LEADER 02553nam 2200349 450 001 9910136269103321 005 20231206214108.0 010 $a1-5044-0749-0 024 7 $a10.1109/IEEESTD.1974.7409888 035 $a(CKB)3710000000595629 035 $a(NjHacI)993710000000595629 035 $a(EXLCZ)993710000000595629 100 $a20231206d1974 uy 0 101 0 $aeng 135 $aur||||||||||| 181 $ctxt$2rdacontent 182 $cc$2rdamedia 183 $acr$2rdacarrier 200 10$aANSI/IEEE Std 352-1975 (Revision of IEEE Std 352-1972) $eIEEE guide for general principles of reliability analysis of nuclear power generating station protection systems /$fInstitute of Electrical and Electronics Engineers 210 1$aPiscataway, New Jersey :$cIEEE,$d1974. 215 $a1 online resource (75 pages) 330 $aThis document was prepared to provide the designers and operators of nuclear power plant protection systems and the concerned regulatory groups with the essential methods and procedures of reliability engineering that are applicable to protection systems. By applying principles given, systems may be analyzed, acceptable test intervals may be established, results may be reconciled with reliability objectives, and the analyses may be suitably documented. The quantitative principles are applicable to the analysis of the effects of random failures on protection system reliability. They are not intended for use in treating the problem of systematic or common-mode failure. The principles are applicable during any phase of a protection system's lifetime. They have their greatest value during the design phase. During this phase reliability engineering can have the greatest effect for enhancing safety. The principles may also be applied during the per-operational phase or at any time during the normal lifetime of a system. When the principles are applied during either of these two phases, they will aid in the evaluation of systems and in improving test programs. Although not inherently limited, these principles are intended for application to systems covered in the scope of IEEE Std 279-1971, Criteria for Protection Systems for Nuclear Power Generating Stations, ANSI N42.7-1972. 517 $aANSI/IEEE Std 352-1975 606 $aNuclear power plants$xSafety measures 615 0$aNuclear power plants$xSafety measures. 676 $a621.4835 801 0$bNjHacI 801 1$bNjHacl 906 $aDOCUMENT 912 $a9910136269103321 996 $aANSI$92072434 997 $aUNINA