ML20217D614
| ML20217D614 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1997 |
| From: | Curtis J, Floyd E TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | |
| Shared Package | |
| ML20217D608 | List: |
| References | |
| NUDOCS 9804240404 | |
| Download: ML20217D614 (102) | |
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55-1UELECTRIC TU ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION 1997 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Reviewed by: Date: Y 78 Edwin T. Floyd Senior Radiation Protection Technician Approved by: ; - b Date: Yd!7f Johi. R. Curtis Radiation Protection Manager b ADO K O 00 445 R PDR P.O. Box 1002 Glen Rose, Texas 76043-1002
r TABLE OF CONTENTS SECTION PAGE i
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I. .......................................................................................................1 j l
I A Site and Station De scription ................................................................ 2 H Objectives and Overview of the............................................................ 2 CPSES Monitoring Program IL PROGRAM NWRIPIf0NS. . .. .. . . . . . . . .. . . . .. . .. .. . . .. . .. . . . . . . . . . .. . . . . . ... . .. . .. .. . . . . . . . .. . .. .. . .. . . . . .. 6 A. Sample Locatio n s ...... ........... ...... ...... ... .. ...... ....... .. .... .. .. ......... .. ...... ......... 7 I H Sampling Methods and Procedures.................... ........................... 7 l
- 1. Direct Radiation. . . . . . . . . . . .. . .. . . . . . . . . . . . .. .... ... . .. . . ... ... . . ... . . .. ... ... . . ... .. .. 8 l
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- 2. Air Particulates and Air Iodine .......................................... 8
- 3. Milk.............................................................................................9
- 4. Water............................................................................................9
- 5. Fish...........................................................................................11
- 6. Sh o relin e Sedim ent ............. .... ............................................ I 1
- 7. Food Products.. . . . . . ... . . .. ... .. . . .. .. .. .... .... .. . .. ... . .. . .. . . . .. .. . .. . .. .... . ..... 1 1
- 8. Broadleaf Vegetation ........................................................... 12 C. Interlaboratory Comparison Program ......................................... 12 l
l D. Deficiencies in the Sample Program........................................... 13 III.
SUMMARY
AND DISCUSSION OF 1997 ANALYTICAL RESULTS......14 A. Direct Radiation.... . .... . . .. . . . . . . .. . . .. . . . . ... . . .. . .. .. .. . . .. . . . . . . .. . .. . . . . ... . . . ... .. . .. ... . ... 1 5 H Air Particulates and Air Iodine ...................................................... 17 l C Milk..........................................................................................................18 D. Water........................................................................................................18 E. Fish...........................................................................................................19 11
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l F. Sh o relin e Se d im en t s ....... .... .. ................. ......................... ................ 2 0 !
l G. Food Products. . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . ..
H. B ro ad leaf Vege tatio n .... .... .... ... .. .. ................... ..... .. .. .... .. ..... ...... ..... .. .. . 2 1 l .
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IV. CON CLU SION S .. .. .. . . .. .. .. .. .. .. .... .. . . .. . . .. . .. . . . . .. . . .. .. . .. .. .. .. .. .. . . . . ... . . . . .. .. .. . . .. . .. .. .
V. REFERENGE...............................................................................................25 i
VI. IMTATAIEES . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . .l l
APPENDICES l APPENDIX A Cross-Check Progmms. .. .. ... .. .. .. . .. .. ..... .. ... .. .. .. . . . . . ... . . ... . . . . ... .. .. ... .. .. . .. .A- 1 APPENDIX B Synopsis of Analytical Procedures.................. .............................B-1 :
APPENDIX C Exceptions to the 1997 REMP.............. ..... .. ... ............................. .C- 1 APPENDIX D Exce ed ed Rep orting Levels ........................................................... D- 1 APPENDIX E Iand Use Census... ... ......... . ... . ... . . . .. ... .. ..... .... . .. .... .... . .. .... ... .. . ....... . ..... .. E - 1 i
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I2ST OF TABLES TABLE TITLE PAGE 1 CPSES Radiological Environmental ...................................... ................. 2 8 Monitoring Program 2 Direct Radiation - 'Ihermoluminescent Dosimetry......................... 31 3 Concentrations of Iodine-131 in Filtered Air...................................... 33 4 Concentrations of Gross Beta Emitters in Air Particulates............ 36 5 Concentrations of Gamma Emitters in Air Particulate Filters...... 39 6 Concentrations of Iodine- 131 in Milk.................................................... 41 7 Concentrations of Gamma Emitters in Milk ........................................ 4 2 8 Concentrations of Gamma Emitters in Groundwater....................... 43 9 Concentrations of Tritium in Groundwater.......................................... 44 10 Concentrations of Gross Beta in Water-Surface / Drinking.............. 45 11 Concentrations of Gamma Emitters in Water-Surface / Drinking 46 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 Coneentrations 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 Prograin Summary -
January 1 to December 3 1, 1 9 9 7 .. .. . . . . .. .. . .. .. .. ... . . .. .. .. . .. .. .. .. ... .. .. . . . . . .. .. . . .. . . 5 7 iv
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LIST OF FIGURES FIGURE TITLE PAGE I Radiological Environmental Monitoring locations............................ 3 0
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1 INTRODUCTION 1
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j I. INTRODUCTION l
Results of the Radiological Environmental Monitoring Program for the l Comanche Peak Steam Electric Station for 1997 is contained within this re-port. This report covers the period from January 1, 1997 through December 31,1997 and summarizes the results of measurements and analy-ses of data obtained from samples collected during this interval. ;
A. Site and Station Description i Comanche Peak Steam Electric Station (CPSES) consists of two -
1 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 ope' rating 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.
R 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 unrestricted areas as low as reasonably achievable (ALARA) (10 CFR 50.34a). To assure that these criteria are met, each license autho-j rizing reactor operation includes technical specifications (10 CFR l 50.36a) governing the release of radioactive effluents.
In-plant monitoring is used to assure that these predetermined 2
1 release limits are not exceeded. However, as a precaution against I unexpected and undefined processes which might allow undue ac-cumulation of radioactivity in any sector of the environment, a pro-gram for monitoring the plant environs is also included.
Sampling locations were selected on the basis of local ecology, me-teorology, physical characteristics of the region, and demographic and land use features of the site vicinity. The radiological environ-mental 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 (Noveinber 1979)(1), the CPSES Technical Specifications (4) and j the CPSES Offsite Dose Calculation Manual (ODCM)(5),
In 1997, the Radiological Environmental Monitoring Program in-cluded the measurement of ambient gamma radiation by thermo- ,
luminescent 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 determina-tion of gamma emitters and iodine-131 in milk; and the measure-l- ment 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 - Environmental Services.
The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most only a
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few percent increase above normal background radioactivity.
l 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 re-i flecting variations in geological composition. To differentiate be-i tween background radiation levels and increases resulting from op-eration of CPSES, the radiological surveys of the plant environs are I divided into preoperational and operational phases. The preopera-tional phase of the program pennits a general characterization of .
the radiation levels and concentrations prevailing prior to plant op-l eration along with an indication of the degree of natural variation to be expected. The operational phase of the program obtains data I which, when considered along with the data obtained in the preop-erational phase, assist in the evaluation of the radiological impact of plant operation.
