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  • IEEE 497-2010

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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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    IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations

    Available format(s):  PDF

    Superseded date:  29-07-2016

    Language(s):  English

    Published date:  10-11-2010

    Publisher:  Institute of Electrical & Electronics Engineers

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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

    Abstract - (Show below) - (Hide below)

    This standard contains the functional and design criteria for accident monitoring instrumentation for nuclear power generating stations.

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

    Committee Nuclear Power Engineering Committee
    Development Note Supersedes IEEE DRAFT 497. (02/2005) Also numbered as IEC 63147. (12/2017)
    Document Type Standard
    Publisher Institute of Electrical & Electronics Engineers
    Status Superseded
    Superseded By
    Supersedes

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

    IEEE 1023-2004 REDLINE IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities
    ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
    IEC TR 63123:2017 Nuclear power plants - Instrumentation, control and electrical power systems - Guidance for the application of IEC 63147:2017/IEEE Std 497™ -2016 in the IAEA / IEC framework
    18/30376682 DC : DRAFT APR 2018 BS IEC/IEEE 63113 - NUCLEAR FACILITIES - INSTRUMENTATION IMPORTANT TO SAFETY - SPENT FUEL POOL INSTRUMENTATION
    17/30357475 DC : 0 BS IEC/IEEE 63113 - NUCLEAR FACILITIES - INSTRUMENTATION IMPORTANT TO SAFETY - SPENT FUEL POOL INSTRUMENTATION
    IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    ANS 59.1 : 1986 COOLING WATER SYSTEMS FOR LIGHT WATER REACTORS, NUCLEAR SAFETY RELATED,
    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
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    BS IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    IEEE 627-2010 IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
    ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,

    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
    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
    IEEE 7-4.3.2-2010 REDLINE IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
    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
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    IEEE 308-2001 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    IEC 60880:2006 Nuclear power plants - Instrumentation and control systems important to safety - Software aspects for computer-based systems performing category A functions
    IEEE 344-2004 IEEE Recommended Practice for Seismic Qualification of Class 1E Equipment for Nuclear Power Generating Stations
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
    IEEE 379-2000 IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    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
    ISA 67.01.01 : 2002 TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
    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 1023-2004 REDLINE IEEE Recommended Practice for the Application of Human Factors Engineering to Systems, Equipment, and Facilities of Nuclear Power Generating Stations and Other Nuclear Facilities
    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
    IEEE 577-2004 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities
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