CPSES-200201244, (CPSES) Transmittal of the Annual Radiological Environmental Operating Report for 2001

(CPSES) Transmittal of the Annual Radiological Environmental Operating Report for 2001

ML021220439
Person / Time
Site:	Comanche Peak
Issue date:	04/18/2002
From:	Walker R TXU Energy
To:	Document Control Desk, Office of Nuclear Reactor Regulation
References
CPSES-200201244, TXX-02077
Download: ML021220439 (59)

Text

LA TXU TXU Energy C.Lance Terry Comanche Peak Steam Senior Vice President &

Electric Station Principal Nuclear Officer P.O. Box 1002 (E01)

Glen Rose, TX 76043 Tel: 254 897 8920 Fax: 254 897 6652 lance.terry@txu.com CPSES-200201244 Log # TXX-02077 File # 10300 Ref. # 10CFR50 App. I RP-10 April 18, 2002 U. S. Nuclear Regulatory Commission Attn: Document Control Desk Washington, DC 20555

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)

DOCKET NOS. 50-445 AND 50-446 TRANSMITTAL OF THE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2001 Gentlemen:

Enclosed is one (1) copy of the Annual Radiological Environmental Operating Report for the CPSES Radiological Environmental Monitoring Program. This report is submitted pursuant to Section 5.6.2 of the CPSES Unit 1 and 2 Technical Specifications (Appendix A to Operating License Nos. NPF-87 and NPF-89). The report covers the period from January 1, 2001 through December 31, 2001 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, contact Connie Wilkerson at (254) 897-0144 or Scott Bradley at (254) 897-5495.

f TxU TXX-02077 Page 2 of 2 This communication contains no new licensing basis commitments regarding CPSES Units 1 and 2.

Sincerely, TXU Generation Company LP By: TXU Generation Company Management LLC Its General Partner C. L. Terry Senior Vice President and Principal Nuclear Officer By: ,

Roge Regulatory Affairs Manager CLW/clw Enclosure c- E. W. Merschoff, Region IV w/encl.

W. D. Johnson, Region IV (clo)

D. H. Jaffe, NRR (clo)

Resident Inspectors, CPSES w/encl.

Comanche Peak Steam Electric Station Annual Radiological Environmental Operating Report for 2001

TXU ENERGY COMANCHE PEAK STEAM ELECTRIC STATION ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 2001 JANUARY 1, 2001 through DECEMBER 31, 2001 TXU REVIEW and APPROVAL REVIEWED BY: 3-66-02 Edwin T. Floyd-"1-d 6 Date Radiation Protection Technician APPROVED BY:

Scott E. Bradley Date Health Physics Supervisor

Table of Contents Section Title I. Introduction A. Site and Station Description page 5 B. Objectives and Overview of the CPSES Radiological Environmental Nlonitoring Program page 5 II. Program Descriptions and Results A. Sample Locations page 7 Table 1 -- Comanche Peak Steam Electric Station Radiological Environmental Monitorina Program for 2001 Table 2-- Key to Environmental Sampling Locations B. Direct Radiation Progra in page I1 Methods, Procedures and Result Summaries Exceptions to the Program Table 3 -- 2001 Environmental Direct Radiation Results C. Airborne Prograni page 14 Methods, Procedures and Result Summaries Exceptions to the Program Table 4 -- 2001 Environmental Airborne Particulate Gross Beta Results Graph 1-- 2001 Environmental Air Sample Gross Beta Results Maximum and Minimum Table 5 -- 2001 Environmental Air Sample Iodine-131 Results Table 6 -- 2001 Environmental Air Particulate Composite Gamma Isotopic Results 2

D. Suri-face Wlater Programg page 20 Methods, Procedures and Result Summaries Exceptions to the Program Table 7 -- 2001 Environmental Surface Water Tritium and Gamma Isotopic Results Graph 2-- 2001 Environmental Surface Water Tritium Results E. Surface Drinking \,Vater Program page 26 Methods, Procedures and Result Summaries Exceptions to the Program Table 8 -- 2001 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results Graph 3-- 2001 Environmental Surface Drinkin2 Water Tritium Results Graph 4-- 2001 Environmental Surface Drinking Water Gross Beta Results F. Groundwater Program page 31 Methods, Procedures and Result Summaries Exceptions to the Program Table 9 -- 2001 Environmental Groundwater Tritium and Gamma Isotopic Results G. Sediment Program page 33 Methods, Procedures and Result Summaries Exceptions to the Program Table 10 -- 2001 Environmental Sediment Gamma Isotopic Results

i. Fish Program page 35 Methods, Procedures and Result Summaries Exceptions to the Program Table 11 -- 2001 Environmental Fish Gamma Isotopic Results 3

i. Food Products P1rogramp page 38 Methods, Procedures and Result Summaries Exceptions to the Program Table 12 - 2001 Environmental Food Products Gamma Isotopic Results J. Broadleaf Program page 40 Methods, Procedures and Result Summaries Exceptions to the Program Table 13 -- 2001 Environmental Broadleaf Iodine-131 and Gamma Isotopic Results K. Conclusions page 42 L. Interlaboratory Comparison and Cross Check Program page 42 Appendix A Comanche Peak Steam Electric Station Land Use Census 2001 page 44 4

1. Introduction Results of the Radiological Environmental Monitoring Program for the Comanche Peak Steam Electric Station (CPSES) for the year 2001 are contained within this report. This report covers the period from January 1, 2001 through December 31, 2001 and summarizes the results of measurements and analysis of data obtained from environmental samples collected during this same timeframe.

A. Site and Station D)escription CPSES consists of two pressurized water reactor units, each designed to operate at a power level of about 1150 megawatts (electrical). The Station is located on Squaw Creek reservoir in Somervell and Hood counties, about forty miles southwest of Fort Worth, Texas. Unit 1 received a low power operating license February 8, 1990 and achieved initial criticality on April 3, 1990. A full power license for Unit 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. Objectives and Overviews of the CPSES Radiological Environmental

" 0on itoring 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 CPSES Technical Specification "Comanche Peak Steam Electric Station 5

Units 1 and 2 Technical Specifications" and the "CPSES Offsite Dose Calculation Manual" (ODCM).

In 2001, the Radiological Environmental Monitoring Program included the following:

"* The measurement of ambient gamma radiation by thermoluminescent dosimetry;

"* The determination of airborne gross beta, gamma emitters, and Iodine- 131;

"* The determination of tritium and gamma emitters in surface water;

"* The determination of gross beta, tritium, Iodine- 131, and gamma emitters in drinking water;

"* The determination of tritium and gamma emitters in ground water;

"* The determination of gamma emitters in sediment and fish;

"* The determination of gamma emitters in food products and;

"* The determination of gamma emitters and Iodine-131 in broadleaf vegetation.

The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most, only a small percentage increase above normal background radioactivity. Background levels at any one location are not constant but vary with time as they are influenced by external events such as cosmic ray bombardment, weapons test fallout, and seasonal variations. These levels also can vary spatially within relatively short distances reflecting variations in geological composition. To differentiate between background radiation levels and increases resulting from operation of CPSES, 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 CPSES 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; 6

"* Measure background levels and the variations along potentially important pathways and;

"* Provide baseline data for statistical comparisons with future operational analytical results.

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 and;

"* Identify changes in the areas at and beyond the site boundary that may impact the principal pathways of exposure.

This report documents the twelfth year of operational measurements and is submitted in accordance with the requirements of the CPSES Offsite Dose Calculation Manual, Part I, Administrative Control 6.9.1.3.

II. Program Descriptions and Results A. Sample Locations Within a radius of twenty miles of the CPSES site there are seventy-two (72) sample locations included in the monitoring program for the year 2001. 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 Steam Electric Station Land Use Census 2001" is provided in Appendix A to this report.

Table 1 - Comanche Peak Steam Electric Station Radiological Environmental Monitoring Program for 2001 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 7

for each sample location, the sample frequency, the type of analysis required and the analytical frequency required.

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.

The only change made to the sample locations for the year 2001 was the deletion of the control milk location at SW-14.5. This commercial dairy sold all of their milking cattle at the end of the year 2000 and did not resume milking activities at any time during the year 2001. Currently there are no milk sample locations within ten miles of the CPSES site and there are no milk sample locations within twenty miles that will participate in the environmental program. CPSES already samples extra broadleaf locations as required due to no milk locations within the ten-mile radius therefore, no other 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 Steam Electric Station Radiological Environmental Monitoring Program for 2001 Media Number of Identification by Sampling Frequency(a) Analysis Analytical F:requency Sector and Distance (miles) (a)

Locations Gamma Exposure 43 N-1.45; N-4.4; N-6.5; N-9.4; NNE-1.1; NNE-5.65 Q, A Thermoluminescent Q, A NE-i.7; NE-4.8; ENE-2.5; ENE-5.0; E-0.5; E-1.9 Dosimetry E-3.5; E-4.2; ESE -1.4; ESE-4.7; SE-1.3; SE-3.85 SE-4.6; SSE-1.3; SSE-4.4; SSE-4.5; S-1.5; S-4.2 SSW-1.1; SSW-4.4; SW-0.9; SW-4.8; 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 Air Particulate 8 N-9.4; E-3.5; SSE-4.5; SW-12.3; NW-1.0; N-1.45 W Gross Beta W SW/WSW-0.95; S/SSW-1.2 Gamma Isotopic Filter QC Air Iodine Gamma Isotopic Charcoal W Surface Water 4 N-19.3; ESE-1.4; N-1.5; NE-7.4 M (b) Gamma Isotopic M Tritium QC Surface Water 2 NNW-0.1; N-9.9 M (c) Gross Beta M Drinking Gamma Isotopic M Iodine - 131 M Tritium QC Q

Ground Water 5 SSE-4.6;W-1.2;WSW-0.1; N-9.8; N-1.45 Q Gamma Isotopic Tritium Q Sediment 4 N-9.9; NNE-1.0; NE-7.4; SE-5.3 SA Gamma Isotopic SA Fish 2 NNE-8.0; ENE-2.0 SA Gamma Isotopic SA Food Products 1 ENE-9.0 MH Gamma Isotopic MH Iodine - 131 MH Broadleaf Vegetation 3 N-1.45; SW-1.0; SW-13.5 M Gamma Isotopic M (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 Lake 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.

Table 2 Key To Environmental Sampling Locations SAMPLING LOCATION SAMPLE SAMPLING LOCATION SAMPLE POINT (SECTOR-MILE) TYPE* POINT (SECTOR-MILE) TYPE*

Al N-1.45 A R28 SW-4.8 R A2 N-9.4 A R29 SW-12.3 R A3 E-3.5 A R30 WSW-l.0 R A4 SSE-4.5 A R31 WSW-5.35 R A5 S/SSW-1.2 A R32 WSW-7.0 R A6 SW-12.3 A R33 W-l.0 R A7 SW/WSW-0.95 A R34 W-2.0 R A8 NW-l.0 A R35 W-5.5 R R36 WNW-I.0 R R37 WNW-5.0 R R38 WNW-6.7 R R39 NW-1.0 R R40 NW-5.7 R R1 N-1.45 R41 NW-9.9 R R2 N-4.4 R42 NNW-1.35 R R3 N-6.5 R43 NNW-4.6 R R4 N-9.4 SW1 N-1.5 SW R5 NNE-I.1 SW2 N-9.9 SW/DW R6 NNE-5.65 SW3 N-19.9 SW R7 NE-1.7 SW4 NE-7.4 SW R8 NE-4.8 SW5 ESE-1.4 SW R9 ENE-2.5 SW6 NNW-0.1 SW/DW R10 ENE-5.0 GWl W-1.2 GW/DW Ri1 E-0.5 GW2 WSW-0.1 GW/DW R12 E-1.9 GW3 SSE-4.6 GW/DW R13 E-3.5 GW4 N-9.8 GW/DW R14 E-4.2 GW5 N-1.45 GW/DW R15 ESE-1.4 SS1 NNE-1.0 SS R16 ESE-4.7 SS2 N-9.9 SS R17 SE-1.3 SS3 NE-7.4 Ss R18 SE-3.85 SS4 SE-5.3 SS R19 SE-4.6 F1 ENE-2.0 F R20 SSE-1.3 F2 NNE-8.0 F R21 SSE-4.4 FP1 ENE-9.0 FP R22 SSE-4.5 BL1 N-1.45 BL R23 S-1.5 BL2 SW-1.0 BL R24 S-4.2 BL3 SW-13.5 BL R25 SSW-1.1 R26 SSW-4.4 R27 SW-0.9 Sample A - AIR SAMPLE GW - GROUNDWATER F - FISH Type* R - DIRECT RADIATION S S - SHORELINE SEDIMENT FP - FOOD PRODUCT SW - SURFACE WATER BL - BROADLEAF VEGETATION DW - DRINKING WATER

B. Direct Radiationi Thermoluminescent dosimeters (TLDs) 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. TLDs were placed in each of these sectors. The thermoluminescent 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 TLDs were located at points of special interest, including two control locations. For routine direct radiation measurements, two sets of the Panasonic CaSO4:Dy TLDs were used at each of the 43 monitoring locations. One set of TLDs was exchanged on a quarterly basis and a second set of TLDs was exchanged on a yearly basis. Additional sets of in-transit TLD's were used as control TLDs for the quarterly and annual TLDs.

