ML20206E009
| ML20206E009 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1998 |
| From: | Curtis J, Floyd E TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20206E000 | List: |
| References | |
| NUDOCS 9905040310 | |
| Download: ML20206E009 (95) | |
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i nlELECTRIC TU ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION l
1998 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT l
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Reviewed By:
Date:
~2!" f f Edwin T.
Floyd l
Senior Radiation Protection Technician 1
//!2/!77 Approved By:
CD Date:
John (R. Curtis I-Radiation Protection Manager l
9905040310 990429 PDR ADOCK 050004 5 R
P.O. Box 1002 Glen Rose. Texas 76043-1002 j
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TABLE OF CONTENTS SECTION PAGE L
DmtG)UCIEW.......................................................................................................1 A. Site and Station Description................................................................ 2 B. Objectives and Overview ofthe............................................................ 2 CPSES Monitoring Program IL PROGRAM IESQtIPIEON5.................................................................................. 6 A.
Sample Loc ation s................................................................................... 7 R
Sampling Methods and Proced ures................................................ 7 1.
Dimet Fadia tion....................................................................... 8 2.
Air Particulates and Air Iodine.......................................... 8 uim U
o avaiK...............................................................................................a v.
4.
Water............................................................................................9 I
5.
F1sh............................................................................................11 6.
Sh oreline Sedim ent............................................................. I 1 7.
Food Pmducts........................................................................ 1 1 8.
Broadleaf Vegetation........................................................... 12 C
Interlaboratory Comparison Program......................................... 12 D.
Deficiencies in the Sample Program........................................... 13 IIL
SUMMARY
AND DISCUSSION OF 1998 ANALYTICAL RESULTS......14 A.
Dimet Radiatinn................................................................................... 1 5 B
Air Particulates and Air Iodine...................................................... 17 C
Milk..........................................................................................................18 D.
Water........................................................................................................18 E.
F1sh...........................................................................................................20 11
F.
Sh o reli n e S e d im e n ts........................................................................ 2 0 G.
Food Products..................................................................................
H.
B ro ad le af Vege tatio n.......................................................................... 2 1 IV.
C ON C LU SION S.............................................................................................. 2 3 V.
REFERENGEL............................................................................................
VI.
DEATAN32...............................................................................................27 APPENDICES APPENDIX A Cross-Check Progmms......................................................................A-1 APPENDIX B Synopsis of Analytical Procedures................................................B-1 j
APPENDIX C Exceptions to the 1998 REMP......................................................C-1 APPENDIX D Exc e e d e d Repo rting Levels........................................................... D-1 i
l APPENDIX E Iand Use Census................................................................................. E-1 1
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LIST OF TABLES TABLE TITLE PAGE 1
CPSES Radiological Environmental......................................................... 2 8 Monitoring Program 2
Direct Radiation -- Thermoluminescent Dosimetry......................... 31 3
Concentrations of Iodine-131 in Filtered Air...................................... 33 4
Concentrations of Gross Beta Emitters in Air Particulates............ 36 j
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Concentrations of Gamma Emitters in Air Particulate Filters...... 39 1
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Concentrations of Iodine-131 in Milk.................................................... 41 i
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Concentrations of Gamma Emitters in Milk........................................ 42 l
8 Concentrations of Gamma Emitters in Groundwater....................... 43 9
Concentrations of Tritium in Groundwater.......................................... 4 4 l
10 Concentrations of Gross Beta in Water-Surface / Drinking.............. 45 l
11 Concentrations of Gamma Emitters in Water-Surface / Drinking 46 l
12 Concentrations of Iodine-131 in Water-Surface / Drinking............. 47 13 Concentrations of Tritium in Water-Surface / Drinking.................... 48 14 Concentrations of Gamma Emitters in Surface Water...................... 49 15 Concentrations of Tritium in Surface Water........................................ 51 16 Concentrations of Gamma Emitters in Fish......................................... 52 17 Concentrations of Gamma Emitters in Sediment.............................. 53 18 Concentrations of Gamma Emitters in Food Products..................... 54 19 Concentrations of Gamma Emitters in Broadleaf Vegetation........ 55 20 Radiological Environmental Monitoring Program Summary -
January 1 to December 3 1, 19 98............................................................. 5 6 iv
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i IJST OF FIGURES 1
FIGURE TITLE PAGE 1
Radiological Environmental Monitoring locations............................ 30 v
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i INTRODUCTION 1
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I, INTRODUCTION Results of the Radiological Environmental Monitoring Program for the Comanche Peak Steam Electric Station for 1998 is contained within this report.
This report covers the period from January 1, 1998 through December 31,1998 and summarizes the results of measurements and analy-ses of data obtained from samples collected during this interval.
A.
Site and Station Description Comanche Peak Steam Electric Station (CPSES) consists of two PWR units, each designed to operate at a power level of about 1150 megawatts (electrical).
The station is located on Squaw Creek Reservoir in Somervell County about forty miles southwest of Fort Worth, Texas. Unit I received a low power operating license February 8,1990 and achieved initial criticality on April 3,1990. A full power license for Unit I was issued on April 17, 1990, and commercial operation was declared on August 13, 1990. Unit 2 achieved initial criticality on March 24, 1993 and synchronized to the electrical grid on April 9,1993.
B.
Objectives and Overview of the CPSES Monitoring Program The United States Nuclear Regulatory Commission (USNRC) regu-lations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to l
l unrestricted areas as low as reasonably achievable (ALARA) (10 CFR l
50.34a). To assure that these criteria are met, each license autho-i rizing reactor operation includes technical specifications (10 CFR 50.36a) governing the release of radioactive effluents.
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monitoring is used to assure that these predetermined release limits are not exceeded. However, as a precaution against unexpected and undefined processes which might allow undue accumulation of a program for radioactivity.in any sector of the environment, 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 on radiological environmental monitoring issued by the Radiological Assessment Branch, Revision 1 (November 1979)(1), the CPSES Technical Specifications (4) and the CPSES Offsite Dose Calculation Manual j
(ODCM)(5).
In 1998, the Radiological Environmental Monitoring Program included the measurement of ambient gamma radiation by thermoluminescent dosimetry; the determination of gamma emitters in sediment and fish the determination of airborne gross beta, gamma emitters, and iodine-131: the measurement of tritium and gamma emitters in surface water; the measurement of tritium and gamma emitters in groundwater; the measurement of gross beta, tritium, iodine-131 and gamma emitters in drinking water; the determination of gamma emitters and iodine-131 in milk; and the measurement of gamma emitters in food products and gamma emitters and iodine-131 in broadleaf vegetation. Samples were collected by CPSES personnel.
Sample analyses were performed by Teledyne Brown Engineering -
l Environmental Services.
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i The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most, only a few percent 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 are divided into preoperational and operational phases. The preoperational phase of the program permits a general characterization of the radiation levels and concentrations prevailing prior to plant operation along with an indication of the degree of natural variation to be expected.
The operational phase of the program obtaine data which, when considered along with the data obtained in the preoperational phase, assist in the evaluation of Gie radiological impact of plant operation.
Preoperational measurements were conducted at CPSES from 1981 to j
1989. These preoperational measurements were performed to:
1.
Evaluate procedures, equipment and techniques.
2.
Identify potentially important pathways to be monitored after I
the the plant is in operation.
3.
Measure background levels and their variations along potentially important pathways in the area surrounding the plant.
