EPRI/NRC-RES PRA Volume 1: Summary & Overview
EPRI 1011989NUREG/CR-6850Final ReportEPRI/NRC-RESFire PRA Methodology for NuclearPower FacilitiesVolume 1: Summary & OverviewElectric Power Research Institute3420 Hillview AvenuePalo Alto, CA 94303F POWERI ELECTRICRESEARCH INSTITUTEU.S. Nuclear Regulatory CommissionOffice of Nuclear Regulatory ResearchWashington, DC 20555-0001
AVAILABILITY OF REFERENCE MATERIALSIN NRC PUBLICATIONSNRC Reference MaterialNon-NRC Reference MaterialAs of November 1999, you may electronically accessNUREG-series publications and other NRC records atNRC's Public Electronic Reading Room athtto /hwww.nrc.aov/readinc-rm.html. Publicly releasedrecords include, to name a few, NUREG-seriespublications; Federal Register notices; applicant,licensee, and vendor documents and correspondence;NRC correspondence and internal memoranda;bulletins and information notices; inspection andinvestigative reports; licensee event reports; andCommission papers and their attachments.Documents available from public and special technicallibraries include all open literature items, such asbooks, journal articles, and transactions, FederalRegisternotices, Federal and State legislation, andcongressional reports. Such documents as theses,dissertations, foreign reports and translations, andnon-NRC conference proceedings may be purchasedfrom their sponsoring organization.NRC publications in the NUREG series, NRCregulations, and Title 10, Energy, in the Code ofFederal Regulations may also be purchased from oneof these two sources.1. The Superintendent of DocumentsU.S. Government Printing OfficeMail Stop SSOPWashington. DC 20402-0001Internet: bookstore.gpo.govTelephone: 202-512-1800Fax 202-512-22502. The National Technical Information ServiceSpringfield, VA 22161-0002www.ntis.gov1-800-553-6847 or, locally, 703-605-6000A single copy of each NRC draft report for comment isavailable free, to the extent of supply, upon writtenrequest as follows:Address: Office of the Chief Information Officer,Reproduction and DistributionServices SectionU.S. Nuclear Regulatory CommissionWashington, DC 20555-0001E-mail:DlSTRIBUTION@nrc.govFacsimile: 301-415-2289Some publications in the NUREG series that areposted at NRC's Web site ns/nurecsare updated periodically and may differ from the lastprinted version. Although references to material foundon a Web site bear the date the material wasaccessed, the material available on the date cited maysubsequently be removed from the site.Copies of industry codes and standards used in asubstantive manner in the NRC regulatory process aremaintained atThe NRC Technical UbraryTwo White Flint North11545 Rockville PikeRockville, MD 20852-2738These standards are available in the library forreference use by the public. Codes and standards areusually copyrighted and may be purchased from theoriginating organization or, if they are AmericanNational Standards, fromAmerican National Standards Institute11 West 42 StreetNew York, NY 10036-8002www.ansi.org212-642-4900Legally binding regulatory requirements are statedonly in laws; NRC regulations; licenses, includingtechnical specifications; or orders, not inNUREG-series publications. The views expressedin contractor-prepared publications in this seriesare not necessarily those of the NRC.The NUREG series comprises (1) technical andadministrative reports and books prepared by thestaff (NUREG-XXXX) or agency contractors(NUREG/CR-XXXX), (2) proceedings ofconferences (NUREG/CP-XXXX), (3) reportsresulting from international agreements(NUREG/IA-XXXX), (4) brochures(NUREGIBR-XXXX), and (5) compilations of legaldecisions and orders of the Commission andAtomic and Safety Ucensing Boards and ofDirectors' decisions under Section 2.206 of NRC'sregulations (NUREG-0750).DISCLAIMER: This report was prepared as an account of work sponsored by an agency of the U.S. Government.Neither the U.S. Government nor any agency thereof, nor any employee, makes any warranty, expressed orimplied, or assumes any legal liability or responsibility for any third party's use, or the results of such use, of anyinformation, apparatus, product, or process disclosed in this publication, or represents that its use by such thirdparty would not infringe privately owned rights.
