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:
of eccentric masses (e.g., valve operators) in seismic system analyses are reviewed. J. Seismic Category I Buried Piping Systems. For Seismic Category I buried piping, the seismic criteria and methods which consider the effect of fill settlement, including pipe profile and pipe stresses, the movements at support points, penetrations, and anchors, are reviewed. K. Interaction of Other Piping With Seismic Category I Piping. The seismic analysis procedures to account for the seismic motion of non-Seismic Category I piping systems in the seismic design of Seismic Category I piping are reviewed. L. Criteria Used for Damping. The criteria to account for damping in systems, components, equipment and their supports are reviewed. 3. Analyses of dynamic responses of structural components within the reactor vessel caused by steady-state and operational flow transient conditions, including all fluctuating loading induced by flow, acoustic, or mechanical sources, are reviewed to confirm that they are consistent with the approach described in RG 1.20, “Comprehensive Vibration Assessment Program for Reactor Internals during Preoperational and Initial Startup Testing,” Revision 4. For example, reviews are conducted of analyses required for prototype, limited prototype, and nonprototype plants and components (such as steam dryers in boiling water reactor [BWR] nuclear power plants), and for operating plants requesting a power uprate, or replacing a reactor internal component. The breadth of analyses needed for prototype, limited prototype, and nonprototype plants and components depends on the type and complexity of the reactor internals, and their classification. For guidance on classification of SSCs as prototypes, limited prototypes, and nonprototypes, see Section C.1 of RG 1.20, 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