4.
Provide baseline data for statistical comparison with future operational analytical results.
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The operational Radiological Environmental Monitoring Program is conducted to:
1.
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 i
exposure pathways.
2.
Verify the effectiveness of in-plant measures used for controlling the release of radioactive materials.
3.
Identify changes in the use of areas at and beyond the site boundat.y that may impact the principal pathways of exposure.
J This report documents the ninth 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.
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i PROGRAM DESCRIPTIONS 4
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- PROGRAM DESCRIPTIONS A
Sample Locations Seventy-five locations within a radius of 20 miles from the CPSES site were included in the monitoring program for 1998. The number and location of monitoring points were determined by considering the locations where the highest off-site environmental concentrations have been predicted from plant efiluent source terms, site hydrology, i
and site meteorological conditions.
Other factors considered were applicable regulations, population distribution, 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 use of areas surrounding the plant. If changes are identified that impact the principal pathways of exposure, appropriate changes to the radiological environmental monitoring program are implemented. The results of the 1998 Land Use Census are provided in Appendix E.
The Radiological Environmental Monitoring Program for Comanche Peak is summarized in Table 1.
R Sampling Methods and Procedures To derive meaningful and useful data from the Radiological Environmental Monitoring Prograra, sampling methods and proce-dures are required which will provide samples representative of potential pathways of the area. The methods and procedures used for each pathway monitored are described below.
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1.
Direct Radiation Thermoluminescent dosimeters (TLDs) were used to determine the direct (ambient) radiation levels at monitoring points.
- Sampling locations were chosen according to the criteria given in the USNRC Branch Technical Position on Radiological Monitoring (Revision 1. November 1979)(1) The area around the station was divided into 16 radial sectors of 22-1/2 degrees each.
TLDs were placed in all sectors.
Thermoluminescent dosimeters were located in two rings around the station. An inner ring was located at 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, l
J including two control locations. For routine TLD measurements, two dosimeters of CaSO :Dy in teflon cards were deployed at 4
each selected location. One set of dosimeters was exchanged on I
a quarterly basis and the second set was exchanged on an annual l
basis.
Additional sets of dosimeters were shipped with each exchange cycle to serve as in-transit controls.
Individual l
dosimeters were calibrated by exposure to an accurately known radiation field from a calibrated Cs-137 source.
2.
Air Particulates and Air Iodine Air particulate and air iodine samples were collected from the cight locations described in Table 1. Each air particulate sample was collected by drawing air through a 47 millimeter diameter ss-fiber filter. Air iodine was collected by drawing air through a TEDA impregnated charcoal cartridge which was connected in 8
. series behind the filter. The filters and charcoal cartridges were collected weekly by CPSES staff.
In the laboratory, air particulate filters were analyzed for gross beta activity and were composited quarterly for gamma spectrometry analysis.
Charcoal cartridges were analyzed for iodine-131.
3.
Milk Milk. samples were collected by CPSES staff monthly for January, February, November and December. March through October samples were collected every two weeks. Upon arrival at the laboratory, the milk samples were promptly analyzed for gamma emitters and for -I-131 by utilizing radiochemistry techniques.
4.
Water The CPSES staff collected water at 11 locations. Surface water was collected at four locations (N-19.3, ESE-1.4, N-1.5 and NE-7.4). 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 the return line. (Note: There have been no discharges of water from Squaw Creek Reservoir to Lake Granbury via the return line since the start up of Unit 1.) Location NE-7.4 provides samples of Lake Granbury surface water down stream of the discharge from the return line from Squaw Creek Reservoir.
A control 9
l sample is obtained from the Brazos River, upstream of Lake l
Granbury at location N-19.3.
i Surface water samples from Squaw Creek Reservoir locations were collected weekly and composited for monthly gamma I
isotopic analysis. Samples from Lake Granbury locations were collected monthly 'and analyzed by gamma spectroscopy.
All i
surface water samples were also composited quarterly by location for tritium analysis.
Surface-drinking water was collected at two locations (N-9.9 and NNW-0.1).
Samples of Squaw Creek Reservoir water were collected at location NNW-0.1. Samples from this location were analyzed pursuant t'o the drinking water requirements even l
though Squaw Creek Reservoir is not used as a potable water i
supply. Location N-9.9 was used to sample surface water from Lake Granbury near the intake of the City of Granbury potable water plant.
Surface-drinking water samples were collected weekly and composited for iodine-131 analysis, gamma isotopic and gross beta analyses monthly.
Tritium analyses were performed quarterly.
There are five groundwater locations (SSE-4.6, W-1.2, WSW-0.1, N-1.45 which are indicators and the control station, N-9.8).
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.
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i Groundwater samples were collected quarterly. Gamma isotopic and tritium analyses were performed by location.
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Eish Fish samples were collected at two locations for the 1998 program. An area 2.0 miles east-northeast of the site in Squaw Creek Reservoir was chosen as the indicator location, and a location at Lake Granbury (NNE-8) was chosen as a control location.
Fish sampling was conducted in April, May, and October for Station ENE-2.0 and NNE-8.
Fish were collected by CPSES staff.
Available edible species were gutted at the time of collection. Samples were then frozen and shipped to the laboratory for analysis. Fish were filleted in the laboratory and the edible portion analyzed by gamma spectrometry.
6.
Shoreline Sediment Shoreline sediment samples were collected in January and July from locations N-1.0 and SE-5.3.
Samples were also collected from Lake Granbury at the control location N-9.9, and location NE-7.4, which is downstream of the discharge of the return line from Squaw Creek Reservoir.
CPSES staff collected the sediment samples and shipped them to the laboratory for analysis by gamma spectrometry.
7.
Food Products
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During the period of January through October, no food samples were available.
One food sample was collected in November, 11
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none were available for December. "Ihe food product sample was collected by the CPSES stafY and shipped to the laboratory where i
l it was analyzed for gamma emitters, j
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Broadleaf Vegetation Broadleaf vegetation was collected from the control location (SW-13.5) and two indicator stations (N-1.45 and SW-1.0) near the site boundary. Collection of broadleaf vegetation started in January 1998. Broadleaf samples consisted of native grasses.
Gamma isotopic and iodine-131 analyses were performed for all broadleaf vegetation samples.
C Interlaboratory Comparison Program To demonstrate that the results of the environmental analyses are valid, the CPSES Radiological Environmental Monitoring Program requires that independent checks on the precision and accuracy of the measurements of radioactive materials in environmental sample matrices be performed. To fulfill this requirement, Teledyne Brown Engineering Environmental Services participates in the environmental sample cross-check program conducted by the U.S. Environmental Protection Agency (EPA).
Beginning with 1996 the USEPA discontinued providing milk and air particulate filter samples. For replacements, Teledyne Brown l
l Engineering Environmental Services purchased comparable spiked samples from Analytics, Inc. (see Analytics table).
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I The purpose of the interlaboratory compacison program is to provide an independent check on the laboratory's analytical procedures and to alert it to any possible problems. Participant laboratories measure the concentrations of specified radionuclides and report them to the issuing agency. The agency then furnishes the known values to the participant laboratory and specifies the control limits.
Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results of Teledyne Brown Engineering - Environmental Services' l
participation in the U.S. EPA Interlaboratory Comparison Program and the Analytic's program for 1998 are provided in Appendix A.
D.
