Text

CPSES Radiological Environmental Monitoring Program 1993 Annual Rept. W/940428 Ltr
	ML20029C994
Person / Time
Site:	Comanche Peak
Issue date:	12/31/1993
From:	Floyd E, Kay D, Robert Prince; TEXAS UTILITIES ELECTRIC CO. (TU ELECTRIC)
To:	; NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM)
References
	TXX-94111, NUDOCS 9405030187
	Download: ML20029C994 (106)
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= Log # TXX-94111

""'""" 7 File # 10300

,_. _ _- 10160 clo r r 916 (6) clo Ref. # 10CFR50 App. I 7UELECTRIC William J. Cahill, Jr.

Group Vice President Apik1 S0e 50$b U. S. Nuclear Regulatory Commission Attn: Document Control Room 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 1993 i Gentlemen:

Enclosed is one (1) copy of the Annual Radiological Environmental Operating -

Report for the CPSES Radiological Environmental Monitoring Program. This report is submitted pursuant to Section 6.9.1.3 of the CPSES Units 1 and 2 Technical Specifications. The report covers the period from January 1, 1993, through December 31, 1993, and summarizes the results of measurements and analysis of data obtained f rom samples collected during this interval.

- - If there are any questions regarding this report, contact Connie Wilkerson at (214) 812-8819 or Doug Kay at (817) 897-5204.

Sincerely, William J. Cahill, Jr.

By: O D. R. Woodlan Docket Licensing Manager p.

CLW/grp Enclosure

, c- Mr. L. J. Callan, Region IV w/ enclosure Resident Inspectors, CPSES w/ enclosure (1)

Mr . T. A. Bergman, NRR (clo) 9405030107 931231 1 PDR ADOCK 05000445 L i

* \' L v, g 400 N. Olive street LB. 81 Dallas. Texas 75201

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TUELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION DI J

) RADIOLOGICAL ENVIRONMENTAL q

) MONITORING PROGRAM J

1993 ANNUAL REPORT D

D D

j REVIEW / APPROVAL !

l Reviewed by: C '#

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E. T. Floyd Date Senior Radiation Protection Technician Reviewed by: cua[aA d , 4-11-'f 4 D. c.0xay J Date Radiation Protection Supervisor D

Approved by: A ww< /-/3- f/

R. J. Prince Date Radiation Protection Manager t - - .,- - -

TABLE OF CONTENTS SECTION PAGE I. INIRODUCIlON. . . . . . . .. . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 A Site an d Stati on De scrip tion ................................................................ 2 a Objectives and Overview of the............................................................ 2 ,

CPSES Monitoring Program {

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II. PRO G RAM D ES C RI PTI O N . .. .. . .. .. .. .. ... .. .. .... .. .. ... .... . .... .. ..... .... .. .... ... .. .. .. .. .. ..... .... .. 6 j A Sa m ple Lo c atio n s ...... .... .. ....... .. ... ............ ........... .. .. .... .. .. ... .. .... . ... .. ... ...... 7 1

4 R Sampling Me thods and Proced ures . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .. . . . . . . . . . . . . . . 8 1

1. Dimct Radiation... . . .. . . .. . . . . . . . ... . . . . . ... . . . . . .. . .. . . . . . . . . . .. .. . . .. .. . . ... . . . . .. . . 8

2. Air Particulates and Air lodine ..................... ........ ........... 9 l 1,

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3. Milk..............................................................................................9 i

4. Water............................................................................................9

5. Fish............................................................................................I1

6. Sh orelin e Sedim en t ...... .................. .................................... 1 2

7. Food Products. . . . . . .. .. . . . . ... . . . ... . . . . .. . ... . . . ... ... . . .. . .. . . .. . . .. .. . . . . . . .. . . . .. 1 2

8. B roadleaf Vege tation .................. ....... .................. .... ......... ... 1 2 C Interlaboratory Comparison Program ......................................... 13 l D. Deficiencies in the Sample Program........................................... 13 III.

SUMMARY

AND DISCUSSION OF 1993 ANALYTICAL RESULTS......15 A Direct Radia tion... . . . . . .. ..... . .... .. .. ... ... . .. ... ... ... . . .. . ... ...... .. .. . . .. ... . . . .. . . . .. . . .. .. 1 6 H Air Particulates and Air lodin e ........................... ......................... 18 C Milk.........................................................................................................19 D. Water........................................................................................................I9 E. Fish...........................................................................................................21 11

F. Sh o relin e Se d im e n ts ..... ..... ...... .. . . ........ ... . . ...... ... . .. .... ...... ... 2 1 G. Food Pmd ucts. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 2 2

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) H. B ro adie af Ve de tatio n ... .. . ...... ...... ...... ... ............ .. . ....... ... . .... ..... . 2 2

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, IV. CO NC LU SIO NS . . .. .... . ... . ....... .. .......... .. . . ...........................24 3 V. hem <ENCES....... ...............................................................26 i

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) VI. DATATABLES.... .. . ... . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . .....................28 o;

s, APPENDICES U

APPENDIX A EPA Cros s-C he ck Pro gram . . ...... .... ....... .. ....... ......... ............ ...A- 1 i

APPENDIX B Synopsis of Analytical Proced ures .. . ... .. ..... . .. ..... .. .............B- 1 J{ -

[) APPENDIX C Exceptions to the 1993 REMP. . .. . .. .. .. . . .... . .. . . . .. .. ... . . .. ... .. .. .. . .C- 1 i

APPENDIX D Exceed ed Reporting Levels ...... ..... ..... .............. .......... .... .... D- 1

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^) APPENDIX E I;tnd Use Census. . .. . . . . . . . . . . . . . . .. .. . . . . .. . . . . . ... . . . . .. . .. . . . . . . . . .. . .. . . . . . . . .. . . .. . . . . E - 1 j

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1 LIST OF TABLES TABLE TITLE PAGE l1 i

1 C PSES Radiological Environmental ......................................................... 2 9 )

Monitoring Program 2 Direct Radiation -- Thermoluminescent Dos 1 metry........ ................ 33 3 Concentrations of Iodine-131 in Filtered A1r................................ ..... 3 5 4 Concentrations of Gross Beta Emitters in Air Particulates............ 38 5 Concentrations of Gamma Emitters in Air Particulate Filters...... 41 6 Concentration s of Iodine- 131 in Milk .................................................... 4 3 7 Coneentrations of Gamma Emitters in Milk ........................................ 4 4 8 Concentrations of Gamma Emitters in Groundwater........ .............. 4 5 9 Concentrations of Tritium in Groundwater.......................................... 47 10 Concentrations of Gross Beta in Water-Surface / Drinking.............. 49 11 Concentrations of Gamma Emitters in Water-Surface / Drinking 50 12 Concentrations of Iodine-131 in Water-Surface / Drinking.... ........ 52 13 Concentrations of Tritium in Water-Surface / Drinking.................... 53 14 Concentrations of Gamma Emitters in Surface Water...................... 54 15 Concentrations of Tritium in Surface Water ........................................ 5 6 l 16 Conccntrations of Gamma Emitters in Fish ......................................... 5 7 17 Concentrations of Gamma Emitters in Sediment.............................. 58 18 Concentrations of Gamma Emitters in Food Products..................... 59 19 Concentrations of Gamma Emitters in Broadleaf Vegetation........ 60 20 Radiological Enviroranental Monitoring Program Summary -

January 1 to December 3 1, 1 9 9 3 .. .. .. .. . . ... .. .. .. .. . .. .. . . .. .. . .. .. . . . .. .. . . .. .. ... . . . . .. .. 6 2 iv

LIST OF FIGURES FIGURE TITLE EAQE ]

l 1 Radiological Environmental Monitoring Locations............................ 31 l 1

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INTRODUCTION l

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I. INTRODUCTION The Radiological Environmental Monitoring Program for the Comanche Peak Steam Electric Station was conducted under contract with T U Electric. This report covers the period from January 1,1993 through December 31,1993 and summarizes the results of measurements and analy-ses of data obtained from samples collected during this interval.

A. Site and Station Description Comanche Peak Steam Electric Station (CPSES) consists of two PWR units, each designed to operate at a power level of about 1150 megawatts (electrical). The station is located on Squaw Creek Reservoir in Somervell County about forty miles southwest of Fort Worth, Texas. Unit I received a low power operating license February 8,1990 and achieved initial criticality on April 3,1990. A full power license for Unit I was issued on April 17,1990, and l 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.

Il Objectives and Overview of the CPSES Monitoring Program The United States Nuclear Regulatory Commission (USNRC) regu-lations require that nuclear power plants be designed, constructed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA) (10 CFR 50.34a). To assure that these criteria are met, each license autho-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 l

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release limits are not exceeded. However, as a precaution against unexpected and undefined processes which might allow undue ac-

,. cumulation of radioactivity in any sector of the environment, a pro-gram for monitorir.'g the plant environs is also included.

Sampling locations were selected on the basis of local ecology, me-teorology, physical characteristics of the region, and demographic and land use features of the site vicinity. The radiological environ-mental monitoring program was designed on the basis of the USNRC Branch Technical Position on radiological environmental monitoring issued by the Radiological Assessment Branch, Revision 1 (November 1979)(1), the CPSES Technical Specifications (4) and the CPSES Offsite Dose Calculation Manual (ODCM)(5),

In 1993, 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 cmitters, and iodine-131; the measurement of tritium and gamma emitters in surface water; the measurement of tritium and gamma emitters in groundwater; the measurement of gross beta, tritium, I iodine-131 and gamma emitters in drinking water; the determi-I nation of gamma emitters and iodine-131 in milk; and the mea-surement of gamma emitters in food products and gamma emitters and lodine-131 in broadleaf vegetation. Samples were collected by CPSES Environmental Personnel. Sample analyses were performed by Teledyne Isotopes.

The regulations governing the quantities of radioactivity in reactor effluents allow nuclear power plants to contribute, at most, only a 1

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l few percent increase above normal background radioactivity.

i Background levels at any one location are not constant but vary with time as they are influenced by external events such as c' osmic ray bombardment, weapons test fallout, and seasonal variations. These levels also can vary spatially within relatively short. distances re-flecting variations in geological composition. To _ differentiate be-tween background radiation levels and increases resulting from op-eration of CPSES, the radiological surveys of the plant environs are divided into preoperational and operational phases. The preopera-tional phase of the program permits a general characterization of the radiation levels and concentrations prevailing prior to plant op-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-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.

2. Identify potentially important pathways to be monitored af-i ter the plant is in operation. j

3. Measure background levels and their variations along po- f; tentially important pathways in the area surrounding the i

plant. I l

4. Provide baseline data for statistical comparison with future )

operational analytical results.

The operational Radiological Environmental Monitoring Program is 1

i conducted to:

1. Verify that measurable concentrations of radioactive mate- .

rials and levels of radiation are not higher than expected on the basis of the effluent measurements and modeling of the environmental exposure pathways.

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2. Verify the effectiveness of in-plant measures used for con-trolling the release of radioactive materials.

3. Identify changes in the use of areas at and beyond the site boundary that may impact the principal pathways of expo-sure.

This report documents the fourth year of operational measurements and is submitted in accordance with the requirements of the CPSES Offsite. Dose Calculation Manual. Part I, Administrative Control 6.9.1.3.

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PROGRAM DESCRIPTIONS 6

, .i II. . . PROGRAM DESCRIPTION A Samole Locations Seventy-four locations within a radius of 20 miles from the CPSES-site were included in the monitoring program for 1993. The num-ber and location of monitoring points were determined by consid -

ering the locations where the highe . off-site environmental con-centrations have been predicted from plant ' effluent source terms, site hydrology, and site meteorological conditions. Other factors considered were applicable regulations, population distribution, ease of access to sampling stations, availability of samples at desired 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.

The results of the 1993 Land Use Census are provided in Appendix E.

The Radiological Environmental Monitoring Program for Comanche -

Peak is summarized in Table 1. Figure 1 shows the locations of the various sampling points.

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l R Samoling Methods and Procedures ,

To derive meaningful and useful data from the Radiological Environmental Monitoring Program, sampling methods 'and proce- .

I dures are required which will provide samples representative of 1 potential pathways of the area. The methods and procedures used for each pathway monitored are described below.

1. Direct Radiation Thermoluminescent dosimeters (TLDs) were used to de-termine the direct (ambient) radiation levels at monitoring points. Sampling locations were chosen according to the criteria given in the USNRC Branch Technical Position on Radiological Monitoring (Revision 1 November 1979)(1)-

The area around the station was divided into 16 radial sec-tors of 22-1/2 degrees each. TLDs were placed in all sec-tors. Thermoluminescent dosimeters were located in two rings around the station. An inner ring was located at the i

site boundary and an outer ring was located at a distance of l I

4 to 6 miles from the station. Eleven additional TLDs were located at points of special interest, including two control ~

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locations. For routine TLD measurements, two dosimeters of CaSO4 :Dy in teflon cards were deployed at each selected q location. One set of dosimeters was exchanged on a quar-terly basis and the second set was exchanged on an annual )

basis. Additional sets of dosimeters were shipped with each exchange cycle to serve as in-transit controls.

Individual dosimeters were calibrated by exposure to an accurately known radiation field from a calibrated Cs-137 8

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source. 1 1

2. Air Particulates and Air Iodine i

Air particulate and air lodine samples were collected from ]

the eight locations described in Table 1.

Each air particulate sample was collected by drawing air through a 47 millimeter diameter glass-fiber filter. Air iodine was collected by drawing air through. a TEDA im-pregnated charcoal cartridge which was connected 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 1

and were composited quarterly for gamma spectrometry analysis. Charcoal cartridges were analyzed for iodine-131.

3. Milk Milk samples were collected by CPSES staff monthly for ,

the period January through April. May through ' October.

samples were collected semimonthly, except for June when three samples were collected. November ' and j i

December samples were collected ' monthly. There was .I I

one milk sampling location (SW-13.5). Upon arrival at the j laboratory, the milk samples were promptly analyzed for 1

gamma emitters and for l-t 31 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-9

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1.5 and NE-7.4). Location N-1.5 provides samples repre-sentative of Squaw Creek Reservoir surface water at a lo -

cation beyond significant influence of the plant discharge.

Location ESE-1.4 provides samples representative of dis- !

l charges from Squaw Creek Reservoir downstream to j Squaw Creek and to Lake Granbury via the return line.

Location NE-7.4 provides samples of Lake Granbury. surface .

l water down stream of the discharge from the return line l

from Squaw Creek Reservoir. A control sample is obtained from the Brazos River, upstream of Lake Graubury at loca-tion N-19.3.

