ML19298B523
| ML19298B523 | |
| Person / Time | |
|---|---|
| Site: | Browns Ferry  |
| Issue date: | 10/04/2019 |
| From: | Tennessee Valley Authority |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML19298B540 | List: |
| References | |
| Download: ML19298B523 (85) | |
Text
{{#Wiki_filter:BFN-26 TABLE OF CONTENTS 9.0 RADIOACTIVE WASTE CONTROL SYSTEMS 9.1 Summary Description ................................................................................................9.1-1 9.2 Liquid Radwaste System ...........................................................................................9.2-1 9.2.1 Power Generation Objective .........................................................................9.2-1 9.2.2 Power Generation Design Basis ...................................................................9.2-1 9.2.3 Safety Design Basis......................................................................................9.2-1 9.2.4 Description ....................................................................................................9.2-1 9.2.5 Power Generation Evaluation .......................................................................9.2-5 9.2.6 Safety Evaluation ..........................................................................................9.2-6 9.2.7 Inspection and Testing..................................................................................9.2-7 9.3 Solid Radwaste System ............................................................................................9.3-1 9.3.1 Power Generation Objective .........................................................................9.3-1 9.3.2 Power Generation Design Basis ...................................................................9.3-1 9.3.3 Safety Design Basis......................................................................................9.3-1 9.3.4 Description (See Figures 9.2-3a, 9.2-3d, 9.2-3e, and 9.2-3f) ........................9.3-1 9.3.5 Power Generation Evaluation .......................................................................9.3-5 9.3.6 Safety Evaluation ..........................................................................................9.3-5 9.3.7 Inspection and Testing..................................................................................9.3-6 9.4 Gaseous Radwaste System (Deleted) ......................................................................9.4-1 9.5 Gaseous Radwaste System (Modified) .....................................................................9.5-1 9.5.1 Power Generation Objective .........................................................................9.5-1 9.5.2 Power Generation Design Basis ...................................................................9.5-1 9.5.3 Safety Design Basis......................................................................................9.5-1 9.5.4 Description ....................................................................................................9.5-1 9.5.5 Safety Evaluation ..........................................................................................9.5-6 9.5.6 Inspection and Testing..................................................................................9.5-10 9.0-i
BFN-26 LIST OF TABLES RADIOACTIVE WASTE CONTROL SYSTEMS Table Title 9.2-1 Deleted 9.2-2 Deleted 9.2-3 Normal and Maximum Concentration of Liquid Radioactive Wastes and Volumes of Radwaste Tankage 9.2-4 Radioactivity Contents of Tanks and Systems not Designed to withstand Tornado, Maximum Probable Flood or Design Basis Earthquake 9.5-1 Estimated Offgas Release Rates Per Unit Sheets 1-2 9.5-2 Process Instrument Alarms 9.5-3 Offgas System Major Equipment Items Sheets 1-2 9.5-4 Equipment Malfunction Analysis Sheets 1-2 9.5-5 Isotopic Inventory - Charcoal Offgas System Sheets 1-5 9.5-6 Radiological Exposures - Modified Offgas System Component Failure 9.5-7 Effluent - Gland Seal Offgas Subsystem 9.0-ii
BFN-26 LIST OF ILLUSTRATIONS RADIOACTIVE WASTE CONTROL SYSTEMS Figure Title 9.2-1a (Deleted) 9.2-1b (Deleted) 9.2-2 (Deleted) 9.2-3a Radwaste System - Flow Diagram 9.2-3b Radwaste System - Flow Diagram 9.2-3c Radwaste System - Flow Diagram 9.2-3d Radwaste System - Flow Diagram 9.2-3e Radwaste System - Flow Diagram 9.2-3f Radwaste System - Flow Diagram 9.2-3g Radwaste System - Flow Diagram 9.2-3h Radwaste System - Flow Diagram 9.2-3i Radwaste System - Flow Diagram 9.2-3j Radwaste System - Mechanical Control Diagram 9.2-3k Radwaste System - Mechanical Control Diagram 9.2-3l Radwaste System - Mechanical Control Diagram 9.2-3m Radwaste System - Mechanical Control Diagram 9.2-3n Radwaste System - Mechanical Control Diagram 9.2-3o Radwaste System - Mechanical Control Diagram 9.2-3p Radwaste System - Mechanical Control Diagram 9.2-3q Radwaste System - Mechanical Control Diagram 9.2-3r Radwaste System - Mechanical Control Diagram 9.2-3s Radwaste System - Mechanical Control Diagram 9.2-3t Radwaste System - Mechanical Control Diagram 9.2-4 (Deleted) 9.2-4a (Deleted) 9.2-4b (Deleted) 9.2-4c (Deleted) 9.2-4d (Deleted) 9.2-4e (Deleted) 9.2-4f (Deleted) 9.3-1a (Deleted) 9.3-1b (Deleted) 9.3-2a (Deleted) 9.3-2b (Deleted) 9.5-1 sht 1 Offgas System Flow Diagram 9.5-1 sht 2 Offgas System - Flow Diagram 9.5-1 sht 3 Offgas System - Flow Diagram 9.5-1 sht 4 Offgas System - Flow Diagram 9.5-1 sht 5 Offgas System - Flow Diagram 9.5-1 sht 6 Offgas System - Flow Diagram 9.0-iii
BFN-26 LIST OF ILLUSTRATIONS RADIOACTIVE WASTE CONTROL SYSTEMS Figure Title 9.5-2 Offgas System - Flow Diagram 9.5-3 Offgas System - Flow Diagram 9.5-4 Offgas System - Flow Diagram 9.0-iv
BFN-18 9.0 RADIOACTIVE WASTE CONTROL SYSTEMS 9.1
SUMMARY
DESCRIPTION The radioactive waste systems are designed to process the radioactive wastes generated during plant operation. These wastes can be liquid, solid, or gaseous. Where permitted, the liquid and gaseous radioactive wastes are discharged to local water streams or the atmosphere, respectively, at concentrations which at a maximum are well below established regulatory limits. Radioactive wastes are subject to the requirements of applicable plant procedures. The Liquid Radwaste System collects, treats, and returns processed radioactive liquid wastes to the plant for reuse. Treated radioactive wastes not suitable for reuse are discharged from the plant through the condenser circulating water discharge system packaged for onsite storage in approved storage areas or shipped to offsite processing or disposal facilities. The Solid Radwaste System collects, processes, stores, packages, and prepares solid radioactive waste materials for transfer to approved onsite storage areas or shipment to offsite processing or disposal facilities. The Gaseous Radwaste System collects and processes gaseous radioactive wastes from the main condenser air ejectors, the startup vacuum pumps, condensate drain tank vent, and the steam packing exhauster, and controls their release to the atmosphere through the plant stack so that the total radiation exposure to persons outside the controlled area is as low as reasonably achievable and does not exceed applicable regulations. 9.1-1
BFN-26 9.2 LIQUID RADWASTE SYSTEM 9.2.1 Power Generation Objective The Liquid Radwaste System collects, treats, and returns processed radioactive liquid wastes to the plant for reuse. Treated radioactive wastes not suitable for reuse and the suitable liquid waste for reuse whose volume is not needed for plant operations or not desired for reuse are discharged from the plant or packaged for offsite disposal. 9.2.2 Power Generation Design Basis The Liquid Radwaste System shall be designed so that the liquid radwastes which are discharged from the plant are within the limits specified in the ODCM and the operation or availability of the plant is not limited thereby. 9.2.3 Safety Design Basis The Liquid Radwaste System shall be designed to prevent the inadvertent release of significant quantities of liquid radioactive material from the restricted area of the plant so that resulting exposures are within the guideline values of 10 CFR 20, Appendix I of 10 CFR 50, and/or 40 CFR 190. 9.2.4 Description The Liquid Radwaste System collects, processes, stores, and disposes of all radioactive liquid wastes. The system is sized to handle the radioactive liquid wastes from all three units of the plant. The radwaste facility is located in the radioactive waste building. The Radwaste Building is located and the radwaste equipment is arranged as shown in Figures 1.6-23 and 1.6-24. Included in the Liquid Radwaste System are the following:
- a. Piping and equipment drains carrying potential radioactive wastes,
- b. Floor drain systems in controlled access areas and/or those areas which may contain potentially radioactive wastes, and
- c. Tanks, piping, pumps, process equipment, instrumentation, and auxiliaries necessary to collect, process, store, and dispose of potentially radioactive wastes.
