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| {{#Wiki_filter:FNP NFPA 805 LAR Submittal Overview OverviewMarch19-21, 2013 Circuit Analysis Summary*Circuit Analysis Process and ControlsAltQlifiti | | {{#Wiki_filter:FNP NFPA 805 LAR Submittal Overview March 19-21, 2013 Circuit Analysis |
| *A na l ys t Q ua lifi ca ti ons*Governing Analysis Criteria SC*N SC A vs. PR A*Analysis Methodology*Circuit Analysis Database
| |
| *Associated CircuitsCircuit AnalysisSlide 2of 14 Process and Controls*Circuit Analysis ProcessPerformedIAWapprovedprocedure
| |
| -Performed IAW approved procedure-Strict and formal analysis conventions
| |
| -Emphasisonconsistencyandstandardization Emphasis on consistency and standardization-Integrated PRA and NSCA requirements
| |
| *Controls Controls-Rigidly defined Function States-Independent verification for each analysis-Detailed documentation in database (FDM/ARCPlus)Circuit AnalysisSlide 3 of 14 Analyst Qualifications*All analysts formally qualified to SNC & ContractorQUALCARDforindependentwork Contractor QUAL CARD for independent work*Internalized industry lessons learned on training, qualificationsandoversight qualifications , and oversight*Procedure and database established to force consistency consistency*Maintained awareness of dual use -PRA and NSCA NSCACircuit AnalysisSlide 4of 14 Governing Criteria*NEI 00-01, Rev.1-Initial Work to Rev.1
| |
| -Gap analysis performed to Rev. 2 (per Generic RAI 10 and RG 1.205)
| |
| *NEI00-01Rev2 NEI 00 01 , Rev. 2-Later work
| |
| -Integrated emerging PIRT issuesNdittkfffhli-N o cre dit t a k en f or o ff-sc h eme exc l us i ons*NUREG/CR-6850
| |
| -Included O p en circuits pNote: Integrated requirements for conservative, but universal criteria between PRA and NSCA Circuit AnalysisSlide 5 of 14 NSCA vs. PRA*Implementing Concepts
| |
| -95% of circuit anal ysis criteria for PRA and NSCA are y the same*Establish single dataset for criteria to assure dual use and betterinterfacebetweenNSCAandPRA better interface between NSCA and PRA*Provide procedure and database flexibility to accommodate the 5% difference Longtermconfigurationcontrolextremelydifficultif
| |
| -Long-term configuration control extremely difficult if redundant data sets are maintained
| |
| -Differences p rimaril y handled throu g h:pyg*Use of Function States*Interlock identification and documentationCircuit AnalysisSlide 6 of 14 Analysis Methodology*All circuit analysis drive by FUNCTION STATES
| |
| *FunctionStates Function States-Component + Initial State + Desired State-Permits maximum flexibility to accommodate PRA and NSCA differences (primarily auto signals)-Minimize false failures up frontEffiitdl-Effi c i en t an d less error prone-Consistent with NUREG/CR-6850 methods for Tasks 3&9 3 & 9Circuit AnalysisSlide 7 of 14 Analysis Methodology, cont-*Work package development to facilitate process
| |
| *Single,controlleddatabase(FDM)
| |
| Single, controlled database (FDM)*Process and techniques based on NRC/EPRI trainin g modules g*Major Steps Prere q uisites satisfied q*Function state established*Plant specific rules and conventions
| |
| *Generalclassification
| |
| *General classification*Resolve questionsCircuit AnalysisSlide 8 of 14 Analysis Methodology, cont-*Major Steps Work Packa g e Develo p ment gp*Drawings*Supplemental informationCableSelection Cable Selection*All scheme cables dispositioned
| |
| *Fault codes applied to all cables*Basis documented for excluded cables
| |
| *Selection of required cables with "hot probe" method
| |
|
| |
|
| *Cablesgenerallyexcludedbasedonlyondesignfeaturesat Cables generally excluded based only on design features at this stage (NUREG/CR-6850 concept)Circuit AnalysisSlide 9 of 14 Analysis Methodology, cont-*Major Steps Power Su pp l y Identificationppy*All Power Supplies identified*Required and not-required determined based on Function Staterequirements State requirements*Sensitive to alternate PS lineups and how they are creditedDependencies & Interlocks*All circuit interlocks formally dispositioned | | Summary |
| *Equipment dependencies established or off-scheme cables directly incorporated*Differentiate auto functions so NSCA and PRA can apply as credited by Basic EventCircuit AnalysisSlide 10 of 14 Analysis Methodology, cont-*Major Steps Documentation*Controlled database, with individual analysis originate and check sign-offs | | * Circuit Analysis Process and Controls |
| *Referencedrawing Reference drawing*Final calculation for circuit analysis and PRA NotebookCircuit AnalysisSlide 11 of 14 Circuit Analysis DatabaseCircuit AnalysisSlide 12 of 14 Associated Circuits*Electrical Coordination | | * A l t Qualifications Analyst Q lifi ti |
