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| | number = ML101670548 | | | number = ML101670548 |
| | issue date = 06/08/2010 | | | issue date = 06/08/2010 |
| | title = 06/08/2010 - Farley Nuclear Plant, NRC Screening Criteria Response | | | title = Farley Nuclear Plant, NRC Screening Criteria Response |
| | author name = Ajluni M, Lattner J, Martin R, Sutton D | | | author name = Ajluni M, Lattner J, Martin R, Sutton D |
| | author affiliation = Southern Nuclear Operating Co, Inc | | | author affiliation = Southern Nuclear Operating Co, Inc |
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| {{#Wiki_filter:Enclosure 4 Farley Nuclear Power Plant Presentation Meeting Summary of the 6/8/2010 Meeting with NRC/SNC/FPL/SCE&G Dated June 17, 2010 Farley Nuclear Plant NRC Screening Criteria Response Mark Ajlun i SNC Nuclear Licensing Manager Dom Sutton SNC Programs Manager Ray Mart in FNP Technica l Services Manager John Lattner FP Principle Engineer June 8, 2010 c 0 .-co U .-l... Q) Q) "'-' 0 .-C l... U S-o CL .-01 C "'-' Ul U C Q) 0 .-Q) ::l .-> Ul CO "'0 C .-::l S-Q) "'-' "0 0 CO .-Q) u LL c l... .-"'-' l... "'-' C OJ c u .-0 c CL 01 ....... (J) ....... U z << * * * | | {{#Wiki_filter:Enclosure 4 Farley Nuclear Power Plant Presentation Meeting Summary of the 6/8/2010 Meeting with NRC/SNC/FPL/SCE&G Dated June 17, 2010 |
| * LL 0 FNP Fire Protection o Introduction
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| * FNP -Two 900 MWe 3 loop Westinghouse PWR Units | | Farley Nuclear Plant NRC Screening Criteria Response Mark Ajlun i SNC Nuclear Licensing Manager Dom Sutton SNC Programs Manager Ray Martin FNP Technica l Services Manager John Lattner FP Principle Engineer June 8, 2010 |
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| | FNP Fire Protection o Introduction |
| | * FNP - Two 900 MWe 3 loop Westinghouse PWR Units |
| * Committed to 10CFR 50 App R. | | * Committed to 10CFR 50 App R. |
| * The FNP fire protection program provides defense-in-depth protection: | | * The FNP fire protection program provides defense-in-depth protection: |
| Design Features Personnel Training Fire Fighting Equipment Operating Procedures NRC Screening Criteria Criteria Applies to Reason/Info FNP Large Number of Operator Yes* FNP is estimated to h ave sign i ficantly less than Actions BFN but more than th e other SNC plants. S i ngl e Fire ca n effect more No* Fire a r eas/equipment re li ed upon for App R safe than one Unit. shutdown are not common. Shared DG's can be im pacted. DG redundancy ensures SSD. Use of Thermop l ast i c Cables Not Some thermoplastic used for low voltage Sign i ficant* applications s u ch as cameras o r te l ecommun i cations. Less tha n 8 % of cab l es installed. | | Design Features Fire Fighting Equipment Personnel Training Operating Procedures |
| Problems docu m ent in g cable No No signif i cant issues w i th documenting cab l e routing rout i ng. Ana l ysis Credits Se l f Induced No SISBO not cred i ted Stat i on Blackouts Comp li cated Manua l Operato r Yes | | |
| * Based on NRC cr i teria. Current manua l act i ons are Actions fe l t to be reasonab l e. Operators are trained and drilled on actions. Compensatory actions in place. M i t i gat ion o f a fire requ i res Not No electr i cal cross connections credited. | | NRC Screening Criteria Criteria Applies to Reason/Info FNP Large Number of Operator Yes* FNP is estimated to have sign ificantly less than Actions BFN but more than th e other SNC plants. |
| Lim i ted the use of systems f r om Sign i ficant use of cross connected a i r systems. N2 backup to mult i p l e units (electrical or PORV's is cred i ted and is not a cross connected mechanical cross-unit t i es). system. Use of Symptom based Yes* A l though decision required, event recogn i t i on is not Procedu r es. req u i r ed. | | Singl e Fire ca n effect more No |
| | * Fire areas/equipment relied upon for App R safe than one Unit. shutdown are not common. Shared DG's can be im pacted . DG redundancy ensures SSD. |
| | Use of Thermop lastic Cables Not Some thermoplastic used for low voltage Sign ificant* applications such as cameras or telecommun ications . Less tha n 8 % of cables installed. |
| | Problems docu mentin g cable No No significant issues with documenting cab le routing routing. |
| | Ana lysis Credits Self Induced No SISBO not cred ited Station Blackouts Comp li cated Manua l Operato r Yes |
| | * Based on NRC criteria. Current manua l actions are Actions felt to be reasonable. Operators are trained and drilled on actions . Compensatory actions in place . |
| | Mit igation of a fire requ ires Not No electrical cross connections credited. Lim ited the use of systems f rom Sign ificant use of cross connected air systems. N2 backup to multiple units (electrical or PORV's is cred ited and is not a cross connected mechanical cross-unit t ies). system . |
| | Use of Symptom based Yes* Although decision required, event recogn it ion is not Procedu res. req uired. |
| | |
| FNP Fire Protection Initiatives D Initiatives | | FNP Fire Protection Initiatives D Initiatives |
