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.
- Sponsor Committee
- PE/NPEC - Nuclear Power Engineering Committee
Learn More About 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- Superseded Standard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- Superseded by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
Learn More About IEEE Power and Energy Society - Sponsor Committee
- PE/NPEC - Nuclear Power Engineering Committee
Learn More About 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.
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.
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.
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.
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.