Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)
Download citation file:
- Ris (Zotero)
- Reference Manager
A modern full scope Level 1 and Level 2 PSA covers all operational modes for a nuclear power plant. Further the PSA shall be plant specific and reflect the current state of the plant. In a Living PSA the PSA is updated on a regular basis.
PSA requires input data and the quality of these input data affects the quality of the calculated results. There exist today a number of databases that contain information that, to more or less extent, can be used for input data to the PSA-model. These databases can be in-house databases at the plant, national databases or international databases. There exist also databases from non-nuclear industry.
In the nuclear industry in Sweden (and to some extent in Finland) there is an interest to set up a frame of requirements for the handling of data for PSA. These requirements should be used when new data-projects are started and when there is a need for changes in existing systems. The requirements could also be used to modify the data-systems at the plants for logging events from operation and maintenance in that these systems record data in a way that is useful for PSA-modeling.
This paper describes a procedure to identify and formulate appropriate requirements on vital parts of the data processing for PSA.