ML20108C625
| ML20108C625 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1995 |
| From: | Terry C, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-96129, NUDOCS 9605070055 | |
| Download: ML20108C625 (100) | |
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r7 Log # TXX-96129 File # 10300 l
10160 clo i r = 916 (6) clo Ref. # 10CFR50 App. I 7UELECTR/C
- c. tance Ter.y April 30, 1996 Gmup Mce President l U. S. Nuclear Regulatory Commission Document Control Desk Washington, DC 20555
SUBJECT:
COMANCHE PEAK STEAM ELECTRIC STATION (CPSES)
DOCKET NOS. 50-445 AND 50 446 OPERATING LICENSES NPF 87 AND NPF 89 TRANSMITTAL OF THE ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT FOR 1995 Gentlemen:
Enclosed is one (1) copy of the Annual Radiological Environmental Operating Report for the CPSES Radiological Environmental Monitoring Program. This report is submitted pursuant to Section 6.9.1.3 of the CPSES Unit 1 and 2 Technical Specifications. The report covers the period from January 1, 1995, through December 31, 1995, and summarizes the results of measurements and analysis of data obtained from samples 1 collected during this interval. l l
If there are any questions regarding this report, contact Connie Wilkerson I at (214) 812 8819 or Doug Kay at (817) 897-5204.
Sincerely, l C. L. Terry By:
D. R. Woodlan Docket Licensing Manager CLW/grp i Enclosure l l
c- Mr. L. J. Callan, Region IV w/ encl.
Mr. T. J. Polich, NRR (clo)
Resid n t Inspectors, w/ encl.
i 0G01~9.-J t
! 9605070055 951231 1 PDR ADOCK 05000445 R PDR l
, i Energy Plaza 1601 Bryan Street Dallas, Texas 75201 3411
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Z Z 1UELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM 1995 ANNUAL REPORT REVIEW / APPROVAL Reviewed By:
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Date: h/7'b Edwin T. Floyd Senior Radiation Protection Technician Reviewed By: &l <
N Date: L4- \9 d b ,
Douglas (p. Kay [] {
Radiation Protection supervisor '
Approved By: M Date: hf/9f7b Jo@ 'R. Curtis Radiation Protection Manager P.O. Box 1002 Glen Rose, Texas 76(M3-1002
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f TABLE OF CONTENTS
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SECTION PAGE I
L INIRG)UCITGV. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
I A Site an d Station Description ................................................................ 2 H Objectives and Overview of the............................................................ 2 1 CPSES Monitoring Program 1
II. PROGRAM DESCRIPTI ON ... .. .. .. .. .. ..... .. .... .. .... ... .. .. .. .. . . ..... .. .. .. ...... ... ...... .. .. .. ... .. .... 6 A Sa mp le Lo c a ti on s .. .. .. .. . . ........... .. .... .. ..... . . .. .. ....... .. .. .. ...... ... ............ ...... .. 7 i B Sampling Methods and Proced ures. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 1
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- 1. Direct Radia tion. .. .. .. . .. . ... . ... . ... ... . .. . . . .. .... ... . . . . .... . . .. . .. . ... .... .... . . .. 8
- 2. Air Particulates and Air Iodine .......................................... 8
- 3. Milk..............................................................................................9
- 4. Water............................................................................................9
- 5. Fish..........................................................................................11
- 6. S h o reli n e Se dim en t ................... .......................................... I 1
- 7. Food Pmducts. .. . . . . . . . . ...... .. ... . .... .. . . ... . .. . . . . .. . . .. .. .. . .... . . . . . ...... .. .. . 1 1
- 8. Broadl eaf Vege tat 1on .................. ......................................... 1 2 l 1
l C. Interlaboratory Comparison Program ......................................... 12 l D. Deficiencies in the Sample Program........................................... 13 III.
SUMMARY
AND DISCUSSION OF 1995 ANALYTICAL RESULTS......14 A Direct Radiation. .. . . . . ... ..... . . . ... . . . ... . ... . . . . . . . . .. .. . . . . . .. . . .. .. .. . . . . ... .. .. .. . . .. ... . . .. . 1 6 H Air Particulates and Air Iodine ...................................................... 17 l C. M11k.........................................................................................................18 D. Water........................................................................................................18 E. Fish...........................................................................................................20 11
F. S h o relin e Se d im en ts ... ............... .. .... ............................... ...... .. .... ...... 2 0 G. Food Pmducts. . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . .. . . . . ... . . . . . . . . . . . . . . . . .. .
H. B ro ad le af Vege ta tio n ...... .... ......... .. .. ..... ...... ........... .. .. .... ... ...... ......... ... 2 1 IV. C ON CLU SION S .. .. . . . . .. . . . . .. .. . .. .. .. .. .. . ... .. . .. .. .. .. .. .. .. .. . .. .. .. .. .. .. .. ... .. .. .. .. . . . . . . ... . . . . .
V. REPl!REN38. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .
VI. IMTATNWFR................................................................,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,,27 i
I APPENDICES APPENDIX A EPA Cros s -C he ck Program ..............................................................A- 1 1
APPENDIX B Synopsis of Analytical Procedures ................................................B- 1 APPENDIX C Exceptions to the 1995 REMP..... ................... ................... .......... .C- 1 1
i APPENDIX D Exc e e d e d Rep o rting Levels ........................................................... D- 1 l
APPENDIX E Iand Use Census... . ......... . . . .... . . . . . . .... ........... ...... . . ...... . ........ ... .. . . . . . . . . . . . . E - 1 l 111 i
LIST OF TAB 1JCS TABLE TITLE PAGE 1 CPSES Radiological Environmental ......................................................... 2 8 Monitoring Program 2 Direct Radiation -- Thermoluminescent Dosimetry......................... 31 3 Concentrations of Iodine-131 in Filtered Air...................................... 33 4 Concentrations of Gross Beta Emitters in Air Particulates............ 36 5 Concentrations of Gamma Emitters in Air Particulate Filters...... 39 6 Concentration s of Iodine- 131 in Milk.................................................... 41 7 Concentrations of Gamma Emitters in Milk ........................................ 42 8 Concentrations of Gamma Emitters in Groundwater....................... 43 9 Coneentrations of Tritium in Groundwater.......................................... 45 10 Concentrations of Gross Beta in Water-Surface / Drinking.............. 46 11 Concentrations of Gamma Emitters in Water-Surface / Drinking.47 12 Concentrations of Iodine-131 in Water-Surface / Drinking............. 48 i 13 Concentrations of Tritium in Water-Surface / Drinking.................... 49 14 Concentrations of Gamma Emitters in Surface Water...................... 50 l
15 Coneentrations of Tritium in Surface Water ........................................ 52 16 Coneentrations of Gamma Emitters in Fish ......................................... 53 i
17 Concentrations of Gamma Emitters in Sediment.............................. 54 18 Concentrations of Gamma Emitters in Food Products..................... 55 19 Concentrations of Gamma Emitters in Broadleaf Vegetation........ 56 20 Radiological Environmental Monitoring Program Summary -
January 1 to December 3 1, 19 9 5 .. .. .. .. . . .. . .. . . .. .. . . . .. .. .. . . . .. . . .. ... .. .. . . . . .. . . . .. .. . . 5 8 iv
l INTRODUCTION 1
I. INTRODUCTION Results of the Radiological Environmental Monitoring Program for the Comanche Peak Steam Electric Station for 1995 is contained within this re-port. This report covers the period from January 1, 1995 through December 31,1995 and summarizes the results of measurements and analy-ses of data obtained from samples collected during this interval.
A. Site and Station Description Comanche Peak Steam Electric Station (CPSES) consists of two PWR units, each designed to operate at a power level of about 1150 megawatts (electrical). The station is located on Squaw Creek Reservoir in Somervell County about forty miles southwest of Fort Worth. Texas. Unit I received a low power operating license February 8,1990 and achieved initial criticality on April 3,1990. A full power license for Unit 1 was issued on April 17,1990, and commercial operation was declared on August 13, 1990. Unit 2 achieved initial criticality on March 24,1993 and synchronized to the electrical grid on April 9,1993.
H Qbjectives 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-rizing 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 j 2 i
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release limits are not exceeded. However, as a precaution against 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 lan<j :.2se 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 j monitoring issued by the Radiological Assessment Branch, Revision 1 (November 1979)(1), the CPSES Technical Specifications (4) and the CPSES Offsite Dose Calculation Manual (ODCM)(5),
in 1995, 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-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 3
few percent increase above normal background radioactivity. '
l Background levels at any one location are not constant but vary with i l
time as they are influenced by external events such as cosmic ray I bombardment, weapons test fallout, and seasonal variations. These levels also can vary spatially within relatively short distances re-flecting variations in geological composition. To differentiate be-tween background radiation levels and increases resulting from op-eration of CPSES, the radiological surveys of the plant environs are divided into preoperational and operational phases. The preopera-tional phase of the program permits a general characterization of the radiation levels and concentrations prevailing prior to plant op-cration 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 preop-erational phase, assist in the evaluation of the radiological impact of plant operation.
Preoperational measurements were conducted at CPSES from 1981 :
to 1989. These preoperational measurements were performed to:
- 1. Evaluate procedures, equipment and techniques. I 1
- 2. Identify potentially important pathways to be moittored 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
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conducted to:
- 1. Verify that measurable concentrations of radioactive mate-rials and levels of radiation are not higher than expected on the basis of the effluent 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.
- 3. Identify changes in the use of areas at and beyond the site boundary that may impact the principal pathways of expo-sure.
This report documents the sixth year of operational measurements and is submitted in accordance with the requirements of the CPSES Offsite Dose l l
Calculation Manual. Part I, Administrative Control 6.9.1.3.
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PROGRAM DESCRIPTIONS 1
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H. PROGRAM DESCRIPTION A. Samole Locations Seventy-five locations within a radius of 20 miles from the CPSES site were included in the monitoring program for 1995. 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 considered were applicable regulations, population distribution, ease of access to sampling stations, availability of samples at desired ,
1 locations, security and future program integrity. Additionally an l annual land use census is conducted to identify changes in the use of areas surrounding the plant. If changes are identified that im-pact the principal pathways of exposure, appropriate changes to the radiological environmental monitoring program are implemented.
The results of the 1995 Land Use Census are provided in Appendix l E.
The Radiological Environmental Monitoring Program for Comanche Peak is summarized in Table 1.
H Sampling Methods and Procedures To derive meaningful and useful data from the Radiological Environmental Monitoring Program, sampling methods and proce-dures are required which will provide samples representative of potential pathways of the area. The methods and procedures used foi aach pathway monitored are described below.
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- 1. Direct Radiation Thermoluminescent dosimeters (TLDs) were used to de-termine the direct (ambient) radiation levels at monitoring points. Sampling locations were chosen according to the criteria given in the USNRC Branch Technical Position on Radiological Monitoring (Revision 1, November 1979)(1).
The area around the station was divided into 16 radial sec-tors of 22-1/2 degrees each. TLDs were placed in all sec-tors. Thermoluminescent dosimeters were located in two rings around the station. An inner ring was located at the site boundary and an outer ring was located at a distance of 4 to 6 miles from the station. Eleven additional TLDs were located at points of special interest, including two control 1
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 1 l
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 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 l 8
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iodine was collected by drawing air through a TEDA im-pregnated charcoal cartridge which was connected in se-ries behind the filter. 'Ihe filters and charcoal cartridges i were collected weekly by CPSES staff. In the laboratory, I air particulate filters were analyzed for gross beta activity and were composited quarterly for gamma spectrometry analysis. Charcoal cartridges were analyzed for iodine-131.
- 3. Milk Milk samples were collected by CPSES staff monthly for the period January through April. May through December samples were collected every two weeks. Upon arrival at the laboratory, the milk samples were promptly analyzed for gamma emitters and for 1-131 by utilizing radio-chemistry 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 lo-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 line since the start up of Unit 1.) Location NE-7.4 9
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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.
Surface water samples from Squaw Creek Reservoir loca- ;
tions were collected weekly and composited for monthly gamma isotopic analysis. Samples from Lake Granbury lo-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 Iake 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 every two weeks and gamma isotopic and gross beta analyses monthly. Trit:um analyses were performed quarterly.
There are five groundwater locations (SSE-4.6, W-1.2, WSW-0.1, N-1.45 and N-9.8). Groundwater supplies in the site area are not affected by plant effluents and are sampled only to provide confirmation that groundwater is 10
not affected by plant discharges.
Groundwater samples were collected quarterly. Gamma isotopic and tritium analyses were performed by location.
- 5. Bsh Fish samples were collected at two locations for the 1995 program. An area 2.0 miles east-northeast of the site in Squaw Creek Reservoir was chosen as the indicator loca-tion, and a locatJon 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 Shmiine sediment samples were collected in January and July from location N-1.0 and in July from the new location SE-5.3. Samples were also collected from Lake Granbury at the control location N-9.9, and location NE-7.4, which is downstream of the discharge of the return line from Squaw Creek Reservoir. CPSES staff collected the sediment samples and shipped them to the laboratory for analysis by gamma spectrometry.
- 7. Food Products During the period of January through December,16 sam-ples were collected from two indicator sampling locations 11
(ENE-9.0 and E-3.5) and one control location (SW-12.7).
