Steven Eide Email & Phone Number

Idaho Falls And Sun Valley, Idaho

Idaho Falls And Sun Valley, Idaho

Mr. Eide managed and performed seismic probabilistic risk assessments (PRAs) for two US commercial nuclear power plant sites. He directed two RG 1.200 internal event PRA upgrade projects. Those projects included successfully defending the work during external peer reviews and resolving findings and observations (F&O's). Mr. Eide performed external event screening analyses for three plant sites, including external flooding and local intense precipitation. He also performed various component reliability studies using RADS/EPIX to support plant PRAs and methods development.

Mr. Eide was the principal investigator and principal technical contributor for several major NRC projects. The NRC projects dealt with (1) development and analysis of performance indicators at both the plant level and industry level, (2) development of industry-average performance baselines for component reliability and availability, (3) reevaluation of station blackout risk, and (4) various enhancements to the NRC standardized plant analysis risk (SPAR) models of U.S. commercial nuclear power plants. The performance indicator work included research into risk-based performance indicators at the plant level (NUREG-1753), support in the development of the Mitigating Systems Performance Index (NUREG-1816), and development of the industry-level Baseline Risk Index for Initiating Events (NUREG/CR-6932). Recent work involved a review of MSPI performance during its first years of implementation. Performance indicator projects involved interaction with the NRC, its Advisory Committee on Reactor Safeguards, and the commercial nuclear reactor industry through periodic meetings and workshops. Development of new industry-average baselines for component reliability and availability led to the publishing of NUREG/CR-6928. These baselines have been incorporated into the SPAR models and are being used throughout the commercial nuclear power plant industry. Baselines were developed using the EPIX database that is maintained by the Institute for Nuclear Power Operations. Reevaluation of station blackout risk included data collection and analysis for loss of offsite power frequency and emergency diesel generator reliability and is documented in NUREG/CR-6890. Finally, SPAR model enhancements included work to include external events (seismic, fire, and flood) and support Level 2 (core damage progression and containment response) modeling.

Master Of Science (Ms) And Engineer Degree, Mechanical Engineering

Bachelor'S Degree, Engineering Science