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

Editor
Michael G. Stamatelatos
Michael G. Stamatelatos
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Harold S. Blackman
Harold S. Blackman
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ISBN-10:
0791802442
No. of Pages:
2576
Publisher:
ASME Press
Publication date:
2006

An international “BETA project” has been underway since 1995 to 2003. It was based upon an agreement between the U.S. Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation (Gosatomnadzor of Russia). The main task of the project was to transfer advanced nuclear power plant (NPP) probabilistic safety assessment (PSA) methods to the Russian regulatory and operating organizations. This would be achieved by conducting a demonstrative PSA of the Russian Kalinin Nuclear Power Plant (KNPP), Unit 1, VVER-1000 reactor type.

Brookhaven National Laboratory (BNL) and other PSA experts assisted NRC in providing technical and analytical support, training and advice on the project. Six organizations took part in the project from the Russian side. Under the project's auspice Russian team received training and performed PSA Level 1 and Level 2 for the KNPP, covering internal initiating events with the unit at nominal power, including limited consideration of fire, flooding and earthquake.

The BETA project has impacted the developing PSA policy of Russian regulatory body, resulting in improvements in the understanding and regulation of risk-informed PSA application. Experience and knowledge gained from the project are being employed in ongoing Russian Federation regulatory activities.

This paper provides a brief description of the project and its impact on the application of probabilistic safety assessment in regulatory activity in Russia, and a specific description of the Level 1 PSA of KNPP Unit 1.

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