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:
rformance of RWMS in treating process streams and controlling amounts of radioactivity discharged in the environment. The technical rationale for the above considerations is discussed in the following paragraphs: 1. 10 CFR Part 50, Appendix I, provides numerical guides on offsite individual doses due to liquid and gaseous effluents and air doses (as beta and gamma absorbed dose rates) due to gaseous effluents. It also provides an acceptance criterion for cost-benefit analysis as it relates to population doses due to liquid and gaseous effluents (Section II.D of Appendix I.) Conformance with Section II.D of Appendix I demonstrates that the plant design includes all items of reasonably demonstrated technology that, when added to reactor makeup water storage in order of diminishing return, will effect a reduction in releases of radioactive materials and cumulative population doses to ALARA levels. Calculations using the PWR-GALE code or the BWR-GALE code and source term parameters, as given in NUREG-0017 or NUREG-0016, take into account current technology and the availability of equipment based on that technology to reduce radioactivity levels in liquid and gaseous process streams. The assumptions used in the calculations, based on the performance of such equipment, have an impact on design 11.1-11 Draft Revision 4 –August 2014 parameters used in modeling the performance of radwaste management systems reviewed in SRP Section 11.2 and SRP Section 11.3. If either code is modified to model specific design features, the modifications should be described in sufficient detail that they can be reviewed. If an alternate calculation model is proposed by the applicant, it should be described in sufficient detail, and the bases of all parameters used in the model should be described to allow the staff to conduct an independent evaluation. Meeting the coolant source term calculation criteria of SRP Section 11.1 provides reasonable assurance that the system designs reviewed in