Document: NUREG-0800
Document ID: 8160c1fd-7cef-4c93-8e12-456019f2cfd2
Document Type: srp
Title: FOUNDATIONS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1319/ML13198A267.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.5
CFR Part: 
CFR Title: 

Content:
f performing their required safety functions even if they are shared by multiple nuclear power units. 3.8.5-18 Revision 4 – September 2013 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, which also refers to SRP Section 3.8.4, provides guidance specifically related to the design, construction, testing, and inservice surveillance of structural concrete and steel used in nuclear power plants. Subsection II.2 of SRP Section 3.8.4 cites ACI 349, with additional guidance provided by RG 1.142, ANSI/AISC N690-1994 including Supplement 2 (2004), and RGs 1.127 and 1.160, to satisfy the requirements of Appendix B to 10 CFR Part 50. Meeting these requirements and criteria provides additional assurance that the foundations of structures other than containment covered in this SRP section will meet the requirements of Appendix B to 10 CFR Part 50 and thus perform their intended safety functions. III. REVIEW PROCEDURES 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. In accordance with 10 CFR 52.47(a)(8), (21) and (22), and 10 CFR 52.79(a)(17) and (20), for new reactor license applications submitted under 10 CFR Part 52, the applicant is required to (1) address the proposed technical resolution of unresolved safety issues and medium- and high-priority generic safety issues which are identified in the version of NUREG-0933 current on the date up to 6 months before the docket date of the application and which are technically relevant to the design; (2) demonstrate how the operating experience insights have been incorporated into the plant design; and, (3) provide information