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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
{{#Wiki_filter:Brunswick Nuclear Plant Units 1 and 2 TS 3.8.1 Diesel Generator Completion Time Extension License Amendment Request Pre-Submittal Meeting June 7, 2012
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
Agenda Introductions / Opening Remarks License Amendment Request (LAR) Overview Project Overview Probabilistic Risk Assessment (PRA) Overview 2
-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.
Introduction/Opening Remarks Nuclear Safety - Emergency AC Power EDG Collector Rings Switchyard Breaker/Panel/Relay Replacements 27SX-1 Relay UV/DUV Relays Switchyard Insulator Coatings Air Start Modification 14 Dayy LCO EDG 3
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)
LAR Overview - Proposed Change Extend Technical Specification Diesel Generator (DG) Completion Time (CT) from 7 days to 14 days Branch Technical Position (BTP) 8-8 LAR supported by PRA BNP installing a 4MW non-safety Supplemental DG (SUPP-DG)
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
Capacity to bring affected unit to Cold Shutdown Capable of powering E  E-bus bus within 1 hour of SBO event Technical Specifications include:
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
Verify availability of SUPP-DG before entering extended CT A il bili off SUPP Availability  SUPP-DG DG checked h k d once per shift hif Action should SUPP-DG become unavailable during extended CT Monthly Test 4
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)
Emergency Diesel Generator Improvement p                                         Actions EDG Actions Action                          2007 2008  2009 2010  2011      2012          2013          2014        2015      2016          2017  2018 EDG #2 Exhaust Bellows                                                                                            Completed Allen Bradley Relays                                                                                              Working Jacket Water TCV's                                                                                                Scheduled SAMG DG's Capacitor Leakage EDG PM Evaluations Ultra Low Sulfur Fuel Latent Design Issues Human Performance Issues High Quality Potentiometers GEMCO Control Switches Clean Fuel Tanks Refurbish JW Coolers Voltage Reg Replacement                                      Eng/Procure      Planning        Install    Install  Install      Install Air Start Configuration                                      Eng/Plan/Install  Install Collector Ring Replacement Governor Replacement                                          Eng/Planning Eng/Planning        Install    Install  Install 14 Day EDG LCO                                                Eng/Planning      Install EDG PM Optimization Rebuild Turbo Critical Spare Parts (Identify)
Application ApplicationNUREG 6850Used Acce p ted Alternatives (e.g., FAQ 08-0046
(Identif )
)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}}
Spare Generator                                                Procure          Fab        Receive Generator Inspection                                          Eng/Planning Eng/Planning      Inspect    Inspect Data Acquisition                                              Eng/Planning Eng/Planning        Install Digital Relays                                                    Study                    Eng/Planning  Install  Install Replace FO Buried Piping                                      Eng/Planning      Install New Safety Maintenance DG                                    Spec p Dvpmt  p          Hold. Pending Fukishima recommendation resolution.
Loadbank to Support Online LOOP/LOCA Equivalent                                                                        Eng/Planning  Install 5
 
Project Overview Project Status & Schedule Note: Automatic Voltage Regulator (AVR) 6
 
PRA Overview PRA Includes: Internal Events, Internal Flooding, E t External l Events, E   t High Hi h Wi Winds, d E External t   l Fl Flooding, di   Fi Fire All Completed Peer Reviews against ANS/ASME PRA Standard and RG 1 1.200 200 R2 Seismic has qualitative assessment 7
 
PRA Overview Results of Emergency Diesel Generator (EDG)
Allowed Outage Time (AOT) Risk Evaluation Risk Metric Results Risk Metric Unit 1      Unit 2 Total CDF        4.2E-05      4.1E-05 Total CDF      8.5E-07      8.3E-07 Total LERF      3.7E-06      2.5E-06 Total LERF     4 8E-09 4.8E-09      6 2E-09 6.2E-09 Total ICCDP      4.3E-07      4.1E-07 Total ICLERP    2.0E-09      3.5E-09 8
 
PRA Overview Brunswick Nuclear Plant (BNP) Internal Events Peer Review June 2010 All Supporting Requirements (SR) Reviewed Resolved to Capability Category (CC) II except for 7 Findings and Observations (F&Os) 4D  Documentation t ti iissues 3 LERF SRs at CCI 9
 