The thermoluminescent dosimeters were processed on-site by CPSES 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 CPSES used the Panasonic TLD System to supply all the required direct radiation (ambient) monitoring.

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 TLD 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.

Table 3 - 2001 Environmental Direct Radiation Results contains the measured dose (mr) for each quarterly TLD 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 TLDs 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 11

each annual TLD 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 TLDs is reported along with the average dose rate (mr/day) for the entire set of annual TLDs.

For the year 2001, the statistical average dose rate of all the quarterly TLD's was 0.0579 mr/day. The quarterly measured dose rates ranged from a minimum of 0.0077 mr/day to a maximum of 0.112 mr/day. The statistical average dose rate of all the annual TLDs was 0.0622 mr/day.

The annual measured dose rates ranged from a minimum of 0.0056 mr/day to a maximum of 0.1147 mr/day. There was good agreement between the measured dose of the quarterly TLDs and the measured dose of the annual TLDs. The quarterly measured dose averaged 20.91 mr for all the monitoring stations while the annual measured dose averaged 22.71 mr for all the monitoring stations.

Comparing the pre-operational data and operational data collected through the year 2001 did not produce any anomalies. The direct radiation dose data for 2001 was consistently lower than previous years of data during both the pre-operational program and the previous years of the operational program. The implementation of the Panasonic TLD system and the algorithms used to process the data from these new type TLDs accounts for the lower values as well as different type holders for the TLDs.

During the year 2001, there were exceptions to the Direct Radiation Program. All quarterly and annual TLDs were placed into the field at their proper locations and on the appropriate frequency. Collection of all TLDs occurred as specified and were delivered to dosimetry personnel for processing. As the processing of the TLDs was performed it was determined that there were indications of moisture damage to some of the TLD's crystals in some of the processed TLDs. Since the TLDs contain multiple crystals, official results of ambient direct radiation were obtained from all the quarterly TLDs. The annual TLDs at the monitoring stations NNE-1.1, SW-0.9 and WSW-1.0 were processed but due to moisture damage that accumulated over the year, dose could not be determined. The ODCM Table 3.12-1 Radiological Environmental Monitoring Program does not require the annual TLDs. All quarterly dose values for each of these monitoring locations were obtained as required.

No abnormal quarterly results were obtained by either CPSES or by the State of Texas, Bureau of Radiation Control, which has co-located TLDs at these specific locations. Different type TLD holders and different methods of protecting the crystals from moisture will be used during 2002 to try to eliminate the moisture problems.

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Table 3 -- 2001 Environmental Direct Radiation Results (Units of mr dose and mr/day dose rate) 1ST QTR Average 2ND QTR Average 3RD QTR Average 4TH QTR Average QTR Annual Average Location Total mr/day Total mr/day Total mr/day Total mr/day Total Total mr/day N-1.45 4.50 0.0511 4.55 0.0495 3.00 0.0333 4.15 0.0456 16.20 19.55 0.0536 N-4.4 7.05 0.0801 8.20 0.0891 5.30 0.0589 7.85 0.0863 28.40 32.75 0.0897 N-6.5 4.80 0.0545 5.05 0.0549 3.10 0.0344 6.35 0.0698 19.30 22.65 0.0621 N-9.4 5.85 0.0665 5.30 0.0576 4.25 0.0472 6.15 0.0676 21.55 22.60 0.0619 NNE-1.1 5.10 0.0580 3.90 0.0424 2.25 0.0250 4.30 0.0473 15.55 NNE-5.65 5.40 0.0614 6.70 0.0728 6.65 0.0739 6.70 0.0736 25.45 22.75 0.0623 NE-1.7 3.75 0.0426 3.60 0.0391 2.65 0.0294 4.65 0.0511 14.65 17.40 0.0477 NE-4.8 4.70 0.0534 5.90 0.0641 5.80 0.0644 6.35 0.0698 22.75 27.15 0.0744 ENE-2.5 7.15 0.0813 6.80 0.0739 6.20 0.0689 7.85 0.0863 28.00 35.90 0.0984 ENE-5.0 9.20 0.1045 10.30 0.1120 9.20 0.1022 9.65 0.1060 38.35 41.85 0.1147 E-0.5 6.20 0.0705 6.75 0.0734 4.00 0.0444 8.05 0.0885 25.00 29.80 0.0816 E-1.9 2.90 0.0330 2.55 0.0277 1.80 0.0200 3.25 0.0357 10.50 13.05 0.0358 E-3.5 8.60 0.0977 9.55 0.1038 8.25 0.0917 9.25 0.1016 35.65 39.90 0.1093 E-4.2 6.35 0.0722 8.45 0.0918 6.90 0.0767 7.70 0.0846 29.40 33.75 0.0925 ESE-11.4 4.50 0.0511 5.60 0.0609 4.05 0.0450 5.05 0.0555 19.20 21.30 0.0584 ESE-4.7 6.20 0.0705 7.45 0.0810 5.05 0.0561 6.85 0.0753 25.55 32.05 0.0878 SE-1.3 7.15 0.0813 7.20 0.0783 6.25 0.0694 6.70 0.0736 27.30 28.25 0.0774 SE-3.85 4.25 0.0483 4.20 0.0457 3.05 0.0339 4.50 0.0495 16.00 17.85 0.0489 SE-4.6 4.70 0.0534 5.30 0.0576 5.00 0.0556 5.60 0.0615 20.60 20.25 0.0555 SSE-1.3 4.20 0.0477 4.10 0.0446 3.75 0.0417 5.30 0.0582 17.35 21.70 0.0595 SSE-4.4 5.80 0.0659 6.40 0.0696 3.80 0.0422 5.85 0.0643 21.85 21.75 0.0596 SSE-4.5 4.80 0.0545 5.20 0.0565 3.35 0.0372 5.20 0.0571 18.55 20.15 0.0552 S-1.5 4.20 0.0477 4.75 0.0516 2.70 0.0300 4.50 0.0495 16.15 17.95 0.0492 S-4.2 4.70 0.0534 5.25 0.0571 3.40 0.0378 5.15 0.0566 18.50 18.10 0.0496 SSW-I.1 4.20 0.0477 5.95 0.0647 3.25 0.0361 4.70 0.0516 18.10 17.20 0.0471 SSW-4.8 6.05 0.0688 6.55 0.0712 4.15 0.0461 6.20 0.0681 22.95 23.50 0.0644 SW-0.9 4.90 0.0557 4.95 0.0538 6.10 0.0678 5.70 0.0626 21.65 SW-4.8 3.65 0.0415 5.60 0.0609 3.20 0.0356 5.25 0.0577 17.70 18.05 0.0495 SW-1 2.3 Control 5.55 0.0631 7.00 0.0761 3.65 0.0406 5.50 0.0604 21.70 21.50 0.0589 WSW-1.0 5.70 0.0648 5.70 0.0620 4.05 0.0450 7.55 0.0830 23.00 WSW-5.35 4.95 0.0563 4.40 0.0478 3.05 0.0339 4.95 0.0544 17.35 19.75 0.0541 WSW-7.0 Control 7.50 0.0852 6.40 0.0696 4.65 0.0517 6.65 0.0731 25.20 22.20 0.0608 W-1.0 4.05 0.0460 3.15 0.0342 1.70 0.0189 4.15 0.0456 13.05 10.15 0.0278 W-2.0 2.85 0.0324 2.05 0.0223 2.15 0.0239 3.10 0.0341 10.15 21.15 0.0579 W-5.5 5.05 0.0574 7.50 0.0815 3.65 0.0406 4.60 0.0505 20.80 18.45 0.0505 WNW-1.0 6.00 0.0682 7.55 0.0821 6.30 0.0700 6.55 0.0720 26.40 24.95 0.0684 WNW-5.0 7.40 0.0841 6.60 0.0717 4.85 0.0539 5.55 0.0610 24.40 21.35 0.0585 WNW-6.7 5.20 0.0591 6.00 0.0652 4.65 0.0517 5.35 0.0588 21.20 22.00 0.0603 NW-1.0 4.60 0.0523 4.70 0.0511 3.75 0.0417 4.55 0.0500 17.60 17.45 0.0478 NW-5.7 5.60 0.0636 5.70 0.0620 4.15 0.0461 5.85 0.0643 21.30 23.75 0.0651 NW-9.9 4.25 0.0483 3.50 0.0380 2.15 0.0239 4.20 0.0462 14.10 17.15 0.0470 NNW-1.35 1.05 0.0119 0.95 0.0103 0.95 0.0106 0.70 0.0077 3.65 2.05 0.0056 NNW-4.6 6.85 0.0778 7.25 0.0788 5.85 0.0650 7.05 0.0775 27.00 29.45 0.0807 AVERAGES 5.29 0.0601 5.69 0.0618 4.23 0.0470 5.70 0.0626 20.91 22.71 0.0622

C. Airborne Program Air particulate and air iodine samples were collected each week from the eight monitoring locations described in Table 1 - Comanche Peak Steam Electric Station Radiological Monitoring Program for 2001. Each air particulate sample was collected by drawing air through a 47millimeter 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 2001, a total of 415 air particulate filters were collected and analyzed for gross beta activity. The reported gross beta activity ranged from a minimum value of 7.10e-3 pCi/m3 to a maximum value of 7.62e-2 pCi/m3. Table 4 - 2001 Environmental Airborne Particulate Gross Beta Results contains the reported values of all samples. There were no anomalies noted in the data reported for 2001 when compared to pre operational and previous operational data. Graph 1 - 2001 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 415 charcoal cartridges were analyzed for airborne Iodine- 131.

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

Table 5 - Environmental Air Sample Iodine- 131 Results contains the reported values of each Iodine-131 analysis, all of which are less than the required lower limit of detection (LLD).

All air particulate filters were collected and composited quarterly and then analyzed by gamma spectrometry. The gamma isotopic data is presented in Table 6 - 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 2001, there were exceptions to the Airborne Program.

The air sample pump located at monitoring location NW-1.0 was found broken on 06 November 2001. The pump was immediately replaced with a spare sample pump and returned to service. The air sample was not of sufficient volume to be used as a valid sample and therefore no values were obtained at this location for the week of 30 October 2001 through 06 November 2001. The failure of the equipment was beyond the control of CPSES. The State of Texas has a co-located air 14

monitoring station (NW-1.0) and results from the State of Texas air sample analysis did not indicate any anomalies.

