COL Application Part 2, FSAR - nrc.gov

Revision 211-i

Comanche Peak Nuclear Power Plant, Units 3 & 4COL Application

Part 2, FSAR

CHAPTER 11

RADIOACTIVE WASTE MANAGEMENT SYSTEM

TABLE OF CONTENTS

Section Title Page

11.0 RADIOACTIVE WASTE MANAGEMENT SYSTEM.......................... 11.1-1

11.1 SOURCE TERMS.............................................................................. 11.1-1

11.2 LIQUID WASTE MANAGEMENT SYSTEM ...................................... 11.2-1

11.2.1.5 Site-Specific Cost-Benefit Analysis........................................ 11.2-111.2.1.6 Mobile or Temporary Equipment ........................................... 11.2-211.2.2 System Description................................................................ 11.2-311.2.3.1 Radioactive Effluent Releases and Dose Calculation in Normal

Operation ............................................................................... 11.2-511.2.3.2 Radioactive Effluent Releases Due to Liquid Containing Tank

Failures .................................................................................. 11.2-811.2.3.4 Evaporation Pond .................................................................. 11.2-811.2.4 Testing and Inspection Requirements ................................. 11.2-1311.2.5 Combined License Information ............................................ 11.2-1311.2.6 References .......................................................................... 11.2-14

11.3 GASEOUS WASTE MANAGEMENT SYSTEM ................................ 11.3-1

11.3.1.5 Site-Specific Cost-Benefit Analysis........................................ 11.3-111.3.2 System Description................................................................ 11.3-111.3.3.1 Radioactive Effluent Releases and Dose Calculation in Normal

Operation ............................................................................... 11.3-211.3.7 Combined License Information .............................................. 11.3-311.3.8 References ............................................................................ 11.3-4

11.4 SOLID WASTE MANAGEMENT SYSTEM ....................................... 11.4-1

11.4.1.3 Other Design Considerations................................................. 11.4-111.4.1.5 Site-Specific Cost-Benefit Analysis........................................ 11.4-111.4.1.6 Mobile or Temporary Equipment ........................................... 11.4-211.4.2.1.1 Dry active wastes............................................................. 11.4-211.4.2.2.1 Spent Resin Handling and De-watering Subsystem........ 11.4-211.4.2.3 Packaging, Storage, and Shipping ........................................ 11.4-311.4.3.2 Process Control Program ...................................................... 11.4-411.4.4.5 Mobile De-watering System................................................... 11.4-511.4.6 Testing and Inspection Requirements ................................... 11.4-511.4.8 Combined License Information .............................................. 11.4-6


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11.5 PROCESS EFFLUENT RADIATION MONITORING AND SAMPLING SYSTEMS ......................................................................................... 11.5-1

11.5.2.5.3 Startup Steam Generator Blowdown Heat Exchanger Downstream Radiation Monitor (RMS-RE-110)............... 11.5-1

11.5.2.5.4 Evaporation Pond Discharge Radiation Monitor (RMS-RE-111) ................................................................. 11.5-1

11.5.2.6 Reliability and Quality Assurance .......................................... 11.5-211.5.2.7 Determination of Instrumentation Alarm Setpoints for

Effluents................................................................................. 11.5-211.5.2.8 Compliance with Effluent Release Requirements.................. 11.5-211.5.2.9 Offsite Dose Calculation Manual ........................................... 11.5-311.5.2.10 Radiological Environmental Monitoring Program................... 11.5-311.5.2.11 Site-Specific Cost-Benefit Analysis........................................ 11.5-411.5.5 Combined License Information .............................................. 11.5-4


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LIST OF TABLES

Number Title

11.2-10R Liquid Releases Calculated by PWR GALE Code

11.2-11R Liquid Releases with Maximum Defined Fuel Defects

11.2-12R Comparison of Annual Average Liquid Release Concentrations with 10 CFR 20 (Expected Releases)

11.2-13R Comparison of Annual Average Liquid Release Concentrations with 10 CFR 20 (Maximum Releases)

11.2-14R Input Parameters for the LADTAP II Code

11.2-15R Individual Doses from Liquid Effluents

11.3-8R Input Parameters for the GASPAR II Code

11.3-9R Calculated Doses from Gaseous Effluents

11.3-201 Population Distribution within 50 mi for Population Dose Calculation

11.3-202 Release Rates from the Evaporation Pond to Atmosphere

11.3-203 Input Parameters for Dose Calculation from Evaporation Pond

11.3-204 Calculated Doses from Evaporation Pond

11.3-205 Total Doses Due to Gaseous Effluent from Vent Stack and Evaporation Pond

11.3-206 Total Gaseous Doses to the Maximally Exposed Individual at Squaw Creek Reservoir

11.5-201 Effluent Liquid Monitors (Site-Specific)


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LIST OF FIGURES

Number Title

11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram

11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram

11.4-201 Solid Waste Management System Piping and Instrumentatiom Diagram

11.5-201 Typical Process In-Line Radiation Monitor Schematic


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ACRONYMS AND ABBREVIATIONS

A/B auxiliary buildingAC/B access buildingACC accumulatorAMC Annual Maintenance CostAOC Annual Operating CostAOO anticipated operational occurrenceCFR Code of Federal RegulationsCOL Combined LicenseCPNPP Comanche Peak Nuclear Power PlantCRF Capital Recovery FactorCVCS chemical and volume control systemCVDT containment vessel reactor coolant drain tankCWS Circulating Water SystemDCD Design Control DocumentDCEM Direct Cost of Equipment and MaterialsDLC Direct Labor CostDOT Department of TransportationEAB exclusion area boundaryESW essential service waterFSAR final safety analysis reportGWMS gaseous waste management systemHT holdup tankHVAC heating, ventilation, and air conditioningHx heat exchangerICF Indirect Cost FactorLCCF Labor Cost Correction FactorLWMS liquid waste management systemMCR Main Control RoomNEI Nuclear Energy InstituteODCM offsite dose calculation manualPCP process control programPERMS process effluent radiation monitoring and sampling systemP&ID piping and instrumentation diagramPMW primary makeup waterPWR pressurized-water reactorR/B reactor buildingRCP reactor coolant pump


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RCS reactor coolant systemRG regulatory guideRWSAT refueling water storage auxiliary tankSG steam generatorSRST spent resin storage tankSSC structure, system, and componentSWMS solid waste management systemTAC Total Annual CostVCT volume control tankWHT waste holdup tankWMT waste monitor tankWMS Waste Management System

ACRONYMS AND ABBREVIATIONS


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11.0 RADIOACTIVE WASTE MANAGEMENT SYSTEM

11.1 SOURCE TERMS

This section of the referenced Design Control Document (DCD) is incorporated by reference with no departures or supplements.


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11.2 LIQUID WASTE MANAGEMENT SYSTEM

This section of the referenced DCD is incorporated by reference with the following departures and/or supplements.

11.2.1.5 Site-Specific Cost-Benefit Analysis

Replace the third paragraph in DCD Subsection 11.2.1.5 with the following.

The cost benefit analysis performed to satisfy the requirements of 10 CFR Part 50, Appendix I, Section II.D used the guidance and methodology given in RG 1.110, March 1976. The generic parameters used in calculating the Total Annual Cost (TAC) are given in RG 1.110 for each radwaste treatment system augment. The fixed generic parameters provided in RG 1.110 include the Annual Operating Cost (AOC) (Table A-2), Annual Maintenance Cost (AMC) (Table A-3), Direct Cost of Equipment and Materials (DCEM) (Table A-1), and Direct Labor Cost (DLC) (Table A-1). The following variable parameters were used in the plant specific cost benefit analysis:

• Capital Recovery Factor (CRF) -This factor is taken from Table A-6 of RG 1.110 and reflects the cost of money for capital expenditures. A cost-of-money value of 7% per year is assumed in this analysis, consistent with the "Regulatory Analysis Guidelines of the U.S. Nuclear Regulatory Commission" (NUREG/BR-0058). Using the formulation following Table A-6, an interest rate of 7%, and a service life of 60 years, a CRF of 0.07123 was obtained.

• Indirect Cost Factor (ICF) -This factor takes into account whether the radwaste system is unitized or shared (in the case of a multi-unit site) and is taken from Table A-5 of RG 1.110. It is assumed that the radwaste system for this analysis is a unitized radwaste system at a multi-unit site, which equals an ICF of 1.75.

• Labor Cost Correction Factor (LCCF) -This factor takes into account the differences in relative labor costs between geographical regions and is taken from Table A-4 of RG 1.110. A LCCF of 1.1 is assumed in this analysis.

The first augment considered is a near replica train of the current US-APWR LWMS system which includes a single cartridge filter and four PWR clean waste demineralizers. Other augments considered independently were; 1) a liquid waste evaporator, 2) a reverse osmosis unit, and 3) a 90 gpm cartridge filter. The direct costs for the examined augments were scaled in order to represent the flow rates of the site-specific design and a 10% contingency factor was used.

CP COL 11.2(5)


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Of the augments considered, the lowest total annual cost (TAC) was a 90 gpm cartridge filter with a TAC of $14,910 in 1975 dollars. Using the $1,000 per person-rem criterion prescribed by Appendix I to 10 CFR Part 50 the dose reduction would have to be 14.91 person-rem whole body (or thyroid) to be cost beneficial. Because the site specific population dose estimate is well below this value (i.e., 2.36 person-rem/yr and 2.07 person-rem/yr, Total Body and Thyroid respectively) there are no cost-beneficial liquid radwaste augments and no further cost-benefit analysis is needed to demonstrate compliance with 10 CFR 50, Appendix I Section II.D.

11.2.1.6 Mobile or Temporary Equipment

Replace the last sentence in the first paragraph in DCD Subsection 11.2.1.6.

Process piping connections have connectors different from the utility connectors to prevent cross-connection and contamination. The use of mobile or temporary equipment will require applicable regulatory requirements and guidance such as 10 CFR 50.34a, 10 CFR 20.1406 and RG 1.143 to be addressed. As such the purchase or lease contracts for any temporary and mobile equipment will specify the applicable criteria.

The space allocated for the temporary and mobile equipment is located in the Auxiliary Building to minimize the impact to the environment in the event of an accident or spillage of radioactive materials. Shield walls are provided on three sides with one side open for access during installation, operation, inspection, and maintenance. The shield walls also serve to minimize spread of contamination to the entire area. A shield door is provided with truck bay access door from the common walkway inside the A/B. At the door opening a curb with sloped sided is constructed to prevent spreading of any liquid spillage into the truck bay area. The connection for the spent resin is provided on the process piping panel and the transfer line is built into the pipe chase for shielding purposes. The location of the mobile unit facilitates short transfer distance. Drainage collection is provided for liquid leakage and is routed to the waste holdup tanks, which are located on a floor below, for reprocessing. Provisions are included to mitigate contamination of the facility. Demineralized water piping is provided for decontaminating the facility. The floor in the area for the mobile system is sloped away from the truck bay door and the stairwell. The floor is sloped toward the plant west wall, where contamination from leaks from the mobile systems can enter the floor drain for processing by the LWMS. A level detector is provided within the drain collection header.

Replace the second paragraph of DCD Subsection 11.2.1.6 with the following.

STD COL 11.2(1)STD COL 12.3(7)



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The temporary mobile/portable equipment installed in the LWMS is vendor- supplied and operated within the specified requirements. The temporary mobile/portable equipment includes the necessary connections and fittings to interface with the plant piping. The connectors are uniquely designed to prevent inadvertent cross connection between the radioactive and non-radioactive plant piping. The piping also includes backflow inhibitors. Liquid effluent from the temporary mobile/portable equipment is routed to the LWMS. An operating procedure will be provided prior to fuel load to ensure proper operation of the temporary mobile/portable equipment to prevent contamination of non-radioactive piping or uncontrolled releases of radioactivity into the environment so that guidance and information in Inspection and Enforcement (IE) Bulletin 80-10 (Ref. 11.2-25) is followed.

11.2.2 System Description

Replace third paragraph in DCD Subsection 11.2.2 with the following.

Process flow diagrams with process equipment, flow data, tank batch capabilities, and key control instrumentation are provided to indicate process design, method of operation, and release monitoring for the site specific liquid waste management system (LWMS).

Figure 11.2-201, Sheets 1 through 10 illustrate the piping and process equipment, instrumentation and controls for Comanche Peak Nuclear Power Plant (CPNPP) Units 3 and 4 LWMS.

The Liquid Waste Management System (LWMS) boundary ends at the discharge isolation valve and the radiation monitor of the discharge header from the waste monitor tanks, which is considered the controlled discharge point. The evaporation pond is not part of the LWMS because the pond only contains treated effluent for discharge. Unlike the waste monitor tanks, which could contain off-specification effluent that may need to be re-processed; the evaporation pond is designed to manage the tritium concentration in the SCR by providing temporary holdup of treated effluent for discharge.

The treated liquid effluents released from the CPNPP Units 3 and 4 and the evaporation pond are piped directly into the Unit 1 Waste Management System (WMS) flow receiver and head box, which includes the discharge flume. The effluents enter from the top of the receiver and head box and are above the liquid level in the box so that they flow freely into the box, from where the content flows to the Unit 1 WMS discharge flume, and by gravity to the Unit 1 Circulating Water System (CWS), via an existing Unit 1 pipeline connecting the WMS to the CWS. At this pipeline intersection, the Unit 3 and 4 treated effluent and the Unit 3 and 4 evaporation pond effluents are commingled with various Unit 1 and 2 waste effluent streams. This Unit 1 circulating water flow path then goes to the Unit 1 condenser water box outlet, where it joins the Unit 2 condenser water box outlet

CP COL 11.2(2)

CP COL 11.2(6)


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flow. The joined flows from the Unit 1 and 3 condenser water boxes are then sent to the SCR via the Unit 1 and 2 discharge tunnel and outfall structure from all four units (see Figure 11.2-201 Sheet 10) for a visual representation of the above described flow path.

The header where the WMS intersects with the CWS is located within the Unit 1 Turbine building. The header contains two flow balancing valves (1CW-247 and 1CW-248) for Units 1 and 2. This arrangement ensures that there is always circulating cooling water flow for Unit 1 and/or Unit 2. The circulating water discharge piping then becomes progressively larger and flows freely (no valves) into the Unit 1 condenser water discharge box. This flow path also ensures there is less back pressure into the treated effluent flow. Based on the fact that the effluent piping flows freely into the box and that there is less back pressure, there is no need for a mixing orifice and backflow preventer, as the large circulating water return flow and length of pipe is sufficient to thoroughly mix the release.

The bypass valve, VLV-531, is located in the same area with the radiation monitor and the discharge control valves (RCV-035A and RCV-035B), which are inside the Auxiliary Building. All normal discharge is required to go through the discharge control valves. To ensure discharge operation is not prevented by the failure of the control valves at any time, a bypass valve is added around the radiation monitor and the discharge control valves. Plant procedures require that an operator verify the tank water radioactivity concentration by sampling and water volume by level indicator prior to a liquid effluent release via the bypass valve. The ODCM and supporting procedures ensure appropriate actions to prevent an unmonitored release.

Any leakage from the piping and the valves inside the buildings is collected in the floor drain sump, and is forwarded to the waste holdup tank for re-processing. It should be noted that the discharge control valves are downstream of the discharge isolation valve (AOV-522A and AOV-522B). During normal operations, the discharge is anticipated to occur once a week for approximately three hours for treated effluent, and one discharge (approximately an hour at 20 gpm) of detergent waste (filtered personnel showers and hand washes) daily. After each discharge, the line is flushed with demineralized water for decontamination.

