RESUME TEMPLATE-9/94

Senior Executive Consultant

Summary

·         Nuclear and Chemical Plant Probabilistic Risk Assessment,

·         Probabilistic Risk Assessment for non-commercial reactors,

·         Human Reliability Analysis,

·         Safety Analysis,

·         Design and Operational Application of Reliability Engineering and Reliability Assurance

·         Economic evaluation and Economic decision making,

·         Application of Risk Based Decision Making in an operational environment,

·         Root Cause Analysis, and Process Safety Incident Investigation,

·         Power Plant Reliability and Availability Improvement and Reliability Centered Maintenance. 

Education

·         Bachelor of Engineering (with honor), Mechanical Engineering Stevens Institute of Technology, 1971

As Adjunct Professor of Reliability Engineering, developed and taught two graduate Reliability Engineering courses at the University of Maryland:  ENNU 648B, Advanced Reliability Engineering, ENNU 648F, Human Reliability Assessment

Licenses and Certifications

Registered Professional Engineer  (Mechanical Engineering) State of Maryland (Cert #: 10986 (1978)

Qualifications and Professional Experience

·         Senior Executive Consultant, SCIENTECH, Inc

Ø             Worldwide consulting in all aspects of risk and reliability engineering

·         Manager of Safety Analysis for NUS

Ø             Technical and managerial oversight for numerous RETRAN and RELAP 5 assessments performed for domestic and foreign utilities

Ø             Oversight of RELAP 5 assessments for ROSA / AP600

·         Manager of PRA at INEL responsible for DOE facility activities.

Ø             Led the development and implementation of PSA into Safety analyses for INEL facilities

·         Reliability Engineering Consultant, Baltimore Gas and Electric Company

Qualifications

Probabilistic Risk Assessment and PSA Applications

·         Shutdown Fire PRA for the Westinghouse AP600 Advanced Reactor

·         Performed independent peer reviews of Level 1 IPEs for St. Lucie (PWR), Yonggwang (PWR), River Bend (BWR-6/Mark III) and Brunswick (BWR-4 Mark II).

·         Rebaselined the Level 1 IPE, completed a streamlined Level 2 PRA, applied the results to prioritize MOVs (response to GL 89-10) and Common Cause Failure Analysis to prevent MOV failures at WNP-2 (BWR-5/Mk II)

·         Project manager for River Bend Level 2 PRA (BWR-6/MARK III).

·         Developed and applied a Master Plant Logic Diagrams for River Bend (BWR-6/Mk III) and Indian Point 2 (PWR) to assist in risk based management of plant configuration.

·         IREP team member for Level 1 PRA and IPEM-CE methodology verification (Calvert Cliffs PWR)

·         Peer review team member for St. Lucie and River Bend IPEs

·         Performed technical review of the Rovno PSA (VVER-440)

Quantitative Risk Assessment (QRA) for Chemical Plants

·         QRA to support the engineering and economic decision making process for a hydrazine handling operation at a mid-west fuels additive manufacturing plant.

·         Developed a Hazard and Risk Management Plan for an offshore oil production facility.

·         Developed and reviewed risk and reliability analyses for more than twenty-eight chemical manufacturing and process facilities in the Republic of China.

Aging Risk Assessment

·         Project Manager and technical director for an aging risk assessment for a Japanese (Westinghouse-type) PWR.

·         Developed an updated component specific aging rate data base

Human Reliability Assessment (HRA)

·         Performed HRA for the Calvert Cliffs IREP, Calvert Cliffs Pressurized Thermal Shock (PTS) study and IPEM

·         Performed HRA studies for the DOE sponsored Nuclear Plant Information System project for Calvert Cliffs

·         Used HRA for several Root Cause Analyses where human error was an important causal factor.

Reliability Assurance (RAP)

·         Currently the Risk and Reliability lead for a Department of Energy Nuclear Waste Vitrification Facility – Applying Risk and Reliability techniques in throughout the design process to ensure that it is optimal in terms of safety, performance and economics.

·         Recently Completed a  RAM analysis to support the optimized design and operation of a hydrogen production plant (11 million scfm/day)

·         Developed the algorithms and architecture for the cost effectiveness module for EPRI’s Power Delivery Systems RCM workstation

·         Authored the Reliability Assurance Program Guidebook for IAEA to assure the Safe, Reliable and Economic operation of the next generation of advanced light water reactors (ALWR’s).

·         Performed a Reliability, Availability and Maintainability (RAM) study for a Korean C-E System 80+, to predict SCRAM, forced and planned outage rates and develop a prioritized list of design improvement items, and list of candidate critical SSCs for RCM.

