ML19298B523

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Amendment 28 to Updated Final Safety Analysis Report, Chapter 9, Radioactive Waste Control Systems
ML19298B523
Person / Time
Site: Browns Ferry  Tennessee Valley Authority icon.png
Issue date: 10/04/2019
From:
Tennessee Valley Authority
To:
Office of Nuclear Reactor Regulation
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{{#Wiki_filter:BFN-26 9.0-i 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

BFN-26 9.0-ii 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

BFN-26 9.0-iii 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

BFN-26 9.0-iv 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

BFN-18 9.1-1 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.

BFN-26 9.2-1 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

BFN-26 9.2-2 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

BFN-26 9.2-3 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.

BFN-26 9.2-4 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

BFN-26 9.2-5

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

BFN-26 9.2-6 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.

BFN-26 9.2-7 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.

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) Condensate Backwash 3 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 Receiver Tank (a) Spent Resin Tank (a) 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 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.

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l"lNNNNN n n = = ~ n n n

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  • 1 *R W BLDG
  • n
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  • n El 537.0

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  • n
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  • m 3'

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  • n ry, :

TO WASTE COLL ______________________ _l ______ l':_-_-_-_ -i_;---**-*-TA_N_*_1_0-_.~_1_E_*'.,o,.-_2_,_~.,.---1-__ 11_2~.-------------------, I BLD~-:-:-i-- SUMP PUMP OISCH $ 1"1>----. a +1E:o ! I BLDG NO. 1 z z BLDG NO. 2 I RADIASTE BLDG

    • 1* -
    • 1*

Vl ~ ~ Vl DEMINERALIZE C0-47E830-9)--......._,,__1_-_11_2_*_.

  • E 13/4"

~ ~ c c ~ WATER (MAKEUP) l" t--', ~-"-,----3/4" i ~ ~ i Q1~-~4~7~E~B~5~6:-~2~, ~A~7=)>---!.::.~.:-] M < 1 * < m, m N 77-24 f'l ,,t-l"'I ,,t-i 8~ ~ ~ 0~ ~ '; ~ '.;::.a;:: .. ;::.h;:: w w FCVVI... LE ~ ~ ~ ~ .I X R I--' ~ I--' LL.. LL.. 77-2TP 77-~4 ~ ~ "A" "B" EL 5 65. 5

C- '

r-!2' VENT TO DUCT ~,-1~~ ,~~+--+-~./~-1~,-1~ f-;;:::======:l===l:===::::.m-rr,--'-lfl!¢===1=====:;::;t N 8" FLOATWELL - 4"

~..... --

'---------1+-- 4" -+,lj,-. .-----1 E a El 559'-9"

== ~

' ;a ALARM A SECOND PUMP STARTS El 562'-10-3/+" FIRST PUMP STARTS EL 562'-2-3/4" LOW LEVEL MAKEUP STOPS El 561 '-0" PUMPS STOP El 560'-8-3/4" LOW LEVEL MAKEUP STARTS EL 560'-6" L _J ~ STANDBY GAS TREATMENT BLDG NO. 1 -,._ El 558'-9" STANDBY GAS TREATMENT SUMP STANDBY GAS TREATMENT SUMP PUijPS CAPACITY +a GPM o 50 FT TOH --- 8 7 6 5 ~ zz w

  • n

~< ~ o:::..... a.. z CON VI >-,_, I-< <C:i: C ..,.0::: O:::~ VI < jl ;::c w I- ~ 1 1-...J z o:::o::: Uz ....1LL..o w

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n n n 4" 3" n n 4' 6" 680 716

  • n TO WASTE COLLECTOR TANK (CONT SH 2)

~ ' 1--~*s><:i--.... 7078 = N < I:; r-3/4" DR 1---,..--3/+" DR ~ m

  • 7 "'

~ 0~

  • 0

~ " -~ ___,5* VENT TO EXHAUST ~DUCT (0-47E865-6) 8" FLOATWELL 'IFEL~5~3~*-* -_4""====SS-6

  • --~.--.-WATER SEAL
  • n

' N EQUIPMENT DRAIN SUMP N N

  • n I ?

.---.* FROM H7 J

  • THIS DWG TO FDC TK (CONT SH 3).

