ML16257A071
| ML16257A071 | |
| Person / Time | |
|---|---|
| Site: | Waterford  |
| Issue date: | 08/25/2016 |
| From: | Entergy Operations |
| To: | Office of Nuclear Reactor Regulation |
| Shared Package | |
| ML16256A115 | List:
|
| References | |
| W3F1-2016-0053 | |
| Download: ML16257A071 (37) | |
Text
WSES-FSAR-UNIT-3 11.2-1 Revision 308 (11/14) 11.2 LIQUID WASTE MANAGEMENT SYSTEM 11.2.1 DESIGN BASES Radioactive liquid wastes which are discharged from the plant are first processed by the Waste Management System (WMS) or the Boron Management System (BMS). The Chemical and Volume Control System (CVCS), Fuel Pool System (FPS), and Steam Generator Blowdown System (SGBS), all process potentially radioactive liquids in the confines of the plant in preparation for reuse. The contents of turbine building sumps and detergent wastes will be routinely discharged unprocessed due to their very small potential for radioactive contamination.
(EC-47424 R308)
The principal design objective of the overall system is to protect plant personnel, the general public, and the environment by ensuring that all releases of radioactive materials, both in plant and to the environment, are as low as reasonably achievable (ALARA) and within the requirements of 10CFR20 and Appendix I to 10CFR50. The liquid radioactive waste system conforms to Regulatory Guide 1.143 as described in FSAR Section 1.8.1.143. The numerical design objectives for the BMS and WMS are:
(EC-47424 R308) a)
The calculated annual total quantity of all radioactive materials in liquid effluents during normal operation including anticipated operational occurrences should not result in a dose or dose commitment from liquid effluents for any individual in an unrestricted area from all pathways of exposure of more than three millirem to the total body, or 10 millirem to any organ.
b)
The concentrations of radioactive materials in liquid effluents released during operation with one percent failed fuel to an unrestricted area should not exceed ten times the effluent concentration limits in 10CFR20 Appendix B, Table 2, Column 2.
11.2.1.1 Chemical And Volume Control System (CVCS)
The basic CVCS operations, process flows, and evolutions are described in Subsection 9.3.4.
Radiological data for shielding design is contained in Subsection 12.2.1. The decontamination factors for CVCS equipment are provided in Table 11.1-1.
11.2.1.2 Fuel Pool System (FPS)
Basic operations of the FPS are discussed in Subsection 9.1.3. Radiological data for shielding design are provided in Subsection 12.2.1. The decontamination factors for FPS equipment are provided in Table 11.2-8.
11.2.1.3 Steam Generator Blowdown System (SGBS)
Basic operations of the SGBS are discussed in Subsection 10.4.8. Radiological data for shielding design is contained in Subsection 12.2.1.
WSES-FSAR-UNIT-3 11.2-2 Revision 15 (03/07) 11.2.1.4 Turbine Building Sump
(DRN 03-2065, R14)
The Turbine Building Floor drains will collect leakage at a rate of approximately five gpm at main steam activity (see Table 11.1-20 for steam generator liquid activity). Since the activity will be extremely low, it will be routinely discharged unprocessed after monitoring. However, if monitoring reveals significant levels of activity the sump water will be routed to the Waste Management System.
(DRN 03-2065, R14) 11.2.1.5 Waste Management System (WMS) and Boron Management System (BMS)
(DRN 00-1045, R11-A; 01-1248, R11-B)
The BMS and the liquid subsystem of the WMS are designed with sufficient capacity, redundancy, and flexibility to meet ten times the effluent concentration limits of 10CFR20 during periods of equipment downtime when operating at design bases fuel leakage of one percent. The BMS has redundancy in its tanks, pumps, filters, and ion exchangers. The WMS has redundancy in its tanks and pumps.
Radioactive liquid waste is normally processed through the piping taps in the LWMS process stream to a demineralizer system. In the case of the WMS, if a filter cartridge must be changed or an ion exchanger bed be replaced, sufficient tankage is provided to hold the waste so that these operations can be performed with no loss of efficiency. The same is true for the BMS with the added advantage of redundant equipment.
(DRN 00-1045, R11-A; 01-1248, R11-B)
The WMS and BMS are located in the seismic Category I Reactor Auxiliary Building.
Tanks outside of containment are provided with level indication and alarms for high level conditions. The level alarms will alert operators when tanks are nearly full and transfer flow from a filled tank to alternate tanks may proceed. For cubicles which contain tanks with significant radioactivity and thus require shielding, the floors in these cubicles will be pitched to floor drains located at low points to facilitate floor drainage.
Collection tanks and tanks which receive processed waste are generally provided in pairs. The pairing of tanks allows one tank to be in the fill mode while the other tank is in the sampling, recirculation, process, or standby mode. Since the schedule of influent waste (See Table 11.2-3 and 11.2-4) can be processed with approximately 10 percent operational time or less using the subsystems described in Subsection 11.2.2, an empty standby tank would normally be available for any filled tank. Thus, switching from one tank to another will normally prevent overflow of tanks.
(DRN 99-2361, R11;06-537, R15)
The monitor tanks (i.e., boric acid condensate tanks, waste condensate tanks, and laundry tanks) can be sampled prior to discharge or prior to transferring to the outside water storage tanks (i.e., the discharge structure). If analysis indicates further processing is required the water will be reprocessed prior to leaving the building. These measures reduce the potential of an uncontrolled release of radioactive material due to an overflowing of outside storage tanks. The outside storage tanks have level detection instrumentation which will annunciate under high level conditions.
(DRN 99-2361, R11;06-537, R15)
WSES-FSAR-UNIT-3 11.2-3 Revision 11 (05/01)
In addition to the outside storage tanks discussed previously, equipment drain tank, spent resin tank, waste storage tank and concentrate storage tank do not have backup tanks. The equipment drain tank does not have an overflow nozzle and hence does not have the potential for overflow to the floor.
Overflow of the concentrate storage tank and spent resin tank will go onto the floor of tanks respective cubicles. Curbing will prevent the spread of liquid from the cubicles. Provisions to prevent entry of the concentrates and resin into the floor drain system are necessary to prevent potential solidification within the drainage system.
The portions of the CVCS, BMS, and WMS which contain significant radioactivity are located in the Reactor Auxiliary Building which is designed to seismic Category I standards. Therefore, uncontrolled release to the environs would not occur as a result of a seismic occurrence. The two release points of the BMS and WMS have radiation monitors which automatically close valves to prevent uncontrolled release of radioactivity. These monitors and their operation are described in Section 11.5.
Equipment in the CVCS, BMS, WMS which requires shielding is placed in separate cubicles. The separate cubicles are provided with appropriate shielding. This allows operation to continue by using alternate process routes while performing maintenance on a particular piece of equipment.
To reduce gaseous radioactive releases to the building atmosphere the following design features have been incorporated into the plant design; (a) venting of high radiation level equipment is provided and collected in the vent gas collection header, (b) tanks are provided with water seals on overflow lines to prevent radioactive gases from escaping, and (c) diaphragm valves are used to provide protection against leakage.
The expected and design inventories of individual radioisotopes (curies) in WMS and BMS equipment and components containing radioactive liquids are provided in Section 12.2. The geometry and layout of equipment, as required for shielding design calculation, are shown on the General Arrangement Drawing in Section 1.2. Tanks receive influent liquid until processing begins or until tank liquid volume reaches a predetermined level. The tank is then isolated from the feed while its contents are processed.
Appropriate control devices and alarms are utilized to alert operators of tank high or low level and to shut off the pump on low level. Overflow lines are provided with loop seals to contain potential radioactive gases.
The WMS and BMS provide means to control the discharge of liquid waste. The operator in the main control room discharges the waste from either the waste condensate, laundry, or boric acid condensate tanks through flow meters recorders and radiation monitors, which automatically alarms and terminates discharge flow on high activity. Other features and procedures used to prevent inadvertent releases to the environment from the systems include strict administrative procedures, operator training, and redundant discharge valves.
The systems are designed for ALARA operation as discussed in Chapter 12.
