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“To develop, review, and maintain, for publication in Section XI of the Boiler and Pressure Vessel Code, requirements for protecting pressure integrity of systems, structures and components (SSC) that affect reliability. It is applicable to all advanced design reactor technologies. RIM establishes requirements to determine credible degradation mechanisms that could lead to the failure of SSC and imposes Monitoring and NDE (MANDE) criteria to detect the onset of degradation mechanisms. It is a “technology neutral standard” that may be applied to any reactor technology, including light water cooled, gas cooled, liquid metal cooled as well as other advanced design nuclear power plants. Areas covered include defining the requirements and responsibilities for the following: - implementation of the RIM Program, - the RIM Expert Panel, - scope of the SSC to be included in the RIM Program, - developing Reliability Target values to be assigned to SSC, - MANDE methods, techniques, procedures, personnel qualifications, frequency of inspection, records and evaluation and disposition of MANDE results through performance demonstrated MANDE protocol, - continuously evaluating SSCs performance for onsets of degradation to maintain the reliability of in scope SSC, - repair/replacement activities, - procedures for analytical evaluation of plant operating events, and - The regular update of the RIM Program and MANDE parameters through gained operating experience as a continuous living program. RIM is applicable regardless of the Construction Code classification initially employed for a SSC and complete nuclear power plants that have met all the requirements of the Construction Code.”  

Officers Staff Contact
CHAIR A. Thomas Roberts III
SECRETARY Daniel Vetter
Daniel Miro-Quesada
The American Society of Mechanical Engineers
Two Park Avenue
New York, NY 10016
Phone: 1(212)591-7386
Fax: 1(212)591-8501
Associated Committee Pages
ASME/JSME Joint Working Group on RIM Processes and System Based Code
BPV XI Working Group on MANDE
Additional Committees
BPV Committee on Nuclear Inservice Inspection (XI)
Subgroup on Evaluation Standards (SGES)(SC XI)
Working Group on Flaw Evaluation (SGES) (SC XI)
Working Group on Operating Plant Criteria (SGES) (SC XI)
Working Group on Pipe Flaw Evaluation (SGES) (SC XI)
Subgroup on Nondestructive Examination (SGNDE) (SC XI)
Working Group on Personnel Qualification and Surface Visual and Eddy Current Examination (SGNDE) (SC XI)
Working Group on Procedure Qualification and Volumetric Examination (SGNDE) (SC XI)
Subgroup On Reliability and Integrity Management Program (BPV XI)
Subgroup on Repair/Replacement Activities (SGRRA) (SC XI)
Working Group on Design and Programs (SGRRA) (SC XI)
Working Group on Welding and Special Repair Processes (SGRRA) (SC XI)
Subgroup on Water-Cooled Systems (SGWCS)(SC XI)
Working Group on Containment (SGWCS) (SC XI)
Working Group on Inspection of Systems and Components (SGWCS) (SC XI)
Working Group on Pressure Testing (SGWCS)(SC XI)
Working Group on Risk-Informed Activities (SGWCS) (SC XI)
Special Working Group on Editing and Review (SC XI)
Working Group on General Requirements (SC XI)
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