ML20073H580
| ML20073H580 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1990 |
| From: | TELEDYNE ISOTOPES |
| To: | |
| Shared Package | |
| ML20073H577 | List: |
| References | |
| NUDOCS 9105070183 | |
| Download: ML20073H580 (99) | |
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COMANCHE PEAK STEAM ELECTRIC STKflON
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RADIOLOGICAL ENVIRONMENTAL l MONITORING PROGRAM 1990 ANNUAL REPORT
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T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1990 ANNUAL REPORT Prepared by TELEDYNE ISOTOPES 50 Van Buren Avenue Westwood, NJ 07675 I
I T U ELECTRIC REVIEW / APPROVAL I Reviewed by: /7/ O. c / m n 4t -A - 9)
Date M.0, Green g Environmental Supervisor 49, Y -l S 'f/
Reviewed by: ,
Date D.C. KQ g Sr. Engineer, Radiation Protection Y- / f~
Approved by: M Uate '
R.d. Prince I Radiation Protection Manager TELEX 134474 TDYl807 WTWD * *
- EasyLint 62877194 * *
- P AX (201) 664 6666
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TABLE OF CONTENTS 1
SECTION TITLE PAGE i
INTR 00VCTION..............................................
- 1. 1 I- A. Site and St at ion Description. . . . . . . . . . . . . . . . . . . . . . . . . . 2 l
B. Object ives and Overvi ew of the. . . . . . . . . . . . . . . . . . . . . . . . ,2 CPSES Monitoring Program I !!. PROGRAM DESCRIPT10N....................................... 6 A. Sample Locations B. Sampling Methods and Procedures ......................,7
- 1. Di re c t R a d i at i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7
- 2. Air Part icul ates/Ai r lodine. . . . . . . . . . . . . . . . . . . . . . . 8
- 3. Milk.............................................. 8 I
4 Water.............................................8
- 5. Fish.............................................10 l 6.
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S h ore l i n e S e d i me n t . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 Food Products.................................... 10
- 8. Broadleaf Vegetatien............................. 10 C. Interlaboratory Comparison Program 11
SUMMARY
AND 0!SCUSSION OF 1990 ANALYTICAL RESULTS........ 12 A. D i r e c t R a d i a t i o n . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 14 B. Air P art icu l ates/Ai r lodi ne. . . . . . . . . . . . . . . . . . . . . . . . . . 15 C. Milk..........................................,-...... 15
- 0. Water................................................ 16 E. Fish.................................................17 F. Shoreline Sediment................................... 17 G. Food Products........................................ 18 H. Broadleaf Vegetation................................. 18 ii
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't IV. CONCLUSIONS..............................................20 1
V. REFERENCES...............................................22 VI. DATA TABLES.............................................. 24 APPENDICES 4
APPENDIX A EPA Cross Check Program..................................,A-1 APPENDIX B- Synopsis of Analytical Procedures....................... ,8-1 APPENDIX C E xcep t i ons to t he 19 90 R EMP . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .C-1 APPENDIX D Exceeded Reporting Levels................................ 0-1 APPENDIX E Land Use Census...........................................E-1 i
APPENDIX F REMP 1988 ANNUAL REP 0RT...................................F-1 REMP 1989 ANNUAL REP 0RT..................................,G-1 J
I APPENDIX G l11 i
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I I LIST OF TABLES TABLE TITLE PAGE 1 CPSES Radiologi cal Envi ronment al . . . . . . . . . . . . . . . . . . . . . . . . . . . . 25 Monitoring Program 2 Di rect R adi at ion - Thermolumi nescent. . . . . . . . . . . . . . . . . . . . . . . . 29 Dosimetry 3 Concentrations of lodi ne-131 i n Fi ltered Ai r. . . . . . . . . . . . . . . . 31 4
Concentrations of Gross Beta Emitters in Air Particulates... 34 5 Concentrations of Gamma Emitters in Air Particulate Filters. 37 6 Concentrations of lodine-131 in Milk........................ 39 7
Concentrat ions of Gamma Emi tters i n Mi lk . . . . . . . . . . . . . . . . . . . . 40 8 Concentrations of Gamma Emitters in Groundwater............. 42 9 Concentrations of Tri t ium i n Groundwater. . . . . . . . . . . . . . . . . . . . 43 10 Gross Bet a Concentrations in Water-Surf ace /0rinking. . . . . . . . . 44 L. 11 Concentrations of Gamma Emitters in Water-Surf ace /0rinking.. 45 12 Concentrations of Iodine-131 in Water-Surface / Drinking...... 47 13 Concentrations of Tritium in Water-Surf ace /0rinking. . . . . . . . . 48 l 14 Concentrations of Gamma Emitters in Surf ace Water. . . . . . . . . . . 49 l
l 15 Concentrations of Tritium in Surf ace Water. . . . . . . . . . . . . . . . . . 51 16 Concentrat ions of Gamma Emi tters i n F i sh. . . . . . . . . . . . . . . . . . . . 52 17 Concentrations of Gamma Emitters in Sediment................ 53 18 Concentrations of Gamma Emi tters in Food Products. . . . . . . . . . . 54 19 Concentrations of Gamma Emitters in Broadleaf Vegetation.... 55 ll 20 Radiological Environmental Monitoring Program Summary -
January 1 to December 31, 1990 ............................. 57 I
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i' LIST OF FIGURES i i I FIGURE TITLE '
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l 1 Radiological Envi ronmental Moni toring Locations, . . . . . ,, . . . 27 i
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I INTRODUCTION I
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I 1, INTRODUCTION l l
The Radiological Environmental Monitoring Program for the Comanche Peak Steam Electric Station was conducted under contract with T U Electric, l This report covers the period from January 1,1990, through December 31, i 1990 and summarizes the results of measurements and analyses of data obtained from samples collected during this interval, A. Site and Station Description l Comanche Peak Steam Electric Station (CPSES) consists of two PWR units, each designed to operate at a power level of about 1150 megawatts (electri-cal), The station is located on Squaw Creek Reservoir in Somervell County about 40 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 One was issued on April 17, 1990, and commercial operation was declared on August 13, 1990, During 1990, Unit 1 operated for approximately 140 effective full power days. Unit 2 is still under construction with completion estimated in 1993.
B, Objectives and Overview of the CPSES Monitoring Program United States Nuclear Regulatory Commission (USNRC) regulations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA) (10 CFR 50,34). To assure that these criteria are met, each license authorizing reactor operation includes technical specifications (10 CFR 50,36a) governing the release of radioactive effluents.
In-plant monitoring is used to assure that these predetermined release limits are not exceeded. However, as a precaution against unexpected l .
and undefined processes which might allow undue accumulation of radioactivity in any sector of the environment, a program for monitoring the plant environs i is also included.
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I l Sampling locations were selected on the basis of local ecology, meter-ology, 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 Specifica-tions(4) , and the CPSES Offsite Dose Calculation Manual (0DCM)(5),
I In 1990, the Radiological Environmental Monitoring Program included the me asurement of ambient gamma radiation by thermoluminescent dosimetry; the determination of gamma emitters in sediment and fish; the determination of airborne gross beta, gamM emitters, and iodine-131; the measurement of tritium and gamma emitters in surf ace water; the measurement of tritium and gamma emitters in groundwater; the measurement of gross beta, tritium, I-131 and gamma emitters in drinking water; the determination of gamma emitters and I-131 in milk; and the measurement of gamma emitters in food products and I
gamma emitters and I-131 in broadleaf vegetation. Samples were collected by CPSES Environmental Personnel. Sample analyses were performed by Teledyne isotopes.
The regulations governing the quantities of radioactivity in reactor l
l effluents allow nuclear power plants to contribute, at most, only a few percent increase above normal background radioactivity. Background levels at g any one location are not constant but vary with time as they are influenced lg l
by external events such as cosmic ray bombardment, weapons test f allout, and l seasonal variations. These levels also can vary spatially within relatively short distances reflecting variations in geological composition. To dif-ferentiate between background radiation levels and increases resulting from operation of CPSES, the radiological surveys of the plant environs are I
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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 obtains data which, when considered along with the data obtained in the preoperational phase, assist in the evaluation of the radiological impact of plant operation.
Preoperational measurements were conducted at CPSES f rom 1981 to 1989 These preoperational measurements were performed to:
1 Evaluate procedures, equipment and techniques.
2 Identify potentially important pathways to be monitored after the plant is in operation.
- 3. Measure background levels and their variations along poten-tially 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 conducted to:
- 1. Verify that measurable concentrations of radioactive materials and levels of radiation are not higher than expected on the basis of the I effluent measurements and modeling of the environmental 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 boundary that may impact the principal pathways of l
exposure.
This report documents the first year of operational measurements and is submitted in accordance with the requirements of the CPSES Offsite Dose Calculation Manual, Part 1, Administrative Control 6.9.1.3. As required, l reports of the preoperational Radiological Environmental Monitoring Progam l
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4 I for the two years prior to initial criticality are included as appendicies to this report. Appendicies F and G contain the 1988 and 1989 reports, respec-tively.
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- I I PROGRAM DESCRIPTIONS l
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!!. PROGRAM DESCRIPTION A.- Sample locations Seventy five (75) locations within a radius of 20 miles from the CPSES site were included in the monitoring program for 1990. The number and location of monitorino points were determined by considering the locations where the highest of f-site environmental concentrations have been predi;ted from plant effluent source terms, site hydrology, and site meterolo jical 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 1990 Land Use Census are provided in Appendix E. Changes to or additions of sampling locations were not required based on the 1990 Land Use Census.
The Radiological Environmental Monitoring Program for Comanche Peak is summarized in Table 1. Figure 1 shows the locations of the various sampling points.
B. Samplino Methods and Procedures To derive meaningful and useful data from the Radiological Environmental Monitoring Program, sampling methods and procedures 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.
- 1. Direct Radiation l 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 l
I on Radiological Monitoring (Revision 1, November 1979).(1) The area around the station was divided into 16 radial sectors o" 22-1/2 degrees each. TL0s were placed in all sectors. TLDs 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 addi-tional 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 quarterly 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 source.
- 2. Air Particulates/ Air Iodine Air particulate and air iodine samples were collected f rom the 8 locations described in Table 1.
Each air particulate sample was collected by drawing air through a 47-millimeter di ameter glass-fiber filter. Air iodine was collected by drawing air through a TE0A impregnated charcoal cartridge which was connected in series behind the filter. The filters and charcoal cartridges were collected weekly by CPSES staff. In the laboratory, air particulate filters t were analyzed for gross beta activity and were composited quarterly for gamma
- spectrometry analysis. Charcoal cartridges were analyzed for iodine-131,
- 3. Milk l
Milk samples were collected by CPSES staff monthly for the period January through April. May through December samples were collected bi-monthly, except for July when three samples were collected. There were two milk sampling locations; one indicator location (SSE-2.2) and one control 8
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location (SW-13.5). Upon arrival at the laboratory, the milk samples were I
promptly analyzed f or gamma emitters and f or 1-131 by utilizing radio-chemistry techniques.
4 Water The CPSES staff collected water at 11 locations. Surf ace water was collected at four locations (N 19.3, ESE-1.4, N-1.5 and NE-7.4) . Location N-1.5 provider samples representative of Squaw Creek Reservoir surf ace water at a loca*. ion 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. Location NE-7.4 provides samples of Lake Granbury surf ace 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.
Surf ace water samples from Squaw Creek Reservoir locations were col-lected weekly and composited for monthly gamma isotopic analysis. Samples from Lake Granbury locations were collected monthly and analyzed by gamma spectoscopy. All surf ace water samples were also composited quarterly by location for tritium analysis.