2-1/2' I EQUIPMENT DRAIN SUMP PUMPS CAPACITY 50 GPM o 60 FT TOH EL 537.0

  • n
  • n
  • n
  • n
  • n
  • n TO CWST TK 2-1/ 2" -70~

( CONT SH 3)..,,__....;_-1.,..H I - 703 2* TO CWPS 'F' (CONT SH 4) M 77-13 ~ 77-J} 7028 = N ~.-3;4* 1283 DR 1---,..--3/4" DR 0 '-~ "A"R"' "B"R 0 -~. "' ~s* VENT TO EXHAUST r---,DUCT (0-47EB65-6) El 546.0 3" - 1~~8" FLOATWELL ~ .,.,_ _______ -.!+---.. n ... ------,H,----_. n ' N - ... ----+~------.....JI... ,-El 537'-6" El 538'-4" ,.=-~~~~ I ? r---_ WATER SEAL ~--+/- El 537.0 FLOOR DRAIN SUMP FLOOR DRAIN SUMP PUMPS CAPACITY 50 GPU o 55 FT TOH 3 COMPANION ORAWINGS, 0-47E830-2 THRU -9 ,CQNTON~ I

0-47E85~~~

4' ' N NOTES:

1. FOR DETAILED OPERATING INSTRUCTION, BACKWASH RATES, ETC, 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.
4. OPERATIONAL VALVES ARE SHOWN IN THEIR NORMAL OPERATING POSITION.
5. All PRESSURE AND TEST CONNECTIONS ARE 1/2" UNLESS OTHERWISE NOTED.
6. INSTRUMENT NUMBERS ARE cot.MON TO All UNITS EXCEPT WHERE A PREFIX OF THE UNIT NUMBER IS ADDED. VALVES ARE PREFIXED WITH 0-77 UNLESS OTHERWISE NOTED.
7. DESIGN PRESSURE AND TEMPERATURE FOR ENTIRE DRAINAGE SYSTEM IS ATIAOSPHERIC AND 140"F: RADWASTE SUMP PUMPS DISCHARGE SYSTEMS ARE 100 PSI AND 140°F EXCEPT FOR U1 AS FOLLOWS. THE UNIT 1 DRYWELL EQUIPMENT DRAIN SUMP PUMP PIPING IS DESIGNED FOR 100 PSIG AND 165 DEG F FROM THE U1 DRYWELL, INCLUDING U1 PENETRATION X-19, THROUGH THE WASTE COLLECTOR TANK INLET HEADER, AND NOT INCLUDING TIE-IN PIPING FROM U2 AND U3 EQUIPMENT DRAIN SUMP PUMP DISCHARGES.
8. DELETED
9. THE DESIGN PRESSURE AND TEMPERATURE OF All DRAIN AND VENT LINES THROUGH THE LAST ISOLATION VALVE SHALL BE THE SAME AS PROCESS LINE.
10.

1,. 12,

13.

HYDROSTATIC TESTING FOR PIPING SYSTEMS SHALL BE AT LEAST 1-1/2 TIMES THE DESIGN PRESSURE. C ~ WSP STAND FOR CONDENSATE AND WASTE PHASE SEPARATOR, CO STANDS FOR CLEAN OUT. VENT, DRAIN, AND TEST CONNECTIONS 1-1/2" AND BELOW CAN BE PROVIDED WITH PIPE CAPS OR HOSE CONN(CTION FITTINGS WHERE REQUIRED BY PLANT PERSONNEL. THIS CONFIGURATION IS SUPPORTED BY ENGINEERING CALCULATION CD-00999-923399. THIS ORAWING SERIES SUPERSEOES DRAWING 729E429-2. LEGEND I-t- T-CLOSED DRAIN (WELDED CONNECTION) OPEN DRAIN {FUNNEL CONNECTION) CAPPED DRAIN (SPARE) OR CLEAN OUT (CO) y FLOOR DRAIN 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 AMENDMENT 28 STANDBY GAS TREATMENT & RADIOACTIVE WASTE BLDG UNIT 0 BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT RADWASTE SYSTEM FLOW DIAGRAM FIGURE 9.2-3a H G F E D C B A

A B C D E F 1 GZO!I l-0£83Lv-O 2-1/2" 2 L9 r.....--3/4"

  • ~

~ ~ 3 VENT AIR COOLED HEAT EXCHANGER - -f--- 2 1/2" n-.e;;,,,,_.___, DESIGN PRESS. 150 PSI~--< - EL 578.0 WASTE DEMINERALIZER FILL 5 RESIN ADDITION FUNNEL LEAKOFf DR TO PAIL -:-\\ r+-'----t> .<:l-_--1 770 ATM TSOPSC'

