IEEE 384-2008 REDLINE
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
View Superseded by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
19-04-2021
English
20-12-2008
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Superseded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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