Our Team

Ricky L. Summitt

• MAAP/Severe Accidents
  - primary responsibility
• Seismic Events
  - primary responsibility
• Accident Sequence Modeling
  - primary responsibility

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.

Education

• B.S., Nuclear Engineering, University of Tennessee, 1980
• M.S., Nuclear Engineering, University of Tennessee, 1994

• Data
  - primary responsibility
• System Modeling
  - primary responsibility

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.

Education

• B.S., Nuclear Engineering, Texas A&M University, 1990
• M.S., Environmental Engineering, University of Tennessee, 1997

Jeffrey D. Miller, PE

• External Events (non-seismic)
  - primary responsibility
• Initiating Events
  -primary responsibility
• Accident Sequence Modeling
  - secondary responsibility

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.

License:
Registered Professional Engineer, State of Tennessee

Education

• B.S., Mechanical Engineering, University of Tennessee, 2001

Bruce W. Logan

• Human Factors
  - primary responsibility

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.

Education

• B.S., Electrical Engineering, Auburn University, 1971
• M.S., Electrical Engineering, Auburn University, 1973

Neil H. Johnson

• Quantification
  - primary responsibility

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.

Licenses:
Registered Professional Engineer, State of North Carolina
Professional Contractor, State of North Carolina

Education

• B.S., Mechanical Engineering, North Carolina State University, 1985
• M.S., Mechanical Engineering, North Carolina State University, 1992