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
11.2.4
11.2.5
11.3
GASEOUS WASTE MANAGEMENT SYSTEM.................................11.3-1
11.3.1.5
11.3.2
11.3.3.1
11.3.3.3
11.3.7
11.3.8
11.4
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 ...............................................................................11.2-2
Radioactive Effluent Releases Due to Liquid Containing Tank
Failures ..................................................................................11.2-4
Combined License Information ..............................................11.2-4
References.............................................................................11.2-4
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
Offsite Dose Calculation Manual............................................11.3-2
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
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.......................................................11.4-3
Mobile De-watering System ...................................................11.4-4
Combined License Information ..............................................11.4-4
11-i
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2 - FSAR
CHAPTER 11
RADIOACTIVE WASTE MANAGEMENT SYSTEM
TABLE OF CONTENTS
Section
11.5
Title
Page
PROCESS EFFLUENT RADIATION MONITORING AND SAMPLING
SYSTEMS..........................................................................................11.5-1
11.5.2.6
11.5.2.7
11.5.2.8
11.5.2.9
11.5.2.10
11.5.2.11
11.5.5
11.5.6
Reliability and Quality Assurance ..........................................11.5-1
Determination of Instrumentation Alarm Setpoints for
Effluents .................................................................................11.5-1
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
References.............................................................................11.5-3
11-ii
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2 - FSAR
LIST OF TABLES
Number
11.2-10R
11.2-11R
11.2-12R
11.2-13R
11.2-14R
11.2-15R
11.3-8R
11.3-9R
11.3-201
11.3-202
11.3-203
11.3-204
11.3-205
Title
Liquid Releases Calculated by PWR GALE Code
Liquid Releases with Maximum Defined Fuel Defects
Comparison of Annual Average Liquid Release Concentrations
with10 CFR 20 (Expected Releases)
Comparison of Annual Average Liquid Release Concentrations
with10 CFR 20 (Maximum Releases)
Input Parameters for the LADTAP II Code
Individual Doses from Liquid Effluents
Input Parameters for the GASPAR II Code
Calculated Doses from Gaseous Effluents
Population Distribution within 50 mi for Population Dose Calculation
Release Rates from the Evaporation Pond to Atmosphere
Input Parameters for Dose Calculation from Evaporation Pond
Calculated Doses from Evaporation Pond
Total Doses Due to Gaseous Effluent from Vent Stack and
Evaporation Pond
11-iii
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2 - FSAR
LIST OF FIGURES
Number
11.2-201
11.3-201
11.4-201
Title
Liquid Waste Management System Piping and Instrumentation
Diagram
Gaseous Waste Management System Piping and Instrumentation
Diagram
Solid Waste Management System Piping and Instrumentation
Diagram
11-iv
Revision 0
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 0
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 0
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
Mobile or Temporary Equipment
CP COL 11.2(1) Add the following text at the end of the paragraph in DCD Subsection 11.2.1.6.
Process piping connections are designed to have connectors different from the
utility connectors to prevent cross-connection and contamination.
11.2.2
System Description
CP COL 11.2(2) Replace third paragraph in DCD Subsection 11.2.2 with the following.
CP COL 11.2(6)
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).
11.2-1
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Figure 11.2-201, Sheets 1 through 9 illustrate the piping and process equipment,
instrumentation and controls for Comanche Peak Nuclear Power Plant (CPNPP)
Units 3 and 4 LWMS.
The treated liquid effluent is discharged to Squaw Creek Reservoir via CPNPP
Units 1 and 2 circulating water return line with provision to divert a portion of the
flow to an evaporation pond. The shape of the flow orifices and other technical
details will be developed in the detail design phase. Subsection 11.2.3.1
discusses the design of the evaporation pond and return line connections.
11.2.3.1
CP COL 11.2(4)
Radioactive Effluent Releases and Dose Calculation in
Normal Operation
Replace the second and third sentences of the second paragraph in DCD
Subsection 11.2.3.1 with the following.
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.
CP COL 11.2(2) Replace the last four paragraphs in DCD Subsection 11.2.3.1 with the following.
CP COL 11.2(4)
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, the tritium concentration in Squaw
Creek Reservoir is anticipated to be 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. A
portion of the liquid effluent from CPNPP Units 3 and 4 discharge header can be
diverted to an evaporation pond located within the site boundary. Under this
maximum tritium generation condition, and maintaining a 20 percent margin
below the offsite dose calculation manual (ODCM) limit, up to half of liquid
effluent is diverted into the evaporation pond. In the event that both CPNPP Units
11.2-2
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1 and 2 are temporarily not in operation, or when there is no dilution flow, the
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 liquid effluent on a temporary basis. It is
noted that before CPNPP Units 1 and 2 retire, an evaluation is needed to
address the requirement of the circulating water as dilution water to CPNPP
Units 3 and 4 effluents.
CPNPP Units 3 and 4 discharge header and the evaporation pond discharge
lines are connected to the circulating water return line for CPNPP Units 1 and 2
in two locations before the circulating water is discharged into Squaw Creek
Reservoir. The locations of the connections provide sufficient distance for
thorough mixing before the liquid is released into Squaw Creek Reservoir. The
exact locations of the connections into the circulating water discharge header is
determined in the detail design phase with consideration of the impact of sharing
structure, system, and components (SSCs) among the nuclear units.
The evaporation pond is designed to provide sufficient surface area for natural
evaporation based on the local area rainfall and evaporation rate and half of
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. A discharge line connects into CPNPP Units 1 and 2 circulating
water return line to keep the pond from overflowing during periods of extreme
weather conditions. Doses from airborne particulates from the evaporation pond
are described in Subsection 11.3.3.
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 Table 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. 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.
11.2-3
Revision 0
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 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.
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.
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 11.215R.
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.
11.2-4
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
11.2-5
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-10R (Sheet 1 of 2)
Liquid Releases Calculated by PWR GALE Code (Ci/yr)
Isotope
Shim
Bleed
Na-24
P-32
Cr-51
Mn-54
Fe-55
Fe-59
Co-58
Co-60
Ni-63
Zn-65
W-187
Np-239
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
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
0.00005
0.00003
0.00000
0.00003
0.00001
0.00000
0.00001
0.00012
0.00000
0.00013
0.00001
0.00000
0.00002
0.00000
0.00000
0.00000
0.00001
0.00000
0.00001
0.00002
0.00000
0.00002
0.00003
0.00000
0.00004
Fission Products
0.00187
0.00000
0.00187
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
0.00002
0.00000
0.00002
0.00001
0.00000
0.00001
0.00001
0.00000
0.00001
0.00011
0.00000
0.00011
0.00011
0.00000
0.00011
0.00020
0.00000
0.00021
0.00020
0.00000
0.00021
0.00243
0.00005
0.00257
0.00243
0.00005
0.00257
0.00003
0.00000
0.00004
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00001
0.00002
0.00000
0.00002
0.00002
0.00000
0.00002
0.00000
0.00000
0.00001
0.00001
0.00000
0.00002
0.00003
0.00000
0.00003
0.00001
0.00001
0.00002
0.00002
0.00003
0.00005
0.00001
0.00000
0.00001
0.00005
0.00000
0.00007
0.00002
0.00003
0.00005
0.00112
0.00000
0.00141
0.00008
0.00000
0.00011
Detergent
Waste(3)
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
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
Rb-88
0.00000
N/A
2.80E-02
Sr-89
0.00000
N/A
6.00E-05
Sr-90
0.00000
N/A
8.00E-06
Sr-91
0.00000
N/A
6.80E-05
Y-91m
0.00000
N/A
4.40E-05
Y-91
0.00000
N/A
1.00E-05
Y-93
0.00000
N/A
2.90E-04
Zr-95
0.00000
N/A
2.00E-04
Nb-95
0.00000
N/A
1.00E-04
Mo-99
0.00000
N/A
1.64E-03
Tc-99m
0.00000
N/A
1.70E-03
Ru-103
0.00001
N/A
3.11E-03
Rh-103m
0.00001
N/A
3.10E-03
Ru-106
0.00010
N/A
3.81E-02
Rh-106
0.00010
N/A
3.90E-05
Ag-110m
0.00000
N/A
6.00E-04
Ag-110
0.00000
N/A
7.20E-05
Sb-124
0.00000
N/A
0.00E+00
Te-129m
0.00000
N/A
7.80E-05
Te-129
0.00000
N/A
3.10E-04
Te-131m
0.00000
N/A
2.50E-04
Te-131
0.00000
N/A
7.60E-05
I-131
0.00002
N/A
4.00E-04
Te-132
0.00000
N/A
4.70E-04
I-132
0.00000
N/A
3.10E-04
I-133
0.00001
N/A
8.10E-04
I-134
0.00000
N/A
8.90E-05
Cs-134
0.00002
N/A
1.00E-03
I-135
0.00000
N/A
7.80E-04
Cs-136
0.00030
N/A
2.16E-02
Cs-137
0.00003
N/A
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.
11.2-6
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-10R (Sheet 2 of 2)
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
Turbine
Building
Combined
Releases
Fission Products
0.00000
0.00003
0.00001
0.00033
0.00001
0.00053
0.00000
0.00000
0.00000
0.00003
0.00000
0.00001
0.00000
0.00011
0.00000
0.00011
0.00000
0.00000
Detergent
(3)
Waste
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
TOTAL
Releases
(1)
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
TOTAL
(except
0.00065
0.01053
0.00025
0.01143
1.70E-01
N/A
H-3)
H-3 release
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.
11.2-7
Revision 0
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
Na-24
P-32
Cr-51
Mn-54
Fe-55
Fe-59
Co-58
Co-60
Ni-63
Zn-65
W-187
Np-239
Shim
Bleed
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)
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
TOTAL
Releases
(1)
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.
11.2-8
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-11R (Sheet 2 of 2)
Liquid Releases with Maximum Defined Fuel Defects (Ci/yr)
Isotope
Ba-137m
Ba-140
La-140
Ce-141
Ce-143
Pr-143
Ce-144
Pr-144
TOTAL
(except
H-3)
H-3 release
Shim
Bleed
Misc.
Wastes
0.20917
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00010
0.00002
0.00000
0.00000
0.00000
0.00001
0.00001
1.50367
3.51883
Turbine
Building
Combined
Releases
Fission Products
0.00000
0.20917
0.00000
0.00010
0.00000
0.00002
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00000
0.00001
0.00000
0.00001
0.00633
5.02883
Detergent
Waste(3)
TOTAL
Releases
(1)
N/A
N/A
N/A
N/A
N/A
N/A
N/A
N/A
2.16E-01
1.03E-04
2.06E-05
0.00E+00
0.00E+00
0.00E+00
1.03E-05
1.03E-05
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.
11.2-9
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-12R (Sheet 1 of 2)
Comparison of Annual Average Liquid Release Concentrations with
10 CFR 20 (Expected Releases)
Isotope (1)
Discharge
Concentration
(2)
(μCi/ml)
Effluent
Concentration Limit
(3)
(μCi/ml)
Fraction of
Concentration Limit
Na-24
1.19E-11
5.00E-05
2.39E-07
P-32
0.00E+00
9.00E-06
0.00E+00
Cr-51
3.30E-12
5.00E-04
6.60E-09
Mn-54
1.78E-12
3.00E-05
5.92E-08
Fe-55
1.27E-12
1.00E-04
1.27E-08
Fe-59
2.54E-13
1.00E-05
2.54E-08
Co-58
4.82E-12
2.00E-05
2.41E-07
Co-60
0.00E+00
3.00E-06
0.00E+00
Ni-63
0.00E+00
1.00E-04
0.00E+00
Zn-65
5.58E-13
5.00E-06
1.12E-07
W-187
8.88E-13
3.00E-05
2.96E-08
Np-239
1.35E-12
2.00E-05
6.73E-08
Rb-88
7.11E-11
4.00E-04
1.78E-07
Sr-89
1.52E-13
8.00E-06
1.90E-08
Sr-90
2.03E-14
5.00E-07
4.06E-08
Sr-91
1.73E-13
2.00E-05
8.63E-09
Y-91m
1.12E-13
2.00E-03
5.58E-11
Y-91
2.54E-14
8.00E-06
3.17E-09
Y-93
7.36E-13
2.00E-05
3.68E-08
Zr-95
5.08E-13
2.00E-05
2.54E-08
Nb-95
2.54E-13
3.00E-05
8.46E-09
Mo-99
4.16E-12
2.00E-05
2.08E-07
Tc-99m
4.32E-12
1.00E-03
4.32E-09
Ru-103
7.89E-12
3.00E-05
2.63E-07
Rh-103m
7.87E-12
6.00E-03
1.31E-09
Ru-106
9.67E-11
3.00E-06
3.22E-05
Ag-110m
1.52E-12
6.00E-06
2.54E-07
Sb-124
0.00E+00
7.00E-06
0.00E+00
Te-129m
1.98E-13
7.00E-06
2.83E-08
Te-129
7.87E-13
4.00E-04
1.97E-09
Te-131m
6.35E-13
8.00E-06
7.93E-08
Te-131
1.93E-13
8.00E-05
2.41E-09
I-131
1.02E-12
1.00E-06
1.02E-06
Te-132
1.19E-12
9.00E-06
1.33E-07
I-132
7.87E-13
1.00E-04
7.87E-09
I-133
2.06E-12
7.00E-06
2.94E-07
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
11.2-10
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.2-12R (Sheet 2 of 2)
Comparison of Annual Average Liquid Release Concentrations with
10 CFR 20 (Expected Releases)
CP COL 11.2(4)
Isotope (1)
Discharge
Concentration
(2)
(μCi/ml)
Effluent
Concentration Limit
(μCi/ml) (3)
Fraction of
Concentration Limit
I-134
Cs-134
I-135
Cs-136
Cs-137
Ba-140
La-140
Ce-141
Ce-143
Pr-143
Ce-144
Pr-144
H-3
2.26E-13
2.54E-12
1.98E-12
5.49E-11
5.08E-12
1.24E-11
2.03E-11
1.52E-13
1.27E-12
2.01E-13
4.32E-12
4.32E-12
4.06E-06
4.00E-04
9.00E-07
3.00E-05
6.00E-06
1.00E-06
8.00E-06
9.00E-06
3.00E-05
2.00E-05
2.00E-05
3.00E-06
6.00E-04
1.00E-03
5.65E-10
2.82E-06
6.60E-08
9.15E-06
5.08E-06
1.55E-06
2.26E-06
5.08E-09
6.35E-08
1.00E-08
1.44E-06
7.19E-09
4.06E-03
TOTAL
Notes:
1.
2.
3.
4.12E-03
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.
Annual average discharge concentration based on release of average daily discharge for
292 days per year with 247,500 gpm dilution flow.