The sample analysis of the second quarter air filter composites were deficient in reporting of a LLD value for the Barium-140 radionuclide. Barium-140 is not one of the required isotopes for LLD determination but the results of the analysis performed on these composites failed to report the LLDs due to the decay correction factor being less than 0.01. The gamma spectrometry software used did not report a value due to this low decay correction value. The laboratory did not discover the deficient condition and by the time CPSES could review the data, a recount could not provide the expected level of analysis.

Although Barium-140 is not on the required radionuclide listing for airborne analysis, the independent laboratory has committed to enhancing the software to include the required LLD values. The software will set a warning flag to indicate a failure to achieve the required LLD so that an immediate recount can be performed at the time of failure. The State of Texas has two co-located air monitoring stations at NW-1.0 and SW-12.3; neither station indicated any anomalies.

15

Table 4 -- 2001 Environmental Airborne Particulate Gross Beta Results (Units of pCiIm3)

Location N-1.4 N-9.4 E-3.5 SSE-4.5 S/SSW -1.2 SW-1 2.3 sw/wsw -0.95 NW-1.0 Date Control Control 112101 3.22E-02 4.43E-02 2.98E-02 2.55E-02 5.11E-02 3.81E-02 4.20E-02 3.16E-02 119/01 3.22E-02 4.39E-02 3.93E-02 2.80E-02 5.63E-02 4.74E-02 5.33E-02 3.73E-02 1116101 3.20E-02 3.01 E-02 3.39E-02 2.29E-02 4.98E-02 3.99E-02 4.24E-02 3.04E-02 1/23/01 3.68E-02 4.14E-02 3.27E-02 2.62E-02 5.64E-02 4.10E-02 4.88E-02 3.79E-02 1/30/01 4.84E-02 5.66E-02 4.89E-02 3.88E-02 7.16E-02 5.28E-02 6.36E-02 4.47E-02 2/6/01 2.84E-02 2.80E-02 2.72E-02 2.06E-02 4.77E-02 2.94E-02 4.27E-02 2.55E-02 2/13/01 2.27E-02 2.66E-02 2.88E-02 2.15E-02 4.12E-02 3.83E-02 3.19E-02 2.68E-02 2/20/01 4.76E-02 4.55E-02 4.OOE-02 4.30E-02 5.83E-02 5.66E-02 5.23E-02 5.02E-02 2/27/01 4.19E-02 3.82E-02 3.24E-02 3.64E-02 4.77E-02 4.61 E-02 4.10E-02 3.66E-02 3/6/01 4.05E-02 3.94E-02 3.31 E-02 3.09E-02 5.43E-02 4.38E-02 4.57E-02 3.70E-02 3/13101 4.10E-02 3.94E-02 3.97E-02 3.77E-02 5.92E-02 4.59E-02 4.68E-02 4.11 E-02 3120101 1.87E-02 2.75E-02 1 .96E-02 2.05E-02 3.09E-02 2.68E-02 3.05E-02 1.91 E-02 3/27/01 3.82E-02 3.45E-02 3.OOE-02 3.16E-02 4.86E-02 4.25E-02 4.04E-02 3.19E-02 4/3/01 2.49E-02 2.61 E-02 2.14E-02 2.30E-02 3.32E-02 3.16E-02 3.25E-02 2.42E-02 4/10/01 3.53E-02 3.60E-02 3.20E-02 2.99E-02 5.61 E-02 4.30E-02 3.56E-02 3.64E-02 4/17/01 2.73E-02 2.51E-02 2.1OE-02 2.55E-02 4.17E-02 3.19E-02 3.70E-02 2.96E-02 4/24/01 3.56E-02 2.92E-02 2.73E-02 3.01E-02 4.95E-02 3.60E-02 3.77E-02 2.78E-02 5/1/01 3.68E-02 3.42E-02 2.80E-02 3.OOE-02 4.75E-02 3.68E-02 3.82E-02 3.15E-02 5/8/01 1.86E-02 1.73E-02 1.81 E-02 1.94E-02 2.49E-02 2.33E-02 2.33E-02 2.01 E-02 5/15/01 3.06E-02 3.34E-02 2.88E-02 3.06E-02 3.93E-02 3.43E-02 3.45E-02 3.12E-02 5/22/01 2.89E-02 2.79E-02 2.78E-02 2.29E-02 3.50E-02 4.06E-02 3.43E-02 2.77E-02 5/29/01 2.22E-02 2.22E-02 1.78E-02 1.64E-02 2.97E-02 2.57E-02 2.87E-02 1.98E-02 6/5/01 1.78E-02 2.04E-02 1.99E-02 1.55E-02 2.75E-02 2.43E-02 2.13E-02 2.02E-02 6/12/01 1.93E-02 2.08E-02 1.53E-02 1.35E-02 2.48E-02 1.87E-02 1.78E-02 1.83E-02 6/19/01 2.97E-02 2.75E-02 2.72E-02 2.43E-02 3.69E-02 2.82E-02 3.05E-02 2.55E-02 6/26/01 3.39E-02 2.83E-02 2.93E-02 2.51 E-02 4.27E-02 3.65E-02 3.43E-02 3.1OE-02 7/3/01 3.13E-02 2.92E-02 2.95E-02 2.70E-02 4.40E-02 3.28E-02 3.30E-02 3.05E-02 7/10/01 2.31E-02 1.95E-02 2.18E-02 1.72E-02 3.06E-02 2.33E-02 2.45E-02 2.27E-02 7/17/01 3.56E-02 3.02E-02 2.49E-02 2.51 E-02 4.18E-02 4.12E-02 3.16E-02 2.99E-02 7/24/01 2.75E-02 3.79E-02 2.61 E-02 2.38E-02 2.52E-02 2.59E-02 2.32E-02 2.62E-02 7/31/01 1.87E-02 2.85E-02 2.OOE-02 1.85E-02 1.95E-02 2.28E-02 1.82E-02 2.01 E-02 8/7/01 2.71 E-02 3.85E-02 2.86E-02 2.46E-02 2.45E-02 2.66E-02 2.03E-02 2.76E-02 8/14/01 2.56E-02 3.31E-02 2.37E-02 1.99E-02 2.24E-02 2.64E-02 2.56E-02 2.32E-02 8/21/01 3.49E-02 3.43E-02 2.75E-02 2.43E-02 2.65E-02 3.06E-02 3.20E-02 3.01E-02 8/28101 1.86E-02 2.67E-02 2.05E-02 1.59E-02 1.49E-02 2.11 E-02 1 .74E-02 1.97E-02 9/4/01 8.40E-03 1.17E-02 1.OOE-02 8.60E-03 7.10E-03 9.50E-03 9.OOE-03 7.70E-03 9/11/01 2.45E-02 2.71E-02 2.49E-02 1.75E-02 1.72E-02 1.90E-02 1.87E-02 1.69E-02 9/18/01 4.61E-02 5.08E-02 4.05E-02 3.58E-02 3.25E-02 3.54E-02 4.25E-02 4.37E-02 9/25/01 2.11 E-02 2.38E-02 1.93E-02 1.84E-02 2.20E-02 1.86E-02 2.17E-02 2.63E-02 10/2/01 3.68E-02 3.74E-02 3.42E-02 2.87E-02 3.13E-02 2.84E-02 2.98E-02 4.33E-02 10/9/01 3.60E-02 4.68E-02 3.42E-02 3.11 E-02 3.47E-02 2.90E-02 3.09E-02 4.08E-02 10116/01 2.51 E-02 3.07E-02 2.22E-02 1.89E-02 2.56E-02 1.95E-02 2.40E-02 2.97E-02 10/23/01 3.24E-02 3.89E-02 2.75E-02 2.71 E-02 2.67E-02 2.14E-02 2.67E-02 3.75E-02 10/30/01 3.14E-02 3.75E-02 2.66E-02 2.76E-02 3.06E-02 2.47E-02 2.86E-02 3.67E-02 11/6/01 2.53E-02 2.93E-02 2.50E-02 2.07E-02 2.35E-02 1.75E-02 2.05E-02 11/13/01 6.55E-02 7.62E-02 6.05E-02 5.67E-02 6.24E-02 5.14E-02 5.92E-02 5.84E-02 11/20/01 4.23E-02 5.49E-02 3.78E-02 4.03E-02 4.04E-02 3.20E-02 4.15E-02 4.01 E-02 11/27/01 2.82E-02 3.36E-02 2.63E-02 2.48E-02 2.22E-02 1.73E-02 2.41 E-02 2.16E-02 12/4/01 2.99E-02 2.96E-02 1.73E-02 2.19E-02 2.36E-02 1.74E-02 2.05E-02 2.49E-02 12/11101 2.92E-02 3.47E-02 2.71 E-02 2.52E-02 2.39E-02 1.86E-02 2.30E-02 2.37E-02 12/18/01 3.17E-02 3.92E-02 2.67E-02 2.41 E-02 3.24E-02 2.51 E-02 2.21 E-02 3.00E-02 12/24/01 2.95E-02 3.62E-02 3.18E-02 2.91E-02 2.86E-02 2.19E-02 2.66E-02 2.96E-02 Required LLD's 1.OOE-02

Graph 1 -- 2001 Environmental Air Sample Gross Beta Results - Maximum and Minimum 9.OOE-02 8.OOE-02 E 7.OOE-02 6.OOE-02 5.OOE-02 0 4.OOE-02 NE 3.OOE-02

.j 2.0OE-02 1.OOE-02 O.OOE+O0 C) Co 0 0 0 0 0 0 0 CNJ (NLO)~ 1 CD NII- M0 M CNJ Weekly Data Points

Table 5 -- 2001 Environmental Air Sample Iodine-131 Results (Units of pCi/m3)

