Nuclear | London
PD615 | Nuclear Piping Systems ASME BPV Code Section III and B31.1: Design, Integrity Operability Assessment, and Repairs
- London: 17-19 June 2019
- 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 BPV 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 BPV Code, XI, operability assessment per NRC Inspection Manual, and piping repairs per ASME BPV Code, 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 of nuclear piping systems.
Participants 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
Please click HERE to view the course outline.
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 Piping Systems
- 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
Who Should Attend
This course is intended for engineers involved in the design, analysis, and qualification, troubleshooting and operability determination of ASME BPV 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.
- Course Type: Public Course
- Course Number: PD615
- Language: English
François Claeys is a Principal mechanical engineer at Tractebel Engineering S.A., which is a member of Engie group. He has 30 years of experience in piping and support analysis, seismic qualification and margin assessment, 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.