ML19270F813

Annual Environ Operating Rept,Part B:Radiological, for 1978

ML19270F813
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Site:	Farley
Issue date:	03/22/1979
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ALABAMA POWER COMPANY ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOLOGICAL JOSEPH M. FARLEY NUCLEAR PL\NT UNIT NO. 1 PERIOD ENDING DECEMBER 31, 1978 7 9 0 3 2 7 0 5M

This annual report is submitted pursuant to paragraph 5.6.1 of the Environmental Technical Specifications, Appendix B, to Operating License No. NPF-2. This report summarizes the off-site radiological Environmental Monitoring program for the Joseph M. Farley Nuclear Plant, Unit 1, from January 1, 1978 through December 31, 1978.

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS Section Title Page I Introduction 1 II Radiological Sampling and Analysis 1 III Results and Discussion 24 IV Conclusions 27 i

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF FIGURES Figure Title Page 1 Farley Nuclear Plant Indicator En- 17 vironmental Radiological Sampling Stations.

2 Farley Nuclear Plant Community and 18 Background Environmental Radiological Sampling Stations.

3 Farley Nuclear Plant Waterborne (River) 22 Radiological Sampling Stations, 11

RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES Table Title Page i Scope of Operational Radiological Environ- 2 mental Monitoring Program.

2 Outline of Operational Radiological Environ- 3 mental Monitoring Program.

3 Detection Capabilities for Environmental 12 Sample Analysis.

4 Sampling Deviations During 1978 14 5 Analytical Data Not Reported During 1978 16 F02-1 Airborne: Particulates and Iodiae - Opera- 28 tional Radioactivity Summary.

F02-2 External Raii3 tion - Operational Summary 31 F02-3 Milk - Operational Radioactivit" Summary 32 F02-4 Vegetatiin:

f Forage, Vegetablee and Fruits - 34 Operational Radioactivity Summary.

F02-5 Soil - Operational Radioactivit y Summary. 44 F02-6 Waterbo rne: Surface and Grounr4 Water - 46 Operational Radioactivity Summ ary.

F02-7 Vegetation: Aquatic - Operatianal Radio- 48 activity Summary.

F02-8 Benthos: Clams - Operational Radioactivity 49 Summary.

F02-9 Fish: River - Operational Radioactivity 50 Summary.

F02-10 Sediment: River - Operational Radioactivity 52 Summary.

iii

OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM I. Introduction The Joseph M. Farley Nuclear Plant, owned and operated by Alabama Power Company (APCo), located in Houston County, Alabama is approximately fifteen miles east of Dothan, Alabama on the west bank of the Chattahoochee River. Unit 1, a Westinghouse Electric Corporation Pressurized Water Reactor (PWR) with a rated power output of 760 megawatts electrical (MWe) achieved initial criticality at 12:35 p.m. on August 9, 1977. The unit was declared " commercial" on December 1,1977 and with exception of short outages uas operated continuously during 1978 at or close to full rated power.

The off-site operational radiological environmental monitoring program has the objective of assessing the radiological impact of the operation of the Farley Nuclear Plant (FNP) upon the surrounging region. It is conducted to verify projected or anticipated radioactivity concentrations and related public exposures from plant operations.

The sample collection and analysis schedule for the operational off-site radiological environmental monitoring program was implemented during May, 1977 and was continued during 1978. This program was designed to monitor any radioactivity contribution to the environs from the plant through either the airborne or waterborne pathways. The type of mamples monitored, and number and type of sampling stations are shown in Table 1. Indicator sampling stations were located, where practical, at locations where detection of the radiological effects of the plant's operation was thought to be most likely, where the samples collected should provide a significant indication of potential dose to man, and where an adequate comparison of predicted radiological levels might be made with measured levels. The control stations were placed at lo..ations where radiological levels were not expected to be significantly influenced by plant operation, i.e. , at background locations.

for some airborne radioactivity samples, community stations were located at the principal population centers between the indicator and the control stations (3-8 miles). These in normal operation could be used, if desired, as additional control stations, and alternatively, as indicator stations in the nearest population centers in the event of a major airborne release of radioactivity from the plant.

II. Radiological Sampling and Analysis A detailed outline of the operational radiological sampling and analysis activities for the off-site environmental program is given in Table 2. The smaples were collected by APCo's technical staff except for the in situ Ge(Li) gamma-ray spectroscopy measurements of soil. The latter were made by staff members of the University of Georgia, Center for Applied Isotope Studies.

All sample analyses were contracted to either the University of Georgia (U.Ga.) or the Eberline Instrume.it Corporation (EIC). Southeastern Facility.

NOTE: EIC's Southeastern Facility was closed on March 31, 1978. After April 1, 1978 samples were sent to EIC's Sudwestern Facility). The minimum detectable concentration (MDC), specified to the contractor laboratories

(2)

Table 1 SCOPE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Principal Type of Minimum Number of Sampling Stations a Pathway Samples Indicator Community Control Airborne Particulates 4 3 3 Airborne Iodine 3 1 1 External Radiation 16 3 5 Airborne Milk lb _ y Forage c 2 -

1 Vegetables and Fruits 1 -

1 d

Soil 9 3 3 River Water 1 -

1 River Vegetation 1 -

1 River Benthos 1 -

1 Waterborne River Fish 1 -

1 River Sediment 1 -

1 Groundwater 1 -

1 aAdditional stations may be added at discretion of licensee above the minimum commitment shown.

bIf available cForage sampling in lieu of meat and poultry sampling.

dSemi Annual In nSitu Gamma Measurements.

(3) -

Table 2 OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Types of Samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles) Collection Frequency Analysis AIRBORNE Continuous sampler operation Cross Beta - Weekly or af ter with sample collection weekly filter change.

Pa rt icula tes or as required by dust loading of filters, whichever is more Camma Isotopic - Quarterly Indicator Stations; frequent, site (by location) and for any single filter having North Perimeter (N-0.8) gross beta activity that is greater than 10 times River Intake Structure the mean of the control (ESE-0.8) samples.

South Perimeter (SSE-1.0) Strontium-89,90 Analyses -

Quarterly composite (by Plant Entrance - Nearest location).

Residence (WSW-0.9)

Community Stations:

Columbia, Ala. (N-5)

Great Southern Paper Co. ,

Ga. (SSE-3)

Ashford, Ala. (WSW-8)

Control Stations:

Blakely, Ca. (NE-15)

Neals Landing, Fla.

(SSE-18)

Dothan, Ala. (W-18) l

(4)

Table 2 (Con't)

Type of Samples Sampling Type and Frequency and and of Sampling Locations Collection Frequency Analysis Iodine Indicator Stations: Continuous Sampler operation Iodine-131 - Weekly with charcoal canister col-North Perimeter (N-0.8) lection weekly.

South Perimeter (SSE-1.0)

Plant Entrance - Nearest Residence (WSW)-0.9 Community Stations:

Great Southern Paper Co.,

Ca. (SSE-3)

Background Stations:

Dothan, Ala. (W-18)

External Radiation Indicator Stations: Each measurement location has two Read Gamma doses quarterly dosimeters (TLD's) side-by-side, and annually.

Sixteen stations, one in each one collected quarterly and one meteorological sector, along the collected annually. Each dosimeter plant perimeter. (N-0.8, NNE-0.9, contains five individual TLD chips.

NE-1.0, ENE-0.9, E-0.8, ESE-0.8, SE-0.9, SSE-1.0, S-1.0, SSW-1.0, SW-0. 9, WSW-0. 9, W-0. 8, WNW-0. 8, NW-0.9, and NNW-0.9)

(5)

Table 2 (Con' t) .

Types of Samples Sampling Type and Frequency and and of Sampling Loca t ions Collection Frequency Analysis Community Stations :

Columbia, Ala. (N-5)

Great Southern Paper Co.,

Ga. (S SE-3)

Ashford, Ala. (WSW-8)

Control Stations:

Blakely, Ca. (NE-15)

Georgia Rt. 39 (ENE-15)

Neals Landing, Fla. (SSE-18)

Ala. Rt. 52 (WSW-26)

Dothan Ala. (W-18)

Soll Indicator Stations: Semi-annual fjt situ Ce(Li) gamma- Camma Isotopic -

ray spectroscopy measurements. Semi-annually.

Nine stations along the plant perimeter. (N-0.8, NE-1.0, E-

0. 8, ES E-0. 8, SSE-1. 0, S-1. 0, SW-0.9, WSW-0.9, and NNW-0.8

(6)

Table 2 (Con't) -

Type of Samples Sampling Type and Frequency and and of Sampling Locations Collection Frequency Analysis Community Stations:

Columbia, Ala. (N-5)

Great Southern Paper Co.,

Ga. (SSE-3)

Ashford, Ala. (WSW-8)

Control Stations:

Blakely, Ga. (NE-15)

Neals Landing, Fla. (SSE-18)

Dothan, Ala. (W-18)

Milk Indicator Stations: Semi-Monthly Gamma Isotopic-Monthly Early Co . , Ga. (E-5)a Strontium 89,90 Analyses-Monthly Control Station:

Radioiodine analysis - Semi-Brooks-Silcox Dairy, Ashford, Monthly, when animals are on Ala. (WSW-10) pasture (a) Milk was not available at this location after !!ay, 1978.

(7) .

Table 2 (Con't)

Type of Samples Sampling Type and Frequency and and of Sampling Locations Collection Frequency Analysis Fo ra ge Indicator Stations: Grab Sample Monthly (when Gamma 1sotopic-Monthly available)

North Perimeter (N-0.8 or NE-1.0)

South Perimeter (SSE-1.0 or S-1.0)

Control Station:

Dothan Area (W-10 to 20)

Vegetables and Fruits Grab sample at harvest, except Gamma Isotopic-Edible portion monthly for green leafy vege-Indicator Station: tables during growing season. Radioiodine-Monthly on green (Principal food crops grown in leafy vegetables during growing Plant Vicinity (SW-1, W-1, plant vicinity). season.

NNE-2, or NNE-3)

Control Station:

Dothan Area (W-10+ , WSW-10 +,

WNW-10&)

(8)

Table 2 (Con't) .

Type of Samples Sampling Type and Frequency and and of Sampling Locations Collection Frequency Analysis WATERBORNE River Water Composite taken with propor- Gamma Isotopic - Monthly tional semi-coninuous sampler, Indicator Station: having a minimum sampling fre- Tritium - Quarterly Composite quency of once each hour.

