Document: NUREG-0800
Document ID: a6b987fc-c417-44e5-83d7-01df25e2a4f5
Document Type: srp
Title: apply and are checked for consistency.
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052340551.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.11.6
CFR Part: 
CFR Title: 

Content:
ntake. The staff concludes that the plant meets the requirements of GDC 2 with respect to floods caused by channel diversions. This conclusion is based on the fact that the plant is well away from the path of any potential diversion of the A River and well above the level of any resultant flood. Based upon the above evaluation, we conclude that channel diversions. present no safety-related hazard to the plant and that the requirements to 10 CFR Part 100 relative to channel diversions have been met. V. IMPLEMENTATION The following is intended to provide guidance to applicants and licensees regard- ing 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 con- formance with Commission regulations. Implementation schedules for conformance to parts of the method discussed herein are contained in the referenced regulatory guides. VI. REFERENCES No specific publications can be cited for general use; however, site-specific publications and maps can be obtained from the United States Geologic Survey, Soil Conservation Service, National Oceanic and Atmospheric Administration, Corps of Engineers, and state and other agencies and organizations, to identify historical and.potential future channel diversions. 1. 10 CFR Part 50, Appendix A, General Design Criterion 2, "Design Bases for Protection Against Natural Phenomena." 2. 10 CFR Part 50, Appendix A, General Design Criterion 44, "Cooling Water." 3. 10 CFR Part 100, "Reactor Site Criteria." 4. Regulatory Guide 1.70, "Standard Format and Content of Safety Analysis Reports for Nuclear Power Plants." 5. Regulatory Guide 1.27, "Ultimate Heat Sink for Nuclear Power Plants." 2.4.9-3 Rev. 2 - July 1981