  • m

~ .~ 2-1/2" & ACCESS ROOM EL 580.0l~ ~>----- LJ -----1--- < /COOLER &=; BYPASS 755 __ 2 1/2" 1 ..J 754 756 1.. DR TO EQPT DR SUMP '----'---<~D-47E830-1, FS WASTE FILTER tpJ\\}-tcx:J--l HOLDING PUMP 77-72 358A ,-------,1-47E610-43-2, G6 1/2" 1/2" 447 3/'.. TUE \\..-f<l-{),<J---'""-'~~*1-, 351 TW 77-7 TI 77-75 e!. 753_

  • w J"7j_E91*'-i<l.._-',1f~aa ix

--£:-x<Xl--f'.,J-,;,6_*.,,1-r..-1>::l-~-------------------------....;,6-I ..... 1 765 768 ,e:-,, "'I 4" VENT ( Fcv, c.. FCV 7J-"!,.9 ~I~ 7J.:!.,,2 /.,:j0

  • w 6"

2" ~< 1 /2" VESSEL VENT X DOME VENT AND AIR INLET (Pr'\\ (FCV\\ WASTE DEMINERALIZER (WD) EL 565.0 /\\/ ~ \\l' ' :-,..._ INLET w 8" OVERFLOW 6" z < ~ ' m 0-2-9253 2" 781A 7 0-2-9252 w 8 CNDS 0-47E830-6, E4 (FCV\\ 1?.;J!O . I. 3

  • 10-47E830-13, H12 FROM ULTREX

... 2379 I 6" ~ IF 9 10 TANK A-1 &. A-2 s* SPARE\\_ DRAIN TO ED SUMP 20" MH """'\\ <0-47E830-1, HS, H-1-:1--~ L .~_r-(0-yTT )--1,1--~ ~ c:o TANK A-1 IF 2380 ..... __ Ui.Q. f..SJ 67 PSI ~ - ~ l 6" 3" SPARE J. ~ 6" IF IF..-~~~~~~~~~~~~~--1-i f I x 1,e:-,_ ~ lvi 817 (FCV)816. ~la.. 7~~0 co DISTILLATE TANK 6" 6 * <1~ 813 _ 1"' 6,, PUt.tP DISCH I i!l TANK A-2 X~D / 77-82 1/2" 77-81 Y,12.. DESIGN PRESS. 150 PSI DISTRIBUTOR ~ 1ii ...... t-----eJ-----/\\----7-93--------1,'8.-1'12-£><.3:J, x3!111'-' ---0.._,...... -< 0-47E830*8, 07 ~ dMll-r---**----"'-11---, IF TO DISCHARGE CONDUIT ~ -' N 0 1150 PSI T2lr !'Sr 103°F ~X150__!~ r~ 100 PSI PRECOAT RETURN 0-47E832-1. F-7 WASTE FILTER EL 565.0 (WF I 1 ". - I-355A L!.'-"t><-h ~~ 8f 356A A ,x !l;i.!l.f.SI 100 PSI z ~

  • u w

0 WASTE FILTER DESIGN PRESS. Ar1~5D:::_:P:,:S'.,'.I-17~6~2-~' _!1.:'."-"..:::=jj~*:4 _7~6~':,hL ffi

J w

~ u m..£. 2-1/2" (XTK\\ 77-21J1 'C PULSATION DAMPENER FG 77-85 250 PSI :150 0406"F 1 PSI FG 77-87 N 0 ~. w ~ ~ ' "' 0 ~ o m z w ~.. ~ m "'.£. DRTOWBR ~~ 1 * ~lbIR~R~L~!~~ER/ VALVE ROOM EL 565.0 D~RLZ WATER 0 47E856 1, B 6 ~ w ~-----....,LD~--*~7=E=8~30~*-*~*c...:.A=3 _ __,> z ~ ~ TO CATION FLOC = t.tIXING TK {THIS DWG, G10) ~ ,.... 1-112* 797 EVAC""\\. ~ ' 0 V 11 o~ DUST 100 PSI I ATM AT.M..iae..L., SET TO RELIEVE 150 PSI 11 AT 150 PSI (TYP 2) AGITATOR _Jr 1" 1/2" 8oi-A;;J---,~----:;,:-_.---c,+-'=--t I\\.... 2" r OVFL EL 572'-10"- HIGH LEVEL.!_A~L!_A:".RM~--:::i-- EL 572'-7" I ~ LOW LEVEL ALARM ~'ls:7'_ EL 568'-6" 800 1262:,_ (XTK\\ 1 rl. ~ 1-1/4" 77-21J2 ~ 6 N 0 ~ 2" DR "-7' = LL.I. 802 ~ ~ 6 ~ FILTER AID 1 = I. ', CAP. 520 GAL 150 PSI,.... \\_,.... L_ DESIGN PRESS. ~ ATM___ j r._1-1/2" ~ 799 /\\ TANK ATM 798... 1.. w w /\\ VENT TO EXH DUCT <0-47E865-6. G5 ~ (FCV\\ I-

