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:
pending on the details of the reactor internals FIV review. 8. COL Action Items and Certification Requirements and Restrictions. For a DC application, the staff reviewer verifies that the DC documents include the appropriate COL action items, and requirements and restrictions (e.g., interface requirements and site parameters). For a COL application referencing a DC, the staff reviewer determines whether the COL applicant has adequately addressed the COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, the staff reviewer also verifies that the COL applicant adequately addressed the requirements and restrictions (e.g., interface requirements and site parameters) included in the referenced DC). Review Interfaces Other SRP sections interface with this section as follows: 1. Some of the computer programs used in the analyses addressed in this SRP section are reviewed under SRP Section 3.9.1. Computer programs and modeling approaches used to calculate dynamic and stress responses of structures and systems at frequencies above those of seismic events are reviewed according to the acceptance criteria described in subsection II.3 of this SRP section. 2. The designs of ASME Code Class 1, 2, and 3 components, component supports, and core support structures related to load combinations and stress limits are reviewed under SRP Section 3.9.3. 3. The design of reactor vessel internal components is reviewed under SRP Section 3.9.5. 4. The seismic qualification testing of seismic Category I mechanical equipment is reviewed under SRP Section 3.10. 5. Verification that (i) the various flow modes to be used to conduct the vibration test of the reactor internals represent the steady-state and operational transient conditions anticipated for the reactor during its service, and (ii) an acceptable hydraulic analysis has determined the loads acting on the reactor coolant system (RCS) piping and the reactor internals is