Text

Transmittal of Year 2009 Radiological Environmental Operating Report
	ML101260142
Person / Time
Site:	Comanche Peak
Issue date:	04/29/2010
From:	Flores R; Luminant Generation Co, Luminant Power
To:	; Document Control Desk, Office of Nuclear Reactor Regulation
References
	CP-201000646, TXX-10067
	Download: ML101260142 (55)
	v • d • e

Rafael Flores Luminant Power Senior Vice President P 0 Box 1002 0____

& Chief Nuclear Officer 6322 North FM 56 Rafael.flores@Luminant.com Glen Rose, TX 76043 Lum inant 254 897 5550

817 559 0403 F 254 897 6652 CP-201000646 Ref. #

Tech. Spec. 5.6.2 Log # TXX-10067 April 29, 2010 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 2009 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, 2009 through December 31, 2009 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:

W. Madden Director, Oversight & Regulatory Affairs A member of the STARS (Strategic Teaming and Resource Sharing) Alliance Callaway Comanche Peak - Diablo Canyon Palo Verde

San Onofre South Texas Project

Wolf Creek

U.S. Nuclear Regulatory Commission TXX-10067 Page 2 04/29/10 Enclosure Comanche Peak Annual Radiological Environmental Operating Report for 2009 c -

E. E. Collins, Region IV L. K. Gibson, NRR Resident Inspectors, Comanche Peak

LUMINANT COMANCHE PEAK NUCLEAR POWER PLANT ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2009 JANUARY 1, 2009 through DECEMBER 31, 2009 LUMINANT REVIEW and APPROVAL CREATED BY:

Mike Watts R:ý adiation Protection Technician REVIEWED BY:

r. Nuclear Analyst APPROVED BY:

Deborah O'Connor L-'*ealth Physics Supervisor 4-/s 7-/QG Date

/-/3 C2 o Date Date I

Table of Contents Section Title

1.

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 Pro2ram for 2009 Table 2 --

Key to Environmental Sampling Locations B.

Direct Radiation Program page 11 Methods, Procedures and Result Summaries Exceptions to the Program Table 3 --

2009 Environmental Direct Radiation Results Table 14 --

2009 Environmental OSL Trend C.

Airborne Program page 15 Methods, Procedures and Result Summaries.

Exceptions to the Program Table 4 --

2009 Environmental Airborne Particulate Gross Beta Results Graph 1--

2009 Environmental Air Sample Gross Beta Results -

Maximum and Minimum Table 5 --

2009 Environmental Air Sample Iodine-131 Results Table 6 --

2009 Environmental Air Particulate Composite Gamma Isotopic Results 2

D.

Surface Water Program page 21 E.

Methods, Procedures and Result Summaries Exceptions to the Program Table 7 --

2009 Environmental Surface Water Tritium and Gamma Isotopic Results Graph 2--

2009 Environmental Surface Water Tritium Results Surface Drinking Water Program page 25 Methods, Procedures and Result Summaries Exceptions to the Program Table 8 --

2009 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results Graph 3--

Squaw Creek Maximum Tritium Values Graph 4--

2009 Environmental Surface Drinking Water Tritium Results Graph 5--

2009 Environmental Surface Drinkin2 Water Gross Beta Results F.

Groundwater Program page 30 Methods, Procedures and Result Summaries Exceptions to the Program Table 9 --

2009 Environmental Groundwater Tritium and Gamma Isotopic Results G.

Sediment Program page 32 Methods, Procedures and Result Summaries Exceptions to the Program Table 10 --

2009 Environmental Sediment Gamma Isotopic Results H.

Fish Program page 34 Methods, Procedures and Result Summaries Exceptions to the Program Table 11 --

2009 Environmental Fish Gamma Isotopic Results 3

I.

Food Products Program page 36 Methods, Procedures and Result Summaries Exceptions to the Program Table 12 --

2009 Environmental Food Products Gamma Isotopic Results J.

Broadleaf Program page 38 Methods, Procedures and Result Summaries Exceptions to the Program Table 13 --

2009 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 2009 page 42 4

I.

Introduction Results of the Radiological Environmental Monitoring Program for the Comanche Peak Nuclear Power Plant (CPNPP) for the year 2009 are contained within this report. This report covers the period from January 1, 2009 through December 31, 2009 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 onApril 3, 1990. A full power license for Unit 1 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.

Obiectives 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 "Comanche Peak Nuclear Power Plant Units 1 and 2 Technical Specifications" and the "CPNPP Offsite Dose Calculation Manual" (ODCM).

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In 2009, 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 groundwater; 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 CPNPP 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 2009. 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 2009" is provided in Appendix A to this report.

Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2009 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.

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Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2009 Number of Identification by Sector and Distance (miles)

Sampling Analytical Media Locations Frequency (a)

Analysis Frequency (a)

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; 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-I.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-I.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

Tritium QC Gross Beta M

Surface 2

NNW-0.1; N-9.9 M(c)

Gamma Isotopic M

Water/Drinking Iodine-1 31 M

Tritium QC Groundwater 5

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 Gamma Isotopic MH Food Products 1

ENE-9.0 MH Isooic MH Iodine-1 31 MH Broadleaf Vegeat 3

N-1.45; SW-1.0; 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 POINT Al A2 A3 A4 A5 A6 A7 A8 RI R2 R3 R4 R5 R6 R7 R8 R9 RIO R11 R12 R13 R14 R15 R16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 LOCATION (SECTOR-MILE)

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-I.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-l.1 SSW-4.4 SW-0.9 SW-4.8 SAMPLE TYPE*

A A

R R

RR SAMPLING POINT R29 R30 R31 R32 R33 R34 R35 R36 R37 R38 R39 R40 R41 R42 R43 SW1 SW2 SW3 SW4 SW5 SW6 GW1 GW2 GW3 GW4 GW5 SS1 SS2 SS3 SS4 F1 F2 FP1 BLI BL2 BL3 LOCATION (SECTOR-MILE)

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 SAMPLE TYPE*

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 - GROUNDWATER 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 - 2009 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 theaverage dose rate (mr/day) for the entire set of annual OSLs.

For the year 2009, the statistical average dose rate of all the quarterly OSL's was 0.058 mr/day. The quarterly measured dose rates ranged from a minimum of 0.000 mr/day to a maximum of 0.144 mr/day. The statistical average dose rate of all the annual OSLs was 0.062 mr/day. The annual measured dose rates ranged from a minimum of 0.001 mr/day to a maximum of 0.121 mr/day. The summation of the individual quarterly measured doses averaged 21.00 mr for all the forty three monitoring stations while the annual measured dose averaged 23.32 mr for all the monitoring stations.

Comparing the pre-operational data and operational data collected through the year 2009 did not produce any anomalies. The direct radiation dose data for 2009 was consistently lower than previous years of data during both the pre-operational program and the previous years of the operational program.

During the year 2009, there was one exception to the Direct Radiation Program.

The first quarter of 2009, all OSL's were collected with the exception of R8. The Annual OSL for this location was also missing. One of the Annual Environmental Background OSL's was used to replace the missing Annual OSL for Location R8. This OSL was placed in the field the same day as change out occurred.

No abnormal quarterly results were obtained by either CPNPP or by the State of Texas, Bureau of Radiation Control.

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Table 3 - 2009 Environmental Direct Radiation Results (Units of mr dose and mr/day dose rate) 1ST 2ND QTR Average QTR Location Total N-1.45 R1 6.00 N-4.4 R2 9.00 N-6.5 R3 5.00 N-9.4 R4 2.00 NNE-I.1 R5 0.00 NNE-5.65 R6 4.00 NE-1.7 R7 3.00 NE-4.8 R8 n/a ENE-2.5 R9 4.00 ENE-5.0 RIO 4.00 E-0.5 R11 2.00 E-1.9 R12 2.00 E-3.5 R13 7.00 E-4.2 R14 13.00 ESE-1.4 R15 3.00 ESE-4.7 R16 8.00 SE-1.3 R17 3.00 SE-3.85 R18 4.00 SE-4.6 R19 0.00 SSE-1.3 R20 8.00 SSE-4.4 R21 5.00 SSE-4.5 R22 3.00 S-1.5 R23 4.00 S-4.2 R24 6.00 SSW-1.1 R25 1.00 SSW-4.8 R26 3.00 SW-0.9 R27 1.00 SW-4.8 R28 4.00 SW-1 2.3 (C) R29 5.00 WSW-1.0 R30

,8.00 WSW-5.35 R31 3.00 WSW-7.0 (C) R32 6.00 W-1.0 R33 0.00 W-2.0 R34 3.00 W-5.5 R35 7.00 WNW-1.0 R36 7.00 WNW-5.0 R37 5.00 WNW-6.7 R38 10.00 NW-1.0 R39 2.00 NW-5.7 R40 2.00 NW-9.9 R41 5.00 NNW-1.35 R42 0.00 NNW-4.6 R43 3.00 AVERAGES 4.29 mr/day 0.067 0.100 0.056 0.022 0.000 0.044 0.033 n/a 0.044 0.044 0.022 0.022 0.078 0.144 0.033 0.089 0.033 0.044 0.000 0.089 0.056 0.033 0.044 0.067 0.011 0.033 0.011 0.044 0.056 0.089 0.033 0.067 0.000 0.033 0.078 0.078 0.056 0.111 0.022 0.022 0.056 0.000 0.033 0.047 Total 2.20 8.20 6.20 8.20 0.00 6.20 2.20 5.20 4.20 12.20 5.20 6.20 8.20 7.20 3.20 11.20 6.20 6.20 4.20 4.20 3.20 10.20 3.20 2.20 5.20 7.20 1.20 0.00 4.20 6.20 5.20 6.20 2.20 1.20 6.20 4.20 8.20 420 6.20 7.20 5.20 0.00 10.20 5.26 Average mr/day 0.026 0.096 0.073 0.096 0.000 0.073 0.026 0.061 0.049 0.144 0.061 0.073 0.096 0.085 0.038 0.132 0.073 0.073 0.049 0.049 0.038 0.120 0.038 0.026 0.061 0.085 0.014 0.000 0.049 0.073 0.061 0.073 0.026 0.014 0.073 0.049 0.096 0.049 0.073 0.085 0.061 0.000 0.120 0.062 3RD QTR Total 5.60 6.60 5.60 9.60 2.60 7.60 0.60 3.60 6.60 12.60 7.60 7.60 6.60 12.60 4.60 7.60 3.60 5.60 7.60 4.60 7.60 8.60 5.60 6.60 4.60 10.60 7.60 3.60 8.60 7.60 8.60 1.60 6.60 4.60 3.60 6.60 6.60 5.60 6.60 3.60 7.60 2.60 7.60 6.32 Average mr/day 0.058 0.068 0.058 0.099 0.027 0.078 0.006 0.037 0.068 0.130 0.078 0.078 0.068 0.130 0.047 0.078 0.037 0.058 0.078 0.047 0.078 0.089 0.058 0.068 0.047 0.109 0.078 0.037 0.089 0.078 0.089 0.016 0.068 0.047 0.037 0.068 0.068 0.058 0.068 0.037 0.078 0.027 0.078 0.065 4TH QTR Total 6.20 6.20 8.20 4.20 1.20 6.20 0.00 8.20 7.20 5.20 8.20 7.20 5.20 7.20 4.20 1.20 6.20 5.20 8.20 2.20 9.20 5.20 8.20 2.20 3.20 5.20 8.20 7.20 6.20 2.20 2.20 4.20 6.20 2.20 3.20 8.20 10.20 2.20 3.20 3.20 5.20 0.20 9.20 5.13 Average QTR Annual mr/day Total Total 0.068 20.00 20.25 0.068 30.00 34.25 0.090 25.00 15.25 0.046 24.00 24.25 0.013 3.80 10.25 0.068 24.00 18.25 0.000 5.80 2.25 0.090 17.00 23.25 0.079 22.00 34.25 0.057 34.00 44.25 0.090 23.00 28.25 0.079 23.00 19.25, 0.057 27.00 34.25 0.079 40.00 32.25 0.046 15.00 14.25 0.013 28.00 31.25 0.068 19.00 26.25 0.057 21.00 23.25 0.090 20.00 26.25 0.024 19.00 23.25 0.101 25.00 28.25 0.057 27.00 24.25 0.090 21.00 23.25 0.024 17.00 21.25 0.035 14.00 17.25 0.057 26.00 27.25 0.090 18.00 16.25 0.079 14.80 23.25 0.068 24.00 16.25 0.024 24.00 26.25 0.024 19.00 15.25 0.046 18.00 23.25 0.068 15.00 11.25 0.024 11.00 8.25 0.035 20.00 18.25 0.090 26.00 28.25 0.112 30.00 26.25 0.024 22.00 21.25 0.035 18.00 25.25 0.035 16.00 30.25 0.057 23.00 11.25 0.002 2.80 0.25 0.101 30.00 32.25 0.056 21.00 23.32 Average mr/day 0.055 0.094 0.042 0.066 0.028 0.050 0.006 0.085 0.094 0.121 0.077 0.053 0.094 0.088 0.039 0.086 0.072 0.064 0.072 0.064 0.077 0.066 0.064 0.058 0.047 0.075 0.045 0.064 0.045 0.072 0.042 0.064 0.031 0.023 0.050 0.077 0.072 0.058 0.069 0.083 0.031 0.001 0.088 0.062 13