Surface water samples from Squaw Creek Reservoir loca-tions were collected weekly and composited for monthly gamma isotopic analysis. Samples from Lake Granbury lo-cations were collected monthly and analyzed by gamma spectroscopy. All surface water samples were also com-posited quarterly by location for tritium analysis.

Surface-drinking water was collected at two locations (N- -

9.9 and NNW-0.1). Samples of Squaw Creek Reservoir wa-ter were collected at location NNW-0.1. Samples from this location were analyzed pursuant to the drinking water requirements even though Squaw Creek Reservior is not used as a potable water supply. Location N-9.9 was used to sample surface water from Lake Granbury near the intake of the City of Granbury potable water plant.

L Surface-drinking water samples were collected weekly and composited for iodine-131 analysis every two weeks and j

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gamma isotopic and gross beta analyses monthly. Tritium analyses were performed quarterly.

There are five groundwater locations (SSE-4.6, W-1.2, l l

WSW-0.1, N-1.45 and N-9.8). ODCM Table 3.1, Note (5) '

states that Jroundwater supplies in the site area are not affected by plant effluents and are sampled only to provide confirmation that groundwater is not affected by plant dis-charges.

Groundwater samples were collected quarterly. Gamma isotopic and tritium analyses were performed by location. j

5. Elsh Fish samples were collected at two locations for the 1993 program. An area 2.0 miles east-northeast of the site. in Squaw Creek Reservoir was chosen as the indicator loca-tion, and a location at Lake Granbury (NNE-8) was chosen as a control location. Fish sampling was conducted in June and November for Station ENE-2.0 and June and October for the control station..

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.

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6. Shoreline Sediment Shoreline sediment samples were collected in January and July from Squaw Creek Reservoir at location NNE-1.0. -l Samples were also collected from Lake Granbury at the control location N-9.9, and location NE-7.4. which is downstream of the discharge of the return line from Squaw Creek Reservlor. CPSES staff collected the j sediment samples and shipped them to the laboratory for analysis by gamma spectrometry.

7. Food Products During the period of May through October,12 samples were collected from two indicator sampling locations '(E-4.2. ENE-9.0) and from the control station (SW-12.2) A total of 8 different types of food products were collected during this sampling period. Food product samples were a

collected by the CPSES staff and shipped to the laboratory where they were analyzed for gamma emitters. -!

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8. Broadleaf Vegetation i Broadleaf vegetation was collected from the control loca-tion (SW-13.5) and two indicator stations (N-1.45 and SW- ,

1.0) near the site boundary. Collection of broadleaf vege-tation started in April 1993. Broadleaf samples consisted 1

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of available tree leaves; if tree leaves were unavailable, l

native grasses and weeds were substituted.

Gamma isotopic and iodine-131 analyses were performed for all broadleaf vegetation samples.

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> C. Interlaboratory Comparison Program To demonstrate that the results of the environmental analyses are l 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 Isotopes participates in the environmental sample cross-check program conducted by the U.S. Environmental Protection Agency (EPA),

i 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- l tories measure the concentrations of specified radjonuclides 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 instru-ments or procedures used. '

The results of Teledyne Isotopes' participation in the U.S. . EPA I

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Interlaboratory Comparison Program for 1993 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 .i from the sampling schedule of Table 3.12.1 of the ODCM shall be reported in the annual environmental monitoring report. - During the year 1993, one deviation in sampling occurred in the air 13

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sampling requirements in that the air sample pump was not started

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by the field technician prior to leaving the sample station.

Therefore, the air sample for the indicator location E-3.5 for the 1

-j week of August 3 through August 10 was not collected. This deviation was due to personnel error and corrective actions have been taken to ensure that no further deviations of this type occur in the future. There were no other deficiencies during 1993.

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SUMMARY

AND DISCUSSION OF 1993 ANALYTICAL RESULTS I

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. . III.

SUMMARY

AND DISCUSSION OF 1993 ANALYTICAL RESULTS Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The proce-dures and specifications followed in the laboratories for these analyses are as required in the Teledyne Isotopes Quality Assurance Manual IWL-0032-395 ;

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and are detailed in Teledyne Isotopes Analytical Procedures Manual. A syn- i opsis of analytical procedures is contained in Appendix B of this report.

1 Radiological analyses of environmental media characteristically ap-

). proach and frequently fall below the. detection limits of state-of-the-art mea-surement methods as discussed in NCRP Report No. 50(2). The use of"<" in k-the data tables symbolizes that the _ result is less than the lower limit of de-tection (LLD) as defined in Appendix B. Not Detected, "ND", is used period-ically in the tables presenting gamma analysis results for various media. It

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j primarily appears under the "Others" column, and indicates that no other

) detectable gamma emitting nuclides were identified. The Teledyne Isotopes

) analytical methods meet the LLD requirements addressed in the CPSES

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)- Offsite Dose Calculation Manual. q Tables 2 through 19 give the radioanalytical results for individual )

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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-

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) tion. In table 20, the fraction (f) of the total number of analyses with de-

>- tectable activity follows in parentheses. Also given in. parentheses are the

) minimum and maximum values of detectable activity during the report pe-riod.

A. Direct Radiation Environmental radiation dose rates determined by thermolumines-

d cent dosimeters (TLDs) are given in Table 2. Thermoluminescent' dosimetry badges with four readout areas each were deployed at each location on quarterly and annual cycles. The mean values of four readings (corrected individually for response to_ a known dose and for in-transit exposure) are reported.

A statistical summary of the 1993 data is included in Table 20. For the quarterly analyses the average dose rate of the control locations was 0.15 mR/ day with a range of 0.12-0.21 mR/ day. The average of the indicator locations for the quarteuy samples was 0.14 mR/ day with a range of 0.05 to 0.23 mR/ day. For the annual samples, the average dose rate for the control samples was 0.17 mR/ day. The Indicator locations had an average of 0.16 mR/ day with a range of 0.09-0.21 mR/ day.

Oakley(3) calculates an ionizing background radiation dose equiva-lent of 82.2 mR/ year for Fort Worth including a terrestrial compo-nent of 45.6 mR/ year and an ionizing cosmic ray component of 36.6 mR/ year (excludes neutron component). Since Oakley's values rep-resent averages covering wide geographical areas, the measured ambient radiation average of 58 mR/ year for the immediate locale of CPSES is consistent with Oakley's observations. Significant variations occur between geographical areas as a result of geological composition and altitude differences. Temporal variations result from changes in cosmic ray intensity, local human activities, and factors such as ground cover and soil moisture.

Anomalies in the 1993- 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 17

(range of 0.11 to 0.17), for the quarterly and annual samples re-spectively. The 1988 averages for the quarterly and annual indica-tor locations were 0.16 mR/ day (range of 0.10 to 0.20) and 0.15 mR/ day (range of 0.12 to 0.18) respectively.

a Air Particulates and Air Iodine A total of 407 charcoal cartridges were analyzed for airborne to-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 407 air particulate filters were collected and analyzed for gross beta activity. For 1993 the average gross beta activity for the control location was 0.020 pC1/m3 with a range from 0.009 to 0.047 pC1/m3- For the seven indicator locations the yearly average was 0.021 pC1/m3 with a range from 0.0043 to 0.067 pCi/m3 The .l gross beta analysis data are presented in Table 4. Anomalies in gross beta measurements relative to preoperational data were not noted.

Air filters were composited quarterly and then analyzed by gamma 1

spectrometry. The gamma spectrometry data is presented in Table 1 1

5. Cosmogenic beryllium-7 was detected in all 32 samples; potas- l 1

stum-40, a naturally occurring nuclide, was measured in seven sam- )

4 ples. The average beryllium-7 activity for the control location was O.069 pCi/m3 with a range of 0.057 to 0.085 pC1/m3 For the indi-cator locations, the average beryllium-7 activity was 0.070 pC1/m3 with a range of 0.0048 to 0.087 pCi/m3. The average potassium-40 for the control location was 0.012 pC1/m3- The average potassium-40 activity for the indicator locations was 0.011 pCi/m3 with a 18

range of 0.005-0.019 pC1/m3 C. M11h A total of 19 milk samples were collected in 1993. 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.

Results of the gamma spectrometry measurements are presented in Table 7. Naturally occurring potassium-40 was detected in all of the milk samples. The average activity for the control location was I 1365 pCi/l with a range of 1200 to 1580 pCi/1, Cesium-137 was not detected in any of the samples.

D. Water Groundwater samples were collected from five locations during 1993. The samples were analyzed for gamma emitters and tritium on a quarterly basis, pursuant to the ODCM requirements for groundwater. Twenty-three samples were analyzed for gamma emitters by gamma spectrometry. Potassium-40 was detected in one indicator station with an average activity of 133 pCi/1. The control station samples were less than the lower limit of detection.

Quarterly composites for each sampling location were analyzed for tritium; no tritium was detected. Results of these analyses are con-l tained in Table 8 and 9 respectively, Surface-drinking water was collected from two stations. All sam-ples were analyzed for gamma emitters; results were below the i

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lower limit of detection. Thirty samples were analyzed for gross l beta activity. The indicator station had an average activity of 16 pC1/1 with a range of 11 to 21 pCi/1. The control station had an l average activity of 11 pC1/1 with a range of 6.2 to 19 pCi/1. Eight quarterly composites were analyzed for tritium. The indicator sta-tion had an average activity of 4400 pC1/1 with a range of 3800 to 4800 pCi/l. The control station showed no tritium activity above the lower limit of detection.

lodine-131 analyses by radiochemistry were performed on 56 samples of surface-drinking water; there was no measurable activ-ity. Results of these analyses are contained in Tables 10-13.

Surface water was sampled from four locauons during 1993.

Samples were analyzed for gamma isotopic on a' monthly basis and tritium composites on a quarterly basis, per the ODCM require-ments for surface water. Fifty-six samples were analyzed by gamma spectrometry. Potassium-40 was not detected in any of the samples. Sixteen composited surface water samples were analyzed for tritium. The indicator stations had an average activity of 4313 pCi/l with a range of 3400-5700 pCi/1. The tritium detected in

> Squaw Creek Reservoir samples is attributed to liquid effluent discharges from CPSES. The results of these analyses can be found in Table 14 and 15 respectively. The level of tritium in the Squaw Creek Reservoir is well within the expected value predicted in the CPSES Final Safety Analysis Report.

20

E . E Ls h The results of gamma isotopic analyses of fish samples collected during 1993 are presented in Table 16. A total of ten samples were analyzed, seven from the indicator location (ENE-2) and three from the control location (NNE-8). Sampling efforts concentrated on the larger edible species of commercial and/or recreational im-portance.

Cesium-137 was detected in three of the samples from Squaw Creek Reservoir with an average activity of 38 pCi/kg wet and a range of 28 to 49 pC1/kg wet. 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 concentrauon for the two indicator samples is 2506 pCi/kg wet with a range of 1590 to 3600 pCi/kg wet. The average concentration for the control location is 2883 pCi/kg wet with a j

) range of 2680 to 3160 pCi/kg wet.

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 particles enriched with .f l

i 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 j from the CPSES environment are given in Table 17. For 1993 21

three locations, one control and two indicators, were sampled semiannually. The average, fraction of detectables, and range of radionuclide concentrations are summarized in Table 20.

Naturally occurring gamma emitters found in detectable concen-trations were K-40, Pb-212, Bi-214, Pb-214. Ra-226 and Th-228.

Cesium-137 was measured in one sample from an indicator location with an activity of 47 pCi/kg. Preoperational levels of cesium-137 have ranged from 9.2 to 150 pC1/kg on four different occasions.

G. Food Products l Results of gamma isotopic analyses of food samples are contained in Table 18. A total of 12 samples were analyzed from three locations.

l Potassium-40, a naturally occurring isotope, was found in all 12 samples. For the indicator locations the average potassium-40 activity was 2906 pC!/kg wet with a range of 1120 to 5080 pCl/kg wet. Naturally occurring beryllium-7 was detected in two samples, one from indicator station E-4.2 with an activity of 194 pCi/kg wet and from control station SW-12.2 with an activity of 873. No I-131, Cs-134 or Cs-137 were detected in food products during 1993.

H. Broadleaf Vegetation Results of gamma isotopic analyses of broadleaf vegetauon samples are contained in Table 19. A total of 25 samples were analyzed !

I from three locations. Potassium-40, a naturally occurring Isotope, was found in all samples. The average potassium-40 activity for the control location was 5501 pC1/kg wet with a range of 1310 to 9240 ,

1 pCi/kg wet. For the indicator locations the average potassium-40 J

'l activity was 3813 pC1/kg wet with a range of 2010 to 5840 pC1/kg wet. Naturally occurring beryllium-7 was detected in sixteen ind!- l 1

22

id.

10- .

cy

-O- cator samples with an average activity of 2087 pC1/kg_ wet; the fO range was 1010 to 6030 pC1/kg wet. The nine samples from

0-c ntr 1 st ti n SW-13.5 were found to have heryllium-7 with an

$O.

!O- average activity of 1895 pC1/kg wet and a range of 646-3940 pCi/kg 0- wet, 10.

I dine-131. Cs-134 and Cs-137 were below the lower limit of de-O'

!O tecuon in all samples.

!a LO 40

!O IO 1 O

IO

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'O

'O '

O.

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O

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> l CONCLUSIONS

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24

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IV. CONCLUSIONS It is concluded from the levels obtained in environmental samples during 1993 and comparison of these levels to preoperational measurements, operational measurements of 1991 and 1992, and operational controls that the operation of CPSES in 1993 resulted in no changes in measurable levels of radiation or radioactive materials in the environment except the tritium detected in Squaw Creek Reservoir has increased from averages of approximately 2400 pCi/l in 1991 and 3400 pCi/l in 1992, to 4400 pCi/l in 1993. This increase has been expected; CPSES Unit 2 began operations in 1993. The i atmospheric environment was sampled for airborne particulate matter, radioiodine, and direct radiation. The terrestrial environment was sampled for milk, groundwater, surface- l l

drinking water, food products and broadicar 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 q indicative of natural terrestrial and cosmic ray radiation levels, except for the tritium in the surface water of Squaw Creek Reservoir which was far below the reporting levels for radioactivity concentrations in environmental samples.

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REFERENCES -l 1

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V. REFERENCES '

1. U.S. Nuclear Regulatory Commission, "An Acceptable Radiological Environmental Monitoring Program", Radiological Assessment Branch Technical Position, November 1979, Rev.1

2. National Council on Radiation - Protection and Measurements,

" Environmental Radiation Measurements" NCRP Report No. 50, Washington, D.C., December 27,1976

3. Oakley, D.C., " Natural Radiation Exposure in the Unlted States",

ORP/SID 72-1 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 Comancho Peak Steam Electric Station Units 1 and 2.