The bypass valve is normally locked-closed and tagged. It requires an administrative approval key to open and the valve position is verified by at least two technically qualified members of the CPNPP Operations staff before discharge can start. Thus, a single operator error does not result in an unmonitored release. In the unlikely event that the valve is inadvertently left open, or partially open, the flow element detects flow and initiates an alarm for operator action. Also, a portion of the flow continues to flow through the radiation monitor sample chamber. Because the monitor output depends on radionuclide concentration and not flow rate, there is no impact on radiation monitor sensitivity from reduced flow conditions. Prior to opening VLV-531 to establish the alternate flow path, the tanks (ATK-006A and ATK-006B) will be sampled and water volume verified by level indicator to confirm that the contents meet the discharge


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specifications. Therefore, there is no impact on the annual liquid release and the annual dose to the members of the public if the bypass valve is inadvertently left fully-open.

If the monitor reaches the high setpoint, it sends signals to initiate pump shutdown, valve closure and operator actions.

11.2.3.1 Radioactive Effluent Releases and Dose Calculation in Normal Operation

Replace the last six paragraphs in DCD Subsection 11.2.3.1 with the following.

The detailed design information of release point is described in Subsection 11.2.2.

The annual average release of radionuclides is estimated by the PWR-GALE Code (Ref.11.2-13) with the reactor coolant activities that is described in Section 11.1. The version of the code is a proprietary modified version of the NRC PWR-GALE code reflecting the design specifics of US-APWR design (Ref. 11.2-27). The parameters used by the PWR-GALE Code are provided in Table 11.2-9, and the calculated effluents are provided in Table 11.2-10R. The calculated effluents for the maximum releases are provided in Table 11.2-11R. On this site-specific application, handling of contaminated laundry is contracted to off-site services. Therefore, the detergent waste effluent need not be considered.

The calculated effluent concentrations using annual release rates are then compared against the concentration limits of 10 CFR 20 Appendix B (see Tables 11.2-12R and 11.2-13R.).

Once it is confirmed that the treated effluent meets discharge requirements, the effluent is released into Squaw Creek Reservoir via the CPNPP Units 1 and 2 circulating water return line. The liquid effluent is maintained at ambient temperature, as it is stored inside the auxiliary building (A/B) waste monitoring tanks. Currently, Squaw Creek Reservoir has a tritium concentration limit of 30,000 pCi/L (Reference 11.2-201). Based on an analysis, the tritium concentration in Squaw Creek Reservoir is anticipated to remain within the tritium limit due to the local rainfall, evaporation, and spillover (control release) from Squaw Creek Reservoir to Squaw Creek.

However, during the maximum tritium generation condition (i.e., all four units operating at full power), the tritium concentration could be exceeded. When the tritium concentration in Squaw Creek Reservoir is determined to be close to the offsite dose calculation manual (ODCM) limit, as much as half of the liquid effluent from CPNPP Units 3 and 4 can be diverted to the evaporation pond for temporary staging.

CP COL 11.2(2)

CP COL 11.2(4)


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When the tritium concentration in Squaw Creek Reservoir again decreases below the operating target, the effluent in the pond is sampled and analyzed for suitability to discharge back into Squaw Creek Reservoir. In the event that both CPNPP Units 1 and 2 are temporarily not in operation, or when there is no dilution flow, the CPNPP Units 3 and 4 waste holdup tanks (WHTs) and waste monitor tanks (WMTs) have enough capacity to store more than a month of the daily waste input. The evaporation pond can also receive 100 percent of the CPNPP Units 3 and 4 liquid effluent on a temporary basis. The treated effluent release piping is non-safety and does not have any safety function. In addition, the Unit 1 flow receiver and head box, circulating water system and discharge box are not required to perform any safety function or important to safety functions.

The evaporation pond is designed to provide sufficient surface area for natural evaporation based on the local area rainfall, evaporation rate, and receiving half of the CPNPP Units 3 and 4 liquid effluent. The evaporation pond is sized to prevent overflow due to local maximum rainfall condition. Rainfall is the primary contributing source for dilution of the pond. The pond design includes a transfer pump and discharge line to keep the pond from overflowing during periods of extreme weather conditions, and to forward the effluent to Squaw Creek Reservoir. The effluent is sampled before discharge and is monitored for radionuclide concentration by a radiation monitor which can turn off the pump, shut off the discharge valve and initiate an alarm signal to the Main Control Room and the Radwaste Control Room for operator actions. Doses from airborne particulates from the evaporation pond are described in Subsection 11.3.3.

The evaporation pond is designed with two layers of high density polyethylene (HDPE) with smooth surfaces and a drainage net in between for leak detection and collection. The bottom of the pond is sloped towards the leak drainage pit and a separate discharge pump pit. The leak drainage pit is a small pit underneath the two layers of HDPE, and leakage through the HDPE is caught and detected in this pit. The discharge pump pit is designed to faciliate pumping water out of the pond and is equipped with a discharge pump. An operating requirement is established to wash the pond and discharge the wash water to a flow receiver and head box for disposal each time the pond is drained. Based on the design evaluation, the pond does not need to be used continuously, because during normal operating conditions and anticipated operational occurrences, diversion of flow is not required. Diversion is required only when the tritium concentration in the SCR is approaching the set limit due to adverse meteorological conditions (e. g., drought condition leading to minimal spillover). The pond also has a berm to minimize infiltration of storm water. These design features (using HDPE, the leak detection pit, and sloping towards the drainage pit for discharge) and operating procedures (cleaning, diversion only when required) ensure ease of decontamination and minimization of cross contamination (leakage to the groundwater), and thus satisfy 10 CFR 20.1406 and RG 4.21.

The evaporation pond discharge pump and discharge isolation valve are under supervisory control. Prior to discharge, multiple effluent samples around the pond perimeter are required to ensure the pond effluent meets the discharge


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specifications. The evaporation pond is a relatively small pond. The effluent to the pond has been filtered and ion exchanged and it is expected that effluent concentration in the pond is uniform. Stagnation and stratification of concentrations is not expected. This is confirmed by obtaining representative samples from the pond. The bottom of the pond is designed to be sloped towards the discharge pit to facilitate complete drainage. The pond is washed each time the contents are emptied to significantly reduce the potential for accumulation of residual contamination. Further, a radiation monitor is located close to the pump discharge to monitor the radiation level of the contents. The radiation monitor alarms in the Main Control Room and the Radwaste Operator Control Room and also isolates the pump and its discharge valve in the unlikely event of the content exceeding the setpoint. The radiation monitor setpoint for the evaporation pond discharge is the same as that used at the Waste Monitor Tank discharge.

Isotopic concentrations are calculated, assuming 247,500 gpm per unit of circulating water from CPNPP Units 1 and 2 (Reference 11.2-201, ODCM for CPNPP Units 1 and 2). The isotopic ratios between the expected releases and the concentration limits of 10 CFR 20 Appendix B are listed in Tables 11.2-12R. The isotopic ratios between the maximum releases and the concentration limits of 10 CFR 20 Appendix B are listed in Table 11.2-13R. These ratio values are less than the allowable value of 1.0.

The individual doses and population doses are evaluated with the LADTAP II Code (Reference 11.2-14). The site-specific parameters used in the LADTAP II Code are listed in Table 11.2-14R, and the calculated individual doses are listed in Table 11.2-15R. Population dose due to public use of SCR is estimated to be 250 times the maximum SCR individual dose based on an estimated maximum usage of 250 people. The exposure pathways considered due to the public use of SCR are fishing and shoreline recreation. There are no drinking water pathways or irrigated food pathways associated with SCR. Swimming is not a significant contributor to population dose and the 50-mile population dose due to fish ingestion is unchanged due to the public use of SCR. Therefore, drinking water, irrigated foods, swimming and fish ingestion are not considered for the 50-mile population dose.The calculated population dose from liquid effluents is 2.36 person-rem for whole-body and 2.07 person-rem for thyroid. Based on these parameters, the maximum individual dose to total body is 0.90 mrem/yr (adult) and the maximum individual dose to organ is 1.29 mrem/yr (teenager’s liver). These values are less than the 10 CFR 50 Appendix I criteria of 3 mrem/yr and 10 mrem/yr, respectively. Evaluating the dose contribution from the evaporation pond (conservatively assuming 50% evaporation of the diverted flow) amounts to 1.15E-01 mrem/yr (Adult’s GI-Tract) described in FSAR Table 11.3-204 and the combined dose from the vent stack gaseous emission and the evaporation pond emission amounts to 2.73E+00 mrem/yr (Adult’s GI-Tract) described in FSAR Table 11.3-205, which is well within the 10 CFR Appendix I limit. Based on the above, the evaporation pond meets the acceptance criteria of SRP 11.2. With regards to RG 1.143, RG 1.143 does not provide any guidance on specific design requirements for an evaporation pond. Hence RG 1.143 is not applicable to the desing of the evaporation pond.According to NUREG-0543 (Reference 11.2-202),


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there is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40 CFR 190. Once the proposed CPNPP Units 3 and 4 are constructed, the Comanche Peak site will consist of four operating reactors.

11.2.3.2 Radioactive Effluent Releases Due to Liquid Containing Tank Failures

Replace the last sentence in the second paragraph in DCD Subsection 11.2.3.2 with the following.

Source term for each tank is provided in the DCD and the assessment of this model using the site-specific parameters to evaluate the conservatism of this analysis is described below.

Replace the first two sentences in the last paragraph in DCD Subsection 11.2.3.2 with the following.

The evaluation of potential radioactive effluent releases to surface water or groundwater due to failure of the holdup tank is provided in Subection 2.4.13. Releases from this tank result in concentrations at the nearest unrestricted potable water supply that are within the limits of 10 CFR 20, Appendix B (Ref 11.2-8).

Add the following Subsection after DCD Subsection 11.2.3.3.

11.2.3.4 Evaporation Pond

The primary purpose of the evaporation pond is to provide a means to receive, store, and process treated radioactive effluent from the CPNPP Units 3 and 4 liquid radioactive waste management systems when the tritium concentration in Squaw Creek Reservoir is approaching the ODCM limit.

In order to minimize contamination, the pond is rinsed each time the pond content is emptied. The rinse water is also forwarded to Squaw Creek Reservoir, via the discharge box and blended with the CPNPP Units 1 or 2 circulation water flow.

The evaporation pond is equipped with a leak detection system. In the event a leak is developed, a signal is sent to the Main Control Room and the Radwaste

CP COL 11.2(3)

CP COL 11.2(3)

CP SUP 11.2(1)


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Control Room for operator actions, which may include removing the contents from the pond to facilitate inspection and repair as required.

The pond liner is inspected regularly to determine liner integrity with respect to the liners and their seams. In the event of punctures and/or rupture and repair is required, the pond contents are removed, and the pond is rinsed before repair is performed.

The construction, testing, and inspection requirements for the evaporation pond meet the TCEQ permit process and requirements.

The evaporation pond is designed and constructed in accordance with the following standards (others may be applicable as the design is finalized):

Texas Administrative Code (TAC), Title 30 on Environmental Quality, Part 1 Texas Commission on Environmental Quality (TCEQ):

TCEQ 321.255, Requirements for Containment of Wastes and Pond(s)

TCEQ 330, Municipal Solid Waste

TCEQ 217.203, Design Criteria for Natural Treatment Facilities

American Society for Testing and Materials (ASTM)

ASTM D3020, Specification for Polyethylene and Ethylene Copolymer Plastic Sheeting for Pond, Canal and Reservoir Lining

ASTM D5514-06, Standard Test Method of Large Scale Hydrostatic Puncture Testing of Geosynthetics

ASTM D7002-03, Standard Practice for Leak Location on Exposed Geomembranes Using the Water Puddle System

Industry standards such as ANSI / HI -2005 “Pump standard” will be used in designing the pumps

Geosynthetic Research Institute Standard GM13 will be utilized for HDPE

The evaporation pond will be initially inspected and tested following construction and prior to the initial release of liquid effluents from the liquid waste management system to the pond. The evaporative pond construction requirements from the TECQ and ASTM codes and standards listed above are specified in a construction specification that includes sloping the pond, liner type, instrument calibration, number of layers, thickness, etc. After construction, initial testing and inspection of the evaporation pond will consist of the following:


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• Inspection of the liner for integrity, lack of damage, and welt seams construction

• Slope and drainage capability

• Instrumentation calibration

• Leakage detection system

The specific requirements are listed in the following paragraphs.

The evaporation pond will be periodically tested and inspected. Using the acceptance criteria established in the codes and standards listed above. The periodic testing and inspection procedures for the evaporation pond will include the following:

• Water sample and analysis before draining and decontamination to monitor concentration buildup

• Liner and welt integrity

• Drainage capability

• Instrument calibration

• Soil and groundwater contamination analysis per NEI 07-07

The evaporation pond is designed and constructed to contain treated effluent that is contaminated with radioactive nuclides. The pond opens to the environment to allow the tritiated water to naturally evaporate.

The evaporation pond is constructed with two layers of High Density Polyethylene material suitable for this service. The High Density Polyethylene is a minimum of 60 mils thickness.

A drainable mesh mat, with a minimum thickness of 30 mils, is provided in between the two layers of High Density Polyethylene to allow movement of the liquid due to leakage of the content from the top layer of High Density Polyethylene.

The evaporation pond is constructed with a total depth of six feet, with four feet below grade and two feet freeboad. A berm is constructed to prevent surface water from entering the pond during rainy seasons.

The evaporation pond is constructed with a layer of clay with permeability less than 1E-7 centimeter per second to support the pond. The overall construction meets or exceeds the requirements for waste water pond stipulated by TCEQ. Some TCEQ requirements are as follows:


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• In situ clay soils or placed and compacted meeting:

i. more than 30% passing a Number 200 mesh sieve

ii. liquid limit greater than 30%

iii. plasticity index greater than 15

iv. a minimum thickness of two feet

v. Permeability equal to or less than 1x10-7centimeter per second

• Soil compaction will be 95% standard proctor density at optimum moisture content

• The pond is protected from inundation by a ten-year 2 hour rainfall event

The evaporation pond is equipped with a centrifugal pump to return the contents to the Squaw Creak Reservoir as tritium concentration in Squaw Creak Reservoir permits. The return piping leaving the evaporation pond is connected to the circulating water return line discharge box upstream of the discharge point. A radiation monitor is provided close to the pump discharge to monitor radiation level of the content, and provides a signal to automatically turn off the pump, shut off the discharge valve, and initiate a signal to alarm in the Main Control Room and the Radwaste Control Room for operator actions.

The LWMS effluent release piping for transporting radioactive effluent from the discharge valve inside the Auxiliary Building (A/B) to the pond and the piping from the pond to the Unit 1 flow receiver and head box consists of the following piping segments:

1. From the discharge valve, single-walled carbon steel pipe is routed in pipe chases from the A/B, through the Power Source Building (PS/B), up to the Turbine Building (T/B) exit wall penetration.

2. The effluent pipe is then connected to a single-walled carbon steel pipe or double-wall High Density Polyethylene (HDPE) piping from the T/B wall to the yard near the CST. This portion of pipe is run via the condensate transfer piping trench. A transition manhole is constructed near the plant pavement boundary to accomodate splitting the radwaste effluent pipe into two piping segments: first segment goes to the Unit 1 flow receiver and headbox, and second effluent pipe to the radwaste evaporation pond.

