Document: NUREG-0800
Document ID: 7024eeeb-1819-4d56-9b72-fb63eab3836b
Document Type: srp
Title: and 3.9.3.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1006/ML100620981.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
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. 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 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: 3.8.3-15 Revision 3 - May 2010 Code, Standard, or Specification Title ACI 349 Code Requirements for Nuclear Safety-Related Concrete Structures (supplemented with additional guidance by RGs 1.142 and 1.199) ASME Code Section III, Division 2, Subsection CC, ACode for Concrete Reactor Vessels and Containments@ ASME Code Section III, Division 1, Subsection NE, AClass MC Components@ ANSI/AISC N690-1994 Specification for the Design, Fabrication and including Supplement 2 (2004) Erection of Steel Safety-Related Structures for Nuclear Facilities Regulatory Guides 1.57 Design Limits and Loading Combinations for Metal