10 CFR 20 Appendix B, Table 2
11.2-11
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-13R (Sheet 1 of 2)
Comparison of Annual Average Liquid Release Concentrations with
10 CFR 20 (Maximum Releases)
Isotope (1)
Discharge
Concentration
(2)
(μCi/ml)
Effluent
Concentration Limit
(3)
(μCi/ml)
Fraction of
Concentration Limit
Na-24
8.12E-13
5.00E-05
1.62E-08
P-32
0.00E+00
9.00E-06
0.00E+00
Cr-51
2.10E-13
5.00E-04
4.19E-10
Mn-54
1.05E-13
3.00E-05
3.49E-09
Fe-55
7.86E-14
1.00E-04
7.86E-10
Fe-59
2.62E-14
1.00E-05
2.62E-09
Co-58
3.14E-13
2.00E-05
1.57E-08
Co-60
2.62E-14
3.00E-06
8.73E-09
Ni-63
0.00E+00
1.00E-04
0.00E+00
Zn-65
2.62E-14
5.00E-06
5.24E-09
W-187
5.24E-14
3.00E-05
1.75E-09
Np-239
7.86E-14
2.00E-05
3.93E-09
Rb-88
1.01E-10
4.00E-04
2.52E-07
Sr-89
0.00E+00
8.00E-06
0.00E+00
Sr-90
0.00E+00
5.00E-07
0.00E+00
Sr-91
0.00E+00
2.00E-05
0.00E+00
Y-91m
0.00E+00
2.00E-03
0.00E+00
Y-91
0.00E+00
8.00E-06
0.00E+00
Y-93
0.00E+00
2.00E-05
0.00E+00
Zr-95
2.62E-14
2.00E-05
1.31E-09
Nb-95
5.24E-14
3.00E-05
1.75E-09
Mo-99
3.49E-11
2.00E-05
1.75E-06
Tc-99m
1.38E-11
1.00E-03
1.38E-08
Ru-103
2.62E-14
3.00E-05
8.73E-10
Rh-103m
2.62E-14
6.00E-03
4.37E-12
Ru-106
2.62E-14
3.00E-06
8.73E-09
Ag-110m
0.00E+00
6.00E-06
0.00E+00
Sb-124
0.00E+00
7.00E-06
0.00E+00
Te-129m
0.00E+00
7.00E-06
0.00E+00
Te-129
0.00E+00
4.00E-04
0.00E+00
Te-131m
8.64E-13
8.00E-06
1.08E-07
Te-131
0.00E+00
8.00E-05
0.00E+00
I-131
4.43E-12
1.00E-06
4.43E-06
Te-132
1.38E-11
9.00E-06
1.53E-06
I-132
7.86E-13
1.00E-04
7.86E-09
I-133
2.57E-11
7.00E-06
3.67E-06
I-134
1.31E-13
4.00E-04
3.27E-10
Cs-134
6.73E-09
9.00E-07
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
11.2-12
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-13R (Sheet 2 of 2)
Comparison of Annual Average Liquid Release Concentrations with
10 CFR 20 (Maximum Releases)
Isotope (1)
Discharge
Concentration
(2)
(μCi/ml)
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
11.2-13
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-14R (Sheet 1 of 2)
Input Parameters for the LADTAP II Code
Parameter
Value
Midpoint of Plant Life(yr)
Circulating Water System discharge rate (gpm)
Water type selection
Reconcentration model index
Discharge rate to receiving water(ft3/sec)
Total impoundment volume(ft3)
Shore-width factor
Dilution factor -Squaw Creek(3)
Dilution factor - Brazos River(4)
Dilution factor - Whitney Reservoir(5)
Transit time – Squaw Creek
Transit time – Brazos River
Transit time – Whitney Reservoir
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)
30
247,500
Freshwater
1 (Complete mix)
(1)
1.5
(2)
45.4
6.3E+09
0.2 (Squaw Creek)
0.3(Whitney Reservoir)
1.0
(1)
822.7
27.2(2)
(1)
1645.4
(2)
54.4
7.3
66
77
74.6
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
Annual local harvest for sports harvest
324,375
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
None
invertebrate 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)
11.2-14
Revision 0
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
Total shoreline usage time(person-hr/yr)
Total swimming usage time(person-hr/yr)
Total boating usage time(person-hr/yr)
Other parameters
11.2-15
3722 (City of Whitney)
53,440 (City of Cleburne)
22,358,746
22,358,746
22,358,746
RG 1.109
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.2(4)
Table 11.2-15R
Individual Doses from Liquid Effluents
PATHWAY
SKIN
Adult
Teenager
Child
Infant
-
Adult
Teenager
Child
-
Adult
Teenager
Child
1.52E-03
8.47E-03
1.77E-03
Adult
Teenager
Child
-
Adult
Teenager
Child
-
Adult
Teenager
Child
-
Adult
Teenager
Child
-
Adult
Teenager
Child
Infant
1.52E-03
8.47E-03
1.77E-03
-
Annual Doses（mrem/yr）
LIVER
T.BODY THYROID KIDNEY
Drinking
2.40E-05 6.39E-03 6.39E-03 6.37E-03 6.38E-03
2.24E-05 4.51E-03 4.50E-03 4.49E-03 4.50E-03
6.32E-05 8.67E-03 8.63E-03 8.62E-03 8.64E-03
6.16E-05 8.52E-03 8.47E-03 8.46E-03 8.48E-03
Fish
7.86E-01 1.25E+00 8.83E-01 1.36E-01 5.15E-01
8.38E-01 1.26E+00 5.22E-01 1.04E-01 4.98E-01
1.05E+00 1.13E+00 2.49E-01 8.64E-02 4.26E-01
Shoreline
1.30E-03 1.30E-03 1.30E-03 1.30E-03 1.30E-03
7.25E-03 7.25E-03 7.25E-03 7.25E-03 7.25E-03
1.51E-03 1.51E-03 1.51E-03 1.51E-03 1.51E-03
Irrigated Foods：Vegetables
1.17E-04 4.64E-03 4.60E-03 4.53E-03 4.57E-03
1.89E-04 5.72E-03 5.60E-03 5.53E-03 5.60E-03
4.38E-04 9.09E-03 8.82E-03 8.77E-03 8.89E-03
Irrigated Foods：Leafy Vegetables
1.44E-05 5.72E-04 5.68E-04 5.58E-04 5.64E-04
1.26E-05 3.82E-04 3.74E-04 3.70E-04 3.74E-04
2.19E-05 4.55E-04 4.42E-04 4.39E-04 4.45E-04
Irrigated Foods：Milk
6.84E-05 2.80E-03 2.77E-03 2.71E-03 2.74E-03
1.23E-04 3.69E-03 3.58E-03 3.52E-03 3.58E-03
2.95E-04 5.86E-03 5.62E-03 5.58E-03 5.67E-03
Irrigated Foods：Meat
4.04E-05 9.71E-04 9.71E-04 9.60E-04 1.03E-03
3.39E-05 5.81E-04 5.79E-04 5.72E-04 6.27E-04
6.34E-05 7.05E-04 7.01E-04 6.93E-04 7.65E-04
Total
7.88E-01 1.27E+00 9.00E-01 1.52E-01 5.32E-01
8.46E-01 1.28E+00 5.44E-01 1.26E-01 5.20E-01
1.05E+00 1.16E+00 2.75E-01 1.12E-01 4.52E-01
6.16E-05 8.52E-03 8.47E-03 8.46E-03 8.48E-03
BONE
11.2-16
LUNG
GI-LLI
6.37E-03
4.49E-03
8.62E-03
8.47E-03
6.42E-03
4.52E-03
8.65E-03
8.48E-03
2.61E-01
2.56E-01
2.08E-01
1.72E-01
1.32E-01
9.74E-02
1.30E-03
7.25E-03
1.51E-03
1.30E-03
7.25E-03
1.51E-03
4.54E-03
5.56E-03
8.81E-03
4.74E-03
5.80E-03
8.99E-03
5.60E-04
3.71E-04
4.41E-04
5.85E-04
3.88E-04
4.50E-04
2.72E-03
3.54E-03
5.61E-03
2.71E-03
3.53E-03
5.58E-03
9.61E-04
5.73E-04
6.94E-04
3.04E-03
1.87E-03
1.48E-03
2.77E-01
2.78E-01
2.34E-01
8.47E-03
1.91E-01
1.55E-01
1.24E-01
8.48E-03
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
INSIDE C/V
OUTSIDE C/V
R
3"-LMS-151R
TIA
1099
1/2"-LMS-151R
RHS-MOV-002B
TE
M
1099P
1/2"-LMS-151R
RHS-MOV-001C
EC4
EC6
VLV-012
1/2"-T56
TE
1099Q
M
LO
1/2"-LMS-151R
RHS-MOV-002C
1/2"-LMS-151R
RHS-MOV-001D
TE
1099S
M
1/2"-LMS-151R
RHS-MOV-002D
EC4
LO
EC6
VLV-013
1/2"-T56
CVS
G-4
2169 CVS-07-02
C RCP NO3 SEAL LEAK
OFF
CVS
G-11
2171 CVS-07-02
D RCP NO3 SEAL LEAK
OFF
RWS
B-3
3330 RWS-02-01
REACTOR CAVITY
DRAIN
RWS
B-1
3331 RWS-02-01
PERMANENT CAVITY
SEAL DRAIN
SIS
B-4
2868 SIS-04-03
A-ACC. TANK DRAIN
R
P
EC4
EC6
VLV-023
4"-X42D
EC6
EC4
R
P
VLV-024
4"-C42L
SIS
H-4
2871 SIS-04-03
D-ACC. TANK DRAIN
Figure 11.2-201
EC4
R
2"-LMS-151R
EC6
VLV-030 VLV-046
2"-X42D 2"-C56L
4"-LMS-151R
EC6
R
T
P
T
R
200
200
>=37(L)
P
T
R
3"-LMS-151R
CGS
CGS-01-01
N2
1"-LMS-122N
150
120
R <37(G)
E-5
3310
2485
650
>=37(L) EC4
VLV-037
3"-C42
RWS
C-8
3340 RWS-02-01
RWSAT
OUTSIDE C/V
FC
EC2
PEN# P
205 T
T
RCS
A-11
RCS-03-01 1775
A-LOOP DRAIN RCS
G-11
RCS-03-01 1768
B-LOOP DRAIN RCS
H-1
RCS-03-01 1763
C-LOOP DRAIN
3"-LMS-2561R
200
200
<37(L)
T
T
RCS
D-11
RCS-03-02 1849
PMW
EC4
P
T
R
INSIDE C/V
T
T.C
VLV-079
3/4"-X42D
3"-LMS-2561R
2"-LMS-2561R
RCS
A-1
RCS-03-01 1747
D-LOOP DRAIN
PI
1002
3"-LMS-151R
4"x3"
R
T
P
VLV-031A
3"-X42D
R
DS
DS 3336
C/V SUMP
R
EC5
P
PCV-1004
T
1"-RA32RZ
EC4
3"-LMS-151R 4"x3"
2"-LMS-151R
T
EC6
VLV-058
1"-C36L
B-C/V REACTOR
COOLANT DRAIN
PUMP
CPP-001B
P 200
T 200
R >=37(L)
3"x2"
4"x3"
LMS
A-2
3592 LMS-08-04
WHT
VLV-080
3/4"-X42D
3"-LMS-151R
VLV-059
3/4"-T58MJ
FC
EC6
AOV-016
2"-DA42R
NOTE 1
VLV-031B
3"-X42D
DS
DS 3338
C/V SUMP
FC
2"x1"
3"x2"
3"-LMS-151R
150
175 VLV-044
<37(L) 3"-C42
P
T
R
VLV-017
2"-T56
VLV-029
3"-X42D
200
200
>=37(L)
3/4"x3/8"
VLV-087
3/4"-X32D
200
150
<37(L)
P
T
R
EC4
P
T
R
T.V
T
FC
P
A-11
CVS-07-06
HT
LOCAL
SAMPLE
VLV-038
3/4"-T56
RCS
A-6
RCS-03-01 1742
R/V FLANGE LEAK OFF
DS
3328 DS
C/V SUMP
RCS
D-6
RCS-03-02 1855
PRT
VLV-064
3/4"-C36L
VDS
VDS 3329
RCS VENT DRAIN
25
200
>=37(L)
EC6
DS
3326 DS
A/B SUMP
3/4"-LMS-122R
PIC
1004
2"-LMS-122R
25
200
>=37(L)
VLV-071
2"-X42D
A-1
3222
EC6
PT
1004
P 150
T 200
R >=37(G)
2"-LMS-151R
P
T
R
GMS
GMS-03-01
VH
2"-LMS-122R
200 LCV-1000B
300 3"-DA42R
R >=37(L)
3/4"x3/8"
EC4
VLV-015
3/4"-C56L
VLV-018
2"-C56
3"-LMS-151R
2"-LMS-151R
CVS
C-9
AOV-060
CVS-07-01 2187
2"-DA32R
EXCESS LETDOWN HX.
3"x2"
2"-LMS-151R
2"-LMS-151R
ACR
CVS
2792
P
VLV-036
3"-T42
3/4"x3/8"
EC6
2"-LMS-151R
VLV-022
2"-X42D
SIS
F-4
2870 SIS-04-03
C-ACC. TANK DRAIN
TIA
1000
FC
H
P
4"-LMS-151R
T
EC3
VLV-035
3"-X42D
EC2
3/4"-LMS-122R
TE
1000
T
300
200 VLV-041
>=37(L) 3"-C42
LCV-1000A
3"-DA42R
VLV-085
3/4"-X32D
3/4"x3/8"
VLV-051
3/4"-X42D
CVS
G-10
2180 CVS-07-01
B RCP NO3 SEAL LEAK
OFF
T
3/4"-LMS-151R EC6
P
T
R
P
EC6
VLV-057
2"-X42D
P
T
R
EC4
EC6
0
VLV-021
200
3/4"-C56L
>=37(L)
B-6
1857
VLV-043
3"-T42
R
3"-LMS-151R
3"-LMS-151R EC6
P
25
T 200
R >=37(G)
EC4
P
T
R
SIS
D-4
2869 SIS-04-03
B-ACC. TANK DRAIN
CP COL 11.2(6)
NOTE4
3/4"-LMS-151R
P
TE
1099R
M
NOTE3
DS
3337 DS
A/B SUMP
R
VLV-042
3"-X42D
T
P
A-C/V REACTOR
COOLANT DRAIN
PUMP
CCP-001A
VLV-033B
3"-C42
VLV-034B
3"-T42
VLV-033A
3"-C42
VLV-034A
3"-T42
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.
