ML20113A146
ML20113A146 | |
Person / Time | |
---|---|
Site: | Farley |
Issue date: | 12/31/1981 |
From: | Clayton F ALABAMA POWER CO. |
To: | NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION II) |
References | |
NUDOCS 8504090516 | |
Download: ML20113A146 (64) | |
Text
,
.\\.
M ALABAMA POWER COMPANY ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOLOGICAL JOSEPH M. FARLEY NUCLEAR PLANT UNIT NO. 1 LICENSE NO. NPF-2 AND UNIT NO. 2 LICENSE NO. NPF-8 PERIOD ENDING DECEMBER 31, 1981 8504090516 811231
/
DR ADOCK0500g8
-,/ g s
.T$
o This annual report is submitted pursuant to Paragraph 5.6.1.a of the Environmental Technical Specifications, Appendix B, to Operating License
~No. NPF-2, and Paragraphs 6.9.1.6 and 6.9.1.7 of Technical Specifications to Operating License NPF-8.
This report summarizes the Offsite Radiological Environmental Monitoring Program for the Joseph M. Farley Nuclear Plant, Units 1 and 2, January 1, 1981 through December 31, 1981.
r
+
,s
.s s
RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT TABLE OF CONTENTS Section Title Page
-I Introduction 1
II Radiological Sampling and Analysis 1
III.
Results and Discussion 7
IV Land Use Census and Interlaboratory Comparison 11 Program
.V Data Trends and Conclusions 11 f
l e
t I
i l
r i
r i
S..
s RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF FIGURES l
Figure Title Page 1
Indicator Sampling Locations for Environmental 12 Radioactivity at the Farley Nuclear Plant (Unit No. 1) 2 Community (Indicator _II) Sampling Locations for Airborne 13 Radioactivity in.the Farley Nuclear Plant Area (Unit No. 1) 3 Control Sampling Locations for Airborne Environmental 14 Radioactivity in the Farley Nuclear Plant Area (Unit No. 1) 4 Indicator and Control Sampling Locations for Waterborne 15 Radioactivity in the Farley Nuclear Plant Area (Unit No. 1) 3.12-1 Indicator Sampling Locations for Airborne Environmental 16 -
Radioactivity at the Farley Nuclear Plant (Unit No. 2) l 3.12-2 Community (Indicator II) Sampling Locations for Airborne 17 Radioactivity in the Farley Nuclear Plant Area (Unit No. 2) 3.12-3 Control Sampling Locations for Airborne Environmental 18 Radioactivity in the Farley Nuclear Plant Area f
(Unit No. 2) 3.12-4 Indicator and Control Sampling Locations for Waterborne 19 Environmental Radioactivity in the Farley Nuclear Plant (Unit No. 2) t 11
s "n
4 RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT LIST OF TABLES Table Title Page 1
Scope of Operational Radiological Environmental 20 Monitoring Program at.the Farley Nuclear Plant 2
. Outline of Operational Radiological Environmental 22 Monitoring Program for Farley Unit'No. 1 3
Outline of Operational Radiological Environmental 27 M nitoring Program for Farley Unit No. 2 o
4 Detection Capabilities for Environmental Sample 31 Analysis.for Farley Unit No. 1' 5
Detection Capabilities for Environmental Sample 33 Analysis for Farley Unit No. 2 6
Sampling and Analysis Deviations During 1981 34 i
1 F05-1 Airborne: Particulates and Iodine -. Operational-36 Radioactivity Summary-F05-2 External Radiation - Operational Summary 38 F05-3 Milk - Operational Radioactivity Summary 39 F05-4 Vegetation: Forage,-Vegetables and Fruits -
40 Operational Radioactivity Summary F05-5 Soil - Operational Radioactivity Stummary 46 F05-6 Waterborne: Surface and Ground Water --Operational 47 Radioactivity Summary i
F05-7 Vegetation: Aquatic
.0perational' Radioactivity 48 Summary F05-8 Benthos: Clams - Operational Radioactivity Summary 50 F05-9 Fish: River. Operational Radioactivity Summary 51 F05-10 Sediment: River Operational' Radioactivity Summary 53 f
111 i
.4--w r,e
. ~
r---m,
---w
, = - -
-mw-e 4
g -.
i RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT
. LIST OF ATTACHNENTS Pjipe Attachment Title j
1 Land Use Survey for Radiological Environmental 54 Monitoring Program, Farley Nuclear Plant, June 1-5,-1981
-2 Milk Animal Survey for Farley Nuclear Plant 56 Radiblogical Environmental Monitoring Program, December 22-23, 1981 4
e
.4.
f y
iv 4
- g 7
+
g-Y c,.
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT 7
UNITS 1 AND 2
.I.
Introduction The Joseph M.LFarley 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 860 megawatts electrical (MWe) achieved initial criticality on' August 9, 1977. The unit was declared " commercial" on December 1 1977. Unit No. 2, also a 860 MWe Westinghouse PWR, achieved' initial criticality on May 8, 1981 and was declared." commercial" on July 30, 1981.
d During 1981, Unit No.1 was shut down for a scheduled refueling outage from January 1 to _ March 24. On September 10, Unit No.1 was shut down, for an '
unscheduled outage, due.to an electric generator failure and remained sh~t down u
through December.31, 1981.
The-sample collection and analysis schedule for the operational off-site radiological environmental monitoring program implemented in May,1977 and as modified on July 1, 1980 with the addition of 14:TLD stations was continued during 1981 for both-Units No. 1 and 2.
This_programLwas designed to monitor any radioactivity contribution-to the environs-from the plant 1through either the airborne' or waterborne pathways.' The type of samples monitored, and number and_ type.of sampling 1 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 11evels might be made with l
measured levels. The. control stations were placed at; locations where radiological, levels were not expected to be'significantly_ influenced by plant operation, i.e.,
at background locations.- - For some airborneiradioactivity = samples, community stations were located at the' principal 1 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 j
release of radioactivity from the plant, f
.II.' Radiological Sampling-and Analysis A' detailed outline of1the operational radiological _ sampling and analysis activities for the off-site environmental; program to meet the requirements of
- the Unit :No. lLEnvironmental Technical Specifications istgiven 'in Table 2.-
The corresponding sampling and analysis. requirements for the Unit No. 2 Technical 4
l
-Specifications _aregivenin; Table 3.1{Wherethesamesamplingand. analysis j
requirements are specified only one sample was collected and one analysis performed.to. meet the specifications for both Units No. 1 and 2.
..u----,
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL PROGRAM JOSEPH M. FARLEY NUCLEAR PLANT UNITS 1 AND 2 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 860 megawatts electrical (MWe) achieved initial.
I criticality on August 9, 1977. The unit was declared " commercial".on December 1, 1977. Unit No. 2, also'a'860 MWe Westinghouse PWR, achieved initial criticality i'
on-May 8,1981 and was declared " commercial" on July 30,-1981.
1'
. During 1981, Unit No. I was shut down for a scheduled refueling outage
. from January 1 to March 24. On September 10, Unit.No. ~ 1 was' shut down, for an' i
unscheduled outage, due to an electric. generator failure and remained shut down through December 31, 1981.
The sample collection and analysis schedule for the operational off-site radiologica1' environmental monitoring program implemented in May, 1977 and as modifiedLon July 1, 1980 with the addition of 14 TLD stations was continued during 1981 for both Units No. 1 and 2.
This program was designed to monitor any radioactivity' contribution to the environs from the plant through either
!~
the-airbornesor waterborne pathways. The type of samples 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-j measured levels..The control stations were placedlat locations where~ radiological levels were not expected to'be significantly influenced by plant' operation, i.e.,
i Lat 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 controlcatations, 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 to meet'the requirements of the Unit'No.-1 Environmental Technical Specifications is given in Table 2.
The corresponding; sampling and analysis requirements for the Unit No. 2 Technical Specifications are given in' Table 3.
