L-2017-074, Redacted - St. Lucie, Unit 1, Updated Final Safety Analysis Report, Amendment No. 28, Chapter 11, Radioactive Waste Management System
Text
RADIOACTIVE WASTE MANAGEMENT SYSTEM CHAPTER 11 TABLE OF CONTENTS Section Title Page 11.1 SOURCE TERMS 11.1-1 11.1.1 FISSION PRODUCTS 11.1-1 11.1.2 CORROSION PRODUCTS 11.1-4 11.1.3 TRITIUM PRODUCTION 11.1-5 11.1.4 NITROGEN-16 PRODUCTION 11.1-6 11.1.5 FUEL EXPERIENCE 11.1-7 11.1.6 LEAKAGE SOURCES 11.1-7 11.1.7 REACTOR COOLANT ACTIVITY AT EPU CONDITIONS 11.1-7 REFERENCES 11.1-8 11.2 LIQUID WASTE SYSTEMS 11.2-1 11.2.1 DESIGN BASES 11.2-1 11.2.2 SYSTEM DESCRIPTION 11.2-2 11.2.2.1 Boron Recovery System (BRS) 11.2-2 11.2.2.2 Liquid Waste System 11.2-5 11.2.3 SYSTEM DESIGN 11.2-9 11.2.4 OPERATING PROCEDURES 11.2-10 11.2.4.1 Boron Recovery System 11.2-10 11.2.4.2 Liquid Waste System 11.2-11 11.2.5 PERFORMANCE TESTS 11.2-11 11.2.6 ESTIMATED RELEASES 11.2-12 11.2.7 RELEASE POINTS 11.2-12 11.2.8 DILUTION FACTORS 11.2-12 11.2.9 ESTIMATED DOSES 11.2-12 REFERENCES 11.2-14
11-i Amendment No. 26 (11/13)
CHAPTER 11 TABLE OF CONTENTS (Cont'd)
Section Title Page 11.6.1 EXPECTED BACKGROUND 11.6-1 11.6.2 CRITICAL PATHWAYS 11.6-1 11.6.3 SAM PLING MEDIA, LOCATIONS AND FREQUENCY 11.6-2 11.6.4 ANALYTICAL SENSITIVITY 11.6-2 11.6.5 DATA ANALYSIS AND PRESENTATION 11.6-3 11.6.6 PROGRAM STATISTICAL SENSITIVITY 11.6-3 11-iv Am. 3-7/85 RADIOACTIVE WASTE MANAGEMENT SYSTEM CHAPTER 11 LIST OF TABLES Table Title Page 11.1-1 Reactor Coolant Specific Activity 11.1-9 11-1-1A Reactor Coolant Specific Activity (EPU) 11.1.9a 11.1-2 Bases for Reactor Coolant Radioactivity 11.1-10 11.1-3 Crud Specific Activity-Operating Reactors 11.1-11 11.1-4 Long-Lived Isotopes in Crud 11.1-12 11.1-5 Long-Lived Crud Activity 11.1-12 11.1-6 Equilibrium Crud Film Thickness 11.1-13 11.1-7 Sources of Tritium Production 11.1-14 11.1-8 Nitrogen-16 Production Parameters 11.1-14 11.2-1 Sources and Volumes of Liquid Waste 11.2-15 11.2-2 Design Data for Boron Recovery System Components (Historical) 11.2-16 11.2-3 Boron Recovery System Process Flow Data (Historical) 11.2-18 11.2-4 Expected Filter and Ion Exchanger Performance (Historical) 11.2-20 11.2-5 Boron Recovery System Performance Data (Historical) 11.2-21 11.2-6 Boron Recovery System (BRS) Maximum Nuclide 11.2-22 Concentrations During Normal Operations (Historical)
11.2-7 Boron Recovery System (BRS) Maximum Nuclide 11.2-24 Concentrations During Anticipated Operations (Historical) 11.2-8 Design Data for Liquid Waste System Components (Historical) 11.2-26 11.2-9 Liquid Waste System Pressure, Temperature 11.2-28 and Flow Data (Historical) 11.2-10 Liquid Waste System Expected Performance (Historical) 11.2-30 11.2-11 Deleted 11.2-12 Deleted 11.2-13 Assumptions Used in Calculating Estimated Normal 11.2-35 and Anticipated Operational Occurrence Releases
11-v Amendment No. 26 (11/13)
CHAPTER 11 LIST OF TABLES (Cont'd)
Table Title Page 11.5-7 Estimated Activity on Filter Cartridges After Decay (Historical) 11.5-16 11.5-8 Design Data for Solid Waste System Components 11.5-17 11.6-1 Practical Reporting Limits 11.6-5
11-vii Amendment No. 26 (11/13)
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- 11. 1-1 St. Lucie Plant
The boric acid concentrator is designed to concentrate a dilute solution of boric acid (30 to 1720 ppm) to 10,900 to 21,000 ppm. The resultant condensate (distillate) has a maximum boron concentration of 10 ppm.The major components of the boric acid and waste concentrators are: the concentrator, vapor separator, feed preheater, vapor condenser, distillate cooler, concentrate cooler, and pumps as shown of Figures 11.2-2 and 11.2-4A.
When the boric acid concentrator is in use, the preheated boric acid solution is piped into the lower shell of the concentrator. Low pressure heating steam in the concentrator upper shell heats the boric
acid solution to boiling. The water vapor along with remaining liquid rises through the tubes, into the
steam chest and then out of the concentrator.
The vapor in the tubes causes a natural circulation upward at a flow rate of many times the boric acid feed rate. The entire volume of liquid slowly rises in concentration as water is boiled off and more solids
enter with the feed boric acid solution until the desired concentration rate is reached. The concentrate
fluid is pumped out of the concentrator into the boric acid holding tank at a rate that maintains the
desired concentration.
In the vapor separator, the distillate is sprayed over the demisters to wash the vapors free of boric acid.
Two stage vapor washing in the vapor separator is necessary to lower the boric acid content of the distillate below 10 ppm.
