ML20245E710
| ML20245E710 | |
| Person / Time | |
|---|---|
| Site: | Callaway  |
| Issue date: | 12/31/1988 |
| From: | Schnell D UNION ELECTRIC CO. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| ULNRC-1994, NUDOCS 8905020110 | |
| Download: ML20245E710 (339) | |
Text
{{#Wiki_filter:-. _-. . _ - - _ _ -_ -. i Q, CALLA WAY PLANT ANNUAL ENVIRONhfENTAL OPERATING REPORT 1988 l i l
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DOCKET NO. 50-483 N ELNB1UC o a 890502011D 881231 gas Anockosoogs
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i O TABLE OF CONTENTS { 1.0 Introduction 2.0 Conclusion 3.0 Radiological Environmental Monitoring 3.1 Summary Report 1988 3.2 First Quarter Report 1988 3.3 Second Quarter Report 1988 , 3.4 Third Quarter Report 1988 3.5 rourth Quarter Report 1988 l l 4.0 Non-Radiological Environmental Monitoring 5.0 Plant Modification Environmental Evaluation O l l I i i i 1
1.0 INTRODUCTION
The Callaway Plant received an Operating License on June 11, 1984. This report presents the analytical data from the environmental monitoring programs with appropriate interpretation for 1988 and the environmental evaluations for plant modifications completed during 1988. The first section of this report summarizes and interprets the resultc of the radiological environmental monitoring program conducted in accordance with Technical Specification Section 3/4.12. Section 2 describes the non-radiological environmental program and its results conducted in accordance with Section ~. 2 of Appendix B to the Callaway Plant Operating License. The third section of this report describes changes in plant design or operation, test, and experiments made in accordance with section 3.1 of Appendix B of the Callaway Plant Operating License. This Annual Environmental Operating Report is submitted in accordance with Section 6.9.1.6 of the Technical Specification and Appendix B to the Callaway Plant Operating License. 9
2.0 CONCLUSION
The first section of this report contains all the radiological environmental monitoring conducted in the vicinity of the Callaway Plant during 1988. The comparison of the results for the radiological environmental monitoring conducted during 1988 to the preoperational data showed no unexpected or adverse effects from the operation of the Callaway Plant on the environment. Thaze was no non-radiological monitorinc conducted in the vicinty of the Callaway Plant during 1988. There were no plant modifications completed during 1988 with an unreviewed environmental question as shown in Section 3 of this report. O
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I 1 4 1 l 1 i l 1 SECTION 3.0' UNION ELECTRIC COMPANY O. CALLAWAY PLANT l d RADIOLOGICAL ENVIRONMENTAL MONITORING 1988 s
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l SECTION.3.1 RADIOLOGICAL ENVIRONMENTAL MONITORING ~ ANNUAL
SUMMARY
REPORT 1988 i i l l
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UNION ELECTRIC COMPANY ST. LOUIS, MISSOURI , CALLAWAY PLANT UNIT I j i OPERATIONAL RADIOLOGICAL MONITORING PROGRAM 1988
SUMMARY
REPORT j I SUBMITTED BY: CONTROLS FOR ENVIRONMENTAL POLLUTION,INC. 1925 ROSINA STREET SANTA FE, NEW MEXICO Copy No. 11 l Prepared by: M Bob Bates, Contract Manager f .N ^ Approved by:
&mes I Mueller, President i
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g CONTENTS Section Title Page Abstract 1 1.0 Introduction 2 2.0 Description of the Monitoring Program 3 3.0 Data Interpretations and Conclusions 3 4.0 Annual Summary 50 Appendix A 1988 Land Use Census 58 O O
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i] TABLES Number Title Page I Thermoluminescent Dosimetry (1988 Annual) 13,
!! 1988 Mean Gross Alpha and Gross Beta Activities in Well Water (pCi/l) 20 III 1988 Mean Gross Alpha and Gross Beta Activities in Surface Water (pCi/l) 26 IV 1988 Mean Gross Alpha and Gross Beta Acti'! ties in Sedim ents (pCi/g - dry) 35 V 1988 Mean Gross Alpha and Gross Beta Activities j in Fish (pCl/g - dry) 43 VI Environmental Radiological Monitoring Program, Annual Summary 51 /~
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FIGURES f% a s Number Title Page 1 Gross Beta in Air Particulate Weekly Activity (pCi/m3) l Station Al 6 2 Gross Beta in Air Particulate Weekly Activity (pCi/m3) l Station A7 7 3 Gross Beta in Air Particulate Weekly Activity (pCi/m3) l Station A8 3 4 Gross Beta in Air Particulate Weekly Activity (pCi/m3) Station A9 9
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'5 Cross Beta in Air Particulate Weekly Activity (pCi/m3)
Station B3 10 6 Gross Beta in Air Particulate-Mean Weekly Activity (pCi/m3) 11 7 Monthly Gross Alpha and Gross Beta Activity (pCi/l) Well Water Station D01 21 8 Monthly Gross Alpha and Gross Beta Activity (pCi/l) O weii weter steriom eo5 22 l 9 Monthly Gross Alpha and Gross Beta Activity (pCi/1) Well Water Station FI5 23 10 Monthly Cross Alpha and Gross Beta Activity (pCi/l) Surface Water Station S01 27 11 Month!y Gross Alpha and Gross Beta Activity (pCi/1) Surface Water Station 502 28 12 Monthly Gross Alpha and Gross Beta Activity (pCi/l) Surface Water Station 503 29 13 Quarterly Gross Alpha Activity (pCi/g) Washload Sediment Location A 36 l 14 Quarterly Gross Beta Activity (pCi/g) Washload Sediment Location A 36 15 Quarterly Gross Alpha Activity (pC1/g) Washload Sediment Location C 36 16 Quarterly Gross Beta Activity (pCl/g) j Washload Sediment Location C 36 l l O '
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FIGURES O Number Title Page ; 17 Quarterly Gross Alpha Activity (pCi/g) Washload Sediment Location D 37 1 18 Quarterly Gross Beta Activity (pCi/g) Washload Sediment Location D 37 19 Quarterly Gross Alpha Activity (pC1/g) Bedload Sediment Location A 37 20 Quarterly Gross Beta Activity (pCi/g) Bedload Sediment Location A 37 - 21 Quarterly Gross Alpha Activity (pCi/g) Bedload Sediment Location C 38 22 Quarterly Gross Beta Activity (pCi/g) Bedload Sediment Location C 38 I 23 I Quarterly Cross Alpha Activity (pCi/g) Bedload Sediment Location D 38 l 24 Quarterly Cross Beta Activity (pCl/g) I Bedload Sediment Location D 38 25 Quarterly Cross Alpha Activity (pCi/g) Bottom Sediment Location A 39 26 Quarterly Gross Beta Activity (pCi/g) Bottom Sediment Location A 39 27 Quarterly Cross Alpha Activity (pCi/g) Bottom Sediment Locatloa C 39 28 Quarterly Cross Beta Activity (pCi/g) Bottom Sediment Location C 39 29 Qurrterly Gross Alpha Activity (pCi/g) Bottom Sediment Location D 40 30 Quarterly Gross Beta Activity (pCi/g) l Bottom Sediment Location D 40 31 Monthly Gross Alpha and Gross Beta Activity (pCi/g) Fish Location A 44 2 Monthly Cross Alpha and Gross Beta Activity (pCi/g) Fish Location C 45 I O 33 Monthiv Gross nighe and Cress Bete activitz (aCi/s) Fish Location D 46 l
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O ^8strect The Radiological Environmental Monitoring Program is an ongoing study conducted by Controls for Environmental Pollution, Inc. (CEP) for Union Electric Company (UEC), Callaway Plant, Unit 1. This report is a sumrnary of all data obtained from samples collected by UEC personnel during 1988. Tne monitoring program provides a co.mprehensive environmental analysis of radiological activity in the area surrounding the Ca!!away Plant Site. CEP analyzed the following types of samples: air particulate and radioiodinc, ground water, surface water, milk, washload sediment, bedload sediment, bottom sediment, shoreline sediment, fish, vegetation, soil and 3 direct radiation (TLD). A statistical analysis and graphic presentation for all analytical results for samples collected during 1988 are included in this summary report. Possible trends and anomalous results, as interpreted by CEP are also discussed. l l 0 f L - - - - - - - - - - - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - . - - - - - - - - - - m - - - - - - _ - - _ - _ - _ _ - - - - -
l l 1 1.0 Introduction h i This report presents an analysis of the results of the Radiological Environmental Monitoring Program (REMP) conducted during 1988 for Union Electric Company, Callaway Plant, Unit 1. . In cornpliance with federal and state regulations and in its concern to maintain the quality of the local environment UEC began its radiological monitoring program in April,1982. The objectives of the radiological environmental monitoring program are as follows:
- 1) to establish baseline radiation levels in the environs prior to reactor operations; 2) to monitor potential critical pathways of radioeffluent to man; 3) to determine radiologicalimpact on the environment caused by the operation of the Callaway Plant.
O A number of techniques are being used to distinguish Callaway Plant effects from other sources during the operational phase, including application of established background levels. Operational radiation levels measured in the vicinity of the Callaway Plant will be compared with the pre-operational measure r.cnts at each of 1 the sampling locations. In addition, results of the monitoring program wi!! help to ) evaluate sources of elevated Jevels of radiation during reactor operation in the environment, e.g., atmospheric fa!!out or abnormal plant releases. The Callaway Plant is located on a plateau approximately five miles north of the i Missouri River in Callaway County, Missouri. The plant consists of a 1150 MWE pressurized water reactor, which achieved initial criticality on October 2,1984. O h 2.0 Description of the Monitoring Program Union Electric Company has contracted with Controls for Environmental Pollution, Inc starting May,1983, to determine the radiation levels existing in and around the i l Callaway Plant area. Prior to this time, all analyses were performed by Radiation Management Company. l l I i UEC personnel collected the samples and shipped them to CEP for analysis. The type l of samples collected were: milk, surface water, groundwater, shoreline sediment, bottom sediment, bedload sediment, washload sediment, soil, fish, vegetation, airborne particulate, airborne radioiodine and direct radiation (TLD). Information regarding sample preparation and analytical methods, instrumentation, detection limits, etc. used by CEP may be found in the First Quarterly Report for l O 1988. ' i 3.0 Data Interpretations and Conclusions This section addresses interpretations and conclusions regarding all types of samples analyzed during this report period. A varie , of radionuclides, both naturally occuring and man-made, were detected in the environment around the Callaway Plant. The man-made radionuclides found were the fission products typically found in nuclear test fallout. The levels and fluctuations of radioactivity detected in the samples collected around the Callaway Plant were consistent with previously accumulated environmental data. For this reporting period there was no reportable levels of radioactivity as a result of plant effluents, or analysis in which the detection limit was not achievable.
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3.1 Airborne Particulate and Radioiodine $ l Airborne particulate samples were co!!ected from five monitoring stations. All i of the air particulate samples were analyzed for Gross Beta activity. ' Gamma Spectrometry, Strontium-89 and Strontium-90 analyses were performed on quarterly composites from each station. The airborne' particulate s.ations were j also sites for airborne radiolodine. . . The range and 1988 ' annual mean. Gross Beta activity at each of the sampling locations follows. Measurements are in pCi/m3 Collection 1988 Location Minimum Maximum Annual Mean .{ A1 0.00310.001 0.04420.002 0.02210.007 A7 0.00820.001 0.05110.002 0.02210.008 A8 0.00910.002 0.05120.002 0.02210.006 A9 0.01120.002 0.03810.002 0.02220.006 l B3 0.00710.001 0.04310.002 0.02310.006 Gross Beta levels at all monitoring stations during 1988 are consistent with the control station and do not indicate any anomolous data. Graphic presentations of the Weekly Gross Beta activities for each collection location are presented in Figures 1 through 5. Invalid samples are those with anomolous Gross Beta activity due to air sampler malfunction (i.e. hour meter malfunction, sampler malfunction, etc.) or other circumstances which may have compromised the sample integrity. I Figure 6 presents the Mean Weekly Gross Beta activity for all collection locations. The lowest Mean Weekly Gross Beta activity (0.01010.002 pCi/m3) was observed from 09/22/88-09/29/88 while the week exhibiting the highest activity was 02/04/88-02/12/88 (0.04520.006 pCi/m3). g) s I Q Mean Quarterly Cross Beta activities were as follows: pCi/m 3 January - March 1988 0.024 1 0.010 April- June 1988 0.021 2 0.005 July - September 1988 0.021 2 0005 October - December 1988 0.023 2 0.005 Strontium-90 was detected in one of the quarterly composite samples during 1988. The first quarter cv.nposite for Site A8 indicated Strontium-90 activity of 0.00230.001 pCi/m3 Gamma-emitting nuclides of interest detected in quarterly air particulate composites were limited to Beryllium-7. (See individual quarterly reports). Airborne radiciodine was detected in one sample during the first quarter of 1988. O
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3.2 Thermoluminescent Dosimetry h l Thermoluminescent Dosimetry (TLD) was employed to determine direct radiation ) levels in and around the Callaway Site. Panasonic model UD-814 TLD's sealed in plastic bags were placed in polypropylene mesh cylindrical holders at 52 i locations and exchanged quarterly and annually. Listed below are the mean readings in mrem /Std. Qtr for all TLD's placed around the Callaway Site. First Quarter 17.921.6 Second Quarter 19.931.9 Third Quarter 21.222.0 Fourth Quarter 19.011.3 Annual 17.421.3 Data appearing in Table Iis the result of reading and averaging the Ca 504 : Tm elements. Net exposures were obtained by normalizing the total exposure to a 90-day quarter (standard quarter). Exposure levels for all monitoring locations during 1988 were consistent with background levels observed during previous years. ,
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TABLEI THERMOLUMINESCENT DOSIMETRY 1988 ANNUAL ! 1 Net Field Total , Exposure Station Time Exposure Identification (mrem /Std Collection Location (Days) (mrem i 20) Qtri 2o) C A-ID M-1 11 Mi NW, City Limits of Fulton on Hwy 2, 0.8 Mi East of Business 54 365.0 71.0 10 5 17.5 12 1 C A-IDM-2 6.6 MI NW, County Road 111, 0.6 Mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No.17571 364.9 75.3 12 7 18.6 18 1 CA-IDM-3 1.3 Mi NW,0.1 Mi West of Hwy CC on gravel Road 0.8 Mi South Hwy 0, Callaway Electric Cooperative Utility Pole No.'18559 366.0 78.6 10 19.3 5 22 1 C A-IDM-4 1.9 Mi N,0.3 Mi East of the O and CC ' Junction, Callaway Electric Cooperative Utility Pole No.18892 366.0 64.6 205 15.9 12 1 O c^-io"-5 i 3 mi e"e. erimerx "eteoroto8 ceii Tower - 237.0 40.9 1 1.s 15.3 17 0 C A-IDM-6 2.0 Mi W, County Road 428,1.2 Mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18609 364.8 73.7 + 6.0 18.2 + 1.5 CA 4DM-7 1.3 Mi S, County Road 459,2.6 Mi North of Hwy 94, Callaway Electric Cooperative j Utility Pole No. 35097 365.9 71.2 14 2 17.5 160 C A-IDM-8 2.9 Mi S, County Road 459,1.4 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06823 365.9 77.1 179 19.0 14 2 C A-ID M-9 3.7 Mi S, NW Side of the County Road 459 and 94 Junction, Callaway Electric Cooperative Utility Pole No. 06754 365.9 77.1 155 19.0 131 C A-IDM-10 4.0 Mi SSE, Hwy 94,1.8 Mi East of County Road 459, Callaway Electric Cooperative Utllity Pole No.12182 365.9 74.5 299 18.3 14 2 CA-IDM-ll 4.8 Mi SE, City of Portland, Callaway Electric Cooperative Utility Pole No.12112 365.9 80.6 243 19.8 18 0 O
1 l TABLE I (Cont.) THERMOLUMINESCENT DOSIMETRY hl 1988 ANNUAL Net Field Total Exposure Station Time Exposure (mrem /Std ; Identification Collection Location (Days) (mrem 1 2 0) _Qtr i 20) q CA-IDM-12 5.3 Mi SE, Hwy 94,0.6 Mi South of Hwy D, Utility Pole on East Side of Hwy 366.9 75.4 11 7 18.5 17 1 C A-ID M- 13 5.6 Mi ESE, Hwy 94,0.75 Mi East of Hwy D, Kingdom Telephone Pole No. 2X1 366.9 77.3 + 5.2 19.0 + 1.3 C A-IDM-14 5.0 Mi ESE, SE Side of Intersection D and 94, Callaway Electric Cooperative Utility Pole No.I1940 366.9 76.3 38 4 18.7 32 1 C A-IDM-15 4.2 Mi ESE, Hwy D,2.5 M1 North of Hwy 94, Callaway Electric Cooperative Utility Pole No.27379 366.9 70.2 + 8.9 17.2 + 2.2 l C A-ID M-16 4.1 Mi ENE, Hwy D,3.6 Mi North of Hwy 94, 3 Callaway Electric Cooperative Utility Pole W No.12976 366.9 65.4 + 5.6 16.1 1.4 C A-IDM-17 4.0 Mi E, County Road 4053, 0.3 Mi East of Hwy 94, Kingdom Telephone Company Pole No.3X12 366.9 72.2 17 6 17.7 26 1 C A-IDM-18 3.8 Mi ENE, Hwy D,0.4 Mi South of Hwy O, Callaway Electric Cooperative Utility Pole { No.12952 366.9 71.8_+ 4.9 17.6 _+ 1.2 CA-1DM-19 4.2 hii NE, Hwy D,0.3 Mi North of Hwy O, Callaway Electric Cooperative Utility Pole No.12918 366.9 73.7 + 3.2 18.1 + 0.8 CA-IDM-20 4.8 Mi NE, City of Readsville, Callaway Electric Cooperative Utility Pole No.12830 366.9 73.1 14 6 18.4 16 1 C A-IDM-21 4.0 Mi NNE, County Road 155,1.9 Mi North of Hwy O, Callaway Electric Cooperative
' Utility Pole No.19100 366.9 72.5 30 5 17.8 32 1 C A-ID M-22 2.5 Mi NNE, County Road 150,0.5 Mi North of Hwy O, Callaway Electric Cooperative Utility Pole No.19002 366.9 74.6_+ 3.7 18.3_+ 0.9
TABLE IX (Cont.) , i THERMOLUMINESCENT DOSIMETRY FOURTH CUARTER 1988 ; Net Field Total Exposure Station Time Exposure (mrem /Std Identification Collection Location (Days) (mrem i 2 0) Otr i 20) , CA-IDM-23 6.7 Mi NNE, City of Yucation, Callaway Electric Cooperative Utility Pole No.12670 366.9- 75.9 189 18.6 142 CA-IDM-24 7.0 Mi NE, County Road 191,2.1 Mi North of
' Hwy K, Callaway Electric Cooperative Utility Pole No.12498 366.9 65.9 + 5.0 16.2 32 1 C A-ID M-25 8.7 Mi E, County Road 289,0.3 Mi South of ,
County Road 287, Callaway Electric l Cooperative Utility Pole No.11295 366.9 71.9 358 17.6 312 C A-ID M-26 12.1 MI E, Town of Americus, Callaway Electric Cooperative Utility Pole No. I1159 366.9 48.4 114 11.9 101 C A-ID M-27 9.5 Mi ESE, Town of Bluff ton, Callaway 0 - eiectric cooperative utility Pole No.11496 366.9 _73.0 162 17.9 160 CA-IDM-28 3.3 Mi SE, County Road 469,2.0 Mi North of 1 Hwy 94, Callaway Electric Cooperative Utility Pole No. 06896 ) 365.9 MISSING MISSING ! CA-IDM-29 2.7 Mi SSW, County Road 448,1.2 Mi North l of County Road 459, Callaway Electric l Cooperative Utility Pole No. 06851 365.9 66.9 127 16.3 181 CA-IDM-30 A.6 Mi SSW, W Side of County Road 447 and 463 Junction, Kingdom Telephone Company I Pole No. 2K1 365.9 68.5 16.8,10 6 162 C A-IDM-31 7.6 Mi SW, City of Mokane, Callaway Electric Cooperative Utility Pole No. 06039 365.9 73.4 174 18.0 12 1 CA-IDM-32 5.4 Mi WSW, Hwy VV,0.6 Mi West of County Road 447_, Callaway Electric Cooperative Utility Pole No. 27031 365.1 72.9 178 18.0 11 2 CA-ID M-33 7.3 Mi W, City of Hams Prairie, SE of Hwy C and AD Junction l 365.1 70.3 183 17.3 19 0 O 1 i
l TABLE I (Cont.) - THERMOLUMINESCENT DOSIMETRY h-1988 ANNUAL Net-Field Total Exposure - Station Time Exposure (mrem /Std _ Identification Collection Location (Days) (mrem t 2 0) - Qtr i 20) CA-IDM-34 9.7 Mi WNW, NE Side of Hwy C and County Road 408 Junction 365.1 68.4 + 4.4 16.9 + 1.1 CA-IDM-35 5.8 Mi NNW, City of Toledo, Callaway Electric Cooperative Utility Pole No.17684 364.9 68.8 18 5 17.0 1 1.4 C A-IDM-36 5.2 Mi N, County Road 155,0.8 Mi South of County Road 132, Callaway Electric Cooperative Utility Pole No.19137 366.9 73.3 17 6 18.0 16 1 CA-IDM-37 0.7 Mi SSW, County Road 459,0.9 Mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35077 365.9 69.7 12 6 17.1 15 1 CA-IDM-38 4.8 Mi NNW, County Road 133,1.5 Mi South of Hwy UU, Ca!!away Electric Cooperative a W Utility Pole No. 34708 364.9 58.0 11 2 14.3 15 0 CA-IDM-39 5.4 Mi NW, County Road 112,0.7 Mi East of County Road 111, Callaway Electric Cooperative Utility Pole No.17516 364.9 69.6 175 17.2 14 1 CA-IDM-40 4.2 Mi WNW, NE Side of County Road 112 and
+ Hwy 0, Callaway Electric Cooperative Utility Pole No. 06326 364.9 70.3 104 17.3 i 1.0 C A-IDM-41 4.8 Mi W, Hwy AD,2.8 Mi East of Hwy C, Callaway Electric Cooperative Utility Pole No. I8239 365.1 68.6 125 16.9 13 1 !
CA-IDM-42 4.4 Mi SW, County Road 447,2.6 Mi North of i
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County Road 463, Callaway Electric Cooperative Utility Pole No. 06326 365.1 59.1 195 14.6 15 1 i C A-ID M-43 0.5 Mi SW, County Road 459,0.7 Mi South of i l Hwy CC, Callaway Electric Cooperative ! Utility Pole No. 35073 365.8 69.3 116 17.0 151 C A-IDM-44 1.7 Mi WSW, Hwy CC,1.0 Mi South of County Road 459, Callaway Electric Cooperative Utility Pole No.18769 i 365.8 71.8 144 17.7 11$1 1
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l l J TABLE I (Cont,)
. THERMOLUMINESCENT DOSIMETRY 1988 ANNUAL Net I Field Total Exposure l Station - Time Exposure Identification (mrem /Std Collection Location (Days) (mrem 1 20) ' Qtr i 7 0) !
CA-IDM-45 1.0 Mi WNW,' County Road 428, 0.1 Mi West i i of Hwy CC, Callaway Electric Cooperative l Utility Pole No.-18580 364.8 69.0
, 107 '17.0 17 1 CA-IDM-46 1.5 M1 NNW, NE Side of Hwy CC and County Road 466 Intersection, Callaway Electric Cooperative Utility Pole No. 28242 366.0 71.2 246 17.5 g 1.6 CA-IDM-47 0.9 M1 NNE, County Road 448, 0.9 Mi '
South of Hwy 0, Callaway Electric Cooperative Utility Pole No. 28151 365.9 66.1 238 16.3 112 C A-ID M-48 0.4 Mi NE, County Road 448,1.5 Mi South . of Hwy O, Plant Security Sign Post 365.9 73.8 123 18.1 .018 C CA-IDM-49 1.7 M1 E, County Road 448, Callaway Electric Cooperative Utility Pole No. 06959, Reform Wildlife Management Parking Area 365.9 70.0 17 5 17.2 241 CA-IDM-50 0.9 Mi SSE. County Road 459,3.3 Mi North of Hwy 94, Callaway Electric Cooperative j Utility Pole No. 35086 365.9 69.2 31 6 17.0 151 j C A-IDM-51 0.7 Mi SE, Located in the "Y" of the Railroad Spur, NW of Sludge Lagoon 366.0 72.8 12 5 17.9 331 CA-IDM-52 0.4 Mi ESE, Light Pole near the East Plant Security Fence 365.9 69.0 24 7 17.0 281 i l i I l O !I i I
)
i 3.3 Well Water h Well water samples were collected monthly from three locations and analyzed l l 1 for Gross Alpha, Gross Beta, Tritium, Strontium-89, Strontium-90 and Gamma-emitting nuclides. A summary of the Mean Gross Alpha and Gross Beta activities for Well Water samples may be found in Table II. Collection location Dol (4.0 mi SE, Holzhouser Grocery Store / Tavern) had Cross Alpha activities ranging from less than 2.0 pCi/l to 3.9 31.2 pCi/1, with an annual mean Gross Alpha activity of 2.92 0.5 pCi/1. Gross Beta activities from this collection location ranged from less than 3.0 pCi/l to 4.2 10.7 pCi/1, with a 1988 mean Gross Beta activity of 3.8 20.5 pCi/1. A graphic presentation of the l monthly Gross Alpha and Gross Beta results for Well Water sarrples obtained from collection location DOI may be found in Figure 7. No detectable levels of Tritium, Strontium-90 or Strontium-89 were observed in any of the Well Water samples collected at Site DOI during 1938. Gross Alpha activities at collection location FOS (1.0 mi SSE, Onsite Groundwater Monitoring Well) ranged from less than 2.0 pCi/l to 3.011.1 pCi/1. The 1988 mean Gross Alpha activity for Site FOS was 2.510.4 pCi/1. Gross Beta activities at collection location F05 ranged from 4.420.6 pCi/l to 10.120.7 pCi/l, with a mean annual Gross Beta activity of 7.811.6 pCi/1. Figure 8 graphically presents the monthly Cross Alpha and Cross Beta activities for collection location FOS. All Well Water samples from collection location F05 were less than 500 pCi/l for Tritium activity and less than 1.5 pCi/l for Strontium-89 activity and less than 1.0 pCi/l for Strontium-90 activity. O l
l Figure 9 illustrates the monthly Gross Alpha and Gross Beta activities for.all Well Water. samples collected from site FIS (0.55 ~mi NE, Onsite Groundwater Monitoring We.1) during 1988. Gross A_lpha activities ranged from less than-2.0 pCl/l to 3.2 11.2 pC1/l, with a mean annual Gross Alpha activity of 2.610.5 pCl/1. Gross Beta activities ranged from 4.51 0.6 pCi/l to 10.420.8 pCi/1. The mean annual Gross Beta activity for FIS was 6.311.7 pCi/1. All Well Water. samples ) l collected at Site FIS were less than the detection limits for Tritium, Strontium-89 and Strontium-90 (500 pC1/l,1.5 pCl/1, and 1.0 pCl/l respectively). j i Overall, the 1988 mean annual Gross Alpha activity for all Well Water samples I was 2.81 0.5 pC1/l. A 1988 mean Gross Beta activity for all Well Water samples was calculated to be 6.612.1 pCi/1. No gamma-emitting nuclides of interest were detected in any of the Well Water samples collected during 1988. . q o i , l 1 l 4 i k j i O l l . . .
Table II h 1988 Mean Cross Alpha and Gross Beta Activities in Well Water (pci/0 Gross Alpha Cross Beta CA-WWA-DOI 2.9 15 0 3.8 10 5-CA-WWA-F05 2.5 140 7.8 161 C A-WWA-F 15 2.6 150 6.3 241 All Locations 2.8 250 6.6 2.1 4 O Oi i 1 Figure 7
- ~ MONTHLY GROSS ALPHA ACTMTY s
WELL WATER - STATION D01 4 1988 20 - 15 m ) 5 v 110-
-)
t 5 c, . F
~
Q ,, 0
,1 I
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-5 J F M A M J J A- S O N D I O M "'"
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MONTHLY GROSS BETA ACTMTY WEL' WATER - STATION D01 1988 20-
)
15-
=
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4
-.__-.-_.._W._=..__-_____-__-_-_--.--_-------
4 Figure 8 , MONTHLY GROSS- ALPHA ACTMTY . WELL WATER - STATION F05 g 1988 J 20- 'i I 3 15 3 r, l 50 1 10-O D 5 g 0
-5 J F M A M J J A S O N D MONTH g' MONTHLY GROSS BETA ACTMTY WELL WATER - STATION F05 1988 20 i
l 15-O N :' Q 10 t t } f 4 3
+
t + + + + 5 c F " t . W 0 gl
-5 J F M A M J J A S O N D MONTH
. . . )
a, : Figure 9 MONTHLY GROSS ALPHA ACTMTf
,_ WELL WATER - STATION F15 l (m ,) 1988 l 20 l
15- l
^-
l s, 1 9 10 0 i 1 C I 2 w 5-o .. st " i i O l -5 l F J M A M J J A S O N D MONTH m U MONTHLY GROSS BETA ACTMTY WELL WATER - STATION F15 1988 20 : l I 15-o N.- " 0 v c_10 i i
+
3 -
+ t +
s o t f + + l 1 W 0 = q l v
-6 J F M A M J J A S O N D MONTH
.,. -._ ._______._______a
1 3.4 Surface Water h 1 Surface Water samples were collected from three locations on a monthly basis. )1 Samples were analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-89, Strontium-90 and for Gamma-emitting nuclMes. A summary of the Mean Gross Alpha and Gross Beta activities for Surface Water samples may be found in Table Ill. ' i Samples obtained from collection location 501 (4.8 mi SE, 84 feet upstream of discharge, North Bank) yielded a 1988 mean Gross Alpha activity of 3.01 1.1 pCi/l with a range from less than 2.0 pC1/1 to 5.111.3. The mean annual Gross Beta activity for Sol was calculated to be 5.21.7 1 pC1/1 with a range of Gross Beta activity from 3.1 1 0.5 pCi/l to 9.7 0.7 1 pCi/1. The monthly Gross Alpha and Gross Beta results are shown in Figure 10. No Strontium-89, Strontium-90 or Tritium activity was observed above detection limit in any of the Surface Water samples collected from location 501 during 1988. I Collection location SO2 (5.2 mi SE,1.1- River miles downstream of discharge, North Bank) had a range of Gross Alpha activity from less than 2.0 pCi/l o 3.611.1 pCi/1. The 1988 mean Gross Alpha activity from this location was 2.810.5 pCi/1. An annual mean Gross Beta activity of 6.8 12.1 pCi/l was observed ; while the range of Gross Beta activity for this site was from less than 3.0 pCi/l to 12.010.8 pCl/L Figure 11 shows the monthly Gross Alpha and Gross Beta j results graphically. All Surface Water samples collected from location 50? ; during 1988 were less than the detection limits for Tritium, Strontium-90 and i Strontium-89 (500 pCi/1,1.0 pCi/l and 1.5 pCi/1, respectively). Figure 12 presents the monthly Gross Alpha and Gross Beta results for samples collected during 1988 from collectien location 503 (68 mi E, City of St. Louis O I
Q Water intake). A range of Gross Alpha activity from less than 2.0 pCi/l to 4.811.7 pCi/l was observed in the samples collected from location 503. The 1988 mean Gross Alpha activity for samples from this location was 3.1 21.0 pCi/1. Results of Gross Beta analyses for Surface Water samples from Location 503 ranged from 3.41 0.5 pCi/l to 7.10.7 2 pCi/1. A 1988 mean Gross Beta activity of 5.41 1.0 pC1/1 was observed for this site. No Strontium-90, Strontium-89 or Tritium were detected in any of the Surface Water samples collected from this location during 1988. The 1988 mean Gross Alpha and Gross Beta activities for all Surface Water samples were 2.93 0.8 pCi/l and 5.82 1.8 pCi/1, respectively. No gamma-emitting nuclides of interest were detected in the 1988 Surface Water samples. O Dvrias 1988. the ogstreem Surfece Weter comgesite semeier wes out of service from May 5,1988 through May 19, 1988. The downstream Surface Water composite sampler was out of service from March 17,1988 through June 23,1988 and from September 8,1988 through December 31, 1988. When the samplers were out of service daily grab samples were taken and composited over the month. O
Table III h~ 1988 Mean Gross Alpha and Gross Beta Activities in Surface Water (pCi/1) Gross Alpha . Gross Beta C A-SWA-SOI 3.0 111 5.2 17 1 CA-SWA-SO2 '2.8 150 6.8 112 CA-SWA-SO3 3.1 101 5.4 101 All Locations 2.9 180 5.8 281 e i O e
Figure 10 MONTHLY GROSS ALPHA ACTMTY SURFACE WATER - STATION S01 1988 (] 20-15 m 5 v M.10 D E5 " O
-5 - - + -
J F M A M J J A S O N D MONTH G V MONTHLY GROSS BETA ACTMTY SURFACE WATER - STATION S01 l 1986 I 20 l 15 O N.- l l Q10-v t i N } $ h5 Y t 4 4 4 I W + + O ! O
-5 -
J F M A M J J A S O N D MONTH e ._ . _ _ _ - _ - _ _ _ _ _ _ _ _ _ -
Figure' 11' MONTHLY GROSS ALPHA ACTMT( SURFACE WATER - STATION.S02 1988 $'.- 20-15- ^ 5 0 10-8 D E 5- i
< ~
O
-5 J F M A M J J A S O N D MONTH O
MONTHLY GROSS BETA ACTMTY SURFACE WATER - STATION S02 1983 20-15 O .. h Q10 p W + 0 0
-5 J F M A M J J A S O N D MONTH I
Figure 12 MONTHLY GROSS ALPHA. ACTIVITf SURFACE WATER - STATION S03 (') '~' 1988 20-15 O S 4 0O 10 N 5 5 .. l 4 ,, 0
-5 J F M A M J J A S O N D MONTH l
O MONTHLY GROSS BETA ACTMTY SURFACE WATER - STATION S03 1986 . 20 15 o S Q 10 v s t t + + 5- t +
$ t Y y y 9
W + 0 G v
-5 J F M A M J J A S O N D' MONTH
3.5 Sediment h Washload, Bedload and Bottom sediment samples were collected quarterly from three locations along the Missouri River. Samples were analyzed for Gross Alpha, Gross Beta, Strontium-89, Strontium-90 and by Gamma Spectrometry. A l summary of mean Gross Alpha and Gross Beta activities for all sediment samples - collected during 1988 is presented in Table IV. Washload sediment samples collected from Location A (4.9 mi SSE,0.6 river mile upstream of discharge, North Bank) had a range 'of Gross Alpha activity from 4.611.2 pCi/g to 16.816.0 pCi/g. The mean Gross Alpha activity for 1988 was 10.314.8 pCi/g for Washload sediment samples collected from Location A. Gross Beta activity in the samples from this site ranged from 7.5 21.9 pC1/g to 10.011.0 pCi/g. The 1988 mean Gross Beta activity for Washload sediments collected at Location A was calculated to be 9.110.9 pCi/g. A chronological presentation of all Gross Alpha and Gross Beta results for Washload sediment samples from this site may be found in Figures 13 and 14. Strontium-90 was not detected in Washload sediment samples collected during 1988. No Strontium-89 was ' ) detected in any of the Location A Washload samples. No ' gamma-emitting i nuclides of interest were detected in any of the Washload sediment samples collected from Location A during 1988. l Figures 15 and 16 present the' quarterly Cross Alpha and Gross Beta results for l Washload sediment collected from Location C (5.1 mi SE, 1.0 river mile downstream of discharge, North Bank). Gross Alpha activity for Washload sediment ' samples from Collection Location C ranged from 6.91.2 1 pCi/g to l 15.61 2.9 pCi/g. Gross Beta activity in the samples from this site ranged from 5.610.4 pCi/g to 18.311.3 pCi/g. h,
I i O rhe 1988 meen cross ^inhe -nd Cress Bete ieveis fer Weshieed seeimeats l 1 collected at Location C were 9.413.6 pCl/g and 12.014.8 pCi/g, respectively. Strontium-90 was not detected in Washload sediment samples collected from Location C during 1988. No Strontium-89 was detected in the Washload samples collected from this location. No gamma-emitting nuclides of interest were observed in any of the 1988 Washload sediment samples collected from Location C. The monthly Gross Alpha and Gross Beta results for the Washload sediment samples collected from Location D (53.0 mi ESE,59.5 river miles downstream of l discharge, South Bank) are graphically presented in Figures 17 and 18. Gross l Alpha activity in these samples ranged from 7.612.2 pCi/g to 15.512.9 pCi/g wl'th a 1988 1ean of 10.813.0 pCi/g. The annual mean Gross Beta activity for O Weshieed sempies ceiiected et tecetion D wes 12.9 1 3.5 pCi/s with e rense of activity from 7.7 11.0 pCi/g to 17.6 11.7 pCi/g. Strontium-90 was not observed in l Washload sediment samples from Collection Location D. Strontium-89 was not detected in any samples from this location. No gamma-emitting nuclides of interest were detected in any of the Washload sediments collected from Location D during 1988. Bedload sediment samples collected from Location A (4.9 mi SSE,0.6 river mile upstream of discharge, North Bank) yielded a range of Gross Alpha activity from 1.01 0.2 pCi/g to 10.212.2 pCi/g. The Gross Beta activity for these samples ranged from 2.810.1 pCi/g to 13.81.1 2 pCi/g. The 1988 mean Gross Alpha and l Gross Beta activities for Bedload samples from Collection Location A were 5.513.4 pCi/g and 7.214.3 pCi/g, respectively (See Figures 19 and 20).