Preoperational measurements were conducted at CPSES from 1981 l to 1989. These preoperational measurements were performed to: >
- 1. Evaluate procedures, equipment and techniques.
- 2. Identify potentially important pathways to be monitored af-ter the plant is in operation.
- 3. Measure background levels and their variations along po-tentially important pathways in the area surrounding the plant.
- 4. Provide baseline data for statistical comparison with future operational analytical results.
The operational Radiological Environmental Monitoring Program is 4
I conducted to:
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- 1. Verify that measurable concentrations of radioactive mate-rials and levels of radiation are not higher than expected on the basis of the efIluent measurements and modeling of the environmental exposure pathways.
- 2. Verify the effectiveness of in-plant measures used for con-trolling the release of radioactive materials. l
- 3. Identify changes in the use of areas at and beyond the site boundary that may impact the principal pathways of expo- i sure.
This report documents the eighth 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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l PROGRAM DESCRIPTIONS l ,
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1 H. PROGRAM DESCRIPTIONS l A. Sample Locations Seventy-five locations within a radius of 20 miles from the CPSES site were included in the monitoring program for 1997. The num- ;
ber and location of monitoring points were determined by consid-ering the locations where the highest off-site environmental con-centrations have been predicted from plant effluent source terms, site hydrology, and site meteorological conditions. Other factors I I
considered were applicable regulations, population distribution, ease of access to sampling stations, availability of samples at desired l 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 im- ,
i pact the principal pathways of exposure, appropriate changes to the radiological environmental monitoring program are implemented.
The results of the 1997 Land Use Census are provided in Appendix E.
The Radiological Environmental Monitoring Program for Comanche Peak is summarized in Table 1. 1 l
Bs Samnling Methods and Procedures To derive meaningful and useful data from the Radiological l
Environmental Monitoring Program, sampling methods and proce- l dures are required which will provide samples representative of l
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 de- l termine the direct (ambient) radiation levels at monitoring points. Sampling locations were chosen according to the criteria given in the USNRC Branch Tech tical Position on Radiological Monitoring (Revision 1, November 1979)(1)-
The area around the station was divided into 16 radial sec-tors of 22-1/2 degrees each. -TLDs were placed in all sec-tors. Thermoluminescent dosimeters were located in two
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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, including two control locations. For routine TLD measurements, two dosimeters of CaSO4:Dy in teflon cards were deployed at each selected location. One set of dosimeters was exchanged on a quar-terly basis and the second set was exchanged on an annual basis. Additional sets of dosimeters were shipped with each exchange cycle to serve as in-transit controls.
Individual dosimeters were calibrated by exposure to an accurately known radiation field from a calibrated Cs-137 l
l source.
- 2. Air Particulates and Air Iodine Air particulate and air iodine samples were collected from the eight locations described in Table 1.
Each air particulate sample was collected by drawing air through a 47 millimeter diameter glass-fiber filter. Air 8
l fodine was collected by drawing air through a TEDA im-pregnated charcoal cartridge which was connected in se- i ries behind the filter. The filters and charcoal cartridges were collected weekly by CPSES staff. In the laboratory, l l
air particulate filters were analyzed for gross beta activity and were composited quarterly for gamma spectrometry analysis. Charcoal cartridges were analyzed for iodine-131.
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- 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 repre-sentative of Squaw Creek Reservoir surface water at a 10-cation beyond significant influence of the plant discharge.
Location ESE-1.4 provides samples representative of dis-charges 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 9
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 sample is obtained from the Brazos River, upstream of Lake Granbury at location N-19.3.
Surfsce water samples from Squaw Creek Reservoir loca-tions were collected weekly and composited for monthly gamma isotopic analysis. Samples from Lake Granbury 10-cations were collected monthly and analyzed by gamma spectroscopy. All surface water samples were also com-posited 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 wa-ter were collected at location NNW-0.1. Samples from this location were analyzed pursuant to the drinking water re-quirements even though Squaw Creek Reservoir is not used as a potable water 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 10
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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. Gamma isotopic and tritium analyses were performed by location.
- 5. Bah Fish samples were collected at two locations for the 1997 program. An area 2.0 miles east-northeast of the site in Squaw Creek Reservoir was chosen as the indicator loca-tion, and a location at Lake Granbury (NNE-8) was chosen as a control location. Fish sampling was conducted in April 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 analy-sis. Fish were filleted in the laboratory and the edible portion analyzed by gamma spectrometry.
- 6. Shoreline Sediment i
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 dis-charge of the return line from Squaw Creek Reservoir. !
1 CPSES staff collected the sediment samples and shipped I them to the laboratory for analysis by gamma spectrometry. !
- 7. Food Products During the period of January through November, 3 sam-11
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l ples were co!!ected from two indicator sampling locations l
l (ENE-9.0 and E-3.5). A total of 2 different types of food products were collected during this sampling period.
Food product samples were collected by the CPSES staff and shipped to the laboratory where they were analyzed for gamma emitters.
- 8. Broadleaf Vegetation Broadleaf vegetation was collected from the control loca-tion (SW-13.5) and two indicator stations (N-1.45 and SW-1.0) near the site boundary. Collection of broadleaf vege-tation started in January 1997. Broadleaf samples consisted of native grasses.
Gamma isotopic and iodine-131 analyses were performed for all broadleaf vegetation samples.
C Interlaboratory Comnarison 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 Engineering - Environmental Services purchased comparable spiked samples from Analytics, Inc. (see Analytics table).
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i l The purpose of the interlaboratory comparison program is to pro- l vide an independent check on the laboratory's analytical proce-dures and to alert it to any possible problems. Participant labora-
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tories 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' participation in the U.S. EPA Interlaboratory Comparison i
Program and the Analytic's program for 1997 are provided in l Appendix A.
D. ))eficiencies in the Samole 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. 1 Deficiencies in the program are deviations from the sampling schedule that were preventable by CPSES staff.
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SUMMARY
AND DISCUSSION OF 1997 ANALYTICAL RESULTS 1
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III.
SUMMARY
AND DISCUSSION OF 1997 ANALYTICAL RESULTS I 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 syn-opsis of analytical procedures is contained in Appendix B of this report. 1 Radiological analyses of environmental media characteristically ap-proach and frequently fall below the detection limits of state-of-the-art mea- l surement 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 de-tection (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 re-ported averages are based only on concentrations above the limit of detec-tion. In Table 20, the fraction (f) of the total number of analyses with de-tectable activity follows in parentheses. Also given in parentheses are the minimum and maximum values of detectable activity during the report pe-riod.
A. Direct Radiation Environmental radiation dose rates determined by thermolumines-3 cent dosimeters (TLDs) are given in Table 2. Thermoluminescent 15
dosimetry badges with four readout areas each were deployed at j each location on quarterly and annual cycles. The mean values of four readings (corrected individually for response to a known dose i and for in-transit exposure) are reported, i
A statistical summary of the 1997 data is included in Table 20. For the quarterly analyses the average dose rate of the controllocations was 0.13 mR/ day with a range of 0.10-0.15 mR/ day. '111e average of the indicator locations for the quarterly samples was 0.12 mR/ day l
with a range of 0.07 to 0.20 mR/ day. For the annual samples, the average dose rate for the control samples was 0.16 mR/ day. 'line
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indicatur locations had an average of 0.16 mR/ day with a range of 0.11-0.20 mR/ day.
