Document: NUREG-0800
Document ID: f689fb6d-4711-4972-b900-1b2001877b19
Document Type: srp
Title: TSUNAMI HAZARDS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1819/ML18190A200.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.6
CFR Part: 
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 the plant. The staff reviews information presented by an applicant for a construction permit (CP), operating license (OL), design certification (DC), early site permit (ESP), or combined license (COL) concerning hydrological setting of the site as it relates to those 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 reviewed taking into account the effects of the tsunami flood-causing mechanism by considering all plausible tsunamigenic sources to ensure that those SSCs important to safety can perform their intended functions. 2.4.6-2 Revision 4 - September 2018 In order to evaluate the applicant’s site characteristic flood, it is necessary for the staff to first determine that tsunami or tsunami-like waves1 are physically credible at the site, and that these waves produce consequential flooding2. If this flood-causing mechanism is considered to be credible at the site, then the staff should assure that the application includes a flood inundation map3 depicting the extent and elevation of the tsunami-based flood. In addition to a flood inundation map, the staff should confirm that the application provides information on the duration of the flooding event as well as any associated effects4. General Design Criterion (GDC) 2 of Appendix A (“General Design Criteria for Nuclear Power Plants”) to CFR Part 50 (“Domestic Licensing of Production And Utilization Facilities”) requires that nuclear power plant SSCs important to safety be