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  1. Home
  2. ASME BPVC.XI.2-2023

ASME BPVC.XI.2-2023 Historical

2505376  Preview

2023 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Reactor Facility Components - Division 2: Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities

standard by ASME International , 07/01/2023

This document has been replaced. View the most recent version.

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Full Description

Please note: the format of this publication is loose-leaf. Please visit this page if you would like to add a binder to your order.

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 2 provides the requirements for establishing Reliability and Integrity Management (RIM) Programs for any type of nuclear reactor facility. The program shall include the following elements:

  • Owner’s responsibility
  • Areas subject to inspection or monitoring or both
  • Provisions for accessibility and inspection
  • Examination methods and procedures
  • Personnel qualifications
  • Frequency of inspection
  • Record keeping and report requirements
  • Procedures for evaluation of inspection and monitoring results and subsequent disposition of results of evaluations
  • Repair and replacement activity requirements, including procurement, design, welding, brazing, defect removal, fabrication, installation, examination, and leakage testing

The RIM Program addresses a facility's entire life cycle. It is applicable over the entire life of the facility and includes each passive structure, system, or component (SSC) that is in its scope. It specifies a combination of monitoring, examination, tests, operation, and maintenance requirements that ensure SSCs meet the facility risk and reliability goals (i.e., Reliability Targets) that are selected for the RIM Program.

Division 2 rules also stipulate duties of the Authorized Nuclear Inservice Inspector to verify that the program has been completed, implemented, and updated in accordance with the requirements of Division 2.

Application of Division 2 begins when the requirements of the Construction Code have been satisfied. It is applicable regardless of the Construction Code classification used for an SSC if the SSC is designated as important to the safety and reliability of an operating facility.

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.

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Document History

  1. ASME BPVC.XI.2-2025

    July 2025
    Section XI, Rules for Inservice Inspection of Nuclear Reactor Facility Components, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities

    • Most Recent  Most Recent
  2. ASME BPVC.XI.2-2023

    You are currently viewing this product 👀 currently
    viewing

    July 2023
    2023 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Reactor Facility Components - Division 2: Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Reactor Facilities

    • Historical Version
  3. ASME BPVC.XI.2-2021

    July 2021
    2021 ASME Boiler and Pressure Vessel Code, Section XI.2: Rules for Inservice Inspection of Nuclear Power Plant Components, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants

    • Historical Version
  4. ASME BPVC.XI.2-2019

    July 2019
    2019 ASME Boiler and Pressure Vessel Code, Section XI.2: Rules for Inservice Inspection of Nuclear Power Plant Components, Division 2, Requirements for Reliability and Integrity Management (RIM) Programs for Nuclear Power Plants

    • Historical Version
  5. ASME BPVC.XI-2017

    July 2017
    2017 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components

    • Historical Version
  6. ASME BPVC-XI-2015

    July 2015
    2015 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components

    • Historical Version
  7. ASME BPVC-XI-2013

    July 2013
    2013 ASME Boiler and Pressure Vessel Code (BPVC), Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components

    • Historical Version
  8. ASME BPVC-XI-2010

    July 2010
    2010 ASME Boiler and Pressure Vessel Code (BPVC), Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components, Includes 2011 Addenda Reprint

    • Historical Version

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  • ASME International > ASME Enterprise Collections > ASME BPVC Nuclear Technology
  • ASME International > ASME Enterprise Collections > ASME Small Modular Reactor (SMR)

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Product Details

Published:

07/01/2023

ISBN(s):

9780791875889

Number of Pages:

151

Part of:

ASME BPVC-2023 SET, ASME BPVC-2023 SET with Binders

Product Code(s):

400112

Note:

This product is restricted and cannot be purchased in the following countries Ukraine, Russia, Belarus
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