3. Buried double-walled HDPE piping from the transition manhole to the Unit 1 flow receiver and head box.


Part 2, FSAR

Revision 211.2-12

4. Buried double-walled HDPE piping from the transition manhole to the radwaste evaporation pond. Additional manholes are constructed to monitor leakage along the buried pathway.

5. The radwaste evaporation pond return pipe is buried double-walled HDPE piping from the pond to the Unit 1 flow receiver and head box. This return pipe is buried parallel to the effluent pipe and passes through the same manholes for testing and inspection for piping integrity.

Additional manholes are provided for testing and inspection for the buried piping. Each manhole is equipped with drain collection basins and leak detection instruments to send the signal when activated by fluid in the manhole to a receiver in the Main Control Room (MCR) for operator action. This design approach minimizes leakage and provides accessibility to facilitate periodic testing (hydrostatic or pressure), or visual inspection to maintain pipe integrity and is compliant with RG 4.21. A back flow preventer is provided near the CPNPP Units 1 and 2 discharge boxes to prevent back flow from the circulating pipe.

Evaporation Pond Design Summary:

Volume: 2.1 million gallon net capacity

Surface area: 1.5 acre

Depth: Total 6 feet deep (4 feet liquid depth with 2 feet freeboard)

Type: Open with no cover

Liner material: High Density Polyethylene, 60 mils, two layers

Permeability: 1x10-7cm/sec

The evaporation pond contains treated liquid effluents in trace amounts that meet discharge requirements specified in 10 CFR 20 Appendix B, Table 2, and has radionuclide contents below that of the boric acid tank contents. Hence, the contamination level due to the failure of the evaporation pond is bounded by the failure of the boric acid tanks.

The evaporation pond is designed to meet and operate in accordance with RG 4.21. Preventive maintenance, monitoring and routine surveillance programs are an important part to minimize the potential for contamination. Leakage detection design, radiation monitors are added for early detection to prevent spread of contamination. The current CPNPP pond management program is expanded to include the above requirements for the evaporation pond and its supporting components including the radiation monitor, pumps and valves.

Operating procedures limit the use of the pond to receive treated effluent on an as-needed basis and the pond will be washed each time it is emptied. Sampling


Part 2, FSAR

Revision 211.2-13

procedures confirm the tritium concentration in the SCR is below the pre-determined setpoint, and that the effluent is acceptable for release. The tritium sampling procedures will be included in the site-wide ODCM, which will be part of Radiological Effluent Controls Program. The Radiological Effluent Controls Program already has an implementation milestone established as shown in Table 13.4-201.

11.2.4 Testing and Inspection Requirements

Add the following sentences to the end of the last paragraph of DCD Subsection 11.2.4.

The licensee has an Epoxy Coatings Program used to facilitate the ALARA objective of promoting decontamination in radiologically controlled areas outside containment. The program controls refurbishment, repair, and replacement of coatings in accordance with the manufacturers' product data sheets and good painting practices. The program will be implemented as described in FSAR Table 13.4-201.

11.2.5 Combined License Information

Replace the content of DCD Subsection 11.2.5 with the following.

11.2(1) The mobile and temporary liquid radwaste processing equipment

This combined license (COL) item is addressed in Subsection 11.2.1.6.

11.2(2) Site-specific information of the LWMS

This COL item is addressed in Subsections 11.2.2 and 11.2.3.1.

11.2(3) The liquid containing tank failure

This COL item is addressed in Subsection 11.2.3.2.

11.2(4) The site-specific dose calculation

This COL item is addressed in Subsection 11.2.3.1, Table 11.2-10R, Table 11.2-11R, Table 11.2-12R, Table 11.2-13R, Table 11.2-14R and Table 11.2-15R.

11.2(5) Site-specific cost benefit analysis


11.2(6) Piping and instrumentation diagrams

This COL item is addressed in Subsection 11.2.2 and Figure 11.2-201.

11.2(7) The implementation milestones for the coatings program used in the LWMS

CP COL 11.2(7)

STD COL 11.2(1)

CP COL 11.2(2)

CP COL 11.2(3)

CP COL 11.2(4)

CP COL 11.2(5)

CP COL 11.2(6)

CP COL 11.2(7)


Part 2, FSAR

Revision 211.2-14

This COL item is addressed in Subsection 11.2.4.

11.2(8) The mobile/portable LWMS connections


11.2.6 References

Add the following references after the last reference in DCD Subsection 11.2.6.

11.2-201 Offsite Dose Calculation Manual for CPNPP Units 1 & 2, Revision 26.

11.2-202 U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR 190), NUREG-0543, Washington, DC, 1980.

STD COL 11.2(8)


Part 2, FSAR

Revision 211.2-15

Table 11.2-10R (Sheet 1 of 2)

Liquid Releases Calculated by PWR GALE Code(4) (Ci/yr)

IsotopeShim Bleed

Misc. Wastes

Turbine Building

Combined Releases

Detergent

Waste(3)TOTAL

Releases (1)

Corrosion and Activation ProductsNa-24 0.00000 0.00029 0.00002 0.00031 N/A 4.70E-03P-32 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Cr-51 0.00000 0.00008 0.00000 0.00008 N/A 1.30E-03Mn-54 0.00000 0.00004 0.00000 0.00005 N/A 7.00E-04Fe-55 0.00000 0.00003 0.00000 0.00003 N/A 5.00E-04Fe-59 0.00000 0.00001 0.00000 0.00001 N/A 1.00E-04Co-58 0.00000 0.00012 0.00000 0.00013 N/A 1.90E-03Co-60 0.00000 0.00001 0.00000 0.00002 N/A 0.00E+00Ni-63 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Zn-65 0.00000 0.00001 0.00000 0.00001 N/A 2.20E-04W-187 0.00000 0.00002 0.00000 0.00002 N/A 3.50E-04Np-239 0.00000 0.00003 0.00000 0.00004 N/A 5.30E-04

Fission ProductsRb-88 0.00000 0.00187 0.00000 0.00187 N/A 2.80E-02Sr-89 0.00000 0.00000 0.00000 0.00000 N/A 6.00E-05Sr-90 0.00000 0.00000 0.00000 0.00000 N/A 8.00E-06Sr-91 0.00000 0.00000 0.00000 0.00000 N/A 6.80E-05Y-91m 0.00000 0.00000 0.00000 0.00000 N/A 4.40E-05Y-91 0.00000 0.00000 0.00000 0.00000 N/A 1.00E-05Y-93 0.00000 0.00002 0.00000 0.00002 N/A 3.10E-04Zr-95 0.00000 0.00001 0.00000 0.00001 N/A 2.00E-04Nb-95 0.00000 0.00001 0.00000 0.00001 N/A 1.00E-04Mo-99 0.00000 0.00011 0.00000 0.00011 N/A 1.64E-03Tc-99m 0.00000 0.00011 0.00000 0.00011 N/A 1.70E-03Ru-103 0.00001 0.00020 0.00000 0.00021 N/A 3.11E-03

Rh-103m 0.00001 0.00020 0.00000 0.00021 N/A 3.10E-03Ru-106 0.00010 0.00243 0.00005 0.00257 N/A 3.81E-02Rh-106 0.00010 0.00243 0.00005 0.00257 N/A 3.90E-05

Ag-110m 0.00000 0.00003 0.00000 0.00004 N/A 6.00E-04Ag-110 0.00000 0.00000 0.00000 0.00000 N/A 7.20E-05Sb-124 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00

Te-129m 0.00000 0.00000 0.00000 0.00001 N/A 7.80E-05Te-129 0.00000 0.00002 0.00000 0.00002 N/A 3.10E-04

Te-131m 0.00000 0.00002 0.00000 0.00002 N/A 2.50E-04Te-131 0.00000 0.00000 0.00000 0.00001 N/A 7.60E-05I-131 0.00002 0.00001 0.00000 0.00002 N/A 4.00E-04

Te-132 0.00000 0.00003 0.00000 0.00003 N/A 4.70E-04I-132 0.00000 0.00001 0.00001 0.00002 N/A 3.10E-04I-133 0.00001 0.00002 0.00003 0.00005 N/A 8.10E-04I-134 0.00000 0.00001 0.00000 0.00001 N/A 8.90E-05

Cs-134 0.00002 0.00005 0.00000 0.00007 N/A 1.00E-03I-135 0.00000 0.00002 0.00003 0.00005 N/A 7.80E-04

Cs-136 0.00030 0.00112 0.00000 0.00141 N/A 2.16E-02Cs-137 0.00003 0.00008 0.00000 0.00011 N/A 2.00E-03

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-16

Notes:1. The release totals include an adjustment of 0.16 Ci/yr added by the PWR-GALE Code to account for

AOOs.2. An entry of 0.00000 indicates that the value is less than 1.0E-5 Ci/yr.3. For this site-specific application, contaminated laundry is contracted for off-site services.4. These releases are for a single reactor.


Liquid Releases Calculated by PWR GALE Code(4) (Ci/yr)

Isotope Shim Bleed

Misc. Wastes

Turbine Building

Combined Releases

Detergent

Waste(3)TOTAL

Releases (1)

Fission Products

Ba-137m 0.00003 0.00000 0.00000 0.00003 N/A 4.60E-04

Ba-140 0.00001 0.00031 0.00001 0.00033 N/A 4.89E-03

La-140 0.00001 0.00051 0.00001 0.00053 N/A 8.00E-03

Ce-141 0.00000 0.00000 0.00000 0.00000 N/A 6.00E-05

Ce-143 0.00000 0.00003 0.00000 0.00003 N/A 5.00E-04

Pr-143 0.00000 0.00001 0.00000 0.00001 N/A 7.90E-05

Ce-144 0.00000 0.00011 0.00000 0.00011 N/A 1.70E-03

Pr-144 0.00000 0.00011 0.00000 0.00011 N/A 1.70E-03

All others 0.00000 0.00000 0.00000 0.00000 N/A 1.20E-05

TOTAL (except

H-3)

0.00065 0.01053 0.00025 0.01143 N/A 1.70E-01

H-3 release 1.60E+03

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-17


Liquid Releases with Maximum Defined Fuel Defects(4) (Ci/yr)

Isotope Shim Bleed

Misc. Wastes

Turbine Building

Combined Releases

Detergent

Waste(3)TOTAL

Releases(1)

Corrosion and Activation ProductsNa-24 0.00000 0.00029 0.00002 0.00031 N/A 3.20E-04P-32 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Cr-51 0.00000 0.00008 0.00000 0.00008 N/A 8.25E-05Mn-54 0.00000 0.00004 0.00000 0.00004 N/A 4.13E-05Fe-55 0.00000 0.00003 0.00000 0.00003 N/A 3.09E-05Fe-59 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Co-58 0.00000 0.00012 0.00000 0.00012 N/A 1.24E-04Co-60 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Ni-63 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Zn-65 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05W-187 0.00000 0.00002 0.00000 0.00002 N/A 2.06E-05Np-239 0.00000 0.00003 0.00000 0.00003 N/A 3.09E-05

Fission ProductsRb-88 0.00000 0.03849 0.00000 0.03849 N/A 3.97E-02Sr-89 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Sr-90 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Sr-91 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Y-91m 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Y-91 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Y-93 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Zr-95 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Nb-95 0.00000 0.00002 0.00000 0.00002 N/A 2.06E-05Mo-99 0.00000 0.01333 0.00000 0.01333 N/A 1.38E-02Tc-99m 0.00000 0.00527 0.00000 0.00527 N/A 5.44E-03Ru-103 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Rh-103m 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Ru-106 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Rh-106 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05Ag-110m 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Ag-110 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Sb-124 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Te-129m 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Te-129 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00Te-131m 0.00000 0.00033 0.00000 0.00033 N/A 3.40E-04Te-131 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00I-131 0.02891 0.01445 0.00000 0.04336 N/A 4.47E-02Te-132 0.00000 0.00526 0.00000 0.00526 N/A 5.43E-03I-132 0.00000 0.00015 0.00015 0.00030 N/A 3.09E-04I-133 0.00163 0.00327 0.00491 0.00981 N/A 1.01E-02I-134 0.00000 0.00005 0.00000 0.00005 N/A 5.16E-05Cs-134 0.73457 1.83643 0.00000 2.57100 N/A 2.65E+00I-135 0.00000 0.00083 0.00125 0.00208 N/A 2.15E-03Cs-136 0.12019 0.44873 0.00000 0.56892 N/A 5.87E-01Cs-137 0.43698 1.16528 0.00000 1.60226 N/A 1.65E+00

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-18

Notes:1. The release totals include an adjustment of 0.16 Ci/yr added by the PWR-GALE Code to account for

AOOs.2. An entry of 0.00000 indicates that the value is less than 1.0E-5 Ci/yr.3. For this site-specific application, contaminated laundry is contracted for off-site services.4. These releases are for a single reactor.


Liquid Releases with Maximum Defined Fuel Defects(4) (Ci/yr)Isotope Shim

BleedMisc. Wastes

Turbine Building

Combined Releases

Detergent

Waste(3)TOTAL

Releases (1)

Fission ProductsBa-137m 0.20917 0.00000 0.00000 0.20917 N/A 2.16E-01

Ba-140 0.00000 0.00010 0.00000 0.00010 N/A 1.03E-04

La-140 0.00000 0.00002 0.00000 0.00002 N/A 2.06E-05

Ce-141 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00

Ce-143 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00

Pr-143 0.00000 0.00000 0.00000 0.00000 N/A 0.00E+00

Ce-144 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05

Pr-144 0.00000 0.00001 0.00000 0.00001 N/A 1.03E-05

TOTAL (except H-3)

1.53145 3.53272 0.00633 5.07050 N/A 5.23E+00

H-3 release 1.60E+03

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-19


Comparison of Annual Average Liquid Release Concentrations with 10 CFR 20 (Expected Releases)

Isotope (1) Discharge Concentration

(μCi/ml) (2)(5)

Effluent Concentration Limit

(μCi/ml) (3)

Fraction of

Concentration Limit(4)

Na-24 1.19E-11 5.00E-05 2.39E-07

P-32 0.00E+00 9.00E-06 0.00E+00

Cr-51 3.30E-12 5.00E-04 6.60E-09

Mn-54 1.78E-12 3.00E-05 5.92E-08

Fe-55 1.27E-12 1.00E-04 1.27E-08

Fe-59 2.54E-13 1.00E-05 2.54E-08

Co-58 4.82E-12 2.00E-05 2.41E-07

Co-60 0.00E+00 3.00E-06 0.00E+00

Ni-63 0.00E+00 1.00E-04 0.00E+00

Zn-65 5.58E-13 5.00E-06 1.12E-07

W-187 8.88E-13 3.00E-05 2.96E-08

Np-239 1.35E-12 2.00E-05 6.73E-08

Rb-88 7.11E-11 4.00E-04 1.78E-07

Sr-89 1.52E-13 8.00E-06 1.90E-08

Sr-90 2.03E-14 5.00E-07 4.06E-08

Sr-91 1.73E-13 2.00E-05 8.63E-09

Y-91m 1.12E-13 2.00E-03 5.58E-11

Y-91 2.54E-14 8.00E-06 3.17E-09

Y-93 7.87E-13 2.00E-05 3.93E-08

Zr-95 5.08E-13 2.00E-05 2.54E-08

Nb-95 2.54E-13 3.00E-05 8.46E-09

Mo-99 4.16E-12 2.00E-05 2.08E-07

Tc-99m 4.32E-12 1.00E-03 4.32E-09

Ru-103 7.89E-12 3.00E-05 2.63E-07

Rh-103m 7.87E-12 6.00E-03 1.31E-09

Ru-106 9.67E-11 3.00E-06 3.22E-05

Ag-110m 1.52E-12 6.00E-06 2.54E-07

Sb-124 0.00E+00 7.00E-06 0.00E+00

Te-129m 1.98E-13 7.00E-06 2.83E-08

Te-129 7.87E-13 4.00E-04 1.97E-09

Te-131m 6.35E-13 8.00E-06 7.93E-08

Te-131 1.93E-13 8.00E-05 2.41E-09

I-131 1.02E-12 1.00E-06 1.02E-06

Te-132 1.19E-12 9.00E-06 1.33E-07

I-132 7.87E-13 1.00E-04 7.87E-09

I-133 2.06E-12 7.00E-06 2.94E-07

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-20

Notes:1. Rh-106, Ag-110, Ba-137m are not included in Table 2 of 10 CFR 20 Appendix B. Therefore, these

nuclides are excluded from the calculation of the discharge concentration.2. Annual average discharge concentration based on release of average daily discharge for 292 days per

year with 247,500 gpm dilution flow. This includes a Safety Factor of 0.9 to compensate for flow fluctuations.

