Document: NUREG-0800
Document ID: 6b7eddf4-f7ce-4821-9f11-e37070221e57
Document Type: srp
Title: DYNAMIC TESTING AND ANALYSIS OF SYSTEMS, STRUCTURES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1613/ML16133A418.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
Revision 4. For BWRs, the following reactor internals might be included in the dynamic analysis and reviewed by the staff. Those marked with an asterisk, such as the steam dryer, are nonsafety-related components; they do not perform a safety function but must retain their structural integrity to avoid the generation of loose parts that might adversely impact the capability of other plant equipment to perform their safety functions. · chimney* and partitions* · chimney head* and steam separator assembly* · steam dryer assembly* · feedwater spargers* · standby liquid control header and spargers and piping · RPV vent assembly · core plate · top guide · control rod drive housing and guide tube · orificed fuel support · jet pump and support · shroud and shroud support 3.9.2-5 Revision 4 – March 2017 · core plate and reactor pump differential pressure lines · in-core monitoring housing system/in-core guide tubes and stabilizers For pressurized water reactors (PWRs), the following reactor internals might be included in the dynamic analysis and reviewed by the staff: · Core barrel · Upper core support assembly · Lower core support assembly · Control rod guide assembly · In-core instrumentation guide tubes · Flow distribution device · Heavy reflector · Irradiation specimen baskets For small modular reactors (SMRs), the Comprehensive Vibration Assessment Program (CVAP) might address the following additional components because of their location inside the integral RPV module, even though some components might not be traditionally classified as reactor internals: · Core support structures · Reactor coolant/recirculation pumps (RRPs) · Riser · Steam generator · Pressurizer · Control rod drive mechanisms and supports · In-core instrumentation guide tubes · Feedwater lines Note that new reactor internals designs might include additional components not in the lists above that need to be evaluated. The purpose of the analyses is to assess the