200
200
>=37(L)
TE
1099N
M
EC6
VLV-011
1/2"-T56
TI
3"-LMS-151R
RHS-MOV-001B
EC4
P
CVS
G-4
2183 CVS-07-01
A RCP NO3 SEAL LEAK
OFF
4"-LMS-151R
1/2"-LMS-151R
LO
EC6
1000
3"x2"
EC6
TE
1099M
M
3"x2"
VLV-014
2"-C56L
1/2"-LMS-151R
RHS-MOV-002A
2"-LMS-151R
3/4"-LMS-151R
VLV-040
3"-T42
PI
1001
P
T
R
TE
1099L
P 100
T 200
R >=37(G)
EC6
AOV-056
2"-DA42R
EC2
NOTE2
EC6
VLV-010
1/2"-T56
RHS-MOV-001A
M
LO
FC
P
T
RCS
RCS-03-02
PRT
VLV-039
3"-X42D
2"-LMS-2561R
EC4
GMS
D-5
3278 GMS-03-03
GA
VLV-062
3/4"-C36L
2"x3/4"
VLV-028 AOV-027
4"-C42 4"-DA42D
1/2"-LMS-151R
NOTE2
FO
M
T
2"-LMS-2561R
TE
1099K
3/4"-LMS-151R
VLV-004
3/4"-T58M
EC2
PEN#
284
3/8"-LMS-2521R
VLV-063
3/4"-X32D
C/V REACTOR
COOLANT
DRAIN TANK
CTK-001
P 25 / 15
T 200
R >=37(L)
4"-LMS-151R
RCS-MOV-111B
ACR
LT
1000
EC2
P 150
T 300
R >=37(G)
VLV-032B
3/4"-T58M
1/2"-LMS-151R
LICA
1000
FC
EC6
EC6
3/4"-LMS-151R
VLV-003
3/4"-T58M
T
T
T
VLV-032A
3/4"-T58M
2"-LMS-151R
TE
1099J
M
H
3/4"x3/8"
VLV-061
3/4"-X42D
EC4
VLV-009
1/2"-T56
LI
1000
H
4"-LMS-151R
EC4
P
0
T 200
R <37(L)
R
LMS
D-4
3324 LMS-08-02
C/V SUMP
P
25
T 200
R >=37(G)
EC6
2"-LMS-2561R
VLV-008
1/2"-T56
LO
EC6
EC4
PT
1000
ACR
3/4"x3/8"
3/4"x3/8"
AOV-053
3/4"-DA42R
T.V
VLV-026
2"-C56
1/2"-LMS-151R
RCS-MOV-111A
PIA
1000
T
AOV-055
2"-DA42R
P 150
T 200
R >=37(G)
P
EC6
P
EC6
FC
EC2
PEN#
276R
T
T.V
SS CS
2"-LMS-122R
VLV-054
2"-X42D
VLV-001
3/4"-RV42N
VLV-025
2"-T56
M
LO
P
VLV-077B
3/4"-X42D
EC4
TE
1099H
3"x2"
EC2
1"-LMS-151R
1099G
CVS-HCV-190
3"x2"
PI
1000
TE
1/2"-LMS-151R
2"-LMS-151R
P
60
T 300
R >=37(G)
FC 3/4"-LMS-151R
AOV-052
3/4"-DA42R
2"x1"
1/2"-LMS-151R
RCS-MOV-118
P
P
25
T 200
R >=37(G)
TE
1099F
M
CVS
E-11
2172 CVS-07-02
RCP D NO2 SEAL LEAK
OFF
3"x2"
EC6
RCS-MOV-116B
2"-LMS-151R
3"-LMS-151R
1/2"-LMS-151R
CVS
E-6
2170 CVS-07-02
RCP C NO2 SEAL LEAK
OFF
T
T.C
3/4"-LMS-151R
EC6
VLV-007
1/2"-T56
TE
1099E
M
LO
EC4
RCS-MOV-116A
EC4
2"-LMS-151R
2"-LMS-151R
1/2"-LMS-151R
CVS
E-11
2181 CVS-07-01
RCP B NO2 SEAL LEAK
OFF
3"-LMS-151R
EC6
VLV-006
1/2"-T56
TE
1099D
M
LO
VLV-002
3/4"-T58M
RCS-VLV-021
EC4
2"-LMS-151R
2"-LMS-151R
1/2"-LMS-151R
CVS
E-6
2179 CVS-07-01
RCP A NO2 SEAL LEAK
OFF
25
200
>=37(L)
1/2"-LMS-151R
TE
1099C
3/8"-LMS-151R EC6
P
T
R
1099B
RCS-PCV-451B
T
3/4"x3/8"
VLV-005
1/2"-T56
TE
T
VLV-077A
3/4"-X42D
EC6
NOTE3
LO
2"x1/2"
RCS-PCV-451A
EC4
3/4"-LMS-151R
EC6
3/4"x3/8"
TE
1099A
T.V
VLV-086
3/4"-X42D
CVS
A-4
2174 CVS-07-02
RCP PURGE WATER
HEAD TANK
VLV-083
3/4"-X42D
T.C
1/2"-LMS-151R
3"-LMS-301R
EC4
EC6
VLV-084
3/4"-X42D
H
3"-LMS-151R
3"-LMS-151R EC6
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
LMS-###-+++
P 200
T 200
R >=37(L)
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 1 of 9)
11.2-17
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
INSIDE C/V
OUTSIDE C/V
FM
1084
VLV-107
3/4"-T58M
3/4"x3/8"
LOCAL
SAMPLE
VLV-108
3/4"-T56
VLV-173
3/4"-X42D
NOTE2
FIA
1083B
ACR
LIA
1083A
H
L
LT
1083A
3356
LI
1083B
VS
VS
LT
1083B
H
L
LICA
1095A
ACR ACR
LT
1095A
VLV-145
1"-T56
NCS
B-5
NCS-09-01 2555
A-SURGE TANK
4"-LMS-151R
NCS
B-5
NCS-09-02 2562
B-SURGE TANK
P
0
T 150
R <37(L)
H
2"-LMS-151R
L
VS
3353 VS
R/B EXHAUST
LT
1095B
DS
DS 3366
EQUIP.DRAIN
P 150
T 200
R <37(L)
B-C/V SUMP
PUMP
CPP-002B
P 150
T 200
R <37(L)
DS
DS 3358
FLOOR DRAIN
A-C/V SUMP
PUMP
CPP-002A
C/V SUMP
4"-LMS-151R
NOTE5
DS
DS 3357
EQUIP.DRAIN
P
0
T 200
R <37(L)
LICA
1095B
A-10
LMS-08-04
WHT
P
0
T 150
R <37(L)
VLV-141B
3/4"-T58M
VLV-142B
2"-C56
P 150
T 150
R <37(L)
VLV-143A
2"-T56
VLV-141A
3/4"-T58M
HH
H
P 150
T 175
R <37(L)
P
0
T 150
R <37(L)
L
LICA
1083A
VLV-147
2"-C56
EC6
0
200
R <37(L)
1"-LMS-151R
3/4"x3/8"
H
VLV-124 P
3/4"-X42D T
P 150
T 150
R <37(L)
EC4
EC4
VLV-123 3/4"-LMS-151R
3/4"-C56
PI
1097
EC4
VLV-122
3/4"-X56N
P 150
T 150
R <37(L)
T
PI
1096
P
EC4
FC
SOV-121
3/4"-TS52S
A-10
LMS-08-04
WHT
LMS
3596
VLV-146
2"-T56
P
0
T 150
R <37(L)
DWS
E-2
3359 DWS-01-01
DW
3/4"-LMS-151R
VLV-125
3/4"-T58M
P
LMS
3597
VLV-109
2"-T56
T
A-R/B SUMP
PUMP
RPP-003A
S
P 150
T 175
R <37(L)
2"-LMS-151R
EC6
VLV-103B
1-1/2"-T56
LT
1082
L
VLV-127
3/4"-X56N
3"-LMS-151R
LI
1082
1-1/2"x3/4"
LIA
1082
3/4"-LMS-151R
AOV-1261"-LMS-151R
1"x3/4"
1"-DA42D
T
2"-LMS-151R
P 150
T 200
R <37(L)
4"-LMS-151R
3"x1-1/2"
1"-LMS-151R
FO
NOTE1
HH
H
AOV-105
2"-DA42R
FE
1084
EC6
VLV-144
3/4"-T56
4"-LMS-151R
T
STAND PIPE
P 150
T 300
R <37(L)
T
VLV-143B 2"-LMS-151R
2"-T56
LOCAL
SAMPLE
3"-LMS-151R
VLV-102B
1-1/2"-C56
V
CVS
A-8
CVS-07-02 2168
RCP PWHT RELIEF
LINE
LMS
C-4
LMS-08-01 3324
CVDT RELIEF LINE
RWS
D-1
RWS-02-01 3836
RWSP OVERFLOW
LINE
VLV-103A
1-1/2"-T56
3"-LMS-151R
1-1/2"-LMS-151R
VLV-102A
1-1/2"-C56
P
0
T 200
R <37(L)
AOV-104
2"-DA42R
EC2
P 150
T 150
R <37(L)
VS
VS 3365
D-CONTAINMENT
RECIRCULATION UNIT
EC2
VLV-142A
2"-C56
2"-LMS-151R
T
B-R/B SUMP
PUMP
RPP-003B
VS
VS 3364
C-CONTAINMENT
RECIRCULATION UNIT
FC
PEN#
207
P 150
T 150
R <37(L)
2"-LMS-151R
T
FC
P 150
T 200
R <37(L)
VS
VS 3363
B-CONTAINMENT
RECIRCULATION UNIT
EC6
T
2"-LMS-151R
2"-LMS-151R
EC4
3"-LMS-151R
VLV-172
3/4"-X42D
NOTE3
VS
VS 3362
A-CONTAINMENT
RECIRCULATION UNIT
2"-LMS-151R
FT
1084
T.V
VLV-106
3/4"-T58M
T.C
VS
VS 3361
CRDM COOLING UNIT
2"-LMS-151R
DS
DS 3367
FLOOR DRAIN
R/B SUMP TANK
RTK-002
P
0
T 150
R <37(L)
NOTE4
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.
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
LMS-###-+++
CP COL 11.2(6)
Figure 11.2-201
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 2 of 9)
11.2-18
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
A/B
2"-LMS-151R
VLV-207
2"-C56
P
T
R
150
175
<37(L)
T
A-10
LMS-08-04
WHT
VLV-226
2"-T56
LMS
3585
2"-LMS-151R
VLV-227
2"-C56
P
T
R
150
175
<37(L)
B-1
LMS-08-04
WHT
3603
TURBINE SUMP
3/4"x3/8"
3/4"x3/8"
LOCAL
SAMPLE
VLV-204
3/4"-T56
VLV-223B
2"-T56
150
150
<37(L)
LT
1091B
NOTE2
LT
1085A
ACR ACR
H
EC6
L
LT
1085B
VS
3601 VS
A/B EXHAUST
L
LICA
LICA
1088A
1088B
LT
1088A
ACR ACR
H
VLV-242B
1-1/2"-T56
VLV-242A
1-1/2"-T56
L
VS
3606 VS
R/B EXAUST
LT
1088B
DS
DS 3605
EQUIP. DRAIN
(NON-RADIOACTIVE)
NOTE2
DS
3400
FLOOR DRAIN
P
0
T 150
R <37(L)
VLV-225
1"-T56
H
3/4"-T58M
LICA
1085B
VLV-241B
1-1/2"-C56
L
LICA
1085A
PI
1090
VLV-241A
1-1/2"-C56
2"x1-1/2"
H
2"-LMS-151R
L
VS
3399 VS
A/B EXHAUST
P 150
T 150
R <37(L)
EC6
PI
1089
3/4"-T58M
1"-LMS-151R
0
150
<37(L)
VLV-221B
3/4"-T58M
P
P
T
R
P
T
R
VLV-222B
2"-C56
VLV-222A
2"-C56
PI
1087
B-A/B
EQUIPMENT
DRAIN SUMP
PUMP
APP-005B
LT
1091A
ACR ACR
H
P 150
T 150
R <37(L)
2"x1-1/2"
LICA
1091B
2"-LMS-151R
L
LICA
1091A
PI
1086
VLV-221A
3/4"-T58M
P
T
R
0
150
<37(L)
VLV-201B
3/4"-T58M
1"-LMS-151R
P 150
T 150
R <37(L)
B-A/B SUMP
PUMP
APP-006B
2"x1-1/2"
P 150
T 150
R <37(L)
2"x1-1/2"
A-A/B SUMP
PUMP
APP-006A
H
VLV-205
1"-T56
P
T
R
VLV-202B
2"-C56
P
2"-LMS-151R VLV-223A
2"-T56
150
150
<37(L)
PI
1093
P
T
R
PI
1092
A-A/B
EQUIPMENT
DRAIN SUMP
PUMP
APP-005A
150
150
<37(L)
VLV-203B
2"-T56
2"-LMS-151R
VLV-201A
3/4"-T58M
DS
DS 3602
EQUIP.DRAIN
DS
DS 3604
FLOOR DRAIN
(NON-RADIOACTIVE)
P
0
T 150
R <37(L)
P
0
T 200
R <37(L)
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
P 150
T 200
R <37(L)
NONRADIOACTIVE
DRAIN SUMP
B-NONRADIOACTIVE
DRAIN PUMP
RPP-004B
NOTE1
A/B EQUIPMENT
DRAIN SUMP
TANK
ATK-003
P 150
T 200
R <37(L)
NOTE1
A/B SUMP TANK
ATK-004
A-NONRADIOACTIVE
DRAIN PUMP
RPP-004A
VLV-202A
2"-C56
2"-LMS-151R VLV-203A
2"-T56
150
150
<37(L)
P
T
R
LOCAL
SAMPLE
VLV-224
3/4"-T56
2"-LMS-151R
2"-LMS-151R
EC6
EC6
P
T
R
150
200
<37(L)
2"-LMS-151R
2"-LMS-151R
VLV-206
2"-T56
LMS
3578
EC6
T
R/B
NOTES
1, SLUDGE SEPARATOR BAFFLE PLATE.
2, OIL SEPARATOR.
LMS-###-+++
CP COL 11.2(6)
Figure 11.2-201
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 3 of 9)
11.2-19
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
SFS
E-5
3618 SFS-02-02
B-SFP DEMI.
LMS
E-2
3661 LMS-08-05
ACTIVATED CARBON
FILTER
LMS
E-6
3655 LMS-08-05
C-WASTE EFFLUENT
DEMI.
LMS
B-6
3382 LMS-08-05
A-WASTE EFFLUENT
DEMI.
LMS
B-3
3578 LMS-08-03
A/B SUMP TANK
SGS
E-6
3488 SGS-03-02
A-SG BLOWDOWN MIX
DEMI.
SGS
G-4
3474 SGS-03-02
SGBD RADIATION
MONITOR
SMS
B-11
3999 SMS-01-01
DEWATERING PUMP
LMS
A-9
4097 LMS-08-06
WASTE MONITOR
TANK PUMP
LMS
B-9
3385 LMS-08-05
B-WASTE EFFLUENT
DEMI.
LMS
B-11
3597 LMS-08-02
C/V SUMP
2"-LMS-151R
3"x1-1/2"
LMS
D-11
3596 LMS-08-02
R/B SUMP TANK
3"-LMS-151R
1-1/2"x1"
3"x1-1/2"
3"-LMS-151R
2"-LMS-151R
3"-LMS-151R
2"-LMS-151R
3"x1-1/2"
2"-LMS-151R
3"x1-1/2"
1"-LMS-151R
6"-LMS-151R
2"-LMS-151R
3"x2"
3"-LMS-151R
LMS
B-7
3585 LMS-08-03
A/B EQUIP. DRAIN
SUMP TANK
2"-LMS-151R
P
VLV-301
2"-C56L
2"-LMS-151R
T
2"-LMS-151R
R
DS
3624 DS
EQUIP.DRAIN
B-11
LMS-08-01
CVDT
2"-LMS-151R
LMS
3592
VLV-302
3"-X42D
P
T
R
2"-LMS-151R
SGS
A-9
3476 SGS-03-02
B-SG BLOWDOWN
CATION DEMI.
1-1/2"x1"
RWS
D-9
3575 RWS-02-02
REFUELING WATER
STORAGE AUX. TANK
1-1/2"x1"
LMS
F-9
4096 LMS-08-08
CHEMICAL DRAIN
TANK PUMP
1-1/2"x1"
LMS
H-8
4098 LMS-08-07
DETERGENT DRAIN
MONITOR PUMP
3"-LMS-151R
LMS
E-9
3657 LMS-08-05
D-WASTE EFFLUENT
DEMI.
1"-LMS-151R
SFS
E-2
3619 SFS-02-02
A-SFP DEMI.
2"-LMS-151R
SGS
A-6
3475 SGS-03-02
A-SG BLOWDOWN
CATION DEMI.
3"x2"
NOTE2
3997
TURRBINE BUILDING
SUMP
SGS
E-9
3499 SGS-03-02
B-SG BLOWDOWN MIX
DEMI.
