Document: NUREG-0800
Document ID: 0c95c042-addf-4bad-84f5-1d1692769268
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550052.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
duced by the safe-shutdown earthquake (SSE) specified for the plant site. E. Loads to be sustained during abnormal plant conditions. The design-basis LOCA is the most critical abnormal plant condition during which most of the containment internal structures have to perform their primary function. Ruptures of other high-energy pipes should also be considered. Time-dependent and dynamic loads induced by such accidents include elevated temperatures and differential pressures across compartments, jet impingement, impact forces associated with the postulated ruptures of piping, and loads applicable to some structures, such as drag forces in the PWR ice-condenser containment. In addition, for structures or structural components located in or above the suppression pools of BWR containments, the review should consider the applicable LOCA-related and SRV-related hydrodynamic loads manifested as jet loads and/or pressure loads. The appendix to SRP Section 3.8.1 further describes the loads associated with LOCAs. The various combinations of the above loads that are normally postulated and reviewed include construction loads, normal operating loads, normal operating loads with severe environmental loads, normal operating loads with extreme environmental loads, normal operating loads with abnormal loads, normal operating loads with severe environmental and abnormal loads, and normal operating loads with extreme environmental and abnormal loads. 4. Design and Analysis Procedures. The review evaluates the design and analysis procedures used for the containment internal structures, with an emphasis on the extent of compliance with the applicable codes as indicated in Subsection II.2 of this SRP. The review includes the design and analysis procedures applicable to the following areas: 3.8.3-8 Revision 2 - March 2007 A. PWR Dry Containment Internal Structures i. Concrete Supports for Reactor Coolant System The support system for the reactor vessel and steam generators, as described in