01937nam 2200373 450 991013642440332120231206214252.01-5044-0367-310.1109/IEEESTD.1977.7426304(CKB)3710000000609618(NjHacI)993710000000609618(EXLCZ)99371000000060961820231206d1977 uy 0engur|||||||||||txtrdacontentcrdamediacrrdacarrierIEEE Std 497-1977 IEEE Trial Use Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations /Institute of Electrical and Electronics EngineersPiscataway, NJ, USA :IEEE,1977.1 online resource (12 pages)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.IEEE Std 497-1977Nuclear power plantsSafety measuresNuclear facilitiesSafety measuresNuclear power plantsSafety measures.Nuclear facilitiesSafety measures.621.4835NjHacINjHaclDOCUMENT9910136424403321IEEE Std 497-19773647080UNINA