TXX-9709, TU Electric Cpes 1996 Annual Radiological Environ Operating Rept. W/Two Oversize Drawings &
| ML20137Y445 | |
| Person / Time | |
|---|---|
| Site: | Comanche Peak  |
| Issue date: | 12/31/1996 |
| From: | Curtis J, Floyd E, Woodlan D TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC) |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| TXX-97092, NUDOCS 9704230090 | |
| Download: ML20137Y445 (103) | |
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l Log # TXX 97092 l =.
e-File # 10300 l""
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April 18,1997 Grump We Pressdent 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 1996 _
Genti m n:
Enclosed is one (1) copy of the Annual Radiological Environmental Operating Report for the CPSES Radiological Enviornmental 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, 1996, through December 31, 1996, and summarizes the '
results of measurements and analysis of data obtained from samples collected during this interval.
I If there are any questions regarding this report, contact Connie Wilkerson f at (817) 897 0144 or Doug Kay at (817) 897 5204. r Sincerely, C. L. Terry By:
D. R. Woodlan Docket Licensing Manager CLW/grp Enclosure '
c- Mr. E. W. Herschoff Region IV w/ encl. l
{%ll /
Hr. T. J. Polich, NRR (clo)
Resident Inspectors, w/ encl.
9704230090 961231
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P O. Box 1002 Glen Rose Texas 76043 0 c4 Wings. Ioc.chd in CtMW Fih l
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F7 8 1UELECTRIC TU ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION 1996 ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT Reviewed By: ! Date: O [ f'7 Edwin T. Floyd Senior Radiation Protection Technician Approved By: wb Date: '/[g[f7 JohhR. Curtis Radiation Protection Manager P.O. Box 1002 Glen Rose Texas 76043-1002 2
TABLE OF CONTENTS SECTION PAGE L INIRCEUCIKE......................................................................................................1 A. Site and Station De scriptlon ................................................................ 2 H Objectives and Overview of the............................................................ 2 CPSES Monitoring Program II. PROGRAM DESCRIPTI ON . .. .. .... .. ......................................... ........... .... .. .. .. ........... 6 l
A. Sam pl e Loc ati on s .. ................................ ................... .. .. ........... .. .... ......... 7 i 1
H Sampling Methods and Procedures......... ....................................... 7 l l
. 1. Direct Rnd ia tion... .... .... . .. .... .... .. . . . .. .... .. . . .... .. . . ... .. .. . . . . .. . .... .. . . .... 8 4
- 2. Air Particulates and Air Iodine .......................................... 8 l 4
- 3. Milk..............................................................................................9
- 4. Water............................................................................................9 i 5. Fish.............................................................................................I1
- 6. Sh o reli n e Se d im e n t ............................................................. I 1
- 7. ' Food Pmd ucts... . .... . .. ...... .. . .. ....... .. .. .. .. ... ... ... ..... ... ... . . . .. ... .. ...... I 1
- 8. Broadl e af Vege tat 1on ........................................................... 1 2 C 1nterlaboratory Comparison Program ......................................... 12 D. Deficiencies in the Sample Program........................................... 13
. III.
SUMMARY
AND DISCUSSION OF 1996 ANALYTICAL RESULTS......14 A. Direct Radiation. .. . ...... ...... ...... . .... .. .. . . .... .. .. ... ..... . ... . .. .. .. .. .... . .. . . .. ..... . . .. . 1 6 B Ai r Particulates and Air lodine ...................................................... 17 C Milk..........................................................................................................18 D. Water........................................................................................................18 E. Fish.........................................................................................................19 11
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F. Sh o rel i n e Se d im en ts ................ ........ ..... ........ .. ........... ..... .. .. ............. . 2 0
],
G. Food Products. . . . . . . . . . . . .. . . . . . . . . .. . . .. . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . .
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H. B ro ad le af Vege tati o n ............... ...... .... ..... ... . .... ............... ... ................. . 2 1
{
i IV. CO N CLU SI ON S .. .. .. .... . ....... ... .. .... . . .. .. ... . . .. . . . . . . .. .. . . . .. . . . . ...... .. . .. .. .. .. . . . . . . .. . . . . . I.
V. REERENCEE...............................................................................................25 VI. DATATNrFR...............................................................................................27 APPENDICES i APPENDIX A Cross-Check Pmgmms... .. ... .. .. . .. .. . . .. ... . . ... . . . . .. . .. .. .. . . . .. . . . . . . . . .. .. . . . .. . . . . . .A- 1 APPENDIX B Synop sis o f An alytical Pro ce d ures ................................................B- 1 APPENDIX C Exceptions to the 1996 REMP..... .... .......... .......... ......... .......... ......C- 1 APPENDIX D Exceed ed Re p o rting Levels ........................................................... D - 1 APPENDIX E Land Use Census. ..... ...... ......... . ..... ... . . . . .... . .. ... . .. ... ... . . . .. . . ... .. . . ... . . . . ..... . . E - 1 111
e 1
'IJST OF TABLES TABLE TITLE PAGE j~
1 CPSES Radiological Environmental ......................................................... 2 8 Monitoring Program
- 2 Direct Radiation -- Thermoluminescent Dosimetry......................... 31 3 Concentrations of Iodine-131 in Filtered Air...................................... 33 i 4 Concentrations of Gross Beta Emitters in Air Particulates............ 36 l
! 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 ........................................ 4 2 1
i 8 Concentrations of Gamma Emitters in Groundwater....................... 43 1
l 9 Coneentrations of Tritium in Groundwater.......................................... 44 10 Concentrations of Gross Beta in Water-Surface / Drinking.............. 45 1
- 11 Concentrations of Gamma Emitters in Water-Surface / Drinking.46 1 12 Concentrations of Iodine-131 in Water-Surface / Drinking............. 47 !
l 13 Concentrations of Tritium in Water-Surface / Drinking.................... 48 )
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14 Concentrations of Gamma Emitters in Surface Water...................... 49 1
15 Concentrations of Tritium in Surface Water ........................................ 51 i
16 Concentrations of Gamma Emitters in Fish ......................................... 5 2 i 17 Concentrations of Gamma Emitters in Sediment.............................. 53 4
18 Concentrations of Gamma Emitters in Food Products..................... 54
$ 19 Concentrations of Gamma Emitters in Broadleaf Vegetation........ 55
' l 20 Radiological Environmental Monitoring Program Summary - l 4
January 1 to December 3 1. 19 96 .. .. .... . . ... .. .. .. ... .. .. .. .. .. . .. .. . . .. . . . . . .. . . ... .. .. .. .. 5 7 1
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LIST OF FIGURES FIGURE TITLE PAGE
-1 Radiological Environmental Monitoring Locations............................ 30 if I
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f INTRODUCTION 1
L 1
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I. INTRODUCTION Results of the Radiological Environmental Monitoring Program for the Comanche Peak Steam Electric Station for 1996 is contained within this re- !
port. This report covers the period from January 1, 1996 through !
December 31,1996 and summarizes the results of measurements and analy-1 ses of data obtained from samples collected during this interval. l i
A. Site and Station Descriotion Comanche Peak Steam Electric Station (CPSES) consists of two i
- PWR units, each designed to operate at a power level of about 1150
) megawatts (elect-ical). The station is located on Squaw Creek Reservoir in Somervell County about forty miles southwest of Fort i
Worth, Texas. Unit I received a low power operating license February 8,1990 and achieved initial criticality on April 3,1990. A full power license for Unit I was issued on April 17,1990, and commercial operation was declared on August 13, 1990. Unit 2 achieved initial criticality on March 24,1993 and synchronized to the electrical grid on April 9,1993. '
11 Objectives and Overview of the CPSES Monitoring Program The United States Nuclear Regulatory Commission (USNRC) regu- I 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 I
2
I release limits are not exceeded. However, as a precaution against j unexpected and undefined processes which might allow undue ac-cumulation of radioactivity in any see: tor of the environment, a pro-4 gram for monitoring the plant environs is also included.
Sampling locations were selected on the basM of local ecology, me-
, teorology, physical characteristics of the region, and demographic
! and land use features of the site vicinity. The radiological environ-I mental monitoring program was designed on the basis of the i USNRC Branch Technical Position on radiological environmental 4
i monitoring issued by the Radiological Assessment Branch, Revision 1 (November 1979)(1), the CPSES Technical Specifications (4) and .
1
) the CPSES Offsite Dose Calculation Manual (ODCM)(5),
i in 1996, 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 i
emitters, and iodine-131: the measurement of tritium and gamma l 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 l iodine-131 in broadleaf vegetation. Samples were collected by CPSES personnel. Sample analyses were performed by Teledyne
'v j Brown Engineering - Environmental Services.
The regulations governing the quantities of radioactivity in reactor s
effluents allow nuclear power plants to contribute, at most, only a i
)
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..- - . - . -. . .- _- . . ~ - . . . . . - - . - . -- . . .-
].
few percent increase above normal background radioactiv .
Background levels at any one location are not constant but time as they are influenced by external events such as cosm bombardment, weapons test fallout, and seasonal variations. 'I '
levels also can vary spatially within relatively short distances re-flecting variations in geological composition.
To differentiate be-i tween background radiation levels and increases resulting from op-eration of CPSES, the radiological surveys of the plant environs are :l divided into preoperational and operational phases. The preopera-tional phase of the program permits a general characterization of i
the radiation levels and concentrations prevailing prior to plant op-eration 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-F 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.
3 2.
e Identify potentially important pathways to be monitored af- ;
t ter the plant is in operation. l 3.
! Measure background levels and their variations along po-tentially important pathways in the area surrounding the
$ plant.
i 3
4.
i Provide baseline data for statistical comparison with future operational analytical results.
, The operational Radiological Environmental Monitoring Program is t
1 2 4
I
?
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l 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 i
the environmental exposure pathways.
- 2. . Verify the effectiveness of in-plant measures used for con-i trolling the release of radioactive materials.
4
- 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 seventh year of operational measurements and is j submitted in accordance with the requirements of the CPSES Offsite Dose i
Calculation Manual Part 1. Administrative Control 6.9.1.3.
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'T 1
2 5
l PROGRAM DESCRIPTIONS l
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i II. PROGRAM DESCRIPTION A. Sample Locations
^
Seventy-five locations within a radius of 20 miles from the CPSES site were included in the monitoring program for 1996. The num-ber and location of monitoring points were determined by consid-ering the locations where the highest off-site environmental con-cer;trations 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 locations, security and future program integrity. Additionally an annual land use census is conducted to identify changes in the use of areas surrounding the plant. If changes are identified that im-pact the principal pathways of exposure, appropriate changes to the radiological environmental monitoring program are implemented.
'Ihe results of the 1996 Land Use Census are provided in Appendix E.
The Radiological Environmental Monitoring Program for Comanche Peak is summarized in Table 1.
Il 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 for each 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 4
points. Sampling locations were chosen according to the i
criteria given in the USNRC Branch Technical Position on
, Radiological Monitoring (Revision 1, November 1979)(1)- 1 l
The area around the station was divided into 16 radial sec-l tors of 22-1/2 degrees each. TLDs were placed in all sec- i tors. Thermoluminescent dosimeters were located in two a
rings around the station. An inner ring was located at the l site boundary and an outer ring was located at a distance of i 4 to 6 miles from the station. Eleven additional TLDs were
! located at points of special interest, including two control locations. For routine TLD measurements, two dosimeters i of CaSO4 :Dy in teflon cards were deployed at each selected location. One set of dosimeters was exchanged on a quar-terly basis and the second set was exchanged on an annual
- basis. Additional sets of dosimeters were shipped with i
j each exchange cycle to serve as in-transit controls.
i Individual dosimeters were calibrated by exposure to an accurately known radiation field from a calibrated Os-137 source.
- 2. Air Particulates and Air Iodine Air particulate and air iodine samples were collected from the eight locauons described in Table 1.
Each air particulate sample was collected by drawing air through a 47 millimeter diameter glass-fiber filter. Air 8
I lodine was collected by drawing air through a TEDA im-pregnated charcoal cartridge which was connecte.d in se-ries behind the filter. The filters and charcoal cartridges were collected weekly by CPSES staff. In the laboratory, air particulate filters were analyzed for gross beta activity I and were composited quarterly for gamma spectrometry analysis. Charcoal cartridges were analyzed for iodine-131.
