The Omaha Public Power District (OPPD) owns and operates the Fort Calhoun Station Unit 1 (FCS), a single unit Pressurized Water Reactor (PWR) plant. This plant was licensed by the U. S. Nuclear Regulatory Commission (NRC) to operate at a core power level of 1500 MWt for a period of 40 years. In 2002 OPPD submitted a license renewal application to the NRC and recently, this application for a license renewal for a period of 20 more years was approved by the NRC. In order to secure the license renewal, the utility evaluated Severe Accident Mitigation Alternatives (SAMAs) and identified potential risk significant and cost-beneficial plant changes. This process consisted of a review of past industry changes obtained via past SAMA analyses and advanced reactor design efforts as well as a review of FCS PSA insights. While most of the industry-based SAMAs were screened out, the internally focused changes were mostly found to be risk significant and cost effective. This paper presents the SAMA analysis performed in support of the FCS license renewal application and discusses the insights from this analysis.
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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
SAMA Analysis in Support of License Renewal Application for the Fort Calhoun Station
Raymond E. Schneider,
Raymond E. Schneider
Westinghouse Electric Company, LLC
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Harold A. Hackerott,
Harold A. Hackerott
Omaha Public Power District
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Mathew C. Jacob
Mathew C. Jacob
Westinghouse Electric Company, LLC
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Raymond E. Schneider
Westinghouse Electric Company, LLC
Harold A. Hackerott
Omaha Public Power District
Mathew C. Jacob
Westinghouse Electric Company, LLC
Paper No:
ICONE12-49544, pp. 239-244; 6 pages
Published Online:
November 17, 2008
Citation
Schneider, RE, Hackerott, HA, & Jacob, MC. "SAMA Analysis in Support of License Renewal Application for the Fort Calhoun Station." 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. 239-244. ASME. https://doi.org/10.1115/ICONE12-49544
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