Document: NRC Regulatory Guide
Document ID: de79d411-4fc9-456e-a5a0-f4a910ca4c9a
Document Type: regulatory_guide
Title: Assumptions Used for Evaluating a Control Rod Ejection Accident for Pressurized Water Reactors (Rev. 2)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML2111/ML21119A157.pdf
Revision Date: 2023-05
Chapter: 
Section ID: RG-1.77
CFR Part: 
CFR Title: 

Content:
y concerns involving use or storage of hazardous or toxic chemicals. Applicable Regulations • The GDC in Appendix A to 10 CFR Part 50 establish minimum requirements for the principal design criteria for water-cooled nuclear power plants. o GDC 19 requires that a CR be provided from which actions can be taken to operate the nuclear power unit safely under normal conditions and to maintain it in a safe condition under accident conditions. o GDC 4, “Environmental and Dynamic Effects Design Bases,” requires, in part, that, like the CR, structures, systems, and components important to safety be designed to accommodate the effects of and to be compatible with normal operation, maintenance, testing, and postulated accidents. • 10 CFR Part 50 provides regulations for licensing production and utilization facilities. o 10 CFR 50.34(3)(i) requires that an applicant for a water-cooled nuclear power plant establish the minimum principle design criteria as specified in the GDC in Appendix A of 10 CFR Part 50. • 10 CFR Part 52 governs the issuance of early site permits, standard design certifications, combined licenses, standard design approvals, and manufacturing licenses for nuclear power facilities. The guidance in this RG is intended for standard design certifications and combined license applicants under 10 CFR Part 52. o Section 52.47(a)(3)(i) requires an applicant for a design certification to include the facility’s principle design criteria, the minimum requirements for which are in Appendix A of 10 CFR Part 50. o Section 52.79(a)(4)(i) requires an applicant for a combined license to include the facility’s principle design criteria, the minimum requirements for which are in Appendix A of 10 CFR Part 50. • 10 CFR Part 20, “Standards for Protection against Radiation,” Subpart H, “Respiratory Protection and Controls to Restrict Internal Exposure in Restricted Areas” (Ref. 4) establishes requirements to mitigate the intake of chemicals and radionuclides