ML20044H494
| ML20044H494 | |
| Person / Time | |
|---|---|
| Issue date: | 05/24/1993 |
| From: | Selin I NRC COMMISSION (OCM) |
| To: | Press F NATIONAL ACADEMY OF SCIENCES |
| References | |
| NUDOCS 9306090095 | |
| Download: ML20044H494 (13) | |
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Nay 24, 1993 CHAIRMAN Dr. Frank Press, President National Academy of Sciences 2101 Constitution Avenue, N.W.
Washington, D.C.
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Dear Dr. Press:
I understand from correspondence between your executive officer and Mr. Paul Bird, the Nuclear Regulatory Commission's Director of Personnel, that you have been expanding the utilization of government engineers and scientists on National Research Council study committees.
As you already know, I believe that the technical staffs of Federal agencies are an excellent source of talent for Council programs and that broad participation in such collaborative efforts ultimately benefits the Council, individual Federal scientists or engineers, and their home agencies.
In particular, I am confident that members of the NRC's technical staff could make substantial contributions to the Council's study committees.
Accordingly, I have enclosed the resumes of six highly qualified NRC professionals with significant background in some of the topics with which these committees are concerned.
I hope you will consider them for appropriate committee assignments.
Should you or your staff need further information, please contact me or Paul Bird at (301) 492-4661.
Sincerely, Ivan Selin
Enclosures:
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NATIONAL RESEARCH COUNCIL COMMITTEE NOMINEES Comittee on Women in Science & Engineering Patricia L. Eng, NRR - (301) - 594-1361 Comittee on Human Factors Jay Persensky, RES - (301) - 492-3551 Comittee on Scientists & Engineers in the Federal Government Cynthia Jones, NMSS - (301) - 504-2629 Comittee on Transportation of Hazardous Materials Cass R. Chappell, NMSS - (301) - 504-2457 Comittee on Risk Assessment Methodology Mark Cunningham, RES - (301) - 492-3965 Comittee on Nuclear Engineering Education Denwood Ross, AE0D - (301) - 492-7361
PATRICIA L. ENG, P.E.
Patricia L. Eng, P.E. is currently serving as a Senior Operations Engineer in the Human Factors Assessment Branch for the Nuclear Regulatory Commission. As such, she is responsible for evaluating the human performance aspects associated with the operation of commercial nuclear power plants.
She is also responsible for the review of control room designs for advanced reactors as it relates to human / system interface.
t Prior to joining the Human Factors Branch, Ms. Eng served as Technical Assistant to Commissioner E. Gail de Planque for the U.S. Nuclear Regulatory Commission. As such, Ms. Eng was responsible for advising the Commissioner on matters regarding the formulation of Commission policies and programs, and evaluating proposed agency activities, including complex technical issues.
Ms. Eng previously served as the NRC Project Manager for a commercial nuclear power plant. As such, she was responsible for the review and evaluation of licensing and operational activities associated with her assigned plant.
Prior to moving to the Washington D.C. area, she served as the NRC Resident Inspector at the Zion Nuclear Power Plant where she was responsible for reviewing and inspecting testing, maintenance, operations, and quality control activities to ensure that the plant was being operated safely and in compliance with Federal regulations. While at Zion, Ms. Eng received the NRC Meritorious Service Award for outstanding resident inspector effort - the first woman so honored.
She also received the Society of Women Engineers' Distinguished New Engineer of the Year Award.
Ms. Eng joined the NRC in 1983 as the first female reactor inspector in the NRC Region III office's Division of Reactor Safety, located in Glen Ellyn, Illinois.
As a reactor inspector, she performed inspections of components in power plant safety systems and authored the inspection procedure currently in use by NRC inspectors.
In 1986, she received the NRC's Special Achievement Award for outstanding inspection efforts.
Prior to joining the NRC, Ms. Eng worked at Garrett AiResearch where she conducted structural stress analyses on a nuclear gas centrifuge.
