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| {{#Wiki_filter: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 | | {{#Wiki_filter:Fleet Fire Protection Pro gram gNFPA 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 Pro ject Overview j*License Amendment Request Overview |
| | *Fire PRA Overview 2 |
| | Participants |
| | *Jeffery Ertman-NFPA 805 Project ManagerDidGfthNFPA805PjtM |
| | *D av id G o f or th -NFPA 805 P ro j ec t Manager*Donna Alexander -Manager Fleet Regulatory Affairs |
| | *BobRishel-PRAManager Bob Rishel PRA Manager*Jeff Robertson -Manager Regulatory Affairs |
| | *Julius Br yant -Re gulator y Affairs y gy*Sarah Chisholm -PRA Engineer |
| | *Kelly Lavin -Site Technical Lead |
| | *Al Maysam |
| | -Regulatory Affairs |
| | *Jamie McCrory -PRA EngineerBdiWPRAEi*Bran di Weaver -PRA E ng i neer 3 Acronyms*AFW -Alternate Feed Water |
| | *CNS-CatawbaNuclearStation |
| | *MNS -McGuire Nuclear Station |
| | *MOV-MotorOperatedValve CNS 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 Analysis F&OFtdObti*PORV -Power Operated Relief Valve |
| | *RAI -Request for Additional Information |
| | *RCP -Reactor Coolant Pump RNPRbiNlPlt*F&O -F ac t s an d Observa ti ons*HEAF -High Energy Arcing Fault |
| | *HRR -Heat Release Rate |
| | *LAR-LicenseAmendmentRequest |
| | *RNP -R o bi nson N uc l ear Pl an t*SSA -Safe Shutdown Analysis |
| | *TDEFWP -Turbine Driven Emergency FeedwaterPump LAR License Amendment Request*LERF -Large Early Release Frequency |
| | *LOOP -Loss of Offsite Power |
| | *UAM -Un-reviewed Analytical Method |
| | *VFDR -Variance From Deterministic Requirements 4 |
| | Fleet Transition to NFPA 805MilestonesCNSMNSRNP LAR09/30/201309/30/201309/30/2013SafetyEvaluation09/30/201509/30/201509/30/2015NFPA 805 Program Implementation03/31/201603/31/201603/31/2016 5 |
| | 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 implementation 6 |
| | Catawba Nuclear Station 7 |
| | 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 status fl-FPRA Quanti fication Comp lete*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 FeedwaterFlow 8 |
| | 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 modifications 9 |
| | 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(NEI05 04)-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 Centers 11 CNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for administrative controls (transients) |
| | *Credit for hot short duration failure probabilities for DC circuits 12 Catawba Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCredit for Admin Controls (Transients)YesYesIgnition Frequency (FAQ-48)YesYesHot Short Duration (DC)YesNo |
| | : 11) 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 Station 15 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 |
| | -Recover y Action y*Local Trip of Reactor Coolant Pumps |
| | *Local throttling of Emergency FeedwaterFlow |
| | *Local operation of the PressurizerHeaters 16 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 Modification 17 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(NEI05 04)-Focused LERF Peer Review in December 2012 (NEI 05-04)-F&Os from these reviews will be dispositionedin the LAR for fire PRA impact 18 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 Centers 19 MNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for hot short duration failure probabilities for DCii DC c ircu i ts 20 McGuire Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskHot Short Duration (DC)YesNo 1 ()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 findings 22 Robinson Nuclear Plant 23 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 re quests -Clarification of Prior NRC A pprovals q pp*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 Completed 24 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 4 thTrain of AFW |
| | *Credit Westinghouse RCP Shutdown Seal |