The distillate vapors are condensed in the vapor condenser and a distillate is formed which is pumped out of the system after being cooled by the distillate cooler.
The hot boric acid concentrate from the concentrator is pumped through the concentrate cooler and is cooled to the design temperature.
The bottoms from each boric acid concentrator are pumped via the boric acid discharge strainer to the boric acid holding tank for temporary storage and sampling. The recovered boric acid may then be
returned to the makeup tanks
.The concentrator distillate passes through the boric acid condensate ion exchangers to remove boron
carryover and into one of the two boric acid condensate tanks. While one boric acid condensate tank is
filling, the other is sampled and recycled to the primary water tank. In the event that the contents of the
tank do not meet the chemical or radioactivity limitations, the contents can be recycled to the holdup
tanks for further processing, recycled through the boric acid condensate ion exchanger or drained to the
liquid waste system.
A local high and low water level alarm is provided on the boric acid condensate tanks. The boric acid condensate pumps automatically stop on low water level in the tanks.
The liquid waste is pumped through a waste ion exchanger and then to the Waste Monitor Tanks. The waste can then be pumped to the circulating water discharge for release or returned to the aerated
waste storage tank for reprocessing if the activity is too high.
11.2-4 Amendment No. 17 (10/99)
Low activity, aerated, and potentially dirty liquid drains and building sumps discharge to the chemical and equipment drain tanks. Low activity chemical drains from the sampling system, decontamination
drains, and chemical laboratory drains flow to the chemical drain tank or to local drums. When a
sufficient volume is collected in the drain tanks, the contents are pumped to the Aerated Waste Storage
Tank (AWST). From the AWST, liquid wastes are normally processed through two to four waste ion
exchangers, depending on waste chemistry and activity. These ion exchangers can be operated in
series, parallel or a combination of the two. The ion exchanger vessels can contain mixed bed, cation, anionic resins, or and/or activated carbon or other filter media. Typically, the liquid waste is processed
through two mixed bed ion exchangers in series, holding the other two in reserve.
The waste ion exchangers discharge to the Waste Monitor Tanks (WMT's). After a sample analysis has determined that the radioactivity of the WMT contents is within the discharge limit, the WMT is emptied at a controlled rate into the condenser water discharge. The radioactivity of the dischage is continuously monitored and recorded. Should the high set point of the monitor be exceeded, WMT
release is automatically terminated.
In the event that discharge criteria are not met, the contents of the WMT are pumped back to the AWST for reprocessing through the waste ion exchangers
.NOTE: The information that follows in this subsection about the waste concen trator is maintained here for historical purposes only. The concentrator and supporting equipment are no longer used
.The major components of the waste concentrator are: the concentrator, vapor separator, vapor
condenser and sub cooler, concentrate cooler and pumps
.Liquid waste containing dissolved solids and/or radioactive nuclides are collected in the aerated waste
storage tank and are passed through a waste filter prior to entering the lower shell of the concentrator.
Low pressure steam heats the waste solution in the concentrator causing water vapor and liquid waste
solution to rise through the tubes into the steam chest and then out of the concentrator into the vapor
separator. In the vapor separator, recycled distillate is sprayed over the demisters to scrub boric acid from the 11.2-6 Amendment No. 17 (10/99) water vapor. Two water vapor scrub stages are necessary to lower the boric acid concentration in the distillate to less than 10 ppm. The water vapor is then condensed in the vapor condenser and cooled by the distillate cooler. Approximately half of the condensed water vapor (distillate) is used for the boric
acid scrub stages in the vapor separator. The balance is either collected in the waste condensate. tank
and then pumped to WMT's through the waste ion exchangers or directly to the WMT's via the ion exchangers.
After the sample analysis has determined that the radioactivity of a WMT is within the discharge limit, the contents are pumped at a controlled rate into the condenser water discharge. The radioactivity of
the discharge is continuously monitored and recorded. Should the high set point of the monitor be
exceeded, the release is automatically terminated.
In the event that discharge criteria are not met, the waste is circulated through the waste ion exchanger and returned to the waste monitor tank for re-analysis. If the discharge criteria cannot be obtained by
the waste ion exchanger, the waste may be processed via the waste concentrator. Should the volume
of liquid wastes exceed the capacity of the waste concentrator, the boric acid concentrator(s) could be
used as a waste evaporator.
The laundry wastes are collected in the laundry drain tank and are analyzed for radioactivity. If the
radioactivity is within the established discharge limit, the laundry wastes are pumped from the tanks
through a cartridge filter into the WMT's. Should the radioactivity exceed the established discharge limits, the laundry wastes are processed.
All tanks are equipped with water level instrumentation alarms and their respective pumps are tripped automatically on low level signals.
All piping 21/2 inches and smaller is field run. Line sizes are shown on Figure 11.2-4.
11.2-7 Amendment No. 17 (10/99)
where: A i sg= the total activity of isotope i in the steam generator liquid at time t , µCi.Q i=the steam generator leak rate for isotope i, µCi/sec F c=condensate flow rate, condenser volume/sec A i C=condenser condensate activity of isotope i at time t, µCi!i= decay constant for the i th isotope, sec
-1B= steam generator blowdown rate, vol/sec F sg= steam generator flow rate, vol/sec PF i 1=steam generator partition factor for the i th isotope.L T=the turbine system leakage rate, vol/sec A i T=activity in turbine steam for isotope i at time t, µCi F T=turbine flow rate, vol/sec PF i 2=condenser partition factor for isotope iThe above equations were solved for the equilibrium values of A i A i T and A i sg The turbine systemvolume for this analysis includes the steam generator steam space, piping between the steamgenerator and turbine steam space, and condenser steam space. Condenser activity is based on the condensate volume in the hotwell and the piping between the hotwell and steam generator. Steam generator activity is based on the liquid inventory of the steam generator.11.2.3 SYSTEM DESIGN The liquid waste system is designed on a batch mode basis for flexibility of operation. These batchingoperations proceed intermittently at faster flow rates than the annual average process rates and therefore the system components are sized per this criteria. Tables 11.2-2 and 11.2-8 list the design parameters for the major components of the liquid waste system.Process and radiation instrumentation are depicted in Figures 11.2-1, 11.2-3, and 11.2-4 and aredescribed in Table 11.2-16.11.2-9 11.2.4 OPERATING PROCEDURES 11.2.4.1 Boron Recovery System Operating procedures for the boron recovery system are written to logically reflect the different monitoring and operating functions required of t h e plant operators. Procedures include the following.
