Document: NUREG-0800
Document ID: f994604a-3360-4514-afe7-68461d4dfd34
Document Type: srp
Title: FLOODING PROTECTION REQUIREMENTS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070256.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.10
CFR Part: 
CFR Title: 

Content:
.10-7 DRAFT Rev. 3 - April 1996 V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regarding the NRC staff's plans for using this SRP section. This SRP section will be used by the staff when performing safety evaluations of license applications submitted by applicants pursuant to 10 CFR 50 or 10 CFR 52. Except in those 55 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. The provisions of this SRP section apply to reviews of applications docketed six months or more after the date of issuance of this SRP section.56 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 acceptability 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. 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 52, "Early Site Permits; Standard Design Certifications; and Combined Licenses for Nuclear Power Plants."57 4. 10 CFR Part 100, "Reactor Site Criteria." 5. Regulatory Guide 1.70, "Standard Format and Contents of Safety Analysis Reports for Nuclear Power Plants." 6. Regulatory Guide 1.59,