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IEEE 7-4.3.2-1993

Historical Revision

IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations

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Revision Standard - Superseded. Additional computer specific requirements to supplement the criteria and requirements of IEEE Std 603-1991 are specified. Within the context of this standard, the term computer is a system that includes computer hardware, software, firmware, and interfaces. The criteria contained herein, in conjunction with criteria in IEEE Std 603-1991, establish minimum functional and design requirements for computers used as components of a safety system.
The use of computers as part of safety systems elicits additional requirements not specifically addressed in IEEE Std 603-1991. This standard serves to amplify criteria in IEEE Std 603-1991 for computers used as components of safety systems in nuclear power generating stations. Within the context of this standard, the term computer is a system that includes computer hardware, software, firmware, and interfaces. The criteria contained herein, in conjunction with criteria in IEEE Std 603-1991, establish minimum functional and design requirements for computers used as components of a safety system.

SDO IEEE: Institute of Electrical and Electronics Engineers
Document Number 7-4.3.2
Publication Date Feb. 3, 1994
Language en - English
Page Count 48
Revision Level
Supercedes
Committee Nuclear Power Engineering Committee
Publish Date Document Id Type View
Aug. 25, 2016 7-4.3.2-2016 Revision
Aug. 2, 2010 7-4.3.2-2010 Revision
Dec. 17, 2003 7-4.3.2-2003 Revision
Feb. 3, 1994 7-4.3.2-1993 Revision