]
i No Strontium-90 activity was observed in any of the Bedload samples collected h from Location A during 1988. In addition, no Strontium-89 activity was detected l In any of the 1988 Location A Bedload sediment samples. No gamma emitting 4 nuclides of interest were detected in any of the Bedload sediment samples collected from Location A during 1988. Location C (5.1 mi SE,1.0 river mile downstream of discharge, North Bank) Bedload sediment samples ranged from 1.0 1 0.2 pCi/g to 7.71.3 1 for Cross Alpha ; 1 activity while the _1988 mean Gross Alpha activity'was calculated to be 3.512.5 j pCi/g. A mean annual Gross Beta activity of 4.8 13.1 pCi/g was observed in ' Bedload samples from Location C. The range of Gross Beta activity was from 2.310.1 pCi/g to 9.9 11.1 pCi/g (See Figures 21 and 22). No Strontium-90 was detected in any Location C Bedload samples during 1988. No Strontium-89 was observed in any of the Bedload samples from Collection Location C. No gamma-emitting nuclides of interest were detected in the Bedload samples collected i from Location C during 1988. 'l A chronological presentation of the Gross Alpha and Gross Beta activities for Bedload sediment samples from Location D (53.0 mi ESE, 59.5_ river miles downstream of discharge, South Bank) may be found in Figures 23 and 24. The Gross Alpha activity ranged from 1.01 0.2 pCi/g to 3.510.8 pCi/g for these samples. Gross Beta levels ranged from 1.7 1 0.1 pCi/g to 5.91 0.4 pCi/g. The l Bedload sediment samples from Location D had a mean annual Gross Alpha activity of 2.6 1 1.0 pCi/g and a mean annual Gross Beta activity of 3.311.6 pCi/g. No Strontium-90 was observed in any of the 1988 Location D Bedload samples. No Strontium-89 was observed in any of the Location D Bedload sediment samples. No gamma emitting nuclides of interest were detected. O
g Bottom sediment samples collected from Location A (4.9 mi SSE,0.6 river mile upstream of discharge, North Bank) had a mean annual Gross Alpha activity of 1.02 0.4 pCi/g and a mean annual Gross Beta activity of 0.72 0.3 pCi/g. Figures 25 and 26 exhibit the quarterly Gross Alpha and Gross Beta results for these samples. The quarterly Gross Alpha results ranged from 0.31 0.1 pCi/g to 1.320.2 pCi/g while the range of Gross Beta results was from 0.410.1 pCi/g to 1.130.1 pCi/g. All Bottom sediment samples collected from Location A during 1988 were below the detection limits of 0.30 pCi/g and 0.20 pCi/g for Strontium-89 and Strontium-90, respectively. Cesium-137 was detected in one Bottom sediment sample collected from Location A during 1988 (0.051 0.03 pCi/g on 11/01/83). Location C (5.1 mi SE,1.0 river mile downstream of discharge, North Bank) had h a range of Gross Alpha activity from 1.210.2 pCi/g to 1.5 20.2 pCi/g and a Gross Beta activity range from 1.010.1 pCi/g to 2.9 10.1 pCi/g for Bottom sediment samples. All Gross Alpha and Beta results from 1988 are graphed in Figures 27 and 28. The 988 mean Gross Alpha and Gross Beta activities for Location C Bottom sediment samples were 1.4 2 0.1 pCi/g and 1.62 0.8 pCi/g, respectively. Strontium-90 was detected in none of the Bottom sediment samples collected from this site. No Strontium-89 was detected in any of these samples. Cesium-137 was detected in one Bottom Sediment sample collected from Location C during 1988 (0.191 0.04 pCi/g on 08/11/88). Cobalt-58 was detected in the sample collected on 03/22/88 (0.2710.10 pCi/g). Cobalt-60 (0.091 0.04 pCi/g) was detected in the sample collected 03/22/88, W resium-134 (0.0710.03 pCi/g) was detected in the sample collected 08/11/88. O
Figures 29 and 30 graphically present the quarterly Gross Alpha and. Gross Beta h' results for Bottom sediment samples collected during 1988 from Location D (53.0 mi ESE, 59.5 river miles downstream of discharge, South Bank).' The range of . Gross Alpha activity for these samples was.from 1.21 0.2 pCi/g to 1.820.2 pCl/g, while Gross Beta activity. ranged from 0.81 0.1 pCl/g to l.9 10.1 pC1/g. The 1988 mean Gross Alpha and Gross Beta' activities'for Bottom sediment samples from Location D were 1.510.2 pCl/g and 1.410,4 pCi/g, respectively. No Strontium-90 was detected in any of the four Location D Bottom sediments. No Strontium-89 was observed in any of the Bottom sediment samples collected from Location D during 1988. Cesium-137 was detected in one of the 1988 Bottom Sediment: samples collected from Location D (0.1210.'05 pCi/g on 03/23/88). Two Shoreline sediment samples were collected from Location C during 1988. The Shoreline sediment collected 11/01/88 exhibited a Cesium-137 activity of h 0.061 0.03 pCi/g. No other gamma-emitting, nuclides of i..terest c and no Strontium-89/90 activity was detected in the Shoreline sediments collected during 1988. l l l l l 9:
'y .
i' h Table IV ' 1988 Mean Annual Gross Alpha Activities in Sediments (pCl/g-dry) Washload Bedload Bottom Location A 10.3 18 4 5.5 24 3 1.0 3 0.4 Location C 9.4 163 -3.53,2.5 1.4 110 Location D 10.8 10 3 2.6 101 1.5 120 A11 Locations 10.1 4.1 3.9 19 2 1.3 140 1988 Mean Annual Cross Beta Activities in Sediments (pCi/g-dry) Washload Bedload Bottom O Location A 9.1 190 7.2 23 4 0.7 130 Location C 12.0 28 4 4.8 113 1.6 180 Location D 12.9 2 3.5 3.3 2 1.6 1.4 240 All Locations 11.3 1 4.0 5.1 28 3 1.2 270 O
._._e_____--__-____-_--a
Agure 13 Rgure 14 QUARTERLY GROSS ALPHA ACTMTY WASHLOAD SEDIMENT '_OCATION A OUARTERLY GROSS BETA ACTMTY WASHLOAD SEDIMENT - LOCATION A g 1988 1988 i 20 20 l 15 15 m g 5 i {10 {10
} } l W e 5 ,
5 0 0 l 1 2 3 4 1 2 3 4' l QUARTER QUARTER l 1 01 l l Agure 15 Rgure 16 OUARTERLY GROSS ALPHA ACTMTY OUARTERLY GROSS BETA ACTMTY WASHLOAD SEDIMENT - LOCATION C WASHLOAD SEDIMENT - LOCATION C 1988 1988 20 20 15 15 eg n NY a a
- 10 ~
i a i 10 e 5 5 O O O 1 2 3 4 1 2 3 4 QUARTER QUARTER
1 (l 1 Agure 17 Rgure 18 QUARTERLY GROSS ALPHA ACTMTY O wAssLO^o sEoiuEnr - 'oc4TiO" o QlJARTERLY GRQSS BETA ACTMTY wAssLOto seoiue"T - loc 4TiO" o 1966 4 1966_ t 20 . ,
'20
]
15 , 15 m k k 1 ~ s
- 10
- 10 2 N o
5 5 i i 0 0 ; 1 2 3 4 1 2 3 4 QUARTER QUARTER o FigJre 19 Figure 20 QUARTERLY GROSS ALPHA ACTMTY BEDLOAD SEDIMENT LOCATION A QUARTERLY GROSS BETA ACTMTY 1966 BEDLOAD SEDIMENT - LOCATION A 1966 20 20 15 15 kb E 10 l10 1 - t 9 5 5 O + O O
.1 2 3 4 1 2 3 4 QUARTER QUARTER
_- y Figure 21 Figure 22 QUARTERLY GROSS ALPHA ACTMTY BEDLOAD SEDIMENT - LOCATION C QUARTERLY GROSS BETA ACTMTY SEDLOAD SEDIMENT - LOCATION _C 1988 1988 20 20 - 15 15 i 4 0 10
- 10 "
h " l 'Q .e 5 5
} } .-
- D I D '
1 2- 3 4 1 2 3 4 QUARTER QUARTER O (
}
Figure 23 _ Figure 24 OUARTERLY GROSS ALPHA ACTMTY QUARTERLY GROSS BETA ACTIVITY BEDLOAD SEDIMENT - LOCATION D BEDLOAD SEDIMENT - LOCA ND 1988 1988 20 20 15 15 1 l'. E 5 i 10 s 10 h e a 5 5 { { + 4
+
O O 2 1 3 4 1 2 3 4 ' QUARTER
,3g, QNB i
l I Agure 25 Agure 26 OUARTERLY GROSS ALPHA ACTMTY O eotTou scoiac"T - 'oc^T'o" ^ QUARTERLY GROSS BETA ACTMTY soTTou scoiuttiT - 'oceT'o" ^ 1966 1988 20 20 15 15 I k 2 R s :
*$ 10 " 10 W , W 5 5
+ 0 I
+
O 0 1 2 3 4 1 2 3 4 QUARTER QUARTER n () Agure 27 ngure 28 QUARTERLY GROSS ALPHA ACTMTY 80TTOM SEDIMENT - LOCATION C CUARTERLY GROSS PETA ACTMTY 1968 BOTTOM SECIMENT - LOCATION C 1986 20 1 20 15 15 2 & R R
" 10 E 10
$ E v v 5
5 O + +
+
- + +
l . 0 0 1 2 3 4 1 2 3 4 QUARTER WM
,39,
T' l Figure 29 Figure 30 I QUARTERLY GROSS ALPHA ACTMTY BOTTOM SEDIMENT - LOC ATION D OUARTERLY GROSS BETA ACTMTY BOTTOM SEDIMENT - LOCATION D 1988 1988 20 20 15 15 kn ka f 10 10 a N iN 5 5
+ +
- l + + +
0 0 1 2 3 $ 1 2 3 4 QUARTER QUARTER
/
O O 1
1 l l O 3.6 risa Five species of fish were collected on a mont?Jy basis from the same locations l on the Missouri River as the sediment samples. Five fish species were not l l collected from location A and C during January due to a paucity of fish and ice ' cover behind dike fields limited sampling effectiveness. Species of fish collected during 1988 include freshwater drum, bigmouth buffalo, smallmouth buffalo, carp, grass carp, bighead carp, goldeye, river carpsucker, shorthead redhorse, shortnose gar, longnose gar, gizzard shad, blue catfish, channel catfish, largemouth bass, flathead catfish, blue sucker, paddlefish, white bass, bluegill, 1 and white crappie. Gross Alpha, Gross Beta, Strontium-89, Strontium-90 and I Gamma Spectralanalyses were performed on all fish samples. All results are in terms of pCi/g (dry). The 1988 mean Gross Alpha and Gross Beta activities for each sampling location are summarized in Table V. . O V The monthly Gross Alpha activities in fish samples collected from Location A (4.9 mi SSE,0.6 river mile upstream of discharge, North Bank) ranged from less i than 0.3 pCi/g to 0.720.2 pCi/g with a 1988 mean Cross Alpha activity of 0.410.1 pCi/g. Gross Beta activities in these samples ranged from 2.510.1 pCi/g to 1 10.51 0.2 pCi/g. The mean Gross Beta activity for 1988 Fish samples collected at Location A was 6.511.6 pCi/g. Figure 31 is a chronological presentation of all Gross Alpha and Gross Beta activities for 1988. Strontium-90 and Strontium-89 were not detected in fish samples collected in 1988 from Location A. No Gamma emitting nuclides were detected in the fish samples collected from a Location A. , Fish samples collected from Location C (5.1 mi SE,1.0 river mile downstream of ' b U discharge, North Bank) had mean annuai Gross Alpia and Cross Beta activities of l J i l
)
0.310.1 pCi/g and 6.611.3 pCi/g, respectively. Figure 32 illustrates the monthly h Gross Alpha and Gross Beta activities for fish collected from Location C. Gross Alpha levels in these samples ranged from less than 0.3 pCi/g to 0.510.1 pCi/g, while Gross Beta levels ranged from 3.71 0.1 pCi/g to 9.910.3 pCi/g. No Strontium-89 or Strontium-90 was detected in any of the Fish from Collection Location C. Cobalt-60 was detected in the Carp collected 11/01/88 (0.3910.16 pCi/g). No other gamma emitting nuclides of interest were detected in 1988 Location C fish. l l Figure 33 graphically presents the monthly Gross Alpha and Gross Beta results for fish samples collected from Location D. Gross Alpha activities ranged from less than 0.3 pCi/g to 0.510.1 pCi/g, with a mean Gross Alpha activity of 0.4 10.1 pCi/g for all fish collected from Location D during 1988. Gross Beta ranged from 3.510.1 pCi/g to 9.620.2 pCi/g with a 1988 mean of 6.71 1.1 pCi/g. No Strontium-89 or Strontium-90 activity was observed in any of the fish collected from this location. Cesium-137 was detected in two samples; Largemouth Bass (0.311 0.30 pCi/g) collected 11/02/88 and Channel Catfish (0.2310.14 pCi/g) collected 12/08/88. Cobalt-60 was detected in the Bigmouth Buffalo (0.4620.18 l pCi/g) collected 11/02/88. No other gamma emittings nuclides of interest were j detected. i O
I i
.O rasie v l
.I 1988 Mean Annual Gross Alpha and Cross Beta Activities in Fish (pCi/g-dry)
Gross Alpha Gross Beta Location A 0.4 11 0 6.5 16 1 Location C 0.3 11 0 6.6 1 1 3' Location D 0.4 3 0.1 6.7 11 1 All Locations 0.4 11 0 ' 6.6 141 O i O
Figure 31 MONTHLY GROSS ALPHA ACTIVITY FISH - LOCATION A 1988 g 20 - 15-- n N" a 1 0 -- 8 D 55-- W O t t t t t t t
-5 J F M A M J J A S 0 N D l
l MONTH O MONTHLY GROSS BETA ACTMTY FISH - LC' CATION A 25 - 20--
^
m I > o 15 -- l 0 C E 10-- G
< t 5' "
O O J F M A M J J A S O N D MONTH j i e .__ . _ _ _ - _ -
Figure 32 MONTHLY GROSS ALPHA ACTIVITf FISH - LOCATION C O '*** 20 - 15-- I a 10-- 3 5-- W
- + +
D + 4 + + + + t
-5 J F M A M J J A S O N D MONTH O
MONTHLY GROSS BETA ACTMTY FISH - LOCATION C 1988 25 - 20-- Yn d15-- 8 C E 10-- G
+
f T f .. 5-- 0 0 J F M A M J J A S O N D MONTH
Figure 33 MONTHLY GROSS ALPHA ACTIVITY FISH LOCATION D 20 - 1988 $i I i 15 - l 1 i m ' R i a 10 -- 8 b g5 _ i V 0 t t i t t t i t t
-5 J F M A M J J A S O N D MONTH O
MONTHLY GROSS BETA ACTMTY FISH - LOCATION D 1988 25 - 20 - Tn N O 15 - S b 5 l c 10 - i o '
+
+
4
.. t "
f ; O O J F M A M J J A S O N D MONTH i m _ __ ____ _ _j
i j l I O 3.7 Milk I V ) During 1988, milk samples were collected from two locations, the Green Farm (M-1), and the Schneider Farm. The Schneider Farm provided cow milk (M-5A) i and goat milk (M-5B). Analyses for Iodine-131, elemental Calcium, Strontium- t 89, Strontium-90 and Gamma emitting nuclides were performed on all milk samples. No goat milk samples were collected from the Schneider Farm during January, February and December because the goats were dry. ; lodine-131 was detected ir ;ne goat milk sample collected during 1988. Activity of 1.210.5 pCi/l (collected 08/21/88) was detected at the Schneider Farm. Strontium-90 was detected in seven milk samples during 1988. Activity rang'ed from less than 1.0 pCl/l to 10.12.91 pCi/l in the goat milk sample (Schneider i O F rm-M5B) collected 08/06/88. No Strontium-89 was detected in the milk samples. , l 2 Elemental Calcium ranged from 760 mg/l to 2340 mg/1. No gamma emitting nuclides of interest were detected in any of the milk samples collected during 1988. l
3.8 Vegetation Vegetation samples were collected during the second, third and fourth quarters of 1988 from three locations. Samples were analyzed for Gross Alpha, Gross Beta, Iodine-131 and Gamma-emitting nuclides. Gross Alpha activity was detected in thirteen (13) of the vegetation samples. Levels of Gross Alpha activity ranged from less than 0.3 pCi/g to 1.210.2 pCi/g. The 1988 mean Gross Alpha activity was 0.8 1 0.2 pCi/g. Gross Beta activity ranged from 1.0+0.1 to 25.9+0.3 pCi/g. The mean Gross Beta activity of the vegetation samples collected during 1988 was 13.71 5.0 pCi/g. Iodine-131 was not detected in any vegetation samples collected during 1988. No gamma emitting nuclides of interest were observed in the vegetation r,amples h collected during 1988. l l l l l O f r
3.9 Soil Soil samples were collected on 11/09/87 from eleven locations. Soll was analyzed for Gross Alpha, Gross Beta and Gamma emitting nuclides of interest. - Gross Alpha activity in the soil samples ranged from 1.51 0.2 pCi/g to 3.310.3 pCi/g with a 1988 mean of 2.410.6 pCi/g. Gross Beta activity ranged from 1.01 0.1 pCi/g to 3.410.1 pCi/g with a 1988 Mean Gross Beta activity of 2.710.7 pCi/g. Cesium-137 was observed in all the 1988 soil sami . _The range of Cesium-137 was from 0.4110.04 pCi/g to 1.551 0.04 pCi/g. No other gamma emitting nuclides of Interest were detected in the soil samples collected during 1988. O i l i l O I
4.0 Annual Summary h Table VI, Environmental Radiological Monitoring Program Annual Summary, contains a condensed summary of all data for 1988. 1 I l 1 O l 1 Ol l L_______.__.______._ _ _ _ _ _ _ . . _ . _ . _ _ _ . _ _ .__ . _ _ . _ _ l
O mnpa uoe e r os 0 0 0 0 NNRM 0 _ ) 21 3 _ s 55 ) 9 )
/ 0 l
n) 2 / 44
/
4 oi(o1 50 40 e ( ( - 1 ( tr t a ng 28 33 22 Y 3 nco an o ea 20 00 71 1 0 00 00 D L D L R 8 ClMR 00 00 00 L L A 9 M 3 1
) < <
23 1
)
M 8 4 ) 54
/0
) A 2 U -
f ( 2 / 41
/
5 S 0 d 50 40 ng e 1 5 ( L o t 37
- (
21
- (
66 i s A r e e an ea 20 00 01 1 0 00 U h 00
. P g MR 00 00 N o g i 00 N N n H A t i
t h & & & e r t n ) M k o ia we On On Ono ( f A c o p e f io00 f i o0 f i 0 s R D R nM ol e on ci ot c6 ot 0 c6 ot c60 i r G En3 En3 En3 e a u e ac O ia t nt i u u u bt R cnmt ser mJ mi imJ mi - i mJ m i n P onaii L A '" DD 3.C 9 0C1 3.C 9 - 3 C9 e r G 0C1 - 0C1 a p N 1 I ) n v R r 3 i O o 0 ) d e T t as 24
/ 4 61 1
8
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t e 2 l I N ic n) d i( of 8 0 0
/1 6 5 a c
C1 O i nt a ng e ( 20
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1 0
- (
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1 i d M r u I 33 51 66 n c an 20 91 D D 00 i L o l l oea 00 00 L L 00 s A t n s s ALMR 00 00 L L 00 i s C a i
< y n I
l M < o G P , t n l n it y O y t i mio o a L a n it s c O w u Lc ) t o I a o e* 8 n l D e d l l C rt 8 9 me A a y e e )D wD 3 0 1 2 0 2 6 0 1 e f i R C a of L 0 0 0 0 0 0 ( r i L w L o (L 0 0 0 0 t r s e u c 0 A la o a p T l p e s a N C ) ) R e mt a E ) 0 0
)
0 ) e r s M r 0 6 2 2 ( 2 0 e b l t N : y e 2 ( c7 0 ( 9 6 2 t r t a ne a ec m ( O : i t b s e - 9 8 ( R y l med a pm - u Qt e re i - 1 I t c dn u se t e S u m m 3 V N i l i F a aNlym ar B i al l u u 1 t d us E c a l no s my i t n i t e
- s r a a f e ptaAf r s r n o e F o yof e o
r me aB o r o r in i F pu m f n t t d o 0 _ o o TToP G G S S e e i. t l 6 de b l a n s a a m a c d o t o e s it b c N L e c e e lp t e g e t
) a e
_ m t n lu) n S ra d a e c3 i e r fo rS o d)3 e O im eo S dn n y m t ma f e r r/ ai nim r ic/ - a o uw to s u PC odi D n t i i d thin a r (p br aC L a c - ea e iA i R (p A L e ar M P (U M
- M F
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/
A A
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)
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)
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)
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- M F
0 0 0 0 0 0 0 0 NNRM s ) ) ) n) 2 2 2 l of 1 8 1 8 1 oi( / / / rt e 26 1 23 1 t a ng ( nc a n 1 1 1 Y ( - ( - D D D 55 D D R 8 8 oo CLMR e a 63 50 74 L L L 00 L L 50 L L L 00 L L A 1 9 . M 3 M 8 ) ) ) ) ) ) 4 ) 2 2 U f 2 2 2 2
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L 5 o t s nge 2 51 28 1 ( 1 1 ( ( 1 ( 1 a en i 1 1 A r e ( - ( - 7799 7799 U e h a 00 l. 0 001 1 2200
. P g MR 51 61 0000 0000 N o g i N N n H 0 A t i
t h 2 e r t n 1 0 0 M k c o p ia we m1 m m m m8 m8 A o e n a s ee a0 a0 a0 a6 a6 R D R nM eo rl e8 tr6 e8 e8 e r s es t l e tr le ol ci r6 r6t G ia t i s t au e ac nt si si si si si O t n m nm nmnm R cnmt e w0 w w w wnmnm w P onaii s r o3 o1 o1 o1 o1 o1 ) e G LANDD D5 D5 D5D5 D3D5 t n N I o R r C ( O o t I T a sn) ) ) ) ) ) ) V I c 4 4 4 49 4 4 N i of 26 23 2 21 2 2 E O dnti( / / a nge
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)
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uoee 0 0 0 0 0 0 00 NNRM -
)
s 3 n) ) 3
)
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)
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f 3 31 1 / 9 S 0 d 3 3 20 2 L 5 o t s nge / 1
/
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)
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)
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. g MR 33 33 N o g i 1 1 N N n H t t A t e
i t h t n n n t nO . r a a aI 0 ) M k o ia f we l PR 5 l l A c p P60 P60 ( s o e n y F54 y F 45 P 2 R D R n M eo y 2 i s G ol ci ai ai ai e O ia t a u e nt ac awtsm wts m a we m ar i ht R P cnmt e onaii sr l l ao7 e2 r l l e2 r l l i5 a5 n e ao7 a r r
)
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)
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70
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)
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)
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)
APPENDIX A UNION l'LECTRIC COMPANY CALLAWAY PLANT 1988 LAND USE CENSUS
O APPENDIX A UNION ELECTRIC COMPANY CALLAWAY PLANT 1988 LAND USE CENSUS Prepared by 84 T G L I/3, e Approved by 7 _ 7 7 c -- - , 7 O l 1 i O E
1.O INTRODUCTION In accordance with Technical Specification 3.12.2, the iniual Land Use Census within a 5 mile radius of the "o'laway Plant was performed during July, 1988 by the Union 2(actric Real Estate Department. Observations were made in each of the 16 meteorological sectors of the nearest milking animals (cows and goats), gearest rgsidence, and the nearest garden of greater than 50m (500 ft ) producing broad leaf vegetation. This census was completed by contacting the families identified in the 1987 census and driving the roads within a 5 mile radius of the Callaway Plant noting the location of the above-mentioned items. The results of the Land Use Census are presented in Table 1 thru 3 and discussed below. In the tables the radial direction and mileage from the Callaway Plant containment are presented for each location. The radial direction is one of the 16 different compass points. The mileage was j estimated from map position for each location. 2.0 CENSUS RESULTS 2.1 Milking Animals Table 1 presents the locations where milking animals were (~' observed within the 5 mile radius of the Callaway Plant. All milking animals whose milk is not used for human consumption and/or not yielding milk are identified on Table
- 1. There were several changes in the location and number of milking animals observed during the 1988 census. However, none of the changes observed resulted in changes to the current milk sampling locations.
2.2 Nearest Resident Table 2 presents the location of the nearest resident to the Callaway Plant in each of the 16 meteorological sectors. There were no changes in the nearest resident noted in the 1988 census. 2.3 Vegetable Gardens Thejocationofthenearestvegetablegardenofgreaterthan l 50 m producing broad leaf vegetation is presented in Table
- 3. Several changes were noted in the garden locations during the 1988 census. However, none of the changes noted resulted in changes to the current vegetable sampling locations.
A V
I l TABLE 1 NEAREST MILKING ANIMALS WITHIN FIVE MILES OF THE CALLAWAY PLANT 1988 Meteorological Radial Number Number Sector Mileage of Cows of Goats ENE 3.80 25
- 30
- ESE 2.28 13
- None SE 2.40 90
- None SSE 2.58 1* None S 2.90 7 ** None SSW 3.30 20
- None WSW 1.35 14
- None NW 3.10 7 *** 6 i
- Milk producing animals whose milk is not used for human consumption and/or for milk producing animals that are not yielding milk. !
l Milk from one cow is being used for human consumption. Milk from two cows is being used for human consumption. i i _ _ _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ . _ _ . _ _ _ _ _ _ _ _ . _ __ _ _ B
() TABLE 2 NEAREST RESIDENCE WITHIN FIVE MILES OF THE CALLAWAY PLANT 1988 Meteorological Radial Sector Mileage N 1.76 NNE 2.00 NE 2.00 ENE 3.80' E 3.37 ESE 2.28 , 1 gg SE 2.38
)
v SSE 2.58 s 2.64 SSW 2.60 SW 2.57 WSW 1.35 W 1.60 WNW 2.60 NW 2.13 NNW 1.78 1 1 i ($) a
TABLE 3 NEAREST GARI EN WITHIN FIVE MILES OF THE CALLAWAY PLANT 1988 Meteorological Radial Sector Mileaqe l N 1.76 NNE 2.00 NE 2.00 ENE 3.80 E --- ESE 2.28 SE --- SSE --- S 2.90 SSW --- SW --- WSW 1.80 W --- WNW 2.60 NW 2.13 NNW 1.78 O
E ( O 1 l l l s SECTION 3.2 RADIOLOGICAL ENVIRONMENTAL MONITORING O FIRST QUARTER REPORT 1988
/
O ! l
)
j
1 r1 V UNION ELECTRIC COMPANY ST. LOUIS, MISSOURI ; CALLAWAY PLANT UNIT 1 RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM QUARTERLY REPORT FOR JANUARY, FEBRUARY AND MARCH 1928 SUBMITTED BY: CONTRCLS FOR ENVIRONMENTAL POLLUT!ON,INC. 1925 ROSINA STREET SANTA FE, NEW MEXICO COPY NO.11 l Prepared By: I db Bob Bates, Contracts Manager j
// , ~
Approved By: "' / O ' 3 '6e=3 ="eiier.ereside#t
CONTENT 3 Section Title 3g Abstract 1 1.0 Introduction 2 2.0 Description of the Monitoring Program 3 l 3.0 Analytical Procedures 15 4.0 Sample Preparation Method 19 5.0 Major Instrumentation 20 6.0 Isotopic Detection Limits and Activ' / Determinations 21 7.0 Quality Control Program 27 8.0 Data Interpretations and Conclusions 27 Appendix A: EPA Cross-check Results 62 Appendix B: Isotopic Detection Limits and Activity Determinations 71 l 1 l TABLES Number Yitle Page
! Sampling Locations 6 l
11 Collection Schedule 12 111 Detection Limits for Radiochemical and Chemical-Parameters 23 IV Detection Limits by Gamma Spectrometry 24 1 i V Sample Counting Times 25 VI Aliquot used for Detection Limit Calculations 26 1 VII Gross Beta in Airborne Partir"! acs 30 i Vill Airborne Radiolodine 31
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IX Thermoluminescent Dosimetry (First Qual ter 1933) 33 1 X Te!! Water - Radiochemical 39 i XI Well Water - Gamma Spectrometry 40 XII Surf ace Water - Radiochemical 42 , Xill Surface Water - Gamma Spectrometry 43 XIV Washload Sediment - Radiochemical 45 XV Washload Sediment - Gamma Spectrometry 46 XVI Bedload Sediment - Radiochemical 47 XVII Bedload Sediment - Gamma Spectrometry 48 XVli! Bottom Sediment - Radiochemical 49 XIX Bottom Sediment - Gamma Spectrometry 50 XX Fish, CA-AQF .A - Radiochemical 52 XXI Fish, CA-AQF-A - Gamma Spectrometry 53 XXII Fish, CA-ACF-C - Radiochemical 54 XXIll Fish, CA-AQF-C - Gamma Spectrometry 55 XXIV Fish, CA-AQF-D - Radiochemical 56 XXV Fish, CA-AQF-D - Gamma Spectrometry 57 XXVI Milk - Radiochemical 59 XXVII Milk - Gamma SNctrometry 60 1 0 -u-
Q FIGURES i l Number Title Page l 1 Area Collection Locations - Map 4 l 2 Site Collection Locations - Map 5 l j l O i l i O -lil-
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O ^8 tr ci Controls for Environmental Pollution, Inc (CEP) has conducted a radiological environmental monitoring program (REMP) for Union Electric Company (UEC), Callaway Plant, Unit 1, since May 5,1983. This quarterly report presents data for the months of January, February 3 and March 1988. 1 Evaluation of radiation levels in the environs around Union Electric Company's Callaway .i Plant entailed sampling at strategic points in various exposure pathways. The following types of samples were collected and analyzed: milk, vegetation, surface water, well water, bottom sediment, bedload sediment, washload sediment, fish, airborne particulate, airborne radiciodine, direct radiation (TLD) and soil. Analytical results are presented and discussed along with other pertinent information. Possible trends and anomalous results, as interpreted by Controls for Environmental Pollution, Inc., are discussed. i l 1 O l.0 Introduction h This report presents an analysis of the results of the Radiological Environmental Monitoring Program (REMP) conducted during the first quarter of 1983 for Union 1 Electric Company, Callaway Plant. In compliance with federal and state regulations and in its concern to maintain the quality of the local environment UEC began its radiological monitoring program in April,1982. 1 1 The objectives of the radiological environmental monitoring program are as follows:
- 1) to establish baseline radiation levels in the environs prior to reactor operations; 2) to monitor potential critical pathways of radioeffluent to man; 3) to determine radiologicalimpact on the environment caused by the operation of the Callaway Plant.
