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

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

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

ASME BPV Code, Section XI: Inservice Inspection of Nuclear Power Plant Components (On Demand)
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Buying for a group? Get 5 seats for 25% off.

Get 5 seats in any Self Study course, Guided Study course, or Learning Path for 25% off.

Use discount code 5FOR25 at checkout.

 

Learn more about our Design and Analysis of Piping Systems and Operability Assessment of Nuclear Power Plant Components Learning Path.

This Self Study course is available on ASME’s Learning Hub, our online learning platform and is designed to be taken at your convenience, and on your own schedule. You have 90 days to complete the course from the date of purchase.
 
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.
 
This On Demand course features recordings of Live Virtual Classroom sessions taught by ASME’s expert Instructor.  Course material includes published ASME Interpretations that explain how Code requirements can be applied to problems that have confronted other companies. This video-based course also highlights significant changes in the Code requirements in the last ten to fifteen years.
 
By participating in this course, you will learn how to successfully:

  • 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?
The course is designed to provide an introduction to Section XI for people who are not at all familiar with it, as well as to provide, for the experienced Section XI user, an entirely new understanding of some of the many confusing and controversial parts of Section XI. This includes 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.

A certificate of completion with 2.7 CEUS / 27 PDHs will be issued to registrants who successfully complete the course.

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Outline

Course Introduction

  • Meet Your Instructor
  • History, Background & Scope
  • Introduction to Section XI | Front Matter

Introduction to Section XI Subsections (Subsection IWA-IWE, IWL; Articles 1000 & 2000) 

  • General Requirements | IWA-1000 
  • General Requirements | IWA-2000 
  • Class 1 Components | IWB-1000, IWB-2000
  • Class 2 Components | IWC-1000, IWC-2000
  • Class 3 Components | IWD-1000, IWD-2000
  • Class MC and Metallic Liners of Class CC Components | IWE-1000, IWE-2000
  • Class 1, 2, 3, and MC Component Supports | IWF-1000, IWF-2000
  • Class CC Concrete Components | IWL-1000, IWL-2000

Acceptance Standards (Article 3000) 

  • Standards for Examination Evaluation | IWA-3000, IWB-3000, IWC-3000, IWD-3000, IWF-3000, IWL-3000

Repair/Replacement Activities (Article 4000) 

  • Definitions | IWA-9000 & NCA-9000
  • General Requirements | IWA-4100
  • Items for Repair/Replacement Activities | IWA-4200
  • Design | IWA-4300
  • Welding, Brazing, Metal Removal, Fabrication and Installation | IWA-4400
  • Alternative Welding Methods | IWA-4600
  • Heat Exchanger Tubing | IWA-4700
  • Repair/Replacement Activities for Class CC Concrete Components | IWL-4000
  • Examination and Testing | IWA-4500

Pressure Testing (Article 5000) 

  • System Pressure Tests | IWA-5000
  • System Pressure Tests | IWB-5000, IWC-5000, IWD-5000, IWE-5000, IWL-5000

Documentation and Data Reports (Article 6000) 

  • Records and Reports | IWA-6000
  • Glossary | IWA-9000
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Course Developer

Rick Swayne

Senior Consultant, Reedy Engineering

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

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