ML091400694
| ML091400694 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 04/30/2009 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML091400694 (190) | |
Text
Table of Contents10-iWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.0MAIN STEAM AND POWER CONVERSION SYSTEMS10.1
SUMMARY
DESCRIPTION10.1-1 10.2TURBINE-GENERATOR10.2-110.2.1Design Bases10.2-110.2.2Description10.2-110.2.3Turbine Rotor and Disc Integrity10.2-5 10.2.3.1 Materials Selection10.2-510.2.3.2Fracture Toughness10.2-710.2.3.3 High Temperature Properties10.2-9 10.2.3.4 Turbine Disc Design10.2-910.2.3.5 Preservice Inspection10.2-910.2.3.6 Inservice Inspection10.2-11 10.2.4Evaluation10.2-1310.3MAIN STEAM SUPPLY SYSTEM10.3-110.3.1Design Bases10.3-110.3.2System Description10.3-110.3.2.1System Design10.3-1 10.3.2.2Material Compatibility, Codes, and Standards10.3-210.3.3Design Evaluation10.3-210.3.4Inspection and Testing Requirements10.3-3 10.3.5Water Chemistry10.3-310.3.5.1Purpose10.3-310.3.5.2Feedwater Chemistry Specifications10.3-4 10.3.5.3Operating Modes10.3-410.3.5.4Effect of Water Chemistry on the Radi oactive Iodine Partition Coefficient 10.3-510.3.6Steam and Feedwater System Materials10.3-510.3.6.1Fracture Toughness10.3-510.3.6.2Materials Selection and Fabrication10.3-510.4OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-110.4.1Main Condenser10.4-1 10.4.1.1Design Bases10.4-110.4.1.2System Description10.4-110.4.1.3Safety Evaluation10.4-410.4.1.4Inspection and Testing10.4-510.4.1.5Instrumentation10.4-5 10.4.2Main Condenser Evacuation System10.4-510.4.2.1Design Bases10.4-510.4.2.2System Description10.4-5 10-iiTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.2.3Safety Evaluation10.4-610.4.2.4Inspection and Testing10.4-610.4.2.5Instrumentation10.4-610.4.3Turbine Gland Sealing System10.4-710.4.3.1Design Bases10.4-710.4.3.2System Description10.4-7 10.4.3.3Safety Evaluation10.4-710.4.3.4Inspection and Testing10.4-810.4.3.5Instrumentation10.4-8 10.4.4Turbine Bypass System10.4-810.4.4.1Design Bases10.4-810.4.4.2System Description10.4-8 10.4.4.3Safety Evaluation10.4-910.4.4.4Inspection and Testing10.4-1010.4.5Condenser Circulating Water System10.4-10 10.4.5.1Design Basis10.4-1110.4.5.2System Description10.4-1110.4.5.3Safety Evaluation10.4-13 10.4.5.4Inspection and Testing10.4-1410.4.5.5Instrumentation Application10.4-1410.4.6Condensate Polishing Demineralizer System10.4-1510.4.6.1Design Bases - Power Conversion10.4-1510.4.6.2System Description10.4-1510.4.6.3Safety Evaluation10.4-17 10.4.6.4Inspection and Testing10.4-1810.4.6.5Instrumentation10.4-1810.4.7Condensate and Feedwater Systems10.4-19 10.4.7.1Design Bases10.4-1910.4.7.2System Description10.4-1910.4.7.3Safety Evaluation10.4-26 10.4.7.4Inspection and Testing10.4-2810.4.7.5Instrumentation10.4-2810.4.8Steam Generator Blowdown System10.4-28 10.4.8.1Design Bases10.4-2810.4.8.2System Description and Operation10.4-3010.4.8.3Safety Evaluation10.4-30 10.4.8.4Inspections and Testing10.4-3110.4.9Auxiliary Feedwater System10.4-3210.4.9.1Design Bases10.4-3210.4.9.2System Description10.4-3210.4.9.3Safety Evaluation10.4-34 10.4.9.4Inspection and Testing Requirements10.4-3710.4.9.5Instrumentation Requirements10.4-3710.4.10Heater Drains and Vents10.4-38 Table of Contents10-iiiWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle Page10.4.10.1Design Bases10.4-3810.4.10.2System Description10.4-3810.4.10.3Safety Evaluation10.4-4310.4.10.4Inspection and Testing10.4-4410.4.10.5Instrumentation10.4-4410.4.11Steam Generator Wet Layup System10.4-44 10.4.11.1Design Bases10.4-4410.4.11.2System Description10.4-4410.4.11.3Safety Evaluation10.4-45 10.4.11.4Inspection and Testing10.4-4510.4.11.5Instrumentation10.4-45 10-ivTable of ContentsWATTS BARWBNP-76TABLE OF CONTENTS SectionTitle PageTHIS PAGE INTENTIONALLY BLANK List of Tables10-vWATTS BARWBNP-76LIST OF TABLES SectionTitleTable 10.1-1(Sheet 1 of 6) Summary of Important Component Design Parameters Vertical Steam GeneratorsTable 10.1-1(Sheet 2 of 6) Summary of Important Component Design Parameters Moisture Separator and ReheatersTable 10.1-1(Sheet 3 of 6) Summary Of Important Component Design Parameters (Continued) Standby Main Feedwater PumpsTable 10.1-1(Sheet 4 of 6) Summary of Important Component Design Parameters No. 7 Heater Drain PumpsTable 10.1-1(Sheet 5 of 6) Summary of Important Component Design Parameters (Continued) CondenserTable 10.1-1(Sheet 6 of 6) Summary of Im portant Design Parameters Safety ValvesTable 10.3-1Main Steam Supply System Appl icable Codes, Standards, and Design ConditionTable 10.3-2Ethanolamine AVT Steam Gene rator Side and Feedwater Chemistry Specifications Limits1Table 10.3-3Deleted by Amendment 43Table 10.3-4Deleted by Amendment 43Table 10.4-1Deleted by Amendment 43 Table 10.4-2Auxiliary Feedwater Pump ParametersTable 10.4-3Failure Analysis, St eam Generator Blowdown SystemTable 10.4-4Failure Mode & Effects Analysis Steam Supply SubsystemTable 10.4-5Failure Mode & Effects Analys is Turbine-Driven (TD) Pump Subsys-tem (Steam Generator (SG) - Loop No. 4 TypicalTable 10.4-6Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical)Table 10.4-7Auxiliary Feedwater Flow to Steam Generators Following an Acci-dent/Transient - GPM 10-viList of TablesWATTS BARWBNP-76LIST OF TABLES SectionTitleTHIS PAGE INTENTIONALLY BLANK List of Figures10-viiWATTS BARWBNP-91 LIST OF FIGURES SectionTitleFigure 10.1-1Powerhouse Units 1 & 2 Fl ow Diagram General Plant SystemsFigure 10.1-2Powerhouse Units 1 & 2 Maximum Calculated Throttle Flow-2 MFPT'sFigure 10.1-3Powerhouse Units 1 & 2 Maxi mum Calculated Throttle Flow- MFPT'sFigure 10.2-1Powerhouse Unit 1 Wiring Diag ram Turbo-Generator Auxiliaries Sche-matic DiagramsFigure 10.2-2Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont SystemFigure 10.2-2Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A)Figure 10.2-3Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont SystemFigure 10.2-3Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont Sys (Sheet A)Figure 10.2-4Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont SystemFigure 10.2-4Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A)Figure 10.3-1Powerhouse Unit 1 Flow Diagram - Main and Reheat SteamFigure 10.3-2Powerhouse Unit 1 Electrical Control Diagram - Main Steam SystemFigure 10.3-3Powerhouse Unit 1 Electrical Control Diagram - Main Steam SystemFigure 10.3-3Powerhouse Unit 1 Electrical Control Diagram Main Steam System (Sheet A)Figure 10.3-4Powerhouse Unit 1 Electrical Control Diagram Main Steam SystemFigure 10.3-4aPowerhouse Unit 1 Electri cal Control Diagram Main Steam SystemFigure 10.3-5Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat SteamFigure 10.3-6Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat SteamFigure 10.3-7Powerhouse Units 1& 2 Elect rical Logic Diagram Main and Reheat SteamFigure 10.3-8Electrical Unit 1 Electrical Logic Diagram Safety Injection SystemFigure 10.3-9Powerhouse Units 1 & 2 Flow Diagram Feedwater Treatment Second-ary Chemical FeedFigure 10.4-1Powerhouse Unit 1 Flow Diag ram Turbine Drains and Miscellaneous PipingFigure 10.4-2General Units 1 & 2 Flow Diagram Condenser Circulating WaterFigure 10.4-3General Unit 1 Flow Di agram Condenser Circulating WaterFigure 10.4-4Powerhouse Units 1 & 2 Elect rical Control Diagram Condenser Circu-lating Water SystemFigure 10.4-5Powerhouse Units 1 & 2 Elect rical Control Diagram Condenser Circu-lating Water SystemFigure 10.4-6Powerhouse Unit s 1 & 2 Electrical Logic Diagram Condenser Circulat-ing Water SystemFigure 10.4-7Powerhouse Units 1
& 2 Flow Diagram CondensateFigure 10.4-8Powerhouse Unit 1 Flow Diagram FeedwaterFigure 10.4-9Powerhouse Unit 1 Electri cal Control Diagram Condensate System 10-viiiList of FiguresWATTS BARWBNP-91 LIST OF FIGURES SectionTitleFigure 10.4-10Powerhouse Unit 1 Electri cal Control Diagram Condensate SystemFigure 10.4-11Powerhouse Units 1 & 2 El ectrical Control Diagram Condensate Sys-temFigure 10.4-11aPowerhouse Units 1 & 2 El ectrical Control Diagram Condensate Sys-temFigure 10.4-12Powerhouse Units 1 & 2 El ectrical Logic Diagram Condensate SystemFigure 10.4-13Powerhouse Unit 1 Electrical Logic Control Diagram Condensate Sys-temFigure 10.4-13aPowerhouse Unit 1 Elect rical Logic Diagram Condensate SystemFigure 10.4-14Powerhouse Units 1 & 2 Elect rical Control Diagram Main Auxiliary Feedwater SystemFigure 10.4-14Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet A)Figure 10.4-14Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet B)Figure 10.4-14Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet C)Figure 10.4-14Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet D)Figure 10.4-15Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater SystemFigure 10.4-15Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet A)Figure 10.4-15Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet B)Figure 10.4-15Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet C)Figure 10.4-16Powerhouse Unit 1 Auxili ary Feedwater System Control DiagramFigure 10.4-16aPowerhouse Unit 1 Auxili ary Feedwater System Control DiagramFigure 10.4-17Powerhouse Units 1 & 2 El ectrical Logic Diagram Feedwater Pump Turbine AuxFigure 10.4-18Powerhouse Units 1 & 2 El ectrical Logic Diagram Feedwater SystemFigure 10.4-19Powerhouse Unit 1 Electrical Logic Diagram Auxi liary Feedwater Sys-temFigure 10.4-20Powerhouse Units 1 & 2 Auxi liary Feedwater System Logic DiagramFigure 10.4-21Powerhouse Units 1 & 2 Flow Diagram Auxiliary FeedwaterFigure 10.4-21aPowerhouse Units 1 & 2 Flow Diagram Main & A uxiliary FeedwaterFigure 10.4-22DeletedFigure 10.4-23DeletedFigure 10.4-24Powerhouse Units 1 & 2 Fl ow Diagram Steam Generator Blowdown SystemFigure 10.4-25DeletedFigure 10.4-26Deleted List of Figures10-ixWATTS BARWBNP-91 LIST OF FIGURES SectionTitleFigure 10.4-27Powerhouse Unit 1 Flow Diag ram High Pressure Heater Drains and VentsFigure 10.4-28Powerhouse Unit 1 Flow Di agram Low Pressure Heater Drains and VentsFigure 10.4-29Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents SystemFigure 10.4-30Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents SystemFigure 10.4-31Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents SystemFigure 10.4-32Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents SystemFigure 10.4-33Powerhouse Unit 1 Mechanic al Control Diagram Heater Drains and Vents SystemFigure 10.4-34Powerhouse Unit 1 Electrical Logic Diagram Heater Drains and VentsFigure 10.4-35Powerhouse Unit 1 Electri cal Logic Diagram Heater and VentsFigure 10.4-36aTurbine Building Units 1 & 2 Flow Diagram Condens ate Demineralizer SystemFigure 10.4-36bTurbine Building Units 1 & 2 Flow Diagram Condens ate Demineralizer SystemFigure 10.4-36cTurbine Building Units 1 & 2 Flow Diagram Condens ate Demineralizer SystemFigure 10.4-37Powerhouse Unit 1 Flow Diagram Steam Generator Wet Layup Sys.
Closed Recirculation-Loop Sys.
10-xList of FiguresWATTS BARWBNP-91 LIST OF FIGURES SectionTitleTHIS PAGE INTENTIONALLY BLANK
SUMMARY
DESCRIPTION 10.1-1WATTS BARWBNP-82021_TVA_WB_FSAR_Section_10.pdf 10.0 MAIN STEAM AND POWER CONVERSION SYSTEMS 10.1
SUMMARY
DESCRIPTIONThe steam and power conversion system is designed to convert the heat produced in the reactor to electrical energy through conversion of a portion of the energy contained in the steam supplied from the steam generators, to condense the turbine exhaust steam into water, and to return the water to the steam generator as heated feedwater.The major components of the steam and power conversion system are: turbine-generator, main condenser, vacuum pumps, turbine seal system, turbine bypass system, hotwell pumps, demineralized condensate pumps, condensate booster pumps, steam-turbine-driven and electric-motor-driven main feed pumps, main feed pump turbines (MFPT), MFPT condenser-feedwater heaters, feedwater heaters, heater drain pumps, demineralizers, and condensate storage system. Component arrangement is shown in Figure 10.1-1. The heat rejected in the main condenser is removed by the circulating water system.The saturated steam produced by the steam generators is expanded through the high pressure turbine and then exhausted to the moisture separator/reheaters. The moisture separator section removes the moisture from the steam and the two stage reheaters superheat the steam before it enters the low pressure turbines. The steam then expands through the low pressure turbines and exhausts into the main condenser where it is condensed and deaerated and then returned to the cycle as condensate.The first stage reheater is supplied with steam from the No. 1 extraction point; the condensed steam is cascaded to the No. 2 heater. The second stage reheater is supplied with main steam; the condensed steam cascades to the highest pressure (No. 1) heater.Condensate is withdrawn from the condenser hotwells by motor-driven hotwell pumps. The pumps discharge into a common header which normally carries the condensate through the gland steam condenser, the main feed pump turbine condensers, and then through three parallel strings of low-pressure heaters. Each string consists of three stages (Nos. 5 through 7, with No. 5 the highest pressure) of low-pressure extraction feedwater heaters to the condensate booster pumps. Whenever condensate demineralization is required, the common header for the hotwell pumps carries the condensate through the demineralizers to the gland steam condenser, the main feed pump turbine condensers, and then to the demineralized condensate pumps. These pumps discharge to a common header which then carries the condensate through three parallel strings of low pressure heaters. The condensate booster pumps discharge to a common header which divides the flow back into three parallel strings of intermediate pressure heaters, each string consisting of three stages (Nos. 2 through 4) of extraction feedwater heaters. The condensate from the intermediate pressure heater strings is then routed to the main feed pumps. These pumps discharge to a common header which divides and passes through three parallel strings of single-stage high pressure heaters and returns to a common line before dividing into four streams to the four steam generators.
10.1-2
SUMMARY
DESCRIPTION WATTS BARWBNP-82Heat for the feedwater heating cycle is supplied by the moisture separator reheater drains and by steam from the turbine extraction points. A summary description of the important components and design parameters of the steam and power conversion system is contained in Table 10.1-1. Heat balances for the steam and power conversion cycle are shown in Figures 10.1-2 and 10.1-3.
SUMMARY
DESCRIPTION 10.1-3WATTS BARWBNP-82Table 10.1-1 (Sheet 1 of 6) Summary of Important Component Design Parameters Vertical Steam GeneratorsNumber -4 per unitLength-812.0, in. (overall)
Diameter -176.28 in. (maximum) 0D Heating surface - 48,000 sq ft.
Tubes -4674 U-tubes - 0.75 in. 0D x 0.043 nom. wall, Inconel (ASME-SB-163) materialOperating conditions at 100 Percent LoadSteam flow rate - 3.785 x 106 lb/hrSteam temperature - 544.6 E FSteam pressure - 1000 psia Steam quality - 99.75 percent minimumTURBOGENERATORManufacturer - Westinghouse Electric CorporationTurboqenerator nameplate rating - 1,218,225 kW Turbine type -Horizontal, impulse-reaction, tandem-compound,two stage reheat, extraction, condensing 1800-rpm single shaft - 1 HP and 3 LP turbines with 6-flow exhaust and 44 in. last-stage bucketsGenerator type and maximum nameplate rating - One direct connected, Hydrogen cooledrotor, water-cooled stator, 1,411,000 kVA, 0.9 PF, 75 pisg hydrogen, 3 ph, 60 Hz, 24,000 V, 33,943 Amp, 0.6 scr, Y-connectedExciter type and capacity - One shaft-driven, brushless - 6000 kW, 550 volt DC, 1800 rpm Heat RateGuaranteed performance based on extraction for feedwater heating,including all losses in the unit, also exciter and rheostat losses, rated throttle steam conditions, and 2.0 in. of Hg absolute exhaust pressure with zero makeup:kW Btu/kWh1,218,225 9593 10.1-4
SUMMARY
DESCRIPTION WATTS BARWBNP-91Table 10.1-1 (Sheet 2 of 6) Summary of Important Component Design Parameters Moisture Separator and ReheatersNumber 6 per unitType Moisture removal separator and 2-stage reheat (HP and LP)
Size45 ft - 11.75 inches length, 10 ft - 9 inches diameterMAIN FEEDWATER PUMP TURBINENumber -(1 Turbine per pump) - 2Manufacturer-Westinghouse Electric Corporation Type and speed-EMM-32AIN, multistage, dual inlet, 5460 rpm Design Steam,-Pressure 146 PSIG, Temperature 513°F Auxiliary Steam, -Pressure 995 PSIG, Temperature 546°FBack pressure-6.9 in. of Hg absolute Number of stages -6 Extraction points -None Rated horsepower -12,200MAIN FEEDWATER PUMPSNumber-2Manufacturer -Borg-Warner Corporation, Byron-Jackson Pump Division Type-HDR, single stage, double suction, double *volute,centrifugalSize-20 x 20 x 18B Design point -23,600 gpm, 1890 ft head Service conditions -Pump suitable for continuous se*rvice to deliver up to 17,630 gpm at 402.3°F against a total head of approximately 2012 ft at 5012 rpm, while operating under a minimum net positive suction head of 200 ft
SUMMARY
DESCRIPTION 10.1-5WATTS BARWBNP-91Table 10.1-1 (Sheet 3 of 6) Summary Of Important Component Design Parameters (Continued) Standby Main Feedwater PumpsNumber - 1Manufacturer - Borg-Warner Corporation, Byron-Jackson PumpDivisionType - DVS, single stage, double suction, double volute,centrifugalSize - 12 x 12 x 16 Design point - 6100 gpm, 1890 ft head Motor manufacturer - Parsons-Peebles, Ltd.
Motor design - 3700 HP, 3584 rpm, 6600 V, 3 ph, 60 Hz,constant speedSpeed increaser - Lufkin model N1400C, 1.50:1 ratioCONDENSATE BOOSTER PUMPSNumber - 3Manufacturer -Borg-Warner Corporation, Byron-Jackson PumpDivisionType - DVDSR, single stage, double suction, double volute, centrifugal Size - 14 x 14 x 15H Design point - 9000 gpm, 680 ft head Motor manufacturer - Parsons-Peebles, Ltd.
Motor design - 1750 HP, 3584 rpm, 6600 V, 3 ph, 60 Hz,horizontal, constant speedNO. 3 HEATER DRAIN PUMPSNumber - 3Manufacturer - Borg-Warner Corporation, Byron-Jackson PumpDivisionType - DSJH, sinqle stage, double suction, double volute, centrifugal Size - 8 x 10 x 18H Design point - 3600 gpm, 1200 ft head Motor manufacturer - Parsons-Peebles, Ltd.
Motor design - 1250 HP, 3580 rpm, 6600 V, 3 ph, 60 Hz, horizontal, constant speed 10.1-6
SUMMARY
DESCRIPTION WATTS BARWBNP-91Table 10.1-1 (Sheet 4 of 6) Summary of Important Component Design Parameters No. 7 Heater Drain PumpsNumber - 2Manufacturer - Borg-Warner Corporation, Byron-Jackson Pump Division Type - DSJH, sinqle stage, double suction, double volute, centrifugal Size - 8 x 10 x 15L Design point - 2000 gpm, 730 ft Motor manufacturer - Parsons-Peebles, Ltd.
Motor design - 450 HP, 3565 rpm, 6600 V, 3 ph, 60 Hz, horizontal, constant speedCONDENSATE HOTWELL PUMPSNumber - 3Manufacturer - Borg-Warner Corporation, Byron-Jackson Pump Division Type - VMT, four stages, single suction, vertical process Size - 28KXFH Design point - 6700 gpm, 600 ft head*
Motor manufacturer - Parsons-Peebles, Ltd.
Motor design - 1250 HP, 1180 rpm, 6600 V, 3 ph, 60 Hz, vertical, constant speedDEMINERALIZED CONDENSATE PUMPSNumber - 3Manufacturer - Ingersoll-Rand Company Type - A, single stage, single suction, end suction process Size - 10 x 18AA Design point - 6700 gpm, 150 ft head*
Motor manufacturer - Westinghouse Motor design - 350 HP, 1770 rpm, 460 V, 3 ph, 60 Hz, horizontal, constant speed*During preoperational testing of the hotwell and demineralized condensate pumps, the pumps did not meet vendor pump performance curves. However, review of the test data indicates the pumps will deliver sufficient flow and head to satisfy operational requirements and the test results are acceptable.
SUMMARY
DESCRIPTION 10.1-7WATTS BARWBNP-73Table 10.1-1 (Sheet 5 of 6) Summary of Important Component Design Parameters (Continued) CondenserNumber - 1Manufacturer - Ingersoll-Rand Company Type - Horizontal, single shell, triple pressure, single pass, surface, deaerating Total surface area, sq ft - 824,000 Tube data - 27,410 Tubes, 114 ft 8-1/2 in. effective length seamless, drawn, 1.0 in. outside diameter, No. 20 BWG, 90-10 Cu-Ni Tube sheets - Cooper bearing steel Waterboxes - Divided, two inlet (102 in. dia) and two outlets (102 in. dia) bottom connections per shell Hotwell data - Deaerating type, storage capacity of hotwell at normal operating level, 56,000 gal Circulating water quality, gpm - 410,000 Cleanliness, percent - 95 Duty, 10 9 Btu/hr - 7.789Design pressures: Shell, psig - 25Hotwell, psig - 30 Waterboxes, psig - 72Air Removal EquipmentNumber - 3Manufacturer - Nash Engineering Company Size - AT2004E Type - Mechanical, vacuum Design point -Suction pressure in. of Hg absolute - 1.0,Rated capacity, each - 15 SCFMMotor Manufacturer - General Electric Company Motor design -100 HP, 500 rpm, 460 V, 3 ph, 60 HZhorizontal, constant speedFEEDWATER HEATERNumber - 21 (7 stages, divided into 3 streams)Manufacturers No. 1 and 2 - Yuba Heat Transfer CorporationNo. 3 and 4 - Foster Wheeler Energy Corporation No. 5, 6, and 7 - McQuay-Perfex IncorporatedType - Closed, horizontal, U-tube Tubes - 304 SST 10.1-8
SUMMARY
DESCRIPTION WATTS BARWBNP-89Table 10.1-1 (Sheet 6 of 6) Summary of Important Design Parameters Safety ValvesNumber - 5 per steam generatorMinimum flow capacity, lb/hr steam generator - 3,975,200Note1 - The licensing basis for the WBN plant is 10% maximum blowdown (See Section 3.9, Reference 13). This is more conservative that the 5% maximum blowdown specified by the ASME Section III requirements.Atmospheric Relief ValvesNumber 1 - per steam generatorMinimum capacity, lb/hr/inlet pressure, psig - 64,000/85Maximum capacity, lb/hr/inlet pressure, psig - 970,000/1185 outlet pressure, psig - 0Turbine Bypass ValvesNumber of valves - 12Flow per valve, lb/hr - 532,170 Main steam pressure at valve inlet (for above flow), psig - 900 Maximum flow per valve at 1185 psig inlet pressure, lb/hr - 970,000 Time to open (full stroke), 3 seconds (design) -
< 7 seconds (tested and accepted) Full stoke modulation, seconds 20 Failure position - Closed ValveMark No.Set Press.
(psig)Accumu-lation Press.
to fully Open Valve
% Max.Expected Accumu-lation Press at max Flow
% Press.in Steam Header at Rated Relieving Flow (psig) Rated Flow at Set Pressure
+ 3%
Accumu-lation (lb/hr)
Blowdown Press.
Below Set Pressure to Close
(%)[1] Press.In.
