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Abbreviations and Acronyms - NRC: Home Page · PDF fileBFN Browns Ferry Nuclear Plant BLDG...

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BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms Page i Abbreviations and Acronyms This section contains the abbreviations that pertain to the administrative and technical information within the license renewal application. The abbreviations that pertain to the environmental information are included in the front of Appendix E (Environmental Report). Abbreviation Definition AC Alternating Current ACI American Concrete Institute ACSR Aluminum Conductor Steel Reinforced ADHR Auxiliary Decay Heat Removal ADS Atmospheric Dilution System AEC Atomic Energy Commission AERM Aging Effect Requiring Management ALARA As Low As Reasonably Achievable AMP Aging Management Program AMR Aging Management Review ANSI American National Standards Institute AOT Abnormal Operational Transient AOV Air Operated Valve API American Petroleum Institute APRM Average Power Range Monitor ART Adjusted Reference Temperature ASCE American Society of Civil Engineers ASME American Society of Mechanical Engineers ASTM American Society for Testing and Materials ATWS Anticipated Transient Without Scram B&PV Boiler and Pressure Vessel B&W Babcock and Wilcox BFN Browns Ferry Nuclear Plant BLDG Building BP Business Practice BPV Bypass Valve BTP Branch Technical Position
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  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page i

    Abbreviations and Acronyms This section contains the abbreviations that pertain to the administrative and technical information within the license renewal application. The abbreviations that pertain to the environmental information are included in the front of Appendix E (Environmental Report).

    Abbreviation Definition AC Alternating Current

    ACI American Concrete Institute

    ACSR Aluminum Conductor Steel Reinforced

    ADHR Auxiliary Decay Heat Removal

    ADS Atmospheric Dilution System

    AEC Atomic Energy Commission

    AERM Aging Effect Requiring Management

    ALARA As Low As Reasonably Achievable

    AMP Aging Management Program

    AMR Aging Management Review

    ANSI American National Standards Institute

    AOT Abnormal Operational Transient

    AOV Air Operated Valve

    API American Petroleum Institute

    APRM Average Power Range Monitor

    ART Adjusted Reference Temperature

    ASCE American Society of Civil Engineers

    ASME American Society of Mechanical Engineers

    ASTM American Society for Testing and Materials

    ATWS Anticipated Transient Without Scram

    B&PV Boiler and Pressure Vessel

    B&W Babcock and Wilcox

    BFN Browns Ferry Nuclear Plant

    BLDG Building

    BP Business Practice

    BPV Bypass Valve

    BTP Branch Technical Position

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page ii

    Abbreviation Definition BWR Boiling Water Reactor

    BWRVIP Boiling Water Reactor Vessel and Internals Project

    CAD Containment Atmosphere Dilution

    CAM Containment Air Monitoring

    CAP Corrective Action Plan

    CAS Central Alarm Station

    CASS Cast Austenitic Stainless Steel CC Criticality Control CCCW Closed Cycle Cooling Water

    CCRIS Calculation Cross Reference Information System

    CDF Core Damage Frequency CE Conducts Electricity CF Chemistry Factor

    CFR Code Of Federal Regulations

    CLB Current Licensing Basis

    CMAA Crane Manufacturers Association of America

    CO2 Carbon Dioxide

    COLR Core Operating Limits Report

    CRD Control Rod Drive

    CRDA Control Rod Drop Accident

    CREVS Control Room Emergency Ventilation System

    CS Core Spray

    CSD Cold Shutdown

    CSPE Chlorosulfonated Polyethylene

    CST Condensate Storage Tank

    CUF Cumulative Usage Factor

    DBA Design Basis Accident

    DBE Design Basis Event

    DC Direct Current

    DCD Design Criteria Document

    DG Diesel Generator

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page iii

    Abbreviation Definition DG Draft Regulatory Guide

    DOR Division of Operating Reactors DP Debris Protection ECCS Emergency Core Cooling System

    ECP Electrochemical Potential

    EDG Emergency Diesel Generator

    EDMS Electronic Document Management System

    EECW Emergency Equipment Cooling Water

    EFPD Effective Full-Power Day

    EFPY Effective Full-Power Year

    EHC Electro-Hydraulic Control

    EMA Equivalent Margin Analysis

    EMPAC Enterprise Maintenance Planning and Control system

    EOL End of Life

    EOP Emergency Operating Procedure

    EPDM Ethylene Propylene Diene Monomer

    EPR Ethylene Propylene Rubber

    EPRI Electric Power Research Institute

    EQ Environmental Qualification ES/SEP Expansion/Separation ESF Engineered Safety Feature

    FAC Flow-Accelerated Corrosion FB Fire Barrier FD Flow Distribution Fen Environmental Fatigue Life Correction Factor

    FERC Federal Energy Regulatory Commission

    FHA Fire Hazards Analysis FLB Flood Barrier FOS Fuel Oil Storage

    FP Fire Protection

    FPC Fuel Pool Cooling and Cleanup

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page iv

    Abbreviation Definition FPR Fire Protection Report

    FR Federal Register FR Flow Restriction FSAR Final Safety Analysis Report

    FW Feedwater

    GALL Generic Aging Lessons Learned report

    GE General Electric

    GL Generic Letter

    GPM Gallons per Minute

    GSI Generic Safety Issue

    H2 Hydrogen

    HAZ Heat Affected Zone

    HCU Hydraulic Control Unit HE/ME High/Low (Moderate) Energy Line Break HELB High-Energy Line Break

