Westinghouse is currently conducting the pre-application licensing of the International Reactor Innovative and Secure (IRIS) on behalf of the IRIS Consortium. One of the key aspects of the IRIS design is the concept of safety-by-design. The PRA is being used as an integral part of the design process. As part of this effort, a PRA of the initial design was generated to address two key areas. First, the IRIS PRA supported the evaluation of IRIS design issues by providing a solid risk basis for design and analyses required for the pre-licensing evaluation of the IRIS design. The PRA provides the tool for quantifying the benefit of the safety-by-design approach. Second, the current PRA task is beginning the preparation of the more complete PRA analyses and documentation eventually required for Design Certification. One of the key risk-related goals for IRIS is to reduce the EPZ to within the exclusion area by demonstrating that the off-site doses are consistent with the US Protective Action Guidelines (PAGs) for initiation of emergency response so that the required protective actions would be limited to the exclusion area. The results of the preliminary PRA indicated a core damage frequency of 1.2E−08 for internal initiators. This is a very good result but much work is needed to meet the ambitious goal of no emergency response. The next phase of the PRA analyses will involve a two-fold expansion of the PRA. First, as the design and analyses approach a greater level of detail, the assumptions used for the initial PRA will be reviewed and the models will be revised as needed to reflect the improved knowledge of the system design and performance. Furthermore, as the full plant design advances, the PRA will be expanded to incorporate risk associated with external challenges such as seismic and fire, and to address low power and shutdowns modes of operation. As with the initial work, the PRA will serve as a tool to help improve, not just to evaluate the design.
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12th International Conference on Nuclear Engineering
April 25–29, 2004
Arlington, Virginia, USA
Conference Sponsors:
- Nuclear Engineering Division
ISBN:
0-7918-4689-X
PROCEEDINGS PAPER
IRIS PRA Preliminary Results and Future Direction
David J. Finnicum,
David J. Finnicum
Westinghouse Electric Company, LLC, Windsor, FL
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Charles L. Kling,
Charles L. Kling
Westinghouse Electric Company, LLC, Windsor, FL
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Mario D. Carelli
Mario D. Carelli
Westinghouse Electric Company, LLC, Windsor, FL
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David J. Finnicum
Westinghouse Electric Company, LLC, Windsor, FL
Charles L. Kling
Westinghouse Electric Company, LLC, Windsor, FL
Mario D. Carelli
Westinghouse Electric Company, LLC, Windsor, FL
Paper No:
ICONE12-49500, pp. 229-234; 6 pages
Published Online:
November 17, 2008
Citation
Finnicum, DJ, Kling, CL, & Carelli, MD. "IRIS PRA Preliminary Results and Future Direction." Proceedings of the 12th International Conference on Nuclear Engineering. 12th International Conference on Nuclear Engineering, Volume 3. Arlington, Virginia, USA. April 25–29, 2004. pp. 229-234. ASME. https://doi.org/10.1115/ICONE12-49500
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