DeSciencies in the Sample Program In accordance with section 6.9.1.3 of the ODCM(5), any deviations from the sampling schedule of Table 3.12.1 of the ODCM shall be reported in the annual environmental monitoring report. Appendix C contains a listing of all deviations of the sampling schedule Deficiencies in the program are deviations from the sampling schedule that should have been preventable by CPSES staff. There was one deficiency during 1998. The air sample pump at S/SSW-1.2 (A-5) was found off, with only 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> of run time for the previous week. The electrical plug had worked loose or had not been connected properly.
The pump was restarted upon discovery.
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SUMMARY
AND DISCUSSION OF 199S ANALYTICAL RESULTS 14
III.
SUMMARY
AND DISCUSSION OF 1998 ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below.
The proce-dures and specifications followed in the laboratories for these analyses are as required in the Teledyne Brown Engineering Environmental Services Quality Assurance Manual IWL-0032-395 and are detailed in Teledyne Brown Engineering - Environmental Services Analytical Procedures Manual.
A synopsis of analytical procedures is contained in Appendix B of this report.
Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measurement methods as discussed in NCRP Report No. 50(2). The use of
"<" in the data tables symbolizes that the result is less than the lower limit of detection (LLD) as defined in Appendix B. The Teledyne Brown Engineering
- Environmental Services analytical methods meet the LLD requirements addressed in the CPSES Offsite Dose Calculation Manual.
Tables 2 through 19 give the radioanalytical results for individual samples. A statistical summary of the results appears in Table 20.
The reporterl averages are based only on concentrations above the limit of detection. In Table 20, the fraction (f) of the total number of analyses with detectable activity follows in parentheses. Also given in parentheses are the minimum and maximum values of detectable activity during the report j
period.
A.
Direct Rad 4% ion Environmental radiation dose rates determined by thermoluminescent dosimeters (TLDs) are given in Table 2.
Thermoluminescent dosimetry badges with four readout areas each were deployed at each 15
location on quarterly and annual cycles.
The mean values of four readings (corrected individually for response to a known dose and for in-transit exposure) are reported.
A statistical summary of the 1998 data is included in Table 20. For the quarterly analyses the average dose rate of the control locations was 0.11 mR/ day with a range of 0.104-0.13 mR/ day. The average of the indicator locations for the quarterly samples was 0.11 mR/ day with a range of 0.06 to 0.15 mR/ day. For the annual samples, the average dose rate for the control samples was 0.10 mR/ day. The indicator locations had an average of 0.10 mR/ day with a range of 0.061-0.132 mR/ day.
Oakley(3) calculates an ionizing background radiation dose equivalent of 82.2 mR/ year for Fort Worth including a terrestrial component of 45.6 mR/ year and an ionizing cosmic ray component of 36.6 mR/ year (excludes neutron component).
Since Oakley's values represent averages covering wide geographical areas, the measured ambient I
radiation average of 40.2 mR/ year for the immediate locale of CPSES is consistent with Oakley's observations.
Significant variations occur between geographical areas as a result of geological composition and altitude differences.
Temporal variations result from changes in cosmic ray intensity, local human activities, and factors such as ground cover and soll moisture.
Anomalies in the 1998 measured doses relative to preoperational data were not noted.
For 1989, the averages for the indicator locations were 0.16 mR/ day (range of 0.11 to 0.22) and 0.13 mR/ day (range of 16
0.11 to 0.17), for the quarterly and annual samples respectively. The l
1988 averages for the quarterly and annual indicator locations were 0.16 mR/ day (range of 0.10 to 0.20) and 0.15 mR/ day (range of 0.12 to 0.18) respectively.
R Air Particulates and Air Iodine A total of 414 charcoal cartridges were analyzed for airborne iodine-131 by gamma spectrometry. No iodine-131 was detected at any of the sampling stations. Results of these measurements are presented in Table 3.
A total of 414 air particulate filters were collected and analyzed for gross beta activity. For 1998 the average gross beta activity for the control location was 0.018 pC1/m3 with a range from 0.007 to 0.036 pCi/m3 For the seven indicator locations the yearly average was 0.020 pC1/m3 with a range from 0.008 to 0.040 pC1/m3 The gross beta analysis data are presented in Table 4.
Anomalies in gross beta measurements relative to preoperational data were not noted.
Air filters were composited quarterly and then analyzed by gamma spectrometry. The gamma spectrometry data is presented in Table 5.
Cosmogenic beryllium-7 was detected in all 32 samples. The average beryllium-7 activity for the control location was 0.078 pC1/m3 with a range of 0.066-0.091 pC1/m3 For the indicator locations, the average beryllium-7 activity was 0.083 pCi/m3 with a range of 0.066 to 0.111 pC1/m3 Potassium-40, a naturally occurring nuclide, was measured in thirteen samples. 'lhe average potassium-40 for the control location was 0.009 pC1/m3 with a range of 0.006 to 0.013 The average 17
potassium-40 activity for the indicator locations was 0.008 pC1/m3 with a range of 0.005-0.013 pC1/m3 C
Rguk A total of 21 milk samples were collected in 1998. All samples were analyzed for iodine-131 by radiochemistry and for other gamma emitting isotopes by gamma spectrometry.
Results of these measurements are presented in Table 6 and 7.
No iodine-131 was found in any of the milk samples. The lower limits of detection can be found in Table 6.
Results of the gamma spectrometry measurements are presented in Table 7.
Naturally occurring potassium-40 was detected in all of the I
milk samples. The average activity for the control locatiam was 1339
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I pCi/l with a range of 1180 to 1470 pCi/l. Cesium-134, Cs-137 and La-140/Ba-140 were not detected in any of the samples.
The lower i
limits of detection can be found in Table 7.
D.
Water Groundwater samples were collected from five locations during 1998.
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The samples were analyzed for gamma emitters and tritium on a i
quarterly basis, pursuant to the ODCM requirements for groundwater.
Twenty samples were analyzed for gamma emitters by gamma spectrometry.
Potassium-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65, Nb/Zr-95, Cs-134, Cs-137 and Ba/La-140 were not detected in any of the samples.
Quarterly samples for each sampling location were analyzed for tritium.
Tritium was detected in one sample with a concentration of 910 pCi/1.
On-site and Teledyne reanalysis of this 18
1 ground water location showed no detectable tritium and this sample was considered to be in error. Results of these analyses are contained in Table 8 and 9 respectively.
Surface-drinking water was collected from two stations. All samples were analyzed for gamma emitters; results were below the lower limit of detection.
Twenty-four samples were~ analyzed for gross beta activity. The indicator station had an average activity of 19.5 pCi/l with a range of 13 to 23 pCi/1. The control station had an average activity of 8.94 pC1/1 with a range of 5.5 to 14 pCi/1. Eight quarterly I
composites were analyzed for tritium. The indicator station had an average activity of 10750 pC1/1 with a range of 10000 to 11000 pCi/1.
The control station showed no tritium activity above the lower limit of detection. Iodine-131 analyses by radiochemistry were performed on 4
1 24 samples of surface-drinking water; there was no measurable activity. Results of these analyses are contained in Tables 10 through 4
13.
Surface water was sampled from four locations during 1998. Samples were analyzed for gamma isotopic on a monthly basis (composite (2) and monthly (2)) and tritium composites on a quarterly basis. Forty-eight samples were analyzed by gamma spectrometry. Results of these analyses were below the lower limit of detection. Sixteen composited surface water samples were analyzed for tritium.