A total of 9 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-l tion (SW-13.5) and two indicator stations (N-1.45 and SW- j 1.0) near the site boundary. Collection of broadleaf vege-tation started in May 1995. Broadleaf samples consisted of available tree leaves, native grasses and weeds.
Gamma isotopic and iodine-131 analyses were performed for all broadleaf vegetation samples.
C. Interlaboratory Comparison Program To demonstrate that the results of the environmental analyses are l 1
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).
The purpose of the interlaboratory comparison program is to pro-vide an independent check on the laboratory's analytical proce-dures and to alert it to any possible problems. Participant labora-tories measure the concentrations of specified radionuclides and report them to the issuing agency. The agency then furnishes the 12
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known values to the participant laborderf 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. j The results of Teledyne Brown Engineering - Environmental Services' participation in the U.S. EPA Interlaboratory Comparison Program for 1995 are provided in Appendix A.
D. Deficiencies in the Sample Program In accordance with section 6.9.1.3 of the ODCM(5), any deviations from the sampling schedule of Table 3.12.1 of the ODCM shall be reported in the annual environmental monitoring report. Appendix C contains a listing of all deviations of the sampling schedule.
Deficiencies in the program are deviations from the sampling schedule that were preventable by CPSES staff. During the year 1995, one deficiency in sampling occurred in the air sampling program. The air particulate sample at location E-3.5 for the week of 1/24/95-1/31/95 was not available due to personnel error in not starting the air pump. Therefore, the sample results were invalid.
As a corrective action, new type air sample pumps are now being used that do not require being turned off and on in order to replace the sample filter head. There were no other deficiencies during 1995.
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l SUMARY AND DISCUSSION OF 1995 ANALYTICAL RESULTS 1
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III.
SUMMARY
AND DISCUSSION OF 1995 ANALYTICAL RESULTS i
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- Data from the radiological analyses of environmental media collected i
, 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 4
, Quality Assurance Manual IWL-0032-395 and are detailed in Teledyne Brown !
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l Engineering - Environmental Services Analytical Procedures Manual. A syn-opsis of analytical procedures is contained in Appendix B of this report.
Radiological analyses of environmental media characteristically ap-i
- proach and frequently fall below the detection limits of state-of-the-art mea-surement methods as discussed in NCRP Report No. 50(2), Ihe use of "<" in
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] the data tables symbolizes that the result is less than.the lower limit of de-1 tection (LLD) as defined in Appendix B. Not Detected, "ND", is used period- l l Ically in the tables presenting gamma analysis results for various media. It l primarily appears under th'e "Others" column, and indicates that no other l detectable gamma emitting nuclides were identified. The Teledyne Brown Engineering - Environmental Services analytical methods meet the LLD re-
{ quirements addressed in the CPSES Offsite Dose Calculation Manual.
J j Tables 2 through 19 give the radioanalytical results for individual f
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.
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l A Direct Radiation Environmental radiation dose rates determined by thermolumines-cent dosimeters (TLDs) are given in Table 2. Thermoluminescent dosimetry badges with four readout areas each were deployed at each location on quarterly and annual cycles. The mean values of four readings (corrected individually for response to a known dose and for in-transit exposure) are reported.
A statistical summary of the 1995 data is included in Table 20. For the quarterly analyses the average dose rate of the control locations l 1
was 0.12 mR/ day with a range of 0.10-0.13 mR/ day. 'Ihe average of I l
the indicator locations for the quarterly samples was 0.11 mR/ day I with a range of 0.08 to 0.15 mR/ day. For the annual samples, the average dose rate for the control samples was 0.14 mR/ day. The indicator locations had an average of 0.12 mR/ day with a range of 0.07-0.16 mR/ day. 1 Oakley(3) calculates an tonizing 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 va'ues rep-1 resent averages covering wide' geographical areas, the measured ambient radiation average of 43.8 mR/ year for the immediate locale of CPSES is consistent with Oakley's observations. Significant vari-l ations occur between geographical areas as a result of geological l ccmposition and altitude differences. Temporal variations result from changes in cosmic ray intensity, local human activities, and l l
factors such as ground cover and soil moisture.
Anomalies in the 1995 measured doses relative to preoperational I
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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 re-
. spectively. The 1988 averages for the quarterly and annual indica-tor locations were 0.16 mR/ day (range of 0.10 to 0.20) and 0.15 mR/ day (range of 0.12 to 0.18) respectively.
R Air Particulates and Air Iodine A total of 414 charcoal cartridges were analyzed for airborne io-dine-131 by gamma spectrometry. No iodine-131 was detected at any of the sampling stations. Results of these measurements are presented in Table 3.
A total of 414 air particulate filters were collected and analyzed for gross beta activity. For 1995 the average gross beta activity for the control location was 0.022 pC1/m3 with a range from 0.011 to 0.040 pC1/m3- For the seven indicator locations the yearly average was 0.023 pCi/m3 with a range from 0.011 to 0.043 pC1/m3. The gross beta analysis data are presented in Table 4. Anomalies in gross beta measurements relative to preoperational data were not noted.
Air filters were composited quarterly and then analyzed by gamma spectrometry. The gamma spectrometry data is presented in Table
- 5. Cosmogenic beryllium-7 was detected in all 32 samples. The average beryllium-7 activity for the control location was 0.085 pC1/m3 with a range of 0.072 0.102 pC1/m3 For the indicator locations. the average beryllium-7 activity was 0.091 pC1/m3 with a range of 0.064 to 0.128 pC1/m3 Potassium-40, a naturally occurring nuclide, was measured in eight samples. The average 17 o
potassium-40 for the control location was 0.023 pC1/m3- '1he average potassicm-40 activity for the indicator locations was 0.011 pCi/m3 with a range of 0.065-0.017 pCi/m3 C Milk A total of 22 milk sar.1ples were collected in 1995. All samples were analyzed for iodine-131 by radiochemistry and for other gamma emitting isotopes by gamma spectrometry. Results of these measurements are presented in Table 6 and 7.
No iodine-131 was found in any of the milk samples. The lower I 1
limits of detection can be found in Table 6.
Results of the gamma spectrometry measurements are presented in Table 7. Naturally occurring potassium-40 was detected in all of the milk samples. The average activity for the control location was l l
1389 pC1/1 with a range of 1200 to 1670 pCi/1, Cesium-134, Cs-137 and La-140/Ba-140 were not detected in any of the samples.
The lower limits of detection can be found in Table 7.
D. Water Groundwater samples were collected from five locations during 1995. The samples were analyzed for gamma emitters and tritium on a quarterly basis, pursuant to the ODCM requirements for groundwater. Seventeen samples were analyzed for gamma emit-ters 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 i sampling location were analyzed for tritium; no tritium was detected. Results of these analyses are contained in Table 8 and 9 respectively.
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Surface-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 19 pCi/l with a range of 13 to 23 pCi/1. The control station had an av-erage activity of 10 pC1/1 with a range of 6.0 to 14 pCi/1. Eight quarterly composites were analyzed for tritium. We indicator sta-tion had an average activity of 7875 pC1/1 with a range of 7000 to 8600 pCi/1. The control station showed no tritium activity above the lower limit of detection. Iodine-131 analyses by radiochemistry were performed on 52 samples of surface-drinking water; there was no measurable activity. Results of these analyses are contained in Tables 10-13.
Surface water was ' sampled from four locations during 1995.
Samples were analyzed for gamma isotopic on a monthly basis (composite (2) and monthly (2)) and tritium composites on a quarterly basis. Fifty-two samples were analyzed by gamma spectrometry. Potassium-40 was detected in one sample at Station I N-19.3 a control station, with an average activity of 66 pCi/1.
Sixteen composited surface water samples were analyzed for tri-tium. The indicator stations had an average activity of 8300 pC1/1 with a range of 6800-9900 pCi/1. He results of these analyses can I be found in Table 14 and 15 respectively. The tritium detected in Squaw Creek Reservoir samples of surface water and surface-drinking water is attributed to liquid effluent discharges from CPSES. The level of tritium in the Squaw Creek Reservoir is well within the expected value predicted in the CPSES Final Safety 19
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l Analysis Report. {
E. ELSh The results of gamma isotopic analyses of fish samples collected during 1995 are presented in Table 16. A total of eight samples were analyzed, four from the indicator location (ENE-2) and four from the control location (NNE-8). Sampling efforts concentrated on the larger edible species of commercial and/or recreational im-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 occasions. Naturally occurring potassium-40 was detected in all samples. The average potassium-40 concentration for the four in-dicator samples is 2843 pC1/kg wet with a range of 2210 to 3160 1 I
pCi/kg wet. The average concentration for the control location is 3338 pC1/kg wet with a range of 2740 to 4110 pCi/kg wet. No i other gamma emitters were detected in any samples.
I F. Shoreline Sediments l
- The processes by which radionuclides and stable elements are con-centrated in bottom sediments are complex, involving physiochem-ical interaction in the environment between the various organic and inorganic materials from the watershed. These interactions can proceed by a myriad of steps in which the elements are absorbed in or displaced from the surfaces of colloidal particles enriched with l chelating organic materials. Biological action of bacteria and other I benthic organisms also contribute to the concentration of certain elements and in the acceleration of the sedimentation process.
Results of the gamma isotopic analyses of the sediments sampled i 20 .
1 I
i i
from the CPSES environment are given in Table 17. For 1995 four i
l locations, one control and three indicators, were sampled. New location SE-5.3 was added in the second half of the year. l l
Naturally occurring gamma emitters found in detectable concen-
! trations were Be-7, K-40, Pb-212, Bi-214, Pb-214 Ra-226 and Th-228. No cesium-137 was measured in any sample during 1995. l l Preoperaticual levels of cesium-137 have ranged from 9.2 to 150 i pC1/kg on four different occasions. !
G. Food Products l l
Results of gamma isotopic analyses of food semples are contained in Table 18. A total of 16 samples were analyzed from three locations.
Potassium-40, a naturally occurring isotope, was found in all 16 !
samples. For the indicator locations the average potassium-40 ac-tivity was 2341 pCi/kg wet with a range of 708 to 3640 pCi/kg wet.
Naturally occurring beryllium-7 was detected in five samples, from control station SW-12.7, with an average activity of 305 pC1/kg wet l
and a range of 82-726 pCi/kg wet.
No I-131, Cs-134 or Cs-137 were detected in food products during !
1995.
H. Broadleaf Vegetation Results of gamma isotopic analyses of broadleaf vegetation samples are contained in Table 19. A total of 32 samples were analyzed from three locations. Potassium-40, a naturally occurring isotope, was found in all samples. The average potassium-40 activity for the control location was 6501 pC1/kg wet with a range of 3830 to 10400 pCi/kg wet. For the indicator locations the average potas-slum-40 activity was 4171 pC1/kg wet with a range of 2110 to 7220
\
21 l
l
pCi/kg wet. Naturally occurring beryllium-7 was detected in twenty-one indicator samples with an average activity of 2331 pC1/kg wet; the range was 706 to 4840 pCi/kg wet. The eleven stunples from control station SW-13.5 were found to have beryl-llum-7 with an average activity of 2233 pCi/kg wet and a range of 938-4630 pCi/kg wet.
Thorium-228 was detected in one sample from control e,tation SW-1 13.5 with an average activity of 78 pCi/kg wet.
Iodine-131, Os-134 and Cs-137 were below the lower limit of de-tection in all samples.
I I
l 4
22
1 1
i l
l l
l l
l l
l l
l l
l CONCLUSIONS '
23
IV. CONCLUSIONS It is concluded from the levels obtained in environmental samples 1
during 1995 and comparison of these levels to preoperational measure-ments and operational controls, that the operation of CPSES in 1995 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 Reservoir which has increased from the 1994 average of approximately 6450 pCi/l to approximately 8675 pC1/l. This increase has been expected,
, based on 2 unit operation. The atmospheric environment was sampled for
) airborne particulate matter, radiolodine, and direct radiation. The d
i terrestrial environment was sampled for milk, groundwater, surface-
) drinking water, food products and broadleaf vegetation. The aquatic j environment was sampled for surface water, fish and shoreline sediment.
1 i The analyses of these samples provided results which were either below the measurement detection limits or were indicative of natural terrestrial and !
j cosmic ray radiation levels, except for the tritium in the surface water of Squaw Creek Reservoir which was far below the reporting levels for i radioactivity concentrations in environmental samples.
One improvement item for the 1996 year will be the collection of broadleaf vegetation on a monthly basis, in the past this had been done only in the months of the growing season and while milk animals were on pasture, )
i i
24
REFERENCES l
V. REFERENCES
- 1. U.S. Nuclear Regulatory Commission "An Acceptable Radiological Environmental Monitoring Program", Radiological Assessment Branch Technical Position, November 1979, Rev.1
- 2. National Council on Radiation Protection and Measurements,
" Environmental Radiation Measurements", NCRP Report No. 50, Washington, D.C., December 27,1976
- 3. Oaldey, D.C., " Natural Radiation Exposure in the United States".
ORP/SID 22-1 Offlee of Radiation Programs, U.S. Environmental Protection Agency, Washington, D.C., June 1972
- 4. Comanche Peak Steam Electric Station Units 1 and 2 Technical Specifications
- 5. Offsite Dose Calculation Manual For TU Electric Comanche Peak Steam Electric Station Units 1 and 2.
