Document: NUREG-0800
Document ID: 5887ec11-6ad2-46aa-be7f-d596fb3777b6
Document Type: srp
Title: CONCRETE CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070324.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.1
CFR Part: 
CFR Title: 

Content:
he internal compartments will be able to withstand loads resulting from pressure and temperature conditions and will perform their design safety function. 6. Compliance with 10 CFR 50.34 requires that plant designs (a) accommodate loadings associated with hydrogen generation equivalent to 100% metal-water reaction of the fuel cladding accompanied by hydrogen burning or the added pressure of inerting system actuation. At a minimum, 10 CFR 50.34(f)(3)(A)(1) requires that containment structures should be designed to withstand a combined dead load and internal pressure of 310 kPa (45 psig). These requirements have been incorporated into SRP Section 3.8.1 by means of the load combination equations provided in subsection II.5.b. Meeting these requirements provides assurance that the containment will be able to withstand loads from the sources specified above and will perform its intended safety function. 7. Compliance with 10 CFR 50.55(a) requires that structures, systems, and components be designed, fabricated, erected, constructed, tested, and inspected to quality standards commensurate with the importance of their safety function and that suitable optional Code Cases be applied to such structures, systems, and components. The SRP Section 3.8.1 cites Regulatory Guides 1.35, 1.35.1, 1.90, 1.94, 1.107, and 1.136, which provide guidance regarding construction, quality control, tests, and inspections that is acceptable to the staff. ASME Code Section III, Division 2, addresses concrete containments. The Code requirements impose specific restrictions to ensure that structures, systems, and components will perform their intended safety function. Meeting these requirements provides assurance that the containment structure will perform its safety function to limit the release of radioactive material. III. REVIEW PROCEDURES The reviewer selects and emphasizes material from the review procedures described below as may be appropriate for a particular case. 1. Description of the