Surf ace-drinking water was collected at two locations (N-9.9 and NNW-0.1). Samples of Squaw Creek Reservoir water which is used for potable water for the CPSES plant site, were collected at Location NNW-0.1. Location N-9.9 was used to sample surf ace water from Lake Granbury near the intake of the City of Granbury potable water plant.
Surf ace-drinking water samples were collected weekly and composited for 1-131 analysis every two weeks and gamma isotopic and gross beta analyses monthly.
There are five groundwater locations (SSE-4.6, W-1.2, WSW-0.1, N-1.45 I '
Ii and N 9.8). ODCM Table 3.1, Note (5) states that groundwater supplies in the site area are not affected by plant effluents and are sampled only to provide confirmation that groundwater is not affected by plant discharges.
Groundwater samples were collected quarterly, Gamma isotopic and tritium analyses were performed by location.
5 Fish Fish samples were collected at two locations for the 1990 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 and October for Station NNE-8 and April and September for Station ENE-2.
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 February and August from Squaw Creek Reservoir at location NNE-1.0. Samples were also collected on the same dates 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 Reservior. CPSES staff collected the sediment samples and shipped them to the laboratory for analysis by gamma spectrometry.
7 Food Products During the period February through December, eleven samples were collected from three sampling locations. Food products were collected from a control (SW-13.5) and two indicator (E-4.2 and ENE-9.0) stations. A total of seven different types of food products were collected during this sampling period. Food product samples were collected by the CPSES staf f and shipped I
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to the laboratory where they were analyzed for gamma emitters.
- 8. 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.
l Collection of broadleaf vegetation started in February 1990, as part of the transition to the operational program required by the ODCM. Broadleaf samples consisted primarily of available tree leaves; if tree leaves were unavailable, native grasses and weeds were substituted.
Gamma isotopic and 1-131 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 participates in the environmental s ample crosscheck program conducted by the U.S. Environmental Protection Agency (EFA).
The purpose of the interlaboratory comparison 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 concen-trations of specified radionuclides and report them to the issuing agency.
The agency then furnishes the known values to the participant laboratory and I 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's participation in the U.S. EPA Interlaboratory Comparison Program for 1990 are provided in Appendix A.
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SUMMARY
AND OlSCUS$10N OF 1990 ANALYTICAL RESULTS l
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SUMMARY
AND DISCUSSION OF 1990 ANALYTICAL RESULTS Data from the radiological analyses of envi ronment al media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laboratories for these analyses are as required in the Teledyne isotopes Quality Assurance manual, IWL-0032-395 and are detailed in Teledyne Isotopes Analytical Procedures manual. A synopsis of analytical procedures is contained in Appendix B of this report.
I Radiological analyses of environmental media characteristically approach and frequently f all celuw the enction limits of state-of-the art measure-ment 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. "ND" (Not Detected) is used periodically in the tables presenting gamma analysis results for various media. It primarily appears under the "Others" column, and indicates that no other detectable gamma emitting nuclides were identified. The Teledyne isotopes 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 reported averaget are based only on concentrations above the limit of detec-tion. 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 period.
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A. Direct Radiation Environmental radiation dose rates determined by thermoluminescent dosimeters (TLDs) are given in Table 2. TLD badges with four readout areas each were deployed at each location on quarterly and annual cycles. The mean l values of four readings (corrected individually fo, response to a known dose and for in-transit exposure) are reported.
A statistical summary of the 1990 data is included in Table 20. For the cuarterly analyses the average dose rate activity of the control locations was 0.13 mR/ day with a range of 0.10-0.16 mR/ day. The average of the indicator locations for the quarterly samples was 0.13 mR/ day with a range of 0.05 to 0.19 mR/ day. For the annual samples: The average activity for the control samples was 0.13 mR/ day. The indicator locations had an average of I 0.12 mR/ day with a range of 0.05-0.19 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 radiation average of 47 mR/yecr for the immediate locale of CPSES is not inconsistent with Oakley's observations.
l Significant variations occur between geographical areas as a result of geological composition and altitude differences. Temporal variations result t
from changes in cosmic ray intensity, local human activities, and f actors l
l such as ground cover and soil moisture.
Anomalies in the 1990 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 0.11 to 0.17), for- the quarterly and annual samples respectively. The 1988 averages for the quarterly and annual indicator locations were 0.16 mR/ day (range of
l 0.10 to 0.20) and 0.15 mR/ day (range of 0.12 to 0.18), respectively. l B. Air Particulates/ Air lodine A total of 410 charcoal cartridges were analyzed for airborne iodine-131 I l
by gamma spectrometry. No iodine-131 was detected at any of the sampling stetions. Results of these measurements are presented in Table 3.
A total of 408 air particulate filters were collected and analyzed for gross beta activity. For 1990 the average gross beta activity for the control location was 0.023 pC1/m3 with a range from 0.011 to 0.052 pCi/m3 For the seven indicator locations the yearly average was 0.022 pCi/m3 with a range from 0.0077 to 0.062 pCi/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; potassium-40, a naturally occurring nuclide, was measured in thirteen samples. The average beryllium-7 activity for the control location was 0.074 pCi/m3 with a range of 0.068 to 0.080 pCi/m3 For the indicator locations, the average beryllium-7 activity was 0.068 pCi/m3 with a range of 0.012 to 0.111 pCi/m3 The average potassium-40 for the control location was 0.014 with a range of 0.012 to 0.015. The average potassium-40 activity for the indicator locations was 0.013 pCi/m3 with a range of 0.0079 to 0.021 pCi/m3 C. Milk There was a total of 38 milk samples collected in 1990; 19 from the indicator location and 19 from the control location. All samples were analyzed for iodine-131 by radiochemistry and for other gamma-emitting l isotopes by gamma spectrometry. Results of these measurements are presented in Table 6 15
No iodine-131 was found in any of tho milk samples. The lower limits of detection can be found in Table 6.
Results of the gamma spectrometry measurements are presented in Table I 7. Naturally occurring potassium 40 was detected in all of the milk samples.
The average activity for the control location was 1305 pCi/l with a range of 1100 to 1520 pC1/1. For the indicator location the average activity was 1233 pCi/l with a range of 1090 to 1360 pCi/1. Cesium-137 was not detected in any of the samples.
D. Water Groundwater samples were collected from five locations during 1990. The samples were analyzed for gamma isotopic and tritium on a quarterly basis, pursuant to the ODCM requirements for groundwater. Twenty samples were analyzed for gamma emitters by gamma spectrometry. The gamma spectrometry analyses showed no detectable activity above the LLD for all samples.
Quarterly composites for each sampling location were analyzed for tritium.
No tritium was detected. Results of these analyses are contained in Table 8 and 9 respectively.
Surf ace / drinking water was collected from two stations. All samples were analyzed for gamma emitters; results were below the lower limit of detection. Thirty samples were analyzed for gross beta activity. The indicator station had an average activity of 15 pC1/1 with a range of 12 to 18 pCi/1. The control station had an average activity of 11 pCi/l with a range of 5.4 to 17 pCi/1. The quarterly composites for tritium were below the lower limit of detection.
Iodine-131 analyses by radiochemistry were performed on 48 samples of surf ace / drinking water. There was no measurable activity. Results of these analyses are contained in Tables 10-13.
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l Surface water was sampled from four locations during 1990. Samples were analyzed for gamma isotopic on a monthly basis and tritium composites on a quarterly basis, per the ODCM requirements for surf ace water. Fifty-two samples .ere analyzed by gamma spectrometry. No radioactivity was detected above the lower level of detection. Sixteen composited surf ace water samples were analyzed for tritium and all were below the lower level of detection.
Results are presented in Tables 14 and 15 respectively.
E. Fish The results of gamma isotopic analyses of fish samples collected during 1990 are presented in Table 16. A total of ten samples were analyzed, seven from the indicator location (ENE-2) and three from the control location (NNE-8). Sampling efforts concentrated on the larger edible species of commercial and/or recreational importance.
Cesium-137,was detected in one of the samples with an average activity of 22 pCi/kg wet. This level of cesium-137 is similar to levels seen in preoperational neasurements. In 1989 cesium-137 was detected in one sample at 13 pCi/kg. In 1988 three positive measurements were observed with an average activity of 16.9 pCi/kg (range 9.9 to 25.1).
Naturally occurring potassium-40 was detected in all samples. The average potassium-40 concentration for the seven indicator samples is 1782 pCi/kg wet with a range of 753 to 2990 pCi/kg wet. The average concen-tration for the control location is 2260 pCi/kg wet with a range of 1110 to 2870 pC1/kg wet.
F. Shoreline Sediments The processes by which radionuclides and stable elements are concen-
-l trated in bottom sediments are complex, involving physiochemical interaction in the environment between the various organic and inorganic materials from the watershed. These interactions can proceed by a myriad of steps in 17
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which the elements are absorbed in or displaced from the surf aces of collodial particles enriched with chelating organic materials. Biological action of bacteria and other benthic organisms also contribute to the con-centration of certain elements and in the acceleration of the sedimentation process.
Results of the gamma isotopic analyses of the sediments sampled from the CPSES environment are given in Table 17 For 1990 three locations, one control and two indicators, were sampled semiannually. The average, fraction of detectables, and range of radionuclide concentrations are summarized in Table 20.
Naturally occurring gamma emitters found in detectable concentrations were K-40, Pb-212, Ra-226, Bi-214, Pb-214 and Th-228. Cesium-137 was measured in one sample from the indicator location with an activity of 19.2 pCi/kg. Cesium-137 was measured in 1989 at the same location with an activity of 20.6 pCi/kg.
G. Food Products Results of gamma isotopic analyses of food samples are contained in Table 18. A total of 11 samples were analyzed from 3 locations. Potassium-40, a naturally occurring isotope, was found in 11 samples. The average l potassium-40 activity for the control location was 4160 pCi/kg wet with a range of 1890 to 5610 pCi/kg wet. For the indicator locations the average potassium-40 activity was 1924 pCi/kg wet with a range of 125 to 3440 pCi/kg wet. Naturally occurring beryllium-7 was detected in one sample from control station SW-13.5; the activity was 426 pCi/kg wet. No Cs-134 Cs-137 or I-131 were detected in food products during 1990.
H. Broadleaf Vegetation Results 'of gamma isotopic analyses of broadleaf vegetation samples are contained in Table 19. A total of 39 samples were analyzed from 3 18
I locations. Potassium-4*, a naturally occurring isotope, was found in 39 samples. The average potassium-40 activity for the control location was 6052 pCi/kg wet with a range of 1210 to 8510 pCi/kg wet. For the indicator locations the average potassium-40 activity was 4843 pCi/kg wet with a range of 8.4 to 11900 pCi/kg wet. Naturally occurring beryllium-7 was detected in twenty-six indicator samples with an average activity of 2910 pC1/kg wet; the range was 387 to 12200 pCi/kg wet. Thirteen samples from control station, l SW-13.5 were found to have beryllium-7 with an average activity of 1533 pCi/kg (wet) and a range of 346-4280 pCi/kg (wet). One indicator sample and l one control sample were found to contain cesium-137 Cesium-137 was measured 1
at location N-1.45 with an activity of 197 pCi/kg. This satidple was collected I
l 2/13/90, prior to initial criticality of Unit 1. Analysis of a sample from the control location collected 12/18/90 showed a Cs-137 activity of 21.9 oCi/kg. Similar activities were observed in preoperational measurements.
Iodine-131 and cesium-134 were below the lower limit of detection in all samples.