Steam Header at Valve Closing (psig) 47W400-101
47W400-10511851195 1205 1215 1224 3 3 3
3 3 8.4 7.5 6.6 5.8 4.912841284 1284 1284 1284791,563798,163 804,764 811,364 817,304 4 4 4
4 41066.51075.5 1084.5 1093.5 1101.6 Main Steam and Power Conversion Systems 10.1-9WATTS BAR WBNP-86Figure 10.1-1 Powerhouse Units 1 & 2 Flow Diagram General Plant Systems
10.1-10Main Steam and Power Conversion Systems WATTS BAR WBNP-86Figure 10.1-2 Powerhouse Units 1 & 2 Maximum Calculated Throttle Flow-2 MFPT's Main Steam and Power Conversion Systems 10.1-11WATTS BAR WBNP-86Figure 10.1-3 Powerhouse Units 1 & 2 Maximum Calculated Throttle Flow- MFPT's 10.1-12Main Steam and Power Conversion Systems WATTS BAR WBNP-86 THIS PAGE INTENTIONALLY BLANK TURBINE-GENERATOR 10.2-1WATTS BARWBNP-92 10.2 TURBINE-GENERATOR 10.2.1 Design BasesThe purpose of the turbine generator is to use steam supplied by the pressurized water reactor (PWR) in the conversion of thermal energy to electrical energy, and to provide extraction steam for feedwater heating. The turbine generator together with its associated systems and their control characteristics are integrated with the features of the reactor and its associated systems to obtain an efficient and safe energy conversion and power generation unit.The turbogenerator unit receives steam from the four steam generators and converts the thermal energy to electric energy. The original Westinghouse turbine generator data is 1,218,225 kW when the steam flow is 15,143,600 lb/hr steam conditions of 975 psia, 0.25% 0.39% at turbine) moisture, and at a back pressure of 2.0-inches of Hg absolute, with 0% makeup under normal conditions. At the valves wide open or stretch condition the generator is rated at 1,269,837 kW with a steam flow of 15,900,800 lb/hr at 975 psia, 0.39% moisture, at a back pressure of 2-inches of Hg absolute, and 0%
makeup. Actual plant operating conditions and design will differ slightly from the rated parameters given above. The design heat balance for the 100% power case is shown in Figure 10.1-2.Under emergency conditions the turbine protection system provides the necessary protection for the turbine-generator equipment.The intended mode of operation for the unit is to be utilized primarily as a base loaded unit.10.2.2 DescriptionThe turbine generator unit consists of the following components: turbine, generator, exciter, controls, and required support subsystems. The turbine is a tandem compound double-stage reheat unit with 44-inches last-stage blades. The turbine consists of a double-flow, high pressure turbine and three double-flow, low pressure turbines with extraction nozzles arranged for seven stages of feedwater heating. Exhaust steam from the unit passes through six moisture separator/reheaters before entering the low pressure turbines. The moisture separator/reheaters are shell and tube-type heat exchangers containing a section of chevron vanes for moisture separation. The chevron-type vanes alter the steam flow direction to reduce the moisture content of the steam through centrifugal separation of the moisture particles. Heating steam enters the reheater U-tube bundles to provide two stages of reheat for the steam flowing from the chevron section.The generator is a direct-connected, hydrogen-cooled, 3 phase, 60 Hz, 24,000 volt, 1800 rpm synchronous generator rated at 1,411,000 kVA, 0.90 power factor (PF), with a short circuit ratio (scr) of 0.60. It is designed with conductor cooling of the armature winding. Hydrogen gas pressure is 75 psig and conductor coolant is demineralized water. The excitation system is rated at 6,000 kW and 550 volts.
10.2-2TURBINE-GENERATOR WATTS BARWBNP-92The turbogenerator and its associated systems and controls are integrated with the reactor and its associated systems and controls at all times to obtain an efficient and safe energy conversion and power generator unit. The reactor controls enable the NSSS to follow plant (turbogenerator) load changes automatically, including the acceptance of step load increases or decreases of 10% and ramp increases or decreases of 5% per minute within the load range of 15% to 100% without reactor trip or steam dump. Manual control is required below 15% load. The difference between the highest measured average reactor coolant loop temperature and the programmed reference temperature (based on turbine impulse chamber pressure) which is processed through a lead-lag compensation unit, constitutes the primary control signal for the reactor control system. An additional control input signal to the reactor is derived from the reactor power versus turbine load mismatch signal. These signals provide input to the rod control system to control the reactor coolant temperature by regulation of the control rod bank position.The turbine control system is electrohydraulic and consists of several different control subsystems that are used to control turbine speed, plant load, speed and load rates, and other turbine features during plant startup, plant operation at rated conditions, and plant shutdown. Also, normal, pre-emergency, and emergency governing devices are incorporated into the control system to prevent turbine overspeed conditions.The control system consists of five major components as follows:
(1)A solid-state electronic controller cabinet.
(2)An operator's panel.
(3)Steam valve servo-actuators.
(4)A high pressure fluid control system.
(5)A lube oil and associated mechanical-hydraulic emergency trip system.The electronic controller cabi net contains circuits for the system such as logic, reference, signal input channels with solid-state operational amplifiers, and automatic and manual controllers. It performs basic analog computations on reference and turbine feedback signals and generates an output signal to the steam valve actuators.The operator's panel is in the unit control center. Through various push buttons the operator can change the reference input to the electronic controller to vary the speed or load at different rates.Operator settings made at the panel are used by the electronic controller to position the steam valves. The position of each steam valve is controlled by an actuator which consists of a hydraulic cylinder using fluid pressure to open and spring action to close. The cylinder is connected to a control block upon which are mounted isolation, dump, and check valves. (see Figures 10.2-2, 10.2-3, and 10.2-4 for steam, actuator, and other valve numbers and system arrangements).
TURBINE-GENERATOR 10.2-3WATTS BARWBNP-92The main stop (throttle) valve, reheat stop valve, and interceptor valve actuators position these steam valves (see FCV-1-61, -64, -67, -70, -87, -88, -94, -95 , -101, -102, -123, -124, -128, -129, -133, and -134 on Figure 10.2-3) only in the fully open or fully closed position (except for a brief period during startup when the main stop throttle valves (FCV-1-61, -64, -67, and 70) are used for initial speed control). High pressure fluid is supplied through an orifice to the area below the hydraulic cylinder piston. Fluid pressure in this area is controlled by a pilot-operated dump valve for the reheat stop and interceptor valves and by a servo- and/or pilot-operated dump valves for the main stop valves. With the turbine autostop mechanism latched, the pilot-operated dump valves close to build up fluid pressure under the cylinder piston, opening the reheat stop and interceptor valves. Solenoid valves provided for testing of the reheat stop and interceptor valves also open the dump valves, releasing the fluid to drain thus testing the valves capability to close.The control (governor) valve actuators position these steam valves (FCV-1-62, -65, -68, and -71) in any intermediate position to proportionally regulate the steam flow to the required amount. The control (governor) and stop (throttle) valve actuators are provided with a servo-valve and a linear variable differential transformer (LVDT). High pressure fluid is supplied to the servo-valve which controls the actuator position in response to a position signal from the servoamplifiers. The LVDT develops an analo signal proportional to the valve position, which is fed back to the controller to complete the control loop. A signal can be introduced to the controller to test the main stop and
control valves.Isolation valves permit on-line maintenance of the actuator components, including the hydraulic cylinder. Check valves prevent fluid backflow from the drain or emergency trip circuits.The function of the high pressure fluid control system is to provide a motive force which positions the turbine steam valves in response to electronic commands from the controller, acting through the servo-actuators. The fluid is stored in a reservoir assembly on which is mounted a duplicate system of fluid pumps, controls, filters, and heat exchangers. The system is so arranged that one pump and one set of the various control components function while the duplicate set serves as a standby system.The turbine protection system has as its bas is two serially connected fluid systems: the autostop oil system, and two parallel stop valve and control valve emergency trip fluid systems in the high pressure fluid control system (See Figures 10.2-2 and 10.2-3). Tripping of the control valve emergency trip fluid system causes trip closure of all control and intercept valves and also the extraction non-return valves (See XDV-47-27 on Figure 10.2-3). Tripping of the stop valve emergency trip fluid system causes tripping of all stop and reheat stop valves and also tripping of the control valve emergency trip fluid. Tripping of the autostop oil system causes tripping of the stop valve emergency trip fluid systems. Two solenoid-operated valves (shown as FSV-47-26A and FSV-47-26B on Figure 10.2-1) are energized when turbine speed exceeds 103% of rated turbine speed releasing to drain the control valve emergency trip fluid and causing immediate closing of the control and interceptor valves. A check valve between the control valve emergency trip fluid circuit and the stop valve 10.2-4TURBINE-GENERATOR WATTS BARWBNP-92emergency trip fluid circuit retains the fluid pressure in the latter line, and the reheat stop and main stop valves remain open. With a reduction in speed, the solenoid valves close and the control, interceptor, and extraction non-return valves reopen. The stop valve emergency trip fluid system contains an interface emergency trip valve (FCV-47-27) and a solenoid valve (FSV-47-27) serving as a backup to the interface emergency trip valve which when activated, trips the turbine. The interface emergency trip valve uses lubricating oil from the mechanical-hydraulic trip system as its control medium. This trip valve, which is diaphragm operated, is the link between the high pressure fluid system and the mechanical-hydraulic lube oil trip system. Lube oil supplied to the interface trip valve acts to overcome a spring force to hold the valve closed. A decay in the lube oil pressure allows the spring to open the valve, dumping the high pressure operating fluid in the stop valve emergency trip fluid system to drain. High pressure operating fluid and lube oil are not in contact with each other.The solenoid valve (FSV-47-27) may be activated by a pressure switch in the autostop lube oil header, a control room handswitch, or reactor or turbine trip signals (see Figure 10.2-1). When this valve is activated, the fluid in the stop valve fluid system is dumped to drain with all steam admission valves being tripped closed. The autostop oil system will automatically trips (depressurizes) on evidence of low condenser vacuum, abnormal thrust bearing wear, or low bearing oil pressure. The autostop oil system is also equipped with a solenoid-operated trip device (FSV-47-24) which provides a means to dump the autostop oil to drain, and initiate direct tripping of the turbine upon receipt of appropriate electrical signals as shown on Figure 10.2-1. The autostop oil system and thus the turbine may be tripped manually on detection of high temperature differences between condenser shells, high exhaust hood temperature, high back pressure on the main condenser, high journal or thrust bearing metal temperature, excessive shaft vibration, high bearing oil discharge temperatures, or high differential expansion. When a turbine trip is initiated, the extraction system nonreturn valves are also tripped closed by means of a pilot dump valve (XDV-47-27) connected to the turbine trip system as shown on Figure 10.2-1.Three types of overspeed protection mechanisms are provided to isolate main steam to the turbogenerator when the rated operating speed of 1800 rpm is exceeded. During normal speed-load control, the overspeed protection controller (OPC) which is set at 1854 rpm (103% of rated speed) will rapidly close the governor and interceptor valves in case of an overspeed condition. Rotational speed is then maintained below this setpoint by oscillating the interceptor valves between the closed and open position until the reheater steam (steam between the high pressure turbine exhaust and the low pressure turbines) is dissipated. If the control system is in speed control mode, the governor valves will take over speed control .If for some reason the OPC control system does not function and the turbine speed increases to 1980 rpm (110% of rated speed), the mechanical overspeed mechanism will trip closed all steam valves (throttle, governor, reheat stop, and interceptor valves) and prevent the turbine speed from exceeding 120% of rated speed. The unit will then coast down to turning gear operation.
TURBINE-GENERATOR 10.2-5WATTS BARWBNP-82In addition to the two control systems described above, an independent electrical overspeed trip is provided in the Analog Electro Hydraulic (AEH) control system. If the turbine generator speed increases to 1998 rpm (approximately 111% of rated speed), all steam valves (as specified in the previous paragraph) trip closed. This trip actuates by a contact output from the AEH controller which energizes a trip solenoid in the auto stop oil line and a trip solenoid in the stop valve emergency trip fluid circuit. Again, during the overspeed condition, turbine speed remains below 120% of rated speed.
The unit will then coast down to turning gear operation.The turbine trip system is also equipped with solenoid-operated trip devices, which provide means to initiate direct tripping of the turbine upon receipt of appropriate electrical signals, as shown in Figure 10.2-1. Turbine governor functions and turbine control are discussed more fully in Section 7.7.For overpressure protection of the turbine exhaust hoods and the condenser, four rupture diaphragms which rupture at approximately 5 psig are provided on each turbine exhaust hood. Additional protective devices include exhaust hood high temperature alarm and manual trip.A discussion of turbine missiles is found in Section 3.5.
10.2.3 Turbine Rotor and Disc IntegrityThe failure of a turbine disc or rotor might produce a high energy missile that could damage a safety-related component (see Section 3.5 for turbine missile analysis). The risk from missiles from a hypothetical turbine-generator failure on safety-related systems or components is discussed in Sections 3.5.1.3.3 through 3.5.1.3.6. Integrity of the turbine discs and rotors is demonstrated by information provided in this section.
10.2.3.1 Materials SelectionThe detailed materials specifications, fabrication history, and chemical analysis of the disc and rotor forgings are considered proprietary information of the turbine manufacturer, Westinghouse Electric Corporation. The high pressure rotor is made of NiCrMoV alloy steel. The specified minimum mechanical properties are as follows:Tensile Strength, psi 105,000Yield Strength, psi (0.2% offset)90,000 Elongation in 2-inches, percent 17 Reduction of Area, percent 50 Impact Strength, Charpy V-Notch, ft-lb50 (min. at room temperature) 50% Fracture Appearance Transition40 Temperature, F, max.
10.2-6TURBINE-GENERATOR WATTS BARWBNP-82The blade rings and the casing cover and base are made of carbon-steel castings. The specified minimum mechanical properties are as follows:The casing cover and base are tied together by means of more than 100 studs. The stud material is an alloy steel having the following minimum properties:The low pressure rotors are made of NiCrMoV alloy steel. The specified minimum mechanical properties are as follows:The outer cylinder and the two inner cylinders are fabricated mainly of ASTM 515-GR65 material. The minimum specified properties are as follows:Tensile Strength, psi 70,000Yield Strength, psi 36,000 Elongation in 2-inches, percent 22 Reduction of Area, percent 352-1/2 inch and lessOver 2-1/2 to 4 inch Over 4 to 7 inchTensile Strength, psi125,000115,000110,000 Yield Strength, psi 105,00095,000 85,000 (0.2% offset)Elongation in 2-inches,161616 percent Reduction of area, percent505045Tensile Strength, psi 115,000Yield Strength, psi (0.2% offset)100,000Elongation in 2-inches, percent 17Reduction of Area, percent 50 Impact Strength, Charpy V-Notch, ft-lb40 (at room temperature) 50% Fracture Appearance Transition50 Temperature F, (max.)Tensile Strength, psi 65,000Yield Strength, psi 35,000 TURBINE-GENERATOR 10.2-7WATTS BARWBNP-82The shrunk-on discs are made of NiCrMoV alloy steel. There are ten discs shrunk on the shaft with five per flow. These discs experience different degrees of stress when in operation. Disc No. 2, starting from the transverse centerline, experiences the highest stress, while disc No. 5 experience the lowest. The minimum specified mechanical properties for the discs are as follows:
10.2.3.2 Fracture ToughnessFracture mechanics analysis by Westinghouse (reference "Techniques for Fracture Mechanics Analysis of Nuclear Turbine Discs" by G. T. Campbell, dated September 1974) indicates that a very large initial defect would have to be present in the low pressure turbine discs to cause bursting during normal operation after a nominal 2000 cycles of startup and shutdown. Preservice and inservice inspection procedures will assure that no such large defects are present in these discs. A description of the analytical method employed is given in the following paragraphs.First, the critical flaw size is determined using the equation for a semi-elliptical surface flaw with the major axis of the crack normal to the applied stress:Elongation in 8 ft, percent 19Elongation in 2 ft, percent 23Disc 1Disc 2Discs 3-5Tensile Strength, psi130,000140,000120,000 Yield Strength, psi120,000130,000110,000Elongation in 2 ft (disc hub) percent141315Elongation in 2 ft (disc rim)161517 percent Reduction of area (disc hub) percent353538 Reduction of area (disc rim) percent404043 Impact strength (hub and rim) Charpy V-Notch, ft-lb (at room temp)50505050% Fracture Appearance Transition Temp. (disc hub and rim) °F (max)000Tensile Strength, psi 65,000 a CR K IC t---------
2 Q 1.21-------------
-=
10.2-8TURBINE-GENERATOR WATTS BARWBNP-82 where a CR = Critical flaw size K IC = Critical Stress Intensity factor t = Applied tangential stress (highest stresses present in a disc)Q = Flaw shape parameter By using conservative values for t , K IC, and Q (80KSI, 170KSI /in and 1.0, respectively) it was determined that a CR = 1.19-inch. Hence, the disc would have to have a crack 1.19-inch deep by 11.9-inches long present at the bore before bursting.Once a CR is known, it is possible to determine the initial flaw size (a i) which would grow to the critical size in a given number of stress cycles (i.e., number of startups and shutdowns of a turbine). This is done by solving the generalized cyclic life expression developed by W. K. Wilson (DCC Report AD 801005, June 24, 1966) for a
- i. Using the value of 1.19-inch developed above for a CR and a conservative value of 2000 cycles yields a value for a i of 0.93-inch. Since the tangential stresses are highest at the bore of the disc, this is the initial flaw size for a flaw at the bore. Therefore, values of a i at other locations in the disc would be smaller than this value. It must be noted that for any given condition, the evaluation of a i is conservative because it is assumed that the initial defect is crack like and will behave as a fatigue crack. This is a conservative assumption since, in general, natural flaws are not expected to act as sharp cracks and a finite number of cycles will be required prior to the initiation of a fatigue crack which will obey the equation for crack growth.Keyways are employed on turbines to maintain the position of a disc on the rotor shaft. These keyways represent a localized stress concentration which affects the stress intensity factor associated with a given size defect. Several methods are available for analysis of such a situation. The most conservative method and easiest to use from a computational standpoint is the technique where the depth of the keyway is assumed to act as part of the defect and hencewhere, R is the radius of the keyway and t is the nominal bore stress. In the case of the modern tough materials employed by Westinghouse for nuclear turbine discs, this method suffices to evaluate discs which experience little crack growth from cyclic stresses.K IC1.9497 t aR+Q=
TURBINE-GENERATOR 10.2-9WATTS BARWBNP-82For a keyway radius of 0.375-inch (using the same conservative values for K IC , t , and Q used above), it was determined that a CR = 0.813-inch for the keyway. Hence, the defect on the keyway which would cause failure for the given conditions is 0.813-inch deep by 11.9-inches long.As with the smooth bore, a defect can be expected to undergo cyclic growth with the startup and shutdown of the turbine unit. Essentially the same procedure is used to evaluate a i on the keyway as is used on the smooth bore. The procedure is as follows:
(1)Determine a CR (2)Determine a i for selected number of cycles (3)Subtract radius of keyway (R) from a i.Again, for a conservative 2000 cycles, a i = 0.63-inch. As the shape factor assumed is 1.0, the defect on the keyway which would lead to failure under the conditions given is 0.63-inch deep by 10-inches long.
10.2.3.3 High Temperature PropertiesThe stress-rupture properties of the high pressure rotor material are considered to be proprietary information of the turbine manufacturer, Westinghouse Electric Corporation.10.2.3.4 Turbine Disc DesignInformation on the tangential and radial stresses in the low pressure discs and high pressure rotors is considered proprietary information of the turbine manufacturer, Westinghouse Electric Corporation. However, the actual maximum tangential stresses are less than those assumed previously in Section 10.2.3.2.10.2.3.5 Preservice Inspection 10.2.3.5.1 Low Pressu re Turbine RotorThe low pressure turbine rotor and discs are heat treated nickel-chromium-molydenum-vanadium alloy steel procured to specifications that define the manufacturing method, heat treating process, and the test and inspection methods.
Specific tests and test documentation, in addition to dimensional requirements, are specified for the forging manufacturer.The low pressure turbine rotor has the following inspections and tests conducted at the forging manufacturer's plant:
(1)A ladle analysis of each heat of steel for chemical composition is to be within the limits defined by the specification.
10.2-10TURBINE-GENERATOR WATTS BARWBNP-82 (2)Following preliminary machining and heat treatment for mechanical properties but prior to stress relief, all rotor diameters and faces are subjected to ultrasonic tests defined in detail by a Westinghouse specification which is similar to the requirements of ASTM A-418.
(3)After all heat treatment has been completed, the rotor forging is subjected to a thermal stability test defined by a Westinghouse specification which is more restrictive than the requirements of ASTM A-472.
(4)The end faces of the main body and the fillet areas joining the body to the shaft ends of the machined forging are subjected to a magnetic particle surface inspection as defined by ASTM A-275.
(5)After the bore of the rotor is finish machined, the bore is given a visual examination followed by a wet magnetic particle inspection defined in detail by a Westinghouse specification which exceeds the requirements of ASTM A-275.(6)Utilizing specimens removed from the rotor forging at specified locations, tensile, Charpy V Notch impact and FATT properties are determined following the test methods defined by ASTM A-370.In addition, after the rotor body is finished machined, the rotor surface is given a fluorescent magnetic particle examination as defined by a Westinghouse specification which is similar to ASTM E-138.The low pressure turbine rotor discs have the following inspections and tests conducted at the forging manufacturer's plant:
(1)The ladle analysis of each heat of steel is to be within the composition limits defined by the specification.
(2)After all heat treatment, rough machining and stress relief operations, the hub and rim areas of the completed disc forging are subjected to ultrasonic examinations. These ultrasonic tests are defined by a Westinghouse specification which exceeds the requirements of ASTM A-418.
(3)The tensile, Charpy V Notch impact and FATT properties are determined from specimens removed from the discs at specific locations. The test methods used for determining these mechanical properties are defined by ASTM A-370.In addition, after the discs are finish machined, the disc surfaces, except blade grooves, are given a fluorescent magnet ic particle examination as defined by a Westinghouse specification which is similar to ASTM E-138.After the preheated discs are assembled to the rotor body to obtain the specified interference fit, holes are drilled and reamed for axial locking pins at the rotor and disc interface. These holes are given a fluorescent penetrant inspection defined by a TURBINE-GENERATOR 10.2-11WATTS BARWBNP-82Westinghouse specification which is similar to ASTM E-165. Prior to shipping, each fully bladed rotor is balanced and tested to 120% of rated speed in a shop heater box.
10.2.3.5.2 High Pressure Turbine RotorThe high pressure turbine rotor for low temperature light water reactor applications has the same basic material composition as the low pressure rotors. This nickel-chromium-molybdenum-vanadium alloy steel forging is procured, processed, and subjected to test and inspection requirements the same as the low pressure rotor, which include:
(1)Ladle analysis (2)Ultrasonic tests (3)Magnetic particle inspection (4)Thermal stability test (5)Bore Inspection (6)Tensile and impact mechanical properties (7)Fluorescent magnetic particle inspection (8)Heater box and 120% speed test10.2.3.5.3 Preoperational and Initial Startup TestingThe complete turbine generator control system including the turbine overspeed protection system is given a thorough prestart check and initial startup test verification during the preoperational and hot functional tests and initial heatup of the plant. These tests are documented in Chapter 14.0.
10.2.3.6 Inservice Inspection 10.2.3.6.1 Turbine RotorsTo help guard against possible failure of low pressure nuclear st eam turbine discs, Westinghouse Electric Corporation has developed an ultrasonic inservice inspection method for these discs. The program includes methods and hardware for field inspection of LP turbine discs for incipient cracking located at the bore surface and particularly at the keyways.The inspection intervals recommended by Westinghouse and based on NRC criterion vary with the construction and makeup of each rotor (and discs). The recommended Westinghouse inspection intervals for the initial WBN rotors vary between 3.34 years and 4.65 years on the various LP rotors and are based on actual operating time. When the initial rotors are replaced or refurbished, the rotor disc inspection intervals will be either approximately every five years based on actual operating time or the Westinghouse inspection interval based on the NRC criterion, whichever provides the 10.2-12TURBINE-GENERATOR WATTS BARWBNP-92lesser inspection interval. In addition, if there is evidence of significant corrosion found during any of the low pressure turbine rotor inspections, Westinghouse will be consulted and the inspection intervals adjusted accordingly. If measurable cracks are detected, the inspection intervals will be adjusted after considering Westinghouse recommendations. The disc inspection will be performed by personnel that are expert and highly skilled in their field.
