VCPD192 - ASME BPV Code, Section XI: Inservice Inspection of Nuclear Power Plant Components (Virtual Classroom) has been added to your cart.

ASME BPV Code, Section XI: Inservice Inspection of Nuclear Power Plant Components (Virtual Classroom)

Understand ASME Section XI rules for in-service inspection, maintenance, testing, and the regulatory requirements of nuclear power plant components with Virtual Training Course

This Standard was last reviewed and reaffirmed in {{activeProduct.ReaffirmationYear}}. Therefore this version remains in effect.

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This course runs from 9:30 AM to 6:00 PM Eastern each day, with scheduled breaks throughout.


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Covering all aspects of ASME BPV Code, Section XI, this course highlights repair, replacement, modification, and maintenance activities; pressure testing; and the relationship between the Code and regulatory and enforcement requirements for in-service inspection of nuclear power plant components. It addresses many controversial issues facing the nuclear industry and presents a broad spectrum of opinions regarding practical application of Code requirements. After taking this course, participants gain specific insight into how effective use of Section XI can significantly reduce plant operating costs.

Course material includes published ASME Interpretations that explain how Code requirements can be applied to problems that have confronted other companies. The course also highlights significant changes in the Code requirements in the last ten to fifteen years.

You Will Learn to:

  • Explain in-service inspection requirements for Class 1, 2, and 3 systems, components, and supports, and steel and concrete containment vessels
  • Describe requirements for qualification of nondestructive examination personnel and performance of nondestructive examination
  • Explain basic requirements for flaw evaluation and acceptance
  • Identify Section XI requirements for repair, replacement, modification, maintenance activities, and pressure testing
  • Explain how to use recent revisions to Section XI to your advantage
  • Describe the relationship of 10CFR50.55a and NRC Regulatory Guides, Bulletins, Generic Letters, and Regulatory Issue Summaries to inservice inspection, nondestructive examination, repair, replacement, and modification

Who Should Attend
This course is designed for utility operating personnel responsible for in-service inspection, nondestructive examination, evaluation, repair, replacement, and modification of nuclear power plants, and for personnel responsible for assessment or third-party inspection, regulation or enforcement. While experience with Section XI or other ASME Codes or Standards is not required, participants should have a strong technical background or hands-on experience with Code work.

Course Materials (included in purchase of the course) 

  • Participants will receive access to the following Code/Standard(s) via ASME’s Digital Collection for the duration of the course:
    • ASME BPV Code, Section XI:  Rules for Inservice Inspection of Nuclear Power Plant Components
  • Digital course notes via ASME’s Learning Platform

This ASME Virtual Classroom course is held live with an instructor on our online learning platform.  Certificate of completion will be issued to registrants who successfully attend and complete the course. 

Can't make one of the scheduled sessions? This course is also available On Demand


Topics Covered

  • Introduction to the ASME Boiler & Pressure Vessel Code and Code Committees
  • Organization of Section XI
  • General Requirements
  • Scope and applicability
    • Jurisdiction
    • Classification of components, including 10CFR50.2(v),
    • 10CFR50.55a and Regulatory Guide 1.26
    • Regulatory and jurisdictional requirements and responsibilities
    • (10CFR50.55a), including relief requests
    • Duties and responsibilities of the Owner
    • Authorized Inspection
  • Nondestructive examination, including personnel qualification
  • Inspection Plans and Schedules
  • Application of Code Cases
  • Examination requirements and exemptions
  • Acceptance criteria and corrective measures
  • Brief discussion on flaw evaluation
  • Evaluation of plant operating events not specifically included in Design Specifications (evaluations of non-anticipated events, such as water hammer, overpressurization, or new loads)
  • Scope of repair/replacement activities
  • Applicability of Section XI to repair, replacement, modification, and maintenance activities
  • Alternative requirements for small items
  • Items rotated from stock
  • Mechanical clamping devices
  • Responsibilities of Owners and Repair/Replacement Organizations
  • Stamping requirements for fabrication and installation
  • Preparation and content of Repair/Replacement Programs and Plans
  • Verification of acceptability (Suitability evaluations)
  • Authorized Inspection
  • Procurement of replacement items; reconciliation of changes in later Editions and Addenda of the Construction Code
  • Procurement of replacement items; reconciliation of changes in later Editions and Addenda of the Construction Code; NRC Generic Letter 89-09
  • Application of B31.1 and Section II, III, and VIII rules to Section XI repair, replacement, and modification, including quality assurance, materials, design, welding, heat treatment, examination, and testing requirements
  • Design documents; configuration control
  • Mitigation of defects by modification
  • Welding, brazing, and defect removal, including fabrication and installation; NRC Generic Letter 90-05 & IE Notice 93-41
  • Examination (Construction Code and preservice inspection)
  • Pressure testing (periodic and repair/ replacement)
  • Documentation and Data Reports

Rick Swayne

President, Reedy Engineering

Rick Swayne is the President of Reedy Engineering. He has worked in many different areas of the nuclear power industry, including consulting and teaching, for forty-five years.

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Virtual Classroom

Live course with an instructor and peers held in an online learning environment with digital enhancements and online materials.
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