150
175
<37(L)
P
T
R
R
T
R
DS
3571 DS
A/B SUMP
T
VLV-313B
3/4"-C56
P
DS
3588 DS
A/B SUMP
FO
FC
2"-LMS-151R
4"-LMS-151R
4"x3"
2"-LMS-151R
AOV-303C
3"-DA42D
4"-LMS-151R 4"x3"
AOV-321C
3"-DA42R
AOV-321D
3"-DA42R
VLV-306D
3/4"-T58M
DWS
DWS-01-01
DW
E-6
3570
L
LICA
1012
2"-LMS-151R
LT
1013
ACR
NOTE1
VLV-307C
3/4"-T58M
(D)
R
T
C-WASTE
HOLDUP TANK
ATK-005C
DS
3616 DS
A/B SUMP
P
0
T 175
R <37(L)
H
L
LICA
1013
ACR
VLV-307D
3/4"-T58M
(D)
FC
LT
1012
H
AOV-308D
4"-DA42R
P
0
T 175
R <37(L)
T
VS
3615 VS
A/B EXHAUST
2"-LMS-151R
NOTE1
P
DS
3587 DS
A/B SUMP
P
P
VLV-371D
2"-X42D
P
0
T 175
R <37(L)
P
LOCAL
SAMPLE
AOV-308C
4"-DA42R
ACR
B-WASTE
HOLDUP TANK
ATK-005B
VLV-371B
2"-X42D
(ED)
P
VLV-371C
2"-X42D
LICA
1011
L
VLV-315B
3/8"-T58
VLV-307B
3/4"-T58M
AOV-308B
4"-DA42R
DS
3586 DS
A/B SUMP
H
LMS
C-2
3610 LMS-08-08
NEUTRALIZING AGENT 3/4"-LMS-151R
TANK
VLV-306C
3/4"-T58M
FC
NOTE1
A-WASTE
HOLDUP TANK
ATK-005A
VLV-371A
2"-X42D
(ED)
AOV-308A
4"-DA42R
E-6
3608
4"-LMS-151R
DWS
DWS-01-01
DW
0
175
<37(L)
VLV-313A
3/4"-C56
T
LT
1011
ACR
VLV-307A
3/4"-T58M
FC
P
LICA
1010
L
P
2"-LMS-151R
FC
VLV-314A
3/4"-T56
LT
1010
NOTE1
CVS
C-7
CVS-07-06 3560
C-HOLDUP TANK
0
175
<37(L)
2"-LMS-151R
H
6"-LMS-151R
P
T
R
LOCAL
SAMPLE
VLV-315A
3/8"-T58
VLV-306B
3/4"-T58M
6"-LMS-151R
CVS
C-4
CVS-07-06 3562
B-HOLDUP TANK
VLV-319C VLV-320C
3"-T42
3"-C42
4"-LMS-151R
VLV-306A
3/4"-T58M
CVS
C-2
CVS-07-06 3561
A-HOLDUP TANK
FC
4"x3"
VLV-305B
4"-X42D
VLV-304B
4"-C42
6"-LMS-151R
VLV-314B
3/4"-T56
VLV-304A
4"-C42
LO
0
175
<37(L)
150
175
<37(L)
VS
3614 VS
A/B EXHAUST
VLV-318 VLV-319D VLV-320D
3"-T42
3"-C42
3"-X42D
6"x4"
P
T
R
P
T
R
LMS
D-2
LMS-08-08 3611
3/4"-LMS-151R NEUTRALIZING AGENT
TANK
3"-LMS-151R
VS
3590 VS
A/B EXHAUST
3"-LMS-151R
VLV-305A
4"-X42D
FO
FO
4"-LMS-151R
4"-LMS-151R
LO
3"-LMS-151R
P
4"-LMS-151R
2"-LMS-151R
AOV-321A 3"-LMS-151R
3"-DA42R
P
4"-LMS-151R 4"x3"
FC
P
FC
VS
3589 VS
A/B EXHAUST
VLV-317 VLV-319B VLV-320B
3"-C42
3"-T42
3"-X42D
P
2"-LMS-151R
3"-LMS-151R
LMS
D-2
3591 LMS-08-08
NEUTRALIZING AGENT 3/4"-LMS-151R
TANK
AOV-303B
3"-DA42D
LMS
D-2
LMS-08-08 3572
3/4"-LMS-151R NEUTRALIZING AGENT
TANK
150
175
<37(L)
AOV-321B
3"-DA42R
P
VLV-319A VLV-320A
3"-T42
3"-C42
P
T
R
AOV-303A
3"-DA42D
FO
3"-LMS-151R
AOV-303D
3"-DA42D
FC
AOV-316
3"-DA42R
R
DS
3609 DS
A/B SUMP
T
D-WASTE
HOLDUP TANK
ATK-005D
DS
3612 DS
A/B SUMP
P
0
T 175
R <37(L)
P
DS
3613 DS
A/B SUMP
FC
P
T
R
VLV-311A
3/4"-T58M
PI
1014
P
P
T
R
200
175
<37(L)
3"-LMS-151R
P
R
LMS
A-2
3669 LMS-08-05
WASTE EFFLUENT
INLET FILTER
P 200
T 175
R <37(L)
2"-LMS-151R
T
A-WASTE
HOLDUP TANK
PUMP
APP-007A
AOV-309
4"-DA42R
VLV-312A
3"-C42
VLV-372A
3/4"-X42D
VLV-310A
4"-X42D
200
175
<37(L)
P
T
R
2"-LMS-151R
VLV-322A VLV-323A AOV-324A
2"-C42
2"-T42 2"-DA42R
0
175
<37(L)
DS
3563 DS
A/B SUMP
EC6
ALL PIPING VALVES AND COMPONENTS IN THIS
SHEET ARE CLASSIFIED AS EQUIPMENT CLASS6
3"-LMS-151R
PI
1015
P
P
T
R
R
T
P
VLV-372B
3/4"-X42D
3"-LMS-151R
VLV-310B
4"-X42D
P 200
T 175
R <37(L)
B-WASTE
HOLDUP TANK
PUMP
APP-007B
P 200
T 175
R <37(L)
200
175
<37(L)
REMARK:
VLV-322B VLV-323B AOV-324B
2"-C42
2"-T42 2"-DA42R
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
VLV-312B
3"-C42
VLV-311B
3/4"-T58M
NOTES
1,THE TANK IS EQUIPPED WITH MIXING NOZZLES INSIDE.
2,TRANSFERRED ONLY IF THE CONTENT IS RADIOACTIVE.
LMS-###-+++
3"-LMS-151R
DS
3584 DS
A/B SUMP
CP COL 11.2(6)
Figure 11.2-201
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 4 of 9)
11.2-20
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
T
VLV-421
2"-T56
VLV-431B
2"-X42D
CVS
H-3
CVS-07-07 4188
B.A. EVAP FEED DEMI.
EC4
VLV-422
2"-C56
2"-LMS-151R
2"-LMS-151R
EC6
VLV-431A
2"-X42D
R
LMS
F-6
3669 LMS-08-04
WASTE HOLDUP TANK
PUMP
VLV-432A
3/4"-T58M
VLV-432B
3/4"-T58M
R
SMS
A-1
SMS-01-01 3407
SRST
T
P
H
dPIA
1021
VLV-436A
2"-X42D
3415
A/B SUMP
VLV-438A
1"-T56
3/4"x3/8"
R
T
P
T
VLV-433B
3"-X42D
VLV-436B
2"-X42D
H
dPIA
VLV-435B
3/4"-T58M
T
3416
A/B SUMP
1"-LMS-151R
VLV-479B
3/4"-X42D
R
VLV-438B
1"-T56
3/4"x3/8"
LOCAL
SAMPLE
VLV-444B
2"-X42D
VLV-439B
3/4"-T56
VLV-444A
2"-X42D
CONNECTION FOR MOBILE EQUIP.
T
VLV-437B
1"-T56
1022
LOCAL
SAMPLE
VLV-439A
3/4"-T56
VLV-473
2"-X42D
P 200
T 175
R <37(L)
DS
1"-LMS-151R
VLV-479A
3/4"-X42D
R
B-WASTE DEMI.
ADM-002B
SMS
A-1
SMS-01-01 3408
SRST
VLV-435A
3/4"-T58M
3"-LMS-151R
VLV-433A
3"-X42D
VLV-437A
1"-T56
T
VLV-405
2"-X42D
VLV-404B
3/4"-T58M
T
150
T 175
R <37(L)
VLV-440
3"-X42D
P 200
T 175
R <37(L)
DS
VLV-404A
3/4"-T58M
3"-LMS-151R
A-WASTE DEMI.
ADM-002A
1"-LMS-151R
VLV-434B
1"-X42D
2"-LMS-151R
VLV-403B
2"-X42D
DS
DS 3671
A/B SUMP
H
P
LMS
A-9
LMS-08-04 3385
WHT
P
T
2"-LMS-151R
VLV-471A
3/4"-X44D
VLV-472B
3/4"-X44D
VLV-403A
2"-X42D
DS
DS 3670
A/B SUMP
dPIA
1019
RESIN FILL
VLV-441
3"-X42D
1018
VLV-472A
3/4"-X44D
150
T 175
R <37(L)
B-WASTE
EFFLUENT
INLET FILTER
AFT-001B
H
1"-LMS-151R
VLV-434A
1"-X42D
2"-LMS-151R
dPIA
P
LMS
A-9
LMS-08-04 3382
WHT
P
VLV-471B
3/4"-X44D
A-WASTE
EFFLUENT
INLET FILTER
AFT-001A
VLV-401B
3/4"-T58M
2"-LMS-151R
VLV-401A
3/4"-T58M
VLV-402B
2"-X42D
VLV-402A
2"-X42D
RESIN FILL
VLV-474
2"-C56
VLV-409
3/4"-T58M
VLV-432C
3/4"-T58M
T
EC6
VLV-416
2"-T56
VLV-414
2"-C56
CVS
G-5
CVS-07-03 3664
PMW SUPPLY.
P
4"x2"
VLV-447A
2"-X42D
DS
DS 3674
A/B SUMP
P
P
VLV-433D
3"-X42D
3"-LMS-151R
VLV-442
3"-X42D
dPIA
1024
VLV-435D
3/4"-T58M
T
R
VLV-479D
3/4"-X42D
LOCAL
SAMPLE
1"-LMS-151R
VLV-438D
1"-T56
3/4"x3/8"
VLV-439D
3/4"-T56
LOCAL
SAMPLE
VLV-444D
2"-X42D
VLV-444C
2"-X42D
dPIA
EC6
ALL PIPING VALVES AND COMPONENTS IN THIS
SHEET ARE CLASSIFIED AS EQUIPMENT CLASS6.
H
1026
B-WASTE EFFLUENT
OUTLET STRAINER
4"x2"
VLV-447B
2"-X42D
R
DS
DS 3675
A/B SUMP
Figure 11.2-201
T
T
VLV-436D
2"-X42D
VLV-437D
1"-T56
H
4"x2"
VLV-446A
2"-X42D
T
R
T
H
A-WASTE EFFLUENT
OUTLET STRAINER
R
VLV-443
3"-X42D
1"-LMS-151R
VLV-438C
1"-T56
3/4"x3/8"
1025
2"-LMS-151R
DS
DS 3653
A/B SUMP
T
dPIA
P 200
T 175
R <37(L)
SMS
A-2
SMS-01-01 3656
SRST
VLV-435C
3/4"-T58M
VLV-479C
3/4"-X42D
D-WASTE DEMI.
ADM-002D
2"-LMS-151R
VLV-433C
3"-X42D
3"-LMS-151R
1023
VLV-436C
2"-X42D
R
LOCAL
SAMPLE
VLV-448A
3/4"-T58M
VLV-419
3/4"-T56
LMS
A-5
LMS-08-06 3672
WASTE MONITOR
TANK
CP COL 11.2(6)
dPIA
VLV-439C
3/4"-T56
3/4"x3/8"
2"x3/4"
EC4
T
DS
DS 3654
A/B SUMP
T
VLV-437C
1"-T56
H
1"-LMS-151R
VLV-434D
1"-X42D
150
T 175
R <37(L)
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
4"x2"
VLV-446B
2"-X42D
T
P
LMS-###-+++
VLV-481B
3/4"-X42D
VLV-476
3/4"-X42D
VLV-417
2"-X42D
R
R
SMS
A-2
SMS-01-01 3652
SRST
LMS
A-6
LMS-08-04 3657
WHT
P
T
2"-LMS-151R
WMS
A-9
LMS-08-06 3665
WASTE MONITOR
TANK PUMP
VLV-420
2"-C56
RESIN FILL
P
VLV-445B
3/4"-T58M
T
P 200
T 175
R <37(L)
2"-LMS-151R
VLV-412
3/4"-T58M
C-WASTE DEMI.
ADM-002C
2"-LMS-151R
1020
2"-LMS-151R
dPIA
VLV-445A
3/4"-T58M
P
H
VLV-448B
3/4"-T58M
T
T
VLV-413
2"-X42D
1"-LMS-151R
VLV-434C
1"-X42D
VLV-481A
3/4"-X42D
DS
DS 3663
A/B SUMP
R
LMS
A-7
LMS-08-04 3655
WHT
P
VLV-415
2"-T56
SMS
A-6
SMS-01-01 3659
SRST
2"-LMS-151R
P 200
T 175
R <37(L)
2"-LMS-151R
VLV-418
2"-X42D
T
ACTIVATED
CARBON FILTER
ADM-001
P
150
T 175
R <37(L)
3"-LMS-151R
LMS
A-6
LMS-08-04 3661
WHT
2"-LMS-151R VLV-411
P 150
2"-X42D
T 175
R <37(L)
VLV-432D
3/4"-T58M
RESIN FILL
VLV-410
3"-X42D
RESIN FILL
P
VLV-431D
2"-X42D
VLV-408
2"-X42D
VLV-431C
2"-X42D
CVS
B-10
3666 CVS-07-07
B.A.EVAP DESTILLATE.
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 5 of 9)
11.2-21
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
LMS
G-5
LMS-08-05 3672
WASTE DEMIN.
CONNECTION FOR MOBILE EQUIP.
VLV-577
2"-C56
VLV-576
2"-X42D
VLV-571
2"-X42D
VLV-575
2"-C56
LMS
B-2
3643 LMS-08-09
DISCHARGE HEADER
LMS
F-4
3665 LMS-08-05
WASTE DEMIN.
VLV-541
2"-X42D
CVS
B-10
4091 CVS-07-07
B.A.EVAP
LMS
A-7
4097 LMS-08-04
WHT
CONNECTION FOR MOBILE EQUIP.
VLV-532 3"-LMS-102R VLV-533
3"-X42D
3"-C42
P
2"-X42D
P 150
T 150
R <37(L)
R
T
P
VLV-573A
3/4"-X42D
VLV-505
3"-X42D
VLV-506A
3"-X42D
VLV-508A
2"-C42
VLV-507A
3/4"-T58M
1030
3"-LMS-151R
VLV-509A
3/4"-T56
2"-LMS-151R
LOCAL
SAMPLE
3"-LMS-102R
FIA
1034
LC
VLV-531
3"-X42D
RCV-035A
3"-DA42R
RE
35
ACR
RIA
35
VLV-515A
2"-X42D
VLV-515B
2"-X42D
3/4"x3/8"
RCV-035B
3"-DA42R
FC
35
H
P
RICA
H
PI
3"-LMS-151R
3"-LMS-151R
H
FT
ACR
VLV-529
3"-X42D
DS
3704 DS
A/B SUMP
3"x2"
ACR
3"-LMS-151R
P 150
T 150
R <37(L)
SS CS
VLV-517
3/4"-T58M
3"x2"
P
0
T 150
R <37(L)
P
L
LICA
1029
ACR
VLV-528
3/4"-T58M
FE
1034
P
0
T 150
R <37(L)
R T
DS
DS 3706
A/B SUMP
H
FI
1033
VLV-516
2"-T56
B-WASTE
MONITOR TANK
ATK-006B
AOV-504B
3"-DA42R
DS
3681 DS
A/B SUMP
VLV-503B
3/4"-T58M
FC
FC
3"-LMS-151R AOV-504A
3"-DA42R
VLV-572A
2"-X42D
P
0
T 150
R <37(L)
1034
VLV-527
3/4"-T58M
P
1-1/2"-LMS-151R
3"x1-1/2"
LC
VLV-525
1-1/2"-T56
VLV-526
1-1/2"-C56
P 150
T 150
R <37(L)
VLV-514A
3"-C42
A-WASTE
MONITOR TANK
PUMP
APP-008A
VLV-521A
3"-T42
AOV-522A
3"-DA42R
P 150
T 150
R <37(L)
3/4"-LMS-151R VLV-524
3/4"-C56
AOV-523
3/4"-IA52R
2"-LMS-151R
P 150
T 150
R <37(L)
T
R
PWS
G-4
PWS-01-01 3754
PMW PUMP
DWS
DWS-01-01
DW
G-6
3628
LMS
G-9
LMS-08-07 3430
DETERGENT DRAIN
MONITOR TANK PUMP
DS
3690 DS
A/B SUMP
3/4"x3/8"
PI
P
VLV-507B
3/4"-T58M
VLV-508B
2"-C42
1031
P 150
T 150
R <37(L)
R
T
P
VLV-573B
3/4"-X42D
VLV-506B
3"-X42D
B-WASTE
MONITOR TANK
PUMP
APP-008B
3"-LMS-151R
VLV-509B
3/4"-T56
3"-LMS-151R
2"-LMS-151R
P
LT
1029
NOTE1
ACR
VLV-503A
3/4"-T58M
A-WASTE
MONITOR TANK
ATK-006A
P
0
T 150
R <37(L)
R T
DS
DS 3685
A/B SUMP
L
LICA
1028
2"-LMS-151R
FT
1033
FC
VLV-502B
3/4"-T58M
VLV-572B
2"-X42D
NOTE1
H
VLV-520
2"-X42D
1033
FE
VLV-518
3/4"-T58M
2"-LMS-151R
LT
1028
P
2"-C42
VLV-502A
3/4"-T58M
T
2"-LMS-151R
AOV-513B
2"-DA42R
FC
2"-LMS-151R
P
VS
3709 VS
A/B EXHAUST
2"-LMS-151R
P
VS
3686 VS
A/B EXHAUST
2"-LMS-151R
VLV-512A
2"-C42
FC
VLV-511A
2"-T42
VLV-512B
2"-C42
AOV-513A 2"-LMS-151R
2"-DA42R
VLV-510
2"-X42D
VLV-511B
2"-T42
EC6
ALL PIPING VALVES AND COMPONENTS IN THIS
SHEET ARE CLASSIFIED AS EQUIPMENT CLASS6.
VLV-530
3"-X42D
T
AOV-501B
2"-DA42D
FO
P
2"-LMS-151R
3"-LMS-151R
T
P 200
T 175
R <37(L)
AOV-501A
2"-DA42D
FO
2"-LMS-151R
LOCAL
SAMPLE
NOTE
1,THE TANK IS EQUIPPED WITH MIXING NOZZLE INSIDE.
