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

Comanche Peak Nuclear Power Plant, Units 3 & 4
COL 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
11.2.1.6
11.2.2
11.2.3.1
11.2.3.2
11.2.3.4
11.2.4
11.2.5
11.2.6
11.3
GASEOUS WASTE MANAGEMENT SYSTEM ................................ 11.3-1
11.3.1.5
11.3.2
11.3.3.1
11.3.7
11.3.8
11.4
Site-Specific Cost-Benefit Analysis........................................ 11.2-1
Mobile or Temporary Equipment ........................................... 11.2-2
System Description................................................................ 11.2-3
Radioactive Effluent Releases and Dose Calculation in Normal
Operation ............................................................................... 11.2-5
Radioactive Effluent Releases Due to Liquid Containing Tank
Failures .................................................................................. 11.2-6
Evaporation Pond .................................................................. 11.2-7
Testing and Inspection Requirements ................................. 11.2-11
Combined License Information ............................................ 11.2-12
References .......................................................................... 11.2-12
Site-Specific Cost-Benefit Analysis........................................ 11.3-1
System Description................................................................ 11.3-1
Radioactive Effluent Releases and Dose Calculation in Normal
Operation ............................................................................... 11.3-2
Combined License Information .............................................. 11.3-3
References ............................................................................ 11.3-4
SOLID WASTE MANAGEMENT SYSTEM ....................................... 11.4-1
11.4.1.3
11.4.1.5
11.4.1.6
11.4.2.1.1
11.4.2.2.1
11.4.2.3
11.4.3.2
11.4.4.5
11.4.6
11.4.8
Other Design Considerations................................................. 11.4-1
Site-Specific Cost-Benefit Analysis........................................ 11.4-1
Mobile or Temporary Equipment ........................................... 11.4-1
Dry Active Wastes............................................................ 11.4-2
Spent Resin Handling and De-watering Subsystem ........ 11.4-2
Packaging, Storage, and Shipping ........................................ 11.4-2
Process Control Program ...................................................... 11.4-4
Mobile De-watering System................................................... 11.4-5
Testing and Inspection Requirements ................................... 11.4-6
Combined License Information .............................................. 11.4-6
11-i
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
TABLE OF CONTENTS (Continued)
Section
11.5
Title
Page
PROCESS EFFLUENT RADIATION MONITORING AND SAMPLING
SYSTEMS ......................................................................................... 11.5-1
11.5.2.5.3
11.5.2.5.4
11.5.2.6
11.5.2.7
11.5.2.8
11.5.2.9
11.5.2.10
11.5.2.11
11.5.5
Startup Steam Generator Blowdown Heat Exchanger
Downstream Radiation Monitor (RMS-RE-110)............... 11.5-1
Evaporation Pond Discharge Radiation Monitor (RMS-RE-111)
11.5-1
Reliability and Quality Assurance .......................................... 11.5-2
Determination of Instrumentation Alarm Setpoints for Effluents ......
11.5-2
Compliance with Effluent Release Requirements.................. 11.5-2
Offsite Dose Calculation Manual ........................................... 11.5-3
Radiological Environmental Monitoring Program................... 11.5-3
Site-Specific Cost-Benefit Analysis........................................ 11.5-4
Combined License Information .............................................. 11.5-4
11-ii
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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)
11-iii
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
Instrumentation Diagram
11.5-201
Typical Process In-Line Radiation Monitor Schematic
11-iv
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
ACRONYMS AND ABBREVIATIONS
A/B
AC/B
ACC
AMC
AOC
AOO
CFR
COL
CPNPP
CRF
CVCS
CVDT
CWS
DCD
DCEM
DLC
DOT
EAB
ESW
FSAR
GWMS
HT
HVAC
Hx
ICF
LCCF
LWMS
MCR
NEI
ODCM
PCP
PERMS
P&ID
PMW
PWR
R/B
RCP
auxiliary building
access building
accumulator
Annual Maintenance Cost
Annual Operating Cost
anticipated operational occurrence
Code of Federal Regulations
Combined License
Comanche Peak Nuclear Power Plant
Capital Recovery Factor
chemical and volume control system
containment vessel reactor coolant drain tank
Circulating Water System
Design Control Document
Direct Cost of Equipment and Materials
Direct Labor Cost
Department of Transportation
exclusion area boundary
essential service water
final safety analysis report
gaseous waste management system
holdup tank
heating, ventilation, and air conditioning
heat exchanger
Indirect Cost Factor
Labor Cost Correction Factor
liquid waste management system
Main Control Room
Nuclear Energy Institute
offsite dose calculation manual
process control program
process effluent radiation monitoring and sampling system
piping and instrumentation diagram
primary makeup water
pressurized-water reactor
reactor building
reactor coolant pump
11-v
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
ACRONYMS AND ABBREVIATIONS
RCS
RG
RWSAT
SG
SRST
SSC
SWMS
TAC
VCT
WHT
WMT
WMS
reactor coolant system
regulatory guide
refueling water storage auxiliary tank
steam generator
spent resin storage tank
structure, system, and component
solid waste management system
Total Annual Cost
volume control tank
waste holdup tank
waste monitor tank
Waste Management System
11-vi
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
11.1-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
CP COL 11.2(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.
11.2-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
STD COL 11.2(1)
STD COL 12.3(7)
Mobile or Temporary Equipment
Replace the last sentence in the first paragraph in DCD Subsection 11.2.1.6 with
the following.
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.
STD COL 11.2(8)
STD COL 12.3(7)
Replace the second paragraph of DCD Subsection 11.2.1.6 with the following.
11.2-2
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
The temporary mobile/portable equipment installed in the LWMS is vendorsupplied 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
CP COL 11.2(2)
CP COL 11.2(6)
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.
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 flow. The joined flows from the
11.2-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
This arrangement ensures that there is always circulating cooling water flow for
Unit 1 and/or Unit 2 and that 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
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.
11.2-4
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
If the monitor reaches the high setpoint, it sends signals to initiate pump
shutdown, valve closure and operator actions.
11.2.3.1
CP COL 11.2(2)
CP COL 11.2(4)
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 described in Section 11.1.
The version of the code is a proprietary modified version of the NRC PWR-GALE
code reflecting the specifics of the US-APWR design (Ref. 11.2-27). The
parameters used by the PWR-GALE Code are provided in DCD 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. For this site-specific
application, handling of contaminated laundry is contracted to off-site services.
Therefore, the detergent waste effluent is not 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 (SCR) 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 (WMTs). Currently, SCR has a tritium reporting level of 30,000 pCi/L
(Reference 11.2-201, ODCM for CPNPP Units 1 and 2). Based on an analysis, the
tritium concentration in SCR is anticipated to remain within the limit due to local
rainfall, evaporation, and controlled release to Squaw Creek.
However, during the maximum tritium generation condition (i.e., all four units
operating at full power), the tritium reporting level in SCR could be exceeded.
When it is determined to be undesirable to increase the tritium concentration in
SCR by discharging treated effluent from Units 3 and 4, up to half of the treated
liquid effluent from CPNPP Units 3 and 4 can be diverted to the evaporation pond
for temporary staging (Subsection 11.2.3.4).
Isotopic concentrations are calculated assuming 247,500 gpm per unit of
circulating water from CPNPP Units 1 and 2 (Reference 11.2-201). 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
11.2-5
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
2.37E+00 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 2.55E+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. 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 design of the
evaporation pond. According to NUREG-0543 (Reference 11.2-202), 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 Units 3
and 4 are constructed, the Comanche Peak site will consist of four operating
reactors.
11.2.3.2
CP COL 11.2(3)
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.
11.2-6
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
CP COL 11.2(3)
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 boric acid tank is provided in Subsection 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).
CP SUP 11.2(1)
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 receive, store, and process
treated radioactive effluent from the LWMS when it is undesirable to potentially
increase the SCR tritium concentration by discharging Unit 3 and 4 treated
effluent into SCR.
The open evaporation pond covers approximately 1.5 acres and can hold up to
2.1 million gallons of treated effluent from the LWMS. The pond liquid depth is 4 ft
with a 2-ft freeboard provided by a berm designed to prevent surface flooding from
entering the pond.
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 Units 3 and 4 treated 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 evaporation pond is constructed with two layers of high-density polyethelene
(HDPE) material suitable for this service. The HDPE 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 HDPE to allow movement and detection of leakage
from the top layer of HDPE. An alarm signal is sent to the MCR and the Radwaste
Control Room for operator action if leakage is detected.
The bottom of the evaporation pond is sloped toward the leak detection pit and
toward the discharge pump pit. The leak detection pit is a small pit underneath the
two layers of HDPE in which leakage through the HDPE is caught and detected.
The discharge pump pit is designed to facilitate pumping water out of the pond.
11.2-7
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
The pond does not need to be used continuously because diversion of flow is not
required during normal operating conditions and anticipated operational
occurrences. The design features (HDPE, 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 LWMS piping for transporting treated effluent from the discharge valve inside
the A/B to the evaporation 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 WMT discharge valves, 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 HDPE piping from the T/B wall to the yard near the
condensate storage tank. This portion of pipe is run in the condensate
transfer piping trench. A transition manhole is constructed near the plant
pavement boundary to accommodate splitting the radwaste effluent pipe
into two piping segments: the first segment goes to the Unit 1 flow receiver
and headbox, and the second segment goes to the radwaste evaporation
pond.
3.
Buried double-walled HDPE piping from the transition manhole to the Unit
1 flow receiver and head box and to the evaporation pond.
4.
Buried double-walled HDPE piping from the radwaste evaporation pond to
the Unit 1 flow receiver and head box. This pipe is buried parallel to the
effluent pipe from the WMTs and passes through the same manholes for
testing and inspection for piping integrity.
Additional manholes are provided for testing and inspection of the buried piping.
Each manhole is equipped with drain collection basins and leak detection
instruments to send a signal when activated by fluid in the manhole to a receiver
in the 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 Units 1 and 2 discharge boxes to prevent back
flow from the circulating water.
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.
11.2-8
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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 Standards” will be used in
designing the pumps
Geosynthetic Research Institute Standard GM13 will be utilized for HDPE
The evaporation 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.
The evaporation pond is constructed on top of a layer of clay with permeability
less than 1E-7 centimeter per second. The overall construction meets or exceeds
the requirements for waste water ponds stipulated by TCEQ. Some TCEQ
requirements are as follows:
•
In situ clay soils or placed and re-compacted clay soils meeting:
-
more than 30% passing a Number 200 mesh sieve
-
liquid limit greater than 30%
-
plasticity index greater than 15
-
a minimum thickness of two feet
11.2-9
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
-
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, two-hour rainfall
event
The evaporation pond will be initially inspected and tested following construction
and prior to the initial release of treated liquid effluents from the LWMS to the
pond. Testing and inspection of the evaporation pond will consist of the following:
•
Inspection of the liner for integrity, lack of damage, and welt seam
construction
•
Slope and drainage capability
•
Instrumentation calibration
•
Leakage detection system
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 meet the
TCEQ permit process and requirements, and include the following:
•
Water sample and analysis before draining and decontamination to
monitor concentration buildup
•
Liner and welt seam integrity
•
Drainage capability
•
Instrument calibration
•
Soil and groundwater contamination analysis per NEI 07-07
If testing and/or inspection results require the liner to be repaired, the pond
contents are removed, and the pond is rinsed before repair is performed.
