Document: NUREG-0800
Document ID: db9f5ff5-cad8-4af5-848b-a22889b3fb51
Document Type: srp
Title: describes the design acceptance criteria for waste gas systems (as part of the
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070730056.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
eral procedural steps should be used for this analysis: i. The radioactive noble gas inventory should be determined based on the maximum expected radioactive source term and the system design capacity using the parameters and principal components considered for pretreatment and collection of waste gas to the waste gas charcoal delay or decay beds during normal operation, including anticipated operational occurrences. The assumptions and parameters used in the analysis should be described and justified to include among others: a description of the event leading to the release, release pathway from the affected system and building to the environment, type of release, duration of the release, basis for the noble gas source term after 30-minute decay, assumed receptor location, atmospheric dispersion parameters, and any modifying factor specific to the event. ii. The radiological impact should be determined using the noble gas radionuclide inventory determined step 1 above, total-body dose factor listed as DFBi in Table B-1 of Regulatory Guide 1.109, in mrem-m3/pCi-yr, any modifying factor specific to the event, and the relative concentration (X/Q, in s/m3) at the nearest exclusion area boundary given in Figure 1 of Regulatory Guide 1.24 for ground-level releases. iii. The dose, summed over all radionuclides, shall not exceed 1 mSv (0.1 rem). Using the same parameters, a corresponding TS can be defined to set a maximum release rate to the waste gas system of 100 μCi/s per MWt (after 30-minute decay) or use the value of Qi (in μCi/s) as determined above. Using the lowest of these two values will assure that the BTP criteria are met for an exposure duration of 2 hours at the exclusion area boundary. BTP 11-5-6 Revision 3 - March 2007 C. REFERENCES 1. 10 CFR Part 50.34a, “Design Objective for Equipment to Control Releases of Radioactive Materials in Effluents—Nuclear Power Reactors.” 2. 10 CFR 50.36a, “Technical Specifications on Effluents from Nuclear Power