Document: NUREG-0800
Document ID: 39169f01-cad7-4157-8b41-e77433086afc
Document Type: srp
Title: SOURCE TERMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070607.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.1
CFR Part: 
CFR Title: 

Content:
e processing systems and during anticipated transients will not result in offsite radiation doses exceeding the limits specified in 10 CFR Part 50, Appendix I, and the effluent concentration limits in unrestricted areas exceeding the limits specified in 10 CFR Part 20.15 III. REVIEW PROCEDURES The reviewer will select and emphasize material from this SRP section as may be appropriate for a particular case. 1. In the review of the mathematical models and parameters given in the SAR to calculate primary coolant concentrations, and of the leakage rates to the radioactive waste management systems, ETSB SPLB compares parameters and calculations given in the SAR with the models and parameters given in NUREG-0016 and NUREG-0017. If the SAR includes models or parameters to estimate reactor coolant concentrations and leakage rates that differ from these reports, the parameters and calculations used need to be substantiated. The preferred method of substantiation is by presentation of operating data from similar reactors. 2. ETSB The SPLB performs an independent calculation of the primary and secondary (PWR) coolant concentrations and of the release rates of radioactive materials using the GALE Computer Code, and the "Principal Parameters for Source Term Calculations" given in NUREG-0016 and NUREG-0017, and the information supplied by the applicant in accordance with Appendices A and B of Regulatory Guide 1.112. 3. In the calculation, ETSB the SPLB will use the applicant's values as given in the SAR for the following parameters: design core thermal power level, steam flow rate, coolant mass, and coolant purification rates. DRAFT Rev. 3 - April 1996 11.1-6 4. ETSB The SPLB will use the coolant concentrations, leakage rates, and effluent release rates calculated above as inputs for evaluation of the liquid waste system, under SRP Section 11.2, and the gaseous waste systems, under SRP Section 11.3, to determine if these systems meet the dose design objectives of Appendix I to 10