Section III — Rules for Construction of Nuclear Facility Components
Provides general requirements which address the material, design, fabrication, examination, testing and overpressure protection of the items specified within each respective Subsection, assuring their structural integrity.
Division 1, Subsection NCA
Subsection NCA, which is referenced by and is an integral part of Division 1, Subsections NB through NG, and Division 2 of Section III, covers quality assurance requirements, ASME product-certification marks, and authorized inspection for Class 1, 2, 3, MC, CS, and CC construction.
Division 1, Subsections NB, NF, APP
Subsection NB addresses items which are intended to conform to the requirements for Class 1 construction.
Subsection NF addresses supports which are intended to conform to the requirements for Classes 1, 2, 3, and MC construction.
Subsection APP contains appendices, both mandatory and non-mandatory for Section III, Division 1 (Subsection NCA through NG), Division 2 and Division 3, including a listing of design and design analysis methods and information, plus Data Report Forms. These appendices are referenced by, and are an integral part of, Subsection NCA through NG, Division 2 and Division 3.
Division 1, Subsections NC, ND
Subsection NC addresses items which are intended to conform to the requirements for Class 2 construction.
Subsection ND addresses items which are intended to conform to the requirements for Class 3 construction.
Other Subsections and Divisions
Subsection NE addresses items which are intended to conform to the requirements for Class MC construction.
Subsection NF addresses the supports which are intended to conform to the requirements for Classes 1, 2, 3, and MC construction.
Subsection NG addresses structures which are designed to provide direct support or restraint of the core (fuel & blanket assemblies) within the reactor pressure vessel.
Division 2 addresses concrete containment structures, pre-stressed or reinforced. These requirements are applicable only to those components that are designed to provide a pressure retaining or containing barrier.
Division 3 addresses the design and construction of the containment systems, including internal support structures, used for the transportation and/or storage of spent nuclear fuel and high-level radioactive material.
The all-new Division 5 provides construction rules for high-temperature reactors, including both high-temperature, gas-cooled reactors (HTGRs) and liquid-metal reactors (LMRs).
Referenced BPVC Sections
• BPVC-II-A, B, C, D — Section II, Materials, Parts A through D
• BPVC-V — Section V, Nondestructive Examination
• BPVC-IX — Section IX, Welding and Brazing Qualifications
• BPVC-XI — Section XI, Rules for Inservice Inspection of Nuclear Power Plant Components
Referenced ASME Standards
• 3 Standards from the B1 Series on screw threads
• 8 Standards from the B16 Series on pipe flanges and fittings
• 3 Standards from the B18 Series on hex bolts
• B36.10M — Welded and Seamless Wrought Steel Pipe
• B36.19M — Stainless Steel Pipe
• NQA-1 — Quality Assurance Program Requirements for Nuclear Facilities
• QAI-1 — Qualifications for Authorized Inspection

Resources for the Nuclear Industry
Related ASME Product Certifications:
• "N," "NA," "NPT," "NS" (N-Type Certificates of Authorization and Certificates of Accreditation)
• "NV" (Nuclear Safety and Pressure Relief Valves — includes BPVC-II-A, Section II, Part A, Ferrous Materials Specifications)
• "NV" (Nuclear Safety and Pressure Relief Valves — includes BPVC-II-B, Section II, Part B, Nonferrous Materials Specifications)
• "NV" (Nuclear Safety and Pressure Relief Valves — includes BPVC-II-D, Section II, Part D, Properties, Customary or Metric)
• "N3" (N-Type Certificates of Authorization and Certificates of Accreditation)

Section XI — Rules for Inservice Inspection of Nuclear Power Plant Components
Contains Division 1 and 3, in one volume, and provides rules for the examination, inservice testing and inspection, and repair and replacement of components and systems in light water cooled and liquid metal cooled nuclear power plants. Application of Section XI begins when the requirements of the "construction code" (e.g., Section III) have been satisfied.
Section XI constitutes requirements to maintain the nuclear power plant while in operation and to return the plant to service, following plant outages, and repair or replacement activities. These rules require a mandatory program of scheduled examinations, testing, and inspections to evidence adequate safety. The method of nondestructive examination to be used and flaw size characterization are also contained within this Section.
Referenced BPVC Sections
• BPVC-II-A, B, C, D — Section II, Materials, Parts A through D
• BPVC-III — Section III, Rules for Construction of Nuclear Facility Components:
• Subsection NCA, General Requirements for Division 1 and Division 2
• Subsection NB, Class 1 Components
• Subsection NC, Class 2 Component
• Subsection ND, Class 3 Components
• Subsection NE, Class MC Components
• Subsection NF, Supports
• Subsection NG, Core Support Structures
• Subsection NH, Class 1 Components in Elevated Temperature Service
• Appendices
• Division 2-Code for Concrete Containments
• Division 3-Containments for Transportation & Storage of Spent Nuclear Fuel and High Level Radioactive Material & Waste
• Division 5, High Temperature Reactors
• BPVC-V — Section V, Nondestructive Examination
• BPVC-VIII-1-2 — Section VIII, Pressure Vessels, Division 1 and Division 2
• BPVC-IX — Section IX, Welding and Brazing Qualifications
Referenced ASME Standards
• NQA-1 — Quality Assurance Requirements for Nuclear Facilities Applications (QA)
• QAI-1 — Qualifications for Authorized Inspection
• RA-S — Standard for Level 1 / Large Early Release Frequency Probabilistic Risk Assessment for Nuclear Power Plant Applications

Related ASME Product Certifications:
"QSC" (Quality Systems Certificates — Material Manufacturers, Material Suppliers) — contact ASME