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:
nts important to safety be designed, fabricated, erected, and tested to quality standards commensurate with the importance of their safety function, that a quality assurance program be established and implemented, and that sufficient and appropriate records be maintained. SRP Section 3.8.1 describes staff positions related to static and dynamic loadings and evaluation programs for concrete containments. It describes acceptable materials, design methodology, quality control procedures, construction methods, and inservice inspections as well as documentation criteria for design and construction controls at nuclear power plants. Meeting these criteria provides assurance that the engineering analysis and design of concrete containments for nuclear power plants will comply with 10 CFR Part 50 and that containments will perform their intended safety function. 2. Compliance with GDC 2 requires that systems, structures, and components important to safety be designed to withstand the effects of expected natural phenomena when combined with the effects of normal and accident conditions without loss of capability to perform their safety function. To ensure that the containment of a nuclear plant is designed to withstand natural phenomena, it is necessary to specify the most severe natural phenomena event that may occur as a function of the frequency of occurrence. To meet the requirements of GDC 2 for all natural phenomena related to meteorological events (e.g., earthquakes, snow and ice load, meteorological conditions affecting the ultimate heat sink, tornado parameters, and wind speed), it is necessary to review historical data and obtain the expected frequency of the most severe occurrences. These data are then used to specify the design requirements for nuclear plant components to be evaluated as part of construction permit (CP), OL, combined license (COL), or early site permit reviews or for site parameter envelopes in the case of design certifications, thereby ensuring