Evaporation Pond Operation
When it is determined to be undesirable to increase the tritium concentration in
SCR by discharging treated effluent from CPNPP Units 3 and 4, the liquid effluent
from CPNPP Units 3 and 4 can be diverted to the evaporation pond for temporary
staging. When the tritium concentration in SCR decreases to a level that allows
discharge to the reservoir, the effluent in the evaporation pond is sampled and
analyzed for discharge into SCR. In the event that both CPNPP Units 1 and 2 are
11.2-10
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
temporarily not in operation, or when there is no dilution flow, the CPNPP Units 3
and 4 waste holdup tanks (WHTs) 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 treated liquid effluent on a temporary basis,
up to two years.
The evaporation pond is equipped with a centrifugal pump to discharge the
contents to SCR when the tritium concentration in SCR permits. The discharge
piping leaving the evaporation pond discharges into the Unit 1 receiver and head
box. A radiation monitor close to the evaporation pond discharge pump provides a
signal to automatically turn off the pump, shut the discharge valve, and alarm in
the MCR and the Radwaste Control Room. The setpoint of the evaporation pond
discharge radiation monitor is the same as the setpoint of the WMT discharge
radiation monitors that monitor flow going into the evaporation pond.
The evaporation pond discharge pump also acts as a recirculation pump for the
pond. The pond is recirculated sufficiently to obtain a representative sample at the
discharge pump before discharging the pond contents to the CPNPP Unit 1 flow
receiver and head box. The procedures for recirculation and sampling are
governed by the site-wide ODCM, which adopts NEI 07-09A, thus addressing
NRC guidance such as NUREG-1301 and RG 1.21.
The evaporation pond discharge pump and discharge isolation valve are under
supervisory control.
Operating procedures limit the use of the evaporation pond to receive treated
effluent on an as-needed basis and the pond will be washed each time it is
emptied. Sampling procedures require that the tritium concentration in SCR is
confirmed to be below the pre-determined setpoint before the evaporation pond
contents are discharged to SCR. The tritium sampling procedures are governed
by the site-wide ODCM, which has an implementation milestone established as
shown in Table 13.4-201.
11.2.4
CP COL 11.2(7)
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.
11.2-11
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.2.5
Combined License Information
Replace the content of DCD Subsection 11.2.5 with the following.
STD COL 11.2(1)
11.2(1) The mobile and temporary liquid radwaste processing equipment
This combined license (COL) item is addressed in Subsection 11.2.1.6.
CP COL 11.2(2)
11.2(2) Site-specific information of the LWMS
This COL item is addressed in Subsections 11.2.2 and 11.2.3.1.
CP COL 11.2(3)
11.2(3) The liquid containing tank failure
This COL item is addressed in Subsection 11.2.3.2.
CP COL 11.2(4)
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.
CP COL 11.2(5)
11.2(5) Site-specific cost benefit analysis
This COL item is addressed in Subsection 11.2.1.5.
CP COL 11.2(6)
11.2(6) Piping and instrumentation diagrams
This COL item is addressed in Subsection 11.2.2 and Figure 11.2-201.
CP COL 11.2(7)
11.2(7) The implementation milestones for the coatings program used in the
LWMS
This COL item is addressed in Subsection 11.2.4.
STD COL 11.2(8)
11.2(8) The mobile/portable LWMS connections
This COL item is addressed in Subsection 11.2.1.6.
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.
11.2-12
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-10R (Sheet 1 of 2)
CP COL 11.2(4)
Liquid Releases Calculated by PWR GALE Code(4) (Ci/yr)
Isotope
Shim
Bleed
Na-24
P-32
Cr-51
Mn-54
Fe-55
Fe-59
Co-58
Co-60
Ni-63
Zn-65
W-187
Np-239
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
Rb-88
Sr-89
Sr-90
Sr-91
Y-91m
Y-91
Y-93
Zr-95
Nb-95
Mo-99
Tc-99m
Ru-103
Rh-103m
Ru-106
Rh-106
Ag-110m
Ag-110
Sb-124
Te-129m
Te-129
Te-131m
Te-131
I-131
Te-132
I-132
I-133
I-134
Cs-134
I-135
Cs-136
Cs-137
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00001
0.00001
0.00010
0.00010
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00002
0.00000
0.00000
0.00001
0.00000
0.00002
0.00000
0.00030
0.00003
Detergent
Misc.
Turbine
Combined
Wastes
Building
Releases
Waste(3)
Corrosion and Activation Products
0.00029
0.00002
0.00031
N/A
0.00000
0.00000
0.00000
N/A
0.00008
0.00000
0.00008
N/A
0.00004
0.00000
0.00005
N/A
0.00003
0.00000
0.00003
N/A
0.00001
0.00000
0.00001
N/A
0.00012
0.00000
0.00013
N/A
0.00001
0.00000
0.00002
N/A
0.00000
0.00000
0.00000
N/A
0.00001
0.00000
0.00001
N/A
0.00002
0.00000
0.00002
N/A
0.00003
0.00000
0.00004
N/A
Fission Products
0.00187
0.00000
0.00187
N/A
0.00000
0.00000
0.00000
N/A
0.00000
0.00000
0.00000
N/A
0.00000
0.00000
0.00000
N/A
0.00000
0.00000
0.00000
N/A
0.00000
0.00000
0.00000
N/A
0.00002
0.00000
0.00002
N/A
0.00001
0.00000
0.00001
N/A
0.00001
0.00000
0.00001
N/A
0.00011
0.00000
0.00011
N/A
0.00011
0.00000
0.00011
N/A
0.00020
0.00000
0.00021
N/A
0.00020
0.00000
0.00021
N/A
0.00243
0.00005
0.00257
N/A
0.00243
0.00005
0.00257
N/A
0.00003
0.00000
0.00004
N/A
0.00000
0.00000
0.00000
N/A
0.00000
0.00000
0.00000
N/A
0.00000
0.00000
0.00001
N/A
0.00002
0.00000
0.00002
N/A
0.00002
0.00000
0.00002
N/A
0.00000
0.00000
0.00001
N/A
0.00001
0.00000
0.00002
N/A
0.00003
0.00000
0.00003
N/A
0.00001
0.00001
0.00002
N/A
0.00002
0.00003
0.00005
N/A
0.00001
0.00000
0.00001
N/A
0.00005
0.00000
0.00007
N/A
0.00002
0.00003
0.00005
N/A
0.00112
0.00000
0.00141
N/A
0.00008
0.00000
0.00011
N/A
11.2-13
TOTAL
Releases (1)
4.70E-03
0.00E+00
1.30E-03
7.00E-04
5.00E-04
1.00E-04
1.90E-03
0.00E+00
0.00E+00
2.20E-04
3.50E-04
5.30E-04
2.80E-02
6.00E-05
8.00E-06
6.80E-05
4.40E-05
1.00E-05
3.10E-04
2.00E-04
1.00E-04
1.64E-03
1.70E-03
3.11E-03
3.10E-03
3.81E-02
3.90E-05
6.00E-04
7.20E-05
0.00E+00
7.80E-05
3.10E-04
2.50E-04
7.60E-05
4.00E-04
4.70E-04
3.10E-04
8.10E-04
8.90E-05
1.00E-03
7.80E-04
2.16E-02
2.00E-03
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-10R (Sheet 2 of 2)
CP COL 11.2(4)
Liquid Releases Calculated by PWR GALE Code(4) (Ci/yr)
Isotope
Shim
Bleed
Misc.
Wastes
Ba-137m
Ba-140
La-140
Ce-141
Ce-143
Pr-143
Ce-144
Pr-144
All others
0.00003
0.00001
0.00001
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00031
0.00051
0.00000
0.00003
0.00001
0.00011
0.00011
0.00000
TOTAL
(except
H-3)
H-3 release
0.00065
0.01053
Turbine
Building
Combined
Releases
Fission Products
0.00000
0.00003
0.00001
0.00033
0.00001
0.00053
0.00000
0.00000
0.00000
0.00003
0.00000
0.00001
0.00000
0.00011
0.00000
0.00011
0.00000
0.00000
0.00025
0.01143
Detergent
Waste(3)
TOTAL
Releases (1)
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
4.60E-04
4.89E-03
8.00E-03
6.00E-05
5.00E-04
7.90E-05
1.70E-03
1.70E-03
1.20E-05
N/A
1.70E-01
1.60E+03
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.
11.2-14
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-11R (Sheet 1 of 2)
Liquid Releases with Maximum Defined Fuel Defects(4) (Ci/yr)
CP COL 11.2(4)
Isotope
Shim
Bleed
Na-24
P-32
Cr-51
Mn-54
Fe-55
Fe-59
Co-58
Co-60
Ni-63
Zn-65
W-187
Np-239
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
Rb-88
Sr-89
Sr-90
Sr-91
Y-91m
Y-91
Y-93
Zr-95
Nb-95
Mo-99
Tc-99m
Ru-103
Rh-103m
Ru-106
Rh-106
Ag-110m
Ag-110
Sb-124
Te-129m
Te-129
Te-131m
Te-131
I-131
Te-132
I-132
I-133
I-134
Cs-134
I-135
Cs-136
Cs-137
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.02891
0.00000
0.00000
0.00163
0.00000
0.73457
0.00000
0.12019
0.43698
Misc.
Wastes
Turbine
Building
Combined
Releases
Corrosion and Activation Products
0.00029
0.00002
0.00031
0.00000
0.00000
0.00000
0.00008
0.00000
0.00008
0.00004
0.00000
0.00004
0.00003
0.00000
0.00003
0.00001
0.00000
0.00001
0.00012
0.00000
0.00012
0.00001
0.00000
0.00001
0.00000
0.00000
0.00000
0.00001
0.00000
0.00001
0.00002
0.00000
0.00002
0.00003
0.00000
0.00003
Fission Products
0.03849
0.00000
0.03849
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00001
0.00000
0.00001
0.00002
0.00000
0.00002
0.01333
0.00000
0.01333
0.00527
0.00000
0.00527
0.00001
0.00000
0.00001
0.00001
0.00000
0.00001
0.00001
0.00000
0.00001
0.00001
0.00000
0.00001
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00033
0.00000
0.00033
0.00000
0.00000
0.00000
0.01445
0.00000
0.04336
0.00526
0.00000
0.00526
0.00015
0.00015
0.00030
0.00327
0.00491
0.00981
0.00005
0.00000
0.00005
1.83643
0.00000
2.57100
0.00083
0.00125
0.00208
0.44873
0.00000
0.56892
1.16528
0.00000
1.60226
11.2-15
Detergent
Waste(3)
TOTAL
Releases(1)
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
3.20E-04
0.00E+00
8.25E-05
4.13E-05
3.09E-05
1.03E-05
1.24E-04
1.03E-05
0.00E+00
1.03E-05
2.06E-05
3.09E-05
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
3.97E-02
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
1.03E-05
2.06E-05
1.38E-02
5.44E-03
1.03E-05
1.03E-05
1.03E-05
1.03E-05
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
3.40E-04
0.00E+00
4.47E-02
5.43E-03
3.09E-04
1.01E-02
5.16E-05
2.65E+00
2.15E-03
5.87E-01
1.65E+00
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-11R (Sheet 2 of 2)
CP COL 11.2(4)
Liquid Releases with Maximum Defined Fuel Defects(4) (Ci/yr)
Isotope
Shim
Bleed
Ba-137m
0.20917
Ba-140
0.00000
La-140
Misc.