a)P rocedures for the initial valve lineup to the holdup tanks and to the flash tank when RCS activity is high
.b)M onitoring requirements of reactor drain tank operations and procedures for processing the tank contents directly to a holdup tank, bypassing the flash tank
.c)M onitoring and actions to be taken in the event of flash tank bypass operation to avoid explosive mixtures of hydrogen and air in the holdup tanks
.d)M onitoring requirements for the conditions of the four holdup tanks and processing requirements for chemical and radioactivity sample analysis
.e)P rocedures and valve lineups for processing a holdup tank contents through a preconcentrator filter and ion exchanger back to the same or different tank and processing sampling
requirements
.f)M onitoring requirements for the condensate tanks conditions and procedures for valve lineups.
Sampling and reprocessing procedures.
g)O perating procedures for the environmental discharge instrumentation and valves. The method for determining the discharge flow rate in terms of radioactivity discharge limits.
11.2-10 Amendment No. 17 (10/99) 11.2.4.2 Liquid Waste System Operating procedures for the liquid waste system include the following:
a)procedures for equipment drain tank and aerated waste storage tank influent valve lineups, monitoring tank conditions sampling, and waste discharge
.b)procedures for chemical drain tank influent valve lineups, monitoring tank conditions, and
sampling.c)procedures for laundry tank influent valve lineups, monitoring tank conditions, sampling, and
valve lineup for discharge
.d)procedure for waste ion exchanger system valve lineups, operation, monitoring and sampling.
e)procedu res for monitoring requirements for waste condensate tank conditions, valve lineups, sampling, and reprocessing. Discharge is done under the same procedure used for the boron
recovery system.
11.2.5 PERFORMANCE TESTS The boron recovery and liquid waste systems we re tested prior to initial power plant start up to verify satisfactory flow characteristics through the equipment, to demonstrate satisfactory performance of
pumps and instruments, to check for leak tightness of piping and equipment, and to verify proper
operation controls. All piping and components we re checked to ensure that they are properly installed.
All manual and automatic valves we re operated and checked for functionability. All alarms we re checked for operability and verification of locations. The concentrators we re tested for operation before installation at the site and after installation to assure proper integration with the system. The boric acid
and waste concentrators we re shop tested prior to shipment to demonstrate compliance with performance objectives. During hot functional testing, the boron recovery system operation wa s integrated with the chemical and volume control system. The purpose of this test wa s to check the procedures and system components used for receiving and processing waste water. Boric acid transfer
operations and waste liquid disposal procedures we re tested.
During normal plant operation, periodic testing as described below, verifies that the system components are operating as designed.
Filters are monitored for differential pressure and radiation level on a regular basis.
Ion exchangers are monitored for 11.2-11 Amendment No. 17 (10/99)
TABLE 11.2-16 (Cont'd)
Indication AlarmNormalSystem ParameterContrInst.OperatingInstr.
and Location
Local Room High Low Rec 1 Control Function Range 4 Range Accuracy 4Holdup Drain Pumps
- 20-60 psigDischarge PressureBoric Acid Condensate Pumps 5*60 psigDischarge PressureEquipment Drain Pump
- 60 psigDischarge PressureChemical Drain Pump
- 0-60 psigDischarge PressureLaundry Drain Pumps**0-60 psigDischarge PressureWaste Condensate Pumps
- 0-60 psigDischarge PressureResin Dewatering Pump 5*0-60 psigDischarge PressureWaste Gas Compressors
- 0-165 psigDischarge PressureWaste Gas Discharge
- 0-15 psigPressureNitrogen Supply Press.
- 150-240 psigHydrogen Supply Press.
- 90-110 psig 11.2-47Amendment No. 18 (04/01)
TABLE 11.2-16 (Cont'd.)
Indication AlarmNormalSystem ParameterContrOperatingInstr.
and Location
Local Room High Low Rec 1 Control Function
Inst. Range 4 Range Accuracy 4Waste Condensate Tanks**2*2Waste Condensate PumpsLevelsEquipment Drain Tank Level**2*2Equipment Drain Pump 1AAerated Waste Storage Tank**2*2Equipment Drain Pumps 1B & 1CLevelChemical Drain Tank Level**2*2Chemical Drain PumpLaundry Drain Tanks Levels**2*2Laundry Drain PumpSpent Resin Tank Level
- 2Gas Surge Tank Level
- Flash Tank N 2 Supply Flow*
1.5 scfmFlash Tank Flow
- Flash Tank Pumps, N 2 Supply Flow
Sluicing Water Flow
- 0-100 gpmLiquid Waste Discharge Flow
- Liquid Waste Dischg. Isolation and 10-50 gpmFlow Control ValvesWaste Gas Discharge Flow**
- .5-2.0 scfm 11.2-49Amendment No. 18 (04/01)
TABLE 11.2-16 (Cont'd.)WASTE MANAGEMENT SYSTEM INSTRUMENTATION APPLICATION Indication
AlarmNormalSystem ParameterContrOperatingInstr.
and Location
Local Room High Low Rec 1 Control Function
Inst. Range 4 Range Accuracy 4Liquid Waste Dischg. (WMT) Radiation****Liquid Waste Dischg. Isolation Valves VariableMonitorWaste Gas Dischg. Radiation Monitor***Waste Gas Dischg. Isolation Valves VariableBoric Acid Concentrator 1A Pkg.