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I CONCLUSIONS I
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I I
I I
I 20
1 l
IV. CONCLUSIONS I
It'is concluded from the levels obtained in environmental samples during 1990 and comparison of these levels to preoperational measurements and operational controls, that the operation of CPSES in 1990 did not result in an increase in measureable levels of radiation or radioactive materials in the environment. The atmospheric environment was sampled for airborne particulate matter, radioiodine, and direct radiation. The terrestrial environment was sampled for milk, groundwater, surface-drinking water, food products and broadleaf vegetation. The aquatic environment was sampled for surf ace water, fish and shoreline sediment. 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.
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I 21
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REFERENCES E
I l
I -
22
I l
l V. REFERENCES l
1
- 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.
I j 3. Oakley, D. C., " Natural Radiation Exposure in the United States",
ORP/SID 72-1 Office of Radiation Programs, V. S. Environmental
, Protection Agency, Washington, D. C., June 1972.
l
, 4 Comanche Peak Steam Electric Station Technical Specifications, i Unit 1.
l S. Comanche Peak Steam Electric Station Offsite Dose Calculation l Manual.
l l
l l
l 23
( 3 I
b I
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- D
- I
- I L I
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I w - __. J
m M M M M M M M M m m m m m m m M M M TABLE I (Pay I of 2)
CPSES RADIOLOGICAL EntlR0etENTAL MonIT0itING PR9GIAM - 1990 Identification by Sector end Distance Sampling Analyt ic al humber of .
Erequency (a)
Locatloses (Miles) Frequency (a) Analyses Media Gamma Exposure 43 m-1.45; n-4.4; s-6.5; Q.A Thermolissinesc ent 0.A m-9.4; anE-1.1: Dosimetr y amE-5.65; mE-1.7; WE-4.8; ENE-2.5; ENE-$.0; E-0.5; E-1.9; E-3.5; E-4.2; E5E-1.4; ESE-4.7; SE-1.3; SE-3.85; SE-4.6; $5E-1.3;
$5E-4.4; 55E-4.5; 5-1.5; 5-4.?; 55W-1.1; 55W-4.4;
$W-0.9; W -4.8; 5W-12.3; W5W-1.0; WW-5.35; W5W-7.0; W-1; W.2; W-5.5; m
e WW-1; WW-5.0; WW-6.7; W -1; W -5.1; W -9.9; mw-1.35; hw 4.6 W Gross Beta W Air Particulate. 8 N.9.4 E-3.5; 55E-4.5 Gesume sentrometry Filter GC Air Iodine SW-12.3; Gamma spectress try w -1.0; #-1.45. SW/W9 -0.95 Eharcoal Eartridy W 5/55W-1.2 4 n-19.3; E5E-1.4; m-1.5 m (b) Gamma SpMtrometry M Surf ace water NE-7.4 M-3 UC 55E -4.6 0 Gmune Spectrometry 0 Groundwater 5 W-1.2; WW-0.1 E-9.8; N-1.45. H-3 Q 2 mMW-0.1; N-9.9 SM (c) Gross Beta M Water-Surface Gasuna $patrosm try M Drink ing *>t I-131 H-3 QC Iw
M M M M M M M E E M M M M -
TABLE I (Page 2 of 2)
CPSES RADIOLOGICAL EmVIRow(mIAL MONITORING ruoGpe - 1990 Identification by Sampling Analyt ic al misaber of Sector and Distance f requency (a)
Frequency (a) Analyses Media locations (Miles)
Gausa Spatrumetry 5A Sediment 3 m-9.9; SE-1. NE-7.4 5A 8mE-8; ENE-2 5A Gamma spectrometry 5A Fish 2 2 SW-13.5; 55E-2.2 SM (d) 1-I31 9 . (d)
Milk Gawaa Spatr w try SM. (d) to os E-4.2; SW-13.5; ENE-9.0 fH Gamma 5pectrometry MH Fcod Products 3 pH I-131 Gamma spectrometry M Broadleaf 3 t'l.45; SW-1.0; Sw-13.5 M M
1-131 Vegetation (a) Frequency Codes Are W = iseekly M = Monthly Q = Quarterly E = Overterly Composite SM = Semimonthly (i.e.. Once per 2 weet period) 904 = Monthly during availability for harvest SA = Semiannual A = Annual Samples from Lake Granbury (b) Surf ace water samples from Sqeaw Creet Reservoir are s>3nthly composites of weekly grab samples.
are monthly composites of weekly grab samples amen Lake Granbury is receiving letdown from Squaw Creek Reservoir; otherwise they are monthly grab samples.
(c) Drink tog water samples are composite of weekly grab samples over a 2 waet period when 1-131 analysis 's perfow; otherwise they are su>nthly composites of weekly grab samples.
Otherwise, samles are .ollated (d) Milk seaple (ollet. tion and analysis frequency is seetmanthly when animals are on pasture.
and analyred monthly.
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RADIOLOGICAL ENVIRONMENTAL 5 i'r AITRTURE L s y 4 10
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lI Figure 1 (Page 2 of 2)
! KEY OF ENVIRONMENTAL SAMPLING LOCATIONS I
I
, S ampli ng Locatsen Sample Sampling Location Sample Point (Sector-Miles) Type
- Point (Sector Miles) Type
A A
R29 R30 R31 SW 12.3 WSW-1.0 WSW-5.35 R
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S/SSW-1.2 A R32 WSW-7.0 l
AS R A6 SW 12.3 A R33 W 1.0 R A7 SW/WSW-0.95 A R34 W-2.0 R A8 NW-1.0 A R35 W-5.5 R I R36 R37 R38 WNU-1.0 WNW-5.0 WNW-6.7 R
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R R3 N-6.5 R R43 NNW-4.6 R R4 N 9.4 R SW1 N-1.5 SW R5 NNE-1.1 R SW2 N 9.9 SW/DW I R6 R7 R8 NNE-5.65 NE 1.7 NE-4.0 R
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R9 R SW6 NNW 0.1 SW/DW RIO ENE-5.0 R GW1 W-1,2 GW/DW R11 E-0.5 R GW2 WSW-0.1 GW/DW R12 E-1.9 R GW3 SSE-4.6 GW/DW I R13 R14 E-3.5 E-4.2 R
R GW4 GW5 N 9.8 N-1.45 GW/DW GW/DW R15 ESE-1.4 R 551 NNE-1.0 SS I R16 R17 R18 ESE-4.7 SE-1,3 SE 3.85 R
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R FP2 FP3 E-4.2 SW-13.5 FP FP R25 R BL1 N-1.45 BL I R26 R27 SSW-4.4 SW-0.9 R
R BL2 BL3 SW-1.0 SW-13.5 BL BL
- Types:
A - Air Sample GW - Groundwater F - Fish R - Direct Radiation SS - Shore Line Sediment FP - Food Product l SW - Surface Water M - Milk BL - Broadleaf Vegetation l DW - Drinking Water
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M M M M M M M M M M M M TABLE 4 (PAGE 2 OF 3)
T U ELECTRIC COMANCHE PEAK STEAM EIECTRIC STATION CONCENIRA110NS OF BETA EMTITERS IN AIR PARIlCUIATES Results in Units of 10 3 pC1/m3 12 s.d.
SW- 12.3 SSE-4.5 E-3.5 N- I .45 N-9.4 STATION NW-1.0 SW/WSW Lal* S/SSW-1.2 COtf FCI1ON DATE MAY 1714 1614 1514 1614 1213 1613 1614 1614 1513 05/02-05/08/90 1613 1813 1613 1913 1513 1513 05/08-05/15/90 1416 1813 1313 1413 1414 1413 1713 1813 1113 05/15-05/22/90 1313 1313 1613 1213 1313 1613 12 3 1213 05/22-05/29/90 JUNE 1613 1413 1513 1513 1013 1113 9.412.8 1713 05/29-06/05/90 2213 2113 2013 2313 2013 2113 2013 06/05-06/12/90 1612 1413 1313 1513 1213 1513 1413 1614 1513 06/12-06/19/90 1713 14 3 1713 1513 1913 1713 1813 06/19 06/26/90 1614 1713 M 1813 2213 15t3 1713 1713 2113 1313 06/26-07/03/90 d13.1 3114 2713 3014 28t4 28 3 2713 2713 2713 07/03-07/10/90 1813 1513 1713 3314 1413 1613 1313 07/10-07/17/90 1613 1513 1713 1613 1613 1313 1413 1413 1713 07/17-07/24/90 2714 2314 3514 2113 3114 2514 3014 2714 07/24-07/31/90
' AUGUST 1613 15 3 1813 1413 1813 2316 1813 1513 07/31-08/07/90 3014 1913 3014 2614 30 4 3114 25i4 08/07-08/14/90 2514 1313 1513 1413 1413 1513 1714 1513 1914 08/14-08/21/90 29f3 2313 2913 2313 2913 3114 2313 08/21-08/28/90 2713 1713 2414 3914 2814 2113 2414 2113 2614 08/28-09/04/90
M 4
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- 1111 1t1 111 11111 N 2614 7697 076* 46250 2123 1 324 323 32644 5
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TADLE6 I T U ELECTRIC COMANCllE PEAK STEAM ELECTRIC STATION I CONCENTRATIONS OF 1131 IN MILK Results in pCl/l i 2 s.d.
I MONTH COLLECTION DATE SW 13.5 SSR 2._2 g JANUARY 01/16/90 <0.2 <0.3 FEBRUARY O2/13/90 <0.2 <0.2 MARCil 03/13/90 <1 <0.4 APRIL 04/10/90 <0.3 <0.2 MAY 05/08/90 <0.2 <0.3 05/22/90 <0.2 <0.3 JUNE 06/05/90 <0.2 <0.2 06/19/90 <0.2 <0.2 JULY 07/05/90 <0.1 < 0.1 07/10/90 <0.3 < 0. 3 I 07/31/90 <0.2 < 0,3 AUGUST 08/14/90 < 0. 3 <0.3 I 08/28/90 <0,3 <0.3 l SEPTEMBER 09/11/90 09/25/90
<0.2
< 0. 2
<0.2
<0.2 l OCTOBER 10/09/90 10/23/90
<0.2
<0,2
<0,2
<0.3 l NOVEMBER 11/19/90 <0.2 <0,2
<0.3 DECEMBER 12/18/90 <0.2 I
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M M M M M M M M M M M M TABLE 7 (PAGE 2 OF 2)
T U ELECTRIC COMANCIIE PEAK STEAM EECTRIC STATION CONCENIRA110NS OF GAMMA EMTTIERS* IN Mile Pesults in Units of pC1/ liter i 2 s.d_
K-40 Cs-134 Cs- 137 12- 140/Ba- 140 IDCATION COLECI1ON DATE STATION SSE42
<4 <4 <6 JANUARY OI/16/90 12301120
<4 <4 <6 FEBRUARY O2/13/90 1190t120
<4 <4 <s MARCII 03/I3/90 12201120
<4 <4 <6 APRIL 04/10/90 1090t110
<4 <4 <7 l MAY 05/08/90 11401110
<4 <4 <5 05/22/90 11701120
<4 <g 13601140 <4 JUNE 06/05/90 <6 11601120 <4 <4 06/19/90 <4 <4 12001120 <3 JULY 07/05/90 3 13601140 <4 <4 <6 07/10/90 <6 13301130 <4 <4 07/31/90 <9 13101130 <4 <4 AUGUST 08/14/90 <s 11801120 <4 <4 08/28/90 <s 11301110 <4 <4 SEI7 EMBER 09/1I/90 <5 <6 13001130 <4 09/25/90 <7 13001130 <4 <4 OCTOBER 10/09/90 <7 12501130 <4 <5 10/23/90 <7 12701130 <4 <4 NOVEMBER II/19/90 <4 <6 124')i120 <3 DECEMBER 12/18/90 Average i 2 s.d_
- All ottkr gamma crmtiers Orc <LLD.
