ML18123A479

Nea Operational Experience Paris 2018

ML18123A479
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Issue date:	04/26/2018
From:	John Lane NRC/RES/DRA/PRB
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lane John 415-2476
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U.S. NRC OperationalExperienceData Collection ProgramNEA Workshopon theUse of Operational Experience in PSAApril 26-27 2018John C LaneOffice of Nuclear Regulatory ResearchU.S. NRC Topics of DiscussionRecognition of Importance of OpE dataWhere does U.S. OpE data come from?How is OpE data gathered, coded, analyzed?Where is OpE data housed?Who uses OpE data?2 WASH-1400 (1975)Mid-1stcomputer file of Reportable Documented the need for comprehensive OpENuclear Plant Reliability Data System (NPRDS)Managed by Southwest Research Institute for Edison Electric Institute (1974)Voluntary industry initiativeEngr & failure data on components3

-President Jimmy Carter -1977-mandatory the current voluntary reporting of minor mishaps and component failures at operating reactors, in order to develop the reliable data base needed to improve reactor design and operating NUREG-0161-LER Data Entry Guidance for Tech Formalized in LER Rule (1983, 10 CFR 50.73)Originally managed at ORNL via the Sequence Coding Search System (SCSS, 1984)Idaho National Lab has managed since 20004 LER Reporting5Reportable Events require submission within 60 days:PlantshutdownresultingfromaTechnicalSpecificationrequirementOperationsorplantconditionsprohibitedbyTechSpecsSafetybarriersdegradedApreviouslyunanalyzedconditionAnaturalphenomenaposingathreattothefacilityManualorautomaticreactorscram(except pre-planned scrams)Inadvertentactuationof:ContainmentIsolationSystemECCSEmergency dieselgeneratorsContainmentheatremovalsystemEmergency service water system LER Search6 Maintenance Rule-1991 (10CFR50.65)Required additional OpE capability to track component failures in safety and non-safety systemsUse OpE to help set performance goalsPRA Policy STMT--1995INPO (Institute for Nuclear Power Operations)EPIX-1998 (Equip Performance & Information Exchange)Voluntary Upgrade and expansion of NPRDS (managed by INPO since 1982)7 MSPI-Mitigating Systems Performance Index (2005)Monitor(s) the performance of 5 systems based on their ability to perform risk-significant functionsHP coolant injection/core spray/safety injectionRx Core Isolation Cooling/Emergency FeedwaterResidual Heat Removal Emergency AC powerCooling water support systemAttempts to balance the need for maintenance (availability) with equipment performance (reliability)8 92018 Publicly Available Data Summarieshttp://nrcoe.inl.gov/resultsdb/10 Primary Data Source for Reliability DataEquipment failure data captured in the INPO Consolidated Events Database (ICES)Formerly EPIX (prior to 2013)Data from 1998 transition from NPRDSSupports data for:Maintenance RuleMitigating Systems Performance Index (MSPI)Reactor Oversight Process (ROP)Data is proprietary, only accessible by INPO membersData is input by each utility in the U.S.Amount of data provided varies by utilityAll provide required MSPI data, but some provide significantly moreIncludes demand and run time data for some systems11 RADS (Reliability & Availability Data System)INL Computer ProgramUses either plant-specific or generic dataReliability (failures per demand probability/failure rate to operate)Train or component level data on unavailability (planned/unplanned unavailability) due to test and maintenanceUsed by NRC staff and industry for submission of licensing action requestsProvides reliability parameters for SPAR modelsHelps focus NRC inspections on the most risk significant systemsAids in the review of requests for unit-specific licensing actionsMonitors maintenance rule implementationSupports reliability analyses of risk-significant systems/components12 Primary Data Source for Initiating Events13Licensee Event Reports (LERs)Reports required to be submitted to the NRC per Event Report Guidance provided in NUREG-1022Primary source of initiating events informationSignificant safety system failures are reportedEvent Notification Reports (ENs) (10 CFR 50.72)Inspection Reports (IRs) Monthly Operating Reports (MORs)Primary source of operating time dataRequired by NRC Generic Letter 97-02 Initiating Event StudiesReview all unexpected reactor trips during power operationsEach event is categorized according to the initial plant fault and functional impactThe collected data are analyzed for time dependence, reactor-type dependence, and between-plant varianceDependencies and trends are reported, along with the raw counts and the best estimate for initiating event frequencies

References:

