ASME BPVC.XI.1-2023

ASME BPVC Section XI Division 1 2023 PDF

The rules of Section XI constitute requirements to maintain the nuclear reactor facility and to return the facility to service, following facility outages, in a safe and expeditious manner.

Section XI – Division 1 provides requirements for inservice inspection and testing of light-water-cooled nuclear power plants. The requirements identify the areas subject to inspection, responsibilities, provisions for accessibility and inspectability, examination methods and procedures, personnel qualifications, frequency of inspection, record keeping and report requirements, procedures for evaluation of inspection results and subsequent disposition of results of evaluations, and repair/replacement activity requirements, including procurement, design, welding, brazing, defect removal, fabrication, installation, examination, and pressure testing. Application of Division 1 begins when the requirements of the Construction Code have been satisfied.

Division 1 rules require a mandatory program of examinations, testing, and inspections to evidence adequate safety and to 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 an expeditious manner.

Careful application of this Section will help users to comply with applicable regulations within their jurisdictions, while achieving the operational, cost and safety benefits to be gained from the many industry best-practices detailed within these volumes.

LIST OF SECTIONS

SECTIONS

I Rules for Construction of Power Boilers

II Materials

• Part A — Ferrous Material Specifications

• Part B — Nonferrous Material Specifications

• Part C — Specifications for Welding Rods, Electrodes, and Filler Metals

• Part D — Properties (Customary)

• Part D — Properties (Metric)

III Rules for Construction of Nuclear Facility Components

• Subsection NCA — General Requirements for Division 1 and Division 2

• Appendices

• Division 1

– Subsection NB — Class 1 Components

– Subsection NCD — Class 2 and Class 3 Components

– Subsection NE — Class MC Components

– Subsection NF — Supports

– Subsection NG — Core Support Structures

• Division 2 — Code for Concrete Containments

• Division 3 — Containment Systems for Transportation and Storage of Spent Nuclear Fuel and High-Level

Radioactive Material

• Division 4 — Fusion Energy Devices

• Division 5 — High Temperature Reactors

IV Rules for Construction of Heating Boilers

V Nondestructive Examination

VI Recommended Rules for the Care and Operation of Heating Boilers

VII Recommended Guidelines for the Care of Power Boilers

VIII Rules for Construction of Pressure Vessels

• Division 1

• Division 2 — Alternative Rules

• Division 3 — Alternative Rules for Construction of High Pressure Vessels

IX Welding, Brazing, and Fusing Qualifications

X Fiber-Reinforced Plastic Pressure Vessels

XI Rules for Inservice Inspection of Nuclear Reactor Facility Components

• Division 1 — Rules for Inspection and Testing of Components of Light-Water-Cooled Plants

• Division 2 — Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor

Facilities

XII Rules for Construction and Continued Service of Transport Tanks

XIII Rules for Overpressure Protection