radioactive waste control systems flood or design basis … · 25-03-1971 · 9.5-3 offgas system...

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

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9.0-iii

LIST OF ILLUSTRATIONS


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





BFN-26

9.0-iv

LIST OF ILLUSTRATIONS


Figure Title

9.5-2 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.

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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 μs/cm) or high radioactivity concentration (>10-3 μCi/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.

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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-3μCi/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

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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


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


BFN-16

Figure 9.2-2

Deleted by Amendment 7.

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"-...._ B" fLOATWELL

' "--12•-o• WATER SEAL

OFF-GAS CONDENSATE SUMP OFF-GAS CONDENSATE DRAIN SUMP PUMPS CAPACITY 50 GPM o 67 FT TDH

<D

. ' .. "'

'

' <D

,r 0

Fl El 546.0

•=•=== l"lNNNNN

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= = ~

n n n

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= =

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' 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

• .. . ..

. ..

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~ zz w

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CON VI >-,_, .... -- I-< <C:i: C ..,.0:::

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El 537'-6"

• n • n • n

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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

ItT-

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----1- 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 1

1 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 -1-~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 ~

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zz --<<n ~w 0~

w ' 0 ~ m w ~ ' 0 v.,

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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-t0~------------------'~ 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 " :" , < <I - "' I l, I"' L-C:c:".7:-:--:c:,

-..1---,-+·-------RECYCLE _______ 117,---,..~~.J· a.. a..,o-47E830-1 E5 1'--JMllf--> .., 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


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

"':,,,.,"

" .. ---": ",., ~ ~ ~

' ' -2--"',., "'

' ' ' _:jJi

°'"D,NSAT£ ~ WAST£ SI.LrlG£ P ... PS

AMENDMENT 24 TUR81NEa.RAOIOACTIVEIIASTEBUILDING UNITO



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. ~ 1 0 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-·-,0.-!-~><!--:"1-il'\"11"11------, .--1l-·-!ll--l>il><:l--:1t:v1 ... 1-------------. -

: c======::::i--0--0~ I :M1-:----.

: c======::::i- -~\ :..:!::: :: I '------------"·o"'.<1 ?

.¢._ ,>. ·o· '.

', •• <!. .~

<1·· 0 • ~ 0 .'I ·.·,.;.. ~t'~· .

SOLID IASTE PACKAGE <FOR STATIONS 1, 2. 3, OR 4 AS REQUIRED)

120 PSI. I

xi 103 •r I

SEAL WATER

1 • . . . -1064

ATM

1 /2"

3"

•

1 /2" 0-47E856-1,A5'>---C><ll--'...:a.-----..-~ . '

3/4'' SAMPLE

SPENT RESIN FROM WASTE DMNRLZR lo ,2 ,3 47E830 2,D6"

TO BLDG EXHAUST DUCT 2• VENT

<o-47E865-6 H71-"--'~'-----.

1054

3•

rs ' Ti~,

., ~ ~ 0

• _____r{FCV\ X ~235X

• •

. ~ -' - .,

:;; 0

- .. ff:

. -, ~ 0

409A

STATION Jo. 1 I

-~ 77-256 1 .>.

Pl 77-1628

. ~ -' -

.--n---1~

.--·-Ill-

• < :;; . e

. , : ~ 0

'---C,:,:J--{ p I :.. r 77-162A

410A

LT 77-161 ''v---'1 ' .J

B SPENT RESIN PUMPS r A

100 PSI ATM (TYP 2)

TOP OF OVFL EL 555'-5"---

" HIGH LEVEL ALARM EL 554'-9•

\..

PUMPS STOP EL 549'-8" -~

~

SCREEN

SPENT RESIN TANK CAP.: 1800 GAL. DESIGN PRESS. ATM

• ..

Ci) 50 GPM 0170 FT TOH Ci)

. ..1114· ,..~ t-,r-:.,, ~ ~ -'

' N ., ~ ~ 0

2"

, N 0 ..

~oR, TYP 2 (CONT SH 1)

-' ' N

< ~ ~ 0 ,,

LOW LEVEL ALARM EL 549'-5" ------+--,-----------------0-----....... ---,--l-=...-1

........... -- j ..

(FCV'\ 7!-~3

' >

LU 3/4• SAt.tPLE

1-1/4" 2"

I

.. .. - .. ..

• _____r{FCV\ X ~239X ~40X

s- .. - .. - .--0-·-0~ ..~-·-ti- .. .. ..-............

--@41

• • I :_ • •

• ..

.

3" DR

STATION NO. 2

-

IASTE PACKAGE ROOM EL 565.0

1-112·

1" CNDS

1068 1069 X I r VENT TO C .t. WPS RM120 PSI I ATM

' 103°F I

. ~

' N

INVERT EL 557'-4"

4" OVFL .t. VENT

3•

TANK CLEANING 1__.. ..... ~._~f-....jl_ NOZZLE ----.. /"'

HIGH LEVEL ALARM ~ .t. SECOND PUMP STARTS EL 553'-6"--.i FIRST PUMP STARTS ['\..~~~~-EL 553 '-o• -----.._ -....

'-OVFL TO EQPT DR SUMP (SH 1)

PUMPS STOP EL 550'-3"

LOW LEVEL A~,-

---

EL 550'-0" -----!'~,,.__~=--EL 549'-3" ----,1"':......~"'=~-

3"

STATION NO. 3

. ~

SEAL WATER /0-47E856-1 ,A3I

. ' ' .

< .. 8

1--C,:x:J--{p I = 77-186A

413A

-

1/2"

A m WASTE PACKAGE

DRAIN TANK PUMPS 25 GPM 0105 FT TDH .

~ -'

M11-:-----. .. ..

.. I

I

• • •

STATION NO. 4 • ~

ATM I 50 PSI I

43-744

-' - ., ~

. '

8

m .. 8

X

. -0

1-1/2"

(FCV'\ 77-188A

i 1-1/2"

·;a (FCV'\ 77-1888

i 1-1/2"

. N

TO WASTE COLLECTOR TANK 0-47E830-2, I7 '>

TO CLEANUP PHASE SEPARATORS 0-47E830-5, 88 '>

TO CNOS .t. WASTE PHASE SEPARATORS 0 47E830 4,E1 >

. -, \ X ~PLATFORM

EL 555.0

f--Co::J-{ p I = 77-1868

414A 50 PSI - -----

, .... -8 .. ATM (TYP 2)

m . ~ -'

>

120 PSI, 103"F I ATM

\•J BLOWOUT .

2" DR _ _ ,

1059

7

SPENT RESIN PUMPS A TANK ROOMS EL 546.0

6 5

IASTE PACKAGE DRAIN TANK CAP.: 500 GAL. DESIGN PRESS. 16 PSI

• N

DR TYP 2 (CONT SH 1)~

2"

·~ •a!

IASTE PACKAGE DRAIN TANK ROOM EL 546.0

., 0 ~ . e 2"

3

COMPANION DRAWINGS: 0-47E830-1,-2,-3,-4,-7,-8,-9 0-47E830-5

0-77-1412

NOTES,

O-SMPL-077-01 89 1.1.1 ~ N .. < ~

.

~----0-77-1409 MANUAL SAMPLE POINT

N

0-77-1413

L] PORTABLE COLLECTION FLASK (BY FIELD)

~ ~ ._ u~

~ ~

"' ' N

' 0

• al N

.,

' m ~ ~ ~

"' !;: C

6

1. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-+7E830-1.

-~ .. u

"' w "' .. < -~ .. u

2. FOR SYSTEM 2 GENERAL NOTES AND REFERENCE DRAWINGS SEE 1-47E818-1. 3. UNIDS ON DRAWINGS ARE FOR REFERENCE ONLY AND ARE ABBREVIATED

AS SHOWN IN THE EXAMPLE TO MEET SPACE CONSTRAINTS. REFER TO MEL FOR COMPLETE UNIDS. ALL UNIDS ARE IN UNIT O AND SYSTEM 077 UNLESS OTHERWISE NOTED. LEADING ZEROES SHOWN IN MEL AS PART OF THE UNID ARE NOT DEPICTED. FOR ADDITIONAL GUIDANCE. REFER TO SPP 9.6. EXAMPLE: MEL UNID

BFN-0-CKV-077-1039 BFN-O-SHV-002-1575 BFN-0-PI-077-0250

REFERENCE DRAWINGS:

DRAWING UNID 1039 0-2-1575 PI-77-250

1-,2-,3-47E818-1 ... FLOW DIAGRAM CONDENSATE STORAGE AND SUPPLY SYSTEM 0-47E832-1 ......... FLOW DIAGRAM FUEL POOL FILTER/DEMINERALIZED SYSTEM 0-47E856-1 ......... FLOW DIAGRAM DEMINERALIZED WAIER 0-47E865-6 ......... FLOW DIAGRAM HEATING .t. VENT AIR FLOW

AMENDMENT RADIOACTIVE WASTE BUILDING UNIT 0

28



FIGURE 9.2-3f

H

G

F

E

D

M

C

B

A

RADWASTE EVAPORATOR BLDG & RADIOACTIVEWASTE BLDGUNIT 0

BROWNS FERRY NUCLEAR PLANTFINAL SAFETY ANALYSIS REPORT

RADWASTE SYSTEMFLOW DIAGRAM

FIGURE 9.2-3g

I•> """''"' 1,,,\S'

' '

AMENDMENT 22

,:,,;,;1_.,,.,_L, .-,

RADWASTE EVAPORATOR BLDG &RADIOACTIVE WASTE BLDGUNIT 0


RADWASTE SYSTEMFLOW DIAGRAM

FIGURE 9.2-3h

M,1ENDl,1ENT 1 6

'' ,---,- ,-.-.-·1 i---. 1--• • -.---i---. 1 , I , , ,-,-- f--,-,-- l -.-.-,10

-

-<.

·- .,.~. . "'°I .,. ... :·::'· A ]' r1 a r "'·

mu. .. Tr ,. · t I;=:· ~==.. ~,----t---'----w-. .,t===~...;,

. . . ~. . I i ----~----·-··, -- I . I !!'!:i'~ '

. ----+I+-' --f··---:.. I 1· '""'--~ ~~----~1~--t~: I :~~~-

l I ii! 1· 1 · 1 ..... ~ ~. I .: I! i I ~-=···

I ! I i : ,•4•,-~ I I .,.,,~·=· 'I : • I • .11......; .lL I ; .:.·~· - w- 0 =~·-----.,,-------·--.c~ -·--- '..