WSES-FSAR-UNIT-3 11.2-4 Revision 11-A (02/02)
The BMS shall have the capacity to accommodate all liquid wastes generated during the following anticipated operational occurrences:
a)
Base-loaded operation at warranted output up to approximately 97 percent of equilibrium cycle core life
¨(DRN 00-1045) b)
Back-to-back cold shutdowns to five percent subcritical and startups to approximately 85 percent of equilibrium cycle core life.
The BMS also provides sufficient flexibility to allow the plant operator to select the desired balance between holdup for radioactive decay, evaporation, ion exchange, filtration, and dilution. This capability permits removal of radioactivity as soon as feasible in the process in order to concentrate activities into areas where adequate shielding can be provided, thus preventing the build-up of excessive activity in the remainder of the system.
All components within the BMS are designed in accordance with the applicable codes and design parameters at Table 11.2-1. Safety classes and seismic categories are as shown in Table 3.2-1.
Provisions are incorporated on all BMS tanks to contain and collect overflows in the event that any of these tanks are inadvertently over-filled. High level alarms have been provided on all these tanks to minimize the possibility of inadvertent overfilling. In addition, the overflow lines are either interconnected (headered) to other tanks within the BMS or are provided with liquid relief to the containment or radwaste sump. All BMS tanks can also be vented to appropriate gas surge and collection headers for protection against inadvertent gas releases.
All BMS storage and collection tanks were sized to receive maximum expected influent surges with the capability of holding the liquid waste prior to routine batch processing.
The WMS waste tank sizes were selected to receive maximum influent surges to 3600 gpd (see Table 11.2-4 for normally expected liquid waste) with the capability of holding this waste for two days before processing. The process flow rate is 20 gpm, which is sufficient to handle the assumed maximum influent surges. The capacity of the laundry tanks was determined to allow a 2.5 day holdup in a single tank with a maximum influent surge rate of 1400 gpd. The average waste input into the tank (450 gpd) gives an eight day holdup time in a single tank. A single, 38,000 gallon, waste storage tank is provided to supplement the capacity of the two waste tanks.
All components in the liquid portion of the WMS are non-seismic Category I and non-safety related. The design and fabrication codes, seismic category and classification of components meet or exceed the requirements of Regulatory Guides 1.26 (Rev. 1) and 1.29 (Rev. 1). Table 11.2-2 lists the system components and their design parameters.
All tanks in the WMS are closed atmospheric tanks that are vented to the gas collection header, except for the waste storage tank which is vented via duct to the RAB ventilation system.
WSES-FSAR-UNIT-3 11.2-5 Revision 11-B (06/02) 11.2.2 SYSTEM DESCRIPTION 11.2.2.1 Boron Management System (BMS)
The BMS (see Figure 11.2-1) is designed to accept, collect, and process radioactive waste from various plant systems for recycle or disposal.
The major influent to the BMS is from the letdown line in the CVCS and is the result of feed and bleed operations during plant shutdowns, startups, and dilution due to fuel burnup over core life. A schedule of the waste generated for the various plant evolutions is presented in Tables 9.3-11 and 9.3-12. Other sources into the BMS consist of valve and equipment leakoffs, miscellaneous drains and relief valve discharges. The reactor drain tank collects these discharges within the containment, while the equipment drain tank and equipment drain sump accumulates those from outside the containment. Both the reactor drain tank and equipment drain tank are maintained with a nitrogen blanket to prevent the buildup of hydrogen in each tank.
All processing components in the BMS from the discharge of the collection tanks and CVCS, except the holdup tanks and the boric acid condensate tanks, can be bypassed individually or collectively. Chemistry and radiological concerns determine which processing components are lined up in the processing flowpath. Also water from any point in the processing flowpath can be recirculated back to any point in the processing flowpath.
From the discharge of the collection tanks and CVCS, water is sent to the on line holdup tank. (Note that the Flash Tank is no longer used. Temporary equipment could be utilized if required due to significant increases in noble gas activity.) The holdup tanks provide sufficient storage capacity to accumulate discharges until a sufficient volume is available for further processing on a batch basis. The radioactivity of the liquid is significantly reduced during storage by natural decay of the short half-live radionuclides.
During this period, any degasification and radioactive decay can be monitored by liquid sample analysis.
The gas analyzer can be used to monitor the holdup tanks for hydrogen and oxygen content. The holdup tanks also have a continuous nitrogen blanket to eliminate the possibility of a buildup of hydrogen. The holdup tanks can be vented to the plant stack. The holdup tanks have high and low, level and pressure alarms, which annunicate in the control room.
The contents of the holdup tanks are normally sent to the boric acid condensate tanks through some or all of the following process equipment: the preconcentrator filters, the preconcentrator ion exchangers and the boric acid condensate ion exchangers. Prior to recycle or controlled discharge of the treated liquid waste, the fluid is analyzed for acceptability of both chemistry and activity. Recycle capability is provided for water conservation. Controlled discharge is accomplished through an effluent radiation monitor which records the release activity level and automatically terminates discharge on high radiation.
WSES-FSAR-UNIT-3 11.2-6 Revision 15 (03/07)
(DRN 00-1045, R11-A;06-537, R15)
Design data for the major components is given in Table 11.2-1. Flow, temperature, and pressure are given in Table 11.2-9. Process flow modes one and two indicate the system parameters during the normal processing of the reactor drain tank and equipment drain tank contents respectively through the flash tank. Modes three, four and five indicate the system parameters during three possible conditions of processing the CVCS letdown flow which has been diverted from the volume control tank. In the event that the holdup tank contents require additional processing, recirculation mode seven can be employed to cycle the tank's contents through the preconcentrator filter and ion exchanger or back to the flash tank if necessary before mode six is initiated. Mode eight indicates the process data during discharge operations of the boric acid condensate tank contents to the circulating water discharge piping. In the event that the boric acid condensate tank contents require additional processing, mode nine is initiated to recirculate the tank's contents through the boric acid condensate ion exchanger or back to the holdup tanks if necessary.
(DRN 00-1045, R11-A;06-537, R15)
All process components have been used extensively in the nuclear industry to remove radioactive contaminants from liquids. The performance of process units used in the analysis is in agreement with general industry experience. Decontamination factors are presented in Table 11.2-6.
11.2.2.2 Waste Management System The design of the WMS is presented in Figure 11.2-2. Principal flow paths through the system (heavy lines) and the release point (circulating water discharge) are clearly indicated on the figure. The figure indicates all system interconnections.
WSES-FSAR-UNIT-3 11.2-7 Revision 11-B (06/02)
Process data is presented in Table 11.2-10. Input streams into the WMS are identified in Figure 11.2-2 and expected sources, volumes, and activities of waste influent are listed in Table 11.2-4.
Decontamination factors are presented in Table 11.2-7 for WMS process equipment.
11.2.2.2.1 Miscellaneous Waste
(DRN 99-1050; 01-1248)
Miscellaneous non-detergent waste is collected in one of two waste tanks. Additional storage capacity is provided in the waste storage tank. As wastes are collected, they are processed on a batch basis through the portable demineralization system which consists of vessel(s) typically containing various filtration media and/or Ion exchange media. The demineralization system removes suspended solids, dissolved solids, and radioactivity. An ion exchanger is provided in the path from the Portable Demineralizer should further treatment be desired. The effluent is collected in one of two waste condensate tanks for sampling and analysis prior to release to the circulating water discharge. Discharge activity is monitored for radioactivity, as described in Section 11.5.
(DRN 99-1050; 01-1248)
All potential bypass routes in the WMS are indicated in Figure 11.2-2. Because of the redundancy of equipment; it is not expected that equipment will need to be bypassed very frequently. If process equipment is bypassed for any reason, and sampling of the waste condensate tank shows that further processing is necessary, the contents of one tank can be recycled back through a filter, or ion exchanger as desired, including the portable demineralizer system and collected in the second tank.
The WMS has sufficient capacity to accept liquid waste during startup, shutdown, and refueling.
11.2.2.2.2 Laundry Waste
Liquid detergent waste from the laundry, laundry sump, contaminated showers, and contaminated sinks are collected in two laundry tanks. The waste may be sampled to assure low activity and then be pumped through a filter directly to the circulating water discharge. The waste water may be processed through the LWMS portable demineralization skid and handled as miscellaneous waste. Discharge activity is monitored as described in Section 11.5.