Wastes
Detergent
Waste(3)
TOTAL
Releases (1)
0.00000
Turbine
Combined
Building
Releases
Fission Products
0.00000
0.20917
N/A
2.16E-01
0.00010
0.00000
0.00010
N/A
1.03E-04
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
1.53145
(except
H-3)
H-3 release
3.53272
0.00633
5.07050
N/A
5.23E+00
1.60E+03
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.
11.2-16
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-12R (Sheet 1 of 2)
CP COL 11.2(4)
Comparison of Annual Average Liquid Release Concentrations
with 10 CFR 20 (Expected Releases)
Isotope (1)
Na-24
P-32
Cr-51
Mn-54
Fe-55
Fe-59
Co-58
Co-60
Ni-63
Zn-65
W-187
Np-239
Rb-88
Sr-89
Sr-90
Sr-91
Y-91m
Y-91
Y-93
Zr-95
Nb-95
Mo-99
Tc-99m
Ru-103
Rh-103m
Ru-106
Ag-110m
Sb-124
Te-129m
Te-129
Te-131m
Te-131
I-131
Te-132
I-132
I-133
Discharge
Concentration
(μCi/ml) (2)(5)
1.19E-11
0.00E+00
3.30E-12
1.78E-12
1.27E-12
2.54E-13
4.82E-12
0.00E+00
0.00E+00
5.58E-13
8.88E-13
1.35E-12
7.11E-11
1.52E-13
2.03E-14
1.73E-13
1.12E-13
2.54E-14
7.87E-13
5.08E-13
2.54E-13
4.16E-12
4.32E-12
7.89E-12
7.87E-12
9.67E-11
1.52E-12
0.00E+00
1.98E-13
7.87E-13
6.35E-13
1.93E-13
1.02E-12
1.19E-12
7.87E-13
2.06E-12
Effluent
Concentration Limit
(μCi/ml) (3)
5.00E-05
9.00E-06
5.00E-04
3.00E-05
1.00E-04
1.00E-05
2.00E-05
3.00E-06
1.00E-04
5.00E-06
3.00E-05
2.00E-05
4.00E-04
8.00E-06
5.00E-07
2.00E-05
2.00E-03
8.00E-06
2.00E-05
2.00E-05
3.00E-05
2.00E-05
1.00E-03
3.00E-05
6.00E-03
3.00E-06
6.00E-06
7.00E-06
7.00E-06
4.00E-04
8.00E-06
8.00E-05
1.00E-06
9.00E-06
1.00E-04
7.00E-06
11.2-17
Fraction of
Concentration Limit(4)
2.39E-07
0.00E+00
6.60E-09
5.92E-08
1.27E-08
2.54E-08
2.41E-07
0.00E+00
0.00E+00
1.12E-07
2.96E-08
6.73E-08
1.78E-07
1.90E-08
4.06E-08
8.63E-09
5.58E-11
3.17E-09
3.93E-08
2.54E-08
8.46E-09
2.08E-07
4.32E-09
2.63E-07
1.31E-09
3.22E-05
2.54E-07
0.00E+00
2.83E-08
1.97E-09
7.93E-08
2.41E-09
1.02E-06
1.33E-07
7.87E-09
2.94E-07
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-12R (Sheet 2 of 2)
CP COL 11.2(4)
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)
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
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 2
4. 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.
11.2-18
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-13R (Sheet 1 of 2)
CP COL 11.2(4)
Comparison of Annual Average Liquid Release
Concentrations with 10 CFR 20 (Maximum Releases)
Isotope (1)
Discharge
Concentration
(μCi/ml) (2)(5)
Effluent
Concentration Limit
(μCi/ml) (3)
Fraction of
Concentration
Limit(4)
Na-24
P-32
Cr-51
Mn-54
Fe-55
Fe-59
Co-58
Co-60
Ni-63
Zn-65
W-187
Np-239
Rb-88
Sr-89
Sr-90
Sr-91
Y-91m
Y-91
Y-93
Zr-95
Nb-95
Mo-99
Tc-99m
Ru-103
Rh-103m
Ru-106
Ag-110m
Sb-124
Te-129m
Te-129
Te-131m
Te-131
I-131
Te-132
I-132
I-133
I-134
Cs-134
8.12E-13
0.00E+00
2.09E-13
1.05E-13
7.86E-14
2.62E-14
3.14E-13
2.62E-14
0.00E+00
2.62E-14
5.24E-14
7.86E-14
1.01E-10
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
2.62E-14
5.24E-14
3.49E-11
1.38E-11
2.62E-14
2.62E-14
2.62E-14
0.00E+00
0.00E+00
0.00E+00
0.00E+00
8.64E-13
0.00E+00
1.14E-10
1.38E-11
7.86E-13
2.57E-11
1.31E-13
6.73E-09
5.00E-05
9.00E-06
5.00E-04
3.00E-05
1.00E-04
1.00E-05
2.00E-05
3.00E-06
1.00E-04
5.00E-06
3.00E-05
2.00E-05
4.00E-04
8.00E-06
5.00E-07
2.00E-05
2.00E-03
8.00E-06
2.00E-05
2.00E-05
3.00E-05
2.00E-05
1.00E-03
3.00E-05
6.00E-03
3.00E-06
6.00E-06
7.00E-06
7.00E-06
4.00E-04
8.00E-06
8.00E-05
1.00E-06
9.00E-06
1.00E-04
7.00E-06
4.00E-04
9.00E-07
1.62E-08
0.00E+00
4.19E-10
3.49E-09
7.86E-10
2.62E-09
1.57E-08
8.73E-09
0.00E+00
5.24E-09
1.75E-09
3.93E-09
2.52E-07
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
0.00E+00
1.31E-09
1.75E-09
1.75E-06
1.38E-08
8.73E-10
4.36E-12
8.73E-09
0.00E+00
0.00E+00
0.00E+00
0.00E+00
1.08E-07
0.00E+00
1.14E-04
1.53E-06
7.86E-09
3.67E-06
3.27E-10
7.48E-03
11.2-19
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-13R (Sheet 2 of 2)
CP COL 11.2(4)
Comparison of Annual Average Liquid Release
Concentrations with 10 CFR 20 (Maximum Releases)
Isotope (1)
Discharge
Concentration
(μCi/ml) (2)(5)
Effluent
Concentration Limit
(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
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 2
4. 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.
11.2-20
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-14R (Sheet 1 of 2)
Input Parameters for the LADTAP II Code
CP COL 11.2(4)
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
(6)
1.0
Dilution factor
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/yr
Vegetable : 5,270,000 kg/yr
Milk : 943,000 L/yr
Meat : 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
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.
11.2-21
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-14R (Sheet 2 of 2)
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
11.2-22
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-15R
CP COL 11.2(4)
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
Teenager
-
1.89E-04 5.72E-03 5.60E-03
5.53E-03
5.60E-03
5.56E-03
5.80E-03
Child
-
4.38E-04 9.09E-03 8.82E-03
8.77E-03
8.89E-03
8.81E-03
8.99E-03
Adult
-
1.44E-05 5.72E-04 5.68E-04
5.58E-04
5.64E-04
5.60E-04
5.85E-04
Teenager
-
1.26E-05 3.82E-04 3.74E-04
3.70E-04
3.74E-04
3.71E-04
3.88E-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 : Leafy Vegetables
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
Teenager
-
1.23E-04 3.69E-03 3.58E-03
3.52E-03
3.58E-03
3.54E-03
3.53E-03
Child
-
2.95E-04 5.86E-03 5.62E-03
5.58E-03
5.67E-03
5.61E-03
5.58E-03
Adult
-
4.04E-05 9.71E-04 9.71E-04
9.60E-04
1.03E-03
9.61E-04
3.04E-03
Teenager
-
3.39E-05 5.81E-04 5.79E-04
5.72E-04
6.27E-04
5.73E-04
1.87E-03
Child
-
6.34E-05 7.05E-04 7.01E-04
6.93E-04
7.65E-04
6.94E-04
1.48E-03
Irrigated Foods : Meat
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
6.16E-05 8.52E-03 8.47E-03
8.46E-03
8.48E-03
8.47E-03
8.48E-03
Infant
-
Note:
Doses are for a single unit from liquid effluent releases during normal operation including AOOs.
11.2-23
Revision 3
CP COL 11.2(6)
RHS-MOV-002D-S
M
RHS-MOV-001D-S
M
RHS-MOV-002C-S
M
RHS-MOV-001C-S
M
RHS-MOV-002B-S
M
RHS-MOV-001B-S
M
RHS-MOV-002A-S
M
RHS-MOV-001A-S
M
RCS-MOV-111B-S
M
RCS-MOV-111A-S
M
CVS-HCV-100-S
CVS-HCV-012-S
RCS-MOV-118-S
M
RCS-MOV-116B-S
M
RCS-MOV-116A-S
M
RCS-VLV-021-S
RCS-PCV-061B-S
L.O
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
EC6
L.O
EC6
VLV-014 -N
EC8
VLV-013 -N
EC8
L.O
VLV-012 -N
EC8
VLV-011 -N
EC8
VLV-010 -N
EC8
VLV-009 -N
EC8
VLV-008 -N
EC8
VLV-007 -N
EC8
EC6
VLV-006 -N
EC8
VLV-005 -N
LICA
010 -N
PIA
010 -N
ACR
ACR
LIA
010 -N
PI
010 -N
L
H
EC8
P
T
EC6
EC8
0
200
VLV-021 -N
P
T
EC6
C/V SUMP
EC6
P
EC6
RCS
C/V REACTOR
COOLANT
DRAIN TANK
MTK-001 -N
LMS
0
200
EC6
EC8
VLV-030 -N VLV-046 -N
P
EC8
P
P
SRV-001 -N
P 25 / 15
T 200
EC8
P
T
T.C
VLV-054 -N
200
200
PRT
TI
010 -N
P
SS CS
EC6
T
F.C
T
T
EC2
EC2
T
ACR
H
RCS
P
T
150
300
EC2
60
300
VLV-031A-N
VLV-031B-N
EC8
VLV-018 -N
25
200
EC6
T
EC2
EC8
VLV-017 -N
P
T
T
P
T
EC6
P
T
P
T
EC6
T.V
EC6
T.V
P
T
T.V
VLV-057 -N
150
200
200
150
2485
650
EC8
V
200
200
V
P
T
200
200
A-C/V REACTOR
COOLANT DRAIN
PUMP
MPP-001A-N
P
T
B-C/V REACTOR
COOLANT DRAIN
PUMP
MPP-001B-N
P
T
AOV-016 -N
EC6
F.C
VDS
RCS VENT DRAIN
PMW
PI
011 -N
PI
012 -N
T
EC9
PCV-014 -N
EC6
F.C
100
200
P
T
PIC
014 -N
25
200
P
T
N2
VH
GA
VLV-033A-N
VLV-033B-N
VLV-034B-N
RCS D-LOOP DRAIN
RCS C-LOOP DRAIN
NGS
GMS
GMS
RCS B-LOOP DRAIN
RCS A-LOOP DRAIN
PT
014 -N
RCS
VLV-058 -N
RCS
R/V FLANGE LEAK OFF
AOV-060 -S
F.C
AOV-056 -S
F.C
VLV-016 -N
T
T
AOV-053 -S
F.C
CVS
EXCESS LETDOWN HX.
