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10 CFR 50.71(e) - Maritime Administration - U.S. Department of ...

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Updated Final Safety Analysis Report - (STS-004-002)Figure 4-2Containment Inerting Schematic4.2.5 Containment Performance RequirementsNo leak rate tests on the pressure containment have been performed since final shutdown November8, 1970.4.3 Reactor Compartment (Secondary Containment)4.3.1 General DescriptionAs shown in Figures 4-3 and 4-4, the reactor compartment surrounds the containment vessel andforms a secondary containment around the pressure containment. The concrete, lead andpolyethylene form the secondary shield. The volume enclosed by the concrete is the lower reactorcompartment or secondary shield area. This shield is described in 5.3.2.The principal auxiliary system associated with this compartment is the reactor space ventilation(RSV) system. It was installed during the spring 1963 outage. The system consists <strong>of</strong> twophysically independent sections. One section was for heat removal from the upper part <strong>of</strong> the reactorcompartment; the other section was for exhausting air from the reactor compartment.Rev. VI 36

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