PRA Overview BNP External Events High Winds/External Flooding Peer Review January 2012 All Supporting Requirements Reviewed High Winds 3 F&Os remain on documentation External Flooding All F&Os resolved 10
 
PRA Overview Significant External Events Conservatisms High Winds/ External Flooding Some Operator Actions could be Credited 11
 
Fire PRA Fire PRA Overview Important Fire Areas and Scenarios Fire PRA Peer Review Current Status 12
 
Fire PRA Overview Methods Similar to Harris Nuclear Plant (HNP)
Application NUREG 6850 p
Used Accepted    Alternatives ((e.g.,
g , FAQ 08-0046))
RG 1.200 Peer Review Process Methods Beyond NUREG/CR-6850 The 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 Cabinets Method was Used to Address RAI 5-32 for the HNP NFPA-805 Application 13
 
Fire PRA Overview Significant Efforts Bus Ducts and Below Ground Cable Ducts p
Electrical Coordination of PRA Components Walkdowns and Related Documentation Significant Conservatism No Credit taken for Flame Retardant Coating Installed on Thermoset Cable Cable Spread Room (CSR)
Diesel Generator Building Basement 14
 
Fire PRA Overview Incipient Detection Main Control Boards - Credit per FAQ 08-0046 CSR Area Wide - Normal Detection Credit Crediting Existing Solid Bottom Trays to Delay Damage Per NUREG/CR-6850 15
 
Important Fire Areas and Scenarios Cable Spread Room Control Room Abandonment Detailed Human Reliability Analysis (HRA)
Control Room g
Turbine Building Battery Rooms Switchgear Rooms 16
 
Fire PRA Peer Review Fire PRA Peer Review Peer Review December 2011 Performed by Boiling Water Reactor Owners G
Group per NEI 07-12 07 12 PProcess Incorporated Findings Resulted in Improved Core Damage Frequency Greater than 50% improvement 17
 
Fire PRA Status One Modification Credited Additional Fire Modeling Diesel Generator Building Basement Main Control Room Cable Spread Room 18
 
Questions 19}}

Revision as of 02:42, 12 November 2019

06/07/12 Meeting Slides for Pre-Application Meeting with Carolina Power and Light Company Regarding Emergency Diesel Generator Completion Time Extension for Brunswick Steam Electric Plant, Units 1 and 2
ML12158A344
Person / Time
Site: Brunswick  Duke Energy icon.png
Issue date: 06/06/2012
From:
Progress Energy Co
To: Farideh Saba
Plant Licensing Branch II
Saba, Farideh
References
Download: ML12158A344 (19)
v • d • e


Text

Brunswick Nuclear Plant Units 1 and 2 TS 3.8.1 Diesel Generator Completion Time Extension License Amendment Request Pre-Submittal Meeting June 7, 2012

Agenda Introductions / Opening Remarks License Amendment Request (LAR) Overview Project Overview Probabilistic Risk Assessment (PRA) Overview 2

Introduction/Opening Remarks Nuclear Safety - Emergency AC Power EDG Collector Rings Switchyard Breaker/Panel/Relay Replacements 27SX-1 Relay UV/DUV Relays Switchyard Insulator Coatings Air Start Modification 14 Dayy LCO EDG 3

LAR Overview - Proposed Change Extend Technical Specification Diesel Generator (DG) Completion Time (CT) from 7 days to 14 days Branch Technical Position (BTP) 8-8 LAR supported by PRA BNP installing a 4MW non-safety Supplemental DG (SUPP-DG)

Capacity to bring affected unit to Cold Shutdown Capable of powering E E-bus 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 event Technical Specifications include:

Verify availability of SUPP-DG before entering extended CT A il bili off SUPP Availability SUPP-DG DG checked h k d once per shift hif Action should SUPP-DG become unavailable during extended CT Monthly Test 4

