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
11.3
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........................................ 11.3-1
System Description................................................................ 11.3-1
Radioactive Effluent Releases and Dose Calculation in Normal
Operation ............................................................................... 11.3-1
Combined License Information .............................................. 11.3-3
References ............................................................................ 11.3-3
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
11.4.8
11.5
Site-Specific Cost-Benefit Analysis........................................ 11.2-1
Mobile or Temporary Equipment ........................................... 11.2-1
System Description................................................................ 11.2-1
Radioactive Effluent Releases and Dose Calculation in Normal
Operation ............................................................................... 11.2-3
Radioactive Effluent Releases Due to Liquid Containing Tank
Failures .................................................................................. 11.2-6
Evaporation Pond .................................................................. 11.2-6
Combined License Information .............................................. 11.2-8
References ............................................................................ 11.2-9
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................................................... 11.4-4
Combined License Information .............................................. 11.4-5
PROCESS EFFLUENT RADIATION MONITORING AND SAMPLING
SYSTEMS ......................................................................................... 11.5-1
11.5.2.6
11.5.2.7
Reliability and Quality Assurance .......................................... 11.5-1
Determination of Instrumentation Alarm Setpoints for
Effluents................................................................................. 11.5-1
11-i
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
TABLE OF CONTENTS (Continued)
Section
11.5.2.8
11.5.2.9
11.5.2.10
11.5.2.11
11.5.5
Title
Page
Compliance with Effluent Release Requirements.................. 11.5-1
Offsite Dose Calculation Manual ........................................... 11.5-2
Radiological Environmental Monitoring Program................... 11.5-2
Site-Specific Cost-Benefit Analysis........................................ 11.5-2
Combined License Information .............................................. 11.5-3
11-ii
Revision 1
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-iii
Revision 1
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-iv
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
ACRONYMS AND ABBREVIATIONS
A/B
AC/B
ACC
AOO
CFR
COL
CPNPP
CVCS
CVDT
DCD
DOT
EAB
ESW
FSAR
GWMS
HT
HVAC
Hx
LWMS
NEI
ODCM
PCP
PERMS
P&ID
PMW
PWR
R/B
RCP
RCS
RG
RWSAT
SG
SRST
SSC
SWMS
VCT
WHT
WMT
auxiliary building
access building
accumulator
anticipated operational occurrence
Code of Federal Regulations
Combined License
Comanche Peak Nuclear Power Plant
chemical and volume control system
containment vessel reactor coolant drain tank
Design Control Document
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
liquid waste management system
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
reactor coolant system
regulatory guide
refueling water storage auxiliary tank
steam generator
spent resin storage tank
structure, system, and component
solid waste management system
volume control tank
waste holdup tank
waste monitor tank
11-v
Revision 1
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 1
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.
A site-specific cost benefit analysis using the guidance of regulatory guide (RG)
1.110 was performed based on the site-specific calculated radiation doses as a
result of radioactive liquid effluents during normal operations, including anticipated
operational occurrences (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. Based on a population dose results of 2.14 person-rem per year (Total
Body), 2.04 person-rem per year (Thyroid) 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 Title 10, Code of
Federal Regulations (CFR), Part 50, Appendix I.
11.2.1.6
CP COL 11.2(1)
Mobile or Temporary Equipment
Replace the last sentence in the paragraph in DCD Subsection 11.2.1.6.
Process piping connections have connectors different from the utility connectors
to prevent cross-connection and contamination. The use of mobile or temporary
equipment will require Luminant to address applicable regulatory requirements
and guidance such as 10 CFR 50.34a, 10 CFR 20.1406 and RG 1.143. As such
the purchase or lease contracts for any temporary and mobile equipment will
specify the applicable criteria.
11.2.2
CP COL 11.2(2)
System Description
Replace third paragraph in DCD Subsection 11.2.2 with the following.
CP COL 11.2(6)
11.2-1
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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 treated liquid effluents released from the CPNPP Units 3 and 4 and the
evaporation pond are piped directly into the Unit 1 Waste Management System
(WMS) flow receiver and head box, which includes the discharge flume. The
effluents enter from the top of the receiver and head box and are above the liquid
level in the box so that they flow freely into the box, from where the content flows
to the Unit 1 WMS discharge flume, and by gravity to the Unit 1 Circulating Water
System (CWS), via an existing Unit 1 pipeline connecting the WMS to the CWS.
At this pipeline intersection, the Unit 3 and 4 treated effluent and the Unit 3 and 4
evaporation pond effluents are commingled with various Unit 1 and 2 waste
effluent streams. This Unit 1 circulating water flow path then goes to the Unit 1
condenser water box outlet, where it joins the Unit 2 condenser water box outlet
flow. The joined flows from the Unit 1 and 3 condenser water boxes are then sent
to the SCR via the Unit 1 and 2 discharge tunnel and outfall structure from all four
units (see Figure 11.2-201 Sheet 10) for a visual representation of the above
described flow path.
The header where the WMS intersects with the CWS is located within the Unit 1
Turbine building. The header contains two flow balancing valves (1CW-247 and
1CW-248) for Units 1 and 2. This arrangement ensures that there is always
circulating cooling water flow for Unit 1 and/or Unit 2. The circulating water
discharge piping then becomes progressively larger and flows freely (no valves)
into the Unit 1 condenser water discharge box. This flow path also ensures there
is less back pressure into the treated effluent flow. Based on the fact that the
effluent piping flows freely into the box and that there is less back pressure, there
is no need for a mixing orifice and backflow preventer, as the large circulating
water return flow and length of pipe is sufficient to thoroughly mix the release.
The bypass valve, VLV-531, is located in the same area with the radiation monitor
and the discharge control valves (RCV-035A and RCV-035B), which are inside the
Auxiliary Building. All normal discharge is required to go through the discharge
control valves. To ensure discharge operation is not interrupted by the failure of
the control valves at any time, a bypass valve is added around the radiation
monitor and the discharge control valves.
Any leakage from the bypass valve 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
11.2-2
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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 initiate an alarm for operator
action. Also, at least a portion of the flow goes through the radiation monitor. 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)
Radioactive Effluent Releases and Dose Calculation in Normal
Operation
Replace the last five paragraphs in DCD Subsection 11.2.3.1 with the following.
CP COL 11.2(4)
The annual average release of radionuclides is estimated by the PWR-GALE
Code (Ref.11.2-13) with the reactor coolant activities that is described in Section
11.1. The parameters used by the PWR-GALE Code are provided in Table 11.2-9,
and the calculated effluents are provided in Table 11.2-10R. The calculated
effluents for the maximum releases are provided in Table 11.2-11R. On this
site-specific application, handling of contaminated laundry is contracted to off-site
services. Therefore, the detergent waste effluent need not be considered.
The calculated effluent concentrations using annual release rates are then
compared against the concentration limits of 10 CFR 20 Appendix B (see Tables
11.2-12R and 11.2-13R.).
Once it is confirmed that the treated effluent meets discharge requirements, the
effluent is released into Squaw Creek Reservoir via the CPNPP Units 1 and 2
circulating water return line. The liquid effluent is maintained at ambient
temperature, as it is stored inside the auxiliary building (A/B) waste monitoring
tanks. Currently, Squaw Creek Reservoir has a tritium concentration limit of
30,000 pCi/L (Reference 11.2-201). Based on an analysis, the tritium
concentration in Squaw Creek Reservoir is anticipated to remain within the tritium
limit due to the local rainfall, evaporation, and spillover (control release) from
Squaw Creek Reservoir to Squaw Creek.
However, during the maximum tritium generation condition (i.e., all four units
operating at full power), the tritium concentration could be exceeded. When the
tritium concentration in Squaw Creek Reservoir is determined to be close to the
11.2-3
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
offsite dose calculation manual (ODCM) limit, as much as half of the liquid effluent
from CPNPP Units 3 and 4 can be diverted to the evaporation pond for temporary
staging.
When the tritium concentration in Squaw Creek Reservoir again decreases below
the operating target, the effluent in the pond is sampled and analyzed for
suitability to discharge back into Squaw Creek Reservoir. In the event that both
CPNPP Units 1 and 2 are temporarily not in operation, or when there is no dilution
flow, the CPNPP Units 3 and 4 waste holdup tanks (WHTs) and waste monitor
tanks (WMTs) have enough capacity to store more than a month of the daily waste
input. The evaporation pond can also receive 100 percent of the CPNPP Units 3
and 4 liquid effluent on a temporary basis.The treated effluent release piping is
non-safety and does not have any safety function. In addition, the Unit 1 flow
receiver and head box, circulating water system and discharge box are not
required to perform any safety function or important to safety functions.
The evaporation pond is designed to provide sufficient surface area for natural
evaporation based on the local area rainfall, evaporation rate, and receiving half
of the CPNPP Units 3 and 4 liquid effluent. The evaporation pond is sized to
prevent overflow due to local maximum rainfall condition. The pond design
includes a discharge line and transfer pump to keep the pond from overflowing
during periods of extreme weather conditions, and to forward the effluent to
Squaw Creek Reservoir. The effluent is sampled before discharge and is
monitored for radionuclide concentration by a radiation monitor which can turn off
the pump, shut off the discharge valve and initiate an alarm signal to the Main
Control Room and the Radwaste Control Room for operator actions. Doses from
airborne particulates from the evaporation pond are described in Subsection
11.3.3.
The evaporation pond is designed with two layers of high density polyethylene
(HDPE) with smooth surfaces and a drainage net in between for leak detection
and collection. The bottom of the pond is sloped towards the leak drainage pit and
a separate discharge pump pit. The leak drainage pit is a small pit underneath the
two layers of HDPE, and leakage through the HDPE is caught and detected in this
pit. The discharge pump pit is designed to faciliate pumping water out of the pond
and is equipped with a discharge pump. An operating requirement is established
to wash the pond and discharge the wash water to a flow receiver and head box
for disposal each time the pond is drained. Based on the design evaluation, the
pond does not need to be used continuously, because during normal operating
conditions and anticipated operational occurrences, diversion of flow is not
required. Diversion is required only when the tritium concentration in the SCR is
approaching the set limit due to adverse meteorological conditions (e. g., drought
condition leading to minimal spillover). The pond also has a berm to minimize
infiltration of storm water. These design features (using HDPE, the leak detection
pit, and sloping towards the drainage pit for discharge) and operating procedures
(cleaning, diversion only when required) ensure ease of decontamination and
minimization of cross contamination (leakage to the groundwater), and thus
satisfy 10 CFR 20.1406 and RG 4.21.
11.2-4
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
The evaporation pond discharge pump and discharge isolation valve are under
supervisory control. Prior to discharge, multiple effluent samples around the pond
perimeter are required to ensure the pond effluent meets the discharge
specifications. The evaporation pond is a relatively small pond. The effluent to the
pond has been filtered and ion exchanged and it is expected that effluent
concentration in the pond is uniform. Stagnation and stratification of
concentrations is not expected. This is confirmed by obtaining representative
samples from the pond. The bottom of the pond is designed to be sloped towards
the discharge pit to facilitate complete drainage. The pond is washed each time
the contents are emptied to significantly reduce the potential for accumulation of
residual contamination. Further, a radiation monitor is located close to the pump
discharge to monitor the radiation level of the contents. The radiation monitor
alarms in the Main Control Room and the Radwaste Operator Control Room and
also isolates the pump and its discharge valve in the unlikely event of the content
exceeding the setpoint. The radiation monitor setpoint for the evaporation pond
discharge is the same as that used at the Waste Monitor Tank discharge.
Isotopic concentrations are calculated, assuming 247,500 gpm per unit of
circulating water from CPNPP Units 1 and 2 (Reference 11.2-201, ODCM for
CPNPP Units 1 and 2). The isotopic ratios between the expected releases and the
concentration limits of 10 CFR 20 Appendix B are listed in Tables 11.2-12R. The
isotopic ratios between the maximum releases and the concentration limits of 10
CFR 20 Appendix B are listed in Table 11.2-13R. These ratio values are less than
the allowable value of 1.0.
The individual doses and population doses are evaluated with the LADTAP II
Code (Reference 11.2-14). The site-specific parameters used in the LADTAP II
Code are listed in Table 11.2-14R, and the calculated individual doses are listed in
Table 11.2-15R. And the calculated population dose from liquid effluents is 2.14
person-rem for whole-body and 2.04 persom-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 1.28 mrem/yr (teenager’s liver).
These values are less than the 10 CFR 50 Appendix I criteria of 3 mrem/yr and 10
mrem/yr, respectively. Evaluating the dose contribution from the evaporation
pond (conservatively assuming 50% evaporation of the diverted flow) amounts to
1.15E-01 mrem/yr (Adult’s GI-Tract) described in FSAR Table 11.3-204 and the
combined dose from the vent stack gaseous emission and the evaporation pond
emission amounts to 2.73E+00 mrem/yr (Adult’s GI-Tract) described in FSAR
Table 11.3-205, which is well within the 10 CFR Appendix I limit. Based on the
above, the evaporation pond meets the acceptance criteria of SRP 11.2. With
regards to RG 1.143, RG 1.143 does not provide any guidance on specific design
requirements for an evaporation pond. Hence RG 1.143 is not applicable to the
desing of the evaporation pond.According to NUREG-0543 (Reference 11.2-202),
there is reasonable assurance that sites with up to four operating reactors that
have releases within Appendix I design objective values are also in conformance
with the EPA Uranium Fuel Cycle Standard, 40 CFR 190. Once the proposed
CPNPP Units 3 and 4 are constructed, the Comanche Peak site will consist of four
operating reactors.
11.2-5
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.2.3.2
CP COL 11.2(3)
Radioactive Effluent Releases Due to Liquid Containing Tank
Failures
Replace the first sentence in the last paragraph in DCD Subsection 11.2.3.2 with
the following.
Site-specific hydrogeological data indicate that contaminant migration time is
about two years (see Subsection 2.4.12), exceeding the travel time used in the
above analysis. Additionally, the tank cubicles are equipped with drainpipes to a
local sump that is designed to detect leakage and/or overflow, and initiate an
alarm for operator action. Hence, the potential for groundwater contamination is
greatly reduced and further analysis is not warranted.
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 provide a means to receive,
store, and process treated radioactive effluent from the CPNPP Units 3 and 4
liquid radioactive waste management systems when the tritium concentration in
Squaw Creek Reservoir is approaching the ODCM limit.
In order to minimize contamination, the pond is rinsed each time the pond content
is emptied. The rinse water is also forwarded to Squaw Creek Reservoir, via the
discharge box and blended with the CPNPP Units 1 or 2 circulation water flow.
The evaporation pond is equipped with a leak detection system. In the event a
leak is developed, a signal is sent to the Main Control Room and the Radwaste
Control Room for operator actions, which may include removing the contents from
the pond to facilitate inspection and repair as required.
The pond liner is inspected regularly to determine liner integrity with respect to the
liners and their seams. In the event of punctures and/or rupture and repair is
required, the pond contents are removed, and the pond is rinsed before repair is
performed.
The evaporation pond is designed and constructed in accordance with the
following standards (others may be applicable as the design is finalized):
Texas Commission of Environmental Quality (TCEQ)
TCEQ 330, Municipal Solid Waste
11.2-6
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
The evaporation pond is designed and constructed to contain treated effluent that
is contaminated with radioactive nuclides. The pond opens to the environment to
allow the tritiated water to naturally evaporate.
The evaporation pond is constructed with two layers of High Density Polyethylene
material suitable for this service. The High Density Polyethylene is a minimum of
60 mils thickness.
A drainable mesh mat, with a minimum thickness of 30 mils, is provided in
between the two layers of High Density Polyethylene to allow movement of the
liquid due to leakage of the content from the top layer of High Density
Polyethylene.
The evaporation pond is constructed with a total depth of six feet, with four feet
below grade and two feet freeboad. A berm is constructed to prevent surface
water from entering the pond during rainy seasons.
The evaporation pond is constructed with a layer of clay with permeability less
than 1E-7 centimeter per second to support the pond. The overall construction
meets or exceeds the requirements for waste water pond stipulated by TCEQ.
Some TCEQ requirements are as follows:
•
In situ clay soils or placed and compacted meeting:
i.
more than 30% passing a Number 200 mesh sieve
ii.
liquid limit greater than 30%
iii.
plasticity index greater than 15
iv.
a minimum thickness of two feet
v.
Permeability equal to or less than 1x10-7centimeter per
second
11.2-7
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
•
Soil compaction will be 95% standard proctor density at optimum moisture
content
•
The pond is protected from inundation by a ten-year 2 hour rainfall event
The evaporation pond is equipped with a centrifugal pump to return the contents
to the Squaw Creak Reservoir as tritium concentration in Squaw Creak Reservoir
permits. The return piping leaving the evaporation pond is connected to the
circulating water return line discharge box upstream of the discharge point. A
radiation monitor is provided close to the pump discharge to monitor radiation
level of the content, and provides a signal to automatically turn off the pump, shut
off the discharge valve, and initiate a signal to alarm in the Main Control Room
and the Radwaste Control Room for operator actions.
The piping for transporting the fluid from the discharge valve inside the Auxiliary
Building to the pond, and the piping from the pond to the discharge point near
Squaw Creak Reservoir, are High Density Polyethylene material. Leak collection
and detection instrumentation are provided along the path of the pipe. Inspection
ports are also provided to allow access for inspection of the integrity of the pipe. A
back flow preventer is provided near the CPNPP Units 1 and 2 discharge boxes to
prevent back flow from the circulating pipe.
