ML13127A080
| ML13127A080 | |
| Person / Time | |
|---|---|
| Site: | Mcguire, Catawba, Robinson, McGuire  |
| Issue date: | 04/18/2013 |
| From: | Ertman J, Goforth D Duke Energy Corp |
| To: | Billoch-Colon A T Plant Licensing Branch II |
| Billoch-Colon A T | |
| Shared Package | |
| ML13127A050 | List: |
| References | |
| TAC MF0956 | |
| Download: ML13127A080 (34) | |
Text
Fleet Fire Protection ProgramgNFPA 805National Fire Protection AssociationNFPA 805 Pre-LAR Application for CNS, MNS, RNPJefferyErtmanDavidGoforth-NFPA805ProjectManagersJeffery Ertman, David Goforth -NFPA 805 Project ManagersApril 18, 2013 Agenda*NFPA 805 Transition Project Overviewj*License Amendment Request Overview*Fire PRA Overview2 Participants*Jeffery Ertman-NFPA 805 Project ManagerDidGfthNFPA805PjtM*David Goforth -NFPA 805 Project Manager*Donna Alexander -Manager Fleet Regulatory Affairs*BobRishel-PRAManagerBob Rishel PRA Manager*Jeff Robertson -Manager Regulatory Affairs*Julius Bryant -Regulatory Affairs ygy*Sarah Chisholm -PRA Engineer*Kelly Lavin -Site Technical Lead*Al Maysam -Regulatory Affairs *Jamie McCrory -PRA EngineerBdiWPRAEi*Brandi Weaver -PRA Engineer 3 Acronyms*AFW -Alternate Feed Water*CNS-CatawbaNuclearStation*MNS -McGuire Nuclear Station*MOV-MotorOperatedValveCNS Catawba Nuclear Station*CPT -Control Power Transformer*CSR -Cable Spreading Room*FAQ -Frequently Asked QuestionMOV Motor Operated Valve*NEI -Nuclear Energy Institute*NRC -Nuclear Regulatory Commission*OE -Operating Experience*FPRA -Fire Probabilistic Risk Assessment*FRE -Fire Risk Evaluation*FSA -Fire Safety AnalysisF&OFtdObti*PORV -Power Operated Relief Valve*RAI -Request for Additional Information*RCP -Reactor Coolant PumpRNPRbiNlPlt*F&O -Facts and Observations*HEAF -High Energy Arcing Fault*HRR -Heat Release Rate*LAR-LicenseAmendmentRequest*RNP -Robinson Nuclear Plant*SSA -Safe Shutdown Analysis*TDEFWP -Turbine Driven Emergency FeedwaterPumpLAR License Amendment Request*LERF -Large Early Release Frequency*LOOP -Loss of Offsite Power*UAM -Un-reviewed Analytical Method*VFDR -Variance From Deterministic Requirements4 Fleet Transition to NFPA 805MilestonesCNSMNSRNPLAR09/30/201309/30/201309/30/2013SafetyEvaluation09/30/201509/30/201509/30/2015NFPA 805 Program Implementation03/31/201603/31/201603/31/20165 LAR Document Submittal*Using Current Industry LAR Template-NEI Incorporating Generic RAIs*Incorporating Lessons Learned-Current Generic RAIs-Current Industry NFPA 805 LAR Submittals and RAIsInternalOEfrompreviousplantsubmittalsreviewsand-Internal OE from previous plant submittals, reviews, and implementation6 Catawba Nuclear Station7 Catawba Project Status*Traditional Fire Protection Elements -AttachmentL-NFPA805Chapter3RequirementsforApprovalAttachment L NFPA 805 Chapter 3 Requirements for Approval (10CFR50.48(c)(2)(vii)*Approval for existing wiring above the control room ceiling*ReactorCoolantPumpOilMistingReactor Coolant Pump Oil Misting-No Attachment T requests -Clarification of Prior NRC Approvals*FRE statusfl-FPRA Quantification Complete*CNS meets the requirements of acceptability for RG-1.174-Defense-in-Depth actions in review-Recovery Action*Local Trip of Reactor Coolant Pumps*Local throttling of Emergency FeedwaterFlow8 Catawba Project Status (continued)*LAR development started*Proposed Modifications -Breaker Coordination modifications-Inverter cable re-route-VCT Outlet Valve spurious closure issue resolved by modificationmodification-Additional modifications may result from FRE DID review or Chapter 3 required systems code review*Completed Modifications-4 Breaker Coordination modifications9 Catawba PRA*InternalEventsInternal Events-NEI 00-02 Internal Events Peer Review March 2002-Internal Gap Assessment to ASME/ANS PRA Standard