    HEPA High Efficiency Particulate Air

    HIC High Integrity Container

    HMWPE High Molecular Weight Polyethylene

    HP High Pressure

    HPCI High Pressure Coolant Injection

    HPFP High Pressure Fire Protection

    HSD Hot Shutdown HT Heat Transfer HVAC Heating, Ventilation, and Air Conditioning

    H W W V Hardened Wetwell Vent

    I&C Instrumentation and Control

    IASCC Irradiation Assisted Stress Corrosion Cracking

    ID Inside Diameter

    IEB Inspection and Enforcement Bulletin

    IEEE Institute of Electrical and Electronics Engineers

    IGA Intergranular Attack

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page v

    Abbreviation Definition IGSCC Intergranular Stress Corrosion Cracking

    ILRT Integrated Leak Rate Test

    IN Information Notice

    INPO Institute of Nuclear Power Operations INS Insulation Electrical IPA Integrated Plant Assessment

    IPE Individual Plant Examination

    IPEEE Individual Plant Examination of External Events

    IPS Intake Pumping Station

    IR Insulation Resistance

    IRM Intermediate Range Monitor

    ISG Interim Staff Guidance

    ISI Inservice Inspection

    IST Inservice Testing

    ITG Issues Task Group

    kV Kilovolt

    LCD Liquid Crystal Display

    LCO Limiting Condition for Operation

    LED Light Emitting Diode

    LER Licensee Event Report

    LLRT Local Leak Rate Test

    LLRW Low Level Radioactive Waste

    LOCA Loss Of Coolant Accident

    LOOP Loss Of Offsite Power

    LP Low Pressure

    LPCI Low Pressure Coolant Injection

    LPRM Local Power Range Monitor

    LR License Renewal

    LRA License Renewal Application

    LRT Leak Rate Test

    LWR Light Water Reactor

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page vi

    Abbreviation Definition MB Missile Barrier MC Mechanical Closure MCC Motor Control Center

    MEL Master Equipment List

    MELB Medium-Energy Line Break

    MeV Million electron Volts

    MIC Microbiologically Influenced Corrosion

    MOV Motor Operated Valve

    MRC Management Review Committee

    MRV Minimum Required Value

    MS Main Steam

    MSIV Main Steam Isolation Valve

    MSR Moisture Separator/Reheater

    MSRV Main Steam Safety Relief Valve

    MT Magnetic Particle Testing

    MWD/T Megawatt Days per Ton

    n/cm2 Neutrons per Square Centimeter

    NDE Nondestructive Examination

    NDT Nil-Ductility Temperature

    NEI Nuclear Energy Institute

    NESC National Electrical Safety Code

    NFPA National Fire Protection Association

    NGCC Natural Gas Combined Cycle

    NPS Nominal Pipe Size

    NPSH Net Positive Suction Head

    NRC Nuclear Regulatory Commission

    NRMS Normalized Root Mean Square

    NRR NRC Office of Nuclear Reactor Regulation

    NSAC Nuclear Safety Analysis Center

    NSR Nonsafety-Related

    NSSS Nuclear Steam Supply System

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page vii

    Abbreviation Definition NUMARC Nuclear Management and Resources Council

    NUREG U. S. Nuclear Regulatory Commission Regulatory Guide

    O2 Oxygen

    OCCW Open-Cycle Cooling Water

    OD Outside Diameter

    OE Operating Experience

    OM Operation and Maintenance

    PAM Post Accident Monitoring

    PASS Post Accident Sampling System PB Pressure Boundary PC Pulverized Coal

    PER Problem Evaluation Report PL Fission Product Plateout PRA Probabilistic Risk Assessment

    PSIA Pounds per Square Inch (absolute)

    PSIG Pounds per Square Inch (gage)

    PSPMP Periodic Surveillance and Preventive Maintenance Program

    PT Penetrant Testing

    P-T Pressure Temperature

    PTS Pressurized Thermal Shock

    PUAR Plant Unique Analysis Report

    PVC Polyvinyl Chloride PW Pipe Whip Restraint PWR Pressurized Water Reactor

    QA Quality Assurance

    QAPM Quality Assurance Program Manual

    RAI Request for Additional Information

    RBCCW Reactor Building Closed Cooling Water

    RCIC Reactor Core Isolation Cooling

    RCPB Reactor Coolant Pressure Boundary

    RCS Reactor Coolant System

  • BFN Units 1, 2, and 3 License Renewal Application Abbreviations and Acronyms

    Page viii

    Abbreviation Definition RCW Raw Cooling Water

    RG Regulatory Guide

    RHR Residual Heat Removal

    RHRSW Residual Heat Removal Service Water

    RICSIL Rapid Information Communication Services Information Letter

    RPS Reactor Protection System

    RPT Recirculation Pump Trip

    RPV Reactor Pressure Vessel

    RPVII Reactor Pressure Vessel Internals Inspection

    RSW Raw Service Water

    RT Reference Temperature

    RTNDT Nil-Ductility Reference Temperature

    RVLIS Reactor Vessel Level Instrumentation System

    RWCU Reactor Water Cleanup

    SAS Secondary Alarm Station

    SAW Submerged Arc Weld

    SBLOCA Small Break Loss Of Coolant Accident

    SBO Station Blackout

    SCC Stress Corrosion Cracking SCW Source of Cooling Water SDC Shutdown Cooling

    SEIS Supplem


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