O A number of techniques are being used to distinguish Callaway Plant effects from other sources during the operational phase, including application of established background levels. Operational radiation levels measured in the vicinity of the Callaway Plant are compared with the pre-operational measurements at each of the sampling locations. In addition, results of the monitoring program help to evaluate sources of elevated levels of radiation during reactor operation in the environment, e.g., atmospheric fallout or abnormal plant releases. The Callaway Plant ir located on a plateau approximately five miles north of the , 4 Missouri River in Callaway County, Missouri. The plant consists of one 1150 MWE pressurized water reactor, which achieved initial criticality on October 2,1984 l
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l 1 0 2o oescriati # er the = "it ri"# erenr - Union Electric Company has contracted with Controls for Environmental Pollution, Inc. starting May 1983, to determine the radiation levels existing in and around the Callaway Plant area. UEC personnel collected the samples and shipped them to CEP for analysis. The type of samples collected this quarter were: milk, surface water, well water, bottom I sediment, bedload sediment, washload sediment, fish, airborne particulate, airborne radiciodine and direct radiation (TLD). Locations of the monitoring sites are shown in Figures I and 2. Table I presents the I monitoring sites and the respective samples collected. Sample collection frequency for each of the monitoring locations is depicted in Table II. O The meaning of the sample type codes used in Table I are as follows: Code Sample Collected AIO Air Iodine APT Air Particulate AQF Fish AQS Sediment i FPL Leafy Creen Vegetables IDM TLD MLK Milk SOL Soil SWA Surface Water WWA Well Water O O l l l 4
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c TABLEI h SAMPLING LOCATIONS Location . Sample Description
- Types Code
^
1** 11 mi NW, City Limits of Fulton on Hwy Z,0.8 mi East of Business 54. IDM 2 6.6 mi NW, County Road 111,0.6 mi South of Hwy UU, Callaway Electric Cooperative Utility Pole IDM No.17571 3 1.3 mi NW,0.1 mi West of Hwy CC on Gravel Road, 0.3 mi South Hwy 0, Callaway Electric Cooperative Utility Pole No.~18559 IDM 4,B3 1.9 mi N,0.3 mi East of the 0 and CC Junction, Callaway Electric Cooperative Utility Pole No.18892 IDM, APT,AIO - 5, A l 1.3 mi ENE, Prima.v Meteorological Tower IDM, APT,AIO 6 2.0 mi W, County Road 428,1.2 mi West of Hwy CC, 3 Callaway Electric Cooperative Utility Pole No.18609 IDM W 7 1.3 mi S, County Road 459,2.6 mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35097 IDM 8 2.9 mi S, County Road 459,1.4 mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06823 IDM 9 3.7 mi S, NW Side of the County Road 459 and and 94 Junction, Callaway Electric Cooperative Utility Pole No. 06754 IDM 10 4.0 mi SSE, Hwy 94,1.8 mi East of County Road 459, Callaway Electric Cooperative Utility Pole No.12182 IDM 11 4.8 mi SE, City of Portland, Callaway Electric Cooperative Utility Pole No.12112 IDM 12 5.3 mi SE, Hwy 94,0.6 mi South of Hwy D, Utility Pole on East side of Hwy IDM 13 5.6 mi ESE, Hwy 94,0.75 mi East of Hwy D, Kingdom Telephone Pole No. 2XI IDM 14 5.0 mi ESE, SE Side of Intersection D and 94, Callaway Electric Cooperative Utility Pole No.11940 IDM h 15 4.2 mi ESE, Hwy D,2.5 mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 27379 IDM
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4 l] TABLE I (Cont.) SAMPLING LOCATIONS l l Location Sample Code Description
- Types !
l 16 I.1 mi ENE, Hwy D,3.6 mi North of Hwy 94, Callaway { Electric Cooperative Utility Pole .No.12976 IDM i 17 4.0 mi E, County Road 4053, 0.3 mi East of Hwy 94, Kingdom Telephone Company Pole No. 3X12 IDM 13 3.3 mi ENE, Hwy D,0.4 mi South of O, Callaway Electric Cooperative Utility Pole No.12952 IDM 19 4.2 mi NE, Hwy D,0.3 mi North of Hwy 0, Callaway Electric Cooperative Utility Pole No.12913 IDM 20 4.3 mi NE, City of Readsville, Callaway Electric Cooperative Utility Pole No.12S30 IDM 21 4.0 m NNE, County Road 155,1.9 mi North of Hwy O, p Callaway Electric Cooperative Utility Pole No.19100 IDM 22 k 2.5 mi NNE, County Road 150,0.5 mi North of Hwy 0, Callaway Electric Cooperative Utility Pole No.19002 IDM 23 6.7 mi NNE, City of Yucation, Callaway Electric Utility Pole No.12670 IDM 24 7.0 mi NE, County Road 191,2.1 mi North of Hwy K, Callaway Electric Cooperative Utility Pole No.12498 IDM 25 8.7 mi E, County Road 2S9,0.3 mi South of County Road 287, Callaway Electric Cooperative Utility Pole No.11295 IDM 26 12.1 mi E, Town of Americus, Callaway Electric Cooperative Utility Pole No.11159 IDM 27 9.5 mi ESE, Town of Bluffton, Callaway Electric Cooperative Utility Pole No.11496 IDM 23 3.3 mi SE, County Road 469,2.0 mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06896 IDM 29 2.7 mi SSW, County Road 448,1.2 mi North of County Road 459, Callaway Electric Cooperative Utility Pole No. 06851 IDM
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TABLE I (Cont.) SAMPLING LOCATIONS Location . Sample Code Description * ' Types-30 4.6 mi SSW, W side of County Road 447 and 463. Junction, Kingdom Telephone Company Pole No. 2K1 IDP 31 7.6 mi SW, City of Mokane, Callaway Electric a Cooperative Utility Pole No. 06039 IDM 32 5.4 mi WSW, Hwy VV,0.6 mi West of County Road 447, Callaway Electric Cooperative Utility Pole No. 27031 IDM 33 7.3 mi W, City of Hams Prairie, SE of Hwy C and AD Junction IDM 34** 9.7 mi WNW, NE Side of Hwy C'and County Road 408 .. Junction IDM i 35 5.8 mi NNW, City of Tolede, Callaway Electric Cooperative Utility Pole No.17684 IDM g 36 5.2 mi N,' County Road 155,0.8 mi South of County Road 132, Callaway Electric Cooperative Utility Pole No.19137 IDM 37 0.7 mi SSW, County Road 439,0.9 mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35077 IDM - 38 4.8 mi NNW, County Road 133,1.5 mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No. 34708 IDM 39 5.4 mi NW, County Road 112,0.7 mi East of County ' Road 1i1, Callaway Electric Cooperative Utility Pole No.17516 . ID M ~) q 40 4.2 mi WNW, NE Side of County Road 112 and Hwy 0, Callaway Electric Cooperative Utility Pole No. 06326 IDM .l 1 41 4.8 mi W, Hwy AD,2.8 mi East of Hwy C, Callaway ) Electric Cooperative Utility Pole No.18239 IDM 42 4.4 mi SW, County Road 447,2.6 mi North of County Road 463, Callaway Electric Cooperative Utility . Pole No. 06326 IDM 43 0.5 mi SW, County Road 459,0.7 mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35073 IDM h ! I
1 i I
/ T/.BLE I (Cont.)
SAMrLING LOCATIONS I Location Saiaple Code Description
- Types
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44 ! 1.7 mi WSW, Hwy CC,1.0 mi South of County Road 459, ! Callaway Electric Cooperative Utility Pole No.13769 IDM ' 45 1.0 mi WNW, County Road 428,0.1 mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18530 IDM 46 1.5 mi NNW, NE Side of Hwy CC and County Road 466 Intersection, Callaway Electric Cooperative Utility Pole No. 2S242 IDM j 47 i 0.9 mi NNE, County Road 443,0.9 mi South of Hwy 0, I Callaway Electric Coopertive Utility Pole No. 28151 IDM l 43 0.4 mi NE, County fload 448,1.5 ini South of Hwy 0, Plant Security Sign Post IDM 49 1.'7 mi E, County Road 448, Callaway Electric O Cooperative Utility Pole No. 06959, Reform Wildlife Management Pari <ing Area IDM 50 0.9 mi SSE, County Road 459,3.3 mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35036 IDM 51 0.7 mi SE, Located in the "Y" of the Railroad Spur, NW of Sludge Lagoon IDM 52 0.4 mi ESE, Light Pole near the East Plant Security Fence ID M I i 1 1 9
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TABLE I - (Cont.) SAMPLING LOCATIONS
.i Location ' Sample Code _
Description
- Types i A7** 9.5 mi NW, C. Bartley Farm
. APT,AIO 4 A8 0.9 mi NNE, County Road 448,0.9 miles South of HWY 0 APT,AIO .
A9 1.7 mi NNW, Community of Reform ' APT,AIO D01 5.1 mi SE, Holzhouser Grocery Store / Tavern (Portland, M0) -WWA F05 1.0 mi SSE, Onsite Groundwater Monitoring Well .WWA FIS 5.5 mi NE, Onsite Groundwater Monitoring Well WWA. l Mi** 12.3 mi WSW, Green's Farm MLK M5 3.1 mi NW, Schnider Farm MLK V3** 15.0 mi SW, Beazley Farm FPL, SOL $-{1J V6 1.8 mi NNW, Becker Farm FPL V7 1.8 mi N, Meehan FPL { l A** 4.9 mi SSE,0.6 River Miles Upstream of Discharge -- i' North Bank AQS,AQF C 5.1 mi SE,1.0 River Miles Downstream of Discharge North Bank AQS,AQF. ! D 53.0 mi ESE,59,5 River Miles Downstream of Discharge South Bank AQS,AQF j S0l *
- 4.8 mi SE,84 feet Upstream of Discharge North Bank SWA 502 5.2 mi SE,1.1 River Miles Downstream of Discharge North Bank SWA 503 68 mi E, City of St. Louis Water Intake SWA i
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O T ^ a ' e r (c e "t-) SAMPLING LOCATIONS Location Sample Code Description
- Types F1 0.98 mi 5, Callaway Plant Forest Ecology Plot F1 SOL F2 1.64 mi SW, Callaway Plant Forest Ecology Plot F2 SOL F6 1.72 mi NE, Callaway Plant Forest Ecology Plot F6 SQL F3 1.50 mi NE, Callaway Plant Forest Ecology Plot F3 SOL F9 1.45 mi NNW, Callaway Plant Forest Ecology Plot F9 SOL PR3 1.02 mi ESE, Callaway Plant Prairie Ecology Plot PR3 SOL PR4 1.34 mi ESE, Callaway Plant Prairie Ecology Plot PR4 SOL P'~J 1.39 mi NE, Callcway Plant Prairie Ecology Plot PR5 SOL p, PR7 0.45 mi NNW, Callaway Plant Prairie Ecology Plot PR7 SOL O \
PRIO 1.55 mi NNW, Callaway Plant Prairie Ecology Plot PRIO SOL l I
*All distances are measured from the center line of the reactor ;
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- Control locations I
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O 3o ^neivticei erecedere. The analytical procedures described below are those routinely used by CEP to analyze samples. 3.1 Airborne 3.1.1 Gross Alpha and Gross Beta The glass-fiber filter, type A/E (99 percent removal efficiency at I micron particulate), is placed into a two-inch stainles,= steel planchet and counted for Gross Alpha and Cross Beta radioactivity using an internal gas flow, ten channel low-level planchst counting system (Berthold LB770). 3.1.2 Gamma Spec,trometry The filters are composited according to station and sealed in a small, plastic Marinelli beaker. The filters are then counted using either a Ge(Li) or intrinsic germanium detector which is coupled to a computer based, multi-channel analyzer (Nuclear Data). The resulting spectrum is then analyzed by the computer and specific nuclides, if present, identified and quantized. 3.1.3 Strontium-89 and Strontium-90 The composited filters are dissolved in acid and brought to a known volume. Strontium carrier is added and the solution is evaporated to dryness. The resulting residue is taken up in dilute acid. Yttrium carrier is added and placed into ingrowth for 14 days. After the ingrowth period has been estat!ished it is back extracted into an aqueous phase, precipitated as the oxalate, counted in a low background proportional counter (Berthold LB770), and calculated as Strontium-90 activity. The aqueous phase is evaporated to a low volume, precipitated with fuming nitric acid, redissolved in water, made basic with dilute ammonium hydroxide and
precipitated as the oxalate. The dried precipitate is counted in a low h background proportional counter (Berthold LB770) and the Strontium-89 activity is determined by subtracting the previously measured Strontium-90 activity and its corresponding Yttrium-90 ingrowth from the_ measured gross Strontium activity. 3.1.4 Iodine-131 3.1.4.1 Alkaline Leach Method The radiciodine is stripped' off activated charcoal by reduction ster using concentrated ammonium hydroxide (NH40H) and hydrogen I peroxide (H220 )._ The charcoal is then filtered and the remaining solution is acidified with nitric acid (HNO3 ) and extracted with carbon tetrachloride (CCl4 ) to remove the Iodine. It is then back extracted using 0.2% hydrazine solutioni which supplies further purification and an aqueous media for precipitation. It is then precipitated with silver nitrate (AgNO3 ) and filtered on a tared glass-fiber filter as silver iodide (Agl). The dried precipitate is weighed for recovery anj counted for Iodine-131 in a thin window gas flow proportional counter (Berthold LB770). 3.1.4.2 Gamma Spectrometry Method l The charcoal canister is placed directly on an intrinsic germanium detector and Iodine-131 activity determined using Method 3.1.2. 3.1.5 Direct Radiation Direct - radiation measurements are taken by UEC using Thermoluminescent Dosimeters (TLD's). The UEC program employs the Panasonic model UD-814 TLD and model UD-710 automatic dosimeter reader. Each dosimeter consists of three elements of CaSO4 :Tm and one element of Li24 B 07:Cu. The d 1simeters are sealed in a moisture resistant plastic bag and placed inside a polypropj!ene O mesh cylindrical holder in the environment. Af ter exposure in the environment, the dosimeters are read and the exposure for the time period is determined from the CaSO4:Tm elements. The Li2B40 7:Cu element is not used to determine exposure during routine operations. 3.2 Vegetation 3.2.1 Iodine-131 A suitable aliquot of wet Ds received) sample is placed into a small, plastic Marinelli beaker and Iodine-131 activity determined using Method 3.1.2. 3.2.2 Gross Alpha and Gross Beta A suitable aliquot of prepared sample is muffled, dissolved in dilute acid and transferred to a tared two-inch stainless steel planchet. The planchet is counted for Cross Alpha and Gross Beta activity using Method 3.1.1. 3.2.3 Gamma Spectrometry O ^ seitebie eiisuet of gregered semgie ie pieced into a smeti, giestic ; 1 Marinelli beaker and specific nuclides, if present, identified and quantized l using Method 3.1.2. I 3.3 Milk 3.3.1 Iodine-13_l, :
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Two liters of milk containing standardized Iodine carrier are stirred with Amberlite IRA-400 anion exchange resin for one hour. The Iodine is stripped from the resin with sodium perchlorate (NaCIO4 ) acidified with nitric acid, precipitated with silver nitrate (AgNO3) and filtered on a tared glass-fiber filter. The dried precipitate is weighed for percent recovery and counted for Iodine-131 in a thin window, gas flow, proportional counter (Berthold LB770). p 3.3.2 Strontium-39 and Strontium-90 0 Two liters of milk containing Strontium carrier is stirred with Dowex 50TX8 cation exchange resin at a pH of 6 for thirty minutes. All nuclides
r; l l are stripped from the resin with strong acid. Method 3.1.3 is then followed beginning at the ingrowth period. 3.3.3 Gamma Spectrometry ; 1 A one liter aliquot of milk is placed in a plastic Marinelli beaker and specific nuclides identified and quantized using Method 3.1.2. 3.3.4 Elemental Calcium One milliliter of milk is diluted to 100 milliliters and acidified with nitric acid. The diluted sample is analyzed for Calcium using Instruments S.A. Jy-38 Sequential Plasma Spectrometer. 3.4 Surface and Well Water 3.4.1 Gross Alpha and Gross Beta A suitable aliquot of water is evaporated to dryness and transferred to a tared two-inch stainless steel planchet. The planchet is counted for Gross Alpha and Gross Beta activity as in Method 3.1.1. 3.4.2 Tritium Three milliliters of water sample are mixed with liquid scintillation cocktail. This gives a riixture of twenty-three percent sample in a clear gel type cocktail. The mixture gives a Tritium counting efficiency of approximately thirty percent. The counting system used is a Beckman LS l 3801 Liquid Scintillation System. 1 3.4.3 Strontium-89 and Strontium-90 A one liter aliquot of water, containing Strontium carrier,is evaporated to dryness and the residue taken up in dilute acid. Method 3.1.3 is then followed beginning at the ingrowth period. 3.4.4 Gamma Spectrometry A one liter aliquot of the water sample is placed in a plastic Marinelli beaker and specific nuclides identified and quantized using Method 3.1.2. 1
O 3.5 vish 3.5.1 Gross Alpha and Cross Beta - Refer to Method 3.2.2. 3.5.2 Strontium-89 and Strontium-90 A suitable aliquot of prepared sample is muffled, ' dissolved . in acid, transferred to a 100 mi beaker and Strontium-Yttrium carriers added. The sample is then wet ashed with nitric acid and hydrogen peroxide, taken to dryness and up to volume in dilute acid. Method 3.1.3 is then followed beginning at the ingrowth period. 3.3.3 Gamma Spectrometry - A suitable aliquot of prepared sample is placed in a plastic Marinelli beaker and specific nuclides identified and quantized using Method 3.1.2. 3.6 Bottom, Bedload and Washload Sediment O 3.6.1 Gross Ai he eed C,oss Beta A suitable aliquot of prepared sample is muffled, dissnived in acid, ] nitrated, evaporated and transferred to a tared two-inch stainless steel planchet. The planchet is counted for Gross Alpha and Cross Beta activity as in Method 3.1.1. 3.6.2 Strontium-89 and Strontium-90 Refer to Method 3.5.2. ! 3.6.3 Gamma Spectrometry Refer to Method 3.5.3. j 4.0 Sample Preparation Methods 4.1 Vegetation
- 1. Sample wet weight is recorded.
O 2. A known wet weight is gieced in e piestic Merineiii beeker 1er Gamma Spectrometry.
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- 3. Remaining sample is transferred to' a drying pan and placed in an- kj oven at 1100C.
- 4. The dry sample is weighed, ground to a fine powder and homogenized.
- 5. Specific aliquots of the sample are then taken for further analysis.
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4.2 Bottom Sediment J 1.- Sample is transferred to a drying pan and placed in an oven at 1100C.'
- 2. The dry sample is weighed, ground to a fine powder and homogenized.
- 3. Specific aliquots of the sample are then taken for analysis.
4.3 Bedload and Washload Sediment 1
- l. Sample containers are allowed to stand undisturbed to allow. 1 t
suspended solids to settle. l
- 2. Liquid portion of the samples is then decanted and saved. l
- 3. Remaining residue is then transferred to a beaker and placed on a hot plate (Iow heat) to drive off remaining liquid.
4. 5. The dry weight of the sediment is recorded. Sediment is then placed. in a plastic Marinelli beaker for Gamma g j Spectrometry.
- 6. After gamma counting, sample is ground to a fine powder and homogenized. j
- 7. Specific aliquots of the sample are then taken for further analysis.
?
l l 4.4 Fish 1
- 1. Each specimen is dissected and filleted and a~ wet weight recorded.
- 2. Filleted portions are transferred into drying pans according to species and placed in an oven at 1100C. ;
- 3. The dry sample is weighed, ground, blended and placed in a plastic container.
- 4. Specific aliquots of the sample are then taken for analysis. ,
5.0 . Major Instrumentation 5.1 Nuclear Data Computer Based Gamma Spectrometer i The Gamma Spectrometer consists of a Nuclear Data Multichannel Analyzer g equipped with two solid state Ge(Li) detectors and three intrinsic detectors
j
'I !
O having 2.8 kev, 3.0 kev, 2.07. kev, 2.20 kev . and 1.85 kev resolutions and respective efficiencies of 16.1%, 8.9%, 22.6%, 30.6% and 25.1%. j l The Computer Based Nuclear Data Gamma Spectrometry System is used for all i gamma analysis. The system uses Nuclear Data developed sof tware.(automatic l isotope analysis) to search and Identify, as well as quantize the. peak' s of interest. 5.2 Beckman Liquid Scintillation Counting Systems A Beckman LS-5801 Liquid Scintillation Counter will be used for all: Tritium determinations. The system background averages approximately 30 cpm with a counting efficiency of approximately sixty percent with an unquenched standard. 5.3 Sequential Plasma Spectroanalyzer l The JY-38P (Instruments SA) Sequential Plasma Spectroanalyzer is an emission spectrometer system designed for rapid, automatic sequential elemental analyses. It is comprised of three main sub-systems: O - The inductively Ceegied eiesme oCe> Source
- The Scanning Monochromator
- The Data Acquistion and Control Package 5.4 Berthold-10-Channel Low-Level Planchet Counting System - ;
l The Berthold LB770 is capable of simultaneously counting 10 planchets for Cross ! Alpha and Gross Beta activities alternately with proportional gas flow detectors. The system has an average background count rate of less than I count per minute for Beta and less than 0.05 count per minute for Alpha. The instrument has an ; Alpha efficiency of thirty-three percent for Plutonium-239 and Beta efficiencies of forty-five percent for Strontium-Yttrium-90, and forty-three percent for Cesium-137. Data from the system is input into to a computer to calculate . activity as pCi/ unit volume. Q 6.0 Isotopic Detection Limits and Activity Determinations A discussion of the calculations used in determining detection limits and activity by Controls for Environmental Pollution, Inc.,is found in Appendix B.
Table III gives the detection limits for radiochemical and chemical analytical methods. ${ i For each sample type, the table lists the detection level for each isotope analyzed. i Table IV gives the detection limits for Gamma Spectrometry. The table lists isotopes and respective detection levels for air particulate, vegetation, milk, water, sediment and fish. The sample counting times and the aliquot .'ze used for detection limit calculations and actual analyses are shown in Tables V and VI, respectively. l l i l O O 3 1
- 3 m m l
/i 1 /
i Cp / g C e p n i i 6 Cp 5 d o 0 3 0 S l 0 0 R 0 0 E l T m
/
i E u C M it p A i - r 0 _ R T 0 5 A _ P 3 *
- L 0 *
- _ A 9 m l l C
/ /i / m m m i i g g I
M u Cp C Cp / / i p i i E l t n 2 0 0 Cp Cp i o 0 C r 1 0 0 1 t 0 2 2 D S 0 _ 0 0 _ N A I I L A 9 8 3 m l l _ I / / / m m C m i i i g g E I u Cp Cp Cp / / L M i i O i _ B E t n 2 0 5 Cp Cp A 1 o 0 T 1 r 2 1 0 0 0 _ C S t 0 3 3 O I 0 0 D 3
- A *
- a m * *
- _ R t
/
l - e i m / m m R g i B Cp g g
/ Cp / /
_ O s i i i _ F s o 3 Cp 0 C Cp r 0 p S 0 3 T I G 2 2 2 _ 0 0 0 0 M I L * *
- _ a * *
- N h p
l O m / m m l g i g g I T A / Cp / / _ i i i C s s Cp 0 Cp Cp E o _ T r 3 2 3 3 _ E G 0 0 0 _ D r d e o _ s ht _ e e t a t e t in n e _ p l a d W e M _ y u o l dm T c i o l e ai h t ode c h e it r i d W a t e h g _ lp a a d ldS e L g e i P R n n B d eWeW i m o a ,al - a e e i n n loio O n e t t S r o r o t a c a mhS os i l a y rW e b b e k t adn k - r r g i f r L D
- oWa l t l e s i
A i A u i A *
- V M S B F * *
- LY
r 1 1 TABLE IV g-DETECTION LIMITS BY CAMMA SPECTROMETRY 4 l Fish, Vegetation Airborne Energy Milk and Water and Sediments Particulate meV isotope pCl/ liter pCi/gm pC1/m3 _ 1 I O.122 Cobalt-57 1 .0.002 0.001 0.134 Cerium-144 18 0.02 0.005 i 0.320 Chromium-51 18 0.004 0.010- , 0.364 Iodine.131 'l 0.03 0.02 i 0.477 Beryllium-7 40 0.75 0.01 0.537 Ba/La-140 4 0.01 0.03 0.605 Cesium-134 10 0.03 0.010 0.ti22 Ru , Rh-106 10 0.04 0.001 0.662 Cesium-137 2 0.04 0.001 h 0.765 Zr, Nb-95 8 0.08 0.026 0.810 Cobalt-58 3 0.02 0.001 0.835 Manganese-54 2 0.02 0.001-1.095 Iron-59 3 0.02 0.006 1.115 Zinc-65 16 0.05 0.045 l 1.173 Cobalt-60 5 0.02 0.014 l O l l 1
;I l l ~ .
