IEEE DRAFT 379 : D5 2000
Superseded
A superseded Standard is one, which is fully replaced by another Standard, which is a new edition of the same Standard.
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DRAFT STANDARD APPLICATION OF THE SINGLE-FAILURE CRITERION TO NUCLEAR POWER GENERATING STATION SAFETY SYSTEMS
14-03-2001
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Superseded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 51.1-1983(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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