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About This Item
Full Description
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.
Document History
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ASME BPVC.XI.2-2023
currently
viewing
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- Most Recent
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ASME BPVC.XI.2-2021
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
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ASME BPVC.XI.2-2019
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
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ASME BPVC.XI-2017
2017 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-2015
2015 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-2013
2013 ASME Boiler and Pressure Vessel Code (BPVC), Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-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 BPVC-XI-2007
2007 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components, Includes Addenda (2008 and 2009)- Historical Version
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ASME BPVC-XI-2004
2004 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-2001
2001 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-1998
1998 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-1995
1995 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-1992
1992 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-1989
1989 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-1986
1986 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version
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ASME BPVC-XI-1983
1983 ASME Boiler and Pressure Vessel Code, Section XI: Rules for Inservice Inspection of Nuclear Power Plant Components- Historical Version