Document: NUREG-0800
Document ID: ed40908c-6d5d-42a3-bb9e-fcf4f68dd278
Document Type: srp
Title: FLOODING PROTECTION REQUIREMENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340554.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.10
CFR Part: 
CFR Title: 

Content:
o wave forces. We have independently evaluated the effects of the probable maximum surge stillwater elevation plus wind-generated waves on all seismic Category I structures and have concluded that the wave forces and wdve runup estimates used by the applicant are conservative and therefore meet the requirements of 10 CFR Part 50, §50.55a, GDC 2, and 10 CFR Part 100. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. Except in those cases in which the applicant proposes an acceptable alternative method for complying with specified portions of the Commission's regulations, the method described herein will be used by the staff in its evaluation of conformance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. ; VI. REFERENCES Other SRP sections in the 2.4 series provide hydrologic design basis flood levels and environmental condition descriptions. Reports of the Corps of Engineers, United States Geologic Survey, Bureau of Reclamation, National Oceanic and Atmospheric Administration, and others will be used on an "as available" basis to evaluate flood warning systems, if applicable. The references for accepta- bility of protection will be completed projects of the Corps of Engineers and other Federal, State, and local agencies, and similar types of protection previously reviewed and found acceptable for other nuclear plants. 2.4.10-4 Rev. 2 - July 1981 1. 10 CFR Part 50, §50.55a, "Codes and Standards." 2. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 3. 10 CFR Part 100, "Reactor Site Criteria." 4. Regulatory Guide 1.70, "Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants." 5. Regulatory Guide 1.59, "Design Basis Flood for Nuclear Power Plants." 6. Regulatory Guide