Document: NUREG-0800
Document ID: 2768345e-44b7-48d8-bfa7-69652aa4faa8
Document Type: srp
Title: CONCRETE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1319/ML13198A245.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
mbinations and acceptance criteria acceptable to the staff to demonstrate that the containment structural integrity is maintained under these loads. RGs 1.7, 1.136 and 1.216 are referenced for further guidance on the analytical technique, loading combination, and acceptance criteria. Meeting these criteria provides reasonable assurance that the containment will be able to withstand loads from the sources specified above and will perform its intended safety function as required by 10 CFR 50.44 . 9. Compliance with 10 CFR 50.55a requires that (1) SSCs be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of the safety function to be performed; (2) containments, systems, and components of BWRs and PWRs meet the requirements of the ASME Code; and (3) RG 1.84 and 1.147, lists NRC approved ASME Code cases that may be applied to design, fabrication, erection, construction, testing and inspection of containments, systems, and components. Compliance with 10 CFR 50.55a also requires that reinforced and prestressed concrete containments, and the metal components of concrete containments be examined in accordance with the requirements of Section XI, Subsections IWL and IWE, of the ASME Code, and supplemental requirements specified in 10 CFR 50.55a(b)(2)(viii) and 10 CFR 50.55a(b)(2)(ix). These subsections of the ASME Code provide requirements for preservice examination and inservice inspection, acceptance criteria, and repair/replacement requirements. This SRP section provides review guidance to ensure that the requirements of 10 CFR 50.55a are appropriately addressed for concrete containments. Meeting these requirements provides assurance that the containment structure will perform its safety function to limit the release of radioactive material throughout its licensing period. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular