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:
ic resin cleaning rinses, reverse osmosis reject streams, decontamination solutions, disposition of laboratory samples and rinses; plant sampling station drains; and detergent wastes. C. Liquid wastes (dissolved or entrained noble gases, radio-iodine, particulates, carbon-14, and tritium) consisting of steam generator blowdown discharges and releases from steam generator blowdown and blowdown treatment systems based on secondary coolant concentrations expected during normal operations, AOOs, and design basis accident conditions, or at default activity levels or steam generator leakage rates derived from TS for secondary coolant. Other sources of liquid wastes may include discharges from auxiliary steam systems where those systems interface with PWR main steam systems and could become contaminated following the rupture of steam generator tubes. D. In recognition of differences between and among PWR and BWR plants, the review will consider design features or processes that would affect the development of the radioactive source terms. Among other considerations, the review should address the production rate of tritium and operational features governing its inventory in primary and secondary coolant; radioactivity removal rates for U-tube and once-through steam generators; containment internal cleanup systems; waste gas input to pressurized holdup decay tanks, with and without charcoal beds; frequency and duration of containment purges; main 11.1-5 Draft Revision 4 –August 2014 condenser air ejector exhaust system; main condenser air in-leakage and mechanical vacuum pump; turbine gland sealing system; ratio of condensate demineralizer flow rate to steam flow rate; types and number of charcoal delay beds; and type of BWR condenser tubing alloy. While NUREG-0016, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from Boiling Water Reactors (BWRs),” NUREG-0017, “Calculation of Releases of Radioactive Materials in Gaseous and Liquid