Equipment is selected, arranged, and shielded to permit operation, inspection, and maintenance with personnel exposures within the limits specified in 10 CFR 20 and applicable plant procedures. For example, sumps, pumps, valves, and instruments 9.2-1
BFN-26 are located in controlled access areas. A resin trap with differential pressure instrumentation is installed in the effluent line for the radwaste waste demineralizer. Details of the radwaste system are shown in Figures 9.2-3a through t. Operation of the waste system is essentially manual start-automatic stop. The system is divided into several subsystems so that the liquid wastes from various sources can be kept segregated and processed separately. Cross connections between the subsystems provide additional flexibility for processing of the wastes by alternate methods. The liquid radwastes are classified, collected, and treated as either high purity, low purity, chemical, or detergent wastes. The terms "high" purity and "low" purity refer to conductivity and not radioactivity. These liquid radwastes are referred to in the figures as "CRW" (clean radwaste) and "DRW" (dirty radwaste). 9.2.4.1 High Purity Wastes High purity (low conductivity) liquid wastes which are collected in the waste collector tank are from the following main sources:
- a. Drywell equipment drain sumps,
- b. Radwaste Building equipment drain sump,
- c. Turbine Building equipment drain sumps,
- d. Reactor cleanup systems,
- e. Decantate from cleanup phase separators,
- f. Decantate from condensate phase separators,
- g. Waste package drain tank,
- h. Turbine Building condensate pump pit equipment drain sumps,
- i. Standby Gas Treatment Building sumps,
- j. Floor drain filter and sample tank pump discharge,
- k. Residual Heat Removal System.
The high purity wastes are processed by filtration and ion exchange through the waste filter and waste demineralizer. After processing, the waste is pumped to a waste sample tank where it is sampled and then, if satisfactory for reuse, and there 9.2-2
BFN-26 is sufficient available volume in the condensate storage tanks to accept the waste it is transferred to the condensate storage tanks as makeup water. An alternate method of processing high purity wastes is the use of vendor supplied skid mounted equipment interconnected with the Radwaste System. After processing, depending on effluent quality and plant needs, the water can be sent to either the waste sample tank, floor drain sample tank, waste surge tank, or waste collector tank. If the analysis of the sample reveals water of high conductivity (>1 s/cm) or high radioactivity concentration (>10-3 Ci/ml), it may be returned to the system for additional processing. These wastes may be released to the discharge canal if allowable discharge canal concentrations are not exceeded. 9.2.4.2 Low Purity Wastes Low purity (high conductivity) liquid wastes which are collected in the floor drain collector tank are from the following sources:
- a. Drywell floor drain sumps,
- b. Reactor Building floor drain sumps,
- c. Radwaste Building floor drain sumps,
- d. Turbine Building floor drain sumps,
- e. Chemical waste tank,
- f. RHR Systems,
- g. Turbine Building backwash and receiver pit floor drain sumps,
- h. Turbine Building condensate pump pit floor drain sumps, and
- i. Offgas condensate collector sump.
These wastes generally have low concentrations of radioactive impurities; therefore, processing consists of demineralization, filtration, and subsequent transfer to the floor drain sample tank for sampling and analysis. An alternate method of processing low purity wastes is the use of vendor supplied skid mounted equipment interconnected to the permanent Radwaste System. After processing, depending on effluent quality and plant needs, the water can be sent to either the waste sample tank, floor drain sample tank, waste surge tank, or waste collector tank. 9.2-3
BFN-26 If the analysis indicates that the concentration of radioactive contaminants is sufficiently low and the water is not needed for plant reuse, the sample tank batch is transferred to the circulating water discharge canal for dilution with condenser circulating water as necessary to meet plant effluent discharge requirements of the ODCM. Manual valves are present between the floor drain sample tank and the discharge to preclude the possibility of unanalyzed radioactive water leaking directly to the river. Large-mesh, basket-type strainers are located in the floor drain and waste subsystems to prevent surge tank eductors from becoming plugged. The ODCM provides the methodology to administratively control limits below regulatory limits. Tritium is typically present in the radwaste effluents. The 10 CFR 20 limit for tritium is 1E-3Ci/ml - and the incremental contribution of the plant release is insignificant compared to current regulatory guidance. Liquid wastes are released at a rate to give Effluent Concentration Limit (ECL) fraction of 10 in the discharge canal during the period of the discharge. Since the discharge is on a batch basis, the daily average concentration in the canal is correspondingly less. The discharge from the canal to the environs, therefore, is equal to or less than an ECL fraction of 10. Mixing in Wheeler Reservoir provides additional dilution. Average annual concentrations of released isotopes and the resulting dose to members of the public are provided in the Annual Release Report. 9.2.4.3 Chemical Wastes Chemical wastes are collected in the chemical waste tank and are from the following main sources:
- a. Shop decontamination solutions,
- b. Laboratory drains,
- c. Reactor Building decontamination drains,
- d. Chemical waste from cleanup and condensate precoat tanks,
- e. Radwaste Building floor drain sump,
- f. Radwaste floor drain and waste filter decontamination drain, and 9.2-4
BFN-26
- g. Fuel pool filters decontamination drain.
Chemical wastes are typically transferred in small quantities to the floor drain collector tank for processing. The chemical contaminants and radioactivity concentrations are variable and largely dependent on plant operational activities which drain to the chemical waste tank. Normally, the radioactivity concentrations are low enough to meet discharge canal concentration limits (after dilution). These wastes may also be transferred to the floor drain collector tank and processed in the same manner and with the same equipment as low purity wastes. 9.2.4.4 Detergent Wastes Detergent and other plant cleaning wastes are collected in the laundry drain tanks. These wastes are primarily from plant cleaning and decontamination activities and are typically of low radioactivity concentration. The laundry drain tanks may be crosstied with the cask decontamination tank. Prior to discharge, tank contents are recirculated through the laundry drain filter, sampled, and discharged into the circulating water canal at a rate not to exceed the limits of the ODCM. As an alternative, tank contents may be transferred to the floor drain collector tank and be processed in the same manner and with the same equipment as low purity waste. Cask decontamination liquid is collected in the 15,000-gallon cask decontamination tank. This liquid is essentially high conductivity water of low radioactivity concentration. The liquid is sampled, filtered through the laundry drain filter, and discharged into the circulating water canal at a rate such that the limits of the ODCM are not exceeded. As an alternative, tank contents may be transferred to the floor drain collector tank and be processed in the same manner and with the same equipment as low purity waste. 9.2.5 Power Generation Evaluation Liquids having levels of radioactivity above technical specification limits are not discharged from the plant. Pumpout rates of the liquid radwastes are variable. Prior to discharge, wastes are sampled and analyzed in batches. The liquid waste is then discharged at a rate such that technical specifications are not exceeded. Discharge is into the discharge canal of Units 1, 2, and 3 or into the cooling tower blowdown. A monitor on the waste system discharge line will alarm on excessive activity concentration and will automatically stop the discharge. The tank level and laboratory analysis records are retained as a record of waste discharge from the plant (see Subsection 7.12). The monitor will be set to trip at a total ECL fraction of less than or equal to 10 in the plant effluent. When in the open cooling tower mode, the minimum dilution flow rate will be approximately 400,000 gpm or approximately 360,000 gpm in the helper mode. (One unit in operation, with two of the three circulating water pumps 9.2-5
