Document: NUREG-0800
Document ID: 7c104096-d040-463a-a94b-a0af08ab3478
Document Type: srp
Title: DYNAMIC TESTING AND ANALYSIS OF SYSTEMS, STRUCTURES, AND
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230008.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.9.2
CFR Part: 
CFR Title: 

Content:
uctural components within the reactor vessel caused by steady-state and operational flow transient conditions should be analyzed for prototype (first of a design) reactors. Generally, this analysis is also required from licensees requesting a power uprate for an existing power plant or steam generator replacement in a pressurized-water reactor (PWR). However, it is not required for non-prototypes except that segments of an analysis (in particular, assessments of any potential adverse flow effects) may be necessary if there are deviations from the prototype internals design or operating conditions, or if the non-prototype is based on a conditional prototype which has experienced problems in the past due to adverse flow effects. If the reactor internal structures are a non-prototype design, reference should be made to the results of tests and analyses for the prototype reactor and a brief summary of the results should be given. A more detailed summary of results associated with assessing the potential of any adverse flow effects should also be given. Plant components, such as the steam dryer in a boiling water reactor (BWR) nuclear power plant, perform no safety functions 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. Therefore, the following structures in BWRs should also be included in the dynamic analysis : • Chimney head* and steam separator assembly* • Steam dryers assembly* • Feedwater spargers* • Standby liquid control header, spargers, and piping • Reactor pressure vessel (RPV) vent assembly • Sampling probes in feedwater, steam, and condensate systems (* denotes non-safety related components.) Similarly, for PWR nuclear power plants, the internal components of steam generators also must be included in the dynamic analysis. The purpose of this analysis is to assess the vibration behavior of the components,