- 3. Milk Milk samples were collected by CPSES staff monthly for January, February, November and December. March through October samples were collected every two weeks.
Upon arrival at the laboratory, the milk samples were promptly analyzed for gamma emitters and for I-131 by utilizing radiochemistry techniques. >
- 4. Water The CPSES staff collected water at 11 locations. Surface water was collected at four locations (N-19.3, ESE-1.4, N-1.5 and NE-7.4). Location N-1.5 provides samples repre-sentative of Squaw Creek Reservoir surface water at a 10-cation beyond significant influence of the plant discharge.
Location ESE-1.4 provides samples representative of dis-charges from Squaw Creek Reservoir downstream to Squaw Creek and to Lake Granbury via the return line.
(Note: There have been no discharges of. water from Squaw Creek Reservoir to Lake Granbury via the return 9
1 line since the start up of Unit 1.) Location NE-7.4 provides samples of Lake Granbury surface water down stream of the discharge from the return line from Squaw Creek Reservoir. A control sample is obtained from the Brazos River, upstream of Lake Granbury at location N-19.3.
Surface water samples from Squaw Creek Reservoir loca-tions were collected weekly and composited for monthly .
I gamma isotopic analysis. Samples from Lake Granbury lo- -
l 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- j 9.9 and NNW-0.1). Samples of Squaw Creek Reservoir wa-ter were collected at location NNW-0.1. Samples from this -
1 location were analyzed pursuant to the drinking water re-quirements even though Squaw Creek Reservoir is not used as a potable water supply. I4 cation N-9.9 was used to sample surface water from Lake Granbury near the intake of the City of Granbury potable water plant. I l
Surface-drinking water samples were collected weekly and composited for iodine-131 analysis, gamma isotopic and gross beta analyses monthly. Tritium analyses were performed quarterly.
1 There are five groundwater locations (SSE-4.6, W-1.2, '
WSW-0.1, N-1.45 which are indicators and the control station, N-9.8). Groundwater supplies in the site area are 10
, not affected by plant effluents and are sampled only to l provide confirmation that groundwater is not affected by plant discharges.
Groundwater samples were collected quarterly. Gamma 1
isotopic and tritium analyses were performed by location.
! 5. Eish l Fish samples were collected at two locations for the 1996 program. An area 2.0 miles east-northeast of the site in Squaw Creek Reservoir was chosen as the indicator loca-tion, and a location at Lake Granbury (NNE-8) was chosen J
- . as a control location. Fish sampling was conducted in 2
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 4
Shoreline sediment samples were collected in January and f
- July from locations N-1.0 and SE-5.3. Samples were also j collected from Lake Granbury at the control location N-i '
3 9.9, and locadon NE-7.4, which is downstream of the dis-charge 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. Epod Products
, During the period of January through November,11 sam-11
, ,e 4 -- L 4 . m. e-L, 4 d.#A+- 4 ,-AL.d--a .m.- h _a __E.m e.- J-+4lma-S --.A--- m-- m me-- +=A4.--%n+- *.L---- - sami .--
I I
i ples were collected from two indicator sampling locations
) (ENE-9.0 and E-3.5) and one control location (SW-12.7).
1 A total of 7 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. ,
j 8. Broadleaf Vegetation Broadleaf vegetation was collected from the control loca-1 tion (SW-13.5) and two indicator stations (N-1.45 and SW-l 1.0) near the site boundary. Collection of broadleaf vege-
! tation started in January 1996. Broadleaf samples consisted of sumac, native grasses and weeds.
} Gamma isotopic and iodine-131 analyses were performed
- for all broadleaf vegetation samples.
C Interlaboratory Comoarison Program
. To demonstrate that the results of the environmental analyses are
- valid,'the CPSES Radiological Environmental Monitoring Program
- requires that independent checks on the precision and accuracy of
- the measurements of radioactive materials in environmental sample matrices be performed. To fulfill this requirement, Teledyne Brown Engineering - Environmental Services participates in the environmental sample cross-check program conducted by the U.S.
Environmental Protection Agency (EPA).
1 Beginning with 1996 the USEPA discontinued providing milk and air particulate filter samples. For replacements, we have purchased comparable spiked samples from Analytics, Inc. (see Analytics table).
12
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 known values to the participant laboratory and specifies the control limits. Results consistently higher or lower than the known values or outside the control limits indicate a need to check the instruments or procedures used.
The results of Teledyne Brown Engineering - Environmental l
Services' participation in the U.S. EPA Interlaboratory Comparison Program and the Analytic's program for 1996 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.
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SUMMARY
AND DISCUSSION OF 1996 ANALYTICAL RESULTS 14
IIL
SUMMARY
AND DISCUSSION OF 1996 ANALYTICAL RESULTS I'
! 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 Quality Assurance Manual IWL-0032-395 and arc detailed in Teledyne Brown 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-proach and frequently fall below the detection limits of state-of-the-art mea-surement methods as discussed in NCRP Report No. 50(2). The use of"<" in 4
the data tables symbolizes that the result is less than the lower limit of de-tection (LLD) as defined in Appendix B. The Teledyne Brown Engineering -
Environmental Services analytical methods meet the LLD requirements addressed in the CPSES Offsite Dose Calculation Manual.
Tables 2 through 19 give the radioanalytical results for individual samples. A statistical summary of the results appears in Table 20. The re-ported averages are based only on concentrations above the limit of detec-tion. In Table 20. the fraction (0 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 acuvity during the report pe- i riod.
A. Direct Radiation Environmental radiation dose rates determined by thermolumines-cent dosimeters (TLDs) are given in Table 2. Thermoluminescent 15
i i
- dosimetry badges with four readout areas each were deployed at each location on quarterly and annual cycles. The mean values of r
four readings (corrected individually for response to a known dose and for in-transit exposure) are reported.
A statistical summary of the 1996 data is included in Table 20. For the quarterly analyses the average dose rate of the control locations was 0.16 mR/ day with a range of 0.13-0.19 mR/ day. The average of the indicator locations for the quarterly samples was 0.15 mR/ day with a range of 0.10 to 0.27 mR/ day. For the annual samples, the average dose rate for the control samples was 0.15 mR/ day. The indicator locations had an average of 0.15 mR/ day with a range of 0.11-0.20 mR/ day.
Oakley(3) calculates an ionizing back,round t radiation dose equiva-lent of 82.2 mR/ year for Fort Worth including a terrestrial compo-nent of 45.6 mR/ year and an ionizing cosmic ray component of 36.6 mR/ year (excludes neutron component). Since Oakley's values rep-resent averages covering wide geographical areas, the measured i
ambient radiation average of 53.2 mR/ year for the immediate locale
]
of CPSES is consistent with Oakley's observations. Significant vari- )
ations occur between geographical areas as a result of geological composition and altitude differences. Temporal variations result from changes in cosmic ray intensity, local human activities, and factors such as ground cover and soil moisture.
Anomalies in the 1996 measured doses relative to preoperational 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 16
l l
I respectively. The 1988 averages for the quarterly and . annual I indicator locations were 0.16 mR/ day (range of 0.10 to 0.20) and l 0.15 mR/ day (range of 0.12 to 0.18) respectively.
- 11 Air Particulates and Air lodine A total of 416 charcoal cartridges were analyzed for airborne 10-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 415 air particulate filters were collected and analyzed for L
j gross beta activity. For 1996 the average gross beta activity for the control location was 0.019 pCi/m3 with a range from 0.009 to 0.041 pCi/m3. For the seven indicator locations the yearly average <
was 0.019 pC1/m3 with a range from 0.007 to 0.043 pC1/m3 The gross beta analysis data are presented in Table 4. Anomalies in i gross beta measurements relative to preoperational data were not
- i noted.
i 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 aver. ige beryllium-7 activity for the control location was 0.079 pCi/m3 with a range of 0.071-0.087 pCi/m3 For the indicator locations, the average beryllium-7 activity was 0.077 pCi/m3 with a range of 0.051 to 0.105 pC1/m3 Potassium-40, a naturally occurring nuclide, was measured in sixteen samples. The average potassium-40 for the control location was 0.007 pCi/m3- 'Ihe <
average potassium-40 activity for the indicator locations was 0.009 pC1/m3 with a range of 0.006-0.012 pCi/m3 17
C. Milk A total of 21 milk samples were collected in 1996. All samples were analyzed for lodine-131 by radiochemistry and for other gamma emitting isotopes by gamma spectrometry. Results of these measurements are presented in Table 6 and 7.
No iodine-131 was found in any of the milk samples. The lower limits of detection can be found in Table 6. l Results of the gamma spectrometry measurements are presented in Table 7. Naturally occurring potassium-40 was detected in all of l the milk samples. The average activity for the control location was 1372 pC1/1 with a range of 1230 to 1540 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 1996. The samples were analyzed for gamma emitters and tritium on a quarterly basis, pursuant to the ODCM requirements for groundwater. Twenty samples were analyzed for gamma emitters by gamma spectrometry. Potassium-40, Mn-54, Co-58, Fe-59, Co-60, Zn-65. Nb/Zr-95, Cs-134, Cs-137 and Ba/La-140 were not detected in any of the samples. Quarterly samples for each sampling location were analyzed for tritium; no tritium was detected. Results of these analyses are contained in Table 8 and 9 respectively.
Surface-drinking water was collected from two stations. All samples were analyzed for gamma emitters: results were below the lower limit of detection. Twenty-four samples were analyzed for 18
1 gross beta activity. The indicator station had an average activity of 22 pCi/l with a range of 15 to 34 pCi/1. He control station had an average activity of 13 pC1/1 with a range of 6.0 to 30 pCi/1. Eight quarterly composites were analyzed for tritium. We indicator sta- ,
tion had an average activity of 10375 pC1/1 with a range of 8800 to i
13000 pCi/1. The control station showed no tritium activity above 1 the lower limit of detection. Iodine-131 analyses by radiochemistry were performed on 24 samples of surface-drinking water; there l was no measurable activity. Results of these analyses are contained in Tables 10 through 13.
Surface water was sampled from four locations during 1996.
Samples were analyzed for gamma isotopic on a monthly basis (composite (2) and monthly (2)) and tritium composites on a quarterly basis. Forty-eight samples were analyzed by gamma spectrometry. Potassium-40 was detected in one sample at Station NE-7.4 an indicator station, with an average activity of 63 pC1/l.
Sixteen composited surface water samples were analyzed for tri-tiu m. The indicator stations had an average activity of 9529 pCi/l l l
with a range of 7300-11000 pCl/1. We results of these analyses l can be found in Table 14 and 15 respectively. The tritium detected j 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 Analysis Report.
E. Bsh The results of gamma isotopic analyses of fish samples collected 19
J during 1996 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 2978 pCi/kg wet with a range of 2700 to 3620 pC1/kg wet. The average concentration for the control location is 3105 pC1/kg wet with a range of 2520 to 3500 pC1/kg wet. No other gamma emitters were detected in any samples.
F. Shoreline Sediments 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 peJcles enriched with chelating organic materials. Biological action of bacteria and other 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 from the CPSES environment are given in Table 17. For 1996 four locations, one control and three indicators, were sampled.
Naturally occurring gamma emitters found in detectable concen-20
4 l
trations were Be-7, K-40 Pb-212, Bi-214, Pb-214. Ra-226 and Th-228. Cesium-137 was measured in one sample at stadon SE-5.3, an indicator station, at 61 pCi/kg dry. Preoperational levels of cesium-137 have ranged from 9.2 to 150 pCi/kg on four different :
4 occasions.
i G. Food Products i
Results of gamma isotopic analyses of food samples are contained in Table 18. A total of 11 samples were analyzed from three locations.
Potassium-40, a naturally occurring isotope, was found in all 11 samples. For the indicator locations the average potassium-40 ac-tivity was 1907 pCi/kg wet with a range of 898 to 2660 pCi/kg wet.
The average potassium-40 for the control station was 1571 with a range of 673 to 2830 pCi/kg wet. Naturally occurring beryllium-7 was not detected in any sample.
No I-131, Cs-134 or Cs-137 were detected in food products during 1996.
