0CAN058402, Annual Environ Radiological Monitoring Rept,1983
| ML20092N919 | |
| Person / Time | |
|---|---|
| Site: | Arkansas Nuclear  |
| Issue date: | 12/31/1983 |
| From: | John Marshall ARKANSAS POWER & LIGHT CO. |
| To: | Jay Collins NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION IV) |
| References | |
| 0CAN058402, CAN58402, NUDOCS 8407050210 | |
| Download: ML20092N919 (71) | |
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l 1983 ANNUAL ENVIRONMENTAL RADIOLOGICAL i t
MONITORING REPORT FOR !
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1.0 INTRODUCTION
This report summarizes the Environmental Radiological Moni-toring' Program conducted for the Arkansas Nuclear One-Units 1 and 2 during the calendar year 1983. All sample analyses and data interpretation were performed by the staff of Arkansas Power and Light Company.
1.1 PLANT AND LOCATION Arkansas Nuclear One - Units 1 and 2 are both lighwater cooled pressurized water nuclear reactors located approximately 5.0 miles west of Russellville, Arkansas. ANO Unit 1 began commercial operation in December 1974 and the second unit at the same site, ANO Unit 2, followed in Itarch 1980. Lake Dardanelle is the source of the circulating cooling water for A!!O Unit 1, and ANO Unit 2 is cooled by a cooling tower, also dependent upon Lake Dardanelle water.
1.2 ENVIRON!! ENTAL 110NITORiflG PROGRAM The Environmental itonitoring Program was established based upon the Environmental Technical Specifications for ANO Unit 1. These specifications have remained essentially the same, except for the addition and deletion of sampling stations where milk, ground water, or food products are collected. The 1983 Environmental Radiological ltonitoring Report is governed by present environ-mental technical specifications. The 1983 report includes summaries, interpretations, and statistical evaluation of the a
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o'f the results of the radiological environmental sur:,te111ance
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activities at Atl0. ' Table 1-1 details the surveillance pro- i gram listing sample type, frequency of collection, and the
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method of analysis used. Table 1-2 lists the sample loca-tion and, type of samples collected at each locatidn. ;
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y A t 1.3 C0tlTROL LOCATl0tlS ,
During the calendar yeabl983, the following locations were des'ignated ab control stations along with the respective sample type add analysis.
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a) AP&L's SubAtation a6Danville, Arkansas (Station #7) i
- 1) Air Particulate ,
- 2) Air Iodine ,
- 3) Precipitation N ,
x -
- 4) Vegetation y :
, 5) Soil i y 6); TLD' %
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i b) Pin'eyCreekAreal{ Station #16) ll 1)' Lake Water
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- 2) 'dottom' Sediment '
- 3) ,
Aqu'Itic Biota (including fish)
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E c)- R. A. Young's Dairy (Station #23)
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- 1) 1111k '
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- 2) Vegetation r
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r-2.0 INTERPRETATI0flS AtlD C0flCLUSI0flS Data collected from radiological analyses of environmental samples collected in the area surrounding the AN0 facility indicate no
, detectable environmental impact in excess of design objectives as a result of liquid and gaseous discharges from the ANO site during 1983. Also, no non-routine environmental radiological monitoring reports resulting from analyses of environmental samples were submitted to the U.S. NRC during 1983.
Sample types that indicated activation or fission-produced radio-
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isotopes present are discussed in the paragraphs below:
2.1 SAMPLES ASSOCIATED WITH AIR 110flITORIflG flone of the 311 samples collected from indicator locations for radiciodine in air (using activated charcoal filters) indicated iodine-131 activities greater than the lower limit of detection, which is 0.050 pCi per cubic meter of air.
Also, none of the 84 monthly composites of air particulate filters collected in the calendar year 1983, including the control air particulate samples from Danville, Arkansas indicated the presence of radioactive fission or activation products.
! TLD data collected for the calendar year 1983 is divided into two l categories . The first category includes the lithium fluoride (LiF)
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l TLDs which were collected and read quarterly, and the second cate-i gory includes LiF TLDs which were collected and read semi-annually l in 1983. The quarterly TLD data for 1983 indicated a total yearly l average dose for the forty-thnio indicator locations to be 70 mrem
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per year compared to the total yearly average dose of 63 mrem for 1982.
The control location at Danville, Arkansas (109 - 19.3 miles) indi-cated a total dose, based upon quarterly TLD's, of 56 mrem per year for 1983 compared to 59 mrem per year for 1982. Table 2.1.1 lists the total yearly average dose for the indicator location for the calendar years of 1981,1982, and 1983 compared to the total dose of background radiation (control station), also based upon quarterly TLD reports.
The difference between the indicator locations and the control loca-tion for quarterly TLDs results is not statistically significant.
The standard deviation for the indicator locations is 5.1 mrem annual dose. For a one sample t-test, (i.e., a single control compared to all indicator locations), a t-value of 1.72 is obtained.
This t-value does not indicate a significant difference between the control and indicator locations at the 95% confidence level. A t-value of greater than 2,06 would be necessary to indicate a signifi-cant difference.
Factors other than statistical fluctuations that may affect the variation in recorded dose include variations of up to 155 in response of the TLD chips to the same radiation exposure, different soil types at monitoring locations, and varying heights above ground level for TLD placement.
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.The TLDs collected every six months during 1983 indicated slightly l
lower readings than the quarterly TLDs, which is consistent with TLD readings recorded in 1982,1981, and 1980. The lower dose
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measurement for the dosimeters deployed in the field for six months compared to the quarterly readings is attributed to " fading" of the lithium fluoride chips. The TLDs collected every six months indicated a total yearly average dose for the indicator locations of 57 mrem, compared to 48 mrem per year for 1982. The six-month TLD's are located at six indicator locations and one control loca-tion. The control location indicated a total dose, base upon TLDs collected and read semi-annually, of 58 mrem.
The small difference in six month TLD data between indicator locations and control location is not significant. The standard deviation for the indicator locations is 7.5 mrem annual dose. A t value of 0.05 is calculated for a single sample t-test comparing the indicator loca-tions to the control . At the 95% confidence-level at t value of greater than 2.18 would be necessary to indicate any statistically significant difference.
!!ane of the 98 rain samples collected and analyzed in 1983, as in 1982, indicated the presence of radioactive fission or ' activation products. Analyses performed were gamma spectrometry.and gross beta.