Downstream of Plant dis- Strontium-89,90 - Quarterly charge 62 miles) Composite.

Control Statior:

Upstream of Andrews Lock and Dam

(~3 miles above plant intake).

Ground Water Grab sample taken quarterly. Gamma Isotopic - Quarterly Indicator Station: Tritium - Quarterly Great Southern Paper Company Well (SSE-4)

Cor. trol Station:

King's Court Trailer Park Well (WSW-0.9)

(9)

Table 2 (Con' t) -

Type of Samples Sampling Type and Frequency and and of Sampling Locations Collection Frequency Analysis Indicator Station: Grab sample taken semi-annually. Gamma Isotopic -

Semi-annually Strontium-89,90 -

Semi-annually.

Downstream of plant discharge at first available location.

Control Station:

Upstream of Andrews Inck and Dam.

River Fish Grab sample taken semi-annually. Camma Isotopic - Edible Portion semi-annually Indicator Station:

Downstream of Plant discharge in vicinity of Smith's Bend

(-2 miles)

Control Station:

Upstream of Andrews lock and Dam.

River Benthos Grab sample taken semi-annually Gamma Isotopic - Semi-(Clams) annually (Tissue)

(10) .

Tabl e 2 (Con ' t)

Type of Samples Sampling Type and Frequency and and of Sampling Locations Collection Frequency Analysis Indicator Station:

Downstream of Plant discharge Strontium-89,90 -

at firs t available location. Semi-annually (Tissue)

Control Station:

Upstream of Andrews Lock and Dam.

River Sediment Grab sample taken semi-annually. Gamma Isotopic - Semi-annually.

Indicator Station:

Strontium Semi-Downstream of Plant dischages annually.

at Smith's Bend (~2 miles)

Control S tation:

Upstream of Andrewa lock and Dam.

(11) for the various samples and their respective analyses are given in Table 3.

A number of sampling problems were encountered during 1973 which are listed in Table 4. In January the Chattahoochee River water level reached flood stage which disrupted collection of water at the Andrews Lock and Dam and collection of air samples at the Plant River Intake Structure due to loss of electrical power. At the North Perimeter Air Sampling Station repeated pump failures resulted in several particulate and iodine samples having reduced volumes and for one week no samples were collected. After May an indicator milk sample was no longer available at Cedar Springs, Georgia resulting in this sampling location being dropped from the schedule.

Other sampling deviations ranged from the technician failing to turn on the power to the air pump after filter change to missing TLD's, as listed in the table.

Probably the one event which influenced the analysis program more than any other was the decision by Eberline Instrument Corp. to close their South-eastern Facility on March 31, 1978 and to transfer the contract for analytical services to their Midwestern Facility. The net result was loss of samples and/or analytical data as listed in Table 5. The major causes appear to have been deficiencies in timely communications and transportation of samples.

Positive steps have been taken to correct these deficiencies during 1979.

A. Airborne Particulates and Iodine All of the airborne particulates and iodine monitoring stations shown in Figures 1 and 2 were equipped with Bell and Gossett vacuum pumps which operate continuously at a flow rate of about 0.04 m3/ min (1.5 ft3/ min). The particulates were collected on Gelman Metricel 50 mm filters. In series with, but downstream of the particulate filters, Gelman 50 mm activated charcoal cartridges (or equivalent) were used for collection of iodine. The latter were mounted horizon-tally to insure uniform airflow through the filter. The accumulative air flows were measured with Rockswell Gas Meters which were calibrated against a certified flow meter. Both the particulate filters and charcoal cartridges were collected weekly and were sent to U. Ga. for radioactivity analysis.

Gross beta radioactivity measurements were made on each air par-ticulate filter using a Beckman Lowbeta II low background proportional counter. The filters from each station were composited and at the end of each quarter were analyzed for gamma emitters using a nine percent relative efficiency low background Ge(Li) detector (18% efficiency detector after May, 1978) and a Canberra 4096 channel computer-based multichannel analyzer (MCA). In addition, strontium-89, 90 were separated from the quarterly composite filters following the gamma-ray spectroscopy analyses and the beta activity measured using a Beckman Lowbeta II low background proportional counter. The single separation, dual count technique was used for the determination of the strontium-89 and strontium-90 present. Stable strontium carrier was added to each sample for determination of the radiochemical yield.

All the air monitoring station locations shown in Figures 1 and 2 have the capability of monitoring airborne iodine. However, weekly routine samples were collected only at the stations listed in Table 2.

These were analyzed for iodine-131 by U. Ga. using a Canberra 1024

(12) .

Table 3 DETECTION CAPABILITIES FOR EINIRONME?TTAL SAMPLE ANALYSIS Nominal MINIMUlf DEIECTABLE CONCEIrrxATICMa UDC)

Sample Gross Radio-Strontium Radio-Iodine Sample Size Beta Camma Isotopic 89 90 131 Tritium AIRBORNE:

Particulates 400 m3 1 10-2 10-2pci/m31 sot. 5 10-3 10-3 ----

per week pCi/m pCi/m3 pCi/m3

-2 Iodine 400 m 3 ---- ----

7*10 per week pC1/m 3 Milk 10 1 ----

25 pCi/1/isot. 10pci/1 2pci/1 0.5pci/1 ----

Forage 1 kgb ----

100 pCi/kg b/isot. 80pC1/kg b Vegetables 1 kgb ----

100pCi/kg/ isot. 80pci/kg b and Fruits (Edible)

Soil In Situ ----

200pci/kg/isot. -

200pC1/kg ----

WATERBORNE:

River Water 41 ----

25pci/1/isot. 10pci/1 2pci/1 200pci/1 Ground Water 41 ----

25pci/1/isot. 100pci/1

(13)

Table 3 (Cont'd)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS Nominal MINIMUM DETECTABLE CONCENTRATION" (MDC)

Sample Gross Radio-Strontium Radio-Iodine Sample Size Beta Gamma Isotopic 89 90 131 Tritium River 1kg b 100pCi/kg b/isot. SpC1/kg b 5pci/kg b Vege ta tion River Fish 1kg b 100pCi/kg b/isot.

(Edible)

River Benthos 0.5kgD ----

100pci/kg b/isot. 10pCi/kg b ____

Tissue River Sediment ikg 200pci/kg /isot. 200pci/kg ----

(a) Nominal Values Achievable in Practice at Normally Expected Environmental Radioactivity Concentrations. (Called Lower Limit of Detection (LLD) in 1977 Operational Report and ETS).

(b) Wet Weight.

(14)

TABLE 4 SAMPLING DEVIATIONS DURING 1978 Week Starting Location and Nature of Deviation 1/9 Cedar Springs, Ga Milk Sampling Station: Milk Not Available Andrews Lock & Dam Water Sampling Station: Out of Ser-vice for One Day, Battery Not Charged Adequately 1/16 Silcox Dairy and Cedar Springs, Ga Milk Sampling Stations:

Milk Samples were collected Andrews Lock & Dam Water Sampling Station: Pump Not Operable - Back-up Pump Also being Repaired 1/23 River Water Intake Structure Air Sampling Station:

Loss of Power - Particulate Sample has Reduced Volume Blakely Air Sampling Station: Air Particulate Filter Damaged - Approximately one-half lost due to high wind.

Andrews Lock & Dam Water Sampling Station: Sample was not collected for week - Due to high water.

1/30 River Water Intake Structure Air Sampling Station:

Particulate Sample Not collected - Due to station loss of power from high water 2/6 River Water Intake Structure Air Sampling Station:

Particulate sample had reduced volume - No power for part of week Ashford Air Sampling Station: No sample collected -

Technician failed to turn pump on after filter change.

Andrews Lock & Dam Water Sampling Station: Pump removed from service for repair.

3/13 North Perimeter Air Sampling Station: Pump failure -

Reduced volume for particulate and iodine sample No green leafy vegetables were available.

4/10 North and South Perimeter Air Sampling Stations: Pump Failures - Reduced volume for particulate and iodine samples.

4/17 North Perimeter Air Sampling Station: Malfunction of pump - Slightly reduced volume for particulate and iodine samples.

4/24 River Intake Structure Air Sampling Station: Particulate Filter Lost during change - Due to high wind.

5/1 River Intake Structure Air Sampling Station: Temporary Loss of power - Slight reduction in particulate air sample volume.

(15)

TABLE 4 (Cont'd)

SAMPLING DEVIATIONS DURING 1978 Week Starting Location and Nature of Deviation 5/8 5/15 West Perimeter TLD Sampling Station (WNW): Quarterly TLD missing.

Neals Landing, Fla. TLD Sampling Station: Annual TLD missing.

5/22 North Perimeter Air Sampling Station: Pump Failure -

Slightly reduced air volume for particulate and iodine samples.

6/12 Cedar Springs, Ga. Milk Sampling Station: Milk no longer available from this location.

North Perimeter Air Sampling Station: Pump failure -

Reduced sample volume for particulate and iodine samples.

6/19 North Perimeter Air Sampling Station: Pump out of service for repair - No particulate or iodine sample.

6/26 East Perimeter TLD Sampling Station: Quarterly TLD missing.

7/3 Neals Landing, Fla. Air Sampling Station: Pump failure -

Reduced volume for particulate sample.

7/17 Whatley Farm - Resampled watermellon due to loss of first mellon in shipment.

9/4 River Intake Structure Air Sampling Station: Particulate filter - Delay for one week in shipment due to omission.

9/11 Benthos (Clams) and aquatic vegetation samples for 1st has of 1978 were reported as lost in transit.

9/25 North Perimeter Air Sampling Station: Pump failure - Low volume for particulate and iodine samples.

(16)

TABLE 5 ANALYTICAL DATA NOT REPORTED DURING 1978 Sample Analytical Date Sample and Nature of Problem Contractor 3/78 Milk - Gamma Spec and Radiostrontium Re- EIC sults were not Reported For Indicator Sample 4/78 Milk - Both Indicator and Control Samples EIC Lost in Processing - No gamma Spec or radiostrontium results reported 8/78 Milk - Sample apparently lost in transit EIC No iodine, gamma spec or radiostrontium results reported 7/78 Watermellon - Initial Indicator Sample and UGA Replacement Lost in transit - No gamma spec results reported 5/78 Aquatic Vegetation - Both indicator and EIC control samples apparently lost in transit -

No gnmma spec or radiostrontium results re-ported 5/78 Benthos (Clams) - Both indicator and control EIC samples apparently lost in transit - No gamma spec or radiostrontium results re-ported

(17)

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(19) channel MCA and a special counter designed and built by the U. Ga.

for counting iodine-131 activity in charcoal cartridges, using two 1 x 3 NaI(Tl) detectors and matched photomultiplier tubes.