26
.n- -e. 3 a 1
DATA TABLES 1
l l
l l
l l
27
TABE I (PAGE 1 OF 2)
T U EECTRIC COMANCHE PEAK STEAM EECI'RIC STA*I1ON RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -- 1995 Identification by Number of Sector and Distance Sampling Analytical Media locations fMiles) Freanency fal Analvses Freauenev fal Gamma Exposure 43 N-1.45: N-4.4: N-6.5: Q.A Thermoluminescent Q.A N-9.4: NNE-1.I Dosimetry NNE-5.65: NE-1.7: NE-4.8:
ENE-2.5: ENE-5.0; E-0.5:
E-1.9; E-3.5: E-4.2:
ESE-1.4: ESE-4.7; SE-1.3:
SSE-4.4: SSE-4.5: S-1.5:
S-4.2: SSW-1.1: SSW-4.4; SW-0.9: SW-4.8: SW-12.3:
WSW-1.0; WSW-5.35:
WSW-7.0; W-1: W-2: W-5.5 g WNW-1: WNW-5.0; WNW-6.7:
NW-1: NW-5.7: NW-9.9:
NNW-1.35: NNW-4.6 Air Particulate 8 N-9.4 W Gross Beta W Air Iodine E-3.5: SSE-4.5 Gamma Spectrometry Filter QC SW-12.3: Gamma Spectrometry NW-1.0; N-1.45: SW/WSW-0.95 Charcoal Cartridge W S/SSW-1.2 Surface Water 4 N-19.3: ESE-1.4: N-1.5 M (b) Gamma Spectrometry M NE-7.4 Tritium QC Groundwater 5 SSE-4.6 Q Gamma Spectrometsy Q W-1.2: WSW-0. I N-9.8: N-1.45 Tritium Q Water-Surface 2 NNW-0.1: N-9.9 S M (c) Gruss Beta M Drinking Gamma Spectrometry M Iodine- 131 SM Tritium QC
TABLEI (PAGE 2 OF 2)
T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION RADIOLOGICAL ENVIRONMENTAL MONTIURING PROGRAM - 1995 Identification by Number of Sector and Distance Sampling Analytical Media Imations (Milesi Freauency fal Analvses Frennen,v fal Sediment 4 N-9.9: NNE-1: NE-7.4 SA Gamma Spectrometry SA SE-5.3 Fish 2 NNE-8; ENE-2 SA Gamma Spectrometry SA Milk 1 SW- 14.5 SM, (d) Iodine-131 SM (d)
Gamma Spectrometry SM (d)
Food Products 4 E-4.2: ENE-9.0: E-3.5: MH Gamma Spectrometry MH SW- 12.7 Iodine-131 MH Broadleaf 3 N-1.45: SW-1.0: SW-13.5 M Gamma Spectrametry M y Vegetation Iodine-131 M (a) Frequency Codes Are: W = Weekly M = Monthly Q = Quarterly QC = Quarterly Composite SM = Semimonthly (i.e., once per 2-week period)
MH = Monthly during availability for harvest SA = Semiannual A = Annual (b) Surface water samples from Squaw Creek Reservoir are monthly composites of weeldy grab samples. Samples from Lake Granbury are monthly composites of weekly grab samples when Lake Granbury is receiving letdown from Squaw Creek Reservoir; otherwise they are monthly grab samples.
(c) Drinking water samples are a composite of weekly grab samples over a 2-week period when I-131 analysis is performed: otherwise they ase monthly composites of weekly grab samples.
(d) Milk sample collection and analysis frequency is semimonthly when animals are on pasture. Otherwise samples are collected and analyzed monthly.
F1GURE 1 (Page 2 OF 2)
EET OF ENVIRONMENTAL SAMPLING LOCATIONS SAMPLING LOCATION SAMPLE SAMPLING LOCATION SAMPLE POINP (SECIOR-MU MI TYPE
- ICINP i% 3UKMUMI *IYIE' A1 N- 1.45 A R28 SW-4.8 R A2 N-9.4 A R29 SW-12.3 R A3 E-3.5 A R30 WSW-1.0 R A4 SSE-4.5 A R31 WSW-5.35 R A5 S/SSW-1.2 A R32 WSW-7.0 R A6 SW-12.3 A R33 W-1.0 R l A7 SW/WSW-0.95 A R34 W 2.0 R l A8 NW-1.0 A R35 W-5.5 R R36 WNW-1.0 R R37 WNW-5.0 R R38 WNW-6.7 R R39 NW-1.0 R R40 NW-5.7 R R1 N- 1.45 R R41 NW-9.9 R R2 N-4.4 R R42 NNW-1.35 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 R6 NNE-5.65 R SW3 N 19.3 SW l R7 NE- 1.7 R SW4 NE-7.4 SW l R8 NE-4.8 R SW5 ESE-1.4 SW R9 ENE-2.5 R SW6 NNW-0.1 SW/DW R10 ENE-5.0 R GW1 W-1.2 GW/DW R11 E-0.5 R GW2 WSW-0.1 GW/DW l R12 E-1.9 R GW3 SSE-4.6 GW/DW l R13 E-3.5 R GW4 N-9.8 GW/DW l R14 E-4.2 R GW5 N-1.45 GW/DW R15 ESE-1.4 R SSI NNE-1.0 SS R16 ESE-4.7 R SS2 N-9.9 SS R17 SE- 1.3 R SS3 NE-7.4 SS R18 SE-3.85 R R19 SE-4.6 R M4 SW-14.5 M R20 SSE-1.3 R F1 ENE-2.0 F R21 SSE 4.4 R F2 NNE-8.0 F R22 SSE-4.5 R FP1 ENE-9.0 FP R23 S-1.5 R FP2 E-4.2 FP R24 S-4.2 R FP5 SW-12.7 FP R25 SSW-1.1 R FP6 E-3.5 FP R26 SSW-4.4 R BL1 N-1.45 BL R27 SW-0.9 R BL2 SW-1.0 BL BIS SW-13.5 BL 1
- TYPES: A - Air Sample GW - Groundwater F- Fish R- Direct Radiation SS - Shoreline Sediment FP - Food Product SW - Surface Water M- Milk BL - Broadleaf Vegetation DW - Drinking Water 30
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TABLE 4 (PAGE 1 OF 3)
T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STAllON CONCENTRAllONS OF GROSS BETA EMITIERS IN AIR PARI 1CUIEIES Results in Units of 10-3 pCI/m3 i 2 s.d.
STATION NW .I.O SW/WSW-0.95 S/SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9.4 JANUARY 01/03-01/10/95 3314 3314 3714 3214 3414 4214 3314 3914 01/10-01/17/95 2013 2113 2313 2113 2013 2513 2213 2413 01/17-01/24/95 2113 2113 2213 2213 2313 2613 22 3 2313 01/24-01/31/95 2513 2713 2513 2613 2613
- 2513 2813 FEBRUARY 01/31-02/07/95 2213 2413 2013 2113 2013 1713 2213 2213 02/07-02/13/95 1713 1713 1613 1413 1413 1513 1413 19i3 02/13-02/21/95 2013 2913 2513 2313 2413 2113 2713 2513 02/21-02/28/95 1713 2213 1913 1713 1513 18i3 1913 2213 g MARCH 02/28-03/07/95 1613 1513 1413 1413 1813 1513 1713 1413 03/07-03/14/95 1414 24i3 2413 2313 1813 20i3 2613 2213 03/14-03/21/95 1913 1913 2013 1813 1514 1713 22i3 2213 03/21-03/28/95 2613 2413 2213 2413 2413 2113 2513 25i3 03/28-04/04/95 2313 21i3 2013 20i3 1913 2013 2313 2213 APRIL 04/04-04/11/95 1713 1713 1613 1613 1513 1713 1913 1813 04/11-04/18/95 2213 1913 2213 1813 2013 20i3 1913 2413 04/18-04/25/95 1813 1213 1413 1313 14i3 15i3 1813 1913 04/25-05/02/95 2513 23i3 1813 1913 18i3 1713 1713 20i3
- Personnel failed to turn pump on.
TABLE 4 (PAGE 2 OF 3)
T U ELECTRIC COMANCIIE PEAK STEAM ELEC11UC STATION CONCENTRKI1ONS OF GROSS BETA EMITIERS IN AIR PARI 1CULKIES Results in Units of 10-3 pC1/m3 i 2 s.d.
5 ATION NW-1.0 SW/WSW4.95 S/SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9.4 1
MAY 05/02-05/09/95 14i3 1313 1213 1113 1313 1313 1413 16i3 05/09-05/16/95 2413 1913 1613 1613 1613 1613 1813 20t3 ;
05/16-05/23/95 1512 1713 1813 1913 1612 1813 1913 3114 05/23-05/30/95 20i3 1513 1713 1513 1213 1713 1713 1312 JUNE 05/30-06/06/95 2113 1613 1613 1613 1513 1413 1613 16i3 06/06-06/13/95 1813 1813 1813 1913 1813 1713 1913 1713 06/13-06/20/95 2513 2013 2213 2413 2313 22i3 2513 2513 w 06/20-06/27/95 28i3 2213 23t3 27i3 2313 2913 2813 2913 '
" 2113 2313 2013
- 2213 2413 06/27-07/04/95 1913 2013 JIILY >
07/04-07/11/95 2613 2113 2113 2113 22i3 2213 2413 2513 07/11-07/18/95 2613 2913 2713 2513 2413 2613 2713 2813 07/18;-07/25/95 20 3 1613 1913 1713 1813 1713 20i3 2213
- 07/25-08/01/95 1613 1413 1313 1213 11i3 1413 15i3 1613 AUGUST 08/01-08/C8/95 15t3 1213 1312 1313 1112 1413 1513 15i3 08/08-08/15/95 1913 1913 1913 1813 19i3 20i3 1913 2513 08/15-08/22/95 2013 1713 2113 17i3 1913 2113 2313 2514 i 08/22-08/29/95 3514 3214 3314 2714 3314 4214 4014 4314 "Ihe LLD was not met because of the low air volume - pump failed. !
i
TABLE 4 (PAGE 3 OF 3)
T U ELECTRIC COMANCHE PEAK STEAM EIECIRIC STATION CONCENIRATIONS OF GROSS BETA EMITIERS IN AIR PARI 1CUIATES Results in Units of 10-3 pC1/m3 1 2 s.d.
S AT NW-1.0 SW/WSW-0.95 S/SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9.4 SEI'IEMBER 08/29-09/05/95 3814 3314 3414 3514 3614 3714 3415 4514 09/05 09/12/95 3514 3414 3114 3314 3214 3714 3614 4114 09/12-09/19/95 2414 1714 1613 1813 1413 1813 1713 1813 09/19-09/26/95 2114 2014 1713 1813 1513 1613 1914 1813 09/26-10/03/95 2714 3114 3114 2714 3014 2914 3414 3314 OCIOBER 10/03-10/10/95 1613 1613 2213 2013 2013 2013 1813 23i3 10/10-10/17/95 2914 3014 3014 2714 3114 3014 3114 3114 w 10/17-10/24/95 1813 1513 1713 1613 1714 1613 1813 1613 00 10/24-10/31/95 1613 1713 2113 1613 2113 1913 2113 20i3 NOVEMBER 10/31-11/07/95 1913 1813 2014 1913 2114 2314 2314 2414 11/07-11/14/95 3114 2313 2614 2413 2514 27i4 3114 2914 11/14-11/21/95 3214 2814 2914 2814 3314 3014 3314 3414 11/21-11/28/95 33i4 2814 2814 3014 3314 3414 3214 3114 l DECEMBER 11/28-12/05/95 4014 3414 4114 4014 4314 3614 3914 42i4 12/05-12/12/95 3914 3514 3414 3514 3914 3514 3714 3214 12/12-12/19/95 3314 2814 2914 3014 3214 2514 3314 32i4 12/19-12/26/95 3214 3414 3114 3414 3815 2914 3114 3214 12/26-01/02/96 3914 3314 3514 3314 3614 37 4 3814 3514
TABLE 5 (PAGE 1 OF 2)
T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCEN'IRATIONS OF GAMMA EMTITERS* IN AIR PARTICULKIE F1LTERS Results in Units of E-03 pCf/m3 i 2 s.d.
