• PD IEC/TR 62987:2015

    Current The latest, up-to-date edition.

    Nuclear power plants. Instrumentation and control systems important to safety. Use of Failure Mode and Effects Analysis (FMEA) and related methods to support the justification of systems

    Available format(s):  Hardcopy, PDF

    Language(s):  English

    Published date:  08-09-2015

    Publisher:  British Standards Institution

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

    FOREWORD
    INTRODUCTION
    1 Scope
    2 Normative references
    3 Terms and definitions
    4 References to FMEA in published standards
    5 Scope of application of FMEA
    6 Examples of applications
    7 Industry practice and regulatory relevance
    8 Conclusions
    Annex A (informative) - Standardized form used in survey
    Bibliography

    Abstract - (Show below) - (Hide below)

    Gives guidance on nuclear-specific issues when applying Failure Mode and Effects Analysis (FMEA) and related methods to instrumentation and control systems important to safety in nuclear power plants.

    Scope - (Show below) - (Hide below)

    This Technical Report provides guidance on nuclear-specific issues when applying Failure Mode and Effects Analysis (FMEA) and related methods to instrumentation and control systems important to safety in nuclear power plants. The information in this Technical Report complements, for nuclear power plant applications, the procedure for FMEA in IEC 60812.

    This Technical Report attempts to provide information, in the context of applications to nuclear power plant instrumentation and control systems important to safety, on:

    • terminology used in FMEA processes,

    • benefits of using FMEA,

    • shortcomings and limitations of FMEA methods,

    • anticipated outcomes of and claims to be made from application of FMEA,

    • relationships to other analysis methods used in establishing the safety / reliability of nuclear power plant designs,

    • typical FMEA process inputs,

    • typical FMEA process outputs,

    • typical initiators of FMEA processes,

    • most prevalent uses of FMEA processes,

    • recommended uses of FMEA processes,

    • discouraged uses of FMEA processes,

    • FMEA work product contents and characteristics,

    • FMEA work product configuration management practices,

    • good practices,

    • supporting tools,

    • specific examples of FMEA use for nuclear power plant licensing, and

    • FMEA references.

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

    Committee NCE/8
    Document Type Standard
    Publisher British Standards Institution
    Status Current

    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
    IEC 61226:2009 Nuclear power plants - Instrumentation and control important to safety - Classification of instrumentation and control functions
    IEC 60812:2006 Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA)
    IEC 62138:2004 Nuclear power plants - Instrumentation and control important for safety - Software aspects for computer-based systems performing category B or C functions
    IEC 60987:2007+AMD1:2013 CSV Nuclear power plants - Instrumentation and control important to safety - Hardware design requirements for computer-based systems
    IEC 60880:2006 Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
    IEC 61513:2011 Nuclear power plants - Instrumentation and control important to safety - General requirements for systems
    MIL-STD-1629 Revision A:1980 PROCEDURES FOR PERFORMING A FAILURE MODE, EFFECTS AND CRITICALITY ANALYSIS
    IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
    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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