B. External Radiation For the continuous measurement of environmental gamma radiation, natural LiF (TLD-100) chips were supplied and read by EIC. These LiF chips were pre-selected for environmental radiation monitoring to fall within a total dose range of 14 per cent relative to an exposure of 200-300 mR from a calibrated source. TLD packets each containing five ultrasonically cleaned and annealed LiF chips were supplied on both a quarterly and an annual basis. The chips were first sealed in opaque polyethylene to give a packet that was light-tight, weather-proof, and which had a low mass attenuation for radiation (approximately 50 mg/cm 2),

Two control TLD packets were shipped with each quarterly and annual batch of TLD's as an indicator of any unusual exposure during transit, and at the plant site prior to, or af ter field exposure.

On the plant site, all TLD packets were kept in a lead safe with 2-inch walls except for those receiving field exposure or in the process of being exchanged. Control Packet No. I which had been received with the new batch of TLD's and Control Packet No. 2 received with the previous batch of TLD's were returned with the field exposed TLD's for a reading of their respective doses. The new Control Packet No. 2 remained in the safe until the next TLD exchange and the above procedure was repeated.

At each external radiation monitoring station, shown in Figures 1 and 2, two TLD packets, one changed and read quarterly and one changes and read annually, were exposed side-by-side on wooden stakes at a height of one meter above the ground. For the computation of the net field doses, a log of all exposure periods was maintained for each TLD packet.

C. Milk Milk samples were collected semi-monthly at the two locations shown in Figure 2 and were analyzed by EIC for iodine-131, gamma emitters, and strontium-89, 90 in accordance with the schedule shown in Table

2. As a preservative during shipment, 1 ml of a 25 per cent (by weight) merthiolate (Thimerasol) solurion and 4 ml of a 6N NaOH solu-tion were added to each 2.5 gallon sample. (Samples of milk were not available at the indicator station in Early County, Georgia after May, 1978).

The iodine-131 concentration in each sample was determined by collection on avion exchange resin, elution with sodium hypochlorite, and precipitation as silver iodine for measurement of the beta activity with a deckman Widebeta II or Lowbeta II low background proportional counter. Stable iodine carrier was added to each sample for determina-tion of the radiochemical yield.

(20)

For each sampling station, once each month a 0.6 liter sample was evaporated to dryness at 1000C using a thin plastic film to re-tain the residue. The residues were then analyzed by EIC for gamma emitters using a 10 per cent relative efficiency low background Ge(Li) detector (either an 18 or 20% efficiency detector was used after March, 1978) and a computer based Nuclear Data 4096 channel MCA.

Also, once each month for each sampling station, a one or two liter aliquot of milk was taken for radiostrontium analysis. Follow-ing an EDTA separation of calcium, the single separation dual count technique, using a Beckman Widebeta II or Lowbeta II background pro-portional counter, was used for beta measurements. Following the second count, the in-growth of ythium-90 determined. Stable strontium and yttrium carriers were added, respectively, for determination of radiochemical yields. From these data, the strontium-90 and strontium-89 concentrations were calculated.

D. Vegetation

1. Forage Once each month, forage was collected from indicator grass plots located near the air monitoring stations at the plant site perimeter in sectors 9 (SSE) and 16 (N), and from a control grass plot located near the air monitoring station in Dothan, After drying and pulverizing the samples were analyzed by U. Ga. for gamma emitters using a 9 per cent relative efficiency low background Ge(Li) detector (18%

efficiency detector after May, 1978) and a Canberra 4096 channel computer based MCA.

2. Vegetables and Fruits

a. Green leafy vegetables During the growing season, October through March, green leafy vegetables were obtained monthly as available from gardens in the vicinity of the plant (1-3 miles) and from gardens in the Dothan area (>10 miles) and were analyzed by U. Ga. for gamma emitters using a 9 per cent relative efficiency low background emitters using a 9 per cent relative efficiency low background Ge(Li) detector (18%

efficiency detector after May, 1978) and a Canberra 4096 channel computer-based MCA.

b. Other Vegetables and Fruits As available, samples of the principal vegetables and fruits (non-green leafy) grown in the plant vicinity (1-3 miles) were obtained at harvest along with samples from gardens in the Dothan area (>10 miles). The edible portions of these samples were prepared and analyzed fer gamma emitters by U. Ga. using a 9 per cent relative efficiency low background Ge(Li) detector (18% efficiency

(21) detector af ter Fby,1978) and a Canberra 4096 channel computer-based FEA.

E. Soil Semi-annual irl situ gamma-ray spectroscopy measurements were made by U. Ca. using a 14 per cent relative efficiency Ge(Li) detector and gamma-ray spectroscopy system specially designed for field use, at the 9 indicator locations shown in Figure 1 and at the 6 community and con-trol (background) locations shown in Figure 2. A 1024 channel Canberra MCA was interfaced to a Hewlett-Packard 9825A calculator for data storage and analysis.

F. Surface Water (River)

Samples of water from the Chattahoochee River, above and below the plant site at the locations shown in Figure 3, were collected on a semi-continuous basis with Instrumentation Specialties Company (ISCO) samplers.

Monthly composites were sent to U. Ca. for radioactivity analysis. One liter aliquots from each monthly composite were placed in trays lined with plastic film and evaporated to dryness at 100 C. The residue and plastic film was folded to fit a petri-dish and analyzed for gamma emitters using a 9 per cent relative efficiency Ge(Li) low background detector (18% efficiency detector after May, 1973) and a Canberra 4096 channel computer-based MCA.

At the end of each quarter, for each sampling location, the balance of the three monthly compcsites were combined to give a quarterly com-posite sample. Approximately 30 m1 from each quarterly composite sample was distilled and a 25 ml aliquot taken for tritium analysis using a large volume (100 ml) low background liquid scintillation counter specially designed and built by U. Ga.

One liter aliquots were taken from the quarterly strontium-89, 90 composites, evaporated to dryness, acidified and the strontium converted to the carbonate for strontium-89, 90 analysis using the single separation dual count technique. Stable strontium carrier was used for determination of radiochemical yield. The beta activity was determined using a Beckman Lowbeta II low background proportional counter.

G. Aquatic Vegetation (River)

Samples of aquatic vegetation were collected from the Chattahoochee River above and below the plant site on a semi-annual schedule at loca-tions. shown in Figure 3 and were sent to EIC for radioactivity analysis.

A portion of each sample was taken, dried, pulverized, and analyzed for gamma emitters using a 10 per cent relative efficiency low background Ge(Li) detector (either an 18 or 20% efficiency detector was used after March, 1978) and 4096 channel computer-based Nuclear Data MCA.

The remainder of each sample was dried, ashed, acidified and converted to strontium carbonate for strontium-89, 90 analysis. The single separation dual count technique, using a Beckman Widebeta II or Lowbeta II low back-ground proportional counter was used. This was followed by a yttrium separation and a count of the in-grown yttrium-90. Stable strontium and yttrium carriers were added for determination of the respective radio-chemical yields.

(22)

UMBIA U

ANDREWS LOCK S DAM lFARLEY

_ C MILES l N' # #"

P

--~

g 4s sN EARLY COUNTY ASHFORD !

12 S

^

, s 9 Y o

84 - Se HOUSTON COUNTY ALABAMA S INDICATORS STATIONS CONTROL STATIONS S FISH AND SEDIMENT SURFACE WATER AND FISH E SURFACE AND GROUND WATER BENTHCS AND VEGETATION E BENTHOS AND VEGETATION (WHERE AVAIL ABLE- ABOVE (WHERE AVAIL ABL E- BELOW ANDREWS LOCK 8 DAM)

PLANT DISCHARGE) b GROUND WATER FIGURE 3. INDICATOR AND CONTROL SAMPLING LOCATIONS FOR WATERBORNE ENVIRON MENTAL RADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA.

s (23)

H. Benthos (Clams)

Samples of clams were collected from the Chattahoochee River above and below the plant site on a semi-annual schedule at locations shown in Figure 3 and were sent to EIC for radioactivity analysis. The tissue was separated from the shells, dried and pulverized for analysis of gamma emitters using a 10 per cent relative efficiency low background Ge(L1) detector (either an 18 or 20% efficiency detector was used after March, 1978) and 4096 channel computer-based Nuclear Data MCA. After completion of the gamma-ray spectroscopy analysis, the tissue samples were ashed, acidified and converted to strontium carbonate for strontium-89, 90 analysis. The single separation dual count technique using a Beckman Widebeta II or Lowbeta II low background proportional counter was used. This was followed by a uttrium separation and a count of the in-grown yttrium-90. Stable strontium and yttrium carriers were added for determination of the respective radiochemical yields.

I. Fish (River)

On a semi-annual basis three types of fish - game, forage feeding, and bottom feeding - were collected from the Chattahoochee River at the locations shown in Figure 3 and were sent to EIC for gamma-ray spectro-scopy analysis. The edible tissue was removed, dried, pulverized and analyzed for gamma emitters using a 10 per cent relative efficiency low background Ge(Li) detector (either an 18 or 20% efficiency detector was used after March, 1978) and a 4096 channel computer-based Nuclear Data MCA.

J. Sediment (Rive r)

On a semi-annual basis sediment samples were collected from the Chattahoochee River above and below the plant site at the locations shown in Figure 3. Approximately 1 kg from each sampling point was sent to U. Ga. for gamma-ray spectroscopy analysis. The samples were dried, mixed, and analyzed using a 9 per cent relative efficiency low background Ge(L1) detector (18% efficiency detector after May, 1978) and a Canberra 4096 channel computer-based MCA.

Also, approximately 1 kg from each location was sent to EIC for strontium-90 analysis. The samples were dried, mixed, and a portion of each was treated with acid. The strontium was converted to the carbonate and the strentium-90 content determined using the single separation dual count technique. The beta activity was measured with a Beckman Widebeta II or Lowbeta II low background proportional counter.

Stable strontium carrier was added for determination of radiochemical yield.

