Document: NUREG-0800
Document ID: 23331bab-fa00-40fd-8357-d8db908b4532
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0707/ML070710366.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
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entation and design features to annunciate and prevent the buildup of potentially explosive mixtures, satisfies the requirements of GDC 3. Meeting the requirements of GDC 3 provides assurance that the GRS is protected from the effects of an explosive mixture of hydrogen and oxygen and that the safety functions of other SSCs will not be compromised. 11.3-11 Revision 3 - March 2007 5. Compliance with GDC 60 requires that design provisions be included in the nuclear power unit to control releases of radioactive materials in gaseous effluents to the environment during normal reactor operation, including anticipated operational occurrences. GDC 60 specifies that the radwaste processing systems provide for a holdup capacity sufficient to retain radioactive waste, particularly where unfavorable site environmental conditions may impose unusual operational limitations upon the release of effluents. The holdup capacity also provides time to allow shorter lived radionuclides to decay before they are further processed or released to the atmosphere. The holdup or decay times are used in source term calculations based on the methods described in NUREG-0016 or NUREG-0017 and Regulatory Guide 1.112. The review will evaluate the types and characteristics of filtration and adsorbent media proposed to treat gaseous process and effluent streams, including removal efficiencies and decontamination factors, taking into account the expected physical, chemical, and radiological properties of gaseous process and effluent streams. The review should determine whether performance meets or exceeds that noted in NRC guidance (Regulatory Guide 1.140 and NUREG-0016 or NUREG-0017), standard DCs, industry standards, or topical reports. Meeting the requirements of GDC 60 provides assurance that releases of radioactive materials in gaseous effluents to unrestricted areas during normal plant operation and anticipated operational occurrences will not result in offsite radiation doses exceeding the dose