P 150
T 150
R <37(L)
REMARK:
VLV-514B
3"-C42
VLV-521B
3"-T42
AOV-522B
3"-DA42R
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
LMS-###-+++
P 150
T 150
R <37(L)
DS
3711 DS
A/B SUMP
CP COL 11.2(6)
Figure 11.2-201
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 6 of 9)
11.2-22
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
3442
SHOWER DRAIN
3443
HAND WASH DRAIN
4"x3"
3"-LMS-151R
3"-LMS-151R
T
VLV-601A
3"-X42D
P
DS
3429 DS
A/B SUMP
0
175
<37(L)
R
VLV-672A
3/4"-X42D
VLV-602A 4"x3"
3"-X42D
T
VLV-672B
3/4"-X42D
P
T
R
VLV-602B 4"x3"
3"-X42D
R
P
VLV-601B
3"-X42D
DS
3435 DS
A/B SUMP
AOV-603
3"-DA42D
FO
EC6
ALL PIPING VALVES AND COMPONENTS IN THIS
SHEET ARE CLASSIFIED AS EQUIPMENT CLASS6.
4"x3"
P
1"-LMS-151R
1"-LMS-151R
2"-LMS-151R
VLV-604
3/4"-T58M
P
T
R
P
VLV-608
1"-C56
P
T
R
VLV-613
1"-C58
150
175
<37(L)
VLV-614
1"-X42D
DETERGENT
DRAIN FILTER
AFT-002
T
P
R
CONNECTION FOR ALTERNATE PROCESS
DS
DS 3440
A/B SUMP
H
L
ACR
LT
1067
150
150
<37(L)
2"-LMS-151R
P
0
T
175
R <37(L)
DS
3431 DS
A/B SUMP
NOTE1
FC
P
T
R
P
P
T
R
2"-LMS-151R
2"-LMS-151R
T
0
150
<37(L)
R
P
2"-LMS-151R
VLV-680
3/4"-X42D
DS
DS 3433
A/B SUMP
P
T
R
P
DETERGENT
DRAIN MONITOR
TANK
ATK-008
LICA
1067
1"-LMS-151R
VS
3432 VS
A/B EXHAUST
2"-LMS-151R
VLV-619
3/4"-T58M
2"-LMS-151R
AOV-627
2"-DA42R
0
150
<37(L)
VLV-626
2"-C56
2"x1"
P
P
VLV-681
3/4"-X42D
T
LOCAL
SAMPLE
VLV-624
3/4"-T56
FC
2"-LMS-151R
2"-LMS-151R LMS
AOV-631
2"-DA42R
VLV-623
2"-X42D
DETERGENT
DRAIN MONITOR
TANK PUMP
APP-010
P 150
T 150
R <37(L)
DS
3441 DS
A/B SUMP
NOTES
1,THE TANK IS EQUIPPED WITH MIXING NOZZLE INSIDE.
3/4"x3/8"
VLV-622
2"-C56
R
VLV-625
2"-T56
PI
1068
VLV-620
2"-X42D
Figure 11.2-201
P
P 150
T 175
R <37(L)
DS
3438 DS
A/B SUMP
VLV-618
3/4"-T58M
CP COL 11.2(6)
T
1"-LMS-151R
VLV-615
1"-X42D
150
150
<37(L)
R
1"-LMS-151R
P
T
R
P 150
T 175
R <37(L)
150
175
<37(L)
1"-LMS-151R
VLV-609
1"-T56
R
T
VLV-632
2"-T56
VLV-633
2"-C56
F-11
3430 LMS-08-06
DISCHARGE HEADER
VLV-628
2"-X42D
DETERGENT
DRAIN TANK
PUMP
APP-009
T
2"-LMS-151R
VLV-606
2"-X42D
P
VLV-679
1"-X42D
VLV-607
3/4"-T58M
DS
3434 DS
A/B SUMP
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
LMS-###-+++
VLV-629
2"-T56
2"-LMS-151R
VLV-610
3/4"-T56
VLV-630
2"-C56
0
175
<37(L)
VLV-673
3/4"-X42D
P
VLV-674
3/4"-X42D
P
T
R
T
VLV-616
3/4"-T58M
3/4"x3/8"
SAMPLING
R
H
dPIA
1062
PI
1060
VLV-678
3/4"-X42D
2"-LMS-151R
VLV-605
3/4"-T58M
ACR
VLV-621
3/4"-T58M
DS
DS 3437
A/B SUMP
LICA
1059
VLV-677
3/4"-X42D
L
VLV-612
3/4"-T58M
H
LT
1059
P
0
T 175
R <37(L)
FC
DETERGENT
DRAIN TANK
ATK-007
AOV-617
1"-DA42R
VS
VS 3436
A/B EXHAUST
VLV-611
1"-T56
LMS
A-7
4098 LMS-08-04
WHT
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 7 of 9)
11.2-23
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
NAOH
3/4"-LMS-151N
3450
SUPPLY
VLV-731
3/4"-T56
P
DWS
DWS-01-01
DW
3/4"-LMS-151N
P
T
R
VLV-733
3/4"-C56
0
150
<37(L)
VLV-732
3/4"-T56
F-6
3451
EC6
ALL PIPING VALVES AND COMPONENTS IN THIS
SHEET ARE CLASSIFIED AS EQUIPMENT CLASS6.
T
VS
3452 VS
A/B EXHAUST
2"-LMS-151R
R
VLV-734
3/4"-X42D
LO
NOTE2
P
0
T 150
R <37(L)
NEUTRALIZING
AGENT
MEASURING
TANK
ATK-010
GLASS GAUGE
3448
SAMPLE SINK
3/4"-LMS-151N
SS CS
3/4"-LMS-151R
2"-LMS-102R
2"-LMS-102R
VLV-735C
3/4"-X42D
0
175
>=37(L)
0
175
>=37(L)
P
T
R
2"x3/4" 2"-LMS-151R
P
T
R
T
T
VLV-735B
3/4"-X42D
VLV-701
3/4"-T68M
L
LICA
1049
ACR
LT
1049
2"-LMS-161R
P
T
R
0
175
>=37(L)
P
T
R
VLV-735A
3/4"-X42D
T
150
175
>=37(L)
H
T
3/4"-LMS-161R
VLV-713
3/4"-C66
VLV-712
3/4"-X62D
3/4"x3/8"
VLV-715
3/8"-T66
3/4"-LMS-161R
VLV-711
3/4"-T68M
P
1-1/2"x3/4"
R
T
P
R
T
15
0
>= 175
37
(L)
150
150
<37(L)
VLV-718
3/4"-T66
P
T
R
P
T
R
150
175
>=37(L)
VLV-705
3/4"-X62D
FC
3/4"-LMS-151R
VLV-709
3/4"-X56N
R
VLV-707
3/4"-X62D
R
FI
1050
T
VLV-710
3/4"-C66
3/4
"-L
MS
-16
1R
3/4"-LMS-161R
VLV-706
3/4"-C66
150
150
R <37(L)
3/4"-LMS-161R
DWS
DWS-01-01
DW
F-6
3453
LOCAL
SAMPLE
PI
1050
NCS
AOV-708 P
3/4"-DA42R T
150
150
<37(L)
3/4"-LMS-161R
DS
4189 DS
A/B SUMP
NOTE1
DWS
G-6
3446 DWS-01-01
DW
P
T
R
3/4"-LMS-161R
P
0
T 175
R >=37(L)
VLV-716
3/4"-T66
P
R
VLV-714
3/4"-X62D
3/4"-LMS-161R
150
150
<37(L)
3/4"-LMS-161R
VLV-717
3/4"-C66
CHEMICAL
DRAIN TANK
ATK-009
VLV-702
3/4"-T68M
150
175
>=37(L)
VLV-703
3/4"-C66
P
P
T
R
DWS
F-6
3447 DWS-01-01
DW
P
T
R
T
3/4"-LMS-161R
R
VLV-751
3/4"-X62D
LMS
C-2
LMS-08-04 3572
A-WHT
R
VLV-704
3/4"-X62D
LMS
C-3
LMS-08-04 3591
B-WHT
T
VLV-735D
3/4"-X42D
3/4"-LMS-151R
LMS
C-8
LMS-08-04 3611
C-WHT
T
VLV-736
3/4"-X42D
LMS
C-9
LMS-08-04 3610
D-WHT
AOV-719
3/4"-DA62R
3449
TO DISPOSAL NOTE3
LMS
4096
VLV-720
3/4"-T66
CHEMICAL
DRAIN TANK
PUMP
APP-011
A-9
LMS-08-04
WHT
NCS
NOTES
1,DRAIN TO PORTABLE CONTAINER.
2,TANK ACCESSORIES(SIGHT GLASS)
3,DISPOSAL OPTIONS INCLUDING TRANSFERING
CONTENT TO CONTAINERS FOR OFFSITE PROCESSING
AND/OR ADDING SORBING AGENTS FOR DISPOSAL.
P 150
T 175
R >=37(L)
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
LMS-###-+++
CP COL 11.2(6)
Figure 11.2-201
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 8 of 9)
11.2-24
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
LMS
A-10
3643 LMS-08-06
UNIT3 WLS
DISCHARGE HEADER
EXISTING UNIT1
CIRCULATING WATER
EXISTING UNIT2
CIRCULATING WATER
LMS
3"-DA42R
3"-C42
3"-DA42R
3"-C42
3"-DA42R
3"-C42
3"-DA42R
3"-C42
3"-DA42R
UNIT4 WLS
DISCHARGE HEADER
EVAPORATION
POND
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
SQUAW CREEK
RESERVOR
CP COL 11.2(6)
Figure 11.2-201
LMS-###-+++
Liquid Waste Management System Piping and Instrumentation Diagram (Sheet 9 of 9)
11.2-25
Revision 0
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
Site-Specific Cost Analysis
CP COL 11.3(8) 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
System Description
STD COL 11.3(9) 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 0
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 (χ/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: 4.72E-02 mrem/yr for 5 mrem/yr, 8.55E-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. Calculated individual doses are
listed in Table 11.3-204. 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. 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.
11.3.3.3
Offsite Dose Calculation Manual
11.3-2
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(5) Replace the content of DCD Subsection 11.3.3.3 with the following.
The ODCM provides the methodology for calculating the radiation doses to
offsite personnel from released effluents. This document is site-specific as it must
take into consideration local meteorology, land use patterns, and distances to the
site boundary. The ODCM also provides the rationale for compliance with the
radiological effluent Technical Specifications and for the calculation of
appropriate setpoints for radioactive effluent monitors. The ODCM is developed
using the guidance of Nuclear Energy Institute (NEI) Technical Report 07-09, and
is implemented in accordance with the milestone listed in Table 13.4-201.
CPNPP Units 1 and 2 also have an existing ODCM (Reference 11.3-202) that is
to reflect the new reactor units.
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.
CP COL 11.3(5)
11.3(5) Offsite dose calculation manual
This COL item is addressed in Subsection 11.3.3.3.
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.
11.3-3
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
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.
11.3-202
Offsite Dose Calculation Manual for CPNPP Units 1 & 2, Revision
26.
11.3-4
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-8R
Input Parameters for the GASPAR II Code
Parameter
Value
3
χ/Q (s/m )
For maximum individual dose calculation
No Decay, Undepleted
2.28 Day Decay, Undepleted
8 Day Decay, Depleted
For population dose calculation
D/Q (1/m2)
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
11.3-5
4.40E-07
4.40E-07
3.90E-07
Section 2.3
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
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-9R
Calculated Doses from Gaseous Effluents (Sheets 1 of 2)
Dose (1)
5.77E-03
4.46E-02
3.69E-03
3.45E-02
Type of Dose
Gamma dose in air (mrad/yr)
Beta dose in air (mrad/yr)
Dose to total body (mrem/yr)
Dose to skin (mrem/yr)
Note:
1. Dose due to noble gases that include Ar-41
11.3-6
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-9R
Calculated Doses from Gaseous Effluents (Sheets 2 of 2)
Pathway
Dose to each organ (1) (mrem/yr)
Bone
Liver
Kidney
Thyroid
4.35E-02
4.35E-02
4.35E-02
4.35E-02
Lung
4.35E-02
5.70E-02
7.71E-02
1.59E-01
2.27E-02
3.53E-02
8.04E-02
8.79E-03
7.13E-03
1.28E-02
7.42E-03
6.16E-03
1.13E-02
5.40E-02
8.75E-02
1.82E-01
4.28E-01
9.43E-03
1.69E-02
3.87E-02
7.89E-02
6.42E-02
1.03E-01
2.13E-01
5.03E-01
1.23E-02
2.19E-02
4.63E-02
9.18E-02
4.27E-03
5.09E-03
5.74E-03
4.74E-03
2.98E-03
3.59E-03
3.08E-03
1.95E-03
2.32E-01
3.23E-01
6.16E-01
9.79E-01
9.83E-02
1.27E-01
2.23E-01
2.16E-01
GI-Tract
Ground
4.35E-02
Vegetable
Adult
3.44E-02
2.50E-01
3.09E-02
2.48E-02
Teen
4.75E-02
3.62E-01
4.76E-02
3.83E-02
Child
8.77E-02
7.99E-01
1.01E-01
8.53E-02
Meat
Adult
1.42E-02
3.70E-02
8.36E-03
7.68E-03
Teen
9.96E-03
3.09E-02
6.90E-03
6.35E-03
Child
1.33E-02
5.77E-02
1.23E-02
1.16E-02
Cow Milk
Adult
9.72E-03
5.06E-02
1.65E-02
1.14E-02
Teen
1.66E-02
9.04E-02
2.91E-02
2.02E-02
Child
3.72E-02
2.17E-01
5.95E-02
4.42E-02
Infant
7.52E-02
3.96E-01
1.19E-01
8.71E-02
Goat Milk
Adult
1.09E-02
6.92E-02
3.33E-02
1.78E-02
Teen
1.83E-02
1.21E-01
5.78E-02
3.07E-02
Child
3.97E-02
2.86E-01
1.07E-01
6.13E-02
Infant
7.90E-02
4.95E-01
2.09E-01
1.14E-01
Inhalation
Adult
1.91E-03
4.80E-04
1.87E-03
1.85E-03
Teen
1.92E-03
5.67E-04
1.91E-03
1.88E-03
Child
1.65E-03
6.72E-04
1.70E-03
1.66E-03
Infant
9.38E-04
2.97E-04
9.92E-04
9.60E-04
Total(2)
Adult
1.15E-01
4.51E-01
1.34E-01
1.07E-01
Teen
1.38E-01
6.48E-01
1.87E-01
1.41E-01
Child
2.23E-01
1.40E+00
3.25E-01
2.48E-01
Infant
1.99E-01
9.35E-01
3.72E-01
2.46E-01
Note:
1. Dose due to iodine, particulate, H-3 and C-14
2. Conservatively, both Cow Milk and Goat Milk are considered.
11.3-7
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-201
Population Distribution within 50 mi
for Population Dose Calculation
Distance(mi)
Direction
N
NNE
NE
ENE
E
ESE
SE
SSE
S
SSW
SW
WSW
W
WNW
NW
NNW
0-1
1-2
2-3
3-4
4-5
5-10
10-20
20-30
30-40
40-50
0
0
0
0
0
0
0
0
0
16
15
33
13
1
1
0
13
17
11
0
0
4
25
40
114
126
95
109
17
5
3
1
39
39
37
25
84
74
151
265
40
19
33
31
31
12
7
17
111
92
228
46
141
82
4644
136
29
1135
35
62
105
57
8
32
266
180
282
146
37
145
3679
1314
588
32
70
29
161
110
6
114
74921
12920
5473
5377
340
1162
1920
5917
1153
369
206
204
313
560
2295
1949
16318
12812
6950
4410
2658
836
500
382
1650
780
905
888
645
925
1243
6660
25429
12527
17815
67032
94985
3528
2778
5164
1003
2903
1528
40500
5302
1675
2789
5089
138627
125434
694190
134023
16681
7779
34161
14827
1320
451
1488
10651
2108
1691
2885
58611
30361
145586
1245916
270180
17747
18881
4755
4572
3655
6930
1424
5304
923
1495
1440
10106
11.3-8
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-202
Release Rates from the Evaporation Pond to Atmosphere
Isotope
Release Rate(1)
(Ci/yr)
2.35E-03
0.00E+00
6.50E-03
3.50E-04
2.50E-04
5.00E-05
9.50E-04
0.00E+00
0.00E+00
1.10E-04
1.75E-04
2.65E-04
1.40E-02
3.00E-05
4.00E-06
3.40E-05
2.20E-05
5.00E-06
1.45E-04
1.00E-04
5.00E-05
8.20E-04
8.50E-04
1.56E-03
1.55E-03
1.91E-02
Isotope
Na-24
Rh-106
P-32
Ag-110M
Cr-51
Ag-110
Mn-54
Sb-124
Fe-55
Te-129M
Fe-59
Te-129
Co-58
Te-131M
Co-60
Te-131
Ni-63
I-131
Zn-65
Te-132
W-87
I-132
Np-239
I-133
Rb-88
I-134
Sr-89
Cs-134
Sr-90
I-135
Sr-91
Cs-136
Y-91M
Cs-137
Y-91
Ba-137M
Y-93
Ba-140
Zr-95
La-140
Nb-95
Ce-141
Mo-99
Ce-143
Tc-99M
Pr-143
Ru-103
Ce-144
Rh-103M
Pr-144
Ru-106
H-3
Note:
1. The release rates are half of the total liquid release rates
that be shown in Table 11.2-10R.