PEN#
284
EC2
PEN#
276R
P
T
OUTSIDE C/V
VLV-029 -N
EC6
P
T
EC6
PRT
AOV-055 -S
F.C
EC6
150
200
TIA
010 -N
EC6
P
T
T.C
AOV-052 -S
P
INSIDE C/V
VLV-034A-N
EC6
T
T
EC6
T
VLV-080 -N
VLV-038 -N
VLV-079 -N
EC6
T
11.2-24
T
EC8
T.C
T.V
200
200
INSIDE C/V
RWS
VLV-044 -N
VLV-041 -N
VLV-037 -S
150
175
300
200
OUTSIDE C/V
LOCAL
SAMPLE
P
T
T
VLV-043 -N P
VLV-040 -N P
P
VLV-035 -S VLV-036 -S
EC3
P
EC8
VLV-042 -N
T
EC6
VLV-039 -N
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 1 of 10)
SIS
D-ACC. TANK DRAIN
SIS
C-ACC. TANK DRAIN
SIS
B-ACC. TANK DRAIN
SIS
A-ACC. TANK DRAIN
CVS D RCP NO3 SEAL
LEAK OFF
CVS C RCP NO3 SEAL
LEAK OFF
CVS B RCP NO3 SEAL
LEAK OFF
CVS A RCP NO3 SEAL
LEAK OFF
VLV-015 -N
L
H
H
CVS RCP D NO2 SEAL
LEAK OFF
CVS RCP C NO2 SEAL
LEAK OFF
CVS RCP B NO2 SEAL
LEAK OFF
CVS RCP A NO2 SEAL
LEAK OFF
CVS RCP PURGE
WATER HEAD TANK
25
200
P
T
VLV-051 -N
EC6
VLV-083 -N
L.O
VLV-085 -N
EC8
25
200
P
T
EC6
VLV-086 -N
RCS-PCV-061A-S
TIA
109 -N
25
200
P
T
VLV-084 -N
VLV-087 -N
H
VLV-026 -N
VLV-025 -N
EC6
F.O
25
200
P
T
AOV-027 -N
VLV-028 -N
EC8
LCV-010B-S
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-092A-N
VLV-092B-N
EC8
EC6
EC8
EC6
200
200
P
T
F.C
F.C
200
200
P
T
T
EC6
EC2
EC2
EC6
200
300
LCV-010A-S PEN#
205 P
WHT
HT
RWSAT
LMS
CVS
Revision 3
CP COL 11.2(6)
DWS
DW
S
F.C
LIA
092 -N
P
LI
092 -N
P
T
150
150
T
EC4
VLV-124 -N
AOV-126 -N
F.O
P
T
0
200
VLV-127 -N
VS D-CONTAINMENT
RECIRCULATION UNIT
VS C-CONTAINMENT
RECIRCULATION UNIT
VS B-CONTAINMENT
RECIRCULATION UNIT
VS A-CONTAINMENT
RECIRCULATION UNIT
EC8
L
H
LICA
093A-N
0
200
LIA
093A-N
C/V SUMP
P
T
ACR
FIA
093A-N
L
H
HH
H
LI
093B-N
FIA
093B-N
RWS
RWSP
OVERFLOW LINE
LMS
CVDT RELIEF LINE
CVS RCP PWHT
RELIEF LINE
INSIDE C/V
OUTSIDE C/V
HH
H
T.C
T.V
T
T
T
F.C
VLV-173 -N
EC8
F.C
VLV-172 -N
EC8
FQ
094 -N
T
EC6
EC8
VLV-108 -N
P
T
0
150
LOCAL
SAMPLE
T
VLV-109 -N
P
T
WHT
EQUIP.DRAIN
VS
LMS
DS FLOOR DRAIN
DS
150
175
PI
106 -N
PI
109 -N
EC6
EC6
A-R/B SUMP
TANK
MTK-002A-N
B-R/B SUMP
TANK
MTK-002B-N
L
H
L
H
P
T
LICA
108A-N
PI
110 -N
P
T
LICA
105A-N
PI
107 -N
0
150
ACR
ACR
0
150
ACR
ACR
P
LICA
105B-N
P
L
H
LICA
108B-N
L
H
EC8
VLV-146 -N
VLV-150 -N
11.2-25
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 2 of 10)
VLV-123 -N
EC10
STAND PIPE
SOV-121 -N VLV-122 -N
L
HH
H
EC4
0
200
P
T
VS
CRDM COOLING UNIT
A-C/V SUMP
PUMP
MPP-002A-N
VLV-103A-N
VLV-102A-N
P
T
150
150
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
150
200
P
T
EC6
150
300
P
T
EC2
PEN#
207
EC2
EC6
AOV-105 -S
AOV-104 -S
VLV-103B-N
VLV-102B-N
150
200
P
T
B-C/V SUMP
PUMP
MPP-002B-N
VLV-142A-N VLV-143A-N
VLV-142C-N VLV-143C-N
150
200
P
T
150
200
P
T
A-R/B SUMP
PUMP
MPP-003A-N
C-R/B SUMP
PUMP
MPP-003C-N
150
150
P
T
150
150
P
T
150
150
P
T
150
150
P
T
150
150
P
T
B-R/B SUMP
PUMP
MPP-003B-N
D-R/B SUMP
PUMP
MPP-003D-N
VLV-142B-N VLV-143B-N
VLV-142D-N VLV-143D-N
VLV-144 -N
VLV-148 -N
150
150
P
T
150
150
P
T
EC6
EC8
LOCAL
SAMPLE
EC6
EC8
LOCAL
SAMPLE
0
150
P
T
0
150
P
T
VLV-145 -N
VLV-149 -N
EC8
EC6
EC6
0
150
P
T
0
150
0
150
P
T
P
T
VLV-151 -N
T
0
150
P
T
VLV-147 -N
T
P
T
P
T
150
175
150
175
WHT
EQUIP.DRAIN
R/B EXHAUST
WHT
EQUIP.DRAIN
R/B EXHAUST
DS FLOOR DRAIN
DS
VS
NCS B-SURGE TANK
LMS
DS FLOOR DRAIN
DS
VS
NCS A-SURGE TANK
LMS
Revision 3
CP COL 11.2(6)
P
T
150
150
EC6
P
T
EC8
0
150
PI
102 -N
VLV-204 -N
VLV-206 -N
LOCAL
SAMPLE
VLV-207 -N
VLV-203B-N
150
150
P
T
L
H
A/B SUMP TANK
MTK-004 -N
VLV-202B-N
EC6
150
150
P
T
ACR
ACR
LICA
101B-N
150
175
P
L
H
LMS
EC6
VS
P
DS REFUELING WATER
STORAGE AUX.TANK
DS FLOOR DRAIN
A/B EXHAUST
T
VLV-332 -N VLV-261 -N VLV-331 -N
WHT
EC6
VLV-205 -N
EC6
P
T
PI
096 -N
VLV-224 -N
VLV-226 -N
EC8
LOCAL
SAMPLE
VLV-227 -N
T
TURBINE BUILDING
SUMP
0
150
A/B EQUIPMENT
DRAIN SUMP
TANK
MTK-003 -N
L
H
LICA
095A-N
PI
097 -N
ACR
LICA
095B-N
150
175
ACR
P
T
P
L
H
LMS
EC6
WHT
VS
DS
EQUIP.DRAIN
A/B EXHAUST
A/B
R/B
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-225 -N
LICA
098A-N
ACR
L
H
LICA
104A-N
0
200
ACR
P
T
0
200
B-NONRADIOACTIVE
DRAIN SUMP
P
T
A-NONRADIOACTIVE
DRAIN SUMP
L
H
LICA
098B-N
ACR
LICA
104B-N
LOCAL
SAMPLE
ACR
LOCAL
SAMPLE
L
H
L
H
PI
099 -N
VLV-246 -N
PI
111 -N
VLV-249 -N
11.2-26
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 3 of 10)
LICA
101A-N
PI
103 -N
P
T
0
150
VLV-203A-N
VLV-202A-N
A-A/B SUMP
PUMP
MPP-006A-N
150
150
P
T
B-A/B SUMP
PUMP
MPP-006B-N
150
150
P
T
P
T
150
150
P
T
VLV-223B-N
150
150
P
T
VLV-222B-N
VLV-223A-N
VLV-222A-N
A-A/B
EQUIPMENT
DRAIN SUMP
PUMP
MPP-005A-N
150
150
P
T
B-A/B
EQUIPMENT
DRAIN SUMP
PUMP
MPP-005B-N
0
150
P
T
T
0
150
P
T
0
150
P
T
PI
100 -N
VLV-243 -N VLV-244 -N
PI
112 -N
VLV-247 -N VLV-248 -N
VLV-242C-N
VLV-241C-N
150
200
P
T
A-NONRADIOACTIVE
DRAIN PUMP
MPP-004A-N
C-NONRADIOACTIVE
DRAIN PUMP
MPP-004C-N
VLV-242A-N
VLV-241A-N
150
200
EC8
150
200
P
T
VLV-242D-N
D-NONRADIOACTIVE
DRAIN PUMP
MPP-004D-N
VLV-241D-N
P
T
VLV-242B-N
VLV-241B-N
B-NONRADIOACTIVE
DRAIN PUMP
MPP-004B-N
EC8
0
150
P
T
0
150
P
T
150
200
P
T
EC8
150
200
P
T
EC8
150
200
P
T
A/B EXAUST
TURBINE SUMP
R/B EXAUST
DS FLOOR DRAIN
(NON-RADIOACTIVE)
DS EQUIP. DRAIN
(NON-RADIOACTIVE)
VS
DS FLOOR DRAIN
(NON-RADIOACTIVE)
DS EQUIP. DRAIN
(NON-RADIOACTIVE)
VS
VLV-251 -N
Revision 3
CP COL 11.2(6)
VLV-315A-N
LOCAL
SAMPLE
P
VLV-319A-N VLV-320A-N
VLV-317 -N VLV-319B-N VLV-320B-N
AOV-316 -N
F.C
LMS
A/B EQUIP.
