Document: NUREG-0800
Document ID: 808cea66-69b8-4f91-9fb2-62b3b99bc87a
Document Type: srp
Title: NUREG-0800
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340579.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3
CFR Part: 
CFR Title: 

Content:
5) as augmented by Regulatory Guide 1.57 (Ref. 9). 4. Design and Analysis Procedures The design and analysis procedures utilized .for the containment internal structures are reviewed with emphasis on the extent of compliance with the applicable codes as indicated in subsection I.3 of this SRP section, including those applicable to the following areas: a. For 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 Section I of this SRP Section, should be designed to resist various combinations of loadings, including normal operating loads, seismic loads, and loss of coolant and other pipe rupture accident loads. Analytical procedures for determining seismic loads are as described in Standard Review Plan Section 3.7.3.. After the procedures for determining individual loads and combinations thereof are so reviewed, the design and analysis methods utilized for the supports are reviewed 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 the applicable loads including those transmitted through the reactor supports. It is subjected to most of the loads described in Subsection I.3 of this SRP section and should be designed and analyzed for all the applicable load combinations. During normal plant operation, RWhenever reference is made to ACI 349, it implies that the code is augmented by Regulatory Guide 1.142. 3.8.3-7 Rev. 1 - July 1981 a thermal gradient across the wall is generated by the attenuation heat of gamma and neutron radiation originating from the reactor core. 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 Standard