1

)

I 27 j i

_ _ - _ _ _ _ _ _ _ . . __ _ _ _a

1 DATA TABLES I

l 28 1

v---

TABLEI (PAGE 1 OF 2)

T U ELECTRIC COMANCilE PEAR STEAM ELECTRIC STAllON RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -- 1993 ,

)

t Identiflcauon by Number of Sector and Distance Sampling Analytical Media locations fMiles) Frecuency tal Analyses Frecuency Ial j Gamma Exposure 43 N-1.45: N-4.4: N-6.5: Q.A Thermoluminescent QA N-9.4: NNE-1.1 Dostmetry ,I 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:

e.SE-1.4; ESE-4.7: SE-1.3:

SE-3.85: SE-4.6: SSE-1.3; l 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:

,4 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:

NNW-1.35: NNW-4.6 i $ W Air Particulate 8 N-9.4 W Gross Beta Air Iodine E-3.5: SSE-4.5 Gamma Spectrometry Filter QC SW- 12.3: Gamma Spectrometry NW-1.0; N-1.45: SW/WSW-0.95 Charcoal Cartridge W S/SSW-1.2 Surface Water 4 N-19.3: ESE-1.4: N-1.5 M (b) Gamma Spectrometry M NE-7.4 Tritium QC Groundwater 5 SSE-4.6 Q Gamma Spectrometry Q W-1.2: WSW-0.1 N-9.8; N-1.45 Tritium Q Water-Surface 2 NNW-0.1: N-9.9 SM (c) Gross Beta M Drinking Gamma Spectrometry M Iodine- 131 SM Tritium QC c_ _ _ _ _ _ _ .__ __________. ________ __ _ _ _ _ _ . . _

TABLE 1 (PAGE 2 OF 2)

T U ELECTRIC COMANCliE PEAK STEAM ELECTRIC STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM -- 1993 Identification by Number of Sector and Distance Sampling Analytical Media Locations (Miles) Freauency fal Analyses Frecuency fal Sediment 3 N-9.9: NNE-1: NE-7.4 SA Gamma Spectrometry SA Fish 2 NNE-8: ENE-2 SA Gamma Spectrometry SA Milk 1 SW- 13.5 SM (d) lodine-131 SM (d)

Gamma Spectrometry SM (d)

Food Products 3 E-4.2: ENE-9.0 Mil Gamma Spectrometry M ri SW-12.2 lodine- 131 Mil

$ Bmadleaf 3 N-1.45: SW-1.0; SW-13.5 M Gamma Spectrometry M Vegetation Iodine-131 M (a) Frequency Codes Are: W = Weekly M = Monthly Q = Quarterly QC = Quarterly Composite SM = Semimonthly (i.e., once per 2-week period)

MH = Monthly during availability for harvest SA = Semiannual A ~= Annual (b) Surface water samples from Squaw Creek Reservoir are monthly composites of weekly grab samples. Samples from lake Gra.. are monthly composites of weekly grab samples when Lake Granbury is receiving letdown from Squaw Creek Reservoir; otherwise tney are monthly grab samples.

(c) Drinking water samples are a composite of weekly grab samples over a 2-week period when 1-131 analysis is performed: otherwise they are monthly composites of weekly grab samples.

(d) Milk sample collection and analysis frequency is semimonthly when animals are on pasture. Otherwise samples are collected and analyzed monthly.

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TABLE 4 (PAGE 1 OF 3)

T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF GROSS BETA EMITIERS IN AIR PARI 1CUIATES Results in Units of 10 3 pC1/m3 i 2 s.d.

r STA ON NW-1.0 SW/WSW-0.95 S/SSW-1.2 SW-12.3 SSE-4.5 E-3.5 N-1.45 N-9.4 JANUARY 12/29-01/05/93 2513 2513 2613 2213 3114 2813 2614 28t3 01/05-01/12/93 2413 2713 2813 2413 3113 2713 2914 2613 01/12-01/19/93 48i5 4514 5415 4715 6715 4915 5415 4715 01/19-01/26/93 7.312.6 9.512.7 9.512.7 9.212.7 1212 9.912.7 1113 6.812.6 01/26-02/02/93 2213 2513 2613 2513 2013 2313 2913 2413 FEBRUARY 02/02-02/09/93 22i3 2013 2213 2413 2013 2013 2413 2113 02/09-02/16/93 1913 2013 1813 1913 2113 17i3 2013 1813 02/16-02/23/93 3013 2413 2513 2313 2913 2413 2713 2713 02/23-03/02/93 2113 1913 1813 2013 1913 1613 2313 20i3 ca MARCH 03/02-03/09/93 1813 2113 2113 1813 2313 1813 2213 2313 03/09-03/16/93 16 3 1713 1213 1313 1913 1413 1513 1713 03/16-03/23/93 1313 1413 1413 1613 1613 1213 1813 1713 03/23-03/30/93 1913 2113 1513 2313 2013 1613 1813 1913 APRIL 03/30-04/06/93 9.412.9 7.812.8 1213 1713 11 3 1013 1413 1313 04/06-04/13/93 1813 2013 1813 1813 2113 1613 1713 1413 04/13-04/20/93 1613 1413 1613 1513 1613 1413 1713 1513 04/20-04/27/93 2013 1613 1913 1913 2413 2013 1813 2013

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TABLE 5 (PACE 1 OF 2)

T U EIECTRIC COMANCHE PEAK STEAM ELECITdC STA'I1ON CONCENIRA'HONS OF GAMMA EMITTERS

IN AIR PARDCULATE FIL'IERS Results in Units of E-03 pC1/m3 1 2 s.d.

IDCKHON COMPOSITE PERIOD Be-7 K-40 RU- 103 Cs-134 CS-157

, FIRST OUARTER I

NW-1.0 12/29/92-03/30/93 52.815.9 <8 <0.4 <0.4 <0.4 SW/WSW-0.95 12/29/92-03/30/93 48.815.4 17.0 4.9 <0.5 <0.5 <0.5 S/SSW-1.2 12/29/92-03/30/93 70.417.0 <10 <0.6 <0.6 <0.6 SW-12.3 12/29/92-03/30/93 59.415.9 <7 <0.4 <0.4 <0.4 SSE-4.5 12/29/92-03/30/93 70.717.6 9.714.0 <0.6 <0.6 <0.5 E-3.5 12/29/92-03/30/93 48.215.4 <9 <0.6 <0.5 <0.7 N-1.45 12/29/92-03/30/93 56.915.7 <9 <0.5 <0.4 <0.7 N-9.4 12/29/92-03/30/93 49.916.1 <20 <0.7 <0.7 <0.6 2 !

SECOND QUARTER NW- 1.0 03/30/93-06/29/93 67.016.7 <9 <0.5 <0.4 <0.5 ;

SW/WSW-0.95 03/30/93-06/29/93 87.219.7 10.114.0 <0.8 <0.7 <0.6 1 S/SSW-1.2 03/30/93-06/29/93 64.416.8 <20 <0.7 <0.6 <0.6 SW 12.3 03/30/93-06/29/93 56.816.4 <9 <0.7 <0.5 <0.7 SSE-4.5 03/30/93-06/29/93 79.518.0 <9 <0.7 <0.5 <0.5 E-3.5 03/30/93-06/29/93 56.915.7 <7 <0. 5 <0.4 <0.3 J N- 1.45 03/30/93-06/29/93 68.716.9 <7 <0.4 <0.4 <0.3 N-9.4 03/30/93-06/29/93 72.I17.2 <10 <0.7 <0.6 <0.5

All other gamma emitters were <LLD.

V UUUD U t , V U k[ U U V O ([U O () 6([O U V LJO'VT_d[U[Ul A [C U V U V U U V V U J '

s TABLE 5 (PAGE 2 OF 2)

T U ELECTRIC COMANCIIE PEAK SIEAM ELECTRIC STA110N CONCEhTRATIONS OF GAMMA EMrIIERS* IN AIR PARTICULA'IE FILTERS Results in Units of E-03 pC1/m3 1 2 s.d.

LOCATION COMPOSITE PERIOD Be-7 K-4 0 RU- 103 Cs-134 CS-137 1

l THIRD QUARIER l

! NW- 1.0 06/29/93-09/27/93 78.417.8 <20 <0.7 <0.6 <0.6 I SW/WSW-0.95 06/29/93-09/27/93 83.318.3 7.6214.27 <0.7 <0.5 <0.7 S/SSW-1.2 06/29/93-09/27/93 85.918.6 <9 <0.6 <0.5 <0.5 SW-12.3 06/29/93-09/27/93 73.717.4 1214.8 <0.6 <0.5 <0.5 SSE-4.5 06/29/93-09/27/93 79.518.0 <8 <0.6 <0.4 <0. 5 E-3.5 06/29/93-09/27/93 78.517.8 <7 <0.5 <0.4 <0.4 N- 1.4 5 06/29/93-09/27/93 72.417.2 <8 <0. 5 <0.3 <0.3 N-9.4 06/29/93-09/27/93 74.217.4 <20 <0.7 <0.6 <0.5 0 .

FOURTH QUARTER j NW- 1.0 09/27/93-12/28/93 81.218.1 <9 <0.6 (0.5 <0.4 i SW/WSW-0.95 09/27/93-12/28/93 79.3i7.9 <10 <0.7 <0.6 <0.5 S/SSW-1.2 09/27/93-12/28/93 67.016.7 18.714.6 <0.6. <0.5 <0.5 SW-12.3 09/27/93-12/28/93 85.118.5 <8 <0.5 <0.4 <0.4 SSE-4.5 09/27/93-12/28/93 78.617.9 <8 <0.5 <0.4 <0.4 E-3.5 09/27/93-12/28/93 65.616.6 <6 <0.4 <0.3 <0.3 N- 1.45 09/27/93-12/28/93 83.618.4 5.3212.54 <0.4 <0.4 <0.4 N-9.4 09/27/93-12/28/93 68.416.8 <20 <0.6 <0.5 <0.6 l

'All other gamma em'iters wem <LLD.

l TABLE 6 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN MILK Results in pC1/1 2 s.d.

1 COLLECTION MONTH DATE SW-13.5 i l

JANUARY 01/12/93 <0.2 FEBRUARY 02/09/93 < 0. 3 MARCH 03/09/93 < 0. 2 APRIL 04/06/93 < 0. 2 MAY 05/04/93 <0.2-05/18/93 <0.2 JUNE 06/01/93 <0.2 06/15/93 < 0. 3 06/29/93 <0.2 JULY 07/13/93 < 0.2 07/26/93 <0.2 AUGUST 08/10/93 < 0. 2 08/24/93 < 0. 2 SEMEMBER 09/08/93 <0.2 09/21/93 <0.2 OcrOBER 10/05/93 <0.1 10/19/93 <0.2 NOVEMBER 11/16/93 <0.02 DECEMBER 12/14/93 <0.2 4

43

TABLE 7 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STA110N CONCEffrRA110NS OF GAMMA EMITTERS

IN MILK Results in Units of pCl/ liter i 2 s.d.

LOCATION COLLEC110N DATE K-40 Cs.134 Cs-137 La-140/Ba-140 STA110N SW-13.5 JANUARY 01/12/93 13001130 <3 <4 <6 FEBRUARY 02/09/93 13501140 <4 <4 <6 f MARCH 03/09/93 12501120 <3 <3 <4 I APRIL 04/06/93 13701140 <4 <4 <6 MAY 05/04/93 12601130 <5 <5 <6 05/18/93 1410i140 <3 <3 <4 JUNE 06/01/93 14001140 <4 <4 <5 06/15/93 12901130 <4 <4 <5 06/29/93 13101130 <4 <4 <6 JULY 07/13/93 12701130 <4 <4 <6

$ 07/26/93 14701150 <4 <4 <5 AUGUST 08/10/93 15801160 <3 <4 <5 08/24/93 13901140 <4 <4 <6 SEPTEMBER 09/08/93 14601150 <4 <4 <5 I 09/21/93 14201140 <3 <3 <4 OCTOBER . 10/05/93 1200 120 <4 <4 <6 ]

10/19/93 13901140 <3 <3 <5 i NOVEMBER 11/16/93 13801140 <4 <4 <6 l DECEMBER 12/14/93 14401140 <4 <4 <6 )

l l

All other gamma emitters were <LLD t

L L_ - -

V W TABLE 8 (PAGE 1 OF 2)

T U ELECIRIC COMANCHE PEAK STEAM ELECDUC STABON CONCENTRATIONS OF GAMMA EMITTERS

IN GP.OUNDWATER Results in Units of pct /l 12 s.d.

}

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/la-140 STABON W-1.2 01/05/93 <3 <3 <7 <4 <7 <4 <3 <4 <7 04/07/93 <3 <4 <8 <4 <7 <4 <4 <4 <7 07/06/93 <3 <3 <6 <3 <6 <3 <3 <3 <4 10/05/93 <3 <3 <8 <4 <7 <4 <4 <4 <7 12/31/93 <3 <4 <7 <3 <7 <4 <4 <4 <6 STAT 10N WSW-0.1

! 01/05/93 <3 <3 <7 <3 <7 <3 <4 <4 <6 l 04/07/93 <3 <3 <6 <3 <7 <3 <3 <3 <5 07/06/93 <3 <4 <8 <3 <8 <4 <4 <4 <4

@ 10/05/93 <4 <3 <7 <4 <7 <4 <4 <4 <6 12/31/93 STA110N SSE-4.6 01/05/93 <3 <4 <8 <3 <8 <4 <4 <4 <7 04/06/93 <3 <4 <8 <4 <7 <4 <3 <4 <6 07/06/93 <3 <3 <5 <3 <7 <3 <3 <3 <4 10/05/93 <3 <4 <8 <4 <8 <4 <4 <4 <6 12/31/93 <3 <4 <8 <3 <7 <4 <4 <4 <7 STAT 10N N-9.8 01/05/93 <4 <4 <8 <3 <8 <4 <4 <4 <7 04/06/93 <3 <3 <7 <3 <7 <3 s3 <4 <6 07/06/93 <S <3 <6 <3 <6 <3 <3 <3 <4 10/05/93 <3 <3 <7 '<3 <7 <3 <3 <5 <5 12/31/93 All other ganma emitters were LLD.

- Sample not collected -- See Appendix C for explanation.

- vw-TABLE 8 (PAGE 2 OF 2)

T U ELECTRIC COMANCilE PEAK STEAM ELECTRIC STATION

' CONCENmATIONS OF GAMMA EMITIERS* IN GROUNDWATER Results in Units of pCl/li 2 s d.