K. Groundwater (Well)

In the Farley Plant area, there were no indicator sources of groundwater in the true sense of the definition. A well which serves the Great Southern Paper as a source of potable water, which is located on the east bank of the Chattahoochee River about four miles south-southeast cf the plant was sampled on a quarterly basis and designated as an indicator station. A deep well which supplies water to King's Trailer Court located about 0.9 mile west of the center of the plant was sampled on a quarterly basis and designated as a control (back-

(24) ground) station. Samples from both were sent to U. Ga. for radio-activity analysis. An aliquot from each sample was taken for tritium analysis. After distillation, 25 mi samples were analyzed using a large volume (100 ml) low background liquid scintillation counter specially designed and built by U. Ga. From the remainder of each sample, a one liter aliquot was taken and evaporated to dryness at 1000C in a tray lined with plastic film. The residue and film was folded to fit a petri dish and analyzed for gamma emitters using a nine relative per cent Ge(Li) detector (18% efficiency detector was used after May, 1978) and a Canberra 4096 channel computer-based MCA.

III. Results and Discussion Two atmospheric nuclear tests were conducted by the Peoples Republ}; of China during this operational period. The fallout radioactivity from the test on March 14, 1978 arrived at the plant site about 10 days later during an extended dry period. The second test occurred on December 17, 1978, thus had little influence on this report period.

For measurements involving radioactivity concentrations by volume or mass the designation " minimum detectable concentration" (MDC) is used to denote the limit of detection applicable at the 95 percent confidence level.

The MDC is defined as "the smallest concentration of radioactive material in a sample that will be detected with 95 percent probability with only 5 percent probability of falsely concluding its presence." For a particular measurement, which may include radiochemical separation:

MDC =

2.22 EMY where MDC is the estimated minimum detectable concentration as defined above (pCi per unit mass or volume)

Sb is the standard deviation of the background counting rate for the sample being analyzed ( a posteriori) or of a blank sample (a priori) as appropriate (counts per minute) 2.22 is the number of transformations per picocurie per minute E is the counting efficiency (counts per transformation)

M is the weight of sample in kilograms or volume of sample in liters, as applicable Y is the fractional radiochemical yield (when applicable)

For measurements involving a quantity of radioactivity or radiation that is independent of the sample volume or mass the designation " lower limit of detection" (LLD) is used to denote the limit of detection applicable at the 95 percent confidence level. The LLD is defined as "the smallest amount of sample activity that will yield a net count for which there is confidence at a predetermined level that activity is present". It applica-tions are limited to measurement systems to denote a limiting detection capability without respect to the size of sample and/or radicchemical yield and to measurements which by their nature do not involve concentrations, such as radiation dose rates (mrad /hr., mrad /qtr., etc.)

(25)

A. Airborne Particulates and Iodine The results of the radioactivity analyses of airborne particulate filters and iodine charcoal cartridges are shown in Table F02-1. The mean gross beta activity was slightly higher for the indicator stations than for the cammunity and control station locations. The mean values for this operational period were also slightly greater than the preopera-tional mean values. However, the differences in both cases is not con-sidered to be significant.

The gamma-ray spectroscopy data for the air particulate filters following the March 15, 1978 Chinese nuclear test showed the presence of fission product fallout similar to that noted during the preoperational period following the September 26, 1976 Chinese nuclear test. This is also true for the strontium-89 and strontium-90 analysis resalts. However, for the first time iodine-131 was measured at concenetraions above the MDC in both the particulate samples and the charcoal cartridges. No significant differences were noted between the indicator and control locations. The detection of measurable particulate iodine-131 is attri-buted to the fact that it was formed during a nuclear test about 10 days earlier, thus a portion of the gaseous iodine-131 had been absorbed on perticulates, and the very short time interval from collection to gamma spec measurement of the filter paper composites. The detection of iodine-131 on some charcoal cartridges resulted from the use of new detection equip-ment which lowered the MDC by approximately a factor of two.

B. External Radiation The results of the external radiation measurements using TLD packets, each containing five LiF chips, are shown in Table F02-2. Because of dif ferences in soil radioactivity site specific dif ferences in external radiation levels are reflected in these data. The mean values for the annual TLD's were higher than the four quarterly TLD's for the same locations, as had been noted during the preoperational period. However, the difference was greater for the indicator locations than for the community and control locations. This is an example of the unexplainable variability in results, which was noted during the preoperational period from the use of LiF TLD's to measure external radiation levels.

(NOTE: At some TLD measurement locations duplicate TLD packets were exposed for QA purposes, thus the number of TLD values reported exceeds the number of external radiation measurement locations shown in Table 2.)

C. Milk The results from the analysis of milk for radioactivity are shown in Table F02-3. Milk from the Brooks-Silcox Dairy was sampled as the control, whereas milk from a single individually owned cow was sampled for the indicator location f rom January through May. The effect of the fallout radioactivity f rom the Chinese nuclear test for iodine-131 and

(26) strontium-90 was enhanced, for the indicator cow primarily on pasture, when compared to the control dairy. This difference was noted following atmospheric nuclear tests by the Chinese during the preoperational period.

The maximum value for iodine-131 during this operational period was 51 pC1/1 as compared to 120 pC1/1 during the p~reoperational period. Also, the gamma-ray spectroscopy data did not reflect the effect of the fallout radioactivity to the extend that had been noted during the preoperational period.

D. Vegetation The vegetation sampled during this operational period included forage, green leafy vegetables and food crops grown in the area. The radioactivity analysis results for this operational period are shown in Table F02-4.

Forage, as during the peroperational period, continued to be a very effective and sensitive indicator of airborne radioactivity. All of the expected gamma emitting fission products were measured at both the indica-tor and control locations following the Chinese nuclear test on March 5, 1978. The specific activity values for the various gamma emitting radio-nuclides were not significantly different for the indicator locations and the control location. The average value for those measurements in which the radioisotope concentration exceeded the MDC was significantly less than for the preoperational period. This is attributed to dry deposition as compared to wet deposition during the preoperational period. The number of gamma emitting fission products measured on the green leafy vegetables was much smaller and the radioactivity levels were much lower per kilogram of sample, even when both are compared on a wet weight basis.

This is in part due to no samples of green leafy vegetables being available immediately after the Chinese nuclear test. As noted during the preoperational period the vegetables and fruits sampled during the summer were poor indica-tors of airborne radioactivity. Occasionally cesium-137 was measured at levels near its FEC in both the indicator and control samples.

E. Soil The results of the in situ Ge(Li) gamma-ray spectroscopy analysis of soil during this operational period are shown in Table F02-5. Cesium-137 was measured at all locations in detectable quantities. However, niobium-95 and cesium-134 were present in measurable quantities only in the spring following the Chinese nuclear test. The differences between indicator and control locations were not significant.

F. Waterbornc: Surface and Ground Water The results of radioactivity analyses of surface water from the Chattahoochee River and ground water from wells are shown in Table F02-6.

For the monthly surface water composite samples only one sample from the upstream control location showed the presence of man-made gamma emitters in excess of the MDC. For the quarterly composites the upstream control location showed a higher strontium-89 level in one sample. No significant

e 4 (27) difference were noted for tritium in the indicator and control station samples. For the ground water samples a detectable quantity of tritium was measured in only one control sample. During the preoperational period a number of man-made and natural radionuclides were detected on a somewhat random basis at very low concentrations in both the surface and ground water samples.

G. Aquatic Vegetation (River)

The results of the radioactivity analysis of aquatic vegetation from the Chattahoochee River are shown in F02-7. From the one set of samples only strontium-90 was found in detectable concentrations and these were considerably less than measured during the preoperational period.

H. Benthos: Clams The results of the radioactivity analysis of tissue from Chattahoochee River clams are shown in Table F02-8. From the one set of samples only strontium-90 was found in detectable quantities. As noted during the preoperational period clams appear to be a poor indicator for waterborne radioactivity.

1. Fish: River The results of gamma-ray spectroscopy analysis of the edible portions of three types of fish taken from the Chattahoochee River are shown in Table F02-9. As was noted during the preoperational period, Cesium-137 was the only man-made radienuclide found in excess of the measurement MDC and this true for only one sample.

J. Sed iment : River The results of radioactivity analysis of sediment samples from the Chattahoochee River are shown in Table F02-10. No man-made radionuclides were found in the samples. The results were typical of those found during the preoperational period.

IV. Conclusion During this operational period there was no evidence to indicate any increase in airborne or waterborne environmental radioactivity as the result of plant operation. This conclusion resulted from a comparison of indicator and control location values, as well as, with data for the preoperational surveillance period. This conclusion is supported by the very small quantities of radioisotopes measured in the plant effluents discharged to the environment, as reported in the semi-annual radioactive effluent release reports for 1978.

TABLE F02-1 AIRBORNE: PARTICULATES AND IODINE - OPERATIONAL RADIOACTIVITY SUNILSRY JOSEPH H. FARLt.Y NUCLEAR PIANT LICENSE NO. NPF-2, HOUSTON COUNTY, ALABAMA January - December, 1978C Indicator Location Type and All Indicator With 111ghest Community Control Pkdium or Pathway Total Number Locations Annual Hean Locations Locations Sampled of Analyses Nominal Mean (f)b Name Hean (f)b Hean (f)b Hean (f)D (Unit of Meas trement) Pe r f o rmed MDCa Rangeb Distance and Direction Rangeb Rangeb Rangeb Cross B 516 0.002 0.125 (205/205) River Intake Structure 0.125 (50/50) 0.115 (155/155) 0.!!S (156/156)

Air Pat'ttculates 0.020 - 1.55) 0.8 Mile - ESE (0.025 - 1.35) (0.021 - 1.35) (0.023 - 1.45)

P "

Camma Spec 40 7Be 0.016 0.073 (1(/16) River Intake Structure 0.082 (4/4) 0.084 (12/12) 0.083 (12/12)

(0.065 - 0.10) 0.8 title - ESE (0.078 - 0.083) (0.067 - 0.15) (0.069 - 0.098) 40 K 0.021 0.062 (3/16) North Perimeter 0.077 (1/4) 0.050 (4/12) 0.053 (3/12)

(0.048 - 0.077) 0.8 Hile - N - - - -

(0.043 - 0.055) (0.040 - 0.068) 9 Zr 0.005 0 010 (2/16) South Perimeter 0.010 (1/4) 0.007 (3/12) 0.008 (1/12)