The indicator stations had an average activity of 11000 pCi/l with a range of 11000-11000 pCi/1. The results of these analyses can be found in Table 14 and 15 respectively. The tritium detected in Squaw Creek Reservoir samples of surface water and surface-drinking water is attributed to 19
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liquid effluent discharges from CPSES.
The level of tritium in the Squaw Creek Reservoir is within the expected value predicted in the CPSES Final Safety Analysis Report.
E.
Bah The results of gamma isotopic analyses of fish samples collected during 1998 are presented in Table 16. A total of eight samples were analyzed, four from the indicator location (ENE-2) and four from the control location (NNE-8). Sampling efforts concentrated on the larger edible species of commercial and/or recreational importance.
Cesium-137 was not detected in any of the samples. Preoperational I
levels have ranged from 3 to 39 pCi/kg wet on thirteen different i
occasions.
Naturally occurring potassium-40 was detected in all samples.
The average potassium-40 concentration for the four in-dicator samples is 2840 pCi/kg wet with a range of 2160 to 3540 pC1/kg wet.
The average concentration for the control location is 3005 pCi/kg wet with a range of 2230 to 3460 pCi/kg wet. No other gamma emitters were detected in any samples.
F.
Shoreline Sediments l
The processes by which radionuclides and stable elements are con-j centrated in bottom sediments are complex, involving physiochemical interaction in the environment between the various organic and
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inorganic materials from the watershed.
These interactions can proceed by a myriad of steps in which the elements are absorbed in or displaced from the surfaces of colloidal particles enriched with chelating organic materials. Biological action of bacteria and other 20 i
benthie organisms also contribute to the concentration of certain elements and in the acceleration of the sedimentation process.
l Results of the gamma isotopic analyses of the sediments sampled from the CPSES environment are given in Table 17.
For 1998 four locations, one control and three indicators, were sampled.
I Naturally occurring gamma emitters found in detectable i
concentrations were Be-7, K-40, Pb-212, Bi-214, Pb-214, Ra-226 and i
Th-228. Cesium-137 was measured in one sample, from an indicator 1
station, with an activity of 25.1 pC1/kg dry. This is lower than the two measurements from 1997 with an average activity of 48 pCi/kg.
l Preoperational levels of cesium-137 ranged from 9.2 to 150 pCi/kg on four different occasions.
G.
Food Products l
Results of gamma isotopic analyses of food samples are contained in i
Table 18. One sample was obtained from the pecan harvest at ENE-9.0.
Potassium-40, a naturally occurring isotope, was found in the sample. For the indicator location the potassium-40 activity was 3090 t
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l pC1/kg wet. Naturally occurring beryllium-7 was not detected. Iodine-l 131, Cs-134 and Cs-137 were not detected in food products during 1998. The number of samples available in 1998 was low due to an i
abnormally wet spring and extremely dry summer.
H.
BroadleafVegetation Results of gamma isotopic analyses of broadleaf vegetation samples are contained in Table 19. A total of 36 samples were analyzed from three locations. Potassium-40, a naturally occurring isotope, was found in all 21 j
36 samples. The average potassium-40 activity for the control location was 5450 pCl/kg wet with a range of 3060 to 7830 pCi/kg wet. For the indicator locations the average potassium-40 activity was 3243 pCi/kg wet with a range of 617 to 6120 pCi/kg wet.
Naturally occurring beryllium-7 was detected in the twenty-four indicator samples with an average activity of 4541 pC1/kg wet; the range was l
378 to 15100 pC1/kg wet.
Beryllium-7 was detected in the 12 l
samples from control station SW-13.5 with an average activity of 1230 pCi/kg wet and a range of 215 to 4150 pCi/kg wet.
Thorium-228 was detected at one indicator location with an average activity of 143 pCi/kg wet and a range of 44.3 to 242 pCi/kg wet.
Iodine-131, cesium-134 and cesium-137 were below the lower limit of detection in all samples.
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CONCLUSIONS l
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IV.
CONCLUSIONS It is concluded from the levels obtained in environmental samples during 1998 and comparison of these levels to preoperational measurements and operational controls, that the operation of CPSES in 1998 resulted in no changes in measureable levels of radiation or radioactive materials in the environment except for the tritum detected in Squaw Creek Reservoir which leveled out during 1998 to approximately 11000 pCi/1.
The atmospheric environment was sampled for airborne particulate matter, radiciodine and direct radiation.
The terrestrial i
environment was sampled using milk, groundwater, surface drinking water, food products and broadleaf vegetation samples. The aquatic environment was sampled using surface water, fish and shoreline sediment samples. The analyses of these samples provided results which were either below the measurement detection limits or were indicative of natural terrestrial and cosmic ray radiation levels, except for the tritium in the surface water of Squaw Creek Reservoir which was below the reporting levels for radioactivity concentrations in environmental samples.
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l REFERENCES l
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REFERENCES 1.
U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program", Radiological Assessment Branch Technical Position, November 1979, Rev.1 2.
National Council on Radiation Protection and Measurements,
" Environmental Radiation Measurements", NCRP Report No. 50, Washington, D.C., December 27,1976 3.
- Oakley, D.C., " Natural Radiation Exposure in the United States",
ORP/SID 72-1 Office of Radiation Programs, U.S. Environmental Protection Agency, Washington, D.C., June 1972 1
4.
Comanche Peak Steam Electric Station Units 1 and 2 Technical Specifications 5.
Offsite Dose Calculation Manual For TU Electric Comanche Peak Steam Electric Station Units 1 and 2.
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FIGURE 1 i
RADIOLOGICAL ENVIRONMENTAL MONITORING LOCATIONS SAMPLING LOCATION SAMPLE SAMPLING LOCATION SAMPLE POINT (SECTOR-MILE)
TYPE
- POINT (SECTOR-MILE)
TYPE
- j 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
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R31 WSW-5.35 R
A5 S/SSW-1.2 A
R32 WSW-7.0 R
l A6 SW-12.3 A
R33 W-1.0 R
A7 SW/WSW-0.95 A
R34 W-2.0 R
l A8 NW-1.0 A
R35 W-5.5 R
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R37 W N W-5.0 R
R38 WNW-6.7 R
R39 NW-1.0 R
R40 NW-5.7 R
R1 N-1.45 R
R41 NW-9.9 R
i R2 N-4.4 R
R42 NNW-1.35 R
R3 N-6.5 R
R43 NNW-4.6 R
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R4 N-9.4 R
SW1 N-1.5 SW R5 NNE-1.1 R
SW2 N-9.9 SW/DW R6 NNE-5.65 R
SW4 NE 7.4 SW R8 NE-4.8 R
SW5 ESE-1.4 SW R9 ENE-2.5 R
SW6 NNW-0.1 SW/DW j
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R11 E-0.5 R
GW2 WSW-0.1 GW/DW R12 E-1.9 R
GW3 SSE-4.6 GW/DW R13 E-3.5 R
GW4 N-9.8 GW/DW R14 E-4.2 R
GW5 N-1.45 GW/DW R15 ESE-1.4 R
SS1 NNE-1.0 SS R16 ESE-4.7 R
SS3 NE-7.4 SS i
R18 SE-3.85 R
M4 SW-14.5 M
R20 SSE 1.3 R
F1 ENE-2.0 F
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F2 NNE-8.0 F
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FP1 ENE-9.0 FP R23 S-1.5 R.
