Active Standard

IEEE 933-2023

IEEE Approved Draft Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities

Guidelines for the definition of a reliability program at nuclear power generating stations and other nuclear facilities are provided. The document emphasizes reliability programs during the operating phase of such stations; however, the general approach applies to all phases of the nuclear power generating station life cycle (e.g., design, construction, start-up, operating, and decommissioning).

Sponsor Committee
PE/NPEC - Nuclear Power Engineering Committee
Learn More About PE/NPEC - Nuclear Power Engineering Committee
Status
Active Standard
PAR Approval
2021-03-25
Superseding
933-2013
Board Approval
2023-11-08

Working Group Details

Society
IEEE Power and Energy Society
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Sponsor Committee
PE/NPEC - Nuclear Power Engineering Committee
Learn More About PE/NPEC - Nuclear Power Engineering Committee
Working Group
WG_3.3 - Reliability
IEEE Program Manager
Christian Orlando
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Working Group Chair
Khoi Nguyen

Other Activities From This Working Group

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


P352

Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities

This guide contains general reliability and availability analysis methods that can be applied to structures, systems, and components (SSCs) in nuclear power generating stations and other nuclear facilities.

Learn More About P352

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


352-2016

IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities

General reliability and availability analysis methods that can be applied to structures, systems, and components (SSCs) in nuclear power generating stations and other nuclear facilities are contained in this guide.

Learn More About 352-2016

577-2022

IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations and Other Nuclear Facilities

The minimum acceptable requirements for the performance of reliability analyses for safety systems when used to address the reliability considerations discussed in industry standards and guidelines are set forth in this standard. The requirement that a reliability analysis be performed does not originate with this standard. However, when reliability analysis is used to demonstrate compliance with reliability requirements, this standard describes an acceptable response to the requirements.

Learn More About 577-2022

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.


352-1987

IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems

The basic principles that are needed to conduct a reliability analysis of safety systems are provided for designers and operators of nuclear power plant safety systems and the concerned regulatory groups. By applying the principles given, systems may be analyzed, results may be compared with reliability objectives, and the basis for decisions may be suitably documented. The quantitative principles are applicable to the analysis of the effects of component failures on safety system reliability. Although they have their greatest value during the design phase, the principles are applicable during any phase of the systemu00d5s lifetime. They may also be applied during the preoperational phase or at any time during the normal lifetime of a system.

Learn More About 352-1987

577-2004

IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities

This standard sets forth minimum acceptable requisites for the performance of reliability analyses for safety-related systems of nuclear facilities when used to address the reliability requirements identified in regulations and other standards. The requirement that a reliability analysis be performed does not originate with this standard. However, when reliability analysis is used to demonstrate compliance with reliability requirements, this standard describes an acceptable response to the requirements.

Learn More About 577-2004

577-2012

IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations

The minimum acceptable requirements for the performance of reliability analyses for safety systems when used to address the reliability considerations discussed in industry standards and guidelines are set forth in this standard. The requirement that a reliability analysis be performed does not originate with this standard. However, when reliability analysis is used to demonstrate compliance with reliability requirements, this standard describes an acceptable response to the requirements.

Learn More About 577-2012

933-1999

IEEE Guide for the Definition of Reliability Program Plans for Nuclear Power Generating Stations

Guidelines for the definition of a reliability program at nuclear power generating stations are developed. Reliability programs during the operating phase of such stations are emphasized; however, the general approach applies to all phases of the nuclear power generating station life cycle (e.g., design, construction, start-up, operating, and decommissioning).

Learn More About 933-1999

933-2013

IEEE Guide for the Definition of Reliability Program Plans for Nuclear Generating Stations and Other Nuclear Facilities

Guidelines for the definition of a reliability program at nuclear generating stations and other nuclear facilities are provided. The document emphasizes reliability programs during the operating phase of such stations; however, the general approach applies to all phases of the nuclear power generating station life cycle (e.g., design, construction, start-up, operating, and decommissioning).

Learn More About 933-2013

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.


No Inactive-Reserved Standards
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