Text

Amendment 3 to Updated Final Safety Analysis Report, Chapter 9, Auxiliary System
	ML20323A303
Person / Time
Site:	Watts Bar
Issue date:	10/29/2020
From:	; Tennessee Valley Authority
To:	; Office of Nuclear Reactor Regulation
Shared Package
ML20323A313	List: ML20323A300; ML20323A301; ML20323A303; ML20323A305; ML20323A306; ML20323A308; ML20323A309; ML20323A310; ML20323A311; ML20323A312; ML20323A314; ML20323A315; ML20323A316; ML20323A317; ML20323A318; ML20323A319; ML20323A320; ML20323A322;
References
	WBL-20-047
	Download: ML20323A303 (865)
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{{#Wiki_filter:WBN TABLE OF CONTENTS Section Title Page 9.0 AUXILIARY SYSTEM 9.1-1 9.1 FUEL STORAGE AND HANDLING 9.1-1 9.1.1 New Fuel Storage 9.1-1 9.1.1.1 Design Bases 9.1-1 9.1.1.2 Facilities Description 9.1-1 9.1.1.3 Safety Evaluation 9.1-2 9.1.2 Spent Fuel Storage 9.1-2 9.1.2.1 Design Bases 9.1-2 9.1.2.2 Facilities Description 9.1-3 9.1.2.3 Safety Evaluation 9.1-3 9.1.2.4 Materials 9.1-4 9.1.3 Spent Fuel Pool Cooling and Cleanup System (SFPCCS) 9.1-5 9.1.3.1 Design Bases 9.1-5 9.1.3.1.1 Spent Fuel Pool Cooling 9.1-5 9.1.3.1.2 Spent Fuel Pool Dewatering Protection 9.1-6 9.1.3.1.3 Water Purification 9.1-6 9.1.3.1.4 Flood Mode Cooling 9.1-6 9.1.3.2 System Description 9.1-6 9.1.3.2.1 Component Description 9.1-8 9.1.3.3 Safety Evaluation 9.1-10 9.1.3.3.1 Availability and Reliability 9.1-10 9.1.3.3.2 Spent Fuel Pool Dewatering 9.1-11 9.1.3.3.3 Pool and Fuel Temperature 9.1-11 9.1.3.3.4 Water Quality 9.1-12 9.1.3.3.5 Leakage Detection for the Spent Fuel Pool 9.1-13 9.1.3.4 Tests and Inspections 9.1-13 9.1.3.5 Instrument Application 9.1-13 9.1.3.5.1 Temperature 9.1-13 9.1.3.5.2 Pressure 9.1-13 9.1.3.5.3 Flow 9.1-14 9.1.3.5.4 Level 9.1-14 9.1.4 Fuel Handling System 9.1-14 9.1.4.1 Design Bases 9.1-14 9.1.4.2 System Description 9.1-15 9.1.4.2.1 Refueling Procedure 9.1-16 9.1.4.2.2 Component Description 9.1-19 9.1.4.3 Design Evaluation 9.1-23 9.1.4.3.1 Safe Handling 9.1-23 9.1.4.3.2 Seismic Considerations 9.1-28 9.1.4.3.3 Containment Pressure Boundary Integrity 9.1-28 9-i

WBN-1 TABLE OF CONTENTS Section Title Page 9.1.4.3.4 Radiation Shielding 9.1-29 9.1.4.4 Tests and Inspections 9.1-29 9.1.5 Tritium Producing Burnable Absorber Rods (TPBARs) Consolidation Activity 9.1-29 9.1.5.1 Design Bases 9.1-29 9.1.5.2 Facilities Description 9.1-30 9.1.5.3 Safety Evaluation 9.1-30 References 9.1-31 9.1.6 Independent Spent Fuel Storage Installation (ISFSI) 9.1.6.1 Regulatory Basis 9.1-32 9.1.6.2 System Description 9.1-32 9.1.6.3 Dry Cask Storage Operations 9.1-33 9.1.6.4 Evaluation of 10 CFR Part 50 Reactor Power & 9.1-34 10 CFR Part 72 ISFSI Facilities Interfaces 9.2 WATER SYSTEMS 9.2-1 9.2.1 Essential Raw Cooling Water (ERCW) 9.2-1 9.2.1.1 Design Bases 9.2-1 9.2.1.2 System Description 9.2-1 9.2.1.3 Safety Evaluation 9.2-4 9.2.1.4 Tests and Inspections 9.2-8 9.2.1.5 Instrument Applications 9.2-8 9.2.1.5.1 General Description 9.2-8 9.2.1.5.2 Pressure Instrumentation 9.2-9 9.2.1.5.3 Flow Instrumentation 9.2-9 9.2.1.5.4 Temperature Instrumentation 9.2-9 9.2.1.5.5 Control Valves 9.2-9 9.2.1.6 Corrosion, Organic Fouling, and Environmental Qualification 9.2-10 9.2.1.7 Design Codes 9.2-11 9.2.2 Component Cooling System 9.2-11 9.2.2.1 Design Bases 9.2-11 9.2.2.2 System Description 9.2-13 9.2.2.3 Components 9.2-16 9.2.2.3.1 Component Cooling Heat Exchangers 9.2-16 9.2.2.3.2 Component Cooling Pumps 9.2-16 9.2.2.3.3 Thermal Barrier Booster Pumps 9.2-16 9.2.2.3.4 Component Cooling Surge Tanks 9.2-17 9.2.2.3.5 Seal Leakage Return Unit 9.2-17 9.2.2.3.6 Valves 9.2-17 9.2.2.3.7 Piping 9.2-18 9.2.2.4 Safety Evaluation 9.2-18 9.2.2.5 Leakage Provisions 9.2-21 9.2.2.6 Incidental Control 9.2-21 9.2.2.7 Instrument Applications 9.2-22 9.2.2.7.1 General Description 9.2-22 9.2.2.7.2 Flow Instrumentation 9.2-22 9-ii

WBN TABLE OF CONTENTS Section Title Page 9.2.2.7.3 Level Instrumentation 9.2-22 9.2.2.7.4 Pressure Instrumentation 9.2-23 9.2.2.7.5 Temperature Instrumentation 9.2-23 9.2.2.7.6 Valves 9.2-23 9.2.2.7.7 Conclusion 9.2-23 9.2.2.8 Malfunction Analysis 9.2-23 9.2.2.9 Tests and Inspections 9.2-24 9.2.2.10 Codes and Classification 9.2-24 9.2.3 Demineralized Water Makeup System 9.2-24 9.2.3.1 Design Bases 9.2-24 9.2.3.2 System Description 9.2-24 9.2.3.3 Safety Evaluation 9.2-25 9.2.3.4 Test and Inspection 9.2-26 9.2.3.5 Instrumentation Applications 9.2-26 9.2.4 Potable and Sanitary Water Systems 9.2-26 9.2.4.1 Potable Water System 9.2-26 9.2.4.1.1 System Description 9.2-26 9.2.4.1.2 Safety Evaluation 9.2-27 9.2.4.1.3 Tests and Inspections 9.2-27 9.2.4.1.4 Instrumentation Applications 9.2-27 9.2.4.2 Sanitary Water System 9.2-28 9.2.4.2.1 Design Bases 9.2-28 9.2.4.2.2 System Description 9.2-28 9.2.4.2.3 Safety Evaluation 9.2-29 9.2.4.2.4 Tests and Inspections 9.2-30 9.2.4.2.5 Instrumentation Applications 9.2-30 9.2.5 Ultimate Heat Sink 9.2-31 9.2.5.1 General Description 9.2-31 9.2.5.2 Design Bases 9.2-32 9.2.5.3 Safety Evaluation 9.2-32 9.2.5.4 Instrumentation Application 9.2-34 9.2.6 Condensate Storage Facilities 9.2-34 9.2.6.1 Design Bases 9.2-34 9.2.6.2 System Description 9.2-35 9.2.6.3 Safety Evaluation 9.2-35 9.2.6.4 Test and Inspections 9.2-35 9.2.6.5 Instrument Applications 9.2-35 9.2.7 Refueling Water Storage Tank 9.2-37 9.2.7.1 ECCS Pumps Net Positive Suction Head (NPSH) 9.2-38 9.2.8 Raw Cooling Water System 9.2-40 9.2.8.1 Design Bases 9.2-40 9.2.8.2 System Description 9.2-41 9.2.8.3 Safety Evaluation 9.2-43 9-iii

WBN TABLE OF CONTENTS Section Title Page 9.2.8.4 Tests and Inspection 9.2-44 References 9.2-44 9.3 PROCESS AUXILIARIES 9.3-1 9.3.1 Compressed Air System 9.3-1 9.3.1.1 Design Basis 9.3-1 9.3.1.2 System Description 9.3-1 9.3.1.3 Safety Evaluation 9.3-2 9.3.1.4 Tests and Inspections 9.3-5 9.3.1.5 Instrumentation Applications 9.3-5 9.3.2 Process Sampling System 9.3-6 9.3.2.1 Design Basis 9.3-6 9.3.2.2 System Description 9.3-6 9.3.2.3 Safety Evaluation 9.3-8 9.3.2.4 Tests and Inspections 9.3-9 9.3.2.5 Instrumentation Applications 9.3-9 9.3.2.6 Post Accident Sampling Subsystem 9.3-9 9.3.2.6.1 System Description 9.3-9 9.3.2.6.2 Post Accident Sampling Facility 9.3-10 9.3.2.6.3 Sampling Equipment 9.3-10 9.3.2.6.4 Sample Points 9.3-12 9.3.2.6.5 Post Accident Counting Facilities 9.3-12 9.3.2.6.6 Piping, Tubing, and Valves 9.3-12 9.3.2.6.7 Safety Evaluation 9.3-12 9.3.2.6.8 Tests and Inspections 9.3-12 9.3.3 Equipment and Floor Drainage System 9.3-13 9.3.3.1 Design Bases 9.3-13 9.3.3.2 System Design 9.3-13 9.3.3.2.1 Drains from Lowest Floor Level in the Auxiliary Building 9.3-14 9.3.3.2.2 Residual Heat Removal Pump and Containment Spray Pump Compartments 9.3-14 9.3.3.2.3 CVCS Holdup Tank Compartment and Tritiated Drain Collector Tank Room 9.3-15 9.3.3.2.4 Volume Control Tanks 9.3-15 9.3.3.2.5 Boric Acid Tanks 9.3-16 9.3.3.3 Drains - Reactor Building 9.3-16 9.3.3.4 Design Evaluation 9.3-16 9.3.3.5 Tests and Inspections 9.3-16 9.3.3.6 Instrumentation Application 9.3-16 9.3.3.7 Drain List 9.3-17 9-iv

WBN TABLE OF CONTENTS Section Title Page 9.3.4 Chemical and Volume Control System 9.3-17 9.3.4.1 Design Bases 9.3-17 9.3.4.2 System Description 9.3-19 9.3.4.2.1 Component Description 9.3-25 9.3.4.2.2 System Operation 9.3-37 9.3.4.3 Safety Evaluation 9.3-41 9.3.4.4 Tests and Inspections 9.3-43 9.3.4.5 Instrumentation Application 9.3-43 9.3.5 Failed Fuel Detection System 9.3-44 9.3.5.1 Design Bases 9.3-44 9.3.5.2 System Description 9.3-44 9.3.5.3 Safety Evaluation 9.3-45 9.3.5.4 Tests and Inspections 9.3-45 9.3.5.5 Instrument Applications 9.3-45 9.3.6 Auxiliary Charging System 9.3-45 9.3.6.1 Design Bases 9.3-45 9.3.6.2 System Design Description 9.3-46 9.3.6.3 Design Evaluation 9.3-47 9.3.6.4 Tests and Inspection 9.3-47 9.3.6.5 Instrument Application 9.3-47 9.3.7 Boron Recycle System 9.3-48 9.3.8 Heat Tracing 9.3-48 References 9.3-48 9.4 AIR CONDITIONING, HEATING, COOLING AND VENTILATION SYSTEMS 9.4-1 9.4.1 Control Room Area Ventilation System 9.4-1 9.4.1.1 Design Bases 9.4-1 9.4.1.2 System Description 9.4-3 9.4.1.3 Safety Evaluation 9.4-8 9.4.1.4 Tests and Inspection 9.4-9 9.4.2 Fuel Handling Area Ventilation System 9.4-9 9.4.2.1 Design Bases 9.4-9 9.4.2.2 System Description 9.4-11 9.4.2.3 Safety Evaluation 9.4-11 9.4.2.4 Inspection and Testing 9.4-12 9-v

WBN TABLE OF CONTENTS Section Title Page 9.4.3 Auxiliary and Radwaste Area Ventilation System 9.4-13 9.4.3.1 Design Bases 9.4-13 9.4.3.2 System Description 9.4-14 9.4.3.2.1 Building Air Supply and Exhaust Systems (General Ventilation) 9.4-14 9.4.3.2.2 Building Cooling System (Chilled Water) 9.4-16 9.4.3.2.3 Safety Feature Equipment Coolers 9.4-16 9.4.3.2.4 Shutdown Board Room Air-Conditioning System 9.4-16 9.4.3.2.5 Auxiliary Board Rooms Air-Conditioning System 9.4-17 9.4.3.2.6 Shutdown Transformer Room Ventilating System 9.4-19 9.4.3.2.7 Auxiliary Building Miscellaneous Ventilation and Air-Conditioning Systems 9.4-19 9.4.3.3 Safety Evaluation 9.4-20 9.4.3.3.1 Auxiliary Building General Ventilation System 9.4-20 9.4.3.3.2 Building Cooling System 9.4-21 9.4.3.3.3 Safety Feature Equipment Coolers 9.4-21 9.4.3.3.4 Shutdown Board Room Air-Conditioning System 9.4-21 9.4.3.3.5 Auxiliary Board Rooms Air-Conditioning System 9.4-22 9.4.3.3.6 Shutdown Transformer Room Ventilating System 9.4-23 9.4.3.3.7 Auxiliary Building Miscellaneous Ventilation and Air-Conditioning System 9.4-24 9.4.3.4 Inspection and Testing Requirements 9.4-25 9.4.4 Turbine Building Area Ventilation System 9.4-25 9.4.4.1 Design Bases 9.4-25 9.4.4.2 System Description 9.4-25 9.4.4.2.1 Elevation 755.0 Ventilation 9.4-26 9.4.4.2.2 Elevation 729.0 and Elevation 708.0 Ventilation 9.4-26 9.4.4.2.3 Elevation 685.5 Ventilation 9.4-26 9.4.4.2.4 Cold Weather Building Pressurization 9.4-26 9.4.4.2.5 Turbine Building Miscellaneous Ventilating Systems 9.4-27 9.4.4.2.6 Coolers 9.4-27 9.4.4.2.7 Building Heating System 9.4-27 9.4.4.3 Safety Evaluation 9.4-28 9.4.4.4 Inspection and Testing Requirements 9.4-28 9-vi

WBN TABLE OF CONTENTS Section Title Page 9.4.5 Engineered Safety Feature Ventilation System 9.4-28 9.4.5.1 ERCW Intake Pumping Station (IPS) 9.4-29 9.4.5.1.1 Design Bases 9.4-29 9.4.5.1.2 System Description 9.4-30 9.4.5.1.3 Safety Evaluation 9.4-30 9.4.5.1.4 Inspection and Testing Requirements 9.4-31 9.4.5.2 Diesel Generator Buildings 9.4-31 9.4.5.2.1 Diesel Generator Building 9.4-31 9.4.5.3 Auxiliary Building Engineered Safety Features (ESF) Equipment Coolers 9.4-35 9.4.5.3.1 Design Bases 9.4-35 9.4.5.3.2 System Description 9.4-37 9.4.5.3.3 Safety Evaluation 9.4-38 9.4.5.3.4 Inspection and Testing Requirements 9.4-39 9.4.6 Reactor Building Purge Ventilating System (RBPVS) 9.4-39 9.4.6.1 Design Bases 9.4-39 9.4.6.2 System Description 9.4-42 9.4.6.3 Safety Evaluation 9.4-44 9.4.6.4 Inspection and Testing Requirements 9.4-45 9.4.7 Containment Air Cooling System 9.4-46 9.4.7.1 Design Bases 9.4-46 9.4.7.2 System Description 9.4-47 9.4.7.2.1 Lower Compartment Air Cooling System 9.4-47 9.4.7.2.2 Control Rod Drive Mechanisms Air Cooling System 9.4-48 9.4.7.2.3 Upper Compartment Air Cooling System 9.4-48 9.4.7.2.4 Reactor Building Instrument Room Air Cooling System 9.4-49 9.4.7.2.5 Controls and Instrumentation 9.4-49 9.4.7.3 Safety Evaluation 9.4-49 9.4.7.4 Test and Inspection Requirements 9.4-50 9.4.8 Condensate Demineralizer Waste Evaporator Building Environmental Control System 9.4-50 9.4.9 Post Accident Sampling Facility Environmental Control System 9.4-51 9.4.9.1 Design Basis 9.4-51 9.4.9.2 System Description 9.4-51 9.4.9.2.1 PASFVS 9.4-51 9.4.9.2.2 PASFHCS 9.4-52 9.4.9.2.3 PASFGTS 9.4-52 9.4.9.3 Safety Evaluation 9.4-52 9.4.9.4 Inspection and Testing Requirements 9.4-52 References 9.4-52 9.5 OTHER AUXILIARY SYSTEMS 9.5-1 9.5.1 Fire Protection System 9.5-1 9.5.2 Plant Communications System 9.5-1 9.5.2.1 Design Bases 9.5-1 9.5.2.2 General Description Interplant Communications 9.5-1 9.5.2.3 General Description Interplant System 9.5-4 9-vii

WBN TABLE OF CONTENTS Section Title Page 9.5.2.4 Evaluation 9.5-5 9.5.2.5 Inspection and Tests 9.5-8 9.5.3 Lighting Systems 9.5-8 9.5.3.1 Design Bases 9.5-8 9.5.3.2 Description of the Plant Lighting Systems 9.5-9 9.5.3.3 Diesel Generator Building Lighting System 9.5-10 9.5.3.4 Safety-Related Functions of the Lighting System 9.5-10 9.5.3.5 Inspection and Testing Requirements 9.5-10 9.5.4 Diesel Generator Fuel Oil Storage and Transfer System 9.5-11 9.5.4.1 Design Bases 9.5-11 9.5.4.2 System Description 9.5-12 9.5.4.3 Safety Evaluation 9.5-15 9.5.4.4 Tests and Inspections 9.5-16 9.5.5 Diesel Generator Cooling Water System 9.5-16 9.5.5.1 Design Basis 9.5-16 9.5.5.2 System Description 9.5-16 9.5.5.3 Safety Evaluation 9.5-17 9.5.5.4 Tests and Inspections 9.5-17 9.5.6 Diesel Generator Starting System 9.5-18 9.5.6.1 Design Bases 9.5-18 9.5.6.2 System Description 9.5-18 9.5.6.3 Safety Evaluation 9.5-19 9.5.6.4 Tests and Inspection 9.5-19 9.5.7 Diesel Engine Lubrication System 9.5-20 9.5.7.1 Design Bases 9.5-20 9.5.7.2 System Description 9.5-21 9.5.7.3 Safety Evaluation 9.5-22 9.5.7.4 Test and Inspections 9.5-22 9.5.8 Diesel Generator Combustion Air Intake and Exhaust System 9.5-23 9.5.8.1 Design Bases 9.5-23 9.5.8.2 System Descriptions 9.5-23 9.5.8.3 Safety Evaluation 9.5-23 9.5.8.4 Tests and Inspection 9.5-24 References 9.5-24 9-viii

WBN-1 LISTS OF TABLES Number Title 9.1-1 Spent Fuel Pool Cooling and Cleanup System Design Parameters 9.1-2 Spent Fuel Pool Cooling and Cleanup System Design and Operating Parameters 9.1-3 Basis for Design Criteria of the Watts Bar Nuclear Plant Spent Fuel Racks 9.1-4 10 CFR Part 50 Reactor Power & 10 CFR Part 72 ISFSI Facilities Interface Documents 9.2-1 Essential Raw Cooling Water System Pump Design Data 9.2-2 Essential Raw Cooling Water System Failure Modes and Effects Analysis 9.2-3 Moved to Table 6.3-12 9.2 7 Deleted 9.2-8 Component Cooling System Component Design Data 9.2-9 Component Cooling Water System Failure Modes and Effects Analysis 9.2-10 Component Cooling System Code Requirements 9.2-11 Raw Cooling Water System Pump Design Data 9.3-1 Compressed Air System Descriptive Information; Station Control and Service Air Systems 9.3-2 Process Sampling System Sample Locations and Data 9.3-3 Equipment and Floor Drainage Data Reactor Coolant System 9.3-4 Chemical and Volume Control System Design Parameters 9.3-5 Principal Component Design Data Summary 9.3-6 Deleted 9.3-7 Failure Mode and Effects Analysis; Auxiliary Air Supply Equipment 9-ix

WBN-2 LISTS OF TABLES Number Title 9.3-8 Equipment Supplied with Auxiliary Control System Air 9.4-1 Purge Air Cleanup Data 9.4-2 Failure Modes and Effects Analysis Intake Pumping Station Ventilation System 9.4-3 Failure Modes and Effects Analysis for Active Failures; Subsystem: Safety Feature Equipment Coolers 9.4-3A Failure Modes and Effects Analysis for Active Failures; Subsystem: Turbine Driven Auxiliary Feedwater Pump Room Ventilation 9.4-4 Failure Modes and Effects Analysis Diesel Generator Ventilation System 9.4-4A Deleted 9.4-5 Failure Modes and Effects Analysis for Active Failures; Subsystem: Auxiliary Board Rooms Air Conditioning System 9.4-6 Failure Modes and Effects Analysis for Active Failures; Subsystem: 480V Shutdown Transformer Room Ventilation 9.4-7 Failure Modes and Effects Analysis Control Building HVAC System 9.4-8 Failure Modes and Effects Analysis for Active Failures; Subsystem: Auxiliary Building General Ventilation System 9.4-8A Failure Modes and Effects Analysis for Active Failures for Components Common to the Auxiliary Building HVAC Subsystem 9.4-8B Failure Modes and Effects Analysis for Auxiliary Building HVAC Subsystem Passive Failures 9.4-9 Failure Modes and Effects Analysis; Subsystem: Shutdown Board Room Air Conditioning and Ventilation 9.4-10 Failure Modes and Effects Analysis, Subsystem: Main Steam Valve Vault Ventilation System 9.4-10A Failure Modes and Effects Analysis for Active Failure; Subsystem: Post Accident Sampling System 9.5-1 Deleted 9.5-2 Failure Mode and Effects Analysis of the Standby Diesel Generator Auxiliary Systems 9-x

WBN LIST OF FIGURES Number Title 9.1-1 New Fuel Storage Racks 9.1-2 Deleted 9.1-3 Powerhouse, Auxiliary, and Reactor Buildings Units 1 and 2 - Mechanical Flow Diagram for Fuel Pool Cooling and Cleaning System 9.1-4 Powerhouse Aux Bldg Units 1 & 2 Control Diagram for Spent Fuel Pit Cooling System 9.1-5 Logic Diagram for Spent Fuel Pit Cooling System 9.1-6 Typical Manipulator Crane 9.1-7 Typical Spent Fuel Pit Bridge 9.1-8 New Fuel Elevator 9.1-9 Fuel Transfer System Assembly 9.1-10 Rod Cluster Control Changing Fixture 9.1-11 Typical Spent Fuel Handling Tool 9.1-12 Typical New Fuel Handling Tool 9.1-13 Reactor Building Units 1 and 2 Internal Lifting Rig Platform and Mech Tools Arrangement and Details 9.1-14 Typical Stud Tensioner 9.1-15 Plan View of Spent Fuel Pool 9.1-16 Flux Trap Spent Fuel Storage Rack 9.1-17 Spent Fuel Pool Cask Loading Area - TPBAR Consolidation Fixture Layout Plan View 9.1-18 Spent Fuel Pool Cask Loading Area - TPBAR Consolidation Fixture Elevation View 9.1-19 TPBAR Consolidation Canister 9-xi

WBN-3 LIST OF FIGURES Number Title 9.2-1 Flow Diagram for Essential Raw Cooling Water System 9.2-2 Powerhouse and Auxiliary Building Units 1 and 2 Flow Diagram for Essential Raw Cooling Water System 9.2-3 Powerhouse and Reactor Building Unit 1 Flow Diagram for Essential Raw Cooling Water System 9.2-3 Powerhouse and Reactor Building Unit 2 Flow Diagram for Essential Raw Cooling Water System 9.2-4 Powerhouse Auxiliary and Control Buildings Mechanical Flow Diagram for Essential Raw Cooling Water System 9.2-4A Powerhouse Turbine Building Units 1 and 2 Mechanical Flow Diagram for Essential Raw Cooling Water System 9.2-4B Powerhouse Auxiliary Building Mechanical Flow Diagram for Essential Raw Cooling Water System (Unit 2) 9.2-4C Powerhouse Auxiliary Building Units 1 and 2 Mechanical Flow Diagram for Essential Raw Cooling Water 9.2-5 Powerhouse Electrical Logic Diagram for Essential Raw Cooling Water System 9.2-6 Powerhouse Electrical Logic Diagram for Essential Raw Cooling Water System 9.2-7 Logic Diagram for Essential Raw Cooling Water System 9.2-8 Logic Diagram for Essential Raw Cooling Water System 9.2-9 Powerhouse Electrical Logic Diagram for Essential Raw Cooling Water System 9.2-10 Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 1) 9.2-10 Sh A Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 2) 9.2-11 Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 1) 9.2-11 Sh A Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 2) 9.2-12 Electrical Control Diagram for Essential Raw Cooling Water System (Unit 1) 9-xii

WBN-3 LIST OF FIGURES Number Title 9.2-12 Sh A Electrical Control Diagram for Essential Raw Cooling Water System (Unit 2) 9.2-13 Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System 9.2-14 Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 1) 9.2-14 Sh A Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 2) 9.2-14 Sh B Powerhouse Electrical Control Diagram for Essential Raw Cooling Water System (Unit 1) 9.2-15 Deleted 9.2-16 Powerhouse, Auxiliary Building Units 1 and 2 Mechanical Flow Diagram for Component Cooling Water System 9.2-17 Powerhouse, Auxiliary and Reactor Building Mechanical Flow Diagram for Component Cooling System (Unit 2) 9.2-18 Powerhouse, Auxiliary and Reactor Building Mechanical Flow Diagram for Component Cooling System (Unit 1) 9.2-19 Powerhouse, Auxiliary Building Mechanical Flow Diagram CCS (Units 1 and 2) 9.2-20 Powerhouse Electrical Control Diagram for Component Cooling Water System 9.2.20A Powerhouse Unit 2 Electrical Control Diagram for Component Cooling Water System 9.2-21 Powerhouse Electrical Control Diagram for Component Cooling Water System (Unit 1) 9.2-21 Sh A Powerhouse Electrical Control Diagram for Component Cooling Water System (Unit 2) 9.2-22 Powerhouse Electrical Control Diagram for Component Cooling Water System (Unit 1) 9.2-22 Sh A Powerhouse Electrical Control Diagram for Component Cooling Water System (Unit 2) 9.2-23 Powerhouse Electrical Logic Diagram for Component Cooling Water System 9.2-24 Powerhouse Electrical Logic Diagram for Component Cooling Water System 9-xiii

WBN LIST OF FIGURES Number Title 9.2-25 Powerhouse Electrical Logic Diagram for Component Cooling System 9.2-25A Powerhouse Electrical Logic Diagram for Component Cooling System 9.2-26 Powerhouse, Turbine Building Mechanical Flow Diagram for Water Heater and Demineralizers 9.2-27 Powerhouse, Turbine Building Mechanical Flow Diagram for Makeup Water Heater and Demineralizers 9.2-28 Powerhouse, Service and Office Buildings Units 1 and 2 Flow Diagram for Demineralized Water and Cask Decon System 9.2-29A General Flow Diagram for Potable Water Distribution System 9.2-29B General Flow Diagram for Potable Water Distribution System 9.2-29C Turbine, Service and Office Buildings Flow Diagram for Potable Water Distribution System 9.2-29D Flow Diagram for Potable Water Distribution System 9.2-30 Deleted 9.2-31 Deleted 9.2-32 Mechanical Flow Diagram for Raw Cooling Water 9.2-33 Mechanical Flow Diagram for Raw Cooing Water 9.2-34 Mechanical Flow Diagram for Raw Cooling Water 9.2-35 Powerhouse Mechanical Flow Diagram for Raw Cooling Water 9.2-36 Powerhouse and Intake Pumping Station Electrical Control Diagram for Raw Cooling Water System 9.2-37 Powerhouse Units 1 and 2 Electrical Control Diagram for Raw Cooling Water System 9.2-38 Powerhouse Units 1 and 2 Electrical Control Diagram for Raw Cooling Water 9.2-39 Powerhouse Units 1 and 2 Logic Diagram for Raw Cooling Water 9.2-40 Essential Raw Cooling Water Control Air and HPFP Piping (Unit 1) 9.2-41 Diver Protection Barriers 9.3-1 Electrical Control Diagram for Control Air System 9-xiv

WBN-3 LIST OF FIGURES Number Title 9.3-2 Electrical Control Diagram for Control Air System 9.3-2A Electrical Control Diagram for Control Air System 9.3-3 Electrical Logic Diagram for Compressed Air System 9.3-4 Electrical Logic Diagram for Control Air System 9.3-4A Electrical Logic Diagram for Control Air System 9.3-5 Turbine Building and Yard Flow Diagram for Control and Service Air System 9.3-5A Control, Auxiliary, Reactor, Turbine, Office and Service Building Flow Diagram for Control and Service Air 9.3-6 Powerhouse Mechanical Flow Diagram for Control Air System 9.3-6A Powerhouse Mechanical Flow Diagram for Control Air System 9.3-6B Powerhouse Mechanical Flow Diagram for Control Air System 9.3-7 Powerhouse Mechanical Flow Diagram - Floor and Equipment Drains 9.3-8 Powerhouse Mechanical Flow Diagram - Floor and Equipment Drains 9.3-9 Auxiliary Building Mechanical Flow Diagram - Floor and Equipment Drains 9.3-10 Auxiliary Building Mechanical Flow Diagram - Floor and Equipment Drains 9.3-11 Auxiliary Building Mechanical Flow Diagram - Floor and Equipment Drains 9.3-12 Auxiliary Building Flow Diagram Roof Drains and Floor Equipment Drains 9.3-13 Powerhouse Electrical Logic Diagram for Waste Disposal System 9.3-14 Powerhouse Electrical Logic Diagram for Waste Disposal System 9.3-15 Powerhouse Electrical and Auxiliary Building Flow Diagram for Chemical and Volume Control System and Boron Recovery System (Sheets 1 through 6A) 9.3-15 Powerhouse Electrical Control Diagram for Chemical and Volume Control System (Sheets 7, 8, 9, 9A, 10, 11 and 12) 9.3-16 Gross Failed Fuel Detector Flow Diagram 9.3-17 Gross Failed Fuel Detector Electronics Diagram 9-xv

WBN LIST OF FIGURES Number Title 9.3-18 Powerhouse Auxiliary Building Units 1 & 2 Flow Diagram for Flood Mode Boration 9.3-19 Deleted 9.3-20 Deleted 9.3-21 Boric Acid Tank Limits Based on RWST Boron Concentration 9.4-1 Powerhouse, Control Building Flow Diagram for Heating, Ventilating, and Air Conditioning Air Flow 9.4-2 Powerhouse Flow Diagram for Air Conditioning Chilled Water 9.4-3 Powerhouse, Control Building Flow Diagram for Air Conditioning Chilled Water 9.4-4 Powerhouse, Control Building Electrical Control Diagram for Air Conditioning 9.4-4A Control Building Air Conditioning Electrical Control Diagram-Chilled Water 9.4-5 Control Building Air Conditioning Electrical Control Diagram-Chilled Water 9.4-6 Control Building Control Diagram for Air Conditioning System 9.4-7 Control Building Electrical Logic Diagram for Ventilation System 9.4-8 Powerhouse, Auxiliary Building Flow Diagram, Heating, and Ventilating Air Flow 9.4-9 Auxiliary Building Electrical Logic Diagram for Ventilation System 9.4-10 Auxiliary Building Electrical Logic Diagram for Ventilation System 9.4-11 Powerhouse Electrical Control Diagram for Containment Ventilation System 9.4-12 Powerhouse Electrical Control Diagram for Radiation Monitoring System 9.4-13 Powerhouse, Auxiliary Building Flow Diagram for Heating, Cooling, and Ventilating Air Flow 9.4-14 Auxiliary Building Flow Diagram for Heating, Cooling, and Ventilating Air Flow 9.4-15 Powerhouse, Auxiliary Building Flow Diagram for Heating, Ventilation and Air Conditioning Air Flow 9.4-16 Powerhouse, Auxiliary Building and Additional Equipment Building Flow Diagram for Heating, Cooling, and Ventilating Air Flow 9.4-17 Powerhouse Electrical Control Diagram for Containment Ventilating System 9-xvi

WBN LIST OF FIGURES Number Title 9.4-18 Turbine Building and Control Flow Diagram for Heating and Ventilating Air Flow 9.4-19 Powerhouse Flow Diagram for Building Heating 9.4-20 Powerhouse Flow Diagram for Building Heating (Unit 2) 9.4-21 Pumping Stations Mechanical Heating and Ventilating 9.4-22 Diesel Generator Building Flow and Control Diagram for Heating, Ventilating Air Flow 9.4-23 Diesel Generator Building Mechanical Heating and Ventilating 9.4-24 Diesel Generator Building Mechanical Heating and Ventilating 9.4-24A Diesel Generator Building Mechanical Heating and Ventilating 9.4-25 Diesel Building Electrical Logic Diagram for Ventilation System 9.4-26 Powerhouse Electrical Control Diagram for Containment Ventilation System (Unit 1) 9.4-27 Powerhouse Electrical Control Diagram for Containment Ventilation System (Unit 1) 9.4-28 Reactor Building Flow Diagram for Heating and Ventilating Air Flow 9.4-28 Sh A Reactor Building Unit 2 Flow Diagram for Heating and Ventilating Air Flow 9.4-29 Powerhouse Electrical Logic Diagram for Ventilation System (Unit 1) 9.4-30 Powerhouse Electrical Control Diagram for Containment Ventilation System (Unit 1) 9.4-30 Sh A Powerhouse Electrical Control Diagram for Containment Ventilation System (U2) 9.4-30 Sh B Powerhouse Electrical Control Diagram for Containment Ventilation System (U1) 9.4-31 Powerhouse Electrical Control Diagram for Containment Ventilation System 9.4-32 Powerhouse Electrical Logic Diagram for Ventilation System 9.4-33 Electrical Logic Diagram for Ventilation System 9.4-34 Powerhouse Logic Diagram for Ventilation System 9-xvii

WBN LIST OF FIGURES Number Title 9.4-35 Powerhouse Post-Accident Sampling System Flow Diagram for Heating, Ventilating and Air Conditioning Air Flow 9.4-36 Auxiliary Building Electrical Logic Diagram for Post-Accident Sampling System 9.4-37 Auxiliary Building Electrical Control Diagram for Post-Accident Sampling 9.5 18 Deleted 9.5-19 Communications Equipment Availability 9.5-20 Yard, Powerhouse, and Diesel Generator Building Flow Diagram for Fuel Oil Atomizing Air and Steam 9.5-20A Deleted 9.5-20 Sh B Additional Diesel Generator Building Unit 2 Flow Diagram for Fuel Oil, Atomizing Air and Steam 9.5-21 Powerhouse Electrical Control Diagram for Fuel Oil System 9.5-22 Powerhouse Electrical Logic Diagram for Fuel Oil System 9.5-23 Schematic Diagram - Jacket Water System with Heat Exchanger 9.5-24 Diesel Generator Building Flow Diagram for Diesel Starting Air System (Unit 1) 9.5-25 Diesel Generator Building Control Diagram for Diesel Starting Air System (DG 1A-A) 9.5-25A Diesel Generator Building Control Diagram for Diesel Starting Air System (DG 1B-B) 9.5-25B Diesel Generator Building Control Diagram for Diesel Starting Air System (DG 2A-A) 9.5-25C Diesel Generator Building Control Diagram for Diesel Starting Air System (DG 2B-B) 9.5-26 Schematic Diagram for Lube Oil System 9.5-27 Diesel Engine Lubrication System 9.5-28 Deleted 9.5-29 Diesel Air Intake Piping Schematic 9.5-30 Diesel Exhaust System Piping Schematic 9-xviii

WBN 9.0 AUXILIARY SYSTEMS 9.1 FUEL STORAGE AND HANDLING 9.1.1 New Fuel Storage 9.1.1.1 Design Bases New fuel is stored in racks (Figure 9.1-1). Each rack is composed of individual vertical cells which can be fastened together in any number to form a module that can be firmly bolted to anchors in the floor of the new fuel storage pit. The new fuel storage racks are designed to include storage for 1/3 core for each unit at a center to center spacing of 21 inches. This spacing provides a minimum separation between adjacent fuel assemblies of 12 inches which is sufficient to maintain a subcritical array even in the event the building is flooded with unborated water. Space between storage positions is blocked to prevent insertion of fuel. All surfaces that come into contact with the fuel assemblies are made of annealed austenitic stainless steel, whereas the supporting structure may be painted carbon steel. A three inch drain is provided in the new fuel storage vault. The racks are designed to withstand nominal operating loads as well as safe shutdown earthquake (SSE) and operating basis earthquake (OBE) seismic loads in accordance with Regulatory Guides 1.29 and 1.13. The new fuel storage racks are located in the new fuel pit area which has a cover that protects the racks from dropped objects. Administrative controls are utilized when a section of the protective cover is removed for handling of the new fuel assemblies. 9.1.1.2 Facilities Description The location of the new fuel storage vault is shown in Figures 1.2-3 and 1.2-8. The design of the new fuel storage racks is shown in Figure 9.1-1. The new fuel storage vault is a reinforced concrete structure. This vault is a part of the Auxiliary Building, which is a Seismic Category I Structure (See Section 3.2). The new fuel storage vault opens on to the Elevation 757 floor, but is normally covered by a series of hatches which are designed to withstand the effects of an OBE or SSE. These hatches are removed as necessary during handling of the new fuel. 9.1-1

WBN 9.1.1.3 Safety Evaluation The center-to-center distance between new fuel assemblies is sufficient to assure keff < 0.98 when the new fuel storage area is dry or fogged (optimally moderated). For the fully flooded condition assuming cold, clean, unborated water, the value of keff is less than or equal to 0.95. The new fuel assemblies are stored dry, the 21 inch center to center spacing ensuring an ever safe geometric array. Under these conditions, a criticality accident during refueling and storage is not considered credible. Design of the storage racks is in accordance with Regulatory Guide 1.13 and 1.29 and ensures adequate safety under normal and postulated accidents. Consideration of criticality safety analysis is discussed in Section 4.3.2.7. 9.1.2 Spent Fuel Storage 9.1.2.1 Design Bases The spent fuel racks are designed in accordance with the following listed criteria:

1. The spent fuel storage racks were designed for storage of 1386 fuel assemblies. The design meets all the structural and seismic requirements of Category I equipment as defined by the NRC Position Paper dated April 14, 1978, on spent fuel storage and handling applications and the references listed in Table 9.1-3.

2. Burnup credit and fuel assembly placement controls are used to ensure the fuel array in the spent fuel racks is maintained subcritical assuming the array is fully flooded with nonborated water, the fuel is new with a maximum anticipated enrichment of 5.0 weight percent U-235 and the geometric array is the worst possible considering mechanical tolerances and abnormal conditions.

3. The spent fuel storage facility is designed to prevent severe natural phenomena, including missiles generated from high winds, from causing damage to the spent fuel.

The spent fuel storage facility, including the spent fuel racks, is Seismic Category I.

4. The spent fuel storage racks are designed to withstand handling and normal operating loads and the maximum uplift forces generated by the fuel handling equipment.

9.1-2

WBN

5. A loss of pool cooling accident is not considered a credible accident because the pool cooling system is Seismic Category I and single failure proof.

6. The spent fuel storage racks are designed to withstand the impact of a dropped spent fuel assembly from the maximum lift height of the spent fuel pit bridge hoist.

7. The spent fuel storage facilities provide the capability for limiting the potential offsite exposures, in the event of significant release of radioactivity from the stored fuel, to well less than 10 CFR 100 guidelines.

9.1.2.2 Facilities Description The spent fuel storage pool is a reinforced concrete structure with a stainless steel liner for leak tightness. This storage pool is a part of the Seismic Category I Auxiliary Building, and is shared between Units 1 and 2. Both the liner and pool walls are designed to withstand the effects of an OBE and SSE. The location of the spent fuel storage pool is shown on Figures 1.2-3 and 1.2-8. The storage rack configuration in the pool is shown on Figure 9.1-15. Typical storage racks are shown on Figure 9.1-16. The spent fuel storage pool opens onto the Elevation 757 floor, and is protected by a guard rail which surrounds the pool. The depth of the pool is sufficient to allow some 26 feet of water shielding (nominally) above the spent fuel. This water depth ensures that the doses on the operating floor from stored spent fuel are negligibly small. The spent fuel storage racks consist of stainless steel structures with cells or receptacles for nuclear fuel assemblies as they are used in a reactor. Twenty-four of these flux trap racks, provide 1386 storage positions in eighteen 7 x 8 cell array modules and six 7 x 9 cell array modules. Figure 9.1-15 shows the layout of the storage racks in the spent fuel pool. Each rack is supported by four pedestals (one rack has five pedestals) sitting on two-inch thick stainless steel bearing pads which spread the load on the pool floor. 9.1.2.3 Safety Evaluation Design of these storage racks is in accordance with Regulatory Guide 1.13 and ensures a safe condition under normal and postulated accident conditions. The distance between spent fuel assemblies is maintained to ensure a keff < 0.95 even if unborated water is used to fill the spent fuel storage pool. Consideration of criticality safety analysis is discussed in Section 4.3.2.7. 9.1-3

WBN The spent fuel racks are designed as free standing and are qualified as seismic Category I structures. The seismic design considered fully loaded racks in water at less than boiling temperature undergoing a SSE. Composite, dynamic simulations which modeled all racks in the pool were utilized to determine limiting loads and displacements for each rack in the pool, to establish limiting relative motion between racks, and to evaluate the potential for and the consequences of inter-rack and rack-wall phenomena in the entire assemblage of racks. The racks were also checked for OBE loads and found to be satisfactory. See section 3.8.4 for related pool structure information. The racks can withstand the drop of a fuel assembly from its maximum supported height and the drop of tools used in the pool. The racks are also capable of withstanding accidental drops of the gates which cover the slots between the spent fuel pool and the transfer canal and cask loading pit from a height of eight feet above the top of the racks. Electrical and mechanical stops prevent the movement of heavy objects over the spent fuel pool including the shipping casks. The movement of the casks is restricted to areas away from the pool. The wall which separates the fuel storage area from the cask loading area has been designed to restrict damage to the cask loading area if a cask were dropped even in a tipped position in the cask loading area. Loss of pool cooling and pool water events are discussed in Section 9.1.3. Radiation sources and protection for the pool water are discussed in Sections 12.2.1 and 12.3.2.2. Although the number of stored fuel assemblies is increased, the capacity of the pool water cleanup system is adequate to maintain radionuclide concentrations within design limits. Therefore no increase in personnel exposures is expected. 9.1.2.4 Materials The materials used in the construction of the spent fuel racks are 304 stainless, CF-3M stainless and 17-4 PH stainless. The neutron poison material is a commercial product known as Boral and contains B4C powder in a matrix. The flux trap racks contain the following proven materials:

a. Poison inner can and outer tubes: 304 stainless steel, ASTM A-666-72 Grade B

b. Top and bottom grid castings: CF-3M, ASTM A-296-77

c. Threaded pedestal foot: 17-4 PH, ASTM A-564-66 9.1-4

WBN-3 In addition to the stainless steel material, the racks employ Boral, a patented product of AAR Brooks and Perkins, as the thermal neutron absorber material. Boral is a thermal neutron absorbing material consisting of finely divided particles of boron carbide (B4C) uniformly distributed in type 1100 aluminum, pressed and sintered in a hot rolling process. Boron carbide is a compound having a high boron content in a physically stable and chemically inert form. The 1100 alloy aluminum is a light weight metal with high tensile strength which is protected from corrosion by a highly resistant oxide film. The two materials, boron carbide and aluminum, are chemically compatible and ideally suited for long term use in the radiation, thermal and chemical environment of a spent fuel pool. However, since the criticality analysis discussed in Section 4.3.2.7 takes credit for this material, a Neutron Absorber Monitoring Program following the Guidance of NEI 16-03-A has been implemented. Representative Boral coupon samples are available on a mounting called a tree for monitoring the integrity of the neutron absorber material without disrupting the Integrity of the storage system. The coupon tree is placed in a designed cell and surrounded by spent fuel. Specimens may be removed from the coupon tree array and certain physical and chemical properties measured from which the stability and integrity of Boral in the spent fuel storage cells may be inferred. 9.1.3 Spent Fuel Pool Cooling and Cleanup System (SFPCCS) The SFPCCS is designed to remove from the spent fuel pool water the decay heat generated by stored spent fuel assemblies. Additional functions of the SFPCCS are to clarify and purify the water in the spent fuel pool, transfer canal, and refueling water storage tanks (RWSTs). If a warning of flood above plant grade is received when the one with both reactor vessels are open or vented to the containment atmosphere, the SFPCCS will be modified as indicated in Section 2.4.14 to accomplish cooling the reactor core(s). 9.1.3.1 Design Bases SFPCCS design parameters are given in Table 9.1-1. 9.1.3.1.1 Spent Fuel Pool Cooling The SFPCCS is designed to remove the decay heat from the spent fuel assemblies stored in the pool and maintain acceptable pool temperatures following a full core discharge. The temperatures listed in Table 9.1-1 can be maintained for the various full core offload scenarios assuming the SFPCCS heat exchangers are supplied with component cooling water at its design flow and temperature. If it is necessary to remove a complete core after a normal refueling, the system can maintain the spent fuel pool water at or below 159.2°F in the worst case design basis single failure scenario. 9.1-5

WBN The SFPCCS incorporates two trains of equipment (plus a spare pump capable of operation in either train). The flow through the pool provides sufficient mixing to ensure uniform water conditions throughout the pool. Under design basis Ultimate Heat Sink (UHS) temperatures and heat exchanger fouling conditions, the heat load in the spent fuel pool is limited to 28.1E+06 BTU/hr during refueling outages. Under more favorable conditions, up to 50.2E+06 BTU/hr may be accommodated. Cycle specific calculations may be performed prior to the start of a refueling outage to determine the exact heat removal capability of the SFPCCS using recent heat exchanger performance testing and anticipated UHS temperatures; otherwise, 28.1E+06 BTU/hr may not be exceeded. The rate of fuel transfer from the reactor to the SFP is controlled such that, with one (1) train of SFPCCS in service, the SFP temperature will remain below 151.2 °F. Operating procedures provide the controls to ensure these limitations are met. A decay heat calculation is routinely performed at the end of each operating cycle to produce heat decay vs time curves for the core and spent fuel pool. This calculation can be used to determine the time to begin core offload and the rate at which the core can be off loaded. 9.1.3.1.2 Spent Fuel Pool Dewatering Protection System piping is arranged so that failure of any pipeline cannot drain the spent fuel pool below the water level required for radiation shielding. A water level of ten feet or more above the top of the stored spent fuel assemblies is maintained to limit direct gamma dose rate. 9.1.3.1.3 Water Purification The system's demineralizer and filter are designed to provide adequate purification to permit unrestricted access to the spent fuel storage area for plant personnel and maintain optical clarity of the spent fuel pool water surface by use of the system's skimmers, strainer, and skimmer filter. 9.1.3.1.4 Flood Mode Cooling Section 2.4.14 presents the design basis operation of the SFPCCS when it may be used for reactor core cooling during flooded plant conditions. 9.1.3.2 System Description The SFPCCS, shown in Figure 9.1-3, consists of two cooling trains (plus a backup pump capable of operation in either train), a purification loop, and a separate skimmer loop. The electrical logic control diagrams for this system are shown in Figures 9.1-4 and 9.1-5. 9.1-6

WBN-1 The SFPCCS removes decay heat from fuel stored in the spent fuel pool. Spent fuel is placed in the pool during the refueling sequence and stored there until it is shipped offsite or the spent fuel assemblies may be placed in interim storage at WBN Independent Spent Fuel Storage Installation (ISFSI) (Section 9.1.6). The system normally handles the heat load from either a full core or 1/3 of a core freshly discharged from each reactor plus the decreasing heat load from previously discharged fuel. Heat is transferred from the SFPCCS through the heat exchangers to the component cooling system. When the SFPCCS is in operation, water flows from the spent fuel pool to both spent fuel pool pump suctions, is pumped through the tube side of the heat exchangers, and is returned to the pool. Each pump's suction line, which is protected by a strainer, is located at an elevation four feet below the normal spent fuel pool water level, while the return line contains an anti-siphon hole near the surface of the water to prevent gravity drainage of the pool. While the heat removal operation is in process, a portion of the spent fuel pool water may be diverted through a demineralizer and a filter to maintain spent fuel pool water clarity and purity. This purification loop is sufficient for removing fission products and other contaminants which may be introduced if a fuel assembly with defective cladding is transferred to the spent fuel pool. The spent fuel pool demineralizer may be isolated, by manual valves, from the heat removal portion of the SFPCCS. By this means, the isolated demineralizer may be used in conjunction with a refueling water purification pump and filter to clean and purify the refueling water while spent fuel pool heat removal operations proceed. Connections are provided such that the refueling water may be pumped from either the RWST or the refueling cavity of either unit, through the demineralizer and filter, and discharged to the refueling cavity or RWST of either unit. Connections are also provided to allow cleanup of the water in the transfer canals. Water can be drawn from the canal, and is pumped by a refueling water purification pump through the spent fuel pool demineralizer and a refueling water purification filter before being returned to the transfer canal. To further assist in maintaining spent fuel pool water clarity, the water surface is cleaned by a skimmer loop. Water is removed from the surface by the skimmers, pumped through a strainer and filter, and returned to the pool surface at three locations remote from the skimmers. The spent fuel pool is filled with water that is at least 2000 ppm. Borated water may be supplied from the RWST via the refueling water purification pump connection, or by running a temporary line from the boric acid blender, located in the chemical and volume control system directly into the pool. Demineralized water can also be added for makeup purposes (i.e., to replace evaporative losses) through a connection in the recirculation return line. 9.1-7

WBN The spent fuel pool water may be separated from the water in the transfer canal by a gate. The gate is installed so that the transfer canal may be drained to allow maintenance of the fuel transfer equipment. The water in the transfer canal is pumped via a refueling water purification pump (RWPP) to a RWST. The transfer canal will be refilled from the RWST by the RWPP when the maintenance is complete. An alternate method when the transfer canal water is outside the chemistry limit for use in the RWST is to pump the transfer canal water to the chemical and volume control system (CVCS) holdup tank via the RWPP. The water will be pumped back to the transfer canal via the CVCS holdup tank recirculation pumps. A description of the operation of the SFPCCS during flood mode operation is given in Section 2.4.14. 9.1.3.2.1 Component Description Spent fuel pool cooling and cleanup system codes and classifications are given in Section 3.2. Equipment operating parameters are given in Table 9.1-2. System design parameters are given in Table 9.1-1. Spent Fuel Pool Pumps The two pumps are horizontal, centrifugal units. They circulate spent fuel pool water through the heat exchangers, demineralizer, and filter. The pumps are controlled manually from a local station. A third pump is installed to serve as a backup to either of the two pumps normally used for cooling the spent fuel pool water (refer to Section 2.4.14 and Section 9.1.3.3.1). Spent Fuel Pool Skimmer Pump This horizontal, centrifugal pump circulates surface water through a strainer and a filter and returns it to the pool. Refueling Water Purification Pumps These horizontal, centrifugal pumps are used to circulate water from the transfer canal, the refueling cavity and the RWST through the spent fuel pool demineralizer, and a refueling water purification filter. The pumps are operated manually from a local station. 9.1-8