EPRI/NRC-RES Fire PRA Methodologyfor Nuclear Power' FacilitiesVolume 1: Summary and OverviewEPRI 1011989NUREG/CR-6850Final ReportSeptember 2005Electric Power Research Institute (EPRI) Division of Risk Analysis and ApplicationsOffice of Nuclear Regulatory Research (RES)3420 Hillview AvenueU.S. Nuclear Regulatory CommissionPalo Alto, CA 94303Two White Flint North, 11545 Rockville PikeRockville, MD 20852-2738EPRI Project ManagerR. P. KassawaraU.S. NRC-RES Project ManagerJ. S. Hyslop
DISCLAIMER OF WARRANTIES AND LIMITATION OF LIABILITIES.THIS DOCUMENT WAS PREPARED BY THE ORGANIZATION(S) NAMED BELOW AS ANACCOUNT OF WORK SPONSORED OR COSPONSORED BY THE ELECTRIC POWER RESEARCHINSTITUTE, INC. (EPRI). NEITHER EPRI, ANY MEMBER OF EPRI, ANY COSPONSOR, THEORGANIZATION(S) BELOW, NOR ANY PERSON ACTING ON BEHALF OF ANY OF THEM:(A) MAKES ANY WARRANTY OR REPRESENTATION WHATSOEVER, EXPRESS OR IMPLIED, (I)WITH RESPECT TO THE USE OF ANY INFORMATION, APPARATUS, METHOD, PROCESS, ORSIMILAR ITEM DISCLOSED IN THIS DOCUMENT, INCLUDING MERCHANTABILITY AND FITNESSFOR A PARTICULAR PURPOSE, OR (II) THAT SUCH USE DOES NOT INFRINGE ON ORINTERFERE WITH PRIVATELY OWNED RIGHTS, INCLUDING ANY PARTY'S INTELLECTUALPROPERTY, OR (III) THAT THIS DOCUMENT IS SUITABLE TO ANY PARTICULAR USER'SCIRCUMSTANCE; OR(B) ASSUMES RESPONSIBILITY FOR ANY DAMAGES OR OTHER LIABILITY WHATSOEVER(INCLUDING ANY CONSEQUENTIAL DAMAGES, EVEN IF EPRI OR ANY EPRI REPRESENTATIVEHAS BEEN ADVISED OF THE POSSIBILITY OF SUCH DAMAGES) RESULTING FROM YOURSELECTION OR USE OF THIS DOCUMENT OR ANY INFORMATION, APPARATUS, METHOD,PROCESS, OR SIMILAR ITEM DISCLOSED IN THIS DOCUMENT.ORGANIZATION(S) THAT PREPARED THIS DOCUMENTScience Applications International CorporationSandia National LaboratoriesORDERING INFORMATIONRequests for copies of this report should be directed to EPRI Orders and Conferences, 1355 WillowWay, Suite 278, Concord, CA 94520, (800) 313-3774, press 2 or internally x5379, (925) 609-9169,(925) 609-1310 (fax).Electric Power Research Institute and EPRI are registered service marks of the Electric PowerResearch Institute, Inc. TOGETHER. .SHAPING THE FUTURE OF ELECTRICITY is a service mark ofthe Electric Power Research Institute, Inc.