Where the same sampling and analysis requirements:are specified only one sample was collected.an'd one analysis performed to meet the, specifications ~for both Units No.-1 and 2.
7 4.
~
l
+
V '-
A-
,m
,; 4.
~
~
- o -
- t (2)
The samples 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.)
.cr the Eberline-Instrument Corporation (EIC) Santa Fe Facility. The minimum j
detectable concentration (MDC), specified for the various samples and their respective analyses are given in Table 4 for Unit No. 1 and Table 5 for Unit No. 2.
apling problems and/or deviations'from the sampling schedule were encountered during 1981. These are-listed in Table 6.
Aside from the
. usual occasional air sampling' station pump problems and non-availability of forage' at the prepared plots during the winter months the major _ deviation was
..the failure to make igt situ Ge(L1) gamma-ray; spectroscopy measurements in the-
. Fall of 1981. Repeated attempts by Princeton Gamma-Tech to repair the University i
of Georgia in situ. Ge(Li) detector failed,'thus resulting in the ultimate decision to scrap.the detector and purchase a new intrinsic Ge(Li) detector.
~
A. -A1 6 Particulates and Iodine-All'of the airborne particulates and iodine monitoring stations shown in Figures 1, 2, 3, 3.12-1, and 3.12-3 were equipped with Bell and Gossett vacuum pumps which operate continuously at a flow rate of about 0.04/m3/ min 3
(1.5 ft / 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 j
collection of iodine. The latter were mounted horizontally to the' ground
-to insure uniform airflow through the filter. The accumulative air flows were measured with Rockwell 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.
4 Gross beta radioactivity m?asurements were made on each air particulate L.
filter using a Beckman Lowbeta II low background proportional-counter, j-The filters from each station were composited and at the end of each
~
quarter were analyzed for gamma emitters using an eighteen percent relative c
efficiency low backgr'ound Ge(Li) detector and a Canberra 4096 channel b
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.
~ he. single separation, T
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, 2, 3,
' 3.12-1, Land 3.12-3 have the capability of. monitoring ' airborne. iodine.
However,[ weekly routine samples.were. collected only:at the stations listed i
in Table 2.
These.were analyzed'for iodine-131 by U. Ga. using a Canberra
'1024.' channel MCA'and a special counter designed and built.by U. Ga. for counting iodine-131 activity'in charcoal cartridges, using two 1 x 3 NaI(Tl)' detectors and matched photomultiplier. tubes.
F P
f 4
~
9 (3)
.s B.
External Radiation j
For the continuous measurement of environmental gamma radiation, natural LiF (TLD-100) chips were supplied and read by Eberline Instrument Corporation. 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 2
radiation (approximately 50 mg/cm ),
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 after 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. 1 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, 2, 3, 3.12-1, 3.12-2, and 3.12-3, two TLD packets, one changed and read quarterly and one changes and read annually, were exposed side-by-side on metal 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 location shown in Figures 3 and 3.12-3 and were analyzed by U. Ga. 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 percent (by weight) merthiolate (Thimerasol) solution and 4 ml of a 6N NaOH solution were added to each 2.5 gallon sample.
The iodine-131 concentration in each sample was determined by collection on anion exchange resin, elution with sodium hypochlorite, followed by organic extraction and counting by beta-gamma coincidence the resultant toluene-iodine solution in a'special design (UGA) low level liquid scintillation counter. Stable iodine carrier was added to each sample for determination of the radiochemical yield.
Once each month a 1 liter sample was placed in a marinelli beaker and was then analyzed for gamma emitters using an 18 per cent relative efficiency low background Ge(Li) detector and a Canberra 4096 channel computer based MCA.
~
9
t w
(4)~
J
/
Also,'once each month for each sampling station, a 1.5 liter aliquot of milk was taken for radiostrontium analysis. Following an EDIA separation of calcium, the single separation dual count technique, using a Beckman Lowbeta II background proportional counter. was used for beta measurements.
~Following th~e second count, the in-growth of yttrium-90 was determined and stable strontium carrier was added for determination of radiochemical yield.
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 4
site perimeter in sectors 7 (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 an 18 per cent relative efficiency low. background Ge(Li) detector and a Canberra 4096 channel computer based MCA.
2.
Vegetables and Fruits a.
Green leafy vegetables During the growing season. 0ctober 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. Ca. for gamma emitters using an 18 per cent relative efficiency low background Ge(L1) detector, and a Canberra i-4096 channel computer-based MCA.
I b.
Other Vegetables and Fruits i
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 the samples
.from gardens in the Dothan area (>10 miles). The edible portions of these samples were prepared and analyzed for gamma emitters by U. Ga. using an 18 per. cent. relative efficiency low background Ge(Li) detector'and a Canberra 4096 channel. computer-based MCA.
E.
Soil Semi-annual in situ gamma-ray spectroscopy measurements were made.
by U. Ga. using a 14 per cent relative efficiency Ge(Li) detector and gamma-ray spectroscopy system specially designed for field use, at the-l 9 indicator locations shown.in Figure 1 and at the 6 community and control (background) locations shown.in Figures 2 and 3.
A 1024 channel Canberra MCA was interfaced to a Hewlett-Packard 9825A calculator for data storage-
[
and analysis, i
4
,--.4
= _
- o.
(5)
.=#
l F.
Surface Water (River).
l~
Samples of~ water from the Chattahoochee River, above and below the plant site at the locations shown in Figures 4 and 3.12-4, were collected
.on a semi-continuous basis with Instrumentation Specialties Company (ISCO)
F samplers. Monthly composites were sent to U. Ga. for radioactivity i-analysis. Two. 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'an 18 per cent relative efficiency Ge(Li) low back-4 ground detector and a Canberra 4096 channel computer-based MCA.
t At the end of each quarter, for each sampling location,-the balance of the three monthly. composites were combined to give a quarterly composite sample. Approximately 50 ml 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 t
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 locations shown-in Figures 4 and 3.12-4, and were sent to U. Ga. for radioactivity.
analysis.. A portion of each sample was taken, dried, pulverized. and analyzed for gamma-emitters using an 18 per cent relative efficiency' low background Ge(Li) detector and 4096 channel Canberra computer-based MCA.
The remainder of each sample was dried, ashed, acidified and converted to strontium carbonate for strontium-89, 90 analysis. The single separation j.
dual count technique, using a Beckman Lowbeta II low background proportional counter was used. This was followed by a second count.to determine the in-grown yttrium-90. Stable strontium carrier was added~for determination l
of the radio-chemical yield.
j.
'H.
Benthos (Clams) i Samples of clams were collected-from the Chattahoochee River above t
l and below'the plant. site on a semi-annual schedule at locations shown in t
Figure 4 and were sent to U. Ga.'for radioactivity analysis. The tissue was separated from the shells, dried and pulverized for analysis of' gamma-emitters using an 18 per cent relative efficiency low, background Ge(Li)L detector and 4096 channel Canberra computer-based 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 Lowbeta II low background proportional counter was'used. This was followed by a second count'to determine the in-grown yttrium-90.
Stable strontium carrier was
~
added for determination of the radiochemical yield.
r e
,,_,.,~-r,
~-~--,m.--
w---..
....,---wn-.
(6)
- r 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 Figures 4 and 3.12-4, and were sent to U. Ga. for gamma-ray cpectroscopy analysis. The edible tissue was removed, dried, pulverized and analyzed for gamma emitters using an 18 per cent relative efficiency low background Ge(Li) detector and a 4096 channel Canberra computer-based MCA.
J.
Sediment (River)
On a semi-annual basis sediment samples were collected from the Chattahoochee River above and below the plant site at the locations shown in. Figures 4 and 3.12-4.
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'an 18 per. cent relative efficiency low background Ge(Li) detector and a Canberra 4096 channel computer-based MCA.
