Document: NUREG-0800
Document ID: cb58882e-0e3d-4a21-bffc-b5cc5a9428f6
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070367.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
tures, components, assemblies, and systems should be presented , including the manner of positioning and 5 securing such items within the reactor pressure vessel, the manner of providing for axial and lateral retention and support of the internals assemblies and components, and the manner of accommodating dimensional changes due to thermal and other effects. b. The loading conditions that provide the basis for the design of the reactor internals to sustain normal operation, anticipated operational occurrences, postulated accidents, and seismic events should be specified . All combinations of design and service loadings 6 should be listed (e.g., operating pressure differences and thermal effects, seismic loads, and transient pressure loads associated with postulated loss-of-coolant accidents) that are accounted for in design 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 7 under dynamic loads; deflection, cycling, and fatigue limits; and core mechanical and thermal restraints (positioning and holddown). 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 8 the allowable design or service limits ([defined in the ASME Code (Reference 7) and 9 SRP Section 3.9.53 , Reference 5 and 7)] , and the associated stress intensity or 10 11 deformation limits should be stipulated . Design or service loadings should include safe 12 shutdown earthquake (SSE) and operating basis earthquake (OBE) loads as appropriate. 13 Review Interfaces EMEB also performs the following reviews under the SRP sections indicated:14 1. Evaluates the rupture locations, rupture loads, and dynamic effects associated with the postulated rupture of piping as part of its primary review responsibility for SRP