Document: NUREG-0800
Document ID: a09b1666-b289-4ea9-9e8f-3ee5fbd5bf41
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1319/ML13198A250.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
res 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: 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 Subsection I of this SRP section, should be designed to resist various combinations of loadings, including normal operating loads, seismic loads, and LOCA and other pipe rupture accident loads. SRP Section 3.7.2 describes the analytical procedures for determining seismic loads. After the procedures for determining individual loads and combinations thereof are reviewed, the design and analysis methods used for the supports are considered, including the type of analysis, the methods of load transfer, and the assumptions of boundary conditions. ii. Primary Shield Wall and Reactor Cavity The primary shield wall should withstand all applicable loads, including those transmitted through the reactor supports. The wall is subjected to most of the loads described in Subsection I.3 of this SRP section and should be designed and analyzed for all applicable load combinations. During normal plant operation, the attenuation heat of gamma and neutron radiation originating from the reactor core generates a thermal gradient across the wall. Insulation and cooling systems may be provided to reduce the severity of this gradient by limiting the rise in temperature to an acceptable level. Procedures for determining seismic loads on the primary shield wall are reviewed in accordance with SRP Section 3.7.2. 3.8.3-9 Revision 4 – September 2013 LOCA loads applicable to the primary shield wall include a differential pressure created across the reactor cavity by a pipe break in the vicinity of the reactor nozzles. Such a transient pressure may act on the entire cavity or