Document: NUREG-0800
Document ID: 65414bbc-012c-477d-8c25-466f94c1671f
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEMS
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0523/ML052350105.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
r Analysis a) Pressurized Storage Tanks: The safety analysis for the radio- logical consequences of a single failure of an active component in a waste gas system with compressed gas storage (holdup or decay) tanks or cover gas tanks assumes that the tank being filled has a major leak to the environs. The radioactive noble gas inventory in the tank, at 100% capacity, should be deter- mined based on the system design capacity source term using the parameters and principal components considered for pretreatment and collection of waste gas to the waste gas system tanks during normal operation, including anticipated operational occurrences. To determine the pressurized storage tank noble gas inventory, the staff method of calculation alters the PWR-GALE Code (NUREG-0017) and requires manual calculations to determine the radiological impact. 1) Enter a value of zero for the "Holdup Time, in days, for Xe." 2) Enter a value of zero for the "Holdup Time, in days, for Kr." 3) Check the value entered for "Fill Time, in days." This should be the average volume for all storage or cover gas tanks. If this is a cover gas system, calculate the effective fill time based on 20; of the liquid tank volumes. (Charcoal delay systems are not applicable.) The PWR-GALE Code limits the minimum fill time to 0.01 days. 4) Rerun the computer program for this analysis only. 5) Multiply each noble gas printout given under "Gas Stripping - Continuous" by 7 to account for the design capacity source term correction. 11.3-14 Rev. 0 - July 1981 6) Divide the values in step 5 above by the number of tanks filled per year (equal to 365/value in step 3 above). This gives to tank inventory Ai for each nuclide. 7) Calculate the radiological impact by the following equation: Dose (mrem) = I K1Ai (x7Q)(1012 pCi/Ci)/3.15x107 sec/year where, Ai = The noble gas nuclide activity determined in step 6 above, in curies/event. K1 = The total-body dose factor given as DFB1 in Table B-1 of Regulatory Guide 1.109, in