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  • IEEE 379-2014

    Current The latest, up-to-date edition.

    IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems

    Available format(s):  Hardcopy, PDF

    Language(s):  English

    Published date:  30-05-2014

    Publisher:  Institute of Electrical & Electronics Engineers

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    Table of Contents - (Show below) - (Hide below)

    1 Overview
    2 Normative references
    3 Definitions, acronyms, abbreviations, and terms
    4 Statement of the single-failure criterion
    5 Requirements
    6 Design analysis for single failure
    Annex A (informative) - Bibliography
    Annex B (informative) - Examples of nondetectable
            failures

    Abstract - (Show below) - (Hide below)

    Defines the application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems.

    General Product Information - (Show below) - (Hide below)

    Committee Nuclear Power Engineering Committee
    Development Note Supersedes IEEE DRAFT 379 (04/2001)
    Document Type Standard
    Publisher Institute of Electrical & Electronics Engineers
    Status Current
    Supersedes

    Standards Referenced By This Book - (Show below) - (Hide below)

    IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
    ANS 56.5 : 79(R1987) PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA
    ASME AG-1 : 2019 CODE ON NUCLEAR AIR AND GAS TREATMENT
    ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
    ASME AG 1 : 2012 CODE ON NUCLEAR AIR AND GAS TREATMENT
    IEEE/ANSI N42.4-1971 American National Standard for High Voltage Connectors for Nuclear Instruments
    ANS 54.1 : 1989 GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT
    ANS 56.10 : 82(R1987) NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS
    IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    IEEE DRAFT 338 : D4 2006 CRITERIA FOR THE PERIODIC SURVEILLANCE TESTING OF NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
    ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
    ANS 51.10 : 1991(R2008) AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS
    IEEE 3006.7-2013 IEEE Recommended Practice for Determining the Reliability of 7x24 Continuous Power Systems in Industrial and Commercial Facilities
    ANS 56.7 : 78(R1987) VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
    IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
    IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
    ANS 56.3 : 77(R1987) OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
    IEEE 1819-2016 IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities
    ANS 58.6 : 1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
    BS IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
    ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
    ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
    ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
    ANS 56.4 : 83(R1988) PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS
    IEEE 308-2020 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    IEEE 384-2018 IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    IEEE/IEC 63147-2017 IEEE/IEC International Standard - Criteria for accident monitoring instrumentation for nuclear power generating stations
    IEEE 497-2016 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

    Standards Referencing This Book - (Show below) - (Hide below)

    IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
    CFR 10(PTS0-199) : JAN 87 ENERGY - NUCLEAR REGULATORY COMMISSION
    IEEE 741-2007 IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
    IEEE 7-4.3.2-2010 REDLINE IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
    IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
    IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
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