5 Alarms**3-Boric Acid Concentrator 1B Pkg.
5 Alarms**3-Radioactive Waste Concentrator Pkg.
5**3-AlarmsWaste Management System Annunciator*
- 3-PanelGas Analyzer
- 3-Equipment Drain Tank Differential Pres.*
- 2Waste Monitor Tank Level
- 2*Waste Monitor Pump 1A & 1B; Drain &Condensate PumpsWaste Monitor Tank Pump Dischg. Pres.*
0-60 psigWMT Strainer Delta P
- --------_______________1All alarm and recorders are in the control room unless otherwise indicated.
2Alarmed on local Waste Management System annunciator panel.
3Master alarm annunciated in control room for any individual system alarm condition.
4 Instrument ranges are selected in accordance with standard engineering practices. Instrument accuracies are selected such that existing instrument loop performance andsafety analysis assumptions remain valid. Where applicable, instrument accuracies are also evaluated for their impact on setpoints in accordance with the FPL SetpointMethodology.5 These components are no longer used.
11.2-50Amendment No. 18 (04/01)
FLORIDA POWER & LIGHT COMPANYFLOW DIAGRAM WASTE MANAGEMENT SYSTEMAmendment No. 16, (1/98)
FLORIDA POWER & LIGHT COMPANYFLOW DIAGRAM WASTE MANAGEMENT SYSTEMAmendment No. 16, (1/98)
FLORIDA POWER & LIGHT COMPANYFLOW DIAGRAM WASTE MANAGEMENT SYSTEMAmendment No. 16, (1/98)
FLORIDA POWER & LIGHT COMPANYBORIC ACID CONCENTRATOR-PIPING AND INSTRUMENTATIONAmendment No. 15, (1/97)
I/ ct_ OF OCEAN I TO YI I I -. -jl TO DISCHARGE CANAL EL *. 1'6" .........
......__ _
SEAL WELL I 3"
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STEAM 3" WMS PIPING DUMP EXHAUST----+-------------.
TURB. GEN. BLDG. STEAM JET EJECTOR CONTROL ROOM AIR INLET DAMPERS EL. 78' 9" Amendment No. 18, (04/01) NOTE: NOT TO SCALE 8 FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 PLANT LIQUID AND GASEOUS RELEASE POINTS FIGURE 11.2-5
Waste gas is collected from the various source components by three headers; containment vent header, gas surge header, and gas collection header. The containment vent header receives hydrogenated
potentially radioactive gas mixtures vented from the reactor drain tank, quench tank, refueling failed fuel
detector vent, and reactor vessel head vent within the containment and directs the gases to the gas
surge header. Hydrogenated and potentially radioactive gases vented from the volume control tank, flash
tank, and boric acid concentrators in the reactor auxiliary building are also directed to the gas surge
header along with the discharge gas from the gas analyzer. The vented gases flow to the surge tank
where they are collected prior to being monitored for activity and released or compressed and sent to
the Gaseous Radwaste Treatment System. If waste gases are entering the Gaseous Radwaste Treatment System they will remain in the surge tank until removed by the waste gas compressors.
These compressors are automatically controlled by pressure instrumentation located on the surge tank.
The surge tank is equipped with a drain line to remove any water that accumulates in the tank due to
condensation. A level switch with a local alarm is on the surge tank and indicates to the operator when
the drain trap is not functioning properly if continuously aligned
.Since the contents of the surge tank are expected to contain significant amounts of hydrogen, the gas
stored in the surge tank is sampled frequently by the gas analyzer to determine the oxygen content of
the tank. A nitrogen line connected to the surge tank and a pressure regulating valve in the line opens
when pressure in the tank falls below 1.5 psig thereby maintaining a positive pressure above
atmospheric and preventing air ingress.
Waste gas requiring holdup prior to release flows from the gas surge tank to a compressor where it is compressed to 165 psig and cooled by an aftercooler prior to entering the gas decay tanks. Holdup in these tanks permits additional radioactive decay. Chemistry procedures contain guidelines which are used to determine whether radioactive gaseous effluent requires holdup prior to release. Two
compressors are available for transferring the gas to the gas decay tanks and are controlled by pressure
instrumentation on the surge tank. One compressor starts when pressure in surge tank increases to 3
psig and stops when pressure falls to 1.5 psig. The second compressor starts at 7 psig and stops at 5
psig.Aftercoolers supplied with each gas compressor cool the compressed gas prior to entering the gas decay tanks. There are three gas decay tanks (each provided with a pressure indicator including local
alarm and temperature indicator) which receive the compressed gas from the waste gas compressors.
The decay tanks have sufficient storage capacity for an average 30 day holdup, and after radioactivity
has decayed to an acceptable level consistent with the design objective and has been verified by
laboratory sample analysis, the gas is released to the environment via the plant vent at a controlled rate.
The fill procedure for the decay tanks is to have only one tank lined up to the compressor discharge.
When the pressure in the tank increases to 165 psig the tank is isolated and manually switched over to
an empty tank. The gaseous radioactivity in the filled isolated tank is allowed to decay until release can
be made within the established limits. During this decay period the gas is periodically sampled and
activity level determined. The sampling technique used prior to release of gas and the continuous
monitoring systems are further discussed in Section 11.4.3.
11.3-2 Amendment No. 18, (04/01)
Extra margin is also available in the overall holdup time in that gas production generally increases exponentially with core life because of boron dilution waste. For end of core cycle operation, sufficient
gas decay tank capacity for 30 day holdup is provided assuming the following conservative operational
conditions:
a.Boron dilution wastes are eliminate d by use of the Chemical and Volume Control System ion exchanger(s) at approximately 97 percent core life.
b.220 gpd reactor coolant leakage to the reactor drain tank.
c.Cold shutdown and startup at 90 percent life.
11.3-4 Amendment No. 17 (10/99)
The following components are located in the discharge line from the gas decay tanks to the vent pipe; a pressure reducing valve, pressure indicator, needle valve, pneumatic operated fail closed on-off valve, an
in-line radiation monitor, and a gas flow meter.