10.2.3.6.2 Turbine Overspeed ProtectionIn order to assure that the Turbine Overspeed Protection System (TOPS) continues to carry out its design function in a highly reliable manner, a rigorous program of inspecting, testing, maintaining, and calibrating the various parts of the TOPS has been developed. The development of this program has considered the recommendations of Westinghouse. Various aspects of the TOPS inspection program such as scope and frequency of test, inspections, and other pertinent items are described in the following paragraphs.The TOPS include the following major component groups: (a)Turbine valves which control or prevent steam admission into either the high pressure or low pressure turbines.(b)The control valve emergency trip, stop valve emergency trip, and autostop oil trip systems which include the mechanical overspeed trip, electrical overspeed trip, and the overspeed protection controllers (See Section 10.2.2 for additional details).The throttle valves, governor valves, reheat stop valves and reheat intercept valves will be tested and visually checked after each turbine startup and at intervals of approximately 3 months to verify complete freedom of valve stem travel. The interval of valve testing may be changed based on plant conditions or overall TVA power system conditions. For example, if equipment necessary to shut the unit down is inoperable, the valve testing would be postponed to avoid the potential for tripping the unit. Also, if the demand for power on the TVA system is large enough that the loss of a unit would create a shortage of power to the system, the testing would wait until more favorable conditions exist. The interval for testing turbine valves shall not exceed 1.25 times the required test interval without prior approval of the plant manager, and no more than two consecutive tests shall be deferred without the prior review and approval by the Plant Operations Review Committee (PORC). Extraction and moisture separator reheater (MSR) drain non-return valves will be tested monthly. Additionally, one or more of each valve type will be disassembled and inspected during outages with all throttle and governor valves being disassembled and inspected initially at least once every 39 operating months with the interval being reevaluated later if there are no significant valve problems or defects. All of the remaining valves (reheat stop, reheat intercept, and above non-return valves) will be disassembled and inspected at least once every 60 operating months (once every three refueling cycles). If during the inspection of one type of valve a problem or defect is noted, all similar valves will be disassembled and inspected. These inspections will consist of detailed dimensional TURBINE-GENERATOR 10.2-13WATTS BARWBNP-92and related checks to assure that critical clearances and fits are maintained with the manufacturer's recommendations.The overspeed trip oil device which provides an interface between the autostop oil trip system and the mechanical overspeed trip is tested at approximately monthly intervals. This device utilizes high pressure oil to force the overspeed trip weight outward against spring force until it strikes the trigger and actuates an overspeed trip. The above test simulates an actual overspeed trip by comparing the oil pressure at which the mechanism operates with previous test readings. No steam admission or control valves are actuated which allows on-line testing of this feature. This testing is also repeated following repair or adjustment to the turbine electrohydraulic control system.Additionally, during unit startup prior to synchronizing the unit, if the turbine remote and overspeed trips have not been tested during the previous six months of operation, the remote solenoid, the overspeed protection controller, the mechanical overspeed, and the backup electrical overspeed trips will each be actuated to verify proper turbine and valve action. If the unit operates continuously for periods longer than six months and there have been no significant problems with the overspeed trip weight mechanism, the above remote and overspeed tests will be deferred until the unit is shutdown and performed during the subsequent startup. The remote solenoid and overspeed trip tests will trip the turbine and close all throttle, governor, reheat intercept, and reheat stop valves. The overspeed protection controller trip test includes verification of closure of the turbine governor and reheat intercept valves.The monthly on-line test of the mechanical overspeed trip device and the six month off-line test of the turbine remote and overspeed trips will not be deferred for longer than 1.25 times the required test interval without the performance of an engineering evaluation and the review and approval of the PORC.Calibration and checks of TOPS overspeed protection circuits overspeed controller and components (speed sensors, including OPC and electrical trip sensors, pressure sensors, load sensors, reference signals, comparators, relays, solenoid valves, etc.) is performed during each refueling outage (approximately once every 18 months) or following major modifications or adjustments to this system. These calibrations and checks can only be performed safely with the unit off-line.
10.2.3.6.3 Other Turbine Protection FeaturesThere are other turbine protection features which serve to trip the turbine during abnormal operation (see Section 10.2.4 for a list of mechanical and electrical turbine trips). Inspections, tests, maintenance, and calibrations of these components will be based on Westinghouse recommendations.
10.2.4 EvaluationThe following operational occurences can be caused by operation of turbine, generator, or distribution system protection equipment:
(1)Turbine trip due to turbine abnormalities.
10.2-14TURBINE-GENERATOR WATTS BARWBNP-92 (2)Turbine trip due to generator abnormalities.
(3)Transients due to rapid load changes or system abnormalities.Turbogenerator protective trips that will automatically trip the turbine due to turbine (mechanical) and generator (electrical) abnormalities are tabulated below. Reactor trip and AMSAC signals will also automatically trip the turbine. (I)Automatic Turbine Trips Due To Turbine (Mechanical) Abnormalities (1)Low Bearing Oil Pressure Trip (2)Low Vacuum Trip (3)High Thrust Bearing Wear TripHigh Turbogenerator Vibration Trip (4)Low Differential Water Pressure Across Generator Stator Coils Trip (Alarm only below 15% power)
(5)High Stator Coil Outlet Water Temperature Trip (Alarm only below 15% power)(6)Low EHC Fluid Tank Level (7)Low Lube Oil Tank Pressure (8)Low EHC Fluid Pressure Trip (9)Low Auto Stop Oil Pressure Trip (10)111% Rated Speed Electrical Overspeed Trip (11)110% Rated Speed Mechanical Overspeed Trip (12)EHC dc Power Failure Trip (13)Loss of Both Main Feedwater Turbines Trip (14)Steam Generator High-High Level Trip (II)Automatic Turbine Trips Due To Generator (Electrical) Abnormalities (1)Generator Differential Current Trip (2)Generator Neutral Overvoltage Trip (3)Generator Time Overcurrent (Voltage Supervised) Trip (4)Generator Negative Sequence Trip (5)Generator Backup and Main Transformer Feeder Differential Trip TURBINE-GENERATOR 10.2-15WATTS BARWBNP-92 (6)Generator Loss of Field Trip (7)Generator Over-volts per hertz trip (8)Generator Reverse Power Trip (9)Unit Station Service Transformer A Overcurrent Trip (10)Unit Station Service Transformer B Overcurrent Trip (11)Main Transformer Sudden Pressure Trip (12)Main and Unit Station Service Transformers Differential Trip (13)Unit 1, 500 kV Bus 2, Section 3 Breaker Failure Trip (14)Unit 1, 500 kV Bus 2, Section 3 Differential Trip (15)Unit 2, 500 kV Bus 1, Section 1 Breaker Failure Trip (16)Unit 2, 500 kV Bus 1, Section 1 Differential Trip (17)1 and/or 2 Generator Breaker OpenThe analyses of the consequences of the most severe of these events with respect to reactor safety are discussed in Chapter 15.There can be any number of component or system operational abnormalities that can be postulated to produce a turbogenerator load transient. However, since the effects of such abnormalities can be no worse than a turbine or generator trip, these occurrences are not formally listed.Any noble gas activity in the secondary system as well as the particulate activity present due to moisture carryover from the steam generators enters the high pressure turbine.The subsequent activity entering the low pressure turbine is reduced due to the moisture separation that occurs between the exit of the high pressure turbine and the entrance to the low pressure turbines. Radiation monitors are installed to monitor steam generator blowdown and condenser vacuum pump exhaust flows for particulate and airborne radioactivity. Details of the radiological evaluation of the condener evacuation system are contained in Chapter 11.Activity levels in the turbine are expected to be very low and all necessary shielding is provided by the piping, turbine casing, and other components. If any additional shielding is required in local areas, it will be provided so that unlimited access to the turbine area is possible. Shielding design is discussed further in Section 12.3.2.The main steam stop (throttle) and control (governor) and reheat stop and interceptor valves are capable of fast closure upon receipt of a closure signal. Each of the four 10.2-16TURBINE-GENERATOR WATTS BARWBNP-92throttle valves is arranged with a paired governor valve and each of the six reheat stop valves is arranged in series with an interceptor valve.If the turbine unit should overspeed, the overspeed protection controller (OPC) will open two solenoid valves (FSV-47-26A and FSV-47-26B) and dump the control fluid from the control and interceptor valves (causing the valves to rapidly close) at 103% of rated turbine speed. If the turbine speed should continue to increase to 11%, the mechanical overspeed trip mechanism will actuate a hydraulic dump valve which dumps autostop oil to drain. Depressurization of the autostop oil system then causes FCV-47-27 to open and depressurize both the stop and control valve emergency trip fluid systems which causes all control, stop, reheat stop, and interceptor valves to trip close (see Figure 10.2-3). Concurrently with the above trip fluid action, an independent, redundant electrical trip signal is also generated when the autostop oil system is depressurized which energize FSV-47-24 and FSV-47-27 to independently depressurize both the stop and control valve emergency trip fluid systems and thus cause all of the above steam valves to trip closed (See Figure 10.2-1). In addition to the above mechanical overspeed trip, an independent electrical overspeed trip will also energize both of the above solenoid valves (FSV-47-24 and FSV-47-27) at 111% of rated speed to depressurize the autostop oil, and the stop valve emergency trip fluid, and thus trip all of the above steam valves closed.Redundancy in the overspeed protection system is assured by independent mechanical and electrical overspeed trips, a separate overspeed controller, redundant electrical trip circuitry, serial and parallel trip fluid systems, and double isolation in the steam systems. A single failure will not prevent the overspeed protection system from tripping the turbine. Since the electrical and mechanical overspeed trips are independent, only one of these trips need to function to trip the turbine. The electrical trip circuitry and the trip fluid systems are designed such that if the single failure occurred in these systems, the overspeed protection system will still perform its intended function. Isolation of either the stop valves or control valves upstream of the high pressure turbine and of either the reheat stop valves or intercept valves upstream of the low pressure turbines will prevent steam from entering the turbine and, consequently, limit the overspeed to within the acceptable range. Therefore, the single failure of a steam valve or any other component in the overspeed protection system will have no effect on the overspeed protection system performing its intended protection function.A turbine trip signal also generates an electrical trip signal which deenergizes the solenoid dump valves on the power assist non-return valves in the Number 1, 2, 3, and 4 extraction lines and the MSR drain lines. When the above solenoid dump valves are deenergized, a quick exhauster vents the air from the power assist non-return valve cylinder allowing a spring loaded piston to provide positive force to close the above non-return valves. Concurrently, the above turbine trip signal also activates a fluid operated air pilot valve, XDV-47-27 (see Figure 10.2-3). If the above solenoid dump valves fail to deenergize, this valve (XDV-47-27) will vent the air from the non-return valve cylinders causing the non-return valves to close. In either of the above cases, the non-return valves will close prior to flow reversal occurring in these extraction and TURBINE-GENERATOR 10.2-17WATTS BARWBNP-92MSR drain lines. Consequently, the above heaters and MSR drains cannot 'flash back' and cause or significantly contribute to a turbine overspeed situation.Since heaters 5, 6, and 7 are located in the condenser neck, physical piping arrangements and economic considerations prohibit the use of non-return valves in these extraction lines. However, anti-flash baffles in the heater shells (sized in accordance with the turbine manufacturer's recommendations) restrict the reverse flow from these heaters to a sufficiently low flow so that it cannot adversely affect turbine overspeed or thermally shock the LP turbine. REFERENCES
None 10.2-18TURBINE-GENERATOR WATTS BARWBNP-82THIS PAGE INTENTIONALLY BLANK Turbine-Generator10.2-19WATTS BAR WBNP-91Figure 10.2-1 Powerhouse Unit 1 Wiring Diagram Turbo-Generator Auxiliaries Schematic Diagrams
10.2-20Turbine-GeneratorWATTS BAR WBNP-89Figure 10.2-2 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System Turbine-Generator10.2-21WATTS BAR WBNP-89Figure 10.2-2 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A) 10.2-22Turbine-GeneratorWATTS BAR WBNP-91Figure 10.2-3 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System Turbine-Generator10.2-23WATTS BAR WBNP-89Figure 10.2-3 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont Sys (Sheet A) 10.2-24Turbine-GeneratorWATTS BAR WBNP-89Figure 10.2-4 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System Turbine-Generator10.2-25WATTS BAR WBNP-89Figure 10.2-4 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A) 10.2-26Turbine-GeneratorWATTS BAR WBNP-89THIS PAGE INTENTIONALLY BLANK MAIN STEAM SUPPLY SYSTEM 10.3-1WATTS BARWBNP-92 10.3 MAIN STEA M SUPPLY SYSTEM 10.3.1 Design BasesThe main steam supply system is designed to conduct steam from the steam generator outlets to the high pressure turbine and to the condenser steam dump system. This system also supplies steam to the feedwater pump turbines, an auxiliary feedwater pump turbine, moisture-separator reheaters, and the turbine seals.The main steam supply system includes self-actuating safety valves to provide emergency pressure relief for the steam generators and atmospheric relief valves to provide the means for plant cooldown by steam discharge to atmosphere if the turbine bypass (condenser steam dump) system is not available.The main steam supply system is designed to the classifications indicated on flow diagram Figure 10.3-1 and specified in Section 3.2.2.Pipe failures or malfunctions of any portion of the system have been considered and protection provided.System design assures that a postulated main steam line break coincident with a single active failure will not develop consequences outside the current plant design bases.
10.3.2 System Description 10.3.2.1 System DesignThe main steam supply system is shown schematically in Figure 10.3-1. The control and logic diagrams for this system are presented in Figures 10.3-2 through 10.3-7. The steam is conducted from each of four steam generators through the containment and out through the main steam line isolation valves. Each steam generator outlet nozzle contains an internal multiple venturi type flow restrictor which, in the event of a steam line break, will act to limit the maximum flow and the resulting thrust.The steam generator safety valves and atmospheric relief valves are located upstream of the main steam line isolation valve. There are five safety valves per steam generator. The steam generator safety valves provide emergency pressure relief in the event that steam generation exceeds steam consumption. The safety valve settings are provided in Table 10.1-1.There is one atmospheric relief valve per steam generator. Each valve has a minimum capacity and a maximum capacity based upon steam generator pressure.These atmospheric relief valves provide the means for plant cooldown by steam discharge to the atmosphere if the condenser steam dump is not available. The valves will also provide a means of steam generator pressure control if the condenser steam dump is not available, and will thus preclude unnecessary lifting of steam generator safety valves. Pressure setting of these valves is based on a slow and rapid rate of steam generator pressure increase.
10.3-2MAIN STEAM SUPPLY SYSTEM WATTS BARWBNP-92The maximum actual capacity at a steam pressure of 1185 psig of any single safety or atmospheric relief valve does not exceed a flow of 970,000 lb/hr. This limits steam release if any one valve is inadvertently stuck open.Steam supply for the auxiliary feedwater pump turbine is provided by one connection each on two of the main steam lines upstream of the main steam line isolation valves. This arrangement provides both redundancy and dependability of supply.Each of the two main steam chests includes two turbine stop valves and two turbine control valves. The steam lines are cross-connected upstream of the turbine stop valves. The cross connections provide both an entrance to the condenser steam dump system and a distribution manifold for the turbine stop valves. The turbine is described in Section 10.2 and the turbine bypass system is described in Section 10.4.
10.3.2.2 Material Compatibil ity, Codes, and StandardsAll pressure containing components in the main steam supply system are in accordance with applicable codes or standards. Applicable codes, standards, and design conditions (pressure and temperature) are shown in Table 10.3-1.The materials for piping and fittings in the TVA Class B Portion of the system are impact tested as required by ASME Section III for Class 2 components.
10.3.3 Design EvaluationThe portion of the main steam supply system designed to TVA Class B requirements is Category I seismically qualified (see Table 3.2-2a). This portion of the system is protected from internal missiles as discussed in Section 3.5.1. Redundant electrical power and air supplies to critical components assure reliable system operation and safe shutdown capability. Redundant steam supply connections are provided for the turbine-driven auxiliary feedwater pump.The safety valves provide 100% relieving capacity to protect the system from overpressure. The capacity provided by the atmospheric relief valves is over and above the safety valve capacity. The atmospheric relief valves, which have a set pressure slightly lower than the safety valves, prevent unnecessary opening of the safety valves.Four atmospheric relief valves have been provided per unit (one per steam generator).
Bidirectional steam line isolation valves are installed to protect the plant during the following accident situations:
(1)Break in the steam line piping either inside or outside the containment.
(2)Break in the feedwater piping downstream of the last check valve before the steam generator.
(3)Steam generator tube rupture.
MAIN STEAM SUPPLY SYSTEM 10.3-3WATTS BARWBNP-92The main steam line isolation valves are 32-inch wye type bidirectional globe, straight through flow, air to open, spring to close. These valves are capable of closing within 6 seconds after receipt of a closure signal on a 'high-high' containment pressure signal, low steamline pressure in any steamline, or high steamline negative pressure rate in any steamline as shown in Figures 7.3-3, Sheet 3, and 10.3-5.For accident situation No. 1, inside containment, the steam generator associated with the damaged line discharges completely into the Containment. The other steam generators would act to feed steam through the interconnecting header to reverse flow into the damaged line and then release into the Containment. The approximate 6-second closing time for the isolation valves in the other three lines will limit containment pressure rise below design pressure. If any of these three valves fail to close, protection is provided by closure of the valve in the broken line. Hence, redundancy is provided to allow for a single failure of any one isolation valve.For accident situation No. 1, outside containment, the four main steam isolation valves act similarly to prevent the uncontrolled blowdown of more than one steam generator, even after the failure of any one main steam isolation valve. This prevents any of the system transients from exceeding those described in Chapter 15.For accident situation No. 2, the isolation valve closure time requirement is not as critical as it is for situation No. 1. Hence, the isolation valve arrangement is satisfactory for requirements resulting from this situation. Valve redundancy to shut off flow in the forward direction is not required.For accident situation No. 3, valve closure time is not limiting. A fast acting valve is not required nor is valve redundancy. The isolation valve serves to limit the total amount of primary coolant leakage during the shutdown period by isolating the damaged steam generator after pressure is reduced below steam generator shell side design pressure.Inservice inspection requirements are given in Chapter 3.See Section 3.11 for Environmental Design of the main steam supply system.
10.3.4 Inspection and Testing RequirementsPerformance tests of individual and periodic performance tests of the actuation circuitry and mechanical components assures reliable performance.Surveillance test requirements are given in Chapter 16.
The main steam supply system complies with ASME Section XI.
Preoperational test requirements are given in Chapter 14.
10.3.5 Water Chemistry 10.3.5.1 PurposeWater chemistry control in the secondary systems such as the steam generator steam side, feedwater, and condensate for various operating modes and conditions has been 10.3-4MAIN STEAM SUPPLY SYSTEM WATTS BARWBNP-92established to minimize corrosion and damage to the steam generators and to minimize fouling of steam generator heat transfer surfaces.10.3.5.2 Feedwater Ch emistry SpecificationsThe plant chemistry program establishes the steam generator steam side and feedwater chemistry specifications for normal power operations. This program is based on the latest EPRI and Westinghouse PWR secondary water chemistry guidelines.Experience with steam generators using an ammonia and/or ethanolamine all volatile treatment (AVT) method has indicated that corrosion and fouling have been effectively
controlled.
10.3.5.3 Operating Modes (1)Power Operation:During normal power operation the feedwater and secondary side steam generator chemistry is maintained in accordance with the plant chemistry program. Prompt action is taken to correct any problem indicated by transient excursion outside these guidelines. Feedwater chemistry is maintained within the specified guidelines by providing make-up water of adequate purity and continuously supplying hydrazine, ethanolamine (ETA) and ammonia to the condensate system. Independent hydrazine,ammonia, ETA, ammonium chloride and boric acid systems inject their respective solutions into the condensate system downstream of the condensate demineralizer. These chemical addition systems are shown in Figure 10.3-9.Steam generator steam side chemistry during power operations is controlled by steam generator blowdown (Section 10.4.8) and the presence of residual ammonia, ETA and hydrazine from the feedwater.(a)Blowdown. The blowdown system removes contaminants (particulates and dissolved solids) introduced into the steam generators by the feedwater system or fission products that may leak into the steam generators via steam generator tube leak. The quality of water in the steam generators is controlled by maintaining a minimum blowdown rate of 5 gpm per steam generator. At full power the maximum flow rate is 65.5 gpm per steam generator. In the event of primary to secondary leakage or condenser in-leakage, higher blowdown rates may be employed to help keep the steam generator chemistry within limits. Blowdown may help to control radioactive iodine present in the event of primary to secondary leakage.(b)Ammonia, ETA, ammonium chloride, boric acid and hydrazine. The ammonia, ETA and ammonium chloride* supplied by the secondary chemical feed system are transported through the main feedwater lines to the steam generator and are carried along with steam through the MAIN STEAM SUPPLY SYSTEM 10.3-5WATTS BARWBNP-92piping, feedwater heaters, and turbines. Hydrazine is supplied by the secondary chemical feed system and reacts with any oxygen in the feedwater. Consequently, corrosion is inhibited in these components due to the pH control afforded by ammonia. Boric acid* is supplied by the secondary chemical feed system to the condensate system to buffer the solution within the steam generator. These additional systems are shown in Figure 10.3-9.
(2)Cold Shutdown/Wet Layup:Hydrazine and ammonia are supplied by the secondary chemical feed system to the steam generator wet layup recirculation system for use during wet layup of the steam generators.
(3)Auxiliary System Support:The hydrazine and ammonia additions are capable of being fed to the auxiliary boiler feedwater pump suction. Thus, corrosion inhibitors are available to the auxiliary boiler system.
10.3.5.4 Effect of Water Ch emistry on the Radioactive I odine Partition CoefficientAs a result of the basicity of the secondary side water, the radioiodine partition coefficients for both the steam generator and the air ejector system are increased (i.e., a greater portion of radioiodine remains in the liquid phase). However, the lack of data on the exact iodine species and concentrations present prevents a quantitative determination of the coefficient increase for these systems. The partition coefficients used for site boundary dose calculations due to secondary side releases are those given in NUREG-0800, Revision 2. For the steam generators, a partition coefficient of 0.01 was used. 10.3.6 Steam and Feedwa ter System Materials 10.3.6.1 Fracture ToughnessRequirements of the ASME Boiler and Pressure Vessel Code,Section III, Articles NC-2310 and ND-2310 of the summer of 1973 Addenda for fracture toughness for ferritic materials are met in all Class 2 and 3 components. Impact testing is not specified for the auxiliary feedwater piping because the pipe wall thicknesses do not exceed 5/8-inch.
10.3.6.2 Materials Selection and FabricationCode class pressure boundary materials in this system are included in Appendix I to ASME Code Section III.Austenitic stainless steel pressure boundary components may be used in these systems. Therefore, this system conforms to Regulatory Guides 1.31, 1.36, and 1.44.Topical Report TVA-NQA-PLN89 contains TVA's position for the cleaning and handling of Class 2 and 3 components in accordance with Regulatory Guide 1.37.
10.3-6MAIN STEAM SUPPLY SYSTEM WATTS BARWBNP-92Cleaning and cleanness of fluid systems and components are in accordance with ANSI N45-2-1-1973, or later.Since there are no low-alloy pressure retaining materials used in the steam and feedwater systems, compliance with Regulatory Guide 1.50 is not required.With the exception of Regulatory Position C-1 and C-2.a, this system complies with Regulatory Guide 1.71, "Welder Qualification for Areas of Limited Accessibility."REFERENCES
None MAIN STEAM SUPPLY SYSTEM 10.3-7WATTS BARWBNP-63Table 10.3-1 Main Steam Supply System Applicable Codes, Standards, and Design ConditionSteam Generator Shella. Design pressure, 1185 psig
- b. Design temperature, 600
°Fc. Code, ASME BOILER AND PRESSURE VESSEL Code,Section III, Division 1, Class 1 Main Steam Piping
- a. Design pressure, 1185 psig
- b. Design temperature, 600
°Fc. TVA Class B - Code, ASME Boiler and Pressure Vessel Code,Section III, Class 2TVA Class H - Code, ANSI B31.1, Code for Pressure PipingMain Steam Isolation Valves
- a. Design pressure, 1185 psig
- b. Design temperature, 600
°Fc. Code, ASME Boiler and Pressure Vessel Code,Section III, Class 2Main Steam Safety Valves
- a. Design pressure, 1185 psig
- b. Design temperature, 600
°Fc. Code, ASME Boiler and Pressure Vessel Code,Section III, Class 2Main Steam Atmospheric Relief Valves
- a. Design pressure, 1185 psig
- b. Design temperature, 600
°Fc. Code, Boiler and Pressure Vessel Code, section III, Class 2 10.3-8MAIN STEAM SUPPLY SYSTEM WATTS BARWBNP-89N/A Not Applicable.Comments: 1This table is based on EPRI PWR Secondary Water Chemistry Guidelines (Revision 3) and on Westinghouse Guidelines for Secondary Water Chemistry as required for site specific chemistry program. Actual chemistry specifications are based on the EPRI PWR Guidelines (Revision 3) and on Westinghouse Guidelines.
2Actual limits to be controlled by station pH program.
3These are diagnostic parameters and do not constitute limits.Table 10.3-2 Ethanolamine AVT Steam Generator Side and Feedwater Chemistry Specifications Limits 1Normal Power OperationsCHEMISTRY PARAMETERFEEDWATERBLOWDOWNpH 25°C>8.8 2>8.5 2Cation Conductivity mhos/cm 25
°C<0.2 3<0.8Sodium, ppb<1 3<20Chloride, ppbN/A
<20Hydrazine, ppb
>20N/ADissolved Oxygen, ppb
<5N/AFe, ppb<5N/ASulfate, ppbN/A
<20Ammonium ChlorideAs required to maintain control parameters N/A Cu, ppb<1N/ABoric acid, ppmN/A5-10 Blowdown Rate, gpm/SGN/AAs required to maintain control parameters.