Oakley(3) calculates an ionizing background radiation dose equiva-lent of 82.2 mR/ year for Fort Worth including a terrestrial compo-nent of 45.6 mR/ year and an ionizing cosmic ray component of 36.6 mR/ year (excludes neutron component). Since Oakley's values rep-resent averages covering wide geographical areas, the measured ambient radiation average of 58.4 mR/ year for the immediate locale of CPSES is consistent with Oakley's observations. Significant vari-ations' 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 soil moisture.
Anomalies in the 1997 measured doses relative to preoperational I
data were not noted. For 1989, the averages for the indicator loca-tions were 0.16 mR/ day (range of 0.11 to 0.22) and 0.13 mR/ day (range of 0.11 to 0.17), for the quarterly and annual samples i
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respectively. The 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.
H Air Particnintes and Air Iodine A total of 416 charcoal cartridges were analyzed for airborne 10-dine-131 by gamma spectrometry. No iodine-131 was detected at I any of the sampling stations. Results of these measurements are
. presented in Table 3.
A total of 416 air particulate filters were collected and analyzed for gross beta activity. For 1997 the average gross beta activity for the control location was 0.018 pC1/m3 with a range from 0.008 to 0.042 pCi/m3- For the seven indicator locations the yearly average was 0.019 pC1/m3 with a range from 0.005 to 0.044 pCi/m3. 'Ihe gross beta analysis data are presented in Table 4. Anomalies in l
gross beta measurements relative to preoperational data were not noted.
Air filters were composited quarterly and then analyzed by gamma spectrometry. 'Ihe 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 0.073 pCi/m3 with a range of 0.061-0.092 pC1/m3 For the indicator l locations, the average beryllium-7 activity was 0.071 pCi/m3 with a range of- 0.050 to 0.092 pC1/m3 Potassium-40, a naturally occurring nuclide, was measured in fourteen samples. The average potassium-40 for the control location was 0.008 pC1/m3- The average potassium-40 activity for the indicator locations was 0.015 pC1/m3 with a range of 0.007-0.038 pCi/m3 17
c Milk A total of 20 milk samples were collected in 1997. 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. l
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No iodine-131 was found in any of the milk samples. The lower limits of detection can be found in Table 6. I Results of the gamma spectrometry -easurements are presented in Table 7. Naturally occurring potas.um-40 was detected in all of the milk samples. The average activity for the control location was
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1337 pC1/1 with a range of 1230 to 1410 pCi/1. Cesium-134, Cs-137 and La-140/Ba-140 were not detected in any of the samples. .
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'Ihe lower limits of detecuon can be found in Table 7. !
D. Water l Groundwater samples were collected from five locations during l l
1997. 'Ihe samples were' analyzed for gamma emitters and tritium on a quarterly basis, pursuant to the ODCM requirements for i 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 no tritium was detected. 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 j 18
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i gross beta activity. The indicator station had an average activity of 21 pCi/l with a range of 13 to 32 pCi/1. De control station had an average activity of 9 pC1/1 with a range of 4.2 to 12 pCi/1. Eight quarterly composites were analyzed for tritium. The indicator sta-tion had an average activity of 11600 pC1/1 with a range of 9400 to 14000 pCi/1. The control station showed no tritium activity above the lower limit of detection. Iodine-131 analyses by radiochemistry were performed on 24 samples of surface-drinking water; there was no measurable activity. Results of these analyses are contained in Tables 10 through 13.
I Surface water was sampled from four locations during 1997.
Samples were analyzed for gamma isotopic on a monthly basis (composite (2) and monthly (2)) and tritium composites on a i 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 !
I analyzed for tritium. The indicator stations had an average activity l 1
of 10838 pC1/1 with a range of 9000-13000 pC1/1. The results of these analyses can be found in Table 14 and 15 respectively. The l
tritium detected in Squaw Creek Reservoir samples of surface water and surface-drinking water is attributed to liquid effluent discharges from CPSES. The level of tritium in the Squaw Creek Reservoir is well within the expected value predicted in the CPSES <
l Final Safety Analysis Report.
E. Ssh he results of gamma isotopic analyses of fish samples collected during 1997 are presented in Table 16. A total of eight samples l
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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 im-a portance.
Cesium-137 was not detected in any of the samples. Preoperational levels have ranged from 3 to 39 pCi/kg wet on thirteen different l occasions. Naturally occurring potassium-40 was detected in all samples. The average potassium-40 concentration for the four in-i dicator samples is 3055 pC1/kg wet with a range of 2810 to 3450 pC1/kg wet. The average concentration for the control location is 3108 pCi/kg wet with a range of 2780 to 3470 pC1/kg wet. No other gamma emitters were detected in any samples.
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F. Shoreline Sediments The processes by which radionuclides and stable elements are con- l l
centrated in bottom sediments are complex, involving physiochem- I
( ical interaction in the environment between the various organic and
! i inorganic materials from the watershed. These ir;teractions can ;
i proceed by a myriad of steps in which the elements are absorbed in l
l- or displaced from the surfaces of colloidal particles enriched with chelating organic materials. Biological action of bacteria and other benthic organisms also contribute to the concentration of certain i l
l elements and in the acceleration of the sedimentation process.
- Results of the gamma isotopic analyses of the sediments sampled l
from the CPSES environment are given in Table 17. For 1997 four locations, one control and three indicators, were sampled.
Naturally occurring gamma emitters found in detectable concen-trations were Be-7, K-40, Pb-212, Bi-214, Pb-214 Ra-226 and Th-f 20 l
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228. Cesium-137 was measured in two samples, one from station SE-5.3 and one from N-1.0, both indicator stations, with an average !
, of 48 pC1/kg dry. Preoperational levels of cesium-137 have ranged 1 \
l from 9.2 to 150 pC1/kg on four different occasions.
l G. Food Products
- l. Results of gamma isotopic analyses of food samples are contained in I Table 18. A total of 3 samples were analyzed from two locations.
Potassium-40, a naturally occurring isotope, was found in all 3 samples. For the indicator locations the average potassium-40 ac-tivity was 2430 pCi/kg wet with a range of 2210 to 2580 pCi/kg wet. Naturally occurring beryllium-7 was not detected in any '
sample. Iodine-131, Cs-134 and Cs-137 were not detected in food products during 1997. The number of samples available in 1997 was low due to an abnormally wet spring and extremely dry summer.
