Document: NUREG-0800
Document ID: faf774de-7226-41f8-ba11-7cf612907af6
Document Type: srp
Title: GASEOUS WASTE MANAGEMENT SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML1306/ML13065A119.pdf
Revision Date: 2023-06
Chapter: 11
Section ID: 11.3
CFR Part: 
CFR Title: 

Content:
component, nor may it prevent the safe shutdown of the plant. However, the failure of specific systems or components may have some impacts on the means to treat, control, and monitor gaseous effluent releases and compliance with Title 10 of the Code of Federal Regulations (10 CFR) Part 20 regulations in controlling gaseous effluent releases to unrestricted areas and doses to members of the public. The GWMS is relied on to control releases of radioactive materials in gaseous effluents to the environment; therefore it has a direct impact in complying with 10 CFR Part 20 regulations. As such, the review of the GWMS must be sufficient to assure that the staff has reasonable assurance that public health and safety is adequately protected. The applicant's Final Safety Analysis Report (FSAR) must provide sufficient information to confirm that any failure of essential systems will not compromise public health and safety under NRC regulations. The review of the GWMS includes the design, design objectives, design criteria, methods of treatment, system interfaces, bypass routes to nonradioactive systems, expected releases, components to terminate or divert effluent releases, and methods and principal parameters used in deriving effluent source terms and releases of radioactive materials (as noble gases, radioiodines, tritium, carbon-14, and particulates). The review includes system piping and instrumentation diagrams (P&IDs), process flow diagrams showing methods of operation that influence waste treatment, and any additional equipment necessary to route effluents to the point of discharge, such as plant stacks and building exhaust vents. SRP Section 12.3-12.4, 11.3-3 Draft Revision 4 – August 2014 “Radiation Protection Design Features,” considers the presence of N-16 in assessing doses from external radiation from the turbine buildings of BWR plants. The specific areas of review include the following topics: 1. Equipment and ventilation system design capacities,