(0.009 - 0.010) 1.0 Mile - SSE ----

(0.007 - 0.008) ----

95tib 0.002 0.003 (6/16) Plant Lntracnce 0.004 (1/4) 0.004 (6/12) 0.003 (5/12)

(0.002 - 0.004) 0.9 !!1le - WSW ----

(0.002 - 0.004) (0.002 - 0.005) 103Ru 0.002 0.038 (4/16) River Intake Structure 0. 0 50 (1/4) 0.036 (3/12) 0.026 (4/12)

(0.034 - 0.050) 0.8 Mlle - ESE ----

(0.030 - 0.041) (0.003 - 0.062) 106Ru 0.01G (0.028 (2/16) River Intake Structure 0.029 (1/4) 0.020 (2/12) 0 025 (4/12)

(0.027 - 0.029) 0.8 Mile - ESE ----

(0.014 - 0.025) (0.023 - 0.028) 1311 0.002 0.034 (4/16) River Intake Structure 0.041 (1/4) 0.032 (3/12) 0.029 (3/12)

(0.031 - 0.041) 0.8 Mile - ESL ----

(0.031 - 0.034) (0.018 - 0.036)

D h

\

l'

TABLE F02-1 (Cont'd) I29)

AIRBORNE: PARTICULATES AND IODINE - OPERATIONAL RADI0 ACTIVITY SUMF1ARY JOSEPl! M. FARLEY NUCLEAR PLANT LICENSE NO. NPF-2. HOUSTON COUNTY, ALABAMA January - December,1973c Indicator Location Type and All Indicator With 111ghest Community Control Medium or Pathway Total Number Locations Annual Mean Locations Locations Sampled of Analyses Nominal Mean (f)b Name Mean (f)b Hean (f)b Hean (f)b (Unit of tkasurement) Performed HDCa Rangeb Distance and Direction Rangeb Rangeb Rangeb 137Cs 0.002 0.004 (9/16) Plant Entracne 0.D05 (2/4) 0.005 (8/12) 0.005 (7/12)

(0.002 - 0.006) 0.9 ftile - WSW (0.004 - 0.006) (0.002 - 0.007) (0.002 - 0.007) 140Ba 0.009 0.050 (4/16) River Intake Structure 0.064 (1/4) 0.050 (3/12) 0.043 (3/12)

(0.034 - 0.064) 0.8 1111e - ESC ----

(0.047 - 0.054) (0.033 - 0.051) 140La 0.005 0.056 (t./16) River Intake Structure 0.078 (1/4) 0.050 (3/12) 0.049 (3/12)

(0.043 - 0.078) 0.8 Mile - ESE ----

(0.043 - 0.054) (0.034 - 0.060) 141Ce 0.003 0.023 (4/16) River Intake Structure 0.027 (1/4) 0.021 (3/12) 0.021 (3/12)

(0.020 - 0.027) 0.3 Hile - ESE ----

(0.019 - 0.023) (0.013 - 0.027) 144Ce 0.010 0.032 (8/16) South Perimeter 0.035 (2/4) 0.030 (6/12) 0.032 (6/12)

(0.026 - 0.044) 1.0 Mile - SSL (0.026 - 0.044) (0.025 - 0.036) (0.025 - 0.040) 203r1 0.002 < HDC ---- ----

< MDC < HDC 212Pb 0.002 < HDC --- ----

< HDC ----

214Pb 0.004 < FUC ---- ---- ----

< HDC 214B1 0.003 0.003 (1/16) River Intake Structure 0.003 (1/4) 0.004 (1/12) < PDC 0.8 Mile - ESE ---- ----

i.3J

s

(,,,

en

TABLE F02-1 (Cont'd)

AIRBORNE: PARTICULSTES AND IODINE - OPERATIONAL RADIOACTIVITY

SUMMARY

JOSEPH H. FARLEY NUCLEAR PLANT LICENSE NO. NPF-2, !!OUSTON COUNTY, ALABAMA January - December, 1973c Indicator Location Type and All Indicator With liighest Community Control Medium or Pathway Total Number Locations Annual Mean Locacions Locations Sampled of Analyses Nominal Hean (f)b Name Mean (f)b Mean (f)b Hean (f)b Performed Rangeb Distance and Direction Rangeb Rangeb Rangeb (Unit of Measurement) MDCa Radiostrontium 40 89S r 0.0003 0.0115 (8/16) North Perimeter 0.0195 (1/4) 0.C125 (5/12) 0.0120 (5/12)

(0.0010 - 0.0250) 0.8 Mlle - N ----

(0.0015 - 0.0210) (0.0012-0.0230) 90Sr 0.0002 0.0019 (15/16) Plant Entrance 0.0020 (4/4) 0.0018 (12/12) 0.0023 (12/12)

(0.0006 - 0.0033) 0.9 Mile - WSW (0.0006 - 0.0033) (0.0006 - 0.0033) (0.0010-0.0036) lodine 259

^f[g

1. "'l C"'~ I3I I 0.041 0.039 (4/155) North Perimeter 0.043 (1/51) 0.037 (1/52) 0.048 (2/52)

(pC1/m3) (0.034 - 0.043) 0.8 Mile - N -- ----

(0.045 - 0.050)

(a) Mean Minimum Detectable Concentrations Calculated per Equatirp 1 (b) Hean and Range Based Upon Detectable Measurements Only. Fraction of this report. The MIK:'s for Cross 8. Radiostrontium and Iodine of Detectable Measurements at Specified locations in Parenthesis were obtained Using Blank Backgrounds (A Priori) Whereas, for (f). ,

'd Gamma-Ray Spectroscopy Actual Sample Backgrounds were Used (A (c) No routine Anomalous Measurements Reported During This Period. #j g *. Postertori).

Y

,- m f}4 y; 1

TABLE F02-2 EXTLRNAL RADIATION - OPERATIONAL

SUMMARY

JOSLPH M. FARLLY NUCLEAR PLA!Tf LICENSE NO. NPF-2,1100STO!I COUNTY, ALABAMA January - December, 1973c Indicator Location Type and All Indicator With Highest Community Control Medium or Pathway Total Number Locations Annual Mean Locations Locations Sampled of Analyses Nominal Mean (f)b Name Mean (f)" Mean (f)b Mean (f)b

(!!n i t of Measurement) Performed LIDa Rangeb Distance and Direction Rangeb Range b Range b

• TLD - Quarterly Gross y 110 10 15.0 (70/70) East Perimeter 23 (3/3) 12.0 (16/16) 13.5 (24/24)

(MRAD) (9.9 - 27) 0.8 ftile - E (20-27) (9.3 - 13.0) (9.0 - 18.0)

ILD - Annual Cross y 27 10 70 (18/18) East Perimeter 100 (1/1) 54 (4/4) 61 (5/5)

(HRAD) (58 - 100) 0.8 Mile - E ---

(58 - 60) (49 - 70)

TLD - Annuald Cross y 26 10 58 (16/16) East Perimeter 34 (1/l) 47 (4/4) 53 (6/6)

(MRAD) (48 - 84) 1.0 Mile - NE ---

(46 - 43) (46 - 62)

(a) Im er Limit of Detection as Defined in HASL-300, For LIF TLDs as Achieveable in Practice.

(b) Mean and Range Based on Detectable Measurements only. Fraction of Detectable Measurements at Specified I.ocation in Parenthesis (f).

(c) No Nonrautine Anomalous Measuresents Reported During This Period.

(d) Sum of Four Quarters for Comparative Purposes.

TABLE F02-3 (32)

MILK - OPERATIONAL RADI0 ACTIVITY SUM?tARY JOSEPH M. FARLEY NUCLEAR PLANT LICENSE h0. NPF-2, !!OUSTON COUtTTY, ALABAMA January - December,1978C Type and All Indicator Medium or Pathway Total fiumber Location 6d Ir.dic tor 1.ocation with Highest Annual Mean Control Location Samples of Analyses tiominal Name Mean (f) Mean (f)b (Unit of Maasurement) Performed imCa Mean{f)b Range Distance and Direction Rangeb Range b Mlli Radioiodine 34 (pC1/1) g3gI 0.4 (0.5) 30 (2/10) Cedar Springs 30 (2/10) 11 (2/24)

(10 - 51) 5 Mi.ies - E (10 - 51) (1.0 - 21)

Camma Spec 13 40K 400 1000 (3/3) Cedar Springs 1000 (3/3) 1300 (9/10)

(620 - 1600) 5 Miles - E (620 - 1600) (840 - 1900) 137Ca 31 (25) 15 (1/3) Cedar Springs 15 (1/3) 17 (1/10) 5 Miles - E -- ----

208 T1 23 -- ~~- -

< MDC 212 Pb 84 < ?!DC ---- ---

< MDC Pb 100 < itDC ---

< MDC 214 B1 64 ---- - ---

< MDC 226 Ba 810 -- --- --

< MDC 9

j.i

(33)

TABLE F02-3 (Cont'd)

MIIK - OPERATIONAL RADIOACTIVITY SDtMARY JOSEPH M. FARLEY NUCLEAR PLANT LICENSE h0. NPF-2,110USTON COUh'TY, ALABAMA January - Decesher, 1978C Type and All Indicator Medium or Pathway Total 14 umber Locationsd Indicator Location with itiRhest Annual Mean Control Location Samples of Analyses I;omina l Name Mean (f) Mean (f)b (Unit of Measurement) Performed itDCa Mean{f)b Range Distance and Direction Rangeb Range b Radiostrontium 13 89S r 1.0 (10) tuC ---- ----

tu)C Sr 1.4 (2) 14 (3/3) Cedar Springs 14 (3/3) 4 (9/10)

(9 - 23) 5 Miles - E (9 - 23) (1.6 - 6)

(a) Mean minimum detec table concentrations calculated per equation 1 of (c) tio nonroutine anomalous measurements reported during this period.

this report using blank backgrounds (a prior!). For the period April- (d) indicator milk samp!!ng locations not available af ter tby, 1978.