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs-137 Ba/la-140 STATION N-1.45 01/05/93 <3 <3 <7 <4 <7 <3 <3 <4 <6 04/06/93 <3 <3 <8 <3 <7 <4 <4 <4 <6 1

07/06/9" <3 <3 <6 <3 <7 <3 <3 <4 <4 10/05/L3 <3 <3 <6 <3 <5 <3 <3 <4 <5 12/31/93 <3 <3 <7 <3 <6 <3 <3 <3 <5 N

l All other gamma emitters were 11D. i L- --_-

t TABLE 9 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN GROUNDWATER )

Results in pC1/1 i 2 s.d.

l COLLECTION ..

TRITIUM ;

OUARTER PERIOD LOCATION ACTIVITY l 1 01/05/93 W- 1.2 <100 i 01/05/93 WSW-0.1 <100 01/05/93 SSE-4.6 <100 01/05/93 N-9.8 <100 01/05/93 N- 1.45 <100' 2 04/07/93 W-1,2 <200 04/07/93 WSW-0.1 <200 04/06/93 SSE-4.6 <200 04/06/03 N-9.8 <200 04/06/93 N- 1.45 <200-3 07/06/93 W- 1.2 <200 07/06/93 WSW-0.1 <200 07/06/93 SSE-4.6. <200

) 07/06/93 N-9.8. <200 07/06/93 N- 1.4 5 <200 4- 10/05/93- W-1.2 <2000 10/05/93 WSW-0.1 - <2000 10/05/93 SSE-4.6 <2000-10/05/93 N-9.8 <2000~

10/05/93 N- 1.4 5 <2000-47

TABLE 9 T U E.LECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN OROUNDWATER Results in pCi/l i 2 s.d.

COLLECTION TRITIUM OUARTER PERIOD LOCATION ACTIVrIY 4 12/31/93 W- 1.2 <100 12/31/93 WSW-0.1

12/31/93 SSE-4.6 <100 12/31/93 N-9.8

12/31/93 N- 1.4 5 <100 i

)

Sample not collected -- see Appendix C for explanation.

R E __

TABLE 10 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION GROSS BETA CONCENTRATIONS IN WATER-SURFACE / DRINKING Results in pC1/1i 2 s.d.

l 1

COLLECTION l MONTH DATE NNW-0.1 N-9.9 l

JANUARY 12/23/92-01/12/93 14i3 10i3 1 1

FEBRUARY 01/19/93-02/09/93 1413 7.212.5 02/16/93-03/09/93 14i3 9.4 i 2.5 MARCH 03/16/93-04/06/93 16i3 8.2i2.3 APRIL 04/13/93-05/04/93 1613 10i3 MAY 05/11/93-06/01/93 1613 10i3 JUNE 06/08/93-06/29/93 13i3 13i3 JULY 07/06/93-07/26/93 19i3 1413 AUGUST 08/03/93 08/24/93 21i4 13i3 SEFI' EMBER 08/30/93 09/21/93 1116 11i4 i

OCTOBER 09/28/93-10/19/93 21i4 19i4

, NOVEMBER 10/26/93-11/16/93 15i4 11i3 11/23/93-11/30/93 16i3 16i2 l

DECEMBER 11/23/93-12/14/93 16i3 12i3 12/21/93-01/11/94 17i4 6.2i2.7 49

0 0 O i) G T O O O O O O O O O O O O O O t.; O O O O O O O O () O O O O O O O.C :_'t.J O E TABl.E 11 (PAGE 1 OF 2)

T U ELECTRIC COMANCIIE PEAK STLLM ELECTRIC STABON CONCENIRADONS OF GAMMA EMITIERS* IN WATER SURFACE / DRINKING Results in Units of pCl/l i 2 s.d.

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs- 134 Cs- 137 Ba/la-?40 COILECI1ON DA'IE STATION NNW-0.1 12/23/92-01/12/93 <4 <4 <8 <4 <7 <4 <4 <4 <6 01/19/93-02/09/93 <3 <3 <6 <3 <6 <3 <3 <3 <5 02/16/93-03/09/93 <3 <3 <7 <3 <7 <3 <3 <4 <6 03/16/93-04/06/93 <3 <3 <8 <3 <7 <4 <3 <3 <7 04/13/93-05/04/93 <3 <3 <7 <3 <6 <3 <2 <3 <4 05/11/93-06/01/93 <3 <3 <7 <4 <7 <4 <4 <4 <6 06/08/93-06/29/93 <3 <3 <6 <3 <6 <3 <3 <3 <6 07/06/93-07/26/93 <3 <3 <8 <4 <7 <4 <4 <4 <6 08/03/93-08/24/93 <3 <3 <7 <3 <7 <4 <3 <4 <6 08/30/93-09/21/93 <3 <3 <7 <3 <7 <3 <4 <5 <6 09/28/93-10/19/93 <4 <4 <9 <4 <8 <4 <4 <4 <7 10/26/93-11/16/93 <2 <2 <5 <2 <5 <2 <2 <3 <4 11/23/93-11/30/93 <4 <4 <8 <4 -<8 <4 <4 <4 <6 11/23/93-12/14/93 <3 <3 <6 <3 <6 <3 <3 <3 <4 12/21/93-01/11/94 <3 <3 <6 <3 <6 <3 <3 <3 <5 All other gamma emitters were 11D.

0 4

1 a 5 5 5 8 G 5 6 4 5 7 8 5 6 4 5 L < < < < < < < < < < < < < < <

/

a B

7 3

1 4 3 3 4 4 4 3 4 3 4 5 3 5 3 4 s < < < < < < < < < < < < < < <

C G

N I

K N

I R 4 D 3

/

1 4 3 3 4 4 3 3 4 3 4 4 3 4 3 3 E s < < < < < < < < < < < < < < <

C C A

NF OR I

T U 5 AS 9-T r S R . Z CI E d.

I 'A s

/

b 4

3 3 4

4 3 3 3 3 4

4 3 3 3 3 H 2 N t W i c

)

2 C LE Nl 1

I / t 1 F uE' SCp OcMRf I l 5

6-E L 2EA ;t osi n 8 6 6 7 7 8 6 7 7 8 7 G 7 6 7 BE L E s t AG ET Z i i TAUP SMn KE U

(

TA n E Ai s P Mt 0 6-Ml u E A se l

C o 4 3 3 3 3 4 3 3 3 4

4 3 4 3 3 C G R l

NF AO M S ON 9 5-CO1 e 8 6 7 8 8 7 6 7 7 7 8 7 7 6 7 I

' F < < < < < < < < < < < < < < <

A R

I' N

E 8 C 5- 3 3 3 4 4 3 3 3 3 4 4 3 3 3 3 D N o < < < < < < < < < < < < < < < L O C L C e r

e w

4 s 5- r 3 3 3 3 3 3 3 3 3 3 3 3 3 3 3 e n < < < < < < < < < < < < < < < t t

i M

m e

3 3 3 3 3 3 3 3 3 3 3 3 3 3 4 a E 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 m T / / / / / / / / / / / / / / /

m A 9 2 9 9 G 4 1 9 6 4 1 9 6 10 4 1 a

D 1 0 0 0 0 0 2 2 2 2

/ / / / / / / / / / / / / / /

1 3 1 1 g

N 9- 1 2 3 4 5 6 6 7 8 9 0 1 1 2 1 r 0 N 0 0 0 0 0 0 0 0 0 0 1 1 1 1 0- e 1

- - - - - - - - - - - - - - h 1

N 2 3 3 3 3 3 3 3 3 3 3 3 3 3 3 t o

C 9 9 9 9 9 9 9 9 9 9 9 9 9 9 9 F O / / / / / / / / / / / / / / / l l

I 3 9 6 6 3 1 8 6 3 0 8 6 3 3 1 A

H T 2 1 1 1 1 1 0 0 0 3 2 2 2 2 2 A / / / / / / / / / / / / / / /

O T 2 1 2 3 4 5 6 7 8 8 9 0 1 1 2 C S 1 0 0 0 0 0 0 0 0 0 0 1 1 1 1 *

,?

e

} TABLE 12 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF I-131 IN WATER-SURFACE / DRINKING ;

Results in pC1/1 2 s.d. ]

COLLECTION l j MONTH DATE NNW-0.1 N-9.9

) JANUARY 12/23/92-01/12/93 < 0. 2 <0.2 l

) 01/19/93-01/26/93 <0.2 <0.3 1

l FEBRUARY 02/16/93-02/23/93 <0.2 <0.2 4 02/16/93-03/09/93 < 0. 4 <0.4 j MARCH 03/16/93-03/23/93 < 0. 3 <0.2 03/16/93-04/06/93 < 0. 4 <0.4

} APRIL 04/13/93-04/20/93 <0.2 <0.3 04/13/93-05/04/93 < 0. 5 <0.4 j D 1 p MAY 05/11/93-05/18/93 <0.3 <0.2 )

s 05/11/93-06/01/93 < 0. 5 <0. 5

)

JUNE 06/08/93-06/15/93 06/08/93-06/29/93

< 0. 3

<0.5

<0.2

< 0. 5 JULY 07/06/93-07/13/93 <0.2 <0.2 p 07/06/93-07/26/93 < 0. 4 <0.4 l AUGUST 08/03/93-08/10/93 <0.4 <0.3 j 08/03/93-08/24/93 < 0. 4 <0.4 SEPTEMBER 08/30/93-09/07/93 < 0. 2 <0.2 08/30/93-09/21/93 <0.9 <0.6 OCTOBER 09/27/93-10/05/93 < 0. 2 <0.2 09/28/93-10/19/93 <0.4 <0.4 10/26/93-11/02/93 < 0. 3 <0.2 NOVEMBER 10/26/93-11/16/93 < 0. 4 <0.4 11/23/93-11/30/93 < 0. 3 <0.3 DECEMBER 11/23/93-12/14/93 <0.4 <0.4 12/21/93-01/11/94 < 0. 4 < 0. 5 12/21/93-12/28/93 < 0. 2 <0.3

52 9

TABLE 13 T U ELECTRIC COMANCHE PEAK STEAM ELECTRIC STATION CONCENTRATIONS OF TRITIUM IN WATER-SURFACE / DRINKING Results in pCi/l i 2 s<d.

d d COLLECTION ;

OUARTER PERIOD NNW-0.1 N-9.9 _l I

1 12/23/92-03/09/93 3800i200 <200 l 2 03/16/93-06/29/93 4500il200 <2000 )

3 07/06/93-09/21/93 4800i1300 <2000 l 4 09/28/93-12/14/93 4500i200 <100

)

2 s

?

D D

l 53

V TABLE 14 (PAGE 1 OF 2)

T U ELECT 11C COMANCIIE PEAK STEAM ELECTRIC STA110N CONCENIRADONS OF GAMMA EMITIERS* IN SURFACE WATER Results in Units of pCl/l i 2 s.d.

Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs-134 Cs- 137 Ba/La-140 COMFCT10N DA'IE STA'I1ON ESE-1.4 12/23/92-01/12/93 <3 <3 <7 <3 <7 <4 <3 <4 <5 01/19/93-02/09/93 <4 <4 <8 <3 <9 <4 <4 <4 <6 02/16/93-03/09/93 <3 <3 <7 <3 <7 <3 <4 <4 <5 03/16/93-04/06/93 <3 <3 <7 <'o <7 <4 <3 <4 <6 04/13/93-05/04/93 <3 <4 <7 <3 <7 <4 <4 <4 <5 05/11/93-06/01/93 <3 <3 <8 <4 <7 <4 <4 <4 <6 06/08/93-06/29/93 <3 <3 <7 <3 <7 <3 <3 <3 <6 ,

07/06/93-07/26/93 <4 <4 <9 <4 <9 <4 <5 <5 <5 l 08/03/93-08/24/93 <3 <4 <7 <3 <7 <4 <4 <4 <5 i 08/30/93-09/21/93 <3 <3 <7 <3 <6 <4 <4 <4 <6 09/28/93-10/19/93 <3 <3 <6 <3 <8 <4 <3 <3 <6 10/26/93-11/16/93 <3 <3 <7 <3 <7 <4 <4 <4 <5 11/23/93-12/14/93 <3 <4 <8 <4 <9 <4 <4 <4 <5 12/21/93-01/11/94 <2 <3 <5 <3 <5 <3 <3 <3 <5

$ STATION N-1.5 12/23/92-01/12/93 <4 <4 <10 <4 <10 <5 <5 <5 <7 01/19/93-02/09/93 <2 <3 <6 <3 <6 <3 <3 <3 <5 02/16/93-03/09/93 <3 <3 <6 <3 <6 <3 <3 <3 <4 03/16/93-04/06/93 <4 <5 <10 <4 <10 <5 <5 <5 <7 04/13/93-05/04/93 <3 <4 <7 <3 <7 <4 <4 <4 <6 05/11/93-06/01/93 <3 <3 <7 <3 <7 <4 <4 <4 <6 06/08/93-06/29/93 <3 <3 <7 <3 <6 <3 <3 <3 <5 07/06/93-07/26/93 <3 <3 <6 <4 <6 <3 <3 <3 <4 08/03/93-08/24/93 <3 <3 <6 <3 <6 <3 <3 <3 <5 08/30/93-09/21/93 <4 <3 <8 <4 <7 <4 <4 <4 <6 09/28/93-10/19/93 <3 <3 <6 <3 <6 <3 <3 <3 <5 10/26/93-11/16/93 <3 <3 <6 <4 <7 <4 <4 <4 <6 11/23/93-12/14/93 <3 <3 <5 <3 <6 <3 <3 <3 <3 12/21/93-01/11/94 <3 <3 <7 <3 <8 <3 <4 <4 <5-All other gamma emitters were <LLD.