Evaporation Pond Design Summary:
Volume: 1.4 million gallon net capacity
Surface area: 1 acre
Depth: Total 6 feet deep (4 feet liquid depth with 2 feet freeboard)
Type: Open with no cover
Liner material: High Density Polyethylene, 60 mils, two layers
Permeability: 1x10-7cm/sec
The evaporation pond contains treated liquid effluents in trace amounts that meet
discharge requirements specified in 10 CFR 20 Appendix B, Table 2, and has
radionuclide contents below that of the boric acid tank contents. Hence, the
contamination level due to the failure of the evaporation pond is bounded by the
failure of the boric acid tanks.
11.2.4
Combined License Information
Replace the content of DCD Subsection 11.2.4 with the following.
CP 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.
11.2-8
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
11.2.5
References
Add the following references after the last reference in DCD subsection 11.2.5.
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.
11.2-9
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-10R (Sheet 1 of 2)
Liquid Releases Calculated by PWR GALE Code (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
0.00001
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
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
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.
11.2-10
Revision 1
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 (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 Detergent
Releases
Waste(3)
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
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.
11.2-11
Revision 1
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 (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
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
0.00056
0.00000
0.00169
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
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
3.10E-05
1.03E-05
1.24E-04
1.03E-05
0.00E+00
1.03E-05
2.06E-05
3.10E-05
Rb-88
0.00000
N/A
3.97E-02
Sr-89
0.00000
N/A
0.00E+00
Sr-90
0.00000
N/A
0.00E+00
Sr-91
0.00000
N/A
0.00E+00
Y-91m
0.00000
N/A
0.00E+00
Y-91
0.00000
N/A
0.00E+00
Y-93
0.00000
N/A
0.00E+00
Zr-95
0.00000
N/A
1.03E-05
Nb-95
0.00000
N/A
2.06E-05
Mo-99
0.00000
N/A
1.38E-02
Tc-99m
0.00000
N/A
5.44E-03
Ru-103
0.00000
N/A
1.03E-05
Rh-103m
0.00000
N/A
1.03E-05
Ru-106
0.00000
N/A
1.03E-05
Rh-106
0.00000
N/A
1.03E-05
Ag-110m
0.00000
N/A
0.00E+00
Ag-110
0.00000
N/A
0.00E+00
Sb-124
0.00000
N/A
0.00E+00
Te-129m
0.00000
N/A
0.00E+00
Te-129
0.00000
N/A
0.00E+00
Te-131m
0.00000
N/A
3.40E-04
Te-131
0.00000
N/A
0.00E+00
I-131
0.00113
N/A
1.74E-03
Te-132
0.00000
N/A
5.43E-03
I-132
0.00000
N/A
3.10E-04
I-133
0.00163
N/A
1.01E-02
I-134
0.00000
N/A
5.16E-05
Cs-134
0.73457
N/A
2.65E+00
I-135
0.00000
N/A
2.15E-03
Cs-136
0.12019
N/A
5.87E-01
Cs-137
0.43698
N/A
1.65E+00
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.
11.2-12
Revision 1
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 (Ci/yr)
Isotope Shim
Misc.
Turbine
Combined Detergent TOTAL
Bleed
Wastes Building Releases
Waste(3)
Releases (1)
Fission Products
Ba-137m
0.20917
0.00000
0.00000
0.20917
N/A
2.16E-01
Ba-140
0.00000
0.00010
0.00000
0.00010
N/A
1.03E-04
La-140
0.00000
0.00002
0.00000
0.00002
N/A
2.06E-05
Ce-141
0.00000
0.00000
0.00000
0.00000
N/A
0.00E+00
Ce-143
0.00000
0.00000
0.00000
0.00000
N/A
0.00E+00
Pr-143
0.00000
0.00000
0.00000
0.00000
N/A
0.00E+00
Ce-144
0.00000
0.00001
0.00000
0.00001
N/A
1.03E-05
Pr-144
0.00000
0.00001
0.00000
0.00001
N/A
1.03E-05
TOTAL
1.50367
(except
H-3)
H-3 release
3.51883
0.00633
5.02883
N/A
5.19E+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.
11.2-13
Revision 1
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)
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
Fraction of
Concentration Limit
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
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.
3. 10 CFR 20 Appendix B, Table 2
11.2-14
Revision 1
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)
Effluent
Concentration
Limit (μCi/ml) (3)
Fraction of
Concentration
Limit
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.
3. 10 CFR 20 Appendix B, Table 2
11.2-15
Revision 1
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)
Effluent
Concentration Limit
(μCi/ml) (3)
Fraction of
Concentration Limit
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
2.10E-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
4.43E-12
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
4.37E-12
8.73E-09
0.00E+00
0.00E+00
0.00E+00
0.00E+00
1.08E-07
0.00E+00
4.43E-06
1.53E-06
7.86E-09
3.67E-06
3.27E-10
7.48E-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.
3. 10 CFR 20 Appendix B, Table 2
11.2-16
Revision 1
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)
Effluent
Concentration Limit
(μCi/ml) (3)
Fraction of
Concentration Limit
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
4.37E-11
H-3
4.06E-06
1.00E-03
4.06E-03
TOTAL
1.60E-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.
3. 10 CFR 20 Appendix B, Table 2
11.2-17
Revision 1
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)
Circulating Water System discharge rate (gpm)
Water type selection
Reconcentration model index
30
247,500
Freshwater
1 (Complete mix)
Discharge rate to receiving water(ft3/sec)
1.5(1)
45.4(2)
6.3E+09
Total impoundment volume(ft3)
Shore-width factor
Dilution factor -Squaw Creek(3)
0.2 (Squaw Creek)
0.3(Whitney Reservoir)
1.0
Dilution factor - Brazos River(4)
822.7(1)
27.2(2)
Dilution factor - Whitney Reservoir(5)
1645.4 (1)
54.4 (2)
7.3
66
77
74.6
Transit time – Squaw Creek (hr)
Transit time – Brazos River (hr)
Transit time – Whitney Reservoir (hr)
Irrigation rate(Liter/m2-month)
Animal considered for milk pathway
Fraction of animal feed not contaminated
Fraction of animal water not contaminated
Source terms
Source term multiplier
50 mile population
Total Production within 50 miles(kg/yr,L/yr)
Cow
0
0
Table 11.2-10R
1
3,493,553
Leafy Vegetable : 25,000 kg/yr
Vegetable : 5,270,000 kg/yr
Milk : 943,000 L/yr
Meat : 281,000 kg/yr
324,375
Annual local harvest for sports harvest
fishing(kg/yr)
Annual local harvest for commercial fishing
None
harvest(kg/yr)
Annual local harvest for sports invertebrate
None
harvest (kg/yr)
Annual local harvest for commercial invertebrate None
harvest (kg/yr)
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)
11.2-18
Revision 1
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
11.2-19
Revision 1
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
1.52E-03 1.30E-03 1.30E-03 1.30E-03 1.30E-03 1.30E-03 1.30E-03
1.30E-03
Teenager
8.47E-03 7.25E-03 7.25E-03 7.25E-03 7.25E-03 7.25E-03 7.25E-03
7.25E-03
Child
1.77E-03 1.51E-03 1.51E-03 1.51E-03 1.51E-03 1.51E-03 1.51E-03
1.51E-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
Irrigated Foods : Leafy Vegetables
Adult
-
1.44E-05 5.72E-04 5.68E-04 5.58E-04 5.64E-04 5.60E-04
5.85E-04
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 : 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
Irrigated Foods : Meat
Adult
-
4.04E-05 9.71E-04 9.71E-04 9.60E-04 1.03E-03 9.61E-04
3.04E-03
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
Total
Adult
1.52E-03 7.88E-01 1.27E+00 9.00E-01 1.52E-01 5.32E-01 2.77E-01
1.91E-01
Teenager
8.47E-03 8.46E-01 1.28E+00 5.44E-01 1.26E-01 5.20E-01 2.78E-01
1.55E-01
Child
1.77E-03 1.05E+00 1.16E+00 2.75E-01 1.12E-01 4.52E-01 2.34E-01
1.24E-01
Infant
-
6.16E-05 8.52E-03 8.47E-03 8.46E-03 8.48E-03 8.47E-03
11.2-20
8.48E-03
Revision 1
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
RCS-MOV-118-S
M
RCS-MOV-116B-S
M
RCS-MOV-116A-S
M
RCS-VLV-021-S
RCS-PCV-061B-S
RCS-PCV-061A-S
TE
109F-N
TE
109E-N
TE
109D-N
TE
109C-N
TE
109B-N
TE
109A-N
TE
109L-N
TE
109K-N
TE
109J-N
TE
109P-N
1/2"-LMS-01F1
1/2"-LMS-01F1
TE
109S-N
TE
109R-N
TE
109Q-N
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
TE
109N-N
TE
109M-N
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
TE
109H-N
TE
109G-N
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
1/2"-LMS-01F1
EC6
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
L.O
EC6
VLV-013 -N
1/2"-T56
EC8
VLV-012 -N
1/2"-T56
EC8
VLV-011 -N
1/2"-T56
EC8
VLV-010 -N
1/2"-T56
EC8
VLV-009 -N
1/2"-T56
EC8
VLV-008 -N
1/2"-T56
EC8
VLV-007 -N
1/2"-T56
EC8
EC6
VLV-006 -N
1/2"-T56
EC8
L.O
VLV-005 -N
1/2"-T56
EC8
L.O
2"-LMS-01FA
VLV-014 -N
2"-C56L
ACR
H
LT
010 -N
H
CVS
G-11
2171 N0-EE10022
D RCP NO3 SEAL LEAK
OFF
CVS
G-4
2169 N0-EE10022
C RCP NO3 SEAL LEAK
OFF
3"x2"
2"-LMS-01F1
2"-LMS-01F1
2"-LMS-01F1
2"-LMS-01F1
NOTE3
P
T
R
P
NOTE4
EC8
R
P
EC8
EC6
VLV-021 -N
3/4"-LMS-01F1 3/4"-C56L
0
200
>=37(L)
3/4"-LMS-01FA
EC6
VLV-030 -N VLV-046 -N
2"-C56L
2"-X42D
2"-LMS-01FA
4"-LMS-01FA
4"x2"
P
EC6
VLV-091 -N
3/4"-X42D
EC6
4"-LMS-01FA
H.C
P
T
R
T.C
T
3/4"x3/8"
VLV-054 -N
2"-X42D
200
200
>=37(L)
D-6
1855
DS
3328 DS
C/V SUMP
TE
010 -N
P
T.C
F.C
EC6
H
ACR
4"x3"
TIA
010 -N
P 150
T 300
R >=37(G)
P
T
R
F.C
F.C
EC2
F.C
T
AOV-056 -S
2"-DA32R
T
T
P
AOV-053 -S
3/4"-DA42R
DS
DS 3336
C/V SUMP
VLV-031A-N
3"-X42D
R
4"x3"
R
3"-LMS-01FA 4"x3"
DS
DS 3338
C/V SUMP
VLV-031B-N
3"-X42D
3"-LMS-01FA
EC8
R
P
T
T
T
P
P
EC8
T.V
EC6 3/8"-LMS-25CA
T.V
VLV-057 -N
2"-X32D
P 150
T 200
R >=37(G)
2"-LMS-01CB
3"x2"
2485
650
>=37(L) EC8
EC8
P 200
T 200
R >=37(L)
VLV-058 -N
1"-C36L
SST-002 -N
P 100
T 200
R >=37(G)
SST-001 -N
P
25
T 200
R >=37(G)
3/4"-LMS-01FA
3/4"-LMS-01CB
2"-LMS-01CB
STR-001 -N
VLV-062 -N
3/4"-C56L
T
R
150
120
R <37(G)
EC9
P
PCV-014 -N
T
1"-RA32RZ
T
STR-002 -N
VLV-064 -N
P
3/4"-C36L
P
F.C
EC6
T
T
3/8"-LMS-25CA
V
V
PI
012 -N
3"-LMS-25G1
1"-NGS-01C2
NGS
N0-EE10251
N2
PI
011 -N
VLV-033A-N
3"-C42
3"-LMS-01FA
VLV-034A-N
3"-T42
E-2
3310
T
T
3"-LMS-01FA EC6
RCS
A-1
N0-EE10011 1747
D-LOOP DRAIN
VLV-034B-N
3"-T42
2"-LMS-25G1
VLV-033B-N
3"-C42
3"-LMS-01FA
3"-LMS-25G1
A-1
3222
DS
3326 DS
A/B ED SUMP
GMS
N0-EE10141
VH
DS
3337 DS
A/B ED SUMP
GMS
C-5
3278 N0-EE10143
GA
RCS
A-11
N0-EE10011 1775
A-LOOP DRAIN RCS
G-11
N0-EE10011 1768
2"-LMS-25G1
B-LOOP DRAIN RCS
3"x2"
H-1
N0-EE10011 1763
C-LOOP DRAIN
A-C/V REACTOR
COOLANT DRAIN
PUMP
MPP-001A-N
P 200
T 200
R >=37(L)
2"x1"
PIC
014 -N
RCS
D-11
N0-EE10012 1849
PMW
B-C/V REACTOR
COOLANT DRAIN
PUMP
MPP-001B-N
P
T
R
AOV-016 -N
2"-DA42R
EC6
F.C
VDS
N0-EE10511 3329
RCS VENT DRAIN
3"x2"
200
150
<37(L)
PT
014 -N
VLV-063 -N
3/4"-X32D
2"x3/4"
VLV-061 -N
3/4"-X42D
3/4"-LMS-01FA
3/4"x3/8"
3/4"x3/8"
RCS
A-6
N0-EE10011 1742
R/V FLANGE LEAK OFF
EC6
T.V
3/4"x3/8"
T
EC6
NOTE 1
VLV-017 -N
T
2"-T56
P
P
T
R
3/4"x3/8"
EC8
VLV-015 -N
3/4"-C56L
2"-LMS-01FA
VLV-018 -N
2"-C56
25
200
>=37(L)
2"-LMS-01FA
VLV-029 -N
3"-X42D
EC6
3"x2"
EC2
T
CVS
C-9
AOV-060 -S
N0-EE10021 2187
2"-DA32R
EXCESS LETDOWN HX.
B-6
1857
PEN#
284
EC2
PEN#
276R
P
60
T 300
R >=37(G)
OUTSIDE C/V
3/4"-LMS-01FA EC6
EC6
RCS
N0-EE10012
PRT
P 150
T 200
R >=37(G)
TI
010 -N
EC2
AOV-055 -S
2"-DA32R
T
T
F.C 3/4"-LMS-0151
T
INSIDE C/V
EC2
AOV-052 -S
3/4"-DA42R
P
EC6
SS CS
2"-LMS-01CB
3/8"-LMS-25CA EC6
RCS
N0-EE10012
PRT
EC8
VLV-071 -N
2"-X42D
3"x2"
NOTE2
C/V REACTOR
COOLANT
DRAIN TANK
MTK-001 -N
4"-LMS-01F1
LMS
D-4
3324 N0-EE10152
EC8
C/V SUMP
P
0
T 200
R <37(L)
NOTE2
P
2"-LMS-01FA
P 25 / 15
T 200
R >=37(L)
EC6
R
VLV-001 -N
3"-RV42N
EC6
3/4"x3/8"
EC6
11.2-21
R
EC3
3"-LMS-03A1
P
T
R
200
200
<37(L)
P 150
VLV-043 -N T 175 VLV-044 -N
3"-T42 R <37(L) 3"-C42
P
P 300
VLV-040 -N T 200 VLV-041 -N
3"-T54 R >=37(L)
3"-C54
P
T
VLV-080 -N
3/4"-X42D
VLV-038 -N
3/4"-T56
VLV-079 -N
3/4"-X42D
EC6
T
EC8
T.C
T.V
3/4"x3/8"
RWS
C-8
3340 N0-EE10191
RWSAT
LMS
A-4
3592 N0-EE10154
WHT
CVS
A-5
2792 N0-EE10026
HT
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
NOTES
1,SPOOL PIECE NORMALLY REMOVED ONLY TO BE INSTALLED
WHEN DRAINING AFTER DEPRESSURIZATION.
2,LOCATE LEAK-OFF INLET NOZZLE AS FAR AS POSSIBLE FROM
OUTLET NOZZLE.
3,LAYOUT PIPING WITH A DOWN SLOPE TO CVDT.
4,LOCATE VALVE BY CVDT AS NEAR AS POSSIBLE.
