Nuclear Piping Systems ASME BPV Code, Section III and ASME B31.1: Design, Integrity-Operability Assessment, and Repairs (On Demand)
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Self Study
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EL551Credits:
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Apply ASME Section III Division 1, Subsections NB/NC/ND to the design, analysis, and qualification of nuclear power plant piping systems in this On Demand course.
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This Self Study course is designed to be taken at your convenience and on your own schedule. You have 365 days from the time of purchase to finish the course.
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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.
This On Demand course features recordings of Live Virtual Classroom sessions taught by ASME’s expert Instructor. This video-based 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.
By participating in this course, you will learn how to successfully:
- 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, qualification, troubleshooting and operability determination of ASME BPV Code, Safety Class 1, 2 & 3 piping systems, and ASME B31.1 for nuclear power plants.
A Certificate of Completion will be issued to registrants who successfully complete the course.
Module 1: Overview of Codes and Regulations
Module 2: Pressure Design
Module 3: Thermal Effects + Finite Element Analysis
Module 4: Sustained and Occasional Loads
Module 5: Evaluation of Wall Thinning
Module 6: Evaluation of Crack-Like Flaws
Module 7: Evaluation of Over-Loads
Module 8: Repair Techniques - ASME PCC-2, ASME XI, and NBIC
George Antaki, P.E.
ASME Fellow
George Antaki, P.E., is an ASME Fellow with over 45 years of experience in pressure equipment. He is internationally recognized for his expertise in design, analysis, and fitness-for-service evaluation of pressure equipment & piping systems.
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Self Study
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