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Indian Point Emergency Preparedness

Independent Expert Task Force

nuclear stations and leadership of numerous technical assessments on various issues related to nuclear safety, spent fuel management, nuclear facility deactivation, and the like, in the public and private sectors.

Prior to forming Polestar in 1992, Mr. DeVine was with the General Public Utilities (GPU) system for 23 years. From 1970 through 1979, he held engineering and management positions involving design and construction of new nuclear plants and major plant modifications. Mr. DeVine had a major role in the response and recovery from the March 1979 nuclear accident at the GPU Three Mile Island Unit 2, serving as part of the Emergency Response Team immediately following the accident, and in the following years as Recovery Engineering Manager and Technical Planning Director. Subsequently, on special assignment to the Electric Power Research Institute (EPRI) in Palo Alto, California (1986 - 1989), Mr. DeVine had responsibility for overall direction of the U.S. Advanced Light Water Reactor (ALWR) Program, coordinating U.S. and international utility industry efforts in developing advanced reactor design concepts for the next generation.

From 1989 through 1992, he served as the GPU Nuclear Corporation Vice President & Director - Technical Functions, with overall responsibility for all engineering work in support of the company's operating nuclear plants, and as a member of the GPU Nuclear Board of Directors. His work at GPU also included executive-level participation in utility industry activities, including the Project Management Board of the Advanced Reactor Corporation, the EPRI Nuclear Power Division Advisory Committee, the Executive Board of the Edison Electric Institute (EEI) Utility Waste Management Group, and others.

Mr. DeVine is a graduate of the U.S. Naval Academy with a B.S. in Engineering and Mathematics. He served as a commissioned officer aboard the fast attack nuclear submarine USS Sunfish (SSN 649).

Mr. DeVine is the principal author of the Indian Point Emergency Preparedness IETF report.

Mario H. Fontana, Ph.D., P.E., has over 40 years of experience in the areas of nuclear reactor safety research and technology at the Oak Ridge National Laboratory (ORNL) and in industry. After retiring from ORNL, he became a member of the U. S. Nuclear Regulatory Commission Advisory Committee on Reactor Safety where he chaired the Severe Accident Subcommittee and the License Renewal Subcommittee and was a member of the Probabilistic Risk Assessment Subcommittee and the Thermal Hydraulic Subcommittee.

At ORNL, Dr. Fontana was assistant director of Nuclear Safety Research Programs, manager of Liquid Metal Breeder Reactor Safety and Core Systems Programs, head of the Advanced Concepts Development Section of the Engineering Technology Division, and assistant director of the Engineering Technology Division. He initiated and conducted research on fission product release and transfer in reactor accidents, reactor heat transfer and fluid flow, severe accident behavior, and accelerator transmutation of

Indian Point Emergency Preparedness

Independent Expert Task Force

waste. He started the DOE research on LMFBR sodium heat transfer in fuel assemblies; the NRC Severe Accident Sequence Assessment Program; and the NRC LMFBR Aerosol Release and Transport Program.

In addition, Dr. Fontana was the Technical Director of the Industry Degraded Core
(IDCOR) program to assess in depth the initiation and progression of potential severe
accidents in commercial light water reactors. IDCOR was sponsored by 54 organizations
in the U. S. and international nuclear industry and directed over 20 subcontractors,
including the Electric Power Research Institute, major architect-engineer firms, and
major nuclear system manufacturers. Subsequently he was the technical director of the
DOE Severe Accident Assessment Program to address severe accident issues for
advanced light water reactors under development at the time. He participated in the
development of WASH 1400 - The Reactor Safety Study (known as the Rasmussen
Report), which was the first extensive probabilistic risk assessment of commercial
nuclear reactors. He is a research professor at the University of Tennessee. He has
authored over 120 reports and publications, including a chapter on fission product release
and transport for Atomic Energy Commission "Handbook of U.S. Containment
Technology." He is a registered professional engineer (retired), fellow of the American
Nuclear Society, a member of the American Society of Mechanical Engineers and of the
engineering honor society Tau Beta Pi.

He received a B.S. from the University of Massachusetts, an M.S., from the
Massachusetts Institute of Technology and a Ph.D. from Purdue University, all in
Mechanical Engineering.