Cs-134 Cs-137 K-40 Ru-103 COMPOSITE PERIOD Be-7 LOCAT10N FIRST QUARTER
<0.7 <0.4 <0.5 80.718.1 <10 NW-1.0 01/03/95-03/28/95 <0.8 <0.6 <0.6 87.118.7 <20 01/03/95-03/28/95 <0.6 <0.5 <0.5 SW/WSW-0.95 95.119.5 <9 01/03/95-03/28/95 <0.6 <0,5 <0.5 S/SSW-1.2 78.517.9 37.015.8 01/03/95-03/28/95 <0.6 <0,5 SW-12.3 <10 <0.8 95.219.5 <0.5 SSE-4.5 01/03/95-03/28/95 <9 <0.7 <0.6 93.919.4 <0.7 E-3.5 01/03/95-03/28/95 <10 <0.8 <0.7 01/03/95-03/28/95 110111 <0.6 <0.6 N-1.45 <20 <0.7 84.418.4 N-9.4 01/03/95-03/28/95 SECOND QUARIER <0.5
<0.6 <0.5 128113 16.715.1 03/28/95-06/27/95 <0.5 <0.4 <0.4 NW-1.0 <10 03/28/95-06/27/95 102110 <0.4 SW/WSW-0.95 <0.5 <0.5 125i13 10.513.6 03/28/95-06/27/95 <0.5 <0.4 <0.5 S/3SW-1.2 102i10 <7 SW-12.3 03/28/95-06/27/95 <0.4 <0.3 <0.4 109111 <6 SSE-4.5 03/28/95-06/27/95 <0.4 <0.3 <0.3 95.819.6 <7 03/28/95-06/27/95 <0.6 <0.6 <0.5 E-3.5 <10 03/28/95-06/27/95 108111 <0.6 <0.6 N-1.45 <20 <0.8 03/28/95-06/27/95 124112 N-9.4
- All other gamma emitters were <LLD.
TABLE 5 (PAGE 2 OF 2)
T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCE!URA~I1ONS OF GAMMA EMrrIERS* IN AIR PARTICULA'IE FIL'IERS Results in Units of E-03 pCi/m3 1 2 s.d.
LOCA'I1ON COMPOSTIE PERIOD Be-7 K-40 Ru-103 Cs-134 Cs-137 "IlllRD QUARIER NW- 1.0 06/27/95-10/03/95 67.916.8 <10 <0.4 <0.5 <0.4 SW/WSW-0.95 06/27/95-10/03/95 64.116.4 13.614.1 <0.6 <0.5- <0.5 S/SSW-1.2 06/27/95-10/03/95 79.417.9 <9 <0.5 <0.4 <0.3 SW-12.3 ,
06/27/95-10/03/95 88.718.9 9.3714.1 <0.6 <0.5 <0.4 SSE-4.5 06/27/95-10/03/95 6816.8 <10 <0.6 <0.5 <0.5 E-3.5 06/27/95-10/03/95 92.719.3 6.4513.6 <0.5 <0.4 <0.4 N- 1.45 06/27/95-10/03/95 80.418 <8 <0.4 <0.4 <0.5
$ N-9.4 06/27/95-10/03/95 81.918.2 <20 <0.7 <0.6 <0.7 FOURITI OUARIER NW- 1.0 10/03/95-12/26/95 99.9110 <10 <0.6 <0.6 <0.5 SW/WSW-0.95 10/03/95-12/26/95 73.617.4 9.4215.31 <0.5 <0.5 <0.5 S/SSW-1.2 10/03/95-12/26/95 95.019.5 <10 <0.7 <0.6 <0.6 SW-12.3 10/03/95-12/26/95 71.917.2 <20 <0.6 <0.6 <0.6 SSE-4.5 10/03/95-12/26/95 81.218.1 <10 <0.5 <0.5 <0.6 E-3.5 10/03/95-12/26/95 70.0i7.0 9.6614.4 <0.4 <0.4 <0.5 N- 1.45 10/03/95-12/26/95 84.118.4 <20 <0.8 <0.6 <0.7 N-9.4 10/03/95-12/26/95 72.917.3 <10 <0.6 <0.5 <0.5
- All other gamma emitters were <LLD.
TABLE 6 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN MILK Results in pC1/1i 2 s.d.
COLLECTION MONTH DATE SW- 14.5 JANUARY 01/11/95 <0.2 l
FEBRUARY 02/07/95 < 0. 4 MARCH 03/07/95 <0.2 l APRIL 04/04/95 <0.2 MAY 05/02/95 <0.2 05/16/95 <0.2 05/30/95 <0.2 JUNE 06/13/95 <0.3 06/27/95 <0. 4 JULY 07/11/95 <0.2 l 07/25/95 <0.1 AUGUST 08/08/95 <0.3 08/22/95 < 0. 4 SEFFEMBER 09/05/95 < 0. 2 09/19/95 < 0. 2 OCTOBER 10/03/95 < 0. 5 10/17/95 < 0. 2 10/31/95 < 0. 4 NOVEMBER 11/14/95 < 0. 4 11/28/95 <0.3 DECEMBER 12/12/95 < 0. 2 12/26/95 <0.2 l
41
TABLE 7
- (PAGE 1 OF 1)
T U ELECTRIC l
COMANCHE PEAK STEAM ELECIRIC STATION CONCENTRARONS OF GAMMA EMITIERS* IN MILK Results in Units of pCi/ liter i 2 s.d.
LOCA110N COLLECI1ON DA'IE K-40 Cs-134 Cs-137 La-140/Ba-140 STATION SW-14.5 JANUARY 01/11/95 14001140 <4 <4 <5 FEBRUARY 02/07/95 1330i130 <4 <4 <5 MARCH 03/07/95 14901150 <4 <4 <5 APRIL 04/04/95 14001140 <4 <4 <5 MAY 05/02/95 13101130 <6 <6 <8 05/16/95 13801140 <4 <4 <6 05/30/95 13101130 <5 <5 <6 JUNE 06/13/95 16701170 <5 <4 <6 g 06/27/95 1530i150 <4 <5 <6 JULY 07/11/95 1200i120 <4 <4 <6 07/25/95 14001140 <4 <4 <4 AUGUST 08/08/95 14701150 <3 <4 <4 08/22/95 12901130 <4 <4 <6 SEPIEMBER 09/05/95 14001140 <4 <4 <6 09/19/95 13501130 <5 <5 <4 OCTOBER 10/03/95 1430i140 <4 <4 <5 10/17/95 1390t140 <4 <4 <5 10/31/95 1390tl40 <4 <4 <4 NOVEMBER 11/14/95 13101130 <4 <4 <4 11/28/95 14201140 <4 <5 <4 DECEMBER 12/12/95 13001130 <3 <3 <4 12/26/95 13901140 <4 <4 <5 "All other gamma emitters were <LLD.
! TABLE 8 (PAGE 1 OF 2)
T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STA'110N '
CONCENTRA~I1ONS OF GAMMA EMITIERS* IN GROUNDWATER Results in Units of pC1/1i 2 s.d.
K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/La-140 STATION W-1.2 04/11/95 <70 <4 <4 <7 <4 <8 <4 <4 <4 <5 07/05/95 <90 <3 <3 <7 <3 <7 <3 <3 <4 <6 10/03/95 <60 <3 <3 <8 <4 <7 <4 <4 <4 <6 12/26/95 <50 <2 <3 <5 <3 <6 <3 <3 <3 <4 STA110N WSW-0.1 04/11/95" 07/05/95" 10/03/95" ,
12/26/95 <90 <3 <3 <7 <3 <7 <3 <3 <4 <4 b STAT 10N SSE-4.6 i
04/11/95 <100 <3 <3 <7 <4 <7 <4 <4 <4 <5 07/05/95 <50 <2 <3 <5 <3 <5 <3 <3 <4 <5 10/03/95 <100 <4 <4 <8 <4 <8 <4 <4 <4 <6 r 12/26/95 <60 <3 <3 <6 <3 <6 <3 <3 <3 <3 !
r STATION N-1.45 04/11/95 <50 <3 <3 <5 <3 <6 <3 <3 <4 <4 07/05/95 <40 <2 <2 <5 <2 <5 <2 <2 <3 <4 10/03/95 <50 <3 <3 <6 <3 <6 <3 <3 <4 <5 12/26/95 <40 <2 <2 <4 <2 <5 <3 <2 <2 <3
" Pump out of sesvice.
All other gamma emittem were LLD. ;
TABLE 8 (PAGE 2 OF 2)
- T U ELECIRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRA110NS OF GAMMA EMITIERS* IN GROUNDWKIER Results in Units of pCl/li 2 s.d.
K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/Im-140 STATION N-9.8 04/11/95 <50 <3 <2 <6 <3 <6 <3 <3 <4 <4 07/05/95 <80 <3 <3 <6 <3 <7 <3 <3 <3 <5 10/03/95 <50 <3 <3 <6 <3 <6 <3 <3 <4 <4 12/26/95 <80 <3 <2 <6 <3 <6 <3 <3 <3 <3 i
All other gamma emitters wear LLD.
t
TABLE 9 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER Results in pC1/1 i 2 s.d.
COLLECTION TRITIUM OUARTER DATE LOCATION ACTIVITY 1 04/11/95 W-1.2 <2000 04/11/95 WSW-0.1
- 04/11/95 SSE-4.6 <2000 04/11/95 N- 1.45 <2000 04/11/95 N-9.8 <2000 2 07/05/95 W-1.2 <1000 07/05/95 WSW-0.1
- 07/05/95 SSE-4.6 <1000 07/05/95 N- 1.45 <1000 07/05/95 N-9.8 <1000 3 10/03/95 W-1.2 <1000 10/03/95 WSW-0.1 10/03/95 SSE-4.6 <1000 10/03/95 N-1.45 <1000 10/03/95 N-9.8 <1000 4 12/26/95 W-1.2 <1000 12/26/95 WSW-0.1 <1000 12/26/95 SSE-4.6 <1000 12/26/95 N- 1.45 <1000 12/26/95 N-9.8 <1000
- Pump out of service.
45
i l
, TABLE 10 T U ELECTRIC
- COMANCHE PEAK STEAM ELECTRIC STATION I
GROSS BETA CONCENTRATIONS IN WATER-SURFACE / DRINKING Results in pCi/l i 2 s.d. 1 COLLECTION MONTH DATE NNW-0.1 N-9.9 JANUARY 01/17/95-02/07/95 21i4 12i3 FEBRUARY 02/14/95-03/07/95 18i4 11i3 MARCH 03/14/95-04/04/95 13i3 8.7i2.6 APRIL 04/11/95-05/02/95 22i4 9.3i3.0 MAY 05/09/95-05/16/95 20i4 14i3 05/09/95-05/30/95 22i4 8.2i2.3 JUNE 06/06/95-06/13/95 18i4 6.6 i 2.3 I 06/06/95-06/27/95 14i3 9.6 i 2.4 JULY 07/04/95-07/25/95 19i3 13i3 AUGUST 08/01/95-08/22/95 18i4 9.6i2.7 SEIYTEMBER 08/29/95-09/19/95 16i3 6.0i2.3 OCTOBER 09/26/95-10/17/95 21i4 8.8i2.5 NOVEMBER 10/24/95-11/14/95 20i3 11i2 DECEMBER 11/21/95-12/12/95 19i3 14i3 12/19/95-12/26/95 23i4 8.7i2.7 46
= . _ . . . _ . . .. -
TABLE 11 (PAGE 1 OF 1)
T U ELECTRIC COMANCHE PEAK S'IEAM ELECTRIC STATION CONCENTRA~I1ONS OF GAMMA EMTI'IERS* IN WATER SURFACE / DRINKING Results in Units of pCl/l i 2 s.d.
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/Im-140 COM FCT10N DA'IE STA'I1ON NNW-0.1 01/17/95-02/07/95 <4 <4 <8 <3 <8 <4 <4 <4 <5 02/14/95-03/07/95 <2 <2 <5 <2 <5 <2 <2 <2 <7 03/14/95-04/04/95 <3 <3 <6 <3 <6 <3 <3 <4 <4 04/11/95-05/02/95 <3 <3 <7 <3 <6 <3 <4 <3 <6 05/09/95-05/16/95 <3 <3 <7 <3 <6 <3 <4 <4 <5 05/09/95-05/30/95 <3 <3 <6 <3 <6 <3 <3 <3 <5 06/06/95-06/13/95 <4 <4 <7 <4 <8 <4 <4 <4 <6
'E/06/95-06/27/95 <3 <3 <6 <3 <6 <3 <3 <4 <5 3 07/04/95-07/25/95 <3 <3 <6 <3 <6 <3 <3 <4 <4 N 08/01/95-08/22/95 <2 <2 <5 <2 <5 <2 <2 <3 <3 08/29/95-09/19/95 <3 <3 <6 <4 <7 <4 <4 <3 <6 09/26/95-10/17/95 <4 <3 <7 <4 <8 <4 <4 <4 <5 10/24/95-11/14-95 <4 <4 <7 <4 <8 <4 <4 <4 <6 11/21/95-12/12/95 <3 <3 <7 <3 <8 <4 <4 <3 <6 12/19/95-12/26/95 <3 <3 <6 <3 <6 <3 <3 <3 <4 S' RATION N-9.9 01/17/95-02/07/95 <4 <4 <9 <4 <10 <5 <5 <5 <5 02/14/95-03/07/95 <2 <2 <4 <2 <4 <2 <2 <2 <5 03/14/95-04/04/95 <5 <5 <10 <5 <10 <5 <5 <5 <6 04/11/95-05/02/95 <3 <3 <8 <3 <7 <4 <4 <4 <6 05/09/95-05/16/95 <4 <4 <8 <4 <9 <4 <4 <5 <6 05/09/95-05/30/95 <4 <4 <8 <4 <8 <4 <4 <5 <6 06/06/95-06/13/95 <3 <3 <6 <3 <6 <3 <3 <4 <5 06/06/95-06/27/95 <3 <3 <6 <3 <6 <3 <3 <4 <4 07/04/95-07/25/95 <3 <3 <5 <3 <6 <3 <3 <4 <3 08/01/95-08/22/95 <3 <3 <7 <3 <6 <3 <3 <3 <4 08/29/95-09/19/95 <3 <3 <7 <4 <7 <4 <4 <4 <5 09/26/95-10/17/95 <4 <4 <e <4 <8 <4 <4 <4 <7 10/24/95-11/14-95 43 <3 <6 <3 <6 <3 <3 <3 <4 1
.11/21/95-12/12/95 <3 <3 <7 <3 <7 <3 <3 <3 <5 12/19/95-12/26/95 <3 <3 <6 <3 <6 <3 <3 <3 <4 All other gamma emitters were LLD.
