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  • IEEE 338-2012

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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety

    Available format(s):  PDF

    Superseded date:  07-04-2023

    Language(s):  English

    Published date:  23-03-2012

    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. System design requirements for testing
    5. Testing program requirements
    Annex A (informative) - Bibliography
    Annex B (informative) - General overview of risk-informed
            surveillance testing
    Annex C (informative) - Evaluation process for surveillance
            test changes
    Annex D (informative) - Programmatic approach to risk-informed
            surveillance test interval management

    Abstract - (Show below) - (Hide below)

    The standard provides criteria for the performance of periodic testing of nuclear power generating station safety systems.

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

    Committee Nuclear Power Engineering Committee
    Development Note Supersedes IEEE DRAFT 338. (07/2007)
    Document Type Standard
    Publisher Institute of Electrical & Electronics Engineers
    Status Superseded
    Superseded By
    Supersedes

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

    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
    ISA 67.06.01 : 2002 PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS
    IEEE DRAFT 833 : D3 2004 PRACTICE FOR THE PROTECTION OF ELECTRIC EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS FROM WATER HAZARDS
    IEEE 384-2018 IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    IEEE/ANSI N42.4-1971 American National Standard for High Voltage Connectors for Nuclear Instruments
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    IEC 61888:2002 Nuclear power plants - Instrumentation important to safety - Determination and maintenance of trip setpoints
    IEEE 387-1995 IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations
    IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
    ANS 56.3 : 77(R1987) OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment 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
    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 1819-2016 IEEE Standard for Risk-Informed Categorization and Treatment of Electrical and Electronic Equipment at Nuclear Power Generating Stations and Other Nuclear Facilities
    ISA 67.06 : 1984 RESPONSE TIME TESTING OF NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS
    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 DRAFT 741 : D1 2006 CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS
    ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
    IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    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
    ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
    ISA 67.04.01 : 2006 SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
    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 577-2022 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations and Other Nuclear Facilities
    IEEE 308-2020 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    IEEE 741-2022 REDLINE IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in 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 566 : 1977 RECOMMENDED PRACTICE FOR THE DESIGN OF DISPLAY AND CONTROL FACILITIES FOR CENTRAL CONTROL ROOMS OF 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
    ISA 67.06.01 : 2002 PERFORMANCE MONITORING FOR NUCLEAR SAFETY-RELATED INSTRUMENT CHANNELS IN NUCLEAR POWER PLANTS
    IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    IEEE 7-4.3.2-2010 REDLINE IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations
    ISA 67.04.01 : 2006 SETPOINTS FOR NUCLEAR SAFETY-RELATED INSTRUMENTATION
    NACE RP 01 89 : 2002 ON-LINE MONITORING OF COOLING WATERS
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    IEEE 308-2001 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    IEC 60951-4:2009 Nuclear power plants - Instrumentation important to safety - Radiation monitoring for accident and post-accident conditions - Part 4: Equipment for continuous in-line or on-line monitoring of radioactivity in process streams
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment for Nuclear Power Generating Stations
    IEEE 450-2010 REDLINE IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications
    ANS 3.2 : 2012(R2017) MANAGERIAL, ADMINISTRATIVE, AND QUALITY ASSURANCE CONTROLS FOR THE OPERATIONAL PHASE OF NUCLEAR POWER PLANTS
    IEC 60768:2009 Nuclear power plants - Instrumentation important to safety - Equipment for continuous in-line or on-line monitoring of radioactivity in process streams for normal and incident conditions
    IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
    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 387-1995 IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations
    IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
    IEEE 650-2006 IEEE Standard for Qualification of Class 1E Static Battery Chargers and Inverters for Nuclear Power Generating Stations
    IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
    ASME RA-S : 2008 LEVEL 1/LARGE EARLY RELEASE FREQUENCY PROBABILISTIC RISK ASSESSMENT FOR NUCLEAR POWER PLANT APPLICATIONS
    IEEE 317-2013 REDLINE IEEE Standard for Electric Penetration Assemblies in Containment Structures 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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