Following are selected examples of this expert's work experience.
Evaluated NDE data from an emergency diesel generator heat exchanger channel head that was leaking. Determined degradation mechanism and extent, determining acceptability of leakage. Prepared request for relief from NRC requirements.
Reviewed designs for full structural overlay welds to mitigate PWSCC cracking of nickel alloy welds. Became a member of the EPRI committee developing standards for such overlays.
Oversaw vendor activities, showed how stainless steel nozzles could be used for an alloy steel pressurizer vessel despite the fatigue issues caused by severe thermal transients at the nozzles. Served as the owner’s technical representative and reviewed all vendor analyses. Performed on-site review of fabrication at a facility in France.
Served as one of the founding members and eventually chair of the EPRI MRP committee on reactor internals, which has developed a guideline for inspection and evaluation of these components. Developed the rationale for basing inspection requirements on aging analysis of the internals, utilizing a comprehensive material behavior model that includes the effects of void swelling, creep, irradiation assisted stress corrosion cracking, and others.
Spearheaded the development of a specialized methodology for evaluating leaking brazed piping joints. Methodology included straight beam UT of brazed joint, development of a lab testing program to determine strength of low-bond joints, development of the correlation between bond measurements and joint strength, development of a spreadsheet program to quickly determine joint strength based on measured bond, preparation and defense of an alternative request to NRC to permit future use of the methodology without their prior approval.
With a consultant, developed a specialized analysis program to predict pressure pulsations and pipe forcing functions due to a triplex positive displacement charging pump. The analysis model included all discharge piping and also a dynamic hydro-mechanical model of the relief valves. The analysis model was used to simulate relief valve lift and chattering events during pump start, and predict the effectiveness of attached dampener devices.
Was one of the initial members in a team sponsored by a vendor to develop risk-informed piping ISI methodologies. Utilized probabilistic fracture mechanics programs to determine probability of failure for piping welds. Helped developed one of the first pilot applications of the technology to an actual power plant. Defended the methodologies and results to the regulator. Applied the final approved methodology to two nuclear power plants.
Performed finite element analysis (FEA) of a power plant steam condenser including shell, waterbox, and tube bundle showing the acceptability of alternative tubing/tube sheet material. This analysis showed the high degree of coupling between the inlet and outlet tubesheet/waterbox assemblies.
Involved in development of a program for a new plant design to utilize an alternative to ASME quality requirements for instrumentation tubing systems.
Managed a team of engineers in tasks to reconstitute a nuclear plant design basis. In this capacity was responsible for proposal development, schedule, budget, quality and client interface. Completed tasks included engineering review of structural seismic analysis methods and development of valve, equipment and support flexibilities for piping analysis.
Responsible for as-built reconciliation of small bore piping at two power plants. Each of the small bore programs entailed the as-built reconciliation of over 800 packages leading to ASME N-5 certification of the safety-related piping systems.
Performed plant startup testing activities at two power plants included planning, procedure development, direction of field activities and evaluation of test results for both thermal expansion and piping vibrations.
Assigned overseas at the site of the ARC Ras Lanuf, Libya ethylene refinery/power generation complex. Responsible for direct liaison with the piping, supports and steel erection contractor to resolve installation problems and approve related design changes.
Served as Lead Engineer for all engineering mechanics responsibilities (piping, equipment, supports) during completion of construction of a nuclear power station. Responsible for technical direction and supervision of personnel.
Reviewed hundreds of pipe support baseplates for excessive flexibility per NRC IE Bulletin 79-02.
Prepared ASME III Design Stress Reports for Class 1 piping.
While a physics graduate student, refurbished a vacuum system for a small van DeGraf accelerator.