DRAIN SUMP TANK
F.O
(ED)
P
VLV-301 -N
AOV-321A-N
EQUIP.DRAIN
0
175
LICA
020 -N
150
175
0
175
P
T
0
175
VLV-310B-N
P
T
VLV-310A-N
ACR
VLV-304B-N
LMS NEUTRALIZING
AGENT TANK
P
T
P
P
DS
CVDT
P
T
200
175
P
(ED)
F.O
PI
024 -N
200
175
PI
025 -N
200
175
P
T
200
175
B-WASTE
HOLDUP TANK
PUMP
MPP-007B-N
P
T
P
T
P
T
L
H
0
175
0
175
ACR
VLV-322A-N VLV-323A-N AOV-324A-N
P
T
LICA
021 -N
A/B EXHAUST
B-WASTE
HOLDUP TANK
MTK-005B-N
VS
VLV-302 -N
SGS
SGBD
RADIATION MONITOR
A-WASTE
HOLDUP TANK
PUMP
MPP-007A-N
A/B SUMP
VLV-305B-N
L.O
P
LMS
AOV-321B-N
VLV-322B-N VLV-323B-N AOV-324B-N
A/B SUMP
LMS WASTE EFFLUENT
INLET FILTER
DS
CVS
C-HOLDUP TANK
CVS
B-HOLDUP TANK
CVS
A-HOLDUP TANK
LMS
A/B SUMP TANK
P
T
VLV-315B-N
0
175
LOCAL
SAMPLE
F.C
AOV-309 -N
P
VLV-319C-N VLV-320C-N
VLV-318 -N VLV-319D-N VLV-320D-N
(D)
P
LMS DETERGENT
DRAIN MONITOR PUMP
LMS CHEMICAL
DRAIN TANK PUMP
SMS
DEWATERING PUMP
AOV-308C-N
C/V SUMP
L
H
P
T
0
175
LICA
022 -N
A/B EXHAUST
C-WASTE
HOLDUP TANK
MTK-005C-N
VS
LMS NEUTRALIZING
AGENT TANK
P
T
150
175
DS
A/B SUMP
P
(D)
P
LMS WASTE
MONITOR TANK PUMP
LMS NEUTRALIZING
AGENT TANK
ACR
LMS
B-R/B SUMP TANK
LMS
LMS
A-R/B SUMP TANK
11.2-27
L
H
P
T
0
175
LICA
023 -N
A/B EXHAUST
D-WASTE
HOLDUP TANK
MTK-005D-N
VS
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 4 of 10)
P
T
A-WASTE
HOLDUP TANK
MTK-005A-N
L
H
VLV-304A-N
A/B EXHAUST
VLV-305A-N
L.O
VS
LMS NEUTRALIZING
AGENT TANK
B-SFP DEMI.
SFS
AOV-308A-N
A-SFP DEMI.
F.C
SFS
AOV-308B-N
P
AOV-303B-N
F.C
DS
F.C
F.O
AOV-321C-N
SGS A-SG BLOWDOWN
CATION DEMI.
F.C
SGS
A-SG
BLOWDOWN MIX DEMI.
F.O
SGS B-SG BLOWDOWN
CATION DEMI.
F.C
T
AOV-303A-N
F.C
0
175
P
T
AOV-321D-N
SGS
B-SG
BLOWDOWN MIX DEMI.
VLV-312A-N
VLV-312B-N
AOV-303C-N
F.C
0
175
P
T
AOV-303D-N
F.C
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
AOV-308D-N
ACR
DS
LMS D-WASTE
EFFLUENT DEMI.
LMS C-WASTE
EFFLUENT DEMI.
LMS B-WASTE
EFFLUENT DEMI.
LMS A-WASTE
EFFLUENT DEMI.
LMS ACTIVATED
CARBON FILTER
A/B SUMP
Revision 3
CP COL 11.2(6)
T
LMS WASTE
HOLDUP TANK PUMP
VLV-405 -N
SMS
LMS
SRST
WHT
P
T
150
175
200
175
VLV-402A-N
H
T
H
VLV-419 -N
T
PDIA
030 -N
VLV-416 -N
RESIN FILL
PDIA
028 -N
LOCAL
SAMPLE
VLV-415 -N
VLV-418 -N
B-WASTE
EFFLUENT
INLET FILTER
MFT-001B-N
H
LMS WASTE
MONITOR TANK
PDIA
029 -N
VLV-420 -N
VLV-422 -N
SMS
LMS
SMS
LMS
EC6
P
T
150
175
T
VLV-436A-N
150
175
P
200
175
PDIA
035 -N
H
VLV-436C-N
T
P
T
S
SST-003A-N
VLV-446A-N
200
175
VLV-439A-N
VLV-438A-N
T
RESIN FILL
RESIN FILL
PDIA
036 -N
H
VLV-439C-N
VLV-438C-N
T
SST-003B-N
S
H
H
T
LOCAL
SAMPLE
PDIA
033 -N
VLV-437C-N
LOCAL
SAMPLE
T
VLV-437A-N
PDIA
031 -N
VLV-446B-N
B-WASTE EFFLUENT
OUTLET STRAINER
VLV-447B-N
C-WASTE DEMI.
MDM-002C-N
VLV-434C-N
A-WASTE EFFLUENT
OUTLET STRAINER
P
T
VLV-447A-N
SRST
WHT
P
T
A-WASTE DEMI.
MDM-002A-N
VLV-434A-N
P
WMS WASTE
MONITOR TANK PUMP
CVS
B.A. EVAP FEED DEMI.
CVS
B.A.EVAP DESTILLATE.
SRST
WHT
VLV-421 -N
T
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-443 -N
VLV-441 -N
WHT
LMS
SRST
SRST
SMS
SMS
WHT
LMS
P
T
P
T
150
175
150
175
T
200
175
VLV-436D-N
T
P
T
200
175
D-WASTE DEMI.
MDM-002D-N
VLV-434D-N
P
VLV-436B-N
P
T
B-WASTE DEMI.
MDM-002B-N
VLV-434B-N
P
11.2-28
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 5 of 10)
VLV-413 -N
T
P
T
ACTIVATED
CARBON FILTER
MDM-001 -N
VLV-411 -N
P
A-WASTE
EFFLUENT
INLET FILTER
MFT-001A-N
VLV-410 -N
VLV-402B-N
VLV-403B-N
VLV-431A-N
VLV-444A-N
VLV-403A-N
VLV-408 -N
VLV-417 -N
VLV-433A-N
VLV-433C-N
RESIN FILL
VLV-439B-N
VLV-438B-N
T
VLV-433B-N
RESIN FILL
VLV-439D-N
VLV-438D-N
T
VLV-433D-N
VLV-431C-N
VLV-444C-N
VLV-440 -N
VLV-442 -N
VLV-431B-N
VLV-444B-N
VLV-431D-N
VLV-444D-N
H
H
LOCAL
SAMPLE
PDIA
034 -N
VLV-437D-N
T
VLV-414 -N
EC6
LOCAL
SAMPLE
PDIA
032 -N
VLV-437B-N
T
CVS PMW SUPPLY.
Revision 3
CP COL 11.2(6)
150
150
VLV-510 -N
P
T
P
AOV-513A-N
P
T
0
150
A-WASTE
MONITOR TANK
MTK-006A-N
F.C
VLV-511A-N VLV-512A-N
VLV-511B-N VLV-512B-N
P
F.C
AOV-501A-N
VS
0
150
VLV-506B-N
VLV-506A-N
P
T
A/B EXHAUST
P
T
P
T
0
150
L
H
0
150
CVS
LICA
038 -N
P
P
ACR
B.A.EVAP
DS
VLV-541 -N
F.C
150
150
P
T
150
150
B-WASTE
MONITOR TANK
PUMP
MPP-008B-N
PI
041 -N
P
T
A-WASTE
MONITOR TANK
PUMP
MPP-008A-N
PI
040 -N
A/B SUMP
P
AOV-513B-N
200
175
P
T
0
150
P
T
P
T
150
150
150
150
B-WASTE
MONITOR TANK
MTK-006B-N
P
T
F.O
T
P
AOV-504B-N
F.C
VLV-514B-N
VLV-509B-N
VLV-514A-N
VLV-509A-N
VS
LOCAL
SAMPLE
LOCAL
SAMPLE
A/B EXHAUST
L
H
LICA
039 -N
ACR
DS
A/B SUMP
T
VLV-520 -N
T
VLV-521B-N
VLV-521A-N
P
FI
043 -N
WHT
H
H
H
AOV-522B-N
AOV-522A-N
ACR
P
T
FIA
044 -N
RIA
035 -N
RICA
035 -N
150
150
ACR
ACR
LMS WASTE DEMIN.
LMS
SS CS
VLV-515B-N
11.2-29
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 6 of 10)
P
T
0
150
F.O
T
AOV-504A-N
VLV-505 -N
F.C
F.C
LMS WASTE DEMIN.
AOV-501B-N
VLV-508A-N
VLV-508B-N
VLV-521 -N
VLV-517 -N
VLV-516 -N
VLV-515A-N
VLV-533 -N
VLV-532 -N
RCV-035B-N
RCV-035A-N
VLV-530 -N
VLV-529 -N
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
EC6
VLV-531-N
P
VLV-526 -N VLV-525 -N
L.C
DISCHARGE HEADER
LMS DETERGENT DRAIN
MONITOR TANK PUMP
PWS PMW PUMP
Revision 3
CP COL 11.2(6)
A/B EXHAUST
A/B SUMP
VS
DS
0
175
P
T
P
T
0
175
VLV-606 -N
P
T
0
175
DETERGENT
DRAIN TANK
MTK-007 -N
VLV-602B-N
S
L
H
ACR
VLV-601B-N
VLV-601A-N
P
T
150
175
DETERGENT
DRAIN TANK
PUMP
MPP-009 -N
P
LICA
069 -N
SST-004B-N
S
SST-004A-N
PI
070 -N
P
T
150
175
VLV-608 -N
L
H
LICA
077 -N
VLV-609 -N
P
ACR
P
T
0
175
DETERGENT
DRAIN MONITOR
TANK
MTK-008 -N
VLV-611 -N
P
T
150
175
P
VLV-620 -N
P
T
P
0
175
VS
F.C
150
175
PI
078 -N
A/B SUMP
P
T
P
T
150
175
VLV-615 -N
VLV-622 -N VLV-623 -N
VLV-626 -N VLV-625 -N
DETERGENT
DRAIN MONITOR
TANK PUMP
MPP-010 -N
AOV-627 -N
P
DS
H
DETERGENT
DRAIN FILTER
MFT-002 -N
A/B EXHAUST
VLV-613 -N VLV-614 -N
PDIA
072 -N
150
175
T
AOV-631 -N
F.C
P
T
LMS
VLV-633 -N
150
150
WHT
VLV-632 -N
P
T
11.2-30
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 7 of 10)
F.O
VLV-602A-N
HAND WASH DRAIN
SAMPLING
VLV-610 -N
AOV-603 -N
SHOWER DRAIN
AOV-617 -N
F.C
0
175
P
T
LOCAL
SAMPLE
VLV-624 -N
150
175
P
T
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-630 -N VLV-629 -N VLV-628 -N
LMS
DISCHARGE HEADER
Revision 3
CP COL 11.2(6)
D-WHT
C-WHT
B-WHT
A-WHT
LMS
LMS
LMS
LMS
T
0
150
VLV-733 -N
P
T
NEUTRALIZING
AGENT
MEASURING
TANK
MTK-010 -N
VLV-736 -N
0
175
P
T
VLV-732 -N
EC10
L
H
L.O
EC6
EC10
ACR
DW
DWS
LICA
059 -N
SUPPLY
NAOH
SS CS
VLV-705 -N
P
T
P
T
0
175
0
175
CHEMICAL
DRAIN TANK
MTK-009 -N
A/B EXHAUST
DS
P
A/B SUMP
P
T
150
175
CHEMICAL
DRAIN TANK
PUMP
MPP-011 -N
VLV-717 -N
SAMPLE SINK
NCS
VS
PI
060 -N
P
T
0
175
P
VLV-712 -N
NCS
VLV-718 -N
VLV-716 -N
VLV-720 -N
AOV-719 -N
VLV-715 -N
LOCAL
SAMPLE
11.2-31
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 8 of 10)
VLV-735A-N
T
VLV-735B-N
T
VLV-735C-N
T
VLV-735D-N
T
GLASS GAUGE
P
T
0
150
VLV-731 -N
VLV-734 -N
0
175
P
T
EC6
0
175
P
T
P
T
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
150
175
P
T
LMS
WHT
TO DISPOSAL
Revision 3
CP COL 11.2(6)
B- Waste
Monitor Tank
ATK-006B
A- Waste
Monitor Tank
ATK-006A
B- Waste
Monitor Tank
ATK-006B
A- Waste
Monitor Tank
ATK-006A
Unit 4
Unit 3
VLV-521B
3"-T42
VLV-521A
3"-T42
AOV-522B
3"-DA42R
AOV-522A
3"-DA42R
AOV-522B
3"-DA42R
AOV-522A
3"-DA42R
VLV-521B
3"-T42
VLV-521A
3"-T42
FE
FE
RE
RE
VLV-531
3"-X42D
RCV-035A
3"-DA42R
VLV-531
3"-X42D
Unit 4
RCV-035B
3"-DA42R
RCV-035B
3"-DA42R
RCV-035A
3"-DA42R
Outside
Yard
Evaporation Pond
Evaporation Pond
Discharge Pump
Local Sample
RE
Unit 1 Flow
Receiver &
Head Box
(existing)
11.2-32
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 9 of 10)
B- Waste
Monitor Tank
Pump
APP-008B
A- Waste
Monitor Tank
Pump
APP-008A
B- Waste
Monitor Tank
Pump
APP-008B
A- Waste
Monitor Tank
Pump
APP-008A
Unit 3
(shown in
detail on
Sheet 6)
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
FE
To SCR via
Unit 1
Circulating
Water Return
Header and
Discharge
Outfall
(exisiting)
Revision 3
CP COL 11.2(6)
11.2-33
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 10 of 10)
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.3
GASEOUS WASTE MANAGEMENT SYSTEM
This section of the referenced DCD is incorporated by reference with the following
departures and/or supplements.
