This document was prepared to provide the designers and operators of nuclear power plant protection systems and the concerned regulatory groups with the essential methods and procedures of reliability engineering that are applicable to protection systems. By applying principles given, systems may be analyzed, acceptable test intervals may be established, results may be reconciled with reliability objectives, and the analyses may be suitably documented. The quantitative principles are applicable to the analysis of the effects of random failures on protection system reliability. They are not intended for use in treating the problem of systematic or common-mode failure. The principles are applicable during any phase of a protection system's lifetime. They have their greatest value during the design phase. During this phase reliability engineering can have the greatest effect for enhancing safety. The principles may also be applied during the per-operational phase or at any time during the normal lifetime of a system. When the principles are applied during either of these two phases, they will aid in the evaluation of systems and in improving test programs. Although not inherently limited, these principles are intended for application to systems covered in the scope of IEEE Std 279-1971, Criteria for Protection Systems for Nuclear Power Generating Stations, ANSI N42.7-1972.
- Standard Committee
- PE/NPEC - Nuclear Power Engineering Committee
- Status
- Superseded Standard
- Superseded by
- 352-1987
- Board Approval
- 1974-09-05
- History
-
- ANSI Approved:
- 1976-01-05
- Published:
- 1974-10-31
Working Group Details
- Society
- IEEE Power and Energy Society
- Standard Committee
- PE/NPEC - Nuclear Power Engineering Committee
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.
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.
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.
933-2023
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 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).
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 system's lifetime. They may also be applied during the preoperational phase or at any time during the normal lifetime of a system.
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.
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.
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).
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).
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