N-1.45 N-9.4 E-3.5 SSE-4.5 S/SSW-1.2 SW-12.3 swIwsw-o.9s NW-I.0 Date Control Control 112/01 <4.8e-2 <4.7e-2 <5.2e-2 <6.0e-2 <5.5e-2 <5.5e-2 <6.2e-2 <3.8e-2 1/9/01 <6.le-2 <3.7e-2 <4.6e-2 <4.5e-2 <6.1e-2 <7.0e-2 <6.6e-2 <6.6e-2 1/16/01 <4.3e-2 <4.2e-2 <3.7e-2 <5.5e-2 <5.4e-2 <4.6e-2 <4.9e-2 <5.2e-2 1/23/01 <3.8e-2 <3.9e-2 <3.7e-2 <4.1e-2 <4.0e-2 <4.2e-2 <4.0e-2 <4.2e-2 1/31/01 <5.4e-2 <6.1e-2 <3.7e-2 <3.5e-2 <4.8e-2 <4.6e-2 <4.8e-2 <4.9e-2 2/6/01 <4.2e-2 <3.6e-2 <4.5e-2 <4.0e-2 <4.7e-2 <4.0e-2 <4.4e-2 <4.1 e-2 2/13/01 <3.9e-2 <3.2e-2 <3.3e-2 <3.9e-2 <3.4e-2 <3.4e-2 <4.5e-2 <4.le-2 2/20/01 <4.4e-2 <5.7e-2 <4.7e-2 <4.5e-2 <5.2e-2 <4.6e-2 <5.8e-2 <6.1e-2 2/27/01 <5.1e-2 <4.5e-2 <3.7e-2 <4.6e-2 <3.9e-2 <6.9e-2 <5.9e-2 <5.1e-2 3/6/01 <4.1e-2 <4.0e-2 <3.9e-2 <3.9e-2 <3.7e-2 <3.5e-2 <4.2e-2 <4.te-2 3/13/01 <4.8e-2 <4.0e-2 <3.6e-2 <5.7e-2 <4.5e-2 <4.6e-2 <5.4e-2 <5.3e-2 3/20/01 <4.8e-2 <4.9e-2 <4.7e-2 <5.0e-2 <5.0e-2 <5.1e-2 <5.2e-2 <4.8e-2 3/27/01 <5.4e-2 <4.0e-2 <5.2e-2 <4.9e-2 <4.2e-2 <4.4e-2 <4.2e-2 <4.2e-2 4/3/01 <3.6e-2 <3.6e-2 <3.8e-2 <4.5e-2 <3.9e-2 <4.3e-2 <4.0e-2 <4.5e-2 4/10/01 <4.2e-2 <4.3e-2 <3.9e-2 <3.7e-2 <4.le-2 <4.2e-2 <4.5e-2 <4.6e-2 4/17/01 <3.8e-2 <3.9e-2 <4.1 e-2 <4.0e-2 <5.le-2 <4.le-2 <4.5e-2 <4.4e-2 4/24/01 <4.8e-2 <4.1e-2 <3.7e-2 <4.le-2 <4.3e-2 <3.8e-2 <4.4e-2 <3.8e-2 5/1/01 <4.4e-2 <4.4e-2 <5.9e-2 <4.6e-2 <5.4e-2 <5.6e-2 <4.8e-2 <4.8e-2 5/8/01 <5.0e-2 <4.6e-2 <6.0e-2 <5.7e-2 <5.2e-2 <4.7e-2 <5.2e-2 <5.1e-2 5/15/01 <5.7e-2 <5.7e-2 <5.6e-2 <5.9e-2 <4.5e-2 <6.1e-2 <5.9e-2 <5.8e-2 5/22/01 <4.1e-2 <3.8e-2 <3.8e-2 <4.0e-2 <3.7e-2 <4.1e-2 <4.5e-2 <3.8e-2 5/29/01 <5.7e-2 <5.7e-2 <6.4e-2 <6.5e-2 <5.6e-2 <5.7e-2 <6.4e-2 <6.5e-2 6/5/01 <5.2e-2 <5.le-2 <4.8e-2 <4.8e-2 <5.4e-2 <5.5e-2 <5.1 e-2 <5.0e-2 6/12/01 <3.9e-2 <4.4e-2 <4.6e-2 <4.2e-2 <4.1e-2 <4.1e-2 <5.2e-2 <5.2e-2 6/19/01 <4.6e-2 <4.8e-2 <4.1e-2 <4.2e-2 <4.9e-2 <4.1e-2 <4.9e-2 <4.6e-2 6/26/01 <4.6e-2 <4.1e-2 <4.9e-2 <4.4e-2 <4.6e-2 <4.8e-2 <4.7e-2 <5.1e-2 7/3/01 <5.0e-2 <4.9e-2 <5.4e-2 <5.3e-2 <5.3e-2 <5.0e-2 <5.3e-2 <5.1 e-2 7/10/01 <5.4e-2 <5.4e-2 <4.9e-2 <5.1 e-2 <4.7e-2 <4.9e-2 <5.1 e-2 <5.3e-2 7/17/01 <5.3e-2 <4.8e-2 <5.5e-2 <5.6e-2 <4.9e-2 <5.0e-2 <5.3e-2 <5.6e-2 7/24/01 <4.4e-2 <4.5e-2 <3.8e-2 <4.3e-2 <4.5e-2 <4.4e-2 <4.7e-2 <4.6e-2 7/31/01 <6.4e-2 <5.8e-2 <6.7e-2 <6.4e-2 <4.7e-2 <4.3e-2 <4.3e-2 <4.3e-2 8/7/01 <6.0e-2 <5.3e-2 <6.0e-2 <5.7e-2 <5.9e-2 <5.3e-2 <5.1e-2 <5.9e-2 8/14/01 <5.1e-2 <6.1e-2 <4.4e-2 <4.5e-2 <5.5e-2 <5.5e-2 <4.9e-2 <5.5e-2 8/21/01 <5.le-2 <4.4e-2 <5.0e-2 <4.5e-2 <4.7e-2 <6.2e-2 <5.4e-2 <4.7e-2 8/28/01 <4.6e-2 <5.3e-2 <4.6e-2 <4.4e-2 <3.8e-2 <3.6e-2 <5.2e-2 <5.6e-2 9/4/01 <3.0e-2 <3.le-2 <6.1e-2 <5.3e-2 <4.7e-3 <5.2e-2 <5.0e-2 <4.2e-2 9/11/01 <5.8e-2 <6.5e-2 <5.2e-2 <6.1e-2 <5.1e-2 <6.9e-2 <6.2e-2 <6.1e-2 9/18/01 <4.3e-2 <4.7e-2 <4.4e-2 <4.7e-2 <4.8e-2 <4.7e-2 <5.2e-2 <4.9e-2 9/25/01 <5.1e-2 <4.8e-2 <5.0e-2 <4.5e-2 <5.0e-2 <4.9e-2 <5.0e-2 <5.0e-2 10/2/01 <6.5e-2 <6.0e-2 <4.9e-2 <5.7e-2 <6.3e-2 <5.le-2 <5.7e-2 <5.7e-2 10/9/01 <5.4e-2 <4.5e-2 <5.3e-2 <4.9e-2 <5.1 e-2 <4.9e-2 <3.2e-2 <4.7e-2 10/16/01 <5.8e-2 <6.3e-2 <5.8e-2 <6.3e-2 <6.1e-2 <6.3e-2 <6.2e-2 <6.7e-2 10/23/01 <5.8e-2 <5.7e-2 <5.6e-2 <5.6e-2 <6.1e-2 <5.8e-2 <5.7e-2 <6.4e-2 10/30/01 <5.8e-2 <5.3e-2 <6.3e-2 <5.8e-2 <5.3e-2 <5.4e-2 <5.3e-2 <6.2e-2 11/6/01 <4.7e-2 <4.9e-2 <4.7e-2 <5.2e-2 <5.1 e-2 <5.8e-2 <5.6e-2 11/13/01 <5.9e-2 <5.0e-2 <5.le-2 <4.9e-2 <4.8e-2 <4.5e-2 <5.2e-2 <5.2e-2 11/20/01 <3.8e-2 <3.9e-2 <5.8e-2 <5.8e-2 <5.5e-2 <5.9e-2 <5.6e-2 <6.4e-2 11/27/01 <5.0e-2 <5.4e-2 <5.6e-2 <5.2e-2 <5.5e-2 <5.2e-2 <5.3e-2 <5.0e-2 12/4/01 <6.5e-2 <5.2e-2 <5.8e-2 <6.6e-2 <5.9e-2 <4.6e-2 <5.0e-2 <6.9e-2 12/11/01 <4.7e-2 <4.8e-2 <4.4e-2 <4.9e-2 <4.7e-2 <4.8e-2 <5.1 e-2 <5.0e-2 12/18/01 <4.2e-2 <4.4e-2 <4.6e-2 <4.7e-2 <4.2e-2 <4.6e-2 <4.0e-2 <4.6e-2 12/24/01 <6.0e-2 <5.1e-2 <5.6e-2 <5.0e-2 <5.5e-2 <5.6e-2 <2.7e-2 <2.7e-2 Required LLD 7.00E-02

Table 6 -- 2001 Environmental Air Particulate Composite Gamma Isotopic Results (Units of pCi/m3)

Location N-1.4 N-9.4 E-3.5 SSE-4.5 SSW-1.2 SW-12.3 ;w/wsw-o.9 NW-1.0 Nuclides Control Control Be-7 1.10E-01 7.90E-02 9.30E-02 1.04E-01 1.60E-01 7.50E-02 1.12E-01 9.30E-02 K-40 <2.0e-2 <2.6e-2 <2.8e-2 <2.3e-2 <2.0e-2 <3.4e-2 <3.4e-2 <2.8e-2 Mn-54 <2.7e-3 <1.9e-3 <2.3e-3 <2.4e-3 <2.5e-3 <2.4e-3 <2.6e-3 <2.7e-3 Co-57 <8.0e-4 <8.5e-4 <9.2e-4 <9.4e-4 <8.2e-4 <9.2e-4 <7.6e-4 <7.7e-4 Composite Dates Co-58 <4.1e-3 <4.9e-3 <4.1e-3 <3.3e-3 <3.2e-3 <3.5e-3 <3.8e-3 <3.9e-3 1ST QTR Fe-59 <1.7e-2 <2.0e-2 <1.7e-2 <1.5e-2 <2.9e-2 <2.5e-2 <1.9e-2 <1.9e-2 01/02/01- 03/27/01 Co-60 <3.3e-3 <2.6e-3 <2.9e-3 <1.7e-3 <2.9e-3 <6.le-4 <2.0e-3 <2.9e-3 Zn-65 <7.9e-3 <8.2e-3 <7.4e-3 <5.6e-3 <6.3e-3 <7.6e-3 <3.9e-3 <3.9e-3 Zr-95 <1.8e-3 <7.4e-3 <6.8e-3 <6.8e-3 <7.5e-3 <9.5e-3 <8.4e-3 <4.9e-3 Nb-95 <1.0e-2 <1.2e-2 <1.1e-2 <6.4e-3 <8.6e-3 <1.4e-2 <8.8e-3 <7.0e-3 Cs-134 <1.3e-3 <1.9e-3 <2.3e-3 <2.3e-3 <2.6e-3 <1.9e-3 <2.2e-3 <2.1e-3 Required LLD 5.0e-2 Cs-137 <1.7e-3 <2.0e-3 <2.1e-3 <1.7e-3 <1.9e-3 <2.0e-3 <2.0e-3 <1.7e-3 Required LLD 6.0e-2 Ba-140 <1.5e-1 <1.8e-1 <2.2e-1 <2.2e-1 <1.9e-1 <1.6e-1 <1.9e-1 <2.8e-1 La-140 <1.7e-1 <2.1e-1 <2.5e-1 <2.5e-1 <2.2e-1 <1.9e-1 <2.2e-1 <3.3e-1 Be-7 1.56E-01 1.54E-01 1.40E-01 1.16E-01 1.94E-02 1.57E-01 1.74E-01 1.28E-01 K-40 <3.1e-2 <2.5e-2 <2.7e-2 <2.2e-2 <2.5e-2 <2.3e-2 <2.5e-2 <5.5e-2 Mn-54 <1.5e-3 <2.3e-3 <1.8e-3 <1.7e-3 <2.3e-3 <2.1e-3 <2.3e-3 <2.5e-3 Co-57 <9.1e-4 <8.6e-4 <8.8e-4 <9.6e-4 <7.5e-4 <8.2e-4 <1.0e-3 <8.6e-4 Co-58 <3.6e-3 <2.7e-3 <2.8e-3 <4.0e-3 <4.4e-3 <3.5e-3 <3.8e-3 <3.5e-3 2ND QTR Fe-59 <1.8e-2 <6.9e-3 <2.0e-2 <1.8e-2 <2.5e-2 <2.5e-2 <2.4e-2 <3.1e-2 03/27/01- 06/26/01 Co-60 <2.9e-3 <6.8e-4 <2.0e-3 <1.8e-3 <2.9e-3 <3.3e-3 <6.le-4 <2.5e-3 Zn-65 <6.8e-3 <7.0e-3 <6.5e-3 <7.2e-3 <8.4e-3 <7.0e-3 <4.5e-3 <7.0e-3 Zr-95 <5.9e-3 <1.1e-2 <8.3e-3 <6.8e-3 <7.3e-3 <7.5e-3 <1.0e-2 <6.5e-3 Nb-95 <8.8e-3 <1.le-2 <1.2e-2 <6.le-3 <1.3e-2 <1.3e-2 <1.2e-2 <1.4e-2 Cs-134 <2.6e-3 <2.2e-3 <2.1e-3 <1.9e-3 <1.8e-3 <1.3e-3 <2.6e-3 <1.3e-3 Required LLD 5.0e-2 Cs-137 <1.3e-3 <2.3e-3 <2.4e-3 <2.2e-3 <2.0e-3 <2.4e-3 <1.9e-3 <2.0e-3 Required LLD 6.0e-2 Ba-140 <3.3e-1 <1.0e-1 <2.7e-1 <2.3e-1 <2.8e-1 <1.0e-1 <3.4e-1 <4.1e-1 La-140 Be-7 1.46E-01 1.34E-01 1.04E-01 5.90E-02 9.70E-02 1.07E-01 1.49E-01 8.60E-02 K-40 <2.5e-2 <2.8e-2 <2.6e-2 <3.1e-2 <2.5e-2 <1.9e-2 <2.8e-2 <2.9e-2 Mn-54 <2.0e-3 <2.1e-3 <2.4e-3 <2.6e-3 <2.2e-3 <2.4e-3 <2.8e-3 <1.7e-3 Co-57 <7.9e-4 <8.7e-4 <7.5e-4 <1.1e-3 <8.5e-4 <8.7e-4 <1.le-3 <8.4e-4 Co-58 <3.6e-3 <4.8e-3 <4.1e-3 <4.2e-3 <3.7e-3 <4.9e-3 <3.7e-3 <3.4e-3 3RD QTR Fe-59 <4.6e-3 <1.9e-2 <1.5e-2 <2.4e-2 <1.9e-2 <5.2e-3 <2.6e-2 <2.3e-2 06/26/01- 09/25/01 Co-60 <6.0e-4 <1.9e-3 <2.5e-3 <3.8e-3 <3.2e-3 <2.0e-3 <2.9e-3 <2.9e-3 Zn-65 <7.2e-3 <7.1e-3 <6.2e-3 <6.0e-3 <7.1e-3 <7.7e-3 <4.9e-3 <5.6e-3 Zr-95 <6.7e-3 <5.1e-3 <7.5e-3 <1.0e-2 <7.8e-3 <7.4e-3 <8.6e-3 <6.2e-3 Nb-95 <8.9e-3 <6.6e-3 <8.0e-3 <1.4e-2 <9.2e-3 <8.0e-3 <1.3e-2 <8.7e-3 Cs-1 34 <1.8e-3 <1.5e-3 <1.3e-3 <2.4e-3 <2.5e-3 <1.6e-3 <2.0e-3 <1.6e-3 Required LLD 5.0e-2 Cs-137 <1.9e-3 <1.8e-3 <1.4e-3 <2.4e-3 <1.4e-3 <1.7e-3 <2.2e-3 <1.7e-3 Required LLD 6.0e-2 Ba-140 <2.9e-2 <1.3e-1 <9.1e-2 <1.3e-1 <1.1e-1 <9.1e-2 <3.0e-2 <1.3e-1 La-140 <3.3e-2 <1.5e-1 <1.0e-1 <1.5e-1 <1.3e-1 <1.0e-1 <3.4e-2 <1.6e-1 Be-7 8.1OE-02 1.61E-01 1.33E-01 6.70E-02 8.60E-02 1.32E-01 1.12E-01 1.08E-01 K-40 <2.0e-2 <3.0e-2 <2.5e-2 <2.8e-2 <2.6e-2 <3.1e-2 <2.5e-2 <3.0e-2 Mn-54 <1.5e-3 <2.3e-3 <2.5e-3 <2.4e-3 <2.0e-3 <2.4e-3 <2.0e-3 <3.1e-3 Co-57 <1.1e-3 <6.8e-4 <7.7e-4 <1.le-3 <7.1e-4 <5.5e-4 <8.8e-4 <8.1e-4 Co-58 <3.8e-3 <3.6e-3 <3.4e-3 <4.6e-3 <3.6e-3 <3.2e-3 <3.9e-3 <3.3e-3 4TH QTR Fe-59 <1.5e-2 <1.5e-2 <1.2e-2 <1.5e-2 <1.7e-2 <1.5e-2 <1.0e-2 <1.6e-2 09/25/01 - 12/24/01 Co-60 <2.2e-3 <1.8e-3 <3.5e-3 <2.2e-3 <1.8e-3 <1.8e-3 <2.7e-3 <6.7e-4 Zn-65 <7.0e-3 <6.9e-3 <5.0e-3 <6.5e-3 <6.0e-3 <7.3e-3 <7.3e-3 <7.4e-3 Zr-95 <5.6e-3 <6.0e-3 <6.2e-3 <5.6e-3 <6.5e-3 <6.2e-3 <7.7e-3 <3.7e-3 Nb-95 <5.6e-3 <6.9e-3 <5.5e-3 <6.1e-3 <5.0e-3 <7.7e-3 <7.4e-3 <7.0e-3 Cs-134 <2.0e-3 <2.4e-3 <2.1e-3 <2.0e-3 <1.1e-3 <2.2e-3 <2.0e-3 <2.2e-3 Required LLD 5.0e-2 Cs-1 37 <1.1e-3 <1.5e-3 <1.7e-3 <1.8e-3 <1.5e-3 <1.6e-3 <2.0e-3 <1.8e-3 Required LLD 6.0e-2 Ba-140 <4.1 e-2 <6.4e-2 <4.4e-2 <5.2e-2 <5.6e-2 <6.5e-2 <1.4e-2 <7.0e-2 La-140 <4.7e-2 <7.4e-2 <5.1e-2 <6.0e-2 <6.5e-2 <7.5e-2 <1.7e-2 <8.1e-2