MAIN STEAM SUPPLY SYSTEM 10.3-9WATTS BAR WBNP-0Table 10.3-3 Deleted by Amendment 43 10.3-10MAIN STEAM SUPPLY SYSTEM WATTS BAR WBNP-0Table 10.3-4 Deleted by Amendment 43 Main Steam Supply System10.3-11WATTS BAR WBNP-89Figure 10.3-1 Powerhouse Unit 1 Flow Diagram - Main and Reheat Steam
10.3-12Main Steam Supply SystemWATTS BAR WBNP-82Figure 10.3-2 Powerhouse Unit 1 Electrical Control Diagram - Main Steam System Main Steam Supply System10.3-13WATTS BAR WBNP-82Figure 10.3-3 Powerhouse Unit 1 Electrical Control Diagram - Main Steam System 10.3-14Main Steam Supply SystemWATTS BAR WBNP-89Figure 10.3-3 Powerhouse Unit 1 Electrical Control Diagram Main Steam System (Sheet A)
Main Steam Supply System10.3-15WATTS BAR WBNP-89Figure 10.3-4 Powerhouse Unit 1 Electrical Control Diagram Main Steam System 10.3-16Main Steam Supply SystemWATTS BAR WBNP-89Figure 10.3-4a Powerhouse Unit 1 Electrical Control Diagram Main Steam System Main Steam Supply System10.3-17WATTS BAR WBNP-89Figure 10.3-5 Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat Steam 10.3-18Main Steam Supply SystemWATTS BAR WBNP-89Figure 10.3-6 Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat Steam Main Steam Supply System10.3-19WATTS BAR WBNP-89Figure 10.3-7 Powerhouse Units 1& 2 Electrical Logic Diagram Main and Reheat Steam 10.3-20Main Steam Supply SystemWATTS BAR WBNP-89Figure 10.3-8 Electrical Unit 1 Electrical Logic Diagram Safety Injection System Main Steam Supply System10.3-21WATTS BAR WBNP-89Figure 10.3-9 Powerhouse Units 1 & 2 Flow Diagram Feedwater Treatment Secondary Chemical Feed 10.3-22Main Steam Supply SystemWATTS BAR WBNP-89THIS PAGE INTENTIONALLY BLANK OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1WATTS BARWBNP-89 3410.4 OTHER FEATURES OF STEAM AND POWER CONV ERSION SYSTEM 10.4.1 Main Condenser 10.4.1.1 Design BasesThe design basis for the main condenser is to provide a heat removal rate of at least 7.789 x 10 9 Btu/hr per unit for the steam system by condensing the steam from the turbine exhaust. There are three pressure zones with back pressures of 1.63 (Low Pressure, LP), 2.38 (Intermediate Pressure, IP), and 3.40 (High Pressure, HP) inches of mercury, absolute. For purposes of guarantees and calculations, the steam flow is considered to be equally divided between these three zones. During a cold startup, the condenser must also deaerate the initial inventory of water contained within the condensate and feedwater system.
10.4.1.2 System DescriptionTo provide sufficient capability to meet the functional requirements stated in Section 10.4.1.1, the main condenser has the following specifications:Tubes:Total surface area, sq. ft.824,000Circulating water quantity, gpm410,000 Circulating water temperature70.5 (yearly average), FCirculating water temperature rise, F38Number of shells1Number of passes1Overall length, ft.115Size, inches OD-Birmingham Fire Gauge (BWG)1-20 Material90-10 Cu-Ni Number27,410Cleanliness, %95 Duty, 10 9 Btu/hr7.789 10.4-2OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-89Overall dimensions:Design pressure:Steam Flowrate to condenser, lb/hrBypass system:The condensers are of conventional design, having a rubber belt type expansion joint in the neck and the required impingement baffles to protect the tubes from incoming drains and steam dumps. A condenser seal through-arrangement maintains the rubber belt expansion joints flooded with seal water for minimizing any air inleakage through the expansion joint. The hotwell of the condenser has a water storage Length, ft.137.5Height, ft62.5Width, ft.27.0Shell, psig25Hotwell, psig30 Waterboxes, psig72Hotwell storage (normal), gallons56,000Oxygen content of condensate, cc/liter0.005Maximum guaranteed condition8,100,000Valves-wide-open condition8,500,000Flow, lb/hr6,057,000Pressure (at nozzle), psig250Enthalpy, Btu/lb1191.3Air inleakage, scfm24 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-3WATTS BARWBNP-89capacity equivalent to approximately 3-1/2 minutes of full-load operation. Provisions have been made for mounting three, 1/3 capacity, low pressure extraction feedwater heaters in the neck of each condenser pressure zone.The main condenser system will produce back pressures of 1.63, 2.38, and 3.40 inches mercury, absolute for the three zones, when operating at rated turbine output with 70° cooling water and 95% clean tubes. A continuous tube cleaning system is provided to keep the condenser operating at peak performance.The condenser is designed to remove dissolved gases from the condensate, limiting oxygen content to 0.005 cc per liter at any load during normal operation. During startup, the initial inventory of water contained within the condensate and feedwater system is deaerated using steam piped from the auxiliary steam system along with that steam flowing through the turbine exhaust from the shaft sealing system. A recirculation line is run from immediately upstream of the feedwater isolation valves to a perforated pipe running across the condenser hotwell (see Section 10.4.7). Recirculated condensate is sprayed across the condenser while being deaerated with auxiliary steam sprayed up through it from steam sparger nozzles located in a header arrangement in the hotwell.The condenser can accept a bypass steam flow of approximately 40% of maximum guaranteed steam generator flow, without exceeding the turbine high back pressure trip point or an exhaust hood temperature of 170°F with a circulating water temperature of up to 96°F. This bypass steam dump to the condenser is in addition to the normal duty expected with a throttle flow of 60% of maximum guaranteed steam generator flow. The flow is distributed to the three pressure zones of the condenser by twelve, 10-inch perforated pipes which are designed to ensure that no high velocity steam jet can impinge on the tubes. Supports for these perforated pipes were designed for the dynamic loading which the bypass flow will impose.The correct secondary cycle water inventory is maintained by the automatic dumpback-makeup condensate system. The level controller, which is sensitive to the hotwell level, positions the dumpback valve or makeup valve (to or from condensate storage) as required to maintain the hotwell water level within present limits.Separate makeup and return lines further provide the capability to clean up or maintain the condensate storage tank water quality during startup by continuously recirculating through this piping and the condensate system demineralizers, if required.Each condenser is equipped with a sampling system that continuously monitors the cation conductivity. A given increase in cation conductivity at one or more of the nine sampling points after unit startup or during steady-state operation may indicate condenser cooling water inleakage. The nine sampling points were located in such a manner that the operator could determine (1) which tube bundle is leaking, (2) where the leak is located within the three condenser pressure zones, and (3) whether the leak is in the area of the tube-to-tube sheet joint, and if so, which of the four tube sheets is leaking.
10.4-4OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-89Since each unit's condenser waterbox is divided into two sections, one section can be isolated during unit operation if the other section is found to be leaking. Each unit has the capability of operating at a reduced power level while one-half of its condenser waterboxes are isolated. By isolating one-half of the condenser waterboxes at a time, repairs and/or plugging of defective tubes can be accomplished within the action times specified for each action level in the Secondary Water Chemistry Program.Any impurities in the condenser cooling water which are introduced into the condensate stream by condenser inleakage are removed by the condensate demineralizer system (CDS). The CDS is capable of maintaining the condensate and feedwater quality within the specified limits during a continuous inleakage of up to 1.5 gpm (total inleakage into either or both unit condensers). When the condenser inleakage is greater than 1.5 gpm, the leak must be located as soon as possible, the effected condenser section isolated and the leak repaired. The time required to detect and locate condenser inleakage and to isolate a condenser section for corrective action is 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> maximum. Each unit's CDS is capable of maintaining the condensate and feedwater quality for 6 hours6.944444e-5 days <br />0.00167 hours <br />9.920635e-6 weeks <br />2.283e-6 months <br /> with condenser inleakage of up to 20 gpm.The condenser tubes are alloy 706, 90-10 Cu-Ni, which is a corrosion resistant material. The corrosion resistance of copper and its alloys is primarily due to the formation of a cuprous oxide film on the surface of electro-chemical reactions. The particular advantages of alloy 706 are (1) the resistance to ammonia attack (steam side) is excellent and (2) it has the best combination of bio-fouling and pitting resistance (water side) of any of the copper-nickel alloys.Also, the condenser tube cleaning system (AMERTAP) will provide additional protection against pitting attack by keeping sediment and other particulate matter cleaned from the inside tube surfaces.10.4.1.3 Safety EvaluationThe inventory of radioactive contaminants in the main condensers is a function of the percentage of defective fuel rods, the escape rate coefficients, the steam generator primary-to-secondary leak rate, and the steam generator and condenser partition. Primary-to-secondary leakage has the potential for supplying measurable quantities of hydrogen. However, for large primary-to-secondary leakage rates (1.0 gpm/unit), the rate of hydrogen release would be less than 0.01 scfm. This rate is small when compared to the normal design condenser inleakage of 24 scfm with vacuum pump operation. Thus, hydrogen entering the condenser is effectively exhausted via the condenser evacuation system and the potential for hydrogen buildup is negligible.The condenser could become ineffective because of the loss of some or all of its cooling water and/or excessive air inleakage. Either of the above conditions would cause the condenser pressure to increase, and upon reaching the Westinghouse recommended limits the units would be manually or automatically tripped, in accordance with operations instructions.The residual heat during the above conditions is removed by dumping steam to the condenser through the turbine bypass valves when the condenser pressure is below OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-5WATTS BARWBNP-896.5-inches Hg absolute or at least one circulating water pump is operating. At a condenser pressure of 6.5-inches Hg absolute or higher or when no circulating water pumps are operating, the turbine bypass valve will automatically trip closed if open (and be prevented from opening if closed). The residual heat will then be removed by dumping steam to the atmosphere through the power operated atmospheric relief valves and/or the ASME code safety valves.There is no interface between the loss of main condenser vacuum and the MSIVs because the turbine bypass valves provide isolation of the steam source.The Turbine Building does not contain any Engineered Safety Features (ESF); hence, no ESF would be affected by failure of a condenser shell, or hotwell, or by loss of condenser vacuum. The condenser is in its own pit, with a free volume much greater than the hotwell/condensate water volume. The effects of the failure of a condenser waterbox or circulating water piping are discussed in Section 10.4.5.
10.4.1.4 Inspection and TestingThe condenser has been tested for leaks by completely filling the shell with condensate. The waterboxes have been leak tested by filling them with raw water. Manways provide access to water boxes, tube sheets, lower steam inlet section, shell, and hotwell for purposes of inspection, repair or tube plugging.
10.4.1.5 InstrumentationSufficient level controllers, level switches, pressure switches, temperature switches, etc., are provided to permit personnel to conveniently and safely operate the condenser system. The condenser instrumentation is included in the control diagrams for the condensate system, Figures 10.4-9 through 10.4-11A.10.4.2 Main Condenser Evacuation System 10.4.2.1 Design BasesThe design basis for the main condenser evacuation system is the capability to create and maintain condenser back pressure at 1.0-inch mercury, absolute by removing noncondensable gas and air inleakage. The design evacuation rate is 24 scfm. The condenser evacuation system piping is designed in accordance with ANSI B31.1 1973 Edition through Summer 1973 Addenda.
10.4.2.2 System DescriptionThe main condenser evacuation system is shown in Figures 10.4-7, 10.4-9, 10.4-10, and 10.4-12. These figures show the flow, control, and logic diagrams, respectively, for the condensate system. To provide sufficient capability to meet the functional requirements as stated in Section 10.4.2.1, the main condenser evacuation system 10.4-6OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-89has been designed with the following specifications which meet the requirements of the Heat Exchange Institute for steam surface condensers:The vacuum pumps are two stage, liquid ring type pumps. Two pumps, operating in parallel, are adequate for the removal of the maximum expected air inleakage of 24 scfm. The third vacuum pump is arranged to start automatically on increasing condenser back pressure.10.4.2.3 Safety EvaluationOne of the three vacuum pumps is a backup unit. This unit automatically starts when the condenser high pressure zone back pressure increases to approximately 4.6-inches Hg absolute. Should the back pressure continue to increase (because of inadequate air removal capability), the turbine would trip and, consequently, cause a reactor trip. The turbine trip would automatically occur at approximately 6 to 12 inches Hg absolute.Details of the radiological evaluation of the condenser evacuation system are contained in Chapter 11.
10.4.2.4 Inspection and TestingThe operating characteristics for each vacuum pump, throughout the operating range, have been determined by factory tests. A flowmeter is provided with each vacuum pump for leakage measurement. Periodic readings of these flowmeters will indicate whether or not the air inleakage to the condenser is within acceptable limits. These readings will also indicate the effectiveness of the operating vacuum pumps.Preoperational test requirements are given in Chapter 14.
10.4.2.5 InstrumentationThe necessary pressure and temperature switches are provided to automatically start the standby vacuum pump or shut down a malfunctioning (vacuum) pump. Two radiation monitors are provided for added environmental protection. A low-range monitor gives early indication of primary to secondary leakage and a high range monitor annunciates in the Main Control Room when the radiation level reaches limits Type of evacuating equipmentMechanical vacuum pumpNumber of vacuum pumps, per unit3Air capacity at suction pressure of 1-inch Hg absolute, per pump at normal operation,scfm 15Air capacity at suction pressure of 15-inch Hg absolute, per pump at startup, scfm800 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-7WATTS BARWBNP-86discussed in the WBN ODCM (at this point, the plant goes into controlled shutdown for correction action). The instrumentation for this system is shown on the electrical control diagram for the condensate system, Figure 10.4-10.10.4.3 Turbine Gland Sealing System 10.4.3.1 Design BasesThe turbine gland sealing system is designed to seal the main turbine shafts and valve stems and the main feed pump turbine shafts using steam from upstream of the turbine stop valves. The sealing can be accomplished automatically with steam supply of pressure 185 psia or more, and manually with steam supply pressure between 108 psia and 185 psia. Steam from the auxiliary boiler is supplied to the seals during startup. The turbine gland sealing system is designed in accordance with ANSI B31.1 1973 Edition through Summer 1973 Addenda.
10.4.3.2 System DescriptionThe turbine gland sealing system is shown on Figure 10.4-1.The purpose of the gland steam sealing system is to prevent leakage of air into the turbine casing, and conversely, prevent the leakage of steam into the turbine room when the turbine casing is pressurized.The system utilizes labyrinth type seals. Each seal is equipped with two annular chambers which are located among the packing rings. The chamber nearest the turbine casing is maintained at a pressure of approximately 16 psia by the admission of sealing steam or the controlled leak-off of higher pressure steam. The outer chamber is maintained at a slight vacuum (approximately 3- to 5-inches water) by the gland steam exhauster system. The vacuum causes the sealing steam to leak outward and mix with any inward leaking air. This mixture flows to the gland steam condenser where most of the steam is condensed and returned to the secondary cycle. The noncondensibles are forced by the exhauster through piping to the outside of the Turbine Building.10.4.3.3 Safety EvaluationSince this is a PWR, radioactive steam in the steam seal system is of very small consequence. The exhauster discharge is piped outside of the building to prevent the possible accumulation of radioactive particles in a stagnant building area.In the event one exhauster is lost, the ineffective exhauster will isolate and the spare one will automatically start. Should both exhausters fail, seal steam will leak into the turbine room. If the steam seal supply fails, excess air leakage will probably trip the turbine because of high condenser back pressure. A number of safety valves and rupture diaphragms are installed on this system to protect the various components against high pressure. The radiological effects of this system are negligible during normal operation. A radiological evaluation of the loss of the system is presented in Chapter 11.
10.4-8OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-89 10.4.3.4 Inspection and TestingThis equipment will be tested by the vendor in accordance with the various applicable code requirements.
10.4.3.5 InstrumentationSufficient instrumentation has been provided to satisfy all system functional requirements and to permit safe, convenient operation by plant personnel. System performance is constantly monitored by measuring gland steam exhauster vacuum and supply header pressure.10.4.4 Turbine Bypass System 10.4.4.1 Design BasesThe turbine bypass system is designed to reduce the magnitude of nuclear system transients following large turbine load reductions by dumping throttle steam directly to the main condenser, thereby creating an artificial load on the reactor.The turbine bypass system has the following functional requirements:
(1)Permit a direct bypass flow to the main condenser of 40% of rated turbine flow, thereby allowing a turbine step load reduction of 50% without a resultant reactor trip.
(2)Permit turbine trip (accompanied by reactor trip) from full load without opening steam generator safety valves.
(3)Provide plant flexibility during operation by allowing turbine load changes in excess of the base NSSS design, without reactor trip.
(4)Provide controlled cooldown of the NSSS.
(5)Assist in achieving stable startup of the plant.The turbine bypass system piping is designed in accordance with ANSI B31.1 1973 Edition through Summer 1973 Addenda.
10.4.4.2 System DescriptionThe turbine bypass system and its instrumentation and controls are shown on Figures 10.3-1 through 10.3-7, which are the flow, control and logic diagrams for the main and reheat steam.The capability for meeting the functional requirements of Section 10.4.4.1 has been provided by designing the equipment to the following specifications:Number of valves - 12Flow per valve - 532,170 lb/hr OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-9WATTS BARWBNP-91The steam leads from the four steam generators are cross-connected immediately upstream of the turbine stop valves. Piping is run from this header to the 12 turbine bypass valves and then to the condenser. Eight valves discharge into the low pressure zone of the condenser, three valves discharge into the intermediate pressure zone, and one valve discharges into the high pressure zone. This arrangement helps to prevent exceeding of the differential backpressure/temperature limits between low pressure turbines during steam dump operation.The normal operating mode is a comparison of T-average (the average temperature of the reactor coolant into and out of the steam generator - indication of reactor power level), to the turbine impulse chamber pressure (indication of turbine load). When the reactor power level exceeds the analog of the turbine load, the turbine bypass valves will open in proportion to the mismatch.The alternate mode of operation is steam pressure-control. This can be either automatic or manual (direct use of valve loading signal) control and is normally used during unit startup and shutdown.The bypass valves are built in accordance with ANSI Standard B16.5. All piping in the steam bypass system is in accordance with ANSI Standard B31.1.10.4.4.3 Safety EvaluationLow-low reactor coolant system average temperature will block the signals which supply air to the individual turbine bypass valves. A manual bypass (momentary) of this interlock is provided only for the three turbine bypass valves, which are designated as "cooldown valves."Loss of the control air supply to the diaphragms of the bypass valves will prevent the valves from opening, or, if the valves are open, will trip them closed. Loss of control air can result from indication of inadequate condenser circulating water flow rate, high condenser pressure, low-low T-average, or from failure of certain system components.
In the event of loss of control air, the steam generators will still be protected during all transients by the ASME code safety valves. Steam generator cooldown capability will be available through use of the power operated relief valves (atmospheric dump).Main steam pressure at valve inlet (for above flow) - 900 psigMaximum flow per valve at 1185 psig inlet pressure - 970,000 lb/hrTime to open (full stroke)3 secondsFull stroke modulation20 seconds Failure positionClosed 10.4-10OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-91Inadvertent or accidental opening of any one bypass valve during power operation will not subject the reactor coolant system to an uncontrolled cooldown.Failure of the turbine bypass system can result in discharge of steam to the atmosphere through the steam generator safety valves. If tube leaks are present prior to the incident, some radioactivity accumulated in the steam generator shell side water would be discharged through the safety valves. This radioactivity will be well within limits established by 10 CFR 100. Failure of the turbine bypass system will not affect, directly or indirectly, any engineered safety feature system.
10.4.4.4 Inspection and TestingThis equipment will be tested in accordance with the various code requirements. Periodic tests will be performed to assure that the system remains capable of its functional requirements. Inservice inspection in accordance with ASME Section XI is not required.Preoperational test requirements are given in Chapter 14.
10.4.4.4.1 InstrumentationSufficient instrumentation has been provided to permit this system to:
(1)Satisfy all its functional requirements, (2)Protect the reactor (from low-low T-average), (3)Protect the turbine (from high condenser pressure).The instrumentation for this system is shown on Figures 10.3-5 and 10.3-7, the logic diagrams for the main and reheat steam.
10.4.5 Condenser Circ ulating Water SystemThis section covers the design and safety related aspects of the condenser circulating water (CCW) system, including the circulating water pumps, the circulating water conduits, the main condenser, the hyperbolic natural draft cooling towers, the yard holding pond, and the desilting basin. The primary function of the CCW system is to provide cooling water to the condensers for the main steam turbines. The system provides an efficient means of dissipating waste heat from the power generation cycle into the ambient surroundings while meeting all applicable chemical and thermal effluent criteria. Because of the capacity and convenience, the blowdown from the CCW system is used to dilute and dispense the low-level radioactive liquid wastes from the waste condensate pump, cask decontamination pump discharges, and, on occasion, steam generator blowdown and radioactively contaminated regeneration wastes from the condensate polishing demineralizer system (CPDS).
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-11WATTS BARWBNP-91 10.4.5.1 Design Basis (1)The CCW system will provide for each plant unit a flow of 410,000 gpm to the main steam turbine condensers. The main condenser flows result in a maximum temperature rise of 38°F for the circulation water through the condensers in the process of receiving 7.789 x 10 9 Btu/hr of waste heat per unit. This water flow is a sufficient quantity to condense the steam at an optimum main condenser back pressure and to dissipate all rejected heat.
(2)The CCW system provides a means of meeting all applicable water thermal criteria by dissipating the waste heat directly to the atmosphere by means of a single hyperbolic natural draft cooling tower for each unit. Some waste heat may be utilized as a heat source by commercial facilities which could be located adjacent to the power plant.(3)The CCW system provides for dilution and dispersion of low-level radioactive liquid wastes. The upper limits on the activity levels are discussed in Section 11.2.
10.4.5.2 System DescriptionThe flow diagram for the CCW system is shown in Figures 10.4-2 and 10.4-3. The system control and logic diagrams are shown in Figures 10.4-4 through 10.4-6. A single closed loop CCW system is employed for each of the two units. The system is unitized so that the cooling tower, conduits, circulating water pumps, and main condenser of each unit are independent of those of the other unit. The CCW pumping station is an independent structure located in the yard between the Turbine Building and the cooling towers. Four pumps for each unit are provided in this pumping station to operate in parallel and circulate water from the cooling tower cold water basin, through the condenser, and back to the heat exchanger section of the cooling tower.The eight condenser circulating water pumps are of the electric-motor-driven, vertical, dry pit, single-stage, double-suction, centrifugal, volute type. Each pump has a capacity of 102,500 gpm at a design head of 103 feet such that each group of four pumps supplies the full flow requirements of one generating unit. System required head is 98 feet. Adequate positive pressure is maintained on the pump suction by the available static head between the normal water level in the cooling tower basin, elevation 730.0, and the centerline elevation of the pump suction, elevation 715.25.The main condenser is of the single shell, triple pressure type with a divided water box, as described in Section 10.4.1. An Amertap condenser tube cleaning system is provided for automatic continuous cleaning of the condenser tubes during normal operation.Tandem, metal expansion joints are provided on both inlets and both outlets of the main condenser to accommodate the thermal expansion of the condenser shell and tubes resulting from the differing temperatures encountered during various modes of 10.4-12OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-91operation. A motor-operated butterfly valve is located in each inlet and outlet line to the condenser. These valves provide for isolation of either half of the condenser and the related expansion joint or tube cleaning system.Each of the two hyperbolic natural draft, counterflow cooling towers is designed to reject the full-load waste heat of a single unit main condenser to the atmosphere by evaporation as the CCW passes through the film-type heat exchange section. The cooling towers are designed to cool the circulating water to 73.5°F based on a mean annual design wet bulb temperature of 52.3°F and a mean annual design dry bulb temperature of 57.0°F. The normal maximum cold water temperature is 92.0°F.A portion of the waste heat could be used in the future as a heat source for a proposed Waste Heat Park by diverting a part of the CCW system flow from the hot water supply to the cooling towers via piping and valves which are now installed to avoid precluding such future waste heat usage. All CCW flow diverted would be returned to the CCW system either through the hot water supply to the cooling tower or into the cold water basin of the cooling tower.Blowdown water is extracted from the discharge flume of each cooling tower and is normally returned directly to the reservoir through a system of multiport diffusers. The rate of flow of blowdown will be such that the dissolved solids within the CCW system will be maintained at a level of approximately twice the concentration in the reservoir. The blowdown rate is determined by the height of the water level in the flume over the crest of a blowdown weir; therefore, it is directly related to the control of the makeup flow. Blowdown is continuously discharged to the reservoir during normal operation of the circulating water system as long as the river flow rate is not below 3500 cfs. The river flow past the plant is determined by the measurement of flow release through the hydro units of Watts Bar Dam. The flow rate through a single hydro unit at minimum operating lake level is 3500 cfs, which is the minimum flow that can be accurately determined. Whenever river flow drops below 3500 cfs, it becomes necessary to withhold CCW blowdown to avoid violation of thermal or chemical discharge standards. Under this situation the blowdown will continue to be discharged from the cooling towers; however, the diffusers will be isolated and the blowdown will be diverted to the yard holding pond. This pond will serve as a storage area for the blowdown until such time as the river flow again becomes sufficient to accept the discharge. The duration of low river flow should never exceed 12 hours1.388889e-4 days <br />0.00333 hours <br />1.984127e-5 weeks <br />4.566e-6 months <br /> during which time less than half the 190 acre-feet volume of the pond would be required for storage of blowdown. Upon resumption of sufficient river flow, the blowdown from the two towers and the water stored in the holding pond will be discharged into the river through the diffuser. The diffuser system has been designed to provide the proper dilution of the discharge into the river for the various combinations of two unit operation and draw down of the holding pond, while remaining within the limits of all applicable effluent standards.Whenever blowdown water is being discharged to the river, the blowdown serves as the source of dilution flow for the discharge from the plant radioactive waste disposal system and for radioactively contaminated regenerative waste (if it is within the OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-13WATTS BARWBNP-91 discharge specification described in Section 10.4.6). Refer to Section 11.2 for a detailed description of the liquid waste management systems. The cooling tower blowdown system will also serve as an alternate source for disposal of blowdown from the steam generators as described in Section 10.4.8.Discharge of radioactive waste into the cooling tower blowdown is discontinued when either the blowdown flow rate is not sufficient for proper dilution or when blowdown is diverted to the yard holding pond.Evaporation, drift, and blowdown losses from the system are replaced by the ERCW discharge, sewage plant effluent, and raw cooling water (RCW) discharge, as required. To enable the raw cooling water system to be utilized to the fullest extent, a bypass line with modulating valve is provided from the RCW supply to RCW discharge headers. This line will permit that portion of RCW system flow in excess of the RCW component requirements to bypass the Turbine Building and serve as additional makeup to the CCW system. Refer to Sections 9.2.1, and 9.2.8, for additional discussion of the cooling tower makeup.Chemical additives other than intermittent biocide injection (see Section 9.2.1.6) for biological control will not be required since cooling water concentration factors will normally be held to about 2. The water in Chickamauga Reservoir at the Watts Bar site normally shows a slight corrosive nature, and corrosion inhibitors are added to minimize corrosion rates.