WBN Spent Fuel Pool Heat Exchangers The spent fuel pool heat exchangers are of the shell and U-tube type with the tubes welded to the tube sheet. Component cooling water circulates through the shell, and spent fuel pool water circulates through the tubes. Spent Fuel Pool Demineralizer This flushable, mixed-bed demineralizer is designed to provide adequate fuel pool water purity for unrestricted access by plant personnel to the pool working area, and to maintain water visual clarity. Spent Fuel Pool Filter The spent fuel pool filter is designed to improve the pool water clarity by removing particles which obscure visibility. Spent Fuel Pool Skimmer Filter The spent fuel pool skimmer filter is used to remove particles which are not removed by the strainer. Refueling Water Purification Filters The refueling water purification filters are designed to improve the clarity of the refueling water in the refueling canal or in the RWST by removing particles which obscure visibility. Spent Fuel Pool Strainer A strainer is located in each spent-fuel pool pump suction line for removal of relatively large particles which might otherwise clog the spent fuel pool demineralizer or damage the spent fuel pool pumps. Spent Fuel Pool Skimmer Strainer The spent fuel pool skimmer strainer is designed to remove debris from the skimmer process stream. Spent Fuel Pool Skimmers Two spent fuel pool skimmers are provided to remove water from the spent fuel pool water surface in order to remove floating debris. 9.1-9

WBN Valves Manual stop valves are used to isolate equipment, and manual throttle valves provide flow control. Valves in contact with spent fuel pool water are of austenitic stainless steel or equivalent corrosion resistant material. Piping All piping in contact with spent fuel pool water is austenitic stainless steel. The piping is welded except where flanged connections are used to facilitate maintenance and access to shadowed fuel storage cells. 9.1.3.3 Safety Evaluation 9.1.3.3.1 Availability and Reliability The SFPCCS is located in a Seismic Category I structure that is tornado missile protected. Active components of the cooling portion of the system are located above the design basis flood level in the Auxiliary Building (Section 2.4.14). The SFPCCS heat removal equipment is designed to remain functional for the design basis earthquake and within the required stress limits for the operational basis earthquake. Electrical power is supplied from emergency power buses to each of the spent fuel pool pumps. Each pump is connected to these emergency power buses so that it receives power from a separate diesel generator set should offsite power be lost. The use of emergency power buses assures the operation of these pumps for open reactor cooling during plant flooding conditions. This manually controlled system may be shut down for limited periods of time for maintenance or replacement of malfunctioning components. The pool is sufficiently large that an extended period of time would be required for the water to heat up appreciably if cooling were interrupted (see Table 9.1-1). In the event of a failure of one spent fuel pool pump, the backup pump would be aligned and operated. In the event of loss of cooling to one spent fuel pool heat exchanger, cooling of the spent fuel pool water could be maintained by the remaining equipment; however, the reduced heat removal capacity would result in elevation of the spent fuel pool water equilibrium temperature to a higher, but acceptable, temperature. In the event that cooling capability were lost for an extended period, the pool water temperature would approach boiling. At the maximum decay heat production rate, the water loss by vaporization would be about 102 gpm. A seismically qualified line is available from the common discharge of the refueling water purification pumps to the spent fuel pool cooling loop. All piping, valves, and pumps from the RWST to the common discharge of the refueling water purification pumps are seismically qualified. Other sources for makeup available are the demineralized water system and the fire protection system. A sufficient portion of the fire protection system is a Seismic Class I system. Fire hose stations located on seismic and non-seismic piping in the fire protection system are capable of supplying a sufficient quantity of makeup water. 9.1-10

WBN 9.1.3.3.2 Spent Fuel Pool Dewatering The most serious failure of this system would be complete loss of water in the storage pool. To protect against this possibility, the spent fuel pool cooling suction connections enter near the normal water level such that it cannot be lowered appreciably by siphoning. The cooling water return line contains an anti-siphon hole to prevent draining of the pool. These design features assure that the pool cannot be drained below four feet of normal water level (normal water level in the spent fuel pool is approximately 26 feet above the top of the stored spent fuel). The transfer canal has a drain connection in the bottom of the canal. The line runs upward, embedded in concrete, to a level about 13 feet below the normal pool surface. The line continues embedded, dropping below the bottom of the transfer canal. At the high point of the drain line, a siphon breaker line connects into the drain line, terminating in the canal above the normal pool surface. A valve in this line is locked open at all times except when the canal is to be drained. The transfer canal is isolated from the spent fuel pool with a sectionalizing gate during "Transfer Canal Dewatering", (draining operation). With this arrangement, if the transfer canal drain line ruptures, the pool level will not be affected. If the transfer canal drain line ruptures with the syphon valve open and the sectionalizing gate open, 13 feet of water will be above the fuel assemblies in the storage racks. 9.1.3.3.3 Pool and Fuel Temperatures The cooling of the spent fuel assemblies stored within the storage racks has been analyzed for effective and adequate cooling under all postulated pool storage conditions. Two discharge scenarios have been evaluated for both single and dual SFP cooling train operation. Case one considers a full core discharge while a second case considers a full core discharge following a normal refueling. Each case considers the accumulated decay heat of all previously discharged spent nuclear fuel assemblies stored in the SFP. Maximum bulk water temperatures for each core off load scenario are given in Table 9.1-1. Following unit shutdown, a decay time of approximately 33 days prior to the completion of core offload is required to maintain the total SFP decay heat below 28.1E+06 BTU/hr design basis limit. For full core offload following a normal refueling outage (Emergency Offload), it is assumed that a unit is required to shutdown 36 days after a refueling outage on the opposite unit. Following shutdown, it is assumed that core offload will be completed after a 60 day decay time. Under these conditions, the maximum SFP decay heat will be less than 25.61E+06 BTU/hr, which is less than the normal refueling case. Specific guidance in the form of allowable spent fuel pool decay heat curves for better than design conditions of spent fuel pool heat exchanger fouling and shell side cooling temperatures has been developed. Decay heat curves are provided which allow outage specific variation in maximum spent fuel pool decay heat load based on known values of spent fuel pool heat exchanger fouling factors and component cooling system temperatures. Sufficient spent fuel pool cooling equipment is operated and the rate of fuel transfer is controlled to assure that the spent fuel pool temperature does not exceed 150°F during anticipated refueling activities. Operating procedures provide the controls to ensure these limitations are met. A decay heat calculation is routinely performed at the end of each operating cycle to produce heat decay vs time curves for the core and spent fuel pool. This calculation may be used to determine the time to begin core off load and the rate at which the core can be off loaded. 9.1-11

WBN The maximum local water temperature and maximum local fuel temperature have been determined to evaluate the possibility of nucleate boiling on the surface of the fuel assemblies. Analysis has shown that for any scenario with at least one SFPCCS train available, localized boiling does not occur within the fuel racks. The decay heat flux of the rods is greatest at the fuel mid-height. Mid height fuel cladding temperatures of 208.2°F, 217.1°F, and 208.9°F have been calculated based on no blockage, partial blockage, and off-center placement of an assembly in a rack cell respectively. Local maximum water temperatures of 193.7°F, 204.1°F, and 195.2°F have been calculated for the no blockage, partial blockage, and off-center placement cases respectively. The local saturation temperature at the top of the racks (240.7°F) is greater than any calculated local water temperature, which precludes the possibility of nucleate boiling. Additionally, the local saturation temperature is greater than any calculated fuel cladding temperature, which would preclude the possibility of film boiling at the surface of the fuel rods. The approach to localized boiling within the racks has been evaluated for highest allowable spent fuel decay heat load (50.21 Mbtu/hr) in Reference [1]. The conclusions of the evaluation indicate that greater than 6°F margin to localized boiling exist between the maximum calculated fuel clad temperature and the local saturation temperature even at the highest allowable heat load. The total volume of water contained in the pool and cask pit area at the start of a loss of cooling scenario is 372,460 gallons. The expected water heat-up rates for a total loss of cooling capability accident for both a full core discharge and a full core discharge following a normal refueling are listed in Table 9.1-1. 9.1.3.3.4 Water Quality Except for operation of this system in the flood mode of reactor cooling, only a very small amount of water is interchanged between the refueling canal and the spent fuel pool as fuel assemblies are transferred in the refueling process. Whenever a fuel assembly with defective cladding is transferred to the spent fuel pool, a small quantity of fission products may enter the spent fuel cooling water. The purification loop provided removes fission products and other contaminants from the water. Radioactivity concentrations in the spent fuel pool water are maintained at a level such that the dose rate at the surface of the pool is low enough to allow minimum-restricted access for plant personnel (refer to Section 12.3.2.2). 9.1-12

WBN With the use of high purity water, it is expected that the racks and pool walls will not see any significant crud buildup. 9.1.3.3.5 Leakage Detection for the Spent Fuel Pool Leakage detection is provided for the spent fuel pool (SFP) by leakage channels located on the back side of each welded joint of the floor and walls of the SFP steel liner. Leakage into these channels will drain to the perimeter leakage channels located at the bottom of the SFP. The leakage will then flow into the SFP drain pipe to a normally open manual gate valve. Visual detection of the leakage from the SFP may be witnessed as the leakage exits the manual valve and drips into a funnel. The leakage is then routed to the tritiated drain collector tank (TDCT) of the waste disposal system. In the event of excessive leakage, the manual gate valve may be closed to prevent further leakage. Similar type design of leakage channels and visual display of leakage are also provided for the fuel transfer canal and the cask loading area. Non qualified instrumentation are provided in the SFP and the TDCT with MCR low and local high level alarms, respectively. 9.1.3.4 Tests and Inspections Active components of the SFPCCS are either in continuous or intermittent use during normal plant operation. Periodic visual inspection and preventive maintenance are conducted using normal industry practice. 9.1.3.5 Instrument Application The instrumentation for the SFPCCS is discussed below. Alarms and indicators are provided as noted. 9.1.3.5.1 Temperature Instrumentation is provided to measure the temperature of the water in the spent fuel pool and give local indication as well as annunciation in the control room when normal temperatures are exceeded. Instrumentation is also provided to give local indication of the temperature of the spent fuel pool water as it leaves the heat exchangers. 9.1.3.5.2 Pressure Instrumentation is provided to give local indication of the pressure at points upstream and downstream of each pump and filter. 9.1-13

WBN 9.1.3.5.3 Flow Instrumentation is provided to give local indication of the flow leaving the spent fuel pool filter and in the main cooling loops. 9.1.3.5.4 Level Instrumentation is provided which gives an alarm in the control room when the water level in the spent fuel pool reaches either the high or low level condition. 9.1.4 Fuel Handling System 9.1.4.1 Design Bases The fuel handling system (FHS) consists of equipment and structures utilized for safely implementing refueling operation in accordance with requirements of General Design Criteria 61 and 62 of 10 CFR 50, Appendix A. The following design bases apply to the FHS.

1. Fuel handling devices have provisions to avoid dropping or jamming of fuel assemblies during transfer operation.

2. Handling equipment has provisions to avoid dropping of fuel handling devices during the fuel transfer operation.

3. Handling equipment used to raise and lower spent fuel has a limited maximum lift height so that the minimum required depth of water shielding is maintained. See New Fuel Elevator description for use with spent fuel.

4. The Fuel Transfer System (FTS), where it penetrates the containment, has provisions to preserve the integrity of the containment pressure boundary.

5. Criticality during fuel handling operations is prevented by geometrically safe configuration of the fuel handling equipment.

6. Handling equipment will not fail in such a manner as to damage Seismic Category I equipment in the event of a safe shutdown earthquake.

7. The inertial loads imparted to the fuel assemblies or core components during handling operations are less than the loads which could cause damage.

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8. Physical safety features are provided for personnel operating handling equipment.

9.1.4.2 System Description The FHS consists of the equipment needed for the refueling operation on the reactor core. Basically this equipment is comprised of the reactor component hoisting equipment, fuel handling equipment and the FTS. The structures associated with the fuel handling equipment are the refueling cavity, the refueling canal, the transfer canal, the spent fuel storage pit, the cask loading area and the new fuel storage vault. New fuel assemblies are received one or two per shipping container and moved one assembly at a time using the Auxiliary Building crane. The assemblies are temporarily stored in either the new fuel vault for dry storage or in the spent fuel pool as a staging area for the next refueling. When storage in the spent fuel pool is desired, assemblies are placed into the new fuel elevator and lowered into the transfer canal where normal spent fuel handling equipment is used to complete the movement into its storage location. New assemblies may be transferred directly from the shipping container or from the new fuel vault into the reactor core or spent fuel pool via the new fuel elevator and normal spent fuel handling equipment. The fuel handling equipment is designed to handle the spent fuel under water from the time it leaves the reactor vessel until it is placed in a container for shipment from the site or the spent fuel assemblies may be placed in interim storage at WBN Independent Spent Fuel Storage Installation (ISFSI) (Section 9.1.6). Underwater transfer of spent fuel provides an effective, economic and transparent radiation shield, as well as a reliable cooling medium for removal of decay heat. The boric acid concentration in the water is sufficient to preclude criticality. The associated fuel handling structures may be generally divided into three areas: the refueling cavity and refueling canal which are flooded only during plant shutdown for refueling, the spent fuel storage area which is kept full of water and is always accessible to operating personnel, and the new fuel storage vault which is separate and protected for dry storage. The refueling canal and the transfer canal are connected by a fuel transfer tube. This tube is fitted with a blind flange on the refueling canal end and a gate valve on the transfer canal end. The blind flange is in place except during refueling to ensure containment integrity. Fuel is carried through the tube on an underwater transfer car. Fuel is moved between the reactor vessel and the refueling canal by the refueling machine. A rod cluster control changing fixture is located on the refueling canal wall and may be used for transferring control elements from one fuel assembly to another. The rod cluster control assembly (RCCA) change tool is used from the spent fuel pool bridge crane to transfer control elements from one assembly to another in the spent fuel pool. 9.1-15

WBN-1 The lifting arm at either end of the fuel transfer tube is used to pivot a fuel assembly. Before entering the transfer tube the lifting arm pivots a fuel assembly to the horizontal position for passage through the transfer tube. After the transfer car transports the fuel assembly through the transfer tube, the lifting arm at that end of the tube pivots the assembly to a vertical position so that it can be lifted out of the upender frame. In the spent fuel storage area, spent fuel assemblies are moved about by the spent fuel pit bridge hoist. When lifting spent fuel assemblies, the hoist uses a long-handled tool to assure that sufficient radiation shielding is maintained. A shorter tool is used to handle new fuel assemblies with the Auxiliary Building crane, but the new fuel elevator must be used to lower the assembly to a depth at which the spent fuel pit bridge crane using the long-handled tool, can place the new fuel assembly into the upending device. The new fuel elevator may be used to raise or lower an irradiated fuel assembly to facilitate maintenance activities under administrative controls that ensure sufficient radiation shielding is maintained. Decay heat, generated by the spent fuel assemblies in the spent fuel pit, is removed by the spent fuel pool cooling system. After a sufficient decay period, the fuel may be removed from the racks and loaded into a shipping ask for removal from the site or the spent fuel assemblies may be placed in interim storage at the WBN Independent Spent Fuel Storage Installation (ISFSI) (Section 9.1.6). 9.1.4.2.1 Refueling Procedure The refueling operation follows a detailed procedure which provides a safe, efficient refueling operation. Reactor core alterations or handling of irradiated fuel are suspended during a tornado warning. Prior to initiating refueling operations the reactor coolant system is borated and cooled down to refueling shutdown conditions as specified in the Technical Specifications. Criticality protection for refueling operations, including a requirement for periodic checks of boron concentration, is specified in the Technical Specifications. The following significant points are assured by the refueling procedure:

1. The refueling water and the reactor coolant contain the required concentration of boron.

This concentration is sufficient to keep the core reactivity of keff 0.95 during the refueling operations with all control rods inserted except the most reactive rod.

2. The water level in the refueling cavity is high enough to keep the radiation levels within acceptable limits when the fuel assemblies are being removed from the core.

The refueling operation is divided into four major phases. A general description of a typical refueling operation through the four phases is given below: 9.1-16

WBN

1. Phase I - Preparation The reactor is shut down and cooled to refueling conditions with a final keff < 0.95 (all rods in except the most reactive rod). At this time, the coolant level in the reactor vessel is lowered to a point slightly below the vessel flange. Then the fuel transfer equipment is checked for proper operation. The refueling machine is checked for proper operation prior to or during Phase I.

2. Phase II - Reactor Disassembly Missile shields are removed from around the reactor head, allowing all piping, supports, cables, air ducts, and insulation to be removed from the vessel head. The refueling cavity is then prepared for flooding by sealing off the reactor cavity, checking of the underwater lights, tools, and FTS, closing the refueling canal drain holes, and removing the blind flange from the fuel transfer tube. After the reactor vessel head has been detensioned, the vessel head is unseated and raised above the vessel flange. Water from the RWST is pumped into the reactor coolant system by the residual heat removal pumps. During reactor pressure vessel (RPV) head removal and lift, radiation levels are monitored and direct inspections are performed to detect potential rod cluster control assembly (RCCA) withdrawal. This inspection may be performed by monitoring the source range instrumentation for any unusual unexpected change during RPV head removal. The RPV head is raised to clear obstructions, and moved to the storage stand.

The reactor cavity water level is raised to just above the vessel flange, leak inspections are initiated and the level is increased to cover the upper internals guide tubes. The cavity water level is raised to the normal refueling level. The control rod drive shafts are disconnected and, with the upper internals, are removed from the vessel. The fuel is now free from obstructions and the core is ready for refueling.

3. Phase III - Fuel Handling The general fuel handling sequence for a full core off load is:

a. The refueling machine is placed over the first assembly to be removed.

b. The fuel assembly is lifted and moved into the upender.

c. The upender is then pivoted to the horizontal position by the lifting arm.

d. The fuel is moved through the fuel transfer tube to the transfer canal area by the transfer car.

9.1-17

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e. The fuel assembly is pivoted to the vertical position by the lifting arm. The fuel assembly is lifted and moved by the spent fuel handling tool attached to the spent fuel pit bridge crane.

f. The fuel assembly is then placed into a spent fuel rack storage cell.

g. This sequence is repeated until all 193 fuel assemblies are removed from the core and placed into the spent fuel pit.

h. Fuel related components are then shuffled/removed from assemblies and placed into their proper locations. After fuel related components shuffles are completed, the fuel is loaded back into the core in the prescribed sequence by reversing the above steps.

4. Phase IV - Dry Cask Storage Operations Dry cask storage operations are provided in WBN Independent Spent Fuel Storage Installation (ISFSI) (Section 9.1.6).

9.1-18

WBN 9.1.4.2.2 Component Description Refueling Machine The refueling machine (Figure 9.1-6) is a rectilinear bridge and trolley crane with a vertical mast extending down into the refueling water. The bridge spans the refueling cavity and runs on rails set into the edge of the refueling cavity. The bridge and trolley motions are used to position the vertical mast over a fuel assembly. A long tube with a pneumatic gripper on the end is lowered down out of the mast to grip the fuel assembly. The gripper tube is long enough so that the upper end is still contained in the mast when the gripper end contacts the fuel. A winch mounted on the trolley raises the gripper tube and fuel assembly up into the mast tube. The fuel is transported while inside the mast tube to its new position. The refueling machine uses three AC servo motors to control bridge, trolley, and hoist motions. Boundaries, interlocks, and speeds are controlled by an industrial programmable logic controller. All major controls for the refueling machine are mounted in a console on the trolley. The bridge and trolley are positioned in relation to a grid pattern referenced to the core by a series of redundant digital encoder systems. The drives for the bridge, trolley and hoist are variable speed. The maximum speed for the bridge is approximately 60 fpm and the maximum speed for the trolley is approximately 40 fpm. The maximum speed for the hoist is approximately 40 fpm. The refueling machine has two auxiliary monorail hoists, one on each side of the bridge upper structure. 9.1-19

WBN Electrical interlocks and limit switches on the bridge and trolley drives prevent damage to the fuel assemblies. The hoist is also provided with redundant limit switches to prevent a fuel assembly from being raised above a safe shielding depth should the limit switch fail. In an emergency, the bridge, trolley, and hoist can be operated manually using a handwheel on the motor shaft to return the system to a safe configuration.. Portable underwater cameras are used, as required, during refueling operations and can permit viewing of all fuel assembly positions. Spent Fuel Pit Bridge Crane The spent fuel pit bridge crane (Figure 9.1-7) is a steel-mounted walkway spanning the spent fuel pit, which carries an electric monorail hoist on an overhead structure. The spent fuel pit bridge crane is used exclusively for handling fuel assemblies within the spent fuel pit and transfer canal by means of a long-handled tool suspended from the hoist. The hoist travel and tool length are designed to limit the maximum lift of a fuel assembly to a safe shielding depth. The spent fuel bridge crane has two step magnetic controllers for the bridge and hoist. The bridge speeds are 11 and 33 fpm and the hoist speeds are 7 and 20 fpm. A hydraulic coupling is used in the bridge drive to limit starting acceleration. The hoist pendent control is equipped with a load sensing device to indicate an overload in the up direction or an underload in the down direction to prevent damage to the fuel elements. The hoist trolley is hand operated by a chain drive. New Fuel Elevator The new fuel elevator (Figure 9.1-8) consists of a box-shaped elevator assembly with its top end open and sized to house one fuel assembly. The new fuel elevator is used primarily to lower a new fuel assembly to the bottom of the fuel transfer canal where it is transported to the fuel transfer system by the spent fuel pit bridge hoist. The new fuel elevator may also be used to raise and lower an irradiated fuel assembly to facilitate maintenance activities. Prior to placing an irradiated fuel assembly in the elevator, safety precautions will be implemented to limit the maximum lift of the fuel assembly to a safe shielding depth. Fuel Transfer System The fuel transfer system (Figure 9.1-9) includes a cable-driven transfer car that runs on tracks extending from the reactor cavity through the transfer tube into the transfer canal. At each end of the transfer tube are lifting arms. The upender in the refueling cavity receives a fuel assembly in the vertical position from the refueling machine. 9.1-20

WBN The fuel assembly is then pivoted to a horizontal position with the lifting arm for passage through the transfer tube. The transfer car is positively connected to the drive train in the transfer canal. After passing through the tube, the fuel assembly is pivoted to a vertical position for removal to the spent fuel pit storage location via the spent fuel pit bridge crane. During reactor operation, the transfer car is stored in the transfer canal. A blind flange is bolted on the refueling canal end of the transfer tube to seal the reactor containment. The terminus of the tube in the transfer canal is closed by a gate valve. Rod Cluster Control (RCC) Changing Fixture The RCC changing fixture is supplied for periodic RCC element inspections and for transfer of RCC elements from one fuel assembly to another in the event this operation is ever required (Figure 9.1-10). The major subassemblies which comprise the changing fixture are the frame and track structure, the carriage, the guide tube, the gripper, and the drive mechanism. The carriage is a moveable container supported by the frame and track structure. The tracks provide a guide for the four flanged carriage wheels and allows horizontal movement of the carriage during changing operation. The positioning stops on both the carriage and frame locate each of the three carriage compartments directly below the guide tube. Two of these compartments are designed to hold individual fuel assemblies while the third is made to support a single rod cluster control element. Situated above the carriage and mounted on the refueling canal wall is the guide tube. The guide tube provides for the guidance and proper orientation of the gripper and rod cluster control element as they are being raised and lowered. The gripper is a pneumatically actuated mechanism responsible for engaging the rod cluster control element. It has two flexure fingers which can be inserted into the top of the rod cluster control element when air pressure is applied to the gripper piston. Normally the fingers are locked in a radially extended position. Mounted on the operating deck is the drive mechanism assembly which consists of the manual carriage drive mechanism, the operating handle, the pneumatic selector valve for actuating the gripper piston, and the electric hoist for elevation control of the gripper. Spent Fuel Assembly Handling Tool The spent fuel assembly handling tool (Figure 9.1-11) is used to handle new and spent fuel assemblies in the spent fuel pit. It is a manually actuated tool, suspended from the spent fuel pit bridge crane, which uses four cam actuated latching fingers to grip the underside of the fuel assembly top nozzle. The operating handle to actuate the fingers is located at the top of the tool. When the fingers are latched, a pin is inserted into the operating handle which prevents the fingers from being accidentally unlatched during fuel handling operations. 9.1-21

WBN New Fuel Assembly Handling Tool The new fuel assembly handling tool (Figure 9.1-12) is used to lift and transfer fuel assemblies between the new fuel shipping containers, the new fuel storage racks, and/or the new fuel elevator. It is a manually actuated tool suspended from the Auxiliary Building crane which uses four cam actuated latching fingers to grip the underside of the fuel assembly top nozzle. The operating handles to actuate the fingers are located on the side of tool. When the fingers are latched, the safety screw is turned in to prevent the accidental unlatching of the fingers. Reactor Vessel Head Lifting Device The reactor vessel head lifting device consists of a welded and bolted structural steel frame with suitable rigging to enable lifting and storing the head during refueling operations. The lifting device is permanently attached to the reactor vessel head. Reactor Internals Lifting Device The reactor internals lifting device (Figure 9.1-13) is a structural steel frame. The frame is lowered onto the guide tube support plate of the internals, and is mechanically connected to the support plate by three bolts. Bushings on the frame engage guide studs in the vessel flange to provide guidance during removal and replacement of the internals package. Reactor Vessel Stud Tensioner The stud tensioners (Figure 9.1-14) are employed to secure the head closure joint at every refueling. The stud tensioner is a hydraulically operated device that uses oil as the working fluid. The device permits preloading and unloading of the reactor vessel closure studs at cold shutdown conditions. Stud tensioners minimize the time required for stud tensioning and detensioning operations. Three tensioners are provided and are applied simultaneously to three studs located 120 degrees apart. A single hydraulic pumping unit operates the tensioners, which are hydraulically connected. The studs are tensioned to their operational load in two steps to prevent high stresses in the flange region and unequal loadings in the studs. Relief valves on each tensioner prevent overtensioning of the studs due to excessive pressure. 9.1-22

WBN 9.1.4.3 Design Evaluation 9.1.4.3.1 Safe Handling Design Criteria for the Refueling Machine

1. The primary design objective of the refueling machine is reliability. A conservative design approach is used for all load bearing parts. Throughout the design consideration is given to the fact that the machine spends long idle periods stored in an atmosphere of 80°F and high humidity. In general, the crane structure is considered in the Class AI, Standby Service, as defined by the Crane Manufacturers Association of American Specification No. 70.

2. Seismic design considerations are discussed in Section 9.1.4.3.2.

3. All components critical to the operation of the crane and parts which could fall into the reactor are positively restrained from loosening. Fasteners above water that cannot be lockwired or tack welded are coated with locking compound.

Industrial codes and standards used in the design of the fuel handling equipment are:

1. Refueling machine and fuel handling machine: Applicable sections of Crane Manufacturer Association of America Specification No. 70.

2. Structural: AISC, Part 5, 7th Edition

3. Electrical: Applicable standards and requirements of the IEEE Standard 279, National Electric Code, NFPA#70, and NEMA Standard MG 1 and shall be used in the design of all electrical equipment.

4. Materials: Materials conform to the specifications of the ASTM standard.

5. Safety: OSHA Standards 29 CFR 1910 and 29 CFR 1926, including load testing requirements, the requirements of Regulatory Guide 1.29, and General Design Criteria 61 and 62.

Refueling Machine The refueling machine design includes the following provisions to ensure safe handling of fuel assemblies: 9.1-23

WBN

1. Electrical Interlocks

a. Bridge, Trolley and Hoist Drive Interlocks Bridge, along with the trolley drives are interlocked with the hoist, using redundant interlocks to prevent simultaneous operation of the hoist with the bridge and/or trolley.

b. Bridge Trolley Drive - Gripper Tube Up Bridge and trolley drive operation is prevented except when the gripper tube up position switches are actuated or during indexing operations. The interlock is redundant.

c. Gripper Interlock An interlock is supplied which prevents the opening of a solenoid valve in the air line to the gripper except when zero suspended weight is indicated by a force gage. As backup protection for this interlock, the mechanical weight actuated lock in the gripper, prevents operation of the gripper under load even if air pressure is applied to the operating cylinder. This interlock is redundant.

d. Excessive Suspended Weight Two redundant excessive suspended weight switches open the hoist drive circuit in the up direction when the loading is excessive based on the vendor recommendations. The interlock is redundant.

The hoist is also provided with a low-load safety circuit, which prevents down-travel of the hoist if the load cell weight is sufficiently reduced. This minimizes the possibility of fuel assembly damage if one fuel assembly were to be lowered on top of another fuel assembly. The low load safety circuit setpoint is established using vendor recommendations.

e. Hoist-Gripper Position Interlock An interlock in the hoist drive circuit in the up direction permits the hoist to be operated only when either the open or closed indicating switch on the gripper is actuated. The hoist-gripper position interlock consists of two separate circuits that work in parallel so that one circuit must be closed for the hoist to operate. If one or both interlocking circuits fail in the closed position, an audible and visual alarm on the console is actuated.

9.1-24

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2. Bridge and Trolley Hold-Down Devices Both refueling machine bridge and trolley are horizontally restrained on the rails by two pairs of guide rollers, one pair at each wheel location on one truck only. The rollers are attached to the bridge truck and contact the vertical faces on either side of the rail to prevent horizontal movement. Vertical restraint is accomplished by anti-rotation bars located at each of the four wheels for both the bridge and trolley. The anti-rotation bars are bolted to the trucks and, for the bridge restraints, extended under the rail flange, while the trolley restraints extend beneath the top flange of the bridge girder which supports the trolley rail. Both horizontal and vertical restraints are adequately designed to withstand the forces and overturning moments resulting from the Safe Shutdown Earthquake.

3. Design Load The structure which supports the fuel assembly is designed for a static load of 5500 pounds. The refueling machine hoist has a manufacturer's rated capacity of 4000 pounds but is capable of supporting a static load of 5000 pounds with a safety factor of 5.0, and has been evaluated to be capable of a 5500 lb. static load in an emergency.

Under normal conditions, the working load of the hoist is 2500 pounds (the weight of a fuel assembly, approximately 1600 pounds, plus gripper tube which weighs less than 1000 pounds). During normal hoist operation, the overload setpoint limits the hoist load to a value well below the rated capacity of the hoist. This value is based on vendor recommendations. The maximum allowable emergency pullout load (total maximum load which can be applied using the handwheel without danger of over stressing the hoist and supporting structure) is 5500 pounds. The 5500 pound load is a static load to be applied with the handwheel only, and only under emergency conditions. A load sensing device allows the load to be measured, so the operator knows the load being imposed on the hoist when using the handwheel.

4. Main Hoist Braking System The main hoist is equipped with two independent braking systems. A solenoid release, spring-set electric brake is mounted on the motor shaft. This brake operates in the normal manner to release upon application of current to the motor and set when current is interrupted. The second brake is a mechanically actuated load brake internal to the hoist gear box that sets if the load starts to overhaul the hoist. It is necessary to apply torque from the motor to raise or lower the load. In raising, this motor cams to brake open; in lowering, the motor slips the brake allowing the load to lower. This brake actuates upon loss of torque from the motor for any reason and is not dependent on any electrical circuits. The motor brake capacity is 100% of the rated hoist capacity of 4000 pounds. The mechanical brake has a capacity of 150% of the rated hoist capacity.

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5. Fuel Assembly Support System The main hoist system is supplied with redundant paths of load support such that failure of any one component will not result in free fall of the fuel assembly. Two wire ropes are anchored to the winch drum and carried over independent sheaves to a load equalizing mechanism on the top of the gripper tube. In addition, supports for the sheaves and equalizing mechanism are backed up by passive restraints to pick up the load in the event of failure of this primary support. Each wire rope has a load rating 5 times the design load.

The gripper mechanism contains a spring actuated mechanical lock which prevents the gripper from opening unless the gripper is under a compressive load. The gripper and hoist systems are routinely load tested to the requirements listed in the plant Technical Requirements Manual. Fuel Transfer System The following safety features are provided for in the fuel transfer system.

1. Transfer Car Permissive Switch The primary transfer car controls are located on the operating floor and some conditions in the containment may, therefore, not be visible to the operator. The transfer car controls include an e-stop function on the containment side transfer control console allowing a second operator in the containment to exercise some control over car movement if conditions visible to him warrant such control. Transfer car operation is possible only when both lifting arms are in the down position as indicated by the underwater proximity switches. A second set of underwater proximity switches monitor the full up position of each of the upenders. Control logic provides a second permissive condition as a backup for the transfer car lifting arm interlock. Assuming the upender is in the upright position in the containment and the lifting arm interlock circuit fails in the permissive condition, the operator on the operating floor still cannot operate the car because the logic prevents car motion if either upender is indicated as being full up, or if either upender is indicated as being in motion.

2. Lifting Arm - Transfer Car Position Lifting arm operation is permitted only when the transfer car is at the respective end of its travel. Transfer car position indication, limit sensing, and braking controls are displayed on the control panel. The backup lifting arm interlock, a mechanical latch device which is opened by the weight of the fuel container when in the horizontal position, has been abandoned.

9.1-26

WBN

3. Transfer Car - Valve Open Interlocks on the transfer tube valve permit transfer car operation only when the transfer tube valve position switch indicates the valve is fully open.

4. Transfer Car - Lifting Arm The transfer car lifting arm interlock is primarily designed to protect the equipment from overload and possible damage if an attempt is made to move the car when the upender is not in the horizontal position. The basic interlock is a position limit switch in the control circuit made up from a 150 pound load, cart in position, and cart in zone.

5. Lifting Arm - Refueling Machine The refueling canal lifting arm is interlocked with the refueling machine. Whenever the transfer car is located in the refueling canal, the lifting arm cannot be operated unless the refueling machine mast is in the fully retracted position or the refueling machine is not over the upender.

6. Lifting Arm - Spent Fuel Pit Bridge The transfer canal lifting arm is interlocked with the spent fuel pit bridge position and hoist. The lifting arm cannot be operated when the spent fuel pit bridge is over the lifting arm area and the hoist is not in the full up position or when the spent fuel pit bridge crane is in bypass mode.

Spent Fuel Pit Bridge The spent fuel pit bridge includes the following safety features.

1. The spent fuel pit bridge controls are interlocked to prevent simultaneous operation of bridge drive and hoist.

2. Bridge drive operation is prevented except when the hoist is in the full up position unless in bypass mode which allows bridge slow speed when the hoist is not in the full up position.

3. An overload protection device is included on the load monitor to limit the uplift force.

The overload is set and administratively controlled based on Westinghouse recommendations.

4. Restraining bars are provided on each track to prevent the bridge from overturning.

9.1-27

WBN Fuel Handling Tools and Equipment All fuel handling tools and equipment handled over an open reactor vessel are designed to prevent inadvertent decoupling from machine hooks (i.e., lifting rigs are pinned to the machine hook and safety latches are provided on hooks supporting tools). Tools required for handling internal reactor components are designed with fail safe features that prevent disengagement of the component in the event of operating mechanism malfunction. These safety features apply to all tools which handle or service new or spent fuel or fuel related components. 9.1.4.3.2 Seismic Considerations The safety classifications for all fuel handling and storage equipment are listed in Table 3.2-2. These safety classes provide criteria for the seismic design of the various components. Class 1 and Class 2 equipment is designed to withstand the forces of the OBE and SSE. For normal conditions plus OBE loadings, the resulting stresses are limited to allowable working stresses as defined in the ASME Code, Section III, Appendix XVII, Subarticle XVII-2200 for normal and upset conditions. For normal conditions plus SSE loadings, the stresses are limited to within the allowable values given by Subarticle XVII-2110 for critical parts of the equipment which are required to maintain the capability of the equipment to perform its safety function. Permanent deformation is allowed for the loading combination which includes the SSE to the extent that there is no loss of safety function. The Class 3 fuel handling and storage equipment satisfies the Class 1 and Class 2 criteria given above for the SSE. Consideration is given to the OBE only insofar as failure of the Class 3 equipment might adversely affect Class 1 or 2 equipment. For non-nuclear safety equipment, design for the SSE is considered if failure might adversely affect a Safety Class 1, 2 or 3 component. Design for the OBE is considered if failure of the non-nuclear safety component might adversely affect a Safety Class 1 or 2 component. 9.1.4.3.3 Containment Pressure Boundary Integrity The fuel transfer tube which connects the refueling cavity (inside the reactor containment) and the operating floor (outside the containment) is closed on the refueling cavity side by a blind flange when containment integrity is required, except during refueling operations. Two seals are located around the periphery of the blind flange with leak-check provisions between them. 9.1-28

WBN-1 9.1.4.3.4 Radiation Shielding During all phases of spent fuel transfer, the gamma dose rate at the refueling bridge is 2.5 mr/hr or less. This is accomplished by maintaining a minimum of 9.9 feet of water above the active fuel region which correlates to 8 feet and 10.875 inches above the top of the fuel assembly during all handling operations. The two fuel handling devices used to lift spent fuel assemblies are the refueling machine and the spent fuel pit bridge. The refueling machine contains positive stops which prevent the active fuel region of a fuel assembly from being raised to within a minimum of 9.9 feet of the water level in the refueling cavity. The hoist on the spent fuel pit bridge moves spent fuel assemblies with a long handled tool. Hoist travel and tool length likewise limit the maximum lift of the active fuel region of a fuel assembly to within a minimum of 9.9 feet of the water level in the spent fuel pit and transfer canal. 9.1.4.4 Tests and Inspections As part of normal plant operations, the fuel handling equipment is inspected for operating conditions prior to each refueling and dry cask storage (Reference 9.1.6) operation. During the operational testing of this equipment, procedures are followed that will affirm the correct performance of the fuel handling system interlocks. 9.1.5 Tritium Producing Burnable Absorber Rods (TPBARs) Consolidation Activity (Unit 1 Only) 9.1.5.1 Design Bases Equipment is installed in the Spent Fuel Pit (SFP) cask loading and set-down areas for consolidating up to 300 TPBARs into a consolidation canister. The loaded consolidation canisters will be stored in the existing fuel pool racks to await shipment to the DOE Tritium Extraction Facility. The design basis applicable to the consolidation equipment is to consolidate TPBARs in a manner that ensures existing fuel handling equipment functional and design requirements are met. Functions which support this basis include requirements to meet existing seismic qualification, environmental compatibility, materials compatibility, NUREG-0612, and ALARA. 9.1-29

WBN 9.1.5.2 Facilities Description The consolidation equipment performs its consolidation function in the SFP fuel cask loading pit, and is stored in the SFP cask set-down area below Elevation 757. Control cabinets, camera equipment, cables, etc, which contain combustible materials will be stored in an area that is acceptable from a fire loading standpoint. See UFSAR Figures 9.1-17, 9.1-18 and 9.1-19 respectively for a pictorial Consolidation Plan, Layout and Canister design. The equipment and fixtures that will be submerged in the SFP have been fabricated of stainless steels or non-stainless materials compatible with borated water communicating with the RCS. The roller brake, cables, and rollers are made of materials known to withstand the hot borated water, and expected radiation environment without affecting the function of the plant systems. TPBAR assemblies containing irradiated TPBARs are moved from the SFP to equipment contained in the SFP cask area for consolidation into canisters. Loaded TPBAR canisters will be moved under-water through the opening connecting the SFP cask loading area to designated fuel storage racks in the Spent Fuel Pool for storage. When ready for shipment, canisters containing irradiated TPBARs will be removed from the SFP storage rack, moved underwater to the SFP cask loading area, and loaded into a TPBAR Transport Cask for shipment to the Tritium Extraction Facility. Special fixtures and lifting devices will be used in conjunction with the existing bridge crane to facilitate movement of the loaded TPBAR canisters to and from their designated storage rack. 9.1.5.3 Safety Evaluation a) Design of the consolidation equipment, cabinet and controls, appurtenances, supports, and framing is in accordance with Regulatory Guide 1.13 and 1.29, which ensures adequate safety under normal condition, postulated SSE and OBE, and accidents. b) The equipment and fixtures that will be submerged in the SFP have been fabricated of stainless steels or other materials compatible with the hot, borated water, radiation environment and the stainless SFP liner in communication with RCS. This equipment will not affect operation of the plant, will not adversely affect the function of plant systems, and will have no adverse affect on safe shutdown or the safety of plant personnel or the public. c) The TPBAR handling and consolidation equipment is designed and configured such that minimum water shielding in the Spent Fuel Pool and Cask Loading Pit is maintained to keep dose rates ALARA. Equipment, tools, and design features prevent inadvertently raising the TPBAR assemblies, loaded canisters, or post-consolidation baseplates above safe shielding depths. 9.1-30

WBN-2 d) The existing auxiliary building crane or bridge crane fuel handling equipment will be used, with new handling fixtures/devices as required to move the consolidation fixture and TPBAR canister within normal boundaries; thus ensuring that handling events are bounded by existing fuel handling safety and accident analyses. e) Refer to the LAR for a description of TPBAR consolidation and safety analysis. REFERENCES

1. Holtec Report No. HI-2002607, R0, LOCA Temperature Analysis of the Watts Bar Spent Fuel Pool.

2. LAR TVA-WBN-TS-00-015, Watts Bar Nuclear Plant (WBN) - Unit 1 - Revision of Boron Concentration Limits and Reactor Core Limitations for Tritium Production Cores (TPCs) - Technical Specification (TS) Change No. TVA-WBN-TS-00-015 (T04010821812). (Unit 1 Only) 9.1.6 Independent Spent Fuel Storage Installation (ISFSI) 9.1.6.1 Regulatory Basis Under 10 CFR 72.210, WBN is issued a general license for storage of spent fuel in an Independent Spent Fuel Storage Installation (ISFSI). An ISFSI is a complex that is designed and constructed for interim storage of spent nuclear fuel, solid reactor-related GTCC waste, and other radioactive materials associated with spent fuel and reactor-related GTCC waste storage.

TVA selected HOLTEC Internationals HI-STORM FW storage system for use at WBNs ISFSI to maintain adequate on-site spent fuel storage capacity. Upon NRC approval of the Final Safety Analysis Report (FSAR) for the HI-STORM FW storage system, the NRC issued Certificate of Compliance (CoC) Docket No. 72-1032 and Safety Evaluation Report (SER) Docket No. 72-1032 for use of the HI-STORM FW system. As a General Licensee, WBN is authorized to use the HI-STORM FW storage system in accordance with: NUREG-1536, Standard Review Plan for Dry Cask Storage Systems CoC 72-1032, Containing: o Appendix A: Technical Specifications o Appendix B: Approved Contents and Design Features HOLTEC FSAR for the HI-STORM FW NRC Safety Evaluation Report: HI-STORM FW System 10 CFR 72, as applicable per 10 CFR 72.13 WBN 10 CFR 72.212 Evaluation Report 9.1.6.2 System Description The HI-STORM FW system used at WBN is comprised of stainless steel multi-purpose canister (MPC-37), a transfer cask (HI-TRAC VW), and a HI-STORM metal / concrete overpack. WBN implemented Holtec Internationals HI-STORM FW Version XL overpack during the second ISFSI campaign. The FW Version XL is an alternative to the standard HI-STORM FW cask and features a more effective closure lid to further improve sky shine and vent outlet dose performance. The use of the term HI-STORM FW is considered synonymous with HI-STORM 9.1-31

WBN-2 FW Version XL throughout Chapter 9.1.6. The MPC fuel basket provides criticality control and can hold 37 PWR spent fuel assemblies or radioactive materials associated with spent fuel and reactor-related waste components. The outer shell, top lid, bottom baseplate, closure ring, and associated welds constitute the MPC-37 confinement boundary which precludes radioisotopes leakage into the environment, provides the heat transfer medium from the contents to the environment, and provides an inert environment to prevent corrosion of the stored fuel. The HI-TRAC VW hold the MPC-37 during spent fuel loading, processing, and unloading operations and provides ALARA for personnel in accordance with 10 CFR 20. The HI-TRAC VW is used to transfer the MPC-37 to and from the cask pit pool and the HI-STORM FW overpack for onsite storage in accordance with 10 CFR 72 or to an off-site shipment cask licensed under 10 CFR

71. The MPC-37 is stored inside the HI-STORM FW overpack for protection against extreme natural phenomena, tornado generated missiles, radiological shielding, and allows for the transfer of heat from the stored fuel to the environs. The WBN ISFSI is located within the existing owner controlled area, northwest of the Diesel Generator Building. The ISFSI storage pad (see Figure 2.4-40B sheet 6) is sufficient to store the 80 HI-STORM FW storage systems.

In addition to the storage pad, the ISFSI is surrounded by protected fencing and monitored by various security systems. Confinement of all radioactive materials in the HI-STORM FW system is provided by the MPC. The design of the HI-STORM FW MPC assures that there are no credible design basis events that would result in a radiological release to the environment. The HI-STORM FW overpack and HI-TRAC VW transfer cask are designed to provide physical protection to the MPC during normal, off-normal, and postulated accident conditions to assure that the integrity of the MPC is maintained. The dry inert atmosphere in the MPC and the passive heat removal capabilities of the HI-STORM FW also assure that the SNF assemblies remain protected from long-term degradation. A detailed description of the HI-STORM FW storage system is provided in the HOLTEC HI-STORM FW FSAR (Report HI-2114830). Chapter 7 describes the HI-STORM FW confinement design and describes how the design satisfies the confinement requirements of 10CFR72. It also provides an evaluation of the MPC confinement boundary as it relates to the criteria contained in Interim Staff Guidance (ISG)-18 and applicable portions of ANSI N14.5-1997 as justification for reaching the determination that leakage from the confinement boundary is not credible and, therefore, a quantification of the consequence of leakage from the MPC is not required. This chapter is in general compliance with NUREG-1536. 9.1.6.3 Dry Cask Storage Operations

a. Holtec International HI-TRAC VW transfer cask and multi-purpose canister (MPC) are placed in a cask work area (CWA) on the auxiliary building refueling floor by the auxiliary building overhead crane with a lift yoke attached to the crane hook using site established safe load path.

b. Activities associated with the preparation of the transfer cask such as inspection, placing the MPC into the transfer cask, draining the neutron shield water jacket, partial filling of the MPC with borated water, installation of the inflatable annulus shield, etc. will be performed in the CWA.

c. After the transfer cask preparations are completed, the transfer cask and MPC are moved from the CWA to the cask stand in the shallow end of the cask loading area.

d. To prevent submerging the main hoist crane hook in the deep end of the cask loading area, a lift yoke extension will be installed between the crane hook and the lift yoke.

9.1-32

WBN-2

e. With these lifting devices in place, the transfer cask and MPC are moved from the shallow end of the cask loading area to the deep end cask stand. The cask support stand in the deep end of the cask loading area is ergonomically sized such that the top of the MPC is positioned approximately level with the top of the spent fuel pool fuel racks.

f. Underwater camera and surveillance will be used as needed to ensure placement of the transfer cask, verify lift yoke is engaged or disengaged, verify MPC lid placement, monitor fuel loading, etc.

g. The gate between the cask loading area and the spent fuel pit is not to be installed.

h. Using the spent fuel pit bridge, spent fuel assemblies are transferred from the spent fuel storage racks to the MPC wherein 10 CFR 72 regulation is in effect. After spent fuel assemblies are loaded, the MPC lid is placed on the MPC. Radiation monitoring may be performed prior to transfer cask and MPC breaching the pool surface.

i. Following verification of MPC lid placement, the transfer cask and loaded MPC are placed back on the shallow end shelf and the lift yoke extension removed. Note that the 10 CFR 50 Technical Specification (Reference LCO 3.7.13) requirement of maintaining 23 feet of water shielding no longer applies.

j. The upper portion of the transfer cask and loaded MPC is raised above the SFP water surface. After radiation dose rate measurements confirm that it is safe to continue, a relatively small amount of water is removed from the MPC to facilitate MPC lid welding.

Radiological surveys and preliminary decontamination of the MPC lid and transfer cask are performed as the transfer cask continues to be raised until it has been removed from the SFP. The transfer cask and loaded MPC are placed back in the CWA where the next phase of decontamination of the transfer cask, disengagement of the annulus overpressure system, and MPC closure operation are performed.

k. After the MPC lid is seal welded, the MPC is hydrostatically tested, drained, dried and filled with helium.

l. The transfer cask and MPC are moved to the auxiliary building railroad bay where the MPC is transferred to the HI-STORM FW overpack.

m. The HI-STORM FW overpack is transported to the ISFSI and placed at a designated location.

n. If necessary, unloading operations are performed using similar methodology in reverse.

9.1.6.4 Evaluation of Reactor Power & ISFSI Facilities Interface Documents Analyses used to demonstrate ISFSI compliance to 10 CFR 50 and 10 CFR 72 regulations are listed in Table 9.1-4. These analyses address SSCs that are shared or utilized to facilitate WBN 10 CFR 50 and 10 CFR 72 facilities. This section is not intended to be all inclusive of design features between the two facilities however, this listing provides examples of SSCs having design basis requirements in both the 10 CFR 50 and 10 CFR 72 regulations. The applicability of these regulations also includes the associated drawings and procedures of the commonly shared SSCs. Therefore, implementing a change, test, or experiment for these shared SSCs shall require a 10 CFR 50.59 review and a 10 CFR 72.48 review. This position demonstrates compliance with 10 CFR 50 Appendix A, GDC-5 and 10 CFR 72.122 paragraphs (d), (e), and (k) (4). 9.1-33

WBN TABLE 9.1-1 SPENT FUEL POOL COOLING AND CLEANUP SYSTEM DESIGN PARAMETERS Spent fuel pool storage capacity 1386 Assemblies (1) Spent fuel pool water volume 372,460 gallons Nominal boron concentration of the spent fuel pool water 2,000 ppm Decay Maximum Maximum SFP Loss Boil-Off Time (2) Heat SFP SFP of Cooling to 10 Above Temperature Temperature Heatup Rack With No (MBtu/hr) (2-Train) (1-Train) Rate Makeup (°F) (°F) (°F/hr) (hr) Normal Full Core 28.1 124.7 151.2 9.88 47.4 (3) Discharge Emergency 25.6 129.3 159.2 8.40 55.1 (4) Offload Optimum (Better 50.2 129.3 159.2 16.46 28.1 than Design) (5) Conditions (1) Including cask pit area volume. (2) Decay Heat in accordance with ANS Standard 5.1, "Decay Heat Power in Light Water Reactors," and USNRC Regulatory Guide 3.54, "Spent Fuel Heat Generation in an Independent Spent Fuel Pool Storage Installation." (3) Stored legacy fuel assemblies, plus an additional full core (193 assemblies) discharged after 33 days decay time at design basis heat exchanger fouling conditions and Technical Specification Ultimate Heat Sink (UHS) temperatures. The normal refueling interval for WBN is 18 months, with refueling outages typically scheduled in the spring and fall. (4) Stored legacy fuel assemblies, plus 96 assemblies discharged the previous refueling outage, decayed 96 days, plus an additional full core (193 assemblies) discharged after 60 days decay time. The SFP has been analyzed for a maximum water temperature of 159.2 °F. (5) Considers better than design heat exchanger fouling and better than design UHS temperature.