-

L --I ·

-

I i ' ' I I I 10

i---.. ,,,, •2~

.......... - .... -... -·--·

AMENDMENT 16 ~f-.,,,0.lf C..•S lttlirwll'f1 IUILOI~ 11t11, Q ,-9ROUIS FERRY NUCLEAR PLANT f'lN~L s-.Hn ANAl YSJS R(PORT

1U0WA.S1( St·STE\t "tOW 0),1.~~At,1

tlGURt 9 2-JI

ZLO~~-LL-0~93Lt-O V>l LS

TABLE B (LS\_ _____ -, 7 __ 1 1----FRCJ.1 TURBINE BLDG ~ 0-47E610-77-11, A4

PIPE TUNNEL UNIT ZS VALVE POSITION ZS-77-2AA ORYWELL FD SUMP INBD ISOL VLV POSN. OPEN

77-12

I SUMP B NOTES:

s -@9-4

,- C

I I I

~9-19

IS r- 11-1• I 9-4 I .._ - ---1'ii'i I -@s-1~ IS t-- 77-1A

w-:::.r~-,

SEE TABLE B

X-18 x I ~-a, 1 11 1 ~-u:;-, 1 ~,>Q,11111,,(B(g I

SEE TABLE B

TYPICAL OF UNITS 1,2 & 3

1 . 2 ZS-77-2AB & 3 2S-77-2BA

ZS-77-288

TABLE C UNIT ZS

ZS-77-1 SAA

1 , 2, 3 ZS-77-15AB 2S-77-15BA ZS-77-1588

zI-77-2A~5- 17 111 11 I 2~ 17 I f fill- ,o-73DE934-21~ -T-:::..t-% r,:,<I 11 l'r,,{' .. I R ~ R

DRYWELL, REAC I R .. ~ I I 11 I~' @. I I I , ,

DRYWELL FD SUMP INBD ISOL VLV POSN. CLOSED DRYWELL FD SUMP OUTBD ISOL VLV POSN. OPEN ORYWELL FD SUMP OUTBD ISOL VLV POSN. CLOSED

VALVE POSITION DRYWELL EQPT DR SUMP INBD ISOL VLV POSN. OPEN DRYWELL EQPT DR SUMP INBD ISOL VLV POSN. CLOSED DRYWELL EQPT DR SUMP OUTBD ISOL VLV POSN. OPEN DRYWELL EQPT DR SUMP OUTBD ISOL VLV POSN. CLOSED

SEE NOTE 11

9-22~ _

~ '---'

UNIT 3 ONLY SEE NOTE 10

CONDENSATE PIPING TUNNEL SUMP & PUMP UNIT 0

!!1~ -z << ~~ 0 ~ ~o

0~ OU ~w ~~ ~

00 ~"

REACTOR RADWASTE BUILDING BUILDING

TURBINE RADWASTE BUILDING BUILDING /,.,~~ I

9-4 /HS\:_ ..r 1-~-A I

0-730[934-17 , BLDG I L~_J 1 11 Li-.:_: '"-j-zI-n-28 1 2@:5-17 I I -@25-17

- ..... WV-./Y-,< -- I HS ...l 1... HS 1 .. !EZ ® ~ ~ _J l 7-8A-AI I 11-88-A r-T-,

L'G ~:_. CISS £r : c~ss 1zl°:ts11 i----~E (Hs\_J ~_/HS\~~h 6 ~ ~ r+-1 ~-~-~i 2s-11 I

@;_. -t I

MCC I

SEE NOTE 18

I - ~-A I A I LOG I NOT?$i\z.:;..~A-BI I 77~-B 25-17

+-:;:1;w-Qr ,oo 1 - - 1 25-102 LA 25 11 1 1 ~ 25-11-102 (Hs\_ J I 25-17 I I PLC -- ---I ~~}BJ, n-2A a I ~ n-aA I I e_@Lc ~A-Al

./HS\ 1 I 77-8A Mee,.,, :,., Mee 77-88 (Hs\_ I

o[-:Z7}30Q!E]9}34[-]2}3J-I--,- -,.. - -,

I~ >Q I -®25-11 j... HS I 77-98-A

I _/HS\

r--~-~~[o-~7~3~0~E9[3B<~-I2•~;-~--,

'1f*I I'@'* ~ ~11 I I ' ' ~ 4 j... _[Hs'\25-17

A-A I I \Qj OB-A

(Hs\_ I I _/HS\ ~1 OA:;, 1 t' - 'Q:J be-e

,--,-1-~ >QI

25-171 4

A-A I

OQ:-:17}3])iOE~91!3~4::C:-2~71J-I- "f" - ~ - -, :

: ~ >Q i::. 1 .J'Hs'\ I 77~-A

I ../HS'\ r--77-118-8 t- 11.]-e I : 1 ~ 3 ~ ~ I ~ME 6 ~;;:~

--1.,.----- ----------.J I I 77---8~ CROSSTIE r1 1 ~A 25-2601 ' 9-19 I y UNIT 2 I 7 9

'-.);.<Mee i'fl'L_--,1 I .J ONL v - I 25-~7:: -

~ ~ L I LT PAREI ~

~6fE 6 9-4 ~..J.-

(08 @,A

t' \Z.:j!B-e I I

SEE NOTE 6

I I I I

-~~2

(Hs\_ I ~1A=1i1

I 25-260 I (w\_

/LA\ ~l}

I '---'

_fo\__ I

y;~-17 ~:P

1--1-----!---I ~5-111 LIS LT f"" 77-1A - 77-1A I 25-111 L~ LT 'ZZ;J 9- 11-,·"•,....,:::::::: __________ ~

I I I I I I I

r--_J

UNIT 1 DRYWELL FLOOR DRAINS SUMP PUMP PIT & PUMPS EL 549.92 TYPICAL OF UNITS 2 & 3

r--,.---,----,

:@:~>Q I 9-4 I

~ - -!--lll@o~-1[3!!D!!E}9~34[-:]1IJ1 I :o/-~1

:@:~>Q: ~25-171 I HS 1---'

11~-e I

SEE NOTE 6

I I

SEE NOTE 18

X-19

TYPICAL Of UNITS 1, 2,

I -T I 11-8e I 25-11

I ,\~ I ~ I LE A I LE I I ¥J I I 77-8A I 77-88 t- _j_ E:5:MCC

I .l_ UNIT 1 I 25-703 I I (Li\ REACTOR BUILDING FLOOR I, fLJ\ I I 77~-B DRAINS SUMPS & PUMPS 1 '--'i,8d I

"' /LA\ '\_~ 77-10 25-17

;c y ~cc! r~-----

I ___ J h 77L-~ 1 25-17 (l \.cc~ Y ~ _J

r----..J--~t'4CC_

1 ~ =--=-..::::-_--=--~ UNITS 1 &. 2 ONLY I

~11

I I ___ ...J

I f}rf~fL 0oF UNIT 2. FOR I g~[i 2 I LE I UNIT 3 SEE DET C12 ! r,::-. I 77-o/L==----------J

I w LI '

I I

UNIT 1 I TURBINE BUILDING FLOOR DRAIN I

UNIT 1

LS ___/LIT\____J__ 7-1 lA'Z:.:J~----------~

BACKWASH RECEIVER PIT FLOOR DRAIN SUMP PUMPS COi.NON TO UNITS 1 & 2 -/-4 --=---==- ----- 77~8~

--- ~t

1 I I I I I L _____ l

---- ---

REACTOR BUILDING EQUIPMENT ACCESS LOCK MACHINERY PIT SUMP & PUMP

ONLY

SUMPS & PUMPS @a El 557 .0 FOR UNITS 2 ~ 3 SEE DET H12

TURBINE BUILDING CONDENSATE ® PUMP PIT FLOOR DRAIN SUMP & PUMPS EL 551 .0 TYPICAL OF UNIT 2, FOR UNIT 3 SEE DET G12

DA

25-703

El 533.0 TYPICAL OF UNIT 3

0-45E775-3 0-730E934-29

~ zm m <~ ~ ~ . ~ WN

' ~ ' . ~ "' ~ ~~ <~ . ' "' ' 0 0

"' - " -~m wm "' w ,cw "~ "~ ... ~ o, ~o o, ~o

&3~

~-------- ---------, +- -hi;JLOG~;:1 77-16

I I 9-1 9

t--@ I '---'

~-~1 SEE TABLE C

r----l2-730E937-23!

r--r--r-w ;@: I ~' 25-171 /HS\:_j 77~-A I

(HS\__~ 77-20A-8 '---' I

-' ~

I I _/Plc\__

77-20 j25-702

~

' 0 ~ I I I MCC

I

r-iD-730E934-26I

RADWASTE BUILDING FLOOR DRAIN SUMP & PUMPS El 546.0 UNIT 0

--t-'f-~ I/~~' I 25-11

,-i0-730E934-37 ! : Ai SEE NOTE 6

I LS(// I ~-../HS'\ I 77~-A

I ../HS'\ r--77-208-8 I ~

I --l

l'l ~MCC

t' 77-211--/-h

I 2s-if 1/ I _f'u;<., r 77-21-A

'---' 125-11 /

t--@. I '---

FROM DEMINERALIZED WATER SYSTEM __ ./'

STACK SUMP El 556.0 UNIT 0

OVERFLOW TO FLOOR DRAINS COLLECTOR TANK

-47E610-77-2, F8

r-iD-730E934-29t- 1 I

i:T-' R I ..

25-11 I r,:;;\_ ..J

77 -:.:3J-A 1

(HS\_~ 77-22A-8

'---' I

L,x-~ I )2.z r®.. 1 25-11

1--../HS'\ 1 77~-A

~-../HS'\ 77-228-B I '---' I

m ~

. N

' ~ ~

' 0 m w ~ ~

' 0

*i:l 25-11 I

r,:;;\_ ..J 77~-A 1

r,:;;\_~ 77-23A-8

'---' I

,. NORMALLY EACH SUMP IS EQUIPPED WITH A FLOAT WELL IN WHICH LEVEL SWITCHES OR TRANSMITTERS ARE INSTALLED TO AUTOMATICALLY INITIATE ACTIONS AT SEVERAL SUMP LEVELS AS FOLLOWS: A. HIGH LEVEL-START PUMP SELECTED BY AUTOMATIC PUMP

SELECTOR SWITCH OR PLC. B. HIGH-HIGH LEVEL-START SECOND PUMP AND ENERGIZE

HIGH-HIGH LEVEL ANNUNCIATOR CIRCUIT. C. LOW LEVEL-STOP PUI.P(S). 0. A FOURTH CONTACT IS INCLUDED TO OPEN A DEMINERALIZED

WATER INLET VALVE AT LOW-LOW SUMP LEVEL TO MAINTAIN A MINIMUM SUMP WATER SEAL LEVEL ON THE FOLLOWING SUMPS ONLY: ( 1 l STACK SUMP (2 STANDBY GAS-TREATMENT BUILDING (3 OFF-GAS CONDENSATE COLLECTOR SUMP IN THE RADWASTE BU LDING

THE DRAIN LINE FROM THE OFF-GAS SYSTEM DEHUMIDIFICATION COIL TO THE TURBINE BUILDING CONDENSATE PUMP PIT EQUIPMENT DRAIN SUMP FORMS A LOOP SEAL IN WHICH A LEVEL SWITCH IS LOCATED TO OPEN A SOLENOID VALVE AND ADMIT CONDENSATE TO THE OFF-GAS LOOP SEAL PIPE AT A LOW LOOP SEAL LEVEL.

2. THE DRYWELL FLOOR AND EQUIPMENT DRAIN SUMPS, THE REACTOR BUILDING EQUIPMENT DRAIN SUMP FOR EACH UNIT, AND THE RADWASTE BUILDING EQUIPMENT DRAIN SUMP IS EQUIPPED WITH TWO FLOAT WELLS AND TWO LEVEL SWITCHES OR TRANSMITTERS. THE TWO LEVEL SWITCHES ARE INTERCONNECTED TO ACHIEVE REDUNDANCY FOR PUMP CONTROL TO PREVENT SUMP OVERFLOW IF A PUMP FAILS TO START DUE TO A SINGLE LEVEL SWITCH OR TRANSMITTER MALFUNCTION.

3. THE CONDENSATE PIPING TUNNEL SUMP AND THE REACTOR BUILDING EQUIPMENT ACCESS SUMP USE ONLY A SINGLE FLOAT SWITCH WHICH IS PART OF THE SUBMERSIBLE PUMP.

4. THE DRYWELL EQUIPMENT DRAIN SUMP AND THE REACTOR BUILDING EQUIPMENT DRAIN SUMP FOR EACH UNIT ARE PROVIDED WITH AUTOMATIC TEMPERATURE CONTROLLED RECIRCULATION SYSTEMS WHICH ROUTE SUMP WATER THROUGH HEAT EXCHANGERS TO PREVENT HIGH - TEMPERATURE SUMP EFFLUENTS FROM BEING PUMPED INTO THE RADWASTE SYSTEM. THE HIGH TEt.iflERATURE ANNUNCIATOR IS INITIATED BY TS-77-14, NOT THE CONTROLLER TIS-77-14.