TABLE 12 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN WATER-SURFACE / DRINKING Results in pC1/1 2 s.d.
COLLECTION MOBTrH DATE NNW-0.1 N-9.9 JANUARY 01/17/95-02/07/95 <0.4 <0.5 01/17/95-01/24/95 <0.2 <0.2 FEBRUARY 02/14/95-02/21/95 < 0. 3 <0.3 MARCH 02/14/95-03/07/95 < 0.3 <0.3 02/28/95-03/07/95 < 0.3 <0.3 03/14/95-03/21/95 < 0.2 <0.2 03/14/95-04/04/95 <0.4 <0.3 APRIL 04/11/95-04/18/95 < 0.3 <0.3 04/11/95-05/02/95 <0. 5 <0.4 MAY 05/09/95-05/16/95 <0.2 <0.2 05/09/95-05/30/95 < 0. 3 <0.3 JUNE 06/06/95-06/13/95 < 0. 3 <0.3 06/06/95-06/27/95 < 0. 7 <0.7 JULY 07/04/95-07/11/95 <0.2 <0.2 07/04/95-07/25/95 <0.3 <0.3 AUGUST 08/01/95-08/08/95 < 0. 4 <0.4 08/01/95-08/22/95 <0.4 <0.4 SENEMBER 08/29/95-09/05/95 <0.2 <0.3 08/29/95-09/19/95 < 0. 3 <0.3 OCTOBER 09/26/95-10/03/95 <0.5 <0.5 09/26/95-10/17/95 <0. 5 <0.5 10/24/95-10/31/95 < 0. 4 <0.4 NOVEMBER 10/24/95-11/14/95 < 0. 4 <0.5 11/21/95-11/28/95 < 0.3 <0.3 DECEMBER 11/21/95-12/12/95 < 0. 4 <0.4 12/19/95-12/26/95 < 0. 3 <0.3 48
TABLE 13 T U ELECTRIC i COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN WATER-SURFACE / DRINKING Results in pCi/li 2 s.d.
COLLECTION QUARTER PERIOD NNW-0.1 N-9.9 1 12/20/94-03/07/95 8600il700 <2000 2 03/14/95-06/27/95 8000i2000 <1000 3 07/04/95-09/19/95 7900i2300 <2000 4 09/26/95-12/26/95 7000i600 <600 l
49
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 OUARTER PERIOD NNW-0.1 N-9.9 1 12/20/94-03/07/95 8600il700 <2000 2 03/14/95-06/27/95 8000i2000 <1000 3 07/04/95-09/19/95 7900i2300 <2000 4 09/26/95-12/26/95 7000i600 <600 49 i
TABLE 14 (PAGE 1 OF 2)
T U EIECIRIC COMANCHE PEAK S'IEAM ELECIF;C STATION CONCENIRA"I1ONS OF GAMMA EMITIER3' IN SURFACE WA~IER Results in Units of pct /li 2 s.d.
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/Im-140 STA"I1ON ESE-1.4 01/17/95-02/07/95 <3 <3 <7 <4 <7 <3 <3 <4 <6 02/13/95-03/07/95 <4 <4 <7 <4 <8 <4 <4 <4 <4 03/14/95-04/04/95 <3 <3 <6 <3 <7 <3 <3 <3 <5 04/11/95-05/02/95 <4 <4 <8 <4 <7 <4 <4 <4 <5 05/09/95-05/30/95 <3 <4 <6 <4 <7 <3 <3 <4 <5 06/06/95-06/27/95 <3 <3 <8 <4 <6 <4 <3 <4 <6 07/04/95-07/25/95 <3 <3 <6 <3 <6 <3 <3 <3 <4 08/01/95-08/22/95 <3 <3 <S <4 <6 <3 <4 <4 <5
<3 <7 08/29/95-09/19/95 <3 <4 <7 <> <3 <4 <4 g 09/26/95-10/17/95 <4 <4 <10 <4 <9 <5 <4 <5 <6 10/24/95-11/14/95 <3 <3 <7 <3 <7 <3 <3 <3 <4 11/21/95-12/12/95 <2 <3 <6 <3 <5 <3 <3 <3 <3 12/19/95-12/26/95 <3 <3 <7 <3 <7 <3 <3 <4 <4 STAI1ON N-1.5 01/17/95-02/07/95 <4 <4 <8 <4 <8 <4 <4 <4 <6 02/13/95-03/07/95 <3 <3 <6 <3 <7 <3 <3 <4 <4 03/14/95-04/04/95 <3 <3 <7 <4 <7 <3 <4 <4 <5 04/11/95-05/02/95 <4 <4 <8 <4 <7 <4 <4 <4 <6 05/09/95-05/30/95 <3 <3 <6 <4 <8 <4 <4 <4 <6 06/06/95-06/27/95 <4 <4 <7 <3 <8 <4 <4 <4 <5 07/04/95-07/25/95 <3 <3 <7 <3 <7 <3 <3 <4 <5 08/01/95-08/22/95 <4 <3 <7 <4 <7 <4 <4 <4 <6 08/29/95-09/19/95 <3 <3 <7 <4 <8 <4 <4 <4 <4 09/26/95-10/17/95 <3 <3 <8 <4 <6 <4 <3 <5 <6 10/24/95-11/14/95 <2 <2 <5 <2 <5 <3 <2 <4 <4 11/21/95-12/12/95 <3 <3 <6 <3 <5 <3 <3 <3 <5 12/19/95-12/26/95 <2 <2 <5 <3 <5 <3 <2 <4 <3 "All other gamma emitters were <LLD
TABLE 14 (PAGE 2 OF 2)
T U ELECUllC COMANCilE PEAK STEAM ELECIRIC STA110N CONCENIRAT10NS OF GAMMA EMITIERS* IN SURFACE WA'IER Results in Units of pCl/li 2 s.d.
Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/Im-140 STADON NE-7.4 02/07/95 <4 <3 <7 <3 <8 <3 <4 <4 <6 03/07/95 <3 <3 <6 <3 <7 <3 <3 <3 <4 04/04/95 <3 <3 <7 <3 <7 <3 <3 <4 <5 05/02/95 <3 <4 <7 <4 <8 <4 <4 <4 <6 05/30/95 <4 <4 <8 <4 <8 <4 <4 <4 <6 06/27/95 <3 <3 <7 <3 <6 <3 <4 <3 <6 07/25/95 <2 <2 <5 <3 <5 <3 <3 <4 <4 08/22/95 <4 <4 <8 <4 <8 <4 <4 <4 <6 09/19/95 <3 <3 <7 <4 <6 <3 <3 <3 <4 10/17/95 <3 <3 <6 <3 <7 <3 <3 <4 <5 11/14/95 <2 <2 <5 <2 <5 <2 <2 <3 <3 12/12/95 <2 <2 <4 <3 <5 <2 <2 <3 <4 O 12/26/95 <2 <2 <4 <2 <5 <2 <2 <3 <3 STATION N-19.3 02/07/95 <3 <3 <6 <3 <6 <3 <3 <4 <5 03/07/95 <3 <3 <6 <3 <7 <3 <3 <4 <3 04/04/95 <4 <4 <8 <5 <8 <4 <5 <5 <6 05/02/95 <3 <3 <6 <3 <6 <3 <3 <4 <5 05/30/95 <3 <3 <6 <3 <6 <3 <3 <4 <5 06/27/95 <4 <4 <8 <4 <8 <4 <4 <4 <6 07/25/95 <2 <2 <5 <2 <5 <2 <3 <3 <4 08/22/95 <3 <3 <6 <3 <7 <3 <3 <4 <5 09/19/95 <3 <3 <6 <3 <7 <3 <3 <4 <4 10/17/95 <5 <5 <10 <5 <10 <5 <6 <6 <8 11/14/95 <3 <3 <6 <3 <6 <3 <3 <3 <4 12/12/95 <2 <2 <4 <2 <5 <2 <2 <3 <3 12/26/95 <3 <3 <6 <3 <6 43 <3 <3 <4
- All other gamma emitters were <LLD
I TABE 15 T U ELECTRIC COMANCHE PEAK SIEAM ELECTRIC STA110N CONCEN1RA110NS OF TRrI1UM IN SURFACE WATER Results in pCi/l i 2 s.d.
QUARIER COLLECTION PERIOD ESE-1.4 N-1.5 NE-7.4 N-19.3 1 12/20/94-03/07/95 850011700 980011700 <2000 <2000 2 03/14/95-06/27/95 930011200 990011200 2 04/04/95-06/27/95 <1000 <1000 3 07/04/95-09/19/95 710012300 800012300 3 07/25/95-09/19/95 <2000 <2000 4 09/26/95-12/26/95 68001600 70001600 g 4 10/17/95-12/26/95 <600 <600 4
- _ _ _ - ~ _ _ - . - _ - - - - _ _ - - - _ _ - - - - _ _ - _ _ - . - - ,
TABLE 16 T U EECTRIC COMANCHE PEAK SIEAM ELECTRIC STATION CONCEN'IRATIONS OF GAMMA EMrrIERS* IN FISH Results in pC1/Kg (wet) i 2 s.d.
COLLEC110N DKIE STA*I1ON DESCRIPI1ON K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 04/21/95 ENE-2.0 Channel Cat 30801310 <10 <20 <40 <20 <30 <10 <10 04/21/95 ENE-2.0 Lgnth Bass 31601320 <20 <20 <50 <20 <50 <20 <20 10/19/95 ENE-2.0 Channel Cat 22101220 <10 <10 <30 <20 <30 <10 <20 10/19/95 ENE-2.0 Yellow Catfish 29201290 <10 <10 <30 <10 <30 <10 <10 04/28/95 NNE-8.0 Catfish 27401270 <10 <10 <30 <10 <30 <10 <20 04/28/95 NNE-8.0 Crapple 3120i370 <30 <40 <90 <30 <70 <40 <40 10/19/95 NNE-8.0 Yellow Catfish 33801340 <10 <10 <30 <10 <30 <10 <10 10/19/95 NNE-8.0 Crapple/ Stripper 41101410 <20 <20 <40 <20 <40 <20 <20
- All other gamma emitters were LLD.
TABIE 17 T U ELEC'IRIC COMANCHE PEAK SIEAM ELECTRIC STADON CONCENIRABONS OF GAMMA EMITIERS* IN SEDIMENT Results in pC1/kg (dry) i 2 s.d.
COLLECBON DATE STATION Be-7 K-40 Cs-134 Cs- 137 Pb-212 Bi-214 Ib214 Ra-226 'Ih-228 STKI1ON N-1.0 01/10/95 SSI <200 12601200 <20 <30 207125 221141 227140 8751301 203125 07/11/95 SSI <200 45701460 <30 <20 296134 402148 449153 12101420 288133 STA110N NE-7.4 01/10/95 SS3 <200 19301200 <20 <20 105118 147130 178132 <300 103118
- 07/11/95 SS3 3711153 27001270 <20 <20 188121 284i37 318137 6101276 183121 STAT 10N N-9.9 01/10/95 SS2 <300 88701890 <30 <30 461146 545161 517157 123144 451145 07/11/95 SS2 <300 77301770 <30 <30 387139 525157 587159 10501390 376138 STA'110N SE-5.3 07/11/95 SS4 7111223 21401310 <30 <30 248133 483155 526158 11401420 241132
- All other gamma emitters were LLD.
TABLE 18 [
(PAGE 1 OF 1) i T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STA~I1ON CONCENTRAT10NS OF GAMMA EMTITERS* IN FOOD PRODUCTS Results in Units of pCl/kg (wet) i 2 s.d. l COLLECI1ON STATION DESCRIlmON DA'IE Be-7 K-40 I-131 Cs-134 Cs-137 SW- 12.7 Turnip 01/10/95 7261115 35101350 <20 <10 <10 i Turnip 02/07/95 <60 2440t240 <10 <7 <7 >
03/07/95*"
04/04/95*" ;
05/02/95*" I Pinto Bean 05/30/95 121i55 25701260 <10 <8 <9 Squash 06/27/95 <60 22701230 <10 <8 <8 Peaches 07/25/95 82135 26701270 <9 <6 <6 Okra 08/22/95 <80 37601380 <10 <9 <10 :
09/19/95*" +
Turnips 10/17/95 191168 31601320 <20 <10 <10 Turnips 11/14/95 405159 19601200 <10 <8 <9 Turnip 12/12/95 <40 1710il70 <7 <6 <6 Turnip 12/26/95 <50 19601200 <10 <5 <6 E-3.5 01/10/95*"
02/07/95"*
03/07/95*"
04/04/95*"
05/02/95*"
Onions 05/30/95 <50 708171 <10 <6 <6 -
Green Beans 06/27/95 <80 22101220 <30 <8 <8 Okra 07/25/95 <60 22201220 <10 <7 <7 Tomatoes 08/22/95 <40 24401240 <7 <4 <4 ,
Squash 09/19/95 <60 36401360 <8 <8 <8 1O/17/95***
12/12/95***
12/26/95*" 5 ENE-9.0 Pecans 11/14/95 <70 2830i280 <10 <9 <9 All other gamma emitters were <LLD.