I). Surface WYater Program Surface water monitoring stations are found at four locations as detailed in Table 1 - Comanche Peak Steam Electric Station 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 installedreturn line to Lake Granburyhas 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 2001, all surface water samples were collected as required.

Table 7 -- 2001 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 1.25e+4 pCi/l to a low of 1.08e+4 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 - 2001 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. 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 CPSES 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 20

data indicated the 2001 results were both expected and consistent with previous data and that no anomalies had occurred.

For the year 2001, there were no exceptions to the Surface Water Program.

21

0+3007 ZO+3OO7 L0+3o00' L031O+3OO0e 30.0'V Z0+300't ZO+300T ZO+30oot ZO+3o'V CO+300"L CO+30OO1 ZO~O+ t'o+goos iOAel olqEwodaej O+3O9*1 L0+309"L 0+308L LO+O9'1 LO+3O9'L LO+3O9'1 LO+3O9i. L0+300T L0+309'L LO+300T L0+309"L LO+3O9' EO+3O0*t s,c3ill paainbeNj OG0*L> 00Z*9> PE~T> 00 It> OGC'9> 099T> 089'9> 00Z'L> Oa~c> 0017*6> 0PET> 096'Z> 101V1I> L967> PEI1> V'6L-N L0IVZIZ I 00989> 006'9> O09 C> 096*Z> OOL'g> 096*C> 089'V> 0699*> 009T> 10117> I09'Z> C"6L-N L0ILZIL I OBC'6> 001L9> 00617r> le VIS> 00L17> 0 11'C>

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Graph 3 -- Squaw Creek Maximum Tritium Values 30000 25000 0

CL20000 0.

0 15000 IM-*- maximum tritium I 10000 5000 0

(V Yearly Maximum

V. Surface I)rinking WN'ater Proogram Surface drinking water was collected at two monitoring locations. Table 1

-- Comanche Peak Steam Electric Station Radiological Environmental Monitoring Program for 2001 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 2001, 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 10,300 pCi/l to 13,000 pCi/l and averaged 11,650 pCi/l. Tritium reported from all Lake Granbury water samples indicated less than the required LLD as expected. Graph 4 - 2001 Environmental Surface Drinking Water Tritium Results trends the results reported for the year 2001. Gross Beta results at the indicator location NNW-0. 1 ranged from 15.0 pCi/l to 36.7 pCi/I with an average of 24.3 pCi/l. Gross Beta results at the control location N-9.9 ranged from 8.4 pCi/I to 18.8 pCi/l with an average of 12.2 pCi/l. Graph 5 -2001 Environmental Surface Drinking Water Gross Beta Results trends the gross beta results for the two monitor locations but does not show a definite 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 and therefore this yearly trend does not indicate a clear influence from the operations of Comanche Peak. This will be watched for the next few sample periods till a positive inference can be made. 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 2001 there was an exception to the Surface Drinking Water Program. Gamma isotopic analysis reported by the independent laboratory, for the February monthly gamma radionuclide analysis, failed to achieve the required LLD for the Iodine-131 radionuclide. The required LLD is 1.0 pCi/l and the laboratory reported values of less than 3.5pCi/I and less than 4.0 pCi/l.

These discrepancies were reported to the laboratory, but due to the long 26

time delay between sampling and the actual analysis and the additional time for mailing results, a reanalysis was not possible. The independent laboratory procedurally sent the water first to the gamma spectrometry lab area and then to the Iodine-131 lab area. This delay was the cause of the discrepancy. The laboratory has changed the method used to track the analysis of time sensitive radionuclides such as Iodine- 131. Comanche Peak has also committed to send two gallons of each water sample to the laboratory so that water samples may be sent simultaneously to both lab areas. The laboratory has also revised their report format for the year 2002 to include the required LLDs for each radionuclide and to have a software flag reported if the analysis results fail to achieve the required LLDs. If the warning flag is set, the lab will immediately reanalyze the sample.

These corrective actions should eliminate this discrepancy from future sample analysis. No other exceptions were noted for the Surface Drinking Water Program.

27

Table 8 -- 2001 Environmental Surface Drinking Water Tritium, Gross Beta and Gamma Isotopic Results (Units of pCiII)

