IEEE 379-2014
Withdrawn
A Withdrawn Standard is one, which is removed from sale, and its unique number can no longer be used. The Standard can be withdrawn and not replaced, or it can be withdrawn and replaced by a Standard with a different number.
IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems
Hardcopy , PDF
English
30-05-2014
27-03-2025
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
This standard covers 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 |
978-0-7381-9124-9
|
| Pages |
27
|
| PublisherName |
Institute of Electrical & Electronics Engineers
|
| Status |
Withdrawn
|
| 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, |
| IEEE 3006.7-2013 | IEEE Recommended Practice for Determining the Reliability of 7x24 Continuous Power Systems in Industrial and Commercial Facilities |
| ANS 56.7-1978(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 51.1-1983(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 56.4-1983(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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