Document: NUREG-0800
Document ID: 223f4b43-406b-4b45-903d-f3f8e31d0b7a
Document Type: srp
Title: POTENTIAL DAM FAILURES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070730417.pdf
Revision Date: 2023-06
Chapter: 2
Section ID: 2.4.4
CFR Part: 
CFR Title: 

Content:
ifies the level of conservatism that should be used to assess the severity of the flood for the purpose of determining the design bases for SSC important to safety. For applications pursuant to 10 CFR Part 52, meeting the applicable requirements of 10 CFR 52.17 and 10 CFR 52.79 that correspond to GDC 2 provides a level of assurance that the most severe hydrologic site characteristics have been identified; whether GDC 2 is met with respect to the adequacy of the associated design bases will be evaluated pursuant to other SRP sections. 2.4.4-6 Revision 3 - March 2007 2. 10 CFR 100.23(d) and Appendix A to 10 CFR Part 100 require that geologic and seismic factors include a determination of site suitability and acceptability of the nuclear power plant design. Paragraph IV(c) in Appendix A describes the investigation required to obtain geologic and seismic data for evaluating seismically induced floods, including failure of an upstream dam during an earthquake. These requirements are applicable to SRP Section 2.4.4 because it requires investigation of seismically induced floods or low water levels that guide the Commission in its consideration of the suitability of proposed sites for nuclear power plants. More detailed guidance on the investigation of seismically induced floods is provided by Regulatory Guide 1.70 and ANSI/ANS-2.8-1992, including results for seismically induced dam failures and antecedent flood flows coincident with the flood peak. Meeting this requirement provides a level of assurance that SSC important to safety have been designed to withstand the effects of floods induced by seismic failure of upstream or downstream dams. 3. Sections 100.10(c) and 100.20(c) of 10 CFR Part 100 require that the site’s physical characteristics (including seismology, meteorology, geology, and hydrology) be taken into account when determining its acceptability for a nuclear power reactor. 10 CFR Part 100 is applicable to SRP Section 2.4.4 because it addresses the physical