Document: NUREG-0800
Document ID: 615ce987-401a-49b0-a317-08e4662db9df
Document Type: srp
Title: AUXILIARY AND RADWASTE AREA VENTILATION SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550039.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.4.3
CFR Part: 
CFR Title: 

Content:
the ARAVS for each unit should be designed to accommodate the load resulting from accident conditions. At the same time, the operating environment of equipment associated with unaffected units must be maintained within specified limits. Meeting the GDC 5 requirements provides assurance that a failure or accident in one unit will not affect other units of a multiple-unit site. 3. GDC 60 requires provisions to be included in the nuclear power unit design to ensure suitable controls on the release of radioactive materials in gaseous effluents during normal reactor operation, including anticipated operational occurrences. GDC 60 requirements apply to the design of the ARAVS because its function is to control the quantities of radioactive materials in gaseous effluents released to the environment from normal ventilation systems. RGs 1.140 and 1.52 provide design, testing, and maintenance criteria acceptable to the staff for air filtration and adsorption units of normal ventilation exhaust systems and for engineered safety-feature atmospheric cleanup systems in light-water-cooled nuclear power plants. Meeting the GDC 60 requirements provides assurance that release of radioactive materials entrained in gaseous effluents will not exceed the limits specified in 10 CFR Part 20 for normal operation and anticipated operational occurrences. III. REVIEW PROCEDURES The reviewer will select material from the procedures described below, as may be appropriate for a particular case. These review procedures are based on the identified SRP acceptance criteria. For deviations from these acceptance criteria, the staff should review the applicant’s evaluation of how the proposed alternatives provide an acceptable method of complying with the relevant NRC requirements identified in Subsection II. The procedures are used during the construction permit or standard DC review to determine that the design criteria and bases and the preliminary design, as set forth in the preliminary SAR, meet