3. 10 CFR 20 Appendix B, Table 24. Fractions of 10 CFR 20 concentration limits are for a single unit.5. The basis of the PWR-GALE source term calculation uses a built-in capacity factor of 80%, which is

less than the expected capacity factor for the US-APWR. This difference in capacity factor has no impact on liquid effluent release concentrations.


Comparison of Annual Average Liquid Release Concentrations with 10 CFR 20 (Expected Releases)


(μCi/ml) (2)(5)


(μCi/ml) (3)

Fraction of

Concentration Limit(4)

I-134 2.26E-13 4.00E-04 5.65E-10

Cs-134 2.54E-12 9.00E-07 2.82E-06

I-135 1.98E-12 3.00E-05 6.60E-08

Cs-136 5.49E-11 6.00E-06 9.15E-06

Cs-137 5.08E-12 1.00E-06 5.08E-06

Ba-140 1.24E-11 8.00E-06 1.55E-06

La-140 2.03E-11 9.00E-06 2.26E-06

Ce-141 1.52E-13 3.00E-05 5.08E-09

Ce-143 1.27E-12 2.00E-05 6.35E-08

Pr-143 2.01E-13 2.00E-05 1.00E-08

Ce-144 4.32E-12 3.00E-06 1.44E-06

Pr-144 4.32E-12 6.00E-04 7.19E-09

H-3 4.06E-06 1.00E-03 4.06E-03

TOTAL 4.12E-03

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-21


Comparison of Annual Average Liquid Release Concentrations with 10 CFR 20 (Maximum Releases)


(μCi/ml) (2)(5)


(μCi/ml) (3)

Fraction of Concentration

Limit(4)

Na-24 8.12E-13 5.00E-05 1.62E-08P-32 0.00E+00 9.00E-06 0.00E+00Cr-51 2.09E-13 5.00E-04 4.19E-10Mn-54 1.05E-13 3.00E-05 3.49E-09Fe-55 7.86E-14 1.00E-04 7.86E-10Fe-59 2.62E-14 1.00E-05 2.62E-09Co-58 3.14E-13 2.00E-05 1.57E-08Co-60 2.62E-14 3.00E-06 8.73E-09Ni-63 0.00E+00 1.00E-04 0.00E+00Zn-65 2.62E-14 5.00E-06 5.24E-09W-187 5.24E-14 3.00E-05 1.75E-09Np-239 7.86E-14 2.00E-05 3.93E-09Rb-88 1.01E-10 4.00E-04 2.52E-07Sr-89 0.00E+00 8.00E-06 0.00E+00Sr-90 0.00E+00 5.00E-07 0.00E+00Sr-91 0.00E+00 2.00E-05 0.00E+00Y-91m 0.00E+00 2.00E-03 0.00E+00Y-91 0.00E+00 8.00E-06 0.00E+00Y-93 0.00E+00 2.00E-05 0.00E+00Zr-95 2.62E-14 2.00E-05 1.31E-09Nb-95 5.24E-14 3.00E-05 1.75E-09Mo-99 3.49E-11 2.00E-05 1.75E-06Tc-99m 1.38E-11 1.00E-03 1.38E-08Ru-103 2.62E-14 3.00E-05 8.73E-10Rh-103m 2.62E-14 6.00E-03 4.36E-12Ru-106 2.62E-14 3.00E-06 8.73E-09Ag-110m 0.00E+00 6.00E-06 0.00E+00Sb-124 0.00E+00 7.00E-06 0.00E+00Te-129m 0.00E+00 7.00E-06 0.00E+00Te-129 0.00E+00 4.00E-04 0.00E+00Te-131m 8.64E-13 8.00E-06 1.08E-07Te-131 0.00E+00 8.00E-05 0.00E+00I-131 1.14E-10 1.00E-06 1.14E-04Te-132 1.38E-11 9.00E-06 1.53E-06I-132 7.86E-13 1.00E-04 7.86E-09I-133 2.57E-11 7.00E-06 3.67E-06I-134 1.31E-13 4.00E-04 3.27E-10Cs-134 6.73E-09 9.00E-07 7.48E-03

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-22

Notes:1. Rh-106, Ag-110, Ba-137m are not included in Table 2 of 10 CFR 20 Appendix B. Therefore, these nuclides

are excluded from the calculation of the discharge concentration.2. Annual average discharge concentration based on release of average daily discharge for 292 days per year

with 247,500 gpm dilution flow. This includes a Safety Factor of 0.9 to compensate for flow fluctuations.3. 10 CFR 20 Appendix B, Table 24. Fractions of 10 CFR 20 concentration limits are for a single unit.5. The basis of the PWR-GALE source term calculation uses a built-in capacity factor of 80%, which is less than

the expected capacity factor for the US-APWR. This difference in capacity factor has no impact on liquid effluent release concentrations.


Comparison of Annual Average Liquid Release Concentrations with 10 CFR 20 (Maximum Releases)


(μCi/ml) (2)(5)


(μCi/ml) (3)

Fraction of Concentration

Limit(4)

I-135 5.45E-12 3.00E-05 1.82E-07

Cs-136 1.49E-09 6.00E-06 2.48E-04

Cs-137 4.20E-09 1.00E-06 4.20E-03

Ba-140 2.62E-13 8.00E-06 3.27E-08

La-140 5.24E-14 9.00E-06 5.82E-09

Ce-141 0.00E+00 3.00E-05 0.00E+00

Ce-143 0.00E+00 2.00E-05 0.00E+00

Pr-143 0.00E+00 2.00E-05 0.00E+00

Ce-144 2.62E-14 3.00E-06 8.73E-09

Pr-144 2.62E-14 6.00E-04 4.36E-11

H-3 4.06E-06 1.00E-03 4.06E-03

TOTAL 1.61E-02

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-23

Note:1. The conditions for maximum individual dose calculation.2. The conditions for population dose calculation.3. The water of Squaw Creek is considered following evaluations.

- Dose from fish (Maximum individual dose)- Dose from shoreline (Maximum individual dose)

4. The water of Brazos River is considered following evaluation.- Dose from drinking water in Cleburne (Maximum individual dose and population dose)- Dose from irrigation water (Maximum individual dose and population dose)- Dose from sports fishing (Population dose)

5. The water of Whitney Reservoir is considered following evaluation.- Dose from drinking water in Whitney (Population dose)- Dose from shoreline, swimming and boating (Population dose)

6. Maximum individual doses are calculated for Squaw Creek Reservoir (SCR) considering fishing, swimming and shoreline activities.

Table 11.2-14R (Sheet 1 of 2)Input Parameters for the LADTAP II Code

Parameter Value

Midpoint of Plant Life(yr) 30

Circulating Water System discharge rate (gpm) 247,500

Water type selection Freshwater

Reconcentration model index 1 (Complete mix)

Discharge rate to receiving water(ft3/sec) 1.5(1)

45.4(2)

Total impoundment volume(ft3) 6.3E+09

Shore-width factor 0.2 (Squaw Creek)0.3(Whitney Reservoir)0.3 (SCR)

Dilution factor -Squaw Creek(3) 1.0

Dilution factor (6) 1.0

Dilution factor - Brazos River(4) 822.7(1)

27.2(2)

Dilution factor - Whitney Reservoir(5) 1645.4 (1)

54.4 (2)

Transit time – Squaw Creek (hr) 7.3

Transit time (SCR) 0.0

Transit time – Brazos River (hr) 66

Transit time – Whitney Reservoir (hr) 77

Irrigation rate(Liter/m2-month) 74.6

Animals considered for milk pathway Cows and Goats

Fraction of animal feed not contaminated 0

Fraction of animal water not contaminated 0

Source terms Table 11.2-10R

Source term multiplier 1

50 mile population 3,493,553

Total Production within 50 miles(kg/yr,L/yr) Leafy Vegetable : 25,000 kg/yrVegetable : 5,270,000 kg/yrMilk : 943,000 L/yrMeat : 281,000 kg/yr

Annual local harvest for sports harvest fishing(kg/yr) 324,375

Annual local harvest for commercial fishing harvest(kg/yr)

None

Annual local harvest for sports invertebrate harvest (kg/yr)

None

Annual local harvest for commercial invertebrate harvest (kg/yr)

None

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-24


Input Parameters for the LADTAP II Code

Parameter Value

Population using water-supply system 3722 (City of Whitney)53,440 (City of Cleburne)

Total shoreline usage time(person-hr/yr)

22,358,746

Total swimming usage time(person-hr/yr)

22,358,746

Total boating usage time(person-hr/yr) 22,358,746

Other parameters RG 1.109

CP COL 11.2(4)


Part 2, FSAR

Revision 211.2-25

Note:

Doses are for a single unit from liquid effluent releases during normal operation including AOOs.

Table 11.2-15R

Individual Doses from Liquid Effluents

Annual Doses (mrem/yr)

PATHWAY SKIN BONE LIVER T.BODY THYROID KIDNEY LUNG GI-LLI

Drinking

Adult - 2.40E-05 6.39E-03 6.39E-03 6.37E-03 6.38E-03 6.37E-03 6.42E-03

Teenager - 2.24E-05 4.51E-03 4.50E-03 4.49E-03 4.50E-03 4.49E-03 4.52E-03

Child - 6.32E-05 8.67E-03 8.63E-03 8.62E-03 8.64E-03 8.62E-03 8.65E-03

Infant - 6.16E-05 8.52E-03 8.47E-03 8.46E-03 8.48E-03 8.47E-03 8.48E-03

Fish

Adult - 7.86E-01 1.25E+00 8.83E-01 1.36E-01 5.15E-01 2.61E-01 1.72E-01

Teenager - 8.38E-01 1.26E+00 5.22E-01 1.04E-01 4.98E-01 2.56E-01 1.32E-01

Child - 1.05E+00 1.13E+00 2.49E-01 8.64E-02 4.26E-01 2.08E-01 9.74E-02

Shoreline

Adult 2.27E-03 1.95E-03 1.95E-03 1.95E-03 1.95E-03 1.95E-03 1.95E-03 1.95E-03

Teenager 1.27E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02 1.09E-02

Child 2.65E-03 2.27E-03 2.27E-03 2.27E-03 2.27E-03 2.27E-03 2.27E-03 2.27E-03

Irrigated Foods : Vegetables

Adult - 1.17E-04 4.64E-03 4.60E-03 4.53E-03 4.57E-03 4.54E-03 4.74E-03


Child - 4.38E-04 9.09E-03 8.82E-03 8.77E-03 8.89E-03 8.81E-03 8.99E-03

Irrigated Foods : Leafy Vegetables

Adult - 1.44E-05 5.72E-04 5.68E-04 5.58E-04 5.64E-04 5.60E-04 5.85E-04


Child - 2.19E-05 4.55E-04 4.42E-04 4.39E-04 4.45E-04 4.41E-04 4.50E-04

Irrigated Foods : Milk

Adult - 6.84E-05 2.80E-03 2.77E-03 2.71E-03 2.74E-03 2.72E-03 2.71E-03


Child - 2.95E-04 5.86E-03 5.62E-03 5.58E-03 5.67E-03 5.61E-03 5.58E-03

Irrigated Foods : Meat

Adult - 4.04E-05 9.71E-04 9.71E-04 9.60E-04 1.03E-03 9.61E-04 3.04E-03


Child - 6.34E-05 7.05E-04 7.01E-04 6.93E-04 7.65E-04 6.94E-04 1.48E-03

Total

Adult 2.27E-03 7.88E-01 1.27E+00 9.00E-01 1.53E-01 5.32E-01 2.78E-01 1.91E-01

Teenager 1.27E-02 8.49E-01 1.29E+00 5.48E-01 1.29E-01 5.24E-01 2.81E-01 1.59E-01

Child 2.65E-03 1.05E+00 1.16E+00 2.75E-01 1.13E-01 4.53E-01 2.34E-01 1.25E-01

Infant - 6.16E-05 8.52E-03 8.47E-03 8.46E-03 8.48E-03 8.47E-03 8.48E-03

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VLV-242B-N

VLV-

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VLV-

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VLV-

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VLV-

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VLV-

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VLV-

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VLV-

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VLV-222B-N

VLV-

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VLV-223B-N

VLV-242D-N

VLV-222A-N

VLV-241D-N

VLV-

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VLV-

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VLV-203B-N

VLV-223A-N

VLV-202A-N

VLV-241C-N

VLV-202B-N

VLV-242A-N

VLV-205 -N

VLV-242C-N

VLV-203A-N

VLV-

226 -

N

VLV-225 -N

LH

LH

LL

HH

LL

HH

EC8

LL

HH

EC8

LMS

W

HT

LMS

W

HT

VS

A

/B E

XHAU

STV

S

A/B

EXH

AUST

DS

FLO

OR

DR

AIN

DS

E

QU

IP.D

RAI

N

VS

A/B

EXA

UST

DS

EQ

UIP

. DR

AIN

(NO

N-R

ADIO

ACTI

VE)

DS

FLO

OR

DR

AIN

(NO

N-R

ADIO

ACTI

VE)

TUR

BIN

E S

UM

P

VS

R/B

EXA

UST

DS

EQ

UIP

. DR

AIN

(NO

N-R

ADIO

ACTI

VE)

DS

FLO

OR

DR

AIN

(NO

N-R

ADIO

ACTI

VE)

REFU

ELIN

G W

ATER

STOR

AGE

AUX.