INSIDE C/V
OUTSIDE C/V
LOCAL
SAMPLE
3"-LMS-0151
VLV-035 -S VLV-036 -S
VLV-037 -S
3"-X42D
3"-T42
3"-C42
3"-LMS-01FA
R
EC8
VLV-042 -N
3"-X42D
T
EC6
VLV-039 -N
3"-X42D
3"-LMS-01FA
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 1 of 10)
SIS
H-4
2871 N0-EE10033
D-ACC. TANK DRAIN
SIS
F-4
2870 N0-EE10033
C-ACC. TANK DRAIN
SIS
D-4
2869 N0-EE10033
B-ACC. TANK DRAIN
PT
010 -N
EC8
3"x2"
3/4"-LMS-01FA
VLV-004 -N
3/4"-T58M
CVS
G-10
2180 N0-EE10021
B RCP NO3 SEAL LEAK
OFF
SIS
B-4
2868 N0-EE10033
A-ACC. TANK DRAIN
ACR
2"-LMS-01F1
2"-LMS-01F1
2"-LMS-01F1
2"-LMS-01F1
3/4"-LMS-01FA
VLV-003 -N
3/4"-T58M
PIA
010 -N
CVS
G-4
2183 N0-EE10021
A RCP NO3 SEAL LEAK
OFF
LICA
010 -N
LI
010 -N
PI
010 -N
CVS
E-11
2172 N0-EE10022
RCP D NO2 SEAL LEAK
OFF
CVS
E-6
2170 N0-EE10022
RCP C NO2 SEAL LEAK
OFF
CVS
E-11
2181 N0-EE10021
RCP B NO2 SEAL LEAK
OFF
CVS
E-6
2179 N0-EE10021
RCP A NO2 SEAL LEAK
OFF
EC6
2"-LMS-01FA
2"x1/2"
2"x1/2"
P
T
R
25
200
>=37(L)
VLV-025 -N VLV-026 -N
2"-T56
2"-C56
VLV-002 -N
3/4"-T58M
NOTE3
EC8
CVS
A-4
2174 N0-EE10022
RCP PURGE WATER
HEAD TANK
4"-LMS-01FA
3/4"x3/8"
3"-LMS-01FA
P
25
T 200
R >=37(G)
VLV-051 -N
3/4"-X42D
3/4"-LMS-01FA
2"x3/4"
P
25
T 200
R >=37(G)
VLV-085 -N
3/4"-X32D
3/4"x3/8"
VLV-086 -N
3/4"-X32D
VLV-083 -N
3/4"-X42D
3/4"-LMS-01CB
3"-LMS-01FA
2"-LMS-0152
VLV-084 -N
3/4"-X42D
VLV-087 -N
3/4"-X32D
TIA
109 -N
EC6
F.O
4"-LMS-01FA
25
200
>=37(L)
P
T
R
AOV-027 -N
4"-DA42D
VLV-028 -N
4"-C42
2"-LMS-25G1
H
3"-LMS-01FA
1"-LMS-01FA
2"x1"
3"-LMS-01FA
F.C
3"-LMS-01FA
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-077B-N
3/4"-X42D
VLV-077A-N
3/4"-X42D
3"x2"
EC8
2"-LMS-25G1
VLV-059 -N
3/4"-T58MJ
VLV-092A-N
3/4"-X42D
VLV-092B-N
3/4"-X42D
EC8
EC6
EC8
EC6
VLV-032B-N
3/4"-T58M
VLV-032A-N
3/4"-T58M
200
200
>=37(L)
P
T
R
R
EC6
EC2
3"-LMS-0151
EC2
F.C
3"-LMS-01FA EC6
200
200
>=37(L)
P
T
R
200 LCV-010B-S
3"-DA42R
300
>=37(L)
LCV-010A-S PEN# P
3"-DA42R 205 T
Revision 1
CP COL 11.2(6)
DWS
E-2
3359 N0-EE10211
DW
LI
092 -N
F.C
L
HH
H
3/4"-LMS-01F1
NOTE1
P
T
1"x3/4"
EC4
AOV-126 -N 1"-LMS-01F1
1"-DA42D
F.O
V
0
200
<37(L)
NOTE2
L
H
T
LT
093A-N
LICA
093A-N
4"-LMS-01F1
L
H
P
0
T 200
R <37(L)
LIA
093A-N
ACR
LT
093B-N
LI
093B-N
FIA
093B-N
HH
H
CVS
A-8
N0-EE10022 2168
RCP PWHT RELIEF
LINE
LMS
C-4
N0-EE10151 3324
CVDT RELIEF LINE
RWS
D-1
N0-EE10191 3836
RWSP OVERFLOW
LINE
C/V SUMP
1-1/2"-LMS-01F1
INSIDE C/V
OUTSIDE C/V
EC8
T.C
EC8
T.V
FT
094 -N
F.C
F.C
VLV-172 -N
3/4"-X42D
T
T
T
VLV-173 -N
3/4"-X42D
VLV-106 -N
3/4"-T58M
T
EC6
2"-LMS-01FA
2"-LMS-01F1
VLV-109 -N
2"-T56
T
P
T
R
VS
VS
LMS
A-8
3597 N0-EE10154
WHT
DS
DS 3358
FLOOR DRAIN
DS
DS 3357
EQUIP.DRAIN
3356
150
175
<37(L)
PI
106 -N
PI
109 -N
EC6
EC6
VLV-143B-N 2"-LMS-01FA
2"-T56
A-R/B SUMP
TANK
MTK-002A-N
NOTES
1,1 1/2INCH STAND PIPE OF 40INCH LENGTH.
2,FLANGE CONNECTION FOR REMOVAL.
3,LAYOUT PIPING WITH A DOWN SLOPE.
4,SLUDGE SEPARATOR BAFFLE PLATE.
5,OIL SEPARATOR.
B-R/B SUMP
TANK
MTK-002B-N
H
L
H
PI
107 -N
PI
110 -N
ACR ACR
L
P
0
T 150
R <37(L)
LT
108A-N
LICA
108A-N
LT
105B-N
LICA
105B-N
P
2"-LMS-01FA
ACR ACR
P
0
T 150
R <37(L)
LT
105A-N
LICA
105A-N
P
2"-LMS-01FA
L
H
LT
108B-N
LICA
108B-N
L
H
NOTE4
NOTE5
NOTE4
NOTE5
VLV-146 -N
2"-T56
VLV-150 -N
2"-T56
11.2-22
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 2 of 10)
R
VLV-127 -N
3/4"-X56N
3/4"-LMS-01F1
1"-LMS-01F1
3"-LMS-01F1
VS
VS 3365
D-CONTAINMENT
RECIRCULATION UNIT
VS
VS 3364
C-CONTAINMENT
RECIRCULATION UNIT
VS
VS 3363
B-CONTAINMENT
RECIRCULATION UNIT
VLV-123 -N 3/4"-LMS-01F1 VLV-124 -N P
3/4"-C56
3/4"-X42D T
EC10
VLV-125 -N
3/4"-T58M
SOV-121 -N VLV-122 -N
3/4"-TS52S 3/4"-X56N
P 150
T 150
R <37(L)
S
LT
092 -N
LIA
092 -N
NOTE3
EC4
0
200
<37(L)
P
T
R
3"-LMS-01F1
STAND PIPE
3"x1-1/2"
1-1/2"x3/4"
VS
VS 3362
A-CONTAINMENT
RECIRCULATION UNIT
3"-LMS-01F1
4"x1-1/2"
4"-LMS-01F1
EC8
VS
VS 3361
CRDM COOLING UNIT
FQ
094 -N
A-C/V SUMP
PUMP
MPP-002A-N
VLV-107 -N
3/4"-T58M
VLV-103A-N
1-1/2"-T56
VLV-102A-N
1-1/2"-C56
VLV-108 -N
3/4"-T56
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
P 150
T 200
R <37(L)
FE
094 -N
EC6
EC2
PEN#
207
B-C/V SUMP
PUMP
MPP-002B-N
2"-LMS-0151
2"-LMS-01FA
EC2
EC6
150
200
<37(L)
P
T
R
AOV-105 -S
2"-DA42R
150
300
<37(L)
P
T
R
AOV-104 -S
2"-DA42R
150
200
<37(L)
P
T
R
VLV-103B-N
1-1/2"-T56
VLV-102B-N
1-1/2"-C56
P 150
T 200
R <37(L)
VLV-141A-N
3/4"-T58M
A-R/B SUMP
PUMP
MPP-003A-N
VLV-141C-N
3/4"-T58M
C-R/B SUMP
PUMP
MPP-003C-N
150
150
<37(L)
P
T
R
P 150
T 150
R <37(L)
P 150
T 150
R <37(L)
VLV-143A-N
2"-T56
VLV-142A-N
2"-C56
VLV-143C-N
2"-T56
VLV-142C-N
2"-C56
P 150
T 150
R <37(L)
P 150
T 150
R <37(L)
150
150
<37(L)
P
T
R
150
150
<37(L)
P
T
R
B-R/B SUMP
PUMP
MPP-003B-N
150
150
<37(L)
P
T
R
D-R/B SUMP
PUMP
MPP-003D-N
EC8 3/4"x3/8"
LOCAL
SAMPLE
0
150
<37(G)
P
T
R
VLV-141D-N
3/4"-T58M
VLV-142B-N
2"-C56
VLV-143D-N 2"-LMS-01FA
2"-T56
VLV-142D-N
2"-C56
EC6
VLV-141B-N
3/4"-T58M
VLV-144 -N
3/4"-T56
VLV-148 -N
3/4"-T56
VLV-145 -N
1"-T56
EC8
EC8 3/4"x3/8"
LOCAL
SAMPLE
EC6
EC8 3/4"x3/8"
LOCAL
SAMPLE
0
150
<37(L) 1"-LMS-01FA
P
T
R
0
150
<37(L) 1"-LMS-01FA
P
T
R
EC6
P
T
R
EC6
VLV-149 -N
1"-T56
4"-LMS-01F1
EC8
T
P
T
R
T
R
DS
DS 3367
FLOOR DRAIN
DS
DS 3366
EQUIP.DRAIN
VS
3353 VS
R/B EXHAUST
NCS
B-5
N0-EE10102 2562
B-SURGE TANK
DS
DS 4582
FLOOR DRAIN
DS
DS 4583
EQUIP.DRAIN
VS
4578 VS
R/B EXHAUST
NCS
A-5
N0-EE10101 2555
A-SURGE TANK
LMS
A-8
3596 N0-EE10154
WHT
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
2"-LMS-01FA
150
175
<37(L)
3"x2"
150
175
<37(L)
VLV-151 -N
P
2"-C56
T
2"-LMS-01FA
4"-LMS-01F1
VLV-147 -N
2"-C56
P
T
R
P
T
R
0
150
<37(L)
0
150
<37(G)
0
150
<37(L)
0
150
<37(G)
P
T
R
2"-LMS-01FA
Revision 1
CP COL 11.2(6)
EC6
150
150
<37(L)
P
T
R
2"-LMS-01FA
VLV-202A-N 2"-LMS-01FA VLV-203A-N
2"-T56
2"-C56
PI
102 -N
2"-LMS-01FA
VLV-204 -N
3/4"-T56
P
0
T 150
R <37(L)
LOCAL
SAMPLE
L
H
PI
103 -N
2"-LMS-01FA
A/B SUMP TANK
MTK-004 -N
A-A/B SUMP
PUMP
MPP-006A-N
VLV-203B-N
2"-T56
150
150
<37(L)
P
T
R
VLV-202B-N
2"-C56
3/4"x3/8" EC8
VLV-201A-N
3/4"-T58M
P 150
T 150
R <37(L)
2"x1-1/2"
LT
101B-N
LICA
101B-N
150
175
<37(L)
ACR ACR
P
T
R
P
H
1"-LMS-01FA
L
NOTE1
NOTE2
EC6
DS
3400
FLOOR DRAIN
VS
3399 VS
A/B EXHAUST
LMS
A-7
3578 N0-EE10154
WHT
EC6
PI
096 -N
2"-LMS-01FA
VLV-224 -N
3/4"-T56
T
LOCAL
SAMPLE
VLV-227 -N
2"-C56
3/4"x3/8"EC8
VLV-226 -N
2"-T56
P
0
T 150
R <37(L)
A/B EQUIPMENT
DRAIN SUMP
TANK
MTK-003 -N
L
H
PI
097 -N
2"-LMS-01FA
LT
095A-N
LICA
095A-N
LT
095B-N
LICA
095B-N
150
175
<37(L)
ACR ACR
P
T
R
P
L
H
1"-LMS-01FA
NOTE1
NOTE2
DS
DS 3602
EQUIP.DRAIN
VS
3601 VS
A/B EXHAUST
B-1
N0-EE10154
WHT
EC6
LMS
3585
R/B
LT
098A-N
LICA
098A-N
LT
104A-N
LICA
104A-N
ACR ACR
ACR ACR
LT
104B-N
LICA
104B-N
LT
098B-N
LICA
098B-N
LOCAL
SAMPLE
L
H
L
H
PI
099 -N
PI
111 -N
VLV-246 -N
3/4"-T56
3/4"x3/8"
VLV-249 -N
3/4"-T56
3/4"x3/8"
NOTES
1, SLUDGE SEPARATOR BAFFLE PLATE.
2, OIL SEPARATOR.
3, CONNECTION FOR DISCHARGING TO LIQUID WASTE MANAGEMENT SYSTEM.
P
0
T 200
R <37(L)
B-NONRADIOACTIVE
DRAIN SUMP
L
H
P
0
T 200
R <37(L)
A-NONRADIOACTIVE
DRAIN SUMP
L
H
LOCAL
SAMPLE
11.2-23
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 3 of 10)
LT
101A-N
LICA
101A-N
VLV-201B-N
3/4"-T58M
EC6
2"x1-1/2"
P 150
T 150
R <37(L)
B-A/B SUMP
PUMP
MPP-006B-N
VLV-205 -N
1"-T56
0
150
<37(L)
P
T
R
2"-LMS-01F1
EC6
150
150
<37(L)
P
T
R
2"-LMS-01FA
VLV-222A-N 2"-LMS-01FA VLV-223A-N
2"-C56
2"-T56
P 150
T 150
R <37(L)
2"x1-1/2"
VLV-223B-N
2"-T56
150
150
<37(L)
P
T
R
VLV-222B-N
2"-C56
T
VLV-221A-N
3/4"-T58M
A-A/B
EQUIPMENT
DRAIN SUMP
PUMP
MPP-005A-N
VLV-221B-N
3/4"-T58M
VLV-207 -N
2"-C56
A/B
EC8
PI
100 -N
VLV-243 -N VLV-244 -N
2"-T56
2"-C56
3"x2"
PI
112 -N
EC8
3603
TURBINE SUMP
3"-LMS-01F1
REMARK:
DS
4597
FLOOR DRAIN
(NON-RADIOACTIVE)
DS
4596
EQUIP. DRAIN
(NON-RADIOACTIVE)
VS
4594
R/B EXAUST
DS
DS 3604
FLOOR DRAIN
(NON-RADIOACTIVE)
DS
DS 3605
EQUIP. DRAIN
(NON-RADIOACTIVE)
VS
3606 VS
R/B EXAUST
NOTE3
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
VLV-247 -N VLV-248 -N
2"-T56
2"-C56
2"-LMS-01F1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
2"x1-1/2"
P 150
T 150
R <37(L)
B-A/B
EQUIPMENT
DRAIN SUMP
PUMP
MPP-005B-N
VLV-225 -N
1"-T56
0
150
<37(L)
P
T
R
2"-LMS-01F1
P 150
T 200
R <37(L)
P 150
T 200
R <37(L)
VLV-206 -N
2"-T56
0
150
<37(G)
P
T
R
0
150
<37(G)
P
T
R
VLV-245A-N
3/4"-T58M
VLV-242A-N
1-1/2"-T56
VLV-242C-N
1-1/2"-T56
P 150
T 200
R <37(L)
A-NONRADIOACTIVE
DRAIN PUMP
MPP-004A-N
VLV-245C-N
3/4"-T58M
C-NONRADIOACTIVE
DRAIN PUMP
MPP-004C-N
150
200
<37(L) EC8
P
T
R
150
200
<37(L) EC8
P
T
R
VLV-241C-N
1-1/2"-C56
2"-LMS-01F1
VLV-242D-N
1-1/2"-T56
D-NONRADIOACTIVE
DRAIN PUMP
MPP-004D-N
VLV-241D-N
1-1/2"-C56
2"-LMS-01F1
VLV-241A-N
1-1/2"-C56
2"-LMS-01F1
VLV-242B-N
1-1/2"-T56
B-NONRADIOACTIVE
DRAIN PUMP
MPP-004B-N
VLV-241B-N
1-1/2"-C56
2"-LMS-01F1
P 150
T 200
R <37(L)
VLV-245B-N
3/4"-T58M
0
150
<37(G)
P
T
R
VLV-245D-N
3/4"-T58M
0
150
<37(G)
P
T
R
VLV-250 -N
2"-T56
Revision 1
CP COL 11.2(6)
F.C
VLV-313A-N
3/4"-C56
P
T
EC10
VLV-315A-N
3/8"-T58
P
VLV-301 -N
2"-C56L
P
3"-LMS-01FA
DWS
N0-EE10211
DW
LOCAL
SAMPLE
P
VLV-319A-N VLV-320A-N
3"-T42
3"-C42
VLV-317 -N VLV-319B-N VLV-320B-N
3"-X42D
3"-T42
3"-C42
T
F.O
(ED)
E-8
3608
AOV-321A-N 3"-LMS-01FA
3"-DA42R
AOV-316 -N
3"-DA42R
F.C
R
4"-LMS-01FA 4"x3"
LMS
C-7
3585 N0-EE10153
A/B EQUIP. DRAIN
SUMP TANK
VLV-314A-N
3/4"-T56
EC6
NOTE1
R
P
P
0
T 175
R <37(L)
L
ACR
VLV-310B-N
4"-X42D
P 200
T 175
R <37(L)
P
VLV-310A-N
4"-X42D
P 200
T 175
R <37(L)
P
LICA
020 -N
R
L.O
T
T
P
P
P
T
R
P
T
R
3"-LMS-01FA
P 200
T 175
R <37(L)
PI
025 -N
DS
3563 DS
A/B SUMP
V
3"-LMS-01FA
V
DS
3584 DS
A/B SUMP
P 200
T 175
R <37(L)
B-WASTE
HOLDUP TANK
PUMP
MPP-007B-N
200
175
<37(L)
R
PI
024 -N
(ED)
6"-LMS-01FA
NOTE1
A-WASTE
HOLDUP TANK
PUMP
MPP-007A-N
200
175
<37(L)
DS
3586 DS
A/B SUMP
VLV-305B-N
4"-X42D
R
P
DS
3588 DS
A/B SUMP
P
0
T 175
R <37(L)
VLV-322B-N VLV-323B-N AOV-324B-N
2"-T42
2"-DA42R
2"-C42
3"-LMS-01FA
ACR
2"-LMS-01FA
LICA
021 -N
VLV-322A-N VLV-323A-N AOV-324A-N
2"-T42
2"-DA42R
2"-C42
T
L
H
B-WASTE
HOLDUP TANK
MTK-005B-N
VLV-307B-N
3/4"-T58M
6"-LMS-01FA
6"-LMS-01FA
LMS
F-9
N0-EE10158 4096
CHEMICAL DRAIN
TANK PUMP
LMS
H-8
N0-EE10157 4098
DETERGENT DRAIN
MONITOR PUMP
LMS
A-2
3669 N0-EE10155
WASTE EFFLUENT
INLET FILTER
DS
3587 DS
A/B SUMP
CVS
C-7
N0-EE10026 3560
C-HOLDUP TANK
CVS
C-4
N0-EE10026 3562
B-HOLDUP TANK
CVS
C-2
N0-EE10026 3561
A-HOLDUP TANK
3"-LMS-01FA
2"-LMS-01FA
6"-LMS-01FA
2"-LMS-01FA
6"x4"
VLV-302 -N
3"-X42D
LT
021 -N
0
175
<37(L)
VLV-306B-N
3/4"-T58M
P
T
R
VS
3590 VS
A/B EXHAUST
SGS
G-4
N0-EE10182 3474
SGBD RADIATION
MONITOR
3/4"-LMS-01FA
3"-LMS-01FA
2"-LMS-01FA
P
T
R
F.C
F-8
3570
AOV-309 -N
4"-DA42R
DWS
N0-EE10211
DW
0
175
<37(L)
EC10
T
VLV-313B-N
3/4"-C56
P
VLV-315B-N
3/8"-T58
LOCAL
SAMPLE
P
VLV-319C-N VLV-320C-N
3"-T42
3"-C42
VLV-318 -N VLV-319D-N VLV-320D-N
3"-T42
3"-C42
3"-X42D
3"-LMS-01FA
P
LMS
C-3
N0-EE10153 3578
A/B SUMP TANK
SMS
B-11
N0-EE10161 3999
DEWATERING PUMP
(D)
3"-LMS-01FA
3"-LMS-01FA
3"-LMS-01FA
NOTE1
R
P
P
0
T 175
R <37(L)
DS
3609 DS
A/B SUMP
T
LT
022 -N
L
H
C-WASTE
HOLDUP TANK
MTK-005C-N
VLV-307C-N
3/4"-T58M
VLV-306C-N
3/4"-T58M
VS
3614 VS
A/B EXHAUST
150
175
<37(L)
LMS
A-9
N0-EE10156 4097
WASTE MONITOR
TANK PUMP
LICA
022 -N
ACR
DS
3616 DS
A/B SUMP
P
LMS
C-2
3610 N0-EE10158
NEUTRALIZING AGENT 3/4"-LMS-01FA
TANK
P
T
R
2"-LMS-01FA
2"-LMS-01FA
LMS
A-11
N0-EE10152 3596
R/B SUMP TANK
LMS
A-7
N0-EE10152 3597
C/V SUMP
LMS
D-2
N0-EE10158 3611
3/4"-LMS-01FA NEUTRALIZING AGENT
TANK
3"-LMS-01FA
2"-LMS-01FA
P
2"-LMS-01FA
(D)
3"x2"
1"-LMS-01FA
1"-LMS-01FA
1"-LMS-01FA
1"-LMS-01FA
2"-LMS-01FA
NOTE1
R
11.2-24
T
L
P
ACR
T
NOTE2
3997
TURRBINE BUILDING
SUMP
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
NOTES
1,THE TANK IS EQUIPPED WITH MIXING NOZZLES INSIDE.
