SAFETY P R A C TIC E S - gnssn - International Atomic Energy Agency

This publication is no longer validPlease see http://www-ns.iaea.org/standards/550553561570581586590591592593599600605611618631632635640648Safety of nuclear installations: Future directionComputer codes for Level 1 probabilistic safetyassessmentReviewing computer capabilities in nuclear power plantsOSART mission highlights 1988-1989Safety implications of computerized process controlin nuclear power plantsSimulation of a loss of coolant accident with rupturein the steam generator hot collectorCase study on the use of PSA methods:Determining safety importance of systems and componentsat nuclear power plantsCase study on the use of PSA methods:Backfitting decisionsCase study on the use of PSA methods:Human reliability analysisCase study on the use of PSA methods:Station blackout risk at Millstone Unit 3Use of probabilistic safety assessment to evaluate nuclearpower plant technical specificationsNumerical indicators of nuclear power plant safetyperformanceOSART good practices: 1986-1989Use of plant specific PSA to evaluate incidents atnuclear power plantsHuman reliability data collection and modellingReviewing reactor engineering and fuel handling:Supplementary guidance and reference material forIAEA OSARTsASSET guidelines: Revised 1991 editionOSART guidelines: 1992 editionRanking of safety issues for WWER-440 model 230nuclear power plantsProcedures for conducting common cause failure analysisin probabilistic safety assessment1990199019901990199119911991199119911991199119911991199119911992199119921992199284