Table 14 - 2009 Environmental OSL Trend (Units in mr) 2004 2005 2006 2007 2008 2009 Location 2001 2002 2003 R1 R2 R3 R4 R5 R6 R7 R8 R9 R10 R11 R12 R13 R14 R15 R16 R17 R18 R19 R20 R21 R22 R23 R24 R25 R26 R27 R28 R29 R30 R31 R32 R33 R34 R35 R36 R37 R38 R39 R40 R41 R42 R43 19.55 32.75 22.65 22.60 N/A 22.75 17.40 27.15 35.90 41.85 29.80 13.05 39.90 33.75 21.30 32.05 28.25 17.85 20.25 21.70 21.75 20.15 17.95 18.10 17.20 23.50 N/A 18.05 21.50 N/A 19.75 22.20 10.15 21.15 18.45 24.95 21.35 22.00 17.45 23.75 17.15 2.05 29.45 16.75 19.60 29.25 32.30 19.60 24.15 21.00 26.10 15.40 19.05 22.55 N/A 16.95 18.25 23.80 24.10 28.50 30.30 36.20 41.90 22.75 26.15 9.15 10.20 31.30 55.40 27.60 29.15 16.95 20.55 25.40 28.35 27.00 29.45 15.70 19.75 21.70 21.85 16.75 18.25 21.15 25.15 17.75 21.50 18.95 16.60 17.55 21.10 19.00 17.30 25.80 N/A 22.30 18.50 16.20 20.85 21.75 24.10 25.45 22.45 18.70 23.05 25.60 26.65 13.10 13.40 11.90 13.70 14.65 18.00 25.50 25.60 22.85 23.45 21.10 23.65 19.20 21.35 19.20 23.45 14.95 17.35 5.20 6.70 23.95 30.40 18.9 33.7 23.2 25.75 21.9 27.65 18.7 25.5 32.6 41 29.45 33.8 37.25 32.45 21.5 28.55 31.3 19.35 20.7 22.65 24.25 22 18.85 25.45 19.5 20.5 22.55 14 24.4 28.35 24.7 25.1 14.75 13.9 17.95 28.55 22.95 23.1 24.2 20.9 19.65 5.95 30.9 20.1 30.05 23.25 23.2 4.95 23.15 8.4 23.7 29.2 36 25.65 16 35.25 27.3 17 28.4 28.85 17.2 18.95 17.9 22.15 18.25 17.3 19.85 22.65 18.7 16.15 15.6 22.2 23.3 20.55 27.8 13.75 13.4 19.4 26.5 24.15 20.1 16.95 24.45 17.7 1.35 24.95 18.9 28.6 21.1 25.2 6.9 25.6 5.4 21.8 25.7 40.6 29.5 14.9 36.9 27.4 21.5 27.1 28.1 21 18.8 19.8 23.3 23.8 16.9 19.9 23.4 21.2 19.4 4.35 21.2 25.1 21.2 27.5 13.8 14.9 16.1 26.2 24.6 23 19.5 22.6 18.2 8

28.1 15.90 24.60 20.60 19.90 3.30 19.50 4.20 17.20 24.10 35.70 26.90 12.60 33.40 25.50 16.80 22.20 22.10 17.20 15.80 18.80 22.40 19.90 15.50 16.60 19.10 18.90 18.20 14.80 19.20 18.60 17.70 20.00 9.10 10.10 14.40 21.20 19.70 18.60 16.10 19.20 17.80 0.70 28.70 19.10 30.95 21.15 22.40 4.15 22.35 4.35 20.20 30.25 36.75 22.30 14.70 37.60 31.25 20.95 22.20 25.50 19.60 10.50 20.45 12.75 21.60 16.40 21.35 24.00 17.90 17.00 18.40 21.50 24.45 18.05 15.00 14.45 12.60 19.35 24.35 24.20 21.60 18.75 25.25 19.25 0.00 27.95 20.25 34.25 15.25 24.25 10.25 18.25 2.25 23.25 34.25 44.25 28.25 19.25 34.25 32.25 14.25 31.25 26.25 23.25 26.25 23.25 28.25 24.25 23.25 21.25 17.25 27.25 16.25 23.25 16.25 26.25 15.25 23.25 11.25 8.25 18.25 28.25 26.25 21.25 25.25 30.25 11.25 0.25 32.25 2001-

% Diff 2008

% Diff 2009 to mR 2009 to 2008 Avg Average 6%

18.59 9%

10%

30.27 12%

-32%

21.96

-36%

8%

23.26 4%

10.81

-5%

-20%

23.36

-25%

-64%

11.71

-136%

14%

22.93 1%

12%

29.56 15%

19%

38.75 13%

24%

26.56 6%

15.55 21%

-9%

38.37

-11%

3%

29.29 10%

-38%

19.57

-31%

26.78 15%

3%

27.57

-5%

17%

18.45 23%

18.56 13%

19.53 17%

21.61 12%

20.62 16%

4 17.30 0%

19.98 6%

-33%

20.26

-16%

20.92

-5%

19.15

-16%

23%

15.28

-28%

21.98

-30%

7%

23.95 9%

-17%

20.46

-29%

23.73

-2%

-25%

12.81

-13%

-42%

13.95

-51%

-6%

17.29 5%

15%

25.36 11%

8%

22.90 14%

..... -2%

21.64

-2%

~19.19 18%

22.35

-52%

17.75

-45%

3.74

-175%

14%

28.05 14%

R5 & R7 & R42-Historically reported low results reported for these locations from 2005 - 2008 R12 - Historical anomalous reading previously identified in 2004 R28 - Historical issue during 2nd issue period (4/21/06 - 12/29/06) from missing TLD.

Legend:

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 2009. 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 2009, 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< 5.7E-03 pCi/m 3 to a maximum value of 7.73E-02 pCi/mr3. Table 4 - 2009 Environmental Airborne Particulate Gross Beta Results contains the reported values of all samples. There were no anomalies noted in the data reported for 2009 when compared to pre-operational and previous operational data. Graph 1 - 2009 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 416 charcoal cartridges were analyzed for airborne Iodine-131.

No Iodine-131 was detected at any of the eight monitoring locations.

Table 5 - 2009 Environmental Air Sample Iodine-i131 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 - 2009 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.

During the year 2009 there was one discrepancy to the Airborne Program.

Location A-4 lost power on 9/4/09 at 0509 due to a GFI breaker trip.

Approximately 100 hours0.00116 days <br />0.0278 hours <br />1.653439e-4 weeks <br />3.805e-5 months <br /> of run time was lost. LLD on the particulate air sample was not met according to reported data from AREVA. AREVA Laboratory Lead was contacted 3/30/10 to review data. AREVA Lead reviewed Location A-4 results and reported it met LLD when reviewed beyond the standard automatic process.

Condition Reports CR-2010-2898 and CR-2010-3031 were initiated for tracking, reviewing, and documenting this environmental air sample result. A review of all the State of Texas air sample data for 2009 indicated no anomalies.

15

Table 4 -- 2009 Environmental Airborne Particulate Gross Beta Results (Units of pCi/m3) 5 A-6 Date 01/06/2009 01/15/2009 01/20/2009 01127/2009 02/03/2009 02/10/2009 02/17/2009 02/24/2009 03103/2009 03/10/2009 03117/2009 03/24/2009 03/31/2009 04/08/2009 04/14/2009 04/21/2009 04/28/2009 05/05/2009 05/12/2009 05/19/2009 05/26/2009 06/02/2009 06/09/2009 06/16/2009 06/23/2009 06/30/2009 07/07/2009 07/14/2009 07/21/2009 07/28/2009 08/04/2009 08/11/2009 08/18/2009 08/25/2009 09/0112009 09108/2009 09/15/2009 09/22/2009 09/29/2009 10/06/2009 10/13/2009 10/20/2009 10/27/2009 11/03/2009 11/10/2009 11/17/2009 11/24/2009 12/01/2009 12/08/2009 12/15/2009 12/22/2009 12/28/2009 A-8 Location NW-1.0 5.10E-02 4.60E-02 4.20E-02 3.43E-02 4.06E-02 2.98E-02 3.16E-02 3.51 E-02 4.79E-02 3.20E-02 2.33E-02 4.58E-02 2.47E-02 2.48E-02 1.92E-02 2.23E-02 2.89E-02 1.81 E-02 2.39E-02 2.45E-02 2.28E-02 2.62E-02 3.11 E-02 2.38E-02 1.67E-02 3.46E-02 2.50E-02 3.53E-02 2.78E-02 3.37E-02 2.59E-02 2.29E-02 3.19E-02 2.73E-02 3.34E-02 4.22E-02 2.22E-02 3.98E-02 2.26E-02 1.60E-02 1.81 E-02 2.69E-02 2.34E-02 2.37E-02 3.27E-02 5.16E-02 5.44E-02 3.47E-02 2.38E-02 4.23E-02 3.92E-02 3.14E-02 A-7 SW/WSW-0.95 4.74E-02 4.25E-02 3.73E-02 4.25E-02 3.78E-02 3.16E-02 3.02E-02 3.55E-02 4.81 E-02 3.17E-02 2.80E-02 4.54E-02 2.52E-02 2.70E-02 2.27E-02 2.37E-02 2.59E-02 1.39E-02 2.13E-02 1.93E-02 1.93E-02 2.99E-02 3.56E-02 2.64E-02 1.94E-02 3.07E-02 2.44E-02 3.18E-02 2.89E-02 3.06E-02 2.76E-02 3.05E-02 2.86E-02 2.58E-02 3.45E-02 4.92E-02 1.98E-02 4.16E-02 2.48E-02 2.34E-02 2.01E-02 2.47E-02 1.93E-02 2.29E-02 3.53E-02 4.54E-02 4.63E-02 2.92E-02 2.01 E-02 3.67E-02 4.13E-02 2.71 E-02 S/SSW-1.2 SW-12.3 Control 3.39E-02 4.56E-02 3.54E-02 3.47E-02 2.41 E-02 3.04E-02 2.79E-02 3.52E-02 3.18E-02 3.64E-02 1.86E-02

,2.31 E-02 2.33E-02 2.66E-02 3.01 E-02 3.32E-02 3.22E-02 3.57E-02 2.51E-02 2.78E-02 1.90E-02 2.39E-02 3.57E-02 3.99E-02 1.69E-02 2.14E-02 2.16E-02 2.89E-02 1.59E-02 2.18E-02 1.64E-02 1.92E-02 2.53E-02 2.28E-02 1.96E-02 1.36E-02 3.34E-02 2.39E-02 2.60E-02 2.35E-02 2.91E-02 2.19E-02 3.86E-02 3.10E-02 3.96E-02 3.28E-02 3.02E-02 2.86E-02 2.42E-02 1.98E-02 4.36E-02 3.72E-02 3.43E-02 2.79E-02 5.14E-02 3.22E-02 3.80E-02 2.98E-02 4.65E-02 3.13E-02 3.11 E-02 2.64E-02 2.93E-02 2.13E-02 4.24E-02 3.05E-02 3.20E-02 2.66E-02 4.89E-02 3.76E-02 6.66E-02 5.04E-02 2.57E-02 2.OOE-02 4.77E-02 4.59E-02 2.40E-02 3.34E-02 2.15E-02 2.46E-02 1.98E-02 2.08E-02 3.21 E-02 3.74E-02 2.34E-02 2.27E-02 3.02E-02 2.98E-02 3.85E-02 3.96E-02 5.68E-02 5.53E-02 5.68E-02 6.06E-02 3.64E-02 3.68E-02 2.75E-02 2.89E-02 4.37E-02 4.28E-02 4.67E-02 4.64E-02 2.97E-02 3.54E-02 A-5 A-4 SSE-4.5 5.OOE-02 3.98E-02 3.84E-02 3.98E-02 4.1O E-02 2.95E-02 2.94E-02 3.78E-02 4.79E-02 3.74E-02 2.47E-02 4.67E-02 2.56E-02 3.30E-02 3.13E-02 2.63E-02 3.59E-02 2.1O E-02 3.46E-02 3.29E-02 2.97E-02 4.11 E-02 4.45E-02 3.77E-02 2.84E-02 5.05E-02 4.03E-02 4.4E-02 4.13E-02 5.05E-02 4.06E-02 2.92E-02 4.35E-02 3.97E-02 5.43E-02 7.73E-02 2.60E-02 4.81 E-02 3.08E-02 2.78E-02

<5.7E-03 3.44E-02 2.24E-02 3.03E-02 4.69E-02 5.91 E-02 5.91 E-02 3.98E-02 3.20E-02 4.79E-02 5.16E-02 4.14E-02 A-3 E-3.5 5.23E-02 4.77E-02 4.09E-02 4.25E-02 4.80E-02 3.11 E-02 3.15E-02 3.67E-02 4.19E-02 3.27E-02 2.76E-02 4.16E-02 2.52E-02 2.94E-02 2.46E-02 1.93E-02 2.89E-02 1.56E-02 2.48E-02 2.38E-02 2.25E-02 2.78E-02 3.03E-02 2.52E-02 2.OOE-02 3.59E-02 2.46E-02 3.39E-02 2.71 E-02 3.39E-02 1.60E-02 1.97E-02 2.96E-02 2.28E-02 3.55E-02 5.14E-02 2.36E-02 4.71 E-02 2.38E-02 2.69E-02 2.01 E-02 3.11 E-02 2.34E-02 3.19E-02 4.46E-02 5.30E-02 5.16E-02 3.88E-02 2.48E-02 4.23E-02 4.21 E-02 3.34E-02 A-1 N-1.45 4.67E-02 3.67E-02 3.04E-02 3.21 E-02 3.30E-02 2.33E-02 2.47E-02 3.49E-02 2.37E-02 2.73E-02 2.OOE-02 3.55E-02 2.58E-02 2.37E-02 1.65E-02 1.83E-02 2.43E-02 1.69E-02 2.13E-02 2.12E-02 2.23E-02 2.81 E-02 4.11 E-02 2.63E-02 1.86E-02 3.66E-02 2.71 E-02 3.4E-02 2.72E-02 3.38E-02 2.61 E-02 2.55E-02 3.16E-02 2.77E-02 3.55E-02 4.60E-02 2.14E-02 4.92E-02.