5. THE EFFLUENT FROM All FLCXlR DRAIN SUt.FS IS PUMPED INTO THE FLOOR DRAIN COLLECTOR TANK IN THE RADWASTE SYSTEM. THE EFFLUENT FROM All EQUIPMENT DRAIN SUMPS IS PUMPED INTO THE WASTE-COLLECTOR TANK IN THE RADWASTE BUILDING (SEE 0-47E610-77-2).

6. All RADWASTE ALARMS ARE REPEATED IN THE MAIN CONTROL ROOM ON ONE DROP "RADWASTE SYSTEM ABNORMAL" ON PANEL 1-9-228 XA-77-302.

7. THE SIX LEVEL SWITCHES LS-77-25A THROUGH LS-77-25F ARE SET TO SOUND AN ALARM IN THE CONTROL ROOM WHEN THE WATER LEVEL IN THE RESPECTIVE ROOMS REACHES 2" ABOVE THE FLOOR LEVEL.

8. All VALVE STYLES WILL BE CHANGED, AS REQUIRED. WHEN PURCHASE SPECIFICATIONS ARE APPROVED.

9. FOR PANEL LOCATIONS OF PILOT LIGHTS. SEE THE PANEL NUMBER FOR THE ASSOCIATED HAND SWITCH.

10. VALVE INTERNALS REMOVED BY DCN 50572. 11. SEE 0-47W600-157 DETAIL D157 FOR MTG. 1 2. DELETED. 13. FOR GENERAL NOTES AND REFERENCE DRAWINGS SEE 0-47ES10-77-2

AND -4. 14. All COMPONENTS ARE PREFIXED UNIT "D-" UNLESS OTHERWISE NOTED. 15. PARTIAL LOGIC FOR RADWASTE SYSTEM IS SHOWN ON MECHANICAL LOGIC

DIAGRAM LISTED IN REFERENCE DRAWINGS. 1 6. DELETED

17. UNIDS ON DRAWING ARE FOR REFERENCE ONLY AND ARE ABBREVIATED TO MEET SPACE CONSTRAINTS. REFER TO MEL COMPLETE UNIDS.

18. LEAD/LAG RELAY LOGIC IN LIEU OF XS, UNIT 1.

REFERENCE DRAWINGS:

FOR

1,2,3-47E852-1,-2 ............... FLOW DIAGRAM- CLEAN RADWASTE A DECON DRAINAGE

MEL ............................. INSTRUMENT TABULATIONS-RADWASTE SYSTEM

0-47ES30-1 THRU -15 ............. FLOW DIAGRAMS-RADWASTE 0-47ES51-1 THRU-4 ............... FLOW DIAGRAM-DRAINAGE 1,2,3-47E852-1, -2 .............. FLOW DIAGRAM-REACTOR BLDG DRAINAGE 0-47E852-3 ...................... FLOW DIAGRAM-REACTOR BLDG DRAINAGE 0-47E800-2 ...................... MECHANICAL SYMBOLS AND

FLOW DIAGRAM INDEX 0-47ES00-1 ...................... FLOW DIAGRAM-GENERAL PLANT SYSTEMS 0-47E611-77-SERIES .............. MECHANICAL LOGIC DIAGRAM RADWASTE

SYSTEM 45E615-SERIES .................. CONTAINMENT ISOLATION STATUS SYSTEM

(CISS) GE DRAWINGS:

730E769 .......... FUNCTI0NAL CONTROL DIAGRAM 0-730E934-SERIES ... ELEMENTARY DIAGRAM

CROLL-REYNOLDS ENGRG CO: D-69784 .......... RADWASTE FILTRATION SYSTEM

25-702

TO WASTE COLLECTOR TANK 0-47E610-77-2, DB

0-730E934-29 r 0-45E775-3 I

r-:-t:-,;:i_.. I .@_ ~ 1 25-11

t- -@38-A

~ _/HS\ I ~2,e-e

I

9-19 9-4

I I

---' SEE NOTE 6

I I _ _/Plc\__

77-22 'lts-702 I

I SEE NOTE 6

I I _µcc\_

77-23 y

I

TE ..Loci_~ 77-14~ 914 9-4

DRYWELL REACTOR BUILDING

~w-r--2,-111

"'40-730E934-26 ~

(Hs'\" -l ~••-A I

® I 4

A-8 I

I I ...r---

~6fE 6~A 25-17 (.

77-24-A ~ SEE 25-17 MCC NOTE 6 t---------

'(LA\_~ 4A \zz...::..24-BI 1\:24 5-103 I A

I I _____ _J

TO WASTE COLL TANK -47E610-77-2, D8

--r-*i I -®2s-11 1- HS I 77-248-A

I -® ~ HS I 11-2<•-• I I --...,.._

:-i ~

t--------t-- MTR-24A B

MTR-24B

© I I

48 HV 77-24

0-47E847-2, CS

VENT

FROM DEMINERALIZED WATER SYSTEM 1-47E856-2, A7

STANDBY GAS TREATMENT BLDG NO. 1 SUMP El 565.0 UNIT 0

8 7

EQPT ACCESS REACTOR LOCK BLDG

UNIT 1

DEMINERALIZED WATER SYSTEM

El 565.0

TO REACTOR BLDG FLOOR DRAIN SUMP

WATERSEAL BETWEEN EQUIPMENT ACCESS LOCK AND REFUELING FLOOR VENTILATION ZONE El 565.0 1 ONLY

6 5

RADWASTE EVAPORATOR BUILDING FLOOR DRAIN SUMP & PUMPS El 565.0 UNIT 0

4

25-17 r-..., / LA 1 77-22 y I

ID-730E934-29 I- -,1-- - -

@)2A I I ~L25-703

@2.

e:: I I I I

~\A

- -I0-45E77 5-3

RADWASTE BUILDING OFF-GAS CONDENSATE DRAIN SUMP & PUMPS El 5+6.0 UNIT 0

e:: e:: e:: e:: I I I I

®58

I I I I

@5c

I I I I

@oo

I I I I

@5E CORE SPRAY A RCIC ROOM

CORE SPRAY ROOM

RHR PUMP ROOM

RHR PUMP ROOM

HPCI ROOM

UNIT 1 FLOOD LEVEL SWITCHES El 519.0 (SEE NOTE 7) TYPICAL OF UNIT 2 &. 3

COMPANION DRAWINGS: 0-47E610-77 SERIES

3

(LA\ A 77-23 (

25-17~c~ r--..J_.::_ __

I I ___ ...J

01\ I 77-23A I

125-7031 1--

~4

y" I I I I

r.;;--, 1.z0s,

PRESS. SUPPRESSION CHAMBER ROOM

2

LE 77-23 ~-----------~

RADWASTE BUILDING EQUIPMENT DRAIN SUMP & PUMPS El 546.0 UNIT 0

AMENDMENT 28 POWERHOUSE UNIT 0

BROWNS FINAL

FERRY SAFETY

NUCLEAR ANALYSIS

PLANT REPORT

RADWASTE SYSTEM MECHANICAL CONTROL DIAGRAM

FIGURE 9.2-3j

H

G

F

E

D

C

B

A

.............. ,=, ... ,_, __ ,,

AMENDMENT 27 l'Ol'ERHCUSE UNITO


MECHANRl'iltScTJNr5RycitTEDMIAGRAM

FIGURE 9. 2-3n

AMENDMENT 24 POWERHOUSE UNITO


RADWASTE SYSTEM MECHANICAL CONTROL DIAGRAM

FIGURE 9,2-Jp

POWERHOUSEUNIT 0


RADWASTE SYSTEMMECHANICAL CONTROL DIAGRAM

FIGURE 9.2-3q

G

C

M,1ENDl,1ENT 1 6

A

5

RADWASTE EVAPORATOR BUILDINGUNIT 0



FIGURE 9.2-3r

~---~

C

M,1ENDl,1ENT 1 6

A

5

RADWASTE EVAPORATOR BUILDINGUNIT 0



FIGURE 9.2-3s

M,1ENDl,1ENT 1 6

---.-. ,.-.-.·r--.-. ,-.-.-.-.-r-.-.-.-. ~-.-~--~--~--·--~-- --~--·~ -~--·,---·,i--,---i--•• ---r-.-.-.-.1.,~ r-.-.-.-.,,-, -. -. Fl_• -· ............. , .. u _.

-

O· CONOfNSAT( Pf';!, 1UliHH SOW it SUNDBY GAS tRE,~

1~ENI BLOC NO. 2 SUW

-

-

•·

-

' C ' ' ' ' I ' ' ' ' 2 ' ' ' ' I ' ' ' ' ~ ' I .!. ' .!. .!. ' I ..!.. 10

AMENDMENT 25

BROWNS f(flRY HUCU:AR P'LANl

f' IH/.l s ... rETY ANAL YSJS ftEPOfitl

~ ... OIASJC S't'STUI M[CHANlCAL CONl~l OU.CRAM

f'lCUR£ 9.1-3t

·C

BFN-22

Figure 9.2-4(Deleted by Amendment 22)

BFN-16

Figures 9.2-4a through 9.2-4f

Deleted by Amendment 9.

BFN-25

9.3-1

9.3 SOLID RADWASTE SYSTEM 9.3.1 Power Generation Objective The objective of the Solid Radwaste System is to collect, process, store, package, and prepare for shipment solid radioactive waste materials produced through operation of the three reactor units. 9.3.2 Power Generation Design Basis 1. The Solid Radwaste System shall be capable of handling the following types of

wet solid wastes: Reactor Water Cleanup System Sludge, Condensate System Sludge, Fuel Pool Demin, Waste and Floor Drain Filter Sludge, Waste Demin Resins, and Thermex Sludge.

2. The system shall be capable of handling contaminated dry wastes, such as

rags, paper, spent filter elements, used laboratory apparatus, used parts and equipment, and tools.

3. The system shall be capable of handling irradiated reactor components, such

as spent control rods, and incore instruments. 9.3.3 Safety Design Basis 1. Packaged solid wastes shall comply with appropriate regulations of the U.S.

Nuclear Regulatory Commission (10 CFR 71), 10 CFR 61 and U.S. Department of Transportation (49 CFR 170-189) disposal site criteria and the states through which the wastes pass enroute to the disposal area and disposal site criteria.

2. The Solid Radwaste System shall be designed so that operations can be

conducted without exceeding maximum permissible radiation dosage to operating personnel.

9.3.4 Description (See Figures 9.2-3a, 9.2-3d, 9.2-3e, and 9.2-3f) 9.3.4.1 Wet Solid Wastes Wet solid wastes consist of spent powdered ion exchange resins, filter aid sludge, and bead-type ion exchange resins. These are stored, packaged, and prepared for shipment in the Radwaste Building.