After completion of the gamma-ray spectroscopy analysis, a 25 g sample from each location was used 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 strontium-90 content determined using the single separation dual count technique. The beta activity was measured with a Beckman 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 are 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, located on the east bank of the Chattahoochee River about four miles south-southeast of the plant, was sampled on a quarterly basis and designated as an indicator station. A deep well which supplies water to the Whatley Residence located about 1.2 miles southwest of the center of the' plant was sampled on a quarterly basis and designated as a control (background) station. ' Samples from both were-sent to U. Ga. for radioactivity analysis.- An aliquot from each sample was taken for tritium analysis. After distillation, 25 m1 samples were analyzed using a large volume (100 ml) low background liquid scintilla-tion counter specially designed and built by U. Ga. From the remainder of each sample, a.two liter aliquot was taken and evaporated to dryness at 100'C in a tray lined with plastic film. The residue and film was folded to' fit a petri dish and analyzed for gamma emitters using an 18 relative per cent Ge(Li) detector and a Canberra 4096 channel computer-based MCA.
1
+.
12 (7) 5 III.
Results and Discussion During the operational period no known atmospheric nuclear tests were conducted. However. measurable levels of radioactivity.from the test conducted by the Peoples Republic of_ China on October 16, 1980 were found in several
-sample media throughout the spring and summer. By the end of 1981 the airborne radioactivity levels in all samples had shown a substantial decrease.
For measurements involving radioactivity concentrations by volume or mass the' designation " minimum-detectable concentration" (MDC) is used to denote the t'
limit of detection applicable at the 95 per cent confidence level. The MDC-is defined as "the smallest concentration-of radioactive material in a sample that will be detected with 95 per. cent probability with only 5 per cent' probability of falsely concluding-its presence". For a particular measurement, which may include radiochemical separation:
4.66 Sb MDC = 2.22 EMY (1).
'where i
[
MDC:is'the estimated minimum detectable concentration as defined above (pCi per unit mass or volume) i 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) l' For measurements-involving a quantity of radioactivity or radiation that i
is independent of the sample volume or mass the designation " lower limit of I
detection"~(LLD)'is used to' denote'the limit of detection applicable at the 95 per cent confidence level..The LLD is' defined as "the smallest amount of l
sample activity' that will' yield a net count for which there'is confidence at a predetermined level that activity is present".
It's applications are limited
~
to measurement systems which denote a limiting detection capability without respect to the size of sample and/or radiochemical yield and.to measurements which by their nature do not involve concentrations, such as radiation dose rates-(arad/hr., mrad /qtr., etc.)
i A.
. Airborne Particulates and Iodine
-The results of the radioactivity analyses of airborne particulate filters and' iodine charcoal cartridges are shown in Table F05-1.
The mean gross beta activity values were slightly higher for the indicator than for.
community and control sampling locations,.but is not considered significant.
Also, allLlocations including-the control locations have slightly higher
' average. values;than for the preoperational period =and are about four times higher than the' respective 1980' values.
i
'.o l
l l
1 l
(8)
The gamma-ray spectroscopy data for the air particulate filter composites showed the presence of fission product fallout from the
~
October 1980 Chinese nuclear test during the first, second and third quarters of 1981. The activities found were generally about the same level as found during the preoperational period which included several Chinese atmospheric ~ nuclear tests. Although they were higher than found j
in 1980 there were no significant differences between the indicator, community'and control locations.
Strontium-89 and strontium-90 were found in most of the indicator, community, and. control!1ocation samples. The average strontium-89 values were somewhat higher'than the respective 1980 values and were slightly higher than the preoperational values. The average strontium-90 values were not significantly different from the 1980 and preoperational values. For both strontium-89 and strontium-90 the average values for
-the community and control stations were slightly higher than for the indicator values. Alliodine-131 values were below the measurement MDC as was found in 1980 and during the preoperational period.
- B.
External Radiation The results of the' external ~ radiation measurements using TLD packets, each containing five LiF chips,.are shown in Table F05-2. As found during the preoperational measurement period and during 1980, the data reflects j
the differences in site specific soil radioactivity, with the average indicator values higher than for the community and control values. All
- the averages were lower than found in 1980 but.were' higher than found '
during the preoperational period. Although, the sums for the four 3
quarterly measurements were higher than-the averages for the annual TLD's the difference was less than in 1980. During the preoperational period that average values for the annual TLD's was slightly higher than the respective sums of the four quarterly measurements which is the reverse of that found in 1981.
}
C.
. Milk
~ The results from the analysis of milk for radioactivity'are shown in Table F05-3.
Milk from the Brooks-Silcox Dairy was sampled as
.the control. No indicator milk locations were available for comparison during 1981. Other-than natural radioactivity and a very low level of
' cesium-137 in one sample only' strontium-89 and strontium-90 were found
.at detectable levels. The average strontium-89 value was slightly higher than found during the preoperational period but the strontium-90 value was a factor of two lower. During 1980 only strontium-90 was found for which'the average value was slightly lower..
2
-D.--Vegetation The vegetation sampled during'this operational period' included i
. forage, green leafy vegetables and food crops grown in the area. The radioactivity analysis results for this operational period are'shown in Table F05-4.-
[
i i
I I
.h (9) l' a
g.1 p
[
Forage, as during the preoperational period, continued to be-l
-a'very effective and sensitive indicator of airborne radioactivity.
The specific' activity. values for the various gamma emitting radio-nuclides 1-were not significantly different-for the indicator locations and the control location.. Fission product radioactivities from the October 1980 Chinese nuclear test were seen at declining levels from January to November
~
{
1981.1
-As_noted during the preoperational period, the vegetables and j'
' fruits sampled during the summer were poor indicators of. airborne radio-i activity..However, fission product radioactivity was found on green l
1eafy vegetables at a: higher. level for the control than for the indicator j
location. Also, fission product radioactivity at levels near the MDC's was found in several indicator and control vegetable and fruit samples, which are comparable with the preioerational period. During 1980 only cesium-137 was found in green leafy vegetables, j
E.
Soil j;
.The results of the one in situ Ge(Li): gamma-ray spectroscopy-analysis of soil during this operational period are shown in Table F05-5.n
-During the measurement in the spring of 1981, the fission products _.
l I
zirconium,-niobium-95and' cesium-134wereseenatmostofthe' location in addition to cesium-137 that has always been found in measurable
/;
quantities in the soil. No:significant differences were found between j_
(
-the indicator, community and control' locations.- The' average values fo zirconium niobium-95 were generally higher than those for the pre- {
operational period, but the difference is not considered significant.l The levels of cesium-137 were about the same as for.the 1980 and pre-operational' periods.
F.
Waterborne:- Surface and Ground Water l
The results of radioactivity analyses of surface. water from the.
Chattachoochee Rivny and ground' water from wells are shown,in Table'F05-6.
In a few surface Wter samples very low levels of fission product '
/
4
)
radioactivity' vere seen, but are too close to the MDC to be considered significant. The average tritium levels for the surface water indicator I i
l location downstream of the plant was about a factor of two higher than the average for the upstream control location. Again because of:the low levels the differenceLis not. considered significant since the average values ~are only slightly higher than those found in 1980 and during the preoperational period.
Again as in-1980, no detectable gamma. radioactivity was found L
'in the around' water samples. However, two of the indicator samples from aother Great Southern Paper Company Well~ indicated tritium at an average-level only slightly lower than that for the surface water from the river.
Tritium-was also'found-in one. sample.from the.well during 19d0 and in one sample during the preoperational period.
L L
,-.m.,
4.
., - -, - - - -, ~. _.,
Q (10)
G.
Aquatic Vegetation (River)
The results of the radioactivity analysis of aquatic vegetation from the Chattahoochee River are shown in F05-7.
The influence of the 1980 Chinese nuclear test on fission product radioactivities was found at both the indictfor and control locations. The levels were quite low and are not consi ' red significant. Cesium-137 was found in all the 1980 samples at comparuole levels and in some preoperational samples at higher levels.
