Technical guidance for siting criteria development

Scoping Study Investigating PWR Instrumentation during a Severe Accident Scenario

“…The NRC initiated the SOARCA project 9 to develop best estimates of the offsite radiological health consequences for a set of important severe reactor accidents for two representative nuclear power plants: the Peach Bottom BWR 10 and the Surry PWR. 11 The SOARCA project evaluated plant improvements and modeling changes not reflected in earlier NRC efforts, such as "Technical Guidance for Siting Criteria Development" (NUREG/CR-2239), 14 "Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants," (NUREG-1150), 15 and "Reactor Safety Study: An Assessment of Accident Risks in U.S. Commercial Nuclear Power Plants" (WASH-1400). 16 Improvements and changes not reflected in earlier assessments include enhancements in systems, training and emergency procedures, offsite emergency response, and security-related measures, as well as plant modifications, such as power uprates and operating fuel at higher burnup.…”

Sandia National Laboratories performance assessment methodology for long-term environmental programs : the history of nuclear waste management.

“…This work led to the publication of the Reactor Safety Study (WASH-1400(NRC 1975, which set the stage for the probabilistic risk methodology used to evaluate nuclear power plants. By the late 1970s and early 1980s, SNL was advocating a probabilistic approach for the modeling of geologic waste repositories, which was influenced by the earlier involvement on WASH-1400, as well as ongoing consequence analyses that SNL developed for the NRC, specifically CRAC-II (Aldrich, et al 1982), and NUREG-1150 (NRC 1990). Concurrent with work on NUREG-1150, SNL was also applying the probabilistic risk assessment methodology to the evaluation of the reliability of nuclear weapons systems (Carlson, et al 1991).…”

“…This work led to the publication of the Reactor Safety Study (WASH-1400(NRC 1975, which set the stage for the probabilistic risk methodology used to evaluate nuclear power plants. By the late 1970s and early 1980s, SNL was advocating a probabilistic approach to the modeling of geologic waste repositories (Campbell, Dillon, et al 1978, Runkle, Cranwell and Johnson 1981, Cranwell, Campbell and Helton, et al 1987, which was influenced by SNL's investigations and PA for the SDP as well as the involvement on WASH-1400 (NRC 1975) and ongoing consequence analyses that SNL developed for the NRC, specifically CRAC-II (Aldrich, et al 1982) and NUREG-1150(NRC 1990. A timeline of the SNL support to NRC, shown against the backdrop of other contemporary developments in PA, is shown in Figure 21.…”

Health effects models for nuclear power plant accident consequence analysis. Modification of models resulting from addition of effects of exposure to alpha-emitting radionuclides: Revision 1, Part 2, Scientific bases for health effects models, Addendum 2

“…Table 1.1 lists the radionuclides and lung clearance classes used in MACCS. The relative values obtained by such calculations were then scaled by the release fractions specified for a particular release scenario called SSTl (Aldrich and Sprung, 1982) to obtain an indication of the potential importance of various elements/nuclides in producing early-or late-occurring health effects. These calculations showed that alpha-emitting radionuclides of elements such as Pu, Am, and Cm can contribute to both the earlyand late-occurring health effects that might result from a nuclear reactor accident.…”