BFN-25

9.3-2

Storage Spent powdered ion exchange resin and filter aid sludge are accumulated and stored in phase separator tanks. Batches of slurried materials are pumped into the tanks, where the solids settle out. The supernatant liquid is decanted off to make room for more slurry. Successive batches are accumulated until the desired settled slurry volume has been reached. After an appropriate decay period, the sludge is reslurried and pumped to the packaging area. The cleanup phase-separator tanks are closed-top, vertical cylinders with conical bottoms. Each has an overflow outlet leading to the Radwaste Building equipment drain sump. Decant outlets are located at three levels above the maximum settled sludge level. A bottom outlet leads to the suction of a sludge transfer pump. To ensure complete reslurrying, sludge pump discharge flow is directed through a set of eductors located in the settled sludge region. A flow through the eductors is maintained throughout the slurry transfer period. The condensate phase-separator tanks are vertical cylinders with conical bottoms. Each has an overflow outlet leading to the Radwaste Building equipment drain sump. Decant outlets are located at three levels above the maximum settled sludge level. A bottom outlet leads to the suction of a sludge transfer pump. To ensure complete reslurring, sludge pump discharge flow and air operated spargers are used to stir up the settled sludge. Air flow through the sparger is maintained throughout the slurry transfer period. High-activity-level sludge from the reactor water cleanup filter-demineralizers is stored in three cleanup phase-separator tanks. Each has a total capacity of about 785 cubic feet, which consist of water and settled sludge. The tanks are of stainless steel. Normal operating requirements can be met with two tanks with a 60-day decay period. The third tank provides operating flexibility and additional decay time. Six condensate phase-separator tanks are provided for storage of sludge from the condensate, the fuel pool filter-demineralizers, and the waste and floor drain filters. Sludge from the various sources may be mixed in the six tanks or segregated. Each tank has a total capacity of about 1850 cubic feet which consist of water and settled sludge. The tanks are fabricated out of stainless steel. Bead-type ion exchange resins from the waste demineralizer are stored in the spent resin tank. The tank is a closed-top, vertical cylinder with a conical bottom. It has a capacity of 245 cubic feet and is capable of holding the resin and water resulting from one backwash of the waste demineralizer. The tank is made of stainless steel. The spent resin remains in the tank until operations personnel determine it needs to

BFN-25

9.3-3

be transferred. From the tank the spent resin is transferred to the phase separators where it is mixed with other sludges. After mixing it is sent to the packaging area. Thermex sludge is stored in a shielded container located in the Radwaste Building. Packaging The packaging system is designed to permit the use of several different types of containers. These include disposable tanks (liners) in reusable shields constructed of carbon steel or high density polyethylene plastic. Each type of container has a slurry inlet connection and a vent connection. A connection is provided also for the attachment of a level indicator during filling of the container. A diagram of the packaging system is shown in Figure 9.2-3f. Prior to a packaging run, a container is positioned at one of two dewatering systems, either in a shipping cask or in a shielded enclosure. For a condensate phase-separator, hoses are connected and the sludge pump and air-operated spargers are used to stir up the settled sludge in the phase-separator and bring it into suspension. For a cleanup phase-separator, eductors are used to mix the slurry instead of air spargers. The slurry then is pumped to the loading station and back to the phase-separator tank. A portion of the slurry is drawn off into the waste package until the package is nearly filled. Water is withdrawn through the built-in filter elements via the portable dewatering system(s) and drained into the waste package drain tank via one of the drain header valves shown in Figure 9.2-3f. This process is repeated until the package is nearly full of dewatered slurry. The portable dewatering system hoses are disconnected, package penetrations are plugged, and the package is prepared for onsite storage or offsite shipment. Thermex sludge is packaged and shipped offsite for further processing if required. Processed sludge may be shipped to a licensed disposal facility or returned to BFN for onsite storage in an approved storage area. 9.3.4.2 Dry Solid Wastes Dry solid wastes include contaminated rags, paper, clothing, spent filter elements, laboratory apparatus, small parts and equipment, and tools. Items of dry solid waste are collected in suitable containers located throughout the plant. Spent elements from air and gas filtration systems, liquid filter elements from the filter demineralizers and laundry system, and elements from the offgas system, which may have a high-radiation level, are packaged in accordance with applicable burial site requirements prior to being transported for processing, burial, or approved onsite storage. Low-level solid wastes, such as sand, dewatered sludges, dewatered resins, overpacked damp or wet wastes and solidified or stabilized wastes, may be stored onsite in approved storage areas. In such instances a

BFN-28

9.3-4

maximum curie inventory of 325 curies will not be exceeded. After a period of storage, the containers are removed from the storage area and prepared for disposal. Shielded containers are provided for offsite shipment of high-activity waste if required. Waste may be shipped offsite to a processor for volume reduction. An equipment decontamination unit is in operation allowing equipment and tools previously disposed of as radioactive material to be placed back into inventory or disposed of as clean trash. Some LLW, stored in drums or boxes, are placed in trailers until they can be sent to commercial processing or disposal facilities or transferred to approved onsite storage facilities. 9.3.4.2.1 Onsite Storage Facility (OSF) In order to provide storage for low-level radioactive waste (LLRW), an onsite storage facility has been constructed. This facility is located on the Browns Ferry Nuclear Plant reservation outside the existing security fence. The grade elevation is approximately 574 feet above sea level, which is above the probable maximum flood elevation. The LLWR facility is comprised of modules numbers 1 and 2. The modules are designed to contain radioactive waste generated at Browns Ferry and are segmented into compartments. LLWR Trash Module 1 is used for the storage of low level radwaste, including the OEM steam dryers removed during the EPU outages. Radioactive wastes will be stored in Module Number 2 in High Integrity Containers (HICs) or AVANTech steel liners within those compartments. The modules are above ground, safety-related structures constructed of reinforced concrete. Access to the modules is provided only from above and is primarily used for placing LLWR in or removing LLRW from the modules. The modules are designed to resist loads resulting from extreme environmental events, such as high winds, tornadoes, and seismic events. The structural characteristics of the OSF meet or exceed the criteria applicable to the Browns Ferry site. The storage module’s foundations are composed of concrete base slab and walls, placed on either in situ soil or compacted fill. The module’s compartments are provided with internal liquid drainage and collection capability routed to an external point for sampling and collection. The external collection point is surrounded by a covered concrete sump connected to the module.

BFN-28

9.3-5

The sumps for the modules’ compartments will be used as passive sumps to collect any liquid. This liquid will be sampled as necessary to detect the presence of water and/or radioactive releases in the modules. The OSF structure is designed to contain (within the module) all fire suppression water from a design basis fire in a way that will not preclude processing of the water (if determined to be radioactive) using the existing Browns Ferry liquid radioactive waste treatment system. The modules are enclosed within an access controlled security fence. 9.3.4.3 Irradiated Reactor Components Spent control rods and incore instrument strings and other miscellaneous irradiated components are stored in the spent fuel pools. They are loaded into shielded containers under water. These containers may then be stored onsite in approved areas or shipped offsite. 9.3.5 Power Generation Evaluation The system is capable of handling the necessary types, quantities and radioactivity levels of solid waste materials. Therefore, the Solid Radwaste System fulfills the power generation design bases. 9.3.6 Safety Evaluation A study of containers for shipping spent resins and filter aid was made under a contract awarded by TVA. The purpose of this study was to develop and test designs for licensable containers. All containers used to package low-level spent resins or filter media for offsite shipment have been approved for use by NRC and/or authorized by the Department of Transportation. Spent control rods, irradiated components, and spent resins or filter media, may also be shipped in shielded containers owned by vendors. Filling of containers with spent resins and filter aid is carried out without significant radiation exposure to personnel. Containers being filled are usually inside shields. Container connections are designed so that hose connections can be disconnected and plugs inserted easily and quickly. Filling lines may be rinsed with condensate before personnel enter the packaging area. Personnel involved with the entire operation of filling, disconnecting, plugging, and loading of solid radwaste will adhere to the various plant radiological procedures to maintain radiation exposures as low as reasonably achievable. It is therefore concluded that the safety design bases are met.

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9.3-6

9.3.7 Inspection and Testing Prior to operation with radioactive materials, the wet solids handling system was tested with nonradioactive spent powdered resin, filter aid, and bead resin to determine performance characteristics of the system.

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Figures 9.3-1a through 9.3-1b


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Figures 9.3-2a and 9.3-2b


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9.4-1

9.4 GASEOUS RADWASTE SYSTEM

(Deleted)

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9.5-1

9.5 GASEOUS RADWASTE SYSTEM (Modified) This subsection describes the Gaseous Radwaste System as it now exists with recombiners and activated carbon adsorbers installed in the condenser offgas system. 9.5.1 Power Generation Objective 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. 9.5.2 Power Generation Design Basis 1. The Gaseous Radwaste System is designed to limit offsite doses from routine

plant releases to significantly less than the limits or guideline values given in applicable NRC rules and regulations, and to stay within the limits established in the plant operating license. The offgas system is designed to provide adequate time for corrective action to limit the activity release rates should they approach established limits.

2. Arrangements have been made to allow decay of the short-lived radioisotopes

such as nitrogen-16 and oxygen-19. 3. Adequate safeguards have been provided against the possible explosion

hazard of the hydrogen and oxygen present due to the radiolytic decomposition of reactor water.

4. Shielding has been provided as necessary for process piping and equipment. 9.5.3 Safety Design Basis The Gaseous Radwaste System is designed to prevent the inadvertent release of significant quantities of gaseous and particulate radioactive material from the restricted area of the plant, so that resulting radiation exposures are within the guideline values of Appendix I of 10 CFR 50. 9.5.4 Description The Gaseous Radwaste System (Figures 9.5-1 sheets 1, 2, 3, 4, 5, and 6, 9.5-2, 9.5-3, and 9.5-4) includes the subsystems that process and dispose of the gases

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9.5-2

from the main condenser air ejectors, the startup vacuum pumps, condensate drain tank vent, and the steam packing exhauster. One Gaseous Radwaste System is provided for each unit. The processed gases from Units 1, 2, and 3 are routed to the plant stack for dilution and elevated release to the atmosphere. The air ejector offgas line of each unit and the stack are continuously monitored by radiation monitors (see Subsection 7.12, "Process Radiation Monitoring"). Activities of activation gases and fission product gases leaving the reactor vessel steam nozzles during normal operation are listed in Table 9.5-1. The corresponding activity arriving at the turbine and air ejector will be less due to decay in transit and the fact that part of the N-13, N-16, and most of the 0-19 remain with the condensate and do not follow the noncondensables. Other radioactive gases which may also be present are H-3, N-17, Ar-37, and Ar-41. These are present in low enough quantities as to be insignificant by comparison with the N-13. Of the activity arriving in the primary steam at the turbine, a fraction will go through the turbine shaft steam seals to the gland seal offgas subsystem. Of this small fraction of the total activity, most of the 0-19 and N-16 will stay with the gland seal condensate. Gases routed to the plant stack include air ejector and gland seal offgases and gases from the Standby Gas Treatment System (see Subsection 5.3, "Secondary Containment System"). Dilution air is provided by fans within the plant stack. The stack is designed such that prompt mixing of all gas inlet streams occurs in the base to allow location of sample points as near to the base as possible. The stack sump drainage is routed to the Liquid Radwaste Collection System via a submerged inlet sump. Air Ejector OffGas Subsystem Noncondensable radioactive offgas is continuously removed from the main condenser by the air ejector during plant operation. This is the major source of radioactive gases and is larger than all other sources combined. The air ejector offgas will also contain the radioactive noble gas parents of biologically significant Sr-89, Sr-90, Ba-140, and Cs-137. The concentration of these noble gases depends upon the amount of tramp uranium in the coolant and on the cladding surface (usually extremely small), as well as the number and size of cladding leaks. Radioactive particulate daughters are retained on the HEPA filters and on the activated carbon. The offgas is discharged to the environs via the plant stack. The activity of the gas entering and leaving the offgas treatment system is continuously monitored. Thus, the system performance is known to the operator at all times. The air ejector offgas system shown in Figures 9.5-1 sheets 1, 2, 3, 4, 5, and 6 use a high temperature catalytic recombiner to recombine radiolytically dissociated