- " Sample not available.
TABLE 19 (PAGE 1 OF 2)
T U ELECIRIC COMANCHE PEAK S'IEAM ELECIRIC STADON CONCENTRA710NS OF GAMMA EMfrIERS* IN BROADLEAF VEGETA~I1ON Results in Units of pC1/kg (wet) i 2 s.d.
COLLECHON STATION DESCRIPI1ON DA~IE Be-7 K-40 1-131
- Cs-134 Cs-137 N- 1.45 **
01/10/95 (BL1) 02/07/95 03/07/95 04/04/95 Sumac 05/02/95 8441110 50301500 <5 <20 <20 Sumac 05/30/95 28001280 50701510 <9 <20 <20 Sumac 06/27/95 20901210 52801530 <10 <20 <20 Sumac 07/25/95 22301220 52601530 <7 <20 <20 Sumac 08/22/95 17501170 50201500 <20 <10 <10 Sumac 09/19/95 11501160 49701500 <10 <20 <20 Sumac 10/17/95 12101120 53301530 <8 <10 <10 m Sumac 10/24/95 20001200 36301360 <5 <20 <30 m Native Grasses 11/14/95 31501460 41801530 <5 <60 <60 Grass 12/12/95 48401480 24101370 <6 <40 <40 Grass 12/26/95 41401410 30201430 <20 <40 <40 SW- 13.5 01/10/95 (BL3) 02/07/95 03/07/95 Bloodweed 04/04/95 1420i140 48701490 <6 <10 <10 Bloodweed 05/02/95 9501111 46901470 <5 <20 <20 Broadleaf 05/30/95 36201360 61901620 <7 <20 <20 Bloodweed 06/27/95 15501150 87001870 <6 <20 <20 Bloodweed 07/25/95 44801450 1040011000 <6 <20 <20 Bloodweed 08/22/95 14001140 84101840 <10 <20 <20 Johnson Grass 09/19/95 938tl49 38301380 <10 <20 <20 Johnson Grass 10/17/95 11201200 48301480 <7 <30 <30 Johnson Grass 11/14/95 46301470 53701630 <4 <50 <50 Grass 12/12/95 14701250 53401530 <5 <30 <30 Grass 12/26/95 29901400 88801890 <7 <50 <50 All other gamma emitters are LLD Sample not collected - sample not available.
- " By Radiochemical Analysis
TABLE 19 (PAGE 2 OF 2)
T U ELECTRIC COMANCHE PEAK S1EAM ELECTRIC STA110N CONCEN1 RAT 10NS OF GAMMA EMrI*IERS* IN BROADLEAF VEGETKI10N Results in Units of pCl/kg (wet) i 2 s.d.
COLLECHON STA110N DESCRIPIlON DATE Be-7 K-40 I-131*" Cs-134 Cs-137 SW-1.0 01/10/95" >
(BL2) 02/07/95 "
03/07/95" ,
04/04/95 "
Sumac 05/02/95 706181 72201720 <5 <10 <10 Sumac 05/30/95 28201280 38101380 <10 <20 <20 Sumac 06/27/95 31201310 57001570 <40 <30 <20 Sunmc 07/25/95 33201330 36601370 <5 <20 <20 Sumac 08/22/95 14701150 35401350 <10 <10 <10 Sumac 09/19/95 10101140 28901290 <10 <20 <20 Sumac / grasses 10/17/95 1270tl40 50801510 <9 <20 <20 Johnson Grass 11/14/95 28701290 21601270 <4 <20 <30 Grass 12/12/95 32401370 22301400 <6 <50 <40
$ Grass 12/26/95 29201320 21101340 <20 <40 <40 All other gamma emitters are LLD Sample not collected - sample not available.
"* By Radiochemical Analysis
TABLE 20 (PAGE 1 OF 6)
RADIOLOGICAL ENVIRONMENTAL MONTIORING PROGRAM
SUMMARY
T U ELECTRIC - COMANCHE PEAK STEAM ELECTRIC STATION JANUARY l TO DECEMBER 31.1995 Analysis and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations location with Highest Mean Contml Imcations Nonroutine Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (f)(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements TLDs (Quarterly) Gamma (170) 0.11(162/162) ENE-5 0.15(4/4) 0.12(8/8) 0 (mR/ day) (0.07-0.16) (0.15-0.16) (0.10-0.13)
TLDs (Annual) Gamma (42) 0.12(40/40) E-3.5 0.16(1/1) 0.14(2/2) 0 (mR/ day) (0.07-0.16) --
(0.13-0.14)
Air Iodine-131 I-131(414) 70 -(0/362) NA NA -(0/52) 0 (10 3 pcl/m3) -- --
Air Particulate Gross (414) 10 23(362/362) N-9.4 25(52/52) 22(52/52) 0 g (10 3 pct /m3) Beta (11-43) (13-45) (11-40)
Gamma (32)
Be-7 -
91(28/28) S/SSW-1.2 99(4/4) 85(4/4) 0 (64-128) (79-125) (72-102)
K-40 -
11(6/28) SW-12.3 23(2/4) 23(2/4) 0 (6.5- 17) (9.4-37) (9.4-37)
Ru-103 -
-(0/28) N/A N/A -(0/4) O Cs-134 -
-(0/28) N/A N/A -(0/4) O Cs-137 -
-(0/28) N/A N/A -(0/4) 0 (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program.. Revision 1. November 1979.
(2) (f) is the ratio of positive results to the number of samples analyzed for the parameter of interest.
raeans are of positive results only.
TABLE 20 (PAGE 2 OF 6)
RADIOLOGICAL ENVIRONMEITTAL MONfIORING PROGRAM
SUMMARY
T U ELEC1RIC - COMANCHE PEAK STEAM ELECTRIC STA'llON JANUARY I 'ID DECEMBER 31,1995 Analysis and lower Limit Number of Medium of Pathway Total Number of All Indicator Imcations imcation with Hishest Mean Control Incation Nonmutine Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (f)(2) Reported (Unit of Measurement) Performed (LLD) (!! Range D stance and Direction Range Range Measumments Milk I-131 (22) -
N/A N/A N/A -(0/22) 0 (pCl/l) (IW RADIOCllEMISTRY) --
Gamma (22)
K-40 -
N/A N/A N/A 1389(22/22) 0 (1200-1670)
Cs-137 -
N/A N/A N/A -(0/22) 0 (n
- Surface Water Gamma (52)
(pCl/l)
K-40 N/A N- 19.3 66(1/13) 66(1/13) 0 Tritium (16) -
8300(8/12) N-1.5 8675(4/4) -(0/4) 0 (6800-9900) (7000-9900) --
Ground Drinking Gamma (17) -
Water (pCi/l)
K-40 -
-(0/13) N/A N/A -(0/4) 0 Tritium (17) -
-(0/13) N/A N/A -(0/4) O (1) ILD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program.. Revision 1. November 1979.
(2) (1) is the ratio of positive results to the number of samples analyzed for the parameter of interest.
means are of positive results only.
TABLE 20 i (PAGE 3 OF 6)
RADIOIDGICAL ENVIRONMENTAL MONTIURING PROGRAM
SUMMARY
j T U ELECTRIC - COMANCHE PEAK STEAM ELEclRIC STA110N JANUARY 1 TO DECEMBER 31,1995 Analysis and Iower Limit Number of Medium of Pathway Total Number of All Indicator locations Letion with Ihhest Mean Contml location Nonroutine Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (f)(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements Water-Surface Gamma (30)
Drinking (pCl/l)
K-40 - -(0/15) N/A N/A -(0/15) O Tritium (8) -
7875(4/4) NNW-0.1 7875(4/4) -(0/4) 0 (7000-8600) (7000-8600) --
Gross Beta (30) -
19(15/15) NNW-0.1 19(15/15) 10(15/15) 0
, (13-23) (13-23) (6.0-14) ca 1-131 (52) -
-(0/26) N/A' N/A -(0/26) 0 (BY RADIOCllEMISTRYI -- --
Fish Gamma (8)
(pCl/kg/ dry)
K-40 -
2843(4/4) NNE-8.0 3338(4/4) 3338(4/4) 0 (2210-3160) (2740-4110) (2740-4110)
(1) LID is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Envirnnmental Monitoring Program . Revision 1. November 1979.
(2) (f) is the ratio of positive results to the number of samples analyzed for the parameter of interest, means are of positive results only.
TABLE 20 (PAGE 4 OF 6)
RADIOLOGICAL ENVIRONMENTAL MONTIORING PROGRAM
SUMMARY
T U ELECTRIC - COMANCHE PEAK STEAM ELECTRIC STA'I1ON JANUARY I 70 DECEMBER 31,1995 Analysis and lower Limit Number of Medium of Pathway Total Number of All Indicator locations location with Hwhest Mean Control location Nonroutine Sampled ofAnalysis Detection Mean Name Mean (0(2) Mean (0(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements Shoreline Gamma (7)
Sediments (pC1/kg dry) Be-7 -
541(2/5) SE-5.3 711(1/1) -(0/2) 0 (371-711) -- --
K-40 -
2520(5/5) N-9.9 8300(2/2) 8300(2/2) 0 (1260-4570) (7730-8870) (7730-8870)
Ra-226 -
959(t/5) SE-5.3 1140(1/1) 587(2/2) 0 (610-1210) --
(123-1050)
Th-228 -
204(5/5) N-9.9 414(2/2) 414(2/2) 0 (103-288) (376-451) (376-451) cn Pb-212 -
209(5/5) N-9.9 424(2/2) 424(2/2) 0 (105-296) (387-461) (387-461)
Bi-214 -
307(5/5) N-9.9 535(2/2) 535(2/2) 0 (147-483) (525-545) (525-545)
Pb-214 -
340(5/5) N-9.9 552(2/2) 552(2/2) 0 (178-526) (517-587) (517-587) i i i i
i (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program. Revision 1. November 1979.
(2) (0 is the ratio of positive results to the number of samples analyzed for the parameter of interest. ,
means are of positive results only.
TABLE 20 (PAGE 5 OF 6)
RADIOIDGICAL ENVIRONMEffrAL MONITORING PROGRAM
SUMMARY
I T U ELECTRIC - COMANCHE PEAK STEAM ELECTRIC STA~I1ON i JANUARY l "IO DECEMBER 31.1995 t Analysis and lower Limit Number of Medium of Pathway Total Number of All Indicator Imcations Imcation with Highest Mean fdul*rol Imcatkm Nonroutine Sampled ofAnalysis Detection Mean Name Mean (0(2) Mean (0(2) Reported (Unit of Measurement) Performed (LID) (1) Range Distance and Direction Range Range Measurements Broadleaf Gamma (32)
Vegetation (pCl/kg wet) Be-7 -
2331(21/21) N- 1.45 2382(11/1I) 2233(11/11) 0 (706-4840) (844-4840) (938-4630)
K-40 -
4171(21/21) SW-13.5 6501(11/11) 6501(11/11) 0 (2110-7220) (3830-10400) (3830-10400) 1-131 -
-(0/21) NA NA -(0/11) 0 O Cs-134 -
-(0/21) NA NA -(0/11) 0 Cs-137 -
-(0/21) NA NA -(0/11) 0 TH-228 -
-(0/21) SW-13.5 78(1/11) 78(1/11) 0 (1) ILD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program . Revision 1. November 1979.
(2) (f) is the ratto of positive results to the number of samples analyzed for the parameter of interest.
means are of positive results only.
- wu_ - - - - - - - - - - - - - . - - - - _ _ - - - - - - - - - - _ _ _ _ - _ _ _ _ - - - , - - - _ - _ _ _ _ - _ _ - - - _ - - - - - - _ ------ - - - _--_- _ _.----_-- _ - - - - - - _ _ . _ -- - _ _ - - -
TABLE 20 (PAGE 6 CF 6)
RADIOLOGICAL ENVIRONMENTAL MONTIURING PROGRAM
SUMMARY
T U ELEC17UC - COMANCIIE PEAK STEAM ELECTRIC STATION JANUARY l TU DECEMBER 31.1995 Analysis and Lower Limit Number of Medium of Pathway Total Number of All Indicator Imcations location with Hiahest Mean Control Location Nonroutine Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (f)(2) Reported (Unit of Measumment) Performed (LLD) (1) Range Distance and Direction Range Range Measurements Food Products Gamma (16)
(pCl/kg wet)
Be-7 -
-(0/6) SW-12.7 305(5/10) 305(5/10) 0 (82-726) (82-726)
K-4 0 -
2341(6/6) ENE-9.0 2830(l/1) 2601(10/10) o (708-3640) --
(1710-3760)
I-131 -
-(0/16) NA NA -(0/0) 0 Cs-134 -
-(0/16) NA NA -(0/0) 0 g .. .. ..