3.38E-02 3.21 E-02 1.96E-02 3.17E-02 2.89E-02 3.12E-02 4.50E-02 5.85-02 6.51-02 4.22-02 3.2E-02 4.87-02 6.52-02 3.61-02 A-2 N-9.4 Control 5.16E-02 6.94E-02 3.59E-02 3.54E-02 4.23E-02 2.98E-02 3.58E-02 3.98E-02 4.47E-02 3.31 E-02 2.78E-02 4.89E-02 3.20E-02 3.32E-02

<6.8E-03 2.24E-02 3.02E-02 1.67E-02 2.90E-02 3.68E-02 3.05E-02 3.60E-02 4.10E-02 3.44E-02 2.73E-02 4.63E-02 4.08E-02 4.58E-02 3.87E-02 4.58E-02 2.83E-02 3.24E-02 3.85E-02 3.90E-02 5.23E-02 6.17E-02 2.63E-02 5.70E-02 2.83E-02 3.22E-02 2.23E-02 3.03E-02 2.49E-02 2.91 E-02 4.44E-02 6.26E-02 5.75E-02 3.89E-02 3.24E-02 4.78E-02 4.76E-02 3.94E-02 Required LLD's 1.OOE-02 16

Graph 1 -- 2009 Environmental Air Sample Gross Beta Results - Maximum and Minumum E

0~

0 2'

c 9.00E-02 8.00E-02 7.00E-02 6.00E-02 5.00E-02 4.00E-02 3.00E-02 2.00E-02 1.OOE-02 0.00E+00 1

5 9

13 17 21 25 29 Weekly Data Points 33 37 41 45 49 17

Table 5 -- 2009 Environmental Air Sample Iodine-131 Results A-8 A-7 NW-1.0 SWIWSW-0.95 Date 01/06/2009 01/15/2009 01/20/2009 01/27/2009 02/03/2009 02/10/2009 02/17/2009 02/24/2009 03/03/2009 03/10/2009 03/17/2009 03/24/2009 03/31/2009 04/08/2009 04/14/2009 04121/2009 04/28/2009 05/05/2009 05/12/2009 05/19/2009 05/2612009 06/02/2009 06/09/2009 06/i6/2009 06123/2009 06/30/2009 07/07/2009 07/14/2009 07/21/2009 07/28/2009 08104/2009 08/11/2009 08/18/2009 08/25/2009 09/01/2009 09/08/2009 09115/2009 09/2212009 09/29/2009 10/06/2009 10/1312009 1012012009 10/2712009 11/03/2009 11/1012009 11/1712009 11/2412009 12/0112009 12/08/2009 12/15/2009 12/22/2009 12/28/2009

<3.7E-02

<3.6E-02

<5.3E-02

<3.6E-02

<3.3E-02

<2.2E-02

<3.OE-02

<2.6E-02

<4.9E-02

<3.OE-02

<3.5E-02

<3.2E-02

<4.2E-02

<3.OE-02

<3.6E-02

<3.4E-02

<2.5E-02

<3.2E-02

<3.6E-02

<2.4E-02

<2.6E-02

<4.8E-02

<4.5E-02

<3.2E-02

<4.5E-02

<4.6E-02

<3.6E-02

<3.8E-02

<2.8E-02

<4.1 E-02

<5.6E-02

<3.OE-02

<3.9E-02

<2.9E-02

<6.3E-02

<3.5E-02

<3.OE-02

<3.1 E-02

<2.6E-02

<3.8E-02

<4.3E-02

<2.9E-02

<3.9E-02

<5.2E-02

<3.4E-02

<6.4E-02

<3.8E-02

<6.5E-02

<4.4E-02

<2.8E-02

<4.OE-02

<5.4E-02

<5.2E-02

<4.5E-02

<3.7E-02

<3.OE-02

<3.8E-02

<2.8E-02

<4.2E-02

<4.3E-02

<4.1 E-02

<3.4E-02

<5.3E-02

<3.1 E-02

<3.3E-02

<4.6E-02

<4.7E-02

<3.4E-02

<3.9E-02

<3.7E-02

<2.4E-02

<4.2E-02

<3.8E-02

<4.9E-02

<3.2E-02

<3.OE-02

<4.3E-02

<4.2E-02

<4.OE-02

<3.8E-02

<5.2E-02

<4.4E-02

<3.2E-02

<4.6E-02

<2.1 E-02

<5.4E-02

<4.1 E-02

<2.9E-02

<4.5E-02

<2.2E-02

<4.1 E-02

<6.2E-02

<2.2E-02

<5.OE-02

<5.3E-02

<3.2E-02

<9.8E-02

<5.7E-02'

<5.6E-02

<5.1 E-02 (Units of pCi/m3)

A-5 A-6 S/SSW-1.2 SW-12.3 Control

<3.7E-02

<3.4E-02

<3.7E-02

<4.3E-02

<4.4E-02

<4.1 E-02

<5.9E-02

<3.9E-02

<4.OE-02

<3.OE-02

<3.3E-02

<3.6E-02

<3.7E-02

<3.8E-02

<3.3E-02

<3.5E-02

<3.3E-02

<3.OE-02

<2.4E-02

<4.7E-02

<4.3E-02

<3.4E-02

<3.9E-02

<3.5E-02

<3.7E-02

<3.8E-02

<3.7E-02

<5.1E-02

<4.3E-02

<3.4E-02

<2.6E-02

<3.3E-02

<3.9E-02

<4.1E-02

<3.5E-02

<5.8E-02

<3.7E-02

<2.2E-02

<3.2E-02

<3.6E-02

<3.4E-02

<5.2E-02

<3.4E-02

<3.OE-02

<2.2E-02

<3.3E-02

<4.OE-02

<3.9E-02

<5.4E-02

<4.4E-02

<3.6E-02

<5.3E-02

<4.7E-02

<3.4E-02

<5.4E-02

<3.5E-02

<4.4E-02

<4.5E-02

<3.7E-02

<3.6E-02

<2.5E-02

<2.6E-02

<5.3E-02

<4.1E-02

<4.5E-02

<3.6E-02

<4.3E-02

<5.7E-02

<3.5E-02

<4.OE-02

<2.9E-02

<2.5E-02

<5.7E-02

<5.OE-02

<4.1E-02

<4.5E-02

<3.9E-02

<3.5E-02

<4.3E-02

<4.2E-02

<3.1 E-02

<2.1 E-02

<5.5E-02

<4.1E-02

<4.2E-02

<5.2E-02

<3.9E-02

<3.4E-02

<4.OE-02

<5.1E-02

<4.5E-02

<5.9E-02

<4.1E-02

<5.3E-02

<5.5E-02

<5.6E-02

<5.1E-02

<4.2E-02

<5.1E-02

<4.7E-02

<5.2E-02

<5.4E-02 A-4 SSE-4.5

<3.7E-02

<3.5E-02

<5.OE-02

<5.3E-02

<4.4E-02

<3.OE-02

<3.2E-02

<2.8E-02

<2.9E-02

<3.2E-02

<4.8E-02

<3.3E-02

<2.6E-02

<3.7E-02

<5.2E-02

<3.1 E-02

<2.7E-02

<3.8E-02

<4.8E-02

<3.6E-02

<2.6E-02

<4.OE-02

<2.5E-02

<2.8E-02

<3.6E-02

<4.4E-02

<3.7E-02

<3.9E-02

<3.6E-02

<4.OE-02

<2.1 E-02

<4.7E-02

<4.6E-02

<5.3E-02

<5.5E-02

<2.2E-02

<5.9E-02

<3.5E-02

<3.2E-02

<3.4E-02

<3.1 E-02

<4.1 E-02

<6.4E-02

<4.5E-02

<4.4E-02

<5.5E-02

<3.7E-02

<6.4E-02

<3.4E-02

<6.OE-02

<6.4E-02 A-3 E-3.5

<3.8E-02

<3.6E-02

<4.2E-02

<3.1 E-02

<3.2E-02

<2.9E-02

<4.1 E-02

<3.OE-02

<3.4E-02

<5.3E-02

<3.9E-02

<3.5E-02

<4.6E-02

<5.5E-02

<3.8E-02

<3.2E-02

<4.6E-02

<4.9E-02

<2.8E-02

<3.5E-02

<4.6E-02

<3.7E-02

<2.9E-02

<3.6E-02

<4.8E-02

<4.7E-02

<4.6E-02

<4.4E-02

<4.1 E-02

<3.8E-02

<3.2E-02

<5.OE-02

<3.8E-02

<3.7E-02

<3.6E-02

<3.2E-02

<4.4E-02

<3.OE-02

<4.OE-02

<3.OE-02

<5.7E-02

<5.8E-02

<3.4E-02

<6.3E-02

<4.3E-02

<5.OE-02

<3.6E-02

<4.5E-02

<5.9E-02

<6.4E-02 A-1 N-1.45

<2.3E-02

<4.1 E-02

<5.9E-02

<5.6E-02

<2.5E-02

<3.7E-02

<3.6E-02

<3.OE-02

<3.3E-02

<5.4E-02

<3.7E-02

<2.8E-02

<4.1 E-02

<5.2E-02

<3.4E-02

<2.9E-02

<4.1 E-02

<4:5E-02

<3.3E-02

<3.OE-02

<4.6E-02

<3.OE-02

<2.9E-02

<3.7E-02

<4.1 E-02

<4.8E-02

<4.1 E-02

<3.8E-02

<3.7E-02

<3.3E-02

<2.9E-02

<4.6E-02

<4.9E-02

<3.9E-02

<4.9E-02

<3.4E-02

<4.4E-02

<2.5E-02

<3.6E-02

<3.1 E-02

<3.8E-02

<6.1 E-02

<5.3E-02

<4.1 E-02

<5.5E-02

<5.2E-02

<5.6E-02

<3.8E-02

<4.1 E-02

<6.5E-02

<6.4E-02 A-2 N-9.4 Control

<3.4E-02

<6.3E-02

<3.9E-02

<3.8E-02

<3.5E-02

<3.4E-02

<3.5E-02

<3.6E-02

<2.9E-02

<2.8E-02

<4.OE-02

<4.1 E-02

<3.6E-02

<4.3E-02

<4.4E-02

<3.OE-02

<3.7E-02

<5.2E-02

<5.5E-02

<3.9E-02

<3.1 E-02

<4.3E-02

<3.4E-02

<3.OE-02

<4.3E-02

<4.2E-02

<4.5E-02

<3.2E-02

<4.4E-02

<4.1 E-02

<2.7E-02

<4.3E-02

<4.OE-02

<4.4E-02

<4.1 E-02

<2.5E-02

<5.OE-02

<5.4E-02

<3.1E-02

<3.7E-02

<2.6E-02

<4.3E-02

<6.1 E-02

<4.5E-02

<4.4E-02

<6.3E-02

<4.6E-02

<4.9E-02

<4.4E-02

<5.4E-02

<6.6E-02 Required LLD 7.OOE-02 18

Table 6 -- 2009 Environmental Air Particulate Composite Gamma Isotopic Results Composite Dates 1 ST QTR 01/06/09-03/31109 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 A-8 NW-1.0

<9.5E-02 2.3E-01

<6.7E-04

<2.4E-03

<1.8E-03

<1.1E-03

<9.1 E-03

<1.7E-02

<9.5E-02

<1.4E-03

<6.4E-03

<4.4E-03

<4.OE-03

<3.3E-02 1.87E-01

<9.1 E-04 7.50E-04

<2.7E-03

<1.8E-03

<2.OE-03

<2.2E-03

<2.5E-02

<3.3E-02

<2.2E-03

<7.8E-03

<4.8E-03

<6.4E-03 A-7 SW)WSW-0.95

<4.9E-02 2.03E-01

<4.4E-04

<2.1 E-03

<1.OE-03

<8.1 E-04

<6.7E-03

<1.3E-02

<4.9E-02

<9.5E-04

<4.5E-03

<2.7E-03

<3.9E-03 (Units of pCi/m3)

A-5 A-6 SSW-1.2 SW-12.3 SS Control

<1.1E-01

<1.3E-01

<9.

