Nuclear Piping Systems ASME BPV Code, Section III and ASME B31.1: Design, Integrity-Operability Assessment, and Repairs
About This Course
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.
- Downloadable course notes via ASME’s Learning Platform.
- Access to a digital copy of ASME PCC-2 Repair of Pressure Equipment and Piping Standard during the course
- This ASME Virtual Classroom course is held live with an instructor on our online learning platform. A certificate of completion will be issued to registrants who successfully attend and complete the course.
- 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.
Overview of ASME III requirements for piping systems
Overview of B31.1 requirements for nuclear plant piping systems
Historical perspective and key changes to codes of record 1960’s-current
Overview of regulatory requirements
Design loads and load combinations
Design qualification requirements
Sustained loads design
Flexibility analysis and fatigue
Pipe stress modeling guidance
Dynamic loads in nuclear plant piping
Seismic OBE and SSE
Hydraulic transient loads
Wind and tornado loads
Primary stress equations Class 2-3 and B31.1
Class 1 equations and difference with Class 2-3
Class 1 fatigue, life extension, and environmental fatigue effects
Operability assessment in accordance with NRC Inspection Manual
Case study accidental over-pressure
Case study locked snubber
Corrosion-erosion assessment using Section XI code cases
Assessment of crack-like flaws, fracture mechanics using Section XI Ap.H
Repair options for safety-related piping systems per ASME XI and NRC
Repair options for non-safety-related piping systems per ASME XI and NRC
Authorized Training Instructor, ASME