c _ e p s s s s s s S r r r r r r u O a m h S o h S o u h 8 u o h 8 u o h u o h S u o m 3 a G 1 . 3
- s n 1 s r i
- r u e u o m n o h 0 i h 0 d 3 I
o 3 1 m n - u i i i t m _ r 0 T 5 1 0 9 . . n n n n n n S u r i i i i E i im m m m m t M n 0 0 0 0 0 I o 0 0 0 0 0 _ T t r 1 1 1 1 1 _ G S _ V N I E T 9 L N 8 B U - n n n n n O A m .- O u i i i T C i m m im im m - t n 0 0 0 0 E 0 0 L o r 1 0 1 0 1 0 1 0 1 P t M S A S a t . . . . . e i n n n n n B m i i i i s s m m m m e s 0 0 t o 0 0 0 0 0 u r 1 1 0 1 0 1 0 1 i n G m 0 a 0 1 h . . p n n n r l i i in o A m m m im f s 0 0 d s 0 0 e o r 0 0 0 0 t 1 1 1 1 n G u o c r d e o e t h e . t in a t n t e _ e p l a d W ,e M o y u l dm c i c l e h T i ai ode c e t r i d W l a l a a d dS e p P R n n e d L m e e o a Bal e a n n i t e ,oi o n S r r a c mhSl i l nv b o b o t e g k f a t os ad h k a - r r r oWan l t l i i e i u s A A i A V M S B F *
. f,'
i
! l1l i\l
a G m i u l l c m a 1 SI C S Y 1 L 3 3 A 1 1 N - m e 0 A n 5 6 2 _ L id 2 A I o _ U T _ C A m u l D i t m N i r 3 A T S - N O - I T A 0 9 L m u U i t I V C n L or 3 E A t g 1 1 g g L C S m B , 5 0 0 0 0 0 A T I 9 6 1 2 1 1 1 T 3 2 I M - L m i u N t O n I o T r _ t _ C S _ E _ T _ E a _ D t _ e R B O _ d F n 3 a _ D a m g 1 g g E 0 h 5 0 0 0 S p 6 1 1 1 1 U l 2 T A s O s U o r Q I G _ L A e e t i n e la d l p u io i o y c o S T i t r id d e a a n l p P R n a _ m e e o t a n n i t n _ S r r a r e _ o o t e e m _ b b g k t i h r r d i i e l i a e i s A A V M W S F 4e'
O 7o co iitv centrei erenrem CEP employs a multi-faceted Quality Control Program designed to maintain high performance of its laboratory. The overall objectives of the program are to: 1.) Verify that work procedures are adequate to rneet specifications of UEC. 2.) Coordinate an in-house quality control program independent of external programs, to assure that CEP is operating at maximum efficiency. Objectives are met by a variety of procedures that oversee areas of sample receipt and handling, analysis and data review. These procedures include standard operating procedures, internal lab spike analysis, blank analysis, reagent, carrier and nuclide standardization as well as participation in the U.S. Environmental Protection Agency's Interlaboratory Cross-check Program (See Appendix A for EPA Cross-check Results). CEP's Quality Assurance Program is reviewed and revised (when necessary) on a O resuierix scheduied besis. This review esseres the1 1he prearem meets eii cerrent regt.fatory guidelines as well as maintaining the highest standards of quality assurance pM ctices. 8.0 Data Interpretations and Conclusions This section addresses interpretations and conclusions regarding all types of samples analyzed during this report period. Analysis and review of data incorporates various techniques from historical comparison to statisical evaluation. Results which do not compare with the historical range are recalculated for verification. If the recalculation verifies the original result, the sample is reanalyzed if possible (i.e. sufficient sample volume or isotope half life). Once it is determined that the results obtained are accurate, a statistical 1 analysis is made. Results which are outliers with respect to historical comparison of O previous data are considered out of baseline range or anomolous and will be so noted in l i the report. " I j
s 8.1- Airborne Particulate and Radiolodine h Airborne particulate samples were collected at five (5) monitoring stations on a~- a weekly. basis from December 30,-1987,' through March 31g 1988. The five' airborne particulate stations were also collection sites for airborne radioiodine
- (see Table Vill).-
4 All of the air particulate samples were analyzed for Gross Beta ' activity. Gamma Spectrometry, Strontium-90 and Strontium-89 analyses were performed on quarterly composites from each station. The range of Gross Beta activity at each of the sampling locations follows. Collection Location Minimum (pC1/m3) ' Maximum (pC1/m3) Site A1 0.00310.001 0.04410.002 Site A7 0.01310.002 0.05110.002 Site A8 0.01210.002 0.05110.002 Site A9 0.011 +0.002 0.038 +0.002 Site B3 0.01020.002 0.04310.002 Table VII, Gross Beta in Airborne Particulate, shows that the Gross Beta activity ranged from a minimum at Site A1 of 0.003 10.001 pCl/m3, collected 03/10/88-03/17/88 to a maximum of 0.0511 0.002 pCi/m3 at Sites A7 and A8 during the collection period of 02/04/88-02/12/88. The highest mean Gross Beta activity during the report period was observed at Site A7 with a mean activity of 0.0271 0.011 pCi/m3 . Mean weekly Gross Beta activities ranged from a low of 0.01210.005 pC1/m3 h during the collection period of 03/10/88-03/17/88 to a high of 0.04510.006 I
O nCi/m3 deries 1he coitectiee geriod of 02/0a/88-02/12/88. i Strontium-90 was detected in one airborne particulate sample composite. Site ( i A8 indicated activity of 0.0021 0.001 pCi/m3 All of the other airborne particulate composite analyses for Strontium-89 and Strontium-90 were less than the lower limit of detection (0.002 pCi/m3). Gamma spectratanalysis of the site composites indicated the following activities: Collection Location Isotope Identified pCi/m3 Site A1 Beryllium-7 0.17210.078 Site A7 Beryllium-7 0.49310.210 Site A8 Beryllium-7 0.07210.029 Site A9 Beryllium-7 0.179 + 0.077 Site B3 Beryllium-7 0.181 0.085 No other gamma emitting isotopes of interest were detected in the quarterly site composites. Results of the airborne radioiodine analyses may be found in Table Vill. Iodine-131 activity above the lower limit of detection (0.'006 pCi/m3) was detected in one sample this quarter. Site B3 indicated Iodine-131 activity of 0.00610.004 pC1/m3 on 01/28/88. Levels and fluctuations of activity in the air particulate and radioiodine samples are consistent with the previously accumulated preoperational data. l ya 0 0 0 0 ~0 0 0 0 0 0 0 0 0 l t d e 1 5 4 + + + + + + + + + + + 1 kerh 4 6 6 5 3 7 9 9 2 17 3 3 3 2 2 2 4 2 eBat e d f 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 Wssnot a o 0 0 0 0 0 0 0 0 0 0 0 0 O ' rS G+~ 2 2 2 2 2 2 2 2 2 2 2 2 2 0 3 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 e 1 + + + + +2 + 6 4 4 3 3
+ + + + + 1 +
t 1 1 7 3 0 3 2 4 i 3 3 2 3 2 4 2 2 1 1 1 1 1 2 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0
) 0 0 0 0 0 O 0 0 0 0 0 0 0 3 0 m
_ /i ' . Cp 2 0 2 0 2 0 2 0 2 0 2 2 2 2 2 2 2 2 0 0 0 0 0 0 0 0 8 _ 0 ( 9 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A S _ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ E e 1 + +0 5+5 + + + + + + + + 1 + _ T i t 0 1 3 3 2 2 2 3 2 3 5 4 0 8 3 2 1 3 2 _ A S 0 0 0 0 0 0 0 0 0 0 0 0 0 1 1 1 1 1 2 0 _ L _ U 0 0 0 0 0 0 0 0 0 O 0 0 0 0 _ CI R T E I R T 2 0 2 0 2 0 2 0 2 0 2 0 2 2 2 2 2 2 2 0 0 0 0 0 0 0 0 A I _ V R 8 0 0 0 0 0 0 0 0 0 0 0 0 0 1 0 P A 8 A E U 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E 8 1 6+6 + 3 5 + + + +3 9+5 9 +5 + + + 1 2 L 9 e + _ B N Q 1 i t 1 3 3 2 2 2 1 5 2 1 1 1 1 1 2 1 4 2 A R T S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T _ O S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B R - - R I F _ I A 2 2 2 2 2 2 2 2 2 2 2 2 2 1 N 7 0 0 0 0 0 0 0 0 0 0 0 0 0 1 I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ A A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 T t e 1 + + + + + +9 3+2 0+ 7 +8 3+ + 1 9 9 3 9 2 1 7
+
E i S 3 3 2 2 3 5 2 1 2 2 1 1 1 2 B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ S S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O R - G 2 2 2 2 2 2 2 2 2 2 1 2 2 1 0 0 0 0 0 0 0 0 0 0 0 0 0 1 l 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ t e 71 + 8+2 7+ 4 +3 5+ + + + + 3+9 4+ 1 1 1 1 4
+
i 3 3 2 2 2 4 3 1 2 2 0 1 2 S 1 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 0 O 0 0 0 0 0 0 0 0 y _ t _ i
' v 3 8 3 3 3 8 3 3 3 3 3 8 8 i t
_ d 3 3/ 8/ 3/////////
// 3 3 3 3 3 8 3 3 8 cn
_ i o 7 4 1 3 4 2 3 5 3 0 7 4 1 Aito r 0 1 2 2 0 2 0 _ e // / / ///////// 1 1 1 1 2 3 aa t i _ P 1 1 1 1 2 2 2 2 3 3 3 3 3 ev _ n 0 0 0 0 0 0 0 0 0 0 0 0 0 Be _ i o - - - - - - - - - - - - - sDn s a t c 7 8 8 8 8 3 3 8 8 8 8 8 8 ode r r l e 3 8 3 8 3 3 3 3 3 3 3 3 8
//
0 7
/ / 4///////// gam d l
o 3 0 1 1 2 2 0 8 4 2 3 5 3 1 1 0 7 2 0 1 1 4 2 n ne ah _ C /// 2 1
/ /////////
1 1 1 2 2 2 2 3 3 3 3 at t _ eS 1 0 0 0 0 0 0 0 0 0 0 0 0 f M 1o h
0 0 9 _ A ' e * * * * * * * - _ t _ i S 8 A -
) e * * * * * * * * * * * *
- t 3 i m S
/i C p
( E R N E I I I D T I V R O A 8 7 E I O U 8 A ' L I Q 9 e * * * * * * * * * * * *
- B D 1 t O A T i A S S T R R E I F
N R O B R I A l . A 3 e * * * * * * * * * *
- a * /i m
t i S Cp 6 0 0 0 e v o b a s d i d 8 8 8 8 8 3 8 8 8 8 8 8 8 e sy
/8 3 8 8 3 8 /8/ 8/ 8/ 8/ 3/ 8/ 8 t 7 4/ / / /8 /
i o cl a r e 0 1 1 2 2 0 4 2 3 5 3 0 7 1 1 2 0 1 4 2 3 1 ten P / / / / ///////// 1 e a 1 1 1 1 2 2 2 2 3 3 3 3 3 d Mt n 0 0 0 0 0 0 0 0 0 0 0 0 0 1 i o - - - - - - - - - - - - - 3 y t 1 b c 7 8 8 8 8 8 8 8 8 8 8 8 8 e d e 8 3 8 8 8 3 8 8 8 3 8 8 8 n e l l /0 7/ 4/ / /// 8/ /4 / / / / i i o 3 0 1 1 2 2 0 2 81 5 3 0 7 4 d f 1 2 0 2 o re i C /2 /1 / / ///////// 1 1 I O 2 2 2 2 3 3 3 3 1 1 1 1 0 0 0 0 0 0 0 0 0 0 0 0 oV N *
,u 7 l , i
8.2 Thermoluminescent Dosimetry h Thermoluminescent Dosimeters (TLD's) were employed to determine direct radiation levels in and around the Callaway Site. Panasonic model UD-314 TLD's sealed in plastic bags were placed in polypropylene mesh cylindrical holders at 52 Jocations and exchanged quarterly. Data appearing in Table IX are the result of reading and averaging the CaSO4 :Tm elements. Net exposures were obtained by normalizing the total l exposure to a 90-day quarter (standard quarter). Exposure levels for all monitoring locations during the first quarter, !933, are consistent with background levels observed during previous quarters. j O 1 l i 1 0 TABLE IX O THERMotUMINESCeNT DoSiuErRv FIRST QUARTER 1988 Net Field Total Exposure Sation Time Exposure (mrem /Std identification Collection Location (Days) (mrem 1 20) Otr 12 c) C A-IDM-1 11 Mi NW, City 1.imits of Fulton on Hwy Z, 0.8 Mi East of Business 54 98.1 18.7 263 17.2 1 3.3 C A-ID M-2 6.6 Mi NW, County Road 111,0.6 Mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No.17571 98.1 19.6 1 5.5 17.9 2 5.1 C A-IDM-3 1.3 Mi NW',0.1 Mi West of Hwy CC on gravel Road 0.3 Mi South Hwy 0, Callaway Electric Cooperative Utility Pole No.18559 99.0 20.4 214 18.5 2 3.3 C A-ID M-4 1.9 Mi N,0.3 Mi East of the 0 and CC Junction, Callaway Electric Cooperative Utility Pole No. ISS92 98.9 13.4 23 4 16.7 13 4 O C ^-ID M-5 1.> Mi aNe, erimery Meteoroiosicei rewer 8.9 17.3 1 4.9 15.7 1 u.4 C A-ID M-6 2.0 Mi W, County Road I;28,1.2 Mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18609 98.1 18.1 + 2.8 16.6 + 2.6 C A-ID M-7 1.3 Mi S, County Road 459,2.6 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35097 98.9 19.5 1 4.2 17.7 2 3.3 C A-ID M-8 2.9 Mi S, County Road 459,1.4 Mi North of l Hwy 94, Callaway Electric Cooperative Utility Pole No. 06823 98.9 22.0 298 20.0 i S.1 C A-ID M-9 3.7 Mi S, NW Side of the County Road 459 and 94 Junction, Callaway Electric Cooperative Utility Pole No. 06754 98.9 21.6 29 6 19.6 2 6.3 C A-IDM-10 4.0 Mi SSE, Hwy 94,1.8 Mi East of County Road 459, Callaway Electric Cooperative Utility Pole No.12182 98.9 22.1 2 5.2 20.1 174 C A-IDM-Il 4.3 Mi SE, City of Portland, Callaway Electric Cooperative Utility Pole No.12112 98.9 23.6 124 21.4 283 O
'l l
TABLE IX (Cont.) . THERMOLUMINESCENT DOSIMETRY h FIRST QUARTER 1988 Net Fleid Total Exposure l Sction Time Exposure (mrem /Std j Identification Collection Location (Days) (mrem'1 20) Otr i 20) j C A-IDM-12 5.3 Mi SE, Hwy 94,~ 0.6 Mi South of Hwy D, ' j Utility Pole on' East Side of Hwy 98.9 21.3 2 5.2 19.4 37 4 C A-ID M- 13 5.6 Mi ESR, Hwy 94,0.75 Mi East of Hwy D, Kingdom Telephone Pole No. 2X1 98.9 23.7 25 7 21.6 28 6 CA-IDM-14 5.0 Mi ESE, SE Side of Intersection D and 94, Callaway Electric Cooperative Utility Pole i No.I1940 98.9 19.5 142 -17.8 2 2.2 C A-IDM-15 4.2 MI ESE, Hwy D,2.5 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No.27379 98.9 19.9 114 18.I 17 3 C A-ID M-16 4.1 Mi ENE, Hwy D,3.6 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole 3 W No.I2976 98.9 17.8 1 3 6- 16.2 13 3 C A-IDM-17 4.0 M1 E, County Road 4053, 0.3 Mi East of Hwy 94, Kingdom Telephone Company Pole No.3X12 98.9 21.9 27 7 20.0 10 7 l CA-ID M-18 3.8 Mi ENE, Hwy D,0.4 Mi South of Hwy 0, Callaway Electric Cooperative Utility Pole a No.12952 98.9 19.0 26 2 17.3 + 2.4 C A-IDM-19 4.2 Mi NE, Hwy D,0.3 Mi North of Hwy 0, 1 Callaway Electric Cooperative Utility Pole No.12918 98.9 20.7 + 4.2 18.8 + 3.8 ) C A-ID M-20 4.8 M1 NE, City of Readsville, Callaway ' Electric Cooperative Utility Pole No.12830 98.9 19.5 14 3 17.7 21 3 l C A-IDM-21 4.0 Mi NNE, County Road 155,1.9 Mi North of Hwy 0, Callaway E!ectric Cooperative j Utility Pole No.19100 98.9 19.5 17 6 17.7 11 6 J C A-IDM-22 2.5 Mi NNE, County Road 150,0.5 Mi North of Hwy O, Callaway Electric Cooperative !
?
i - Utility Pole No.19002 98.9 20.2 + 5.3
- 18.4 .+. 4.9 -
i j
TABLE IX (Cont.) O rueauotuuisesceur oosi=erav FIRST QUARTER 1988 Net Field Total Exposure Station Time ' Exposure (mrem /Std Identification Collection Location (Days) (mrem i 2a) Qtr i 2 o) CA-IDM-23 6.7 M1 NNE, City of Yucation, Callaway Electric Cooperative Utility Pole No.12670 98.9 19.9 144 13.1 2 4.0 C A-ID M-24 7.0 M1 NE, County Road 191, 2.1 Mi North of Hwy K, Callaway Electric Cooperative Utility Pole No.12498 98.9 19.0 135 17.2 184 C A-ID M-25 8.7 M1 E, County Road 289,0.3 Mi South of County Road 287, Callaway Electric Cooperative Utility Pole No. I1295 98.9 20.9 215 19.0 164 C A-ID M-26 12.1 MI E, Town of Americus, Callaway Electric Cooperative Utility Pole No. Ii159 98.9 14.2 183 12.9 143 C A-ID M-27 9.5 M1 ESE, Town of Bluff ton, Callaway O- Electric Cooperative Utility Pole No. I!496 98.9 20.9 i 5.4 19.0 194 CA-IDM-28 3.3 Mi SE, County Road 469,2.0 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06896 99.8- 15 19.4 2 17.5 13 2 CA-IDM-29 2.7 Mi SSW, County Road 448,1.2 Mi North of County Road 459, Callaway Electric Cooperative Utility Pole No. 06851 98.9 20.4 17 6 18.6 11 6 CA-IDM-30 4.6 Mi SSW, W Side of County Road 447 and' 463 Junction, Kingdom Telephone Company Pole No. 2K1 98.9 17.9 15 2 16.3 12 2 C A-ID M-31 7.6 Mi SW, City of Mokane, Callaway Electric Cooperative Utility Pole No. 06039 93.9 21.6 16 5 19.6 11- 5 C A-ID M-32 5.4 M1 WSW, Hwy VV,0.6 Mi West of County Road 447, Callaway Electric Cooperative Utility Pole No. 27031 98.1 1' 19.1 25 17.5 17 4 CA-IDM-33 7.3 Mi W, City of Hams Prairie, SE of Hwy C and AD Junction 98.1 19.2 16 3 17.6 13 3 CA-IDM-34 9.7 Mi WNW, NE Side of Hwy C and County Q Road 408 Junction 98.1 20.2 15 5 18.5 10 5
TABLE IX (Cont.) THERMOLUMINESCENT DOSIMETRY h FIRST QUARTER 1988 i Net i Field Total Exposure i Station Time Exposure (mrem /Std i Identification Collection Location (Days) (mrem 1 20) Qtr i 20) ! C A-ID M-35 5.8 Mi NNW, City of Toledo, Callaway Electric Cooperative Utility Pole No.17684 98.1 18.6 204 17.0 163 j i C A-IDM-36 5.2 Mi N, County Road 155,0.8 Mi South of County Road 132, Callaway Electric Cooperative Utility Pole No.19137 98.9 18.9 223 17.2 292 C A-ID M-37 0.7 Mi SSW, County Road 459,0.9 Mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35077 93.9 21.2 397 19.3 327 C A-ID M-38 4.8 Mi NNW, County Road 133,1.5 Mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No. 34708 93.1 15.7 + 2.3 14.4 + 2.1 C A-ID M-39 5.4 Mi NW, County Road 112,0.7 Mi East of County Road 111, Callaway Electric Cooperative Utility Pole No.17516 98.1 21.5 1 4.3 19.8 2 3.9 i C A-ID M-40 4.2 Mi WNW, NE Side of County Road 112 and i Hwy 0, Callaway Electric Cooperative Utility Pole No. 06326 98.1 20.7 20 4 19.0 3.7 C A-ID M-41 4.8 Mi W, Hwy AD,2.3 Mi East of Hwy C, l Callaway Electric Cooperative Utility Pole No.18239 98.1 19.5 _+ 4.0 17.9 + 3.7 C A-ID M-42 4.4 Mi SW, County Road 447,2.6 Mi North of County Road 463, Callaway Electric Cooperative Utility Pole No. 06326 98.1 15.5+ 1.4 14.2 33 1 C A-ID M-43 0.5 Mi SW, County Road 459,0.7 Mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35073 98.9 19.6 + 4.7 17.8 + 4.3 C A-ID M-44 1.7 Mi WSW, Hwy CC,1.0 Mi South of County Road 459, Callaway Electric Cooperative Utility Pole No.18769 98.9 13.8 + 3.2 17.1 + 3.0 C A -ID M-45 1.0 Mi WNW, County Road 428,0.1 Mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18580 97.8 18.1 + 2.3 16.6 + 2.2 h 1 l
ll
. TABLE IX (Cont.) 1 O THERuoto 1NeSCEur ooSiuerRv l FIRST QUARTER 198_8
)-l 1
. Net Field Total Exposure ]
Station Time Exposure (mrem /Std 1 Identification Cellection Location (Days) (mrem 1 20) Otr i 20) k C A-!D M-46 1.5 Mi NNW, NE Side of Hwy CC and County Road 466 Intersection, Callaway Electric - Cooperative Utility Pole No. 28242 98.9 20.7 11 4 18.8 17 3 1 C A-ID M-47 0.9 M1 NNE, County Road 448,0.9 M1 .l South of Hwy O, Callaway Electric ! Cooperative Utility Pole No. 23151 98.9 19.4 2' 4.6 17.7 12 4 i C A-ID M-48 0.4 Mi NE, County Road 448,1.5 Mi South of Hwy O, Plant Security Sign Post 98.8 18.9 22 3 17.2 29 2 CA-IDM-49 1.7 Mi E, County Road 448, Callaway Electric j Cooperative Utility Pole No. 06959, Reform Wildlife Management Parking Area 98.9 20.1 23 6 18.3 2 5.7 ' C A-ID M-50 0.9 Mi SSE, County Road 459,3.3 M1 North l of Hwy 94, Callaway Electric Cooperative ' Utility Pole No. 35086 98.9 18.7 206 17.0 14 5 C A-ID M-51 0.7 Mi SE, Located in the "Y" of the Reilroad Spur, NW of Sludge Lagoon 99.3 18.9 + 3.4 17.1 + 3.1 ; C A-ID M-52 0.4 Mi ESE, Light Pole near the East Plant Security Fence 99.3 20.7 , 6.1 18.8 + 5.6 O s3 Well Water $ Well water samples were collected monthly from three locations and analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-89, Strontium-90, and gamma-emitting nuclides. Table X presents the results of the radiochemical analyses. Gross Alpha activity ranged frorn less than 2.0 pCi/l to 3.311.? pCl/1. Gross Beta levels varied from less than 3.0 pCi/l to 10.4 10.8 pCi/1. The Gross Alpha and Gross Beta levels were consistent with the preoperational data. Results for Tritium analys's were below the lower limit of detection (500 pCi/l) for all samples. All sample results for Strontium S9 and Strontium 90 analysis were below the lower limits of detection (1.5 pCi/l and 1.0 pCi/l respectively). Gamma spectrometry showed no detectable levels of isotopes of interest. Results are summarized in Table XI. i l 0 r t S 0 9 m i u 0 0 0 0 0 0 0 0 0 t l l l l l l l l l n
)
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/ // / / / i t 1 1 2 3 1 2 3 t i C 0 0 0 0 0 0 0 0 0 ce mi t l
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O 8.4 Serfece weter Surface water samples were collected from three locations on a monthly basis. Samples were analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-90, I Strontium-89, and by Gamma Spectrometry. Results are summarized in Tables XII and XIII. l 1 Gross Alpha and Gross Beta analyses of surface water samples showed a range of activities from 2.011.4 pCi/l to 4.8 11.7 pCi/l and 4.810.6 pCi/l to 7.1 10.7 pCi/1, respectively. The positive Gross Alpha and Gross Beta activities can be attributed to naturally occurring isotopes, such as Potassium-40, and are consistent with the preoperational data. i All Tritium data from surface water samples were below the lower limit of n (.) detection (500 pC1/l). No Strontium-89 or Strontium-90 was detected in any of the surface water samples collected this quarter. Gamma Spectra! analysis of surface water samples showed no detectable activity from isotopes of interest. i j V L - _ ---- - - - - - - - - - - - - - _ - - . - - - - - - - - - - - -
r t S 0 9 m - i u 0 0 '0 0 0 0 0 0 0 t l l 1 l l l l l l n < < < < < < < < <
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_ d e e r n f w o 1 1 1 2 2 2 3 3 3 o o l i 0 0 0 0 0 0 0 0 0 t _ et a 5 5 5 5 5 5 5 5 5 i n ima l _ pc - - - - - - - - - mif A A A A A A A A A l h ait WWW WWW WWW r t e ss O Sn S- S S S S S S S S e A A A A A A A A A w e d o L I C C C C C C C C C L
- Y
8.5 Sediment h Washload, Bedload and Bottom Sediment samples were collected in March from three locations along the Missouri River. Samples were analyzed for Gross Alpha, Gross Beta, Strontium-90, Strontium-39, and by Gamma Spectrometry. Results are summarized in Tables XIV thru XIX. ! The following ranges of Gross Alpha and Gross Beta activities were observed in i the washload, bedload and bottom sediments. j l Gross Alpha Cross Beta I Range Range l
- Sample Type pCi/g pCi/g I l
Washload 4.6+ 1.2 - 7.6 + 2.2 9.4 +0.7 - 14.3+ 0.9 Bedload 2.S + 0.5 - 10.212.2 4.3 0.3 - 13.8_1.1 l Bottom 1.20.2-1.20.2 1 1 0.30.1-1.50.1 1 1 The highest activity of Gross Alpha (10.212.2 pCi/g) was seen in the Bedload sediment at sample location A (0.6 river miles upstream of discharge north bank). The highest activity of Gross Beta (14.310.9 pCi/g) was seen in the Washload sediment at sample location C (1.0 river miles downstraam of discharge north bank). ) l 1 No Strontium-89 or Strontium-90 was detected in the washload, bedload, or bottom sediments collected during the first quarter of 1988. i Gamma Spectralanalysis of the sediment samples collected during this report period are detailed in Tables XV, XVil and XIX, and are consistent with previous j data. l l l Ol! i i i , l l \ r
h TABLE XIV WASHLOAD SEDIMENT Sample Collection Radiochemical Analysis pCi/g (dry) Identification Date Gross Alpha Gross Beta Strontium Strontium-89 CA-AQS-A 03/22/88 4.611.2* - 9.40.7* 1 < 0.20 < 0.30 CA-AQS-C 03/22/88 7.31.7* 1 14.310.9* < 0.20 < 0.30 CA-AQS-D 03/23/88 7.62.2* 1 13.411.2* .<0.20 -< 0.30.
- Quantity not sufficient for reanalysis.
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i i h TABLE XVI 4 I BEDLOAD SEDIMENT. Sample Collection Radiochemical Analysis pCi/g (dry)
. Identification Date Gross Alpha Gross Beta Strontium Strontium-89 {
l CA-AQS-A 03/22/88 10.21 2.2* 13.81 1.l* < 0.20 - < 0.30 ' )
?
CA-AQS-C 03/22/88 12.81 0.5* 4.30.3 1 < 0.20 < 0.30 CA-AQS-D - 03/23/88 '3.510.8
- 5.90.4*
1 < 0.20 < 0.30 ;j
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- Quantity not sufficient for reanalysis.- f O
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' BOTTOM SEDIMENT 1 t
I i Sample Co!Iection Radiochemical A'nalysis pCi/g (dry) , Identification ' Date ' Gross Alpha Gross Beta Strontium-90 Strontium-89 CA-AQS-A 03/22/88 1.20.2 1 0.80.1 3 < 0.20 < 0.30
]
CA-AQS-C 03/22/83 1.20.2. 1 1.00'1 1 < 0.20' < 0.30 - 1 CA-AQS-D 03/23/38 1.210.2 1.50.1 2 < 0.20 < 0.30 O l l I J l l O 1
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3 3 n o o i t 0 0 0 C t i _ ce mi - t l _ e r _ d e - n f w _ o o o A C D i l t _ eta mahn i l _ pc S S S _ mif Q Q Q i l t _ ait A A A r Sn e A A A we ess _ d _ I C C C o L L
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O 8.6 eish Fish were collected during the quarter from .three locations. Types of ' fish collected during this quarter were: freshwater drum, grass carp, carp, bighead carp, white crapple, shortnose gar, bigmouth buffalo, river carpsucker, goldeye, l shorthead redhorse, channel catfish, largemouth bass, blue catfish and gizzard 1 ! shad. Gross Alpha, Gross Beta, Strontium-90, Strontium-89 and Gamma Spectralanalysis were performed on all fish collected each month. Results are presented in Tables XX thru XXV. The activity levels are consistent with the preoperational data. l Cross Alpha activity during this quarter ranged from less than 0.3 pCi/g to ) 0.510.1 pCl/g. Gross Beta activities ranged from a low of 5.1 10.1 pCl/g (sample CA-AQF-C, channel catfish collected 03/22/88) to a high of 9.710.2 pCi/g O V (sample CA-AQF-A, grass carp collected 01/29/88). Gross Alpha and Gross Beta l i activities seen in fish samples can be attributed to naturally occurring isotopes I (e.g. Potassium-40). All fish data for Strontium-90 and Strontium-89 were below the lower limits of detection of 0.20 pCi/g and 0.30 pCi/g, respectively. Results of Gamma Spectralanalysis may be found in Tables XXI, XXIll, and XXV.
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8.7 Milk $ Milk samples were collected from two locations, the Green Farm and the Schneider Farm. The Green Farm supplies cow's milk while the Schneider Farm provides both cow's milk and goat's milk. Analyses for Iodine-131, elemental Calcium, Strontium-90, Strontium-89 and Gamma-emitting isotopes were performed on all milk samples. Tables XXVI and XXVII present results of these analyses. 1 1 No lodine-131 above the lower limit of detection (0.5 pCi/l) was detected in the l milk samples during this period. 1 i l No milk samples collected during the first quarter were above the lower limit of detection of 2.0 pC1/1 for Strontium-89 and 1.0 pCi/l for Strontium-90. O. : No gamma-emitting isotopes of interest were detected in any of the milk ) j i samples. ] l t { No goat milk samples (M5B) were collected during January and February due to { { non-production by th goats. l 1 l O I J
O r^Bte xxvi FRESH MILK Radiochemical Collection ~ lodine-131 Calcium Strontium-90 Strontium-89 Date pCl/l mg/l pCi/l pCi/l l Green Farm (M-1)
-01/12/88 < 0.5 980 < l .0 < 2.0 4 02/09/88 < 0.5 1160 < l .0 < 2.0 03/09/88 < 0.5 980 < l .0 < 2.0 .l I
.. I Schneider Farm (M5A) .j 01/10/88 < 0.5 1300 < 1.0 < 2.0 -
02/07/88 < 0.5 890- <l.0 < 2.0 03/06/88 < 0.5 910 <l.0 < 2.0 Q Schneider Farm (M5B)
< 0.5 03/07/88 1400 < l .0 - < .2. 0l 1
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O 88 venetetie" No vegetation samples were collected during the first quarter of 1988. O O
O l APPENDIX A EPA CROSS-CHECK RESULTS $ 1988 l l i l l l 1 l
O eP^ caoss-caecx enoce^= l 1988 Radionuclides'in Air Filters EPA CeP Known Value Reported Value . Date Parameter pCl/ filter i 1 a pCi/ filter i 20 3/88 Gross Alpha 20 + 5 23 + 1 26 1 1 3 28-+ 1 ) i Gross Beta 50 + 5
~
46 + 2 l 5172 54_I2 Strontium-90
- 17 + 1.5 13 + 2 {
14 1 2 l 15 1 2 ( l O cesium-i37 16 1 3 19 1 7 l
-22 2 7 24 1 7
- Review of raw data indicated initial miscalculation (parent recovery value not factored) and activities of 17,19, and 17 (Y = 17.7) should have been reported.
l a i l O l-l
EPA CROSS-CHECK PROGRAM h
.1988 .l Gross Alpha and Gross Beta in Water EPA. CEP i Known Value Reported Value Date Parameter ' pCi/li 1 a ' pCi/112 o j 1/88- Gross Alpha 415 512
~6 1 2 6 2 Gross Beta
- 315 30 1 2 32 + 2 34_7 2 3/88 Gross Alpha 625 512 512 3 W'
612 Gross Beta 13 1 5 14 2 2 15 1-2 ] 17 1 2 i l .
- Reanalysis obtained values of 14,15,15 (Y = 15). Initial values were the result of QA glassware having beta contamination.
e' 4
-( EPA CROSS-CHECK PROGRAM 1988 Gamma in Water EPA CEP Known Value - Reported Value Date Parameter pCi/li 1 a pCi/l12 a -
2/88 Cobalt-60 69 1 5 56 3 5-62 2 5 68 1 5 Zinc-65 94 1 9.4 '81 1 6 86 2 6 91 1 6. Ruthenium-106 105 + 10.5 - 88 + 5 96 + 5~ 104 + 5 Cesium-134* 64 1 5 47 2 3 54 5 59 2 5 Cesium-137 94 1 5 77 1 5
-89 1 5' 92 1 5
' Values of $8, 58, and 61 dr = 59) should have been reported. Onitial vale _
reported before analysis was complete). O
EPA CROSS-CHECK PROGRAM
$i 1988 Tritium in Water l
EPA CEP l Known Value Reported Value Date Parameter pCi/111 a pCi/112 a 2/88 Tritium 3327 + 362 2760 + 300 j 2994 + 300 1 3062 1 300 l i el 1 l l I O
I O ee^ caoss-ciiecx enoca^u 1988
' Strontium in Water EPA CEP Known Value ' Reported Value Date Parameter pCi/l 21 a pCi/li 2 a 1/88 5trontium-89 30 1 5 30 2 5 35 2 5 40 2 5
- Strontium-90* 13 + 2 9+2 11 + 2
^
11 _ 2
- Review of calculations indicates no reason for lower values.
O O
EPA CROSS-CHECK PROGRAM h 1988 Jodine-131 in Water EPA CEP Known Value Reported Value Date Parameter pCi/l11 cy pCi/li 2 a 4/88 Low Level 7.30 1 075 614 924 924 O O
O ce^ enoss-c"ecx enoca^= 1988 Iodine-131 in Milk EPA CEP Known Value Reported Value Date Parameter pCi/l11 a pCi/l12 a 2/88 Low Level 4.0 + 0.4
- 3.0 + 0.7 4.0 17 ~0 4.0 17 0 O
l @
EPA CROSS-CliECK PROGRAM h 1988 Radionuclides in Food EPA CEP Known Value Reported Value Date Parameter pCi/kgi t a pC1/kg i 2 a 1/88 Strontium-89 46 1 5 Not Reported Strontium-90 55 1 2.75 Not Reported Iodine-131 102 + 10.2 101 + 25 107 2 25 l 111_+ 25 1 l Cesium-137 91 + 5 81 + 10 91 ~ 10 98 1 10 Potassium 1230 2 61.5 mg/kg 1320 + 132 mg/kg 1320 2 132 mg/kg 1320 2 132 mg/kg O I
O APPE'.9 DIX B O Isotopic Detection Lirnits And Activity Determinations l 0
]
l l l 1 Isotopic Detection Limits and Activity Determinations h Making a reasonable estimate of the limits of detection for a counting procedure or a radiochemical method is usually complicated by the presence of significant background. i i It must be considered that the background or blank is not a fixed value but that a series of replicates would be normally distributed. The desired net activity is thus the difference between the gross sample activity and background activity distributions, j i
)
The interpretation of this difference becomes a problem if the two distributions intersect as i indicated in the diagram. ) 1 Background Gross j l j
,\
l l J _ _ _ . - ~_ _ If a sufficient number of replicate analyses are run, it is to be expected that the results would fall in normal Gaussian distribution. Standard statistics allow an estimate of the probability of any particular deviation from the mean value. It is common practice to report the mean i one or two standard deviations as the final result. In routine analysis such replication is not carried out, and it is not possible to report a Gaussian standard deviation 2 one or two Poisson standard deviations. The reported values are then considered to give some indication of the range in which the true value might be expected to occur. l l The simplest possible case to consider would be one where the background is negligible and the sample activity is zero. It is sometimes not realized that if a series of counts is taken 0 l O en sech e sxstem, heir ef the met veiees shouid.be iess thea zero. sesetive coents ere eet possible, of course. But when there is an appreciable background, the entire scale is raised. The resulting situation: half of the sample counts on a zero activity sample would be less than background. This negative net count occurs frequently in low-level measurements, causing considerable concern. Actually, such results are to be expected. .i Analytical detection limits are governed by a number of factors including:
- 1. Sample Size
- 2. Counting Efficiency The fundamental quality in the measurement of a radioactive substance is the number of disintegrations per unit time. As with most physical measurements in analytical chemistry, it is seldom possible to make an absolute measurement of the disintegration rate, but rather, it is necessary to compare the sample with one or more standards. The standards determine the counter efficiency which may then be used to convert 1
sample counts per minute (cpm) to disintegrations per minute (dpm).
- 3. Background Count Rate Any counter will show a certain counting rate without a sample in position.
This background counting rate comes from several sources: 1) natural environmental radiation from the surroundings, 2) cosmic radiation, and 3) the natural radioactivity in the counter material itself. The background
- j. counting rate will depend on the amounts of these types of radiation and sensitivity of the counter to the radiation.
l
- 4. Background and Sample Counting Time The amount of time devoted to the counting of the background depends on
! the level of activity being measured. In general, with low level samples, ! O this time should be about equal to that devoted to counting a sample.
1 1
- 3. Time Interval Between Sample Collection and Counting h Decay measurements are useful in identifying certain short-lived isotopes.
1 The disintegration constant is one of the basic characteristics of a specific l radionuclides and is readily determined,if the half-life is sufficiently short.
- 6. Chemical Recovery of the Analytical Procedures Most radiochemical analyses are carried out in such a way that losses occur during the separations. These losses occur due to a large number of contaminants that may be present and interfere during chemical separations. Thus it is necessary to include a technique for estimating these losses in the development of the analytical procedure.
The activities per unit sample mass or volume are determined using the following formula: E' C+B T2 A= C-B + 1.96 l (2.22) (V) (T) (R) (E) (e-Aat) (2.22) (V) (R) (E) (e-Aat) l WHERE: A= Activity as pCi per unit sample mass or volume. C= Sample counts. B= Background counts. V= Sample volume or mass analyzed. E= Counter efficiency in cpm /dpm. 2.22 = Numerical constant to comtert disintegrations per minute to picocuries. (e -Aa t) = Decay factor to correct the activity to time of collection. T= Counting time in minutes for sample and background. 1.96 = Statistical constant for the 95% confidence level. R= Chemical recovery or photon yield. O Q CCP uses the following method to determine lower limit of detection (LLD) as per NRC Regulatory Guide 4.1, Rev.1, " Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants", and the NRC Branch Technical Position, November 1979, "An Acceptable Radiological Environmental Monitoring Program". The LLD is defined, for purposes of this guide, as the smallest concentration of radioactive material in a sample that will yield a net count (above system background) that will be detected with 95% probability with only 5% probability of falsely concluding that a blank observation represents a "real" signal. For a particular measurement system (which may include radiochemical separation): LLD = 4.66 sb E V 2.22 Y exp ( A at) WiiERE: O LLD = "A priori" lower limit of detection as defined above (as pCi per unit mass or volume),
=
sb Standard deviation of the background counting rate or of the counting rate of a blank sample as appropriate (as counts per minute). E = Counting efficiency (as counts per disintegration). V = Sample size (in units of mass or volume). 2.22 = Number of disintegrations per minute per picocurie. Y = Fractional radiochemical yield (when applicable).
=
A Radioactive decay constant for the particular radioisotope, at = Elapsed time between sample collection (o.- end of the sample collection period) and time of counting. The value of sb used in the calculation of the LLD for a particular measurement system is based on the actual observed variance of the background counting rate, or, of the counting rate of the blank sample, (as appropriate), rather than on an unverified theoretically predicated variance. In calculating the LL D for a radionuclides determined by gamma-ray spectrometry, the background included the typical contributions of other nuclides normally present in the samples.
- - ii O -
l , SECTION 3.3 l RADIOLOGICAL ENVIRONMENTAL MONITORING SECOND QUARTER REPORT 1988 O
l l : UNION ELECTRIC COMPANY ST. LOUIS, MISSOURI CALLAWAY PLANT ONIT I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM L QUARTERLY REPORT FOR ! APRIL, MAY, AND JUNE 1988 i l l O SUeMiTTEo BY: CONTROLS FOR ENVIRONMENTAL POLLUTION,INC.