2.2 SAMPLES ASSOCIATED WITH WATER I40NITORING Lake water samples are collected from five different sample sites in Lake DardanelTe rronthly, plus the Arkansas Department of Health and Arkansas Power and Light Company split a surface water sample from
-the ANO Discharge Canal monthly. Each laboratory analyzes the sample for gamma emitters. The surface water sample with maximum quantities of plant related radionuclides was collected from the ANO Discharge Canal. This surface water grab sample was collected by and split t
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t with the Arkansas Department of Health on January 17, 1983. The iodine-131 detected in the grab sample had a concentration of 3.8 E-8 pC1. per milliliter, and the value listed in 10 CFR 20 Appendix B, e Table II, Column 2, is3E-07 pCi per milliliter. The 10 CFR 20 j concentration limit given above is for liquids in unrestricted areas. :
The measured quantity was well below the 10 CFR 20 limit. l l
Other radioisotopes determined in grab sanples from the ANO Discharge '
Canal include Cobalt-58, Cobalt-60, Xenon-133 and Cesium-137. '
As in previous years, bottom sediments collected from the ANO Dis-charge Canal (0.1 mile 180 ) during 1983 indicated the greatest con- !
centration of radionuclides attributable to ANO operations. To i determine. the maximum dose to the skin of an individual ( a teenager) i and the maximum whole body dose exposure from sediments, dose calcu- l lations were performed according to the mathematical model for deter-' !
i mining external dose from sediment given by U.S. Nuclear Regulatory l Commission Regulatory Guide 1.109. Tables 2.2.1 and Table 2.2.2 give the results of these calculations for sanples collected from the ANO Discharge Canal in February and August 1983. The maximum external dose to the skin from sediments for all measurable radionuclides was approximately 0.2 mrem per year, and the maximum whole body dose was approximately 0.15 mrem per year.
.c According to AN0 Technical Specifications, the design objectives.for the dose to the whole body or any organ of an individual is 5 mrem per year as the result of release of liquid wastes. The value of 6
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a 0.20 mrem per year for maximum whole body dose or maximum external dose to skin of a teenager is well within the design objective criteria.
The 1983 fish samples collected include the three categories listed in. previous annual environmental radiological reports: 1) bottom feeder fish, usually buffalo and carp, 2) carnivorous fish, usually catfish, crappie and bass, and 3) plankton feeder fish, usually shad.
Edible portions of bottom feeder fish and carnivorous fish and whole plankton feeder fish are analyzed by gamma spectrometry for radio-nuclides. The highest level of reactor-produced radionuclides at-
' tributed to operations at ANO were found in whole plankton feeder fish collected September 9, 1983 frcm the ANO Discharge Canal (0.1 mile 180).
Dose calculations based upon the plankton feeder fish radioisotope concentrations were performed according to the mathematical model for detennining maximum total dose to total body from fish consump-tion given by the U.S. NRC Regulatory Guide 1.109. Although, shad are forage for carnivorous fish species, for this calculation it was assumed that shad serve as human food. Table 2.2.9 identifies the radioisotopes found in the plankton feeder fish, the amount of radioactivity present, and the contribution of the total maximum
. calculated dose for either whole body or specific body organs. ,
'According to these calculations , the maximum dose to adults to total l . body from plankton feeder fish consumption is about -1.0 mrem per f
year. ~ The value of 1.0 mrem per year is well within the design l objective criteria of 5 mrem per unit as defined in the AN0 Techni-l '
l cal Specifications for liquid wastes.
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Tables 2.2.3 through 2.2.10 identifies all radioisotopes found in the eight fish samples collected and analyzed in 1983. According to dose calculations given in U.S. NRC Regulatory Guide 1.109, the carnivorous sample fish collected from the ANO Discharge Canal on October 9,1983 revealed the highest dose from edible fish samples collected in 1983. The calculated maximum organ dose was 0.51 mrem per year.
In addition to the fish samples described above, edible portians of fish were collected by the Arkansas Department of Health. Edible portions of fish collected from the ANO Discharge Canal November 8, 1983 contained the highest levels of reactor-produced radionuclides for these split fish samples. In Table 2.2.3 and 2.2.4, dose cal-culations were performed according to the mathematical model given by U.S. NRC Regulatory Guide 1.109. The highest calculated dose to adults from consumption of fish split with the Arkansas Department of Health is 0.5 mrtm per year, which is also well within the design objective criteria of 5 mrem per year per unit.
Table No. 2.2.11 is a listing of concentrations of radionuclides detected in fish samples split with the Arkansas Department of Health collected during the calendar years 1978, 1979, 1980, 1981, and 1983. Figures 2.2.1 and 2.2.1 graphically depict the Cs-134 and Cs-137 concentrations given in Table 2.2.11.
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.The Spearman rank-correlation test was applied to the Cs-134 and Cs-137 activity concentrations in sport fish tissue given in Table 2.2.11.
Date of sample collection and activity concentration were ranked and the correlation calculated to determine if a significant increase in 8
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activity concentration has occurred during the five year period of 1978 through 1983. The calculated Spearman ranked-correlation co-efficient for Cs-134 is 0.393. At the 95% confidence level the Spearman coefficient would have to be greater than 0.714 for seven observations to indicate a positive correlation of Cs-134 activity concentration with increasing time. Similiarly, the Spearman co-efficient for Cs-137 is 0.430 and at the 95% confidence level the coefficient would have to be greater than 0.564 fer ten observations to indicate a positive correlation of Cs-137 activity concentration with increasing time. (William Volk, Apolied Statistics for Enaineers, 2nd Edition,ficGraw-Hill, New York, 1969, p. 366-368).
Whole mollusks samples were collected in April and October 1983.
Samples of live mollusks caged in the ANO Discharge Canal (0.1 mile
.180 ) indicated reactor-produced radionuclides present. Reactor-produced radionuclides found include Cobalt-58, Cobalt-60, Cesium-134, and Cesium-137. Radionuclide concentrations in mollusks are comparable to fish concentrations discussed above.
2.3 SAMPLES ASSOCIATED WITH TERRESTRIAL MONITORING Milk samples were collected by the split with the Arkansas Department of Health in all twelve months of 1983. Three indicator locations for -collection of milk at dairies and one control location, the R. A.
Young Dairy (12.0 miles 73 ), were active during 1983.
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. Monthly milk samples are analyzed for Iodine-131 by concentrating the iodine with anion exchange resin and counting the concentrated iodine sample in a low-background alpha / beta counting system. No I-131 was detected in any milk samples collected in 1983.
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In determining gamma emitters in milk samples, cesium-137 was detected in two samples collected from R.A. Young Dairy, the control dairy.
Strontium-89 and strontium-90 analyses in milk produced average strontium activities at indicator locations equivalent to 1982 4
and 1981 levels. Average strontium activity for indicator loca-tions during 1983, as in 1982 was also less than that determined for the control location. .
Vegetation samples were divided into two categories in 1983, pasturage vegetation and garden products vegetation. Of the 39 pasturage samples collected and analyzed in 1983, cesium-137 was the only gamma-emitting radionuclide determined in 3 pasturage samples.
Garden products vegetation was collected in June, July, and August 1983 from two separate gardens. Garden vegetation collected and analyzed included cabbage, lettuce, and tomatoes. No gamma-emitting radionuclides were detected in any garden products vegeta- i tion during 1983.
Soil samples were collected in flay and October 1983 from seven sampling stations each time. Cesium-137 was detected in thirteen of the fourteen soil samples. International fallout is the probable .
L source of this radionuclide. !!aganese-54 was detected in the sample ;
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taken in the spring at sampling site no. 3 (0.4 mile-4 ) however, I
only cesium-137 was detected at this location during the October 1983 sampling period.