Emergency Diesel Generator Improvement p Actions EDG Actions Action 2007 2008 2009 2010 2011 2012 2013 2014 2015 2016 2017 2018 EDG #2 Exhaust Bellows Completed Allen Bradley Relays Working Jacket Water TCV's Scheduled SAMG DG's Capacitor Leakage EDG PM Evaluations Ultra Low Sulfur Fuel Latent Design Issues Human Performance Issues High Quality Potentiometers GEMCO Control Switches Clean Fuel Tanks Refurbish JW Coolers Voltage Reg Replacement Eng/Procure Planning Install Install Install Install Air Start Configuration Eng/Plan/Install Install Collector Ring Replacement Governor Replacement Eng/Planning Eng/Planning Install Install Install 14 Day EDG LCO Eng/Planning Install EDG PM Optimization Rebuild Turbo Critical Spare Parts (Identify)

(Identif )

Spare Generator Procure Fab Receive Generator Inspection Eng/Planning Eng/Planning Inspect Inspect Data Acquisition Eng/Planning Eng/Planning Install Digital Relays Study Eng/Planning Install Install Replace FO Buried Piping Eng/Planning Install New Safety Maintenance DG Spec p Dvpmt p Hold. Pending Fukishima recommendation resolution.

Loadbank to Support Online LOOP/LOCA Equivalent Eng/Planning Install 5

Project Overview Project Status & Schedule Note: Automatic Voltage Regulator (AVR) 6

PRA Overview PRA Includes: Internal Events, Internal Flooding, E t External l Events, E t High Hi h Wi Winds, d E External t l Fl Flooding, di Fi Fire All Completed Peer Reviews against ANS/ASME PRA Standard and RG 1 1.200 200 R2 Seismic has qualitative assessment 7

PRA Overview Results of Emergency Diesel Generator (EDG)

Allowed Outage Time (AOT) Risk Evaluation Risk Metric Results Risk Metric Unit 1 Unit 2 Total CDF 4.2E-05 4.1E-05 Total CDF 8.5E-07 8.3E-07 Total LERF 3.7E-06 2.5E-06 Total LERF 4 8E-09 4.8E-09 6 2E-09 6.2E-09 Total ICCDP 4.3E-07 4.1E-07 Total ICLERP 2.0E-09 3.5E-09 8

PRA Overview Brunswick Nuclear Plant (BNP) Internal Events Peer Review June 2010 All Supporting Requirements (SR) Reviewed Resolved to Capability Category (CC) II except for 7 Findings and Observations (F&Os) 4D Documentation t ti iissues 3 LERF SRs at CCI 9

PRA Overview BNP External Events High Winds/External Flooding Peer Review January 2012 All Supporting Requirements Reviewed High Winds 3 F&Os remain on documentation External Flooding All F&Os resolved 10

PRA Overview Significant External Events Conservatisms High Winds/ External Flooding Some Operator Actions could be Credited 11

Fire PRA Fire PRA Overview Important Fire Areas and Scenarios Fire PRA Peer Review Current Status 12

Fire PRA Overview Methods Similar to Harris Nuclear Plant (HNP)

Application NUREG 6850 p

Used Accepted Alternatives ((e.g.,

g , FAQ 08-0046))

RG 1.200 Peer Review Process Methods Beyond NUREG/CR-6850 The 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 Cabinets Method was Used to Address RAI 5-32 for the HNP NFPA-805 Application 13

Fire PRA Overview Significant Efforts Bus Ducts and Below Ground Cable Ducts p

Electrical Coordination of PRA Components Walkdowns and Related Documentation Significant Conservatism No Credit taken for Flame Retardant Coating Installed on Thermoset Cable Cable Spread Room (CSR)

Diesel Generator Building Basement 14

Fire PRA Overview Incipient Detection Main Control Boards - Credit per FAQ 08-0046 CSR Area Wide - Normal Detection Credit Crediting Existing Solid Bottom Trays to Delay Damage Per NUREG/CR-6850 15

Important Fire Areas and Scenarios Cable Spread Room Control Room Abandonment Detailed Human Reliability Analysis (HRA)

Control Room g

Turbine Building Battery Rooms Switchgear Rooms 16

Fire PRA Peer Review Fire PRA Peer Review Peer Review December 2011 Performed by Boiling Water Reactor Owners G

Group per NEI 07-12 07 12 PProcess Incorporated Findings Resulted in Improved Core Damage Frequency Greater than 50% improvement 17

Fire PRA Status One Modification Credited Additional Fire Modeling Diesel Generator Building Basement Main Control Room Cable Spread Room 18

Questions 19

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