H. Broadleaf Vegetation l
Results of gamma isotopic analyses of broadleaf vegetation samples l are contained in Table 19. A total of 36 samples were analyzed from three locations. Potassium-40, a naturally occurring isotope, was found in 34 samples. The average potassium-40 activity for the control location was 4638 pCi/kg wet with a range of 1310 to 9980 I
pC1/kg wet. For the indicator locations the average potassium-40 l activity was 3427 pCi/kg wet with a range of 449 to 7250 pC1/kg l
wet. Naturally occurring beryllium-7 was detected in twenty-four indicator samples with an average activity of 5158 pCi/kg wet; the I range was 83 to 15800 pC1/kg wet. All of the 12 samples from control station SW-13.5 were found to have beryllium-7 with an l
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1 average activity of 3020 pCi/kg wet and a range of 124-7220 pCi/kg wet. )
i Thorium-228, I-131, Cs-134 and Cs-137 were below the lower limit of detection in all samples.
l 1
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22 1
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l CONCLUSIONS i
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23
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l l l
IV. CONCLUSIONS 1 It is concluded from the levels obtained in environmental samples during 1997 and comparison of these levels to preoperational measure- l l
1 ments and operational controls, that the operation of CPSES in 1997 re-sulted in no changes in measurable levels of radiation or radioactive materi-als in the environment except for the tritium detected in Squaw Creek j Reservoir which has increased from the 1994 average of approximately 6450 pC1/1 to approximately 11600 pCi/1. This increase has been expected, !
l based on 2 unit operation. The atmospheric environment was sampled for airborne particulate matter, radiolodine, and direct radiation. The i terrestrial 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 far below the reporting levels for radioactivity concentrations in environmental samples.
24
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REFERENCES l
l l
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1 l
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- v. REFERENCES I
- 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", j ORP/ SIR Z2-1 Offlee of Radiation Programs, U.S. Environmental Protection Agency, Washington, D.C., June 1972
'4. Comar.che Peak Steam Electric Station Units 1 and 2 Technical ,
3 Specifications
- 5. Offsite Dose Calculation Manual For TU Electric Comanche Peak
- Steam Electric Station Units 1 and 2.
l l
l' 26
4 DATA TABLES t
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i TABLE 6 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF 1-131 IN MILK Results in pC1/1i 2 s.d.
COLLECTION MOBTrH DATE SW-14.5 JANUARY 01/28/97 <O.1 FEBRUARY 02/25/97 <0.2 MARCH 03/11/97 <0.2 03/25/97 < 0. 2 APRIL 04/08/97 <0.2 04/22/97 <0.1 l
MAY 05/06/97 <0.2 05/20/97 <O.2 JUNE 06/03/97 <0.1 06/17/97 <0.2 JULY 07/01/97 <0.2 07/15/97 <0.2 07/29/97 <0.2 AUGUST 08/12/97 <0.2 08/26/97 <0.2 SEFFEMBER 09/09/97 <0.1 ,
09/23/97 <0.1 i
! OCTOBER 10/07/97 <0.1 10/21/97 <0.2 l NOVEMBER 11/25/97 <0.2 i
DECEMBER 12/30/97 <0.2 i i
i i
41
0 4
1 a
B
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ECM C L EA MfA o BL AE TE Gs T t U SFn i TAKOU E
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////
3692 T 3692 T S S 0001 S 0001 S 0001
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TABLE 9 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER Results in pCi/li 2 s.d.
COLLECTION TRITIUM ,
QUARTER DATE LOCATION ACTIVilY 1 03/25/97 W-1.2 <2000 i 03/25/97 SSE-4.6 <2000
( 03/25/97 N- 1.45 <1000 03/25/97 WSW-0.1 <1000 03/25/97 N-9.8 <2000 2 06/24/97 W-1.2 <2000 06/24/97 SSE-4.6 <2000 06/24/97 N-1.45 <2000 06/24/97 WSW-0.1 <2000 j 06/24/97 N-9.8 <2000 l
3 09/30/97 W-1.2 <2000 09/30/97 SSE-4.6 <2000 l 09/30/97 N- 1.45 <2000 09/30/97 WSW-0.1 <2000 09/30/97 N-9.8 <2000 4 12/31/97 W-1.2 <1000 12/31/97 SSE-4.6 <1000 12/31/97 N- 1.45 <1000 12/31/97 WSW-0.1 <1000 .
l N-9.8 <1000 !
12/31/97 a
l
TABLE 10 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS of GROSS BETA IN WATER-SURFACE / DRINKING Results in pC1/1i 2 s.d.
COLLECTION MONTH DATE NNW-0.1 N-9.9 JANUARY 01/07/97-01/28/97 31i5 11i3 FEBRUARY 02/04/97-02/25/97 19i4 8.8i2.5 MARCH 03/04/97-03/25/97 17i3 8.9i2.5 APRIL 04/01/97-04/29/97 20i4 8.5i2.5 MAY 05/06/97-05/27/97 21i4 9.0i2.3 JUNE 06/03/97-06/24/97 13i3 10i3 JULY 07/01/97-07/29/97 23i4 9.7i2.9 AUGUST 08/05/97-08/26/97 18i3 8.6i2.7 SEFFEMBER 09/02/97-09/30/97 32i5 11i4 l
OCTOBER 10/07/97-10/28/97 20i4 12i3 NOVEMBER 11/04/97-11/25/97 14i3 42i2.8 DECEMBER 12/02/97-12/30/97 21i4 9.6i3.2 l
45 l
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I 744163152742 1 744163152742 A T
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////////////
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- 8
TABLE 12 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN WATER-SURFACE / DRINKING l Results in pCi/li 2 s.d.
COLLECTION MOPTTH DATE NNW-0.1 N-9.9 JANUARY 01/07/97-01/28/97 < 0. 4 <0.3 FEBRUARY 02/04/97-02/25/97 < 0. 5 <0.4 MARCH 03/04/97-03/25/97 < 0. 4 <0.4 APRIL 04/01/97-04/29/97 <0. 7 <0.6 MAY 05/06/97-05/27/97 < 0. 7 <0.6 JUNE 06/03/97-06/24/97 <0.6 <0.6 JULY 07/01/97-07/29/97 <0.8 <0.8 AUGUST 08/05/97-08/26/97 <0.7 <0.7 SEPTEMBER 09/02/97-09/30/97 < 0. 7 <0.7 OCTOBER 10/07/97-10/28/97 < 0. 5 <0.6 NOVEMBER 11/04/97-11/25/97 < 0. 8 <0.9 DECEMBER 12/02/97-12/30/97 <0. 5 <0.6 47
TABLE 13 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN WATER-SURFACE / DRINKING Results in pC1/1i 2 s.d.