| -Consolidated calculation-Addresses NSCA & PRA*Common Enclosure-Addresses secondary fire concerns-Addresses loss of DC control power to Switchgear*CPT Open Circuits-Followed PIRT recommendations*MHIF Analysis-Followed NEI 00-01, Appendix B methodCircuit AnalysisSlide 13 of 14 Qti?Q ues ti ons ?Circuit AnalysisSlide 14 of 14}} | | * Governing Analysis Criteria |
| | * NSCA SC vs. PRA |
| | * Analysis Methodology |
| | * Circuit Analysis Database |
| | * Associated Circuits Circuit Analysis Slide 2 of 14 |
| | |
| | Process and Controls |
| | * Circuit Analysis Process |
| | - Performed IAW approved procedure |
| | - Strict and formal analysis conventions |
| | - Emphasis on consistency and standardization |
| | - Integrated PRA and NSCA requirements |
| | * Controls |
| | - Rigidly defined Function States |
| | - Independent verification for each analysis |
| | - Detailed documentation in database (FDM/ARCPlus) |
| | Circuit Analysis Slide 3 of 14 |
| | |
| | Analyst Qualifications |
| | * All analysts formally qualified to SNC & |
| | Contractor QUAL CARD for independent work |
| | * Internalized industry lessons learned on training, qualifications and oversight qualifications, |
| | * Procedure and database established to force consistency |
| | * Maintained awareness of dual use - PRA and NSCA Circuit Analysis Slide 4 of 14 |
| | |
| | Governing Criteria |
| | * NEI 00-01, Rev.1 |
| | - Initial Work to Rev.1 |
| | - Gap analysis performed to Rev. 2 (per Generic RAI 10 and RG 1.205) |
| | * NEI 00-01 00 01, Rev Rev. 2 |
| | - Later work |
| | - Integrated emerging PIRT issues |
| | - No N creditdit ttaken k ffor off-scheme ff h exclusions l i |
| | * NUREG/CR-6850 |
| | - Included Open p circuits Note: Integrated requirements for conservative, but universal criteria between PRA and NSCA Circuit Analysis Slide 5 of 14 |
| | |
| | NSCA vs. PRA |
| | * Implementing Concepts |
| | - 95% of circuit analysis y criteria for PRA and NSCA are the same |
| | * Establish single dataset for criteria to assure dual use and better interface between NSCA and PRA |
| | * Provide procedure and database flexibility to accommodate the 5% difference |
| | - Long Long-term term configuration control extremely difficult if redundant data sets are maintained |
| | - Differences p primarily y handled through: g |
| | * Use of Function States |
| | * Interlock identification and documentation Circuit Analysis Slide 6 of 14 |
| | |
| | Analysis Methodology |
| | * All circuit analysis drive by FUNCTION STATES |
| | * Function States |
| | - Component + Initial State + Desired State |
| | - Permits maximum flexibility to accommodate PRA and NSCA differences (primarily auto signals) |
| | - Minimize false failures up front |
| | - Efficient Effi i t and d lless error prone |
| | - Consistent with NUREG/CR-6850 methods for Tasks 3&9 Circuit Analysis Slide 7 of 14 |
| | |
| | Analysis Methodology, cont |
| | * Work package development to facilitate process |
| | * Single, controlled database (FDM) |
| | * Process and techniques based on NRC/EPRI training g modules |
| | * Major Steps Prerequisites q satisfied |
| | * Function state established |
| | * Plant specific rules and conventions |
| | * General classification |
| | * Resolve questions Circuit Analysis Slide 8 of 14 |
| | |
| | Analysis Methodology, cont |
| | * Major Steps Work Package g Development p |
| | * Drawings |
| | * Supplemental information Cable Selection |
| | * All scheme cables dispositioned |
| | * Fault codes applied to all cables |
| | * Basis documented for excluded cables |
| | * Selection of required cables with hot probe method |
| | * Cables generally excluded based only on design features at this stage (NUREG/CR-6850 concept) |
| | Circuit Analysis Slide 9 of 14 |
| | |
| | Analysis Methodology, cont |
| | * Major Steps Power Supply pp y Identification |
| | * All Power Supplies identified |
| | * Required and not-required determined based on Function State requirements |
| | * Sensitive to alternate PS lineups and how they are credited Dependencies & Interlocks |
| | * All circuit interlocks formally dispositioned |
| | * Equipment dependencies established or off-scheme cables directly incorporated |
| | * Differentiate auto functions so NSCA and PRA can apply as credited by Basic Event Circuit Analysis Slide 10 of 14 |
| | |
| | Analysis Methodology, cont |
| | * Major Steps Documentation |
| | * Controlled database, with individual analysis originate and check sign-offs |
| | * Reference drawing |
| | * Final calculation for circuit analysis and PRA Notebook Circuit Analysis Slide 11 of 14 |
