Superseded Standard

IEEE 384-2008

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

The independence requirements of the circuits and equipment comprising or associated with Class 1E systems are described. Criteria for the independence that can be achieved by physical separation and electrical isolation of circuits and equipment that are redundant are set forth. The determination of what is to be considered redundant is not addressed.

Standard Committee
PE/NPEC - Nuclear Power Engineering Committee
Status
Superseded Standard
PAR Approval
2001-03-17
Superseded by
384-2018
Superseding
384-1992
Board Approval
2008-09-26
History
ANSI Approved:
2009-02-10
Published:
2008-12-20

Working Group Details

Society
IEEE Power and Energy Society
Standard Committee
PE/NPEC - Nuclear Power Engineering Committee
Working Group
WG_6.5 - Independence Criteria and Design of Control Boards, Panels, and Racks Working Group
IEEE Program Manager
Christian Orlando
Contact Christian Orlando
Working Group Chair
Matthew Evans

Other Activities From This Working Group

Current projects that have been authorized by the IEEE SA Standards Board to develop a standard.


No Active Projects

Standards approved by the IEEE SA Standards Board that are within the 10-year lifecycle.


384-2018
IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits

The independence requirements of the circuits and equipment comprising or associated with Class 1E systems are described in this standard. Criteria for the independence that can be achieved by physical separation and electrical isolation of circuits and equipment that are redundant are set forth. The determination of what is to be considered redundant is not addressed.

Learn More About 384-2018

420-2023
IEEE Standard for Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations

Design requirements for new and/or modified Class 1E control boards, panels, and racks are specified, and methods to verify that these requirements have been satisfied are established in this standard. Methods for meeting the separation criteria contained in IEEE Std 384™ are addressed. Qualification is also included to address the overall requirements of IEC/IEEE 60780-323 and recommendations of IEC/IEEE 60980-344.

Learn More About 420-2023

These standards have been replaced with a revised version of the standard, or by a compilation of the original active standard and all its existing amendments, corrigenda, and errata.


420-2001
IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations

This standard specifies the design requirements for new and/or modified Class 1E control boards, panels, and racks and establishes the methods to verify that these requirements have been satisfied. Methods for meeting the separation criteria contained in ANSI/IEEE Std 384-1992 are addressed. Qualification is also included to address the overall requirements of ANSI/IEEE Std 323-1983 and ANSI/IEEE Std 344-1987.

Learn More About 420-2001

420-2013
IEEE Standard for the Design and Qualification of Class 1E Control Boards, Panels, and Racks Used in Nuclear Power Generating Stations

This standard specifies the design requirements for new and/or modified Class 1E control boards, panels, and racks and establishes the methods to verify that these requirements have been satisfied. Methods for meeting the separation criteria contained in IEEE Std 384 are addressed. Qualification is also included to address the overall requirements of IEEE Std 323 and recommendations of IEEE Std 344.

Learn More About 420-2013

These standards have been removed from active status through a ballot where the standard is made inactive as a consensus decision of a balloting group.


No Inactive-Withdrawn Standards

These standards are removed from active status through an administrative process for standards that have not undergone a revision process within 10 years.


622-1987
IEEE Recommended Practice for the Design and Installation of Electric Heat Tracing Systems for Nuclear Power Generating Systems

Recommended practices for designing, installing, and maintaining electric heat tracing systems are provided. These electric heat tracing systems are applied, both for critical process temperature control and for process temperature control, on mechanical piping systems that carry borated water, caustic soda, and other solutions. Electric heat tracing systems are also applied on water piping systems to prevent them from freezing in cold weather. The recommendations include identification of requirements, heater design considerations, power systems design considerations, temperature control considerations, alarm considerations, finished drawings and documents, installation of materials, startup testing, temperature tests, and maintenance of electric pipe heating systems.

Learn More About 622-1987

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