Prior to release, the required flow rate is determined, and the set point on the radiation monitor established. Initially the discharge valve from the gas decay tank, needle valve, and pneumatic operated
valve are closed. The on-off pneumatic operated valve is opened and placed in automatic, and the
discharge valve on the desired gas decay tanks is opened. The pressure reducing valve automatically
closes when pressure from the decay tank in excess of 10 psig is sensed at the pressure reducing valve
outlet. The needle valve is then opened as required to establish the desired flow rate to the vent pipe, and the pressure reducing valve opens to maintain constant downstream pressure of 10 psig. The on-off
pneumatic operated valve automatically closes on high radioactivity level thus terminating discharge
flow. An alarm will annunciate this event in the control room. When discharge flow decreases and the
decay tank pressure decreases to approximately 10 psig, as noted by observing the gas flow meter and
pressure indicator on the gas tank, the pressure reducing valve set point must be reduced to vent the
tank down to atmospheric pressure.
The system flow paths and release points of the gases from the gas decay tanks and gas collection header are indicated on Figure 11.3-1. The diagram also shows the only flow bypass line in the waste
gas system. This line from the gas surge tank to the vent pipe bypasses the waste gas compressor and
gas decay tanks. This path is used to bypass compressors and gas decay tanks when Chemistry guidelines determine that holdup of gaseous effluent is not required prior to release, or when air or nitrogen is purged from process equipment after initial plant startup or for maintenance operations.
A locked closed valve facilitates administrative control of this bypass line.
The waste gas system has connections for sampling the gas in the containment vent header, gas surge tank, and each gas decay tank. The gas to the gas surge header is primarily hydrogen and a gas
analyzer located in the sampling system is used to monitor the oxygen concentration. Connections are
available in the sampling system as outlined in Section 11.4.3 for taking a grab sample via gas analyzer
to determine activity level prior to release.
The gas collection header collects the gases from primarily aerated vents of process equipment in the waste management system, chemical and volume control system, and fuel pool system. A listing of
sources is given in Table 11.3-3. Because of the large volume of gas and the low activity level from the
sources, the gases are routed directly to the vent pipe. The gases and expected activities to the vent
pipe from the gas collection header are given in Table 11.3-1 at process data point No. 12. As a further
check on activity from this source the vent pipe contains radioactivity monitors with alarms to indicate
unexpected activity release.
11.3-5 Amendment 15, (1/97)
The hydrogen and nitrogen required for plant operations are also a part of this system and redundant supply headers for each gas are provided. Hydrogen gas is supplied to the volume control tank gas
space to maintain the desired concentration of reactor coolant dissolved hydrogen to suppress the net
decomposition of water in the reactor. Nitrogen cover and/or purge gas is provided to the holdup tanks, quench tank, reactor drain tank, safety injection tanks, spent resin tank, and gas surge tank. A
nitrogen stream is supplied to the flash tank for degassing liquid waste when the flash tank is operated
, and periodic purges with nitrogen are provided as required for various waste management system and
chemical and volume control system components. The two gas supply systems include relief valves, regulators, and instrumentation with alarms and valving to allow flexible operation. A low pressure alarm indicates when the backup source should be placed in service.
The design criteria and controls for limiting radiation exposure of personnel from lines which normally carry radioactive fluids are described in Sections 12.1.3 and 12.1.5.
11.3.3 SYSTEM DESIGN The Gaseous Radwaste Treatment System is designed on a batch mode basis for flexibility of operation. These batching operations proceed intermittently at faster flow rates than the annual average process rates and therefore the system components are sized accordingly. Table 11.3-2 lists the
design parameters for the major components of this system.
Process and radiation instrumentation are depicted in Figure 11.3-1 and are described in Table 11.2-16.
An accident analysis for the waste gas decay tanks is presented in Section 15.4.2.
11.3-6 Amendment No. 17 (10/99) 11.3.4 OPERATING PROCEDURE The Gaseous Radwaste Treatment System operating procedures include the following:
a)tank purging and venting procedures for all tanks venting to the waste gas system and for the tanks in the waste gas system
- b)gas surge tank to gas decay tank valve and compresso r lineup procedures, requirements for monitoring proper automatic operation of the gas compressors, procedures for servicing the
compressors, filters, and after coolers
- c)procedures for isolating a gas decay tank after filling and for monitoring the contents during the decay period
- d)procedures for setting the high trip set point on the discharge radiation monitor, for lining up the
valves for discharge, and for determining the discharge flow rate and establishing it, monitoring
requirements during the discharge period, procedure to reduce gas decay tank pressure to
atmospheric at the end of the discharge period
- e)procedures for draining water from the gas surge tank and the gas decay tanks
- f)procedures for valve lineup, and establishing regulato r set points and criteria for changing hydrogen gas cylinder s;g)procedures for valve lineup and establishing regulator set points and criteria for changing
nitrogen gas cylinder
- and h)procedures for gas analyzer manual and automatic control of sample point selection, procedures for obtaining a gas sample in the sampling cylinder for laboratory analysis and for
setting the sequential timer and for calibrating the gas analyzers to assure representative
automatic sampling.
11.3-7 Am endment No. 16, (1/98) 11.3.5 PERFORMANCE TESTS The gas compressors including suction filter and discharge aftercooler are shop tested to assure proper operation. The gas analyzer system is shop tested.
The system preoperational tests are as follows:
a)instrumentation is checked for accuracy of readout and control and alarm set points; b)control valves are checked for proper operation and relief and pressure regulation valve set points are confirmed; c)operation of the entire system is checked by supplying nitrogen from various points such as the
reactor drain tank and flash tank. Proper automatic operation of the compressors and
controllability of discharge flow rate is verified; and d)leak testing is done to assure negligible leakage.
During plant operation, periodic testing is done as follows:
a)the discharge radiation monitor is periodically calibrated with standard radiation source; b)the gas analyzers are periodically calibrated with zero and upscale gases; and c)process instrumentati on is periodically calibrated.
