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
Course Number:
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 ASME III Requirements for Piping Systems
Module 2: Overview of Regulatory Requirements
Module 3: Design Loads and Load Combinations
Module 4: Nuclear Piping Qualification Criteria
Module 5: Pressure Design
Module 6: Flexibility Analysis Secondary Stresses
Module 7: Fatigue Analysis and Environmental Fatigue Effects
Module 8: Primary Stress Equations Class 2-3 and B31.1
Module 9: Historical Perspective and Key Changes
Module 10: Problem Input Software
Module 11: Class 1 Difference with Class 2-3 and B31.1
Module 12: Metal Loss Assessment Using Section XI Code Cases
Module 13: Assessment of Crack-Like Flaws, Fracture Mechanics Using Section XI Ap.H
Module 14: Operability Assessment in Accordance with NRC Inspection Manual
Module 15: Case Study of Over-Pressure
Module 16: Case Study Thermal Over-Stress
Module 17: Repair Options for Non-Safety-Related Piping Systems per ASME PCC-2
Module 18: Repair Options for Safety-Related Piping Systems per ASME XI and NRC
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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