CP-201100564, Transmittal of Year 2010 Radiological Environmental Operating Report
| ML11116A057 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 04/20/2011 |
| From: | Flores R Luminant Power |
| To: | Document Control Desk, Office of Nuclear Reactor Regulation |
| References | |
| CP-201100564, TXX-11048 | |
| Download: ML11116A057 (60) | |
Text
Luminant Rafael Flores Senior Vice President
& Chief Nuclear Officer Rafael.flores@Luminant.com Luminant Power P 0 Box 1002 6322 North FM 56 Glen Rose, TX 76043 T 254 897 5550 C 817 559 0403 F 254 897 6652 CP-201100564 Log# TXX-11048 Ref. #
Tech. Spec. 5.6.2 April 20, 2011 U. S. Nuclear Regulatory Commission ATTN: Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK NUCLEAR POWER PLANT DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF YEAR 2010 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
Dear Sir or Madam:
Enclosed is the Annual Radiological Environmental Operating Report for the Comanche Peak Radiological Environmental Monitoring Program. This report is submitted pursuant to Section 5.6.2 of the Comanche Peak Units 1 and 2 Technical Specifications (Appendix A to Operating License Nos. NPF-87 and NPF-89). The report covers the period from January 1, 2010 through December 31, 2010 and summarizes the results of measurements and analysis of data obtained from samples collected during this interval.
If there are any questions regarding this report, please contact Steve Dixon at (254) 897-5482 or Scott Bradley at (254) 897-5495.
Sincerely, Luminant Generation Company LLC Rafael Flores By:
Ad ",y2_.
Fred W. Madden Director, Oversight & Regulatory Affairs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance j~Z~3 Callaway
- Comanche Peak
- Diablo Canyon
- Palo Verde
- San Onofre South Texas Project
- Wolf Creek
U.S. Nuclear Regulatory Commission TXX-11048 Page 2 04/20/11 Enclosure Comanche Peak Annual Radiological Environmental Operating Report for 2010 c -
E. E. Collins, Region IV B. Singal, NRR Resident Inspectors, Comanche Peak
LUMINANT COMANCHE PEAK NUCLEAR POWER PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2010 JANUARY 1, 2010 through DECEMBER 31, 2010 LUMINANT REVIEW and APPROVAL
-4')
,9~ c'&7-/f CREATED BY:
John M. Watts Sr. Radiation Protection Technician Y:92PV,ý Date 3- <9- /i hF.VIP W~f l:
APPROVED BY:
MifdMacho"'
Date Sr. Nuclear Analyst eborah O'Connor Date Aealth Physics Supervisor I
LUMINANT COMANCHE PEAK NUCLEAR POWER PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2010 JANUARY 1, 2010 through DECEMBER 31, 2010 LUMINANT REVIEW and APPROVAL CREATED BY:
REVIEWED BY:
APPROVED BY John M. Watts Date Sr. Radiation Protection Technician Mike Macho Date Sr. Nuclear Analyst Deborah O'Connor Date Health Physics Supervisor I
Table of Contents Section Title I.
Introduction A.
Site and Station Description page 5 B.
Objectives and Overview of the CPNPP Radiological Environmental Monitoring Program page 5 II.
Program Descriptions and Results A.
Sample Locations page 7 Table 1 --
Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2010 Table 2 --
Key to Environmental Sampling Locations B.
Direct Radiation Program page 11 Methods, Procedures and Result Summaries Exceptions to the Program Table 3 --
2010 Environmental Direct Radiation Results Table 14 --
OSL Trend Ouarterlv Average C.
Airborne Program page 15 Methods, Procedures and Result Summaries Exceptions to the Program Table 4 --
2010 Environmental Airborne Particulate Gross Beta Results Graph 1--
2010 Environmental Air Sample Gross Beta Results -
Maximum and Minimum Table 5 --
2010 Environmental Air Sample Iodine-131 Results Table 6 --
2010 Environmental Air Particulate Composite Gamma Isotopic Results 2
D.
Surface Water Program page 21 Methods, Procedures and Result Summaries Exceptions to the Program Table 7 --
2010 Environmental Surface Water Tritium and Gamma Isotopic Results Graph 2--
2010 Environmental Surface Water Tritium Results E.
Surface Drinking Water Program page 25 Methods, Procedures and Result Summaries Exceptions to the Program Table 8 --
2010 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results Graph 3--
Squaw Creek Maximum Tritium Values Graph 4--
2010 Environmental Surface Drinking Water Tritium Results Graph 5--
2010 Environmental Surface Drinking Water Gross Beta Results F.
Groundwater Program page 30 Methods, Procedures and Result Summaries Exceptions to the Program Table 9 --
2010 Environmental Groundwater Tritium and Gamma Isotopic Results G.
Sediment Program page 32 Methods, Procedures and Result Summaries Exceptions to the Program Table 10 --
2010 Environmental Sediment Gamma Isotopic Results H.
Fish Program page 34 Methods, Procedures and Result Summaries Exceptions to the Program Table 11 --
2010 Environmental Fish Gamma Isotopic Results 3
I.
Food Products Program page 36 Methods, Procedures and Result Summaries Exceptions to the Program Table 12 --
2010 Environmental Food Products Gamma Isotopic Results J.
Broadleaf Program page 38 Methods, Procedures and Result Summaries Exceptions to the Program Table 13 --
2010 Environmental Broadleaf Iodine-131 and Gamma Isotopic Results K.
Conclusions page 40 L.
Inter Laboratory Comparison and Cross Check Program page 40 III.
Appendix A Comanche Peak Nuclear Power Plant Land Use Census 2010 page 46 4
I.
Introduction Results of the Radiological Environmental Monitoring Program for the Comanche Peak Nuclear Power Plant (CPNPP) for the year 2010 are contained within this report. This report covers the period from January 1, 2010 through December 31, 2010 and summarizes the results of measurements and analysis of data obtained from environmental samples collected during this same timeframe.
A.
Site and Station Description CPNPP consists of two pressurized water reactor units, each designed to operate at a power level of about 1250 megawatts (electrical). The Station is located on Squaw Creek reservoir in Somervell and Hood counties, about forty miles southwest of Fort Worth, Texas. Unit 1 received a low power operating license February 8, 1990 and achieved initial criticality on April 3, 1990. A full power license for Unit I was issued on April 17, 1990 and commercial operation was declared on August 13, 1990. Unit 2 achieved initial criticality on March 24, 1993 and synchronized to the electrical grid on April 9, 1993.
B.
Objectives and Overviews of the CPNPP Radiological Environmental Monitoring Program The United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To assure that these criteria are met, each license authorizing reactor operation includes technical specifications governing the release of radioactive effluents.
In-plant monitoring is used to assure that these predetermined release limits are not exceeded. However, as a precaution against unexpected and undefined processes that might allow undue accumulation of radioactivity in any sector of the environment, a program for monitoring the plant environs is also included.
Sampling locations were selected on the basis of local ecology, meteorology, physical characteristics of the region, and demographic and land use features of the site vicinity. The radiological environmental monitoring program was designed on the basis of the USNRC Branch Technical Position "An Acceptable Radiological Environmental Monitoring Program" on radiological environmental monitoring issued by the Radiological Assessment Branch, Revision 1 (November 1979), the CPNPP Technical Specification "Technical Specifications for Comanche Peak Nuclear Power Plant Units 1 and 2" and the "CPSES Offsite Dose Calculation Manual" (ODCM).
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In 2010, the Radiological Environmental Monitoring Program included the following:
- The measurement of ambient gamma radiation by Optically Stimulated Luminescent dosimetry;
- The determination of airborne gross beta, gamma emitters, and Iodine-131;
- The determination of tritium and gamma emitters in surface water;
- The determination of gross beta, tritium, Iodine-131, and gamma emitters in drinking water;
" The determination of tritium and gamma emitters in ground water;
" The determination of gamma emitters in sediment and fish;
" The determination of gamma emitters in food products and;
" The determination of gamma emitters and Iodine-131 in broadleaf vegetation.
The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most, only a small percentage increase above normal background radioactivity. Background levels at any one location are not constant but vary with time as they are influenced by external events such as cosmic ray bombardment, weapons test fallout, and seasonal variations. These levels also can vary spatially within relatively short distances reflecting variations in geological composition. To differentiate between background radiation levels and increases resulting from operation of CPNPP, the radiological surveys of the plant environs were divided into pre-operational and operational phases.
The pre-operational phase of the program provided a general characterization of the radiation levels and concentrations prevalent in these areas prior to plant operation along with an indication of the degree of natural variation to be expected. The operational phase of the program obtains data which, when considered along with the data obtained in the pre-operational phase, assists in the evaluation of the radiological impact of plant operation.
Pre-operational measurements were conducted at CPNPP from 1981 to 1989. These pre-operational measurements were performed to:
- Evaluate procedures, equipment, and techniques;
- Identify potentially important pathways to be monitored after plant operation;
" Measure background levels and the variations along potentially important pathways;
" Provide baseline data for statistical comparisons with future operational analytical results.
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The operational Radiological Environmental Monitoring Program is conducted to:
- Verify that measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways;
- Verify the effectiveness of in-plant measures used for controlling the release of radioactive materials;
- Identify changes in the areas at and beyond the site boundary that may impact the principal pathways of exposure.
This report documents the twentieth year of operational measurements and is submitted in accordance with the requirements of the CPSES Offsite Dose Calculation Manual, Part I, Administrative Control 6.9.1.3.
II.
Program Descriptions and Results A.
Sample Locations Within a radius of twenty miles of the CPNPP site there are seventy-two (72) sample locations included in the monitoring program for the year 2010. The number of sample points and the specific locations for the sample points were determined by considering locations where the highest off-site environmental concentrations have been predicted from plant effluent source terms, site hydrology, and site meteorological conditions.
Other factors considered were applicable regulations, population distribution, and ease of access to sampling stations, availability of samples at desired locations, security and future program integrity.
Additionally an annual land use census is conducted to identify changes in the areas surrounding the plant. If changes are identified that impact the principle pathways of exposure, appropriate changes to the radiological environmental monitoring program are implemented. A copy of the report "Comanche Peak Nuclear Power Plant Land Use Census 2010" is provided in Appendix A to this report.
Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2010 contains a brief outline of the current program. This table specifies the sample media type, the number of locations for each media type, the sector and distance identifier for each sample location, the sample frequency, the type of analysis required and the analytical frequency required.
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Table 2 - Key To Environmental Sampling Locations provides a reference that links the sampling point designations used in procedures and forms to the appropriate physical sample location (sector and distance) and to the correct sample type. This cross-reference enhances the ability to review data and tie the data to the correct sample points and to ensure all samples are collected and analyzed as specified.
Currently there are no milk sample locations within ten miles of the CPNPP site and there are no milk sample locations within twenty miles that will participate in the environmental program. CPNPP already samples extra broadleaf locations as required due to no milk locations within the ten-mile radius therefore, no changes to the program are necessary. Milk sampling will be resumed if any future annual land use census determines a dairy has been established within the specified area.
8
Table I - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2010 Media Number of Identification by Sector and Distance (miles)
Sampling Analysis Analytical Locations Frequency (a)
Frequency (a)
N-1.45; N-4.4; N-6.5; N-9.4; NNE-I.I; NNE-5.65; NE-1.7; NE-4.8; ENE-2.5; ENE-5.0; E-0.5; E-1.9; E-3.5; E-4.2; ESE-1.4; ESE-4.7; SE-1.3; Gamma SE-3.85; SE-4.6; SSE-1.3; SSE-4.4; SSE-4.5; Optically Stimulated Exposure 43 S-1.5; S-4.2; SSW-1.1; SSW-4.4; SW-0.9; Q, A Luminescent Dosimetry Q A SW-4.8; SW-12.3; WSW-1.0; WSW-5.35; WSW-7.0; W-1.0; W-2.0; W-5.5; WNW-1.0; WNW-5.0; WNW-6.7; NW-1.0; NW-5.7; NW-9.9; NNW-1.35; NNW-4.6 Gross Beta Air Particulate 8
N-9.4; E-3.5; SSE-4.5; SW-12.3; NW-1.0; W
Gamma Isotopic Filter QC Air Iodine N-1.45; SW/WSW-0.95; S/SSW-1.2 Gamma Isotopic W
Charcoal Surface Water 4
N-19.3; ESE-1.4; N-1.5; NE-7.4 M(b)
Gamma Isotopic M
Surface NNW-0.1; N-9.9 M(c)
Gamma Isotopic M
Water/Drinking Iodine-131 M
SSE-4.6; W-1.2; WSW-0.1; N-9.8; N-1.45 Q
Gamma Isotopic Q
Tritium Q
Sediment 4
N-9.9; NNE-1.0; NE-7.4; SE-5.3 SA Gamma Isotopic SA Fish 2
NNE-8.0; ENE-2.0 SA Gamma Isotopic SA Food Products 1
ENE-9.0 MH Gamma Isotopic MH Iodine-131 MH Broadleaf Vegeat 3
N-1.45; SW-I.0; SW-13.5 M
Gamma Isotopic M
Vegetation (a) Frequency codes are: W-Weekly; M-Monthly; Q-Quarterly; QC-Quarterly Composite; MH-Monthly at Harvest; SA-Semiannual; A-Annual (b) Surface water samples from Squaw Creek are monthly composites of weekly grab samples. Surface water samples from Lake Granbury are monthly grab samples.
(c) Surface water drinking samples are a monthly composite of weekly grab samples.
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Table 2 Key To Environmental Sampling Locations SAMPLING LOCATION SAMPLE SAMPLING LOCATION SAMPLE POINT (SECTOR-MILE)
TYPE*
POINT (SECTOR-MILE)
TYPE*
Al A2 A3 A4 A5 A6 A7 A8 Ri R2 R3 R4 R5 R6 R7 R8 R9 RIO RI1 R12 R13 R14 R15 R16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 N-1.45 N-9.4 E-3.5 SSE-4.5 S/SSW-1.2 SW-12.3 SW/WSW-0.95 NW-1.0 N-1.45 N-4.4 N-6.5 N-9.4 NNE-1.1 NNE-5.65 NE-1.7 NE-4.8 ENE-2.5 ENE-5.0 E-0.5 E-1.9 E-3.5 E-4.2 ESE-1.4 ESE-4.7 SE-1.3 SE-3.85 SE-4.6 SSE-1.3 SSE-4.4 SSE-4.5 S-1.5 S-4.2 SSW-1.1 SSW-4.4 SW-0.9 SW-4.8 R29 R30 R31 R32 R33 R34 R35 R36 R37 R38 R39 R40 R41 R42 R43 SW1 SW2 SW3 SW4 SW5 SW6 GWI GW2 GW3 GW4 GW5 SSI SS2 SS3 SS4 FI F2 FP1 BLI BL2 BL3 SW-12.3 WSW-1.0 WSW-5.35 WSW-7.0 W-1.0 W-2.0 W-5.5 WNW-1.0 WNW-5.0 WNW-6.7 NW-1.0 NW-5.7 NW-9.9 NNW-1.35 NNW-4.6 N-1.5 N-9.9 N-19.9 NE-7.4 ESE-1.4 NNW-0.1 W-1.2 WSW-0.1 SSE-4.6 N-9.8 N-1.45 NNE-1.0 N-9.9 NE-7.4 SE-5.3 ENE-2.0 NNE-8.0 ENE-9.0 N-1.45 SW-1.0 SW-13.5 R
R R
R R
R R
R R
R R
R R
R R
SW SW/DW SW SW SW SW/DW GW/DW GW/DW GW/DW GW/DW GW/DW SS SS SS SS F
F FP BL BL BL Sample Type*
A - AIR SAMPLE F-FISH SS - SHORELINE SEDIMENT SW - SURFACE WATER DW - DRINKING WATER GW - GROUND WATER R - DIRECT RADIATION FP - FOOD PRODUCT BL - BROADLEAF VEGETATION 10
B.
Direct Radiation Starting in 2009 Optically Stimulated Luminescent dosimeters (OSLs) were used to determine the direct (ambient) radiation levels at the designated monitoring locations. The monitoring locations were chosen according to the criteria given in the USNRC Branch Technical Position on Radiation Monitoring (Revision 1, November 1979). The area around the station was divided into 16 radial sectors of 22-1/2 degrees each, corresponding to the cardinal points of the compass. OSLs were placed in each of these sectors. The Optically Stimulated Luminescent dosimeters were placed in two rings around the station. An inner ring was located as close as possible to the site boundary and an outer ring was located at a distance of 4 to.6 miles from the station. Eleven additional OSLs were located at points of special interest, including two control locations. For routine direct radiation measurements, two sets of the Optically Stimulated Luminescent dosimeters (OSLs) were used at each of the 43 monitoring locations. One set of OSLs was exchanged on a quarterly basis and a second set of OSLs was exchanged on a yearly basis. Additional sets of in-transit OSL's were used as control OSLs for the quarterly and annual OSLs.
From years 2001 to 2008 thermoluminescent dosimeters TLDs were processed on-site by CPNPP National Voluntary Laboratory Accreditation Program (NVLAP) certified dosimetry personnel. Individual dosimeters were calibrated by exposure to an accurately known radiation field from a certified Cs-137 source. The year 2001 was the first year that CPNPP used the Panasonic TLD System to supply all the required direct radiation (ambient) monitoring.
In 2009 CPNPP contracted the services of Landauer Inc. to provide and process Optically Stimulated Luminescent dosimeters (OSLs.) The OSLs are used to determine the direct (ambient) radiation levels in designed monitoring locations. Landauer Inc. is accredited by the National Voluntary Laboratory Accreditation Program (NVLAP.)
D. C. Oakley's report "National Radiation Exposure in the United States",
published in 1972, calculated a background radiation dose rate equivalent of 0.22 mr/day for the area surrounding Fort Worth, Texas. This calculated value varies widely with changes in location but represents an appropriate reference value to compare with actual measured OSL doses.