WBN TABLE 9.1-2 (Sheet 1 of 4) SPENT FUEL POOL COOLING AND CLEANUP SYSTEM DESIGN AND OPERATING PARAMETERS Spent Fuel Pool Pump Number 3 Design pressure, psig 150 Design temperature, F 200 Design flow, gpm 2300 Total developed head, ft 125 Material Stainless Steel Spent Fuel Pool Skimmer Pump Number 1 Design pressure, psig 150 Design temperature, F 200 Design flow, gpm 100 Total developed head, ft 50 Material Stainless Steel Refueling Water Purification Pump Number 2 Design pressure, psig 150 Design temperature, F 200 Design flow, gpm 200

WBN TABLE 9.1-2 (Sheet 2 of 4) SPENT FUEL POOL COOLING AND CLEANUP SYSTEM DESIGN AND OPERATING PARAMETERS Total developed head, ft 170 Material Stainless Steel Spent Fuel Pool Heat Exchanger Number 2 Design heat transfer, Btu/hr 11.94 x 106 Shell Tube Design pressure, psig 150 150 Design temperature, °F 200 200 6 6 Design flow lb/hr 1.49 x 10 1.14 x 10 Inlet temperature, °F 95 120 Outlet temperature, °F 103 109.5 Fluid circulated Component Cooling Water Spent Fuel Pool Water Material Carbon Steel Stainless Steel Spent Fuel Pool Demineralizer Number 1 Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm 100* 1 Resin volume, ft 30 Material Stainless Steel

Flow may be increased to 180 gpm for refueling cavity and RWST cleanup.

WBN TABLE 9.1-2 (Sheet 3 of 4) SPENT FUEL POOL COOLING AND CLEANUP SYSTEM DESIGN AND OPERATING PARAMETERS Spent Fuel Pool Filter Number 1 Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm 150 Filtration requirement 98% retention of particles above 5 microns Materials, vessel Stainless Steel Spent Fuel Pool Skimmer Filter Number 1 Design pressure, psig 300 Design temperature, °F 250 Design flow, gpm (Filter) 150 Rated flow, gpm (Pump) 100 Filtration requirement 98% retention of particles above 5 microns Material, vessel Stainless Steel Refueling Water Purification Filter Number 2 Design pressure, psig 200 Design temperature, °F 250 Design flow, gpm 200

WBN TABLE 9.1-2 (Sheet 4 of 4) SPENT FUEL POOL COOLING AND CLEANUP SYSTEM DESIGN AND OPERATING PARAMETERS Filtration requirement 98% retention of particles above 5 microns Material, vessel Stainless Steel Spent Fuel Pool Strainer Number 2 Rated flow, gpm 2300 Perforation, inches Approximately 0.2 Material Stainless Steel Spent Fuel Pool Skimmer Strainer Number 1 Rater flow, gpm 100 Design pressure, psig 50 Design temperature, °F 200 Perforation, inches 1/8 Material Stainless Steel Spent Fuel Pool Skimmers Number 2 Design flow, gpm 50 Piping and Valves Design pressure, psig 150 Design temperature, °F 200 Material Stainless Steel

WBN TABLE 9.1-3 BASIS FOR DESIGN CRITERIA OF THE WATTS BAR NUCLEAR PLANT SPENT FUEL RACKS ASME B&PV Code III, Subsection NF AISC Manual of Steel Construction, Seventh Edition, 1970. USNRC Standard Review Plan, Section 3.8.4, "Other Seismic Category I Structures". USNRC Regulatory Guide 1.13, "Spent Fuel Storage Facility Design Basis." USNRC Regulatory Guide 1.29, "Seismic Design Classification". USNRC Regulatory Guide 1.92, "Combining Model Responses and Spatial Components in Seismic Response Analysis". OT Position for Review and Acceptance of Spent Fuel Storage and Handling Applications, dated April 14, 1978. 10 CFR Part 50, Appendix B, "Quality Assurance Criteria For Nuclear Power Plants and Fuel Reprocessing Plants".

WBN-1 TABLE 9.1-4 (Sheet 1 of 3) 10 CFR Part 50 Reactor Power & 10 CFR Part 72 ISFSI Facilities Interface Documents CIVIL / STRUCTURAL CALCULATIONS CDQ0000792013000357, HI-STORM FW Cask Handling Weights at WBN, HI-2135734, HI-STORM FW Cask Handling Weights at WBN CDQ0006912014000556, Watts Bar Nuclear Plant Haul Path Design Calculations, Multiple HOLTEC Reports, HI-2135812, Watts Bar Plant ISFSI Haul Path Design Criteria CDQ0006912014000558, Watts Bar Nuclear Plant ISFSI Haul Path - Underground Utility Evaluation , HI-2135818 CDQ0006912014000633, Dynamic Analysis of Loaded HI-STORM FW on LPT at Watts Bar, HI-2135883, Dynamic Analysis of Loaded HI-STORM FW on LPT at Watts Bar CDQ0009992013000358, Time History Generation for Watts Bar, HI-2135731, Time History Generation for Watts Bar CDQ0000792014000632, Calculation Package on the Seismic Stability Analysis of Watts Bar HI-STORM/HI-TRAC Stack Using NRC-Concurred Methodology, HI-2135902, Calculation Package on the Seismic Stability Analysis of Watts Bar HI-STORM/HI-TRAC Stack Using NRC Concurred Methodology CDQ0000792014000660, Watts Bar Auxiliary Building Floor Structural Analysis, HI-2146106, Watts Bar CDQ0000792014000634, WBN Auxiliary Building ISFSI Analysis for HI-TRAC & MPC: HI-2135779, Kinematic Stability Analysis of the Loaded HITRAC VW on RFF and in CLP for WBN HI-2135781, Seismic Stability Analysis of Empty MPC on the Refueling Floor HI-2146331, Auxiliary Building Floor Structural Qualification Under Loaded HI-TRAC VW Configurations CDQ0000792014000639, WBN Cask Loading Area ISFSI Analysis of HI-TRAC & Pedestal: HI-2146229, Seismic Analysis of HI-TRAC VW of Cask Loading Area Shelf at EL, 731 at Watts Bar Plant HI-2146299, Seismic Analysis of HI-TRAC VW on Freestanding Pedestal in Cask Loading Area at WBN HI-2146417, Structural Evaluation of Pedestal in Cask Loading Area for HI-TRAC VW at WBN CDQ0006912014000638, Watts Bar Nuclear Plant Haul Path-Rail Slab, HI-2146034, Watts Bar Nuclear Plant Haul Path-Rail Slab

WBN-1 TABLE 9.1-4 (Sheet 2 of 3) 10 CFR Part 50 Reactor Power & 10 CFR Part 72 ISFSI Facilities Interface Documents CDQ0006912014000706, Analysis of the Lift Yoke Extension and Storage Bracket HI- 2156662 & HI-2156589 HI-2156662, Structural Analysis of the Watts Bar Lift Yoke Extension Storage Bracket HI-2156589, Structural Analysis of the HI-TRAC Lift Yoke Extension for WBN CDQ0000792015000712 Low Profile Transporter (LPT) Analysis HI-2146330, Low Profile Transporter (LPT) Analysis CDQ0006912014000557, Watts Bar ISFSI Geotechnical Soil Parameters Recommendations Report, HI-2135638 CDQ0006912014000559, WBN Subgrade Modulus and Bearing Capacity for Heavy Haul Path, HI-2145966 CDQ0000792014000647, Vertical Cask Transporter Stability Analysis on the Haul Path and the ISFSI Pad at Watts Bar Nuclear Plant, HI-2146169 CDQ0000782015000761, Evaluation of Live Loads and Seismic Interaction Requirements for Dry Cask FHD Main Skid and FHD Chiller Skid, RRTI-2246-007 CDQ0006912014000560, Watts Bar Nuclear Plant Haul Path - Fabrication Pad, HI-2145996 CDQ0006912014000571, Liquefaction Analysis for Proposed WBN ISFSI Pad, HI-2135836 CDQ0006912014000572, Calculation Package of Seismic Analysis of WBN ISFSI Pad Using LS-DYNA, HI-2146101 CDQ0006912014000573, Structural Analysis of ISFSI Pad at WBN, HI-2146251 CDQ0009992015000754, Accidental Drop of a Spent Fuel Assembly During the course of MPC Loading Operations NUCLEAR / MECHANICAL CALCULATIONS EPMDBG092088, Spent Fuel Pool Cooling and Cleanup System (78) Operating Modes Calculation MDQ0000782013000405, Environmental Conditions for Spent Fuel Pool Level Instrumentation during Extended Station Blackout Conditions MDQ0000782015000732, WBN Aux Bldg-El. 757 Refueling Floor Temperature Transient (LOCA) During Dry Cask Storage Operations MDQ0009992015000746, MPC CLOSURE TIME TO BOIL & THERMAL ANALYSIS

WBN-1 TABLE 9.1-4 (Sheet 3 of 3) 10 CFR Part 50 Reactor Power & 10 CFR Part 72 ISFSI Facilities Interface Documents NDQ0000782015000757, SPENT FUEL POOL BORON CONCENTRATION ANALYSIS DURING DCS ACTIVITIES NDQ0000782015000760, Thermal Response of the HI-STORM under Flood Condition and Design Basis for Post-Flood Restorative Measures NDQ0000792015000729, WBN Site Boundary Normal and Off Normal Doses including ISFSI NDQ0000792015000730, Comparison of the Dose Consequences between a Single Fuel Assembly FHA and a Dropped Loaded HI-TRAC VW/MPC-37 Cask NDQ0000792015000731, Post-LOCA and Transient Response to Place MPC in Safe Condition during LOCA NDQ0000792015000734, OCCUPATIONAL DOSE RATES AROUND THE HI-STORM FW SYSTEM FOR WBN, HI-2135814 NDQ0000792015000763, ISFSI and Haul Route Fire Hazards Analysis Calculation NDQ0009992013000356, WBN ISFSI Compliance to 10CFR72.104 & 10CFR72.106 Criteria for Radioactive Materials in Direct Radiation, HI-2135709 & HI-2135760 NDQ0009992015000747, Alternate Cooling Water System (ACWS) Equipment Sizing Calculation WBNAPS4004, Summary of Mild Environment Conditions for Watts Bar Nuclear Plant WBNNAL3025, Normal Operating Dose for Equipment Outside the Shield Building WBNTSR020, Safety Limit for the Spent Fuel Pool Radiation Monitors WBNTSR075, Location Specific Radiation Dose to Area A6 to A10 and T to U, El. 757 WBNTSR090, Determine the Dose Rate at the Site Boundary due to Tanks in the Yard and ISFSI WBNTSR104, Location Specific Radiation Dose to the Spent Fuel Pool Radiation Monitors WBNTSR112, Shield Design Review and Equipment Qualification Study

                ---21"         36" FLOORPLATE T_

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218A 225 6 201A W 8-18 ORIFICE NOTE 10 1/~,

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                                                                                                                                                                                                                                                                                     +                                                         cca>a::             cca~.-                        P~                                                                                                     SPENT FUEL 573                                                                    1                                                            .° SPENO Z                                                                                                                         PI                                 PI                                                                                                                   ZSotS                                                                                                                                                                             202A                                 PIT SKIMMER                                                                   EL 731.0' 11_18                       209A            210A                 3 4T              3  4T 8-14                                                                                                                                                                                       2-SPPC-78-825                                                                                                                                                                STRAINER                                                ELE708I23                     ~

FE 0-HTX-78-32 .o *~* iu *~*~C7 3° 2° 2° 3° 2' 8-18 p FI 888 TI ~ B X 10 1 8 X 10 V UNIT 2 i 207A 578 208A 574 1/4° 225 '~ 8-418 560 B 8-17 Y NOTE 10 Y NOTE 10 REFULING CAVITY < 3/4° 225 73 C PH7A PHU PENT 3/4' y°ty°.N.B5772PBOA 6876 1~,/2. FE I 111 10°Q DRAIN > PRIMARY WATER ?° 3° SPENT FUFILTER CASK 8-418 78-6 8-17

v 898'_ OF I ° 8 572 K + LOADING AREA SYST8878_t 3 4° NG 7s O-STN-78-138 ~ ~'~

EL 725'-1-1/2' p COORD 8-11 823 824 826 880 j^ M M 3 4° DRAIN K KEYN,~'LAl S EL 705.48

                                                                                                                                                                         ,.I                                                                                                                                                                              m

( Q j 0-ISV-78-522 ~~ Q-FLTR-78-1 878 V S/4° z- 888 I~ .r~ NOTES: a- STATION DRAINAGE C 188 ~* 1-SPPC- C-PMP-78-1 v, PBOA

                                                                                                                                                                         """"'111                    IN 588                   3/4'              %,I          Rio                                        SYSTEM                    2'                                                                                                                                                                            1. THIS PL06 DIAGRAM IS FOR UNIT 1 AND UNIT 2.

3* C 225 o~ 78-825 "I G 78* 821 VENT 0-478852-2 2. ALL VALVES ARE THE SAME SIZE AS THE PIPE UNLESS OTHERWISE NOTED. 3/4° zi COURT) 6-1C N K 875 "a PENT ~ ;61 o 3. UNIT 1 VALVES HAVE PREFIX ER UNIT 2 VALVES HAVE PREFIX FROM 528 581 g~ o VALVES BITH NO PREFIX NUMBER ARE COMdON TO NTH UNITS. VALVES ARE SIINT n! SPENT FUEL FLOW 859 2Sd 18 557 o I d: iv+l 527 pg~ P%}A PIT FILTER 8 SYS 78 (SFP) UNLESS NOTED 9Y A DIFFERENT SYS NO. LOCATED BETWEEN FILL V RESTRICTING y. l^ ~~~ttt TANK ORIFICE A 511 8° 2' NEI aj PREFIX AN VALVE N. 529 SEE NOTE 10 g* 10* 10* T8 ti C K '~' + 2* 4. FOR DEFINITION OF SYMBOLS OF "L.C." OR 'L.C.", REFER TO pgpA 828 SPENT FUEL PIT COOLING SYSTEM 0-SPPC-78-31 TV 8-18 p D-SPPC-78-625 ~4 MEW 8268904-02001. SAMB'LE STATION O-OR-78-31 78-8 .° DRAIN o 2* M:i S. ALL PRESSURE, SAMPLE Aim TEST CONNECTIONS ARE 3/4° UNLESS G K 0-478825-11 0-HTX_78-51 OTI-5iR8ISE NOTED. N N CODRD D-8 S20 587 ^ a`y'° '~-

                                                                  +                                                                                                                                                                                    SPENT FUEL PIT                                    DEMINERALIZED                         814                                  592                                                               SPENT FUEL PIT SKIMMER PUA9'                              8. NA CLASSIFICATION OF THE PIPING SYSTEM IS DENOTED BY                              GD ary.                                                                                                                                                                HEAT EXCHANGERS                                                              2y                                                                      STATION DRAINAGE                                                                                    7. LOCATE HOLE IN PIPE 2 FEET BELOW NORMAL RATER LEVEL.

y. FE WATER SYSTEM FI MAKE_85 MCAP 100 GPM O 50 FT TDH RING VENT NOTE SYSTE47 (gyp 2

n :VA; 78-41 8-41A 0-471858-1 513 X22 HI LEVEL OF SFP AREA AN) 8 INIT~ RPLUSHING OPERATIONSD ISTRAIN:RMUSTI BEEREMOVED U SCREEN3 4' DRAIN COORD D-2 G C 10 TRANSFER CANAL Aim REACTOR SUCTION 519 561 3' BLDG REFUELING CAVITY (WITH CLEANING BEFORE PLANT STAN-UP. TEST CONNECTION IS CONNECTED TO SPENT FUEL PIT 878 CASK IN LOADING AREA) CONNECTION PRESSURE GAUGE DURING INITIAL FLUSHING.

DEMII NERALIZER 3° 588 4° EL 748'-8° S. SYSTEM DESIGN PARAMETERS ARE AS FOLLOWS: Q-DEM1N-78-1 M 3' NOR MAX OPER LEVEL WITHOUT MAX HI-LEVEL OF SFP HI LEVEL OF SFP AREA AND SUB-SYSTEM PRESSURE TEMPERATURE SPENT FUEL CASK EL 749'-2-1/2° 93 3/4' TRANSFER CANAL (WITH 570 SPENT FUEL PIT COOLING 150 PSIG 200* F AREA (WITH CASK IN NOR MIN OPER LEVEL EL 749'-1-1/2' LOADINp AREA11 VENT 3/p* CASK IN LCADING AREA) SPENT FUEL PIT SKIMMER 150 PSIG 200° F NOTE: 817 EL 748'-8-1/2° _ EL 748'-g-1/2' LOW LEVEL ALARM EL 748'-11-1/2' 516 594 NT SPENT FUEL PIT SKIMMER STRAINER 50 PSIG 200* F DO NOT EXCEED DESIGN m 0-SKR-78-137A 588 FLOW LIMITS THROUGH' Big PI CASING VENT PI C G 788KibS N REFUELING WATER PURIFICATION 150 PSIG 200° F THE DEMINERALIZER 0-LE 832 8-13 K 78_11 '~10. SPOOL PIECES IN THIS LINE TO BE INSTALLED FOR OPEN REACTOR WRING FLOODS ABOVE PLANT GRADE ONLY. ORIFICES ARE TO C 188 NESNLss

                                                                                                                                                                                                                                                                                                                                ~Q'4.14                                                                                                                                                                         11. 88 225 INDICATES THE HYDROSTATIC TEST PRESSURE.                                         RET6-309                        /                  307        NA 2                  221A                             _ _                                                                                                                                   888 THE                           THE AASMCODE
                               ~°                   2*                          11gp          COORD B-4                                                                           y~+D ~                 o             '                                g*                  O-PMP                                                                                                                                                                                                                                      LLIIH~INRCOMPONENNTSNTOITHE                     ATIC         TEST.
                                                                                                                                                  ~r+a                                                                                                                      12                                                                                                                                                                                                                                                OI'HLEINOAHYDRROSTITIC TTESTIN) MAY RE USED IF EN DES PBQA                                                               m(no                           G:   <
                                                                                                                                                                                      -o                                                                           A_A                                                        O-STN-78                                         I NI                    1N                                                             ^t                                              CASES ES
                                                                                                                                                                                                                                                                                                                              -158A                                                                                                                                                                              12. CLASS G PIPING LABELED WITH PBOA IS ANALYZED FOR SEISMIC 883                                                                                                                                                                                                                                                     34        C                                                                        1-1 } 1-1 }                                                                    1° HALE                                                                                  CAT. 1(L) PRESSURE BOUNDARY RETENTION A IS WITHIN THE SCOPE 501                                                                                                                         (NOTE 7)                                                                                 OF THE HYDROSTATIC GA PROGRAM ((THE VALVE SEAT TERMINATES THE I' N                                                                                                                                          gM             8811               DRAIN             3/4'             +{    503         NOTE 8                                                                                                                                                                                                                   PBOA BOUNDARY). ALL REMAINING WASs G PIPING IS SEISMICALLY Iu~                                                                                     SKIMMERS                                                                                       1" 1                                                  SUPPORTED FOR POSITION RETENTION ONLY.
                                                             ++                   G 225 PROA                                                                                                                                                                                          C   188 1105                                                                                                                             EL 731.0                                                      ,   '~                                            13. DESIGN CRITERIA/SYSTEM DESCRIPTION REFERENCE DOCUMENTS.

831 K 8' K DIFFUSER ;/ 0' 4,IE 7)E ,, USE THE LATEST REVISION ON ALL WORK UNLESS OTHERWISE SPECIFIED. d cl flfl NEE THE LATEST REVISION OF THE 47821 SERIES DRAWINGS °PIPING 834 voi _ + gyg7~ p~ASSIFICATI STRAINERS p_SIN_78-188 EL 705.48 ER CANAL F 2* N3-78-4001 DENT FUEL POOL COOLING AND CLEANING SYSTEM Nj lM _ CYCS RECIRC 14. FOR NA CLASS C PIPING ALL PIPING DOWNSTREAM SE ONE LAST 3" 2° C-STN-788121 C G EL 709.23 p. EL 709.23 ( °( PUMP ISOLATICN VALVE ON LOCI. DRAINS, VENTS AND TEST CONNECTIONS 581 _ 1 _1 0-471809-S IS VA CLASS K. 3y STATION DRAINAGE 2° ° ° - - n ' L 388 CCCRD C-9 is. UNLESS OTHERWISE NOTED ALL ROUT VALVES HAVE AN 'A' SUFFIX IF NOT SHORN IN THE ADDRE§S. UT8852-2 SEE NOTE 19 SPENT FUEL~PIT REFUEL BATOR GOURD B-2 1p < S. NOT USED. PBGA 3/4'S4 PURIFICATION FILTER 54{ SAMPLE STATION 17. NOT USED. 0-471825-S CASING VENT CASING VENT a: PI COORD 0-1 PI ~/~ PI PI 18. NOT USED 8-22 PI 8-10 78-8 8-38 19. EITHER VALVE O-ISV-078-0581 OR 0-ISY-Q78-0982 SHOULD BE NORMALLY 9-24 TEST OPEN DURING NORMAN. OPERATION OF THE SYSTEM, NOT BOTH. M C 18g COUN M C 188 204A `~' K u 224A `~' PI 588 0-PMP-78-20 88s gtp M M . 11 37 20. VALVES DENMED AS L.C. ARE LOOKED CLOSED WRING NORMAL PLANT

3. 212A~ BOB 203A 222A 583 223A OPERATION.

214A 3' 333 ~* O-PMP-78-9 NOTE 8 582 ~* 549 S51 9 3* 4' 10' 8-B C-S *>1 +*i PI C 888 3 4° C /4° C

                                                                                                                                                                                                                                                                                                      -S                                                                                                                       0-PHA'-78-38 838      8-28                                                                                                                                                                                                    3/4'                                                                                                                      3/4°                     584 3/4pRA CASING                                                                          DRAIN                                    504                                        o                                     DRAIN 225 G                                                                                                                                                                                                                                                                 o-sPPcae-e If                                                                                                                                                                                                                                                       C 188          O-STN-78-8                                                                          888                     C~188 216A                                                                          so           PBOA                                                                                                            506 VENT                                °v:i                                                                          228 B                                       STATION DRAINAGE             2'                                                                                                                                        188                          K                 SEE NOTE 19                                                                 188            8           C%

3' N REFERENCE DRAWINS: NA DRAWINGS:

                                                                          +        SYSTEMD     5210                                                                                                                                             N         ~M                                                                                                            N           ~M                                                                                                                              471454-SERIES ---- MECHANICAL FUEL POOL COOLING AND CLEANING SYSTEM 538                     342                                                                                                                                                                                        tl                                                                                                                      tl                        2*

2' 471811-78-1 ----- LOGIC DIAGRAM 0-FLTR-78-28 g~ SYSTEM DRAINAGE 2* STATION DRAINAGE 2* 1-,2-47W610-78-1 --- CONTROL DIAGRAM PI 78-21 0-47W552-2 0-47WB52-2 47M%54-SERIES --- BILL OF MATERIAL PBOA 22S C W9-DO-40-28 ----- DESIGN CRITERIA FOR FLOOD PROTECTION PROVISIONS K 0-PMP-78-18 PI GOURD 9-2 COORD 9-2 8-23 SPENT FUEL PIT PUMPS 2-47W888-101 ------ MECHANICAL STRESS ANALYSIS PROBLEM DRAIN _ 590 211A CAP 23M GPM O 125 FT TDH BOUNDARY - FUEL POOL COOLING AND M CLEANING SYSTEM 1 188 C 3* 213A 2' WESTINGHOUSE DRAWINGS: 228 G STATION DRAINAGE 550 552 C 3° 4° 113E794 ----- FLOW DIAGRAM. SPENT FUEL PIT COOLING SYSTEM PBOA 119DE52 ----- PROCESS FLOW DIAGRAM. SPENT FUEL PIT COOLING SYSTEM O-47W882-2 5$8 GOURD E-8 I PBOA G G E. 3/4D' vl CASING PI + "~ 554 8° 838 8 K G 22s 223 G STSATI ELO/N DRAINAGE 2L K 4'NM X 5' 1163 217A 0-478852-2 STORZ A CAP ~* ~ 4 4°NPS X 5° VENT COORD E-10 g STORZ R CAP A ffi REFUELING HATER 1 _IgY_ 1,-Iy~r_ 3' 3y °* PURIFICATION PUMPS PENETRATION X93 071 OW D78-12Oo 4y 547 CAP. 200 a 170 FT TDH P%M 537 543 4y mr m I I I E oR 41 ' 1-878 o mn 541 0-FLTR-78-2A 546 3/4° 3/4° VENT GB G / 2-567 m 83 ^ 215A 843 M 2-897 2-588 2_858 7 mil 2* 1-887 1-225A G B G UFSAR AMENDMENT 1 PBOA 225 G 2- TEST PBQA 1-887 K DRAIN °+ CCN54 l Oil 1-557 1-588 1-558 M'I _ PB]A 2-230A PEA_ 3 4°8 -SB /4' TEST 3-28 N L.p C* WATTS BAR

        ,_*~                         +                                                                                                                           ft1TI0N 5                                            M                                                                                                                                                                                              EL 748'-8° REFUEL RATER                                                                                    3/4° TEST              X~                                             2-231A             2-DRV-                     4

1 3/4° VENT o 1-23M PURIFICATION FILTER EL 748'-2° NN 2-D 2-581 a 78-837 m 7 G EL 749'-2-1/2° FINAL SAFETY SAMS*LE STATION LC 1° DR. 1-231A ffi STATION DRAINAGE SYSTEM 0.47,825-5 EL 749'-8° L.C.

COORD D-3 y. LC 2- 1-882 ANALYSIS REPORT E282 227A 2-1162 I 1-588 v1 RD 2-229A a p. ~' e PBOA 2-VN-78-838 1° VT. 1 GB G 1-227A 1-581 °i 1-580

                                                                                              '1/4°                                                                                                                                                                2'                                                                                                                1-229A                                              1 4° 2-DRV-78-839 1° DR.                                                               G 228        PSQA           B   1-~eA                  NE-                                                            /

B TRA" POWERHOUSE REFUELING WATER ~ Ne-~ ~ ~1 G 225 G X82 1~ 2-82-300 PURIFICATION FILTERS INSIDE REACTOR OUTSIDE REACTOR C -TUBE-78-1 8 i N ^ 3 4' TEST' UNITS 1 ~. 2 CONTAINMENT CONTAINMENT ~N TYP 4XDI4NETEST

                                                                                   ~> v                                                                                                            G                    N              N G 8 OUTSIDE REACTOR INSIDE REACTOR                                                    *v                                                                           MECHANICAL-FLOW DIAGRAM 1                                                   FUEL TRANSFER TUBE                                                                                                                                                                                                                                                               /2" TEST          tl

-. w :-. CONTAINMENT MMTAINAiNO 2-TUBE-7 -1 ~~ ~< zy^" ~*-cFUEL TRANSFER TUBE FUEL POOL COOLING

_ 2-gD0 N NN N ^N N ^ j -6G0 AND CLEANING SYSTEM EL 709'-2-3/4° ~Qo m ~g EL 7C8'-2-3/4' n M t VENT OPEN ~g .~. o

                                                                                 '                                         -                  WDS REACTOR                                                               G=ic                            ,zoarb1'atO1i                                                   1      PENT OPEN                           8DS REACTOR                                                                          ° n          n" °         °                 N         COOLANT DRAIN TK                                   AMN ATM                                 n                              ~a                   ~`

YN V= COOLANT DRAIN TK TVA DWG NO. 0-47W855-1 R2 COUo7gg8 EL 782'-8* Y2*~' TO ANN ATM O COST ON gt H ^ a EL 752,_8* CONT ON PENETRATION X3 &.-25 Z3 e b C d ~Bo- 41 FIGURE 9.1-3 UNIT 2 REFUELING CAVITY COOW 7W85 D711 ^U PENETRATION X3 UNIT 1 REFUELING CAVITY

RTES:

1. THE SPENT FUEL PIT COOLING SYSTEM MAINTAINS THE NECESSARY TEMPERATURE OF THE WATER IN THE SPENT FUEL PIT AND CLARIFIES, PURIFIES, AND DEMINERALIZES THE WATER IN THE SPENT FUEL PIT, FUEL TRANSFER CANAL, AND REFUELING WATER STORAGE TANK. THE SURFACE OF THE WATER IS CLEANED OF FLOATING TRASH AND IMPURITIES BY A SKIMMER LOOP CONTAINING A SKIMMER PUMP. SKIMMER HEADS, A STRAINER, AND A FILTER.

2. THE SPENT FUEL PIT COOLING SYSTEM IS OPERATED WHEN THERE IS A NEED TO LOWER THE PIT WATER TEMPERATURE OR TO CLARIFY AND PURIFY THE PIT WATER. THESE OCCASIONS ARE DETERMINED SY THE AMOUNT OF FUEL IN THE PIT AND THE LENGTH OF TIME THE FUEL HAS BEEN IN THE PIT. COOLING WATER FOR THE HEAT EXCHANGER IS SUPPLIED FROM COMPONENT COOLING WATER.

3. THE DEMINERALIZER PORTION OF THE SPENT FUEL PIT COOLING SYSTEM MAY BE ISOLATED FROM THE HEAT REMOVAL PORTION OF THE SYSTEM BY PROPER VALVING AND USED TO PURIFY THE WATER IN THE REFUELING WATER STORAGE TANK.

4. PIPING AND INSTRUMENT SYMBOLS ARE SHOWN ON DRAWING 308817-3R1 OF MECHANICAL DESIGN STANDARDS.'

8. THIS SYSTEM IS COMMON TO UNITS 1 AND 2, EXCEPT AS NOTED.

8. UNDER EMERGENCY CONDITIONS THE DEVICE MAY BE MANUALLY TRANSFERRED TO THE OPPOSITE POWER TRAIN.

7. TEMPORARY PIPING TIE-IN BETWEEN SFPCS AND RHRS WILL BECOME FUNCTIONAL WITH THE ADDITION OF SPOOL PIECES. THIS PIPING WILL OPERATE DURING OPEN REACTOR COOLING FOR FLOODS ABOVE PLANT GRADES, ONLY.

8. UNIT INTERFACE SEPARATION BOUNDARIES ARE CONTROLLED BY INSTRUCTION TI-12.08, CONTROL OF UNIT INTERFACES.

9. LEVEL LOOPS C-LPL-78-42 AND -43 MAINTAIN PHYSICAL SEPARATION TO THE EXTENT PRACTICAL.

0-L-948 0-L-980 0-LT 0-LI 78-42 --T' ------ 78-42 G-L-BBC 0-L-8SC Q-PX 0-UPX 78-42 78-42 0-L-948 0-L-851 0-LT 0-LI 0-L-881 0-L-981 0-PX 0-UPX 78-43 78-43 REFERENCE DRAWINGS: 0-470811-78-1 -------- LOGIC DIAGRAM 470434 1. ... ------- PIPING 0-47WB55-1 ---------- FLCO DIAGRAM WESTINGHOUSE - 113E794 ------ SPENT FUEL PIT COOLING SYSTEM FLOW DIAGRAM WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNITS 1 & 2 ELECTRICAL CONTROL DIAGRAM SPENT FUEL PIT COOL SYS TVA DWG NO. 0-47W610-78-1 R1 FIGURE 9.1-4

NOTES: DIGITAL AND ANALOG LOGIC SYMBOLS ARE USED ON LOGIC DIAGRAMS TO FUNCTIONALLY DESCRIBE THE PROCESS CONTROL. REFER TO THE ASSOCIATED HIRING SCHEMATIC FOR THE ELECTRICAL COMPONENTS USED TO IMPLEMENT THE CONTROL SCHEME. NIT INTERFACE SEPARATION BOUNDARIES ARE CONTROLLED BY NSTRUCTION TI-12.08. CONTROL OF UNIT INTERFACES. BENCE DRAWINGS: W611-O-1--------LOGIC INDEX W811-0-1---------LOGIC INDEX W610-78-1--------CONTROL DIAGRAM REFUELING CAV UNIT 2 REFUELING CAV UNIT 1 SIB RWST UNIT 2 SIS RWST UNIT 1 SPENT RESIN STORAGE TANK IMARY WATER SYSTEM WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE PUMP C S UNITS 1 & 2 SPENT FUEL PIT ELECTRICAL BACK-UP PUMP LOGIC DIAGRAM SPEN T FUEL PIT COOLING SYSTEM TVA DWG NO. 0-47W611-78-1 R1 FIGURE 9.1-5

POWER CANE JUNCTION BOS 00 THIS RD u OPERATIRR FLOOR AR ELEVATION

                                                                                                                          'WTEI TRO                                                                                                                         SURFACE TRA'                                                                                                                       ELEVATION M

PLAN VIEW ISERNILY (TOP OF WPPORT STRUCTURE RENIM& FOR CLA1I71')

1. TROLLEY

2. CONTROL CONSOLE S. MOTOR CONTROL CAINET M. MAIN MOIST S. TROLLEY MIME ACCESS MATCH A. TROLLEY POSITION SCALE T. SUPPORT STRUCTM B. GIIPPER TuK

 . GRIPPER

10. GRIPPER TUBE DOWN POSITION SWITCH V EW SHOWING GRIPPER TUNE ASSY. RETRACTED

11. GRIPPER TIME UP POSITION SWITCH

12. LOAD CELL IB

11. AIR NOSE AND ELECTRIC CAKE REELS 1%. MAST SUPPORT TUN IS. OUTER MAST TUE

16. WIDE ROLLEAS IT. FUEL ASSY. GUIDE ARS BRIDGE (RIDGE POSITION TRANSMITTER IYDRAULIC BUMPER SPRING RUDER SECTION 6-8 Iff. MONORAIL MOIST

23. BRIDGE DRIVE I

SECTION A-A WATTS BAR NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Typical Manipulator Crane FIGURE 9.1-6

Ls nano

                                                                                 .a .eel
                                                                      ~~ciuunf nr.

1 I uu uq[ I 1+

Loy II~*o.

1 ; (LILI I 1 1 11 11 II ILL LNIIL I I -- neD1 UMii 1 11 1 Le.P ur IA orf 1 t" I rr[l - ryrl Unl 1 1 I 1 1 wto

                                                                 '"t, 1 1                      nrEs 1 1 1 1
                       'USU SISfIM Il14MM r

SK" FUEL 11i a.arw WLIAKI III. Uef. dots 1 1 I I I 1 I I I II I I II I I I 1 I I 1 1 1 EeF 1 1 1r aDS sU[rtC.AVV

1 u~. ot 1

to of Irii( IIYIMLIL WATTS BAR NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Typical Spent Fuel Pit Bridge FIGURE 9.1-7

OPERATING FLOOR 12'-0" 8' 8" I I I

                                  +                       I I    I

{ A I 2' 0 ELEVATOR I

       ~                                                  I I

I ELEVATOR WINCH

                                                 ~ I VIEW A-A WATTS BAR NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT New Fuel Elevator FIGURE 9.1-8

WATTS BAR NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Rod Cluster Control Changing Fixture FIGURE 9.1-10

6894-10 13.375 18 12 q::p 3.375 I I I I I I I I I I 1.875 I I I I I I I I 4.312 I

                   -T 12.25 WATTS BAR NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT 2.188                      Typical Spent Fuel Handling Tool FIGURE 9.1-11

t-- 188 WATTS BAR NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT Typical New Fuel Handling Tool FIGURE 9.1-12

(.!) z

s, Ct

C, C, w z 1-z

I:

C, u MK*( PLATFORM (Sff 0£TAILJ GENERAL CONSTRUCTION SPECIFICATION G*55, LI LI I 4. TVA Fi[LD TO PROViC)E AND FABRICATE. ALL EL 749'-;~* ! 5. Fdt: ...... "t;.'-Ull'l'J ,W,J'IU lflt::>r-'C.1,, 11Vr1 VI" TfC.LLJ::> In A""'-'Vl"'CUAN\..C.

                                                            'v\\ \                            / ~WA rER. LEVEL {REF) rrrn 11                                                         WITH GENERAL CONSTRUCTION SPEC G-29M.
                                                                \ \                                                  I                                                               I
                                                                 \ \                 ~
                                                                  \  \                                                        I '""//'--~//~-~"'+-'//~-~//-"
                                                                    \ \                                                       I l:i                                      1
                                                                     \\                                                       ! 11                                       '1/
                              /'-SLING UG
                        /
                          /

I I \

                                                                            \
                                                                            µ      rMK*](POST, SffSH.2) 11 If                                          .,._>-£XISTING TS 8 x 8 x .375 l//                                                   \\r                                                 l                         >                                                                                             PUMP                                                                                                  >                                                           8-A      O-FG-067-0032
                                                                                         ~<                        ~m                                                                                                                                                                                                  ~m   ~
                                                                                         ~N                        ~N                                                                                                                                                                                                                                                              C-A      0-FG-067-0036 ERCW PUMP
                                                                                                                                                                                                                                                                                                                       ~-    '                                                     0-A      0-FG-067-0040
                                                                                         ~~                        ~~

