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

Updated Final Safety Analysis Report - (STS-004-002)7 PRIMARY COOLANT SYSTEM7.1 General DescriptionTwo closed loops in the primary system circulated demineralized water through the reactor and steamgenerators; each loop contained two circulating pumps, one steam generator, two check valves and twostop valves with associated piping. A pressurizer was incorporated into the system on the reactor side ofthe starboard loop stop valve. The cooling water in each loop flowed from the discharge of the pumps tothe reactor, to the steam generator and back to the suction of the pumps.7.1.1 General Design DataAll of the primary coolant system equipment is deactivated, disabled and performs no active function.The primary coolant system was drained as completely as practical in March 1976.At rated full power, the primary coolant system transferred 80 MW th from the reactor core with a coolantflow rate of 9.2E+6 lb/hr. The normal operating volume of the primary system ranged from 1290 – 1375cubic feet (9,650 – 10286 gallons). The inlet temperature to the reactor at this power level was 494.6°Fand the outlet temperature was 521.4°F. The reactor average temperature was normally held constant atall power levels, as was the system flow rate, except for decay-heat removal.The heat added to the primary water as it flows through the reactor was given up to the secondary systemin the steam generator, where the saturated steam was generated. The temperature of the secondarysystem feedwater entering the steam drum was normally 345°F. The steam generated for the design loadcondition was 303,000 lb/hr. The heat transport system was designed for a maximum allowable workingpressure of 2000 psig on the primary side and 800 psig on the secondary side. The maximum mainprimary coolant loop heatup rate was limited to an average of 40°F per hour; its coo1down rate waslimited to 50°F per hour. These limits were established to prevent overstressing the reactor vessel flange.Each loop in the primary system could be vented and drained. Primary water expansion volume forheatup and cooldown transients was readily available from two makeup storage tanks (PD-T2 and PD-T3). The vents were connected to the gaseous waste disposal (WL) system header and the drains wereconnected to the equipment drain and waste collection (PD) system.The primary system equipment is arranged on a single supporting structure that offered little restraint tothe containment vessel (Figure 7-1). This is accomplished by locating the heaviest component (thereactor vessel) on the centerline of the containment and as close to the bottom of the containment aspossible. The next largest components (the steam generators) are located in the widest part of thecontainment on the port and starboard sides of the reactor. With this arrangement of the majorcomponents, a steel supporting structure was designed to adequately support the equipment under normalconditions and under the design pitch and roll conditions. Sway braces have been added to assure that thereactor vessel will be laterally supported if the ship capsizes. With this structure, all loads are carried intothe ring girders of the containment in the lower quadrant of the containment vessel. There is noconnection between the structural steel and the hemispherical ends of the containment, nor to the middleor upper quadrants of the containment, to produce restraints to the free flexure of the containment shell.The major components of the primary system-the reactor vessel, pressurizer and the steam generatorswerebuilt, inspected and stamped in accordance with contemporary USCG and ABS regulations. Whereexisting regulations did not apply, the ASME code was used as a guide and the matter was referred to theAEC and USCG for approval.Rev. VI 60