December, 1978 MDC values trom Farley ETS Table 3.2-3 were used as the basis f o t' reporting measurement data. (Shown in parenthesis where applicable)

(b) Hean and range based on. detectable measurements only. Fraction of detectable measurements at specified locations in parenthesis (f).

e

(34)

TABLE F02-4 VEGETATION: FORACE, VEGETABLES A:lD FRUITS - OPERATIONAL RADIDACTIVITY SU?2tARY JOSEP!l H. FARLEY NUCLEAR PLAhi LICENSE NO. NPF-2, il0USTON COUlTTY, ALABAMA January - December, 1978C Type and All Indicator Medium or Pathway Total !! umber Locations Indicator Location with Highest Annual Mean Control Location Samples of Analyses llomina l Name Mean (f) Mean (f)b gnit of Measurement) Mean ff)b Performed MDCa Range Distance and Direc tion Rangeb Ranne b Forage d Camuu Spec 42 (pCi/kg-Dry) 7 Be 920 4900 (22/28) North Ferimeter 5300 (9/14) 4600 (11/14)

(1200 - 12000) 0.8 Mile - 14 (1850 - 12000) (1350 - 10600)

K 2500 17000 (28/28) North Perimeter 13500 (14/14) 12500 (14/14)

(3400 - 39000) 0.3 Mile - N (6500 - 39000) (4400 - 19>00)

Zr 255 330 (2/28) North Perimeter 410 (1/14) 360 (1/14)

(360 - 410) 0.8 Mile - N ---- ----

Nb 145 600 (4/23) South Perimeter 650 (2/14) 300 (3/14)

(550 - 650) 1.0 Mile - SSE (560 - 740) (140 - 550) 103 Ru 140 470 (4/28) South Perimeter 580 (2/14) 560 (2/14)

(220 - 930) 1.0 title - SSE (230 - 930) (480 - 630)

Ru 920 1500 (1/23) South Perimeter 1500 (1/14) < MDC 1.0 Mile - SSE ----

1 130 880 (4/28) Souti. Perimeter 950 (2/14) 960 (2/14)

(230 - 1650) 1.0 Mile - SSE (230 - 1650) (270 - 1650)

Cs 130 210 (11/23 South Perimeter 220 (7/14) 130 (5/14)

(77 - 330) 1.0 Mile - SSE (77 - 330) (100 - 250)

(35)

TABLE F02-4 (Cont'd)

VEGETATIO:1: FORAGE, VECETABLES AND FRulTS - OPERATIO:4AL RADIGACTIVITY

SUMMARY

JOSEPH M. FARLEY NUCLE

• R PIANT LICENSE NO. NPF-2, !!OUSTON COUNTY, ALABAMA January - December,1978C Type and All Indicator Medium or Pathway Total Number Locations Indicator Location with Highest Annual Mean Control Location Samples of Analyses liominal Name Mean (f) Mean (f)b (Unit of Measurement) Performed ifDC 8 Mean{f)b Range Distance and Direction Rangeb Range b Ba 600 1400 (2/28) South Perimeter 2000 (1/14) 1350 (1/14)

(800 - 2000) 1.0 Itile - SSE ---- ----

La 240 1000 (3/28) South Perimeter 1450 (1/14) 800 (2/14)

(400 - 1450) 1.0 Mile - SSE ----

(400 - 1200)

Ce 180 470 (3/28) North Perimeter 500 (1/14) 340 (2/14)

(220 - 700) 0.8 Mile - N ----

(210 - 480)

Ce 630 1900 (9/28) South Perimeter 1950 (4/14) 1650 (5/14)

(660 - 4000) 1.0 Mile - SSE (940 - 3000) (720 - 3000) 08 TI 105 150 (2/20) South Perimeter 170 (1/14) < MDC (125 - 170) 1.0 Mile - SSE ----

Pb 185 310 (5/2H) South Perimeter 320 (4/14) 155 (2/14)

(155 - 430) 1.0 Mlle - SSE (155 - 430) (120 - 190)

Pb 200 440 (4/28) South Perimeter 440 (4/14) 260 (2/14)

(280 - 850) 1.0 Mile - SSE (28J - 850) (240 - 290) 81 230 610 ( 7/25) South Perimeter 640 (6/14) 230 (3/14)

(250 - 1900) 1.0 Mile - SSE (250 - 1900) (170 - 310)

(36)

TABLE F02-4 (Cont'd)

VU;ETATION: FORAGE, VEGETABLFS AND FRUITS - OPLRATIONAL RADIOACTIVITY SUt01ARY JOSEPil H. FARLEY NIICLEAR PIMT LICENSE h0. NPF-2,ll0USTON COUNTY, ALABAMA January - December, 1978C Type and All Indicator Medium or Pathway Total Number Locations Indicator Location with Highest Annual Hean Control Location Samples of Analyses Nominal Meanff)b Name Mean (f) Mean (f)b (Unit of Measurement) Performed MDCa Range Distance and Direction Rangeb Range b Ac 530 420 (1/28) South Perimeter 420 (1/14) ----

1.0 Mile - SSE - - - -

Creen Isa f y Vegetables G.uuma Spec 8 P "~ "I Be 135 165 (1/4) Farley Plant Area 161 (1/4) 160 (1/4)

--- 1-3 Hiles - All Directiona ---- ----

40 6200 (4/4) 5700 (4/4)

K 320 6200 (4/4) Farley Plant Area (2700 - 9300) 1-3 !!!!es - All Directions (2700 - 9300) (4700 - 6800) 95 28 (1/4)

Nb 26 --- ---- ----

I < HDC ----

26 (1/4)

Cs -24 ----

144 < ----

Ce 75 Mi>C ---- ----

'l

• Pb 36 57 (1/4) Farley Plant Area 57 (1/4) < MDC 1-3 Miles - All Directions ----

?b 43 60 (2/4) Farley Plant Area 60 (2/4) 60 (2/4)

( 50 - 70) 1-3 Miles - All Directions (50 - 70) (52 - 69)

TABLE F02-4 (Cont'd) I37}

VECETATION: FORACL, VEGETABLES A!1D FRUITS - OPl. RATIO:AL RADICACTIVITY SU:OtARY JOSEPil M. FARLEY NUCLEAR PLA!(T LICENSE h0. NPF-2, ll0USTON COU! TTY, ALABAMA January - December,1978C Type and All Indicator Medium or Pathway Total !Jumber Locations indicator Location with liighest Annual Mean Control Location Samples of Analyses liomina l Name Mean (f) Mean (f)b Performed Meanff)b Ranye Rangeb Range b Enit of Measurement) MDCa Distance and Direction Bi 50 85 (2/4) Farley Plant Area 85 (2/4) 66 (1/4)

(66 - 105) 1-3 Miles - All Directions (66 - 105) ---

22bg , g __ ,,,, __

Ac 64 < MDC ---- ---

130 (1/4)

Beans ( Bitt t e r ) Gamma Spec 2 (pCi/kg-Wet) 40 K 495 4600 (1/1) Farley Plant Area 4600 (1/1) 3800 (1/1) 1-3 Miles - All Directions ---- ----

214 Pb 51 < MDC --- ---- ----

214 B1 43 60 (1/l) Farley Plant Area 60 (1/1) < MDC 1-3 Miles - All Directions ----

cantaloupe Gauma opec 2 (pC1/kg-Wet) 40 K 495 1200 (1/1) Farley Plant Area 1200 (1/1)  !!00 (1/1) 1-3 Miles - All Directions --~~ ----

137 Gs 25 --- ---- ----

25 (1/1)

(33)

TABLE F02-4 (Cont'd)

VECETATION: FORACI:, VECLTABLES AND FRUITS - OPERATIONAL RADIOACTIVITY SUIDIARY JOSEPl! M. FARLEY NL' CLEAR PIANT LICENSE h0. iPF-2,llOUSTON COUtrTY, ALABAMA January - December,1978c type and All Indicator Medium or Pathway Total Number Locations Indicator Location with Highest Annual Mean Control Location Samples of Analyses Nominal Name Mean (f) Mean (f)b (Unit of Measurenent) Performed MDCa Mean{f)b Range Distance and Direction Rangeb Rangeb 214 81 43 < MDC ---- ----

< tidC Corn Canuna Spec 2 (pC1/kg-Wet) 40 K 495 2100 (1/1) Farley Plant Area 2100 (1/1) 1800 (1/1) 1-3 Miles - All Directions ---- ----

137 Ca 25 21 (1/1) Farley Plant Area 21 (1/1) 31 (1/1)

--~~

1-3 Mlles - All Directions ---- ----

208 Tl 20 < MDC ---- ---- ----

212 Pb 41 < itDC ---- ---- ----

214 B1 43 ---- --- ---

< MDC Cuc umbe r s Camma Spec 2 (pCi/k K-Wet) 40 K 495 1100 (1/1) Farley Plant Area 1100 (1/1) 1200 (1/l) 1-3 Miles - All Directions ---- ----

137 Ca 25 ---- ---- ----

27 (1/1)

N a'

(39)

TABLE F02-4 (Cont'd)

VEGETATION: l'ORAGE, VECETABLES AND FRUITS - OPERATIONAL RADIOACTIVITY SUtttARY JOSEPl! M. FAkLEY NUCLEAR PLANT LICENSE t 0. NPF-2,110USTON COUttrY, ALABAMA January - December, 1978c Type and All Indicator Medium or Pathway Total Ilumber Locations Indicator Location with Highest Annual Mean Control 1.oeation Samples of Analyscs 130minal Name Mean (f) Mean (f)b (Unit of Measurement) Performed itDCa Mean Range ff)b Distance and Direction Rangeb Range b 212 Pb M --- --- ---

<E 214 Pb 51 <E ---- - - -

< WC 214 B1 43 < !!DC ---- ----

< !!DC Okra Gamcw Spec 2 (p I - t) O K 495 2000 (1/1) Farley Plant Area 2000 (1/1) 1850 (1/1) 1-3 Miles - All Directions ---- ----

Ti 20 < MDC ---- ----

212 Pb 41 < MDC ---- ----

< MDC 214 Pb 51 < MDC ---- --- ----

'Bi 43 48 (1/1) Farley Plant Area 48 (1/1) < MDC 1-3 Miles - All Directions ----

Peanuts Gamma Spec 2 (pcth gWet) 40 K 495 3000 (1/1) Farley Plant Area 3000 (1/1) 4100 (1/1) 1-3 Miles - All Directions --- ----

11 2

. 6

(40)

TABLE F02-4 (Cont'd)