11.3-9
Release Rate(1)
(Ci/yr)
1.95E-02
3.00E-04
3.60E-05
0.00E+00
3.90E-05
1.55E-04
1.25E-04
3.80E-05
2.00E-04
2.35E-04
1.55E-04
4.05E-04
4.45E-05
5.00E-04
3.90E-04
1.08E-02
1.00E-03
2.30E-04
2.45E-03
4.00E-03
3.00E-05
2.50E-04
3.95E-05
8.50E-04
8.50E-04
8.00E+02
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-203
Input Parameters for Dose Calculation from
Evaporation Pond
Parameter
Value
3
χ/Q (s/m )
For maximum individual dose calculation
No Decay, Undepleted
2.28 Day Decay, Undepleted
8 Day Decay, Depleted
For population dose calculation
D/Q (1/m2)
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
11.3-10
3.10E-06
3.10E-06
2.90E-06
Section 2.3
2.10E-08
Section 2.3
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
Table 11.3-201
Table 11.3-202
RG 1.109
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
Table 11.3-204
Calculated Doses from Evaporation Pond
CP COL 11.3(6)
Pathway
Dose to each organ (1) (mrem/yr)
Bone
Liver
Kidney
Thyroid
2.20E-02
2.20E-02
2.20E-02
2.20E-02
Lung
2.20E-02
1.10E-01
1.26E-01
1.99E-01
1.04E-01
1.19E-01
1.85E-01
1.50E-02
9.01E-03
1.10E-02
1.48E-02
8.91E-03
1.08E-02
4.38E-02
5.95E-02
1.00E-01
1.78E-01
3.61E-02
4.80E-02
7.58E-02
1.17E-01
8.15E-02
1.09E-01
1.80E-01
3.05E-01
7.51E-02
1.01E-01
1.59E-01
2.47E-01
5.68E-02
5.74E-02
5.08E-02
2.94E-02
7.43E-02
8.74E-02
7.74E-02
5.08E-02
3.29E-01
3.83E-01
5.63E-01
5.34E-01
3.26E-01
3.86E-01
5.30E-01
4.37E-01
GI-Tract
Ground
2.20E-02
Vegetable
Adult
2.87E-01
1.33E-02
1.16E-01
1.13E-01
Teen
3.38E-01
2.04E-02
1.38E-01
1.34E-01
Child
3.54E-01
4.68E-02
2.17E-01
2.09E-01
Meat
Adult
1.89E+00
2.97E-02
1.62E-02
7.12E-02
Teen
1.18E+00
2.50E-02
9.98E-03
5.62E-02
Child
7.22E-01
4.69E-02
1.21E-02
7.31E-02
Cow Milk
Adult
3.97E-02
7.69E-03
5.11E-02
4.18E-02
Teen
5.10E-02
1.36E-02
7.35E-02
5.73E-02
Child
7.53E-02
3.18E-02
1.18E-01
9.07E-02
Infant
1.13E-01
5.32E-02
2.00E-01
1.39E-01
Goat Milk
Adult
7.39E-02
2.24E-02
1.19E-01
9.15E-02
Teen
9.59E-02
3.97E-02
1.76E-01
1.27E-01
Child
1.48E-01
9.33E-02
2.83E-01
2.02E-01
Infant
2.23E-01
1.56E-01
4.93E-01
3.09E-01
Inhalation
Adult
5.85E-02
5.16E-04
5.68E-02
5.69E-02
Teen
5.91E-02
7.25E-04
5.75E-02
5.75E-02
Child
5.13E-02
9.89E-04
5.08E-02
5.09E-02
Infant
2.93E-02
5.44E-04
2.93E-02
2.93E-02
Total(2)
Adult
2.37E+00
9.57E-02
3.81E-01
3.97E-01
Teen
1.75E+00
1.21E-01
4.78E-01
4.54E-01
Child
1.37E+00
2.42E-01
7.02E-01
6.48E-01
Infant
3.87E-01
2.32E-01
7.45E-01
4.99E-01
Note:
1. Dose due to iodine, particulate and H-3
2. Conservatively, both Cow Milk and Goat Milk are considered.
11.3-11
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.3(6)
Table 11.3-205
Total Doses Due to Gaseous Effluent from Vent Stack
and Evaporation Pond
Pathway
GI-Tract
6.55E-02
Dose to each organ (1) (mrem/yr)
Bone
Liver
Kidney
Thyroid
6.55E-02
6.55E-02
6.55E-02
6.55E-02
Lung
6.55E-02
1.67E-01
2.03E-01
3.58E-01
1.27E-01
1.54E-01
2.65E-01
2.38E-02
1.61E-02
2.38E-02
2.22E-02
1.51E-02
2.21E-02
9.78E-02
1.47E-01
2.82E-01
6.06E-01
4.55E-02
6.49E-02
1.15E-01
1.96E-01
1.46E-01
2.12E-01
3.93E-01
8.08E-01
8.74E-02
1.23E-01
2.05E-01
3.39E-01
6.11E-02
6.25E-02
5.65E-02
3.41E-02
7.73E-02
9.10E-02
8.05E-02
5.28E-02
5.61E-01
7.06E-01
1.18E+00
1.51E+00
4.25E-01
5.14E-01
7.53E-01
6.53E-01
Ground
Vegetable
Adult
3.21E-01
2.63E-01
1.47E-01
1.38E-01
Teen
3.86E-01
3.82E-01
1.86E-01
1.72E-01
Child
4.42E-01
8.46E-01
3.18E-01
2.95E-01
Meat
Adult
1.90E+00
6.67E-02
2.46E-02
7.89E-02
Teen
1.19E+00
5.59E-02
1.69E-02
6.25E-02
Child
7.35E-01
1.05E-01
2.44E-02
8.47E-02
Cow Milk
Adult
4.94E-02
5.83E-02
6.76E-02
5.32E-02
Teen
6.76E-02
1.04E-01
1.03E-01
7.75E-02
Child
1.12E-01
2.49E-01
1.77E-01
1.35E-01
Infant
1.88E-01
4.49E-01
3.19E-01
2.26E-01
Goat Milk
Adult
8.48E-02
9.16E-02
1.52E-01
1.09E-01
Teen
1.14E-01
1.61E-01
2.34E-01
1.58E-01
Child
1.88E-01
3.79E-01
3.90E-01
2.63E-01
Infant
3.02E-01
6.51E-01
7.02E-01
4.23E-01
Inhalation
Adult
6.04E-02
9.96E-04
5.87E-02
5.88E-02
Teen
6.10E-02
1.29E-03
5.94E-02
5.94E-02
Child
5.29E-02
1.66E-03
5.25E-02
5.26E-02
Infant
3.02E-02
8.41E-04
3.03E-02
3.03E-02
Total(2)
Adult
2.48E+00
5.47E-01
5.16E-01
5.04E-01
Teen
1.88E+00
7.70E-01
6.64E-01
5.95E-01
Child
1.60E+00
1.65E+00
1.03E+00
8.96E-01
Infant
5.86E-01
1.17E+00
1.12E+00
7.45E-01
Note:
1. Dose due to iodine, particulate and H-3
2. Conservatively, both Cow Milk and Goat Milk are considered.
11.3-12
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
STD COL 11.3(9)
P 100
T 200
R >=37(G)
1"-GMS-122R
R
T
R
FC
P
PICA-233
1"-GMS-122R
EC6
VLV-042
2"-C36L
VLV-041
2"-X32D
2"x1"
1"-GMS-122R
DS
DS 3252
A/B SUMP
GMS
A-1
3246 GMS-03-02
WASTE GAS DRYER
T
P
VLV-044
1"-X32D
C-8
3953
VS
4095 VS
A/B EXHAUST.
AOV-039D
1"-DA42R
VLV-040D
1"-C36L
AOV-036D
3/4"-DA42R
P 150
T 200
R >=37(G)
FC
1"-GMS-122R
VLV-038D
3/4"-C36L
PCV-1152B
3/4"-DA42R
D-WASTE GAS
SURGE TANK
ATK-001D
VLV-037D
3/4"-X32D
AOV-036C
3/4"-DA42R
VLV-040C
1"-C36L
3/4"-GMS-122R
FC
3/4"x3/8"
2"-GMS-122R
P 150
T 200
R >=37(G)
GMS
A-2
3243 GMS-03-02
WASTE GAS DRYER
REMARK:
SS CS
R
P
1"-RV32
R
1"x3/4"
FC
T
VLV-031D
1"-C36L
VLV-030D
1"-X32D
FC
VLV-032D
3/4"-T58M
GMS
A-4
3221 GMS-03-01
VH
3/4"-GMS-122R
GMS
A-1
3245 GMS-03-02
WASTE GAS DRYER
PT
1152
PWS
F-3
PWS-01-01 3753
PMW
CGS
3/4"-GMS-122R EC6
CGS-01-01
EC5
N2
1"x3/4" VLV-034D VLV-033D 3/4"-CGS-122N
3/4"-X32D 3/4"-C36
P 150
T 120
R <37(G)
SS CS
FC
AOV-039C
1"-DA42R
ACR
1"-GMS-122R
CS SS
VS
4094 VS
A/B EXHAUST.
PICA
1152
VLV-038C
3/4"-C36L
P 150
T
200
R >=37(G)
FC
PCV-1151B
3/4"-DA42R
PI
1152
H
1"-GMS-122R
1"x3/4"
C-WASTE GAS
SURGE TANK
ATK-001C
P 100
T 200
R >=37(G)
VLV-021B
1"-C56
VLV-043D
1"-X32D
2"-GMS-122R
VLV-018B
3/4"-X42D
1"-GMS-122R
P
P 150
T 200
R >=37(G)
3/4"-GMS-122R
C-8
3962
3/8"-GMS-2521R
T
1"-RV32
R
VLV-037C
3/4"-GMS-122R 3/4"-X32D
AOV-036B
3/4"-DA42R
VLV-040B
1"-C36L
T
PCV-1152A
1"-DA42R
R
CGS
3/4"-GMS-122R EC6
CGS-01-01
EC5
1"x3/4" VLV-034C VLV-033C 3/4"-CGS-122N N2
3/4"-X32D 3/4"-C36
P 150
T 120
R <37(G)
VLV-027B VLV-026B
1"-C36L
1"-X32D
P 150
T 200
R >=37(L)
VLV-043C
1"-X32D
3/4"x3/8"
200
150
<37(L)
P
VLV-020B
1"-X42D
1"-GMS-151R
VLV-031C
1"-C36L
VLV-030C
1"-X32D
PCV-1151A
1"-DA42R
1"-GMS-122R
VLV-032C
3/4"-T58M
FC
P 150
T 200
R >=37(G)
3/4"-GMS-122R
T
P
SS CS
FC
AOV-039B
1"-DA42R
PT
1151
2"x1"
1"-GMS-151RVLV-012B
1"-X42D
VLV-010B
3/4"-T58M
SS CS
T
FC
VS
4093 VS
A/B EXHAUST.
PICA
1151
ACR
VLV-038B
3/4"-C36L
P 150
T 200
R >=37(G)
GMS
B-1
3242 GMS-03-02
WASTE GAS DRYER
PI
1151
H
1"-GMS-122R
FC
PCV-1150B
3/4"-DA42R
B-WASTE GAS
SURGE TANK
ATK-001B
1"x3/4"
3/4"-GMS-122R
C-8
3963
P
T
VLV-019B
3/4"-C56
R
1"-GMS-122R
2"-GMS-122R
VLV-037B
3/4"-GMS-122R 3/4"-X32D
3/4"x3/8"
T
3/8"-GMS-2521R
P
1"-RV32
VLV-030B
1"-X32D
FC
PCV-1150A
1"-DA42R
R
NCS
3/4"-GMS-151R R
LO
VLV-029
1"-X32D
CGS
3/4"-GMS-122R EC6
CGS-01-01
EC5
N2
1"x3/4" VLV-034B VLV-033B 3/4"-CGS-122N
3/4"-X32D 3/4"-C36
P 150
T 120
R <37(G)
T
NCS
B-WASTE GAS
COMPRESSOR
AEQ-001B
VLV-016B
3/4"-C56L
VLV-028
1"-X32D
P
2"x1-1/2"
R
R
150
1"-GMS-122R
1"-GMS-122R
PCV-1144
2"-RA52DB
PT
1144
R
VLV-032B
3/4"-T58M
PCV-1142
1"-RA52DB
T 200
R >=37(G)
P
0
T 150
R <37(L)
DS
DS 3235
A/B SUMP
VLV-013B
1"-X42D P
PIC
1144
2"-GMS-151R
2"-GMS-151R
DS
3234 DS
A/B SUMP
P 150
T 200
R >=37(G)
FC
FO
P
1"-GMS-151R
VLV-014B
1"-C56L
P 150
T 120
R <37(G)
2"x1"
EC6
2"-GMS-151R
P 100
T 200
R >=37(G)
P 150
T 200
R >=37(G)
EC6
VLV-009B
3/4"-X42D
3/4"-GMS-151R
VLV-008
3/4"-C36
3/4"-GMS-122N
CS SS
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET OTHER THAN SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
ACR
VLV-011B
3/4"-X42D
P
VLV-015B
3/4"-T58M
T
SS CS
SS CS
H
PICA
1142
CS SS
R
1"x3/4"
R
FO
T
3/4"-GMS-122N
EC5
EC5
PT
1142
P 100
T 200
R >=37(G)
P
VLV-007B
2"-X42D
2"-GMS-151R
2"-GMS-151R
2"-GMS-151R
VLV-007A
2"-X42D
SS CS
VLV-009A
3/4"-X42D
PCV-1143
2"-RA52DB
FO
VLV-010A
3/4"-T58M
CS SS
VLV-006
2"-X42D
VLV-002B
2"-C56L
1"-GMS-122R
GMS
C-5
3239 GMS-03-03
GA
EC4
T
1"-GMS-122R
CS SS
3/4"-GMS-151R
PT
1150
3/8"-GMS-2521R
B-8
2788
P
0
T 150
R <37(L)
SS CS
3/4"-GMS-122R
1"x3/4"
PICA
1150
3/8"-GMS-2521R
CVS
CVS-07-06
HT
P
E-6
3248
2"-GMS-151R
P 100
T 200
R >=37(G)
VLV-016A
3/4"-C56L
P
2"-GMS-151R
P 100
T 200
R >=37(G)
VLV-038A
3/4"-C36L
VLV-043A
1"-X32D
VLV-040A
1"-C36L
AOV-036A
3/4"-DA42R
AOV-039A
1"-DA42R
VLV-037A
3/4"-GMS-122R 3/4"-X32D
P 150
T
200
R >=37(G)
1"-GMS-122R
FC
PCV-1149B
3/4"-DA42R
1"-GMS-122R
3/8"-GMS-2521R
A-WASTE GAS
SURGE TANK
ATK-001A
3/4"-GMS-122R
PT
1143
SS CS
FC
3/8"-GMS-2521R
P
ACR
3/4"-GMS-122R
T
PI
1150
1"x3/4"
R
T
B-8
3952
VS
4092 VS
A/B EXHAUST.