11.3.1.5
CP COL 11.3(8)
Site-Specific Cost-Benefit Analysis
Replace the third paragraph in DCD Subsection 11.3.1.5 with the following.
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
STD COL 11.3(9)
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).
CP COL 11.3(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.
11.3-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.3.3.1
CP COL 11.3(6)
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 11.3-6 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
11.3-2
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
11.3.7
Combined License Information
Replace the content of DCD Subsection 11.3.7 with the following.
11.3(1) Deleted from the DCD.
11.3(2) Deleted from the DCD.
CP COL 11.3(3)
11.3(3) Onsite vent stack design parameters
This COL item is addressed in Subsection 11.3.2.
11.3(4) Deleted from the DCD.
11.3(5) Deleted from the DCD.
CP COL 11.3(6)
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(7) Deleted from the DCD.
CP COL 11.3(8)
11.3(8)Site-specific cost-benefit analysis
This COL item is addressed in Subsection 11.3.1.5.
STD COL 11.3(9)
CP COL 11.3(9)
11.3(9) Piping and instrumentation diagrams
This COL item is addressed in Subsection 11.3.2 and Figure 11.3-201.
11.3-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
11.3-4
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-8R
CP COL 11.3(6)
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-07
2.26 Day Decay, Undepleted
4.40E-07
Day Decay, Depleted
3.90E-07
For population dose calculation
Section 2.3
2
D/Q (1/m )
For maximum individual dose calculation
For population dose calculation
4.50E-09
Section 2.3
Distance to Residence (mi)
0.79
Midpoint of plant life (s)
9.46E+08 (30yr)
Fraction of the year that leafy vegetables are grown.
1.0
Fraction of the year that milk cows are on pasture.
1.0
Fraction of milk-cow feed intake that is from pasture
while on pasture.
Fraction of the year that goats are on pasture.
1.0
Fraction of goat feed intake that is from pasture while on
pasture.
Fraction of the maximum individual’s vegetable intake
that is from his own garden.
Average absolute humidity over the growing season
(g/m3).
Fraction of the year that beef cattle are on pasture.
1.0
Fraction of beef-cattle feed intake that is from pasture
while the cattle are on pasture
Animal considered for milk pathway
Annual milk production for each distance and direction
within 50 miles (l)
Annual meat production for each distance and direction
within 50 miles (kg)
Annual vegetable production for each distance and
direction within 50 miles (kg)
Population Distribution
11.3-5
1.0
0.76
8.0
1.0
1.0
Cow and Goat
9.08E+08
4.25E+07
4.81E+08
Table 11.3-201
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-8R
CP COL 11.3(6)
Input Parameters for the GASPAR II Code (Sheet 2 of 2)
Parameter
Value
Source term
DCD Table 11.3-5(2)
(Sheet 1 to 3)
Other parameters
RG 1.109(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
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.
11.3-6
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-9R
CP COL 11.3(6)
Calculated Doses from Gaseous Effluents (Sheet 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
Note:
1. Dose due to noble gases, including Ar-41.
2. Calculated doses are due to the addition of a single new unit.
11.3-7
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-9R
CP COL 11.3(6)
Calculated Doses from Gaseous Effluents (Sheet 2 of 2)
Doses from Vent Stack Only
Pathway
Dose to each organ (1)(3) (mrem/yr)
GI-Tract
1.01E-01
Bone
1.01E-01
Liver
1.01E-01
Kidney
1.01E-01
Thyroid
1.01E-01
Lung
1.01E-01
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
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
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
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
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
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
2.58E-01
9.93E-01
4.32E-01
3.05E-01
1.05E+00
2.78E-01
Ground
Vegetable
Meat
Cow Milk
Goat Milk
Inhalation
Total(2)
Infant
Note:
1. Dose due to iodine, particulate, H-3 and C-14
2. Conservatively, both Cow Milk and Goat Milk are considered.
3. Calculated doses are from the addition of a single new unit.
11.3-8
Revision 3
CP COL 11.3(6)
0
0
0
0
0
0
0
0
0
16
15
33
13
1
1
0
ENE
E
ESE
SE
SSE
S
SSW
SW
WSW
W
WNW
NW
NNW
0-1
N
NNE
NE
Direction
0
0
4
25
40
114
126
95
109
17
5
3
1
13
17
11
1-2
25
84
74
151
265
40
19
33
31
31
12
7
17
39
39
37
2-3
46
141
82
4644
136
29
1135
35
62
105
57
8
32
111
92
228
3-4
5377
340
1162
1920
5917
1153
369
206
204
313
560
2295
1949
74921
12920
5473
5-10
11.3-9
146
37
145
3679
1314
588
32
70
29
161
110
6
114
266
180
282
4-5
4410
2658
836
500
382
1650
780
905
888
645
925
1243
6660
16318
12812
6950
10-20
Distance(mi)
67032
94985
3528
2778
5164
1003
2903
1528
40500
5302
1675
2789
5089
25429
12527
17815
20-30
134023
16681
7779
34161
14827
1320
451
1488
10651
2108
1691
2885
58611
138627
125434
694190
30-40
Population Distribution within 50 mi for Population Dose Calculation
Table 11.3-201
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Revision 3
30361
145586
124591
6
270180
17747
18881
4755
4572
3655
6930
1424
5304
923
1495
1440
10106
40-50
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-202
CP COL 11.3(6)
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
Note:
1. The release rates are half of the total liquid release rates
that be shown in Table 11.2-10R.
11.3-10
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-203
CP COL 11.3(6)
Input Parameters for Dose Calculation from Evaporation
Pond (Sheet 1 of 2)
Parameter
χ/Q
Value
(s/m3)
For maximum individual dose calculation
No Decay, Undepleted
3.10E-06
2.26 Day Decay, Undepleted
3.10E-06
8 Day Decay, Depleted
2.90E-06
For population dose calculation
Section 2.3
(1/m2
D/Q
)
For maximum individual dose calculation
For population dose calculation
2.10E-08
Section 2.3
Distance to Residence (mi)
0.31
Midpoint of plant life (s)
9.46E+08(30yr)
Fraction of the year that leafy vegetables are grown.
1.0
Fraction of the year that milk cows are on pasture.
1.0
Fraction of milk-cow feed intake that is from pasture while
on pasture.
Fraction of the year that goats are on pasture.
1.0
Fraction of goat feed intake that is from pasture while on
pasture.
Fraction of the maximum individual’s vegetable intake that
is from his own garden.
Average absolute humidity over the growing season
(g/m3).
Fraction of the year that beef cattle are on pasture.
1.0
Fraction of beef-cattle feed intake that is from pasture
while the cattle are on pasture
Animal considered for milk pathway
1.0
0.76
8.0
1.0
1.0
Cow and Goat
Annual milk production for each distance and direction
within 50 miles (l)
Annual meat production for each distance and direction
within 50 miles (kg)
Annual vegetable production for each distance and
direction within 50 miles (kg)
Population Distribution
Table 11.3-201
Source term
Table 11.3-202
11.3-11
9.08E+08
4.25E+07
4.81E+08
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-203
CP COL 11.3(6)
Input Parameters for Dose Calculation from Evaporation
Pond (Sheet 2 of 2)
Parameter
Value
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
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.
11.3-12
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-204
CP COL 11.3(6)
Calculated Doses from Evaporation Pond
Pathway
Dose to each organ (1) (mrem/yr)
GI-Tract
2.27E-02
Bone
2.27E-02
Liver
2.27E-02
Kidney
2.27E-02
Thyroid
2.27E-02
Lung
2.27E-02
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
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
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
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
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
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
Ground
Vegetable
Meat
Cow Milk
Goat Milk
Inhalation
Total(2)
Note:
1. Dose due to iodine, particulate and H-3
2. Conservatively, both Cow Milk and Goat Milk are considered.
11.3-13
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-205
CP COL 11.3(6)
Total Doses Due to Gaseous Effluent from Vent Stack and
Evaporation Pond
Pathway
Dose to each organ (1)(3) (mrem/yr)
GI-Tract
1.24E-01
Bone
1.24E-01
Liver
1.24E-01
Kidney
1.24E-01
Thyroid
1.24E-01
Lung
1.24E-01
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
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
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
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
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
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
Ground
Vegetable
Meat
Cow Milk
Goat Milk
Inhalation
Total(2)
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.
11.3-14
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-206
CP COL 11.3(6)
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
Note: Calculated doses are from the addition of a single new unit.
11.3-15
Revision 3
CP COL 11.3(9)
H
CVS
GMS
PCV-019B-N
F.C
SS CS
PI
019 -N
VH
PMW
PICA
019 -N
GMS
PWS
HT
GA
ACR
NCS
NCS
GMS
P
T
VLV-021A-N
VLV-018A-N
HT
HT
200
150
EC6
VLV-020A-N
P
VLV-019A-N
EC6
150
200
VLV-042 -N
P
T
15
200
EC6
T
P
AOV-039A-N
F.C
CVS-PICA-143-N
GMS
WASTE GAS DRYER
VLV-040A-N
A/B EXHAUST.
N2
GMS
A-WASTE GAS COMP.
GMS
B-WASTE GAS COMP.