2,TRANSFERRED ONLY IF THE CONTENT IS RADIOACTIVE.
3,CONNECTION FOR RECIEVING RADIOACTIVE CONTAMINATED
NON RADIOACTIVE DRAIN SUMP WATER.
DS
3612 DS
A/B SUMP
NOTE3
R
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
DS
3613 DS
A/B SUMP
P
0
T 175
R <37(L)
LICA
023 -N
2"-LMS-01FA
D-WASTE
HOLDUP TANK
MTK-005D-N
VLV-307D-N
3/4"-T58M
LT
023 -N
H
VLV-375 -N VLV-374 -N
2"-C42
2"-X42D
VS
3615 VS
A/B EXHAUST
VLV-306D-N
3/4"-T58M
P
VLV-332 -N VLV-331 -N
2"-C42
2"-X42D
LMS
E-2
N0-EE10155 3661
ACTIVATED CARBON
FILTER
LMS
B-6
N0-EE10155 3382
A-WASTE EFFLUENT
DEMI.
LMS
B-9
N0-EE10155 3385
B-WASTE EFFLUENT
DEMI.
LMS
E-6
N0-EE10155 3655
C-WASTE EFFLUENT
DEMI.
LMS
E-9
N0-EE10155 3657
D-WASTE EFFLUENT
DEMI.
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 4 of 10)
3"-LMS-01FA
DS
3571 DS
A/B SUMP
T
LT
020 -N
H
VLV-304B-N
4"-C42
4"-LMS-01FA
P
P
RWS
D-9
N0-EE10192 3575
REFUELING WATER
STORAGE AUX. TANK
LMS
D-2
3591 N0-EE10158
NEUTRALIZING AGENT 3/4"-LMS-01FA
TANK
P
T
R
150
175
<37(L)
2"-LMS-01FA
2"-LMS-01FA
VLV-304A-N
4"-C42
A-WASTE
HOLDUP TANK
MTK-005A-N
VLV-307A-N
3/4"-T58M
VLV-306A-N
3/4"-T58M
VLV-305A-N
4"-X42D
L.O
4"-LMS-01FA
VS
3589 VS
A/B EXHAUST
LMS
D-2
N0-EE10158 3572
3/4"-LMS-01FA NEUTRALIZING AGENT
TANK
3"-LMS-01FA
SFS
E-5
3618 N0-EE10112
B-SFP DEMI.
1"-LMS-01FA
1"-LMS-01FA
3"-LMS-01FA
F.C
2"-LMS-01FA
AOV-303A-N
3"-DA42D
F.C
0
175
<37(L)
P
T
R
2"-LMS-01F1
3"-LMS-01FA
2"-LMS-01FA
AOV-321B-N
3"-DA42R
DS
3624 DS
EQUIP.DRAIN
4"-LMS-01FA AOV-308A-N
4"-DA42R
F.O
2"-LMS-01FA
VLV-372B-N
3/4"-X42D
VLV-371A-N
2"-X42D
4"x3"
4"-LMS-01FA
F.O
AOV-321C-N
3"-DA42R
2"-LMS-01FA
F.C
VLV-311A-N
3/4"-T58M
F.C
SGS
A-9
N0-EE10182 3476
B-SG BLOWDOWN
CATION DEMI.
SGS
A-6
N0-EE10182 3475
A-SG BLOWDOWN
CATION DEMI.
LMS
B-11
N0-EE10151 3592
CVDT
AOV-321D-N
3"-DA42R
3"-LMS-01FA
VLV-372A-N
3/4"-X42D
AOV-303B-N
3"-DA42D
VLV-311B-N
3/4"-T58M
2"-LMS-01FA
AOV-308B-N
4"-DA42R
VLV-373A-N
3/4"-X42D
VLV-373B-N
3/4"-X42D
VLV-371B-N
2"-X42D
VLV-312A-N
3"-C42
VLV-312B-N
3"-C42
F.C
2"-LMS-01FA
2"-LMS-01FA
4"-LMS-01FA 4"x3"
F.O
4"-LMS-01FA
4"x3"
SGS
E-9
3499 N0-EE10182
B-SG BLOWDOWN MIX
DEMI.
SGS
E-6
3488 N0-EE10182
A-SG BLOWDOWN MIX
DEMI.
SFS
E-2
3619 N0-EE10112
A-SFP DEMI.
4"-LMS-01FA AOV-308C-N
4"-DA42R
VLV-314B-N
3/4"-T56
EC6
3"-LMS-01FA
2"-LMS-01FA
VLV-371C-N
2"-X42D
AOV-303D-N
3"-DA42D
F.C
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
AOV-308D-N
4"-DA42R
AOV-303C-N
3"-DA42D
F.C
0
175
<37(L)
P
T
R
2"-LMS-01FA
VLV-371D-N
2"-X42D
Revision 1
CP COL 11.2(6)
T
VLV-405 -N
2"-X42D
P
DS
DS 3663
A/B SUMP
SMS
A-9
N0-EE10161 3659
SRST
T
V
SSG-001A-N
VLV-482 -N
3/4"-X42D
T
R
VLV-476 -N
3/4"-X42D
VLV-413 -N
P
2"-X42D
R
P 200
T
175
R <37(L)
ACTIVATED
CARBON FILTER
MDM-001 -N
LMS
A-10
N0-EE10154 3661
WHT 2"-LMS-01FA VLV-411 -N
P 150
2"-X42D
T 175
R <37(L)
DS
DS 3670
A/B SUMP
VLV-472A-N
3/4"-X42D
A-WASTE
EFFLUENT
INLET FILTER
MFT-001A-N
VLV-402A-N
2"-X42D
2"-LMS-01FA
2"-LMS-01FA
VLV-401A-N
3/4"-T58M
VLV-471A-N
3/4"-X42D
H
RESIN FILL
VLV-409 -N
3/4"-T58M
T
LOCAL
SAMPLE
SSG-001B-N
EC6
VLV-414 -N
2"-C56
EC8
CVS
G-5
N0-EE10023 3664
PMW SUPPLY.
CONNECTION FOR MOBILE EQUIP.
DS
DS 3671
A/B SUMP
VLV-472B-N
3/4"-X42D
B-WASTE
EFFLUENT
INLET FILTER
MFT-001B-N
2"-LMS-01FA
VLV-401B-N
3/4"-T58M
H
LMS
A-5
N0-EE10156 3672
WASTE MONITOR
TANK
VLV-404B-N
3/4"-T58M
PDIA
029 -N
SMS
B-9
N0-EE10161 3407
SRST
1"-LMS-01FA
T
R
P
R
P
1"-LMS-01FA
VLV-479A-N
3/4"-X42D
VLV-436A-N
2"-X42D
T
P 200
T 175
R <37(L)
DS
DS 3654
A/B SUMP
SMS
A-9
N0-EE10161 3652
SRST
DS
DS 3674
A/B SUMP
T
VLV-447A-N
2"-X42D
R
T
PDIA
035 -N
R
H
VLV-479C-N
3/4"-X42D
VLV-436C-N
P
2"-X42D
R
P 200
T 175
R <37(L)
P
R
RESIN FILL
VLV-432A-N
3/4"-T58M
VLV-439A-N
3/4"-T56
RESIN FILL
VLV-432C-N
3/4"-T58M
H
VLV-439C-N
3/4"-T56
PDIA
036 -N
T
P
PDIA
031 -N
PDIA
033 -N
VLV-446B-N
2"-X42D
T
VLV-437C-N
1"-T56
LOCAL
SAMPLE
LOCAL
SAMPLE
1"-LMS-01FA
VLV-438C-N
1"-T56
3/4"x3/8"
T
VLV-435C-N
3/4"-T58M
H
T
VLV-437A-N
1"-T56
1"-LMS-01FA
VLV-438A-N
1"-T56
3/4"x3/8"
T
VLV-435A-N
3/4"-T58M
H
SST-003B-N
B-WASTE EFFLUENT
OUTLET STRAINER
4"x2"
4"x2"
VLV-447B-N
2"-X42D
DS
DS 3675
A/B SUMP
VLV-446A-N
2"-X42D
SST-003A-N
A-WASTE EFFLUENT
OUTLET STRAINER
4"x2"
4"x2"
T
V
C-WASTE DEMI.
MDM-002C-N
150 VLV-434C-N
1"-X42D
T 175
R <37(L)
LMS
A-10
N0-EE10154 3655
WHT
P
V
A-WASTE DEMI.
MDM-002A-N
CVS
B-10
3666 N0-EE10027
B.A.EVAP DESTILLATE.
3415
A/B SUMP
DS
P
WMS
A-9
N0-EE10156 3665
WASTE MONITOR
TANK PUMP
CVS
H-3
N0-EE10027 4188
B.A. EVAP FEED DEMI.
150 VLV-434A-N
1"-X42D
T 175
R <37(L)
LMS
A-10
N0-EE10154 3382
WHT
P
VLV-421 -N
2"-T56
2"-LMS-01FA
VLV-420 -N
2"-C56
VLV-422 -N
2"-C56
T
EC8
150
T
DS
DS 3653
A/B SUMP
SMS
A-9
N0-EE10161 3656
SRST
T
T 175
R <37(L)
LMS
B-10
N0-EE10154 3657
WHT
P
3416
A/B SUMP
SMS
B-9
N0-EE10161 3408
SRST
DS
P
1"-LMS-01FA
V
1"-LMS-01FA
VLV-434D-N
1"-X42D
P
VLV-479B-N
3/4"-X42D
VLV-436B-N
2"-X42D
T
T
R
VLV-479D-N
3/4"-X42D
VLV-436D-N
P
2"-X42D
R
P 200
T 175
R <37(L)
D-WASTE DEMI.
MDM-002D-N
R
P
R
P 200
T 175
R <37(L)
B-WASTE DEMI.
MDM-002B-N
150 VLV-434B-N
1"-X42D
T 175
R <37(L)
LMS
A-10
N0-EE10154 3385
WHT
P
V
RESIN FILL
VLV-432B-N
3/4"-T58M
VLV-431B-N
2"-X42D
VLV-439B-N
3/4"-T56
RESIN FILL
VLV-432D-N
3/4"-T58M
VLV-439D-N
3/4"-T56
11.2-25
T
PDIA
034 -N
VLV-437D-N
1"-T56
LOCAL
SAMPLE
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
LOCAL
SAMPLE
1"-LMS-01FA
VLV-438D-N
1"-T56
3/4"x3/8"
T
VLV-435D-N
3/4"-T58M
H
T
VLV-437B-N
1"-T56
PDIA
032 -N
1"-LMS-01FA
VLV-438B-N
1"-T56
3/4"x3/8"
T
VLV-435B-N
3/4"-T58M
H
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 5 of 10)
2"x3/4" VLV-419 -N
3/4"-T56
3/4"x3/8"
T
PDIA
030 -N
VLV-416 -N
2"-T56
VLV-412 -N
3/4"-T58M
H
VLV-473 -N VLV-474 -N
2"-C56
2"-X42D
VLV-404A-N
3/4"-T58M
PDIA
028 -N
VLV-410 -N
3"-X42D
3"-LMS-01FA
VLV-403A-N
2"-X42D
2"-LMS-01FA
VLV-408 -N
2"-X42D
VLV-417 -N
2"-X42D
2"-LMS-01FA
VLV-415 -N
2"-T56
VLV-402B-N
2"-X42D
VLV-403B-N
2"-X42D
R
VLV-448A-N
3/4"-T58M
VLV-471B-N
3/4"-X42D
EC6
VLV-481A-N
3/4"-X42D
2"-LMS-01FA
2"-LMS-01FA
VLV-483A-N
3/4"-X42D
2"-LMS-01FA
VLV-483C-N
3/4"-X42D
2"-LMS-01FA
VLV-445A-N
3/4"-T58M
VLV-448B-N
3/4"-T58M
VLV-431A-N
2"-X42D
VLV-444A-N
2"-X42D
VLV-431C-N
2"-X42D
VLV-444C-N
2"-X42D
LMS
F-6
3669 N0-EE10154
WASTE HOLDUP TANK
PUMP
VLV-443 -N
2"-X42D
VLV-433A-N
3"-X42D
3"-LMS-01FA
VLV-433C-N
3"-X42D
3"-LMS-01FA
VLV-481B-N
3/4"-X42D
VLV-441 -N
2"-X42D
VLV-418 -N
2"-X42D
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-445B-N
3/4"-T58M
VLV-440 -N
2"-X42D
VLV-442 -N
2"-X42D
VLV-483B-N
3/4"-X42D
2"-LMS-01FA
VLV-483D-N
3/4"-X42D
2"-LMS-01FA
VLV-433B-N
3"-X42D
3"-LMS-01FA
VLV-433D-N
3"-X42D
3"-LMS-01FA
2"-LMS-01FA
2"-LMS-01FA
VLV-444B-N
2"-X42D
VLV-431D-N
2"-X42D
VLV-444D-N
2"-X42D
REMARK:
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
Revision 1
CP COL 11.2(6)
VLV-511A-N VLV-512A-N
2"-C42
2"-T42
P
AOV-513A-N 2"-LMS-01FA
2"-DA42R
P 150
T 150
R <37(L)
P
0
T 150
R <37(L)
R T
DS
DS 3685
A/B SUMP
A-WASTE
MONITOR TANK
MTK-006A-N
F.C
VLV-510 -N
2"-X42D
T
P
P
2"-LMS-01FA
F.O
2"-LMS-01FA
NOTE1
AOV-501A-N
2"-DA42D
VLV-572A-N
2"-X42D
VLV-511B-N VLV-512B-N
2"-C42
2"-T42
2"-LMS-01FA
F.C
VLV-506B-N
3"-X42D
P
VLV-506A-N
3"-X42D
P
P
0
T 150
R <37(L)
VLV-503A-N
3/4"-T58M
VLV-502A-N
3/4"-T58M
VS
3686 VS
A/B EXHAUST
L
P 150
T 150
R <37(L)
P 150
T 150
R <37(L)
LT
038 -N
H
LICA
038 -N
R
R
ACR
T
T
P
P
2"-LMS-01FA
F.C
PI
040 -N
P
PI
041 -N
DS
3690 DS
A/B SUMP
P 150
T 150
R <37(L)
DS
3711 DS
A/B SUMP
P 150
T 150
R <37(L)
B-WASTE
MONITOR TANK
PUMP
MPP-008B-N
V
A-WASTE
MONITOR TANK
PUMP
MPP-008A-N
V
3"-LMS-01FA
DS
3681 DS
A/B SUMP
VLV-571 -N VLV-575 -N
2"-X42D
2"-C56
2"-LMS-01FA
CONNECTION FOR MOBILE EQUIP.
