352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems

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Organization: IEEE - Institute of Electrical and Electronics Engineers, Inc.
Publication Date: 1 January 1987
Status: active
Page Count: 147
ICS Code (Nuclear power plants. Safety): 27.120.20
ISBN (Online): 0-7381-0685-2
DOI: 10.1109/IEEESTD.1987.101069

Abstracts

Standard

The standard provides the user with basic principles needed to conduct a reliability analysis of safety systems for nuclear power generating stations. These principles, together with further information provided in the references, are sufficient to develop a reliability/availability analysis not only for nuclear power plant safety systems, but for other protection systems as well. A user may select a specific section of the standard that applies to the particular needs of his/her organization. Some areas discussed are: quantitative analysis and mathematical modeling; problems of failure data; probability distribution, estimation, and confidence intervals used in evaluating failure and repair rate data; and information on established data programs. Application of the principles and procedures of reliability engineering that are presented will allow designers and operators to analyze the system, compare the results with reliability objectives, and suitably document the basis for decisions made at various phases of the system's lifetime.<>

Document History

352-2016 - IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities
April 7, 2017 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

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.

P352/D4D6, Feb 2016 - IEEE Approved Draft Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities
January 1, 2016 - IEEE - Institute of Electrical and Electronics Engineers, Inc.
A description is not available for this item.
P352/D5, Feb 2016 - IEEE Draft Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Systems and Other Nuclear Facilities
January 1, 2016 - IEEE - Institute of Electrical and Electronics Engineers, Inc.
A description is not available for this item.
ST 352:2013 - Payload Identification Codes for Serial Digital Interfaces
February 5, 2013 - Society of Motion Picture and Television Engineers

This standard defines the specification of a 4-byte payload identifier that describes aspects of the payload carried on the SMPTE Serial Digital Interface (SDI) such as: the digital interface standard; picture rate; sampling structure; aspect ratio; colorimetry; bit depth and channel or link assignm...

ST 352:2011 - Payload Identification Codes for Serial Digital Interfaces
March 30, 2011 - Society of Motion Picture and Television Engineers

This standard defines the specification of a 4-byte payload identifier which may be added to digital interfaces for the purpose of identifying the payload. The payload identifier is applicable to all serial digital interfaces and all payloads that produce a directly viewable image on a display devic...

352-1987 - IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
January 1, 1987 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

The standard provides the user with basic principles needed to conduct a reliability analysis of safety systems for nuclear power generating stations. These principles, together with further information provided in the references, are sufficient to develop a reliability/availability analysis not onl...

352-1975 - IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Protection Systems
October 31, 1974 - IEEE - Institute of Electrical and Electronics Engineers, Inc.

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...

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