AUX BLDG WALL MOTOR BEAR I NG AUX BLDG W A L L ~ ~ a ~~:~ ERCW zcw zcw E-8 O-FG-067-0047 i!ii! ~ COOLER DRAIN i!ii! PUMP
<wI <wI DETAIL D1 G-8 O-FG-067-0055 INSIDE n~ ~I~ LINE INSIDE~
D AIR RELEASE LINE CML CS DET B1 ~:~§ <( MATERIAL BOUNDARIES TYPICAL FOR ERCW PUMP OUTSIDE (TYP FOR 8 ERCW PUMPS) OUTSIDE u 36" DISCHARGE HEADER A A-A, 8-A, C-A, 0-A, E-8, ERCW PUMP
~! F-8, G-8, H-8 ADD IT ION AL DS STUFFING BOX GENERATOR HX BLEED-OFF SHEET 5 COORD D-6 1-FT-67-61C NOTE:
THESE VALVES DRAIN THE DIESEL GENERATOR DETAIL A1 JACKET WATER SIDE (SHELL SIDE) Of THE HEAT TYPICAL FOR ERCW PUMP EXCHANGER, THEY ARE NOT PART OF THE ERCW CLG~~~ A-A, B-A, C-A, 0-A, E-B, G-8 SYSTEM. 1-FLV-67-6 'f 2-67-8008
' 16' 14" DIESEL GENERATOR BUILDING ------f---------t--,1 ------f--------H (SS VALVE)
DET C1 {18-8 ONLY) 5'.:
\"
ADDITIONAL DIESEL 16" NOTES: GENERATOR HX ---~=----------<[)>1-I---- DISCHARGE B 1. ALL VALVES ARE SAME SIZE AS PIPE UNLESS OTHERWISE NOTED. SHEET 5 2-HTX-82-72082 2. EXPLANATION OF VALVE AND INSTRUMENT NUMBERS. COORD B-8 ~1 2-THV- 2-6 INSTRUMENT 1- FE- 67- 10D
!:> 67-8021-8 516 NO. (UNIT) {TYPE) (SYSTEM) (INSTRUMENT NO.) -1111 CS CML VALVE 1- FCV- 67- 10D NO. (UNIT) {FUNCTION) (SYSTEM) (VALVE NO.)
2-s1- 1~c
3. SOURCE NOTE NCR SWP79-W-3 REPORT.
"' ADDITIONAL DSL 4. MAIN PROCESS SYSTEM VALVES ARE SHOWN IN THEIR NORMAL OPERATING c ~ ~! GENERATOR HX POSITION.
DISCHARGE A TIONS ARE 1/2" UNLESS OTHERWISE NOTED. SHEET 5 ARE TVA CLASS 8 FOR CONTAINMENT ISOLATION AND COORD B-5 IPING AND VALVES TVA CLASS C, EXCEPT AS NOTED ON AKEOFFS ARE SAME CLASS AS HEADERS THROUGH CS CML REFER TO ~ ~ NOTE 47 ~ ~ 36" C C
<~~ ; ; m 2-67 ~~g: ~ t , ...
OVERFLOW ~ - 984
~~!:. ~ ~ ~~
STRUCTURE ~~L \? ~~
~ A 3/4 ~ L CML CS ~I';;~a------'=,p"---
TO r;~r-0 ~ MPT 24D
~ ~<..>t-------- 5*
2-67 w.L TES C -985 INT
13. LERS W >---------------------=:,c...====-----+1----====----------___l------/',,1-----------__J ~! BUILD IFIED SEISMIC CATEGORY 1 (L) PER WB-DC C CAT C _i!: ~------
10" PRESSURE BOUNDARY DURING AND AFTER cs ALL PRIMARY SAFETY-RELATED COOLERS 2-ISV-050-0759 ,.. 1 PER
1. (C* l ON THESE "VENO SAFETY RELATED EQU REQUI NED ON 47B21-1 &. -1A. T
-- WITH TROL ROOM AND ELECTRIC CHILL E DRAIN VALVES WERE ORI ALLED 30" A1 ERCW PUMP PRELUBE AS CLASS M BUT SHOULD BE CONSIDERED C* FOR FUTURE REPLACEMENT WITH TVA CLASS C MATERIAL. (Y) INDICATES SEISMIC CATEGORY 1 (L)B WITHOUT ERCW PUMP WELL PRESSURE BOUNDARY RETENTION.
14. DENOTES A PIPE MATERIAL BOUNDARY:
" HOLE DRILLED IN OISC FOR FREEZE PROTECTION (TYP 8) CS = CARBON STEEL ER TO DETAIL D1 FOR MATERIAL CS/SS BOUNDARY CHANGES (TYP 8) SS - STAINLESS STEEL CML - CS WITH CEMENT MORTAR LINING NOTES CONTINUED ON SHEET 5 ING STATION PIPING 1-471800-1 ----------- FLOW DIAGRAM-GENERAL PLANT SYSTEMS 1-47\11844-3 ----------- FLOW DIAGRAM-RAW COOLING WATER 1-47\11803-2 ----------- FLOW DIAGRAM-FEEDWATER 1-47\11859-1 THRU 3 ---- FLOW DIAGRAM-COMPONENT COOLING SYSTEM 1-471¥850 SERIES ------ FLOW DIAGRAM-FIRE PROTECTION AND RAW SERVICE WATER 1-47\11610-67 SERIES --- CONTROL DIAGRAM 47W611-67 SERIES --- LOGIC DIAGRAM 17W586, 171¥585 ----- PIPING-DIESEL GENERATOR BUILDING ~Rf If~ T~~f T~~Q~fI6~T6~ ~crc:a~J 1fi~L~§~ E§rn~~w~~~u~~~tIFf ~5~ SEE THE LATEST REVISION OF THE 47B21 SERIES DRAWINGS "PIPING SYSTEM CLASSIFICATION."):
WB-OC-20-20 ---------- TRAVELING WATER SCREENS FOR WATER SUPPLY INTAKE PUMPING STATION N3-67-4002 ----------- ESSENTIAL RAW COOLING WATER 37W845-100 SERIES----- STRESS ANALYSIS PROBLEM BOUNDARY 47W845-100 SERIES----- STRESS ANALYSIS PROBLEM BOUNDARY UFSAR AMENDMENT 3 WATTS BAR Is FINAL SAFETY PROBABLE MAXUAUM FLOOD SEE WB-DC-40-29 ANALYSIS REPORT NORMAL MINIMUM WATER EL 675.0' NORMAL MAXIMUM WATER EL 683.0' I PS, YARD, DCB LOSS OF DOWNSTREAM OAM EL 665. 9' UNITS 1 & 2 MECHANICAL COMPANION DRAWINGS: FLOW DIAGRAM ESSENTIAL TO 0-47W845-2 &. 5 HOLDING 1,2-471¥845-3 POND 1-471¥845-4 RAW COOLING WATER SYSTEM 2-471¥845-7 TVA DWG NO. O-47W845-1 R2O FIGURE 9.2-1
~:i~),n 8318 831A 1-FE ~~. ~ 1 4 ll.::. 67-224A 1021A 0-~w 4 1 ~~--~-----------------------------~--~5\_)(1>-~6,..7~-2,_2_48---,--------------~---i !>-I------~ 1" SEE NOTE 26, co, 1 SEE NOTE 23e.v ~v ~5r1: 26 1-FE c, C 67-224A SHEET 5 v47 1147SH 5 67-2248 3/4 3/4" VENT 0-67-619A + r,CYO;;::MIPPnoMiNE"N:iiT'rcnooniL~l"N;;:G~sV:vs<--;----;:::=====~----------------------------------:---7 ERCW ~,~Ai3i.~~~ANGERS ~I SAMPLE STATION u;gi 1-47W625-4 AP=3.8 PSI o 12,000 GPM C00RD 8-9
TRAIN 18.--/2_8_ _ _ _-+~ ERCW D SEE NOTE 23, SAMPLE STATION
<( SHEET 5 1-47W625-4 u SEE NOTE 23 ~ - F C V COOR 8-7 1-FCV 67-127 AIR CONDITION EQPT 2A - 6" f1 3/4"~ TC T 2 676
~:::D N:~: 23 tj 8 ~
AIR CONDITION ALT SPOOL FOR EOPT 28 ~ _'",,'a"'",~~,-*,:-".',, g~ rr-DrMld--.----1 r~E~v:Eg~~~~\ E~ok C-6 SHUTDOWN BD ROOM
~ - - - ~ 3 " N P S x 5 ' 2 2-A/C WATER CHILLER EMERGENCY MAKEUP I STORZ 5438 55 (EL 737 .0) f~P~L6-i?w~5~-fURGE Hhcrlf--....h----,-.,e-1 .4P-8.8 H2D 560 GPM 2-FCV -+- <>
COOR G-1 ~ CCS &. AUX FW 67-146 PUMP SPACE ~ 0
~~Fr~=:~-~~j~ ~;~~~x5" 0 COOLER 1A 0 SH 4 COOR A-1 SPOOL PIECE 2 1 4" CLEAN .; 3 2-SPPC-067-0687 OUT PORT c, 2-FLV-67-925 u [g 67-125 F~! v-,cv 4"NPSx5" lf6 cs i f ss u:; "' f 2-67-555 6" ~---------1-------f----~ ";~v, +
1/2" 1/2' UPPER CNTMT VENT COOLERS 28 .t 2D UPPER CNTMT VENT SH 3 (U2), COOLERS 18 &. 10 COOR 8-11 SH 3 (U1), COOR B-11 FLOOD MODE SUPPLY TO RCW-ICE CONDENSER UPPER CNTMT VENT 0-47W844-4
~~5En2~~ .t 2C f----,X:H UPPER CNTMT VENT COOR H-9 COOR C-11 H_XJ----,~~O~EfG, }~ &. 1C COOR C-11 LOWER CNTMT VENT ';======'--------j~~O~E~G,1~ &. 1D COOR E-10 LOWER CNTMT VENT ~--------<COOLERS 1A &. 1C SH 3 (Ul),
COOR H-10
SEE NOTE 13 SH 1 AND NOTE 19 ON SH 5
~/1 .__ 923A LOWER CNTMT VENT COOLERS 2A .t 2C I]
SH 3 (U2), COOR G-10 ss cs UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE 2~<> UNITS 1 & 2 6~ SEE NOTE MECHANICAL 23 FLOW DIAGRAM ESSENTIAL COMPANION OWG: RAW COOLING WATER SYSTEM 0-47W845-1 &. 5 TVA DWG NO. O-47W845-2 R15 1-47W845-3 &. 4 2-47W845-3 & 7 FIGURE 9.2-2
(TYP) (TY 1" Tl cs
SEE NOTE 1.3 SHEET 1 AND NOTE
_,_ . _3_"_ DISCH HOR 8 19 ON SHEET 5. SH 2 X-68 COOR G-8 I I cs X-72 ,'-;;-------,----,-K.:>t--~.--K.>1---,-------1 ---G EQUIPMENT DR 1-47W851-1 COOR 8-8 I MAIN SUPPLY HEADER 1 B SH 2 COOR E-10 D <( u I I ~ X-70 EQUIPMENT DR 1-47W851-1 I COOR 8-4 6 _,.. I _3_"_ DISCH HOR A SH 2 lf----_r:::;;::==_:r=---t0-1---_[_----==-----------------------------~-----J/'r--~-----,-------I--CBITrjlf------k>l----_[_------':r::_------::I--,--{ COOR F-7 cs I I X-71 .',----,,-----,----K:>t---t:XK.f--K.>t----,----,-- ---G EQUIPMENT DR 1-47W851-1 1" COOR 8-2 582A
$ _,_. I _._._ MAIN SUPPLY HEADER 1 A f--------'----ir----L-t{:>-t--L-------------------------------------~----i,,,-,-~--,---=--------,I--CEIT3--jf------K.>I-----L---'-----=-----i SH 2 COOR F-10
_1_* I I I EQUIPMENT DR r-~=========::;---__c_--'------'---___c--__.:'_________________________________________________---t<Ji---'---;-;1r;;;:;:::.1K-;,r--,,---11-CEIB-1f-------1<::,--_j__ ___:_c:r::_~---( 1-47W851-1 COOR 8-10 SEE NOTE 4 INSIDE CRANE OUTSIDE CRANE 0 I WALL WALL 589A
~ : (TYP 4) VT ~(TYP)
C 8 VT 1" TC 1-fCV CB TO WASTE ! 67 _ 111 573D ~ s I ~; (TYP) (TYPI ss--+--cs
- I - DISCH HOR 8 SH 2 COOR G-8 698A, 8, C, D SEE NOTE 4 ~ D C 8 VT 2 TYP CS SS TV _._ .
1-FCV 1060 1-FCV CG 67-113 67-107
,. M "fyp 1022 ~ cs (UNIT 1 ONLY) 1-RFV-67-1025A, 8, C, D ;.,) ;.,)
MAIN SUPPLY HEADER 18 SH 2
~ ~ COOR F-11 DETAIL A3
{ TYP 4 PLACES) _'-;;-----{)X}-~~~~:--~~--K,----,---v~T------1 ~"e---**_*- ~ L __ _ _ _ _ _ _ s_,_*_"_Tj~c--~,---,--6;~~1-~'--.-ss_~-'--s---(x::S,:IT:)----s-,_'_"_'~<'~4'--,-'-_ _-,-'-_ _-'-----, NOTES:
~~--- 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS, SEE SHEET 1.
VT j c B SEE NOTE 4 CS
~J 2. THESE CONNECTIONS ARE CLOSED WITH BLIND FLANGES INSTALLED OR ALLOWED ~ 1-FCV 10608 1-FCV ;.,! OPEN WITH THE ESTABLISMENT OF A LOOP SEAL DURING TIMES WHERE ABSCE IS REQUIRED OPERABLE. DURING OUTAGES OR OTHER MAINTENANCE NEEDS, THESE 67-105 " 67-99 CONNECTIONS CAN BE USED TO SUPPLY CHILLED WATER TO THE LOWER COMPARTMENT COOLERS IN ORDER TO PROVIDE AN ADEQUATE WORKING ENVIRONMENT IN THE M REACTOR BUILDING OR GENERICALLY ALLOW THE TRANSFER OF WATER TO/FROM THE AUXILIARY BUILDING AND THE YARD. THIS PIPING IS TVA CLASS G, 1 (L)A.
STRESS ANALYSIS IS DOCUMENTED IN THE CALCULATION N3-67-93A. cs 3. NOT USED.
4. HEX STOP NUTS HAVE BEEN REMOVED AND A NEW DRIVE SLEEVE AND WORM GEAR TO ALLOW FOR 360" OF OPERATION HAVE BEEN INSTALLED FOR THIS VALVE. MANUAL OPERATION OF THIS VALVE TO THE CLOSED POSITION WILL 774 RENDER THE VALVE INOPERABLE UNTIL A LEAK RATE TEST IS PERFORMED.
TO WASTE DR (TYP) ~(TYP) 5668 s,;r TC c 8 SEE NOT~4 VT 1-FCV 1-FCV 568C 1 ' TO WASTE j 67-95 67-96
~ :.,.! 1005C ~ $ 574 c S r------'---,,r-~------,/'-----~--------~~-~~- Cf--'--~-,-'-------1 8 vi 0::- SEE NOTE 4 CS VT 1 -FCV Vl ~ 1060C 1-FCV 67-97 ~ 67-91 M
cs UFSAR AMENDMENT 3
.lQ..'._ WATTS BAR 573A TC SEE NOT~ VT 1 ' TO WASTE j FINAL SAFETY ~;:~~ 693A ANALYSIS REPORT £ ~
h-+---<:Efilr3-- 1-----_L_--Kf--~~~-----, ~< c B SEE NOTE 4 ~ ~ POWERHOUSE VT 1-FCV 1060A 1-FCV
"'~w ZCJ('.10::
67-89 67-8 REACTOR BUILDING UNIT
~i~§ MECHANICAL " FLOW DIAGRAM ESSENTIAL cs COMPANION DRAWINGS:
1-47W8-45-1,2,4,5 a: 7 RAW COOLING WATER LOWER CONT (TYP) BC VENT COOLERS
~-' (EL 716.0') (TYPI TVA DWG NO. 1-47W845-3 R47 DESIGN FLOW=306 GPM FIGURE 9.2-3
l'.) z (TYPJ (TYP) <( 0:: _,_. 11T ~ D 4'x2i-,.,------1iHr,_-_--c:_:-_;~_g1i----,------rr~~------j<:::;t---':!:~::-_:_..:~==------------------------------~--v?1------'----~~----------1~ D w (TYP 4 PLACES) ~)e[f'~c--l---------------------- I I z <( f- f;)d:_____r:=======-------------------------------------:;:;::-JOl-----,-----=~.,---K=?!-:-n----,I--CTiill--ll-------K:>1-_j_------'=:-'-'------'------::r::-----J z EQUIPMENT DR 2-47W851-1 C00RD 8-8 D _,_. ,~ I ,I MAIN SUPPLY <( HEADER 2B u ~:xx:h-.----:-c-+r:~~~~~~~lJ+----::-:"-----,:~::----k>l----L------;----=~==-------------------------------~---:-:.*f---~--.-------------i~r----K;>t----~-=-;--~---------;:i::;-, SH 2 COORO E-1 CONSTRUCTION TIE-IN (TYP 4 PLACES) I I THV 2 1 1 2
--1..:_
EQUIPMENT DR "t----'===========--------------------------------:;:;;::--1<::::>1-----:--,=C.,.,---K)t-n----il-CBill-lf----K,:>t-~~=-;--~~-,--, 588B
UNLESS OTHERWISE SHOWN 2-47W851-1 C00RD 8-4 f----~ I I DISCH HOR A Lf~'i--.~---,H_Je'.l.___Tl--lf-------,--h--~LK>l----'2L____'.__:~-=2 -*=*
~~~ - - - - - - - - - - - - - - - - - - - - - - - - - - = : : . _ : : r : : . . . __ _---i__,.,.!-'='------'-;--;:-----;i;;--::::::---------11--C8ffi7f------K..>t-----'----'"'c=-~--------,--;i::;-----j SH 2 COORD f-5 I I I EQUIPMENT DR -fs--'===========--------------------------------:::::i'~C>l---;-,:c.,;.,----1<~:--Tl,---,1--CEIB-11------+c:>t-_j_------'"';-"-'------'------;:r:;-----\
2-47W851-1 COORD B-2 I I MAIN SUPPLY HEADER 2A
~-----:-----j~~~----Jl1i---:::.1,-~--K>l---',J___~-'. SH 2 =--------------:::c.___~~----.----:::=:~rnl--K>t--~~--------;,;-1 COORD E-1 EQUIPMENT OR '-=-~-------,--+Ct-_.:4---+Ct--F2 *=-
2-47W851-1 588A COOR B-10 OUTSIDE CRANE WALL 589A VT s s ~ s ~ Fcv(TYP c 2-6950 ~s1-111 67 1005D 1---------'------'---L--Kf---,--~~-/l---------'--------'--'-L_----~---,---- f--r--------Qx~-~57~AB-- NOTES: 1osoo cs vr 1 . THESE ALLOWED 2-FCV OPEN ABSCE IS REQU I UT AGES OR OTHER , THESE 67-107 CONNE SUPPLY CHILLE COMPARTMENT COOLE AN ADEQUATE IN THE REACTOR BUILDING OR GENERICALLY ALLOW THE TRANSFER OF WATER TO/FROM THE AUXILIARY BUILDING AND THE YARD. THIS PIPING IS TVA CLASS G, 1 (L)A. STRESS ANALYSIS IS DOCUMENTED IN THE CALCULATION N3-67-93A. cs 2 THE PRESSURE CLASS BREAK BETWEEN ERCW AND THE REACTOR COOLANT PUMP MOTOR AIR
. COOLERS OCCURS AT THE FLEX HOSE CONNECTIONS WHICH ARE DESIGNED TO 150 psig.
772 DR
SEE NOTE 13 ON SHEET 1 , AND NOTE 19 ON SHEET 5.
s s ~ C 2 MAIN SUPPLY 2-FCV G HEADER 28 67-103 SH 2 COORD f-1
~s 2-FCV ;.,I r** CONSTRUCTION 67-105 TIE-IN 11 l" TO WASTE s
5668 573C VT 2-FCV 67-95 695C
+l 1005C ~ DISCH HDR A f----~~---KJ---.--~----,/f----~~-------~-----,- SH 2 COORD f-1 CV 67-97 ..§_'._
ss UFSAR AMENDMENT 3 l" TO WASTE (TYP) (T MAIN SUPPLY 566C HEADER 2A 573A CB SH 2 2-FCV 2-FC COOR F-1 WATTS BAR l
TO WASTE 67-87 67-8 FINAL SAFETY ANALYSIS REPORT 2-FCV 2-FCV VT 67-89 67-8 POWERHOUSE
" UN IT 2 04A ~ MECHANICAL ~l cs "I°'N""SI;=D"-E-=="f-'==~= FLOW DIAGRAM ESSENTIAL
_,._, 778 B C WALL DR (TYP) (TYP) RAW COOLING WATER COMPANION DRAWINGS: INSIDE 1-47W845-1 4:. 4 CONT 1-,2-47W845-2, 5 .t. 7 TVA DWG NO. 2-47W845-3 R26 VESSEL OUTSIDE CONT VESSEL ALL VALVE NUMBERS PREFIXED WITH (2-67) FIGURE 9.2-3(U2)
l'.) TC TC z 887A 1-67 ~ SEE DET A4
0 f - - - - - - - - - - - - - ( ~;~~7.'

-4---j_;-

C6B(_Dt-,----------,
Ll ""0 X DR
~ :"
0 < z DR w z ~ 0-TCV DR 67-1222A 112 .. ""zr- ~
\
1~ 5548 1" 1/2' 1 ; 1/2"
a
"" 1/2" CYLINDER 3/8" 0 0 ""u 678A RELIEF 1" VALVE 0-67-671 0-67-679 1" AF TERCOOL ER 3/4" e------* ~l 4 4 uiJ [rt,] AUXILIARY CONTROL AIR COMPRESSOR A SEE DETAIL A4 1 (EL 757 .0) NOTE 3 715A 1-67 602B NOTE:
1. FOR GENERAL NOTES AND REFERENCE DRAWINGS, SEE SHEET 1

2. NOT USED.

3. BIOCIDE CIRCULATION VALVES 1-67-715A, 1-67-716A, a:. 1-67-7158 TO BE NORMALLY CLOSED. THEY ARE OPENED FOR BIOCIDE INJECTION OR OTHER MAINTENANCE ACTIVITIES.
SEE NOTE 13 SH 1 AND NOTE 19 ON SH 5 _
872A 872B 1"---C:C(}-----'--_j_----( ~;~~4~7~ - - - - - - - - ' - - ! 1-67 609A 2'.._ 1-1/2"
;.,I 1-FCV ;_I 67-356 1-67 610A ~ ~
THV v
~'
ox ~ ~ I 0 PEN. RM CLR
~~
00 ( L 737 .q*) TC
~~ UFSAR AMENDMENT 3 8ffi DR DR WATTS BAR (EL 692,D') I ~ :6.P = 15' o 15 GPM ~ FINAL SAFETY ANALYSIS REPORT 2 1/2" VENT 0-67 614A POWERHOUSE 9A 1/2" VENT TC AUX & CONTROL BLDG UNIT 0-67 ELEC BO RM 0-67 A/C CON H~ 6148 MECHANICAL SH 2 COOR F-6 COMPANION DRAWINGS:
CORROSION FLOW DIAGRAM ESSENTIAL O TEST SECT IONS 1-47W845-1, 2, 3, 5, &. 7 ELECTRIC BDRM A/C ELECTRIC BD RM RAW COOLING WATER GPM
\{C.,~~~PENSER TVA DWG NO. 1-47W845-4 R52 ~p = 10'@ 440 GPM DESIGN FLOW 300 GPM CONTROL BLDG i~ ~9 tbq~l 440=
DESIGN FLOW = 300 GPM
----------- FIGURE 9.2-4 AUXILIARY BLDG
I '
~-----------------------------------------------------------------------~
UNIT 1 RAW ~Jr- ol-HISV 638 §__" UNIT 2 RAW MAIN SUPPLY COOLING WATER ~ _+/-.'.'. ~ COOLING WATER HEADER 28 DISCHARGE f--'--C:,1-;__-,---.__ '---f-----Kf----1 DISCHARGE SH 1 1-47W844-3 t3 l / 2-47W844-3 COORD D7 8
~c_o_o*__c_-_,_ _~ ______ c_oo_*__c_-_'_ _ __ MAIN SUPPLY %rc_______,_ ,_,_-_"_ HEADER 2A SH 1 COORD D6 COMPR D TOTAL COOLER STATION AIR COMPRESSOR D FLOW RATE (96.3 GPM o 15 PSI .6.Pl ,------ ----------------------------------------7 DISCHARGE HEADER A - - - - k C l+l_1_4_"-, ~~~g~~R~E SH 1 SH 1 COOR CJ ADDITIONAL DIESEL COORD 81 \;~~r GENERA TOR D
<(
~----
0 u 636D 1-FCV ~6h C G(TYP) SEE NOTE 33 AND NOTE 41 0-THV- 67-72 65 D 67-1111 SEE NOTE SEE NOTE 42 SEE DETAIL SEE NOTE 42 VENT REFERENCE PER 321930. TO BE EVALUATED FOR 0-67 DUAL UNIT OPERATION. SEE NOTE STATION AIR COMPRESSOR C ~~~~~~ 0-067-10148 COMPRESSOR C TOTAL COOLER FLOW RATE ( 54 GPM @35 PSI.6.P) I G 6" 0-PI ,- - - ~C~3~7- -7 : C I NOTES CONTINUED:
15. THE FAILURE POS1TION FOR NON-MANUALLY OPERATED VALVES IS SHOWN AS BELOW:

26. VALVES 1-FCV-67-147, 0-FCV-67-151 AND 1-FCV-67-458-A 0 = OPENS WHEN IT FAILS 0-THV- ARE ADMINISTRATIVELY LOCKED IN THE CLOSED POSITION. X = CLOSES WHEN IT FAILS
~ 67-632C S.!. (WITH BREAKER OPEN) (APPENDIX R). O= STAYS AS IS WHEN IT FAILS
27. VALVES D-67-506A THROUGH H ARE TO BE ADJUSTED, THROUGH THE USE 16. ALL CLASS G PIPING IS SEISMICALLY SUPPORTED TO MAINTAIN Q OF ULTRASONIC FLOW METERS, TO SUPPLY THE DESIRED PRELUBE FLOW OF 2 PRESSURE BOUNDARY AND THE HYDROSTATIC TEST IS WITHIN THE QA 627C GPM TO EACH DEENERGIZED ERCW PUMP WITH ONE PUMP RUNNING IN PROGRAM EXCEPT FOR PIPING ON THE DISCHARGE SIDE OF DRAIN THE RESPECTIVE TRAIN. A MINIMUM OF 1/2 GPM IS REQUIRED BY THE AND VENT VALVES AND RELIEF VALVES WHICH DISCHARGE TO THE NOTE: VENDOR BEFORE STARTING AN ERCW PUMP. IF A FLOW OF 2 GPM CANNOT ATMJSPHERE. SINCE THESE PIPES DISCHARGE ATMOSPHERIC PRESSURE, THESE VALVES DRAIN THE DIESEL GENERATOR JACKET BE ACHIEVED, THE HIGHEST VALUE ABOVE .5 GPM SHOULD BE USED. NO HYDROSTATIC TESTING OF THESE LINES IS NEEDED. (SEE NOTE 22)
WATER SIDE (SHELL SIDE) OF THE HEAT EXCHANGER. 28. NOT USED.
17. IO] THIS SYMBOL DENOTES THOSE VALVES WHICH HAVE A LOCKING
~ THEY ARE NOT PART OF THE ERCW SYSTEM. 29. NOT USED. l2...J DEVICE SO VALVES CAN BE LOCKED IN THEIR PROPER POSITION.
30. ALL VALVES HAVE SUFFIX "A" UNLESS OTHERWISE NOTED.

18. ALL INSTRUMENTATION SENSE LINES AND VALVES SHALL BE OF

31. FLUSHING CONNECTIONS ARE ADDED TO THE BLIND FLANGES STAINLESS STEEL.
TO FACILITATE CHEMICAL FLUSHING. THESE FLUSHING CONNECTIONS 19. THE HVAC COOLERS/CHILLERS SUPPLIED BY ERCW WHICH ARE DESIGNATED AS
~" MAIN SUPPLY SHALL BE TVA CLASS G. TVA CLASS Y ARE SEISMIC CATEGORY 1 (L )8 WITHOUT PRESSURE BOUNDARY HEADER 18 FOR SPOOL PIECES 0-SPPC-67-05588 AND 0-SPPC-67-05598, FLUSHING STATION AIR COMPRESSOR B SH 1 INTEGR1TY.
CONNECTIONS ARE ADDEO TO THE BOTTOM OF THE SPOOL PIECES COORD 88 20. THE ERCW SUPPLIED COOLERS WHICH ARE DESIGNATED AS TVA CLASS Z ARE TO FACILITATE CHEMICAL FLUSHING. THERE IS A 1" CAP WITH A 3/16" HOLE IN THE CENTER THAT MUST REMAIN ON THE 1" DRAIN LINES WHEN SEISMIC CATEGORY 1 (L )A WITH PRESSURE BOUNDARY INTEGRITY. TEST I NG IS NOT IN PROGRESS 21. FLOW DIRECTION FOR NORMALLY CLOSED VENT, DRAIN, RELIEF AND TEST VALVES SHALL BE OUTWARD FROM THE SYSTEM UNLESS OTHERWISE SPECIFIED. NOTE 38 CONT: 32. NOT USED. WHEN DISCHARGE IS TO ATMOSPHERE. PIPING DOWNSTREAM OF THESE VALVES SHALL BE CLASS G, UNLESS OTHERWISE SPECIFIED. 2-RFV-67-1020A-A 15D PSIG 2-RFV-102D-8-A 150 PSIG 33. VALVES 0-67-511A, -516A, -665A, -6658, -666A AND -6668 ARE U1/U2 2-RFV-67-1022-A 16D PSIG 2-RFV-1022-8 160 PSIG INTERFACE POINTS. VALVES ARE ADMINISTRATIVELY LOCKED IN THE 22. THE ESSENTIAL RAW COOLING WATER SCREEN WASH PUMPS 1A-A, 2A-A, 2-RFV-67-1 D22-C 16D PSIG 2-RFV-1022-D 16D PSIG CLOSED POSITION WITH HANDWHEEL LEFT IN PLACE. 18-8, 28-8 AND THE ASSOCIATED DISCHARGE PIPING (1(L)A) ARE 2-RFV-67-1024-A 150 PSIG 2-RFV-1024-8 150 PSIG REQUIRED TO MAINTAIN PRESSURE BOUNDARY INTEGRITY. ANY MODIFICATIONS 2-RFV-67-1024-C 150 PSIG 2-RFV-1024-D 150 PSIG 34. SOME CI S ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM OR REPAIR TO THE SCREEN WASH PUMPS, PIPING, OR VALVES AFTER 2-RFV-67-1 026-A 160 PSIG 2-RFV-1 026-8 160 PSIG THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE ALTERNATE ID CAN BE ACCESSED IN MAXIMO AS NECESSARY JUNE 17, 1995 SHALL BE MADE TO THE REQUIREMENTS OF TVA CLASS C. 2-RFV-67-1 D26-C 16D PSIG 2-RFV-1026-D 160 PSIG THE PRELUBE PIPING TO THESE PUMPS IS NOT REQUIRED TO MAINTAIN PRESSURE 4" NPS X 5' STORZ TYP 2-RFV-67-1029-A-A 160 PSIG 2-RFV-1029-8-8 160 PSIG TO DETERMINE IF PREVIOUS CIDS EXISTED FOR A SPECIFIC COMPONENT. BOUNDARY INTEGRITY (1(L)B). {SOURCE NOTES 55E NCR WBN MEB 8408 ANO
~\ 2-RFV-67-1031-A 2-RFV-67-1032-A 160 160 PSIG PSIG 2-RFV-1031-8 2-RFV-1032-8 160 160 PSIG PSIG 35. THIS VALVE IS A UNIT 1/2 INTERFACE POINT AND MUST BE CLOSED WBPER950260).
23. VALVES 1 &. 2-FCV-67-22, 1 &. 2-FCV-67-24, 1-FCV-67-127, 1-FCV-67-128, 2-RFV-67-1033-A 160 PSIG 2-RFV-1033-8 160 PSIG WITH THE HANDWHEEL REMOVED. IF VALVE HAS UNACCEPTABLE SEAT DETAIL AS 2-RFV-67-1034-A 160 PSIG 2-RFV-1034-8 160 PSIG LEAKAGE. THE VALVE SHALL BE FITTED WlTH A 1/16 INCH RED RUBBER 1 &. 2-FCV-67-81, 1 &. 2-FCV-67-82, 2-FCV-67-147, 1 &. 2-FCV-67-223, AND 2-RFV-67-1035-A 160 PSIG 2-RFV-1035-8 160 PSIG GASKET FULL SHEET WHICH EXTENDS OVER THE UNIT 1 SIDE OF THE 1-FCV-67-478 ARE ADMINISTRATIVELY LOCKED IN THE OPEN POSITION (WITH TYP 2-RFV-67-1 038-A 160 PSIG 2-RFV-1038-8 160 PSIG BREAKER OPEN) (APPENDIX R). HEADERS 1A &. 2A MAY BE CROSS-CONNECTED VALVE DISC. THE SPACE BETWEEN THE GASKET AND DISC SHALL BE 2-RFV-67-566-A 160 PSIG 2-RFV-566-8 160 PSIG FILLED WITH A CASTING MADE OF SYLGARD 170 A &. B SILICONE FOR STRAINER MAINTENANCE DURING ERCW OPERATION BY 2-RFV-67-566-C 160 PSIG 2-RFV-566-0 160 PSIG ELASTOMER. OPENING BOTH CROSS-CONNECT VALVES 1-ISV-67-1117 AND 2-ISV-67-1119 2-RFV-67-573-A 160 PSIG 2-RFV-573-8 160 PSIG BEFORE CLOS I NG EITHER 1 - OR 2-FCV-67-22. EITHER 1 - OR 2-FCV-67-22, 2-RFV-67-573-C 160 PSIG 2-RFV-573-0 160 PSIG 36. THE DISC ON THESE VALVES IS MADE OF AUSTENITIC GRAY IRON, WHICH IS NOT WHICHEVER IS REQUIRED TO SUPPORT THE OPERATING STRAINER, SHALL REMAIN 2-RFV-67-582-A 160 PSIG 2-RFV-582-8 160 PSIG SUITABLE FOR RAW WATER SERVICE. REPAIR OR REPLACEMENT OF THESE IN THE OPEN POSITION AS REQUIRED ABOVE. HEADERS 18 &. 28 MAY BE 2-RFV-67-582-C 160 PSIG 2-RFV-582-D 160 PSIG VALVES REQUIRES THE USE OF MATERIALS WHICH ARE NOT INCOMPATIBLE WITH CROSS-CONNECTED FOR STRAINER MAINTENANCE DURING ERCW OPERATION O-THV- 2-RFV-67-539-A 150 PSIG 2-RFV-539-8 150 PSIG RAW WATER SERVICE. SPECIFICALLY PROHIBITED ARE AUSTENITIC GRAY IRON, BY OPENING BOTH CROSS-CONNECT VALVES 1-ISV-67-1118 ANO 67-635A 2-RFV-67-1 025A 160 PSIG 2-RFV-67-1025C 160 PSIG C95400 ALUMINUM BRONZE NOT PROPERLY HEAT TREATED, OR OTHER 2-RFV-67-1 0258 160 PSIG 2-RFV-67-1025D 160 PSIG 2-ISV-67-1120 BEFORE CLOSING EITHER 1- OR 2-FCV-67-24. EITHER 1- OR MATERIALS NOT COMPATIBLE WITH RAW WATER OR COMPATIBLE ONLY WHEN IN 2-FCV-67-24, WHICHEVER IS REQUIRED TO SUPPORT THE OPERATING STRAINER, STATION AIR COMPRESSOR A THE PROPER HEAT TREATED CONDITION (UNLESS THE PROPER HEAT TREATMENT SHALL REMAIN IN THE OPEN POSITION AS REQUIRED ABOVE.

39. AUXILIARY BUILDING SECONDARY CONTAINMENT ENCLOSURE (ABSCE) MUST BE IS SPECIFIED IN THE PROCUREMENT DOCUMENT). VALVES 2-FCV-67-127 AND 2-FCV-67-128 ARE ADMINISTRATIVELY LOCKED OPEN CONSIDERED WHENEVER SYSTEM BREACH WILL OCCUR IN NORTH/SOUTH VALVE (WITH BREAKER OPEN) (NOT APPENDIX R).
ROOMS (Al &. All). BEFORE PERFORMING ANY MODIFICATION/MAINTENANCE 37. NOT USED. COMPRESSOR A TOTAL COOLER FLOW RATE ACTIVITIES IN ROOMS A10 &. A11 ENSURE APPROPRIATE PRECAUTIONS ARE 24. VALVES 1 &. 2-FSV-67-17D-8, FSV-67-168A, FSV-67-188A &. FSV-67-190B ( 54 GPM 035 PSI.6.P l (WHICH ARE ASSOCIATED WITH FCV'S OF SAME NUMBERS) HAVE BEEN TAKEN TO MAINTAIN ABSCE BOUNDARY. 0-PI ELECTRICALLY DISCONNECTED AT THE MOTOR CONTROL CENTER DUE TO I- - - ~C~3;=;5- - 7 40. CHECK VALVES 0-67-508A, 0-67-5088, 0-67-51 3A AND 0-67-5138 HAVE HAD APPENDIX R INTERACTION. 67-663A THE INTERNALS REMOVED TO PERMIT REVERSE FLOW WHEN REQUIRED. 38. THE SET PRESSURE {WITH NO BACK PRESSURE) FOR THE FOLLOWING ERCW RELIEF VALVES IS LISTED BELOW: 25. NOT USED. I 41. HEAT EXCHANGERS Al AND OA2 HAVE BEEN DISCONNECTED FROM THE 8" SUPPLY PIPING AND THE HEAT EXCHANGER INLETS HAVE BEEN BL IND 0-RFV-67-1021A-A 150 PSIG 0-RFV-67-10218-8 150 PSIG FLANGED. THESE BLIND FLANGES ARE NOT TO BE REMOVED FROM THE HEAT 0-RFV-67-1039A-A 150 PSIG 0-RFV-67-1 0398-8 150 PSIG I EXCHANGERS WITHOUT PRIOR ENGINEERING APPROVAL. THE INTERFACE 1-RFV-67-1 020A-A 150 PSIG 1-RFV-67-1 0208-8 150 PSIG POINTS REMAIN AS PREVIOUSLY ESTABLISHED ANO ALLOWS CONFIGURATION 1-RFV-67-1022-A 150 PSIG 1-RFV-67-1022A-A 160 PSIG CONTROL OF THE CLASS G PIPING EVEN THOUGH IT WILL NOT BE USED 1-RFV-67-10228-B 160 PSIG 1-RFV-67-1022C-A 160 PSIG DURING NORMAL MODES OF OPERATION. THE CLASS G PIPING AND 1-RFV-67-10220-8 160 PSIG 1-RFV-67-1024A-A 150 PSIG COMPONENTS ARE REQUIRED FOR OPERATION FOR CONVENIENCE AND 1-RFV-67-10248-B 150 PSIG 1-RFV-67-1024C-A 150 PSIG CAN NOT BE REMOVED. 1-RFV-67-1024D-B 150 PSIG 1-RFV-67-1025A-A 160 PSIG 1-RFV-67-10258-8 160 PSIG 1-RFV-67-1025C-A 160 PSIG
42. 1-FCV-67-72 AND 2-FCV-67-73 ARE POSITIONED OPEN AND POWER REMAINS 1-RFV-67-1 0250-B 1 60 PSIG 1-RFV-67-1026A-A 160 PSIG REMOVED. ONLY THE OPEN FLOW PATH THROUGH THE VALVE IS MAINTAINED 1-RFV-67-10268-B 160 PSIG 1-RFV-67-1026C-A 160 PSIG WITHIN CONFIGURATION CONTROL. 1-RFV-67-1026D-B 160 PSIG 1-RFV-67-1027A-A 160 PSIG
________ J 43. NOT USED. 1-RFV-67-1027B-B 160 PSIG 1-RFV-67-1028A-A 160 PSIG 1-RFV-67-10288-B 160 PSIG 1-RFV-67-1 029A-A 160 PSIG 1-RFV-67-10298-B 160 PSIG 1-RFV-67-1 030-8 160 PSIG
44. HEX STOP NUTS HAVE BEEN REMOVED AND A NEW DRIVE SLEEVE AND WORM GEAR 1-RFV-67-1031A-A 160 PSIG 1-RFV-67-10318-8 160 PSIG TO ALLOW FOR 360° OF OPERATION HAVE BEEN INSTALLED FOR THIS VALVE. 1-RFV-67-1032A-A 160 PSIG 1-RFV-67-10328-8 160 PSIG

45. NOT USED. 1-RFV-67-1033A-A 160 PSIG 1-RFV-67-10338-8 160 PSIG RAW SERVICE 1-RFV-67-1034A-A 160 PSIG 1-RFV-67-1 0348-8 160 PSIG WATER AND FIRE NOTE: 1-RFV-67-1035A-A 160 PSIG 1-RFV-67-1035B-B 160 PSIG PROTECTION 1-RFV-67-1036A-A 160 PSIG 1-RFV-67-10368-8 160 PSIG 0-47W850-1. THIS CONNECTION SUPPLIES WATER FOR INITIAL 1-RFV-67-1038A-A 160 PSIG 1-RFV-67-10388-8 160 PSIG UFSAR AMENDMENT 3 COOR G-10 1-RFV-67-1042A-A 160 PSIG 1-RFV-67-10428-8 160 PSIG OPERATION OF THE 46. VALVES 1-ISV-67-1117, 1-ISV-67-1118, 2-ISV-67-1119, ANO 2-ISV-67-112D, CAN 2-RFV-67-1037A-A 160 PSIG 2-RFV-67-1 0378-8 160 PSIG STATION AIR BE OPENED BY OPE RAT IONS TO CROSS-TIE THE 1 A & 2A HEADERS AND THE 18 & 28 2-RFV-67-1040A-A 160 PSIG 2-RFV-67-10408-8 160 PSIG 0 0 COMPRESSORS HEADERS TO REDUCE STRAINER DIFFERENTIAL PRESSURE. 2-RFV-67-1 041 A-A 1 60 PSIG 2-RFV-67-1 0418-8 160 PSIG 626B 2-RFV-67-1043A-A 160 PSIG 2-RFV-67-10438-8 160 PSIG WATTS BAR
~~~~~~~~~- ------~~~ - - -- 47. THE PIPING BETWEEN THE STANDPIPES (HYDRAULIC GRADIENTS) AND THE VALVE 2-RFV-67-1044-8 150 PSIG O-RFV-67-0550-8 160 PSIG AUXILIARY BUILD G ----------------------------------4 BOXES 1 AND 2 (CONTAINING VALVES 0-FCV-067-0360 AND -0362) HAS BEEN 0-RFV-67-0671-A 80 PSIG 0-RFV-67-0672-A 80 PSIG QUALIFIED FOR PRESSURE BOUNDARY RETENTION (REF. N3-67-4002). 1-RFV-67-0509A-A 1 60 PSIG 1-RFV-67-05098-8 160 PSIG FINAL SAFETY 1-RFV-67-0514A-A 160 PSIG 1-RFV-67-05148-8 160 PSIG 1 -RFV-67-0539A-A 150 PSIG 1-RFV-67-05398-8 150 PSIG ANALYSIS REPORT 1-RFV-67-0550 160 PSIG 1-RFV-67-0566A-A 160 PSIG 1-RFV-67-0566B-B 160 PSIG 1-RFV-67-0566C-A 160 PSIG 1-RFV-67-0566D-B 160 PSIG 1-RFV-67-0573A-A 160 PSIG l _ _ L_ _c--!'C,1----'L._i;~o_,__:.._!_J 1-RFV-67-057 38-8 1 60 PSIG 1-RFV-67-0573C-A 160 PSIG 1-RFV-67-057 3D-B 1 60 PSIG 1-RFV-67-0582A-A 160 PSIG POWERHOUSE 1-RFV-67-05828-8 160 PSIG 1-RFV-67-0582C-A 160 PSIG 1-RFV-67-0582D-B 160 PSIG 2-RFV-67-0509A-A 160 PSIG 2-RFV-67-05098-8 160 PSIG 2-RFV-67-0514A-A 160 PSIG TURBINE BUILDING UNITS 2 2-RFV-67-05148-B 160 PSIG 2-RFV-67-0550-A 160 PSIG MECHANICAL 1 FLOW DIAGRAM ESSENTIAL COMP AN ION DRAWINGS:
RAW COOLING WATER SYSTEM 0-47W845-1, 2 TVA DWG NO. O-47W845-5 R1 1, 2-47W845-3 1-47W845-4 2-47W845-7 FIGURE 9.2-4A
l'.) z ~
TC TC
""0 "' 2 s " s 0-TCV 0 685A 0-FSV 67-1224A w 67-1223 1-1/4" 1 /2" 1/2" z ~
=-1 THV 1"
i t 1' 1" 3/8" CYLINDER 1/2"
~ f - - - . , .. ~~67-995 EMERGENCY GAS TREATMENT ROOM COOLER
""zr- 0-PCV ~ DR 0 0 5 10 GPM 6818 2-67-990 '!~ ~~cl l 681A 67-1224
a
"" 2 ~ 1' 1" RELIEF
-680 VALVE 1' 0 0-67-672 0-67-682
""u 4,i 1" 1"
;..j AFTERCOOLER ~ 3/4" 1' V,
Oj VT 2-67-989 Cc, C l f1 4 1 i<©>
~ AUXILIARY CONTROL AIR COMPRESSOR B BA TRANSFER PUMP It. AUX FW ~m PUMP SPACE CLR (EL 713.0') ~N
i: DETAIL A7
{EL 757 .0)
.6.P-10' @ 60 GPM v,~
w z ~
,_,<NO <1..1.1:i:O
i;::CV>U ;.j BA TRANSFER PUMP &. AUX FW PUMP SPACE CLR (EL 713.0')
TO CNTFGL CHG .6.P=l O' o 60 GPM PMP 2A-A OIL CLR r----~ 0-47W859-4 B-12 2-67-715A 2-67-10168 SEE NOTE 24 SEE 2-67-1017B NOTE 3 SH 5 TC TC
;.I NOTE:
1. FOR GENERAL NOTES AND REFERENCE DRAWINGS, SEE SH. 1.

2. NOT USED.

3. BIOCIDE CIRCULATION VALVES 2-67-715A. 2-67-7158 TO BE NORMALLY CLOSED.
pi" THEY ARE OPENED FOR BIOCIDE INJECTION OR OTHER MAINTENANCE ACTIVITIES. 2 ~
SEE NOTE 13 SH 1 AND NOTE 19 ON SH 5.
613A 2 1
'"'~- 1/2' (TYP) i 2 2-1/2" (TYP)
NOTE: INTERFACE HOLD ORDER H.O. 20011, 20015 PLACED ON INDICATED VALVES TO 6038 MAINTAIN CLOSED CONFIGURATION. 2A 28 PUMP RM COOLER SIS PUMP RM (.EL 692.0') 01< C a. Cf~L~:2.0') oi,c 2
.0!.P - 10' @ 22 GPM 1 2 1 ~p = 10' O 22 GPM 1 2 G C DR ~ 2 1/2" ~ S 2-1/2' ~
2'.. I I , I _2" A 28-8 C Ct ~6ar~~p RM °" ~~p RM °" 2 2 1 GPM l 2 1 2 R} ! 1,\P'J 33 ! 1,55P'J 33 cPM 2-FE c c 2-67-1033A DESIGN FLOW = 28 GPM GN FLOW = 28 GPM 67-189A TC DR ss 2-1/2"1 ss S 2-1/2"~ I~ 3-:.
-A 8-8
.! il 1-1/2" RM 2 2-67
~,~~-1 o, C / 607A RM °" C \ 612B O' I ' o 19 GPM 1 2 ! 7 ~()~*~19GPM 1 2 ~*
cs
.1." cs cs ss ss ss 2 6098 THV UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UN IT 2 THV COMPANION DRAWINGS: MECHANICAL 0-47W845-1, 2 &. 5 DR 1-47W845-4 PIPE CHASE COOLER 1, 2-47W845-3 FLOW DIAGRAM ESSENTIAL PIPE CHASE COOLER ZN ! 9,25P'~ 15 GPM tJ! 91\P'J 15 GPM RAW COOLING WATER SYSTEM TVA DWG NO. 2-47W845-7 R18 FIGURE 9.2-4B
c., z 3' < SAFETY INJ TEST 0::: 1-+5W760-211-16 SIGNALYBO-S1 0 0 A-AUTO w ,..,,.---------------, STRAINER 2A-A z BACKWASHING
.-----~sr~OP~+:="~~s~r*~*~r------,
< PUMP A-A @ PUMP C-A 1-------i 1-z 67-285
~::iE:AJJ~f~H TO SEE NOTE 6 (SEE NOTE 3) 0 OPEN
< PULL TO LOCK u IN STOP
~~igo~L TAGE BLACKOUT AVAILABLE *AUXILIARY SHUTDOWN NORMAL BOARD VOLT AGE AUTO AVAILABLE START 1/o-H~_'c-'S~TO~P--;---,
67-36C ERCW PUMP SEE NOTE 11 HEADER 1A A-A RUNNING SEE NOTE B HEADER A ISOLATION VALVE CONTINUED ON
,1--l 0-471611-67-2 COORD, E-3 to--_,H;;;E;;;A,.DE.R.2_.A.,__ _ _ _\-'HEADER 2A ISOLATJON VALVES AND STRAINER(SAME AS 1A) ---1> 8~:Ji~~,~ ~~
6 2 COORD, G-3 CONTROL LOGIC SIMILAR TO ERCW PUMP A-A NOTE 9 NOTE 9 DERIVED FRCM UNIQUE LIMIT AND TORQUE SW REQ OF VALVE CONTROL LOGIC SHULAR TO ERCW PUMP C-A
........ DETAIL A1 TYPICAL ~ CONTROL ERCI PUMP E-B l--"'HE;;;AaaDEa;:.R"""2B._.,_ HEADER 28 ISOLATION VALVES AND STRAINER (SAME AS IA) __
CONTINUED ON
) 0-471611-67-2 COORD, G-3, E-3 NOTES:
ERCW PLIAP G-8 1. FOR Sne:JLS OTHER THAN THOSE NOTED SEE INSTRUMENTATION AND IDENTIFICATION STANDARDS, LATEST ISSUE. WATTS BAR
2. FOR CCIFLETE INSTRU~NTATION AND CC..PONENT SEPARATION DESICNATIONS FINAL SAFETY SEE CONTROL DIAGRAM, 1-47W610-67-1, 2, J, 4, 5, OR 2-471610-1, -2, -3, -4, -5.
J. PAIRED PUMPS (A-A a. C-A. 8-A a. D-A. E-8 a. G-8. a. F-8 a. H-8) ARE TIED ANALYSIS REPORT TO COli,HON SHUTDOWN BOARD, PURPOSE Of XS-67-XXX JS TO PREVENT MORE THAN ONE PUMP AT A TIME BEING HD FRCN A SINGLE DIESEL GENERATOR.
4. *oIGITAL AND ANALOG LOGIC SYMBOLS ARE USED ON LOGIC DIAGRAMS TO FUNCTIONALLY DESCRIBE THE PROCESS CONTROL. REFER TO THE ASSOCIATED I WIRJNG SCHEMATIC FOR THE ELECTRJCAL COMPONENTS USED TO IMPLEMENT POWERHOUSE I THE CONTROL SCHEME. *

5. O-HS-67-288, 32B, 36B, 408, 518 a. 55B ARE DISCONNECTED TO PREVENT SPURIOUS UN ITS 1 & 2 OPERATION CF PUMPS A-A, 8-A, C-A, 0-A, G-8 ~ F-B IN CASE OF FIRE.

6. THE BACKWASH/FLUSH MASTER TI~R ACTIVATES AT 12 HOUR INTERVALS SYMBOLS:
FOR A PERIOD CF BETWEEN 5 AND 20 MINUTES. *- LOCATED ON ELECTRICAL SWITCHGEAR ELECTRICAL
7. VALVES 1 AND 2-FCV-67-22 AND 1 AND 2-FCV-67-24 ARE ADMINJSTRATIVELY J LOCKED IN THE OPEN POSJTION. (11TH BREAKER OPEN) (APPENDIX R)

8. INPUT TO MICROBIOLOGICAL INDUCED CORROSION (MIC) REt.OVAL SYSTEM
# - LOCATED IN AUXILIARY CONTROL ROOM LOGIC DIAGRAM A - TEST SWITCH SUPPLIED ON CONTRACT 91NNA-75954A, DRAWING 1'EIEC5001. ESSENTIAL RAW COOLING WATER
9. SEAL-IN NOT FOR 1-FCV-67-143, 2-FCV-67-143 &. O-FCV-67-144.

10. TVA DWG NO. 0-47W611-67-1 R2

11. DURING CROSS TIE OPERATION, STRAINER WILL BE RUN IN CONTINUOUS BACKWASH. FIGURE 9.2-5
(!) z ....., DIESEL
,------------------------------iSPEED 31= a 40 RPM C,
°" MAIM ERCW MAIM ERCW SEE NOTE 7) MOTES, DISCHARGE DISCHARGE Cl HEADER B HEADER A 1. FOR SYMBOLS ANO GENERAL NOTES, SEE 0-471611-67-1. w OPEN ;f,_H~ CLOSE 2. DIESEL GENERATOR OC-S IS A SPARE DIESEL THAT CAN BE z ....., 67-66A CONNECTED TO REPLACE ANY OF THE OTHER DIESELS. OC-5 WILL USE THE liilCR CONTROLS Of THE DIESEL REPLACED
1- 3. THE HEAT EXCHANGER INLET MANUAL VALVES ARE TO BE POSITIONED TO ALIGN DIESEL OC-S TO THE SAME TRAIN z
....., HEADERS AS THE DIESEL BEING REPLACED. AUX AUX 4. VALVES 1 I: 2-FCV-67-81. 1 a: 2-FCV-67-82 ARE ADMINISTRATIVELY < LOCKED IN THE OPEN POSITION. (WITH BREAKER OPEN) (APPENDIX R).
5. THE LOGIC FOR 1-FCV-67-72 IS IDENTICAL TO 1-fCV-67-66 Cl EXCEPT FOR A.) TIMER OLR IS 30 SECONDS. 8.) 1-HS-67-66C
< IS REPLACED BY 1-HS-67-72A AND C.) RELAY CONTACT R02 u IS CONTROLLED BY 1-HS-67-66A. (1-HS-67-72A DOES NOT EXIST).
6. THE LOGIC FOR 2-FCV-67-7J IS IDENTICAL TO 1-FCV-67-68 EXCEPT FOR A.) 1-HS-67-68C IS REPLACED BY 2-HS-67-73A AND 8.) RELAY CONTACTS R01/RCI ARE CDNTOLLED BY 1-HS-67-68A
( 1-HS-67-73A DOES NOT EXIST).
7. THE CLOSING CIRCUIT OF .CR HAND SWITCHES 1- I: 2-HS-67-66A AND 1- I:. 2-HS-67-67A ARE DELETED TO PREVENT SPURIOUS CLOSING OF VALVES 1- I: 2-FCV-67-66 AND 1- &. 2-fCV-67-67 IN CASE OF FIRE.

8. 1-FCV-67-72 AND 2-FCV-67-7J ARE POSITIONED OPEN AND POWER REMAINS REIIOVEO. ONLY THE OPEN FLOW PATH THROUGH THE VALVE IS MAINTAINED WITHIN CONFIGURATION CONTROL.