FP5 SW-12.7 FP R24 S-4.2 R
FP6 E-3.5 FP t
l R25 SSW-1,1 R
BL1 N-1.45 BL R26 SSW-4.4 R
BL2 SW-1.0 BL R27 SW-0.9 R
BL3 SW-13.5 BL TYPE
- A - AIR SAMPLE GW -GROUNDWATER F - FISH R -DIRECT RADIATION SS -SHORELINE SEDIMENT FP -FOOD PRODUCT SW -SURFACE WATER M - MILK BL -BROADLEAFVEGETATION DW - DRINKING WATER 30 l
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TABLE 6 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF 1-131 IN MILK Results in pCi/l 2 s.d.
COLLECTION MONTH DATE SW-14.5 JANUARY 01/27/98
<0.1 FEBRUARY 02/24/98
<0.2 MARCH 03/10/98
<0.1 03/24/98
<0.2 APRIL 04/07/98
< 0. 2 04/21/98
<0.1 MAY 05/05/98
<0.3 05/19/98
<0.1 JUNE 06/02/98
<0.1 06/16/98
<0.1 06/30/98
<0.3 JULY 07/14/98
<0. 2 0'7/28/98
<0.2 AUGCST 08/11/98
<0.2 08/25/98
<0.4 SEPTEMBER 09/08/98
<0.2 09/22/98
<0.2 i
OCTOBER 10/06/98
<0.2 10/20/98
<0. 2 NOVEMBER 11/24/98
< 0. 2 l
DECEMBER 12/29/98
<0.2 41 u
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i TABLE 9 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER Results in pC1/1i 2 s.d.
COLLECTION TRITIUM OUARTER DATE LCCATION ACTIVITY 1
04/01/98 W-1.2
<1000 04/01/98 SSE-4.6
<1000 04/01/98 N-1.45
<1000 04/01/98 WSW-0.1
<1000 04/01/98 N-9.8
<1000 2
06/30/98 W-1.2
<2000 06/30/98 SSE-4.6
<2000 06/30/98 N-1.45
<2000 06/30/98 WSW-0.1
<2000 06/30/98 N-9.8
<2000 3
09/29/98 W-1.2
<800 09/29/98 SSE-4.
<800 09/29/98 N-1.45 910 i' 520 (a) 09/29/98 WSW-0.1
<800 09/29/98 N-9.8
<800 4
12/29/98 W-1.2
<1000 12/29/98 SSE-4.6
<1000 12/29/98 N-1.45
<1000 12/29/98 WSW-0.1
<1000 j
12/29/98 N-9.8
<1000 (a) Reanalysis performed 11/06/98 indicating < 1000 pCi/1. Original sample results in error.
Confirmatory samples by CPSES indicated < 300 pCi/1.
44 I
TABLE 10 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS of GROSS BETA IN WATER-SURFACE / DRINKING Results in pC1/1 i 2 s.d.
COLLECTION MONTH DATE NNW-0.1 N-9.9 JANUARY 01/06/98-01/27/98 18 i 3 6.2 2.0 l
FEBRUARY 02/03/98-02/24/98 19 i 4 9.7 i 2.9 MARCH 03/03/98-03/31/98 22 i 4 8.6 2.2 APRIL 04/07/98-04/28/98 22 i 4 8.7 2.3 MAY 05/05/98-05/26/98 15 3
5.5 1.8 JUNE 06/02/98-06/30/98 20 4
8.0 2.7 JULY 07/07/98-07/28/98 23 i 4 14 i 3 AUGUST 08/04/98-08/25/98 21 i 4 12 i 3 SEPTEMBER 09/01/98-09/29/98 21 4
13 i 3 OCTOBER 10/06/98-10/27/98 13 3
8.3 2.9 NOVEMBER 11/03/98-11/24/98 18 4
6.1 2.2 DECEMBER 12/01/98-12/29/98 22 i 4 7.2 2.3 45
04 1
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r; TABLE 12 l
T U ELECTRIC l
COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN WATER-SURFACE / DRINKING Results in pC1/1 2 s.d.
COLLECTION MONTH DATE NNW-0. i N-9.9 JANUARY 01/06/98-01/27/98
< 0.5
< 0.4 FEBRUARY 02/03/98-02/24/98
< 0.4
< 0.5 MARCH 03/03/98-03/31/98
< 0.5
< 0.5 APRIL 04/07/98-04/28/98
< 0.6
< 0.7 MAY 05/05/98-05/26/98
< 0.5
< 0.5 JUNE 06/02/98-06/30/98
< 0.6
< 0.7 JULY 07/07/98-07/28/98
< 0.6
< 0.5 AUGUST 08/04/98-08/25/98
< 0.8
< 0.7 SEPTEMBER 09/01/98-09/29/98
< 0.8
< 1.0 OCTOBER 10/06/98-10/27/98
< 0.8
< 0.8 NOVEMBER 11/03/98-11/24/98
< 0.4
< 0.7 DECEMBER 12/01/98-12/29/98
< 0.7
< 0.7 i
1 47
TABLE 13 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN WATER-SURFACE / DRINKING Results in pC1/112 s.d.
COLLECTION OUARTER PERIOD NNW-0.1 N-9.9 1
01/06/98-03/31/98 11000 i 1000
< 100 2
04/07/98-06/30/98 11000 i 1000
< 200 3
07/07/98-09/29/98 11000 1000
< 300 4
10/06/98-12/29/98 10000 i 1000
< 200
\\
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48
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\\
l APPENDIX A 4
CROSS CHECK PROGRAM A-1
Interlaboratory Comparison Program Teledyne Brown Engineering participates in the EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the program for all radioactive isotopes prepared and at the maximum frequency of availability. Beginning with 1996 the EPA discontinued providing milk and air particulate filter samples. For replacements, we have purchased comparable spiked samples from Analytics,Inc.
In this section the 1998 data summary tables are presented for isotopes in the various sample media applicable to the Comanche Peak Steam Electric Station's Radiological Environmental Monitoring Program. The footnotes of the table discuss investigations of problems encountered in a few cases and the steps taken to prevent reoccurrence.