Before that, she worked at Westinghouse Hanford where she initially conducted radiation protection research and development activities and later coordinated construction activities at a prototype materials research facility.
Ms. Eng has published technical reports on the subjects of structural safety analysis, radiation exposure rates, containment evaluations and pump testing.
She has also authored and contributed to a number of articles related to the differences between men and women engineers.
She is a registered professional mechanical engineer with a bachelor of science degree in nuclear engineering from the University of Illinois. Ms. Eng is active in the Society of Women Engineers where she serves both as Director of the Mid Atlantic Region and a member of the Society's Board of Directors. She also serves as Commissioner-At-Large for the Engineering Manpower Commission, and has published a comparative survey on men and women engineers. This survey was the first of its kind and largely confirmed widely held beliefs on the differences in demographics and attitudes between men and women engineers.
Julius J. Persensky, Ph.D.
Education Ph.D.
University of Cincinnati, 1971 Applied Experimental Psychology M.A.
University of Cincinnati, 1968 Experimental Psychology B.A.
University of Cincinnati,1966 Psychology Experience Current Position Section Leader, Human Factors Section July 1988-Present Human factors Branch Division of Systems Research Office of Nuclear Regulatory Research Responsibilities Research and Technical Support in the erehs of human performance measurement, training, qualifications, procedures, man-machine interf ace, staffing, working hours.
Nov.1952-July 1988 Section Leader Office of Nuclear Reactor Regulation Responsib111 ties Licensing, inspection, and regulatory development in the areas of training, qualifi-cations, procedures, staffing, working hours, organization and management, operator culture and morale.
Mar. 1981-Nov. 1982 Engineering Psychologist Office of Nuclear Reactor Regulation Responsibilities Licensing and regulatory development in the areas of organization and management, qualifica-tions, training, staffing, working hours Sept. 1971-Mar. 1981 Research Psychologist U.S. National Bureau of Standards Responsibilities Performed human factors research for the Department of Comerce, U.S. Postal Service, U.S. Consumer Product Safety Comission, and other government agencies on areas ranging from safety of children's toys, lawn mowers, and kitchen ranges, to usability of' postal service equipment and information processing.
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Professional 85 Articles, Presentations, Technical Reports Member-Human Factors Society, Sigma X1, Psi Chi Society for Applied Learning Technology Civic Activities Elected Councilman, City of Gaithersburg, 1980 to Present.
Board of Directors, Metropolitan Washington Council of Governments, 1986 to Present.
Boaro of Directors, Family Service of Montgomery County,1985 to Present.
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Cynthia G. Jones Curriculum Vitae Ms. Jones graduated with a B.S. degree in Physics (Mathematics minor) from Augsburg College, Minneapolis, Minnesota in 1981, having completed the degree in three years. Already introduced to and interestad in the field of health physics, she accepted a position with Oak Ridge Associated Universities (0RAU) as a health physics laboratory instructor and remained there until 1984. At that time, she moved to a position as both a resident reactor and medical health physicist in the Radiation Safety Department at the University of California at Los Angeles.
Recognizing the value of higher education, in 1986, she earned her H.S. degree i-health physics, on a full scholarship at the Georgia Institute of Technology.
After graduation, she entered government service as a physicist in the Center f*
Radiation Research at the National Bureau of Standards (currently called the National Institute of Standards and Technology) where she developed a calibration system for use in x-ray and gamma beam intercomparisons.
In 1988, she moved to the Division of Industrial and Medical Nuclear Safety at the Nuclear Regulatory Commission. While currently employed as a Section Leader in the Programmatic Safety Section in the Operations Branch, her primary responsibilities are for the coordination of Division's health physics activities regarding issues concerning environmental engineering, sewer reconcentration of radionuclides, neutron-irradiated gemstone licensing, materials inspection oversight in all five regional offices, implementation of the revised 10 CFR Part 20, and coordination of the recommendations in the international community.