| | |
| | Circuit Analysis Database Circuit Analysis Slide 12 of 14 |
| | |
| | Associated Circuits |
| | * Electrical Coordination |
| | - Consolidated calculation |
| | - Addresses NSCA & PRA |
| | * Common Enclosure |
| | - Addresses secondary fire concerns |
| | - Addresses loss of DC control power to Switchgear |
| | * CPT Open Circuits |
| | - Followed PIRT recommendations |
| | * MHIF Analysis |
| | - Followed NEI 00-01, Appendix B method Circuit Analysis Slide 13 of 14 |
| | |
| | Q Questions ti ? |
| | Circuit Analysis Slide 14 of 14}} |
|
---|
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
FNP NFPA 805 LAR Submittal Overview March 19-21, 2013 Circuit Analysis
Summary
- Circuit Analysis Process and Controls
- A l t Qualifications Analyst Q lifi ti
- Governing Analysis Criteria
- Circuit Analysis Database
- Associated Circuits Circuit Analysis Slide 2 of 14
Process and Controls
- Performed IAW approved procedure
- Strict and formal analysis conventions
- Emphasis on consistency and standardization
- Integrated PRA and NSCA requirements
- Rigidly defined Function States
- Independent verification for each analysis
- Detailed documentation in database (FDM/ARCPlus)
Circuit Analysis Slide 3 of 14
Analyst Qualifications
- All analysts formally qualified to SNC &
Contractor QUAL CARD for independent work
- Internalized industry lessons learned on training, qualifications and oversight qualifications,
- Procedure and database established to force consistency
- Maintained awareness of dual use - PRA and NSCA Circuit Analysis Slide 4 of 14
Governing Criteria
- Initial Work to Rev.1
- Gap analysis performed to Rev. 2 (per Generic RAI 10 and RG 1.205)
- Later work
- Integrated emerging PIRT issues
- No N creditdit ttaken k ffor off-scheme ff h exclusions l i
- Included Open p circuits Note: Integrated requirements for conservative, but universal criteria between PRA and NSCA Circuit Analysis Slide 5 of 14
NSCA vs. PRA
- 95% of circuit analysis y criteria for PRA and NSCA are the same
- Establish single dataset for criteria to assure dual use and better interface between NSCA and PRA
- Provide procedure and database flexibility to accommodate the 5% difference
- Long Long-term term configuration control extremely difficult if redundant data sets are maintained
- Differences p primarily y handled through: g
- Interlock identification and documentation Circuit Analysis Slide 6 of 14
Analysis Methodology
- All circuit analysis drive by FUNCTION STATES
- Component + Initial State + Desired State
- Permits maximum flexibility to accommodate PRA and NSCA differences (primarily auto signals)
- Minimize false failures up front
- Efficient Effi i t and d lless error prone
- Consistent with NUREG/CR-6850 methods for Tasks 3&9 Circuit Analysis Slide 7 of 14
Analysis Methodology, cont
- Work package development to facilitate process
- Single, controlled database (FDM)
- Process and techniques based on NRC/EPRI training g modules
- Major Steps Prerequisites q satisfied
- Function state established
- Plant specific rules and conventions
- Resolve questions Circuit Analysis Slide 8 of 14
Analysis Methodology, cont
- Major Steps Work Package g Development p
- Supplemental information Cable Selection
- All scheme cables dispositioned
- Fault codes applied to all cables
- Basis documented for excluded cables
- Selection of required cables with hot probe method
- Cables generally excluded based only on design features at this stage (NUREG/CR-6850 concept)
Circuit Analysis Slide 9 of 14
Analysis Methodology, cont
- Major Steps Power Supply pp y Identification
- All Power Supplies identified
- Required and not-required determined based on Function State requirements
- Sensitive to alternate PS lineups and how they are credited Dependencies & Interlocks
- All circuit interlocks formally dispositioned
- Equipment dependencies established or off-scheme cables directly incorporated
- Differentiate auto functions so NSCA and PRA can apply as credited by Basic Event Circuit Analysis Slide 10 of 14
Analysis Methodology, cont
- Major Steps Documentation
- Controlled database, with individual analysis originate and check sign-offs
- Final calculation for circuit analysis and PRA Notebook Circuit Analysis Slide 11 of 14
Circuit Analysis Database Circuit Analysis Slide 12 of 14
Associated Circuits
- Consolidated calculation
- Addresses NSCA & PRA
- Addresses secondary fire concerns
- Addresses loss of DC control power to Switchgear
- Followed PIRT recommendations
- Followed NEI 00-01, Appendix B method Circuit Analysis Slide 13 of 14
Q Questions ti ?
Circuit Analysis Slide 14 of 14