Logo
Login Sign Up
Current Revision

ASME BPVC.XI.1-2025

2025 ASME Boiler and Pressure Vessel Code, Section XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components
Best Price Guarantee
5-10 Days

$615.00


Sub Total (1 Item(s))

$ 0.00

Estimated Shipping

$ 0.00

Total (Pre-Tax)

$ 0.00


View in Library
or
American Society of Mechanical Engineers Logo

ASME BPVC.XI.1-2025

2025 ASME Boiler and Pressure Vessel Code, Section XI, Division 1, Rules for Inservice Inspection of Nuclear Power Plant Components

PUBLISH DATE 2025
ASME BPVC.XI.1-2025
The purpose of ASME BPVC.XI.1-2025 is to establish the mandatory Rules for Inservice Inspection and Testing of components in Light-Water-Cooled Nuclear Power Plants (LWRs). It is the code that governs the operational life of the reactor after construction is complete.
What It Is Used For This document, ASME Section XI, Division 1, forms a mandatory program, required by nuclear regulatory bodies worldwide, to manage the safety and aging of operating nuclear facilities. It ensures that components originally built to the construction code (ASME Section III) maintain their integrity throughout their operating life. Its primary uses are:
  • Inservice Inspection (ISI) Program: It dictates a mandatory program of scheduled examinations, inspections, and pressure tests for safety-related Class 1, 2, and 3 pressure-retaining components (vessels, pumps, valves, and piping) and their supports.
  • Managing Degradation: The rules are specifically designed to manage deterioration and aging effects (such as fatigue, stress corrosion cracking, and neutron embrittlement) that occur during service, ensuring component safety margins are maintained.
  • Flaw Evaluation: It provides the criteria and methodologies for evaluating flaws or defects discovered during inspections. This includes determining the acceptability of the flaw, assessing its potential for growth, and stipulating conditions for continued operation.
  • Repair/Replacement Activities: It mandates the processes, qualifications, and quality assurance requirements for all repair, replacement, and modification activities performed on nuclear components during plant outages to ensure they meet construction code standards before the plant returns to service.
  • Oversight: It stipulates the duties of the Owner and the Authorized Nuclear Inservice Inspector (ANII), whose verification is required before the plant can legally return to service following an outage.
In summary, BPVC.XI.1 is the indispensable operational Code for the nuclear power industry, providing the comprehensive rules for maintaining the safety and reliability of the reactor and its critical systems once they are placed into service.
SDO ASME: American Society of Mechanical Engineers
Document Number BPVC.XI.1
Publication Date July 1, 2025
Language en - English
Page Count
Revision Level
Supercedes
Committee
Loading...

Failed to load document history.

Publish Date Document Id Type View