Active Standard

IEEE 379-2014

IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems

Requirements for the application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating safety systems are provided in this standard.

Sponsor Committee
PE/NPE - Nuclear Power Engineering
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Status
Active Standard
PAR Approval
2010-02-05
Superseding
379-2000
Board Approval
2014-05-16
History
Published:
2014-05-30

Working Group Details

Society
IEEE Power and Energy Society
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Sponsor Committee
PE/NPE - Nuclear Power Engineering
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Working Group
WG_6.3 - Safety Systems and Single-Failure Criteria Working Group
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IEEE Program Manager
Christian Orlando
Contact
Working Group Chair
Francis Novak

P379.1

Guide for Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems

This guide provides guidance on the application of the Single Failure Criterion. Note: the Single Failure Criterion is provided in IEEE Std 603-2018 Clause 5.1.

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603-2018

IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations

Minimum functional and design criteria for the power, instrumentation, and control portions of nuclear power generating station safety systems are established. The criteria are to be applied to those systems required to protect the public health and safety by functioning to mitigate the consequences of design basis events. The intent is to promote appropriate practices for design and evaluation of safety system performance and reliability. Although the standard is limited to safety systems, many of the principles may have applicability to equipment provided for safe shutdown, post-accident monitoring display instrumentation, interlock features, or any other systems, structures, or equipment related to safety.

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379-2000

IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generating Station Safety Systems

Application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems is covered. Conformance with the requirements of IEEE Std 603-1991 and the single-failure criterion as stated in that document is established. Interpretation and guidance in the application of the single-failure criterion, a discussion of the failures, and an acceptable method of single-failure analysis are presented.

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603-2009

IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations

Minimum functional and design criteria for the power, instrumentation, and control portions of nuclear power generating station safety systems are established in this standard. The criteria are to be applied to those systems required to protect the public health and safety by functioning to mitigate the consequences of design basis events. The intent is to promote appropriate practices for design and evaluation of safety system performance and reliability. Although the standard is limited to safety systems, many of the principles may have applicability to equipment provided for safe shutdown, post accident monitoring display instrumentation, preventive interlock features, or any other systems, structures, or equipment related to safety.

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No Inactive-Reserved Standards
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