ML20238D824
| ML20238D824 | |
| Person / Time | |
|---|---|
| Site: | North Anna  |
| Issue date: | 12/31/1986 |
| From: | TELEDYNE ISOTOPES MIDWEST LABORATORY, VIRGINIA POWER (VIRGINIA ELECTRIC & POWER CO.) |
| To: | |
| Shared Package | |
| ML20238D809 | List: |
| References | |
| NUDOCS 8709110418 | |
| Download: ML20238D824 (155) | |
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VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM I FOR 1986 - i Prepared by VIRGINIA ELECTRIC AND POWER COMPANY and TELEDYNE IS0 TOPES Of0YD
ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPOR, { l NORTH ANNA POWER STATION JANUARY 1, 1986 to DECEMBER 31, 1986 1 l: i i 1 l l p Reviewed by: /J/ 8 a d Assistant Supervisor Health Physics (Count Room and i Environmental) f Reviewed by: ,MM- -
,A-Supervisor ealth Physics (Technical Services)
}- Reviewed by: / nysics auperrnteppntseei Approved by: A _St aTTUn ger "/
TABLE OF CONTENTS SECTION TITLE PAGE I. INTRODUCTION............... ................................ 1 II. SAMPLING AND ANALYSIS PR0 GRAM............................... 5 III. PR OGR AM E XC E PT I ON S . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 19 I 1 IV.
SUMMARY
AND DISCUSSION OF 1986 ANALYTICAL RESULTS.......... 23 A. AIRBORN E EXPOSURE PATHWAY. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 24 1
- 1. Air Iodine / Particulate............................ 24
- 2. Precipitation...................................... 41
- 3. 50i1...............................................44 B. WATERBORNE EXPOSURE PATHWAY............................ 48
- 1. Ground /Well Water.................................. 48
- 2. River Water........................................ 51
- 3. Surface Water...................................... 54 C. AQUATIC EXPOSURE PATHWAY............................... 60
- 1. Sediment / Silt...................................... 60
- 2. Shoreline 5011..................................... 67 D. ING2STION EXPOSURE PATHWAY............................. 70
- 1. Milk............ ................................. 70
- 2. Fish...............................................76
- 3. Terres tri al Veget at i on . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 7 9 E. DIRECT RADIATION EXPOSURE PATHWAY...................... 82
- 1. TLD Dosimeters...................................... 82 V. CONCLUSION.................................................90 VI. 1986 LAND USE CENSUS....................................... 96 VII. SYN 0PSIS OF ANALYTICAL PROCEDURES......................... 100 VIII. EPA INTERLABORATORY COMPARIS0N PROGRAM.................... 111 IX. REFERENCES......... ...................................... 146 i
l TABLE OF CONTENTS (Cont) LIST OF FIGURES l
- 1. ENVIRONMENTAL SAMPLING LOCATIONS.... ...................... 15
- 2. LAND USE CENSUS MAP........................................ 99 s
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FORWARD This report is submitted as required by Technical Specification 6.9.1.8, Annual Radiological Environmental Operating Report for North Anna Power Stations Units 1 and 2, Virginia Electric and Power Company Docket Nos. 50-338 and 50-339. , , i 9 5 t O 4 ( iii k
I ' N N N l l e
- 1. INTRODUCTION ,
Y
VIRGINIA ELECTRIC AND POWER COMPANY NORTH ANNA POWER STATION RADIOLOGICAL ENVIRONMENTAL OPERATING PROGRAM I. INTRODUCTION The operational radiological environmental monitoring program conducted for the year 1986 for the North Anna Power Station is provided in this report. The results of measurements and analyses of data obtained from i samples collected from January 1,1986 through December 31, 1986 is stmmarized. A. The North Anna Power Station of Virginia Electric and Power Company is located on Lake Anna in Mineral, Virginia, approximately 35 miles west of Fredericksburg, Virginia. The site consists of two units, each with pressurized water reactor (PWR) nuclear steam supply systems and turbine generator furnished by Westinghouse Eled ric Corporation. Each unit is designed with a gross electrical output of 970 megawatts electric (MWe). Unit I achieved commercial opera-tion on June 6, 1978, and Unit 2 on December 14, 1980. B. The United States Nuclear Regulatory Commission (USNRC) regulations (10CFR50.34a) require that nuclear power plants be designed, con-structed, and operated to keep levels of radioactive material in effluents to unrestricted areas as low as reasonably achievable (ALARA). To ensure these criteria are met, the operating license 1 for North Anna Power Station includes Technical Specifications which govern the release of radioactive effluents. Inplant monitoring is l used to determine that these predetermined release limits are not exceeded. As a precaution against unexpected or undefined 2
environmental processes which might allow undue accumulation of radioactivity in the environment, a program for monitoring the plant environs is also included in North Anna Power Station Technical Specifications. C. Virginia Electric and Power Company is responsible for collecting the various indicator and control (background) environmental samples. l Teledyne Isotopes is responsible for sample analysis and the submission of reports of radioanalyses. The results are used to determine if changes in radioactivity levels could be attributable to station operations. Measured values are compared with background levels, which vary with time due to such external events as cosmic ray bombardment, weapons test fallout, and seasonal variations of naturally occurring isotopes. Data collected prior to the plant operation is used to indicate the degree of natural variation to be expected. This preoperational data is compared with data collected during the operational phase to assist in evaluating the radiological impact of the plant operation. D. Occasional samples of environmental media show the presence of man-made isotopes. As a method of referencing the measured radio-nuclide concentrations in the sample media to a dose ccmsequence to man, the data may be compared to the reporting level concentrations listed in the USNRC Regulatory Guide 4.8 and Table 4.12-2 of North Anna's Technical Specifications. These concentrations are based upon the annual dose commitment recommended by 10CFR50, Appendix I, to meet ti,e criterion of "As Low As Is Reasonably Achievable". 3
E. This report documents the results of the Radiological Environmental Monitoring Program for 1986 and satisfies the following objectives of the program: !
- 1. To provide measurements of radiation and of radioactive materials in those exposure pathways and for those radionuclides that lead to the highest potential radiation exposure of the maximum exposed members of the public resulting from the station operation.
- 2. To supplement the radiological effluent monitoring program by verifying that radioactive releases are within allowable limits.
- 3. To identify changes of radioactivity in the environment.
- 4. To verify that the plant operations have no detrimental effect on the health and safety of the public.
4
II. SAMPLING AND ANALYSIS PROGRAM A. Sampling Program
- 1. Table 1 summarizes the sampling program for North Anna Power Station during 1986. Figure 1 indicates the i locations of the environmental monitoring stations.
- c. For routine TLD measurements, two dosimeters made of CaSO 4 :0y in a teflon card are deployed at each sampling location. Sevee,0 TL0s are co-located with NRC and Common-l wealth of Virginia direct radiation recording devices.
These are indicated as "co-location" samples.
- 3. In addition to the Radiological Environmental Monitoring Program required by North Anna Technical Specifications, Virginia Electric and Power Company splits samples with the Commonwealth of Virginia. All samples listed in Table 1 are collected by Vepco personnel except for those labeled state split. All samples are shipped to Teledyne Isotopes $n Westwood, New Jersey,
- 4. All samples listed in Table 1 are taken at indicator loca-tions except those labeled " control".
l l l 5
B. Analysis Program
- 1. Table 2 summarizes the analysis program conducted by Teledyne Isotopes for North Anna Power Station during 1986.
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TABLE 2 (Page 1 of 3) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLO* REPORT UNITS Thermoluminescent mR/ month Dosimetry (TLD) Quarterly Gamma Dose (84 routine station TLD's) 12 station TLD's Annually Gamma Dose mR/ month Airborne Weekly I-131 0.07 pCi/m3 Radioiodine Airborne Weekly Gross Beta 0.01 pCi/m3 Particulate Quarterly (1) Gamma Isotopic pCi/m3 Cs-134 0.05 Cs-137 0.06 Surface Water Monthly Gamma Isotopic pCi/E Mn-54 15 Fe-59 30 Co- 58,60 15 Zn-65 30 Zr-Nb-95 15 I-131 10 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly (1) Tritium (H-3) 130 pCi/t (1) Quarterly Composites of each location's samples will be used for the required analysis.
- LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environ-mental Program. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed.
12
TABLE 2 (Page 2 of 3) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM l SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS River L'ater Quarterly Gamma Isotopic pCi/f Mn-54 15 Fe-59 30 Co-58,60 15 Zn-65 30 Zr-Nb-95 15 I-131 10 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (H-3) 130 pCi/E Ground Water Quarterly Gamma Isotopic pCi/E (Well Water) Mn-54 15 Fe-59 30 t Co-58,60 15 i Zn-65 30 Zr-Nb-95 15 I-131 10 Cs-134 15 Cs-137 18 Ba-La-140 15 Quarterly Tritium (H-3) 130 pCi/E Aquatic Semi-Annually Gamma Isotopic pCi/kg (dry) Sediment Cs-134 150 Cs-137 180
- +
Shoreline Semi-Annually Gcmma Isotopic pCi/kg (dry) , Soil Cs-134 150 Cs-137 180 Soil Once per 3 yrs. Gamma Isotopic pCi/kg (dry) Cs-134 150 Cs-137 180 LLD's indicate those levels that the environmental samples should be , analyrea to, in accordance with the North Anna Radiological Environ-mental Progran. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed. 13
TABLE 2 (Cont.) (Page 3 of 3) NORTH ANNA POWER STATION SAMPLE ANALYSIS PROGRAM SAMPLE MEDIA FREQUENCY ANALYSIS LLD* REPORT UNITS Milk Monthly I-131 1.0 pCi/f Monthly Gamma Isotopic pCi/f Cs-134 15 Cs-137 18 Ba-La-140 15
~
Fish Semi-Annually Gamma Isotopic pCi/kg (wet) (Quarterly- Mn-54 130 interim period) Fe-59 260 Co-58,60 130 Zn-65 260 Cs-134 130 Cs-137 150 Food Products Monthly if Gamma Isotopic pCi/kg (wet) (Broadleaf available or Vegetation) at harvest Cs-134 60 Cs-137 80 1-131 60 pCi/kg (wet) , NOTE: This table is not a complete listing of nuclides which can be detected , and reported. Other peaks that are measurable and identifiable, together
- with the above nuclides, shall also be identified and reported.