7~~!IB-X 7~9-7.

l~,l'~I;r 2" _tp_ ATM ~------~----{ IX 1-1 I(' ~lo <I~ (FCV\\ N 709 ~ FG );-l~tpf----l,.:.2 _" ~-l<Jf--~-,.,.:6:..."-1 77-100 ""x...., 2" I N SERVICE AIR r(0-47E845-3, CS I N 1" ~ (PCV\\ 77-135 (PI', \\?_7;135 ~ 420A 774 MIXING AIR SET TO MAINTAIN 6 PSIG (PCV\\ 77-134 417A PI 77-134 m -.. 1.. 1-1 I(' ~lo <I~ FI 77-103, 2" (FCV\\ 77-102 FE 1;-..1..-t,1*~-f"'-,r,2-*--I 77-103

  • X 1

1772 ~I~ olo e1~ FCV\\.., W' Tl~ LSQ..f.S..l ___ _// 120 PSI, 103 Cf' \\_ RESIN TRANSFER AIR SET TO MAINTAIN 30 PSIG CNDS I0-47E830-6. EJ >-- 6" N ~05 /\\ tl 810 ATM 1s0Psf~ ~ ~ z w ~ 0>< ~~ zz -- <<n ~w 0~ w ' 0 ~ m w ~ ' 0 v.,

  • w w

z ~ ~ ~ w ~ w I- "' ~/ z -§ ~ RO c., = 7'95 L--- ---fO::m:s,o-a.'"cio~') N 10-47E830-3, C10 I = ~,.., ~ ~ ~.. ~ IF 0~ ~ 7 ~J.= ~

t. '

n ~ LEAKOFF DR TO EQPT DRAIN SUt.F ~0-47E830-1, H-5 (FCV\\ 7~0 < --m - *.r,G\\ X 77-111 ..* 6;."---.,,i-1.. --1---.1..-..&--;....1..---t>"<"l--l.,---'l---!:*3;...," X /\\ 787A 786A N IF A_\\ '-./) TO DISCHARGE CONDUIT 1 0 47E830 3. C10 4" - IF 785A 783A w 6" ',), (FCV\\

0...__ OFF STANDARD RECYCLE AND CROSSTIE
  • L~..--CROSSTIE 0

w ' ~ t"..... 'r,.. (FCV\\ ' CD 7~4, ~ 7~5 - I - X s*_I_ J" ...... -.xol,ll_,-,,--1--1-------.t,.<_:l---l,,-.~.l-!>1.;;..~IF 7____J{Fcv\\ 0 ~116 \\_RECYCLE ~RO RESTRICTION ORIFICE -m m 7878 7868 ............__OFF STANDARD RECYCLE IF w 4" IF j,'--,<j,,--£""_1---1, WASTE SAMPLE PUMPS 440 GPM 075 FT TOH 7858 STARTUP STRAINER 7838. w 6" - l 3" SPARE J TANK B-1 l 3" SPARE J. 6" 5* SPARE\\ 20" MH'i_ l._ TT ~

  • J. ~

FCv.):a*,J{lll-------f"--J--'L-------------""I 77-107 IF J----6-t 0 ~------------------'~ TANK B-2 IF,--...,.--., 7818 67 PSI 67 PSI 150PsI1 ~ fsOPsll ~ 77-10~, ~ :i--:t;°;\\l'T'"-----i----1:/'I'-~ 792 6" ~

m.

m 67 PSI N ------ 2" 150 PSI ~ 11 N WASTE & DRAIN TANK ROOM EL 578.D SAMPLE 6_* ___ _. l 3" SPARE J IF ~ 3" 3" 3" 3" N N N N 1 1 3" N N l 3" N ' 12 /6" SPARE T {20" MH J VENT TO EXHAUST DUCT 4" SPARE J LT 77-108A N ~~D-47E865-6, H7 '2-1/2" 3" N

3.

j,1. ~ -' 2" SPAR~ sCJH-' r ~ 1-1/2" t.tIXING EDUCTORS 55 CPt.t 020 PSID EACH (TYP 4 TKS)

l.

4" SPARE J 2" SPARE N 3" N 3" 2" SPAR~ IF 1--, ~ 3" N I '1 3" N 6" SPARE / £20" MH T T J 6" SPARE / £20" MH T T J

l.

