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Electric power systems in stationary generating stations that provide electric power to the power system are covered. Nomenclature is included for the following interrelated systems: generating unit power system, generating unit auxiliaries power system, station auxiliaries power system, generating unit dc auxiliaries power system, and station dc auxiliaries power system. Nomenclature for instrumentation, controls, or auxiliaries is not included.
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The standard provides criteria for the performance of periodic surveillance testing of nuclear power generating station safety systems. The scope of periodic surveillance testing consists of functional tests and checks, calibration verification, and time response measurements, as required, to verify that the safety system performs its defined safety function. Postmaintenance and post-modification testing are not covered by this document. This standard amplifies the periodic surveillance testing requirements of other nuclear safety-related IEEE standards. Keywords: functional tests, IEEE 338, periodic testing, risk-informed testing, surveillance testing.
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The scope of this document is the independence requirements of the circuits and equipment comprising or associated with Class 1E systems. It sets forth criteria for the independence that can be achieved by physical separation and electrical isolation of circuits and equipment which are redundant but does not address the determination of what is to be considered redundant.
Nuclear power plants --- Nuclear engineering --- Safety measures.
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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 for Nuclear Power Generating Stations, and by required specified manual actions. Following the automatic initiation of the protection systems, the operator has the responsibility of bringing the nuclear power plant to and maintaining it in a safe condition. The operator requires specific information to assist him in fulfilling this role. The scope of this document is limited to the design criteria for the monitoring display instrumentation required by the operator during the post accident period.
Nuclear power plants --- Nuclear facilities --- Safety measures.
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