- LLD's indicate those levels that the environmental samples should be analyzed to, in accordance with the North Anna Radiological Environmental Progr am. Actual analysis of the samples by Teledyne Isotopes may be lower than those listed, t 4 1 14
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l ) 1 LEGEND FOR THE NORTH ANNA POWER STATION ENVIRONMENTAL MONITORING STATT.ONS OVERVIEW MAPS (FIGURES 1, 2, 3) l MAP ENVIRONMENTAL STATION MAP ENVIRONMENTAL STATION [ DESIGNATION IDENTIFICATION DESIGNATION IDENTIFICATION l 1 N-1/33 23 WSW-23/55 i
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i l 1 III. EXCEPTIONS 1 l l 1 l I i 19
f III. PROGRAM EXCEPTIONS During the environmental reporting period, three samples were not available and several analyses of samples did not meet the requireo sensi-tivity(LLD). The following is a discussion of the exceptions and actions taken to limit re-occurrence. Two air iodine / particulate samples were lost, one due to a sampler being unplugged and another due to a timer malfunction. Another was lost due to insufficient volume and a fourth caused by a lab technican error. A precipitation sample was not available due to insufficient rainfall. Two ground /well water samples failed to meet the LLO for I-131 due l to an oversight by TI. Surface water samples are collected by the Commonwealth of Virginia on a monthly basis from two stations. The analyses for barium /lanthanium-140, and I-131 failed to meet the required Lower Limit of Detection (LLD) in several cases due to delay in receipt of samples from the State of Virginia. There were six food / vegetation samples that failed to meet the required l LLD for I-131 due to an oversight by TI. An automatic flagging system is being established for improving the review of LLD requirements. The computer will automatically flag a sample that failed to meet the LLD Tech Spec requirements. l 20
j l REMP EXCEPTIONS FOR SCHEDULED 1 SAMPLING AND ANALYSIS DURING 1986 - NORTH ANNA j i i j Date of Reason (s) for Loss / Location Description Sampling Exception 05 Air Particulate / 10/21/86-10/28/86 Sampler unplugged; no Air Iodine sample available. 22 Air Iodine 11/12/86-11/18/86 Sample lost while technican was perform-ing the analysis. 02 Air Particulate / 12/02/86-12/09/86 Timer malfunctioned; Air Iodine no sample available. 07 Air Particulate / 12/16/86-12/23/86 Insufficient volume; Air Iodine no sample available. l 01 Gross Beta / Tritium 01/01/86-01/31/86 Insufficient rainfall; Gamma in Precipitation no sample available. ! 4 01A Gamma in Ground /Well 06/30/86 LLD For I-131 not met Water due to heavy work load from the Chernobyl accident. Priority was given to sample media which were affected by the accident. < 01A Gamma in Ground /Well 12/30/86 LLD for I-131 was not Water met due to an oversight by TI. W-27 Gamma in Surface 02/14/86-03/14/86 LLD for I-131 could Water 03/15/86 not be met due to long 04/15/86 lapse of time from 05/15/86 collection to receipt 06/15/86 at TI. 08/15/86 09/15/86-10/10/86 I 11/15/86 12/15/86 21
l [ I REMP EXCEPTIONS FOR SCHEDULED SAMPLING AND ANALYSIS DURING 1986 - NORTH ANNA (Cont.) i l Date of Reason (s) for Loss / l Location Description Sampling Exception W-27 Gamma in Surface 03/15/86 LLD cou M not be met Water 04/15/86 for Pa/ La-140 due to 05/15/86 long lapse of time from 06/15/86 collection to receipt 08/15/86 at TI. 11/15/86 12/15/86 i W-33 Gamma in Surface 03/15/86 LLD for I-131 could Water 04/15/86 not be met due to long l 05/15/86 lapse of time from i 06/15/86 collection to receipt 08/15/86 at TI. i 09/15/86-10/10/86 ! 11/15/86 12/15/86 W-33 Gamma in Surface 03/15/86 LLD could not be met l Water 04/15/86 for Ba/La-140 due to l 05/15/86 long lapse of time from. 06/15/86 collection to receipt 08/15/86 at TI. 11/15/86 12/15/86 14 Gamma in Food / 05/30/86 LLD could not be met Vegetation for 1-131 due to an oversight by TI. 15 Gamma in Food / 06/30/86 LLD could not be met Vegetation for I-131 due to an oversight by TI. 21 Gamma in Food / 05/30/86 LLD could not be met < Vegetation for 1-131 due to an oversight by TI. 22 C______
I l i l REMP EXCEPTIONS FOR SCHEDULED ! l i l SAMPLING AND ANALYSIS DURING 1986 - NORTH ANNA (Cont.) 1 Date of Reason (s) for Loss / Location Description Sampling Exception 23 Gamma in Food / 05/30/86 LLD could not be met Vegetation for 1-131 due to an oversight by TI. 92 Gamma in Food / 07/04/86 LLD could not be met Vegetation for I-131 due to an oversight by TI. 98 Gamma in Food / 07/04/86 LLD could not be met , Vegetation for I-131 due to an ' oversight by TI. l 22a
1 I i l l i il 1 IV.
SUMMARY
AND DISCUSSION OF i 1986 ANALYTICAL RESULTS I i 23
i l I 1 l IV.
SUMMARY
AND DISCUSSION OF 1986 ANALYTICAL RESULTS ) i 1 i Data from the radiological analyses of environmental media collected during the report period are tabulated and discussed below. The procedures and specifications followed in the laboratory for these analyses are as I required in the Teledyne Isotopes Quality Assurance Manual and are explained in the Teledyne Isotopes Analytical Procedures. A synopsis of analytical procedures used for the environmental samples is provided in Section VII. In addition to internal quality control measures performed by Teledyne, the laboratory also participates in the Environmental Protection Agency's Interlaboratory Comparison Program. Participation in this program ensures 1 that independent checks on the precision and accuracy of the measurements of l radioactive material in environmental samples are performed. The results of i 1 tre EPA Interlaboratory Comparison are provided in Section VIII. Radiological analyses of environmental media characteristically approach and frequently fall below the detection limits of state-of-the-art measure-ment methods. Teledyne Isotopes analytical methods meet the Lower Limit of , Detection (LLD) requirements given in Table 2 of the USNRC Branch Technical Position of Radiological Monitoring (November 1979, Revision 1). The following is a discussion and summary of the results of the environmental measurements taken during the reporting period. A. Airborne Exposure Pathway
- 1. Air Iodine / Air Particulate On April 25,1986 at 1725 hours EST there was a Russian nuclear reactor accident at Chernobyl . Sufficient quantities of radioactivity were released into the atmosphere so that various radioisotopes were 24
i measured in certain sample media collected at all the commercial nuclear utilities in the U.S. for which Teledyne Isotopes provides environmental anal3 tical services. At the North Anna Power Station the radioactivity I l was first detected during the week beginning Fay 5, 1986. Elevated gross { l beta activity levels in weekly air particulate were measured from May 5 i i through June 10. The second quarter composite (by sampling location) in air particulate analyzed by gamma ray spectroscopy had measurable levels of f ruthenium-103, cesium-134, and cesium-137. Iodine-131 was measured in weekly charcoal cartridges from May 5 through June 10. Iodine-131 was also measured in milk samples collected between May 9 and June 10. i Results of airborne iodine-131 analyses of charcoal cartridges are presented in Table 4 Iodine-131 attributable to the Chernobyl accident, was detected in all twelve sampling locations during the three week period May 6 through May 27. The average concentration per week was 0.21, 0.056, and 0.049 pCi/m3 . In subsequent weeks as the iodine-131 continued to decrease due to radioactive decay and atmospheric mixing, the concentrations dropped below the detection limit. During the week of May 27 to June 4, iodine-131 was detected in three sampling locations with an average activity of 0.029 pCi/m3 During the week of June 3 to June 10, iodine-131 was detected in only one sampling location with an average activity of 0.044 pCi/m3 . There was no statistical difference of the average of the weekly iodine-131 results of the eleven indicator locations compared to the control location. During the same five week period of May 6 through June 10 elevated gross beta activities at all twelve sampling locations were measured with weekly average concentrations of 0.206, 0.080, 0.103, 0.093 and 0.050 25
pCi/m3 . For the week of highest gross beta activity the individual j sampl.ing locations had a range of 0.11 to 0.29 pCi/m3 During the remaining 47 weeks of 1986 the gross beta activity was measured in all of the 570 samples collected with an average concentration of 0.024 pCi/m3, and a range from 0.015 to 0.042 pCi/m3 The results of the gross beta activities are listed in Table 5. The monthly averages of the gross beta concentrations for the eleven indicator locations and the control locations are plotted from 1977 through 1986. With the exception of the five week period influenced by the Chernobyl accident, the gross beta activities were comparable to levels in the 1982-1985 period. Prior to that period the gross beta activities were higher due to atmospheric nuclear weapons testing by other countries. , Air particulate filters were composited by locations on a quarterly I basis and were analyzed by gamma ray spectroscopy. The results are listed in Table 6. Cosmogenically produced beryllium-7 was measured in 46 of 48 composite samples with an average activity of 0.072 pCi/m3 and a range between 0.043 and 0.0892 pCi/m3 Naturally occurring potassium-40 was detected in ten samples with an average activity of 0.017 pCi/m3 and a range from 0.008 to 0.037 pCi/m3 . In the second quarter composites, three fission-produced isotopes, ruthenium-103, cesium-134 and cesium-137 were measured in the twelve samples. These isotopes are attributed to the Chernobyl accident; there was no statistical significance to the average concentrations in the eleven indicator locations compared to the control location. The average activity of ruthenium-103 was 0.008 pCi/m 3 and the range was from 0.0047 to 0.0108 pCi/m3, The average activity of cesium-134 was 0.008 pCi/m3 and the range was from 0.0057 to 0.0098 pCi/m3. The 26
i average activity of cesium-137 was 0.0143 pCi/m3 and the range was from 0.0098 to 0.019 pCi/m3, The second quarter composites of air particulate filters from all j twelve stations were analyzed for strontium 89 and 90. There were no l detections of these fission products at any of the eleven indicator stations nor at the control station. l l 1 l l I 27
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- 2. Precipitation i