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2.4 SAMPLES ?!0T COLLECTED Ill 1983 Caged mollusks were sampled in 1983 as representatives of benthic organisms. It is impossible to place a cage at location 15, the Dardanelle Dam area, because of the water depth. Naturally occurring benthos are not present in quantities sufficient for analysis, therefore, no benthic organisms were analyzed at sample station No. 15.
Also, most of the caged mollusks in the ANO Discharge Canal collected in October 1983 were dead upon retrieval and only the shells remained.
Gamma analysis was performed on the shells of these dead mollusks.
The net used for collection of plankton samples became inoperable during the August 1983 plankton sampling, and only one plankton sample was collected and analyzed during the second half of 1983.
To correct this, a pump has been purchased to collect and filter plankton samples in 1984.
DJring the week of December 18-24, 1983, a severe winter storm pre-vented the collection of air filters and air iodine cartridges from sample stations number 5 and number 7, the control location.
The air filter pumps continued to operate at these two locations, and the air filter samples and air iodine cartridges represented two weeks collection of air particulates and air iodine. Also, precipitation samples were frozen at the other two precipitation c
. sample stations and were not collected until December 28, 1983.
Forty-four lithium fluoride thermoluminescent dosimeters (TLDs) are placed in the environment around Af;0, most within a 10 mile 11
radius of the plant boundary and are recovered and read every three months. TLDs which were missing when TLD retrieval was conducted include TLD flo. 36 for the First Quarter 1983, TLDs No. 3 and 27 for the Second Quarter 1983, TLD flo. 25 for the Third Quarter 1983, and TLD Nos.13 and 25 for the Fourth Quarter 1983.
A rain sample, 022383Pil05 was accidentally disposed before gamma analysis was performed, however, gross alpha and gross beta analyses were performed. ,
2.5 COMPARIS0il 0F RESULTS OF EPA CROSS-CHECK PROGRAM The Technical Analysis Section of Arkansas Power and Light Company participates in the U.S. Environmental Protection Agency's Environ- [
mental Radioactivity Laboratory Intercomparison Studies Program. The major objective of this program is to assist laboratories involved in environmental radiation measurements to develop and maintain both an intra-laboratory and an inter-laboratory quality control program.
This is partially accomplished through a laboratory intercomparison studies program involving environmental media (milk, water and air) and a variety of radionuciides with activities at or near environmental levels.
During the calendar year 1983, the following sample types were received and analyzed: 4
- 1) Gross Alpha-Beta in Water - A one-liter sample for the analysis
.of gross alpha and gross beta activity.
- 2) Gamma in Water - A one-liter sample containing chromium-51, zinc-65, cobalt'-60, ruthenium-106, cesium-134 and cesium-137.
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- 4) Iodine-131 in Water - A four-liter sample containing iodine-131.
- 5) Strontium in Water - A one-liter sample containing strontium-89 and strontium-90.
- 6) EPA Blind in Water - A one-liter blind sample containing a mixture of radionuclides.
- 7) Milk - Four-liter milk sample containing potassium, strontium-89, strontium-90, iodine-131, cesium-137 and barium-140.
- 8) Air - a two-inch diameter air filter is distributed quarterly for gross alpha, gross beta, cesium-137 and strontium-90 analyses.
- 9) Low-level Water - A four-liter sample containing very low quantities of I-131.
- 10) Low-Level Milk - A four-liter sample containing very low quantities of I-131.
A report listing the results of the analysis containing the laboratory standard deviation, calculation of the normalized range, normalized deviation, sample standard deviation, and the grand average of all laboratories is mailed after each participating laboratory performs there independent determinations for each radionuclide involved in the study.
. Table 2.5.1 lists the various analyses that are performed, the radio-activity levels found in the EPA cross-check samples, and one standard deviation for a single determination. c If the Technical Analysis Section Environmental Laboratory results differ from the unknown results given by more than 3 standard deviations in the EPA cross-check reports, the instrument and procedure are checked for error.
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Table 2.5.2 lists the types of EPA cross-check samples received, the total number of analyses performed, and the average sample standard deviation, based upon three independent determinations for each radionuclide in each sample.
Most of the results were well within two standard deviations of the known values supplied by the U.S. EPA. The May 1983 EPA strontium-90 determination in water has been lower than the EPA values, and new efficiency curves were determined for strontium-90 in 1983. The September 1983 strontium in water was analyzed within two standard deviations for both strontium-89 and strontium-90.
Results from analyses for strontium-90 in EPA milk samples were outside the control limit of 3 standard deviations for the June,
~ 1983 samples. The October,1983 strontium-90 in milk samples results were outside the warning limit but within the control limit. ' Investigation in the areas of chemical separation techniques and counting instrument efficiency are continuing in an effort to reduce the degree of disagreement with the EPA values.
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TABLE 1-1 SAMPLE TYPE AND ANALYSIS I. AIR A. Particulate
- 1. Continuous 7-day samples, filters changes weekly (Eberline Model RAP-1 sample pumps, Gelman 47 mm glass fiber filters, calibrated to one cubic foot per minute (0.028m3 / min) air sampling rate), seven (7) locations.
- 2. Analyses
- a. Gross alpha
- b. Gross beta
- c. Gamma isotope on a monthly composite (each station) and on high beta levels (>100 DPM/ sample)
- d. Radiostrontium on quarterly composite if gamma isotopic analysis shows presence of Cs-137.
B. Iodine 131
- 1. Continuous 7-day samples, activated charcoal filter trap on inlet of air sampler downstream of particulate filter, changed weekly, seven (7) locations.
- 2. Analyses
- a. Iodine-131 C. Direction Radiation
- 1. Four (4) thermoluminescent dosimeters (LiF), seven (7) locations.
- a. Two (2) thermoluminescent dosimeters (LiF),
thirty-seven (37) locations.
- 2. Analyses
- a. Change and readout one set dosimeters quarterly at all 44 locations and one set semi annually at the first 7 locations. ,
D. Precipitation
- 1. Four (4) locations, samples collected weekly (as available).
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- 2. Analyses
- a. Gross beta
- b. Gamma Isotopic II. -WATER A. Lake Water
- 1. Samples (one gallon) monthly from five (5) locations (discharge canal, intake canal, and lake south of plant between discharge and intake). (Sample stations 8, 9, 10, 15, 16)
- 2. Analyses
- a. Gross beta (monthly)
- b. Gamma isotopic (monthly if gross beta exceeds 30 pCi/L and on quarterly composites)
- c. Tritium (quarterly composites)
- d. Radiostrontium (quarterly composites)
- 8. Bottom Sediments
- 1. Samples (~Kg) semi-annually from near the same locations as lake water. Station 15 sample to be taken in pool above dam.
- 2. Analyses
- a. Gamma isotopic
- b. Radiostrontium (anndal composites)
C. Ground Water
- 1. Samples (one gallon) quarterly from one onsite and two 4
offsite wells.
- 2. Analyses
- a. Gross alpha
- b. Gross beta
- c. Gamma isotopic
- d. Tritium D. Russellville City Water C
- 1. Samples (one gallon) monthly from system intake.
