Document: NUREG-0800
Document ID: 36b6a414-c2ba-46ab-ae85-e214a0f457fa
Document Type: srp
Title: COOLANT SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1502/ML15029A022.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
f GDC 60 provides reasonable assurance that releases of radioactive materials, during normal operation and AOOs of radwaste processing systems, will not result in offsite radiation doses exceeding the numerical design objectives specified in 10 CFR Part 50, Appendix I, and effluent concentration limits for unrestricted areas specified in 10 CFR Part 20 (Appendix B, Table 2, Columns 1 and 2) and Note 4 for mixtures of radionuclides. 3. GDC 61 requires that the facility design include shielding used for the safe storage and handling of radioactive materials, and other systems containing radioactivity, for the purpose of assessing radiological safety under normal operations and postulated accident conditions. Inventories of the amounts of radioactive materials contained in RWMS must be determined for the purpose of assessing whether the design of RWMS assures 11.1-12 Revision 4 – January 2016 radiological safety under normal operations and postulated accident conditions. NUREG-0016, NUREG-0017, or ANSI/ANS 18.1-1999 describe acceptable methods in determining the inventories of radioactive materials in RWMS components during normal operations, which could be modified to develop source terms for postulated accidents. Meeting this requirement of GDC 61 provides reasonable assurance that the necessary information is available to identify the amounts of radioactive materials contained in RWMS and assess the radiological impacts during postulated accidents. Acceptable NRC guidance and methods are described in SRP Sections 2.4.13, “Accidental Releases of Radioactive Liquid Effluents in Ground and Surface Waters;” SRP 11.2 using Branch Technical Position (BTP) 11-6, “Postulated Radioactive Releases Due to Liquid-containing Tank Failures;” SRP 11.3 using BTP 11-5, “Postulated Radioactive Releases Due to a Waste Gas System Leak or Failure,” (Former Section 11.3 BTP has been separated into individual sections), and the analysis of RG 1.143, “Design Guidance for