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9.5-3

hydrogen and oxygen from the air ejector system. After chilling to strip the condensibles and reduce the volume, the remaining noncondensables (principally kryptons, xenons and air) will be delayed in the six hour holdup volume, then cooled to ≈45°F (dewpoint) with a chilled glycol cooler passed through a moisture separation, heated to ≈74°F (relative humidity ≈35 percent), and passed through a HEPA filter before reaching the adsorption bed. The activated carbon adsorption bed, operating in a constant temperature vault, will selectively adsorb and delay the xenons and kryptons from the bulk carrier gas (principally air). This delay on the activated carbon permits xenon and krypton radioisotopes to decay in place. This system results in a reduction of the offgas activity (curies) released by a factor of approximately 25 relative to the original 30 minute holdup volume and based on a modified gas mixture. Table 9.5-1 shows the estimated release rates of various isotopes of krypton and xenon compared to a system releasing 100,000 μCi/sec after a 30 minute holdup. The adsorption of noble gases on activated carbon depends upon gas flow rate, holdup time, mass of activated carbon, temperature, moisture content, and a gas-unique coefficient known as the dynamic adsorption coefficient. The parametric interrelationships and governing equations are well proven from three years of operation of a similar unit at KRB in Germany. Each of the six supply lines from the adsorber vessels to the unloading nozzle drain is equipped with low point drains for minimization of moisture buildup. As a design basis for this system, a noble gas input equivalent to an annual average off gas rate per unit (based on 30 minute decay) of 100,000 μCi/sec modified gas mixture will be used. Table 9.5-1 indicates the design-basis noble-gas activity referenced to 30 minutes after exiting from the reactor. Air in-leakage, during normal operation, will vary with the performance of the equipment that forms the vacuum boundary for the condenser. The in-leakage rate is not a limiting factor in meeting the design basis of the system to minimize radioactive release. Release limits for the Offgas System are specified in the Offsite Dose Calculation Manual (ODCM). The Offgas System is designed to control the release of plant-produced radioactive material to within the limits specified in the ODCM. The following data and discussion is maintained for historical reference. The information was used to estimate an 18.5 SCFM in-leakage rate for Browns Ferry prior to operation Air in-leakage design basis is 7 ft3/min. (at 130°F, 1 atm) per condenser shell. Leakage from three condenser shells corrected to standard conditions gives 18.5 SCFM, the original design leakage of the plant. With good-to-average maintenance

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9.5-4

within the utility industry, in-leakage varies from approximately 3 to 5 SCFM per shell for large shells. Where special maintenance is employed and leaks are detected and sealed, leakage is reduced to 1 to 2 SCFM per shell and remains at that level during extended plant operation. In three operating BWRs where condenser in-leakage has a significant effect on offgas holdup time, the following leakage has been observed. Number of Type of Total Air

Condenser Gas In-Leakage Plant Mw(e) Shells System SCFM) KRB 250 1 R/CG 4.1 Tsuruga 342 1 R/CG 4.7 Fukushima 1 440 2 R/CG 7.0 R/CG - Recombiner/Compressed Gas Data from six of TVA's coal-fired units are given below:

Number of Air In-Leakage Condenser Rate (SCFM)

Plant Period Mw(e) Shells Range Average Bull Run 1 4.5 950 4 5-48 14.5 Colbert 5 6.3 550 2 7-22 10.4 Paradise 1 7.6 704 1 2-14 5.6 Paradise 2 7.3 704 1 1-9 4.4 Widows Creek 7 9.2 575 1 2-18 8.8 Widows Creek 8 6.4 550 2 6-50 22.8 Period - Period covered by data in years The average in-leakage for the first four of these units was below 6.2 SCFM per shell, while that for the last two units was above this value. Examination of operating records indicates that the latter units were allowed to operate for extended periods with high in-leakage rates. Normally, no dilution air is added to the offgas stream, the air present during operation is from air in-leakage. There is an oil-free air supply which bleeds into the

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9.5-5

system during startup of the system. Its flow rate is ≈4 SCFM, which is stopped after the recombiner comes up to temperature. During times of low in-leakage, dilution air may be bled into the system to ensure minimum air flow rate for recombiner operation. The radiation levels at the air ejector offgas discharge line and after the offgas treatment system are continuously monitored by pairs of detectors. This system is also monitored by flow and temperature instrumentation and hydrogen analyzers to ensure proper operation and control and to ensure that hydrogen concentration is maintained below the flammable limit. In addition, any hydrogen analyzer abnormality will be annunciated in the Main Control Room. Process radiation instrumentation is described in Subsection 7.12. Table 9.5-2 lists process instrument alarms. The decay time provided by the six hour holdup pipe and the long-delay, activated carbon adsorbers is established to provide for radioactive decay of the activation gases and fission gases in the main condenser offgas. The adsorbers provide a 7.3 day xenon and a 9.7 hour krypton holdup. These holdup times may vary depending on offgas flow rates. The daughter products, which are solids, are removed by filtration following the six hour holdup and/or are retained on the activated carbon. Final filtration of the activated carbon adsorber effluent precludes escape of charcoal fines which would contain radioactive materials. Particulates are reduced to levels at or near the lower limits of detection. The activated carbon will remove iodines entering the system by adsorption and effectively reduce its release to insignificant amounts. A valve which is automatically closed on a signal from the offgas post treatment radiation monitors is placed in the offgas line close to the plant stack to retain gases when the instantaneous permissible release rate is exceeded. A signal from both channels is required to close this valve when this release rate limit is reached. If the valve has been manually jacked open, it is manually closed after receipt of a validated pre-treatment radiation high-high alarm if necessary to prevent the release limit from being exceeded. A steel mesh screen and support structure is installed downstream of the after-filters to ensure filter retention in the event of an explosion in the offgas system. Shielding is provided for offgas system equipment to maintain safe radiation exposure levels for plant personnel. The equipment is principally operated from the control room. A description of the condensate side of the offgas condensers is included in Section 11.8.3.6.

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9.5-6

Gland Seal OffGas Subsystem The gland seal offgas subsystem collects gases from the turbine shaft and large steam control valve gland seals through the steam packing exhauster and the mechanical vacuum pumps and passes them through holdup piping prior to release to the stack. Gland seal offgases and gases from the mechanical vacuum pump, used during each startup and at "hot standby," are routed to the stack via the gland seal holdup line, which is separate from the air ejector holdup line. The gland seal offgas subsystem provides a 1.75 minute holdup time to allow decay of N-16 and O-19. The holdup time is provided by a long, large diameter pipe between the steam packing exhauster and the stack. Operating and design pressure is atmospheric; no explosive mixture is present. No filters or radiation monitors are required in the holdup line. Release rates for the gland seal offgas subsystem are given in Table 9.5-7. A valve between the main condenser and each mechanical vacuum pump is closed by a high radiation signal from the main steam line radiation detectors to isolate the mechanical vacuum pump from the main condenser. In addition, the mechanical vacuum pumps are automatically stopped by the same signal. 9.5.5 Safety Evaluation The activated carbon adsorbers operate at essentially room temperature so that, upon system shutdown, radioactive gases in the adsorbers will be subject to the same holdup time as during normal operation, even in the presence of continued air flow. The radioactive materials are thus not subject to an accidental release evaluation. The activated carbon adsorbers are designed to limit the temperature of the activated carbon to well below its ignition temperature, thus precluding overheating or fire and consequent escape of radioactive materials. The adsorbers are located in a shielded room, maintained at a constant temperature by an air conditioning system which removes the decay heat generated in the adsorbers. Failure of the air conditioning system will cause an alarm in the control room. In addition, a radiation monitor is provided to monitor the radiation level in the activated carbon bed vault. High radiation will cause an alarm in the control room. The hydrogen concentration of the gases from the air ejector is maintained below the flammable limit by maintaining adequate steam flow for dilution. The pressure of the steam supplied to the first and third stage steam jet air ejectors is monitored. The steam jet air ejector inlet and effluent are automatically isolated on low steam supply pressure. The preheaters are heated with steam, rather than electrically, to eliminate presence of potential ignition sources and to limit the temperature of the

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9.5-7

gases in the event of cessation of gas flow. The recombiner temperatures are monitored and an alarm is actuated to indicate any deterioration of performance. A hydrogen analyzer downstream of the recombiners provides an additional check on recombiner performance. The air ejector offgas system operates at a pressure of about 5 psig or less, so the differential pressure which could cause leakage of radioactive gases is small. To minimize the possibility of leakage of radioactive gases, the system is welded wherever possible, and bellows seal valve stems or equivalent are used wherever possible. Operational control is maintained by the use of radiation monitors to assure that the release rate is within the established limits. Environmental monitoring is used to determine resultant dose rates and to relate these to the release rates as a check on plant performance. Provision is also made for sampling and periodic analysis of the influent and effluent gases for purposes of determining their composition. This information can be used in comparisons and calibration of the monitors and in relating the release-to-environs dose. Table 9.5-4 contains a detailed malfunction analysis indicating consequences of failure of various components of the system and design precautions taken to prevent such failures. The air ejector offgas holdup pipe and the steam packing exhauster holdup pipe meet the requirements of USAS B31.1.0, Section 1 and Case N-12, with the exception that the stresses recommended by NACA-TN-3935 are acceptable as a minimum requirement. All piping and equipment added in connection with the activated carbon system are designed in accordance with the ASME Boiler and Pressure Vessel Code, Section III, Class 3, Nuclear Power Plant Components. The inadvertent release of significant quantities of gaseous and particulate radioactive material is prevented by the combination of the air ejector offgas, six-hour holdup, activated-carbon adsorber, and the automatic isolation of the air ejector offgas subsystem from the stack by high-high-high radiation signals from the air ejector offgas post treatment monitors, or manual isolation based on a pre-treatment radiation monitor high-high alarm. In addition, the mechanical vacuum pumps are stopped and isolated from the condenser by a main steamline high radiation signal indicating gross fuel failure. It is therefore concluded that the safety design basis is met. Table 9.5-5 is a list of the isotopic inventories of the equipment in the modified offgas system. This analysis was based upon the modified gas mixture source terms, holdup times calculated for the equipment, and postulated removal and holdup mechanism.

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9.5-8

The bases for the calculations are given below: 1. 18.5 SCFM air in-leakage, 2. 100,000 μCi/sec NG modified gas mixture (λ4) after 30 minute delay, 3. 6 activated carbon beds - 18 tons of activated carbon, and 4. Retention of daughter products by equipment:

a. Offgas condenser - 100 percent but washed-out,

b. Water separator - 100 percent but washed-out,

c. Holdup pipe - 60 percent but washed-out,

d. Prefilter - 100 percent,

e. Carbon beds - 100 percent, and f. Post filter - 100 percent.

The assumptions generally give conservative daughter inventories or do not have a significant effect on daughter inventories. For example, 100 percent washout in the offgas condenser removes daughter products from the prefilter; but this represents less than one minute of delay compared to 360 minutes of delay experienced in the holdup pipe. Washout of 60 percent in the holdup pipe is conservative compared to 60 percent to 99 percent that has been measured in the EVESR facility at Vallecitos. At Dresden 2, iodine activities were measured in the reactor water, condensate pump discharge, and offgas after being discharged from the 30 minute holdup pipe. An iodine reduction factor from the condensate (primary steam) to discharge of the holdup pipe was calculated. The following basis was used to calculate the iodine inventories shown in Table 9.5-5. 1. Standard plant iodine source terms at 100,000 μCi/sec NG at 30 minute decay

for the reactor water; 2. Steam separation of 2 percent (reduction by a factor of 50 for iodine from the

reactor water to the steam); and

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9.5-9

3. Iodine reduction factor for primary steam to discharge of the holdup pipe as measured at Dresden 2.

Because of erratic removal of iodine by HEPA filters, the iodine inventory on the prefilter assumed 100 percent removal, while the inventory on the activated carbon assumed no removal by the prefilter. The design approach for the system is to prevent/minimize an explosion, so that this is not considered as a failure mode. The following equipment failures are postulated: 1. Activated Carbon Beds (4'-diameter by 21-1/2'-high, dished heads, and 350

psig design pressure). The activated carbon beds are in vessels contained in a single vault . The vault is normally not accessible during operation because of the activity level; therefore, no failure due to an operator accident is considered.

