LEADER 01833nam 2200409 450 001 996279410203316 005 20231208090914.0 010 $a0-7381-0731-X 035 $a(CKB)3780000000093026 035 $a(NjHacI)993780000000093026 035 $a(EXLCZ)993780000000093026 100 $a20231208d1994 uy 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aIEEE Std 7-4.3.2-1993: $eIEEE Standard Criteria for Digital Computers in Safety Systems of Nuclear Power Generating Stations /$fIEEE 210 1$aNew York, USA :$cIEEE,$d1994. 215 $a1 online resource (48 pages) 330 $aAdditional computer specific requirements to supplement the criteria and requirements of IEEE Std 603-1991 are specified. Within the context of this standard, the term computer is a system that includes computer hardware, software, firmware, and interfaces. The criteria contained herein, in conjunction with criteria in IEEE Std 603-1991, establish minimum functional and design requirements for computers used as components of a safety system. 517 $aIEEE Std 7-4.3.2-1993 606 $aNuclear power plants$xElectronic equipment$xStandards 606 $aNuclear power plants$xSafety measures$xStandards 606 $aSystems engineering$xStandards 606 $aInformation technology$xStandards 615 0$aNuclear power plants$xElectronic equipment$xStandards. 615 0$aNuclear power plants$xSafety measures$xStandards. 615 0$aSystems engineering$xStandards. 615 0$aInformation technology$xStandards. 676 $a004.16 801 0$bNjHacI 801 1$bNjHacl 906 $aDOCUMENT 912 $a996279410203316 996 $aIEEE Std 7-4.3.2-1993$93646775 997 $aUNISA