| | *Credit the Diesel Generators on the DeepwellPumps 25 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 & Char g in g Pum p Make-u p Modificationggp pReplacement 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 Building Ke y Locked Isolation Switch in Control Room to Isolate DC Electrical Power to Ke y 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 Equipment 26 Robinson PRA |
| | *Internal Events |
| | -Full Scope ASME/ANS PRA Standard Peer Review in October 2009 |
| | -F&Oswillbe dispositionedintheLARforfirePRAimpact |
| | -F&Os will be dispositioned in 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 used 28 Robinson Fire PRA Overview (Continued)(Continued) |
| | *Credit taken for Flame Retardant Coatin g g-IntumasticInstalled on Thermoplastic Cable |
| | *Unit 2 Cable Spread Room (CSR)/2Sih*E1/E 2 S w i tc hgear Room*Incipient Detection InCabinetInstallationCreditperFAQ08 0046-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 Room 29 RNP Deviations from NRC-Accepted FPRAMethods FPRA 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 tRNP a t RNP 30 Robinson Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCPT credit for spurious failuresYesYesIitiF(FAQ 48)Y Y I gniti on F requency (FAQ-48)Y es Y esIncipient Detection (FAQ-46)YesYes 31 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 iss u e 32 Robinson Project Summary |
| | *Developing committed modifications final scope and hdli sc h e d u li ng*Appendix R non-compliances identified lddd-Compensatory actions imp lemente d as nee d e d*Completed NRC Fire Protection Triennial InspectionNb2012-N ovem b er 2012-No significant findings 33 Questions 34}} |
Letter Sequence Request |
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MONTHYEARML13072B2022013-03-19019 March 2013
Meeting Notice with Duke Energy Concerning NFPA-805 Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants License Amendment Request for Catawba, McGuire, and H. B. Robinson
Project stage: Meeting
ML13127A0802013-04-18018 April 2013
Fleet Fire Protection Program NFPA 805 National Fire Protection Association NFPA 805 Pre-LAR Application for CNS, MNS, RNP
Project stage: Request
ML13127A0502013-05-20020 May 2013
Summary of April 18, 2013, Meeting with Duke Energy Concerning the National Fire Protection Association (NFPA) 805: Performance-Based Standard for Fire Protection for Light Water Reactor Electric Generating Plants
Project stage: Meeting
2013-04-18
[Table View] |
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Category:Meeting Briefing Package/Handouts
MONTHYEARRA-24-0203, Regulatory Conference Supporting Information2024-07-31031 July 2024
Regulatory Conference Supporting Information
ML24143A0612024-05-22022 May 2024
NRC Presentation Slides for Topical Reports to Support SLR (5-22-24 Public Meeting) V2
ML24100A8062024-04-0909 April 2024
Duke Energy Sites Annual Assessment Meeting Presentation Slides April 23, 2024
ML22336A0382022-12-0808 December 2022
Presentation Slides December 8, 2022, pre-submittal Meeting to Discuss Proposed License Amendment Request Regarding TS 3.7.11, Control Room Area Chilled Water System (Cracws)
ML22325A3142022-11-30030 November 2022
November 30, 2022, Pre-Submittal Presentation Slides TSTF-505 and 10 CFR 50.69 (L-2022-LRM-0084)
ML22251A2352022-09-14014 September 2022
Presentation Slides for September 14, 2022, Observation Public Meeting
ML22067A1992022-03-0303 March 2022
Annual Assessment Meeting Presentation
ML22007A2592022-02-0202 February 2022
Presubmittal Licensee Presentation for TS 3.5.3 PIV Testing LAR
ML21336A1422021-12-0707 December 2021
December 7, 2021, Pre-submittal Presentation Slides Regarding Embedded Flaw Repair Relief Request - Revised
ML21327A2112021-11-23023 November 2021
December 7, 2021, Pre-submittal Presentation Regarding Embedded Flaw Repair Relief Request
ML21236A2862021-08-30030 August 2021
License Amendment Request for Revision 1 of DPC-NE-1007-P, Conditional Exemption of the End-of-Cycle (EOC) Moderator Temperature Coefficient (Mtc) Measurement Methodology
ML21167A0852021-06-24024 June 2021
Licensee Presentation for Robinson Pre-submittal Meeting TSTF-577
ML21174A3212021-06-24024 June 2021