Chemicals will be periodically injected into the CCW system as necessary to prevent organic fouling. When chemicals are introduced into the CCW system, it is injected into the CCW conduits on the suction side of the CCW pumps. Provisions are made to comply with the requirements of t he National Pollutant Discharge Elimination System (NPDES) permit.All water discharged into the CCW system, including initial filling and makeup, comes from the river via the ERCW and RCW systems. Provisions made in the ERCW and RCW to control the introduction of Asiatic clams will also prevent their introduction into the CCW loop. Refer to Sections 9.2.1 and 9.2.8 for a description of these provisions.10.4.5.3 Safety EvaluationThe Cooling Towers, Condenser Cooling Water Pumping Station, pumps and motors, and conduits are not required to be designed to Seismic Category I, tornadic wind, or maximum flood requirements, since they are not required for safe shutdown of plant. The Cooling Towers are located such that the towers' structural failure due to a seismic event, a tornado, or any other natural phenomenon could not damage any safety-related structure, system, or component.If a rupture of the CCW system were to occur in the Turbine Building, such as failure of the tandem, metal expansion joints, redundant flood level instruments located in the condensate drain tank pump area (floor elevation, 666.0) would alarm in the Main Control Room.
10.4-14OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-91If the CCW system completely drained into the Turbine Building (taking no credit for non-qualified features to terminate the flow), the Service Building would partially flood, but the water level in the Turbine and Service Buildings would not exceed plant grade.Makeup to the CCW system is provided from the RCW system and the ERCW system. If water from these sources was not terminated, the water level in the Turbine and Service Buildings could eventually reach plant grade. If the water reached plant grade it would have access out of the Turbine Building into the yard.All penetrations and passageways from the Turbine or Service Buildings to the Auxiliary or Control Buildings are sealed up to elevation 729.0 (plant grade elevation plus 1-foot) in the Service and Turbine Buildings. This requirement applies to all doorways, electrical penetrations, and mechanical piping penetrations. Also, there is no equipment essential to plant safety located either in the Turbine or Service Buildings. Consequently, water from a CCW system rupture cannot endanger any safety-related equipment, including essential electrical systems. Figure 1.2-5 shows the personnel passageways below elevation 729.0 that connect the Turbine and Service Buildings to the Control and Auxiliary Buildings. Piping of any system which conveys flow (makeup) to the heat rejection system has provisions to prevent back flow of the condenser circulating water into any area where flooding of safety-related components would result from a failure of the system providing the flow.
10.4.5.4 Inspection and TestingAlthough not required from a safety standpoint, the CCW system has undergone hydrostatic and performance tests prior to system operation to ensure the adequacy of the system to meet operational requirements. Once the plant becomes operational, routine visual inspection of the system components and instrumentation should be sufficient to verify continued operability.
10.4.5.5 Instrument ation ApplicationSince low level radioactive liquid waste from the waste disposal system, the condensate polishing demineralizing system, and, at times, the steam generator blowdown are discharged into the Cooling Tower blowdown, provisions are made to isolate these discharges when adequate dilution does not exist or upon high radiation signal. Specifically, a flow element is provided in the CCW blowdown line immediately upstream of the diffusers. If there is not at least 20,000 gpm passing through the blowdown line or if the waste source exceeds a predetermined high radiation level setpoint, based on dilution, valves in the discharge lines from the three waste sources are automatically closed. (See Sections 10.4.6, 11.2, and 11.5).As described in Section 10.4.5.2, a signal of less than 3500 cfs is flowing through the hydro units of the upstream dam will result in cessation of blowdown discharge to the river. This same signal will also close the valves in the waste disposal system and steam generator blowdown discharge lines in order to preclude the possibility of discharging radioactive waste in the yard holding pond.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-15WATTS BARWBNP-91 10.4.6 Condensate Polish ing Demineralizer System 10.4.6.1 Design Bases - Power ConversionThe function of the condensate polishing demineralizer system (CPDS) is to remove dissolved and suspended impurities from the secondary system. The CPDS removes corrosion products which are carried over from the turbine, condenser, feedwater heaters (after startup), and piping. The removal of impurities and corrosion products in the secondary system reduces corrosion damage to the secondary system equipment. The CPDS also removes impurities which might enter the system in the makeup water, and removes radioisotopes which are then carried over to the secondary cycle in the event of a primary-to-secondary steam generator tube leak. The CPDS will also be used to remove impurities which enter the secondary system due to condenser circulating water tube leaks. The continuous steam generator blowdown flow may be processed through the CPDS in normal operation, or it may be discharged when the radioactivity level is low. The blowdown will be treated by the CPDS when radioactivity levels exceeding release limits determined in accordance with ODCM are detected in this stream.The CPDS will polish condensate before startup and restarts. During this mode the steam generator is isolated from the feedwater. This will assure that the feedwater quality is acceptable before steam generation begins. Before feedwater is introduced into the steam generator, the CPDS demineralizer service vessel effluent quality will be such that the Feedwater Chemistry Specification, as shown in Table 10.3-2, can be met.The CPDS has the capability of polishing the full flow of condensate up to a maximum flow of 17,000 gpm per reactor unit. The CPDS demineralizer service vessel design temperature is 160°F and the design pressure is 300 psig. The pressure drop across the CPDS demineralizer service vessels does not normally exceed 60 psi. When this pressure differential across the vessels is exceeded, the major part of the condensate flow will automatically bypass the demineralizer.
10.4.6.2 System DescriptionThe CPDS for each power generation unit co nsists of six mixed-bed demineralizer service vessels; five in service and one in standby. The system also includes an external regeneration facility, shared between the demineralizer service vessels of the two generating units.The basic regeneration system consists of a resin separation/cation regeneration tank, anion regeneration tank, and resin storage tank. The concentrated chemicals used in regeneration are supplied from the acid and caustic storage tanks.Additional equipment is provided in the regeneration system to promote efficiency in the process. A hot water tank supplies hot dilution water at the caustic mixing tee. An ammonium hydroxide tank and a pump are provided to inject ammonium hydroxide into the resin separation/cation regeneration tank prior to and during regeneration.
10.4-16OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-91A chemical reclaim feature is provided to promote chemical economy and reduce regenerant wastes by reducing the amounts of fresh regenerant chemicals required for resin regeneration. This feature consists of an acid reclaim tank and two pumps and a caustic reclaim tank and two pumps. This feature permits the reclamation of up to 50% of the latter portion of the regenerant chemicals applied for use as the first portion (reclaim chemical application) of the next regeneration. The first portion of the regenerant chemicals that are not reclaimed, and the high conductivity rinse water containing regenerant chemicals flow to the batch neutralization tank or, alternatively, to the nonreclaimable waste tank. Both the neutralization tank and nonreclaimable waste tank are provided with the capability of adjusting the Ph of the regenerant chemical waste. If the inventory of these tanks is radioactive, it may be discharged to the cooling tower blowdown if the radioactivity level is within specification; otherwise, it is evaporated and the evaporator bottoms (concentrates) are pumped to the radwaste facility for subsequent packaging. If the inventory of these tanks is not radioactive, it is pumped to the turbine building sump and subsequently discharged through the diffuser pond or, alternately, it is discharged to the Cooling Tower blowdown. The wash, rinse, and resin sluicing waters of low conductivity are collected in two high crud tanks. If the inventory of the high crud tanks is not radioactive, it is pumped to the Turbine Building sump and subsequently discharged through the diffuser pond or, alternately, it is discharged to the cooling tower blowdown if both the suspended solids and radioactivity levels are within discharge specification; otherwise, it is pumped to the radwaste facility for subsequent treatment. Flow diagrams for the demineralizer service vessels, regeneration equipment and waste handling equipment are shown in Figures 10.4-36A, 10.4-36B and 10.4-36C, respectively.The CPDS demineralizer service vessels and all regeneration equipment are located within the Turbine Building. Each set of six demineralizer service vessels is arranged in three shielded compartments (two to a compartment) and dedicated to a plant unit.
All regeneration vessels and chemical reclaim tanks are arranged in individual compartments. The hot water tank is also in the Turbine Building. The acid and caustic storage tanks are located in a separate structure near the Turbine Building.The tanks in the CPDS are rubber-lined to prevent corrosion except the hot water tank (Keysite lined), the acid storage tank (unlined), and ammonium hydroxide tank (unlined). CPDS tanks are closed and are designed and fabricated in accordance with the ASME Code for Unfired Pressure VesselsSection VIII, 1974 edition.The CPDS is not a safety-related system and is not required for the orderly shutdown of the reactor. The Turbine Building housing the CPDS equipment is a nonseismic structure; piping, piping hangers, and equipment in the CPDS are nonseismic. The system piping is in accordance with American National Standard Institute B31.1.The CPDS demineralizer service vessels for each unit are arranged in parallel and are supplied by the condenser hotwell pumps via the inlet header. An outlet header collects the effluent from the demineralizer service vessels and supplies suction flow to either the condensate booster pumps or demineralized condensate pumps (see Section 10.4.7.1). The bypass valve is located across the influent and effluent headers OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-17WATTS BARWBNP-91in parallel with the demineralizer service vessels. Outlet piping from each service vessel is equipped with a resin trap.The CPDS demineralizer service vessels operate in either of three modes as determined by the position of the bypass valve and the service vessel inlet and outlet valves.(1)Mode 1 - Full flow polishing (bypass valve closed), will be the normal operating mode during the automatic control of the unit's demineralizer service vessel bypass valve.
(2)Mode 2 - Throttle bypass (bypass valve partially open), will be the operating mode during automatic control when the pressure differential across the demineralizer service vessel influent and effluent headers exceeds 60 psid. In this mode, the major part of the condensate flow will be bypassed around the demineralizer service vessels. Only a minimum flow will be processed through the demineralizer service vessels which is enough to maintain the resin beds in a compact, standby condition.
(3)Mode 3 -Full bypass (bypass valve fully open), will be the operating mode in the event the CPDS experiences loss of control air and/or electrical failure.The CPDS bypass valve will normally be operated under automatic control. Override is provided for manually positioning the bypass valve in the 'open,' 'close,' and 'throttle' positions. Automatic bypass protects the demineralizer service vessels from excessive pressure drop. The bypass valve may be manually placed in the throttle bypass position when the influent condensate water quality is such that the Feedwater
Chemistry Specifications, as given in Table 10.3-2, can be maintained without processing the condensate through the CPDS demineralizer service vessels. The bypass valve may be manually placed in the full bypass position (and the demineralizer service vessel inlet valves closed) when the inlet condensate temperature exceeds 130°F in order to protect the functional characteristics of the ion exchange resins. Continued operation is dependent upon influent condensate water quality.10.4.6.3 Safety EvaluationRadionuclides are released to the secondary system when there is a steam generator tube leak. The radionuclides have essentially no effect on the resin ion exchange capacity. Also, filtered suspended solids do not affect ion exchange capacity.
Although the radionuclide concentrations have no effect on resin capacity, potential activity levels in the demineralizer service vessels and associated regeneration equipment make it necessary to shield the CPDS equipment.Liquid radwaste is processed by the waste disposal system. Chapter 11 describes the radioactivity level and removal of radioactive material from the CPDS.
10.4-18OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-89 10.4.6.4 Inspection and TestingThe CPDS undergoes a preoperational test prior to startup (refer to Chapter 14). After startup and during shutdowns, each vessel in the system can be separately isolated for testing and visual inspection.The CPDS is designed so that all demineralizer service vessels, regeneration equipment, and most valves can be individually isolated from the system if testing or inspection is required, with no curtailment or interruption of power generation. Isolation valves on inlet and outlet of demineralizer service vessels and system bypass valves can be tested and inspected during shutdown if required.
10.4.6.5 InstrumentationInstrumentation and controls are provided to perform the following functions:
(1)Measure, indicate, and record condensate conductivity in the influent header, the effluent line of each demineralizer service vessel, and the effluent header.High conductivity downstream of a particular demineralizer service vessel indicates resin exhaustion, and high influent conductivity indicates condenser tube leakage. Conductivity elements in the effluent header provide an indication of system efficiency and total condensate water quality.High system conductivity as measured in the effluent header and high conductivity at all other points are annunciated at the CPDS local control panel.(2)Measure pressure differential between influent and effluent headers, and open the valve bypassing the demineralizer service vessels on high differential signal when the bypass valve is under automatic control.
(3)High differential pressure across the demineralizer service vessels and opening of the bypass valve are annunciated on the CPDS local control panel.(4)Measure and indicate condensate temperature at the influent header. High influent condensate temperature is alarmed at the CPDS local control panel.
(5)Measure, record, and indicate flow rates through indivi dual demineralizer service vessels. Flow rates through each demineralizer service vessel indicate extend of crud loading.
(6)Measure, indicate, and record the dissolved silica content in the effluent of each demineralizer service vessel and in the influent condensate header.High level silica content is annunciated at the CPDS local control panel.
(7)Annunciate at the CPDS local control panel high pressure differential across each resin trap.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-19WATTS BARWBNP-82 (8)Measure, indicate, and record the dissolved sodium content in the effluent of each demineralizer service vessel, in the influent condensate header, and in the effluent condensate header. High level sodium content is annunciated at the CPDS local control panel.
10.4.7 Condensate an d Feedwater Systems 10.4.7.1 Design BasesThe condensate and feedwater systems are designed to supply a sufficient quantity of feedwater to the steam generator secondary side inlet during all normal operating conditions and to guarantee that feedwater will not be delivered to the steam generators when feedwater isolation is required. A complete discussion of feedwater isolation is included in Chapter 15.The condensate and feedwater systems pumps take condensate from the main condenser hotwells and deliver water to the steam generators at an elevated temperature and pressure. These systems are capable of delivering 15,216,620 lb/hr of 441.6°F water to the steam generators for the guaranteed throttle flow to the turbine.
10.4.7.2 System DescriptionThe flow diagrams for the condensate and feedwater systems are presented in Figures 10.4-7 and 10.4-8. Figures-10.4-9 through 10.4-15 and 10.4-17 and 10.4-18 provide the control and logic diagrams for this system.The ability to meet the design requirements of Section 10.4.7.1 is provided by the following equipment (per unit):
(1)Hotwell Pumps Number - 3Manufacturer - Borg-Warner Corporation, Byron Jackson Pump DivisionType - VMT, four stages, single suction, vertical processDesign Point - 6700 gpm, 600 feet headMotor Manufacturer - Parsons-Peebles, Ltd.
Motor Design - 1250 hp, 1180 rpm, 6600 V, 3 phase, 60 Hz, vertical, constant speed (2)Condensate Booster Pumps Number - 3Manufacturer - Borg-Warner Corporation, Byron Jackson Pump DivisionType - DVDSR, single stage, double suction, double volute centrifugalDesign Point - 9000 gpm, 680 feet headMotor Design - 1750 hp, 3584 rpm, 6600 V, 3 phase, 60 Hz, horizontal, constant speedMotor Manufacturer - Parsons-Peebles, Ltd.
10.4-20OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82 (3)Main Feedwater Pumps Number - 2Manufacturer - Borg-Warner Corporation, Byron Jackson Pump Division Type - HRD, single stage, double su ction, double vo lute centrifugalDesign Point - 23,600 gpm, 1890 feet head Service Conditions -Pump suitable for continuous service to deliver up to 17,630 gpm at 402.3°F against a total head of approximately 2012 feet at 5012 rpm, while operating with a minimum net positive suction head of 200 feet.
(4)Standby Main Feedwater Pumps Number - 1Manufacturer - Borg-Warner Corporation, Byron Jackson Pump DivisionType - DVS, single stage, double suction, double volute, centrifugal Design Point - 6100 gpm, 1890 feet head Motor Design - 3700 hp, 3584 rpm, 6600 V, 3 phase, 60 Hz horizontal constant speedMotor Manufacturer - Parsons-Peebles, Ltd.
(5)Demineralized Condensate Pumps Number - 3Manufacturer - Ingersoll-Rand CompanyType - A, single stage, single suction, end suction process Design Point - 6700 gpm, 150 feet head Motor Manufacturer - WestinghouseMotor Design - 350 hp, 1770 rpm, 460 V, 3 phase, 60 Hz, horizontal, constant speed (6)Main Feedwater Pump Turbine (see also Table 10.1-1)
Number - 2Manufacturer - Westinghouse Electric Corporation Type and Speed - EMM-32AIN, Multi-stage, dual inlet, 5460 rpm Throttle Pressure - LP steam, 146 psig HP steam, 995 psigThrottle Temperature - LP steam, 513°FHP steam, 546°F Back Pressure - 6.9 in of Hg absoluteNumber of Stages - 6Extraction Points - None OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-21WATTS BARWBNP-82Rated Horsepower - 12,200 hp (7)Main Feedwater Pump Turbine Condenser Number - 2Manufacturer - Westinghouse Electric CorporationTube Material - ASME SA688, 304 SSTChannel Design pressure* - 350 psi Channel Design temperature* - 259°F (8)Gland Steam Condenser Number - 1Manufacturer - Westinghouse Electric CorporationTube Material 10 Cu-Ni Channel Design pressure* - 400 psig Channel Design temperature* - 125°F (9)Feedwater HeatersNumber - 21 (3 streams of 7 heaters)Manufacturers - Nos. 1 and 2: Yuba Heat Transfer Corp.Nos. 3 and 4: Foster Wheeler Energy Corp.
Nos. 5, 6, and 7: McQuay-Perfex Incorp.Type - Closed, horizontal, U-tubeTube Material - 304 SST*Channel side design conditions only tabulated here. For shell side design conditions, see Section 10.4.9.Heater No.Channel Design Pressure* (psi)Channel Design Temp* ( F) 12000480 22000440 3725380 4725300 5350300 6350300 7350300 10.4-22OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-89Feedwater heaters are designed in accordance with HEI standards for closed feedwater heaters and the ASME Boiler and Pressure Vessel Code,Section VIII. All piping and valves from the condenser hotwell to the feedwater isolation valve are designed in accordance with ANSI B31.1, while the remainder of the feedwater system is designed in accordance with the ASME Boiler and Pressure Vessel Code,Section III, Class 2.The system boundaries extend from the condenser hotwell to the inlet of the steam generator. Condensate is taken from the main condenser hotwells by three vertical, centrifugal, motor-driven hotwell pumps. The head imparted by these pumps is sufficient to provide adequate NPSH to the main feedwater pumps during unit startup and low load operation.A signal that NPSH to the main feedwater pumps is approaching a preset minimum level (signal provided by differential pressure between main feed pump suction and No. 2 feedwater heater shell at approximately 50% unit guaranteed load) automatically starts the three horizontal, centrifugal, motor-driven condensate booster pumps. These pumps, when operating in series with the hotwell pumps, are capable of delivering required flow with sufficient NPSH to the main feedwater pumps under all normal operating conditions as long as the condensate demineralizers are being by-passed.However, when the condensate demineralizers are in service at higher loads, additional pumps are needed to provide sufficient NPSH to the main feedwater pumps. The demineralizer condensate pumps provide this capability for all normal operating conditions by manually starting at approximately 80% of full feedwater flow.The condensate demineralizers will act to keep condensate water quality within the limits of Section 10.3.5 for the steam generator feedwater. During normal operation, all flow except for 5500 gpm is bypassed around the demineralizer. This small flow acts to keep the resin beds compacted so that their filtration capability is not momentarily unavailable in the event of a condenser tube leak and the subsequent rapid switch from the bypass mode to full flow condensate demineralization. Conductivity recorders in the hotwell detect the tube leakage and automatically close the demineralizer bypass valve on high conductivity. In addition to this automatic switch, the demineralizers may be manually placed on full flow operation either during startup or normal operation, as water chemistry requirements dictate.Adequate NPSH at the main feed pumps suction is ensured by manually starting the demineralized condensate pump at 80% plant load.The two turbine driven, variable speed main feedwater pumps are capable of delivering feedwater to the four steam generators under all expected operating conditions.* Feed pump speed is automatically adjusted to meet system demands. The feed pump speed control system consists of three inter-related parts:
(1)The setpoint calculators sum the four steam flows, provide the lag on setpoint changes, and contain the basic scaling adjustments.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-23WATTS BARWBNP-82 (2)The differential pressure controller compares the steam header pressure, feedwater header pressure, and the calculated setpoint to determine the speed signal required.
(3)The feed pump manual/auto stations provide the operator with the flexibility of choosing various operating modes. The unit operator will have the options to operate either or both pumps on manual speed control to base load his operation, to operate one pump on manual with the other automatically swinging with plant load changes, or to let both pumps swing with the load changes.At high power levels, i.e., above 22% feedwater flow on increasing power and down to 14% feedwater flow on decreasing power, feedwater flows through each main feedwater line into the lower section of each steam generator. Flow is controlled automatically by adjustment of a feedwater control valve in each line. Each main feedwater control valve position is determined by a three element controller in which steam generator steam flow and feedwater flow are the primary input control variables and steam generator level is a secondary control signal. At low power levels, i.e., below 22% feedwater flow on increasing power and below 14% feedwater flow on decreasing power, each main feedwater control valve and feedwater isolation valve are closed, and for each steam generator, feedwater is routed through a small bypass line directly into the upper section of the steam generator. The required steam generator water level is maintained by automatically controlling the position of the feedwater bypass control valve in each feedwater bypass line.-------------------
- Normally, startup will be accomplished using the electric motor driven, standby main feedwater pump.The feedwater bypass control valve position is determined by a controller that uses steam generator water level, reference water level, and nuclear power as control input signals. These valves are also used to maintain a tempering flow into the upper section of the steam generator during normal power operation when feedwater is flowing through the main feedwater lines into the lower section of each steam generator.Switchover from the feedwater bypass lines to the main feedwater lines on increasing power is manually performed. On decreasing power, changeover from the main feedwater lines to the bypass lines is achieved by manually switching on the automatic bypass controller. Manual control of the main feedwater control valves or feedwater bypass control valves is possible in any mode of operation.Both the main feedwater control valves and the feedwater bypass control valves are pneumatically operated and are designed to fail close on loss of air.
10.4-24OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82During plant startup, the low-load automatic feedwater control system is used up to approximately 22% of full feedwater flow. Before switching to the lower feedwater nozzle, the feedwater in the line to the lower (main) nozzle must be warmed to not less than 250°F in order to minimize the potential for waterhammer (steam bubble collapse) in the steam generator preheater. Waterhammer could occur if cold feedwater were injected into the steam generators. Feedwater line warming is accomplished by flushing the cold water in the line downstream of the main feedwater regulator valves through the deaeration line to the condenser. This forward flush operation is accomplished at 20 to 22% feedwater flow by flowing hot feedwater through this flow path to the condenser until temperature instrumentation in the feedwater line upstream of the junction with the deaeration line indicates a temperature greater than 250°F. During forward flush, the isolation valves upstream of each main feedwater regulator valve are closed and the bypass around each of these valves is opened. This procedure will cause the pressure upstream of the closed main feedwater isolation valves to be lower than the steam generator pressure. Consequently, no cold water in the main feedwater line can leak into the steam generator and cause waterhammer (bubble collapse) in the steam generator.The remaining portion of the main feedwater line from the junction with the deaeration line to the steam generator is purged of cold water by flowing hot water from the steam generators back through the main feedwater lines to the condenser via the deaeration line. This backflush operation is continued until temperature instrumentation in the main feedwater line downstream of the junction with the deaeration line indicates a temperature greater than 250°F. Backflush flow is limited to 80,000 lb/hr per steam generator to prevent steam bubbles in the steam generator from entering the feedwater lines which could cause waterhammer from the bubbles collapsing, due to cooling.The forward/back flush operation is accomplished manually by the operator using a single switch in the control room. The switch aligns the feedwater valves in forward flush mode then in back flush mode. Status lights are located in the control room so that the operator knows the position of the valves and knows when feedwater lines for each steam generator are warmed.The systems normally operate at full load with three hotwell, three condensate booster and two main feed pumps in service. However, with all feedwater heaters in service and all heater drains being pumped forward, 100% load can be maintained with only two hotwell and two condensate booster pumps running. Unit load can be continuously maintained at 85% guaranteed load with one main feed pump and the standby main feed pump in operation.Heating of the condensate and feedwater is accomplished by passing it through a series of closed heat exchangers. A summary of secondary cycle heat exchangers used to preheat the condensate and feedwater are described below:
(1)Gland Steam Condenser - This exchanger condenses the steam leak off from all turbine shaft seals and removes the non-condensibles (the result of shaft inleakage of air) from this steam. An externally connected, weighted check OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-25WATTS BARWBNP-89valve is provided to ensure minimum required flow through the condenser at low condensate flow conditions and to minimize pressure drop through the condenser during high condensate flow conditions.
(2)Main Feed Pump Turbine Condensers - Each main feed pump turbine is equipped with an individual surface type condenser. Control valves in the inlet and outlet condensate piping to these condensers provide the ability to isolate condenser if its associated drive turbine is rendered inoperative and to force 100% condensate flow through the operating condenser, thus allowing maximum power operation of the remaining drive turbine.
