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  • IEEE 308-2012 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    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.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 Class 1E Power Systems for Nuclear Power Generating Stations

    Available format(s):  PDF

    Superseded date:  19-03-2020

    Language(s):  English

    Published date:  16-01-2013

    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. Principal design criteria
    5. Supplementary design criteria
    6. Surveillance and test requirements
    7. Multiunit station considerations
    8. Documentation

    Abstract - (Show below) - (Hide below)

    Covers Class 1E portions of ac and dc power systems and I&C power systems in single-unit and multiunit nuclear power generating stations.

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

    Committee Nuclear Power Engineering Committee
    Development Note Supersedes IEEE DRAFT 308. (08/2002)
    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    Status Superseded
    Superseded By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
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    ANS 56.5 : 79(R1987) PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA
    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
    IEEE 383-2015 IEEE Standard for Qualifying Electric Cables and Splices for 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
    ANS 59.2 : 1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
    IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
    IEEE/ANSI N42.4-1971 American National Standard for High Voltage Connectors for Nuclear Instruments
    IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems for Nuclear Power Generating Stations
    IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
    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 387-2017 IEEE Standard for Criteria for Diesel Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations
    IEEE 384-2018 IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    IEEE DRAFT 379 : D5 2000 DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
    IEEE 535-2013 IEEE Standard for Qualification of Class 1E Vented Lead Acid Storage Batteries for Nuclear Power Generating Stations
    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 56.2 : 84(R1989) NUCLEAR POWER PLANTS - CONTAINMENT ISOLATION PROVISIONS FOR FLUID SYSTEMS AFTER A LOCA
    IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
    ANS 51.10 : 1991(R2008) AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS
    ANS 56.7 : 78(R1987) VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT
    ANS 59.51 : 1997(R2015) FUEL OIL SYSTEMS FOR SAFETY-RELATED EMERGENCY DIESEL GENERATORS
    IEEE DRAFT 765 : 0 PREFERRED POWER SUPPLY (PPS) FOR NUCLEAR POWER GENERATING STATIONS (NPGS)
    IEEE 628-2011 IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations
    ANS 56.3 : 77(R1987) OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY
    ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
    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 765-2012 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
    IEEE 1792-2011 IEEE Recommended Practice for Nuclear Power Generating Station (NPGS) Preferred Power Supply (PPS) Reliability
    ANS 58.6 : 1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
    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
    IEEE DRAFT 741 : D1 2006 CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS
    IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
    ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
    IEEE 379-2014 IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
    ANS 57.2 : 1983 LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
    ANS 59.3 : 1992(R2002) NUCLEAR SAFETY CRITERIA FOR CONTROL AIR SYSTEMS
    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 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
    IEEE 741-2017 IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
    IEEE 1792-2017 IEEE Recommended Practice for Nuclear Power Generating Station Preferred Power Supply Reliability

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

    IEEE 494-1974 IEEE Standard Method for Identification of Documents Related to Class 1E Equipment and Systems 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 741-2007 IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
    IEEE 535-2006 IEEE Standard for Qualification of Class 1E Lead Storage Batteries for Nuclear Power Generating Stations
    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
    IEEE 317-1983 IEEE Standard for Electric Penetration Assemblies in Containment Structures for Nuclear Power Generating Stations
    IEEE 484-2002 IEEE Recommended Practice for Installation Design and Installation of Vented Lead-Acid Batteries for Stationary Applications
    IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
    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
    IEEE 450-2010 REDLINE IEEE Recommended Practice for Maintenance, Testing, and Replacement of Vented Lead-Acid Batteries for Stationary Applications
    ASME NQA 1 : 2015 Quality Assurance Requirements for Nuclear Facility Applications (NQA-1 - 2015)
    IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
    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 415-1986 IEEE Guide for Planning of Preoperational Testing Programs for Class 1E Power Systems for Nuclear Power Generating Stations
    IEEE 765-2012 IEEE Standard for Preferred Power Supply (PPS) for Nuclear Power Generating Stations (NPGS)
    IEEE 485-2010 IEEE Recommended Practice for Sizing Lead-Acid Batteries for Stationary Applications
    IEEE 338-2012 IEEE Standard for Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety
    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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