Since 1984, she has written or co-authored numerous publications and documents. They include a wide range of topics such as gamma spectroscopy, the use of cobalt-60 to free fouled pipe lines, environmental assessments of various industrial applications of radiation (including the new californium-252 based explosive detection to be used at airports), and review of the future implications of the recommendations from the International Commission on Radiological Protection (ICRP) Report 60. As part of her current activities with the International Atomic Energy Agency (IAEA) in Vienna, Austria, she has chaired two Advisory Group meetings on the development of radiation protection technical guides for developing Member States and has authored an IAEA Safety Series Training Manual' entitled, "The Safe Use and Regulation of Radiation Sources,"
i which was publi.shed (in draft) by the IAEA in Fall 1992 (final publication Fall 1993).
In 1990, Ms. Jones was accepted as a PhD candidate in the School of Nuclear Engineering at the University of Maryland, College Park. She continues to pursue her degree in this field on a part-time basis while working at the NRC.
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CASS ROSS CHAPPELL, Jr.
Address:
U.S. Nuclear Regulatory Commission Transportation Branch Mail Stop 4E4 Washington, DC 20555 Phone:
(301) 504-2457 Present Section Chief, Cast Certification Section Position:
Transportation Branch, USNRC GS-15, Step 9 Education:
Bachelor of Civil Engineering-----------Georgia Tech 1966 Master of Science in Civil Engineering--Georgia Tech 1970 Registered Professional Engineer (Virginia)
WORK EXPERIENCE 1966-1967 Georgia State Department of Transportation Engineer at bridge :onstruction site. Surveyed and set construction points. Verified that construction was in accordance with plans and met State standards.
Verified quality and quantity of materials.
1967-1969 United States Navy, Commissioned Officer Served aboard USS UHLMANN (DD-687) in the U.S. Pacific Fleet. One overseas cruise (Viet Nam).
OC Division Officer, supervised 25-30 enlisted men.
Responsible for administration and operation of ship's communications, including associated equipment.
Plan work ac'tivities for Division, make out watch schedule, conduct training of assigned men, schedule maintenance and repair of equipment.
Administrative record keeping. Appraise performance of assigned men and recommend for promotion.
Registered Publications Custodian.
Regular underway and in-port watch officer (bridge and CIC).
Miscellaneous collateral duties.
1969-1970 Graduate School at Georgia Tech. Master of Science in Civil Engineering (Structural Engineering).
CASS ROSS CHAPPELL, Jr. 1970-1972 Bechtel Power Corporation (Gaithersburg, Md)
Structural design engineer.
Structural design of nuclear power plant structures and components. Design and analysis of reinforced concrete and structural steel buildings, tanks, frames, shear walls, foundations, columns, beams, etc.
Elastic, plastic, static and dynamic analyses.
Design for seismic, tornado, and other natural phenomena.
Write specifications.
Review and approve vendor drawings for compliance with specifications and criteria. Supervise preparation of drawings before issuance for constructions. Resolve field change requirements.
Extensive use of computer programs for analysis and design.
1972-1987 Structural Engineer (AEC and NRC Transportation Branch)
Technical review of license applications for radioactive material shipping containers.
Stress analysis of vessels under impact, thermal, v bration and pressure loads.
Project manager for staff 4
safety evaluation report and licensing documents.
Participate on ANSI committees.
Develop Regulatory Guides.
Identify research needs.
Prepare and evaluate RFP's.
Serve as project manager for technical assistance contracts, both private companies and national laboratories. Prepare principal correspondence, Commission papers, and rule changes to 10 CFR 71.
Presentations to ACRS and National Academy of Sciences.
Brief Commission.
Atteno IAEA meetings.
Prepared NUREG-0360, " Criteria to certify a Package for Air Transport of Plutonium."
1987-Section Chief, Cask Certification Section (NRC Transportation Presert Branch)
Supervise group of 10 wineers and scientists, a licensing assistant, and a secretary.