Using data from the pre-operational program for the two years prior to the startup of Unit 1, the quarterly TLDs averaged a calculated dose rate of 0.14 mr/day while the yearly TLDs averaged a calculated dose rate of 0.16 mr/day. The range of measured values from this same two-year period varied from a minimum of 0.11 mr/day to a maximum of 0.22 mr/day.
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Table 3 - 2010 Environmental Direct Radiation Results contains the measured dose (mr) for each quarterly OSL from each of the 43 monitoring locations. The corresponding quarterly calculated dose rate (mr/day) values are listed as well. The statistical average doses (mr) and dose rate (mr/day) values for each set of quarterly OSLs is also displayed.
Additionally, the table includes the total dose (mr) of all four quarters for each specific location. The table also includes the measured dose (mr) for each annual OSL from each of the 43 monitoring locations. The corresponding annual calculated dose rate (mr/day) values are listed as well. The statistical annual average dose (mr) for the entire set of annual OSLs is reported along with the average dose rate (mr/day) for the entire set of annual OSLs.
For the year 2010, the measured dose rates of all the quarterly OSL's ranged from a minimum of 0.154 mr/day to a maximum of 0.330 mr/day with an average dose rate of 0.242 mr/day. This resulted in an average quarterly dose of 21.9 mr and an average annual dose of 87.6 mr for all of the forty three monitoring stations.
The measured dose rates of all the annual OSL's ranged from a minimum of 0.118 mr/day to a maximum of 0.214 mr/day with an average dose rate of 0.177 mr/day. This resulted in an average quarterly dose of 16.0 mr and an average annual dose of 64 mr for all of the forty three monitoring stations.
Comparing the pre-operational data and operational data collected through the year 2010 did not produce any anomalies. The direct radiation dose data for 2010 was consistently lower than previous years of data during both the pre-operational program and the previous years of the operational program. The implementation of the Landauer OSL system and the algorithms used to process the data from the OSL badge (implemented in 2009) accounts for the lower values as well as different type holders for the OSL's.
No abnormal quarterly results were obtained by either CPNPP or by the State of Texas, Bureau of Radiation Control.
During the year 2010, there were no exceptions to the Direct Radiation Program.
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Table 3 - 2010 Environmental Direct Radiation Results (Units of mr dose and mr/day dose rate) 1ST QTR Average Location Total Mr/day N-1.45 RI 26 0.286 N-4.4 R2 27 0.297 N-6.5 R3 25 0.275 N-9.4 R4 28 0.308 NNE-I.1 R5 19 0.209 NNE-5.65 R6 24 0.264 NE-1.7 R7 22 0.242 NE-4.8 R8 26 0.286 ENE-2.5 R9 26 0.286 ENE-5.0 R10 29 0.319 E-0.5 Rll 24 0.264 E-1.9 R12 25 0.275 E-3.5 R13 24 0.264 E-4.2 R14 24 0.264 ESE-1.4 R15 22 0.242 ESE-4.7 R16 24 0.264 SE-I.3 R17 27 0.297 SE-3.85 R18 22 0.242 SE-4.6 R19 24 0.264 SSE-1.3 R20 26 0.286 SSE-4.4 R21 25 0.275 SSE-4.5 R22 26 0.286 S-1.5 R23 24 0.264 S-4.2 R24 21 0.231 SSW-I.I R25 21 0.231 SSW-4.8 R26 29 0.319 SW-0.9 R27 20 0.220 SW-4.8 R28 24 0.264 SW-12.3 (C) R29 25 0.275 WSW-I.0 R30 22 0.242 WSW-5.35 R31 24 0.264 WSW-7.0 (C) R32 30 0.330 W-1.0 R33 23 0.253 W-2.0 R34 27 0.297 W-5.5 R35 21 0.231 WNW-1.0 R36 25 0.275 WNW-5.0 R37 27 0.297 WNW-6.7 R38 22 0.242 NW-I.0 R39 24 0.264 NW-5.7 R40 26 0.286 NW-9.9 R41 23 0.253 NNW-1.35 R42 20 0.220 NNW-4.6 R43 26 0.286 AVERAGES 24.40 0.268 2ND QTR Average 3RD 4TH AVG QTR Average QTR Average QTR Annual Total 20 22 22 19 17 19 18 21 24 25 19 19 20 24 22 25 22 20 22 21 24 22 20 19 18 23 21 23 21 22 18 18 18 18 22 22 22 23 23 22 20 19 24 21.01 mr/day 0.222 0.244 0.244 0.211 0.189 0.211 0.200 0.233 0.267 0.278 0.211 0.211 0.222 0.267 0.244 0.278 0.244 0.222 0.244 0.233 0.267 0.244 0.222 0.211 0.200 0.256 0.233 0.256 0.233 0.244 0.200 0.200 0.200 0.200 0.244 0.244 0.244 0.256 0.256 0.244 0.222 0.211 0.267 0.233 Total 18 19 20 18 14 24 17 24 21 23 23 16 22 23 20 21 21 20 21 19 20 21 21 21 21 17 19 21 19 19 21 24 18 19 19 21 22 23 20 21 21 17 24 20.30 mr/day 0.198 0.209 0.220 0.198 0.154 0.264 0.187 0.264 0.231 0.253 0.253 0.176 0.242 0.253 0.220 0.231 0.231 0.220 0.231 0.209 0.220 0.231 0.231 0.231 0.231 0.187 0.209 0.231 0.209 0.209 0.231 0.264 0.198 0.209 0.209 0.231 0.242 0.253 0.220 0.231 0.231 0.187 0.264 0.223 Total 23 23 22 21 17 24 18 27 23 20 27 19 22 27 24 22 23 21 20 24 23 24 20 20 23 20 20 21 25 24 24 22 21 22 18 23 23 22 24 23 19 17 23 22.05 mr/day Total Total 0.256 21.75 67 0.256 22.75 72 0.244 22.25 65 0.233 21.50 62 0.189 16.75 43 0.267 22.75 71 0.200 18.75 48 0.300 24.50 77 0.256 23.50 78 0.222 24.25 78 0.300 23.25 64 0.211 19.75 54 0.244 22.00 70 0.300 24.50 72 0267 22.00 65 0.244 23.00 70 0.256 23.25 71 0.233 20.75 61 0.222 21.75 59 0.267 22.50 66 0.256 23.00 67 0.267 23.25 63
.0222 21.25 66 0.222 20.25 63 0.256 20.75 69 0.222 22.25 61 0.222 20.00 65 0.233 22.25 64 0.278 22.50 60 0.267 21.75 73 0.267 21.75 67 0.244 23.50 64 0.233 20.00 58 0.244 21.50 53 0.200 20.00 57 0.256 22.75 70 0.256 23.50 57 0.244 22.50 58 0.267 22.75 57 0.256 23.00 68 0.211 20.75 61 0.189 18.25 43 0.256 24.25 75 0.245 21.94 64.00 Average mr/day 0.184
.0198 0.179 0.170 0.118 0.195 0.132 0.280 0.214 0.214 0.176 0.148 0.192 0.198 0.179 0.192 0.195 0.168 0.162 0.181 0.184 0.173 0.181 0.173 0.190 0.168 0.179 0.176 0.165 0.201 0.184 0.176 0.159 0.146 0.157 0.192 0.157 0.159 0.156 0.186 0.167 0.118 0.205 0.177 13
Table 14 - OSL Trend Quarterly Average Location 2001 2002 2003 2004 2005 2006 R1 19.55 16.75 19.60 18.90 20.10 18.85 R2 32.75 29.25 32.30 33.70 30.05 28.55 R3 22.65 19.60 24.15 23.20 23.25 21.10 R4 22.60 21.00 26.10 25.75 23.20 25.15 R5 N/A 15.40 19.05 21.90 4.95 6.90 R6 22.75 22.55 N/A 27.65 23.15 25.55 R7 17.40 16.95 18.25 18.70 8.40 5.40 R8 27.15 23.80 24.10 25.50 23.70 21.75 R9 35.90 28.50 30.30 32.60 29.20 25.65 R10 41.85 36.20 41.90 41.00 36.00 40.60 Rll 29.80 22.75 26.15 29.45 25.65 29.50 R12 13.05 9.15 10.20 33.80 16.00 14.90 R13 39.90 31.30 55.40 37.25 35.25 36.85 R14 33.75 27.60 29.15 32.45 27.30 27.35 R15 21.30 16.95 20.55 21.50 17.00 21.50 R16 32.05 25.40 28.35 28.55 28.40 27.05 R17 28.25 27.00 29.45 31.30 28.85 28.10 R18 17.85 15.70 19.75 19.35 17.20 20.95 R19 20.25 21.70 21.85 20.70 18.95 18.75 R20 21.70 16.75 18.25 22.65 17.90 19.75 R21 21.75 21.15 25.15 24.25 22.15 23.25 R22 20.15 17.75 21.50 22.00 18.25 23.80 R23 17.95 18.95 16.60 18.85 17.30 16.85 R24 18.10 17.55 21.10 25.45 19.85 19.85 R25 17.20 19.00 17.30 19.50 22.65 23.35 R26 23.50 25.80 N/A 20.50 18.70 21.15 R27 N/A 22.30 18.50 22.55 16.15 19.35 R28 18.05 16.20 20.85 14.00 15.60 4.35 R29 21.50 21.75 24.10 24.40 22.20 21.20 R30 N/A 25.45 22.45 28.35 23.30 25.05 R31 19.75 18.70 23.05 24.70 20.55 21.20 R32 22.20 25.60 26.65 25.10 27.80 27.45 R33 10.15 13.10 13.40 14.75 13.75 13.75 R34 21.15 11.90 13.70 13.90 13.40 14.85 R35 18.45 14.65 18.00 17.95 19.40 16.10 R36 24.95 25.50 25.60 28.55 26.50 26.20 R37 21.35 22.85 23.45 22.95 24.15 24.55 R38 22.00 21.10 23.65 23.10 20.10 22.95 R39 17.45 19.20 21.35 24.20 16.95 19.50 R40 23.75 19.20 23.45 20.90 24.45 22.60 R41 17.15 14.95 17.35 19.65 17.70 18.15 R42 2.05 5.20 6.70 5.95 1.35 8.00 R43 29.45 23.95 30.40 30.90 24.95 28.10 2007 2008 2009 2010 15.90 19.10 20.25 21.75 24.60 30.95 34.25 22.75 20.60 21.15 15.25 22.25 19.90 22.40 24.25 21.50 3.30 4.15 10.25 16.75 19.50 22.35 18.25 22.75 4.20 4.35 2.25 18.75 17.20 20.20 23.25 24.50 24.10 30.25 34.25 23.50 35.70 36.75 44.25 24.25 26.90 22.30 28.25 23.25 12.60 14.70 19.25 19.75 33.40 37.60 34.25 22.00 25.50 31.25 32.25 24.50 16.80 20.95 14.25 22.00 22.20 22.20 31.25 23.00 22.10 25.50 26.25 23.25 17.20 19.60 23.25 20.75 15.80 10.50 26.25 21.75 18.80 20.45 23.25 22.50 22.40 12.75 28.25 23.00 19.90 21.60 24.25 23.25 15.50 16.40 23.25 21.25 16.60 21.35 21.25 20.25 19.10 24.00 17.25 20.75 18.90 17.90 27.25 22.25 18.20 17.00 16.25 20.00 14.80 18.40 23.25 22.25 19.20 21.50 16.25 22.50 18.60 24.45 26.25 21.75 17.70 18.05 15.25 21.75 20.00 15.00 23.25 23.50 9.10 14.45 11.25 20.00 10.10 12.60 8.25 21.50 14.40 19.35 18.25 20.00 21.20 24.35 28.25 22.75 19.70 24.20 26.25 23.50 18.60 21.60 21.25 22.50 16.10 18.75 25.25 22.75 19.20 25.25 30.25 23.00 17.80 19.25 11.25 20.75 0.70 0.00 0.25 18.25 28.70 27.95 32.25 24.25
% Diff 2001-
% Diff 2010 to 2009 mR 2009 to 2009 Avg Average 7%
-40%
21.22 5%
-12%
23.37
-8%
10.74 22%
22.72 0%
10.66 5%
22.96 6%
-37%
30.08
-25%
-58%
39.36
-48%
-19%
26.75
-14%
3%
15.96 21%
-44%
37.91
-53%
-27%
29.62
-19%
18.98 15%
-30%
27.27
-17%
-12%
27.42
-16%
-11%
18.98 9%
-19%
19.42 11%
-3%
19.94 12%
-20%
22.34 3%
-4%
21.02 10%
-9%
17.96 17%
-5%
20.12 1%
18%
19.93 4%
-20%
21.71 2%
21%
18.79 6%
-4%
16.17 21.34 5%
-19%
24.24
-11%
-28%
19.88 9%
1%
23.67
-1%
.12.63
~13.32 9%
17.39 14%
-22%
25.68
-12%
-11%
23.27 1 %
6%
21.59 4%
-10%
19.86 14%
-27%
23.23
-1%
17.03 20%
~3.36
-28%
28.52
-16%
R5 - All TLD readings low, elements could have been wet in 2005, 2006, 2007, 2008 (on Squaw Creek Reservoir)
Legend:
R7 - All TLD and OSL readings were low, elements could have been wet from 2005 to 2009 (on Squaw Creek Reservoir)
R12 - Anomalous reading from 2004 R28 - Missing 2nd issue (4/21/06 - 12/29/06)
R42 - Location consistently low because it is over water on Squaw Creek Reservoir Note: Change from Panasonic TLD to OSL badges provided a change to a better current technology.
14
C.
Airborne Program Air particulate and air iodine samples were collected each week from the eight monitoring locations described in Table 1 - Comanche Peak Nuclear Power Plant Radiological Monitoring Program for 2010. Each air particulate sample was collected by drawing air through a 47 millimeter-diameter glass-fiber filter. Air iodine was collected by drawing air through a TEDA impregnated charcoal cartridge which was connected in series behind the air particulate filter. Shipped to an independent laboratory, air particulate filters were analyzed weekly for gross beta activity and were composited quarterly for gamma spectrometry analysis.
Charcoal cartridges were analyzed weekly for Iodine-131.
For the year 2010, a total of 416 air particulate filters were collected and analyzed for gross beta activity. The reported gross beta activity ranged from a minimum value of 1.O1E-02 pCi/m3 to a maximum value of 9.50E-02 pCi/m 3. Table 4 - 2010 Environmental Airborne Particulate Gross Beta Results contains the reported values of all samples. There were no anomalies noted in the data reported for 2010 when compared to pre-operational and previous operational data. Graph 1 - 2010 Environmental Air Sample Gross Beta Results - Maximum and Minimum trends the weekly high and low gross beta values to show the seasonal variation of the results as well as providing indication of consistency between the individual monitoring locations.
A total of 424 charcoal cartridges were analyzed for airborne Iodine-131.
No Iodine-131 was detected at any of the eight monitoring locations.
Table 5 - 2010 Environmental Air Sample Iodine-131 Results contains the reported values of each Iodine-131 analysis, all of which are less than the required lower limit of detection (LLD).
All air particulate filters were collected and composited quarterly and then analyzed by gamma spectrometry. The gamma isotopic data is presented in Table 6 - 2010 Environmental Air Particulate Composite Gamma Isotopic Results. Typical of pre-operational and previous operational data results, the only radioactive nuclide identified in all the samples was cosmogenic Beryllium-7, a naturally occurring isotope.
A review of all the State of Texas air sample data indicated no anomalies.
During the year 2010, there were no exceptions to the Airborne Program.