(DRN 99-2361) 11.2.2.3 Steam Generator Blowdown System
The Steam Generator Blowdown System (SGBS) is described in Subsection 10.4.8. The waste removed by the blowdown filters and the waste produced by regeneration of the blowdown demineralizers is collected in the filter flush tank and the regenerative waste tank. The waste collected in the regenerative waste tank and the filter flush tank will normally be disposed of in the Waterford 1 and 2 Waste Processing facility or the Waterford 3 Low Volume Wastewater Basin. In case of radioactivity in the blowdown, blowdown demineralizer waste and the filter flushing water will be transferred to a Radwaste Processing System via a temporary connection.
WSES-FSAR-UNIT-3 11.2-8 Revision 14 (12/05) 11.2.3 RADIOACTIVE RELEASES
(DRN 00-1045, R11-A)
During liquid processing by the BMS and WMS, radioactivity is removed so that the bulk of the liquid is restored to clean water, which is either recycled in the plant or discharged to the environment. The radioactivity removed from the liquids is concentrated in filters and ion exchange resin. These concentrated wastes are sent to the SWMS for packaging and eventual shipment to an approved offsite disposal location. If the water is to be recycled back to the RCS, it must meet the purity requirements for reactor coolant. If the liquid is to be discharged, the activity level must be consistent with the discharge criteria of 10CFR20 and Appendix I to 10CFR50. The BMS and WMS are capable of monitoring radioactive liquid discharge from the systems to ensure that activity concentrations do not exceed predetermined limits. If a limit is exceeded, discharge will be automatically terminate.
(DRN 00-1045, R11-A)
(DRN 03-2065, R14)
An estimate of the normal liquid effluent from the facility, including anticipated operational occurrences, is presented in Table 11.2-11. Table 11.2-12 presents the assumption used. The values were obtained using the guidance presented in NUREG 0017, Calculation of Releases of Radioactive Materials in Gaseous and Liquid Effluents from PWRs (April 1976). It should be noted that the evaluation demonstrates compliance with the September 4, 1975 Annex to Appendix I. Accordingly, a rigorous cost benefit analysis of compliance with Section II D of Appendix I is not provided.
(DRN 03-2065, R14)
The liquid effluent concentrations after uniform dilution in the circulating discharge flow of 2130 cfs, are presented in Table 11.2-13 for normal operation, including anticipated operational occurrences. These concentrations are compared to ten times of the effluent concentration limits of 10CFR20, Table 2, Column 2, and are shown to be much less. The doses caused by the release of radioactivity in the liquid effluents are given in Table 11.2-14. The exposures are well within the limits of Appendix I to 10CFR50.
The doses were calculated in accordance with Regulatory Guide 1.109 (March, 1976).
(DRN 99-2361, R11)
The discharge points are shown on the general site plan of Figure 2.1-4.
(DRN 03-2065, R14)
Tritium will build up in the process streams during the life of the plant. However, the buildup will be limited by evaporation from the surface of the spent fuel pool and radioactive decay. Assuming a tritium production rate of 1292 Ci/yr, as presented in Table 11.1-15, and an evaporation rate of 500 lbs/hr from the surface of the spent fuel pool, the concentration of tritium in the process streams is not expected to exceed 0.5 ci/gm. At this concentration air saturated with this water would have a concentration of 2.11 x 10-5 ci/cc.
(DRN 03-2065, R14)
The following is the method by which this calculation was performed.
a s
V V
+
4.2 W
G cc Ci C
(DRN 99-2361, R11)
WSES-FSAR-UNIT-3 11.2-9 Revision 14 (12/05) where:
C
=
Airborne (Ci/cc) concentration of tritiated water
(DRN 03-2065, R14)
G
=
Tritium generation rate in reactor coolant (1292 Ci/yr)
(DRN 03-2065, R14)
Ws
=
Humidity ratio at 90F (0.0312)
Va
=
Specific Volume of air at 90F (13.85 ft3/lb)
=
radioactive decay constant (0.05/yr)
=
evaporation coefficient =
500 lbs/ hr 8760 hr / yr 10 gal 8.34 lb / gal 6
=
0.53/yr V
=
combined volume of coolant plus spent fuel pool plus refueling water storage pool (106 gal)
(DRN 99-2361, R11; 00-1045, R11-A; 03-2065, R14)
This analysis indicates that the airborne levels of tritiated water vapor will slightly exceed the DAC of 2.0E-5 Ci/cc; however, the analysis assumes no dilution in the process streams due to purification losses (shim bleed) and water makeup (demineralized water). The ventilation provided for the Fuel Handling Building keeps the concentration of the airborne tritium much below the value calculated above.
(DRN 99-2361, R11; 00-1045, R11-A; 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 1 of 7)
Revision 11-B (06/02)
BMS EQUIPMENT DESCRIPTION Reactor Drain Tank Quantity 1
Type Horizontal, cylindrical Internal Volume (useful), gallons 1600 Design Pressure, psig 25 (internal)/15 (external)
Design Temperature, F 250 Normal Operating Pressure, psig 2.0 Normal Operating Temperature, F 120 Code ASME VIII, Div 1 1968 Edition, Sammer 1970 Addenda Material SA-240, Type 304 Equipment Drain Tank Quantity 1
Type Horizontal, cylindrical Internal Volume (useful), gallons 4,000 Design Pressure, psig 10 Design Temperature, F 200 Normal Operating Pressure, psig 3
Normal Operating Temperature, F 120 Code ASME VIII, Div 1, 1968 Edition, Summer 1970 Edition Material SA-240, Type 304
Flash Tank (Inactive per ER-W3-00-0225-00-00)
Quantity 1
Type Vertical, cylindrical Internal Volume (useful), gallons 400
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 2 of 7)
Revision 11 (05/01)
BMS EQUIPMENT DESCRIPTION Flash Tank (Contd)
Design Pressure, psig 75 internal/15 external Design Temperature, F 250 Normal Operating Pressure, psig 0.5 Normal Operating Temperature, F 120 Code ASME III, Class 3, 1968 Edition, Summer 1970 Addenda Material SA-240, Type 304 Holdup Tanks Quantity 4
Type Vertical, cylindrical
Internal Volume (useful) gallons 47,960
Design Pressure, psig 10 internal/2 external Design Temperature, F 240 Normal Operating Pressure, psig 0.5 to 1.5 Normal Operating Temperature, F 120 Code ASME III, Class 3 1968 Edition, Summer 1970 Addenda Material SA-240, Type 304 Boric Acid Condensate Tanks Quantity 4
Type Vertical, cylindrical Internal Volume (useful), gallons 17,200 Design Pressure, psig Atmospheric Design Temperature, F 250
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 3 of 7)
Revision 11-B (06/02)
BMS EQUIPMENT DESCRIPTION Boric Acid Condensate Tanks (Cont'd)
Normal Operating Pressure, psig Atmospheric Normal Operating Temperature, F 120 Code ASME VIII, Div 1, 1968 Edition, Summer 1970 Addenda Material SA-240, Type 304 Reactor Drain Tank and Equipment Drain Tank Pumps Quantity 1 (each)
Type Centrifugal Design Pressure, psig 150 Design Temperature, F 200 Normal Operating Temperature, F 120 Capacity, rate, gpm 50 Rated Head, ft.
145
NPSH Available, ft.
Reactor Drain Tank Pump 49.3 Equipment Drain Tank Pump 36.25
Motor Horsepower 7.5 Wetted Materials Austenitic stainless steel Code ASME III, Class 3, 1971 Edition, Summer 1972 Addenda
Flash Tank Pumps (Inactive per ER-W3-00-0225-00-00)
Quantity 2
Type Centrifugal Design Pressure, psig 150 Design Temperature, F 200 Normal Operating Temperature, F 120
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 4 of 7)
BMS EQUIPMENT DESCRIPTION Flash Tank Pumps (Contd)
Capacity, rate, gpm 150 Rated Head, ft.
60 NPSH Available, ft.
24.1 Motor Horsepower 7.5 Wetted Materials Austenitic stainless steel Code ASME III, Class 3, 1971 Edi-tion, Summer 1972 Addenda Holdup Drain and Recirculation Pumps Quantity I drain, I recirc/drain I recirc Type Centrifugal Design Pressure, psig 150 Design Temperature, F 200 Normal Operating Temperature, F 120 Capacity, rated, gpm 50 Rated Head, ft.