. _ _ _ _ - --_~-.-_.- ---
I I e I 0 3
sess vvvv eese V-vv ezse vvvv zees vvvv eest vvvv I n I y bb vvvv bYnb vvvv nYbb vvvv Y
vvvv nN YnJ vvvv I e.
a a nenn nenn Ynen Ymnn nnnn g u vvvv vvvv vvvv vvvv vvvv I zk oo M<k C , d Pff Es-d 9"99 9T99 9999 I999 9999 l .=uBys8 a.c oU o
-g<Wg A CCCC @@CC oocs cccc I
csCC gg, gg N vvvv vvvv vvvv --vv vvvv 980 ds
=F3 N 5 I 9 09S a 8 h 9999 9599 9I99 i99 9999 I 1 o
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a U
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,enn vvvv nenn vvvv y
=
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I z 4 4 In W e i I o 5
z z
e 8888 ssss oz 8888 k
ssss ez 8888 k
ssss oz 8
ssss z
8888 oz 8888 ssss 3,
$ 8228 A 8228 9 8228 A pg < 8228 :
I o y 2'3o-pt o n'Bo-e Me='Bo- ng M* 8228 2'Bo- p<pg e o M n'3o-pt 2 I 42
_ _ . = .- ..
I I
g TM3G 9 T U ELECTRIC I COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER Results in pCi/l 2 s.d.
I OUARTER COLLECTION PERIOD LOCATION TRITIUM ACTIVITY l 1 01/09/90 01/09/90 SSE 4.6 N 9.8
<2000
<2000 l 01/09/90 01/09/90 W 1.2 WSW 0.1
<2000
<2000 g 01/09/90 N 1.45 <2000 2 04/10/90 SSE 4.6 <2000 1 04/10/90 N 9.8 <2000 04/10/90 W 1.2 <2000 l 04/10/90 04/10/90 WSW 0,1 N 1.45
<2000
<2000 3 07/10/90 SSE 4.6 <2000 g 07/10/90 N 9.8 <2000 07/10/90 W-1.2 <2000 07/10/90 <2000 I 07/10/90 WSW 0.1 N 1.45 <2000 4 10/09/90 SSE 4.6 <900 10/09/90 N 9.8 <900 l 10/09/90 10/09/90 W- 1,2 WSW 0.1
<900
<900 g 10/09/90 N 1.45 <900 I
43 w
I I
l TABLE 10 T 11 ELECTRIC g COMANCHE PEAK STEAM ELECTRIC STKHON GROSS BETA CONCENTRATIONS IN WATER SURFACE / DRINKING Results in pCl/li 2 s.d.
I l MONTH COLLECTION DATE* N NW-0,1 N 9,9 l JANUARY 12/26/89 01/16/90 17 3 1714 FEBRUARY 01/23/90 02/13/90 15 3 12i3 I MARCH 02/20/90 03/13/90 1613 1413 03/20/90 04/10/90 18i3 17 3 I APRIL 04/17/90 05/08/90 1513 1313 I MAY 05/15/90 05/22/90 05/15/90 06/05/90 1413 1313 9.712.3 1112 JUNE 06/12/90 07/05/90 1313 9.612.2 JULY 07/10/90 07/31/90 16i3 6.912.0 AUGUST 08/07/90 08/28/90 13i3 7.512.0 g SEPTEMBER 09/04/90 09/25/90 12t3 5.411.9 OCTOBER 10/03/90 10/23/90 1413 10i3 I NOVEMBER 10/30/90 11/19/90 1613 1313 DECEMBER 11/27/90-12/18/90 I 12/26/90 01/02/91 1313 1613 1013 1313 Samples are composites of weekly grab samples collected over a 4 week period, except for the periods 5/15/90 5/22/90 and 12/26/901/2/91 which were composited over a 2 week period. These two samples collected over two I week periods were inadvertently analyzed for gross beta and are in addition to the required monthly composite samples.
I 44
M M M M M M M M M M M M M M M M TABLE I1 0' AGE I OF 21 T U EIECIRIC COMANCIIE PEAK STEAM ELECTRIC STATION CONCENIRA~nONS OF GAMMA EMTI'TERS* IN WATER SURFACE / DRINKING Results in Units of pCI/I i 2 s.d.
_ Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs- 134 Cs- 137 Ba/la- 140 STA"nON NNW-0.1 12/26/89-01/16/90 <3 <3 <7 <3 <7 <3 <4 <4 <6 01/23/90-02/13/90 <3 <3 <7 <4 <7 <4 <3 <4 <7 02/20/90-03/13/90 <3 <3 <7 <4 <7 <4 <4 <4 <7 03/20/90-04/10/90 <3 <3 <7 <3 <7 <3 <3 3 <7 04/17/90-05/08/90 <4 <4 <8 <4 <8 <4 <4 <4 <9 05/15/90-05/22/90 <3 <3 <7 <4 <7 <4 <4 <4 <5 05/15/90-06/05/90 <3 <3 <7 <3 <G <3 <3 <3 <9 06/12/90-07/05/90 <2 <3 <7 <2 <5 <3 <2 <2 <10 07/10/90-07/31/90 <3 <3 <8 <4 <7 <4 <4 <4 <7 08/07/90-08/28/90 <3 <3 <8 <4 <6 <4 <3 <3 <9 09/04/90-09/25/90 <3 <3 <6 <3 <6 <3 <3 <3 <7
, 10/03/90-10/23/90 <1 <2 <7 <1 <2 <2 <1 <0.9 <9 0 * **
u, 10/30/90-11/19/90 (5 <5 <10 <5 <10 <5 <5 <5 <8 II/27/90-12/18/90 <3 <3 <6 <4 <7 <4 <3 <4 <a 12/26/90-01/02/91 <4 <4 <9 <4 <9 <5 <4 <5 <a Averaget 2 s.d.
l l
All other gamma emitters were LLD.
l Samples are composites of weekly grab sarapies co!!ccted over a 4 week perxxi. cacept for the perux?s 5/I5/90-5/22/90 and 12/26/90-1/2/91 which were composited over a 2 week perxx1. These samples were analyzed for gamma emitters in adostu,n to the required monthly composite samples.
Rcquired LLD m.t athseved; we Ap!vnJa C f or esplanatum
M M M M M M M TABIE II PAGE 2 OF 2)
T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STAT 10N CONCENTRATIONS OF GAMMA EMTTIERS* IN WATER SURFACE / DRINKING Results in Units of pC1/112 s.d.
,, Mn-54 Co-58 Fe-59 Co4'0
> Zn-65 Nb/Zr-95 Cs- 134 Cs- 137 Ba/La-140 STAT!ON N-9.9 12/26/89-01/16/90 <3 <3 <8 <4 <7 <4 <4 <4 <6 01/23/90-02/13/90 <3 <3 <6 <4 <6 <3 <3 <3 <6 02/20/90-03/13/90 <3 <3 <8 <4 <7 <4 <3 <4 <8 03/20/90-04/10/90 <4 <4 <9 <4 <9 <4 <4 <4 <10 04/17/90-05/08/90 <3 <3 <7 <3 <6 <4 <3 <4 <8 05/15/90 45/22/90 <4 <4 <10 <4 <10 <4 <5 <5 <7 05/15/90-OG/05/90 <3 <3 <7 <3 <G <4 <3 <3 <9 06/12/90-07/05/90 <2 <3 <7 <2 <5 <3 <2 <2 <10 07/10/90-07/31/90 <4 <4 <9 <4 <10 <5 <5 <S <6 08/07/90 08/28/90 <3 <3 <9 <4 <7 <4 <3 <3 <10 09/04/90-09/25/90 <3 <3 <7 <3 <6 <3 <3 <3 <7 a 10/03/90-10/23/90 <O.9 <2 <6 <I <2 <2 <1
- <0.4 <9 0 * **
10/30/90-11/19/90 <3 <3 <7 <4 <7 <3 <3 <4 <7 '
11/27/90-12/18/90 <3 <3 <7 <4 <7 <4 <3 <4 <9 12/26/90-01/02/91 <3 <3 <7 <3 <7 <3 <3 <3 <6 Aircrage 2 s.d.
i All other gamma emitters were LLD.
Samples are composites of weekly grab samples collected over a 4 week period, except for the permis 5/I5/90-5/22fM) and 12/26/90-1/2/91 which were composited over a 2 week perm 1. These samples were analyzed for gamma ennners en addition to the required monthly composite sampics.
"* itequires! LLD rm achtesed; see Appenda C for cuplanation.
i
I TABLE 12 l T U ELECTRIC COMANCllE PFAK STEAM ELECTRIC STATION '
g CONCENTRATIONS OF 1131 IN WATER SURFACE / DRINKING Results in pCi/l 2 s.d.
COLLECTION MONTH DATE* N NW-0.1 N 9.9 JANUARY 12/26/89 01/10/90* < 0. 4 <0.3 01/23/90 01/30/90 <0.2 < 0. 2 FEBRUARY 01/23/90 02/13/90 < 0. 5 < 0. 7 02/20/90 02/27/90 < 0. 3 <0.4
! MARCH 02/20/90 03/13/90 03/20/90 03/27/90
< 0. 4
< 0. 2
<1
<0.3 03/20/90 04/10/90 < 0. 2 <0.2 APRIL 04/17/90 04/24/90 <0.2 < 0. 2 04/17/90-05/08/90 < 0. 5 < 0. 5 MAY 05/15/90 05/22/90 < 0. 2 <0.4 05/22/90 06/05/90 <0.2 <0.3 JUNE 06/12/90 06/19/90 <0. 2 < 0. 2 06/12/90 07/05/90 < 0.1 < 0.1 I JULY 07/10/90 07/17/90 < 0. 4 < 0. 4 07/10/90 07/31/90 < 0. 2 <0.2 I AUGUST 08/07/90 08/14/90 < 0. 2 <0.2 08/07/90 08/28/90 <0.2 < 0.1 I SEPTEMBER 09/04/90 09/11/90 < 0.1 < 0. '
09/04/90 09/25/90 <0.2 <0.2 OCTOBER 10/03/90-10/09/90 < 0. 3 < 0. 2 10/03/90 10/23/90 < 0.1 <0.2 NOVEMBER 10/30/90 11/06/90 < 0. 2 < 0. 2 10/30/90 11/20/90 < 0.1 ,0.4 DECEMBER 11/27/90 12/04/90 < 0. 4 < 0. 3 11/27/90 12/18/90 < 0. 2 <0.2 12/26/90 01/02/91 < 0,5 <0.5 g
Samples are composites of weekly grab samples collected over a 2 or 4 week period, as indicated.
1 47
I I
l TABLE 13 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN WATER SURFACE / DRINKING Results in pCi/li 2 s.d.
I COLLECTION OUARTER PERIOD NNW 0,1 N 9.9 l 1 12/26/89 03/27/90 <2000 <2000 2 03/20/90 06/05/90 <2000 <2000
! 3 06/12/90 09/25/90 <1000 <1000 l 4 10/03/90 01/02/91 <2000 <2000 I
I I
I I '
I I
I I -
48
M M -
M . M M M M '
M TAf t!.E 14 (PAGE 1 OF 2)
T U EIECTRIC COMANCllE PEAK SITAM ELECTRIC STATION CONCENPIAT10NS OF CAMMA EMITIERS* IN SURFACE WATER Results in Units of pCf/112 s.d.
