications (RITF)
- Methods license condition identical to Vogtle
- Tech Spec Section 3.3, Instrumentation, not in scope
- Use of either Common Cause Failure (CCF) Risk Managed Actions (RMAs) or modify CCF factors as required when applying an emergent Risk-Informed Completion Time (RICT)
- Use of 24 hour2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> backstop and design-basis parameter success criteria for Loss of Function (LOF) RICT
- Providing examples of RMAs planned during RICTs related to TS inoperability of electrical equipment, like Diesel Generators (DGs),
Inverters and offsite sources.
- Vogtle Requests for Additional Information (RAI) incorporated and explicitly described in Attachment 1.
4
Implementation Plans
- Implementing procedures are based on
- NEI 06-09 guidance
- NRC Vogtle 4b audit inputs
- Vogtle RAI responses
- Vogtle 4b LAR NRC SE.
- FNP site is planning for a 4b implementation by the middle to end of 2019 by focusing on:
- Change management
- Procedures changes to make fleet procedures applicable to Farley
- Training to be delivered to Operations , Work Management and Supervision; as it was for Plant Vogtle.
5
Farley PRA Models
- F&O resolutions reviewed in previous submittals
- NFPA 805
- ILRT (SE - ML17261A087)
- 5b, Surveillance frequency control program(SE ML11167A226)
- Incipient Detection
- Reactor Coolant Pump Shutdown Seal model credit
- Fire Ignition Frequencies (NUREG 2169)
- Heat Release Rates (NUREG 2178) 6
LAR Enclosures : List of Revised Required Actions to Corresponding PRA Functions.
- Similar to VEGP LAR in content
- RICT calculations based on PEER Reviewed frozen models (previous version of the model)
- Example calculations of RICTs
- Actual RICTs may vary based on plant configuration
- Review of Vogtle RAI for DC subsystems : Information Supporting Consistency with Reg. Guide 1.200, Revision 2.
- Documents resolution of F&Os for Internal, Internal Flooding and Internal Fire PRAs : Information Supporting Justification of Bounding Analysis or Excluding Sources of Risk Not Addressed by the PRA Models
- Documents use of Seismic bounding value based on convolution of FNP IPEEE and EPRI 2014 hazard : Baseline CDF and LERF
- Total CDF/LERF meet 1E-04/1E-05 RG 1.1.74 risk thresholds based on latest version FNP models : PRA Model Update Process : Attributes of the CRMP Model : Key Assumptions and Sources of Uncertainty : Program Implementation : Cumulative Risk and Performance Monitoring Program 0: Risk Management Action Example 7
SNC Requests
- Alignment on plant specific applications
- Identical to Vogtle
- Any issues with NRC approval of Vogtle 4b
- Use of previously approved models and recent changes
- NRC Staff feedback on SNC approach to Enclosure 1 8