TABLE 14 (PAGE 2 OF 2)

T U ELECIRIC COMANCIIE PEAK STEAM ELECIRIC STK110N CONCEffl' RATIONS OF GAMMA EMITIERS* IN SURFACE WATER Results in Units of pC1/1 2 s.d.

l Mn-54 Co-58 Fe-59 Co-60 Zn-65 Nb/Zr-95 Cs- 134 Cs- 137 Ba/la-140 l

COLLECf1ON DATE STAT 10N NE-7.4 12/23/92-01/12/93 <3 <3 <7 <4 <7 <3 <3 <4 <G 01/19/93-02/09/93 <3 <3 <6 <3 <6 <3 <3 <3 <5 02/16/93-03/09/93 <3 <3 <7 <3 <6 <3 <4 <4 <5 03/16/93-04/06/93 <3 <3 <8 <4 <6 <4 <3 <4 <5 04/13/93-05/04/93 <3 <3 <7 <3 <6 <3 <4 <4 <4 05/11/93-06/01/93 <3 <3 <7 <4 <8 <4 <4 <4 <6 06/08/93-06/29/93 <4 <4 <8 <4 <8 <4 <4 <4 <7 07/06/93-07/26/93 <3 <3 <7 <4 <8 <4 <4 <4 <5 08/03/93-08/24/93 <3 <3 <6 <3 <6 <3 <3 <3 <4 08/30/93-09/21/93 <4 <4 <8 <4 <8 <4 <4 <4 <6 09/28/93-10/19/93 <4 <4 <7 <4 <7 <4 <4 <4 <6

, 10/26/93-11/16/93 <4 <4 <8 <4 <8 <4 <4 <4 <5 m 11/23/93-12/14/93 <3 <3 <6 <4 <6 <3 <3 <3 <5 12/21/93-01/11/94 <4 <4 <10 <4 <10 <5 <5 <5 <7 l

STA'110N N-19.3 12/23/92-01/12/93 <3 <3 <8 <3 <7 <4 <4 <4 <G I 01/19/93-02/09/93 <3 <3 <7 <3 <7 <3 <3 <4 <6 02/16/93-03/09/93 <4 <4 <8 <4 <8 <4 <4 <4 <7 4 03/16/93-04/06/93 <3 <3 <7 <3 <7 <4 <4 <4 <7 1 04/13/93-05/04/93 <4 <4 <7 <4 <8 <4 <4 <5 <6 l 05/11/93-06/01i93 <4 <4 <9 <4 <7 <4 <4 <4 <6 l 06/08/93-06/29/93 <3 <3 <7 <3 -<7 <3 <3 <3 <5 07/06/93-07/26/9J <4 <3 <8 <4 <8 <4 <4 <4 <5 l 08/03/93-08/24/93 <4 <4 <8 <3 <8 <4 <4 <4 <5 08/30/93-09/21/93 <3 <3 <7 <3 <7 <3 <3 <5 <6 09/28/93-10/19/93 <3 <3 <7 <4 <6 <4 <3 <4 <7 10/26/93-11/16/93 <3 <3 <7 <4 <6 <4 <3 <5 <5 11/23/93-12/14/93 <3 <3 <6 <3 <6 <3 <3 <3 <4 12/21/03-01/11/94 <3 <3 <6 <3 <7 <3 <3 <3 <4 All other gamma emitters were <LLD.

L . . _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ ___ _ _ a

Ij l )llil 3 0 0 0 0 -

9 0 0 0 0 1 1 0 0 2

- < 2 2 <

N < <

A _

7- 0 0 0 0 E

N 0

2 0

0 2

0 0

2 0

1 R < <

E T

NA OW I

T A E T C SAF 0 0

0 0

0 0 CR 0 2 3 0 I

2 1 1 2 R U .

T S d.

5 1 1 1 1 1 0 0 0 0 CN s N 0 0 0 0 C EI 2i 8 0 7 4 5 d LEM 1

t 4 l 3 4 5 4 E cMU/ l LEADC B L Er Rp A ETST n _

TU K F s i t

T A Olu E S se 0 0

0 0

0 0 P

EON R 0 2 3 0 4 2 1 1 2 HT CA I

1 1

0 1

0 0 i

NR AT E 0

8 0

4 0

8 0

6 MN S 3 3 4 4 E

OE _

CC N O

C D

O 3 3 3 3 3 3 3 3 I

9 9 9 9 9 9 9 9 R / / / / / / / /

E 9 9 9 9 1 1 4 4 -

P 0 0 2 2 2 2 1 1

/ / / / / / / /

N 3 3 6 6 9 9 2 2 O

I 0- 0 0 0 0 0 1

1 T 2 3 3 3 3 3 3 3 C 9 9 9 9 9 9 9 9

/ / / / / / / /

E 3 2 16 6 1 6 6 8 9 L 2 0 0 2 2 1 L / / / / / / / /

O 2 1 3 4 7 7 9 0 C 1 0 0 0 0 0 0 1 R

E T

R A 1 1 2 2 3 3 4 4 U

Q E

Il ll i , Illl l . 1i !l t

J N NO C

'A N A e @ OOOOOD OOO Q Nv5 vM-M M-N V V V V V V V b OOOOOOO

- OOO k M M C c) M-N M-N g V V V V V V V V V V tO

@ OOOOOOO OOO c' CCOC@ Mv c M c)

N V V- V V V V V V V V

O C OO OOOOO OOO 6 M N to c) N-N M--

y V V V V V V V V V V W

2 o z e !

~ to OOOOOO O OOO

4 5 C O b b M to c v to .

g V V -V V V V V V V l

h. Y u31

N

{2M uyw= m cc O 000000 000 3

l l

e3mpi 8 99*99~9 999 J Sd gw 3!

o-s :a w%

p Og 3 ooooooo ooo m NNtaMM-N M--

za E C vvvvvvv vvv o?

Y E U COOOOOO OOO 3 6 O 6 to O MO to 5 co !

2e ou O

?

S20%%QO 0000000

%QQ 000 ug * @QQ@CE@

"~""""~

585 u

2 0 0 a a 2

- m d ws Edd E

y ]vvnv 9 ~a it 0 ~~

T E

Q Ea a a a.

=E 545 i

o e

u $ 2u$3o

- =o Xeoe a o-b a

z 0000000 000 b E'

wwwwwww www j

o k zzzzzzz zzz wwwwwww zzz g.

e z a O

MMMMMMM M MM e E RRRRRRR RRR -s

$g< 3333388 2N9

- - ~

O ua 88888:: 822 ?

57 1

. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ _ _ . _ _ _ _ . _ _ _ . _ _ _ _ __ _ _i

TABLE 17 T U ELECTRIC COMANCHE PEAK SEULM ELECIRIC STATION CONCENTRATIONS OF GAMMA EMITTERS

IN SEDIMENT Results in pC1/kg (dry) i 2 s.d.

COLLECBON DATE STATION Be-7 K-40 Cs-134 Cs-137 14)-212 Bi-214 Pb-214 Ra-226 Th-228 STATION N-9.9 01/12/93 SS2 <200 43101430 <20 <20 197134 215138 172135 <400 191133 07/13/93 SS2 <200 6911212 <20 -<20 90126 377145 479151 7001335 87125 STAT 10N NNE-1.0 01/13/93 SSI 3091141 26901310 <20 <20 154t24 279139 301140 7341308 149123 07/13/93 SSI <200 18101250 <20 47118 122123 386142 451145 5631243 119122 m

STATION NE-7.4 01/12/93 SS3 <200 25401260 <20 <20 89117 209135 238133 4751217 86116 07/13/93 SS3 <100 18901210 <20 <20 134118 227129 316132 4821243 130118 i I

l i

i l

All other gamma emitters were LLD.

TABLE 18

. (PAGE 1 OF 1) -

T U ELECIRIC COMANCHE PEAK STEAM ELECTRIC STA110N CONCENTRATIONS OF GAMMA EMITIERS* IN FOOD PRODUCTS Results in Units of pC1/kg (wet) i 2 s.d.

COLLECITON STATION DESCRIP110N DA1E Be-7 K-40 1-131 Cs-134 Cs-137 E-4.2 01/12/93 *" l' 02/09/93 "*

03/09/93 *"

04/06/93 *" 1 FP-2 Spinach 05/04/93 194139 50801510 < 10" <6 <6 )

FP-2 Grn Beans 06/01/93 <100 49601500 <2 0" <10 <10 1 FP-2 Pickle cuke 06/29/93 <50 21301210 < 10" <6 <6 i FP-2 Wtrmelon 07/26/93 <60 11201110 < 10" <7 <7 d FP-2 Pickle Cuke 08/24/93 <50 15201150 < 10" <6 <6 FP-2 Squash 09/21/93 <40 23201230 <8 " <5 <5 FP-2 10/12/93*"

FP-2 11/16/93*"

FP-2 ?.2 /14 /93"'

ui SW- 12.2 01/12/93 *"

C2/09/93 "*

03/09/93 "*

04/06/93 "*

FP-4 Lettuce 05/04/93 873187 63301630 ." <9 <8 ,

FP-4 Squash 06/02/93 <50 .16701170 < 10" <6 <6 i FP-4 Ylw Squash 06/29/93 <70 12501130 <20" <9 <8 FP-4 Squash 07/26/93 <50 15201150 <9 " <6 <6 FP-4 Potatoes 08/24/93 <50 4580 460 < 10" <G <6 FP-4 09/2I/93*"

FP-4 1O/12/93 "*

FP-4 11/16/93 "*

FP-4 12/14/93***

ENE-9.0 FP-1 Pecan 10/12/93 <90 32101320 <60 <10 <10 I All other gamma emitters were <llD. !

" . By gamma spectroscopy i

" Sample not collected. See Appendix C for explanation.

j

TABLE 19 (PAGE 1 OF 2)

T U ELECIRIC COMANCHE PEAK STEAM ELECTRIC STAT 10N CONCENTRA110NS OF GAMMA EMITIERS* IN BROADLEAF VEGETATIONr Retults in Units of pC1/kg (wet) i 2 s.d.

COLLECI1ON STA'ITON DESCRIFI1ON DATE Be-7 K-40 1-131 Cs- 134 Cs- 137 SW- 13.5 01/12/93 (BL3) 02/09/93 03/09/93 Bloodweed 04/06/93 646167 70601710 < 10" * <8 <8 Bloodweed 05/04/93 18101180 67401670 <4"* <10 <10 Bloodweed 06/01/93 19001190 92401920 <4*" <10 <10 Bloodweed 06/29/93 12401120 71901720 < 10 " * <7 <7 Hackberry 07/26/93 27301270 40301400 <2 0" * <10 <10 Hackberry 08/24/93 18501180 52701530 <5*" <20 <20 llackberry 09/21/93 12801150 49601500 < 10" * <20 <20 Johnson Grass 10/19/93 16601170 37101370 <10"* <10 <10 Bloodweed 11/16/93 39401390 13101210 <2 0" * <20 <20

@ 12/14/93 "

N-1.45 01/12/93 **

(BLI) 02/09/93 **

03/09/93 **

04/06/93 Sumac - '05/04/93 12101130 40001400 <5"* <20 <20 Sumac 06/01/93 12901140 41501420 <6*" <20 <20 Sumac 06/29/93 15801160 45901460 <2 0" * <2 0,' <20 Sumac 07/26/93 10101130 2090 210 <4 0"* <20 <20 Sumac 08/24/93 23101230 48501480 <9 " * <10 <10 Sumac 09/21/93 15901160 58401580 <2 0" * <10 <10 Sumac 10/19/93 27101270 20101200 <5*" <10 <10 Sumac 11/16/93 29901300 32101320 <2 0 " * <20 <20 12/14/93**

All other gamma emitters are LLD Sample Not Collected. See Appendix C for explanation.

'* By Radiochemical Analysis

_- - _- __ - - _ _ - _ _ = _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _

{' i

) lllll! l' ! ,il l1 ;'

7 3

1 008005 00 s 1 1 < 1 1 < 2 2 C < < < < < <

4 3

1

- 00 0 0 0 0 s 1 1 8 1 1 6 2 C < < < < < <2< <

N 0

1 T

A T

E G 1 E 3 * " *

V 1 NF I

" 00 " " 0 OA 3 62 3 6 9' 5 3 BE A L d.

T D s SA I

M O2 C Ri B )t A e 0 0

2 0 00 0 0 0 0 7 7 1 4 7 8 7 _

UIN w (

4- 4 32 4 3 3 3 4

)

2 CE*

I L g K 0 1 1 1 1 1 1 1 1 00 0 00 00 S

9 FRE R, 1 I k/ 1 8 1 0 0 5 5 8 9 7 7 1 3 7 7 6 OCMt Cp 1

E 1 4 32 4 333 4 L L E 2 EA 1 1

BE AG E d Mo 1

f T PAU E s t

( KAn i TAE MU 0 0 0 0 0 00 0 PMnAi 7-e 5 1 6 4 1 2 8 0 1 1 1 1 21 3 6 E G s B 1 1 1 1 1 1 1 1 H t 00 0 0 0 000 CF u l

8 8 9 1 4 61 3 4 0 5 4 1 1 80 NO s e 1 1 1 1 21 36 A SR M N O

C1 0 N """" "

T O 3333 3 3 3 3 3 3 3 3 3 A 1 9999 9 9 99 9 999 9 R I

//// / / / / / / // /

CE T 2996 61 96 5 1 964 -

N EI 1000 0 0 22 221 1 1 E L LD K //// / / / / / / / / / ,

C 1234 5 6 67 8 90 1 2 n N O 0000 0 0 0 0001 1 1 O C n C < -

r e -

e N w 0

1 y y s i s

T r s r r e P

I r

e r

e t

t l y

t R c c c cb cb c i u

C a mmmmc a a ak mc ak am mler ebA S

E uu uu a ua u alal D SSSSI SI SI l miaac -

mvi a am gt e -

oh rnc e o hei tl d N o pa O

I 0 l l

Aay mR T 1) 2 SB A

T S

WL S(B * " "" -

n c" -

illji l( } ll lIIl!f1li lI , {1I tL

TABLE 20 (PAGE 1 OF 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

T U ELECTRIC - COMANCHE PEAK STEAM ELECTRIC STA"ITON q JANUARY I 'ID DECEMBER 31.1993 Number of Analysis and Lower Limit Control locations Nonroutine

- Medium of Pathway Total Number of All Indicator Imcations location with Hfchest Mean Reported Detection Mean Name Mean (f)(2) Mean (0(2)

Sampled ofAnalysis Distance and Direction Range Range Measurements (LLD) (1) Range (Unit of Measurement) Performed ENE-5 0.18(4/4) 0.15(8/8) O

'ILDs (Quarterly) Gamma (170) 0.14(162/162)

(0.05-0.23) (0.15-0.22) (0.12-0.21)

(mR/ day)

E-3.5 0.22(1/1) O.17(2/2) O I

'ILDs (Annual) Gamma (43) O.16(41/4 I)

(0.09-0.21)

(O.16-0. I8) I (mR/ day)

NA NA -(0/52) O j Air Iodine-131 1-131(407) 70 -(0/355) --

(10 3 pel/m3) --

N- 1.45 22(52/52) 20(52/52) O R Air Particulate Gross (407) 10 21(355/355) 3 Beta (4.3-67) (11-54) (9-47)

(10 3 pel/m )

Gamma (32)

SSE-4.5 77(4/4) 69(4/4) O Be-7 -

70(28/28)

(48-87) (71-80) (57-85) j 19(1/4) 12(1/4) 0 K-40 -

11(6/28) S/SSW-1.2 (5.3- 19)

N/A N/A -(0/4) O 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)

(1) ILD is lower limit of detection as de!!ned and required in USNRC Branch Technical I%ttson on an Acceptable Radiological Environmental Monitoring Program . Revtston I, Nwember 1979.