9. CHECK VALVES 0-67-508A, 0-67-5088, 0-67-513A AND 0-67-5138 HAVE HAO THE INTERNALS REt-<<lVED.
SEE DET A1 SEE DET A1 (0-47W&11-67-1) (0-+71611-67-11 I CONTROL LOGIC I I IDENTICAL I I 1-FCV-67-66TO I L SEE DET A1 (0-47W611-67-1) COMTIMUEO FROM SHEET 0-4-71611-67-1 67 -3) HEADER 18
- _l_L___ I AUXILIARY OPEN 1 BUILDING --=--IJ_ _ _l_' _ _" '-_ _ ]~~irm:_
Il n n ' I CONTROL LOGIC I ID ENT I CAL TO I 1-FCV-67-81 TO CCW I ,~rr-*-f---~~~R~S-RE&-s___ f _i_ _ _f I SYSTEM 1-4-7W611-27-1 FROM DIESEL GENERATOR OC-S
~~~~E:E,URN _ _ _ _ _ _ _ _ _. __ _ _ _ _ _ _ __.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ____,
I HEmER 2A l ,--.,------J--__-___-___-___-___-___-___-___-___-___-- _____________________ 7
~iT i-------------i--i-----L--}-i-~-g~-~-!G-s~-~-~T---1---.-}-~-~-g..~i-~-:~-t-~-T-----i LOGIC IS IDENTICAL TO LOGIC SHOWN ABOVE r ]i::T
{0-471611 ~ 2AI AND 2A2 281 AND 282 I I 1-4-71611-67-3
1) (SIMILAR TO (SIMILAR TO I I
__H_Em_,_R_2_*__________.._____,_,_,_,_*o_,_,2_i_._____,_e_,_,_*_o_,_*_21....___ 1_ - L------------------------------------------------------~ WATTS BAR FINAL SAFETY ANALYSIS REPORT CCM'ANION DRAWINGS: POWERHOUSE TO DIESEL 0-47'1611-67-SERIES UNITS 1 &. 2 ENGINE HTX 1-47W611-67-SERIES oc-s 2-471611-67-SERIES ELECTRICAL (SEE NOTE 2) LOGIC DIAGRAM ESSENTIAL RAW COOLING WATER TVA DWG NO. 0-47W611-67-2 RO FIGURE 9.2-6
(!) z ....., NOTES: CPEN 31= 1. FOR SYMBOLS AND GENERAL NOTES, SEE 0-471611-67-1. QC 2. 1-HS-67-2958, -2968, -297B, I: -298B HAVE BEEN REt.DVED TO PREVENT A-AUTO A-AUTO C, A CONDITION ADVERSELY AFFECTING THE SAFETY FUNCTION OF ASSOCIATED VALVES DURING AN ACCIDENT. Cl OPEN CLOSE w OPEN CLOSE z 1-z ....., PHASE B # CNTMT ISLN < 1-47W611-88-1 ~ A-AUTO u ~--------~ CPEN DETAIL A1 PHASE 8 OPEN CNTMT ISLN 1-47W611-88-1 OPEN FAN 1A START SIGNAL I PHASE 8 I CNTMT ISLN 1-47W611-88-1 I SEE OET A1 1-TM THIS DRAWING SEE DET A1 IN/I© 67-1298 OPEN THIS DRAWING OPEN CLOSE OPEN CLOSE I I
,---------7 I lMJV CONTROL KIV CONTROL I ~1af~~ ~gene I I I 1-FCV-67-83 I I I
1-TE 67-129
,---------7 CONTROL LOGIC SIMILAR TO 1-FCV-67-130 P-AUTO CLOSE 1-HS OPEN 67-86 1-4 11-68-1 TO ERCW RETURN 'CONTROL LOGICl I I SIMILAR TO HEADERS Ll~C\1-67~4- J RC PUMP l<<>TOR 1----*- - - - - - - - - - - - - - - - - - -{ ~;r~: f:l~/ENT COOLER IC } - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
COOLER 1A2 CONTROL ROD -------------------{ ~;r~: f~T~)VENT COOLER 18 DRIVE MOTOR _ _ _ _ _ _ {LOWER CONTROL CNTMT ROD VENT DRIVECOOLER 1C RC MOTOR K>TOR COOLER COOLERS lC (SAME 1C a: AS ABOVE) COOLER 1A
}- ------------------------------,-----..
o TO ERCW RETURN HEADER 18 ------------------- { UPPER CNTMT (SAME AS IA) VENT COOLER 1D
}-----------------------:r } ,!. HEADER 1 A HEADER 1 A 'f CNTMT 1B RC MOTOR COOLERS 18 a: ~
l5~ l - - - - - - {LOWER CONTRCl..
----aWE:R ROO VENT DRIVECOOLER K1TOR CCXX.ER 18 (SAME AS ABOVE)
CNTMT VENT CCXX.ER 10 RC t.<<JTOR COOLE:RS ID a.
} - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - , - - - - - . . } TO } - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ -----,-----..
ERCW
~n~~~S l g2N~!~~~g11-67 ~6 -...:,H~EA~D~E~R~l~B...J'---------.::;°";;;;;T~RO=L;_;;;ROIJ;;;.,;O=R~IV~E;_;;MO~T~OR:;,,.::C~OO=L=ER:;_;1~D~(~SAM=E~A=S~A~BOV::.:;E~)_,::::.,__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __:,_ _ _ _ _ _ _ _ _ _ _ _ _ _"T"_ _ _.;.,._ _ _ _ L _______________JH~E~AD~E~R~1~8' - - - - - - - - - -
TAP fRCM WATER COOLER REFRIGERANT LINE INSTR Rliil COOLER PACKAGE A TO ERCW RETURN HEADERS INSTRUMENT ROCM { f~kfR PACKAGE B WATTS BAR
------------------ r:~: }----I--
l FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNIT 1 ELECTRICAL LOGIC DIAGRAM ESSENTIAL RAW COOLING WATER TVA DWG NO. 1-47W611-67-3 R6 FIGURE 9.2-7
(!) z 31= < OPEN QC C, PHASE 8 CNTMT ISCIL Cl 2-47W611-88-1 w z < NORMAL OPEN 1-z
. NORMAL DETAIL A1 Cl u
OPEN FAN 2-A-A ST ART SIGNAL FROM CNTMT VENT SYSTEM SEE 2-471611-30-4 (COORD D-8) SEE OET A1 I . N /2-TM 1~ THIS DRAWING SEE DET Al 87-1298 OPEN SEE DET A1 OPEN CLOSE THIS DRAWING THIS DRAWING MDV CONTROL I MDV CONTROL 2-TE 67-129 OPEN CLOSE OPEN MO\/ CONTROL
,------*"'-+----------a::::=:::J--------+',~---------r-1, P-AUTO SEE DET Al SEE DET Al THIS DRAWING CLOSE 2-HS OPEN THIS DRAWING OPEN U-86 RC PUMP MOTOR RUNNING 2-+7W811-68-1,0-4 TO ERCW RETURN HEADERS .,__ _..,_ _ _ _ _ _ _ _ _ -{~~;~~:/ENT COOLER 2 C } - - - - - _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___,,,_ __.
________ -{ r~: ~~11 VENT COOLER 28} _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ----,-----,-: _____ - - - - { ~~: ~~l)VENT COOLER 2}--- _________________ ---,-----J HEADER 2A HEADER 2A LOWER CNTMT VENT COOLER 2-8 RC MOTOR ___________________ _ _, ___ l
---.- - - - - - - - - - - COOLERS 2-8 a. CONTROL ROD DRIVE MOTOR COOLER 2-B (SAME AS ABOVE)
FROM CONTINUED ON 2-47W611-67-3 LOWER CNTMT VENT COOL ER 2-D RC KITOR 2-471611-67-4 t---.- - - - - - - - - - - { COOLERS 2-D &. CONTROL ROD DRIVE t<<lTOR }- - ------ - - ------ - ----.---I~~lm: RETURN HEAGER 28 COOLER 2-D (SAME AS ABOVE) HEADER 28 TAP FROM WATER COOLER REFRIGERANT LINE INSTR COOLERRM 1 PACKAGE 2A TO ERCW RE TURN HEADERS
- - - - - - - - -1]~~~i:u~~IE~~CKAGE - - - - - - - - - - - --,----
20 (SAME AS 2A) t WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNIT 2 ELECTRICAL LOGIC DIAGRAM ESSENTIAL RAW COOLING WATER TVA DWG NO. 2-47W611-67-3 R10 FIGURE 9.2-7(U2)
XS NOR AUX NOTES: 67-431
1. FOR SYMBOLS AND GENERAL NOTES. SEE 1-47W611-67-1.
OPEN 2. COOLERS ON HEADERS 2A a. 28 ARE SAME AS THOSE ON HEADERS 1 A ,1 1 B EXCEPT FOR THE UNIT 2 ONLY COOLERS.
3. VALVES 1 -FCV-67-127 ANO 1-FCV-67-128 ARE AOMI NISTRA TIVEL Y LOCKED IN THE OPEN POSITION (WITH BREAKER OPEN)(APPENDIX R)
NORMAL VALVES 2-FCV-67-127 AND 2-FCV-67-128 ARE ADMINISTRATIVELY LOCKED OPEN ( WITH BREAKER OPEN J ( NOT APPEND IX R).
4. NOT USED.
RESET
5. 1-HS-67-1238 HAS BEEN DISCONNECTED DUE TO APPENDIX R INTERACTION.
*AUXILIARY 0
<t: u OPEN 1-HS CLOSE
~--~=~*--161-12'-=acc==~--~
TIMER 18 MINUTES EVERY 60 HRS OPEN //,-H~ CLOSE 67-123A FROM PUMPING STATION FOREBAY STORAGE SCREEN WASH PUMP 1 A-A (CONTROLS SHOWN ARE TYPICAL FOR SCREEN WASH 4 f--+----- TO SCREEN WASH PUMP 1 B-B PUMP 2A-A
./4 /4 SEE ET A1 0-47W611-67-1 TRAVELING SCREEN 1 A-A (CONTROLS SHOWN ARE TO ERCW PUMP ' / TYPICAL FOR TRAVELING INTAKE SCREEN 18-8 0-47W611-67-1 \ 7\_SEE SEE DET A1 ~~----"--*; __ ,_N__T_E_5~-----r 1-47W611-67-3 r-------------,
I CONTROL LOGIC I CLOSE I SIMILAR TO I I 1-FCV-67-123 I MDV CONTROL L ---------- ...J OPEN /('HS~ CLOSE 67-205A NORMAL CONTAINMENT SPRAY 1-FCV r-------------, HEAT EXCHANGER 1 B 'i I CONTROL LOGIC I I SIMILAR TO I ERCW SUPPLY TO I 1-FCV-67-128 I AUXILIARY BUILDING L J AIR COOLERS (CONTINUED OPEN :,= rn me,""""" ON 0-47W611-67-5
~ HEADER 18 >---------ii.G:71::,'" I --------f~:J:1:~E,N;/PRAY HEAT EXCHANGER 1A --------',--------< ~~A5~~w,:nuRN HEADER 1 A HEADER 1 A l CONTINUED g~N6!.~~~~11-67-5 FROM 1-47W611-67-3 l-~---~----H~E~A~RE~R~1*~---------------------------------~---------------------~H~E~A~E~R_1~8_ _ _ _ __
L T O AUX. COMP c-s 0-47W611-32-4
~ - - - - - TO AUX. COMP C-S 0-47W611-32-4 LOGIC DETAIL FOR FCV-67-205 &. 208
( REF SHEET 5) UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNIT 1 ELECTRICAL LOGIC DIAGRAM ESSENTIAL RAW COOLING WATER TVA DWG NO. 1-47W611-67-4 R11 FIGURE 9.2-8
(!) NOR z ....., AUX NOTES, 31= 1. NOT USED. QC OPEN 2. NOT USED. C,
3. VALVES 2-FCV-67-127 AND 2-FCV-67-128 ARE ADMINISTRATIVELY Cl LOCKED OPEN (WITH BREAKER OPEN)(NOT APPENDIX R).
w z 1- RESET z
< *AUXILIARY Cl u<
OPEN TIMER I);
18 MINUTES EVERY 60 HRS OPEN ;1/2-H~ CLOSE 67-124,\
FROA PUMPING STATION F'OREBAY STORAGE A TO SCREEN WASH PUW 1A-A
/4 k SEE DET A1 0-47W611-67-1 TRAVELING SCREEN 2A-A (CONTROLS SHOWN ARE TO ERCW PUMP TYPICAL FOR TRAVELING INTAKE SEE DET A1 SCREEN 2A-A, 28-B 0-47W611-67-1 SEE OET A1 2-471611-67-3 2-471611-67-J OPEN OPEN CLOSE I/IN CONTROL UIJV CONTROL ,---------7 I ~:mk ~gc:ic I ERCW SUPPLY TO I 2-FCV-67-128 I AUXILIARY BUILDING ~~R o~~m-l9~~TINUED HEARER 26 HE:ADU 26 l CONTINUED g3Ni!~¥1211-67-5 FROM 2-47W611-67-3 _..J_ _ _ _ _ _ _.,1Hlf;E,QiAR111E;1:R_.2111e.__ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __._ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _-'H"E"'AD"'E'"R-'2"B'------
l s 2-FS}.-----------@-sTART SIGNAL 67-3 6 FROA FAN 0-47W611-65-1 EMERGENCY GAS r-----t,1.0*-----------1 (UNIT ~~~Rsxs RCXJ.t 2 ONLY) TO ERCW RETURN 1----------i TO ERCI RETURN HEADER 2A HEADER 1A B.A. TRANSFER A AFW SPACE COOLER A (UNIT 2 ONLY) _ _ L_________-._
- - - (SAME AS EMERGENCY GAS TRTMT SYS ROCM COOLER A) r---"'
HEADER 2A I r
-------------------------------------------------------------------7 I HEADER 2A CONTINUED LOGIC JS SIMILAR TO LOGIC SHOWN ABOVE CONTINUED ON 0--47W611-67-5 ~~~ws11-s1-3 I l------------"'HE_,A.. E.:R....,2B,_______________-I L ________ _ ___________________________________________________________________ J .1 .""""E"'ADaa*aaR...2..*....,
l WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE FRO.. ERCI SUPPLY TO AUX BLDG AIR COOLERS UNIT 2 HEADER 28
- - T O AUXILIARY CONTROL AIR CPRSR 8-8 (1--471611-32-2, H-4) (UNIT 2 ONLY) ERCW RETURN ELECTRICAL 1I , --------------------,---..)TO ~- - - B.A. TRANSFER._ AFW SPACE COOLER B (SAME AS EMERGENCY GAS TRTMT SYS ROOM COOLER AHUNIT 2 ONLY) - - ---,-- HEADER ZB LOGIC DIAGRAM - - - EMERGENCY GAS TRTMT SYS ROCM COCll.ER B (SM.£ AS EMERGENCY GAS TRTMT SYS ROOM COOLER A)(UNIT 2 ONLY) - - ~
ESSENTIAL RAW COOLING WATER TVA DWG NO. 2-47W611-67-4 R4 FIGURE 9.2-8(U2)
'-' NOTE: z
1. FOR SYMBOLS ANO GENERAL NOTES SEE 0-47W611-67-1.
3' <( 2. SEE ALSO 0-471611-lJ-1. 0 "' J. VALVES 0-FCV-67-151, 1-FCV-67-147 ANO 1-FCV-67-458 ARE ADt.lINISTRATIVELY LOCKED IN CLOSED POSITION AND VALVES 0 ADt.llNISTRATIVEL Y 2-FCV-67-147, 1 ,t. 2-FCV-67-223 AND 1-FCV-67-478 TRAINB FAN START SIGNAL ARE LOCKED IN OPEN POSITION. (WITH BREAKER OPEN) (APPENDIX R). w POWER SEE 1-47W611-65-1 z AVAILABLE (2-47W611-65-1)
4. 1 & 2-FSV-67-168, 170, 188 & 190 HAVE BEEN ELECTRICALLY
<( DISCONNECTED AT THE t.40TOR CONTROL CENTER DUE TO APPENDIX R >- INTERACTION. z 5. 1-HS-67-14JB, 2-HS-67-14JB. 1-HS-67-146B. AND 2-HS-67-146B HAVE <( BEEN DISCONNECTED DUE TO APPENDIX R INTERACTION.
,e

6. POSITION A: TO BE DETERMINED BY FLOW BALANCE TEST.
0 0 <( 7. POSITION B: TO BE DETERMINED BY FLOW BALANCE TEST. FROM :"-:,-'-:'"-,~, {--""~:c:::= -~-------J~l---------------l~~~!f>?lff u 1-47W611-67-4 8. NOT USED. Z- 47 wSll-SJ-Z ---~:-:-':-:,-;'-,-,_ -------S CS PUMP 18 (28) ROCM COOLER (SAME AS CS PUl.4P 1A {2A) ROCJ.I COOLER) 1--------
9. ABANDONED IN PLACE FOR RECIPROCATING CHARGING PUMP ROOM COOLER 2C.
CCS PUMPS & AUX FW SPACE COOLER A UNIT 1 ONLY 1--------
-------S CCS PUMPS & AUX FW SPACE COOLER 18 UNIT 1 ONLY 1--------
CENTRIFUGAL CHARGING PUMP 1A (2Al ROOM COOLER (SEE NOTE 4) 1--------
-------S CENTRIFUGAL CHARGING PUMP 18 (28) ROOM COOLER (SEE NOTE 4) 1-------- -------S RECIPROCATING CHARGING PUMP ROOM COOLER 1C (2C SEE NOTE 9) (SAME AS CS PUMP 1A 1--------
ROC>.4 COOLER) R.H.R. PUMP 1A (2A) ROOM COOLER (SEE NOTE 4) 1--------
-------S R.H.R. PUMP 1B (2B) ROOM COOLER (SEE NOTE 4) 1--------
SIS PUMP 1A (2A) ROOM COOLER (SAME AS CS PUMP 1A ROC>.4 COOLER) TO ERCW 1-------- RETURN HEADERS
-------'i SIS PUMP 1B (2B) ROOM COOLER (SAME AS CS PUMP 1A ROC>.4 COOLER) 1--------
PIPE CHASE COOLER 1A (2A) (SAME AS CS PUMP 1A (2A} ROOt.l COOLER) 1--------
-------S PIPE CHASE COOLER 18 (28) (SAME AS CS PUMP 1A (2A) ROOM COOLER) 1--------
PENETRATION ROOM EL 7J7 COOLER 1A (2A) (SAME AS CS PUMP 1A (2A) ROC>.4 COOLER) r----- PENETRATION ROOM EL 713 COOLER 1A (2A) (SAME AS CS PUMP 1A (2A) ROC>.4 COOLER) 1 I CONTROL PENETRATION ROOM EL 692 COOLER 1A (2A) (SAME AS CS PUMP 1A (2Al ROOM COOLER)
~i2gMV-67-458 -------S PENETRATION ROOM EL 7J7 COOLER 1B (2B) (SAME AS CS PUMP 1A (2A) ROOM COOLER)
I EXCEPT OPEN I ~-+---1-FROt.l AUX. Co.4P C-S I ON LOSS OF I -------S PENETRATION ROOM EL 71J COOLER 1B (2B) (SAME AS CS PUMP 1A (2A) ROC>.4 COOLER) \-------- 0-47W611-J2-4 I TN-B POWER I rcNTROL LOGIC SU,HLAR7 I TO 1-FCV-67-128 I -------S PENETRATION ROOM EL 692 COOLER 1B (2B) (SAME AS CS PUMP 1A (2A) ROOM COOLER) IL ______ _ I U-41ws11-s1-4 ___ J 1-------- r-S_E_E_NO_TE_3--,--< ~~A~~~W ARETURN SPENT FUEL PIT PUMP A-A SPACE COOLER (UNIT 1 ONLY) 1-------- (SAME AS CS PUMP 1A ROOM COOLER)
-------S SPENT FUEL PIT PUMP 8 SPACE COOLER (UNIT 1 ONLY) I------
(SAME AS CS PUMP 1A ROOM COOLER) r------- r------- ,f-------------------------------~ r---CONTROL LOGIC-7 I SEE I 1 ISEE bl 1
rn~rnoL INOTE J ::

r~rnOL I SIMILAR TO rcoNTROL LOGIC SU.4ILAR7 I~fJMf~Mv-61-223 I 6~ I 2-FCV-67-128 I TO 2-FCV-67-128 I 1 z-47W611-67-4 L2-47W611-67-4 ____ J I I I (NOTE 3)
I IL ______ _ I I IL ______ _ SEE NOTE 5
'gfil' TO STATION SERVICE & CONTROL AIR CPRSR CLR A (1-47W611-J2-1) (UNIT 1 ONLY) r CONTROL LOGIC 7 I IDENTICAL TO I TO STATION SERVICE & CONTROL AIR CPRSR CLR 8 (1-47W611-J2-1) (UNIT 1 ONLY)
SEE NOTE 5 TO STATION SERVICE & CONTROL AIR CPRSR CLR C (1-47W611-J2-1) (UNIT 1 ONLY) HEADER 2A ,-*_l_l- - ~ - TO ERCW RETURN HEADER A TO STATION SERVICE & CONTROL AIR CPRSR CLR D {1-47W611-J2-1) (UNIT 1 ONLY) COMPONENT COOLING HEAT EXCHANGER 8 J{
* ' ~*""'~'~"~'~'~'------------~
1~-L e-------------TO AUXILIARY CONTROL AIR CPRSR A-A (1-47W611-J2-2, A-6)
-TCV 7-1051 MAIN CONTROL e--------------, ROOM A.C.
CONDA TO ERCW
-TC RETURN 7-150 HORS.
f-------------1~66ST~:g_eoAROf----t:o:J------~ CONDA r-'--~-~O~P~EN'-i/o-Hs\~C~LO=S~E-----~
~52C -TC 67-105J MAIN CONTROL f - - - - - - - - - - - - - - - - i R O O M A.C.
COND B UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT SHUTDOWN
~------------! BOARD ROOM POWERHOUSE A.C. CON A UN ITS 1 & 2 ELECTRICAL SHUTDOWN LOGIC DIAGRAM ~---------------< BOARD ROOM A.C. CON B ESSENTIAL RAW COOLING WATER TVA DWG NO. O-47W611-67-5 R3 TO ERCW RETURN FIGURE 9.2-9 HEADERS
(.!) ~ z 27A-227C .
s, 6 m
- N < ~ ,,, . Ct: ~~ ~~ R-129 lii ~N C,
-M-27~xs * @s
C, A-- 67 - 67-22C TP-1 w
@ R-129 z
l-1O R-129 1/V R-129 1- - I~ ~ ~ :-------@, I 67-61C z ml_l ,.;;\ @. -r- @. --.!,,. 9
~02
< "\IJ"" I ~28 L-413 PDS
I:
C,
~,-c
-IZI,.J l-413 I L-193 u FT l8J TRAIN A ERCW Pl.MPS I W,,~sio967 i. )>---- I FT L-193
~-129 67-61 @129 I IZI ~0-M-27A y'" ~.---1 1 j--- I/V~-129 I I 21s-129 FM V/~R-129 l/V~-129 POM 7-61E FM R-129 I 7-9FE I 1-s1e POM I 7-9DE I ~~-129 I V/1 R-129 I FM ----,-----!----~---~
TP13-i -t ~-l--_J 7-61A I ~ ~ R-129f-129 TP-2 ~ POS R-129 !.I IL -@" HS 7-9FA -129 129 67-9A
~
TP-15 I R-129 12, I I
--~~ re ffi ~~
O-M-27A ~ 0 0 0l-1O Y22O5A Fl
@ 67-62C I I V/~R-132 V/~R-132 ©l-903 I l-223 FM FM ~~1;i PX _ _J__ FT 7-628 7-620 A 67-62C 67-62C R-132 I I L.!p. ~ R-132 I/V R-132 UD_ __ _. _____ ~ ___ J __ ~ ~ c;jjl FT ~2 ~--~-- 67-62 L-223 NOTES:
1. FOR NOTES AND REFERENCE DRAWINGS SEE 1-47W610-67-1.

2. NOT USED.

3. All UNID PREFIXES ARE "2-" UNLESS OTHERWISE NOTED.
\
WATTS BAR FINAL SAFETY
~ Gu._gi __ ~ ~ /HS'\*~ ANALYSIS REPORT 1
0-M-27A~ y 4 - - ~ - 4C POWERHOUSE ml---l-----~
'\jJ" I ~~ UNIT 2 ~/7s'\~ c;jjl ELECTRICAL ~;B CONTROL DIAGRAM NGS:
ERCW SYSTEM JES JES TVA DWG NO. 2-47W610-67-1 R6
!ES FIGURE 9.2-10 SH A
0-L-202 O-L-202 0-PS ERCW PUMP B-A RUNNING 0-PS ERCW PUMP A-A RUNNING ~ - - ~ S E E NOTE 13 TO YARD DRAINAGE
~ - - - - ' S E E NOTE 13 067-0481 067-0480 LOG FOXBORO 0CS 1-47W610-98-16A, COORD E-7 T3112A ,--------- (FBl.4-98-L916806, CH 3) 1 L 10 1-47W610-98-16, COORD A-3 ------------T---@r*27A - - l-FI r ------- (FBM-98-L906BOJ, CH JJ ~
I LOOIC REF 67-61C : ~U~S1~47~2~8-~FD~-l~X=NS~-O=°'='-~
~~M~A @).~ ~ I I
I I
--~!---©c* 193 I D I
<( _ _ _ _ _ _J A-A u 1-R-128
---------L~--~~ I~
I 1-R-128 27A-2238 ERCW SUPPLY HDR 1 A 0-HS I 6 61 - 2
~------< bob1~ 1~3 67-2881 ~91 1Eill © Lfp. B----~
I __________ : -t---+--PI 0-M-27A 193 @0-M-27A I I 67-29A 67-61IZI ,---- 1-FI 1-R-127 0-PT 0-L-202 ~-M-27© 1-R-127 1-R-1271 67-61 1/1 67-29 O-XS O-PI 0-L-202 LOG I 1/1~ r------- 1-FM __ LOG E3 67-285 67-298 T3113A @ _J 1-FM I 67-61D Y2201A
'"f7 I 67-618 I 1-R-127 --.___ I 0 I ~~,2 1-R-127 I @*FS I
o:: 0 1 ~ 1 -FM 4----~-- NOTE 1 6 I
~ ~: 67-61A ----r-...J 67-61 L __________ _ -+--- ,,'I ~ X§ 'o/
I I I :L_/;~-HS NOTES: ( 1-HS 1 FOR INSTRUMENTS WITH XX-30-XX NUMBERS REFERENCE CONTROL DIAGRAM 67-9A 67-98 47W610-30.
2. THE ESSENT1AL RAW COOL1NG WATER (ERCW) SYSTEM IS A SHARED FACILITY SERVING BOTH UNITS 1 AND 2. THE SYSTEM IS DESIGNED 1-R-1280-M-27A TO PROVIDE AN EMERGENCY OR CONTINUOUS SUPPLY OF COOL1NG WATER 0-PI TO ESSENTIAL PLANT EQUIPMENT.

3. THE PRIMARY COMPONENTS OF THE SYSTEM ARE 8 ERCW PUMPS AND 1-L-143 67-18 67-18A 1-R-128 ASSOCIATED PIPING, STRAINERS, AND VALVES.
I I @27A-223A ~ 4. UNDER NORMAL OPERATING CIRCUMSTANCES COOL1NG WATER IS SUPPL1ED IN THE OPEN CYCLE CO0L1NG MODE TO THE VARIOUS COOLERS OR HEAT
------$'~---- ~;:~ 8 [::J ~ EXCHANGERS BY THE ERCW PUMPS. ~~ 5. ERCW IS SUPPL1ED TO EACH UPPER AND LOWER CONTAINMENT AND CONTROL -L-14J ~~,- ROD DRIVE VENTILATION COOLER THROUGH A THR0TTL1NG ACTION VALVE 1 ~
r - - - - ~1-L-10 ,-, i8n~~f it 0 oelR~ 1 J~M~6Rt 8~~9 l~8§~A t~~G c8~~~~~L~ i~ VE M1~ut~o¢~8t8R B : :;::2c ~ ~~ FOR BY MEANS OF A HAND SWITCH AND/OR LOGIC SIGNAL.
6. ERCW IS SUPPL1ED TO EACH AIR CONDITIONER CONDENSING UNIT THROUGH
-~;R~~N~;;:~------7 ~ !§ A WATER REGULATING VALVE CONTROLLED BY C0OL1NG COIL PRESSURE.
2-47W610-67-1, I 7. IN GENERAL, ERCW IS SUPPL1ED TO EACH COOLER OR HEAT EXCHANGER
\ COORD 8-8 I (OTHER THAN THOSE COVERED IN NOTES 5 AND 6) THROUGH AN ON-OFF I ACTION VALVE CONTROLLED BY A HAND SW1TCH. TEMPERATURE SWITCH.
I MANUAL VALVE, LOGIC SIGNAL, OR A COMBINATION OF THESE.
~--------;,,-------~--------~ ~ I 8. A FLOW ELEMENT IS PROVIDED IN THE DISCHARGE LlNE OF EACH COOLER "WO I OR HEAT EXCHANGER FOR USE DURING SYSTEM BALANCING. BALANCING I IS ACC0MPL1SHED BY SETTING THE DESIRED FLOW RATE THROUGH EACH L________ _ PIECE OF EQUIPMENT BY MEANS OF A MANUAL THROTTL1NG VALVE IN THE DISCHARGE LlNE.
9. FOR DETAILED SPECIFICATIONS OF THE ERCW SYSTEM, SEE DESIGN
!;; CRITERIA FOR ESSENTIAL RAW COOL1NG WATER SYSTEM, WB-DC-40-16.
10. INSTRUMENTS ASSOCIATED WITH BACKUP CONTROL AND MARKED WITH AN ASTERISK ( *) WILL BE LOCATED ON THE APPROPRIATE 480V MOTOR OPERATED VAL VE OR 6. 9KV SHUTDOWN BOARDS. OTHER INSTRUMENTS ASSOCIATED WITH BACKUP CONTROL WILL BE LOCATED IN THE AUXIL1ARY CONTROL ROOM ON PANELS INDICATED ON THE DIAGRAM.

11. HS-67-288. 328. 368, 408. 518 &. 558 ARE DISCONNECTED TO PREVENT SPURIOUS OPERATION OF PUMPS A-A, 8-A, C-A, D-A, G-8 &. F-8 1N CASE OF FIRE.
~--------------------------------~ 12. TRANSFER SWITCHES 1-XS-67-431, -440, 2-XS-67-437 AND -447 ARE LOCATED ON 480V C &. A BUILDING VENT BOARDS 1A1-A. 181-8, 2A1-A MTR-67-440 AND 281 -8 RESPECTIVELY.
e 13. INPUT TO MlCR0BIOL0GICAL INDUCED CORROSION (MIC) REMOVAL SYSTEM SUPPL1ED ON CONTRACT 91NNA-75954A, DWG #BEC 50001.
14. NOTE DELETED

15. REFER TO TABLE A6 FOR ADDITIONAL DIGITAL COMPUTER POINTS (POWER AVAILABLE. PUMP RUNNING. ETC.).

16. 1-FS-67-61 &. 1-FS-67-62 ARE IN LOOP ONLY FOR CONTINUITY.
REFERENCE DRAWINGS: TVA 47W450 SERIES----------MECHANICAL-ESSENTIAL RAW COOL1NG WATER PIPING 0, 1, 2-47W610-30 SERIES-ELECTRICAL-CONTROL DIAGRAM-CONTAINMENT VENTILATION 0, 1 , 2-47W611-30 SER IES-LOG1C DIAGRAM-CONTAINMENT VENTILATION
\ 0.1. 2-47W611-67 SERIES-LOG1C DIAGRAM-ESSENTIAL RAW COOLING WATER 47W845 SERIES----------MECHANICAL-FLOW DIAGRAM-ESSENTIAL RAW CO0L1NG WATER 47W920 SERIES----------MECHANICAL-COOL1NG AND VENTILATING SYSTEM COMPANION DRAWINGS: 1-47W610-67-SERIES 2-47W61 0-67-SERIES 0-47W610-67-SERI ES UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UN IT 1 ELECTRICAL CONTROL DIAGRAM ERCW SYSTEM TVA DWG NO. 1-47W610-67-1 R34 FIGURE 9.2-10
(.!) TO BIOCIDE TRTMT RECIRCN ERCW SUPPLY HEADER 28 r- - z 2-471610-67-3,COORD G-2 I
s,
- N m'< Ct: C, CISP '>c( ):-( L-2S M-6 ~ ),!!.{ FI FE C, [!II '>c( r.(
67-251 67-251 ERCW SUPPLY HEADER 1A w 1-471610-67-1, z }::{ }!{-M-27A~s1-, s01----------,--~cv
- ~ ~ '>c( >;.< ,-.J I ©I 61-101 ~ I- @s- @7 z < I 67 m ~ - M - 27 A 67-66D ~ N N < ~ ~A---7 \ ~ 668
I: 3
- ~
~~ ~ i I ~ ~ ~ 1 0 1 c __ ...J ~,,-r-'\27
~~ ~ Cps* l-+--~cv 67-66 17:i\ 67-66 [;jl I
~6*c___ ...J @ IZI
I ~ ~
l-2~1 TM A ~
~108 67-y13--e13c ),:::( I '>i(CISP 1 A I )-!!(w-6
6
~:~
I M-27A
co P2
@J @ JA
___ _J 7 --+ ~ ~ EMERGENCY DIESEL ENGINE HEAT EXCHANGER Pl L-11~xs r l - ~HSO L-26 I 67-108- s1-1osc MV/1 - 67-100 TIC TM I R 67 67- ~ ~wl t--@ I HS 0-M-27A
~-,o~~-11B 1 67-I0BA TW I ~1ooc~1Do7 I 67-250 };:( r,,( CISP I ~:~ ~ ~M-6 I
I 0-M-27A@ HS I ~ ~@] ~ ~ 67-100A I I CISP };:( r.( 'O-M-27A I L_ ------' 67-20 M-6 ~ },!!.( L-~-~7-111C
©* ~ ~ ~ ~ @]~ ~
Gu_' rxs-,,l-11 '__fiis\ G ~ 0-M-27A@ _ _ _ _ _ .JI I I ~ ~ 92-~92C ~-~~103A I I 0--M-27A l-10 ~103C ~103
~~ :~ :
I t"l-......,.~l~---..J L - 1H 0S ~_ -1 -:"0J ffi-7 I CISP };:( r.( X~SB
M-6 .>E( ~ r----...,;*:....___.J 67-109C 67-109--, I I : ~:~ L_~
~~ O-M-27A~ 67~
[!II ~O-M-27A i ~: ~~ FCV I r~-l-1fHs\l-1D Q9o9A [;jl
~ 67-86 ~ ~ YA &1-103-r-1 i~1'o1~1*01c ~-1 __ ~0-M-27A ~~
HS wi te;' ~I~
~6 ~O-M-27A *-@5c* w ~01A
~ I CISP };:( r.(
i"-+1 M-6 ~ ~ 1 L-~-1 FCV ~ 67-95 [!II~ ~ IZI WATTS BAR FINAL SAFETY rn~L~:s~:UMENT RC04 WATER TO ERCW RETURN HEADER A -471610-67-3, COORD G-ANALYSIS REPORT 1-47W610-67-3, CCXJRD H-POWERHOUSE I UNIT 2 ELECTRICAL TO LOWER COMP CLRS CONTROL DIAGRAM 1-<J7W610-67-2, COORD H- ERCW SYSTEM 18 a. 1D DISCH HDR TVA DWG NO. 2-47W610-67-2 R13 FIGURE 9.2-11 SH A
c.., ERCW SUPPLY z HEADER 1B
""Cl CISP'>c( ~
ERCW SUPPLY M-6 ~ }!!{ LJQi[J_ Cl HEADER 1A w 1-471810-&7-1. ~ ~ COORD B-10 z
~-;:1 >- -M-27A~ 167-107 < ~~~),,<~ ___ XS ---------,--' 0 1-
-z 21 0 i'i
@.i ~-100 I m @ *~** ~ 1.~.~ol ,
N I ;-;;\ 668 -:;i ~*~-, \) y MTR~67-66I : ~~ I \IJ
);,( 'r.-( FCV ~ *___ .JI MTR-67-107 ~ A 0 ~ *.- j_ - -t ---- s1-** !
7C
@.-:c-J @ 0
[81 L-26 L-26 TM jric'\ 67-100 ~ 1 0 0 I I I LER I ____ J EMERGENCY DIESEL ENGINE HEAT EXCHANGER 67-100
~ ~ wil t- ---ffi ~-lO~L-11B ~100C~10o7 ~I~
O-M-27A@ HS 67-100A CISP'>c< )'ji{ M-6~ ~
~~ ~ ~ O-M-27A~S I 67-103A I XS I s1-10, ~ @ Jc ~
MTR-67-87 ~ ~ - 1.~~.1 ~~ I~ I 0 I I L-1~8 -:'\I7 ~ L-10~- XS ---, ~ I MT~-67-111 I I
~109C 67-109 );,( I 'r.< I ~0-M-27A ~IA L_ FCV 67-111 ©r - ~ \:;;,9SA ~@I~~ f /7.s\* 3 ~ L-118 l-lO 0-M-27 A I !;ii XS HS TO HOLDING I li:i] @ D9A IFoL~sl _...J ._I---... ~ ~ j---~87 CISP 67-86 ~ ~ j 67-101~01C POND LJQi[J_
I~~ HEADER A ~7 I }!:.l )!:.(. --1 HS L__ -@O-M-27A ~I~ RETURN U-2 DIESEL HTX
@ac* I ~I~* I"ii-*~
HS l);,('r.-( - 67-86
~_Rs\* ~O-M-27A NOTES:
FRa.t DSL GEN HTX 2B
MTR~67-88 I 67-87C I ~ ).'!.{ y 9 5 ~9-5C FCV ' O-l4-27A~S ~01A 1. REFER TO TABLE A6 FOR ADDITIONAL DIGITAL CCIFUTER POINTS (POWER AVAILABLE, PUliil' RUNNING, ETC.).
---ffi67-88 L;., 67-87A 67 Lf.!i I ~ );,( I ~CISP
wil .--...aaaa..-r-.J... I \.V MTR-67-9
)::.(. I }!:.(.M-6 I I ~I~ L-~- ~0-M-27A ~A~
TO HOLDING WATTS BAR POND FLOOD MOOE RETURN FROM LWR CNTMT FINAL SAFETY VENT CLR Al£ 1-471610-70-3, COORD F-1 ECN 1438 FRCM INSTRUt.ENT ROOM WATER I I 2-471610-67-2. COORD H-4 CHILLER B ANALYSIS REPORT ERCW RETURN HEADER A FROM AUXILIARY BUILDING 1-471610-67-3, RC P~P T.B. AND SAMPLING HTX AND CONTROL BUILDING A/C 1-.2-HW610-67-3. COORD G-1 FROM CONTROL BUILDING AND AUXILIARY BUILDING,......., ~ A/C ECUIPIENT 28 .1. 2-471f61D-67-3, COORD H-2
~.l fROM LWR CNTMT POWERHOUSE TO UNIT 2 \ VE:NT CLRS B.t.D TO TURB DRIVEN AUX FD PMP 2A-S :~~J~l$~~ PUliil'S \ 2-47W610-67-2, COORD H-I UNIT 1 AND MTR DRIVEN AUX FD PMP 28-8 ELECTRICAL CONTROL DIAGRAM .......,...--40-Tw...,,...______________._-+......._l---\~~gfRt:'ffl~~gRN RETURN HEADER B ERCW SYSTEM / FRa.t CONTAINMENT COOLERS ;;o I 87 - 459 RADIATION MONITORING SAMPLING HTX T c::;:N;A,INMENT HTX \ .________________, ~§: 1-471610-90-2, COORD 0- . spry CCMPANIO.. DRAWINGS:
TVA DWG NO. 1-47W610-67-2 R22 0-47W610-67 SE:RIE:S 1-471610-67 SE:RIE:S FIGURE 9.2-11
~; I 2-471610-67 SE:RIE:S <m
(.!) z
s, Ct

C, C, w TO FLOOO t.<<lOE z SUPPLY TO CCS-SS EQPT. ERCW SUPPLY HEADER 28 ERCW SUPPLY HEADER 28 1- - -----11 z 2-47W610-67-2, COORD A-11 0-47W610-67-4, COORD A-8
.1.
< ERCW SUPPLY HEADER 2A ERCW SUPPLY HEADER 2A
I:
C, 2-+7W610-67-2, COORD A-6 0-47W610-67-4, COOR0 A-5 < .1. u c1sr'>c< ~ c1sr'>c;< >ii< M-6):.(. ~ M-6 }!!( ~ M-6 CISPm m l!iJ G R ~~ ~
~~~ HS 0-M-2 ~D-M-27A ~O-M-27A 67-14-lA ~-133A ~-IJBA t----
I FCV I FCV 1 67-133 67-138 I
~~
r--- r--- O-M-27A FCV I IZI I I.iii I I ,,-T
' 61-1,, - o I I I I I I I © I.iii I I fii\ © © '21 TO WASTE ~~
O-M-27A ~ FCV UPPER CNTMT VENT CLRS UPPER CNTMT VENT CLRS ..--r----- *1-12, - o TO AUX BLDG AIR COOLERS 2A 0-47W610-67-4, C00RD A-11 Ml//lw.-336 TM © IZI MV/I~-336 67-1408 INSTRUMENT TM ROOM 67-1378 I WATER VENT I COOLER 1/P I I FOXBORO DCS L-27 2-471610-98-11.COORO H-2 (FBM-98-R124BOJ,CH 6) 2-471610-98-11,COORD H-3 I (FBM-98-R124906,CH 6) CISP'>c( R M-6 ~ I 5~Jg,:~;-FD-2826 W ~~ ~M-27A
~~-~~7 H 67 ~JS 3 L-336 I I L_ CONTAINMENT I SPRAY HEAT I
I EXCHANGERS I 7A HS I 01-1:is,i _ _ _ _ ...JI I I
,£?-I I I.iii I ,----£?-I IZI I~~ I ~~
I __t,;;"\ I __i7s\ 11 _..J,.J i~124B r-----~-1.260 67 VENT
'r.< I I I~~ I ~~
TO LOWER COIIPT CLRS 2A t. 2C TO LOWER CCM'T CLRS 28 ~ 20 )-:{M-27A I I M-27A 11 I I HS 27A ~ HS 27A DISCHARGE HEADER DISCHARGE HEADER (?s'\_ __ lJ @ __ .JJ I- ~O-M- 67-124-A
-@O-M-67-126A 2-47W610-67-2. COOR G-3 2-471610-67-2. COOR G-9 67 67-v 7 7 ERCW RETURN HEADER A ©* ©*
1-+7W610-67-2, COOR H-6 ERCW RETURN HEADER 8 1-471610-67-2, COORD H-6 FRCM ERCW SUPPLY HEADER 28 FOR BIOCIDE TRTMT RECIRCN TO TURB DRIVEN AUX FRCM SHUTDOWN EE ROOM AND FROM AUX A/C EQPT 1A ELEC BO ROOM A/C COND A 2-4-1ws10-s1-2. COORD A-&>---C><f----T--<*~-~*1~*~6~1 o~-~,-~,~-~co~o*§o~H~-~*) WATTS BAR lo 41ws10 s, 4, COOR F 10) ( 47W610 67 4, COOR H 8 I FW PUI.I" 2A-S
.l MCR a. CCS a. AUX FW SPACE CLR A FINAL SAFETY TO ERCW RETURN HEADER B { ERCW RETURN HEAOER A ANALYSIS REPORT 1-4-7W610-67-2, COORD H-5)--f f +------ rn~~~NT .,_,,_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ._1.---------1-<( 2--471610-67-2, COORD H-3>
BIOCJOE TRTMT RECIRCN POWERHOUSE BIOCIDE TRTMT RECIRCN TO MOTOR DRIVEN AUX 2--t-71610-67-2, COORD A-6 UNITS 2 2-4-7W610-67-4, COORD A-1 2-471610-3-3, COORD E-1 TO TURBINE DRIVEN AUX FW PUW 2B-8 BlOCIDE TRTMT RECIRCN 2--t-71610-3-3, COORO H-3 ELECTRICAL 0-4-7W610-67-4, COOR A-1 CONTROL DIAGRAM FW PUt.f" 2A-S TO l.OTOR DRIVEN AUX ERCW SYSTEM 2-471610-3-3, COOR F-1 TVA DWG NO. 2-47W61O-67-3 R17 FW PUMP 2A-A FIGURE 9.2-12 SH A
Cl z MAIN CONTROL ROOM 3' 1-47W610-67-5, COOR A-10 <( Q:'. A/C WATER CHILLER B 0 TO CCS SURGE TANK A 0 0-47W610-70-1, COORD G-1 w TO FLOOD MODE z SUPPLY TO RCW ----JL__J~ ICE CON -------i~ <( ERCW SUPPLY HEADER 1B (UNIT 1 ONLY) ERCW SUPPLY HEADER 18 f-z 0-47W610-67-4, COORD 8-1 ERCW SUPPLY HEADER 1A 0 0-47W610-67-4, COORD A-6 <( u MAIN CONTROL ROOM 1-47W610-67-5, COORD A-9> A/C WATER CHILLER A
~ ~ CISP ~ ~ s:~p ~ ~ M-6 ~ ~ MTR-67-141 ~ ~~
0-M-27A @_MTR @ -M-27A z LOG
~~~~0-M- ~~
y~38A y~41A " i- FD2152 ~ ~27A 05'C ~
I [ill I [ill I ~1278 ~7A- ~127-~1-27C
+--- +----- FCV I 121 I I I I 67-141
I I : I.iii:
I I I I I ~ I
~7 ----1---------------'
I : ~--_J I
© © © UPPER CNTMT TO AUX BLDG AIR COOLERS 1 A VENT COOLERS ~--------------0-< 0-47W610-67-4, COORD A-11 MV/1©-336 CONTROL BLDG A/C AND TURB TM BLDG AIR COMPRESSOR INSTRUMENT ROOM R-130 67-140B WATER VENT COOLER I
22 7A W,R-130 L-27 TEST TEST FM
-122 67-122 'o/
ffi CISP \.V M-6 I
~: I ~: NOTES:
I I 0-M-27A: 1. 1-HS-67-123B WAS ABANDONED IN PLACE BY DCN 54912 DUE TO APPENDIX R I --- CONSIDERATIONS, A I 1 I 2. REFER TO TABLE A6 FOR ADDITIONAL DIGITAL COMPUTER POINTS I (POWER AVAILABLE, PUMP RUNNING, ETC.).
© ----'
TO EQUIPMENT DRAINS LOC II FD2150 -7 MTR-67~126: FCV FCV r-- -+- r---67-124 I 67-126 I I 121
!~~ i~~
I
+--- -@s I +--- -@s 1 67-1248 1 67-1268 VENT VENT I I TO LOWER COMPT COOLERS 1A a: 1C HS 27A DISCHARGE HEADER I:~~ ~ -@0-M-67-124A I:~~ ~ HS -@0-M- 27A 67-126A 1-47W610-67-2, COOR G-2 1-47W610-67-2, COOR H-10 © 7 © 7 ERCW RETURN HEADER A 4 4 1-47W610-67-2. COOR H-6 ERCW RETURN HEADER 8 1-47W610-67-2, COOR H-9 UFSAR AMENDMENT 3 BIOCIDE TRTMT RECIRCN TO TURB DRIVEN AUX FROM AUX A/C EQPT 1A FROM SHUTDOWN BD ROOM AND ELEC BD ROOM A/C COND A 1-47W610-67-2. COORD B-s>-----1:xf---,--- 1-47W610-3-3. COORD H-5 FW PUMP 1 A-S 0-47W610-67-4, COORD E-10>----,,._--<.0-47W610-67-4, COORD H-8 WATTS BAR MCR &. CCS &. AUX FW SPACE CLR A FINAL SAFETY FROM ERCW RETURN HEADER B I ERCW RETURN HEADER A ANALYSIS REPORT 1-47W610-67-2, COORD H-8)-----{./ FROM 2A 2-47W610-67-2, COORD H-3 EQUIPMENT BIOCIDE TRTMT RECIRCN POWERHOUSE FROM COMP COOLING HTX B \
BIOCIDE TRTMT RECIRCN TO MOTOR DRIVEN AUX TO UNIT 2 1-47W610-67-2, COORD 8-8 0-47W610-67-4, COORD E-3 AUX FW PUMPS UN IT 1 0-47W610-67-4, COORD A-11 1-47W610-3-3, CDORD E-1 TO TURBINE DRIVEN AUX FW PUMP 18-8 BIOCIDE TRTMT RECIRCN 1-47W610-3-3. COORD H-3 ELECTRICAL 0-47W61 0-67-4. COORD A-10 CONTROL DIAGRAM FW PUMP 1 A-S COMPANION DRAWINGS: TO MOTOR DRIVEN AUX 1-47W610-67 SERIES ERCW SYSTEM 2-47W610-67 SERIES 1-47W610-3-3, COORD F-1 0-47W610-67 SERIES TVA DWG NO. 1-47W610-67-3 R17 FW PUMP 1 A-A FIGURE 9.2-12
t!) ~ z 3'
- - l u a::
Cl Cl
*.:~.~. ~:2~~~t;---1~~.~---;~~~m~: ~;. ~--! =-~L~.:~;~q-~ ffi--!~-,wil'---~i ~-* li 17 y 5 I 5 \!'.,:5" ~;. ~ I 1
ce-~* e~*.~ 17~~ ~~ ; 8 ~ I 7~:,. ~ : : _ _ _-_ _ _ _
, _, ,. y ---e"' 1 1-MTR-67-147 IZI _< 'j_ ~ -i w - )';;{ }:-( 67-223 I 17-223 O-L-29 , _, * '~- @-*-m 87-222 {UNIT 1 I ~ - -
z 17-1%411 >=-(. A ©3 [ZI I 2-FT ERCI SUPPLY 1-1:lR 1A ... - - ~ 2-NTR-17-147 SUP'PLY HEADER 2B ~- ii!
~--~-l-rcv I i-fcvIZI-~--==-:~=~-*=m
< 1 I 2--rE !1-+1ws10-&1-3, COORD e-1) --- I+ +----.--- I ------------';-+1ws10-&1-J, <XJORD" 12 I ~ ~ 1-z o-+27A *-HS
@~-@
17-+5aA.
,-xs 67-458 1-HS f7-4511C 1--MTR-17-22J (UNIT I)
_ _ ..J
+------+ 2--MTR-fi7-22J (UN_IT_Z_l_ _ _ _ _ _ _ _ _ _ _ _ _ _,j 67-224A }-J~L-===JE~-<~~~-~~~~r---J~
2-471'610-fi7-l, COORO B-12
"<: . ~ !... ~ i
< ~ Sll'PLY HEADER 1A
E Cl Lev,-(;,.. 1-R-
< D-PX u
~ IITR-67-4511 0-M-VA l-R-1215 17- AUX 11..DG AIR CLRS SUPPLY l-l>R IA ~ - ERCWSUPPLYHDR1B Q_-..,---~ 1-471910-67-J. COORD C-1Z + f--<1-1-1n10-s1-J, cocm A-n I ~7~&~
I
~
I CCIIPONENT COOLING SYS HEAT Exat
~ o-N-Z7A ~~ ~~ ~ . ~~~l>-M-ZJA @*17-151C r1--~~ -TS '-?... ,....
L-~Jy1 I I I I
~~
l_/4:;;;\ I r ~ial
!MTR~87-151 © I ifE2 J- o-rcv - <> ,L ___ 7 7 r;;\.67-151 f 11 I ~ 0: I I I I I I I I I I o:li<D_...J I ~ I EltCI RETURN HOit A I 1-47HIO-t7-J. COOIIID H-7 I
I NOTES:
1. NOT USED WATTS BAR

2. 1 AND Z-FSV-67-168 AND 1 AND 2-FSV-67-170 HAVE BEEN ELECTRICALLY DISCONNECTED AT THE KITOR CONTROL CENTER DUE TO u' FINAL SAFETY APPENDIX R INTERACTION. C

3. 1-HS-67-1 438, 2-HS-67-1438, 1-HS-67-1468, AND 2-HS-67-1+68 HAVE ANALYSIS REPORT BEEN DISCONNECTED DUE TO APPENDIX R INTERACTION. 8 FRatl ELEC ROClil A/C

4. 1-Tl-67-308 IS DAMAGED AND INACCESSIBLE AND HAS BEEN ABANDONED IN PLACE. 1-4711i10-67-5, COORD H-11

5. NOT USED COND (LNIT 1 ONLY)
POWERHOUSE MAJ N CONTROL ROClil A/C TD ERCI' RETUll'N HDA B UNITS 1 &. 2
6. REFER TO TABLE A6 FOR ADDITIONAL DIGITAL COIPUTER POINTS (POWER AVAILABLE, Pl.MP RUNNING, ETC.). 1-47HIO-fi7-5, COCJAD F-9 1-47H10-17 5, COCJAD F I 1-479610-&7-Z, COCJAD H-1

7. NOT USED. IATER a-llLLER B IATEA DULLEA A ELECTRICAL TD RETURN tl>R B 10 RETURN HDA A FRatl CONT 11..DG ELEC AM A/C CONTROL DIAGRAM

8. 1-FE-67-224A, -2248. 2-FE-67-224A. AND -2248 PROVIDE BIDIRECTIONAL 1-471&10-47-2, COORD H-1 1-47H10-S7-3, COORD l;-t 1-471110-S7-6. COORO H-t FLOW MEASUREMENT. FLOwt.£TER 1-FIT-67-224 IS CONFIGURED TO DISPLAY ERCW SYSTEM ANO OUTPUT THE SUM OF THE FLOW MEASURED BY SENSORS (FE). FLOWMETER COND ll.NIT 1 ONLY) 2-FIT-67-224 IS CONFIGURED TO DISPLAY AND OUTPUT THE MEASUREl.ENT OF 2-FE-67-224" MINUS 2-FE-57-2248. TVA DWG NO. 0-47W610-67-4 R1 COMPANION DWCS: D-47W610-67 SERIES 1-47W610-67 SERIES 2-47W610-67 SERIES FIGURE 9.2-13
(.!) z AUX BLDG AIR CLRS SUPPLY HOR 28 0-47W610-67-4, COORD A-12 Cl
°"
Cl 0-471610-67-4, w z 1-z -:;i Cl u ABANDONED IN PLACE I I _£1 N .... ~1
"'~ ~ \
z Q
~ § ~ ~ "'u ,= ~
g .~ al !;: X 6
a' NOTES:

1. 2-FSV-&7-188 A 2-FSV-67-190 HAVE BEEN ELECTRICALLY DISCONNECTED AT THE t.t:ITOR CONTROL CENTER DUE TO APPENDIX R INTERACTION.
----f/+------------1----------------11-------.. . . .--------1--------~ ----1,....-1--------------'-------------------.....__________________. . .,__________________ ~
WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNIT 2 ELECTRICAL CONTROL DIAGRAM ERCW SYSTEM TVA DWG NO. 2-47W61O-67-5 R1O FIGURE 9.2-14 SH A
,-------------------7
~27A-225E :
I I $ I
¥I I -FC I AUX BLDG AIR CLRS SUPPLY HDR 18 I r-----~+ ---- --+-------------7 ' I W 67-205 I r;c{ )-;;-( I r;c{ )-;;-(
0-47W610-67-4, C00RD A-12 >-------r-------------------1:Xf-------,---------------------,--------------------- I I 0-M-IZI I >E<~ I ,>E.{~ FROM AUX BLDG ERCW SUPPLY HOR 1 A AUX BLDG AIR CLRS SUPPLY HDR 1A L ~ 0-47W610-67-4, COOR A-10 -~6-0-47W610-67-4. COOR B-12 >----------,---D*:::1--------<~---------------------,~---------------------,,-, ~ @r-2'~* ~ *
~Oss s1-2osA--~20s-~Osc 12]
MTR-67-205
$ @a_" ERCW SUPPLY HOR 1A r __ _j ZS I
I TS 0 I 3 <t: I u TURBINE BLDG~ RECIPROCATING CHG PUMP ROOM CLR I I I 0-TW 0-FE 67-313 0-FE 67-198 67-202 TEST y ELECTRICAL ROOM A/C CONDENSER NOTES:
1. UNIT 1 FSV-67-188 & FSV-67-190 HAVE BEEN ELECTRICALLY DISCONNECTED AT THE MOTOR CONTROL CENTER DUE TO APPENDIX R INTERACTION.

2. NOT USED.

3. CONTROL OF O-FSV-67-1101 a:. O-FS-67-1109 IS SHOWN ON 1-47W610-32-3.
I I UFSAR AMENDMENT 3
---------j/f---~--------
WATTS BAR
------1/1---------------~------------------~-------------------~------------------~ 0-FE 0-FE FINAL SAFETY 67-196 67-200 ANALYSIS REPORT POWERHOUSE TO AUX BLDG ERCW RETURN HOR A TO AUX BLDG ERCW RETURN HOR B 0-47W610-67-4, COOR G-10 0-47W610-67-4, COORD G-10 UN IT 1 ELECTRICAL COMPANION DRAWINGS: CONTROL DIAGRAM 0-47W610-67 SERIES 1-47W610-67 SERIES ERCW SYSTEM 2-47W610-67 SERIES 47W845 SERIES TVA DWG NO. 1-47W61O-67-5 R18 FIGURE 9.2-14
FIGURE 9.2-15 DELETED
188 HTP CENTRIFUGAL CHARGING PUMP 1B-B CENTRIFUGAL CHARGING PUMP 1A-A 188 HTP 188 HTP 188 HTP CENTRIFUGAL CHARGING PUMP 2B-B CENTRIFUGAL CHARGING PUMP 2A-A 188 HTP LUBE AND GEAR OIL COOLERS LUBE AND GEAR OIL COOLERS OIL HX LUBE AND GEAR OIL COOLERS "zm J~ ow z 2-70-556A 1 " SET PRESS. SET PRESS.
> 150 PSIG 150 PSIG LUBE OIL COOLER 1/2' LUBE OIL COOLER 1-CLR-062-0104A-B 1-CLR-062-01 OBA-A LUBE OIL COOLER VENT 1/2" VENT 2-CLR-062-01 OBA-A i~;~ ~i~§ D
<( u FROM ERCW
~------< 2-47W845-7 ='-!--~~==--+--~ COORD C-2 DR SAFETY INJECTION DR PUMP 2A-A 1-1/2" DR DR DR DR DR DR DR CONTAINMENT SPRAY CONTAINMENT SPRAY CONTAINMENT SPRAY PUMP 1B-B OIL HX PUMP 1A-A OIL HX CONTAINMENT SPRAY PUMP 2A-A OIL HX PUMP 2B-B OIL HX r z
r r > z f--_.,..__,f!i~-~!~J ~ w RHR HEAT RHR HEAT RHR HEAT EXCHANGER EXCHANGER EXCHANGER 2A-A
.6. P = 20 PSI 1A-A 2B-B AT 5000 GPt.1 .6. P = 20 PSI l::,,. P = 20 PSI AT 5000 GPM AT 5000 GPM 3/4' DRAIN 1-70-5488
..I SURGE TANK A SHEET 1 COOR H-3 UNIT 1 UNIT 2 NOTES:

1. NOT USED

2. SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT.
THE ALTERNATE ID CAN BE ACCESSED IN MAXIMO AS NECESSARY TO DETERMINE IF PREVIOUS CIDS EXISTED FOR A SPECIFIC COMPONENT.
3. NOT USED.

4. AUXILIARY ADAPTER MAY BE ADDED TO SUPPLY COOLING WATER FROM THE UFSAR AMENDMENT 3 HPFP HOSE STATION.

5. VALVE POSITIONED AS NECESSARY TO BE THROTTLED
FULL OPEN, OR FULL CLOSED TO MAINTAIN REQUIRED CCS TRAIN B FLOW PATH. IF CONTINUOUSLY THROTTLED, VALVE POSITION IS TO BE SET SUCH THAT FLOW, AS INDICATED WITH FE-7D-155, READS NO LESS THAN 289D GPM. WATTS BAR A FLOW OF 2. 725 GPM IS ALLOWED DURING INFREQUENT OPERATION SUCH AS DURING CCS STARTUP TESTING OR DBE (WHEN NON-ACCIDENT UNIT IS IN REFUELING OR COLD SHUTDOWN MODE, IN CONJUNCTION WITH A LOOP FINAL SAFETY AND LOSS OF TRAIN A}.
ANALYSIS REPORT POWERHOUSE COMPANION DRAWINGS: AUXILIARY BUILDING UNITS & 2 0-47W859-1, 1-47W859-2 &. MECHANICAL 2-47W859-3 FLOW DIAGRAM COMPONENT COOLING SYSTEM TVA DWG NO. O-47W859-4 R3 FIGURE 9.2-16
lO" CLASS K I NOTES, Cl ----=~----<I I z 2-70-637 SEE NOTE 5 COMPONENT COOLING 1. THE FOLLOWING LISTED VALVES HAVE BEEN QUALIFIED TO A DESIGN TEMPERATURE HEAT EXCHANGER B OF 250" F PER CALCULATION EPM-GRS-022593. SHEET 1 3' COORD 8-2 2-70-143 2-70-762 2-70-702C 2-70-6788 2-70-760 <( 2-SPPC-067-068~7 Q:'. 2-70-85 2-70-735 2-70-134 2-70-702F 2-70-703 3" 662 2-70-7028 2-70-7228 2-70-702E 2-70-679 2-70-759 0 ERCW SUPPL y I
- I 2-47W845-2 SET ~c_oo_,_
_c_-_1- - ~ 2. SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED ANO MAY DIFFER FROM THE CIDS 0 SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE ALTERNATE ID CAN BE w PRESSURE 150 PSI 1" ACCESSED IN MAXIMO AS NECESSARY TO DETERMINE IF PREVIOUS CIDS EXISTED FOR z 741 A SPECIFIC COMPONENT. <( \'. _____ _ 3. NOT USED f-z 4. VALVES DENOTED AS L.C. ARE LOCKED CLOSED DURING NORMAL PLANT OPERATION. _1_:_..
5. VALVES 2-ISV-70-637 AND 2-ISV-70-661 HAVE BEEN SEALED WITH A FULL FACE GASKET ANO SILICONE CASTING WHICH MUST BE REMOVED PRIOR TO OPERATION.
0 6. NOT USED. <( u THE STRUCTURAL BOUNDARY FOR CATEGORY 1 PIPING IS THE FIRST ANCHORED EQUIPMENT OR PIPE ANCHOR ON THE UNIT 2 SIDE OF THE INTERFACE POINT. BECAUSE OF TEES, SOME INTERFACE POINTS WILL HAVE MORE THAN ONE STRUCTURAL TERMINATION. FOR U1/U2 ISOLATION, THE FLOOR PENETRATION MK#1442 BEYOND ISOLATION VALVE 2-ISV-70-773 WILL BE USED. THERE ARE ADEQUATE SUPPORTS (IN THE GLOBAL DIRECTIONS) TO ISOLATE UNIT 2 PIPING. STRUCTURALLY, TO ABANDONED MAINTAIN THE ISOLATION VALVE PRESSURE BOUNDARY INTEGRITY DURING THE IN PLACE COURSE OF U1 OPERATION. (REFERENCE CALCULATION 70046). 2-70-773 CLASS K + 770 LC TV I f------------~702,
*g 188 "zm HTP C ABANDONED IN PLACE 188 HTP w ~
0 z w V, 2-70-690 2 I' DR 8 8 FIELD CONN TO 1/2" VENT l,r----=c:---------,----1 ERCW RET HOR 8 2-47W845-2 COOR H-3 i:7/'ol.l 2-FLG-70-688 774 2485 PSIG I DESIGN PRESS. L I 650°F DESIGN TEMP OUTSIDE CONTAINMENT INSIDE CONTAINMENT 3106 HTP ERCW TO THERMAL BARRIER BOOSTER PUMPS 1/2" 2A & 28 VENT SH 1 COORD G-6 .,-32 PS I1040 GPM I is TV
~v, ~-" :; ~~ ~o ~~ I THERMAL BARRIER ~
BOOSTER PUMPS (160 GPM @130 FT
~
HEAD) 0 UFSAR AMENDMENT 3
~~ s 188 188 HTP HTP WATTS BAR ~~ ~ 200° F 250° F FINAL SAFETY ANALYSIS REPORT 25o' F POWERHOUSE, AUX & REACTOR BLDG 250° F 200° F UN IT 2 TC MECHANICAL ~~~mJ~~1S~E~TS FLOW DIAGRAM 678C 679 680 3/4" COMPONENT COOLING SYSTEM TVA DWG NO. 2-47W859-3 R35 250 H T P
250 HTP FIGURE 9.2-17
10" 2" 775 6" 8" 1--------Dt---1-/2-'-"----, r-_1_1_,_"----,<. e--~ 3= ~ <( 0-70-61~ u - , u - O U L ~ ~ oc: 0 L .C. 781 SEE NOTE 4 777 2" 0 --w w
THV z NOTE 13
<( 1/2" DR t- 776 z ~--------------7 NOTES: RECIPROCATING _l_"_ 1/2" :
1. THE FOLLOWING LISTED VALVES HAVE BEEN QUALIFIED TO A DESIGN CHARGING DR I TEMPERATURE OF 25D"F PER CALCULATION EPt.1-GRS-022593:
PUMP 1C 730 L_ TO FLR DRAIN 1-70-143 1-70-735 1-47WB52-3 1-70-85 1-70-92 COOR D-2 1-70-702B 1-70-140 1-CLR-62-101 E 1-70-702C 1-70-722B FLOW REDUCI 1-70-702F 1-70-100 ORIFICE 1-70-760 1-70-134 SAMPLE 1-70-759 1-70-6788
~ - ~ - - CHILLER 1-70-762 1-70-679 PACKAGE 1-70-89 1-70-703 22 GPM {SEE ~-~-~ 1-47W625-22) 2. SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME ABANDONED IN PLACE Co.1PONENT. THE AL TERNA TE ID CAN BE ACCESSED IN MAXH.-10 AS NECESSARY TO DETERMINE IF PREVIOUS CIDS EXISTED FOR A SPECIFIC COMPONENT.
3. VALVES MARKED WITH <1}p ARE SAFETY RELATED UNIT 1/ UNIT 2 INTERFACE POINTS AND MUST BE LOCKED CLOSED. VALVES 1-ISV-70-637, AND 1-ISV-70-661 HAVE BEEN SEALED WITH A FULL FACE GASKET AND SILICONE CASTING WHICH MUST BE REMOVED PRIOR TO UNIT 2 OPERAT10N.
THESE VALVES ARE TO BE CLOSED WITH THE HANDWHEELS REMOVED.
4. VALVES DENOTED AS L .C. ARE LOCKED CLOSED DUR I NG NORMAL PLANT OPERATION.
0-FCV COMPONENT COOL ING DR DR PUMP 18 SUCTION 70-111 ~ SHEET 1 COORD D-10 8" 636 TO FLR DRAIN f-------1<1 - 1-47W852-J 1- I! L ABANDONED RETURN COOR C-2 10' FROM WDS 16" 625-22 770 2" 2" {SEE NOTE 13) 1/2" VENT
-EX_C_E_S_S _L_E_T_ -OW_N_ - - -
702F HEAT EXCHANGER 7u LC v TV I 232 GPM ~-----~----~~-------,,-0-.---------------------------------------~ 1,l -- I t :~~~3 8" THV I f--------< OaH---.___ 702 701 3/4" DR SPOOL PIECE 188 188 3/4" DR HTP HTP 689 0-SPPC-067-0558A 20D"F 250°F 3" 688 FIELD CONN TO 2"
~~--------
1 f~ifw~U-~DR COORD H-8 A 774 671 00~ 2" 772 OUTSIDE CONTAINMENT INSIDE CONTAINMENT ~~ ERCW FLOOD MODE SUPPLY 4" 1/2" TO THERMAL VENT BARRIER BOOSTER PUMPS 1A &. 1B SH 1 COOR G-3 11 TV TV TV 0
~
u THERMAL
~ BOOSTER < ( 160 GPM O 130FT ~ " HEAD) 0 r '-' 8u r UFSAR AMENDMENT 2 WATTS BAR FINAL SAFETY ANALYSIS REPORT INSIDE CRANE WALL POWERHOUSE AUXILIARY & REACTOR BLDG UNIT COMPANION SHEETS MECHANICAL 1-47W859-1, 3 & 4 I
I FLOW DIAGRAM 680 COMPONENT COOLING SYSTEM L _______ _ TVA DWG NO. 1-47W859-2 R43 FIGURE 9.2-18
Cl z ~ NOTES: 3' 1. ALL VALVES ARE SAME SIZE AS PIPE UNLESS OTHERWISE NOTED. REACTOR BLDG <( 2. EXPLANATION OF VALVE ANO INSTRUMENT NUMBERS: 0c'. ~~I~ 1 INSTRUMENT 1 PCV 7D 100 CCS RETURN TO COORD E-2 AUXILIARY BLDG. NO. (UNIT) (TYPE) (SYSTEM) (INSTRUMENT NO.) 0 COORD F-10 VALVE 1 70 100 ERCW FLOOD t.lODE THIS SHEET BANDON ED SUPPLY TO S.F. NO. (UNIT) (SYSTEM) (VALVE NO.) 0 PJT.tT.B. IN PLACE w B'STR J. ALL VALVE AND INSTRUt.ENT NUMBERS ON A UNIT BASIS ARE 1-HW845-2 PREFIXED WITH THE UNIT NUMBER I.E. ,(1-) FOR UNIT 1 z ENG SAFEGUARD COORD C-5 ANO {2-J FOR UNIT 2. INSTRUMENTS ANO VALVES CCM.OM TO BOTH UNITS ~ WASTE GAS EOPT 1A PREFIXEDWITH(O-). <( COMPRESSOR SH< COORD A-6 4. MAIN PROCESS SYSTEM VALVES ARE SHOWN IN THEIR NORMAL t- SPOOL SECTION (INSTALL ONLY OPERATING POSITION. z HEAT EXCHANGER ~i WHEN ERCW IS REO D) CL H CL K ALL INSTRUMENT CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED. l[ NORMALLY BLIND FLANGE 225HTP 225HTP SET PRESS. 150 PSIG ALL PIPING AND VALVES FOR CONTAINMENT ISOLATION ARE TVA CLASS B, <( MISC THE REMAINDER OF SYSTEM PIPING ANO VALVES ARE TVA CLASS C,G,H b-SPOOLPIECEO-SPPC-067-0529
EOPT ANO AS NOTED INSTRUt.ENT TAKEOFFS THRU THE FIRST VALVE ARE UNIT 1 THE SAME TVA CLASS AS THE PROCESS PIPING.
SH 1 7. ALL VALVE NUMBERS ON SHEET 2 ARE TO BE PREFIXED WITH 1-7D 0 ANO SHEET J WITH 2-70 UNLESS OTHERWISE SPECIFIED, <( COORD A-1 T ey, 8. VALVES WITH AN "THV" ARE USED TO BALANCE SYSTEM FLOWS TO u THE EQUIPMENT SERVICED.
9. STRAINERS ARE TO BE INSTALLED FOR USE DURING SYSTEM CLEAN
~ j'~f UP ANO REMOVED BEFORE NORMAL OPERATION BEGINS.
1D. THE COMPONENT COOLING SYSTEM DESIGN PRESSURE IS 150 PSIG ANO THE DESIGN TEMPERATURE IS 200'F, UNLESS OTHERWISE NOTED.
11. HTP-INDICATES THE HYDROSTATIC TEST PRESSURE-{PSIG) ~iis1cil~tLNLENTS WASTE GAS HYDROSTATIC 0
COMPRESSOR ANO HEAT EXCHANGER ALL CLASS G PIPING IS SEISMICALLY SUPPORTED. HOWEVER THE AP- 1.5 PSI 050 GPt.l HYDROSTATIC TEST IS NOT WITHIN THE QA PROGRAM. ALL CLASS H PIPING IN THE CDWE BUILDING IS SUPPORTED WITH 47AD59 TYPICALS AND THE PRESSURE BOUNDARY IS NOT WITHIN THE QA PROGRAM. ALL SEENOTE27 PIPING DOWNSTREAM OF TES\" RELIEF, VENT, OR DRAIN VALVES WHICH OPEN TO ATMOSPHERE IS TVA PIPING CLASS G UNLESS OTHERWISE NOTED, AND IS NOT RAO MON WITHIN THE PRESSURE BOUNDARY QA PROGRAM.
~~~NC-6 1J. VALVES ARE TO REMAIN LOCKED CLOSED EXCEPT DURING SAMPLING THIS SHT OPERATIONS.
14. FOR CLASS C* DEFINITION, SEE CLASS C NOTE 4 ON 47B21-1.
ENG SAFEGUARD 15. FLOW CONTROL VALVES (FCV) M"RKED WITH "PD' ARE ADMINISTRATIVELY ECPT1A LOCKED IN THE OPEN/CLOSED POSITION (SHOWN ON FLOW DIAGRAM) SH< COORD A-4 AT t.<<lTOR CONTROL CENTER DUE TO APPENDIX R INTERACTION. 1-70-716 BREAKERS ARE SET IN THE TRIP POSITION TO PREVENT UNAUTHORIZED 3/4"VENT SEE - 1r,4 S~F[C 1-70-514 OPERATION. FOR DEFINITION OF SYMBOLS OF 'LC.' OR 'LO", REFER
" ~~TE 70-3 70-9 0-1 N0~~/-4 ~tf-_.,,._7 f----;-~-"-1~--"-*---{ 1-TW TO MEMO B26850402001.
M M 3/4"VENT 17. VALVES O-ISV-70-524A, 524B, 529A ANO 529B AT THE SPENT FUEL PIT HX CAN BE CENTRIFUGAL ::~n~~LXN8p~~NrnI~~S~5IsJ~E THVa IN THROTTLING TO MAINTAIN SYSTEM FLOW CHARGING PUMP H SEE NOTE 23 28-BLUBEAND fOPT GEAR OIL COOLERS
~~I¥ NOT USED. -F SEE SH2 ~DA-7 0-12 NOTE 23 COORD D-6
19. THIS VENDOR SUPPLIED SKID t.OUNTED EQUIPMENT HAS BEEN DETERMINED TO BE ACCEPTABLE FOR USE WITH THE DESIGN PARAMETERS OUTLINED IN NOTE

