Document: NUREG-0800
Document ID: d0743544-9964-4f40-acba-386523f70c7f
Document Type: srp
Title: SPENT FUEL POOL AREA VENTILATION SYSTEM
Source: NUREG-0800
Source URL: https://www.nrc.gov/docs/ML0705/ML070550038.pdf
Revision Date: 2023-06
Chapter: 9
Section ID: 9.4.2
CFR Part: 
CFR Title: 

Content:
e shown that such sharing will not significantly impair their ability to perform safety functions, including, in the event of an accident in one unit, an orderly shutdown and cooldown of the remaining units. For the SFPAVS, GDC 5 requires that its component parts be essentially independent in order to ensure that an accident in one unit of a multiple-unit facility will not propagate to other units. Therefore the SFPAVS needs to be designed to accommodate loss of services from any one unit without affecting operation of the overall system. Meeting the GDC 5 requirements provide assurance that a failure or accident in one unit will not affect additional 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. During transfer or movement of spent fuel in the fuel storage pool, damage to the fuel cladding could result in potential releases of radioactive gases and aerosols to the atmosphere; thus, GDC 60 is applicable to spent fuel storage areas. Atmosphere cleanup systems are included in the SFPAVS design to reduce the quantities of radioactive materials in gaseous effluents released to the environment. RGs 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 GDC 60 requirements 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. 4. GDC 61 requires that the fuel storage and handling, radioactive waste, and other systems that may contain radioactive materials be designed to