145 NPSH Available, feet 36.3 (drain), 13.5 (recirc)
Motor Horsepower 7.5 Wetted Materials Austenitic stainless steel Code None Boric Acid Condensate Pumps Quantity 2
Type Centrifugal
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 5 of 7)
Revision 11 (05/01)
BMS EQUIPMENT DESCRIPTION Boric Acid Condensate Pumps (Contd)
Design Pressure, psig 150 Design Temperature, F 200 Normal Operating Temperature, F 120 Capacity, rated, gpm 50 Rated Head, ft.
145 NPSH Available, ft.
25 Motor Horsepower 7.5
Material Austenitic stainless steel
Code None Preconcentrator Ion Exchanger Quantity 2
Type Flushable Design Pressure, psig 150 Design Temperature, F 250 Normal Operating Pressure, psig 60 Normal Operating Temperature, F 120 Resin Volume (total), ft.3 36 Resin Volume (useful) required, ft.3 34 Design Flow, gpm 100 Normal Flow, gpm 20 Code for Vessel ASME VIII, Div 1, 1968 Edition, Summer 1970 Addenda Material Austenitic stainless steel
Resin Bead Type
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 6 of 7)
Revision 11-A (02/02)
BMS EQUIPMENT DESCRIPTION Boric Acid Condensate Ion Exchangers Quantity 2
Type Flushable Design Pressure, psig 150 Design Temperature, F 250 Normal Operating Pressure, psig 60 Normal Operating Temperature, F 140 Resin Volume (total) 36 Resin Volume (useful) required 34
¨ (DRN 99-2361)
Design Flow, gpm 50 Normal Flow, gpm 20 (DRN 99-2361)
Code for Vessel ASME VIII, Div 1, 1968 Edition Summer 1970 Addenda Material Austenitic stainless
¨ (DRN 99-1050)
Resin Bead Type (DRN 99-1050)
¨(DRN 00-1045)
WSES-FSAR-UNIT-3 TABLE 11.2-1 (Sheet 7 of 7)
Revision 11-A (02/02)
BMS EQUIPMENT DESCRIPTION
¨(DRN 00-1045)
Preconcentrator Filters Quantity 2
¨ (DRN 99-1050)
Type Element Cartridge (DRN 99-1050)
¨ (DRN 99-2361)
Normal Operating Pressure, psig 60-90 (DRN 99-2361)
Design Pressure, psig 150 Design Temperature, F 240
¨ (DRN 99-2361)
Normal Operating Temperature, F 90-120 (DRN 99-2361)
Design Flow, gpm 100 Normal Flow, gpm 20 Code for Vessel ASME VIII, 1968 Edition, Winter 1970 Addenda Material Austenitic stainless steel
WSES-FSAR-UNIT-3 Table 11.2-2 (Sheet 1 of 3)
Revision 14 (12/05)
WMS EQUIPMENT DESCRIPITION Waste Waste Tanks Waste Condensate Laundry Storage Quantity 2
2 2
1 Type (cylindrical)
Horizontal Horizontal Horizontal Vertical
(DRN 99-2361, R11)
Internal volume (useful),
gallons 4000 15000 4000 38,000
(DRN 99-2361, R11)
Design Pressure ATM ATM ATM ATM Normal Operating Pressure ATM ATM ATM ATM Design Temperature, F 200 250 200 120 Normal Operating Temperature, F 120 120 120 120 Code None(1)
None(1)
None(1)
ASME VIII, 1983 Edition-Winter Addenda Material SA-240 SA-240 SA-240 SA-240 Type 304 Type 304 Type 304 Type 304
(DRN 99-2361, R11)
Filters Waste Laundry
(DRN 99-2361, R11)
Quantity 1
1
(DRN 99-1050, R11)
Type element Cartridge Cartridge
(DRN 99-1050, R11)
Design Pressure, psig 150 150 Normal Operating Pressure, psig 60 60 Design Temperature, F 200 200 Normal Operating Temperature, F 120 120 Design Flow, gpm 50 50 Normal Operating Flow, gpm 20 50
(DRN 03-2065, R14)
Code for vessel ASME VIII, 1968 ASME VIII, 1968
(DRN 03-2065, R14)
Material Edition - Winter 1970 Edition - Winter 1970 Addenda Addenda Type 316 Stainless Steel Type 316 Stainless Steel Oil Removal Filter
(DRN 01-458, R11-A)
Quantity 1
Type Pleated Paper Cartridge
(DRN 01-458, R11-A)
Design Pressure, psig 150 Normal Operating Pressure, psig 60 Design Temperature, F 200 Normal Operating Temperature, F 120 Design Flow, gpm 50 Normal Operating Flow, gpm 20
WSES-FSAR-UNIT-3 Table 11.2-2 (Sheet 2 of 3)
Revision 15 (03/07)
WMS EQUIPMENT DESCRIPITION Oil Removal Filter (Cont'd)
Code for vessel ASME VIII, 1968 Edition Winter 1970 Addenda
(DRN 99-2361, R11)
(DRN 99-2361, R11)
Material Austenitic Stainless Steel Waste Condensate Ion Exchanger Quantity 1
Type Flushable deep resin bed Design Pressure, psig 150 Normal Operating Pressure, psig 60 Design Temperature, F 250 Normal Operating Temperature 120 Design Flow, gpm 50
(DRN 99-2361, R11)
Normal Operating Flow, gpm 20
(DRN 99-2361, R11)
Resin Volume (total), ft.-3 36 Resin Volume (useful), ft.-3 32 Code for vessel ASME VIII, 1968 Edition, Summer 1970 Addenda Material Austenitic Stainless Steel
(DRN 99-1050, R11)
Resin Bead Type
(DRN 99-1050, R11)
(DRN 01-1248, R11-B)
Waste Demineralizer System
(DRN 01-1248, R11-B)
Quantity 1
Design DF 104
(DRN 02-263, R11-B;06-558, R15)
Design Pressure, psig 150 Design Temperature, F 150 Design Flow, gpm 50
(DRN 02-263, R11-B)
Normal Operating Flow, gpm 20
(DRN 06-558, R15)
Electric Load 480V 3OA/3
120V 30A 120V 15A Material Austenitic Stainless Steel
(DRN 02-263, R11-B)
Code ASME VIII "U" Stamp and ANSI B31.1
(DRN 02-263, R11-B)
WSES-FSAR-UNIT-3 Table 11.2-2 (Sheet 3 of 3)
Revision 11-A (02/02)
WMS EQUIPMENT DESCRIPTION
¨ (DRN 98-1595)
Waste Waste Pumps Waste Condensate Laundry Storage (DRN 98-1595)
Quantity 2
2 2
Type Centrifugal Centrifugal Centrifugal Centrifugal Design Pressure, psig 150 150 150 150
¨(DRN 00-1882)
Design Temperature, F 200 250 200 200 (DRN 00-1882)
Normal Operating Temperature, F 120 120 120 120 Capacity, rated, gpm 50 50 50 60
¨ (DRN 98-1595,00-543, 00-1028; 00-1882;01-551)
Rated head, ft.
147.9 147.9 147.9 125 (DRN 98-1595,00-543, 00-1028; 00-1882;01-551)
NPSH, Available, ft.
15.5 23.4 24 5
Motor Horsepower 7 1/2 7 1/2 7 1/2 7 1/2 Wetted Materials Stainless Stainless Stainless Stainless Steel Steel Steel Steel
¨ (DRN 98-1595,00-543, 00-1028;01-551)
(DRN 98-1595,00-543, 00-1028;01-551)
¨ (DRN 99-2361)
(1)
The tank is designed and fabricated to ASME VIII Division I but is not stamped.
WSES-FSAR-UNIT-3 TABLE 11.2-3 SOURCES, VOLUMES, AND ACTIVITIES FOR BMS LIQUID INFLUENTS Expected Fraction of (a)
Operations from CVCS gallons/year RCS Activity Shim Feed and Bleed for Fuel Burnup 252,300 (b)
Refueling Shutdown and Startup 106,508 (b)
Hot Shutdown at 55% and 65% of Core Life 131,000 (b)
Cold Shutdown at 30%, 60%, and 90%
of Core Life 292,672 (b)
TOTAL 782,480 Expected Fraction of gallons/day RCS Activity Reactor Drain Tank 200 1.0 Equipment Drain Tank 50 0.1 (a)
The expected RCS specific activities are given in Table 11.1-3.