P 200
T 175
R <37(L)
3"-LMS-01FA
3"-LMS-01FA
P 150
T 150
R <37(L)
P 150
T 150
R <37(L)
P
0
T 150
R <37(L)
R T
DS
DS 3706
A/B SUMP
B-WASTE
MONITOR TANK
MTK-006B-N
AOV-513B-N
2"-DA42R
T
P
P
NOTE1
3/4"x3/8"
VLV-514B-N
3"-C42
VLV-509B-N
3/4"-T56
VLV-514A-N
3"-C42
VLV-509A-N
3/4"-T56
3/4"x3/8"
LOCAL
SAMPLE
LOCAL
SAMPLE
VLV-503B-N
3/4"-T58M
VLV-502B-N
3/4"-T58M
VS
3709 VS
A/B EXHAUST
LT
039 -N
L
H
LICA
039 -N
ACR
2"-LMS-01FA
DS
3704 DS
A/B SUMP
T
VLV-518 -N
3/4"-T58M
VLV-519 -N
3/4"-T58M
VLV-521B-N
3"-T42
VLV-521A-N
3"-T42
T
H
FT
043 -N
VLV-520 -N
2"-X42D
P
AOV-522B-N
3"-DA42R
VLV-528 -N
3/4"-T58M
ACR
VLV-527 -N
3/4"-T58M
P 150
T 150
R <37(L)
FT
044 -N
RIA
035 -N
RICA
035 -N
ACR
ACR
AOV-522A-N
3"-DA42R
FIA
044 -N
H
H
FI
043 -N
LMS
A-7
3665 N0-EE10155
WASTE DEMIN.
LMS
A-9
4097 N0-EE10154
WHT
SS CS
RE
035 -N
EC6
11.2-26
P
AOV-523 -N
3/4"-IA52R
T
EC8
EC8
R
E-8
3628
LMS
G-9
N0-EE10157 3430
DETERGENT DRAIN
MONITOR TANK PUMP
DWS
N0-EE10211
DW
PWS
D-1
N0-EE10201 3754
PMW PUMP
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
NOTE
1,THE TANK IS EQUIPPED WITH MIXING NOZZLE INSIDE.
2"-LMS-01FA
VLV-524 -N
3/4"-C56
EC6
VLV-526 -N VLV-525 -N
1-1/2"-C56 1-1/2"-T56
L.C
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
4481
DISCHARGE HEADER
1-1/2"-LMS-01FA
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 6 of 10)
P
0
T 150
R <37(L)
2"-LMS-01FA
3"-LMS-01FA AOV-504A-N
3"-DA42R
VLV-505 -N
3"-X42D
F.O
2"-LMS-01FA
VLV-577 -N VLV-576 -N
2"-X42D
2"-C56
F.C
VLV-541 -N
2"-X42D
VLV-507A-N
3/4"-T58M
VLV-507B-N
3/4"-T58M
2"-LMS-01FA
AOV-504B-N
3"-DA42R
LMS
G-5
N0-EE10155 3672
WASTE DEMIN.
FE
043 -N
CVS
B-10
4091 N0-EE10027
B.A.EVAP
VLV-573A-N
3/4"-X42D
VLV-573B-N
3/4"-X42D
VLV-578A-N
3/4"-X42D
VLV-578B-N
3/4"-X42D
AOV-501B-N
2"-DA42D
VLV-572B-N
2"-X42D
VLV-508A-N
2"-C42
VLV-508B-N
2"-C42
F.C
F.C
CONNECTION FOR MOBILE EQUIP.
VLV-515B-N
2"-X42D
3"-LMS-01FA
3"-LMS-01FA
VLV-533 -N
3"-C42
VLV-532 -N
3"-X42D
3"-LMS-01FA
RCV-035B-N
3"-DA42R
VLV-521 -N
2"-X42D
VLV-517 -N
2"-C42
VLV-516 -N
2"-T56
2"-LMS-01FA VLV-515A-N
2"-X42D
3"-LMS-01FA
3"x2"
RCV-035A-N
3"-DA42R
VLV-530 -N
3"-X42D
VLV-529 -N
3"-X42D
3"-LMS-01FA
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
3"-LMS-01FA
L.C
3/4"-LMS-01FA
3"x2"
FE
044 -N
VLV-531 -N
3"-X42D
Revision 1
CP COL 11.2(6)
DS
DS 3437
A/B SUMP
VS
VS 3436
A/B EXHAUST
2"-LMS-01FA
F.O
0
175
<37(L)
P
T
R
3"-LMS-01FA
T
T
P
DS
3434 DS
A/B SUMP
VLV-606 -N
2"-X42D
P
P
VLV-605 -N
3/4"-T58M
P
0
T 175
R <37(L)
DETERGENT
DRAIN TANK
MTK-007 -N
VLV-604 -N
3/4"-T58M
R
VLV-672A-N
3/4"-X42D
P 150
T 175
R <37(L)
T
P
L
R
T
P
H
PI
070 -N
DS
3438 DS
A/B SUMP
V
DS
3435 DS
A/B SUMP
VLV-601B-N
3"-X42D
ACR
4"x3"
LICA
069 -N
1"-LMS-01FA
DETERGENT
DRAIN TANK
PUMP
MPP-009 -N
LT
069 -N
R
VLV-602B-N 4"x3"
3"-X42D
SST-004B-N
DS
3429 DS
A/B SUMP
VLV-601A-N
3"-X42D
L
H
ACR
VLV-609 -N
1"-T56
LICA
077 -N
VLV-608 -N
1"-C56
150
175
<37(L)
P
T
R
R
VLV-619 -N
3/4"-T58M
P
0
T
175
R <37(L)
150
175
<37(L)
1"-LMS-01FA
DETERGENT
DRAIN MONITOR
TANK
MTK-008 -N
VLV-618 -N
3/4"-T58M
1"-LMS-01FA
P
T
R
VLV-610 -N
3/4"-T56
3/4"x3/8"
DS
DS 3433
A/B SUMP
LT
077 -N
SAMPLING
VLV-611 -N
1"-T56
P
T
P
P
VLV-612 -N
3/4"-T58M
NOTE1
VLV-620 -N
2"-X42D
P
P
T
R
R
0
175
<37(L)
2"-LMS-01FA
2"-LMS-01FA
2"-LMS-01FA
T
P
F.C
AOV-627 -N
2"-DA42R
P
R
T
V
P 150
T 175
R <37(L)
DS
3441 DS
A/B SUMP
P
1"-LMS-01FA
2"-LMS-01FA
R
VLV-615 -N
1"-X42D
VLV-622 -N VLV-623 -N
2"-C56
2"-X42D
2"-LMS-01FA
VLV-626 -N VLV-625 -N
2"-C56
2"-T56
DETERGENT
DRAIN MONITOR
TANK PUMP
MPP-010 -N
2"x1"
T
H
DS
DS 3440
A/B SUMP
PI
078 -N
DS
3431 DS
A/B SUMP
VS
3432 VS
A/B EXHAUST
P 150
T 175
R <37(L)
DETERGENT
DRAIN FILTER
MFT-002 -N
VLV-613 -N VLV-614 -N
1"-C56
1"-X42D
P
PDIA
072 -N
F.C
VLV-624 -N
3/4"-T56
3/4"x3/8"
P
T
R
AOV-631 -N
2"-DA42R
T
150
175
<37(L)
P
T
R
F-11
3430 N0-EE10156
DISCHARGE HEADER
2"-LMS-01FA LMS
VLV-633 -N
2"-C56
150
150
<37(L)
LMS
A-6
4098 N0-EE10154
WHT
VLV-632 -N
2"-T56
LOCAL
SAMPLE
CONNECTION FOR ALTERNATE PROCESS
1"-LMS-01FA
VLV-616 -N
3/4"-T58M
11.2-27
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
NOTES
1,THE TANK IS EQUIPPED WITH MIXING NOZZLE INSIDE.
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 7 of 10)
0
175
<37(L)
R
VLV-673 -N
3/4"-X42D
P
T
R
AOV-603 -N
3"-DA42D
2"-LMS-01FA
VLV-672B-N
3/4"-X42D
VLV-674 -N
3/4"-X42D
4"x3"
VLV-683 -N
3/4"-X42D
VLV-602A-N 4"x3"
3"-X42D
F.C
3"-LMS-01FA
VLV-607 -N
3/4"-T58M
3443
HAND WASH DRAIN
1"-LMS-01FA
VLV-680 -N
3/4"-X42D
SST-004A-N
2"-LMS-01FA
2"-LMS-01FA
3442
SHOWER DRAIN
VLV-681 -N
3/4"-X42D
AOV-617 -N
1"-DA42R
0
175
<37(L)
P
T
R
VLV-677 -N
3/4"-X42D
VLV-621 -N
3/4"-T58M
VLV-678 -N
3/4"-X42D
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
2"-LMS-01FA
SSG-002 -N
VLV-684 -N
3/4"-X42D
150
175
<37(L)
P
T
R
VLV-630 -N VLV-629 -N VLV-628 -N
2"-C56
2"-T56
2"-X42D
VLV-679 -N
1"-X42D
Revision 1
CP COL 11.2(6)
DS
DS 3437
A/B SUMP
VS
VS 3436
A/B EXHAUST
2"-LMS-01FA
F.O
0
175
<37(L)
P
T
R
0
175
<37(L)
R
VLV-673 -N
3/4"-X42D
P
T
R
AOV-603 -N
3"-DA42D
2"-LMS-01FA
3"-LMS-01FA
P
DS
3434 DS
A/B SUMP
VLV-606 -N
2"-X42D
P
P
VLV-605 -N
3/4"-T58M
P
0
T 175
R <37(L)
VLV-672A-N
3/4"-X42D
P 150
T 175
R <37(L)
T
P
L
R
T
P
H
PI
070 -N
DS
3438 DS
A/B SUMP
V
DS
3435 DS
A/B SUMP
VLV-601B-N
3"-X42D
ACR
4"x3"
LICA
069 -N
1"-LMS-01FA
DETERGENT
DRAIN TANK
PUMP
MPP-009 -N
LT
069 -N
R
VLV-602B-N 4"x3"
3"-X42D
SST-004B-N
DS
3429 DS
A/B SUMP
L
H
ACR
VLV-609 -N
1"-T56
LICA
077 -N
VLV-608 -N
1"-C56
150
175
<37(L)
P
T
R
R
VLV-619 -N
3/4"-T58M
P
0
T
175
R <37(L)
150
175
<37(L)
1"-LMS-01FA
DETERGENT
DRAIN MONITOR
TANK
MTK-008 -N
VLV-618 -N
3/4"-T58M
1"-LMS-01FA
P
T
R
VLV-610 -N
3/4"-T56
3/4"x3/8"
DS
DS 3433
A/B SUMP
LT
077 -N
SAMPLING
VLV-611 -N
1"-T56
P
T
P
P
VLV-612 -N
3/4"-T58M
NOTE1
VLV-620 -N
2"-X42D
P
P
T
R
R
0
175
<37(L)
2"-LMS-01FA
2"-LMS-01FA
2"-LMS-01FA
T
P
F.C
AOV-627 -N
2"-DA42R
P
R
T
V
P 150
T 175
R <37(L)
DS
3441 DS
A/B SUMP
P
1"-LMS-01FA
2"-LMS-01FA
R
VLV-615 -N
1"-X42D
VLV-622 -N VLV-623 -N
2"-C56
2"-X42D
2"-LMS-01FA
VLV-626 -N VLV-625 -N
2"-C56
2"-T56
DETERGENT
DRAIN MONITOR
TANK PUMP
MPP-010 -N
2"x1"
T
H
DS
DS 3440
A/B SUMP
PI
078 -N
DS
3431 DS
A/B SUMP
VS
3432 VS
A/B EXHAUST
P 150
T 175
R <37(L)
DETERGENT
DRAIN FILTER
MFT-002 -N
VLV-613 -N VLV-614 -N
1"-C56
1"-X42D
P
PDIA
072 -N
F.C
VLV-624 -N
3/4"-T56
3/4"x3/8"
P
T
R
AOV-631 -N
2"-DA42R
T
150
175
<37(L)
P
T
R
F-11
3430 N0-EE10156
DISCHARGE HEADER
2"-LMS-01FA LMS
VLV-633 -N
2"-C56
150
150
<37(L)
LMS
A-6
4098 N0-EE10154
WHT
VLV-632 -N
2"-T56
LOCAL
SAMPLE
CONNECTION FOR ALTERNATE PROCESS
1"-LMS-01FA
VLV-616 -N
3/4"-T58M
11.2-28
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 8 of 10)
T
T
DETERGENT
DRAIN TANK
MTK-007 -N
VLV-604 -N
3/4"-T58M
R
VLV-601A-N
3"-X42D
VLV-672B-N
3/4"-X42D
VLV-674 -N
3/4"-X42D
4"x3"
VLV-683 -N
3/4"-X42D
VLV-602A-N 4"x3"
3"-X42D
F.C
3"-LMS-01FA
VLV-607 -N
3/4"-T58M
3443
HAND WASH DRAIN
1"-LMS-01FA
VLV-680 -N
3/4"-X42D
SST-004A-N
2"-LMS-01FA
2"-LMS-01FA
3442
SHOWER DRAIN
VLV-681 -N
3/4"-X42D
AOV-617 -N
1"-DA42R
0
175
<37(L)
P
T
R
VLV-677 -N
3/4"-X42D
VLV-621 -N
3/4"-T58M
VLV-678 -N
3/4"-X42D
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
2"-LMS-01FA
SSG-002 -N
VLV-684 -N
3/4"-X42D
150
175
<37(L)
P
T
R
VLV-630 -N VLV-629 -N VLV-628 -N
2"-C56
2"-T56
2"-X42D
VLV-679 -N
1"-X42D
STD-LMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
NOTES
1,THE TANK IS EQUIPPED WITH MIXING NOZZLE INSIDE.
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Unit 3
(shown in
Outside
Yard
detail on
Unit 3
Sheet 6)
A-Waste
Monitor Tank
ATK-OOSA
RCV-035A
3"-DA42R
RE
RCV-035B
3"-DA42R
~
:r
--@
B- Waste
Monitor Tank
ATK-OOSB
VLV-521B
3"-T42
VLV-531
3"-X42D
AOV-522B
3"-DA42R
'r..
~
~~.
I
I
1_ -.J.J
®-
Header and
Discharge
Outfall
(exisiting)
U it 1 Flow
Receiver &
~
B- Waste
Monitor Tank
Pump
APP-008B
To SCR via
Unit 1
Circulating
Water Return
ead Box
( existing)
Unit 4
Unit 4
M
A-Waste
Monitor Tank
ATK- OOSA
A-Waste
Monitor Tank
Pump
APP-OOBA
VLV-521A
3"-T42
RE
RCV-035A
3"-DA42R
RCV-035B
3"-DA42R
-
B- Waste
Monitor Tank
ATK-OOSB
VLV-521B
3"-T42
AOV-522B
3"-DA42R
Evaporation Pond
C
VLV-531
3"-X42D
B- Waste
Monitor Tank
Pump
APP-008B
CP COL 11.2(6)
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 9 of 10)
11.2-29
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CPNPP Units 3 and 4 Discharge Schematic
Existing
Unit 4
I
Unit 3
1
:----------1
N
-
III
8-1f'.oM5-X-049-
8·VVMS-X.(I52·
00lX
00lX
8-VVMS-X-002152G
8-V'.MS-X-062152G
s.cWX·271).
100G
s.cW-'-05€
100G
i
I
I
I
I t~
I
II
I_-.JJ
Evaporation Pond
8-WvlS-X· OS200lX
r - - + - - - - - - - ...- - - - - - r - - - - -+
8-CW-l..(lS7100G
12·CW1 -028100G
48-CW-l-021·
100G
-+- - - .- - - .- - - - +- -
I
I
Discharge
Flume
60-CW-l-022·
100G
6(}-CW1-022·
- - - - - - - - - - - - - - 100G:
- ---+ .
Unit 1
:
I
:'- Discharge
Box i1
______________
I
I
I
I
I
I
I
I
I
I
I
:
I
I
I
I
I
I
:
I
I
I
I
I
I
CW
:.
:
-+! Discharge ~ :I Structure II
CW
I
Return
__L_
: x:
I
1
I
IN
I .....
Drawing M 1-0280-A
UFSAR Fig 9.2-15
Sh 2
Drawing
M1-0280
UFSAR Fig
9.2-15
Sh 1
Drawing M1-0210
UFSAR Fig 10.4-5 Sh 1
Drawing M1-021 O-A
UFSAR Fig 10.4-5 Sh 2
0,
OJ,
,
WI
0>1
."-
I
I=:>
~ I
I
CP COL 11.2(6)
SCR
~-- ...- ______ I
Waste
Water
Unit 1 Flow
Receiver &
Head Box
Drawing M1-0281-A
UFSAR Fig 9.2-16 Sh 2
--+
1
I
I
I
It....
c: ro
I
() ,
(/J'
.- I
0,
I_____ J
Figure 11.2-201 Liquid Waste Management System Piping and Instrumentation Diagram(Sheet 10 of 10)
11.2-30
Revision 1
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. Based on a population dose results of
2.59 person-rem per year (Total Body), 2.97 person-rem per year (Thyroid) 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.