H-3 Gross Beta Nuclides Date Location Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-1 37 Ba-140 La-I 40 1/30/01 N-9.9 1.18E+01 <3.6e0 <4.2e0 <1.lel <4.7e0 <2.1 el <6.6e0 <4.4e0 <7.3e-1 <3.9e0 <4.6e0 <5.7e0 <6.6e0 2/27/01 N-9.9 9.30E+00 <3.9e0 <5.1leO <9.4e0 <4.OeO <2.3e1 <6.5e0 <5.3e0 <3.5eO*** <3.3e0 <5.OeO <6.7e0 <7.7e0 3/27/01 N-9.9 <1.2e3 9.30E+00 <4.6e0 <4.6e0 <8.8e0 <4.8e0 <1.Oel .e7.6e0 <5.4e0 <3.9e-1 <4.7e0 <4.6e0 <7.7e0 <8.9e0 4/24/01 N-9.9 8.40E+00 <6.5e0 <7.1leO <1.8e1 <8.6e0 <1.9e1 <1.lel <8.1leO <6.5e-1 <7.3e0 <8.4e0 <1.3e1 <1.5e1 5/29/01 N-9.9 1.21 E+01 <3.8e0 <3.9e0 <1.6e1 <4.9e0 <1.lel <6.5e0 <4.6e0 <8.8e-1 <5.4e0 <4.2e0 <6.9e0 <8.OeO 6/26/01 N-9.9 <1.5e3 7.20E+00 <4.2e0 <4.1leO <9.OeO <4.1leO <2.Oel <6.3e0 <4.4e0 <8.7e-1 <3.7e0 <4.OeO <6.5e0 <7.5e0 7/31/01 N-9.9 1.09E+01 <4.3e0 <4.2e0 <1.2e1 <3.7e0 <2.1 el <7.1leO <5.2e0 <1 .OeO <4.BeO <4.4e0 <7.5e0 <8.6e0 8/28/01 N-9.9 1.48E+01 <3.OeO <3.5e0 <8.1leO <3.2e0 <7.8e0 <5.3e0 <3.8e0 <9.4e-1 <3.2e0 <3.1leO <6.4e0 <7.4e0 9/25/01 N-9.9 <1.0e3 1.40E+01 <2.4e0 <3.1 eO <1.Oel <3.2e0 <6.3e0 <4.9e0 <3.4e0 <7.7e-1 <2.8e0 <3.1leO <6.4e0 <7.4e0 10/30/01 N-9.9 1.41 E+01 <3.9e0 <3.8e0 <1.Oel <4.1leO <8.5e0 <6.2e0 <3.5e0 <1.OeO <3.8e0 <4.1leO <6.7e0 <7.7e0 11/27/01 N-9.9 1.55E+01 <5.OeO <4.7e0 <1.6e1 <6.OeO <1.3e1 <8.6e0 <7.OeO <8.3e-1 <4.8e0 <5.3e0 <9.5e0 <1.lel 12/24/01 N-9.9 <1.30e3 1.8817+01 <3.5e0 <3.7e0 <1.Oel <3.8e0 <1.9e1 <6.4e0 <4.8e0 <8.6e-1 <3.8e0 <4.8e0 <6.9e0 <7.9e0 1/30/01 NNW-O.1 2.59E+01 <3.6e0 <4.4e0 <8.1leO <3.3e0 <1.9e1 <5.1leQ <5.6e0 <7.6e-1 <4.1leO <4.2e0 <7.OeO <8.OeO 2/27/01 NNW-O.1 1.50E+01 <6.3e0 <5.9e0 <1.8e1 <6.5e0 <1.3e1 <8.8e0 <7.1leO <4.OeO*" <4.8e0 <7.1leO <8.4e0 <1.Oel 3/27/01 NNW-O.1 1.30E+04 1.50E+01 <5.1leO <6.2e0 <1.6e1 <6.6e0 <1.4e1 <9.OeO <6.6e0 <4.Oe-1 <6.4e0 <6.6e0 <8.5e0 <l.Oel 4/24/01 NNW-O.1 2.25E+01 <4.6e0 <4.6e0 <1.3e1 <4.OeO <1.5e1 <8.3e0 <5.5e0 <5.6e-1 <5.3e0 <4.8e0 <7.7e0 <8.9e0 5/29/01 NNW-O.1 2.42E+01 <6.7e0 <6.3e0 <1.9e1 <6.2e0 <1.4e1 <1.Oel <li1el <8.7e-1 <5.5e0 <5.5e0 <8.1leO <9.3e0 6/26/01 NNW-O.1 1.14E+04 2.37E+01 <3.6e0 <4.4e0 <1.Oel <3.9e0 <1.6e1 <5.6e0 <3.7e0 <8.8e-1 <4.3e0 <4.1leO <5.OeO <5.8e0 7/31/01 NNW-O.1 2.48E+01 <3.2e0 <3.9e0 <1.2e0 <4.OeO <1.9e1 <5.8e0 <4.9e0 <8.3e-1 <4.OeO <4.1leO <5.9e0 <6.8e0 8/28/01 NNW-O.1 2.34E+01 <2.4e0 <3.1leO <8.4e0 <3.OeO <6.4e0 <6.2e0 <3.4e0 <6.8e-1 <2.8e0 <2.9e0 <6.5e0 <7.5e0 9/25/01 NNW-O.1 1.03E+04 2.04E+01 <5.6e0 <5.2e0 <1.6e1 <5.lIeO <1.Oel <8.8e0 <7.5e0 <1 .OeO <6.2e0 <5.OeO <9.3e0 <1.lel 10/30/01 NNW-O.1 2.89E+01 <4.OeO <4.3e0 <1.3e1 <4.9e0 <1.Oel <6.9e0 <5.OeO <9.3e-1 <4.6e0 <4.4e0 <7.3e0 <8.4e0 11/27/01 NNW-O.1 3.07E+01 <4.3e0 <5.3e0 <1.3e1 <6.9e0 <1.2e1 <8.8e0 <7.3e0 <7.0e-1 <4.3e0 <5.8e0 <1.2e1 <1.4e1 12/24/01 NNW-O.1 1.19E+04 3.67E+01 <3.6e0 <3.7e0 <1.Oel <4.4e0 <1.8el <7.OeO <5.1leO <9.4e-1 <3.6e0 <3.9e0 <6.1leO <7.OeO Required LLD's 2.OOE+03 4.OOE+0O 1.50E+01 1.50E+01 3.OOEi-01 1.50Ei-01 3.OOE+O1 1.50E+01 1.50E+01 1.OOE+OO 1.50E+01 1.80E+01 1.50E+01 1.50E+01 Reportable Level 2.OOE+04 None 1.OOE+03 1.OOE+03 4.OOE+02 3.OOE+02 3.OOE+02 4.OOE+02 4.OOE+02 2.OOE+0O 3.OOE+01 5.OOE+01 2.OOE+02 2.OOE+02

Graph 4 -- 2001 Environmental Surface Drinking Water Tritium Results 1.40E+04 1.20E+04 0

1.00E+04 0.

8.00E+03 -a-- N-9.9 0

6.00E+03 -U- NNW-0.1 DI 4.00E+03 2.OOE+03 0.00E+00 - I I Mar-01 Jun-01 Sep-01 Dec-01 Composite Sample Dates

Graph 5 -- 2001 Environmental Surface Drinking Water Gross Beta Results 4.OOE+01 3.50E+01 3.OOE+01 2.50E+01 W.

NN-9.9 0

C',

2.OOE+01 ---NN -.

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• 03 t.O I* 0-Ob Monthly Data Points

F. Ground Water Pro-rain Table 1 - Comanche Peak Steam Electric Station Radiological Environmental Monitoring Program for 2001 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 2001, 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 -- 2001 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 2001, there were no exceptions to the Ground Water Program.

31

Table 9 -- 2001 Environmental Groundwater Tritium and Gamma Isotopic Results (Units of pC111)

Nuclides H-3 Mn-64 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-I 34 Cs-I 37 Ba-140 La-140 Date Location 3/27/01 W-1.2 <1.2e3 <5.6e0 <4.6e0 <1.6e1 <6.3e0 <1.4e1 <8.2e0 <6.2e0 <8.9e0 <5.l1eO <5.6e0 <il1el <1.3e1 6/26/01 W-1 .2 <9.6e2 <3.4e0 <3.6e0 <9.l1eO <2.7e0 <8.3e0 <5.l1eO <3.7e0 <6.OeO <3.6e0 <3.3e0 <5.OeO <5.8e0 9/25/01 W-1 .2 <9.4e2 <5.4e0 <5.3e0 <1.5e1 <5.5e0 <1.2e1 <6.9e0 <4.6e0 <9.4e0 <4.3e0 <4.8e0 <1liel <1.2e1 12/24/01 W-1.2 <1.1e3 <4.8e0 <3.7e0 <1.3el <4.2e0 <1.4e1 <8.4e0 <5.8e0 <8.2e0 <3.8e0 <5.4e0 <7.2e0 <8.3e0 3/27/01 WSW-O.1 <1.2e3 <9.5e0 <1.4e1 <2.6e1 <9.3e0 <2.lel <1.3e1 <1.5e1 <1.4e1 <9.l1eO <1.2e1 <1.3e1 <1.5e1 6/26/01 WSW-O.1 <9.7e2 <3.7e0 <6.7e0 <li1el <4.2e0 <2.3e1 <6.7e0 <7.7e0 <9.5e0 <3.5e0 <4.8e0 <6.8e0 <7.8e0 9/25/01 WSW-0.1 <9.4e2 <3.9e0 <4.6e0 <1 .6e1 <4.4e0 <1.2e1 <5.7e0 <7.9e0 <9.l1eO <3.7e0 <5.6e0 <8.3e0 <1.Oel 12/24/01 WSW-0.1 <1.1e3 <3.7e0 <3.4e0 <9.5e0 <3.4e0 <1.7e1 <6.OeO <6.6e0 <7.4e0 <3.2e0 <3.8e0 <5.OeO <5.7e0 3/27/01 SSE-4.6 <1.2e3 <4.3e0 <4.OeO <1.4e1 <5.9e0 <1.2e1 <7.3e0 <4.4e0 <7.5e0 <5.2e0 <5.l1eO <8.9e0 <l.Oel 6/26/01 SSE-4.6 <9.6e2 <3.8e0 <1.2el <5.OeO <6.2e0 <5.8e0 <7.6e0 <5.2e0 <8.3e0 <4.l1eO <4.8e0 <6.7e0 <7.7e0 9/25/01 SSE-4.6 <9.4e2 <3.2e0 <2.7e0 <7.3e0 <3.OeO <8.6e0 <5.7e0 <3.8e0 <7.6e0 <3.9e0 <3.6e0 <6.8e0 <7.8e0 12/24/01 SSE-4.6 <1.1e3 <2.9e0 <3.l1eO <8.4e0 <3.7e0 <6.6e0 <5.6e0 <2.7e0 <6.8e0 <3.l1eO <3.l1eO <5.2e0 <5.9e0 3/27/01 N-9.8 <1 .2e3 <3.8e0 <4.2e0 <8.9e0 <3.7e0 <2.2e1 <6.4e0 <6.3e0 <7.7e0 <3.9e0 <4.l1eO <5.9e0 <6.8e0 6/26/01 N-9.8 <9.6e2 <3.9e0 <5.4e0 <1.lel <4.9e0 <1.2e1 <7.8e0 <5.7e0 <7.9e0 <4.8e0 <5.6e0 <l.Oel <1.lel 9/25/01 N-9.8 <9.4e2 <3.4e0 <3.leO <8.2e0 <3.2e0 <8.5e0 <5.7e0 <3.8e0 <7.5e0 <2.8e0 <3.8e0 <5.9e0 <6.7e0 12/24/01 N-9.8 <1.1 e3 <4.2e0 <4.l1eO <1.2e1 <4.6e0 <7.9e0 <6.5e0 <4.3e0 <8.OeO <4.2e0 <4.6e0 <8.l1eO <9.3e0 3/27/01 N-1.45 <1.2e3 <4.l1eO <4.OeO <1.5e1 <5.OeO <1.4e1 <6.7e0 <4.5e0 <8.l1eO <4.8e0 <4.9e0 <8.2e0 <9.4e0 6/26/01 N-1.46 <1.3e3 <5.OeO <4.OeO <1.4e1 <4.OeO <1.2e1 <8.3e0 <5.5e0 <1.Oel <4.6e0 <5.5e0 <9.3e0 <1.lel 9/25/01 N-1.45 <9.4e2 <2.6e0 <2.8e0 <7.6e0 <3.l1eO <6.2e0 <5.3e0 <3.4e0 <6.4e0 <2.8e0 <2.8e0 <5.4e0 <6.2e0 12/24/01 N-1.45 <1.1e3 <4.5e0 <4.4e0 <1.4e1 <5.8e0 <8.6e0 <7.6e0 <4.9e0 <9.1eO <5.2e0 <5.OeO <8.2e0 <9.4e0 Required LLD's 3.OOE+03 1.50E+01 1.50E+01 3.OOE+O1 1.50E+01 3.OOE+O1 1.50E+01 1.50E+01 1.50E+01 1.50E+01 1.80E+01 1.50E+01 1.50E+01 Reportable Levels 2.OOE+04 1.OOE+03 1.OOE+03 4.OOE+02 3.OOE+02 3.OOE+02 4.OOE+02 4.OOE+02 2.OOE+O1 3.OOE+O1 5.OOE+O1 2.OOE+02 2.OOE+02

G. Sediment Progrmi Shoreline sediments were collected at four different monitoring locations.

Two sample locations are along the shore of Squaw Creek reservoir 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 2001, results from the gamma isotopic analysis of shoreline sediments is reported in Table 10 -- 2001 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 samples indicated less than the required LLDs. During previous years, both pre operational and operational, positive indications occasionally had been noted for Cesium-137 but during 2001 no positive Cesium-137 results were reported. The only other positive value reported for 2001 was for naturally occurring Beryllium-7. As expected, there were no results in any sediment sample that indicated any influence from CPSES discharges to the local environment.

For the year 2001, there were no exceptions to the Sediment Program.