Section is responsi~ ole for technical review of applications for approval of radioactive material shipping containers. The Section annually completes about 110 applications (new designs, amendments, and renewals). The Section currently has two technical assistance ccatracts (LLNL and ORNL).
The Section participates on the ASME Committee which is developing a code fer snipping containers.
The Section coordinates with NRC Office of Research on standards, rules, and technical research. The Section has extensive contract with all sectors of the commercial nuclear industry.
The Section also reviews package designs submitted by DOE, and by DOT for revalidation of foreign Competent Authority j
Cer6ificates.
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Mark A. Cunningham Education Massachusetts Institute of Technology, Master of Science Deg ?e in Nuclear Engineering, 1975 (Thesis Topic:
Reliability Analysis of the Power Conversion System of a High-Temperature, Gas-Cooled Reactor).
University of Florida, Bachelor of Sciences Degree in Nuclear Engineering Sciences (Magna Cum Laude), 1974.
Professional Experience Since graduation, employment with the U.S. Nuclear Regulatory Commission, with increasing responsibilities in the areas of probabilistic risk assessment and severe reactor accident analysis, and leading to present position as:
P Chief, Probabilistic Risk Analysis Branch, Divi; ion of Safety Issue Resolution, Office of Nuclear Regulatory Research.
Position involves management of roughly twelve, t ofessional staff experienced in analysis of the frequencies and consequences of severe accidents in commercial nuclear power plants.
Branch is responsible for performing, reviewing, and developing methods for risk assessments, with an annual contracting bud;nct of roughly seven million dollars.
Honors and Awards NRC Meritorious Service Award (agency's second highest award) - 1987; Special Achievement Award - 1979; High Quality increases - 1978, 1984, 1987, 1988.
Publications While at NRC, have authored, cr-ruthored, or contributed to roughly twenty technical publications, incluf %
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Risk Assessment: A survey of Cnar d.tristics, Applications, and Methods Used by Federal Agencies for Engineered Systems, prepared for Federal Coordinating Committee on Science, Engineering, and Technology, Ad-Hoc Working Group on Risk Assessment, 1992.
NUREG-1150, " Severe Accident Risks: An Assessment for Five U.S. Nuclear Power Plants," 1991, and NUREG/CR-1250, "Three Mile Island: A Report to the Commissioners anc the Public," 1980.
RESUME Denwood F. Ross, Jr.
Deputy Director Office for Analysis and Evaluation of Operational Data U.S. Nuclear Regulatory Commission Washington, DC 20555 Tele:
(301) 492-7361 (Work)
(301) 869-1483 (Home)
General The Nuclear Regulatory Commission (NRC) is an independent agency charged with regulating nuclear reactors and the associated fuel cycle to assure the health and safety of the public, using the best available science and engineering technology.
PROFESSIONAL EXPERIENCE
SUMMARY
March 1990 to Present - Deputy Director, Office for Analysis and Evr;uation of Operational Data (AEOD).
As an aftermath of the reactor accident at Three Mile Island in 1979, the USNRC established an independent office to review the operating experiences of nuclear reactors.
The purpose, among other things, was to assure that precursors of more severe event:; were detected, and corrective actions initiated, so that we could prevent recurrences of such severe events.
In march 1990 I transferred to that office.
severe as the Deputy Director.
In addition to these independent assessment duties, the office also provides all of the technical training for the NRC staff (about 3200 people). We also staff and maintain the NRC incident response center.
This is a central communications and technical work function, staffed around the clock, to monitor nuclear facilities around the country.
The Deputy Director of the office is responsible for the orderly technical direction on a day to day basis for these items.
Also, thce is a significant involvement ' ith international aspects of nuclear safety.
I represent the NRC w
on various international safety groups and con.mittees.
April 1981 to March 1990 - Deputy Director, Office of Nuclear Regulatory Research (RES).
