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  • BS IEC 63147:2017

    Current The latest, up-to-date edition.

    Criteria for accident monitoring instrumentation for nuclear power generating stations

    Available format(s):  Hardcopy, PDF

    Language(s):  English

    Published date:  11-01-2018

    Publisher:  British Standards Institution

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

    1. Overview
    2. Normative references
    3. Definitions
    4. Selection criteria
    5. Performance criteria
    6. Design criteria
    7. Qualification criteria
    8. Display criteria
    9. Quality assurance
    Annex A (informative) - Accident monitoring instrument
            channel accuracy
    Annex B (informative) - Examples of monitoring channel
            displays
    Annex C (informative) - Operational state diagram
    Annex D (informative) - Bibliography
    Annex E (informative) - IEEE list of participants

    Abstract - (Show below) - (Hide below)

    Describes the functional and design criteria for accident monitoring instrumentation for new plant designs and nuclear power generating stations desiring to perform design modifications.

    Scope - (Show below) - (Hide below)

    IEC 63147:2017(E) contains the functional and design criteria for accident monitoring instrumentation for new plant designs and nuclear power generating stations desiring to perform design modifications. The purpose of this standard is to establish selection, design, performance, qualification, and display criteria for accident monitoring instrumentation for anticipated operational occurrences, design basis events, and severe accidents.
    This standard applies to accident monitoring instrumentation intended for use during the following operations:
    - As required for planned operator action related to accident mitigation,
    - For assessing plant conditions, safety system performance, and making decisions related to plant response to abnormal events,
    - For achieving and maintaining safe shutdown following an accident
    This standard does not apply to the following:
    - Accident monitoring instrumentation that is intended solely for historical recording or solely for maintenance purposes
    - Other instrumentation that may be available during accident conditions.
    This standard is an adoption of IEEE 497-2016 by IEC.
    When applied in an IAEA / IEC environment this standard is to be used in conjunction with IEC TR 63123.

    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 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation 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
    ASME PV CODE 3 NCA DIV 1&2 : 2017 BPVC Section III-Rules for Constructions of Nuclear Facility Components BOILER AND PRESSURE VESSEL CODE - RULES FOR THE CONSTRUCTION OF NUCLEAR FACILITY COMPONENTS - GENERAL REQUIREMENTS FOR DIVISION 1 AND DIVISION 2
    IEC 60812:2006 Analysis techniques for system reliability - Procedure for failure mode and effects analysis (FMEA)
    IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    IEC 62340:2007 Nuclear power plants - Instrumentation and control systems important to safety - Requirements for coping with common cause failure (CCF)
    ANS 4.5 : 80(R1986) ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR
    IEC 60980:1989 Recommended practices for seismic qualification of electrical equipment of the safety system for nuclear generating stations
    IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
    ISA 67.04.01 : 2006 SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    IEC 60880:2006 Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
    IEC 60780:1998 Nuclear power plants - Electrical equipment of the safety system - Qualification
    IEC 61225:2005 Nuclear power plants - Instrumentation and control systems important to safety - Requirements for electrical supplies
    ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
    IEC 60709:2004 Nuclear power plants - Instrumentation and control systems important to safety - Separation
    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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