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| | author name = | | | author name = |
| | author affiliation = Southern Nuclear Operating Co, Inc | | | author affiliation = Southern Nuclear Operating Co, Inc |
| | addressee name = Brown E A | | | addressee name = Brown E |
| | addressee affiliation = NRC/NRR/DORL/LPLII-1 | | | addressee affiliation = NRC/NRR/DORL/LPLII-1 |
| | docket = 05000348, 05000364 | | | docket = 05000348, 05000364 |
| | license number = NPF-002, NPF-008 | | | license number = NPF-002, NPF-008 |
| | contact person = Brown E A | | | contact person = Brown E |
| | package number = ML13078A284 | | | package number = ML13078A284 |
| | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs | | | document type = Meeting Briefing Package/Handouts, Slides and Viewgraphs |
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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
[Table view] |
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FNP Fire Modeling LAR Submittal Oi O verv i ewMarch 19, 2012FireModelingOverview Fire Modeling Overview Fire Modeling TopicsThe purpose of this presentation is to describe the fire modeling applications at FNC that are used to support thNFPA805liibiFidlii th e NFPA 805 li cens i ng b as i s. Fi re mo d e li ng i s performed in one of three general areas:*Generic Fire Modeling Treatments-Original report (2008)Slt12d3-S upp l emen t s 1 , 2 , an d 3*Main Control Room Abandonment CalculationMGStMtZOICllti
- MG S e t M o t or ZOI C a l cu l a ti on FM Overview Slide 2of 20 Generic Fire Modeling Treatments Treatments*PurposeQantif/tablatetheZOIdimensionsarondplantignition
-Q u antif y/tab u late the ZOI dimensions aro u nd plant ignition sources*NUREG/CR-6850 ignition sources (bins)Cbtiblliidillfi
- C om b us tibl e li qu id sp ill fi res-Quantify/tabulate the time to reach threshold HGL temperatures*ZOI Concept-ZOI is defined by one or more lateral dimensions and a vertical dimension-Th e Z O I i s assoc i ated wi t h a steady state da m age t hr es h o l d eOsassocatedtasteadystatedaagetesod heat flux*5.7 kW/m² (thermoplastic/non-IEEE-383 qualified cables*11.4 kW/m² (thermoset/IEEE-383 qualified cables FM OverviewSlide 3of 20 Generic Fire Modeling Treatments Treatments*ZOI Calculation-Uses empirical plume models and steady state damage thresholds*Includes same models used in NUREG-1805; selects most adverse amon g all models used g-Variable fire diameter/area (via heat release rate per area)*Ignition SourcesFiNUREG/CR6850ltill(fiftHRRbi
-Fi ve NUREG/CR-6850 e l ec t r i ca l pane l s cases (fift een HRR bi ns each)-Transient (fifteen HRR bins)
-Unconfined/confined liquid fire-Cable tray stacks (applicable to thermoplastic cables only)
FM OverviewSlide 4of 20 Generic Fire Modeling Treatments TreatmentsTransient ZOI DimensionsPanel ZOI Dimensions FM OverviewSlide 5of 20 Generic Fire Modeling Treatments Treatments*ZOI Im p lementation p-98 thpercentile ZOI dimensions assembled in walkdown form-Largest horizontal ZOI dimension used when there are multiple dimensions(panels) dimensions (panels)-Vertical ZOI dimension used if no secondary combustibles in ZOI
-Ceiling height used do define vertical ZOI dimension if secondarycombustiblesareinZOI secondary combustibles are in ZOI-Vertical ZOI dimension is relative to:*The fire base (transient and combustible liquid fires)Thfl(lfi)*Th e fl oor (pane l fi res)*The lowest tray in stack (cable tray fires)