A-2 f
i
g I
EPA INTERLABORATORY COMPARISON PROGRAM 1998 Environmental i
Collection Teledyne Brown Date Media Nuclide EPA Result (a)
Engineering Result (b)
Deviation (c) 01/16/98 Water Sr-89 8.0 i 5.0 5.00 i 1.73
-1.04 Sr-90 32.0 i 5.0 31.67 i 0.58
-0.12 01/30/98 Water Gr-Alpha 30.5i 7.6 33.00 i 2.65 0.57 Gr-Beta 3.9 i 5.0 5.60 1 0.90 0.59 j
02/06/98 Water I-131 104.9 i 10.5 110.00 i 0.00 0.84 02/13/98 Water Ra-226 16.0 1 2.4 14.67 i 0.58
-0.96 Ra-228 33.3 i 8.3 32.00 1 2.00
-0.27 03/13/98 Water H-3 2155.0 i 348.0 1833.33 i 57.74
-1.60 04/21/98 Water Gr-Alpha 54.4 t 13.6 50.00 i 1.73
-0.56 Ra-226 15.0 i 2.3 15.00 i 0.00 0.00 Ra-228 9.3 i 2.3 8.50 1 0.20
-0.60 Gr-Beta 94.7 i 10.0 102.00 i 6.56 1.26 Sr-89 6.0 i 5.0 4.67 i 1.15
-0.46 Sr-90 18.0 i 5.0 21.67 i 1.15 1.27 Co-60 50.0 i 5.0 52.33 i 1.53 0.81 Cs-134 22.0 i 5.0 21.00 i 1.00
-0.35 Cs-137 10.0 5.0 11.67 i 0.58 0.58 06/05/98 Water Co-60 12.0 i 5.0 13.00 i 1.00 0.35 Zn-65 104.0 i 10.0 111.67 i 2.52 1.33 Cs-134 31.0 i 5.0 32.33 i 0.58 0.46 Cs-137 35.0i 5.0 37.67 1 2.08 0.92 Ba-133 40.0 i 5.0 35.00
- 2.65
-1.73 06/12/98 Water Ra-226 4.9 i 0.7 4.47 i 0.85
-1.07 Ra 228 2.1 i 0.5 1.93 1 0.21
-0.58 07/17/98 Water Sr-89 21.0 1 5.0 21.00 i 1.00 0.00 Sr-90 7.0 i 5.0 6.33 i 0.58
-0.23 07/24/98 Water Gr-Alpha 7.2 5.0 5.43 i 0.64
-0.61 Gr-Beta 12.8 i 5.0 14.67 i 2.08 0.65 08/07/98 Water H-3 17996.0 i 1800.0 16000.00 i 0.00
-1.92 09/11/98 Water 1-131 6.l i 2.0 5.93 I 0.55
-0.14 09/18/98 Water Ra-226 1.7 i 0.3 1.53 i 0.46
-0.96 Ra-228 5.7 i 1.4 6.70 i 0.35 1.24 10/20/98 Water Gr-Beta 94.0 i 10.0 74.67 i 7.64
-3.35 (d)
Sr-89 19.0 5.0 18.33 i 1.53
-0.23 Sr-90 8.0 i 5.0 8.33 i 1.15 0.12 Co-60 21.0 i 5.0 22.33 i 1.15 0.46 l
I Cs-134 6.0 1 5.0 6.67 0.58 0.23 Cs-137 50.0 t 5.0 56.33 i 3.79 2.19 (e)
A-3
EPA INTERLABORATORY COMPARISON PROGRAM 1998 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (a)
Engineering Result (b)
Deviation (c) 10/20/98 Gr-Alpha 30.1 i 7.5 21.67 i 2.31
-1.95 Ra-226 4.5 i 0.7 4.67 i 0.25 0.41 Ra-228 1.5 1 0.4 1.9 i 0.20 1.73 11/11/98 Water Co-60 38.0 i 5.0 39.67 i 2.52 0.58 Zn-65 131.0 i 13.0 140.67 i 10.97 1.29 Cs-134 105.0 5.0 103.00 1 2.00
-0.69 Cs-137 111.0 i 6.0 115.33 i 1.53 1.25 Ba 133 56.0 i 6.0 46.33 1 2.52
-2.79 (e)
Footnotes:
(a)
EPA Results-Expected laboratory precision (1 sigma). Units are pCl/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters.
(b)
Teledyne Results - Average i one sigma. Units are pCl/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters.
(c)
Normalized deviation from the known.
(d)
The special EPA instructions concerning multiple evaporation with concentrated nitric acid (to purge chlorides derived from hcl preservative) were omitted by oversight. The chlorides cause greater self absorption and lead to lower results. Two additional aliquots using two evaporations with concentrated nitric acid were analyzed. The results, when corrected for decay of Sr-89, were 87 and 83 pCl/ liter which compare favorably with the EPA result.
(e)
An investigation is being conducted; results will be available shortly.
l l
A-4 1
r-i f
l ANALYTICS CROSS CHECK COMPARISON PROGRAM 1998 Teledyne Brown Analytics
%mple ID Media Nuclide Engineering Result (a)
Result Ratio (b)
E1346-396 Milk 1131 87 2 9
82 4
1.06 TI#71657 Ce-141 66
- 7 70 2 4
0.94 03/12/98 Cr-51 220 30 201 10 1.09 Cs-134 85 2 9
84 4
1.01 Cs-137 180 2 20 161 2 8
1.12 Mn-54 130 10 133 7
0.98 Fe-59 110 2 10 95 5
1.16 Zn-65 160 20 142 2 7
1.13 CO-60 82
- 8 85 2 4
0.96 E1460-396 Milk I-131 68 2 7
67 2 3
1.01 j
TI #78921 Ce-141 94 9
99 2 5
0.95 06/11/98 Cr-51 97 31 132 2 7
0.73 Cs-134 101 10 95 2 5
1.06 Cs-137 79 8
70 2 4
1.13 Mn-54 112 11 106 2 5
1.06 Fe-59 58 2 9
45 2
1.29 Zn-65 143 14 122 2 6
1.17 CO-60 157 2 16 143 7
1.10 E1630-396 Milk 1-131 65
- 1 71
- 4 0.92 TI#94881 Ce-141 647 65 746 2 37 0.87 12/14/98 Cr 51 900 90 979 2 49 0.92 Cs-134 200 20 220 2 11 0.91 Cs-137 1772 18 183 2 9
0.97 Mn 54 136 14 142t 7
0.96 Fe-59 156 2 16 148 7
1.05 Zn-65 132
- 14 140 7
0.94 CO-60 169 17 178 2 9
0.95 Sr-89 20 2
69 2 3
0.29 (c)
Sr-90 16 1
41 2
0.39 (c)
E1631-396 Filter Ce-141 566 2 57 5242 26 1.08 T1#94882 Cr-51 800 80 687 49 1.16 12/14/98 Cs-134 147 15 154 2 8
0.95 Cs-137 158 16 128 6
1.23 Mn-54 122 12 100 5
1.22 Fe-59 134 13 104 5
1.29 Zn-65 129 2 13 98 5
1.32 CO-60 134 13 125 6
1.07 E1632-396 Water H3 5500 200 5980 299 0.92 l
T1#94883 f
12/14/98 E1633-396 Water Am-241 8.3 1.5 7.9 2 0.4 1.05 f
T1#94884 Pu-239 9.8 1.8 8.9 2 0.4 1.10 l
12/14/98 A-5
Footnotes:
(a)
Teledyne Results - counting error is two standard deviations. Units are pC1/ liter for water and milk. For gamma results, if two standard deviations are less than 10%, then a 10% error is reported. Units are total pCi for air particulate filters.
(b)
Ratio of Teledyne Brown Engineering to Analytics results. Acceptance criteria are based on USNRC acceptance criteria described in USNRC Procedure 84750 dated March 15,1994.
(c)
An investigation is being conducted; results will be available shortly.
ll 1
)
l I
s l
l A-6 j
i i
I APPENDIX B SYNOPSIS OF ANALYTICAL PROCEDURES B-1 t-
ANALYTICAL PROCEDURES SYNOPSIS Appendix B is a synopsis of the analytical procedures performed during 1998 on samples collected for the Comanche Peak Steam Electric Station's Radiological Environmental Monitoring Program.
All analyses have been mutually agreed upon by Texas. Utilities and Teledyne Brown Engineering and include those recommended by the USNRC Regulatory Guide 4.8,BTP, Rev.1.
November 1979.