Strontium-89 was found in one of the indicator samples but not in the control samples. Whereas, strontium-90 was found in all both control samples but in only one indicator sample. During the preoperational period strontium-89 was found in one indicator and one control sample, whereas strontium-90 was found in most of the samples at much higher average values.
H.
Benthos: Clams The results of the radioactivity analysis of tissue from Chattahoochee River clams are shown in Table F05-8.
As shown in the table the only manmade radioactivity is niobium-95 at very near the MDC in one indicator sample. During 1980 cesium-134 was found in one sample and during the preoperational period low levels of both strontium-89 and strontium-90 were found most of the samples.
I.
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 F05-9.
For the first time manmade radioactivity other than cesium-137, which was found in 1980 and during the preoperational period, was found in fish.
Zirconium-95 and niobium-95 were found in both forage feeding and bottom feeding species of fish. For the forage feeding fish they were both found in one of the indicator samples, whereas, for bottom feeding fish niobium-95 was found in one indicator sample and zirconium-95 in one control sample. The levels in all samples were quite low and no significance is placed on the values other than the movement of radioactivity in the environment from the atrborne to waterborne media.
J.
Sediment: River The results of radioactivity analysis of sediment samples from the Chattahoochee River are shown in Table F05-10. Manmade radioactivity was not found at detectable levels during 1980 and during the preoperational period. However, in 1981 niobium-95 was found in one and cesium-137 in both control samples. No detectable manmade radioactivity was found in the indicator samples.
Strontium-90 was also found in one of the c ntrol samples.
(11)
K.
Sampling and Analysis Deviations T
l With the implementation of the Unit 1 Technical Specifications upgrade I
gfg (Amendment No. 26, issued March 1, 1982) all sampling and analysis deviations
-l indicated on Table 6 that were found to be not in accord with the upgraded Unit 1 and.the Unit-2 Technical Specifications have been corrected, or are in p being corrected as of date of this report (April 1, 1982).
/
IV.
Land Use Census and Interlaboratory Comparison Program A.
Land Use Census The results of the June 1981 Land Use Census are given in Attachment 1.
.Likewise the results of the December 1981 Milk Animal Survey (Specification of Unit 1 ETS) are given in Attachment 2.
B.
Interlaboratory Comparison Program
, The University of Georgia Center for Applied Isotope Studies was a participant in.the EPA Crosscheck Program. The U. Ga. EPA Program code designation is EA.-
V.
Data Trends and Conclusion Review of the analysis data against 1980 and preoperational revealed no trends indicating changes in radioactivity levels in the environs of the Farley Nuclear Plant as the result ~of its operation. This is supported by the low levels of radioactivity measured in plant effluents discharged to the environment, as reported in the semi-annual radioactive effluent release reports for 1981.
Based on information supplied in,this report there is no significant evidence to indicate any increase in airborne or waterborne environmental radioactivity as the result of plant operations.
I
.I i
--c n
,n
,g.
(12)
L iI
--D-
'".2'." g-
- g-16 73 75 m 1
N IT-W W d
llS
)
NNW NNEi gjg, g, g, gg6 3
[
SEC/ M
,.... /*
f 14 p
2 h
(,.
NW NE t.
i g
+
-_s WNWI ENE J'e. u..-
m..,
1 N -N V
l 12 d
4 W
u. m I-E une =
x r
'm %
eg=g,W
~
k E!E I"
E"7
' ~
/
@(
p*S*
t;.
' d.
(. l.......
,q\\
\\
"s"=""
SE q
'-)
2." *". *"'
4-7 g
8 SSE A
~~i 1.)
<?.~.
uu 4 FORAGE SAMPLING A TLD 8 SOIL SAMPLING A TLD SAMPLING,
l
@ TLD. SOIL, PARTICULATES & IODINE SAMPLING i
stat e FECT FIGURE 1. INDICATOR SAMPLING LOCATIONS FOR ENVIRONMENTAL RADIO ACTIVITY AT THE FARLEY NUCLE AR PLANT.
(Unit No.1)
(13)
\\l6 sLAKcLV N
/
IS 01 NNW NNE 14 02 NW NE c0 usia i
HILTON is 03 WNW ENE es A
I
~
evC'tgaI
)
Ng CEDAR SPRisees ll ASHFORO 05 WSW ESE GCRDON d,\\
10 04 SW SE JAKIN 09 07 SSW SSE 08' S
- ne e
e a
e e
a TLD SAuPL No scaLEN esetts g Jgo,Q'y,'jg,A,7,ts, soil &
0 FIGURE 2.
COMMUNITY (INDICATOR 21:1 SAfJ9 LING LOCATIONS FOR AIRBORNE R ADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA.
(Unit No.1)
+
e I
pgTI.WF5 t
Ones p
unne sabe - nonass
,.e
{
~***.**,/
(A)N#8. B.O. Io*
I to! w.e.. a..o so' o
ic
..o. w 1
s I
1 s.
l s
g
.lLQ..
i.
\\T h
N..-
1 j
j I
==== ensw..
1 is
/
3 wese ENE i-
.]
\\
q
~
If
- ), -
gi 4
s' i
4 g
1 ;f.
, ',i
-.l
./.
.1
=
i
=
as l
=
SE j
{
N.,..-
1 e
T
..1
}f e
asE s
.s.
....;;)
_ ::lE
............ ' g
_j m-k 1
A
,0. A.E.A..
TLo SAasrLIIu.
FIGURE 3.
CONTRot sauPLesse LOCAfsoest FOR A
soil &
ainsonut taveronastasTAL maceoAcTevity g Tgp, paniscutATES,
o I'#"*
IN THE FARLEY nucle AR PLANT AREA.
e us a saa n :=s (Unit No. 1)
(15)
N COLUMBIA
)
i j
ANDREWS LOCK & DAM lFARLEY to MILES
[ en ' #
EARLY COUNTY
- ]
% pv GEORGIA
{
l 2
- 5 7.A 5
k 4
HOUSTON COUNTY 4
ALABAMA INDICATORS STATIONS CONTROL STATIONS S FISH AND SEDIMENT SURFACE WATER AND FISH E SURFACE AND GROUND WATER BENTHOS AND VEGETATION E BENTHOS AND VEGETATION (WHERE AVAILABLE-ABOVE (WHERE AVAILABLE-8ELOW ANDREWS LOCK & DAM)
PLANT DISCHARGE)
@ GROUND WATER FIGURE 4.
INDICATOR AND CONTROL SAMPLING LOCATIONS FOR WATERBORNE ENVIRONMENTAL RADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA. (UnitNO. 1)
(16)
L iI
- ?**.t*!T
- 8 e --
3-16 71-75 VAKE l
N IT-NORMALg
)
kl5
/
8 NNW NNE X/Q = l.016 3
J SEC/ M
,.../.
1 L) 2 NW NE i
I '.
v E
~.
- i
~%
a ENE L
WNW peu va.
v f
i g'/
4 1
w
' 22 f'C E
f
"' ***/
im N 8
b
~
2;%
k E!E N'"
1[
wsw
(___,
l-I s[s, so g ('~~S W
.,/.
a se 4
]gt~*C'",.
r
\\-)~./
C'"J::""
e--
7 S!w 8
SSE A
l l.)
')
i m
u._
A. A-4 FOR AGE SAMPLING A TLD SAMPLING
@ TLD. PARTICULATES 8 IODINE SAMPLING NO O 900 em SCALL Inn 9iL1 FIGURE 3.12-1 INDICATOR SAMPLING LOC ATIONS FOR AIRBORNE ENVIRONMENTAL RADIO ACTIVITY AT THE FARLEY NUCLE AR PL Ar.T. (Unit No. 2) l
O (17) e
\\ls eLaurLv 01 15 NNW NNE 14 cct mesa i
HILTON 83 03 WNW ENE (I
e6 12
- Yv'EsaI EEP h
~ g N
CtoaR s
4 r
))
ASHPORO 05 so E3E WSW
~
a k
GORoon
\\
e^
=
II SSE 08' S
- ve e s
a
, 7L,
,A,,L,,,e SCALE in estas FIGURE 3.12-2 COMMUNITY UN0tCATOR E SAMPUNG LOCATIONS FOR AIR 80RNE RADICACTIVITY IN THE FARLEY NUCLEAR PLANT AREA.
