Document: NUREG-0800
Document ID: 025e5140-015c-4e77-ad4f-ff52a81956fe
Document Type: srp
Title: WIND LOADING
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070570001.pdf
Revision Date: 2023-06
Chapter: 3
Section ID: 3.3.1
CFR Part: 
CFR Title: 

Content:
For a DC application, the review will also address COL action items and requirements and restrictions (e.g., interface requirements and site parameters). For a COL application referencing a DC, a COL applicant must address COL action items (referred to as COL license information in certain DCs) included in the referenced DC. Additionally, a COL applicant must address 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. The adequacy of the most severe regional and local meteorological data used to specify design wind load parameters for SSCs of the nuclear power plant that may be affected by weather phenomena is reviewed in accordance with SRP Sections 2.3.1 and 2.3.2. The specific acceptance criteria and review procedures are contained in the referenced SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. 10 CFR 50, Appendix A, GDC 2 requires that SSCs important to safety shall be designed to withstand the effects of natural phenomena such as earthqakes, tornados, hurricanes, floods, tsunami, and seiches without loss of capability to perform their safety functions as it relates to natural phenomena. The design bases for these SSCs shall reflect appropriate combinations of the effects of normal and accident conditions with the effects of the natural phenomena. 2. 10 CFR 52.47(b)(1), which requires that a DC application contain the proposed ITAAC that are necessary and sufficient to provide reasonable assurance that, if the inspections, tests, and analyses are performed and the acceptance criteria met, a plant that incorporates the design certification is built and will operate in accordance with the design certification, the provisions of the Atomic Energy Act, and the NRC's regulations; 3.3.1-3 Revision 3 - March 2007 3.