]
1925 ROSINA STREET SANTA FE, NEW MEXICO COPY NO. l i l l l 1 Prepared By: Bob Bates, Contract Mam ger Approved By: / ./ [arn6s J. Mueller, President i O_:-__-_____________._-__ _.__-_:_
CONTENTS Section Title Page Abstract 1 1.0 Introduction 2 2.0 Description of the Monitoring Program 3 1 3.0 Analytical Procedures - 4.0 Sample Preparation Method 3 1 5.0 Major Instrumentation 3 6.0 Isotopic Detection Limits and Activity ( Determinations 3 I l 7.0 Quality Control Program 4 8.0 Data Interpretations and Conclusions 4 Appendix A: 1988 EPA Cross-check Results 44 fq b 1 1 I i 1 O .
.g.
(h TABLES Number Title Page VII Gross Beta in Airborne Particulate 7 VIII Airborne Radiolodine 8 IX Thermoluminescent Dosimetry (Second Quarter 1988) 10 X Well Water - Radiochemical 16 XI Well Water - Gamma Spectrometry 17 XII Surface Water - Radiochemical 19 XIII Surface Water - Gamma Spectrometry 20 XIV Washload Sediment - Radiochemical 23 XV Washload Sediment - Gamma Spectrometry 24 XVI Bedload Sediment - Radiochemical -25 XVII Bedload Sediment - Gamma Spectrometry 26 XVIII Bottom Sediment - Radiochemical 27 XIX Bottom Sediment - Gamma Spectror try 28 XX Fish, CA-AQF-A - Radiochemical 30 XXI Fish, CA-AQF-A - Gamma Spectrometry 31 XXII Fish, CA-AQF-C - Radiochemical 32 XXI!! Fish, CA-AQF-C - Gamma Spectrometry 33 XXIV Fish, CA-AQF-D - Radiochemical 34 XXV Fish, CA-AQF-D - Gamma Spectrometry 35 XXVI Milk - Radic, chemical 37 XXVII Milk - Gamma Spectrometry 38 XXVIII Vegetation - Radiochemical 40 XXIX Vegetation - Gamma Spectrometry 43 O bv s
4.. O i
)
l I
O
~
abs 1,ect Controls for Environmental Pollution, Inc (CEP) has conducted a radiological environmental monitoring program (REMP) for Union Electric Company (UEC), Callaway Plant, Unit 1, since May 5,1983. This quarterly report presents data for the months of April, May, and 1; June 1938. - e Evaluation of radiation levels in the environs around Union Electric Company's Callaway i
]
Plant entailed sampling at strategic points in various exposure pathways. The following types of samples were collected and analyzed: milk, vegetation, surface water, well water, l bottorn sediment, bedload sediment, washload sediment, fish, airborne particulate, airborne radiciodine, and direct radiation (TLD). l ] Analytical results are presented and discussed along with other pertinent information. Possible trends and anomalous results, as interpreted by Controls for Environmental Pollution, Inc., are discussed. 5 O
l 1.0 Introduction $ This report presents an analysis of the resu!ts of the Radiological Environmental Monitoring Program (REMP) conducted during the second quarter of 1988 for Union Electric Company, Callaway Plant. 1 In compliance with federal and state regulations and in its concern to maintain the quality of the local environment UEC began its radiological monitoring program in j l April,1982. I l The objectives of the radiological environmental monitoring program are as follows: 1
!) to establish baseline radiation levels in the environs prior to reactor operations; 2) to monitor potential critical pathways of radioeffluent to man; 3) to determine l radiological impact on the environment caused by the operation of the Callaway Plant.
O l A number of techniques are being used to distinguish Callaway Plant effects from other sources during the operational phase, including application of established background levels. Operational radiation levels measured in the vicinity of the Callaway Plant are compared with the pre-operational measurements at each of the sampling locations. In addition, results cf the monitoring program help to evaluate sources of elevated levels of radiation during reactor operation in the environment, e.g., atmospheric fallout or abnormal plant releases. The Callaway Plant is located on a plateau approximately five miles north of the Missouri River in Callaway County, Missouri. The plant consists of one 1150 MWE pressurized water reactor, which achieved initial criticality on October 2,1984. O
2.0 Description of the Monitoring Program Union Electric Company has contracted with Controls for. Environmental Pollution, Inc. starting May 1983, to determir:e the radiation levels existing in and around the Callaway Plant area. A summary of the Callaway Plant Monitoring Program is contained in the first quarter report 1988 (page 3). No changes in the monitoring program occured during the second quarter,1988. 3.0 Analytical Procedures The analytical procedures routinely used by CEP to analyze samples are discussed in the First Quarter 1988 Report (pages 14 to 18). No new analytical methods were used this quarter. O 4.0 Sample Preparation Methods Sample preparation methods used by CEP. are discussed in the First Quarter 1988 Report (page 18). No new sample preparation methods were used this quarter. 5.0 Major Instrumentation Major analytical instrumentation used by CEP are discussed in the First Quarter 1988 i Report (pages 19 to 20). No new instrumentation was used for sample analysis this L quarter. ! 6.0 Isotopic Lower Limits of Detection and Activity Determinations A discussion of the calculations used in determining lower limits of detection and , activity by Controls for Environmental Pollution, Inc., is found in Appendix B, First Quarter 1988 Report.
Table 111 in the first quarter 1983 report gives the lower limits of detection for h radiochemical and chemical analytical methods. Table IV in the first quarter 1988 report gives the lower limits of detection for Gamma Spectrometry. The sample counting times and the aliquot size used for lower limit of detection calculations and actual analyses are shown in Tables V and VI, in the first quarter 1938 report. 7.0 Qtmlity Control Program A summary of CEP's Quality Control Program is contained in the First Quarter 1988 j I Report (page 26). No changes in the Quality Control Program occured this quarter. l O t 3.0 Data Interpretations and Conclusions This section addresses interpretations and conclusions regarding all types of samples I analyzed during this report period. Analysis and review of data incorporates various techniques from historical comparison to statisical evaluation. Results which do not compare with the historical range are recalculated for verification. If the recalculation verifies the original result, the sample is reanalyzed if possible (i.e. sufficient sample volume or Isotope half life). Once it is determined that the results obtained are accurate, a statistical analysis is made. Results which are outliers with respect to historical comparison of previous data are considered out of baseline range or anomolous and will be so noted in the report. O
.a i
l O 8.1 Airseree v er1: cerates end a a dieiediee l Airborne particulate samples were co!!ected at five (5) monitoring stations on a
.. weekly basis from April 7,1988, through June 30, 1988. The five airborne-I particulate stations were also collection sites for airborne radiciodine (see Table Vlll).
1 I
.j All of the air particulate samples were. analyzed for Gross Beta- activity. '
Gamma Spectrometry, Strontium-90.and Strontium-89 analyses were performed on quarterly composites from each station. The range of Gross Beta activity at each of the sampling locations follows. Collection Location Minimum (pCi/m3) Maximum (pCi/m3) Site A1 0.01510.002 0.02510.002 Site A7 0.01210.002 0.02810.002 Site A8 0.00910.002 0.02810.002
.! :e A9 0.01210.002 0.03010.002 Site B3 0.01210.002 0.03410.002 1
I Table VII, Gross Beta in Airborne Particulate, shows that the Gross Beta activity ranged from a minimum at Site A8 of 0.009 0.002 1 pC1/m3, collected 04/07/88-04/14/88 to a maximum of'0.03410.002 pCi/m3 at Site B3 during the collection period of 06/16/88-06/23/88. 1 The highest mean Gross Beta activity during the report period was observed at Site B3 with a mean activity of 0.02310.006 pCi/m3 .
)
O Mean weekly Gross Beta activities ranged from a low of 0.01410.004 pC1/m3 during the collection period of 04/07/88-04/14/88' to a high of 0.02910.003 _ _ _ - _ _ _ _ __ - - . - - J
pCi/m3 during the collection period of 06/16/38-06/23/33. The airborne particulate composite analyses for Strontium-39 and Strontium-90 were less than the lower limit of detection (0.002 pCi/m3) for all sites. Gamma spectralanalysis of the site composites indicated the following activities: Collection Location Isotope Identified pCi/m3 Site A1 Beryllium-7 0.1310.03 Site A7 Beryllium-7 0.0920.02 Site A8 Beryllium-7 0.1120.03 Site A9 Beryllium ~ 0.0810.02 Site B3 Beryllium-7 0.1010.02 No other gamma emitting isotopes of interest were detected in the quarterly g site composites. Results of the airborne radioiodine analyses may be found in Table VIII. No lodine-131 activity above the lower limit of detection (0.006 pCi/m3) was detected this quarter. I.evels and fluctuations of activity in the air particulate and radiciodine samples are consistent with the previously accumulated preoperational data. O
ya DM t d e 0 0 0 0 0 0 0 0 0 0 0 0 0
+ + + 1 3 0 3+ 3+ 0+ 3+ 2+ 4+ 9+ 3+ 1 l
6 4 1 k erh 1 1 2 1 2 2 2 2 2 2 2 2 2 eBat e d f 0 0 0 0 0 0 0 0 0 0 0 0 0 Wssot'an o 0 O 0 0 0 0 0 0 0 0 0 0 O rS G+- 2 2 2 2 2 2 2 2 2 2 2 2 2 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 t e + + + 1 4 2 3 1
+ + + + + + + + 13 2 5 5 3 6 1 4 4 3
+
i 1 1 2 2 2 2 2 1 2 2 2 3 2 2 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0
) 0 0 0 0 0 0 0 O 0 0 0 0 0 0 3 -
m
/i '
_ Cp 2 2 2 2 2 2' 2 2 2 2 2 2 2 6 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ ( 9' 0 0 0 0 0 0 0 0 0 0 0 0 0 0 S A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E e + 4 + 1 + + + + +6 +6 9+0 +7 1 + T t 2 3 9 6 2 4 4' 1 2 i 1 1 1 1 2 2 2 2 2 2 2 3 2 2 A S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 L U 0 0 0 0 0 0 O 0 0 0 0 0 0 0 R C I E T T 2 2 2 2 2 2 '2
~
R 2 2 2 2. 2 2 5 _ I R 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I V A A 3 0 0 0 0 0 0 0 0 0 0 0 0 0 0 P U 8 A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 E E 8 + + + 1 + + + + + Q e + + + 1 + OB _ L 9 8 9 0 7 5 3 0 5 3 2 3 4 _ N D 1 i t 1 0 2 1 2 2 2 2 2 2 2 2 2 1 1 2 A R S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 N _ T O O 0 0 0 0 0 0 0 0 0 O 0 0 0 0 B . L C - R I E ~ A S 2 2 2 2 2 2 2 2 2 2 2 2 2 4 N 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ I 7 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ A 0 0 0 0 0 0 0 +0 0 0 0 0 0 0 _ A e + + + 1 + + + + + + + 1 + T t 0 8 0 7 2 2 51 0 3 9 2 3 4 1 _ E i S 2 1 2 1 2 2 2 2 1 2 2 2 2 B 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ S 0 0 0 0 0 0 0 0 0 0 O 0 0 O _ S ' _ O R 2 2 2 2 2 2 2 2 2 2 2 2 2 3 G 0 0 0 0 0 0 0 0 0 0 0 0 0 0 I 0 0 0 0 0 0 0 0 0 0 0 0 0 0 A 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ e + + + 1 + + + + + + + + 1 + _ t 3 3 1 3 72 9 0 2 5 9 0 2 51 7 1 0 i 1 1 1 2 2 2 2 2 1 2 S 0 0 0 0 0 0 0 0 0 0 0 0 0 0 _ 0 0 0 0 0 0 0 0 0 0 0 0 0 0 y t i i v 8 8 3 8 8 8 8 8 3 8 8 8 8 t d 8 8 3 8 8 8 3 3 8 8 8 3 8 cn i o r
// / / /////////
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h 8.2 Thermoluminescent Dosimetry - Thermo!uminescent Dosimeters (TLD's) were employed to determine direct radiation levels in and around the Callaway Site. Panasonic model UD-814 TLD's sealed in plastic bags were placed in polypropylene mesh cylindrical holders at 52 locations and exchanged quarterly. Data appearing in Table IX are the result of reading and averaging the CaSO4 :Tm elements. Net exposures were obtained by normalizing the total exposure to a 90 day quarter (standard quarter). Exposure level; for all monitoring locations during the second quarter 1988 are consistent with background levels observed during previous quarters. O I l 0 9
1 i TABLE IX THERMOLUMINESCENT DOSIMETRY SECOND QUARTER 1988 l
. Net - I Field- Total Exposure )
l Station Time' Exposure (mrem /Std i Identification pays) (mrem 128 )! Qtr i 2 )8 Collection Location C A-IDM-1 11 M! NW, City Limits of Fulton on Hwy Z, 0.8 Mi East of Business 54 84.0 18 4 16 5 19.7 20 6 C A-ID M-2 6.6 Mi NW, County Road 111,0.6 Mi South of . Hwy UU, Callaway Electric Cooperative . 6 Utility Pole No.17571 84.0 17.0 15- 3 18.2 17 3 C A-ID M-3 1.3 Mi NW,0.1 Mi West of Hwy CC on gravel Road 0.8 Mi South Hwy 0, Callaway Electric Cooperative Utility Pole No.18559 84.0 19.8 18 5 21.2 22 7 i C A-ID M-4 1.9 M1 N,0.3 Mi East of the O and CC Junction, Callaway Electric Cooperative Utility Pole No. I8892 84.0 18.5 + 7.6 19.8 32 8 C A-ID M-5 1.3 Mi ENE, Primary Meteorological Tower 54.1 9.8 10' 2 16.2 24 3 O C A-ID M-6 2.0 Mi W, County Road 428,1.2 MI West of Hwy CC, Callaway Electric Cooperative l Utility Pole No.18609 84.8 19.0 36 3 20.2 + 3.8 C A-IDM-7 1.3 Mi S, County Road 459,2.6 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35097 84.0 18.7 1 6.7 20.1 11 7 C A-ID M-8 2.9 Mi S, County Road 459,1.4 Mi North of ; Hwy 94, Callaway Electric Cooperative Utility Pole No. 06823 84.0 19.9 34 6 21.3 39 6 l C A-ID M-9 3.7 Mi S, NW Side of the County Road 459 and 94 Junction, Callaway Electric Cooperative Utility Pole No. 06754 84.0 21.5 35 9 23.1 3 10.2 CA-IDM-10 4.0 Mi SSE, Hwy 94,1.8 M1 East of County Road 459, Callaway Electric Cooperative Utility Pole No.12182 84.0 10 18.8 5 20.1 13 5 C A-ID M-11 4.8 Mi SE, City of Portland, Callaway Electric : Cooperative Utility Pole No.12112 84.0 22.7 31 24.3 C 37 8 9; 1 1 E--__-------_- - - - - - _ - - . _ - - - - - - - - .
i 1
- I i
TABLE IX (Cont.)- h THERMOLUMINESCENT DOSIMETRY SECOND QUARTER 1988 Net j Field Total Exposure Station Time Exposure (mrem /Std Identification Collection Location (Days) (mrem i 2a) Qtr i 20) CA-IDM-12 5.3 Mi SE, Hwy 94,0.6 Mi South of Hwy D, . Utility Pole on East Side of Hwy 84.0 20.4 238 21.9 19 8 CA-IDM-13 5.6 Mi ESE, Hwy 94,0.75 Mi East of Hwy D, Kingdom Telephone Pole No. 2X1 84.0 21.7 12 23.2 8 18 8 C A-IDM-14 5.0 Mi ESE, SE Side of Intersection D and 94, Callaway Electric Cooperative Utility Pole No. I1940 84.0 21.2 286 22.7 13 7 C A-IDM-15 4.2 Mi ESE, Hwy D,2.5 MI North of Hwy 94, Callaway Electric Cooperative Utility Pole No.27379 84.0 20.3 285 21.7 12 6 CA-IDM-16 O 4.1 Mi ENE, Hwy D,3.6 MI North of Hwy 94, Callaway Electric Cooperative Utility Pole No. I2976 84.0 18.4 10 7 19.7 15 7 C A-IDM-17 4.0 Mi E, County Road 4053, 0.3 Mi East of Hwy 94, Kingdom Telephone Company Pole No.3X12 84.0 17.5 192 18.7 2 3.1 , i C A-IDM-18 3.8 Mi ENE, Hwy D,0.4 Mi South of Hwy O, , Callaway Electric Cooperative Utility Pole ! No.12952 84.0 19.8 5.6 21.2 20 6 CA-IDM-19 4.2 Mi NE, Hwy D,0.3 Mi North of Hwy 0, Callaway Electric Cooperative Utility Pole No.12918 84.0 19.0 15 5 20.4 195 1 CA-IDM-20 4.8 Mi NE, City of Readsville, Callaway Electric Cooperative Utility Pole No.12830 84.0 19.3 18 20.6 4 12 5
]
CA-IDM-21 4.0 Mi NNE, County Road 155,1.9 Mi North of Hwy O, Callaway Electric Cooperative Utility Pole No.19100 . 84.0 20.5 25 7 21.9 i 8.1 C A-ID M-22 2.5 M1 NNE, County Road 150, 0.5 Mi North of Hwy 0, Callaway Electric Cooperative Utility Pole No.19002 84.0 18.7 + 4.6 20.0 + 4.9 L _ - _ _ _ _ _ - - - _ _ - _ - - _ _ _ _ - - _ = _ _ - _ _ - _ - _ _ _ - _ _ - _ _ _ _ _ _ \. , TABLE IX (Cont.) THERMOLUMINESCENT DOSIMETRY h SECOND QUARTER 1988 Net Field Total Exposure Statto.) Time Exposure (mrem /Std Identification Collection Location (Days) (mrem 1 2 0) - Qtr't 20) C A-ID M-23 6.7 Mi NNE, City of Yucation, Callaway Electric Cooperative Utility Pole No.12670 84.0 19.2 + 4.3 20.6 + 4.6 C A-ID M-24 7.0 M1 NE, County Road 191,2.1 M1 North of Hwy K, Callaway Electric Cooperative Utility Pole No.12498 84.0 16.1 +5.8 17.3 + 6.2 - CA-IDM-25 8.7 Mi E, County Road 289,0.3 Mi South of County Road 287, Callaway Electric Cooperative Utility Pole No.11295 84.0 18.1 1 4.3 19.4 164 C A-ID M-26 12.1 Mi E, Town of Americus, Callaway Electric Cooperative Utility Pole No.11159 _ 84.0 13.0 + 4.8 14.0 + 5.2 CA-IDM-27 9.5 M1 ESE, Town of Bluff ton, Callaway Electric Cooperative Utility Pole No.11496 84.0 19.7 + 6.2 21.1 + 6.7 g. CA-IDM-28 3.3 Mi SE, :ounty Road 469,2.0 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06896 83.1 20.5 + 7.1 22.2 + 7.7 CA-IDM-29 2.7 Mi SSW, County Road 448,1.2 Mi North of County Road 459, Callaway Electric Cooperative Utility Pole No. 06851 84.0 15.4 134 16.5 164 C A-ID M-30 4.6 Mi SSW, W Side.of County Road 447 and 463 Junction, Kingdom Telephone Company Pole No. 2K1 84.0 18.4 2 5.4 19.7 185 i C A-ID M-31 7.6 Mi SW, City of Mokane, Callaway Electric Cooperative Utillty Pole No. 06039 84.0 18.2 126 19.4 176 CA-IDM-32 5.4 M1 WSW, Hwy VV,0.6 Mi West of County Road 447, Callaway Electric Cooperative Utility Pole No. 27031 84.0 18.7 106 20.1 146 CA-ID M-33 7.3 Mi W, City of Hams Prairie, SE of Hwy C and AD Junction 84.1 18.1 + 4.9 19.445.3 CA-IDM-34 9.7 Mi WNW, NE Side of Hwy C and County Road 408 Junction 84.1 19.6 105 21.0 143 > j' TABLE IX (Cont.) O r"ca=o'U=r"esce"r oos>=erav SECOND QUARTER 1988 Net e Field Total Exposure Station Time Exposure (mrem /Std Identification Collection Location (Days) (mrem i 28) Otr i 28) CA-ID M-35 5.8 MI NNW, City of Toledo, Callaway Electric Cooperative Utility Pole No.17684 84.0 18.1 14-5 19.3.15 8 CA-IDM-36 5.2 Mi N, County Road 155,0.8 Mi South of , County Road 132, Callaway Electric Cooperative Utility Pole No.19137 84.0 18.4 308 19.7 1 8.5 C A-ID M-37 0.7 Mi SSW, County Road 459,0.9 M1 South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35077 84.1 18.0 173 19.3 2 _4.0 CA-IDM-38 4.8 Mi NNW, County Road 133,1.5 Mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No. 34708 84.0 i 15.8 284 17.0 215 l O(> C A-ID M-39 5.4 Mi NW, County Road 112,0.7 Mi E2st of County Road 111, Callaway Electr!c 1 Cooperative Utility Pole No.17516 84.0 18.3 256 19.6 237 CA-ID M-40 4.2 M1 WNW, NE Side of County Road 112 and I Hwy O, Callaway Electric Cooperative Utility Pole No. 06326 84.0 19.6 + 6.7 21.0 + 7.1 C A-IDM-41 4.8 Mi W, Hwy AD,2.8 Mi East of Hwy C, Callaway Electric Cooperative Utility Pole No.18239 84.1 20.0 15 7 21.4 21 8 CA-IDM-42 4.4 Mi SW, County Road 447,2.6 Mi North of County Road 463, Callaway Electric ; Cooperative Utility Pole No. 06326 84.0 15.9 + 5.1 17.0 + 5.5 ! C A-ID M-43 0.5 Mi SW, County Road 439,0.7 Mi South of i Hwy CC, Callaway Electric Cooperative Utility Pole No. 35073 84.0 !d.5 + 4.9 19.9 + 5.2 I C A-ID M-44 1.7 Mi WSW, Hwy CC,1.0 Mi South of County i Road 439, Callaway Electric Cooperative Utility Pole No.18769 84.0 16.9 11 4 18.1 144 CA-IDM-45 1.0 Mi WNW, County Road 428,0.1 Mi West O or "~r cc ceiiewer rectric Utility Pole No.18580 e cooeeretive 85.0 18.7 28 4 19.8 215
-- )
TABLE IX (Cont.)
- THERMOLUMINESCENT DOSIMETRY ;
i SECOND QUARTER 1988 Net , Field Total Exposure f Station Time Exposure (mrem /Std Identification Collection Location (Days) - (mrem 120)- Qtr i 20) C A-ID M-46 1.5 Mi NNW, NE Side of Hwy CC and County I Road 466 Intersection, Callaway Electric Cooperative Utility Pole No. 28242 84.0 20.0 175 21.4 116 C A-ID M-47 0.9 Mi NNE, County Road 448,0.9 Mi South of Hwy O, Callaway Electric Cooperative Utility Pole No. 28151 84.0- 17.5 22 6 18.7 166 C A-ID M-48 0.4 Mi NE, County Road 448,1
- Mi South of Hwy 0, Plant Security Sign Post 84.1 20.9 1 10.7 22.3 1 11.4
)
C A-ID M-49 1.7 M1 E, County Road 448, Callaway Electric ! Cooperative Utility Pole No. 06959, Reform Wildlife Management Parking Area 84.0 16.4 + 3.0 -- 17.6 + 3.2 ) O C A-IDM-50 0.9 Mi SSE, County Road 459,3.3 Mi North ! of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35086 l 84.0 17.7 19 3 18.9 114 C A-IDM-51 0.7 Mi SE, Located in the "Y" of the Railroad Spur, NW of Studge Lagoon 83.7 17.8 165 19.2 106 CA-IDM-52 0.4 Mi ESE, Light Pele near the East Plant Security Fence 83.7 17.7 11 3 19.0 133 t. I i O; i 3.3 Well Water Well water samples were collected monthly from three locations and analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-89, Strontium-90, and gamma-emitting nuclides. Table X presents the results of the radiochemical analyses. Gross Alpha activity l ranged from less than 2.0 pCi/l to 3.1 11.0 pCi/1. Cross Beta levels varied from 1 3.81 0.7 pCl/l to 9.6 1 0.7 pCi/1. The Gross Alpha and Cross Beta levels were j consistent with the preoperational data. , I Results for Tritium analysis were below the lower limit of detection (500 pCi/1) for all samples. 1 O All sample results for Strontium 89 and Strontium 90 analysis were below the i
)
i lower limits of detection (1.5 pCi/l and 1.0 pCi/l respectively). j Gamma spectrometry showed no detectable levels of isotopes of interest. Results are summarized in Table XI.
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1 8.4 Surface Water Surface water samples were collected from threc locations en a monthly basis. Samples were analyzed for Gross Alpha, Cross Beta, Tritium, Strontium-90, s Strontium-39, and by Gamma Spectrometry. Results are summarized in Tables XII and XIII. Gross Alpha and Cross Beta analyses of surface water samples showed a range of activities from less than 2.0 pCi/l to 5.1 2 13 pCi/l and 3.9 20.7 pCi/l to 12.0 10.S pCi/1, respectively. The positive Gross Alpha and Gross Beta activities can be attributed to naturally occurring isotopes, such as Potassium-40, and are consistent with the preoperational data. All Tritium data from surface water samples were below the lower limit of detection (500 pCi/1). No Strontlum-89 or Strontium-90 was detected in any of the surface water samples collected this quarter. l Gamma Spectralanalysis of surface water samples showed no detectable activity J from isotopes of interest. I O r - t S 0 9 m . i u 0 0 0 0 0 0 0 0 0 t l l 1 l l l l l l n < < : < < < < < <
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l O 85 sedimeet l Washload, Bedload and Bottom Sediment samples were collected in May from three locations along the Missouri River. Samples were analyzed for Gross I Alpha, Gross Beta, Strontium-90, Strontium-89, and by Gamma Spectrometry. J I Results are summarized in Tables XIV thru XIX. l I W l The following ranges of Gross Alpha and Gross Beta activities were observed in the washload, bedload and bottom sediments. f J Gross Alpha Cross Beta Range Range Sample Type pCi/g pC1/g Washfoad 6.81.0-10.91.8 1 2 9.30.7-17.61.7 1 2 Bedload 3.00.4-7.71.3 1 1 2.40.2-9.91.1 1 1 Dottom 0.3_+ 0.1 - 1.4_+0.2 0.4_+0.1 - 1.3_+0.1 1 q l The highest activity of Gross Alpha (10.9 11.8 pCl/g) was seen in the Washload sediment at sample location D (59.5 river miles downstream of discharge south bank). The highest activity cf Gross Beta (17.611.7 pCi/g) was seen in the l Washload sediment at sample location D (59.5 river miles downstream of discharge south bank). No Strontium-89 or Strontium-90 was detected in the washload, bedload, or bottom sediments collected during the second quarter of 1988. Gamma Spectralanalysis of the sediment samples collected during this report period are detailed in Tables XV, XVII and XIX, and are consistent with previous data. (
One shoreline sediment sample was collected on 05/18/88 and exhibited a Cross Alpha activity of 1.3 10.2 pCi/g, and a Cross Beta activity of 1.1 20.1 pCi/g. l Gamma Spectralanalysis indicated no activity of interest and no Strontium-89 or l Strontium-90 activity was detected. I I i k l O l I O h TABLE XIV WASHLOAD SEDIMENT Sample Collection Radiochemical Analysis pCi/g (dry) Identification Date Gross Alpha Gross Beta Strontium-90 Strontium-89 C A- A QS- A 05/18/88 6.8 + 1.0 9. 3 + 0.7 <0.20 <0.30 C A-A QS-C 05/18/88 7.7+1.2 9.9 + 0.8 <0.20 < 0.30 CA-AQS-D 05/19/38 10.911.8 17.621.7 < 0.20 <0.30 NOTE: Quantity not sufficient to reanalyze washload samples. O O
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O rABte xvi BEDLOAD SEDIMENT - Sample Collection . Radiochemical Analysis pCi/g (dry) Identification Date Gross Alpha Cross Beta Strontium-90 Strontium-89 CA-AQS-A 05/18/88 4.00.8 1 i ,0. 7 ' < 0.20 < 0.30
' C A- AQS-C .05/18/88 7.71.3 2 :. <0.20 <0.30 CA-AQS-D 05/19/88 3.00.4 1 2. 6 . . < 0.20 <0.30 NOTE: Quantity not sufficient to verify values by reanalysis.
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1 O u Fish ; Fish were collected during . the quarter from ' three locations. Types ' of :- fish collected 'during this quarter were: . freshwater drum, paddlefish, carp,. smallmouth buffalo, shortnose gar, bigmouth buffalo, river carpsucker, channel catfish, blue catfish and gizzard shad. Gross Alpha, Gross Beta, . Strontium-90, Strontium-89 and Gamma Spectralanalysis were performed on all fish collected ' each month. Results are presented in Tables XX thru XXV. The activity levels-
'i are consistent with the preoperational data. j Gross Alpha activity during this quarter ranged from. less than 0.3 pCi/g to 0.710.1 pCi/g. Gross Beta activities ranged from a low of 3.510.1 pCi/g (sample CA-AQF-D, freshwater drum collected 06/23/88) to a high of 10.5 10.2 pC1/g (sample CA-AQF-A, gizzard-shad collected 04/18/88). . ' Gross Alpha and Gross O Beta activities seen in fish samples can be attributed to naturally occurring
[ isotopes (e.g. Potassium-40). All fish data for Strontium-90 and Strontium-89 were below the lower limits of detection of 0.20 pCi/g and 0.30 pCi/g, respectively. l 1 Results of Gamma Spectralanalysis may be found in Tables XXI, XXIII, and XXV. i
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8.7 Milk Milk samples were collected from two locations, the Green Farm and the Schneider Farm. The Green Farm supplies cow's milk while the Schneider Farm provides both cow's milk and goat's milk. Analyses for lodine-131, elemental Calcium, Strontium-90, Strontium-89 and Gamma-emitting isotopes were performed on all milk samples. Tables XXVI and XXVII present results of these analyses. No Iodine-131 above the lower limit of detection (0.5 pCi/l) was detected in the milk samples during this period. No milk samples cellected during the second quarter were above the lower limit of detection of 2.0 pCi/l for Strontium-89 and 1.0 pCi/l for Strontium-90. O No gamma-emitting isotopes of interest were detected in any of the milk samples. 9
O 148tE xxyl FRESH MILK l l Radiochemical Collection Iodine-131 Calcium Strontium-90 Strontium-89 Date pC1/1 mrff pCi/l pCi/l Green Farm (M-1) 04/12/88 < 0. 5 1010 < l .0 < 2.0 04/26/88 < 0. 5 1080 < l .0 < 2.0 05/10/88 < 0. 5 1290 < l .0 < 2.0 05/24/88 < 0.5 1480 < l.0 < 2.0 06/14/88 < 0.5 1350 < l.0 < 2.0 06/27/88 < 0.5 1080 < l.0 < 2.0 Schneider Farm (MSA) 04/10/88 < 0.5 940 < l.0 < 2.0 0 04/ w 88 < 0.5 840 < i.0 < 2.0 05/08/88 < 0.5 1080 < l.0 < 2.0 ' 05/22/88 < 0.5 920 < l.0 < 2.0 06/12/88 < 0.5 760 < l.0 < 2.0 06/26/88 < 0.5 850 < !.0 < 2.0 Schneider Farm (M5B) 04/09/88 < 0.5 1200 < l .0 < 2.0 04/24/88 < 0.5 970 < l .0 < 2.0 05/08/88 < 0.5 1240 < 1.0 < 2.0 05/21/88 < 0.5 1300 < l.0 < 2.0 06/12/88 < 0.5 1170 < l .0 < 2.0 06/25/88 < 0.5 1050 < l .0 < 2.0 0 0 4 1 a' * * * * * * * * * * * * * * * * *
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O- 8.8 Vegetation Vegetation samples were collected from three (3) sampling locations during the second quarter of 1988. Vegetation samples consisted of spinach, lettuce, mustard greens, turnip greens and cabbage collected from the Beazley, Becker and Meehan Farms. All vegetation samples were analyzed for Gross Alpha, Gross Beta, Iodine-131 and by Gamma Spectrometry. Results are presented in Tables XXVill and XXIX. All Gross Alpha activity was less than the lower limit of detection (0.3 pCl/g). This Gross Alpha activity is consistent with the levels found during monitoring in previous years. Gross Beta activity observed in the vegetation samples ranged from 5.910.1 pC1/g to 24.910.3 pCi/g. No gamma emitting nuc!! des of interest were detected in the vegetation samples collected during the second quarter of 1988. l l \ O-l
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m I 1 TABLE XXVIII VEGETATION g 1 1 Sample Identification; Sample Radiochemical Analysis (pCi/g) ! Date Collected Location Gross Alpha Cross Beta Iodine-131 l I C A-F P L-V 3 Lettuce 05/31/88 Beazley Farm < 0. 3 11.6 2 0.2 < 0.03 l C A-FPL-V 3 I Spinach l 05/31/88 Beazley Farm < 0. 3 22.4 + 0.3 < 0.03 ! CA-FPL-V3 Mustard Greens 05/31/88 Beazle~y Farm < 0.3 12.3 120 < 0.03 C A-FPL-V 3 Turnip Greens 05/31/38 Beasley Farm < 0.3 11.7 + 0.2 < 0.03 C A-FPL-V 3 Cabbage 06/28/38 Beazley Farm < 0. 3 13.0 2 0.2 < 0.03 g C A - FPL-V3 Spinach j 06/23/88 Beazley Farm < 0.3 < 0.03 15.9 1 0.2 C A - F PL-V 3 Mustard Greens 06/23/3S Beazley Farm < 0.3 < 0.03 S.9 1 0.2 C A -F PL-V 3 Lettuce 06/28/83 Beazley Farm < 0. 3 < 0.03 11.1 1 0.2 l C A-FPL-V6 Lettuce 1 05/31/SS Becker Farm < 0. 3 < 0.03 16.7 1 0.2 j C A -FPL-V6 Spinach 05/31/33 Becker Farm < 0. 3 < 0.03 21.5 1 0.3 C A-FPL-V6 Cabbage 05/31/S8 Becker Farm < 0. 3 < 0.03 5.9 2 0.1 9
TABLE XXVIII(Cont.) O L aer^rio" Sample identification; Sample Radiochemical Analysis (pCi/g) Date Collected Location Gross Alpha Gross Beta Iodine-131 ._ CA-FPL-V6 Mustard Greens 05/31/88 Becker Farm < 0.3 9.2 22 0 < 0.03 CA-FPL-V6 Turnip Greens 05/31/88 Becker Farm < 0.3 8.4 12 0 < 0.03 CA-FPL-V6 Mustard Greens 06/28/88 Becker Farm < 0.3 14.3 12 0 <0.03 CA-FPL-V6 Turnip Greens - 06/28/88 Becker Farm < 0.3 6.4 120 <0.03 CA-FPL-V6 Cabbage 06/28/88 Becker Farm < 0.3 9.1 220 < 0.03 CA-FPL-V6 Lettuce 06/28/88 Becker Farm < 0.3 9.9 1 0.2 < 0.03 CA-FPL-V7 L ettuce 05/3I/88 Meehan Farm <0.3 7.8 120 < 0.03 C A-FPL-V7 Spinach 05/31/88 Meehan Farm < 0. 3 24.9 13 0 <0.03 C A-FPL-V 7 Cabbage 05/31/S8 Meehan Farm < 0.3 12.6 12 0 < 0.03 CA-FPL-V7 l Mustard Greens 05/31/88 Meehan Farm < 0.3 6.2 1 12 0 < 0.03 1 C A-FPL-V 7 Turnip Greens 05/31/88 Meehan Farm < 0.3 12.9 120 < 0.03 0
<a TABLE XXVIII (Cont.) ,
VEGETATION h j Sample Identification' Sample Radiochemical Analysis (pCi/g)- I Date Collected Location Gross Alpha Gross Beta -Iodine-131 CA-FPL-V7 Spinach- ) 06/28/88i Meehan Farm < 0.3 19.0 0.3 0.03 CA-FPL-V7 Turnip Greens 06/28/88 Meehan Farm < 0.3 - ' 7.9 1.0.2 < 0.03 CA-FPL-V7 Cabbage '- 06/27/88 Meehan Farm < 0.3 12.7 12 0 < 0.03
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1 l l O l I i I l l APPENDIX A EPA CROSS-CHECK RESULTS l 1988 l l 1 0
O ce^ caoss-c"ecx enoGa^= 1988 Radionuclides in Air Filters EPA CEP Known Value Reported Value Date Parameter pCl/ filter i 10 pCl/ filter i 2 a 3/88 Gross Alpha 20 1 5 23 1 1 26 1 1 28 1 1 Gross Beta 50 + 5
~
46+2 51 -1 2 54 2 2 Strontium-90* 17 + 1.5 13 + 2 14 + 2 15 ~ 2 O cesiem-137 16 1 5 19 1 7 22 1 7 24 1 7
- Review of raw data indicated initial miscalculation (parent recovery value not factored) and activities of 17,19, and 17 dr = 17.7) should have been reported.