·         Developed a company-wide Availability Improvement Plan (AIP) for a major U.S Utility

·         Led company and industry (EPRI) development of the “GO” methodology and for RAM analysis

·         Evaluated the impact of PWR and BWR issues within the context of both ISAP and AIP.

Safety Analysis

·         More than seventeen years working for the Baltimore Gas and Electric Company:

Ø             Assisted in the development and approval process for the Calvert Cliffs FSAR and Technical Specifications

Ø             Part of the Calvert Cliffs (CCNPP) commissioning team, where responsibilities included preparation of plant licensing documents, pre-operational testing and hot-functional testing.

Ø             Developed the Maintenance Surveillance Testing Program for Calvert Cliffs and served as Assistant Maintenance Engineer with specific responsibilities in the E, I&C areas.

Ø             Developed and implemented numerous NPP modification and enhancement packages when working in the BG&E Electric Engineering Department

Ø             Spent three years working in BG&E’s QA department,

Ø             Worked in the CCNPP Safety Analysis unit for 2 years

Ø             Led plant efforts to respond to various Environmental Qualification concerns which threatened continued plant operation

Nuclear and Fossil Plant Operations, Maintenance and Engineering

·               Recently (1998) led an Operations Assessment Team  to assess the quality of Operations at the Browns Ferry Nuclear Plant and provide documented recommendations for improvement,

·               Performed thermal efficiency testing, thermal analysis and “BTU chasing” activities in both nuclear and fossil plants,

·               Served as start-up and pre-operational engineer for both fossil and nuclear (PWR) plants

·               Assistant Maintenance Engineer, Surveillance Test Engineer and Performance Engineer in a two unit PWR (Calvert Cliffs), with specific responsibilities associated with oversight of the Instrument and Control Group.

·               Electric Engineering -  mechanical design and modification packages for nuclear and fossil plants, Responsible Engineer for Turbine-Generator and Feedwater  Systems in new 2-unit 1200 MW coal plant

Economic Evaluation

·         As an engineer in a utility  Electric Engineering Department, spent six years performing economic and energy  usage evaluations to justify the optimum selection of vendor offerings for fossil and nuclear generating station equipment,

·         Recently developed the technical basis and algorithms for cost-effectiveness modules installed in the Transmission and Distribution system RCM Workstation, based on estimation of the life-cycle costs for differing maintenance strategies,

·         Currently providing technology transfer in the area of economic decision making to a foreign client

·         Performed economic risk assessments for fires involving PCB contaminated oil

·         Presented seminar on risk based economic loss control techniques to US Army personnel.

Root Cause Analysis

·         Currently provide one, two and three day training seminars in Incident Investigation and Root Cause analysis for the AIChE Center for Chemical Process Safety and for several domestic and foreign refinery and chemical plant clients.

·         Led performance of several root cause analyses which included:

Ø             Chemical reactor explosion, petrochemical complex in Taiwan

Ø             Analysis of a major nuclear plant condensate system failure

Ø             Reactor coolant pump vibration spectrum shifts

Ø             Detailed root causes for feedwater system failures in a 300Mw (Coal fired) station,.

Ø             Technical lead for many in-plant root cause analyses performed as an integral part of a PWR SCRAM reduction and prevention program and in the resolution of nuclear plant LERs

Non-Commercial Reactor and Non-Reactor Risk and Reliability Assessment

·         Led high level independent review committees for Savannah River PRA and independent reviews of PRA's performed for High Flux Isotope Reactor (HFIR) and High Flux Beam Reactor (HFBR)

·         Developed the "Reliability in Design" process to support SDI and applied it during the development of INEL’s conceptual Small Ex-ore Heat Pipe Thermionic Reactor (SEHPTR)  and to a reliability assessment for the Stirling Space Engine developed by NASA Lewis R.C.

·         Managed risk assessments for individual mixed waste processes and processing facilities at INEL.

Employment

·         Associate SARACon, 2000

·         Senior Executive Consultant, SCIENTECH Inc,  1997 to 2000

·         Manager of Safety Analysis NUS 1990 to 1997

·         Manager of PRA, Idaho National Engineering Laboratory / EG&G Idaho, 1988 to 1990

·         Reliability Engineering Consultant, Baltimore Gas & Electric Company, 1971 to 1988

·         Associate Consultant, Technology Research Corporation, 1984 to 1988

·         Adjunct. Faculty, Dept. of Chemical and Nuclear Engineering, University of Maryland, 1987-1988

Specialized Training

·         Suite of Training Courses provided to engineers involved in nuclear plant start-up

·         Attended several Utility Finance and Economics and several utility management and technical courses

·         Requirements Awareness Program Training (INEL),

Technology Transfer

·         In addition to teaching graduate courses in reliability Engineering, well known for the numerous short courses presented to Nuclear and Fossil Generation, Chemical and Aerospace industries. Topics range from basic Risk, Reliability and Maintainability Engineering to the specialized use of these topics in design and operational decision making processes.