(Unit No. 2) l i
i
e 1
9973-1975
^
Ouse
[
uses ashi - saw=es (Al X/O e I.O. 10'
/
(9) X/Go 2.0. t
/
..j f (C) X/0 = s.O e
.w 7
I w
j' V
l 1
e is t
- e..
N ll.
-~
NME t
s i
14 2
fee
/
OT b
13
=
g,E 1
i N -l
\\-- E A
S E
w
- . \\
4 h
i o
it -
i w
T
~
J
\\
I f
/
j Il.
.=
1 WSW *.*.
W s
l E8C i.
H
.*m 5
SE unaw -.
~
I.
""""'7
. s!W 7
i SsE t..
0 S
- =
E
_m a & a e 66 t....
-/
6*
C0 v
t e FORASE sAMPLINe seats = tes FIGURE 3.12-3 cos: Trot sAuPLING Locations FOR A TLD SAesPLisee TLD PARTscuLATES Af00 I
AIRBORNE ENVIRONMENTAL RADICACTavtTV g
01 E SAWNNS IN THE FARLEY NUCLE AR PLANT AREA.
e uita sAmetiNo (Unit No. 2)
(19)
J COLUMBIA sa i
sa 5
ANDREWS LOCK & DAM FARLEY j
'l0 MILES lE
[
EARLY COUNTY
- @ g%
l GEORGIA l
h ASHFORD I
f in I
"5
!l Q
GORDON*
^
HOUSTON COUNTY 1
ALABAMA e,
s INDICATOR STATIONS CONTROL STATIONS E
SURFACE AND GROUND WATER SURFACE WATER AND FISH E
FISH AND SEDIMENT GROUND WATER FIGURE 3.12-4 INDICATOR AND CONTROL SAMPLING LO, CATIONS FOR WATERBORNE ENVIRONMENTAL RADIOACTIVITY IN THE FARLEY NUCLEAR PLANT AREA.
(UnitNo.2)
1
- s; (20);
TABLE 1 1.
SCOPE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL' MONITORING PROGRAM AT THE FARLEY NUCLEAR PLANT l1 Principal'
. Type of-Minimum Number of Sampling Stations
- Pathway Samples Indicator Community
-Control 4'
Airborne Particulates 4
3 3
t..
Airborne Iodine 3
1 1
' External Radiation 16' 16' 5
Airborne-1 Milk 1
^
C 1
Forage 2
1 Vegetables and Fruits l'
d Soil 9
3 3
t J
1 River' Water 1
i 1
River Vegetation 1
1 River Benthos 1
l Waterborne 1
River Fish 1
River Sediment 1-
~
l i
1-Groundwater 1
" Additional stations may be added at discretion of~ licensee above the minimum commit-ment'shown.
j bIf available.
I
" Forage sampling in' lieu of meat and poultry sampling.
Semi-Annual _In, Situ Gamma Measurements.
[
" Fourteen additional.l sampling stations-added July-1, 1980'at a distance of approxi-mately 4-5 miles.
I
,-.s
TABLE 2.
OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FARLEY UNIT NO. 1 Types of Samples and Sampling' Type and Frequency Sampling Locations and of (Distances Given in Miles)
Collection Frequency
~ Analysis AIRBORNE Continuous sampler operation Gross' Beta - Weekly after with sample collection weekly filter change..
Particulates.
or as required by dust loading of filters, whichever is more.
Gamma Isotopic - Quarterly
-Indicator Stations:
frequent.
composite (by location) and for any single filter North Perimeter (N-0.8) having gross beta activity River Intake Structure (ESE-0.8) that is greater than 10 South Perimeter (SSE-1.0) times the mean of the Plant. Entrance - Mearest Residence control samples.
(WSE-0.9)
Strontium-89, 90 Analyses Community Stations:
Quarterly composite (by location).
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)
Iodine t
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 (WSE)-0.9 n
v
TABLE 2 (CONT'D)
Types of Samples and Sampling Type and Frequency Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis Community Stations:
Great Southern Paper Co., Ga. (SSE-3)
Background Stations:
Dothan, Ala. (W-18)
External Radiation Indicator Stations:
Each measurement location has Read Gamma doses quarterly dosimeters (TLD's) side-by-side, and annually.
Sixteen stations, one in each meteorolog-one collected quarterly and one ical sector, along the plant perimeter.
collected annually.
Each (N-0.8, NNE-0.9. NE-1.0, ENE-3.9, E-0.8, dosimeter contains five ESE-0.8, SE-1.1, SSE-1.0, S-1.0, SSW-1.0, individual TLD chips.
SW-0.9, WSW-0.9, W-0.8. WNW-0.8, NW-1.1, (Quarterly TLD packets only were and NNW-0.9) located at the 14 community stations added on July 1, 1980).
Community Stations:
Columbia, Ala. (N-5)
Great Southern Paper Co., Ca. (SSE-3)
Ashford, Ala. (WSW-8)
Fourteen stations, one in each meteorolog-ical sector, except for first two above, at a distance of 4-5 miles (NNE-4, NE-4 ENE 's, E-5, ESE-5. SE-5, S-5, SSW-4, SW-5, WSE-4, W-4, WNW-4, NW-4, and NNW-4).
O
~
~. -
TABLE 2 (CONT'D)
N I*"
iTypes of Samples and
. Sampling Type and Frequency.'
Sampling Locations and
'of
-(Distances Given in Miles)
Collection Frequency-Analysis Control: Stations:
Blakely, Ga.-(NE-15)
Georgia Rt. 39-(ENE-15)
Neals Landing, Fla.'(SSE-18)
Ala. Rt. 52 (WSW-26)
-Dothan, Ala. (W-18).
Soil 4
4 Indicator Stations:
Semi-ar.nual in situ Ge(Li) gamma-- Gamuna Isotopic - Semi-ray spectroscopy measurements.
annually.
Nine stations along the plant perimeter.
(N-0.8, NE-1.0, E-0.8, ESE-0.8, SSE-1.0, 6
S-1.0, SW-0.9.WSW-0.9 and NNW-0.8 Community Stations:
Columbia Ala.~(N-5) i Great' Southern Paper Co...Ga.~(SSE-3)
- Ashford, Ala.: (WSW-8)
Control Stations:
i (NE-15)
Blakely, Ga.
Neals Landing.: Fla. (SSE-18)
.Dothan, Ala. (W-18) i Milk 1
.n N
Indicator Stations:
Semi-Monthly Camma Isotopic-Monthly 8
i.
Not Available Strontium 89, 90 Analyses l
Monthly Radioiodine analysis -
Semi-Monthly, when animals ~
i are on pasture
TABLE 2 (CONT'D)
Types of Samples and Sampling Type and Frequency '
Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis Control Station:
Brooks-Silcox Dairy, Ashford, Ala. (WSW-10)
Forage 4
Indicator Stations:
Grab Sample Monthly (when Gamma Isotopic-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) i Vegetables and Fruits Grab sample at harvest, except-Gamma Isotopic-Edible monthly for green leafy vege-Indicator Station:
tables during growing season..
Radiciodine-Monthly on (Principal food crops' grown in green leafy vegetables Plant Vicinty (SW-1, W-1, NNW-2, or NNW-3) plant vicinity).
during growing season.
Control Station:
Dothan Area (W-lO+, WSW-10+, WNW-lO+)
WATERBORNE River Water Composite taken with propor-Gamma Isotopic - Monthly tional semi-continuous sampler, Indicator Station:
having a minimum sampling Tritium - Quarterly frequency of once each hour.