BFN-26 running.) The monitor will be set to limit the canal concentrations to less than the applicable regulatory limits. At this level, the monitor will close valves 77-58B and 77-58A (Figure 9.2-3c of the FSAR). In all cooling modes, discharge from the radwaste system is accomplished by a 3-inch and a 1-inch line upstream of the radiation monitor. In the open mode, interlocks are provided which prevent the discharge of liquid waste into a condenser cooling water discharge conduit when fewer than two of the associated circulating water pumps are in operation. When the cooling towers are in the helper mode, additional interlocks are provided which prevent discharging liquid waste into a discharge conduit in which the flow is being routed to the towers. An additional waste discharge line connects with the cooling tower blowdown line. A flow restricting valve is installed in the waste discharge line which connects to the tower blowdown line. The valve will be used to vary the flow rate, depending upon the radioactivity of the waste, to assure that the canal concentration is within technical specifications and the ODCM. The processing equipment is located within concrete buildings to provide secondary enclosures for the wastes in the event of leaks or overflows. Tanks and equipment which contain wastes with high radioactive concentrations that could be determined to result in increased dose to personnel are shielded. Except where flanges are required for maintenance, most pipe connections are welded to reduce the probability of leaks. Process lines which penetrate shield walls are routed to prevent a direct radiation path from the tanks or equipment. Control of the waste system is from local panels in the Radwaste Building. Because the radioactivity concentrations in the plant discharge canal do not exceed the limits of the ODCM and the technical specifications and because the operation and availability of the plant is not limited, the Liquid Radwaste System fulfills the power generation design basis. 9.2.6 Safety Evaluation Table 9.2-3 shows the total activity of liquid and solid radwaste that could be stored within the radwaste system if all operating tanks were full to working level. The tanks are located inside the Radwaste Building which extends 20 feet below grade to its lowest floor. The total maximum activity of solid and liquid contents of all tanks, when full to their maximum operating levels, is also shown. Loss of tank contents within the Radwaste Building will result in the water flowing to the lowest floor level within the radwaste structure by way of stairwells and other openings. Using the approximate floor surface area of 12,232 square feet at elevation 546.5', a maximum volume of 383,060 gallons will result in a liquid depth of 50 inches above elevation 546'. At an average concentration of 0.2 microcurie/cc, the liquid activities will be 290 curies for the maximum volume conditions. 9.2-6
BFN-26 The concrete walls and slabs of the Radwaste Building have been examined for seismic loading. It has been determined that the Radwaste Building walls and slabs housing radioactive equipment can withstand the Design Basis Earthquake (DBE). Should a failure of the tanks, vessels and piping containing radioactivity occur, the spilled liquid would be retained in the Radwaste Building. In order to assess the impact of a liquid radwaste spill on the nearest potable water supply surrounding the BFNP site, a study was conducted to determine if the limits of 10CFR20, Appendix B, Table 2, Column 2 will be exceeded. The results of the study involving a postulated release of liquid radwaste from the worst offending tank indicates that the limits of 10CFR20 will not be exceeded. The worst offending tank identified is the waste collector tank with a maximum operating volume of approximately 38,000 gallons and maximum activity of 1.4E+8 microcuries. The isotopic distribution contained in Table 9.2-4 served as the basis of the study. Actual isotopic distribution may vary with plant operation and related support activities. Since a postulated release of liquid radwaste from the worst offending tank resulted in radionuclide concentrations well below the limits of 10CFR20 in the unrestricted area around the BFNP site then it can be concluded that the design basis is met. 9.2.7 Inspection and Testing The Liquid Radwaste System is normally operating on an "as required" basis during operation of the nuclear plant thereby demonstrating operability without any special inspections or testing. 9.2-7
BFN-18 Table 9.2-1 (Deleted by Amendment 18)
BFN-18 TABLE 9.2-2 (Deleted by Amendment 18)
BFN-28 Table 9.2-3 NORMAL AND MAXIMUM CONCENTRATION OF LIQUID RADIOACTIVE WASTES AND VOLUMES OF RADWASTE TANKAGE Liquid Total Solid (each) Volume Normal Max. Normal Max. Normal Max. (Total) Conc. Conc. Act. Act. Act. Act. Tank/Vessel Quantity (Gal.) (c) Ci/cc Ci/cc Ci Ci Ci Ci Waste Surge 1 73,220 8.3 x 10-6 8.3 x 10-4 2.3 x 103 2.3 x 105 --- --- Waste Sample 4 75,470 3 x 10-5 3 x 10-3 8.6 x 103 8.6 x 105 --- --- Floor Drain Sample 1 15,785 7 x 10-6 2 x 10-3 4.2 x 102 1.2 x 105 --- --- Laundry Drain 2 1,920 1 x 10-5 1 x 10-2 7.3 x 101 7.3 x 104 --- --- Waste Collector 1 37,780 1 x 10-2 1 x 100 1.4 x 106 1.4 x 108 --- --- Floor Drain Collector 1 31,400 3 x 10-5 8 x 10-2 3.6 x 103 9.5 x 106 --- --- Cleanup Phase Separator 3 14,840 2 x 10-2 1 x 100 1.1 x 106 5.6 x 107 1 x 109 1 x 109 Cleanup Backwash 3 6,000 2 x 10-2 1 x 100 4.5 x 105 2.3 x 107 6 x 107 5 x 109 Receiving (a) Condensate Phase 4 50,700 5 x 10-5 1 x 10-4 9.6 x 103 1.9 x 104 3.9 x 107 9.7 x 107 Separators A, B, C & D Condensate Phase 2 25,400 5 x 10-5 1 x 10-4 4.8 x 103 9.6 x 103 1.5 x 107 1.5 x 109 Separators E & F Condensate Backwash 3 19,500 5 x 10-5 1 x 10-4 3.7 x 103 7.4 x 103 3 x 106 1 x 108 Receiving (b) Spent Resin 1 1,630 5 x 10-5 1 x 10-4 3.1 x 102 6.2 x 102 2 x 106 2 x 108 Waste Backwash Receiver 1 7,170 5 x 10-5 1 x 10-4 1.4 x 103 2.7 x 103 8 x 106 2 x 108 Chemical Waste 1 5,100 2 x 10-4 7 x 10-3 3.9 x 103 1.4 x 105 --- --- Cask Decontamination Tank 1 15,300 1 x 10-5 1 x 10-2 5.8 x 102 5.8 x 105 --- --- NOTES: (a) Cleanup Backwash Receiving Tanks in Reactor Building (b) Condensate Backwash Receiving Tanks in Turbine Building (c) Additional liquid radwaste operating volume of 26,890 gal. is not shown, but is included in the total working volume in 9.2.6. This volume represents the liquid contained in the piping, fitter vessels, sumps and miscellaneous tanks/vessels in the Radwaste Building. The total working volume does not include the tanks represented by Notes (a) and (b) above.
BFN-28 Table 9.2-4 (Sheet 1) RADIOACTIVITY CONTENTS OF TANKS AND SYSTEMS NOT DESIGNED TO WITHSTAND TORNADO, MAXIMUM PROBABLE FLOOD OR DESIGN BASIS EARTHQUAKE Maximum Activity Per Tank Number or System of (Ci) Isotopic Distribution, Percent of Total Activity (b) Vessel or System Name Tanks Total Sr-89 Sr-90 Sr-91 Mo-99 1-131 1-133 1-135 Cs-134 Cs-137 Ba-140 Ce-144 Np-239 CO-58 CO-60 Waste Surge Tank 1 2.3 x 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Waste Sample Tank 4 2.1 X 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Floor Drain Sample Tank 1 0.6 x 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Laundry Drain Tank 2 3.6 X 104 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Waste Collector Tank 1 1.4 x 108 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1
- Floor Drain Collector 1 9.5 x 106 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Tank Cleanup Backwash 3 5.0 X 109 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Receiver Tank (a) 8 Condensate Backwash 3 1.0 x 10 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Receiver Tank (a) 8 Spent Resin Tank (a) 1 2.0 X 10 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Waste Backwash Receiver 1 2.0 x 108 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Tank (a)
Chemical Waste 1 1.4 X 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Condensate Storage Tank 5 2.0 X 106 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Condensate Transfer - 6.0 x 104 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 System Condensate Filter/ 27 1.0 X 108 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Demineralizer Tanks (a) Fuel Pool Filter/ 4 2.0 x 108 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Demineralizer Tanks (a) Waste Demineralizer Tank (a) 1 3.0 X 108 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Evaporator Feed Tank 1 5.0 x 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Waste Filter Tank (a) 1 1.0 X 106 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Floor Drain Filter Tank (a) 1 9.0 x 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1
BFN-28 Table 9.2-4 (Sheet 2) RADIOACTIVITY CONTENTS OF TANKS AND SYSTEMS NOT DESIGNED TO WITHSTAND TORNADO, MAXIMUM PROBABLE FLOOD OR DESIGN BASIS EARTHQUAKE Maximum Activity Per Tank Number or System of (Ci) Isotopic Distribution, Percent of Total Activity (b) Vessel or System Name Tanks Total Sr-89 Sr-90 Sr-91 Mo-99 1-131 1-133 1-135 Cs-134 Cs-137 Ba-140 Ce-144 Np-239 CO-58 CO-60 Cask Decontamination 1 5.8 X 105 0.7 0.2 8.6 18.3 8.6 14.3 6.4 0.1 0.2 18.3 0.1 18.6 1.0 0.1 Tank Cleanup Phase Separator (a) 3 1.02 x 109 11.9 7.9 - - 2.0 - - 3.9 7.9 29.6 8.7 - 22.9 4.2 Condensate Phase Separators:
- A, B, C & D (a) 4 9.7 x 107 2.2 0.7 - 19.8 17.2 - - 0.3 0.7 46.5 0.1 8.7 3.3 0.4 - E & F (a) 2 1.5 x 109 2.2 0.7 - 19.8 17.2 - - 0.3 0.7 46.5 0.1 8.7 3.3
- The percent of Cs-134 and Cs-137 may be elevated if THERMEX/Ultrex Train A brine is being reprocessed.
(a)Most of the activity is in solid form. (b)Original design basis isotopic distribution valid for historical reference. Actual distribution may vary with plant operation and related activities.
BFN-19 Figures 9-2-1a and 1b (Deleted by Amendment 17)
BFN-16 Figure 9.2-2 Deleted by Amendment 7.
££0~ l-0£83Lt-O VII L9 CONT Cl -.,_..;2;.-,. 1 /;.;2;._-c,1-,
0 THIS DWG
- C CNDS p
w
...I a
LL Z
~
0-47E830-6. f5 2297 (1/4") z z IL
- ii:
Z
- ...J z " z -
< c o::.....
