ML093370377
| ML093370377 | |
| Person / Time | |
|---|---|
| Site: | Watts Bar  |
| Issue date: | 11/24/2009 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| References | |
| Download: ML093370377 (184) | |
Text
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.0 MAIN STEAM AND POWER CONVERSION SYSTEMS 10.1
SUMMARY
DESCRIPTION 10.1-1 10.2 TURBINE-GENERATOR 10.2-1 10.2.1 Design Bases 10.2-1 10.2.2 Description 10.2-1 10.2.3 Turbine Rotor and Disc Integrity 10.2-5 10.2.3.1 Materials Selection 10.2-5 10.2.3.2 Fracture Toughness 10.2-7 10.2.3.3 High Temperature Properties 10.2-9 10.2.3.4 Turbine Disc Design 10.2-9 10.2.3.5 Preservice Inspection 10.2-9 10.2.3.6 Inservice Inspection 10.2-11 10.2.4 Evaluation 10.2-13 10.3 MAIN STEAM SUPPLY SYSTEM 10.3-1 10.3.1 Design Bases 10.3-1 10.3.2 System Description 10.3-1 10.3.2.1 System Design 10.3-1 10.3.2.2 Material Compatibility, Codes, and Standards 10.3-2 10.3.3 Design Evaluation 10.3-2 10.3.4 Inspection and Testing Requirements 10.3-3 10.3.5 Water Chemistry 10.3-3 10.3.5.1 Purpose 10.3-3 10.3.5.2 Feedwater Chemistry Specifications 10.3-4 10.3.5.3 Operating Modes 10.3-4 10.3.5.4 Effect of Water Chemistry on the Radioactive Iodine Partition Coefficient 10.3-5 10.3.6 Steam and Feedwater System Materials 10.3-5 10.3.6.1 Fracture Toughness 10.3-5 10.3.6.2 Materials Selection and Fabrication 10.3-5 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1 10.4.1 Main Condenser 10.4-1 10.4.1.1 Design Bases 10.4-1 10.4.1.2 System Description 10.4-1 10.4.1.3 Safety Evaluation 10.4-4 10.4.1.4 Inspection and Testing 10.4-5 10.4.1.5 Instrumentation 10.4-5 10.4.2 Main Condenser Evacuation System 10.4-5 10.4.2.1 Design Bases 10.4-5 10.4.2.2 System Description 10.4-5 Table of Contents 10-i
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.4.2.3 Safety Evaluation 10.4-6 10.4.2.4 Inspection and Testing 10.4-6 10.4.2.5 Instrumentation 10.4-6 10.4.3 Turbine Gland Sealing System 10.4-7 10.4.3.1 Design Bases 10.4-7 10.4.3.2 System Description 10.4-7 10.4.3.3 Safety Evaluation 10.4-7 10.4.3.4 Inspection and Testing 10.4-8 10.4.3.5 Instrumentation 10.4-8 10.4.4 Turbine Bypass System 10.4-8 10.4.4.1 Design Bases 10.4-8 10.4.4.2 System Description 10.4-8 10.4.4.3 Safety Evaluation 10.4-9 10.4.4.4 Inspection and Testing 10.4-10 10.4.5 Condenser Circulating Water System 10.4-10 10.4.5.1 Design Basis 10.4-11 10.4.5.2 System Description 10.4-11 10.4.5.3 Safety Evaluation 10.4-13 10.4.5.4 Inspection and Testing 10.4-14 10.4.5.5 Instrumentation Application 10.4-14 10.4.6 Condensate Polishing Demineralizer System 10.4-15 10.4.6.1 Design Bases - Power Conversion 10.4-15 10.4.6.2 System Description 10.4-15 10.4.6.3 Safety Evaluation 10.4-17 10.4.6.4 Inspection and Testing 10.4-18 10.4.6.5 Instrumentation 10.4-18 10.4.7 Condensate and Feedwater Systems 10.4-19 10.4.7.1 Design Bases 10.4-19 10.4.7.2 System Description 10.4-19 10.4.7.3 Safety Evaluation 10.4-26 10.4.7.4 Inspection and Testing 10.4-28 10.4.7.5 Instrumentation 10.4-28 10.4.8 Steam Generator Blowdown System 10.4-28 10.4.8.1 Design Bases 10.4-28 10.4.8.2 System Description and Operation 10.4-30 10.4.8.3 Safety Evaluation 10.4-30 10.4.8.4 Inspections and Testing 10.4-31 10.4.9 Auxiliary Feedwater System 10.4-32 10.4.9.1 Design Bases 10.4-32 10.4.9.2 System Description 10.4-32 10.4.9.3 Safety Evaluation 10.4-34 10.4.9.4 Inspection and Testing Requirements 10.4-37 10.4.9.5 Instrumentation Requirements 10.4-37 10.4.10 Heater Drains and Vents 10.4-38 10-ii Table of Contents
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page 10.4.10.1 Design Bases 10.4-38 10.4.10.2 System Description 10.4-38 10.4.10.3 Safety Evaluation 10.4-43 10.4.10.4 Inspection and Testing 10.4-44 10.4.10.5 Instrumentation 10.4-44 10.4.11 Steam Generator Wet Layup System 10.4-44 10.4.11.1 Design Bases 10.4-44 10.4.11.2 System Description 10.4-44 10.4.11.3 Safety Evaluation 10.4-45 10.4.11.4 Inspection and Testing 10.4-45 10.4.11.5 Instrumentation 10.4-45 Table of Contents 10-iii
WATTS BAR WBNP-76 TABLE OF CONTENTS Section Title Page THIS PAGE INTENTIONALLY BLANK 10-iv Table of Contents
WATTS BAR WBNP-76 LIST OF TABLES Section Title Table 10.1-1 (Sheet 1 of 6) Summary of Important Component Design Parameters Vertical Steam Generators Table 10.1-1 (Sheet 2 of 6) Summary of Important Component Design Parameters Moisture Separator and Reheaters Table 10.1-1 (Sheet 3 of 6) Summary Of Important Component Design Parameters (Continued) Standby Main Feedwater Pumps Table 10.1-1 (Sheet 4 of 6) Summary of Important Component Design Parameters No. 7 Heater Drain Pumps Table 10.1-1 (Sheet 5 of 6) Summary of Important Component Design Parameters (Continued) Condenser Table 10.1-1 (Sheet 6 of 6) Summary of Important Design Parameters Safety Valves Table 10.3-1 Main Steam Supply System Applicable Codes, Standards, and Design Condition Table 10.3-2 Ethanolamine AVT Steam Generator Side and Feedwater Chemistry Specifications Limits1Deleted by Amendment 95 Table 10.3-3 Deleted by Amendment 43 Table 10.3-4 Deleted by Amendment 43 Table 10.4-1 Deleted by Amendment 43 Table 10.4-2 Auxiliary Feedwater Pump Parameters Table 10.4-3 Failure Analysis, Steam Generator Blowdown System Table 10.4-4 Failure Mode & Effects Analysis Steam Supply Subsystem Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsys-tem (Steam Generator (SG) - Loop No. 4 Typical Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical)
Table 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Acci-dent/Transient - GPM List of Tables 10-v
WATTS BAR WBNP-76 LIST OF TABLES Section Title THIS PAGE INTENTIONALLY BLANK 10-vi List of Tables
WATTS BAR WBNP-95 LIST OF FIGURES Section Title Figure 10.1-1 Powerhouse Units 1 & 2 Flow Diagram General Plant Systems Figure 10.1-2 Deleted by Amendment 95 Figure 10.1-3 Deleted by Amendment 95 Figure 10.2-1 Powerhouse Unit 1 Wiring Diagram Turbo-Generator Auxiliaries Sche-matic Diagrams Figure 10.2-2 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System Figure 10.2-2 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A)
Figure 10.2-3 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System Figure 10.2-3 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont Sys (Sheet A)
Figure 10.2-4 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System Figure 10.2-4 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A)
Figure 10.3-1 Powerhouse Unit 1 Flow Diagram - Main and Reheat Steam Figure 10.3-2 Powerhouse Unit 1 Electrical Control Diagram - Main Steam System Figure 10.3-3 Powerhouse Unit 1 Electrical Control Diagram - Main Steam System Figure 10.3-3 Sh A Powerhouse Unit 1 Electrical Control Diagram Main Steam System Figure 10.3-4 Powerhouse Unit 1 Electrical Control Diagram Main Steam System Figure 10.3-4 Sh A Powerhouse Unit 1 Electrical Control Diagram Main Steam System Figure 10.3-5 Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat Steam Figure 10.3-6 Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat Steam Figure 10.3-7 Powerhouse Units 1& 2 Electrical Logic Diagram Main and Reheat Steam Figure 10.3-8 Deleted by Amendment 95 Figure 10.3-9 Powerhouse Units 1 & 2 Flow Diagram Feedwater Treatment Second-ary Chemical Feed Figure 10.4-1 Powerhouse Unit 1 Flow Diagram Turbine Drains and Miscellaneous Piping Figure 10.4-2 General Units 1 & 2 Flow Diagram Condenser Circulating Water Figure 10.4-3 General Unit 1 Flow Diagram Condenser Circulating Water Figure 10.4-4 Powerhouse Units 1 & 2 Electrical Control Diagram Condenser Circu-lating Water System Figure 10.4-5 Powerhouse Units 1 & 2 Electrical Control Diagram Condenser Circu-lating Water System Figure 10.4-6 Powerhouse Units 1 & 2 Electrical Logic Diagram Condenser Circulat-ing Water System Figure 10.4-7 Powerhouse Units 1 & 2 Flow Diagram Condensate Figure 10.4-8 Powerhouse Unit 1 Flow Diagram Feedwater Figure 10.4-9 Powerhouse Unit 1 Electrical Control Diagram Condensate System Figure 10.4-10 Powerhouse Unit 1 Electrical Control Diagram Condensate System List of Figures 10-vii
WATTS BAR WBNP-91 LIST OF FIGURES Section Title Figure 10.4-11 Powerhouse Units 1 & 2 Electrical Control Diagram Condensate Sys-tem Figure 10.4-11a Powerhouse Units 1 & 2 Electrical Control Diagram Condensate Sys-tem Figure 10.4-12 Powerhouse Units 1 & 2 Electrical Logic Diagram Condensate System Figure 10.4-13 Powerhouse Unit 1 Electrical Logic Control Diagram Condensate Sys-tem Figure 10.4-13a Powerhouse Unit 1 Electrical Logic Diagram Condensate System Figure 10.4-14 Powerhouse Units 1 & 2 Electrical Control Diagram Main Auxiliary Feedwater System Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet A)
Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet B)
Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet C)
Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwa-ter System (Sheet D)
Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet A)
Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet B)
Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet C)
Figure 10.4-16 Powerhouse Unit 1 Auxiliary Feedwater System Control Diagram Figure 10.4-16a Powerhouse Unit 1 Auxiliary Feedwater System Control Diagram Figure 10.4-17 Powerhouse Units 1 & 2 Electrical Logic Diagram Feedwater Pump Turbine Aux Figure 10.4-18 Powerhouse Units 1 & 2 Electrical Logic Diagram Feedwater System Figure 10.4-19 Powerhouse Unit 1 Electrical Logic Diagram Auxiliary Feedwater Sys-tem Figure 10.4-20 Powerhouse Units 1 & 2 Auxiliary Feedwater System Logic Diagram Figure 10.4-21 Powerhouse Units 1 & 2 Flow Diagram Auxiliary Feedwater Figure 10.4-21a Powerhouse Units 1 & 2 Flow Diagram Main & Auxiliary Feedwater Figure 10.4-22 Deleted Figure 10.4-23 Deleted Figure 10.4-24 Powerhouse Units 1 & 2 Flow Diagram Steam Generator Blowdown System Figure 10.4-25 Deleted Figure 10.4-26 Deleted 10-viii List of Figures
WATTS BAR WBNP-94 LIST OF FIGURES Section Title Figure 10.4-27 Deleted by Amendment 94 Figure 10.4-28 Deleted by Amendment 94 Figure 10.4-29 Deleted by Amendment 94 Figure 10.4-30 Deleted by Amendment 94 Figure 10.4-31 Deleted by Amendment 94 Figure 10.4-32 Deleted by Amendment 94 Figure 10.4-33 Deleted by Amendment 94 Figure 10.4-34 Deleted by Amendment 94 Figure 10.4-35 Deleted by Amendment 94 Figure 10.4-36a Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System Figure 10.4-36b Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System Figure 10.4-36c Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System Figure 10.4-37 Deleted by Amendment 94 List of Figures 10-ix
WATTS BAR WBNP-91 LIST OF FIGURES Section Title THIS PAGE INTENTIONALLY BLANK 10-x List of Figures
WATTS BAR WBNP-95 021_TVA_WB_FSAR_Section_10.pdf 10.0 MAIN STEAM AND POWER CONVERSION SYSTEMS 10.1
SUMMARY
DESCRIPTION The 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 heaters. The second stage reheater is supplied with main steam.The condensed steam cascades to the No. 1 heaters.
