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:
nces. The criteria in Section II, below, provide adequate and acceptable design solutions for the concerns outlined above. This position paper sets forth minimum requirements and does not prohibit the implementation of more rigorous design codes, standards, or quality assurance measures than those indicated. It also does not require a reevaluation of waste gas systems with limiting conditions for operation based on more conservative analysis and calculational assumptions. B. BRANCH TECHNICAL POSITION 1. Waste Gas System Leak or Failure Analysis A. Criteria The SAR (Section 11.3) should provide an analysis of the radiological consequences of a single failure of an active component in the waste gas system. The analysis should provide reasonable assurance that, in the event of a postulated failure or leak of the waste gas system, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 25 mSv (2.5 rem) for systems designed to withstand explosions and earthquakes, or 1 mSv (0.1 rem) for systems not designed to withstand explosions and earthquakes. The bases for the analysis should include the assumption that the waste gas system fails to meet its design intent as required by 10 CFR 50.34a(c) and GDC 60 of Appendix A to 10 CFR Part 50. B. Source Term The safety analysis on the radiological consequences of a single failure of an active component in the waste gas system should use a system design-basis source term for light-water-cooled nuclear power plants. The NRC staff method of calculation for this analysis is based on conservative assumptions to maximize the design capacity source term (sustained power operation). These assumptions are given below: i. For a PWR: 1 percent of the operating fission product inventory in the core being released to the primary coolant ii. For a BWR: A fission product release rate consistent with the noble gas release to the reactor coolant of 100 μCi/s per MWt (after 30-minute decay) The