- z iii
< < ~ ~ ~ i :! < ~ ..._~ .. ~~
~ ~ ~=~
Z Z j:Ji 0
~-- < < §~z ~<
" - 1r HEADER SEAL ~e,,j
<::c
~ <
~
CD i
~
Z.-. a:::::c C
~
.,,"lz Z
It:: CL~
~
0
~
ID~U"I c...
- i:
~ ~u
- rii::!z:
<o c~::C Zl-0::
>1-<
WZD:::
- ii~
w.,~8~ H 1" 1 " VENT
' . ~--
Vl(IJ < m cu:, :rii:: CL... o <..._.o t:;~o
-N HL MAKEUP STOP EL 549' -r-...,..
X ,..._ I ~ _,4" VENT TO
~C .t. WPS ~F~L~E~L_5~7~*~~~-0~~---l!l---1~--It--~*I~,,---llf-___1,~l-----------~-~--~---l~~c-~-~---I1!:;f----'~1.-~*I~,-]1r----------------------'...-./~r-~;-i~!~-./~r-7'_ _,l....-~1~§-,!__ :r-7;.,r-T~--:..-~';....-~'-F~L~E~L~5~*~o_.~o-l TURB-;NE BLDG--1
" ,-,---'~-~-~_.,,~BA[_ LS_, ROOM 1" SERVICE _,, 1 LL MAKEUP START I' ,,. _ I 7 'l:;J M CONNECTION __.,. EL 5+9'-4" '/ I~ I~
cnl,~ I J 0 2288 77-22 6"
,CQNTON~ I'
. . *N *N *N O"J
~
~
N ( LE ~ T!._-'9 Q
.n ---- 0-47E85~~~
r-.
- N N
.n *n *n *n *n *n *n *n
""n' z ~ V burLET "A H_.., *r*~ "B"R '
3" I 4" .- EL 546.0
'<D
*n *n
- 3"
/
.- 1" 1 " SEAL HOR DR --'
1-77-718 C N
~
w ~
= '
~
!;;: ..._ ~
G f
~
OFF-GAS C' >o ~ W zz w DRAINS ~ CONT ON 1"
0 ~
- E1- I< "T ~< o:::.....
~
a.. z (1,2,3- . zz ::::,z
...., .... 11..0 1-Z O CON VI I-<
47E809-3) 2-77-718
\ t :::~ I - ~
~c c§z ==;:iO
.... z <C:i:
O:::~ VI C
<~jl ..,.0:::
;::c IL 0 .... 001- w I- 1 1-...J z o:::o::: Uz LL:::I! w< ~c~ ....1LL..o w :iw
/ ,_FROM SJAE c:i o:::o::: o:::zu ->u. 1-D.. C:::E J, I ',.: r2 LLD.. n.C a..<_. N ....1::::1= zw 1* i...o ....
.~r, ::
r,
~ s~,
3-77-718 4" CONT ON (1,2,3-47E809-2) 4" 4" 1*
.-*'"*-3----1-,J- *--, '11 A 0-11-2311 a,;*'- LOOP 0-11-2310 SEAL El 537'-4" i...
I STACK DRAIN CONT ON 0-47E851-1
.4" 4 "~
717 I 6
"-...._ B" fLOATWELL
= *n 4' 680 4'
~
El 537 .0 - m m w ~
' ' 716 F
- L FROM STEAM "--12*-o* WATER SEAL
- NOTES:
-C' PACKING EXHAUSTER 1. FOR DETAILED OPERATING INSTRUCTION, BACKWASH RATES, ETC, OFF-GAS CONDENSATE SUMP OFF-GAS CONDENSATE DRAIN SUMP PUMPS CAPACITY 50 GPM o 67 FT TDH
*n SEE MANUFACTURER'S INSTRUCTION MANUAL.
- 2. All VALVES ARE SAME SIZE AS PIPE UNLESS OTHERWISE NOTED.
- 3. HEAVY LINES SHOW WATER FLOW THROUGH SYSTEM DURING NORMAL OPERATION.
3* 4. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING TO WASTE COLLECTOR POSITION.
<D
~ TANK (CONT SH 2) 5. All PRESSURE AND TEST CONNECTIONS ARE 1/2" UNLESS OTHERWISE
~
- NOTED .
-"~ ~ " ~ 6. INSTRUMENT NUMBERS ARE cot.MON TO All UNITS EXCEPT WHERE A C w ~
~ ~<
Vl j 8 I=
~
~-~-
ZNZ~
" 1--~*s><:i--....
7078 = PREFIX OF THE UNIT NUMBER IS ADDED. VALVES ARE PREFIXED WITH 0-77 UNLESS OTHERWISE NOTED. w 7. DESIGN PRESSURE AND TEMPERATURE FOR ENTIRE DRAINAGE SYSTEM z :;~ ... ~z I- ::c I- :I: N z - W ...JZ < IS ATIAOSPHERIC AND 140"F: RADWASTE SUMP PUMPS DISCHARGE 8 czn. I-l/lz
...J......
O< 0::: ......
- i<
w "' "' z C,1- ...... 1- I:; r-3/4" SYSTEMS ARE 100 PSI AND 140°F EXCEPT FOR U1 AS FOLLOWS. THE
<1- < ...... uo:::
VlO::: 0:::z VlZ " DR UNIT 1 DRYWELL EQUIPMENT DRAIN SUMP PUMP PIPING IS DESIGNED c., Z C C :io I.LIO 1---,..--3/+" DR FOR 100 PSIG AND 165 DEG F FROM THE U1 DRYWELL, INCLUDING U1 Cl o:::I.LI I.LI 1/lU o:::U
- i Vl<
cu
=i I.I.IC 1-Q.
0::: 1-.,,0. PENETRATION X-19, THROUGH THE WASTE COLLECTOR TANK INLET
...J ...J Ill::!: I.LI :::E w ~ < <
- 7 "'
HEADER, AND NOT INCLUDING TIE-IN PIPING FROM U2 AND U3
,r"' '0 'w *
.l"'I, 11r1rrrr1 N
1
~
8 z"w a.. :in. <:i C I ,", 7~ I .~~ I O 1-:::E
*a.. <
o::: <:i
,-=a_
1-...J Z...J VlLL.. LL.ILL.. _,O VlO
,o a..>
~
0~
- 0
~
m
" -~ ~
___,5* VENT TO EXHAUST
~DUCT (0-47E865-6)
EQUIPMENT DRAIN SUMP PUMP DISCHARGES.
- 8. DELETED
- 9. THE DESIGN PRESSURE AND TEMPERATURE OF All DRAIN AND VENT Fl El 546.0 ' ' LINES THROUGH THE LAST ISOLATION VALVE SHALL BE THE SAME E
. *N *N
=
=
'N 'N *m .
. AS PROCESS LINE.
- 10. HYDROSTATIC TESTING FOR PIPING SYSTEMS SHALL BE AT LEAST 1-1/2 TIMES THE DESIGN PRESSURE.
. N I 3""' "' 8" FLOATWELL 1,. C ~ WSP STAND FOR CONDENSATE AND WASTE PHASE SEPARATOR,
"' . . . =
= 2" CO STANDS FOR CLEAN OUT.
N N '
- 2* 3'
- 12, VENT, DRAIN, AND TEST CONNECTIONS 1-1/2" AND BELOW CAN BE 4"
*=*=== - .
"' 3*
PROVIDED WITH PIPE CAPS OR HOSE CONN(CTION FITTINGS WHERE REQUIRED BY PLANT PERSONNEL. THIS CONFIGURATION IS SUPPORTED BY ENGINEERING CALCULATION CD-00999-923399. l"lNNNNN
*N *N *l"l
*l"'I *l"'I *N 3*
*n *n
' EQUIPMENT DRAIN SUMP PUMPS CAPACITY 50 GPM o 60 FT TOH
- 13. THIS ORAWING SERIES SUPERSEOES DRAWING 729E429-2.
'<D
. I ?
LEGEND
'n I- CLOSED DRAIN (WELDED CONNECTION)
'IFEL~5~3~*-*-_4""====SS-6 t- OPEN DRAIN {FUNNEL CONNECTION)
El 537'-6" *--~.--.-WATER SEAL T- CAPPED DRAIN (SPARE) OR CLEAN OUT (CO) D
<D EL 537 .0 y FLOOR DRAIN EQUIPMENT DRAIN SUMP REFERENCE ORAWINGS, 0-45E775 SERIES ........ WIRING DIAGRAM 480V AUXILIARY POWER SCHEMATIC DIAGRAM 0-47E800-1 ............. FLOW DIAGRAM - GENERAL PLANT SYSTEMS 0-47E800-2 ............. MECHANICAL SYMBOLS A FLOW DIAGRAM DRAWING INDEX 1-,2-,3-+7E809 SERIES .. FLOW DIAGRAM - OFF-GAS SYSTEM 0-47E832-1 ............. FLOW DIAGRAM - FUEL POOL FILTER OMNRLZR SYSTEM 0-47E851 SERIES ........ FLOW DIAGRAM - DRAINAGE 0-47E856-1 ............. FLOW DIAGRAM - DMNRLZR WATER 1-47E865-1 ............. FLOW DIAGRAM - HEATING A VENT AIR FLOW MEL .................... VALVE MARKER TAG TABULATION
= =
~
~
.n . . .
n n
"' N N
- w
- C 3'
~
*n *n *n *n *n *n *n *n *n *n *n 'N *n *m *n *n *n *n *n *n *n *n 'N *n *n *n *n *n *n *n 'N 'N
= = ~
*n *n
*n *n *n *n *n *n '
"'n
-~5~
~"
tJ "'
- - 6" TO FDC TK 2-1/2' I
.---.* FROM H7 J
- THIS DWG
- 3" n n n "z wo (CONT SH 3).