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- 2. Analyses
- a. Gross alpha
- b. Gross beta
- c. Gamma isotopic
- d. Tritium (quarterly composite)
- e. Radiostronium (quarterly composite)
E. Aquatic Biota
- 1. Semi annual samples are taken as available at or near the same sample points as lake water and bottom sediments.
Samples will be as large as practicable not to exceed 2Kg.
- 2. Analyses
- a. Gross beta (plankton)
- b. Gamma isotopic (fish flesh, plankton, benthic organisms, aquatic plants)
- c. Radiostrontium (benthic organisms, aquatic plants)
'F. Fish Bone
- 1. Annual sample (~500g bone) in the Fall. Sampled as in E.1 above.
- 2. Analyses
- a. Strontium 89-90 III. TERRESTRIAL A. Milk
- 1. One gallon samples will be taken monthly from farms or dairies within a ten-mile radius of plant.
- 2. Analyses Frequency
- a. Iodine-131 Monthly
- b. Strontium 89, 90 Quarterly
- c. Gamma isotopic Monthly B. Vegetation
- 1. Samples (~1Kg) of grass and leafy portions of other "
vegetatioli in the vicinity of the seven air sampling locations are taken in the Spring, Summer, and Fall seasons.
- 2. Similar samples of pasturage vegetation of dairies of farms sampled for milk within a ten-mile radius of the plant will be taken at time coinciding with those of 1 above.
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- 3. Food crops and leafy vegetables in the vicinity of the plant shall be collected as available at harvest time.
- 4. Analyses
- a. Radiciodine (upon collection) by gamma analysis
- b. Gamma isotopic C. Soil 1.
Samples sites sem (i-annually.~1.5 liters) are taken at each of the air samp
- 2. Analyses
- a. Gamma isotopic
- b. Strontium 89-90 determined annually.
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TABLE 1-2 SAMPLE LOCATION AND SCHEDULE Sample Direction and Sample Station Station # Distance from Plant Location Sample Types Sample Frequency Remarks 1 92 - 0.5 miles Near Meteoro- 1) Air Sample 1) Weekly 1) 7-day continuous-weekly logy on site 2) TLD 2) Quarterly 2) Readout and record at
- 2) Semi-annually stated frequency
- 3) Soil Sample 3) Semi annually 3) Spring and Fall-
- 4) Vegetation 4) 3 times / year 4) Spring, Summer and Fall
. 5) Precipitation 5) Weekly, as available 2 235 - 0.5 miles Near AP&L lodge 1) Air Sample 1) Weekly 1) 7-day continuous-weekly on site 2) TLD- 2) Quarterly 2) Readout and record at
- 2) Semi-annually stated frequency
- 3) Soil Sample 3) Semi-annually 3) Spring and Fall
- 4) Vegetation 4) 3 times / year 4) Spring, Summer and Fall 3 4 - 0.4 miles. South of Hershel 1) Air Sample 1) Weekly 1) 7-day continuous-weekly Bennet home 2) TLD 2) Quarterly 2) Readout and record at
- 2) Semi-annually stated frequency
- 3) Soil Sample 3) Semi-annually 3) Spring and Fall
- 4) Vegetation 4) 3 times / year 4) Spring, Summer and Fall
- 5) Precipitation 5) Weekly, as j available i 4 171 - 0.4 miles Near the May 1) Air Sample 1) Weekly 1) 7-day continuous-weekly Cemetery 2) TLD 2) Quarterly 2) Readout and record at
- 2) Semi-annually stated frequency
- 3) Soil Sample 3) Semi-annually 3) Spring and Fall j 4) Vegetation 4) 3 times / year 4) Spring, Summer and Fall i
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l TABLE 1-2 (Cent'd)'
SAMPLE LOCATION AND SCHEDULE Sample ~ Direction and Sample Station Station # Distance from Plant Location Sample Types Sample Frequency Remarks 5 298 - 8.5 miles At Ray Walter's 1) Air Sample 1) Weekly residence, 1) 7-day continuous-weekly
- 2) TLD 2) Quarterly 2) Readout and record at Knoxville,- 2) Semi-annually state frequency Jof.nson. County 3) Soil Sample 3) Semi annually 3) Spring and Fall
- 4) Vegetation 4) 3 times / year 4) Sprin0, Summer and Fall
- 5) Precipitation 5) Weekly, as available 6 109 - 6.8 miles At AP&L's 1) Air Sample 1) Weekly 1) 7-day continuous-weekly Russellville 2) TLD 2) Quarterly 2) Readout and record at Local Office 2) Semi-annually state frequency
- 3) Soil Sample 3) Semi-annually 3) Spring and Fall
- 4) VeDetation 4) 3 times / year 4) Spring, Summer and Fall 7 209 - 19.3 miles At AP&L's Sub- 1) Air Sample 1) Weekly 1) 7-day continuous weekly station in 2) TLD 2) Quarterly 2) Readout and record at Danville, Yell 2) Semi-annually County state frequency
- 3) Soil Sample 3) Semi-annually 3) Spring and Fall
- 4) Vegetation 4) 3 times / year 4) Spring, Summer and Fall
- 5) Precipitation 5) Weekly, as available 8 180 - 0.1 miles Mouth of 1) Lake Water 1) Monthly 1) Record status of plant Discharge Canal discharge operations
- 2) Aquatic Biota 2) Semi-annually 2) Summer and Winter
- 3) Bottom Sedi- 3) Semi-annually 3) Summer and Winter ments 9 160 - 1.8 miles South of Bunker 1) Lake Water 1) Monthly 1) Record status of plant Hill near Main discharge operations
' River Channel 2) Aquatic Biota 2) Semi annually 2) Summer and Winter
- 3) Bottom Sedi- 3) Semi-annually 3) Summer and Winter ments
r TABLE 1-2 (Cont'd)
SAMPLE LOCATION AND SCHEDULE Sample Direction and Sample Station Station # Distance from Plant Location Sample Types Sample Frequency Remarks 10 90* - 1.0 miles Mouth of inlet 1) Lake Water 1) Monthly canal
- 1) Record status of plant discharge operations
- 2) Aquatic Biota 2) Semi ar> 1ually 2) Summer and Winter 3)~ Bottom Sedi- 3) Semi-annually 3) Summer and Winter ments 14 65 - 5.8 miles Inlet to City 1) City of 1) Monthly Water System Russellville from Illinois Water Supply Bayou 15 150 - 5.0 miles Discharge of 1) Lake Water 1) Monthly 1) Record status of plant Dardanelle Dam 2) Bottom Sedi- 2) Semi-annually discharge operations Pool above ments Dardanelle Dam 3) Aquatic Biota 3) Semi annually ~
16 295 - 6.0 miles Pine Creek Area 1) Lake Water 1) Monthly
- 2) Bottom Sedi- 2) Semi-annually ment
- 3) Aquatic Biota 3) Semi-annually 19 99 - 5.0 miles Arkansas Tech. 1) Milk 1) Monthly 2) Spring, Summer and Fall Dairy 2) Pasturage 2) 3 times / year 20 290 - 8. 0 r.a les Odom-Meyers 1) Milk 1) Monthly 2) Spring, Summer and Fall Dairy 2) Pasturage 2) 3 times / year 23 73 - 12 miles R. A. Young 1) Milk 1) Honthly 2) Spring, Summer and Fall Dairy 2) Pasturage 2) 3 times / year 29 25 - 7.0 miles H. Steuber's 1) Milk 1) Monthly 2) Spring, Summer and Fall Dairy 2) Pasturage 2) 3 times / year n
TABLE 'l-2 (Cont'd)
SAftPLE LOCATION AND SCHEDULE Sample Direction and Sample Station Station # Distar.ce fnom Plant Location Sample Types Sample Fre_qu_ency Remarks 30 160 - 0.8 miles James Taylor 1) Food Crop 1) 3 times / year 1) Collected during Fruit, Flow- harvest season ering and Tubular Vegetables 32 155* - 0.8 miles Clifton 1) Ground Water 1) Quarterly Stewart's residence, front yard Russellville
- 2) Food Crop 2) 3 times / year 2) Alternate for.30 j collected during harvest season.