1.53E-01 2.17E-01 2.6

<8.2E-04

<7.4E-04

<8.

<4.3E-03

<3.8E-03

<3.

<2.3E-03

<1.02E-03

<2.

<1.3E-03

<1.4E-03

<1.

<2.OE-03

<1.4E-03

<1.

<9.7E-03

<1.4E-02

<9.

<2.8E-02

<2.5E-02

<2.

<1.1E-01

<1.3E-01

<9.

<1.7E-03

<1.6E-03

<1.

<8.1E-03

<8.3E-03

<6.

<6.5E-03

<4.8E-03

<4.

<6.7E-03

<8.5E-03

<5.

7E-02 9E-01 4E-04 OE-03 OE-03 3E-03 1 E-03 6E-03 3E-02 7E-02 8E-03 5E-03 3E-03 1 E-03

<1.8E-01 2.02E-01

<6.5E-04

<2.4E-03

<2.9E-03

<1.3E-03

<1.9E-03

<1.2E-02

<3.3E-02

<1.8E-01

<2.4E-03

<6.OE-03

<7.8E-03

<6.9E-03

<6.8E-02 1.51 E-01

<6.2E-04

<6.1 E-03

<3.1 E-03

<6.5E-04

<1.5E-03

<1.5E-02

<2.3E-02

<6.8E-02

<2.5E-03

<7.5E-03

<6.5E-03

<9.6E-03 A-4 A-3

.E-4.5 E-3.5 A-i N-1.45

<8.7E-02 1.76E-01

<8.2E-04

<3.3E-03

<1.5E-03

<2.2E-03

<1.5E-03

<8.3E-03

<1.8E-02

<8.7E-02

<1.5E-03

<7.4E-03

<6.3E-03

<7.1 E-03

<8.8E-02 I1.67E-01

<7.7E-04

<3.6E-03

<2.OE-03

<1.9E-03

<1.7E-03

<1.2E-02

<2.7E-02

<8.8E-02

<2.2E-03

<8.OE-03

<7.1 E-03

<5.9E-03 A-2 N-9.4 Control

<1.2E-01 2.69E-01

<9.3E-04

<2.8E-03

<1.2E-03

<1.4E-03

<1.6E-03

<1.1E-02

<1.6E-02

<1.2E-01

<2.3E-03

<9.7E-03

<4.9E-03

<7.2E-03

<1.5E-02 1.94E-0i

<9.4E-04

<3.2E-03

<2.6E-03

<2.0E-03

<1.7E-03

<1.OE-02

<2.8E-02

<1.5E-02

<2.5E-03

<5.8E-03

<3.4E-03

<6.9E-03 Required LLD 5.0e-2 Required LLD 6.0e-2 Composite Dates 2ND QTR 03/31109-06130/09 Ba-140 Be-7 Co-57 Co-58 Co-60 Cs-134 Cs-1 37 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95

<5.1 E-02 1.38E-01

<7.8E-04

<2.8E-03

<2.6E-03

<2.OE-03

<1.7E-03

<9.7E-03

<3.OE-02

<5.1 E-02

<2.1 E-03

<4.9E-03,

<4.9E-03

<3.4E-03

<1.OE-01 1.89E-01

<9.2E-04

<3.6E-03

<2.3E-03

<1.9E-03

<1.OE-02

<2.3E-02

<1.0E-01

<2.2E-03

<4.7E-03

<7.5E-03

<8.4E-03

<2.4E-02 1.55E-01

<8.7E-04 1.18E-03

<3.4E-03

<1.7E-03

<2.5E-03

<1.OE-02

<3.5E-02

<2.4E-02

<2.2E-03

<6.9E-03

<6.2E-03

<7.1 E-03

<4.1 E-02 2.46E-01

<8.2E-04

<2.5E-03

<2.3E-03

<1.8E-03

<1.5E-02

<1.9E-02

<4.1 E-02

<1.2E-03

<5.8E-03

<6.1 E-03

<5.8E-03 Required LLD 5.0e-2 Required LLD 6.0e-2 19

Table 6 - 2009 Environmental Air Particulate Composite Gamma Isotopic Results (continued)

(Units of pCi/m3)

Composite Dates 3RD QTR 6/30/09-9/29/09 Location Nuclides 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 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

<4.OE-02 1.43E-01

<1.1E-03

<5.5E-03

<1.4E-03

<2.5E-03

<2.8E-03

<5.6E-03

<3.1 E-02

<4.OE-02

<3.8E-03

<1.1E-02

<9.7E-03

<1.1E-02

<4.5E-02 1.08E-01

<1.1E-03

<4.4E-03

<3.7E-03

<1.3E-03

<2.8E-03

<1.3E-02

<2.7E-02

<4.5E-02

<2.OE-03

<6.OE-03

<5.9E-03

<6.8E-03

<1.4E-01 1.43E-01

<1.OE-03

<5.2E-03

<1.4E-03

<9.9E-04

<2.3E-03

<5.7E-03

<3.3E-02

<1.4E-01

<4.7E-03

<9.3E-03

<1.1E-02

<7.5E-03

<2.9E-02 1.37E-01

<9.7E-04

<2.8E-03

<8.1 E-04

<1.8E-03

<1.7E-03

<1.2E-02

<2.3E-02

<2.9E-02

<2.6E-03

<6.4E-03

<4.6E-03

<8.1 E-03 NW-1.0 SW/wSW-0.95 SSW-I.2 SW-12.3 Control

<8.7E-02

<1.4E-01 1.49E-01 1.59E-01

<1.7E-03

<1.2E-03

<3.OE-03

<6.3E-03

<8.7E-04

<1.5E-03

<2.OE-03

<2.5E-03

<1.5E-03

<3.3E-03

<1.4E-02

<1.6E-02

<3.1 E-02

<8.7E-02

<1.4E-01

<2.3E-03

<2.6E-03

<8.4E-03

<7.3E-03

<5.1E-03

<9.7E-03

<8.9E-03

<9.1E-03 SSE-4.5

<1.1E-01 1.66E-01

<1.2E-03

<1.9E-03

<1.4E-03

<3.3E-03

<3.9E-03

<2.OE-02

<3.5E-02

<1.1E-01

<2.6E-03

<7.8E-03

<9.7E-03

<7.8E-03

<4.5E-02 1.62E-01

<9.9E-04

<3.1 E-03

<3.7E-03

<2.4E-03

<3.4E-03

<3.9E-03

<3.7E-02

<4.5E-02

<3.6E-03

<4.8E-03

<5.9E-03

<6.8E-03 E-3.5

<2.5E-02 1.42E-01

<1.2E-03

<5.3E-03

<3.OE-03

<2.OE-03

<2.6E-03

<3.7E-03

<4.2E-02

<2.5E-02

<3.2E-03

<8.5E-03

<7.5E-03

<8.8E-03

<4.3E-02 1.13E-01

<1.2E-03

<2.8E-03

<2.9E-03

<3.OE-03

<1.9E-03

<9.5E-03

<3.2E-02

<4.3E-02

<2.4E-03

<5.3E-03

<5.4E-03

<5.OE-03 N-1.45 N-9.4 Control

<4.OE-02

<1.4E-01 1.72E-01 2.08E-01

<9.8E-04

<1.2E-03

<4.3E-03

<1.6E-03

<3.7E-03

<5.8E-03

<2.8E-03

<3.2E-03

<2.2E-03

<3.7E-03

<2.OE-02

<1.5E-02

<3.1E-02

<5.OE-02

<4.OE-02

<1.4E-01

<2.6E-03

<9.7E-04

<1.3E-02

<9.3E-03

<9.7E-03

<2.7E-03

<2.8E-03

<1.1E-02 Required LLD 5.0e-2 Required LLD 6.0e-2 Composite Dates 4TH QTR 9/29109-12/28/09

<1.1E-02 1.38E-01

<4.4E-04

<1.3E-03

<1.1E-03

<8.8E-04

<7.5E-04

<3.6E-03

<1.4E-02

<1.1E-02

<8.4E-04

<2.4E-03

<2.3E-03

<2.5E-03

<1.OE-02 1.67E-01

<6.6E-04

<1.8E-03

<2.6E-03

<1.3E-03

<1.9E-03

<2.3E-03

<3.6E-02

<1.OE-02

<2.1 E-03

<5.1 E-03

<6.4E-03

<5.2E-03

<1.7E-02 1.61 E-01

<8.6E-04

<4.4E-03

<3.1 E-03

<2.7E-03

<2.8E-03

<1.7E-02

<3.8E-02

<1.7E-02

<2.7E-03

<4.8E-03

<9.4E-03

<1.OE-02

<1.6E-02 1.41 E-01

<9.OE-04

<1.76E-03

<1.1E-03

<2.OE-03

<2.8E-03

<1.1E-02

<2.7E-02

<1.6E-02

<2.OE-03

<6.9E-03

<8.7E-03

<7.8E-03 Required LLD 5.0e-2 Required LLD 6.0e-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 2009 all surface water samples were collected as required.

Table 7 -- 2009 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 1.512E+04 pCi/l to a low of 1.001E+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/l 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 - 2009 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 28. 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. 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 2009 results were both expected and consistent with previous data and that no anomalies had occurred.

21

For the year 2009, there were no exceptions to the Surface Water Program.

22

Table 7 -- 2009 Environmental Surface Water Tritium and Gamma Isotopic Results (Units of pCi/I)

SW-5 Date Location 1/27/09 ESE-1.4 2/24/09 ESE-1.4 3131/09 ESE-1.4 4/28/09 ESE-1.4 5126/09 ESE-1.4 6130/09 ESE-1.4 7/28/09 ESE-1.4 8/25/09 ESE-1.4 9129/09 ESE-1.4 10/27/09 ESE-1.4 11/24/09 ESE-1.4 12/28/09 ESE-1.4 Sw-1 1/27/09 N-1.5 2/24/09 N-1.5 3/31/09 N-1.5 4/28/09 N-1.5 5/26109 N-1.5 6/30109 N-1.5 7/28/09 N-1.5 8/25/09 N-1.5 9/29109 N-1.5 10/27/09 N-1.5 11/24/09 N-1.5 12/28/09 N-1.5 SW-4 1/27/09 NE-7.4 2/24/09 NE-7.4 3/31/09 NE-7.4 4/28/09 NE-7.4 5/26/09 NE-7.4 6/30/09 NE-7.4 7/28/09 NE-7.4 8/25/09 NE-7.4 9/29/09 NE-7.4 10/27/09 NE-7.4 11/24/09 NE-7.4 12/28/09 NE-7.4 SW-3 1/27109 N-19.3 2/24/09 N-19.3 3/31/09 N-19.3 4/28/09 N-19.3 5/26/09 N-19.3 6/30/09 N-19.3 7/28/09 N-19.3 8/25/09 N-19.3 9/29/09 N-19.3 10/27/09 N-19.3 11124/09 N-19.3 12128/09 N-19.3 Required LLD's Reportable Level H-3 Nuclides Ba-140