as endorsed by RG 1.200*Performed in 2008*PerformedtoRG1200Revision1*Performed to RG 1.200 Revision 1-LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2FocusedLERFPeerReviewinDecember2012(NEI0504)-Focused LERF Peer Review in December 2012 (NEI 05-04)-F&Os from these reviews will be dispositionedin the LAR for Fire PRA impact 10 Catawba Fire PRA*Full Scope Peer Review in 2010*F&Os will be addressed in LAR*NR/CR-6850/ EPRI 108239 methods used*Fire Modeling methods per NR/CR-6850/ EPRI 108239 *Removed credit for electrical cabinet treatment refinement*Well sealed Motor Control Centers11 CNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for administrative controls (transients)*Credit for hot short duration failure probabilities for DC circuits12 Catawba Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCredit for Admin Controls (Transients)YesYesIgnition Frequency (FAQ-48)YesYesHot Short Duration (DC)YesNo11) It is not practical to vary the hot short duration credit for the deterministic variant and deterministic compliant case for each fire area; however, the impact on VFDR Risk may be estimated from the overall impact on FPRA CDF/LERF and the scope of VFDRs.13 Catawba Project Summary*NUREG-0800 non-compliances identified-Compensatory actions implemented as needed*NRC Fire Protection Triennial Inspection-Scheduled for April 2013 14 McGuire Nuclear Station15 McGuire Project Status*Traditional Fire Protection Elements-AttachmentL-NFPA805Chapter3RequirementsforApprovalAttachment L NFPA 805 Chapter 3 Requirements for Approval (10CFR50.48(c)(2)(vii)*Approval for existing wiring above the control room ceiling*Reactor Coolant Pump Oil Misting-No Attachment T requests -Clarification of Prior NRC Approvals*FRE status-FPRA Quantification CompleteFPRAQuantificationComplete*MNS meets the requirements of acceptability for RG-1.174-FRE Defense-in-Depth review complete-Recovery Actiony*Local Trip of Reactor Coolant Pumps*Local throttling of Emergency FeedwaterFlow*Local operation of the PressurizerHeaters16 McGuire Project Status (continued)*LAR development in progress*Proposed Modifications-Eliminate spurious operation of TDEFWP Suction Valve-Modify condensate drain from containment to improve overall LERF*CompletedModifications*Completed Modifications-Current Transformer Modification-PressurizerHeaterModificationPressurizerHeater Modification17 McGuire PRA*InternalEventsInternal Events-NEI 00-02 Internal Events Peer Review October 2000-Internal Gap Assessment to ASME/ANS PRA standard as endorsed by RG 1.200*Performed in 2008*PerformedtoRG1200Revision1*Performed to RG 1.200 Revision 1-LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2FocusedLERFPeerReviewinDecember2012(NEI0504)-Focused LERF Peer Review in December 2012 (NEI 05-04)-F&Os from these reviews will be dispositionedin the LAR for fire PRA impact18 McGuire Fire PRA*Full Scope Peer Review in 2009*F&Os will be addressed in LAR*NR/CR-6850/ EPRI 108239 methods used*Fire Modeling methods per NR/CR-6850/ EPRI 108239 *Removed credit for electrical cabinet treatment refinement*Well sealed Motor Control Centers19 MNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for hot short duration failure probabilities for DCiiDC circuits20 McGuire Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskHot Short Duration (DC)YesNo1()Ignition Frequency (FAQ-48)YesYes1) It is not practical to vary the hot short duration credit for the deterministic variant and deterministic compliant case for each fire area; however, the impact on VFDR Risk may be estimated from the overall impact on FPRA CDF/LERF and the scope of VFDRs.21 McGuire Project Summary*Appendix R non-compliances identified -Compensatory actions implemented as needed*Completed NRC Fire Protection