15
Table 4 -- 2010 Environmental Airborne Particulate Gross Beta Results (Units of pCi/m3) 5 A-6 A-8 A-7 A-*
A-4 A-3 A-1 A-2 Location NW-1.0 SW/WSW-0.95 Date 01/05/2010 01/12/2010 01/19/2010 01/26/2010 02/02/2010 02/09/2010 02/16/2010 02/23/2010 03/02/2010 03/09/2010 03/16/2010 03/23/2010 03/30/2010 04/06/2010 04/13/2010 04/20/2010 04/27/2010 05/04/2010 05/11/2010 05/18/2010 05/25/2010 06/01/2010 06/08/2010 06/15/2010 06/22/2010 06/29/2010 07/06/2010 07/13/2010 07/20/2010 07/27/2010 08/03/2010 08/10/2010 08/17/2010 08/24/2010 08/31/2010 09/07/2010 09/14/2010 09/21/2010 09/28/2010 10/05/2010 10/12/2010 10/19/2010 10/26/2010 11/02/2010 11/09/2010 11/16/2010 11/23/2010 11/30/2010 12/07/2010 12/14/2010 12/21/2010 12/28/2010 5.04E-02 5.24E-02 4.52E-02 2.75E-02 2.83E-02 3.25E-02 2.98E-02 2.04E-02 3.32E-02 2.42E-02 2.47E-02 2.55E-02 3.55E-02 3.90E-02 3.21 E-02 3.14E-02 2.11 E-02 3.09E-02 3.07E-02 2.86E-02 2.17E-02 3.86E-02 3.13E-02 2.29E-02 1.74E-02 1.80E-02 3.12E-02 4.44E-02 4.95E-02 4.70E-02 4.29E-02 4.39E-02 4.50E-02 4.23E-02 6.70E-02 5.47E-02 4.54E-02 6.83E-02 5.27E-02 6.80E-02 6.04E-02 9.05E-02 8.06E-02 5.82E-02 5.54E-02 4.95E-02 6.29E-02 7.64E-02 7.63E-02 9.50E-02 9.37E-02 1.08E-02 4.37E-02 4.65E-02 4.47E-02 2.69E-02 2.81 E-02 2.92E-02 3.04E-02 2.26E-02 2.85E-02 3.17E-02 2.31 E-02 2.98E-02 3.55E-02 4.04E-02 3.13E-02 3.13E-02 1.88E-02 1.68E-02 2.15E-02 2.01 E-02 1.54E-02 2.93E-02 2.78E-02 1.77E-02 1.57E-02 1.85E-02 2.77E-02 3.25E-02 4.60E-02 3.68E-02 3.46E-02 3.66E-02 3.47E-02 3.41 E-02 6.27E-02 3.77E-02 3.40E-02 5.11 E-02 3.54E-02 4.98E-02 5.30E-02 7.77E-02 8.05E-02 5.72E-02 4.77E-02 3.94E-02 5.97E-02 6.31 E-02 7.16E-02 7.53E-02 7.02E-02 1.02E-02 S/SSW-1.2 SW-12.3 SSE-4.5 E-3.5 Control 4.99E-02 4.94E-02 6.04E-02 4.93E-02 6.24E-02 5.84E-02 7.25E-02 5.38E-02 5.57E-02 5.28E-02 5.96E-02 4.29E-02 2.72E-02 3.95E-02 3.41E-02 2.25E-02 3.08E-02 3.04E-02 3.92E-02 3.10E-02 3.48E-02 3.11E-02 4.43E-02 2.75E-02 3.65E-02 3.57E-02 4.36E-02 3.35E-02 2.77E-02 2.05E-02 3.33E-02 2.48E-02 3.22E-02 3.63E-02 3.36E-02 2.92E-02 2.93E-02 3.34E-02 3.38E-02 3.28E-02 2.57E-02 3.24E-02 2.61 E-02 1.87E-02 3.43E-02 3,49E-02 2.89E-02 2.33E-02 3.75E-02 4.36E-02 3.12E-02 2.81E-02 4.14E-02 4.60E-02 4.29E-02 3.54E-02 3.03E-02 3.60E-02 3.25E-02 2.67E-02 3.68E-02 3.33E-02 3.86E-02 2.72E-02 2.58E-02 2.49E-02 2.77E-02 2.38E-02 2.50E-02 2.78E-02 2.45E-02 2.44E-02 3.25E-02 2.95E-02 2.99E-02 2.35E-02 2.81 E-02 2.74E-02 2.22E-02 1.88E-02 1.78E-02 1.99E-02 1.61 E-02 1.62E-02 3.53E-02 3.88E-02 3.65E-02 3.31 E-02 3.38E-02 2.69E-02 3.03E-02 3.47E-02 2.14E-02 2.02E-02 2.09E-02 2.07E-02 1.81 E-02 1.99E-02 1,73E-02 1.22E-02 1.85E-02 1.73E-02 1.74E-02 2.10E-02 2.61 E-02 2.14E-02 2.26E-02 2.57E-02 3.39E-02 3.50E-02 3.80E-02 3.40E-02 4.71 E-02 4.65E-02 4.99E-02 4.24E-02 4.49E-02 4.19E-02 4.27E-02 3.85E-02 4.42E-02 4.13E-02 4.03E-02 4.09E-02 4.22E-02 4.17E-02 4.03E-02 6.19E-02 4.03E-02 4.65E-02 4.17E-02 4.06E-02 3.76E-02 3.71E-02 3.94E-02 3.29E-02 6.18E-02 6.29E-02 6.30E-02 5.16E-02 3.73E-02 3.91E-02 3.72E-02 3.50E-02 3.94E-02 3.71 E-02 4.16E-02 3.58E-02 5.63E-02 5.86E-02 6.18E-02 5.91 E-02 3.81 E-02 4.30E-02 4.25E-02 4.26E-02 4.40E-02 4.42E-02 4.95E-02 4.57E-02 4.96E-02 5.13E-02 5.56E-02 5.54E-02 7.03E-02 8.18E-02 7.30E-02 7.15E-02 6.09E-02 8.03E-02 7.62E-02 6.40E-02 4.76E-02 5.66E-02 5.38E-02 4.81E-02 4.81E-02 4.73E-02 5.45E-02 4.45E-02 3.94E-02 4.86E-02 5.OOE-02 4.68E-02 5.70E-02 5.93E-02 6.06E-02 5.80E-02 6.42E-02 7.71 E-02 7.32E-02 7.07E-02 6.08E-02 6.85E-02 6.64E-02 7.28E-02 7.22E-02 8.69E-02 8.09E-02 9.16E-02 6.77E-02 8.98E-02 6.88E-02 8&28E-02 9.07E-02 1.01 E-02 9.40E-02 1.06E-02 N-1.45 5.89E-02 6.71 E-02 6.65E-02 3.45E-02 4.13E-02 4.45E-02 3.86E-02 3.30E-02 3.69E-02 3.94E-02 2.84E-02 4.04E-02 4.57E-02 5.38E-02 4.30E-02 4.63E-02 2.65E-02 2.93E-02 3.52E-02 3.32E-02 2.34E-02 4.78E-02 3.79E-02 2.47E-02 2.06E-02 2.24E-02 3.16E-02 4.68E-02 5.66E-02 4.52E-02 5.05E-02 4.92E-02 4.87E-02 4.11 E-02 7.08E-02 4.05E-02 4.45E-02 6.53E-02 4.36E-02 5.28E-02 5.88E-02 8.30E-02 7.71 E-02 6.90E-02 4.94E-02 4.42E-02 6.06E-02 7.61E-02 8.83E-02 8.32E-02 7.90E-02 1.02E-02 N-9.4 Control 4.91 E-02 6.71 E-02 6.06E-02 3.15E-02 3.55E-02 4.30E-02 3.50E-02 3.15E-02 3.97E-02 3.77E-02 2.04E-02 2.34E-02 2.81 E-02 2.69E-02 3.18E-02 3.16E-02 2.35E-02 2.21 E-02 2.98E-02 2.42E-02 2.41E-02 3.70E-02 3.04E-02 1.98E-02 1.93E-02 1.38E-02 2.80E-02 4,29E-02 3.99E-02 4.35E-02 3.97E-02 3.86E-02 3.74E-02 4.08E-02 5.76E-02 4.63E-02 4.23E-02 5.61 E-02 4.54E-02 4.50E-02 4.93E-02 7.65E-02 7.18E-02 5.15E-02 4.74E-02 3.78E-02 5.49E-02 6.67E-02 6.62E-02 7.54E-02 7.39E-02 8.41 E-02 Required LLD 1.OOE-02 16
Graph 1 -- 2010 Environmental Air Sample Gross Beta Results - Maximum and Minumum 1.O0E-01 9.00E-02 8.00E-02 e
7.00E-02 E
6.OOE-02 5.00E-02 4.00E-02
- -3.00E-02 2.OOE-02 1.OOE-02 0.OOE+00 1
5 9
13 17 21 25 29 33 37 41 45 49 Weekly Data Points 17
Table 5 -- 2010 Environmental Air Sample Iodine-131 Results A-8 A-7 NW-1.0 SWIWSW-0.95 Date 01/05/2010 01/12/2010 01/19/2010 01/26/2010 02/02/2010 02/09/2010 02/16/2010 02/23/2010 03/02/2010 03/09/2010 03/16/2010 03/23/2010 03/30/2010 04/06/2010 04/13/2010 04/20/2010 04/27/2010 05/04/2010 05/11/2010 05/18/2010 05/25/2010 06/01/2010 06/08/2010 06/15/2010 06/22/2010 06/29/2010 07/06/2010 07/13/2010 07/20/2010 07/27/2010 08/03/2010 08/10/2010 08/17/2010 08/24/2010 08/31/2010 09/07/2010 09/14/2010 09/21/2010 09/28/2010 10/05/2010 10/12/2010 10/19/2010 10/26/2010 11/02/2010 11/09/2010 11/16/2010 11/23/2010 11/30/2010 12/07/2010 12/14/2010 12/21/2010 12/28/2010
<3.3E-02
<3.1 E-02
<2.3E-02
<3.8E-02
<3.OE-02
<3.8E-02
<3.OE-02
<4.9E-02
<4.2E-02
<3.9E-02
<4.6E-02
<3.7E-02
<4.4E-02
<3.OE-02
<4.4E-02
<3.2E-02
<4.2E-02
<3.6E-02
<3.9E-02
<3.2E-02
<3.7E-02
<6.4E-02
<4.9E-02
<6.1 E-02
<5.9E-02
<6.4E-02
<1.54E-02
<1.45E-02
<1.67E-02
<1.57E-02
<1.41 E-02
<1.08E-02
<1.86E-02
<2.19E-02
<1.64E-02
<1.59E-02
<1.33E-02
<1.40E-02
<1.42E-02
<1.19E-02
<1.66E-02
<1.30E-02
<1.65E-02
<1.30E-02
<1.48E-02
<1.71 E-02
<1.60E-02
<2.57E-02
<1.36E-02
<3.38E-02
<3.OOE-02
<2.64E-02
<3.7E-02
<2.7E-02
<3.9E-02
<4.5E-02
<3.9E-02
<5.9E-02
<3.5E-02
<4.2E-02
<3.2E-02
<3.3E-02
<4.5E-02
<5.OE-02
<3.8E-02
<3.6E-02
<3.OE-02
<3.7E-02
<4.3E-02
<4.3E-02
<5.2E-02
<3.3E-02
<2.9E-02
<5.6E-02
<4.5E-02
<3.6E-02
<6.4E-02
<5.7E-02
<9.72E-03
<2.09E-02
<1.38E-02
<1.44E-02
<1.73E-02
<1.78E-02
<1.99E-02
<1.40E-02
<1.44E-02
<1.53E-02
<1.93E-02
<9.64E-03
<1.35E-02
<1.71E-02
<1.93E-02
<1.51E-02
<1.52E-02
<1.28E-02
<1.41E-02
<1.30E-02
<2.46E-02
<2.57E-02
<1.56E-02
<2.37E-02
<2.45E-02
<3.01 E-02 (Units of pCi/m3)
A-5 A-6 S/SSW-1.2 SW-2.3 Control
<3.9E-02
<3.4E-02
<3.4E-02
<3.7E-02
<2.4E-02
<3.6E-02
<4.1E-02
<3.9E-02
<4.6E-02
<3.9E-02
<4.5E-02
<3.4E-02
<4.1E-02
<2.5E-02
<6.OE-02
<4.2E-02
<5.1E-02
<3.4E-02
<3.7E-02
<3.7E-02
<5.3E-02
<4.6E-02
<4.8E-02
<4.4E-02
<4.OE-02
<3.6E-02
<4.3E-02
<3.OE-02
<4.5E-02
<4.2E-02
<3.2E-02
<3.OE-02
<5.1E-02
<4.5E-02
<4.5E-02
<4.1E-02
<6.OE-02
<5.1E-02
<4.7E-02
<3.9E-02
<5.1E-02
<4.9E-02
<5.3E-02
<4.3E-02
<5.9E-02
<3.6E-02
<5.5E-02
<3.6E-02
<3.9E-02
<2.8E-02
<5.1E-02
<5.9E-02
<1.53E-02
<1.11E-02
<1.73E-02
<1.42E-02
<1.51E-02
<1,05E-02
<1.39E-02
<1.73E-02
<1.52E-02
<1.30E-02
<1.12E-02
<1.97E-02
<1.53E-02
<1.79E-02
<1.86E-02
<1.56E-02
<1.33E-02
<1.62E-02
<1.59E-02
<1.46E-02
<1.51E-02
<1.88E-02
<1.27E-02
<1.24E-02
<1.77E-02
<1.80E-02
<2.32E-02
<1.35E-02
<1.39E-02
<1.73E-02
<1.60E-02
<1.16E-02
<1.38E-02
<1.39E-02
<1.77E-02
<1.29E-02
<1.93E-02
<1.25E-02
<1.41E-02
<1.53E-02
<1.92E-02
<3.68E-02
<2.15E-02
<2.80E-02
<1.81E-02
<1.58E-02
<3.09E-02
<3.76E-02
<1.96E-02
<3.64E-02
<3.96E-02
<2.36E-02 A-4 SSE-4.5
<2.5E-02
<3.4E-02
<2.6E-02
<5.1E-02
<5.9E-02
<4.1 E-02
<3.4E-02
<3.6E-02
<4.3E-02
<3.9E-02
<5.OE-02
<3.5E-02
<4.OE-02
<3.6E-02
<3.5E-02
<2.4E-02
<3.9E-02
<3.6E-02
<5.3E-02
<4.3E-02
<3.5E-02
<5.2E-02
<5.5E-02
<3.6E-02
<4.6E-02
<6.8E-02
<1.56E-02
<1.72E-02
<1.43E-02
<1.61E-02
<1.92E-02
<1.19E-02
<1.31E-02
<1.63E-02
<1.68E-02
<1.33E-02
<1.96E-02
<1.27E-02
<1.34E-02
<2.02E-02
<1.87E-02
<1.70E-02
<2.16E-02
<1.19E-02
<1.13E-02
<1.60E-02
<2.29E-02
<3.87E-02
<1.77E-02
<2.04E-02
<3.15E-02
<3.40E-02 A-3 E-3.5
<4.1 E-02
<2.9E-02
<3.5E-02
<3.6E-02
<3.4E-02
<5.2E-02
<3.6E-02
<3.9E-02
<6.OE-02
<5.3E-02
<6.2E-02
<4.8E-02
<3,9E-02
<4.3E-02
<3.4E-02
<3.OE-02
<4.7E-02
<5.9E-02
<5.3E-02
<5.1 E-02
<3.3E-02
<6.3E-02
<4.6E-02
<5.1 E-02
<5.2E-02
<4.5E-02
<1.27E-02
<1.68E-02
<1.92E-02
<1.82E-02
<1.26E-02
<1.67E-02
<1.46E-02
<1.92E-02
<8.64E-03
<1.17E-02
<1.53E-02
<1.07E-02
<1.09E-02
<1.79E-02
<1.54E-02
<1.54E-02
<1.66E-02
<1.59E-02
<1.23E-02
<1.18E-02
<1.71E-02
<1.94E-02
<1.30E-02
<2.74E-02
<3.71 E-02
<1.88E-02 A-1 N-1.45
<3.OE-02
<3.8E-02
<2.8E-02
<4.9E-02
<4.4E-02
<4.3E-02
<4.1 E-02
<5.2E-02
<4.8E-02
<4.2E-02
<4.4E-02
<5.7E-02
<4.5E-02
<2.3E-02
<4.5E-02
<3.2E-02
<5.4E-02
<4.OE-02
<4.9E-02
<4.7E-02
<5.1 E-02
<5.8E-02
<5.3E-02
<3.3E-02
<4.6E-02
<6.2E-02
<1.14E-02
<1.53E-02
<1.50E-02
<1.42E-02
<1.92E-02
<1.24E-02
<2.27E-02
<1.33E-02
<1.82E-02
<1.OOE-02
<1.34E-02
<1.52E-02
<1.46E-02
<1.56E-02
<2.08E-02
<1.26E-02
<1.19E-02
<1.44E-02
<1.20E-02
<1.86E-02
<1.96E-02
<2.84E-02
<2.13E-02
<2.04E-02
<2.48E-02
<1.80E-02 A-2 N-9.4 Control
<3.9E-02
<3.OE-02
<4.OE-02
<4.2E-02
<4.4E-02
<3.8E-02
<3.5E-02
<3.8E-02
<3.7E-02
<4.2E-02
<3.8E-02
<4.OE-02
<5.OE-02
<2.8E-02
<3.7-02
<4.4E-02
<4.OE-02
<4.7E-02
<4.5E-02
<4.9E-02
<4.5E-02
<5.1 E-02
<4.6E-02
<4.OE-02
<6.3E-02
<5.3E-02
<1.43E-02
<1.06E-02
<1.39E-02
<1.50E-02
<1.40E-02
<1.34E-02
<1.68E-02
<1.34E-02
<1.81E-02
<1.58E-02
<1.41 E-02
<1.19E-02
<1.82E-02
<1.48E-02
<1.47E-02
<2.11 E-02
<1.29E-02
<1.41E-02
<1.90E-02
<1.30E-02
<3.72E-02
<2.62E-02
<1.43E-02
<2.89E-02
<2.58E-02
<3.25E-02 Required LLD 7.OOE-02 18
Table 6 -- 2010 Environmental Air Particulate Composite Gamma Isotopic Results (Units of pCi/m3)
A-8 A-7 NW-1.0 SW/WSW-0.95 Composite Dates 1ST QTR Location Nuclides Ba-140 Be-7 Co-57 Co-58 Co-60 Cs-1 34 Cs-1 37 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Ba-140 Be-7 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95
<1.9E-01 1.3E-01
<1.OE-03
<6.OE-03
<1.3E-03
<1.9E-03
<2.2E-03
<1.7E-02
<4.2E-02
<1.9E-01
<3.OE-03
<1.1E-02
<1.3E-02
<9.3E-03
<1.5E-01 1.9E-01
<8.1 E-04
<3.9E-03
<2.6E-03
<2.OE-03
<2.OE-03
<1.3E-02
<3.4E-02
<1.5E-01
<2.8E-03
<6.6E-03
<5.7E-03
<4.3E-03
<4.5E-02 1.8E-01
<1.3E-03
<4.2E-03
<4.4E-03
<2.5E-03
<2.9E-03
<2.OE-02
<3.3E-02
<4.5E-02
<3.6E-03
<7.7E-03
<7.3E-03
<7.6E-03
<1.1E-01 1.5E-01
<1.OE-03
<5.2E-03
<1.4E-03
<2.6E-03
<2.9E-03
<1.5E-02
<3.3E-02
<1.1E-01
<3.1E-03
<7.4E-03
<2.7E-03
<9.3E-03 A-5 A-6 SSW-1.2 SW-12.3 Control
<4.5E-02
<4.5E-02 1.8E-01 1.9E-01
<8.7E-04
<9.4E-04
<5.2E-03
<5.3E-03
<1.3E-03
<5.1E-03
<1.9E-03
<9.8E-04
<2.2E-03
<2.9E-03
<1.7E-02
<1.6E-02
<3.1E-02
<3.3E-02
<4.5E-02
<4.5E-02
<3.OE-03
<3.1E-03
<9.5E-03
<1.1E-02
<7.6E-03
<9.2E-03
<7.4E-03
<7.6E-03
<1.3E-01 1.6E-01
<8.2E-04
<4.1 E-03
<4.6E-03
<9.6E-04
<2.2E-03
<2.1 E-02
<3.1 E-02
<1.3E-01