<1.2E+01

<9.9E+00 1.209E+04

<6.5E+00

<1.5E+01

<1.0E+01 1.058E+04

<7.2E+00

<7.8E+00

<9.1E+00 1.415E+04

<7.4E+00

<1.1E+01

<5.3E+00 IAI9E+04

<7.8E+00 Ba-140

<7.3E+00

<8.1E+00 1.212E+04

<7.3E+00

<8.9E+00

<8.4 E+00 1.001E+04

<9.8 E+00

<8.2 E+00

<7.3 E+00 1A,03E+04

<1.1E+01

<9.2E+00

<6.OE+00 1.512E+04

<6.8E+00 Ba-140

<1.3E+01

<1.4E+01

<1.2E+03

<1.5E+01

<1.1E+01

<1.5E+01

<1.3E+03

<1.4E+01

<1.1E+01

<1.4E+01

<1.OE+03

<1.5E+01

<1.2E+01

<1.4E+01

<1.3E÷03

<1.0E+01 Ba-140

<1.3E+01

<1.0E+01

<1.2E+03

<1.2E+01

<1.3E+01

<1.4E÷03

<1.4E+01

<1.3E+01

<1.OE+03

<1.5E+01

<1.3E+01

<9.9E+00

<1.3E+03

<5.6E+00 3.00e+03 1.50e+01 3.00e+04 2.00e+02 Be-7

<3.3E+01

<2.4E+01

<1.4E+01

<3.4E+00

<2.9E+01

<1.8E+01

<1.9E+01

<2.0E+01

<1.7E+01

<2.2E+01

<1.1E+01

<2.4E+01 Be-7

<2.5E+01

<3.0E+01

<1.4E+01

<2.8E+01

<3.0E+01

<2.3E+01

<2.5E+01

<2.0E+01

<1.8E+01

<2.11+01

<1.5E+01

<1.6E+01 Be-7

<4.7E+01

<4.4E+01

<4.7E+01

<4.9E+01

<4.7E+01

<4.4E+01

<4.2E+01

<4.5E+01

<4.8E+01

<5.3E+01

<2.7E+01

<3.5E+01 Be-7

<5.8E+01

<4.0E+01

<4.9E+01

<5.4E+01

<5.7E+01

<4.6E+01

<4.3E+01

<5.1E+01

<2.4E+01

<3.1E+01 Co-58

<4.6E+00

<3.1E+00

<1.6E+00

<4.2E+00

<3.9E+00

<2.6E+00

<2.3E+00

<2.5E+00

<2.1E+00

<2.7E+00

<9.2E-01

<2.6E+00 Co-58

<3.0E+00

<3.8E+00

<1.6E+00

<3.2E+00

<3.4E+00

<2.7E+00

<2.8E+00

<2.2E+00

<2.3E+00

<1,5E+00

<1.7E+00 Co-58

<5.9E+00

<5.1E+00

<6.7E+00

<5.7E+00

<7.6E+00

<6.5E+00

<5.0E+00

<6.0E+00

<7.7E+00

<5.2E+00

<3.4E+00

<5.0E+00 Co-58

<7.9E+00

<4.5E+00

<7.4E+00

<5.9E+00

<8.2E+00

<5.1E+00

<5.0E+00

<5.8E+00

<5.9E+00

<6.0E+00

<3.0E+00

<3.4E+00 1.50e+01 1.00e+03 Co-60

<4.4E+00

<2.6E+00

<1.4E+00

<4.3E+00

<3.7E+00

<2.2E+00

<3.1E+00

<1.8E+00

<2.7E+00

<9.4E-01

<2.8E+00 Co-60

<2.8E+00

<3.3E+00

<1.2E+00

<2.9E+00

<3.4E+00

<2.3E+00

<1.9E+00

<2.4E+00

<2.2E+00

<1.2E+00

<1.7E+00 Co-60

<6.7E+00

<6.0E+00

<5.9E+00

<6.8E+00

<9.0E+00

<8.0E+00

<6.9E+00

<6.2E+00

<8.6E+00

<5.1E+00

<3.8E+00

<4.9E+00 Co-60

<7.1E+00

<5.0E+00

<6.9E+00

<6.0E+00

<7.8E+00

<5.9E+00

<6.6E+00

<5.0E+00

<7.5E+00

<5.0E+00

<3.0E+00

<3.0E+00 1.50e+01 3.00e+02 Cs-1 34

<3.0E+00

<2.9E+00

<1.3E+00

<3.7E+00

<4.2E+00

<2.OE+00

<2.1E+00

<2.4E+00

<1.7E+00

<2.5E+00

<8.4E-01

<2.1E+00 Cs-134

<2.3E+00

<2.8E+00

<1.3E+00

<2.8E+00

<3.2E+00

<2.6E+00

<2.4E+00

<1.9E+00

<2.1E+00

<1.2E+00

<1.6E+00 Cs-134

<6.7E+00

<5.8E+00

<6.5E+00

<5.8E+00

<7.8E+00

<4.9E+00

<5.1E+00

<5.5E+00

<6.6E+00

<5.8E+00

<3.3E+00

<4.5E+00 Cs-134

<5.8E+00

<3.6E+00

<6.6E+00

<5.9E+00

<7.2E+00

<5.7E+00

<5.2E+00

<5.4E+00

<6.2E+00

<5.7E+00

<2.6E+00

<3.6E+00 1.50e+01 3.00e+01 Cs-137

<3.2E+00

<2.8E+00

<1.2E+00

<3.7E+00

<3.5E+00

<2.0E+00

<2.4E+00

<1.7E+00

<2.3E+00

<9.0,-01

<2.4E+00 Cs-137

<2.4E+00

<1.3E+00

<2.5E+00

<3.0E+00

<2.3E+00

<2.5E+00

<1.9E+00

<2.1E+00

<2.2E+00

<1.4E+00

<1.6E+00 Cs-1 37

<6.0E+00

<4.9E+00

<6.9E+00

<6.8E+00

<6.5E+00

<6.0E+00

<5.8E+00

<4.9E+00

<7.3E+00

<5.4E+00

<3.1E+00

<4.3E+00 Cs-1 37

<7.3E+00

<4.8E+00

<5.5E+00

<5.3E+00

<6.2E+00

<5.8E+00

<5.2E+00

<6.1E+00

<7.0E+00

<5.1E+00

<2.8E+00

<4.1E+00 1.80e+01 5.00e+01 Fe-59

<9.4E+00

<6.3E+00

<3.8E+00

<9.7E+00

<1.0E+01

<5.5E+00

<4.9E+00

<5.9E+00

<4.6E+00

<6.7E+00

<2.8E+00

<5.4E+00 Fe-59

<5.8E+00

<8.5E+00

<3.3E+00

<7.6E+00

<6.8E+00

<6.3E+00

<6.1E+00

<4.8E+00

<5.5E+00

<5.3E+00

<3.8E+00

<3.8E+00 Fe-59

<1.5E+01

<1.1E+01

<1.4E+01

<1.1E+01

<1.7E+01

<1.4E+01

<1.2E+01

<1.1E+01

<1.4E+01

<1.1E+01

<8.0E+00

<9.8E+00 Fe-59

<1.6E+01

<8.8E+00

<1.6E+01

<1.3E+01

<1.7E+01

<1.3E+01

<1.1E+01

<1.3E+01

<7.9E+00

<7.3E+00 3.00e+0t 4.00e+02 1-131

<1.4E+01

<1.5E+01

<1.3E+01

<1.1E+01

<1.2E+01

<1.4E+01

<1.2E+01

<1.3E+01 1-131

<1.4E+01

<1.3E+01

<1.5E+01

<1.3E+01

<9.9E+00

<1.4E+01

<1.3E+01

<1.1E+01 1-131

<1.1E+01

<1.3E+01

<1.4E+01

<1.2E+01

<1.1E+01

<1.0E+01

<9.6E+00

<9.3E+00

<1.2E+01

<1.5E+01

<8.2E+00 1-131

<1.0E+01

<1.4E+01

<1.5E+01

<1.2E+01

<1.1E+01

<1.2E+01

<1.0E+01

<1.1E+01

<1.2E+01

<1.4E+01

<6.5E+01 1.50e+01 2.00e+01 K-40

<5.6E+01 2.3E+01 1.22E+01

<5.4E+01 4.6E+01 1.9E+01 2.34E+01

<3.8E+01

<2.9E+01

<3.9E+01 1,87E+01 2.46E+01 K-40 2.90E+01

<4.6E+01 1.86E+01

<3.9E+01

<3.8E+01 2.7E+01

<4.0E+01

<3.1E+01

<3.6E+01

<3.5E+01

<2.0E+01 2.76E+01 K-40

<7.9E+01

<8.1E+01

<9.8E+01

<9.2E+01

<1.1E+02

<9.1E+01

<8.2E+01

<8.8E+01

<1.0E+02

<7.1E+01

<4.4E+01

<6.5E+01 K-40

<9.7E+01

<6.3E+01

<1.0E+02

<9.7E+01

<1.0E+02

<9.3E+01

<8.7E+01

<8.2E+01

<9.4E+01

<8.2E+01

<4.3E+01

<5.3E+01 La-140

<1.2E+01

<9.9E+00

<6.5E+00

<1.5E+01

<1.0E+01

<7.2E+00

<7.8E+00

<9.1E+00

<7.4E+00

<1.1E+01

<5.3E+00

<7.8E+00 La-140

<7.3E+00

<8.1E+00

<7.3E+00

<8.9E+00

<8.4E+00

<9.8E+00

<8.2E+00

<7.3E+00

<1.1E+01

<9.2E+00

<6.0E+00

<6.8E+00 La-140

<1.3E+01

<1.4E+01

<1.5E+01

<1.1E+01

<1.5E+01

<1.4E+01

<1.1E+01

<1.4E+01

<1.5E+01

<1.2E+01

<1.4E+01

<1.0E+01 La-140

<1.3E+01

<1.0E+01

<1.2E+01

<1.3E+01

<1.4E+01

<1.3E+01

<1.5E+01

<1.3E+01

<9.9E+00

<5.6E+00 1.50e+01 2.00e+02 Mn-54

<3.5E+00

<2.6E+00

<1.3E+00

<3.8E+00

<3.6E+00

<2.2E+00

<2.4E+00

<1.6E+00

<2.5E+00

<8.9E-01

<2.5E+00 Mn-54

<2.3E+00

<2.8E+00

<1.2E+00

<2.6E+00

<3.3E+00

<2.1E+00

<2.4E+00

<1.8E+00

<2.1E+00

<1.9E+00

<1.4E+00

<1.6E+00 Mn-54

<6.3E+00

<5.4E+00

<6.7E+00

<6.4E+00

<7.3E+00

<4.9E+00

<5.6E+00

<6.0E+00

<6.7E+00

<5.3E+00

<3.4E+00

<3.4E+00 Mn-54

<6.7E+00

<4.0E+00

<6.1E+00

<6.9E+00

<7.3E+00

<5.7E+00

<4.6E+00

<5.1E+00

<6.4E+00

<5.5E+00

<2.5E+00

<3.4E+00 1.50e+01 1.00e+03 Nb-95

<5.3E+00

<4.2E+00

<2.4E+00

<5.1E+00

<2.8E+00

<2.6E+00

<2.9E+00

<3.2E+00

<1.4E+00

<3.4E+00 Nb-95

<3.5E+00

<4.0E+00

<2.0E+00

<4.2E+00

<3.9E+00

<3.1E+00

<2.6E+00

<2.7E+00

<2.5E+00

<2.8E+00 Nb-95

<6.9E+00

<7.3E+00

<8.8E+00

<6.6E+00

<8.1E+00

<5.9E+00

<6.2E+00

<5.7E+00

<7.3E+00

<6.9E+00

<4.1E+00

<5.2E+00 Nb-95

<1.1E+01

<6.2E+00

<7.5E+00

<8.4E+00

<6.5E+00

<6.3E+00

<5.9E+00

<7.1E+00

<6.0E+00

<3.7E+00

<4.2E+00 1.50e+01 4.00e+02 Zn-65 Zr-95

<9.9E+00

<6.2E+01

<5.9E+00

<4.9E+00

<3.1E+00

<2.9E+00

<I.0E+00

<6.4E+00

<9.0E+00

<6.8E+00

<4.7E+00

<3.7E+00

<4.8E+00

<3.9E+00

<5.4E+00

<4.7E+00

<4.3E+00

<3.3E+00

<5.1E+00

<4.4E+00

<1.7E+00

<8.5E+00

<4.0E+00 Zn-65 Zr-95

<6.2E+00

<5.5E+00

<6.4E+00

<5.9E+00

<3.0E+00

<2.7E+00

<5.2E+00

<6.2E+00

<7.3E+00

<5.6E+00

<7.4E+00

<5.5E+00

<5.7E+00

<4.5E+00

<4.3E+00

<3.6E+00

<4.9E+00

<4.3E+00

<4.6E+00

<4.1E+00

<4.6E+00

<2.5E+00

<3.4E+00

<3.0E+00 Zn-65 Zr-95

<1.7E+01

<1.1E+01

<8.9E+00

<1.0E+01

<1.9E+01

<1.2E+01

<2.4E+01

<1.1E+01

<2.1E+01

<1.3E+01

<1.4E+01

<9.8E+01

<1.6E+01

<8.5E+00

<1.6E+01

<9.7E+00

<2.9E+01

<1.0E+01

<1.8E+01

<1.1E+01

<8.0E+00

<5.9E+00

<1.0E+01

<8.4E+00 Zn-65 Zr-95

<1.3E+01

<1.0E+01

<1.4E+01

<8.9E+00

<1.5E+01

<1.1E+01

<2.3E+01

<1.1E+01

<1.5E+01

<1.4E+01

<9.4E+00

<1.4E+01

<9.4E+00

<1.4E+01

<1.1E+01

<1.4E+01

<1.1E+01

<1.5E+01

<1.1E+01

<5.0E+00

<7.1E+0023 <5.8E+00 3.00e+01 1.50e+01 3.00e+02 4.00e+02

Graph 2 -- 2009 Environmental Surface Water Tritium Results 0.

0 401

'I' 16000 14000 12000 10000 8000 6000 4000 2000 0

-,- N-19.3 N-1.5 NE-7.4

--ESE-1.4 Mar-0EI Jun-09 Sep-09 Dec-09 Monthly/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 2009 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. 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 2009, 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 1.15E+04 pCi/I to 1.45E+04 pCi/i and averaged 1.31E+04 pCi/l. Tritium reported from'all Lake Granbury water samples indicated less than the required LLD as expected. Graph 4 - 2009 Environmental Surface Drinking Water Tritium Results trends the results reported for the year 2009. Gross Beta results at the indicator location NNW-0. 1 ranged from 1.59E+01 pCi/i to 3.67E+01 pCi/i with an average of 2.50E+01 pCi/i. Gross Beta results at the control location N-9.9 ranged from 7.OE+00 pCi/i to 1.57E+01 pCi/i with an average of 1.02E+00 pCi/I. Graph 5 - 2009 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.

