ML12158A344: Difference between revisions
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{{#Wiki_filter:BrunswickNuclearPlant Brunswick Nuclear Plant Units 1 and 2 TS 3.8.1 Diesel Generator CompletionTimeExtension Completion Time ExtensionLicense Amendment Request Pre-Submittal Meeting June 7, 2012 Agenda AgendaIntroductions / Opening RemarksLicense Amendment Request (LAR) OverviewProject OverviewProbabilistic Risk Assessment (PRA) Overview 2 | |||
Introduction/Opening RemarksNuclearSafety | |||
-EmergencyACPowerEDG Collector Rings Nuclear Safety Emergency AC Power Switchyard Breaker/Panel/Relay | |||
Replacements 27SX-1 RelayUV/DUVRelays UV/DUV RelaysSwitchyard Insulator Coatings Air Start Modification 14 Da y LCO EDG y 3 LAROverview | |||
-ProposedChangeExtend Technical Specification Diesel Generator (DG) Completion Time (CT) from 7 days to 14 days LAR Overview Proposed ChangeBranch Technical Position (BTP) 8-8LARsupportedbyPRALAR supported by PRABNP installing a 4MW non-safety Supplemental DG (SUPP-DG)Capacity to bring affected unit to Cold ShutdownCapableofpoweringEbuswithin1hourofSBOeventCapable of powering E-bus within 1 hour of SBO eventTechnical Specifications include:Verify availability of SUPP-DG before entering extended CTAilbilifSUPPDGhkdhifA va il a bility o f SUPP-DG c h ec k e d once per s hif t Action should SUPP-DG become unavailable during extended CTMonthly Test 4 | |||
Emergency Diesel Generator Im p rovement Actions pAction200720082009201020112012201320142015201620172018EDG #2 Exhaust BellowsAllenBradleyRelaysEDG ActionsCompletedWorkingAllen Bradley RelaysJacket Water TCV'sSAMG DG'sCapacitor LeakageEDG PM EvaluationsUltra Low Sulfur FuelLatent Design IssuesScheduledWorkingHuman Performance Issues High Quality PotentiometersGEMCO Control SwitchesClean Fuel TanksRefurbish JW CoolersVoltage Reg ReplacementEng/ProcurePlanningInstallInstallInstallInstallAir Start ConfigurationEng/Plan/InstallInstallCollector Ring ReplacementGovernor ReplacementEng/PlanningEng/PlanningInstallInstallInstall14 Day EDG LCOEng/PlanningInstallEDG PM OptimizationRebuild TurboCriticalSpareParts(Identif)Critical Spare Parts (Identif y)Spare GeneratorProcureFabReceiveGenerator InspectionEng/PlanningEng/PlanningInspectInspectData AcquisitionEng/PlanningEng/PlanningInstallDigital RelaysStudyEng/PlanningInstallInstallReplace FO Buried PipingEng/PlanningInstallNewSafetyMaintenanceDG S pec Dv p mtHold.PendingFukishimarecommendationresolution. | |||
5New Safety Maintenance DG ppLoadbank to Support Online LOOP/LOCA EquivalentEng/PlanningInstallHold. Pending Fukishima recommendation resolution. | |||
ProjectOverview Project OverviewProject Status & Schedule 6Note: Automatic Voltage Regulator (AVR) | |||
PRAOverview PRA OverviewPRA Includes: Internal Events, Internal Flooding, EtlEtHihWidEtlFldiFi E x t erna l E ven t s, Hi g h Wi n d s, E x t erna l Fl oo di ng, Fi reAll Completed Peer Reviews against ANS/ASME PRA StandardandRG1200R2 Standard and RG 1.200 R2Seismic has qualitative assessment 7 | |||
PRAOverview PRA OverviewResultsofEmergencyDieselGenerator(EDG)RiskMetricResultsResults of Emergency Diesel Generator (EDG) Allowed Outage Time (AOT) Risk Evaluation Risk Metric Risk Metric ResultsUnit 1Unit 2Total CDF4.2E-054.1E-05Total CDF8.5E-078.3E-07Total LERF3.7E-062.5E-06TotalLERF48E-0962E-09Total LERF 4.8E-09 6.2E-09Total ICCDP4.3E-074.1E-07 Total ICLERP2.0E-093.5E-09 8 | |||
PRAOverview PRA OverviewBrunswick Nuclear Plant (BNP) Internal EventsPeer Review June 2010 All Supporting Requirements (SR) ReviewedResolved to Capability Category (CC) II except for 7 Findings and Observations (F&Os)4Dttii4 D ocumen t a ti on i ssues3 LERF SRs at CCI 9 | |||
PRAOverview PRA OverviewBNP External EventsHigh Winds/External FloodingPeerReviewJanuary2012Peer Review January 2012All Supporting Requirements ReviewedHighWindsHigh Winds 3 F&Os remain on documentationExternalFloodingExternal FloodingAll F&Os resolved 10 PRAOverview PRA OverviewSignificant External Events ConservatismsHigh Winds/ External FloodingSomeOperatorActionscouldbeCreditedSome Operator Actions could be Credited 11 FirePRA Fire PRAFire PRA OverviewImportant Fire Areas and Scenarios FirePRAPeerReviewFire PRA Peer ReviewCurrent Status 12 FirePRAOverview Fire PRA OverviewMethods Similar to Harris Nuclear Plant (HNP) | |||