<3.9E-03
<7.6E-03
<7.6E-03
<1.1E-02
<1.OE-01 2.OE-01
<9.9E-04
<5.3E-03
<3.2E-03
<2.8E-03
<8.8E-04
<1.4E-02
<4.1 E-02
<1.OE-01
<2.9E-03
<9.9E-03
<6.5E-03
<6.9E-03 A-4 A-3 SSE-4.5 E-3.5 A-1 N-1.45
<4.5E-02 1.3E-01
<9.8E-04
<5.3E-03
<5.1 E-03
<3.1 E-03
<2.2E-03
<5.8E-03
<3.3E-02
<4.5E-02
<3.1 E-03
<3.OE-03
<7.3E-03
<7.6E-03
<4.OE-02 1.2E-01
<8.7E-04
<5.9E-03
<1.4E-03
<1.9E-03
<2.2E-03
<2.1 E-02
<3.2E-02
<4.OE-02
<3.5E-03
<7.3E-03
<7.9E-03
<9.2E-03
<1.3E-01 2.3E-01
<8.2E-04
<6.6E-03
<4.6E-03
<2.4E-03
<7.5E-04
<2.1E-02
<3.1 E-02
<1.3E-01
<4.3E-03
<1.1E-02
<2.7E-03
<1.1E-02
<4.OE-02 2.2E-01
<9.9E-04
<1.6E-03
<4.4E-03
<1.4E-03
<2.3E-03
<2.OE-02
<3.3E-02
<4.OE-02
<2.5E-03
<7.5E-03
<2.7E-03
<7.5E-03 A-2 N-9.4 Control
<4.5E-02 1.3E-01
<7.8E-04
<5.3E-03
<1.4E-03
<2.5E-03
<2.2E-03
<1.6E-02
<5.2E-02
<4.5E-02
<3.1E-03
<3.OE-03
<1.1E-02
<7.6E-03
<8.7E-02 2.3E-01
<8.4E-04
<4.9E-03
<8.8E-04
<2.6E-03
<3.1E-03
<1.9E-02
<3.1 E-02
<8.7E-02
<2.6E-03
<9.1E-03
<7.5E-03
<1.OE-02 Required LLD 5.OE-2 Required LLD 6.OE-2 Composite Dates 2ND QTR
<1.1E-01 1.9E-01
<7.2E-04
<3.5E-03
<2.9E-03
<1.8E-03
<2.1 E-03
<1.2E-02
<3.4E-02
<1.1E-01
<2.OE-03
<8.8E-03
<6.1 E-03
<7.1E-03
<1.4E-01 1.8E-01
<1.2E-03
<1.6E-03
<4.5E-03
<2.8E-03
<3.8E-03
<2.OE-02
<4.4E-02
<1.4E-01
<2.5E-03
<2.9E-03
<7.3E-03
<9.4E-03 Required LLD 5.OE-2 Required LLD 6.OE-2 19
Table 6 -2010 Environmental Air Particulate Composite Gamma Isotopic Results (continued)
(Units of pCi/m3)
A-8 A-7 A-5 A-6 A-4 A-3 A-1 A-2 NW-1.0 Sw/wsw-0.95 SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9. 4 Composite Dates 3RD QTR Location Nuclides Ba-140 Be-7 Co-57 Co-58 Co-60 Cs-1 34 Cs-1 37 Fe-59 K-40 La -140 Mn-54 Nb-95 Zn-65 Zr-95 Ba-140 Be-7 Co-57 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95
<2.3E-02 1.1 E-01
<4.1 E-04
<1.1E-03
<8.7E-04
<1.2E-03
<8.OE-04
<3.1 E-03
<1.7E-02
<4.0E-03
<7.8E-04
<1.2E-03
<2.2E-03
<1.8E-03
<9.0E-03 1.2E-01
<4.4E-04
<9.3E-04
<1.1E-03
<6.4E-04
<6.3E-04
<3.4E-03
<1.7E-02
<9.OE-03
<9.2E-04
<1.6E-03
<1.4E-03
<1.3E-03
<2.5E-02 1.0E-01
<6.3E-04
<1.2E-03
<1.1E-03
<1.2E-03
<9.3E-04
<2.4E-03 9.8E-03
<8.1E-03
<1.1E-03
<1.5E-03
<2.6E-03
<2.3E-03
<1.2E-02 8.8E-02
<6.OE-04
<1.5E-03
<9.3E-04
<9.4E-04
<9.7E-04
<2.8E-03 9.8E-03
<1.2E-02
<7.8E-04
<1.7E-03
<1.7E-03
<2.3E-03
<2.5E-02 1.0E-01
<6.3E-04
<4.3E-03
<1.5E-03
<1.3E-03
<1.OE-03
<3.7E-03
<1.3E-02
<1.OE-02
<1.OE-03
<1.3E-03
<3.0E-03
<3.3E-03
<1.7E-02 7.7E-02
<5.0E-04
<1.1E-03
<7.4E-04
<1.2E-03
<6.OE-04
<3.2E-03
<1.3E-02
<1.7E-02
<1.0E-03
<1.8E-03
<2.4E-03
<2.6E-03 Control
<3.2E-02 9.1 E-02
<7.4E-04
<1.5E-03
<9.6E-04
<1.3E-03
<9.9E-04
<3.5E-03
<1.6E-02
<1.2E-02
<8.5E-04
<1.4E-03
<2.0E-03
<3.2E-03
<1.3E-02 9.7E-02
<3.6E-04
<9.3E-04
<7.8E-04
<5.4E-04
<9.OE-04
<3.3E-03
<1.6E-02
<1.3E-02
<1.OE-03
<1.3E-03
<1.9E-03
<2.6E-03
<2.3E-02 8.1 E-02
<4.9E-04
<1.4E-03
<9.9E-04
<1.1E-03
<1.0E-03
<2.7E-02
<1.6E-02
<1.1E-02
<8.7E-04
<1.1E-03
<2,6E-03
<2.3E-03
<1.2E-02 8.7E-02
<4.6E-04
<1.3E-03
<6.6E-04
<8.6E-04
<1.0E-03
<3.2E-03
<1.6E-02
<1.2E-02
<8.8E-04
<1.4E-03
<2.OE-03
<2.3E-03
<2.OE-02 8.7E-02
<5.7E-04
<1.3E-03
<7.5E-04
<1.1E-03
<9.OE-04
<2.6E-03
<1.7E-02
<9.7E-03
<9.2E-04
<1.3E-03
<1.9E-03
<2.1 E-03
<1.4E-02 8.7E-02
<3.8E-04
<8.6E-04
<8.5E-04
<7.OE-04
<6.5E-04
<2.7E-03
<1.7E-02
<1.4E-02
<8.2E-04
<1.3E-03
<1.2E-03
<1.9E-03
<1.9E-02 1.1E-01
<5.2E-04
<9.8E-04
<9.8E-04
<1.2E-03
<7.4E-04
<2.7E-03
<1.1E-02
<9.1 E-03
<1.OE-03
<1.3E-03
<2.6E-03
<1.9E-03
<1.4E-02 1.OE-01
<4.9E-04
<1.1E-03
<9.OE-04
<8.6E-04
<9.4E-04
<3.2E-03
<1.1E-02
<1.4E-02
<4.3E-04
<1.2E-03
<1.8E-03
<2.OE-03 Control
<2.7E-02 1.OE-01
<7.5E-04
<1.8E-03
<1.1E-03
<7.3E-04
<1.3E-03
<2.8E-03
<1.8E-02
<1.5E-02
<1.5E-03
<1.8E-03
<2.8E-03
<2.5E-03
<9.OE-03 9.0E-02
<5.5E-04
<1.4E-03
<1.1E-03
<8.5E-04
<6.OE-04
<3.1E-03
<1.8E-02
<9.OE-03
<8.1 E-04
<1.2E-03
<2.3E-03
<2.4E-03 Required LLD 5.OE-2 Required LLD 6.OE-2 Composite Dates 4TH QTR Required LLD 5.0E-2 Required LLD 6.OE-2 20
D.
Surface Water Program Surface water monitoring stations are found at four locations as detailed in Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program. Location N-1.5 provides samples representative of Squaw Creek reservoir surface water at a location beyond significant influence of the plant discharge. Location ESE-1.4 provides samples representative of discharges from Squaw Creek reservoir downstream to Squaw Creek and to Lake Granbury via an installed return line. [NOTE:
The installed return line to Lake Granbury has never been used to send water back to Lake Granbury.] Location NE-7.4 provides samples of Lake Granbury surface water downstream of the discharge from the return line from Squaw Creek reservoir. A control sample is obtained from the Brazos River, upstream of Lake Granbury at location N-19.3. Surface water samples from Squaw Creek reservoir locations were collected weekly and composited for monthly gamma isotopic analysis. Samples from Lake Granbury locations were collected monthly and analyzed by gamma spectrometry. All surface water samples were also composited quarterly by location for tritium analysis.
For the year 2010 all surface water samples were collected as required. Table 7 -- 2010 Environmental Surface Water Tritium and Gamma Isotopic Results contains the reported values. Forty-eight samples were analyzed by gamma spectrometry. All results for the required radionuclides were reported as less than the required LLDs. Sixteen quarterly composited samples were analyzed for tritium. The results of the reported tritium values for Squaw Creek reservoir were in line with expected concentrations.
The tritium values ranged from a high of 1.58E+04 pCi/l to a low of 1.OOE+04 pCi/l. The results from Lake Granbury were all less than the required LLDs as expected. The tritium concentration reported in Squaw Creek is well below the action level of 3.0e+4 pCi/i and is following the expected concentration variations based on fuel cycles, power histories and reservoir makeup due to rain and pump transfers from Lake Granbury. Graph 2 - 2010 Environmental Surface Water Tritium Results indicates the current results and the short-term trend of the tritium concentration in Squaw Creek reservoir. The tritium value varies only slightly and is leveling off which possibly indicates that equilibrium may have been reached or soon will be reached. Graph 3 - Squaw Creek Maximum Tritium Values trends the reservoir tritium concentration since it was first detected in 1990 after Unit 1 startup and is located on page 27. This long-term graph also indicates that equilibrium concentrations may have been obtained. Squaw Creek reservoir tritium is a direct product of the operation of CPNPP and is the only consistent indicator detectable in the environment surrounding Comanche Peak.
21
There should not be any significant changes in the tritium concentrations in the near future and no action levels are anticipated. A review of pre-operational and operational data indicated the 2010 results were both expected and consistent with previous data and that no anomalies had occurred.
Note - On July 1st CPNPP contracted GEL Laboratories to process our REMP samples. They do not analyze for 1-131 in Surface Water as part of the typical REMP sample protocol. 1-131 analysis is not a requirement per ODCM for Surface Water. These values are indicated with an *N/A in Table 7 -- 2010 Environmental Surface Water Tritium and Gamma Isotopic Results.
During the year 2010, there were no exceptions to the Surface Water Program.
22
Table 7 -2010 Environmental Surface Water Tritium and Gamma Isotopic Results (Units of pCill)
SW-5 Date Location 1/26/10 ESE-1.4 2/23/10 ESE-1.4 3/30/10 ESE-1.4 4/27/10 ESE-1.4 5/25110 ESE-1.4 6/29/10 ESE-1.4 7/27/10 ESE-1.4 8/31/10 ESE-1.4 9/28/10 ESE-1.4 10/26/10 ESE-1.4 11/30110 ESE-1.4 12128/10 ESE-1.4 SW-1 1/26/10 N-1.5 2/23/10 N-1.5 3/30/10 N-1.5 4/27/10 N-1.5 5/25/10 N-1.5 6/29/10 N-1.5 7/27/10 N-1.5 8/31/10 N-1.5 9/28/10 N-1.5 10/26/10 N-1.5 11/30/10 N-1.5 12/28/10 N-1.5 SW-4 1/26/10 NE-7.4 2123/10 NE-7.4 3/30/10 NE-7.4 4127/10 NE-7.4 5/25/10 NE-7.4 6/29/10 NE-7.4 7/27110 NE-7.4 8/31/10 NE-7.4 9/28/10 NE-7.4 10/26/10 NE-7.4 11130/10 NE-7.4 12/28/10 NE-7.4 SW-3 1/26/10 N-19.3 2/23/10 N-19.3 3/30/10 N-19.3 4/27/10 N-19.3 5/25/10 N-19.3 6/29/10 N-19.3 7/27/10 N-19.3 8/31/10 N-19.3 9/28/10 N-19.3 10/26/10 N-19.3 11/30/10 N-19.3 12/28/10 N-19.3 Required LLD's Reportable Level H-3 Nuclides Ba-140 Be-7 Co-58 Co-60
<1.0E+01
<2.6E+01
<3.6E+00
<4.1E+00
<6.6E+00
<1.8E+01
<1.7E+00
<1.5E+00 1.5$E+04
<6.5E+00
<1.6E+01
<1.6E+00
<1.4E+00
<7.1 E+00
<1.9E+01
<2.1 E+00
<2.1 E+00
<5.1E+00
<1.3E+01
<1.4E+00
<1.3E+00 1.48E+04
<6.3E+00
<1.5E+01
<1.3E+00
<1.3E+00
<9.8E+00
<1.IE+01 1.29E+04
<1.3E+01
<1.3E+01
<1.1E+01 1.00E+04
<5.1 E+00 Ba-I 40
<1.1E+01
<8.6E+00 1.55E+04
<5.2E+00
<8.4E+00
<8.6E+00 1.50E+04
<6.1 E+00
<1.1E+01
<1.5E+01 1.22E+04
<1.lE+01
<1.1E+01
<9.OE+00 1.20E+04
<6.2E+00 Ba-I 40
<1.1 E+01
-<6.9E+00
<1.20E+03
<1.4E+01
<9.7E+00
<1.OE+01
-0.30E+03
<8.8E+00
<1.OE+01
<1.2E+01
<5.45E+02
<1.2E+01
<9.6E+00
<1.1E+01
<5.7E+02
<6.2E+00 Ba-I 40
<1.4E+01
<1.5E+01
<1.30E+03
<1.5E+01
<1.1E+01
<9.2E+00
<1.30E+03
<1.4E+01
<9.3E+00
<1.4E+01
<5.47+02
<9.6E+00
<1.1E+01
<9.8E+00
<5.SE+02
<6.2E+00 3.00e+03 I.50e+0I 3.00e+04 2.00e+02
<1.5E+01
<1.6E+00
<1.9E+00
<1.6E+01
<1.9E+00
<1.9E+00
<2.0E+01
<2.1E+00
<2.4E+00
<2.OE+01
<2.2E+00
<2.5E+00
<1.8E+04
<2.1E+00
<2.3E+00
<2.1E+01
<2.1E+00
<2.2E+00 Be-7 Co-58 Co-60
<2.7E+01
<2.7E+00
<3.0E+00
<1.8E+01
<2.1E+00
<2.3E+00
<1.2E+01
<1.1E+00
<9.9E-01
<2.2E+01
<2.5E+00
<2.7E+00
<1.7E+01
<2.4E+00
<2.0E+00
<1.4E+01
<1.5E+00
<1.3E+00
<1.7E+01
<1.8E+00
<1.9E+00
<2.1E+01
<2.5E+00
<2.3E+00
<1.8E+01
<2.1E+00
<2.1E+00
<1.7E+01
<2.1E+00
<2.3E+00
<1.6E+01
<1.8E+00
<2.OE+00
<2.3E+01
<2.6E+00
<2.7E+00 Be-7 Co-58 Co-60
<4.0E+01
<5.OE+00
<5.6E+00
<3.7E+01
<4.1 E+00
<4.3E+00
<6.7E+01
<8.9E+00
<7.6E+00
<3.7E+01
<5.4E+00
<5.8E+00
<3.8E+01
<3.4E+00
<3.9E+00
<2.8E+01
<3.1E+00
<3.6E+00
<1.5E+01
<1.7E+00
<1.9E+00
<1.7E+01
<1.8E+00
<1.8E+00
<2.OE+01
<2.1E+00
<2.5E+00
<1.5E+01
<1.7E+00
<1.8E+00
<1.9E+01
<2.2E+00
<2.5E+00
<2.OE+01
<2.5E+00
<2.0E+00 Be-7 Co-58 Co-60
<7.3E+01
<7.1 E+00
<8.4E+00
<4.5E+01
<7.OE+00
<7.9E+00
<5.4E+01
<7.0E+00
<6.8E+00
<6.1E+01
<6.2E+00
<7.3E+00
<3.1E+01
<3.5E+00
<3.4E+00
<2.7E+01
<3.3E+00
<3.3E+00
<1.4E+01
<1.5E+00
<1.7E+00
<2.OE+01
<2.3E+00
<2.2E+00
<1.5E+01
<1.8E+00
<2.1E+00
<1.8E+01
<1.9E+00
<2.OE+00
<1.8E+01
<2.OE+00
<2.1E+00
<2.2E+01
<2.5E+00
<3.OE+00 1.50e+01 1.500+01 1.00e+03 3.00e+02 Cs-134
<2.8E+00
<1.6E+00
<1.3E+00
<2.1EE+00
<1.3E+00
<1.4E+00
<2.0E+00
<2.OE+00
<2.6E+00
<2.7E+00
<2.8E+00
<2.3E+00 Cs-134
<2.5E+00
<1.7E+00
<1.OE+00
<2.4E+00
<1.6E+00
<1.4E+00
<2.2E+00
<2.7E+00
<2.7E+00
<2.6E+00
<2.3E+00
<3.2E+00 Cs-134
<4.8E+00
<4.4E+00
<7.OE+00
<5.8E+00
<4.OE+00
<3.1E+00
<2.1 E+00
<2.4E+00
<2.7E+00
<2.1 E+00
<3.OE+00
<2.5E+00 Cs-1 34
<7.6E+00
<6.1E+00
<5.5E+00
