Document: NUREG-0800
Document ID: 0c95c042-addf-4bad-84f5-1d1692769268
Document Type: srp
Title: CONCRETE AND STEEL INTERNAL STRUCTURES OF STEEL OR CONCRETE
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550052.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.8.3
CFR Part: 
CFR Title: 

Content:
or if an equivalent static analysis is performed using the peak of the jet load amplified by an appropriately chosen dynamic load factor. The design and analysis procedures for concrete weir walls are acceptable if found to be in accordance with conventional methods described in ACI 349, with additional guidance provided by RG 1.142 and 1.199, for concrete and anchors (steel embedments), respectively. 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 structural steel. The design and analysis procedures are acceptable 3.8.3-23 Revision 2 - March 2007 if found to be in accordance with conventional methods described in ACI 349, with additional guidance provided by RG 1.142 and 1.199, for concrete and anchors (steel embedments), respectively, and in ANSI/AISC N690-1994 including Supplement 2 (2004) for structural steel. iv. Supports for Reactor The 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 LOCA loads. The design and analysis procedures used for the reactor supports (beyond the jurisdictional boundary of the ASME-designed supports) are acceptable if found to be in accordance with the same criteria for concrete and steel that apply to the refueling pool and operating floor. v. Reactor Pedestal The reactor pedestal, which supports the reactor and must 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 used for the reactor