A sample of rain water was collected monthly at station 01, on site, 0.2 miles, 42 degrees NE and analyzed for gross beta activity. The average gross beta activity for eleven months was 4.7 pCi/t with a range from 2.5 to 13.0 pCi/t. (There was no sample available for the month of January). A i semi-annual composite w6s prepared and analyzed for gamma emitting isotopes ! and tritium. Beryllium-7, a naturally occurring isotope, was measured in the semi-annual composite of f u ruary 1, to July 1, 1986 at a level of 31.6 pCi/f. Cesium-137, was detected at a level of 1.95 pCi/f. This is a fission product and was probably due to the fallout from the Chernobyl reactor accident. Tritium was detected in the January to June composite at normal environmental level of 130 pCi/f. The results are presented in Table
- 8. There were no gamma emitters detected in the July to December composite and tritium activity was below the normal level of detection of 100 pCi/f.
41
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- P 6 9 5 I 8 7 1 R C / 3 E E 1 71
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P / es - A I e A 0 8 7 7 7 6 3 6 6 7 6 7 BCH N M t T . . . . . . . F 0 N E a i Ef 1 0 0 1 0 0 0 1 0 0 0 6 O A m s B/ ) A g i a i i 1 i 1 1 i i 1 i 1 i S H M i n SC ( E 8 T M S O S p 2 5 2 3 2 1 8 1 3 8 7 7 T R A ( O . 1 . . . . I E O G 2 R 8 2. 4 4 3 2 6 2 2 2 4 S L N - G O B D i P 6 A - N 1 M 6 T R A f
/
0 O C 8
/
3 5.0 708 E M i N 1 W U C O L 0 iii O I p I A / P T T U 7 650 I A N 0 3 A I T R T S N - 1 9.1 A 6 31 N - 8 I , I / 7 G A M 1 3 R T E 0 71 I E 6 6 6 6 6 6 6 6 6 6 6 6 S / - - 3 V B 8 8 8 8 8 8 8 8 8 8 8 8 2 es - S / / / / / / / / / / / / 0 BCH S E 1 7 1 0 0 1 9 2 0 8 5 1 S T 3 2 3 3 3 0 2 0 3 2 2 3 O A / / / / / / / / / / / / R D 1 2 3 4 5 7 7 9 9 0 1 2 G 0 0 0 0 0 0 0 0 0 1 1 1 N - - - - - - - - - - - - F O 6 6 6 6 6 6 6 6 6 6 6 6 . O I 8 8 8 8 8 8 8 8 8 8 8 8 T / / / / / / / / / / / / eg d. S C 1 1 1 1 1 0 1 9 2 0 8 5 as N E 0 0 0 0 0 3 0 2 0 3 2 2 r O L / / / / / / / / / / / / e2 I L 1 2 3 4 5 5 7 7 9 9 0 1 v T O 0 0 0 0 0 0 0 0 0 0 1 1 Ai A C R T N E C N O C 3
f-
- 3. Soil l i
Soil samples which are collected every three years from twelve L stations, were collected in July and analyzed by gamma ray spectroscopy. The results are presented in Table 10. The naturally occurring nuclide I potassium-40 was detected in all twelve samples at an average level of-9782 pCi/kg (dry weight) with a ' range of 1740 to 22900 pCi/kg (dry weight). The ; 1 terrestrial nuclide radium-226 was monitored in eight of twelve stations at I an average level of 2088 pCi/kg (dry weight) with a range of 1200 to 3690 ; pCi/kg (dry weight). Thorium-228, also a naturally occurring nuclide, was analyzed in twelve of twelve samples at an average level of 1193 pCi/kg (dry weight) with a range of 477 to 2480 pCi/kg (dry weight). There were no detections of cesium-134. The fission product cesium-137 was detected. in nine of the twelve stations at an average level of 431 pCi/kg (dry weight) with a range of 136 to 709 pCi/kg (dry weight). No cesium-137 was monitored in the sample from station 24, the control station. The twelve soil samples were analyzed for strontium-89 and strontium-90. There were no detections of strotnium-89. Strontium-90 was detected in three of the twelve samples at an average level of 163 pCi/kg (dry weight) with a range of 130 to 190 pCi/kg (dry weight). These fission products occurred in previous years and are believed to be from atmospheric nuclear weapons testing in previous years. 44
TEE RUTR 0 0 0 0 O 0 EORU BROS MNPA UOEE NNRM N O
) ) )
I 1 1 1 T / / / A 1 ) 1 1 ) ) C E ( - 1 ( ( 1 1 ONG 0 / - 0 - 0 - / / - LAN 4 0 6 9 0 0 EA 7 ( 0 2 ( ( LMR 1 - 2 1 - - O R T N O C 6 ) 8 1 ) ) 9 / ) 1 1 ) 1 1 1 / / 1 9 NG ( / 1 1 / 3 , AN 0 - 1 - ( - ( - 1 3 1 NEA 0 ( 0 0 ( - - / 3 AMR 9 9 0 8 0 8 E 2 0 6 4 A 9 3 R M 2 7 3 2 N 1 Y 3 E N R - B T A 0 M S IO n P 5 E E T o M C H C U E G E n S O. D I R M N o H I D E io E E . A T t H S W S S E it 9 R E T D S S S S S s7 G K , I N S S O C 1 WEA i i i o9 R O M P1 P D Y NAE m i m m i R ONC 3 m m r G A I N 9 3 3 9 3 9 3 lae N U T A cb I N A T 0 im R A C S 5 0 0 7 ne O h v T J O I co I L D 3 2 3 3 A 7 eN N 2 0 2 2 N 0 T 9 O M h1 E S c L L N nn B A O ao A T I ri T N N T B s i E O A )) C v M I C 10 ) ) R e N T O 10 )0 O A L /9 )) 1 9 1) NR T 10 )) S RI S 12 19 16 /8 1 0 U , R E 12 10 /3 14 ) 19 n V ONG N R T AN ( 30
- /7 9 -
7 - (0 (12 1 /1 na E
- 1 3 - r E
W A AEA CMR 18 59 (3 6 1 0 92 47 / (0 i g L O 1 87 0 33 do A P I N I 02 31 01 14 ( 61 er D 1( 4( 2( 1( - 1( rP C N I R GI I iug G A R qn O E I L ei L L V L O C A rr I U , o D N Y dt A T ni R A N T an N U I o N O M N) dM M C I O1 e H A L I( T - - - inl a T S RFC)
- - 8 f t R I EOED en O U W TL 0 de N O L
O L EL D( sn m aor 2 2 2 2 2 2 2 ni DR 1 1 1 1 1 1 1 NES ABE iov n MSD tE SUYE c I NLM el S t a AR ec YLNO di LAAF 7 6 8 g AT R a 3 2 2 9 0 f o NOFE m 0 1 2 2 8 9 ol ATOP m 4 - - - - - o a - s a h r r ti G K C R T S S i d
)
T N ima l R E e Y M A E rl W eb H R U wa T S lotp A A ) e P E t sC DM e iC RE w OLF ( A PO D MM g L n UAT k L a I 5I l / D N E M U ( loc S p i
)
1 ( S
0 0 4 0 6 3 5 0 6 A8 0 0 0 S/ 0 i 0 1 0 0 0 0 0 0 i O2 2 1 5 6 4 5 6 1
- 2 < 0 < 0 < < < < < < 9 A/ 3 8 9 T7 1 9 5 S0 2
_ 0 0 0 9 8 5 3 6 8 7 9 1 58 0 0 0/ 0 0 0 i 0 0 0 0 i 1 i 2 2 4 9 1 8 6 8 l A2 < < < 0 < < < < 6 0 0 l T/ 9 7 3 9 0 S7 6 4 0 2 _ 5 0 8 2 1 N I 5 R E 6 T 0 8 T 4 1 7 9 I 6 6 6 0 6 1 M 48 0 0 0 0 E 0/ 0 0 0 1 0 0 0 0 i 0 t
- - 2 2 2 6 5 5 4 5 1 A A2 < < < 0 < < < < 6 < 3 A M T/ 4 0 7
) N M a S7 2 5 6 2 N A m 0 4 A G g 0 f i 1 o H D S T N E 1 R A 2 L O B e N 0 A g 9 T a - - g P r k 0
( R S / 9 1 5 E t 6 0 0 0 5 6 0 5 W , C 38 0 0 0 0 0 0 0 0 O 9 p 0/ 2 1 7 i 4 6 3 4 1 8 i P 8 2 < < < < < < < <
- A2 0 0 7 A R T/ 2 2 7 I S S7 7 5 4 N 0 3 I F G O R
I S V N O I T A 0 R 9 8 . T 6 8 1 4 D N 28 0 0 7 0 L E 0/ 0 0 0 i 0 0 0 0 0 i L C 2 2 6 5 4 5 4 5 i 7 < N A2 < < < 0 < < < < < 2 O T/ 8 9 8 e C S7 8 0 4 r 0 8 7 e w s r e t t i m 0 e 0 0 0 6 0 5 4 a 18 2 6 1 m 0/ 0 0 m 2 0 0 1 0 0 0 0 0 1 t a A2 2 6 7 6 7 5 7 6 g T / < < < 0 < < < < < 0 0 S7 0 2 6 r 0 3 8 3 e 0 1 1 h 2 t o l l E A D 4 7 6 8 I 9 0 4 8 0 3 3 2 2 L 8 9 7 0 5 5 6 1 1 2 2 C - - - 4 - - - - - - U r r e - n o o s s a h N S 5 B K M C C C C R T l
Iji]lill 3 2 0 2
. 6 5 4 5 1 4 4 5 2 E d. 6 1 3 1 1 Gs A - 1 - i - - - - i i i R2 E 3 2 1 8 3 Vt 6 8 3 8 9 A 1 7 4 0 1 9 2 1
^
^
^
0 0 0
^
. 7 4 3 6 9 1 6 48 0 0 i 1 t - 2/ 0 0 0 0 0 0 0 0 - 2 2 5 8 0 6 8 7 8 7 0 0 ^ A2 < < < 4 < < < < < 6 9 ^ T/ 7 0 2 S7 1 2 1 ~ 0 _ l - _ l 0 5 N 0 0 I 0 6 0 3 3 1 5
- 6 2 8 -
5 1 2 38 0 0 0 6 R 2/ 0 0 0 1 0 0 0 0 i i i ' 8 E 2 2 4 9 8 9 6 1 s 9 T A2 < < < 0 < < < < 6 0 0 d 1 T T/ 0 9 9 8 1 h I S7 9 1 6 4
- M 0 2 3 2 '
E 2 A c-m N A a 'm i N M m 1 A M g N A i m
) H G S w 2 T u R D 2 -
0 f O N 0 m. 1 o N A i 0 0 0 6 9 5 4 4 E 2 - 0 g 28 0 0 1 5 L 9 k 8 1 2/ 0 0 0 0 0 0 0 B e R - / 2 1 3 7 i 5 6 4 6 A g i i e E W S r i A2 < < < < < < < T C T/ 0 6 0 0 P O p S7 0 3 2 4 ( P , 0 2 1 9 4 9 9 1 1 A 8 1 I - N R I S _ G . R F
)
I O y V l S l N 0 O 6 a I 0 0 u 18 0 2 0 9 8 n T 2/ 0 3 0 A - 2 0 0 1 6 6 8 n R 0 0 0 O .a A2 2 7 t 5 1 4 T 1 t i D T T/ ( < < < < < Ld N S7 0 0 2 0 E 8 Le C 0 7 1 0 3 7 4 0 2 7 8
<mr N 2 O 1 1 eo C rf er we p
s( r ed t e t r 0 0 0 ii 6 0 0 7 7 0 3 mu 78 0 4 0 9 8 8 1 eq 0/ 0 0 0 0 0 0 e 2 2 1 1 t 1 9 7 9 1 1 i ar A2 < ( < < < < m T/ 0 0 2 0 0 mt S7 9 3 5 0 1 7 1 6 a o 4 4 2 gn 4 1 1 rs ei hs t y ol a l n E l n O 4 7 AA 6 8 I 9 0 4 8 0 3 3 2 2 L 8 9 7 0 5 5 6 1 1 2 2 C - - - 4 - - - - - - - ) U N S r rS e - n 0 o s s a h
- a B K M C C C C R T (
g j {l! j l! 1jll l 1!!l
l B. Waterborne Exposure Pathway
- 1. Ground /Well Water f
I Water was sampled quarterly from the on site well at the biology laboratory. These samples were analyzed by gamma ray spectroscopy and tritium. The results are presented in Table 12. No gamma emitting isotopes were detected except for the naturally occurring nuclide l 1 potassi zn-40 at a level of 87 pCi/f in the third quarter composite. Tritium was detected in all four quarterly samples at an average level of;198 pC1/f with a range from 150 to 310 pCi/2. This is a normal epironmentallevel. The second quarter sample was analyzed for s':rontium-89 and 90. There were no detections of these isotopes above the detection level.
?
48
OIDM TEE RUTR O O EORU BROS MNPA UOEE NNRM N _ O I T A C E ONG E E LAN M N EA O O LMR N N O R T N O C 6 8 ) 9 )0 1 E ) 41 NG 4 /3 3 9 , AN / 4 - 1 NEA 1 (0 3
/
3 ARR ( 85 E 7 91 Y 8 3 R E M' N 8 1( R 3 B T O A - M S I n M 0 E E T o M 5 C H C U E G E n S O D I R o N H I i M o D t . A T t H i9 R E T D s7 G K , I N o9 O C 1 WEA P1 R O M P D Y NAE r R ONC lae G A I N cb N U T A m I R N A A C T A A ine O J O IS I I h v co T D O I L O eN N T 1 O h1 1 M c S nn E L N L A O ao B T ri I B A T N E O N T is A C v M I C R e N T O O A NR R T L S
) U ,
I S R E )0 m V ONG N R T AN
) 41 na E
4 /3 ir E W A AEA / 4 - g CMR 1 (0 d o L O I I ( 85 er A P N D 7 91 rP C I N 8 1( I G R A G R I iug qn O E I t ei L L V t rr O C A o I U , dt D N Y ni A T an R A N T o N U I dM N O M N) e A C I O1 nl L I( i a H A T f t T S RFC) en R O I EOED 0 0 d e U W TL 6 0 N O L O EL D( 1 s rw L ao r ni DR 4 4 4 ov NES i n ABE tE MSD c SUYE el INLM t a S AR ec YLNO m di LAAF g AT R a iu f o NOFE m 0 t ol ATOP m 4 i o a - r ti G K T i d
)
T N ima l R E e _ Y M r rl A E e eb - W R t wa H U a ot T S 'J l p A A e P E l _ DM l isc c RE e A OLF W D MM PO /) df L n L a ILAT SI n/ ui D N oC ) E U rp 1 M ( G( ( 3
,i
_ T 0 4 5 0 1 9 l 7 1 a B R E T A W ) ) L b c ( ( L 1 E 3 0 0 6 W 1 1 6 8 1
/
D I
- < < < < o t
N U n O e R v G i g N _ I s a
- 9 9 w 6 S 2 2 8 R 0 0 0 0 y 9 E 4 5 2 i 6 1 t 1 T - < < < i T K 7 7 r
- I 8
M 8 o i A E r N A N A M
.P M a e l .
2 H A m pt 1 T G g R i 7 0 0 0 0 mn E O D S - ae 4 2 3 5 sd L N N e < < < ( i B A 2 S rc A - ec T M i t a R U r E I f al W T / uy O I 1 qb P R C o T p A d n .
, nrt I
0 oen N M 9 ) 1 ) ) ch e I U - a < a a ecd G I r ( ( ( s i R T S ec I N V O nh c R ot a T yme S l oh . F nrtI O of T
. y Dddb y S
N L ea b 9 L mod O 8 ) ) )
< rl et I - a 4 a a o t h T r ( < ( ( efk co A S rrr el R
T eeof s wpwf r N E ssy ee C v N reveo O esar t yeen C 0 1 tl h wa 0 0 0 0 5 i a 8 8 9 1 1 mnoh o 3 eat ct
- i t t i H a0 eh e 0 0 0 0 8 m9 uwu 5 1 6 7 9 m/d d 1 3 1 1 1 a9 a
- g8ti t
- ede
_ rmmem eu m _ hit t A tt oeo N l onnl n O I O 6 6 6 6 l o rDmD p _ TS N 8 8 9 8 e d. l t L aL CE O / / / / gs ASL sL ET I 1 0 8 0 a , LA T 3 3 0 3 r . LD A / / / / e2 )) ) O T 3 6 0 2 v
- ab c C S 0 0 1 1 A i (( (
_ _ _ _ - _ _ - - _ _ - - _ _ _ - . - - _ _ _ _ - . . _ _ _ _ _ _ = . _ _ . - _ _ - -
- 2. River Water
' A sample of- water from the North Anna River was collected quarterly at station 11, 5.8 miles downstream from the discharge lagoon,128 degrees SSE. The results are presented in Table 14. The sample' was analyzed by gamma spectroscopy, for tritium and the secono quarter sample was analyzed for strontium-89 and strontium-90.
