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:
ocuments are made available to the. public as part of the Commission's policy to Inform the nuclear Industry and the general public of regulatory procedures and policies. Standard review plans are not substitutes for regulatory guides or the Commission's regulations and compliance with them Is not required. The standard review plan sections are keyed to the Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants. Not all sections of the Standard Format have a corresponding review plan. Published standard review plans will be revised periodIcally, as appropriate, to accommodate comments and to reflect new Informa- tion and experience. Comments and suggestions for improvement will be considered and should be sent to the U.S. Nuclear Regulatory Commission, Office of Nuclear Reactor Regulation, Washington, D.C. 21 . a. For PWR Dry Containment Internal Structures i. Concrete Supports for Reactor The PWR vessel should be supported and restrained to resist normal operating loads, seismic loads, and loads induced by postulated pipe rupture including the loss of coolant accident. The support and restraint system should limit the movement of the vessel to within allowable limits under the applicable combinations of loadings. The support system should nevertheless minimize resistance to the thermal movements expected during operation. With these functional requirements in mind, the general arrangement and principal features of the reactor vessel sup- ports are reviewed with emphasis on methods of transferring loads from the vessel to the support and eventually to the structure and its foundations. ii. Concrete Supports for Steam Generator Steam generators should be supported and restrained to resist normal operating loads, seismic loads, and loads induced by pipe rupture. The support system should prevent the rupture of the primary coolant pipes due to a postulated rupture in steam or feed water pipes and vice versa. The system should nevertheless