33 98* - 4.8 miles Quita Lake 1) Ground Water 1) Quarterly
! Recreation Area of Illinois Bayou off Dyke Road Pump near boat ramp i
Alt. 235 - 3.5 miles Delaware 1) Ground Water 1) Quarterly Recreation ,
- area l 34 295 - 6.6 miles Flat Rock 1) Ground Water 1) Quarterly Recreation area 35 35 - 1.2 miles Tom Cook 1) Leafy and 1) Seasonal Residence Tuberous Vegetables I _. . _ _ . .. . _ _ _ _ _ . , , _ _ . , _ _ . . _ , . . . . . , _ _ _ _ . , , , _ , . . . . . _ .- , ,
TABLE l-2 (Cont'd) sat 1PLE LOCATION AND _ SCHEDULE Sample Direction and Sample Station Station # Distarice f rom Plant Location Sample Types Sample Frequency Remarks 36 140* - 0.05 miles Chemical Pond 1) Pond Water 1) Quarterly on Afl0 Site east of dis-
- 2) Pond Sediment 2) Quarterly fl0TE: These sample stations will 'be determined as per Specification 4.2.10 and will be reported in the Operating Report as per Specification 5.6.1 CAlternate Daries may be substituted when those listed are not available.
TABLE 1-3 TLD LOCATIONS Location Relative AP&L-TLD-No. to ANO 1
0.5 miles 92*
2 0.5 miles 235 3 0.4 miles 4*
4 0.4 miles 171*
5 8.5 miles 298 6 6.8 miles 109 7 19.3 miles 209 8 1.8 miles 313 9 1.2 miles 308 10 0.8 miles 136 11 2.3 miles 108 12 3.3 miles 60 13 1.4 miles 48 14 '1.4 miles 24 15 1.5 miles 343 16 1.9 miles 315 17 17.2 miles 305 18 5.8 miles 291 19 4.8 miles 313
~
20 4.2 miles 338 21 5.5 miles 338*
22 3.5 miles 12 23 3.5 miles 48
u.
TABLE 1-3 (Cont'd)
TLD LOCATIONS Location Relative AP&L TLD No. to ANO 24 3.3 miles 62 25 9.2 miles 47 26 5.6 miles 78*
27 5.7 miles 103 28 8.5 miles 115 29 7.5 miles 118 30 4.6 miles 245 31 2.7 miles 253 32 4.8 miles 274 33 3.8 miles 231 34 2.8 miles 207 35 3.1 miles 186 36 4.3 miles 166 37 8.5 miles 152 38 5.8 miles 195 39 19.2 miles 178 40 21.8 miles 151 41 3.3 miles 134 42 5.2 miles 127 43 17.5 miles 106 44 13.0 miles 314
TABLE 2.1.1 DIRECT RADIATION MEASURED BY QUARTERLY LITHIUM FLUORIDE DOSIMETERS INDICATOR LOCATIONS 1981 1982 1983 (mrem / year) (mrem / year) (mrem / year) 64 63 70 CONTRCL OR BACKGROUND LOCATI0ft 1981 1982 1983 (mrem / year) (mrem / year) (mrem / year) 60 59 56 e
a
TABLE 2.2.1 CALCULATI0ft 0F MAXIMUM ANilUAL. DOSE TO IMit FROM BOTTOM SEDIf1EliT SAflPLE 021983BS08 Afi0 Discharge Canal Dose to Skin Dose to Whole Body Isotooe Activity (pCi/Kg)
(mrem /yr) (mrem /yr)
Mn-54 72 0.001 0.001 Co-58 278 0.006 0.005
.C0160 1380 0.074 0 .0 63 Cs-134- 815 0 .0 31 0.026 Cs-137 4283 0.056 0.046 TOTAL 0.168 0.143 NOTE: Dose. calculations made according to the guidance of fluclear Regulatory Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/kg)(40 Kg/m2) U(hr/yr) D(mrem /hr per pCi/m2)
Where: R is the annual dose to an organ or whole body C is concentration of a particular nuclide, U is the maximum e,xposure time. (67 hrs, for teen),
D is the dose factor.
C o
i
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- i
5 e
TABLE 2.2.2 CALCULATION OF MAXIMUM flNUAL DOSE TO MAN FROM BOTTOM SEDIt1ENT St#.PLE 082083B508 ANO Discharge Canal Dose to Skin Dose to Whole Body Isotope Activity.(pci/Kg) _ (mrem /yr) (mrem /yr)
Mn-54 69 / 0.001 0.001 Co-58 263 0.006 0.005 Co-60 1185 0.063 0.054 Cs-134 815 '
O.031 0.026 Cs-137 _4102. _0.054 0.046 m TOTAL 0.155 0.132 i;0TE: Qose calculations made according to the guidance of fluclear Regulatory Cconission Regulatory Guide 1.109, using the equation:
?
R(mrem /yr) = C(pCi/Kg)(40' Kg/m 2 ) . U(hr/yr)
D(mrem /hr per pCi/m2)
Where: R is the annual dose to an organ or whole body
' C is concentration of a particular nuclide, U is the maximum exposure time (67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> for teen),
D is the dose factor.
o L d l .
- i. :
TABLE 2.2.3 CALCULATION OF MAXIMUM ANNUAL DOSE TO MAN FROM EDIBLE FISH SAMPLE SPLIT W/ADH 042183FC08-S ANO Discharge Canal Activity Annual Organ Dose to Adult Isotope (pCi/Kg) (nrem/vr)
Cs-134 41 0.09 (Liver)
Cs-137 127 0.29 (Liver)
Total *
(LIV 8#)
NOTE: Dose calculations made according to the guidance of Nuclear Regulatory Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg)
- U(Kg/yr)
- D(mrem /pCi)
Where: R is the annual dose to an organ or whole body C is concentration of a particular nuclide, U is the maximum intake of fish for adult (21 Kg/yr)
D is the dose factor.
c i
e
~
A TABLE 2.2.4
, . CALC'ULATI0tl 0F MAXIMUM ANNUAL DOSE
.T0 MAN RbM ANO EDIBLEFISH SAMPLE SPLIT W/ADH
'T 110883FC08-S
' ANO Discharge Canal Activity Annual Organ Dose to Adult
-Isotope- (pCi/Kg) '(mrem /yr)
Cs-134 47 ,, 0.15 (Liver) ,
Cs-137 143' . 0.33 (Liver)
Xe-133' 171
- Total '
O.48 (Liver)
NOTE: ' Dose calculations made'according to the guidance of tJuclear Regulatory Commission. Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg) *. U(Kg/yr) D(mrem /pCi)
Where: R is the annual dose to an organ _' or _whole body C is' concentration of a particular nuclide, U is the maximum intake of fish for adult 1(21 Kg/yr)
D is the dose factor.