2"-GMS-122R
P 150
T 200
R >=37(G)
FC
1"-GMS-122R
P 150
T 200
R >=37(G)
VLV-032A
3/4"-T58M
GMS
GMS-03-03
GA
3/4"-GMS-151R
1"x3/4"
LO
VLV-035
3/4"-X32D
SS CS
3/4"x3/8"
R
R
P 150
T 200
R >=37(L)
H
1"-RV32
PT
1149
VLV-031A
1"-C36L
VLV-030A
1"-X32D
FC
ACR
1"-GMS-122R
PICA
1149
PCV-1149A
1"-DA42R
PI
T
CGS
3/4"-GMS-122R EC6
CGS-01-01
EC5
N2
1"x3/4" VLV-034A VLV-033A
P 150
3/4"-X32D 3/4"-C36
T 120
3/4"-CGS-122N R
<37(G)
VLV-027A VLV-026A
1"-C36L 1"-X32D
1"-GMS-151R
VLV-020A
1"-X42D
2"-GMS-151R
CGS
D-6
3964 CGS-01-01
N2
PIC
1143
VLV-019A
3/4"-C56
VLV-021A
1"-C56
CS SS
EC6
P 100
T 200
R >=37(G)
VLV-014A
1"-C56L
2"x1-1/2"
3/4"-GMS-151R
VLV-018A
3/4"-X42D
SS CS
VLV-004A VLV-003A P 100 VLV-003B VLV-004B
1"-C56L 1"-X32D T 200 1"-X32D 1"-C56L
R >=37(G)
LO
LO
VLV-005
2"-X42D
P 100
T 200
R >=37(G)
VLV-015A
3/4"-T58M
P
VLV-011A
3/4"-X42D
VLV-012A
1"-GMS-151R 1"-X42D
2"x1"
PCV-1141
VLV-013A
1"-RA52DB P 150 1"-X42D
T 200
R >=37(G)
1"-GMS-122R
P 200
T 150
R <37(L)
P
2"-GMS-151R
1"x3/4"
2"x1"
P 100
T 200
R >=37(G)
1"-GMS-122R
1"-GMS-151R
A-WASTE GAS
COMPRESSOR
AEQ-001A
A-7
3247
1149
PT
1141
ACR
FO
1"-GMS-122R
P
H
H
PICA
1141
NCS
GMS
GMS-03-01
VH
1"-GMS-151R
1"-GMS-151R
C-1
2772
VLV-001B
2"-X42D
1"-GMS-151R
CVS
CVS-07-06
HT
EC4
GMS
D-1
GMS-03-01 3247
A-WASTE GAS COMP.
P
NCS
PWS
E-4
3752 PWS-01-01
PMW
SMS
B-1
SMS-01-01 3982
BREAK UP PIPE
1"-GMS-151R
2"-GMS-151R
VLV-002A
2"-C56L
1"x3/4" VLV-017A
1"-X32D
P 150
T 200
R >=37(G)
P
1"-GMS-122R
2"x1"
GMS
D-1
3232 GMS-03-02
VCT
CS SS
GMS
G-1
GMS-03-02 3249
CHARCOAL BED
3/4"-GMS-151R
VLV-031B
1"-C36L
VLV-001A
2"-X42D
1"-GMS-122R
VLV-017B
1"x3/4" 1"-X32D
3/4"-GMS-151R
2"x1"
2"-GMS-151R
EC6
EC4
GMS
D-6
3233 GMS-03-03
GA
VLV-043B
1"-X32D
B-1
CVS-07-06
HT
1"-GMS-151R
CVS
D-11
2800 CVS-07-07
B.A. EVAP.
P
CS SS
CVS
2794
C-9
LMS-08-01
CVDT
CS SS
LMS
3222
P 150
T 200
R >=37(G)
GMS
D-11
3221 GMS-03-01
B-WASTE GAS COMP.
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
GMS-###-+++
1"-GMS-122R
PCV-233
1"-RA32RB
Figure 11.3-201
Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 1 of 3)
11.3-13
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
1"x3/4"
FC
PCV-122B
3/4"-IA52RZ
PCV-1162
3/4"-RA52RZ
ACR
FC
T
P
HCV-1162
3/4"-RA52RZ
B-1
3254
3/8"-GMS-2521R
XIA
1165A
XIA
1165B
CS SS
3/4"x3/8"
150
200
<37(G)
TIA
1167
3/8"-GMS-2521R
3/8"-GMS-2521N
PIA
1167
3/4"-GMS-151R
3/4"-GMS-122N
VLV-164
3/4"-X42D
P
T
R
DS
DS 3260
A/B SUMP
VLV-135B
3/4"-T56Z
T
H
ACR
H
ACR
XE
1165B
NOTE4
H
ACR
H
ACR
TE
1167
3/4"-GMS-151R
PT
1167
VLV-149
1"-C36L
P
0
T 200
R >=37(G)
RCV-072B
1"-DA32R
3/4"-GMS-151R
NOTE4
RCV-072A
1"-DA32R
VLV-148
1"-X42D
1"x3/4"
1"x3/4"
PCV-1169A
3/4"-RA52RZ
P 150
T 200
R >=37(G)
VLV-144
3/4"-X42D
72
RE
72
SS CS
EC6
H
ACR
1"x3/4"
VLV-142 3/4"-GMS-122N
3/4"-X32D
P
T
R
150
120
<37(G) EC5
3/8"-GMS-2521R
1"-GMS-151R
RICA
3/4"-GMS-151R
0
300
<37(G)
P
T
R
P
T
R
0
150
<37(L)
DS
3271 DS
A/B SUMP
P 150
T 200
R >=37(G)
NOTE4
3/4"-GMS-151R
VLV-136
3/4"-T56Z
NOTE5
P 150
T 200
R >=37(G)
B-CHARCOAL
BED
AEQ-004B
P 150
T 200
R >=37(G)
NOTE1
NOTE1
3/4"-GMS-151R
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.
EC6
ALL PIPING VALVES AND COMPONENTS
IN THIS SHEET UNLESS SPECIFIED
ARE CLASSIFIED AS EQUIPMENT CLASS 6.
NOTE5
REMARK:
3/4"-GMS-151R
3/4"-GMS-151R
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
VLV-138A
3/4"-T56Z
FC
4"-VS-151N
0
300
<37(G)
A-CHARCOAL
BED
AEQ-004A
NOTE5
VLV-138B
3/4"-T56Z
CS SS
H
D-CHARCOAL
BED
AEQ-004D
VLV-139
3/4"-X42D
FC
P
72
R
VLV-157
3/4"-C56L
C-6
3951
VLV-141
3/4"-X42D
FC
1"-VS-122R
RIA
T
VLV-143
3/4"-C56
PCV-1169B
3/4"-RA52RZ
PT
1169
R
3/4"-GMS-151R
FC
HVAC FAN SWITCH SIGNAL
PLANT STACK MONITOR SIGNAL
VS
VS 3257
A/B EXHAUST.
CS SS
RCV-072C
1"-DA32R
AOV-145
3/4"-DA42R
1"-GMS-122R
ACR
VLV-147
3/4"-T58M
GMS
A-7
GMS-03-01 3249
WASTE GAS COMP.
FC
PIC
1169
FC
T
C-6
3949
VLV-134
3/4"-T58M
P 150
T 200
R >=37(G)
VLV-137
3/4"-T56Z
NOTE4
CGS
CGS-01-01
N2
P
EC5
FC
3/4"-GMS-122N
CGS
CGS-01-01
N2
AOV-151
3/4"-DA32R
VLV-161
3/4"-X42D
NOTE5
C-1
3255
150
200
>=37(L)
3/4"-GMS-151R
XE
1165A
3/4"-GMS-151R
C-CHARCOAL
BED
AEQ-004C
GMS
GMS-03-03
GA
ACR
150
120
<37(G)
T
R
NCS
3/8"-GMS-2521R
OXYGEN GAS
ANALYZER
AEQ-003
3/4"-GMS-151R
P 150
T 120
EC5 R <37(G)
CGS
E-2
3950 CGS-01-01
N2
R
AOV-133
3/4"-DA42R
NOTE6
P 150
T 200
R >=37(G)
P
T
R
4"-VS-151N
FC
GMS
GMS-03-03
GA
P
T
R
P 150
VLV-156 T 200
3/4"-X42D R >=37(G)
VS
VS 3269
A/B EXHAUST
P
T
R
O2
HIC
1162
ACR
PCV-1163 3/4"-GMS-151R PCV-122C
3/4"-RA52RZ
3/4"-IA52RZ
VLV-114
1"-X42D
0
300
<37(G)
P
T
R
3268
0
150
<37(L)
P
FC
FT
1162
EC5
R
GMS
A-4
GMS-03-01 3232
A-WASTE GAS COMP.
VLV-113
3/4"-T56Z
P 100
T 200
R >=37(G)
FC
FIA
1162
3/4"-GMS-151R
P 150
T 200
R >=37(G)
ACR
PT
1162
VLV-110
3/4"-C56L
VLV-109
3/4"-X42D
H
VLV-155 VLV-154
3/4"-C56 3/4"-X32D
3/4"-GMS-151N
VLV-131
3/4"-X42D
HCV-1161
3/4"-RA52RZ
H
SS CS
VLV-132
3/4"-C56L
PIC
1163
FC
FC
FIA
1160
FT
1160
3/4"-GMS-151N
ACR
3/4"-GMS-151R
R
PIC
1162
SS CS
VLV-153 VLV-152
3/4"-C56 3/4"-X32D
P 150
T 200
R >=37(G)
VLV-111
3/4"-T56Z
NCS
VLV-117
3/4"-T56B
AOV-116
3/4"-DA42R
WASTE GAS
DRYER
AEQ-002
FT
3/4"-GMS-151R
VLV-108
3/4"-T56Z
VLV-112
3/4"-C56L
HIC
1161
ACR
1161
T
R
H
3/4"-GMS-151R
PCV-1161
3/4"-RA52RZ
T
VS
VS 3263
A/B EXHAUST
VLV-135A
3/4"-T56Z
1161
AOV-115
3/4"-DA42R
P
P 150
T 200
R >=37(G)
1161
P 150
T 200
R >=37(G)
FC
3/4"-GMS-151R
FIA
VLV-107
3/4"-T56Z
PT
VLV-106 3/4"-GMS-151R
3/4"-C56L
VLV-105
3/4"-X32D
P
15
T 120
R >=37(G)
PCV-122A
3/4"-IA52RZ
P
FC
FC
3/4"-GMS-151R
3/4"x3/8" 3/4"x3/8"
ACR
FT
1156
CS SS
HCV-1156
3/4"-RA32RB
VS
VS 3261
A/B EXHAUST
4"-VS-151N
ACR
VLV-165 P
3/4"-C56L T
T
DS
DS 3270
A/B SUMP
ACR
3/8"-GMS-2521N VLV-163
3/4"-X42D
1161
FIA
1156
VS
VS 3262
A/B EXHAUST
3/4"-GMS-151R
PIC
P 150
T 200
R >=37(G)
CVS
D-11
2804 CVS-07-07
B.A.EVAP
H
VLV-162
3/4"-C56L
VLV-102
3/4"-X32D
PCV-1156 3/4"-GMS-122R
3/4"-RA32RB
FC
HIC
1156
FC
VCT
NOTE3
CVS
A-8
2264 CVS-07-04
VCT
PT
1156
FC
3/4"-GMS-122R VLV-101
3/4"-X32D
P 150
T 200
R >=37(G)
ACR
3/4"-VS-122R
3/4"-GMS-122R
PIC
1156
GMS
E-6
3258 GMS-03-03
GA
VLV-104
3/4"-T58M
3/4"-GMS-122R
EC6
T
3/4"-GMS-122R
GMS
G-6
3245 GMS-03-01
B-WASTE GAS SURGE
TANK
GMS
G-3
3242 GMS-03-01
A-WASTE GAS SURGE
TANK
R
VLV-103
3/4"-C36
GMS
G-11
3243 GMS-03-01
D-WASTE GAS SURGE
TANK
GMS
G-8
3246 GMS-03-01
C-WASTE GAS SURGE
TANK
150
120
<37(G)
3/4"-GMS-151R
P
T
R
CGS
C-6
EC5
3948 CGS-01-01
N2
3/4"-GMS-122N
GMS-###-+++
VLV-140
3/4"-X42D
LC
VLV-146
3/4"-X42D
STD COL 11.3(9)
Figure 11.3-201
Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 2 of 3)
11.3-14
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
EC6
3/8"-GMS-2521R
SOV-219A
3/8"-TS52S
EC6
R
T
R
S
FC
3/8"-GMS-2521R
EC6
P 150
T 200
R >=37(G)
GMS-S208
EC4
P
T
T
EC6
R
S
R
3/8"-GMS-2521R
EC6
P 15
T 200
R >=37(G)
P
T
S
EC4
FC
T
T
P
T
P
SOV-224
3/8"-TS52S
EC4
R
T
P
LMS
B-9
LMS-08-01 3278
CVDT
P 15
T 120
R >=37(G)
3/8"-GMS-2521R
STD COL 11.3(9)
Figure 11.3-201
EC6
EC5
EC5
3/4"-GMS-122N P
150
T 120
R <37(G)
P 150
T 120
R <37(G)
3/4"-GMS-122N
15
T 120
R <37(G)
VLV-254 3/8"-GMS-2521R
3/4"-X42D
EC6
VLV-255 3/8"-GMS-2521R
3/4"-X42D
EC5 P
CGS
CGS-01-01
H2
3544
H2
A-9
3956
EC6
P 100
T 200
P
R >=37(G) 3/4"x3/8"
FC
DS
3281 DS
A/B SUMP
CVS
C-4
CVS-07-06 2781
B-HOLDUP TANK
GMS
A-4
3/4"-GMS-151R
GMS-03-01 3233
A-WASTE GAS COMP.
VLV-236A VLV-235A
3/4"-C56L 3/4"-X42D
AOV-234
3/4"-DA42R
GMS
A-7
3/4"-GMS-151R
GMS-03-01 3248
B-WASTE GAS COMP.
VLV-236B VLV-235B
3/4"-C56L 3/4"-X42D
FC
GMS
A-5
GMS-03-02 3258
WASTE GAS DRYER
DS
3282 DS
A/B SUMP
EC6
3/4"-GMS-151R
P
P
3/4"-GMS-151R
VLV-232
3/4"-X42D
T
3/8"-GMS-2521R
T
P
P 15
T 120
R >=37(G)
T
NOTE1
VLV-238
3/4"-C56L
P 150
T 200
R >=37(G)
AOV-237
3/4"-DA42R
WASTE GAS
SAMPLE
VESSEL
3/8"-VS-2521R
A-11
1856
EC5
3292
O2
3/4"x3/8" EC6
3/4"x3/8"
3/4"x3/8"
EC6 3/4"x3/8"
3/8"-GMS-2521R VLV-233 EC5 P
T
3/4"-X42D
DS
3548 DS
A/B SUMP
R
T
P
3/8"-GMS-2521R
VLV-232
3/4"-X42D
P 15
T 120
R <37(G)
VS
3291 VS
A/B EXHAUST
B-WASTE GAS
ANALYZER
AEQ-005B
VLV-231 3/8"-GMS-2521R
3/4"-X42D
P 15
T 120
R <37(G)
P 15
T 120
R >=37(L)
CGS
A-2
3947 CGS-01-01
N2
EC6
CS SS
3/4"x3/8"
CGS
A-2
3968 CGS-01-01
N2
DS
DS 3293
A/B SUMP
R
3/4"x3/8"
DS
3280 DS
A/B SUMP
RCS
RCS-03-02
PRT
VLV-223
3/8"-PR52
EC6
GMS
G-1
GMS-03-01 3239
WASTE GAS SURGE
TANK
CS SS
3/4"x3/8"
3/4"x3/8"
P 200
T 400
FC R >=37(G)
3/8"-GMS-2521R
SOV-219C
3/8"-TS52S
P
GMS-S207B
3/8"-GMS-2521R
SOV-221 P
3/8"-TS52S
GMS-S207C
P 15
T 200
R >=37(G)
SOV-219B
3/8"-TS52S
S
FC
EC4
T
3/4"x3/8"
EC5
EC5
3/4"-GMS-122N P
150
T 120
R <37(G)
15
120
3290
H2
R <37(G)
VLV-234 3/8"-GMS-2521R
3/4"-X42D
T
FC
SOV-217
3/8"-TS52S
P 15
T 120
R >=37(L)
EC6
EC4
P
T
GMS-S206
3/8"-GMS-2521R
VLV-231
3/4"-X42D
FC
P
P
VLV-252
3/4"-X42D
3/4"x3/8" 3/4"x3/8"
T
S
VLV-218A
3/4"-X42D
P
P 25
T 200
R >=37(G)
S
P 15
T 200
R >=37(G)
T
T
3/4"x3/8"
R
3/4"x3/8"
EC6
P 15
T 120
R >=37(G)
T
R
GMS-S207A
VLV-210
3/4"-X42D
3/4"x3/8"
VLV-207
3/4"-X42D
VLV-213
3/4"-X42D
3/4"x3/8"
3/8"-GMS-2521R
SOV-215 P
3/8"-TS52S
R
DS
DS 3547
A/B SUMP
CS SS
3/4"x3/8"
DS
DS 3287
A/B SUMP
T
GMS-S204
VLV-211
3/8"-PR52
SOV-212
3/8"-TS52S
EC6
3/8"-GMS-2521R VLV-253
3/4"-X42D
DS
3279 DS
A/B SUMP
VS
3543 VS
A/B EXHAUST
A-WASTE GAS
ANALYZER
AEQ-005A
EC6
CVS
C-7
2784 CVS-07-06
C-HOLDUP TANK
P
S
FC
P 150
T 200
FC R >=37(G)
P
SMS
C-6
SMS-01-01 3296
B-SPENT RESIN
STORAGE TANK
3/4"x3/8" EC6
VLV-251 3/8"-GMS-2521R
3/4"-X42D
VLV-235 3/8"-GMS-2521R
3/4"-X42D
DS
DS 3286
A/B SUMP
VLV-214
3/8"-PR52
EC4
P
T
3/4"x3/8"
EC5
P
15
T 120
R <37(G)
CS SS
3/4"x3/8"
CVS
E-11
2805 CVS-07-07
B.A.EVAP.
