Document: NUREG-0800
Document ID: 3d313c6f-7766-49fb-8400-3b6dae97fe7d
Document Type: srp
Title: SPECIAL TOPICS FOR MECHANICAL COMPONENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340595.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.1
CFR Part: 
CFR Title: 

Content:
uct and operate nuclear power plants. These documents 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. 206 4. Description of the analysis methods which will be used if the applicant elects to use elastic-plastic stress analysis methods in the design of any of the above-noted components. II. ACCEPTANCE CRITERIA MEB acceptance criteria is based on meeting the relevant requirements of the following regulations: 1. General Design Criterion 1 as it relates to components important to safety being designed, fabricated, erected, constructed, tested and inspected in accordance with the requirements of applicable codes and standards commen- surate with the importance of the safety-function to be performed. 2. General Design Criterion 2 as it relates to safety-related mechanical com- ponents of systems being designed to withstand seismic events without loss of capability to perform their safety function. 3. General Design Criterion 14 as it relates to the reactor coolant pressure boundary being designed so as to have an extremely low probability of abnormal leakage, of rapidly propagating failure, and of gross rupture. 4. General Design Criterion 15 as it relates to the mechanical components of the reactor