11.3.6 ESTIMATED RELEASES The gaseous releases have been calculated in consideration of the guidance provided by Regulatory Guide 1.42 (RG 1.42), "Interim Licensing Policy on as Low as Practicable for Gaseous Radioiodine
Releases from Light-Water-Cooled Nuclear Power Reactors" (June 1973). The interim policy
calculational methodology recommends an assumed failed fuel rate of 0.25 percent. Over the operating
lifetime of this reactor, it is expected that failed fuel rates of 0.1% or less will predominate (see Section
11.1.5). Thus, average annual releases anticipated over the lifetime of the plant will be lower than those
calculated by RG 1.42 methods by the ratio of the failed fuel rates (1/2.5). Likewise, releases during anticipated normal occurrences (1.0 percent) will be higher by the ratio of the failed fuel rates (10/2.5).
Gaseous releases based on RG 1.42 recommendations are provided in Table 11.3-4. The analysis assumed a steam generator blowdown rate per RG 1.42 of about 18 gpm and a cold water iodine partition factor of 10
-4.11.3-8 Amendment No. 16, (1/98)
TABLE 11.3-2 COMPONENT DATA (1)1. Waste Gas Compressor Type Diaphragm Positive Displacement Quantity 2 Capacity, SCFM 2 Discharge Pressure, psig 0-165 Codes ASME P&V III for Nuclear Power Nov.
1968 ASME Power Test Code PTC-9
Displacement Compresso rs, Vacuum Pumps and Blowers.
Materials Carbon Steel Design Temperature, F 150 - Inlet; 350 - Outlet Design Pressure, psig 200 2. Compressor Aftercooler Type Tube in Tube Quantity Codes: Gas Side ASME Boiler and Pressure Vessel Code 1968 Section III Unfired Pressure Vessels, Class C Water Side Section VIII of above code Materials Carbon Steel Discharge Temperature, F 110 3. Compressor Inlet Filter Type Stainless Steel Screen Quantity 2 Rating 5 micron Clean Pressure Drop, psi @ 2 CFM 0.3 Code ASME Boiler and Pressure Vessel
Code 1968 Section III
Unfired Vessels, Class C 11.3-14 Amendment No. 18, (04/01)
TABLE 11.3-2 (Cont'd)
- 4. Gas Surge Tank Type Vertical Quantity 1 Volume, ft 3 9 Design Pressure, psig 40 Design Temperature, F 200 Code ASME Boiler and Pressure Vessel Code 1968,Section III, Class C Material Carbon Steel
- 5. Gas Decay Tank Type Vertical Quantity 3 Volume, each, ft 3 144 Design Pressure, psig 190 Design Temperature, F 250 Codes ASME Boiler and Pressure Vessel Code 1968,Section III, Class C Material Carbon Steel
_________(1) Original procurement information 11.3-15 Amendment No. 18, (04/01)
TABLE 11.3-3 GAS COLLECTION HEADER SOURCE POINTS 1.Preconcentrator ion exchanger vent 2.Holdup tank vent 3.Boric acid condensate ion exchanger vent
- 4.Boric acid holding tank vent
- 5.Boric acid condensate tank vents
- 6.Waste ion exchanger 7.Equipment drain tank vent 8.Chemical drain tank vent 9.Laundry drain tank ve nts 10.Waste condensate tank vents 11.Spent resin tank vent 12.Waste concentrator vent
- 13.CVCS ion exchanger vents 14.Fuel pool system ion exchanger vent 15.Boric acid makeup tank vents 16.Charging pump vents
- 17. Boric acid makeup pump vents (c apped per PC/M 86150)
- 18. Aerated water storage tank vent
- 19. Resin dewatering pump vent
- 20. Seal lube water tank vent
- 21. Post-accident sampling vent
- Note: These components are no longer used and vents have been isolated.
11.3-16 Amendment No. 17 (10/99)
FLORIDA POWER & LIGHT COMPANYFLOW DIAGRAM WASTE MANAGEMENT SYSTEMAmendment No. 16, (1/98)
- aTOAllT
- HUTCHINSON ISLAND ZONING MAP Dmt.All lrt!ll r21:;, SOHH *H* DWULIH coo* CLAlllFICATIC*
V*ITI *** ac ..
llH
- roar Plaaca &'IUlll'IC OCUI E::::J *-1 u Note: Kiatorical Information A*l(***P9r*
.. *t ll c=J *-l l J
u*
- JI fer let*l*
- l*\*1* PlO't!DA POWU & lla4T COMPN<< If. &.UOI f'\.AMT UMtT l lllTTCll I llSOll 111.A.Q IOlllllC MAI flCURE 11. J-J Amendment 15, (1/97)
,l'1 '1 FLORIDA POWER 6 LIGHT COMPANY ST. LUCIE PLANT UNIT 1 PLANT LOCATION -5 MILE RADIUS FIGURE 11.3-3 SEPT. 1973 C\I fl) w .J 2 !: w .J "' u NII fl) ::::: 0
TABLE 11.4-1PROCESS RADIATION MONITORS Maximum AreaMinimumRadiationMonitorType DetectorSensitivity**IsotopeRangeLevel DetectorRemarksChemical andGamma Scint-10
-4 µCi/ccI-13510-4 to 10 2 µCi/cc5 mR/hr gammaThe setpoint can be adjustedVolume Controlillation crystalCo-60 as operations dictateSystem Processwith photomulti-Radiation plier tubeMonitor preamplifierWasteGamma Scint-1 x 10
-7 µCi/ccCs-13710-7 to 10-2 µCi/cc0.1 mR/hr gammaThe monitor is adjusted to aManagementillation crystalCo-60setpoint following anSystem Liquidwith photo-isotopic analysis of the Effluent multiplier tubeliquid waste to be discharged.
and integralThe monitor will verify the preamplifieranalysis by alarming should the discharge activity exceed the predetermined value.WasteBeta Scintillation2 x 10
-5 µCi/ccXe-13310-5 to 10+3 µCi/cc0.1 mR/hr gammaThe monitor is adjusted to aManagementDetectorCo-60setpoint following anSystem Gaseousisotopic analysis of the Effluent gas to be discharged.