- No dose factor for this isotope giien ~in Regulatory Guide 1.109'.
g ..
m 3
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k a
c r
.--# --rvy -
vm
TABLE 2.2.5 CALCULATION OF MAXIMUM ANNUAL DOSE TO MAN FROM CARNIV0ROUS FISH SAMPLE 051783FC08 ANO Discharge Canal Activity Annual Organ Dose to Adult
. Isotope (pCi/Kg) (mrem /yr)
Cs-58 19 0.01 (GI-LLI) *
(Liver)
Cs-60 33 0.03 (GI-LLI) *
(Liver)
, LCs-134 42 *
(GI-LLI) 0.13 (Liver)
Cs-137 124 0.01 (GI-LLI) 0.28 (Liver)
Nb-95 32 0.01(GI-LLI) *
(Liver)
Total 0.06 (GI-LLI) 0.41 (Liver)
NOTE: Dose calculations made according to the guidance of Nuclear Regulatory. Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg)
- U(Kg/yr) ~ 0(mrem /pCi)
Where: R is.the annual dose to an organ or whole body C is concentration of a particular nuclide, U is the maximum intake of fish for adult (21 Kg/yr)
D is the dose factor.
- Calculated dose for this isotope is less than 0.01 mrem /yr.
c k
L .
TABLE 2.2.6 CALCULATION OF MAXIMUM ANNUAL DOSE TO MAN FROM CARNIV0ROUS FISH SAMPLE 100983FC08 ANO Discharge Canal Activity Annual Organ Dose to Adult Isotope (pCi/Kg) (mren/yr)
Co-58 25 0.01 *
(GI-LLI) (Liver)
- - Co-60 20 0.02 (GI-LLI) *
(Liver)
- Cs-134 54 *
(GI-LL1) 0.17 (Liver)
Cs-137 150 0.01 (GI-LLI) 0.34 (Liver Total 0.04 0.51(Liver)
NOTE: Dose calculations made according to the guidance of Nuclear Regulatory Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg)
- U(Kg/yr) ' D(mrem /pCi)
Where: _ R is the annual dose to an organ or whole body C is concentration of a particular nuclide.
U is the maximum intake of fish for adult (21 Kg/yr)
D is -the dose factor.
- Calculated dose for this isotope is less than 0.01 mrem /yr.
c c
e
?
I
TABLE 2.2.7 CALCULATION OF MAXIMUM ANNUAL 00SE TO MAN FROM BOTTOM FEEDER FISH SAMPLE 051783F808 ANO Discharge Canal Activity Annual Organ Dose to Adult Isotope (pCi/Kg) (mrem /yr)
Cs-134 25 0. 08 (Liver)
Cs-137 69 0.16__ (Liver)
Total 0.24 (Liver)
NOTE: Dose calculations made according to the guidance of Nur. lear Regulatory Commission Regulatory Guide 1.100, using the equation:
R(mrem /yr) = C(pCi/Kg)
- U(Kg/yr)
- D(mrem /pCi)
Where: R is the annual dose to an organ or whole body C is concentration of a particular nuclide, U is the maximum intake of fish for adult (21 Kg/yr)
D is the dose factor.
l I-1 t
t I
TABLE 2.2.8 CALCULATION OF MAXIMUM ANNUAL DOSE TO MAN FROM BOTTOM FEEDER FISH SAMPLE 090983FB08 ANO Discharge Canal Isotope Activity Annual Organ Dose to Adult (pCi/Kg) (mrem /vr)
- Cs-134 51 0 . 16 ' liver)
Cs-137 136 0.31 (Liver)
Total 0.47 (Liver)
NOTE: . Dose calculations made according to the guidance of Nuclear Regulatory Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg)
- U(Kg/yr)
- D(mrem /pCi)
Where: R is the annual dose to an organ or whole. body C is concentration of a particular nuclide, U is the maximum intake of fish for adult (21 Kg/yr)
D is the dose factor.
O 6
9
)
TABLE 2.2.9 CALCULATION OF MAXIMUM ANNUAL DOSE TO MAN FROM PLANKTON FEEDER FISH SAMPLE.
090983FP08 ANO Discharge Canal 4
Activity Annual Crgan Dose to Adult Isotope (pCi/Kg) (mrem /yr)
Co-58 47 0.01 (GI-LLI) *
(l.iver
.Co-60 71 0.06 (GI-LLI) *
(Liver)
Cs-134 103 0.01 (GI-LLI) 0.32 (Liver)
Cs-137 259 0.01 (GI-LLI) 0.59 (Liver)
Total 0.09 0.91 (Liver)
. NOTE: Dose calculations made according to the guidance of Nuclear Regulatory Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg)
- U(Kg/yr)
- 0(mrem /pCi)
Where: R is the annual dose to an organ or whole body C is concentration of a particular nuclide, U is the maximum intake of fish for adult (21 Kg/yr)
D is the dose factor.
- Calculated dose for this isotope is less than 0.01 mrem /yr.
C s'
8
n, TABLE 2.2.10 CALCULATION OF MAXIMUM ANNUAL DOSE TO MAN FROM PLANKTON FEEDER FISH SAMPLE 051783FP08 ANO Discharge Canal Activity Annual Organ Dose to Adult Isotope (pCi/Kg) (mren/yr)
Co-60 29 0.02 (GI-LLI) *
(Liver Cs-134 32 *
(GI-LLI) 0.10 (Liver)
Cs-137. 97 *
(GI-LLI) 0.22 (Liver)
Total 0.02 (GI-LLI) 0.32 (Liver)
NOTE: Dose calculations made according to the guidance of Nuclear Regulatory Commission Regulatory Guide 1.109, using the equation:
R(mrem /yr) = C(pCi/Kg) U(Kg/yr) ' 0(mrem /pCi)
Where: R is the annual dose to an organ or whole body C is concentration of a particular nuclide, U is the maximum intake of fish for adult (21 Kg/yr)
D is the dose factor.
- Calculated dose for this isotope is less than 0.01 mrem /yr.
. c Ph 0
7-TABLE 2.2.11 COMPARISON OF GAf1MA-EMITTING P.ADI0tluCLIDES Ill SPORT FISH FROM THE ANO DISCHARGE CAtlAL
.Radionuclide Date and Activity (pCi/Kg) r.
