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.

Subsection NH addresses Class 1 components, parts, and appurtenances which are expected to function even when metal temperatures exceed those covered by the rules and stress limits of Subsection NB and Tables 2A, 2B, and 4 of Section II, Part D, Subpart 1.

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 system of a nuclear spent fuel or high level radioactive waste transport packaging.

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

Ordering Information:

Product-Certification Packages per "Designator":

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