Application ApplicationNUREG 6850Used Acce p ted Alternatives (e.g., FAQ 08-0046 | |||
)p(g,)RG 1.200 Peer Review ProcessMethods Beyond NUREG/CR-6850The BNP Fire PRA calculates using:A Severity Factor 0.1, Where 90% of the Fires are Contained Within the Motor Control Centers (MCC)Heat Release Rate (HRR) Severity Factors are Treated Independently, Similar to Other CabinetsMethod was Used to Address RAI 5-32 for the HNP NFPA-805 Application 13 FirePRAOverview Fire PRA OverviewSignificant EffortsBus Ducts and Below Ground Cable DuctsElectrical Coordination of PRA Com p onents pWalkdowns and Related Documentation Significant Conservatism No Credit taken for Flame Retardant Coating Installed on ThermosetCableCable Spread Room (CSR)Diesel Generator Building Basement 14 FirePRAOverview Fire PRA OverviewIncipient DetectionMain Control Boards -Credit per FAQ 08-0046CSR Area Wide -Normal Detection Credit Crediting Existing Solid Bottom Trays to DelayDamage Delay Damage Per NUREG/CR-6850 15 ImportantFireAreasandScenarios Important Fire Areas and ScenariosCable Spread RoomControl Room AbandonmentDetailed Human Reliability Analysis (HRA)Control RoomTurbine Buildin g gBattery RoomsSwitchgearRoomsSwitchgear Rooms 16 FirePRAPeerReview Fire PRA Peer ReviewFire PRA Peer Review Peer Review December 2011 Performed by Boiling Water Reactor Owner's GNEI0712P G roup per NEI 07-12 P rocessIncorporated Findings Resulted in Improved CoreDamageFrequency Core Damage FrequencyGreater than 50% improvement 17 FirePRAStatus Fire PRA StatusOne Modification CreditedAdditional Fire ModelingDiesel Generator Building BasementMain Control RoomCable Spread Room 18 Questions 19}} | |||
Revision as of 01:25, 2 August 2018
| ML12158A344 | |
| Person / Time | |
|---|---|
| Site: | Brunswick  |
| Issue date: | 06/06/2012 |
| From: | Progress Energy Co |
| To: | Saba F E Plant Licensing Branch II |
| Saba, Farideh | |
| References | |
| Download: ML12158A344 (19) | |
Text
BrunswickNuclearPlant Brunswick Nuclear Plant Units 1 and 2 TS 3.8.1 Diesel Generator CompletionTimeExtension Completion Time ExtensionLicense Amendment Request Pre-Submittal Meeting June 7, 2012 Agenda AgendaIntroductions / Opening RemarksLicense Amendment Request (LAR) OverviewProject OverviewProbabilistic Risk Assessment (PRA) Overview 2
Introduction/Opening RemarksNuclearSafety
-EmergencyACPowerEDG Collector Rings Nuclear Safety Emergency AC Power Switchyard Breaker/Panel/Relay
Replacements 27SX-1 RelayUV/DUVRelays UV/DUV RelaysSwitchyard Insulator Coatings Air Start Modification 14 Da y LCO EDG y 3 LAROverview
-ProposedChangeExtend Technical Specification Diesel Generator (DG) Completion Time (CT) from 7 days to 14 days LAR Overview Proposed ChangeBranch Technical Position (BTP) 8-8LARsupportedbyPRALAR supported by PRABNP installing a 4MW non-safety Supplemental DG (SUPP-DG)Capacity to bring affected unit to Cold ShutdownCapableofpoweringEbuswithin1hourofSBOeventCapable of powering E-bus within 1 hour1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br /> of SBO eventTechnical Specifications include:Verify availability of SUPP-DG before entering extended CTAilbilifSUPPDGhkdhifA va il a bility o f SUPP-DG c h ec k e d once per s hif t Action should SUPP-DG become unavailable during extended CTMonthly Test 4
Emergency Diesel Generator Im p rovement Actions pAction200720082009201020112012201320142015201620172018EDG #2 Exhaust BellowsAllenBradleyRelaysEDG ActionsCompletedWorkingAllen Bradley RelaysJacket Water TCV'sSAMG DG'sCapacitor LeakageEDG PM EvaluationsUltra Low Sulfur FuelLatent Design IssuesScheduledWorkingHuman Performance Issues High Quality PotentiometersGEMCO Control SwitchesClean Fuel TanksRefurbish JW CoolersVoltage Reg ReplacementEng/ProcurePlanningInstallInstallInstallInstallAir Start ConfigurationEng/Plan/InstallInstallCollector Ring ReplacementGovernor ReplacementEng/PlanningEng/PlanningInstallInstallInstall14 Day EDG LCOEng/PlanningInstallEDG PM OptimizationRebuild TurboCriticalSpareParts(Identif)Critical Spare Parts (Identif y)Spare GeneratorProcureFabReceiveGenerator InspectionEng/PlanningEng/PlanningInspectInspectData AcquisitionEng/PlanningEng/PlanningInstallDigital RelaysStudyEng/PlanningInstallInstallReplace FO Buried PipingEng/PlanningInstallNewSafetyMaintenanceDG S pec Dv p mtHold.PendingFukishimarecommendationresolution.