One detection of the naturally occurring nuclide, potassium-40 was
- monitored in the fourth quarter sample at a level of 43.4 pCi/2. All other
-gamma. emitters were below the detection level. No detections of strontium-89 or strontium-90 occurred. Tritium was analyzed by gas counting at an average level of 4020 pCi/E with a range from 3400 to 5000 pCi/f. The average tritium' activity level for 1985 had been 3258 pCi/E with a range of 3100 to 3400 pCi/2.
i
-)
4 51
TEE _ RUT R EORU BROS O O - MNPA UOEE NNRM N O TI A _ C E . ONG E E LAN N N EA O O LMR N N O R T N O C
)
6 0 8 ) )0 9 4 40 1 E / /5 NG 1 4 - . 9 , AN ( (0 3 1 NEA - 4 00 3
/
3 AMR 24 E 3 03 8 R M 4 4( Y 3 E N R 3 B T O A 4
- M S I n
J 0 E E T o P 5 C H C U E G E n S O D I R o N H I M o D E E i A T t H S S it 9 R E T D S S s7 G K , N O R C O 1 IWEA M i i o9 P1 P D Y NAE m m R l r G ONC - 8 8 ae A I N cb N U T A 5 5 I N A T im R A C S ne O J h v T O I 1 1 co I L D 1 1 eN 3 N T 1 O M h1 E S c L L N nn B A O ao A T I ri T N N B s T E O A C iv M C N TI O ) R e O A NR R T L
)
0 S S )0 U , I V R E 4 40 m N ONG / /5 na R T AN 1 4 - ir E E AEA W A CMR ( (0 g L O I 4 00 do A P N I D 3 24 03 er C I N 4 rP 4( I G R A G R I iug O E I qn L ei L L V L rr O C A I U , o D N Y dt A T ni R A N T an N U I o N O M N) dM A C I O1 e H A L I( T inl a T S f t RFC) 0 0 en R I EOED 6 0 de O U W TL 1 N O O EL m L L D( sn aor 4 4 4 ni DR NES ABE iov n MSD tE SUYE c el INLM t a S AR YLNO n ec LAAF s di AT g R a it f o NOFE m 0 ol ATOP m 4 it o a - r
)
G K T iti d T N ima l R E Y M e A E rl - W eb H R U wa T S ot l p A A - P DM E r e ic sc e RE t A OLF a D PO W) L n NM t AT r/ f L a _ I SI ei _ D N - E U ivc p ) 1 M ( R( ( R
6 0 0 2 0 0 0 0 2 1 2 7 6 - R a G 5 0 0 4 5 l 1 1 1 < < < < R a _ T E B A W R E V I R 7 3 N 1 4 9 3 3 I - < < < < s
- C 5
6 R 8 E 9 T 7 7 1 T . . I 4 4
- M 2 2 E
A 0 i 1 N A 0 0 0 0 N M 4 5 2 9 4 4 A M < < < A a K 3 3 4 H G m 4 4 1 T g R D i E O N S L N A B 2 A - M T U i R I 7 E T 2 - 0 0 0 0 W I / e 4 9 4 4 O R 1 B < < < < P T C p A , I M e N U l I I p G T m R N a I O 5 s V R 0 0 0 0 3 T 0 1 0 0 4 r S 3 2 4 2 1 e 3 t F - i i i i r O H a 0 0 0 0 0 u S 0 8 0 0 2 .q N 4 5 1 0 0 O O 3 3 4 5 4 Ld I T L n A
<o R
c T 0 ee rs N 9 5 e E C r
- )
a
)
a
) wn N S 0 a o
( < ( ( s O rd C ee t m t r i o mf cr 9 e 8 ) ) ) ap
- a 2 a a m r ( < ( ( my S al gn o
r es 1 hi 1 t s N oy O - l IS 6 6 6 6 . l a TE N 8 8 8 8 l n CT O / / / / e g d. AA EA I 3 7 8 9 as LD T 1 1 1 1 r L A / / / / e2 ) O T 3 6 9 2 v
- a C S 0 0 0 1 A1 (
l
- 3. Surface Water Samples of surface water were collected monthly from two stations.
Station 08 is at the discharge lagoons,1.1 miles,148 degrees SSE on Lake [' ' An n a . Station 09 is 2.2 miles upstream on Lake Anna, 320 de.grees NW. The samples were analyzed for iodine-131 by radiochemical separation. No iodine was detected in the 24 samples analyzed. The results are presented in Table
- 16. The samples were monitored by gamma ray spectrometry and no gamma emitters were detected above the detection level at either station.
The second quarter composite from each station was analyzed for the fission products strontium-89 and strontium-90. The activity of these isotopes were below the limit of detection. A quarterly composite from each station was prepared and analyzed for tritium. The tritium at station 08 was at an average level of 3918 pCi/l with a range of 3450 to 4900 pCi/f. The trend of the tritium activity at station 08 has been plotted. The tritium level has been increasing since the middle of 1978 when the average level was below 300 pCi/f. The tritium in the four quarterly composites from station 09 was at a level of 2883 pCi/f with a range of 1690 to 4100 pCi/f. This is particu-larily significant since this level is found upstream of the plant. The l 1 level of tritium at both stations showed an increasing trend over the year. l 1 l Samples of surf ace water were collected by the Commonwealth of Virginia ) from two stations. Station W-33 is located at the discharge lagoon and station W-27 is located on the North Anna River at the RT. 208 Bridge, which is upstream of the site. Ten grab samples and two composite samples were collected and analyzed by gamma ray spectroscopy, for gross beta and tritium. 54
The results are shown in Table 17. The gross beta results at station W-33 were at an average level of 4.5 pCi/f with a range of 2.1 to 20 pCi/f. The results at station W-27 were at an average level of 2.6 with a range of 1.4 to 4.2 pCf /2. This is an expected level for surface waters. The gamma ray spectrometer monitored one detection of the natural nuclide potassium-40 at station W-27. There was one detection of the fission product cesium-137 at a level of 4.5 pCi/E at station W-33. A quarterly composite was analyzed for tritium. The average level at { station W-33 was 3130 pCi/l with a range from 2600 to 3400 pCi/f. This is l similar to the average result of 3918 pC1/2 detected at station 08, also the j 4 discharge lagoon. The average level of tritium at station W-27 was 1183
]
I pCi/E with a range of 320 to 1730 pCi/f. For the first quarter composite tritium was below the detection level. l l 1 55
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OI DM TEE RUTR O O O O 0 0 EORU BROS MNPA UOEE NNRM N O I T ) ) A 2 2 C E 1 1 ONG E E E E / / LAN N N N N 0 0 EA O O O O ( ( LMR N N N N - - O R T N O C
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6 )) ) ) 0 8 20 2 2 )0 9 1 1 1 44 1 E /0 / / /3 9 . NG 22 1 1 4 - 3 AN 1 - ( ( (0 1 NEA (1 9 9 00 3 3 AMR . 4 46
/
8 R E M 4. 4( 2 2 1 02 A A Y 3 4 3( N N E N R 3 B T O A - M S I M 0 E E T M 5 C H C U E G E S O D I R N H I M o D A T t H R E T D G K , N O R C O 1 IWEAM P D Y NAE R ONC G A I N N U T A I N A T R A C S 3 7 3 3 O J O I 3 2 3 3 T L D - - - - I W A A N W W W N N 5 O 1 M S E L N L A O B T I A N N T T E O A M I C N T O O A L )) ) ) )) R T 40 4 4 40 I S R E 2 2 2 20 V ONG /0 / / N R /4 ) ) TAN 42 1 1 73 2 2 E E AEA 2 - ( ( L W O I A CMR I 4 9 4 9 (60 - 1
/
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-C. AQUATIC EXPOSURE PATHWAY
- 1. Sediment / Silt
+
Sediment samples were collected in March and in September from each of three locations and were analyzed by gamma spectrometry. The results are presented in Table 19. A number of man-made and naturally occurring radioisotopes were detected in these samples. Cesium-137 was detected in all samples with an average activity of 663 pCi/kg (dry weight) and a range from 138 to 1670 pCi/kg (dry weight). Cesium-134 was measured in 4 of the 6 samples with an average activity of 321 pCi/kg (dry weight) and a range of 113 to 666 pCi/kg (dry weight). Manganese-54 was measured in one sample with an average activity of 62.8 pCi/kg (dry weight). Cobalt-60 was measured in one sample at a level of 38.9 pCi/kg (dry weight). The highest readings for cesium-134 and cesium-137 were obtained at station 11, 5.8 miles downstream in the North Anna River, 128 degrees SSE. The activation products manganese-54 and cobalt-60 were also found at station 11. Naturally occurring potassium-40 was observed in all samples with an average activity of 8483 pCi/kg (dry weight) and a range from 865 to 22300 pCi/kg (dry weight). Radium-226 was also measured in five of six samples with an average concentration of 1677 pCi/kg (dry weight) and a ! range of 737 to 2710 pCi/kg (dry weight). Also naturally occurring, thorium-228 was observed in all six samples with an average concentration i of 1531 pCi/kg (dry weight) and a range of 674 to 3980 pCi/kg (dry weight). A composite was prepared of the semi-annual samples and analyzed for strontium-89 and strontium-90. There were no detections of these fission products in aquatic sediment / silt. In the accompanying figures the isotopes cobalt-58, cobalt-60, cesium-134, and cesium-137 are plotted for the sediment samples collected in 1986 at stations 08, 09, and 11. All results are comparable with previous years. 60 L___-________- -
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S9 0 5 0 0 0 0 7 3 3 9 3 0 0 8 2 2 1 0 6 2 3 7 8 T 98 0 2 2 2 0 7 0/ ) ) 0 0 0 0 0 L - 0 a a 3 1 2 3 2 1 5 i I A3 ( ( < < < < < S T/ 0 3 6 9
/ S9 8 1 3 7 T 0 1 N
1 2 7 1 E MI 6 D 8 E 9 S 1 N
- I a 0 0 6 0 5 0 7 A
- m 88 0 3 N S g 0/ 2 4 6
) ) 0 0 0 0 0 N R i
- 0 a a 3 1 3 3 2 3 1 i i A E S A3 ( ( < < < < <
T T/ 0 9 H T 2 S9 8 0 4 1 T I 0 3 9 7 0 4 1 4 6 R M 2 1 E O E L N g B A k A - M / T M i R A C E G p W O F 0 9 5 P O 0 0 0 0 6 2 3 7 7 7 9 0 A S l8 0 0 2 1 1 6 1 3 I N i / 0 0 0 4 N O 0 3 7 4 3 i 2 i i i i 1 I G I T A1 < < < < T/ 0 8 9 6 u 0 0 R A S3 0 6 / 1 8 I R 0 3 2 8 6 6 7 9 V T 2 6 3 N 1 2 3 E 2 C N O C 6 2 2 . 98 2 6 6 4 5 y 0/ 0 0 1 1 2 2 7 .l
- 3 0 0 0 0 0 0 Ol A1 8 4 1 1 1 1 i i i L a T/
S3
< < < < < < L u 5 8 6 7 0 <n 0 6 0 5 3 5 n 8 1 2 7 7 ea r
ed we m sr ro ef t - t e 6 i p 0 0 0 m 88 3 0 3 9 7 es - 0/ 0 0 5 4 1 3 9 e
- 3 0 0 0 0 0 0 as A1 7 7 2 1 2 2 2 i i 1 i n y T/
S3
< < < < < < i nl
_ 0 5 0 0 1 aa 0 5 9 0 gn - 2 3 3 2 4 7 9 5 1 a 1 r e0 h9 t/ o9 E l 8-D I 9 0 4 8 0 4 3 7 3 6 2 8 2 lASr L 8 9 7 0 5 5 6 1 1 2 2 C - - - 4 - - - - - - - ) U r r e - n o o s s a h
- a N S S B K M C C C C R T (
_ m* l
- 2. . ;_ Shoreline Soil lA sample of shoreline sediment was collected in March and September l
from station 09, 2.2 miles _ upstream of the discharge lagoon on Lake Anna.