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/2r-95 Cs-134 Cs-137 Ba/La-140 STATION ESE-1.4 12/26/89-01/16/90 <4 <4 <8 <4 <8 <4 <4 <4 <7 01/23/90 42/13/90 <3 <3 <6 <3 <7 <3 <3 <3 <6 02/20/90-03/13/90 <3 <3 <8 <4 <7 (4 <4 <3 <9 03/20/90-04/10/90 <3 <3 <6 <3 <6 <3 <3 <3 <6 04/17/90 4 5/08/90 <3 <3 <8 <3 <7 <4 <4 <4 <7 05/15/90-06/05/90 <5 <5 <10 <5 <10 <5 <6 <6 <9 06/12/90-07/05/90 <3 <3 <7 <3 <6 <3 <3 <4 <6 07/10/90-07/31/90 <.3 <2 <6 <4 <7 <3 <3 <3 <6 08/07/90-08/28/90 <3 <3 <7 <4 <7 <4 <3 <4 <8 09/04/90-09/25/90 <3 <3 <7 <4 <7 <4 <3 <4 <8 a 10/03/90-10/23/90 <3 <3 <7 <3 <6 <3 <3 <3 <6 o 10/30/90-11/19/90 <5 <5 <10 <6 <10 <5 <5 <5 <8 i1/27/90-12/18/90 <3 <3 <6 <4 <6 <3 <3 <4 <6 Average 2 2 s.d.
STATION N-1.5 l
12/26/89 01/16/90 <3 <3 <8 <4 <7 <3 4 <3 <7 01/23/'30-02/13/90 <3 <4 <9 <4 <d <4 <4 (5 <9 02/20/90 43/13/90 <5 <5 <10 <6 <10 <6 <5 <G <10 03/20/90-04/10/90 <2 <2 <5 <3 <5 <3 <3 <3 <6 04/17/90-05/08/90 <4 <4 <10 <4 <9 <5 <4 <5 (9 05/15/96-06/05/90 <4 <4 <8 <4 <9 <4 <5 <5 <8 06/12/90 4 7/05/90 <3 <3 <7 <4 <6 <3 <3 <3 <7
( 07/10/90-07/31/90 <3 >3 <7 <4 <7 <4 <4 <4 <G l 08/07/90-08/28/90 <3 <4 <9 <4 <7 <4 <4 <4 <10 09/04/90 49/25/90 <3 <3 <7 <3 <7 <3 <3 <3 <8 10/03/90-10/23/90 <3 <3 <7 <3 <7 <3 <3 <3 <7 1O/30/90-1I/19/90 <4 <4 <10 <5 <10 <5 <5 <5 <7 11/27/90-12/18/90 <4 <4 <9 <4 <9 <5 <4 <5 <7 l Average 2 s.d.
All other gamma emitters werc <LLD.
l l ~ Samples from Squaw Creek Reservoir (ESE-l.4 and N-1.5) are composites Of weekly grab samples collected over a 4 week period.
Samples from Lake Granbury (NE-7.4 and N-19.3) are grab samples collected on the date irdkated.
l
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m M M ;
M M M M M M m M M m M TABIE 14 (PAGE 2 OF 21 T U ELECTRIC COMANCIIE PEAK STEAM E2,ECTRIC STATION CONCENTLATIONS OF GAMMA EMITTERS
- IN SURFACE WATER Results in Units of pC1/112 s d.
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr 95 Cs-134 Cs- 137 Ba/La-140 STAT 10N NE-7.4 -
01/16/90 <3 <3 <7 <4 <7 <4 <3 <4 <6 02/13/90 <5 <5 <10 <5 <10 <5 <6 <6 <10 03/13/90 <3 <3 <7 <4 <7 <4 <3 <3 <7 04/10/90 <3 <3 <6 <3 <6 <3 <3 <3 <6 l 05/08/90 <3 <3 <7 <3 <6 <4 <3 <3 <7 06/05/90 <5 <6 <10 <6 <10 <6 <6 <6 <9 07/05/90 <3 <3 <6 <3 <7 <4 <4 <3 <7 07/31/90 <3 <3 <7 <3 <7 <3 <4 <4 >6 08/28/90 <3 <4 <8 <3 <6 <4 <3 <4 <8 09/25/90 <3 <3 <8 <3 <7 <4 <4 <4 <9 10/23/90 <3 <3 <6 <3 <6 <3 <3 <3 <8 11/19/90 <3 <3 <6 <3 <7 <3 <3 <3 <5 12/18/90 <3 <3 <6 <3 <7 <3 <3 <3 <6
$ Average 2 2 s d.
STAT 10N N-19.3 01/16/90 <3 <3 <8 <3 <7 <4 <4 <4 <7 02/13/90 <4 <3 <8 <4 <7 <4 <3 <4 <6 03/13/90 <4 <4 <9 <4 <B <5 <5 <5 <10 04/10/90 <3 <3 <6 <3 <5 <3 <3 <3 <S
-05/08/90 <3 <3 <7 <3 <7 <3 <3 <3 <7 06/05/90 <3 <3 <7 <3 <6 <3 <4 <4 <8 07/05/90 <3 <3 <7 <3 <6 <3 <3 <4 <6 07/31/90 <4 <3 <7 <3 <7 <3 <4 .4 <5 08/28/90 <3 <3 <7 <4 <6 <4 <3 <3 <8 09/25/90 <3 <4 <8 <3 <7 <4 <4 <4 <8 10/23/90 <2 <3 <6 <3 <6 <3 <3 <3 <7 11/19/90 <4 <4 <9 (5 <8 <4 <4 <5 <8 12/18/90 <3 <3 <7 <3 <6 <3 <3 <3 <7 Average 12 s.d_
All other gamma emitters werc <LLD.
" Samples from Squaw Creek Reservoir (ESE-1.4 and N-l.5) are composites of weekly grab sampics coliccted over a 4 week period.
Samples from Lake Granbury (NE-7.4 and N-193) are grab sarapies collected on the date indkated.
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M M M M M M m M m _ m M TABLE 19 (PAGE I OF 2)
T U ELECTRIC COMANCIIE PEAK STEAM ELECIRIC STATION CONCENTRATIONS OF GAMMA EMITIERS* IN BROADLEAF VEGETATION Results in Units of pCI/kg (wet) i 2 s.d.
COILECI1ON Be-7 K-4 0 1-131 Cs- 134 Cs-137 STATION DESCRIFT10N DATE 14401240 12101290 <6" <20 <20 SW- 13.5 Forage Grass 01/16/90 <50 <10 <10 Vegetation 02/13/90 23101230 73601740 5971 60 56001560 <G" <6 <G Vegetation 03/13/90 <20 <10 <10 Vegetation 04/10/90 9001104 62301620 21001210 85101850 <2 0 " <10 <10 Weed Lys 05/08/90 <8 <7 Weed Lvs 06/05/90 14901150 82301820 <7 "
346t 70 49001490 < 10" <9 <9 Weed Lvs 07/05/90 <8 <8 Weed Lvs 07/31/90 9861 99 59901600 <2 0 "
7971109 85001050 < 10" <10 <10 Weed Lvs 08/28/90 <8 <7 Weed Lvs 09/25/90 12601130 6520iG50 < 10" 15901160 58101580 <2 0" <8 <7 Bloodweed 10/23/90 <20" <20 <20 Johnson Grass 11/19/90 42801430 20801270 18301180 77401770 <8" <10 21.9110.I Rye Grass 12/18/90 9331103 440188 <9 " <9 <10 N - 1. 45 Forage Grass 01/16/90 <30 197138 Vegetation 02/13/90 89001890 23401370 <200"*
(BLI) 1070011100 30201400 <7 " <30 <30 Vegetation 03/13/90 <20 <10 <10 VegetatJon 04/10/90 10001110 57001570 13001210 55601560 <10** <20 <20 Sumac Lvs 05/08/90 <7 <0.02 <0.02 Sumac Lvs 06/05/90 14501260 8.4310.84 11001200 66101660 <8 " <20 <20 Sumac Lvs 07/05/90 <40" <30 <30 Sumac Lvs 07/31/90 17901270 51801520 17901240 55901560 <20" (20 <20 Sumac Lvs 08/23/90 <20 <20 Weed Lvs 09/25/90 15501240 55901560 < 10" .
15101160 64001640 <7 " <20 <20 l' Sunwc Lvs 10/23/90 <10 <10 Cttn Wd Lvs 11/19/90 1250.1130 28301280 <30" 26801270 28401280 < 10" <10 <10 Cottenwd 12/18/90 i
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- All other gamma emitters were <LLD.
" - todine-131 by radiochemical method.
"*lodme-131 analysis failed; See Appendit C for explanation.
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~M M M M M TABLE 20 (PAGE 1 OF 5)
RADIOLOGICAL ENVIRONMENTAL MONTFORING PROGRAM
SUMMARY
T U ELECIRIC - COMANCliE PEAK STEAM ELECTRIC STATION JANUARYI'IO DECEMBER 31.1990 Analysts a'.ul lower Limit Number of Medium of Pathway Total Number of All Indicator locations Iecation with II! chest Mean Control locations Nonrouune Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (!)(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements "IU)s Gamma (212 ) O.I2(202/202) E-3.5 O.15(5/5) O.13(I0/10) 0 (mR/ day) (0.05-0.19) (0.12-0.19) (0.10-0.16)
Air lodine-131 1-131(410) 70 -(0/358) NA NA f 1/52) 0 (10 3 pct /m3) -- --
Air Particulate Gross (408) 10 22(356/356) SW- 12.3 23(52/52) 23(52/52) 0 (10 3 pct /m'll Beta (7.7-62) (11-52) (11-52)
Gamma (32)
Be-7 -
68(28/28) SW/WSW-0.95 83(4/4) 74(4/4) 0 (12-111) (68-108) 168-80)
K-40 -
13(13/28) SW/WSW-0.95 15(4/4) 14(2/4) 0 (7.9-21) (8.3-21) (12-15)
Ru-103 -
-(0/28) N/A N/A -(0/4) O Cs-132 -
-(0/28) N/A N/A -(0/4) 0 ,
Cs-137 -
-(0/28) N/A N/A -(0/4) 0 (1) LLD is hwer Itmit of detection as defined arw] required in USNRC firanch Technical Ibsstion on an Acceptable Radiohg6 cal Enytronmental Monitoring I"rogram.. Reviston 1. November 1979.
(2) [0 ts the ratto of smittve results to the num'xr of samples analym! for the parameter of interest.
me. ins are of gettive ecsults only.
L
g M M' M E M E E E E '
g g g TABLE 20 (PAGE 2 OF 5)
RADIOIDGICAL ENVIRONMENTAL MONTIORING PROGRAM
SUMMARY
T U EIECITUC - COMANCilE PEAK STEAM ELECTRIC STATION JANUARY I 'IO DECEMBER 31.1990 Analysts and Imver Ilmit Number of Medium of Pathway Total Number of All Indicator Incations locauon with Highest Mean Control location Nontoutine Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (I)(2) Reported (LID) (1) Range Distance and Direction Range Range Measurements (Unit of Measurement) Performed Milk I-131 (38) - -(0/19) NA NA -(0/19) O (pC1/I) ggy mg)cugug37pyj ._
Gamma (38) l K-40 -
1233(19/19) SW- 13.S 1305(19/19) 1305(19/19) 0 !
(1090-1360) (1100-1520) (1100-1520) l Cs-137 -
-(0/19) NA NA -(0/19) 0 i $
Surface Water Gamma (52) -(0/39) NA NA -(OfI 3) O l
- fpCf/l) --
-(0/12) NA NA -(0/4) 0 l Tritium (16) -
Grotmd Drinking Gamma (20) -
-(0/16) NA NA -(0/4) 0 Water (pC1/1) --
Tritium (20) -
-(0/16) NA NA -(0/4) 0 (1) Lil) is lower limit of detection as defined and required in USNRC Branch Technical Ibsittors on an Acceptable Radiological Erwironmental Monitoring Program.. Hevtskus 1. November 1979.
