Document: NUREG-0800
Document ID: 81a2e18b-7311-4c4e-822e-8dfe1b0ba7aa
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230009.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
the reactor internals in this SRP section). 2. Control rod drive elements (the drive elements inside the guide tubes are covered in SRP Section 3.9.4, but the guide tubes are reviewed with the reactor internals in this SRP section). 3. In-core instrumentation (in-core instrumentation support structures are reviewed with the reactor internals in this SRP section). The specific areas of review are as follow: 1. The physical or design arrangements of all reactor internals structures, components, assemblies, and systems, including the positioning and securing of such items within the RPV, the provision for axial and lateral retention and support of the internals assemblies and components, and the accommodation of dimensional changes due to thermal and other effects. 2. The basis for the design of the reactor internals, loading conditions of normal operation, anticipated operational occurrences, potential adverse flow effects of flow-excited vibrations and acoustic resonances, postulated accidents, and seismic events. All combinations of design and service loadings (e.g., operating differential pressure and thermal effects, potential adverse flow effects (flow-excited vibrations and acoustic resonances), seismic loads, and transient pressure loads of postulated LOCA) accounted for in design of the reactor internals should be listed. The distribution of the design and service loadings acting on the internal components and structures should be described. The analytical or experimental methods for determining the loading conditions and their validation should be described along with their random uncertainties and bias errors. Regulatory Guide RG 1.201 provides further details on the determination of loading conditions caused by adverse flow effects. 3. If computational methods (e.g., the finite element method) are used to determine stresses in the reactor internal components and structures, validation of the modeling procedures for the analyses should be presented. The