Document: NUREG-0800
Document ID: dfd1fbdb-0dd1-46f4-8489-99de53d66afc
Document Type: srp
Title: OTHER SEISMIC CATEGORY I STRUCTURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550054.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.4
CFR Part: 
CFR Title: 

Content:
t the resulting structural designs provide for mutual independence of shared structures. Meeting this requirement provides added assurance that structures other than the containment and its associated components are capable of performing their required safety function even if they are shared by multiple nuclear power units. 6. Compliance with 10 CFR Part 50, Appendix B requires that applicants establish and maintain a quality assurance program for the design, construction, and operation of SSCs. This SRP section provides guidance specifically related to the design, construction, testing, and inservice surveillance of structural concrete and steel in nuclear power plants. Subsection II.2 of this SRP section cites ACI 349, with additional guidance provided by RG 1.142, ANSI/AISC N690-1994, including Supplement 2 (2004), and RG 1.127 and 1.160 to satisfy the requirements of 10 CFR Part 50, Appendix B. Meeting these requirements provides added assurance that structures covered in this SRP section will meet the requirements of 10 CFR Part 50, Appendix B and thus perform their intended safety function. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. 3.8.4-15 Revision 2 - March 2007 These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. 1. Description of the Structures. After the type of structure and its functional characteristics are identified, the staff obtains information on similar and previously licensed plants for reference. Such information, which is available in SARs and amendments of previous license applications, enables identification of differences for the case under review. These differences require additional