Licensee Presentation for Robinson Presubmittal Meeting TSTF 577, Rev. 1
ML21105A7522021-04-15015 April 2021
2020 Robinson - EOC Presentation Slides
ML21116A2542021-04-15015 April 2021
C2R24 Relief Request Pre-Submittal Slides Call 1
ML21089A1732021-03-30030 March 2021
EOC Slides Final
ML21081A1242021-03-22022 March 2021
EOC Slides Final
ML19318F2912019-11-18018 November 2019
Duke Energy Presentation for the Pre-submittal Meeting on November 18, 2019, Regarding the RPV Stud Examination Relief Request
ML19214A0562019-08-0707 August 2019
Presentation: Duke Energy Presubmittal Meeting - August 7, 2019
ML18239A3682018-08-27027 August 2018
License Amendment Request Pre-Submittal Conference Call August 29, 2018
ML18157A0322018-06-0606 June 2018
Nw System LAR Presubmittal Meeting
ML18144A0632018-05-24024 May 2018
Summary of Meeting Concerning Annual Assessment of H.B. Robinson Steam Electric Plant Unit 2 for Period of January 1, 2017 - December 31, 2017
ML18089A0532018-03-30030 March 2018
Summary of Public Meeting with McGuire Nuclear Station
ML17331A6272017-11-29029 November 2017
Duke Energy Pre-Submittal Meeting Presentation, Brunswick, Harris, and Robinson License Amendment Requests Regarding 10 CFR 50.69
ML17278A1342017-10-0404 October 2017
Duke Presentation for Public Meeting 09-20-17
ML17244A2272017-09-0707 September 2017
Duke Energy Presentation - H.B. Robinson 2017-09-07 Pre-sub Transmission Upgrade Meeting
ML16242A2382016-08-30030 August 2016
Catawba/Mcguiproposed Changes to Technical Specification 3.8.1, AC Sources - Operating.
ML16112A2932016-05-0202 May 2016
05/02/2016 Presentation for Closed Pre-Submittal Meeting with Duke Energy Progress, Inc., to Discuss Fuel Reload Design Methodology Reports and Proposed LAR Re. H. B. Robinson And Shearon Harris Plants (CAC Nos. MF7443 And MF7444)
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[Table view] |
Text
Fleet Fire Protection Pro gram gNFPA 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 Pro ject Overview j*License Amendment Request Overview
Participants
- Jeffery Ertman-NFPA 805 Project ManagerDidGfthNFPA805PjtM
- D av id G o f or th -NFPA 805 P ro j ec t Manager*Donna Alexander -Manager Fleet Regulatory Affairs
- BobRishel-PRAManager Bob Rishel PRA Manager*Jeff Robertson -Manager Regulatory Affairs
- Julius Br yant -Re gulator y Affairs y gy*Sarah Chisholm -PRA Engineer
- Kelly Lavin -Site Technical Lead
-Regulatory Affairs
- Jamie McCrory -PRA EngineerBdiWPRAEi*Bran di Weaver -PRA E ng i neer 3 Acronyms*AFW -Alternate Feed Water
- CNS-CatawbaNuclearStation
- MNS -McGuire Nuclear Station
- MOV-MotorOperatedValve CNS 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
- FRE -Fire Risk Evaluation
- FSA -Fire Safety Analysis F&OFtdObti*PORV -Power Operated Relief Valve
- RAI -Request for Additional Information
- RCP -Reactor Coolant Pump RNPRbiNlPlt*F&O -F ac t s an d Observa ti ons*HEAF -High Energy Arcing Fault
- LAR-LicenseAmendmentRequest
- RNP -R o bi nson N uc l ear Pl an t*SSA -Safe Shutdown Analysis
- TDEFWP -Turbine Driven Emergency FeedwaterPump LAR License Amendment Request*LERF -Large Early Release Frequency
- LOOP -Loss of Offsite Power
- UAM -Un-reviewed Analytical Method
- VFDR -Variance From Deterministic Requirements 4
Fleet Transition to NFPA 805MilestonesCNSMNSRNP LAR09/30/201309/30/201309/30/2013SafetyEvaluation09/30/201509/30/201509/30/2015NFPA 805 Program Implementation03/31/201603/31/201603/31/2016 5
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 implementation 6
Catawba Nuclear Station 7
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 status fl-FPRA Quanti fication Comp lete*CNS meets the requirements of acceptability for RG-1.174
-Defense-in-Depth actions in review
-Recovery Action
- Local throttling of Emergency FeedwaterFlow 8
Catawba Project Status (continued)
-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
-4 Breaker Coordination modifications 9
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
- PerformedtoRG1200Revision1
