Kalinin VVER-1000 Nuclear Power Station Unit 1 PRA: Procedure Guides for a Probabilistic Risk Assessment (NUREG/CR-6572, BNL-NUREG-52534-R1, Revision 1, English Version)
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Manuscript Completed: May 2005
Date Published: December 2005
The Joint Cooperative Program Between the Governments of the United States and Russia
The BETA Project
J. Lehner et al.
Brookhaven National Laboratory
Upton, New York 11973-5000
J. Lane, NRC Project Manager
Division of Risk Analysis and Applications
Office of Nuclear Regulatory Research
U.S. Nuclear Regulatory Commission
Washington, DC 20555-0001
NRC Job Code R2001
In order to facilitate the probabilistic risk assessment (PRA) of a VVER-1000 nuclear power plant, a set of procedure guides has been written. These procedure guides, along with training supplied by experts and supplementary material from the literature, were used to advance the PRA carried out for the Kalinin Nuclear Power Station in the Russian Federation. Although written for a specific project, these guides have general applicability. Guides are procedures for all the technical tasks of a Level 1 (determination of core damage frequency for different accident scenarios), Level 2 (probabilistic accident progression and source term analysis), and Level 3 (consequence analysis and integrated risk assessment) PRA. In addition, introductory material is provided to explain the rationale and approach for a PRA. Procedure guides are also provided on the documentation requirements.