Composite 3
Great Southern Paper Co.,
(3 miles below plant discharge)
Strontium-89, 90 -Quarterly.
Composite Control Station:
O D
Upstream of Andrews Lock and Dam (N3 miles above plant intake) r
TABLE 2 (CONT'D)
Types of Samples and Sampling Type and Frequency' Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis Ground Water Grab sample taken quarterly.
Gamma Isotopic - Quarterly Indicator Station:
Tritium - Quarterly Great Southern Paper Co., Well (SSE-4)
Control Station:
Whatley Residence Well (SW-1)
Aquatic Vegetation Grab sample taken semi-Gamma Isotopic - Semi-annually.
annually.
Indicator Station:
Strontium-89, 90 - Semi-Downstream of plant discharge at first annually.
available location.
Control Station:
Upstream of Andrews Lock and Dam River Fish Grab sample taken semi-Gamma Isotopic - Edible annually.
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 G$
' +-
TABLE 2 (CONT'D) 1 -
Types of Samples and --
Sampling Type and Frequency; Sampling Locations.
and of (Distances Given in Miles)
Collection Frequency Analysis River Benthos Grab sample taken semi-annually Gamma Isotopic --Semi-(Clams) annually (Tissue)
Indicator Station:
Strontium-89, 90 - Semi-Downstream of Plant discharge at'first..
annually.(Tissue) available location Control Station:
Upstream of.Andrews Lock and Dan River Sediment Grab sample taken semi-annually Ga-am Isotopic - Semi-annually.
Indicator Station:
Strontium Semi-Downstream of Plant discharges at Smith's
-annually-
' Bend (~2 miles)
Control Station:
Upstream of.Andrews Lock and Dam 1
fh a
l a
w
TABLE 3 s.
OUTLINE OF OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM FOR FARLEY UNIT NO. 2 Types of Samples and
. Sampling Type and Frequency.
Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis AIRBORNE Continuous operation of sampler Particulate sampler.
with sample-collection as Particulates required by dust loading ifut at Analyze for gross beta least once per 7 days.
radioactivity > 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> Indicator Stations:
following filcer change.
Perform gamm isotopic North Perimeter (N-0.8) analysis'on each sample Plant Entrance - Nearest Residence (WSE-0.9)
, when gross beta activity-South Perimeter (SSE-1.0) is > 10 times the yearly mean of control samples.
Control Stations:
Perform gamma isotopic analysis on composite Blakely, Ga. (NE-15)
(by location) sample at Dothan, Ala. (W-18) least once per 92 days.
Iodine Continuous Sampler operation Radioiodine canister.
with charcoal canister Analyze at least once Indicator Stations:
collection weekly.
per 7 days for.1-131.
North Perimeter (N-0.8)
South Perimeter (SSE-1.0)
Plant Entrance - Nearest 4
Residence (WSW)-0.9 Control Stations:
Blakely, Ga. (NE-15)
Dothan, Ala. (W-18) 4 n
TABLE 3 (CONT'D)
Types'of Samples and Sampling
. Type and Frequency Sampling Locationa and of (Distances Civen in Tales)
Collection Frequency Analysis
.t '-
DIRECT RADIATION At least-once per 92 days.
Camma dose. Readout at'least once per 92 days.
Indicator I Stations:
Sixteen stations, one in each meteorological sector, along the plant perimeter.
(N-0.8, NNE-0.9, NE-1.0, ENE-0.9, E-0.8, ESE-0.8, SE-1.1,.SSE-1.0, S-1.0, SSW-1.0, SW-0.9, WSW-0.9, W-0.8, WNW-0.8, NW-1.1, and NNW-0.9(
Indicator II (Community) Stations:
Sixteen stations, one in each meteorological sector at'a distance of 4-5 miles.
(NNE-4, NE-4, ENE-4, E-5. ESE-5. SE-5. SSE-3, S-5, SSW-4, SW-5, WSW-4, W-4, WNW-4, NW-4, NNW-4, and N-5)
Control Stations:
Blakely, Ga. (NE-15)
Neals Landing, Fla. (SSE-18)
Dothan, Ala. (W-18)
. WATERBORNE Surface Water Indicator Station:-
Composite taken'with propor-Gamma isotopic analysis tional semi-continuous sampler, of each composite sample.
Great Southern Paper Co., (3 miles below having a minimum sampling fre-Tritium analysis of com-plant discharge) quency not exceeding two hours posite sample at least collected over a period < 31 once per 92 days.
days.
O8 P
TABLE 3 (CONT'D)
Types of Samples and Sampling Type and Frequency
Sampling. Locations and of
_ Distances Given in Miles)
Collection Frequency Analysis
(
Control Station:'
-Upstream of Andrews Lock and Dam ('3 miles above plant intake)-
Ground Water
-Indicator Station:
Grab sample taken at least Gamma isotopic and tritium once per 92 days..
analyses of each sample.
Great Southern Paper Co., Well (SSE-4)
Control Station:
Whatley Residence, Well (SW-1)
River Sediment Indicator Station:
Grab sample taken at least Gamma isotopic analysis once per 184 days.
of each sample.
Downstream of plant discharges at Smith's Bend (~2 miles)
INGESTION Milk Indicator Stations:
At least once per 16 days Gamma isotopic and I-131 Not Available when animals are on pasture; analysis of each sample.
at least once per 31 days at other times.
Control Station:
Brooks-Silcox Dairy, Ashford, Ala. (WSW-10)
C3 t
.-+ _
TABLE 3 (CONT'D)
Types of Samples and Sampling Type and Frequency,
-Sampling Locations and of (Distances Given in Miles)
Collection Frequency Analysis
' Fish Indicator Station:
One sample of the following Gamma isotopic analysis-species at least once per 184 on edible portions.
Downstream of plant discharge in vicinity days:
of Smith's Bend (~2 miles) 1.
Game Fish Control Station:
2.
Botton Feeding Fish Upstream of Andrews Lock and Dan Forage Indicator Stations:
Grab sample cut from green Gamma isotopic analysis forage at least once per 31 which includes I-131 North Perimeter (N-0.8) or days.
analyses of each sample.
South Perimeter (SSE-1.0)
Control Station:
Dothan (W-18)
L P
O i
8 i
i m.
e TABLE 4 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS (FARLEY UNIT NO. 1 Nominal MINIMUM DETECTABLE CONCENTRATION" (MDC)
Sample Gross Radio-Strontium Radio-Iodine Sample Size Beta Gamma Isotopic 89 90
'131 Tritium
~ AIRBORNE:'
-2
-2 3
-3 Particulates 400 m 1.10 10 pci/m 1 sot.
5.10-10 3
3 per week pCi/m pCi/m pCi/m 7.10- '
Iodine 400 m per week pCi/m Milk 10 1 25 pCi/1/isot.
10pCi/1 2pci/1 0.5pci/1 Forage.
1 kg 100 pCi/kg /isot.
80pCi/kg b
80pci/kg Vegetables 1kg 100pci/kg /isot.
and Fruits (Edible).
-Soil ~
In Situ
'200pCi/kg/isot.
200pci/kg WATERBORNE:
River Water 41 25pci/1/isot.
10pci/1 2pci/1 200pci/1 100pci/1
-Ground Water 41 25pci/1/isot.
O C
o TABLE 4 (CONT'D)
Nominal MINIMUM DETECTABLE CONCENTRATION" (MDC)
Sample Gross Radio-Strontium Radio-Iodine Sample Size' Beta Ganuna Isotopic 89 90 131 Tritium-b b
River.
'lkb -
100pci/kg /isot.
SpCi/kg SpCi/kg Vegetation b
River Fish-Ikg 100pC1/kg /isot.
(Edible) b b
b 100pci/kg /isot.
10pci/kg River Benthos 0.5kg Tissue 200pci/kg/isot.