10. SEE CALCULATION NO. EPM-MJD-051289 / WBN-70-0053 / MEB-IIBN-70, REV. 0. REFERENCE DRAWING 1-821JJ6-104 ABANDONED REACTOR BLDG

20. DESIGN CRITERIA/SYSTEM DESCRIPTION REFERENCE DOCUMENTS UNIT1 (USE THE LATEST REVISION ON ALL WORK UNLESS OTHERWISE SPECIFIED.
IN PLACE SH2 SEE THE LATEST REVISION OF THE 47B21 SERIES DRAWINGS COORD C-11 "PIPING SYSTEM CLASSIFICATION."), NJ-7D-4D02- - - - -co.1PONENT COOLING SYSTEM DESCRIPTION
21. VALVES 2-ISV-70-516, -574, -587, -705, AND 2-FCV-70-92 HAVE BEEN FITTED
~~~Hu~Ii/~ 6s!~~HolH~~~ ~~~~~E~~~~B~~~ ~~!~~T B~~i~E~H~~~ ~~~~~T E:~~NDS OVER THE VALVE DISC IS FILLED WITH A CASTING MADE OF SYLGARD 170 A & B SILICONE ELASTOMER. PRIOR TO UNIT 2 FUEL LOAD FULL FUNCTION OF THESE ENG SAFEGUARD VALVES WILL BE RESTORED, REFERENCE OCN P-05634.
EQPT1B SH< 22. TEMPORARY CONDITION FOR VALVE UNTIL UNIT 2 OPERATION. COORD A-J VALVE IS ADMINISTRATIVELY LOCKED IN THE OPEN POSITION. (WITH BREAKER OPEN) (APPENDIX R) VALVE IS ADMINISTRATIVELY LOCKED IN THE CLOSED POSITION. (WITH BREAKER OPEN) (APPENDIX R) COMPONENT COOLING OR ISOLATION VALVES 1,2-ISV-70-5448 IS OPEN. HEAT EXCHANGERS ENG SAFEGUARD I~XLi~;;5~t~T~L iA~WRi3;:~~4~P~~ YD3~ I ~~~68Egu~~:~ AP= 20PSI 012000 GPM EQPT2B OPENED IF EMERGENCY SURGE TANK MAKEUP WATER IS SH< COORD A-9 NOT USED TYPICAL CONTROLS FOR CCS LIQUID EFFLUENT (RADIATION) ~ITORS 0, 1, 2-RE-90-12J ARE DEPICTED ON 1-471610-90-2.
29. VALVE IS ADMINISTRATIVELY LOCKED IN CLOSED POSITION. (APPENDIX R)
JD. SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE AL TERNA TE ID CAN BE WASTE GAS ACCESSED IN MAXIMO AS NECESSARY TO DETERMINE IF PREVIOUS CIDS EXISTED C0\4PRESSOR B FOR A SPECIFIC Co.4PONENT. SHl COORD A-1 J1. VALVES MARKED WITH <1ID ARE SAFETY RELATED UNIT 1/UNIT 2 INTERFACE POINTS ANO MUST BE LOCKED CLOSED. 1-FCV-70-207 HAS BEEN SEALED WITH A FULL FACE GASKET AND SILICONE CASTING WHICH MUST BE REt.OVED PRIOR TO ITS USE. THIS SYMBOL ... INDICATES THE COMPONENT MAY BE REPLACED WITH A CO,t,IERCIAL GRADE ITEM IN AN ASME SECTION III SYSTEM IN ACCORDANCE WITHNRCGENERICLETTER89-09. J3. VALVE IS ADMINISTRATIVELY LOCKED IN THE OPEN POSITION, WITH BREAKER OPEN UNIT2 (NOT FOR APPENDIX R). MISC EOPT a-, 34. NOT USED. REACTOR BLDG SH3 JS. CABLES TO THE FORMER MOTOR ACTUATOR FOR 0-ISV-70-206 ARE DISCONNECTED COILED, COORD D-7 AND TAPED. J6. TEl.f>ORARY HOSE TO BE CONNECTED AT THIS FITTING DURING FILTERING ACTIVITIES WITHFILTERSKIDO-FLTR-70-1511. LC DENOTES A VALVE THAT IS IN THE LOCKED CLOSED POSITION. J8. THE FLOW DIRECTION ARROWS ONLY APPLY WHEN THE FILTER IS IN OPERATION. ENG SAFEGUARD SEE TABLE H/r---"-". r'-Dt-~ ECPT2A "A" FOR VALVE SH< CID NO's COORD A-9 REFERENCE DRAWINGS:
~ 0 ~~- L~r~Q~~-1526 47W464 SERIES- - - - - -co.1PONENT COOLING SYSTEM PIPING ~---+<I*-1----<ll *-HoTE " 1-471800 - - - - - -GENERAL PLANT SYSTEM FLOW DIACRAM 1-471610-70-1,2,& J- - -Co.4PONENT COOLINC SYSTEM CONTROL DIAGRAM NOTE JS 2-ISV 47W611-70-1,2,& J- - - -CCMPONENT COOLINC SYSTEM LOCIC OIACRAt.1 1504A 47B601-70 SERIES - - - -SERIES INSTRUMENT TABULATION --1..: 47W859-100 SERIES- - - -STRESS ANALYSIS PROBLEM BOUNDARY 1-471610-90 - - - - -RADIATION t.ONITORING SYSTEM CONTROL DIAGRAM A.t.BSIDE:
E 88~~~~~N~ATER HI LEVEL-EL 770'-10 1/2' 2-0R-070-1527 PUMPS LO LEVEL-EL 768'-4 1/2" BSIDE: LO LEVEL-EL 768'-0 1/2"
~1 ~1 1/2"VENT UFSAR AMENDMENT 3 0-ISV-D7D-05J1A WATTS BAR Q Q FINAL SAFETY COMPONENT LEGEND:
ANALYSIS REPORT COOLING ~ - - - - 1/2" NPT PLUG OR CAP TYPE DRAIN SURGE TANKS TC - - - - - - - - 1/2" TEST CONNECTION (DESIGN PRESSURE: 33 PSIG) TV--------1/2"TESTVENT ~ 1-FC POWERHOUSE 0-75 TABLE A M PO--SEENOTE15 AUX BLDG UNITS 1 & 2 CCS PUMP SEAL/VENT VALVE CID NOS INDICATES MATCH NUMBER bc:Rl VALVE PUMP lA-A PUMP 18-8 PUMP C-S PUMP 2A-A PUMP 28-8 ~-CLEANUP STRAINER MECHANICAL (SEENOTE9) A 1-VTV-70-809A 1-VTV-70-8138 O-VTV-70-817 2-VTV-70-809A 2-VTV-70-8138 1-VTV-70-811A 1-VTV-70-8158 O-VTV-70-819 2-VTV-70-811A 2-VTV-70-8158 FLOW DIAGRAM 1-ISV-70-808A 1-ISV-70-8128 O-ISV-70-816 2-ISV-70-808A 2-ISV-70-8128 COMPONENT COOLING SYSTEM 1-ISV-70-810A 1-ISV-70-8148 O-ISV-70-81 B 2-ISV-70-BlOA 2-ISV-70-8148 SPENT FUEL DESIGN PRESSURE: 150 PSIG (EXCEPT AS NOTED) PIT HEAT DESIGN TEMPERATURE: 200'F (EXCEPT AS NOTED) TVA DWG NO. O-47W859-1 R8 ISLTDENOTESIN-SERVICELEAKTEST EXCHANGERS O-ORV-070-0528A AP- 9PSI 03000 GPM l"DRAIN FIGURE 9.2-19 COMPANION DRAWINGS: 1-471859-2, 2-471859-J a: 0-471859-4
RECIRC LINE TO TO SPENT FUEL PIT HTX 8 TO FLOOR DR 0-47W610-70-1A COOR H-4 UNIT 2 SURGE TANK O-M-27B ~-----<1,2-47W610-70-2, COORD 8-1/C-1 CONTROLS SAME AS ON UNIT 1 ~ ~ ~ ~ dM-2~ ~* 1A B-140 0-M-278 ERCW TO TB BST PUMPS 2-MTR-070-0077 ~ A - - ~16 -~16c 0-P/TR ~~ +I "' (1.2-47'610-70-3, CODRO B-3/8-4) I1-R-140 ~2218-- 70-162POD2 SEE 0-M-278 QB[] 27C-251A m~ TO UNIT 2 ~ NOTE 9 0-HS 4A
~ I~~ ~------~~-4 ~--~-------~--<1,2-47W610-70-2, COOR B-1/C-1 -7 I 70-1948 ~_i __A ~A I L----1 1/1 I ~-t~16B V +---- FROM ERCW ,0, I -LG rn~kA~~AL -7 :
6 ifili-~~------l 70-80 COLLECTION TANK _J.+7 2-MTR-70-16 12] ~1 _g-11B TO FS 0-FS-70-6----
-+-
1 4 I I {1-47W610-70-2 I I 0-MTR-70-194
,-~2C I I I D I I I
<( I _ _ _ _ _ _ _JI II I 2-47W610-70-3A COOR 0-3 u I I I ~-10 ENG SG 2A ~ ~ I ~ ~ ~ ~ ~ ~ m~ DRAIN : I I O-M-278 D-M-278 ~ ~
~- (,a\ ___________________ J I ~222C I I <ft,rM-27B ~~* ~ ~~ ~ ~ 70-2A ~195C~195-~5A ~196C~196-~6A ~~~
L--- IL _ _ _ _ _ _ JI §:a 8c'i lo-L-155 0-PT I.iii i~ ~ i~ ~ ~~ 70-222C ~,_A ~,_A ,1:0
~i~-~ ~--;--~1958 ~~--;--~19-68 ; 9 2-FCV 2-FCV '\D ~ 70-196 ~2C 2 -MTR-~~M-T1R9-;0-196 ~ <' 27C-252D ~--------------~------,
TO ENG SG 28 COOR
~r--:_-=..:i7~___,:;".SA~M°:;P(,Ll~N~G~S~Y~S::Z,ccXJRiJB::;-;;
1,2-47W610-43-2, 8-11 1-L-214 I 2-47W610-70-2 COOR C-3 2 R-129 V/1 2-R-129 0-M-278 TP-14 ~ -~
~~ 1 2-R-129 i ~ B ~ 1 ~ ~ 2 R-129 4 I V/I 2-R-129 0-M-278 9 , .. 1 ___ _. _ _. _ ___Q__ 2 P/TR NOTES:
1. THE COMPONENT COOLING SYSTEM (CCS) IS A CLOSED LOOP SYSTEM A !/~ ~D 0-161 P001 WHICH PROVIDES COOLING WATER FOR UNITS 1 ANO 2 TO:
L.........1 2-RM A. REMOVE HEAT FROM COMPONENTS AND HEAT EXCHANGERS WHICH 2-TM
-:@' 90-123 70-161E HANDLE RADIOACTIVE FLUID DURING NORMAL OPERATION, SHUTDOWN OF THE REACTOR, OR ACCIDENT CONDITIONS.
B. PROVIDE AN INTERMEDIATE LOOP BETWEEN NUCLEAR EQUIPMENT I HANDLING RADIOACTIVE FLUID AND THE NATURAL ENVIRONMENT. MV/1 0-L-486 2. FOR DETAILED SPECIFICATIONS OF THE CCS, SEE: A. DESIGN CRITERIA FOR COMPONENT COOLING SYSTEM, WB-DC-40-15.
8. DESIGN CRITERIA AND FUNCTIONAL REQUIREMENTS FOR COMPONENT COOLING WATER SYSTEM SINGLE UNIT STATION, WESTINGHOUSE S.O. AEN-162.

3. LEVEL IN PUMP SEAL LEAKAGE COLLECTION TANK IS MAINTAINED BY OPERATION OF SEAL WATER PUMPS A AND 8. THE PUMPS ARE 0-MTR-70-51 CONTROLLED BY A MECHANICAL ALTERNATOR WHICH ALTERNATES THE OPERATION OF THE PUMPS AND STOPS AND STARTS THE PUMPS AT THE DESIGNATED LEVELS.

4. ISOLATION VALVES FCV-70-87 AND FCV-70-90 CLOSE IN THE EVENT OF A DIFFERENTIAL FLOW {OUTLET> INLET) IN THE THERMAL BARRIER COOLANT LOOP. ISOLATION IS INITIATED BY FdS-70-81, WHICH SENSES THE DIFFERENTIAL IN FLOW RATES AS MEASURED BY FE-70-BlA AND FE-70-818.

5. ALL TRANSFER SWITCHES, XS. TO ANNUNICATE WHEN PLACED IN AUXILIARY POSITION.
FROM ENGR SAFEGUARDS 28 6. SOME CIDs ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER 2-47W610-70-2, COOR D - 1 1 ) - - - - - - - - - - - , ~ FROM THE CIDs SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE ALTERNATE ID SCREEN (AII) IN EMS CAN BE ACCESSED AS NECESSARY TO DETERMINE IF PREVIOUS CIDs EXISTED FOR A SPECIFIC COMPONENT. f------+--------------------+----<'-.__>---- 7. 1-LS-70-99D IS IN LOOP ONLY FOR CONTINUITY. THE LS PERFORMS ZERO e-M-27B ~ ~ OUTPUT FUNCTIONS.
~~~ 8. REFER TO TABLE AlA FOR ADDITIONAL DIGITAL COMPUTER POINTS @ -M-278 (POWER AVAILABLE. PUMP RUNNING, ETC.). ~~r ~ ~ @i::M-27B 9. O-HS-70-1948 HAS BEEN DISCONNECTED DUE TO APPENDIX R INTERACTION.
c;fit27B ~38A A~~~~ REFERENCE DRAWINGS: I TVA: MV/1 : 1-L-46~*-- ~*r,::( ro{ I "Y" ~*~ 47W464 SERIES --------- MECHANICAL-PIPING DETAILS-COMPONENT COOLING
<2-m,10-10-2, CDORO 8-11nl j I --~14c ~s4C- SYSTEM 47W611-70 SERIES------ LOGIC DIAGRAM 47W859 SERIES --------- MECHANICAL-FLOW DIAGRAM-COMPONENT COOLING ~i ccs SYSTEM I ~**~* PUMP SYMBOLS: ~ ~7G)~~r:~~ I 18-8 1-TE 1-MTR-70-75 -FC MV/@1-L-57 1-TM C)-#- bH~~~~~E~E~~L~i~~F ~~rnR~~~ ~E~Eb~j~~~~~T snR T~H~E DEVICE 70-72 LOG 70-75 BEING SUPPLIED.
70-61 * ----- COMPONENT ASSOCIATED WITH BACKUP CONTROL. COMPONENT FROM ENG SAFEGUARDS 18 '>--------; l -TW [8J FD2310 -:__. i:::;;jjjjl @.: WILL BE LOCATED ON THE APPROPRIATE 480-V ~V OR 1-47W610-70-2, COOR D-9., 7D-l2 _ _ ___, I 6. 9-KV SHUTDOWN BOARD. 1-MTR-70-38 COMPANION DRAWINGS: 0-, 1 - , 2-47W61 0-70-SERIES CCS FROM MISC 1-47W610-70-3, COORD D-10 >-~----------< COOR E-2 ERCW 1-47W610-67-3. COORO A-12 FROM DMNRLZ WATER UFSAR AMENDMENT 3 0-47W610-59-1, COOR E-7 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNITS 1 & 2 ELECTRICAL CONTROL DIAGRAM 1-47W610-98-17,COORDA-5 COMPONENT COOLING WATER SYSTEM 1-47W610-70-3, COORD C-10 MV/1 1-L-57 ~ 0-M-278 (F11,1-98-L907804,CH3)
~ ___ .A LOCICREF TVA DWG NO. 0-47W610-70-1 RS FROM SPENT FUEL PIT HTX A US14728-F0-1.MS-002-I -~o-- ~
I1-47W610-70-2, COOR A-2~ FIGURE 9.2-20
(.!) z a::: TABLE A1A Cl - DIGITAL COMPUTER POINTS Cl INSTRUMENT IO POINT IO DESCRIPTION INSTRUMENT ID POINT ID DESCRIPTION w O-BKR-070-0051 X02101 CCS PMP C POWER SOURCE 1-FCV-070-0089 FD2329 RCP OIL CLR RET CNTMT ISO VLV z 1-FCV-070-0002 fD2165 RHR HX A HDR INLET VLV 1-FCV-070-0090 fD2177 RCP THRM BAR RET CNTMT ISO VLV < 1-FCV-070-0003 FD2389 RHR HX 8 HDR INLET VLV 1-FCV-070-0092 FD2175 RCP OIL CLR RET CNTMT ISO VLV 1- 1-FCV-070-0004 FD2163 MISC EQPT HOR INLET VL V 1-FCV-070-0133 FD2171 RCP THRM BAR BSTR PMP DISH VLV z ...... 1-FCV-070-0008 FD2157 CCS HX A OUTLET VL V 1-FCV-070-0134 FD2325 RCP THRM BAR CNTMT ISO VLV 1-FCV-070-0009 FD2319 CCS HX A ,1;. C OUTLET ISO VL V 1-FCV-070-0140 FD2323 RCP OIL CLR HOR CNTMT ISO VLV ~ 1-FCV-070-0010 FD2161 CCS HX A a: C OUTLET ISO VLV 1-FCV-070-014-3 FD217J EXCESS L TDN HX CONT INLET ISV Cl O-FCV-070-0012 FD2315 CCS HX C OUTLET VLV 1-FCV-070-0153 FD2321 RHR HX 8-8 OUTLET VLV < 1 -FCV-070-0013 FD2311 CCS HX A ~ C INLET ISO VL V 1-FCV-070-0156 FD2167 RHR HX A-A OUTLET VLV u 0-FCV-070-0022 FD2313 CCS HX C INLET Vl V 0-FCV-070-0194- FD2317 SFPCS HX 8 SUP HDR ISO VLV 1-FCV-070-0023 FD2155 CCS HX A .t. C INLET ISO VLV 0-FCV-070-0197 FD2159 SFPCS HX A. SUP HDR ISO VLV 1-FCV-070-0025 FD2153 CCS HX A INLET Vl V 1-HS-070-0038A HD2059 CCS TR-B HS-38A. 2-HS-70-51 A 1-FCV-070-0026 FD2301 CCS PMPS A-Aa:B-8 TO C-S OUT IS\ 1-HS-070-0046A HD2027 CCS TR-A HS-46A 1-FCV-070-0027 FD2303 CCS PMPS A-Aa:B-8 TO C-S OUT IS\ 1-HS-070-0051 A H0-1-001 CCS Pl.MP C-S TR-A HS-51 A 1-FCV-070-0034 FD2299 CCS PMPS A-A TO 8-8 ISO VLV 1-PMP-070-0038 XD2086 CCS Pl.MP 1 8-8 1-FCV-070-0064 FD2305 CCS PMPS A-Aa.B-8 TO C-S XTIE 1-PMP-070-0038 XD2085 CCS PWP 18-8 1-FCV-070-007 4 FD2307 CCS PMPS A-Al:.B-8 TO C-S XTIE 1-PMP-070-004-6 XD2035 CCS Pl.MP 1A-A 1-FCV-070-0075 FD2309 RHR HX 8 RET HOR ISO VLV 1-PMP-070-004-6 XD2106 CCS Pl.MP 1A-A 1-FCV-070-0085 FD4001 CCS EXCESS LTON HX OUTLET VLV 0-Pt.f'-070-0051 XD2089 CCS Pl.MP C (NOR FDR) 1-FCV-070-0087 FD2327 RCP THRM BAR RET CNTMT ISO VLV 0-Pt.f'-070-0051 XD2039 CCS Pt.t.tP C (ALT FDR} O-Pl.F-070-0051 X02038 CCS Pl.MP C (ALT FDR} O-Pl.F-070-0051 XD2087 CCS Pl.MP C ( NOR FDR} SEE SHEETS 1. 2. 3 ~ DWG 45W749-4A FOR ASSOCIATED INSTRI.IIENTATION NOTES:
1. FOR NOTES, REFERENCE, COMPANION DWGS, AND SYMBOLS SEE 0-4-7W610-70-1.
WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNITS 1 &. 2 ELECTRICAL CONTROL DIAGRAM COMPONENT COOLING WATER SYSTEM TVA DWG NO. 0-47W610-70-1A R4 FIGURE 9.2-20A
ccs ~ TO CCS OORD C-1 > (o-47W610-70-1, COORD H-2 I - l rl 0-471¥610-70-1' C
---..__ ~~~-M-278 HS 70-207A CONTROL POWER FUSES )Q: AND THE~~A~AVE BEEN 27C-250E * ~-M-278 OVERLOA TO ISOLATE REMOVED UN IT 2 R-127 I R-140 0-M-27 ! ~~ilR;{cE POINTS. ---+- 1/1@,M ~ dJ REFERENCE 27C-253E ' O- /I -L-30 ~ 70-16513~5A R-131 1Jx 1-45W76D-70-10, MV/I 0-T 70-19 0 ~ µ.:µ_J ~~~~-+--Eb w NOTE 7 7 - ~ 51 -R-130 :
O-M-278 :~1-R-130 ~A : R-131 I __M.__J L-515B~ g'-:;_ 70~~. -
<@--t-~r FT -~- 70-165A I ~: @--+ I -M-278 : 70-165@.AI -131 I I I C-252E I l -R- ' '1 : 5A 0-M-278 ~I V-- 0-F I 0-F I BA!9N5 1 70- I L-259 @--t--- 70- _J 1
C-249E I 1-R-127 I 0-F I N -- - I I
-- ~ lQ ~
c:it278!
~O-M-27B L-10 7I ~@slQ r--~
_M 70-38 : * ~145 ~ 1 3 0 L~165C~~' I ~
<!B--t--~S L-335 ~ 3 L+-~3 ~ lQ -130 FT o L__ 17 -145 I
0-47W610-70-1. ccs FROM HX C COOR C-11
!L ~-3© @*
FOL203G20 I R-130 R-142 8- R-142 UNIT 1 ONLY
~ @ ' 45 4A ~ , ~+'A a-g:7C-248A R-142 I 0-M-278 L-2991~'-@I FT 70-164A l 7~~164A+ I 70-164A ~
TO REACTOR BLDG
~~____::__~ '- 1-47W610-70-3' COOR A-2 TO FLOOR DRAIN AREA TO BE GAS STRIPPER &. BORIC ACID EVALUATED FOR EVAP PKG A ABANDON IN PLACE REFERENCE PER 321930 27C-247A
___QHi[J 7:B.D NIT 1 ONLY 0-M-278 R-125 V-: Fl
----,-- 70-190 -~~ O I 0-HS I
27C-2478 70-111~
R-125
~\f' UNIT 1 YM-278lQ P, <!B--t- 70-173 R-142 ONLY 0 MTR 70-1111 -@
L-46 FS I 0-HS 70-190 8__ I A_~N3 I TM 70-1 I
-+-- 70-1118 70-173 UFSAR AMENDMENT 3 ~191 ;-M-278 L-349 1@I R-125: 0@ ~--+- 70-191 V-: I ~191 s& FM -+ - 70-184 I -125 I J
IN PLACE POWERHOUSE UN IT 1
~~:7W610-70-3, COORD D-10 ELECTRICAL M FROM CCS HOR 1-MTR-70-183 1-47W610-70-3' COORD C-3 CONTROL DI\~\\R SYSTEM COMPONENT C001L-\N?W610-70-2 R37 1-47W610-70-3, COORD D-11 TVA DWG ~~CURE 9.2-21
TO CCS PUMP 2A I. 28 (.!) z 0-471610-70-1, COORD 0-2
s

- SUCTION < ABANDONED IN PLACE a::: C, C, w z TW 70-213 1-z
I:
. .l I C,
u 2-471610-98-16,COORD G-9 (FBM-98-L916C06, CH 8) FOXBORO DCS OGIC REF. 2-471'610-98-12C,C:OORO B-6 BF802403-FD-2975 I (F8M-96-R142D04-.CH 5) FOXBORO DCS FOXBORO DCS I ff~!;~~Rf!2~~~:g.xi;~ B-J 2-4-71'610-98-12C.COORO B-6 2-471610-98-12C,CXXlRD B-6 O-M-278 FOXBORO DCS r- (FBM-98-R142004,CH 1) (FBM-98-R142004,CH J) I f~!~~~~~21~/~)B-IO -, I 2-4-71'610-98-12C.COOR B-3 2-47W610-98-12C,CXXlRD B-3 I LOGIC REF ~I MV~IL-+J (FBM-98-R1420DJ,CH 1) (FBM-98-R14200J,CH J) I 08f802403-FD-284J &f 2-471610-98-16,COORD C-9
*--* 2F~:1~-~98o;:o~tH 053 _A (FBM-98-L916C06. CH 7) TM trt::~~R~~-;b~i~~) 8-10 --,
2-4-71610-98-12C,COORO 8-10 I 270-255E l 1 r----------- 1
-~64C l,~~:=i- c'~:~=*-14_2_DD_7c.. ,C_H_4.c.l- - I - I OCIC REF. 7o-l 5+ 1-,L~OG=1c~RE=F--'--'----I ;l; I -~1 8F802403-F0-2974 08F80240J-FD-284J ~I I ~°J I FOXBORO DCS I ~08F_802_40_3_~_D-_2_B<<
_ _ _~ *l L------------- L 2-47W610-98-12C,COORD B-6 l-16 CFBM-96-lt142004,CH 61 CCS FRCIJ HX C ~-!J ~ __tJ 2-47W610-96-12C,COORD B-J liiiil (FBM-98-R142DOJ,CH 8) 0-47W610-70-1, COORD A-10 2--471610-96-12C,COORD 8-10 FOXBORO DCS liiiil 2--47W610-9a-12C,COORD 8-6
,.,~~:-=i-c'~:~=*-"-'_oo_,_,c_H_,_,_ _, - -~7 y____._______,SL-496 O-M-27B lfBM-98-lt142D04,at -41
(]8='802-403-FD-2843 ~l 2--47W610-98-12C,COOltD 8-3
~ m ~ m (FBM-98-ft1-42DOJ,at -4) 27D-25"° J,I m ~~ ~ ~ ~ 2--471610-98-12C,CllH> B-10 ~--~-' @-M-27B ~ *A ~ ,_~-:--Ic-'-:;-~-14-20_0_7,_CH_O_l--I ~
y53C y153A r----------------- 1
~+A ~4C ~0_BF_OD_2_40_3_~_D-_2_M_3_ _~ ~1 L_~ s _J 70-153 27D-257D J, I L ~ __ J FOXBORO DCS ! FOXBORO DCS ~4 2-471610-98-128,COORD E-3 0-M-27B L 2-47H10-96-12C,COOltD B-6 O-M-27B EfJE-°J (FBM-98-ft142C01,CH 6) <fBM-98-lt142D04,CH 2) ~~~~--!
I ~ ~ 2-471610-98-128,COORD C-2 '\.!._T I
~ (f'BM-98-ft142C03,CH 6) I 2-471610-98-128,COORD C-7 I (FBM-98-ft142C07,CH 2) --<7 FCV ___ J LOGIC REF 70-153 70-4 ~~~~2~~-F0-2845 ~l 08F80240J-FD-2843 filf~---@
IZI TO REACTOR BLOG 27D-254A
~
ll 2-471610-70-3, COORD A-2 ~--:J 0-471610-70-lA, COORD H-3 ccs
._,....________________________________...,.-+! I FROM SURGE TANk A COIi' 2B 70-72 ERCW ~i",- -~--~-R---<(0-47161D-7D-1, COORD E-2) 1 0-M-27B 4,. MV~-46 ~-47W610-67-3, COORD B-1~ 5 @, --4--~,2 L-575 I@R-129 \t.~-129 FT FM FM IZl70-215AIZI ~ ~ 7x R-** 9 70-215AE 70-215A IN PLACE -+--@. ~ ~
FCV . ~ l!,, @129 L fo't ~-*-21* ABANDONED IN PLACE - -r-~2i - - y-7S ~A FOXBORO DCS 3 2-471610-96-12B,COORO E-3 ,-MT:~~:~: 15 70-21S NO:: \,,,---,txx:J,----, (FBM-98-R142C01 ,CH 3 I 1 70-218
~
I ~70C I I GAS STRIPPER a. BORIC ACID ~~ I EVAP PKG B I NOTES I W/I L-349 I ;::::J*~o!E]xe~o:*o[]oc~s[:::~ 1. NOT USED. J r- fF:.?::!~;;:5~~~:~~~ e- 7 2. NOT USED.
-@------ TO FLOOR I 1-,-_.-,.-.-,0--,-.-_,-,.-.-COORO--,-_-,0-1 DRAIN 3. FOR LOOP POWER SUPPLIES SEE CONTRACT 71252, owe OBF826663-RL-2101. ~ r---- __ _J (FBM-98-R125E06,CH J) O 176 270 259A
4. FOR LOOP POWER SUPPLIES SEE CONTRACT 71252. DWG OBF826663-RL-2201.
2-47W610-98-12B,COORO E-8 - ~ 0-M-27~8 FI ..,c,=-=-*=*-="-"-*-'°-'c...*c_*_*.c.l_-l~~,76~ 0-190 LOGIC REF 08F802403-FD-2BJ6
..---,,,.,o"'xoo=*"'o""o"'cs,,,_--,
te,,-_,,.,,"'""'1o='-""**:"-"°1,e::e".COOR""""o""e"-,:-i I (FBM-98-R125EOJ,CH 2} 2-471610-98-128.~D E-10 _j FOXBORO OCS (FBM-98-R125E06,CH 2) 2-47W610-98-12A,COORD E-2 TO FLOOR L(X;IC REF (FBM-98-Rl zimo, ,CH 1) DRAIN 08F80240l-F0-28J4 2-47W610-98-12A,COORD G-2 (FBM-98-R12500J,CH 1) 2-47W610-98-12A,COORD G-8 N N (FBM-98-Rl zimo7 ,CH 1) r _________________ ( - ~ F M(+)_ _.J
' ' LIEIC REF 70-215D 08F802403-F0-2Sl 1 6 J I ~ m ~ ~ R-129 IIJ U> Ill u, WATTS BAR v-s@-12* HS O-M-27~xs * -@s * ~,~~ ~ 5~ 5 ~=
r- 2-4-71610-98-128.COOR B-7 FM 70-1 SJA - 70-183 70-183C
<t8--+ r FOS FINAL SAFETY ! (FBM-98-R125EOJ.CI-I 4) O-M--27B 70-2158 7D-215A I 2-471610-98-128,COORD E-10 -@I R-12~ I ANALYSIS REPORT I (FBM-98-R125E06.CI-I 4) r--, 70-181 I I ----- FDS _.J I r---------------J ~-291 1 ,_,,..10-,.-1,*. COORD ,_. ~ 2* 10-2,. 1 m I (FBM-98-R125EOB.CI-I 7) --7 FM j -...
a I FOXBORO DCS I t-r ~ POWERHOUSE
'Y182 I LOOIC REF ~!I R-12~ 70-215BE ------------ '- fF~!:J~R~:z~r~;~ E-J D-M-27B 1 D8F8024-03-FD-28J7 o a' ~
2--47W610-98-128,COORD G-2 i,..-@l ccs I I 27D-255A 1 1
@ -t UNIT 2 (FBM-98-R1-42COJ.CH 2) 70-191 27D-2608 -+7W610-70-J, COORD D-1 ~...~ "' ELECTRICAL N
2--47W610-98-12B.COORD G-7 (FBM-98-R1-42C07.CH J) 1-----~ l-TS-?O-l 9~
~--.J NOTE J ..- FT L - 0 70-2158 2-MTR-70-183 CONTROL DIAGRAM LOOIC REF IZI 0BF802400-FD-2Bl2 ~ COMPONENT COOLING WATER SYSTEM TVA DWG NO. 2-47W61O-7O-2 R17 FIGURE 9.2-21A
(.!) z
s, Ct

C, C, w z 1-z
I:
C, u CCS FROM HX 8 0-+71610-70-1, COORO B-10 FOXBORO OCS FOXBORO DCS
.. 2-+71810-98-12 COOR0 E-3 .. 2-471610-98-12 COORD E-3 (FBN-98-R124-F01 ,CH 2) r (FEll-98-R124FOl ,Dt 4) 2-+71610-98-12 COORD E-5
_ZS I (FBN-98-R12+F03,CH 2) ff~~:~~;;:.~g3,~:~ E-S ~ 2-+71810-98-12 COOR0 E-10_ (FBN-98-R124-F07 ,CH 3) F
~1 I I 2-471610-98-12 COORD E ( FEll-98-RI 24F07, Dt 5) ~* ~7 FS:70-1477 S:io-Ts"il LOGIC REF r.k-, I LOGIC REF r.k-,
08F802403-FD-2841 08F802 03-FD-2839 I
~ I t:&tJ 27D-256E 27D-25-4-E I
I fOXBORO OCS I 2-471610-98-12 COORD E-3 . _J (FBM-98-Rl 24F01,CH 3)
~ 0-M-27 B E-~ '2tS__ - ~;~::~;;:;~i.w:~
7~ FOXBORO DCS _ 2-471610-98-12 COORD E-10 FOXBORO DCS ~o r..:,0-150 (FBM-98-Rl 24F07 ,CH 4) 2-47W810-98-12 COORO E-3 (FBM-98-RI 24F01,CH 1) r.k-, LOGIC REF t;-~m;1:.n1 _g~~ E-J i-- t---~
- 08F802403-FD-2840 fu 2-471610-98-12 COORD E-5 IEftj & _ 2-471610-98-12 COORD E-5 ,~-- CfBM-98-RI 24F03 ,CH 1 l lfBIH8-R124F03.CH 5) MY/I(;;\ L-57 E3 270-256D 7~ E3 ,_ 2-471610-98-12 COORD E-10 _ 2-471610-98-12 COORD E-10 r.s=io-,se "1 (FBM-98-RI 24F07 ,CH 1) ~s=,0-1..6 lfBM-98-R124F07.CH 6) Yo r---.k-, I LOGIC REF LOGIC REF 08F802403-rD-2842 r.k-, 08F802403-FD-2838 I t::&w I t::&tl 27D-258D I 27D-254D I TO CCS Pl.MP 2A-A I
0-47W610-70-1, COORD C-1 ffi---J---------------------------------------------------------------7~ FROM SURGE TANK 8 COMP 2A 0-471610-70-1A, COORO H-3
~ ~ ~~156 ~ ~
o-M-27B IZI~ (es\* y156A r-.-~ y156C L__________ /7s'\ ______ J THIS DRAWING HAS BEEN DIVIDED AND
~'ss PORTIONS OF THE DRAWING ARE ON 2-471610-70-J.
WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNIT 2 ELECTRICAL CONTROL DIAGRAM COMPONENT COOLING WATER SYS TVA DWG NO. 2-47W610-70-3A R11 FIGURE 9.2-22 SH A
CCS FROM HX Cl 1-47W610-70-2, COORD D - 3 1 > - - - - - - - - - - - - - - - - - - - - - , LOG z 3' <( Q:'. 0 0 w z <( f-z 0 <( u 27C-241 D
~ ~~~
@ -M-278 I 46 I
1271 L-335 s+---e> -127 FM FT 1a-14sr-1 -,46
& I El r;';\R-127 ~46 X
I R-131 {2j
~810 +------<1-47W610-70-3, COOR C-1>
I TO ERCW I NOTES:
1. SWITCH LOCATED ON 480V MOTOR OPERATED VALVE BOARD.

