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
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radiation monitoring equipment in plant areas. These uses are consistent with Title 10 of the Code of Federal Regulations (10 CFR) Part 20, Subparts G and H. The design basis source term represents a conservative characterization of primary and secondary coolant concentrations. The source term is based on a combination of assumptions of failed fuel fractions (e.g., 0.25 to 1 percent,) TS limits for halogens (I-131 dose equivalent) and noble gases (Xe-133 dose equivalent,) presence of activation and corrosion products, and steam generator TS limits on primary-to-secondary leakage. This information may be used, in part, to support the development of other source terms, such as source terms framing assumptions for design basis accidents, source terms used in evaluating radiation doses for equipment qualification, and source terms used as the basis for radiation protection measures for other materials stored in spent-fuel pools. For these specific applications, the requirements and guidance, and the staff’s evaluation process are addressed in SRP Sections 3.11, 12.2, and 15.0.3, “Design Basis Accident Radiological Consequences of Analyses for Advanced Light Water Reactors.” Guidance on how the results of the staff’s evaluation and acceptability of these source terms and associated system parameters are applied in their development is provided in SRP Section 3.11 for equipment qualifications, SRP Section 12.2 for radiation protection purposes and shielding design, and SRP Section 15.0.3 for design basis accidents. Reactor coolant and steam source terms for normal operation are based on operating experience of plants with similar types of fuels used in PWRs and BWRs. The normal operation source terms are used to assess the performance of RWMS and other systems under normal operating conditions (including AOOs). The design basis reactor coolant and steam source terms are used to assess equipment qualification and model releases under design basis accident