(3)Steam Generator Blowdown Heat Exchangers - Two steam generator blowdown heat exchangers (dual shell first stage and single shell second stage) are provided to continuously subcool blowdown such that it may be processed and returned to the secondary cycle or discharged via a site drain header (see Section 10.4.8).
(4)Feedwater Heaters - Three parallel strings (A, B, and C) of heaters, each consisting of three low pressure feedwater heaters, three intermediate pressure feedwater heaters, and one high pressure feedwater heater are provided. The heaters are numbered from 1 to 7, with the highest pressure heater designated as No. 1. Motor operated isolation valves are provided at the inlet to each No. 7 heater and the outlet of each No. 5 heater, the inlet to each No. 4 heater and the outlet of each No. 2 beater, and at the inlet and outlet of each No. 1 heater. High-high water level in a heater shell will cause the isolation of the group of heaters in the stream in which the high-high level occurred (either the 5, 6, and 7 heaters, 2, 3, and 4 heaters, or No. 1 heater in either the A, B, or C streams). With all pumps in service, a complete string of 7 heaters can be out of service and full unit load can be maintained.Tubes for all heaters are 304 SST. Tube-to-tube sheet joints in all feedwater heaters are expanded and welded.Minimum flow bypasses are provided for equipment protection. The condensate system minimum flow bypass is located immediately upstream of the No. 7 heaters. The bypass control valve receives its operating signal from the station flow nozzle located upstream of the gland steam condenser. The valve plug's position is modulated to maintain at least 5500 gpm flow through the flow nozzl
- e. This flow is sufficient to protect the hotwell pumps and demineralized condensate pumps, to provide adequate cooling water to the gland steam condenser, and to keep the demineralizer beds compacted at all times.The condensate booster pumps are protected by automatic recirculation control (ARC) valves. The checking elements of these valves are calibrated to actuate pilot valves which, in turn, open or close the recirculation valves to maintain a minimum of flow of 1500 gpm through each pump.The feedwater system has a minimum flow bypass line originating downstream of each feedwater pump to permit direct recirculation back to the main condensers. The 10.4-26OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82bypass control valve modulates in a manner similar to the condensate minimum flow valve and maintains a minimum flow of 4000 gpm (at rated speed) through each operating, turbine driven main feed pump. However, for extended periods of operation at recirculation flows, due to high vibration signature caused by high speed and low flow, the pump can be throttled to approximately 3300 rpm at which time flow should be approximately 2650 gpm and vibration signature would be acceptable. Minimum flow for the standby main feed pump when it is operating is 1500 gpm (vendor evaluation has determined that minimum flows as low as 1100 gpm are acceptable). Piping is also provided around the main feed pumps to allow filling the steam generators without operating the main feed pumps.An additional recirculation line is provided from each main feedwater loop, between the feedwater control valve and motor operated isolation valve, back to the main condenser. This deaeration line is used to deaerate and improve the water chemistry of the condensate and feedwater systems during startup using the hotwell pumps; and to provide a path for warming flow during the warming of the main feedwater piping loops prior to switching from the upper feedwater bypass loops.10.4.7.3 Safety EvaluationThe feedwater system from the steam generator back through the motor operated isolation valves and check valves is a safety system and is designed to TVA Class B.
This portion of the feedwater system is an integral part of the auxiliary feedwater system.Feedwater flow to the steam generators must be interrupted within 6.5 seconds of initiation of a feedwater isolation signal (the direct result of high-high level in a steam generator, high flood level detection in either the South or North MSV vault rooms, safety injection signal, or a reactor trip coincident with reactor coolant low Tavg). This isolation, accompanied by a reactor trip, is accomplished by closure of redundant valves in the piping to each steam generator. The feedwater regulator valves will close within 6.5 seconds. The signal to initiate closure of these valves is available from both power Train A and power Train B. The Class 2, motor operated containment feedwater isolation valves will close within 6.5 seconds. The isolation valves associated with steam generator Nos. 1 and 3 are connected to power Train A while those associated with steam generator Nos. 2 and 4 are connected to power Train B. Closure of the startup valves bypassing the feedwater regulator valves is also guaranteed within 6.5 seconds. Each feedwater bypass isolation valve can be closed by Train "A" or Train "B" of the feedwater isolation signal. Each feedwater bypass regulator valve can be closed by a train A signal for steam generator Nos. 2 and 4 or train B signal for steam generator Nos. 1 and 3. The feedwater bypass regulator valve is a backup to the feedwater bypass regulator isolation valve.For additional protection, a feedwater isolation signal also trips the standby main feedwater pump and both main feedwater pumps (from either Train A or Train B), all condensate booster pumps and all demineralized condensate pumps. Trips of these pumps will reduce the condensate system pressure to a pressure less than the 400 psig and initiate an orderly shutdown of the remainder of the condensate and feedwater system pumps, except the hotwell pumps which are left on line to facilitate OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-27WATTS BARWBNP-82restart of the unit. On a feedwater isolation trips of both main feedwater pumps, at least one main feedwater pump condenser is left unisolated. This allows the condensate system to continue to operate with hotwell pumps running on the recirculation to condenser mode with flow through the gland steam condenser and
demineralizers. With all heater drains being pumped forward, the condensate demineralizer in the bypass mode, and all heater banks in service, each hotwell pump and each condensate booster pump is capable of delivering 50% of the unit guaranteed flow while imparting sufficient head to the feedwater to meet all system demands. With the demineralizer in the full flow mode, two of the three demineralized condensate pumps are sufficient to meet all system demands. Thus, loss of any one of the three condensate booster pumps and/or any one of the demineralized condensate pumps simply results in flow being transferred to the remaining operational pumps with the reactor coolant system being unaffected.With the No. 7 heater drains cascading to the main condenser and all heater banks in service, loss of any one hotwell pump and/or one condensate booster pump will not affect the reactor coolant system, because the unit will still be capable of maintaining 100% guaranteed load. Cascading of the No. 3 heater drains initiates logic which prevents unit operation above the 85% power level. Thus, the loss of a hotwell pump and/or a condensate booster pump during this mode of operation will not affect the reactor coolant system.If the unit is operating below 67% guaranteed load, loss of one main feed pump has no affect on the reactor coolant system, since one main feed pump is capable of delivering 67% guaranteed flow.If the unit is operating above 85% guaranteed load and loss of one main feed pump occurs, feedwater flow to the steam generators must be restored to 85% guaranteed flow within 20 seconds to prevent a reactor trip. This is accomplished by the following:
(1)Automatic starting of the electric motor driven standby main feedwater pump.
(2)Isolation of the main feed pump turbine condenser associated with the tripped pump. Thus, 100% condensate flow is passed through the active main feed pump turbine condenser allowing maximum power operation of the active feed pump turbine.
(3)Acceleration of the active drive turbine to its 'high speed stop' speed.
(4)Unit load runback is initiated and unit load is decreased to 85%.If the unit is operating at above 67% but below 85% load, the above actions occur except that no unit load runback is required.Insufficient NPSH at the main feed pump suction can result in a decrease in steam generator level. Low NPSH at the main feed pump suction is annunciated in the Main 10.4-28OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82Control Room, thereby alerting the unit operator of the need for a load runback to avoid a reactor coolant system transient.The feedwater piping layout has been optimized to prevent water hammer induced by the piping system.
10.4.7.4 Inspection and TestingThe operating characteristics for each system pump has been established throughout the operating range by factory tests. Each hotwell, demineralized condensate and condensate booster pump casing has been tested hydrostatically in accordance with the appropriate codes and standards. All parts of each turbine driven main feed pump and motor driven standby main feed pump subject to hydraulic pressure in service has been hydrostatically tested in accordance with the appropriate codes and standards.All parts and assemblies of parts of the feedwater heaters has been hydrostatically tested and tested otherwise as required by applicable sections of the Heat Exchange Institute Standards for Closed Feedwater Heaters; Standards of Feedwater Heater Manufacturers Association, Incorporated; and Section VIII, Unfired Pressure Vessels of the ASME Boiler Code. Heater tubes will be tested as required by ASME SA 688.Hydrostatic and other testing of the parts and assemblies of parts of the main feed pump turbine condenser channel and tubes will be in accordance with applicable sections of the Heat Exchange Institute Standards for Closed Feedwater Heaters and Section VIII, Unfired Pressure Vessels, of the ASME Boiler Code.Manways or removable heads are provided on all heat exchangers to provide access to the tube sheet for inspection, repair, or tube plugging. Inservice inspection requirements are given in Chapter 3. Preoperational test requirements are given in Chapter 14. Surveillance test requirements are given in Chapter 16.
10.4.7.5 InstrumentationSufficient level controllers, flow controllers, level switches, limit switches, temperature switches, etc., are provided to permit personnel to conveniently and safely operate the condensate and feedwater system.
10.4.8 Steam Genera tor Blowdown System 10.4.8.1 Design BasesThe design bases for the steam generator blowdown system (SGBS) are:
(1)To achieve optimum effectiveness in the control of steam generator water chemistry, continuous blowdown along with continuous all volatile treatment (AVT) will be maintained for each steam generator during normal plant operation. The minimum blowdown flow rate will be 5 gpm per steam generator.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-29WATTS BARWBNP-82 (2)Facilities are provided to treat up to 262 gpm of cooled blowdown from one unit (65.5 gpm per steam generator).
(3)Blowdown may be discharged to the Cooling Tower blowdown (CTB) without treatment provided that the radioactivity concentration of the blowdown effluent (except tritium) does not exceed the value determined in accordance with the Offsite Dose Calculation Manual (ODCM). In this mode of operation, makeup water will have to be supplied to the condensate system from the condensate storage tanks.
(4)The discharge stream from the blowdown system will be monitored continuously for the radioactivity. The blowdown will be diverted to the condensate demineralizers automatically if the radioactivi ty concentration reaches a variable setpoint consistent with the value determined in accordance with the ODCM. The design temperature for these demineralizers is 120°F, but the heat added to the condensate by this blowdown is not sufficient to endanger the demineralizers.
(5)Blowdown system discharge is sampled and analyzed daily in accordance with plant procedure. When blowdown is being treated, analyses will be performed as often as necessary for evaluation of equipment performance.
(6)Blowdown system components will be designed in accordance with the following code requirements:
(7)Primary-to-secondary leakage and condenser inleakage rates determine the blowdown rates required to maintain the secondary side water chemistry within the limits set forth in Section 10.3.5. The individual leakage rates or the combinations of the two which require the combined blowdown rate from the four steam generators to be 262 gpm, represent the limiting values of these leakage rates.ComponentCodePiping and valves from steam generator through blowdown isolation valvesASME Code III, Class 2Piping and valves downstream of blowdown isolation valves ANSI B31.1 Power PipingBlowdown flash tankASME Section VIII, Division 1Demineralizers and filtersASME Boiler and Pressure Vessel Code,Section VIII, Division 1Blowdown flash tank pumpsStandards of the Hydraulic Institute, Section BHeat ExchangerASME Boiler and Pressure Vessel Code,Section VIII, Division 1 10.4-30OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82 (8)Seismic and quality group classifications of SGBS are provided in Section 3.2 10.4.8.2 System Description and OperationA flow diagram of the steam generator blowdown system (SGBS) is shown in Figure 10.4-24.The blowdown flow from all four steam generators is piped to the turbine building where it is cooled in a stacked and second stage heat exchanger units. Cooling water is supplied from the condensate system and thus the heat given up by the blowdown is returned to the cycle. After the blowdown is cooled, it is normally discharged to the condensate line upstream of the condensate demineralizer service vessels (CDSV) where any impurities are removed. If blowdown is not routed to the CDSV, it may be sent to the CTB or to the condenser hotwell. When dumping to the CTB, the blowdown will automatically be diverted back to the CDSV on loss of CTB flow or if the radiation level of the blowdown exceeds the value determined in accordance with the ODCM.During hot standby and hot shutdown plant operating modes, when steam generator pressure is not high enough (approximately 295 to 0 psig) to flow to the CDSVs, the blowdown is routed to the blowdown flash tank. The water remaining in the flash tank is pumped to either the CDSVs, CTB, or the condenser hotwell. The maximum blowdown flow rates when using the flash tank flow path is approximately 50 gpm from one unit (12.5 gpm per steam generator).Individual blowdown sample lines from each steam generator may be monitored for radioactivity so that a leaking steam generator can be identified. A blowdown sampling system to analyze the blowdown chemistry at major points is provided.The radioactive waste treatment, and process and effluent radiological monitoring aspects of the SGBS are described in Sections 11.2, 11.3 and 11.5.There are temperature sensors located at the entrance to demineralizer beds, which initiates bypass of the beds if the temperature exceeds the maximum allowable for demineralizer resins.The blowdown control valve, located in the common line downstream of the heat exchangers, is used to regulate the blowdown flow rate. The manual throttling valves, located in the individual lines from each steam generator, are used to proportion the flow as required.Main condenser inleakage may result in full-flow condensate demineralizer operation as described in Section 10.4.8.1. Steam generator blowdown will not need to be increased for this mode of operation.10.4.8.3 Safety EvaluationThe blowdown system described in Section 10.4.8.2 provides greater capacity for treating radioactive blowdown liquid than the system as originally designed. It also minimizes release of radioactivity, and permits recycle of most of the water in the
blowdown stream.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-31WATTS BARWBNP-82CapacityThe present system provides capacity for treating up to 262 gpm of blowdown liquid per unit. This is sufficient to treat the highest expected blowdown flow rate from the steam generators. Water chemistry requirements are discussed in Section 10.3.5.Radioactivity ReleasesRadioactivity releases due to normal operation of the steam generator blowdown system are discussed in Section 11.2.Unusual Design ConditionIn the event of a flood above plant grade, the normal blowdown paths are isolated and the blowdown is released to the roof. The system is capable of operating for 100 days in this mode and with only emergency diesel power available (refer to Section 2.4.14).System Performance During Abnormally High Primary-to-Secondary LeakageAbnormally high primary-to-secondary leakage has no significant effect on the blowdown. A leak rate in excess of the Technical Specification limit requires shutdown of the unit. The blowdown system is capable of operating with a leak rate approaching 1 gpm. A 1 gpm leak rate would not require that the blowdown rate be increased above 262 gpm in order to maintain specified secondary system water chemistry unless it occurred at a time when condenser inleakage was high. With a 1 gpm leak and about 0.12% failed fuel, radiation levels in the vicinity of the blowdown system equipment would be higher than with normal operating radiation levels, but would be below design levels.In the event of a primary-to-secondary leak in excess of 1 gpm, the blowdown system could be operated after unit shutdown in order to clean the secondary system.Failure Analysis of System ComponentsAnalyses of various failures in the system are given in Table 10.4-3.
10.4.8.4 Inspections and TestingPrior to operation of the steam generator blowdown system, instruments will be calibrated and interlocks and controls will be tested to verify that they function properly. The performance of the heat exchangers, tank and demineralizers will be determined during tests of the secondary system. Routine inspections and maintenance will be performed on system components.Preoperational test requirements are given in Chapter 14. Surveillance test requirements are given in Chapter 16.
10.4-32OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82 10.4.9 Auxiliary Feedwater System 10.4.9.1 Design BasesThe auxiliary feedwater (AFW) system supplies, in the event of a loss of the main feedwater supply, sufficient feedwater to the steam generators to remove primary system stored and residual core energy. It may also be required in some other circumstances such as the evacuation of the Main Control Room (MCR), cooldown after a LOCA for a small break, maintaining a water head in the steam generators following a LOCA, a flood above plant grade, Anticipated Transient Without Scram (ATWS) event, and 10 CFR 50, Appendix R, Fires.The system is designed to start automatically in the event of a loss of offsite electrical power, a trip of both main feedwater pumps, a safety injection signal, an ATWS Mitigation System Actuation Circuitry (AMSAC) signal, or low-low steam generator water level, any of these conditions will result in, may be coincident with, or may be caused by a reactor trip. The AFW will supply sufficient feedwater to prevent the relief of primary coolant through the pressurizer safety valves and the uncovering of the core. It has adequate capacity to maintain the reactor at hot standby for two hours and then cool the RCS to the temperature at which the residual heat removal (RHR) system may be placed in operation, but it cannot supply sufficient feedwater for power generation.Note that with reactor power less than 50%, the AFW start signal is delayed by the lo-lo steam generator level trip time delay. See Section 7.2 for details.Engineered Safety Feature (ESF) standards are met for the AFW System except for the condensate water supply, which is backed up by the essential raw cooling water (ERCW). The ESF grade portion of the system is designed for seismic conditions and single failure requirements, including consideration that the rupture of a feedwater line could be the initiating event. It will provide the required flow to two or more steam generators regardless of any single active or passive failure in the long term.Seismic and quality group classifications of the AFW system are shown in Figures 10.4-21 and 10.4-21A. The industry codes and standards corresponding to these TVA classifications are given in Section 3.2.
10.4.9.2 System DescriptionThe two reactor units have separate AFW systems, as shown in Figure 10.4-21, which share some support facilities such as parts of the Control System. As on all other engineered safety features, the independence of the two systems will be guaranteed in accordance with GDC 5.Each system has two electric motor-driven pumps and one turbine-driven pump. Each of the electric pumps serves two steam generators; the turbine pump serves all four. All three pumps automatically deliver rated flow within one minute upon a trip of both main feedwater pumps, loss of offsite power, an AMSAC signal, a safety injection signal or low-low steam generator water level. The motor driven pumps start on a two-out-of-three low-low level signal in any steam generator and the turbine driven OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-33WATTS BARWBNP-82pump starts on a two-out-of-three low-low level signal in any two steam generators. Each pump supplies sufficient water for evaporative heat removal to prevent operation of the primary system relief valves or the uncovering of the core. Significant pump design parameters are given in Table 10.4-2.The preferred sources of water for all auxiliary feedwater pumps are the two 395,000 gallon condensate storage tanks. A minimum of 200,000 gallons in each tank is reserved for the AFW Systems by means of a standpipe through which other systems are supplied. As an unlimited backup water supply, a separate ERCW system header feeds each motor-driven pump. The turbine-driven pump can receive backup water from either ERCW header. The ERCW supply is automatically (or remote-manually) initiated on a two-out-of-three low pressure signal in the AFW system suction lines. Pump protection during the automatic transfer to the ERCW supplies is assured by providing sufficient suction head and flow to the pumps and is verified by system analysis. Since the ERCW system supplies poor quality water, it is not used except in emergencies when the condensate supply is unavailable.In addition, the high pressure fire protection (HPFP) system may be connected downstream of each motor driven AFW pump by a spool piece to supply unlimited raw water directly to the steam generators in the unlikely event of a flood above plant grade. Water from the HPFP system is supplied by four high pressure, vertical turbine, motor-driven, Seismic Category I pumps conforming to the requirements of ASME B&PV Code Section III, Class 3 with each having a rating of 1590 gpm at 300 feet head. These pumps are installed in the Seismic Category I Intake Pumping Station with motors above the maximum possible flood level. Each pump is capable of supplying 100% of the auxiliary feedwater demands for both units during a flood above plant grade. All four pumps are supplied from normal and emergency power with two pumps assigned to each of the two emergency power trains. Each pair of pumps on the same power train takes suction from a common sump which receives water through a settling baffle arrangement for all normal, and flood reservoir levels. For water levels below minimum normal, flow is provided to the sump through a submerged line with a motor-operated valve supplied from the emergency power train corresponding to that train that powers the pumps in the sump. Therefore, the pumps are capable of operating during any lake condition from minimum level upon loss of downstream dam to the maximum design basis flood level.The AFW system is designed to deliver 40°F to 120°F water to the secondary side of the steam generators at a pressure ranging from the RHR system cut-in point of 350°F in the RCS (equivalent to 110 psig in the steam generators) to the lowest MSSV set pressure, plus 3% set error, plus 3% accumulation pressure (1257 psig).Separate ESF power subsystems and control air subsystems serve each motor driven AFW pump and its associated valves. The valves associated with the turbine-driven pump are served by both electric and control air subsystems, with appropriate measures precluding any interaction between the two subsystems. The turbine-driven pump receives control power from a third dc electric channel that is distinct from the channels serving the motor driven pumps.
10.4-34OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-8210.4.9.3 Safety EvaluationFor the design bases considerations discussed in Section 10.4.9.1, sufficient feedwater can be provided over the required pressure range even if the failure of a feedwater line is the initiating event, any one AFW pump fails to start, and no operator action is taken for 10 minutes.The 'Loss of Normal Feedwater' and loss of offsite power analyses in Chapter 15 demonstrate that the auxiliary feedwater system satisfies the design bases described in this section.In the event that loss of offsite power (LOOP) occurs, 410 gpm of AFW delivered to two steam generators within one minute will prevent relief of reactor coolant via the pressurizer safety valves. Water levels in the steam generators will remain above the required minimum tube sheet coverage. The AFW system meets these requirements even when the single failure criterion is applied.In the event of a feedwater line break, essentially the same requirements are imposed and act as for the LOOP case. Other cases discussed in Section 10.4.9.1 impose less stringent conditions.Following a loss-of-coolant accident (LOCA) for a small break, the RCS pressure and temperature decrease at a relatively slow rate. The AFW system provides sufficient flow to the steam generators so that RCS cooldown can proceed. In this case, the AFW system function is similar to its function following other events described in Section 10.4.9.1, such as loss of offsite electrical power. In contrast, the AFW system serves a distinctly different function during a large break LOCA, where steam generator tube leaks may be present. A large LOCA causes a rapid depressurization of the RCS so that the secondary side pressure and temperature exceed primary pressure and temperature, and consequently any fission products in the RCS cannot escape to the secondary side. Subsequent cooling of the sec ondary side fluid could eventually reduce the secondary side pressure to atmospheric, permitting any fission products in the RCS to escape into the secondary system. The AFW system is used to maintain sufficient water level on the steam generator secondary side so that static head prevents primary-to-secondary tube leakage and prevents the escape of any fission products.Whenever a flood above plant grade is anticipated, an orderly shutdown to hot shutdown and a cooldown to cold shutdown will be initiated immediately. In a little more than 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> after reactor shutdown, the secondary system pressure will be reduced to approximately 100 psig. Within 27 hours3.125e-4 days <br />0.0075 hours <br />4.464286e-5 weeks <br />1.02735e-5 months <br /> after reactor shutdown, the fire-protection system piping will be connected to the auxiliary feedwater discharge piping by means of special spool pieces not normally installed, and the secondary system pressure will be maintained < 100 psia. In the event of the failure of HPFP valve 0-PCV-26-18 to close, the secondary system pressure can be maintained <
80 psig. This pressure is sufficient for decay heat removal. When the flood exceeds plant grade, the auxiliary feedwater pumps will be inoperable, and the fire protection pumps, which are located above the maximum possible flood elevation, will supply feedwater.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-35WATTS BARWBNP-82Appropriate portions of the HPFP system are designed to function under normal conditions as well as for the maximum possible flood with the coincident or subsequent loss of the upstream and/or downstream dams. The HPFP pumps are located in the intake station above the flood line and are arranged to supply water directly to the steam generators in the event the auxiliary feedwater pumps are flooded.The portion of the HPFP system which supplies auxiliary feedwater to the steam generators is ASME Section III, Class 3, Seismic Category I with the exception of the fire pumps discharge relief valve. These valves are replaced by ASME Section III, Class 3 blind flanges during flood mode preparations to ensure the integrity of the ASME Section III, Class 3 auxiliary feedwater supply piping during flood mode operation.The AFW system is required to be available in the event of an ATWS event. The most severe ATWS scenarios have been determined to be those in which there is a complete loss of normal feedwater (Reference WCAP-10858). The design basis events for the AMSAC are Loss of Normal Feedwater/ATWS and Loss of Load/ATWS.