- Performed to RG 1.200 Revision 1-LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2FocusedLERFPeerReviewinDecember2012(NEI05 04)-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 Centers 11 CNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for administrative controls (transients)
- Credit for hot short duration failure probabilities for DC circuits 12 Catawba Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCredit for Admin Controls (Transients)YesYesIgnition Frequency (FAQ-48)YesYesHot Short Duration (DC)YesNo
- 11) 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 Station 15 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
-FPRA Quantification CompleteFPRAQuantificationComplete
- MNS meets the requirements of acceptability for RG-1.174
-FRE Defense-in-Depth review complete
-Recover y Action y*Local Trip of Reactor Coolant Pumps
- Local throttling of Emergency FeedwaterFlow
- Local operation of the PressurizerHeaters 16 McGuire Project Status (continued)
- LAR development in progress
-Eliminate spurious operation of TDEFWP Suction Valve
-Modify condensate drain from containment to improve overall LERF
-Current Transformer Modification
-PressurizerHeaterModificationPressurizerHeater Modification 17 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
- PerformedtoRG1200Revision1
- Performed to RG 1.200 Revision 1-LAR technical adequacy statement will address any deltas to RG 1.200 Revision 2FocusedLERFPeerReviewinDecember2012(NEI05 04)-Focused LERF Peer Review in December 2012 (NEI 05-04)-F&Os from these reviews will be dispositionedin the LAR for fire PRA impact 18 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 Centers 19 MNS Deviations from NRC-Accepted FPRA MethodsMethods*Credit for hot short duration failure probabilities for DCii DC c ircu i ts 20 McGuire Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskHot Short Duration (DC)YesNo 1 ()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 findings 22 Robinson Nuclear Plant 23 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 re quests -Clarification of Prior NRC A pprovals q pp*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 Completed 24 Robinson Proposed Modifications
- Electrically Coordinate Power Supplies
- HEAF mitigation modification in E1/E2 Switchgear room*Protect Shutdown Valves
- Credit Westinghouse RCP Shutdown Seal
- Credit the Diesel Generators on the DeepwellPumps 25 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 & Char g in g Pum p Make-u p Modificationggp pReplacement 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 Building Ke y Locked Isolation Switch in Control Room to Isolate DC Electrical Power to Ke y 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 Equipment 26 Robinson PRA
-Full Scope ASME/ANS PRA Standard Peer Review in October 2009
-F&Oswillbe dispositionedintheLARforfirePRAimpact
-F&Os will be dispositioned in 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 used 28 Robinson Fire PRA Overview (Continued)(Continued)
- Credit taken for Flame Retardant Coatin g g-IntumasticInstalled on Thermoplastic Cable
- Unit 2 Cable Spread Room (CSR)/2Sih*E1/E 2 S w i tc hgear Room*Incipient Detection InCabinetInstallationCreditperFAQ08 0046-In-Cabinet Installation -Credit per FAQ 08-0046*Main Control Boards
-Area Wide -Normal Detection Credit
- Unit 2 Cable Spread Room 29 RNP Deviations from NRC-Accepted FPRAMethods FPRA 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 tRNP a t RNP 30 Robinson Fire PRA SensitivitiesSensitivityFPRA CDF/LERFVFDR RiskCPT credit for spurious failuresYesYesIitiF(FAQ 48)Y Y I gniti on F requency (FAQ-48)Y es Y esIncipient Detection (FAQ-46)YesYes 31 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 iss u e 32 Robinson Project Summary
- Developing committed modifications final scope and hdli sc h e d u li ng*Appendix R non-compliances identified lddd-Compensatory actions imp lemente d as nee d e d*Completed NRC Fire Protection Triennial InspectionNb2012-N ovem b er 2012-No significant findings 33 Questions 34