The Deputy Director for RES duties call for providing managerial and technical direction, planning guidance and implementation of multi-million dollar 4
research programs required by the NRC in carrying out its licensing and regulatory functions.
Specifically the Deputy Director is responsible for the overall short and long range research program plan development in the area of reactor operations and risk analysis, analytical and experimental thermal-hydraulic transients, severe accidents and source term research and waste
mar.agement. This is done through daily contacts with the Executive Director for Operations (E00), Commissioners, advisory groups and Congressional personnel having oversight responsibility for this Office.
In the case of foraign research cooperative activities, the Deputy Director is responsible for negotiating many of the agreements currently in force and represent the USNRC in international negotiations and meetings dealing with the safety of nuclear reactors worldwide.
See attached list of cooperative activities.
Listed belcd are some specific examples of direct involvement by the Deputy Director:
o Chairman of the ED0's Severe Accident Senior Review Group.
This group provides broad guidance with respect to industry interaction (IDCOR),
technology development (NUREG-0956); nec id safety research (NUREG-0900); and risk analysis (NUREG-Il50).
o Senior USNRC representative for thermal hydraulic research cooperation with the Federal Republic of Germany and Japan on emergency core cooling during the refill and reflood phase of a loss-of-coolant accident in PWR.
o Co-author of special report on HLW licensing (June 1984) to Office Director, Nuclear Materials Safety and Safeguards.
o Member of OECD/NEA Committee on the Safety of Nuclear Installations (CSNI) Senior Group of Experts on Severe Accidents and contributor te reports on the subject.
o Member, CSNI, ad hoc Committee on Future Research, and co-author of final report.
o Invited lecturer MIT Reactor Safety Course for last several years.
o Member, Halden Board (Halden is a OECD-sponsored international nuclear safety project in Halden, Norway), vice-chairman of board (1988), and chairman (1989).
o Lead manager for revision of the ECCS criteria (10 CFR 50.46, Appendix K) and the technical basis report NUREG-1230.
o Held various management positions of multi-million dollar technical assistance program used to tailor short-term responses to immediate nuclear safety concerns (frequently building on a research foundation).
o As noted in a letter dated February 25, 1985, set the tone for the independent review of the RES nuclear safety research program by the National Research Council.
o Wrote major sections of the CSNI report priorities in LWR safety research, and formulated criteria to identify the need for regulatory 2
research including:
development of licensing criteria, or audit of submissions provided by applicants, or substantiation of the technical basis of decisions.
o Formulated the Research Program Management Information System, which was delivered to Congress in 1986 in order to provide greater accountability for RES work.
o Chartered the Steam Explosion Review Group, NUREG-1216, which in its report of 1985, provided some stability in an unsettled nuclear safety area.
April 1980 to April 1981 - Director, Division of Systems Integration, NRR.
This division had broad safety responsibility for both operating reactors and reactors under construction.
This Ovision consisted of about 190 people and was divided into 3 areas with a total of 10 operating branches.
During this period the licensing of the hydrogen ignition concept at the Sequoyah Nuclear Power Station wa. done and considerable time was spent by the Director as a witness for the TMI-l restart hearing and as.a witness at the McGuire Appeals Board Hearing on severe accidents.
I also served as chairman of the special Loss of Fluid Test (LOFT) review group which advised the Commission on how to proceed on LOFT testing.
January 1980 to Aoril 1980 - Acting Director, Division of Project Management, NRR was responsible for management and review of Construction Permit (CP) and Operating License (0L) power reactor projects.
This division was also responsible for Operating Licensing, Quality Assurance (QA), Standardization, and Advanced Reactors Licensing. During this interval the first Operating License (for Nor Anna) since TMI-2 was issued.