<6.9E+00
<3.1E+00
<2.8E+00
<2.OE+00
<2.8E+00
<2.2E+00
<2.3E+00
<2.4E+00
<3.3E+00 1.50e+01 3.00e+01 Cs-137 Fe-59
<4.3E+00
<8.5E+00
<1.6E+00
<4.1E+00
<1.3E+00
<3.9E+00
<1.8E+00
<5.1E+00
<1.5E+00
<3.OE+00
<1.2E+00
<3.2E+00
<2.7E+00
<3.7E+00
<1.9E+00
<3.5E+00
<2.5E+00
<4.6E+00
<2.2E+00
<5.OE+00
<2.6E+00
<4.9E+00
<2.2E+00
<4.6E+00 Cs-137 Fe-59
<2.9E+00
<7.2E+00
<2.6E+00
<4.8E+00
<1.1E+00
<2.9E+00
<2.4E+00
<6.7E+00
<1.9E+00
<4.4E+00
<1.3E+00
<3.3E+00
<1.7E+00
<4.OE+00
<2.5E+00
<5.4E+00
<2.2E+00
<4.OE+00
<2.2+00
<4.5E+00
<2.1E+00
<3.7E+00
<2.8E+00
<5.9E+00 Cs-1 37 Fe-59
<5.3E+00
<9.8E+00
<3.6E+00
<1.1E+01
<9.4E+00
<1.7E+01
<4.6E+00
<1.2E+01
<4.1E+00
<7.4E+00
<3.6E+00
<9.3E+00
<1.7E+00
<4.0E+00
<2.OE+00
<4.2E+00
<2.2E+00
<4.8E+00
<1.7E+00
<3.8E+00
<2.4E+00
<4.5E+00
<2.OE+00
<5.2E+00 Cs-1 37 Fe-59
<7.9E+00
<1.5E+01
<6.4E+00
<1.1E+01
<5.7E+00
<1.5E+01
<4.6E+00
<1.3E+01
<2.9E+00
<7.5E+00
<3.2E+00
<8.6E+00
<1.6E+00
<3.6E+00
<2.2E+00
<4.5E+00
<1.8E+00
<3.5E+00
<2.OE+00
<4.OE+00
<2.3E+00
<4.6E+00
<2.9E+00
<5.9E+00 1.80e+01 3.00e+01 5.00e+01 4.00e+02 1-131
<1.2E+01
<1.1 E+01
<1.1 E+01
<8.5E+00
<9.2E+00
<1.3E+01
- N/A
- N/A
- N/A
- N/A
- N/A
- N/A 1-131
<1.4E+01
<1.1E+01
<1.2E+01
<1.1E+01
<1.1E+01
<1.2E+01
- N/A
- N/A
- N/A
- N/A
- N/A
- N/A 1-131
<9.2E+00
<7.3E+00
<1.4E+01
<8.6E+00
<1.3E+01
<8.1 E+00
- N/A
- N/A
- N/A
- N/A
- N/A
- N/A 1-131
<1.4E+01
<1.2E+01
<1.1 E+01
<1.2E+01
<9.6E+00
<1.5E+01
- N/A
- N/A
- N/A
- N/A
- N/A
- N/A K-40 La-140
<5.2E+01
<1.OE+01 1.19+01
<6.6E+00
<2.2E+01
<6.5E+00
<3.1E+01
<7.1E+00 2.3E+01
<5.1E+00 2.3E+01
<6.3E+00
<2.5E+01
<3.3E+00
<3.6E+01
<3.5E+00
<3.5E+01
<4.5E+00
<2.6E+01
<4.4E+00
<2.2E+01
<3.9E+00
<2.8E+01
<5.1E+00 K-40 La-1 40
<4.6E+01
<1.1E+01 2.37E+01
<8.6E+00
<1.6E+01
<5.2E+00
<3.7E+01
<8.4E+00
<2.9E+01
<8.6E+00
<1.9E+01
<6.1E+00
<3.1E+01
<3.6E+00
<3.5E+01
<4.8E+00
<3.4E+01
<4.4E+00
<2.2E+01
<4.3E+00
<2.1E+01
<3.2E+00
<4.1E+01
<6.2E+00 K-40 La-1 40
<8.3E+01
<1.1E+01
<5.8E+01
<6.9E+00
<1.1E+02
<1.4E+01
<7.OE+01
<9.7E+00
<5.2E+01
<1.OE+01
<5.7E+01
<8.8E+00
<2.4E+01
<3.4E+00
<3.2E+01
<3.9E+00
<3.5E+01
<4.7E+00
<1.7E+01
<3.4E+00
<2.2E+01
<4.2E+00
<3.0E+01
<6.2E+00 K-40 La-1 40
<1.1E+02
<1.4E+01
<8.8E+01
<1.5E+01
<8.3E+01
<1.5E+01
<8.7E+01
<1.1E+01
<5.1E+01
<9.2E+00
<5.1E+01
<1.4E+01
<1.6E+01
<3,OE+00
<3.1E+01
<4.4E+00
<2.8E+01
<3.3E+00
<1.7E+01
<4.3E+00
<2.OE+01
<2.9E+00
<2.5E+01
<6.2E+00 1.500+01 2.00e+02 Mn-54
<2.6E+00
<1.6E+00
<1.4E+00
<1.9E+00
<1.IE+00
<1.2E+00
<1.6E+00
<1.9E+00
<2.2E+00
<2.3E+00
<2.3E+00
<2.2E+00 Mn-54
<3.2E+00
<1.7E+00
<1.1E+00
<2.3E+00
<1.7E+00
<1.2E+00
<1.8E+00
<2.2E+00
<1.9E+00
<1.8E+00
<1.7E+00
<2.6E+00 Mn-54
<4.3E+00
<3.6E+00
<7.OE+00
<5.3E+00
<1.9E+00
<3.1 E+00
<1.8E+00
<1.7E+00
<2.3E+00
<1.8E+00
<2.2E+00
<2.1 E+00 Mn-54
<6.6E+00
<5.6E+00
<6.4E+00
<6.4E+00
<3.3E+00
<2.9E+00
<1.6E+00
<2.1 E+00
<1.8E+00
<1.8E+00
<1.9E+00
<2.6E+00 1.500+01 1.00e+03 Nb-95 Zn-65 Zr-95
<4.1E+00
<7.OE+00
<7.6E+00
<2.7E+00
<3.4E+00
<2.9E+00
<2.3E+00
<3.2E+00
<2.8E+00
<2.7E+00
<4.3E+00
<3.8E+00
<2.4E+00
<2.5E+00
<2.5E+00
<1.7E+00
<2.6E+00
<2.3E+00
<1.8E+00
<3.8E+00
<2.9E+00
<1.8E+00
<3.8E+00
<3.3E+00
<2.3E+00
<5.1E+00
<4.4E+00
<2.4E+00
<5.1E+00
<4.5E+00
<2.6E+00
<4.8E+00
<4.1E+00
<2.2E+00
<4.6E+00
<4.1E+00 Nb-95 Zn-65 Zr-95
<4.3E+00
<6.4E+00
<5.3E+00
<3.OE+00
<5.4E+00
<3.8E+00
<2.2E+00
<2.9E+00
<2.1E+00
<3.3E+00
<4.8E+00
<4.6E+00
<2.9E+00
<4.OE+00
<3.3E+00
<2.3E+00
<2.5E+00
<2.6E+00
<2.OE+00
<3.9E+00
<3.3E+00
<2.6E+00
<4.9E+00
<4.OE+00
<2.2E+00
<4.1E+00
<3.6E+00
<2.2E+00
<4.1E+00
<3.7E+00
<1.9E+00
<3.9E+00
<3.3E+00
<2.7E+00
<5.6E+00
<4.5E+00 Nb-95 Zn-65 Zr-95
<5.6E+00
<1.3E+01
<8.9E+00
<4.8E+00
<8.4E+00
<6.4E+00
<9.4E+00
<2.7E+01
<1.2E+01
<5.2E+00
<1.3E+01
<1.OE+01
<4.6E+00
<7.4E+00
<6.4E+00
<4.2E+00
<7.OE+00
<6.2E+00
<1.9E+00
<3.7E+00
<3.1E+00
<2.2E+00
<3.5E+00
<3.7E+00
<2.3E+00
<4.8E+00
<4.2E+00
<2.OE+00
<3.2E+00
<3.3E+00
<2.5E+00
<4.9E+00
<4.1E+00
<2.3E+00
<4.5E+00
<3.4E+00 Nb-95 Zn-65 Zr-95
<8.6E+00
<1.9E+01
<1.3E+01
<7.1E+00
<1.3E+01
<1.OE+01
<7.9E+00
<2.2E+01
<1.1E+01
<5.9E+00
<1.5E+01
<8.8E+00
<4.7E+00
<7.2E+00
<6.2E+00
<3.9E+00
<8.3E+00
<5.9E+00
<1.6E+00
<3.2E+00
<2.7E+00
<2.5E+00
<4.5E+00
<4.OE+00
<2.OE+00
<3.4E+00
<3.1E+00
<2.2E+00
<4.OE+00
<3.4E+00
<2.3E+00
<4. 3E+00
<3 8E+00
<2.7E+00
<5.8E+00
<5.6E+00 1.50e+01 3.00e+01 1.50e+01 4.00e+02 3.00e+02 4.00e+02
Graph 2 -- 2010 Environmental Surface Water Tritium Results cm CL 4-0 U()
18000 16000 14000 12000 10000 8000 6000 4000 2000 0
--- N-1 9.3 4-uN-1.5 NE-7.4 ESE-1.4 Mar-10 Jun-10 Sep-10 Dec-10 Month ly/Composite Sample Dates 24
E.
Surface Drinking Water Program Surface drinking water was collected at two monitoring locations. Table 1
-- Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2010 details the location and types of analysis required. Samples of water from Squaw Creek reservoir were collected at the monitoring location NNW-0. 1 and analyzed at detection levels required for drinking water standards even though the water is not allowed to be used as potable water. There is not a surface water drinking source within a mile of CPNPP. Monitoring location N-9.9 was used as a surface drinking water location based on the proximity of the City of Granbury intake to the Granbury potable water system. All surface drinking water samples were collected weekly and then composited for Iodine-131 analysis, gamma isotopic analysis, and gross beta analysis on a monthly basis. Tritium analysis was performed on a quarterly basis.
For the year 2010, all samples were analyzed for gamma emitting radionuclides. The results are reported in Table 8 - Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results.
There were no gamma emitting radionuclides identified in any of the twenty-four composite samples. Tritium reported in Squaw Creek reservoir ranged from 1.46E+04 pCi/I to 1.18E+04 pCi/I and averaged 1.30E+04 pCi/l. Tritium reported from all Lake Granbury water samples indicated less than the required LLD as expected. Graph 4 - 2010 Environmental Surface Drinking Water Tritium Results trends the results reported for the year 2010. Gross Beta results at the indicator location NNW-0. 1 ranged from <1.02E+01 pCi/I to 3.24E+01 pCi/l with an average of 2.25+01 pCi/I. Gross Beta results at the control location N-9.9 ranged from <4.46E+00 pCi/l to 1.58E+01 pCi/I with an average of 8.78E+00 pCi/I. Graph 5 - 2010 Environmental Surface Drinking Water Gross Beta Results trends the gross beta results for the two monitor locations and indicates no influence from Comanche Peak in the levels detected in the two different bodies of water. Past gross beta results for Lake Granbury have been as high as 83 pCi/I. The gross beta results received are within values previously reported and there is no reportable level for gross beta so no action is required at this time.
During the year 2010, there were no exceptions to the Surface Drinking Water Program.
25
Table 8 -- 2010 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results (Units of pCi/I)
Date 1/26/10 2/23/10 3/30/10 4/27/10 5/25/10 6/29/10 7/27/10 8/31/10 9/28/10 10/26/10 11/30/10 12/28/10 1/26/09 2/23/10 3/30/10 4/27/10 5/25/10 6/29/10 7/27/10 8/31/10 9/28/10 10/26/10 11/30/10 12/28/10 SW-6 Location NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 NNW-0.1 SW-2 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 N-9.9 Gross H-3 Beta 3.24E+01 2.69E+01 1.46E+04 3.07E+01 2.93E+01 2.76E+01 1.37E+04 1.66E+01
<1.02E+01 1.24E+01 1.20E+04
<9.98E+01 1.65E+01 1.47E+01 1.18E+04 1.79E+01 Gross H-3 Beta 8.40E+00 8.OOE+00
<1.30E+03 8.90E+00 1.31E+01 7.80E+00
<1.30E+03 5.30E+00
<5.43E+00
<4.46E+00
<5.41E+02 3.02E+00 1.58E+01 8.66E+00
<5.80E+02
<7.25E+00 Nuclides 1-131
<9.9E-01
<9.OE-01
<9.OE-01
<9.8E-01
<9.5E-01
<8.8E-01
<6.OE-01
<4.7E-01
<4.5E-01
<5.6E-01
<5.OE-01
<6.OE-01 1-131
<9.4E-01
<8.OE-01
<6.6E-01
<9.8E-01
<8.8E-01
<9.4E-01
<4.8E-01
<4.8E-01
<4.9E-01
<5.1E-01
<5.QE-Ol
<5.6E-01 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95
<1.2E+01
<3.4E+00
<4.3E+00
<2.8E+00
<2.8E+00
<7.6E+00
<1.2E+01
<2.7E+00
<3.6E+00
<6.4E+00
<5.8E+00
<8.9E+00
<2.5E+00
<2.5E+00
<1.8E+00
<3.4E+00
<5.2E+00
<8.9E+00
<2.OE+00
<3.OE+00
<5.OE+00
<4.2E+00
<7.5E+00
<1.7E+00
<1.5E+00
<1.5E+00
<1.5E+00
<4.1E+00
<7.5E+00
<1.4E+00
<2.1E+00
<3.OE+00
<2.9E+00
<6.9E+00
<2.3E+00
<2.2E+00
<2.3E+00
<2.2E+00
<5.4E+00
<6.9E+00
<2.OE+00
<3.3E+00
<4.OE+00
<4.5E+00
<1.3E+01
<2.9E+00
<3.7E+00
<2.8E+00
<3.3E+00
<1.4E+01
<1.3E+01
<3.3E+00
<5.6E+00
<6.4E+00
<6.6E+00
<1.3E+01
<2.2E+00
<2.OE+00
<2.OE+00
<2.2E+00
<5.8E+00
<1.3E+01
<2.1E+00
<3.4E+00
<5.OE+00
<4.3E+00
<8.7E+00
<1.5E+00
<1.4E+00
<1.7E+00
<1.5E+00
<2.9E+00
<2.5E+00
<1.3E+00
<1.5E+00
<3.2E+00
<2.6E+00
<9.5E+00
<1.9E+00
<1.9E+00
<2.2E+00
<1.7E+00
<3.5E+00
<3.4E+00
<1.7E+00
<1.9E+00
<3.9E+00
<3.4E+00
<1.2E+01
<2.1E+00
<2.3E+00
<2.4E+00
<2.1E+00
<4.3E+00
<4.2E+00
<2.OE+00
<2.1E+00
<4.5E+00
<3.5E+00
<1.2E+01
<2.3E+00
<2.2E+00
<2.8E+00
<2.3E+00
<4.8E+00
<4.4E+00
<2.2E+00
<2.3E+00
<4.8E+00
<4.2E+00
<1.2E+01
<2.1E+00
<2.5E+00
<2.8E+00
<2.2E+00
<4.8E+00
<4.4E+00
<2.1E+00
<2.2E+00
<4.1E+00
<3.9E+00
<4.7E+00
<2.1E+00
<2.5E+00
<2.2E+00
<2.OE+00
<4.7E+00
<4.7E+00
<2.1E+00
<2.3E+00
<4.5E+00
<4.3E+00 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 Mn-54 Nb-95 Zn-65 Zr-95
<1.4E+01
<5.1E+00
<5.2E+00
<5.OE+00
<4.7E+00
<1.3E+01
<1.4E+01
<4.2E+00
<6.2E+00
<1.2E+01
<7.9E+00
<4.8E+00
<1.7E+00
<1.5E+00
<1.5E+00
<1.5E+00
<3.9E+00
<4.8E+00
<1.5E+00
<2.6E+00
<3.1E+00
<2.8E+00
<1.OE+01
<2.1E+00
<1.9E+00
<1.5E+00
<2.OE+00
<4.5E+00
<1.OE+01
<1.7E+00
<2.7E+00
<3.7E+00
<3.7E+00
<1.1E+01
<3.OE+00
<3.2E+00
<2.5E+00
<3.3E+00
<8.3E+00
<1.1E+01
<2.9E+00
<3.8E+00
<6.1E+00
<5.5E+00
<1.3E+01
<3.3E+00
<3.5E+00
<3.OE+00
<3.1E+00
<9.1E+00
<1.3E+01
<2.9E+00
<5.OE+00
<6.2E+00
<6.3E+00
<1.2E+01
<2.4E+00
<2.1E+00
<2.OE+00
<2.2E+00
<5.9E+00
<1.2E+01
<2.OE+00
<2.9E+00
<4.7E+00
<4.5E+00
<7.8E+00
<1.4E+00
<1.6E+00
<1.7E+00
<1.4E+00
<2.8E+00
<2.6E+00
<1.3E+00
<1.4E+00
<2.6E+00
<2.7E+00
<1.5E+01
<1.8E+00
<1.6E+00
<2.OE+00
<1.8E+00
<3.7E+00
<5.OE+00
<1.7E+00
<2.OE+00
<3.2E+00
<3.3E+00
<9.6E+00
<1.8E+00
<2.OE+00
<2.2E+00
<2.OE+00
<3.8E+00
<3.4E+00
<1.6E+00
<1.9E+00
<3.9E+00
<3.1E+00
<1.4E+01
<2.2E+00
<2.1E+00
<2.5E+00
<22E+00
<4.3E+00
<4.1E+00
<2.2E+00
<2.4E+00
<4.5E+00
<4.1E+00
<9.7E+00
<1.9E+00
<2.2E+00
<2.6E+00
<2.3E+00
<4.4E+00
<4.OE+00
<1.9E+00
<2.1E+00
<4.3E+00
<3.6E+00
<4.8E+00
<2.2E+00
<2.OE+00
<2.5E+00
<2.3E+00
<4.5E+00
<4.8E+00
<1.9E+00
<2.4E+00
<4.OE+00
<4.2E+00 Required LLD's Reportable Level 2.OOE+03 4.O0E+00 1.OOE+00 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.80E+01 3.OOE+01 1.50E+01 1.50E+01 1.50E+01 3.OOE+01 1.50E+01 2.OOE+04 None 2.OOE+00 2.OOE+02 1.00E+03 3,OOE+02 3.OOE+01 5.OOE+01 4.OOE+02 2.OOE+02 1.OOE+03 4.OOE+02 3.OOE+02 4.OOE+02 26
Graph 3 -- Squaw Creek Maximum Tritium Values 30000 25000 -
i
- 0. 20000 15000 10000 5000
- Maximum tritium 0
I I
I I
I I
I I
I I
I I
I I
I I
I N?)