For the year 2009, there were no exceptions to the Surface Drinking Water Program.

25

Table 8 - 2009 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results (Units of pCi/I)

SW-6 Date Location 1/27/09 NNW-0.1 2/24/09 NNW-0.1 3/31/09 NNW-0.1 4/28/09 NNW-0.1 5/26/09 NNW-0.1 6/30/09 NNW-0.1 7/28/09 NNW-0.1 8/25/09 NNW-0.1 9/29/09 NNW-0.1 10/27/09 NNW-0.1 11/24/09 NNW-0.1 12/28/09 NNW-0.1 SW-2 1/27/09 N-9.9 2/24/09 N-9.9 3/31/09 N-9.9 4/28/09 N-9.9 5/26109 N-9.9 6/30/09 N-9.9 7/28/09 N-9.9 8/25/09 N-9.9 9/29/09 N-9.9 10/27/09 N-9.9 11/24/09 N-9.9 12/28/09 N-9.9 Required LLD's Reportable Level Gross Nuclides H-3 Beta 1-131 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 2.03E+01

<9.3E-01

<1.1E+01

<4.2E+00

<4.7E+00

<3.2E+00

<3.7E+00

<1.2E+01

<1.1E+01 1.92E+01

<8.4E-01

<1.3E+01

<3.9E+00

<3.8E+00

<3.OE+00

<3.1E+00

<8.4E+00

<1.3E+01 1.204E+04 1.85E+01

<9.3E-01

<1.3E+01

<3.1E+00

<2.5E+00

<3.1E+00

<8.5E+00

<1.3E+01 2.78E+01

<7.7E-01

<8.9E+00

<3.3E+00

<2.7E+00

<2.5E+00

<7.4E+00

<8.9E+00 2.55E+01

<7.5E-01

<1.4E+01

<3.7E+00

<3.4E+00

<3.5E+00

<9.5E+00

<1.4E+01 1.148E+04 2.76E+01

<8.5E-01

<1.4E+01

<3.8E+00

<3.6E+00

<3.1E+00

<3.OE+00

<7.8E+00

<1.4E+01 2.46E+01

<7.4E-01

<1.OE+01

<2.8E+00

<2.6E+00

<2.OE+00

<2.4E+00

<6.OE+00

<1.OE+01 1.59E+01

<9.3E-01

<6.5E+00

<1.6E+00

<1.4E+00

<3.4E+00

<6.5E+00 1.423E+04 3.32E+01

<99E-01

<6.7E+00

<2.OE+00

<1.8E+00

<1.9E+00

<1.6E+00

<4.1E+00

<6.7E+00 2.52E+01

<6.9E-01

<1.5E+01

<3.9E+00

<3.2E+00

<3.8E+00

<3.4E+00

<8.4E+00

<1.5E+01 2.62E+01

<9.8E-01

<8.8E+00

<1.6E+00

<1.3E+00

<1.4E+00

<1.5E+00

<3.8E+00

<8.8E+00 1.452E+04 3.67E+01

<9.8E-01

<1.5E+01

<3.OE+00

<2.2E+00

<2.4E+00

<7.2E+00

<1.5E+01 Gross H-3 Beta 1-131 Ba-140 Co-58 Co-60 Cs-134 Cs-137 Fe-59 La-140 9.40E+00

<9.3E-01

<1.4E+01

<3.2E+00

<3.7E+00

<3.6E+00

<3.3E+00

<1.OE+01

<1.4E+01 1.57E+01

<8.4E-01

<1.4E+01

<4,3E+00

<4.2E+00

<3.6E+00

<3.8E+00

<1.1E+01

<1.4E+01

<1.3E+03 1.11E+01

<9.OE-01

<1.2E+01

<3.4E+00

<3.3E+00

<2.2E+00

<8.7E+00

<1.2E+01 9.70E+00

<6.9E-01

<1.1E+01

<3.2E+00

<3.6E+00

<3.1E+00

<7.9E+00

<1.1E+01 1.12E+01

<6.1E-01

<1.4E+01

<3.2E+00

<2.9E+00

<3.5E+00

<3.4E+00

<8.6E+00

<1.4E+01

<1.4E+03 1.11E+01

<9.3E-01

<1.4E+01

<2.9E+00

<2.7E+00

<2.5E+00

<6.6E+00

<1.4E+01 1.02E+01

<7.1E-01

<1.1E+01

<2.7E+00

<3.OE+00

<2.7E+00

<2.5E+00

<6.8E+00

<1.1E+01 7.1E+00

<9.7E-01

<9.8E+00

<2.6E+00

<3.OE+00

<2.3E+00

<2.7E+00

<5.8E+00

<9.8E+00

<1.OE+03 9.4E+00

<7.6E-01

<1.5E+01

<2.9E+00

<2.5E+00

<2.8E+00

<2.7E+00

<7.9E+00

<1.5E+01 1.11E+01

<9.3E-01

<1.2E+01

<3.6E+00

<3.4E+00

<5.2E+00

<3.5E+00

<8.2E+00

<1.2E+01 9.7E+00

<9.5E-01

<8.2E+00

<1.6E+00

<1.3E+00

<1.2E+00

<1.1E+00

<3.7E+00

<8.2E+00

<1.3E+03 7.OE+00

<8.8E-01

<8.OE+00

<2.7E+00

<2.8E+00

<2.6E+00

<2.9E+00

<7.2E+00

<8.OE+00 2.OOE+03 4.OOE+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 2.00E+04 None 2.00E+00 2.OOE+02 1.00E+03 3.OOE+02 3.00E+01 5.OOE+01 4.OOE+02 2.OOE+02 Mn-54 Nb-95 Zn-65 Zr-95

<4.5E+00

<6.2E+00

<1.2E+01

<7.6E+00

<3.3E+00

<5.OE+00

<8.2E+00

<6.2E+00

<3.OE+00

<4.2E+00

<6.7E+00

<4.9E+00

<2.7E+00

<4.OE+00

<6.1E+00

<5.5E+00

<3.2E+00

<5.OE+00

<9.OE+00

<6.6E+00

<3.1E+00

<4.4E+00

<7.5E+00

<6.4E+00

<2.2E+00

<3.2E+00

<5.4E+00

<3.8E+00

<1.3E+00

<2.OE+00

<3.4E+00

<2.8E+00

<1.6E+00

<2.3E+00

<3.8E+00

<3.4E+00

<3.1E+00

<4.9E+00

<7.2E+00

<6.6E+00

<1.3E+00

<2.8E+00

<4.OE+00

<2.8E+00

<2.7E+00

<3.8E+00

<8.6E+00

<4.8E+00 Mn-54 Nb-95 Zn-65 Zr-95

<2.7E+00

<4.4E+00

<7.6E+00

<6.2E+00

<3.4E+00

<5.6E+00

<8.1E+00

<6.6E+00

<3.OE+00

<4.6E+00

<7.1E+00

<5.2E+00

<2.9E+00

<4.1E+00

<9.8E+00

<6.1EE+00

<2.9E+00

<4.3E+00

<7.3E+00

<6.5E+00

<2.5E+00

<3.7E+00

<5.6E+00

<5.1E+00

<2.6E+00

<3.6E+00

<5.8E+00

<5.OE+00

<2.1E+00

<3.5E+00

<6.4E+00

<4.4E+00

<2.7E+00

<4.OE+00

<4.9E+00

<4.8E+00

<3.4E+00

<4.5E+00

<8.OE+00

<5.9E+00

<1.2E+00

<2.OE+00

<4.1E+00

<2.7E+00

<2.8E+00

<4.2E+00

<5.2E+00

<4.7E+00 1.50E+01 1.50E+01 3.OOE+01 1.50E+01 11.00E+03 4.OOE+02 3.OOE+02 4.OOE+02 26

Graph 3 -- Squaw Creek Maximum Tritium Values U

4-0 30000 25000 20000 15000 10000 5000 0

--* Maximum tritium

Kb 001 cf,~

0 Yearly Maximum 27

Graph 4 -- 2009 Environmental Surface Drinking Water Tritium Results 0.

CL

'4-0 1.60E+04 1.40E+04 1.20E+04 I.OOE+04 8.OOE+03 6.OOE+03 -

4.OOE+03 2.OOE+03 0.00E+00 Mar-09

-N-9.9

---NNW-0. 1 Jun-09 Sep-09 Dec-09 Composite Sample Dates 28

Graph 5 -- 2009 Environmental Surface Drinking Water Gross Beta Results 4-0 U) 4wI E

4.OOE+01 3.50E+01 3.OOE+01 2.50E+01 2.OOE+01 1.50E+01 1.OOE+01 5.OOE+00 O.OOE+00

-,- N-9.9

--- NNW -0. 1 Monthly Data Points 29

F.

Groundwater Pro2ram Table 1 - Comanche Peak Nuclear Power Plant Radiological Environmental Monitoring Program for 2009 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 2009 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 - 2009 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.

For the year 2009, there were no exceptions to the Groundwater Program.

30

Table 9 -

2009 Environmental Groundwater Tritium and Gamma Isotopic Results (Units of pCI/I)

Location Date GW-3 3131109 SSE-4.6 6/30/09 SSE-4.6 9/29/09 SSE-4.6 12/28/09 SSE-4.6 GW-5 3/31/09 N-1.45 6/30/09 N-1.45 9/29/09 N-1.45 12128/09 N-1.45 GW-4 3/31/09 N-9.8 6/30/09 N-9.8 9/29/09 N-9.8 12/28/09 N-9.8 GW-1 3/31/09 W-1.2 6/30/09 W-1.2 9/29/09 W-1.2 12/28/09 W-1.2 GW-2 3/31/09 WSW-0.1 6/30/09 WSW-0.1 9129/09 WSW-0.1 12/28/09 WSW-0.1 Required LLD's Reportable Levels Nuclides H-3 Ba-140 Co-58