11.3.3.1
Radioactive Effluent Releases and Dose Calculation in Normal
Operation
11.3-1
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
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 (/Q)
are 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, also the radioactive concentrations at exclusion
area boundary (EAB) are bounded by the values given in DCD Tables 11.3-5
through 11.3-7. The maximum individual doses are calculated using the GASPAR
II Code (Reference 11.3-17) which implements the exposure methodology
described in RG1.109. 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 5.77E-03 mrad/yr and the beta dose in
air is 4.46E-02 mrad/yr, which are less than the criteria of 10 mrad/yr and 20
mrad/yr, respectively, that are required in 10 CFR 50, Appendix I. All of the dose to
total body, the dose to skin, and the dose to organ are less than the criteria in 10
CFR 50, Appendix I: 3.69E-03 mrem/yr for 5 mrem/yr, 3.45E-02 mrem/yr for 15
mrem/yr, and 1.40E+00 mrem/yr [child’s bone] for 15 mrem/yr, respectively. The
compliance with 10 CFR 20.1302 is also demonstrated.
The population doses within the 50mi 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. Calculated doses are
1.58 person-rem(Total body) and 1.98 person-rem(Thyroid).
Additionally, the dose from the evaporation pond is also calculated using the
GASPAR II Code (Reference 11.3-17). The half of the liquid effluent is assumed to
be diverted into the evaporation pond. Conservatively, all of the radioactive
nuclides in the evaporation pond are assumed to be discharged to atmosphere as
aerosol and 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). And population doses are 1.01
person-rem(Total body) and 0.995 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 2.48E+00 mrem/yr (Adult’s GI-Tract). And
the total of population doses are 2.59 person-rem(Total body) and 2.97
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.
11.3-2
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
11.2-205.
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)
11.3(9) Piping and instrumentation diagrams
This COL item is addressed in Subsection 11.3.2 and Figure 11.3-201.
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.
11.3-3
Revision 1
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
Parameter
Value
/Q (s/m3)
For maximum individual dose calculation
No Decay, Undepleted
2.28 Day Decay, Undepleted
8 Day Decay, Depleted
For population dose calculation
4.40E-07
4.40E-07
3.90E-07
Section 2.3
2
D/Q (1/m )
For maximum individual dose calculation
For population dose calculation
Distance to Residence (mi)
Midpoint of plant life (s)
Fraction of the year that leafy vegetables are grown.
Fraction of the year that milk cows are on pasture.
Fraction of milk-cow feed intake that is from pasture while
on pasture.
Fraction of the year that goats are on pasture.
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.
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
Source term
Other parameters
4.50E-09
Section 2.3
0.79
9.46E+08(30yr)
1.0
1.0
1.0
1.0
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
DCD Table 11.3-5
(Sheet 1 to 3)
RG 1.109
11.3-4
Revision 1
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 (Sheets 1 of 2)
Type of Dose
Dose (1)
Gamma dose in air (mrad/yr)
5.77E-03
Beta dose in air (mrad/yr)
4.46E-02
Dose to total body (mrem/yr)
3.69E-03
Dose to skin (mrem/yr)
3.45E-02
Note:
1. Dose due to noble gases that include Ar-41
11.3-5
Revision 1
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 (Sheets 2 of 2)
Pathway
Dose to each organ (1) (mrem/yr)
GI-Tract
4.35E-02
Bone
4.35E-02
Liver
4.35E-02
Kidney
4.35E-02
Thyroid
4.35E-02
Lung
4.35E-02
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
1.91E-03
4.80E-04
1.87E-03
1.85E-03
4.27E-03
2.98E-03
Teen
1.92E-03
5.67E-04
1.91E-03
1.88E-03
5.09E-03
3.59E-03
Child
1.65E-03
6.72E-04
1.70E-03
1.66E-03
5.74E-03
3.08E-03
Infant
9.38E-04
2.97E-04
9.92E-04
9.60E-04
4.74E-03
1.95E-03
Adult
1.15E-01
4.51E-01
1.34E-01
1.07E-01
2.32E-01
9.83E-02
Teen
1.38E-01
6.48E-01
1.87E-01
1.41E-01
3.23E-01
1.27E-01
Child
2.23E-01
1.40E+00
3.25E-01
2.48E-01
6.16E-01
2.23E-01
Infant
1.99E-01
9.35E-01
3.72E-01
2.46E-01
9.79E-01
2.16E-01
Ground
Vegetable
Meat
Cow Milk
Goat Milk
Inhalation
Total(2)
Note:
1. Dose due to iodine, particulate, H-3 and C-14
2. Conservatively, both Cow Milk and Goat Milk are considered.
11.3-6
Revision 1
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
11.3-7
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 1
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.
11.3-8
Revision 1
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
Parameter
Value
3
/Q (s/m )
For maximum individual dose calculation
No Decay, Undepleted
2.28 Day Decay, Undepleted
8 Day Decay, Depleted
For population dose calculation
3.10E-06
3.10E-06
2.90E-06
Section 2.3
2
D/Q (1/m )
For maximum individual dose calculation
For population dose calculation
2.10E-08
Section 2.3
Distance to Residence (mi)
Midpoint of plant life (s)
Fraction of the year that leafy vegetables are grown.
Fraction of the year that milk cows are on pasture.
Fraction of milk-cow feed intake that is from pasture while
on pasture.
Fraction of the year that goats are on pasture.
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.
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
Table 11.3-201
Source term
Table 11.3-202
Other parameters
0.31
9.46E+08(30yr)
1.0
1.0
1.0
1.0
1.0
0.76
8.0
1.0
1.0
Cow and Goat
9.08E+08
4.25E+07
4.81E+08
RG 1.109
11.3-9
Revision 1
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
2.20E-02
Bone
2.20E-02
Liver
2.20E-02
Kidney
2.20E-02
Thyroid
2.20E-02
Lung
2.20E-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
5.85E-02
5.16E-04
5.68E-02
5.69E-02
5.68E-02
7.43E-02
Teen
5.91E-02
7.25E-04
5.75E-02
5.75E-02
5.74E-02
8.74E-02
Child
5.13E-02
9.89E-04
5.08E-02
5.09E-02
5.08E-02
7.74E-02
Infant
2.93E-02
5.44E-04
2.93E-02
2.93E-02
2.94E-02
5.08E-02
Adult
2.37E+00
9.57E-02
3.81E-01
3.97E-01
3.29E-01
3.26E-01
Teen
1.75E+00
1.21E-01
4.78E-01
4.54E-01
3.83E-01
3.86E-01
Child
1.37E+00
2.42E-01
7.02E-01
6.48E-01
5.63E-01
5.30E-01
Infant
3.87E-01
2.32E-01
7.45E-01
4.99E-01
5.34E-01
4.37E-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.
11.3-10
Revision 1
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) (mrem/yr)
GI-Tract
6.55E-02
Bone
6.55E-02
Liver
6.55E-02
Kidney
6.55E-02
Thyroid
6.55E-02
Lung
6.55E-02
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
6.04E-02
9.96E-04
5.87E-02
5.88E-02
6.11E-02
7.73E-02
Teen
6.10E-02
1.29E-03
5.94E-02
5.94E-02
6.25E-02
9.10E-02
Child
5.29E-02
1.66E-03
5.25E-02
5.26E-02
5.65E-02
8.05E-02
Infant
3.02E-02
8.41E-04
3.03E-02
3.03E-02
3.41E-02
5.28E-02
Adult
2.48E+00
5.47E-01
5.16E-01
5.04E-01
5.61E-01
4.25E-01
Teen
1.88E+00
7.70E-01
6.64E-01
5.95E-01
7.06E-01
5.14E-01
Child
1.60E+00
1.65E+00
1.03E+00
8.96E-01
1.18E+00
7.53E-01
Infant
5.86E-01
1.17E+00
1.12E+00
7.45E-01
1.51E+00
6.53E-01
Ground
Vegetable
Meat
Cow Milk
Goat Milk
Inhalation
(2)
Total
Note:
1. Dose due to iodine, particulate and H-3
2. Conservatively, both Cow Milk and Goat Milk are considered.
11.3-11
Revision 1
STD COL 11.3(9)
3/4"-GMS-01FA
NCS
NCS
GMS
N0-EE10141
HT
H-3
4478
C-10
N0-EE10026
HT
CVS
2794
EC8
PT
019 -N
ACR
VLV-021A-N
1"-C56
3/4"-GMS-01CB
CVS
N0-EE10026
HT
B-10
2788
EC8
GMS
B-1
3239 N0-EE10143
GA
3/8"-GMS-25CA
PCV-019B-N
3/4"-DA42R
F.C
SS CS
PICA
019 -N
3/4"x3/8"
H
A-7
3247
PI
019 -N
GMS
N0-EE10141
VH
R
P 150
T 200
R >=37(G)
T
P
VLV-041 -N
2"-X32D
P
EC6
T
R
1"-GMS-01FA
2"x1"
2"-GMS-01CB
EC6
A-WASTE GAS
COMPRESSOR
MEQ-001A-N
NGS
N0-EE10251
N2
P 150
VLV-040A-N
1"-C36L
B-8
3952
PICA-143-N
1"-GMS-01CB
GMS
B-1
3242 N0-EE10142
WASTE GAS DRYER
GMS
B-10
N0-EE10141 4480
B-WASTE GAS COMP.
PCV-143 -N
1"-RA32RB
GMS
B-2
N0-EE10141 4478
A-WASTE GAS COMP.
F.C
F.C
AOV-039A-N
1"-DA42R
1"-GMS-01CB
P 150
T 200
R >=37(G)
VS
4092 VS
A/B EXHAUST.
VLV-035 -N
3/4"-X32D
VLV-002A-N
2"-C56L
PICA-011-N
PICA-143-N
VLV-049 -N
3/4"-T56Z
VLV-047 -N
3/4"-T56Z
PT
020 -N
ACR
P 150
T 200
R >=37(L)
STR-001A-N
R
2"x1-1/2"
SST-003 -N
SST-002 -N
1"-GMS-01CB
T
T
P
PT
013 -N
R
P
P
2"x1"
SS CS
P
SS CS
T
P
P
P 150
T 200
R >=37(G)
P
B-WASTE GAS
SURGE TANK
MTK-001B-N
T
VLV-050 -N
3/4"-C56L
VLV-048 -N
3/4"-C56L
R
R
L.O
VLV-028 -N
1"-X32D
R
T
2"-GMS-01CB
F.C
1"x3/4"
DS
4574 DS
A/B ED SUMP
DS
4573 DS
A/B ED SUMP
P
T
P
EC6
100
200
R >=37(G)
VLV-009B-N P
3/4"-X42D T
CS SS
VLV-006 -N
2"-X42D
VLV-040B-N
1"-C36L
C-8
3963
1"-GMS-01CB
3/4"-GMS-01CB
PT
021 -N
ACR
DS
DS 3252
A/B ED SUMP
PCV-021B-N
3/4"-DA42R
F.C
SS CS
PICA
021 -N
3/4"x3/8"
H
PI
021 -N
DS
DS 3235
A/B ED SUMP
DS
4638 DS
A/B ED SUMP
VLV-051B-N
3/4"-X42D
SMS
B-1
N0-EE10161 3982
BREAK UP PIPE
GMS
G-1
N0-EE10142 3249
CHARCOAL BED
PT
014 -N
VLV-029 -N
1"-X32D
R
R
L.O
VLV-016B-N
3/4"-C56L
P
0
T 150
R <37(L)
P 100
T 200
R >=37(G)
P
STR-001B-N
P 150
T 200
R >=37(L)
P
R
T
R
T
P
2"-GMS-01CB
1"-GMS-01CB
PICA-012-N
PICA-143-N
B-WASTE GAS
COMPRESSOR
MEQ-001B-N
VLV-040C-N
1"-C36L
C-8
3962
GMS
A-1
3246 N0-EE10142
WASTE GAS DRYER
AOV-039C-N
1"-DA42R
F.C
VS
4094 VS
A/B EXHAUST.
1"-GMS-01CB
P 150
T 200
R >=37(G)
F.O
PCV-023B-N
2"-IA52DZ
NGS
N0-EE10251
EC9
N2
1"x3/4" VLV-034C-N
3/4"-NGS-01C2
3/4"-X32D VLV-033C-N
3/4"-C36 P 150
T 120
R <37(G)
VLV-044 -N
1"-X32D
SS CS
SST-015B-N
3/4"-GMS-01CBEC6
T
P 150
T 200
R >=37(G)
P
R
2"x1-1/2"
F.O
VLV-002B-N
2"-C56L
PCV-012 -N
150 1"-RA52DB
T 200
R >=37(G)
VLV-013B-N
1"-X42D P
C-WASTE GAS
SURGE TANK
MTK-001C-N
VLV-032C-N
3/4"-T58M
T
T
H
ACR
1"-GMS-01FA
PICA
012 -N
VLV-014B-N
1"-C56L
PIC
014 -N
E-6
3248
2"-GMS-01FA
GMS
N0-EE10143
GA
GMS
D-1
N0-EE10141 3247
A-WASTE GAS COMP.
PT
012 -N
1"-GMS-01FA 3/4"-GMS-01FA
VLV-052B-N
SST-001B-N
3/4"-C56L STR-002B-N
P
0
T 150
R <37(L)
P 150
T 120
R <37(G)
GMS
A-1
3245 N0-EE10142
WASTE GAS DRYER
AOV-039B-N
1"-DA42R
1"-GMS-01CB
P 150
T 200
R >=37(G)
VS
4093 VS
A/B EXHAUST.
T
3/4"-GMS-01C2
EC9
EC9
T
2"-GMS-01FA
VLV-052A-N
SST-001A-N STR-002A-N 3/4"-C56L
DS
P
0
3234 DS
T 150
A/B ED SUMP
R <37(L)
VLV-051A-N
3/4"-X42D
DS
DS 4639
A/B ED SUMP
NGS
D-8
3964 N0-EE10251
N2
VLV-009A-N
3/4"-X42D
EC6
P 100
T 200
R >=37(G)
VLV-005 -N
2"-X42D
NGS
N0-EE10251
EC9
N2
1"x3/4" VLV-034B-N VLV-033B-N 3/4"-NGS-01C2
3/4"-X32D 3/4"-C36
P 150
T 120
R <37(G)
R
P
CS SS
1"-GMS-01FA
1"-GMS-01CB
2"-GMS-01FA VLV-004A-N VLV-003A-N P 100 VLV-003B-N VLV-004B-N 2"-GMS-01FA
1"-X32D
1"-X32D T 200
1"-C56L
1"-C56L
R >=37(G)
L.O
L.O
3/4"-GMS-01CBEC6
VLV-016A-N
3/4"-C56L
P
0
T 150
R <37(L)
P 100
T 200
R >=37(G)
T
1"-GMS-01FA
PT
011 -N
PIC
013 -N
VLV-032B-N
3/4"-T58M
STR-004 -N
T
ACR
VLV-014A-N
1"-C56L
STR-003 -N
3/4"-GMS-01CB
3/8"-GMS-25CA
PCV-020B-N
3/4"-DA42R
F.C
SS CS
PICA
020 -N
3/4"x3/8"
H
PI
020 -N
SST-015A-N
P
1"-GMS-01FA
PICA
011 -N
H
1"-GMS-01FA
3/4"-GMS-01FA
3/4"-GMS-01FA
2"-GMS-01FA
VLV-013A-N
150 1"-X42D
T 200
R >=37(G)
PCV-011 -N
1"-RA52DB P
F.O
GMS
D-1
3232 N0-EE10142
VCT
CVS
D-11
2800 N0-EE10027
B.A. EVAP.
GMS
D-6
3233 N0-EE10143
GA
1"-GMS-01CB
PCV-022B-N
3/4"-DA42R
F.C
P
PT
022 -N
ACR
3/4"-GMS-01CB
SS CS
PICA
022 -N
PI
022 -N
1"-GMS-01FA
3/4"x3/8"
H
1"-GMS-01CB
P
VLV-001B-N
2"-X42D
11.3-12
C-10
2772
VLV-020B-N
1"-X42D
P
P 150
T 200
R >=37(G)
R
T
P
D-WASTE GAS
SURGE TANK
MTK-001D-N
VLV-032D-N
3/4"-T58M
3/4"-GMS-01CB EC6
R
T
GMS
A-4
3221 N0-EE10141
VH
PWS
E-1
N0-EE10201 3753
PMW
2"-GMS-01CB
F.C
VLV-040D-N
1"-C36L
C-8
3953
STD-GMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
GMS
A-2
3243 N0-EE10142
WASTE GAS DRYER
AOV-039D-N
1"-DA42R
1"-GMS-01CB
P 150
T 200
R >=37(G)
VS
4095 VS
A/B EXHAUST.