EC6
H
PCV-020B-N
F.C
ACR
VLV-013A-N
150
200
PI
020 -N
P
T
VCT
SS CS
PICA
020 -N
PCV-011 -N
F.O
GMS
B.A. EVAP.
P
T
P
100
200
PICA
011 -N
PIC
013 -N
VLV-014A-N
H
ACR
150
200
T
T
P
P
T
150
200
SS CS
P
EC9
T
N2
F.C
GMS
WASTE GAS DRYER
P
CS SS
T
P
EC6
H
P
T
PI
021 -N
100
200
PCV-021B-N
F.C
SS CS
PICA
021 -N
VLV-009B-N
CS SS
VLV-006 -N
L.O
VLV-003B-N VLV-004B-N
EC9
100
200
VLV-040B-N
A/B EXHAUST.
NGS
AOV-039B-N
VS
N2
VLV-009A-N
EC6
VLV-034B-N VLV-033B-N
B-WASTE GAS
SURGE TANK
MTK-001B-N
P
T
VLV-028 -N
EC6
100
200
NGS
L.O
P
T
VLV-005 -N
L.O
T
VLV-004A-N VLV-003A-N P
SS CS
P
ACR
SMS BREAK UP PIPE
H
GA
VLV-014B-N
ACR
VLV-029 -N
L.O
PIC
014 -N
PICA
012 -N
GMS
P
P
T
150
200
C-WASTE GAS
SURGE TANK
MTK-001C-N
T
VLV-034C-N
EC6
P
T
VLV-013B-N
P
GMS
A-WASTE GAS COMP.
T
P
T
150
200
F.C
F.O
N2
PICA-012-N
GMS
WASTE GAS DRYER
VLV-040C-N
H
CVS-PICA-143-N
B-WASTE GAS
COMPRESSOR
MEQ-001B-N
PCV-023B-N
A/B EXHAUST.
AOV-039C-N
VS
NGS
PCV-012 -N
VLV-033C-N
150
200
F.O
VLV-002B-N
VLV-012B-N
VLV-007B-N
PI
022 -N
F.C
PCV-022B-N
P
ACR
P
VLV-001B-N
SS CS
PICA
022 -N
EC6
VLV-020B-N
P
VLV-019B-N
GMS
CVS
P
T
100
200
11.3-16
P
P
T
150
200
D-WASTE GAS
SURGE TANK
MTK-001D-N
T
EC6
GMS
PWS
NCS
NCS
T
VH
PMW
P
T
150
200
N2
F.C
GMS
WASTE GAS DRYER
VLV-040D-N
A/B EXHAUST.
NGS
AOV-039D-N
VS
VLV-034D-N VLV-033D-N
VLV-021B-N
VLV-018B-N
200
150
EC6
P
T
HT
HT
Figure 11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 1 of 3)
VLV-046B-N
VLV-002A-N
A-WASTE GAS
COMPRESSOR
MEQ-001A-N
NGS
PCV-143 -N
F.C
150
200
F.O
PCV-023A-N
EC6
VLV-046A-N
VLV-041 -N
P
P
T
VS
VLV-035 -N
VLV-034A-N VLV-033A-N
A-WASTE GAS
SURGE TANK
MTK-001A-N
T
P
EC6
VLV-001A-N
P
PICA-011-N
VLV-027A-N VLV-026A-N
CVS
F.C
CS SS
150
200
P
T
150
200
P
T
CVS-PICA-143-N
VLV-012A-N
CVS
F.C
GA
VLV-031B-N
VLV-007A-N
PCV-013 -N
GMS
VLV-008 -N
CVDT
VLV-031A-N
VLV-030A-N
PCV-019A-N
F.O
VLV-030B-N
PCV-020A-N
150
120
P
T
100
200
P
T
PCV-014 -N
GMS CHARCOAL BED
VLV-031C-N
150
200
VLV-027B-N VLV-026B-N
15
200
P
T
VLV-017B-N
P
T
F.C
F.C
VLV-017A-N
SRV-045A-N
VLV-037A-N
VLV-030C-N
PCV-021A-N
CS SS
150
200
P
T
150
200
P
T
100
200
F.C
F.C
P
T
SRV-045B-N
VLV-037B-N
VLV-030D-N
PCV-022A-N
P
T
F.C
VLV-031D-N
GMS
B-WASTE GAS COMP.
F.C
SRV-045C-N
VLV-037C-N
SRV-045D-N
VLV-037D-N
LMS
AOV-036A-N
VLV-038A-N
AOV-036B-N
VLV-038B-N
AOV-036C-N
VLV-038C-N
AOV-036D-N
VLV-038D-N
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
F.O
Revision 3
CP COL 11.3(9)
P
T
VCT
P
VS A/B EXHAUST.
150
200
P
T
PCV-033 -N
F.C
VLV-147 -N
VLV-114 -N
100
200
P
T
HVAC FAN SWITCH SIGNAL
PLANT STACK MONITOR SIGNAL
GMS
WASTE GAS COMP.
CVS
GMS
A-WASTE GAS COMP.
GMS A-WASTE
GAS SURGE TANK
GMS B-WASTE
GAS SURGE TANK
0
200
P
T
150
200
PCV-032B-N
F.C
CS SS
P
T
P
T
PCV-032 -N
F.C
PCV-031 -N
F.C
VLV-148 -N
150
200
150
200
PCV-026 -N
F.C
PIC
032 -N
PIC
031 -N
PIC
026 -N
NGS
FIA
032 -N
FIA
031 -N
PCV-039A-N
F.C
PCV-039B-N
F.C
ACR
ACR
ACR
GMS
N2
ACR
H
ACR
H
PIC
039 -N
GA
HCV-032 -N
F.C
ACR
ACR
ACR
P
T
ACR
HIC
032 -N
HCV-031 -N
F.C
HIC
031 -N
HCV-026 -N
F.C
HIC
026 -N
150
200
T
RIA
072 -N
VLV-144 -N
H
VLV-164 -N
EC6
H
ACR
150
200
RICA
072 -N
P
T
A/B EXHAUST
VLV-110 -N
VLV-106 -N
VS
CS SS
VLV-109 -N
VLV-105 -N
CS SS
B.A.EVAP
CVS
T
P
NGS
N2
OXYGEN GAS
ANALYZER
MEQ-003 -N
T
FIA
026 -N
H
AOV-115 -N
F.C
ACR
VLV-140 -N
P
T
AOV-116 -N
F.C
O2
150
200
D-CHARCOAL
BED
MEQ-004D-N
C-CHARCOAL
BED
MEQ-004C-N
150
200
150
200
P
T
P
T
GMS
VLV-117 -N
T
H
H
H
H
PIA
037 -N
TIA
037 -N
XIA
035B-N
XIA
035A-N
A/B EXHAUST
GA
VS
VS
A/B EXHAUST
ACR
ACR
B-CHARCOAL
BED
MEQ-004B-N
A-CHARCOAL
BED
MEQ-004A-N
VLV-161 -N
ACR
ACR
AOV-133 -N
F.C
A/B EXHAUST
150
200
150
200
P
T
P
T
WASTE GAS
DRYER
MEQ-002 -N
VS
11.3-17
SS CS
SS CS
P
T
150
120
VLV-155 -N VLV-154 -N
EC6
VLV-153 -N VLV-152 -N
EC6
Figure 11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 2 of 3)
RCV-072A-N
F.C
VCT
PCV-032A-N
F.C
CS SS
RCV-072C-N
F.C
PCV-032C-N
F.C
RCV-072B-N
P
F.C
PIC
033 -N
EC6
VLV-101 -N
T
VLV-102 -N
VLV-103 -N
GMS C-WASTE
GAS SURGE TANK
F.C
GA
EC6
GMS
AOV-144 -N
N2
SS CS
EC6
VLV-162 -N
15
120
P
T
VLV-163 -N
150
120
P
T
NGS
VLV-142 -N
VLV-143 -N
VLV-135B-N
VLV-138B-N
GMS D-WASTE
GAS SURGE TANK
VLV-137 -N
150
200
P
T
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-136 -N
VLV-132 -N VLV-131 -N
150
200
P
T
VLV-135A-N
VLV-138A-N
H
NCS
ACR
F.C
AOV-151 -N
EC9
FIA
030 -N
NCS
NGS
N2
Revision 3
CP COL 11.3(9)
PRT
SMS A-SPENT RESIN
STORAGE TANK
SMS B-SPENT RESIN
STORAGE TANK
RCS
GMS WASTE
GAS SURGE TANK
GMS CHARCOAL BED
S
SST-006A-N
S
SST-006B-N
S
SST-014 -N
S
SST-009 -N
S
SST-008 -N
P
T
P
T
P
T
P
T
150
150
150
150
EC8
200
400
150
200
150
200
F.C
P
S
P
P
P
S
P
SOV-203A-N
F.C
SOV-203B-N
F.C
S
SOV-224 -N
F.C
S
SOV-212 -N
F.C
SOV-209 -N
S
T
T
T
T
T
EC6
T
T
T
T
EC6
EC6
EC6
EC6
EC6
S
F.C
S
F.C
F.C
S
F.C
S
F.C
S
F.C
F.C
SOV-219C-N
S
SOV-219B-N
T
SOV-219A-N
T
SOV-215 -N
P
T
S
SOV-217 -N
P
SOV-206 -N
P
SOV-221 -N
P
P
T
P
T
EC8
EC8
EC8
EC4
75
200
150
200
EC8
150
200
25
200
P
T
P
T
P
T
P
T
15
200
15
200
15
200
15
120
VLV-214 -N
P
T
VLV-205 -N
P
T
S
SST-012B-N
S
SST-012A-N
S
SST-012C-N
EC6
SST-010 -N
S
SST-011 -N
S
SST-007 -N
S
SST-013 -N
S
B.A.EVAP.
VCT
CVDT
CVS
C-HOLDUP TANK
CVS
B-HOLDUP TANK
CVS
A-HOLDUP TANK
CVS
LMS
GMS
WASTE GAS DRYER
CVS
GMS
WASTE GAS DRYER
GMS
B-WASTE GAS COMP.
GMS
A-WASTE GAS COMP.
P
T
DS
VLV-238 -N
O2
150
200
F.C
AOV-237 -N
P
F.C
AOV-234 -N
A/B ED SUMP
P
T
VLV-236B-N VLV-235B-N
VLV-236A-N VLV-235A-N
15
120
O2
P
T
P
T
P
VLV-232 -N
EC6
N2
15
120
T
NGS
P
T
P
T
N2
15
120
15
120
WASTE GAS
SAMPLE
VESSEL
EC6
VLV-242B-N
P
100
200
NGS
VLV-241B-N
EC6
T
EC6
VLV-241A-N
EC6
EC6
VLV-231 -N
P
T
15
120
A-WASTE GAS
ANALYZER
MEQ-005A-N
B-WASTE GAS
ANALYZER
MEQ-005B-N
11.3-18
Figure 11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 3 of 3)
VLV-202A-N
VLV-202B-N
VLV-223 -N
VLV-211 -N
VLV-208 -N
P
T
CS SS
VLV-233 -N
150
120
EC6
P
T
CS SS
150
120
P
T
EC6
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CS SS
VLV-240A-N
VLV-240B-N
150
120
EC6
P
T
CS SS
150
120
P
T
EC6
VLV-239A-N
VLV-239B-N
P
T
P
T
15
120
15
120
H2
HGS
H2
VLV-243B-N
EC6
HGS
VLV-243A-N
EC6
VS
VS
H2
A/B EXHAUST
H2
A/B EXHAUST
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.4
SOLID WASTE MANAGEMENT SYSTEM
This section of the referenced DCD is incorporated by reference with the following
departures and/or supplements.