TANK

DS

CP

CO

L 11

.2(6

)

Co

man

che

Pea

k N

ucl

ear

Po

wer

Pla

nt,

Un

its

3 &

4C

OL

Ap

pli

cati

on

Par

t 2,

FS

AR

Rev

isio

n 2

11.2

-29

Fig

ure

11.2

-201

Liq

uid

Was

te M

anag

emen

t S

yste

m P

ipin

g a

nd

Inst

rum

enta

tio

n D

iag

ram

(S

hee

t 4

of

10)

LOCA

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MPLE

LOCA

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(ED)

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(D)

(ED)

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PP

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ANK

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MP

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D-W

ASTE

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LDU

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NK

MTK

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D-N

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AN

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TK-0

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P

PT

P

PP

L.OL.O

F.C

F.C

F.C

F.C

F.C

F.C

F.O

F.O

F.C

F.C

F.C

F.C

F.O

F.O

025 -

N P

I

024 -

N P

I

ACR

020 -

N LI

CA

ACR

021 -

N LI

CA

ACR

022 -

N LI

CA

ACR

023 -

N LI

CA

P0

T17

5

P0T175

P20

0T

175

P15

0T

175

P15

0T

175

P0

T17

5

P0

T17

5

P20

0T

175

P0

T17

5

P0T175

TP17

50TP

1750

TP17

520

0

TP17

50TP

1750

TP17

520

0

VLV-

320A

-N

VLV-

323B

-N

VLV-

320B

-N

VLV-

322B

-N

VLV-

315A

-N

VLV-

319B

-N

VLV-

302 -

N

VLV-

304B

-NVL

V-30

5A-N

VLV-

310A

-N

VLV-

319C

-N

VLV-

319D

-N

VLV-

322A

-N

VLV-312A-N

VLV-

320D

-N

VLV-

305B

-NVL

V-30

4A-N

VLV-

318 -

N

VLV-

315B

-N

VLV-

310B

-N

VLV-

301 -

N

VLV-312B-N

VLV-

323A

-N

VLV-

317 -

N

VLV-

319A

-NVL

V-32

0C-N

AOV-

316 -

N

AOV-303C-N

AOV-

309 -

N

AOV-321A-N

AOV-303B-N

AOV-303A-N

AOV-

324B

-N

AOV-308A-N

AOV-

324A

-N

AOV-321C-N

AOV-308B-N

AOV-308D-N

AOV-303D-N

AOV-321D-N

AOV-308C-N

AOV-321B-N

LH

LH

LH

LH

DS

E

QU

IP.D

RA

IN

LMS

A

/B E

QU

IP.

DR

AIN

SU

MP

TAN

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SG

S B

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BLO

WD

OW

N M

IX D

EM

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SG

SA

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N M

IX D

EM

I.

SFS

A-S

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EM

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B-S

FP D

EM

I.

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T

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SS

GB

DR

AD

IATI

ON

MO

NIT

OR

SM

SD

EW

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UM

P

LMS

CH

EM

ICA

LD

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IN T

AN

K P

UM

P

LMS

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TER

GE

NT

DR

AIN

MO

NIT

OR

PU

MP

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UM

P T

AN

K

LMS

C

/V S

UM

P

LMS B-R

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UM

P T

AN

KLM

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AS

TEM

ON

ITO

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AN

K P

UM

P

LMS

AC

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DC

AR

BO

N F

ILTE

R

LMS

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AS

TEE

FFLU

EN

T D

EM

I.

LMS

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AS

TEE

FFLU

EN

T D

EM

I.

LMS

C-W

AS

TEE

FFLU

EN

T D

EM

I.

LMS

D-W

AS

TEE

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EN

T D

EM

I.

VS

A

/B E

XHA

US

T

LMS

NE

UTR

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NT

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N

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AG

EN

T TA

NK

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A

/B E

XHAU

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DS

A

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UM

P

CV

S A-H

OLD

UP

TA

NK

CV

S B-H

OLD

UP

TA

NK

CV

S C-H

OLD

UP

TA

NK

LMS

NE

UTR

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ZIN

GA

GE

NT

TAN

KLM

S

N

EU

TRA

LIZI

NG

AG

EN

T TA

NK

VS

A

/B E

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VS

A

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T

WAS

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FFLU

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A

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UM

PD

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MP

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P

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CATI

ON D

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SGS

LMS A

/B S

UM

P T

AN

K

PP

CP

CO

L 11

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)

Co

man

che

Pea

k N

ucl

ear

Po

wer

Pla

nt,

Un

its

3 &

4C

OL

Ap

pli

cati

on

Par

t 2,

FS

AR

Rev

isio

n 2

11.2

-30

Fig

ure

11.2

-201

L

iqu

id W

aste

Man

agem

ent

Sys

tem

Pip

ing

an

d In

stru

men

tati

on

Dia

gra

m (

Sh

eet

5 o

f 10

)

HH

HH

H

H

H

HH

LOCA

LSA

MPLE

LOCA

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MPLE

LOCA

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MPLE

LOCA

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MPLE

LOCA

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MPLE

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T

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AST

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FFLU

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MFT

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B-N

036 -

N P

DIA

035 -

N P

DIA

028 -

N P

DIA

029 -

N P

DIA

031 -

N P

DIA

032 -

N P

DIA

033 -

N P

DIA

034 -

N P

DIA

030 -

N P

DIA

SST-

003A

-N

SST-

003B

-N

P15

0T

175

P15

0T

175

P15

0T

175

P15

0T

175

P15

0T

175

TP17

520

0

TP17

520

0

TP17

520

0TP

175

200

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0

VLV-433D-N

VLV-433C-N

VLV-431A-N

VLV-405 -N

VLV-

439D

-N

VLV-

437C

-N

VLV-

421 -

N

VLV-

438C

-N

VLV-433B-N

VLV-

438A

-N

VLV-415 -N

VLV-

437B

-N

VLV-

447A

-N

VLV-

414 -

N

VLV-

437D

-N

VLV-

439C

-N

VLV-431C-N

VLV-431B-N VLV-444D-N

VLV-

434D

-N

VLV-

419 -

N

VLV-418 -N

VLV-440 -N

VLV-417 -N

VLV-

437A

-N

VLV-

438D

-N

VLV-408 -N

VLV-444A-NVLV-

439A

-N

VLV-444B-N

VLV-410 -N

VLV-403A-N

VLV-

422 -

N

VLV-431D-N

VLV-402B-N

VLV-

434A

-N

VLV-

411 -

N

VLV-

416 -

N

VLV-403B-N

VLV-442 -N

VLV-402A-N


VLV-

439B

-N

VLV-433A-N

VLV-444C-N

VLV-

434C

-N

VLV-

436D

-N

VLV-

446B

-N

VLV-

436B

-N

VLV-

436C

-N

VLV-

447B

-N

VLV-

413 -

N

VLV-

446A

-N

VLV-

438B

-N

VLV-

436A

-N

VLV-

420 -

N

VLV-

434B

-N

RESI

N FIL

L

RESI

N FI

LLRE

SIN

FILL

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N FI

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SIN

FILL

S

S

LMS

WA

STE

HO

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P T

AN

K P

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VS

B.A

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AP

FE

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DE

MI.

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TEM

ON

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LMS

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P

MW

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PP

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MO

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SR

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SR

ST

LMS

W

HT

SM

S

SR

ST

LMS

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HT

SM

S

SR

ST

LMS

W

HT

CP

CO

L 11

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Co

man

che

Pea

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ucl

ear

Po

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Pla

nt,

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its

3 &

4C

OL

Ap

pli

cati

on

Par

t 2,

FS

AR

Rev

isio

n 2

11.2

-31

Fig

ure

11.2

-201

L

iqu

id W

aste

Man

agem

ent

Sys

tem

Pip

ing

an

d In

stru

men

tati

on

Dia

gra

m (

Sh

eet

6 o

f 10

)

LOCA

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MPLE

LOCA

LSA

MPLE

P

P

P

P

P

TT

TP

T

F.C F.C

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MP

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ASTE

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TA

NK

PU

MP

MP

P-00

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EC6

SS CS

040 -

N P

I

041 -

N P

I

ACR

035 -

N R

ICA

ACR

044 -

N F

IA

ACR

038 -

N LI

CA

ACR

039 -

N LI

CA

ACR

043 -

N F

I

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N R

IA

P20

0T

175

P15

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150

P15

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150

P15

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150

P0

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0

P15

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150

P0

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0

P0T150

P0

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0

TP15

015

0

TP15

015

0

TP15

00TP

1500

VLV-

509A

-N

VLV-

510 -

N

VLV-

509B

-N

VLV-

525 -

N

VLV-517 -N

VLV-

506A

-N

VLV-

511B

-N

VLV-529 -N

VLV-505 -N

VLV-

521B

-N

VLV-521 -N

VLV-

521A

-N

VLV-

512A

-N

VLV-515B-N

VLV-

526 -

N

VLV-532 -N

VLV-

514B

-N

VLV-533 -N

VLV-541 -N

VLV-520 -N

VLV-

511A

-N

VLV-

506B

-N

VLV-

514A

-N

VLV-508A-N

VLV-530 -N

VLV-516 -N

VLV-

512B

-N

VLV-515A-N

VLV-508B-N

AOV-513A-N

AOV-504B-N

AOV-501A-N

AOV-

522A

-N

RCV-035B-N

AOV-

522B

-N

AOV-501B-N

AOV-504A-N

AOV-513B-N

RCV-035A-N

LH

LH

P P

HH H

CV

S

B.A

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AP

VS

A

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XHA

US

T

DS

A/B

SU

MP

PW

S

PM

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LMS

W

HT

LMS

WA

STE

DE

MIN

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ISC

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XHA

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T

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MP

DETE

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AIN

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S

LMS

WA

STE

DE

MIN

.

VLV-531-N

CP

CO

L 11

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)

Co

man

che

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ucl

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3 &

4C

OL

Ap

pli

cati

on

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t 2,

FS

AR

Rev

isio

n 2

11.2

-32

Fig

ure

11.2

-201

L

iqu

id W

aste

Man

agem

ent

Sys

tem

Pip

ing

an

d In

stru

men

tati

on

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7 o

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SAMPLING

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P

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SST-

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-N

SST-

004B

-N

ACR

077 -

N LI

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ACR

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CA

P15

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175

P15

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P0T175

P150T175

P15

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175

P15

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P0

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5

TP17

50

TP17

515

0

TP17

515

0

TP17

50

TP17

515

0

VLV-

625 -

N

VLV-

633 -

N

VLV-624 -N


VLV-

614 -

N

VLV-

601B

-N

VLV-

620 -

N

VLV-629 -N

VLV-

602A

-N

VLV-

623 -

NVL

V-63

2 -N

VLV-

613 -

NVL

V-61

5 -N

VLV-

601A

-N

VLV-

608 -

N

VLV-

622 -

N

VLV-

609 -

N

VLV-

611 -

N

VLV-

606 -

N

VLV-

626 -

N

VLV-

602B

-N

VLV-610 -N

AOV-617 -N

AOV-603 -N

AOV-

627 -

N

AOV-

631 -

N

S S LH

P

LH

P

LMS

W

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LMS

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CH

AR

GE

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SH

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WA

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CP

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)

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Pla

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Un

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3 &

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Ap

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cati

on

Par

t 2,

FS

AR

Rev

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n 2

11.2

-33

Fig

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11.2

-201

L

iqu

id W

aste

Man

agem

ent

Sys

tem

Pip

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an

d In

stru

men

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NEUTRALIZINGAGENT

MEASURINGTANK

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EC10

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P

L.O

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P0T175

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1500

TP17

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515

0

VLV-

735B

-N

VLV-

720 -

N

VLV-736 -N

VLV-

715 -

N

VLV-716 -N

VLV-

733 -

N

VLV-

735C

-N

VLV-

705 -

N

VLV-

735A

-N

VLV-

712 -

N

VLV-734 -N

VLV-

735D

-N

VLV-

731 -

N

VLV-

732 -

N

VLV-

718 -

N

VLV-

717 -

N

AOV-

719 -

N

ACR

059 -

N LI

CAH L

P

NA

OH

S

UP

PLY

DW

SD

W

LMS

D

-WH

T

LMS

C

-WH

T

LMS

B

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T

LMS

A

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T

SA

MP

LE S

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A

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A/B

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MP

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ISP

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CP

CO

L 11

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Co

man

che

Pea

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ucl

ear

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nt,

Un

its

3 &

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Ap

pli

cati

on

Par

t 2,

FS

AR

Rev

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n 2

11.2

-34

Fig

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11.2

-201

Liq

uid

Was

te M

anag

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Part 2, FSAR

Revision 211.3-1

11.3 GASEOUS WASTE MANAGEMENT SYSTEM




A site-specific cost benefit analysis using the guidance of RG 1.110 was performed based on the site-specific calculated radiation doses as a result of radioactive gaseous effluents during normal operations, including AOOs. The result of the dose analysis indicated a public exposure of less than 1 person-rem per year resulting from the discharge of radioactive effluents, effecting a dose cost of less than $1000 per year, in 1975 dollars. For conservatism, the population doses considered in the cost-benefit analysis were increased to 5.0 person-rem per year (Total Body) and 5.0 person-rem per year (Thyroid). Based on these population doses and the equipment and operating costs as presented in RG 1.110, the cost benefit analysis demonstrates that addition of processing equipment of reasonable treatment technology is not favorable or cost beneficial, and that the design provided herein complies with 10 CFR 50, Appendix I.

11.3.2 System Description

Add the following text at the end of the second paragraph in DCD Subsection 11.3.2.

The piping and instrumentation diagrams (P&IDs) for the gaseous waste management system (GWMS) are provided in Figure 11.3-201 (Sheets 1 through 3).

Replace the last sentence in the last paragraph in DCD Subsection 11.3.2 with the following.

The release point of vent stack is at an elevation of 1051’ 5”, which is same height of the top of the containment.

CP COL 11.3(8)

STD COL 11.3(9)

CP COL 11.3(3)


Part 2, FSAR

Revision 211.3-2

11.3.3.1 Radioactive Effluent Releases and Dose Calculation in Normal Operation

Replace the fifth and sixth paragraph in DCD Subsection 11.3.3.1 with the following.

The site-specific long-term annual average atmospheric dispersion factors (χ/Q) given in Tables 2.3-340 through 2.3-346 are bounded by the value given in DCD

Table 2.0-1 (1.6E-05 s/m3). These values are calculated by methods presented in RG1.111. Therefore, the radioactive concentrations at the exclusion area boundary (EAB) are bounded by the values given in DCD Tables 11.3-5 through 11.3-7. The maximum individual doses are calculated using the GASPAR II Code (Reference 11.3-17) which implements the methodology described in RG 1.109. The site-specific parameters for the GASPAR II Code calculation are tabulated in Table 11.3-8R. Calculated doses are tabulated in Table 11.3-9R. The gamma dose in air is 8.42E-02 mrad/yr and the beta dose in air is 6.50E-01 mrad/yr, which are less than the criteria of 10 mrad/yr and 20 mrad/yr, respectively,in 10 CFR 50, Appendix I. The doses to the total body, the skin, and the maximum organ are less than the criteria in 10 CFR 50, Appendix I: 5.38E-02 mrem/yr (5 mrem/yr Appendix I limit), 5.03E-01 mrem/yr (15 mrem/yr Appendix I limit), and 1.46E+00 mrem/yr [child’s bone] (15 mrem/yr Appendix I limit), respectively. The compliance with 10 CFR 20.1302 is also demonstrated. The doses to the maximally exposed individual at Squaw Creek Reservoir due to normal effluent releases from the plant vent and the evaporation pond are also calculated. These doses are calculated at the point of maximum exposure at Squaw Creek Reservoir, which occurs at a distance of 0.10 miles NNW of Units 3 & 4 for plant vent releases and at a distance of 0.41 miles NNW of the evaporation pond for evaporation pond releases. The doses to the maximally exposed individual at SCR were calculated based on a person occupying the worst-case location for 134 hours per year. The number of hours was conservatively assumed to be twice the number of hours of shoreline exposure for the maximum age group from Table E-5 of RG 1.109. The doses to an individual at SCR were conservatively included in the maximum individual doses even though SCR is a restricted area per the definition provided in 10 CFR 20.1003 because CPNPP has control of access to the reservoir and has restricted public access in the past. Doses to the maximum individual using SCR are given in Table 11.3-206.