COLLECTION QUARTER PERIOD NNW-0.1 N-9.9 1 01/07/97-03/25/97 11000i2000 <2000 2 04/01/97-06/24/97 9400 1900 <2000 3 07/01/97-09/30/97 12000i1000 <1000
- 4. 10/07/97-12/30/97 14000i2000 <300 l
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APPENDIX A l 1
CROSS-CHECK PROGRAMS j l
1
)
i I l
I i
A-1
EPA INTERLABORATORY COMPARISON PROGRAM 1997 Environmental Teledyne Brown Collection Engineering Result (b) Deviation (c)
Date Media Nuclide EPA Result (a)
' 12.0 i 5.0 10.00 i 1.00 -0.69 i 01/17/97 Water Sr-89 0.00 l Sr-90 25.0 5.0 25.00 i 1.00 l l
5.2 i 5.0 8.10 i 0.89 1.00 l 01/31/97 Water Gross Alpha 0.10 j 14.7 i 5.0 15.00 1.00 Gross Beta 1-131 86.0 i 9.0 106.00 i 4.36 3.85 (d) 02/07/97 Water l_
5.9 0.9 5.27 0.23 -1.22 l 02/14/97 Water Ra-226 0.30 0.16 i
Ra-228 8.2 i 2.1 8.40 1 l
l 7366.67 i 378.59 -1.17 03/07/97 Water H-3 7900.0 i 790.0 i 15.3 103.33 i 5.77 0.14 04/15/97 Water Gr-Beta 102.1 i -0.35 Sr-89 24.0 1 5.0 23.00 i 1.00 l 13.0 i 5.0 12.67 i 1.15 -0.12 Sr-90 0.58 0.58 Co-60 21.0 i 5.0 22.67 i 5.0 28.67 i 0.58 -0.81 Cs-134 31.0 i 0.92 l
Cs-137 22.0 i 5.0 24.67 i 1.53 54.67 i 1.53 0.96 Gr-Alpha 48.0 i 12.0 0.00 i 13.0 i 2.0 13.00 i 1.00 Ra-226 0.12 3.82 (e) i Ra-228 3.1 i 0.8 4.87 i 5.0 19.00 i O.00 0.35 Water Co-60 18.0 t -0.12 06/06/97 100.0 i 10.0 99.33 1.15 Zn-65 l 5.0 18.67 1.15 -1.15 Cs-134 22.0 i -0.12 Cs-137 49.0 i 5.0 48.67 i O.58 5.0 22.33 i 2.52 -0.92 Ba-133 25.0 i 0.5 3.43 i 0.49 1.50 Water Ra-226 3.01 0.72 06/13/97 3.1 i 0.8 3.43 i 0.23 Ra-228 5.0 2.93 0.25 -0.06 Water Gr-Alpha 3.1 0.38
( 06/18/97 15.1 5.0 14.00 1.00 f
Gr-Beta 5.0 38.33 1.53 -1.96 Water Sr-89 44.0 1 3.12 (0 07/11/97 16.0 i 5.0 25.00 1 0.00 Sr-90 12000.00 0.00 1.56 Water H-3 11010 i 1101.0 08/08/97 3.0 20.00 i 1.73 0.00 Water Ra-226 20.0 i 0.17 -0.52 09/12/97 8.0 i 2.0 7.40 i Ra-228 6.0 11.00 0.00 0.29 Water I-131 10.0 i 09/19/97
- Footnotes are located at end of table.
A-2
i ~
I 1
EPA INTERLABORATORY COMPARISON PROGRAM 1997 i Environmental l i
l Collection Teledyne Brown l
Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) l 10/21/97 Water Gr-Beta 143.4 i 21.5 136.67 i 5.77 -0.54 I Sr-89 36.0 1 5.0 36.00 i 1.00 0.00 Sr-90 22.0 i 5.0 21.67 2.08 -0.12 Co-60 10.0 i 5.0 10.67 i 0.58 0.23 Cs-134 41.0 i 5.0 41.33 i 0.58 0.12 l Cs-137 34.0 5.0 36.00 1.00 0.69 Gr-Alpha 49.9i 12.5 45.67 1.15 -0.59 Ra-226 5.0 0.8 5.90 0.10 1.95 Ra-228 5.0 i 1.3 4.27 i 0.12 -0.98 10/31/97 Water Gr-Alpha 14.7 5.0 19.67 i 1.53 1.72 Gr-Beta 48.9 i 5.0 50.67 3.51 0.61 l 11/07/97 Water Co-60 27.0 5.0 25.00 i 1.00 -0.69 Zn-65 75.0 t 8.0 71.00 i 3.61 -0.87 Cs 134 10.0 i 5.0 10.67 0.58 0.23 Cs-137 74.0 5.0 76.00 1.00 0.69 Ba-133 99.0 10.0 78.67 i 0.58 -3.52 (g)
Footnotes:
(a) EPA Results-Expected laboratory precision (1 sigma). Units are pCi/ 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) Erroneously high reading of the stable iodine content by ion specific electrode occurred, causing an erroneously low chemical yield. If the electrode reading is ignored, the average 1-131 result becomes 90 pCi/1, in good agreement with the given value. An erroneous electrode reading can be caused by certain chemical species in the sample, such as sulfide. We will investigate suspiciously high electrode readings by performing a gravimetric yield on the sample without the addition of iodide carrier or the I-131 content of active samples can also be verified by performing a gamma spectral analysis.
(e) An investigation discovered a low chemical yield on one sample and the loss of another during analysis. In the future we will repeat analyses of samples with yields less than 85%.
l l (f) Error apparently caused by insufficient training. The strontium separation chemistry was l performed on 7/22/97 by a summer employee. Initial results for the three samples did not agree well, so all were remilked by a senior analyst. This was insufficient to correct the problem. In-house QC semples showed satisfactory results at this time. There will be additional qualification of analysts according to performance on in-house blanks and spikes.
(g) No apparent cause for the discrepancy could be identified. No corrective action has been taken. The investigation is continuing. An update will be provided, if a cause is determined and corrective action taken.
l I
l A-3 i
ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997
~ ~ ~ '
Teledyne Brown Analytics Staple ID Media Nuclide Engineering Result (a) Result Ratio (b)
Milk I-131 18 i 1 20 1 0.90 E0975-396 TI#41238 Ce-141 L.T. 1. 232 12 -
Cr-51 381 i 38 387i 19 0.98 03/20/97 13 143 7 0.92 Cs 134 132i Cs-137 128 i 13 114 i 6 1.12 Co-58 89 9 79 i 4 1.13 Mn-54 195 20 176 i 9 1.11 Fe-59 161 i 16 144 i 7 1.12 Zn-65 171 i 17 165i 8 1.04 CO-60 179 i 18 176 i 9 1.02 E0976-396 Milk Sr-89 13 i 3 25 f: 1 0.52 (c)
Sr-90 16 i 19 i 1 0.84 TI#41239 1 03/20/97 Air Filter Ce- 141 143 i 8 132 i 7 1.08 E1092-396 1.16 TI #49899-901 Cr-51 229 i 17 198 i 10 Cs-134 74 i 4 81 i 4 0.91 06/19/97 115i 6 1.24 Cs-137 143i 8 Co-58 89 1 5 77 i 4 1.16 Mn 54 102 i 6 84 i 4 1.21 Fe-59 98 i 6 75 i 4 1.31 Zn-65 186; 11 139 7 1.35 Co-60 113 7 104 i 5 1.09 Cartridge I-131 106 i 6 88 4 1.20 EIO93-396 TI #49902-04 06/19/97 Air Filter Sr-90 88 i 5 96 i 5 0.92 E1094-396 TI #498S3-95 06/19/97 Gros. Alpha 103 i 6 93 i 5 1.11 E1095-396 Air Filter 1.09 Gross Beta 210 6 193 10 T1 #49896-98 06/19/97 10 87 i 4 1.11 E1204-396 Milk 1-131 97 i 1.08 TI#57520 Ce 141 83 i 8 77 4 Cr-51 323 i 40 304 i 15 1.06 09/18/97 102 i 5 0.96 Cs-134 98 10 Cs-137 117 12 107 i 5 1.09 Co-58 64 6 60 3 1.07 Mn 54 99 i 10 88 i 4 1.13 Fe 59 132 13 119 i 6 1.11 Zn-65 2181 22 1961 10 1.11 209i 21 197i 10 1.06
_Co-60 A-4
ANALYTICS CROSS CHECK COMPARISON PROGRAM 1997 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a) Result Ratio (b)
E1203-396 Milk Sr-89 14 1 15 i 1 0.93 TI#57517 Sr-90 18 i 1 14 1 1.29 09/18/97 ,
Footnotes:
(a) Teledyne Results - counting error is two standard deviations. Units are pCi/ liter for water and milk. For gamma results, if two standard deviations are less than 10%, then a 10% eror is reported. Units are total pC1 for air particulate filters.