NUREG/CR-5750 "Rates of Initiating Events at U.S. Nuclear Power Plants: 1987-NUREG/CR-6928, Industry-Average Performance for Components and Initiating Events at U.S. Commercial Nuclear Power Plants14 Loss of offsite power Loss of vital AC bus Loss of vital DC bus Very small LOCA Loss of Component Cooling Water Loss of feedwater Partial Loss of Service Water BWR loss of instrument air BWR stuck open SRV BWR loss of heat sink BWR general transients PWR loss of instrument air PWR steam generator tube rupture PWR stuck open SRV PWR loss of heat sink PWR general transients Categories of Initiating Events15 Fire Events Data BaseNRC/EPRI developed Fire Events Database in 2011 from:Event Notifications and LERs from 1990 to presentNew fire events added to the INPO ICES databaseSupports:Development of Fire PRA Initiating Event FrequenciesIndustry compliance with NFPA 805 (National Fire Protection Assoc)NRR Fire Metrics16 Component StudiesTasks:Risk analysis of operating dataEngineering analysis of trendsProvides insights into the performance of components on an industry-wide basis Emergency Diesel Generators (EDG) Turbine-Driven Pumps (TDP) Motor-Driven Pumps (MDP) Air-Operated Valves (AOV) Motor-Operated Valves (MOV) 17 System Reliability StudiesBoiling Water Reactor Systems:High Pressure Coolant Injection (HPCI) System High Pressure Core Spray (HPCS) System Isolation Condenser (IC) System Reactor Core Isolation Cooling (RCIC) System Pressurized Water Reactor Systems:Auxiliary Feedwater (AFW) System High Pressure Safety Injection (HPSI) System Common System:Emergency Power System 18 Common Cause Failure StudiesCommon-Cause Failure Database includes:method for identifying CCF eventscoding and classification of events for use in CCF studiescomputer system for storing and analyzing the dataCCF events are component failures that satisfy four criteria:Two or more individual components fail, are degraded or have deficiencies that would result in component failures if a demand signal had been receivedComponents fail within a selected period of time such that success of the mission would be uncertainComponents fail because of a single shared cause and coupling mechanismComponents fail within the established component boundary19 CCF (continued)Studies:emergency diesel generatorsmotor-operated valvesmotor-driven pumpscircuit breakers

Reference:

"Common-Cause Failure Event Insights" (NUREG/CR-6819), Volumes 1 through 4 (2003)20 21 guidance for completing each field in the IDCCS The IDCCS program utilizes numerous lookup tables and automated checks to ensure data consistency Records are entered by qualified coding engineers Each record is independently checked by a second qualified coding engineer The IDCCS software randomly selects a sample of records for an independent quality review semi-annuallyData Quality Controls22 NRCEquipmentReliability DatabaseSampleInput23 NRC/Industry Uses for OpE DataNRC/RESSPAR ModelsAccident Sequence Precursor ProgramNRC/NRRMitigating System Performance IndexOperating Experience ClearinghouseRegional InspectorsSignificance Determination Process/SRAsIndustry/PublicReference material for plant-specific PRA modelsLERSearch24 25 26NRC OpE ClearinghouseScreeningCommunicationEvaluationApplicationIncident Reporting System (IRS)International Nuclear Event Scale(INES)Bilateral ExchangesInternational OpEDaily Event Reports *Plant Status Reports *Licensee Event Reports *Part 21 Reports *INPO ReportsDomestic OpE: IndustryInspection Findings *Preliminary Notifications *Regional Project CallsConstruction ExperienceStudies/TrendsDomestic OpE: NRCOpE ClearinghouseGeneric Communications *OpE BriefingsCOMMunicationsPeriodic OpE NewsletterOpE NotesNotable OpETech Review Group ReportInforming StakeholdersInspection *Licensing *Influencing Agency programsRulemaking *Information Request *Taking Regulatory ActionsStorageOpE ProgramInputsProducts* Available on the public NRC Web Page Screening-NRR-NRO Reactor Operating Experience ProgramTiered response/dispositionFormal screen in Issue for ResolutionStaff follow-up and summary OpE COMMunicationEmail issue Technical Review Group NoteInformation only No Action 27 CommunicationsGeneric and Safety Significant issues may warrant noticeExamples:Information NoticeGeneric LetterRegulatory Issues SummaryPublication of OpE study28 Coordinated International ActivitiesRelationship focused(WGOE)International Common Cause Database (ICDE)29