11.4.1.3
STD COL 11.4(5)
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.
11.4.1.5
STD COL 11.4(6)
Other Design Considerations
Site-Specific Cost-Benefit Analysis
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
STD COL 11.4(5)
STD COL 11.4(7)
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.
11.4-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
STD COL 11.4(10)
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
STD COL 11.4(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
STD COL 11.4(8)
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
CP COL 11.4(7)
Packaging, Storage, and Shipping
Replace the third paragraph in DCD Subsection 11.4.2.3 with the following.
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.
11.4-2
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.4(1)
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.
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.
The interim storage facility is designed to meet the guidance of NUREG-0800
Appendix 11.4-A. The facility design and operation ensure that radiological
consequences of design basis events (such as fire, tornado, seismic occurrence,
and flood) do not exceed a small fraction of 10 CFR 100 dose limits. The facility
also meets the guidance provided in Generic Letters 80-09, 81-38, and 81-39, and
in SECYs 94-198 and 93-323. The facility is located within the plant’s protected
area and meets the dose limits set in 40 CFR 190 as implemented under 10 CFR
20.1301 (e) and 10 CFR 20.1302. Onsite dose limits from the radwaste interim
storage facility meet the requirements of 10 CFR 20, including the ALARA
principle of 10 CFR 20.1101.
In accordance with 10 CFR 20.1406, the facility includes design features that
would minimize contamination of the waste facility and environment to the extent
practicable; facilitate eventual decommissioning; and minimize the generation of
extraneous radioactive waste. All potential radionuclide release pathways are
monitored in accordance with 10 CFR 50, Appendix A.
The containers selected for use in the facility are chosen based on their ability to
maintain integrity over their storage life, and compatibility with the types of waste
stored. Additionally the containers are inspected periodically to ensure container
integrity is maintained. The facility is also equipped with provisions for collecting
liquid drainage and sampling of collected liquids. The design of the facility also
uses shielded vaults for Class B and C waste; includes separate control and
equipment room ventilation systems and airborne radiation monitor; and a remote
bridge crane with closed circuit television cameras.
11.4-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Detailed records are maintained for all waste stored in the facility including: waste
type, waste contents, radionuclides and radioactive material, dates of storage,
shipment, and other relevant data. The facility has a ventilation exhaust system
and associated airborne radioactivity monitoring, and a fire protection system to
detect and suppress fires.
In accordance with the regulations and guidance listed above, when the detailed
design of the facility is performed, Luminant will consider the use of volume
reduction techniques (such as compactors or shredders), transportation and lifting
devices to prevent dropped containers, and sloped floors, curbs, and sumps to
collect and contain spills or leakage. The facility design will consider proper
shielding to reduce radiation levels. The detailed design will also consider the use
of equipment for decontamination and repackaging of waste containers.
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.
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
11.4-4
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
STD COL 11.4(3)
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.
11.4.4.5
STD COL 11.4(4)
Mobile De-watering System
Replace the last sentence in DCD Subsection 11.4.4.5 with the following.
STD COL 11.4(7)
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.
11.4-5
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.4.6
CP COL 11.4(9)
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.
11.4.8
Combined License Information
Replace the content of DCD Subsection 11.4.8 with the following.
CP COL 11.4(1)
STD COL 11.4(1)
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
STD COL 11.4(3)
11.4(3) Plan for the process control program describing the process and effluent
monitoring and sampling program
This COL item is addressed in Subsection 11.4.3.2.
STD COL 11.4(4)
11.4(4) Mobile/portable SWMS connections
This COL item is addressed in Subsection 11.4.4.5.
STD COL 11.4(5)
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.
STD COL 11.4(6)
11.4(6) Site-specific cost benefit analysis
This COL item is addressed in Subsection 11.4.1.5.
STD COL 11.4(7)
CP COL 11.4(7)
11.4(7) Site-specific solid waste processing facility
STD COL 11.4(8)
CP COL 11.4(8)
11.4(8) Piping and instrumentation diagrams
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.
11.4-6
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.4(9)
11.4(9) The implementation milestones for the coatings program used in the
SWMS
This COL item is addressed in Subsection 11.4.6.
STD COL 11.4(10)
11.4(10) The mobile/portable SWMS connections
This COL item is addressed in Subsection 11.4.1.6.
11.4-7
Revision 3
CP COL 11.4(8)
DS
NGS
N2
A/B ED SUMP
T
DS
VLV-031 -N
CS SS
LCV-022B-N
GA
P
A/B ED SUMP
EC6
GMS
H
ACR
AOV-032A-N
AOV-033A-N
LCA
022 -N
F.C
F.C
F.C
VLV-035A-N
AOV-023A-N
P
PIA
015 -N
T
A-SPENT RESIN
STORAGE TANK
MTK-001A-N
T
P
L.C
LCV-022A-N
H
ACR
T
P
T
P
T
P
P
150
150
SRV-021A-N
VLV-018A-N
P
L
H
LICA
015 -N
ACR
VLV-001A-N
VLV-005A-N
P
P
P
T
P
T
200
150
200
150
017 -N
QI
B-SFP DEMI.
200
150
SFS
P
T
A-SFP DEMI.
SFS
GMS
GA
P
F.C
VLV-035B-N
AOV-023B-N
P
PIA
016 -N
B-SPENT RESIN
STORAGE TANK
MTK-001B-N
T
T
CVS
B-MIXED BED DEMI.
CVS
A-MIXED BED DEMI.
CVS
CATION BED DEMI.
P
H
ACR
T
P
T
P
T
P
P
150
150
SRV-021B-N
P
SGS A-SGBD
MIX BED DEMI.
P
P
L
H
200
150
200
150
P
T
ACR
200
150
FI
013 -N
F.C
LMS D-WASTE
EFFLUENT DEMI.
LMS C-WASTE
EFFLUENT DEMI.
LMS B-WASTE
EFFLUENT DEMI.
LMS A-WASTE
EFFLUENT DEMI.
LMS ACTIVATED
CARBON FILTER
HIC
013 -N
HCV-013 -N
F.C
ACR
P
T
P
T
LICA
016 -N
VLV-001B-N
VLV-005B-N
SGS A-SGBD
CATION BED DEMI.
SGS B-SGBD
MIX BED DEMI.
VLV-045 -N
VLV-046 -N
ACR
11.4-8
Figure 11.4-201 Solid Waste Management System Piping and Instrumentation Diagram
VLV-037A-N
VH
L.C
GMS
VLV-036A-N
AOV-032B-N
AOV-033B-N
VLV-044 -N
VLV-015A-N
VLV-014A-N
F.C
F.C
L.C
CVS
B.A.EVAP. FEED DEMI.
L.C
CVS
B-DEBORATING DEMI.
VLV-037B-N
SGS B-SGBD
CATION BED DEMI.
VLV-018B-N
CVS
A-DEBORATING DEMI.
VLV-036B-N
VLV-048 -N
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-015B-N
VLV-014B-N
VLV-047 -N
200
150
P
T
EC6
EC8
200
150
P
T
EC6
EC8
VLV-006 -N
TIA
VLV-042 -N
VLV-052 -N
VLV-011 -N
PWS
200
150
EC8
200
150
EC8
VLV-041 -N
VLV-051 -N
LCA
PMW
DEWATERING
PUMP
IAS
SA
P
T
P
T
OPTIONAL VENDOR EQUIPMENT
EC6
EC6
LMS
VS
WHT
A/B EXHAUST
CVS PMW SUPPLY.
CVS PMW SUPPLY.
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.5
PROCESS EFFLUENT RADIATION MONITORING AND SAMPLING
SYSTEMS
This section of the referenced DCD is incorporated by reference with the following
departures and/or supplements.
CP SUP 11.5(1)
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 1.2-2.
Add the following Subsections after DCD Subsection 11.5.2.5.2
CP COL 11.5(1)
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.
CP COL 11.5(1)
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
11.5-1
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
CP COL 11.5(4)
CP COL 11.5(5)
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
STD COL 11.5(2)
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
11.5-2
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
STD COL 11.5(4)
STD COL 11.5(5)
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.
STD COL 11.5(1)
STD COL 11.5(2)
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
STD COL 11.5(3)
Radiological Environmental Monitoring Program
Replace the content of DCD Subsection 11.5.2.10 with the following.
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.
11.5-3
Revision 3
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.5.2.11
STD COL 11.5(6)
Site-Specific Cost-Benefit Analysis
Replace the content of DCD Subsection 11.5.2.11 with the following.
The results of site-specific cost-benefit analysis are described in Subsections
11.2.1.5 and 11.3.1.5.
11.5.5
Combined License Information
Replace the content of DCD Subsection 11.5.5 with the following.
CP COL 11.5(1)
STD COL 11.5(1)
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.
STD COL 11.5(2)
11.5(2) Offsite dose calculation manual
This COL item is addressed in Subsection 11.5.2.7 and 11.5.2.9.
STD COL 11.5(3)
11.5(3) Radiological and environmental monitoring program
This COL item is addressed in Subsection 11.5.2.10.
CP COL 11.5(4)
STD COL 11.5(4)
11.5(4) Inspection, decontamination, and replacement
This COL item is addressed in Subsections 11.5.2.6 and 11.5.2.8.
CP COL 11.5(5)
STD COL 11.5(5)
11.5(5) Analytical procedures
This COL item is addressed in Subsections 11.5.2.6 and 11.5.2.8.
STD COL 11.5(6)
11.5(6) The site-specific cost benefit analysis
This COL item is addressed in Subsection 11.5.2.11.
11.5-4
Revision 3
CP COL 11.5(1)
1 for each unit
1
RMS-RE110
RMS-RE111
201
202
γ
γ
Type
1E-7 to 1E-2
1E-7 to 1E-2
µCi/cm3
Range
Cs-137
Cs-137
Calibration
Isotopes
Yes
Yes
Check
Source
No
No
SafetyRelated
Diverse
Diverse
Control
Function
11.5-5
Note 1: The monitor is located adjacent to Startup Generator Blowdown Equipment shown in Figure 1.2-1R (Sheet 2 of 2)
Note 2: The monitor is located adjacent to radwaste evaporation pond shown in Figure 1.2-1R (Sheet 1of 2)
Service
Monitor
Number
Item
No.
Effluent Liquid Monitors (Site-Specific)
Table 11.5-201
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1
1 for
each unit
Quantity
(Note 2)
(Note 1)
GA
Drawing
Number
Revision 3
11.5 – 1d
11.5 – 1d
Schematic
Number
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Applicable Radiation Monitors
201
202
Channel #
RMS-RE-110
RMS-RE-111
Radiation Signal
Processor
Startup SG Blowdown
Heat Exchanger
RE
Process line
Evaporation Pond
CP COL 11.5(1)
Existing Waste Water
Management Pond C
Discharge to Squaw
Creek Reservoir
Figure 11.5-201 Typical Process In-Line Radiation Monitor Schematic
11.5-6
Revision 3