200pci/kg River Sediment ikg (a) Nominal Values Achievable in Practice at Normally Expected Environmental Radioactivity Concentrations.
(Called Lower Limit of Detection (LLD) in-1977 ETS).
(b) Wet Weight.
4 S
I, TABLE 5 DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS i
(FARLEY UNIT No. 2)
MINIMUM DETECTABLE CONCENTRATION (MDC)"
Airborne Particulate Water or Gas Fish Milk Food Products Sediment Analysis
-(PCi/1)
(pCi/m3)
(pCi/kg, wet)
(pci/1)
(pci/kg, wet)
(pCi/kg. dry) gross beta 4
1 X 10-NA.
NA.
NA NA H-3 2000 NA NA NA NA NA Mn-54~
15 NA 130 NA NA NA
~
Fe-59 30 NA 260 NA NA NA Co-58, 60 15 NA 130 NA NA NA Zn-65.
30' NA 260 NA NA NA Zr-95 30 NA MA NA NA NA Nb-95 15' NA NA NA NA NA I-131 1
7 X 10~
NA 1
60 NA Cs-134-
.15 5 X 10~
130 15 60 150 Cs-137 18 6 X 10-150 18 80 180 Ba-140 60 NA NA 60 NA NA La-140 15 NA NA 15 NA NA CS
.l (34)
TABLE 6 SAMPLING AND ANALYSIS DEVIATIONS DURING 1981 WEEK STARTING LOCATION AND NATURE OF DEVIATION 1/12/81 All Direct Radiation Monitoring Stations: Collection of 1980 fourth i
quarter and annual TLD's and installation of 1981 first quarter and annual TLD's were delayed from schedule during last week in December 1980 due to late arrival from Eberline Instrument Corporation and misplacement by Farley storeroom personnel.
1/19/81 Columbia Air Sampling Station: Low volume due to clogged intake line.
l
. Indicator Forage Sampling Stations:
Samples collected at alternate locations due to unavailability at north and south perimeter forage sampling plots.
(Dry weather _and deer grazing on forage plots)
Control Forage Sampling Station:
Sample collected, but size inadequate for valid analysis.
Leafy Vegetables: No control sample available.
2/9/81 Great Southern Paper Air Sampling Station: Low volume due to mechanical pump problem.
Direct Radiation Monitoring Station (NW-4): Quarterly'TLD missing.
~
2/16/81
'All Forage Sampling Stations: -Forage was unavailable from sample
_ plots, thus forage was collected from alternate locations.
2/23/81.
Neals Landing Air Sampling Station:- Low volume due to mechanical failure of pump.
3/2/81.
Air Sampling Locations, North Perimeter Plant Intake Structure, Blakely,'Ashford and Dothan:. Low volume due to possible hose leakage. Check on 3/6/81 indicated that flow rate, pumps and totalizer vere working properly.
3/9/81'
' Indicator Forage Sampling Stations: Forage was unavailable, thus alternate locations were used.
5/25/81
. Milk - Gamma Spectroscopy Analysis:' Inadvertently U. Ga. was not
- notified to perform gamma spectroscopy analysis on each milk q
sample per Unit 2 Technical Specifications.
)
JAir Sampling Stations: Plant Intake St'ructure'and Blakely - Low
- volume due to low flow' rate.
South perimeter - Low volume duc to power interruption during line maintenance.
1 I-l
-e-7 e
+ *er g m,-
-=
(35) 3 TABLE 6 (CONT'D)
WEEK-STARTING' LOCATION AND NATURE OF DEVIATION l
5/25/81 Direct Radiation Monitoring Station (Dothan W-15): Second quarter
. i and annual TLD's missing.
i 7/6/81 Blakely Air Sampling Station: Low volume due to low flow rate.
8/10/81-
- All Air Sampling Stations: Eight day sampling period. Environmental /
f Monitoring Summary Report did not specify reason.
9/21/81-Class - Strontium-89, 90 Analysis: Radiochemical yield inadequate for determination of Strontium-89 and Strontium-90.
i 11/2/81.
All Soil Radioactivity Stations: The fall semi-annual in_ situ Ge(Li) i
. gamma-ray > spectroscopy measurements were not made due to unrepairat'le failure of University of-Georgia Ge(Li) detector. Replacement Ge(Li) detector was not received until 1982.
11/9/81'
- Blakely Air Sampling Station: Low volume'due to mechanical failure of pump.
f 11/16/81 All Air-Sampling Stations: Eight day sampling period due to plant
' emergency drill-which interrupted the normal sampling schedule for the week.-
11/23/81 Plant Intake' Structure Air Sampling Station: Low-volume due to mechanical failure of pump.
j All Air Sampling Stations: Five day sampling period due to emergency drill during prior week and Thanksgiving holidays.
11/30/81 All Air Sampling Stations: 'Eight day sampling period due to Thanksgiving holidays during prior week.
12/7/81.
Plant Intake Structure Air Sampling Station:.. Low volume due to-pump failure.-
12/14/81 Indicator Forage Sampling Stations: Alternate. sampling locations were used.because'of deer eating grass in prepared forage plots.
12/28/81
- Andrews Water? Sampling Station:. Low volume for month of December
=by two' liters due to failure of sampler.
7/13/81-
. Control Milk' Sampling Station:
Sampling period exceeded the.
9/14/81 16-day Unit'.2 specification at the end of each quarter, due to 12/14/81 long established milk sampling schedule _on the second an'd fourth-
-Mondays of each month. A change in schedule was not instituted.
~
- for several reasons, the principal one being that_no indicator milk samples were involved.'
r c-w-
e,
.r-e-
+e--
m, e.--1 e
, ~
TABLE F05-1 AIRBORNE: PARTICUlATES AND IODINE - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR FIANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December, 1981*
(
ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL MAN COBORINITY CONTROL-LOCATIONS LOCATIONS M DIUM OR TYPE AND LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MAN (f)c NAME MAN (f)c MEAN (f)c MEAN (f)c (UNIT OF MASUREENT)
ANALYSES PERFORMED MDCb RANCE c DISTANCE AND DIRECTION RANGEC RANCge RANCEC Air Particulates
' Cross Beta' 528 0.0013 0.121 (211/212)
River Intake Structure 0.127 (52/53) 0.115 (158/158) 0.115 (158/158) d (pC1/m3)
(0.0120 - 0.584) 0.8 Miles - ESE (0.0140 - 0.565)
(0.0130 - 0.534)
(0.0030 - 0.533)
Camma Spec
'40
'Be-7 0.0144 0.0520 (16/16)-
River Intake Structure 0.0558 (4/4) 0.0489 (12/12) 0.0498 (12/12)
(0.0380 - 0.0690) 0.8 Miles - ESE (0.0390 - 0.0690)
(0.0350 - 0.0660)
(0.0300 - 0.0640)
K-40 0.0060 0.0315 (4/16)
River Intake Structure 0.0520 (1/4) 0.0215 (2/12) 0.0260 (2/12)
(0.0240 - 0.0520) 0.8 Miles - ESE (0.0190 - 0.0240)
(0.0210 - 0.0310)
Nb-95 0.0016 0.0321 (12/16)
River Intake Structure 0.0350 (3/4) 0.0296 (9/12) 0.0297 (9/12)
(0.0030 - 0.0530) 0.8 Miles - ESE (0.0040 - 0.0530)
(0.0030 - 0.0470)
(0.0030 - 0.0470)
Zr-95 0.0028 0.0187 (11/16)
River Intake Structure 0.0260 (2/4) 0.0218 (6/12) 0.0218 (6/12)
(0.0020 - 0.0320) 0.8 Miles - ESE (0.0250 - 0.0270)
(0.0180 - 0.0260)
(0.0190 - 0.0250)
Ru-103 0.0022 0.0097 (8/16)
South Perimeter.