(b) Ratio of Teledyne Brown Engineering to Analytics results.
(c) Caused by incorrect rinsing of the strontium extraction column. Additional training was conducted on 9/5/97 and was documented in the analyst's training file. Subsequent tests on two milk samples spiked with T.r-89 produced good results.
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l APPENDIX B 1 SYNOPSIS OF ANALYTICAL PROCEDURES 1
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B-1
APPENDIX B APPLICABLE PROCEDURES NUMBER Tr1LE DATE PAGE PRO-032-1 Determination of Gross Alpha 03/20/96 B-3 and/or Gross Beta in Water Samples PRO-042-5 Determination of Gamma 04/24/93 B-5 Emitting Radioisotopes PRO-032-10 Determination of Gross Beta 03/01/87 B-7 in Air Particulate Filters PRO-032-11 Determination of Radiciodine 12/15/92 B-8 in Milk and Water Samples PRO-032-12 Determination of Radiolodine 12/15/92 B-9 in Vegetation Samples PRO-342-17 Environmental Thermolumi- 06/17/94 B-10 nescent Dosimetry (TLD)
PRO-032-35 Determination ofTritium in 03/16/96 B-11 Water by liquid Scintillation i
i B-2
T'IELEDYNE PRO-032-1 ISOTOPES l
l l
DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA IN WATER SAMPLES
1.0 INTRODUCTION
'Ihe procedures described in this section are used to measure the overall
! radioactivity of water samples without identifying the radioactive species present. No chemical separation techniques are involved.
One liter of the sample is evaporated on a hot plate. Different volumes l l
l may be used if the sample has a significant salt content or if unusual j sensitivity is desired. If requested by the customer, the sample is filtered l
through No. 54 filter paper before evaporation, removing particles greater than i l
30 microns in size. ;
l After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diameter stainless steel planchet which is stamped with a concentric ring pattern to distribute residue evenly. Final evaporation to dryness takes place under heat lamps. Samples which appear to be hygroscopic are dried again under heat lampsjust prior to counting.
Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for alpha and/or beta activity l
on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting I efIlciency caused by the residue mass.
2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually B-3
1 h YNEismwss PRO-032-1 represented on the planchet, the background and the emetency of the counting instrument, and upon self-absorption of alpha and beta particles by the mounted sample. Because the radioactive species are not identified, no decay correcuons are made and the reported activity refers to the counting time.
ne 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 pC1/1 at the 2.83 sigma level), assuming that I liter of sample is used and that 1/2 gram of sample residue is mounted on the planchet. Rese figures are based upon a nominal counting time of 50 minutes and upon representative values of counting emciency and background of 0.2 and 1.2 cpm, respectively. He MDL for gross alpha acuvity is nominally 2.3 picoeuries per liter at the 4.66 sigma level (1.4 pC1/1 at the 2.83 sigma level) also assuming that I liter of sample is ,
used and 1/2 gram of sample residue is mounted on the planchet. R ese j figures are based upon a nominal 200 minute counting time and upon a representative emciency of 0.02 and a background of 0.1 cpm.
The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma l
MDL for gross beta is 0.9 picocuries per liter and the MDL for gross alpha is O.3 picoeuries per liter. These values reflect a beta counting efficiency of 0.38 i and an alpha counting emciency of 0.18.
B-4
l h YNE ISOTOPES PRO-042-5 l
DETEIGENATION OF GAMMA EMITTING RADIOISOTOPES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. he sample is then counted for at least 1000 minutes with a shielded Ge(L1) 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 at least 1000 ;
l minutes with a shielded Ge(LI) detector coupled to a mini-computer-based data
! acquisition system which performs pulse height analysis.
l Fish 1 1
1 As much as possible (up to the total sample) of the edible portion of the !
sample is loaded into a tared Marinelli and weighed. He sample is then counted for at least 1000 minutes with a shielded Ge(LI) detector coupled to a i mini-computer-based data acquisition system which performs pulse height analysis.
Soils and Sediments l
Soils and sediments are dried at a low temperature, less than 100*C.
The soil or sediment is loaded fully into a tared, standard 300 cc container and l weighed. The sample is then counted for at least six hours with a shielded l Ge(LI) detector coupled to a mini-computer-based data acquisition system l which performs pulse height analysis.
Charcoal Cartridges (Air Iodine)
Charcoal cartridges are counted up to five at a time, with one posiuoned l 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. 'Ihe 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, posidoned on the face of the detector.
Air Particulate
'Ihe four or five (depending on the calendar month) air particulate filters for a monthly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(L1) detector 1
B-5 l
TELEDYNE PRO-042-5 l ISMOPES )
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 l
I abundance, half-life, detector efficiency, and net counts in the peak region. I The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume or pC1/ mass:
RESULT = (S-B)/(2.22 t E V F DF) l TWO SIGMA ERROR = 2(S+B)1/2/(2.22 t E V F DF) l i
LLD = 4.66(B)1/2/(2.22 t E V F DF) l where: S = Area, in counts, of sample peak and background (region of spectrum ofinterest)
B = Background area, in counts, under sample peak, i determined by a linear interpolation of the !
representative backgrounds on either side of the peak t = length of time in minutes the sample was counted 2.22 = dpm/pCi E = detector efficiency for energy ofinterest and geometry of sample i V = sample aliquot size (liters, cubic meters, kilograms, or grams) i F = fractional gamma abundance (specific for each emitted gamma)
DF = decay factor from the collection to the counting date l
1
'B-6
D LEDYNE ISOTOPES PRO-032-10 l
DETERMINATION OF GROSS BETA IN AIR PARTICUIATE FILTERS 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 l proportional counter. An unused air particulate filter, supplied by T U Electric, 4 t is counted as the blank.
Calculations of the results, the two sigma error and the lower limit of de-tection (LLD), are performed as follows:
RESULT (pC1/m3) = ((S/T) - (B/t))/(2.22 V E) l TWO SIGMA ERROR (pC1/m3) = 2((S/T2+[B/t2))1/2/(2.22 V E)
LLD (pCi/m3) = 4.66(B/t/T)1/2/(2.22 V E) 1 l
where: S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 2.22 = dpm/pCi B-7 L
D LEDYNE ISOIDPES PRO-032-11 i DETERMINATION OF RADIOIODINE IN Mim AND WATER SAMPLES Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove lodine from the sample.
