Comparison of Novovoronezh Unit 5 NPP and South Ukraine Unit 1 NPP Level 1 PRA Results
- Energy and Environmental Science, Inc., P.O. Box 150261, Kew Gardens, NY 11415 (United States)
- Brookhaven National Laboratory, P.O. Box 5000 Upton, NY 11973-5000 (United States)
This paper describes a study undertaken to explain the risk profile differences in the results of PRAs of two similar VVER-1000 nuclear power plants. The risk profile differences are particularly significant in the area of small steam/feedwater line breaks, small-small LOCAs, support system initiators and containment bypass initiators. A top level (limited depth) approach was used in which we studied design differences, major assumptions, data differences, and also compared the two PRA analyses on an element-by-element basis in order to discern the major causative factors for the risk profile differences. We conclude that the major risk profile differences are due to differences in assumptions and engineering judgment (possibly combined with some design and data differences) involved in treatment of uncertain physical phenomena (primarily sump plugging in LOCAs and turbine building steaming effects in secondary system breaks). Additional major differences are attributable to support system characteristics. (authors)
- Research Organization:
- The ASME Foundation, Inc., Three Park Avenue, New York, NY 10016-5990 (United States)
- OSTI ID:
- 21070061
- Resource Relation:
- Conference: 10. international conference on nuclear engineering - ICONE 10, Arlington - Virginia (United States), 14-18 Apr 2002; Other Information: Country of input: France
- Country of Publication:
- United States
- Language:
- English
Similar Records
The role of PRA in the safety assessment of VVER Nuclear Power Plants in Ukraine.
Applying U.S. EOP Analytical Justification Experience for VVER Plants in the Ukraine