33

Table 10 -- 2001 Environmental Sediment Gamma Isotopic Results (Units of pCi/kg)

Nuclides Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Date Location 1/9/01 N-1.0 <1.7e2 3.73E+03 <1.8el <1.6el <6.2el <t.9el <7.5el <2.7el <3.4el <6.6el <7.3el <2.2el <1.6e2 <1.9e2 1/9/01 N-9.9 <1.8e2 3.68E+03 <2.3el <2.4el <8.1el <2.5el <9.2el <2.8el <2.8el <7.5el <8.3el <2.2el <1.4e2 <1.6e2 1/9/01 NE-7.4 <1.5e2 1.97E+03 <1.6el <1.5el <4.4el <1.8el <6.5el <2.6el <2.2el <5.Oel <6.4el <1.6el <1.1e2 <1.2e2 1/9/01 SE-5.3 <3.9e2 6.65E+03 <4.1el <3.7el <1.4e2 <4.2el <2.0e2 <7.2el <7.5el <1.2e2 <3.8el <4.2el <1.0e2 <1.2e2 7/17/01 N-1.0 <1.7e2 1.88E+03 <1.6el <1.6el <6.4el <1.8el <7.2el <3.2el <2.4el <4.9el <7.7el <1.9el <1.1e2 <1.3e2 7/17/01 N-9.9 <2.3e2 4.70E+03 <2.5el <1.8el <7.2el <2.6el <7.Oel <4.6el <4.4el <6.5el <2.Oel <2.6el <1.5e2 <1.7e2 7/17/01 NE-7.4 <1.6e2 1.98E+03 <2.Oel <1.9el <6.3el <2.3el <1.1e2 <3.5el <2.7el <4.7el <8.3el <1.9el <1.1e2 <1.3e2 7/17/01 SE-5.3 1.30E+03 5.13E+03 <3.5el <4.1el <9.1el <3.9el <1.3e2 <7.2el <3.9el <9.9el <4.1el <5.Oel <2.0e2 <2.3e2 Required LLD's 1.50E+02 1.80E+02 Reportable Levels None None

I1. Fish Program Fish samples were collected at two locations during the year 2001. 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. CPSES personnel collect the fish from these areas. The fish are now caught using rod and reels to eliminate the killing of rough fish and extra game fish that is associated with the past method of using gill nets to obtain the required fish. The collected fish are frozen and shipped to the independent laboratory where the edible portions are analyzed for gamma emitting radionuclides.

For the year 2001, the results of the analysis performed on the collected fish samples is reported in Table 11 -- 2001 Environmental Fish Gamma Isotopic Results. Catfish and bass samples were analyzed as indicated in the table. There were no positive results reported except for the expected Potassium-40, which is naturally occurring in all living organisms. All required radionuclide results were reported as less than the required LLDs.

As a result of the fish-sampling program, there were no anomalies noted and no indication of any influence on the surrounding environment from Comanche Peak plant discharges.

For the year 2001, there were exceptions to the Fish Program. As noted in Table 11 - 2001 Environmental Fish Gamma Isotopic Results, the fish collected and sent to the independent laboratory did not arrive. The investigation into the disappearance of the fish samples was traced to the express shipping company destroying the samples. Water was leaking from the shipping containers and the shipping company assumed it might be hazardous and threw the fish away. They completed the delivery of the other items shipped but did not inform CPSES of the problem. During the investigation it was finally discovered what had happened to the fish and procedures have now been changed in the methods used to ship fish in the future. The shipping company will now accept the frozen fish and not destroy them if water is discovered. The CPSES warehouse will use special containers to package the fish for shipment. These containers are supposed to be leakproof. For the April sampling period, fish were also sent to the State of Texas for analysis and therefore the results from their analysis is reported in the table. No abnormal results were reported by the State of Texas and as expected Potassium-40 was the only positive isotope found.

35

The October sampling period for fish was postponed due to the changes in security associated with September 11, 2001. Due to the threat of sabotage, access to the reservoir was suspended for all site personnel as well as for members of the public. With prior concurrence of the Region 4 - Nuclear Regulatory Commission personnel, fish collection was suspended till access to the reservoir was restored. In November 2001 the access to the reservoir was restored on a limited basis. As a result of restoring access, collection was performed. Access is still being debated and future collection is scheduled and will be done as allowed by security changes. No other exceptions to the Fish Program were noted.

36

Table 11 -- 2001 Environmental Fish Gamma Isotopic Results (Units of pCi/kg wet)

Nuclides K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 1-131 Cs-134 Cs-137 Ba-140 La-140 Fish Type Date Location 5/6/01 Squaw Creek 2.85E+03 <5.6e0 <6.1eO <1.5el <5.5e0 <1.4el <1.1el <7.5e0 <2.6el <4.8e0 <6.1e0 <4.7el <1.1el catfish

• 11/20/01 Squaw Creek 3.15E+03 <5.4el <7.lel <2.2e2 <5.1el <1.6e2 <1.2e2 <9.7el <1.1e3 <5.9el <5.9el <3.6e2 <4.1e2 catfish 4/26/01 Lake Granbury 2.87E+03 <4.8e0 <6.1eO <1.7el <4.9e0 <1.4el <1.1el <8.4e0 <5.7el <4.2e0 <5.3e0 <7.7el <1.8el catfish *-*

11/20/01 Lake Granbury 3.45E+03 <2.8el <3.2el <1.2e2 <2.6el <9.2el <8.1el <5.1el <3.7e2 <2.9el <2.8el <1.1e2 <1.3e2 bass 11/20/01 Lake Granbury 2.97E+03 <4.1el <4.9el <1.7e2 <3.6el <2.1e2 <6.lel <6.2el <4.1e2 <3.9el <3.9el <1.3e2 <1.5e2 catfish Required LLD's 1.30E+02 1.30E+02 2.60E+02 1.30E+02 2.60E+02 1.30E+02 1.50E+02 Reportable Levels 3.OOE+04 3.OOE+04 1.OOE+04 1.00E+04 2.OOE+04 1.00E+03 2.OOE+03

• • • Analysis provided by the State of Texas

!. 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 2001, results of the gamma isotopic analysis are reported in Table 12 -- 2001 Environmental Food Products Gamma Isotopic Results.

There were no gamma emitting radionuclides identified.

For the year 2001, there were exceptions to the Food Products program. The LLD for 1-131 is required to be 60 pCi/kg but the contract laboratory reported a value of 62 pCi/kg for the LLD results therefore the laboratory failed to achieve the required LLD. This discrepancy was reported to the contract laboratory by CPSES, but due to the long time delay between sampling and the actual analysis and the additional time for mailing results, a reanalysis was not possible. As a result of this discrepancy, the laboratory has committed to a revised report format for the year 2002 to include the required LLDs for each radionuclide and to have a software flag reported if the analysis results fail to achieve the required LLDs. If the warning flag is set, the lab will immediately reanalyze the sample. These corrective actions should eliminate this discrepancy from future sample analysis. No other exceptions were noted for this portion of the Food Products Program.

38

Table 12 -- 2001 Environmental Food Products Gamma Isotopic Results (Units of pCi/kg wet)

Nuclides 1-131 Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-134 Cs-137 Ba-140 La-140 Date Food Type Location 11/6/02 Pecans ENE-9.0 <6.2e1*** <3.4e2 4.56E+03 <3.8e-1 <4.4e-1 <1.4e2 <4.4el <1.2e2 <6.8el <4.9el <4.7el <4.2el <5.8el <6.6el Required LLD's 6.OOE+01 6.OOE+01 8.OOE+01 Reportable Levels 1.OOE+02 1.OOE+03 2.OOE+03

1J. B road leaf 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 are analyzed for Iodine-131 and gamma emitting isotopes.

For the year 2001, all radionuclide analyses met their required LLDs and there was no indication of any gamma emitting radionuclides being identified that were directly attributable to the operation of Comanche Peak. There were no indications of Iodine-131 being detected. The naturally occurring radionuclides, Potassium-40 and Beryllium-7, were present in every sample as expected.

For the year 2001, there were no exceptions to the Broadleaf Program.

40

Table 13 -- 2001 Environmental Broadleaf lodine-131 and Gamma Isotopic Results (Units of pCi/kg wet)