Triennial Inspection-February 2013-No significant findings22 Robinson Nuclear Plant23 Robinson Project Status*Traditional Fire protection Elements-AttachmentL-NFPA805Chapter3RequirementsforApprovalAttachment L -NFPA 805 Chapter 3 Requirements for Approval (10CFR50.48(c)(2)(vii)*Approval for existing wiring above control room ceiling-No Attachment T requests -Clarification of Prior NRC Approvalsqpp*FSA development starting in late April-FRE is performed as part of FSA development-Defense-in-Depthactionsinreview-Defense-in-Depth actions in review-FPRA Quantification Revision in Process*RNP meets the requirements of acceptability for RG-1.174*LARDevelopmentStartinginMay*LAR Development Starting in May*Modifications-Potential Modifications Identified-Final Scope After Fire PRA and FSAs are Completed24 Robinson Proposed Modifications*Incipient Detection*Protect MOVs from IN 92-18 Hot Short Failure*Electrically Coordinate Power Supplies*HEAF mitigation modification in E1/E2 Switchgear room*Protect Shutdown Valves*Credit 4thTrain of AFW*Credit Westinghouse RCP Shutdown Seal*Credit the Diesel Generators on the DeepwellPumps25 Robinson Completed ModificationsAuto Start/Auto Load of Dedicated Shutdown Diesel Generator on Loss of All AC Power Auto Reload of Battery Chargers on a LOOPBackup Instrument Air for Charging Pumps Speed Control PressurizerPORV & Charging Pump Make-up ModificationggppReplacement of HemycFire Barrier Wrap Emergency Lighting Modifications Evaluation and Modifications of the MOVs for IN92-18Installation of Fire Walls Between Transformers and Between Transformers And Turbine BuildingKey Locked Isolation Switch in Control Room to Isolate DC Electrical Power to Key yyAuxiliary Panels Protect the E-Bus Incoming Line Breakers from Spurious Operations for a Postulated Fire in the Turbine Bldg. Cable Rerouting to Protect Safe Shutdown Equipment26 Robinson PRA*Internal Events-Full Scope ASME/ANS PRA Standard Peer Review in October 2009-F&OswillbedispositionedintheLARforfirePRAimpact-F&Os will be dispositionedin the LAR for fire PRA impact 27 Robinson Fire PRA Overview*Full Scope Peer Review in 2013*F&Os being addressed in FPRA revision-Documented in LAR*NR/CR-6850/ EPRI 108239 methods used28 Robinson Fire PRA Overview (Continued)(Continued)*Credit taken for Flame Retardant Coatingg-IntumasticInstalled on Thermoplastic Cable*Unit 2 Cable Spread Room (CSR)/2Sih*E1/E2 Switchgear Room*Incipient DetectionInCabinetInstallationCreditperFAQ080046-In-Cabinet Installation -Credit per FAQ 08-0046*Main Control Boards*I & C Racks*Safeguards Cabinets-Area Wide -Normal Detection Credit*Unit2CableSpreadRoom*Unit 2 Cable Spread Room29 RNP Deviations from NRC-Accepted FPRAMethodsFPRA Methods*For closed-cabinet MCCs:-A severity factor of 0.1 is applied, where 90% of fires are contained within the MCC-HRRseverityfactorsaretreatedindependentlysimilarto-HRR severity factors are treated independently, similar to other cabinets-Method was used to Address RAI 5-32 for the HNP NFPA 805 Application*BNP LAR Audit RAIs under evaluation for applicability tRNPat RNP30 Robinson Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCPT credit for spurious failuresYesYesIitiF(FAQ48)YYIgnition Frequency (FAQ-48)YesYesIncipient Detection (FAQ-46)YesYes31 Robinson PRA Considerations*Re-evaluate treatment of 480V Switchgear-Amptectorsare used at RNP on E1/E2 Switchgears-Reviewing HEAF data for 480V SwitchgearNotagenericisse-Not a generic issue32 Robinson Project Summary*Developing committed modifications final scope and hdlischeduling*Appendix R non-compliances identified lddd-Compensatory actions implemented as needed*Completed NRC Fire Protection Triennial InspectionNb2012-November 2012-No significant findings33 Questions34