Cs-137 -
-(0/16) NA NA -(0/0) O (1) 11D is lower limit of detection as defined anc'. .equired in USNRC Branch Technical Position on an Acceptable Radiological Environmental Manitoring Program.. Revision 1. November 1979.
(2) (f) is the ratio of positive results to the numter of samples analyzed for the parameter of interest.
means are of positive results only.
A as e- .- m a l
l l
l l
l APPENDIX A ;
EPA CROSS-CHECK PROGRAM A-1
EPA INTERLABORATORY COMPARISON PROGRAM 1995 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Result (b) Deviation (c) 01/13/95 Water Sr-89 20.0 1 5.0 19.00 1 2.65 -0.35 Sr-90 15.0 i 5.0 14.00 1 0.00 -0.35 01/27/95 Water Gr-Alpha 50i 5.0 5.00 i 1.00 0.00 Gr-Beta 501 5.0 6.00 i 1.00 0.35 02/03/95 Water I131 100.0 i 10.0 88.33 i 2.31 -2.02 (d) 1 02/10/95 Water Ra-226 19.1 1 2.9 20.67 i 0.58 0.94 '
Ra 228 20.0 1 5.0 18.67 i 0.58 -0.46 03/10/95 Water H-3 7435.0 1 744.0 7066.67 i 115.47 -0.86 04/18/95 Water Gr-Beta 86.6 1 10.0 80.33 i 2.52 -1.09 Sr-89 20.0 i 5.0 20.67 1 1.15 0.23 Sr-90 15.0 d 5.0 14.67 i 0.58 -0.12 Co-60 29.0 i 5.0 31.67 1 2.08 0.92 Cs-134 20.0 1 5.0 19.67 i 1.73 -0.12 Cs-137 11.0 1 5.0 11.67 1 1.53 0.23 Gr-Alpha 47.5 11.9 39.67 i 2.52 -1.14 Ra-226 14.9 1 2.2 15.67 1 0.58 0.60 Ra-228 15.8 1 4.0 13.00 1 1.73 -1.21 06/09/95 Water Co-60 40.0 5.0 42.33 1 2.52 0.81 Zn-65 76.0 1 8.0 82.33 3.51 1.37 Cs-134 50.0 1 5.0 46.67 i 2.08 -1.15 Cs-137 35.0 1 5.0 37.67 i 1.15 0.92 Ba-133 79.0 1 8.0 74.33 1 2.08 -1.01 06/16/95 Water Ra-226 14.8 2.2 15.00 t 0.00 0.16 Ra-228 15.0 1 3.8 14.00 i 0.00 -0.46 07/14/95 Water Sr-89 20.0 1 5.0 18.33 1 1.53 -0.58 Sr-90 8.0 1 5.0 8.0 i 0.00 0.00 07/21/95 Water Gr-Alpha 27.5 1 6.9 18.33 i 1.53 -2.30 (e)
Gr-Beta 19.4 5.0 19.33 i 1.53 -0.02 08/04/95 Water H-3 4872.0 i 487.0 4866.67 i 152.75 -0.02 08/25/95 Air Filters Gr-Alpha 25.0 i 6.3 23.67 1 1.53 -0.37 Gr-Beta 86.6 10.0 84.67 i 1.53 -0.33 Sr-90 30.0 1 5.0 25.33 1 0.58 -1,62 Cs-137 25.0 1 5.0 27.00 1 1.00 0.69 09/15/95 Water Ra-226 24.8 1 3.7 27.33 1 1.15 1.19 Ra-228 20.0 5.0 14.67 i 0.58 -1.85 Note: Footnotes are located at end of table.
A-2
~
EPA INTERLABORATORY COMPARISON PROGRAM 1995 Environmental Collection Teledyne Bmwn Date Media Nuclide EPA Result (a) Engineering Resultib) Deviation (c) 09/29/95 Milk Sr-89 20.0 1 5.0 23.33 i 3.06 1.15 Sr-90 15.0 1 5.0 16.33 1 0.58 0.46 I-131 99.0 1 10.0 103.33 1 5.77 0.75 Cs-137 50.0 i 5.0 54.67 i 2.52 1.62 Total K 1654.0 i 83.0 1683.33 i 136.50 0.61 10/06/95 Water I-131 148.0 i 15.0 150.0 i O.00 0.23 10/27/95 Water Gr-Alpha 51.2 i 12.8 37.00 i 3.00 -1.92 Gr-Beta 24.8 5.0 25.33 1 1.53 0.18 Footnotes:
(a) EPA Results-Expected laboratory precision (1 sigma). Units are pC1/ liter for water and milk except K is in mg/ liter. Units are total pC1 for air particulate filters.
(b) Teledyne Results - Average i one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCi for air particulate filters.
(c) Normalized deviation from the known.
(d) The normalized deviation marginally exceeded the warning level and an apparent trend in the results appeared. The cause was a probable high bias in the beta counting efIlciency. Check source control charts did not indicate any changes in the counting equipment, so the I-131 calibration was suspected. New 1-131 calibrations were performed July 3 through 6,1995 after receiving a new standard from the EPA. The intercomparison sample data sheets were recalculated with the new efficiencies and the average result was in excellent agreement with the EPA (96 pCi/l versus the EPA value of 100 pC1/1). The discrepancy in the I-131 efficiency between the current calibration and the previous one (aside from the uncertainty in the standard) appears to be an abnormally low yield in the preparation of the standard for the older calibration which created a high bias in the counter efficiencies. The bias was less than ten percent, therefore further corrective action or revision of previously reported data is deemed not necessary.
(e) The mineral salt content of the water used by the EPA to prepare the samples has been shown to vary substantially throughout the year. Absorption curves to account for mount weight may vary from the true absorption characteristics of a specific sample. Previcus results do not indicate a trend toward "out of control" for gross alpha / beta analysis and the normalized deviation from the grand average is only -0.36. ne nonnalized deviation from the EPA known does not exceed three standard deviations and internal spikes have been in control. No corrective action is planned at this time.
f A-3
ew .a a m,w moa -- + --- -- a - --~~--- w-- w---- -- ,a APPENDIX B SYNOPSIS OF ANALYTICAL PROCEDURES 1
l l
l B-1
APPENDIX B APPLICABLE PROCEDURES 1
NUMBER 'ITILE DA'IE PAGE PRO-032-1 Determination of Gross Alpha 11/30/93 B-3 and/or Gross Beta in Water l Samples l l
PRO-042-5 Determination of Gamma 04/24/93 B-5 i Emitting Radioisotopes PRO-032-10 Determination of Gross Beta 03/01/87 B-7 in Air Particulate Filters l l
PRO-032-11 Determination of Radiciodine 12/15/92 B-8 j in Milk and Water Samples PRO-032-12 Determination of Radiolodine 12/15/92 B-9 in Vegetation Samples j PRO-342-17 Environmental Thermolumi- 06/17/94 B-10 l nescent Dosimetry frLD) !
l PRO-032-35 Determination ofTritium in 10/01/93 B-11 Water by IJguld Scintillation 1
i B-2
T TELEDYNE PRO-032-1 ISOrIOPES DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA 1
IN WATER SAMPLES
1.0 INTRODUCTION
The 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 may be used if the sample has a significant salt content 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 rinsed into 1
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 after mounting tbe 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.
2.0 DETECTION CAPABILITY Detection capability depends upon the sample volume actually B-3
l T'IELEDYNE PRO-032-1 ISOIOPES represented on the planchet, the background and the efficiency of the counting instrument, and upon self-absorption of alpha and beta particles by the mounted sample. Because the radioactive species are not identifled, no decay corrections are made and the reported activity refers to the counting time.
The minimum detectable level (MDL) for water samples is nominally 1.6 I 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. These figures are based upon a nominal counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. %e MDL for gross alpha activity is nominally 2.3 picocuries 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. n ese figures are based upon a nominal 200 minute counting time and upon a representative efIlciency 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 MDL for gross beta is 0.9 picocuries per liter and the MDL for gross alpha is 0.3 picocuries per liter. These values reflect a beta counting efficiency of 0.38 and an alpha counting efficiency of 0.18.
B-4
! PRO-042-5 T TELEDYNE ISOIDPES DETERMINATION OF GAMMA EMITTING RADIOISOTOPES Milk and Water 1
A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. 'Ihe 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 Bolids 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 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. 'Ihe sample is then counted for at least 1000 minutes with a shielded Ge(LI) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
Soils and Sediments Soils and sediments 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 weighed. The sample is 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.
Charcoal Cartridges (Air Iodine)
Charcoal cartridges are counted up to five at a time, with one positioned on the face of a Ge(Li) detector and up to four on the side of the Ge(LI) detector.
Each Ge(Li) detector is calibrated for both positions. '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, positioned on the face of the detector.
Air Particulate 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 B-s
l T'IEmnYNE PRO-042-5 i ISCTIOPES i
, coupled to a mini-computer-based data acquisition system which performs i pulse height analysis.
{ A mini-computer software program defines peaks by certain changes in the slope of the spectrum. 'Ihe program also compares the energy of each peak i with a library of peaks for isotope identification and then performs the
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radioactivity calculation using the appropriate fractional gamma ray abundance half-life, detector efficiency, and net counts in the peak region.
The calculation of results, two sigma error and the lower limit of detection
! (LLD) in pCi/ volume or pCi/ mass:
RESULT = (S-B)/(2.22 t E V F DF) j TWO SIGMA ERROR = 2(S+B)1/2/(2.22 t E V F DF)
LLD = 4.66(B)1/2/(2.22 t E V F DF)
] where: S = Area, in counts, of sample peak and background
- (region of spectrum ofinterest)
B = Background area, in counts, under sample peak, 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 i
2.22 = dpm/pCi E = detector efficiency for energy ofinterest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams)
F = fractional gamma abundance (specific for each emitted gamma) i DF = decay factor from the collection to the counting date B-6
4 T 'IELEDYNE PRO-032-10 4 ISCTIDPES 4
- DETERMINATION OF GROSS BETA IN AIR PARTICULATE FILTERS Air Particulates After a delay of five or more days, allowing for the radon-222 and radon-1 220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. An unused air particulate filter, supplied by T U Electric, is counted as the blank.
l 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)
- TWO SIGMA ERROR (pC1/m3) = 2((S/T2+(B/t2))1/2/(2.22 V E)
) LLD (pC1/m3) = 4.66(B/t/T)1/2/(2.22 V E) 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/pC1 B-7
1 T TELEDYNE PRO-032-11 ISO'IOPES DETERMINATION OF RADIOIODINE IN MIYJC 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 iodine from the sample.
The iodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into toluene as free lodine. 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 iodide 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 pCl/1, are performed as follows:
RESULT = (N/ At-B)/(2.22 E V Y DF) l 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) 1 dpm/pCi 2.22 =
V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted 1 1
DF = decay factor from the collection to the counting date E = efficiency 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 Ms = mass of PdI2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg B-8 l
TTEIEDYNE PRO-032-12 ISOIDPES 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 melt is dissolved in water, filtered and treated with sodium hypochlorite. The j iodine is then reduced with hydroxylamine hydrochloride and is extracted into l toluene. It is then back-extracted as lodide into sodium bisulfite solution and l 1s 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 pC1/1, 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) l B = background rate of counter (cpm)
- 2.22 = dpm/pCi V = volume or weight of sample analyzed l
Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = cfficiency of the counter for I-131, corrected for self absorption effects by the formula:
= Es(eXP-0.0085M)/fexp-0.0085Ms)
Es = efficiency of the counter determined from an I-131 j standard mount Ms = mass of PdI2 on the standard mount, mg I M = mass of PdI2 on the sample mount, mg B-9
T 'IELEDYNE PRO-342-17 ISOFIDPES ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY (TLD)
Teledyne Isotopes uses a CaSO4 :Dy thermoluminescent do.simeter (TLD) which the company manufactures. This material has a high light output, neg-ligible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.
Following the field exposure period the TLDs are placed in a Teledyne Isotopes j Model 8300. One fourth of the rectangular TLD is heated at a time and the I measured light emission (luminescence) is recorded. 'nle TLD is then annealed and exposed to a known Cs-137 dose; each area is then read again. This 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 !
performed as follows: l RESULT D= (D1+D2+D3+D4)/4 i
l TWO SIGMA ERROR = 2((D 1 -D) 2+(D2-D) 2+(D3-D) 2+(94_p) 2)/ 3) 1/ 2 i
where: D1 = the net mR of area 1 of the TLD, and similarly for .
D2. D3. and D4- i
= 11 K/R1 - A 11 = the instrument reading of the field dose in area 1 l K = the known exposure by the Cs-137 source l
R1 = the instrument reading due to the Cs-137 dose on i area 1 !