(b)
The waste entering the BMS from the CVCS is RCS water (Table 11.1-3) that has passed through the purification filter and ion exchanger. The total CVCS DF is 2 for Cs and Rb and 10 for all other nuclides, except tritium and noble gases, which are unity.
WSES-FSAR-UNIT-3 TABLE 11.2-4 Revision 14 (12/05)
SOURCES, VOLUMES, AND ACTIVITIES OF WMS LIQUID INFLUENTS Volumes (gallon/day)
Fraction of(a)
Waste Tanks (a)
Expected Maximum RCS Activities Containment Building Sump 40 40 1.0 Auxiliary Building Floor Drains 200 200 0.1 Laboratory Drains and Waste Water 400 400 0.002 Sampling Drains 35 35 1.0 Miscellaneous 700 700 0.01 Blowdown 50 17,300(b)
(c)
Total 1425 18,675 Laundry Tanks 450 1400 (d)
(a)
The expected RCS activities are given in Table 11.1-3.
(b)
Based on one demineralizer regeneration and one filter backflush being radioactive.
(c)
The specific activities of the waste from the "Blowdown Treatment System" is provided in Table 11.1-3.
(DRN 03-2065, R14)
(d)
Untreated releases of detergent waste are provided in Table 11.2-11.
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-5 Revision 14 (12/05)
(DRN 03-2065, R14)
TABLE 11.2-5 HAS BEEN INTENTIONALLY DELETED.
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-6 Revision 11-B (06/02)
BMS EQUIPMENT DECONTAMINATION FACTORS
Nuclide Flash (b)
Tank Pre-Concentrator Filter Boric Acid Codensate Ion Exchanger Pre-Concentrator Ion Exchanger I
1 1
1 10
Cs 1
1 1
100.
Rb 1
1 1
100.
Mo 1
1 1
1 y
1 1
1 1
other Ca+
1 1
1 10 other A-1 1
1 10 Crud 1
10 1
1 Tritium 1
1 1
1 Noble gases 2
1 1
1
(b) The Flash Tank has been made inactive per ER-W3-00-0225-00-00.
WSES-FSAR-UNIT-3 TABLE 11.2-7 Revision 11-B (06/02)
WMS EQUIPMENT DECONTAMINATION FACTORS
Waste Waste Condensate Nuclide Demineralizer Ion Exchanger Filters (a)
System
I 104 10 1
Cs 104 10 1
Rb 104 10 1
Mo 104 10 1
Y 104 10 1
other Ca+
104 10 1
other A-104 10 1
Crud 100 1
10 Tritium 1
1 1
(a)
Includes Laundry, Waste, and Oil Filter
WSES-FSAR-UNIT-3 TABLE 11.2-8 FPS EQUIPMENT DECONTAMINATION FACTORS Nuclide Filter Ion Exchanger I
1 10 Cs 1
10 Rb 1
10 Mo 1
10 Y
1 10 other Ca+
1 10 Other A-1 10 Crud 10 1
Tritium 1
1 Noble Gases 1
1
WSES-FSAR-UNIT-3 TABLE 11.2-9 (Sheet 1 of 2)
Revision 11-B (06/02)
BORON MANAGEMENT SYSTEM PROCESS DATA (1), (2), (3)
Mode I Processing Reactor Drain Tank Contents to the Holdup Tank Location:
1 2
3 4
5(4) 6(4) 7(4) 8 Flow gpm 200 gpd 50 50 0
50 60 50 50 Pressure, psig 0.5 12 75 7
6 3
40 2
Temp. F 120 120 120 120 120 120 120 120 Mode 2 Processing Equipment Drain Tank Contents to the Holdup Tank Location:
1a 1b 2
3 4
5(4) 6(4) 7(4) 8 Flow gpm 50 gpd 25 50 50 0
50 60 50 50 Pressure, psig 3
3 12 74 7
6 3
40 2
Temp. F 120 120 120 120 120 120 120 120 120 Mode 3 Processing Normal Purification Flow to the Holdup Tank Location:
4 5(4) 6(4) 7(4) 8 Flow gpm 40 40 50 40 40 Pressure, psig 5
4 3
41 2
Temp. F 120 120 120 120 120 Mode 4 Processing Intermediate CVCS Purification Flow to the Holdup Tank Location:
4 5(4) 6(4) 7(4) 8 Flow gpm 84 84 94 84 84 Pressure, psig 21 19 3
36 3
Temp. F 120 120 120 120 120 Mode 5 Processing Maximum CVCS Purification Flow to the Holdup Tank Location:
4 5(4) 6(4) 7(4) 8 Flow gpm 128 128 138 128 128 Pressure, psig 52 47 3
31 4
Temp. F 123 123 123 123 123
Mode 6 Processing Holdup Tank Contents Via the Boric Acid Concentrator Location:
12 13 14 14a 15 16 17 17a 18
Flow gpm 0
0 0
0 0
0 0
0 0
Pressure, psig 0
0 0
0 0
0 0
0 0
Temp. F 0
0 0
0 0
0 0
0 0
WSES-FSAR-UNIT-3 TABLE 11.2-9 (Sheet 2 of 2)
Revision 15 (03/07)
BORON MANAGEMENT SYSTEM PROCESS DATA (1), (2), (3)
(DRN 00-696, R11-B)
Recirculating Holdup Tank Contents Through the Preconcentrator Filter Mode 7 and Preconcentrator Ion Exchanger or Back to the Flash Tank(4) via the Filter &
Ion Exchanger to the Flash Tank (4)
Location:
9 10 11 11a 11b 5
(4) 6 (4) 7 (4) 8 Flow gpm 60 60 50 50 50 50 60 50 50 Pressure,psig 24 86 31 24 5
6 3
40 2
Temp. F 120 120 120 120 120 120 120 120 120
(DRN 00-696, R11-B)
(DRN 06-537, R15)
Discharging Boric Acid Condensate Tank Contents to Mode 8 the Circulating Water Discharge Canal
(DRN 06-537, R15)
Location:
19 20 21 Flow gpm 60 50 50 Pressure, psig 13 62 32 Temp. F 120 120 120 Recirculating Boric Acid Condensate Tank Contents through the Boric Mode 9 Acid Condensate Ion Exchanger or Back to the Holdup Tank via Ion Exchanger to Holdup Tank Location:
19 20 20a 17a 18 8
Flow gpm 60 50 50 50 50 50 Pressure,psig 13 62
.40 34 0
2 Temp.,F 120 120 120 120 120 120 (1)
Process data refers to nodal points of Figure 11.2-1.
(2)
The pressure drop across the BMS filters, ion exchangers and strainers varies with loading. The pressure drops as shown are given with minimal crud deposition.
(3)
Since line pressure drops are dependent on piping layouts and equipment elevations and assumed pipe lengths were used for calculation purposes, the pressure values are approximate.
(DRN 00-696, R11-B)
(4)
This is historical data. The Flash Tank path is inactive per ER-W3-00-0225-00-00. Effluent now flows directly to the Holdup Tanks.
(DRN 00-696, R11-B)
WSES-FSAR-UNIT-3 TABLE 11.2-10 WASTE MANAGEMENT SYSTEM PROCESS FLOW POINT DATA PROCESSING CONTENTS OF A WASTE TANK Mode I Location(1) 1 2 3 4 5 6 7 8 9 10 11 12 Flow, gpm 50 20 30 20 20 1
19 19 60 50 10 50 Pressure, psig 62 62 62 52 42 20 30 20 62 62 62 52 Temperature, F 120 120 120 120 120 180 120 120 120 120 120 120 PROCESSING CONTENTS OF A LAUNDRY TANK Mode 2 Location(1) 13 14 15 16 12 Flow, gpm 60 10 50 50 50 Pressure, psig 62 62 62 52 52 Temperature, F 120 120 120 120 120
(1) Refers to nodal points of Figure 11.2-2.
