Document: NUREG-0800
Document ID: f48fc6fe-7c52-4612-b75c-034cedcfeb13
Document Type: srp
Title: STEEL CONTAINMENT
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070325.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.2
CFR Part: 
CFR Title: 

Content:
e of the safety function to be performed. This SRP section describes staff positions related to static and dynamic loadings and evaluation programs for steel containments. It also describes acceptable materials, design methodology, quality control procedures, construction methods, and inservice inspections and documentation criteria for design and construction controls. SRP Section 3.8.2 cites Regulatory Guide 1.57 to provide guidance that is acceptable to the staff regarding load combination equations. ASME Code Section III, Division 1, provides basic guidance for steel containments; code requirements impose specific restrictions to ensure that structures, systems, and components will perform their intended safety functions when designed in accordance with the Code Case provisions. Meeting these criteria provides assurance that steel containments used for nuclear power plants will be capable of performing their containment function to prevent or mitigate the spread of radioactive material. 2. Compliance with GDC 2 requires that structures important to safety be designed to withstand the effects of expected natural phenomena when combined with the effects of normal accident conditions without loss of capability to perform their safety function. To ensure that the containment of a nuclear power 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 DRAFT Rev. 2 - April 1996 3.8.2-18 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 design requirements of nuclear power plant components, including the containment, to be evaluated