2- 1/ 2 " -70 ~ 2* . TO CWPS 'F' TO CWST TK (CONT SH 3) ..,,__....;_-1.,..H I - . (CONT SH 4) 703 . - 1283 1* D G BLDG *1*R W BLDG 7028 = '
* *n ~ .-3;4*
" DR N
1---,..--3/4" DR
' ry, : TO WASTE COLL M -< . -~ ' "' . "'
'-~
0 77-13 ______________________ _l ______l':_-_-_-_-i_;---**-*-TA_N_*_1_0-_.~_1_E_*'.,o,.-_2_,_~.,.---1-__11_2~ . - - - - - - - - - - - - - - - - - - - , 0
~ " ~s* VENT TO EXHAUST r---,DUCT (0-47EB65-6)
I BLD~-:-:-i-- SUMP PUMP OISCH $ 1"1>----. : 77-J}
"A"R"' "B"R a +1E:o ! I BLDG RADIASTE El 546.0 BLDG NO. 1 z z BLDG NO. 2 I .. < ., ,. '
**1* - - **1* ~ ~ E 13/4" ~
Vl
~
i c
~ ~
c i Vl
~
DEMINERALIZE WATER (MAKEUP) C0-47E830-9)--......._,,__1_-_11_2_*_. Q1~-~4~7~E~B~5~6:-~2~,~A~7=)>---!.::.~.:-] l" M t--',
< 1 * < *
~-"-,----3/4" m, m .
. .,.,________-.!+---.. .
n B 1~~8" FLOATWELL N 77-24 f'l ,,t- l"'I ,,t-
~
...------,H,----_. . '
i : 8~
~
LL..
~
w
~
~
~
w
~
~
0~
~
LL..
,~~+--+-~./~-1~,-1~ f-;;:::======:l===l:===::::.m-rr,--'-lfl!¢===1=====:;::;t
,,----"'----,, EL 5 65 . 5
~
FCVVI... 77-2TP
.I
- C- '
X
~
77-~4 LE
- "A" R
'.;::.a;::
I--' ~ I--'
"B"
.. ;::.h;::
r-!2' VENT TO DUCT I ?
...----+~------.....JI .. .
n
- AMENDMENT 28
~,-1~~
* *
- 8" FLOATWELL -
.-----1 STANDBY GAS TREATMENT & RADIOACTIVE WASTE BLDG ALARM A SECOND N
4" PUMP STARTS El 562'-10-3/+"
,-El 537'-6" UNIT 0
------~.....
~--+/-
El 538'-4"
"' ,.=-~~~~
...._..__ _ _ _4"
'---------1+--
..__ _-+,lj,-. E a ' ;a FIRST PUMP STARTS EL 562'-2-3/4" r---_ WATER SEAL El 537 .0 BROWNS FERRY NUCLEAR PLANT LOW LEVEL MAKEUP STOPS El 561 '-0" ' FINAL SAFETY ANALYSIS REPORT PUMPS STOP FLOOR DRAIN SUMP El 560'-8-3/4" FLOOR DRAIN SUMP PUMPS CAPACITY 50 GPU o 55 FT TOH El 559'-9" LOW LEVEL MAKEUP RADWASTE SYSTEM A
----== ~ STARTS EL 560'-6" COMPANION ORAWINGS, FLOW DIAGRAM L_J ~
- ,._ El 558'-9" 0-47E830-2 THRU -9 STANDBY GAS TREATMENT STANDBY GAS TREATMENT SUMP BLDG NO. 1 STANDBY GAS TREATMENT SUMP PUijPS
-- -* -* --- CAPACITY +a GPM o 50 FT TOH
--- FIGURE 9.2-3a 8 7 6 5 4 3
1 2 3 5 7 8 9 10 11 12 GZO!I 2-1/2" l-0£83Lv-O L9 r
*~
.....--3/4"
~
~
VENT RESIN ADDITION FUNNEL LEAKOFf DR 8" OVERFLOW TANK A-1 &. A-2 s* SPARE\_ 3" 3"
/6" TO PAIL -:-\
. ' SPARE AIR COOLED HEAT EXCHANGER - -f--- n-.e;;,,,,_.___,
2 1/2" r+-'----t> .<:l-_--1 770
- DRAIN TO ED SUMP
<0-47E830-1, HS, H-1-:1--~
20" MH """'\ L N
*N T { 2 0 " MH A DESIGN PRESS. 150 PSI~--< WASTE DEMINERALIZER FILL A
- - ATM N
.~
*m
~
2-1/2"
< /COOLER
&=;
BYPASS 755 EL 578.0 & ACCESS ROOM EL 580.0l~
~>-----
TSOPSC' LJ - - - - - - 10-47E830-13, H12 FROM ULTREX
)--1,1--~ .~_r-(0-yTT "'
~ c:o
- __ 2 1/2" TANK A-1 1 ..J 754 756 "z< - IF J
'-_ '_..,.< 1 .. DR TO EQPT DR SUMP ~ m' ..... __ Ui.Q. f..SJ
"> '----'---<~D-47E830-1, FS
... 2379 2380
- 67 PSI
"';, WASTE FILTER tpJ\}-tcx:J--l HOLDING PUMP
... ,,,. -***-*,:- * ~ -~
- 6" l . l *N
, VENT TO EXHAUST DUCT
~~D-47E865-6, H7 77-72 - ,-------,1-47E610-43-2, G6
~
2" 0-2-9253 CNDS 3" SPARE J . N 4" SPARE J LT
--"1
-- 358A
. - 0-47E830-6, E4 I . 3" ..__,
77-108A 3. j ,1. *
~
'2-1/2" N B .
1/2" TUE 1/2" 447 3/' ..
\..-f<l-{),<J---'""-'~~*1-, - . 0-2-9252 6"
~
IF ..-~~~~~~~~~~~~~--1-i 6" -' a
~
B ix IF 351 * - - 3" 3" e!. 753_ .w 781A .w (FCV\ w J"7j_E91*'-i<l.._-',1f~aa --£:-x<Xl--f'.,J-,;,6 _*.,,1-r..-1>::l-~-------------------------....;,6-I. . , 1?.;J!O 2" S P A R ~ 6" SPARE
...._, - ..... 1 765 768
*N sCJH-' / £ 2 0 " MH TW TI *w 6" .I.
r N
,e:-,, "'I 3*
f 4" VENT
~ TT 77-7 77-75 ( Fcv, c.. FCV .- ~ IF
' 7J-"!,.9 ~I~ 7J.:!.,,2 /.,:j0 ~
Ix lvi 817 1,e:-,_ (FCV)816.
.m 6" ~< --
..- ,,... 1 /2" VESSEL VENT ;: ~la.. 7 ~~0 co DISTILLATE TANK 1-1/2" t.tIXING EDUCTORS
<1~ 1"' 55 CPt.t 020 PSID EACH I
*w 2" DOME VENT AND AIR INLET WASTE /\/ \l' 6" 6* 813 _
---0.._,......-< 6 ,, PUt.tP DISCH (TYP 4 TKS)
'1 X
DEMINERALIZER (WD) . .....t-----eJ-----/\----7-93--------1,'8.-1'12-£><.3:J, -........x3!111'-' 0-47E830*8, 07 I TANK A-2 X~D / (Pr'\ 77-82
'-,-' 1/2" (FCV\
77-81 :._, EL 565.0 DESIGN PRESS. 150 PSI ' :-,..._ INLET DISTRIBUTOR i!l<
~
1ii
~ dMll-r---**----"'-11---, IF TO DISCHARGE CONDUIT J
1150 PSI Y,12 . z RO c., N *
,.., =
.- 7'95 L--- ---fO::m:s,o-a.'"cio~')
0-47E830-3, C10 .> 1 T2lr !'Sr 1" VENT TO EXH DUCT = C 103°F . - A ,x
~
~ ~ ,..,I ;-
~ ~
6" l l. C
' I- * !l;i.!l .f.SI <0-47E865-6. G5 I- ~
w
~ ~
~ J 355A
"!"' ~ IF , *N
. ~X150__!~
r ~ 100 PSI - WASTE L!.'-"t><-h ~~ FILTER .- 356A- 8f 100 PSI w 0~
~
- ._, LEAKOFF DR TO TO DISCHARGE CONDUIT 3" SPARE J 4" SPARE 2" SPARE N
~ I- 7 EQPT DRAIN SUt.F 0 47E830 3. C10
-' EL 565.0 ~ '. (FCV\ "'~ /
~J.=
- t.