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 steam generator blowdown 2nd stage heat exchanger, the main feed pump turbine condensers, and then through three parallel strings of low-pressure heaters. This flow path can also split off to the steam generator blowdown 1st stage heat exchangers. Each string consists of three stages (Nos. 7 through 5, 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, steam generator blowdown 2nd stage heat exchanger, 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 and to the suction of the condensate booster pumps. 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.
4 through 2) of extraction feedwater heaters.
SUMMARY
DESCRIPTION 10.1-1
WATTS BAR WBNP-95 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.
Heat 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.
References
- 1. Westinghouse letter WAT-D-7489, Watts Bar Nuclear Plant Numbers 1 and 2 -
Main Steam Safety Valves Excess Blowdown Analysis - Phase 2, August 28, 1987 10.1-2
SUMMARY
DESCRIPTION
WATTS BAR WBNP-95 Table 10.1-1 (Sheet 1 of 6)
Summary of Important Component Design Parameters Vertical Steam Generators (All Values Nominal)
Number - 4 per unit Length - 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) material Operating conditions at 100 Percent Load Steam flow rate - 3.78 x E6 lb/hr Steam temperature - 542.8 deg F Steam pressure - 986 psia Steam quality - 99.75 percent minimum TURBOGENERATOR Manufacturer - Siemens Energy, Inc.
Turbo generator nameplate rating - 1,241.2 MW Turbine type -Horizontal, reaction, tandem-compound, two stage reheat, extraction, condensing 1800-rpm single shaft - 1 HP and 3 LP turbines with 6-flow exhaust and 46 in. last-stage blades Generator type and maximum nameplate rating - One direct connected, hydrogen cooled rotor, water-cooled stator, 1,411,000 kVA, 0.9 PF, 75 pisg hydrogen, 3 phase, 60 Hz, 24,000 V, 33,943 Amp, 0.6 scr, Y-connected Exciter type and capacity - One shaft-driven, brushless -
6000 kW, 550 volt DC, 1800 rpm Heat Rate Guaranteed 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/kWh 1,218,225 9593
SUMMARY
DESCRIPTION 10.1-3
WATTS BAR WBNP-95 Table 10.1-1 (Sheet 2 of 6)
Summary of Important Component Design Parameters (continued)
Moisture Separator and Reheaters (All Values Nominal)
Number 6 per unit Type Moisture removal separator and 2-stage reheat (HP and LP)
Size 51 ft - 8.25 inches length, 11 ft - 8,5 inches diameter MAIN FEEDWATER PUMP TURBINE (See Section 10.4.7.2.)
MAIN FEEDWATER PUMPS 10.1-4
SUMMARY
DESCRIPTION
WATTS BAR WBNP-95 (See Section 10.4.7.2.)
Table 10.1-1 (Sheet 3 of 6)
Summary Of Important Component Design Parameters (Continued)
Standby Main Feedwater Pumps (All Values Nominal (See Section 10.4.7.2.)
CONDENSATE BOOSTER PUMPS (See Section 10.4.7.2.)
NO. 3 HEATER DRAIN PUMPS Number - 3 Manufacturer - Borg-Warner Corporation, Byron-Jackson Pump Division Type - 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
SUMMARY
DESCRIPTION 10.1-5
WATTS BAR WBNP-95 Table 10.1-1 (Sheet 4 of 6)
Summary of Important Component Design Parameters (continued)
No. 7 Heater Drain Pumps (All Values Nominal)
Number - 2 Manufacturer - 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 speed CONDENSATE HOTWELL PUMPS (See Section 10.4.7.2.)
DEMINERALIZED CONDENSATE PUMPS (See Section 10.4.7.2.)
10.1-6
SUMMARY
DESCRIPTION
WATTS BAR WBNP-95 Table 10.1-1 (Sheet 5 of 6)
Summary of Important Component Design Parameters (Continued)
Condenser (All Values Nominal)
Number - 1 Manufacturer - 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 welded 1.0 in. outside diameter, Tubes are SEA-CURE 104 tubes are 18 BWG (in the top row), the remaining 27,306 tubes are 22 BWG 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 flow, gpm - 410,000 Cleanliness, percent - 95 Duty, 109 Btu/hr - 7.789 Design pressures: Shell, psig - 25 and vacuum Hotwell, psig - 30 Waterboxes, psig - 72 Air Removal Equipment Number - 3 Manufacturer - Nash Engineering Company Size - AT2004E Type - Mechanical, vacuum (2 stage liquid ring)
Design point - Suction pressure in. of Hg absolute - 1.0, Rated capacity, each - 15 SCFM Motor Manufacturer - General Electric Company Motor design -100 HP, 514 rpm, 460 V, 3 ph, 60 HZ horizontal, constant speed FEEDWATER HEATER (See Section 10.4.7.2.)
SUMMARY
DESCRIPTION 10.1-7
WATTS BAR WBNP-95 Table 10.1-1 (Sheet 6 of 6)
Summary of Important Design Parameters (continued)
Safety Valves (All Values Nominal)
Number - 5 per steam generator Minimum flow capacity, lb/hr steam generator - 4,160,597 Rated Blowdown Press.
Accumu- Max. Press. Flow Press. In.
lation Expected in Steam at Set Below Steam Press. Accumu- Header Pressure Set Header to fully lation at Rated + 3% Pressure at Set Open Press at Relieving Accumu- to Valve Valve Press. Valve max Flow Flow lation Close Closing Mark No. (psig) % % (psig) (lb/hr) (%)[1] (psig) 47W400-101 1185 3 8.4 1284 791,563 10 1066.5 47W400-102 1195 3 7.4 1284 798,163 10 1075.5 47W400-103 1205 3 6.6 1284 804,764 10 1084.5 47W400-104 1215 3 5.7 1284 811,364 10 1093.5 47W400-105 1224 3 4.9 1284 817,304 10 1101.6 Note1 - The licensing basis for the WBN plant is 10% maximum blowdown (See Reference [1]). This is more conservative than the 5% maximum blowdown specified by the ASME Section III requirements.
Atmospheric Relief Valves Number 1 - per steam generator Minimum capacity, lb/hr/inlet pressure, psig - 64,000/85 Maximum capacity, lb/hr/inlet pressure, psig - 970,000/1185 outlet pressure, psig - 0 Turbine Bypass Valves Number of valves - 12 Flow 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)
Full stoke modulation, seconds 20 Failure position - Closed 10.1-8
SUMMARY
DESCRIPTION
WATTS BAR Main Steam and Power Conversion Systems WBNP-86 Figure 10.1-1 Powerhouse Units 1 & 2 Flow Diagram General Plant Systems 10.1-9
WATTS BAR WBNP-95 Figure 10.1-2 Deleted by Amendment 95 10.1-10 Main Steam and Power Conversion Systems
WATTS BAR WBNP-95 Figure 10.1-3 Deleted by Amendment 95 Main Steam and Power Conversion Systems 10.1-11
WATTS BAR WBNP-86 THIS PAGE INTENTIONALLY BLANK 10.1-12 Main Steam and Power Conversion Systems
WATTS BAR WBNP-95 10.2 TURBINE-GENERATOR 10.2.1 Design Bases The 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 Siemens (formerly Westinghouse) turbine generator data is 1,241,200 kW when the steam flow is 14,565,293 lb/hr steam conditions of 985 psia, 0.25% (0.39% at turbine) moisture, and at a zonal back pressure of 1.92/2.70/3.75-inches of Hg absolute, with 0% makeup under normal conditions. At the valves wide open or stretch condition the generator is rated at 1,268,900 kW with a steam flow of 14,855,223 lb/hr at 985 psia, 0.31% 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.
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 Description The 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 46-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.
TURBINE-GENERATOR 10.2-1
WATTS BAR WBNP-92 The 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 cabinet 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).
10.2-2 TURBINE-GENERATOR
WATTS BAR WBNP-92 The 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 analog 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 basis 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 system. 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 TURBINE-GENERATOR 10.2-3
WATTS BAR WBNP-92 emergency 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 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.