The only credible failure to these vessels that could result in loss of carbon from the vessels would be failure of the concrete structure surrounding the vessel. A circumferential failure could result from concrete falling on the vessel under one of two conditions:

a. Bending Load - The vessel being supported in the center and loaded on

each end. This could possibly result in a tear around 50 percent of the circumference.

b. Shearing Load - The vessel being supported and loaded near the same

point from above.

In either case, no more than 10 to 15 percent of the carbon would be displaced from the vessel. Iodine is strongly bound to the activated carbon and would not be expected to be removed by exposure to the air. One percent of iodine is a conservative estimate. Moisture leakage from automatic closure valves would also affect the carbon bed performance but this has been considered in Table 9.5-4 and found to be negligible.

Measurements made at KRB indicate that offgas is about 30 percent richer in krypton than air. Therefore, if this carbon is exposed to air, it will eventually attain equilibrium with the noble gases in the air. However, the first few inches of carbon will blanket the underlying carbon from the air. A 10 percent loss of noble gas from a failed vessel is conservative because of the small fraction of carbon exposed to the air.

2. Prefilter (24-inch diameter by 4-feet high, and 350 psig design pressure).

Because of the short length of the vessel, heavy wall thickness due to the

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9.5-10

design pressure, and collapsible nature of the filter media, a failure mechanism cannot be postulated that will result in emission of filter media or daughter products from this vessel.

One percent release is used to illustrate the consequences of loss from this vessel.

3. Holdup pipe. Pipe rupture and depressurization of the pipe is considered. The

pipe will normally operate at less than 16.4 psia and depressurize to 14.4 psia. The possible loss is conservatively taken as 20 percent. The model used assumed plate-out or washout of 60 percent in calculating the holdup pipe inventory.

To provide an estimate of hypothetical radiological doses from equipment failures, assumptions of percentages of the activity contained in the most significant components listed in Table 9.5-5 were assumed to be released to the environment under very stable 1 m/sec meteorological conditions with an effective release height of zero meters. The estimated percentages of activity released, and the resultant estimated radiological exposures based on the above considerations, are presented in Table 9.5-6. In addition, total failure of the nonseismically qualified portions of the system has been assumed and the total site boundary dose calculated. This total dose is included in Table 9.5-6.

4. Activated Carbon Temperature. The activated carbon adsorbers are designed

to limit the temperature of the activated carbon to well below its ignition temperature, thus precluding overheating or fire and consequent escape of radioactive materials. The adsorbers are located in a shielded room, maintained at a constant temperature by an air-conditioning system that removes the decay heat generated in the adsorbers. The maximum centerline temperature of the activated carbon is less than 10°F above room temperature when gas flow is stopped. Failure of the air-conditioning system will cause an alarm in the control room. In any event, the decay heat of 50 Btu/hour is insignificant compared to the thermal mass of the activated carbon vault.

Additions of hydrogen recombiners, downstream of the air ejectors and upstream of the holding pipes, along with charcoal adsorption beds downstream of the holding pipes and upstream of the stack, have led to a lower maximum release limit of 3 x 10-2 Ci/sec annually for three units. The activated carbon vault is controlled at about 77°F during operation of the plant. Failure of the air-conditioning system is alarmed and a redundant chiller is available. During a plant outage when the condenser is not maintained at vacuum, there is no gas flow in the activated carbon and holdup is very high, even if the activated carbon heats up to ambient temperature.

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9.5-11

9.5.6 Inspection and Testing The gaseous waste disposal systems are used on a routine basis and do not require specific testing to assure operability. Calibration and maintenance of monitoring equipment are done on a specific schedule and on indication of malfunction. The particulate filters are tested after installation using a dioctylpthalate (DOP) test or equivalent. During operation, they are periodically tested by laboratory analyses of inlet and outlet Millipore filter samples. Experience with boiling water reactors has shown that the response of the offgas and effluent monitors changes with isotopic content. Isotopic content can change depending on the presence or absence of fuel cladding leaks in the reactor and the nature of the leaks. Conservative setpoints will be calculated using χe - 133 efficiencies. The monitor responses are periodically compared to grab samples to provide timely information of changing plant parameters.

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Table 9.5-1

Sheet 1

ESTIMATED OFFGAS RELEASE RATES PER UNIT Activation Gases (Ci/sec) Isotope Half-Life Evolution Rate Stack Release

N-13 10 min 3.5 X 103 Negligible

N-16 7.4 sec 1.47 X 108 Negligible

0-19 19 sec 0.9 X 106 Negligible Fission Product Gases

Release rates are given in Ci/sec, based on modified (a)

gas mixture Discharge From 30-Min Charcoal

Isotope Half-Life T = O Holdup Adsorbers

Kr-83m 1.86 hr 3.4x103 2.9x103 1.0x101

Kr-85m 4.4 hr 6.1x103 5.6x103 5.2x102 Kr-85(b) 10.74 yr 10-20 10-20 10-20

Kr-87 76 min 2.0x104 1.5x104 3.7x100

Kr-88 2.79 hr 2.0x104 1.8x104 4.1x102

Kr-89 3.18 min 1.3x105 1.8x102

Kr-90 32.3 sec 2.8x105

Kr-91 8.6 sec 3.3x105

Mr-92 1.84 sec 3.3x105

Kr-93 1.29 sec 9.9x104

Kr-94 1.0 sec 2.3x104

Kr-95 0.5 sec 2.1x103

Kr-97 1 sec 1.4x101

Xe-131m 11.96 day 1.5x101 1.5x101 9.8x100

Xe-133m 2.26 day 2.9x102 2.8x102 2.7x101

Xe-133 5.27 day 8.2x103 8.2x103 3.0x103

Xe-135m 15.7 min 2.6x104 6.9x103

Xe-135 9.16 hr 2.2x104 2.2x104

Xe-137 3.82 min 1.5x105 6.7x102

Xe-138 14.2 min 8.9x104 2.1x104

Xe-139 40 sec 2.8x105

Xe-140 13.6 sec 3.0x105

Xe-141 1.72 sec 2.4x105

Xe-142 1.22 sec 7.3x104

Xe-143 0.96 sec 1.2x104

Xe-144 9 sec 5.6x102

Totals 2.5x106 1.0x105 4.0x103 (a) The release rate (R) of each noble gas can be expressed by the simplified form:

Ri = Kgyii

me-it

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Table 9.5-1 (cont'd)

ESTIMATED OFFGAS RELEASE RATES PER UNIT

Sheet 2

The observed experimental data from several operating BWRs including KRB and Dresden 2 have shown a variation in individual noble gas isotopes with respect to each other that can be expressed in terms of variation in m, the exponent of the decay constant term (). The average measured value of m was 0.4 with a standard

deviation of 0.07. With the Ri @ t=30 min set at 100,000 Ci/sec, the value of K

g is 2.6 X 10

7. Y

i is the

fission yield for isotope i. Decay times (t) of 15.7 hrs and 181 hrs were used for Kr and Xe, respectively, in arriving at the values in the column headed "Discharge from Charcoal Adsorbers." These times include a 6 hr delay in the holdup pipe.

(b) Estimated from experimental observations.

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Table 9.5-2

PROCESS INSTRUMENT ALARMS

Main Control Room Functional Parameter Indicated Recorded

Preheater discharge temperature - low X

Recombiner catalyst temperature - high/low X X

Offgas condenser drain well (dual) level - high/low X

Offgas condenser gas discharge temperature - high X

H2 analyzer (condenser discharged) (dual) - high X X

Gas flow (offgas condenser discharge) - high/low X X

Cooler - condenser discharge temperature - high/low X X

Glycol solution temperature - high/low X X

Gas reheater discharge humidity high X* X

Prefilter P - high X

Carbon bed temperature - high X X

Carbon vault temperature - high/low X X

Post filter P - high X

Instrumentation elements:

Temperature - thermocouple

Level - differential pressure diaphram

Hydrogen - thermal conductivity

Gas flow - flow orifice and thermal dispersion

Differential pressure - differential pressure diaphragm

*Disconnected for Unit 2.

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TABLE 9.5-3 OFFGAS SYSTEM MAJOR EQUIPMENT ITEMS Sheet 1 Offgas Preheaters Two Required. Duty: 5.8 X 105 Btu/hr each Construction: Stainless steel tubes and carbon steel shell. 300 ft2 (minimum). 350 psig shell design pressure, 1,000 psig tube design pressure. 400F shell design temperature, 575F tube design temperature. Catalytic Recombiners Two Required. Duty: 2.2 X 106 Btu/hr each Construction: Stainless steel cartridge, low alloy steel shell. Catalyst cartridge containing a precious metal catalyst on nichrome strips. Catalyst cartridge to be replaceable without removing vessel. 350 psig design pressure. 900F design temperature. Offgas Condenser One Required. Duty: 1.25 X 107 Btu/hr Construction: Low alloy steel shell. Stainless steel tubes. 600 ft2 (minimum) surface area. 350 psig shell design pressure. 250 psig tube design pressure. 900F shell design temperature. 150F tube design temperature. Water Separator One Required. Construction: Carbon steel shell, stainless steel wire mesh. 350 psig design pressure. 250F design temperature. Cooler Condenser Duty: 1.1 X 105 Btu/hr Construction: Stainless steel shell. Stainless steel tubes. 100 ft2 (minimum) surface area. 100 psig tube design pressure. 350 psig shell design pressure. 150F tube design temperature. 150F shell design temperature. Moisture Separators (Downstream of Cooler-Condenser) Two Required. Construction: Carbon steel shell, stainless steel wire mesh. 350 psig design pressure. 150F design temperature. Gas Reheater One Required. Duty: 2.8 kW (minimum) Construction: Carbon steel shell. 14 ft2 surface area. 350 psig process pipe design pressure. 150F design temperature.

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TABLE 9.5-3 (Cont'd) OFFGAS SYSTEM MAJOR EQUIPMENT ITEMS Sheet 2 Glycol Storage Tank One Required. 7.5 feet inside diameter, 9.5 feet high. Construction: Carbon steel. 3,000 gal. Water-filled hydrostatic design pressure. 0F design temperature. Code, API 650. Glycol Solution Refrigerators and Motor Drives Two Required.

Duty: 9x104 Btu/hr each, single stage vapor compressor, 20 hp. Construction: Conventional refrigerator units w/chilling self-contained and pump exchangers, glycol exit solution temperature 35F. Glycol Pumps and Motor Drives Two Required. Duty: 65 gal./min. 5 hp Construction: Cast iron, 3-in. connections, 85 ft TDH, 0F design temperature. Glycol Tank Agitator and Motor Drive One Required Duty: 2 hp Eliminate thermal gradients in tank. Prefilters and After Filters Two Required of each type. Duty: 160 cfm rating at 1 in. H20P (clean) Construction: Carbon steel shell. High efficiency moisture resistant filter element. Flanged shell. 350 psig design pressure. 150F design temperature. Carbon Bed Adsorbers Quantity: 6 Beds Construction: Carbon steel, 4 ft o.d. (5/8 inch wall) x 21 ft 6-1/8 inch length vessels each with a 16-ft packed section containing

3 tons of 8-16 mesh carbon (~200 ft3 of activated carbon) Columbia G or equivalent. Design pressure 350 psig. Design temperature 150F. A flow distributor will be placed in the inlet of each column. Channeling is precluded by use of a vertical bed and a large bed to particle diameter ratio (~500). Underhill1 has stated that channeling or wall effects may reduce efficiency of the holdup bed if this ratio is not greater than 12.

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Table 9.5-4

EQUIPMENT MALFUNCTION ANALYSIS

Sheet 1 Equipment Item Malfunction Consequences Design Precautions Preheaters Steam leak Would further dilute process Spare preheater.

offgas Steam consumption would increase.

Low pressure Recombiner performance would Low temperature alarms on steam supply fall off at low power level, preheater exist and recom-

and hydrogen content of recombiner inlet. Recombiner biner gas discharge would H2 analyzer. increase, eventually to a combustible mixture.

