Skip to Main Content
ASME Press Select Proceedings

Proceedings of the Eighth International Conference on Probabilistic Safety Assessment & Management (PSAM)

Editor
Michael G. Stamatelatos
Michael G. Stamatelatos
Search for other works by this author on:
Harold S. Blackman
Harold S. Blackman
Search for other works by this author on:
ISBN-10:
0791802442
No. of Pages:
2576
Publisher:
ASME Press
Publication date:
2006

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.

This content is only available via PDF.
Close Modal
This Feature Is Available To Subscribers Only

Sign In or Create an Account

Close Modal
Close Modal