4" SPARE J VENT TO EXHAUST DUCT 3" N 2" SPARE r, N J

3.

j,1. N HIGH LEVEL ALARt.t ~dD-47E865-6, H7 '2-1/2" ~ -' 3" I N 6" SPARE / £20" MH T T EL 589'-0" ~~~~~ (TYP 4 TKS)_) !OVERFLOW EL 589'-3" (TYP) 'f PUMPS STOP 'EL 580'-9" (TYP) "1 - N - ~ < a w m w z - ~

  • m I

,r---'

l.

4" SPARE J NOTES: LT 77~8B 3

  • N

'-LOW LEVEL ALARM EL 580'-6" (TYP 4 TKS) WASTE SAMPLE TANKS fWSMP) CAPACITY: 19,000 GAL EAC~ EL 578'-0" DESIGN PRESS. 16 PSI

1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-47E8J0-1.
2. VALVES PREFIXED "0-77" AND INSTRUMENTS ARE PREFIXED "0-*

UNLESS OTHERWISE NOTED. --I (TYP7PL I XTK 77-21J3 ii; ~ ~ L _ _l-1...-i-i:, .1--,--l./'I-,--1<:::_>1--' .J WASTE FILTER '~ SET TO MAINTAIN I 777 w AID PUMP 7-15 PSIG ~ 225 GPH 0150 7 X ~ '-----,,-----'.PDT}------------,--j;C(]---J 6 PSI sos'"' ~ = ~;.~;~~ _l_ 7-2.j.4 l_ 361A LL.I TANK 8-1 & 8-2 DRAIN TO ED SUMP <.0-47E830-1, HS, H4 m N m ' ~

3. TO ENSURE THAT USING A STEAM GENERATOR TO CLEAN THE WASTE FILTER DOES NOT CAUSE PIPING DESIGN LIMITS TO BE EXCEEDEO, THE FOLLOWING VALVE ALIGNt.tENTS AND OPERATION INSTRUCTIONS SHOULD BE FOLLOWED:

PRIOR TO ENGAGING THE STEAM GENERATOR: G H I J K A. VALVES 0-77-905 1, -906, -909~ -1585, AND -1586, SHOWN ON 0-47E830-3, SHOuLD BE CLOSEu. T._ _ __.,._*_~ ~ ~XTK ~ 318 * ~ DMNRLZ WATER (!i~ {oIS\\_ 2" ~ g fXTK\\ 1_1_ 7J-!~,3 77y-11J u 1-1/4" , l..)177... -21,34,/FsFS~ 0-47E856-1, 86 1 - =u....---1<1--, 1 WASTE DEMI NERAL IZER \\_ ~ L /\\ 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.

x A.TM110D PSI VALVE RCXJM EL 565.0 RESIN TRAP -. "i' o C. VALVE 0-77-762 SHOULD BE LOCKED OPEN. 77-11 = o ~ 00 FD F~r.~::j_- ~ ~ ~ 362A w $6 1* I AID PUMP ~ 225 GPH 0150 PSI 1-1/2"..l RELIEF VALVE 804 803 8" SAMPLE TANK OVERFLOW ~ 77~J9A 3/4" VENT 6 ,---tGITATO-;i :ie NOTE 4 ___j , ~I 8 :_ I 1" a <I-I D. VALVE 0-FCV-77-86 SHOULD BE OPEN. E. SAFETY RELIEF VALVE 0-77-751 SHOULD BE OPERABLE. DURING STEAM GENERATOR OPERATION: A. VALVES 0-77-1585 AND -1586 SHOULD BE THROTTLED OPEN TO Lit.tIT THE PRESSURE OF THE ENTERING STEAM/WATER TO LESS ,~----w..-.rw.*--11....---,. l1T ! 150 PSQ PRECOAT A FILTER ~ Y',. "FCV' ~ 0-47E830-4, A3 1 !l *751 r7;:_~1\\ AID PUMP ROOM 6" OFF STANDARD RECYCLE

g O

/;_~~ls !;j: l.f-r-T"EL_s_s_s_.o _____....; __________________ 46;;.*-------------------------I ----:::----£><:J--....L.-i::C *,~::---'i::'.. ":i,6---"T-'."""l;fl- ~ N X rr, 1107 r- - J X ,-------J j - 1 /2"

  • ~------1<_1-""'-"--I 6"