April 1979 to December 1979 - Director, Bulletins and Orders Task Force (B&O),
NRR. One of the special groups formed in the NRC in response to TMI-2 accident was the B&O group; the special assignment for this Task Force was to review, for all operating reactors, the adequacy of shutdown cooling (especially auxiliary feedwater system) in light of TMI 2, and the systems and analysis for'off-normal cooling (e.g., feed & bleed).
We met with owner's groups; developed requirements for safety improvements; wrote safety evaluations (including restart SERs for B&W reactors); and prepared hearing testimony for the Rancho Seco hearing.
The B&O group consisted of about 40 people.
May 1978 to April 1979 - Deputy Director, Division of Project Management (DPM), Office of Nuclear Reactor Regulation (NRR). The DPM was the licensing division of the USNRC which included the Quality Assurance Branch, Operator Licensing Branch and Advanced Reactor Branch and several other project management branches.
The work involved review and project management of the operating license applications.
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December 1975 to May 1978 - Assistant Director for Reactor Safety, Division of Systems Safety, NRR. This division consisted of three branches:
Core Performance Branch; and Reactor Systems Branch. The work involved technical review of operating license applications since the short-term operating reactor problems were assigned to the newly-created Division of Operating Reactors.
April 1973 to December 1975 - Branch Chief, Core Performance Branch, Directorate of Licensing, USNRC. This branch was organized to provide more detailed technical review of the licensed commercial power reactors including review of safety aspects of fuels, physics, and thermal-hydraulics of reactor cores. The Core performance Branch grew to be one of the largest in the NRC (39 people).
August 1967 to January 1971 - Project Manager (PM) and Senior Manager in Division of Reactor Licensing, AEC.
The PM had broad responsibilities especially in the systems area.
I was PM for Crystal River 3, Construction Permit (CP);- Quad Cities, Operating License (OL); THI-2 OL (part of the time).
I testified at CP hearings for TMl-1 and Crystal River. At the end of this period the Emergency Core Cooling System (ECCS) became a big concern to the AEC and the nuclear industry, I was assigned to the ECCS task force to address the issues. During a two year period, the group accomplished the following tasks:
o Developed interim acceptance criteria and its supporting technical ba>is; o
P ared and presented NRC testimony during the year-long hearings; and o
Developed Appendix K to its technical bases.
It was the AEC staff witness on ECCS at the 1971 Palisades hearing and testified at the Indian Point (IP-2) hearing.
In 1972, I was granted an aducational leave of absence for about 9 months to return to Catholic University of America to complete the doctoral work which included the study of the mechanisms by which liquid water could penetrate downwards against the upward flow of steam in a reactor LOCA condition.
January 1964 to August 1967 - Operations superintendent for Nuclear Aerospace Research Facility (NARF) (Ft. Worth, Texas).
Prepared and developed training lectures for operator licensing. The reactor operations group responsibilities assignment and responsibilities included:
a) research assignments to design, install and analy7c ~n-core thermometry to measure the heat transfer of the reactor dur~n if-normal conditions (low flow or high power).
One of these projects :.s converted into a MS
- thesis, b)
In 1962-1964, for an upgrade of power license requirement, the first loss-of-fluid test was done at NARF (14 years before LOFT).
The reactor was instrumented, taken to power, coolant expelled, core heatup observed 4
and emergency core coolant system (ECCS) turned on. Although NARF was a Department of Defense Facility, we ronetheless obtained " comments and concurrence" from the AEC.
c)
In 1964, as part of the power upgrade of the pool type reactor, I led the reactor safety technical presentation before the AEC regulatory bodies. Our safety features design, innovative at that time, included:
o Concrete confinement building, exhaust system through an iodine filter system, backup emergency power systems, emergency pool deluge, diverse core spray and poison injection system independent of AC or DC power.
o All of the above engineered safety features had to be tested for performance by the reactor operations group. NARF operators were licensed by the U.S. Air Force in about the same way as civilian operators were licensed by AEC at that time.
d)
Other research done by the reactor operations group included criticality measurements of shipping tasks; response of reactor power-coolant mismatch; fission product development; and Xenon buildup and decay analysis.