The population doses within 50 miles are calculated using the GASPAR II Code (Reference 11.3-17). The GASPAR II Code input parameters for the population dose are tabulated in Table 11.3-8R and Table 11.3-201. The calculated doses due to plant vent releases are 2.71 person-rem (Total body) and 3.25 person-rem (Thyroid).

Additionally, the dose from the evaporation pond is also calculated using the GASPAR II Code (Reference 11.3-17). Half of the liquid effluent is assumed to be diverted into the evaporation pond. Conservatively, all of the radioactive nuclides

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-3

in the evaporation pond are assumed to be discharged to atmosphere as aerosol or vapor. The annual release rates from the evaporation pond to atmosphere are listed in Table 11.3-202, and parameters for the GASPAR II Code calculation are listed in Table 11.3-203. Liquid effluents contain no noble gases. Therefore, noble gases are not presented in the evaporation pond. Calculated individual doses are listed in Table 11.3-204. The maximum organ dose is 2.37E+00 mrem/yr (Adult’s GI-Tract). The population doses, including recreational use of SCR, are 1.05 person-rem (Total body) and 1.04 person-rem (Thyroid). Moreover, the total of individual doses from the vent stack and the evaporation pond are listed in Table 11.3-205. The maximum organ dose is 2.55E+00 mrem/yr (Adult’s GI-Tract). The total population doses resulting from normal plant and evaporation pond releases are 3.77 person-rem (Total body) and 4.29 person-rem (Thyroid). The results are well below the dose criteria in 10 CFR 50 Appendix I. According to NUREG-0543 (Reference 11.3-201), there is reasonable assurance that sites with up to four operating reactors that have releases within Appendix I design objective values are also in conformance with the EPA Uranium Fuel Cycle Standard, 40 CFR 190. Once the proposed CPNPP Units 3 and 4 are constructed, the Comanche Peak site will consist of four operating reactors.



11.3(1) Deleted from the DCD.


11.3(3) Onsite vent stack design parameters




11.3(6) Site-specific dose calculation

This COL item is addressed in Subsection 11.3.3.1, Table 11.3-8R, Table 11.3-9R, Table 11.3-201, Table 11.3-202, Table 11.3-203, Table 11.3-204 and Table 11.3-205 and Table 11.3-206.


11.3(8)Site-specific cost-benefit analysis



This COL item is addressed in Subsection 11.3.2 and Figure 11.3-201.

CP COL 11.3(3)

CP COL 11.3(6)

CP COL 11.3(8)

STD COL 11.3(9)CP COL 11.3(9)


Part 2, FSAR

Revision 211.3-4

11.3.8 References

Add the following references after the last reference in DCD Subsection 11.3.8.

11.3-201 U.S. Nuclear Regulatory Commission, Methods for Demonstrating LWR Compliance With the EPA Uranium Fuel Cycle Standard (40 CFR 190), NUREG-0543, Washington, DC, 1980.


Part 2, FSAR

Revision 211.3-5

Table 11.3-8R

Input Parameters for the GASPAR II Code (Sheet 1 of 2)

Parameter Value

χ/Q (s/m3)For maximum individual dose calculation

No Decay, Undepleted 4.40E-072.26 Day Decay, Undepleted 4.40E-07Day Decay, Depleted 3.90E-07For population dose calculation Section 2.3

D/Q (1/m2)For maximum individual dose calculation 4.50E-09For population dose calculation Section 2.3

Distance to Residence (mi) 0.79Midpoint of plant life (s) 9.46E+08 (30yr)Fraction of the year that leafy vegetables are grown. 1.0Fraction of the year that milk cows are on pasture. 1.0Fraction of milk-cow feed intake that is from pasture while on pasture.

1.0

Fraction of the year that goats are on pasture. 1.0Fraction of goat feed intake that is from pasture while on pasture.

1.0

Fraction of the maximum individual’s vegetable intake that is from his own garden.

0.76

Average absolute humidity over the growing season

(g/m3).8.0

Fraction of the year that beef cattle are on pasture. 1.0Fraction of beef-cattle feed intake that is from pasture while the cattle are on pasture

1.0

Animal considered for milk pathway Cow and GoatAnnual milk production for each distance and direction within 50 miles (l)

9.08E+08

Annual meat production for each distance and direction within 50 miles (kg)

4.25E+07

Annual vegetable production for each distance and direction within 50 miles (kg)

4.81E+08

Population Distribution Table 11.3-201

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-6

Note:

1. The dose conversion factors from GASPAR II are used instead of those found in RG 1.109 because they have been updated to reflect more current information. NUREG/CR-4653 provides further information on the dose factors used by GASPAR II.

2. Ba-137m is not included in the GASPAR library. Because of its short half-life, 2.552 minutes, Ba-137m has a negligible impact on the offsite doses.

Source term DCD Table 11.3-5(2)

(Sheet 1 to 3)

Other parameters RG 1.10(1)

SCR χ/Q and D/Q values for plant vent release

No decay, undepleted 6.0x10-5 s/m3

2.26 day decay, undepleted 6.0x10-5 s/m3

8.00 day decay, depleted 5.6x10-5 s/m3

D/Q for maximum individual dose calculation 3.9x10-7 m-2

Table 11.3-8R

Input Parameters for the GASPAR II Code (Sheet 2 of 2)

Parameter Value

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-7

Note:

1. Dose due to noble gases, including Ar-41.

2. Calculated doses are due to the addition of a single new unit.

Table 11.3-9R

Calculated Doses from Gaseous Effluents (Sheets 1 of 2)

Type of Dose Dose (1)(2)

Gamma dose in air (mrad/yr) 8.42E-02

Beta dose in air (mrad/yr) 6.50E-01

Dose to total body (mrem/yr) 5.38E-02

Dose to skin (mrem/yr) 5.03E-01

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-8

Note:1. Dose due to iodine, particulate, H-3 and C-142. Conservatively, both Cow Milk and Goat Milk are considered.3. Calculated doses are from the addition of a single new unit.

Table 11.3-9R

Calculated Doses from Gaseous Effluents (Sheets 2 of 2)Doses from Vent Stack Only

PathwayDose to each organ (1)(3) (mrem/yr)

GI-Tract Bone Liver Kidney Thyroid Lung

Ground 1.01E-01 1.01E-01 1.01E-01 1.01E-01 1.01E-01 1.01E-01

Vegetable

Adult 3.44E-02 2.50E-01 3.09E-02 2.48E-02 5.70E-02 2.27E-02

Teen 4.75E-02 3.62E-01 4.76E-02 3.83E-02 7.71E-02 3.53E-02

Child 8.77E-02 7.99E-01 1.01E-01 8.53E-02 1.59E-01 8.04E-02

Meat

Adult 1.42E-02 3.70E-02 8.36E-03 7.68E-03 8.79E-03 7.42E-03

Teen 9.96E-03 3.09E-02 6.90E-03 6.35E-03 7.13E-03 6.16E-03

Child 1.33E-02 5.77E-02 1.23E-02 1.16E-02 1.28E-02 1.13E-02

Cow Milk

Adult 9.72E-03 5.06E-02 1.65E-02 1.14E-02 5.40E-02 9.43E-03

Teen 1.66E-02 9.04E-02 2.91E-02 2.02E-02 8.75E-02 1.69E-02

Child 3.72E-02 2.17E-01 5.95E-02 4.42E-02 1.82E-01 3.87E-02

Infant 7.52E-02 3.96E-01 1.19E-01 8.71E-02 4.28E-01 7.89E-02

Goat Milk

Adult 1.09E-02 6.92E-02 3.33E-02 1.78E-02 6.42E-02 1.23E-02

Teen 1.83E-02 1.21E-01 5.78E-02 3.07E-02 1.03E-01 2.19E-02

Child 3.97E-02 2.86E-01 1.07E-01 6.13E-02 2.13E-01 4.63E-02

Infant 7.90E-02 4.95E-01 2.09E-01 1.14E-01 5.03E-01 9.18E-02

Inhalation

Adult 5.89E-03 1.53E-03 5.79E-03 5.70E-03 1.33E-02 9.33E-03

Teen 5.93E-03 1.81E-03 5.90E-03 5.81E-03 1.59E-02 1.13E-02

Child 5.09E-03 2.15E-03 5.25E-03 5.13E-03 1.79E-02 9.67E-03

Infant 2.90E-03 9.47E-04 3.07E-03 2.96E-03 1.48E-02 6.13E-03

Total(2)

Adult 1.76E-01 5.10E-01 1.96E-01 1.69E-01 2.98E-01 1.62E-01

Teen 1.99E-01 7.07E-01 2.48E-01 2.03E-01 3.92E-01 1.93E-01

Child 2.84E-01 1.46E+00 3.86E-01 3.09E-01 6.86E-01 2.88E-01

Infant2.58E-01 9.93E-01 4.32E-01 3.05E-01 1.05E+00 2.78E-01

CP COL 11.3(6)

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CP

CO

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)


Part 2, FSAR

Revision 211.3-10

Note:

1. The release rates are half of the total liquid release ratesthat be shown in Table 11.2-10R.

Table 11.3-202

Release Rates from the Evaporation Pond to Atmosphere

Isotope Release Rate(1)

(Ci/yr)

Isotope Release Rate(1)

(Ci/yr)

Na-24 2.35E-03 Rh-106 1.95E-02

P-32 0.00E+00 Ag-110M 3.00E-04

Cr-51 6.50E-03 Ag-110 3.60E-05

Mn-54 3.50E-04 Sb-124 0.00E+00

Fe-55 2.50E-04 Te-129M 3.90E-05

Fe-59 5.00E-05 Te-129 1.55E-04

Co-58 9.50E-04 Te-131M 1.25E-04

Co-60 0.00E+00 Te-131 3.80E-05

Ni-63 0.00E+00 I-131 2.00E-04

Zn-65 1.10E-04 Te-132 2.35E-04

W-87 1.75E-04 I-132 1.55E-04

Np-239 2.65E-04 I-133 4.05E-04

Rb-88 1.40E-02 I-134 4.45E-05

Sr-89 3.00E-05 Cs-134 5.00E-04

Sr-90 4.00E-06 I-135 3.90E-04

Sr-91 3.40E-05 Cs-136 1.08E-02

Y-91M 2.20E-05 Cs-137 1.00E-03

Y-91 5.00E-06 Ba-137M 2.30E-04

Y-93 1.55E-04 Ba-140 2.45E-03

Zr-95 1.00E-04 La-140 4.00E-03

Nb-95 5.00E-05 Ce-141 3.00E-05

Mo-99 8.20E-04 Ce-143 2.50E-04

Tc-99M 8.50E-04 Pr-143 3.95E-05

Ru-103 1.56E-03 Ce-144 8.50E-04

Rh-103M 1.55E-03 Pr-144 8.50E-04

Ru-106 1.91E-02 H-3 8.00E+02

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-11

Table 11.3-203

Input Parameters for Dose Calculation from Evaporation Pond (Sheet 1 of 2)

Parameter Value

χ/Q (s/m3)For maximum individual dose calculationNo Decay, Undepleted 3.10E-062.26 Day Decay, Undepleted 3.10E-068 Day Decay, Depleted 2.90E-06 For population dose calculation Section 2.3

D/Q (1/m2)For maximum individual dose calculation 2.10E-08For population dose calculation Section 2.3

Distance to Residence (mi) 0.31Midpoint of plant life (s) 9.46E+08(30yr)Fraction of the year that leafy vegetables are grown. 1.0Fraction of the year that milk cows are on pasture. 1.0Fraction of milk-cow feed intake that is from pasture while on pasture.

1.0

Fraction of the year that goats are on pasture. 1.0Fraction of goat feed intake that is from pasture while on pasture.

1.0

Fraction of the maximum individual’s vegetable intake that is from his own garden.

0.76

Average absolute humidity over the growing season

(g/m3).8.0

Fraction of the year that beef cattle are on pasture. 1.0Fraction of beef-cattle feed intake that is from pasture while the cattle are on pasture

1.0

Animal considered for milk pathway Cow and GoatAnnual milk production for each distance and direction within 50 miles (l)

9.08E+08

Annual meat production for each distance and direction within 50 miles (kg)

4.25E+07

Annual vegetable production for each distance and direction within 50 miles (kg)

4.81E+08

Population Distribution Table 11.3-201Source term Table 11.3-202

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-12

Note:

1. The dose conversion factors from GASPAR II are used instead of those found in RG 1.109 because they have been updated to reflect more current information. NUREG/CR-4653 provides further information on the dose factors used by GASPAR II.

Other parameters RG 1.109(1)

SCR χ/Q and D/Q values for evaporation pond release

No decay, undepleted 7.9x10-6 s/m3

2.26 day decay, undepleted 7.9x10-6 s/m3

8.00 day decay, depleted 7.3x10-6 s/m3

D/Q for maximum individual dose calculation 4.8x10-8 m-2

Table 11.3-203

Input Parameters for Dose Calculation from Evaporation Pond (Sheet 2 of 2)

Parameter Value

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-13

Note:

1. Dose due to iodine, particulate and H-3

2. Conservatively, both Cow Milk and Goat Milk are considered.

Table 11.3-204

Calculated Doses from Evaporation Pond

Pathway Dose to each organ (1) (mrem/yr)

GI-Tract Bone Liver Kidney Thyroid Lung

Ground 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02 2.27E-02

Vegetable

Adult 2.87E-01 1.33E-02 1.16E-01 1.13E-01 1.10E-01 1.04E-01

Teen 3.38E-01 2.04E-02 1.38E-01 1.34E-01 1.26E-01 1.19E-01

Child 3.54E-01 4.68E-02 2.17E-01 2.09E-01 1.99E-01 1.85E-01

Meat

Adult 1.89E+00 2.97E-02 1.62E-02 7.12E-02 1.50E-02 1.48E-02

Teen 1.18E+00 2.50E-02 9.98E-03 5.62E-02 9.01E-03 8.91E-03

Child 7.22E-01 4.69E-02 1.21E-02 7.31E-02 1.10E-02 1.08E-02

Cow Milk

Adult 3.97E-02 7.69E-03 5.11E-02 4.18E-02 4.38E-02 3.61E-02

Teen 5.10E-02 1.36E-02 7.35E-02 5.73E-02 5.95E-02 4.80E-02

Child 7.53E-02 3.18E-02 1.18E-01 9.07E-02 1.00E-01 7.58E-02

Infant 1.13E-01 5.32E-02 2.00E-01 1.39E-01 1.78E-01 1.17E-01

Goat Milk

Adult 7.39E-02 2.24E-02 1.19E-01 9.15E-02 8.15E-02 7.51E-02

Teen 9.59E-02 3.97E-02 1.76E-01 1.27E-01 1.09E-01 1.01E-01

Child 1.48E-01 9.33E-02 2.83E-01 2.02E-01 1.80E-01 1.59E-01

Infant 2.23E-01 1.56E-01 4.93E-01 3.09E-01 3.05E-01 2.47E-01

Inhalation

Adult 6.08E-02 5.36E-04 5.90E-02 5.92E-02 5.90E-02 7.72E-02

Teen 6.14E-02 7.53E-04 5.97E-02 5.98E-02 5.96E-02 9.08E-02

Child 5.33E-02 1.03E-03 5.28E-02 5.29E-02 5.28E-02 8.04E-02

Infant 3.04E-02 5.65E-04 3.04E-02 3.04E-02 3.05E-02 5.28E-02

Total(2)