N'q Nq N
0(V 0
(V
@0 00~
(V 0
0(V Yearly Maximum 27
4-0 (0) 16(
14(
12(
10C 8(
6(
2(
Graph 4-- 2010 Environmental Surface Drinking Water Tritium Results
)00
)00 -
)00 -
N-9.9
)00
-"- NNW-O. 1
)UU
)00
)00 0
-f
-f p
Mar-10 Jun-10 Sep-10 Dec-10 Composite Sample Dates 28
Graph 5 -- 2010 Environmental Surface Drinking Water Gross Beta Results 0
4I-0 W,
D 3.50E+01 3.OOE+01 2.50E+01 2.OOE+01 1.50E+01 1.OOE+01 5.OOE+O0 O.OOE+O0 NNW-0.1 ej Monthly Data Points 29
F.
Ground Water Program Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2010 specifies the five groundwater monitoring locations. Groundwater supplies in the site area are not affected by plant effluents and are sampled only to provide confirmation that groundwater is not affected by plant discharges.
Groundwater samples were collected quarterly and analyzed for gamma isotopes and tritium at each location.
For the year 2010 a total of twenty groundwater samples were collected from the five different monitoring locations. There were no radionuclides identified in any of the samples. All required LLDs were met for each required gamma emitting radionuclide. Tritium analysis was performed on twenty samples, all indicated less than the required LLD. Results for all the groundwater analyses are reported in Table 9 - 2010 Environmental Groundwater Tritium and Gamma Isotopic Results. These results confirm that plant discharges are having no effect on groundwater in the area surrounding Comanche Peak.
In the first quarter 2010 samples of perched groundwater were taken quarterly in accordance with ENV-323, "TRITIUM GROUNDWATER MONITORING PROGRAM". A sample from the Water Production plant artesian basin had a positive value of 6.45 E-6 microcuries/cc (6450 picocuries/liter) for Tritium. The sample from the Water Production plant leachate pond A had a positive value of 3.62 E-6 microcuries/cc (3620 picocuries/liter) for Tritium. This condition was previously identified and documented on Condition Report CR-2009-1351 (additionally evaluated in CR-2008-00378 1). The source of the tritium detected in Pond A leachate is associated with using the treated clarifier blowdown water for liner testing. This water was pumped into the leachate collection system to fill the space between the two liners to allow detection of possible leakage of the top liner. Treated clarifier blowdown water is essentially SCR water. The tritium levels in Pond A leachate had been trending down since First quater 2009. No further evaluation is necessary.
Note - On July 1Vt CPNPP contracted GEL Laboratories to process our REMP samples. They do notspecifically analyze for 1-131 in Ground Water as part of the typical REMP sample protocol. Results shall be less than the most restrictive isotope (1-131 = 2 pCi/L) as established in table 3.12-2 of the ODCM. These values are indicated with an *N/A in Table 9
- 2010 Environmental Groundwater Tritium and Gamma Isotopic Results.
During the year 2010, there were no exceptions to the Ground Water Program.
30
Table 9 -- 2010 Environmental Groundwater Tritium and Gamma Isotopic Results (Units of pCi/I)
Location Date GW-3 3130/10 SSE-4.6 6/29/10 SSE-4.6 9/28/10 SSE-4.6 12/28/10 SSE-4.6 GW-5 3130/10 N-1.45 6129110 N-1.45 9/28/10 N-1.45 12128/10 N -1.45 GW-4 3/30/10 N-9.8 6/29/10 N-9.8 9/28/10 N-9.8 12/28/10 N-9.8 GW-1 3/30/10 W-1.2 6/29/10 W-1.2 9/28/10 W-1.2 12/28/10 W-1.2 GW-2 3130/10 WSW-0.1 6/29/10 WSW-0.1 9/28/10 WSW-0.1 12128/10 WSW-0.1 Required LLD's Reportable Levels Nuclides H-3 Ba-140 Co-58
<1.2E+03
<1.5E+01
<5.8E+00
<1.2E+03
<9.3E+00
<2.7E+00
<4.3E+02
<1.2E+01
<2.4E+00
<5.1E+02
<4.7E+00
<1.9E+00
<1.2E+03
<1.4E+01
<6.5E+00
<1.2E+03
<1.1E+01
<4.3E+01
<4.3E+02
<1.1E+01
<2.OE+00
<5.1E+02
<4.3E+00
<2.2E+00
<1.2E+03
<1.2E+01
<6.3E+00
<1.2E+03
<1.OE+01
<4.2E+00
<4.3E+02
<1.2E+01
<2.3E+00
<5.1E+02
<5.8E+01
<2,9E+00
<1.2E+03
<1.3E+01
<5.4E+00
<1.2E+03
<8.6E+00
<2.5E+00
<4.3E+02
<1.1E+01
<2.1E+00
<5.1E+02
<3.6E+00
<1.8E+00 1.2E+03
<1.5E+01
<6.5E+00
<1.2E+03
<1.1E+01
<3.3E+00
<4.3E+02
<1.2E+01
<2.1E+00
<5.1E+02
<4.7E+00
<2.3E+00 3.OOE+03 1.50E+01 1.50E+01 2.OOE+04 2.OOE+02 1.OOE+03 Co-60
<7.9E+00
<2.9E+00
<2.3E+00
<2.6E+00
<8.1 E+00
<5.5E+00
<2.3E+00
<2.1 E+00
<7.7E+00
<4.4E+00
<2.4E+00
<3.2E+00
<7.4E+00
<2.4E+00
<2.3E+00
<1.8E+00
<4.5E+00
<3.2E+00
<2.3E+00
<2.3E+00 1.50E+01 3.OOE+02 Cs-I 34
<6.OE+OO
<2.7E+00
<2.8E+00
<2.7E+00
<6.3E+00
<4.9E+00
<2.6E+00
<2.6E+00
<6.6E+00
<4.1 E+00
<2.9E+00
<3.2E+00
<6.1 E+00
<2.2E+00
<2.OE+OO
<2.OE+OO
<7.1 E+00
<2.5E+00
<3.OE+OO
<2.5E+00 1.50E+01 3.OOE+01 Cs-137
<5.8E+00
<2.6E+00
<2.4E+00
<2.3E+00
<8.OE+OO
<4.8E+00
<2.3E+00
<2.2E+OO
<6.OE+OO
<3.8E+00
<2.4E+00
<2.8E+00
<6.3E+00
<2.4E+00
<2.2E+00
<1.8E+00
<5.9E+00
<4.OE+OO
<2.2E+00
<2.OE+OO 1.80E+01 5.00E+01 Fe-59 1-131
<1.4E+01
<8.2E+00
<6.1E+00
<1.5E+01
<4.1E+00
- N/A
<4.3E+00
- N/A
<1.4E+01
<1.3E+01
<1.1E+01
<1.5E+01
<4.OE+00
- N/A
<4.8E+00
- N/A
<1.3E+01
<1.4E+01
<8.6E+00
<1.2E+01
<4.4E+00
- N/A
<5.7E+00
- N/A
<1.3E+01
<1.4E+01
<5.2E+00
<1.4E+01
<4.2E+00
- N/A
<3.7E+00
- N/A
<1.3E+01
<1.2E+01
<6,6E+00
<1.4E+01
<4.6E+02
- N/A
<4.8E+00
- N/A 3.00E+01 1.50E+01 4.OOE+02 2.OOE+01 La-140 Mn-54 Nb-95 Zn-65 Zr-95
<1.5E+01
<6.OE+00
<6.7E+00
<1.9E+01
<1.OE+01
<9.3E+00
<2.7E+00
<4.1E+00
<5.4E+00
<5.OE+00
<4.OE+00
<2.4E+00
<2.6E+00
<5.OE+00
<4.OE+00
<4.7E+00
<1.9E+00
<2.3E+00
<4.5E+00
<3.9E+00
<1.4E+01
<7.OE+00
<8.OE+00
<1.6E+01
<1.1E+01
<1.IE+01
<4.9E+00
<6.1E+00
<1.OE+01
<7.9E+00
<3.1E+00
<2.OE+00
<2.5E+00
<4.1E+00
<4.1E+00
<4.3E+00
<2.1E+00
<2.2E+00
<4.2E+00
<4.4E+00
<1.2E+01
<5.5E+00
<6.6E+00
<1.4E+01
<1.OE+01
<1.OE+01
<4.2E+00
<5.6E+00
<8.2E+00
<7.OE+00
<4.OE+00
<2.3E+00
<2.3E+00
<4.2E+00
<3.9E+00
<5.8E+00
<2.5E+00
<2.8E+00
<5.6E+00
<4.8E+00
<1.3E+01
<7.1E+00
<7.7E+00
<1.5E+01
<1.1E+01
<8.6E+00
<2.4E+00
<3.OE+00
<4.6E+00
<4.2E+00
<3.5E+00
<1.8E+00
<2.2E+00
<4.2E+00
<3.7E+00
<3.6E+00
<1.8E+00
<1.9E+00
<3.7E+00
<3.3E+00
<1.5E+01
<5.8E+00
<8.OE+00
<1.4E+01
<1.2E+01
<1.1E+01
<2.6E+00
<4.OE+00
<6.OE+00
<5.7E+00
<4.OE+00
<2.4E+00
<2.5E+00
<4.9E+00
<4.2E+00
<4.7E+00
<2.OE+00
<2.2E+00
<4.4E+00
<3.5E+00 1.50E+01 1.50E+01 1.50E+01 3.OOE+01 1.50E+01 2.OOE+02 1.OOE+03 4.OOE+02 3.OOE+02 4.OOE+02 31
G.
Sediment Program Shoreline sediments were collected at four different monitoring locations.
One sample location is along the shore of Squaw Creek Reservoir, one sample location is on Squaw Creek down stream of the dam discharge and two locations are along Lake Granbury's shores. Each sample is collected on a six-month frequency and sent to the contract laboratory for analysis by gamma spectrometry.
The process of shoreline sedimentation is a complex evolution whereby potential radionuclides and stable elements may concentrate in the bottom sediment of particular bodies of water. The concentrations are effected by such things as colloidal particles combining with chelating agents and biological action of bacteria and other benthic organisms. Monitoring of the area shorelines provides one of the first and best indicators of radionuclide deposition.
For the year 2010 results from the gamma isotopic analysis of shoreline sediments is reported in Table 10 - 2010 Environmental Sediment Gamma Isotopic Results. As expected and in agreement with previous results from both the pre-operational and operational programs, naturally occurring Potassium-40 was detected in all eight samples. All required radionuclide results were reported as less than the required LLDs. During previous years, both pre-operational and operational, positive indications occasionally had been noted for Cesium-137 and during 2010 there were two positive Cesium-137 results reported. The results were above the required LLD. The only other positive value reported for 2010 was for naturally occurring Beryllium-7. As expected, there were no results in any sediment sample that indicated any direct influence from CPNPP discharges to the local environment.
During the year 2010, there were no exceptions to the Sediment Program.
32
Table 10 -- 2010 Environmental Sediment Gamma Isotopic Results (Units of pCi/kg)
Nuclides Ba-140 Be-7 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Date 1112/10 1/12/10 1/12/10 1/12110 7/6110 7/6/10 7/6/10 7/6/10 Location SE-5.3 NNE-1.0 NE-7.4 N-9.9 SE-5.3 NNE-1I.0 NE-7.4 N-9.9
<1.5E+02 2.89E+02
<2.3E+01
<2.2E+01
<1.9E+01 4.47E+01
<6.OE+01
<6.OE+01 5.1E+03
<7.3E+01
<2.4E+01
<2.9E+01
<1.OE+02
<3.8E+01
<2.1E+02
<3.1E+02
<3.6E+01
<4.5E+01
<3.9E+01 2.08E+02
<1.OE+02
<9.5E+01 7.OE+03
<1.4E+02
<3.4E+01
<5.6E+01
<1.9E+02
<7.9E+01
<1.2E+02
<1.7E+02
<2.4E+01
<1.9E+01
<2.4E+01
<2.2E+01
<3.7E+01
<6.1E+01 1.3E+03
<7.OE+01
<2.4E+01
<3.7E+01
<8.9E+01
<3.6E+01
<1.2E+02
<1.6E+02
<2.OE+01
<1.4E+01
<2.1E+01
<1.8E+01
<3.OE+01
<5.OE+01 2.3E+03
<5.5E+01
<1.9E+01
<2.5E+01
<7.1E+01
<3.9E+01
<3.9E+02
<6.6E+02
<5.4E+01
<8.6E+01
<6.4E+01
<7.6E+01
<1.1E+02
<1.7E+02 6.5E+03
<1.3E+02
<5.7E+01
<5.2E+01
<1.3E+02
<1.2E+02
<4.2E+02
<7.1E+02
<6.9E+01
<7.2E+01
<9.3E+01
<5.6E+01
<1.8E+02
<2.2E+02 7.3E+03
<1.5E+02
<6.6E+01
<8.6E+01
<1.7E+02
<1.5E+02
<5.3E+02
<5.5E+02
<4.4E+01
<6.1E+01
<6.4E+01
<5.6E+01
<1.4E+02
<3.OE+02 5.7E+03
<1.7E+02
<5.5E+01
<7.3E+01
<1.4E+02
<9.OE+01
<3.6E+02
<4.8E+02
<6.6E+01
<5.8E+01
<8.5E+01
<7.7E+01
<9.1E+01
<1.7E+02 5.6E+03
<1.3E+02
<5.8E+01
<8.4E+01
<1.2E+02
<1.3E+02 Required LLD's Reportable Levels 1.50E+02 1.80E+02 None None NOTE:
During previous years, both pre-operational and operational, positive indications occasionally had been noted for Cesium-137 and during 2010 there were two positive Cesium-137 results reported. The results were above the required LLD.
33
H.
Fish Program Fish samples were collected at two locations during the year 2010. One monitoring location is an area approximately two miles east-northeast of the site on Squaw Creek Reservoir. The second location is on Lake Granbury approximately eight miles north-northeast of the site. Fish sampling is scheduled for the months of April and October. The collected fish are frozen and shipped to the independent laboratory where the edible portions are analyzed for gamma emitting radio-nuclides.
For the year 2010, the results of the analysis performed on the collected fish samples are reported in Table 11 -- 2010 Environmental Fish Gamma Isotopic Results. Catfish and Bass samples were analyzed as indicated in the table. There were no positive results reported except for the expected Potassium-40, which is naturally occurring in all living organisms. All required radionuclide results were reported as less than the required LLDs. As a result of the fish-sampling program, there were no anomalies noted and no indication of any influence on the surrounding environment from Comanche Peak plant discharges.
No abnormal results were reported by CPNPP or by the State of Texas. As expected, Potassium-40 was the only positive isotope found.
During the year 2010, there were no exceptions to the Fish Program.
