Probabilistic Risk Assessment Modeling Support for the Full-Scope Site Level 3 PRA Project

Added: Feb 08, 2012 11:17 am

See attached solicitation.

Added: Jan 06, 2012 3:33 pm Modified: Jan 10, 2012 9:38 amTrack Changes A full-scope site Level 3 probabilistic risk assessment (PRA) for a nuclear power plant site can provide valuable insights into the relative importance of various risk contributors by assessing accidents involving one or more reactor cores as well as other site radiological sources (i.e., spent fuel pools and dry storage casks). These insights can be used to further enhance regulatory decision-making and to help focus limited agency resources on issues most directly related to the agency's mission to protect public health and safety.

A full-scope site Level 3 PRA is a complex model that consists of many technical aspects. Each aspect of the PRA must be adequately developed so that the entire PRA may serve its intended function. Some of these technical aspects include, but are not limited to, initiating event analysis, event tree development and analysis, system reliability model (e.g., fault tree) development and analysis, human reliability analysis, data analysis, accident sequence quantification, and uncertainty analysis. A PRA is considered to be full-scope when the technical aspects are adequately developed for all major hazard groups (e.g., internal fire, internal flooding, seismic) and low power and shutdown modes of reactor operation. Additionally, a site PRA is considered to include the risk contributions from initiating events that impact more than one unit at the site; the impact of accidents at one unit on any other units at the site; and non-reactor sources of radiological material, such as spent fuel pools and dry storage casks.

A solicitation with additional details is expected to be issued by January 25, 2012.

Added: Jan 06, 2012 3:33 pm A full-scope site Level 3 probabilistic risk assessment (PRA) for a nuclear power plant site can provide valuable insights into the relative importance of various risk contributors by assessing accidents involving one or more reactor cores as well as other site radiological sources (i.e., spent fuel pools and dry storage casks). These insights can be used to further enhance regulatory decision-making and to help focus limited agency resources on issues most directly related to the agency's mission to protect public health and safety.

A full-scope site Level 3 PRA is a complex model that consists of many technical aspects. Each aspect of the PRA must be adequately developed so that the entire PRA may serve its intended function. Some of these technical aspects include, but are not limited to, initiating event analysis, event tree development and analysis, system reliability model (e.g., fault tree) development and analysis, human reliability analysis, data analysis, accident sequence quantification, and uncertainty analysis. A PRA is considered to be full-scope when the technical aspects are adequately developed for all major hazard groups (e.g., internal fire, internal flooding, seismic) and low power and shutdown modes of reactor operation. Additionally, a site PRA is considered to include the risk contributions from initiating events that impact more than one unit at the site; the impact of accidents at one unit on any other units at the site; and non-reactor sources of radiological material, such as spent fuel pools and dry storage casks.