NGS
N0-EE10251
EC9
1"x3/4" VLV-034D-N
3/4"-NGS-01C2 N2
3/4"-X32D VLV-033D-N
3/4"-C36 P 150
T 120
R <37(G)
P 100
T 200
R >=37(G)
VLV-021B-N
1"-C56
VLV-019B-N EC6 VLV-018B-N EC8
3/4"-C56
3/4"-X42D
P 200
T 150
3/4"-GMS-01FA R
<37(L)
NCS
NCS
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
GMS
H-3
4480 N0-EE10141
HT
CVS
N0-EE10026
HT
Figure 11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 1 of 3)
VLV-046B-N
1"-C36L
EC6
2"x1" VLV-046A-N
1"-C36L
EC8
EC8
VLV-042 -N
2"-C36L
EC6
R
1"-GMS-01CB
F.O
PCV-023A-N
2"-IA52DZ
EC9
1"x3/4" VLV-034A-N VLV-033A-N
3/4"-X32D
3/4"-C36
T 120
3/4"-NGS-01C2 R <37(G)
A-WASTE GAS
SURGE TANK
MTK-001A-N
VLV-032A-N
3/4"-T58M
P
3/4"-GMS-01CB
VLV-020A-N
1"-X42D
P
EC6
VLV-001A-N
2"-X42D
P
2"-GMS-01FA
1"-GMS-01CB
2"x1"
C-9
N0-EE10151
CVDT
P 200
T 150
PWS
E-1
R <37(L) 3/4"-GMS-01FA
3752 N0-EE10201
EC6
PMW
VLV-019A-N
EC8 VLV-018A-N
3/4"-X42D
3/4"-C56
3/8"-GMS-25CA
2"-GMS-01FA
LMS
3222
3/4"-GMS-01F1
F.C
VLV-030A-N
1"-X32D
PCV-019A-N
1"-DA42R
VLV-012A-N
1"-GMS-01FA 1"-X42D
3/4"-GMS-01CB
P 150
T 200
R >=37(G)
VLV-031A-N
1"-C36L
VLV-043A-N
1"-X32D
3/4"-GMS-01CB
2"-GMS-01FA
2"-GMS-01FA
2"x3/4"
P 15
T 200
R >=37(G)
F.C
1"-GMS-01CB
1"-GMS-01CB
P 150
T 200
R >=37(G)
CS SS
1"-GMS-01CB
1"x3/4" VLV-017A-N
1"-X32D
VLV-045A-N
1"-RV32
1"x3/4"
VLV-037A-N
3/4"-GMS-01CB 3/4"-X32D
3/4"-GMS-01FA
3/8"-GMS-25CA
CS SS
SS CS
PCV-020A-N
1"-DA42R
F.C
VLV-030B-N
1"-X32D
1"-GMS-01CB
1"-GMS-01CB
VLV-011A-N
3/4"-X42D
VLV-015A-N
3/4"-T58M
VLV-010A-N
3/4"-T58M
1"x3/4"
F.O
VLV-031B-N
1"-C36L
VLV-043B-N
1"-X32D
VLV-008 -N
3/4"-C36
VLV-007A-N
P 100
2"-X42D
T 200
R >=37(G)
2"-GMS-01FA
3/4"-GMS-01C2
2"-GMS-01FA
VLV-007B-N
2"-X42D
2"x3/4"
P 100
T 200
R >=37(G)
PCV-014 -N
2"-RA52DB
2"-GMS-01FA
PCV-013 -N
2"-RA52DB
VLV-045B-N
1"-RV32
F.C
1"x3/4"
P 150
T 200
R >=37(G)
3/8"-GMS-25CA
VLV-010B-N
3/4"-T58M
SS CS
VLV-011B-N
3/4"-X42D
1"-GMS-01FA
VLV-027B-N VLV-026B-N
1"-X32D
1"-C36L
CS SS
3/4"-GMS-01CB
1"-GMS-01FA
VLV-012B-N
1"-X42D
P 150
T 200
R >=37(G)
2"x1"
AOV-036A-N
3/4"-DA42R
VLV-038A-N
3/4"-C36L
AOV-036B-N
3/4"-DA42R
VLV-038B-N
3/4"-C36L
1"x3/4"
VLV-037B-N
3/4"-GMS-01CB 3/4"-X32D
CS SS
1"-GMS-01CB
2"x1"
GMS
D-11
3221 N0-EE10141
B-WASTE GAS COMP.
3/8"-GMS-25CA
EC8
EC6
VLV-017B-N
1"-X32D
1"x3/4"
P 15
T 200
R >=37(G)
1"-GMS-01CB
P 150
T 200
R >=37(G)
VLV-015B-N
3/4"-T58M
PCV-021A-N
1"-DA42R
F.C
VLV-030C-N
1"-X32D
1"-GMS-01CB
1"-GMS-01CB
1"x3/4"
VLV-031C-N
1"-C36L
VLV-043C-N
1"-X32D
VLV-045C-N
1"-RV32
F.C
VLV-037C-N
3/4"-GMS-01CB 3/4"-X32D
PCV-022A-N
1"-DA42R
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-043D-N
1"-X32D
3/4"-GMS-01FA
AOV-036C-N
3/4"-DA42R
VLV-038C-N
3/4"-C36L
VLV-031D-N
1"-C36L
F.C
VLV-030D-N
1"-X32D
1"-GMS-01CB
1"-GMS-01CB
VLV-045D-N
1"-RV32
F.C
VLV-027A-N VLV-026A-N
1"-X32D
1"-C36L
1"x3/4"
AOV-036D-N
3/4"-DA42R
VLV-038D-N
3/4"-C36L
1"x3/4"
VLV-037D-N
3/4"-X32D
3/4"-GMS-01CB
F.O
Revision 1
STD COL 11.3(9)
VLV-112 -N
3/4"-C56L
R
P
PIC
033 -N
VLV-111 -N
3/4"-T56Z
P
0
T 200
R >=37(G)
1"-GMS-01FA
VCT
NOTE3
CS SS
CS SS
F.C
ACR
PT
026 -N
PIC
032 -N
F.C
ACR
PT
031 -N
PT
032 -N
PCV-039A-N
3/4"-RA52RZ
F.C
PCV-039B-N
3/4"-RA52RZ
F.C
ACR
H
ACR
H
PT
039 -N
P 150
T 200
R >=37(G)
VLV-144 -N
3/4"-X42D
1"x3/4"
RIA
072 -N
P
T
R
H
RE
072 -N
RICA
072 -N
H
T
VLV-146 -N
3/4"-X42D
L.C
3/4"-GMS-01FA
1"x3/4"
R
P
F.C
NOTE1
NGS
N0-EE10251
N2
D-8
3951
AOV-115 -N
3/4"-DA42R
3/4"-GMS-01FA
ACR
H
OXYGEN GAS
ANALYZER
MEQ-003 -N
T
FT
026 -N
FIA
026 -N
DS
DS 3260
A/B ED SUMP
ACR
150
200
<37(G)
3/8"-GMS-25CA
3/4"x3/8" EC6
VLV-164 -N
3/4"-X42D
T
3/4"-GMS-01FA
VS
VS 3269
A/B EXHAUST
VLV-110 -N
3/4"-C56L
CS SS
VLV-109 -N
3/4"-X42D
150
120
<37(G)
ACR
A-1
3255
PIC
039 -N
GMS
N0-EE10143
GA
P
T
R
ACR
ACR
VLV-106 -N 3/4"-GMS-01FA
3/4"-C56L
CS SS
3/4"-NGS-01C2
EC9
HCV-032 -N
3/4"-RA52RZ
F.C
HIC
032 -N
HCV-031 -N
3/4"-RA52RZ
F.C
HIC
031 -N
VLV-105 -N
3/4"-X32D
ACR
CVS
D-11
2804 N0-EE10027
B.A.EVAP
NGS
C-2
3950 N0-EE10251
N2
FT
032 -N
FIA
032 -N
FT
031 -N
FIA
031 -N
HCV-026 -N
3/4"-RA32RB
F.C
HIC
026 -N
GMS
E-6
3258 N0-EE10143
GA
3/4"-GMS-01FA
VLV-140 -N
3/4"-X42D
AOV-116 -N
3/4"-DA42R
F.C
NOTE1
T
NOTE5
PIA
037 -N
TIA
037 -N
B-5
3254
R
P 150
T 200
R >=37(G)
3/4"-GMS-01FA
3/4"-GMS-01FA
GMS
N0-EE10143
GA
3268
NOTE5
P 150
T 200
R >=37(G)
3/4"-GMS-01FA
D-CHARCOAL
BED
MEQ-004D-N
NOTE4
P
VLV-117 -N
3/4"-T56B
C-CHARCOAL
BED
MEQ-004C-N
NOTE4
3/8"-GMS-25CA
3/8"-GMS-25CA
O2
P 150
T 200
R >=37(G)
ACR
ACR
H
H
VLV-134 -N
3/4"-T58M
VLV-161 -N
3/4"-X42D
3/4"x3/8"
XE
035B-N
XE
035A-N
VS
VS 3263
A/B EXHAUST
WASTE GAS
DRYER
MEQ-002 -N
3/4"-GMS-01FA
B-CHARCOAL
BED
MEQ-004B-N
NOTE4
A-CHARCOAL
BED
MEQ-004A-N
3/4"-GMS-01FA
NOTE4
ACR
ACR
H
3/4"-GMS-01FA
PT
037 -N
TE
037 -N
XIA
035B-N
XIA
035A-N
H
F.C
AOV-133 -N
3/4"-DA42R
3/4"x3/8"
3/8"-GMS-25CA
VS
VS 3261
A/B EXHAUST
VS
VS 3262
A/B EXHAUST
NOTE5
P 150
T 200
R >=37(G)
NOTE5
P 150
T 200
R >=37(G)
SST-005 -N
R
R
P
T
R
150
120
<37(G)
VLV-157 -N
3/4"-C56L
STR-006 -N
P
0
T 150
R <37(L)
T
P
T
R
11.3-13
NCS
H
NCS
C-6
3949
STD-GMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET UNLESS SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
NOTES
1,CONNECTION FOR CHARCOAL BEDS PERFORMANCE TEST.
2,DELETED
3,CLOSE WITH VCT PRESSURE LOW.
4,CHARCOAL FILL.
5,OUTLET FOR CHARCOAL REMOVAL.
6,LOCATED NEAR THE VOLUME CONTROL TANK.
F.C
3/4"-NGS-01C2
NGS
N0-EE10251
EC9
N2
AOV-151 -N
3/4"-DA32R
ACR
DS
3271 DS
A/B ED SUMP
VLV-155 -N VLV-154 -N
3/4"-C56 3/4"-X32D
3/4"-GMS-01FA
SS CS
FT
030 -N
3/4"-GMS-01FA
EC6
FIA
030 -N
SS CS
VLV-153 -N VLV-152 -N
3/4"-X32D
EC6 3/4"-C56
Figure 11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 2 of 3)
VLV-148 -N 1"x3/4"
1"-X42D
ACR
3/4"-GMS-01FA
PIC
031 -N
PCV-032 -N
3/4"-RA52RZ
P 150
T 200
R >=37(G)
PIC
026 -N
VLV-104 -N
3/4"-T58M
PCV-026 -N 3/4"-GMS-01CB
3/4"-RA32RB
F.C
PCV-031 -N
3/4"-RA52RZ
P 150
T 200
R >=37(G)
1"-GMS-01FA
PCV-032B-N
3/4"-IA52RZ
F.C
RCV-002A-N
1"-DA32R
F.C
VLV-102 -N
3/4"-X32D
VLV-103 -N
3/4"-C36
PCV-032A-N
3/4"-IA52RZ
F.C
RCV-001C-N
1"-DA32R
F.C
PCV-032C-N
1"-IA52RZ
F.C
RCV-002B-N
1"-DA32R
P
F.C
T
3/4"-X32D
R
3/4"-GMS-01CB VLV-101 -N
P 150
T 200
R >=37(G)
1"-GMS-01FA
NOTE6
SST-004 -N
PCV-033 -N
1"-RA52RZ
F.C
VLV-147 -N
1"-C36L
1"-VS-01C2
T
STR-005 -N
1"-GMS-01CB
VLV-114 -N
1"-X42D
HVAC FAN SWITCH SIGNAL
PLANT STACK MONITOR SIGNAL
VS
VS 3257
A/B EXHAUST.
T
P 150
T 200
R >=37(G)
P
GMS
A-7
N0-EE10141 3249
WASTE GAS COMP.
CVS
A-8
2264 N0-EE10024
VCT
3/4"-GMS-01CB
3/4"-GMS-01CB
P 100
T 200
R >=37(G)
GMS
A-4
N0-EE10141 3232
A-WASTE GAS COMP.
DS
DS 3270
A/B ED SUMP
GMS
G-6
3245 N0-EE10141
B-WASTE GAS SURGE
TANK
GMS
G-3
3242 N0-EE10141
A-WASTE GAS SURGE
TANK
VLV-113 -N
3/4"-T56Z
EC6
3/4"-GMS-01CB
GMS
G-11
3243 N0-EE10141
D-WASTE GAS SURGE
TANK
GMS
G-8
3246 N0-EE10141
C-WASTE GAS SURGE
TANK
F.C
150
120
<37(G)
3/4"x3/8"
P
T
R
3/4"x3/8" 3/4"x3/8"
NGS
C-6
EC5
3948 N0-EE10251
N2
3/4"-NGS-01C2
3/8"-GMS-25CA
AOV-144 -N
3/4"-DA42R
150
120
<37(G) EC9
3/4"-GMS-01FA
VLV-107 -N
3/4"-T56Z
VLV-108 -N
3/4"-T56Z
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-145 -N
3/4"-T58M
VLV-142 -N 3/4"-NGS-01C2
3/4"-X32D
VLV-143 -N
3/4"-C56
P
T
R
SS CS
EC6
3/4"-GMS-01FA
3/4"-GMS-01FA
3/4"x3/8"
150
120
<37(G)
3/4"-GMS-01FA
VLV-162 -N
P
15
3/4"-C56L
T 120
R >=37(G)
VLV-165 -N P 0
3/4"-C56L T 150
R <37(L)
VLV-141 -N
3/4"-X42D
3/8"-GMS-25C1 VLV-163 -N
3/4"-X42D
3/4"x3/8"
VLV-135B-N
3/4"-T56Z
VLV-138B-N
3/4"-T56Z
VLV-137 -N
3/4"-T56Z
P
T
R
0
300
<37(G)
3/4"-GMS-01FA
P
T
R
VLV-139 -N
3/4"-X42D
VLV-136 -N
3/4"-T56Z
3/4"-GMS-01FA
VLV-135A-N
3/4"-T56Z
P 150
T 200
R >=37(G)
3/4"-GMS-01FA
VLV-132 -N VLV-131 -N
3/4"-C56L 3/4"-X42D
VLV-138A-N
3/4"-T56Z
P
T
R
3/4"-GMS-01FA
0
300
<37(G)
P
T
R
P 150
VLV-156 -N T 200
3/4"-X42D R >=37(G)
0
300
<37(G)
P
T
R
150
200
>=37(L)
P 150
T 200
R >=37(G)
3/4"-GMS-01FA
Revision 1
STD COL 11.3(9)
DS
DS 3548
A/B ED SUMP
A-11
N0-EE10012
PRT
DS
DS 3295
A/B ED SUMP
SMS
C-2
3277 N0-EE10161
A-SPENT RESIN
STORAGE TANK
DS
DS 3279
A/B ED SUMP
SMS
C-6
3296 N0-EE10161
B-SPENT RESIN
STORAGE TANK
RCS
1856
DS
DS 3280
A/B ED SUMP
GMS
G-1
3239 N0-EE10141
WASTE GAS SURGE
TANK
SST-008 -N
SST-009 -N
P 150
T 200
R >=37(G)
DS
DS 3283
A/B ED SUMP
GMS
F-4
3255 N0-EE10142
CHARCOAL BED
3/4"x3/8"
P
T
VLV-207 -N
3/4"-X42D
SST-014 -N
3/4"x3/8"
SST-006B-N
3/4"x3/8"
R
R
SST-006A-N
R
T
R
T
T
T
VLV-202B-N
3/8"-PR52
P
VLV-223 -N
3/8"-PR52
P
VLV-211 -N
3/8"-PR52
P
P 150
T 150
R >=37(G)
P 150
T 150
R >=37(G)
P 200
T 400
R >=37(G)
EC4
P 150
T 200
R >=37(G)
F.C
S
P
P
T
T
S
P
T
EC6
S
P
P
T
T
SOV-203A-N 3/8"-GMS-25CA
3/8"-TS52S
F.C
S
SOV-203B-N
3/8"-TS52S
F.C
SOV-224 -N 3/8"-GMS-25CA
3/8"-TS52S
F.C
SOV-212 -N 3/8"-GMS-25CA
3/8"-TS52S
F.C
SOV-209 -N
3/8"-TS52S
EC6
3/8"-GMS-25CA
P
P
T
EC6
T
EC6
EC6
EC6
S
F.C
F.C
T
S
F.C
T
S
F.C
S
F.C
SOV-219B-N
3/8"-TS52S
SOV-219C-N
3/8"-TS52S
T
F.C
SOV-215 -N
3/8"-TS52S
S
SOV-217 -N
3/8"-TS52S
F.C
SOV-219A-N
3/8"-TS52S
P
P
S
SOV-206 -N
3/8"-TS52S
S
SOV-221 -N
3/8"-TS52S
3/8"-GMS-25CA
T
T
EC8
EC8
P
R
P 15
T 200
R >=37(G)
P
P
15
T 200
R >=37(G)
T
T
T
R
P
EC6
P
VLV-214 -N
3/8"-PR52
P 15
T 200
R >=37(G)
EC8
P 15
T 120
R >=37(G)
EC4
P 75
T 200
R >=37(G)
P
VLV-205 -N
3/8"-PR52
P 25
T 200
R >=37(G)
P 150
T 200
R >=37(G)
P 150
T 200
R >=37(G)
EC8
R
T
T
T
T
R
SST-013 -N
SST-007 -N
SST-011 -N
P
R
R
P
R
SST-010 -N
SST-012A-N
SST-012B-N
SST-012C-N
A-8
2267
DS
3287 DS
A/B ED SUMP
CVS
C-7
N0-EE10026 2784
C-HOLDUP TANK
DS
3282 DS
A/B ED SUMP
CVS
C-4
N0-EE10026 2781
B-HOLDUP TANK
DS
3285 DS
A/B ED SUMP
CVS
C-1
N0-EE10026 2779
A-HOLDUP TANK
DS
3284 DS
A/B ED SUMP
CVS
N0-EE10024
VCT
DS
3281 DS
A/B ED SUMP
LMS
B-9
N0-EE10151 3278
CVDT
DS
3294 DS
A/B ED SUMP
GMS
C-7
N0-EE10142 3254
WASTE GAS DRYER
DS
3286 DS
A/B ED SUMP
CVS
E-11
N0-EE10027 2805
B.A.EVAP.
