Document: NUREG-0800
Document ID: b4185506-3cba-4a2e-8cc2-3651202e2606
Document Type: srp
Title: SPENT FUEL POOL AREA VENTILATION SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0520/ML052070541.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.4.2
CFR Part: 
CFR Title: 

Content:
S to reduce the quantities of radioactive materials in gaseous effluents released to the environment. Regulatory Guides 1.140 and 1.52 offer 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 atmosphere cleanup systems in light-water-cooled nuclear power plants. Meeting the requirements of GDC 60 provides assurance that the 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.47 4. Compliance with GDC 61 requires that the fuel storage and handling, radioactive waste, and other systems that may contain radioactive materials be designed to ensure adequate safety under normal and postulated accident conditions. This criterion specifies that such facilities be designed to include appropriate containment, confinement, and filtering systems. Because it is necessary to move spent fuel within the spent fuel pool, and because damage to the fuel cladding could result in potential releases of radioactive gases and aerosols to the atmosphere, the SFPAVS design must include provisions for isolating the normal ventilation system and actuating the emergency filtration and adsorption system before radioactive airborne particles and gases reach the ventilation exhaust ducts. Guidance on the acceptable design of such systems is provided by Regulatory Guide 1.13, Position C.4, and Regulatory Guide 1.25 (which is referenced in Position C.4.) Meeting the requirements of GDC 61 provides assurance that releases of radioactive materials during normal operation, anticipated operational occurrences, and postulated accidents will not result in radiation doses in excess of the limits specified in 10 CFR Part 20.48 9.4.2-7 DRAFT Rev. 3 - April 1996 III. REVIEW PROCEDURES The procedures below are used during the construction permit (CP) or