H. Broadleaf Vegetation Results of gamma isotopic analyses of broadleaf vegetation samples are contained in Table 19. A total of 36 samples were analyzed from three locations. Potassium-40, a naturally occurring isotope, was found in all samples. The average potassium-40 activity for the control location was 5360 pC1/kg wet with a range of 2480 to 9670 pCi/kg wet. For the indicator locations the average potassium-40 activity was 2875 pCi/kg wet with a range of 929 to 5770 pC1/kg wet. Naturally occurring beryllium-7 was detected in twenty-four-indicator samples with an average activity of 3190 pCi/kg wet; the range was 408 to 9330 pC1/kg wet. Eleven out of the 12 samples 21
i l
from control station SW-13.5 were found to have beryllium-7 with ,
1 an average activity of 1450 pC1/kg wet and a range of 444-4950 l pC1/kg wet.
Thorium-228 was detected in three samples from indicator stations N-1.45 and SW-1.0 with an average activity of 80 pC1/kg wet and a range of 70-95 pCi/kg wet.
Iodine-131 and Cs-134 were below the lower limit of detection in all samples.
Cesium-137 was detected in one sample from indicator station N-1.45 with a value of 45.6 pCi/kg wet. This value is less than previously determined in prior yearly samples.
22
a 4 - J'-4a a - n-.. .J. - 4 A -.as. 6 --.es A ,-A.,4- -J .-
1 i
l 4
s i
CONCLUSIONS 23
IV. CONCLUSIONS It is concluded from the levels obtained in environmental samples during 1996 and comparison of these levels to preoperational measure-ments and operational controls, that the operation of CPSES in 1996 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 pC1/1 to approximately 10375 pCi/1. This increase has been expected, based on 2 unit operation. The atmospheric environment was sampled for airborne particulate matter, radiolodine, and direct radiation. The terrestrial environment was sampled for milk, groundwater. _ surface-drinking water, food products and broadleaf vegetation. The aquatic environment was sampled for surface water, fish and shoreline sediment.
The analyses of these samples provided results which were either below the measurement detection limits or were indicative of natural terrestrial and cosmic ray radiation levels, except for the tritium in the surface water of Squaw Creek Reservoir which was far below the reporting levele for radioactivity concentrations in environmental samples.
24
1 l
1 l
l l
l l
1 4
REFERENCES 1 l
l 1
I 25
=- . . .- . .. - .- -. . . - . . . . . . . -. - - - - . - - . . . - . - - --.
i l
4 b
5 1
V. REFERENCES
} 1. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological i Environmental Monitoring Program", Radiological Assessment Branch Technical Position, November 1979, Rev.1
- 2. National Council on Radiation Protection and Measurements, >
i 1
" Environmental Radiation Measurements", NCRP Report No. 50, !
f Washington, D.C., December 27.1976
- 3. Oakley, D.C., " Natural Radiation Exposure in the United States",
]
ORP/SID E Office 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
l 1
I I
l I
1 l
DATA TABLES l
i 1
r 27 t
i TABLE I (PACE 1 OF 21 -
T U ELECTRIC COMANCilE PEAK STEAM ELECTRIC STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -- 1996 Identification by Number of Sector and Distance Sampling Analytical ;
Media Imations (Miles) Freauency Ial Analyses Freauency fal Gamma Exposure 43 N-1.45: N-4.4: N.6.5: Q.A Thermolu ninescent Q.A' N-9.4: NNE- 1.1 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: i SE-3.85: SE-4.6: SSE-1.3:
SSE-4.4: SSE-4.5: S-1.5:
S-4.2: SSW-1.1: SSW-4.4:
SW-0.9: SW-4.8: SW-12.3:
WSW- 1.0; WSW-5.35: i WSW-7.0: W-1: W-2: W-5.5 WNW-1: WNW-5.0; WNW-6.7:
NW-1: NW-5.7: NW-9.9; !
y NNW-1.35: NNW-4.6 ;
ao
. 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 t NE-7.4 '
Tritium QC l Groundwater 5 SSE-4.6 Q Camma Spectrometry Q ;
W-1.2: WSW-0.1 i N-9 8: N-1.45 Tritium Q l I
Water-Surface 2 NNW-0.1: N-9.9 M (c) Gross Beta M !
Drinking Gamma Spectrometry M .
Iodine-131 M L Tritium QC i t
t t
l TABLE I (PAGE 2 OF 2)
' T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STA110N RADIOLOGICAL ENVIRONMENTAL MONI1DRING PROGRAM -- 1996 Ident1I1 cation by Number of Sector and Distance Sampling Analytical Media locauons IMilesi Freauency fal Analyses Freauency (a)
Sediment 4 N-9.9: NNE-1: NE-7.4 SA Gamma Spectrometry SA SE-5.3 Fhh 2 NNE-8; ENE-2 SA Gamma Spectrometry SA Milk 1 SW-14.5 SM. (d) lodine-131 SM (di Gamma Spectrometry SM (d)
Food Products 4 E-4.2: ENE-9.0: E-3.5: Mit Gamma Spectrometry MH SW- 12.7 lodine-131 Mit Broadleaf 3 N-1.45: SW-1.0; SW-13.5 M Gamma Spectrometry M Vegetation g lodine-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 = Semlannual A = Annual (b) Surface water oamples from Squaw Creek Reservoir are monthly composites of weekly 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 gmb samples.
(c) Drinking water samples are a monthly composite of weekly grab samples.
(d) Milk sample rollection and analysis frequency is semimonthly when animals are on pasture. Otherwise samples are collected and analyzed monthly.
l
d FIGURE 1
, RADIOLOGICAL ENVIRONMENTAL MONITORING I4 CATIONS 1
h SAMPLING LOCATION SAMPLE SAMPLING LOCATION SAMPLE FONT iSEniuM-MHFR) 'IYR* KMNT RFf: Int MUFS) 'IYPE*
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 A7 SW/WSW-0.95 A R34 W-2.0 R 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 NNE1.1 R SW2 N-9.9 SW/DW R6 NNE-5.65 R SW3 N-19.3 SW R7 NE- 1.7 R SW4 NE-7.4 SW R8 NE-4.8 R SW5 ESE- 1.4 SW l R9 ENE-2.5 R SW6 NNW-0.1 SW/DW RIO ENE 5.0 R GW1 W-1.2 GW/DW R11 E-0.5 R GW2 WSW-0.1 GW/DW R12 E 1.9 R GW3 SSE-4.6 GW/DW ,
R13 E 3.5 R GW4 N-9.8 GW/DW 1 R14 E-4.2 R GW5 N-1.45 GW/DW RIS 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 SS4 SE-5.3 SS R19 SE-4.6 R M4 SW-14.5 M R2O 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 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 BL3 SW-13.5 BL
- TYPES: A - Air Sample GW - Groundwater F- Fish R - Direct Radiation SS - Shoreline Sediment FP - Food Product SW - Smface Water M- Milk BL - Broadleaf Vegetation DW - Drinking Water 30
TABLE 2 (PAGE 1 or 21 T U ELECTRIC COMANCIIE PEAK STEAM ELEt TRIC STA'I1ON Direct Radiation - Thermoluminescent Dosimetry Results in mR/ day i 2 s. d..
FIRST QUARTER SECOND QUARTER TillRD QUARTER FOURTH QUARIER AVERAGE ANNUAL Semenan 01/03-04/03/96 04/03 07/05/96 06/12-10/02/96 10/02/96-01/03/97 d 2 S.D. 01/03/96-01/02/97 N.1.4 5 O. I 110.003 0.1510.004 0.1410.007 0.1210.003 0.1310.005 0.1410.004 N.4.4 0.I410.01 0.I810.01 0.I710.009- O.1410.01 0.I510.01 0.1610.009 N-6.5 O.1210.01 0. I610.0c8 0.1510.01 0.1310.03 0.1410.01 0.1410.01 N-9.4 0.1210.008 0.I610.008 0.I510.002 0.1310.01 0.1410.007 0. I5i0.004 NNE- 1.1 0.09810.003 0.1310.005 0.1210.002 0.1310.06 0.1210.02 0.1210.004 NNE-5.65 O.1310.01 0.1710.01 0.1610.01 0.I310.007 0.1510.01 0.1510.01 NE- 1.7 - 0.1110.005 0.1510.003 0.1410.005 0.1310.01 0.1310.006 0.1410.005 NE-4.8 0.1210.009 0.1710.01 0.1510.008 0.1410.01 0.1410.01 0.1510.007 ENE-2.5 O. I410.01 0.1910.01 0.1710.01 0.1510.02 0.I710.01 0.I710.01 ENE-5 O. I 710.02 0.2010.02 - O.I810.02 0.1710.02 0.I810.02 0.2010.02 w E-0.5 O.1210.009 0.I7i0.01 0,1510.005 O.1410.01 0.1410.009 0.I410.003 E-1.9 0.09810.001 0.1510.002 0.1410.008 0.1010.007 0.1210.004 0.1210.005 E-3.5 O. I 610.02 0.2010.01 0.I810.007 0.1610.009 0.1710.01 0.1910.01 E-4.2 0.1310.01 0.I810.007 0.1610.01 0.I410.009 0.1510.01 0.1610.02 ESE- 1.4 0.I210.007 0.1710.01 0.1510.01 0.I310.02 0.I410.01 0.1410.003 ESE-4.7 0.1510.01 0.1910.008 0.I810.01 0.1510.01 0.1710.01 0.1710.01 SE-1.3 0.1410.005 O.1910.01 0.I810.005 O.1510.02 0.1610.01 0.1610.02 SE-3.85 O.1210.01 0.1610.005 O.1610.008 0.I110.002 0.I410.007 0.1410.007 SE-4.6 0.1310.008 0.1610.01 n.1510.01 0. I i10.005 O. I410.008 0.1410.009 SSE-1.3 0.1210.008 0.1610.003 C.1510.01 0.1210.01 0.1410.009 0.1410.008 SSE-4.5 O. I 110.009 0.1610.01 0.1610.004 0.1210.02 0.1410.01 0.1410.005 SSE-4.4 0.1310.005 O.1710.01 0.1610.02 0.1310.01 0.1510.01 0.I510.007
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TABLE 4 (PAGE 1 OF 3) l T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION j CONCENTRATIONS OF GROSS BETA EMITTERS IN AIR PART1CUIATES !
Results in Units of 10-3 pct /m3 12 s.d.
STATION 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 ctw I wnON nATE JANUARY 01/02-01/09/96 4214 3414 3914 3314 3814 3314 3814 3914 l 01/09-01/16/96 2614 2414 3014 23i4 2814 2614 2714 2914 k 01/16-01/23/96 2714 2414 2614 2314 2714 23i4 2314 2814 !
01/23-01/30/96 3014 2714 2814 2714 3314 2814 2714 2914 6 FEBRUARY 01/30-02/06/96 4214 3814 3514 4114 4014 3714 4314 4114 i 02/06-02/13/96 2414 1714 1914 1714 2014 1714 1614 2114 t 02/13-02/20/96 2014 2114 2114 1713 2414 1914 2014 2714 02/20-02/27/96 2013 1913 1913 1713 2113 22i3 1913 2314 I 8 MARCH 02/27-03/05/96 3014 2714 2914 2314 2914 2814 2914 3014 03/05-03/12/96 2414 2414 2414 2614 2414 3014 2214 3114 ;
03/12-03/19/96 2314 1513 2013 1813 1813 20i3 2013 2013 '
03/19-03/26/96 2314 1613 1813 1713 2114 1913 1913 20i3 03/26-04/02/96 1713 1713 1413 1513 1613 1513 1513 1113 APRIL :
I 04/02-04/09/F 2914 2013 2114 2414 2414 2714 2514 2314 ;
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___ _ _ _ _ __ _ __ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ _ . . ~ _ . .
TABE 4 (PAGE 2 OF 3)
T U ELECTRIC
- COMANCHE PEAK STEAM EECTRIC STKi1ON CONCENTRATIONS OF GROSS BETA EMITIERS IN AIR PART1CUIATES Results in Units of 10-3 pCl/m3 1 2 s.d.