(2) (!! is the ratio of posittve results to the number of samples analyzed for the parameter of interest.
means are of posit:ve results only.
M M E E E E M
M M M M M TABE 20 (PAGE 3 OF 5)
RADIOIDGICAL ENVIRONMENTAL MONTIDRING PROGRAM
SUMMARY
T U ELECIRIC - COMANCIIE PEAK SIEAM EECTRIC STATION JANUARY I TO DECEMBER 31.1990 Number of Analysis and lu-u IJmit Control location Nonroutine Medium of Pathway Total Number of All Indicator locations locaUon with Ilichest Mean Reported Detection Mean Name Mean (f)(2) Mean (f)(2)
Sampled ofAnasysis Distance and Direction Range Range Measurements (IlD) (!! Range (Unit of Measurement) Performed
-(0/ I5) NA NA -(0/15)
Water-Surface Gamma (30) -
Drinking (pCl/1) NA NA -(0[4] O Tritium (8) -
-(0)4)
NNW > '.1 15(15/15) 11(15/15) 0 Gross Beta (30) -
15(15/15)
(12-18) (12-18) (5.4- 17)
NA NA -(0/26) 0 1-131 (52) - -(0/26) ' --
(BY RADIOCffEMISTRY)
- u. Ibh Gamma (101
- (pCi/kg/ dry) 1782(7/7) NNE-8.0 2260(3/3) 2260(3/3) 0 K-40 -
(II10-2870) (I I 10-2870)
(753-2990)
ENE-2.0 22(1/7) -(0/3) O CS-137 22(1/7)
Shoreline Gamma (6)
Sediments N-9.9 2755(2/2) 2755(2/i) 0 (pCf/kg dry) K-40 -
1446(4/4)
(482-2110) (2560-2950) (2560-2950)
NNE-1.0 19(1/4) -(0/2) O Cs-137 -
19(1/4)
N-9.9 153(2/2 153(2/2) 0 Pb-212 -
130(4/4)
(103-140) (118-187) (118-187)
(1) LLD is kwer Itmit of detectkin as defined arwi required in USNRC Brarxh Technical Ibsition on an Aneptab' ' Radiological Environmental Monitoring Itogram.. Hevisk>n I. November 1979.
(2) (0 ss the ratio of positive results to the number of samp!cs analyzed for the parameter of interest.
means are of posiuve results only.
M M E E M M M .M M TABLE 20 (PAGE 4 OF 5)
RADIOIDGICAL ENVIRONMENTAL MONTTORING PROGRAM
SUMMARY
T U ELECTRIC - COMANCIIE PEAK SIEAM ELECTRIC STATION JANUARY I 'IO DECEMBER 31.1990 Number of Analysis and lower IJmit Control Incation Nonroutine Medium of Pathway Total Number of All Indicator locations location with IItchest Mean Reported ofAnalysis Detection Mean Name Mean (f)(2) Mean (f)(2)
Sampled Distance and Direction Range Range Measturements (Unit of Measurement) Performed (LI D ) (1) Range Shoreline Gamma (6)
Sediments 219(2/2) 162(2/2) 0 (pC1/kg dry) Bi-214 -
205(4/4) NE-7.4 (165-229) (209-229) (152-172)
NE-7.4 2 54(2/2) 237(2/2) G Pb-214 -
238(4/4)
(210-272) (235-272) (178-295)
Ra-226 -
462(3/4) NE-7.4 476(I/2) -(0/2) 0 (433-477)
N-9.9 181(1/2) 181(1/2) O e Th-228 -
127(4/4) --
(101-138)
Umadleaf Gamma (39)
Vegetation SW- 1.0 3055(13/13) 1533(13/13) 0 (pC1/kg wet) Be-7 -
2910126/26)
(387-12200) (387-12200) (346-4280)
K-40 -
4843126/26) SW-13.5 6052(13/13) 6052(13/13) 0 (8.4-11900) (1210-8510) (1210-8510) 1-131 -
-(0/26) NA -(0/13) -(0/ I3) 0 NA -(0 /13) -(0/13) O l Cs-134 -
-(0/26)
Cs-137 -
197(I/26) N- 1.45 197(1/13) 22(l/13) O (1) 11D is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acreptable Radiological Environmental Monitortng Program.. Revision 1. November 1979.
- 12) (f) is the rauo of posittve results to the number of samples arulyzed for the parameter of mterest.
means are of positive results only.
7 M M M M M M M M m m m M M M M m m e 1ABLE 20 (PAGE 5 OF 5)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
T U EIEClltlC - COMANCilE PEAK S1EAM ELECTRIC STATION JANUARY I TO DECEMBER 31.1990 Number of Analysis arxl lower Limit Control location Nonrouune Medium of Pathway Total Number of All Indicator locauons locauon with litchest Mean Reported Detecuon Mean Name Mean (f)(2) Mean II)(2)
Sampled ofAnalysis Distance and Direcuon Range Range Measurements (LID) (1) Range (Unit of Measurement) Performed Fend Products Gamma (11) fpC1/kg wet) SW-13.5 426(1/3) 426(1/3) 0 Be-7 -
-(0/8) .. ..
SW-13.5 4160(3/3) 4160(3/3) 0 K-40 -
192418/8)
(125-3440) (l890-5610) (l890-5610)
NA -(0/8) -(0/3) O l-131 .
-(0/8) .. ..
NA -(0/8) -(0/3) 0
$ Cs- 134 -
-(0/8) .. ..
l Cs-137 -
-(0/8) NA -(0/8) -(0/3) O j
i1) LLD ts lower limit of detection as deftned and requtred in USNRC I! ranch Technical Ibsition on an Acreptable Radiological Environmental Monitoring f% gram.. Revtston 1. November 1979.
(2) (0 is the ratto of positive results to tbc ruumber of samples analyzed for the parameter of interest.
means are of positive results only.
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I APPENDIX A EPA CROSS-CllECK PROGRAM D
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I US EPA INTERLABORATORY COMPARISON PROGRAM 1.990 g (ENVIRONMENTAL) i I Collection Date Media Nuclide EPA Result (a)
Teledyne Isotopes Result (b) 10/31/89 lab Perf. Gr Alpha 49.00 i I Water Sample A Ra 226 Ra 228 8.40 t 4.10 1 12.00 1.30 0.60 42.33 -i 9.20 i 4.00 t 5.77 0.46 0.50 I Sunple B Gr Beta Sr 89 32.00 i 15.00 i 5.00 5.00 30.33 i 15.00 1 0.58 3.46 Sr 90 7.00 i 1.50 7.00 1 0.00 I Cs 134 Cs 137 5,00 i 5.00 1 5.00 5.00 5.33 i 7.00 i 1.15 0.00 I 11/10/89 Water Ra 226 Ra 228 8.70 i 8.57 i 1.30 1.40 8.47 i 8.57 i 0.49 1,46 Sr 89 25.00 i i
I O1/12/90 Water Sr 90 20.00 i 5.00 1.50 24.00 i 19.67 1 1.73 2.52 01/26/90 Water Gr Alpha 12.0
- 5.0 10.00 t 1.73 l Gr Beta 12.0 i 5.0 12.33 i 1,53 02/09/90 Water Co 60 15.00 i 5.00 15.00 i 3,46 I Zn 65 Ru 106 Cs 134 139.00
- 139.00 i 18.00 1 14.00 14.00 5.00 131.33 i 113.67 i 15.33 9.07 4.04 (c) 2.31 Cs 137 18.00 1 5.00 19.33 i I Ba 133 74.00 i 7.00 66.00
- 3.21 3.46 02/23/90 Water H3 4976.00 i 498.00 4900.00 1 100.00 I 03/09/90 Water Ra 226 4.9 i 0.7 4.73 1 0.47 Ra-228 12.7 i 1.9 13.00 i 1.00 I 03/30/90 Air Filter Gr Alpha 5.0 1 5.0 6.33 i 0.58 Gr Beta 31.0
- 5.0 31.67 i 0.58 I Sr 90 Cs-137 10.0 i 10.0 1 1.5 5.0 9.33 1 10.67 i 0.58 1.15 04/17/90 Water Gr Alpha 79.33 i I (I4b Perf)
Sample A Ra 226 Ra 228 90.0 1 5.0
- 10.2 i 23.0 0.8 1.5 5.67 t 9.37 1 2.89 0.15 1.44 Sample B Gr Beta 52.0 i 5.0 53.33
- 1.53 I Sr 89 Sr90 Cs 134 10.0 t 10.0 i 5.0 1.5 10.67 i 9.67 i 1.15 0.58 15.0 1 5.0 12.67 t 1.53 Cs 137 15.0
- 5.0 16.33 i 1.15 Footnotes at end of table.
A-2
I US EPA INTERLABORATOAY COMPARISON PROGRAM 1990 (cont.)
g (ENVIRONMENTAL)
Collection Teledyne Date Media Nuclide EPA Result (a) Isotopes Result (b) 04/27/90 Milk St 89 23.0
- 5.0 24.67 i 1.53 Sr 90 23.0 1 5.0 24.00 i 0.00 1131 99.0 1 10.0 89.67
- 3.21 Cs 137 24.0
- 5.0 27.33 i 2.52 K 1550.0
- 78.0 1483.33 i 75.06 05/04/90 Water Sr 89 7.0 i 5.0 6.67 1 0.58 Sr90 7.0 i 5.0 6.67
- 0.58 05/11/90 Water I Gr Alpha Gr Beta 22.0 i 15.0 i 6.0 5.0 16.00
- 17.00 1 1.00 1.00 06/08/90 Water Co 60 24.0
- 5.0 25.33 2.52 Zn 65 148.0 i 15.0 148.67
- 3.06 Ru 106 210.0 1 21,0 196.00 1 20.66 Ca 134 24.0 1 5.0 23.67 i 2.89 I Ca 137 Br.-133 25.0 99.0 t 5.0 10.0 24.67
- 93.00 1 2.08 6.08 l
06/22/90 Water H-3 I 07/13/90 Water Ra 226 2933.0 i 12.1 i 358.0 1.8 2900 t 100.00 11.37 i 0.60 i
Ra 228 5.1 i 1.3 4.20
- 0.75 iI 08/10/90 Water I 131 39,0 i 6.0 36.00 i 3.00 I 08/31/90 Air Filter Gr Alpha Gr Beta 10.0 i 62.0 1 5.0 5.0 16.00 i 63.33 i 1.00 (d) 1,53 Sr 90 20.0
- 5.0 18.00
- 1.00 Cs 137 20.0 1 5.0 18.33 t 3.21 09/14/90 Water Sr 89 10.0 5.0 8.07 i 0.58 Sr 90 9.0 i 5.0 9.0 1.00 09/21/90 Water Gr Alpha 10.0 1 5.0 11.00
- 1.00 Gr Beta 10.0 i 5.0 11.00 1.00 Footnotes at end of table.
l A-3
I U8 EPA INTERIABORATO3Y COMPARISON PROGRAM 1900 (cont.)