Adult 2.37E+00 9.64E-02 3.84E-01 4.00E-01 3.32E-01 3.30E-01

Teen 1.75E+00 1.22E-01 4.80E-01 4.57E-01 3.86E-01 3.90E-01

Child 1.38E+00 2.43E-01 7.05E-01 6.51E-01 5.65E-01 5.34E-01

Infant 3.89E-01 2.33E-01 7.47E-01 5.01E-01 5.36E-01 4.40E-01

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-14

Note:

1. Dose due to iodine, particulate and H-3

2. Conservatively, both Cow Milk and Goat Milk are considered.

3. Calculated doses are from the addition of a single new unit.

Table 11.3-205

Total Doses Due to Gaseous Effluent from Vent Stack and Evaporation Pond

Pathway Dose to each organ (1)(3) (mrem/yr)

GI-Tract Bone Liver Kidney Thyroid LungGround 1.24E-01 1.24E-01 1.24E-01 1.24E-01 1.24E-01 1.24E-01

Vegetable

Adult 3.21E-01 2.63E-01 1.47E-01 1.38E-01 1.67E-01 1.27E-01

Teen 3.86E-01 3.82E-01 1.86E-01 1.72E-01 2.03E-01 1.54E-01

Child 4.42E-01 8.46E-01 3.18E-01 2.95E-01 3.58E-01 2.65E-01

Meat

Adult 1.90E+00 6.67E-02 2.46E-02 7.89E-02 2.38E-02 2.22E-02

Teen 1.19E+00 5.59E-02 1.69E-02 6.25E-02 1.61E-02 1.51E-02

Child 7.35E-01 1.05E-01 2.44E-02 8.47E-02 2.38E-02 2.21E-02

Cow Milk

Adult 4.94E-02 5.83E-02 6.76E-02 5.32E-02 9.78E-02 4.55E-02

Teen 6.76E-02 1.04E-01 1.03E-01 7.75E-02 1.47E-01 6.49E-02

Child 1.12E-01 2.49E-01 1.77E-01 1.35E-01 2.82E-01 1.15E-01

Infant 1.88E-01 4.49E-01 3.19E-01 2.26E-01 6.06E-01 1.96E-01

Goat Milk

Adult 8.48E-02 9.16E-02 1.52E-01 1.09E-01 1.46E-01 8.74E-02

Teen 1.14E-01 1.61E-01 2.34E-01 1.58E-01 2.12E-01 1.23E-01

Child 1.88E-01 3.79E-01 3.90E-01 2.63E-01 3.93E-01 2.05E-01

Infant 3.02E-01 6.51E-01 7.02E-01 4.23E-01 8.08E-01 3.39E-01

Inhalation

Adult 6.66E-02 2.07E-03 6.48E-02 6.49E-02 7.23E-02 8.65E-02

Teen 6.73E-02 2.56E-03 6.56E-02 6.56E-02 7.55E-02 1.02E-01

Child 5.84 E-02 3.18E-03 5.80E-02 5.80E-02 7.07E-02 9.01E-02

Infant 3.33E-02 1.51E-03 3.35E-02 3.34E-02 4.54E-02 5.89E-02

Total(2)

Adult 2.55E+00 6.06E-01 5.80E-01 5.68E-01 6.30E-01 4.92E-01

Teen 1.95E+00 8.29E-01 7.29E-01 6.59E-01 7.78E-01 5.83E-01

Child 1.66E+00 1.71E+00 1.09E+00 9.60E-01 1.25E-01 8.21E-01

Infant 6.47E-01 1.23E+00 1.18E+00 8.06E-01 1.58E+00 7.18E-01

CP COL 11.3(6)


Part 2, FSAR

Revision 211.3-15

Note: Calculated doses are from the addition of a single new unit.

Table 11.3-206

Total Gaseous Doses to the Maximally Exposed Individual at Squaw Creek Reservoir

Pathway Calculated Dose (mrem) per unit

Whole Body 7.22E-02

Thyroid 8.02E-02

TEDE 7.46E-02

CP COL 11.3(6)

Co

man

che

Pea

k N

ucl

ear

Po

wer

Pla

nt,

Un

its

3 &

4C

OL

Ap

pli

cati

on

Par

t 2,

FS

AR

Rev

isio

n 2

11.3

-16

Fig

ure

11.3

-201

Gas

eou

s W

aste

Man

agem

ent

Sys

tem

Pip

ing

an

d In

stru

men

tati

on

Dia

gra

m (

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CVS-

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-NP

T

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P

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P

PP

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EC9

EC6

EC9

EC6

EC6

EC6

EC6

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NCS

NCS

NCS

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EC6

EC6

EC6

EC6

EC6

EC6

CVS-

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-N

PICA

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-N

CVS-

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-N

PICA

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-N

F.C

F.C

F.C

F.C

F.C

F.C

F.C

F.C

F.C

F.C

F.C

F.O

F.C

F.C

F.C

F.O

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CS

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CS SS

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ACR

022 -

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ACR

021 -

N P

I

ACR

012 -

N P

ICA

ACR

019 -

N P

I

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011 -

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021 -

N P

ICA

020 -

N P

ICA

022 -

N P

ICA

019 -

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P15

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200

P20

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150

P10

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P100T200

P15

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P150T200

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P15

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P150T200

P10

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P15

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P10

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P100T200

P15

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P15

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200

P10

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P150T200

TP20

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0TP

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150

TP20

015

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200

150

SRV-045A-N

VLV-

021A

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VLV-031D-N

VLV-030B-N

VLV-

029 -

N

VLV-026B-N

VLV-

034D

-N

VLV-026A-N

VLV-012B-N

VLV-

040B

-N

VLV-

020B

-N

SRV-045B-N

VLV-

018A

-N

VLV-030C-N

VLV-

040A

-N

VLV-

009B

-N

VLV-

004A

-N

VLV-

014A

-N

VLV-007B-N

VLV-031B-N

SRV-045D-NVLV-

033D

-N

VLV-017B-N

VLV-

040D

-N

VLV-038D-N

VLV-

021B

-N

VLV-008 -N

VLV-

033C

-N

VLV-

013B

-N

VLV-031A-N

VLV-030D-N

VLV-027B-N

VLV-

046A

-N

VLV-

001A

-N

VLV-

019B

-NVLV-017A-N

VLV-

034B

-N

VLV-

041 -

N

VLV-

033B

-N

VLV-037C-N

VLV-

013A

-N

VLV-

001B

-N

VLV-

018B

-N

VLV-

005 -

N

VLV-

009A

-N

VLV-012A-N

VLV-

003A

-N

VLV-

028 -

N

VLV-037A-N

VLV-

034A

-N

VLV-

014B

-N

VLV-038C-N

VLV-

046B

-N

VLV-

002A

-N

VLV-027A-N

VLV-

019A

-N

VLV-

006 -

N

VLV-038B-N

VLV-037B-N

VLV-

033A

-N

VLV-037D-N

VLV-

002B

-N

SRV-045C-N

VLV-

042 -

N

VLV-

034C

-N

VLV-

020A

-N

VLV-

003B

-N

VLV-

035 -

N

VLV-038A-N

VLV-

040C

-N

VLV-

004B

-N

VLV-007A-N

VLV-030A-N

VLV-031C-N

AOV-036D-N

PCV-

021B

-NAO

V-03

9C-N

AOV-

039A

-N

PCV-

143 -

N

AOV-036C-N

PCV-021A-N

PCV-

023B

-N

AOV-036B-N

PCV-

023A

-N

PCV-022A-N

PCV-020A-N

AOV-

039B

-N

AOV-036A-N

PCV-

019B

-N

PCV-014 -N

AOV-

039D

-N

PCV-019A-N

PCV-

012 -

N

PCV-

022B

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V-02

0B-N

PCV-013 -N

PCV-

011 -

N

H

PT

H

PT

H

PT

PT

LMS

CV

DT

CV

SH

T

GM

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GM

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PW

SP

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.3(9

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Co

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11.3

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Fig

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11.3

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Gas

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Man

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VLV-

161 -

N

VLV-

114 -

N

VLV-132 -N

VLV-102 -N

VLV-

117 -

N

VLV-138A-N

VLV-

101 -

N

VLV-

147 -

N

VLV-135A-N

VLV-

155 -

N

VLV-138B-N

VLV-103 -N

VLV-

154 -

N

VLV-163 -N

VLV-

153 -

N

VLV-

144 -

NVLV-135B-N

VLV-

106 -

NVL

V-10

5 -N

VLV-162 -N

VLV-142 -N

VLV-

109 -

N

VLV-136 -N

VLV-131 -N

VLV-

148 -

N

VLV-143 -N

VLV-

152 -

N

VLV-

164 -

N

VLV-

140 -

N

VLV-

110 -

N

VLV-137 -N

PCV-

039B

-N

HCV-

032 -

N

AOV-

116 -

N

HCV-

031 -

N

PCV-

033 -

NPC

V-03

2C-N

PCV-

032 -

N

PCV-

031 -

N

AOV-

115 -

NPC

V-02

6 -N

RCV-

072C

-N

RCV-

072A

-N

AOV-

133 -

N

PCV-

032B

-N

HCV-

026 -

N

AOV-

151 -

N

PCV-

032A

-N

AOV-144 -N

RCV-

072B

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V-03

9A-N

ACR

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CP

CO

L 11

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)

Co

man

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Pea

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ear

Po

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Pla

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3 &

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Ap

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cati

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AR

Rev

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n 2

11.3

-18

Fig

ure

11.3

-201

Gas

eou

s W

aste

Man

agem

ent

Sys

tem

Pip

ing

an

d In

stru

men

tati

on

Dia

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m (

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SS

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PT

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F.C

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F.C

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EC6

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EC6

EC6

EC6

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PT

CS SS

CS SSCS SS

CS SS

SST-

009 -

N

SST-

014 -

N

SST-

006B

-N

SST-

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-N

SST-

008 -

N

SST-

013 -

N

SST-

007 -

N

SST-

011 -

N

SST-

010 -

N

SST-

012C

-N

SST-

012A

-N

SST-

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-N

P15

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0

P15

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200

P15

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P15

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0

P15

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150

P75

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0

P15

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0

P20

0T

400

P15

0T

200

P15

T20

0

P15

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200

P15

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0

P25

T20

0

P15

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0

P10

0T

200

P15

0T

150

P15

T20

0

VLV-

232 -

N

VLV-240A-N

VLV-

238 -

N

VLV-233 -N

VLV-231 -N

VLV-

241B

-N

VLV-

236A

-N

VLV-

243A

-N

VLV-240B-N

VLV-239B-N

VLV-

241A

-N

VLV-

242B

-N

VLV-

236B

-NVL

V-23

5B-N

VLV-239A-N

VLV-

243B

-N

VLV-

235A

-N

VLV-

205 -

N

SOV-

215 -

N

VLV-

202A

-N

VLV-

214 -

N

VLV-

211 -

N

SOV-

219B

-N

SOV-

219C

-N

SOV-

224 -

N

VLV-

202B

-NSO

V-20

3B-N

VLV-

223 -

N

AOV-

237 -

NSO

V-21

9A-N

SOV-

209 -

N

SOV-

221 -

N

SOV-

206 -

N

SOV-

212 -

N

SOV-

203A

-N

VLV-

208 -

N

SOV-

217 -

N

AOV-

234 -

N

S S

S

S

S SSS

SS S

S

P15

0T

200

PT

P15

T12

0

P15

T12

0

P150T120

P150T120

PT

P15

T12

0

P150T120

P150T120

GM

S

C

HA

RC

OA

L B

ED

GM

SW

AS

TEG

AS

SU

RG

E T

AN

K

RC

S

PR

T

SM

S

B

-SP

EN

T R

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S

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AG

E T

AN

K

SM

S

A

-SP

EN

T R

ESI

N

S

TOR

AG

E T

AN

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CV

S

B.A

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AP

.

GM

SW

AS

TE G

AS

DR

YER

LMS

C

VD

T

CV

S

VC

T

CV

S A-H

OLD

UP

TA

NK

CV

S B-H

OLD

UP

TA

NK

CV

S C-H

OLD

UP

TAN

K

O2

NG

S

N2

VS

A

/B E

XHA

US

T

H2

HG

S

H2

GM

SA

-WAS

TE G

AS

CO

MP

.

GM

SW

AS

TE G

AS

DR

YER

GM

SB

-WAS

TE G

AS

CO

MP

.

O2

NG

S

N2

VS

A

/B E

XHA

US

T

H2

HG

S

H2

DS

A

/B E

D S

UM

P

P15

T12

0

EC6

EC6

CP

CO

L 11

.3(9

)


Part 2, FSAR

Revision 211.4-1

11.4 SOLID WASTE MANAGEMENT SYSTEM


11.4.1.3 Other Design Considerations

Replace the fourth bullet in DCD Subsection 11.4.1.3 with the following.

• The current design provides collection and packaging of potentially contaminated clothing for offsite processing and/or disposal. Laundry services are performed offsite at appropriate vendor facilities. Waste resulting from these processes is forwarded directly from the vendor’s location to the disposal facility or returned to the long-term storage facility, as appropriate.


Replace the second paragraph in DCD Subsection 11.4.1.5 with the following.

The solid waste management system (SWMS) is designed to handle spent resin, sludge, oily waste, spent filters, and dry active waste including contaminated clothing, broken equipment, and maintenance items that cannot be easily decontaminated and reused. The SWMS provides staging areas and handling equipment for waste packaging and storage for the above wastes. Any liquid and gaseous wastes resulting from the solid waste handling operation are collected and returned to LWMS and GWMS, for processing. As such, there is no unique direct release pathway from the solid waste handling operation to the environment, and a cost benefit analysis for the SWMS is included in the consideration of the LWMS and GWMS.

11.4.1.6 Mobile or Temporary Equipment

Replace the last sentence in the paragraph in DCD Subsection 11.4.1.6 with the following.

The de-watering station is contracted for vendor services.

STD COL 11.4(5)

STD COL 11.4(6)



Part 2, FSAR

Revision 211.4-2

Process piping connections for the de-watering station have connectors different from the utility connectors to prevent cross-connection and contamination. The use of mobile or temporary equipment will require applicable regulatory requirements and guidance such as 10 CFR 50.34a, 10 CFR 20.1406 and RG 1.143 to be addressed. As such the purchase or lease contracts for any temporary and mobile equipment will specify the applicable criteria.

11.4.2.1.1 Dry active wastes

Replace the last paragraph in DCD Subsection 11.4.2.1.1 with the following.

Descriptions of wastes other than normally accumulated non-radioactive wastes such as wasted activated carbon from GWMS charcoal beds, solid wastes coming from component (Steam generator, Reactor vessel etc.) replacement activities, and other unusual cases will be described in the process control program and will be implemented in accordance with the milestone listed in Table 13.4-201.

11.4.2.2.1 Spent Resin Handling and De-watering Subsystem

Replace the last sentence in the second paragraph in DCD Subsection 11.4.2.2.1 with the following.

The P&ID for the SWMS is provided in Figure 11.4-201.

11.4.2.3 Packaging, Storage, and Shipping


Some of the dry active waste is only slightly contaminated and permits contact handling. The SWMS design does not include compaction equipment or drum dryer equipment. These wastes are treated by contract services from specialized facilities.

