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  • IEEE DRAFT 379 : D5 2000

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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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    DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS

    Available format(s): 

    Superseded date:  14-03-2001

    Language(s): 

    Published date:  12-01-2013

    Publisher:  Institute of Electrical & Electronics Engineers

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

    Overview
    1.1 Scope
    1.2 Purpose
    2 References
    3 Definitions
    4 Statement of the single-failure criterion
    5 Requirements
    5.1 Independence and Redundancy
    5.2 Nondetectable Failure
    5.3 Cascaded Failures
    5.4 Design Basis Events and Single Failures
    5.5 Common Cause Failures
    5.6 Shared systems
    6 Design analysis for single-failure
    6.1 Procedure
    6.2 Systems Portions Analysis
    6.3 Other Considerations
    7 Bibliography


    Abstract - (Show below) - (Hide below)

    Covers the application of the single failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems. The purpose is to interpret and provide guidance in the application of the single failure criterion, discuss failures, and present an acceptable method of single failure analysis. It is not the function of this standard to identify where the single failure criterion is to be applied or to force compliance on any system; however, in those cases where the single failure criterion has been invoked, this standard establishes the requirements for its application.

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

    Comment Closes On
    Document Type Draft
    Publisher Institute of Electrical & Electronics Engineers
    Status Superseded
    Superseded By

    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
    ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
    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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