Document: NUREG-0800
Document ID: 6d9458c8-25fc-47c7-8406-acd4365b1d3c
Document Type: srp
Title: CONTROL ROD DRIVE SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16133A472.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.4
CFR Part: 
CFR Title: 

Content:
nction. If applicable, fatigue assessments, primarily of connections between CRDS components, should be performed to ensure the assembly maintains integrity throughout the design life of the plant. If the applicant selects an experimental testing option in lieu of establishing a set of stress and deformation allowables, a detailed description of the testing program must be provided for review. The load combinations (which for CRDS internal to the vessel assembly include both static and all postulated alternating flow, acoustic, and mechanical loads, including those from other components throughout the reactor), design stress limits and allowable deformations criteria should be provided for review in the preliminary safety analysis report (PSAR). In the final safety analysis report (FSAR) for an operating license, or the final safety evaluation report (FSER) for design certification (DC) applications, the actual design should be compared with the design criteria and limits to demonstrate that the criteria and limits have not been exceeded. Loadings imposed during normal plant operation and startup and shutdown transients include but are not limited to pressure, deadweight, temperature effects, and anticipated operational occurrences. Loadings associated with specific seismic and other dynamic events (e.g., flow-induced vibration, flow-excited acoustic resonance, and mechanical tones from other components such as RRPs) are then combined with the above plant-type loads. For boiling water reactors (BWRs) only, the CRDS is reviewed to verify that the system is capable of withstanding adverse dynamic loads such as water hammer. The response to each set of combined loads has a selected stress or deformation limit. The selection of a specific limit is influenced by the probability of the 3.9.4-4 Revision 4 – March 2017 postulated event and the need to assure operation during and after the event. Details on the determination of loading conditions caused by adverse flow