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

More documents

Recommendations

Info

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
7.1.2 General Performance DataUpdated Final Safety Analysis Report - (STS-004-002)7.1.2.2 Leakage From Primary SystemDuring the NSS’s operating period, most of the leakage from the primary system was from thebuffer seal (SL) system reciprocating charge pumps and from the diaphragm-operated reliefvalves. Maintenance techniques for the buffer seal charge pumps (which took suctiondownstream of the primary system demineralizers) were steadily improved. Improvements inthe design and testing sequence of the relief valves reduced the leakage. As a result of theseimprovements, leakage was reduced from a maximum of 1200 gpd to 50-100 gpd. Leakagefrom the buffer seals of the control rod drive shafts and from the valve stem packing was alwayswell within acceptable and anticipated limits.7.1.2.2 VibrationThe primary system was subjected to propeller-induced vibrations that were transmitted directlythrough the hull of the ship. During the design of the reactor plant, the vibration characteristicsof the primary system were analyzed using a scale model. As a result, a system of energyabsorbinghydraulic vibration dampers were designed and installed on the major components toprevent harmful vibration of the primary system in the range of the propeller blade frequency (5to 10 cps).Rev. VI 61
Page 1 and 2:
0U.S. Department Savannah Technical
Page 3 and 4:
Docket No. 50-238; License NS-1; N.
Page 5:
Ttit 1 ►'1 ltt tU.S. Department o
Page 8:
PageNo.Rev.No.Updated Final Safety
Page 11 and 12:
Updated Final Safety Analysis Repor
Page 13 and 14:
Page 15 and 16:
Page 17 and 18:
Page 19 and 20:
Page 21 and 22:
Page 23 and 24:
Page 25 and 26:
Page 27 and 28: Updated Final Safety Analysis Repor
Page 33 and 34: U p da te d Fi na lS af et yA n al
Page 43 and 44: Figure 2-2General Arrangement - Inb
Page 47 and 48: 3.2.3 Port Operating CriteriaUpdate
Page 59 and 60: U p da te d Fi na lS af et yA n al
Page 61 and 62: Table 4-1List of Containment Penetr
Page 73 and 74: 5.3.3 Local ShieldingUpdated Final
Page 77: Updated Final Safety Analysis Repor
Page 81 and 82: 7.1.2.3 Water ChemistryUpdated Fina
Page 87 and 88: 7.5 Primary PumpsUpdated Final Safe
Page 91 and 92: 8.1.3 Construction Features8.1.3.1
Page 99 and 100: Figure 8-2Current Electrical Distri
Page 115 and 116: 9.2.1.2 DescriptionUpdated Final Sa
Page 117 and 118: 9.2.2 Buffer Seal (SL) System9.2.2.
Page 129 and 130:
Page 131 and 132:
9.2.8 Shutdown Circulation (SC) Sys
Page 133 and 134:
Page 135 and 136:
Page 137 and 138:
Page 139 and 140:
Page 141 and 142:
10.3.3 Non-nuclear InstrumentationU
Page 143 and 144:
Page 145 and 146:
11.5 Quality Assurance PlanUpdated
Page 147 and 148:
Page 149 and 150:
Page 151 and 152:
Page 153 and 154:
Page 155 and 156:
Deck/compartmentsUpdated Final Safe
Page 157 and 158:
Page 159 and 160:
Page 161 and 162:
Page 163 and 164:
Page 165 and 166:
Page 167 and 168:
Page 169 and 170:
show all

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

You also want an ePaper? Increase the reach of your titles

Delete template?

Save as template?