; T'he ' samples 'are analyzed by gamma ray spectrometry. The results are
, presented in Table 21. The' naturally occurring nuclide potassium-40 was detected in the March sample at a level of 600 pCi/kg (dry weight). 1 Thorium-228 was detected at a level of 225 pCi/kg (dry weight) and-radium-226 at a level of 298 pCi/kg (dry weight) in the March sample. These are-naturally occurring terrestrial nuclides. Cr:sium-134 was detected in the March sample at a ' level of 44.1 pCi/kg (dry weight). Cesium-137, also a fission product was monitored at an average level of 81 pCi/kg (dry weight) with a range of 61.8 to 99.7 pCi/kg (dry weight). The two quarterly samples were composited and analyzed for strontium-89 and 90. There were no detections of either of these fission products in shoreline soil. l i 67
OI DM TEE RUTR O O D O O O O EORU 8ROS HNPA tOEE NNRM N O I T A C E ONG E E E E E E E LAN N N M N N N N EA O O O O O O O LMR N N N N N N N O R T N O C
)
6 7 8 ) ) 9 ) 2 29 ) ) 1 E 2 / /9 2 2 9 NG / 1 2 - / / 3 , AN 1 ( 8 1 1 3 1 NEA ( ( (
/ 3 AMR 0 l. (8. 1 8 5 8 E 0 4 06 9 2 A A 3 R M 6 4 8( 2 2 N N Y 3 E N R - B T O A 0 M S I M 5 E E T M C H C U E G E S O. D I R N H I M o D A T t H R E T D W W W W W G K , N N N N N N O
R C O 1 IWEA M i i i i P D Y NAE m im m m m R ONC G A I N 2 2 2 2 2 N U T A I N A T 2 2 2 2 2 R A C S O J O I T L D 9 9 9 9 9 A A I N 0 0 0 0 0 N N 0 2 O M E S L L N B A O A T I T N N T E O A M I C ) N T O 7 O A L ) ) R T ) 2 29 ) ) I S R E 2 / /9 2 2 V ONG / 1 2 - / / ) ) N R T AN 1 ( 8 1 1 1 1 E E AEA ( ( L W O A CMR 0 l. (8.1 ( 8 5
/
0
/
0 I I 0 4 06 9 2 ( ( A P N D 6 4 8( 2 2 - - C I N I R G I G A R O E I L L L V L O C A U , ID N Y A T R A N T N U I N O M N) A C I O1 L I H T A S T( - - 0 - - - 8 RFC) 8 R I EOED 1 0 O U W TL N O O EL L L D( DR 2 2 2 2 2 2 1 1 NES ABE MSD SUYE I NLM S AR YLNO LAAF 4 7 6 8 - AT R a 3 3 2 2 9 0 NOFE _ m 0 1 1 2 2 8 9 _ ATOP m 4 - - - - - - a - s s a h r r . G K C C R T S S
)
_ T N _ E Y M A E W R H U l T S A P A E io) St DM e RE ew OLF n( PO MM i g L ISI AT lek r/ D N oi E U hC - M ( S p o mc
L I O S E N I L 6 6 E 98 R 0/ 1 O - 2 2 H A1 ) ) 0 0 0 _ S T/ a a 0 0 0 0 0 0 1 0 0 S9 ( ( 3 4 2 3 2 2 4 4 N 0 < < ( < < ( 8 < < 6 I 8 . 1 9
- 6 1 S R
- E T
A T . N I a ) N M m y A E g l i l H A S a T M u 1 R M 2 n 2 O A .n N G i Da E L L - D g Ld B N k A R A /
< e T E i m
W 0 C er O 9 p ro P - ef r - 6 5 3 5 wr A S 98 5 e I 0 0 1 5 3 sp 0/ 0 0 1 1 1 1 2 r( N , 3 0 0 0 0 0 0 I 9 A1 8 4 e 1 i 1 1 1 i 1 i 1 td G 8 T/ < < < < < < t e R - S3 0 1 7 8 5 i r I R 0 0 9 2 V S 6 mi 4 9 2 2 euq 4 9 F O ae mr S m N at go IO n T r A es hi R t s T N oy l E l a C N l n E O AA D 4 7 6 8 C I 9 0 4 8 0 3 3 2 2 L 8 9 7 0 5 5 6 1 1 2 2 C - - - 4 - - - - - - - ) U r r e - n o o s s a h
- a N S 5 B K M C C C C R T (
ee ( ,i lil l ! l
I D. INGESTION EXPOSURE PATHWAY i
- 1. Milk The results of the iodine-131 analysis of milk samples are pre-sented in Table 23. A sample was collected monthly from two stations. 4 A total of 24 samples were analyzed. There was no iodine-131 detected until after the Chernobyl reactor accident. Iodine-131 was detected in the months of May and June at both locatior,s. The activities ranged ,
from 0.67 to 11.0 pCi/f with each result referenced for decay to the collection date. The average activity was 4.4 pCi/f and ranged from ) l 0.67 to 11.0 pCi/2. After June no further detections of this short lived fission product were monitored. The milk samples were also analyzed by gamma ray spectroscopy and
]
the results are shown in Table 23. A total of 24 samples were analyzed. Naturally occurring potassium-40 was measured in all of the samples with n . \x an average of 1317, pCi/t and a range of 1140 to 1960 pCi/f. Cesium-137, i which^is a fis: ion product, hcs been detected sporadically in recent years. The activity has been attributed to global f allout from past atmospheric weapons testing, Cesium-137 was not detected in milk until } Mter the Cherectyl 'c.ccident in April 1986. Beginning in June cesium-137
, . was detected in ) of the 14 farples at an average level of 11.2 pCi/E i
ranging from 6.4 to 21.1 pCi/t. There was one detection of cesium-134 o i at Station 12, 8.3 miles NW in August 1986 which is a fission product attributable to the Cherochy reactor accident.
! c. s ' Equarterly cornposite was prepared from each of the tua collection a stations and analy:Hlfer itrontium-89 aiid strontip-90. The results F
3 s, 70 s. y h,' # g. _ } K w _ _ - - - _ - - - _ _ _ - - - - - - - - _ - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - - -- - - - - - - - - - - ' - - - ' - - - '
i are shown in Table 23. No strontium-89 Was detected in any of the samples monitored. Strontium-90 was detected in eight of the eight samples monitored at an average level of 2.1 pCi/f and a range of 1.1 to 2.9 pCi/f. This is similiar to activities determined in previous years and lower than the reoperation levels of 2.2 to 5.4 pCi/f. n t - -- - - -----__------------_--__ _ _ o
T E N f N E OI DN T EE RUT R O O O O O O EORU BR OS MNPA uOEE hNRM N O I T A C E ONG E E E E E E LAN N N N N N N EA O O O O O U LMR N N N N N N O R T N O C _ 6 20)
) )
8 )
)1 )
9 )0 1 6 2 . 2 ) 1 2 /9 1 1 )7 N6 E 1 1
/1 21 1/2 / 4 9 1 AN 1 - 2 - 1 /2 2 - 0 3
3 3 NEA AMR 3 (20 7 2 (2
- 7. 0
( l 4 - (1 _ (7. 4(
. l
/ R E Y
8 3 E B M N 7 3l 1( 51 1( 1 0 A N 2(
.1 R 3 M T O A - E S I
n t
- 0 5
C E E H T C o U D G E S O I R n N o H I io _ M t D _ A T H t . - R E , T D W i9 P W W W G K 1 N N N N N s7 IWEA N O C o9 R O Y M i i i i F1 P D R NAE m m m i. A m n laer G N U N IONC N 3 3 3 3 3 T A icbm I A A T 8 8 8 a R J C S 8 n e O O I h v T L D 2 2 2 ? A co I 1 1 2 eN _ 2 N 1 I N 1 T 2 O , M h1 E S c L L N nn B A O ao A T I ri T N N T B s E O A i I C ) )) C v M T O
)
H e O R A T L )0 40 26
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)
4 ) NR S 41 /9 21 7 )9 U , I S R E 21 41 /2 V / E N R GNG TKN
/ -
47 2 - (0 7 - 7 1 ) /? na m E A ( 8 8 - r E W i A[A CF T R (6 7 4 (23 l / - (1 i g L A P O I N DI 40 4( 13l 1( 1 1 6 1( 1 0 0 ( l
<(
1 d o er C G N rP R R I i GI A I u g O E V L qn L L L ei O C , A r r I U Y o D A N T N _ dt ni a n R A U T N O I e N A C A M I N) O1 NM H L I T( 0 inl a T IS 5 0 0 . - f t RF C) 0 ! R U E OED 0 2 3 o n O O W T L d s rw N L O EL L D( a e 4 4 4 r 4 4 ni DR 2 2 2 ? / t NES iov ASE n MSD ) t E c SUYE y y el I NL M l a tec l S AR r r Y LNO e o di L AAF 7 AT NOFE R 1 3 a 3 u 9 r t 0 t g o m 0 1 l 9 i 9 fol
- uw AT OP 1 m 4 - - - u I
- a G k C
s r s r q
'- (
r St t io i d
)
T N ima l R E Y M e _ A E rl W P eb _ H 0 w a T A 5 A lot p P L e _ DM isc c RE _ OL f A _ P U ) D NM t L n L AT / L a 5I dl N k 1 l C ) E U i p 1 M ( M( ( g l ,l
0 0 0 0 K 3 _
- 8. 2 3 4 6. 3 L 1 01 4 1 2 3 M
I A 21i50
)) ))
1
. )01 4 aai40 i50 N
T S 60
- << ((
0 ( ( (aai40 ( << 2 0 ' 30 I .2 0 0 _ 12 3 4 12 9 1 1 1 1 5 _ R E _ _ T _ T I M E 6 A _ _ 8 M _ 9 M _ _ 1 A _ _ G _ D A N N A a
) N m 70 0 0 0 3 A 0 g 2 .4 2 3 6. 4 9
_1A i 01 3 1 3 1 2 01 5 3 f H - S - . )) . )) . 2 o T 2 40 aa 60 aa 60 2i 40 R D 2 T < << (( << I( << < < < E 1 O N S 10 0 0 30 L N A i 7 2 7 6 B e 13 2 2 73 A g - 9 f _ 1 1 1 1 T a 9 / _. P R - i _ ( E M C _ W U p _ O I P A T O N m_ _. I R _ N T I S _ G E 7 7 7 7 R F D 90 31 90 3 1' 90 31 90 31 I O I _ 8901 3 89013 89n1 3 8901 3 V L - 4 1 - 1 - - 4 1 - - 4 1 S C rr - s - rr - s - r r - s - r r - s - N U SSKCI SSKCI S$k CI S$K tI O N I T A R T N E C N O _ _ C _ _ Y _ Y R H _ R A T _ A U H L N _ U R C I _ O _ N B R _ _ M _ A J E F M M P A g l lI{ liiI
_ ) _ b _ ( 77 0 6 033 0 0 K 3 1 . 3 . . 2 L 1 4 I 1 0 130 1 3 1 3
- )) )) )) . ))
M A aat5i aatit aa 60 aa
~T (( ( ((
450 N S (( < < (( <<< 0 6 077 ' 0 0 I 4 636 0 0 1 1 2 . 2 4
- 1 1 60 1 1 5
R E T T I M E 6 A 8 M 9 M 1 A G
) ))
D b A N bb _ ( (( N A a N m 0 A 0 g 004 0 040 2 4 0 . 3 2 . .
) 9 i 1 1 3 H - S -
1 240 1 3 1455 _ )) )) )) )) T 3 f R D 2 T A aa (( 4i aati (( aat50. (( ( < aat if 0 (( < 2 o O N S 0 1 023 0 N A 6 1 011 6 . 1 0 . . - E 2 3 L 904 3 201
- 9 I 1 11 1 e 1 1 2 B
A T g a R E 8 M
- i
/
C P ( W O P T U I p _ N _ - A O _ I R N T I S G E 7 7 7 R F D 90 31 47 90 31 90 31 90 331 I O I 89013 89013 8901 3 _ V L 8901 13
- - 4 1 - - 4 1 - 4 1 4 -
S C rr - s - - 1 N U rr - s - r r - s - r r - ss - - SSKCI SSKC1 SS K ( 1 SSKEtI O N - I . T A R _ T N E - C N O C H T _ T 5 _ N E Y O U _ Y N t G M A U U U M J J A - g
) ) )' )
b b b b ( ( (
- (
6 8 709 04 06 00 K 3 _ L 1
.2 0133 2
153 3 2. 2 _ I 135 11 45
. )) ))
M A 21 i0 aai10 aa i0 2 ii0 _ T < < (( < (( < < - < N S 506 00 I .1 09 906 2 03 04 223 21 3 . 22 . .
- 11 1 1 17 S 1 8 t R n E e T d i
T I c M c E a 6 A l 8 M y 9 M b 1 A o G n
- r D e A N h N A C N a 70 0 A 0 m 0 0 e 2 3 3 4 8. 4 9 g 1 01 3 h
) H - i 1 4 1 4 01 4 3 T S A 2 i40
. ))
aa
)) .t R D 40 a ai40 2 40 yo T ( << (( << (( <( < <<
3 f O N 2 S 30 0 l t 2 o N A 0 70 r 4 9 1 7 i 23 ed E 3 2 4 23 t e
- 9 .