VEGLTATION: FORAGE, VECETABLES AND FRUlTS - OPERATIONAL RADIDACTIVITY SUM!!ARY JOSEPH M.'FARLEY NUCLEAR PLAPTT LICENSE h0. NPF-2,1100STON COUttfY, ALABAMA January - December, 1978C Type and All Indicator tiedium or Pathway Total Number Locations Indicator location with liighest Annual Mean Control Location Samples of Analyses 130minal Name Mean (f) Mean (f)b (Unit

• Measurement) Performed itDCa Mean{f)b Range Distance and Direction Range b RanReb 137 Cs 25 < !!DC ---- ----

70 (1/l) 214 B1 43 < MDC ---- ---- < MuC Pe.as Gamma Spec 2 (pC1/kg-Wet) 40 K 495 4200 (1/1) Farley Plant Area 4200 (1/1) 2300 (1/1) 1-3 Miles - All Directions ---- ----

137 Cs 25 17 (1/l) Farley Plant Area 17 (1/1) ----

1-3 Miles - All Directions ----

208 Tl 20 < MDC --- ---- ----

• 12 Pb 41 < MDC ---- ----

< MDC 214 Pb 51 < MDC ---- --- ----

81 43 < MDC ---- ---

< MDC Pecans Gamma Spec 4 (pC1/kg-Wet) 7 Be 215 < MDC ---- ---- ---

4

(41)

TABLE F02-4 (Cont'd)

VEGETATION: FORAGE, VEGETABLES AND FRUITS - OPERATIONAL RADIOACTIVITY SUM!!ARY JOSEPil M. FARLEY NUCLEAR PLAfff LICENSE h0. NPF-2, llOUSTON COU! TTY, ALABAMA January - December, 1978C Type and All Indicator Medium or Pathway Total 13 umber Locations indicator 1.ocation with liighest Annual Mean Control Location Samples of Analyses tiominal Name Mean (f) Mean (f)b

( L'n ! t of Maasurement) Performed MDCa Mean{f)b Ranpc Distance and Direction Rangeb Range b K 495 3000 (2/2) Farley Plant Area 3000 (2/2) 3200 (2/2)

(2600 - 3300) 1-3 Miles - Any Jirection (2600 - 3300) (2800 - 3500) 137 Cs 25 62 (1/2) Farley Plant Area 62 (1/2) < MDC 1-3 Miles - Any Direction ----

214 B1 43 < MDC ---- ----

< flDC 228 Ac 110 134 (1/2) Farley Plant Area 184 (1/2) ----

1-3 Miles - Any Direction Squela Gamma Spec 2 (pC1/kg-Wet) 40 K 495 1300 (1/2) Farley Plant Area 1300 (1/2) 2100 (1/2) 1-3 ftiles - Any Direction ---- ----

137 Ca 25 ,

22 (1/2) 208 Tl 20 < MDC ---- ---- ----

'12 >b i 41 < t1DC ---- ---- ---

214 Pb 51 ---- ---- ----

< MDC' t

t

,[ F.

TABLE F02-4 (Cont'd) (42)

VEGETATION: FORAGE, VEGETABLES Af;D FRUITS - OPERATIONAL RADIOACTIVITY SUtetARY JOSEPH H. FARLEY NUCLEAR P!Mr LICENSE :.0. NPF-2, 1[0USTON COU!!TY, ALABAMA January - December,1973C Type and All Indicator Medium or Pathway Total Number Locations Samples indicator Location with liighest Annual Mean Control Location of Analyses tominal Heanff)b Name Mean (f)

(Unit of Measurement) Performed MDCa Range Mean (t)b Distance and Direction Rangeb Rangeb 214 81 43 < MDC ----

< MIX:

Tomatoes Camma Spec 2 (pC1/kg-Wet) 40 K 495 1600 (1/1) Farley Plant Area 1600 (1/1)

---

1150 (1/1) 1-3 Miles - Any Direction ---- ----

137 Cs 25 16 (1/1) Farley Plant Area 16 (1/1) < MDC 1-3 Miles - Any Direction ----

• 14 B1 43 < MDC ----

< MDC Turntps (Roots Camima Spec 2

• E'

'K 495 3100 (1/1) Farley Plant Area 3100 (1/1) 1-3 Miles - Any Direction 2900 (1/l)

Ac 110 85 (1/1) Farley Plant Area 85 (1/1) ----

1-3 titles - Any Direction Watermellon Gamma Spec 1 (pCi/Lg-Wet) 40 K 495 (e) ----

-- MDC 137 Cs 25 (e) ----

---

< HDC pi. .

G si

?

(4 3)

TABLE F02-4 (Cont'd)

VEGETAT10M: FORACE, VEGETABLES AMD FRUITS - OPERATIONAL RADIDACTIVITY

SUMMARY

JOSEPH M. FARLEY NUCLEAR PIAfrI LICENSE h0. NPF-2, !!OUSTON COU:TIY, ALABAMA January - December, 1978c Type and All Indicator Medium or Pathway Total Number Locations Indicator Location with 111ghest Annual Mean Control Location Samples of Analyses I;ominal Name Mean (f) Mean (f)b (Unit of MeJsure wnt) Performed MDCa Hean{f)b Range Distance and Direction Rangeb Range b 214 81 43 (e) ---- ---

< MDC (a) Mean min Sun detectable concentrations calculated per equation 1 of (d) Mean wet / dry ratio for 1978 was 4.0.

this report using actual sample backgroumis (a posteriori). (e) Initial and replacement samples were both lost in transit to (b) t'+ an and range based on detectable measurements only. Fraction of U. CA.

J cectable measurements at specified locations in parenthesis (f).

. (c) Na nonroutine aiomalous measurements reported during this period.

p 4 h j

TABLE F02-5 (44)

S0!!. - OPLHATIONAL RA010 ACTIVITY SLHi4ARY JOSEPil M. FARLEY NUCLEAR PLANT LICENSE NO. NPF-2,1100STON COUNTY, ALABAMA January - December,1973c Indicator Location Type and All Indicator With liighest Community Control Medium or Pat hway Total Number Locations Annual Mean Locations Locations S a m,31 e.1 of Analyses Nominal Mean (f)b Name Mean (f)D Mean (f)b Mean (f)b (Unit of Measurrm-nt) Performed ttDCa Rangeb Distance and Direction Rangeb RanReb Rangeb Soli (In Situ) G.samve Spec 30 (PCl/kg - Dry) 40K 380 4200 (18/18) East Perineter 13500 (2/2) 1050 (6/6) 3000 (6/6)

(560 - 14500) 0.3 Mile - E (12000 - 14500) (6$0 - 1450) (820 - 5200) 95 1a. 66 (9/18) 30 East Perimeter 125 (1/2) 51 (3/6) 50 (3/6)

(24 - 125) 1.0 Mile - NE ----

(48 - $4) (33 - 65) 1 34 La 25 26 (9/18) East Perimeter 55 (1/2) 25 (1/6) 29 (3/6)

(17 - 55) 0.8 Mile - E --- --~~

(22 - 33)

I 37Cs 50 420 (18/18) South Perimeter 570 (2/2) 310 (6/6) 430 (6/6)

(145 - 600) 1.0 Mile - SSE (540 - 600) (215 - 530) (320 - 530) 20dfl 80 530 (18/18) East Perimeter 1000 (2/2) 360 (5/6) 540 (5/6)

(290 - 1050) 1.0 Mile - NE (1000 - 1050) (260 - 400) (390 - 630) 212Pb 240 1650 (13/18) East Perimeter 3150 (2/2) 1050 (6/6) 1500 (6/6)

(750 - 3250) 1.0 Mile - NE (3050 - 3250) (790 - 1300) (1050 - 1900) 214Pb 200 1450 (18/18) East Perimeter 2750 (2/2) 1150 (6/6) 1150 (6/6)

(630 - 3500) 0.8 Mile - E (2000 - 3500) (770 - 2450) L780 - 1350) 21281 570  !!OO (18/13) East Perimeter 2000 (2/2) d60 (6/6) 1000 (6/6)

(500 - 2350) 1.0 Mile - NE (1600 - 2350) (425 - 1250) (550 - 1600) i N

6. ,A

)

jy

.o

TABLE F02-5 (Cont'd) (45)

SOIL - OPERATIONAL RADIOACTIVITY SUtttARY JOSEPli H. FARLEY NUCLEAR PLANT LICENSE NO. NPF-2,110USTON COUNTY, ALABAMA January - December, 1973c Indicator Location Type and All Indicator With Illghest Community Control tkdlum or Pathway Total Number Locations Annual Mean Locations Locations Sampled at Analyses Nominal Mean (f)b Name Mean (f)b Hean (f)D Hean (f)b

' Unit of Measureient) Pe r f o rmed MDCa Rangeb Distance and Direction Ranged Rangeb Ranged 214 81 130 1450 (18/18) East Perimeter 3000 (2/2) 1150 (6/6) 1100 (6/6)

(680 - 3850) 0.8 Mile - E (2200 - 3850) (750 - 2900) (750 - 1300) 226 Ha 600 ---- ---

590 (1/6) 22H Ac 2 30 1500 (18/18) East Perimeter 2900 (2/2) 9 50 (6/6) 1450 (6/6)

(590 - 3000) 1.0 Mile - NC (2800 - 3000) (790 - 1100) (930 - 1850)

(a) Mean Minimum Detectable Concentrations Calculated per Equation I of this (c) No nonroutine anomalous measurements reported during this report using Actual Sample Backgrounds (A Posterior 1). period.

(b) Hean and Range Based on Detectable iteasurements Only. Fraction of Detect-able Measurements at Specified locations in Parenthesis (f).