FUTURE PUMP CONN~ /\\ ~ 2290 3"*4" ~ .1.!i9...f'fil _ _j - en BASKET STRAINER in m " ~ m ' ~ 1/2" 100 PSI ~ '.fen'. LEA.KOFF DR 3/8" PERFORATIONS ~ \\lj ( F~ (FCV\\ PS LEAKOFF DR'? (FCV\\ J/4" DR TO ED SUMP I 77-~ X 77-77 77-277 77-68BA CRW ):;:( -1

  • 1" CROSSTIE TO FDF

'z::;!{ 6" FUTURE BYPASS_/ CATION FLOC MIXING TANK CAP. 60 GAL DESIGN PRESS. ATt.t PRECOAT SUPPLY 10*47E832-1, CS /'I T 6* ~ 750 767 EFFLUENT 3* RECYCLE _ I _ AROUND STRAINER )>---ti j t---' L..fo-47E8JO-J, 86 ~ x-4" CNDS a. WASTE DECANT CLEANUP DECANT 7J2 2" ,+----------< 0-47E8J0-4, J4 I w X CROSSTIE TO FDF INFLUENT <0-47E830-3, F4 I- ~ ~ N < 0 DR TO FLOOR DR SUt.tP (SH 1 I 0-47E8J0-1, F4 N 6" VENT TO EXHAUST <(p-47E865-6, G4 6" 4" 6" DUCT ~ m w lro=-=47~E=8-3D=-=s=_=c~2-"")>-----------. EQPT DR SUMP PUt.tP DISCHARGE I0-47E830-1, FJ TURB BLOG EQPT I0-47E851-1, 03 2-1/2" 2-1/2" )>-----'-.. 4" ,,>-----1<::>I---. 759 4" FLOOR DRAIN SAMPLE DISCH I 3" ,.-------<0-47E8J0-3, E7 1_112* WASTE PACKAGE DR 47E830-6 ,.-'------<0-47E830-6, C2 I ,_ 112* SGT BLDG SU.,, PUMP DISCH ,---'-----< 0-47E830*1, 86 I VENT TO EXHAUST DUCT ~---~:0-47E865-6, G4 REACTOR BLDG EQUIP DRAINS I 6" w w ,..__-< 1*47E852*2. C1 N 1 /2" PUMP in _?Cl!A~S!JI N!!!GL£D!)lRl...:;:::::::::::::;-..,..: a ~ ~ 6" <D*47E830-1, ES 1-= SLUDGE REMOVAL TO WBR TK ~ HIGH LEVEL ALARM I ...,1 / \\ EL 572*-3* Oi('II""' LovE~FLOW-EL 572'-9" """lloi(' I \\ HIGH LEVEL ALARt.t I 11-t-11() EL 568' -9" 819 3 " :", < 0 1::E OVERFLOW EL 569'-3" -=-=----=-

i:1 0

' *r ~/(4) 2" t.tIXING EDUCTORS t-,. on11- !;;lin 3/4* VENT _A.IM_ __.., 7 6" <"'0-47E830-4, C4 w , ~ N. ~ '" ~ 807 808~ PI FC,n_. X 77-68AA i J52A PI 77-69 WASTE SURGE PUMP 130 GPM o 300 FT TDH 77-67....- ..__... J54A WASTE COLL PUMP 130 GPt.t o 300 FT TOH 150 PSI ATM -~ N L, FUTURE I HPUMP I CONN ..-~--t';t{" 3/8" ____ J 109;

  • 1 3/8"

~ ~2._*_,(:,:('l-+--P, 110 GPM oJO PSID EACH "'--t-i'[Xx:J-,o'2:."-1 r*3_._-_;l<+-----------------+--I-__ ~ 150 PSI ~ ~ 7J61 1733 1 ~/(4) 2" MIXING EDUCTORS t-,. 1 [fo89-- I ~ -f-ll[Xx:J-,o'2:.."-j 2" 1 --D-110 GPM oJO PSID EACH "'-.. -t-i')X3""'F2'-"-j 743 j /2 * ';. ~ ~ 2" 1103 I w n 6" I 123 '~i* 726 _JA 11JO I FCV ~ 150 PSIG (F_c'!_) ~ 150 PSIG I 77-64 ...!::-_Jso5 I 11-261 ~_J,105 2* L..__... _J 3* L-~~-----==~-~~- PIPE GALLERY EL 546.0 LOW POINT DR TO FD SUt.tP 0-47E830-1, C4 OVFL TO EOPT OR SUMP <0-47E830-1, ES PSIG 'F 735 --[:> 3 " 734 7461 SYSTEM SHUTDOWN.t. 1747 .... _3:l,";..JiRi5.Elr,CYjlC~L,!iE---------,(:,:x:J----~ [}AfION ~QC ,..,_ __ +.. 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 I,_