(ENVIRONMENTAL)
Collection Teledyne I Date Media Nuclide EPA Result (a) Isotopes Result (b) 09/28/90 Milk Sr89 16.0 1 5.0 9.0 i I Sr 90 1 131 Co 137 20.0 i 58.0 i 5.0 6.0 15.33 1 54.67 i 2.65 (c) 0.58 1.53 20.0 t 5.0 23.00 i 1,73 K 1700.0 i 85.0 1710.00 1 65.51 10/15/90 Water Co-60 20.0 i 5.0 21.00 i 1.00 Zn 65 115.0 i I Ru 106 Cs 134 151.0
- 12.0
- 12.0 15.0 5.0 115.00 1 142.00
- 11.00 1 11.53 8,66 0.00 Cs 137 12.0 i 5.0 16.33 i 2.52 Ba 133 110.0 i 11.0 94.67 i 5.13 (f) 10/30/90 1.ab Perf. Gr Alpha 62,00 i 16.00 57.00 1 1.00 Water Ra 226 13.6 i 2,0 12.67 *
- l. Sample A Ra 228 5.0
- 1.3 4.87
- 1.27 0.23 Sample B Gr Beta 53.0 1 5.0 51.00
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Sr 89 Sr-90 20.0 i 15.0 1 5.0 5.0 19.00 1 14.33 i 2.31 3.61 0.58
. Cs 134 7.0 i 5.0 9.00
- 0.00 Cs 137 5.0 i 5.0 7.67
- 1.15 10/19/90 Water H3 7203.0 i 720.0 7133.33 1 251.66 l
11/09/90 Water Ra 226 7.4 i 1.1 7.27* 0.38 Ra 228 7.7 1 1.9 7.57 i 0.32
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I US EPA INTERLABORATORY COMPARISON PROGRAM 1990 (Cont.)
(ENVIRONMENTAL)
Footnotes:
(a) EPA Results. Expected laboratory preciaton (1 sigma). Units are pct / liter for water, and milk except K is in mg/hter. Units are total pC1 for air particulate filters.
(b) Teledyne Results Average i one s4;ma. Units art pct /hter for water and milk except K is in mg/ liter. Units are total pCl for air particulate filters.
(c) No apparent cause for the low results were found. nree aliquots of the sample were counted on three separate detectors, ne results of all three were similar, ne cabbration I curve fit is good (0.997). Ruthenium lO6 was obtained from the EPA. Results of spikes were acceptable. Subsequent cross checks from the EPA did not exceed two normalized standard deviations. No additional follow up is necessary, but we will continue to monitor the results. New cahbrauons were cornpleted in March,1991.
I (d) The EPA depoalt occupies a smaller area than our cahbration planchet and hence has a higher counting emetency. No furtht.r correcuve action is required, since our calibrauon I
standard better represents un air particulate filter.
I (e) Incomplete removal of calcium, lead to erroneously high strontium yields. More care is being taken in the strontium nitrate and stmnuum sulfate precipitation steps to ensure a i
I final volume of at least '20 ml in the stronuum sulfate step. Beanalysis of internal QC samples produced good results after trnplementing the correcuve action.
l (f) There is no apparent reason for the deviation between the EPA and Teledyne Isotopes values. Other isotopes in the sample were measured accurately, ne calculauons were i
I reviewed and activities calculated from other Da 133 gamma rays. Results were reproduced as reported.
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I APPENDIX B SYNOPSIS OF ANALYTICAL PROCEDURES 3
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APPENDIX B 4
APPLICABLE PROCEDURES NUMBER TITLE DATE PAGE PRO-032-10 Determination of Gross Beta 03/01/87 B-3 in Air Particulate Filters I PRO 032-35 Determination of Tritium in Water by Liquid Scintillation 12/30/87 B-4 PRO-032-11 Determination of Radiciodine 08/01/88 B-5 in Milk and Water Samples I
PRO-342-17 Environmental Thermoluminescent 09/04/87 B-6 l
Dosimetry (TLD)
PRO-042-5 Determination of Gamma Emitting 10/26/84 6-7 Radioisotopes PRO-032-1 Determination of Gross Alpha 03/21/86 B-9 and/or Gross Beta in Water Samples I PRO-032-12 Determination of Radiciodine in Vegetation Samples 11/15/82 B-11 I
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I-I GROSS BETA ANALYSIS OF SAMPLES, Air Particulates Af ter a delay of five or more days, allowing for the radon-222 and I redon-220 (thoron) daughter products to decay, the filers are counted in a gas-flow proportional counter. An unused air particulate filter, supplied oy TV Electric, is counted as the blank, Calculations of the results, the two sigma error and the lower limit of detection (LLD), are performed as follows:
RESULT (pci/m3 ) = ((S/T) - (8/t))/(2.22 V E)
TWO SIGMA ERROR (pCi/m3 ) = 2((S/T2 ) , (gjg 2))l/2 (2.22
/ V E)
LLO (pCi/m3 ) = 4.66 (B1/2)/(2.22 V E t) where:
S = Gross counts of sample including blank I 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 I
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I ANALYSIS OF WATER SAMPLES FOR TRITIUM I One milliliter of water is added to 20 ml of liquid scintillation l solution in a 25 mi vial.
and counted for 100 minutes.
The sample is inserted into a Liquid Scintillator Calculations of the results, the two sigma error and the lower limit of detection (LLO), are performed as follows:
I RESULT (pCi/f) =
((S/T) - (B/t))/(2.22 V E )
2 TWO SIGMA ERROR (pQi/f) =
2((S/T + (B/t2 ))l/2 (2.22
/ VE)
I LLD(pCi/t) =
4.66 (81 /2)/(2.22 V E t)
I where S = Gross counts of sample B = Counts of blank E = Counting efficiency I T t
= Number of minutes sample was counted
= Number of minutes blank was counted V = Sample aliquot size (f) 2.22 = dpm/pC1 I
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1 ANALYSIS OF SAMPLES FOR 100lNE 131 ,
Milk or Water I 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 l
solution, is reduced with hydroxylamine hydrochloride and is extracted into I carbon tetrachloride as free iodine. It is then back-extracted as icdide into sodium bisulfite solution' and is precipitated as palladium iodide. The I
precipitate is weighed for chemical yield and is mounted on a nylon planchet I
j 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 lower limit of detection (LLD) in pCi/2, are performed as follows:
RESULT = (N/4t-B)/(2.22 E V Y OF)
TWO SIGMA ERROR = 2((N/4t+B)/at)I/2(2.22 E V Y OF)
LLO
4.66(B/4t)l/2 /(2.22 E V Y OF) where: N
total counts from sample (counts) l 4t = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi V = voltne 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 = ef ficiency of the counter for I-131, corrected for self absorption effects by the formula E = E3 (exp-0.0061M)/(exp-0.0061M )
3 E
s = efficiency of the counter determined from an 1-131 standard mount M
s a mass of Pd!2 on the standard mount, mg M = mass of Pd!2on the sample mount, mg B-5
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l ENVIRONMENTAL DOS! METRY Teledyne isotopes uses a CaSO4 :0y thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, negligible I thermally induced signal loss (f ading), 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 TL0s.
I Following the field exposure period the TL0s are placed in a Teledyne Isotopes Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed I and exposed to a known Cs-137 dose; each area is then read again., This provides a calibration of each area of each TLD af ter every field use. The transit controls are read in the same manner.
l Calculations of results and the two sigma error in net milliRoetgen (mR),
are performed as follows:
RESULT = 0 = (0 7+02+03+04 )/4 TWO SIGMA ERROR 1 = 2((02 -0)2+(03 -0)2+(0 4 -0)2+(0 -0)2)f 3)W
, where 0 = the net mR of area 1 of the TLO, and similarly for 0 , 0 , and 0 1
2 3 4 Og =1 1 K/Ry-A I
t = the instraent reading of the field dose in area 1 K = the known exposure by the Cs-137 source R
y = the instr ment reading due to the Cs-137 dose on area 1 A
= average dose in mR, calculated in similar manner as above, of the transit control TL0s I
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I GAMMA SPECTROMETRY OF SAMPLES I
Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the s ample. The sample is then counted for at least 1000 minutes with a shielded I Ge(L1) detector coupled to a mini-computer-based data acquisition system which performs pulst 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 I Marinelli and weighed. The sample is then runted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisi-tion system which performs pulse height analysis.
Fish I 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 sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a l mini-computer-based data acquisition system which performs. pulse height analysis.
Soils and Sediments Soils and sediments are dried to 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 at least six hours with a shieloed Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
l Charcoal Cartridges (Air lodine)
Charcoal cartridges are counted up to five at a time, with one positioneo on I the f ace 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 1-131 of each charcoal cartridge can be determined (assum-ing no positive I-131) uniquely from the volume of air which passed through I- 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 I The 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(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
I B-7
A mini-computer sof tware 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 radio.
I activity calculation using the appropriate fractional gamma ray abundance, half life, detector ef ficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume or pCi/ mass:
RESULT = (S-B)/(2.22 t E V F OF)
I TWO SIGMA ERROR = 2(S+B)l/2/ (2.22 t E V F OF)
I LLO = 4.66(B)l/2/(2.22 t E V F 0F)
I where: 5 = Area, in counts, of sample peak and background (region of spectrum of interest)
B = Background area, in counts, under sample peak, deter-
, mined 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 of interest and geometry I V of sample
= sample aliquot size (liters, cubic meters, kilograms, or grams)
F = fractional gamea abundance (specific for each emitted gamma)
DF = decay factor from the collection to the counting date I
B-8
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1 OETERMINATION OF GROSS ALPHA AND/OR GROSS BETA ACTIVITY IN WATER SAMPLES l
1.0 INTRODUCTION
The procedures described in this section are used to measure the I overall radioactivity of water samples without identifying the radioactive I
i species present. No chemical separation techniques are involved.
One liter of the sample is evaporated on a hot plate. Different ;
volumes may be used if the sample has a significant salt content as measured by a conductivity meter, or if unusual sensitivity is desired. 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 l 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 lamps just prior to counting.
Residue ' mass is determined by weighing the planchet before and af ter mounting the sample. The planchet is counted for alpha and/or 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.
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E B-9
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2.0 DETECTION CAPABILITY Detection capabilit/ depends upon the saple volume actually repre-
, sented on the planchet, the baikground and the efficiency of the counting instrument, and upon self-absorption of aloha and 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 (MOL) for water samples is nominally 1.6 picoeuries per liter for gross beta at the 4.66 sigma level (1.0 pC1/f at the 2.83 sigma level), asstning that I liter of sample is used and that 1/2 gram of sample residue is mounted on the planchet. These figures are based upon a nominal countiro time of 50 minutes and upon reoresentative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. The MDL
_ for gross alpha activity is nominally 2.3 picocuries per liter at the 4.66 sigma level (1.4 pCi/l at the 2.83 sigma level) also assuming that 1 liter of l sample is used and that 1/2 gram of sample residue is mounted on the planchet.
These figures are based upon a nominal 200 minute counting time and upon a representative efficiency of 0.02 and a background of 0.1 cpm.
The MOL becomes significantly lower as the mount weight decreases because of reduced s6if-absorption. At a zero mount weight, the 4.66 sigma MOL for gross beta is 0.9 picrocuries per liter and the MOL for gross alpha is 0.3 picoeuries per liter. These values reflect a beta counting efficiency of 0.38 and an alpha counting efficiency of 0.18.
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ANALYSIS OF SAMPLES FOR !ODINE-131 I Broadleaf Vegetation This procedure presents radiochemical methods for determining the I 131 activity in vegetation samples.
to 25-100 grams of the chopped sample. Stable iodide carrier is first added The sample is then leached with I sodium hydroxide solution, evaporated to dryness and tused in a muffle furnace.
The melt is dissolved in water, filtered and treated with sodium hypochlorite.
The iodine is then reduced with hydroxy! amine hydrochloride and is extracted I into chloroform. 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.
