Document: NUREG-0800
Document ID: c0c5657a-82df-46c2-8cb5-fad0fd37fb58
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEMS1
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070610.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
nction, control error, or bed bypass would require the remedial action by isolation, and that starting an alternate charcoal unit, if available, or reducing reactor power could take up to 2 hours. The radioactive noble gas concentration should be determined 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 charcoal delay units during normal operation, including anticipated operational occurrences. To determine the releases without the charcoal delay unit, the staff method of calculation uses the BWR-GALE Code (NUREG-0016) and requires manual calculations to determine the radiological impact. Alterations to the PWR-GALE Code (NUREG-0017) are also included. 11.3-21 DRAFT Rev. 3 - April 1996 1) Enter a value of 0.02 for the "Holdup Time, in days, for Xe." (BWR- or PWR-GALE Code) 2) Enter a value of 0.02 for the "Holdup time, in days, for Kr." (BWR or PWR GALE Code) (This time, about 30 minutes, is considered for gases to travel through the components in the waste gas system via the release point to the nearest exclusion boundary.) 3) Rerun the computer program for this analysis only. 4) Multiply each noble gas printout given under "Air Ejector" by 7 0.002 MWE where MWE represents the reactor power level to account for the design capacity source term correction.103 5) Add to each noble gas value determined in step 4, above, the applicable value for the nuclide given in the source term for normal operation. This step will account for noble gases which have been delayed in the charcoal unit being released during the event. 6) Calculate the radiological impact by the following equation: Dose (mrem) = E K Q (X/Q)(10 pCi/Ci)(7.25 x 10 yr /event-sec) i i 12 -12 2 where, Q = The noble gas nuclide release rate determined in i steps 4 and 5, above, in curies/yr rate for 2 hrs. K = The total-body dose factor given as DFB in Table B-1 of i i Regulatory Guide