S TION 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 Mbl 04/30-05/07/96 1013 1714 1513 1513 1413 1614 1313 1613 05/07-05/14/96 7.513.2 1313 1213 1213 1414 1013 1213 1213 05/14-05/21/96 1113 1213 1213 1313 1213 9.113 1213 1313 05/21-05/28/96 1113 1713 1713 1813 1813 1313 1313 1913 05/28-06/04/96 2D2J 1914 18t4 1714 1814 1314 1714 1514 JUNE 06/04-06/11/96 7.213.3 1413 1413 1213 8.913.2 1113 1013 1213 06/11-06/18/96 1013 1413 1614 1513 1413 1413 1714 1814 D6/18-06/25/96 9.513.0 1313 9.813.0 9.813.0 1125 1113 1213 1413 06/25-07/02/96 9.413.2 1613 1513 1513- 1413 1313 1213 1714 JULY 07/02-07/09/96 1115 2214 1914 1914 1814 1813 1814 2414 07/09-07/16/96 1413 1513 1613 1313 1213 1113 1513 1713 07/16-07/23/96 1113 1013 ' 9.413.4 1113 1514 1814 1013 1213 07/23-07/30/96 1313 1513 1513 1313 1313 1313 1213 1413 AUGUST 07/33-06/06/96 1914 2114 1613 1914 2114 1713 1813 2214 08/06-06/13/96 1113 1213 9.213.3 1413 1213 9.013.3 1013 1313 08/13-08/20/96 1514 1013 1214 1314 1514 8.913.4 1514 1113 08/20-06/27/96 1213 1213 9.613.2 8.513.2 1013 8.813.2 1213 1313 08/27-09/03/96 9.013.4 1213 1113 9.413.4 II13 7.313.3 1414 8.713.3 o
TABLE 4 (PAGE 3 OF 3)
T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STATION CONCEN1 RATIONS OF GROSS BETA EMITTERS IN AIR PARI 1CUIATES Results in Units of 10-3 pCl/m3 1 2 s.d.
S ON E-3.5 N-9.4 NW-1.0 SW/WSW4 95 S/SSW-l.2 SW- 12.3 SSE-4.5 N- 1.4 5 EEEIEMBER 09/03-09/10/96 2414 2014 1914 2014 1713 18 4 1814 2214 09/10-09/17/96 3314 3614 2714 3214 3014 2514 2814 2714 09/17-09/24/96 1614 1313 1413 1414 1413 1113 1413 1313 09/24-10/01/96 1713 2014 1713 1713 1513 1313 1614 1914 OCIOBER 10/01-10/08/96 3014 3214 3014 2814 2914 2014 2714 2714 10/08-10/15/96 2514 2214 2014 2114 2414 1914 2414 2114 10/15-10/22/96 15i3 1814 1513 1413 1714 1213 1614 1914 10/22-10/29/96 9.413.3 1313 I113 1013 1213 1013 1113 1213 NOVEMBER 10/29-11/05/96 1913 2714 1913 2114 2214 1813 21i4 2114 11/05-11/12/96 1813 2314 1713 2013 2013 1513 2214 1913 11/12-11/19/96 2014 2614 1814 2214 2114 1914 2514 2614 11/19-11/26/96 2816 2414 2314 2914 2214 1814 2214 2414 11/26-12/03/96 1414 2014 <0.005 1714 1714 1313 1314 1814 DECEMBER 12/03-12/10/96 1813 2213 1913 1913 1813 1613 2013 2213 12/10-12/17/96 2814 3114 2514 2514 2414 2214 2314 2814 12/17-12/23/96 7.9i3.8 1314 1414 1314 1314 1114 1314 1114 12/23-12/31/96 3114 3314 31i4 2914 2713 2413 2713 3014
. _ _ __.m _ - __ _ _._._._ __ ___ __ .__ . . _ . _ . . . . . _ . -. _ _ _ - . _ . _ . -, . _ _ . - _ _ . . _ _ . _ - . ____
TABLE 5 (PAGE 1 OF 21 T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STA110N CONCENTRATIONS OF GAMMA EMirIERS* IN AIR PAR 11CULATE FILTERS Results in Units of E-03 pC1/m3 1 2 s.d.
LOCA110N COMFOSTIE PERIOD Be-7 K-40 Ru-103 Cs-134 Cs-137 FIRST QUARIER .
NW- 1.0 12/26/95-04/02/96 105110 6.813.6 <0.4 <0.4 <0.3 SW/WSW-0.95 12/26/95-04/02/96 76.717.7 <8 <0.4 <0.4 <0.4 S/SSW-1.2 12/26/95-04/02/96 92.719.3 <10 <0.5 <0.5 <0.4 SW-12.3 12/26/95-04/02/96 86.818.7 8.614.3 <0.6 <0.5 <0.4 SSE-4.5 12/26/95-04/02/96 90.919.1 11.114.1 <0.4 <0.4 <0.5 E-3.5 12/26/95-04/02/96 83.518.3 7.413.3 <0.4 <0.4 <0.5 N- 1.4 5 12/26/95-04/02/96 87.618.8 8.814.6 <0.7 <0.6 <0.7 ca N-9.4 12/26/95-04/02/96 100110 <10 <0.5 <0.4 <0.4 e
SECOND QUARTER NW- 1.0 04/02/96-07/02/96 72.917.3 <10 <0.5 <0.4 <0.4 SW/WSW-0.95 04/02/96-07/02/96 90.119.0 <10 <0.5 <0.5 <0.5 S/SSW-1.2 04/02/96-07/02/96 82.118.2 <10 <0.5 <0.5 <0.4 SW-12.3 04/02/96-07/02/96 79.818.0 7.0413.3 <0.5 <0.5 <0.5 SSE-4.5 04/02/96-07/02/96 69.116.9 <20 <0.5 <0.5 <0.6 E-3.5 04/02/96-07/02/96 72.117.2 <9 <0.4 <0.4 <0.4 N-1.45 04/02/96-07/02/96 75.517.5 <10 <0.4 <0.4 <0.4 N-9.4 . 04/02/96-07/02/96 95.419.5 <10 <0.5 <0.5 <0.5
'All other gamma emitters were < LID.
l TABLE 5 (PAGE 2 OF 2)
T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STATION CONCEffiRAT10NS OF GAMMA EMrTIERS* IN AIR PARI 1CULATE FIL'IERS Results in Units of E-03 pCl/m3 1 2 s.d.
LOCA110N COMPOSTIE PERIOD Be-7 K.40 Ru-103 Cs-134 Cs-137 THIRD QUARIER ;
NW- 1.0 07/02/96-10/01/96 65.416.5 10.614.5 <0.6 <0.5 <0.5 SW/WSW-0.95 07/02/96-10/0I/96 84.518.4 <9 <0.5 <0.4 <0.4 S/SSW-1.2 07/02/96-10/01/96 82.718.3 10.714.6 so.6 <0.6 <0.5 SW-12.3 07/02/96-10/01/96 79.I17.9 6.213.4 <0.5 <0.4 <0.4 SSE-4.5 07/02/96-10/01/96 77.717.9 11.614.9 <0.7 <0.5 <0.5 E-3.5 07/02/96-10/01/96 60.216.0 8.013.5 <0.5 <0.4 <0.6 N- 1.45 07/02/96-10/01/96 64.616.5 <10 <0.5 <0.4 <0.5 N-9.4 07/02/96-10/01/96 72.517.3 <20 <0.7 <0.6 <0.6 8
j FOURITI QUARIER NW-1.0 10/01/96-12/31/96 71.517.2 6.6113.75 <0.6 <0.5 <0.4 SW/WSW-0.95 10/01/96-12/3I/96 81.718.3 7.9313.82 <0.7 <0.4 <0.6 S/SSW-1.2 10/01/96-12/31/96 64.516.5 <10 <0.5 <0.5 <0.5 SW-12.3 10/01/96-12/31/96 70.617.1 7.7514.15 <0.5 <0.4 <0.6 SSE-4.5 10/01/96-12/31/96 65.316.5 6.1613.33 <0.5 <0.5 <0.5 E-3.5 10/01/96-12/31/96 51.115.2 9.2214.00 <0.5 <0.4 <0.5 .
N-1.45 10/01/96-12/31/96 68.517.0 <20 <0.7 <0.7 <0.7 N-9.4 10/01/96-12/3I/96 63.616.4 <10 <0.6 <0.5 <0. 5
- All other gamma emitters were <LLD.
l I
TABLE 6 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION !
CONCENTRATIONS OF I-131 IN MILK Results in pCi/li 2 s.d. l I
COLLECTION l MONTH DATE SW-14.5 JANUARY 01/30/96 <0.2 FEBRUARY 02/27/96 < 0. 2 MARCH 03/12/96 <0.2 03/26/96 < 0. 2 APRIL 04/09/96 <0.2 l 04/23/96 <0.2 MAY 05/07/96 < 0.1 05/21/96 < 0. 3 JUNE 06/04/96 <0.2 1 06/18/96 < 0. 2 JULY 07/02/96 < 0. 3 07/16/96 <0.1 07/31/96 < 0. 2 AUGUST 08/13/96 <0.1 1 08/27/96 < 0. 2 SEPTEMBER 09/10/96 < 0.1 09/24/96 < 0.1 OCTOBER 10/08/96 <0.2 l 10/22/96 <0.2 NOVEMBER 11/26/96 < 0. 3 DECEMBER 12/31/96 <0.2 41
- .. . . . .~ . . ...
4 TABLE 7 T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STAllON CONCENTRAT10NS OF CAMMA EMITIERS* IN MILK Results in Units of pCl/ liter i 2 s.d.
LOCA110N COLLECI1ON DATE K-40 Cs-134 Cs-137 La-140/Ba-140 STAT 10N SW-14.5 JANUARY 01/30/96 14801150 <4 <4 <3 FEBRUARY 02/27/96 13001130 <4 <4 <4 MARCH 03/12/96 13801140 <4 <4 <4 i 03/26/96 14101140 <4 <3 <3 APRIL 04/09/96 13301130 <5 <5 <5 04/23/96 14401140 <3 <3 <3 MAY 05/07/96 12501120 <4 <4 <4 05/21/96 1540tl50 <4 <4 <4 JUNE 06/04/96 13601140 <5 <5 <5 06/18/96 13001130 <4 <4 <4
$ JULY 07/02/96 13901140 <3 <3 <4 07/16/96 14401140 <5 <5 <6 07/31/96 13301130 <4 <4 <5 '
AUGUST 08/13/96 14801150 <3 <3 <3 08/27/96 13801140 <3 <3 <4 ,
SEFIEMBER 09/10/96 12301120 <4 <4 <4 09/24/96 13201130 <4 <4 <4 OCTOBER 10/08/96 12701130 <4 <4 <4 10/22/96 14001140 <5 <5 <5 NOVEMBER 11/26/96 13001130 <4 <4 <5 DECEMBER 12/31/96 14801150 <3 <3 <3 "All other gamma emitters were <LLD.
- .. . .. ~~ - - .
TABLE 8 T U ELECTRIC COMANCIIE PEAK STEAM ELECTRIC STA110N CONCENTRATIONS OF GAMMA EMITIERS* IN GROUNDWATER Results in Units of pC1/112 s.d.