May 78 Oct 78 June 79 Oct 79 May 80 Dec 81 July 82 .Dec 82 Apr 83 flov 83 Co-58 13 46 Cs-134- 40 29- 19 58 24 41 47 Cs-137 65 95 86 41 12 18 141 75 127 143
- .Xe-133 - 171 i
1 I
I 4
9 -
l C
= e 4
f.
f l_
.. . . - ._. -. . . - . .- . . . . .. ~ -. .
- i. .
TABLE 2.5.2 STANDARD DEVIATI0riS FR0tl Kil0WN VALUES OF EPA CROSS-CilECK sat 1PLES i
l Total No. Analyses ilumber of Standard j Sample Type Analyses Performed. Performed Deviations from Known Value t
- 1. Gross Alpha- flov. 82 Mar. 83 Jul. 83 Nov. 83 Gross Beta in Water. -Gross Alpha 12 -0.6 -0.2 2.0 1.3 -
Gross Beta 12 -3.3 -0.3 -0.3 .1.5 l 2. Gamma in Water Feb. 83 June 83 Oct. 83 l
Chromiun-51 9 1.5 -0.8 -1.5 Zinc-65 9 0 0 0.1 Cobalt-60 9 0 -1.0 -0.3
- Ruthenium-106 9 0.9 -1.0 -2.3
- Cesium-134 9 0 -1.7 -0.3 l Cesium-137 9 0.2 0 0
- 3. Tritium in Water Ayr. 83 Aug. 83 Dec. 83 '
11 - 3 9 0.6_ -0.4 0.5
- 4. Iodine-131 in Water Jan. 83 hay 83 Sept. 83 Iodine-131 9 T0. 8 -0.1 -0.5 i
! 5. Strontium in Water Jan. 83 flay 83 Sept. 83 Strontium-89 9 -2.6 2.5 0.5 j Strontium-90 9 -0.8 -5.5 -1.9 I 6. EPA 31ind'in Water itay 83 Nov. 83 I Gross Alpha 6 1.7 -0.8 Gross Beta 6 -0.8 -0.8 Strontium-89 6 -1.4 -0.8 Strontium-90 6 -1.5 -1.9 l Cobal t-60 -6 -0.8 -0.3 i Cesium-134 6 -1.5 -0.5 ;
j . Cesium-137 6 0.3 0.2 1
_. _ . . _ . _ _ _u_._-_ _ = _ . - .
TABLE.2.5.2 . STANDARD DEVIATIONS FROM KNOWN VALUES.0F EPA CROSS-CHECK SAMPLES (Cont'd)
Total No.L Analyses ' Number of Standard Sample Type Analyses Performed Performed Deviations from Known Value
- 7. Milk Feb. 83 June 83 Oct. 83 Strontium-89 6 See 1 -0.1 -0.1 Strontium-90 6 See 1 -3.5 -2.7
.' Potassium 9 -1.4 1.3 0.5 Iodine-131 9 -0.9 -0.7 -1.4 Cesium-137 9 -0.2 -0.6 0.1 Barium-140 9 NA NA NA
- 8. Air Filter Nov. 82 Mar. 83 Aug. 83 Gross Alpha 9 0 0.5 0.3 Gross Beta 9 -1.0 -1.8 -0.6 Cesium-137 9 0 0.1 -0.3 Strontium-90 9 0.8 0 0.8
- 9. Low-Level Water Jan. 82 June 82 lodine-131 6 -0.1 -0.2
- 10. Low-Level Milk July 82 Iodine-131 3 0.1 I Strontium analysis not performed because sample clabbered.
s O' -,y #-.v-r,,- -,, --y 4 7 i-<.,,,,, -
,,7--e---- -.sv..-e--- ,-ey- __y,.. . - - , _ . - 3
Fig. 2. 2.1 Cs -134 In Edible Fish Samples 100-80-60-ci M
h -
O c.
40-20-
_ ____ __-__-__--___-_ . _ - - - - - - - - - - - D e t ec t ion
. Limit i i I : g l 1 l l
> 8 l C 8 > l 0l -
3 0l L >
5 0 0 m c c a o E o ,3 a 2 a a < z 1978 1979 1980 1981 1982 1983 a . _ _ . _ _ __ _
Fig. 2.2.2 Cs-137 In Edible Fish Samples 150-120-90-01 x
1 o /
a
- 60-30-7 i
4 AI 0
eaI 0 L I JI 2 3 al l s 3 Q c e E O O 7 0 '
E 2 0 O 4 2 j 1978 1979 1980 1981 1982 1983
DETECTION LIMITS ~
Air Aquatic- Veg. Soil
. Particulate Fish- ' Organisms Terrest- ' Bot. Sed. Water Milk pCi/m3 pCi/kg pCi/kg pCi/kg pCi/kg- pCi/1 pCi/1 H3 --- --- --- --- ---
280 ---
.Be7 7 x 10 2 200 200 -200 400 80 150 K40 10 1 300 300 300 500 100 200 Hn54 10 2 50 50 50 70 10 20 i CoS8 10 2 50 50 50 70 10 20 Fe50 2 x 10 2 100- 100 100 130 20 40 CoGo 10 2 50 50 50 70 10 20 Zn" 2.x 10 2 100 100 100 130 20 40 S r* 25 25 25 25 5 5 Srt
- 5 5 5 5 1 1 Zr05-Nb05 5 x 10 3 30. 30 30 50 5 10 Rul06 2 x 10 2 70 70 70 100 15 30 1131(a) 10 2 50 50 50 70 10 20 1131(b) 0.5 0.5 Cstaa 10-2 50 50 50 70 10 20 n
DETECTION LIMITS (Cent'd)
Air Aquatic Veg. Soil Particulate , Fish Organisms- Terrest' Bot. Sed. Water ' Milk pCi/m3 pCi/kg pCi/kg pCi/kg pCi/kg pCi/1 pCi/1 Cst 37 10-2 50 -50 50 70 10 20 Ba 40 talio 3
10-2 50 50 50 70 10 20 CeI44 5 x 10-2 200 200 200 300 40 80 (a) Gamma Isotopic Analysis (b) Radiochemical _ Separation 9
SURVEY OF 111LK-PRODUCIrlG Atili1ALS WITHIrl AN AREA 0F TEfl (10) MILES OF ARKANSAS ?!UCLEAR ONE August 10-11, 1983 In accordance with Environmental Technical Specification 4.2.10, a survey was conducted August 10-11, 1983 to detennine the location of animals which produce milk for human consumption. !! ilk-producing animals (milk cows) are divided into two categories defined as:
- 1. Class A Dairies - Dairies in which milk is intended primarily for human consumption as Grade A milk.
- 2. Individual Milk Cows - Family cows in which the milk is intended primarily for home use.