FM OverviewSlide 6of 20 Generic Fire Modeling Treatments Treatments*Key ZOI Limitations (Original Document)
-Nosecondarycombustibles(seeSupplement2)
No secondary combustibles (see Supplement 2)-No hot gas layer effects-Open fire configuration*Hot Gas Layer Effects on ZOI Dimensions-A modified critical heat flux is used to establish reasonable maximum tem perature and to extend ZOI a pp licabilit ypppy*80°C alters critical heat flux by about 1 kW/m² and is considered the maximum value beyond which non-conservative results could be
generated*Not a required limitation for plume and heat flux models in NUREG-1805 (same methods), but model bias is low due to HGL effects-Used to extend ZOI for some target classes FM Overview Slide 7of 20 Generic Fire Modeling Treatments Treatments W/m 2)10 12/s-ft 2)1.0IEEE-383 Cablenon-IEEE-383 Cable Thermoset cableThermoplasticcable al Heat Flux (k W 6 8 10l Heat Flux (Btu
/0.60.8Class A combustible Thermoplastic cableClass A combustibleModified Critic a 2 4Modified Critica0.20.4Immersion Temperature (°C)050100150200250300350 0ImmersionTemperature(°F)1002003004005006000.0Temperature range forthermoset cable target ZOIImmersion Temperature (F)Temperature range for thermoset cable target ZOI characterized using thermoplastic target ZOI FM OverviewSlide 8of 20 Generic Fire Modeling Treatments Treatments*Wall and Corner ConfigurationsWithin2ftofawallorcornerboundary
-Within 2 ft of a wall or corner boundary-'Image' Method used*Chan ge entrainment characteristics of model plume to account for gpcorner or wall:-Model HRR -2 or 4 X Bin HRR (wall or corner)
-Model fire diameter is 2 1/2 or 2 X Bin fire diameter (wall or (corner) to maintain constant Q/A*Change enclosure characteristics to accommodate 'virtual' portions of model fire plume:-Wall and ceiling area doubled/quadrupled-Natural and forced ventilation flow paths/volumes doubled/quadrupled FM Overview Slide 9of 20 Generic Fire Modeling Treatments Treatments*Hot Gas Layer Tables
-List time the HGL reaches threshold value in generic enclosure-Tabulated by:*Fire size*Enclosure volume*Leakage fraction
-For a g iven fire size and enclosure volume
, the minimum time g,among all leakage fractions is selected-Generic enclosure derived from sensitivity runs:*Minimizes surface area*Adiabatic floor*Three potential vent combinations for each scenario FM OverviewSlide 10of 20 Generic Fire Modeling Treatments Treatments H e=0.63 V1/3 W exL exH e= V H e=0.63 V1/3 W exL exH e= V A 3 A 1= A 2= A 3 A 3 A 1= A 2= A 3 A 1= A 2= A 3 L e=1.26 V 1/3 L e=1.26 V 1/3 A 1 A 2 H e W e or L e W e or L e A 1 A 2 H e W e or L e W e or L e W e=1.26 V1/3 W e=1.26 V1/3Vent Orientation 1Vent Orientation 2Vent Orientation 3Vent Orientation 1Vent Orientation 2Vent Orientation 3Generic SpaceVent Orientations FM OverviewSlide 11of 20 Generic Fire Modeling Treatments Treatments*Verification
-IndependentreviewofallcalculationsperformedusingExcel Independent review of all calculations performed using Excel*Validation-Most applications include at least one fire scenario that falls ithithNUREG 1824diilt w ithi n th e NUREG-1824 non-di mens i ona l parame t er space-Additional basis is provided in LAR Attachment J for plume and heat flux applications that fall outside the NUREG-1824 non-diilt di mens i ona l parame t er space-CFAST simulations include a geometry that by definition conforms with NUREG-1824 validation range. At least one ihiltithtfllithithNUREG scenar i o h as an equ i va l ence ra ti on th a t f a ll s w ithi n th e NUREG-1824 validation range.
