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:
tilizing the source term described in Item 3. As a result, the information needed for the staff to conduct its evaluation will require the review of several PSAR/FSAR sections to confirm the relevance and adequacy of the supporting information used by the applicant in developing source terms. This SRP section addresses the review of coolant source terms used to evaluate RWMS in pressurized water reactors (PWRs) and boiling water reactors (BWRs). The review does not address an evaluation of plant and process equipment, given the purpose and scope of SRP Sections 11.2 to 11.5, but does rely on plant operating characteristics and RWMS design parameters in calculating radionuclide concentrations in primary and secondary coolant and reactor steam. Similarly, this SRP section does not include a review on the generation of neutron-activated components, in-core neutron detectors, or spent-fuel. Two source terms are reviewed: radioactive materials expected during normal operations and AOOs, and design 11.1-3 Draft Revision 4 –August 2014 basis source terms. For the purpose of this SRP section, radionuclide concentrations in primary and secondary coolant and reactor steam are expected to be representative of operating experience and plant conditions over the life of the plant in estimating radioactivity levels in process and effluent streams. The resulting radionuclide concentrations are not intended to be used as the sole basis for the design of the plant and RWMS. The design basis coolant source term is used to derive inventories of radioactivity in system components, assess the adequacy of shielding in maintaining doses to workers and the public as low as reasonably achievable (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 Title 10 of the Code of