10.2-4 TURBINE-GENERATOR
WATTS BAR WBNP-95 In 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 Integrity The 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 Selection The detailed materials specifications, fabrication history, and chemical analysis of the disc and rotor forgings are considered proprietary information of the turbine manufacturer, Siemens (formerly Westinghouse Electric Corporation). The high pressure rotor is made of NiCrMoV alloy steel. The specified minimum mechanical properties are as follows:
Tensile Strength, psi 118,900 Yield Strength, psi (0.2% offset) 84,100 - 98,600 Elongation in 2-inches, percent 16 Reduction of Area, percent 50 Impact Strength, Charpy V-Notch, ft-lb 66 (min. at room temperature) 50% Fracture Appearance Transition -22 Temperature, degrees F, max..
TURBINE-GENERATOR 10.2-5
WATTS BAR WBNP-95 The HP inner casing and guide blade carriers are made of stainless steel castings. The HP outer casing cover and base are made of carbon-steel castings. The specified minimum mechanical properties are as follows:
Property Guide Blade Carriers and Outer Casing Base &
Inner Casing Cover Material Modified ASTM A487 ASTM A216 Grade WCB Grade CA15 Tensile Strength, psi 78,500 - 100,000 70,000 Yield Strength, psi 51,500 36,000 Elongation in 2-inches, percent 18 22 Reduction of Area, percent 45 35 The casing cover and base are tied together by means of more than 100 studs. For most of the horizontal joint, the stud material is an alloy steel; while in the blade ring fit and gland areas, the studs are upgraded to 12 Cr stainless steel. The bolting has the following minimum properties:
12 Cr Studs Property Low Alloy Steel Studs and Bolts and Bolts 2-1/2 inch Over 2-1/2 Over 4 No Size and less to 4 inch to 7 inch Constraint ASTM A193 Grade B7 Modified AISI 616 Tensile Strength, psi 125,000 115,000 110,000 135,000 Yield Strength, (0.2% 105,000 95,000 85,000 110,000 offset), psi Elongation in 2-inches, 16 16 16 14 percent Reduction of area, 50 50 45 32 percent The low pressure rotors are made of NiCrMoV alloy steel. The specified minimum mechanical properties are as follows:
10.2-6 TURBINE-GENERATOR
WATTS BAR WBNP-95 Property Rotor Shaft Tensile Strength, psi 149,390 Yield Strength, psi (0.2% offset) 107,300 - 121,800 Elongation in 2-inches, percent 15 Reduction of Area, percent 45 Impact Strength, Charpy V-Notch, ft-lb (at room temperature) 74 50% Fracture Appearance Transition Temperature °F, (max.) -58 The LP outer cylinder and inner casing are fabricated mainly of carbon steel plate material. The minimum specified properties are as follows:
Property Outer Cylinder Inner Casing ASTM A515 - GR65 ASTM A515- GR60, GR65, GR70*
Tensile Strength, psi 65,000 56,500 - 76,900 Yield Strength, psi 35,000 26,800 - 38,400 Elongation in 8 ft, percent 19 22 Elongation in 2 ft, percent 23 22
- Note: Grade of material depends upon location within LP inner casing fabrication and plate thickness.
The shrunk-on discs are made of NiCrMoV alloy steel. There are six discs shrunk on the shaft with three per flow. The minimum specified mechanical properties for the discs are as follows:
Disc 1 Discs 2 and 3 Tensile Strength, psi 146,500 153,700 Yield Strength, psi 113,100 - 123,300 118,900 -
129,100 Elongation in 2 ft (disc hub) percent 15 15 Elongation in 2 ft (disc rim) percent 15 15 Reduction of area (disc hub) percent 50 50 Reduction of area (disc rim) percent 50 50 TURBINE-GENERATOR 10.2-7
WATTS BAR WBNP-95 Disc 1 Discs 2 and 3 Impact strength (hub and rim) Charpy 96 96 V-Notch, ft-lb (at room temp) 50% Fracture Appearance -112 -112 Transition Temp. (disc hub and rim) °F (max) 10.2.3.2 Fracture Toughness Fracture mechanics analysis by the Siemens Methodology is described in the missile report. A brief 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:
2 Q K IC a CR = -------------- ---------
1.21 eff where aCR = Critical flaw size KIC = Fracture toughness eff = Effective tangential bore stress Q = Flaw shape parameter Stress corrosion cracking (SCC) rate is assumed to be independent of the stress intensity level. The main parameters influencing the SCC rate are temperature, material yield strength and water chemistry. Based on field measurements and laboratory test data, empirical equations for SCC rates were developed. For the probabilistic analysis, the following SCC rate is used:
da 7302 -
= exp - 4.968 - ------------------ + 0.0278 y dt T + 460 Where:
(da/dt) = SCC rate given in inches/hour 10.2-8 TURBINE-GENERATOR
WATTS BAR WBNP-95 T = Temperature in °F y = Yield strenth in ksi For probabilistic computations, Siemens has developed a numerical Monte-Carlo simulation code, PDBURST. As a failure condition, the brittle fracture mode is assumed:
t a cr ( K lc, Y, , , k ) a i + a* ( Y, T ) dt o
Where:
acr = Critical crack size, a = Current crack size, ai = Initial crack size, t = Operating time duration,
= Crack shape factor (crack depth to crack length ratio),
Klc = Fracture toughness, k = Branching factor,
= Applied load due to tangential stress at bore, y = Yield strength, T = Temperature.
For probabilistic analysis the critical crack size is defined as that given by the equation shown or 100 mm whichever is smaller. The 100 mm limit is purely based on the applicability limitation of linear-elastic fracture mechanics concept and does not necessarily represent an imminent burst condition.
In the Monte-Carlo simulation, disc property inputs include disc metal temperature, disc tangential bore stress, fracture toughness, disc yield strength, disc crack initiation probability based on historical data and standard deviation values. Typically, one million simulations are run to determine how many failures occur a a result of crack initiation and growth to critical crack size.
10.2.3.3 High Temperature Properties The stress-rupture properties of the high pressure rotor material are considered to be proprietary information of the turbine manufacturer, Siemens.
TURBINE-GENERATOR 10.2-9
WATTS BAR WBNP-95 10.2.3.4 Turbine Disc Design Information on the tangential and radial stresses in the low pressure discs and low pressure rotors is considered proprietary information of the turbine manufacturer, Siemens.
10.2.3.5 Preservice Inspection 10.2.3.5.1 Low Pressure Turbine Rotor The 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.
(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 Siemens 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 Siemens 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) 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.
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 Siemens specification which exceeds the requirements of ASTM A-418.
10.2-10 TURBINE-GENERATOR
WATTS BAR WBNP-95 (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.
(4) If ultrasonic examination shows indications in the near surface area of the disc bore, a magnetic particle inspection is required.
(5) During heat treatment of the disc, special requirements are applied to ensure that compressive residual stresses shall be induced in the bore by intensive cooling.
After the preheated discs are assembled to the rotor body to obtain the specified interference fit, Disc 1 holes are drilled and reamed for axial locking pins at the rotor and disc interface. Discs 2 and 3 rely upon shrink fit only. 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 Rotor The 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) Tensile and impact mechanical properties (6) Heater box and 120% speed test 10.2.3.5.3 Preoperational and Initial Startup Testing These tests are documented in Chapter 14.0.
10.2.3.6 Inservice Inspection 10.2.3.6.1 Turbine Rotors To help guard against possible failure of low pressure nuclear steam turbine discs, Siemens 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.
TURBINE-GENERATOR 10.2-11
WATTS BAR WBNP-95 The inspection intervals recommended by Siemens and based on NRC criterion are 100,000 operating hours. In addition, if there is evidence of significant corrosion found during any of the low pressure turbine rotor inspections, Siemens will be consulted and the inspection intervals adjusted accordingly. If measurable cracks are detected, the inspection intervals will be adjusted after considering Siemens 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 Protection In 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 Siemens. 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 6 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 10.2-12 TURBINE-GENERATOR
WATTS BAR WBNP-95 and 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 (Unit 2)
/ quarterly (Unit 1) 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 (Unit 2) / quarterly (Unit 1) 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 Features There 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 Siemens recommendations.
10.2.4 Evaluation The following operational occurrences can be caused by operation of turbine, generator, or distribution system protection equipment:
TURBINE-GENERATOR 10.2-13
WATTS BAR WBNP-95 (1) Turbine trip due to turbine abnormalities.
(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 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 Auto Stop Oil Pressure Trip (7) 111% Rated Speed Electrical Overspeed Trip (8) 110% Rated Speed Mechanical Overspeed Trip (9) EHC dc Power Failure Trip (10) Loss of Both Main Feedwater Turbines Trip (11) Steam Generator High-High Level Trip (II) Automatic Turbine Trips Due To Generator (Electrical) Abnormalities (1) Generator Differential Current Trip (2) Generator System Ground Fault Trip (3) Generator Time Overcurrent (Voltage Supervised) Trip (4) Generator Negative Sequence Trip (5) Generator Backup and Main Transformer Feeder Differential Trip (6) Generator Loss of Field Trip (7) Generator Over-volts per hertz trip 10.2-14 TURBINE-GENERATOR
WATTS BAR WBNP-95 (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 Breaker Failure Trip (14) Unit 1, 500 kV Bus 2 Differential Trip (trips both units if Bus 1 is de-energized)
(15) Unit 2, 500 kV Breaker Failure Trip (16) Unit 2, 500 kV Bus 1 Differential Trip (trips both units if Bus 2 is de-energized)
(17) 1 and/or 2 Generator Breaker Open The 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 condenser 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 throttle valves is arranged with a paired governor valve and each of the six reheat stop valves is arranged in series with an interceptor valve.
TURBINE-GENERATOR 10.2-15
WATTS BAR WBNP-95 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 110%, 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 energizes 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 needs 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 MSR drain lines. Consequently, the above heaters and MSR drains cannot 'flash back' and cause or significantly contribute to a turbine overspeed situation.
