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:
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 analysis should assume principal parameters and conditions typical of the equipment designed to remove radioactive gases from the coolant and to process and treat these gases during normal operation, including anticipated operational occurrences, by the waste gas system. The NRC staff believes that no major alteration would occur in the use or performance of gas separation, reduction, and decay equipment before and immediately following this unique BTP 11-5-4 Revision 3 - March 2007 unplanned release affected by the waste gas system maximum design capacity source term. The source terms and releases may be developed using the BWR-GALE Code (NUREG-0016) or PWR-GALE Code (NUREG-0017) with appropriately justified adjustments made in modeling a specific type of event. C. Release The NRC staff considers that the release to the environment resulting from the postulated event will occur via a pathway not normally used for planned releases, and the release will require a reasonable time to detect and take remedial action to terminate the release. The NRC staff considers that the release of a compressed gas storage tank of a batch-type waste gas system or the inadvertent bypass of the main decay portion of a continuous-type waste gas system (such as charcoal delay beds in a BWR-augmented offgas system) will provide a conservative assumption for the release, while the input to the waste gas system is at the system design-basis source term. Only the radioactive noble gases (xenon and krypton) are to be considered since the assumed transit time is long enough to permit major radioactive decay of oxygen and nitrogen isotopes. Particulates and radioiodines are assumed to be removed by pretreatment, gas separation, and intermediate radwaste treatment equipment. The release should be