3 Day Course
Instructor: George Antaki, P.E. or Greg Hollinger, P.E.
This course reviews the application of the ASME Boiler and Pressure Vessel Section III code for the design of nuclear plant components: vessels, tanks, piping systems, pumps and valves. It addresses the roles and responsibilities of the Owner, the designer, the regulator, and the authorized nuclear inspector. The course reviews the design methods, equations, and criteria, with example applications. The course also provides the regulatory requirements which apply to these components and a historical perspective on the evolution of the design and regulatory rules.
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Instructor: George Antaki, P.E.
Becht Engineering's two-day public course that covers the design-analysis-qualification of B31.1 and ASME III nuclear plant piping systems, the evaluation of degraded conditions in accordance with ASME XI (erosion-corrosion, cracking), the evaluation of abnormal conditions in accordance with NRC Inspection Manual Chapter 0326, and repair options in accordance with ASME XI (safety-class piping) and ASME PCC-2 (non-safety piping).
Currently Offered:May 6, 2020 - Houston, TX
1 or 2 Day Courses at YOUR Facility
ASME III Technical Requirements: Understand the technical basis of the design and fabrication requirements for ASME III pressure equipment: vessels, pumps, valves, piping systems, and tanks
ASME XI Code Cases for the Operability Assessment of Corroded Equipment: Review ASME XI CC N-513 and N-597 (above ground piping), and CC N-806 (buried pie), their procedures, their technical basis, and their implementation through case studies. Review the assessment techniques for vessels, tanks, and other pressure equipment.
Introduction to Fracture Mechanics for the Evaluation of Crack-Like Flaws: Types and causes of of crack-like flaws, integrity assessment using ASME XI fracture mechanics, crack stability, crack propagation, environmental fatigue, leak-before-break, repair options.
Piping Systems: Review and understand the technical basis of the design and analysis rules of ASME III and B31.1, high energy line break, seismic design, trouble-shooting, flow-induced vibration, waterhammer, over-pressure.
Buried Pipe Integrity Assessment: Review and understand the technical basis for the design equations and design margins for buried pipe, types of damage mechanisms, operability and end-of-life assessment of corroded buried pipe.
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Mr. Larsen has 15 years of engineering design and analysis experience. He has experience in static, dynamic, thermal, and fatigue analysis for both linear and non-linear problems. He specializes in Finite Element Analysis modeling and simulation of structures, vessels, and equipment that include seismic, external loading, and heat transfer using ANSYS. Code experience with ASME Section VIII, AISC, ASCE-7,
2 Day Course
The course addresses the design and analysis of buried metallic pipe, their technical basis and practical application. We will develop the design loads: normal and transient pressure, temperature, soil and surface loads, flood loads, settlements, and seismic. We will perform design calculations using simplified formulas, and have an introduction to more advanced analysis methods. The course will then provide an example for evaluating the integrity and remaining life of corroded buried pipe.
Mr. Derrick Pease has over 15 years experience in mechanical engineering design and analysis. He is an expert in stress analysis of complex structures that include seismic, fatigue, creep, heat transfer, fluid-structure interaction, impact, and explosion responses. He is also an expert in fluid flow analysis of piping systems, root-cause failure analysis, and fitness-for-service assessments. Mr. Pease specializes in advanced finite element modeling and simulation of
2 to 3 Day Course
Instructor: Greg Hollinger
The course provides a practical step-by-step approach to complying with the analysis and qualification requirements of ASME III Class 1, 2, and 3 pressure vessels. Through a series of example, the course addresses the requirements of the Design Specification, the design and analysis rules of NB/NC/ND-3100, 3200, and 3300; and the preparation of a Design Report. The design rules for vessel supports are presented. The interfaces, roles and responsibilities between the N-stamp fabrication and the NB design are outlined and explained.
Instructor: George Antaki, P.E. and Tony Scribner, P.E.
The course explains the technical basis of the ASME XI wall thinning corrosion code cases N-513 and N-597, and then applies the Code Cases to a series of actual corrosion patterns. The application covers all aspects of the assessment: Inspection methods, collection of necessary design data, prediction of corrosion rate and future wall loss, evaluation in accordance with the Code Cases, and options on what to do if the corrosion does not qualify. The participants will receive a MathCad module to perform hands-on application problems.
Instructor: George Antaki, P.E. and J Robert Sims
The course explains the technical basis of the ASME XI fracture mechanics rules, and then applies the Failure Assessment Diagram method of Appendix H to examples of cracks and crack-like defects in nuclear piping and vessels. The application covers all aspects of the assessment: Inspection methods, collection of necessary design data, prediction of crack growth rate, evaluation in accordance with ASME XI Appendix H (and Appendix C), and options on what to do if the crack does not qualify.
