Provides criteria for the designer which interpret the requirements of Title 10, Code of Federal Regulations, Part 50, "Licensing of Production and Utilization Facilities, " Appendix A, "General Design Criteria for Nuclear Power Plants, " with respect to design against single failures in safety-related Light Water Reactor (LWR) fluid systems [1]. Means of treating both active and passive failures are addressed for safety-related fluid systems following various initiating events. Current acceptable practice is used as a basis for these criteria. Failure criteria for the electric power systems and the protection systems are provided in IEEE Std 308-1980 "IEEE Standard Criteria for Class 1E Power Systems for Nuclear Power Generating Stations", IEEE Std 279-1971 "IEEE Standard Criteria for Protection Systems for Nuclear Power Generating Stations" (N42.7-1971), IEEE Std 379-1977 "IEEE Standard for Application of the Single-Failure Criterion to Nuclear Power Generating Station Class IE Systems", and IEEE Std 603-1980 "Standard Criteria for Safety Systems for Nuclear Power Generating Stations." {2, 3, 4, 5}. Failures of structural components, such as braces, supports, or restraints, as well as occurrences involving common mode failures, are excluded.
ANSI/ANS 58.9-2002 history
2002ANSI/ANS 58.9-2002 Single Failure Criteria for Light Water Reactor Safety-Related Fluid Systems