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

Nuclear | London

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

  • London: 11-13 June 2018
  • Length: 3 days
  • CEUs: 2.30
  • PDHs: 23.00

Description

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

Outline

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
  • 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

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.

  • Course Type: Public Course
  • Course Number: PD615
  • Language: English