Document: NRC Regulatory Guide
Document ID: 5ec01b96-5209-446f-95b3-7342d73ba086
Document Type: regulatory_guide
Title: Design, Inspection, and Testing Criteria for Air Filtration and Adsorption Units of Post-Accident Engineered-Safety-Feature Atmosphere Cleanup Systems in Light-Water-Cooled Nuclear Power Plants + HISTORY - HISTORY 12/2011 – DG-1274 , Proposed Revision 4 10/2000 – DG-1102 , Proposed Revision 3 (Rev. 4)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1124/ML11244A045.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.52
CFR Part: 
CFR Title: 

Content:
tain radioactivity be designed to ensure adequate safety under normal and postulated accident conditions and that they be designed with appropriate containment, confinement, and filtering systems. GDC 19, “Control Room,” requires that adequate radiation protection be provided to permit access to and occupancy of the control DG-1274, Page 2 room under accident conditions and for the duration of the accident without personnel radiation exposures in excess of 5 rem to the whole body, or its equivalent to any part of the body, or 5 rem total effective dose equivalent (TEDE) for licensees that implement an alternative source term pursuant to 10 CFR 50.67 or applicants or licensees under 10 CFR Part 50 or 10 CFR Part 52, “Licenses, Certifications, and Approvals for Nuclear Power Plants” (Ref 2.) who apply after January 10, 1997. In 10 CFR Part 100, “Reactor Site Criteria,” (Ref 3) the NRC requires nuclear power plants to be sited so that radiological doses from normal and postulated accidents are kept acceptably low. A footnote to 10 CFR 100.11, “Determination of Exclusion Area, Low Population Zone, and Population Center Distance,” states that the fission product release assumed in the plant design should be based on a major accident involving substantial core damage with subsequent release of appreciable quantities of fission products. For applicants after January 10, 1997, the siting criteria in 10 CFR 100.21 refer to dose values in §50.34(a)(1), which are also are included in the technical information requirements for applications for early site permits, combined licenses, standard design certifications, standard design approvals, and manufacturing licenses in 10 CFR Part 52; all of which have similarly worded footnotes on the fission product release assumptions. According to 10 CFR 50.67, “Accident Source Term,” an application to revise a licensee’s current accident source term must contain an evaluation of the consequences of applicable DBAs