2. 1-HS-70-898 HAS BEEN REMOVED TO PREVENT A CONDITION ADVERSELY AFFECTING THE SAFETY FUNCTION OF ASSOCIATED VALVES DURING AN FT L-176 A_ ACCIDENT. ASSOCIATED XS 1-XS-70-89A NO LONGER NEEDED.
FT L-351 A_. 3. REFER TO TABLE A1A FOR ADDITIONAL DIGITAL COMPUTER POINTS FT L-351 ~ 70 _ 1 ~ ~ 2 5 : ~-210 70-119 R-125 L!.p 0-M-278 (POWER AVAILABLE, PUMP RUNNING, ETC.). _,-~ I __@ 4. FS-70-159A IS IN LOOP ONLY FOR CONTINUITY. 0-M-278 0-M-278 0-M-278 5. 1-HS-70-156B HAS BEEN DISCONNECTED DUE TO APPENDIX R INTERACTION. 0-M-278 Px R-125 FS R-125 Px R-125 FS R-125 @ 24 Px R-125 FS R-125 70-128 70-128 15 5
~-~~28 R-125 ~_&_,
70-119
&-~~19 R-125 70-119 05 ~4@:'" 70-108 70-108 278-2398 R-125
((:TIJ-~4_._ ___ _
~~' --,...~ FM ~ANN ---,...~ FM ~ ANN [""ANNl ~ ~R-125 I I 70-124 8-114 [EIQ}J-~54----- I 70-115 _
9 62 CEill"-~s_._ I ___ _
--,... 70-105 iANNl I :~:8 I @5 _1_ __ _
278-2408 I ~
'W I 27B-240C R-125 278-2378 'W I 278-237C R-125 278-2388 'W I 278-238C R-l ZS L_______ T ,4 L_______ ...,...~ L_______ _,_- ~
1 ~15 TW I TW I .~5 I I TW I ~--<~If~ 70-123 I I 70-103 : I I I I I UFSAR AMENDMENT 3 I I I I I I I I
L-351
-------- p WATTS BAR Px R-123 FE FT 70-126 70-105 70-105 FINAL SAFETY 0-M-278 [gl ANALYSIS REPORT Pd!
r.k--i 70-126 tE:J:m POWERHOUSE 278-240A UN IT 1 ELECTRICAL CONTROL DIAGRAM COMPONENT COOLING WATER SYS TVA DWG NO. 1-47W61O-7O-3 R21 FIGURE 9.2-22
t!) z 3' a:: Cl Cl TO ERCW w 1-471610-67-2,COORD H-4 z 1-z FOXBORO DCS < ~1
E 2-471610-98-12A..COORO B-7 0-M-27B Cl ABANDONED IN PLACE ~B----- (Fl:N-98-R125CDJ,CH 3) -@
2-471610-98-12A..COORO B-10 < R-132 (Fl:N-98-R125CCM,CH 5) 8 u 2-471610-98-12A..COORO E-8 ~ 27D-261E -@-12~R-129 FM
~ rs rs (FIN-98-R125eo1 ,cH 51 TS-7o-=88~ ~- 70-81A - 0-81AA 70-810~32 lfL"'OG"'I"'c"R"E"'F-~-~--1 210-2s1 o 08F802403-FD-2829 -~32 0-M-278 I L-293 2 NOTE 8 Q_ v~-129 I R-12~/V@r'29 FT ~--~--,- 70-81A - 0-81AE--r70-81A tR-129 I IZI I.iii TP/6 (effj-129 PX 75-Rl 29 NOTE 7 CISP>c( }ji(
M-6}:.(. },:!.{
~~
O-M-278~5 FOXBORO OCS 70-90A
.. 2-47W610-98-12B.COORD E-3 O-M-27B (FBM-98-R1+2C01,CH 5) ~ ~ IE]
rF:~:J~;r:2J~t&°°:? G 6 2-*7W610-98-12B. COORD G-7 ..I::M[J ~or~o~---r
};,( ~ }j;'(CISP }::..(M-6 (FBM-98-R1+2C07 ,CH 7)
LOGIC REF Ts-10-=si--r:::Eru 270-26JE
*~~- I 08F802403-F0-2828 ~ ~~ ~ ffi-1--ffi '-M-27B 2-70-705 >i:< r.(CISP ),!!{ },:!{M-6 I.iii ~y+* ~y+A ~ ~
FOXBORO DCS ~~ FC:V I ~ 2-71610-98-12B.COORD B-7 NOTES:
*f7s"\ 1/Hs\ 0-M-27B I O--M-27B~S (FBM-98-R125E03,CH 5) 1 10-134 7---~4-~4c M V L-29 ~I FOXBORO OCS ~ 70-87A 1. NOT USE:D 2-71610-98-129.COORD E-10 (FBM-98-R125E08,CH 5) TM .. 2-471610-98-120.COORD [-3 2. NOT USED O-M-27B I - -@+
2-71610-98-12B.COORD E-6 70-91 (FBM-98-R142C01,CH 4) ~ ~ 13 3. NOT USED
~ @~@ I (FBM-98-R125E08,CH 8) T~~o-u"'(E[J 2-471610-98-12B .COOR0 G-2 -@ 4. NOT USED LOGIC REF (FBM-98-R142C03,CH 4) - 1 I I 27D-263D 5. NOT USED 08F802+03-FD-2834 2-471610-98-120.COORD G-7 ~ *@c-~---r I1.... _ _ _ _ _ _ _ _ _ _ _jI (FBM-98-R142C07 ,CH 5) T s-10-=-s1 i:::EEJ 6. NOT USED I
LOGIC REF 270-2620 08F802+03-FD-2829 I 7. FOR LOOP POWER SUPPLIES SEE CONTRACT 71252, DRAWING 08f'82&663-RL-2101.
@~@ 8. FOR LOOf' POWER SUf'f"llES SEE CONTRA.CT 71252, owe 08Fs2&&6J-RL-2201 FOXBORO DCS FOXBORO DCS FOXBORO DCS FOXBORO DCS FOXBORO DCS FOXBORO DCS ,. 2-471610-98-128.ClJORO B-2 2-+71610-98-12B.COORD B-+
0-* - 7 lr~!:~~f:sJ5t&~~ 0- 2 ~7 (FEIM-98-R125EOI ,CH 5) o-M-278 fr~~:~~R~:5~~t~:~ e-2 -7 (FBM-98-R125E02,CH 3) r-,. tr:t::J~R~:s~~:. ~~ B- 4 D-t.4-278 fr~!:J~f:sJ~t~:~ - 7 _ 2-471610-98-12B.COORD B-11 _ 2-471610-98-12B.COORO B-9 2-471610-98-128.COORO B-9 Gu___ 2-471610-98-12B.COORD B-9 _ 2-47W610-98-12B.COORD 8-11 2-47W61D-98-12B.COORD B ~ I I ~ I I
& (FBM-98-R125E05,0i 4) 7@8 (FBM-98-R125E04,0i 3) (FEIM-98-R125E04,CH 5) ~ 7~ (fBM-98-R125£04,ctl 4) ~ FBM-98-R125EOS,CH J) (Fl:N-98-R125ED5,CH 5) ~
7~ I I I I
,_ 2-471610-98-12B.COORD E-6 _ 2-471610-98-12B.COORO E-8 ~ 2-+71610-98-12B.COORD E-6 2-471610-98-12B.COORD E-6 _
r.S:10-125 (FEIM-98-R125E08,0i 4) I IFS:f0-11 6 (FBN-98-R125E07 ,Di 31 I tr::::~;~:;J~:~~ E-a F S:10-T1il IFS:iO--Toi fi'~~:~~ft~:5~~--~:~ E-ll I lrS-70:S 6 (FBM-98-R125E08,CH 3) I (FBM-98-R125E08,0i 5) F5-7Q:Sel r.!., LOGIC REF 08F802+03-FD-2835 I LOGIC REF 08F802+03-FD-2835 I LOGIC REF 08F802+03-FD-2835
~* r.k--, LOGIC REF 08F802+03-FD-2835 I r.!., LOGIC REF 08F8024DJ-FD-28J5 I LOGIC REF D8F802403-FD-2835 ~
ANN I I 5 ~-------~ I I
~ ~ ~ 9-108 270-264C I ~
27D-261C I 270-261C 27D-262C I 270-263C I 27D-263C REACTOR COOLANT PUMP 4 REACTOR COOLANT PUMP 1 REACTOR COOLANT PUt.P 2 REACTOR COOLANT PUMP J FOXBORO DCS FOXBORO DCS 4 D-M-210 0 2
r. ~;~~:J~~:;~~::~:~ e- r .. ~F~~=~~~:5~~~:~~ -
I 2-471610-98-128.C<XJRD B-11 ~~I I 2-471610-98-12B.COORO B-9 ~ I (FBM-98-R125E05,CH 6) 70-128 I (fBM-98-R125E04,ctl 6) -~8 I 2-471610-98-12B.COORO [-6 I 2-471610-98-12B.COORD E-8 I (FBM-98-R125E08,CH 6) FS:10-T2ii1 I (fBM-98-R125[07 ,Qi 6) "FS:10-Toil I LOGIC REF ~ I LOGIC REF I 08F8D240J-FD-2835 ANN I D8F802403-FD-28J5 r.!., THIS DRAWING HAS BEEN DIVIDED AND PORTIONS OF THE DRAWi!<<; I 9-114 L-191 I ~ ARE ON 2-471610-70-JA. I 27D-264C -----' I 27D-262C L ____________________ _ ~ _________ _J I ~ I _________ j FOXBORO DCS FOXBORO DCS
- - - - - - - - - - -
f;~~=~~;~:;~~~. ~~ B-l D-M-278 lr~!=~~~:s~Jt~:~ e-4 o-M-278 2-47W610-98-12B.C(X)RD B-9 ~
2-471610-98-128.COORD B-11 ~ (FBM-98-R125E05,CH 2) 4 f;('-'FIM'=,;-9-'8-='R-'12::5=:ED,.;4'-',CH=2=)-=-,-(- ~ 5 2-471610-98-128.COORD E-6 (FBM-98-R125E08,CH 2) FS:10-1241 1,'f'-'F~::7. .a~="'~~"";=~:"';"'~~"'*"':~:::..:~a:.>_*_-*--1FS:1'ii-To5l l,'L':,OG:,:I,::C-',R,:E':,'F===~--t r.k--, LOGIC REF ~ 08F8D24DJ-FD-2835 08F802403-FD-2835 ~ 7 6 27D-2628 WATTS BAR 27D-2648 FOXBORO DCS FOXBORO DCS FOXBORO DCS FOXBORO DCS
., 2-471610-98-12A..COORD 8-5
2-471610-98-12A.COORD B-2 L-351 ., 2-471610-98-12A.COORD B-2 B-5 L-191 FINAL SAFETY r (FBM-98-R125C02,CH J) r (FBM-98-R125C01,a-l J} FOXBORO DCS r {FBM-98-R125C01,CH 4) r .. f~~:~~;~:;~::~:~ ~78 FOXBORO DCS I 2-471610-98-12A..COORD B-10 I 2-471610-98-12B.COORO B-2 I 2-471610-98-12A.ax>RD B-10 I 2-411610-ss-1:zA.CCXH> e-10
;;_95 .. B-4 O-M-278 ANALYSIS REPORT I (FBM-98-R125C04,CH 1) - I ~r:!;i~~~s~7t/~t~, e-rn ~ (FBM-98-R125EOl ,CH 1) ~O-M-lJB I {FBM-98-R1 25co+, CH J) - I (FBM-98-R125C04,CH 4) fr~=~~;f:;~~tg'1~
I 2-471610-98-12A..COORD E-8 I 2-471610-98-12B.COORO B-9 I 2-471610-98-12A.COORD E-8 I 2-471610-98-12A.C<XJRD E-8
-~ lgj 2-471610-98-12B.COORD B-11 ~ - @ I (FBM-98-R125C07, CH 1 ) p E-a ~ (FBM-98-R125E04,CH 1) 5 {FBM-98-R125C07,CH J) p' I (FBM-98-R125C07 ,CH 4)
I I ~F~!;~~~:5JM :&~~ I PDS-70':'941 (FBM-98-R125E05,a-l 1 J 70-95 I LOGIC REF I LOGIC REF 2-471610-98-12B.COORO E-8 I LOGIC REF I LOGIC REF r.k--, 2-47W610-98-128.C(X)RD E-6 POWERHOUSE I OBF 802403-F0-2827 I 08F802403-F0-2827 I O&F8D240J-F0-2827 I OBF 802403-FD- 2827 (FBM-98-R125ED8,a-l 1 J f5-7D:g5l l,':','::-::I,,;;-',s;e::':'!2'-'S""E0"-7'-',C"'H-'1-'-)---1 FS:10-11sl UNIT 2
~ LC.CIC REF D8f80240J-FD-28J5 r.k--, 27D-263A 08F802403-FD-2835 r.k--, ~ ~
ELECTRICAL 270-2618 270-2638 CONTROL DIAGRAM COMPONENT COOLING WATER SYSTEM TVA DWG NO. 2-47W61O-7O-3 R16 FIGURE 9.2-22(U2)
Cl z 3' <( Q:'. 0 0 w z RADIATION DETECTION 0-47W611-70-2, A-AUTO <( f-z A-3. D-3 a. G-3 l OPEN /1/,-HS CLOSE 70-66A
*DERIVED FROM UNIQUE LIMIT AND TORQUE SW REQ OF VAL VE 0 TO PUMP {--
<( 8 CONTROL u P-AUTO TYPICAL MOV CONTROL OPEN 1-HS CLOSE TO CCS A-P AUTO REFERENCE DRAWINGS: 70-63A SURGE TANK A 1-47W611-0-1------------LOGIC DIAGRAM INDEX&. SYMBOLS UNIT 1 2-47W611-0-1------------LOGIC DIAGRAM INDEX&. SYMBOLS AND SURGE START STOP 1-47W61 0-70 SERI ES--------CONTROL DIAGRAM BLACKOUT~ 1-FCV-70-66 TANK 8 70-46A PULL TO 0-47W610-70-SERI ES--------CONTROL DIAGRAM FULLY OPEN UNIT 2 LOCK-OUT 2-47W61 0-70-SERI ES--------CONTROL DIAGRAM 0-47W859-1----------------FLOW DI AGRAM 1-47W859-2----------------FLOW DIAGRAM BO-SI TEST LOW }- 1-45W760-211-16 HEADER PRESS. CLOSE PS-7D-248/A b- 7
~~'-+---- ,----------, ,----------,
I g~Nt~gL~U~;Pf~~~ I I g~Nt~gL~u~?f~~~ I SAFETY I EXCEPT NO PRESSURE : IEXCEPT NO PRESSURE : OPEN CLOSE NOTE 5-i~~~C;,[IDN LS_!:2:~__!~UT___ _. ~!_12._C~ IN~~---_. 70-64A 1-47W611-63-1 BKR CLOSED BKR CLOSED MANUALLY FOR MANUALLY FOR AUXILIARY TRAIN 1A TRAIN 28 CLOSE NORMAL AUTO SHUTDOWN
------~
BOARD 1A1-A VOLTAGE START ~-H~STOP AVAILABLE ~-------< 70-46C 1-47W611-99-5 1-FSV 7 -66 DETAIL 1
~----1-~~g~H~~~ESEAL LEAKAGE NOTES: ,---{XCf---i---1 VENT TO AH.10SPHERE
1. FOR SYMBOLS OTHER THAN THOSE NOTED ABOVE SEE INSTRUMENTATION AND IDENTIFICATION STANDARDS, LATEST ISSUE.

2. FOR COMPLETE INSTRUMENTATION AND CCMPONENT SEPERATION DESIGNATIONS SEE CONTROL DIAGRAM, 47W610-70 SERIES.

3. LOGIC SHOWN FOR UNIT 1, TYPICAL FOR UNIT 2 EXCEPT AS NOTED.
TO WASTE 4. POWERED BY TRAIN 28 NORMALLY. f - - - - - ' < ' . f - - ' - HOLD-UP TANK 1-47W611-77-2 5. C-S PUMP WILL START ON SAFETY INJECTION SIGNAL FROM UNIT 1 OR UNIT 2. PUMPS 1A-A ANO 1B-B START ON A UN[T 1 S[ SIGNAL. PUMPS 2A-A AND 2B-8 START ON A UNIT 2 SI SIGNAL. THE UNIT 2 SI SIGNALS ARE CONTROLLED BY 1A 18 PROCEDURE O-TI-12.08, CONTROL OF UNIT INTERFACES. FROM DISCHARGE
6. "DIGITAL AND ANALOG LOGIC SYMBOLS ARE USED ON LOGIC DIAGRAMS TO f - - - - - - - - - - ~g~~M~F FUNCTIONALLY DESCRIBE THE PROCESS CONTROL REFER TO THE ASSOCIATED 1 A-A &. 18-8 WIRING SCHEMATIC FOR THE ELECTRICAL COMPONENTS USED TO IMPLEMENT THE CONTROL SCHEME."

7. VALVES 1-FCV-70-34. 2-FCV-70-39, AND 1 &. 2-FCV-70-75 ARE ADMINISTRATIVELY

8. Mf~fg l~Fd~~78:f~. PP~?dJ9fo-i!.ITr_f~$~l6~sfPf~hS~fb~frix R) 2-FCV-70-28, 2-FCV-70-29, 2-FCV-70-76 AND 2-FCV-70-78 ARE ADMINISTRATIVELY COMPONENT LOCKED IN THE CLOSED POSITION. (WITH BREAKER OPEN) (APPENDIX R)
COOLING WATER SURGE TANK A 9. NOT USED. FOR UNIT 1 10. SOME CI s ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE CI s OPEN STOP CLOSE SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE AL TERNA TE ID SCREEN (All) IN EMS CAN BE ACCESSED AS NECESSARY TO DETERMINE IF PREVIOUS CIDs FROM mew-,,---~ MOY CONTROL EXISTED FOR A SPECIFIC COMPONENT. TO CCS SURGE TANK UNIT 1 TO CCS
'-.___f----+---------~=~iw~f~~1S-2, C-1 TO PUMPS 1A-A. 18-8 COMP AN ION ORA WINGS :
BUFFERED 0-47W611-70-SERIES-------L0GIC DI AGRAM 1-47W611-70-SERI ES-------LOGIC DIAGRAM 2-47W611-70-SERI ES-------LOGIC DIAGRAM FROM SPENT FUEL PIT HEAT EXCHANGER A 0-47W611-70-2, H-7 NOTE 8 1 TYP 7 FROM UNIT 1 OF VALVE LCONTROLS 1-FCV-70-64J MISC SYS ------~---------------------1'-.___ 0-47W611-70-2 D-10, D-12 NOTE 8 FROM WASTE GAS 1-FCV1 1 cNTROLS TYP 7 COMPRESSOR PACKAGE LOF VALVE 1-FCV-70-64J HEAT EXCHANGER A 70-27 0-47W611-70-2. A-8 CONTROLS FOR PUMP C-S TO CCS
-"r--------+----~-----,-0-=-,-,---8-::_-::_-::_-::_-::_-::'_,"' ~~: jW~~?~7g-2, D-1 UFSAR AMENDMENT 3 'CONTROLS TYP 7 ,-------------------------------,
2-FCV 10-2S LOF VALVE 1-FCV-70-64J WATT s BAR FROM CDWE BLDG 0-47W611-70-4, D-9 NOTE 8 1cNTROLS TYP 7 FINAL SAFETY LOF VALVE 1-FCV-70-64J NOTE 8 1 TYP 7 ANALYSIS REPORT OF VALVE LcoNTROLS 1-FCV-70-G+j CONTROLS FOR PUMP 28-8 FROM UNIT 2 FROM UNIT 2 ENGRG SAFEGUARD . MISC SYS 28 SYS 7_ NOTE 7 POWERHOUSE 0-47W611-70-2, E-6 1 TYP 7 OF VALVE LCONTROLS 1-FCV-70-64J UNITS 1 & 2 I FROM UNIT 2 ELECTRICAL ENGRG SAFEGUARD LOGIC DIAGRAM 2A SYS 2-47W611-7D-2A, A-10 FROM WASTE GAS COMPRESSOR PACKAGE TO CCS SURGE TANK COMPONENT COOLING SYSTEM FROM SPENT FUEL HEAT EXCHANGER 8 UNIT 2 PIT HEAT EXCHANGER B TVA DWG NO. O-47W611-7O-1 R2 0-47W611-70-2. H-7 COMPONENT COOLING PUMPS FIGURE 9.2-23
Cl z OPEN CLOSE r----------7 r----------7 r----------7 3' 70-25A RADIATION CONTROLS TYPICAL : <( DETECTION TO I 8?N!~fEJJJ~JgAL : I 8?~~}~\:11~~CAL : OF 1-FCV-70-25 I II Q:'. 1-FCV-70-66 I I I I 0 NORMAL 0-47W611-70-1 L -------- _J L C COOR A-2 TO UNIT 1 SEE NOTE 5 CCS PUMP 1 A 0 INTAKE HEADER C w (0-47W611-70-1) z WASTE GAS COMPRESSOR LlJQ-~~F~--- 70-2 <( PACKAGE HEAT EXCHANGER A TO INTAKE f- HEADER OF CCS z 't---~-------i'<-..f---------~---~---------------~--~-------------------------------------- ---.__ PUMP 1 A-A FOR UNIT 1 (D-47W611-70-1) CCS HEAT EXCHANGER A FOXBORO DCS 0 r--------~--------------------------7 1-2218124-US14728-FD-1XNS-0007-1 <( I I u I I I I I I TO 1-TIS-62-79 FOXBORO DCS I I 1-47W611-62-3 1-0006367J-08F7J42J5-FD-1608 : I I
~- NORMAL ~ AUXILIARY -~ ~*~
L-------..-----------------~
-- T ---------------~
SEE NOTE 6 NON-REGENERATIVE ( LETDOWN) OPEN HEAT EXCHANGER 1A r---- -----7
8?Nf~fEJJJ~J~AL : CONTAINMENT SPRAY PUMP AND MECH SEAL HEAT EXCHANGERS IL _ _ _ _ _ _ _ _ _ _JI FROM CCS 0-47W611-70-1 SAFETY INJECTION PUMP AND MECH SEAL HEAT EXCHANGERS 1-FCV-70-215 OPEN FULLY OPEN
_CENTRIFUGAL CHARG1NG PUMP HEAT EXCHANGERS ____ _ r----- ----7 I CONTROLS TYPICAL I SEE NOTE 6 1A ENGINEERING SAFEGUARD RADIATION 1-FCV-70-183 I OF 1-FCV-70-25 I DETECTION TO : 8?Nj~f6J-iJ~JgAL : HEAT EXCHANGERS FULLY CLOSED r----------~I I I 1-FCV-70-66 D-47W611-70-1 I I OPEN 0,-H~CLOSE I 8?Nf~fEv!!b!~tL 7 L C ~0-215 I EXCEPT NO AUXILIARY I L---~-----~ COOR A-2 STOP 7-;:22 SEE NOTE 5 SE:O~~~E 6
~c~o~~=-~~;,~,- J SEE NOTE 5 E-------------j ~~Ww~~Z-10-,-------- , TD D-47W611-70-1 TO UNIT 1 CCS COORD G-2 PUMP 1A a. 18 INTAKE HEADER C + 1-----:l (0-47W611-70-1)
CCS HEAT EXCHANGER C L SEE NOTE 5 TO CDWE BLDG (0-47W611-70-4) OPEN STOP TD 0-47W611-70-1, SEE TYP MDV CONTROL (0-47W611-70-1) COOR H-2 MDV CONTROL L TO COWE BLDG {0-47W611-70-4) OPEN CLOSE
-'.--~ ~L-l\(_~:;is SEE NOTE 6 NORMAL E----1 +
I I SEE NOTE 6 I CONTROLS TYPICAL I I OF 1-FCV-70-25 I r----------~I ____ SAMPLE HEAT EXCHANGER 18 _____ _ L---~-----~ ____ SAMPLE HEAT EXCHANGER 1A _____ _ 7-~:16 SE: :~~E 6 ----------7 SEE NOTE 5 I 8?N!~fEJJJ~J~AL : FROM CCS I _ _ _ _ _ _ _ _ _ _ _JI 0-47W611-70-1 -------- FLOW SWITCH 1-FS-70-158 ~
/ ABANDON IN PLACE VALVEl-FCV-70-156-A &
FULL y OPEN NOTE 3 / -FC VENT CONDENSER --+-{:xx:}---1
---.__f-----+ DIST COOLER ____ _.,..._ _ _ _~
RADIATION DETECTION TO BORIC ACID EVAPORATOR AND GAS STRIPPER HEAT EXCHANGER PACKAGE 1-FCV-70-66 0-47W611-70-1 COOR A-2 UFSAR AMENDMENT 3 SEE NOTE 8 NOTES: WATTS BAR
1. FOR SYMBOLS AND GENERAL NOTES SEE SHEET 1. FINAL SAFETY

2. TYPICAL FOR:
1-FS-70-155 (27C-246D) AND 1-FCV-70-153-B ANALYSIS REPORT 1-FS-70-145 (27C-242D) ---.__ ---.__ TO CCS PUMP 2A-A TO BE EVALUATED FOR 1-FS-70-148 (27C-242E) INTAKE HEADER UNIT 1 ABANDON IN PLACE 1-FS-70-149 (27C-244D) (0-47W611-70-1) 1-FS-70-152 (27C-244E) REFERENCE PER 321930 CCS HEAT EXCHANGER B SPENT FUEL PIT
3. TYPICAL FOR VALVE 1-FCV-70-156-A (27C-245D) AND FLOW SWITCH 1-FS-70-158 ( 27C- 2450). HEAT EXCHANGER 8 POWERHOUSE 1-FCV-70-168-A (27D-256A) AND FLOW SWITCH 1-FS-70-170 (27C-24JA). 7. NOT USED.
2-FCV-70-168-A (27C-243A) AND FLOW SWITCH 2-FS-70-170 (27D-256A). UNITS 1 & 2
8. 0-HS-70-1948, 0-HS-70-1978, 1-HS-70-1538 AND 1-HS-70-1568 0-FCV-70-194-8 (27C-252E) AND FLOW SWITCH 0-FS-70-6 (27C-252E). --+--- ~~~~\~~~~Nb~~ A-----~ rnT~~f ~~~bEJAU~n 1 HAVE BEEN DISCONNECTED DUE TO APPENDIX R INTERACTION.

4. NOTE DELETED l ?=~g~=~t~:t: g~~=~!~5l 1~8 ~cg: ~:ng~ ?=~t~8=~~ a~~=~j§fil:
L ( -47W611-7 -1) ELECTRICAL LOGIC DIAGRAM
5. VALVES 0-FCV-70-12, -22, 1-FCV-70-2, -J, -4, -8, -25, AND 2-FCV-70-2, -J AND -4 ARE TO UNIT 2 EQUIPMENT
~ - - - - - - - - - - - - - - - - - - - - - - - - - (2-47W611-70-2A)
ADMINISTRATIVELY LOCKED IN THE OPEN POSITION (WITH BREAKER OPEN)(APPENDIX R). COMPONENT COOLING SYSTEM VALVES 2-FCV-70-15 AND 2-FCV-70-16 ARE ADMINISTRATIVELY LOCKED OPEN (WITH BREAKER OPEN)(NOT APPENDIX R) TVA DWG NO. O-47W611-7O-2 R2
6. 1-FCV-70-9, -10, -13, -23, 2-FCV-70-14, -18, 195, -196 ARE ADMINISTRATIVELY LOCKED IN THE CLOSED POSITION (WITH BREAKER OPEN). FIGURE 9.2-24
A-AUTO CNTMT ISLN, PHASE B. TRAIN B, 1-471611-88-1 OPEN CLOSE CNTMT ISLN, PHASE B, TRAIN A, 1-47W611-88-1 CNTMT ISLN PHASE B TRAIN B 1-47W611-88-1 OPEN OPEN
*DERIVED FROM UNIQUE LIMIT ,--~-~---------~ AND TORQUE SI REQ OF VLV I
I I TYPICAL MOV CONTROL TO REACTOR COOLANT I PUMP Oil COOLER HEAT EXCHANGERS 2, 3 I. 4 I (CONTROLS TYP OF 1) NOTES: I
1. FOR SYMBOLS AND GENERAL NOTES SEE 1-4-7W611-70-1.
I 2. SWITCH LOCATED ON 480V MOV BOARD. I ,-------, 3. 1-HS-70-898 HAS BEEN REMOVED TO PREVENT A CONDITION ADVERSELY AFFECTING THE SAFETY FUNCTION Of THE ASSOCIATED VALVE DURING AN CLOSE OPEN CLOSE ACCIDENT. ASSOCIATED XS 1-XS-70-89A NO LONGER NEEDED. OPEN I CCIHROLS TYP CF A-AUTO MOV CONTROL MOV CONTROL : ~;mr'8s~*~RAIN A : OPEN CLOSE HEAT EXCHANGERS 2, 3, I: 4 FROM COMPONENT I -....':\____. ,...._:------,--.... .... j',l~+---....----~:r-,.L---~7--0r-9 __J COOLING SYSTEM
~!tJwfr,=~t~fR A-------------------------, ~ -----t: o: :1~-~-~_:_~E-It-cc_T~-~-r'-_A_N_T'T"_. . .___....__ INSIDE OUTSIDE AUXILIARY TO CCS INTAKE HEADER FOR UN IT 1 (1-47W611-70-1 l INJECTION
~m SIGNAL~ IN A-AUTO OPEN BLACKOUT l II PULL A-P AUTO ED 1A-A I-------S"'TccA,,_RT'-'/1,-11-HS\\L.:sccTOe,P_ _ _ _ _ _ _ _ _ _ __ VOLTAGE AVAILABLE AT 480V REACTOR 70-131 A PULL TO MOV BO 1A1-A LOCK-OUT NORMAL CNTMT ISLN PHASE A K619 TEST TRAIN 8 CNTMT ISLN } PHASE B TRAIN A 1-47W611-BB-1 AUXILIARY A-AUTO CNTMT ISLN 1-HS\;\ OPEN CLOSE OPEN
- - {PHASE B TRAIN A 1-HW& 11-88-1 70-85A CNTMT ISLN PHASE B FROM 1-FdS TRAIN 8 81 E DIFF FLOW > SETPOINT -,-- OPEN 1 I I I MOV CONTROL I I I I I I I I I I OPEN CLOSE I I BUFFERED I I INSIDE ,-L ___ J_7 1-FCV-70-90 CONTROL REACTOR COOLANT PUW' 1 TO CCS THERMAL BARRIER BOOSTER PUMP 18-8 PUMP IA-A FRCM REACTCE TO REACTOR COOLANT COOLANT PlliilP PUMP THERMAL THERMAL BARR 1ER BARRIERS 2. 3 AND + 2,3,AND-t- - - CONTROLS FOR PUW 1 B WATTS BAR TYPICAL OF PlliilP 1A-A PlliilP 1A-A FINAL SAFETY 1CONTROLS TYP or - 7 1-FCV-70-90, 1-FCV-70-133 ANALYSIS REPORT THERMAL BARRIER BOOSTER I i~c~N~~T9~sC:~EPT I DIFF FLOW > SP PUMPS 1A-A & 18-8 I PHASE A, TRAIN A I I NO FLOW CONT. I L ----- J 1-M-23A POWERHOUSE -re UNIT 1 70-1+3 ELECTRICAL I
LOGIC DIAGRAM
~--~1v:1e--------------I-NS_I_D_E_a::===J OUTSIDE TVA DWG NO. 1-47W611-70-3 R5 EXCESS LETDOWN FIGURE 9.2-25 HEAT EXCHANGER
CNTMT ISOL PHASE B, TRAIN A 2-471811-88-1 TO REACTOR CCXJLA.NT Pl.MP OIL COOLER HEAT EXCHANGERS 2, 3 a. 4-(CONTROLS TYP OF 1 )
*DERIVED FROM UNIQUE LIMIT ,-------7 AND TORQUE SW REO Of VL V ,-------7 OPEN I CONTROLS TYP OF I I ;N;-~s --;Y;;; - 7 I CONTROLS TYP OF I I 2-FCV-70-100 I I 2-FCV-70-100 I I ~~~E;~-i~ TRAIN B I li<<lV CONTROL I EXCEPT USE I TYPICAL MOV CONTROL LT_"_AIN ~ - - - J NOTES:
L ~ - - - - _J L - ~ - - _J
-FC FRCN REACTOR COOLANT -FC 1. FOR GENERAL NOTES SEE 2-471611-70-2.
PUMP OIL COOLER -FC 70-140 70-92 2. SWITCH LOCATED ON 80V w::JV BOARD. HEAT EXCHANGERS 70-89 OPEN 2, J, it. 4 FROM CCU'ONENT
~;i~f~f~i~ A - - - - -....------------------1,1---------- I -----4a:::::::::Ji------1""'--+-----,1--,--1,._ -r----1-NS_I_DE-ec=)OU-TS""'IDE 7 COORD 8-4 OUTSIDE INSIDE TO CCS INTAKE HEADER FOR UNIT 1 (1-471611-70-1)
SAFETY INJECTION SIGNA ~ 11L ~ IN A-AUTO A-AUTO A-AUTO PULL A-P AUTO BLACKOUT BD 2A-A OPEN CLOSE OPEN !1/2-HS\\ CLOSE 1-------~*r~*~*r~!t':~2-H~.'-:i's~ro~*------------, 70-&7A. 0-133A VOLTAGE AVAILABLE AT 480V REACTOR 70-131A PULL TO MDV EID 2A1-A LOCK-OUT NORUAL NORMAL CNTMT ISLN PHASE A K619 TEST TRAIN B CNTMT ISLN } PHASE B TRAIN A 2-47W611-88-1 AUXILIARY A-AUTO CNTMT ISLN OPEN CLOSE OPEN
- - - - {PHASE 8 TRAIN A 2-1'7W611-81!H 70-&5A.
CNTMT ISLN PHASE B FRCM 2-FdS TRAIN 8 PUMP 2A-A 81E DIH FLOW 2-FCV-70-90
> SETPOINT DIFF FLOW > SP 1 I I I I I I I I I I I I I I I BUFFERED I I , - L _ _ _ _l_7 OPEN REACTOR COOLANT PUtr.P 1 MDV CONTROL 2-FCV-70-133 TO CCS THERMAL BARRIER CONTROL BOOSTER PUtr 28-8 OUTSIDE INSIDE PUMP 2A-A.
FROM REACTOR TO REACTOR COOLANT COOL.A.NT PUMP Pl.IF THERMAL THERMAL BARRIER BARRIERS 2, 3 AND 4 2, 3, A.NO 4
- - CONTROLS FOR PUMP 28-B -
TYPICAL Of PUMP 2A-A TO 2-fCV-70-133 LOGIC A.T COORO E-12 THERMAL BARRIER BOOSTER I CONTROlsTYP OF - 7 PUMPS 2A-A & 2B-B I 2-FCV-70-87 EXCEPT I UFSAR AMENDMENT I ~~~s~N!~T r~~~~. A. I WATTS BAR FINAL SAFETY T~r ANALYSIS REPORT
+------ I OUTSIOEa:::::::::J...
IN-S_ID_E______""""------------I-NS-I-DE- OUTSIDE POWERHOUSE EXCESS L ETOOWN HEAT EXCHANGER UNIT 2 ELECTRICAL LOGIC DIAGRAM COMPONENT COOLING SYSTEM TVA DWG NO. 2-47W611-7O-3 R12 FIGURE 9.2-25(U2)
D <(
*DERIVED FROM UNIQUE LIMIT u AND TORQUE SW REQ OF VL V OPEN SEE NOTE 2 TYP !CAL MDV CONTROL ABANDONED IN PLACE NOTES:
1. FOR SYMBOLS AND GENERAL NOTES SEE 0-47W611-70-1.

2. CONTROL POWER FUSES AND THERMAL OVERLOADS FOR 1-FCV-70-207 HAVE BEEN REMOVED TO ISOLATE UNI1/UNIT 2 INTERFACE POINTS.
REFERENCE DRAWING 1-45W760-70-10, NOTE 7.
3. VALVES REFERENCING THIS NOTE ARE MECHANICAL U1/U2 INTERFACE NOTE 3 POlNTS. THEY ARE CLOSED WITH CONTROL AND THERMAL OVERLOAD FUSES REMOVED TO PRECLUDE ADVERSE INTERACTION BETWEEN UNIT 1 AND UNIT 2.
FROM ENGR SAFEGUARDS 18 HEADER (0-47W611-70-2) TO ENGR SAFEGUARDS 8 RETURN HEADER (0-47W611-70-1 l CONDENSATE DEMINERAL IZER WASTE EVAP PACKAGE (DISTILLATE SKID) 0-PL-70-206 FROM ENGR SAFEGUARDS 28 HEADER (0-47W611-70-2) L _________________ _J CONDENSATE DEMINERALIZER WASTE EVAP BLDG UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNITS 1 & 2 ELECTRICAL LOGIC DIAGRAM COMPONENT COOLING SYSTEM TVA owe NO. 0-47W611-70-4 R2 FIGURE 9.2-25A
7 NOTES: i OPEN 1. FOR DETAILED OPERATING INSTRUCTIONS OF THE WATER TREATMENT PLANT 333A I ANO THE OEMINERALIZER EQUIPMENT, SEE THE NEPTUNE ANO l*A INSTRUCTION MANUALS, RESPECTIVELY. I I 2. UNLESS OTHERWISE NOTED, All THE VALVES ARE THE SAME SIZE AS THE PIPE. 0-MTR-028-0025 I 3. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITIONS. I~ +. 1's'. ~~~~~ ~~~i:iib,Ea<:.W.st, _NOTED, ARE TO HAVE PREFIX o. SYSTEM TANK
5. VALVES HAVING FUNCTION DESIGNATION AS FLOW CONTROL VALVES SHALL 28-19 BE NOTED ON THE DRAWING AS FOLLOWS,© rev 28-3 855

6. M-VS, AS-V2, C-V1, ETC. REFER TO liiFGR VALVE IDENTIFICATION, l*A MATERIAL LIST 6000 SERIES.

7. L .JDENOTES PIPING INTERFACE WITH L*A WATER TREATMENT (CONTRACT NO. 74C31-83089),NEPTUNE MICROFLOC, INC (CONTRACT NO. 74C31-83124).
OR UNIVERSAL CORP OF ECOLOGY.
8. ALL PIPING TO BE TVA CLASS H.

9. FOR VALVE MARKER TABULATIONS SH WATTS BAR NUCLEAR PLANT MISC VALVE REPORT-009.
!fl_"__ TURBIDITY f---------+--'-*a53 ANALYZER AND 10
r~H~~ ~~i1~~iv5~s~~r ~~~Ri~r~~ ~j~~:\~~~ ~~g~f~rn. ~~~ET~~ELATEST 0-TANK-028-0021 AIR REt.<<JVAL REVISION OF THE 47821 SER JES ORA.WINGS *rIPING SYSTEM CLASSIFCATION*. I:
ASSEMBLY N3-28--4002 ------ MAKEUP WATER TREATMENT PLANT 3" IASTE: NJ-928--4002 ----- MAKEUP WATE:R TREATMENT PLANT WB-OC--40-35.1 --- MAKEUP WATER TREATMENT PLANT
"-../ AND DEMINERALIZED WATER 508 !fl..:_ TO STATION TRENCH STORAGE AND DISTRIBUTION SYSTEM 1--HH----t f~~Wgg~!7 ON 6"___!L , ... 1
_+_* _ _....J __ +----+ 11. NGEO AND MAY DIFFER FROM COORD LATER 513 HE SAi.£ CO,IPONENT. THE AS NECESSARY TO DETERMINE
----;'66 767 CIDS C~PONENT.
BACKWASH L.2.._J 1--------------------... _I 12
TRENCH ~Sf~T~/~~ff iE 1~~:f~C6l~,~~- ~~~~UFff~AJ~e;.T~[ill].
POINTS MUST BE CLOSED WITH HAND WHEELS REMOVED 536 IN PLACE. _2_*_ 13. VALVE MUST BE CLOSED WHEN LEVEL IN THE LOW VOLUME WASTE HOLDING
-1!:__ (Le'\~ POND IS ABOVE EL 707 '-8".
FLOCCULATOR TO STATION SUMP CONT ON ~~* 0-FLOC-028-0013 1-+7W853-7 REFERENCE DRAWINGS, COORD F-7 ~ 47W800-1 SERIES ------ FLOW DIAGRAM GENERAL PLANT SYSTEMS DR 308617 SERIES -------- INSTRUMENTATION STANDARDS FLOW AND CONTROL VALVE [] SYMBOLS
~ 1-47W610-28 SERIES --- INSTRUMENT AND CONTROL DIAGRAM OVERFLOW CLEARWELL OVERFLOW 479601-28 SERIES ----- TABULATION OF INSTRUMENTS TANK A 47W550 SERIES -------- WATER TREATMENT 4: MAKEUP DEMIN. PIPING a:. EQUIPMENT D ~-~~~K-G rev BOTTCM Of TANK 686. 11 C 28-8 300GPM
40 'HD O-PMP-028-0017
~ ~~B TER EATl.£NT LG STE SUMP --10*
T ON !!_".__ 7W853-9 MAKEUP WATER TREATMENT DATA RO LATER ~-10* FILTRATION PLANT: MAXIMLM CAPACITY (INLET)------------------ 560 GPM
280 GPM/SETTLER-FILTER UNIT MIN!Mlll CAPACITY (INLET)------------------ 133 GPM SETTLER FILTER B NET CAPACITY (OUTLET) - - - - - - - - 800,000 GPO*
CATCH 0-TANK-028-0016 SETTLER-FILTER BACKWASH TIME - - - - - 10 MIN BASIN SETTLER-FILTER BACKWASH WATER REQUIRED --- 10,000 GAL PER Fil TER EMERGENCY OVERFLOW CLEARWELL STORAGE - - - - - - - - - - - - - - - 19,000 GAL EACH, 6 3!, 000 GAL TOT Al HYPOCHLORITE FEED PUii' __ 1o_"t~:B:O:TT:O,l::OF::T:A:NK==*=*1=*=7=5 BASED ON DESIGN INFORMATION FROM NEPTUNE MICROFLOR OWNERS MANUAL ff BASED ON TEST SCOPING DOCUMENT NCS-25A ACCEPTANCE CRITERIA O-PMP-028-0010
=~~~-----tt----D OEMINERALIZER PLANT:
PER TRAIN TOTAL BACKWASH FLOW RATE (INLET) 240 GPM 480 GPM NET CAPACITY (OUTLET)288,000 GPO f f 576,000 GPDff FURNISHED BY PUMP VENDOR DEMINERALIZER WASTE NEUTRALIZATION TANK ---- J,500 GAL IPMP-118 - - - - - - - 7 TRENCH OEMINERALIZER WATER STORAGE TANK ----------- 10,000 GAL I .: t~~8 8~ ~~~fG~cA~~~M~M8CE~~c~~~~Al~~E~~~~~~E~i1f~~I~ucTION MANUAL __1_"_.. SYSTEM PRESS TEMP DATA: LINE MARK NO. DESIGN PRESS TEST PRESS DESIGN TEMP 1 15 PSI Hli PSI 95*f 2 100 PSI 150 PSI 10o*F 3 125 PSI 200 PSI 1 so*F O-TANK-028-0001 4 50 PSI 75 PSI g5*f 5 100 PSI 150 PSI 1 so*F 6 ATWJSPHERIC 15 PSI 95*f Id 7 75 PSI 125 PSI 100"F 8 +O PSI 60 PSI 100"F TEST PRESSURE DATA IS HISTORICAL INFORMATION AND NO LONGER MAINTAINED 1/2" AS DESIGN OUTPUT. 697 I--'f-----t----LEVELS START FURNISHED BY A STOP EFFLUENT PUMP VENDOR 3" PUMPS IPMP-119 -------7 TRENCH TO BE AIIANOONED. REFERENCE PER 321930. 731 UFSAR AMENDMENT WATTS BAR ___!_"_.. FINAL SAFETY 789 736 3* DIFFUSER SUMP
----m 73+ ANALYSIS REPORT B SEE NOTE 13
__3__"_.. ~ POWERHOUSE 733 719 UNITS 1 &. 2 COMPANION DRAIING: MECHANICAL 120E 0-+7183+-2
.j TO PORTABLE FLOW DIAGRAM 1_12_".. SLOPE PUMP CONN HCCt--~~---<~~~ g~QUIREO WATER HEATER&. DEMINERALIZERS 1-47W853-6 CDORD D9 TVA DWG NO. 0-47W834-1 R1 FIGURE 9.2-26
(.!) z
s,
- 6
VENT TO ROOF Ct:
w z I-z ;..j
~
I:
tJ 375 ;..j t1 r TRENCH DR L_'_J L L*A CONT ON COND DEM SYSTEM ~ 1-471838-2 COORD E-1 TURB BLDG YARD 2* OVERFLOW
;1..___**~~
CHEM STDR BLDG IALL LNOT ABANDONED IN PLACE ~ I NOTES: I. SCME CIOS ON THIS FRa.t THE CIDS S THE Al TERNATE ID DETERMINE IF PRE
2. BLANK-OFF PLATE (PANCAKE) INSTALLED AT THIS LOCATION.
3 THIS IS A UNIT I/UNIT 2 INTERFACE POINT. SAFETY RELATED, <Ill)
INTERFACE POINTS WST BE LOCKED CLOSED. NON-SAFETY RELATED, [ill ,
INTERFACE POINTS WST BE CLOSED WITH HAND WHEELS RDIJVED 00 LOCKED IN PLACE. TO NEUTRALIZATION ABANDONED IN PLACE TANK CONT ON REFERENCE PER 321930 0-47W834-2 COORD F-10 UFSAR AMENDMENT WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNITS 1 &. 2 MECHANICAL FLOW DIAGRAM FOR MAKEUP WATER TREATMENT
-112*
AND DEMINERALIZERS TVA DWG NO. 0-47W834-2 R2 FIGURE 9.2-27
NOTE: SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND SHIELD WALL\ - lil"!ll_l TOP OF OVERFLOW. MAY DIFFER FROM THE CIDS SHOWN ON OTHER DOCUMENTS EL 826'6"(TYP) O-TANK-59-116 \ 2 .. FOR THE SAME COMPONENT. THE ALTERNATE ID CAN BE ACCESSED IN MAXIMO AS NECESSARY TO DETERMINE IF PREVIOUS CIDS EXISTED FOR A SPECIF IC COMPONENT. DETAIL A1 REACTO~ ~~-=--==----------------~56" O' 81
§_lc_Qg_ EL 716.D ct. EL 822.0 133"-55' ~t am~ * ~~I GRADE D-59-590-z.j 3**
EL 728.0 0 HOSE CONNECTION <t: TO BAMB u DETAIL C CONT ON
~---~~----<1-47W819-1 COORD 87 1F E-UP TO MARY WATER 0-59-510~
TEM ..w* ,..!\ 4*
~ ) TRENCH 5~~ 7 ~~~~:~ A2
VALVES 2-59-519, -658 AND
-657 MAY BE POSITIONED BY '-1=,=='==="eS'e~ 1~ ~ 0-FC 2 OPERATIONS TO PERMIT PWST 1-,:,0 959-2 MAKEUP V-A13 EL 713 .0 MCR WATER CHILLER 8-8 COMPRESSION TANK 8 2-59-603 0-47W865-3 COOR . D1 ~ - 63 J-S4 J-S7 J-S9 2-59-604 EL 713.0 EL 713 .0 EL 713.0 -- ~ SEE NOTE SDBDR WATER CHILLER 8-8 DETAIL A ------- COMPRESSION TANK B EMsrnorn PIPING 0-47W865-8 COOR . D2 (TYPICAL 8 PLACES) 2 r--------------
1 r----------- 1 I 0 : I I I I I I I 2-59-1292
~c~o~,r~o~,~
f-1'-l~I- 2-47W804-2 COOR E6
~
n CONT. ON 0-47W856-2 1-59-7115/2" VENT ~ COOR Fl 0 I I I I L____ X-A5 EL. 757 .0 - - - - ..:::.-----
,----0 I
(L.C.)1-R£AC.1QR / (L.C. )1-5 FROM DEMIN. WATER I I STORAGE &. DIST BLD.G (L.C. )1 SYS (MDMP-31) CONT.>---~ ON 0-47W872-1 J COOR D9
~ss L 1-59-691 TURBINE BUILDING VALVE UFSAR AMENDMENT 3
I' WATTS BAR FINAL SAFETY 1-59-696 - - ' ... )<. . . /
ANALYSIS REPORT 1-59-697 REFERENCE DRAWINGS 47W490 SERIES -PIPING DRAWINGS - TURBINE BLDG POWERHOUSE,SERVICE & 47W491 SERIES -PIPING DRAWINGS - AUXILIARY BLDG 47W492 SERIES -PIPING DRAWINGS - REACTOR BLDG OFFICE BUILDING 47W570 SERIES -PIPING DRAWINGS - SERVICE BLDG 47W575 SERIES -PIPING DRAWINGS - OFFICE BLDG 47W611-97-1 -LOGIC DIAGRAMS 0-59-704 UNITS 1 & 2
~.63 47W610-59-1 -CONTROL DIAGRAMS PRIMARY WATER 1.2-47W819-1 -HOW DIAGRAM - PRIMARY WATER FLOW DIAGRAM ~ STORAGE TANK 47W800-1 -FLOW DIAGRAM - GENERAL PLANT SYSTEM DETAIL A1 DETAIL B1 478491-59X1 &. 3 -MECH DW &. C DEC SYS MVAR QUALITY CONTROLLED LIST CASK ECON HEAD TANK CONTROLS DEM WATER HEAD TANK CONTROLS GRADE 47W856-101 -MECHANICAL STRESS ANALYSIS PROBLEM (CDHT) (DMWHT)
DEMINERALIZED WATER DETAIL B JllilL.l EL 728.0 BOUNDARY - DEMINERAL IZED WATER &. CASK EMBEDDED PIPING ECON SYSTEM (TYPICAL 6 PLACES) .lJ.tHJ_l CAP. 187,000 GAL AND CASK DECON SYSTEM COMPANION DRAWING: 0-47W856-2 TVA DWG NO. O-47W856-1 R1O
.'!'.ARD.
FIGURE 9.2-28
(.!) FUTURE COHN WATTS BAR UTILITY z TRICT 0-29-200 f'OR WAREHOUSE a:
...... PLANT FACILITIES CNOTE, NEW METER, PIPE AND VALVE HAVE BEEN -~
INSTALLED FOR THE MAINTENANCE BLDG BY
< THE WATTS BAR UTILITY DISTRICT. THIS PIPING AND VALVES ARE ABANDONED.
C,
"" COOLERS ARE NOT C, --j------.-
6. H ARE NOT DIAGRAll,IED.
, 7. ~ .
w TO MAINTENANCE BLOG z ________ 8. []DENOTES OPERATING PRESSURE AND TEMP AS GIVEN IN TABLE.
9. DESIGN PRESSURE AND TE.., f'OR THE ENTIRE SYSTEM IS 110 PSI AT so* F.

10. ALL POTABLE: WATER PIPING AND TANKS, AND ANY SUBSEQUENT ADDITIONS, I- ALTERATIONS ANO REPAIRS TO THE SYSTEM SHALL BE DISINFECTED IN ACCORDANCE WITH CONSTRUCTION SPEC G-11.
z 11. FOR VALVE MARKER TABULATIONS SEE WATTS BAR NUCLEAR PLANT MISC
...... VALVE REPORT -009. < 12. ALL PIPING ON THIS DRAWING IS TVA CLASS H UNLESS OTHERWISE NOTED.
13. LATEST REVISION OF THE 47821 SERIES DRAIINGS "PIPING C, LASSIFICATION.
NORTH ACCESS 14. TO THE CONFIGURATION SHOWN ON THE FLOW DIAGRAM AND TO
(.J CONTROL PORT AL T ALLED CONFIGURATION IN BUILDING NOT SPECIFICALLY DELINATED CONT ON SH 4 ON THE FLOW DIAGRAMS WST BE EVALUATED BY ENGINEERING TO INSURE AT C9 DESIGN STANDARD ARE BEING MET.
-.!:_ O-ISV-029-723 15. DOUBLE CHECK VALVE TYPE BACKFLOW PREVENTER SUPPLIED BY NOOE BLOG 0-TANK-29-JA CL ASS L CLASS H VENDOR UNDER CCIHRACT NO. 89NRB-345J I B.
L , _ _____.._____, 16. INTERNALS OF CHECK VALVE O-CKV-29-587 HAVE BEEN REt.<<JVEO. 0-ISV-029-5265
17. MAINTAIN NO LEVEL IN TANKS.

