Our team provides a full range of PSA and reliability services for nuclear and non-nuclear clients. Our team members have a high degree of technical and project management experience. Our varied backgrounds in deterministic and PSA applications provide a broad knowledge of different analysis approaches that can be applied as needed to accomplish a project. This broad basis allows for easy assimilation of information or work products generated by other organizations. Our team’s experience has been demonstrated by a history of successfully completed projects within budget and on schedule, and by a continuity of client requests for follow-on services. Meet some of our team members below.
Team Member Bios
Our team members each have their own engineering specialties. Specialties include data, external events (non-seismic), seismic events, initiating events, system modeling, accident sequence modeling, MAAP/severe accidents, quantification and human factors. Each engineering specialty is assigned team members with primary and secondary responsibilities.
Ricky L. Summitt
Mr. Summitt provides technical and project management expertise for a variety of projects requiring engineering analysis. Over the course of his thirty years of experience in risk analysis he has used both deterministic and probabilistic techniques to manage and supply lead technical guidance in the assessment of safety and reliability concerns for both nuclear and chemical projects.
He has conducted HAZOP and other qualitative assessments of chemical facilities to evaluate safety concerns. Mr. Summitt has also managed and participated in probabilistic risk assessments for pressurized water reactors, boiling water reactors, chemical facilities, and enrichment facilities that addressed both internal and external events.
He has utilized the Modular Accident Analysis Program (MAAP) for containment analysis. He was involved in the development of severe accident guidance for advanced reactors and supported the industry-funded IDCOR program.
Mr. Summitt has authored several software packages in various languages, including a full-scope PSA package (PRAMS), a seismic risk analysis application (SIP), and database management suite (DBM). All are being used successfully in the industry.
He has also authored or coauthored over one hundred technical reports and papers that have been presented at both national and international conferences on PSA. He has provided training on PRA topics ranging from data development to internal flooding analysis for several nuclear utilities and other organizations. A listing of publications is available upon request.
Jodine Jansen Vehec
Ms. Jansen Vehec has over twenty years of experience performing PSA and safety assessment evaluations for both nuclear and non-nuclear facilities. Ms. Jansen Vehec also has experience in evaluating nuclear waste, hazardous waste, fissile waste and mixed waste operations. Her safety assessment experience includes performance of probabilistic risk analysis, reliability, availability and maintainability (RAM) assessments, safety assessments, accident sequence assessments and fire dispersion analysis.
Ms. Jansen Vehec has experience in the development and review of documentation including: safety analysis reports, limiting conditions for operation documentation, and other safety assessment documents. She has knowledge of, and experience with, several of the most utilized PSA software packages including the CAFTA and Risk Spectrum suite of codes. She also has an application-level of experience with the Modular Accident Analysis Program (MAAP).
Ms. Jansen Vehec's publications are available upon request.
Jeffrey D. Miller, PE
Mr. Miller provides technical support for a variety of projects requiring engineering analysis. He has participated in probabilistic safety assessments for pressurized water reactors and boiling water reactors that addressed internal and external events. He has utilized the Modular Accident Analysis Program (MAAP) for containment analysis. Mr. Miller has also utilized the Severe Accident Management Guidelines (SAMG) and Integrated Leak Rate Test (ILRT) for plant updates as well as detailed fault tree modeling. He has worked with database management suite (DBM) for plant-specific maintenance unavailability and component failure rates, the Ricky Summitt Consulting, Inc. (RSC) fire analysis tool FATCAT, the RSC proprietary BWR initiating events database for PSA applications, the RSC tool internal flooding and the RSC results analysis tool. He has also worked with fire analysis tools such as CFAST, FDS/PyroSim and the NRC Fire Dynamic Tools. Mr.
Miller has additional relevant training through engineering co-op jobs including experience with project management, engineering change procedures, quality control review practices and certified quality assurance programs.
Mr. Miller has authored or coauthored technical reports and papers on various topics that have been formally published and presented at industry topical meetings. A list of publications is available upon request.
Bruce W. Logan
Mr. Logan provides technical and management expertise in projects involving the development of engineering models and their application to plant operation. His more than thirty years of experience in reliability and risk analyses have created an extensive background in the development of plant equipment performance databases, probabilistic safety analysis (PSA) model development, and the incorporation of PSA results into plant operation.
Mr. Logan's experience includes twelve years working for an electric utility working with nuclear power plants, eighteen years with a not-for-profit institute associated with nuclear power plant operation oversight, and over five years as a risk analysis consultant. This experience has produced a broad background in risk assessment in nuclear power operations, including both management and technical responsibilities.
Mr. Logan has helped in the development of several industry databases, including the Nuclear Plant Reliability Data System (NPRDS), the Equipment Performance and Information Exchange (EPIX), IEEE Standard 500 and the Safety System Performance Indicator (SSPI). He participated in the development of the ASME standard for PRA (ASME-RA-S-2002), the IEEE Standard for use of reliability in nuclear power plants (IEEE Std. 352) and several other industry standards related to reliability and risk analysis.
Also Mr. Logan has managed and participated in the development of PSA models for pressurized water reactors. He has participated in the industry certification of PSA models for both pressurized and boiling water reactors. He developed and maintained summaries of the PSA results for each operating U. S. nuclear station for use by teams evaluating plant operations. He has analyzed operator errors and dependencies in support of PSA model development.
Mr. Logan has also authored or coauthored several technical reports and papers on various topics that have been presented at professional society and international conferences. A list of publications is available upon request.
Neil H. Johnson
Mr. Johnson has over twenty years of engineering experience in commercial nuclear power plant probabilistic safety analysis (PSA), commercial/industrial facilities energy engineering, project management and system design. He has extensive experience in PSA software applications, computer-based modeling, programming, systems analysis and data analysis.
Mr. Johnson has been responsible for upgrading all aspects of PSA models and documentation to meet Regulatory Guide 1.200 requirements. He has performed fire risk evaluations for power and shutdown, and has supported clientele in implementing NFPA-805 pilot projects.
He has received training in other fields specific to his experience, including contracts administration, management development and various energy optimization topics.
Mr. Johnson has authored or coauthored several technical reports and papers on varied topics that have been formally published. A list is available upon request.