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:
d operate nuclear power plants. Thee documenta made avaiable to the public as pat of the Commisslon's policy to Inform the nuclear Indus" arnd the general public of regulatory procedures and pollcies. Standard review plans are not substitutes for regulatory guldes or the Commission's regultons 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 Piants. Not al sections of the Standard Format hav a corresponding review plan. Publishd sndard roview pla will be isd perlodaDy. as pproprate to accommodate comments end to eflt new Informa- tion and eeiene. Comments and suggestions for Improvement will be consdered and should be sent to the U.S. Nuclear Reguistory Commission Office of Nuclear Reactor Regulation. Washington. D.C. H The staff review includes the following specific areas: a. The physical or design arrangements of all reactor internals structures, components, assemblies, and systems should be presented, including the manner of positioning and 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 combina- tions of design and service loadings 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