Recombiners Catalyst Temperature profile changes Temperature probes in

gradually through catalyst. Eventually recombiner and H2 deactivates excess H2 would be detected analyzer provided.

by H2 analyzer or by gas Spare recombiner. flowmeter. Eventually the gas could become combustible.

Catalyst H2 conversion falls off Condensate drains, gets wet at and H2 is detected by down- temperature probes in start stream analyzers. Eventually recombiner. Air bleed

the gas could become system at startup. combustible. Recombiner thermal

blanket, spare recombiner and heater. (For Units 2 & 3, low condenser vacuum scram has been removed.) Hydrogen analyzer.

Recombiner Cooling The coolant (reactor conden- None. Condenser water sate) would leak to the

leak process gas (shell) side. This would be detected if drain-well liquid level increases. Moderate leakage would be of no concern from a process standpoint. (The process condensate drains to the hotwell.)

Drain well Liquid level If both drain valves fail to Two separate drain systems

instruments open, water will build up in are provided each with high fail the condenser and pressure and low level alarms.

drop will increase.

The high P, if not detected by instrumentation, could cause pressure buildup in the main condenser and eventually initiate a reactor scram. If a drain valve fails to close, gas will recycle to the main condenser, increase the load on the SJAE, and cause back pressure on the main condenser, eventually causing a reactor scram.

BFN-26

Table 9.5-4 (Continued)


Sheet 2 Equipment Item Malfunction Consequences Design Precautions Water Corrosion of Higher quantity of water Stainless steel separator wire mesh collected in holdup line and mesh specified.

element routed to radwaste. Six-hour Corrosion of Leakage to soil of gaseous Outside of pipe dipped and holdup line line and liquid fission products wrapped. Dehumidification coil provided. Cooler- Corrosion of Glycol-water solution would Stainless-steel-finned condensers finned tube leak into process (shell) tubes specified. The

side and be discharged to inventory of glycol-water clean radwaste. If not can be observed in tank. detected at radwaste, the glycol solution would discharge to the reactor condensate system.

Icing up of Shell side of cooler could Design glycol-H2O finned tube plug up with ice, gradually solution temperature of 33

building up pressure drop. to 50F. Redundant If this happens, the spare temperature indication unit could be activated. and alarm systems. Complete blockage of both units would increase P and lead to a reactor scram.

Moisture Corrosion of Increased moisture would be Stainless steel mesh speci- separators wire mesh retained in process gas fied. Relative humidity

element routed to charcoal1 adsor- instrumentation provided. bers. Over a long period, the charcoal1 performance would deteriorate as a result of moisture pickup.

Gas reheater Heater Cool gas, saturated with Dual heating circuits

element water vapor would enter the provided. Moisture failure charcoal adsorbers. recorder and high moisture

Eventually, charcoal1 per- alarm. (Alarm for formance will deteriorate as Unit 2 is disconnected.) charcoal1 moisture content increases, and plant emissions will increase.

Prefilters Hole in More radioactivity would P instrumentation

filter media deposit on the charcoal1 in provided. Spare unit the first adsorber vessel of provided. the train. This would increase the radiation level in the charcoal1 vault and make maintenance more difficult.

1Charcoal 1Charcoal 1Charcoal performance will Highly instrumented, adsorbers gets wet deteriorate gradually as mechanically simple gas

charcoal gets wet. Holdup dehumidification system times for krypton and xenon with redundant equipment. will decrease, and plant emissions will increase.

BFN-28

Table 9.5-4 (Continued)


Sheet 3 Equipment Item Malfunction Consequences Design Precautions Vault air Mechanical If ambient temperature exceeds Spare refrigerator unit conditioning failure approximately 80F, increased provided. units emission could occur.

If ambient temperature is Vault temperature alarms below approximately 60F, provided.

charcoal1 could pick up additional moisture.

After Hole in Probably of no real conse- P instrumentation filters filter media quence. The charcoal1 media provided. Spare unit

itself should be a good filter provided. at the low air velocity.

Glycol Mechanical If spare unit fails to oper- Spare refrigerator refrigera- failure ate, the glycol solution Glycol solution machines temperature will rise and the temperature alarms

dehumidification system provided. performance will deteriorate. This will cause gradual buildup

of moisture on the charcoal,1 with increased plant emissions.

Steam jet Low flow of When the hydrogen and oxygen The normal steam pressure to the air ejectors motive high concentrations exceed 4 and 5 ejectors is 200 psig. If the steam

pressure vol %, respectively, the pro- supply pressure to the operating steam cess gas becomes combustible. air ejector drops to 145 psig, the steam

supply to the SJAE is shut off. If the steam supply pressure for the standby unit is also less than 145 psig, the steam supply to the standby SJAE is shut off. If neither SJAE is in operation, condenser back pressure will continue to increase. By ensuring adequate steam supply to the SJAEs, the 02 concentration cannot get as high as 5 percent.

Inadequate steam flow will Steam flow to be held at cause overheating and deter- constant maximum flow ioration the catalyst. regardless of plant power

level.

Wear of Increased steam flow to steam supply recombiner. This could nozzle of reduce degree of recombina- ejector tion at low power levels.

1

The term "activated carbon" would be more appropriate than the term "charcoal."

BFN-26

TABLE 9.5-5 ISOTOPIC INVENTORY-CHARCOAL OFFGAS SYSTEM (c) Sheet 1

Offgas Cooler Charcoal First Recom- Con- Water Holdup Con- Moisture Vessel Charcoal

Component Preheater biner denser Separator Pipe denser Separator Reheater Prefilter Train Vessel Afterfilter

Kr-9.7 Hr Kr-1.6 Hrs. Residence Time 0.8 Sec 0.94 Sec 50 Sec 5.1 Sec 6 Hr 178 Sec 6.5 Sec 14.5 Sec 43.5 Sec Xe-7.3 Day Xe-1.2 Day 43.5 Sec Operating Time 0 0 0 0 0 0 0 0 1 Yr 10 Yr 10 Yr 1 Yr Solid Daughter Capture 0 0 100% 100% 60% 0 0 0 100% 100% 100% 100% Solid Daughter Washout - - 100% 100% 100% - - - 0 0 0 0 Isotope Kr-83M 2.77+3 3.26+3 1.73+5 1.76+4 2.98+7 6.57+4 2.38+3 5.30+3 1.58+4 3.43+6 1.59+6 4.33+2 Kr-85M 4.92+3 5.78+3 3.07+5 3.13+4 8.57+7 4.22+5 154+4 3.42+4 1.03+5 4.21+7 1.21+7 2.22+4 Ke-85 1.90+1 2.24+1 1.19+3 1.21+2 5.14+5 4.26+3 1.56+2 3.48+2 1.03+3 8.38+5 1.39+5 1.03+3 Kr-87 1.57+4 1.85+4 9.79+5 9.95+4 1.23+8 1.28+5 4.62+3 1.03+4 3.07+4 4.61+6 2.72+6 1.52+2 Rb-87 0 0 0 0 0 0 0 0 0 6.38-4 3.76-4 0 Kr-88 1.61+4 1.90+4 1.01+6 1.02+5 2.26+8 8.01+5 2.90+4 6.48+4 1.94+5 5.87+7 2.13+7 1.74+4 Rb-88 4.21+0 1.57+1 1.74+4 1.70+2 1.31+8 3.85+5 1.49+4 3.36+4 3.75+6 5.87+7 2.13+7 1.74+4 Kr-89 9.67+4 1.13+5 5.50+6 5.07+5 2.71+7 0 0 0 0 0 0 0 Rb-89 2.94+1 1.09+2 1.14+5 9.84+2 1.63+7 1.29-1 4.38-3 9.70-3 8.76-1 0 0 0 Sr-89 1.27-6 1.15-5 3.17-1 2.65-4 5.14+4 3.04+2 1.11+1 2.48+1 1.07+7 0 0 0 Y-89M 0 0 1.23-1 1.44-5 5.13+4 3.04+2 1.11+1 2.48+1 1.07+7 0 0 0 Kr-90 1.67+5 1.93+5 6.23+6 3.35+5 2.89+6 0 0 0 0 0 0 0 Rb-90 2.87+2 1.06+3 7.95+5 3.70+3 1.73+6 0 0 0 0 0 0 0 Sr-90 0 0 1.15-2 4.83-6 2.81+1 1.56-1 5.71-3 1.27-2 2.74+4 0 0 0 Y-90 0 0 0 0 8.83-1 9.77-3 3.58-4 7.99-4 2.71+4 0 0 0 Kr-91 8.62+4 9.44+4 1.18+6 7.19+3 1.41+4 0 0 0 0 0 0 0 Rb-91 4.17+2 1.50+3 5.10+5 2.30+2 8.49+3 0 0 0 0 0 0 0 Sr-91 2.23-3 2.02-2 2.36+2 8.09-3 2.95+3 1.30+1 4.75-1 1.06+0 3.67+3 0 0 0 Y-91M 0 1.29-6 8.30-1 2.39-6 2.43+3 1.41+1 5.15-1 1.15+0 4.02+3 0 0 0 Y-91 0 0 1.32-6 0 3.18+0 3.94-2 1.44-3 3.23-3 5.58+3 0 0 0 Kr-92 1.41+3 1.20+3 2.81+3 1.58+1 2.70+0 0 0 0 0 0 0 0 Rb-92 8.82+1 2.67+2 5.06+3 2.11+6 1.62+0 0 0 0 0 0 0 0 Sr-92 1.74-3 1.42-2 1.65+1 4.36+2 1.28+0 2.92-3 1.06-4 2.36-4 2.27-1 0 0 0 Y-92 0 0 1.97-2 4.29-2 6.30-1 4.17-3 1.52-4 3.39-4 6.56-1 0 0 0 Kr-93 4.53+1 3.35+1 5.10+1 0 0 0 0 0 0 0 0 0

BFN-26

TABLE 9.5-5 (Cont'd) ISOTOPIC INVENTORY-CHARCOAL OFFGAS SYSTEM (c) Sheet 2


Component Preheater biner denser Separator Pipe denser Separator Reheater Prefilter Train Vessel Afterfilter Rb-93 2.22+0 6.47+0 1.21+2 0 0 0 0 0 0 0 0 0 Sr-93 9.51-4 7.53-3 8.01+0 0 0 0 0 0 0 0 0 0 Y-93 0 0 3.30-3 0 0 0 0 0 0 0 0 0 Zr-93 0 0 0 0 0 0 0 0 0 0 0 0 Nb-93M 0 0 0 0 0 0 0 0 0 0 0 0 Kr-94 1.20+0 7.77-1 8.46-1 0 0 0 0 0 0 0 0 0 Rb-94 1.27-1 3.30-1 2.37+0 0 0 0 0 0 0 0 0 0 Sr-92 3.22-4 2.37-3 9.57-1 0 0 0 0 0 0 0 0 0 Y-94 0 0 1.35-2 0 0 0 0 0 0 0 0 0 Kr-95 7.16-6 2.56-6 0 0 0 0 0 0 0 0 0 0 Rb-95 3.99-6 4.24-6 2.44-6 0 0 0 0 0 0 0 0 0 Sr-95 0 0 1.78-6 0 0 0 0 0 0 0 0 0 Y-95 0 0 0 0 0 0 0 0 0 0 0 0 Zr-95 0 0 0 0 0 0 0 0 0 0 0 0 Nb-95M 0 0 0 0 0 0 0 0 0 0 0 0 Kr-97 7.22-4 4.66-4 5.08-4 0 0 0 0 0 0 0 0 0 Rb-97 5.68-4 5.37-4 5.90-4 0 0 0 0 0 0 0 0 0 Sr-97 2.40-4 5.57-4 8.99-4 0 0 0 0 0 0 0 0 0 Y-97 3.44-5 2.29-4 1.43-3 0 0 0 0 0 0 0 0 0 Zr-97 0 0 0 0 0 0 0 0 0 0 0 0 Nb-97 0 0 0 0 0 0 0 0 0 0 0 0 Xe-131M 1.21+1 1.42+1 7.56+2 7.72+1 3.24+5 2.65+3 9.69+1 2.16+2 6.49+2 7.66+6 1.51+6 4.25+2 Xe-133M 2.22+2 2.61+2 1.39+4 1.41+3 5.76+6 4.57+4 1.67+3 3.72+3 1.11+4 6.45+7 2.25+7 1.19+3 Xe-133 6.60+3 7.76+3 4.13+5 4.21+4 1.75+8 1.42+6 5.19+4 1.16+5 3.47+5 3.26+9 7.78+8 1.36+5 Xe-135M 2.09+4 2.45+4 1.28+6 1.28+5 3.40+7 5.20-1 1.77-2 3.93-2 1.15-1 3.54+0 3.54+0 0 Xe-135 1.78+4 2.09+4 1.11+6 1.13+5 3.97+8 2.58+6 9.43+4 2.22+5 6.45+5 7.06+8 6.28+8 1.16+0 Cs-135 0 0 0 0 2.63-2 2.64-4 9.73-6 2.17-5 4.74+1 2.13+3 1.89+3 0 Xe-137 1.18+5 1.39+5 6.84+6 6.42+5 4.14+7 0 0 0 0 0 0 0 Cs-137 3.45-5 1.29-4 1.37-1 1.19-3 3.84+2 2.14+0 7.83-2 1.75-1 3.75+5 0 0 0 Ba-137M 0 0 1.02-2 9.15-6 3.80+2 2.14+0 7.83-2 1.75-1 3.75+5 0 0 0

