Document: NUREG-0800
Document ID: c75a9de4-9927-49e4-b078-7f5dadd37acd
Document Type: srp
Title: DESIGN BASIS ACCIDENT RADIOLOGICAL CONSEQUENCE ANALYSES FOR
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0702/ML070230012.pdf
Revision Date: 2023-06
Chapter: 15
Section ID: 15.0.3
CFR Part: 
CFR Title: 

Content:
ulting From Spectrum of Postulated Piping Breaks Within the Reactor Coolant System Pressure Boundary” I. Section 15.7.4, “Radiological Consequences of Fuel Handling Accidents” J. Section 15.7.5, “Spent Fuel Cask Drop Accidents” The specific acceptance criteria and review procedures are contained in the reference SRP sections. II. ACCEPTANCE CRITERIA Requirements Acceptance criteria are based on meeting the relevant requirements of the following Commission regulations: 1. Section 50.34(a)(1) of 10 CFR Part 50, “Contents of applications; technical information,” as it relates to the evaluation and analysis of the offsite radiological consequences of postulated accidents with fission product release. 2. General Design Criterion (GDC) 19 of Appendix A to 10 CFR Part 50, “Control room,” as it relates to maintaining the control room in a safe condition under accident conditions by providing adequate protection against radiation. 3. Section 100.21 of 10 CFR Part 100, “Non-seismic siting criteria,” as it relates to the evaluation and analysis of the radiological consequences of postulated accidents for the type of facility to be located at the site in support of evaluating the site atmospheric dispersion characteristics. 4. Paragraph IV.E.8 of Appendix E, to 10 CFR Part 50, “Emergency Planning and Preparedness for Production and Utilization Facilities,” as it relates to adequate provisions for an onsite technical support center (TSC) from which effective direction can be given and effective control can be exercised during an emergency. SRP Acceptance Criteria Specific SRP acceptance criteria acceptable to meet the relevant requirements of the NRC’s regulations identified above are as follows for the review described in this SRP section. The SRP is not a substitute for the NRC’s regulations, and compliance with it is not required. However, an applicant is required to identify differences between the design features, analytical techniques, and