Document: NRC Regulatory Guide
Document ID: c0dbb594-6262-4b83-96b1-366758ad9676
Document Type: regulatory_guide
Title: Interim Licensing policy on as low as Practicable for Gaseous Radiodine Releases from Light-Water-Cooled Nuclear Power Reactors (Rev. 1)
Source: NRC Regulatory Guide Division 1
Source URL: https://www.nrc.gov/docs/ML1229/ML12298A137.pdf
Revision Date: 2023-06
Chapter: 
Section ID: RG-1.42
CFR Part: 
CFR Title: 

Content:
t 3 P = storage pressure, atmospheres (absolute) n total number of storage tanks (n-2) = correction to subtract the tank being filled and the tank held in reserve 140 = average waste gas flow rate per reactor to the storage tanks, ft 3/day (STP) 12. Steam Generator Blowdown Rate - 0.06% of steam flow 13. Partition (PF) and Decontamination Factors (DF) for Radioiodine PF Steam Generator, Internal Partition a. Recirculating U-Tube 0.01 b. Once Through 1 Steam Generator Blowdown Tank Vent 0.05 DF Steam Generator Blowdown Tank Vent Separate Condenser* 100 Charcoal Adsorber 10 Main Condenser Air Ejector 2000 Internal Cleanup System (Kidney) ** 14. Decontamination Factors (DF) for Demineralizers Note: For two demineralizers in series, the DF for the second demineralizer is given in parentheses. *If the steam generator blowdown tank is vented to the turbine condenser, the source term is zero. **Assume the internal cleanup system will operate for 16 hours prior to purging at a DF of 10 for radioiodine and a mixing efficiency of 70%. 1.42-A3 0 DF (Anion) 10 Mixed Bed (Li 3 BO3 ) Mixed Bed (H OH-) Condensate Radwaste Cation Bed (H ) Anion Bed (OH-) Powdex (any system) Reverse Osmosis 10 2(10) 1(1) 10 2(10) 10(10) 1.5 per stage for all radionuclides 15. Decontamination Factors (DF) for Evaporators DF Miscellaneous Radwaste Evaporators Boric Acid Evaporators Separate Evaporator for Detergent Wastes 103 10 2 102 0 16. Flow Through Charcoal Delay System - Negligible release of iodine-131 (<10-4 Ci/yr). 17. Guidelines for Rounding Off Numerical Values in calculating the estimated annual release of radioactive materials in gaseous waste, round off all numerical values to two significant figures. B. Principal Parameters Used in BWR Source Term Calculations 1. Thermal Power Level - The maximum thermal power level (MWt) evaluated for safety considerations in the Safety Analysis Report. 2. Plant Capacity Factor - 80%. 0 1. 42-A4 3. Equilibrium Primary Coolant Radioiodine Concentration