• IEEE 382-2006

    Superseded A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

    IEEE Standard for Qualification of Safety-Related Actuators for Nuclear Power Generating Stations

    Available format(s):  PDF

    Superseded date:  25-11-2019

    Language(s):  English

    Published date:  15-03-2007

    Publisher:  Institute of Electrical & Electronics Engineers

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

    1 Overview
       1.1 Scope
       1.2 Purpose
    2 Normative references
    3 Definitions
    4 Introduction
       4.1 General
       4.2 Requirements
    5 Identification of the generic actuator group
       5.1 Generic actuator group identification
       5.2 Selection of actuator units for type testing
    6 Qualification testing of selected actuators in generic
       actuator group
       6.1 Type test parameter values
       6.2 Type test plan
       6.3 Type test procedure
       6.4 Inspection
       6.5 Acceptance criteria
       6.6 Generic actuator group design modification
    7 Qualification of actuator for specific application
       7.1 General
       7.2 Actuator specification
       7.3 Relationship to generic actuator group
       7.4 Relationship to specification
    8 Documentation
       8.1 General
       8.2 Documentation for qualification of generic actuator group
       8.3 Documentation for qualification for a specific application
    9 Baseline functional test
       9.1 Scope
       9.2 Test setup requirements
       9.3 Test conduct
    10 Normal thermal aging test
       10.1 Scope
       10.2 Test setup requirements
       10.3 Test conduct
    11 Normal radiation aging test
       11.1 Scope
       11.2 Test setup requirements
       11.3 Test conduct
    12 Cycle aging test
       12.1 Scope
       12.2 Test setup requirements
       12.3 Test conduct
    13 Normal pressurization cycle test
       13.1 Scope
       13.2 Test setup requirements
       13.3 Test conduct
    14 Vibration aging
       14.1 Scope
       14.2 Test setup requirements
       14.3 Test conduct
    15 Seismic simulation test
       15.1 Scope
       15.2 Test setup requirements
       15.3 Test conduct
    16 DBE radiation exposure test
       16.1 Scope
       16.2 Test setup requirements
       16.3 Test conduct
    17 DBE environment test
       17.1 Scope
       17.2 Test setup requirements
       17.3 Test conduct
    Annex A (informative) Method of selection of representative
            actuator(s) for type testing
    Annex B (informative) Rationale for vibration and seismic
            test methods
    Annex C (informative) Performance verification test
    Annex D (informative) Glossary
    Annex E (informative) Bibliography

    Abstract - (Show below) - (Hide below)

    Presents criteria for qualification of safety-related actuators, and actuator components, in Nuclear Power Generating Stations in order to demonstrate their ability to perform their intended safety functions.

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

    Committee Nuclear Power Engineering Committee
    Development Note Supersedes IEEE DRAFT 382. (03/2007)
    Document Type Standard
    Publisher Institute of Electrical & Electronics Engineers
    Status Superseded
    Superseded By
    Supersedes

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

    CSA N289.4 : 2012 TESTING PROCEDURES FOR SEISMIC QUALIFICATION OF NUCLEAR POWER PLANT STRUCTURES, SYSTEMS, AND COMPONENTS
    ASME AG-1 : 2019 CODE ON NUCLEAR AIR AND GAS TREATMENT
    ASME AG 1 : 2012 CODE ON NUCLEAR AIR AND GAS TREATMENT
    ASME QME 1 : 2017 QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES
    IEEE/ANSI N42.4-1971 American National Standard for High Voltage Connectors for Nuclear Instruments
    IEEE 334 : 2007 QUALIFYING CONTINUOUS DUTY CLASS 1E MOTORS FOR NUCLEAR POWER GENERATING STATIONS
    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
    IEEE 279-1971 IEEE Standard: Criteria for Protection Systems 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
    CSA N289.1 : 2008 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
    IEEE 1290-2015 REDLINE IEEE Guide for Motor-Operated Valve (MOV) Motor Application, Protection, Control, and Testing in Nuclear Power-Generating Stations
    IEC/IEEE 60780-323:2016 Nuclear facilities - Electrical equipment important to safety - Qualification
    N289.1-08 (R2013) General requirements for seismic design and qualification of CANDU nuclear power plants
    CSA N289.1 : 2008 : INC : UPD 1 : 2014: R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
    CSA N289.1 : 2008 : INC : UPD 1 : 2015 : R201300 GENERAL REQUIREMENTS FOR SEISMIC DESIGN AND QUALIFICATION OF CANDU NUCLEAR POWER PLANTS
    CSA N290.8 : 2015 TECHNICAL SPECIFICATION REQUIREMENTS FOR NUCLEAR POWER PLANT COMPONENTS
    BS EN 60780-323:2017 Nuclear facilities. Electrical equipment important to safety. Qualification
    N289.4-12 (R2017) Testing procedures for seismic qualification of nuclear power plant structures, systems, and components
    IEEE 323-2003 IEEE Standard for Qualifying Class 1E Equipment 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 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
    I.S. EN 60780-323:2017 NUCLEAR FACILITIES - ELECTRICAL EQUIPMENT IMPORTANT TO SAFETY - QUALIFICATION
    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
    ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
    IEEE 572-2019 IEEE Standard for Qualification of Class 1E Connection Assemblies for Nuclear Power Generating Stations and Other Nuclear Facilities

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

    ASME QME 1 : 2012 QUALIFICATION OF ACTIVE MECHANICAL EQUIPMENT USED IN NUCLEAR FACILITIES
    IEEE 344-2013 IEEE Standard for Seismic Qualification of Equipment for Nuclear Power Generating Stations
    IEEE 101 : 1987 GUIDE FOR THE STATISTICAL ANALYSIS OF THERMAL LIFE TEST DATA
    IEEE 1205-2000 IEEE Guide for Assessing, Monitoring, and Mitigating Aging Effects on Class 1E Equipment Used in 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 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
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