LEADER 01937nam  2200373   450 
001 9910136424403321
005 20231206214252.0
010   $a1-5044-0367-3
024 7 $a10.1109/IEEESTD.1977.7426304
035   $a(CKB)3710000000609618
035   $a(NjHacI)993710000000609618
035   $a(EXLCZ)993710000000609618
100   $a20231206d1977      uy             0
101 0 $aeng
135   $aur|||||||||||
181   $ctxt$2rdacontent
182   $cc$2rdamedia
183   $acr$2rdacarrier
200 10$aIEEE Std 497-1977 $eIEEE Trial Use Standard Criteria for Accident Monitoring Instrumentation for Nuclear Power Generating Stations /$fInstitute of Electrical and Electronics Engineers
210  1$aPiscataway, NJ, USA :$cIEEE,$d1977.
215   $a1 online resource (12 pages)
330   $aThe 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.
517   $aIEEE Std 497-1977
606   $aNuclear power plants$xSafety measures
606   $aNuclear facilities$xSafety measures
615  0$aNuclear power plants$xSafety measures.
615  0$aNuclear facilities$xSafety measures.
676   $a621.4835
801  0$bNjHacI
801  1$bNjHacl
906   $aDOCUMENT
912   $a9910136424403321
996   $aIEEE Std 497-1977$93647080
997   $aUNINA