1 1 1 1 rt L 8 t B e R - / au A g E M 1 ub T a W U C qi P O I p . r ( P T Ddt
~
N L et A O l ma I R < r N T oe I S ef r G E 7 7 rra R F D 90 31 90 31 90 7 31 7 ee I O 90 31 wpd I 8901 3 89013 8901 3 8901 3 V L - 1 - 4 - 1 e S - 1 - 4 - 1 ssr C rr - s - rr - s - N U r r - s - r r - s - reu SSKCI SSKCI SSk EI s5EC1 ess O N I t ya T tl e A i am R mn T ea7 N 3 E a01 C m9 - N m/s O a9C C g8 / 4 rm3 eu1 hi - tt s R onC E R o B R E H l re E l t h H M E B P T E B AST M P N T O E E O P T V C M E )) C O S O E
- ab N D ((
U l
- 2. Fish Marine biota can be sensitive indicators of radionuclides accumulatier, l i
in the environment because of their ability to concentrate certain chemicel elements which have radioactive isotopes. The results are presented in Table 25. Three samples of fish were collected from station 08, the dis-charge lagoon. These samples were analyzed by gamma ray spectroscopy and the naturally occurring isotope potassium-40 was found in all three samples at a level of 1957 pCi/kg (wet weight) with a range of 1770 to 2170 pCi/kg (wetweight). Cesium-134, a fission product, was found at a level of 157 pCi/kg (wet weight) with a range of 81.5 to 204 pCi/kg (wet weight). The j fission product cesium-137 was found at a level of 537 pCi/kg (wet weight) with a range of 257 to 701 pCi/kg (wet weight). l l Five samples were collected from station 09, the control location 2.2 miles upstream on Lake Anna. The same nuclides were monitored by gamma ray spectroscopy. Naturally occurring potassium-40 was monitored in all five l samples at a level of 1932 pCi/kg (wet weight) with a range of 1540 to 2420 , pCi/kg (wet weight). Cesium-134 was detected in four of five samples at a ) I level of 112 pCi/kg (wet weight) with a range of 55.6 to 197 pCi/kg (wet j weight). Cesium-137 was found in all five samples at a level of 309 pCi/kg (wet weight) with a range of 66.1 to 631 pCi/kg (wet weight). The levels of the fission products cesium-134 and cesium-137 were somewhat higher at the discharge lagoon than at the control station upstream of the discharge point. The results in 1985 for cesium-134 were 331 pCi/kg (wet weight) and 890 pCi/kg (wet weight) at the discharge lagoon. 76
FN E OIDM TEE . RUTR 0 0 0 EORU BROS NNPA t OEE NNRM
)
N 0 ) ) O )2 7 1 I 54 )9 T A
/2 5 -
51
/ -
)56
/ -
3 C E (0 46 51 ONG 24 ( LAN EA 35 91 25 15 (96 06 LMR 1( 1 ( 3( O R T N O C 6 ) 8 0 ) 9 )7 4 ) 1 31 )0 )1 E /2 32 30 NG 3 - / - /7 9 1 AN (0 35 3 - 3 3 NEA 77 (7 3
/ R APR E
57 91 (71 75 58 32 Y 8 3 E B M 1( 1( 5( N R 3 M T A - E S IO M 0 C E T n M 5 E H C o _ U D G E n S O l R _ N o i I io M t t D E E E t . A T i S S S R E , b D S i9 G K 1 S S s7 N - R O C O Y
!WLA M l
o9 P1 _ P D R NAE m im im - A ONC l r _ G U I N 1 1 1 ae N N T A 1 1 icb I A A T 1 m R J C S ne O O I 8 8 8 h v T L D 0 0 0 co I eN 4 N T O _ 2 _ M h1 _ E S c _ L L N nn B A O ao A T I ri T N N T B s E O A i M I C C v N T O ) R e O A L 0 ) NR R T S
)7 4 ) U ,
I S R E 31 )0 V N R ONG T AN
/2 3 -
32
/ -
)1 30
/7 ne r E E A AEA (0 35 3 - i g W I CMR 77 ( (7 L O N I 57 71 d o A P I D 91 58 75 32 er C G N 1( 1( 5(
rP I R R I iug G A I qn O E V L L L L ei O C , A rr I U Y o D N T dt A N ni R A U T an N O I o N C M N) dM A I O1 e A L I( inl a H S T ft _ T I RFC) R U EOED - en
- - de O O W TL N L O L
EL D( sn m aor 8 8 8 8 ni DR NES iov n ABE tE MSD c SUYE el I NLM t a S AR ec YLNO di LAAF 4 7 g AT R a 3 3 f o NOfE ATCP m 0 4 1 1 ol a r
- s s
- o ti
)
T E N G K C C l i d ima R e Y M A E rl W R eb 1 1 U wa - lot T 5 p A A ) e P E t sc DM e ic _ RE w A _ OLF ( D PO L n _ MM t AT k g L a _ iS? h/ D N si ) _ E U iC 1 M ( F p ( . i'
1 i 1 i i i i 1 i 1 s 7 1 2 1 0 6 1 3 5 C 5 0 5 3 4 7 . 3 9 2 7 6 6 2 1 6 4 3 6 3 1 8 . 0
. 0 9 0 0 1 3 3 4 8 2 1 2 1 1 1 1 3
1 0 i 1 i 1 i 1 1 i 1 s 5 4 5 7 4 6 1 1 C 0 8 9 . 3 3 1 2 1 1 4 5 1 1 8 6 5 H S 8 . I 5 0 0 0 0 0 0 0 6 F - 1 1 1 8 1 1 1 1 8 o < < < < < < < < 9 N C 1 I 5 a A R m N E g N T i A T S I H M 2 5 T E 0 0 0 0 0 2 R 0 0 0 6 i 8 2 9 4 8 5 6 3 3 O A 1 2 1 2 E N M ) 0 1 1 1 2 '6 M L t 4 t i 1 1 1 i i B - A e - A G w K 0 0 0 0 0 0 0 0 1 T R ( 7 7 3 2 3 4 0 7 4 E F 7 1 9 4 8 5 6 W O g 2 9 1 2 1 2 1 1 1 2 1 O k - P S
/
N i A O C I I p N T I A G R E R T P I N Y V E T . C N E D O L L C P l M < A S e r e w s r e t t N i IO m e T 8 8 8 9 9 9 9 9 A 0 0 0 0 0 0 0 0 a T S me ml ap gm a rS e
) ) hl N
a a t o _ O ( ( or t I 6 6 6 - T 8 8 8 6 8 6 8 6 8 6 8 6 8 l n CE l o ET
/ / /
4 8 3
/ / / / / e g d. AC LA 2 0 0 9 9 2 6 9 as LD 0 0 1 2 0 r
/ / / / / / / / e2 )
O 4 9 2 5 9 9 v C 0 0 1 0 1 2
- a 0 0 1 1 A i (
5
3.- Food Products / Vegetation
- l. .
Nine food samples were collected from six locations and analyzed by l gamma. spectrometry. The samples consisted of green leafy vegetables .such as cabbage and lettuce. The results are presented in Table 27. Naturally I occurring; potassium-40 was monitored in all of the samples with an average
'qtivity level of 6279 pCi/kg (wet weight) with a range of 4380 to 14800 pCi/kg(wetweight). Cosmogenic beryllium-7 was detected in six of nine samples at a_ level of 406 pCi/kg (wet weight) with a range of 105 to 925 l pCi/kg (wet weight). 'The. terrestrial nuclide thorium-228 occurred in two of nine samples at an average level of 235 pCi/kg (wet weight) with a range of 63.4to407pCi/kg(wetweight). l The fission' products ruthenium-103, cesium-134 and cesium-137 were detected in the samples collected on May 30, 1986 after.the Chernobyl reactor accident. Ruthenium-103 was detected at' station 21 at a level of 54 pCi/kg (wet weight). Cesium-134 was also detected at station 21 at a level i of38.2pCi/kg(wetweight). Cesium-137 was detected in three samples j collected in May and one in June at a level of 40 pCi/kg (wet weight) with a range of-22.2 to 80.4 pCi/kg (wet weight). These detections are assumed to ,
be from fallout from the Chernobyl reactor accident. All other gamma emitters were below the detection level. There was one detection of cesium-137 at station 15 in the sample collected in January at a level of 318 pCi/kg (wet weight). Cesium-137 has been detected sporadically in recent years and has been attributed to global fallout from past atmospheric weapons testing. r 79 i,
a 1 1 S T E N FN - E OI DM TEE R0TR O O O O O O E0RU BROS MNPA UOEE NNRM N O I T A C E E E E E E E OM% LA EA N O N O N O N O N O N O LMR N N N N N N O R T N O C
)
0 6 0 ) 8 ) )8 ) ) 8 9 )5 24 1 1 )1 ) 1 E 22 /1 / / 23 2 NG /9 2 - 1 1 /< / 9 , AN 2 - (0 ( ( 22 1 - 3 1 N EA (9 59 0 2 ( ( 3 3 A MR 76 93 38 7
/ E 92 54 4 8 72 0 8 R M 5( 9( 5 3 1( 4 Y 3 E N R 3 B T O A - M S I n M 0 E E T o M 5 C H C E E E E E E U E G E S S S S S S n S O D I R E E E E E E o N H I i M o D ) ) ) )
y
)
y
)
y t . A T t H y y y i 9 R E T .D r r r r r r s7 G K , I N a a a a a a o9 O C 1 W EA v v v v v v P1 R O M - P D Y N AE s s s s s s l r R O NC e e e e e e ae G A I N l l l l l l cb N U T A i i i i i i i m I N A T m m m m m m ne R A C - S ( ( ( ( ( ( h v O J O I co T L D 5 5 1 1 5 5 eN I 1 1 2 2 1 1 T 6 N , 2 O h1 M c E S nn L L N ao B A O ri A T I B s T N N T i E O A ) Cv . M I C 0 R e N T O 0 ) ) NR O A L ) )8 ) ) )8 7 S ._ R T )5 94 9 9 91 )0 U , I S - R E. 92 /1 / / /3 94 m _ V O NG /9 9 - 1 1 5 - / - na N R T AN 6 - (0 ( ( (2 24 ir E E A EA (5 98 0 2 ( g
- 8. 2 W A C MR 60 73 53 do L O I I 01 24 4 8 52 36 er A P N D 4( 6( 5 3 9( 2(
irP C I N I R G I ug G A R qn O E I L ei L L V L rr O C A o I U , dt D N Y ni A T an ._ R A N T o _ N U I dM N O M N) e A C I O1 nl . L I( - a H T A S RFC) T - - - - ift en -. R I EOED d e n O U W TL y N O O EL sr L L D( aor 9 9 9 9 9 9 9 ni DR ov NES i n ABE tE MSD c SUYE el INLM t a S AR ec YLNO di LAAF 3 4 7 8 g AT R a 0 3 3 2 f o ~ NOFE ATOP m7e a 0 4 1 u 1 s 1 s 2 h ol o G B K R C C T iti d
)
T iR ma N l E e Y M rl m A W E R n eb wa H U o T S lot p A A it) e P E at sc DM t e ic RE ew g( A OLF D PO e L n MM V g L a IUAT SI
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9 9 3 3 3 30 5 7 31 9 9 2 7 3 0 i i i i - i 1 17 7 7
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C 0 38 0 2 5 3 2 8 2 9 6 6 8 8 4 3 i 1 0 0 00 0
- 181 32 2 2 7 8 2 s <<< ( < < < <
C 8 8 3 3 N O I T 2 2 A T . 5 5 E 3 1 1 6 G 0 0 0 00 0 0 0 8 E 1 192 42 i 3 1 1 i 9 V - <<< < < < < < 1 / u 0 0 D R
- O 4 4 O a 5 5 A F m N g N N i A I S ) ) ) ) ) ')
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E. DIRECT RADIATION EXPOSURE PATHWAY
- 1. TLD Dosimeters Thermoluminescent dosimeters (TLDs) determined environmental radiation dose rates and the results are contained in Table 29. A TLD badge of four readout areas each was deployed quarterly at 12 locations around the periphery of the plant. The mean values of four readings (calibrated individually for response to a known dose and for intransit dose) are reported.in this table. Individual measurements of external rar11ation levels in the environs of the North Anna site had an average dose of 5.7 mR/ standard month with a range of 4.3 to 8.2 mR/ standard month. The control station, No 24 had an average reading of 5.1 mR/ standard month with a range of 4.4 to 6.1 mR/ standard month. The highest dose was at station 23, Aspen Hills, 0.9 miles, 158 degrees SSW, with a reading of 7.5 mR/ standard month and a range of 7.0 to 8.0 mR/ standard month.