'~
- 1 3" 3" N
PRECOAT RETURN (WF I /\
;7~~!IB- X 7~9-7. n
- * .r,G\ ~0-47E830-1, H-5 > 3" 3" 0-47E832-1. F-7 l~,l'~I;r ATM 2"
~------~----{
_tp_ IX
*N z
§~
(FCV\ 7~0 --<m X
- 77-111
. 2" S P A R ~
1--, . .' / 6" SPARE
£ 2 0 " MH 0
z u
~
WASTE FILTER DESIGN PRESS. 1- *w N
, IF N
0 ffi :;J w w Ar1~5D:::_:P:,:S'.,'.I-17~6~2-~' _!1.:'."-"..:::=jj~*:4_7~6~':,hL FG - .
. ~lo
<I~
1 I(' (FCV\ 709 ~
..* 6;."---.,,i-1..--1---.1..-..&--;....1..---t>"<"l--l.,---'l---!:*3;...,"
X /\ 787A 786A IF A_\ IF 4" -
-- -- - '~
TT "u ~
.. 250 PSI :150 PSI 77-85 FG
~
z
'-./)
- 785A 783A
< ' 2" m ..£. 0406"F 1 77-87 FG );-l~tpf----l,.:. 2 _" ~-l<Jf--~-,.,.:6:..."-1 w D N
. 77-100
""x....,
I
~
"'0>< w N TANK B-1 D
~
0
. N 1- ~~ 0' '
,),
,. (FCV\
- 0 ...__ OFF STANDARD
- L~..--CROSSTIE w
RECYCLE AND 1I(' w ~ ~
~
"' 0
' ~lo . zz m
<<n w
0 7~5 CROSSTIE J
~w ~
~
o m z w
< ~ . . ,.
~
m
- SERVICE AIR r(0-47E845-3, CS I
<I~
2" 0~ 0' v., *w ' w
~'r,.. - I-l .
- l.
- VENT TO EXHAUST DUCT w
t". .... X J *N
"' .£. DRTOWBR ~~ (PI',
*N
*w (FCV\ ' CD 3" SPARE J . N 4" SPARE J 2" SPARE
~dD-47E865-6, H7 z
~
~
- __,> w
. ~ *. '2-1/2"
~-----....,LD~--*~7=E=8~30~*-*~*c...:.A=3_ z ~ .w \?_7;135 7~4 , 3" 3. j ,1.
~
~lbIR~R~L~!~~ER/
VALVE ROOM
~
V 0' (PCV\ <
~
FI 77-103
..__, < , (FCV\
s*_I_
......-.xol,ll_,-,,--1--1-------.t,.<_:l---l,,-.~.l-!>1.;;..~IF
- J" 4"
EL 565.0 D~RLZ WATER
~
=
~ TO CATION FLOC
,.... 1-112*
t.tIXING TK {THIS DWG, G10) N 1" 77-135 420A
-:;; ' 77-102 0 ~116 7____J{Fcv\
7878 7868
............__OFF STANDARD RECYCLE IF j,'--,<j,,--£""_1---1, 7858 STARTUP STRAINER 7838.
w 6" 3" 3" E 0 47E856 1, B 6 ' FE 1;-..1..-t,1*~-f"'-,r,2-*--I 5* SPARE\ I 6" SPARE E 797 11 o~ DUST EVAC""\. 774 77-103
*X
- 1 -
1772
\_RECYCLE
~RO RESTRICTION IF WASTE SAMPLE PUMPS 440 GPM 075 FT TOH 6" 20" MH'i_ l._ .N
. / £ 2 0 " MH 100 PSI I ATM MIXING AIR r, N
.iae..L., SET _Jr ~I~ -m ORIFICE TT *N TT AT.M.
15 0 PSI TO RELIEVE 1 AT 150 PSI (TYP 2) 1 8oi-A;;J---,~----:;,:-_.---c,+-'=--t 1" AGITATOR 1/2"
' - SET TO MAINTAIN 6 PSIG olo e1~
~05
/\
~
- J.
m
~
HIGH LEVEL ALARt.t
*m I\....
- 2" r tl EL 589'-0" ~~~~~ !OVERFLOW 1* . PI FCv.):a*,J{lll-------f"--J--'L-------------""I IF , - - . . . , . - - . , IF J----6-t 0 (TYP 4 TKS)_) EL 589'-3" (TYP) 2-1/2" . OVFL EL 572'-10"-
HIGH LEVEL.!_A~L!_A:".RM~--:::i-- - 77-134 FCV\.., W' 77-107 7818
*~
~ - - - - - - - - - - - - - - - - - - ' ~
TANK B-2 'f PUMPS STOP 800 1262:,_ I ~ Tl~ 67 PSI 67 PSI 'EL 580'-9" (TYP) (XTK\ (XTK\ EL 572'-7" LOW LEVEL ALARM EL 568'-6" rl.
~'ls:7'_
~
1 .. * (PCV\ 77-134 .- m LSQ. .f.S..l ___ _// 120 PSI, 103 Cf' fsOPsll
~ :i--:t;°;\l'T'"-----i----1:/'I'-~
150PsI1 ~ m. m
,.., 67 PSI
--- I
,r---'
77-21J1
,,,.. ~ -6 1 ~
417A 77-10~, 2" N ------ 150 PSI . . . .6_*_ _ __. l l.
'-LOW LEVEL ALARM EL 580'-6"
'C 77-21J2 1 .. 792
~
N . F 1-1/4" '
"' :.~ 2" DR
.802
- "-7' \_ RESIN TRANSFER AIR 3" SPARE J
*N 4" SPARE J LT N
(TYP 4 TKS) F
= ....
0 810 *~ WASTE & DRAIN SAMPLE 77~8B 3
- WASTE SAMPLE TANKS fWSMP)
LL.I. SET TO MAINTAIN ' TANK ROOM 3" CAPACITY: 19,000 GAL EAC~
/\
~ ~ 6 ~
CNDS FILTER AID TANK 30 PSIG EL 578'-0" EL 578.D IF 1 = I .', CAP. 520 GAL I0-47E830-6. EJ ATM 1s0Psf~
' NOTES:
DESIGN PRESS. 16 PSI 150 PSI ,.... \_,.... L_ DESIGN PRESS. ATM PULSATION
~ ATM___ j r._1-1/2" .w ;!:
~
' 6"
.~
- 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-47E8J0-1.
- 2. VALVES PREFIXED "0-77" AND INSTRUMENTS ARE PREFIXED "0-*
~ 799 798 ... 11 N UNLESS OTHERWISE NOTED.
DAMPENER 6"
" L _ _l-1...-i-i:, .1--,--l./'I- ,--1<:::_>1--' 3. TO ENSURE THAT USING A STEAM GENERATOR TO CLEAN THE WASTE
- - I (TYP7PL I ii; .J
~ w WASTE AID PUMP FILTER '~ SET TO MAINTAIN 7-15 PSIG I 777 TANK 8-1 & 8-2 DRAIN TO ED SUMP m
N m
~
FILTER DOES NOT CAUSE PIPING DESIGN LIMITS TO BE EXCEEDEO, THE FOLLOWING VALVE ALIGNt.tENTS AND OPERATION INSTRUCTIONS SHOULD BE FOLLOWED:
~ 225 GPH 0150 7 X ~ '-----,,-----'.PDT}------------,--j;C(]---J
~
XTK 6 PSI sos'"' ~ = ~;.~;~~ _l_ 7-2.j.4 l_ 361A LL.I
<.0-47E830-1, HS, H4 PRIOR TO ENGAGING THE STEAM GENERATOR:
A. VALVES 0-77-905 1, -906, -909~ -1585, AND -1586, SHOWN ON T.__ __.,._*_~ ~ ~ 318 * ~ ~ g 77-21J3
~XTK DMNRLZ WATER (!i~ {oIS\_ 2" 0-47E830-3, SHOuLD BE CLOSEu.
G L 1-1/4"
- =u....---1<1--,
fXTK\
, l..)177...-21,34,/FsFS~
x 1_1_ 1 A.TM110D PSI 0-47E856-1, 86 7J-!~,3 WASTE DEMI NERAL IZER VALVE RCXJM EL 565.0 77y-11J _ \_ RESIN TRAP -.
