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:
aximize the 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: These assumptions are given below:98 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 µCI/sec/MWt (after 30 min. decay). The analysis should assume principle parameters and conditions typical of the equipment designed to remove radioactive gases from the coolant and process and treat these gases during normal operation, including anticipated operational occurrences by the waste gas system. The NRC staff considers that there would be no major alteration in the use or performance of gas separation, reduction, and decay equipment prior to and immediately following this unique unplanned release affected by the waste gas system maximum design capacity source term. c) Release: The safety analysis on the radiological consequences of a single failure of an active component in the waste gas system involves a release method having the consequence of being a unique unplanned release. Such releases are less frequent than those considered by anticipated operational occurrences and cannot be included in a meaningful annual average for routine releases applicable to plant effluents in 10 CFR Part 50, Appendix I. At the same time, the radiological impact due to such a unique unplanned release has the characteristics of an accident and is important to the health and safety of workers and the public. Waste gas systems designed to acceptance criteria of SRP Section 11.3 have low probability of passive failure, excluding events required by the guidelines of 10 CFR Part 100. All principal release points are to be