STD COL 11.4(10)

STD COL 11.4(1)

STD COL 11.4(8)

CP COL 11.4(7)


Part 2, FSAR

Revision 211.4-3

Replace the last sentence of the fourth paragraph in DCD Subsection 11.4.2.3 with the following.

A common radwaste interim storage facility is provided between Units 3 and 4 and is designed to store classes A, B, and C wastes from all four CPNPP units for up to 10 years. The common radwaste facility is designed to maintain onsite and offsite radiological doses within the limits in 10 CFR Part 20 and to maintain occupational exposures ALARA. This common radwaste interim storage facility reflects the site-specific waste volume reduction requirements and the current waste disposal strategy of the State of Texas. As design proceeds, the interim storage facility design may be revised to meet future waste acceptance and disposal criteria.

The common radwaste interim storage facility also includes a separate storage area for mixed waste and temporary staging of large equipment items for maintenance.

Specially shielded above grade cell vaults capable of storing a number of containers each are provided in the Remote Handled waste storage bay for very-high activity Class B, C waste. Facility shielding is designed to meet 10CFR 20 and 40 CFR 190 dose levels and minimize total facility construction costs.

The facility is designed to have separate control and equipment room ventilation, radiation monitoring, and fire protection systems designed to meet minimum essential requirements, and reduced capital cost.

The facility have remotely operated bridge crane with closed circuit television cameras and crane mounted storage bay lighting sources. Optimal crane designs are used to minimize total facility construction cost.

The radioactive mixed waste storage area is designed and constructed in accordance with permit application for its operation received from the State of Texas Commission on Environmental Quality.

Primary regulations and NRC/Industry guidance covering the design and operation of interim radioactive waste storage facilities are 10 CFR 20, 10 CFR 20.1801, 10 CFR 50 Appendix A, GDC 61 and 63,10 CFR 61, 10 CFR 71, 40 CFR 190, 49 CFR 173, NUREG-0800 SRP Appendix 11.4-A, Generic Letter 81-38, Information Notice No. 89-27 and SECY-94-0198.

This interim storage facility is provided with the knowledge that as of July 1, 2008, the low level radioactive waste disposal facility in Barnwell, South Carolina, is no longer accepting Class B and C wastes from sources in states such as Texas that are outside of the Atlantic Compact, and that the disposal facility in Clive, Utah, is still accepting Class A waste from out of state. Class B and C waste constitutes a small fraction of the total low level radioactive waste that will be generated by CPNPP.

CP COL 11.4(1)


Part 2, FSAR

Revision 211.4-4

CPNPP Units 3 and 4 are scheduled to load fuel and begin commercial operation no earlier than 2016. Therefore, these units will not be generating Class B and C waste prior to that time. Although the interim storage facility is designed to store the Class A, B and C wastes generated by CPNPP Units 1, 2, 3, and 4 for 10 years, the facility could store waste for a proportionally longer period of operation if only Class B and C wastes were to be stored in that facility. It is likely that another disposal facility will be available that will accept Class B and C waste from sources in Texas well before the storage space in the interim storage facility is filled. In particular, in 2004, Waste Control Specialists applied for a license from the Texas Commission on Environmental Quality to develop a disposal facility in Andrews County, Texas, for Class A, B, and C waste. In August 2008 Waste Control Specialists received a draft license from the Texas Commission on Environmental Quality. According to its website, Waste Control Specialists plans on opening the Andrews County site in about December of 2010. Notwithstanding this, if additional storage capacity were eventually to be needed, CPNPP could expand the interim storage facility or construct additional storage facilities in accordance with applicable NRC guidance, such as Regulatory Issue Summary 2008-12, Considerations for Extended Interim Storage of Low-Level Radioactive Waste by Fuel Cycle and Materials Licenses, and Standard Review Plan 11.4.

11.4.3.2 Process Control Program

Replace the content of DCD Subsection 11.4.3.2 with the following.

This subsection adopts NEI 07-10A, Generic FSAR Template for Process Control Program (Reference 11.4-23). The Process Control Program (PCP) describes the administrative and operational controls used for the solidification of liquid or wet solid waste and the dewatering of wet solid waste. The purpose of the PCP is to provide the necessary controls such that the final disposal waste product meets applicable federal regulations (10 CFR Parts 20, 50, 61, 71, and 49 CFR Part 173), state regulations, and disposal site waste form requirements for burial at a low level waste disposal site that is licensed in accordance with 10 CFR Part 61. Waste processing (solidification and/or dewatering) equipment and services may be provided by third-party vendors. The process used in the existing design meets the applicable requirements of the PCP. Table 13.4-201 provides the milestone for PCP implementation.

Additional onsite radioactive solid waste storage is provided and is discussed in Subsection 11.4.2.3.

STD COL 11.4(3)


Part 2, FSAR

Revision 211.4-5

11.4.4.5 Mobile De-watering System

Replace the last sentence in DCD Subsection 11.4.4.5 with the following.

The temporary mobile de-watering station installed in the SWMS is vendor supplied and operated within the specific requirements and layout based on vendor specifications. The temporary mobile de-watering station includes the necessary connections and fittings to interface with the plant piping. The connectors are uniquely designed to prevent inadvertent cross connection between the radioactive and non-radioactive plant piping. The piping also includes backflow inhibitors. Liquid effluent from the temporary mobile de-watering station is routed to the Liquid Waste Management System and the non-condensables are vented to the A/B ventilation system. An operating procedure will be provided prior to fuel load to ensure proper operation of the temporary mobile de-watering station to prevent the contamination of non-radioactive piping or uncontrolled releases of radioactivity into the environment so that guidance and information in Inspection and Enforcement (IE) Bulletin 80-10 (Ref. 11.4-29) is followed.

Applicable regulatory requirements and guidance, such as Regulatory Guide 1.143, are addressed by lease or purchase agreements associated with the use of a mobile dewatering subsystem for spent resin dewatering. The lease or purchase agreements include applicable criteria such as testing, inspection, interfacing requirements, operating procedures, and vendor oversight.

11.4.6 Testing and Inspection Requirements

Add the following sentences to the end of the last paragraph of DCD Subsection 11.4.6.

The licensee has an Epoxy Coatings Program used to facilitate the ALARA objective of promoting decontamination in radiologically controlled areas outside containment. The program controls refurbishment, repair, and replacement of coatings in accordance with the manufacturers' product data sheets and good painting practices. The program will be implemented as described in FSAR Table 13.4-201.



STD COL 11.4(7)

STD COL 11.4(4)

CP COL 11.4(9)


Part 2, FSAR

Revision 211.4-6

11.4(1) Plant-specific needs for onsite waste storage

This COL item is addressed in Subsection 11.4.2.1.1 and 11.4.2.3.

11.4(2) Deleted from the DCD

11.4(3) Plan for the process control program describing the process and effluent monitoring and sampling program


11.4(4) Mobile/portable SWMS connections


11.4(5) Offsite laundry facility processing and/or a mobile compaction

This COL item is addressed in Subsections 11.4.1.3 and 11.4.1.6.

11.4(6) Site-specific cost benefit analysis


11.4(7) Site-specific solid waste processing facility

This COL item is addressed in Subsections 11.4.1.6, 11.4.2.3 and 11.4.4.5.


This COL item is addressed in Subsection 11.4.2.2.1 and Figure 11.4-201.

11.4(9) The implementation milestones for the coatings program used in the SWMS


11.4(10) The mobile/portable SWMS connections


CP COL 11.4(1)STD COL 11.4(1)

STD COL 11.4(3)

STD COL 11.4(4)

STD COL 11.4(5)

STD COL 11.4(6)

STD COL 11.4(7)

STD COL 11.4(8)CP COL 11.4(8)

CP COL 11.4(9)

STD COL 11.4(10)

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Part 2, FSAR

Revision 211.5-1

11.5 PROCESS EFFLUENT RADIATION MONITORING AND SAMPLING SYSTEMS


Replace the last paragraph in DCD Section 11.5 with the following.

Essential service water (ESW) pipe tunnel structure at elevation 793’-1’’ has been changed in site-specific layout. However, the location of process effluent radiation monitors in DCD Chapter 11 is not affected by the modification of ESW pipe tunnel structure, and Figure 11.5-2 can be used except for the structure of ESW pipe tunnel remains valid. The structure of ESW pipe tunnel is shown on Figure 1.2-2R.

Add the following Subsections after DCD Subsection 11.5.2.5.2

11.5.2.5.3 Startup Steam Generator Blowdown Heat Exchanger Downstream Radiation Monitor (RMS-RE-110)

The startup steam generator blowdown heat exchanger downstream radiation monitor is a gamma detector; the detection range and other details are summarized in Table 11.5-201, item number 201. A process schematic for this monitor is shown in Figure 11.5-201.

This monitor is located downstream of the startup steam generator blowdown heat exchanger in the Steam Generator Blowdown System (refer to Section 10.4.8.2.1). RMS-RE-110 measures the total gamma content in the discharge stream of the Startup Steam Generator Blowdown System. When an abnormally high radiation level is detected, the blowdown lines are isolated and the blowdown water included in the Steam Generator Blowdown System is transferred to a waste holdup tank in the LWMS. The monitor is not safety-related and does not perform any safety function.

11.5.2.5.4 Evaporation Pond Discharge Radiation Monitor (RMS-RE-111)

The evaporation pond discharge radiation monitor is a gamma detector; the detection range and other details are summarized in Table 11.5-201, item number 202. A process schematic for this monitor is shown in Figure 11.5-201.

This monitor is located downstream of the evaporation pond (refer to Section 11.2.3.4). RMS-RE-111 measures the total gamma content in the discharge stream of the evaporation pond. When an abnormally high radiation level is detected, the discharge line is isolated, the discharge pump is secured, and the

CP SUP 11.5(1)

CP COL 11.5(1)

CP COL 11.5(1)


Part 2, FSAR

Revision 211.5-2

Main Control Room and Radwaste Control Room are alarmed automatically. The monitor is not safety-related and does not perform any safety function.

11.5.2.6 Reliability and Quality Assurance

Replace the third paragraph and the forth paragraph in DCD Subsection 11.5.2.6 with the following.

The procedures for acquiring and evaluating samples of radioactive effluents, as well as procedures for inspection, calibration, and maintenance of the monitoring and sampling equipment are developed in accordance with RG 1.21 and RG 4.15. The procedures for the radioactive waste systems are developed in accordance with RG 1.33. The analytical procedures are developed in accordance with RG 1.21. These procedures, described in Subsection 13.5.2, are prepared and implemented under the quality assurance program referenced in Chapter 17. Inspections are conducted daily on the process and effluent monitoring and sampling system through observance of the system channels. Periodically, the system is further checked during the course of reactor operation through the implementation of a check source. The detector response is compared to the instrument’s background count rate to determine functionality. Calibration of monitors is conducted through the use of known radionuclide sources as documented by national standards. Maintenance is conducted routinely on the monitoring and sampling system, which is easily accessible, as is the accompanying power supply. Electronic and sampling components undergo a full servicing, periodically, as detailed in the operational instructions in order to maintain consistent operation.

11.5.2.7 Determination of Instrumentation Alarm Setpoints for Effluents

Replace the second sentence in DCD Subsection 11.5.2.7 with the following.

The methodology for the calculation of the alarm setpoints is part of the ODCM described in Subsection 11.5.2.9.

11.5.2.8 Compliance with Effluent Release Requirements

CP COL 11.5(4)

CP COL 11.5(5)

STD COL 11.5(2)


Part 2, FSAR

Revision 211.5-3

Replace the last sentence in the first paragraph and the second paragraph in DCD Subsection 11.5.2.8 with the following.

Site-specific procedures on equipment inspection, calibration, maintenance, and regulated record keeping, which meet the requirements of 10 CFR 20.1301, 10 CFR 20.1302, and 10 CFR 50 Appendix I, are prepared and implemented under the quality assurance program referenced in Chapter 17.

11.5.2.9 Offsite Dose Calculation Manual

Replace the first paragraph and the second paragraph in DCD Subection 11.5.2.9 with the following.

Fulfillment of the 10 CFR 50 Appendix I guidelines requires effluent monitor data. A description of the monitor controls and the calculation of the monitor setpoints are part of the ODCM. The ODCM also provides the rationale for compliance with the radiological effluent Technical Specifications and for the calculation of appropriate setpoints for effluent monitors. The ODCM follows the guidance of NEI 07-09A. The ODCM and radiological effluent Technical Specifications, which reflect the new reactor units, are implemented in accordance with the milestone listed in Table 13.4-201. The ODCM will be re-written to apply to all units and to conform with the NEI template before receipt of radioactive material in accordance with FSAR Table 13.4-201. The manual will also contain the planned effluent discharge flow rates and addresses the numerical guidelines stated in 10 CFR 50, Appendix I (Ref. 11.5-3). The manual will be produced in accordance with the guidance of NUREG-1301 (Ref. 11.5-21), and NUREG-0133 (Ref. 11.5-18), and with the guidance of RG 1.109 (Ref. 11.5-22), RG 1.111 (Ref. 11.5-23), or RG 1.113 (Ref. 11.5-24). The manual will include a discussion of how the NUREGs, RGs, or alternative methods are implemented.

11.5.2.10 Radiological Environmental Monitoring Program


The program is going to be described in the plant Technical Specification and the ODCM, which reflect the new reactor units, is implemented in accordance with the milestone listed in Table 13.4-201. This program measures direct radiation using thermoluminescent dosimeters as well as analyses of samples of the air, water, vegetation, and fauna in the surrounding area. The guidance outlined in NUREG-1301 (Reference 11.5-21) and NUREG-0133 (Reference 11.5-18) is to be used when developing the radiological environmental monitoring program. The radiological environmental monitoring program follows the guidance of NEI 07-09A.

STD COL 11.5(4)

STD COL 11.5(5)

STD COL 11.5(1)

STD COL 11.5(2)

STD COL 11.5(3)


Part 2, FSAR

Revision 211.5-4



The results of site-specific cost-benefit analysis are described in Subsections 11.2.1.5 and 11.3.1.5.



11.5(1) Site-specific aspects

This COL item is addressed in Subsections 11.5.2.5.3, 11.5.2.5.4 and 11.5.2.9 and Table 11.5-201 and Figure 11.5-201.

11.5(2) Offsite dose calculation manual

This COL item is addressed in Subsection 11.5.2.7 and 11.5.2.9.

11.5(3) Radiological and environmental monitoring program


11.5(4) Inspection, decontamination, and replacement


11.5(5) Analytical procedures


11.5(6) The site-specific cost benefit analysis


STD COL 11.5(6)

CP COL 11.5(1)STD COL 11.5(1)

STD COL 11.5(2)

STD COL 11.5(3)

CP COL 11.5(4)STD COL 11.5(4)

CP COL 11.5(5)STD COL 11.5(5)

STD COL 11.5(6)

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Part 2, FSAR

Revision 211.5-6

Figure 11.5-201 Typical Process In-Line Radiation Monitor Schematic

RE

Radiation Signal Processor

Process line

Existing Waste Water Management Pond C

Discharge to Squaw Creek Reservoir

Applicable Radiation Monitors

Startup SG BlowdownHeat Exchanger

Evaporation Pond

Channel #201 RMS-RE-110202 RMS-RE-111

CP COL 11.5(1)

COL Application Part 2, FSAR - nrc.gov

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