Document: NUREG-0800
Document ID: ab4f353d-c299-479d-ab25-834f97196988
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070326.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
ent load induced by a pipe rupture in a nearby recirculation loop. The deflection of the wall under such a load must be limited so as not to impair the pressure-suppression performance. The procedures utilized to analyze the wall for such a dynamic time-dependent load are acceptable if a detailed time-history dynamic analysis is performed or if an equivalent static analysis is performed utilizing the peak of the jet load amplified by an appropriately chosen dynamic load factor. (iii)iii. Refueling Pool and Operating Floor The refueling pool and the operating floor, which may be supported on the walls of the refueling pool on one side and on the containment shell on the other side, are constructed of a combination of reinforced concrete and 109 structural steel. The design and analysis procedures are acceptable if found in accordance with conventional methods described in the ACI 349 Code for concrete and in the AISC N690 Specifications for 110 structural steel. (iv)iv. Concrete Supports for Reactor The linear support system for the reactor vessel, described in subsection I of this SRP section, should be designed to resist various combinations of loadings as indicated in subsection II.3 of this SRP section. Among the major loads that should be considered are normal operating loads, seismic loads, and loss-of-coolant accidentLOCA loads. 111 (v)v. Reactor Pedestal The reactor pedestal, which supports the reactor and has to withstand the loads transmitted through the reactor supports, should be subjected to most of the loads described in 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. subsection II.4.a.i.112 (vi)vi. Reactor Shield Wall This cylindrical wall, which surrounds the reactor and provides biological shielding, should be subjected