10.2-16 TURBINE-GENERATOR
WATTS BAR WBNP-92 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 (1) None TURBINE-GENERATOR 10.2-17
WATTS BAR WBNP-82 THIS PAGE INTENTIONALLY BLANK 10.2-18 TURBINE-GENERATOR
WATTS BAR Turbine-Generator WBNP-91 Figure 10.2-1 Powerhouse Unit 1 Wiring Diagram Turbo-Generator Auxiliaries Schematic Diagrams 10.2-19
WATTS BAR 10.2-20 Turbine-Generator WBNP-89 Figure 10.2-2 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System
WATTS BAR Turbine-Generator WBNP-89 Figure 10.2-2 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A) 10.2-21
WATTS BAR 10.2-22 Turbine-Generator WBNP-91 Figure 10.2-3 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System
WATTS BAR Turbine-Generator WBNP-89 Figure 10.2-3 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont Sys (Sheet A) 10.2-23
WATTS BAR 10.2-24 Turbine-Generator WBNP-89 Figure 10.2-4 Powerhouse Unit 1 Electrical Control Diagram Turbo-Generator Cont System
WATTS BAR Turbine-Generator WBNP-89 Figure 10.2-4 Powerhouse Unit 2 Electrical Control Diagram Turbo-Generator Cont System (Sheet A) 10.2-25
WATTS BAR WBNP-89 THIS PAGE INTENTIONALLY BLANK 10.2-26 Turbine-Generator
WATTS BAR WBNP-92 10.3 MAIN STEAM SUPPLY SYSTEM 10.3.1 Design Bases The 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 Design The 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.
MAIN STEAM SUPPLY SYSTEM 10.3-1
WATTS BAR WBNP-92 The 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 Compatibility, Codes, and Standards All 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 Evaluation The 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.
10.3-2 MAIN STEAM SUPPLY SYSTEM
WATTS BAR WBNP-95 The 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.
See Section 3.11 for Environmental Design of the main steam supply system.
10.3.4 Inspection and Testing Requirements Performance 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.
Inservice inspection requirements are given in Chapter 3.
Preoperational test requirements are given in Chapter 14.
MAIN STEAM SUPPLY SYSTEM 10.3-3
WATTS BAR WBNP-95 10.3.5 Water Chemistry 10.3.5.1 Purpose Water chemistry control in the secondary systems such as the steam generator steam side, feedwater, and condensate for various operating modes and conditions has been established to minimize corrosion and damage to the steam generators and to minimize fouling of steam generator heat transfer surfaces.
10.3.5.2 Feedwater Chemistry Specifications The 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 approximately 87.5 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 10.3-4 MAIN STEAM SUPPLY SYSTEM
WATTS BAR WBNP-95 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 piping, 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 hydroxide are used during wet layup of the steam generators. The layup chemicals are injected into the steam generators during cold shutdown, sampled using existing steam generator sample line(s), and completely mixed by bubbling nitrogen through the bottom of the steam generator.
(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 Chemistry on the Radioactive Iodine Partition Coefficient As 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 Feedwater System Materials 10.3.6.1 Fracture Toughness Requirements 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.
MAIN STEAM SUPPLY SYSTEM 10.3-5
WATTS BAR WBNP-95 10.3.6.2 Materials Selection and Fabrication Code 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 TVAs position for the cleaning and handling of Class 2 and 3 components in accordance with Regulatory Guide 1.37.
Cleaning and cleanness of fluid systems and components are in accordance with ANSI N45-2-1-1973, or later.
With the exception of Regulatory Position C-1(b), and C-4, this system complies with Regulatory Guide 1.50, Control of Preheat Temperature for Welding of Low-Alloy Steels.
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 10.3-6 MAIN STEAM SUPPLY SYSTEM
WATTS BAR WBNP-63 Table 10.3-1 Main Steam Supply System Applicable Codes, Standards, and Design Condition Steam Generator Shell
- a. Design pressure, 1185 psig
- b. Design temperature, 600°F
- c. 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°F
- c. TVA Class B - Code, ASME Boiler and Pressure Vessel Code,Section III, Class 2 TVA Class H - Code, ANSI B31.1, Code for Pressure Piping Main Steam Isolation Valves
- a. Design pressure, 1185 psig
- b. Design temperature, 600°F
- c. Code, ASME Boiler and Pressure Vessel Code,Section III, Class 2 Main Steam Safety Valves
- a. Design pressure, 1185 psig
- b. Design temperature, 600°F
- c. Code, ASME Boiler and Pressure Vessel Code,Section III, Class 2 Main Steam Atmospheric Relief Valves
- a. Design pressure, 1185 psig
- b. Design temperature, 600°F
- c. Code, Boiler and Pressure Vessel Code, section III, Class 2 MAIN STEAM SUPPLY SYSTEM 10.3-7
WATTS BAR WBNP-95 Table 10.3-2 Deleted by Amendment 95 10.3-8 MAIN STEAM SUPPLY SYSTEM
WATTS BAR WBNP-0 Table 10.3-3 Deleted by Amendment 43 MAIN STEAM SUPPLY SYSTEM 10.3-9
WATTS BAR WBNP-0 Table 10.3-4 Deleted by Amendment 43 10.3-10 MAIN STEAM SUPPLY SYSTEM
WATTS BAR Main Steam Supply System WBNP-89 Figure 10.3-1 Powerhouse Unit 1 Flow Diagram - Main and Reheat Steam 10.3-11
WATTS BAR 10.3-12 Main Steam Supply System WBNP-82 Figure 10.3-2 Powerhouse Unit 1 Electrical Control Diagram - Main Steam System
WATTS BAR Main Steam Supply System WBNP-82 Figure 10.3-3 Powerhouse Unit 1 Electrical Control Diagram - Main Steam System 10.3-13
WATTS BAR 10.3-14 Main Steam Supply System WBNP-89 Figure 10.3-3 Powerhouse Unit 1 Electrical Control Diagram Main Steam System (Sheet A)
WATTS BAR Main Steam Supply System WBNP-89 Figure 10.3-4 Powerhouse Unit 1 Electrical Control Diagram Main Steam System 10.3-15
WATTS BAR 10.3-16 Main Steam Supply System WBNP-89 Figure 10.3-4a Powerhouse Unit 1 Electrical Control Diagram Main Steam System
WATTS BAR Main Steam Supply System WBNP-89 Figure 10.3-5 Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat Steam 10.3-17
WATTS BAR 10.3-18 Main Steam Supply System WBNP-89 Figure 10.3-6 Powerhouse Unit 1 Electrical Logic Diagram Main and Reheat Steam
WATTS BAR Main Steam Supply System WBNP-89 Figure 10.3-7 Powerhouse Units 1& 2 Electrical Logic Diagram Main and Reheat Steam 10.3-19
WATTS BAR WBNP-95 Figure 10.3-8 Deleted by Amendment 95 10.3-20 Main Steam Supply System
WATTS BAR Main Steam Supply System WBNP-89 Figure 10.3-9 Powerhouse Units 1 & 2 Flow Diagram Feedwater Treatment Secondary Chemical Feed 10.3-21
WATTS BAR WBNP-89 THIS PAGE INTENTIONALLY BLANK 10.3-22 Main Steam Supply System
WATTS BAR WBNP-95 10.4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4.1 Main Condenser 10.4.1.1 Design Bases The design basis for the main condenser is to provide a heat removal rate of at least 7.789 x 109 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 1.92 (Low Pressure, LP), 2.70 (Intermediate Pressure, IP), and 3.75 (High Pressure, HP) inches of mercury, absolute when operating at rated turbine output with 70° F cooling water and 95% clean tubes. A tube cleaning system is provided to keep the condenser operating at peak performance. 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 (some data listed below represents one set of variables and may vary based on ambient temperature and cleanliness and required maintenance tube plugging).
10.4.1.2 System Description To provide sufficient capability to meet the functional requirements stated in Section 10.4.1.1, the main condenser has the following specifications:
Total surface area, sq. ft. 824,000 Circulating water quantity, gpm 410,000 Circulating water temperature 70.5 (yearly average), °F Circulating water temperature rise, °F 38 Number of shells 1 Number of passes 1 Tubes:
Overall length, ft. 115 Size, inches OD 1 Birmingham Wire 18 and 22 Gauge (BWG)
Material Sea-Cure Number (18BWG, top-row) 104 tubes OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-1
WATTS BAR WBNP-95 Number (12 BWG, balance of 27,306 tubes tubes)
Cleanliness, % 95 Duty, 109 Btu/hr 7.789 Overall dimensions:
Length, ft. 137.5 Height, ft 62.5 Width, ft. 27.0 Design pressure:
Shell, psig 25 and vacuum Hotwell, psig 30 Waterboxes, psig 72 Hotwell storage (normal), gallons 56,000 Oxygen content of condensate, cc/liter 0.005 Steam Flowrate to condenser, lb/hr Maximum guaranteed condition 8,100,000 Valves-wide-open condition 8,500,000 Bypass system:
Flow, lb/hr 6,057,000 Pressure (at nozzle), psig 250 10.4-2 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-95 Enthalpy, Btu/lb 1191.3 Air inleakage, scfm 24 The Main condenser has 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 trough 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 capacity 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 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 may be 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 hotwell level below the low water level and can be deaerated with auxiliary steam sprayed up through it from steam sparger nozzles located in a header arrangement in the hotwell, if necessary (also below the low water level).
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 exceeding the exhaust hood temperature limits when starting from design circulating water inlet temperature and condenser back pressure conditions. 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 normal 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 monitors the cation conductivity. A given increase in cation conductivity at one or more of the nine OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-3
WATTS BAR WBNP-95 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.
The condenser is divided into two sections; and one section can be isolated during unit operation if 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.
The condenser polishing demineralizer system (CPDS) is designed to be capable of producing feedwater in accordance with EPRI and Westinghouse Guidelines for PWR Secondary Water Chemistry. The system has sufficient ion exchange capacity to maintain condensate/feedwater quality within specified limits during periods of condenser inleakage. How long the unit can operate after the condenser inleakage starts is a direct function of the quality of the raw water leaking into the condenser and the required secondary chemistry limits.
The condenser tubes are SEA-CURE (UNS S44660), which is a ferritic stainless steel highly alloyed with chromium and molybdenum. The alloy additions are used to provide a high level of resistance where chloride induced pitting, crevice, and stress corrosion cracking may be encountered. The high modulus of elasticity of SEA-CURE results in tubing highly resistant to steam-induced vibration. The high strength of SEA-CURE also gives a very high fatigue endurance limit as added insurance against vibration induced failure.