(2) (0 to the ratio of poettive results to the numbe r of samples analyzed for the parameter of interest.

means are of positive results only.

TABLE 20':

(PAGE 2 OF 6)

RADIOLOGICAL ENVIRONMENTAL MONfIURING PROGRAM

SUMMARY

T U ELECTRIC - COMANCHE PEAK SIEAM ELECTRIC STKIlON

l. JANUARY l 'IO DECEMBER 31.1993 l

L Analysis and lower IJmit Number of Medium of Pathway Total Number of All Indicator Imcations locanon with Highest Mean Control Location Nonroutine -

Sampled . ofAnalysis Detection Mean .Name Mean (I)(2) Mean (I)(2) - - Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements '

Milk ~ 1-131 (19) -

NA NA NA -(0/19) 0

' (pC1/l) tuY MDIOCHEMISmY) -- --

Gamma (19)

K-40 -

N/A SW-13.5 1365(19/19) 1365(19/19) 0 (1200-1580) (1200-1580)

Cs-137 -

NA NA NA -(0/19) 0 Ch Surface Water Gamma (56)

!. (pC1/l)

K-40 -(0/42) NA NA -(0/14) 0 Tritium (16) -

-4313(8/12) N- 1.5 4475(4/4) -(0/4) 0 (3400-5700) (3800-5700) --

. Ground Drinking . Gamnsa (f.: -

Water (pC1/I)

- K-40 -

133(1/19) N- 1.45 133(I/5) -(0/4) 0 Tritium (23) -

-(0/19) - NA NA -(0/4) - 0 1

(1) .11D is lower limit of detection as defined and required in USNRC Branch Technical Position on 'l l an Acceptable Radiological Environmental Monitoring Program.. Revision 1. November 1979.

(2) - (f) is the rauo of positive results to the number of samples analyzed for the parameter of interest, means are of positive results only.

l . .. ~

C .

2m 1. . _. -- -_

TABLE 20 (PAGE 3 OF 6)

RADIOLOGICAL ENVIRONMENIAL MONfTORING PROGRAM

SUMMARY

T U ELECIRIC - COMANCIIE PEAK STEAM EIECI'RIC STAllON JANUARY l TO DECEMBER 31.1993 Analysis and Lower Limit Number of Medium of Pathway Total Number of All Indicator Locations location with H! chest Mean Control location Nonroutine Sampled ofAnalysis Detection Mean - Name Mean (0(2) Mean (0(2) Reported (Unit of Measureme -" Perforn:ed (LID) (1) Range Distance and Direction Range Range Measurements Water-Surface Gamma (301 -

-(0/15) NA NA -(0/15)

Drinking (pCl/l) -- --

l Tritium (8) -

4400(4/4) NNW-0.1 3800(4/4) -(0/4) 0 l (3800-4800) (3800-4800) --

Gross Beta (30) -

16(15/15) NNW-0.1 16(15/15) 11(15/15) 0 (11-21) (l1-21) (6.2-19) 1-131 (52) - -(0/26) NA NA -(0/26) 0

$ (BY RADIOCilEMISTRY) --

Fish Gamma (10)

(pCl/kg/ dry)

K-40 -

2506(7/7) NNE-8.0 2883(3/3) 2883(3/3) 0 (1590-3600) (2680-3160) (2680-3160)

CS-137 38(3/7) ENE-2.0 38(3/7) -(0/3) 0 (28-49) (28-49) --

Shoreline Gamma (6)

Sediments (pC1/kg dry) K-40 -

2233(4/4) N-9.9 2501(2/2) 2501(2/2) 0 (1810-2690) (691-4310) (691-4310)

Cs-137 -

47(1/4) NNE-1.0 47(1/2) -(0/2) 0 Pb-212 -

125(4/4) N-9.9 144(2/2) 144(2/2)~ 0 (89-154) (90-197) (90-197) l (1) LLD is lower limit of detection as defined and irquired 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.

_ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _j

6 TABLE 20 (PAGE 4 OF 6)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM

SUMMARY

T U ELECTRIC - COMANCIIE PEAK STEAM ELECIRIC STKDON JANUARY l 'IO DECEMBER 31.1993 Analysis and lower Limit Number of Medium of Pathway Total Number of All Indicator locations Location with Highest Mean Control location Nonroutine Sampled ofAnalysis Detection M'.:an Name Mean (0(2) Mean (0(2) ' Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements Shoreline Gamma (6) i l

Sediments (pCl/kg dry) B1-214 -

275(4/4) NNE-1.0 333(2/2) 296(2/2) 0 (209-386) (279-386) (215-377)

Pb-214 -

327(4/4) NNE- 1.0 376(2/2) 326(2/2) 0 (238-451) (301-451) (172-479)

Ra-226 -

564(4/4) N-9.9 702(1/2) 702(1/2) 0 1 (475-734) -- --

j Th-228 -

121(4/4) N-9.9 139(2/2) 139(2/2) 0 (86-149) (87-191) (87-191) l 4

l

-l (1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Ibsition on an Acceptable Radiological Environmental Monitoring Program . Revision 1. November 1979.

(2) (0 is the rauo of positive results to the number of samples analyr.ed for the parameter of interest.

means are of positive results only. 3

-l l

i

__n__:_-_-____ . _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ , . _ _ _ _ _ __

_;_ J

_ __ ___ ___ _ y_ _m my y -

y TABLE 20 (PAGE 5 OF 6)

RADIOIDGICAL ENVIRONMENTAL MONfIORING PROGRAM

SUMMARY

T U ELEC1RIC - COMANCIIE PEAK STEAM ELEClRIC STAllON JANUARY l 'ID DECEMBER 31,1993 Analysis and Iewer IJmit Number of Medium of Pathway Total Number of All Indicator Locations Location with Highest Mean Control Imcation Nonmutine Sampled ofAnalysis Detection Mean Name Mean (f)(2) Mean (f)(2) Reported (Unit of Measurement) Performed (LLD) (1) Range Distance and Direction Range Range Measurements Broadleaf Gamma (25)

Vegetation (pCl/kg wet) Be-7 -

2087(16/16) SW- 1.0 2338(8/8) 1895(9/9) O

)

(1010-6030) (1080-6030) (646-3940) .i K-40 -

3813(16/16) SW- 13.5 5501(9/9) 5501(9/9) 0 (2010-5840) (1310-9240) (1310-9240) l-131 -

-(0/16) NA NA -(0/9) 0 cn Cs-134 -

-(0/16) NA NA -(0/9) 0 )

cn .. __ __

Cs- 137 -

-(0/16) NA NA -(0/9) O

(

s I

(1) LLD is lower limit of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiological Envimnmental Monitoring Program . Revision 1. November 1979.

(2) (f) is the ratto of positive results to the number of samples analyzed for the parameter of interest.

means are of positive results only.

L__. ._____u. _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ .

__z _ . _ _ _ _ _ ___ _ _ _ _ _____

.. i

- . _ _ _ _ _ _ . . _ - _ . - _ _ y y - --

TABLE 20 (PAGE 6 OF 6)

RADIOLOGICAL ENVIRONMENTAL MONTIURING PROGRAM

SUMMARY

T U ELECTRIC - COMANCHE PEAK STEAM ELECTRIC STATION JANUARY I 'ID DECEMBER 31.1993 Analysis and lower Limit Medium of Pathway Total Number of Sampled All Indicator locations Location with Hichest Mean Number of ofAnalysis Detection Mean Control location Nonroutine (Unit of Measurement) Performed Name (LLD) (1) Range Mean (0(2) Mean (0(2) Reported Distance and Direction Range Range Food Products Measurements Gamma (12)

(pC1/kg wet)

Be-7 194(1/7)

SW- 12.2 873(1/5) 873(1/5) O K-40 2906(7/7)

ENE-9.0 3210(1/1)

(1120-5080) --

3070(5/5) 0 I-131 (1250-6330)

-(0/7) NA NA

-(0/5) 0 O Cs-134

-(0/7) NA NA

-(0/5) 0 Cs-137 -

-(0/7) NA NA

-(0/5) O (I)

LLD ts lower Itmtt of detection as defined and required in USNRC Branch Technical Position on an Acceptable Radiolog! cal Environmental Monitoring Pmgram.. Revision 1. November 1979.

(2)

(0 is the ratio of positive results to the number of samples analyzed for the parameter of interest means are of positive results only. .

i

'i

.1 I

l l

APPENDIX A EPA CROSS-CHECK PROGRAM i

I A-1

EPA INTERLABORATORY COMPARISON PROGRAM 1993 Collection - Teledyne Date Media Nuclide EPA Resultla) Isotopes Result (b) Deviation (c) 01/15/93 Water Sr-89 15.0 1 5.0 12.67 1.15 -0.81 Sr-90 10.0 5.0 8.33 - 1.15 -0.58 01/22/93 Water Pu-239 20.0 2.0 18.00 t 1.00 1.73 ;

01/29/93 Water Gr-Alpha 34.0 9.0 17.33 1.15 -3.21 (d)

Gr-Beta 44.0 t 5.0 52.00 1.00 2.77 (e) h 02/05/93 Water I131 100.0 10.0 106.67 1 5.77 1. l b

)- 1 02/12/93 Water U 7.6 1 3.0 6.93 0.15 -0.38 l 1

03/05/93 Water Ra-226 9.8 1.5 7.67 1 0.12 -2.46 (0 Ra-228 18.5 ! 4.6 19.33 2.31 0.31-04/20/93 Water Gr-Alpha 95.0 24.0 94.33 1 1.15 -0.05 Ra-226 24.9 3.7 19.00 t 1.00 -2.76 (0 Ra 228 19.0 4.8 18.33 0.58 -0.24 Gr-Beta 177.0 27.0 150.0 t 0.00 -1.73 Sr-89 41.0 5.0 35.33 1.53 -1.96 Sr-90 29.0 1 5.0 27.33 1 0.58 -0.58 Co-60 39.0 t 5.0 40.67 ' 3.51 0.58 Cs-134 27.0 5.0 23.67 1.53 -1.15 ;

Cs-137 32.0 5.0 34.33 1 2.08 0.81 l

)

06/04/93 Water H-3 9844.0 1 984.0 9366.67 152.75 -0.84 03/11/93 Water Co-60 15.0 5.0 16.33 1.53 0.46 Zn-65 103.0 10.0 121.33 - 20.09 3. I8 (g)

) Ru-106 119.0 12.0 106.33 15.89 -1.83 Cs-134 5.0 5.0 5.67 1 0.58 0.23

)

i. Cs-137 5.0 5.0 6.67 0.58 0.58 k Ba-133 99.0 10.0 104.33 1 9.29 0.00 I

)

07/10/93 Water Sr-89 34.0i 5.0 31.67 2.52 -0.81 Sr-90 25.0 5.0 24.00 0.00 -0.35

)

h 07/23/93 Water Gr-Alpha 15.0 5.0 18.67 2.08 -1.27 Gr-Beta 43.0 t 6.9 42.67 1 2.52 -0.08 08/13/93 W ater U 25.3 3.0 24.33 0.58 -0.56 1

08/27/93 Air Filter Gr-Alpha 19.0 5.0 17.00 0.00 -0.69 l Gr-Beta 47.0 5.0 49.00 1 1.73 0.69 '

Sr-90 19.0 1 5.0 17.67 1 0.58 -0.46 i Cs-137 9.0 5.0 9.67 0.58 0.23 l

L

EPA INTERLABORATORY COMPARISON PROGRAM 1993 Collection Teledyne Date Media Nuclide EPA Result (a) Isotopes Result (b) 09/09/93 Water Ra-226 14.9 1 2.2 15.33 i O.58 0.34 Ra-228 20.4 i 5.I 20.67 1 1.15 0.09 09/24/93 Milk Sr-89 30.0 5.0 35.67 3.51 1.96 Sr-90 25.0 t 5.0 24.00 1 1.73 -0.35 I-131 120.0 i 12.0 126.67 i 5.77 0.96 5.0 50.67 i 0.58 Cs-137 49.0 1 1. I 5 K 1679.0 1 84.0 1620.00 1 17.32 -1.22 10/08/93 Water 1131 117.0 1 12.0 103.33 5.77 -1.97 10/19/93 Water Gr-Beta 58.0 1 10.0 51.33 1 3.21 -1.15

)- Sr-89 15.0 5.0 15.00 i 1.00 0.00 s Sr-90 10.0 5.0 10.00 i O.00 0.00

/ Co-60 10.0 1 5.0 12.00 i 1.00 0.69 -

. Cs- 134 12.0 1 5.0 9.00 i 1.00 -1.04 Cs-137 10.0 5.0 12.67 1 2.52 0.92

) Gr-Alpha 40.0 10.0 39.67 1 0.58 -0.06

( Ra 226 9.9 1.5 1O.10 1- 0.79 0.23 f Ra-228 12.5 3.1 14.67 i 1.15 1 21 10/29/93 Water Gr-Alpha 20.0 1 5.0 20.33 2.08 0.12-Gr-Beta 15.0 5.0 15.67 1 2.08 0.23

)

f[ l1/5/93 Water H-3 7398.0 740.0 6900.00 1 100.00 -1.17 11/12/93 Water Co-60 30.0 5.0 28.67 2.89 -0.46 Zn-65 150.Oi 15.0 152.00 1 9.17 0.23 Ru 106 201.0 1 20.0 177.33 i 5.51 -2.05 (h).

). Cs-134 59.0 1 40.0 1 5.0 5.0 53.33 41.33 1 4.93 3.06

-1.96 0.46

s. Cs-137

'./ Ba-133 79.0 1 8.0 69.33 3.06 -2.09 (0

)

Y L

)

^-

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 pCi for air particulate filters.

(b) Teledyne Results - Average one sigma. Units are pC1/ liter for water and milk i except K is in mg/ liter. Units are tota pCi for air particulate filters.

(c) Normalized deviation from the known.

(d) The EPA switched from Am-241 to Th-230 alpha spike. We calibrated with Th-230, using sodium nitrate to generate a self-absorption curve. The EPA water, however has minerals which have greater self-absorption than the sodium nitrate matrix. The 1 EPA has agreed to send us a gallon of their water which we can use to prepare a self- )

absorption curve with Th-230. l l

(e) By oversight, we did not use the special self-absorption curve which we had l previously derived using EPA water and Cs-137 standard. We will use the EPA curve i in the future. We may also re-derive this curve using a water sample which the EPA i has agreed to send us. 1 (f) The counting data and backgrounds were vertfled. Possibly some efficiencies used' were erroneously high. causing low values. A less likely cause is an error in dilution.

New Ra-226 standards will be prepared. Closer monitoring of out of control l efficiencies will be done and extra care in preparation of the sample will be maintained.

