IEEE 379-2014
Current
The latest, up-to-date edition.
Hardcopy , PDF
English
05-30-2014
1 Overview
2 Normative references
3 Definitions, acronyms, abbreviations, and terms
4 Statement of the single-failure criterion
5 Requirements
6 Design analysis for single failure
Annex A (informative) - Bibliography
Annex B (informative) - Examples of nondetectable
failures
Defines the application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems.
Committee |
Nuclear Power Engineering Committee
|
DevelopmentNote |
Supersedes IEEE DRAFT 379 (04/2001)
|
DocumentType |
Standard
|
ISBN |
78-0-7381-9124-9
|
Pages |
27
|
PublisherName |
Institute of Electrical & Electronics Engineers
|
Status |
Current
|
Supersedes |
IEEE 497-2010 | IEEE Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations |
ANS 56.5 : 79(R1987) | PWR AND BWR CONTAINMENT SPRAY SYSTEM DESIGN CRITERIA |
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 |
ANS 54.1 : 1989 | GENERAL SAFETY DESIGN CRITERIA FOR A LIQUID METAL REACTOR NUCLEAR POWER PLANT |
ANS 56.10 : 82(R1987) | NUCLEAR REACTORS - SUBCOMPARTMENT PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS IN LIGHT WATER REACTORS |
IEC 63147:2017 | Criteria for accident monitoring instrumentation 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 51.10 : 1991(R2008) | AUXILIARY FEED-WATER SYSTEM FOR PRESSURIZED WATER REACTORS |
IEEE 3006.7-2013 | IEEE Recommended Practice for Determining the Reliability of 7x24 Continuous Power Systems in Industrial and Commercial Facilities |
ANS 56.7 : 78(R1987) | VENTILATION SYSTEMS, BOILING WATER REACTOR CONTAINMENT |
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 |
ANS 56.3 : 77(R1987) | OVERPRESSURE PROTECTION OF LOW-PRESSURE SYSTEMS CONNECTED TO THE REACTOR COOLANT PRESSURE BOUNDARY |
IEEE 279-1971 | IEEE Standard: Criteria for Protection 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 |
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 |
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 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for 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 |
ANSI N13.4 : 71(R1983) | PORTABLE X-OR GAMMA RADIATION SURVEY INSTRUMENTS, SPECIFICATION OF, |
ANS 52.1 : 83(R1988) | NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS |
ANS 56.4 : 83(R1988) | PRESSURE AND TEMPERATURE TRANSIENT ANALYSIS FOR LIGHT WATER REACTOR CONTAINMENTS |
IEEE 308-2020 REDLINE | IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations |
IEEE 384-2018 | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
IEEE/IEC 63147-2017 | IEEE/IEC International Standard - 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 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 7-4.3.2-2010 REDLINE | IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations |
IEEE 384-2008 REDLINE | IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits |
IEEE 352-1987 | IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems |
IEEE 308-2012 REDLINE | IEEE Standard Criteria for Class 1E Power 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 603-2009 REDLINE | IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations |
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