This standard establishes functional and design criteria for nuclear power generating station "safety systems," that is, that collection of systems required to minimize the probability and magnitude of release of…
Cable performance requirements mentioned in this section are particular requirements which should be considered in specifying cable for installation in generating stations. Certain requirements, such as radiation, apply only to…
The protection of nuclear power plants following a design basis event is provided automatically by the protection systems as defined by IEEE Std 279-1971 (ANSI N42.7-1972), Criteria for Protection Systems…
This standard sets forth the requirements for a calibration program to control and verify the accuracy of M&TE (measuring and test equipment) which is used to assure that important parts…
This document interprets the single failure criterion, discusses failures, and presents an acceptable method of single failure analysis for Class IE systems
All of the terms and definitions in this document have been taken from current IEEE standards on nuclear power generating stations. The source of each definition is indicated by a…
This standard describes the qualification of all types of power-driven valve actuators, including damper actuators, for safety-related functions in nuclear power generating stations. This standard may also be used to…
The scope of this document is the independence requirements of the circuits and equipment comprising or associated with Class I E systems. It sets forth criteria for the independence that…
This document applies to the application of diesel-generator units as individual units o f the standby power supplies in stationary landbased nuclear power generating stations.