'Ihe iodine is then stripped from the resin with sodium hypochlorite solution, is i reduced with hydroxylamine hydrochloride and is extracted into toluene as free l iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable lodide content of the milk or the water with a specific ton electrode.
Calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/1, are performed as follows:
RESULT = (N/ At-B)/(2.22 E V Y DF)
TWO SIGMA ERROR = 2((N/ At+B)/At)1/2 (2.22 E V Y DF)
LLD = 4.66(B/ At)1/2/(2.22 E V Y DF) where: N = total counts from sample (counts)
At = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efIlciency of the counter for I-131, corrected for self absorption effects by the formula:
= Es(eXP-0.0085M)/(exp-0.0085Ms)
Es = efficiency of the counter determined from an I-131 standard mount l Ms = mass of PdI2 on the standard mount, mg
! i M = mass of PdI2 on the sample mount, mg l B-8 U
1 n 1r,LEDYNE PRO-032-12 ISOTOPES DETERMINATION OF RADIOIODINE IN VEGETATION SAMPLES BroadleafVegetation
)
This procedure presents radiochemical methods for determining the I-131 activity in vegetation samples. Stable iodide carrier is first added to 25-100 grams of the chopped sample. The sample is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. 'Ihe l melt is dissolved in water, filtered and treated with sodium hypochlorite. The l l iodine is then reduced with hydroxylamine hydrochloride and is extracted into toluene. It is then back-extracted as lodide into sodium bisulfite solution and is precipitated as palladium iodide, The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.
Calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/1, are performed as follows:
RESULT = (N/ At-B)/(2.22 E V Y DF)
TWO SIGMA ERROR = 2((N/ At+B)/At)1/2/(2.22 E V Y DF)
LLD = 4.66(B/ At)1/2/(2.22 E V Y DF) where: N = total counts from sample (counts)
At = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi l V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collecuon to the counting date E = efP.clency of the counter for I-131, corrected for self absorption effects by the formula:
= Es(exp-0.0085M)/(exp-0.0085Msl l
l Es = efficiency of the counter determined from an 1-131 standard mount Ms = mass of PdI2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg B-9
T 'IELEDYNE PRO-342-17 ISUTOPES l
ENVIRONMENTAL THERMOLUMINESCENT DOSInECTRY (TLD)
Teledyne Isotopes uses a CaSO4:Dy thermoluminescent dosimeter (TLD) which the company manufactures. 'Ihis material has a high light output, neg-11gible thermally induced signal loss (fading), and negligible self dosing. 'Ihe energy response curve (as well as all other features) satisfles 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 Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (lumincscence) is recorded. 'Ihe TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. 'Ihis pro-vides a calibration of each area of each TLD after every field use. The transit controls are read in the same manner.
Calculation of results and the two sigma error in net milliRoetgen (mR) are l performed as follows: l RESULT D= (D1+D2+D3+D4 )/4 TWO SIGMA ERROR = 2((D1-D)2+(D2-D)2+(D3-D)2+(D 4 -D)2)/3)1/2 .i where: D1 = the net mR of area 1 of the TLD, and similarly for D2, D3, and D4
= Il K/R1 - A l 11 = the instnunent reading of the field dose in area 1 K = the known exposure by the Cs-137 source R1 = the instrument reading due to the Os 137 dose on area 1 l
A = average dose in mR, calculated in similar manner ;
l as above, of the transit controlTLDs I
l B-10
F . , ,
T 1ELEDYNE PRO-032-35 ISOTOPES DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION Ten milliliters of water is added to 10 ml of liquid scintillation solution in a 25 mi vial. The sample is inserted into a Liquid Scintillator and counted for 100 minutes.
Calculations of the results, the two sigma error and the lower limit of detection (LLD), are performed as follows:
1 RESULT (pC1/1) = (N-B)/(2.22 V E)
! TWO SIGMA ERROR (pCi/1) = 2((N + B)/At)1/2/(2.22 V E)
LLD (pC1/l) = 4.66(B/At)1/2/(2.22 V E) :
where: N = the gross epm of the sample B = the background of the detector in cpm 2.22 = conversion factor changing dpm to pCi l V = volume of the sample in ml E = efficiency of the detector At = counting time for the sample B-11 I
I I
l 1
1 1
1 APPENDIX C EXCEPTIONS TO THE 1997 REMP C-1
I APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1997 l DATE OF REASONS FOR LOSS /
LOCATION DESCRIPTION SAMPLING EXCEFTION SW-12.7 Food Product 01/28/97 Sample not available E-3.5 Food Product 01/28/97 Sample not available SW-12.7 Food Product 02/04/97 Sample not available E-3.5 Food Product 02/04/97 Sample not available SW-12.7 Food Product 03/25/97 Sample not available E-3.5 Food Product 03/25/97 Sample not available SW-12.7 Food Product 04/01/97 Sample not available E-3.5 Food Product 04/01/97 Sample not available j SW-12.7 Food Product 05/27/97 Sample not available E-3.5 Food Product 05/27/97 Sample not avaikhle SW-12.7 Food Product 06/24/97 Sample not available E-3.5 Food Product 06/26/97 Sample not available SW-12.7 Food Product 07/29/97 Sample not available SW-12.7 Food Product 08/26/97 Sample not available SW-12.7 Food Product 09/30/97 Sample not available E-3.5 Food Product 09/30/97 Sample not available SW-12.7 Food Product 10/28/97 Sample not available E-3.5 Food Product 10/28/97 Sample not available i SW-12.7 Food Product 11/25/97 Sample not available E-3.5 Food Product 11/25/97 Sample not available c-2
4 APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1997 !
DATE OF REASONS FOR LOSS /
LOCATION DESCRIFFION SAMPLING EXCEFFION SW-12.7 Food Product 12/30/97 Sample not available E-3.5 Food Product 12/30/97 Sample not available l WSW-5.35 TLD (Qtriy) 01/03/97-04/02/97 TLD chips missing from case. '
WSW-7 TLD (Qtrly) 1/03/97-04/02/97 TLD chips missing from case.
l l
C-3
1 1 b l
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l APPENDIX D EXCEEDED REPORTING LEVELS i l
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D-1 C.
i APPENDIX D EXCEEDED REPORTING LEVELS of the analytical measurements exceeded any notification l
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i D-2 e
I APPENDIX E LAND USE CENSUS 1
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1UELECTRIC 1
l COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS i
1997 ,
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COMANCllE PEAK STEAM ELECTRIC STATION P.O. Dox 1002 Glen Rtn4, Texas 360431002 L.... _m
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l July 14,1997 i
o COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS 1997 l
The Land Use ' Census identified receptors within a five (5) mile radius of the plant in each of the l sixteen (i6) meteorological sectors. The Land Use Census was conducted June 1 land 12,1997 and includes the following items:
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l 1. Evaluation of the 1997 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 s
- 6. Enviror. mental Sample Locations Table
! 7. Environmental Monitoring Locations Map- 2 Mile Radius i 8. Environmental Monitoring Locations Map- 20 Mile Radius
- 9. 5 Mile Sector and Road Map with Field Data'
- The original map is vaulted along with this census, copies of this census will not contain a copy of this map unless specifically requested..