WSES-FSAR-UNIT-3 TABLE 11.2-11 (Sheet 1 of 2)
Revision 14 (12/05)
SOURCE TERMS (NO GAS STRIPPING)
LIQUID EFFLUENTS
(DRN 03-2065, R14)
ANNUAL RELEASES TO DISCHARGE CANAL COOLANT CONCENTRATIONS ---------------------------------------------------------------------------------------------------------- ADJUSTED DETERGENT TOTAL NUCLIDE HALF-LIFE PRIMARY SECONDARY BORON RS MISC. WASTES SECONDARY TURB BLDG TOTAL LWS TOTAL WASTES (DAYS)
(Ci/ml)
(Ci/ml)
(CURIES)
(CURIES)
(CURIES)
(CURIES)
(CURIES)
(Ci/yr)
(Ci/yr)
(Ci/yr)
CORROSION AND ACTIVIATION PRODUCTS Na-24 6.25E-01 7.78E-02 5.83E-06 0.00000*
0.00004 0.00000 0.00022 0.00026 0.00328 0.00000 0.00330 P-32 1.43E+01 0.00E+00 0.00E+00 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00018 0.00018 Cr-51 2.78E+01 6.19E-03 7.27E-07 0.00000 0.00001 0.00000 0.00004 0.00005 0.00063 0.00470 0.00530 Mn-54 3.03E+02 3.22E-03 3.68E-07 0.00000 0.00001 0.00000 0.00002 0.00003 0.00034 0.00380 0.00410 Fe-55 9.50E+02 2.42E-03 2.78E-07 0.00000 0.00001 0.00000 0.00001 0.00002 0.00025 0.00720 0.00750 Fe-59 4.50E+01 6.01E-04 6.74E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00006 0.00220 0.00230 Co-58 7.13E+01 9.23E-03 1.07E-06 0.00000 0.00002 0.00000 0.00005 0.00007 0.00096 0.00790 0.00890 Co-60 1.92E+03 1.07E-03 1.25E-07 0.00000 0.00000 0.00000 0.00001 0.00001 0.00011 0.01400 0.01400 Ni-63 3.36E+04 0.00E+00 0.00E+00 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00170 0.00170 Zn-65 2.45E+02 1.03E-03 1.19E-07 0.00000 0.00000 0.00000 0.00001 0.00001 0.00011 0.00000 0.00011 W-187 9.96E-01 4.34E-03 3.74E-07 0.00000 0.00000 0.00000 0.00002 0.00002 0.00024 0.00000 0.00024 Np-239 2.35E+00 4.09E-03 4.14E-07 0.00000 0.00000 0.00000 0.00002 0.00002 0.00030 0.00000 0.00030 FISSION PRODUCTS Sr-89 5.20E+01 2.81E-04 3.21E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00003 0.00009 0.00012 Sr-90 1.03E+04 2.42E+05 2.78E-09 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00001 0.00002 Sr-91 4.03E-01 1.52E-03 9.76E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00005 0.00000 0.00005 Y-91m 3.47E-02 6.22E-04 6.88E-09 0.00000 0.00000 0.00000 0.00000 0.00000 0.00003 0.00000 0.00003 Y-91 5.88E+01 1.04E-05 1.18E-09 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00008 0.00008 Y-93 4.25E-01 6.67E-03 4.24E-07 0.00000 0.00000 0.00000 0.00001 0.00002 0.00021 0.00000 0.00021 Zr-95 6.50E+01 7.83E-04 9.02E-08 0.00000 0.00000 0.00000 0.00000 0.00001 0.00008 0.00110 0.00120 Nb-95 3.50E+01 5.60E-04 6.17E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00006 0.00190 0.00200 Mo-99 2.79E+00 1.20E-02 1.26E-06 0.00000 0.00001 0.00000 0.00006 0.00007 0.00693 0.00006 0.00099 Tc-99m 2.50E-01 7.09E-03 3.39E-07 0.00000 0.00001 0.00000 0.00003 0.00005 0.00661 0.00000 0.00061 Ru-103 3.96E+01 1.50E-02 1.74E-06 0.00000 0.00003 0.00000 0.00009 0.00012 0.00153 0.00029 0.00180 Rh-103M 3.96E-02 0.00E+00 0.00E+00 0.00000 0.00003 0.00000 0.00009 0.00012 0.00151 0.00000 0.00150 Ru-106 3.67E+02 1.81E-01 2.10E-05 0.00001 0.00044 0.00000 0.00104 0.00149 0.01906 0.00890 0.02800 Rh-106 3.47E-04 0.00E+00 0.00E+00 0.00001 0.00044 0.00000 0.00104 0.00149 0.01906 0.00000 0.01900 Ag-110m 2.53E+02 2.62E-03 3.00E-07 0.00000 0.00001 0.00000 0.00001 0.00002 0.00027 0.00120 0.00150 Ag-110 2.82E-04 0.00E+00 0.00E+00 0.00000 0.00000 0.00000 0.00000 0.00000 0.00004 0.00000 0.00004 Sb-124 6.00E+01 0.00E+00 0.00E+00 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00043 0.00043 Te-129m 3.40E+01 3.80E-04 4.37E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00004 0.00000 0.00004 Te-129 4.79E-02 3.28E-02 4.90E-07 0.00000 0.00000 0.00000 0.00000 0.00000 0.00004 0.00000 0.00004 Te-131m 1.25E+00 2.66E-03 2.42E-07 0.00000 0.00000 0.00000 0.00001 0.00001 0.00016 0.00000 0.00016 Te-131 1.74E-02 1.03E-02 5.92E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00003 0.00000 0.00003 I-131 8.05E+00 8.90E-02 9.83E-06 0.00000 0.00142 0.00000 0.00096 0.00238 0.03054 0.00160 0.03200
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-11 (Sheet 2 of 2)
Revision 14 (12/05)
SOURCE TERMS (NO GAS STRIPPING)
LIQUID EFFLUENTS
(DRN 03-2065, R14)
ANNUAL RELEASES TO DISCHARGE CANAL COOLANT CONCENTRATIONS ---------------------------------------------------------------------------------------------------------- ADJUSTED DETERGENT TOTAL NUCLIDE HALF-LIFE PRIMARY SECONDARY BORON RS MISC. WASTES SECONDARY TURB BLDG TOTAL LWS TOTAL WASTES (DAYS)
(Ci/ml)
(Ci/ml)
(CURIES)
(CURIES)
(CURIES)
(CURIES)
(CURIES)
(Ci/yr)
(Ci/yr)
(Ci/yr)
Te-132 3.25E+00 3.22E-03 3.37E-07 0.00000 0.00000 0.00000 0.00002 0.00002 0.00025 0.00000 0.00025 I-132 9.58E-02 2.96E-01 7.71E-06 0.00000 0.00014 0.00000 0.00014 0.00028 0.00362 0.00000 0.00360 I-133 8.75E-01 2.41E-01 2.02E-05 0.00000 0.00150 0.00000 0.00165 0.00315 0.04041 0.00000 0.04000 I-134 3.67E-02 4.61E-01 5.19E-06 0.00000 0.00002 0.00000 0.00000 0.00003 0.00035 0.00000 0.00035 Cs-134 7.49E+02 1.32E-02 2.74E-06 0.00004 0.00016 0.00000 0.00014 0.00034 0.00436 0.01100 0.01500 I-135 2.79E-01 3.98E-01 2.10E-05 0.00000 0.00078 0.00000 0.00113 0.00190 0.02436 0.00000 0.02400 Cs-136 1.30E+01 1.58E-03 3.16E-07 0.00000 0.00001 0.00000 0.00002 0.00003 0.00041 0.00037 0.00078 Cs-137 1.10E+04 1.75E-02 3.66E-06 0.00006 0.00022 0.00000 0.00018 0.00045 0.00582 0.01600 0.02200 Ba-137m 1.77E-03 0.00E+00 0.00E+00 0.00005 0.00020 0.00000 0.00017 0.00043 0.00544 0.00000 0.00540 Ba-140 1.28E+01 2.57E-02 2.86E-06 0.00000 0.00005 0.00000 0.00014 0.00019 0.00240 0.00091 0.00330 La-140 1.67E+00 4.54E-02 4.38E-06 0.00000 0.00007 0.00000 0.00021 0.00028 0.00357 0.00000 0.00360 Ce-141 3.24E+01 3.00E-04 3.42E-08 0.00000 0.00000 0.00000 0.00000 0.00000 0.00003 0.00023 0.00026 Ce-143 1.38E+00 5.00E-03 4.56E-07 0.00000 0.00000 0.00000 0.00002 0.00002 0.00031 0.00000 0.00031 Pr-143 1.37E+01 0.00E+00 0.00E+00 0.00000 0.00000 0.00000 0.00000 0.00000 0.00001 0.00000 0.00001 Ce-144 2.84E+02 7.85E-03 9.06E-07 0.00000 0.00002 0.00000 0.00005 0.00006 0.00082 0.00390 0.00470 Pr-144 1.20E-02 0.00E+00 0.00E+00 0.00000 0.00002 0.00000 0.00005 0.00006 0.00082 0.00000 0.00082 ALL OTHERS 2.73E-01 1.22E-06 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 0.00000 TOTAL (EXCEPT TRITIUM) 2.26E+00 1.16E-04 0.00017 0.00571 0.00000 0.00767 0.01355 0.17355 0.08975 0.26000 TRITIUM RELEASE 370 CURIES PER YEAR Releases which are less than 10-5Ci/yr are designated as 0.00000.