K-4 0 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/La-140 STATION W-1.2 03/31/96 <70 <3 <3 <6 <3 <6 <3 <3 <3 <3 06/25/96 <50 <3 <3 <5 <3 <7 <3 <3 <3 <4 09/24/96 <50 <3 <3 <6 <3 <6 <3 <3 <4 <5 12/31/96 <40 <3 <3 <6 <3 <6 <3 <3 <3 <4 STATION SSE-4.6 03/31/96 <60 <3 <3 <6 <4 <7 <4 <4 <4 <5 06/25/96 <60 <4 <4 <7 <4 <8 <4 <4 <4 <5 09/24/96 <50 <3 <3 <6 <4 <6 <3 <3 <3 <5 4 12/31/96 <60 <3 <3 <7 <4 <7 <3 <3 <4 <5 ta STATION N-1.45 03/31/96 <60 <3 <3 <8 <4 <10 <4 <4 <4 <5 06/25/96 <50 <3 <3 <6 <4 <6 <3 <3 <4 <4 09/24/96 <50 <3 <3 <5 <3 <6 <3 <3 <4 <4 12/31/96 <50 <3 <3 <6 <3 <6 <3 <3 <3 <4 STA110N WSW-0.1 03/31/96 <60 <3 <3 <7 <4 <8 <4 <4 <4 <4 06/25/96 <50 <3 <3 <5 <3 <6 <3 <3 <3 <4 ,
09/24/96 <100 <4 <4 <10 <5 <10 <5 <5 <5 <6 12/31/96 <80 <3 <3 <6 <3 <6 <3 <3 <3 <3 STATION N-9.8 7
03/31/96 <50 <3 <3 <5 <3 <6 <3 <3 <4 <4 06/25/96 <60 <3 <3 <6 <3 <6 <3 <3 <3 <4 09/24/96 <100 <4 <4 <7 <4 <8 <4 <4 <4 <5 12/31/96 <60 <2 <2 <5 <2 <5 <3 <3 <3 <3 All other gamma emitters were LLD. !
i
- _ -_ - _ _ - - _ _ _ _ - - _ = - - _ _ _ _ _ _ _ - _ - - - _ . _ _ - - . . _ - _ _- . - _ _ _ _ _ -
i TABLE 9 T U ELECTRIC
, COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER Results in pC1/1 2 s.d.
COLLECTION TRITIUM QUARTER DATE LOCATION ACTIVTIY
, 1 03/31/96 W-1.2 <900 03/31/96 SSE-4.6 <900 03/31/96 N- 1.45 <900 03/31/96 WSW-0.1 <900 1
03/31/96 N-9.8 <900 2 06/25/96 W-1.2 <2000 q 06/25/96 SSE-4.6 <2000 06/25/96 N- 1.45 <2000
! 06/25/96 WSW-0.1 <2000
- 06/25/96 N-9.8 <2000 3 09/24/96 W- 1.2 <2000 09/24/96 SSE-4.6 <2000 i 09/24/96 N- 1.45 <2000 09/24/96 WSW-0.1 <2000 09/24/96 N-9.8 <2000
. 4 12/31/96 W-1.2 <2000 12/31/96 SSE-4.6 <2000
- 12/31/96 N-1.45 <2000 12/31/96 WSW-0.1 <2000 I
12/31/96 N-9.8 <2000 4
4
i l
i TABLE 10 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION
! GROSS BETA CONCENTRATIONS IN WATER-SURFACE / DRINKING I
Results in pC1/1
- 2 s.d.
COLLECTION
- MONTH DATE NNW-0.1 N-9.9 1
i JANUARY 01/02/96-01/30/96 2214 12i3 i FESRUARY 02/06/96-02/27/96 20t4 9.113.0 MARCH 03/05/96-03/26/96 18i4 13i3 i APRIL 04/02/96-04/30/96 2214 10i3 MAY 05/07/96-05/28/96 34t5 30 4 JUNE 06/04/96-06/25/96 19 4 12i3 ;
i JULY 07/02/96-07/30/96 2714 11i3 i AUGUST 08/06/96-08/27/96 23i4 17i3 SEPTEMBER 09/03/96-09/24/96 1513 9.2i2.4 OCTOBER 10/01/96-10/29/96 2314 11i3 NOVEMBER 11/05/96-11/26/96 23i4 1013 DECEMBER 12/03/96-12/31/96 22 5 6.012.7 i
f 4
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- g
TABLE 12 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN WATER-SURFACE / DRINKING Results in PC1/112 s.d. l 3
l COLLECTION l MOlVIE DATE NNW-0.1 N-9.9 JANUARY 01/02/96-01/30/96 <0.5 <0.5 ,
FEBRUARY 02/06/96-02/27/96 < 0. 4- <0.4 MARCH 03/05/96-03/26/96 < 0. 4 <0.5 l APRIL 04/02/96-04/30/96 < 0. 5 <0.6 MAY 05/07/96-05/28/96 <1 <0,5 4
JUNE 06/04/96-06/25/96 < 0.1 <0.1 JULY 07/02/96-07/30/96 < 0. 8 <0.6 AUGUST 08/06/96-08/27/96 < 0. 2 <0.2
- SEPTEMBER 09/03/96-09/24/96 < 0. 4 <0.3 OCTOBER 10/01/96-10/29/96 < 0. 6 <0.6 NOVEMBER 11/05/96-11/26/96 <0.2 <0.2 DECEMBER 12/03/96-12/31/96 <0.2 <0.2 d
t 4
d 47 4
i l
TABLE 13 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN WATER-SURFACE / DRINKING Results in pCi/l 2 s.d. l l
COLLECTION i OUARTER PERIOD NNW-0.1 N-9.9 !
l 1 01/02/96-03/26/96 9700i1800 <2000 I
2 04/02/96-06/25/96 1300012000 <2000 3 07/02/96-09/24/96 8800il200 <2000 I 4 10/01/96-12/31/96 10000i1000 <2000 48
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TABIE 16 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STAT 10N
~
CONCENTRATIONS OF GAMMA EMITIERS* IN FISH Results in pCl/Kg (wet) i 2 s.d.
COLLECTION
-DATE STA110N DESCRIFI1ON K-40 Mn-54 Co-58 Fe-59 ~ Co-60 Zn-65 Cs-134 Ca-137- _
i 5
04/16/96 ENE-2.0 Bladc Bass 36201360 <10 <10 <30 <10 <30 <10 <10 04/17/96 ENE-2.0 Catfish 27701280 <10 <10 <30 .<10 <30 <10 <10 ,
F 04/16/96 NNE-8.0 Black Bass 25201250 <20 <20 <40 <20 <40 <20 <20 t
?
04/17/96 NNE-8.0 Catash 33701340 <10 <10 <30 <10 <30 <10 <10 ;
i 10/16/96 ENE-2.0 Bass 28201280 <10 <10 <20 <10 <20 <10 <10 ;
10/15/96 ENE-2.0 Catfish 27001270 <20 <20 <40 <20 <40 <20 <20 3 10/18/96 NNE-8.0 Bass 35001350 <10 <10 <30 <10 <30 <10 <10 f 10/17/96 NNE-8.0 Catfish 30301300 <20 <10 <40 <20 <40 <20 <20 E
[
i i
+
t i
F i
f I
'All other gamena emitters were LLD. [
b TABE 17 T U EECTRIC COMANCHE PEAK STEAM EECIRIC STA110N CONCENTRATIONS OF GAMMA EMITIERS* IN SEDIMElfr Results in pCI/kg (dry) i 2 s.d.
COLECDON DATE STATION Be-7 K-40 Ca-134 Cs-137 Pb-212 Bi-214 Pb-214 Ra-226 "Ih 99R >
STATION N-1.0 01/16/96 SSI <200 36601390 <30 <20 147129 203146 258140 <600 142128 f 07/18/96 SSI <200 21401290 <20 <20 141123 532147 391147 10501380 136123 I t
STA*I1ON NE-7.4 01/16/96 SS3 <200 23901260 <20 <20 228132 221i34 251137 6721248 220i30 C7/18/96 SS3 <200 16801290 <20 <30 173128 317147 297147 <500 167127 3
STATION N-9.9 l
01/16/96 SS2 <100 22701240 <29 <20 131120 206134 214i33 5111259 126i19 i 07/18/96 SS2 <200 1140011100 <30 <20 674167 598160 629163 11201320 653165 STA110N SE-5.3 01/16/96 SS4 7661246 37301470 <30 61125 275142 364166 365171 <700 266141 07/18/96 SS4 8681467 15101490 <60 <60 219173 3301101 3351101 <1000 <200 t
- All other garama emitters were LLD.
i
- - - - - - - - -.._uu., , . _ , . . - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - ---------------------------------------------------------------;------------
I TABLE 18
~ T U ELECTRIC I COMANCilE PEAK STEAM ELEC11UC STATION CONCEffTRA110NS OF GAMMA EMil'IERS* IN FOOD PRODUCTS
! Results in Units of pCI/kg (wet) i 2 s.d.
COLLEC110N -
STATION DESCRIP110N DATE Be-7 K-40 I-131 Cs-134 Cs-137 SW-12.7 01/30/96 =
02/27/96 =
03/26/96
- 04/30/96 * ,
Onions 05/28/96 <40 673167 <6 <5 <5 -
Cucumber 06/25/96 <60 12101120 <9 .<8 <9 08/27/96
- Okra / Beans 09/24/96 <60 28301280 <10 <7. <8 .
10/29/96=
11/26/96
- 12/31/96= 'i E-3.5 01/30/96
- 02/27/96=
g 03/26/95*
Onions 04/30/95 <60 20301200 <9 <8 <7 ,
Onions 05/28/96 <50 898190 <9 <6 <7 Banana Peppers 06/25/96 <80 19901200 <10 <10 <10 Tomatoes / 07/30/96 <40 23901240 <9 <5 <5 "
Cucumbers 'F Tomatoes / Peppers 08/27/96 <50 21001210 <8 <6 <6 Peppers 09/24/96 <50 16001160 <8 <7 <6 Peppers 10/29/96 <60 1590il60 <9 <7 <8 11/26/96
- 12/31/96 * ,
ENE-9.0 ' Pecans 11/05/96 <80 26601270 <10 <10 <10 i
All other gamma emitters were <LLD. .i
- " Sample not available.
._ . .. . ~ ._. . _ . _ . , . - _ - . _ . _.
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TAllLE 20 (PAGE I OF 6)
RADIOLOGICAL ENVIRONMENTAL MONTIURING PROGRAM
SUMMARY
T U ELECIRIC - COMANCIIE PEAK STEAM ELECTRIC STAllON JANUARY l TO DECEMBER 31.1996 inidysts and lower Limit Numt>-r of Medium of Pathway To'ai Number of All Indicator locauons location with Illnhest Mean Control locations Nonroutine Sampled ofAmlysis Detection Mean Name Mean (f)(2) Mean (f)(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measureme_n,ts TIDs (Quarterly) Garama (170) 0.15(162/162) NNW-4.6 0.19(4/4) 0.16(8/8) 0 (mR/ day) (0.10-0.27) (0.15-0.27) (0.13-0.19)
TLDs (Annual) Gamma (42) 0.15(40/40) ENE-5 0.20(1/1) 0.15(2/2) 0 (mR/ day) (O. I l-0.20) --
(0.15-0.15)
Air lodine-131 1-131(416) 70 -(0/364) NA NA -(0/52) 0 (10 3 pel/m3) -- --
Air Particulate Gross (415) 10 19(363/363) N-9.4 20(52/52) 19(52/52) 0 (10 3 pct /m3) Beta (7.2-4 3) (8.7-41) (8.5-41)
Camma (32) 9' '
Be-7 -
77(28/28) SW/WSW-0.95 83(4/4) 79(4/4) O (51-105) (77-90) (71-87)
K-40 -
8.7(12/28) S/SSW-1.2 11(1/4) 7.4(4/4) 0 '
(6.1- 12) --
(6.2-8.6)
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 (I) IID 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, means are of positive results only.
r A - _
_.. . _ . . m_ _..
TABLE 20 (PACE 2 OF 6)
RADIOLOGICAL ENVIRONMENTAL MONflDRING PROGRAM
SUMMARY
T U ElICTRIC - COMANCilE PEAK STEAM ELECTRIC STATION JANUARY l TU DECEMBER 31.1996 Analysis and lewer Limit Number of Medium of Pathway Total Number of All Indicator locations locaUon with Illahest Mean Control location Nonrouune Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (0(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direcuon Range Range Measurements Milk I-131 (21) -
N/A N/A N/A -(0/21) 0 (pCl/l) (BY IMmOCHEMISmY) --
Gamma (21)
K-4 0 -
N/A N/A N/A 1372(21/21) 0 (1230-1540) i
. Cs-137 -
N/A N/A N/A -(0 /21) O Surface Water Gamma (48)
(pC1/I)
K-40 63(l/36_ NE-7.4 63(l/12) -(0/12) 0 Tritium (16) -
9250(8/12) ESE- 1.4 9775(4/4) -(0/4) 0 (7300-11000) (8500-11000) --
Ground Drinlung Gamma (20) -
Water (pC1/l)
K-40 -
-(0/16) N/A N/A -(0/4) 0 Tritium (20) -
-(0/16) N/A N/A -(0/4) 0 (1) ILD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable P=AQal En/=u un atal Monitoring Program . Revision 1. November 1979.
l (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.