5New Safety Maintenance DG ppLoadbank to Support Online LOOP/LOCA EquivalentEng/PlanningInstallHold. Pending Fukishima recommendation resolution.
ProjectOverview Project OverviewProject Status & Schedule 6Note: Automatic Voltage Regulator (AVR)
PRAOverview PRA OverviewPRA Includes: Internal Events, Internal Flooding, EtlEtHihWidEtlFldiFi E x t erna l E ven t s, Hi g h Wi n d s, E x t erna l Fl oo di ng, Fi reAll Completed Peer Reviews against ANS/ASME PRA StandardandRG1200R2 Standard and RG 1.200 R2Seismic has qualitative assessment 7
PRAOverview PRA OverviewResultsofEmergencyDieselGenerator(EDG)RiskMetricResultsResults of Emergency Diesel Generator (EDG) Allowed Outage Time (AOT) Risk Evaluation Risk Metric Risk Metric ResultsUnit 1Unit 2Total CDF4.2E-054.1E-05Total CDF8.5E-078.3E-07Total LERF3.7E-062.5E-06TotalLERF48E-0962E-09Total LERF 4.8E-09 6.2E-09Total ICCDP4.3E-074.1E-07 Total ICLERP2.0E-093.5E-09 8
PRAOverview PRA OverviewBrunswick Nuclear Plant (BNP) Internal EventsPeer Review June 2010 All Supporting Requirements (SR) ReviewedResolved to Capability Category (CC) II except for 7 Findings and Observations (F&Os)4Dttii4 D ocumen t a ti on i ssues3 LERF SRs at CCI 9
PRAOverview PRA OverviewBNP External EventsHigh Winds/External FloodingPeerReviewJanuary2012Peer Review January 2012All Supporting Requirements ReviewedHighWindsHigh Winds 3 F&Os remain on documentationExternalFloodingExternal FloodingAll F&Os resolved 10 PRAOverview PRA OverviewSignificant External Events ConservatismsHigh Winds/ External FloodingSomeOperatorActionscouldbeCreditedSome Operator Actions could be Credited 11 FirePRA Fire PRAFire PRA OverviewImportant Fire Areas and Scenarios FirePRAPeerReviewFire PRA Peer ReviewCurrent Status 12 FirePRAOverview Fire PRA OverviewMethods Similar to Harris Nuclear Plant (HNP)
Application ApplicationNUREG 6850Used Acce p ted Alternatives (e.g., FAQ 08-0046
)p(g,)RG 1.200 Peer Review ProcessMethods Beyond NUREG/CR-6850The BNP Fire PRA calculates using:A Severity Factor 0.1, Where 90% of the Fires are Contained Within the Motor Control Centers (MCC)Heat Release Rate (HRR) Severity Factors are Treated Independently, Similar to Other CabinetsMethod was Used to Address RAI 5-32 for the HNP NFPA-805 Application 13 FirePRAOverview Fire PRA OverviewSignificant EffortsBus Ducts and Below Ground Cable DuctsElectrical Coordination of PRA Com p onents pWalkdowns and Related Documentation Significant Conservatism No Credit taken for Flame Retardant Coating Installed on ThermosetCableCable Spread Room (CSR)Diesel Generator Building Basement 14 FirePRAOverview Fire PRA OverviewIncipient DetectionMain Control Boards -Credit per FAQ 08-0046CSR Area Wide -Normal Detection Credit Crediting Existing Solid Bottom Trays to DelayDamage Delay Damage Per NUREG/CR-6850 15 ImportantFireAreasandScenarios Important Fire Areas and ScenariosCable Spread RoomControl Room AbandonmentDetailed Human Reliability Analysis (HRA)Control RoomTurbine Buildin g gBattery RoomsSwitchgearRoomsSwitchgear Rooms 16 FirePRAPeerReview Fire PRA Peer ReviewFire PRA Peer Review Peer Review December 2011 Performed by Boiling Water Reactor Owner's GNEI0712P G roup per NEI 07-12 P rocessIncorporated Findings Resulted in Improved CoreDamageFrequency Core Damage FrequencyGreater than 50% improvement 17 FirePRAStatus Fire PRA StatusOne Modification CreditedAdditional Fire ModelingDiesel Generator Building BasementMain Control RoomCable Spread Room 18 Questions 19