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-12 (Sheet 1 of 3)
Revision 307 (07/13)
PRINICIPAL PARAMETERS AND CONDITIONS USED IN RADIOLOGICAL EFFLUENT EVALUATIONS (DRN 03-2065, R14)
- 1.
Design Thermal Power Level 3716 MWt (DRN 03-2065, R14)
- 2.
Plant Load Factor 0.8
- 3.
Percent Failed Fuel 0.12
- 4.
Primary System Mass of Coolant 455,950 lbs.
Average Letdown Rate 40 gpm Average Letdown Rate through HBO3 Demineralizers 8 gpm Shim Bleed Rate 0.54 gpm Steam Generator Leak Rate to Secondary (DRN 03-2065, R14)
Side 75 lbs./day (DRN 03-2065, R14)
Leakage Rate to Auxiliary Bldg.
160 lbs./day Source Term to Containment Bldg.
Noble Gases 1% of noble gas coolant inventory Iodine 0.001% of iodine coolant inventory Letdown Stripping (no stripping)
- 5.
Secondary System (DRN 03-2065, R14; EC-8458, R307)
Steam Flow Rate 1.66 x 107 lbs./hr Mass of Steam in each Steam Generator 1.24 x 104 lbs.
Mass of Water in each Steam Generator 1.81 x 105 lbs.
(DRN 03-2065, R14; EC-8458, R307)
Number of Steam Generators 2
Mass of Secondary Coolant (includes Condenser hotwell) 2.8 x 106 lbs.
Rate of Steam Leakage to Turbine Bldg.
1700 lbs./hr (DRN 03-2065, R14)
Steam Generator Blowdown Rate 165 gpm
- 6.
Containment Volume 2.68 x 106 ft.3 (DRN 03-2065, R14)
- 7.
Frequency of Containment Purge 24 purges/yr.
with 16 hrs. of recirculation through filters prior to each purge
- 8.
Gaseous Waste Management System Number of Tanks 3
Decay Tank Volume 600 ft.3 (each)
Fill Time 60 days Holdup Time 60 days
WSES-FSAR-UNIT-3 Table 11.2-12 (Sheet 2 of 3) Revision 7 (10/94)
PRINICIPAL PARAMETERS AND CONDITIONS USED IN RADIOLOGICAL EFFLUENT EVALUATIONS 9.
Iodine Partition Factors Auxiliary Building Leakage 0.0075 Steam Leakage to Turbine Bldg.
1.0 Steam Generator (carryover) 0.01 Main Condenser 0.15 10.
Steam Generator Blowdown Flash Tank Routed to Condenser 11.
Decontamination Factors(2)
Demineralizer Anion CsRb Other Nuclides Mixed Bed:
Primary Coolant Letdown 10 2
10 (Li3 BO3)
Radwaste (H+ OH-)
102 (10)(1) 2(10) 102 (10)
Evaporator Condensate 10 10 10 Polishing Cation Bed (any system) 1(1) 10(10) 10(10)
Anion Bed (any system) 102 (10) 1(1) 1(1)
Powdex (any system) 10(10) 2(10) 10(10)
All Nuclides Evaporators(3)
Except Iodine Iodine
Miscellaneous Radwaste 104 103 Boric Acid Recovery 103 102 Detergent Wastes 102 102 (1)
For demineralizers in series, the DF for the second demineralizer is given in parenthesis.
(2)
These DFs differ from DFs presented in Tables 11.2-6, 11.2-7 and 11.2-8 in that they take less credit for the effectiveness for filters and evaporators in order to place a conservative upper limit on liquid effluent from the plant.
(3) The Waste Concentrator was abandoned per DC-3188.
WSES-FSAR-UNIT-3 Table 11.2-12 (Sheet 3 of 3)
PRINICIPAL PARAMETERS AND CONDITIONS USED IN RADIOLOGICAL EFFLUENT EVALUATIONS 12.
Liquid Waste Streams Collection Decay Stream Flow Rate Fraction Fraction Time Time Gal/Days of PCA Discharged (Days) (Days)
Shim Bleed 7.78(+02) 1.000 0.120 26.000 1.300 Equipment Drains 5.00(+01) 0.100 0.120 90.000 1.300 Clean Wastes 6.22(+02) 1.000 0.120 32.400 1.300 Dirty Wastes 1.38(+03) 0.075 1.000 2.300 0.100 Blowdown 8.69(+04) 0.000 2.300 0.100 Untreated Blowdown 0.
1.000 0.0 0.0 Stream Decontamination Factors Iodine Cesium Others Shim Bleed 1.00(+05) 2.00(+04) 1.00(+05)
Equipment Drains 1.00(+04) 2.00(+04) 1.00(+05)
Clean Wastes 1.00(+04) 2.00(+04) 1.00(+05)
Dirty Wastes 1.00(+04) 2.00(+04) 1.00(+05)
Blowdown 1.00(+01) 2.00(+00) 1.00(+01)
Untreated Blowdown 1.00( 00) 1.00( 00) 1.00( 00) 13.
Filtration of Airborne Effluents Decontamination Factors Iodines Particulates Auxiliary Bldg. Vent 10 100 Reactor Bldg. Vent 10 100 Turbine Bldg.
Unfiltered (open Turbine Building)
Air Ejector 10 100 Decay Tanks Unfiltered 14.
X/Qs and D/Qs based on a ground release model only (i.e., no mixed mode release).
15.
A filtration efficiency of 90% for the RAB filter during all normal operation, including Containment Building purge.
16.
Iodine charcoal filter efficiency of 50% for the ARRS inside the Containment.