CITATIONSThis report was prepared byScience Applications International Corporation (SAIC) Sandia National Laboratories (SNL)4920 El Camino Real1515 Eubank SELos Altos, CA 94022Albuquerque, NM 87185Technical Program ManagerB. Najafi, SAICTechnical Program ManagerS. P. Nowlen, SNLTechnical Area Experts:F. Joglar, SAICD. Funk, Edan EngineeringG. Hannaman, SAICR. Anoba, Anoba ConsultingTechnical Area Experts:M. Kazarians, Kazarians and AssociatesF. Wyant, SNLA. Kolaczkowski, SAICJ. Forester, SNLThis report describes research sponsored jointly by EPRI, and U.S. Nuclear RegulatoryCommission, Office of Nuclear Regulatory Research (RES).The report is a corporate document that should be cited in the literature in the following manner:EPRI/NRC-RES Fire PRA Methodologyfor NuclearPowerFacilities:Volume 1: Summaryand Overview. Electric Power Research Institute (EPRI), Palo Alto, CA, and U.S. NuclearRegulatory Commission, Office of Nuclear Regulatory Research (RES), Rockville,MD: 2005. EPRI - 1011989 and NUREG/CR-6850.iii
ABSTRACTThis report documents state-of-the-art methods, tools, and data for the conduct of a fireProbabilistic Risk Assessment (PRA) for a commercial nuclear power plant (NPP) application.This report is intended to serve the needs of a fire risk analysis team by providing a structuredframework for conduct of the overall analysis, as well as specific recommended practices toaddress each key aspect of the analysis. The methods have been developed under the Fire RiskRequantification Study. This study was conducted as a joint activity between the Electric PowerResearch Institute (EPRI) and the U.S. Nuclear Regulatory Commission (NRC) Office ofNuclear Regulatory Research (RES) under the terms of an NRC/EPRI Memorandum ofUnderstanding and an accompanying Fire Risk Addendum. Participants from the U.S. NuclearPower Industry supported demonstration analyses and provided peer review of this methodology.Methodological issues raised in past fire risk analyses, including the Individual PlantExamination of External Events (IPEEE) fire analyses, have been addressed to the extentallowed by the current state-of-the-art and the overall project scope. While the primary objectiveof the project was to consolidate existing state-of-the-art methods, in many areas, the newlydocumented methods represent a significant advancement over previously documented methods.v
CONTENTS1-11 INTRODUCTION .1.1 Background .1.2 Programmatic Overview .1-11.2.1 Program Objectives .1-21.2.2 Program Approach .1-31.2.3 Program Structure and Status .1-41-21-41.3 Technical Process Overview .1-41.3.1 Technical Issue Resolution .1.3.2 Peer Review . 1-51-61.3.3 Role of the Demonstration Studies .1.4 Intended Audience and Needed Expertise .1-61.5 Estimate of Resources to Conduct a Fire PRA Using this Methodology . 1-71.6 Report Structure .1-91.7 References for Chapter 1.1-92 OVERVIEW OF THE FIRE PRA METHODOLOGY .2.1 General Scope .2-12-12.2 Overview of the Fire PRA .2-12.3 General Assumptions and Technical Positions .2-62.3.1 Component Selection and Fire-Induced Risk Model . 2-6;2.3.1.1 General Component Selection Process .2-62.3.1.2 Post-Fire SSD Procedures .2-7.2.3.1.3 Inclusion of Instrument Circuits .2-72-72.3.2 Circuit Selection and Analysis .2.3.2.1 Proper Polarity Three-Phase Hot Shorts on AC Power Conductors . 2-82.3.2.2 Circuit Selection and Analysis - System-Wide Safety Signals . . 2-82.3.2.3 Multiple High-Impedance Faults .2.3.3 Fire Frequency and Fire Modeling Assumptions .2.3.4 Low Likelihood Fires .-2-82-92-9Vii
2.3.5 Long Duration Fires .2.3.6 General Application of these Methods .2.4 References for Chapter 2 .3 CONCLUSIONS AND CLOSING REMARKS .3.1 Status of Program Objectives .2-92-92-103-13-13.2 Improvement in the State-of-the-Art in Fire PRA . 3-23.2.1 Post-fire Plant Safe Shutdown Response Model . 3-33.2.2 Fire Compartment and Scenario Screening . 3-33.2.3 General Treatment of Fire Event Data and Fire Frequency Analysis . 3-43.2.4 Fire Severity Treatment .3-43.2.5 Detection and Suppression Analysis .3-53.2.6 Circuit Analysis .3-53-63.2.7 Human Reliability Analysis .3.3 Limitations to the State-of-the-Art and their Importance . 3-73.3.1 Number of Combined Fire-Induced Spurious Actuations . 3-73.3.2 Estimating Spurious Actuation Probabilities . 3-73.3.3 Dynamic Versus Static Modeling of Fire Damage and Operator Response . 3-93-93.3.4 Multiple Fires .3.3.5 Multiple Initiating Events from the Same Root Cause . 