Document: NUREG-0800
Document ID: 06ca0ca1-d4e9-478b-ad5d-c52597a36b46
Document Type: srp
Title: COOLANT SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1305/ML13058A173.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
accuracy and adequacy of the guidance previously provided in SRP Section 11.1, Revision 3, dated March 2007. See ADAMS Accession No. ML070790010. The section’s title was revised to “Coolant Source Terms” in recognition that radiological considerations addressed in this SRP section focus on radioactivity that originates only from reactor fuel and migration in primary and secondary coolants and reactor steam. Editorial changes included adding new abbreviations in several places throughout this section and correcting grammatical errors. Other changes reflect the removal of redundant and repetitive information. Technical changes incorporated in this revision include: I. AREAS OF REVIEW The areas of review section was revised by expanding the discussions on the development of source terms and their use in SRP Section 3.11 and SRP Chapters 11, 12, and 15. The discussion distinguishes source terms as radioactive materials expected during normal operations and AOOs, and design basis source terms. The source terms are used to: 1. confirm that radioactive liquid and gaseous effluents meet the numerical design objectives and ALARA provisions of Appendix I to 10 CFR Part 50, and liquid and gaseous effluent concentration limits of 10 CFR Part 20, Appendix B, Table 2, Columns 1 and 2 and Note 4 at the point of release in unrestricted areas. 2. derive inventories of radioactivity in system components, assess the adequacy of shielding in maintaining doses to workers and public ALARA, define ambient radiation exposure levels and zones, and confirm the proper placement of radiation monitoring equipment in plant areas and operating conditions and the design of ventilation systems provided for maintaining doses to workers ALARA, consistent with 10 CFR Part 20 requirements. 3. assess equipment qualifications and model releases under design basis accident conditions for evaluation against reactor siting criteria and control room radiological habitability requirements. 4. assess the