Document: NUREG-0800
Document ID: 0c95c042-addf-4bad-84f5-1d1692769268
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550052.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and procedural measures proposed for its facility and the SRP acceptance criteria and evaluate how the proposed alternatives to the SRP acceptance criteria provide acceptable methods of compliance with the NRC regulations. 1. Description of the Internal Structures. The descriptive information in the safety analysis report (SAR) is considered acceptable if it meets the criteria set forth in Section 3.8.3.1 of RG 1.70 or 1.206. 3.8.3-16 Revision 2 - March 2007 During the application acceptance review, the reviewer identifies deficient areas of descriptive information and initiates a request for additional information. New or unique design features that are not specifically covered in RG 1.70 or RG 1.206 may require a more detailed review. The reviewer determines whether additional information is required to accomplish a meaningful review of the structural aspects of such new or unique features. RG 1.206 provides the basis for evaluating the description of structures to be included in a DC or a COL application. RG 1.70 provides guidance for information to be submitted with an application for construction permit (CP) or operating license (OL). 2. Applicable Codes, Standards, and Specifications. The design, materials, fabrication, erection, inspection, testing, and inservice surveillance, if any, of containment internal structures are covered by codes, standards, and guides that are applicable either in their entirety or in part. The following codes and guides are acceptable: Code, Standard, or Specification Title ACI 349 Code Requirements for Nuclear Safety-Related Concrete Structures (supplemented with additional guidance by RG 1.142 and 1.199) ASME Code Section III, Division 2, Subsection CC, “Code for Concrete Reactor Vessels and Containments” ASME Code Section III, Division 1, Subsection NE, “Class MC Components” ANSI/AISC N690-1994