3-103.3.6 Limitations in Internal Events Analysis that Carry Over to Fire . 3-103.3.7 Smoke Damage .3-103-103.3.8 Seismic/Fire Interactions .3.3.9 Administrative Aspects of the Fire Protection Program . 3-103.3.10 Effectiveness of Fire Protection Systems . 3-103.3.11 Effectiveness of Passive Fire Barriers . 3-113.4 Insights and Observations .3-123.5 Recommendations .3-143.5.1 Low Power and Shutdown Operating Modes . 3-143.5.2 Detailed Fire HRA .3-153.5.3 Automated Fire PRA Information Tracking Tools . 3-153.5.4 Plant-Specific Assessment of Manual Firefighting . 3-153.5.5 Estimating Component Failure Mode Likelihoods . 3-153.6 References for Chapter 3 .Viii3-16
LIST OF FIGURESFigure 1 Overview of the Fire PRA Process .Figure 2-1 Overview of the Fire PRA Process .xiv2-2ix
REPORT SUMMARYThe Fire Risk Requantification Study has resulted in state-of-the-art methods, tools, and data fora fire probabilistic risk assessment (PRA) for commercial nuclear power plant application. Thisstudy was conducted jointly by EPRI and the U.S. Nuclear Regulatory Commission (NRC)Office of Nuclear Regulatory Research (RES) under the terms of an NRC/EPRI Memorandum ofUnderstanding and an accompanying Fire Research Addendum. Industry participants supporteddemonstration analyses and provided peer review of the methods. The documented methods areintended to support future applications of fire PRA, including risk-informed regulatoryapplications.BackgroundThis document is written primarily for practitioners conducting a nuclear power plant fire PRAstudy. A fire PRA requires a team effort because few individuals have the full range of expertiseand knowledge necessary to complete the analysis. This report assumes that the fire risk analysisteam will include individuals with expertise in four key areas: 1) fire analysis (basic firebehavior, fire modeling, fire protection engineering, and plant fire protection regulatorycompliance practices and documentation); 2) general PRA and plant systems analysis (eventtree/fault tree analysis, nuclear power plant systems modeling, reliability analysis, PRA practicesas applied in the internal events domain, and specific knowledge of the plant under analysis); 3)human reliability analysis (emergency preparedness, plant operations, plant-specific safeshutdown procedures, and operations staff training practices); and 4) electrical analysis (circuitfailure modes and effects analysis and post-fire safe shutdown, including plant-specificregulatory compliance strategies and documentation). While some of this expertise is generic,much of it is specific to the plant under analysis.The methods documented in this report represent the current state-of-the-art in fire PRA practice.Certain aspects of PRA continue to evolve and likely will see additional developments in thenear future. Such developments should be easily captured within the overall analysis frameworkdescribed here. It is important to emphasize that while specific aspects of the analysis processwill likely evolve, the overall analysis framework represents a stable and well-proven platformand should not be subject to fundamental changes in the foreseeable future.Objectives* To consolidate recent research and development activities into a single state-of-the-art firePRA methodology.* To serve the needs of a fire risk analysis team by providing a structured framework for theoverall analysis, as well as specific recommended practices to address key aspects of theanalysis.xi
--ApproachDeveloping this fire PRA methodology document involved a consensus process designed to fullydebate and build consensus on past methodological issues. Two technical development teamswere assembled, one by EPRI and the second by RES. Each team provided a full complement ofexperts covering all aspects of the analysis. These experts worked together to develop an overallanalysis framework and specific instructions for key aspects of the fire PRA.Technical differences were aired in sometimes-lively discussions. The technical exchangeprocess was designed to seek consensus where possible. However, the process also allowed RESand EPRI to maintain differing technical views in cases where consensus could not be reached.In practice, this did not prove necessary. The documented methods do, in all cases, represent aconsensus view of the two technical development teams.Another key aspect of the project involved participation of the commercial