1098 i I 1095 CATION FLOC CHARGING PUMPS 18 GPH 0150 PSI EL 547'-0":,. 77-668 LIT':--£><"~2l,'."~!:::::;--t fLOW LEVEL ALARM EL 548'-9" J" <1.-- *+~ w 3 _*_,_.. _:_3_, __ I.__E_L_s~-:-A-*:~T-:-S-U_R_G_E_T_A_N_K_(_W-~-:-~- .. _~~ 18 3

~:'A=~.......,---I-,~: :'~~*::;,_' "*;;-;-~.!'!; ;,;;~: :,*. ~-,:it -

75,000 GAL CAPACITY -I 0-47E8J0-1, CS DESIGN PRESS. ATM DESIGN PRESS. ATM OVFL TO FD SUMP w , m N. ~ CROSSTIE 6" 739 . ~I j ,...I RELIEF VALVE 1092 6" I SET 0150 PSI ,-----------j ~ (TYP)_r,,,,_ I

  • 135 PSI :,so PSI

'_094. ~ I TO FDC TK 1/2"! _. J/8" f j < 0-47 E 830-3. F 3r'

.,c-i41*°"-..... l--'---l4~-'--I_ _ _J 1~9 1096 I

L _______________ l 150 PSI :ATM 1 1100 THAN 250 PSIG AS SHOWN ON 0-PI-468. l_

8. O*TI-468 SHOULD BE USED TO INDICATE WHEN THE USE OF A

--E-*-, STEAM GENERATOR IS IN DANGER OF EXCEEDING THE FILTER I DESIGN TEMPERATURE OF 200"F DURING WASTE FILTER CLEANING. 1 OD PSI 4 NOT IN SERVICE. An~--- I

  • I REFERENCE DRAWINGS:

1-47E610-4J-2..*.*. MECHANICAL CONTROL DIAGRAM-SAMPLING AND WATER ,e:-,_FSV ~ 1 1 1-47E810-1......... ~tiIJlAJJfJErEACTOR WATER CLEANUP SYSTEM ,~~V) ~ 1-,2-,3-,47E811-1 *. FLOW DIAGRAM RESIDUAL HEAT REMOVAL SYSTEM 7.~7-278 I 0-47E815-1...**.*.* FLOW DIAGRAM AUXILIARY BOILER SYSTEt.t o ~ 1-47E818-1......... FLOW DIAGRAM CONDENSATE STORAGE AND SUPPLY e ~ - 1 1 0-47E845-3...*..*..f(J:E~IAGRA.t.t COMPRESSED AIR STATION SERVICE x 1-47ES52-2......... FLOW DIAGRAM CLEAN RADWASTE AND _J DECONTAMINATION DRAINAGE 0-47E865-6........

  • FLOW DIAGRAM HEATING AND VENTILATION AIR FLOW AMENDMENT RADIOACTIVE UNIT 0 WASTE BROWNS FINAL FERRY SAFETY BUILDING NUCLEAR ANALYSIS 28 PLANT REPORT RADWASTE SYSTEM FLOW DIAGRAM DR TO FLOOR DR SUMP WASTE SURGE & WASTE COLLECTOR TANK ROOM L---1 0-47E8J0-1, CS ic~iER~GE & WASTE COLLECTOR L ___ (TYP) ______ J 6"

FIGURE 9.2-3b <o 47E830 1. CS EL 546.0 1 2 3 4 5 6 7 8 EL 546.0 COMPANION DRAWINGS: 0-47E830-1,-3 THRU -9 9 A B C D E F G H

10 10 11 12 ~ ~!:~- AMENDMENT 27 UNIT o LEAR PLANT BROWNS FERRY :~~L YSIS REPORT FINAL SAFETY RAFDLWcfill1 ASJRSfJM FI CURE 9

  • 2-Jc

~ ~ ~ _:jJi °'"D,NSAT£ ~ WAST£ SI.LrlG£ P... PS AMENDMENT 24 TUR81NEa.RAOIOACTIVEIIASTEBUILDING UNITO BROWNS FERRY NUCLEAR PLANT FINAL SAFETY ANALYSIS REPORT 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 z< o wcc ~ ia.. IO ow w Ur~ FROM CLEANUP SLUOGE PUMPS 0-77-1411 ~ 0 ~ r 0-77-1408 SAMPLING STATION O-SMCH-077-0190 "' r ATM O< o