(g) The calculations were checked and found to be correct. The results of six gamma emitting isotopes were reported to the EPA. The results of four were within 1 normalized deviation; a fifth, within 2 normalized deviations. Only the 2n-65 average was outside the control limits. There is no obvious reason why one isotope would be outside the control limits, while five other isotopes were within control limits. )

I (h) Although the T1 average (177.3) was 2.05 deviations low compared to the EPA value, !

the agreement was good with the average (175.2) of 173 participants. The data was )

reviewed for accuracy including halflife and branching intensity used. No problems I were found. No corrective action anticipated because of the good agreement with the l average of all participants. i j

1 I,

A-4

.l

..1 i

i

.j

-i l

1

-1 APPENDIX B

e. SYNOPSIS OF ANALYTICAL PROCEDURES 1

I i

i B-1

. .. _-____=_-_-__________:___-_____________.

APPENDIX B APPLICABLE PROCEDURES' l

NUMBER TITLE DATE PAGE PRO-032-1 Determination of Gross Alpha 03/21/86 B-3 and/or Gross Beta in Water Samples !

PRO-042-5 Determination of Gamma 04/24/93 B-5 Emitting Radioisotopes 1 PRO-032-10 Determination of Gross Beta 03/01/87 B-7 q in Air Particulate Filters '

PRO-032-11 Determination of Radiciodine 12/15/92 B-8 in Milk and Water Samples PRO-032-12 Determination of Radiciodine 12/15/82 B-9 in Vegetation Samples PRO-342-17 Environmental Thermolumi- 09/04/87 B-10 [

nescent Dosimetry (TLD) '

PRO-032-35 Determination of Tritium in 10/01/93 B-11 Water by Liquid Scintillation B-2

I l

D LEDYNE

-ISOTOPES PRO-032 DETERMINATION OF GROSS ALPHA AND/OR GROSS BETA IN WATER SAMPLES 1

1 i

1.0 INTRODUCTION

1 The procedures described in this section are used to measure the overall 1

radioactivity of water samples without identifying the radioactive species ]

present. No chemical separation techniques are involved.

One liter of the sample is evaporated on a hot plate. Different volumes may be used if the sample has a significant salt content as measured by a conductivity meter, or if' unusual sensitivity is desired. If requested by the customer, the sample is filtered through No. 54 filter paper before evaporation, removing particles greater than 30 microns in size.

After evaporating to a small volume in a beaker, the sample is rinsed into a 2-inch diamett.r stainless steel planchet which is stamped with a concentric ,

ring pattern to distribute residue evenly. Final evaporation to dryness takes 1

place under heat lamps. Samples which appear to be hygroscopic are dried again under heat lamps just prior to counting. j Residue mass is determined by weighing the planchet before and after 1

mounting the sample. The planchet is counted for alpha and/or beta activity.

]

on an automatic proportional counter. Results are calculated using empirical self-absorption curves which allow for the change in effective counting efliciency caused by the residue mass.

2.0 DETECTION CAPABILITY j I

Detection capability depends upon the sample volume actually 1

.\

B-3

T TELEDYNE PRO-032-1 ISOTOPES represented on the planchet, the background and the efficiency of the counting instrument, and upon self-absorption of alpha and beta particles by the mounted sample. Because the radioactive species are not identifled, no decay corrections are made and the reported activity refers to the counting time.

The minimum detectable level (MDL) for water samples is nominally 1.6 picoeuries per liter for gross beta at the 4.66 sigma level (1.0 pCl/l at the 2.83 sigma level), assuming that I liter of sample is used and that 1/2 gram of sample residue is mounted on the planchet. These figures are based upon a nominal counting time of 50 minutes and upon representative values of counting efficiency and background of 0.2 and 1.2 cpm, respectively. The MDL for gross alpha activity is nominally 2.3 picocuries per liter at the 4.66 sigma level (1.4 pCi/l at the 2.83 sigma level) also assuming that I liter of sample is used and 1/2 gram of sample residue is mounted on the planchet. These figures are based upcn a nominal 200 minute counting time and upon a l

representative efficiency of 0.02 and a background of 0.1 cpm. l The MDL becomes significantly lower as the mount weight decreases because of reduced self-absorption. At a zero mount weight, the 4.66 sigma MDL for gross beta is 0.9 picoeuries per liter and the MDL for gross alpha is 0.3 picocuries per liter. These values reflect a beta counting eiTiciency of 0.38 and an alpha counting efilciency of 0.18.

4

{

l 1

B-4 :

1 9

E) T TELEDYNE PRO-042-5 ISOTOPES S

u DETERMINATION OF GAMMA EMITTING RADIOISOTOPE 6 5 Milk and Water a

h A 1.0 liter Marinelli beaker is filled with a representative aliquot of the

$ sample. The sample is then counted for at least 1000 minutes with a shielded

( Ge(LI) detector coupled to a mini-computer-based data acquisition system

)

y which perfonns pulse height analysis.

Dried Solids Other Than Soils and Sediments

) A large quantity of the sample is dried at a low temperature, less than 100 C. As much as possible (up to the total sample) is loaded into a tared 1-H

~ liter Marinelli and weighed. The sample is then counted for at least 1000

.- minutes with a shielded Ge(LI) detector coupled to a mini-computer-based data l9 acquisition system which performs pulse height analysis.

Fish As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then

) counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a

) mini-computer-based data acquisition system which performs pulse height analysis.

}H s Soils and Sediments Soils and sediments are dried at a low temperature, less than 100 C. l h The soil or sediment is loaded fully into a tared, standard 300 cc container and j

,) weighed. The sample is then counted for at least six hours with a shielded l j Ge(L1) detector coupled to a mini-computer-based data acquisition system j

, which performs pulse height analysis. l J j D Charcoal Cartridges (Air Iodine)

) Charcoal cartridges are counted up to five at a time, with one positioned

) on the face of a Ge(Li) detector and up to four on the side of the Ge(Li) detector.

i l

p Each Ge(L1) detector is calibrated for both positions. The detection limit for I- !

131 of each charcoal cartridge can be determined (assuming no positive I-131)

) uniquely from the volume of air which passed through it. In the event I-131 is

) observed in the initial counting of a set, each charcoal cartridge is then counted separately, positioned on the face of the detector.

Air Particulate The four or five (depending on the calendar month) air particulate filters for a monthly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(L1) detector l l

l B-5

TELEDYNE ISOTOPES 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 with a library of peaks for isotope identification and then performs the radioactivity calculation using the appropriate fractional gamma ray abundance, half-life, detector eff1ciency, and net counts in the peak region.

The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume or pCi/ mass:

RESULT = (S-B)/(2.22 t E V F DF)

)

) 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 l

) (region of spectrum ofinterest) '

B = Background area, in counts, under sample peak, determined by a linear interpolation of the representative backgrounds on either side of the

) peak

) .l

) t = length of time in minutes the sample was counted

) 2.22 = dpm/pCi

)

) E = detector efilciency for energy of interest and geometry of sample i

) V = sample aliquot size (liters, cubic meters, kilograms, l j or grams) !

) F = fractional gamma abundance (specific for each

) emitted gamma)

) DF = decay factor from the collection to the counting

) date B-6 1 _ _ - _ _ - _ _ -

T TELEDYNE PRO-032-10 ISOTOPES DETERMMATION 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 (pCi/m3) = ((S/T) - (B/t))/(2.22 V E)

'IWO SIGMA ERROR (pC1/m3) = 2((S/T2+(B/t2))1/2/(2.22 V E)

LLD (pC1/m3) = 4.66(B/t/T)1/2/(2.22 V E) where: S = Gross counts of sample including blank B = Counts of blank E = Counting efficiency T = Number of minutes sample was counted t = Number of minutes blank was counted V = Sample aliquot size (cubic meters) 2.22 = dpm/pCi B-7

T TELEDYNE PRO-032-11 ISOTOPES DETERMINATION OF RADIOIODINE IN MILK AND WATER SAMPLES Two liters of sample are first equilibrated with stable iodide carrier. A batch treatment with anion exchange resin is used to remove lodine from the sample.

The lodine is then stripped from the resin with sodium hypochlorite solution, is reduced with hydroxylamine hydrochloride and is extracted into toluene as free iodine. It is then back-extracted as todide into soritum bisulfite solution and is precipitated as palladium iodide. The precipitate is weighed for chemical yield.

and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.

Calculation of results, two sigma error and the lower limit of detection (LLD) in pC1/l, are performed as follows:

RESULT = (N/At-B)/(2.22 E V Y DF)

TWO SIGMA ERROR = 2((N/At+B)/At)1/2 (2.22 E V Y DF)

LLD = 4.66(B/At)1/2/(2.22 E V Y DF) where: N = total counts from sample (counts)

At = counting time for sample (min)

B = background rate of counter (cpm) 2.22 = dpm/pC1 V = volume or weight of sample analyzed i

Y = chemicalyield of the mount or sample counted DF = decay factor from the collection to the counting date E = efficiency of the counter for I-131, corrected for self absorption effects by the formula:

= Es(exP-0.0085M)/(exp-0.0085Ms)

Es = efficiency of the counter determined from an I-131 standard mount !

Ms = mass of PdI2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg q I

B-8

T 7ELEDYNE PRO-032-12 ISOTOPES DETERMINATION OF RADIOIODINE IN VEGETATION SAMPLES Broadleaf Vegetation This procedure presents radiochemical methods for determining the I-131 activity in vegetation samples. Stable iodide carrier is first added to 25-100 grams of the chopped sample. The sample is then leached with sodium hydroxide solution, evaporated to dryness and fused in a muffle furnace. The melt is dissolved in water, filtered and treated with sodium hypochlorite. The lodine 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 lodide. The precipitate is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting.

Calculation of results, two sigma error and the lower limit of detection (LLD) in pC1/l, are performed as follows:

RESULT = (N/At-B)/(2.22 E V Y DF)

'IWO SIGMA ERROR = 2((N/At+B)/At)1/2/(2.22 E V Y DF)

LLD = 4.66(B/At)1/2/(2.22 E V Y DF) where: N = total counts from sample (counts)

At = counting time for sample (min)

B = background rate of counter (cpm) 2.22 = dpm/pCi V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted DF = decay factor from the collecuon to the counting date E = efilciency of the counter for I-131, corrected for self absorption effects by the formula:

= Es(exp-0.0085M)/(exp-0.0085Ms)

Es = efficiency of the counter determined from an I-131 standard mount Ms = mass of PdI2 on the standard mount, mg M = mass of PdI2 on the sample mount, mg 1

l B-9

TIT.LEDYNE . PRO-342-17 ISOMPES ENVIRONMENTAL THERMOLUMINESCENT DOSIMETRY (TLD)

Teledyne Isotopes uses a CaSO4 :Dy thermoluminescent dosimeter (TLD) which the company manufactures. This material has a high light output, neg-11gible thermally induced signal loss (fading), and negligible self dosing. The energy response curve (as well as all other features) satisfles NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs. ,

Following the field exposure period the TLDs are placed in a Teledyne isotopes ']

Model 8300. One fourth of the rectangular TLD is heated at a time and the i measured light emission (luminescence) is recorded. The TLD is then annealed- l and exposed to a known Cs-137 dose; each area is then read again. This pro- I vides a calibration of each area of each TLD after every fleld use. The transit controls are read in the same manner.

Calculation of results and the two sigma error in net mil 11Roetgen (mR) are performed as follows:

RESULT D= (D1+D2+D3+D4)/4 q TWO SIGMA ERROR

= 2((D 1 -D)2+(D2-D)2+(D3-D)2+(D4-D)2)/3) 1/2 where: D1 = the net mR of area 1 of the TLD, and similarly for '

D2. D3, and D4 .

l

= 11 K/R1 - A 1 11 = the instrument reading of the field dose in area 1 K = the known exposure by the Cs-137 source R1 = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR calculated in similar manner as above, of the transit control TLDs I B-10 p-

T TELEDYNE PRO-032-35 l ISOTOPES j 1

DETERMINATION OF TRITIUM IN WATER BY LIQUID SCINTILLATION !

Ten milliliters of water is added to 10 ml ofligdd scintillation solution in a 25 ml vial. The sample is inserted into a Liquid Scintillator and counted for 100 minutes.

1 Calculations of the results, the two sigma error and the lower limit of detection (LLD), are performed as follows:

l RESULT (pC1/l) = (N-B)/(2.22 V E)

TWO SIGMA ERROR (pC1/l) = 2((N + B)/At)1/2/(2.22 V E)

LLD (pC1/1) = 4.66(B/At)1/2/(2.22 V E) where: N = the gross cpm of the sample B = the background of the detector in epm 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 O

s l

l

- - - - - - - -- -------_----_- Y

l l

i i

4 APPENDIX C

) EXCEPTIONS TO THE 1993 REMP l !

C-1

APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCIIEDULED SAMPLING AND ANALYSIS DURING 1993 DATE OF REASONS FOR LOSS /

LOCATION DESCRIFFION SAMPLING EXCEPTION SW/WSW-0.95 Air Charcoal 04/27-05/04 Power out.

SSE-4.5 Air Charcoal 04/27-05/04 Broken vane.

SW/WSW-0.95 Air Charcoal 05/06-05/11 Power out.

SSE-4.5 Air Charcoal 05/06-05/11 Broken vane. i NW- 1.0 Air Charcoal 05/11-05/18 Bad connection.

SW/WSW-0.95 Mr Charcoal 08/03-08/10 Power out.

E-3.5 Air Charcoal 08/03-08/10 Pump off - personnel error.

N- 1.45 Air Charcoal 10/05-10/12 Pump failure.

SW/WSW-0.95 Air Charcoal 11/16-11/23 Power failure SW/WSW-0.95 Air Charcoal 11/23-11/30 Power failure. I SW/WSW-0.95 Air Filter 04/27-05/04 Power out.

SSE-4.5 Air Filter 04/27-05/04 Broken vane.

SW/WSW-0.95 Air Filter 05/10-05/11 Power out.

SSE-4.5 Mr Filter 05/06-05/11 Broken vane, a

NW- 1.0 Air Filter 05/11-05/18 Bad connection.

SW/WSW-0.95 Air Filter 08/03-08/10 Power out.

E-3.5 Mr Filter 08/03-08/10 Pump off - personnel error ,

N- 1.45 Air Filter 10/05-10/12- Pump failure.

SW/WSW-0.95 Mr Filter 11/16-11/17 Power failure C-2 1

]

1 i

APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM q EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1993 l DATE OF REASONS FOR LOSS /

LOCATION DESCRIFTION SAMPLING EXCEPTION

)

SW/WSW-0.95 Air Filter 11/29-11/30 Power failure.

