The application of the single-failure criterion to the electrical power, instrumentation, and control portions of nuclear power generating station safety systems is covered. Conformance with the requirements of IEEE std 603-1991 and the single-failure criterion as stated in that document is established. Interpretation and guidance in the application of the single-failure criterion, a discussion of the failures, and an acceptable method of single-failure analysis are presented.
|Statement||sponsor, Nuclear Power Engineering Committee of the IEEE Power Engineering Society.|
|Series||IEEE std -- 379-1994., IEEE std -- 379-1994.|
|Contributions||IEEE Power Engineering Society. Nuclear Power Engineering Committee., Institute of Electrical and Electronics Engineers., IEEE Standards Board.|
|The Physical Object|
|Pagination||v, 8 p. ;|