Affiliations/Honors

·         Member: Tau Beta Pi

·         American Society of Mechanical Engineers (ASME)

·         American Nuclear Society (ANS) and the Society for Risk Assessment (SRA)

·         Listed in Lexington’s  “Who’s Who of Technical Professionals”, for the year 2000

Patent

·         "Dual Annular Rotating 'Windowed' Nuclear Reactor Control System”, et al.  Notification of approval by the U.S. patent office, October 1993, U.S. Patent #  5,299.242.

Publications

“The Development of a Reliability Assurance Programme (RAP) Guidebook for Advanced Light Water Reactors”, B. O. Cho (IAEA), PSA-99 Conference, August 1999, Washington DC.

“Elements of an Approach to Performance-Based Regulatory Oversight”, NUREG/CR-5392, R.W. Youngblood, et al., January 1999

Aging Risk Assessment Performed for a Two-Loop Westinghouse Plant: Part I - The Methods and Approach”, et al., PSAM 4, NYC, 9/98,

Aging Risk Assessment Performed for a Two-Loop Westinghouse Plant: Part II - Insights and Findings”, et al., PSAM 4, NYC, 9/98,

“The Practical Implications of Using Quantitative Importance Measures to Guide Risk Based Decision Making Processes”, Lichung T. Pong.  PSAM 4, NYC, 9/98

Reliability Assurance Guidelines for Advanced Light Water Reactors”, (Final Draft 1/98), IAEA-TECDOC-XXX (number not yet assigned)

"Understanding the Risk Significance of Technical Specifications", Lichung T. Pong, 1996, Proceedings of the Joint ASME/JSME ICONE-4 International Conference on Nuclear Engineering, New Orleans, March 1996

"Risk Based prioritization of Motor Operated Valves at the Washington Nuclear Plant 2", L.T. Pong, ANS International Topical Meeting, Seattle, September 1995

"Common Cause Failure of Motor Operated Valves at the Washington Nuclear Plant 2", L.T. Pong, ANS International Topical Meeting, Seattle, September 1995

"Application of the Master Plant Logic Diagram (MPLD) for Risk Based Nuclear Plant Configuration Management", Jerry K. Barrett, Ron G. Stewart, Proceedings, ANS Human Factors Topical Meeting, Philadelphia, June, 1995

"Shut-Down Risk Management at the River Bend Station", J.L. Burton, J.J. Lynch, LIS-Trends Conference, Clearwater FL, November 1991.

"The Role of Risk Assessment and Safety Analysis in Integrated Safety Assessments", Thomas E. Wierman ANS International Topical Meeting, The Safety, Status and Future of Non‑commercial Reactors and Irradiation Facilities, Boise, Idaho, October, 1990.

“Reliability Engineering Methodologies and their Role as Design Integration Tools”, Dave Buden. Walt Sullivan and David Satterwhite, Aerospace Conference, Los Angeles 1990.

"Risk Assessment Handbook", (coauthor), EG&G, SSRE-9300, Sept. 1990.

"RAM Methodology Selection", Thomas E. Wierman 17th INTER‑RAM Conference for the Electric Power Industry Hershey, Pennsylvania, June, 1990.

"Savannah River Site Probabilistic Risk Assessment - High Level Review", B. John Garrick, Dennis C. Bley, Robert J. Budnitz, Helmut Filacchione, Karl N. Fleming, Final DOE Report, February 1990.

"A Model‑based Approach to on‑line Process Disturbance Management, The Models". Reliability Engineering and System Safety, 28 (1990) pp. 265 ‑ 305, I.S. Kim, M. Modarres.

"A Model‑based Approach to On‑line Process Disturbance Management, The Application". Reliability Engineering and System Safety, 29, (1990) pp. 185 ‑239,  I.S. Kim, M. Modarres.

"Toward the Practical Use of Expert System Technique for Process Disturbance Management". Reliability Engineering and System Safety, 28, (1990) pp. 307 ‑ 317,  I.S. Kim, M. Modarres.

"IDCOR Task Report: IPE Methodology Verification for Combustion Engineering Plants". Atomic Industrial Forum/IDCOR, 1988 

"A Knowledge Based Approach to Root Cause Failure Analysis", Su Chen, Modarres and Danner, EPRI AI Conference, May, 1989, Orlando, Florida.

"Development of a Root Cause Analysis Workstation and its Application", M. A. Danner, M. Modarres, D. Chung, 15th INTER‑Ram Conference, Portland OR, June 1988.