<1.4E+03

<8.OE+00

<2.4E+00

<1.3E+03

<1.1E+01

<7.OE+00

<1.2E+03

<1.4E+01

<5.5E+00

<1.3E+03

<1.3E+01

<6.7E+00

<1.3E+03

<7.4E+00

<2.4E+00

<1.3E+03

<1.4E+01

<5.1E+00

<1.2E+03

<1.5E+01

<5.4E+00

<1.3E+03

<1.2E+01

<7.7E+00

<1.4E+03

<1.3E+01

<5.7E+00

<1.3E+03

<1.3E+01

<4.5E+00

<1.2E+03

<1.4E+01

<4.9E+00

<1.3E+03

<1.4E+01

<6.7E+00

<1.3E+03

<1.4E+01

<6.OE+00

<1.3E+03

<1.4E+01

<6.2E+00

<1.2E+03

<9.4E+00

<4.5E+00

<1.3E+03

<1.2E+01

<6.3E+00

<1.3E+03

<9.3E+00

<2.4E+00

<1.3E+03

<7.4E+00

<2.6E+00

<1.2E+03

<1.4E+01

<5.6E+00

<1.3E+03

<8.OE+00

<4.OE+00 3.00E+03 1.50E+01 1.50E+01 Co-60

<2.2E+00

<9.7E+00

<5.1 E+00

<6.4E1-00

<2.2E+00

<5.4E+00

<6.2E+00

<7.9E+00

<6.6E+00

<4.8E+00

<5.3E+00

<6.8E+00

<6.2E+00

<6.4E+00

<4.9E+00

<7.8E+00

<2.4E+00

<2.7E+00

<6.1 E+00

<4.2E+00 1.50E+01 Cs-1 34

<2.1E+00

<6.9E+00

<5.1E+00

<7.3E+00

<2.2E+00

<4.1 E+00

<5.6E+00

<7.3E+00

<6.2E+00

<4.4E+00

<5.OE+00

<5.4E+00

<5.8E+00

<5.2E+00

<4.7E+00

<6.8E+00

<2.4E+00

<3.4E+00

<4.7E+00

<3.9E+00 1.50E+01 Cs-137 Fe-59

<2.2E+00

<5.2E+00

<6.3E+00

<1.5E+01

<5.3E+00

<1.2E+01

<5.6E+00

<1.2E+01

<2.2E+00

<5.5E+00

<4.8E+00

<1.OE+01

<5.3E+00

<1.2E+01

<6.8E+00

<1.4E+01

<6.4E+00

<1.3E+01

<4.7E+00

<8.8E+00

<4.6E+00

<1.2E+01

<7.5E+00

<1.5E+01

<5.7E+00

<1.5E+01

<5.3E+00

<1.2E+01

<4.7E+00

<1.1E+01

<6.8E+00

<1.4E+01

<2.3E+00

<5.3E+00

<2.7E+00

<6.OE+00

<6.7E+00

<1.3E+01

<4.7E+00

<8.1E+00 1.80E+01 3.OOE+01 1-131

<1.2E+01

<1.5E+01

<1.3E+01

<1.OE+01

<1.1E+01

<1.3E+01

<1.2E+01

<1.3E+01

<1.2E+01

<1.1E+01

<1.5E+01

<1.4E+01

<1.3E+01

<1.2E+01

<1.4E+01

<9.1 E+00

<1.3E+01

<8.9E+00 1.50E+01 La-140

<8.OE+O0

<1.1E+01

<1.4E+01

<1.3E+01

<7.4E+00

<1.4E+01

<1.5E+01

<1.2E+01

<1.3E+01

<1.4E+01

<9.4E+00

<1.2E+01

<9.3E+00

<7.4E+00

<1.4E+01

<8.0E+O0 1.50E+01 Mn-54 Nb-95 Zn-65

<2.1E+00

<3.7E+00

<4.6E+00

<7.2E+00

<7.7E+00

<1.6E+01

<5.5E+00

<7.4E+00

<1.5E+01

<6.6E+00

<6.5E+00

<1.5E+01

<2.2E+00

<4.OE+00

<8.8E+00

<4.4E+00

<4.8E+00

<1.1E+01

<5.4E+00

<5.2E+00

<1.4E+01

<7.5E+00

<8.1E+00

<2.7E+01

<5.2E+00

<7.1E+00

<1.9E+01

<4.5E+00

<4.9E+00

<1.OE+01

<5.3E+00

<6.4E+00

<1.3E+01

<6.5E+00

<6.8E+00

<1.5E+01

<6.2E+00

<7.2E+00

<1.5E+01

<5.4E+00

<6.7E+00

<1.3E+01

<5.OE+00

<6.3E+00

<1.2E+01

<6.9E+00

<9.3E+00

<1.4E+01

<2.1E+00

<3.OE+00

<5.3E+00

<2.9E+00

<3.3E+00

<7.1E+00

<5.3E+00

<7.OE+00

<1.3E+01

<3.6E+00

<5.OE+00

<8.9E+00 1.50E+01 1.50E+01 3.00E+01 Zr-95

<5.1 E+00

<1.OE+01

<1.1E+01

<4.3E+00

<7.1E+00

<9.OE+00

<1.2E+01

<1.OE+01

<8.2E+00

<8.4E+00

<1.2E+01

<1.OE+01

<1.IE+01

<8.3E+00

<1.2E+01

<4.7E+00

<5.4E+00

<8.9E+00

<7.5E+00 1.50E+01 4.OOE+02 2.OOE+04 2.OOE+02 1.00E+03 3.00E+02 3.00E+011 5.OOE+01 4.OOE+02 2.OOE'-01 2.OOE+02 I.00E+03 4.OOE+02 3.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 2009 results from the gamma isotopic analysis of shoreline sediments is reported in Table 10 - 2009 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. Radioactive nuclides required to be analyzed for were performed and all but one sample indicated less than the required LLDs. During previous years, both pre-operational and operational, positive indications occasionally had been noted for Cesium-137 and during 2009 there was one positive Cesium-137 results reported above the required LLD. The only other positive value reported for 2009 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.

For the year 2009, there were no exceptions to the Sediment Program.

32

Table 10 -- 2009 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 Location 1/13109 SE-5.3

<2.OE+02

<2,3E+02

<4.3E+01

<3.OE+01

<3.5E+01 4E+01

<9.5E+01

<6.6E+01 6.25E+03

<8.7E+01

<4.9E+01

<5.OE+01

<1.4E+02

<7.1E+01 1/13109 NNE-1.0

<2.4E+02

<4.6E+02

<4.2E+01

<4.8E+01

<4.8E+01 3.78E+02

<1.OE+02

<1.OE+02 7.04E+03

<1.1E+02

<4.4E+01

<6.1E+01

<2.7E+02

<7.4E+01 1/13/09 NE-7.4

<1.5E+02

<2.OE+02

<2.5E+01

<2.8E+01

<2.6E+01

<2.8E+01

<6.3E+01

<3.5E+01 2.21 E+03

<6.1E+01

<2.9E+01

<8.3E+01

<3.8E+01 1/13/09 N-9.9

<9.9E+01

<1.7E+02

<2.2E+01

<2.1E+01

<2.2E+01

<2.6E+01

<4.7E+01

<4.OE+o1 1.62E+03

<6.1E+01

<2.1E+01

<2.7E+01

<8.8E+01

<3.7E+01 7/7/09 SE-5.3

<4.3E+02

<3.9E+02

<6.1E+01

<3.9E+01

<4.2E+01

<6.1E+01

<1.5E+02

<2.6E+02 4.82E+03

<2.4E+02

<5.5E+01

<6.4E+01

<1.8E+02

<8.5E+01 7/7/09 NNE-1.0

<9.1E+01 9.3E+01

<1.5E+01

<1.9E+01

<1.5E+01

<1.7E+01

<3.7E+01

<4.3E+01 1.16E+03

<5.4E+01

<1.5E+01

<2.1E+01

<3.8E+01

<2.9E+01 7/7/09 NE-7.4

<1.1E+02

<1.2E+02

<1.9E+01

<2.4E+01

<1.7E+01

<1.9E+01

<4.6E+01

<5.4E+01 2.68E+03

<5.6E+01

<2.OE+01

<2.2E+01

<8.8E+01

<3.2E+01 7/7109 N-9.9

<7.1E+01

<1.OE+02

<1.2E+01

<9.5E+00

<9.6E+00

<1.2E+01

<2.6E+01

<3.2E+01 2.2E+03

<3.6E+01

<9.9E+00

<2.1E+01

<2.2E+01

<1.9E+01 Required LLD's 1.50E+02 1.80E+02 Reportable Levels None None 33

H.

Fish Program Fish samples were collected at two locations during the year 2009. 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. CPNPP has contracted with an off site vendor for collection of fish from these areas. 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 2009, the results of the analysis performed on the collected fish samples are reported in Table 11 -- 2009 Environmental Fish Gamma Isotopic Results. Catfish, Drum 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.

For the year 2009, there were no exceptions to the Fish Program.

No abnormal results were reported by CPNPP or by the State of Texas. As expected, Potassium-40 was the only positive isotope found.

34

Table 11 -- 2009 Environmental Fish Gamma Isotopic Results (Units of pCilkg wet)

Nuclides Ba-140 Date Location 04128109 Squaw Creek

<1.8E+02 04/28109 Squaw Creek

<9.8E÷01 10/20/09 Squaw Creek

<I.IE+02 10/20/09 Squaw Creek

<8.9E+01 Co-58 Co-60 Cs-134 Cs-137 Fe-59 1-131 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Fish Type

<5.8E+01

<6.6E+01

<4.4E+01

<1.7E+02

<1.6E+02 2.94E+03

<1.8E+02

<5.8E+01

<7.2E+01

<1.6E+02

<9.6E+01 Catfish

<5.OE+OI

<4.4E+O1

<4.1E+OI

<8.2E+01

<1.3E+02 2.66E+03

<9.8E+0!

<4.4E+01

<4.8E+01

<I.OE+02

<6.3E+01 Bass

<5.4E+O1

<4.3E+OI

<4.5E+01

<9.6E+01

<9.4E+01 2.23E+03

<I.IE+02

<2.5E+01

<3.9E+01

<1.OE+02

<6.IE+O1 Catfish

<4.9E+01

<4.1E+OI

<3.2E+01

<l.lE+02

<9.5E+01 2.77E+03

<8.9E+01

<3.4E+01

<4.1E+OI

<I.IE+02

<6,OE+O1 Bass

<8.9E+01

<6.9E+01

<7.8E+01

<1.3E+02

<1.4E+02 3.31E+03

<2.3E+02

<5.OE+01

<8.7E+01

<1.9E+02

<I.IE+O1 Catfish

<4.4E+01

<6.2E+01

<6.3E+01

<1.4E+02

<1.7E+02 2.16E+03

<1.2E+02

<4.7E+OI

<6.6E+01

<1,3E+02

<8.2E+01 Bass

<6.6E+O1

<5.4E+01

<5.IE+O1

<1.2E+02

<9.1E+OI 2.87E+03

<1.2E+02

<6.OE+01

<4.6E+01

<1.6E+02

<7.2E+01 Catfish

<3.8E+01

<3.4E+01

<6.7E+01

<8.3E+01 2.81E+03

<6.1E+01

<3.2E+01

<3.9E+01

<8.IE+O1

<5.6E+OI Bass 04/28/09 Lake Granbury

<2.3E+02 04/28/09 Lake Granbury

<1.2E+02 10/20/09 Lake Granbury

<6.IE+01

<8. 1 E+O I

'c3.7E+O I

<5.5SE+01I

<3.1 E+O I Required LLD's Reportable Levels 1.30E+'02 1.30E+02 1.30E--02 1.50E+0-2 2.60E+02 3.OOE-'04 1.00E+04 1.00E'-03 2.OOE--03 I.OOE-.04 1.30E+02 3.00 E-04 2.60E+02 2,OOE-'04 35

I.

Food Products Program Food products (pecan) were collected 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 2009, results of the gamma isotopic analyses are reported in Table 12 -- 2009 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.

For the year 2009, there were no exceptions to the Food Products program.

36

Table 12 -- 2009 Environmental Food Products Gamma Isotopic Results (Units of pCilkg wet)

Food Type - Pecans Nuclides Ba-1 40 Be-7 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 Date Location 11/10/09 ENE-9.0

<4.1E+01

<1.7E+02

<2.3E+01

<2.OE+01

<2.3E+01

<4.9E+01

<4.5E+01 3.02E+03

<4.1E+01

<2.OE+01

<2.2E+01

<5.OE+01

<3.2E+o1 Required LLD's 6.OOE+01 8.OOE+01 6.OOE+01 Reportable Levels I.OOE+03 2.OOE+03 1.00E÷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-1.45 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 2009, all radionuclide analysis met their required LLDs and there was no indication of gamma emitting radionuclides. There was one positive indication of Iodine-131 which was less than the required LLD.

The naturally occurring radionuclide of Potassium-40 was found in 36 of 36 samples taken. The radionuclide Beryllium-7 was present in 30 of 36 samples.

For the year 2009, there were no exceptions to the Broadleaf Program.

38

Table 13 -- 2009 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-1 34 Cs-137 Fe-59 K-40 La-140 Mn-54 Nb-95 Zn-65 Zr-95 Date 1127109 2/24/09 3/31109 4128109 5/26/09 6130/09 7/28109 8/25/09 9/29/09 10/27/09 11/24/09 12128/09 1/27/09 2124/09 3/31/09 4128/09 5126/09 6/30/09 7/28/09 8/25/09 9/29/09 10/27/09 11/24/09 12/28/09 1/27/09 2/24/09 3/31/09 4/28/09 5/26/09 6/30/09 7128/09 8/25/09 9/29/09 10/27/09 11/24/09 12128/09 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 BL-3 Control SW -13.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 SW-3.5 BL-2 SW-I.0 Sw-1.0 SW-1.0 SW-I.0 SW-1.0 SW-1.0 SW-I.0 SW-I.0 SW-1.0 SW-1.0 SW-1.0 SW-1.0

