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IEEE DRAFT 379 : D5 2000

Superseded
Superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

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superseded

A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.

DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
Superseded date

14-03-2001

Published date

12-01-2013

Overview
1.1 Scope
1.2 Purpose
2 References
3 Definitions
4 Statement of the single-failure criterion
5 Requirements
5.1 Independence and Redundancy
5.2 Nondetectable Failure
5.3 Cascaded Failures
5.4 Design Basis Events and Single Failures
5.5 Common Cause Failures
5.6 Shared systems
6 Design analysis for single-failure
6.1 Procedure
6.2 Systems Portions Analysis
6.3 Other Considerations
7 Bibliography


Covers the application of the single failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems. The purpose is to interpret and provide guidance in the application of the single failure criterion, discuss failures, and present an acceptable method of single failure analysis. It is not the function of this standard to identify where the single failure criterion is to be applied or to force compliance on any system; however, in those cases where the single failure criterion has been invoked, this standard establishes the requirements for its application.

DocumentType
Draft
PublisherName
Institute of Electrical & Electronics Engineers
Status
Superseded
SupersededBy

IEEE 577-2012 IEEE Standard Requirements for Reliability Analysis in the Design and Operation of Safety Systems for Nuclear Power Generating Stations
ANS 51.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY PRESSURIZED WATER REACTOR PLANTS
IEEE 384-2008 REDLINE IEEE Standard Criteria for Independence of Class 1E Equipment and Circuits
ANS 52.1 : 83(R1988) NUCLEAR SAFETY CRITERIA FOR THE DESIGN OF STATIONARY BOILING WATER REACTOR PLANTS
IEEE 352-1987 IEEE Guide for General Principles of Reliability Analysis of Nuclear Power Generating Station Safety Systems
IEEE 308-2012 REDLINE IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations
IEEE 7-4.3.2-2016 IEEE Standard Criteria for Programmable Digital Devices in Safety Systems of Nuclear Power Generating Stations
IEEE 603-2009 REDLINE IEEE Standard Criteria for Safety Systems for Nuclear Power Generating Stations

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