34
Table 11 -- 2010 Environmental Fish Gamma Isotopic Results (Units of pCi/kg wet)
Nuclides Ba-140 Date Location 4120/10 Squaw Creek
<6.4E+01 4/20110 Squaw Creek
<3.8E+01 10112/10 Squaw Creek
<1.8E-01 10/12/10 Squaw Creek
<2.IE-01 4120/10 Lake Granbury
<4.8E+01 4120/10 Lake Granbury
<3.5E+01 10/12/10 Lake Granbury
<2.2E-01 10/12/10 Lake Granbury
<2.3E-01 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-1 40 Mn-54 Nb-95 Zn-65 Zr-95 Fish Type
<2.gE-tOI
<2.7E+01
<1.8E-02
<1.9E-02
<3.9E+01
<3.OE+/-O1
<1.9E-02
<2.1 E-02
<4.2E+01
<3.2E+01
<3.4E+01
<7.7E+01
<4.3E+01 3.2EE+03
<6.4E+01
<3.3E+01
<2.6E+O1
<8.IE+01
<5.7E+OI Catfish
<2.7E+01
<2.2E+01
<2.4E+0O1
<6.IE+01
<4.1E+0 I 3.3E+03
<3.8E+01
<2.7E+01
<2.6E+01
<6.6E+01
<4.4E+OI Bass
<1.5E-02
<l.lE-02
<1.2E-02
<28E-02
<1.3E-01 3.5E+00
<6.1E-02
<1.4E-02
<1.6E-02
<2.5E-02
<2.6E-02 Catfish
<1.6E-02
<1.6E-02
<1.4E-02
<4.9E-02
<IIE-01 2.9E+00
<8.9E-02
<1.4E-02
<1.9E-02
<4.5E-02
<2.1E-02 Bass
<4.8E+01
<2.9E+01
<3.5E+01
<7.2E+01
<5.IE+01 3.OE+03
<4.8E+O1
<3.5E+01
<3.8E+01
<8.9E+01
<6.4E+0O1 Catfish
<3.OE+OI
<3.1E+01
<2.8E+01
<6.7E+01
<4.7E+01 3.4E+03
<3.5E+01
<2.5E+01
<3.2E+01
<6.7E+01
<4.9E+01 Bass
<1.2E-02
<1,8E-02
<1.4E-02
<4.7E-02
<1.7E-01 3.3E+00
<6.1E-02
<1.4E-02
<1.9E-02
<3.1E-02
<3.5E-02 Catfish
<1.8E-02
<1.7E-02
<1.9E-02
<4.2E-02
<1.6E-01 2.8E+00
<7.2E-02
<1.IE-02
<2.3E-02
<4.2E-02
<3.2E-02 Bass Required LLD's Reportable Levels 1.30E-t02 1.30E-t02 1.30E-t02 1.50E-t02 2.60E+/-02 1.00E, 04 I.OE404 I.00E+03 2.OOE-i03 1.00E 04 1.30E+02 3.00F1-04 2.60E+02 2,000-04 35
I.
Food Products Program Food products (pecan) were coliected at the time of harvest. The samples are obtained at monitoring location ENE-9.0 and are shipped to the contract laboratory for gamma isotopic analysis.
For the year 2010, results of the gamma isotopic analyses are reported in Table 12 -- 2010 Environmental Food Products Gamma Isotopic Results.
Naturally occurring Potassium 40 was detected in the sample as expected, and there were no other gamma emitting radionuclides identified.
No abnormal results were reported by CPNPP or by the State of Texas.
As expected, Potassium-40 was the only positive isotope found.
During the year 2010, there were no exceptions to the Food Products Program.
36
Table 12 -- 2010 Environmental Food Products Gamma Isotopic Results (Units of pCi/kg wet)
Food Type - Pecans Nuclides Ba-140 Be-7 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Date Location 11109/10 ENE-9.0
<5.1E+01
<9.9E+01
<1.1E+01
<1.4E+01
<1.4E+01
<1.7E+01
<2.6E+01
<1.8E+01 3.9E+03
<1.7E+01
<1.3E+01
<1.3E+01
<2.5E+01
<2.2E+01 Required LLD's 6.OOE+01 8.00E+01 6.OOE+01 Reportable Levels 1.00E+03 2.O0E+03 1.OOE+02 37
J.
Broadleaf Program Broadleaf sample collection is conducted in accordance with the requirements of the Radiological Environmental Monitoring Program.
The program specifies the sampling based on the absence of milk monitoring locations. One broadleaf control location is located at SW-13.5 in the vicinity of the previous control milk location. The two indicator locations, N-I1.45 and SW-1.0, are located near the site boundaries. The broadleaf samples consist of mainly native grasses and cedar leaves and are analyzed for Iodine-131 and gamma emitting isotopes.
For the year 2010, all radionuclide analysis met their required LLDs and there was no indication of gamma emitting radionuclides. There were no indications of Iodine-131 being detected. The naturally occurring radionuclide of Potassium-40 was found in 36 of 36 samples taken. The radionuclide Beryllium-7 was present in 35 of 36 samples.
No abnormal results were reported by CPNPP or by the State of Texas.
During the year 2010, there was one exception to the Broadleaf Program.
On 04/27/10 a sample was taken at location BL-2 that indicated positive for CO-58 this was due to cross contamination from a Radiation Protection Supervisor work gloves. Condition Report #2010-005641 was generated and gives all the details on the event.
38
Table 13 -- 2010 Environmental Broadleaf Iodine-131 and Gamma Isotopic Results (Units of pCi/kg wet)
Nuclides BL-1 1-131 Ba-140 Be-7 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Date 1/26/10 2/23/10 3/30/10 4/27/10 5/25/10 6/29/10 7/27/10 8/31/10 9/28/10 10/26/10 11/30/10 12/28/10 1/26/10 2/23/10 3/30/10 4/27/10 5/25/10 6/29/10 7/27/10 8/31/10 9/28/10 10/26/10 11/30/10 12/28/10 1/26/10 2/23/10 3/30/10 4/27/10 5/25/10 6/29/10 7/27/10 8/31/10 9/28/10 10/26/10 11/30/10 12/28/10 Location N-1.45 N-1.45 N-1.45 N-1.45 N-1.45 N-1.45 N-1.45 N-1.45 N-1.45 N-1.45 N -1.45 N -1.45
<5.1E+01
<1.9E+02 5.2E+03
<5.2E+01
<8.OE+01 1.1E+03
<5.4E+01
<2.8E+02 6.1E+03
<5.1E+01
<1.2E+02 5.6E+03
<5.2E+01
<7.8E+01 8.3E+02
<5.5E+01
<2.OE+02 7.6E+02
<3.1E+01
<7.8E+01 7.8E+02
<5.5E+01
<1.7E+02 6.5E+02
<3.7E+01
<1.1E+02 6.8E+03
<3.OE+01
<9.3E+01 1.4E+03
<2.OE+01
<6.5E+01 9.3E+02
<2.OE+01
<2.OE+01 3.2E+03
<6.3E+01
<6.1E+01
<3.8E+01
<4.OE+01
<5.4E+01
<4.8E+01
<3.8E+01
<4.OE+01
<3.5E+01
<3.6E+01
<4.4E+01
<5.1E+01
<1.7E+01
<2.OE+01
<3.7E+01
<4.4E+01
<2.3E+01
<2.2E+01
<2.2E+01
<2.5E+01
<1.3E+01
<1.5E+01
<1.2E+01
<1.4E+01
<5.5E+01
<3.1E+01
<5.OE+01
<3.6E+01
<3.3E+01
<4.4E+01
<2.1 E+01
<4.6E+01
<2.8E+01
<2.9E+01
<1.6E+01
<1.5E+01
<5.2E+01
<1.4E+02
<3.1E+01
<7.6E+01
<5.1E+01
<1.2E+02
<3.5E+01
<9.2E+01
<3.2E+01
<7.3E+01
<4.3E+01
<1.2E+02
<1.7E+01
<3.3E+01
<6.3E+01
<8.3E+01
<2.4E+01
<4.8E+01
<2.2E+01
<4.8E+01
<1.3E+01
<3.1E+01
<1.4E+01
<2.3E+01 4.3E+03
<1.9E+02 2.9E+03
<8.OE+01 3.2E+03
<2.8E+02 3.5E+03
<1.2E+02 3.1E+03
<7.8E+01 4.6E+03
<2.OE+02 3.8E+03
<2.9E+01 9.3E+03
<6.2E+01 2.3E+03
<3.9E+01 4.6E+03
<3.2E+01 2.4E+03
<1.5E+01 5.OE+02
<2.OE+01
<5.5E+01
<3.4E+01
<4.6E+01
<3.4E+01
<3.OE+01
<4.8E+01
<1.4E+01
<4.OE+01
<2.3E+01
<2.1E+01
<1.4E+01
<1.2E+01
<9.3E+01
<1.8E+02
<3,8E+01
<1.2E+02
<7.6E+01
<9.9E+01
<5.OE+01
<9.OE+01
<4.1E+01
<7.6E+01
<5.8E+01
<1.3E+02
<1.8E+01
<3.8E+01
<3.6E+01
<8.8E+01
<2.3E+01
<5.1E+01
<2.6E+01
<5.1E+01
<1.5E+01
<3.3E+01
<1.2E+01
<2.5E+01
<1.1E+02
<6.4E+01
<1.OE+02
<7.6E+01
<5.4E+01
<8.7E+01
<3.OE+01
<6.7E+01
<4.4E+01
<4.4E+01
<2.5E+01
<2.1E+01 BL-3 1-131 Ba-140 Be-7 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Control SW-13.5 SW-13.5 SW-3.5 SW-13.5 SW-13.5 SW-13.5 SW-13.5 SW-13.5 SW-13.5 SW-13.5 SW-13.5 SW-13.5
<5.6E+01
<1.7E+02 6.1EE+02
<4.3E+01
<1.4E+02 2.7E+03
<4.9E+01
<2.6E+02 7.9E+03
<4.4E+01
<1.5E+02 1.1E+03
<5.1E+01
<1.6E+02 3.2E+03
<4.5E+01
<1.9E+02 9.4E+02
<2.OE+01
<5.7E+01 9.6E+02
<4.3E+01
<1.2E+02 2.6E+03
<3.7E+01
<1.2E+02 1.2E+03
<4.1E+01
<1.2E+02 318E+03
<3.2E+01
<8.5E+01 4.7E+03
<2.5E+01
<2.2E+01 1.9E+03
<4.9E+01
<4.9E+01
<5.8E+01
<6.OE+01
<5.6E+01
<6.3E+01
<5.3E+01
<4.6E+01
<5.2E+01
<4.8E+01
<4.2E+01
<3.8E+01
<1.1E+01
<1.4E+01
<2.4E+01
<2.5E+01
<2.4E+01
<2.7E+01
<2.3E+01
<2.5E+01
<1.8E+01
<2.OE+01
<1.5E+01
<1.7E+01
<5.7E+01
<4.5E+01
<5.9E+01
<4.5E+01
<5.2E+01
<3.2E+01
<1.4E+01
<3.OE+01
<3.OE+01
<2.8E+01
<2.OE+01
<1.8E+01
<4.4E+01
<1.1E+02
<6.2E+01
<1.2E+02
<6.OE+01
<1.5E+02
<4.2E+01
<1.3E+02
<4.7E+01
<1.1E+02
<3.1E+01
<1.1E+02
<1.2E+01
<2.1E+02
<2.4E+01
<5.8E+01
<2.4E+01
<5.OE+01
<2.4E+01
<5.2E+01
<1.7E+01
<3.6E+01
<1.6E+01
<2.3E+01 2.6E+03
<1.7E+02 5.2E+03
<1.4E+02 9.9E+02
<2.6E+02 5.4E+03
<1.5E+02 5.4E+03
<1.6E+02 5.9E+03
<1.9E+02 3.4E+03
<1.8E+01 1.2E+04
<3.5E+01 7.5E+03
<3.7E+01 5.1E+03
<4.1E+01 4.5E+03
<2.9E+01 3.2E+03
<2.2E+01
<4.6E+01
<5.OE+01
<5.3E+01
<4.5E+01
<4.9E+01
<3.4E+01
<1.1E+01
<2.4E+01
<2.4E+01
<2.3E+01
<1.8E+01
<1.5E+01
<7.8E+01
<1.5E+02
<6.5E+01
<1.3E+02
<7.7E+01
<2.OE+02
<5.9E+01
<1.2E+02
<6.OE+01
<2.OE+02
<5.9E+01
<8.7E+01
<1.3E+01
<2.8E+01
<2.3E+01
<5.8E+01
<2.5E+01
<5.2E+01
<2.4E+01
<5.4E+01
<1.7E+01
<4.OE+01
<1.7E+01
<3.6E+01
<9.7E+01
<8.7E+01
<1.1E+02
<8.8E+01
<7.9E+01
<7.5E+01
<2.2E+01
<4.3E+01
<4.3E+01
<4.1E+01
<3.OE+01
<2.8E+01 BL-2 1-131 Ba-140 Be-7 Co-58 Co-60 Cs-134 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 SW-1.0 SW-1.0 SW-1.0 SW-1.0 SW-1.0 sw-1.0 SW-1.0 SW-1.0 sw-1.O SW-1.0 SW-1.0 SW-1.0
<5.6E+01
<2.1E+02 1.5E+03
<5.5E+01
<1.2E+02 9.6E+03
<5.8E+01
<2.2E+02 7.3E+04
<4.4E+01
<1.3E+02 9.5E+02
<3.9E+01
<3,9E+01 1.9E+03
<4.8E+01
<2.5E+02
<6.2E+02
<2.8E+01
<8.2E+01 1.OE+03
<4.5E+01
<1.4E+02 3.1E+03
<1.8E+01
<5.2E+01 1.3E+03
<2.6E+01
<7.5E+01 9.OE+02
<4.OE+01
<1.OE+02 4.6E+03
<2.3E+01
<2.5E+01 2.3E+03
<6.4E+01
<5.9E+01
<5.2E+01
<5.OE+01
<5.8E+01
<6.4E+01 5.1E+01
<4.1E+01
<2.OE+01
<2.1E+01
<6.OE+01
<6.OE+01
<1.7E+01
<1.8E+01
<2.6E+01
<2.8E+01
<1.1E+01
<1.2E+01
<1.7E+01
<1.9E+01
<2.OE+01
<2.2E+01
<1.4E+01
<1.9E+01
<4.8E+01
<4.9E+01
<5.7E+01
<3.5E+01
<2.1 E+01
<4.9E+01
<2.OE+01
<3.1 E+01
<1.5E+01
<2.1E+01
<2.6E+01
<1.8E+01
<6.5E+01
<1.8E+02
<4.7E+01
<1.2E+02
<6.OE+01
<1.4E+02
<3.6E+01
<1.2E+02
<2.2E+01
<4.2E+01
<4.8E+01
<1.5E+02
<1.7E+01
<3.5E+01
<2.8E+01
<6.5E+01
<1.1E+01
<2.4E+01
<1.7E+01
<4.2E+01
<2.1E+01
<4.2E+01
<1.6E+01
<3.3E+01 2.OE+03
<2.1E+02 1.4E+03
<1.2E+02 6.7E+02
<2.2E+02 4.3E+03
<1.3E+02 4.OE+03
<3.9E+01 3.4E+03
<2.5E+02 3.2E+03
<2.6E+01 8.3E+03
<5.1E+01 4.OE+03
<1.7E+01 4.8E+03
<2.7E+01 3.7E+03
<3.4E+01 3.OE+03
<2.5E+01
<4.4E+01
<4.7E+01
<5.5E+01
<3.9E+01
<2.1E+01
<5.2E+01
<1.6E+01
<2.8E+01
<1.1E+01
<1.7E+01
<2.OE+01
<1.5E+01
<8.1E+01
<1.6E+02
<7.5E+01
<2.4E+02
<7.1E+01
<1.5E+02
<3.9E+01
<1.2E+02
<2.6E+01
<4.5E+01
<8.6E+01
<1.2E+02
<1.6E+01
<3.1E+01
<2.7E+01
<6.OE+01
<1.2E+01
<2.4E+01
<1.7E+01
<4.4E+01
<2.2E+01
<4.4E+01
<1.5E+01
<3.5E+01
<1.1E+02
<9.2E+01
<1.OE+02
<5.9E+01
<3.5E+01
<1.1E+02
<2.7E+01
<4.8E+01
<2.OE+01
<2.7E+01
<3.7E+01
<2.5E+01 Required LLD's Reportable Levels 6.OOE+01 1.0OE+02 6.OOE+0I 8.OOE+0I 1.OOE+03 2.OOE+03 39
K.
Conclusions For the year 2010, based on the results presented in this report and from comparisons with the pre-operational and operational program results from previous years, it can be concluded that the impact of Comanche Peak on the environment is very small. The only indication directly attributable to Comanche Peak is the tritium detected in Squaw Creek reservoir.
Gross beta trend indications concerning Squaw Creek Reservoir are consistent with previous values and do not indicate any increase due to influence from Comanche Peak. Future data will be evaluated as it is received and changes will be addressed as necessary.
The atmospheric environment was sampled for airborne particulate matter, radioiodine and direct radiation. The terrestrial environment was sampled using groundwater, surface drinking water, food products and broadleaf vegetation. The aquatic environment was sampled using surface water, fish and shoreline sediments. The analyses of all these samples provided results that were below the measurement detection limits, or were indicative of expected natural terrestrial and cosmogenic levels, except for the tritium in the water samples of Squaw Creek reservoir. The tritium in Squaw Creek reservoir is reaching equilibrium and is expected to remain well below the reportable level.
There were no values reported during the year 2010 that exceeded any NRC reportable limit.
L.
Inter Laboratory Comparison and Cross Check Program Areva NP Environmental Laboratory Areva NP recently published "Analytical Service Annual Quality Assurance Status Report January-December 2010" which included current interlaboratory comparison results and two year trends as appropriate.
These reports explain the Quality Control Program used by Areva NP during their respective time periods. Interlaboratory and third party quality control programs included the Environmental Crosscheck Program administered by Analytics, Inc., the Environmental Resource Associates (ERA) Proficiency Test (PT), the Department of Energy (DOE) Quality Assessment Program (QAP) and the Mixed Analyte Performance Evaluation Program (MAPEP). Areva NP also conducts an internal Quality Control Program that includes QC functions such as instrumentation checks, blank samples, instrumentation backgrounds, duplicates, staff qualification analysis and process controls.
40
Extensive details of the results of the various interlaboratory and cross check programs are contained in the report mentioned above. A summary of the reporting period is reported below:
Environmental Monitoring Programs (REMP) 99.2% of 617 individual QC analyses evaluated during this annual period met E-LAB acceptance criteria for bias.
100.0% of 500 QC analyses met the Laboratory QC acceptance criteria for precision.
Result Summary During this annual reporting period, thirty-one nuclides associated with eight media types were analyzed by means of the E-LAB's internal process control, MAPEP, ERA/ELAP and by Eckert & Ziegler Analytics QC programs. Media types representative of client company analyses performed during this reporting period were selected.