P 75
T 200
R >=37(G)
T
3/8"-GMS-2521R
3/4"x3/8"
DS
DS 3285
A/B SUMP
S
VLV-220
3/4"-X42D
CVS
C-1
2779 CVS-07-06
A-HOLDUP TANK
R
T
R
GMS-S205
3/4"x3/8"
DS
DS 3284
A/B SUMP
T
VLV-218C
3/4"-X42D
CVS
A-8
2267 CVS-07-04
VCT
P
VLV-202B
3/8"-PR52
3/8"-GMS-2521R
SOV-209 P
3/8"-TS52S
3/8"-GMS-2521R
3/4"x3/8"
DS
DS 3283
A/B SUMP
FC
VLV-208
3/8"-PR52
SOV-203B
3/8"-TS52S
3/4"x3/8"
S
GMS-S203
P 150
T 200
R >=37(G)
P
3/4"x3/8"
T
GMS
F-4
3255 GMS-03-02
CHARCOAL BED
FC
3/8"-GMS-2521R
DS
3295 DS
A/B SUMP
O2
GMS-S201B
P 15
T 120
R <37(G)
3/8"-VS-2521R
3542
P 150
T 150
R >=37(G)
VLV-201B
3/4"-X42D
S
R
P
VLV-233
3/4"-X42D
T
T
SMS
C-2
SMS-01-01 3277
A-SPENT RESIN
STORAGE TANK
3/4"x3/8"
R
VLV-216
3/4"-X42D
T
SOV-206 P
3/8"-TS52S
VLV-218B
3/4"-X42D
P
VLV-202A
3/8"-PR52
VLV-222
3/4"-X42D
VLV-204
3/4"-X42D
VLV-205
3/8"-PR52
SOV-203A
3/8"-TS52S
3/8"-GMS-2521R
VLV-204
3/4"-X42D
DS
DS 3294
A/B SUMP
3/4"x3/8"
P 150
T 200
R >=37(G)
P
S
FC
EC6
GMS-S201A
3/4"x3/8"
3/4"-GMS-151R
T
GMS-S202
GMS
C-7
3254 GMS-03-02
WASTE GAS DRYER
P 150
T 150
FC R >=37(G)
VLV-201A
3/4"-X42D
S
3/8"-GMS-2521R
P 150
T 120
R <37(G)
3/4"-GMS-122N
CGS
CGS-01-01
H2
B-9
3961
REMARK:
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
GMS-###-+++
Gaseous Waste Management System Piping and Instrumentation Diagram (Sheet 3 of 3)
11.3-15
Revision 0
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
Other Design Considerations
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
Site-Specific Cost-Benefit Analysis
STD COL 11.4(6) Replace the second paragraph in DCD Subsection 11.4.1.5 with the following.
The solid waste management system (SWMS) is designed to handle spent resin,
sludge, oily waste, spent filters, and dry active waste including contaminated
clothing, broken equipment, and maintenance items that cannot be easily
decontaminated and reused. The SWMS provides staging areas and handling
equipment for waste packaging and storage for the above wastes. Any liquid and
gaseous wastes resulting from the solid waste handling operation are collected
and returned to LWMS and GWMS, for processing. As such, there is no unique
direct release pathway from the solid waste handling operation to the
environment, and a cost benefit analysis for the SWMS is included in the
consideration of the LWMS and GWMS.
11.4.1.6
Mobile or Temporary Equipment
CP COL 11.4(5) Add the following text at the last sentence in DCD Subsection 11.4.1.6.
CP COL 11.4(7)
The de-watering station is contracted for vendor services.
11.4-1
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.4.2.1.1
Dry Active Wastes
CP COL 11.4(1) Replace the last paragraph in DCD Subsection 11.4.2.1.1 with the following.
Descriptions of wastes other than normally accumulated non-radioactive wastes
such as wasted activated carbon from GWMS charcoal beds, solid wastes
coming from component (Steam generator, Reactor vessel etc.) replacement
activities, and other unusual cases will be described in the process control
program and will be implemented in accordance with the milestone listed in Table
13.4-201.
11.4.2.2.1
Spent Resin Handling and De-watering Subsystem
STD COL 11.4(8) Add the following text at the end of the second paragraph in DCD Subsection
11.4.2.2.1.
The P&ID for the SWMS is provided in Figure 11.4-201.
11.4.2.3
Packaging, Storage, and Shipping
CP COL 11.4(1) Replace the last sentence of the fourth paragraph in DCD Subsection 11.4.2.3
with the following.
A common radwaste interim storage facility is provided between Units 3 and 4
and is designed to store classes A, B, and C wastes from all four CPNPP units
for up to 10 years. The common radwaste facility is designed to maintain onsite
and offsite radiological doses within the limits in 10 CFR Part 20 and to maintain
occupational exposures ALARA. This common radwaste interim storage facility
reflects the site-specific waste volume reduction requirements and the current
waste disposal strategy of the State of Texas. As design proceeds, the interim
storage facility design may be revised to meet future waste acceptance and
disposal criteria.
The common radwaste interim storage facility also includes a separate storage
area for mixed waste and temporary staging of large equipment items for
maintenance.
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
11.4-2
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
that are outside of the Atlantic Compact, and that the disposal facility in Clive,
Utah, is still accepting Class A waste from out of state. Class B and C waste
constitutes a small fraction of the total low level radioactive waste that will be
generated by CPNPP.
CPNPP Units 3 and 4 are scheduled to load fuel and begin commercial operation
no earlier than 2016. Therefore, these units will not be generating Class B and C
waste prior to that time. Although the interim storage facility is designed to store
the Class A, B and C wastes generated by CPNPP Units 1, 2, 3, and 4 for 10
years, the facility could store waste for a proportionally longer period of operation
if only Class B and C wastes were to be stored in that facility. It is likely that
another disposal facility will be available that will accept Class B and C waste
from sources in Texas well before the storage space in the interim storage facility
is filled. In particular, in 2004, Waste Control Specialists applied for a license
from the Texas Commission on Environmental Quality to develop a disposal
facility in Andrews County, Texas, for Class A, B, and C waste. In August 2008
Waste Control Specialists received a draft license from the Texas Commission
on Environmental Quality. According to its website, Waste Control Specialists
plans on opening the Andrews County site in about December of 2010.
Notwithstanding this, if additional storage capacity were eventually to be needed,
CPNPP could expand the interim storage facility or construct additional storage
facilities in accordance with applicable NRC guidance, such as Regulatory Issue
Summary 2008-12, Considerations for Extended Interim Storage of Low-Level
Radioactive Waste by Fuel Cycle and Materials Licenses, and Standard Review
Plan 11.4.
11.4.3.2
Process Control Program
CP COL 11.4(3) Replace the content of DCD Subsection 11.4.3.2 with the following.
This subsection adopts NEI 07-10, which is currently under review by the NRC
staff. 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.
11.4-3
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
11.4.4.5
Mobile De-watering System
CP COL 11.4(4) Replace the last sentence in DCD Subsection 11.4.4.5 with the following.
CP COL 11.4(7)
The de-watering station is vendor supplied and operated with the specific
requirements and layout based on vendor specifications. Operating procedures
will be developed and implemented with PCP so that the guidance and
information in IE Bulletin 80-10 (Reference 11.4-29) is followed. The milestone
for procedure implementation is listed in Table 13.4-201.
11.4.8
Combined License Information
Replace the content of DCD Subsection 11.4.8 with the following.
CP COL 11.4(1)
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.
11.4-4
Revision 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
LMS
F-9
3656 LMS-08-05
D-WASTE EFFLUENT
DEMI.
LMS
F-6
3652 LMS-08-05
C-WASTE EFFLUENT
DEMI.
SFS
F-1
1986 SFS-02-02
A-SFP DEMI.
CVS
G-6
2232 CVS-07-03
CATION BED DEMI.
SFS
F-5
1985 SFS-02-02
B-SFP DEMI.
CVS
G-2
2210 CVS-07-03
A-MIXED BED DEMI.
LMS
F-2
3659 LMS-08-05
ACTIVATED CARBON
FILTER
CVS
F-9
2225 CVS-07-03
A-DEBORATING DEMI.
CVS
D-3
2801 CVS-07-07
B.A.EVAP. FEED DEMI.
CVS
G-2
2222 CVS-07-03
B-MIXED BED DEMI.
LCV-1112
2"-DA42R
T
2"-SMS-151R
P
A-5
3277
3/8"-SMS-2521R
PIA
1105
3/4"-SMS-151R
P
T
R
P
2"-SMS-151R
P
T
R
3/4"x3/8"
P
2"-SMS-151R
3/4"-SMS-151R
VLV-035B
3/4"-X42D
2"-SMS-151R
P
T
R
200
150
>=37(L)
P
T
R
200
150
>=37(L)
VLV-001B
2"-X42D
P
TIA
FC
NOTE7
LICA
1105
VLV-002B
3/4"-T58M
NOTE3
B-SPENT RESIN
STORAGE TANK
ATK-001B
ACR
L
TE
NOTE2
NOTE1
H
LT
2"-DA42R
NOTE4
FC
2"-SMS-151R
3/8"-SMS-2521R
LT
1106
P 150
T 150
R >=37(L)
LICA
1106
OPTIONAL VENDOR EQUIPMENT
H
ACR
L
P 150
T 150
R >=37(L)
VLV-003A
3/4"-T58M
P
VLV-003B
3/4"-T58M
1"-SMS-151R
1"-SMS-151R
DEWATERING
PUMP
200
150
>=37(L)
LT
1105
P
EC6
ALL PIPING VALVES AND COMPONENTS IN THIS
SHEET ARE CLASSIFIED AS EQUIPMENT CLASS6.
VLV-017B
3/4"-X42D
VLV-016B
3/4"-X42D
HIC
1103
ACR
FC
HCV-1103
2"-RA52R
Figure 11.4-201
ACR
P
T
R
FE
1103
VLV-012
3/4"-T58M
P
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.
FT
1103
VLV-013
3/4"-T58M
T
FI
1103
VLV-014B
2"-C56
R
2"-SMS-151R
LC
3/4"-SMS-151R
P
3/4"-SMS-151R
VLV-015B
2"-X42D
P
T
R
2"x1"
200
150
>=37(L)
P
VLV-018B
1"-X42D
T
P
2"x1"
LC
R
P
VLV-037B
3/4"-X42D
AOV-033B
1"-DA42R
VLV-016A
3/4"-X42D
P
VLV-036B
1"-X42D
P
VLV-014A
2"-C56
T
2"-SMS-151R
R
DS
DS 1982
A/B SUMP
VLV-036A
1"-X42D
LC
3/4"-SMS-151R
P
3/4"-SMS-151R
VLV-015A
2"-X42D
P
T
R
200
150
>=37(L)
P
VLV-018A
1"-X42D
T
P
2"x1"
LC
R
P
VLV-037A
3/4"-X42D
FC
P
2"x1"
STD COL 11.4(8)
LMS
A-6
3999 LMS-08-04
WHT
FC
EC6
AOV-033A
1"-DA42R
VLV-031
1"-C56
B-5
3296
VLV-017A
3/4"-X42D
1"-SMS-151R
CAS
SA
ACR
VLV-005B
2"-X42D
NOTE1
CS SS
PIA
1106
VLV-001A
2"-X42D
VLV-002A
3/4"-T58M
AOV-032A
1"-DA42R
FC
GMS
GMS-03-03
GA
200
150
>=37(L)
A-SPENT RESIN
STORAGE TANK
ATK-001A
EC5
CVS
F-5
CVS-07-03 2237
PMW SUPPLY.
VS
3985 VS
A/B EXHAUST
LCA
2"-SMS-151R
VLV-035A
3/4"-X42D
T
H
ACR
VLV-005A
2"-X42D
CGS
D-5
3967 CGS-01-01
N2
PT
1106
AOV-023B
2"-DA42R
P
3/4"x3/8"
EC4
VLV-041
2"-T56
FC
AOV-023A
2"-X42D
GMS
GMS-03-03
GA
EC6
3/4"-T58M
T
PT
1105
P
VLV-021B
2"-RV42NB
P
H
P
VLV-021A
2"-RV42NB
200
150
<37(L)
P
T
R
VLV-042
2"-C56
VLV-022B
3/4"-T58M
T
2"-SMS-151R
AOV-026
2"-DA42R
T
2"-SMS-151R
NOTE5
VLV-043
2"-X42D
2"-SMS-151R
VLV-025
3/4"-T58M
200
150
>=37(L)
AOV-032B
1"-DA42R
ACR
VLV-024
3/4"-T58M
LT
1112
NOTE8
SGS
F-9
SGS-03-02 3501
B-SGBD MIX BED DEMI.
NOTE6
FC
LCA
1112
DS
DS 3983
A/B SUMP
QE
1107
2"-SMS-151R
A-7
3982
VLV-022A
3/4"-T58M
GMS
GMS-03-01
VH
200
150
>=37(L)
P
T
R
VLV-006
2"-X42D
P
T
R
NOTE8
SGS
F-6
SGS-03-02 3490
A-SGBD MIX BED DEMI.
R
2"-SMS-151R
2"-SMS-151R
NOTE8
SGS
B-6
SGS-03-02 3484
A-SGBD CATION BED
DEMI.
NOTE8
SGS
B-9
SGS-03-02 3495
B-SGBD CATION BED
DEMI.
CVS
F-11
2227 CVS-07-03
B-DEBORATING DEMI.
VLV-061
2"-X42D
LMS
C-9
3408 LMS-08-05
B-WASTE EFFLUENT
DEMI.
LMS
C-6
3407 LMS-08-05
A-WASTE EFFLUENT
DEMI.
REMARK:
2"-SMS-151R
200
150
>=37(L)
VLV-011
2"-X42D
PWS
PWS-01-01 1981
PMW
SYSTEM NAME OF EQUIPMENT AND
VALVE NUMBERS ARE OMITTED IN
THIS DRAWING.
SMS-###-+++
Solid Waste Management System Piping and Instrumentation Diagram
11.4-5
Revision 0
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
Reliability and Quality Assurance
CP COL 11.5(4) Replace the first sentence in the third paragraph in DCD Subsection 11.5.2.6
CP COL 11.5(5) 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 are prepared and implemented
under the quality assurance program referenced in Chapter 17.
11.5.2.7
Determination of Instrumentation Alarm Setpoints for
Effluents
CP COL 11.5(2) 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 0
Comanche Peak Nuclear Power Plant, Units 3 & 4
COL Application
Part 2, FSAR
CP COL 11.5(4) Replace the last sentence in DCD Subsection 11.5.2.8 with the following.
CP COL 11.5(5)
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 DCD Subection 11.5.2.9 with the following.
CP COL 11.5(1) Fulfillment of the 10 CFR 50 Appendix I guidelines requires effluent monitor data.
CP COL 11.5(2) 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 07-09. 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. CPNPP has already had an existing ODCM (Reference
11.5-201) that is to reflect the new reactor units.
11.5.2.10
Radiological Environmental Monitoring Program
CP COL 11.5(3) Replace the content of DCD Subsection 11.5.2.10 with the following.
CPNPP currently has a radiological environmental monitoring program for
CPNPP Units 1 and 2 that is described in the plant Technical Specifications and
the existing ODCM. 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.
11.5.2.11
Site-Specific Cost-Benefit Analysis
11.5-2
Revision 0
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.
11.5.6
References
Add the following reference after the last reference in DCD Subsection 11.5.6.
11.5-201
Offsite Dose Calculation Manual for CPNPP Units 1 & 2, Revision
26.
11.5-3
Revision 0