<4.5E+01

<5.7E+01

<3.3E+01

<4.7E+01 5.5E+01

<5.4E+01

<3.OE+01

<4.5E+01

<5.1 E+01

<4.9E+01

<5.4E+01

<5.6E+01

<5.4E+01

<3.1E+01

<5.1E+01

<5.5E+01

<5.OE+01

<3.3E+01

<5.2E+01

<4.7E+01

<5.OE+01

<4.OE+01

<4.4E+01

<4.3E+01

<5.1 E+01

<3.5E+01

<5.6E+01

<4.2E+01

<4.6E+01

<3.8E+01

<4.3E+01

<5.4E+01

<4.6E+01

<5.4E+01

<5.5E+01 6.OOE+01 1.OOE+02

<8.OE+01 1.58E+03

<4.2E+01

<1.2E+02 5.88E+03

<5.6E+01

<1.1E+02 8.5E+03

<6.2E+01

<9.4E+01 6.49E+03

<3.4E+01

<9.5E+01 2.99E+03

<3.4E+01

<1.3E+02

<4.7E+03

<5.7E+01

<9.2E+01 1.35E+03

<3.7E+01

<1.2E+02

<4.5E+02

<4.1E+01

<2.2E+02 8.3E+02

<3.1E+01

<3.7E+02 3.25E+03

<4.9E+01

<1.7E+02 7.42E+03

<4.8E+01

<1.1E+02 8.09E+03

<4.OE+01

<1.3E+02 9.9E+02

<4.3E+01

<1.2E+02 3.63E+03

<5.5E+01

<1.2E+02 3.8E+02

<4.OE+01

<1.7E+02 2.88E+03

<5.5E+01

<1.5E+02 1.43E+03

<5.6E+01

<2.3E+02 1.34E+03

<6.OE+01

<2.1E+02 6.8E+02

<7.8E+01

<1.7E+02 3.73E+03

<6.OE+01

<1.7E+02 1.54E+03

<6.OE+01

<3.6E+02 2.8E+03

<6.3E+01

<1.4E+02 1.96E+03

<4.8E+01

<1.4E+02 7.78E+03

<5.6E+01

<9.5E+01 1.36E+03

<4.4E+01

<1.4E+02 3.18E+03

<6.OE+01

<8.6E+01 3.96E+03

<3.1E+01

<2.OE+02 5.06E+03

<6.7E+01

<1.3E+02 6.8E+02

<5.OE+01

<1.7E+02 7.5E+02

<6.8E+01

<1.4E+02 3.9E+02

<3.8E+01

<1.6E+02 1.58E+03

<5.6E+01

<2.2E+02 1.59E+03

<7.4E+01

<2.6E+02 5.69E+03

<4.2E+01

<1.4E+02 1.02E+04

<4.5E+01

<9.2E+01 4.27E+03

<3.6E+01

<3.2E+01

<6.5E+01

<5.7E+01

<3.4E+01

<4.2E+01

<7.2E+01

<3.3E+01

<4.4E+01

<3.3E+01

<4.9E+01

<4.3E+01

<4.1E+01

<5.9E+01

<6.3E+01

<5.5E+01

<4.8E+01

<5.5E+01

<7.1 E+01

<8.3E+01

<5.3E+01

<5.8E+01

<5.2E+01

<4.3E+01

<6.5E+01

<4.5E+01

<7.3E+01

<3.4E+01

<6.2E+01

<5.OE+01

<7.2E+01

<4.6E+01

<6.OE+01

<9.3E+01

<4.7E+01

<4.3E+01

<3.7E+01

<3.8E+01

<3.7E+01

<5.3E+01

<5.4E+01

<5.2E+01

<5.OE+01

<3.2E+01

<2.9E+01

<3.5E+01

<3.4E+01

<5.8E+01

<5.3E+01

<3.3E+01

<4.1E+01

<4.7E+01

<4.5E+01

<3.6E+01

<4.7E+01

<5.3E+01

<4.9E+01

<4.5E+01

<4.8E+01

<4.OE+01

<3.9E+01

<3.8E+01

<4.3E+01

<5.6E+01

<5.8E+01

<4.5E+01

<5.1E+01

<4.4E+01

<3.7E+01

<4.5E+01

<6.2E+01

<5.3E+01

<7.OE+01

<4.9E+01

<7.7E+01

<4.6E+01

<5.3E+01

<5.2E+01

<5.5E+01

<5.2E+01

<4.2E+01

<3.6E+01

<5.9E+01

<5.5E+01

<4.1E+01

<3.7E+01

<5.9E+01

<6.1E+01

<3.1E+01

<3.OE+01

<5.9E+01

<6.2E+01

<4.9E+01

<3.4E+01

<5.9E+01

<6.7E+01

<5.4E+01

<5.8E+01

<5.5E+01

<5.2E+01

<5.9E+01

<6.OE+01

<4.2E+01

<4.4E+01

<4.1E+01

<3.9E+01

<3.6E+01

<3.2E+01 6.OOE+01 8.OOE+01 1.00E+03 2.OOE+03

<8.3E+01

<6.2E+02

<1.2E+02 1.25E+03

<1.2E+02 6.73E+03

<7.4E+01 1.08E+03

<8.3E+01 4.01 E+03

<1.8E+02 4.12E+03

<8.4E+01 2.56E+03

<1.1E+02 7.89E+03

<8.9E+01 2.69E+03

<1.8E+02 3.5E+03

<1.lE+02 3.4E+03

<9.7E+01 1.54E+03

<1.1E+02

<6.4E+02

<1.2E+02

<9.1E+02

<1.2E+02 5.87E+03

<1.3E+02 6.7E+02

<1.5E+02 3.39E+03

<1.1E+02 2.82E+03

<1.8E+02 2.72E+03

<1.1E+02 2.62E+03

<1.5E+02 3.03E+03

<1.1E+02 2.1E+03

<1.2E+02 8.38+03

<1.1E+02 2.04E+03

<8.7E+01

<6.OE+02

<1.4E+02

<1.2E+03

<7.OE+01 4.52E+03

<1.3E+02

<8.9E+02

<1.1E+02 3.76E+03

<1.5E+02 3.78E+03

<1.2E+02 3.67E+03

<1.4E+02 2.91E+03

<1.5E+02 3.26E+03

<1.2E+02 1.74E+03

<1.OE+02 2.68E+03

<7.4E+01 1.78E+03

<8.OE+01

<4.2E+01

<1.2E+02

<5.6E+01

<1.1E+02

<6.3E+01

<9.4E+01

<3.2E+01

<9.5E+01

<3.6E+01

<1.3E+02

<6.OE+01

<9.2E+01

<4.4E+01

<1.2E+02

<3.8E+01

<2.2E+02

<4.5E+01

<3.7E+02

<5.5E+01

<1.7E+02

<4.OE+01

<1.1E+02

<3.9E+01

<1.3E+02

<3.4E+01

<1.2E+02

<5.7E+01

<1.2E+02

<3.7E+01

<1.7E+02

<4.7E+01

<1.5E+02

<6.1E+01

<2.3E+02

<5.4E+01

<2.1E+02

<7.OE+01

<1.7E+02

<5.1E+01

<1.7E+02

<5.3E+01

<3.6E+02

<5.2E+01

<1.4E+02

<4.OE+01

<1.4E+02

<4.9E+01

<9.5E+01

<3.5E+01

<1.4E+02

<6.2E+01

<8.6E+01

<2.8E+01

<2.OE+02

<6.OE+01

<1.3E+02

<5.1E+01

<1.7E+02

<5.2E+01

<1.4E+02

<4.1E+01

<1.6E+02

<4.9E+01

<2.2E+02

<6.IE+01

<2.6E+02

<4.1E+01

<1.4E+02

<4.4E+01

<9.2E+01

<3.4E+01

<5.2E+01

<6.8E+01

<6.4E+01

<4.4E+01

<4.2E+01

<7.9E+01

<4.2E+01

<5.OE+01

<5.7E+01

<7.3E+01

<6.6E+01

<4.9E+01

<4.2E+01

<7.9E+01

<3.9E+01

<6.9E+01

<7.6E+01

<7.2E+01

<7.8E+01

<8.1 E+01

<9.3E+01

<5.4E+01

<6.4E+01

<5.5E+01

<7.4E+01

<4.OE+01

<7.6E+01

<5.5E+01

<7.7E+01

<6.5E+01

<7.2E+01

<7.8E+01

<6.9E+01

<6.1E+01

<4.3E+01

<1.3E+02

<7.5E+01

<1.3E+02

<9.9E+01

<1.7E+02

<9.7E+01

<7.3E+01

<5.5E+01

<8.5E+01

<6.5E+01

<1.2E+02

<1.1E+02

<8.2E+01

<7.3E+01

<1.1E+02

<7.7E+01

<1.1E+02

<5.8E+01

<2.OE+02

<9.8E+01

<9.3E+01

<7.7E+01

<1.4E+02

<7.4E+01

<9.9E+01

<7.1E+01

<1.5E+02

<9.8E+01

<1.2E+02

<6.3E+01

<1.1E+02

<1.OE+02

<1.5E+02

<1.OE+02

<1.3E+02

<1.1E+02

<1.5E+02

<1.2E+02

<1.OE+02

<2.3E+02

<1.OE+02

<2.1E+02

<1.1E+02

<1.2E+02

<8.1E+01

<1.3E+02

<9.8E+01

<1.4E+02

<7.2E+01

<1.4E+02

<1.1E+02

<7.6E+01

<5.3E+01

<1.5E+02

<1.2E+02

<1.3E+02

<8.OE+01

<1.6E+02

<1.2E+02

<1.OE+02

<9.2E+01

<1.2E+02

<1.1E+02

<2.7E+02

<1.1E+02

<8.3E+01

<9.8E+01

<8.2E+01

<9.6E+01

<6.6E+01 Required LLD's Reportable Levels 39

K.

Conclusions For the year 2009, 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 2009 that exceeded any NRC reportable limit.

L.

Inter Laboratory Comparison and Cross Check Proaram Areva NP Environmental Laboratory 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. Areva NP participates in multiple programs to ensure all environmental media sent to them are analyzed to the proper standards..

Areva NP recently published "AREVA NP Environmental Laboratory Annual Quality Assurance Report for Environmental Analysis (January-December 2009)"

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:

During the annual reporting period, there were 32 nuclides associated with 7 media types analyzed by means of the E-LAB internal process control, MAPEP, ERA/ELAP and by Eckert & Ziegler Analyses performed during this reporting period were selected.

The Analytics Cross Check Program provided 426 individual environmental analyses for bias and 426 for precision. 98.6% fell within the Laboratory's acceptance criteria for bias and 99.8% were within tolerance limits for precision.

Of the 478 internal process control analyses evaluated for bias, 99.8% met Laboratory acceptance criteria. Also, 95.5% of the 133 results for precision were found acceptable.

During this reporting period, statistically positive activity, (activity greater than three (3) times the standard deviation) was not reported for any of the 149 environmental analytical blanks analyzed.

The historical summary of the E-LAB process control program performance for the environmental monitoring function for 2009 is 99.1 % of the analysis fell within the E-LAB acceptance criteria for bias as compared to a historical percentage of 97.0. Similarly, 99.1% of the analysis evaluated for precision met the E-LAB acceptance criteria as compared as to 99.4% of analysis for the 33 year operating history.

A review was performed of all Condition Reports (CR) listed in the report.

Twenty-one CRs were closed during this period and Nineteen CRs were issued.

No adverse trend can be detected and the Laboratory is pursuing resolution of all open CRs. As of December 31, 2009, a total of eight CRs remain open, two of which are older than 6 months.

There were two internal audits during the annual reporting period. One External Audit was performed by Exelon Nuclear from August 10. 2009 through August 14, 2009.

The independent laboratory, Areva satisfies the requirements of the ODCM by their participation in the inter-laboratory and cross check programs documented in their annual report.

41

Appendix A Comanche Peak Nuclear Power Plant Land Use Census 2009 COPY 42

COMANCHE PEAK NUCLEAR POWER PLANT LAND USE CENSUS 2009 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 June 29, 30, and Julyl, 2009 and includes the following items:

1.

Evaluation of the 2009 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.

Environmental Monitoring Locations Map-20 Mile Radius*

9.

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.

43

Evaluation of the 2009 Land Use Census The results of the 2009 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 2009.

Since not all 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 2009 Land Use Census did not identify any locations that are "available for sampling" and that would yield a calculated dose 20% greater than at the current sampling locations.

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 2009 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 44

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.

i 45

Nearest Garden by Sector, Distance and D/Q Sector Distance (Miles)*

IFD/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.

46

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.

47

Population by Sector and Distance Sector

[

0-1 1-2 2-3 3-4 4-5 Total N

3 32 109 144 NNE 16 133 22 171 NE 55 93 277 425 ENE 123 14 137 E

120 24 30 174 ESE 3

62 104 147 316 SE 16 136 178 88 418 SSE 61 64 67 2122 2314 S

56 123 53 141 373 SSW 3

53 56 SW 83 5

48 51 187 WSW 298 5

8 311 W

11 5

27 27 70 WNW 3

38 64 105 NW 3

3 NNW 53 38 91 TOTAL 528 723 858 3186 5295 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.

48

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

R1 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

49

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.l 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

50

Environmental Sample Locations Table (cont.)

Sampling Point Location Sample Type*

SWi N-1.5 (Squaw Creek Reservoir Marina)

SW SW2 N-9.9 (Lake Granbury)

SW/DW1 SW3 N-19.3 (CONTROL-Brazos River)

SW SW4 NE-7.4 (Lake Granbury)

SW SW5 ESE-1.4 (Squaw Creek Reservoir)

SW 2 SW6 NNW-0. 1 (Squaw Creek Reservoir)

SW/DW3 GW1 W-1.2 (NOSF Potable Water)

GW GW2 WSW-0. 1 (Plant Potable Water)

GW3'4 GW3 SSE-4.6 (Glen Rose)

GW 4 GW4 N-9.8 (Granbury)

GW 1,4 GW5 N-1.45 (Squaw Creek Park)

GW 4 SS1 NNE-1.0 (Squaw Creek Reservoir)

SS SS2 N-9.9 (Lake Granbury)

SS SS3 NE-7.4 (Lake Granbury)

SS SS4 SE-5.3 (Squaw Creek)

SS F1 ENE-2.0 (Squaw Creek Reservoir)

F F2 NNE-8.0 (Lake Granbury)

F FP1 ENE-9.0 (Leonard Bros. Pecan Farm)

FP 51

Environmental Sample Locations Table (cont.)

Sampling Point Location Sample Type*

BLI N-1.45 BL BL2 SW-1.0 BL5 BL3 SW-13.5 (CONTROL)

BL5

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 groundwater from onsite wells (location GW2). Each of these possible sources of water are sampled.

4) Groundwater 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.

52

E*rvirnn*a*iml Sampf, Locctinss ap - 2 ikvUie Rad~us, 53

CP-201000646, Transmittal of Year 2009 Radiological Environmental Operating Report

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CP-201000646, Transmittal of Year 2009 Radiological Environmental Operating Report

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