~
1 "i' u o
/\
DEMINERALIZED WATER THIS DRAWING, E2-~
- 8. VALVES O-FCV-77-71, -76, -78, -79, -81, -84, -89, -90, -92 AND 0-77-446, -753, -764, -800 a. -805, SHOWN ON THIS DRAWING, SHOULD BE CLOSED.
C. VALVE 0-77-762 SHOULD BE LOCKED OPEN. G I ;
- ,_ 77-11 ; - =
- o ~ 00 D. VALVE 0-FCV-77-86 SHOULD BE OPEN.
FD F~r.~::j_- ~ - ~ ~ . 362A w $6 1* NOTE 4 ___j
,---tGITATO-;i :ie
, ~I 8 :_
E. SAFETY RELIEF VALVE 0-77-751 SHOULD BE OPERABLE. DURING STEAM GENERATOR OPERATION: I 1" a <I-AID PUMP ,* ~ :, A. VALVES 0-77-1585 AND -1586 SHOULD BE THROTTLED OPEN TO 225 GPH 0150 PSI 1-1/2" ..l RELIEF VALVE 804 803 8" SAMPLE TANK OVERFLOW ~ 77~J9A 3/4" VENT 6 I Lit.tIT THE PRESSURE OF THE ENTERING STEAM/WATER TO LESS
,~----w..-.rw.*--11....---,. !
j 1100 THAN 250 PSIG AS SHOWN ON 0-PI-468. l1T 150 PSQ PRECOAT A FILTER ~ Y',. "FCV' ~ l_ - 8. O*TI-468 SHOULD BE USED TO INDICATE WHEN THE USE OF A r /;_~~ls AID PUMP ROOM OFF :g !;j:
,-------J --E-*-, STEAM GENERATOR IS IN DANGER OF EXCEEDING THE FILTER J
< 0-47E830-4, A3 !l *751 7;:_~1\ 6" STANDARD RECYCLE 1 O
.- I DESIGN TEMPERATURE OF 200"F DURING WASTE FILTER CLEANING.
~
FUTURE PUMP CONN~ 1OD PSI 6"
;. l.f-r-T"EL_s_s_s_.o_____....;__________________46;;.*-------------------------I----:::----£><:J--....L.-i::C*,~::---'i::'..":i,6---"T-'."""l;fl- * ~------1<_1-""'-"--I
- 1 /2" An~--- I4
- NOT IN SERVICE.
- N X rr, 1107 r- - - - X /\
I 1-47E610-4J-2 REFERENCE DRAWINGS:
..*.*. MECHANICAL CONTROL DIAGRAM-SAMPLING AND WATER
~ < , 2290 3"*4" ~ *~ m CATION FLOC
.1.!i9 ...f'fil _ in
' ~
100 PSI _j - ,.._ en
~ '.fen'.
LEA.KOFF DR BASKET STRAINER 3/8" PERFORATIONS ~ \lj - ( F~
- m
~
MIXING TANK CAP. 60 GAL 1/2" ,e:-,_FSV
,~~V) ~
1 1 I 1-47E810-1 ......... ~tiIJlAJJfJErEACTOR WATER CLEANUP SYSTEM 1-,2-,3-,47E811-1 *. FLOW DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM H (FCV\ PS LEAKOFF DR'? :- (FCV\ J/4" DR TO ED SUMP I 77-~ X DESIGN PRESS. ATt.t 1 o 7.~7-278
~
0-47E815-1 ...**.*.* FLOW DIAGRAM AUXILIARY BOILER SYSTEt.t 1-47E818-1 ......... FLOW DIAGRAM CONDENSATE STORAGE AND SUPPLY H 77-77
):;:(
77-277
~
-1
- 1" - -
CROSSTIE TO FDF 77-68BA
'z::;!{
CRW 6" FUTURE BYPASS_/
' e ~ - ,. , 0-47E845-3 ...*..*. .f(J:E~IAGRA.t.t COMPRESSED AIR STATION SERVICE 1
T I_ PRECOAT SUPPLY 6* 750 EFFLUENT 3* RECYCLE _ AROUND STRAINER
- x 1-47ES52-2 ......... FLOW DIAGRAM CLEAN RADWASTE AND 1
767
. _J DECONTAMINATION DRAINAGE
)>---ti j t---' L..fo-47E8JO-J, 86 ~ x- 4" CNDS a. WASTE DECANT 10*47E832-1, CS
. X CROSSTIE TO FDF . CLEANUP DECANT lro=-=47~E=8-3D=-=s=_=c~2-"")>-----------.
7J2 2" ,+----------< 0-47E8J0-4, J4 I . w 807
'" ~
, - - - - - 0-47E865-6 ........
- FLOW DIAGRAM HEATING AND VENTILATION AIR FLOW INFLUENT N 3" FLOOR DRAIN SAMPLE DISCH
<0-47E830-3, F4 I- ,.-------<0-47E8J0-3, E7 I 808~ PI 2-1/2" 77-67 ....-
DR TO FLOOR VENT TO EXHAUST DUCT 1_ 112
- WASTE PACKAGE DR 47E830-6 77-68AA FC,n_. X ' ..__... J54A DR SUt.tP (SH 1 I i I
~
EQPT DR SUMP PUt.tP ,.-'------<0-47E830-6, C2 3/8"
' <(p-47E865-6, G4 WASTE 0-47E8J0-1, F4
' ... DISCHARGE I0-47E830-1, FJ ) > - - - - - ' -. .
2-1/2" ,_ 112 *
,---'-----< 0-47E830*1, SGT BLDG SU.,, PUMP DISCH I
, COLL PUMP 130 GPt.t o I .
. 6" TURB BLOG EQPT I0-47E851-1, 03 ,,>-----1<::>I---.
4"
~---~:0-47E865-6, G4 VENT TO EXHAUST DUCT 86
"' J52A PI 77-69
..__, 300 FT TOH 150 PSI N
4"
.w .w WASTE ATM 6"
~
.m . w 759 4"
,..__-<6" REACTOR BLDG EQUIP DRAINS 1*47E852*2. C1 1 /2" PUMP I
N in SURGE PUMP 130 GPM o 300 FT TDH w 6" _?Cl!A~S!JIN!!!GL£D!)lRl...:;:::::::::::::;-..,..: a ~ 1-= -~
/'I ~
N
- 6"
...,1 /
~ HIGH LEVEL ALARM
\ EL 572*-3*
I
.... 6"
<D*47E830-1, ES SLUDGE REMOVAL TO WBR TK
~
i('II""' LovE~FLOW-EL 572'-9" """lloi(' <"'0-47E830-4, C4 L, AMENDMENT 28 O - - I \ HIGH LEVEL ALARt.t I 0 ' 11- t-11() ..., l,OVERFLOW EL EL 568' -9" .... 819 ' I 117,---,..~~.J* 3" :" ,< <I - "' I I"' L-C:c:".7:-:--:c:,1 FUTURE J
-..1---,-+*-------RECYCLE
~2._*_,(:,:('l-+--P,
~/(4) 2" t.tIXING EDUCTORS t-,.
110 GPM oJO PSID EACH "'--t-i'[Xx:J-,o'2:."-1 a.. 1::E 0 on11-r*3_._-_;l<+-----------------+--I-__~ 569'-3" -=-=----=- ::i:1 a..,o-47E830-1
!;;lin 0 '
3/4* VENT
' E5*r '--JMllf-->
_A.IM_ __.., 150 PSI 7
~~
, ~
N
~
HPUMP ____ J CONN I ..-~--t';t{"- 109;
- 1 7J61 1733 ~/(4) 2" MIXING EDUCTORS t-,. [fo89--
~ RADIOACTIVE WASTE BUILDING 1 1 2" I ~ -f-ll[Xx:J-,o'2:.."-j 2" 1 --D- 110 GPM oJO PSID EACH "'-.. -t-i')X3""'F2'-"-j ;., /2 * ';. ~ ~
- 3/8"
- 743 j UNIT 0
. , n
.w --
1103 I 735 --[:> 3" 734 7461 SYSTEM SHUTDOWN .t. 1747 ...._3:l,";..JiRi5.Elr,CYjlC~L,!iE---------,(:,:x:J----~ [}AfION ~QC i 1098 1095 CATION FLOC CHARGING PUMPS I ,_ 6" 6"
'~i*
I FCV ~ 150 PSIG 726 _JA (F_c'!_) ......~ 150 PSIG I 123 PSIG 11JO
'F ,..,___+ ..L-OW-LEVEL ~L!~~~~Ms~gw~p*~4~'-3/ -+-2-.--_-_~ LIT 2" 74~ =-t> :::~T0:~~54~*--_o_* l -~-+-1-7_*_*::.,.2.. *-~-t:_i~><l_hlr-~77~~77
*+~
CROSSTIE 739
- . ~I I 18 GPH 0150 PSI BROWNS FERRY NUCLEAR PLANT EL 547'-0":,. --- 77-668 LIT':--£><"~2l,'."~!:::::;--t fLOW LEVEL ALARM EL 548'-9" J" <1.-- w
,...I ,-
.!'!;;,;;~: :,*. ~-,:it - FINAL SAFETY ANALYSIS REPORT I 77-64 ...!::-_Jso5 I 11-261 ~_J,105 j RELIEF VALVE L..__... 6" I SET 0150 PSI L-~~-----==~-~~-
..__... 2* _J 3*
3 _ _*_,_.._:_3_,__ I.__E_L_s~-:-A-*:~T-:-S-U_R_G_E_T_A_N_K_(_W-~-:-~- 18 3
- ~:'A=~.......,---I-,~: :'~~*::;,_' "*;;-;-~ ,-----------j ~ (TYP)_r,, ,,_
PIPE GALLERY EL 546.0 .. _~~.__*-_- I
- 135 PSI :,so PSI '_094. ~ 1092 K
LOW POINT DR TO FD SUt.tP 0-47E830-1, C4 OVFL TO EOPT OR SUMP 75,000 GAL CAPACITY DESIGN PRESS. ATM *
-I 0-47E8J0-1, CS OVFL TO FD SUMP DESIGN PRESS. ATM .
