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:
on 1.4 of Standard Review Plan Sections 3.8.1 and 3.8.2 for concrete and steel portions, respectively. ii. Weir Wall One of the major loads to which the weir wall may be subjected is a jet impingement load induced by a pipe rupture in a nearby recirculation loop. Under such a concentrated load, the weir wall should not deform to an extent that might impair or degrade the pressure-suppression performance. Accordingly, the proced- ures utilized to analyze the wall for such dynamic time-dependent loads are reviewed with particular emphasis on modeling techniques, assumptions on boundary conditions, and behavior under loads. iii. Refueling Pool and Operating Floor In the BWR Mark III containments reviewed recently, the refueling pool is continuously filled with water to provide biological shielding above the reactor. The operating floor, which may be supported on the walls of the refueling pool on one side an on the containment shell on the other side, is a combination of reinforced concrete and structural steel. The design and analysis procedures for the refueling pool and the operating floor are of the conventional type and are accordingly reviewed, with particular emphasis on the structural framing and behavior under loads. In cases where the floor beams are supported vertically on the containment shell, they should be laterally isolated to minimize interaction between the containment and its interior. iv. Concrete Supports for Reactor and Recirculation Pump The design and analysis procedures utilized for the reactor and recirculation pump supports are reviewed in a manner similar to that for PWR reactor and pump supports, as already described in this SRP section. v. Reactor Pedestal The reactor pedestal supports the reactor and has to withstand the loads transmitted through the reactor supports. It is thus subjected to most of the loads described in subsection I.3 of this SRP section and is designed and analyzed for all the applicable load combinations. 3.8.3-10