ANALYSIS TITLE PAGE Gross Beta Analysis of Air Particulate Samples......................... B-3 Gross Beta Analysis of Water Samples................................ B-4 Analysis of Samples for Tritium (Liquid Scintillation)................... B-5 Analysis of Samples for Iodine-131.................................. B-6 M ilk o r Wa te r............................................... B - 6 i
Gamma Spectrometry of Samples.................................... B-7 M ilk an d Wa te r.............................................. B - 7 Dried Solids other than Soils and Sediment...................... B-7 Fish........................................................B-7 Soils and Sediments.......................................... B-7 Charcoal Cartridges (Air Iodine)................................ B-7 Airborne Particulates......................................... B-7 Environmental Dosimetry.......................................... B-9 i
B-2 L
p.
l l
GROSS BETA ANALYSIS OF SAMPLES Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron)
' daughter products to decay, the filters are counted in a gas-flow proportion ' counter. An unused air particulate filter, supplied by the customer,is counted as the blank.
Calculations of the results, the two sigma error and the lower limit of detection (LLD):
RESULT (pCi/m3)
((S/r)-(B/t))/(2.22 V E)
=
3 2((S/r2) + (B/t ))l/2 (2.22 V E) 2
/
TWO SIGMA ERROR (pCi/m )
=
LLD (pCi/m3) 4.66 (B10)/(2.22 V E t)
=
where:
S
=
Gross counts of auple including blank B
Counts of blank
=
Counting efficiency E
=
Number of minutes sampl; was counted T
=
Number of minutes blank was counted t
=
Sample aliquot size (cubic meters)
V
=
i B-3
DETERMINATION OF GROSS BETA ACTIVITY IN WATER SAMPLES Introduction The procedures descrioed in this section am used to measure the overall radioactivity of.
-water samples without identifying the radioactive species present..No chemical separation
- techniques are involved.
One literof the sample is evaporated on a hot plate. A smaller volume may be used if the sample has a significant salt content as measured by a conductivity meter. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.
After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchette which is stamped with a concentric rmg pattem to distribute residue evenly. Final evaporation to dryness takes place under heat lamps.
Residue mass is determined by weighing the planchette before and after mounting the sample. The planchette is counted for beta activity on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efficiency caused by the residue mass.
Detection Capability.
Detection capability depends upon the sample volume actually represented on the planchette, the background and the efficiency of the counting instrument, and upon self-absorption of beta particles by the mounted sample. Because the radioactive species are not identified, no decay
- corrections are made and the reported activity refers to the counting time.
The minimum detectable level (MDL) for water samples is nominally 1.6 picoCuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 sigma level), assuming that I liter of I
sample is used and that p gram of sample residue is mounted on the planchette. These figures am based upon a counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively.
The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoCuries per liter. These values reflect a beta counting efficiency of 0.38.
B-4
ANALYSIS OF SAMPLES FOR TRITIUM (Liquid Scintillation)
Entsc -
Ten milliliters of water are mixed with 10 ml of a liquid scintillation " cocktail" and then the mixture is counted in an automatic liquid scintillator, Calculation of the results, the two sigma error and the lower limit detection (LLD) in pCi/l:
RESULT (N-B)/(2.22 V E)
=
2((N + B)/At) /2 (2.22 V E)
TWO SIGMA ERROR
/
=
4.66 (B/At)1/2 '2.22 V E )
/
=
the gross cpm of the sample where:
N
=
the background of the detector in cpm B
=
conversion factor changing dpm to pCi 2.22
=
volume of the samp!e in ml V
=
efficiency of the detector E
=
counting time for the sample At
=
]
l B-5 1
p 1
l ANALYSIS OF SAMPLES FOR 10 DINE 131 I
Milk or Water a
Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove iodine from the sample. The iodine is then stripped from
. the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchette for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.
Calculations of results, two sigma error and the hwer limit of detection (LLD) in pCi/l:
(N/At B)/(2.22 E V Y DF)
RESULT
=
2((N/At+B)/At)l/2 (2.22 E V Y DF)
/
TWO SIGMA ERROR
=
= 4.66(B/At)l/2 (2.22 E V Y DF)
/
I1D
=
total counts from sample (counts) when::
N
=
counting time for sample (min)
At
=
background rate of counter (epm)
B
=
dprn/pCi 2.22
=
volume or weight of sample analyzed V
=
chemical yield of the mount or sample counted Y
=
decay factor from the collection to the counting date DF
=
efficiency of the counter for 1-131, corrected for self E
=
absorption effects by the formula i
E (exp-0.006iM)/(exp-0.0061M )
E
=
s 3
efficiency of the counter determined from an I 131 E,
.=
standard mount mass of Pdl2 n the standard mount, mg Ms
=
mass of PD1 on the sample mount, mg M
=
2 B-6 e
GAMMA SPECTROMETRY OF SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer. based data acquisition system which performs pulse height analysis.
Dried Solids Other Than Soils and Sediments A large quantity of the sample is dried at a low temperature, less than 100 C. As much as possible (up to the total sample)is loaded into a tared 1-liter Marinelli and weighed. The sample is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The san.ple is then counted for approximately 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Soils and Sediments Soils and sediments = dried at a low temperature, less than 100 C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for approximately six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height and analysis.
Charcoal Cartridges (Air Iodine)
Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector. Each Ge(Li) detector is calibrated for both positions. The detection limit for I-131 of each charcoal cartridge can be determined (assuming no positive I-131) uniquely from the volume of air which passed through it. In the event I-131 is observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.
Air Particulate The thirteen airborne particulate filters for a quarterly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li)
B-7
detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, halflife, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume of pCi/ mass:
(S-B)/(2.22 t E V F DF)
RESULT
=
2(S+B)l/2 (2.22 t E V F DF)
/
TWO SIGMA ERROR
=
4.66(B)l/2 (2.22 t E V F DF)
/
1.LD
=
Area, in counts, of sample peak and background where:
S
=
(region of spectrum ofinterest)
Background area, in counts, under sample peak, B
=
determined by a linear interpolation of the representative backgrounds on either side of the peak length of time in minutes the sample was counted t
=
dpm/pCi 2.22
=
detector efficiency for energy of interest E
=
and geometry of sample sample aliquot size (liters, cubic meters, kilograms, V
=
or grams) fractional gamma abundance (specific for each F
=
emitted gamma) decay factor from the mid-collection date to the DF
=
counting date i
l B
- L l
l i
ENVIRONMENTAL DOSIMETRY Teledyne Brown Engineering uses a CaSO :Dy thermoluminescent dosimeter (TLD) which 4
l.
the company manufactures. This material has a high light output, negligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.
Following the field exposure period the TLDs are placed in a Teledyne Brown Engineering l
Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission l
(luminescence) is recorded. The TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This provides a calibration of each area of each TLD after every field use.
The transit controls are read in the same manner.
