NRC SUPPORT FOR THE KALININ (VVER) PROBABILISTIC RISK ASSESSMENT

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The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory ... continued below

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7 pages

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BLEY,D.; DIAMOND,D.J.; CHU,T.L.; AZARM,A.; PRATT,W.T.; JOHNSON,D. et al. October 26, 1998.

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Description

The US Nuclear Regulatory Commission (NRC) and the Federal Nuclear and Radiation Safety Authority of the Russian Federation have been working together since 1994 to carry out a probabilistic risk assessment (PRA) of a VVER-1000 in the Russian Federation. This was a recognition by both parties that this technology has had a profound effect on the discipline of nuclear reactor safety in the West and that the technology should be transferred to others so that it can be applied to Soviet-designed plants. The NRC provided funds from the Agency for International Development and technical support primarily through Brookhaven National Laboratory and its subcontractors. The latter support was carried out through workshops, by documenting the methodology to be used in a set of guides, and through periodic review of the technical activity. The result of this effort to date includes a set of procedure guides, a draft final report on the Level 1 PRA for internal events (excluding internal fires and floods), and progress reports on the fire, flood, and seismic analysis. It is the authors belief that the type of assistance provided by the NRC has been instrumental in assuring a quality product and transferring important technology for use by regulators and operators of Soviet-designed reactors. After a thorough review, the report will be finalized, lessons learned will be applied in the regulatory and operational regimes in the Russian Federation, and consideration will be given to supporting a containment analysis in order to complete a simplified Level 2 PRA.

Physical Description

7 pages

Notes

INIS; OSTI as DE00758986

Source

  • 26TH WATER REACTOR SAFETY MEETING, WASHINGTON, DC (US), 10/26/1998--10/28/1998

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  • Report No.: BNL--NUREG-66229
  • Report No.: 401001060
  • Grant Number: AC02-98CH10886
  • Office of Scientific & Technical Information Report Number: 758986
  • Archival Resource Key: ark:/67531/metadc708052

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  • October 26, 1998

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  • Sept. 12, 2015, 6:31 a.m.

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  • Nov. 9, 2015, 1:28 p.m.

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BLEY,D.; DIAMOND,D.J.; CHU,T.L.; AZARM,A.; PRATT,W.T.; JOHNSON,D. et al. NRC SUPPORT FOR THE KALININ (VVER) PROBABILISTIC RISK ASSESSMENT, article, October 26, 1998; Upton, New York. (digital.library.unt.edu/ark:/67531/metadc708052/: accessed August 19, 2017), University of North Texas Libraries, Digital Library, digital.library.unt.edu; crediting UNT Libraries Government Documents Department.