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:
s not intended to prohibit the implementation of more rigorous design codes, standards, or quality assurance measures than those indicated nor reevaluate waste gas systems with limiting conditions for operation based on more conservative calculational assumptions. B. BRANCH TECHNICAL POSITION I. Waste Gas System Leak or Failure Analysis a) Criteria: The safety analysis report (Section 15.7.1) 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 unique unplanned release of radioactive gas from the waste gas system, the resulting total body exposure to an individual at the nearest exclusion area boundary will not exceed 0.5 rem. This is consistent with the guidelines of 10 CFR Part 20 and is substantially below the guidelines of 10 CFR Part 100. 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 Part 50, Section 50.34a(c), and Appendix A, GOC 60. b) Source Term: The safety analysis on the radiological conse- quences 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 a conservative 11.3-12 Rev. 0 - July 1981 assumption that the waste gas system maximum design capacity source term (sustained power operation) is 7 times greater than the source term considered for normal operation, including anticipated operational occurrences, as given in SRP Section 11.1. This assumption is in good agreement with previous design basis analysis which used: 1) For a PWR: 1% of the operating fission product inventory in the core being released to the primary coolant, or 2) For a BWR: A fission product release rate consistent with the noble gas release to the reactor coolant of 100 pCi/sec/