Sector TLDs are deployed quarterly at thirty-two locations in the environs of the North Anna site. Two badges are placed at each location. The results are presented in Table 30. The average level of q the 32 locations (two badges at each location) was 6.7 mR/ standard i month with a rar.ge of 3.9 to 10.2 mR/ standard month. The six control TL0s showed an average reading of 5.4 mR/ standard month with a range of 4.1 to 6.6 mR/ standard month. Two of the badges were vandalized 1 during the third quarter; that is the set at station SSW-19 and SSW-51. The highest dose levels were at station SW-53 with an average level of 1 9.1 mR/ standard month and a range of 8.0 to 9.3 mR/ standard month. The pair of SW-53 had a dose reading of 8.7 mR/ standard month with a range l , of 8.1 to 9.2 mR/ standard month. 1
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On one figure the results of the environmental TLDs are plotted from 1977 through 1985 in mR/ day. For 1986 the results were plotted in mR/ standard month on a second figure. For the period 1985 through 1986, the external radiation levels have remained constant at approximately 0.2 mR/ day (or 6 mR/ standard month). The sector TLDs have been in use since 1984 and the results for 1984 through 1986 are plotted on the same two figures discussed above. The results of the sector TLDs are comparable to the results of the environmental TLDs. 1 I i 83
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l L l' ! V. CONCLUSIONS l The results of the 1986 Radiological Environmental Monitoring Program for the North Anna Nuclear Power Station have been presented. The Chernobyl [ nuclear accident on April 25, 1986 produced fission-related isotopes which I were detected in the vicinity of the North Anna Nuclear Power Station from May 5 through June 30. During the remainder of the year the results were as expected for normal environmental samples, Naturally occurring activity was observed in sample media in the expected activity ranges. Occasional samples of nearly all media showed the presence of man-made isotopes. These have been discussed individually in the text. Observed activities were at very low concentrations and had no significant dose consequence. As a method of referencing the measured radionuclides concentrations in f sample media to the dose consequence, the data may be compared to the Reporting Level Concentrations listed in the NRC Regulatory Guide 4.8. These concentrations are based upon 25% of the annual dose commitment i recommended by 10CFR50, Appendix I, to meet the criterion "As Low as is Reasonably Achievable." Specific examples of sample media with positive
]
analysis results are discussed below. 1 AIRBORNE EXPOSURE PATHWAY Air particulate gross beta concentrations of all the indicator locations for 1986 appear to follow the gross beta concentrations at the control location. Elevated gross beta concentrations, attributed to Chernobyl, were measured at all locations during the five week period 1 beginning May 6. Gamma isotopic analysis of the particulate samples j i identified the majority of the gamma emitting isotopes as natural products l 91 l l _________ ----_ -- _ i
L (beryllium-7 and potassium-40). The second quarter composites also had measurable concentrations of three fission isotopes (attributed to Chernobyl): (ruthenium-103, cesium-134 and cesium-137). These were detected at all locations. No man-made activity was found in the particulate media during the other three quarters. Air iodine-131 was found in charcoal filters during the same five week period from May 6 to June 4. No iodine-131 was detected in the other three quarters indicating that the concentrations detected were from the Chernobyl accident and decayed quickly due to the short half-life of iodine-131. The precipitation samples collected monthly continued to have low levels or undetectable levels of tritiym as in previous years. There was one detection of beryllium-7 and one detection of cesium-137 at a trace i level in the semi-annual composite for the first six months of the year. This is similar to results in previous years. The twelve soil samples, collected triannually, contained the natural nuclides potassium-40, radium-226 and thorium-228. Among the twelve there were three detections of the fission product strontium-90 and light detec-tions of cesium-137. These results are similar to the results obtained in 1983 when there were three detections of strontium-90 and twelve detections of cesium-137 at statistically similar levels. These detections occurred in preoperational samples and may be attributed to fallout from previous atmospheric weapons testing. I WATERBORNE EXPOSURE PATHWAY No man-made or natural isotopes were monitored in the surface water of Lake Anna except tritium. The tritium at the discharge lagoon was 3918 pCi/f. In 1985 the tritium level was 3593 pCi/2. The preoperational level 92
was 150 pCi/E and has been rising since 1977. The tritium level upstream of the site was 2883 pCi/l as compared with 2990 pCi/E in 1985. This is )) particularly significant since it is upstream of the site. ) i River water collected from the North Anna River, 5.8 miles downstream of the site had a tritium level of 4020 pCi/f. The level in 1985 had been 3258 pCi/f. No other gamma emitters were detected except naturally occurring potassium-40. The samples of surface water collected by the Commonwealth of Virginia at the discharge lagoon and upstream of the plant yielded similar results. The level of tritium monitored at the discharge lagoon was 3130 pCi/t and 1183 pCi/E upstream of the plant. These results I indicate that the effluent releases from the reactor consisted mainly of tritium. The concentrations found at the discharge lagoon were 13.1% of the reporting level for water samples. Ground water from the environmental well on site contained no gamma 1 emitters. The average level of tritium in ground /well water is 198 pCi/l which is a low environmental level. AQUATIC PATHWAY Sediment / silt samples provide a sensitive i :dicator of discharges from nuclear power stations. The sediment from North Anna environmental samples indicated that a number of man-made isotopes were present. Cesium-137 was monitored at all six stations. Cesium-134 was monitored at all stations in the spring sample and one station in the fall sample. Manganese-54 and cobalt-60 were monitored in the spring sample downstream from the site. Cesium-137 was monitored in preoperational samples of aquatic sediment; however, additional man-made isotopes appear to have accumulated. Silt contamination does not provide a direct dose pathway to man. 93
The samples of shoreline soil monitored downstream of the site contained l no cesium-134 and cesium-137 occurred at a level 35% lower than in sediment samples. No cobalt-60 or other neutron activation products were found. I INGESTION PATHWAY
.l i
Iodine-131, attributed to the Chernobyl accident was measured in four i i milk samples using the radiochemical separation method during May and June. f Cesium-137 was detected in seven milk samples after May,1986 and the most probable source was the Chernobyl accident. Cesium-137 has been detected occasionally in previous years and then was attributed to past atmospheric nuclear weapons testing. Strontium-90 was measured in all of the milk samples. The values were comparable to the levels in 1985 and somewhat j lower than preoperational years. Strontium-90 from those years is attributed to past atmospheric nuclear weapons testing. The Chernobyl accident does not appear to have affected strontium-90 levels in the environment. No j strontium-89 was detected in any of the milk samples. Naturally occurring potassium-40 was measured in all the milk samples at normal environmental levels. Activity in fish and vegetation samples along with milk does present a direct dose pathway to man. Fish samples in 1986 showed the presence of the man-made isotopes cesium-134 and cesium-137. These isotopes were at an activity level somewhat higher than preoperational levels but statistically similar to levels in 1985. Only cesium-137 was measured in preoperational environmental fish samples. The levels of activity in 1986 of cesium-134 was 13.1% of the reporting level and cesium-137 was 19.8 of the reporting level. Vegetation samples contained the man-made isotopes ruthenium-103, cesium-134 and cesium-137 in samples collected after the accident at the 94
Chernobyl reactor in the Soviet Union. Cesium-137 occurred prior to and ! after the accident. The levels in 1985 and in preoperational samples were i statistically similar to the 1986 level of 95.8 pCi/kg (wet weight). Direct Exposure Pathway The direct exposure pathway as measured in the environment of the 1 North Anna site by thermoluminescent dosimetry has remained essentially the l l same since the preoperational period in 1977 at 5.7 milliroentgen per month l or 0.19 milliroentgen per day. The average dose levels monitored have showed a normal fluctuation about these levels which are less than the estimated whole body dose due to natural terrestrial and cosmic radiation and the internal dosage from natural radionuclides. Based upon the evidence of the environmental monitoring program the , station appears to be operating within regulatory limits. Thus, no unusual ' radiological characteristics were observed in the environs of the North Anna Nuclear Power Station in 1986. i
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l VI. LAND USE CENSUS A. ' Technical Specification 3.12.2 requires that a Land Use Census be conducted within a distance of 8 km (5 miles) from North i Anna on an annual basis. This census identifies the location of the nearest milk cow, the nearest resident and the nearest garden of greater than 50 m2 (500 ft.2) producing broad leaf vegetation in each of the 16 meteorological sectors. B. The results of the Land Use Census are used to calculate the principal exposure pathway from gaseous effluents. This pathway analysis is compared to previous analysis to determine the i requirements for modification of the Radiological Environmental Monitoring Program and/or the calculational model used for determining dose contributions to the unrestricted area. l l l l l 97
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.ESE 2.69 th 1.$7km 8.85 km 6.20 km
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.s NNke 1.93 km 1.45 km 3.62 kr 3.36 km t ,
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- NOTE: No milk cows or miik goats within a five mile radius of North Aqna Poser Statiori.
k ( [ 98 i,. I ,
(AUGUST 04-08) Figure 2 VIRGINIA POWER - NORTH ANNA POWER STATION l ANNUAL RADIOLOGICAL ENVIRONMENTAL LAND USE CENSUS MAP FOR 1986 S k .. .
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i VII. SYNOPSIS OF ANALYTICAL PROCEDURES i i, l i l 100
Vll. SYN 0PSIS OF ANALYTICAL PROCEDURES Section VII is a synopsis of the analytical procedures performed on samples collected for the North Anna Power Station Radiological Environmental Monitoring Program. All analyses have been mutually agreed upon by VEPC0 and Teledyne Isotopes and include those requested by the USNRC Regulatory Guide 4.8,BTP, Rev. 1, November 1979. ANALYSIS TITLE PAGE Gross Beta and Gross Alpha of Air Particulate Samples................. 102 Gross Beta An alysi s of Water Samples . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 103 Analysis of Samples for Tritium....................................... 104 Water............................................................ 104
-Analysis of Samples for Iodine-131.................................... 105 Milk or Water.................................................... 105 Gamma Spectrometry of Samples......................................... 106 Milk and Water...................... ............................ 106 Dried Solids cther than Soils and Sediment....................... 106 Fish.............................................................106 Soils and Sodiments.............................................. 106 Charcoal Cartridge s ( Ai r Iodine) . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 106 Air Particulate................................................. 106 Environmental Dosimetry............................................... 108 An alysi s of Samples for St ronti um-89 and -90. . . . . . . . . . . . . . . . . . . . . . . . . . 109 To t a l W a t e r . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 9 i Mi1k............................................................. 109 So i l a n d S e d i m e n t . . . . . . . . . . . . .. . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 10 9 O r g a n i c So l i d s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 10 A i r P a r t i c u l a t e s . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . . 1 10 101 l
)
i
GROSS BETA AND GROSS ALPHA ANALYSIS OF AIR PARTICULATE SAMPLES After a delay of five or more days, allowing for the radon-222 and radon-220 (thoron) daughter products to decay, the filters are counted in a gas-flow proportional counter. The sample is counted at one operating voltage for gross beta and then changed to a second operating voltage for gross alpha. Calculation of the results, the two sigma error and the lower limit of detection (LLD). RESULT (pCi/m3) =((S/T) - (B/t))/(2.22 V E) TWO SIGMA ERROR (pCi/m3) =((S/T2 ) + (B/t 2))1/2 /(2.22 V E) LLD(pCi/m3) =4.66 (Bl /2)/(2.22 V E t) where: S = Gross counts of sample B = Counts of background (different for alpha and beta) E = Counting efficiency (different for alpha and beta) T = Number of minutes sample was counted t = Number of minutes background was counted V = Sample aliquot size (cubic meters) l [ 102
GROSS BETA ANALYSIS OF WATER SAMPLES One liter of sample is evaporated to near dryness and the residue is trans-ferred to a tared, 2" diameter planchet and final evaporation to dryness takes place under heat lamps. The planchet is weighed and then counted in a gas-flow proportional counter. Calculation of the results, the two sigma error and the lower limit of detection (LLD). RESULT (pCi/f) =((S/T) - (B/t))/(2.22 V E) TWO SIGMA ERROR (pCi/f) =((S/T2) + (B/t2))1/2 /(2.22 V E) LLD (pCi/f) =4.66'(B1 /2)/(2.22 V E t) y where: ' S = Gross counts of sample f B = Counts of background E = Counting efficiency T = Number of minutes sample was counted t = Number of mirutes background was counted V = Sample aliquot size (liter) 1 4 103 l
' ANALYSIS OF SAMPLES FOR TRITIUM 4
Water- q Approximately 2'ml of water are converted to hydrogen by passing the water', j
. heated to its vapor state, over a granular zinc conversion column' heated to 400* C. .The hydrogen is loaded into a one liter proportional detector and the volume is determined by recording the pressure.
L 'The proportional detector is passively shielded by lead and steel and an electronic, anticoincidence system provides additional' shielding from cosmic
-rays..
Calculation of the results, the two sigma error and the lower limit detec-L tion (LLD) in pCi/f: RESULT
= 3.234 TN YI N G - B)/(CN Y) S TWO SIGMA ERROR
= 2((CG + B)At)1/2 3.234 T g V N /((CNYS)(C g-B))
LLD.
= 4.66 (3.234)T N NY ( G) / /(AtNCSY) where: T N
= tritium units of the standard 3.234 = conversion factor changing tritium units to pCi/t 1 V" = volume of the standard used to calibrate the l efficiency of the detector in psia V
3
= volume of the sample-loaded into the detector in psia i
C N
= the cpm activity of the standard of volume V N
C G
= the gross activity in cpm of the sample of volume V 3 1 and the detector volume B = the background of the detector in cpm l At = counting time for the sample i
104
Ll l i ANALYSIS OF~ SAMPLES FOR 10 DINE-131 i Milk' or. Water Two liters of' sample are first equilibrated with stable iodide carrier.. A batch treatment with' anion exchange resin is used to remove iodine from the sample. The . iodine is then stripped from the resin with sodium hypochlorite ) solution, is reduced with hydroxylamines hydrochloride and is extracted-into !. ~ carbon tetrachloride as free iodine. It is then back-extracted as iodide into sodium bisulfite solution and is precipitated as palladium iodide. The precipitate'is weighed for chemical yield and is mounted on a nylon planchet for low level beta counting. The chemical yield is corrected by measuring the stable iodide content of the milk or the water with a specific ion electrode.