David E. W. Leaver, Ph.D., is co-founder and principal of Polestar Applied Technology, Inc. He has been involved in safety analysis and engineering support to the nuclear industry for more than 25 years. At Polestar, Dr. Leaver has been engaged in a variety of source term-related work, developing new methods for evaluating fission product aerosol transport in containment, which were successfully applied to the Westinghouse AP600 design basis source term. He developed improved methods for predicting aerosol retention in steam generator tube rupture and interfacing loss of coolant accidents, and applied these methods to develop a technical basis for reduced emergency planning zones in Advanced Light Water Reactors (ALWRs). Dr. Leaver was the lead technical support for NEI efforts to develop a framework for applying AST to operating plants, and has performed safety-related calculations for over a dozen AST licensing applications.

As a co-founder of Delian Corp., Dr. Leaver conducted PRA studies, participated in several independent assessments of nuclear plant operational and engineering readiness, and worked on fossil plant reliability and heat rate improvement. He was involved in development of safety, source term, and severe accident design requirements for the ALWR. Under DOE sponsorship, Dr. Leaver established and led a team in developing a more realistic design basis fission product source term to support ALWR plant design certification. This work directly led to a major NRC effort to update the source term regulations for advanced plants, and later for operating plants, resulting in the alternate source term (AST). Leaver performed some of the earliest probabilistic risk assessment

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Indian Point Emergency Preparedness

Independent Expert Task Force

(PRA) studies of nuclear plants including the Clinch River Breeder Reactor Plant and the Big Rock Point.

Dr. Leaver received a B.S. in Electrical Engineering from the University of Washington and an M.S. in Engineering Economic Systems and a Ph.D. in Mechanical Engineering from Stanford University. He served as an officer in the U.S. Navy, stationed at the Division of Naval Reactors.

Roger P. Shaw, B.Sc., CHP is the principal of RP Shaw Consulting, providing senior level management and technical support on the national and international level. He is an experienced senior level manager, health physicist and radiological engineer with over 25 years of management experience with nuclear issues, radiation protection and emergency preparedness in the commercial, nuclear power and government sectors. He has performed work in the legal arena with respect to radiation science and radiation health effects. Shaw has provided technical support on decommissioning of nuclear facilities for the National Academy of Sciences. He served as the project manager for the first independent epidemiological study of U.S. nuclear facility workers in collaboration with the International Agency for Research on Cancer, an agency of the World Health Organization.

Mr. Shaw was formerly research scientist with Pacific Northwest National Laboratory. He was the radiological controls/occupational safety director at TMI and Oyster Creek. He was the director at TMI during final de-fueling of the TMI-2 reactor. He has served as a senior member on nuclear emergency response teams for 20 years. He has been an invited lecturer at universities, and national and international seminars.

Mr. Shaw holds a B.S. in nuclear engineering technology from Oregon State University, and has performed graduate studies in health physics and radiobiology at Oregon State and Penn State University and is a graduate of the Penn State Executive Institute. He holds a comprehensive certification with the American Board of Health Physics and is qualified as a technical manager per ANSI 18.1, as a radiation protection manager per ANSI 3.1 and USNRC Regulatory Guide 1.8, and as a radiation safety officer per 10 CFR 33. Shaw is a member of the Health Physics Society, American Academy of Health Physics, American Nuclear Society, American Association of Physicists in Medicine, and Society of Nuclear Medicine.

Mr. Shaw is the Indian Point Emergency Preparedness IETF Project Manager.

John H. Sorensen, Ph.D., has been involved with research on emergency planning and disaster response for over 25 years. He has been the principal investigator on over 40 major projects for federal agencies including FEMA, DOE, EPA, NRC, DOD and CSHIB. Dr. Sorensen has participated in research including the Three Mile Island Public Health Fund Emergency Planning Project on Three Mile Island and the Second Assessment of Research on Natural Hazards where he served as the subgroup leader for Prediction, Forecast Warning and Emergency Planning. He is a distinguished research staff member at Oak Ridge National Laboratory (ORNL).