nuclear powerindustry in review, demonstration, and, to a lesser extent, development of the recommendedmethods. An industry peer-review panel was formed from the six non-pilot utility participants inthis program. Two nuclear power plants participated as pilot plants and supported demonstrationstudies conducted jointly by the EPRI and RES technical development teams. A third nuclearpower plant participated as an independent pilot plant, exercising the proposed methodsindependently and providing feedback to the technical development teams.ResultsThe documented fire PRA method reflects state-of-the-art fire risk analysis approaches.Methodological issues raised in past fire risk analyses, including individual plant examination ofexternal events (IPEEE) fire analyses, have been addressed to the extent allowed by the currentstate-of-the-art and overall project scope. Methodological debates were resolved through aconsensus process between experts representing both EPRI and RES. The consensus processincluded a provision allowing both EPRI and RES to maintain differing technical positions ifconsensus could not be reached. No cases were encountered where this provision was invoked.While the primary objective of the project was to consolidate existing state-of-the-art fire PRAmethods, in many areas, the newly documented methods represent a significant advance overpreviously documented methods. In several areas, this project has, in fact, resulted in newmethods and approaches. Such advances typically relate to areas of past methodological debate.EPRI PerspectiveThis report provides the single most complete and comprehensive methodology for conducting afire PRA to date. Two aspects of the approaches described here are especially unique. First, themethodology has been developed based on a consensus process involving both EPRI and RES.Second, the methods specifically address and resolve previously identified methodologicalissues. Clearly, these fire PRA methods should offer a stable basis for proceeding with riskinformed regulatory approaches to fire protection regulatory compliance.KeywordsFireProbabilistic Risk Assessment (PRA)Nuclear Plant Fire SafetyxiiFire RiskRisk AnalysisRisk-Informed Regulation
PREFACEThis report is presented in two volumes. Volume 1, the Executive Summary, provides generalbackground and overview information including both programmatic and technical, and projectinsights and conclusions.Volume 2 provides the detailed discussion of the recommended approach, methods, data andtools for conduct of a Fire PRA. This information is structured in 18 chapters that describe eachof the project technical tasks as they are shown in Figure 1.-.d.xiii
--m-ITASK 1:Plant Boundary & PartitioningrI-.p::I,TASK 2:.I, -XTASK3t''L':'Wl'.i4 i''t.:''Fire PRA Cable Selection t*3v,I.E-i i !C,11,I,7;.-"I!:ISUPPORTI4TASKA*' SPOTTASK BM:TSK 5,':: ' ':' i: ': Fire-Induced Risk ModelTASK 4:Qualitative ScreeningPlant Walk Downs;F' 4PR's,, ; ',j,.DaabaslF/rI?-,["ii,iR10-IMIIII''.IN ,.4I., jrI.I-TASK 8:Scoping Fire Modelingr"N'rRh"51.ME9,TASK 7B:Quantitative Screening. III.i.Moderate change,,.t,'*.t-.'fssi'\'! 'Figure 1Overview of the Fire PRA Processja.a, '.,;.'.',.',. IIIII:I1-"IABxiv.1, '' i,7'TASK 7A:Quantitative Screening - II:",IIummmmmmmmmr177IIIt.,IIFire PRA Component Selection.IIIIIIII
I :IDetailed Fire Scenario AnalvsisIDetailed Circuit Failure Analysis.Iircuit FaueMode & Ukelihood* Anavss::TASK 13:Seismic-FireInteractionsTASK 14:Fire Risk Quantification,IK'PostreTASK 12B.,I.Dtaed&ecove'rI! TASK 15: :.-NewIgSignificantchangeSinfcn chngModerate changeUncertainty & SenslivityAnaiysejs ITASK 16:Fire PMA DocumentatlonDFigure 1Overview of the Fire PRA Process (Continued)xv
FOREWORDFire probabilistic risk assessment (PRA) methods have been used in the Individual PlantExaminations of External Event (IPEEE) program to facilitate a nuclear power plant examination forvulnerabilities. However, in order to make finer, more realistic decisions for risk-informedregulation, Fire PRA methods needed to be improved. Licensee applications and U.S. NuclearRegulatory Commission (NRC) review guidance with respect to many regulatory activities such asthe risk-informed, performance-based fire protection rulemaking (endorsing National Fire ProtectionAssociation Standard 805) will benefit from more robust Fire PRA methods. In order to address theneed for improved methods, the NRC Office of Nuclear