I
TABLE 20 (PACE 3 OF 6)
RADIOIDGICAL ENVIRONMENTAL MONTIDRING PROGRAM
SUMMARY
T U ELECTRIC - COMANCI1E PEAK STEAM ELECIRIC STATION JANUARY I TO DECEMBER 31.1996 Analysis and lower Limit Number of Medium of Pathway Total Number of All Indicator locations locaUon with H!nhest Mean Control locadon Nontouune Sampled ofAnalysts Detection Mean Name Mean (f)(2) Mean (t)(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direcuon Range Range Measurements Water-Surface Gamma (24)
Drinking (pCI/l)
K-40 . -(0/12) N/A N/A -(0/12) O Triuum (8) -
10375(4/4) NNW-0.1 10375(4/4) -(0/4) 0 (8800-13000) (8800-13000) --
Gross Beta (24) -
22(12/12) NNW-0.1 22(12/12) 13(12/12) 0 (15-34) (15-34) (6.0-30)
@ I-131 (24) -
-(0/12) . N/A' N/A -(0/ 191 0 (BY RADIOCliEMISMYI --
Fish Gamma (8)
(pCI/kg/ wet)
K-40 -
2978(4/4) NNE-8.0 3105(4/4) 3105(4/4) 0 (2700-3620) (2520-3500) (2520-3500)
(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 mtio of positive results to the number of samples analyzed for the parameter of interest, means are of positive results only.
l TABLE 20 i (PAGE 4 OF 6)
RADIOLOGICAL ENVIRONMEffrAL MONfiDRING PROGRAM
SUMMARY
T U ELECTRIC - COMANCIIE PEAK STEAM ELECTRIC STATION f JANUARY I TD DECEMBER 31.1996 Analysis and Imwer Limit Number of Medium of Pathway Total Number of All Indicator Locations Locauon with Hlahest Mean Control Imcauon Nonrouune ;
Sampled ofAnalysis Detection Mean Name Mean (0(2) Mean (0(2) Reported (Unit of Measuremect) Perfo*med (LLD) (1) Range Distance and Direcuon Range Range Measurements Shoreline Gamma (8)
Sediments .
(pCi/kg dry) Be-7 -
817(2/6) SE-5.3 817(2/2) -(0/2) 0 '
(766-868) (766-868) --
K-40 -
2518(6/6) N-9.9 6385(2/2) 6835(2/2) 0 (1510-3730) (2270-11400) (2270-11400)
Cs-137 -
61(1/6) SE-5.3 61(1/2) -(0/2) g Ra-226 -
861(2/6) N- 1.0 1050(1/2) 816(2/2) 0 (672-1050) --
(511-1120)
Th-228 -
186(5/6) N-9.9 390(2/2) 390(2/2) 0 (136-266) (126-653) (126-653)
Pb-212 -
197(6/6) N-9.9 403(2/2) 403(2/2) 0 (141-275) (131-674) (131-674)
Bi-214 -
328(6/6) N 9.9 402(2/2) 402(2/2) 0 (203-532) (206-598) (206-598)
Pb-214 +
316(6/6) N-9.9 422(2/2) 422(2/2) 0 (251-391) (214-629) (214-629) ;
i (1) IlD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological End.u..i.w..tal Monitoring Program.. Revision 1. November 1979.
(2) (0 to the ratio of positive results to the number of samples analyzed for the parameter of interest.
means are of posttsve results only.
[
I
TABLE 20 (PAGE 5 OF 6)
RADIOLOGICAL ENVIRONMENTAL MONfTORING PROGRAM
SUMMARY
T U ELECTRIC - COMANCllE PEAK STEAM ELECTRIC STA~ITON JANUARY I 'IO DECEMBER 31.1996 Analysts and Lower Limit Number of Medium of Pathway Total Number of All inrlicator Imcatjent f_ncation with Hashest Mean Control Incation Nonroutine Sampled ofAnalysis Detection Mean Name Mean (0(2) Mean (0(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direcuon Range Range Measurements Broadleaf Gamma (36)
Vegetation (pCl/kg wet) Be-7 -
3190(24/24) N- 1.45 3651(12/12) 1450(11/12) 0 (408-9330) (893-9330) (444-4950)
K-40 -
2875(24/24) SW-13.5 5360(12/12) 5360(12/12) 0 (929-5770) (2480-9670) (2480-9670) 1-131 -
-(0/24) NA NA -(0/12) 0 e
Cs-134 -
-(0/24) NA NA -(0/12) 'O ;
Cs-137 -
45.6(1/24) N- 1.45 45.6(1/24) -(0/12) 0 (45.6-45.6) (45.6-45.6) --
Th-228 -
80(3/24) SW-1.0 86(2/12) -(0/12) O (70-95) (77-95) --
t (1) LLD is lower limit of detection as denned 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 posittve results only.
I
_ . . . - . . . ~ ~ . - . . . . . ~ . . - - -
[
TABLE 20 (PAGE 6 OF 6)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM
SUMMARY
T U ELECTRIC - COMANCHE PEAK STEAM EI.ECTRIC STAT 10N JANUARY I TO DECEMBER 31.1996 ?
Analysts and lower Lamit Number of ?
Medium of Pathway Total Number of All Indicator Imcations location with filahest Mean Control Imcation Nontoutine '
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 Food Producta Gamma (11) ,
Ipcl/kg wet) ,
Be-7 -
-(0/8) NA NA -(0/3) 0 ,
i K-40 -
1907(8/8) ENE-9.0 2660(l/1) 1571(3/3) o (898-2660) --
(S73-2830) l-131 -
-(0/8) NA NA .(0/3) 0 Cs-134 .
-(0/8) NA NA .(0/3) 0 Cs-137 -
-(0/8) NA NA .(0/3) 0 (1) LLD le lower limit of detection as denned and required in USNRC Branch Technical Position on an Acceptable Radiological Environmental Monitoring Program . Revision 1. November 1979. ;
(2) (0 to the ratio of poestive results to the number of samples analyzed for the parameter of interest.
means are of poettive results only.
l
- _ , . _ _ . _ _ . _ _ . _ . . . . . _ . . .m_. _ . . _ _ _ _ . _ . _ _ _ _ _ . _ _ _ _ _ . _ _ _ . . _ _ _ _ _ . _ . . . _ . _ _ _ _ _ . _ _ .
., ,a _ a--
- 4 = - -
i l
i APPENDIX A CROSS-CHECK PROGRAMS A-1
EPA INTERLABORATORY COMPARISON PROGRAM 1996 Environmental Collection Teledyne Brown Date Media Nuclide EPA Result (a) Enctneering Resultib) Deviation (c) 01/23/96 Water Sr 89 73.0 5.0 73.67 3.21 0.23 (
Sr-90 5.01 5.0 5.00 0.00 0.00 01/26/96 Water Gr-Alpha 12.1 5.0 19.00 1.00 2.39 (d)
Gr-Beta 7.0 5.0 7.13 0.21 0.05 ;
02/02/96 Water 1 131 67.0 1 7.0 71.67 3.06 1.15 03/08/96 Water H3 22002.0 2200.0 22000.00 0.00 0.00 04/16/96 Water Gr-Beta 166.9 25.0 160.00 0.00 -0.48 Sr 89 43.0 5.0 41.33 1 2.31 -0.58 Sr90 16.0 5.0 15.33 0.58 -0.23 Co-60 31.0 5.0 31.67 1.15 0.23 Cs 134 46.0 5.0 42.33 1.53 -1.27 Cs- 137 50.0 5.0 52.33 1.53 0.81 Gr Alpha 74.8 t 18.7 63.67 2.89 -1.03 Ra 226 3.0 0.5 3.40 0.00 1.39 Ra 228 5.01 1.3 3.63 0.61 -1.82 06/07/96 Water Co 60 99.0 5.0 99.00 1.73 0.00 Zn 65 300.0 30.0 309.33 2.08 0.54 Cs.134 79.0 5.0 69.67 1.53 -3.23 (e)
Cs 137 197.0 i 10.0 202.00 2.65 0.87 Ba 133 745.0t 75.0 711.00 1 71.42 -0.79 OG/21/96 Water Ra 226 4.92 0.7 5.50 0.26 1.48 Ra 228 9.0 2.3 9.73 0.46 0.55 07/12/96 Water Sr 89 25.0 5.0 22.67 i 1.53 -0.81 i Sr-90 12.0 1 5.0 12.33 1 1.15 0.12 l l
07/19/96 Water Gr Alpha 24.4 6.1 22.67 1 0.58 -0.49 Gr Beta 44.8 5.0 45.33 2.08 0.18 08/09/96 Water H-3 10879.0 1088.0 9800.00 346.41 -1.72 09/27/96 Water Ra 226 14.0 1 2.1 14.00 1 1.00 0.00 i Ra 228 4.7 t 1.2 6.20 i 0.50 2.17 (f) l 10/02/96 Water I 131 27.0 t 6.0 26.33 2.31 -0.19 A-2
EPA INTERLABORATORY COMPARISON PROGRAM 1996 Environmental Collecuon Teledyne Brown Date Media Nuclide EPA Result (a) Engineering Resultib) Deviation (c) 10/15/96 Water Gr-Alpha 59.1 14.8 55.671 5.03 -0.40 Ra 226 9.9 1 1.5 10.00 1 0.00 0.12 Ra 228 5.1 1 1.3 5.47 0.31 0.49 Gr Beta 111.8 1 16.8 110.0 0.00 -0.19 Sr 89 10.0 5.0 l 9.00 0.00 -0.35 !
Sr90 25.0 5.0 26.00 1.00 0.35 Co 60 15.0 5.0 14.67 1 1.53 -0.12 )
Cs 134 20.0 1 5.0 19.67 i 1.15 -0.12 Cs-137 30.0 5.0 29.33 1 1.15 -0.23 10/25/96 Water Gr-Alpha 10.3 5.0 9.03 0.72 -0.44 Gr Beta 34.6 5.0 39.67 0.58 1.76 11/08/96 Water Co-60 44.0 5.0 44.67 0.58 0.23 Zn 65 35.0 5.0 38.67 0.58 1.27 Cs 134 11.0 5.0 12.00 0.00 0.35 Cs 137 19.0 5.0 20.67 1.15 0.58 Ba 133 64.0 6.0 56.67 3.21 -2.12 (g) i 1
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 pCl for air particulate filters.
(b) Teledyne Results Average one sigma. Units are pCi/ liter for water and milk except K is in mg/ liter. Units are total pCl for air paruculate illters.
(c) Normaltzed devlauon from the known.
(dl The vartauon was due to self absorpuon properties of the EPA sample matrix. On future EPA water samples of this type, we will determine the overall alpha counting emclency by spiking ,
the matrix with Th 230 in accordance with their recent advisory. '
i le) To verify the cause for the deviation. a Cs-134 standard has been purchased. If the Cs 134 !
emetency is lower than the emclency at 604 kev and 795 kev. then rather than change those emclencies (which may be needed for other isotopes of comparable energies), the Cs 134 branching intensity shall be adjusted.
(f) Erroneously low cerium yields were obtained in back-extraction from HDEHP. Greater care to be taken during back extracuon. If this operation is incomplete. the cerium carrier yield becomes lower than the Ac 228 yield. The procedure had been revised to require add 100nal back-extractions for longer periods of ume to ensure that proper cerium carrier yields are obtained. The procedure is under review to determine if additional back-extracuons are required.
(g) An investigauon is being conducted: the results will be available shortly.
