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Category:Meeting Briefing Package/Handouts
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 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 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) 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) 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 ML0729806702007-10-24024 October 2007 Meeting Presentation on GEH Chemical Effects Testing Update ML0715902092007-05-31031 May 2007 Enclosure 7 - Definitions: SSE (Safe Shutdown Earthquake) & OBE (Operating Basis Earthquake) 2024-07-08
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NRC FORM 658 U.S. NUCLEAR REGULATORY COMMISSION (9-19~99 TRANSMITTAL OF MEETING HANDOUT MATERIALS FOR IMMEDIATE PLACEMENT IN THE PUBLIC DOMAIN This form is to be filled out (typed orhand-printed)by the person who announced the meeting (i.e., the person who issued the meeting notice). The completed fohmin and the attachedcopy of meeting handout materials, will be sent to the Document ControlDesk on the same day of the meeting; underno circumstances will this be done later than the working day after the meeting.
Do not include proprietarymaterials.
DATE OF MEETING The attached document(s), which was/were handed out in this meeting, is/are to be placed 09/25/2002 in the public domain as soon as possible. The minutes of the meeting will be issued in the near future. Following are administrative details regarding this meeting:
Docket Number(s) 50-348 AND 50-364 Plant/Facility Name FARLEY, UNITS 1 AND 2 TAC Number(s) (if available)
Reference Meeting Notice AUGUST 19,2002 Purpose of Meeting (copy from meeting notice) TO DISCUSS KAOWOOL ISSUES NAME OF PERSON WHO ISSUED MEETING NOTICE TITLE F. RINALDI JPROJECT MANAGER OFFICE NRR DIVISION DLPM BRANCH PD 11-1 Distribution of this form and attachments:
Docket File/Central File PUBLIC NRC FORM 658 (9-1999) PRINTED ON RECYCLED PAPER Tirls form was designed using inF-orms
Raceway Fire Barrier Resolution Project Farley Nuclear Plant
' Project Status
__SOUTHERNA COMPANY AGENDA
- Kaowool Recap I~ - Current Resolution Status I* - Risk Informed / Performance Based - Fire Modeling of SWIS
-I, 1
Kaowool Recap FNP selected and installed Kaowool to meet original raceway fire protection requirements BTP APCSB 9.5-1 (late 70's)
FNP requested and was granted specific Appendix R exemptions to 1 hr fire barrier requirements based on Kaowool use. (mid 80s)
NRC questioned technical basis of exemptions and acknowledges their approval but no longer understands the basis for granting (1999)
SNC commits to address NRC concerns (2000) i Current Resolution Status 19 Fire Areas Affected Preferred Solutions are:
Reroute Cable Install Fire Rated cables Installation of Local Indication Add controls to Hot Shutdown Panel Enhance operator actions Service Water Intake Structure Fire Modeling Administrative Controls J Upgraded Fire Barrier Walls L Exemptions 2
Current Resolution Status
- 30 to 35 Design Change Packages will be developed
- 5 DCP's have been issued. One is complete; several are being worked during the current Unit 2 outage.
- Our Plan is to be complete with all modifications by end of year 2005.
Project Timeline Project Timeline W r ee 2We are here!
2000 - The Study Year/
- Develop potential resolution and develop recommended resolution plan outageImplementation and non-outageYears mods S
S
/
S200213/415-
.Both to be conducted each year.
S ItJ S S
S
- i. S S
S S
S 2001 - DCP Development Year 2006 - The Clean Up Year
° Obtain management
- Complete 'left-over work concurrence and begin design work for DCPs, begin exemption 'reconstitution.'
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Risk Informed / Performance Based Modeling at the SWIS SWIS houses the service water pumps (ultimate heat sink)
IAz Modeling at the SWIS
-Approximately 1350 feet of Appendix R Kaowool
- Rerouting is not feasible
-Removal of current wrap may involve complex "personnelprotection requirements I *Rewrapping cable with new wrap does not provide significant safety improvement 4
Modeling at the SWIS
-SNC has conducted a pilot study of a risk informed / performance based fire model at the SWIS
-Pilot performed by outside consultants and follows the guidelines of NFPA 805
-Model Results:
Afire of sufficient magnitude to cause loss of function of redundant trains of cables is extremely unlikely Much better improvement in CDF/LERF is achieved by other modifications than re-wrapping cable trays Modeling at the SWIS Modeling of SWIS has shown that other modifications do provide a safety improvement
-Isolation of a DG Control Circuit
-Elimination of the need for Unit 2 service A water booster pumps by modification of service water pump seals
-Enhancement of the swing pump fire barrier to prevent spreading fire from one train to another.
5
Conclusions SNC is on schedule to complete all Kaowool fire barrier work by end of 2005.
This date is contingent on the acceptance of fire modeling for the SWIS Pilot Fire modeling of the SWIS has shown that modifications as opposed to re-wrapping of cables "improves plant safety Utilization of risk insights and fire modeling can result in greater safety improvement than strict compliance with Appendix R 6