training & development
PD632 - Design in Codes, Standards & Regulations for Nuclear Power Plant Construction

PD632 - Design in Codes, Standards & Regulations for Nuclear Power Plant Construction

Pricing and Availability

Pricing and dates are pending, please check back.



The course provides details of the ASME Section III Division 1 code requirements and their technical basis for the design of Class 1, 2 and 3 piping, pumps, valves and vessels in nuclear power plants. Topics include overview of the ASME Section III design requirements, methods of analysis and qualification criteria for each type of component, design by rule, design by analysis and qualification by testing, and supplementary requirements imposed by regulation (regulatory guides, standard review plan, etc.) The course also covers related ASME codes and standards such as B16, QME-1, and OM.

Each student will receive copies of BPVC Section III - Rules for Construction of Nuclear Facility Components, Division 1, Subsection NC: Class 2 Component; and BPVC Section III - Rules for Constructions of Nuclear Facility Components-Subsection NCA - General Requirements for Division 1 and Division 2.

You Will Learn To
 - Identify Regulatory requirements and explain how they affect the contents of a Section III, Division 1 Component Design Specification
 - Define requirements and loads and develop the contents of an ASME Section III Design Specification to ensure that a Section III Division 1 Component Design Specification contains the minimum ASME requirements  Apply the methods and criteria for design-by-rule and design-by-analysis, and the relationship between rules and analysis, such as using finite element methods
 - Apply the NC-3000 design rules and analyses in conjunction with the “design-construction interfaces” in NC-1000, -2000, -4000, -5000, -6000, -7000, -8000
 - Apply the process and analysis and qualification for the Design, Operating Levels A, B, C and D and Test loadings and determine or explain how the results are reported in a Section III Division 1 Component Design Report
 - Describe key differences and similarities between Class 1, 2 and 3 Components

Please click HERE to view the course outline.

Who Should Attend
Engineers, managers and quality personnel and inspectors involved in the design, analysis or fabrication of components or structures for nuclear power plants.

For venue information, please click HERE.

  • Course Type: Public Course
  • Course Number: PD632
  • Language: English
Final invoices will include applicable sales and use tax.


Greg L. Hollinger has over 40 years of experience in power related industries, including commercial nuclear power and other nuclear power technologies. Thirty years of that experience was with The Babcock & Wilcox Nuclear Power Generation Group in areas of design, code certification, completed component shipping, quality assurance and technical training on nuclear and non-nuclear codes and standards. Ten years of experience has been with Becht Engineering’s Nuclear Service Division in similar areas. Mr. Hollinger is retired, but continues as a part-time Engineering Advisor for Becht Engineering. He has been a member of ASME Boiler and Pressure Vessel Nuclear Code committees and the ASME Board on Nuclear Codes & Standards. Mr. Hollinger is an ASME Section III Appendix XXIII Certified Registered Professional Engineer, and serves in that capacity for various companies. In 2004 he was honored with the ASME Pressure Vessels and Piping Division Medal.

George Antaki, P.E., Becht Engineering, is a Fellow of ASME, with over 40 years of experience in pressure equipment. He is an ASME Fellow, internationally recognized for his expertise in design, analysis, and fitness-for-service evaluation of pressure equipment and piping systems. He is the Chairman of ASME B31 Mechanical Design Committee, Chairman of ASME III Working Group Piping Design, member of the ASME III Subgroup Component Design, ASME QME, and ASME Operation and Maintenance Subgroup Piping. He is the author of three textbooks on the subject of pressure equipment design and integrity evaluation, including, “Fitness-for-Service for Piping, Vessels, and Tanks.”

Mr. Antaki earned his degree in Nuclear Engineering from the University of Liege, Belgium in 1975, and his Master’s degree in Mechanical Engineering from Carnegie Mellon University in 1985.
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