.1 EL 796.0' L-J/__ _ _ _ _. , . ~~t~~O~~ BIBB TO NP10 4 18. ELECTRICAL POWER TO THIS INSTRUMENTATION ANO 0-FSV-29-3 HAS BEEN DRAIN TO TURBINE OUAZITE BOX BLDG GUTTER WHICH BLDG REKlVED PER DCN 57DJ1-A.
ORAi NS TO ST A SEE NOTE 16 SUMP
.j 0-29-588 .£__ 0-29-588 DET A1 POTABLE WATER TANKS 0-29-587 LEVEL CONTROL OFFICE BUILDING A4 SEE NOTE 18 BLDG DIST SYS BLOG DIST SYS CONT ON CONT ON AUXILIARY BUILDING CONTROL BUILDING SH J AT B1 SH J AT C7 r.,
0-29-805 171300 171705 171710 47W490 TURBINE 0-29-500 471700 47W702 1-EMER SH, EYE WASH 729.0 FIELD SERVICES 47W705 FACILITY 47W710 0-SHR-29-9375 47W715 CENTRAL ALARM 4-7W550 L STATION 4-7W940 4-7W950 17152~ 0-29-589 17E530 BLOG DIST SYS 0-29-503 CONT ON SH 3 AT 88 SYMBOLS: LC - LOCKED CLOSED 0-29-590 CLASS H BLOG DIST SYS CONT ON CLASS H D-29-547 SH 2 AT C10 CLASS L ~ DIESEL GENERATOR BLOG DIST SYS CONT ON CLASS H CLASS L SH 1 AT H1 0-29-875 0-29-764 ____!'.'_ SERVICE BUILDING 2" 0-29-539 --- RV SET* 5 PSI 0-29-973 HYPOCHLORITE BLDG 0-29-~41 0-29-974 BLDG DIST SYS 1" DR CONT ON 0-29-876 SH 1 AT HJ LC _!"_ TO EMER SHOWER I-SINK 0-29-976 & EYEWASH NEAR 0-29-852 INTAKE PUlioF'ING STA SECURITY BACKUP POWER BLDG ;.I 1-EYE WASH ~~NJ~~ 01 L 1-SINK 1-EI.ER SHOWER BLDG DIST SYS 0-29-761 CONT ON I-SERVICE SINK LC _!"_ SH 2 AT H4 I-EYEWASH 0-29-978 I-EYEWASH 0-29-544 TEMPORARY SUPPLY ACID, CAUSTIC, HYDRAZINE ii. AliMJNIA TO TOILET TRAILERS FILLING AREA (YARD) GENERAL PLANT AREA LC _!"_ 0-29-980 1-SINK I -WATER CLOSET 1" PLUG DISINFECTION TO CCI PUMPING STATION CONNECTION WATTS BAR FINAL SAFETY PRV SET AT ANALYSIS REPORT 45 PSI GENERAL EL 742.0' CCMPANION DIGS: UNITS 1 &. 2 EL 729.0' 0-4718J5-2,3 a:. 4 SYSTEM PRESS-TEMP DAT A FLOW DIAGRAM LINE OPERATING DESIGN POTABLE WATER BLDG SUPPLY BLDG SUPPLY HYPOCHLORITE BUILDING MARk m,t;"ERATURE CONT FRa-l CONT FROM NO rtfrJ~RE DISTRIBUTION SYSTEM SH 1 AT D9 SH 1 AT E9 1 110 80 2 16 80 TVA DWG NO. O-47W835-1 R1 DIESEL GENERATOR BUILDING FIGURE 9.2-29A
(.!) z
s,
< ~1-WATER CLOSET I Ct: 1L2__'_ 11-EYEWASH 1-EYEWASH ,. ~I-LAVATORY I
F 1L2__'_ I 1-..;;;;;.....jl-URINAL w 11-SINK 1-SINK I z ~ -'-:'.. JL+/-:, :======:::::
F-1 I-SHOWERS ~t 1-=;;.&l1= a:.;;;;.,i~I-WATER COOLER I
- ~~rA:~/~10* I ~~rA~~/110* I 1 I- ,a_-_ ,a_-_ ~-JANITOR TROUGH v.... J/4-* ;* I-KITCHEN UNIT I z ~1-EYEIASH ~1-EYEIASH =-1 lfl.:. ~/2" I I 1/i 1/2" 2-LAVATORIES I ..J 1-ICE MACHINE I
I: II-SINK ~I-SINK 1
I I I 1-11.4* 1-wATER cLosn i..... 1* 1......_.,.~ ro-29-s1s w~-----~ 1 I :======:::::"0-29-9-4 '. ~ ....,. 80 GAL IATER HTR tJ ~ r-f1-WATER CLOSET I 0 515 o EL 755'-o* --..,. EL 772.0' \
/i, 0-29-841 0-29-840 EL 757 .O' \
CLASS G SASS H 2'
* ~
0-29-847 0-29-848 7,,"~~2" ........... 1 J, 1
-- ~ TEl.FORARY r ..,. CONST 0-29-620 TIE-IN -j:::::::: 0-29-932 1- 0:._29 CLASS K ,.
CLASS1fl CLASS G
~-1 if ;:i ~ EL 729.0'---------,..
-;.1.,_.,_-,_...2_*....-1lp~MER SH EYEWASH FOR THE TRAP PRIMER TO ~
0-SHR-29-71 / CONT ON 0-47W853 ~~~~~NG TRAP / l<:!, CLASS k
' "-.SH 7 COORD C-9 VACUUM RELIEF VAL VE Ji CLASS G EMER SH, EYEWA9-1 L 0-29-62-4 ---::::I ,.~
SUPPLY, CONT FROM >---..,._. El 708.0'----,, SH 1 AT F8 M" <>~i *'7 0-29-679 BACKFLOW PREVENTER ,,l. ADJACENT TO INTAKE PUl.PING STATION 0-29-961 ~ - m* _ A
*;., ° 94?~ 'VK I1-SINK M" M" ,. *-&:. 112*
[K::{ 0-29-9+8 o.:r9-9+6~. 1,-sINK +---"--"_,_....;;.......;=;..i,_sINK I
~----~O-->,"_zgt,_>' 96"113' 0-29-951 _1.....1.,. l~'""L.,
NOTES:
\ 0-29-949 l~,=-,=v=,w=AS=H==~~ * ~~1-=E=v,=w=,SH===~I 0-29-923 0-29-922 -----EL 7J7.0' 1. NOT USED "-0-29-950 !i 2. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-47W835-1.
l? l? ~1 112-M' 0-29-921 ] 1-----....;;;;;,.i,_sINK I 3. All PIPING ON THIS DRAWING IS TVA CLASS H UNLESS OTHERWISE NOTED. I 2-LAB OUTLETS lfl_" tt 1/2" l--.,;;;;;,_i1-SINK
~------'I n ~
1/2' ~ = = = = ~
.__ _ _ _ _=;;;;..iL,_-E_Y_EW_A_SH_ _ _...JI 11-SINK ,. ~ - - - - I - E l . E R SH I ~t ii EL 692.0'----,,
o-L29-924 M" l.._1_-s_IN_K_ _ ___Jt---+:J::j_...!,'/~2~*; * .tr-_-_-_-_-_-_-_-_-_-_.J-, b~ I(/) 1-LAB OUTLET I- CONTROL BUILDING M" 1'
-IL1=-=LA=B=OU=T=LE=T=~t""."'.:::---1--:,;1n_:.~2:;;* ;r-_-_-_-_-_-_-_-_-_ -_-_....I~
0-29-925 r I-SINK I M"
,,,,----- !""I I -LAB OUTLET r,__l.J IN 1
, a_:. Lr============'.
M" ~ -~1-EYEWASH I
~1-LAB OUTLET
1" ,a:, ,-------,
1/r Sf I-SINK I 0-29-926 IL*_-s_I_*-*-----'J-=, ' 112* ~============'. .------!SERVICE SINK 7 ud .m_* 1--=;;..i,-srn* I El 760.5' \ I _L_J2-LAB OUTLETS 1* ~============'. c0 1/r 1---.;..jl-EMER SH I 0 _29 _927 1,-LAB OUTLET 1-112* . - - - - - - ~ I~ .,.._..;;;;;;..-1,ooueLE SINK
----1-SINK ..._ _____, I ]
0-29-928 0-29-929 ~t O-ZS-91-4
!. 4:><:lf'- . . - - - . . . 1* ~ i ---fwA.TER COOLER 0-29-912 o-29-s21 0-29:Szs 1-1/r . - - - - - - -
913 N ~EMER SH., E:YEWASH it . . . ., 0-29-933 AUXILIARY BUILDING ~-..._ 1-1/r 1 0-29-846
.. EL 742.0' \
WATTS BAR 1-EMER SH, EYEWAst-1,f--- FINAL SAFETY ANALYSIS REPORT EL 729.0'
~I ~1 jl j l "---=sE=c~u=R=1T=Y~B~ACKUP ADDITIONAL DIESEL GEN BLDG GENERAL POWER BUILDING UNITS 1 &. 2 FLOW DIAGRAM BLDG SUPPLY POTABLE WATER CONT FRCM SH 1 AT F9 DISTRIBUTION SYSTEM Cot.f'ANION DRAWINGS SEE SHEET 1 TVA DWG NO. 0-47W835-2 RO FIGURE 9.2-298
EL 796.0 0-CLR-029-0008 ~-------~ 967 IHT SHOP CHILLER PACKAGE t--{::. ..::: 0-29-968 PI 1/~ 1-WATER COOLER
~7 >< 29-95 11-WATER COOLER ~ ~-------11-KITCHEN UNIT HVAC STEAM GEN BYPASS I 0-29-1023 ~-------~ I7 0-29-556 ~(J 0-29-654 IL2_-_u_RI_N_AL_s_ _ _ _ _ F-- f~ ~ 40 GAL. WATER HEATER ~-------~ 662 3/40.-29-557 ~~ _!12" ~4" 1-1/2"
rt HUMIDIFIER I HVAC ST GEN -Hv;;=x~~r--~1_.><::.._1/"JKfv'X~1----,
20 GAL. WATER HEATER I 'n ~-------, 0-29-651 I I 2-WATER CLOSETS r - - - - - - - < 1-SERVICE SINK _!12" 0-29-596 0-29-849 O-DRV- 29 _562 :-.-..-~-----,---l--cl--c/2""'I D-29-655 0-29-653 ~-------~ F - - f--n - V ~ ~ ~- 2~ 01 o-~9 -~~-H_V_A_C_S_TE_A_M_G_E_N_ _ _I 2" 0-CKV-29-562 1-1/2" :g 3/4" 1-SERVICE SINK ~-------~ 650 0-29-652 LOCKER ROOM SHOWERS f - - ~ = - - 1 5DO GAL. WATER HTR 1L2_-_._AT_E_R_C_L_OS_E_Ts ___ F-- ~ d ~-5~ 52 GAL. WATER HEATER __!12" 0-ISV-29-562A 0-CKV-29-562A t~
=~==1-1/4" ( '7 ::::- ~ 7~
1-WATER COOLER X0-ISV-29-561 d ~b~~L ~ATER - ".:'."" _.;i--- PUMP , IL2_-_L_Av_A_rn_,_r_Es_ _ _ _ f---- X '?----, 2-LAVATORIES D tl ~I ii~ <( 0-TE-29-0562°_,..., I - u ~ 0-TH-29-0562---0 3/4" o-Is:2:-5~ EL 741.0 ~ 6 1-LAVATORY
~ EL 744.0 ~ ~< >=C ~-<PUMP 1-URINAL o-29-646 Sf I o-29-665 ] PAINT SPRAY BOOTH I 645 I 0-29-664 I 2-WATER CLOSETS 7 0-2~47 3/4'~
j I I I 1-1/:!c2-".~-------~
~-----< 1-WATER CLOSET 1/2" r--===t 1-LAVATORY 2-1/~
0-29-1053 1/2' 0-CLR-029-1057 1-1/2" i1~r 1/2"
~ _ ~ Ll_-_UR_I_NA_L_ _ _ _ _~ ~--~-~2-SINKS I 0-29-1022 ~L1---EY-E-WA_S_H_ _ _ _ _I 3~ 1/_._2_"_~-------~
1-LAVATORY 1/2" 1/2" z, 1/_._2_"_~-------~ _,Y4 " 0-29-559 11-KITCHEN UNIT n ~ 1-WATER CLOSET ~tx } i-=--- 0-29-560 3/4" 52 GAL. WATER HEATER 11 1/<2"_. ~ - - - - - - - ~ 0-29-564 3/,,4"- . ~ - - - - - - - ~ ~ - - - - - - - ~ _!12" ~ - -__,' 1-LAVATORY I 1-SERVICE SINK I 40 GAL. WATER HTR 11-WATER COOLER f--------1 r - - - - - - - < 1-SERVICE SINK
~ 1-WATER COOLER ~~
0-29-566 I
~,f------- !:'. 1-1/~ 1/2" ~------- .2! 4 " 0-29-~51 1/2" 1/2" ~-------~21.4" 140 GAL. WATER HEATER ~ 1-LAVA TORY 1 / ~ ~~ -~C=LR~-~ =29~-~10=5=8--~ ~, f - - - ~ . ,.---1 I.- .. ,L1_-_s_rN_K_ _ _ _ __ I I -3 ~L2_-_s_rN_K_s_ _ _ _ _ ~I 11-SERVICE SINK r------< 0-29-552 -- ~f::S<:'.'f-=::.j 1-WATER COOLER 1/2" 1/2" 7 d-0-29-565 1/2" - ~ 1-WATER CLOSET 11-LAVATORY ~ 2-LAVATORJES I i=-- I ~I rl 1-SERVICE SINK I ICE MACHINE .,><-.. L.
r---------< 2-URINALS
" 0-29-850 1/2" 1-1/2" ' 1-1/2" 1-1/~
1/-3:.~-------~ - 1-SCRUB SINK I I 2-WATER CLOSET f=-- -------==j 1 -WATER CLOSET I r---------i 1-LAVATORY '
~-------~ 1/2" j;,. !I 1/2" 1-1/.+/-.:_ ~ - - - - - - - ~ I 8-SHOWERS r---------i 1-WATER CLOSET I 2-WASH FOUNTAINS ~ 1-WATER COOLER I 11-SHOWER f=-- Sj -------==j 1-LAVA TORY I 1/2" 1-1/2" 1-1/2" IL1_-_sE_R_v_1c_E_s_r_N_K_ _ _ f------
17-URINALS r-----------i 1-KITCHEN UNIT I I 1-WATER CLOSET f=-- -------==j 1-WATER CLOSET I 1/2" 1"
~ 1-WATER COOLER ~f IL*---*A_T_E_R_c_Lo_s_E_rs_ _ _ f------ I ~--------< 1-SCRUB SINK I I 2-URINALS 1 -WATER COOLER I - - - - , 1-SHOWER lJ -2*-*
I I EL 729.0 r------i 2-LAB OUTLETS&. 1-SINK 0 _ 29 _908 OFFICE BUILDING EL 729.0
;..j 0-29-910 ~r-::° J 1I J I I I II IJ FOUNTAIN I ....... ~ ;::;- -><1~ ~
10." o-29-63 (COURTYARD)
~ ~ z71--
1/2" ~ ' ' $ o-29-909 o'.:°29_:g11 I
~ ~- - - - - -
3/4"
~ :.-j 2-1/2" 2" :.-ti
t-- .,><-..
V o-29~7831 1-1/~ 1-1/~ J V I6 GAL. WATER HEATER H/}-----
;.,! 2 .. v ~, o-1._s;,;29-969 ~ 17 0-29-685 0-29-855 0-29-852A X0-29-853 v -...... I .10-29-0953 1/2" ~ - - - - - ~ l 0-29-854 ~~ ~-29_.:-856.------------,.
7
'7 1ti~Ti~~~5so~IPING L o-29-o;:: 1-SERVICE SINK I I 1-KITCHEN UNIT ~ ;~ '~ *j I ~ 0-29-782 ~-------~7.,.!.L2"1 4 ,:,. 1/2" CONTR 93N3D-41723E !..:._ ,.__P' o-2r*--o=*~*~'----, ,~.... 1/~ ~ - - - - - - - ~
1-SERVICE SINK ,---=j 1-SERVICE SINK I --ys..J I FACE MASK WASHER I
~j 11-LAVATORY f---~-_,f $ *l~. 1-1 /4 NOTES:
1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-47W835-1 .
3/4" 0-29-0954 ~ 2-WATER CLOSETS I r-------~ r-='----t>'<'I---. 2. ALL PIPING ON THIS DRAWING IS TVA CLASS H UNLESS
~ 2-sHowrn I .!...:._ 0- 2 0 OTHERWISE NOTED.
1-WATER CLOSET
,P' r*--WASHER/DRYER=*~'~'----, 1~1--w-AT_E_R_c_-oL-E-,---.>---1 "----< PRV SET 'J Zf 7 --v'--./ ["'" A I ~ 2-LAVATORIES ~I CD 45 PSI ~
.J i-29-851 0-29-0956 I
11-3:. ~-------~..!.:.1/4" ,. 1-LAVATORY 2* !..:._ ,P' -2"*~-0~*~'~1----,
~ L~ r-- WASHER/DRYER 8 I IL2_-_u_,r_N_AL_s_ _ _ _ _ f----- 11-WATER CLOSET f----z-lf ::':
1~ !.x 2-URINALS ' x7-2*- *S2 1;r22'"'..~--_'.:===;---J 1/2" I ,.l 1-SERVICE SINK 2f_4" 0' IL1_-_wA_T_E_R_c_oo_L_E_R_ _ _ F-
~ 1/~
z Nl _1-1/2" tJ o-~-571,_ 0-29-690 0 1-WATER COOLER ~ 3-120GAL. WATER HTRS u 0-29-570 0-29-903 0-29-902 1-11-3:. 1-EMER SH, EYEWASH d ~ BLOG SUPPLY EL 708.0 CONT FROM EL 727 .0 SH 1 AT D6 0-29-649 I 1..'..._ ~ 1-EMER SH, EYEWASH I EL 726.0
~ ~ WASHER/DRYER A UFSAR AMENDMENT 3 N 0-29-568 CENTRAL ALARM STATION 0-CLR-029-1059 !:'. ' 0-29-648 ~ < > C f - - - - - - < 1-WATER COOLER ~I ~j ~ WATTS BAR ~
0-29-769 1/~ 0-CLR-029-1060 ~ WASHER/DRYER 8 0-29-567 0
, ,_<*.~-_*b1/
6,,.;.3 --1~>:._<*-:I"'P'l.. 1:xr----1:a-fM_K_u-,-,-o-c_H_w_s_Ys-,-E-M-~I FINAL SAFETY
\7 st I . ._, "-'0-29-168 ~29~770 V 1-1/4" ANALYSIS REPORT L------------'--l::::-::,/--vl~=x~~f-'--'
CONT ON '7 0-29-965 TURBINE, SERVICE AND OFFICE 1-47WB34-1 0-29-569 COOR , Al il ,, BUILDINGS UNITS 1 &. 2 EL 685.5 EL 713.0 FLOW DIAGRAM TURBINE BUILDING SERVICE BUILDING POTABLE WATER NOTE A: TO AUXILIARY BLDG CONT ON i '~ SH 2 AT H6 DISTRIBUTION SYSTEM TVA DWG NO. O-47W835-3 R1 FIGURE 9.2-29C
(.!) z
s, 1/2" TROUGH Ct

I 1-JANITOR ~
- NOTES, C, 1. FOR GENERAL NOTES AND REFERENCE DRAWING SEE 0-47W83S-1.
2-LAVATORIES 2. All PIPING ON THIS ORAWING IS TVA CLASS H. C, I w z --112* I1 URINAL 1- - :.J z 7 1/2"
, 0-29-82+ ~ I-WATER COOLER I
I:
C, > 2" O-t9-8J3 2" ELECTRONIC HUMIDIFIER 6 WATER CLOSETS I EHU-1 < 0 ~9 822 - u I3 LAVATORIES 0-!9-!09 13/4* O-DRV-029-1013( 1028) 1 52 GAL WATER HEATER I 0-ISV-029-1012( 1027) 1/i TANK DRAIN
- - - 810 0 29 O-CKV-029-1010( 1025): '
I EL 746'-S' I 0-CKV-029-1011 ( 1026) I
~
0-ISV-029-1015( 1030)
- TO FIELD SERVICES ADDITION 0-29-836 ,____,-~ 1/2" ;...f Ia-2s-87.. 0-THV-029-1016(1031)
I 1-COMBO WATER COOLER REDUCED PRESSURE 0-ISV-029-1014( 1029)
-- BACKFLOW PREVENTER
3/4" 0-!9-]21 3-LAVATORIES I r ~
CONHNUEO ON
.------.;, 1 .;1_,l;;;,
2 "_ _ _ _ _ _ _ _.._"P"-C><'.'~--,[:,&<J---!'>(:J-,..,.... 1 _.l._2._"--+sH 1 AT 85 AND o-is-_!16 _!" -- I 5-W,'1ER CLOSETS 1 1/2" o is ~20 SH 1 AT C7
-- +-WATER CLOSETS I I 3-URINALS -~ O-RFV-029-1037 ( 1024) 1 1/2" 0-29-~15 1-1/2" 0-BYV-029-1017 ( 10321 - J/...____
I 3-URINALS r:::;:1-COMBO WATER COOLER I 0-ISV-029-1020( 1035) ELECTRIC 0-DRV-029-1D18(1033 I I;., HOT 1
DRAIN o-,t9-11* J/4"
..I 1"
~ 1--..----C><l---i~m~R I 3-LAVATORIES 1-KITCHEN SINK I TO JANITORS (30 GAL) SINK ~ -- 1/2" D-WATR-029-D936 5 KW ACP BLDG I 1-WASH FOUNTAIN I- I-JANITOR TROUGH (0937)
I I rr_______ I .J o-is-!13 2" 0-DRV-029-1019( 1034) I 5-WATER CLOSETS I 1/2" 3/4" :.
....L l 1-~2 GAL WATER HEATER I I o-29-801 0-29-80..
0-!_9-__!12 t O-ISV-029-1023(0935) 0-29-806 17
-- 17 0-29-819 I P-3 I
I~ I~ I I o-is-_!25 __!Lr ,__.__ o-i9-_!,18 I I 3/+" I DRAIN DRAIN SILLCCX:KS I I
~=- ~ =- ¢~----------------J 3/+"
I 1/2" I I P-4 I I
.1
~I I
I D-IHA-029-1021 ( 1DJ6) 0-29-828 I WHA I P-1 P-2 n WHA 0-29-811 D-29-817 I I 1/ 2 " I 112 " 'y' 0-WHA-029-1022 ( 0934 I _J ____ L, 2" FUTURE CONNECTION L----- PHASE n P.W. SUPPLY El 731 '-5" 1/2" P-1 i P-2 1/2" BLDG SUPPLY CONT FRCM PORTABLE WATER SYSTEM SH 1 AT C10 NORTH ii. WEST ACCESS CONTROL PORTALS (UNIDS NO. SHOWN ARE FOR NORTH ACP. NOS IN ( ) ARE FOR THE WEST ACP) FIELD SERVICES FACILITY - PHASE I WATTS BAR FINAL SAFETY ANALYSIS REPORT GENERAL UNITS 1 &. 2 FLOW DIAGRAM FOR COW'ANION DRAIINGS SEE SHEET 1 POTABLE WATER DISTRIBUTION SYSTEM TVA DWG NO. 0-47W835-4 RO FIGURE 9.2-29D
FIGURE 9.2-30 THRU 9.2-31 DELETED
CJ z 3: <( 0:: 0 0 *rl>f+=~~ _- ~- _- ~-------r-- - - ~- _- ~ -_ -~ -_ - w ~-~~7=------:t-!: z CONT ON 1-47W620-4 <( t-z COOR LATER 7 1@ 5
~1 ~1 ~
SAMPLE HEAT I (SEE (SEE u EXCH NO. 6A NOTE 18 NOTE 18)
/'Ji~
0 EL 721 .5 ...14:' I !~ \~ (SEE I~ : <( NOTE 18) u 4 GPM SAMPLE HEAT
) EXCH NO. BA UNIT 2 CONFIGURATIONS EL 683.5 SHOWN OUT-OF-FUNCTION. ~I SEE 2-47W844-1. §~ ~ {UNSTRAINED) UNIT 2 EMBEDDED SUPPLY ,-~ - - - ~ - - - - - ~ - - - - - - , c ________________________, - - - - - - - - - - - , - - - - - - - - - - - - - - - - 7 j ~ (UNSTRAINED) UNIT 1 EMBEDDED SUPPLY ~ DISCHARGE (EMBEDDED) UNIT 1 1-24-684 ~ UNIT 1 LOOP HEADER (STRAINED) 1~e-"-'--='="~-----~
CONT ON 1-47WB44-2 COOR F-7 ~ CsEE
~ NOTE 18)) INTAKE PUMPING STATION NOTES:
1/2"~ENT ------ RAW COOLING AND SERVICE 1 .NOT USED. WATER PUMPS 2.EXPLANATION OF VALVE AND INSTRUMENT NUMBERS:
---.__f-~-~_L.="~-~
5135 GPM AT 240 FT HEAD INSTRUMENT NO. 1 - TCV - 24 100 1-24-540 CONT ON 0-47W844-4, B-1 D SEE NOTE 16 (UNIT) (TYPE) (SYSTEM) (INSTRUMENT NO.) STRAINER NO. 1 VALVE NO. 1 - 24 100
~ UNIT 1 LOOP HEADER (STRAINED)
N (UNIT) (SYSTEM) {VALVE NO.) CONT ON 1-47W620-2 ALL VALVE AND INSTRUMENT NUMBERS ON A UNIT BASIS ARE PREFIXED WITH THE 0 CCORD LATER UNIT NUMBER. 1.E.1-. FOR UNIT 1 ANO INSTRUMENTS COMMON TO BOTH 2' DRAIN UNITS ARE PREFIXED 0-, 1-24-356A 3.ALL VALVES ARE THE SAME SIZE AS PIPE UNLESS OTHERWISE NOTED. ____ ,_,-2::e-"--~=*=*- 4.MAIN SYSYEM VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITION. 5.ALL INSTRUMENT CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED.
6. THE SYSTEM DESIGN PRESSURE CHANGES FROM 170 PSIG TO 125 PSIG AT VALVES 0-24-1135 AND -1136. SYSTEM DESIGN TEMPERATURE IS 130 DEGREES F. HYDROSTATIC TEST IN ACCORDANCE WITH GENERAL ENGINEERING SPECIFICATION 29 (G29).
7 .SOME HEAT EXCHANGER FLOW RATES LISTED ON THIS SERIES OF DRAWINGS ARE 100 GPMc__ _ _ _ __ DESIGN FLOW RATES BASED ON A RAW COOLING WATER TEMPERATURE OF 95°F. REFER TO CALCULATION MDN00002420090357 FOR THE FLOW RATES ADJUSTED FOR A RAW COOLING WATER TH1PERATURE OF 85°F. 8.FBV DENOTES A VALVE USED FOR SYSTEM FLOW BALANCING. 9.SYSTEM DRAINAGE AS FOLLOWS: I'-- TO TURBINE BLDG. STATION DRAINAGE (47W853).
- T O AUXILIARY BLOG. (NON-TREATED) STATION DRAINAGE AND CDWE BLOG. ~ 10.UPON NOTIFICATION OF IMPENDING FLOOD CONDITIONS AN INTERTIE CONNECTION BETWEEN THE ERCW AND AUXILIARY BLDG., IS TO BE MADE, USING THE FABRICATED CTION CONNECTED TO THE Xtt~~B~~EE~gw Bfutr6 9. BLDG. a. SUPPL y ISOLATION 11 .FOR VALVE MARKER TAG MECH VALVE PROGRAM RPT-009 a.
010. 12.REFER TO 47W447-1 NOTE 29 FOR IDENTIFICATION OF SYSTEM PORTIONS OF CLASS G THAT REQUIRE THE HYDROSTATIC TEST TO BE UNDER THE QA PROGRAM. 13.DESIGN CRITERIA/SYSTEM DESCRIPTION REFERENCE DOCUMENTS: (USE THE LATEST REVISION ON ALL WORK UNLESS OTHERWISE SPECIFIED. SEE 1/2" VENT THE LATEST REVISION OF THE 47821 SERIES DRAWINGS, "PIPING SYSTEM 1/2' VENT CLASSIFICATION" J. WB-DC-40 - - - RAW COOLING WATER SYSTEM 1-24-964 1-24-538 14.ALL EXPOSED PIPING AND VALVES IN THE TURBINE BLDG ARE
\._(UNIT 1 ONLY)_) TVA CLASS H. PIPING AND VALVES IN THE AUXILIARY BLDG ARE 30 -a" TVA CLASS G. ALL EMBEDDED PIPING IS TVA CLASS L. ALL YARD GPM PIPING IS TVA CLASS H. INSTRUMENT CONNECTIONS ARE THE SAME CLASS AS THE PROCESS LINE THROUGH FIRST VALVE.
15.NOT USED. STATOR HEAT EXCH 16.GENERIC TEST GTMXXX-02 R4 DOCUMENTED PUMP PERFORMANCE DEFICIENCIES EL 708.0 8 8Ie~ B~tN 1 ttiL8~~~UG t t~~s~ E~si~s CAPACITY IS ACCEPT Y. REFE WB-DC-40-63, SECT! ICED TO THEM UP TO ORIGINAL DES ANT MAI ENANCE. SAMPLE HEAT s: 1-24-656 17 .sm.1E CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE AL TERNA TE ID EXCH NO. 3A CAN BE ACCESSED IN MAXIMO AS NECESSARY TO DETERMINE IF PREVIOUS eras (EL 708.0) EXISTED FOR A SPECIFIC COMPONENT. 18.REPAIR OR REPLACEMENT OF VALVES IN RAW WATER SYSTEMS REQUIRES THE USE OF MATERIALS WHICH ARE NOT INCOMPATIBLE WITH RAW WATER SERVICE. SPECIFICALLY PROHIBITED ARE AUSTENITIC GRAY IRON, C95400, AL-BRONZE NOT PROPERLY 1-24-565 HEAT TREATED, OR OTHER MATERIALS NOT COMPATIBLE WITH RAW WATER. (REFERENCE DESIGN CRITERIA WB-DC-40-63)
~~~!a-L--{:x:x:J----j 19.NOT USED.
1-24-317A 20.THIS IS FOR THE FUTURE RCW SUPPLY TD DEMINERALIZEO WATER IN THE SPACE COOLERS ADDITIONAL MAKEUP WATER TREATMENT PLANT. NOTES CONTINUED BOTTOM LEFT: 6" X 4" MAIN BUS HEAT EXCH TRANSFORMER YARD 1-24-567 UFSAR AMENDMENT 2 NOTES (CONTINUED),
21. THESE BYPASS VALVES MAY BE USED FOR THROTTLING AS A MEANS OF ACHIEVING THE REQUIRED FLOW THROUGH THE HEAT EXCHANGER/COOLER FOR WHICH IT SERVES. THE TEMPERATURE 1-24-1123 CONTROL VALVE SHALL REMAIN OPERABLE AND OPERATE WITHIN WATTS BAR THE CONTROL RANGE OF THE OPERATING SCALE DURING THE THROTTLING PROCESS.
FINAL SAFETY UNIT 1 ANALYSIS REPORT 260 1-24-521 GPM 1" DRAIN HYDROGEN HEAT EXCH EXCITER HEAT EXCH EL 729.0 TVA REFERENCE DRAWINGS: EL 729.0 UN IT 1 47W447---------RAW COOLING WATER-PIPING 47W474---------RAW COOLING WATER-EMBEDDED BASE SLAB PIPING MECHANICAL 47W475---------RAW COOLING WATER-EMBEDDED FILL SLAB PIPING 1-47W610-24------CONTROL DIAGRAM SEAL OIL FLOW DIAGRAM 1-47W611-24------LOGIC DI AGRAM 1 /2" DRAIN 1-47W801-2-------FLOW DIAGRAM f..1AlN &. REHEAT STEAM TURBINE BLDG HEAT EXCH 1-47W815-SERIES--FLOW DIAGRAM AUX BOILERS EL 729.0 RAW COOLING WATER 1-47W831-SERIES--FLOW DIAGRAM CONDENSER CIRCULATING WATER 1-47W834-SERIES--FLOW DIAGRAM f..1AKEUP WATER TREATMENT 1-47W845-SERIES--FLOW DIAGRAM ESSENTIAL RAW COOLING WATER COMPANION DRAWINGS, TVA DWG NO. 1-47W844-1 R46 1-47W850-SERIES--FLOW DIAGRAM FIRE PROTECTION a. SERVICE WATER 1-47W852-SERIES--FLOW DIAGRAM STATION DRAINAGE AUX. BLDG. 1-47¥1'844-2 It. 3 1-47W853-SERIES--FLOW DIAGRAM STATION DRAINAGE TURBINE BLDG. 0-47WB44-4 &. 5 FIGURE 9.2-32
(.!) z
s,
- CONT ON 2-471620-4 < - - 4 GPM COORD LATER Ct: C,
~Ii~
C, 7 w SAMPLE HE'A-T+-l-f-=:-1 _wj~~:§ z I EXCH NO. 6A _!fl." < El 721.5 _!"__ 1- I z 4 GPM < SAMPLE HEAT
I: EXCH NO. 8A C,
EL 683.5 L H < JON (UNSTRAINED) u UNIT 2 UNIT 1 ,t. COMl!ON EMBEDDED SUPPLY CONFIGURATION SHOWN CONT ON 1-47W844-1 Jo* (UNSTRAINED) OUT-OF-FUNCTION. ___ _J COORD 8-6 UNIT 1 EMBEDDED SUPPLY SEE 1-471844-1. 20
DISCHARGE (EMBEDDE:D) UNIT 2 2-24-681-
.. NOTES:
1. NOT USED

2. EXPLANATION Of' VALVE ANO INSTRUMENT NWBERS:
CONT ON INSTRUMENT NO. 2 - rev - 24 100 2-471844-2 (UNIT) (TYPE) (SYSTEM) (INSTRUMENT NO.) COORD F-7 VALVE NO. 2 24 100 (UNIT) (SYSTEM) (VALVE NO. l CONT ON 47W3H-4, COORD B-9 All VALVE ANO INSTRUMENT NUMBERS ON A UNIT BASIS ARE PREFIXED WITH THE __§_'_ STRAINER NO. 2 1/2* VENT UNIT NUMBER, 1.E.1-. FOR UNIT 1 AND 2-. FOR UNIT 2. 2-24-538 CONT ON 47W844-4, COORD B-10 3. ALL VALVES ARE THE SAME SIZE AS PIPE UNLESS OTHERWISE NOTED. i!i STRAINER NO. 1 4. MAIN SYSTEM VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITION.
~z __!_!: UNIT 2 LOOP HEADER (STRAINED) 5. ALL INSTRUMENT CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED.
CONT ON 2-471620-2 m 1280 GPM 6. NOT USED 0 2-24-625 ~ 7. NOT USED. COORD LATER l..:.!fl* 28 GPM 2 DRAIN
~ 2-24-356A 8. FBV DENOTES A VALVE USED FOR SYSTEM FLOW BALANCING.
2-24-558 1 _£_ 9. SYSTEM DRAINAGE AS FOLLOWS: I'- TO TURBINE BLDG. STATION DRAINAGE ( 47W85J). _£_ ---TO AUXILIARY BLDG. (NON-TREATED) STATION DRAINAGE ANO COIE BLDG. _£_
;,I ~ 10. NOT USED.
100 z 70 GPM ~ 11. DESIGN CRITERIA/SYSTEM DESCRIPTION REFERENCE DOCUMENTS: GPM ~~tE Ti1E L~tt~,T R~~~\~biN JN T~~L .1i~~ i~'R~l\ ik1i~~i~E -i~~1i~IED *
--'-'- SYSTEM CLASSIFICATION*) .WB-OC-40-63----RAW COOLING WATER SYSTEM 14"
12. REFER TO 47W447-1 NOTE 29 FOR IDENTIFICATION CF SYSTEM PORTIONS OF CLASS G THAT REQUIRE THE HYDROSTATIC TEST TO BE UNDER THE OA PROGRAM.
SAMPLE HEAT EXCH
;,) 2-24-924 13. AND VALVES IN THE T BLDG ARE TVA CLASS H.
NO. 2A IN THE AUXILIARY BL TVA CLASS G. ALL EL 708.0 N m TVA CLASS L. All Y ING IS TVA CLASS H. CONT ON 2-471620-2 IONS ARE THE SAME Cl THE PROCESS LINE COORD E5 .,+ E. ii
.!., ~ ~ ;; 14. NOT USED.
m ,-.
' ~
15. VARIOUS HEAT EXCHANGER FLOW TES LISTED ON THIS SERIES OF DRAWINGS 1*:i t z .!., ~ ARE DESIGN FLOW RATES BASE I COOLING WATER TEMPERATURE OF 95'F. REFER TO CALCULATION 2009D357 FDR THE FLOW RATES ADJUSTED FOR A RAW COOL ING MPERATURE OF 85'F *

16. NOT USED.

17. DIFFER FRCM THE NENT. THE 2-24-529 30 TO DETERMINE IF GPM

15. REPAIR OR REP REQUIRES THE Y SEE NOTE 21 STATOR HEAT EXCH USE Cf' MA.TERI WATER SERVICE.
T 3/4* VENT(TYP) EL 708.0 SPECIFICALLY TI 5400, AL-BRONZE NOT PROPERLY PATIBLE WITH RAW WATER. (REFERENCE DESIGN CRITERIA WB-DC-40-63) __L_ SAMPLE HEA~4-s5s 19. NOT USED.
/ / ..,
EXCH NO. 3A 2-24-527 2-24-528 :;; 20. THIS IS FOR THE FUTURE RCI SUPPLY TO OEMENERALIZED WATER IN THE (EL 708.0) ADDITIONAL MAKEUP WATER TREATl.£NT PLANT. _._._ _._._ 21. THESE BYPASS VALVES MAY BE USED F AS A MEANS Cf' 1 ACHIEVING THE REQUIRED FLOW THRO XCHANGER/COOLER FOR WHICH IT SERVES. THE TEMPERA SHALL REMAIN 2-24-561 2-24-565 OPERABLE AND OPERATE WITHIN OF THE THE CPERATINC CONT ON SCALE DURING THE THROTTLING 47W849-1 2-2-4-5~3 2-2-4-502
/ A /o + SPACE COOLERS 2-24-548 ~ ~ I +
_._._ N
' ---8'_
2-24-562 2-24-566 j;o: MAIN BUS HEAT EXCH
~ TRANSFORMER YARD .,) ~ ---8'_
2-24-567
~ +'
WATTS BAR N' ---8'_ FINAL SAFETY UNIT 2 2-24-521 2-24-568 ANALYSIS REPORT 1 DRAIN HYDROGEN EL 729.0 HEAT EXCH TVA REFERENCE DRAWINGS: UNIT 2 47W4--47---------RAI COOLING WATER-PIPING EXCITER HEAT EXCH 4714-74---------RAI COOLING WATER-EMBEDDED BASE SLAB PIPING EL 729.0 MECHANICAL 4714-75---------RAlJ COOLING WATER-EMBEDDED FILL SLAB PIPING 2-47W610-24----CONTROL DIAGRAM 2-47W611-24----LOCIC DIAGRAM FLOW DIAGRAM 2-47W801-2-----FLOI DIAGRAM T STEAM SEAL OIL HEAT EXCH 1/2" DRAIN
+7W815---------FLOW DIAGRAM TURBINE BLDG EL 729.0 RAW COOLING WATER 47W831---------FLOW DIAGRAM RCULATING WATER 47W834---------FLOW DIAGRAM TREATt.ENT 47W845---------FLOW DIAGRAM W COOLING WATER COMPANION DRAWINGS: TVA DWG NO. 2-47W844-1 R22 47W850---------FLOW DIAGRAM ION a: SERVICE WATER 2-47W844-2 &. 3 471852---------FLOW DIAGRAM DRAINAGE AUX. BLDG. FIGURE 9.2-32(U2) 471853---------FLOW DIAGRAM DRAINAGE TURBINE BLDG. 0-47W844-4, -4A &. -5
UN IT 2 CONF !GU RAT IONS SHOWN OUT-OF-FUNCTION. SEE 2-47WB44-2. D <(
~----K-H/f--------------------------------(~U~NS~T~R~Al~N~ED~)~UN~l~T~2~EM~B~ED~D~E~D~S~U~PP~L~Y_ _ _ ~_ _,
u r ~ (UNSTRAINED) UNIT 1 EMBEDDED SUPPLY 2.Q."
\ \
m UNIT 1 LOOP HEADER (STRAINED) ~ z 28 2A is ~~lbE~ z :~ r (STRA1NED) ::i t5 20" z 0 0 f----U_NI_T_1_LO_O_P_H_E_A_DE_R_(S_T_RA_I_NE_D_I_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ u
~
20" EMBEDDED DISCH UNIT 1 S NI e-------------~-----------------------------------~ \ CONT ON
;;;' !!: UNIT 1 LOOP HEADER (STRAINED) ,-'-----~~-------< ;+-~-------~--<c>t-------< 1-47W844-2 COOR , F-5 2" DRAIN 10" UNIT 2 STRAINED WATER SUPPLY UNIT 1 TURBINE BLDG ~
STATION f-----~ j:o 0-24 w 1-24-965 SUMP 40 GPM CONT ON 1-47W85 - COORD D-4/D-5
35 GPM NO. 7 HEATER DRAIN PUMP COOLER 10*
EL 685.5 1-STN-24-171 70 GPM 1 772 FBV 1~2" 20 L GPM 1 1 525 I 7 ° CNDS. BOOSTER PUMP COOLER EL m I 0 0 0 w 70 GPM 1~2" I
~ I HOTWELL EL 685.5 PUMP COOLER EL 685.5 DRAIN TO 1-RTV-24-1117A CONDENSATE BOOSTER PUMP HX TO 1-RTV-24-1119A CONT. FROM EL 685.5 TO 1-RTV-24-1120A 1-47W844-2 ~--
COOR . Cl 1 DETAIL A2 295 GPM FBV UFSAR AMENDMENT 3 1-CLR-J0-885 WATTS BAR 1 FINAL SAFETY SPACE COOLER (UNIT 2 ONLY) 675 NO. 3 HEATER DRAIN TK. HEATER DRAIN PUMP HX EL 685.5 1/2" VENT PUMP COOLER ANALYSIS REPORT EL 685.5 HX 1" VENT POWERHOUSE DISCH (EMBEDDED) COMPANION DRAWINGS, UNITS 1 & 2 NOTES: 1-47W844-1 &. 3 0-47W844-4 &. 5 MECHANICAL
1. SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM 3.
UNIT 1 THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. THE ~~~Ei~~UY P~11/411E~R~N\11t~~ib ~y ITm AL TERNA TE ID CAN BE ACCESSED IN MAXIMO AS NECESSARY TO DETERMINE AND ARE REQUIRED TO BE CLOSED WITH FLOW DIAGRAM TURBINE BLDG IF PREVIOUS CIDS EXISTED FOR A SPECIFIC COMPONENT. HANDWHEEL REMOVED. RAW COOLING WATER
2. NOT USED.
TVA DWG NO. 1-47W844-2 R24 FIGURE 9.2-33
Cl z 3' <( Q:'. 0 0 w z <( f-z 0 _m* <( u .
~$ /rl---~~=--------------------------i~"~'s~'~*~*'~"~'°~l~UN~I~T~2~'"~"~'°~D~E~ ~s~u~PP~L~Y____--<
UN IT 1 It COMMON
~j --;;~2_*~~2---1*-*1-*s-.
CONFIGURATIONS SHOWN (UNSTRAINED) UNIT 1 EMBEDDED SUPPLY OUT-OF-FUNCTION. SEE 1-47W844-2. UNIT 2 LOOP HEADER (STRAINED) ..2Q,;'._ is UNIT 2 LOOP STRAINERS HEADER .J..!:_ 1 0, 000 GPM EACH EL 685.5 8 (STRAINED) lO" UNIT 2 LOOP HEADER (STRAINED) is z ro
. 8 1/2" ~ f---2-_*_"_'_"_2__1s_c_"_**_c_,_1_,_""_'__,__1_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _~
Ni z 0 CONT ON El ~ UNIT 2 LOOP HEADER (STRAINED) r-'------~~---~---< ::<-~------'r-~---L)f------i 2-47W844-2 COOR , E-4 z __[_ z 2" DRAIN \ 2-24-770 I 8 10" UNIT 1 STRAINED WATER SUPPLY N TURBINE BLDG STATION f------~ 2-24-965 SUMP
~NI ~I -TcNT N 1-47WBJ4-1 COOR D-1 JS GPM EXPOSED EMBEDDED 2-24-615 (SEE NOTE 18 SH 1) 1-47W853-4 PUMP COOLER 10* COOR D-10 .l!'.
30 GPM 70 GPM 1..;.!12" I 2 2-24-525 7 ° CNDS. BOOSTER PUMP COOLER EL 685.5 m I CONT. FROM 2-47W844-2 2 COOR , C-11 764 ~i~~---~ 70 GPM 1..;!12" I I BOOSTER PUMP COOLER HOTWELL PUMP COOL ER TO 2-RTV-24-1117 A EL 685.5 1/2" DRAIN TO 2-RTV-24-1119A CONDENSATE BOOSTER PUMP HX TO 2-RTV-24-1120A EL 685.5 ~ 2-'.'. DETAIL A2
-1 2-24-1021 1/2" DRAIN SPACE COOLER CLR-30-873 FOR UNITS 1 & 2 SHOWN _!.'.'..
ON 1-47W844-2. FBV 28 2-24-1022 1/2" DRAIN UFSAR AMENDMENT 3 L FBV WATTS BAR N~
,o 2 675 2A NO. 3 HEATER DRAIN TK. NO. 7 HEATER DRAIN PUMP HX FINAL SAFETY N~
N~
. 685.5 1 /2" VENT 2-24-1023 PUMP COOLER N~ EL 685.5 ANALYSIS REPORT NO. 3 HEATER DRAIN PUMP HX 1" VENT EL 685.5 2" UNIT 2 DISCH (EMBEDDED)
POWERHOUSE NOTES: UN IT 2 SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM MECHANICAL UNIT 2 THE CIDS SHOWN ON OTHER DOCUMENTS FOR THE SAME COMPONENT. TURBINE BLDG THE AL TERNA TE 1D CAN BE ACCESSED IN MAXIMO AS NECESSARY FLOW DIAGRAM TO DETERMINE IF PREVIOUS CIDS EXISTED FOR A SPECIFIC COMPONENT. RAW COOLING WATER COMPANION DRAWINGS, TVA DWG NO. 2-47W844-2 R13 2-47W844-1 &. 3 0-47W844-4, -4A &. -5 FIGURE 9.2-33(U2)
il ~ Q I Q u 7 IIIIT1DISDtMCEIEl&IIJOII .JE._ 10* 1-:14-111 ..J£:. 11"
---------<--->----KJ~--------------~----~------;~~~~~;~~~~~.::jq~.::;--~-----~-----------------~----------Dl=~="~'='~-~=-=*===*="="~---~'-T------i Z" DRAIN 1-24-787 ..r. ,_,...,,, *j COtlJENSER VACUL.11 PIM'S IA, 1B it. 1C HX SAMPLE HX SAMPLE HX i* t
nl FOR PNL
~ li\;~~~ ~P.11~?t i
i f _,:_
~ *j ;,
j
*j *j El&DIJED DlsatAIIQE IIIIT1 UNIT 1 Dlsat (El&DDED) ,. ~ilt::J=tJltin=!!~,;!'caL~J'i::itr. §-1-Cllt-41-112Ho\SIEENBLANKED<l'FB'l'llll-1-2020-024-001)
TMOO WBN-1-2020-024-001-001-0 UFSAR AMENDMENT 3 WATTS BAR FINAL SAFETY ANALYSIS REPORT POWERHOUSE UNITS 1 &. 2 MECHANICAL TltIS aJNFIGLll,\TIQN aJNTllOL DRAWINc. SUPERSEDES IIIIT 1 AS-CXIISTIIUCTED FLOW DIAGRAM UNIT1 DRAIIIC471H4-!REVISIONL. RAW COOLING WATER TURBINE BLDG TVA DWG NO. 1-47W844-3 R28 FIGURE 9.2-34
(.!) z
s, Ct

C, C, w z 4 ' ----- 1-z
I:
C, u TO 0-4-7W8-44--4A CCX>RD A-3
---20* UNIT 2 DISCHARGE UNIT 2 DISCHARGE (EMBEDDED) 2-24-786 ~ .-C-S-EE-NO-TE-18_ _.,1---------------------------,.-------------------------------,,-----------------------------------------_._---------Dl---.. . . . ., _. . . =................;..____..._____ --4 SHEET 1) 8 GPM 2-24-787
.1 2-24-810 :,. j 2-24-883 CONT. ON 2-24-721 2-24-815 229 GPM 2-47W620-5 COORO C-8 24 GPM __1_" 2-24-791 l--l)o(I----~
2-24-33JA ~S~ CONDENSER VACUUM HX FOR 2-RE-90-120/121 PUMPS 2A, 28 .t. 2C HX (280 CPM) 160 CPM 2-STN-24-589 \ SAMPLE HX. NO. 14 4" 2C j EL 708.0 ~CO~N~T~.~ON~---' SAMPLE HX NO. 1OA EL 685.5 SAMPLE HX NO SA El 721.75 2-024-1162 2-24-1000 2"- 2 j SAMPLE HX. NO. 11 EL 729.0 SAMPLE HX. NO. 1A SAMPLE HX. NO. 4A SAMPLE HX. NO. 7A EXPOSED EL 708.0 EL 708.0 EL 708.0 EMBEDDED 30" TO 0-47W844-4 .. COORD A-13 EMBEDDED DISCHARGE UNIT 2 2-24-801 2-24-997 SPACE COOLER EL 729.0 ..!!"- UNIT 2 DISCH (EMBEDDED) NOTES: 2-STN-24-723 SCK CIDS IN THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE CIDS 2-24-599 SHOWN ON OTHER DOCUMENTS FOR THE SAME Cot.FOMENT. THE Al TERNATE ID CAN BE
;., ACCESSED IN MAXIK> AS NECESSARY TO DETERMINE IF PREVIOUS CIDS EXISTED FOR A SPECIF IC CCM"ONENT.
FBV TO 0-47W844--4 ---10* UNIT 2 F .W. PUMP ~ COORD A-13 TURBINE OIL ii,+ LOOP HEADER HX *'
~:;c EL. 729.0 *c ~~~
8!§ i) FBV STANDBY MAIN F. W. PUMP COOLER EL 729.0 135 GPM i) WATTS BAR FBV FINAL SAFETY 2-24-9-48 ANALYSIS REPORT STANDBY MAIN F .W. PUMP OIL HX EL 729.0 POWERHOUSE
---18" EMBEDDED DISCHARGE UNIT 2 UNIT 2 UNIT 2 MECHANICAL TURBINE BLDG FLOW DIAGRAM RAW COOLING WATER COMPANION DRAWINGS: TVA DWG NO. 2-47W844-3 R14 2-47W844-1 ,: 2 0-4718+4-+, -4A a. -5 FIGURE 9.2-34(U2)
l'.) z ~ 3= <( (l:'. D 0-24-385A 0-PE D FROM w EMBEDDED DISCHARGE UNIT 2 2-47W844-J z COOR E-1 <( ~ f- ~------------<----- z (SEE NOTE 18) 2 _4 _~20 lZ" UNIT 2 FROM H L 0-47W844-4A VENT COOR E-2 _!.Q' UNIT 2 LOOP HEADER FROM 2-47W844-3 C00RD F-1 UNIT 1 ~ O-FLG-24-1192--i [---ji*j 6" 0-2-4--1185 NOTE J 1-24-606 11 ~ - (SEE NOTE 18) 1i .,f
"-----j------_...=--"it _ __J (SE~EGN:TE 18) 0 0 827 ~ - ------r--~---~ / 0-24-838 i,l'- 1,1*- i (SEE NOTE 18) / 1-24-820 i
i . 10* I I ~1 0-24 0 _ 24 _ 1129 _ TURB~NE BL~G UN~T_1______________ ~ CONT FROM 0-47W844-4 NOTES: C00RD F-7
1. SOME CIDS ON THIS DRAWING HAVE BEEN CHANGED AND MAY DIFFER FROM THE
'1 §l~s sfH2~~Eg~Egr~~RM~~~E~~s N~2~si~~ys~~E D~~~~s~~~T i FT~~E~ciQ~N~rns ID EXISTED FOR A SPECIF IC CO~PONENT.
CONT FROM 1*
2. NOT USED 0-47W84+-4 COORD G-7 &.__ 0- 3. THESE VALVES ARE STAINLESS STEEL ANO INSTALLED ON CARBON STEEL PIPING CONT FROM w- I 0-24-823 I WITH FLANGE INSULATING KITS.
0-47WB-44-4 COOR H-5 1-1/2' I I EL 763.5 I
\..I.) I ~t-_J UFSAR AMENDMENT 3 0-61-1102 WATTS BAR ISV- FINAL SAFETY 4-1174 CONT ON ~ 0-47W8-44-4 ANALYSIS REPORT COOR , F-2 li'o" I FBV 1-47W845-2 COORD E11 A/C UNIT POWERHOUSE -2* ;\ I EL 750 5 2 ---t----j+_-_-_~~== .. c _) UNITS 1 & 2 18=,.;~~.::i;::.----,---,1---IS~~
024-1175 ADDITIONAL EQUIPMENT BUILDING UNIT 1 L____________~ dJ MECHANICAL DET A4 AUXILIARY BLDG FLOW DIAGRAM COMPANION DRAWINGS: 1-47'11'844-1 THRU 3 RAW COOLING WATER 2-47W844-1 THRU 3 D-47W844-4A & 5 TVA DWG NO. O-47W844-4 R11 FIGURE 9.2-35
----<1-47W610-24-1,COORD H-3 Cl z 1-L-81 '*,J----<1-47W610-24-2,COORD f-1> 1-PI 3= 24-27A
<( LOG 0-TE 1-47W610-24-3,COORD A-8 oc: T3151A 24-6A 0 - - - - ~ - - - - - - - - - ~ - - - - - - - - - - - - - - - - - - - - - < - ~ - - - < : 1 - 4 7 W 6 1 0 - 2 4 - 2 , C O O R D A-2 0 w <)-47W61 0-24-3, COOR A-9 )>-**------<r 1-L-519 / z TO GEN H2 GAS DRYER <( UNIT 1 STRAINED WATER HEADER I 1-47W610-35-1 ,COOR D-9 t-z 24-49 _J_ r-- ---7 I 1 I 0-TE I I
~I I I 24-9A I I 0
<( I I I u LOG 0-TE 24-6B 24 SEAL OIL HEAT 1 EXCHANGERS L ___ _ _ _ _ _ _J fal-511
~ \~.;=?A 1-R-124 ~
I +~ I i- 1~ 0-TE I 0-PI
1-M-15 I I
'"--->---------------------------< I I 24-98 : 24-22 I MV/I@-L-40 MV/I0-L-4 I 1-TM 1-TM LOG 0-TE ~2-M-15 24-74A 24-73A T3155A 24-12A ~D ,------------+ I NOTES:
1-L-96
------* I 1. WATER SUPPLIED FROM PUMPING STATION. ! I}}

ML20323A303

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