. . R Calculations of results, two sigma error and the lower limit of detection (LLD) i in pCi/E ,
RESULT = (N/4t-B)/(2.22 E V Y OF)
.TWO SIGMA ERROR =
2((N/At+B)/At)1/2(2.22 E V Y DF) LLD = 4.66(B/At)1/2 /(2.22 E V Y DF) where: N a totalcountsfromsample(counts) j At = counting time for sample (min) l B = background rate of counter (cpm) _l 2.22 = dpm/pCi j V = volume or weight of sample analyzed Y = chemical yield of the mount or sample counted , i DF = decay factor from the mid-collection date to the i counting date l E = efficiency of the counter for I-131, corrected for '! self absorption effects by the formula E = E (exp-0.0061M)/(exp-0.0061M ) 3 s E S
= efficiency of the counter determined from an I-131 standard mount '
M g
= mass of PdI2 on the standard mount, mg M = mass of PdI 2 on the sample mount, mg 105
GAMMA SPECTROMETRY OF' SAMPLES Milk and Water A 1.0 liter Marinelli beaker is filled with a representative aliquot of the sample. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse _ height analysis. Dried Solids Other Than Soils and Sediments ,
-A large quantity of the sample is dried at a low temperature, less than 100*C.
As much as possible (up to the total sample) is loaded into'a tared 1-liter , Marinelli.and weighed. The sample is then counted for at least 1000 minutes i with a shielded Ge(L1) detector coupled to a mini-computer-based data acquisi- i tion system which performs pulse height analysis. 1 Fish ! As much as possible (up to the total sample) of the edible portion of the sample is loaded into a tared Marinelli and weighed. The sample is then counted for at least 1000 minutes with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height i analysis. '
' Soils and Sediments j Soils and sediments are dried to a low temperature, less than 100*C. The soil or sediment is loaded fully into a tared, standard 300 cc container and weighed. The sample is then counted for at least six hours with a shielded '
Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height analysis. Charcoal Cartridges ( Air Iodine) Charcoal cartridges are counted up to five at'a time, with one positioned on . the face of a Ge(Li) detector and up to four on the side of the Ge(Li) ' detector. Each Ge(Li) detector is calibrated for both positions. The , detection limit for I-131 of each charcoal cartridge can be determined (assum- 1 ing no positive I-131) uniquely from the volume of air which passed through l it. In the event I-131 is observed in the initial counting of a set, each ! charcoal cartridge is then counted separately, positioned on the face of the detector. Air Particulate The four or five (depending on the calendar month) air particulate filters for a monthly composite for each field station are aligned one in front of another and then counted for at least six hours with a shielded Ge(Li) detector coupled to a mini-computer-based data acquisition system which performs pulse height anolysis. 106
A mini-computer software program defines peaks by certain changes in the slope of the spectrum. The program also compares the energy of each peak with a library of peaks for isotope identification and then performs the radio-activity calculation using the appropriate fractional gamma ray abundance, half life, detector efficiency, and net counts in the peak region. The calculation of results, two sigma error and the lower limit of detection (LLD) in pCi/ volume or pCi/ mass: RESULT = (S-8)/(2.22 t E V F DF) TWO SIGMA ERROR = 2(S+B)1/2/ (2.22 t E V F DF) LLD = 4.66(B)1/2/ (2.22 t E V F DF) where: S = Area, in counts, of sample peak and background (region of spectrum of interest) B = Background area, in counts, under sample peak, deter-mined by a linear interpolation of the representative backgrounds on either side of the peak l t = length of time in minutes the sample was counted i 2.22 = dpm/pCi 1 E = detector efficiency for energy of interest and geometry of sample V = sample aliquot size (liters, cubic meters, kilograms, or grams) F = fractional gamma abundance'(specific for each emitted gamma) DF = decay factor from the collection to the counting date t 4 107
l
. ENVIRONMENTAL D0SIMETRY Teledyne Isotopes uses a.CaSO4-:Dy thermoluminescent dosimeter (TLD) which the company manufactures. 'This material has a high light output, negligible
. thermally induced signal loss ~(fading), and negligible self dosing. The energy response curve (as well as.all other features) satisfies NRC Reg. Guide 4.13. Transit doses are accounted for by use of separate TLDs.
Following the field exposure period.the TLDs are placed in a Teledyne Isotopes-Model~8300. One fourth of- the rectangular TLD is heated at'a time and the-measured light emission (luminescence) is recorded. The TLD is then. annealed and exposed to-a known Cs-137. dose; each area is then read again. This provides a calibration of each area of~each TLD after every field use. The transit controls are' read in the same manner. Calculations of results and the two sigma error in net milliroentgen (mR): RESULT = D = (Dy+02 +D +D )/4 3 4 TWO SIGMA ERROR =y 2((D -D)2+(D 2 -D)3 +(D -D)2+(D 4 -D)2)/3) M where D y = the net mR of area 1 of the TLD, and similarly for 02 , 0 3, and D4 l Dy =1 7 K/Ry-A 1 7
= the instrument reading of the field dose in area 1
, K = the known exposure by the Cs-137 source R
y = the instrument reading due to the Cs-137 dose on area 1 A = average dose in mR, calculated in similar manner as above, of the transit control TLDs L 108 u__-_ . _ - _ _ .
m h'
' ANALYSIS OF SAMPLES FOR STRONTIUM-89 AND -90 WATER Stable strontium carrier is added to 1 liter of sample and the volume is
. reduced by evaporation. Strontium is precipitated as Sr(NO3)2 using
-nitric acid. A barium scavenge and an iron (ferric hydroxide) scavenge are performed followed by addition of stable yttrium carrier and a 5 to 7 day period for. yttrium ingrowth. Yttrium.is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a i nylon planchet and'is counted in a' low level beta counter to infer Sr-90
' activity. ~ Strontium-89 activity is determined by precipitating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon
. planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. i MILK
' Stable strontium carrier is added to 1 liter of sample and trichloroacetic acid (TCA) is added to produce a curd. The curd is separated by filtration and is discarded. An oxalate precipitation is performed on the f.iltrate and the. precipitate is ashed in a muffle furnace. The ash is dissolved and strontium is precipitated as SrN03 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then performed.
Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10
- days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and~is counted.in a low level beta counter to infer Sr-90 activity. Strontium-89 is determined by precipitating SrC03 from the sample after yttrium separation. This' precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting.
S0ll AND SEDIMENT The sample is first dried under heat lamps and a 10 gram aliquot is taken. Stable strontium carrier is added and the sample is leached in nitric acid. The mixture is filtered and the liquid portion is reduced in volume by evapo-ration. Strontium is precipitated as Sr(NO )2 3 using fuming (90%) nitric acid. A barium chromate scavenge and an iron (ferric hydroxide) scavenge are then' performed. Stable yttrium carrier is added and the sample is allowed to stand for 7 to 10 days for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to l infer Sr-90 activity. Strontium-89 activity is determined by precipitating ( SrC03 from the sample after yttrium separation. This precipitate is mounted
- on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for
' low level beta counting.
109
Organic Solids A 200g wet portion of the sample is dried and then ashed in a muffle furnace. Stable.strontiun carrier is added and the ash is leached in nitric acid. The sample is filtered and the volume is reduced by evaporation. Strontium is precipitated as Sr(NO 3 )2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium ~ carrier and a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitate as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is deter-mined by precipitating SrC0 3 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with an 80 mg/cm2 aluminum absorber for low level beta counting. Air Particulate Stable strontium carrier is added to the sample and it is leached in nitric acid to bring deposits into solution. The mixture is then filtered and the filtrate is reduced in volume by evaporation. Strontium is precipitated as Sr(NO 3 )2 using fuming (90%) nitric acid. An iron (ferric hydroxide) scavenge is performed, followed by addition of stable yttrium carrier ano a 7 to 10 day period for yttrium ingrowth. Yttrium is then precipitated as hydroxide, is dissolved and re-precipitated as oxalate. The yttrium oxalate is mounted on a nylon planchet and is counted in a low level beta counter to infer strontium-90 activity. Strontium-89 activity is determined by precipi-tating SrC03 from the sample after yttrium separation. This precipitate is mounted on a nylon planchet and is covered with 80 mg/cm2 aluminum absorber for level beta counting. Calculations of the results, two sigma errors and lower limits of detection (LLD) are expressed in activity of pCi/ volume or pCi/ mass: 1 RESULT Sr-89 = (N/At-BC"0A )/(2.22 V Y3DF SR-89 ESR-89) TWO SIGMA ERROR Sr-89 = 2((N/At+B A )/At) 2/ (2.22 V Y3DF SR-89 ESR-89) C +0 LLD Sr-89 = 4.66((BC+BA )/At)1/2/ (2.22 V Y3 0F SR-89 ESR-89) RESULT Sr-90 = (N/At - B)/(2.22 V Y3Y2DF IF E) TWO SIGMA ERROR Sr-90 = 2((N/At+B)/At)1/2 / (2.22y VY 2YDF E IF)) LLD Sr-90 = 4.66(B/At)1/2 /(2.22 V Y y Y2 IF DF E) ( 110 L-- - - -
h L-p l l-L- I, o l l I VIII. EPA INTERLABORATORY COMPARISON PROGRAM l 111
VIII. EPA INTERLABORATORY COMPARIS0N PROGRAM Teledyne Isotopes participates in the US EPA Interlaboratory Comparison Program to the fullest extent possible. That is, we participate in the r program for all radioactive isotopes prepared and at the maximum frequency
~
l of availability. In this section trending graphs (since 1981) and the 1986 l data summary tables are presented for isotopes in the various sample media q applicable to the North Anna Stations Radiological Environmental Monitoring Progr am. The footnotes of the table discuss investigations of problems encountered in a few cases. j
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pr l rd sh n f e b a p - i cl r s sn ah xI sw S s hi o ,me aea on i 7 ei l e a U t ct r 0 an m ri m 3sm s ns w3 l . irt .si t gg g e 1 yr ne i u O u g h a n 3 a ani tl l e ei o 3C s k wpo 4 st i s rsb sat er ni Oa A e / c i n st ooo C ne t o a v CN PR i ds eho an2 fl r ad nt e a E C oea rT c wu p r ea yr N s d p oim e oe d s. ose vr bP s ee f rg w e ech eea f ub eo h e t u e oi .h s t t e o sb d cL as r ct s dtt ae nb n nil a e . u Ds a i a ei ch n u e ovl el my m I t re t mf t i od e i ei h rl . s eoe rio s h cab t rw t n oi od i hb r ol il t h aP e f r ol d s t ah p m h ei e t r 7 f e ro t e e y nl t eao t v w ryo b 3 ot et i l l y rmt e at n i 1 f pc t y i a s1 e gt nl e i l t - ni a a a n 2h sio i r svd ans ef sf h9 M a a t t sb ye ria cec e as t8 s y l l t w eth d t e wi - l t d sl d u2e ei t c yi r rh . t d m Tl o i nn s h vvs l as cvo ut s sa eu u o O o eet ei t i i nef o i i s vi es f e y rh l t l f eh e ff s s et t e l e t n cu hT i sy oy aR r p .b e i eas rt cac 0 l lyg n i n l o D o ms ee k e i i wn 9 na ai er
) f ai s r vd i sr af . f e - en nm bt s
sst h oe pi oe fti rea ar s t yl t bl sh e e r el c St o s N n t sl u at t s seu ui rs sf ih O o i i as e t e e emt esf rii i r g I C n h ne h ee hth hou h ef ohh h e ti T ( U T a r T bs tat T sf T re Ft t T p Ih A AR : PA S EP E E T ) ) ) ) ) ) ) ) ) R O c d e f g h i j k P N ( ( ( ( ( ( ( ( ( _g s li i! '
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IX. REFERENCES l 1 i I l
'1 l
i l l 146
i i IX. REFERENCES f'
- 1. United States Nuclear Regulatory Commission, Regulatory Guide 4.8
" Environmental Technical Specifications for Nuclear Power Plants",
December, 1975.
- 2. Virginia Electric and Power Company, North Anna Power Station Technical Specifications, Units 1 and 2.
l
- 3. NUREG 0472 " Radiological Effluent Technical Specifications for PWRs", Rev. 3, March 1982.
4 United States Nuclear Regulatory Commission Regulatory Guide 1.109, Rev.1, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10CFR50, Appendix I", October, 1977.
- 5. USNRC Branch Technical Position, " Acceptable Radiological Environ-mental Monitoring Program", Rev.1, November 1979.
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