BFN-26



Component Preheater biner denser Separator Pipe denser Separator Reheater Prefilter Train Vessel Afterfilter Xe-138 7.11+4 8.34+4 4.35+6 4.34+5 1.04+8 3.32-1 1.12-2 2.49-2 7.29-2 2.03+0 2.03+0 0 Cs-138 1.02+1 3.81+1 4.18+4 3.97+2 6.26+7 1.98+3 7.01+1 1.56+2 2.98+4 2.03+0 2.03+0 0 Xe-139 1.76+5 2.03+5 7.18+6 4.41+5 4.78+6 0 0 0 0 0 0 0 Cs-139 8.73+1 3.23+2 2.72+5 1.41+3 2.87+6 0 0 0 0 0 0 0 Ba-139 3.20-3 2.99-2 7.01+2 3.36-1 2.71+6 2.64+3 9.50+1 2.12+2 1.05+5 0 0 0 Xe-140 1.21+5 1.36+5 2.63+6 5.50+4 1.94+5 0 0 0 0 0 0 0 Cs-140 5.28+2 1.92+3 9.11+5 1.56+3 1.16+5 0 0 0 0 0 0 0 Ba-140 8.87-5 8.11-4 1.23+1 1.71-3 1.56+3 8.53+0 3.11-1 6.95-1 7.64+4 0 0 0 La-140 0 0 8.69-4 0 7.76+1 8.43-1 3.09-2 6.90-2 7.74+4 0 0 0 Xe-141 7.19+2 5.96+2 1.29+3 0 0 0 0 0 0 0 0 0 Cs-141 8.45+0 2.68+1 1.92+3 0 0 0 0 0 0 0 0 0 Ba-141 1.46-3 1.22-2 3.68+1 0 0 0 0 0 0 0 0 0 La-141 0 0 3.33-2 0 0 0 0 0 0 0 0 0 Ce-141 0 0 0 0 0 0 0 0 0 0 0 0 Xe-142 2.20+1 1.58+1 2.24+1 0 0 0 0 0 0 0 0 0 Cs-142 3.46+0 8.81+0 4.79+1 0 0 0 0 0 0 0 0 0 Ba-142 1.06-3 7.76-3 3.01+0 0 0 0 0 0 0 0 0 0 La-142 0 0 9.02-3 0 0 0 0 0 0 0 0 0 Xe-143 4.17-1 2.63-1 2.71-1 0 0 0 0 0 0 0 0 0 Cs-143 6.68-2 1.61-1 7.23-1 0 0 0 0 0 0 0 0 0 Ba-143 1.09-3 7.60-3 8.85-1 0 0 0 0 0 0 0 0 0 La-143 0 2.40-6 2.45-2 0 0 0 0 0 0 0 0 0 Ce-143 0 0 2.73-6 0 0 0 0 0 0 0 0 0 Pr-143 0 0 0 0 0 0 0 0 0 0 0 0 Xe-144 1.55+2 1.70+2 2.22+3 1.57+1 3.26+1 0 0 0 0 0 0 0 Cs-144 3.35+1 9.64+1 2.41+3 1.14+1 1.95+1 0 0 0 0 0 0 0 Ba-144 5.38-1 4.15+0 2.18+3 1.31+0 1.95+1 0 0 0 0 0 0 0 La-144 1.87-3 3.46-2 7.74+2 3.24-2 1.95+1 0 0 0 0 0 0 0 Ce-144 0 0 3.86-4 0 1.18-2 0 0 0 0 0 0 0 Pr-144 0 0 3.20-6 0 1.10-2 0 0 0 0 0 0 0

BFN-26



Component Preheater bier denser Separator Pipe denser Separator Reheater Prefilter Train Vessel Afterfilter N-13 6.73-3 7.90+3 4.08+5 4.03+4 6.86+6 2.07-5 0 1.50-6 4.34-6 8.39-5 0 0 N-16 4.72-7 5.09-7 5.30+8 1.62+6 2.52+6 0 0 0 0 0 0 0 N-17 4.43+3 4.50+3 2.66+4 3.57+0 2.66 0 0 0 0 0 0 0 O-19 7.12+5 8.18+5 2.41+7 1.13+6 8.01+6 0 0 0 0 0 0 0 Iodine - - - - - - - - 8.70+4 8.70+4 8.70+4 0 TOTAL 4.88+7 5.28+7 5.96+8 7.87+6 1.49+9 5.87+6 2.15+5 4.91+5 2.77+7 4.21+9 1.48+9 1.96+5

BFN-26

TABLE 9.5-5 (Cont.) ISOTOPIC INVENTORY-CHARCOAL OFFGAS SYSTEM (c) Sheet 5

Gas Solid Gas Gas Component Kr + Xe Daughters Kr Xe Preheater 9.24 + 5 1.4 + 3 3.91 + 5 5.33 + 5 Recombiner 1.06 + 6 1. + 4 4.48 + 5 6.1 + 5 Offgas Condenser 3.92 + 7 2.69 + 6 1.54 + 7 2.38 + 7 Water Separator 2.96 + 6 2.12 + 6 1.10 + 6 1.86 + 6 Holdup Pipe 1.25 + 9 2.4 + 8 4.95 + 8 7.6 + 8 Cooler Codenser 5.40 + 6 4.7 + 5 1.42 + 6 3.98 + 6 Moisture Separator 1.97 + 5 1.8 + 4 5.16 + 4 1.45 + 5 Gas Reheater 4.39 + 5 5.2 + 4 1.15 + 5 3.24 + 5 Prefilter 1.31 + 6 6.4 + 6 3.44 + 5 9.7 + 5 Carbon Bed Train 4.15 + 9 5.87 + 7 1.10 + 8 4.04 + 9 First Carbon Bed 1.46 + 9 2.13 + 7 3.78 + 7 1.42 + 9 Afterfilter 1.78 + 5 1.74 + 4 4.11 + 4 1.37 + 5

BFN-26

TABLE 9.5-6 RADIOLOGICAL EXPOSURES - MODIFIED OFFGAS SYSTEM COMPONENT FAILURE

Resultant Component Pri. Act. % Exposure Failed Released Released at 1400M 1st C. Bed Iodine 1% 5.6 mr 6 C. Beds Noble Gas 10% 0.6 mr Prefilter Particulate 1% 2.6 mr Hold-up Pipe Particulate 20% 10.2 mr Total System All See above 20.2 mr* *There is a 1.2 mr contribution from failure of all other components listed in Table 9.5-5.

BFN-26

Table 9.5-7 EFFLUENT - GLAND SEAL OFFGAS SUBSYSTEM*

Release Rate to Environment Isotope c/sec

Kr-83m 3.4 x 100 Kr-85m 5.7 x 100

Kr-85 8.3 x 10-3 Kr-87 2.0 x 101

Kr-88 1.9 x 101

Kr-89 1.3 x 102

Kr-90 5.4 x 101

Kr-91 4.3 x 10-1

Xe-131m 1.3 x 10-2

Xe-133m 2.1 x 10-2

Xe-133 5.4 x 100

Xe-135m 2.9 x 101

Xe-135 1.9 x 101

Xe-137 1.6 x 102

Xe-138 1.0 x 102

Xe-139 8.0 x 101

Xe-140 2.8 x 100

*Table taken from response to AEC Question 9.4, dated March 25, 1971.

~ ............

,.w. ......... -., ....... , .......... _, ...... , . ...... ,._ .. , ... _..,_ .. ,,. .............. ,."""' .:=11.-IK ..... :Ul __ ml__,_ __ ,,_IMIT I l.(Ilm:.IDIIIEIKIMIP ___ ME .. IM, .. ........ ,. ,._,.!asmill . ., __ , __ , .... __ , ....... _

,;N.""'""11111•"":;"'~!~""'

.. ~"1: .........• ,-............. ,.,.,

~ m a 7 6 5 3

AMENDMENT 27

BROWNS FERRY NUCLEAR PLANT f INAL SAFETY ANALYSIS REPORT

OFFGAS SYSTEM now DIAGRAM

FIGURE 9.5-1 SH 1

H

G

F

E

D

C

B

A

£ZOii t-l083tt-Z' " ti

8 7 5

' ~+-I------- !-iir'--------1

· ii 1~ ·,

' I ,:i;.w.,~ .... .,,..,11·1D.EoaL1m..,

Km~IIIT ... ALLl..,._ml..._,_11!_,llll!ll,.IT">"

AMENDMENT 27 TURBINE BUILDING UNIT2


H

G

F

E

D

C

8

OFFGAS SYSTEM A FLOW DIAGRAM

FIGURE 9.5-1 SH 2

3

IZDII Z-60113Lt-£ " LI

LJ

~ m AMENDMENT 27 TURBINEBLDC,YARD.t.STACI< UNIT3


OFFGAS SYSTEM FLOW DIAGRAM

FIGURE 9.5-1 SH J

H

B

A

I"'" "

'

IEDII t-1093Lt-l N Lt

8 7 5

ff'

:: ;L I ...... _, .. 1.,it/1", ..... .,_

:.==.::!.:"'A ·~;;·::i ....... ··-~.lililiMl:llllll"""' ,. :~=- Rl.'..t.Fi ......... ,,, ....... _

~ - 3

AMENDMENT 26


H

G

F

E

D

C

B

OFF GAS SYSTEM A FLOW DIAGRAM

FIGURE 9.5-1 SH 5

F

I ' -

E

C

AMENDMENT mi·:''""'"' 27

5 3

3

AMENDMENT 26 POl'ERHOUSE UNITJ

C

8

BROWNS FERRY NUCLEAR PLANT RT FINAL SAFETY ANALYSIS REPO ~~::.::..:....:::.::.::....: __ IA

OFFGAS SYSTEM - FLOW DIAGRAM

FIGURE 9. 5-2

8 7 6 5 3

AMENDMENT 27 OFF GAS TREATMENT BUILDING UNIT1


OFF GAS SYSTEl.t FLOW DIAGRAM

FIGURE 9. 5-4

D

C

8

A

radioactive waste control systems flood or design basis … · 25-03-1971 · 9.5-3 offgas system...

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