"Development of a Root Cause Analysis Workstation and its Application in Identifying the Cause of Reactor Scrams", M. A. Danner, M. Modarres, D. Chung ASME/ANS Joint Meeting, Myrtle Beach SC, April 1988.

"Integrated Approach Methodology: A Handbook for Power Plant Assessment", M. L. Roush, M. Modarres, D. Kreps, R. Pierce Sandia National Laboratories, Contractor Report SAND87 ‑ 7138 Oct. 1987.

"Probabilistic Risk Assessment: A Look at the Role of Artificial Intelligence", J. Wang, M. Modarres, Nuclear Engineering and Design.

"GOALTRES: An Expert System for Fault Detection and Analysis", D. Chung, M. Modarres, Reliability Engineering and System Safety.

"The Use of Probabilistic Techniques to Assess Reactor Coolant Pump Motor Failure Rates", R. A. Buttner, ANS/ENS International Conference on Reactor Operations, Chicago, August 1987.

"IPE Methodology Test Application for Combustion Engineering Plants - IDCOR Individual Plant Examination for Calvert Cliffs" IDCOR Task, et al. 1987.

"Performing a Plant Specific PRA by Hand ‑ a Practical  Reality", M. Modarres, 1987 INTER‑RAM Conference, Toronto, May 1987.

"The Routine Use of PRA in the Evaluation of Nuclear Plant Modifications", 1986 Joint ANS/ASME Nuclear Power Conference Philadelphia, July 1986.

"Improving the Performance of Critical Plant Components ‑ an Analytical Approach", 1986 INTER‑RAM Conference for the Electric Power Industry, Syracuse, June 1986.

"The Integrated Approach Methodology for Operator Information Evaluation", Mohammed Modarres, R. Pearce, K. Stroube 1986 ANS/ENS Topical Conference on Human Factors Knoxville, April 1986.

"An Integral Approach to Analysis of Potential Plant Improvements", Mohammed Modarres, Marvin Roush, R. Pearce, American Power Conference Chicago, April 1986.

"Equivalent Availability Analysis as an Integral part of a Nuclear Plant Productivity Improvement Program", ASME Winter Annual Meeting Miami Beach, November 1985.

"Application of an LWR Operator Information Systems Analysis to the Calvert Cliffs Nuclear Power Plant ‑ Unit 1" (ALO ‑ 1023), Marvin Roush, Joseph Braun, et al.

"Use of a Plant Level Logic Model for Quantitative Assessment of some Experienced Systems Interaction", B. B. Chu, D. C. Rees, L. J. Kripps, Melissa Bradley, 1985 ASME Winter Annual Meeting Miami Beach, November 1985.

"Application of Goal Trees for Nuclear Power Plant Hardware Protection", Mohammed Modarres, Marvin Roush, 8th International Conference on Structural Mechanics in Reactor Technology Brussels, Belgium, August 1985.

"Use of the Goal Tree Methodology to Evaluate Institutional Practices and their Effect on Power Plant Hardware Performance", Marvin Roush, Mohammed Modarres, presented at the 1985 INTER‑RAM Conference, Baltimore, April 1985.

"Using 'GO' to Routinely Evaluate the Risk Significance of Nuclear Plant System Inter‑actions", Presented at the 1985 INTER‑RAM Conference, Baltimore, April 1985.

"Application of Goal Trees in Reliability Allocation for Systems and Components of Nuclear Power Plants", Mohammed Modarres, Marvin Roush, Presented at the 1985 INTER‑RAM Conference, Baltimore, April 1985.

"Application of Goal Trees to Evaluation of the Impact of Information upon Plant Availability", Marvin L. Roush, Mohammed Modarres, International ANS/ENS Topical Meeting, Probabilistic Safety Methods & Applications, San Francisco, February 1985.

"PRA ‑ A Pragmatic Tool for Utility Risk Management?", Int’l ANS/ENS Topical Meeting, Probabilistic Safety Methods and Applications, San Francisco, February 1985.

"Integrated Economic Risk Management in a Nuclear Power Plant", Mohammed Modarres, Society for Risk Analysis, Annual Meeting in Knoxville, October, 1984.

"Selection of Availability Analysis Techniques", 1984 Reliability Conference for the Utility Industry, Las Vegas, Nevada, April 1984.

"Nuclear Plant Event Evaluation", Melissa Bradley, 1984 Reliability Conference for the Utility Industry, Las Vegas, Nevada, April 1984.

"A Hierarchal Goal Tree Structure for Containment Integrity", Marvin L. Roush, Mohammed Modarres, Second Workshop on Containment Integrity ‑ 1984.