Document: NUREG-0800
Document ID: 694a6d46-6a73-4dcf-afa8-2ea3a4a0181a
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340641.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
ign of the reactor internals. c. The design bases for the mechanical design of the reactor vessel internals should be presented including allowable limits such as maximum allowable stresses; stability under dynamic loads; deflection, cycling, and fatigue limits; and core mechanical and thermal restraints (positioning and hold- down). Details of dynamic. analyses, input forcing functions, and response to loadings are discussed in SRP Section 3.9.2. d. Each combination of design and service loadings should be categorized with respect to the allowable design or service limits (defined in the ASME Code and SRP Section 3:9.5,.Reference 5 and 7), and the associated stress intensity or deformation limits should be stipulated. Design or service loadings should include safe shutdown earthquake (SSE) and operating basis earthquake (OBE) loads as appropriate. In addition, the 14EB will coordinate other branches' evaluations that interface with the overall review of the reactor internals as follows: The Core Performance Branch (CPB) will verify fuel system design, including fuel behavior effects to reactor core design under various normal and accident operating conditions in SRP Section 4.2. The Materials Engineering Branch. (MTEB) will review material aspects of reactor internals in SRP Section 4.5.2. For those areas of review identified above as part of the primary review respon- sibility of other branches, the acceptance criteria necessary for the review and their methods of application are contained in the referenced SRP section of the corresponding primary branch. II. ACCEPTANCE CRITERIA MEB acceptance criteria are based on meeting the requirements of the following regulations: 1. General Design Criterion 1 and 10 CFR Part 50, §50.55a, as it relates to reactor internals, requires that the reactor internals shall be designed to quality standards commensurate with the importance of the safety functions to be performed. 3.9.5-2 Rev. 2 - July 1981 2. General Design Criterion