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2019 ASME BPVC: Nuclear Inservice

In 2019, Section XI was replaced with two divisions of Section XI, with Division 1 being a redesignation of Section XI and Division 2 is an entirely new subsection. Find a detailed description of the ASME BPVC section code related to inspection of nuclear power plant components and pre-order the individual section below:

Return to the main ASME Boiler & Pressure Vessel Code (BPVC) page

Pre-order ASME BPVC Section XI-Division 1: Rules for Inservice Inspection of Nuclear Power Plant Components

ISBN: 9780791871027

This Section provides rules for the examination, inservice testing and inspection, and repair and replacement of components and systems in light water cooled nuclear power plants.

Application of this Section of the Code begins when the requirements of the Construction Code have been satisfied. The rules of this Section constitute requirements to maintain the nuclear power plant while in operation and to return the plant to service following plant outages. The rules require a mandatory program to evidence adequate safety and manage deterioration and aging effects. The rules also stipulate duties of the Authorized Nuclear Inservice Inspector to verify that the mandatory program has been completed, permitting the plant to return to service in a safe and expeditious manner.

Referenced BPVC Sections

  • BPVC-II, A, B, C, D (Section II, Materials, Parts A through D)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection NCA, General Requirements for Division 1 and Division 2)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection NB, Class 1 Components)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection NC, Class 2 Component)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection ND, Class 3 Components)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection NE, Class MC Components)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection NF, Supports)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Subsection NG, Core Support Structures)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Appendices)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Division 2-Code for Concrete Containments)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Division 3-Containments for Transportation & Storage of Spent Nuclear Fuel and High Level Radioactive Material & Waste)
  • BPVC-III (Section III, Rules for Construction of Nuclear Facility Components: Division 5, High Temperature Reactors)
  • BPVC-V (Section V, Nondestructive Examination)
  • BPVC-VIII-1-2 (Section VIII, Pressure Vessels, Division 1 and Division 2)
  • BPVC-IX (Section IX, Welding, Brazing and Fusing Qualifications)

Referenced ASME Standards

  • NQA-1 - Quality Assurance Requirements for Nuclear Facilities Applications (QA)
  • QAI-1 - Qualifications for Authorized Inspection
  • RA-S - Standard for Level 1/Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications
  • NQA-1 - Quality Assurance Requirements for Nuclear Facility Applications (QA). Provides requirements and guidelines for the establishment and execution of quality assurance programs during siting, design, construction, operation and decommissioning of nuclear facilities. This Standard reflects industry experience and current understanding of the quality assurance requirements necessary to achieve safe, reliable, and efficient utilization of nuclear energy, and management and processing of radioactive materials.
  • NQA-1 focuses on the achievement of results, and emphasizes the role of the individual and line management in the achievement of quality. It fosters the application of these requirements in a manner consistent with the relative importance of the item or activity.

Pre-order ASME BPVC Section XI-Division 2: Rules for Inservice Inspection of Nuclear Power Plant Components

This Section provides rules for the examination, inservice testing and inspection, and repair and replacement of components and systems in light water cooled nuclear power plants.

This Section provides the requirements for the creation of the Reliability and Integrity Management (RIM) Program for advanced nuclear reactor designs. This Program is an alternative approach to the rules in Division 1 of this Section.

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