Document: NUREG-0800
Document ID: fabdf65c-d299-4b3a-a971-ae5b21a97177
Document Type: srp
Title: RADIATION SOURCES
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1315/ML13151A413.pdf
Revision Date: 2023-06
Chapter: 12
Section ID: 12.2
CFR Part: 
CFR Title: 

Content:
to safety for nuclear power plants.“ In addition, the quantities will be acceptable if the specific values given in the tables are consistent with ANSI/ANS Standard 18.1 and RG 1.112 for coolant and corrosion activation products source terms. For PWRs designed for the recycling of tritiated water, tritium concentrations in contained sources and airborne concentrations in the regions specified in item I.2 above should be based on a primary coolant concentration of 1.3 E+5 Bq/gm (3.5 μCi/gm). Technical Rationale The technical rationale for application of these acceptance criteria to the areas of review addressed by this SRP section is discussed in the following paragraphs: 12.2-10 Revision 4 – September 2013 1. Compliance with the referenced sections of 10 CFR Part 20 requires that the licensee control both occupational dose limits and dose limits to individual members of the public from radioactivity that may be received from both internal and external sources. The licensee must also maintain the security of licensed radioactive materials that are stored in controlled or unrestricted areas. 2. Compliance with the referenced sections of 10 CFR Part 50 requires that the licensee control the radiation exposure to required plant equipment, and to personnel required to enter important areas, following design bases events. 3. Compliance with 10 CFR 50.34(b)(3), 10 CFR 52.47(a)(5), 10 CFR 52.79(a)(3) and 10 CFR 52.157(e) ensures that the kinds and quantities of radioactive materials expected to be produced in the operation are described so that the means for controlling and limiting radiation exposures within the limits set forth in 10 CFR Part 20 can be identified. Collectively, meeting these acceptance criteria ensures that all of the sources of radiation exposure to workers and members of the public resulting from the licensed activities (normal operations and AOOs and to workers under accident conditions are identified, characterized, and considered in the design