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:
ter a value of 0.02 for the "Holdup Time, in days, for Kr." (BWR or PWR-GALE Code) 11. 3-15 Rev. 0 - July 1981 (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 to account for the design capacity source term correction. 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) = I K, Q, (i7Q) (1012 pCi/Cl) (7.25 x 10-12 yr2/event-sec) where, Q = The noble gas nuclide release rate determined in steps 4 and 5, above, in curies/yr rate for 2 hrs. K1 = The total-body dose factor given as DFB in.Table 8-1 of Regulatory Guide 1.109, in mrem-m3/pti/yr. (i74) = The relative concentration at the nearest exclusion boundary given in Figure 1 of Regulatory Guide 1.24 for ground-level releases, in sec/m3 7) The.sum dose shall be less than 500 mrem. Using the same parameters, the technical specifications will set a maximum release rate to the waste gas system of 100 pCi/sec/HWt (after 30 min. decay) or use the value of Q (in pCi/sec) determined above, whichever is less, to asshre that the BTP criteria of 500 mrem individual exposure for 2 hrs at the nearest exclusion boundary is met. 11.3-16 Rev. 0 - July 1981