| * Elimination of Kaowool fire wrap by cable reroute to ensure proper cable separation was complete in 2006 | | * Elimination of Kaowool fire wrap by cable reroute to ensure proper cable separation was complete in 2006 |
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| * Fire PRA Model under development | | * Fire PRA Model under development |
| * Safe Shutdown Analysis Revalidation | | * Safe Shutdown Analysis Revalidation |
| * OMA Feasibility Study & Compensatory Actions FNP Fire Protection Summary o OMA along with procedures is the main reason for yes screen criteria o Conservative LOSP assumption has added OMAs o Application of NFPA 805 will significantly reduce OMAs o Thermoplastic cables used in lower voltage applications and low 0/0 o No reliance on cable wrap material proper separation exists for cables. o FNP believes that 3 of the 8 screening criteria are material.}} | | * OMA Feasibility Study & Compensatory Actions |
| | |
| | FNP Fire Protection Summary o OMA along with procedures is the main reason for yes screen criteria o Conservative LOSP assumption has added OMAs o Application of NFPA 805 will significantly reduce OMAs o Thermoplastic cables used in lower voltage applications and low 0/0 o No reliance on cable wrap material proper separation exists for cables. |
| | o FNP believes that 3 of the 8 screening criteria are material.}} |
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Category:Meeting Briefing Package/Handouts
MONTHYEARML23361A0812024-01-0808 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) 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 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 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) ML0717004662007-05-31031 May 2007 05/2007 Generation Planning Overview. ML0715901212007-05-30030 May 2007 Mrp/Prwog Mitigation Briefing, Industry Update PWROG Farley Zinc Program. ML0523503432005-08-25025 August 2005 Southern Nuclear/Westinghouse Proposed Test Plan to Demonstrate Benefits of Zinc Additions to Mitigate PWSCC 2024-01-08
[Table view] Category:Slides and Viewgraphs
MONTHYEARML23361A0812024-01-0808 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 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) 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 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) 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) 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) 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 ML0717004662007-05-31031 May 2007 05/2007 Generation Planning Overview. ML0715901212007-05-30030 May 2007 Mrp/Prwog Mitigation Briefing, Industry Update PWROG Farley Zinc Program. ML0633400062006-11-29029 November 2006 SNC Farley Meeting Slides 2024-01-08
[Table view] |
Text
Enclosure 4 Farley Nuclear Power Plant Presentation Meeting Summary of the 6/8/2010 Meeting with NRC/SNC/FPL/SCE&G Dated June 17, 2010
Farley Nuclear Plant NRC Screening Criteria Response Mark Ajlun i SNC Nuclear Licensing Manager Dom Sutton SNC Programs Manager Ray Martin FNP Technica l Services Manager John Lattner FP Principle Engineer June 8, 2010
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FNP Fire Protection o Introduction
- FNP - Two 900 MWe 3 loop Westinghouse PWR Units
Design Features Fire Fighting Equipment Personnel Training Operating Procedures
NRC Screening Criteria Criteria Applies to Reason/Info FNP Large Number of Operator Yes* FNP is estimated to have sign ificantly less than Actions BFN but more than th e other SNC plants.
Singl e Fire ca n effect more No
- Fire areas/equipment relied upon for App R safe than one Unit. shutdown are not common. Shared DG's can be im pacted . DG redundancy ensures SSD.
Use of Thermop lastic Cables Not Some thermoplastic used for low voltage Sign ificant* applications such as cameras or telecommun ications . Less tha n 8 % of cables installed.
Problems docu mentin g cable No No significant issues with documenting cab le routing routing.
Ana lysis Credits Self Induced No SISBO not cred ited Station Blackouts Comp li cated Manua l Operato r Yes
- Based on NRC criteria. Current manua l actions are Actions felt to be reasonable. Operators are trained and drilled on actions . Compensatory actions in place .
Mit igation of a fire requ ires Not No electrical cross connections credited. Lim ited the use of systems f rom Sign ificant use of cross connected air systems. N2 backup to multiple units (electrical or PORV's is cred ited and is not a cross connected mechanical cross-unit t ies). system .
Use of Symptom based Yes* Although decision required, event recogn it ion is not Procedu res. req uired.
FNP Fire Protection Initiatives D Initiatives
- Elimination of Kaowool fire wrap by cable reroute to ensure proper cable separation was complete in 2006
- Fire PRA Model under development
- OMA Feasibility Study & Compensatory Actions
FNP Fire Protection Summary o OMA along with procedures is the main reason for yes screen criteria o Conservative LOSP assumption has added OMAs o Application of NFPA 805 will significantly reduce OMAs o Thermoplastic cables used in lower voltage applications and low 0/0 o No reliance on cable wrap material proper separation exists for cables.
o FNP believes that 3 of the 8 screening criteria are material.