Rasmussen Report WASH

In this period up to the TMI accident, three other facts influenced nuclear safety technology defence against non-natural external events the preparation of the Rasmussen report, WASH 1400 and the introduction of Quality Assurance (QA) in design, construction and operation of plants. 

Rasmussen (1978) Thermal Analyses , The Rasmussen Report, WASH-1400, v.VIII, App.A. 

Rasmussen, N. (1975). Project leader. Reactor Safety Study. Report WASH-1400 NUREG 75/014. US Nuclear Regulatory Commission, Washington, DC. 

Toward the end of the Second World War, systems techniques such as fault tree analysis were introduced in order to predict the reliability and performance of military airplanes and missiles. The use of such techniques led to the formalization of the concept of probabilistic risk assessment (PRA). The publication of the Reactor Safety Study (NRC, 1975)—often referred to as the Rasmussen Report after the name of principal author, or by its subtitle WASH 1400—demonstrated the use of such techniques in the fledgling nuclear power business. Although WASH 1400 has since been supplanted by more advanced analysis techniques, the report was groundbreaking in its approach to system safety. 

Rasmussen, co-ordinator of the famous Reactor Safety Study Wash-1400 (the Rasmussen report), is... 

Obtain a copy of a fault tree analysis for a system and review the analysis and results. You might wish to look at one of the classic reports on nuclear power plant safety Reactor Safety Study An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants, Report WASH-1400, U.S. Nuclear Regulatory Commission, October 1975. (This report is also known as the Rasmussen report.)... 

N.C. Rasmussen, Reactor Safety Study An assessment of accident risk in US commercial nuclear power plants, AEC Report, WASH-1400-MR (NUREG-75/014), United States NRC, Washington, DC, 1975—http //www.iaea.org/inis/collection/NCLCollectionStore/ Public/35/053/35053391.pdf. 

Island/Thurrock Area, HMSO, London, 1978. Rasmussen, Reactor Safety Study An Assessment of Accident Risk in U. S. Commercial Nuclear Power Plants, WASH-1400 NUREG 75/014, Washington, D.C., 1975. Rijnmond Public Authority, A Risk Analysis of 6 Potentially Hazardous Industrial Objects in the Rijnmond Area—A Pilot Study, D. Reidel, Boston, 1982. Considine, The Assessment of Individual and Societal Risks, SRD Report R-310, Safety and Reliability Directorate, UKAEA, Warrington, 1984. Baybutt, Uncertainty in Risk Analysis, Conference on Mathematics in Major Accident Risk Assessment, University of Oxford, U.K., 1986. 

Besides the two methods mentioned in the previous section, also fault tree analysis (FTA) has since the time of the Wash-1400 Report (Rasmussen 1975) been extensively used for evaluating PFD of safety systems. For some more recent applications to SIS, see Paula et al. 1993, Pullum and Bechta Dunga 1996, Summers and Zachary 1999, and Dutuit et al. 2009. 

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