O
i 1 EPA CROSS-CHECK PROGRAM 1988 1 Gross Alpha and Cross Beta in Water I EPA. 'CEP Known Value Reported Value Date Parameter pCi/li 1 a pCi/li 2 a 1/88 Gross Alpha 42 ~5 512 6 + 2.- I 6~2 Gross Beta' 8+5 30 + 2 !
~ ~
l 32 1 2 - 34 2 2 3/88 Gross Alpha 6+5 5+2
~
5~ 6+2 12 hI ' Gross Beta 13 + 5 ~ 14 + 2.
. 1572 17_!2 5/88 Gross Alpha l1 2 5 822 11 + 2 12_I2 Gross Beta 11 + 5 14 + 2 1672 j 1872 _
7/88 Gross Alpha 15 + 3 8+2 9+2~ 10_+ 2 Gross Beta 4+3- 8+2 872 8_I2
- Reanalysis obtained values of 14,15,15 (E = !$). Initial values were the result of QA glassware having beta contamination.
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EPA CROSS-CHECK PROGRAM O 1988 Gamma in Water EPA CEP Known Value Reported Value Date Parameter pCi/li I O pCi/li 2 0 1 2/88 Cobalt-60 56 + 5 69 2 5 6215 68 1 5 Zinc-65 94 + 9.4 81 + 6 86 + 6 91 1 ~6 Ruthenium-106 105 + 10.5 88+5 96 1 5 104 1 5 Cesium-134* 64 + 5 47 + 5 O
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"E' 59 1 3 Cesium-137 94 1 5 77 1 5 89 2 5 92 1 5 6/8s Chromium-51 *
- 302 2 30 210 1 15 220 1 15 240 1 15 Cobalt-60 15 + 5 8 + 15 11 + 15 13315 Zinc-65 * *
- 101 + 10 119 + 15 123 + 15 ~
127 2 15 Ruthenium-106 195 + 20 146 + 15 153 + 15 176[15
- Values of 58, 58, and 61 (T = 59) should have been reported. Unitial values reported before analysis was complete.)
O **Mean of all Chromium-51 analyses was 257 1 15. Omproper computation of original mean.)
* *
- Reanalysis indicated a value of 98 + 15 for Zinc-65.
~ (No reason found for original high results.)
EPA CROSS-CIIECK PROGRAM 1988 i i Gamma in Water (Cont.) EPA CEP Known Value Reported Value Date Parameter pCi/111 a pCi/112 o I Cesium-134 20 1 3 20 2 15 26 15 27 1 15 Cesium-137 25 + 5 19 + 15 26 + 15 27 1- 15 O 1 1 0 O ePn Caoss cneCx PaoCanu 1988 l Tritium in Water EPA CEP Known Value Reported Value Date Parameter pCi/li i n pCi/li 2 g l 2/88 Tritium 3327 2 362 2760 2 300 2994 2 300 3062 3 300 6/88 Tritium 5565 1 557 4800 1 500 5000 1 500 5200 1 500 0 0 EPA CROSS-CHECK PROGRAM 1988 Strontium in Water EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCl/li 2a 1/88 Stront:um-89 30 1 5 30 1 5 35 2 3 40 1 5 Strontium-90* 15 + 2 9+2 11 + 2 1112 5/88 Strontium-39 20 1 5 20 1 3 21 + 3 2223 h
. Strontium-90 20 + 2 18 + 2 19 + 2 20 1- 2
- Review of calculations indicated that values of 15,14, and 18 (Y = 16) should have been reported. (Original results were result of miscalculation.)
O l
EPA CROSS-CHECK PROGRAM 1988 Iodine-131 in Water i EPA CEP Known Value Reported Value ! Date Parameter pCi/111 a pCi/li 2 o
)
4/88 Low Level 7.50 + 0.75 6+4 l 9+4 ! 9_I4 8/88 High Level 76 + 8 76 + 8 81 + 8 85 1- 8 O o 0
EPA CROSS-CHECK PROGRAM l 1988 lodine-131 in Milk EPA CEP Date Parameter /1 Ia pCi/ 12 2/38 Low Level 4.0 1 0.4 3.0 + 7 4.0 + 0.7 O O
y I 1 G
.V EPA CROSS-CHECK PROGRAM 1988 Radionuclides in Food q
EPA CEP-Known Value Reported Value Date Parameter pCi/kg i i o pCi/kg i 2 n 1/88 Strontium-89 46 2 5 Not Reported Strontium-90 55 1 3 Not Reported lodine-131 102 2 10 101 2 25 -) 107 + 25 111 1 ~ 25 . Cesium-137 9145 81 + 10 91710 98710 O Potassium 1230 1 62 mg/kg 1320 1 132 mg/kg
.1320 1132 mg/kg l 1320 1 132 mg/kg -
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l 1 l 1 i i i 1 I i O j j i I
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.1 4
1 i 1 i I l SECTIO,N 3.4 RADIOLOGICAL ENVIRONMENTAL MONITORING THIRD QUARTER REPORT 1988' l 1 l l
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O UNION ELECTRIC COMPANY ST. LOUIS, MISSOURI CALLAWAY PLANT UNIT I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM QUARTERLY REPORT FOR JULY, AUGUST, AND SEPTEMBER 1988 SUBMITTED BY: CONTROLS FOR ENVIRONMENTAL POLLUTION,INC. 1925 ROSINA STREET SANTA FE, NEW MEXICO COPY No. 11 Prepared By: bdl Bob Bates, Contract Manager O ^eerovea Br: f/M/A
/ Jafhes J. Mueller, President
n. U CONTENTS Section Title Page Abstract I
!.0 Introduction 2 2.0 Description of the Monitoring Program 3 3.0 Analytical Procedures 3 4.0 Sample Preparation Method 3 5.0 Major Instrumentation 3 6.0 Isotopic Detection Limits and Activity Determinations 3 7.0 Quality Control Program 4 8.0 Data Interpretations and Conclusions 4 f- Appendix A: 1988 EPA Cross-check Results 42
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TABLES Number Title Page VII Gross Beta in Airborne Particulate 7 VI!! Airborne Radiolodine 8 IX Thermoluminescent Dosimetry (Third Quarter 1938) 10 X Well Water - Radiochemical 16 XI Well Water - Gamma Spectrometry 17 XII Surface Water - Radiochemical 19 XI!! Surface Water - Gamma Spectrometry 20 XIV Washload Sediment - Radiochemical 22 XV Washload Sediment - Gamma Spectrometry 23 XVI Bedioad Sediment - Radiochemical 24 XVII Bedload Sediment - Gamma Spectrometry 25 XVI!! Bottom Sedirnent - Radiochemical 26 XIX Bottom Sediment - Gamma Spectrometry 27 XX Fish, C A-AQF-A - Radiochemical 29 XXI Fish, CA-AQF-A - Gamma Spectrometry 30 XXII Fish, CA-AQF-C - Radiochemical 31 XXIII Fish, CA-AQF-C - Gamma Spectrometry 32 XXIV Fish, CA-AQF-D - Radiochemical 33 XXV Fish, CA-AQF-D - Gamma Spectrometry 34 X XVI Milk - Radiochemical 36 X X Vil Milk - Gamma Spectrometry 37 XXVill Vegetation - Radiochemical 39 XXIX Vegetation - Gamma Spectrometry 41 O --
t O ^8 t< ci Controls for Environmental Pollution, Inc (CEP) has conducted a radiological environmental monitoring program (REMP) for Union Electric Company (UEC), Callaway Plant, Unit 1, since May 5,1983. This quarterly report presents data for the months of July, August, and
)
I September 1988. l l 1 l l Evaluation of radiation levels in the environs around Union Electric Company's Callaway
]
Plant entailed sampling at strategic points in various exposure pathways. The following types of samples were collected and analyzed: milk, vegetation, surface water, well water, j bottom sediment, bedload sediment, washload sediment, fish, airborne particulate, airborne radioiodine, and direct radiation (TLD). l l l Analytical results are presented and discussed along with other pertinent information. I Possible trends and anomalous results, as interpreted by Controls for Environmental I Pollution, Inc., are discussed. t l l l _ ._ .-..-___D
1 l i 1.0 Introduction h This report presents an analysis of the results of the Radiological Environmental Monitoring Program (REMP) conducted during the third quarter of 1988 for Union Electric Company, Callaway Plant. In compliance with federal and state regulations and in its concern to maintain the quality of the local environment UEC began its radiological monitoring program in A pril,1982. The objectives of the radiological environmental monitoring program are as follows:
- 1) to establish baseline radiation levels in the environs prior to reactor operations; 2) to monitor potential critical pathways of radioeffluent to man; 3) to determine radiologicalimpact on the environment caused by the operation of the Callaway Plant.
O A number of techniques are being used to distinguish Callaway Plant effects from other sources during the operational phase, including application of established background levels. Operational radiation levels measured in the vicinity of the Callaway Plant are compared with the pre-operational measurements at each of the sampling locations. In addition, results of the monitoring program help to evaluate sources of elevated levels of radiation during reactor operation in the environment, l l e.g., atmospheric fallout or abnormal plant releases. I l The Callaway Plant is located on a plateau approximately five miles north of the : Missouri River in Callaway County, Missouri. The plant consists of one 1150 MWE I press rized water reactor, which achieved initial criticality on October 2,1984 l
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2.0 Description of the Monitoring Program 1 Union Electric Company has contracted.with Controls for Environmental Pollution, Inc. starting May 1983, to determine the radiation levels existing in and around the Callaway Plant area. A summary of the Callaway Plant Monitoring Program is contained in the first quarter report 1988 (page 3). No changes in the monitoring program occured during the third quarter,1988. 3.0 Analytical Procedures The analytical procedures routinely used by CEP to analyze samples are discussed in the First Quarter 1988 Report (pages 14 to 18). No new analytical methods were used this quarter. O 4.0 Sample Preparation Methods Sample preparation methods used by CEP are discussed in the First Quarter 1988 Report (page 18). No new sample preparation methods were used this quarter. 5.0 Major Instrumentation Major analytical instrumentation used by CEP are discussed in the First Quarter 1988 Report (pages 19 to 20). No new instrumentation was used for sample analysis this quarter. 6.0 Isotopic Lower Limits of Detection and Activity Determination A discussion of the calculations used in determining lower ilmits of detection and activity by Controls for Environmental Pollution, Inc., is found in Appendix B, First Quarter 1988 Report.
Table El in the first quarter 1988 report gives the lower limits of detection for h radiochemical and chemical analytical methods. Table IV in the first quarter 1938 report gives the lower limits of detection for Gamma Spectrometry. The sample counting times and the aliquot size used for lower limit of detection calculations and actual analyses are shown in Tables V and VI, in the first quarter 1988 report. 7.0 Quality Control Program A summary of CEP's Quality Control Program is contained in the First Quarter 1983 Report (page 26). No changes in the Quality Control Program occured this quarter, j O' 8.0 Data Interpretations and Conclusions This section addresses interpretations and conclusions regarding all types of samples analyzed during this report period. l l I l Analysis and review of data incorporates various techniques from historical comparison to statisical evaluation. Results which do not compare with the historical range are recalculated for verification. If the recalculation verifies the original i result, the sample is reanalyzed if possible (i.e. sufficient sample volume or isotope half life). Once it is determined that the results obtained are accurate, a statistical analysis is made. Results which are outliers with respect to historical comparisor, of previous data are considered out of baseline range or anomolous and will be so noted in the report. O
jQ v 8.1 Airborne Particulate and Radioiodine Airborne particulate samples were collected at five (5) monitoring stations on a weekly basis from June 30,1988, through September 29,1988. The five airborne particulate stations were also collection sites for airborne radiciodine (see Table Vill). All of the air particu' ate samples were analyzed for Cross Beta activity. Gamma Spectrometry, Strontium-90 and Strontium-89 analyses were performed on quarterly composites from each station. ' The rangc of Gross Beta act.ivity at each of the sampling locations follows. Collection Location Minimum (pCi/m3) Maximum (pCi/m3) O Site ^ > 0.01010.001 0.02610.002 Site A7 0.00810.001 0.02510.002 j Site A8 0.011+0.001 0.030+0.002 l Site A9 0.01210.001 0.03020.002 Site B3 0.00710.001 0.02810.002 Table VII, Cross Beta in Airborne Particulate, shows that the Gross Beta activity ranged from a minimum at Site B3 of 0.007 0.001 1 pCi/m3, collected 09/22/88-09/29/88 to a maximum of 0.0302 0.002 pCi/m3 at Sites A9 and B3 during the collection period of 09/08/88-09/15/88. The highest mean Gross Beta activity during the report period was observed at ! Site A9 with a mean activity of 0.02410.005 pCi/m3. Mean weekly Gross Beta activities ranged from a low of 0.01010.002 pC1/m3 during the collection period of 09/22/88-09/29/88 to a high of 0.02610.002
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pCi/m3 and 0.0261 0.004 pCi/m3 during the collection periods of 09/01/88- h 09/08/88 and 09/08/88-09/15/88, respectively. The airborne particulate quarterly composite analyses for Strontium-89 and Strontium-90 were less than the lower limit of detection (0.002 pCi/m3) for all sites.
)
1 1 Gamma spectralanalysis of the site composites indicated the following activities: 1 Collection Location Isotope Identified pCi/m3 ; Site A1 Beryllium-7 0.01710.004 Site A7 Beryllium-7 0.01310.004 Site A8 Beryllium-7 0.02110.004 Site A9 Beryllium-7 0.01910.004 Site B3 Beryllium-7 0.01110.003 No other gamma emitting isotopes of interest were detected in the quarterly site composites. Results of the airborne radiciodine analyses may be found in Table Vill. No Iodine-131 activity above the lower limit of detection (0.006 pCi/m3) was detected this quarter. Levels and fluctuations of activity in the air particulate and radioiodine samples are consistent with the previously accumulated preoperational data. 9
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i i th 8.2 Thermoluminescent Dosimetry Thermoluminescent Dosimeters (TLD's) were employed ' to determine direct radiation levels in and around the Callaway Site. Panasonic model UD-814 TLD's sealed in plastic bags were placed in polypropylene mesh cylindrical holders at 52 locations and exchanged quarterly. Data appearing in Table IX are the result of reading and averaging the Ca504:Tm elements. Net exposures were obtained by normalizing the total exposure to a 90 day quarter (standard quarter). Exposure levels for all monitoring locations during the third qualcr 1988 are consistent with background levels observed during previous quarters. O v 1 I i t v I l j l
1 TABLEIX j THERMOLUMINESCENT DOSIME; }Y_ Y g)
' THIRD QUARTER 1988 l
' Net Field Total . Exposure Station Time Exposure - (mrem /Std Identification Collection Location (Days) (mrem 1 2 a) Otr i 2a) I i C A-ID M- 1 11 Mi NW, City Limits of Fulton on Hwy Z, i l 0.8 Mi East of Business 54 91.0- 19.9 173 19.7 17 3 C A-ID M-2 6.6 Mi NW, County Road 111,0.6 M1 South of Hwy UU, Callaway Electric Cooperative Utility Pole No '17571 90.9 21.6 2 6.1 21.4 16 1-C A-ID M-3 1.3 Mi NW,0.1 Mi West of Hwy CC on gravel Road 0.8 M1 South Hwy O,.Callaway 3 Electric Cooperative Utility Pole No.18559 91.I' 21.6 164 21.3 1 4 5-C A-ID M-4. 1.9 Mi N,0.3 M1 East of the O and CC Junction, Callaway Electric Cooperative l Utility Pole No.18892 91.1 . 19.9 335 19.6 3 5 2-C A-ID M-5 1.3 M1 ENE, Primary Meteorological Tower 91.0 21.0 1 10.9 20.8 1 10.h C A-ID M-6 2.0 Mi W, County Road 428,1.2 Mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18609 90.2 20.2 + 5.2 20.2 32 5 C A-ID M-7 1.3 Mi S, County Road 459,2.6 Mi North of l Hwy 94, Callaway Electric Cooperative Utility Pole No. 35097 91.0 20.9 + 4.2 21.1 324 C A-IDM-8 2.9 M15, County Road 459,1.4 M1 North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06823 91.0 23.9 + 8.0 23.6 + 7.9 CA-IDM-9 3.7 Mi S, NW Side of the County Road 459 and 94 Junction, Callaway Electric Cooperative Utility Pole No. 06754 91.0 22.'2 + 6.7 22.0 + 6.6 CA-IDM-10 4.0 Mi SSE, Hwy 94,1.8 M1 East of County l Road 459, Callaway Electric Cooperative i Utility Pole No.12182 91.0 23.0,+ 6.4 23.3 3'6.4 i
C A-IDM-11 4.8 Mi SE, City of Portland, Callaway Electric , Cooperative Utility Pole No.12112 91.0 23.2 38 22.9 + 5.8 5 O1 i TABLE IX (Cont.) O T"ea o'u=isesce"r oos>=erav THIRD QUARTER 1988
' Net
, . Field Total Exposure Station Time Exposure (mrem /Std . Identification Collectica Location (Days) . (mrem 12 c) ' Qtr'12a) - ! CA-IDM-12 5.3 Mi SE, Hwy 94,0.6 Mi South of Hwy D, Utility Pole on East Side of Hwy 91.0. 23.9 228 23.7 218 C A-ID M 5.6 Mi ESE, Hwy 94,0.75 Mi East of Hwy D, Kingdom Telephone Pole No. 2Xl- 91.1 26.0 288 25.7 278 l C A-IDM-14 5.0 Mi ESE, SE Side of Intersection D and 94, Callaway Electric Cooperative Utility Pole No. I1940 91.1 20.5 + 3.8 20.3 + 3.7 C A-ID M-15 4.2 Mi ESE, Hwy D,2.5 M1 North of Hwy 94, Callaway Electric Cooperative Utility Pole No.27379 91.1 21.7 275 21.4 265 , C A-IDM 4.1 Mi ENE, Hwy D,3.6 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole . No.12976 91.1 23.1 + 19.5 22.8 + 19.3 l C A-IDM-17 4.0 Mi E, County Road 4053, 0.3 MI East of Hwy 94, Kingdom Telephone Company Pole No.3X12 91.1 23.3 208 23.1 297 l C A-IDM-18 3.8 Mi ENE, Hwy D,0.4 Mi South of Hwy 0, Callaway Electric Cooperative Utility Pole No.12952 91.1 20.2_+ 3.0 20.0_+ 3.0 C A-ID M-19 4.2 Mi NE, Hwy D,0.3 Mi North of Hwy 0, 1 Callaway Electric Cooperative Utility Pole No.12918 91.0 '24.9 2 10.3 24.7 2 10.1 l CA-IDM-20 4.8 M1 NE, City of Readsville, Callaway l Electric Cooperative Utility Pole No.12830 91.1 20.8 233 20.5'23 2 , , 1 C A-ID M-21 4.0 Mi NNE, County Road 155,1.9 M1 North of Hwy 0, Callaway Electric Cooperative Utility Pole No.19100 91.1 21.3 218 21.1 208 j CA-ID M-22 2.5 Mi NNE, County Road 150,0.5 M1 North ) of Hwy O, Callaway Electric Cooperative ; Utility Pole No.19002 91.1 21.6 + 7.0 21.3 + 6.9 1 o
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TABLE IX (Cont.) THERMOLUMINESCENT DOSIMETRY THIRD QUARTER '983 Net Field Total Exposure Station Time Exposure (mrem /Std identification Collection Location (Days) (mrem i 20) Qtr 120) C A-IDM 43 6.7 Mi NNE, City of Yucation, Callaway Electric Cooperative Utility Pole No.12670 91.1 22.3 + 3.9 22.1 + 3.8 C A-ID M-24 7.0 Mi NE, County Road 191,2.1 Mi North of Hwy K, Callaway Electric Cooperative Utility Pole No.12498 91.1 19.9 + 4.9 19.7 + 4.8 C A-ID M-25 3.'/ Mi E, County Road 289,0.3 Mi South of County Road 287, Callaway Electric Cooperative Utility Pole No.11295 91.1 24.1 18 7 23.8 177 C A-ID M-26 12.1 Mi E, Town of Americus, Callaway Electric Cooperative Utility Pole No.11159 91.1 14.9 + 4.2 14.8 + 4.1 C A-ID M-27 9.5 Mi ESE, Town of Bluffton, Callaway Electric Cooperative Utility Pole No.11496 91.1 23.6 + 3.3 23.3 + 8.2g C A-ID M-28 3.3 Mi SE, County Road 469,2.0 Mi Ncrth of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06396 91.0 20.5 17 3 20.2 17 3 C A-ID M-29 2.7 Mi SSW, County Road 448,1.2 Mi North of County Road 439, Callaway Electric Cooperative Utility Pole No. 06851 91.0 20.7 2 9.6 20.5 159 l CA-IDM-30 4.6 Mi SSW, W Side of County Road 447 and 463 Junction, Kingdom Telephone Company Pole M. 2K1 91.1 20.1 20 4 19.9 3 4.0 C A-ID M-31 7.6 Mi SW, City of Mokane, Callaway Electric Cooperative Utility Pole No. 06039 91.1 21.9 10 7 21.7 1 6.9 C A-ID M-32 5.4 Mi WSW, Hwy VV,0.6 Mi West of County Road 447, Callaway Electric Cooperative Utility Pole No. 27031 91.0 20.6 15 4 20.4 3 4.4 C A-ID M-33 7.3 Mi W, City of Hams Prairie, SE of Hwy C and AD Junction 91.0 20.6 12 4 20.4 2 4.2 C A-ID M-34 9.7 Mi WNW, NE Side of Hwy C and County Road 408 Junction 91.0 20.9 255 20.7 1 4h 5
TABLE IX (Cont.)
- Q - THERMOLUMINESCENT DOSIMETRY THIRD QUARTER 1988 Net Field Total . Exposure Station Time Exposure Identification (mrem /Std Collection Location (Days) '(mrem i 2 o) Otr i 20)
CA-IDM-35 5.8 Mi NNW, City of Toledo, Callaway Electric Cooperative Utility Pole No.17684 90.9 21.1 15 8 20.9 + 8.4 CA-IDM-36 5.2 Mi N, County Road 155,0.8 Mi South of-County Road 132, Callaway Electric Cooperative Utility Pole ^ o.19137 91.1 20.0 15 2 19.7 25 2 CA-IDM-37 0.7 Mi SSW, County Road 459,0.9 Mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35077 90.9 23.8 108 23.5 19 7 CA-IDM-38 4.8 Mi NNW, County Road 133,1.5 Mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No. 34708 90.9 16.8 + 2.4 - 16.7 + 2.4 O C ^-iD M-39 5.4 Mi "W. Co#nty need 112,0.7 Mi cest of County Road 111, Callaway Electric Cooperative Utility Pole No.17516 90.9 24.9 i 4.5 24.6 15 4 CA-IDM-40 4.2 M1 WNW, NE Side of County Road !!2 and Hwy 0, Callaway Electric Cooperative Utility Pole No. 06326 90.9 21.5 164 21.3 15 4 CA-!DM-41 4.8 Mi W, Hwy AD,2.8 Mi East of Hwy C, j Callaway Electric Cooperative Utility Pole No.18239 l 91.0 21.4 17 21.2 4 16 4 C A-IDM-42 4.4 Mi SW, County Road 447,2.6 Mi North of County Road 463, Callaway Electric Cooperative Utility Pole No. 063.26 91 0 15.9 223 15.7 11 3 C A-ID M-43 0.5 Mi SW,' County Road 459,0.7 Mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35073 90.9 21.7 17 6 21.5 16 6 CA-IDM-44 1.7 M1 WSW, Hwy CC,1.0 Mi South of County : Road 459, Callaway Electric Cooperative l Utility Pole No. I8769 91.1 20.9 285 20.7 2 5.7 - 1.0 M1 WNW, County Road 428,0.1 Mi West
'O. CA-IDM-45 of Hwy CC, Callaway Electric Cooperative Utility Pole No.18580 90.1 20.0 + 3.8 19.9 + 3.8 ;
-l 1
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TABLE IX (Cont.) THERMOLUMINESCENT DOSIMETRY h THIRD QUARTER 1988 Net Field Total Exposure Station Time Exposure (mrem /Std Identification Collection Location pays) (mrem 1 2 o) Qtr i 20) C A-ID M-46 1.5 Mi NNW, NE Side of Hwy CC and County Road 466 Intersection, Callaway Electric Cooperative Utility Pole No. 28242 91.1 22.7 14 6 22.4 13 6 C A-ID M-47 0.9 Mi NNE, Cnunty Road 448,0.9 Mi South of Hwy 0, Callaway Electric Cooperative Utility Pole No. 28151 91.0 21.2 14 4 20.9 2 4.4 C A-ID M-48 0.4 Mi NE, County Road 448,1.5 Mi South of Hwy O, Plant Security Sign Post 91.0 21.0 18 4 20.8 18 4 C A-ID M-49 1.7 Mi E, County Road 448, Callaway Electric Cooperative Utility Pole No. 06959, Reform Wildlife Management Parking Area 91.0 21.1 15 8 20.9 14 8 C A-ID M-50 0.9 Mi SSE, County Road 459,3.3 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35086 91.0 20.3 i 5.9 20.1 1 5.8 C A-ID M-51 0.7 Mi SE, Located in the "Y" of the Railroad Spur, NW of Sludge Lagoon 91.1 20.5 + 2.3 20.3 + 2.2 CA-IDM-52 0.4 Mi ESE, Light Pole near the East Plant Security Fence 91.1 22.7 28 6 22.4 1 6.7 l
)
O
O 8> weii ter Well water samples were collected monthly from three locations and analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-89, Strontium-90, and gamma-emitting nuclides. Table X presents the results of the radiochemical analyses. Cross Alpha activity ranged from less than 2.0 pCi/l to 3.9 t1.2 pCi/1. Gross Beta levels varied from less than 3.0 pCl/l to 7.8 30.7 pCl/1. The Gross Alpha and Gross Beta levels were consistent with the preoperational data. Results for Tritium analysis were below the lower limit of detection (500 pCl/l) for all samples. O All sample results for Strontium 89 and Strontium 90 analysis were below the lower limits of detection (1.5 pCi/l and 1.0 pCl/l respectively). Gamma spectrometry showed no detectable levels of isotopes of interest. Results are summarized in Table XI. l I O l I i
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8.4 Surface Water h Surface water samp!cs were collected from three locations on a monthly basis. Samples were analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-90, Strontium-39, and by Gamma Spectrometry. Results are summarized in Tables Xil and XIll. Gross Alpha and Gross Beta analyses of surface water samples showed a range of activities from less than 2.0 pCi/l to 2.311.1 pCi/l and 3.110.5 pCi/l to 6.710.6 pCi/1, respectively. The positive Gross Alpha and Gross Beta activities can be attributed to naturally occurring isotopes, such as Potassium-40, and are consistent with the preoperational data. All Tritium data from surface water samples were below the lower limit of detection (500 pCi/l). h No Strontium-89 or Strontium-90 was detected in any of the surface water samples collected this quarter. Gamma Spectralanalysis of surface water samples showed no detectable activity from isotopes of interest. O
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1 l l. A () 8.5 Sediment Washload, Bedload and Bottom Sediment samples were collected in August from three locations along the Missouri River. Samples were analyzed for Gross Alpha, Gross Beta, Strontium-90, Strontium-89, and by Gamma Spectrometry. Results are summarized in Tables XIV thru XIX. l i The following ranges of Gross Alpha and Gross Beta activities were observed in ) { the washioad, bedload and bottom sediments. j i Gross Alpha Gross Beta l i e Range Sample Type Ranfg pCi pCi/g Washload 6.9_+ 1. 2 - 16.8_+ 6.0 5.6_+ 0.4 - 7.7_+ 1.0 Bedload 1.00.2-6.71.3 1 1 1.70.1-3.90.4 1 1 ! Bottom 1.10.2-1.60.2 1 1 0.60.1-2.90.1 1 1 The highest activity of Gross Alpha (16.8 16.0 pCi/g) was seen in the Washload sediment at sample location A (0.6 river miles upstream of discharge north bank). The highest activity of Gross Beta (7.71.0 1 pCi/g) was seen in the Washload sediment at sample location D (59.5 river miles downstream of ; i discharge south bank). !
)
No Strontium-89 or Strontium-90 was detected in the washload, bedload, or bottom sediments collected during the third quarter of 1988. Gamma Spectralanalysis of the sediment samples collected during this report period are detailed in Tables XV, XVII and XIX, and are consistent with previous data. O V ;
TABLE XIV - g. WASIILOAD SEDIMENT Radiochemical Analysis pCi/n (dry)
~
Sample Collection Identification Date - Gross Alpha Gross Beta Strontium-90 Strontium CA-AQS-A 08/11/88 16.82 6.0* 7.51.9* 1 < 0.20 < 0.30 ! CA-AQS-C 08/11/88 6.91.2* 1 3.60.4* 1 < 0.20 < 0.30 CA-AQS-D 08/11/88 9.02.6* 1 7.71.0* 2 < 0.20 < 0.30
- Quantity not suff.clent for reanalysis.
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- Quantity not sufficient for reanalysis.
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8.6 Fish Fish were collected during the quarter from three locations. Types of fish collected during this quarter were: freshwater drum, carp, blue sucker, smallmouth buffalo, longnose gar, shortnose gar, bigmouth buffalo, river carpsucker, channel catfish, flathead catfish, blue catfish and gizzard shad. Gross Alpha, Gross Beta, Strontium-90, Strontium-89 and Gamma Spectralanalysis were performed on all fish collected each month. Results are presented in Tables .XX thru XXV. The activity levels are consistent with the preoperational data. Gross Alpha activity during this quarter ranged from less than 0.3 pCi/g to 0.710.2 pCi/g (sample CA-AQF-A, gizzard shad collected 08/11/88). Gross Beta activities ranged from a low of 2.5 20.1 pCl/g (sample CA-AQF-A, gizzard shad collected 07/13/88) to a high of 9.6 10.2 pCl/g (sample CA-AQF-D, blue catfish O collected 08/12/88). Gross Alpha and Cross Beta activities seen in fish samples can be attributed to naturally occurring isotopes (e.g. Potassium-40). All fish data for Strontiurn-90 and Strontium-89 were below the lower limits of detection of 0.20 pCi/g and 0.30 pCi/g, respectively. Results of Gamma Spectralanalysis may be found in Tables XXI, XXIII, and XXV. O i
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l O s.7 u > i' l Milk samples were . collected from two locations, the Green Farm and the -! 1 Schneider Farm. The Green Farm supplies cow's milk while the Schneider Farm l provides both cow's milk and goat's milk. Analyses for lodine-131, elemental
)
Calcium, Strontium-90, Strontium-89 and Gamma-emitting isotopes were -l i performed on all milk samples. Tables XXVI and XXVII present results of these analyses. . Iodine-131 was detected in one sample,1.2+ 0.5 pCi/1, at the Schneider Farm (M5B) goat' milk on 08/21/88. No other lodine-131 above the lower limit of detection (0.5 pCl/l) was detected in the milk samples during this period. Five (5) milk samples collected during the third quarter were above the lower O iimit e eetecem a 1.0 gCi/> for Strontium-90. No miik semeies were ebeve the lower limit of detection of 2.0 pCi/l for Strontium-89. j f 1 No gamma-emitting isotopes of interest were detected in any of the milk samples. l l l l O
1 TABLE XXVI h FRESP MILK Radiochemical Collection Iodine-131 Calcium Strontium-90 Strontium-89 Date pCi/l mg/l pCi/l pCi/l Green Farm (M-1) 07/12/58 < 0.5 880 < 1. 0 < 2.0 07/26/88 < 0.5 970 < l .0 < 2.0 08/09/88 < 0. 5 1080 1.30.5* 1 < 2. 0 08/23/88 < 0.5 1160 < l.0 < 2.0 09/13/88 < 0.5 1490 < !.0 < 2.0 09/27/88 < 0.5 820 < l.0 < 2.0 Schneider Farm (MSA) 07/10/88 < 0.5 940 < l.0 < 2.0 07/24/88 < 0.5 .930 < 1.0 < 2.0 g 08/07/S8 < 0.5 1160 5.91.3* 1 < 2.0 08/22/88 < 0.5 1300 < l.0 < 2.0 09/12/88 < 0.5 1340 < l.0 < 2.0 09/25/88 < 0.5 1010 < l .0 < 2.0 i Schneider Farm (M5B) 07/09/88 < 0.5 980 4.90.5* 2 < 2.0 07/23/88 < 0.5 930 1.71.0* 1 < 2.0 j 08/06/88 < 0.5 1070 10.112.9* < 2.0 ) 08/21/88 1.210.5 *
- 1510 < l.0 < 2.0 09/10/8R < 0.5 1440 < l .0 < 2.0 09/24/88 < 0.5 1150 < 1.0 < 2.0 l I
- Verified by reanalysis and tM analysis. !
