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IEEE 384-2008 REDLINE

Superseded

Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

View Superseded by

IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits

Available format(s)

PDF

Superseded date

19-04-2021

Language(s)

English

Published date

20-12-2008

£144.30
Excluding VAT

1 Overview
  1.1 Scope
  1.2 Purpose
2 Normative references
3 Definitions
4 General independence criteria
  4.1 Required independence
  4.2 Methods of achieving independence
  4.3 Equipment and circuits requiring independence
  4.4 Compatibility with auxiliary supporting features
  4.5 Associated circuits
  4.6 Non-Class 1E circuits - General criteria
  4.7 Mechanical systems
  4.8 Structures and equipment
  4.9 Fire protection systems
  4.10 Fire
  4.11 Electromagnetic interference/radio frequency
       interference (EMI/RFI)
5 Specific separation criteria
  5.1 Cables and raceways
  5.2 Standby power supply
  5.3 DC system
  5.4 Distribution system
  5.5 Containment electrical penetrations
  5.6 Control switchboards
  5.7 Instrumentation cabinets
  5.8 Sensors
  5.9 Actuated equipment
  5.10 EMI/RFI
6 Specific electrical isolation criteria
  6.1 Power circuits
  6.2 Instrumentation and control circuits
Annex A (informative) Bibliography
Annex B (informative) Relationship of cable testing programs
        to IEEE Std 384
Annex C (informative) Application of separation criteria
        to fiber-optic cable

Specifies the independence requirements of the circuits and equipment comprising or associated with Class 1E systems.

Committee
Nuclear Power Engineering Committee
DocumentType
Standard
ISBN
978-0-7381-5788-7
Pages
39
PublisherName
Institute of Electrical & Electronics Engineers
Status
Superseded
SupersededBy
Supersedes

IEEE 741-2007 IEEE Standard Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
IEEE 690-2004 IEEE Standard for the Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating Stations
IEEE 946-2004 IEEE Recommended Practice for the Design of DC Auxiliary Power Systems for Generating Systems
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 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
ANS 59.2-1985 NUCLEAR POWER PLANTS - HVAC SYSTEMS LOCATED OUTSIDE PRIMARY CONTAINMENT, SAFETY CRITERIA FOR,
ASME AG 1 : 2012 CODE ON NUCLEAR AIR AND GAS TREATMENT
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 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 387-1995 IEEE Standard Criteria for Diesel-Generator Units Applied as Standby Power Supplies for Nuclear Power Generating Stations
IEEE DRAFT 379 : D5 2000 DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
IEEE C62.23-1995 IEEE Application Guide for Surge Protection of Electric Generating Plants
ANS 56.2-1984(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
IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
IEEE 497-2010 IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations
PD IEC/TR 63084:2017 Nuclear power plants. Instrumentation and control important to safety. Platform qualification for systems important to safety
ANSI N13.4 : 71(R1983) PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF,
IEEE 979-2012 IEEE Guide for Substation Fire Protection
IEEE DRAFT 848 : D17 JAN 96 DRAFT STANDARD PROCEDURE FOR THE DETERMINATION OF THE AMPACITY DERATING OF FIRE PROTECTED CABLES
ANS 58.6-1996(R2001) CRITERIA FOR REMOTE SHUTDOWN FOR LIGHT WATER REACTORS
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
BS IEC 63147:2017 Criteria for accident monitoring instrumentation for nuclear power generating stations
IEEE DRAFT 741 : D1 2006 CRITERIA FOR THE PROTECTION OF CLASS 1E POWER SYSTEMS AND EQUIPMENT IN NUCLEAR POWER GENERATING STATIONS
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems 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 57.2-1983 LIGHT WATER REACTOR SPENT FUEL STORAGE FACILITIES, REQUIREMENTS FOR,
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
ISA 67.01 : 1994 TRANSDUCER AND TRANSMITTER INSTALLATION FOR NUCLEAR SAFETY APPLICATIONS
IEEE 741-2017 IEEE Standard for Criteria for the Protection of Class 1E Power Systems and Equipment in Nuclear Power Generating Stations
IEEE 650-2017 IEEE Standard for Qualification of Class 1E Static Battery Chargers, Inverters, and Uninterruptible Power Supply Systems for Nuclear Power Generating Stations

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 628-2011 IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations
IEEE 628-2001 IEEE Standard Criteria for the Design, Installation, and Qualification of Raceway Systems for Class 1E Circuits for Nuclear Power Generating Stations
NFPA 803 : 1998 FIRE PROTECTION FOR LIGHT WATER NUCLEAR POWER PLANTS
IEEE 383-2003 IEEE Standard for Qualifying Class 1E Electric Cables and Field Splices for Nuclear Power Generating Stations
IEEE 383-2015 IEEE Standard for Qualifying Electric Cables and Splices for Nuclear Facilities
NFPA 80A : 2017 PROTECTION OF BUILDINGS FROM EXTERIOR FIRE EXPOSURES
IEEE 338-2006 IEEE Standard Criteria for the Periodic Surveillance Testing of Nuclear Power Generating Station Safety Systems
IEEE/ASTM SI_10-2010 American National Standard for Metric Practice
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 308-2001 IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
ANS 58.2-1988 DESIGN BASIS FOR PROTECTION OF LIGHT WATER NUCLEAR POWER PLANTS AGAINST THE EFFECTS OF POSTULATED PIPE RUPTURE
IEEE 690-2004 IEEE Standard for the Design and Installation of Cable Systems for Class 1E Circuits in Nuclear Power Generating Stations
NFPA 30 : 2018 FLAMMABLE AND COMBUSTIBLE LIQUIDS CODE
IEEE 603-1998 IEEE Standard Criteria for Safety 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 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations

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