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Evaluation of the 1997 Land Use Census 4
The results of the 1997 Land Use Census were reviewed for impact on the Radiological
. Environmental Monitoring Program (REMP). The speci6c 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.
l 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 l
! 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 i the specified distances. Currently the only location where milk samples are collected is at a control
- location (SW - 14.5).
l l Since not all milk samples are available, the broadleaf vegetation sampling specified in ODCM Table 3.12-1 is being performed. Broadleaf sample recluirements are such that samples of broadleaf vegetation are to be collecced 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 l
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 pmhctuie erp! ' h- : - Hi -*-- 5--+~ n:NE o o mn e a u ann trom one connoi location (SW - 12.7). No changes are required in the food product program.
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The 1997 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, tdtium X/Q is 4.36E-6, and the D/Q value is 3.34 E-8. All these values are conservative based on the 1997 land use census data and therefore no changes are required in the dose calculation i parameters as veri 6ed by the Seld data.
- X/Q units are Sec/ cubic meter
- D/Q units are inverse square meters l
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! Nearest Resident by Sector, Distance, X/Q and D/Q .
Sector Distance (Miles) X/Q D/Q l
1-N 2.2 9.28E-07 5.32E-09 NNE 2.2 5.58E-07 2.90E-09
- NE 2.2 3.92E-07 1.42E-09 ENE- 2.4 2.58E-07 7.08E-10 E 2.4 3.02E-07 6.62E-10 ESE 2.0 4.7E-07 1.20E-09 i
SE . 8.3E-07 3.40E-09 1.9 l- SSE 1.5 1.1E-06 6.60E-09 l
S. 1.5 8.5E-07 5.20E-09 l SSW 3.9 1.06E-07 3.62E-10 l
SW l.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 ;
I WNW 3.0 3.76E-07 1.07E-09 %
NW 2.7 6.98E-07 2.24E-09 i
NNW 2.8 5.28E-07 2.10E-09 Note: The annual average X/Q used for dose calculations is 3.30E-06 sec/ cubic meter.
The Tritium value X/Q used for dose calculations is 4.36E-06 sec/ cubic meter.
The annual average D/Q used for dose calculations is 3.34E-08 inverse square meters.
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! Nearest Garden by Sector, Distance and D/Q l 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 ESE 3.3 3.96E-10 f
l SE 2.4 1.84E-09 SSE 2.2 2.64E-09 l
S None None l SSW None None l
! SW l.5 2.5E-09 WSW None None W 3.3 4.42E-10 l
WNW None None NW None None l NNW None None 5
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l Nearest Milk Animal by Sector, Distance and D/Q ,
i Sector Distance (Miles) D/Q !
N None None ,
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l l NNE None None NE None None ENE None None E None None ESE None None l
t SE None None SSE None None S None None ,
SSW ' None None l
l SW None None WSW None None w
, W None None l
l- WNW None None NW None None ,
4 NNW None None i
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! Population by Sector and Distance l Sector 0-1 1-2 2-3 3-4 '4-5 Total N - - 5 32 88 125 O
NNE - - 8 82 13 103 l l
l NE - - 56 66 207 329 ENE - - 74 8 29 111 l E - - 67 160 19 246 l
l ESE -
3 11 75 133 222 SE -
16 61 32 61 170 SSE -
51 59 35 2032 2177 S -
29 21 40 133 223
! SSVV - - - 3 40 43 l
l SW - 80 5 43 32 160 l
l WSW - 215 3 11 - 229 s
W -
24 11 21 8 64 WNW - - - 40 56 96 NW - - 3 - - 3 l
NNW - - 3 43 16 62 TOTAL - 418 387 691 2867 4363 l
Based on an average of 2.66 residents per house. This average was obtained from North Central Texas Council ofGovernments for Hood and Somervell Counties and is derived from an average residents per house of 2.57 and 2.74, respectively.
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Environmental Sample Locations Table !
! Sampling Point Location Sample Type
- Al - N-1.45 (Squaw Creek Park) A A2 N-9.4 (Granbury) A ,
l A3 E-3.5 (Children's Home) A l 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 l R1 N-1.45 (Squaw Creek Park) R j R2 N-4.4 R R3 N-6.5 R ,
( R4 N-9.4 (Granbury) R R5 NNE-1.1 R l R6 NNE-5.65 R l- R7 NE-1.7 R R8 NE-4 8 R R9 ENE-2.5 R RIO ENE-5.0 R R11 E-0.5 R R12 E-1.9 R R13 E-3.5 (Children's Home) R R14 E-4.2 R R15 -
ESE-1.4 R Rio E52-4.;
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Environmental Sample Locations Table (cont.)
Sampling Point Location Sample Type
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R19 SE-4.6 R l 1
R20 SSE-1.3 R l 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 i
R26 SSW-4.4 (State Park) R '
R27 SW-0.9 R R28 SW-4.8 (Girl Scout Camp) R i R29 SW-12.3 (CONTROL) R R30 WSW-1.0 R !
I 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 l 1
R37 WNW-5.0 R l R38 WNW-6 7 R i
R39 NW-1.0 R R40 NW-5.7 R R41 NW-9.9 (Tolar) R
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NNW-1.35 R R43 10;7/ J.5 9.
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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 l SW4 NE-7.4 (Lake Granbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW 2 SW6 NNW-0.1 (Squaw Creek Reservoir) SW/DW 5
- GW1, W-1.2 (NOSF Potable Water) GW GW2 WSW-0.1 (Plant Potable Water) GW '3 GW3 SSE-4.6 (Glen Rose) GW' GW4 N-9.3 (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
- SS4 SE-5.3 (Squaw Creek) SS M4 SW-14.5 (CONTROL) M F1 ENE-2.0 (Squaw Creek Reservoir) F F2. NNE-8.0 (Lake Granbury) F FPl ENE-9.0 (Leonard Bros. Pecan Farm) FP ,
rP5 Sm>7.7 (en rrynig up FP6' E-3.5 (Happy ftll Farm) it >
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Environmental Sample Locations Table (cont.)
l Sampling Point Location Sample Type
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, BL1 N-1.45 BL 1
.BL2 SW-1.0 BLs 1
BL3 SW-13.5 (CONTROL) BL 8 l
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- 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 j NOTES: 1) The municipal water system for the City of Granbury is supplied by surface water i
from Lake Granbury (location SW2) and ground water (location GW4). Each of I l these supplies is sampled. These samples are not required for compliance with !
Radiological EfBuent Control 3/4.12.1. Table 3.12-1, because they are not affected j l by plant discharges. j
- 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 l possible sources of water are sampled.
- 4) Ground water supplies in the plant site area are not sfrected by plant liquid effluents ,
as discussed in CPSES FSAR Section 2.4.13 and are therefore not required to be l monitored for radioactivity to meet the requirements of the Radiological Effluent l Control 3/4.12.1, Table 3.12-1.
l 5) Broadleaf sampling will be performed at the specified locations if milk samples are j unavailable from any location.
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g/ ' \\ \ s / s Environmental Sample Locations Map - 2 Mile Radius L.
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