scope:

This Code provides minimum requirements for design and construction of nuclear safety-related concrete structures and structural members for nuclear facilities. Safety-related structures and structural members subject to this Code are those concrete structures that support, house, or protect nuclear safety class systems or component parts of nuclear safety class systems.

Specifically excluded from this Code are those structures covered by "Code for Concrete Containments," ASME Boiler and Pressure Vessel Code Section III, Division 2, and pertinent General Requirements (ACI 359).

This Code includes design and loading conditions that are unique to nuclear facilities, including shear design under biaxial tension conditions, consideration of thermal and seismic effects, and impact and impulsive loads.

For structural concrete, f_c′ shall not be less than 3000 psi, unless otherwise specified.

This Code shall govern in all matters pertaining to design and construction of reinforced concrete structures, as defined in 1.1.1, except wherever this Code is in conflict with the specific provisions of the authority having jurisdiction (AHJ).

Same as ACI 318-08.

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Same as ACI 318-08, except the last sentence "See also Section 22.1.3."

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Concrete on steel deck

Same as ACI 318-08.

This Code does not govern the design of structural concrete slabs cast on stay-in-place, composite steel form deck. Concrete used in the construction of such slabs shall be governed by Chapters 1 through 6 of this Code, where applicable. Portions of such slabs designed as reinforced concrete are governed by this Code.

Special provisions for earthquake resistance- Provisions of Chapter 21 shall be satisfied (see Section 21.1.1).

This Code, along with relevant sections of ACI 350, governs design and construction of tanks and reservoirs (non-lined) associated with safety-related nuclear structures.