A = average dose in mR calculated in similar manner as above, of the transit control TLDs l
B-10 s
T TELEDYNE PRO-032-35 IS(7FOPES DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION Ten milliliters of water is added to 10 ml ofliquid scintillation solution in a 25 ml 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:
RESULT (pCi/1) = (N-B)/(2.22 V E)
DVO 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 V = volume of the sample in ml E = efIlciency of the detector At = counting time for the sample B-11
_.,,,-r. .- . J APPENDIX C EXCEPTIONS TO THE 1995 REMP 1
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APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1995 DATE OF REASONS FOR LOSS /
LOCATION DESCRIMION SAMPLING EXCEPTION E-3.5 Air Charcoal 01/24-01/31 Personnel error -
pump not turned on E-3.5 Air Charcotl 06/27-07/04 LLD not met - low air volume - pump failed E-3.5 Air Filter 01/24-01/31 Tersonnel error -
pump not turned on E-3.5 Air Filter 06/27-07/04 LLD not met - low I air volume - pump failed I 1
E-3.5 Food Product 01/10/95 Sample not available '
E-3.5 Food Product 02/07/95 Sample not available SW-12.7 Food Product 03/07/95 Sample not available E-3.5 Food Product 03/07/95 Sample not available SW-12.7 Food Product 04/04/95 Sample not available E-3.5 Food Product 04/04/95 Sample not available SW-12.7 Food Product 05/02/95 Sample not available E-3.5 Food Product 05/02/95 Sample not available SW-12.7 Food Product 09/19/95 Sample not available E-3.5 Food Product 10/17/95 Sample not available l l
E-3.5 Food Product 12/12/95 Sample not available l E-3.5 Food Product 12/26/95 Sample not available j l
N- 1.4 5 Vegetation 01/10/95 Sample not available !
C- 2
APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1995 DATE OF REASONS FOR IDSS/
LOCATION DESCRIFTION SAMPLING EXCEFFION SW-13.5 Vegetation 01/10/95 Sample not available SW- 1.0 Vegetation 01/10/95 Sample not available N- 1.45 Vegetation 02/07/95 Sample not available SW-13.5 Vegetation 02/07/95 Sample not available SW- 1.0 Vegetation 02/07/95 Sample not available N- 1.45 Vegetation 03/07/95 Sample not available SW-13.5 Vegetation 03/07/95 Sample not available SW- 1.0 Vegetation 03/07/95 Sample not available N- 1.45 Vegetation 04/04/95 Sample not available SW- 1.0 Vegetation 04/04/95 Sample not available WSW-0.1 Groundwater 04/11/95 Pump not in service WSW-0.1 Groundwater 07/05/95 Pump not in service WSW-0.1 Groundwater 10/03/95 Pump not in service NE-4.8 TLD (Qtrly) 01/04-04/07/95 Missing SE-4.6 TLD (Qtrly) 07/05-10/04/95 Missing SE 4.6 TLD (Annual) 10/04/95 Missing C-3
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l APPENDM D EXCEEDED REPORTING LEVELS 1
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1 APPENDIX D EXCEEDED REPORTING LEVELS 1995 None of the analytical measurements exceeded any notification level.
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APPENDM E LAND USE CENSUS l
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July 9,1995 COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS The Land Use Census identified receptors within a five (5) mile radius of the plant in each of the sixteen (16) meteorological sectors. The Land Use Census was conducted June 14 and 15,1995 and includes the following items:
- 1. Evaluation of the 1995 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 i
As required by commitment 22585 and Memorandum NE-24059, pertaining to shipment and storage ofliquefied chlorine gas within 5 miles of CPSES, the following conditions were found:
- 2. The following places were called to inquire about any changes or uses of chlorine gas within their areas. These areas reported no change in uses as reported in letter THP-88-0040, December 20,1988.
Happy Hill Farm City of Glen Rose Oakdale Park Glen Lake Camp 1
i Evaluation of the 1995 Land Use Census l
l The results of the 1995 Land Use Census were reviewed for impact on the Radiological
(
Environmental Monitoring Program (REMP). The specific areas reviewed, that could be affected by changes found in the land use census, were the sampling requirements for milk, broadleaf vegetation and food products.
Reviewing the milk sampling requirements from the ODCM Table 3.12-1 requires that samples are ;
to be obtained from milking animals in three locations within a 5 km distance having the highest j I
potential dose. If none are available, samples are acceptable from milking animals in locations 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year. A sample is also required at a control location. There are currently no identified milking animals (cow or goat) within i the specified distances. Currently the only location where milk samples are collected is at a control I location (SW - 14.5).
I Since not all milk samples are available, the broadleaf vegetation sampling specified in ODCM Table !
3.12-1 is being performed. Broadleaf sample requirements are such that samples of broadleaf vegetation are to be collected from each of two offsite locations of the highest predicted annual average D/Q if milk sampling is not performed at all the required locations. Currently, broadleaf vegetation samples are collected at two indicator locations (N - 1.45 and SW - 1.0) and one control location (SW - 13.5). These indicator locations are near the site boundary in sectors where broadleaf vegetation is available and D/Q is high. Therefore, no changes to the broadleaf sampling program are required.
Food product sample requirements of ODCM Table 3.12-1 requires that one sample of each principal class of food product be collected from any area that is irrigated with water in which liquid plant waste has been discharged. Of the gardens identified in the land use census, no gardens are located in any area that irrigates with water in which liquid plant wastes are discharged. Currently, food products are sampled from two indicator locations (ENE - 9.0 and E - 3.5) and from one control location (SW - 12.7). No changes are required in the food product program.
The 1995 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.
2
e 9 Calculated values for the associated X/Q and D/Q values for each controlling receptor location and pathway are included along with the receptor distances in the data tables of this land use census. The values used to determine potential dose due to radioactive effluent ' discharges are the highest calculated values based on annual average values. The annual average X/Q used for dose calculations is 3.30E-6, tritium X/Q is 4.36E-6, and the D/Q value is 3.34 E-8. All these values are conservative
)
based on the 1995 land use census data and therefore no changes are required in the dose calculation parameters as verified by the field data.
- X/Q units are Sec/ cubic meter
- D/Q units are inverse square meters 3
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i Nearest Resident by Sector, Distance, X/Q and D/Q
)
Sector Distance (Miles) X/Q D/Q N 2.2 9.28E-07 5.32E-09 NNE 2.4 4.7E-07 2.30E-09 NE 2.3 3.58E-07 1.28E-09 ENE 2.4 2.58E-07 7.08E-10 E 2.4 3.02E-07 6.62E-10 ESE 2.0 4.7E-07 1.20E-09 SE 1.9 8.3 E-07 3.40E-09 SSE 1.5 1.lE-06 6.60E-09 S 1.5 8.5E-07 5.20E-09 SSW 3.9 1.06E-07 3.62E-10 SW 1.1 1.4E-06 5.50E-09 WSW l.0 1.80E-06 6.50E-09 W l.6 7.64E-07 2.50E-09 WNW 3.0 3.76E-07 1.07E-09 NW 2.7 6.98E-07 2.24E-09 NNW 3.I 6.06E-07 2.46E-09 i
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.- - - . . . . .- .-. - - . -. . . - . - - - - _ . = . . - . - - - _ _ - - . - ..- - , .
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i Nearest Garden by Sector, Distance and D/Q k
Sector Distance (Miles) D/Q N 3.4 2.90E-09 NNE 2.5 2.30E-09 l NE 3.8 3.64E-10
]
, ENE 2.4 7.10E-10 l E 3.5 2.70E-10 i ESE 3.3 3.96E-10 )
SE 2.4 1.84E-09 SSE 2.3 2.36E-09 S 2.3 1.84E-09 I
SSW 4.7 2.80E-10 ;
SW l.5 2.5E-09 WSW l.4 3.06E-09 W 3.3 4.42E-10 WNW 3.8 5.68E-10 NW None None NNW None None l l
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Nearest Milk Animal by Sector, Distance and D/Q l
l Sector Distance (Miles) D/Q
! N None None l
NNE None None NE None None l
ENE None None E None None ESE None None 1
SE None None I SSE None None S None None SSW None None SW None None WSW None None W None None WNW None None NW None None NNW None None l
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l Population by Sector and Distance i Sector 0-1 1-2 2-3 3-4 4-5 Total l N - -
8 32 77 117 i NNE - - 8 80 24 112 NE - -
53 56 218 327 ENE - -
40 11 24 75 E - -
56 158 27 241 ESE -
3 5 106 128 242 I SE -
13 53 32 27 125 1
SSE -
32 48 18 2440 2538 I S -
37 21 35 112 205 l SSYV - - -
3 51 54 SVV -
69 3 45 40 157 WSW -
146 3 11 3 163 W -
11 8 24 13 56 WNW - -
3 35 53 91 l
NW - -
3 - -
3 NNW - - -
37 16 53 TOTAL -
311 296 683 3253 4559 Based on an average of 2.66 residents per house. This average was obtained from North 1 Central Texas Council of Governments for Hood and Somervell Counties and is derived from !
an average residents per house of 2.57 and 2.74, respectively.
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__ . _ _ _ . .. . . - . . - - . ~_ - - .- -
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Attachment 1 Environmental Sampling Locations Sampling Point Location Sample Type
- Al N-1.45 (SQUAW CREEK PARK) A A2 N-9.4 (GRANBURY) A A3 E-3.5 (CHILDREN'S HOhE) A A4 SSE-4.5 (GLEN ROSE) A A5 S/SSW-1.2 A A6 SW-12.3 (CONTROL) A ;
A7 SW/WSW-0.95 A l A8 NW-1.0 A R1 N-1.45 (SQUAW CREEK PARK) R l R2 N-4.4 R l R3 N-6.5 R R4 N-9.4 (GRANBURY) R j l R5 NNE-1.1 R l R6 NNE-5.65 R I R7 NE-1.7 R R8 NE-4.8 R l l R9 ENE-2.5 R RIO ENE-5.0 R j 1
R11 . E-0.5 R l
- R12 E- 1.9 R l R13 E-3.5 (CHILDREN'S HONE) R R14 E-4.2 R R15 ESE-1.4 R l R16 ESE-4.7 R R17 S E-1,3 R j R18 SE-3.85 R I
R19 SE-4.6 R R20 S SE-1.3 R R21 SSE-4.4 (GLEN ROSE) R R22 SSE-4.5 (GLEN ROSE) R R23 S-1.5 R R24 S-4.2 R R25 SSW-1.1 R R26 SSW-4.4 (STATE PARK) R R27 SW-0.9 R R28 SW-4.8 (GIRL SCOUT CAMP) R R29 SW-12.3 (CONTROL) R R30 WSW-1.0 R i R31 WSW-5.35 R
l i l Attachment 1 Environmental Sampling Locations 1 Sampling Point Location Sample Type
- R32 WSW-7.0 (CONTROL) R R33 W-1.0 R l
R34 W-2.0 R R35 W-5.5 R I R36 WNW- 1.0 R R37 WNW-5.0 R R38 WNW-6.7 R l R39 NW-1.0 R l R40 NW-5.7 R l R41 NW-9.9 (TOLAR) R '
R42 NNW-1,35 R R43 NNW-4.6 R SW1 N-1.5 (SQUAW CREEK MARINA) SW SW2 N-9.9 (LAKE GRANBURY) SW/DW SW3 N-19.3 (CONTROL-BRAZOS RIVER) SW SW4 NE-7.4 (LAKE GRANBURY) SW SW5 ESE-1.4 (SQUAW CREEK) SW2 SW6 NNW-0.1 (SQUAW CREEK) SW/DW 3 GW1 W-1.2 (NOSF POTABLE WATER) GW GW2 WSW-0.1 (PLANT POTABLE WATER) GW 34 GW3 SSE-4.6 (GLEN ROSE) GW 4 )
GW4 N-9.8 (GRANBURY) GW
GW5 N-1.45 (SQUAW CREEK PARK) GW' SS1 NNE-1.0 (SQUAW CREEK) 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) F F2 NNE-8.0 (LAKE GRANBURY) F FP1 ENE-9.0 (LEONARD BROS.-PECAN) FP FP5 SW-12.7 (CONTROL) FP FP6 E-3.5 (HAPPY HILL FARM) FP i
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Attachment 1 i Environmental Sampling Locations
]
Sampling Point Location Sample Type
- BL1 N-1.45 BL BL2 SW-1.0 BL 5 BL3 SW-13.5 (CONTROL) BL 5 l
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- Sample Type : A - Air Sample; R - Direct Radiation; SW - Surface Water; DW - Drinking Water l GW - Ground Water; SS - Shoreline Sediments; M - Milk; F - Fish; !
FP - Food Products; BL - Broadleaf Vegetation !
NOTES: 1) The municipal water system for the City of Granbury is supplied by surface water l from Lake Granbury (location SW2) and ground water (location GW4). Each of l these supplies is sampled. These samples are not required for compliance with Radiological Effluent Control 3/4.12.1, Table 3.12-1, because they are not affected !
by plant discharges.
- 2) This sample (location SW6) is representative of discharges from Squaw Creek Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake Granbury.
- 3) Plant potable water can be supplied by surface water from Squaw Creek Reservoir (location SW6) and ground water from onsite wells (location GW2). Each of these possible sources of water are sampled. _
- 4) Ground water supplies in the plant site area are not affected by plant liquid effluents as discussed in CPSES FSAR Section 2.4.13 and are therefore not required for radioactivity to meet the requirements of the Radiological Efiluent Control 3/4.12.1, Table 3.12-1.
- 5) Broadleaf sampling will be performed at the specified locations if milk samples are unavailable from any location.
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Figure 1. Environmental Sample Locations within 2 mile radius
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4 Figure 2. Environmental Sample Locations Greater Than 2 Miles Radius l
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