Document: NUREG-0800
Document ID: 5e3dbec9-a39f-4531-9eb9-705982190066
Document Type: srp
Title: REACTOR PRESSURE VESSEL INTERNALS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16134A059.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.5
CFR Part: 
CFR Title: 

Content:
ures, components, assemblies, and systems, are evaluated 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 reactor internals’ design loading conditions for normal operation, anticipated operational occurrences, potential adverse flow effects, postulated accidents, and seismic events are evaluated. All combinations of design and service loadings (e.g., operating differential pressure and thermal effects, adverse flow effects, seismic loads, and transient pressure loads of postulated LOCAs) addressed in the 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. The determination of loading conditions caused by flow-induced vibration (FIV) and acoustic resonance 3.9.5-3 Revision 4 – March 2017 (AR), acoustic-induced vibration (AIV), and mechanically-induced vibration (MIV) is reviewed as part of the application review using the guidance in SRP Section 3.9.2, “Dynamic Testing and Analysis of Systems, Structures, and Components.” The adequacy of the listed load combinations used in the design is reviewed as part of the application review using the guidance in SRP Section 3.9.3, “ASME Code Class 1, 2, and 3 Components, and Component Supports, and Core Support Structures.” 3. If computational methods (e.g., finite element methods) are used to determine stresses in the reactor internal components and structures, validation of the modeling procedures for the analyses should be presented along with bias errors and uncertainties. The validation may include