FM OverviewSlide 12of 20 Generic Fire Modeling Treatments Treatments*Supplement 1: Closed Panel HRR EstimatesUilidlkfiihd
-U ses vent il at i on an d l ea k age area f ract ions w i t h mass an d energy balance to determine maximum internal HRR-Results compared with available test data (verification) and htbtihtlbiibd s h own t o b e conserva tive w hen no ex t erna l b urn i ng i s o b serve d or the door does not fail*Supplement 2: Expanded HGL Tables-Original Generic Fire modeling treatment approach expanded to include:*Time-de pendent fires p*Secondary combustibles (two side-by-side, 18 inch wide cable trays Ignited at five minutes at a point above a panel; lateral flame spread per NUREG/CR-6850 recommended rates)
FM Overview Slide 13of 20 Generic Fire Modeling Treatments Treatments*Supplement 3: Transient Ignition Source Characteristics (ThilRt)(T ec h n i ca l R epor t)-Characterizes ZOI sensitivity to assumed fire diameter or area-Determines fire area/diameter range for transients based on NUREG/CR-6850 test data-Identifies special case of 98 th percentile transient
-Identifies 98 th percentile transient fire duration based on ener gy pgy content-Provides revised ZOI dimensions based on 98 thfire area and fire duration-Uses same methods as original Generic Fire Modeling Treatments report to generate revised ZOIs FM OverviewSlide 14of 20 Main Control Room AbandonmentCalculation Abandonment Calculation*Pur p ose p-Tabulate the abandonment time for ignition sources present in the MCR
-Provide a sensitivity study of the abandonment times to parameter uncertainty
- Method*Method-CFAST, Version 6.1.1 used
-NUREG/CR-6850OpticalDensity(OD)and NUREG/CR 6850 Optical Density (OD) and temperature criteria used to define abandonment FM Overview Slide 15of 20 Main Control Room AbandonmentCalculation Abandonment Calculation*NUREG/CR-6850 Fire Scenarios (15 HRR Bins Each)
-Panel(closedsingle/multiplebundlenon
-IEEE-383qualified)
Panel (closed , single/multiple bundle , non IEEE 383 qualified)-Panel fire that propagates to adjacent panels (open, non-IEEE-383 qualified cables)
Transient-Transient*Multiple Geometric/Boundary Configurations-Normal HVAC/no HVAC/purge mode-Boundary door open/closed/open at 15 minutes-Operating area/equipment area
- 1080BaseSimulations(4firesX15binsX9Geometries
- 1080 Base Simulations (4 fires X 15 bins X 9 Geometries X 2 Locations)
FM Overview Slide 16of 20 Main Control Room AbandonmentCalculation Abandonment CalculationMCRPlanComputer Rooms(sameHVACZone)
FM OverviewSlide 17of 20 MCR Plan (same HVAC Zone)
Main Control Room AbandonmentCalculation Abandonment Calculation*Sensitivity Analysis (Appendix B)
-Nineparametersassessedforeachignitionsource(Bin14fires)
Nine parameters assessed for each ignition source (Bin 14 fires)-Low sensitivity observed in most computed abandonment times (typically +/-1 -2 minutes or less)
- Someparametersconservativelybiased
- Some parameters conservatively biased*Some parameter are not conservatively biased-Sensitivity is not expected to affect the order of magnitude of risk AdiDPidDiifVifitid
- A ppen di x D P rov id es Di scuss ion o f V er ifi ca ti on an d Validation/Benchmark Installation
-Includes com p arison a gainst NUREG 4527, Vol. 2 test cases pg (validation)-Includes comparison against NUREG 1824 simulations (verification and validation
)()FM OverviewSlide 18of 20 MG Set Motor ZOI Calculation*NUREG 1805 Com p utation p-Thermal plume temperature (vertical ZOI dimension)-Thermal radiation model (horizontal ZOI dimension)
-Enclosurehotgaslayersensitivityanalysis(AppendixB)
Enclosure hot gas layer sensitivity analysis (Appendix B)*Analysis Follows NUREG-1934 Process
- Verification Provided by NUREG-1824 *Applications Outside of NUREG-1824 Validation Range-Results are used with conservative bias
-LARAttachmentJprovidesadditionalbasisforapplication LAR Attachment J provides additional basis for application FM OverviewSlide 19of 20 FNC Fire Modeling Overview Questions?
FM OverviewSlide 20of 20