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 Evaluation The 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 considers the steam generator and condenser partitioning coefficents. Primary-to-secondary leakage has the potential for supplying measurable quantities of hydrogen to the condensate system. However, for large primary-to-secondary leakage rates (1.0 gpm), the rate of hydrogen release would be less than 0.01 scfm. This rate is small when compared to the normal two pump condenser evacuation capacity 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 will cause 10.4-4 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-95 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 approximately 6.5-inches Hg absolute and 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 Testing The condenser is tested for leaks by completely filling the shell with condensate. The waterboxes are 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 Instrumentation Sufficient 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 Bases The 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 Description The 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-5
WATTS BAR WBNP-95 requirements as stated in Section 10.4.2.1, the main condenser evacuation system has been designed with the following specifications which meet the requirements of the Heat Exchange Institute for steam surface condensers:
Type of evacuating equipment Mechanical vacuum pump Number of vacuum pumps, per unit 3 Air capacity at suction pressure of 1-inch 15 Hg absolute, per pump at normal operation,scfm Air capacity at suction pressure of 15-inch 800 Hg absolute, per pump at startup, scfm 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 Evaluation One of the three vacuum pumps is a backup unit. This unit automatically starts when the condenser 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 Testing A flowmeter is provided with each vacuum pump for condenser in 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 Instrumentation Pressure switches are provided to automatically start the standby vacuum pump.
Unit 2 Only The vacuum pump exhaust to atmosphere has three types of radiation monitors. The normal range monitor, sampling vacuum pump exhausts, gives early indication of 10.4-6 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-89 primary-to-secondary steam tube leakage and annunciates in the Main Control Room when radiation level reaches limits specified in the WBN Offsite Dose Calculation Manual (ODCM). Two accident range monitors are employed to monitor this flow path subsequent to a design bases accident. Each is an area radiation monitor mounted directly on the exterior of the Condenser Vacuum Exhaust pipe. The mid-range, mounted area radiation monitor includes a Gieger-Mueller tube detector. The high range, mounted area radiation monitor includes a gas-filled gamma ionization chamber detector. Additional information regarding these three radiation monitors is provided in Section 11.4.2.2.2.
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 Bases The 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 Description The 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 Evaluation Since 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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-7
WATTS BAR WBNP-95 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.
10.4.3.4 Inspection and Testing This equipment will be tested by the vendor in accordance with the various applicable code requirements.
10.4.3.5 Instrumentation Sufficient 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 Bases The 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 or actuating the steam generator safety valves (MSSVs).
(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 and cooldown of the plant.
The turbine bypass system piping is designed in accordance with ANSI B31.1 1973 Edition through Summer 1973 Addenda.
10.4-8 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-95 10.4.4.2 System Description The 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 - 12 Flow per valve - 532,170 lb/hr Main steam pressure at valve inlet (for above flow) - 900 psig Maximum flow per valve at 1185 psig inlet pressure - 970,000 lb/hr Time to open (full stroke) 3 seconds Full stroke modulation 20 seconds Failure position Closed The 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 turbine bypass valves are operated in one of the two control modes: (1) TAVG Mode, (2) steam pressure mode. The TAVG Mode is normally used during plant operation. The Steam Pressure Mode is normally used during plant startup and shutdown. Refer to Section 7.7.1.8 for detailed description of the turbine bypass valve control.
The bypass valves are built in accordance with ASME Section III, Class 2, which invokes ANSI Standard B16.5. All piping in the steam bypass system is in accordance with ANSI Standard B31.1.
10.4.4.3 Safety Evaluation The turbine bypass valves are blocked from operating if any of the following abnormal process conditions exists: 1) condenser is unavailable (hight absolute pressure),
- 2) no condenser circulating water pumps operating, or 3) low-low reactor coolant average temperature. If the above process conditions are normal, the following conditons will arm the control system and allow turbine bypass valve operation:
- 1) reactor trip signal, 2) turbine load rate change greater than setpoint, or 3) control OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-9
WATTS BAR WBNP-95 mode hand switch placed in the Steam Pressure mode. A manual hand switch is used to block the low-low reactor coolant average temperature signal (P-12) to allow operation of the three turbine bypass cooldown valves.
An alternate method of RCS cooldown, below 350°F (i.e., delay RHR cut-in), is provided via the turbine bypass valves. The alternate method provides for disabling the P-12 Interlock during cooldown after entering Mode 4. The temporary disablement can be performed procedurally with no permanent hardware modifications to the unit.
Permanent control board indication of the bypassed condition is not provided nor is the bypass automatically removed when the permissive conditions are no longer met. The use of all twelve turbine bypass valves is optional for the Operator. The turbine bypass valves are controlled using the Steam Pressure Controller before and after the protective interlock is disabled. The interlock disablement procedure for utilization of all twelve valves is performed only after shutdown (and subsequent cooldown) has been initiated and therefore, does not present a reactor trip hazard. An analysis has been performed to assess the cooldown potential following failure of the steam dump controller after placing turbine bypass valves in service. It was determined that the three turbine bypass cooldown valves spuriously opening at the protective interlock setpoint of 550°F can produce a cooldown rate that far exceeds that of all twelve turbine bypass valves opening at 350°F (temperature below which additional valve use is permitted).
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. In the event of loss of the turbine bypass valves, 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).
Inadvertent or accidental opening of any one bypass valve during power operation will not subject the reactor coolant system to an uncontrolled cooldown. Cooldown consequences may be minimized by operation of the rod control system and/or the overpower T runback function.
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 Testing This 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.
10.4-10 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-91 10.4.4.5 Instrumentation Sufficient 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 Circulating Water System This 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).
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 109 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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-11
WATTS BAR WBNP-91 10.4.5.2 System Description The 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 operation. 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 10.4-12 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-91 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 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-13
WATTS BAR WBNP-91 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 the 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 Evaluation The 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.
If 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 10.4-14 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-91 flooding of safety-related components would result from a failure of the system providing the flow.
10.4.5.4 Inspection and Testing Although 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 Instrumentation Application Since 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.
10.4.6 Condensate Polishing Demineralizer System 10.4.6.1 Design Bases - Power Conversion The 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-15
WATTS BAR WBNP-91 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 Description The CPDS for each power generation unit consists 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.
A 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, 10.4-16 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-91 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 in 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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-17
WATTS BAR WBNP-89 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 Evaluation Radionuclides 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.
10.4.6.4 Inspection and Testing The 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 Instrumentation Instrumentation 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.
10.4-18 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 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 individual 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.
(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 and Feedwater Systems 10.4.7.1 Design Bases The 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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-19
WATTS BAR WBNP-82 10.4.7.2 System Description The 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 - 3 Manufacturer - Borg-Warner Corporation, Byron Jackson Pump Division Type - VMT, four stages, single suction, vertical process Design Point - 6700 gpm, 600 feet head Motor Manufacturer - Parsons-Peebles, Ltd.
Motor Design - 1250 hp, 1180 rpm, 6600 V, 3 phase, 60 Hz, vertical, constant speed (2) Condensate Booster Pumps Number - 3 Manufacturer - Borg-Warner Corporation, Byron Jackson Pump Division Type - DVDSR, single stage, double suction, double volute centrifugal Design Point - 9000 gpm, 680 feet head Motor Design - 1750 hp, 3584 rpm, 6600 V, 3 phase, 60 Hz, horizontal, constant speed Motor Manufacturer - Parsons-Peebles, Ltd.
(3) Main Feedwater Pumps Number - 2 Manufacturer - Borg-Warner Corporation, Byron Jackson Pump Division Type - HRD, single stage, double suction, double volute centrifugal Design 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 - 1 Manufacturer - Borg-Warner Corporation, Byron Jackson Pump Division Type - DVS, single stage, double suction, double volute, centrifugal Design Point - 6100 gpm, 1890 feet head 10.4-20 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 Motor Design - 3700 hp, 3584 rpm, 6600 V, 3 phase, 60 Hz horizontal constant speed Motor Manufacturer - Parsons-Peebles, Ltd.
(5) Demineralized Condensate Pumps Number - 3 Manufacturer - Ingersoll-Rand Company Type - A, single stage, single suction, end suction process Design Point - 6700 gpm, 150 feet head Motor Manufacturer - Westinghouse Motor 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 - 2 Manufacturer - Westinghouse Electric Corporation Type and Speed - EMM-32AIN, Multi-stage, dual inlet, 5460 rpm Throttle Pressure - LP steam, 146 psig HP steam, 995 psig Throttle Temperature - LP steam, 513°F HP steam, 546°F Back Pressure - 6.9 in of Hg absolute Number of Stages - 6 Extraction Points - None Rated Horsepower - 12,200 hp (7) Main Feedwater Pump Turbine Condenser Number - 2 Manufacturer - Westinghouse Electric Corporation Tube Material - ASME SA688, 304 SST Channel Design pressure* - 350 psi Channel Design temperature* - 259°F (8) Gland Steam Condenser Number - 1 Manufacturer - Westinghouse Electric Corporation Tube Material 10 Cu-Ni Channel Design pressure* - 400 psig Channel Design temperature* - 125°F OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-21
WATTS BAR WBNP-89 (9) Feedwater Heaters Number - 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-tube Tube Material - 304 SST Channel Design Heater Pressure* Channel Design No. (psi) Temp* (°F) 1 2000 480 2 2000 440 3 725 380 4 725 300 5 350 300 6 350 300 7 350 300
- Channel side design conditions only tabulated here. For shell side design conditions, see Section 10.4.9.
Feedwater 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 10.4-22 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-95 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, he 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.
(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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-23
WATTS BAR WBNP-82 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.
During 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 10.4-24 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-89 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 valve 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-25
WATTS BAR WBNP-89 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 nozzle. 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 bypass 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.
10.4-26 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 10.4.7.3 Safety Evaluation The 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),
allcondensate 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 restart 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-27
WATTS BAR WBNP-82 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 loadrunback 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 Control 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 Testing The 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.
10.4-28 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 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 Instrumentation Sufficient 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 Generator Blowdown System 10.4.8.1 Design Bases The 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.
(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 radioactivity 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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-29
WATTS BAR WBNP-82 (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:
Component Code Piping and valves from steam generator ASME Code III, Class 2 through blowdown isolation valves Piping and valves downstream of ANSI B31.1 Power Piping blowdown isolation valves Blowdown flash tank ASME Section VIII, Division 1 Demineralizers and filters ASME Boiler and Pressure Vessel Code,Section VIII, Division 1 Blowdown flash tank pumps Standards of the Hydraulic Institute, Section B Heat Exchanger ASME Boiler and Pressure Vessel Code,Section VIII, Division 1 (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.
(8) Seismic and quality group classifications of SGBS are provided in Section 3.2 10.4.8.2 System Description and Operation A 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.
10.4-30 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 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 Evaluation The 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.
Capacity The 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 Releases Radioactivity releases due to normal operation of the steam generator blowdown system are discussed in Section 11.2.
Unusual Design Condition In 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).
