Active PAR

P60880

Nuclear power plants–Instrumentation and control systems important to safety–Software aspects for computer-based systems performing category A functions

This standard provides requirements for the software of computer-based Instrumentation and control systems of nuclear power plants performing functions of safety category A as defined by IEC (International Electrotechnical Commission) 61226. This standard provides requirements for the purpose of achieving highly reliable software. It addresses each stage of software development and documentation, including requirements specification, design, implementation, verification, validation and operation.

Sponsor Committee
PE/NPEC - Nuclear Power Engineering Committee
Learn More About PE/NPEC - Nuclear Power Engineering Committee
Status
Active PAR
PAR Approval
2024-09-26

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_6.4 - Programmable Digital Computers to Safety Systems Working Group
IEEE Program Manager
Christian Orlando
Contact Christian Orlando
Working Group Chair
Raymond Herb

Other Activities From This Working Group

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


P63160
Nuclear Power Plants - Instrumentation, Control and Electrical Power Systems Important to Safety - Common Cause Failure Systems Analysis and Diversity

This standard establishes the principles of analysis for and the documentation of the defenses provided against Common Cause Failure (CCF) of Electrical, Instrumentation and Control systems in nuclear facilities. It covers CCF from hazards and also from systematic faults. The standard does not provide requirements on detailed design or of acceptance criteria for the adequacy of CCF defense.

Learn More About P63160

P7-4.3.2
Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations

This standard serves to amplify criteria in IEEE Std 603(TM), to address the use of programmable digital devices as part of safety systems in nuclear power generating stations. The criteria contained herein, in conjunction with criteria in IEEE Std 603, establish minimum functional, performance and design requirements for programmable digital devices used as components of a safety system.

Learn More About P7-4.3.2

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


7-4.3.2-2016
IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations

Additional specific requirements to supplement the criteria and requirements of IEEE Std 603(TM) are specified for programmable digital devices. Within the context of this standard, the term programmable digital device is any device that relies on software instructions or programmable logic to accomplish a function. Examples include a computer, a programmable hardware device, or a device with firmware. Systems using these devices will also be referred to as digital safety systems in this standard. The criteria contained herein, in conjunction with criteria in IEEE Std 603, establish minimum functional and design requirements for programmable digital devices used as components of a safety system

Learn More About 7-4.3.2-2016

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.


7-4.3.2-2003
IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations

Additional computer specific requirements to supplement the criteria and requirements of IEEE Std 603-1998 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 603-1998, establish minimum functional and design requirements for computers used as components of a safety system.

Learn More About 7-4.3.2-2003

7-4.3.2-2010
IEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations

Additional computer specific requirements to supplement the criteria and requirements of IEEE Std 603-2009 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 603-2009, establish minimum functional and design requirements for computers used as components of a safety system.

Learn More About 7-4.3.2-2010

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.


No Inactive-Reserved Standards
Subscribe to our Newsletter

Sign up for our monthly newsletter to learn about new developments, including resources, insights and more.