** Verified by tM analysis.
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8.8 Vegetation h Vegetation samples were collected from three (3) sampling locations during the third quarter of 1988. Vegetation samples consisted of lettuce, mustard greens, turnip greens and cabbage collected from the Beazley, Becker and Meehan Farms. All vegetation samples were analyzed for Gross Alpha, Gross Beta, lodine-131 and by Gamma Spectrometry. Results are presented in Tables XXVill and XXIX. , All Gross Alpha activity was less than the lower limit of detection (0.3 pCi/g). l This Gross Alpha activity is consistent with the levels found during monitoring in previous years. 1 Gross Beta activity observed in the vegetation samples ranged from 1.0 + 0.1 pCi/g to 19.810.3 pCi/g. No gamma emitting nuclides of interest were detected in the vegetation samples collected during the third quarter of 1988. l 1 0'
I TABLE XXVIII (] VEGETATION - Sample Identification; . Sample Radiochemical Analysis (pCl/g) Date Collected Location Gross Alpha Gross Beta Iodine-131 i i C A-FPL-V3 ! Lettuce i 07/20/88 Beazley . Farm < 0. 3 13.0 22 0 <0.03 C A -FPL-V3 Mustard Greens 07/20/88 Beazley Farm < 0.3 12.7 22 0 < 0.03 ~ q C A-FPL-V3 ] Cabbage i 07/20/88 Beazley Farm < 0.3 4.6 11 0 < 0.03 C A-FPL-V3 Turnip Greens 1 08/16/88 Beazley Farm < 0.3 11.4 22 0 < 0.03 l C A-FPL-V3 { Cabbage (q ) 08/16/88 Beazley Farm < 0.3 13.7 + 0.2
~
< 0.03 CA-FPL-V3 Mustard Greens 08/16/88 Beazley Farm < 0.3 18.8 13 0 <0.03 C A-FPL-V 3 Mustard Greens 09/19/88 Beazley Farm < 0.3 19.8 13 0 < 0.03 C A-FPL-V3 Greens Turnip 09/19 /88 Beazley Farm < 0. 3 l
18.5 13 0 <0.03 l C A-FPL-V3 Cabbage : 09/19/88 Beazley Farm < 0. 3 16.5 13 0 <0.03 I CA-FPL-V6 ! Turnip Greens 07/20/88 Becker Farm < 0. 3 1.0 11 0 < 0.03 CA-FPL-V6 Cabbage 07/20/88 Becker Farm < 0. 3 7.1 22 0 <0.03 0 TABLE XXVIII (Cont.) VEGETATION . lh Sample Identification; Sample Radiochemical Analysis (pCi/g)
. Date Collected Location Gross Alpha Gross Beta Iodine-131 C A-FPL-V 6 . 1 Lettuce 07/20/88 Becker Farm < 0.3 9.4 12 0 < 0.03 CA-FPL-V6 Mustard Greens j 07/20/88 Becker Farm . < 0.3 13.1 12 0 < 0.03
. j C A-FPL-V 6 Mustard Greens 08/16/88 Becker Farm < 0.3 14.1 12 0 < 0.03
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O l l APPENDIX A EPA CROSS-CHECK RESULTS h 1988 1 I l l O 1 O eP^ Cross-CneCx Paoca^= 1988 Radionuclides in Air Filters EPA- CEP j Known Value Reported Value Date Parameter pCi/ filter 11 a pCi/ filter i 2 a 3/88 Gross Alpha 20 1 5 23 1 1 26 + 1 -" 28 { l '.:: Gross Beta 50 2 5 46 1 2 i 51 1 2- j 54 1 2 ] Strontium-90* 17 + 1.5 13 + 2 14 ~2 1 1 15 1 2 ) Cesium-137 16 + 5 19 + 7 22 + 7 2457 l 8/88 Gross Alpha 8+5 7+1 f 8+1~ 9_l Gross Beta 28 + 5
~
23 + 2 2452. 25 1 2 Strontium-90 812 _7 1 2 812 9 _+ 2 Cesium-137 12 + 5 13 + 10. 14 + 10 16110
- Review of raw data indicated initial miscalculation (parent recovery value not factored) and activities of 17,19, and 17 7e = 17.7) should have been reported. ;
O
l EPA CROSS-CHECK PROGRAM h. 1988 Gross Alpha and Cross P, eta in Water EPA 'CEP. Known Value Reported Value Date Parameter pCi/li 1 a pC1/112 o '- 1/88 Gross Alpha 4 1 5- 512 6+2 622 Gross Beta
- 8+5~
30 + 2 3222 34 1 2 3/88 Gross Alpha 615 512 5+2 g-6{2 Gross Beta 13 2 5 14 1 2 15 1 2 17 3 2 5/88 Gross Alpha 11 + 5 8+2 11 + 2 1222 Gross Beta 11 + 5
~
14 + 2 1672 i 18 1
~2 I 7/88 Gross Alpha 15 1 5 822 j 9+2 i 10-1 2 )
Gross Beta 415 812 i 8+2 l 812 l
-l 1
- Reanalysis obtained values of 14,15,15 (E = 15). Initial values were the result of QA glassware having beta contamination.
h 1 I 1
)
O 89^ caoss-c"ecx eaoca^= 1988 '. 1 1 l
.i Gross Alpha and Gross Beta in Water (Cont.) i
~l EPA CEP 1 Known Value Reported Value Date - Parameter pCi/l Ia ' pCi/li 2 a :)
.l 9/23 Gross Afpha 815 812 ,
9 1 2- 1
'9 1 2 Gross Beta 10 1 5 12 2 2 13 + 2
~
14_ 2 O , i s
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O j
EPA CROSS-CHECK PROGRAM 1988 h ! Gamma in Water EPA, CEP Known Value Reported Value Date Parameter pCi/li 1 a pCl/li 2 a 2/88 Cobalt-60 69 + 5 56 + 5 62 + 5 6875 4 Zinc-65 94 + 9.4
~ 81+6 8676 91 2 6 Ruthenium-106 105 1 10.5 88 1 5 {
96 + 5 " 104~ 15 Cesium-134' 64 +5~ 47 + 5 54_T S 59 _+ 5 Cesium-137 94 + 5
- 77 + 5 8975 92[+ 5 6/88 Chromium-51 *
- 302 + 30 210 + 15 220 + IS 240 1 15 .-
Cobalt-60 15f,5 l 8 2 15 ; 11 1 15 l 13 2 15 l Zinc-65 * *
- 101 + 10 119 + 15 123 + 15 127 1 15 Ruthenium-106 195 + 20 146 + 15 153 + 15 176 1 15
- Values of 58, 58, and 61 (x = 59) should have been reported. (Initial values reported before analysis was complete.)
- Mean of all Chromium-51 analyses was 257 i 15. (Improper computation of original mean.)-
- ** Review of data indicated a value of 98 + 15 for Zinc-65. (No reason found for
~
original high results.) O ce^ caoss-c"ecx eaoca^=- 1988 Gamma in Water (Cont.) EPA CEP Known Value Reported Value - Date Parameter pCi/li 1 a pCi/li20-Cesium-134 20 + 5 20 + 15 ' 26 + 15 ' 27i15-Cesium-137 2545 19 + 15 - 26 + 15
-27515 O
i l i O EPA CROSS-CHECK PROGRAM -h 1988 Tritium in Water EPA' CEP Known Value Reported Value Date Parameter pCi/li 1 o pCi/li 2 a 2/38 Tritium 3327 + 362 2760 + 300 2994 + 300 30627300 i 1 1 6/88 Tritium 5565 + 557 4800 + 500 5000 + 500 - 1 52001500 O
. 1 1
1
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- _ . _ ______________ ________ _ = _ _._ _ _ _ _ _ ___J
1 l O ee^ caoss-caecx Paoca^u l 1988 Strontium in Water EPA CeP 1 Known Value Reported Value Date Parameter pCi/li 1 a pCi/li 2 a 1/88 Strontium-89 30 + 5 - 30 + 5 35 + 5 40 2 5. Strontium-90* 15 + 2 9+2
~
11 + 2 11 2- 2 i 5/88 Strontium-89 20 + 5 20 + 3 f 21 + 3 l 2213 O. Strontium-90 20 2 2 18 2 2 19 + 2 20 1~2
- Review of calculations indicated that values of 15,14, and 18 di = 16) should have been reported. (original results were result of miscalculation.)
4
EPA CROSS-CHECK PROGRAM h
-1988 I
l Iodine-131 in Water . 1 l EPA CEP. - Known Value Reported Value l Date Parameter pCi/li 1 a - pCi/li 2 a i 1 4/88 Low Level 7.50 1 075 614 924 924 .; 8/88 High Level 76 2 8 76 2 8 81 1 8 85 2 3 O l 1 0
I
.O. Een caoss-cnEcx eaocatu 1988 +
Iodine-131 in Milk' i
')
EPA 'CEP ' Known Value. Reported Value , Date Parameter pC1/111 o . pCi/li 2 o-2/88 Low Level 4.0 g 0,4 3.0 170 4.0 0.7
' 4.0 170 O i l
j O
EPA CROSS-CHECK PROGRAM h 1988 Radionuclides in Food EPA CEP Known Value Reported Value Date Parameter pCl/kg i io pCl/kg i 20 l 1/88 Strontium-89 46 2 5 Not Reported Strontium-90 55 3 3 Not Reported lodine-131 102 + 10
- 101 + 25 107725
~
111 2 25 Cesium-137 91 + 5 81 + 10 91 + 10 98 + 10 Potassium 1230 2 62 mg/kg 1320 1 132 mg kg O 1320 2 132 mg kg 1320 2 132 mg kg l l 0
O
%J SECTION 3.5 RADIOLOGICAL ENVIRONMENTAL MOPITORING O FOURTH QUARTER REPORT 1988 i
O 1 ______________m______ _ _ - - - - - - - - _ - - - _ _- -
0 O I i i UNION ELECTRIC COMPANY l ST. LOUIS, MISSOURI CALLAWAY PLANT UNIT 1 I RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM O oUARTERov REeORT EOR OCTOBER, NOVEMBER, AND DECEMBER 1988 SUBMITTED BY: CONTROLS FOR ENVIRONMENTAL POLLUTION,INC.
.1925 ROSINA STREET SANTA FE, NEW MEXICO Copy No. 11 Prepared By: Y Bob Bates, Contract Manager 2
j Approved By: - O e*rres e aueiier,eresideat
em j U CONTENTS h Section Title Page i Abstract 1 i s I 1.0 Introduction 2 i s 2.0 Description of the Monitoring Program 3 3.0 Analytical Procedures 3 l 4.0 Sample Preparation Method 3 l 5.0 Major Instrumentation 3 6.0 Isotopic Detection Limits and Activity Determinations l! 3 7.0 Quality Control Program 4 , 8.0 Data Interpretations and Conclusions 4 , em Appendix A: 1938 EPA Cross-check Results 46 U i i I J 1 i [I l t i I i V , l l
TABLES Number Title Page VII Gross Beta in Airborne Particulate 7 Vill Airborne Radioiodine 8 IX Thermoluminescent Dosimetry (Fourth Quarter 1988) 10 X Well Water - Radiochemical 16 XI Well Water - Gamma Spectrometry 17 XII Surface Water - Radiochemical 19 XIII Surface Water - Gamma Spectrornetry 20 XIV Washload Sediment - Radiochemical 23 XV Washload Sediment - Gamma Spectrometry 24 XVI Bedload Sediment - Radiochemical 25 X VII Bedload Sediment - Gamma Spectrometry 26 X Vill Bottom Sediment - Radiochemical 27 XIX Bottom Sediment - Gamma Spectrometry 28 XX Fish, CA-AQF-A - Radiochemical 30 XXI Fish, CA-AQF-A - Gamma Spectrometry 31 XXII Fish, CA-AQF-C - Radiochemical 32 X XIll Fish, CA-AQF-C - Gamma Spectrometry 33 XXIV Fish, C A-AQF-D - Radiochemical '34 XXV Fish, CA-AQF-D - Gamma Spectrometry 35 XXVI Milk - Radiochemical 37 XXVII Milk - Gamma Spectrometry 38 X X Vill Vegetation - Radiochemical 40 XXIX Vegetation - Gamma Spectrometry 42 XXX Soil - Radiochemical 44 XXXI Soil - Gamma Spectrometry 45
g Abstract Controls for Environmental Pollution, Inc (CEP) has conducted a radiological environmental monitoring program (REA1P) for Union Electric Company (UEC), Callaway Plant, Unit 1, since Aiay 5, 1983. This quarterly report presents data for the months of October, Novernber, and December 1988. Evaluation of radiation levels in the environs around Union Electric Company's Callaway Plant entailed sampling at strategic points in various exposure pathways. The following types of samples were collected and analyzed: soil, milk, vegetation, surface water, well water, bottom sediment, bedload sediment, washload sediment, fish, airborne particulate, airborne radioiodine, and direct radiation (TLD). Analytical results are presented and discussed along with other pertinent information. Possible trends and anomalous results, as interpreted by Controls for Environmental Pollution, Inc., are discussed. l l l 0 _ _ - _ _ _ _ _ _ _ - _ ~
1.0 Introduction h This report presents an analysis of the results of the Radiological Environmental Monitoring Program (REMP) conducted during the fourth quarter of 1988 for Union Electric Company, Callaway Plant. In compliance with federal and state regulations and in its concern to maintain the { l quality of the local environment UEC began its radiological monitoring program in April,1982. The objectives of the radiological environmental monitoring program are as follows:
- 1) to establish baseline radiation levels in the environs prior to reactor operations; 2) to monitor potential critical pathways of radioeffluent to man; 3) to determine radiological impact on the environment caused by the operation of the Callaway Plant.
O A number of techniques are being used to distinguish Callaway Plant effects from other sources during the operational phase, including application of established background levels. Operational radiation levels measured in the vicinity of the Callaway Plant are compared with t.he pre-operational measurements at each of the sampling locations. In addition, results of the monitoring program help to evaluate sources of elevated levels of radiation during reactor operation in the environment, e.g., atmospheric fallout or abnormal plant releases. The Callaway Plant is located on a plateau approximately five miles north of the Missouri River in Callaway County, Missouri. The plant consists of one 1150 MWE pressurized water reactor, which achieved initial criticality on October 2,1984. O
Q 2.0 Description of the Monitoring Program Union Electric Company' has contracted with Controls for Environmental Pollution, Inc. starting May 1983, to determine the radiation levels existing in and around the Callaway Plant area. - 1 A summary of the Callaway Plant Monitoring Program is contained in the first quarter report 1988 (page 3). No changes in the monitoring program occured during the fourth quarter,1988. i 3.0 Analytical Procedures The analytical procedures routinely used by CEP to analyze samples are discussed in l the First Quarter 1988 Report (pages 14 to 18). No new analytical methods were used this quarter, j O ' 4.0 Sample Preparation Methods Sample preparation methods used by CEP are discussed in the First Quarter 1988 1 Report (page 18). No new sample preparation methods were used this quarter. 5.0 Major Instrumentation Major analytical instrumentation used by CEP are discussed in the First Quarter 1988 Report (pages 19 to 20). No new instrumentation was used for sample analysis this quarter. 6.0 Isotopic Lower Limits of Detection and Activity Determinations l A discussion of the calculations used in determining lower limits of detection and activity by Controls for Environmental Pollution, Inc., is found in Appendix B, First Quarter 1988 Report.
i Table 111 in the first quarter 1988 report gives the lower limits of detection for radiochemical and chemical analytical methods. Table IV in the first quarter-1988 report gives the lower limits of detection for Gamma Spectrometry. The sample counting times and the aliquot size used for lower limit of detection . 1 calculations and actual analyses are shown in Tables V and VI, in the first quarter 1988 l report. J 7.0 Quality Control Program I A summary of CEP's Quality Control Program is contained in the First Quarter 1988 Report (page 26). No changes in the Quality Control Program occured this quarter.
. O 8.0 Data Interpretations and Conclusions This section addresses interpretations and conclusions regarding all types. of samples analyzed during this report period.
Analysis and review of data incorporates various techniques from historical comparison to statisical evaluation. Results which do not compare with the historical range are recalculated for verification. If the recalculation verifies the original result, the sample is reanalyzed if possible (i.e. sufficient sample volume or isotope half life). Once it is determined that the results obtained are accurate, a statistical analysis is made. Results which are outliers with respect to historical comparison of previous data are considered out of baseline range or anomolous and will be so noted in the' report. l O 82 ^ir6er"e e rticoi tes oa dioiodi"e Airborne particulate samples were collected at five (5) monitoring stations on a weekly basis from October 6,1988, through December 28, 1988. The five airborne particulate stations were also collection sites for airborne radiciodine (see Table VIII). All of the air particulate samples were analyzed for Gross Beta activity. Gamma Spectrometry, Strontium-90 and Strontium-89 analyses were performed on quarterly composites from each station. The range of Gross Beta activity at each of the sampling locations follows. Collection Location Minimum (pCi/m3) Maximum (pCi/m3) O Site ai 0.0is10002 0.03810.002 Site A7 0.01710.002 0.03520.002 Site A8 0.01510.001 0.03020.002 Site A9 0.01420.002 0.03020.002 Site B3 0.01810.002 0.03120.002 Table VII, Gross Beta in Airborne Particulate, shows that the Gross Beta activity ranged from a minimum at Site A9 of 0.014 0.0022 pC1/m3, collected 11/18/88-11/23/88 to a maximum of 0.03810.002 pCi/m3 at Site Al during the collection period of 11/18/88-11/23/88. The highest mean Gross Beta activity during the report period was observed at 1 Site A1 with a mean activity of 0.02510.006 pCi/m3 Mean weekly Gross Beta activities ranged from a low of 0.01810.001 pCi/m3 l during the collection period of 10/20/88-10/27/88 to a high of 0.03010.001 l 1 4
l pC1/m3 during the collection period of 11/03/88-11/10/88.. h, l q The airborne particulate quarterly composite analyses for Strontium-89 and Strontium-90 were less than the lower limit of detection (0.002 pC1/m3) for all ]! sites. Camma spectralanalysis of the site composites indicated the following activities: Collection Location Isotope Identified _ pCi/m3 Site A1 Beryllium 0.08710.038' Site A7 Beryllium-7 0.09510.028 Site A8 Beryllium-7 0.11120.036 j Site A9 Beryllium-7 0.11120.029 Site B3 Beryllium-7 0.115+ 0.030 i e1 No other Gamma-emitting isotopes of interest were detected in the quarterly - site composites. Results of the airborne radioiodine analyses may be found in Table VIII. No Iodine-131 activity above the lower limit of detection (0.006 pCi/m3) was detected this quarter. Levels and fluctuations of activity in the air particulate and radioiodine samples are consistent with the previously accumulated preoperational data, l O
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l l (] 8.2 Thermoluminescent Dosimetry Thermnluminescent Dosimeters (TLD's) were employed to determine direct radiation levels in and around the Callaway Site. Panasonic model UD-814 TLD's sealed in plastic bags were placed in polypropylene mesh cylindrical holders at 52 locations and exchanged quarterly, i Data appearing in Table IX are the result of reading and averaging the 1 CaSO4 :Tm elements. Net exposures were obtained by normalizing the total i 1 exposure to a 90 day quarter (standard quarter). I l i l Exposure levels for all monitoring locations during the fourth quarter 1988 are 1 { consistent with background levels observed during previous quarters. ! O j i i l I I l 1
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TABLEIX THERMOLUMINESCENT DOSIMETRY FOURTH QUARTER 1988 Net Field Total Exposure Station Time Exposure (mrem /Std Identification Collection Location (Days) (mrem 1 20) Qtr i 20) C A-IDM- 1 11 Mi NW, City Limits of Fulton on Hwy Z, 0.8 Mi East of Business 54 92.0 19.8 16 2 19.4 25 2 C A-ID M-2 6.6 Mi NW, County Road 111,0.6 Mi South of Hwy UU, Callaway Electric Cooperative Utility Pole No.17571 91.8 20.7 + 1.3 20.3 + 1.3 CA-IDM-3 1.3 Mi NW,0.1 Mi West of Hwy CC on gravel Road 0.8 Mi South Hwy O, Callaway Electric Cooperative Utility Pole No.18559 91.9 20.8 19 0 20.4 29 0 C A-ID M-4 1.9 Mi N,0.3 M1 East of the O and CC ( Junction, Callaway Electric Cooperative Utility Pole No.18892 92.0 18.1_+ 1.4 17.7 _+ 1.3 C A-ID M-5 1. .' r " *E, Primary Meteorological Tower 92.0 17.3 17 1 16.9 16 1 C A-ID M-6 2.0 Mi W, County Road 428,1.2 Mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18609 91.8 20.1 16 2 19.7 152 CA-IDM-7 1.3 Mi S, County Road 459,2.6 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 35097 91.9 19.9 15 2 19.5 142 C A-ID M-8 2.9 Mi S, County Road 459,1.4 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No. 06823 91.9 21.9 18 2 21.5 172 CA-IDM-9 3.7 Mi S, NW Side of the County Road 459 and 94 Junction, Callaway Electric , Cooperative Utility Pole No. 06754 91.9 21.3 11 20.9 3 103
)
CA-IDM-10 4.0 Mi SSE, Hwy 94,1.8 M1 East of County Road 459, Callaway Electric Cooperative l Utility Pole No.12182 91.9 20.4 11 3 20.0 203 l C A-IDM-I l 4.8 Mi SE, City of Portland, Callaway Electric Cooperative Utility Pole No.12112 92.0 21.5 29 2 21.1 282 9: l 1
1 TABLE IX (Cont.) 'O THeRMOtUMiNesCeNr DOSiMETRv i FOURTH QUARTER 1988' u i Net . Field Total Exposure
. Station Time Exposure (mrem /Std i identification Collection Location (Days) - (mrem i 20) Qtr i 2 a) I C A-ID M-12 5.3 Mi SE, Hwy 94,0.6 Mi South of Hwy D, Utility Pole on East Side of Hwy 92.9 20.5 17 1 19.9 26 1 i C A-IDM-13 5.6 Mi ESE, Hwy 94,0.75 Mi East of Hwy D, Kingdom Telephone Pole No. 2X1 92.9 21.1 + l.8 20.4 + 1.8 C A-ID M- 14 5.0 Mi ESE, SE Side of Intersection D and 94, Callaway Electric Cooperative Utility Pole No. I1940 92.9 20.5 + 2.0
- 19.9_+ 1.9 C A-IDM-15 4.2 Mi ESE, Hwy D,2.5 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No.27379 92.9 20.0_+ 1.5 19.4 _+ 1.4 n
(_) C A-ID M-16 4.1 Mi ENE, Hwy D,3.6 Mi North of Hwy 94, Callaway Electric Cooperative Utility Pole No.12976 92.9 18.4 _+ 1.9 17.9_+ 1.9 C A-IDM-17 4.0 Mi E, County Road 4053, 0.3 Mi East of Hwy 94, Kingdom Telephone Company Pole No.3X12 92.9 19.9_+ 2.7 19.3_+ 2.6 CA-IDM-18 3.8 Mi ENE, Hwy D,0.4 Mi South of Hwy 0, Callaway Electric Cooperative Utility Pole No.12952 92.9 19.6 _+ 1.9 19.0_+ 1.9 C A-IDM-19 4.2 Mi NE, Hwy D,0.3 M1 North of Hwy 0, ' Callaway Electric Cooperative Utility Pole No.12918 92.9 20.0 _+ 3.0 19.4 _+ 2.9 C A-ID M-20 4.8 Mi NE, City of Readsville, Callaway - Electric Cooperative Utility Pole No.12830 92.9 19.9 32 2 19.3 31 2 1 C A-ID M-21 4.0 Mi NNE, County Road 155,1.9 Mi North of Hwy 0, Callaway Electric Cooperative Utility Pole No.19100 92.9 20.6 + 2.5 20.0 + 2.4 CA-IDM-22 2.5 Mi NNE, County Road 150,0.5 Mi North t of Hwy O, Callaway Electric Cooperative Utility Pole No.19002 92.9 20.5 + 2.2 19.9 + 2.1 1 O - - 1
.1 '
I a
i I i TABLE IX (Cont.)' l l THERMOLUMINESCENT DOSIMETRY h FOURTH QUARTER 1988 Net Field Total Exposure Station Time Exposure (mrem /Std identification Collection Location (Days) (mrem 12 o) Qtr i 20) I CA-IDM-23 6.7 Mi NNE, City of Yucation, Callaway Electric Cooperative Utility Pole No.12670 92.9 19.5 13 1 18.9 131 CA-IDM-24 7.0 Mi NE, County Road 191,2.1 Mi North of Hwy K, Callaway Electric Cooperative Utility Pole No.12498 92.9 18.9 19 1 18.3 281 CA-IDM-25 8.7 Mi E, County Road 289,0.3 Mi South of i County Road 287, Callaway Electric Cooperative Utility Pole No.11295 92.9 20.3 17 19.7 1 171 C A-ID M-26 12.1 Mi E, Town of Americus, Callaway i Electric Cooperative Utility Pole No.11159 92.9 14.6 + 1.9 14.2 + 1.9 CA-IDM-27 9.5 Mi ESE, Town of Bluff ton, Callaway Electric Cooperative Utility Pole No. I1496 92.9 19.4 131 18.8 1 3g 1 CA-IDM-28 3.3 Mi SE, County Road 469,2.0 Mi North of l Hwy 94, Callaway Electric Cooperative Utility Pole No. 06896 91.9 MISSING MISSING CA-IDM-29 2.7 Mi SSW, County Road 448,1.2 Mi North ' of County Road 459, Callaway Electric i Cooperative Utility Pole No. 06851 91.9 ILS 14 1 18.1 14 1 C A-IDM-30 4.6 Mi SSW, W Side of County Road 447 and 463 Junction, Kingdom Telephone Company < Pole No. 2K1 91.9 18.9 171 13.5 16 1 C A-IDM-31 7.6 Mi SW, City of Mohane, Callaway Electric Cooperative Utility Pole No. 06039 91.9 20.3 122 19.9 22 2 CA-IDM-32 5.4 Mi WSW, Hwy VV,0.6 Mi West of County i Road 447, Callaway Electric Cooperative Utility Pole No. 27031 91.9 20.1 182 19.7 17 2 ! CA-IDM-33 7.3 Mi W, City of Hams Prairie, SE of Hwy C and AD Junction 91.9 19.5 17 2 19.1 16 2 0
TABLE IX (Cont.) THERMOLUMINESCENT DOSIMETRY FOURTH QUARTER 1988 Net Field Total Exposure Station Time Exposure (mrem /Std Identification Collection Location (Days) (mrem i 2o) Qtr i 20) C A-ID M-34 9.7 Mi WNW, NE Side of Hwy C and County Road 408 Junction 91.9 19.3 + 2.4 18.9 + 2.4 CA-IDM-35 5.8 Mi NNW, City of Toledo, Callaway Electric Cooperative Utility Pole No.17684 91.8 18.6 + 1.4 18.3 + 1.3 C A-IDM-36 5.2 Mi N. County Road 155,0.8 Mi South of County Road 132, Callaway Electric Cooperative Utility Pole No.19137 92.9 18.8 25 2 18.2 34 2 CA-IDM-37 0.7 Mi SSW, County Road 459,0.9 Mi South of Hwy CC, Callaway Electric Cooperative Utility Pole No. 35077 92.0 19.8 + 2.1 19.3 + 2.1 C A-ID M-38 4.8 Mi NNW, County Road 133,1.5 Mi South O f Hwy uu, Callaway Electric Cooperative Utili+y Pole No. 34708 91.8 15.6 10 2 15.3 1 2.0 C A-lDM-39 5.4 Mi NW, County Road i12,0.7 Mi East of County Road 111, Callaway Electric Cooperative Utility Pole No.17516 91.8 19.8 162 19.4 2 2.5 CA-IDM-40 4.2 Mi WNW, NE Side of County Road 112 and Hwy 0, Callaway Electric Cooperative Utility Pole No. 06326 91.8 20.2 181 19.8 1 1.8 C A-ID M-41 4.8 Mi W, Hwy AD,2.8 Mi East of Hwy C, Callaway Electric Cooperative Utility Pole No. I8239 91.9 19.9 212 19.5 1 2.1 CA-IDM-42 4.4 Mi SW, County Road 447,2.6 Mi North of County Road 463, Callaway Electric Cooperative Utility Pole No. 06326 91.9 16.2 261 15.9 1 1.6 C A-ID M-43 0.5 Mi SW, County Road 459,0.7 Mi South o.f Hwy CC, Callaway Electric Cooperative Utility Pole No. 35073 92.0 l 18.8 + 1.1 18.4 + 1.1 C A-ID M-44 1.7 Mi WSW, Hwy CC,1.0 Mi South of County Road 459, Callaway Electric Cooperative Utility Pole No.18769 91.8 19.2 281 18.8 38 1
TABLE IX (Cont.) THERMOLUMINESCENT DOSIMETRY h FOURTH QUARTER 1988 Net Field Total Exposure Statica Time Exposure (mrem /Std Identification Collection Location (Days) (mrem 1 2a) Qtr i 20) CA-IDM-45 1.0 Mi WNW, County Road 428,0.1 Mi West of Hwy CC, Callaway Electric Cooperative Utility Pole No.18580 91.9 20.0 25 1 19.6 25 1 CA-IDM-46 1.5 Mi NNW, NE Side of Hwy CC and County Road 466 Intersection, Callaway Electric Cooperative Utility Pole No. 28242 91.9 20.0 + 1.6 19.6 + 1.6 CA-IDM-47 0.9 Mi NNE, County Road 448,0.9 Mi South of Hwy 0, Callaway Electric Cooperative Utility Pole No. 28131 92.0 18.6 24 2 18.2 23 2 l C A-ID M-48 0.4 Mi NE, County Road 448,1.5 Mi South l of Hwy 0, Plant Security Sign Post 92.0 20.2 11 2 19.7 10 2 l C A-ID M-49 1.7 Mi E, County Road 448, Callaway Electric Cooperative Utility Pole No. 06959, Reform Wildlife Management Parking Area 92.0 18.4 14 2 18.0 g 2.4 CA-IDM-50 0.9 Mi SSE, County Road 459,3.3 Mi North of Hwy 94, Callaway Electric Cooperative ' Utility Pole No. 35086 91.9 19.4 11 2 19.0 21 2 C A-IDM-51 0.7 Mi SE, Located in the "Y" of the Railroad Spur, NW of Sludge Lagoon ~ 91.9 20.0 + 1.4 19.6 + 1.3 CA-IDM-52 0.4 Mi ESE, Light Pole near the East Plant Security Fence 91.9 19.3 28 1 18.9 1 .1 .~ l l l l l l l e! l
(3 8.3 Well Water () ; Well water samples were collected monthly from three locations and analyzed l for Gross Alpha, Gross Beta, Tritium, Strontium-89, Strontium-90, and Gamma-emitting nuclides. Table X presents the results of the radiochemical analyses. Cross Alpha activity I ranged from less than 2.0 pCi/l to 3.211.2 pCi/1. Gross Beta levels varied from l less than 3.0 pCi/l to 9.0 10.7 pCi/1. The Gross Alpha and Cross Beta levels were l consistent with the preoperational data. l Results for Tritium analysis were below the lower limit of detection (500 pCi/1)
]
l for all samples.