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-31
WATTS BAR WBNP-82 System Performance During Abnormally High Primary-to-Secondary Leakage Abnormally 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 Components Analyses of various failures in the system are given in Table 10.4-3.
10.4.8.4 Inspections and Testing Prior 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.
10.4.9 Auxiliary Feedwater System 10.4.9.1 Design Bases The 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 10.4-32 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 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 Description The 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 pump 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-33
WATTS BAR WBNP-82 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.
10.4.9.3 Safety Evaluation For 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.
10.4-34 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-82 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 secondary 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.
Appropriate 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-35
WATTS BAR WBNP-82 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 (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.
10.4-36 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-89 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.
10.4.9.4 Inspection and Testing Requirements A 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.
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-37
WATTS BAR WBNP-0 10.4.9.5 Instrumentation Requirements The 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.
Table 10.4-1 Deleted by Amendment 43 10.4-38 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
WATTS BAR WBNP-91 Table 10.4-2 Auxiliary Feedwater Pump Parameters Total Number Per Unit 3 Electric Driven 2 Turbine Driven 1 Design Flow Rate, gpm Electric Driven, each 450 Turbine Driven 790 Design Pressure, psig 1600 Feedwater Design Temperature, °F 40 to 120 Design Head, feet Electric Driven (as tested) 3250.5 Turbine Driven 3350 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-39
10.4-40 WATTS BAR Table 10.4-3 Failure Analysis, Steam Generator Blowdown System (Page 1 of 2)
Failure Consequences Action 1.Rupture of blowdown line between steam Hot water under pressure partially flashes to When containment pressure reaches 1.2 psig, generator and isolation valve inside containment. steam. Pressure in lower compartment reactor is automatically scrammed, and increases, and vapor passes through ice beds. containment isolation valves close. Main Water level in affected steam generator feedwater lines isolate, blowdown isolation valves increases. Radioactivity present in steam close, and auxiliary feedwater pumps start.
generator remains inside containment. 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 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM generator is cut off and the steam generator is allowed to boil and drain itself dry.
2.Rupture of blowdown line from outside Hot water under pressure escapes into main When the leak is discovered, the operator closes containment to blowdown control valve steam valve vault, outside the building, or all blowdown isolation valves and then opens them downstream of heat exchanger. inside the turbine building and partially flashes one at a time to locate the leak. The unit is shut to steam. Some of radioactive material in down as necessary to repair the leak.
blowdown will escape directly to atmosphere or be carried out with turbine building ventilation exhaust, depending on where the rupture occurs.
3.Rupture of blowdown line downstream of the Water under pressure escapes into turbine Same as (2) blowdown control valve in the heat exchanger building and is collected by liquid waste flow path. system.
4.Failure of blowdown control valve. Flow will increase to maximum value allowed When the failure is discovered, the blowdown by manual throttling valves. isolation valves will be closed so that the control valve can be repaired.
WBNP-73
Table 10.4-3 Failure Analysis, Steam Generator Blowdown System (Page 2 of 2)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Failure Consequences Action 5.Tube rupture in a heat exchanger Blowdown water escapes into the heat When the failure is discovered, the blowdown exchanger cooling water channel. isolation valves will be closed so that the heat exchanger can be prepared.
10.4-41 WBNP-73
WATTS BAR WBNP-73 10.4-42 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Table 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. FAILURE METHOD EFFECT ON COMPONENT FUNCTION 1 2 3 4 5 6 MODE OF DET. SUBSYSTEM SYSTEM REMARKS*
- 1. Main Steam Piping Source of Steam X --- --- --- --- See pipe failure analysis Storage Tank X
- 2. FCV 1-16 Provides two different X Fails Closed Control Room Loss of one of two steam None Redundant steam source (FCV 1-15) steam supplies, but to X Fails Open (Valve Position sources. No effect unless available from other SGMotor-prevent blow-down of (Ind.) pipe rupture, then blowdown Driven pump would provide req'd two SG in event of pipe of on SG and loss of flow from feedwater flow.
rup-ture, only one steam TD pump.
sources is available at one time. Isolation Valve only
- 3. Check Valve Prevents reverse flow X Fails Closed None unless valve Loss of one of two steam None Redundant steam source (3-892, 3-891) and blowdown in case of X Fails Open FCV 1-16 open, the sources If pipe rupture could available from the SG and Motor-pipe rutpure. control room ind., close both steam sources and Driven pumps would provide control room, from thus flow from TD pump. req'd flow. Motor-Driven pumps effect on subsystem would provid req'd. flow.
(no feedwater flow).
- 4. FCV 1-18 Isolates in case of pipe X Fails Closed Control Room Loss of steam supply. None Motor-driven pumps would rupture. X Fails Open (Valve Position Ind.) None provide req'd. flow. If isolation Isolation Valve req'd redundant FCV-1-17 would only provide this feature
- 5. FCV 1-17 Isolates in case of pipe X Fails Open Control Room Loss of steam supply None Motor-driven pumps would rupture. X Fails Closed (Valve Position None provide req'd flow. If isolation Ind.) req'd redundant FCV-1-18 would provide this feature
- 6. FCV 1-51 Trip & throttle valve X Fails Closed Control Room Turbine Trip and loss of Aux. None Motor-driven pumps would X Fails Open (Valve Position Ind.) FW Flow from TD pump. In provide req'd flow.
the event of a loss of load WBNP-82 (pipe break) governor viv 10.4-43 would limit pump speed.
Table 10.4-4 Failure Mode & Effects Analysis Steam Supply Subsystem (Sheet 2 of 2)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR 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. FAILURE METHOD EFFECT ON COMPONENT FUNCTION 1 2 3 4 5 6 MODE OF DET. SUBSYSTEM SYSTEM REMARKS*
- 7. FCV 1-52 Governor Valve X Fails Open Control Room Turbine Trip and loss of Aux. None Motor-driven pumps would X Fails Closed (Valve Position FW Flow from TD pump. provide req'd flow.
Ind.)
- 8. Turbine Drives pump X TURBINE Control Room None None Motor-driven pumps would Failure (no FW Flow) req'd flow.
All Components All Functions X X X X X X All modes Visual/Control Room None None Since postulated accidents are (1-8) 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.
- 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.
10.4-44 WBNP-82
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Table 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 ANALYSIS Cooldown for Stage 1 of DBE FloodA Main Feed Line Break with LOOPA Loss of Normal Feedwater with LOOP Large Break LOCA with LOOP Main Steam Line Break with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 1. Check valve Isolates the safety- Stuck closed. Mechanical failure. Control Room Transfer of suction None. MDP 1A-A & 1B-B 1-3-810. related suction line indication via to ERCW. provides flow to all 4 for the TDP pressure switches SG's.
1A-S from its non- PS-3-121A & PS safety water source 125A.
Mechanical failure. No method Degradation of flow TDP will still be Stuck open. available. from TDAFW pump None. operable; however, if supplied from MDP's are still ERCW. available to all SG's.
- 2. TDP 1A-S Provides Feedwater Fails to start. Mechanical failure, Control Room Loss of flow to all None. MDP's 1A-A & 1B-B flow to all four SG's. spurious control indication via four SG's. provides flow to all 4 signal. indicator FI-3-142A. SG's.
Mechanical failure. Control Room MDP's 1A-A & 1B-B Seal fails. indication reduced TDP 1A-S pump None. will provide flow to flow via FI-3-142A. flow is diminished. all four SG's.
10.4-45 WBNP-89
Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 2 of 6)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR TRAIN S FAILURE MODES AND EFFECTS ANALYSIS Cooldown for Stage 1 of DBE FloodA Main Feed Line Break with LOOPA Loss of Normal Feedwater with LOOP Large Break LOCA with LOOP Main Steam Line Break with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 3. Check Valve Maintains water Stuck closed. Mechanical failure. Control Room Loss of flow to all None. MDP's 1A-A & 1B-B 1-3-864 inventory in indication via flow four SG's. provides flow to all downstream piping indicator FI-3-142A. 4 SG's.
of TDP 1A-S by preventing reverse Mechanical failure. None. No loss of pump.
flow. Stuck open. None, if TDP 1A-S None.
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.
10.4-46 WBNP-89
Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 3 of 6)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR TRAIN S FAILURE MODES AND EFFECTS ANALYSIS Cooldown for Stage 1 of DBE FloodA Main Feed Line Break with LOOPA Loss of Normal Feedwater with LOOP Large Break LOCA with LOOP Main Steam Line Break with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 4. AOV Regulates AFW Fails to open. Control failure. Control Room Loss of AFW flow to None. MDP 1B-B will LCV-3-175 (fails in flow to SG 4 from indication via SG 4. provide flow to SG closed position) TDP 1A-S. control switch HS 4.
spring to close air to 175A.
open Fails to close. Control failure. Control Room AFW flow to SG 4 None. Operator action indication via unregulated. required to isolate control switch HS Diminished flow to TDP 1A-S to 175A. SG's 1, 2 & 3. prevent SG 4 overfill.
AFW flow to SG 4 Operator action Stuck open. Mechanical failure. Control Room unregulated. None. required to isolate indication of SG 1. Diminished flow to TDP 1A-S to High level via LA SG's 1, 2 & 3. prevent SG 4 175B and -175D. overfill.
MDP 1A-A will Loss of AFW flow to provide flow to SG Stuck closed. Mechanical failure. Control Room SG 4. 4.
indication via None.
control switch HS 175A.
10.4-47 WBNP-89
Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 4 of 6)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR TRAIN S FAILURE MODES AND EFFECTS ANALYSIS Cooldown for Stage 1 of DBE FloodA Main Feed Line Break with LOOPA Loss of Normal Feedwater with LOOP Large Break LOCA with LOOP Main Steam Line Break with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 5. Condensate Water Supply Tank Discharge Mechanical failure. Control Room Loss of condensate None. On loss of Storage Tank Plugged Alarm (Loss of water supply. condensate supply, suction pressure). the essential raw cooling water (ERCW) system supply is automatically provided.
- 6. Check valve Prevents reverse Stuck Closed. Mechanical failure. Control Room Loss of TDP 1A-S None. MDP 1B-B will 1-3-874 flow in TDP 1A-S indication via flow flow to SG 4. provide flow to SG discharge line to SG indicators FI-3-142A 4.
- 4. & -170A.
Stuck open. Mechanical failure. None. Not a problem if None.
TDP 1A-S is running, if not LCV-3-173 will prevent reverse flow thru pump discharge piping.