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Dr. Abatt, Fellow ASCE, has over 30 years experience in engineering practice, education, and management of multi-disciplinary engineering teams. He has authored numerous technical reports and presentations in his professional career that highlight his technical expertise with linear and nonlinear structural analysis, seismic analysis, soil-structure interaction, fluid-structure interaction, and impact analyses. Dr. Abatt has acted as a Subject Matter Expert for both the US Department of Energy and the US Nuclear Regulatory Commission. He is the Vice-Chair of the ASCE Dynamic Analysis of Nuclear Structures Committee and is the Manager of the Richland, Washington Office of Becht Engineering.
The course covers Fitness-For-Service (FFS) assessment of aged and/or damaged tanks, Vessels and piping systems, in accordance with API 579-1/ASME FFS-1 - using case studies. Make run-or-repair decisions, in accordance with API 579-1/ASME FFS-1. Understand the technical and historical bases of the API 579-1/ASME FFS-1 methods and criteria Repair Options (ASME PCC-2, API-653, NBIC NB-23): If repair is necessary, select the repair, in accordance with ASME PCC-2 and compare to other repair standards (API and NBIC).
Currently Offered:September 21, 2020 - Houston, TX
Mr. Antaki, Fellow ASME, has over 40 years of experience in nuclear power plants and process facilities, in the areas of design, safety analysis, startup, operation support, inspection, fitness for services and integrity analysis, retrofits and repairs. George has held engineering and management positions at Westinghouse and Washington Group International, where he has performed work at power and process plants, and consulted for the Department of Energy (DOE), the Nuclear Regulatory Commission (NRC) and the Electric Power Research Institute (EPRI). He also is an
Mr. Hollinger has 37 years of professional engineering experience in nuclear power generation. He has been involved in design and fabrication of reactor vessels, steam generators and pressurizers, and piping for commercial and non-commercial nuclear systems since 1978, as well as, non-nuclear vessel design, fabrication and certification. Specialization includes stress classification, fatigue and elevated temperature design for pressure vessel components. Additional
Mr. Cole has 37 years of experience in design, analysis, construction and testing of nuclear power plant equipment, piping, vessels, and structures. Mr. Cole’s experience includes twenty seven years of operating nuclear power plant experience and twenty seven years as an ASME Codes and Standards committee volunteer. Prior to retiring from Energy Northwest, Mr. Cole served as the Design Authority for Columbia Generating Station Civil/Structural discipline. He was responsible for approval of plant design changes, assuring
Mr. Stoops has over 11 years of experience in mechanical engineering design and analysis. He also has over 4 years experience in nuclear Quality Assurance (QA), and currently serves as Quality Assurance Manager for Becht Nuclear Services. In his role as an engineer, his fields of expertise include seismic analysis of vessels, piping, lifting beams, air filter housings, and other structures. Mr. Stoops specializes in advanced finite element
The course studies a series of abnormal conditions, failures or near-failures in nuclear power plant vessels and piping systems, and the lessons learned to prevent their recurrence. The failures are reviewed as case studies, and are traced back to short-comings in systems (thermo-hydraulics, abnormal transients, etc.), materials (inadequacy, corrosion, etc.), detailed design (over-loads, abnormal conditions, etc.), operations (operation outside of the design envelope, etc.), and inspections (adequacy of the ISI plan for the damage mechanisms, interpreting inspection results, making the right run-or-repair decision, etc.).
Mr Annon has over 45 years of engineering, managerial (including Nuclear Oversight), training and management consulting experience at approximately 50 nuclear and fossil fueled power plants, and several Department of Energy (DOE) facilities. He has authored multiple technical, project management and training related papers.
Mike's career has included employment with Stone & Webster, Gilbert Associates, Proto-Power (Zachry Engineering), Northeast Utilities (Millstone), and I&C Engineering Associates where his areas of expertise included project management and management consulting, Instrumentation and Control (I&C) and electrical systems as applied to design, licensing, startup, testing, operations, and interfacing with the Nuclear Regulatory Commission (NRC).
The course evaluates a series of plant vibration issues recorded at nuclear power plants. A systematic approach is presented to investigate the root-cause of the vibration, its significance (run-or-repair), the inspection for damage, and the alternatives to eliminate the cause of vibration. The analysis of vibration is presented in the context of ASME O&M Part 3, with example applications of the Standard.
This course covers the fundamentals of design, layout, fabrication, examination and testing as it relates to preventative repairs and modifications of piping systems.
Instructor: Frederick J. Moody, PhD
A practical course to understand and predict transients and hammers in piping systems, including 2‐phase flow and trapped gas effects.