Document: NRC Regulatory Guide
Document ID: 8b2255d1-47a9-4dfe-ba41-568c561a89ee
Document Type: regulatory_guide
Title: Inspection of Water-Control Structures Associated with Nuclear Power Plants + HISTORY – HISTORY 01/2015 – DG-1245 , Proposed Revision 2 (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1325/ML13255A435.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.127
CFR Part: 
CFR Title: 

Content:
TRODUCTION Purpose This regulatory guide (RG) describes a method that the staff of the U.S. Nuclear Regulatory Commission (NRC) considers acceptable for designing water control structures (e.g., dams, slopes, canals, reservoirs, and associated conveyance facilities) such that periodic inspections may be performed. In addition, this guide describes an acceptable inspection and monitoring program for water control structures. Water control structures include those used in the emergency cooling water system and those relied upon for flood protection. Applicable Regulations • General Design Criterion (GDC) 45, “Inspection of Cooling Water System,” of Appendix A, “General Design Criteria for Nuclear Power Plants,” to Title 10 of the Code of Federal Regulations, Part 50, “Domestic Licensing of Production and Utilization Facilities” (10 CFR Part 50) (Ref. 1), requires, in part, that the cooling water system be designed to permit the appropriate periodic inspection of important components to ensure the integrity and capability of the system. • In addition, 10 CFR 50.34(a)(4) and 50.34(b)(4) require, in part, each applicant for a nuclear power plant construction permit or operating license to provide an analysis and evaluation of the design and performance of structures, systems, and components (SSCs) of the facility for the purpose of assessing the risk to public health and safety resulting from the operation of the facility. Pre-Decisional DG-1245, Page 2 • Multiple sections of 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref. 2), including 10 CFR 52.47(a)(3), 52.79(a)(4), and 52.137(a)(3), state, in part, that the GDC in Appendix A to 10 CFR Part 50 establish the minimum requirements for the principal design criteria for water cooled nuclear power plants. The regulations at 10 CFR 52.79(a)(29) state, in part, that an application for a combined license must contain a final safety analysis report that includes