The monitor will verify the analysis by alarming should the discharge activity exceed the predetermined value.
SteamGamma1 x 10-6 µCi/ccCs-13710-6 to 10-1 µCi/cc0.1 mR/hr gammaThe monitors are adjusted to aGenerator ScintillationCo-60setpoint following anBlowdownCrystal withisotopic analysis of liquid Photomultiplierphase of the secondary sideTube and Integral of the steam generator PreamplifierCondenser! Scintillation9 x 10-5 µCi/ccXe-1319(10
-5 ) to 4.5(10
-2)0.1 mR/hr *AirCrystalµCi/ccEjectorComponent" Scintillation1 x 10-7 µCi/ccCs-13710-7 to 10-2 1.0 mR/hr *Cooling WaterCrystalµCi/cc* Normally clean systems. If leakage across system heat exchangers occurs, setpoints are adjusted in order to provide early not ification of leakage.**Note:Minimum sensitivities based on purchase specification values. Radiation monitor performance is equal to or better than purchase specification value.
11.4-17Amendment No. 18, (04/01)
TABLE 11.4-2A SAMPLE LOCATIONS AND ANALYSES - MONITORING OF LIQUID & GASEOUS BATCH RELEASES EFFLUENTS Refer to Offsite Dose Calculation Manual (ODCM) Chemistry Operating Procedure No.
C-200.11.4-18 Amendmen t 15, (1/97)
TABLE 11.4-2B SAMPLE LOCATIONS AND ANALYSES Location Analysis Preconcentrator Filters Isotopic or Gross Activity Preconcentrator Ion Exchangers Isotopic or Gross Activity Boric Acid Concentrator Bottoms Isotopic or Gross Activity and Distillate
- Boric Acid Condensate Ion Exchangers
- Isotopic or Gross Activity Waste Filter Isotopic or Gross Activity Waste Ion Exchanger Isotopic or Gross Activity Waste Concentrator Bottoms and Isotopic or Gross Activity Distillate
- Flash Tank Isotopic or Gross Activity Equipment Drain Tank Isotopic or Cross Activity Chemical Drain Tank Isotopic or Gross Activity Holdup Tanks Isotopic or Gross Activity
- Note: These components are not sampled since they are no longer us ed.11.4-19 Amendment No. 17 (10/99)
TABLE 11.4-3 NOBLE GAS EFFLUENT RADIATION MONITORS CONFORMANCE WITH TMI RELATED CRITERIA Criteria Safety Evaluation - Remarks Reference Monitoring of potential The plant stack, ECCS, and Fuel Position, pathways for noble gas Handling Building monitors have Clarification #1, releases and iodine and filtering for iodines and particulates Table II.F.1-1 particulate releases and high range (10 5 µCi/cc) for the Position, Changes noble gases. The nozzle orifice
- 4, #3, Clarification size and sample flow rate were
- 1, #3, Table II.F.
originally selected to provide an 1-2 isokinetic sample velocity. However as discussed in Safety Eva luation PSL-ENG-SENS-00-108, an isokinetic sample velocity is not necessary to achieve representative sampling in this application.
Range of noble gas All noble gas ranges are 10 5 Position, monitors exceeds accident
µCi/cc, in excess of requ ire-Clarification #2, release ments. Expected maximum
- 4, Table II.F.1-1 release is less than 10 3 µCi/cc.Effluent range overlaps All monitors cover from ALARA Position, with normal range to µCi/cc of noble gases.
Clarification #4,, Table II.F.
1-1 11.4-20 Amendment No. 18, (04/01)
DCS/ERDADS DETECTOR ATMOSPHERIC STEAM DUMP EXHAUST DATA ACOUISITION DETECTOR MODULE ECCS EXHAUST DETECTOR TRAIN A LOCAL PROCESSOR ECCS EXHAUST DETECTOR TRAINS LOCAL PROCESSOR DETECTOR FHB STACK LOCAL RAD PROCESSOR MON P NL PLANT V ENT DETECTOR STACK COMMUNICATION UNE ISOLATOR COMMUNICATION UNE ISOLATOR COMMUNICATION UNE ISOLATOR COMMUNICATION UNE ISOLATOR COMMUNICATION UNE ISOLATOR COMMUNICATION UNE ISOLATOR CONTROL CONTROL ROOM ROOM TERMINAL TERMINAL NUMBER 1 NUMBER2 RAD MONPNL CONTROL ROOM D CS/ERDADS REMOTE D ISP LA Y UNITS FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 NOBL E GAS EFF LUENT RADIATION MONITORING SYSTEM BLOCK DIAGRAM FIGURE 11.4-1 Amendment No. 28 (05/17)
- *
- MONITOR MAIN STEAM LINE -1 A -EL 18 -EL INSULATION FLORIDA POWER & LIGHT COMPANY ST. LUCIE PLANT UNIT 1 EXTERNALLY MOUNTED ATMOSPHERIC STEAM DUMP EXHAUST MONITOR FIGURE 11.4-2
11.5.2SYSTEM DESCRIPTIONThe solid waste system processes radioactive waste in the form of ion exchangers resins and filters,compressible and non-compressible solids. Ion exchanger resins are sluiced into the spent resin tankor shipping container, and dewatered in accordance with plant procedures. Filters are moved fromtheir vessels into shipping containers. Compressible waste is compacted by a compactor locatedinside the drumming station or shipped sorted, uncompacted to an offsite radioactive waste volumereduction facility for processing. Non-compressible waste is packaged in boxes or bags. All of thesewastes are packaged and shipped offsite in accordance with plant procedures.A portable dewatering system is used when processing and packaging wet radioactive resin wastes.11.5-2Amendment No. 17 (10/99)
Filter vessels used in removing particulates from process streams are installed behind labyrinthedconcrete cubicles roofed over by a concrete slab, except for the laundry filter which is not expected to have high levels of radioactivity. The roof slab is fitted with a removable concrete hatch. Holes in the hatch permit long handled tools to operate valves for draining vessel and to undo head bolt nuts to permit vessel head to swing open in a vertical arc. A monorail system above the cubicle roof allows for removing the hatch and setting it aside. Filters of high activity levels require a shielding device simulating an inverted bell to be positioned over the opened hatch. A winch device and appropriate opening allow the filter cartridge to be withdrawn from the filter vessel and into the cartridge (inverted bell) shield. The cartridge shield is placed on a transport device and removed to the drumming area where the cartridge will be prepared for disposal.Low level activity cartridges