A-3
.2- . -- L.2 nm ANALYTICS CROSS CHECK COMPARISON PROGRAM 1996 Teledyne Brown Analytics Sample ID Media Nuclide Engineering Result (a) Result Ratio (b)
E0633-396 Water I-131 39i 5 36 2 1.08 "Il #11912 Cc-141 89 9 88 4 1.01 03/12/96 Cr-51 3301 30 322 16 1.02 Cs-134 53 1 5 58 3 0.91 Cs-137 65 i 7 64 1 3 1.02 Co-58 49 5 48 1 2 1.02 Mn 54 37 1 4 31 2 1.19 Fe-59 93 1 9 83 1 4 1.12 Zn-65 100 10 97 5 1.03 CO-60 81 8 76 i 4 1.07 1
l E0635 396 Milk 1131 16 6 13 1 1.23 71 #11914 Cc-141 240 20 234 12 1.03 03/12/96 Cr-51 880 90 858 43 1.03 Cs-134 150 20 154 8 0.97 Cs 137 180 20 170 9 1.06 Co 58 140 10 128 6 1.09 )
Mn 54 93 9 84 4 1.11 l Fe-59 250 30 223 11 1.12 l Zn 65 260 30 260 13 1.00 l Co-60 220 20 204 10 1.08 l E0636-396 Water H-3 2800 200 2982 149 0.94 T1#11913 03/12/96 E0746 396 Air Filter Gross Beta 150 10 144 i 7 1.04 T1s19220 l 06/19/96 l E0747 396 Air Filter Cc 141 500 50 400 20 1.25 71 #19221 Cr 51 1200 100 10481 52 1.15 06/19/96 Cs 134 3101 30 3101 16 1.00 Cs- 137 910 90 764 38 1.19 Co 58 210 20 1731 9 1.21 Mn 54 6901 70 559i 28 1.23 Fe-59 190 20 1441 7 1.32 Zn 65 140 ! 10 108i 5 1.30 Co-60 180 20 156 8 1.15 Footnotes:
(a) Teledyne Results - counting error is two standard deviations. Units are pC1/ liter for water and rnilk. For gamma results, if two standard deviations are less than 10% then a 10% error is reported. Units are total pC1 for air particulate filters.
(b) Rauo ofTeledyne Brown Engineering to Analytics results.
A-4
i 1
l l
1 I
i 1
1 l
APPENDIX B 1 SYNOPSIS OF ANALYTICAL PROCEDURES l
i i
l B-1
APPENDE B APPLICABLE PROCEDURES 1
NUMBER 'ITILE DATE PAGE ,
1 PRO-032-1 Determination of Gross Alpha 03/20/96 B-3 and/or Gross Beta in Water l Samples J
PRO-042-5 Determination of Gamma 04/24/93 B-5 Emitting Radioisotopes PRO-032-10 Determination of Gross Beta 03/01/87 B-7 l
in Air Particulate Filters '
PRO-032-11 Determination of Radiolodine 12/15/92 B-8 in Milk and Water Samples PRO-032-12 Determination of Radioiodine 12/15/92 B-9 in Vegetation Samples PRO-342-17 Environmental Thermolumi- 06/17/94 B-10 nescent Dosimetry (TLD)
PRO-032-35 Determination ofTritium in 03/16/96 B-11 Water by Uquid Scintillation B-2
i h isaroezs PRO-032-1 i
! DETERMINATION OF GROSS ALPHA l
AND/OR GROSS BETA l IN WATER SAMPLES l
i
1.0 INTRODUCTION
4 i
l The procedures described in this section are used to measure the overall radioactivity of water samples without identifying the radioactive species i
present. No chemical separation techniques are involved.
j One liter of the sample is evaporated on a hot plate. Different volumes i l 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 !
! I l through No. 54 filter paper before evaporation, removing particles greater than !
) 30 microns in size.
l After evaporating to a small volume in a beaker, the sample is rinsed into l a 2-inch diameter stainless steel planchet which is stamped with a concentric j ring pattern to distdbute residue evenly. Final evaporation to dryness takes i
] place under heat lamps. Samples which appear to be hygroscopic are dried 1
again under heat lampsjust prior to counting.
Residue mass is determined by weighing the planchet before and after mounting the sample. The planchet is counted for alpha and/or beta activity 4
i on an automauc proportional counter. Results are calculated using empirical l self-absorption curves which allow for the change in effective counting h efficiency caused by the residue mass.
- 2.0 DETECTION CAPABILITY j Detecuon capability depends upon the sample volume actually l B-3
f h YNE isomes PRO-032-1 l
j represented on the planchet, the background and the efBeiency of the counting instrument, and upon self-absorption of alpha and beta particles by the )
i mounted sample. Because the radioactive species are not identified, no decay l
corrections are made and the reported activity refers to the counting time.
i The minimum detectable level (MDL) for water samples is nominally 1.6 picocuries per liter for gross beta at the 4.66 sigma level (1.0 pCi/l at the 2.83 4 sigma level), assuming that I liter of sample is used and that 1/2 gram of
! sample residue is mounted on the planchet. 'Ihese figures are based upon a
- . nominal counting time of 50 minutes and upon representative values of 1 l l counting efficiency and background of 0.2 and 1.2 cpm, respectively. 'Ihe 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 1 liter of sample is I
used and 1/2 gram of sample residue is mounted on the planchet. These j
) figures are based upon a nominal 200 minute counting time and upon a representative efficiency of 0.02 and a background of 0.1 cpm.
j The MDL becomes significantly lower as the mount weight decreases j because of reduced self-absorpuon. 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 picoeuries per liter. 'Ihese values reflect a beta counting efDcfency of 0.38 and an alpha counting efficiency of 0.18.
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B-4
l h ismoess PRO-042-5 I
DETERMINATION OF GAMMA EMITTING RADIOISOTOPES i
4 Milk and Water a
A 1.0 liter Marinelli beaker is Biled with a representative aliquot of the
! sample ne sample is then counted for at least 1000 minutes with a shielded j
Ge(L1) detector coupled to a mini-computer-based data acquisition system j which performs pulse height analysis.
! Dried Solids Other Than Soils and Sediments l
I A large quantity of the sample is dried at a low temperature, less than i 100 C. As much as possible (up to the total sample) is loaded into a tared 1-
! liter Marinelli and weighed. The sample is then counted for at least 1000 l minutes with a shielded Ge(L1) detector coupled to a mini-computer-based data
- acquis!'Jon system which performs pulse height analysis.
j Fish j
As much as possible (up to the total sample) of the edible portion of the i
4 sample is loaded into a tared Marinelli and weighed. De 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 i analysis.
- i Soils and Sediments Soils and sediments are dried at a low temperature, less than 100*C.
l The soil or sediment is loaded fully into a tared. standard 300 cc container and i weighed. ne sample is then counted for at least six hours with a shielded i Ge(LI) detector coupled to a mini-computer-based data acquis!Uon system which perfonns pulse height analysis.
) Charcoal Cartridges (Air Iodine) 4
! Charcoal cartridges are counted up to five at a time, with one postuoned i on the face of a Ge(LI) detector and up to four on the side of the Ge(U) detector.
! Each Ge(L1) detector is calibrated for both posidons. he detection limit for I-l 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 j counted separately, posidoned on the face of the detector.
- Air Particulate i ne four or five (depending on the calendar month) air particulate filters i for a monthly composite for each field station are aligned one in front of j another and then counted for at least six hours with a shielded Ge(U) detector
. B-5 4
h ismwes PRO-042-5 coupled to a mini-computer-based data acquisition system which performs pulse height analysis.
A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak I with a library of peaks for isotope identificauon and then performs the 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 pC1/ volume or pC1/ mass:
RESULT = (S-B)/(2.22 t E V F DF)
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 representadve backgrounds on either side of the peak l
t = length of time in minutes the sample was counted j 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 = fracUonal gamma abundance (specific for each emitted gamma)
DF = decay factor from the collection to the counting date l
B-6
h iscnwes PRO-032-10 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-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.
Calculations of the results the two sigma error and the lower limit of de-tection (LLD), are performed as follows:
RESULT (pC1/m3) = ((S/'Il - (B/t))/(2.22 V E)
TWO SIGMA ERROR (pC1/m3) =
2((S/T2+(B/t 2)}1/2/(2.22 V E)
LLD (pC1/m3) = 4.66(B/t/T)1/2/(2.22 V E) l j where: S = Gross counts of sample including blank l B = Counts of blank i E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted
. V = Sample aliquot size (cubic meters) l 2.22 = dpm/pC1 B-7
M YNE ISO'IOPES PRO-032-11 DETERMINATION OF RADLOIODINE IN urm AND WATER SAMPLES
- .Two liters of sample are first equdit sted with stable iodide carrier. A batch 4
treatment with anion exchange resin is used to remove iodine from the sample.
The lodine 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 lodide into sodium bisulfite solution and is
- precipitated as palladium iodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. 'Ihe chemical 4
yield is corrected by measuring the stable iodide content of the milk or the j water with a specific lon electrode.
l Calcui&Uon of results, two sigma error and the lower limit of detection (LLD) in i
pCi/1. are performed as follows:
i j 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) 11D = 4.66(B/ At)1/2/(2.22 E V Y DF) where: N = total counts from sample (counts)
At = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collection to the counting date E = efTlciency of the counter for I-131, corrected for self absorption effects by the formula:
= EsleXP-0.0085M)/(exp-0.0085Ms)
Es = efDefency 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
- 1 PRO-032-12 ismum i
DETERMINATION OF RADIOIODINE IN VEGETATION SAMPLES i
BroadleafVegetation i
'. This procedure presents radiochemical methods for determining the I-131 acuvity in vegetation samples. Stable lodide carrier is first added to 25-100 grams of the chopped sample. The sample is then leached with sodium 2
hydroxide solution evaporated to dryness and fused in a muffle furnace. He
- melt is dissolved in water, filtered and treated with sodium hypochlorite ne i iodine is then reduced with hydroxylamine hydrochloride and is extracted into toluene.' It is then back-extracted as iodide into sodium bisulfite solution and
- is precipitated as palladium iodide. The precipitate is weighed for chemical l yield and is mounted on a nylon planchet for low level beta counting.
4 j Calculation of results, two sigma error and the lower limit of detection (LLD) in
- pC1/l. are performed as follows:
i RESULT = (N/ At-B)/(2.22 E V Y DF) l l
e
- IWO SIGMA ERROR =
2((N/At+B)/At)1/2/(2.22 E V Y DF) l
- LLD =
4.66(B/At)1/2/(2.22 E V Y DF) I i
- where: N = total counts from sample (counts) ;
At = counting time for sample (min)
B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay fai: tor 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)/(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 Pdl2 on the sample mount, mg B-9
. - - .. - _ - . - - - . _ .~. . - - - . - .- . -
%ETEDYNE PRO-342-17 ISOIOPES 2
f 4
ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY (TLD) i Teledyne Isotopes uses a CaSO4:Dy thermoluminescent dosimeter (TLD) which the company manufactures. his material has a high light output, neg- '
ligible thermally induced signal loss (fading), and negligible self dosing. The energy response cuIve (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 1
- Model 8300. One fourth of the rectangular TLD is heated at a time and the measured light emission (luminescence) is recorded. The TLD is then annealed 1
and exposed to a known Cs-137 dose; each area is then read again his pro- ,
vides a calibration of each area of each 'ILD after every field use. The transit controls are read in the same manner. 4 Calculation of results and the two sigma error in net milliRoetgen (mR) are !
performed as follows: i
, RESULT D= Ol+D 2+D 3+D4)/4 1
TWO SIGMA ERROR = 2(01-D)2+fD2-D)2+03-D)2+04-D)2)/3)1/2 where: D1 = the net mR of area 1 of the TLD, and similarly for j D2, D3, and D4 i
= 11 K/R1 - A 11 = the instrument reading of the field dose in area 1 i
K = the known exposure by the Cs-137 source R1 = the instrument reading due to the Cs-137 dose on area 1 4
A = average dose in mR. calculated in similar manner as above, of the transit control TLDs 4
L t
i B-10 i
4 D DYNEISCTIOPES PRO-032-35 b
DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION 4
Ten milliliters of water is added to 10 ml of11guld 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:
4 RESULT (pCi/l) = (N-B)/(2.22 V E)
'IWO SIGMA ERROR (pCi/1) = 2((N + B)/At)1/2/(2.22 V E) l 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 = efficiency of the detector At = counting time for the sample B-11
APPENDIX C EXCEPTIONS TO THE 1996 REMP C-1
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APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1996 ,
DATE OF REASONS FOR LOSS /
LOCATION DESCRIFrlON SAMPLING EXCEFFION S/SSW-1.2 Air Filter 11/26-12/03 Very light deposit on filter E-3.5 Food Product 01/30/96 Sample not available SW-12.7 Food Product 01/30/96 Sampic not available E-3.5 Food Product 02/27/96 Sample not available SW- 12.7 Food Product 02/27/96 Sample not available E-3.5 Food Product 03/26/96 Sample not available SW- 12.7 Food Product 03/26/96 Sample not available SW- 12.7 Food Product 04/30/96 Sample not available SW- 12.7 Food Product 08/27/96 Sample not available l SW- 12.7 Food Product 10/29/96 Sample not available E 3.5 Food Product 11/26/96 Sample not available SW- 12.7 Food Product 11/26/96 Sample not available E-3.5 Food Product 12/31/96 Sample not available SW- 12.7 Food Product 12/31/96 Sample not available NNW- 1.35 TLD (Qtrly) 10/02/96-01/03/97 Missing from case NW-9.9 TLD (Qtrly) 10/02/96-01/03/97 Missing due to i construction j NW-9.9 TLD (Annual) 01/03/96-01/02/97 Missing due to construction I
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1 APPENDIX D l EXCEEDED REPORTING LEVELS l 4
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l APPENDIX D EXCEEDED REPORTING LEVELS l
1996 None of the analytical measurements exceeded any notification level.
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l APPENDIX E LAND USE CENSUS E-1
LAND USE CENSUS VERIFICATION SHEET Date Completed: 29 July 1996 Performed By: 'Edwin T. Floyd Print / Signature
[
Receptors with calculated doses increasing by 20%:
YES@
Specific Locations: None Radiological Environmental Monitoring Program Changes Implemented:
YES/NOh Comments: No changes were required.
