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  • IEEE 603-2009 REDLINE

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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 Safety Systems for Nuclear Power Generating Stations

    Available format(s):  PDF

    Superseded date:  17-12-2018

    Language(s):  English

    Published date:  05-11-2009

    Publisher:  Institute of Electrical & Electronics Engineers

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

    1. Overview
        1.1 Scope
        1.2 Illustration
        1.3 Application
    2. Normative references
    3. Definitions
    4. Safety system design basis
    5. Safety system criteria
        5.1 Single-failure criterion
        5.2 Completion of protective action
        5.3 Quality
        5.4 Equipment qualification
        5.5 System integrity
        5.6 Independence
        5.7 Capability for testing and calibration
        5.8 Information displays
        5.9 Control of access
        5.10 Repair
        5.11 Identification
        5.12 Auxiliary features
        5.13 Multi-unit stations
        5.14 Human factors considerations
        5.15 Reliability
        5.16 Common-cause failure criteria
    6. Sense and command features - Functional and design
        requirements
        6.1 Automatic control
        6.2 Manual control
        6.3 Interaction between the sense and command
             features and other systems
        6.4 Derivation of system inputs
        6.5 Capability for testing and calibration
        6.6 Operating bypasses
        6.7 Maintenance bypass
        6.8 Setpoints
    7. Execute features - Functional and design requirements
        7.1 Automatic control
        7.2 Manual control
        7.3 Completion of protective action
        7.4 Operating bypass
        7.5 Maintenance bypass
    8. Power source requirements
        8.1 Electrical power sources
        8.2 Non-electrical power sources
        8.3 Maintenance bypass
    Annex A (informative) - Illustration of some basic concepts
            for developing the scope of a safety system
    Annex B (informative) - Electromagnetic compatibility
    Annex C (informative) - Bibliography

    Abstract - (Show below) - (Hide below)

    Defines minimum functional and design requirements for the power, instrumentation, and control portions of safety systems for nuclear power generating stations.

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

    Committee Nuclear Power Engineering Committee
    Document Type Standard
    Publisher Institute of Electrical & Electronics Engineers
    Status Superseded
    Superseded By
    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
    IEEE 741-2007 IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
    BS IEC 61888:2002 Nuclear power plants. Instrumentation important to safety. Determination and maintenance of trip setpoints
    IEEE DRAFT 387 : D9A MAR 95 DRAFT STANDARD CRITERIA FOR DIESEL-GENERATOR UNITS APPLIED AS STANDBY POWER SUPPLIES FOR NUCLEAR POWER GENERATING STATIONS
    ANS 56.6 : 1986 VENTILATION SYSTEMS, PRESSURIZED WATER REACTOR CONTAINMENT
    ISA 67.06.01 : 2002 PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS
    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 DRAFT 833 : D3 2004 PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS
    IEEE 650-2006 IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations
    ASME AG-1 : 2019 CODE ON NUCLEAR AIR AND GAS TREATMENT
    ASME AG 1 : 2012 CODE ON NUCLEAR AIR AND GAS TREATMENT
    15/30249614 DC : 0 BS IEC/IEEE 60780-323 ED 1.0 - NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION
    BS IEC/IEEE 60780-323 : 2016 NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION
    IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    IEC 61888:2002 Nuclear power plants - Instrumentation important to safety - Determination and maintenance of trip setpoints
    IEC TR 62987:2015 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
    IEEE 497-2016 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
    IEEE/IEC 63147-2017 IEEE/IEC International Standard - Criteria for accident monitoring instrumentation for nuclear power generating stations
    IEEE 387-1995 IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations
    PD IEC/TR 62987:2015 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
    IEEE DRAFT 379 : D5 2000 DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
    IEEE 1290-2015 REDLINE IEEE Guide for Motor-Operated Valve (MOV) Motor Application, Protection, Control, and Testing in Nuclear Power-Generating Stations
    IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
    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 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
    BS EN 60780-323:2017 Nuclear facilities. Electrical equipment important to safety. Qualification
    PD IEC/TR 63084:2017 Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    IEC/IEEE 60780-323:2016 Nuclear facilities - Electrical equipment important to safety - Qualification
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
    IEEE 1786-2011 IEEE Guide for Human Factors Applications of Computerized Operating Procedure Systems (COPS) at Nuclear Power Generating Stations and Other Nuclear Facilities
    IEEE 1205-2014 IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Electrical Equipment Used in Nuclear Power Generating Stations and Other Nuclear Facilities
    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
    I.S. EN 60780-323:2017 NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION
    ISA 67.01.01 : 2002 TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
    IEC TR 63084:2017 Nuclear power plants - Instrumentation and control important to safety - Platform qualification for systems important to safety
    IEEE C37.82-1987 IEEE Standard for the Qualification of Switchgear Assemblies for Class 1E Applications in Nuclear Power Generating Stations
    BS IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    EN 60780-323 : 2017 Nuclear facilities - Electrical equipment important to safety - Qualification
    IEEE 627-2010 IEEE Standard for Qualification of Equipment Used in Nuclear Facilities
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    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
    IEEE DRAFT 741 : D1 2006 CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS
    IEEE 649-2006 IEEE Standard for Qualifying Class 1E Motor Control Centers for Nuclear Power Generating Stations
    IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
    IEEE 420-2013 REDLINE IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations
    IEEE 317-2013 REDLINE IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations
    ISA 67.01 : 1994 TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
    ISA 67.04.01 : 2006 SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
    IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
    IEEE 1682-2011 IEEE Standard for Qualifying Fiber Optic Cables, Connections, and Optical Fiber Splices for Use in Safety Systems in Nuclear Power Generating Stations
    IEEE 741-2017 IEEE Standard for 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

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

    IEEE 420-2013 REDLINE IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations
    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
    CFR 10(PTS0-199) : JAN 87 ENERGY - NUCLEAR REGULATORY COMMISSION
    IEEE 7-4.3.2-2003 IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
    IEEE 497-2002 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
    IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    ANS 59.3 : 1992(R2002) NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS
    ANS 4.5 : 80(R1986) ACCIDENT MONITORING FUNCTIONS IN LIGHT-WATER-COOLED REACTORS, CRITERIA FOR
    ISA 67.04.01 : 2006 SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
    IEEE 338-2006 IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems
    IEEE 420-2001 IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems 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
    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 60231A:1969 Supplement A - General principles of nuclear reactor instrumentation
    ANS 58.9 : 2002(R2015) SINGLE FAILURE CRITERIA FOR LWR SAFETY-RELATED FLUID SYSTEMS
    ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
    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 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
    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 577-2004 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities
    ANS 59.51 : 1997(R2015) FUEL OIL SYSTEMS FOR SAFETY-RELATED EMERGENCY DIESEL GENERATORS
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