Document: NUREG-0800
Document ID: 496b5bd8-c9a2-4cf6-a703-e41c51e155ec
Document Type: srp
Title: CHANNEL MIGRATION OR DIVERSION
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1819/ML18190A201.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.9
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CFR Title: 

Content:
REVIEW RESPONSIBILITIES Primary - Organization responsible for the review of issues related to hydrology Secondary - None. I. AREAS OF REVIEW Chapter 2 of the Standard Review Plan (SRP) discusses the site characteristics that could affect the safe design and siting of a nuclear power plant. The staff reviews information presented by the applicant for a construction permit (CP), operating license (OL), design certification (DC), early site permit (ESP), or combined license (COL) concerning the hydrological setting of the site as they relate to structures, systems, and components (SSCs) important to safety. This SRP section applies to reviews performed for each of these types of applications. The staff’s review and findings are described in the appropriate section of the safety evaluation report (SER). In this section the site characteristic flood elevation is evaluated by staff taking into account the potential flooding effects due to the migration or diversion of some type of channel of flowing 2.4.9-2 Draft Revision 4 – September 2018 water, such as a stream or river, to ensure that SSCs important to safety can perform their intended safety functions. As used in this SRP, “channel migration” generally refers to the geomorphological process where a natural river channel laterally migrates across its floodplain. By contrast, “channel diversion” is the process in which the position of a natural river channel has been altered or diverted artificially by man. That safety function includes ensuring that the plant and its safety-related water supply systems will not be adversely affected by this particular flood-causing mechanism. General Design Criterion (GDC) 2 of Appendix A (“General Design Criteria for Nuclear Power Plants”) to 10 CFR Part 50 (“Domestic Licensing of Production And Utilization Facilities”) requires that nuclear power plant SSCs important to safety be designed to withstand the effects of natural phenomena such as earthquakes,