July 1962 to January 1964 - Day Supervisor and coordinator for +ank reactor at the NARF.
July 1959 to July 1962 - Shift supervisor at NARF; received reactor operator license from USAF (first issued).
Februar_y 1957 to July 1959 - Reactor operator at NARF it.stallation consisting of three reactors:
a critical assembly; a pool-type reactor (up to 10 Mw);
and a tank-type (low-pressure vessel) reactor, also up to 10 Mw.
November 1955 to February 1957 - Reactor Operator in the Material Test Reactor at the National Reactor Testing Station, Idaho and startup test engineer for Engineering Test Reactor.
EDUCATIONAL BACKGROUND I have four academic degrees including a Doctor of Nuclear Engineering degree from the Catholic University of America. See list below:
B.S. Civil Engineering, 1953 33 hours3.819444e-4 days <br />0.00917 hours <br />5.456349e-5 weeks <br />1.25565e-5 months <br /> 0 Southern Methodist University, Dallas, Texas 115 hours0.00133 days <br />0.0319 hours <br />1.901455e-4 weeks <br />4.37575e-5 months <br /> 0 Texas Western College, El Paso, Texas 148 hours0.00171 days <br />0.0411 hours <br />2.44709e-4 weeks <br />5.6314e-5 months <br /> 5
M.S. Nuclear Engineering, 1960 9 hours1.041667e-4 days <br />0.0025 hours <br />1.488095e-5 weeks <br />3.4245e-6 months <br /> 0 University of Idaho (Idaho Falls Branch) 11 hours1.273148e-4 days <br />0.00306 hours <br />1.818783e-5 weeks <br />4.1855e-6 months <br /> 0 S.M.U., Dallas, Texas 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> M.S. Mathematics, 1963 30 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br /> 0 Texas Christian University, Ft. Worth, Texas Doctor of Engineering, 1974 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> plus research at Catholic University of America, Washington, DC Doctoral dissertation on experimental' investigation of counter-current flow of water Teachina I have taught undergraduate and graduate courses in mathematics at the University of Texas, Arlington; Texas Christian University; Rockville Community College; and the University of Maryland for the past 30 years.
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TABLE 1 PROFESSIONAL EXPERIENCE 1967-Present:
Nuclear Regulatory Commission 1990-Present:
Deputy Director, Office for Analysis and Evaluation of Operational Data 1981-90:
Deputy Director for Research, Office of Nuclear Regulatory Research 1980-81:
Director, Division of Systems Integration, Office of Nuclear Reactor Regulation 1979:
Director TMI-2 Task Force reviewing new safety requirements for all reactors 1978-79:
Deputy Director, Division of Project Management and Acting Director 1976-78:
Assistant Director for Reactor Safety (reactor systems, analysis, and instrumentation) 1973-75:
Chief, Core Performance Branch (reactor fuel, physics, thermal-hydraulics) 1971-73 Review of reactor emergency core cooling systems criteria, and year-long assignment to hearings as witness and technical interrogator 1967-71:
Project Manager for Construction Permit and Operating Licensing Reviews 1957-67:
Nuclear Aerospace Research Facility (Ft. Worth, Texas); Reactor Operator, Shift Supervisor Reactor Coordinator, Reactor Operations Supervisor (Three test reactors, design and operations) 1956-57:
.Startup Engineer, Engineering Test Reactor (Idaho) 1955-56:
Reactor Operator, Materials Testing Reactor (Idaho) 7
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TABLE 2 TEACHING EXPERIENCE 1960-63:
University of Texas - Arlington General Undergraduate Mathematics 1963-65:
Texas Christian University' Graduate Mathematics Probability and Statistics 1968-88:
Rockville Community College All undergraduate Mathematics, focussing on calculus and differential equations 1990:
University of Maryland Graduate course in advanced calculus for nuclear engineering t
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