10.4-48 WBNP-89
Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 5 of 6)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR TRAIN S FAILURE MODES AND EFFECTS ANALYSIS Cooldown for Stage 1 of DBE FloodA Main Feed Line Break with LOOPA Loss of Normal Feedwater with LOOP Large Break LOCA with LOOP Main Steam Line Break with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 7. Check valve Prevents blowdown Stuck closed. Mechanical failure. Control Room Loss of AFW to SG AFW flow required 1-3-644 of SG 4 in case of indication via flow 4. None. to only two SG's.
an AFW line break indicator FI-3-170A.
inside containment. In addition to SG level instrumentation.
Stuck open. Mechanical failure. None. None. Check valve None.
1-3-645 will prevent blowdown of SG 4.
- 8. Check valve Backup valve to 1- Stuck closed. Mechanical failure. Control Room Loss of AFW to SG None. AFW flow required 1-3-645 3-644 (same indication via flow 4. to only two SG's.
function) indicator FI-3-170A.
In addition to SG level instrumentation.
Stuck open. Mechanical failure. None. None. Check valve None.
1-3-644 will prevent blowdown of SG 4.
10.4-49 WBNP-89
Table 10.4-5 Failure Mode & Effects Analysis Turbine-Driven (TD) Pump Subsystem (Steam Generator (SG) - Loop No. 4 Typical (Sheet 6 of 6)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR TRAIN S FAILURE MODES AND EFFECTS ANALYSIS Cooldown for Stage 1 of DBE FloodA Main Feed Line Break with LOOPA Loss of Normal Feedwater with LOOP Large Break LOCA with LOOP Main Steam Line Break with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 9. TDP 1A-S min flow Prevents backflow Stuck closed. Mechanical failure. Low flow or none Could cause TDP None. MDP's 1A-A & 1B-B recirc line to CST from CST to TDP thru FE-131 located 1A-S to overheat will provide flow to check valve 3-818. 1A-S discharge on recirc TDP and become all four SG's.
piping. overheating as inoperable indicated by TI 3- preventing AFW 149. flow to all four SG's (only if flow demand is low).
Will not affect recirc Stuck open. Mechanical failure. No method of No effect on system None. flow to CST.
detection. if TDP 1A-S is running. If TDP 1A-S is not running, system resistance would prevent backflow from occurring.
10.4-50 WBNP-89
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Table 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 Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 1. Check valve Isolates the safety- Stuck closed. Mechanical failure. Control Room Loss of flow from None. TD 1A-S provides 1-3-806 related suction line indication via pressure MDP 1B-B. flow to SG's 3 & 4.
for MDP 1B-B from gage PDI-3-132A.
its non-safety water source.
TD 1A-S provides Stuck open. Mechanical failure. Control Room Reduction or loss of None. flow to SG's 3 & 4.
indication via pressure flow if MDP 1A-A gage PDI-3-132A flow is from the ERCW.
- 2. MOV'S Isolation valves Either fails to open Control failure. Control Room Loss of AFW flow to None. TDP 1A-S
- 3. FCV-3-126A between ERCW and or indication via control SG's 3 & 4. provides flows to FCV-3-126B. (fail as MDP 1B-B suction. Either stuck closed. Mechanical failure. switches HS-3-126A & SG's 3 & 4.
is) HS-3-126B.
Both valves fail to Control or power open failure. Control Room Loss of AFW flow to TDP 1A-S or indication via control SG's 3 & 4. None. provides flows to Both valves stuck Mechanical failure. switches HS-3-126A & SG's 3 & 4.
closed. HS-3-126B.
10.4-51 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 2 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 4. MDP 1B-B Provides Feedwater Fails to start. Mechanical failure. Control Room Loss of Train B. None. TDP 1A-S flow to SG's 3 & 4. indication via control provides flow to switch HS-3-128A & SG's 3 & 4.
pressures differential indicator PDI-3-132A.
Seal fails. Mechanical failure. Control Room MDP 1B-B None. TDP 1A-S indication reduced flow capability is provides flow to via FI-3-147B & FI diminished. SG's 3 & 4.
170A.
- 5. Condensate Water Supply Tank Discharge Mechanical failure. Control Room Alarm Loss of Condensate None. On loss of Storage Tank Plugged. (Loss of Suction Water Supply condensate Pressure) supply, the essential raw cooling water (ERCW) system supply is automatically provided.
- 6. Check Valve None N/A N/A N/A N/A None Valve Internals 1-3-821 have been removed.
10.4-52 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 3 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 7. AOV Prevents MDP 1B-B Fails to open. Control failure. Control Room Loss of MDP 1B-B. None. TDP 1A-S PCV-3-132 (fails in runout by controlling indication via flow provides flow to closed position) pump discharge indicators FI-3-142A, - SG's 3 & 4.
spring to close air to pressure. 147B, & -170A.
open.
Fails to close. Control failure. Control Room Possibility of MDP TDP 1A-S indication via flow 1B-B running out None. provides flow to indicators FI-3-142A, - and eventual loss of SG's 3 & 4.
147B, & -170A. Also, pump.
pressure differential indicator PDI-3-132A.
Stuck open. Mechanical failure. Control Room Possibility of MDP None. TDP 1A-S indication via vlow 1B-B running out provides flow to indicators FI-3-142A, - and eventual loss of SG's 3 & 4.
147B, & -170A. Also, pump.
pressure differential indicator PDI-3-132A.
Stuck closed. Mechanical failure. Indication via flow Loss of MDP 1B-B. None. TDP 1A-S indicators FI-3-142A,- provides flow to 147B, & -170A. SG's 3 & 4.
10.4-53 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 4 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 8. AOV Regulates AFW flow Fails to open. Control failure. Control Room Loss of AFW flow to None. TDP 1A-S LCV-3-171 (fails to to SG 4 when indication of SG 4. SG 4. provides flow to open position) pressure is greater High level via LA SG 4.
spring to open air to than setpoint for 171B and -171D.
close. pressure switch PS-3-171. 4" level control valve Control failure. Control Room Fails to close. indication via control AFW flow to SG 4 None. Operator action switch HS-3-171A. unregulated. required to isolate Diminished flow to MDP 1B-B to SG 3. prevent SG 4 overfill.
Mechanical failure. Control Room AFW flow to SG 4 None. Operator action indication via control unregulated. required to isolate Stuck open. switch HS-3-171A. Diminished flow to MDP 1B-B to SG 3. prevent SG 4 overfill.
TDP 1A-S Stuck closed. Mechanical failure. Control Room Loss of AFW flow to None. provides flow to indication via control SG 4. SG 4.
switch HS-3-171A.
10.4-54 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 5 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 9. AOV Regulates AFW flow Fails to open. Control failure. Control Room Loss of AFW flow to None. TDP 1A-S LCV-3-171A (fails in to SG 4 when indication via control SG 4 through LCV- provides flow to closed position) pressure is greater switch HS-3-171A. 3-171A. SG 4.
spring to close air to than setpoint for open. pressure switch PS-3-171. 2" level control bypass valve.
Control failure. Control Room Diminished AFW Fails to close. indication via control flow to SG 3. None. Operator action switch HS-3-171A. required to isolate MDP 1B-B to prevent SG 4 overfill.
Stuck open. Mechanical failure. Control Room Diminished AFW None. Operator action indication of SG 2. flow to SG 3. required to isolate High level via LA MDP 1B-B to 171B & -171D. prevent SG 4 overfill.
Stuck closed. Mechanical failure. Control Room Loss of AFW flow to None. TDP 1A-S indication via control SG 4 through LCV- provides flow to switch HS-3-171A. 3-171A. SG 4.
10.4-55 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 6 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 10. Emergency power Provide AC power Fails. Diesel Generator Control Room MDP 1B-B is lost. None. Train A would be to Train B. to MDP 1B-B & all Shutdown Board indication. available to MOV's in Train B. 1B-B failure. 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 valve Prevents reverse Stuck open. Mechanical failure. None. Not a problem if None.
1-3-833. flow in 4" AFW line MDP 1B-B is to SG 4. running, if not LCV-3-171 and -171A will prevent reverse flow thru pump discharge piping.
Stuck closed. Mechanical failure. Control Room Loss of AFW to SG None. TDP 1A-S indication via flow 4. provides flow to indicators FI-3-142A & SG 4.
-170A.
10.4-56 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 7 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 12. MDP 1B-B min flow Prevents backflow Stuck closed. Mechanical failure. Low flow or none thru MDP 1B-B to None. TDP 1A-S will recirc line to CST from CST to MDP FE-131 located on overheat and provide flow to check valve 3-815. 1B-B discharge recirc line. Pump high become inoperative SG's 3 & 4.
piping. temp as indicated by preventing AFW TI's 3-130 A and B. flow to SG's 3 & 4 (only if flow demand is low).
Stuck open. Mechanical failure. No method of No affect on system None.
detection. if MDP 1B-B is running. If MDP 1B-B is not running, system resistance would prvent backflow from occuring.
10.4-57 WBNP-89
Table 10.4-6 Failure Mode & Effects Analysis Motor Driven (MD) Pump Subsystem (Steam Generator (SG) Loop No. 4 - Typical) (Sheet 8 of 8)
OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM WATTS BAR Train B Failure Modes and Effects Analysis Cooldown for Stage 1 of a DBE Loss of Normal Feedwater with LOOP FloodMain Feed Line Break with LOOP Main Steam Line Break with LOOP Large Break LOCA with LOOP POTENTIAL METHOD OF EFFECT EFFECT ITEM NO. COMPONENT FUNCTION FAILURE MODE CAUSE DETECTION ON SYSTEM ON PLANT REMARKS
- 13. Check valve Prevents blowdown Stuck closed. Mechanical failure. Control Room None. AFW flow 1-3-644 of SG 4 in case of indication via flow Loss of AFW to SG required to only an AFW line break indicator FI-3-170A. In 4. two SG's.
inside containment. addition to SG level instrumentation.
Stuck open. Mechanical failure. None. None. Check valve None.
1-3-645 will prevent blowdown of SG 4.
- 14. Check valve Backup valve to 1- Stuck closed. Mechanical failure. Control Room Loss of AFW to SG None. AFW flow 1-3-645 3-644 (same indication via flow 4. required to only function) indicator FI-3-170A. In two SG's.
addition to SG level instrumentation.
Stuck open. Mechanical failure. None. None. Check valve None.
1-3-644 will prevent blowdown of SG 4.