may be removed without the use of a cartridge shield. Upon removalthrough the hatch it would be deposited in a shipping container positioned to receive the filter. The container would then be removed to the drumming area for final preparation for disposal.The activity level on the filter elements is based on a conservatively high inlet concentration, themaximum removal for each nuclide and the expected flow rate through each unit. The purification filters 1A and 1B are each assumed to process 40 gpm in series (1A upstream and 1B downstream of ion exchangers) continuously over the entire core cycle. The fuel pool purification filter is assumed to remove the portion of reactor coolant system end of life activity which enters the fuel pool water, assuming complete mixing, after being diluted by the refueling water. A temporary portable filter/vacuum is also available to expedite outage activities and to help cleanup the fuel pool purification filter to improve water clarity. When depleted, filters can be remotely changed out while the unit remains underwater and stored in a remote floor mounted or hanging filter storage rack.The waste management system waste filter and the laundry filter are not expected to retain a significant amount of activity due to the very low concentration of activity in the inlet process fluid and the low quantity of liquid each unit must process. Each of the two preconcentrator filters are assumed to process one half of liquid waste processed by the boron recovery system. This waste is assumed to be reactor coolant which has been processed by the chemical and volume control system.The estimated activity on these filters after one core cycle with source activities equivalent to onepercent failed fuel is given in Table 11.5-6. These same filter activities after six months and one year decay are shown in Table 11.5-7. The total activity for a given filter may be divided between a number of cartridges that could be packaged separately. Packaging requirements for filter cartridges based on the activities of Table 11.5-7 are defined in Section 11.5.5.Miscellaneous compressible solid waste such as contaminated clothing, plastic sheeting, and tape,accumulated as a result of health physics and maintenance activities and non-compressible solid waste such as tools and contaminated equipment are stored in designated areas and then shipped offsite in accordance with plant procedures.Solidification of radioactive waste and processing of irradiated components are not activities routinelyperformed at the plant. However, if the need arises to perform these activities, plant procedures will be developed in accordance with Process Control Program requirements to ensure safety.11.5-4Amendment No. 21 (12/05) 11.5.3 EQUIPMENT DESCRIPTIONA data summary of the solid waste system components is given in Table 11.5-8.
The spent resin tank can hold the equivalent of approximately eight to ten beds of spent resin from thevarious plant ion exchangers, and therefore, storage capacity in excess of one year is normallyavailable. Higher activity resin will normally be sluiced to a shielded shipping container, but sluicing to shielded disposable container is also possible.To sluice resin from the spent resin tank, water from the holdup pumps or primary makeup waterenters the tank. The tank fills with water compressing any air in the tank forcing a water and resinslurry up the tank outlet line. The discharge pipe extends upward from near the tank bottom thus minimizing chances of resin binding while allowing efficient removal of nearly all the resin from the tank. A conductance type level sensor allows level to be monitored. The resin and water slurry enters the shipping container and the water is drawn off by a portable dewatering system. Ion exchangerresins can be sluiced into the spent resin tank or directly into a shipping container in accordance withplant procedures.Before sluicing resin from an ion exchanger to the spent resin tank, the tank is vented and partially drained of water into the ECCS pump room sump. After resin is sluiced in,11.5-5Amendment No. 17 (10/99)
Table 11.5-2 Deleted.11.5-11 Amendment No. 17 (10/99)
Table 11.5-3 Deleted 11.5-12 Amendment No. 17 (10/99)
TABLE 11.5-8 DESIGN DATA FOR SOLID WASTE SYSTEM COMPONENTS
- 1. Drum Roller (This equipment is no longer used
.)Quantity 2 Type Horizontal, direct drive Drum size, gal 55 Capacity, lb 1000 Code None 2. Baler (This equipment is no longer used
.)Quantity 1 Type Hydraulic, totally enclosed Drum size, gal 55 Compacting force, psi 8.3 Exhaust fan capacity, CFM 40 Exhaust filter Prefilter and HEPA filter Code None 3. Spent Resin Tank Quantity 1 Type Vertical Volume, gal 3200 Design pressure, psig 50 Design temperature, F 200 Material 55 Code ASME Boiler and Pressure Vessel Code 1968,Section III, Class C
- 4. Dewatering Pump (This equipment is no longer used
.)Quantity 1 Type Self-priming centrifugal Design flow, gpm 100 Design head, ft 95 Design temperature, F 200 Material 55 Code None 5. Resin Addition Tank Quantity 1 Volume, gal 100 Design pressure, psig Atmospheric Design temperature, F N.A.Material 55 Code None 11.5-17 Amendment No. 17 (10/99)
REFERENCES FOR SECTION 11.6 1.U.S. Atom ic Energy Commission, WASH 1258, Final Environmental Statement concerning Proposed Rule Making Action: Numerical Guides for Design Objectives and Limiting Conditions
for Operation to Meet the Criterion "As Low As Practicable" for Radioactive Material in Light-
Water-Cooled Nuclear Power Reactor Effluents, Volume 3, EPA Review of Draft Appendix, Suitability of Environmental Methodology to Detect Environmental Radionuclide Concentrations
from "As Low As Practicable" Discharges, pp. 301-308.
11.6-4