O2
P 150
T 200
R >=37(G)
P
15
120
<37(G)
T
P
R
T
15
120
>=37(L)
T
NOTE1
3/4"x3/8"
EC6
T
P
T
R
15
120
>=37(L)
P
T
A-WASTE GAS
ANALYZER
MEQ-005A-N
P
T
R
B-WASTE GAS
ANALYZER
MEQ-005B-N
150
120
<37(G)
EC9
P
T
R
EC9
P 15
T 120
R >=37(G)
3/8"-GMS-25CA
3/8"-GMS-25CA
NGS
A-2
3947 N0-EE10251
N2
VLV-242B-N
3/4"-X42D
P
P
WASTE GAS
SAMPLE
VESSEL
P
3/4"x3/8"
VLV-232 -N
3/4"-X42D
P 100
T 200
R >=37(G)
EC6
VLV-241B-N 3/8"-GMS-25CA
3/4"-X42D
3/4"x3/8"
P
T
R
3/8"-GMS-25CA
NGS
A-2
3968 N0-EE10251
N2
VLV-242A-N
3/4"-X42D
3/4"-GMS-01FA
EC6
R
3/4"x3/8" EC6
VLV-241A-N3/8"-GMS-25CA
3/4"-X42D
3/4"x3/8"
NOTES
1,ENABLE TO USE THE SAMPLING PIPE.
P
T
R
AOV-237 -N
3/4"-DA42R
DS
DS 3293
A/B ED SUMP
3292
VLV-238 -N
3/4"-C56L
3/4"-GMS-01FA
F.C
GMS
A-5
N0-EE10142 3258
WASTE GAS DRYER
GMS
A-7
3/4"-GMS-01FA
N0-EE10141 3248
B-WASTE GAS COMP. VLV-236B-N VLV-235B-N
3/4"-C56L 3/4"-X42D
F.C
15
120
<37(G)
AOV-234 -N
3/4"-DA42R
3/8"-GMS-25CA
P
T
R
GMS
A-4
3/4"-GMS-01FA
N0-EE10141 3233
A-WASTE GAS COMP. VLV-236A-N VLV-235A-N
3/4"-C56L 3/4"-X42D
P
15
T 120
R >=37(G)
O2
DS
DS 3547
A/B ED SUMP
3542
EC6
EC6
150
120
<37(G)
P
T
R
150
120
<37(G)
P
T
R
150
120
<37(G)
EC9
EC9
EC6
11.3-14
3/4"x3/8"
P
T
R
REMARK:
B-9
3961
H2
3544
H2
3290
VS
3291 VS
A/B EXHAUST
15
120
<37(G)
15
120
<37(G)
P
T
R
VS
3543 VS
A/B EXHAUST
STD-GMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
HGS
N0-EE10251
H2
3/8"-GMS-25CA VLV-243B-N
3/4"-X42D
P
T
R
15
120
<37(G)
A-9
3956
3/4"x3/8"
P
T
R
HGS
N0-EE10251
H2
EC6 3/4"x3/8"
15
120
<37(G)
3/4"x3/8"
3/8"-GMS-25CA VLV-243A-N
3/4"-X42D
Figure 11.3-201 Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 3 of 3)
VLV-202A-N
3/8"-PR52
P
R
VLV-208 -N
3/8"-PR52
3/8"-GMS-25CA
3/8"-GMS-25CA
VLV-204 -N
3/4"-X42D
VLV-216 -N
3/4"-X42D
VLV-210 -N
3/4"-X42D
VLV-222 -N
3/4"-X42D
VLV-201B-N
3/4"-X42D
VLV-201A-N
3/4"-X42D
3/4"x3/8"
3/4"x3/8"
S
3/8"-GMS-25CA
3/4"x3/8"
3/4"x3/8"
VLV-220 -N
3/4"-X42D
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
3/4"x3/8"
3/4"x3/8"
3/4"x3/8"
VLV-233 -N
3/4"-X42D
3/8"-GMS-25CA
3/8"-GMS-25CA
3/8"-GMS-25CA
3/8"-GMS-25CA
3/4"x3/8" 3/4"x3/8"
VLV-213 -N
3/4"-X42D
VLV-218A-N
3/4"-X42D
VLV-218B-N
3/4"-X42D
VLV-218C-N
3/4"-X42D
VLV-231 -N
3/4"-X42D
EC6
CS SS
3/4"x3/8"
CS SS
3/4"x3/8"
EC6
3/4"x3/8"
3/4"x3/8"
3/4"x3/8"
3/8"-GMS-25CA
VLV-240A-N
3/4"-X42D
3/8"-GMS-25CA
VLV-240B-N
3/4"-X42D
EC6
CS SS
3/4"x3/8"
EC6
CS SS
3/4"x3/8"
3/8"-GMS-25CA
VLV-239A-N
3/4"-X42D
3/8"-GMS-25CA
VLV-239B-N
3/4"-X42D
Revision 1
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
CP 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
CP COL 11.4(5)
CP 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 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.4.2.1.1
CP 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 least 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(1)
Packaging, Storage, and Shipping
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.
11.4-2
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Specially shielded above grade cell vaults capable of storing a number of
containers each are provided in the Remote Handled waste storage bay for
very-high activity Class B, C waste. Facility shielding is designed to meet 10CFR
20 and 40 CFR 190 dose levels and minimize total facility construction costs.
The facility is designed to have separate control and equipment room ventilation,
radiation monitoring, and fire protection systems designed to meet minimum
essential requirements, and reduced capital cost.
The facility have remotely operated bridge crane with closed circuit television
cameras and crane mounted storage bay lighting sources. Optimal crane designs
are used to minimize total facility construction cost.
The radioactive mixed waste storage area is designed and constructed in
accordance with permit application for its operation received from the State of
Texas Commission on Environmental Quality.
Primary regulations and NRC/Industry guidance covering the design and
operation of interim radioactive waste storage facilities are 10 CFR 20, 10 CFR
61, 10 CFR 71, 40 CFR 190, 49 CFR 173, NUREG-0800 SRP Appendix 11.4-A,
Generic Letter 81-38, Information Notice No. 89-27 and SECY-94-0198.
This interim storage facility is provided with the knowledge that as of July 1, 2008,
the low level radioactive waste disposal facility in Barnwell, South Carolina, is no
longer accepting Class B and C wastes from sources in states such as Texas that
are outside of the Atlantic Compact, and that the disposal facility in Clive, Utah, is
still accepting Class A waste from out of state. Class B and C waste constitutes a
small fraction of the total low level radioactive waste that will be generated by
CPNPP.
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
11.4-3
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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
CP COL 11.4(3)
Process Control Program
Replace the content of DCD Subsection 11.4.3.2 with the following.
This subsection adopts NEI 07-10A. 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
CP COL 11.4(4)
CP COL 11.4(7)
Mobile De-watering System
Replace the last sentence in DCD Subsection 11.4.4.5 with the following.
The mobile de-watering station is vendor supplied and operated within the specific
requirements and layout based on vendor specifications. The mobile system
includes the necessary connections and fittings to the 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 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
mobile de-watering station to prevent the contamination of non-radioactive piping
or uncontrolled releases of radioactivity into the environment.
11.4-4
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.4.8
Combined License Information
Replace the content of DCD Subsection 11.4.8 with the following.
CP 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
CP 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.
CP COL 11.4(4)
11.4(4) Mobile/portable SWMS connections
This COL item is addressed in Subsection 11.4.4.5.
CP 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.
CP COL 11.4(7)
11.4(7) Site-specific solid waste processing facility
This COL item is addressed in Subsections 11.4.1.6 and 11.4.4.5.
STD COL 11.4(8)
11.4(8) Piping and instrumentation diagrams
This COL item is addressed in Subsection 11.4.2.2.1 and Figure 11.4-201.
11.4-5
Revision 1
STD COL 11.4(8)
A-7
3982
NGS
B-2
3967 N0-EE10251
N2
DS
DS 3983
A/B ED SUMP
GMS
N0-EE10141
VH
VLV-048 -N
2"-X42D
EC9
T
1"-SMS-01FA
P
DS
DS 1982
A/B ED SUMP
EC6
VLV-031 -N
1"-C56
CS SS
3/8"-SMS-25CA
E-1
3277
GMS
N0-EE10143
GA
VLV-025 -N
3/4"-T58M
2"-SMS-01FA
ACR
VLV-024 -N
3/4"-T58M
LCV-022B-N
2"-DA42R
LCA
022 -N
LT
022 -N
2"-SMS-01FA
LCV-022A-N
2"-DA42R
T
P
P
T
P
P
3/4"-SMS-01FA
T
2"-SMS-01FA
2"-SMS-01FA
A-SPENT RESIN
STORAGE TANK
MTK-001A-N
VLV-017A-N
3/4"-X42D
R
F.C
AOV-023A-N
2"-X42D
VLV-035A-N
3/4"-X42D
3/4"x3/8"
NOTE5
AOV-032A-N
1"-DA42R
2"x1"
AOV-033A-N
1"-DA42R
2"-SMS-01FA
L.C
2"x1"VLV-044 -N
2"-X42D
3/4"-SMS-01FA
VLV-037A-N
3/4"-X42D
F.C
1"-SMS-01FA
F.C
2"-SMS-01FA
T
P
PT
015 -N
QE
017 -N
NOTE6
R
P
2"-SMS-01FA
2"-SMS-01FA
P
ACR
H
VLV-003A-N
3/4"-T58M
VLV-002A-N
3/4"-T58M
P
P
VLV-001A-N
2"-X42D
VLV-005A-N
2"-X42D
PIA
015 -N
P 200
T 150
R >=37(L)
P 200
T 150
R >=37(L)
LT
015 -N
VLV-047 -N
2"-X42D
LICA
015 -N
NOTE1
ACR
L
H
GMS
N0-EE10143
GA
D-1
3296
P
P
T
VLV-017B-N
3/4"-X42D
R
F.C
P
P
3/4"-SMS-01FA
R
VLV-046 -N
2"-X42D
3/4"-SMS-01FA
VLV-035B-N
3/4"-X42D
3/4"x3/8"
AOV-023B-N
2"-DA42R
P
T
B-SPENT RESIN
STORAGE TANK
MTK-001B-N
3/8"-SMS-25CA
T
SFS
F-1
N0-EE10112 1986
A-SFP DEMI.
SFS
F-5
N0-EE10112 1985
B-SFP DEMI.
CVS
D-3
N0-EE10027 2801
B.A.EVAP. FEED DEMI.
T
2"x1"
2"-SMS-01FA
P
P
P 150
T 150
R >=37(L)
VLV-021B-N
2"-RV42NB
PT
016 -N
CVS
G-2
N0-EE10023 2222
B-MIXED BED DEMI.
CVS
G-2
N0-EE10023 2210
A-MIXED BED DEMI.
CVS
G-6
N0-EE10023 2232
CATION BED DEMI.
CVS
F-11
N0-EE10023 2227
B-DEBORATING DEMI.
R
P
P
P
ACR
H
VLV-001B-N
2"-X42D
VLV-003B-N
3/4"-T58M
VLV-002B-N
3/4"-T58M
VLV-005B-N
2"-X42D
2"-SMS-01FA
2"-SMS-01FA
PIA
016 -N
P
P 200
T 150
R >=37(L)
P 200
T 150
R >=37(L)
NOTE4
NOTE1
HIC
013 -N
ACR
ACR
L
H
NOTE2
LICA
016 -N
HCV-013 -N
2"-RA52R
F.C
LT
016 -N
2"-DA42R
F.C
LMS
F-6
N0-EE10155 3652
C-WASTE EFFLUENT
DEMI.
LMS
F-9
N0-EE10155 3656
D-WASTE EFFLUENT
DEMI.
LMS
F-2
N0-EE10155 3659
ACTIVATED CARBON
FILTER
LMS
C-6
N0-EE10155 3407
A-WASTE EFFLUENT
DEMI.
LMS
C-9
N0-EE10155 3408
B-WASTE EFFLUENT
DEMI.
P 200
T 150
R <37(L)
11.4-6
EC8
LT
LCA
FE
013 -N
FT
013 -N
FI
013 -N
ACR
OPTIONAL VENDOR EQUIPMENT
TE
TIA
VLV-041 -N
2"-T56
LMS
A-7
3999 N0-EE10154
WHT
VS
3985 VS
A/B EXHAUST
CVS
F-5
N0-EE10023 2237
PMW SUPPLY.
VLV-011 -N
2"-X42D
2"-SMS-01F1
PWS
D-1
N0-EE10201 1981
PMW
STD-SMS-###-+++
PLANT DESIGNATION, SYSTEM NAME
OF EQUIPMENT AND VALVE NUMBERS
ARE OMITTED IN THIS DRAWING.
REMARK:
NOTES
1,FLUSHING STOP VALVE TRIP CLOSED ON HI SIGNAL.
2,FILL HEAD.
3,HIGH INTEGRITY CONTAINER.
4,SAMPLE CONNECTION.
5,BREAKPOT.
6,TURBIDITY METER ELEMENT
7,DEWATERING SKID, FILL HEAD, AND CONTROL PANEL
WILL BE SUPPLIED BY APPLICANT.
8,SPENT RESINS FROM SGS WILL ONRY BE SENT TO THE SWMS
IF RADIOACTIVE CONTAMINATION IS DETECTED.
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
NOTE3
NOTE7
DEWATERING
PUMP
IAS
SA
P 200
VLV-042 -N T
150
2"-C56
R <37(L)
R
2"-SMS-01FA
EC6
Figure 11.4-201 Solid Waste Management System Piping and Instrumentation Diagram
R
2"-SMS-01FA
2"x1"
P
P 150
T
150
R >=37(L)
VLV-021A-N
2"-RV42NB
QI
017 -N
P 200
T 150
R >=37(L)
3/4"-SMS-01FA
P 200
T 150
R >=37(L)
L.C
NOTE8
VLV-016A-N
3/4"-X42D
NOTE8
VLV-018A-N
1"-X42D
NOTE8
AOV-033B-N
1"-DA42R
SGS
B-6
N0-EE10182 3484
A-SGBD CATION BED
DEMI.
SGS
F-6
N0-EE10182 3490
A-SGBD MIX BED DEMI.
AOV-032B-N
1"-DA42R
SGS
F-9
N0-EE10182 3501
B-SGBD MIX BED DEMI.
2"x1"
VLV-036A-N
1"-X42D
F.C
1"-SMS-01FA
F.C
L.C
NOTE8
L.C
SGS
B-9
N0-EE10182 3495
B-SGBD CATION BED
DEMI.
VLV-018B-N
1"-X42D
VLV-022A-N
3/4"-T58M
EC6
2"-SMS-01F1
VLV-015A-N
2"-X42D
P 200
T 150
R >=37(L)
VLV-014A-N
2"-C56
EC8
2"x1"
VLV-036B-N
1"-X42D
VLV-037B-N
3/4"-X42D
CVS
F-9
N0-EE10023 2225
A-DEBORATING DEMI.
VLV-016B-N
3/4"-X42D
VLV-022B-N
3/4"-T58M
EC6
2"-SMS-01F1
VLV-015B-N
2"-X42D
P 200
T 150
R >=37(L)
VLV-014B-N
2"-C56
EC8
VLV-045 -N
2"-X42D
3/4"-SMS-01FA
VLV-006 -N
2"-X42D
VLV-061 -N
2"-X42D
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
VLV-013 -N
3/4"-T58M
3/4"-T58M
VLV-012 -N
3/4"-T58M
Revision 1
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)
Add the following text to the end of the last paragraph in DCD Section 11.5.
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 Figures 11.5-2 can be used except for the structure of ESW pipe
tunnel remains valid. The structure of ESW pipe tunnel is shown on Figure 1.2-2R.
11.5.2.6
CP COL 11.5(4)
CP COL 11.5(5)
Reliability and Quality Assurance
Replace the first sentence in 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.
11.5.2.7
CP 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
11.5-1
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.5(4)
CP 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 sentence in the first paragraph and the second paragraph in
DCD Subection 11.5.2.9 with the following.
CP COL 11.5(1)
CP 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 four CPNPP
units and to conform with the NEI template before receipt of radioactive material in
Unit 3 in accordance with FSAR Table 13.4-201.
11.5.2.10
CP COL 11.5(3)
Radiological Environmental Monitoring Program
Replace the content of DCD Subsection 11.5.2.10 with the following.
The program for CPNPP Units 3 and 4 is going to be described in the plant
Technical Specification of CPNPP Units 3 and 4 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 for CPNPP Units 3 and 4 follows the guidance
of NEI 07-09A.
11.5.2.11
Site-Specific Cost-Benefit Analysis
11.5-2
Revision 1
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.5(6)
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)
11.5(1) Site-specific aspects
This COL item is addressed in Subsection 11.5.2.9.
CP 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.
CP 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)
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)
11.5(5) Analytical procedures
This COL item is addressed in Subsections 11.5.2.6 and 11.5.2.8.
CP COL 11.5(6)
11.5(6) The site-specific cost benefit analysis
This COL item is addressed in Subsection 11.5.2.11.
11.5-3
Revision 1