.t ?- ,s 3

rWl' .

i- o

(46)

TABLE F02-6 WATERh0RiE:

SURFACE A:iD GROUtiD WATER - OPERATIONAL RADIOACTIVITY SU)tIARY JOSEPH M. FARLEY NUCLEAR PLAhi LICENSE h0. NPF-2, ll0USTON COUNTY, AIABAMA January - December, 1978C Type and All Indicator Medium or Pathway Total !1 umber Samples Locations Indicator Location with Highest Annual Mean Control Location of Analyses llominal Name (Unit of Measurement) Performed ttDCa F.ean{f)b Range Mean (f) Mean (f)D Distance and Direction Ranged Rangeb Sur f ace Water (River) Camma Spec 24 K 46 92 (1/12) Creat Southern Paper 92 (1/12)

River Mlle - 40 100 (2/12)

L37 (98 - 105)

Cs 4 < MDC ----

< MOC 140 Ba 7 --

15 (1/12) 208 Tl 4 < MDC ----

212 Pb 6 < MDC ---- ---

< MDC 214 81 7 < !!DC ----

226 Ra 60 ---

< MDC 223 Ac 13 < FUNC ----

Tritium 3 3

H 74 230 (3/4) Creat Southern Paper 230 (3/4)

(180 - 290) River Mile - 40 250 (3/4)

(180 - 290) (140 - 370)

( [.

n f..e

TABLE F02-6 (Cont'd)

WATERBORNE: SURFACE AND GROUND WATER - OPERATIONAL RADIOACTIVITY SUBM\RY JOSEPil M. FARLEY NUCLEAR Pillir LICENSE h0. NPF-2,110USTON COUtTfY, ALABAMA January - December, 1973C Type and All Indicator Medium or Pathway Total Ilurnber Locations Indicator Location with Highest Annual Mean Control Location Samples of Analyses 130minal Name Mean (f) Mean (f)b (Unft of Measurement) Performed FIDCa tieanff)b Range Distance and Direction Rangeb Range b Radiostrontium 8 89 Sr 2.0 6.1 (2/4) Creat Southern Paper 6.1 (2/4) 42 (1/4)

(5.6 - 6.6) River Mile - 40 (5.6 - 6.6) ---

93 Sr 1.4 < MDC --- ---

< MDC Ground Water (Well) Gamma Spec 8 (pCl/l) 40 K 47 33-(1/4) Creat Southern Paper Well 33 (1/4) 61 (1/4) 4 Miles - SSE --- --

137 Cs 3 < MDC --- ---

212 Pb 5 < MDC --- ---

< MDC 21481 7 --- ---- ---

< MDC Tritium 8 11 49 < MDC ---- ---

240 (1/4)

(a) tiean minimum detectable concentrations calculated per equation 1 of this (c) No nonroutine anomalous measurements reported during this report. The MDC's for tritium and radiostrontium were obtained using period.

blank backgrounds (a priori), whereas, for gamma-ray spectroscopy actual sample backgrounds were used (a posteriori).

(b) tiean and range based upon detectable measurements only. Fraction of detectable measurements at specified locations in parenthesis (f).

16,

(48)

TABLE F02-7 VEGETATION: AQUATIC - OPL2AT10NAL RADIOACTIVITY SUMt!ARY JOSEPH M. FARLEY NUCLEAR PLANT LICENSE h0. NPF-2,110USTON COUMTY, ALABAMA January - December, 1978C Type and All Indicator Medium or Pathway Total Number Locations Indicator Location with Highest Annual Mean Control Location Samples of Analyses liominal Name Mean (f) Hean (f)b (Unit of treasurement) Performedd ifDCa Maan{f)b RanPe Distance and Direction Rangeb Range b Aquatic (River) Camma Spec 2 Vegetation 40 (pci/kg-Wet) K --

1800 1/1 Chattahoochee River 1800 1/1 ---

River Mile - 12 ---

1 37 Cs 100 < tnC ---- ---

< MDC Radiostrontium 2 89 Sr 10 < MDC ---- ---

< MDC 90 Sr 5 20 1/1 Chattahoochee River 20 1/1 64 1/1 River Mile - 12 --- ---

(a) Minimum detectable concentrations from Farley ETS Table 3.2-3 used as (c) No nonroutine anomalous measurements were reported during this basis for reporting measurement data, period.

(b) Mean and range based upon detectable measurements only. Fraftion of (d) Samples for first half of 1978 were lost in transit.

detectable measurements at specified locations in parenthesis (f).

TABLE F02-8 BENTHOS: CthtS - OPERAilONAL RADIOACTIVITY SLM1ARY JOSEPl! M. FARLEY NUCLEAR PIANT LICE.NSE h0. NPF-2, ll0USTON COUt!TY, ALABAMA ,

January - December,1978C Type and All Indicator fledium or Pathway Total Number Locations Indicator Location with Highest Annual Mean Control Location Samples of Analyses Nominal Name Mean (f) Mean (f)b (Unit of iteasurement) Performed tinCa Mean{f)b Range Distance and Direction Rangeb Range b Benthos (Clams) Camma Spec 2 (pCi/kg-Wet Tissue) 137 Cs 100 < HDC ---- ---

< M)C Radiostrontium 2 89 Sr 10 < MDC ---- ---

< IS)C 90 Sr 5 51 (1/l) Chattahoochee River 51 (1/l) 42 (1/1)

River Ptile - 14 --- ---

(a) tiinimum detectable concentrations f rom Farley ETS Table 3.2-3 used as basis (c) No nonroutine anomalous measurements were reported during this for reporting measurement data. period.

(b) Mean and range based upon detectable measurements only. Fraction of detect- (d) Samples for first half of 1973 were lost in transit.

dbIe measurements at spec if ied Ioeat ions in pdrenthesis (f).

(50)

TABLE F02-9 FISH: RIVER - OPERATIOIIAL RADIOACTIVITY

SUMMARY

JOSEPH M. FARLEY NUCLEAR PIAttr LICENSE NO. NPF-2, 110USTON C00tTIY, ALABAMA January - December, 1970c Type and All Indicator Medium or Pathway Total Number Locations indicator Location with Highest Annual Mean Control Location Samples of Analyses 120minal Name Mean (f) Mean (f)b (L'n i t of Measurement) Performed itDCa Mean{f)b Range Distance and Direction Rangeb Rangeb Fish (Forage Feeding) Canuma Spec 4 (pci/kg-Wet Tissue) 40 K -

12,000 (1/2) Chattahaochee River 12,000 (1/2) 12,500 (2/2)

River Mile, 41-42 ----

(12,000-13,000) 137 Cs 100 100 (1/2) Chattahoochee River 100 (1/2) < MDC River title, 41-42 ---

Ce 100 < MDC --- ----

< tfDC Fi.h (Game) Canm.a Spec 4 (pC l /k g-We t Tissue) 40 g 2600 (2/2) Chattahoochee River 2600 (2/2) 2100 (1/2)

(2100 - 3000) River Mile, 41-42 (2 00 - 3000) ----

I Cs 100 < MDC ---- ---

• M1)C 144 Ce 100 < MDC ---- ----

200 (1/2)

Fish (Bott om Feeding) Canuna Spec 4

( pe l /k g-We t Tissue) 40 K -

1950 (2/2) Chattahoochee River 1950 (2/2) < MDC (900 - 3000) River Mile, 41-42 (900 - 3000) 4 4

s TABLE F02-9 (Cont'd)

FIS!!: RIVER - OPERATIONAL RADIOACTIVITY SUFetARY JOSEPH M. FARLEY NUCLEAR PIMr LICENSE h0. NPF-2, 110USTON COUNTY, ALABAMA January - December. 1978c Type and All Indicator Medium or Pathway Total fiumber Locations Indicator Location with !!!ghest Annual Mean Control Location Samples of Analyses liomina l Name Mean (f) Mean (f)b (Unit of Measurement) Meanff)b Performed MDCa Ranee Distance and Direction Rangeb Range b

. 137 Cs MO < MDC ---- --

< MDC 144 Ce 100 < MDC ---- ---

< MDC (a) Minimum detectable concentrations from Farley ETS Table 3.2-3 used as basta for reporting measurement data.

(b) tiean and range Famed upon detectable measurements only. Fraction of detectable meaaurements at specified locations in parenthesis (f).

(c) 14o noncout ine anomalous measuruments were repor ted during t his period.

il . ,

r TABLE F02-10 SEDit!ENT: RIVER - OPLRATIO*lAL RADIOACTIVITY SUtttARY JOSEPH M. FARLEY NUCLEAR PLAttr LICENSE t.0. NPF-2, !!OUSTON COUtTrY, ALABAMA January - December, 1978C Type and All Indicator Medium or Pathway Total Number Locations Indicator Location with liighest Annual Mean Control Location Samples of Analyses Dominal Name Mean (f) Mean (f)b (l'n i t o f 11ea s u remen t ) Performed itCa Mean{f)b Range Range D Distance and Direction Ranreb bediment (River) Ganuna Spec 4 (la 1/LK-l.r y) 40 K 480 1300 (2/2) Smith's Bend 1300 (2/2) 1350 (2/2)

(1200 - 1450) River Mile, 41-42 (1200 - 1450) (940 - 1750)

III Cs 51 < MDC ---- --- ---

Od ri 33 110 (2/2) . Smith's Bend 110 (2/2) 58 (2/2)

(78 - 140) River Mile, 41-42 (7J - 140) (31 - 65)

I Pb 62 235 (2/2) Smith's Bend 235 (2/2) 130 (2/2)

(235 - 240) River Mile, 41-42 (235 - 240) (100 - 165)

Pb 77 255 (2/2) Smith's dend 255 (2/2) 185 (2/2)

(220 - 285) River Mile, 41-42 (220 - 285) (135 - 190) 214 81 76 230 (2/2) Smith's Bend 230 (2/2) 170 (2/2)

(200 - 765) River Mile, 41-42 (200 - 265) (165 - 180) 6 Ra 540 < itDC ---- ---

< MDC 223 Ac 170 < MDC ---- --- ---

3

• W ps .

(53)

TABLE F02-10 (Cont'd)

S EDir1LNT: RIVER - OPERATIONAL RADIGACTIVITY

SUMMARY

JOSEPil M. FARLEY Nt' CLEAR PIANT LICENSE h0. NPF-2,110USTON COUt!TY. ALABAMA January - December, 1973C Type and All Indicator Medium or Pathway Total Number Locations Indicator Location with Highest Annual Mean Con.rol Location Samples of Analyses 430minal Name Mean (f) Hean (f)b Mesn{f)b (Unit of Measurement) Performed ftDCa RanPc Distance and Direction Rangeb kJ 3Re b Radiostrontium 4 09 Sr 200 < MDC ---- ---

< MDC 90 Sr 200 < ?UX' ---- --

< HDC (a) .or Gamma Spectroscopy measurements the awan minimum detectable concen- (b) Mean and range based upoa detectable measurements only. Fraction trations were calculated per equation 1 of this report using actual of detectable measurements at specified locations in parenthesis sample backgrounds (a posteriori). For radiostrontium analyses the (f).

MinC's were taken from the Farley ETS Table 3.2-3 as the basis for (c) No noncoutine anomalous measurements were reported during this report ing measurement data. period.

+.

LM Yih l