CLASS A DAIRES WITHIrl A 10-MILE RADIUS OF Aft 0 Dairy No. of Cows Azimuth-Distance
- 1. Ark Tech Univ. Dairy 48 99 - 5. 0
- 2. Bill Harms Dairy 60 21 - 7.75
- 3. R. Meyer Dairy 50 290 - 8. 0
- 4. R. A. Young Dairy (C0flTROL) 50 73 * . 12.0
- 5. Harold Steuber 80 25 - 7.0
- 6. Lawrence Steuber 60 358 - 7.5
- 7. Buddy Boxnick 60 23* - 7.0
- 8. Robberson Dairy 70 183 - 10.5
- 9. Cloyce'Ragsdale 40 45* - 10.2 C
- 10. Wayne Pritchard 30 43" - 10.5 IllDIVIDUAL MILK COWS Name flo. of Cows Azimuth-Distance
- 1. Bobby Steuber 1 346* - 8.3
INDIVIOUAL MILK COWS r
Name No. of Cows Azimuth-Distance i
- 1. Bobby Steuber 1 346 -
8.3 Also, garden vegetation from the James Taylor garden and near Tom Cook's residence was collected June 7, 1983 P
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t R
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l
__ ,er.,--.v--~me*- ~ " ' - " " ^ - " ' " " ^ * " -
SURVEY OF MILK-PRODUCING ANIMALS WITHIN AN AREA 0F TEN (10) MILES OF ARKANSAS NUCLEAR ONE June 7-8, 1983
~
-In accordance with Environmental Technical Specification 4.2.10, a survey was conducted June 7-8, 1983 to determine the location of animals which produce milk for human consumption. Milk-producing animals (milk cows) are divided into two categories defined as:
1.
Class A. Dalries - Dairles in which milk is intended primarily for human consumption as Grade A milk.
- 2. Individual Milk Cows - Family cows in which the milk is intended primarily for home use.
CLASS A DAIRIES WITHIN A 10-MILE RADIUS OF ANO Dairy No. of Cows Azimuth-Distance
- 1. Ark Tech Univ. Dairy 50 99" - 5 0
- 2. Bill Harms Dairy 60 21 - 7.75 3 R. Heyer Dairy 49 2900 - 8.0 4 R. A. Young Dairy (CONTROL) 48 73 - 12.0
- 5. Harold Steuber 80 22 - 7.0
- 6. Lawrence Steuber 60 358 - 7.5
- 7. Buddy Boxnick 60 23 - 7.0
- 8. -Robberson Dairy 80 183 - 10.5
- 9. Cloyce Ragsdale 30 45 - 10.2 c
- 10. Wayne Pritchard 30 43 - 10.5
- 11. Hudson Dairy 40 80 - 14.0
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NAME Of F ACIL II Y ANO-1 AND ANU-2 1OChkT NO. bo-J13 AND LO-160 LOCATIUN OF FACILITY 70 pee AkhANSAS ktPURIING tFAIOD . AA N . - DkC. 1983 (CDUNTY. S T A T t. ) i 1
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' CHEM-042-00 (2/22/84) ,
idP84161 1983 ANO CllEMICAL USAGE t
(Qty. Used Ibs.)
Chemical (Ibs) l Jan. l Feb. l March l April l May l June l July l Aug. l Sept. l Oct. l Nov. l Dec. l Total Un' #1 l Sulf. Acid 66 Baume l 0 0 73.354 6,418 126.457 99,040 36,044 48,278 73.232 21,105 33,293 230.093 747,314-Sodium Hydroxide 50% l 0 0 51,439 46,299 47,514 Ammonium Hyiroxide 0
_3L320 55,858 107,830 83,525 138,364 131,932 210,025 905.106 l 0 2.992 2,618 1.122 17,578 2,012 14,960 20,196 10.225 14.212 Hydrazine 35% 0 0 5.236 91,151 l 6.750 5,063 2,457 9.788 1,575 3,600 900 0 900 2,700 33,751 Sodium Nitrite l 450 200 325 475 200 450 425 550 250 Borax 200 75 250 3,850
] 0 50 50 100 50 50 50 100 Boron 500 50 50 50 1.100 l 0 801 1.316 915 2,574 1,373 1,029 858 Lithium Hydroxide 1,258 0 57 114 10,295 l 0 0 0 2.2 0 6.6 4.4 4.4 0 0 0 0 173 I
Unit #2 l Sulf. Acid 66 Baume l 5,389 35,318 70,542 17,035 123,310 5,717 21,060 11,456 5,785 Cooling Tower Acid 0 0 0 295,612 l
Sulf. Acid 66 Baume l j l,273 90,039 161.457 97,645 715.546 254,057 297,677 412,929 297,037 0 0 0 2.337,660 Sodium Hydroxide 50% l 22,083 23,798 16,961 54.434 25,444 16,733 22.678 32,054 19,259 Ammonium Hydroxide 4,813 0 0 0 23,444 l 1,178 3,635 5,071 3,949 7,989 5,520 6,923 2,805 0 0 Hydrazine 35% 1,350 0 41,883 l 1.350 2,250 1,688 2,475 3,263 1,575 1,600 900 0 Sodium Nitrite 450 0 0 18,451 l 200 325 475 200 450 425 550 250 200 Borax 100 450 2,700 6,675 l Su 50 100 50 50 50 100 500 50 Boron 0 50 1,150 Lithium Hydroxide l 858 972 229 114 3 229 114 572 858 172 1,834 686 6.752 l 0 2.2 0 4.4 0 0 2.2 4.4 0 0 l
2.2 2.2 17.6
_.. Cooling. Tower l Calgon (CL-2490) l 11,543 11,880 33,165 13,306 20,790 36,838 26,512 16,731 ' 37,620 Calgon (CL-5) 0 0 0 208,385 l 520 650 2,340 1.300 1,560 3,380 520 1,820 0 0 0 260 14.430 l
Unit #1 & #2 l Chlorsoe l 0 0 2,000 2,000 1,000 120 4,000 4,000 4,000 8,000 10,000 4,000 3),120 Determents l 16 17 17 17 17 17 17 18
. 17 34 32 17 238
\
s **
Dfh6 ARKANSAS POWER & LIGHT COMPANY POST OFFICE BOX 551 UTTLE ROCK, ARKANSAS 72203 (501) 371-4000 May 1, 1984 Mr. John T. Collins :
RM DMS p' l
Regional Administrator I '*q U. S. Nuclear Regulatory Commission
~
N Region IV ~ y 611 Ryan Plaza Drive, Suite 1000 Arlington, TX 76011
SUBJECT:
Arkansas Nuclear One - Units 1 & 2 Docket Nos. 50-313 and 50-368 License Nos. DPR-51 and NPF-6 Annual Environmental Monitoring Report Gentlemen:
Enclosed is the Arkansas Nuclear One Annual Environmental Monitoring Report for Arkansas Nuclear One - Units 1 and '?. This report is submitted for the calendar year 1983 in accordance with Environmental Technical Specification 5.6.1.
The Annual Chemical Usage Report is submitted for the portion of the year prior to March 11, 1983. The Technical Specification requiring this report was deleted by Amendment #72 dated March 11, 1983.
Very uly yours, John R. M'arshall Manager, Licensing JRM: RJS:ac Attachment cc: Mr. Richard C. DeYoung Office of Inspection and Enforcement U. S. Nuclear Regulatory Commission Washington, DC 20555 Mr. Norman M. Haller, Director Office of Management & Program Analysis U. S. Nuclear Regulatory Commission Washington, DC 20555 1
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