, m N
~
I TO FDC TK j < 0-47 E830-3. F3 r ' 1/2"! _.
- .,c-i41*°"-.....l--'---l4~-'--I__
1~9 J/8" 1096 I f _J RADWASTE SYSTEM FLOW DIAGRAM w L _______________ l 150 PSI :ATM
<0-47E830-1, ES L---1 0-47E8J0-1, CS ;> 6" DR TO FLOOR DR SUMP WASTE SURGE & WASTE COLLECTOR ic~iER~GE & WASTE COLLECTOR L ___ (TYP) _ _ _ _ _ _ J
<o 47E830 1. CS TANK ROOM EL 546.0 EL 546.0 COMPANION DRAWINGS:
0-47E830-1,-3 THRU -9 FIGURE 9.2-3b 1 2 3 4 5 6 7 8 9
10 11 12
~ ~!:~-
AMENDMENT 27 UNIT o LEAR PLANT BROWNS FERRY :~~L YSIS REPORT FINAL SAFETY RAFDLWcfill1 ASJRSfJM FI CURE 9
- 2 -Jc 10
_:jJi
~
" . ---": ~ ~
AMENDMENT 24 TUR81NEa.RAOIOACTIVEIIASTEBUILDING UNITO
-"',., "' BROWNS FERRY NUCLEAR PLANT
' ' ' FINAL SAFETY ANALYSIS REPORT
°'"D,NSAT£ ~ WAST£ SI.LrlG£ P ... PS RADWASTE SYSTEM FLOW DIAGRAM FIGURE 9. 2-Jd
C
.~;~::;;"":,;.:~:.:;"..;:~~.:;..:.:~~~*
JlC'-~lliR:.JJii:i.... -* 0 C 1:** ***
.":i"i::r1.
5 3
ZlO~ 9-0£83Lt-O v,i L9
~
~ /\
4~ N
~VI ~
<WT ~
SAMPLING STATION H
"'z<
wcc
"' o'
~
0 ia.. IO "'
~
O-SMCH-077-0190 I" ow w FROM CLEANUP r Ur~ SLUOGE PUMPS 0-77-1411 0-77-1408 ATM O< o"' r ALTERNATE HOSE CONNECTION FROM 1-1/2" , - 0-11-1;01
~-[::~~+-~~~~~~~~-:---,*
.t-*
80 PSI '- r-
- SPENT RESIN PACKAGING STATION OUTLET 0-47E830-5,88
*-
- ISOLOCK SAMPLER ~
0
~
(TYP ) ~ FC 77-202 x~x~ 77-~ .11-~ X X
~a:O= ~02F O-SMPL-077-01 89 1.1.1
~
._ u~
~
~
~
N
-~"'
w "'
.. u
~
~
z- ~
.!.L._____.;;.!.;&.._____.;;.!.;1.__.:;.!.;&.._____.;;.!.;1._____.;-;;.'L.,,-1;.-.;1..:./.;4_._ __ . ~ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -. ..;1_-;;1/;.4;."______________________.....
~
~----0-77-1409 ~
103"F, 120 PSI I I 80 PSI 1 112" 0-77-1410 0-77-1412 MANUAL SAMPLE POINT "' N'
-~
w "'
.. u 1 II 1* 1"
- 1"
-- I . . 0 o
1" rI .X . G
' ' * ,i .L ,...036° X _I *
.L 1037 X
- X
.L X
- X 1039 X 1038 FROM CONDENSATE &
WASTE SLUDGE PUMPS I 1034 1033 1035 1-1/2"
' 80 PSI I (TYP)
ATM ATM (TYP I I 120 PSI. 1OJ *r ' 1-1/2" MAINTENANCE CONNECTION (TYP OF 6) 1-1/4" N al N lo-47E830-4, H9 0-77-1413 I I
. .------ .. m' L]
2"
- TO CLEANUP SLUDGE PUh.FS 0 47E830 15, G1 ~
TO CLEANUP
-- <0-47E830-5,A8t--- f 2-1s6a TO ULTREX
~
~
<a PHASE SEPARATORS 47E830 5,01 1-1/4" (FCV'\ 1* (FCV'\ 7 ~
- C m
~
PORTABLE COLLECTION FLASK (BY FIELD) C !;: 6 THIS DIG, H2 '- 77-227 77-228 J 0 1044
,. i il- I N
j: i I 1042
- r1-112*
- 1 .. TO OFF-GAS SUMP SEAL HEADER 0 47E830 1,H8) TO HOTWELL DECANT LINE VENT
-~
1" 1* I
< THIS DWG. H2 "' ,. 0-77-961 fo79 1 ..
xI I I 0-2-1576 0-2-1575
'x 0-47E830-4, J3) 80 PSI I ATM Ll.J 1041 I
1100PSI I 80 PSI I 120 PSI, 103"F r-1/2" TO RADWASTE DISCHARGE ....., ). F TO WASTE BACKWASH 1 J.
... ~ 1 0 47E830 3.812)
RECEIVER TANK I/. * ~ <..0-47E830-4,A2 1- 1 +
. 1 ..
6" FROM CNDS SUPPLY ....... 0-2-1567 A-+7E 818 _1 .EBI
. - 0 Pl
~
m 0 VACUUM PUlr s.57 sen.A
. 10+8
.. FDF IWF BACKWASH 1066 ~ 7~0 1 .. 1 I?" ...........--t:0-47E830-3,A3 FROM WASTE BACKWASH 0-2-1565 TRANSFER PUMPS lo-47E830-4.A1 1-1/2" 1*
I I 1046 :-1 1 .. I "' 112" 0-2-6021
~
X .L
- 1045 I X' I
I I TO FPF/0 BACKWASH RECEIVER TANK 1.48CUFT - . - 3/4" DR CAP PIPE WHEN NOT IN SERVICE (TYP) '___;'
~ 1100PSI ATM I 120 PSI. 103 "F CNDS TO CSTRECYCLE 2 ,,
t_..,..a '**J.'..t,;.
'"";._--~:-4~7'.'E'_l8~3'.'2'::-:!_1.,_,Bl3:8i!) 3/8" 1078 1-1/4" 1* ... <0-47EB30-2, B7t-3" TO FPF/D RESIN TRAPS IASTE A DRAIN (FCV'\ * ;,; 1052 ..
1 /2"
-47E832-1, E6) SAll'LE TANK ROOMS
', EL 578.0 771-231 XI 1 .. 1*
- 1049
. IX
' e 1050 I 1 ..
0-2-1566
... TO WASTE DEMIN 47E830 2,F5) .
N E
~
100 PSI I ATM I~ I ATM I 120 PSI, 103°F . - 1061 1063 2" 1062
.' PACKAGE VENT HEADER 2"
~ M : - 1060 . '
77-234 I I I *
- 3/8* I J X I I
1065
~*
.... o::;,,..
.¢.
.¢.
ATM I 25 IN. Hg VAC
- y* NOTES,
.... ".J f:;
- r*
<f*
- o.<1
</"
- o.<1
- o ....
.,:o..... - 1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-+7E830-1.
- 2. FOR SYSTEM 2 GENERAL NOTES AND REFERENCE DRAWINGS SEE 1-47E818-1.
- 3. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED I
I c:=======> ~ I :tvi. ,--IJ,-*-£1--l>il><:l-..lt,vl .:1-:-------!f-------, ,--IJ,-*-El--l>il><:l---il'\ ...11"11------------..... .--1l-*-!ll--l>il><:l--:1t:v1 - ...1-------------. AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT O AND SYSTEM 077
- c======::::i--0--0~
- c======::::i- -~\
'------------"*o"'.<1 ?
I :M1-:----.
- ..:!::: :: I
.--n---1~
.--*-Ill-s- *-,0.-!-~>