United States Nuclear Regulatory Commission - Protecting People and the Environment

Kevin O’Kula

Dr. O’Kula has over 35 years of experience as a manager and technical professional in the areas of nuclear facility source term evaluation, probabilistic and quantitative risk assessment (PRA/QRA) and severe accident analysis, accident and consequence analysis, source term evaluation, hydrogen safety, software quality assurance (SQA), safety analysis standard and guidance development, computer code validation and verification, risk management, and tritium safety applications.  He is currently the Principal Consultant for AECOM Technical Services in PRA/QRA and hydrogen safety applications.  Dr. O’Kula was a member of the Peer Review Committee for NRC’s State-of-the-Art Reactor Consequence Analysis (SOARCA) Program that evaluated source term and offsite consequences of postulated severe accidents in commercial nuclear power plants.

Kevin was part of the Department of Energy (DOE) team writing DOE G 414.1-4, Safety Software Guide.  He was a key technical coordinator support for the Department of Energy (DOE) in addressing Defense Nuclear Facilities Safety Board (DNFSB) Recommendation 2002-1 on Software Quality Assurance (SQA). He was part of a technical writing team developing the Standard for Radiological Accident Offsite Consequence Analysis (Level 3 PRA) to Support Nuclear Installation Applications (ASME/ANS RA-S-1.3-2017).

He has supported multiple commercial plants in Atomic Safety Licensing Board (ASLB) relicensing activities concerning MACCS2 and severe accident mitigation alternatives (SAMA) analysis, including those for Seabrook, Davis-Besse, Indian Point, Prairie Island, and Pilgrim. Dr. O'Kula is the General Chair for the 16th ANS Probabilistic Safety Assessment and Analysis Conference (PSA 2019) in Charleston, South Carolina, April 28 - May, 3 2019.
Page Last Reviewed/Updated Monday, June 04, 2018