Indian Point Emergency Preparedness
Independent Expert Task Force

Dr. Sorensen authored over 140 professional publications including Impacts of Hazardous Technology: The Psycho-Social Effects of Restarting TMI-1. He has published extensively on response to emergency warnings, risk communications, organizational effectiveness in disasters, emergency evacuation, and protective actions for chemical emergencies. Sorensen has led the development of emergency management information systems, simulation models, conventional and interactive training courses, and educational videos. He has served on a advisory committees including the Natural Hazard Research and Applications Center at the University of Colorado, the Atomic Industrial Forum's National Environmental Studies Task Force on Emergency Evacuation, the International City Management Association's Emergency Management "Emergency Planning Greenbook" Project and FEMA's Emergency Management Technology Steering Group. He was a member of the National Research Council, Commission on Physical Sciences, Mathematics, and Resources, Earth Sciences Board, Subcommittee on Earthquake Research.

He has a Ph.D. in Geography from the University of Colorado at Boulder and was an assistant professor at the University of Hawaii.

Keith Woodard, M.S., is the director and senior engineer for ABS Consulting's Washington, D.C. office. With 40 years of experience in atmospheric dispersion modeling and analysis, radionuclide and chemical dose assessment/reconstruction, and probabilistic risk assessment, Mr. Woodard has been directly involved in meteorological data collection and analysis, dispersion assessments, dose calculations, and emergency planning at more than half of the U.S. commercial huclear power plant sites, at U.S. National Laboratories, and for DOD.

Mr. Woodard is responsible for development and continuous support of the computerized Meteorological Information and Dose Assessment System (MIDAS) used in support of emergency planning, training, and response at more than 30 U.S. nuclear plants. He directed design and development of the anti-terrorism version of the MIDAS system (MIDAS-AT) delivered to the U.S. Marine Corps, U.S Navy, U.S. Department of State (Diplomatic Security), and state and local governments for impact assessment of potential terrorist threats involving chemical, biological, and radiological agents. Mr. Woodard was responsible for developing the first site-specific model (CRACIT program) to assess reactor accident consequences, which was used in probabilistic risk assessments for more than 12 plants. He directed development of the CRACEZ consequence model, incorporating three-dimensional wind fields, a complex evacuation dose model, and time-dependent releases.

Mr. Woodard participated in the assessment of the radiation exposure immediately after the accident at TMI, and developed computer models to reconstruct the fission produce release source term using environmental measurements and site meteorological date. He was extensively involved in the development of radiological accident consequence codes, working with nuclear utilities and the U.S. National Laboratories. He was project manager for installation of computerized on-line emergency dose assessment models at

Indian Point Emergency Preparedness
Independent Expert Task Force

Los Alamos National Laboratory including both radiological and chemical versions of MIDAS. He was co-chairman of the DOE committee to review chemical dispersion computer models and made recommendations regarding best practices. He participated in the International Comparison Study of Reactor Accident Consequence Models (benchmark study) conducted by the Organization for Economic Cooperation and Development and recently chaired an IAEA workshop on accident consequences.

Mr. Woodard has a M.S. in Nuclear Engineering from the University of California at Los Angeles and a B.A. in Physics from Occidental College. He completed graduate courses in Reactor Design and Safety Analysis at the Catholic University in Washington, D.C. and has a certificate from the International Institute of Nuclear Science and Engineering at Argonne National Laboratories. He has authored or co-authored 29 journal articles and presentations on topics including dose assessment, atmospheric dispersion and probabilistic risk assessment.

Dennis Mileti, Ph.D., is professor and chair of the Department of the Sociology and director of the Natural Hazards Research Applications and Information Center at the University of Colorado at Boulder. He has served on numerous advisory boards, including chair of the Board of Visitors to the Federal Emergency Management Agency's Emergency Management Institute, chair of the Committee on Natural Disasters of the National Research Council, and member of the Advisory Board on Research to the U.S. Geological Society. Mileti is a member of the Advisory Board to the Southern California Earthquake Center, the Mid-America Earthquake Engineering Center, and the MultiDisciplinary Center for Earthquake Engineering Research, the Earthquake Engineering Research Institute, and member of the Multi-Hazard Mitigation Council.

Dr. Mileti is the co-founder and co-editor-in-chief of the journal Natural Hazards Review, an interdisciplinary all-hazards journal devoted to bringing together the natural and social sciences, engineering, and the policy communities. He is the author of over 100 publications, with focus on the societal aspects of mitigation and preparedness for natural hazards and disasters. He received a Ph.D. in sociology from the University of Colorado, an M.A. in sociology from California State University at Los Angeles; and a B.A. in sociology from the University of California at Los Angeles.

Dr. Mileti reviewed and provided technical comments on the IETF Report; he did not otherwise participate in its preparation.

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