Regulatory Research (RES) and ElectricPower Research Institute (EPRI) embarked upon a program to develop state-of-art Fire PRAmethodology.Under a joint Memorandum of Understanding, RES and EPRI initiated a collaborative, resultsoriented research program, the Fire Risk Requantification Study, with the primary objective todevelop improved methodology for conducting Fire PRA for a nuclear power plant.These studies address the full breadth of Fire PRA technical issues for power operations, and includeconsideration of large early release frequency. The current scope excludes low power/shutdownoperations, spent fuel pool accidents, sabotage, and PRA Level 3 estimates of consequence.Both RES and EPRI have provided specialists in fire risk analysis, fire modeling, electricalengineering, human reliability analysis, and systems engineering for methods development. Theseimproved methods have been applied at pilot plant Fire PRAs to test their viability and effectiveness.Also, the associated procedures have been assessed for technical basis, practicality, and scope bytechnical review panels comprised of industry participants.A formal technical issue resolution process was developed to direct the deliberative process betweenRES and EPRI. The process ensures that divergent technical views are fully considered, yetencourages consensus at many points during the deliberation. Significantly, the process provides thateach party maintain its own point of view if consensus is not reached. Consensus was reached on alltechnical issues documented in this report.The methodology documented in this report reflects the current state-of-the-art in Fire PRA.These methods are expected to form a basis for risk-informed analyses related to the plant fireprotection program. However, such analyses rely upon an evaluation of the condition of fireprotection systems and structures which is beyond this methodology, and may need interpretations ofthis methodology as well.This document does not constitute regulatory requirements. RES participation in thisstudy does not constitute or imply regulatory approval of applications based upon thismethodology.xvii
ACKNOWLEDGMENTSThis work benefited from contributions and considerable technical support from Dominion,American Electric Power, Pacific Gas & Electric, Duke Power, Exelon Corporation, FloridaPower & Light, Southern California Edison, Nuclear Management Corporation, and theCANDU Owners Group. The methodology developed was tested at three nuclear facilities in theU.S. The authors extend their gratitude to the staff of these facilities for their support and forsharing their insights gained from use of the methodology. The process benefited significantlyfrom their input.John Spaargaren (Dominion, Millstone)Paul Raimondi (Dominion, Millstone)Joseph Mangeno (Dominion, Millstone)Fred Ceitek (Dominion, Millstone)Rasool Baradaran (AEP, DC Cook)Richard Gray (AEP, DC Cook)Amir Afzali (PG&E, Diablo Canyon)Clarence Worrell (PG&E, Diablo Canyon)The following individuals served on a peer review team that provided review and comments onthe interim and final report of this project.Dennis Henneke (Duke Power)Christopher Pragman (Exelon Corp.)Ching Guey (Florida Power & Light)Sam Chien and Parviz Moini (Southern California Edison)Robert Ladd (NMC - Point Beach)Keith Dinnie (formerly with CANDU Owners Group, COG)The authors extend particular gratitude to Dennis Henneke of Duke Power and Chris Pragman ofExelon Corp. for their tireless review of multiple revisions of the task procedures. Their effortscontributed substantially to the quality and completeness of the final product.The authors also gratefully acknowledge the technical contributions of Professor Ali Mosleh(University of Maryland) in the development of the fire ignition frequency and uncertaintymethods and Dennis Bley (Buttonwood Consulting Inc.) in the development of the post-firehuman reliability analysis approach.xix
LIST OF ACRONYMSACBAir-cooled Circuit BreakerACRSAdvisory Committee on Reactor SafeguardAEPAbnormal Event ProcedureAFWAuxiliary FeedwaterAGSAssistance General SupervisorAOPAbnormal Operating ProcedureATWSAnticipated Transient Without ScramBNLBrookhaven National LaboratoryBWRBoiling Water ReactorCCDPConditional Core Damage ProbabilityCFCable (Configuration) FactorsCCPSCenter for Chemical Process SafetyCCWComponent Cooling WaterCDFCore Damage FrequencyCFDComputational Fluid DynamicsCFRCode of Federal RegulationsCLERPConditional Large Early Release ProbabilityCMCorrective MaintenanceCRControl RoomCRSCable and Raceway (Database) Systemxxi