SW-12.2 Food Product 01/12/93 Sample not available E-4.2 Food Product 01/12/93 Sample not available

)- SW- 12.2 Food Product 02/09/93 Sample not available E-4.2 Food Product 02/09/93 Sample not available

). SW-12.2 Food Product 03/09/93 Sample not available !

E-4.2 Food Product 03/09/93 Sample not available j SW-12.2 Food Product 04/06/93 Sample not available E-4.2 Food Product 04/06/93 Sample not available

)

SW-12.2 Food Product 09/21/93 Sample not available

) SW-12.2 Food Product 10/12/93 Sample not available

) Food Product E-4.2 10/12/93 Sample not available f- SW-12.2 Food Product 11/16/93 Sample not available E-4.2 Food Product 11/16/93 Sample not available j

[ SW-12.2 Food Product 12/14/93 Sample not available E-4.2 Food Product 12/14/93 Sample not available NE-4.8 TLD 01/13-04/15 TLD missing.

NNW-1.35 TLD 01/13-04/15 TLD missing.

SW-13.5 Vegetation 01/12/93 Sample not available N- 1.45 Vegetation 01/12/93 Sample not available C-3 )

-_______-_________-________-_______-_-____-__A

APPENDIX C RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1993 DATE OF REASONS FOR LOSS /

LOCATION DESCRIFrlON SAMPLING EXCEFFION SW- 1.0 Vegetation 01/12/93 Sample not available SW-13.5 Vegetation 02/09/93 Sample not available N- 1.45 Vegetation 02/09/93 Sample not available SW- 1.0 Vegetation 02/09/93 Sample not available SW-13.5 Vegetation 03/09/93 Sample not available.

N- 1.45 Vegetation 03/09/93 Sample not available.

SW- 1.0 Vegetation 03/09/93 Sample not available.

N- 1.45 Vegetation 04/06/93 Sample not available SW- 1.0 Vegetation 04/06/93 Sample not available SW-13.5 Vegetation 12/14/93 Sample not available N- 1.4 5 Vegetation 12/14/93 Sample not available )

l SW- 1.0 Vegetation 12/14/93 Sample not available j WSW-0.1 Groundwater 12/31/93 Pump out of service.

N-9.8 Groundwater 12/31/93 Unable to sample.

Storage tank under-going repair.

l i

C-4

l f

)

4

) I

>- j

)

) APPENDIX D '

)

EXCEEDED REPORTING LEVELS

)

).

)

I-

)

o

APPENDIX D EXCEEDED REPORTING LEVELS 1993 None of the analytical measurements exceeded any notification level.

1 D-2 I

APPENDIX E LAND USE CENSUS l

1 l

l

)

E-1 j i

_ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ . . _ _ _ . _ _ _ . _ _ . _ . _ _ . _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ .)

M

l:::lr = :::

1. ::

r

_ =___

1UELECTP:C

/ CPSES-9317715 November 19,1993

)

) Tc: John C. Finneran,'Jr. (C39) l fL

SUBJECT:

COMANCHE PEAK STEAM ELECTRIC STATION LAND USE CENSUS

{

f Supersedes: CPSES-9230978

)

j- 1 j 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 includes the f' following items: _l

) )

1. Population by Sector and Distance

). Nearest Resident by Sector and Distance

(

2.

f 3. Nearest Garden by Sector and Distance

) 4. Nearest Milk Animal by Sector and Distance .

5. A Map with an Accompanying Map Legend

')

Listed below are public use areas within the five (5) mile radius and the approximate k attendance for the areas in 1992:

)

1. Camp Arrowhead - 3,250

) Dinosaur State Park - 268,915 L

2.

3. Glen Lake Camp - 12,000

) 4. Cedar Brake Girl Scout Camp - 180 I 5. Squaw Creek Park - 39,019 i

6. Keller's Camp - 7,200 March to November

) Tres Rios Camp - 35,000 to 45,000

7.

f 8. Oakdale Camp & Fish - 5,500

9. Oakdale Park - 110,000

) Creation Science Museum - 14,000

) 10.

l

11. Texas Amphitheater - Glen Rose - 80,000 f 12. CPSES Visitors Center - 19,354

13. Exposition Center - Glen Rose - Under Construction

14. Cherokee Rose Manor Nursing Home - Glen Rose -

34 Permanent Residents

15. Somervell Training Center - 3082 P.o. Box 1002 Glen Row. Texas 76043 1002 E-2

s CPSES-9317715 2-Listed below are public use areas within the ten (10) mile radius and the appro.timate attendance for the areas in 1992:

1. Fossil Rim Wildlife Ranch - 80,000+

2. Granbury Opera House - 77,000

3. Granbury Queen Riverboat - 26,000 4 Other Fishing Camps - 10,000

5. Stevens Ranch Girl Scout Camp - 2,814-As required by commitment 22585 and Memorandum NE-24059, reference shipment' and storage of liquified chlorine gas within 5 miles of CPSES, the following conditions were found.

1. No new areas of usage of chlorine gas was found within 5 miles of CPSES.

2. The following places were called to assure any changes or uses of chlorine gas within their areas.' These areas reported no change in uses as reported in letter THP-88 0040, December 20,1988..

Happy Hill Farm Oakdale Park Glen Lake Camp City of Stephenville City of Glen Rose

)

OmkN Donna Kay Cole (T61)

Environmental Technician -

DKC:am Attachments cc: CCS E06 D. N. Hood TO2 R. J. Prince M37

]

1 i

j

.j E-3

- -J

CPSES 9317715 3-Population (*) By Sector and Distance 0-1 1-2 2-3 3-4 4-5 Total N - -

(112 27 72 101 NNE - -

8 69 13 90 NE - - 48 72 245 365 l ENE - -

43 19 21 83 l 1

E - -

32 (21186 (3)26 244 j ESE -

(4)2 8 96 109 215 SE -

8 66 27 43 144 SSE -

27 35 37 (512471 2570 S -

32 21 21 96 170 SSW - 3 5 (6)2 37 47 SW - 59 3 35 35 132 WSW 13 72 3 11 3 102 W - 48 6 43 6 103 WNW - -

3 24 82 109 NW - -

3 -

3 6 NNW - -

3 35 8 46 TOTAL 13 251 289 704 3270 4527'* -1

)

Based on an average of 2.66 residents per house. (Obtained from North {

Central Texas Council of Governments),1992 based on an average from 2.57 for Hood County and 2.74 for Somervell County.

(1) Includes permanent residents at Squaw Creek Park of 2 residents.

(2) includes permanent residents at Happy Hill Children's Home of 165 residents.

(3) includes permanent residents at Camp Arrowhead of 5 residents and Keller's Camp of 2 residents, i

E-4

CPSES-9317715 (4) includes permanent residents at SomervellTraining Center of 2 residents.

(5) includes permanent resident at Cherokee Rose Manor of 34 residents and the Glen Rose population of 2,400 residents.

(6) includes permanent residents at Dinosaur Valley State Park of 2 residents.

- Difference in population for 1993 Census is due to using an estimate for Glen Rose on 1992 Census based on telephones, water meters, and volume of wastewater treated. Population of 2,400 as stated by Byron St. Clair, City Superintendent.

Nearest Resident by Sector and Distance Sector Distance (Miles)

N 2.2 NNE 2.4

NE 2.3 ENE 2.4 E 2.4 ESE 2.0 SE 1.9 '

SSE 1.5

S 1.5 '

SSW 1.9

)

) SW 1.1

WSW 1.0 W 1.5 WNW 2.95 NW 2.7 NNW 2.7

Denotes change from previous year E-5

CPSES 9317715 l Nearest Garden by Sector and Distance l 4

Sector Distance (Miles) l N 3.4 '

NNE 2.5 NE 2.5 ENE 2.4

E 3.5

ESE 3.3 ' ]

SE None' l

)

SSE 2.3 *

)

) S 1.8 SSW 4.4' )

SW 1.7 '

1.1 * !

WSW J W 1.5 WNW 3.0*

NW None

)

NNW 3.7

) Nearest Milk Animal by Sector and Distance

)

[ .

Sector - Distance (Miles)

)

) NNW 4.9

SSE 2.2 E 3.5 '

NE None

Denotes change from previous year.

E-6

CPSES 9317715 6-Map Legend N-1.0 to 2.5 Squaw Creek Park N 3.4 to 3.5 - Gardens N 4.4 15 SC 4 N-4.5 to 4.8 Gardens N 4.7 Business NNE-2.4 Garden NNE-3.2 2 SC, Garden NNE-3.3 100 SC, Gardens NNE-3.4 40 SC NNE-3.5 to 3.6 Gardens NNE 3.7 Business with 6 Cabins - Flip's NNE-3.8 6 SC, Gardens NNE-4.4 Gardens NNE-4.5 50 SC NNE-4.7 35 SC,15 Goats NE-2.5 to 2.9 Gardens '

NE-2.8 RV Park-Midway Pines NE-3.0 Business with RV Park NE 3.2 20 SC, Gardens NE-3.5 40 SC NE-3.8 13 SC NE-3.9 Garden NE-4.1 Gardens NE-4.3 TO 4.9 Gardens

) N E-4.8 100 SC ENE-2.5 Garden

) ENE-2.6 Garden,4 SC ENE-2.8 Garden,6 SC ENE-4.0 Business - Sand & Gravel ENE-4.2 50 SC ENE-4.3 Pecan Orchard

) ENE 4.5 4GSC l

ENE-4.9 Garden E-2.4 Garden E-3.5 Garden,15 SC, 4 DC, 6 Goats, 8 Sheep - Happy Hill Children's Home

) Business - RV Park (Oakdale Camp and Fish)

( E-3.9 E-4.0 Keller's Camp - RV Park E-4.4 Truck Garden - Hornick E-4.8 Camp Arrowhead - 250 SC ESE 2.0 T.U. Electric - Somervell Training Center ESE-2.4 35 SC E-7

1

\

l CPSES 9317715 7-ESE 2.8 100 SC f ESE 3,3 to 3.4 Businesses, Garden 100 SC

) ESE-3.4 -

Gardens,50 SC ESE 3.7 to 3.9

)

ESE 4.1 Garden ESE 4.7 to 4.9 Gardens

) ESE 4.7 Business SE 3.0 Texas Amphitheater - Glen Rose

)

SE-4.3 New Exposition Center

) SE 4.5 Squaw Valley Golf Course

)

i SE-5.0 Camp Tres Rios

) SSE 2.3 Garden SSE-2.2 Daffan Dairy j h 35 SC SSE-4.2 ]

) SSE-4.3 Cherokee Rose Manor )

( I SSE-4.5 City of Glen Rose, Texas l

) SSE-4.7 Oakdale Park SSE-4.8 Glen Lake Camp

) S-1.8 Garden S-2,2 100 SC

) S-2.6 30 SC

) S-4.0 Business l S-4.9 Business - Day Care Center, Garden,20 SC SSW-3.0 to 4.0 Dinosaur Valley State Park

) SSW-4.4 Garden SSW-4.8 Creation Science Museum,3 SC

)

j SSW-4.9 Business SW-1.1 to 1.7 Trailei Park SW-1. 7 Businesses, Garden

) SW-1.9 Garden

) SW-2.0 30 SC t

SW-3.6 Garden SW-4.6 Cedar Brake Girl Scout Camp,35 SC

) WSW-1.1 to 1.7 Gardens

) WSW-1.6 Trailer Park, Gardens

) WSW-2.8 Gardens WSW-3.4 Garden WSW-4.9 Garden W-1. 5 Gardens,30 SC f

W- 1.9 100 SC f

W-3.4 Garden W-3.8 Garden, Hill City WNW-3.0 Garden WNW-3.3 100 SC t

e-8 f - -

CPSES 9317715 8 WNW-3.7 50 SC WNW-4.4 30 SC WNW 4.6 Gardens WNW-4.8 Business NW. Squaw Creek Ranching Area NNW 2.5 to 2.9 Squaw Creek Ranching Area,200 SC NNW 3.6 Gardens,10 SC NNW-3.7 3 SC NNW 4.4 50 SC NNW-4.6 Garden NNW 4.9 Garden,10 SC,20 DC DC- Dairy Cattle SC - Stocker Cattle O Occupied Residence e Unoccupied House 9 Institutions / Recreational Areas (Green)

E Business A Dairy 35 Truck Farm (Red) a Gardens (Red)

)

E-9

Evaluation of the 1993 Land Use Census Page 1 of 2 The results of the 1993 Land Use Census were reviewed for impact on the Radiological Envirorznental Monitoring Program (REMP). The specific areas revieued, that could be affected by changes found in the land use census, were the sampling requirements for Milk, Broadleaf Vegetation and Food Products.

Reviewing the milk sampling requirements from the ODCM Table 3.12-1 reveals 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.

Currently the only location where milk samples ere collected is at a control location (SW-13.5). There are currently no identified milking animals (cow or goat) within the specified distances.

Since not all milk samples are available the broadleaf vegetation sampling specified in ODCM Table 3.12-1 is being performed. Broadleaf sample requirements are such that samples of broadleaf vegetation are to be collected from each of two offsite locations of highest predicted annual average D/Q if milk sampling is not performed at all required locations.

Currently, broadleaf vegetation samples are collected at two indicator locations (N-1.45 and SW-1.0) and one control location (SW-13.5). These locations are near the site boundary in sectors where broadleaf vegetation is available and D/Q is greatest. Therefore, no changes to the broadleaf sampling program are required.

Food Product sample requirements of ODCM Table 3.12-1 requires that one sample of each principal class of food product be collected from any area that is irrigated with water in which liquid plant wastes have been discharged. Of the gardens identified in the land census, no new gardens were located in an area that irrigate w.ich water in which liquid plant wastes are discharged. Currently, food products are sampled from two indicator locations (ENE-9.0, pecans; E-4.2, vegetables) and one control location (SW-12.2). Therefore, no changes are required in the Food Product sampling program.

E-10 i

Page 2 of 2 In summary, the 1993 Land Use Census did not identify-any new locations that are available for sampling and would yield a calculated dose greater than at the current sampling locations.

In addition to reviewing the sampling location requirements for milk, broadleaf and food products, changes to the controlling receptor locations and pathways and associated atmospheric dispersion parameters given in ODCM, Part II, Table 2.5 were reviewed. This table will also require I revision as these parameters are used in dose calculations i required by Radiological Effluent Control 4.11.2.3. Table 2.5 will be revised to reflect the 1993 Land Use Census data changes. i I

Besides the required reviews and changes mentioned above the i census pointed out that the permanent resident population in the census zone has not changed significantly and the attendance at public use facilities increased only slightly compared to 1992.

Evaluation performed by: [ (.- -

. Date: /~M- W

/

E-11

ML20029C994

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