Calculations of results and the two sigma error in net milliroentgen (mR):
D = (D +D +D +D )/4 RESULT g
2 3 4
=
2((D -D)2+(9 -D)2+(9 9)2+(9 9)2)/3)l/2 TWO SIGMA ERROR g
2 3
4
=
the net mR of area 1 of the TLD, and similarly for D, D, and D4 2 3 WHERE:
D
=
j I K/R g - A D1 l
I;
=, the instrument reading of the field dose in area i the known exposure by the Cs-137 source K
=
the instrument reading due to the Cs-137 dose on area 1 R
=
g average dose in mR, calculated in similar manner as above, A
=
of the transit control TLDs the average net mR of all 4 areas of the TLD.-
D
=
l
{
B-9 l
E i
f'
)
l l
l I
APPENDIX C EXCEPTIONS TO TIIE 1998 REMP 1
l C-1
APPENDIX C CPage Icf 2)
RADIOLOGICAL ENVIRONMENTAL MONTIORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1998 DA'IE OF REASONS FORIDSS/
IDCA'I10N DNMP110N SAMPl]NG EXCEPTION ESE-4.7 Direct Radiation 04/01/98-07/01/98 TLD missing (Qtrly)
SSE-4.4 Direct Radiation 01/07/98-04/01/98
'1LD missing (Qtrly)
WSW-5.35 Direct Radiation 01/07/98-04/01/98 TLD missing (Qtrly)
NW-5.7 Direct Radiation 07/01/98-10/01/98 TLD missing (Qtrly)
ESE-4.7 Direct Radiation 01/07/98-01/04/99
'ILD missing (Annual)
SSE-4.4 Direct Radiation 01/07/98-01/04/99
'ILD missing (Annual)
NW-5.7 Direct Radiation 01/07/98-01/04/99 TLD missing (Annual)
S/SSW-1.2 Charcoal Filters 03/31/98-04/07/98 Sample pump connection loose 1
SW-12.3 Charcoal Filters 06/23/984 6/30/98 Sample pump failure S/SSW-1.2 Air Particulates 03/31/98-04/07/98 Sample pump connection loose SW-12.3 Air Particulates 06/23/98-06/30/98 Sample pump failure SW-12.7 Food 01/27/98 Sample not available l
E-3.5 Food 01/27/98 Sample not available SW-12.7 Food 02/24/98 Sample not available E-3.5 Food 02/24/98 Sample not available SW-12.7 Food 03/31/98 Sample not available E-3.5 Food 03/31/98 Sample not available SW 12.7 Food 04/28/98 Sample not available E-3.5 Food 04/28/98 Sample not available SW-12.7 Food 05/26/98 Sample not available E-3.5 Food 05/26/98 Sample not available SW 12.7 Food 06/30/98 Sample not available C-2
r- -
1 l
APPENDIX C (Page 2 of 2)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDUIED SAMPLING AND ANALYSIS DURING 1998 DATE OF RFASONS FOR LOSS /
LOCATION DESCRIMION SAMPLING EXCEMION E-3.5 Food 06/30/98 Sample not available SW-12.7 -
Food 07/28/98 Sample not available SW-3.5 Food 07/28/98 Sample not available SW-12.7 Food 08/25/98 Sample not available E-3.5 Food 08/25/98 Sample not available SW-12.7 Food 09/29/98 Sample not available E-3.5 Food 09/29/98 Sample not available SW-12.7 Food 10/27/98 Sample not available SW-3.5 Food 10/27/98 Sample not available SW-12.7 Food 11/24/98 Sample not available i
E-3.5 Food 11/24/98 Sample not available SW-12.7 Food 12/29/98 Sample not available E-3.5 Food 12/29/98 Sample not available f
a C-3 L
I.
I i
l APPENDIX D EXCEEDED REPORTING LEVELS D-1
[
l l
APPENDIX D EXCEEDED REPORTING LEVELS 1
l 1998 None of the analytical measurements exceeded any notification level.
i i
l t
D-2
l I
i i
I 1
APPENDIX E LAND USE CENSUS i
E-1
COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS 1998 i
Performed by
[
Date 8-/7-78 Date 1 98 Reviewed by
U August 17,1998 COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS 1998 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 17 and 18,1998 and includes the followingitems:
1.
Evaluation of the 1998 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 speci6cally requested..
I 1
Evaluation of the 1998 Land Use Census The results of the 1998 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 Whi distances Currently the only location where milk samples are collected is at a control location (SW - 14.5).
Since not all milk samples are available, the broadleaf vegetation sampling specified in ODCM Table 3,12-1 is being performed. Droadleaf 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 changes to the broadleaf sampling program are 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 two indicator locations (ENE - 9.0 and E - 3.5) and from one control location (SW - 12.7) when available. No changes are required in the food product program.
2 o
i The 1998 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 j
pathway are irrhvlM 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
=L,d=+M values based on annual average values The annual average X/Q used f'or dose calculations l
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 1998 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 I
i 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 132E-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 8.3E-07 3.40E-09 SSE 1.5 1.lE-06 6.60E-09 S
1.5 8.5E-07 5.20E-09 SSW 2.7 2.18E-07 8.74E-10 SW 1.1 1.4E-06 5.50E-09 WSW l.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 2.10E-09 i
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
i a
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 4.1 3.26E-10 ENE None None E
3.5 2.70E-10 I
ESE 3.3 3.%E-10 SE None None SSE 2.4 2.08E- 09 S
None None SSW 4.5 2.60E-10 SW 1.5 2.50E- 09 WSW None None W
3.3 4.42E-10 WNW None None NW None None NNW 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
n.
Population by Sector and Distance Sector 0-1 1-2 2-3 3-4 4-5 Total N
5 37 85 127 NNE 8
75 24 107
~
NE 69 72 242 383 69 5
29 103 ENE E
88 160 29 277 3
11 106 15,7 277 ESE SE 8
108 51 61 228 SSE 45 43 43 2045 2176 48 19 56 160 283 S
5 3
43 51 SSW SVV 53 8
51 43 155 WSW 263 3
16 282 48 5
24 13 90 W
40 61 101 WNW 3
3 NW 3
40 19 62 NNW 473 442 779 3011 4705 TOTAL Based on an average of 2.66 residents per house. This average was obtained from North Central Texas Couned 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 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
RI1 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
l i
Environmental Sample Locations Table (cont.)
l 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
1 Environmental Sample Locations Table (cont.)
Sampling Point Location Sample Type
- SW1 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 SW5 ESE-1.4 (Squaw Creek Reservoir)
SW 2
3 SW6 NNW-0.1 (Squaw Creek Reservoir)
SW/DW GW1 W-1.2 (NOSF Potable Water)
GW l
GW2 WSW-0.1 (Plant Potable Water)
GW'
- GW3 SSE-4.6 (Glen Rose)
GW' i
GW4 N-9.8 (Granbury)
GW '
GW5 N-1.45 (Squaw Creek Park)
GW' SSI NNE-1.0 (Squaw Creek Reservoir)
SS SS2 N-9.9 (Lake Granbury)
SS SS3 NE-7,4 (Lake Granbury)
SS 1
M4 SW-14.5 (CONTROL)
M F1 ENE-2.0 (Squaw Creek Reservoir)
F F2 NNE-8.0 (Lake Granbury)
F FPI ENE-9.0 (Leonard Bros. Pecan Farm)
FP FP6 E-3.5 (Happy Hill Farm)
FP 10 l
L
Environmental Sample Locations Table (cont.)
Sampling Point Location Sample Type
- BL1 N-1.45 BL 5
BL2 SW-1.0 BL 8
BL3 SW-13.5 (CONTROL)
BL i
- 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.
- 3) Plant potable water can be supplied by surface water from Squaw Creek Reservoir (location SW6) and 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 anylocation.
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t Environmental Sample Locations Map - 2 Mile Radius