CWPCirculating Water PumpEDGEmergency Diesel GeneratorEFError FactorElErroneous Status IndicatorEOPEmergency Operating ProcedureEPREthylene-Propylene RubberEPRIElectronic Power Research InstituteFEDBFire Events DatabaseFEPFire Emergency ProcedureFHAFire Hazards AnalysisFIVEFire-Induced Vulnerability Evaluation (EPRI TR 100370)FMRCFactory Mutual Research CorporationFPRAIGFire PRA Implementation Guide (EPRI TR 105928)FRSSFire Risk Scoping StudyFSARFinal Safety Analysis ReportHEAFHigh Energy Arcing FaultHEPHuman Error ProbabilityHFEHuman Failure EventHPIHigh Pressure InjectionHPCIHigh Pressure Coolant InjectionHRAHuman Reliability AnalysisHRRHeat Release RateHTGRHigh Temperature Gas-cooled ReactorHVACHeating, Ventilation, and Air ConditioningICDPIncremental Core Damage ProbabilityxxII
ILERPIncremental Large Early Release ProbabilityINPOInstitute for Nuclear Power OperationsIPEIndividual Plant ExaminationIPEEEIndividual Plant Examination for External EventsISIgnition SourceISLOCAInterfacing Systems Loss of Coolant AccidentKSKey SwitchLCOLimiting Condition of OperationLERFLarge Early Release FrequencyLFLLower Flammability LimitLOCLoss of ControlLOCALoss of Coolant AccidentLPGLiquefied Petroleum GasLWGRLight-Water-cooled Graphite Reactors (Russian design)MCCMotor Control CenterMCRMain Control RoomMGMotor-GeneratorMFWMain FeedwaterMOVMotor Operated ValveMQHMcCaffrey, Quintiere and Harkleroad's MethodMSMain SteamNCNo ConsequenceNEINuclear Energy InstituteNEILNuclear Electric Insurance LimitedNFPANational Fire Protection Associationxxiii
NPPNuclear Power PlantNPSHNet Positive Suction HeadNQ cableNon-Qualified (IEEE-383) cableNRCNuclear Regulatory CommissionP&IDPiping and Instrumentation DiagramPEPolyethylenePMPreventive MaintenancePMMAPolymethyl MethacrylatePORVPower Operated Relief ValvePRAProbabilistic Risk AssessmentPSFPerformance Shaping FactorPTSPressurized Thermal ShockPVCPolyvinyl ChloridePWRPressurized Water ReactorQ cableQualified (IEEE-383) cableRBMKReactor Bolshoy Moshchnosty Kanalny (high-power channel reactor)RCICReactor Core Isolation CoolingRCPReactor Coolant PumpRCSReactor Coolant SystemRDATComputer program for Bayesian analysisRESThe Office of Nuclear Regulatory Research (at NRC)RHRResidual Heat RemovalRI/PBRisk-Informred / Performnance-BasedRPSReactor Protection Sy
Electric Power Research Institute (EPRI) 3420 Hillview Avenue Palo Alto, CA 94303 EPRI Project Manager R. P. Kassawara Division of Risk Analysis and Applications Office of Nuclear Regulatory Research (RES) U.S. Nuclear Regulatory Commission Two White Flint North, 11545 Rockville Pike Rockville, MD 20852-2738 U.S. NRC-RES Project Manager J. S .
Circuit Analysis Basics Introduction . Fire PRA Workshop, 2014, Rockville, MD Module 2: Circuit Analysis Basics Slide 2 . - Nuclear plant personnel with electrical and plant operating knowledge, but limited exposure to Appendix R and PRA - Nuclear plant personnel with substantial Appendix R and/or PRA
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EPRI and the Lamellibrancid Worm Jesse H. Ausubel EPRI Board of Directors Meeting, Dallas TX 19 November 2009 My title this morning is EPRI and the Lamellibrancid Worm, a title that I am sure electric power executives realize leads to the subject of natural gas. I think
University at San Luis Obispo, Bugwood.org. Symptoms of apple union necrosis and decline (AUND) infection, caused by Tomato Ringspot Virus. Image courtesy of H.J. Larsen, Bugwood.org. Is there a need for a detailed PRA or for a more detailed analysis of particular sections of the PRA? If yes, select the PRA area (UK or EU) and the PRA scheme (UK or
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–NRC, AS, and MML staff – for review of applications NRC Forms in Appendices to document training and experience –NRC Form 313A (AUT), “AU Training and Experience and Preceptor Attestation (for uses defined under 10 CFR 35.300) – NRC Form
Thermal Management and Packaging of High Temperature Automotive Power Electronics Gilbert Moreno 3D Power Electronics Integration and Manufacturing June 26, 2018 This presentation does not contain any proprietary, confidential, or otherwise restricted information. NREL 2 Outline Motivation and objectives Describe the cooling systems currently used in automotive power electronics .