( )
Denotes power of 10
WSES-FSAR-UNIT-3 TABLE 11.2-13 (Sheet 1 of 2)
Revision 14 (12/05)
FRACTION OF EFFLUENT CONCENTRATION (EC) AVERAGED OVER ONE YEAR Nuclide Concentration in Discharge Canal (Ci)*
(Ci/cc)
Effluent Concentration 10ECi**
(uCi/cc)
Ci/10ECi***
(DRN 03-2065, R14)
Cr-51 2.79E-12 5.00E-03 5.57E-10 Mn-54 2.16E-12 3.00E-04 7.19E-09 Fe-55 3.94E-12 1.00E-03 3.94E-09 Fe-59 1.21E-12 1.00E-04 1.21E-08 Co-58 4.68E-12 2.00E-04 2.34E-08 Co-60 7.36E-12 3.00E-05 2.45E-07 Rb-86 0.00E+00 7.00E-05 0.00E+00 Sr-89 6.31E-14 8.00E-05 7.89E-10 Y-91 4.21E-14 8.00E-05 5.26E-10 Np-239 1.58E-13 2.00E-04 7.89E-10 Mo-99 5.20E-13 2.00E-04 2.60E-09 Tc-99m 3.21E-13 1.00E-02 3.21E-11 H-3 1.95E-07 1.00E-02 1.95E-05 I-131 1.68E-11 1.00E-05 1.68E-06 I-132 1.89E-12 1.00E-03 1.89E-09 I-133 2.10E-11 7.00E-05 3.00E-07 I-134 1.84E-13 4.00E-03 4.60E-11 I-135 1.26E-11 3.00E-04 4.21E-08 Cs-134 7.89E-12 8.00E-05 9.86E-08 Cs-136 4.10E-13 1.00E-07 4.10E-06 Cs-137 1.16E-11 7.00E-03 1.65E-09 Te-127m 0.00E+00 9.00E-05 0.00E+00 Te-127 0.00E+00 1.00E-03 0.00E+00 Te-129m 2.10E-14 7.00E-05 3.00E-10 Te-129 2.10E-14 4.00E-03 5.26E-12 Te-131m 8.41E-14 8.00E-05 1.05E-09 Te-132 1.31E-13 9.00E-05 1.46E-09 Na-24 1.73E-12 5.00E-05 3.47E-08 P-32 9.46E-14 9.00E-05 1.05E-09 Ni-63 8.94E-13 1.00E-03 8.94E-10 Zn-65 5.78E-14 5.00E-05 1.16E-09 W-187 1.26E-13 Sr-90 1.05E-14 5.00E-06 2.10E-09 Sr-91 2.63E-14 2.00E-04 1.31E-10 Y-91m 1.58E-14 2.00E-02 7.89E-13 Y-93 1.10E-13 2.00E-04 5.52E-10 Zr-95 6.31E-13 2.00E-04 3.15E-09 Nb-95 1.05E-12 3.00E-04 3.50E-09 Ru-103 9.46E-13 3.00E-04 3.15E-09 Rh-103m 7.89E-13 6.00E-02 1.31E-11 Ru-106 1.47E-11 3.00E-05 4.91E-07 Rh-106 9.99E-12 Ag-110m 7.89E-13 6.00E-05 1.31E-08
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-13 (Sheet 2 of 2)
Revision 14 (12/05)
FRACTION OF EFFLUENT CONCENTRATION (EC) AVERAGED OVER ONE YEAR
(DRN 03-2065, R14)
Nuclide Concentration in Discharge Canal (Ci)*
(Ci/cc)
Effluent Concentration 10ECi**
(uCi/cc)
Ci/10ECi***
Ag-110 2.10E-14 Sb-124 2.26E-13 7.00E-05 3.23E-09 Te-131 1.58E-14 8.00E-04 1.97E-11 Ba-137m 2.84E-12 Ba-140 1.73E-12 8.00E-04 2.17E-09 La-140 1.89E-12 9.00E-05 2.10E-08 Ce-141 1.37E-13 3.00E-04 4.56E-10 Ce-143 1.63E-13 2.00E-04 8.15E-10 Pr-143 5.26E-15 2.00E-04 2.63E-11 Ce-144 2.47E-12 3.00E-05 8.24E-08 Pr-144 4.31E-13 1.00E-03 4.31E-10 Uniform Dispersion in Entire Circulating Water Discharge of 2130 cfs.
Ten times Effluent Concentration in 10CFR20, Appendix B, Table 2, Column 2.
Fraction of Effluent Concentration allowed by 10CFR20.
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-14 (Sheet 1 of 2)
Revision 14 (12/05)
AQUATIC EXPOSURE PATHWAYS (mrem/yr)
Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Whole Body
(DRN 03-2065, R14)
Adults:
Irrigation-Fruits & Vegetables
& Grain 5.2E-04 1.6E-02 1.5E-02 1.5E-02 1.5E-02 1.5E-02 1.6E-02 1.6E-02 Leafy Vegetables 6.4E-05 2.0E-03 2.0E-03 2.1E-03 2.0E-03 1.8E-03 2.0E-03 2.0E-03 Milk 6.3E-04 1.0E-02 2.0E-02 9.3E-03 9.1E-03 9.0E-03 9.7E-03 9.7E-03 Meat & Poultry 8.9E-05 3.3E-03 1.4E-02 3.3E-03 3.2E-03 3.2E-03 3.3E-03 3.3E-03 Fish-8.2E-02 1.4E-01 3.3E-02 4.7E-02 1.6E-02 3.8E-03 1.0E-01 1.0E-01 Drinking-1.6E-03 2.4E-02 1.0E-01 2.3E-02 2.2E-02 2.2E-02 2.4E-02 2.4E-02 Shoreline Activities 5.5E-05 5.5E-05 5.5E-05 5.5E-05 5.5E-05 5.5E-05 6.4E-05 5.5E-05 TOTALS-8.4E-02 2.0E-01 1.8E-01 1.0E-01 6.7E-02 5.4E-02 1.6E-01 1.6E-01 Teen:
Irrigation-Fruits & Vegetables
& Grain 8.3E-04 1.6E-02 1.5E-02 1.8E-02 1.5E-02 1.5E-02 1.5E-02 1.5E-02 Leafy Vegetables 5.6E-05 1.0E-03 1.0E-03 1.3E-03 9.9E-04 9.8E-04 1.0E-03 1.0E-03 Milk 1.1E-03 1.1E-02 2.4E-02 1.3E-02 9.3E-03 9.2E-03 9.9E-03 9.9E-03 Meat & Poultry 6.8E-05 1.6E-03 8.5E-03 2.0E-03 1.5E-03 1.5E-02 1.6E-03 1.6E-03 Fish-8.3E-02 1.4E-01 3.0E-02 3.6E-02 1.8E-02 2.6E-03 5.8E-02 5.8E-02 Drinking-1.5E-03 1.5E-02 7.8E-02 1.6E-02 1.3E-02 1.3E-02 1.3E-02 1.3E-02 Shoreline Activities-3.1E-04 3.1E-04 3.1E-04 3.1E-04 3.1E-04 3.1E-04 3.6E-04 3.1E-04 TOTALS-8.6E-02 1.8E-01 1.5E-01 8.6E-02 5.8E-02 4.3E-02 9.8E-02 9.8E-02 Child:
Irrigation-Fruits & Vegetables
& Grains 2.0E-03 2.5E-02 2.3E-02 1.5E-02 2.3E-02 2.3E-02 2.3E-02 2.3E-02 Leafy Vegetables 1.0E-04 1.3E-03 1.2E-03 7.8E-04 1.2E-03 1.2E-03 1.2E-03 1.2E-03 Milk 2.5E-03 1.7E-02 4.5E-02 9.9E-03 1.5E-02 1.5E-02 1.5E-02 1.5E-02 Meat & Poultry 1.3E-04 2.0E-03 1.3E-02 1.3E-03 1.8E-02 1.8E-02 1.8E-02 1.8E-02 Fish-1.0E-01 1.3E-01 3.1E-02 1.6E-02 1.4E-02 1.2E-03 2.2E-02 2.2E-02 Drinking-4.3E-03 2.9E-02 1.8E-01 1.6E-02 2.4E-02 2.3E-02 2.4E-02 2.4E-02 Shoreline Activities-6.4E-05 6.4E-05 6.4E-05 6.4E-05 6.4E-05 6.4E-05 7.5E-05 6.4E-05 TOTALS-1.1E-01 2.0E-01 3.0E-01 5.9E-02 7.8E-02 6.4E-02 8.6E-02 8.6E-02
(DRN 03-2065, R14)
WSES-FSAR-UNIT-3 TABLE 11.2-14 (Sheet 2 of 2)
Revision 14 (12/05)
AQUATIC EXPOSURE PATHWAYS (mrem/yr)
Pathway Bone Liver Thyroid Kidney Lung GI-LLI Skin Whole Body
(DRN 03-2065, R14)
Infant:
Irrigation-fruits & Vegetables
& Grain Leafy Vegetables Milk*
2.5E-03 1.7E-02 4.5E-02 9.9E-03 1.5E-02 1.5E-02 1.5E-02 1.5E-02 Meat & Poultry Fish Drinking 8.9E-03 4.7E-02 4.3E-01 1.6E-02 3.7E-02 3.6E-02 3.7E-02 3.7E-02 Shoreline Activities TOTALS-1.1E-02 6.4E-02 4.7E-01 2.5E-02 5.2E-02 5.1E-02 5.2E-02 5.2E-02 Assumed to be the same as Child.
(DRN 03-2065, R14)