training & development
PD615 - Nuclear Piping Systems BPV Code, Section III and B31.1: Design, Integrity-Operability Assessment, and Repairs

PD615 - Nuclear Piping Systems BPV Code, Section III and B31.1: Design, Integrity-Operability Assessment, and Repairs

Date & Location   Member Price List Price Qty

London, GBR
Jun 11, 2018 - Jun 13, 2018


Houston, TX, USA
Mar 19, 2018 - Mar 21, 2018


Bellevue, WA, USA
Apr 9, 2018 - Apr 11, 2018




Length: 3 days    CEUs: 2.30    PDHs: 23.00

This course provides information and instruction on the design, analysis, and qualification of nuclear power plant piping systems that are consistent with the ASME Boiler and Pressure Vessel Code, Section III, Division 1, Subsections NB/NC/ND, as well as the parallel requirements of ASME B31.1 for nuclear power plants.  The methods and criteria described throughout the course, apply to new systems, as well as modifications or repairs to existing systems.

The course also addresses the integrity assessment of degraded nuclear piping systems (wall thinning and crack damage) using the methods and criteria of ASME XI, operability assessment per NRC Inspection Manual, and piping repairs per ASME XI and ASME PCC-2.

The course covers (a) the code and regulatory requirements, (b) the technical and historical basis of the requirements, and (c) best industry practices for the correct and cost-effective design, analysis, and integrity assessment.

Each student will receive a copy of the book, Nuclear Power Plant Safety and Mechanical Integrity: Design and Operability of Mechanical Systems, Equipment and Supporting Structures, by George Antaki and Ramiz Gilada

You Will Learn To
 - Describe Class 1, Class 2/3, and B31.1 nuclear piping design requirements
 - Explain the differences between Class 1, Class 2/3, and B31.1
 - Describe the NRC regulatory requirements related to ASME III and B31.1 piping systems
 - Evaluate normal operating loads (pressure, weight, thermal expansion)
 - Evaluate postulated design loads (seismic, waterhammer, vibration, pipe break, etc.)
 - Determine how to make the correct and cost-effective decisions in the design and modification of nuclear piping
 - Evaluate corroded (wall-thinning) nuclear piping
 - Evaluate crack-like flaws in nuclear piping
 - Assess operability of piping systems for abnormal conditions

Please click HERE to view the course outline.

Who Should Attend
Engineers involved in the design, analysis, and qualification of ASME Boiler and Pressure Vessel Code, Safety Class 1, 2 & 3 piping systems, and ASME B31.1 for nuclear power plants.
Participants are expected to have at least one year of experience in the design, maintenance, or operation of a nuclear power reactor facility.

For venue information, please click HERE.

  • Course Type: Public Course
  • Course Number: PD615
  • Language: English
Final invoices will include applicable sales and use tax.


For courses held in the U.S.:

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.

For courses held in Europe:

François Claeys is a Principal mechanical engineer at Tractebel Engineering S.A., which is a member of GDF SUEZ group. He has 25 years of experience in piping and support analysis, seismic qualification, piping vibrations, in-service inspection, repair & replacement activities for nuclear, power and industrial utilities. He has an extensive experience in Class 1 piping fatigue analysis and dynamic analysis in various projects like seismic revaluation, snubber reduction program, and primary circuit re-evaluation after SGR.
François is a member of the piping design working group of ASME Section III Committee. He attended the University of Louvain-La-Neuve in Belgium, where he received his degree in Mechanical Engineering. François is also a Seismic Qualification Utility Group (SQUG) specialist. He is responsible for teaching this course in Europe, only.
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