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CODES & STANDARDS ELECTRONIC TOOLS
 

Board on Nuclear Codes and Standards
C&S Charterslogo  
BNCS Research Evaluation Group (BNREG) Charter:

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BPV Committee on Construction of Nuclear Facility Components (III) Charter:
To develop, review, and maintain, for publication in Section III of the Boiler and Pressure Vessel Code, rules governing the construction of: Division 1 vessels, storage tanks, piping, pumps, valves, metal containments, supports, and core support structures; Division 2 concrete containment vessels with metallic liners; Division 3 storage and transportation containments and their internal support structures for spent fuel and high-level radioactive material and waste; Division 4 components for fusion devices; and Division 5 (high temperature reactors) vessels, storage tanks, piping, pumps, valves, supports, core support structures and nonmetallic core components for use in nuclear power plants and other nuclear facilities. Construction, as used in this charter, is an all-inclusive term that includes material, design, fabrication, installation, examination, testing, overpressure protection, inspection, stamping, and certification. These rules focus on assuring the pressure boundary integrity and the structural integrity, as applicable, of the component or item being constructed.

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BPV Committee on Nuclear Inservice Inspection (XI) Charter:
To develop, review, and maintain, for publication in Section XI of the Boiler and Pressure Vessel Code, requirements for protecting pressure integrity and structural integrity of structures, systems, and components (SSCs) that affect nuclear safety or reliability of nuclear facilities, such as nuclear power plants, nuclear isotope production facilities, nuclear research facilities, and radioactive material storage, transportation, or disposal facilities. The areas covered include Owner responsibilities; provisions for accessibility and reliability; examination and monitoring methods, techniques, and procedures; personnel qualifications; frequency of examination; evaluation and disposition of examination results; repair/replacement activities, and records.

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Committee on Board (NCS) Strategic Initiatives Charter:

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Joint Committee on Nuclear Risk Management (JCNRM) Charter:
To develop and maintain standards in the following subject areas: 1. At-Power Internal Hazards Levels 1, 2 and 3 2. Low Power/Shutdown Internal Hazards Levels 1, 2 and 3 3. External Hazards At-Power and Low Power/Shutdown (including Seismic) 4. Fire PRA At-Power and Low Power/Shutdown 5. Spent Fuel Pool PRA 6. Risk Management Independent Decision Making 7. Assessment of Aggregate Effects

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Standards Committee on Cranes for Nuclear Facilities Charter:
To develop, review, and maintain requirements andguidelines for the design, manufacture, shipment, storage prior to erection and use, erection, testing, and inspection of cranes in nuclear facilities.

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Standards Committee on Nuclear Air and Gas Treatment (CONAGT) Charter:
To develop, review, maintain, and coordinate codes and standards for design, fabrication, installation, testing, and inspection of equipment and systems used in air and gas treatment for nuclear facilities.

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Standards Committee on Nuclear Quality Assurance (NQA) Charter:

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Standards Committee on Operation and Maintenance of Nuclear Power Plants Charter:
To develop, review, maintain, and coordinate codes, standards, and guides applicable to the safe and reliable operation and maintenance of nuclear power plants.

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Standards Committee on Plant Systems Design (PSD) Charter:
To develop, review and maintain a technology neutral standard for design of plant systems for nuclear facilities, including power generation; fossil power generation facilities (e.g., coal, natural gas); oil refining; oil and natural gas production; petrochemical; chemical; and hazardous waste plants and facilities. This standard provides processes and procedures for organizations to: (a) conduct process hazard evaluations and analysis in the early stages of design that (1) advance as the design matures and (2) provide structure to the development of a quantitative risk assessment; (b) incorporate and integrate existing systems engineering design processes, practices and tools with traditional architect engineering design processes, practices and tools; and (c) incorporate and integrate risk informed probabilistic design processes, practices and tools with traditional deterministic design processes using reliability and availability targets. The focus of this standard is to provide requirements and guidance for design processes, practices and tools that will provide a means for organizations to develop safer and more efficient system, structure, and product designs with quantified safety levels.

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Standards Committee on Qualification of Mechanical Equipment Used in Nuclear Facilities (QME) Charter:
To develop and maintain codes and standards for the qualification of active mechanical equipment to be used in nuclear facilities. Qualification is the demonstration of the capability of the equipment to perform its specified function(s) over the expected range of and in service codes and standards.

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