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:
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 radiological impacts during postulated accidents, as required in SRP Section 2.4.13, SRP 11.2 using BTP 11-6, SRP 11.3 using BTP 11-5, and the analysis of RG 1.143 in assigning safety classifications to RWMS for design purposes and compliance with GDC 61. 5. consider design features or processes that would affect the development of the radioactive source terms in recognition of calculation methods and assumptions 11.1-20 Revision 4 – January 2016 presented in NUREG-0016, NUREG-0017, and ANSI/ANS 18.1-1999, given differences between PWR and BWR plants. 6. provide a bounding assessment for ESP applications in demonstrating the capability to comply with the regulatory requirements of 10 CFR Part 20 and 10 CFR Part 50, Appendix I design objectives. II. ACCEPTANCE CRITERIA The acceptance criteria section was revised by providing clarification on methods used to derive radioactive source terms. The major revisions include: 1. Inclusion of revised staff guidance presented in: DC/COL-ISG-5, Interim Staff Guidance on NUREG-0800, SRP Section 11.1, “GALE86 Code for Calculation of Routine Radioactive Releases in Gaseous and Liquid Effluents to Support Design