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:
ormal 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 PlanSRP 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, 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 Review PlanSRP Section 3.7.2. Loss of coolant accidentLOCA loads that are applicable to the primary 25 shield wall include a different pressure created across the reactor cavity by a pipe break in the vicinity of the reactor nozzles. Such a transient 3.8.3-9 DRAFT Rev. 2 - April 1996 pressure may act on the entire cavity or on portions thereof. Procedures for determining such pressures are reviewed by the Containment Systems and Severe Accident Branch (SCSB).26 Other loss of coolant accidentLOCA loads that apply are those 27 transmitted to the wall through the reactor supports, including pipe rupture reaction forces which may induce simultaneous shear forces, torsional moments, and bending moments at the base of the wall. Further, the elevated