I I Calculctions of results, two sigma error and the lower limit of detection (LLO) in pCl/l, are performed as follows:
RESULT
= (N/4t B)/(2.22 E V Y OF)
TWO $!GMA ERROR
= 2((N/At+B)/6t)I/2(2.22 E V Y OF)
LLD / (2.22 E V Y OF) '
4.66(B/4t)1/2 where: N
total counts from Sample (counts) bt = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi V
- voluine or weight of sample analyzed Y
= chemical yield of the mount or sample counted 0F
= decay factor from the collection to the counting date
= ef ficiency of the counter for I-131, corrected for l
E self absorptien ef fects by th6 formula E
=E,(exp0.0061M)/(exp0.0061M,)
E, = efficiency of the counter determined from an 1-131 standard mount l M, = mass of Pd!2 on the standard nount, mg M
= mass of Pd!2 on the sample mount, mg
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I APPEND!X C l REMP PROGRAM EXCEPTIONS FOR SCHEDULED 5AMPLING AND ANALYSI$ DURING 1990 Date of Reasons for Loss /
Location Description Sampling Exception Sta NW 1.0 Air Filter 02/13/90-02/20/90 Sample not enllected due to mispositioned filter.
St a SW/WSW-0.95 Air filter 02/13/90 02/20/90 Pump out of service vane broken l S t a-E -3. 5 Air Filter 10/23/90-10/30/90 Pump out of service l S t a-N-1. 45 Air Filter 10/23/90-10/30/90 electrical failure Pump out of service sample not collected St a S/SSW-1.2 Air Filter 11/13/90 11/19/90 Pump out of service I sample collection i
timer failure Sta-S/SSW-1.2 Air Filter 11/19/90-11/27/90 Pump out of service sample collection timer failure l N-9.4 Air Filter 11/19/90 11/27/90 Pump out of service l electrical failure Sta SW/WSW-0.95 Air Filter 11/27/90-12/04/90 Sample not collected due to mispositioned l filter j Sta SW/HSW-0.95 Air charcoal 02/13/90 02/20/90 Pump out of service vane broken l S t a-NW-1. 0 Air charcoal 05/08/90 05/15/90 The LLD was not !
achieved due to low sample volume resulting from a I power failure Sta-E-3.5 Air charcoal 10/23/90-10/30/90 Pump out of service electrical failure Sta N-1.45 Air charcoal 10/23/90-10/30/90 Pump out of service pump broken j Sta-5/SSW-1.2 Air charcoal 11/13/90-11/19/90 Pump out of service bad timer Sta-S/SSW-1.2 Air charcoal 11/19/90-11/27/90 Pump out of service bad timer C-2
lI APPENDIX C RTMP PROGRAM EXCEPTIONS FOR SCHEDULED lI SAMPL!NG AND ANALYSIS DURING 1990 l
l Date of Re$asonsforLoss/
l Location Description Samoling Exception r l
l l St a N-9.4 Air charcoal 11/19/90 11/27/90 Sample not collected l Power out ll Sta-N 1.45 Veget at ion 02/13/90 Sanple not analyzed **
l 5 two unsuccessful i attempts made to l3 analyze sample by l l radiochemical method.
l Analysis by gamma spectroscopy gave LLD of (200 oCi/kg.
St a-SW-13. 5 Food / garden 07/31/90 Sample from control l l location unavailable l E due to drought Sta-SW-13.6 Food / Garden 08/28/90 " " "
! Sta SW-13.5 Food / Garden 09/25/90 "
Sta-NNW 0.1 Surface / Drinking 10/23/90 LLD for Ba/La 140 was l
Water not achieved. CPSES originally failed to i request a gamma spec analysis of this j sample. The analysis g was subsequently re-g quested and a.rformed l on 01/16/91. This delay in counting i resulted in the failure to achieve i
j the required LLO.
, Sta N-9.9 Surf ace Drinking 10/23/90 " " "
Water l S t a-NE- 7.4 Surface Water 02/13/90 Required LLO for 1 131 of 15 pCi/1 was not achieved (the MDA was 16 pCi/l) l i S t a-S E -1,3 TLD 10/05/90 01/09/91 TLD vandalized l Sta-SE-1,3 TLD 01/04/90 01/09/91 TLD vandalized Sta S-1.5 TLD 04/03/90 07/03/90 TLD vandalized
- See attached letter dated 04/02/90 providing additional explanation.
C-3
APPEND!x C ret 4P PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1990
~
Date of Reasons for loss /
Location Description Sampling Exception
]
Sta S-1.5 TLD 01/04/90 01/09/91 TLD in field from 07/03/90 01/09/91 ll i
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WW NE scrroess l ....v~.....,
wierwme. . si.m ...,
m su nm April 2,1990 I
bir. Chuck Curry TU Electric l PO Box 2300 Glen Rose, T.X 76043
Dear hit. Curry:
I am writing in response to your request for more trVormation concerning the note on Report of Analysis, WO 31542. For each of the two I attempts to analyze Tl M94040 for 1131, each step of PRO 03212 progressed as usual until step 5,4 (e), At that step, nothing theftlter, What should have remained was palladium todide. passed through However, upon I weighing the filter, the apparent yield was several hundred percent. A copy of the procedure is enclosed.
Sincerely, ll 0 A 71 %
. David biartin, Ph.D.
l Vice President Technical l JDht:cm Enc, l
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TELEX 134474 TOYl807 WTWO * *
- Eserunk 028 ?h S4 * *
- FAX (201) 664 550s
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. l APPENDIX 0 h
EXCEEDED REPORTING LEVELS 1990 None of the analytical measurements exceeded any notification level.
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l l \"l1UELECTRIC OFFICEMEMORANDUM CPSES 9028426 December 07, 1990 No Response Required 70: D. H. Bozeman 003
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION LAPD USE CENSUS SUPERSEDES: CPSES 9019888 The Land Use Census identifies receptors within a five (5) mile ras:tus of the plant in each of the sixteen (16) meteorological sectors. The Land Use Census includes the following items:
- 1. Population by Sector and Distance
- 2. Nearest Resident by Secto'. and Distance
- 3. Nearest Garden by Sector and Distance
- 4. Nearest Hilk Animal by Sector and Distance
- 5. A Map with an Accompanying Map Legend
- 6. Environmental Sampling Locations Listed below are public use areas within the five (5) mile radius and the approximate attendance for the areas in 1989:
- 1. Camp Arrowhead 3,600
- 2. Dinosaur State Park- 226,956
- 3. Glen Lake Camp- 8,000 I 4.
5.
Cedar Brake Ctrl Scout Camp- 830 Squaw Creek Park 38,485
- 6. Ke11ers Camp- 7,000 March to November I 7.
8.
Tres Rios Camp- 40,000 Oakdale Camp & Fish- 4,500
- 9. Oakdale Park- 69,000 I 10.
11.
Creation Science Museum- 12,000 Texas Amphitheater- Glen Rose- 10,000 l
cx n-G. J. Brown E02 Environmental Technician CJBiejp ATTACHMENT cci CCS E06 I E-2
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- I Population
- By Sector and Distance Sector Distance (Miles) 01 12 2-3 34 45 Total I N - -
3 26 71 100 NNE 8 71 21 100 NE - -
50 82 184 316 ENE - - 39 5 24 68 26 124 I
E 23 173 ESE - -
11 92 100 203 SE - - 47 21 26 94 SSE -
18 32 26 2534 2610 S 21 8 21 103 153 SSW -
3 3 3 50 59 SW -
79 8 34 21 142 WSW -
82 3 5 -
90 W -
53 5 26 8 92 WNW - -
$ 26 60 91 NW - -
5 - -
5 NNW - -
3 26 11 40 TOTAL
- 256 256 588 3236 4336
- Based on an average of 2.4 residents per house. (Obtained from North Central Texas Council of Governments, 1989 based on an average from 2.6 for single I f amily,1.8 for mobile home residences, 2.66 for multi-f amily.
(1) Includes pennanent residents at Happy Hills Children's Home.
(2) Includes permanent residents at Camp Arrowhead.
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1 i
e ~3-Nearest Resident by Sector and Distance i
Sector Distance (Milee)
)
N 2.2 NNE 2.3 NE 2.3 ENE 2.4 E
?.4 ESE 2.3*
SE 2.0*
i I SSE S
1.6 1.6 SSW l.9 l
SW 1.0 !
WSW 1.0 W i 1.5 i WNW 2.0 NW 2.7*
NNW 2.7
- Denote change from previous year I .
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+4-Nearest Carden by Sector and Distance I Sector Distance (Miles)
N None NNE 2.4 NE 2.7 ENE 2.6*
E None*
ESE 2.3 SE 2.$
SSE 4.8*
S 4.3*
JSW 1.1*
W 1.5 VNW 3.0 NW None I
NNW 4.9*
- Denotes change from previous year I
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i 1 .$.
Nearest Milk Animal by Sector and Distance Sector Distance (Mile:Q SSE 2,2 S 4.2*
SW 4,7*
NNW 4.5 NE 4,2*
All other Sectors None I
- Denotes change from previous year, additional milk animals identified in 1989 at locations WW 4.0 and NNE 4.5 were not identified in 1990.
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) Pago 1 of 2 EVA1,UATION OF 1990 LAND USE CENSUS The results of the 1990 L.and Use Census were reviewed fc a. pact on the Radiological Environmental Monitoring Program (REMP). The sampling program requirements that could be affected by changes in land use are:
(1) Milk -
ODCM Table 3.12 1 requires that samples be obtained from milking animals in three locations within 5 k:n having the highest potential dose. If none are available, samples are acceptable frem milking animals in locations 5 to 8 km distant where doses are calculated to I be greater than 1 mrem per year. A sample is also required at a control location.
I currently, milk samples are collected at one indicator location (SSE 2.2) and at a control location.
(2) Food Products -
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 I in which liquid plant wastes have been discharged.
Currently, food products are sampled from two indicator locations (ENE 9.0, Pecans; E 4.2, vegetables) and one control location.
(3) Broadleaf Vegetation -
ODCM Table 3.12 1 requires a saeple of broadleaf vegetation from each of two offsite locations of highest predicted annual average D/Q if milk sampling is not performed at all required locations, Currently, broadleaf vegetation samples are cellected at two indicator locations (N 1.45 and SV 1.0) and one control location.
I These locations are near the site boundary in sectors where broadleaf is available and D/Q is greatest.
Based on these requirements, the ellk animals identified at locations S 4.2, SV 4.7, NE 4.2 and VNV 4.5 were evaluated for possible inclusion in the REMP. Chemistry and Environmental Personnel have determined that these milk animals are not milked and are not available for sampling.
I Therefore, no changes to the milk sampling locations of the REMP are required.
I Of the gardens that were identified, no new gardens were identified that are irrigated with water in which liquid plant vastes are discharged.
Thenfore, no change to the REMP is required.
Finally, since broadleaf vegetation is currently collected at the site boundary, no changes to broadleaf sartpling locations are required. There are no identified locations closer to the plant.
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I Page 2 of 2 In summary, the 1990 1.and Use Census did not identify any new locations that are available for saapling and would yield a calculated dose greater than at a location from which samples are currently obtained.
I changes to the RE.MP samplin6 locations described in ODCM, Part II, Section 3.1, are not required.
Therefore, Although no regi' ired changes to the RE.MP sampling locations were identified, changes to the controlling receptor locations and pathways, and associated atmospheric dispersion paran.eters were given in ODCM, Part I II, Tables 2.4 and 2.5 were identified. These parametets are used in dose calculations required by Radiological Effluent Controi 4.11.2.3.
2.4 and 2.5 will be revised to reflect the 1990 1.and Use Census data.
Tables I
I Evaluation Performed By:
Date: _ /1~ /N ~ 90 usa 1 y ysicist ,Y g
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