Nuclides 1-131 Be-7 K-40 Mn-54 CO-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Cs-I 34 Cs-I 37 Ba-140 La-140 Date Location 1/30/01 N-I1.45 <3.9e 1I.97E+03 4.13E+03 <1.Oel <1.lel <3.2e1 <9.7e0 <5.1le <1.7e1 <1.2e1 <2.1el <1.3e1 <2.2e1 <2.5e1 2/27/01 N-1.45 <4.6e1 1.95E+03 2.04E+03 <5.8e1 <6.8el <2.0e2 <5.5e1 <3.6e2 <8.6e1 <1.2e2 <5.Oel <5.Oel <2.7e2 <3.1 e2 3/27/01 N-1.45 <l.Oel 1.I0E+03 2.91 E+03 <1.6e1 <1.4el <5.Oel <1.5e1 <4.Oel <2.2e1 <1.8e1 <1.4e1 <l.5e1 <3.1le <3.6e1 4/24/01 N-1.45 <4.9e1 6.80E+02 5.28E+03 <1 .6e1 <1.9el <7.3e1 <2.Ie1 <4.4e1 <3.4e1 <2.3e1 <1.8e1 <1.9e1 <6.lel <7.Oe1 5/29/01 N-1.45 <2.9el1l.31 E+03 5.18E+03 <2.9e1 <2.8e1 <1.1e2 <3.2e1 <9.3e1 <5.3e1 <4.2e1 <3.4e1 <2.9e1 <1.0e2 <1.2e2 6/26/01 N-1.45 <3.4e1 8.OOE+02 4.36E+03 <3.5e1 <3.4e1 <1.1e2 <4.lel <I.0e2 <5.7e1 <4.6e1 <3.9e1 <3.4e1 <9.2e1 <1.le2 7/31/01 N-1.45 <4.3e1 2.29E+03 9.61 E+03 <3.8e1 <4.OeI <1.1e2 <3.6e1 <1.3e2 <6.7e1 <4.5e1 <3.9e1 <3.7e1 <9.OeI <1.0e2 8/28/01 N-1.45 <4.4e1 1.37E+03 5.08E+03 <3.2e1 <3.4el <1.2e2 <3.5e1 <9.7e1 <5.9e1 <4.6e1 <2.9e1 <3.1Iel <1.2e2 <1.4e2 9/25/01 N-1.45 <3.9e1 2.1IOE+03 3.83E+03 <2.lel <2.2el <5.8e1 <2.Iel <7.Iel <3.6e1 <4.1le <2.3e1 <2.3e1 <4.Oel <4.6e1 10/30/01 N-1.45 <4.Oel 2.71 E+03 5.91 E+03 <3.8e1 <4.5el <1.2e2 <3.9e1 <1.5e2 <7.2e1 <1.1e2 <4.4e1 <4.1le <I.1e2 <1.3e2 11/27101 N-1.45 <4.lel 2.52E+03 2.49E+03 <3.2e1 <4.Oel <1.3e2 <3.1lel <1.1e2 <6.7e1 <1.9e2 <3.3e1 <3.3e1 <2.2e2 <2.5e2 12/24/01 N-1.45 <5.Oel 8.68E+03 I1.23E+03 <3.4e1 <3.4e1 <9.1le <3.4e1 <1.1e2 <5.8e1 <7.6e1 <3.6e1 <3.6e1 <5.8e1 <6.6el 1/30/01 Sw-1.0 <2.7e1 1.22E+03 2.50E+03 <1.5e1 <1.7e1 <4.3e1 <I.4e1 <7.8e1 <2.9e1 <1.9e1 <I.6e1 <1.6e1 <3.4e1 <3.9e1 2/27101 SW-I .0 <5.2e1 2.46E+03 8.20E+02 <6.3e1 <7.8el <1.4e2 <5.OeI <3.4e2 <1l1e2 <1.2e2 <4.8e1 <6.9e1 <1.8e2 <2.1 e2 3/27/01 sw-i .o <2.4e1 7.53E+03 6.70E+02 <2.2e1 <2.2el <5.8e1 <2.1Iel <5.Oel <4.8e1 <2.2e1 <2.2e1 <2.2e1 <3.8e1 <4.3e1 4/24/01 Sw-l.a <5.2e1 5.89E+02 4.07E+03 <1 .7e1 <1.9el <5.lel <1.6e1 <6.IeI <2.9e1 <2.3e1 <1.7e1 <l.6e1 <5.5e1 <6.3e1 5/29/01 sw-i .o <2.3el1l.23E+03 5.12E+03 <1.7e1 <2.3e1 <6.Oel <1.8e1 <6.9e1 <3.3e1 <2.5e1 <2.1lel <I.BeI <5.lel <5.8e1 6/26/01 SW-I .0 <4.OeI 8.70E+02 3.58E+03 <2.3e1 <3.Oel <7.5e1 <2.2e1 <5.0e2 <4.3e1 <3.Oel <2.9e1 <3.6e1 <6.Oel <6.9e1 7/31/01 sw-1.0 <4.Oel 2.94E+02 3.06E+03 <2,3e1 <2.6e1 <6.6e1 <2.3e1 <1.2e2 <3.7e1 <5.5e1 <2.3e1 <2.4e1 <4.9e1 <5.6el 8128/01 sw-i .o <4.4e1 2.03E+03 2.75E+03 <2.4e1 <2.3e1 <9.1le <2.4e1 <6.8e1 <4.7el <3.3e1 <2.3e1 <2.2e1 <8.3e1 <9.5e1 9/25/01 sw-i .o <5.4e1 1.25E+03 3.12E+03 <9.OeO <1.Oel <2.9e1 <8.6e0 <3.3e1 <1.7e1 <1.lel <9.4e0 <8.9e0 <2.6el <3.Oel 10/30/01 sw-l.a <3.2e1 2.OOE+03 3.42E+03 <3.2e1 <3.Qel <1.2e2 <3.3e1 <1.0e2 <6.Iel <3.8e1 <3.1lel <3.3e1 <1.0e2 <1.2e2 11/27/01 Sw-l.a <3.6el 4.42E+03 4.69E+03 <3.7e1 <4.3el <1.6e2 <4.2e1 <2.2e2 <7.Iel <6.2e1 <3.5e1 <3.5e1 <2.7e2 <3.1 e2 12/24/01 sw-1.0 <3.5e1 7.67E+03 I1.34E+03 <3.5e1 <3.8e1 <1.2e2 <4.3e1 <9.5e1 <6.lel <3.8e1 <3.7e1 <3.6e1 <8.4e1 <9.7e1 Control 1/30/01 SW-I 3.5 <2.lel 1.56E+03 5.70E+03 <I.2e1 <1.2el <3.5e1 <Il1el <3.2e1 <I.9e1 <1.4e1 <1.2e1 <I.lel <2.3e1 <2.7e1 2/27/01 SW-I 3.5 <3.IeI 7.07E+03 9.30E+02 <4.Oel <4.1 el <1 .2e2 <3.8e1 <1 .0e2 <8.3e1 <5.3e1 <3.8e1 <3.8el <1.3e2 <1.5e2 3/27/01 SW-I 3.5 <1 .8e1 7.63E+02 4.02E+03 <1 .3e1 <1.4el <3.8e1 <1.3e1 <3.2e1 <2.5e1 <I.5el <1.3e1 <I.3e1 <2.4el <2.8e1 4/24/01 SWA13.5 <3.9el 9.41 E+02 4.45E+03 <1 .9e1 <2.Oel <6.2e1 <1.8e1 <4.9e1 <3.2e1 <2.6e1 <I.8e1 <I.7e1 <7.2e1 <8.3e1 5/29/01 SW-I 3.5 <1.6el1I.31 E+03 3.94E+03 <2.2e1 <2.3e1 <8.OeI <2.6e1 <5.2e1 <4.le1 <3.5e1 <2.7e1 <2.lel <8.lel <9.3e1 6/26/01 SW-I 3.5 <4.7e1 4.66E+02 4.56E+03 <2.Iel <2.2e1 <7.6e1 <2.8e1 <5.1lel <3.4e1 <2.9e1 <2.6e1 <2.lel <5.5e1 <6.3e1 7/31/01 SW-I 3.5 <4.8e1 1.71 E+03 7.65E+03 <4.3e1 <4.4e1 <1.7e2 <5.2e1 <5.1 e2 <7.9e1 <5.6e1 <4.4e1 <4.4e1 <1.2e2 <1.4e2 8/28/01 Sw-I 3.5 <3.3e1 2.19E+03 1.95E+03 <2.9eI <3.lel <8.9e1 <2.8e1 <9.6e1 <5.lel <6.2e1 <2.9e1 <2.8e1 <9.1lel <1.0e2 9/25/01 SW-I 3.5 <5.3el1I.17E+03 3.59E+03 <1.1le <1.Oel <4.Oel <I.2e1 <3.8e1 <1.8e1 <I.3e1 <Il1el <1.Oel <3.1lel <3.6e1 10/30/01 SW-i 3.5 <5.Oel 3.51 E+03 3.03E+03 <3.9e1 <7.le 1 <1l1e2 <3.7e1 <1.3e2 <6.8e1 <8.8e1 <4.1el <4.Oel <1.0e2 <1.2e2 11/27/01 SW-I 3.5 <1.3el1 .19E+03 6.32E+03 <5.lel <6.2el <2.2e2 <4.8e1 <1.5e2 <1.2e2 <9.6e1 <5.IeI <5.Oel <3.8e2 <4.3e2 12/24/01 SW-1 3.5 <5.lel 7.12E+03 9.20E+02 <3.5e1 <3.7el <1.0e2 <4.2e1 <1.1e2 <6.Oel <6.8e1 <3.4e1 <3.6e1 <8.5e1 <9.7e1 Required LLD's 6.OOE+01 6.OOE+01 8.OOE+01 Reportable Levels I .OOE+02 I .OOE+03 2.00 E+03

K. Conclusions For the year 2001, 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 attributable to Comanche Peak is the tritium detected in Squaw Creek reservoir.

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 natural terrestrial and cosmic ray radiation 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 2001 that exceeded any NRC reportable limit.

L. Inte'rlaboratory Comparison and Cross Check Progcram Duke Engineering & Services Environmental Laboratory (DESEL) is the independent contract laboratory that processes the radiological environmental monitoring samples collected by CPSES. The contract laboratory is required to participate in an Interlaboratory Comparison Program in accordance with the ODCM Control 3.12.3. DESEL participates in multiple programs to ensure all environmental media sent to them are analyzed to the proper standards.

DESEL recently published "Semi-Annual Quality Assurance Status Report January-June 2001" which included current interlaboratory comparison results and two year trends as appropriate. This report explained the Quality Control Program used by DESEL during this time period. Interlaboratory and third party quality control programs included the Environmental Crosscheck Program administered by Analytics, Inc.,

the National Institute of Standards and Technology (NIST) Measurement Assurance Program (MAP), the Department of Energy (DOE) Quality Assessment Program (QAP) and the Mixed Analyte Performance Evaluation Program (MAPEP). DESEL 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.

42

During each semi-annual reporting period at least one internal assessment is conducted and at least once a year the laboratory is audited by the Laboratory Quality Control Audit Committee (LQCAC) which is a consortium of clients. The NRC also conducts audits as part of the Radiological Environmental Monitoring Program.

Extensive details of the results of the various interlaboratory and cross check programs are contained in the report mentioned above. A summary of these results indicated that during this semi-annual reporting period, twenty-seven nuclides from various media types were analyzed. Using internal process controls, DOE, NIST, and Analytics quality programs the following results were achieved. The Analytics Cross Check Program provided 48 individual environmental analyses, 91.7% of all results fell within DESEL acceptance criteria for bias and 100% for precision. Three of six Iodine-131 individual analyses from NIST met the DESEL internal acceptance criteria. From the DOE Quality Assessment Program, thirty mean analyses were evaluated with five warnings reported. DESEL participated in the Mixed Analyte Performance Evaluation for water analysis. The DOE program EML Gamma Spectrometry Data Evaluation Program resulted in twenty of twenty-two radionuclides being determined by EML acceptance criteria. Of the 144 internal process control analyses, there was a 96.5% acceptance for bias and 100% acceptance for precision.

From the DESEL report noted above, the following quote summaries the overall program. "...the cumulative bias for the three programs evaluated to internal DESEL performance criteria shows 93.9% of the 198 individual results were observed to fall within DESEL bias acceptance criteria, while 100% of the 104 analyses passed DESEL acceptance criteria for precision."

The independent laboratory, DESEL, satisfies the requirements of the ODCM by their interlaboratory and cross check program documented in their semi-annual reports.

43

Appendix A Comanche Peak Steam Electric Station Land Use Census 2001 COPY 44

Sep 28, 2001 COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS 2001 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 20 and 21, 2001 and includes the following items:

1. Evaluation of the 2001 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..

1

Evaluation of the 2001 Land Use Census The results of the 2001 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. For 2001, the previous control milk location (SW-14.5) sold all the cows used for production of milk. Therefore, there will be no milk sampled during the year 2001.

Since not all milk samples are available, the broadleaf vegetation sampling specified in ODCM Table 3.12-1 is beinrg 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 2

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 2001 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 2001 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 3

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 4.70E-07 1.20E-09 SE 1.9 8.30E-07 3.40E-09 SSE 1.5 1.1OE-06 6.60E-09 S 1.5 8.50E-07 5.20E-09 SSW 2.2 3.24E-07 1.41E-09 SW 1.1 1.40E-06 5.50E-09 WSW 1.0 1.80E-06 6.50E-09 W 1.6 7.64E-07 2.50E-09 WNW 3.0 3.76E-07 1.07E-09 NW 2.7 6.98E-07 2.24E-09 NNW 2.8 5.28E-07 2.1OE-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.

4

Nearest Garden by Sector, Distance and D/Q Sector Distance (Miles) D/Q N 3.4 2.90E-09 NNE 2.5 2.30E-09 NE 2.4 1.14E-09 ENE 2.4 7.08E-10 E 2.4 6.62E- 10 ESE 3.3 3.96E-10 SE 3.8 6.26E- 10 SSE 1.9 3.88E-09 S 2.1 2.28E-09 SSW 4.5 2.60E-10 SW 1.5 2.50E-09 WSW 1.6 1.98E-09 W 3.3 4.42E-10 WNW 3.0 1.04E-09 NW None None INNW None None 5

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 6

Population by Sector and Distance Sector 0-1 1-2 2-3 3-4 4-5 Total N 5 - 32 106 143 NNE 11 93 24 128 NE 48 138 253 439 ENE 85 8 24 117 E - 98 166 27 291 ESE 3 24 104 138 269 SE 13 104 53 69 239 SSE 51 59 53 2148 2311 S 53 43 37 162 295 SSW - 5 3 51 59 SW 67 11 51 40 169 WSW 231 5 27 - 263 W 64 5 21 5 95 WNW - - 35 64 99 NW 3 - - 3 NNW - 3 45 21 69 TOTAL 482 509 866 3132 4989 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 residents per house of 2.57 and 2.74, respectively.

7

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 SWfWSW-0.95 A A8 NW-1.0 A RI N-1.45 (Squaw Creek Park) R R2 N-4.4 R R3 N-6.5 R R4 N-9.4 (Granbury) R R5 NNE-1.1 R R6 NNE-5.65 R R7 NE-1.7 R R8 NE-4.8 R R9 ENE-2.5 R R10 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 8

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-1.1 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 9

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/DW' SW3 N-19.3 (CONTROL-Brazos River) SW SW4 NE-7.4 (Lake Granbury) SW ESE-1.4 (Squaw Creek Reservoir) SW 2 SW5 SW6 NNW-0.1 (Squaw Creek Reservoir) SW/DW3 GW1 W-1.2 (NOSF Potable Water) GW WSW-0.1 (Plant Potable Water) GW3' 4 GW2 GW3 SSE-4.6 (Glen Rose) GW 4 GW4 N-9.8 (Granbury) GW'4 GW5 N-1.45 (Squaw Creek Park) GW4 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 Fl ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F FP1 ENE-9.0 (Leonard Bros. Pecan Farm) FP 10

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

4) Ground water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 and are therefore not required to be monitored for radioactivity to meet the requirements of the Radiological Effluent Control 3/4.12.1, Table 3.12-1.

5) Broadleaf sampling will be performed at the specified locations if milk samples are unavailable from any location.

11

Environmental Sample Locations Map - 2 Mile Radius