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:
ports, should be subjected to most of the loads described in 3.8.3-23 Rev. 1 - July 1981 subsection II.3 of this SRP section and should be designed for all applicable load combinations. The design and analysis. procedures are acceptable if found to be similar to those referenced for the primary shield wall of PWR containments in paragraph (i) under PWR dry containments. (vi) Reactor Shield Wall This cylindrical wall, which surrounds the reactor and provides biological shielding, should be subjected to most of the loads described in subsection 11.3 of this SRP section. In most cases, the wall is utilized to anchor most of the pipe restraints placed around the reactor coolant system piping. A pipe rupture in the vicinity of the reactor nozzles may pres- surize the space within the wall. The wall may be lined on both faces with steel plates which may constitute the major structural elements relied upon to resist the design loads. Similar to the reactor pedestal, the biological shield all is also subjected to dynamic loss-of-coolant accident loads and the same methods are, therefore, applicable and acceptable. (vii) Miscellaneous Platforms Platforms inside the drywell are usually of structural steel and their main structural function is to provide foundations for the pipe restraints inside the drywell. Platforms outside the drywell are usually combinations of steel and concrete. The analytical and design procedures for these platforms are acceptable if in accordance with the ACI 349 Code for rein- forced concrete, and with the AISC Specifications for structural steel. Of particular interest are the dynamic loads induced on these floors by pool swell during a LOCA. Computer programs used in the design and analysis of containment interior structure should be described and validated by any of the procedures described in subsection II.4.e of Standard Review Plan Section 3.8.1. d. Structural audit is conducted as described in Appendix B to SRP Section 3.8.4. e. Design report