10.4-58 WBNP-89
WATTS BAR WBNP-89 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-59
WATTS BAR WBNP-89 OTHER FEATURES OF STEAM AND POWER CONVERSION SYSTEM 10.4-60
WATTS BAR WBNP-88 Table 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Accident/Transient - GPM (Sheet 1 of 3)
ITEM AFW MIN MAX FLOW NO OF SG'S SG'S NO. PUMPS REQ'D ALLOWED REQ'D OR AVAILABLE ACCIDENT REQ'D FLOW (MASS & ENERGY (FAULTED) OR RELEASES) NOTE REQUIRED 1
ALL 4 SG'S ARE AVAIL 1 LONF Any 2 820 NA ANY 2 SG'S ARE REQ'D ALL 4 SG'S ARE AVAIL 2 LOOP ANY 1 410 ANY 2 SG'S ARE REQ'D PUMP 3 MS SUDDEN DEPRESSURIZATION ALL 4 SG's ARE AVAIL 3.1 MS S DEPRESS NONE N/A 2840 ANY 2 SG's ARE REQ'D SHORT TERM ALL 4 SG's ARE AVAIL 3.2 MS S DEPRESS ANY 2 820 NA ANY 2 SG's ARE REQ'D LONG TERM 4 MAIN STEAM LINE BREAK (MSLB) WITH CONCURRENT LOOP 4.1 MSLB-SHORT NONE NA 2840 (1 FAULTED) NOT APP TERM 4.2 MSLB-LONG TERM ANY 1 410 NA ANY 2 SG's ARE REQ'D ANY 3 SG's ARE AVAIL 5 MAIN FEED LINE BREAK (MFLB) WITH CONCURRENT LOOP ALL FLOW FAULTED TO SG 5.1 MFLB-SHORT NONE NA 2840 TERM ANY 2 SG's ARE REQ'D 5.2 MFLB-LONG TERM ANY 1 410 NA ANY 3 SG's ARE AVAIL MDP 5.3 MFLB-LONG TERM TDP 720 NA 10.4-61
WATTS BAR WBNP-88 Table 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Accident/Transient - GPM (Sheet 2 of 3)
ITEM AFW MIN MAX FLOW NO OF SG'S SG'S NO. PUMPS REQ'D ALLOWED REQ'D OR AVAILABLE ACCIDENT REQ'D FLOW (MASS & ENERGY (FAULTED) OR RELEASES) NOTE REQUIRED 1
6 LOCA FAULTED SG HAVE TUBE 6.1 LARGE BREAK ANY 1 Note 2 NA LEAKS LOCA ALL 4 SG's ARE AVAIL ANY 2 SG's ARE REQ'D 6.2 SMALL BREAK 1 MD + TD 1050 NA ALL 4 SG'S ARE AVAIL LOCA 6.3 MSLB MASS & ENERGY (M&E) RELEASE CASES FOR BREAK INSIDE CONTAINMENT SHORT TERM ALL FLOW FAULTED TO SG 6.4 MSLB M&E IN NONE NA 2250 CASE 1 ALL FLOW FAULTED TO SG 6.5 MSLB M&E CASES NONE NA 1500 2-4 ALL FLOW FAULTED TO SG 6.6 MSLB M&E CASE 5 NONE NA 2250 ALL FLOW FAULTED TO SG 7 MSLB M&E CASES NONE NA 1500 6-8 ALL FLOW FAULTED TO SG 8 MSLB M&E CASE 9 NONE NA 2250 ALL FLOW FAULTED TO SG 9 MSLB M&E CASES NONE NA 2040 10-13 ANY 2 SG'S ARE REQUIRED 10 MSLB OUTSIDE NONE NA 841 SEE NOTE CONT 3 10.4-62
WATTS BAR WBNP-88 Table 10.4-7 Auxiliary Feedwater Flow to Steam Generators Following an Accident/Transient - GPM (Sheet 3 of 3)
ITEM AFW MIN MAX FLOW NO OF SG'S SG'S NO. PUMPS REQ'D ALLOWED REQ'D OR AVAILABLE ACCIDENT REQ'D FLOW (MASS & ENERGY (FAULTED) OR RELEASES) NOTE REQUIRED 1
ANY 2 SG'S ARE REQUIRED 11 TOTAL LOSS OF TDP 410 NA ALL SG'S ARE AVAIL ALL AC POWER (ONLY TDP AVAIL.)
NOTES:
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.
10.4-63
WATTS BAR WBNP-88 THIS PAGE INTENTIONALLY BLANK 10.4-64
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-1 Powerhouse Unit 1 Flow Diagram Turbine Drains and Miscellaneous Piping 10.4-65
WATTS BAR 10.4-66 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-2 General Units 1 & 2 Flow Diagram Condenser Circulating Water
WATTS BAR WBNP-89 Figure 10.4-3 General Unit 1 Flow Diagram Condenser Circulating Water Other Features of Steam and Power Conversion System 10.4-67
WATTS BAR 10.4-68 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-4 Powerhouse Units 1 & 2 Electrical Control Diagram Condenser Circulating Water System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-5 Powerhouse Units 1 & 2 Electrical Control Diagram Condenser Circulating Water System 10.4-69
WATTS BAR 10.4-70 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-6 Powerhouse Units 1 & 2 Electrical Logic Diagram Condenser Circulating Water System
WATTS BAR WBNP-82 Figure 10.4-7 Powerhouse Units 1 & 2 Flow Diagram Condensate Other Features of Steam and Power Conversion System 10.4-71
WATTS BAR WBNP-89 Figure 10.4-8 Powerhouse Unit 1 Flow Diagram Feedwater 10.4-72 Other Features of Steam and Power Conversion System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-9 Powerhouse Unit 1 Electrical Control Diagram Condensate System 10.4-73
WATTS BAR 10.4-74 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-10 Powerhouse Unit 1 Electrical Control Diagram Condensate System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-11 Powerhouse Units 1 & 2 Electrical Control Diagram Condensate System 10.4-75
WATTS BAR 10.4-76 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-11a Powerhouse Units 1 & 2 Electrical Control Diagram Condensate System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-12 Powerhouse Units 1 & 2 Electrical Logic Diagram Condensate System 10.4-77
WATTS BAR 10.4-78 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-13 Powerhouse Unit 1 Electrical Logic Control Diagram Condensate System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-13a Powerhouse Unit 1 Electrical Logic Diagram Condensate System 10.4-79
WATTS BAR 10.4-80 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-14 Powerhouse Units 1 & 2 Electrical Control Diagram Main Auxiliary Feedwater System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet A) 10.4-81
WATTS BAR 10.4-82 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet B)
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet C) 10.4-83
WATTS BAR 10.4-84 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-14 Powerhouse Unit 1 Electrical Control Diagram Main Auxiliary Feedwater System (Sheet D)
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System 10.4-85
WATTS BAR 10.4-86 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet A)
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet B) 10.4-87
WATTS BAR 10.4-88 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-15 Powerhouse Unit 1 Electrical Control Diagram Main & Aux Feedwater System (Sheet C)
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-16 Powerhouse Unit 1 Auxiliary Feedwater System Control Diagram 10.4-89
WATTS BAR 10.4-90 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-16a Powerhouse Unit 1 Auxiliary Feedwater System Control Diagram
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-17 Powerhouse Units 1 & 2 Electrical Logic Diagram Feedwater Pump Turbine Aux 10.4-91
WATTS BAR 10.4-92 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-18 Powerhouse Units 1 & 2 Electrical Logic Diagram Feedwater System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-19 Powerhouse Unit 1 Electrical Logic Diagram Auxiliary Feedwater System 10.4-93
WATTS BAR 10.4-94 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-20 Powerhouse Units 1 & 2 Auxiliary Feedwater System Logic Diagram
WATTS BAR WBNP-91 Figure 10.4-21 Powerhouse Units 1 & 2 Flow Diagram Auxiliary Feedwater Other Features of Steam and Power Conversion System 10.4-95
WATTS BAR 10.4-96 Other Features of Steam and Power Conversion System WBNP-82 Figure 10.4-21a Powerhouse Units 1 & 2 Flow Diagram Main & Auxiliary Feedwater
WATTS BAR WBNP-82 Figure 10.4-22 Deleted by Amendment 82 Other Features of Steam and Power Conversion System 10.4-97
WATTS BAR WBNP-82 Figure 10.4-23 Deleted by Amendment 82 10.4-98 Other Features of Steam and Power Conversion System
WATTS BAR Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-24 Powerhouse Units 1 & 2 Flow Diagram Steam Generator Blowdown System 10.4-99
WATTS BAR WBNP-82 Figure 10.4-25 Deleted by Amendment 82 10.4-100 Other Features of Steam and Power Conversion System
WATTS BAR WBNP-82 Figure 10.4-26 Deleted by Amendment 82 Other Features of Steam and Power Conversion System 10.4-101
WATTS BAR WBNP-94 Figure 10.4-27 Deleted by Amendment 94 10.4-102 Other Features of Steam and Power Conversion System
WATTS BAR WBNP-94 Figure 10.4-28 Deleted by Amendment 94 Other Features of Steam and Power Conversion System 10.4-103
WATTS BAR WBNP-94 Figure 10.4-29 Deleted by Amendment 94 10.4-104 Other Features of Steam and Power Conversion System
WATTS BAR WBNP-94 Figure 10.4-30 Deleted by Amendment 94 Other Features of Steam and Power Conversion System 10.4-105
WATTS BAR WBNP-94 Figure 10.4-31 Deleted by Amendment 94 10.4-106 Other Features of Steam and Power Conversion System
WATTS BAR WBNP-94 Figure 10.4-32 Deleted by Amendment 94 Other Features of Steam and Power Conversion System 10.4-107
WATTS BAR WBNP-94 Figure 10.4-33 Deleted by Amendment 94 10.4-108 Other Features of Steam and Power Conversion System
WATTS BAR WBNP-94 Figure 10.4-34 Deleted by Amendment 94 Other Features of Steam and Power Conversion System 10.4-109
WATTS BAR WBNP-94 Figure 10.4-35 Deleted by Amendment 94 10.4-110 Other Features of Steam and Power Conversion System
WATTS BAR Other Features of Steam and Power Conversion System 10.4-111 WBNP-89 Figure 10.4-36a Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System
WATTS BAR 10.4-112 Other Features of Steam and Power Conversion System WBNP-89 Figure 10.4-36b Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System
WATTS BAR Other Features of Steam and Power Conversion System 10.4-113 WBNP-89 Figure 10.4-36c Turbine Building Units 1 & 2 Flow Diagram Condensate Demineralizer System
WATTS BAR WBNP-94 Figure 10.4-37 Deleted by Amendment 94.
10.4-114 Other Features of Steam and Power Conversion System