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Reviewed By: Ray Ramsour , , t Date: 29 July 1996 Pnnt/S' ture Approved By: fy ,
Date: 8/// l99lo i Ra!iation Protection Manager l
l RPI7141 Rev.O Page1of1
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, TUELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION 1
LAND USE CENSUS l
1996 Performed by, [4 Date 7 ' 2 9'- 76 Reviewed by Date ? /9.ir.
/~
COMANCHE PEAK STEAM ELECTRIC STATION P.O. Bos 1002 Glen Rose. Texas 76043-1002
_. . . _ _ _ _ . _ . . . _ . _ - . _ _ _ . . . _ _ _ . _ m. _ _ . _ _ _ _ _ _ , . _ . - _ _ _ . . _ . _ . . _ _ . _ _ _ . _
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l July 29,1996 l
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COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS )
l 1996 l l
i 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 12,13 and 14, l
l- 1996 and includes the following items:- i
- 1. Evaluation of the 1996 Land Use Census
- 2. Nearest Resident by Sector, Distance, X/Q and D/Q
- 3. Nearest Garden by Sector, Distance and D/Q o 4. Nearest Milk Animal by Sector, Distance and D/Q
- 5. Population by Sector and Distance
- 6. Environmental Sample Locations Table
- 7. Environmentai Monitoring Locations Map- 2 Mile Radius
- 8. Environmental Monitoring Locations Map- 20 Mile Radius
- 9. 5 Mile Sector and Road Map with Field Data *
- The original map is vaulted along with this census, copies of this census will not contain a copy of this map unless specifically requested.. ;
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Evaluation of the 1996 Land Use Census The results of the 1996 Land Use Census were reviewed for impact on the Radiological ;
Environmental Monitoring Program (REMP). The specific areas reviewed, that could be atT(:cted by changes found in the land use census, were the sampling requirernents for milk, broadleaf vegetation and food products.
Reviewing the milk sampling requirements from the ODCM Table 3.12-1 requires that samples are to be obtained from milking animals in three locations within a 5 km distance having the highest potential dose. If none are available, samples are acceptable from milking animals in locations 5 to 8 km distance where doses are calculated to be greater than 1 mrem per year. A sample is also required at a control location. There are currently no identified milking animals (cow or goat) within the specified distances. Currently the only location where milk samples are collected is at a control l location (SW - 14 5).
Since not all milk samples are available, the broadleaf vegetation sampling specified in ODCM Table 3.12-1 is being performed. Broadleaf sample requirements are such the aamples of broadleaf vegetation are to be collected from each of two orTsite locations of the highest predicted annual j average D/Q if milk sampling is not performed at all the required locations. Currently, broadleaf i 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 I i
vegetation is available and D/Q is high. Therefore, no changes to the broadleaf sampling program i are required.
Food product sample requirements ofODCM Table 3.12-1 requires that one sample of each principal l class of food product be collected from any area that is irrigated with water in which liquid plant I 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 j location (SW - 12.7) No changes are required in the food product program.
The 1996 Land Use Census did not identify any locations that are available for sampling and that l
would yield a calculated dose 20% greater than at the current sampling locations.
2 l
i Calculated values for the associated X/Q and D/Q values for each controlling receptor location and l l
pathway are included along with the receptor distances in the data tabas 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 l is 3.30E-6, tritium X/Q is 4.36E-6, and the D/Q value is 3.34 E-8. All these values are conservative i
based on the 1996 land use census data and therefore no changes are required in the dose calculation parameters as verified by the field data. ,
l
- X/Q units are Sec/ cubic meter
- D/Q units are mverse square meters I
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Nearest Resident by Sector, Distance, X/Q and D/Q Sector Distance (Miles) X/O D/O
'N 2.2 9.28E-07 5 32E-09 NNE 2.2 5.58E-07 2.90E-09 NE 2.2 3.92E-07 1.42E-09 ENE 2.4 2.58E-07 7.08E-10 E 2.4 3.02E-07 6.62E-10 ESE 2.0 4.7E47 1.20E-09 SE 1.9 8.3 E-07 3.40E-09 SSE 1.5 1.1E-06 6.60E-09 S 1.5 8.5 E-07 5.20E-09 SSW 3.9 1.06E-07 3.62E-10 SW l.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 Note: The annual average X/Q used for dose calculations is 3.30E-06 sec/ cubic meter.
The Tritium value X/Q used for dose calculations is 4.36E-06 secicubic meter.
The annual average D/Q used for dose calculations is 3.34E-08 inverse square meters.
4 !
l Nearest Garden by Sector, Distance and D/Q l
Sector Distance (Miles) D/O N 3.4 2.90E-09 NNE 2.5 2.30E-09 NE None None ENE None None E 3.5 2.70E-10 ESE 3.3 3.96E-10 SE 2.4 1.84E-09 !
SSE None None S None None SSW None None SW 1.5 2.5E-09 WSW None None W 3.3 4.42E-10 WNW 3.8 5.68E-10 NTV None None NhTV None None 5
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Nearest Milk Animal by Sector, Distance and D/Q ;
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Sector Distance (Miles) D/O N None None NNE None None l
NE None None ENE None None E None None l
ESE None None l
SE None None SSE None None j S None None SSW None None SW None None WSW None None W None None WNW None None NW None None NNW None 'e _
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4 Population by Sector and Distance J
Sector 0-1 1-2 2-3 3-4 4-5 Total t
i N - -
5 29 80 114 i NNE - -
8 67 16 91 NE - -
56 59 226 341 ENE - -
70 8 21 99 E - -
56 163 32 251 1
ESE -
3 5 96 120 224 SE -
19 69 43 35 166 I SSE -
37 59 16 2000 2112 i
S -
40 19 40 112 211 '
SSVV - - -
3 40 43 SW -
67 5 43 32 147 WSW -
192 5 11 3 211 W -
24 8 21 8 61 WNW - - -
35 64 99 NW - -
3 - -
3 NNW - - -
45 16 61 TOTAL -
382 368 679 2805 4234 Based on an average of 2.66 residents per house. This average was obtained from North Central Texas Council of Governments for Hood and Somenell Counties and is derived from an average residents per house of 2.57 and 2.74, respectively.
7
Environmental Sample Locations Table Sampling Point Location Sample Typ:*
Al N-1.45 (Squaw Creek Park) A A2 . N-9.4 (Granbury) A A3 E-3.5 (Children's Home) A A4 SSE-4.5 (Glen Rose) A A5 - S/SSW-1.2 A A6- SW-12.3 (CONTROL) A A7 SW/WSW-0.95 A A8 NW-1.0 A R1 N-1.45 (Squaw Creek Park) R R2 N-4.4 R R3 N-6. 5 R R4 N-9.4 (Granbury) R R5 NNE-1 I R R6 NNE-5.65 R I 1
R7 hT- 1.7 R. );
R8 NE-4.8 R R9 ENE-2.5 R RIO ENE-5.0 R Ril E-0.5 R R12 E- 1.9 R R13 E-3.5 (Children's Home) R R14'- E-4.2 R R15 ESE-1.4 R R16 ES E. 4.7 R l R17 S E- 1.3 R ;
Environmental Sample Locations Table (cont.)
Sampling Point Location Sample Type
- R19 SE-4.6 R R20 SSE-1.3 R R21 SSE-4.4 (Glen Rose) R R22 SSE-4.5 (Glen Rose) R R23 S- 1. 5 R R24 S-4.2 R R25 SSW- 1.1 R R26 SSW-4.4 (State Park) R R27 SW-0.9 R l R28 SW-4.3 (Girl Scout Camp) R R29 SW-12.3 (CONTROL) R R30 WSW-1.0 R R31 WSW-5.35 R R32 WSW-7.0 (CONTROL) R 1 R33 W-1.0 R R34 W-2.0 R R35 W-5.5 R R36 WNW-1.0 R R37 WNW-5.0 R R38 WNW-6.7 R R39 NTV- 1.0 R R40 NTV-5.7 R R41 NW-9.9 (Tolar) R R42 NNW-1.3 5 R R43 NNW-4.6 R 9
Environmental Sample Locations Table (cont.)
- Sampling Point Location Sample Type
- SW1 N-1.5 (Squaw Creek Reservoir Marina) SW SW2 N-9.9 (Lake Granbury) SW/DW' SW3 N-19.3 (CONTROL-Brazos River) SW SW4 NE-7.4 (Lake Granbury) SW SW5 ESE-1.4 (Squaw Creek Reservoir) SW2 SW6 NNW-0.1 (Squaw Creek Reservoir) SW/DW 3 GW1 W-1.2 (NOSF Potable Water) GW GW2 WSW-0.1 (Plant Potable Water) GW3d GW3 SSE-4.6 (Glen Rose) GWt GW4 N-9.8 (Granbuy) GWd GW5 N-1.45 (Squaw Creek Park) GW4 SSI NNE-1.0 (Squaw Creek Reservoir) SS SS2 . N-9.9 (Lake Granbug) SS SS3- NE-7.4 (Lake Granbury) SS SS4 SE-5.3 (Squaw Creek) SS M4 SW-14.5 (CONTROL) M l F1 ENE-2.0 (Squaw Creek Reservoir) F F2 NNE-8.0 (Lake Granbury) F i
FPl ENE-9.0 (Leonard Bros. Pecan Farm) FP '
FPS SW-12.7 (CONTROL) FP FP6 E-3.5 (Happy Hill Farm) FP 10
1 Environmental Sample Locations Table (cont.)
- Sampling Point Location Sample Type
- 1
- BL1 N-1.45 BL i BL2 SW- 1.0 BL' BL3 SW-13.5 (CONTROL) BL 8 4
4 I
, \
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- Sample Type : A - Air Sample; R - Direct Radiation; SW - Surface Water; DW - Drinking Water i GW - Ground Water; SS - Shoreline Sediments; M - Milk; F - Fish; j FP - Food Products; BL - Broadleaf Vegetation 1
i 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 7 these supplies is sampled. These samples are not required for compliance with l Radiological Efiluent Control 3/4.12.1, Table 3.12-1, because they are not affected
} by plant discharges.
I
') This sample (location SW6) is representative of discharges from Squaw Creek ;
i Reservoir both down Squaw Creek and to Lake Granbury via the return line to Lake j j' Granbury.
j 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 j possible sources of water are sampled.
l 4) Ground water supplies in the plant site area are not affected by plant lign; : effluents
! as discussed in CPSES FSAR Section 2.4.13 and are therefore not re.,wred to be
- monitored 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 rcilk samples are unavailable from any location.
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