Since there is a complete loss of normal feedwater during both of these transients, the accident analysis of both transients (Chapter 15) assumed AFW reaches full flow within 60 seconds after the initiating event for long term reactor protection. Also, the Loss of Normal Feedwater transient assumed a turbine trip within 30 seconds after the initiating event to maintain short term pressures below ASME Service Level C pressure limits. Normally these features will be actuated by the RPS. However, if a common mode failure to the RPS incapacitates AFW initiation and/or turbine trip in addition to prohibiting a scram, then an alternate method of providing AFW flow and a turbine trip is required to maintain RCS pressure below ASME Service Level C pressure limits. These two functions, turbine trip and AFW flow actuation, are provided via the AMSAC.The AFW piping system layout has been optimized to prevent water hammer occurrences induced by the piping system. The AFW piping system, including the feedwater piping adjacent to the steam generators, is observed visually when performing the AFW system preoperational test (during hot functional testing) to verify that no excessive or damaging vibration occurs when the AFW system pumps are running. Minimum flow rate requirements are met by the system for the design transients or accident conditions shown in Table 10.4-7, even if the worst case single active failure occurs simultaneously. The single active failures considered in the table are listed below: (A)Alternating current train failure (B)Turbine-driven pump (TDP) failure (C)Motor-driven pump (MDP) failure (D)Pressure control valve failure (MDP-runout protection)(E)Level control valve failure for TDP 10.4-36OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82 (F)Level control valve failure for MDP (G)Pressure switch failures (MDP and TDP systems)(H)AFW System check valve failure (failure to close on reverse flow)(I)Flow controller failure (TDP-runout protection)Operator intervention within 10 minutes is required in order to meet the minimum flow requirements on the feedline rupture and the maximum flow requirements for the main steamline break inside containment.In addition to using high quality components and materials, the AFW system provides complete redundancy in pump capacity and water supply for all cases for which the system is required. Under all credible accident conditions, at least one AFW pump is available to supply two steam generators not affected by the accident with the required feedwater. Only two steam generators are required to be usable for any credible accident condition.Redundant electrical power and air supplies assure reliable system initiation and operation. The electric motor-driven pumps and all associated controls, valves, and other supporting systems are powered by offsite or onsite ac sources. The exceptions are the motor-driven pump level control valves and the control circuits supplied by trained dc power. The turbine driven pump and all associated valves, controls, and other supporting systems are powered by steam and dc electric power, except for four 480V ac power operated valves in the steam supply lines to the pump turbine which are included to satisfy pipe rupture criteria. Steam for the turbine driven pump is provided from either of two of the four main steam loops as controlled by two of these valves. They assure that only one steam source is available at a time, and, in the event of a pipe rupture, prevent two steam generators from blowing down simultaneously. The other two valves simply isolate in the event of a pipe rupture. All four of these are motor operated, fail as is, and all but the one isolating the standby steam source are normally open. This assures that a steam supply to the turbine will be available for design basis events and a LOOP event (see Table 10.4-4, items 2, 4, and 5). Turbine driven pump bearing lube oil cooling water is taken from a first stage discharge connection on the turbine driven pump. An orifice in the cooling water piping between the turbine driven pump and the lube oil cooler controls the cooling water flow. Failure modes and effects analyses for the AFW System are presented in Tables 10.4-4, 10.4-5, and 10.4-6.During certain postulated 10CRF50, Appendix R fires, the electric cables for the electro-pneumatic controllers of the turbine-driven steam generator level control valves (LCV) could be destroyed. A backup source of compressed nitrogen has been provided to allow manual control of the LCVs. No electric power is required for the operation of this backup nitrogen source. Valves associated with this backup source must be manually operated to align the high pressure nitrogen bottles and associated piping to take local manual control of the LCVs. The LCV position is adjusted upon orders from either the Control Room or the Auxiliary Control Room, based on the observed water level in the steam generators being controlled.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-37WATTS BARWBNP-89 10.4.9.4 Inspection and Testing RequirementsA comprehensive test program is followed for the AFW system. The program consists of performance tests of individual components in the manufacturer's shop, integrated preoperational tests of the system as a whole, and periodic tests of the activation circuitry and mechanical components to assure reliable performance throughout the life of the plant.Test requirements are given in Chapter 14.
During plant operation, the system can be tested by pumping condensate storage water to the condensate storage tank. ERCW and HPFP water will not be fed to the steam generators during tests, but separate tests on the ERCW and HPFP system will assure the availability of the alternate water supplies.Surveillance test requirements are given in Chapter 16. Inservice inspection requirements are given in Chapter 3.
10.4.9.5 Instrument ation RequirementsThe three pumps start automatically on a loss of offsite power, trip of both main feedwater pumps, a safety-injection signal, or a AMSAC signal. The electric-motor-driven pumps also start automatically on a two-out-of-three low-low level signal from any steam generator, and the turbine driven pump starts automatically on a two-out-of-three low-low level signal from any two steam generators. All pumps can be started remote-manually.A modulating level control valve (which is normally closed) between each pump and each steam generator fed by the pump receives an opening signal on a low-low water level in the steam generator. For the motor driven pumps, two modulating level control valves, a 4" and a 2", (which are normally closed) between each pump and each steam generator fed by the pump receives an opening signal on a low-low water level in the steam generator. For the motor driven pumps these valves will continue to modulate and automatically maintain steam generator water level. After the steam generator decreases in pressure to a certain setpoint the 4" valve will close to protect it from cavitation damage. The 2" LCV is designed for extended operation at low flows and high pressure drops. The system may be controlled manually. If the system is being tested in the manual mode and an automatic start signal is received, the control will revert to automatic. After an accident, the operator can take manual control by blocking the accident signal with the handswitch. However, if another accident signal occurs (such as would happen if the operator allowed the steam generator water level to drop to the low-low level) the control will again revert to automatic. As discussed in 10.4.9.3, there are postulated events when the turbine driven AFW pump LCV may be under local manual control. Automatic operation during these events will not be possible.Figures 10.4-16, 10.4-19 and 10.4-20 give details of the control and logic of the AFW system.
10.4-38OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-8210.4.10 Heater Drains and Vents 10.4.10.1 Design BasesThe heater drain system is designed to remove and dispose of all drainage from the moisture separators, reheaters, feedwater heaters, main feed pump turbine condensers and gland steam condensers during all modes of unit operation by returning the condensed water back to the condensate and feedwater system.The vent system is designed to adequately vent all heat exchangers to assure complete removal of noncondensable gases during all modes of unit operation.10.4.10.2 System DescriptionThe flow diagrams for the heater drain and vent systems are shown in Figures 10.4-27 and 10.4-28. The control and logic diagrams are Figures 10.4-29 through 10.4-35.To accomplish the design objectives described in Section 10.4.10.1, the following equipment is provided (per unit):
(1)No. 3 Heater Drain Pumps Number - 3Manufacturer - Borg-Warner Corporations, Byron Jackson Pump DivisionType - DSJH, single stage, double suction, double volute, centrifugal Design Point - 3600 gpm, 1200 feet head*
Motor Design - 1250 hp, 3580 rpm, 6600 V, 3 phase, 60 Hz, horizontal, constant speedMotor Manufacturer - Parsons-Peebles, Ltd.
(2)No. 7 Heater Drain Pumps Number - 2Manufacturer - Borg-Warner Corporation, Byron Jackson Pump DivisionType - DSJH, single stage, double suction, double volute, centrifugalDesign Point - 2000 gpm, 730 feet head*
Motor Design - 450 hp, 3565 rpm, 6600 V, 3 phase, 60 Hz, horizontal, constant speedMotor Manufacturer - Parsons-Peebles, Ltd.* During preoperational testing of the #3 and #7 heater drain tank pumps, the pumps did not meet vendor pump performance curve. However, review of the test data indicates the pumps will deliver sufficient flow and head to satisfy operational requirements and the test results are acceptable.
(3)Feedwater Heaters OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-39WATTS BARWBNP-63Shell side design conditions only are given here. See Section 10.4.7, for channel side design conditions.Number - 21 (3 streams of 7 heaters)
(4)Main Feed Pump Turbine CondensersShell side design conditions only are given here. See Section 10.4.7, for channel side design conditions.
Number - 2 Shell Design Pressure - 20 psig and 30 in. mercury vacuumShell Design Temperature - 160°F (5)No. 7 Heater Drain Tank Number - 1Design Pressure - 1 in. of mercury absolute to 50 psig Design Temperature - 180°F (6)No. 3 Heater Drain Tank Number - 1Design Pressure - 250 psigDesign Temperature - 370°F (7)Moisture Separator Drain Tanks Number - 6Design Pressure - 265 psigDesign Temperature - 550°F (8)High Pressure Reheater Drain TanksHeater No.Shell Design Pressure, psigShell DesignTemperature,F1545480 2355440 3232380 4 75380 5 75285 6 75220 7 75180 10.4-40OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82 Number - 6Design Pressure - 1185 psigDesign Temperature - 566°F (9)Low Pressure Reheater Drain Tanks Number - 6Design Pressure - 450 psig Design Temperature - 500°F (10)Main Feed Pump Turbine Condenser Drain Tanks Number - 2Design Pressure - 30 in. of mercury vacuum to 50 psig Design Temperature - 150°F (11)Gland Steam Condenser Number - 1Design Pressure - 400 psig Design Temperature - 125°F (12)Main Feed Pump Turbine Condenser Drain Pumps Number - 2Manufacturer - Ingersoll-Rand Type - 4x3xl0 H-7.5 Design Point - 400 gpm, 55 feet headMotor Design - 7.5 hp, 1750 rpm, 460 V, 3 phase, 60 Hz, horizontal, constant speedMotor Manufacturer - Reliance ElectricThe tube and shell sides of all feedwater heaters are equipped with manually valved vent lines to the main condenser for venting during unit startup. Venting to the main condenser during normal operation is accomplished through continuous "free blowing" orifices, sized in accordance with recommendations of the Heat Exchange Institute Standards for Closed Feedwater Heaters, 1968. The venting scheme for the moisture separators, high pressure reheaters, and low pressure reheaters is similar to that employed for the feedwater heaters. The only exception is the use of power operated rather than manual valves.The heaters are numbered from 1 to 7 with the highest pressure designated as No. 1. During normal unit operation, the No. 1 heater drains, composed of the high pressure reheater drains and the No. 1 extraction, cascade into the shell of the No. 2 heater.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-41WATTS BARWBNP-82The No. 2 heater drains, the No. 1 drains, plus the No. 2 extraction and the low pressure reheater drains, cascade into the No. 3 heater drain tank. The No. 3 heater drains (No. 3 extraction) and the moisture separator drains also flow into the No. 3 heater drain tank. Water from the No. 3 heater drain tank is then pumped forward into the condensate cycle (between the No. 3 and No. 2 heaters) by the No. 3 heater drain pumps.The first extraction from the low pressure turbines is condensed in the No. 4 heaters. These drains cascade into the shell of the No. 5 heaters. No. 5 heater drains (No. 5 extraction plus No. 4 heater drains) cascade to the No. 6 heater, whose drains cascade in turn to the No. 7 heater drain tank. The condensed No. 7 extractions condensed flashing steam from the steam generator blowdown flash tank, main feed pump turbine condenser drains, and other miscellaneous drains are also routed to the No. 7 heater drain tank. This water is pumped forward into the condensate system (at a point between the No. 7 and No. 6 heaters) by the No. 7 heater drain pumps.Proper levels are maintained in the Nos. 1, 2, 4, 5, and 6 feedwater heaters by modulating level control valves that receive their control signals from level indicating controllers mounted on the heater shells. Should a level drop below the normal control range, a low level alarm is sounded. High level in the shell of a No. 5, or 6 heater results in annunciation of a high level alarm. The No. 1 and 4 heaters are equipped with modulating bypass to condenser valves. Should the level in a No. 1 or a No. 4 heater, exceed the normal control level, the bypass valve begins to open. Indication is given in the Main Control Room when the bypass valve begins to open. If the level exceeds the control range of the bypass valve, high level annunciation occurs. High-high level in a No. 1 heater results in isolation (of both feedwater and extraction steam) of that heater. High-high level in a No. 2 or No. 4 heater results in isolation of the appropriate bank of No. 2, 3 and 4 heaters. High-high level in a No. 5 or 6 heater results in isolation of the appropriate bank of No. 5, 6, and 7 heaters.All No. 3 and No. 7 heaters are "dry" shelled heaters. Thus, particular care in piping design was taken to ensure that choking of drains as a result of steam entrainment will not occur.Level in the No. 3 heater drain tank is maintained within the proper range by modulating level control valves at the discharge of the No. 3 heater drain pumps. Level in excess of the normal control range initiates opening of modulating bypass to condenser valves. Indication that the bypass to condenser valve has left the fully closed position is given in the Main Control Room.Additional increase in level to a point above the range of the bypass valves annunciates a high level alarm. Low level in the drain tank results in a trip of all operating No. 3 heater drain pumps. A level control scheme identical to that for the No. 3 heater drain tank is provided for the No. 7 heater drain tank.The moisture separator drains are routed to the No. 3 heater drain tank, low pressure reheater drains to the No. 2 heater shells, and the high pressure reheater drains to the 10.4-42OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82No. 1 heater shells. Since all moisture separators and reheaters are "dry" shelled vessels, particular care in design of drain piping was taken to prevent choking of drain flow due to steam entrainment.Moisture separator-reheater (MSRH) drain co ntrol is provided by maintaining proper levels in drain tanks connected to the individual moisture separators, HP reheaters and LP reheaters. The level is controlled in the individual drain tanks by modulating level control valves (one per tank).Level in excess of the normal control range of the MSRH causes a modulating bypass to condenser valve (one per tank) to open. Indication that a bypass valve has left the fully closed position is given in the Main Control Room. An increase in level to above the control range of the bypass to condenser valve results in a high level alarm being annunciated in the Main Control Room. Low level alarm is also annunciated if the level drops below the normal control range.Air assisted nonreturn valves are provided in each MSRH drain line downstream of the point where the bypass to condenser piping is connected so that, in the event of a turbine pressure transient due to a load rejection, the water stored in the feedwater heaters cannot flash back to the MSRH. The bypass to condenser valves will still be available for level control during a transient of this type.Feedwater heaters are designed in accordance with applicable sections of Heat Exchange Institute Standards for Closed Feedwater Heaters, Standards of Feedwater Heater Manufacturers Association, Incorporated, and Section VIII, Unfired Pressure Vessels, of the ASME Boiler Code. The No. 3 and No. 7 heater drain tanks are designed in accordance with Section VIII, Unfired Pressure Vessels of the ASME Boiler Code. All moisture separators, reheaters, and associated drain tanks are designed to Section VIII of the ASME code and require an ASME certification stamp. All piping and valves in the heater drains and vents system are designed in accordance with ANS B31.1.A single drain tank receives the drains from both main feed pump turbine condensers. Normal water level in the tank is maintained by a level control valve at the drain pump discharge. This valve receives its control signal from a level indicating controller mounted on the drain tank. Level below the control range of the controller results in annunciation of a low level alarm. Level above the control range results in annunciation of a high level alarm. A further increase in level (to the high-high level) initiates opening of a bypass to condenser valve. Direct operator action is required to close the bypass valve after it has opened.The three No. 3 heater drain pumps start sequentially as the unit load increases. The particular order in which the pumps start is determined by the position of a selector switch. Conditions that must be satisfied before any pump can start include:
(1)Level in the No. 3 heater drain tank above a permissive level set point.
(2)Sufficient lubricating oil pressure.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-43WATTS BARWBNP-82One drain pump starts automatically when feedwater flow reaches 40% guaranteed flow, a second pump starts at 40% feedwater flow, and the third pump starts at 60% feedwater flow.The pumps are sequentially automatic tripped on decreasing load when feedwater flow drops below the 60%, 40%, and 40% setpoints. In addition, the pumps may be tripped by low level in the No. 3 heater drain tank, low lube oil pressure, or a motor protection signal.Minimum flow for pump protection is provided by an automatic recirculation control valve at the discharge of each pump. The No. 7 heater drain pumps are controlled in the same manner as the No. 3 heater drain pumps with one exception. Since there are only two No. 7 heater drain pumps, the unit load setpoints for sequential starting and tripping of these pumps are 40% and 50% only.The main feed pump turbine condenser drains are equipped with two 100% capacity pumps which take suction from a single dr ain tank. One pump is started manually while the second pump is put on standby by placing the selector switch in the auto position. Should the pressure in the discharge of the active pump drop below 25 psia, the standby pump is automatically started.A trip of the main turbine will result in tripping of all No. 3 and No. 7 heater drain pumps due to low extraction pressure (loss of NPSH). All pumps conform to applicable paragraphs of the centrifugal pump section of the applicable standards of the Hydraulic Institute.
10.4.10.3 Safety EvaluationWith few exceptions, the operating mode of the heater drains system has no effect on the reactor coolant system and the ability of the condensate and feedwater system to deliver feedwater to the steam generators in sufficient quantity to meet all system demands. However, some transient conditions can exist that do require proper interfacing between the heater drains system and other secondary cycle systems to prevent a reactor trip.With all drains from the No. 3 heater drain tank being bypassed to the condenser (and being passed through the hotwell and condensate booster pumps) the condensate and feedwater system can deliver only 85% guaranteed flow to the steam generators. Thus, with unit load greater than 85%, indication that the No. 3 heater drain tank bypass to condenser valve has fully opened initiates a load runback to the 85% power level. The fully opened position corresponds to the maximum allowable bypass flow to the condenser without runback.Trip of a No. 3 heater drain pump during operation at unit load in excess of 85% produces a low differential pressure between the No. 3 heater drain tank and pump suction (indicating that the remaining pumps are passing excessive flow and are in danger of damage due to insufficient NPSH). As a result, one of the two level control valves in the drain pump discharge is tripped closed for pump protection.
10.4-44OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-82Bypassing the No. 7 heater drain tank drains to the main condenser will have no effect on the reactor coolant system unless a complete bank of feedwater heaters has been isolated. Should this condition exist, a manual load runback must occur to prevent a reactor trip.Trip of one No. 7 heater drain pump will have no effect on the reactor coolant system.10.4.10.4 Inspection and TestingAll pumps, heaters, and pressure vessels in the heater drains, and vents system have been tested by the manufacturer in accordance with the codes under which they were manufactured. Since there are no Class 2 components in this system, no inservice inspection is required.
10.4.10.5 InstrumentationSufficient instrumentation is provided to permit personnel to conveniently and safely operate this system and to provide proper interfacing with the reactor coolant system.
10.4.11 Steam Generator Wet Layup System 10.4.11.1 Design BasesThe steam generator (SG) wet layup system is designed to independently and completely mix ammonium hydroxide and hydrazine layup solutions in each steam generator and its respective layup piping loop by recirculating the solutions at a rate of approximately 100 gpm per steam generator. This system operates to recirculate to the steam generator only when the reactor unit is in the cold shutdown condition. 10.4.11.2 System DescriptionA flow diagram of the SG wet layup system is shown in Figure 10.4-37.The system consists of an independent recirculation loop for each steam generator. Each loop contains a pump with associated controls and connections for ammonium hydroxide and hydrazine injection; also each loop contains connections for grab sampling, valves for isolation of the wet layup system from the feedwater and steam generator blowdown system when operating in modes other than cold shutdown, and other miscellaneous instrumentation.The recirculation system is manually aligned and operated by opening isolation valves and closing the tell-tale drains only after the reactor unit is placed in the cold shutdown condition. The recirculation system is operated to mix the layup solution in the steam generators. After the initial mixing of the layup solution, the system is only operated when it is necessary to sample the layup solution or adjust the solution chemistry. The ammonium hydroxide and hydrazine for layup are metered into each steam generator wet layup loop using the secondary chemistry control system pumps located in the Turbine Building.Wet layup piping and the first isolation valve attaching to main feedwater system inside the valve vault are designed to ASME Section III, Class 2, TVA Class B requirements.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-45WATTS BARWBNP-82Piping outside of the valve vault is designed to ANSI B31.1, TVA Class G or H requirements. Valves outside of the valve vault meet ANSI B31.1 or ANSI B16.5 requirements, TVA Class G requirements. Double isolation valves are provided at each of the main feedwater, feedwater bypass, and steam generator blowdown connections. Tell-tale drains are provided between each set of isolation valves. The first isolation valve at each connection is locked closed during normal operation.Piping and valves are carbon steel or other materials compatible with ammonium hydroxide and hydrazine solutions.Each layup recirculation loop is equipped with a recirculation pump manufactured in accordance with the applicable manufacture standards.The wet layup recirculation system is located in the Auxiliary Building with portions of the piping routed into the valve vaults.The sampling points for the grab samples are grouped together and can be taken at the discharge side of the recirculation pumps.The wet layup recirculation pump for each loop takes suction from the main feedwater piping and the blowdown piping and discharges into the feedwater bypass piping. The pump suction flow path is manually alternated between the blowdown and main feedwater piping to insure efficient mixing in all areas of the steam generators.The connection to the main feedwater piping is downstream of the flow-control valves in the Class B piping so that the wet layup system can be recirculated at the same time the feedwater system is being recirculated.
10.4.11.3 Safety EvaluationThis system is not required to serve any safety functions as related to safe shutdown of the reactor. However, portions of the system perform a primary safety function because the valves at the main feedwater interface are containment isolation valves. The system is completely isolated from the main feedwater and steam generator blowdown systems for all operating modes except for cold shutdown. Piping that is routed in the Auxiliary Building and the valve vaults is Seismic Category IL, except for the layup piping from the feedwater line through the first isolation valve which is Seismic Category I.10.4.11.4 Inspection and TestingThis equipment is tested in accordance with the applicable code requirements. Periodic tests are conducted to assure that the system is capable of performing its functional requirements.
10.4.11.5 InstrumentationPressure sensors are installed for use in determining pump flow rate.
10.4-46OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR WBNP-0Table 10.4-1 Deleted by Amendment 43 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-47WATTS BARWBNP-91Table 10.4-2 Auxiliary Feedwater Pump ParametersTotal Number Per Unit3Electric Driven2 Turbine Driven1Design Flow Rate, gpmElectric Driven, each450 Turbine Driven790Design Pressure, psig1600 Feedwater Design Temperature, °F40 to 120 Design Head, feetElectric Driven (as tested)3250.5 Turbine Driven3350 10.4-48OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-73Table 10.4-3 Failure Analysis, Steam Generator Blowdown System (Page 1 of 2)FailureConsequencesAction1.Rupture of blowdown line between steam generator and isolation valve inside containment.Hot water under pressure partially flashes to steam. Pressure in lower compartment increases, and vapor passes through ice beds.
Water level in affected steam generator increases. Radioactivity present in steam generator remains inside containment.When containment pressure reaches 1.2 psig, reactor is automatically scrammed, and containment isolation valves close. Main feedwater lines isolate, blowdown isolation valves close, and auxiliary feedwater pumps start. Charging pumps start and pump borated water into the primary system. When it is determined that the fault is not in the primary system, it is put into hot shutdown operation. If the break happens between the isolation valve and the containment penetration, automatic closure of the isolation valves initiated by the containment pressure signal terminates the release. If the break is ahead of the isolation valve when the cause of the fault is identified, auxiliary feedwater to the affected steam generator is cut off and the steam generator is allowed to boil and drain itself dry.2.Rupture of blowdown line from outside containment to blowdown control valve downstream of heat exchanger.Hot water under pressure escapes into main steam valve vault, outside the building, or inside the turbine building and partially flashes to steam. Some of radioactive material in blowdown will escape directly to atmosphere or be carried out with turbine building ventilation exhaust, depending on where the rupture occurs.When the leak is discovered, the operator closes all blowdown isolation valves and then opens them one at a time to locate the leak. The unit is shut down as necessary to repair the leak.3.Rupture of blowdown line downstream of the blowdown control valve in the heat exchanger flow path.Water under pressure escapes into turbine building and is collected by liquid waste system.Same as (2)4.Failure of blowdown control valve.Flow will increase to maximum value allowed by manual throttling valves.When the failure is discovered, the blowdown isolation valves will be closed so that the regulating control valve can be repaired.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-49WATTS BARWBNP-735.Tube rupture in a heat exchangerBlowdown water escapes into the heat exchanger cooling water channel.When the failure is discovered, the blowdown isolation valves will be closed so that the heat exchanger can be prepared.Table 10.4-3 Failure Analysis, Steam Generator Blowdown System (Page 2 of 2)FailureConsequencesAction 10.4-50OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BARWBNP-73THIS PAGE INTENTIONALLY BLANK OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-51WATTS BAR WBNP-82Table 10.4-4 Failure Mode & Effects Analysis Steam Supply Subsystem (Sheet 1 of 2)Mode of Operation: 1-Hot Standby, 2-Startup, 3-Power Operation, 4-Normal Shutdown, 5-Emergency Shutdown, 6-Design Basis Event (Listed in Remarks Column)MODE OF OPER.FAILUREMETHODEFFECT ONCOMPONENTFUNCTION123456MODEOF DET.SUBSYSTEMSYSTEMREMARKS*1. Main Steam Piping Storage TankSource of SteamX X------------See pipe failure analysis2. FCV 1-16 (FCV 1-15)Provides two different steam supplies, but to prevent blow-down of two SG in event of pipe rup-ture, only one steam sources is available at one time. Isolation Valve
only X X Fails Closed Fails Open Control Room(Valve Position (Ind.)Loss of one of two steam sources. No effect unless pipe rupture, then blowdown of on SG and loss of flow from TD pump.NoneRedundant steam source available from other SGMotor-Driven pump would provide req'd feedwater flow.3. Check Valve (3-892, 3-891)Prevents reverse flow and blowdown in case of pipe rutpure.
X X Fails Closed Fails OpenNone unless valve FCV 1-16 open, the control room ind.,
control room, from effect on subsystem (no feedwater flow).Loss of one of two steam sources If pipe rupture could close both steam sources and thus flow from TD pump.NoneRedundant steam source available from the SG and Motor-Driven pumps would provide req'd flow. Motor-Driven pumps would provid req'd. flow.4. FCV 1-18Isolates in case of pipe rupture.