- t All sample results fo- Suontium-89 and Strontium-90 analysis were below the ;
l lower limits of detection (1.5 pCi/l and 1.0 pCi/l respectively). l Gamma spectrometry showed no detectable levels of isotopes of . interest. Results are summarized in Table XI. i [v
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3.4 Surface Water h Surface water samples were collected from three locations on a monthly basis. Samples were analyzed for Gross Alpha, Gross Beta, Tritium, Strontium-90, Strontium-89, and by Gamma Spectrometry. Results are summarized in Tables XII and XIII. Gross Alpha and Gross Beta analyses of surface water samples showed a range of activities from less than 2.0 pCi/l to 3.61.31 pCi/l and less than 3.0 pCi/l to 7.610.6 pCi/1, respectively. The positive Gross Alpha and Gross Beta activities can be attributed to naturally occurring isotopes, such as Potassium-40, and are consistent with the preoperational data. All Tritium data from surface water samples were belosv the lower limit of detection (500 pCi/1). O No Strontium-89 or Strontium-90 was detected in any of the surface water samples collected this quarter. Gamma Spectralanalysis of surface water samples showed no detectable activity from isotopes of interest. O L____ _
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o ow f o 1 1 1 2 2 2 3 3 3 i 0 0 0 0 0 0 0 0 0 t l et a 5 S 5 S 5 5 mahn i l 5 5 5 pc - - - - - - - - mi A A A A A A A A A i l ait f WWW WWW WWW r t Sn S S S S S S S S S e ss d e - A A A A A A A A A we o L I C C C C C C C C C L *
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8.5 Sediment Washload, Bedload and Bottom Sediment samples were collected in November 1 from three locations along the Missouri River. Samples were analyzed for Gross Alpha, Gross Beta, Strontium-90, Strontium-89, and by Gamma. Spectrometry. Results are summarized in Tables XIV thru XIX. The following ranges of Gross Alpha and Gross Beta activities were observed in the washload, bedload and bottom sediments. 1 l Gross Alpha Gross Beta .l Range Range Sample Type pCi/g pCi/g Washload 12.9+2.7 - 15.6+2.9 10.0+ 1.0 - 18.3+ 1.3 Bedload 1.00.2-3.00.5 1 2.50.1-3.10.2 1 1 1 i Bottom 1.30.2-1.80.2 1 1 0.80.1-1.10.1 1 1
-O The aishest ectivixv or cross ^>ns e ci5.612 9 nci/8) wes seea ia the wessioed sediment at sample location C (1.0 river miles downstream of discharge north bank). The highest activity of Gross Beta (18.311.3 pCi/g) was seen in the Washload sediment at sample location C (1.0 river miles downstream of discharge north bank).
No Strontium-89 or Strontium-90 was detected in the washload, bedload, or '!
.i bottom sediments collected during the fourth quarter of 1988. i l
l Gamma Spectralanalysis of the sediment samples collected during this report - period are detailed in Tables XV, XVII and XIX, and are consistent with previous , i data. l O l
)
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j j j One shoreline sediment sample was collected on 11/01/88 and analyzed for Gross h Alpha (1.710.2 pCi/g), Cross Beta (1.71 0.1 pCi/g), Strontium-89 ( 0.3 pCi/g), and Strontium-90 ( 0.2 pCi/g). Gamma Spectralanalysis indicated the presence of I Cesium-137 (0.06 1 0.03 pCi/g). The levels of activity in the shoreline sediment i sample is consistent wih the previously accumulated data. 1 0 1 i 1 1 i 1 9 : l
)
l
TABLE XIV ' { l WASHLOAD SEDIMENT Sample i Collection Radiochemical Analysis pCi/g (dry) Identification - Date Gross Alpha Gross Beta Strontium-90 Strontium-89 CA-AQS-A 11/01/88 12.922.7* 10.021.0*- < 0.20 < 0.30 CA-AQS-C 11/01/88 15.622.9* 18.321.3* < 0.20 < 0.30 j CA-AQS-D 11/02/88 15.522.9* 12.81 1.l* < 0.20 < 0.30 J
- Quantity not sufficient for reanalysis.
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-4 TABLE XVI BEDLOAD SEDIME'NT Sample Collection Radiochemical Analysis pCi/g (dry)
Identification 'Date Gross Alpha Gross Beta Strontium-90 Strontium CA-AQS-A 11/01/88 'l .0 + 0.2 2.8+ 0.1 < 0;20 < 0.30: CA-AQS-C .11/01/88 1.010.2 2.50.1 1 < 0.20 . ' < 0.30 C A- A QS-D 11/01/88 3.00.5 1 3.10.2 2 < 0.20 < 0.30 '- i l O ; 1 0
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Sample Collection Radiochemical Analysis pCi/g (dry) -l Identificutloo _ Date Gross Alpha Gross Beta Strontium-90 Strontium CA-AQS A 11/01/88 .t . 3 + 0. 2 1.10.i 2 < 0.20 < 0.30 CA-AQS-C 11/01/88 1.5+ 0,2 1.1 + 0.1 < 0.20 < 0.30-
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l J l 8.6 Fish [] Fish were collected during the quarter from three locations. Types of fish collected during this quarter were: freshwater drum, carp, blue sucker, smallmouth buff alo, shorthead redhorse, white crappie, bigmouth buff alo, river i l carpsucker, channel catfish, white bass, blue catfish, largemouth bass, bluegill, , l y and gizzard shad. Gross Alpha, Gross Beta, Strontium-90, Strontium-89 and Gamma Spectralanalysis were performed on all fish collected each month. Results are presented in Tables XX thru XXV. The activity levels are consistent with the preoperational data. l l Gross Alpha activity during this quarter was all less than 0.3 pCi/g. Gross Beta activities ranged from a low of 2.9 0.1 1 pCl/g (sample CA-AQF-A, freshwater drum collected 10/20/88) to a high of 9.920.3 pCi/g (sample CA-AQF-C, gizzard O shea ceiiected 12/07/88). Gross Alpha and Gross Beta activities seen in fish samples can be attributed to naturally occurring isotopes (e.g. Potassium-40). All fish data for Strontium-90 and Strontium-89 were below the lower limits of detection of 0.20 pCi/g and 0.30 pCi/g, respectively. Results of Gamma Spectralanalysis may be found in Tables XXI, XXIII, and XXV. l O O
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n i o t d 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 ce e 8 8 8 8 8 8 8 8 8 8 8 8 8 8 8 t et /1 //// / / / / / ///// e t c 1 i 1 1 2 2 2 2 2 8 8 8 8 8 d ae 2 2 2 2 2 0 0 0 0 0 0 0 0 0 0 l / / / // / / / / / / //// . f Dlo 0 0 0 0 0 1 1 1 1 1 1 1 1 1 1 1 1 1 1 2 212 2 2 n o o 1 1 1 1 1 t C i t i ce mi o t l om o s. l a d e e r n h s l a ur h l a s hs ur mf f f w o s a u i i f f f D i f f B i o o eta h t u h f t u h f t D B t l mahn l pc s a B r s a B s a r h i i i C e i C t u s C et t mf f t h t a f t h o a u i ait a en u wh t a o l Ca e n uo m l l t t l B Sn C n o e n w m r s O d I e l e u h a ms p g e i r a r e a u h n mg p r g r e a a t i e p n h h ar ha e s a r l l e s w o L L
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1 j j i 8.7 Milk h
' Milk samples were collected from two locations, the Green Farm and the Schneider Farm. The Green Fa m supplies cow's milk while the Schneider Farm provides both cow's milk and goat's milk. Analyses for lodine-131, elemental Calcium, Strontium-90,' Strontium-89 and Gamma-emitting isotopes were performed on all milk samples. Tables XXVI'and XXVII present results of these '
analyses. No lodine-131 above the lower limit of detection (0.5 pCi/l) was detected in~ the milk samples during this period. Two (2) milk. samples collected during the fourth quarter were above the lower limit of detection of 1.0 pCdl for Strontium-90. No milk samples were above - the lower limit of detection of 2.0 pCi/l for Strontium-89. - No Gamma-emitting isotopes of interest were detected in any of the milk samples. - l l 0
1 I TABLE XXVI' FRESH MILK i l Radiochemical ; Collection Iodine-131 Calcium Strontium-90 Strontium-89 Date pCi/l mg/l oCi/l pCi/l j Green Farm (M-1) 10/11/88 < 0. 5 1770 '<l.0 < 2. 0
-{
11/08/88 < 0.5 1770 < l .0 < 2.0 l 12/12/88 < 0. 5 1180 < l .0 < 2.0 l 1 Schneider Farm (MSA) 10/08/88 < 0.5 870 1.60.7* < 2.0 2 11/06/88 < 0.5 870 < l.0 < 2.0 l 12/11/88 < 0.5 1660 < l.0 < 2.0 i i Schneider Farm (M5B) 10/08/88 < 0.5 1480 1.50.6* < 2.0 2 11/05/88 < 0.5 2340 < l.0 < 2.0 l
- Verified by reanalysis.
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c e m i lk i l i t e r l n M M d e o ow f o t i w a et a o o t l C mahn l i _ pc i m r G mf a r e r e i l t ai t F d d r S n e n i e i e e ss d I e e h n n we o L r h c c L
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- i 8.8 Vegetation Vegetation samples were col!+cted from three (3) sampling locations during the fourth quarter of 1988. Vegetation samples consisted of lettuce, mustard greens, 1
spinach, turnip greens and cabbage collected from the Beazley, Becker and l Meehan Farms. All vegetation samples were analyzed for Gross Alpha, Gross , Beta, fodine-131 and by Gamma Spectrometry. Results are presented in Tables f i XXVIII and XXIX. ' Gross Alpha activity ranged from less than the lower limit of detection (0.3 pCi/g), to a high of 1.2 0.2 1 pCi/g (Beazley Farm, mustard greens collected 10/25/88). This Cross Alpha ac.?ivity is consistent with the levels found during j l monitoring in previous years.
}
)
Gross Beta activity observed in the vegetation samples ranged from 9.310.2 l pCi/g to 25.910.3 pCi/g (Meehan Farm lettuce collected 11/13/88 and 10/25/88 respectively). No Gamma-emitting nuclides of interest were detected in the vegetation samples collected during the fourth quarter of 1988.
/'
G
l
, TABLE XXVIII l VEGETATION h-Sample Identification; Sample Radiochemical Analysis (pCi/g)
Date Collected Location Gross Alpha Gross Beta Iodine-131 CA-FPL-V3 Lettuce i 10/.25/88 Beazley Farm 1.0 220 21.1 13 0 < 0.03 C A-FPL-V 3 Cabbage ' 10/25/88 Pcazley Farm 0.7 120 12.7 120 < 0.03 CA-FPL-V3 Turnip Greens 10/25/88 Beazley Farm 0.7 220 14.9 12 0 < 0.03 C A-FPL-V3 Mustard Greens 10/25/88 Beazley Farm 1.2 220 21.9 13 0 < 0.03 C A-FPL-V3 Turnip Greens 11/18/88 Beazley Farm < 0. 3 15.8 12 0 < 0.03 g C A-FPL-V3 Mustard Greens 11/18/88 Beazley Farm < 0.3 13.1 12 0 < 0.03 C A-F PL-V6 4 Lettuce 10/25/88 Becker Farm 0.8 120 21.3 13 0 < 0.03 i C A-F PL-V 6 Cabbage 10/25/88 Becker Farm 0.3 11 0 11.4 12 0 < 0.03 C A-FPL-V6 Turnip Greens 10/25/88 Becker Farm 0.5 120 16.2 12 0 < 0.03 CA-FPL-V6 Mustard Greens 10/25/88 Becket Farm 0.6 120 12.9 12 0 < 0.03 CA-FPL-V6 Cabbage 11/18/88 Becker Farm < 0.3 12.8 12 0 <0.03 CA-FPL-V6 Mustard Greens h 11/18/88 Becker Farm < 0.3 10.9 12 0 <0.03 l l TABLE XXVIII (Cont.) , h VEGETATION i Sample Identification; Sample Radiochemical Analysis (pCi/g) . Date Collected Location __. Gross Alpha Gross Beta Iodine-131 1 CA-FPL-V6 Lettuce 11/18/88 Becker Farm < 0.3 12.2 32 0 < 0.03 ! CA-FPL-V6 Turnip Greens 11/18/88 Becker Farm < 0.3 13.7 12 0 < 0.03 i CA-FPL-V7 Cabbage 10/25/88 Meehan Farm 1.0 1 0.2 - 12.8 12 0 < 0.03 C A-FPL-V7 Lettuce 10/25/88 Meehan Farm 0.8 12 0 25.9 23 0 < 0.03 CA-FPL-V7 Spinach 10/25/88 Meehan Farm 1.0 32 0 24.7 23 0 < 0.03 CA-FPL-V7 Turnip Greens 10/25/88 Meehan Farm 0.8 12 0 15.5 12 0 < 0.03 CA-FPL-V7 i Mustard Greens j 10/25/88 Meehan Farm 23.9 1.0 3 0.2 23 0 .< 0.03 { CA-FPL-V7 Cabbage 11/18/88 Meehan Farm < 0.3 13.0 0.2 <0.03 C A-FPL-V 7 Mustard Greens 11/18/88 Meehan Farm < 0.3 9.9 12 0 < 0.03 CA-FPL-V7 ) Lettuce 11/18/88 Meehan Farm < 0.3 9.3 + 0.2 <0.03 CA-FPL-V7 Turnip Greens 11/18/88 Meehan Farm < 0.3 12.8 22 0 <0.03 j CA-FPL-V7 , Spinach ' 11/18/88 Meehan Farm < 0.3 11.7 22 0 < 0.03 s
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] 8.9 Soil Soil samples were collected from eleven (11) locations during the fourth quarter .
of 1988. Soil was analyzed for Gross Alpha, Gross Beta and Gamma activity. ( Results of these analyses are found in Tables XXX and XXXI. Cross Alpha activity ranged from a low of 1.530.2 pCi/g at Callaway Plant ( Prairie, Ecology Plot PR4 to a high cf 3.3 10.3 pC1/g at Callaway Plant Forest, ! Ecology Plot F6. 4 Gross Beta activity ranged from 1.01 0.1 pCi/g at Callaway Plant Prairie,
)
I Ecology Plot PR4 to a high of 3.42 0.1 pCi/g at the Hazlett Farm (CA-SOL-V3). l l Cesium-137 was detected in all soil samples collected during the fourth quarter O et i988. Cesicm-137 ectivity rensed from o.410.04 eCi/s to 1.55 0.o eCi/s. 1 1 No other isotopes of interest were detected in the soil samples. I O
s TABLE XXX h SOIL I Sample Identification; Radiochemical Analysis (pCi/g) j Date Collected Sample Location Gross Alpha Gross Beta CA-SOL-F1 11/22/88 Callaway Plant Forest 2.7 130 3.2 110 C A-SOL-F 2 11/22/88 Callaway Plant Forest 2.0 130 2.3 110 C A-SOL-F6 11/22/88 Callaway Plant Forest 3.3 130 3.3 110 CA-SOL-F8 I 11/22/88 Callaway Plant Forest 3.1 + 0.3 3.1 + 0.1 C A-SOL-F 9 11/22/88 Callaway Plant Forest 2.8 23 0 3.01 0 1 CA-SOL-PR3 ' 11/22/88 Callaway Plant Prairie 1.7 12 0 2.3 21 0 i CA-SOL-PR 4 l 11/22/88 Callaway Plant Prairie l 1.5 12 0 1.0 21 0 -] C A-SOL-PR 5 l 1!/h/38 Callaway Plant Prairie 2.0 13 0 2.6 11 0 C A-SOL-PR 7 11/22/88 Callaway Plant Prairie 2.0 13 0 2.6 21 0 C A-SOL-PR IO 11/22/88 Callaway Plant Prairie 3.0 + 0.3 3.2 + 0.1 CA-SOL-V3 ! 11/22/88 Hazlett Farm 2.0 130 3.4 11 0 O E_________-__..--- - - - - - - _ - - - - - - - - - - --- - - - ~ - ~ - ~ - ~ ~
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- 1?
~ l l o I l i APPENDIX A O EPA CROSS-CHECK RESULTS 1988 O t . .
O ee^ caoss-cuecx enoca^= 1988 Gross Alpha and Gross Beta in Water 1 EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a 'pCi/li 2 a 1/22 Gross Alpha 4+5 5+2 6+2 622 Gross Beta
- 8+5
~
30 + 2 3272 3422 3/12 Gross Alpha 625 512 f' 5+2 \ 6_72 Gross Beta 13 + 5
~
14 + 2 1572 17_27 5/20 Gross Alpha 11 2 5 812 _ 11 + 2 12_I2 Gross Beta 11 + 5
~
14 + 2 1672 18I2 7/22 Gross Alpha 15 + 5 8+2 9+2 10-1 2 Gross Beta 4+5 8+2 8+2 8_72 O ae " air i a6* i"ed >" e' <*. 25. 25 (' = i') i itiei QA glassware having beta contamination.
>"e= ~ere **e re="it e' i
EPA CROSS-CHECK PROGRAM h 1988 Gross Alpha and Gross Beta in Water (Cont.) EPA CEP Known Value Reported Value Date Parameter pCi/li 1 a pCi/li 2 o 9/23 Gross Alpha 85 8+2 9+2 9[2 Gross Beta 10 + 5
- 12 + 2 13]2 14 2 2 11/25 Gross Alpha 9+5
- 8+2 922 10 2 2 Gross Beta 9+5 10 + 2 1172 12_I2 i
O
1 EPA CROSS-CHECK PROGRAM ,J O 1988 - l Gamma in Water l j
.]
EPA CEP Known Value Reported Value i Date Parameter pCi/li 1 a pCi/li 2 a 2/5 Cobalt-60 69 + 5~ 56 + 5 6275 68 _I 5 Zinc-65 94 + 9.4
~
81 + 6
~
86_ 6 91 3 6 Ruthenium-106 105 + 10.5 88 + 5 96 + 5 104- 35 Cesium-134* 64 + 5~ 47 + 3 p $4 75 V 59 I 5 Cesium-137 94 + 5 77 + 5 ! 89 + 5 l 92 I_ 5 l
.)
t 6/3 Chromium-51 *
- 302 + 30 210 + 15 220715
~
240 + 15-l Cobalt-60 15 + 5 8+15 11 ~+ 15 13_15 Zinc-65* *
- 101 + 10 119 + 15 l 123 + 15 127 1 15 Ruthenium-106 195 2 20 146 2 15 153 + 15 l 176_715
- Values of 58, 58, and 61 (x = 59) should have been reported. Onitial values reported before analysis was complete.)
**Mean of all Chromium-51 analyses w:s 257 2, 15. Omproper computation of original mean.)
*** Review of data indicated a value of 98 + 15 for Zinc-65. (No reason found for original high results.)
l _A_.- -.._.__--____----_u------ - _ _ - - - _ _ - - - - _ - - -
EPA CROSS-CHECK PROGRAM h 1988 j Gamma in Water (Cont.) l l EPA CEP ! Known Value Reported Value 1 Date Parameter pCi/li i s pCi/li 2 s 6/3 Cesium-134 20 + 5 20 + 15 26 ~'15 271!5 Cesium-137 25 + 5 19 + .15 26 + 15 27115 10/7 Chromium-51
- 251 + 25 196 + 19 200 + 20 l 201 1 ~ 22 Cobalt-60 25 + 5 22 + 2 23_7 2 24 3 2 Zinc-65 151 + 15
~
128 + 3 12973 i 13473 _ i Ruthenium-106* 152 + 15 115 + 15 119 + 16 125i15 l Cesium-134 25 + 5 22 + 2 22 + 2 227_2 Cesium-137 15 + 5
~
13 + 2 1372 1412
- Insufficient volume available for analysis of 1.0 liter resulted in all values being lower than actual values. All client samples use 1.0 liter and therefore, do not require geometry corrections.
O l- , 1 O sea Caoss-C"eCx enoca^= 1988' Tritium in Water EPA CEP' Known Value Reported Value - Date Parameter pCi/li 1 a pCi/li 2 a 2/88 Tritium 3327 + 362 2760 + 300 2994 + 300
.30625300.
6/88 Tritium 5565 + 557
^
4800 + 500 50007 500 52002500 10/14 Tritium 2316 + 350 2393 + 500 24837500 0 ' 2573_I500 l l i O
_ _ _ _ _ - - _ _ _ _ _ _ _ _ _ _ = _ _ i l 4 EPA CROSS-CHECK PROGRAM .h 1988 I i Strontium in Water 1 1 j l EPA CEP i Known Value Reported Value Date Parameter pCi/li 1 a pCi/li 2 o ] j l 1/8 Strontium-89 30 + 5 30 + 5 { 35 + 5 40 I _5 Strontium-90* 15 + 2
~
9+2 - l1 + 2 1172 ~ 1 5/6 Strontium-89 20 + 5 20 + 3 l i l 2113 l 22 1 3 Strontium-90 20 + 2 18 + 2 ) 19 + 2 l 20[2
- Review of calculations indicated that values of 15,14, and 18 (Y = 16) should have been reported. (Original results were result of miscalculation.) I I
i l
h h EPA CROSS-CHECK PROGRAM 1988 l 1 l Iodine-131 in Water
.' {
EPA CEF ! Known Value Reported Value Date Parameter pCi/li 1 a pCi/li 2 a 4/8 Low Level 7.50 + 0.75
~
6 + 4' 974 9i4 8/5 ' High Level 76 2 8 76 3 8 81 + 8 85 i 8 12/9 High Level - 115 + 12 99 + 9 O 104 + 12 109_+ 7 i a l l l l i i 1 0
EPA CROSS-CHECK PROGRAM 1988 lodine-131 in Milk EPA CEP Known Value Reported Value - 4 Date Parameter pCi/11 I a pC1/112 a 2/26 Low Level 4.0 + 0.4 3.0 + 0.7
'4.0 + 0.7 4.0 17 0 l l
1 l ga l - O
g EPA CROSS-CHECK PROGRAM 1988 Radionuclides in Food EPA CEP Known Value Reported Value Datt Parameter pCi/kg t I s pCi/kgi 2 s 1/29 Strontium-89 46 3 5 Not Reported Strontium-90 55 2 3 Not Reported lodine-131 1024~ 10 101 + 25 107725
~
111 2 25 Ceslum-137 91 + 5 81 + 10 91 + 10 98110 h Potassium 1230 3 62 mg/kg 1320 i 132 mg/kg 1320 f 132 mg/kg 1320 2 132 mg/kg 7/29 Strontium-89* Not Reported 33 2 5 Strontium-90* 34 22 Not Reported lodine-131 107 + 11
- 91 + 4 104 - 5 119 i 5 Cesium-137* 49 2 5 Not Reported Potassium 1240 + 62
- 1200 + 120 12257120 1250 2~ 120
- Values : ot reported due to contamination of samples discovered during analysis.
Insufficient time and sasnple remaining for reanalysis. O
1 l q i SECTION 4.0
,l UNION ELECTRIC COMPANY CALLAWAY PLANT NONRADIOLOGICAL ENVIRONMENTAL MONITORING 1988
.l i
i i i
()
1.0 INTRODUCTION
During 1988 there was no nonradiological environmental monitoring conducted in the. vicinity of the Callaway. Plant. This is in agreement with Section 4.2 of Appendix B of the q Callaway Plant Operating License. Section 4.2 requires j aerial photographic monitoring during the first July 15 - September 15 period after the plant has been in operation for one year and once the following year and alternate years q for three additional periods. The aerial photographic monitoring was conducted during 1986 and 1987 which satisfied the first two requirements and will be conducted during 1989,-1991, and 1993 to satisfy the last requirement. l l l l l i O
j O !
)
I i SECTION 5.0 UMION ELECTRIC COMPANY CALLAWAY PLANT PLANT MODIFICATION ENVIF.ONMENTAL EVALUATION 1988 i l I i i
l
,/D
1.0 INTRODUCTION
qi In accordance with Appendix B, Section 5.4.1 of the Callaway Plant Operating License, the following report I was prepared by Union Electric on all changes in plant design, operation, tests or experiments which involved a potentially significant unreviewed environmental question in accordance with Section 3.1 of Appendix B. The report covers all plant modifications / changes that were completed from January 1, 1988, through December 31, 1988. I i During 1988 there were eleven plant modifications / l changes that involved a potentially significant unreviewed environmental question. The interpretations and conclusions regarding these plant , modification / changes along with a description of the ; changes are presented below. l 2.0 _E_N_VIRONMENTAL EVALU ATIONS 2.1 Callaway Modification Package 86-1018 ) j 2.1.1 Description of Change
/^N This change revised the necessary documentation to
() J allow uprating the Callaway Plant from 3411 MWt core j power (3425 MWt NSSS) to 3565 MWt core power (3579 MWt NSSS). This uprated power represents an increase of 4.5% and is equivalent to the Engineered Safety i Features Design Rating of the Callaway Plant. l l l 2.1.2 Evaluation of Change i i This change did not result in significant adverse i environmental impact, nor a significant increase in effluents, nor an adverse land or cultural resource altering activity. The original licensing evaluations for the Callaway Plant, including the NRC Environmental i Evaluations (Ref. NUREG-75/013, 3/75, Section 1.1), l were based on a NSSS thermal power level of 35P3 MWt. Therefore, the uprating remained within the bounds of the original environmental analysis and does not constitute an unreviewed environmental question per Section 3.1 of Appendix B tc the Callaway Plant Operating License.
l 2.2 Callaway Modification Packuge 87-1002 g 2.2.1 Description of Change This change provided a vent header from eight high pressure nitrogen relief valves in Area 5 to the Atmosphere. This change prevents Area 5 from becoming an oxygen deficient area when these valves relieve. 2.2.2 Evaluation of Change l l Releases from the Nitrogen Back-up Gas Supply System are not addressed in the Callaway Plant Environmental Report or Final Environmental Statement - Operating License Stage. However, the release of small quantities of nitrogen gas is not considered significant and is not regulated by any State or Federal agency. Therefore, this change does not constitute an unreviewed environmental question per Section 3.1 of Appendix B to the Callaway Plant Operating License. 2.3 Callaway Modification Package 87-1091. 2.3.1 Description of Change [ This change permanently eliminated oily waste Outfall 005 and removed the installed PVC piping, pumps and ll) filtration system. 2.3.2 Evaluation of Change This change involved the elimination of the oily waste Outfall 005. No changes were made in the treatment of this effluent, however the outfall was routed to the equalization basin and lagoon number 1 and be utilized as makeup to the cooling tower. This change did not result in any significant increase in any adverse environmental impact above that previously evaluated. : Therefore, this change does not constitute an unreviewed environmental question per Section 3.1 of ; Appendix B of the Callaway Plant Operating License. { I 2.4 Callaway Modification Package 87-3005 l 2.4.1 Descri.ption of Change This change involved the installation of Guard Booths ; located inside and outside of the plant security fence.
() 2.4.2 Evaluation of Change i The installation of the guard booths did not result in a significant increase in any adverse environmental impact, since all measurable nonradiological environmental effects were confined to the areas previously disturbed during site preparation and plant construction. Therefore, this change does not constitute an unreviewed environn. ental question per Section 3.1 of Appendix B to the Callaway Plant Operating License. 2.5 Callaway Modification Package 87-3048 1 2.5.1 Description of Change This change involved the construction of a plant viewing area / shelter with access road, parking and turn around area. The plant viewing area is located next to the plant operations road west of the employee parking lot. 2.5.2 Evaluation of Change The construction of the plant viewing area did not result in a significant increase in any adverse () environmental impact, since all measurable nonradiological environmental effects were confined to the area previously disturbed during site preparation and plant construction. Therefore, this change does not constitute an unreviewed environmental question per Section 3.1 of Appendix B to the Callaway Plant Operating License. 2.6 Request for Resolution 04799 2.6.1 Description of Change This change addressed the use of smaller micron size filter cartridges in the various radwaste filter units. This change reduced the amount and size of particulate l entering the radwaste discharge monitor from the plant discharge line, thus reducing the particulate plateout inside the sampling chamber. 1.6.2 Evaluation of Change The reduced micron size filter cartridges resulted in a reduction in the size and concentration of particulate in the liquid effluent. This change did not result in a significant increase in any adverse environment impact above that previously evaluated. Therefore, O~' this change does not constitute an unreviewed environmental question por Section 3.1 of Appendix B to the Callaway Plant Operating License.
l 2.7 Request for Resolution 04940 gg 2.7.1 Descri_ption of Change The railroad rails, floor drains and blackouts in the Railroad Access Area of the Fuel Building and the Turbine Building have been grouted flush to design elevation. Also, the railroad tracks leading'to the Turbine Building have been removed. This change eliminates the tripping hazard associated with the railroad rails which are not used. 2.7.2 Evaluation of Change The removal of the railroad rails, floor drains and blockouts did not result in a significant increase in any adverse environmental impact, since all measurable nonradiological environmental effects were confined.to the areas previously disturbed during site preparation and plant construction. Therefore, these changes do not constitute an unreviewed environmental question per Section 3.1 of Appendix B to the Callaway Plant Operating License. 2.8 Request for Resolucion 05191 2.8.1 Description of Change lll This change involve une installation of two cinder block bunkers side by side for salt and sand storage located plant south of the Daniel Fabrication Shop. This change will allow for containing and covering the winter supply of salt and sand used for ice and snow removal. 2.8.2 Evaluation of Change The construction of the two cinder block bunkers did not result in a significant increase in any adverse environmental impact, since all measurable non-radiological environmental effects were confined to the areas previously disturbed during site preparation and plant construction. Therefore, this change does not constitute an unreviewed environmental question per Section 3.1 of Appendix B to the Callaway Plant Operating License. 2.9 Temporary Modification TM-88-M005 2.9.1 Description of Change This temporary modification provided a nitrogen supply for air inleakage testing and condenser hotwell sparging. This change will help reduce the dissolved oxygen concentration in the condenser condensate during operation. 4_ N
2.9.2 Evaluation of Change The operation of this temporary modification could involve the release of approximately 2 to 3 scfm of nitrogen gas from the condenser. Nitrogen is a major constituent of the normal atmosphere, is not an EPA priority pollutant, and has no regulatory release limit. The release of small quantities of nitrogen would not result in a significant adverse environmental impact. Therefore, this change does not constitute an unreviewed environmental question per Section 3.1 of Appendix B of the Callaway Plant Operating License. 2.10 Te.mnorary Modification TM-88-M016 2.10.1 D_escription of Change This change involved the installation of a 6,000 gallon sodium hypochlorite storage tank and associated piping between the storage tank and water treatment plant clarifiers. This change allows for chlorination of water treatment plant clarifiers to reduce algae growth. 2.10.2 Evaluation of Change () Although this particular chlorination point was not specifically discussed in the Callaway Plant Final Environmental Statement - Operating License Stage (FES-OL) NRC staff did evaluate a maximum chlorine concentration of 0.5 mg/l in the discharge per FES-OL Section 4.2.6.1. Since NPDES limits of 0.5 mg/l maximum concentration will still be met with Temporary Modification TM-88-M016, no significant increase in any adverse environmental impact previously evaluated will take place. Therefore, this change does not constitute an unreviewed environmental question per section 3.1 of Appendix B of the Callaway Plant Operating License. 2.11 Site Restoration - Excavated Material Stockpiles 2.11.1 Description of Work l l There are several excavated material stockpiles located around the site. Appendix 4A, Section 2.1.2 of the Environmental Report - Op6 rating License Stage states that " . excavated material will be spread and seeded." While the stockpiles are spread somewhat, they do not conform to the existing contour of the land. UE proposed to leave the stockpiles as they are due to the expense of earth moving activities required-O to further spread the stockpiles and due to the fact that the existing stockpiles do not increase any adverse environmental impact.
l 2.11.2 Evaluati_on of Change ggg This change will not result in removal of any ' cdditional productive land from use. The disturbed - areas are confined to the on-site areas previously ] ' disturbed during site preparation and plant construction. Use of these on-site areas was previously evaluated by NRC in Section 4 2.1 of ( MUREG-75/Oll, Final Environmental Statement - Construction Permit Stage. The Staff concluded that removal of this land would not constitute a i significantly adverse impact in the large, predominantly rural region covering several counties. The excavation stockpiles are currently in a state where native plants are sufficiently established to maincain a natural cover. This cover and the slopes of , the stockpiles are such that no accelerated erosion is ) expected as a consequence of the existence of the j stockpiles. While some areas of mild erosion do exist, ) most runoff from the excavation stockpiles is collected in site-area settling ponds. The stockpiles do not ; affect local surface water drainage outside the site ' area. I l There are no cultural resources in the area. ] This change will not result in a significantly greater adverse impa c t- than that previously evaluated by NRC. l Therefore, this change does not constitute an unreviewed environmental question per Section 3.1 of Appendix B of the Callaway Plant Operation License. i l i l l l l l l \ llh l 6- 1
_ _7
* )
I901'Gratlue Sueet .1
' i
.,. J Post Office Box I49 e* St. Louis. MissouriG31CG .
314-554 2660
. Gygoy conata.sa,nen Euccnuc. '
April'28,.1989
- '3' ;
1 U. .S. Nuclear.. Regulatory Commission -!
' Document Control Desk .i' Washington, D.C. 20555 Gentlemen:- ULNRC- 1994 DOCKET NUMBER 50-483 I CALLAWAY PLANT-FACILITY OPERATING LICENSE NPF 1988 ANNUAL ENVIRONMENTAL OPERATING REPORT Please find enclosed the 1988 Annual Environmental Operating Report for the Callaway Plant. .-This report is submitted in accordance with section 6.9.1.6 of the Technical Specifications and Appendix B to the Callaway Plant Operating License.
Ver truly rs, .. Donald F. 'c nell-BFH/bjs Enclosure l l f-: t i b i 1
cc: Gerald Charnoff, Esq. Shaw, Pittnan, Potts & Trowbridge 2300 N. Etteet, N.W. Washington, D.C. 20037 Dr. J. O. Cermak CFA, Inc. 4 Professional Drive (Suite 110) Gaithersburg, MD 2087 R. C. Knop 1 Chief, Reactor Project Branch 1 U.S. Nuclear Regulatory Commission Region III 799 Roosevelt Road l Glen Ellyn, Illinois 60137 l l Bruce Little i Callaway Resident Office U.S. Nuclear Regulatory Commission RR#1 Steedman, Missouri 65077 Tom Alexion (2) Office of Nuclear Reactor Regulation [ U.S. Nuclear Regulatory Commission l 1 White Flint, North, Mail Stop 13E21 11555 Rockville Pike Rockville, MD 20852 Manager, Electric Department ' Missouri Public Service Commission P.O. Box 360 Jefferson City, MO 65102 Bill Kesler Regional Administrator Jefferson City Regional Office Dept. of Natural Resources P.O. Box 1368 Jefferson City, MO 65102}}