Presented below is a synopsis of the media types evaluated:
Air Filter Charcoal (Air Iodine)
Water Milk Sediment/soil Vegetation Fish Smears Analytics Environmental Cross Check Program During this period the Eckert & Ziegler Analytics cross check program provided 332 individual environmental analyses for bias and 332 for precision evaluation (Table 1). Of the 332 analyses evaluated for bias, 98.5% (327/332) of all results fell within E-LAB acceptance criteria. Of the 332 analyses evaluated for precision, 100% (332/332) fell within E-LAB tolerance limits. Using the E-LAB's internal acceptance criteria as the basis of evaluation, 109 out of 110 mean results were within agreement criteria. The single failure pertained to the Sr-90 analysis of the 1 St quarter 2010 water sample and was addressed by Condition Report (CR) 10-26.
Process Control Program for REMP Analyses The E-Lab internal (intra-laboratory) process control program evaluated 285 individual analyses for bias and 108 analyses for precision for standard REMP media and nuclides. The results are summarized in Table
- 5. Of the 285 internal process control analyses evaluated for bias, 100%
met Laboratory acceptance criteria. Also, 100% of the 108 results for precision were found to be acceptable.
41
Analytical Blanks During this reporting period, statistically positive activity, (activity greater than three (3) times the standard deviation) was reported for one of the 108 environmental analytical blanks analyzed. One gross beta blank was positive. All client samples in this sample batch were reprocessed.
Overall Data Summary for the Reporting Period January-September 2010 Six hundred thirty-three of 640 individual results evaluated to internal E-LAB performance criteria (98.9%) fell within the E-LAB bias acceptance criteria, while 99.6% of the 552 analyses passed the acceptance criteria for precision.
Status of Condition Reports (CR)
Twenty-two condition reports were closed and fourteen were opened during this reporting period. As of October 12, 2010, no CRs pertaining to environmental processing remain open.
Status of Audits/Assessments Internal The annual management review (Internal Assessment 10-01) was conducted in March, 2010. This assessment is a NELAC and NVLAP requirement. No findings resulted from this assessment. Two observations were addressed and the assessment is closed. Internal Assessment 10-02 evaluated areas of the E-Lab Quality Assurance Program applicable to NVLAP accreditation and environmental dosimetry processing. Three recommendations were entered into the E-Lab task tracking system.
External No external audits of the E-Lab pertaining to environmental monitoring were conducted in 2010 The independent laboratory, Areva, satisfies the requirements of the ODCM by their participation in the inter-laboratory and cross check programs docurhented in their annual report.
42
GEL Laboratories LLC On June 3 0th of 2010 Areva NP Environmental Laboratory no longer accepted REMP samples for analysis. Starting on July 1 st GEL Laboratories LLC is the independent contract laboratory that processes the radiological environmental monitoring samples collected by CPNPP. The contract laboratory is required to participate in an Interlaboratory Comparison Program in accordance with the ODCM Control 3.12.3. GEL participates in multiple programs to ensure all environmental media sent to them are analyzed to the proper standards.
GEL Laboratories, LLC (GEL) is a privately owned environmental laboratory. GEL was established as an analytical testing laboratory in 1981. Now a full service lab, our analytical divisions use state of the art equipment and methods to provide a comprehensive array of organic, inorganic, and radiochemical analyses.
GEL administers the QA program in accordance with the Quality Assurance Plan, GL-QSB-001. Their Quality Systems include all quality assurance (QA) policies and quality control (QC) procedures necessary to plan, implement, and assess the work they perform. GEL's QA Program establishes a quality management system (QMS) that governs all of the activities of their organization.
Summary of Data Results During 2010, forty-three radioisotopes associated with six matrix types were analyzed under GEL's Performance Evaluation program in participation with ERA, MAPEP, NYSDOH ELAP and Eckert & Ziegler Analytics. Matrix types were representative of client analyses performed during 2010. The list below contains the type of matrix evaluated by GEL:
Air Filter Cartridge Water Milk Soil Vegetation Summary of Participation in the Eckert & Ziegler Analytics Environmental Cross-Check Program During 2010, Eckert & Ziegler Analytics provided samples for 106 individual environmental analyses. Of the 106 analyses, 99% (105 out of 106) of all results fell within the PT provider's acceptance criteria. The only analytical failure occurred with the analysis of Iron-59 in milk.
43
Quality Control Program for REMP Analyses GEL's internal (intra-laboratory) quality control program evaluated 1590 individual analyses for bias and 1591 analyses for precision for standard REMP matrix and radionuclides. Of the 959 internal quality control analyses evaluated for bias, 100% met laboratory acceptance criteria. In addition, 100% of the 1591 results for precision were found to be acceptable. GEL performs low-level analysis specifically for Tritium in water. All 2010 analyses were within the acceptance criteria.
Corrective Action Request and Report (CARR)
There are two categories of corrective action at GEL. One is corrective action implemented at the analytical and data review level in accordance with the analytical SOP. The other is formal corrective action documented by the Quality Systems Team in accordance with GLQS-E-002. A formal corrective action is initiated when a nonconformance reoccurs or is so significant that permanent elimination or prevention of the problem is required. GEL includes quality requirements in most analytical standard operating procedures to ensure that data are reported only if the quality control criteria are met or the quality control measures that did not meet the acceptance criteria are documented. A formal corrective action is implemented according to GL-QS-E-002 for Conducting Corrective/Preventive Action and Identifying Opportunities for Improvement. Recording and documentation is performed following guidelines stated in GL-QS-E-012 for Client NCR Database Operation.
Any employee at GEL can identify and report a nonconformance and request that corrective action be taken. Any GEL employee can participate on a corrective action team as requested by the QS team or Group Leaders.
The steps for conducting corrective action are detailed in GL-QS-E-002.
In the event that correctness or validity of the laboratory's test results in doubt, the laboratory will take corrective action. If investigations show that the results have been impacted, affected clients will be informed of the issue in writing within five (5) calendar days of the discovery.
44
Quality Assurance Program for Internal and External Audits During each annual reporting period, at least one internal assessment is conducted in accordance with the pre-established schedule from Standard Operating Procedure for the Conduct of Quality Audits, GL-QS-EOO 1.
The annual internal audit plan is reviewed for adequacy and includes the scheduled frequency and scope of quality control actions necessary to GEL's QA program. Internal audits are conducted at least annually in accordance with a schedule approved by the Quality Systems Director.
Supplier audits are contingent upon the categorization of the supplier, and may or may not be conducted prior to the use of a supplier or subcontractor. Type I suppliers and subcontractors, regardless of how they were initially qualified, are re-evaluated at least once every three years. In addition, prospective customers audit GEL during pre-contract audits.
GEL hosts several external audits each year for both our clients and other programs. These programs include environmental monitoring, waste characterization, and radiobioassay. The following list of programs may audit GEL at least annually or up to every three years depending on the program.
- NELAC, National Environmental Laboratory Accreditation Program DOECAP, U.S. Department of Energy Consolidated Audit Program
" DOELAP, U.S. Department of Energy Laboratory Accreditation Program
- DOE QSAS, U.S. Department of Energy, Quality Systems for Analytical Services
- ISO/IEC 17025 45
Appendix A Comanche Peak Nuclear Power Plant Land Use Census 2010 COPY 46
COMANCHE PEAK NUCLEAR POWER PLANT LAND USE CENSUS 2010 The Land Use Census identified receptors within a five (5) mile radius of the plant in each of the sixteen (16) meteorological sectors. The Land Use Census was conducted July 19th, 2 0 'h, and 2 1st, 2010 and includes the following items:
- 1.
Evaluation of the 2010 Land Use Census
- 2.
Nearest Resident by Sector, Distance, X/Q and D/Q
- 3.
Nearest Garden by Sector, Distance and D/Q
- 4.
Nearest Milk Animal by Sector, Distance and D/Q
- 5.
Population by Sector and Distance
- 6.
Environmental Sample Locations Table
- 7.
Environmental Monitoring Locations Map - 2 Mile Radius*
- 8.
5 Mile Sector and Road Map with Field Data*
- These maps are vaulted along with this census. Copies of this census will not contain a copy of these maps unless specifically requested.
47
Evaluation of the 2010 Land Use Census The results of the 2010 Land Use Census were reviewed for impact on the Radiological Environmental Monitoring Program (REMP). The specific areas reviewed, that could be affected by changes found in the land use census, were the sampling requirements for milk, broadleaf vegetation and food products.
Reviewing the milk sampling requirements from the ODCM Table 3.12-1 requires that samples are to be obtained from milking animals in three locations within a 5 km distance having the highest potential dose. If none are available, samples are acceptable from milking animals in locations 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year.
A sample is also required at a control location.
There are currently no identified milking animals (cow or goat) within the specified distances therefore, there will be no milk sampled during the year 2010.
No milk samples are available, the broadleaf vegetation sampling specified in ODCM Table 3.12-1 is being performed. Broadleaf sample requirements are such that samples of broadleaf vegetation are to be collected from each of two offsite locations of the highest predicted annual average D/Q if milk sampling is not performed at all the required locations. Currently, broadleaf vegetation samples are collected at two indicator locations (N - 1.45 and SW - 1.0) and one control location (SW - 13.5). These indicator locations are near the site boundary in sectors where broadleaf vegetation is available and D/Q is high. Therefore, no change to the broadleaf sampling program is required.
Food product sample requirements of ODCM Table 3.12-1 requires that one sample of each principal class of food product be collected from any area that is irrigated with water in which liquid plant waste has been discharged. Of the gardens identified in the land use census, no gardens are located in any area that irrigates with water in which liquid plant wastes are discharged. Currently, food products are sampled from one indicator location (ENE - 9.0) when in season. The indicator location for ENE-9.0 for pecans at time of harvest will be continued since it is a major source of food products sold to the public.
The 2010 Land Use Census did not identify any locations within 5 miles with a garden of greater than 500 ft2 producing broadleaf vegetation as outlined in CPNPP procedures and Comanche Peak Steam Electric Station Offsite Dose Calculation Manual. The sampling is based on identified locations that would yield a calculated dose or dose commitment 20% greater than established when initial control sampling was performed.
Calculated values for the associated X/Q and D/Q values for each controlling receptor location and pathway are included along with the receptor distances in the data tables of this land use census. The values used to determine potential dose due to radioactive effluent discharges are the highest calculated values based on annual average values. The annual average X/Q used for dose calculations is 3.30E-6, tritium X/Q is 4.36E-6, and the D/Q value is 3.34 E-8. All these values are conservative based on the 2010 Land Use Census data and therefore no changes are required in the dose calculation parameters as verified by the field data.
- X/Q units are Sec/cubic meter
- D/Q units are inverse square meters 48
Nearest Resident by Sector, Distance, X/Q and D/Q Sector Distance (Miles)
X/Q D/Q N
2.2 9.28E-07 5.32E-09 NNE 2.2 5.58E-07 2.90E-09 NE 2.2 3.92E-07 1.42E-09 ENE 2.4 2.58E-07 7.08E-10 E
2.4 3.02E-07 6.62E-10 ESE 2.0 4.7E-07 1.20E-09 SE 1.9 8.28E-07 3.38E-09 SSE 1.5 1.1OE-06 6.60E-09 S
1.5 8.50E-07 5.20E-09 SSW 2.1 3.52E-07 1.56E-09 SW 1.1 1.40E-06 6.5E-09 WSW 1.0 1.80E-06 6.50E-09 W
1.6 7.64E-07 2.50E-09 WNW 2.8 4.07E-07 1.18E-09 NW 2.7 6.98E-07 2.24E-09 NNW 2.5 8.4E-07 3.6E-09 Note: The Annual Average X/Q used for dose calculations is 3.30E-06 sec/cubic meter.
The Tritium value X/Q used for dose calculations is 4.36E-06 sec/cubic meter.
The Annual Average D/Q used for dose calculations is 3.34E-08 inverse square meters.
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Nearest Garden by Sector, Distance and D/Q Sector Distance (Miles)*
D/Q N
None None NNE None None NE None None ENE None None E
None None ESE None None SE None None SSE None None S
None None SSW None None SW None None WSW None None W
None None WNW None None NW None None NNW None None
- There are currently no gardens.
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Nearest Milk Animal by Sector, Distance and D/Q Sector Distance (Miles)*
D/Q N
None None NNE None None NE None None ENE None None E
None None ESE None None SE None None SSE None None S
None None SSW None None SW None None WSW None None W
None None WNW None None NW None None NNW None None
- No Milk samples are currently being collected.
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Population by Sector and Distance Sector 0-1 1-2 2-3 3-4 4-5 Total N
24 93 117 NNE 13 98 24 135 NE 51 125 290 466 ENE 154 8
48 210 E
88 27 39 154 ESE 59 72 157 288 SE 16 120 208 86 430 SSE 80 94 86 2157 2417 S
43 118 62 133 356 SSW 6
54 60 SW 70 8
59 48 185 WSW 349 3
16 3
371 W
14 8
32 27 81 WNW 46 75 121 NW 11 3
14 NNW 59 35 94 TOTAL 572 733 922 3272 5499 Based on an average of 2.66 residents per house, this average was obtained from North Central Texas Council of Governments for Hood and Somervell Counties and is derived from an average of residents per house of 2.57 and 2.74, respectively.
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Environmental Sample Locations Table Sampling Point Location Sample Type*
Al N-1.45 (Squaw Creek Park)
A A2 N-9.4 (Granbury)
A A3 E-3.5 (Children's Home)
A A4 SSE-4.5 (Glen Rose)
A A5 S/SSW-1.2 A
A6 SW-12.3 (CONTROL)
A A7 SW/WSW-0.95 A
A8 NW-1.0 A
RI N-1.45 (Squaw Creek Park)
R R2 N-4.4 R
R3 N-6.5 R
R4 N-9.4 (Granbury)
R R5 NNE-1.1 R
R6 NNE-5.65 R
R7 NE-1.7 R
R8 NE-4.8 R
R9 ENE-2.5 R
RIO ENE-5.0 R
R11 E-0.5 R
R12 E-1.9 R
R13 E-3.5 (Children's Home)
R R14 E-4.2 R
R15 ESE-1.4 R
R16 ESE-4.7 R
R17 SE-1.3 R
R18 SE-3.85 R
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Environmental Sample Locations Table (cont.)
Sampling Point Location Sample Type*
R19 SE-4.6 R
R20 SSE-1.3 R
R21 SSE-4.4 (Glen Rose)
R R22 SSE-4.5 (Glen Rose)
R R23 S-1.5 R
R24 S-4.2 R
R25 SSW-I.]
R R26 SSW-4.4 (State Park)
R R27 SW-0.9 R
R28 SW-4.8 (Girl Scout Camp)
R R29 SW-12.3 (CONTROL)
R R30 WSW-1.0 R
R31 WSW-5.35 R
R32 WSW-7.0 (CONTROL)
R R33 W-1.0 R
R34 W-2.0 R
R35 W-5.5 R
R36 WNW-1.0 R
R37 WNW-5.0 R
R38 WNW-6.7 R
R39 NW-1.0 R
R40 NW-5.7 R
R41 NW-9.9 (Tolar)
R R42 NNW-1.35 R
R43 NNW-4.6 R
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Sampling Point SWI SW2 SW3 SW4 SW5 SW6 GW1 GW2 GW3 GW4 GW5 Environmental Sample Locations Table (cont.)
Location N-1.5 (Squaw Creek Reservoir Marina)
N-9.9 (Lake Granbury)
N-19.3 (CONTROL-Brazos River)
NE-7.4 (Lake Granbury)
ESE-1.4 (Squaw Creek Reservoir)
NNW-0. 1 (Squaw Creek Reservoir)
W-1.2 (NOSF Potable Water)
WSW-0. 1 (Plant Potable Water)
SSE-4.6 (Glen Rose)
N-9.8 (Granbury)
N-1.45 (Squaw Creek Park)
NNE-1.0 (Squaw Creek Reservoir)
N-9.9 (Lake Granbury)
NE-7.4 (Lake Granbury)
SE-5.3 (Squaw Creek)
ENE-2.0 (Squaw Creek Reservoir)
NNE-8.0 (Lake Granbury)
ENE-9.0 (Leonard Bros. Pecan Farm)
SW SW/DW1 SW SW SW2 SW!DW3 Sample Type*
SS1 SS2 SS3 SS4 F]
F2 FPI GW GW3,4 GW 4
F FP 55
Environmental Sample Locations Table (cont.)
Sampling Point Location Sample Type*
BLI BL2 BL3 N-1.45 SW-1.0 BL BL 5
BL5 SW-13.5 (CONTROL)
- Sample Type:
A - Air Sample; R - Direct Radiation; SW - Surface Water; DW - Drinking Water GW - Ground Water; SS - Shoreline Sediments; M - Milk; F - Fish; FP - Food Products; BL - Broadleaf Vegetation NOTES:
- 1) The municipal water system for the City of Granbury is supplied by surface water from Lake Granbury (location SW2) and ground water (location GW4).
Each of these supplies is sampled. These samples are not required for compliance with Radiological Effluent Control 3/4.12.1, Table 3.12-1, because they are not affected by plant discharges.
- 2) This sample (location SW6) is representative of discharges from Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury if used.
- 3) Plant potable water could be supplied by surface water from Squaw Creek Reservoir (location SW6) but is normally supplied by ground water from onsite wells (location GW2). Each of these possible sources of water are sampled.
- 4) Ground water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 and are therefore not required to be monitored for radioactivity to meet the requirements of the Radiological Effluent Control 3/4.12.1, Table 3.12-1.
- 5) Broadleaf sampling will be performed at the specified locations if milk samples are unavailable from any location.
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Environmental Sample Locations Map - 2) Mile Radius
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