.t-* r-80 PSI ALTERNATE HOSE CONNECTION FROM SPENT RESIN PACKAGING STATION OUTLET 0-47E830-5,88 1-1/2" I

0-11-1;01

  • ~-[::~~+-~~~~~~~~-:---,* 0 ISOLOCK SAMPLER

~ ~ w "' (TYP )~ FC 77-202 ~ x~x~ 77-~.11-~ ~ z X X ~02F ~a:O= ~ .!.L. _____ .;;.!.;1. __ .:;.!.;&.. _____.;;.!.;1. _____.;-;;.'L.,,-1;.-.;1..:./.;4_. __ _.~-----------------------------------------------------------.. .;1_-;;1/;.4;." ______________________..... 103"F, 120 PSI I I FROM CONDENSATE & WASTE SLUDGE PUMPS lo-47E830-4, H9 I ' I 80 PSI 1033 1034 1 " 1035 1-1/2" ,i .L 80 PSI I ATM (TYP) 1 II o ,...036° r X _I ATM I 120 PSI. (TYP I I TO CLEANUP PHASE SEPARATORS <a 47E830 5,01 1-1/4" 1

  • 7 ~

1044 0 J THIS DIG, H2 '- (FCV'\\ 77-227 (FCV'\\ 77-228 1 OJ *r X .L 1 *. 1037 X 1-1/2" TO CLEANUP SLUDGE PUh.FS <0-47E830-5,A8t--- X 1 " .L 1038 X 2" f 2-1s6a

  • C..

m ~ i il-I N I 0 47E830 15, G1 TO ULTREX TO OFF-GAS SUMP SEAL HEADER X 1 " 1039 X MAINTENANCE CONNECTION (TYP OF 6) 1-1/4" 0-77-1410 1 112" I j: 1" i I 1042

  • I 1
  • r1-112*

1.. 0 47E830 1,H8) TO HOTWELL DECANT LINE 0-77-961 VENT < THIS DWG. H2 x I I fo79 TO WASTE BACKWASH RECEIVER TANK I/. * <..0-47E830-4,A2 1-1 + FROM WASTE BACKWASH TRANSFER PUMPS lo-47E830-4.A1 -1/2" CNDS7 ~ ~ , e X ~ -.. TO FD SUMP (CONT ON SH 11 8 80 PSI I ATM Ll.J 1 041 'x I I 0-2-1576 0-2-1575 0-47E830-4, J3) 1.. -~....., ). 1-1/2" X

  • .L CAP PIPE WHEN NOT

~ IN SERVICE (TYP) '___;' 1-1/4" (FCV'\\ 771-231 XI 1.. 1 * - 1045 1.. ~ 100 PSI I ATM I ~ . ~*.. ... o::;,,

y*

.¢. .¢. <f* * </"

  • o.<1 o.<1

.... ".J f:; I 1100PSI I X I 1100PSI 1

  • 1 *
  • 1049 ATM 80 PSI I 120 PSI, 103"F IX I

10+8 I 1046 I I I ATM I 120 PSI. 103 "F 1052 ' e 1050 I 120 PSI, 103°F ~M: -. ' 1060 77-234 J X

o....

1..

-1 1.. I I

1061 I 1..

o....

2" I r-1/2" TO RADWASTE DISCHARGE 1 J. ~ 10 47E830 3.812) 1 I?".,_ 0-2-1565 1062 1 /2" 0-2-1566 6" FROM CNDS SUPPLY....... A-+7E818_1.EBI 0-2-1567 FDF IWF BACKWASH ........... --t:0-47E830-3,A3 112" 0-2-6021 TO FPF/0 BACKWASH CNDS RECYCLE t_..,..a '**J. '..t,;. '"";._--~:-4~7'.'E'_l8~3'.'2'::-:!_1.,_, Bl3:8i!) TO CST 2,, <0-47EB30-2, B7t-3" PACKAGE VENT HEADER TO FPF/D RESIN TRAPS -47E832-1, E6) TO WASTE DEMIN 47E830 2,F5) 1063 ~ I 3/8* I I 1065 I ATM I 25 IN. Hg VAC ~ 0 VACUUM PUlr s.57 sen.A 1066 ~ Pl 7~0 ~ m 0 RECEIVER TANK 1.48CUFT 3/8" 1078 IASTE A DRAIN SAll'LE TANK ROOMS EL 578.0 2" 3/4" DR N

r*

I I c:=======> ~ I :tvi. ,--IJ,-*-£1--l>il><:l-.. lt,vl.:1-:-------!f-------,,--IJ,-*-El--l>il><:l---il'\\ ... 11"11------------..... *-,0.-!-~>

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