Isolation Valve
only X X Fails Closed Fails Open Control Room(Valve Position Ind.)Loss of steam supply.NoneNoneMotor-driven pumps would provide req'd. flow. If isolation req'd redundant FCV-1-17 would provide this feature5. FCV 1-17Isolates in case of pipe rupture.X X Fails Open Fails Closed Control Room(Valve Position Ind.)Loss of steam supplyNoneNoneMotor-driven pumps would provide req'd flow. If isolation req'd redundant FCV-1-18 would provide this feature6. FCV 1-51Trip & throttle valveX X Fails Closed Fails Open Control Room(Valve Position Ind.)Turbine Trip and loss of Aux. FW Flow from TD pump. In the event of a loss of load (pipe break) governor viv would limit pump speed.NoneMotor-driven pumps would provide req'd flow.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-52WATTS BAR WBNP-82*Consequences for design basis events are not listed for mode 6 operation unless otherwise noted. Also, see footnote for turbine-driven (T-D) pump subsystem.7. FCV 1-52Governor ValveX X Fails Open Fails Closed Control Room (Valve Position Ind.)Turbine Trip and loss of Aux. FW Flow from TD pump.NoneMotor-driven pumps wouldprovide req'd flow.8. TurbineDrives pumpXTURBINE Failure Control Room(no FW Flow)NoneNoneMotor-driven pumps would req'd flow.All Components (1-8)All FunctionsXXXXXXAll modesVisual/Control RoomNoneNoneSince postulated accidents are considered only for the design basis event, a single component failure (during mode 1-5 operation) will be less severe than the failures considered above and will not affect the ability of the Aux. FW system to perform its intended design function.Table 10.4-4 Failure Mode & Effects Analysis Steam Supply Subsystem (Sheet 2 of 2)Mode of Operation: 1-Hot Standby, 2-Startup, 3-Power Operation, 4-Normal Shutdown, 5-Emergency Shutdown, 6-Design Basis Event (Listed in Remarks Column)MODE OF OPER.FAILUREMETHODEFFECT ONCOMPONENTFUNCTION123456MODEOF DET.SUBSYSTEMSYSTEMREMARKS*
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-53WATTS BAR WBNP-89Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 1 of 6)TRAIN S FAILURE MODES AND EFFECTS ANALYSISCooldown for Stage 1 of DBE Flood AMain Feed Line Break with LOOP ALarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODEPOTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECTON PLANTREMARKS1.Check valve 1-3-810.Isolates the safety-related suction line for the TDP 1A-S from its non-safety water sourceStuck closed.Stuck open.Mechanical failure.Mechanical failure.
Control Room indication via pressure switches PS-3-121A & PS 125A.No method available.Transfer of suction to ERCW.Degradation of flow from TDAFW pump if supplied from ERCW.None.None.MDP 1A-A & 1B-B provides flow to all 4
SG's.TDP will still be operable; however, MDP's are still available to all SG's.2.TDP 1A-SProvides Feedwater flow to all four SG's.Fails to start.Seal fails.Mechanical failure, spurious control signal.Mechanical failure.
Control Room indication via indicator FI-3-142A.
Control Room indication reduced flow via FI-3-142A.Loss of flow to all four SG's.TDP 1A-S pump flow is diminished.None.None.MDP's 1A-A & 1B-B provides flow to all 4
SG's.MDP's 1A-A & 1B-B will provide flow to
all four SG's.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-54WATTS BAR WBNP-893.Check Valve 1-3-864Maintains water inventory in downstream piping of TDP 1A-S by preventing reverse flow.Stuck closed.Stuck open.Mechanical failure.Mechanical failure.
Control Room indication via flow indicator FI-3-142A.None.Loss of flow to all four SG's.None, if TDP 1A-S is running. If pump is not running, (no
initiating event),
water would be maintained in the pump A discharge piping up to LCV's 3-172,-173, -174 & -
175 by pressure of the min reserve water in the CST (EL 745'-6.365" Ref 5.19, Sect 7.3) plus the atmospheric pressure above the water in the tank.None.None.MDP's 1A-A & 1B-B provides flow to all
4 SG's.No loss of pump.Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 2 of 6)TRAIN S FAILURE MODES AND EFFECTS ANALYSISCooldown for Stage 1 of DBE Flood AMain Feed Line Break with LOOP ALarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODEPOTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECTON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-55WATTS BAR WBNP-894.AOV LCV-3-175 (fails in closed position) spring to close air to open Regulates AFW flow to SG 4 from
TDP 1A-S.Fails to open.Fails to close.Stuck open.Stuck closed.
Control failure.
Control failure.Mechanical failure.Mechanical failure.
Control Room indication via
control switch HS 175A.Control Room indication via
control switch HS 175A.Control Room indication of SG 1.
High level via LA 175B and -175D.
Control Room indication via
control switch HS 175A.Loss of AFW flow to SG 4.AFW flow to SG 4 unregulated.
Diminished flow to SG's 1, 2 & 3.AFW flow to SG 4 unregulated.
Diminished flow to SG's 1, 2 & 3.Loss of AFW flow to SG 4.None.None.None.
None.MDP 1B-B will provide flow to SG
4.Operator action required to isolate TDP 1A-S to prevent SG 4
overfill.Operator action required to isolate TDP 1A-S to prevent SG 4
overfill.MDP 1A-A will provide flow to SG
4.Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 3 of 6)TRAIN S FAILURE MODES AND EFFECTS ANALYSISCooldown for Stage 1 of DBE Flood AMain Feed Line Break with LOOP ALarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODEPOTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECTON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-56WATTS BAR WBNP-895.Condensate Storage TankWater SupplyTank Discharge PluggedMechanical failure.Control Room Alarm (Loss of suction pressure).Loss of condensate water supply.None.On loss of condensate supply, the essential raw
cooling water (ERCW) system
supply is
automatically provided.6.Check valve 1-3-874Prevents reverse flow in TDP 1A-S discharge line to SG
4.Stuck Closed.Stuck open.Mechanical failure.Mechanical failure.
Control Room indication via flow indicators FI-3-142A
& -170A.None.Loss of TDP 1A-S flow to SG 4.Not a problem if TDP 1A-S is running, if not LCV-3-173 will prevent reverse flow thru pump discharge piping.None.None. MDP 1B-B will provide flow to SG
4.Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 4 of 6)TRAIN S FAILURE MODES AND EFFECTS ANALYSISCooldown for Stage 1 of DBE Flood AMain Feed Line Break with LOOP ALarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODEPOTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECTON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-57WATTS BAR WBNP-897.Check valve 1-3-644Prevents blowdown of SG 4 in case of an AFW line break inside containment.Stuck closed.Stuck open.Mechanical failure.Mechanical failure.
Control Room indication via flow indicator FI-3-170A.
In addition to SG level instrumentation.None.Loss of AFW to SG 4.None. Check valve 1-3-645 will prevent blowdown of SG 4.None.None.AFW flow required to only two SG's.8.Check valve 1-3-645Backup valve to 1-3-644 (same function)Stuck closed.Stuck open.Mechanical failure.Mechanical failure.
Control Room indication via flow indicator FI-3-170A.
In addition to SG level instrumentation.None.Loss of AFW to SG 4.None. Check valve 1-3-644 will prevent blowdown of SG 4.None.None.AFW flow required to only two SG's.Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 5 of 6)TRAIN S FAILURE MODES AND EFFECTS ANALYSISCooldown for Stage 1 of DBE Flood AMain Feed Line Break with LOOP ALarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODEPOTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECTON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-58WATTS BAR WBNP-899.TDP 1A-S min flow recirc line to CST check valve 3-818.Prevents backflow from CST to TDP 1A-S discharge piping.Stuck closed.Stuck open.Mechanical failure.Mechanical failure.Low flow or none thru FE-131 located on recirc TDP overheating as indicated by TI 3-149.No method of detection.Could cause TDP 1A-S to overheat and become inoperable preventing AFW flow to all four SG's (only if flow demand is low).No effect on system if TDP 1A-S is running. If TDP 1A-S is not running, system resistance would prevent backflow from
occurring.None.None.MDP's 1A-A & 1B-B will provide flow to
all four SG's.Will not affect recirc flow to CST.Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 6 of 6)TRAIN S FAILURE MODES AND EFFECTS ANALYSISCooldown for Stage 1 of DBE Flood AMain Feed Line Break with LOOP ALarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODEPOTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECTON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-59WATTS BAR WBNP-89Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 1 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS1.Check valve1-3-806Isolates the safety-related suction line for MDP 1B-B from its non-safety water source.Stuck closed.Stuck open.Mechanical failure.Mechanical failure.Control Room indication via pressure gage PDI-3-132A.Control Room indication via pressure gage PDI-3-132ALoss of flow from MDP 1B-B.Reduction or loss of flow if MDP 1A-A flow is from the ERCW.None.None.TD 1A-S provides flow to SG's 3 & 4.TD 1A-S provides flow to SG's 3 & 4.
2.3.MOV'S FCV-3-126A FCV-3-126B. (fail as
is)Isolation valves between ERCW and MDP 1B-B suction.Either fails to open or Either stuck closed.Both valves fail to open orBoth valves stuck closed.Control failure.Mechanical failure.
Control or power failure. Mechanical failure. Control Room indication via control switches HS-3-126A &
HS-3-126B.Control Room indication via control switches HS-3-126A &
HS-3-126B.Loss of AFW flow to SG's 3 & 4.Loss of AFW flow to SG's 3 & 4.None.None.TDP 1A-S provides flows to SG's 3 & 4.TDP 1A-S provides flows to SG's 3 & 4.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-60WATTS BAR WBNP-894.MDP 1B-BProvides Feedwater flow to SG's 3 & 4.Fails to start.Seal fails.Mechanical failure.Mechanical failure.Control Room indication via control switch HS-3-128A &
pressures differential indicator PDI-3-132A.Control Room indication reduced flow via FI-3-147B & FI 170A.Loss of Train B.
MDP 1B-B capability is diminished.None. None. TDP 1A-S provides flow to SG's 3 & 4.TDP 1A-S provides flow to SG's 3 & 4.5.Condensate Storage TankWater SupplyTank Discharge Plugged.Mechanical failure.Control Room Alarm (Loss of Suction Pressure)Loss of Condensate Water SupplyNone.On loss of condensate supply, the essential raw
cooling water (ERCW) system supply is automatically provided.6.Check Valve1-3-821NoneN/AN/AN/AN/ANoneValve Internals have been removed.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 2 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-61WATTS BAR WBNP-897.AOVPCV-3-132 (fails in closed position) spring to close air to open.Prevents MDP 1B-B runout by controlling pump discharge pressure.Fails to open.Fails to close.Stuck open.Stuck closed.
Control failure.
Control failure.Mechanical failure.Mechanical failure.Control Room indication via flow indicators FI-3-142A, -
147B, & -170A.Control Room indication via flow indicators FI-3-142A, -
147B, & -170A. Also, pressure differential indicator PDI-3-132A.Control Room indication via vlow indicators FI-3-142A, -
147B, & -170A. Also, pressure differential indicator PDI-3-132A.
Indication via flow indicators FI-3-142A,-
147B, & -170A.Loss of MDP 1B-B.Possibility of MDP 1B-B running out and eventual loss of pump.Possibility of MDP 1B-B running out and eventual loss of pump.Loss of MDP 1B-B.None.None.None.None.TDP 1A-S provides flow to SG's 3 & 4.TDP 1A-S provides flow to SG's 3 & 4.TDP 1A-S provides flow to SG's 3 & 4.TDP 1A-S provides flow to SG's 3 & 4.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 3 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-62WATTS BAR WBNP-898.AOVLCV-3-171 (fails to open position) spring to open air to
close.Regulates AFW flow to SG 4 when pressure is greater than setpoint for pressure switch PS-3-171. 4" level control valveFails to open.Fails to close.Stuck open.Stuck closed.
Control failure.
Control failure.Mechanical failure.
Mechanical failure.Control Room indication of SG 4.
High level via LA 171B and -171D.Control Room indication via control switch HS-3-171A.Control Room indication via control switch HS-3-171A.Control Room indication via control switch HS-3-171A.Loss of AFW flow to SG 4.AFW flow to SG 4 unregulated.
Diminished flow to
SG 3.AFW flow to SG 4 unregulated.
Diminished flow to
SG 3.Loss of AFW flow to SG 4.None.None.None.None.TDP 1A-S provides flow to
SG 4.Operator action required to isolate MDP 1B-B to prevent SG 4
overfill.Operator action required to isolate MDP 1B-B to prevent SG 4
overfill.TDP 1A-S provides flow to
SG 4.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 4 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-63WATTS BAR WBNP-899.AOV LCV-3-171A (fails in closed position) spring to close air to open.Regulates AFW flow to SG 4 when pressure is greater than setpoint for pressure switch PS-3-171. 2" level control bypass valve.Fails to open.Fails to close.Stuck open.Stuck closed.
Control failure.
Control failure.Mechanical failure.
Mechanical failure.Control Room indication via control switch HS-3-171A.Control Room indication via control switch HS-3-171A.Control Room indication of SG 2.
High level via LA 171B & -171D.Control Room indication via control switch HS-3-171A.Loss of AFW flow to SG 4 through LCV-3-171A.Diminished AFW flow to SG 3.Diminished AFW flow to SG 3.Loss of AFW flow to SG 4 through LCV-3-171A.None.None.None.None.TDP 1A-S provides flow to
SG 4.Operator action required to isolate MDP 1B-B to prevent SG 4
overfill.Operator action required to isolate MDP 1B-B to prevent SG 4
overfill.TDP 1A-S provides flow to
SG 4.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 5 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-64WATTS BAR WBNP-8910.Emergency power to Train B.Provide AC power to MDP 1B-B & all MOV's in Train B.Fails.Diesel Generator Shutdown Board
1B-B failure.Control Room indication.MDP 1B-B is lost.None.Train A would be available to service SB's 3 &
- 4. This is acceptable condition since only 2 SB's are required to be operational for any credible accident.11.Check valve1-3-833.Prevents reverse flow in 4" AFW line to SG 4.Stuck open.Stuck closed.Mechanical failure.Mechanical failure.None.Control Room indication via flow indicators FI-3-142A &
-170A.Not a problem if MDP 1B-B is running, if not LCV-3-171 and -171A
will prevent reverse flow thru pump discharge piping.Loss of AFW to SG 4.None.None.TDP 1A-S provides flow to
SG 4.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 6 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-65WATTS BAR WBNP-8912.MDP 1B-B min flow recirc line to CST check valve 3-815.Prevents backflow from CST to MDP 1B-B discharge piping.Stuck closed.Stuck open.Mechanical failure.Mechanical failure.Low flow or none thru FE-131 located on recirc line. Pump high temp as indicated by TI's 3-130 A and B.No method of detection.
MDP 1B-B to overheat and become inoperative preventing AFW flow to SG's 3 & 4 (only if flow demand
is low).No affect on system if MDP 1B-B is running. If MDP 1B-B is not running, system resistance would prvent backflow from
occuring.None.None.TDP 1A-S will provide flow to SG's 3 & 4.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 7 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM10.4-66WATTS BAR WBNP-8913.Check valve 1-3-644Prevents blowdown of SG 4 in case of an AFW line break inside containment.Stuck closed.Stuck open.Mechanical failure.Mechanical failure.Control Room indication via flow indicator FI-3-170A. In
addition to SG level instrumentation.None.Loss of AFW to SG 4.None. Check valve 1-3-645 w ill prevent blowdown of SG 4.None.None.AFW flow required to only two SG's.14.Check valve 1-3-645Backup valve to 1-3-644 (same function)Stuck closed.Stuck open.Mechanical failure.Mechanical failure.Control Room indication via flow indicator FI-3-170A. In
addition to SG level instrumentation.None.Loss of AFW to SG 4.None. Check valve 1-3-644 w ill prevent blowdown of SG 4.None.None.AFW flow required to only two SG's.Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 8 of 8)Train B Failure Modes and Effects AnalysisCooldown for Stage 1 of a DBE FloodMain Feed Line Break with LOOPLarge Break LOCA with LOOPLoss of Normal Feedwater with LOOPMain Steam Line Break with LOOPITEM NO.COMPONENTFUNCTIONFAILURE MODE POTENTIAL CAUSEMETHOD OF DETECTION EFFECTON SYSTEM EFFECT ON PLANTREMARKS 10.4-67WATTS BARWBNP-88Table 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Accident/Transient - GPM (Sheet 1 of 3)ITEM NO.ACCIDENTAFWPUMPSREQ'DMINREQ'D FLOW MAX FLOW ALLOWED(MASS & ENERGY RELEASES) NOTE 1NO OF SG'SREQ'D OR(FAULTED) SG'S AVAILABLE OR REQUIRED 1 LONF Any 2820NAALL 4 SG'S ARE AVAILANY 2 SG'S ARE REQ'D 2 LOOP ANY 1 PUMP 410ALL 4 SG'S ARE AVAILANY 2 SG'S ARE REQ'D3 MS SUDDEN DEPRESSURIZATION3.1 MS S DEPRESS SHORT TERM NONEN/A2840ALL 4 SG's ARE AVAILANY 2 SG's ARE REQ'D3.2 MS S DEPRESS LONG TERM ANY 2820NAALL 4 SG's ARE AVAILANY 2 SG's ARE REQ'D 4 MAIN STEAM LINE BREAK (MSLB) WITH CONCURRENT LOOP4.1 MSLB-SHORT TERM NONENA2840 (1 FAULTED) NOT APP4.2 MSLB-LONG TERM ANY 1410NA ANY 2 SG's ARE REQ'D ANY 3 SG's ARE AVAIL 5 MAIN FEED LINE BREAK (MFLB) WITH CONCURRENT LOOP5.1 MFLB-SHORT TERM NONENA2840ALL FLOW FAULTED TO SG5.2 MFLB-LONG TERM ANY 1 MDP410NAANY 2 SG's ARE REQ'DANY 3 SG's ARE AVAIL5.3 MFLB-LONG TERM TDP720NA 10.4-68 WATTS BARWBNP-88 6 LOCA6.1 LARGE BREAK LOCA ANY 1Note 2NAFAULTED SG HAVE TUBE LEAKS ALL 4 SG's ARE AVAIL6.2 SMALL BREAK LOCA 1 MD + TD1050NAANY 2 SG's ARE REQ'DALL 4 SG'S ARE AVAIL6.3 MSLB MASS & ENERGY (M&E) RELEASE CASES FOR BREAK INSIDE CONTAINMENT SHORT TERM6.4 MSLB M&E IN CASE 1 NONENA2250ALL FLOW FAULTED TO SG 6.5 MSLB M&E CASES 2-4 NONENA1500ALL FLOW FAULTED TO SG 6.6 MSLB M&E CASE 5 NONENA2250ALL FLOW FAULTED TO SG 7 MSLB M&E CASES 6-8 NONENA1500ALL FLOW FAULTED TO SG 8 MSLB M&E CASE 9 NONENA2250ALL FLOW FAULTED TO SG 9 MSLB M&E CASES 10-13 NONENA2040ALL FLOW FAULTED TO SG 10 MSLB OUTSIDE CONT NONENA841 SEE NOTE 3ANY 2 SG'S ARE REQUIREDTable 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Accident/Transient - GPM (Sheet 2 of 3)ITEM NO.ACCIDENTAFWPUMPSREQ'DMINREQ'D FLOW MAX FLOW ALLOWED(MASS & ENERGY RELEASES) NOTE 1NO OF SG'SREQ'D OR(FAULTED) SG'S AVAILABLE OR REQUIRED 10.4-69WATTS BARWBNP-88 11 TOTAL LOSS OF ALL AC POWER (ONLY TDP AVAIL.) TDP410NAANY 2 SG'S ARE REQUIREDALL SG'S ARE AVAILNOTES:1.Maximum allowed flow limit values are dictated by containment pressure and temperature requirements except for Item 10 which is governed by SG pressures.2.For LOCA (Large Breaks), the only AFW flow requirement is to keep the SG's filled above the lower range tap to contain RCS leakage through any failed SG tubes.3.This is the maximum flow from 2 motor-driven pumps (turbine-driven pump assumed to fail) based on faulted steam generator (No. 1) pressure. Reference WCAP-13274, Steamline Break Outside Containment Mass/Energy Releases for the EAGLE-21/Reduced Auxiliary Feedwater Flow Programs.Table 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Accident/Transient - GPM (Sheet 3 of 3)ITEM NO.ACCIDENTAFWPUMPSREQ'DMINREQ'D FLOW MAX FLOW ALLOWED(MASS & ENERGY RELEASES) NOTE 1NO OF SG'SREQ'D OR(FAULTED) SG'S AVAILABLE OR REQUIRED 10.4-70 WATTS BARWBNP-88THIS PAGE INTENTIONALLY BLANK Other Features of Steam and Power Conversion System10.4-71WATTS BAR WBNP-89Figure 10.4-1 Powerhouse Unit 1 Flow Diagram Turbine Drains and Miscellaneous Piping
10.4-72Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-2 General Units 1 & 2 Flow Diagram Condenser Circulating Water Other Features of Steam and Power Conversion System10.4-73WATTS BAR WBNP-89Figure 10.4-3 General Unit 1 Flow Diagram Condenser Circulating Water 10.4-74Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-4 Powerhouse Units 1 & 2 Electrical Control Diagram Condenser Circulating Water System Other Features of Steam and Power Conversion System10.4-75WATTS BAR WBNP-89Figure 10.4-5 Powerhouse Units 1 & 2 Electrical Control Diagram Condenser Circulating Water System 10.4-76Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-6 Powerhouse Units 1 & 2 Electrical Logic Diagram Condenser Circulating Water System Other Features of Steam and Power Conversion System10.4-77WATTS BAR WBNP-82Figure 10.4-7 Powerhouse Units 1 & 2 Flow Diagram Condensate 10.4-78Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-8 Powerhouse Unit 1 Flow Diagram Feedwater Other Features of Steam and Power Conversion System10.4-79WATTS BAR WBNP-89Figure 10.4-9 Powerhouse Unit 1 Electrical Control Diagram Condensate System 10.4-80Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-10 Powerhouse Unit 1 Electrical Control Diagram Condensate System Other Features of Steam and Power Conversion System10.4-81WATTS BAR WBNP-89Figure 10.4-11 Powerhouse Units 1 & 2 Electrical Control Diagram Condensate System 10.4-82Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-11a Powerhouse Units 1 & 2 Electrical Control Diagram Condensate System Other Features of Steam and Power Conversion System10.4-83WATTS BAR WBNP-89Figure 10.4-12 Powerhouse Units 1 & 2 Electrical Logic Diagram Condensate System 10.4-84Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-13 Powerhouse Unit 1 Electrical Logic Control Diagram Condensate System Other Features of Steam and Power Conversion System10.4-85WATTS BAR WBNP-89Figure 10.4-13a Powerhouse Unit 1 Electrical Logic Diagram Condensate System 10.4-86Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-14 Powerhouse Units 1 & 2 Electrical Control Diagram Main Auxiliary Feedwater System Other Features of Steam and Power Conversion System10.4-87WATTS BAR WBNP-89Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet A) 10.4-88Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet B)
Other Features of Steam and Power Conversion System10.4-89WATTS BAR WBNP-89Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet C) 10.4-90Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet D)
Other Features of Steam and Power Conversion System10.4-91WATTS BAR WBNP-89Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System 10.4-92Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet A)
Other Features of Steam and Power Conversion System10.4-93WATTS BAR WBNP-89Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet B) 10.4-94Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet C)
Other Features of Steam and Power Conversion System10.4-95WATTS BAR WBNP-89Figure 10.4-16 Powerhouse Unit 1 Auxiliary Feedwater System Control Diagram 10.4-96Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-16a Powerhouse Unit 1 Auxiliary Feedwater System Control Diagram Other Features of Steam and Power Conversion System10.4-97WATTS BAR WBNP-89Figure 10.4-17 Powerhouse Units 1 & 2 Electrical Logic Diagram Feedwater Pump Turbine Aux 10.4-98Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-18 Powerhouse Units 1 & 2 Electrical Logic Diagram Feedwater System Other Features of Steam and Power Conversion System10.4-99WATTS BAR WBNP-89Figure 10.4-19 Powerhouse Unit 1 Electrical Logic Diagram Auxiliary Feedwater System 10.4-100Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-20 Powerhouse Units 1 & 2 Auxiliary Feedwater System Logic Diagram Other Features of Steam and Power Conversion System10.4-101WATTS BAR WBNP-91Figure 10.4-21 Powerhouse Units 1 & 2 Flow Diagram Auxiliary Feedwater 10.4-102Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-82Figure 10.4-21a Powerhouse Units 1 & 2 Flow Diagram Main & Auxiliary Feedwater Other Features of Steam and Power Conversion System10.4-103WATTS BAR WBNP-82Figure 10.4-22 Deleted 10.4-104Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-82Figure 10.4-23 Deleted Other Features of Steam and Power Conversion System10.4-105WATTS BAR WBNP-89Figure 10.4-24 Powerhouse Units 1 & 2 Flow Diagram Steam Generator Blowdown System 10.4-106Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-82Figure 10.4-25 Deleted Other Features of Steam and Power Conversion System10.4-107WATTS BAR WBNP-82Figure 10.4-26 Deleted 10.4-108Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-27 Powerhouse Unit 1 Flow Diagram High Pressure Heater Drains and Vents Other Features of Steam and Power Conversion System10.4-109WATTS BAR WBNP-89Figure 10.4-28 Powerhouse Unit 1 Flow Diagram Low Pressure Heater Drains and Vents 10.4-110Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-29 Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents System Other Features of Steam and Power Conversion System10.4-111WATTS BAR WBNP-89Figure 10.4-30 Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents System 10.4-112Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-31 Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents System Other Features of Steam and Power Conversion System10.4-113WATTS BAR WBNP-89Figure 10.4-32 Powerhouse Unit 1 Electrical Control Diagram Heater Drains and Vents System 10.4-114Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-33 Powerhouse Unit 1 Mechanical Control Diagram Heater Drains and Vents System Other Features of Steam and Power Conversion System10.4-115WATTS BAR WBNP-89Figure 10.4-34 Powerhouse Unit 1 Electrical Logic Diagram Heater Drains and Vents 10.4-116Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-35 Powerhouse Unit 1 Electrical Logic Diagram Heater and Vents Other Features of Steam and Power Conversion System10.4-117WATTS BAR WBNP-89Figure 10.4-36a Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System 10.4-118Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-36b Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System Other Features of Steam and Power Conversion System10.4-119WATTS BAR WBNP-89Figure 10.4-36c Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System 10.4-120Other Features of Steam and Power Conversion SystemWATTS BAR WBNP-89Figure 10.4-37 Powerhouse Unit 1 Flow Diagram Steam Generator Wet Layup Sys. Closed Recirculation-Loop Sys.