IEEE 577-2004 pdf download IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Facilities
1. Overview
1.1 Scope
This standard sets forth the minimum acceptable requirements for the performance of reliability analyses forsafety-related systems when used to address the reliability considerations discussed in the standards listed inClause 2.
The methods of this standard ay also be applied to other systems, including the interactions, if any.between safety-related and non-safety-related systems. The requirements should be applied during thehases of design, fabrication, testing, maintenance, and repair of systems and components in nuclearfacilities. The timing of the analysis depends upon the purpose for which the analysis is performed. Thisstandard applies to the facility owner and other organizations responsible for the activities previously stated
1.2 Purpose
The purpose of this standard is to provide uniform, minimum acceptable requirements for the performanceof reliability analyses for safety-related systems found in nuclear facilities, but not to define the need for ananalysis. The need for reliability analysis has been identified in other standards that expand the requirements(e.g., IEEE Std 379-2000,’ which describes the application of the single-failure criterion).
IEEE Std 352″*-1987 provides guidance in the application and use of reliability techniques referred to in thisstandard.
2. References
This standard applies to all safety-related systems, or portions of said systems, for which reliabilityconsiderations are discussed, as in the following lEEE standards. When the standards are superseded by anapproved revision, the revision shall apply
IEEE Std 308”-2001, IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power GeneratingStations.2,3
IEEE Std 338-1987 (Reaff 2000) IEEE Standard Criteria for the Periodic Surveillance Testing of NuclearPower Generating Station Safety Systems.
IEEE Std 352-1987 (Reaff 1999) IEEE Guide for General Principles of Reliability Analysis of NuclearPower Generating Station Safety Systems.
IEEE Std 379-2000, IEEE Standard Application of the Single-Failure Criterion to Nuclear Power Generat-ing Station Safety Systems.
IEEE Std 603″“-1998. IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations
3. Definitions
The following definitions establish the meaning of words in the context of their use in this standard. Otherdefinitions can be found in IEEE Std 352-1987.
3.1 availability: The characteristic of an item expressed by the probability that it will be operational at arandomly selected future instant in time.
3.2 reliability: The characteristic of an item expressed by the probability that it will perform a requiredfunction under stated conditions for a stated time.
4. Requirements
4.1 General
The purpose of reliability analysis is to assist in assuring that the nuclear-plant, safety-related systems withinthe scope of this standard will perform their required functions with an acceptable probability of successThe actions required to perform a reliability analysis and evaluate results of the analysis include one or moreof the following elements:
IEEE 577-2004 pdf download
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