0.0105 (2/4) 0.0088 (6/12) 0.0090 (6/12)
(0.0050 - 0.0150) 1.0 Miles - SsE (0.0070 - 0.0140)
(0.0050 - 0.0140)
(0.0050 - 0.0140)
Cs-137 0.0000 0.0028 (10/16)
River Intake Structure 0.0035 (2/4) 0.0026 (5/12) 0.0032 (4/12)
(0.0020 - 4100.)
0.8 Miles - ESE (4100. - 4100.)
(0.0010 - 0.0040)
(0.0020 - 0.0050)
Ce-141 0.0000 0.0061 (7/16)
South Perimeter 0.0110 (1/4) 0.0055 (6/12) 0.0056 (5/12)
(0.0020 - 0.0110) 1.0 Miles - SSE (0.0030 - 0.0090)
(4100. - 4100.)
Ce-144 0.0118 0.0310 (8/16)
Plant Entrance 0.0340 (2/4) 0.0305 (6/12) 0.0292 (6/12)
(0.0190 - 0.0410) 0.9 Miles - WSW (0.0270 - 0.0410)
(0.0140 - 0.0440)
(0.0160 - 0.0430)51-214 0.0000 0.0090 (4/16)
River. Intake Structure 0.0140 (2/4) 0.0030 (3/12) 0.0040 (1/12)
(0.0040 - 4100.)
0.8 Miles - ESE (4100. - 4100.)
(0.0030 - 0.0030)
Pb-214 0.0030 0.0099 (1/16)
River Intake Structure 0.0099 (1/4) 0.8 Miles - ESE 5
i
TABLE F05-1 (Cort'd)
AIRBORNE: PARTICUIATES AND IODINE - OPERATIONAL RADICACTIVITY SUMMART JOSEPH M. FARLET NUCLEAR PIANT
. LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a i
ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL EAN ColGEJNIT CONTROL MEDIUM 0"..
TYPE AND LOCATIONS LOCATIONS IDCATIONS MEAN(f)*
MEAN (f)c MEAN (f)c PATHWAY SAMPLED TOTAL NUMBER OF' NOMINAL MEAN (f)c NAME C
(UNIT OF E ASUREMENT)
ANALYSES PERFORMED MDCb RANCEC DISTANCE AND DIRECTION RANCE RANCE RANCge Ac-228 0.0010 0.0040 (1/16)
Plant Entrance 0.0040 (1/4) 0.0040 (1/12) 0.0060 (1/12) 0.9 Miles - WSW 40 Radiostrogtium
-(X 10' )
Sr-89 3.38 62.7 (12/16)
Plant Entrance 81.7 (2/4) 72.8 (7/12) 90.3 (8/12)
(12.0 - 122.)
0.9 Miles - WSW (76.6 - 86.8)
(14.4 - 104.)
(16.0 - 203.)
Sr-90 1.47 8.58 (13/16)
River Intake Structure 11.3 (3/4) 11.0 (9/12) 17.7 (10/12)
(4.00 - 17.3) 0.8 Miles - ESE (5.60 - 17.3)
(5.00 - 20.4)
(1.80 - 67.6)
Air Charcoal Cartridges Radioiodine 265 (pci/m3) 1-131 0.0470
< MDC
< MDC
< MDC (c) -No Nonroutine Anomalous Measurements Reported During This Petiod.
(b) Mean Minimum Detectable Concentrations Calculated Per Equationy 1 of This Report. The MDC's for Cross S. Radiostrontium and Iodine were Obtained Using Blank Backgrounds '(A Tri ci), h rees for Camma-Ray Spe:troscopy Actual Sample Backgrounds were Used (A Posteriori).
(c) Mean and Range Based Upon Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
(d) To Adjust the Starting and Ending Week for Air Particulate Sanrpling More Closely to the Calendar Year, January 1 through December 31 A 53-Week Sampling Period Was Used for 1981.
3
f' TABLE F05-2 i
EXTERNAL RADIATION - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL MEAN COMMINITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS IDCATIONS-PATHWAY SAMPLED TOTAL NUMBER 0F NOMINAL MEAN (f)C NAME MEAN (f)c MEAN (f)C MEAN (f)C c
c (UZIT OF M!ASUREMENT)
ANALYSES PERFORMED MDCb RANGge DISTANCE AND DIRECTION RANCE RANCEc RANGE TLD - Quarterly Cross Games 154 10.0 16.5 (63/63)
East Perimeter 21.6 (3/3) 14.5 (68/68) 14.9 (23/23)
(MLAD)
(11.1 - 25.5) 1.0 Miles - NE (19.6 - 23.3)
(9.80 - 24.5)
(10.6 - 20.6)
TLD - Annual Cross Camma 34 10.0 61.9 (15/15)
East Perimeter 82.9 (1/1) 49.5 (16/16) 60.8 (3/3)
'(MRAD)
(5?.5 - 82.9) 0.9 Miles - SE (42.8 - 56.8)
(49.9 - 66.9)
TLD'- Annuald Cross Camma 37 10.0 65.1 (15/15)
East Perimeter 85.1 (1/1) 58.0 (17/17) 61.0 (5/5)
(MRAD)
(55.3 - 85.1) 0.8 Miles - E (45.8 - 62.6)
(52.1 - 69.4)
(e)~ No Nonroutine Anoenlous Measurements Reported During This Period.
(b) Lower Limit of Detection as Defined in HASL-3GO, for LiF TLDs as Achieveable in Practice.
(c) Mean and Range Based on Detectable Measurements Only. Fraction of Detectable Measurements at Specified Location in Parenthesis (f).
(d)' Sum of Four Quarters for Comparative Purponen.
C3
TABLE F05-3 MILK - OPERATICIAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PIANT-LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December, 198ga
(
'ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN COMMUNITY ColffROL MEDIUM OR TYPE AND LOCATIONS d LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)C NAME MEAN (f)C MEAN (f)C MEAN{f)C (UNIT OF IEASUREMENT)
ANALYSES PERFORMED MDCb RANGE c DISTANCE AND DIRECTION '
RANGEc RANCEc RANCE Milk Camma Spec 12 (pci/1)
K-40 148.
1590. (12/12)
(1250. - 2090.)
Cs-137 19.0 23.0 (1/12)-
T1-208 -
16.0 17.0 (1/12)
Pb-212 37.5 42.0 (2/12)
(36.0 - 48.0)81-214 35.5 49.0 (2/12)
(40.0 - 58.0)
Ac-228 61.0 76.0 (1/12)
Radiostrontium 12 S r-89 1.98 9.10 (7/12)
(2.70 - 32.4)
Sr-90 1.02 2.39 (11/12)
(1.10 - 5.30)
Radiolodine 24 I-131 0.201
< MDC (c) No Nonroutine Anomalous Measurements Reported During This Period.
(b) Mean Minimum Dc.tectable Concentrations Calculated Per Equation 1 of This Report Using Blank Backgrounds (A Priori) for Radiostrontium and Radiciodine.
For Camaa-Ray Spectroscopy Actual Sample Backgrounds Were Used (A Posteriori).
(c) Mean and Range Based on Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
(d) No Avalable Indicator Milk Sampling Locations.
O3
TABLE F;5-4 VECETATION: FORACE, VEGETABLES AND FRUITS - O*ERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8. HOUSTON COUffrY, ALABAMA January - December,1981 a ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN COMMUNITY CONTROL
. MEDIUM OR TYPE AND LOCATIONS LOCATIONS IDCATIONS MEAN (f) c MEAN (f) C MEAN (f) C -
PATHWAY SAMPLED TOTAL NUMBER OF-NOMINAL MEAN (f)C NAME
~
RANGE RANCE C RANCEc C
C C
(UNIT OF IEASUREMENT)
ANALYSES PERFORMED MDC RANGE DISTANCE AND DIRECTION F rage Camma Spec 34
. (pci/kg - Dry)
Be-7 853.
3720. (19/24)
Plant Entrance
- 9390. (1/1) 3680. (9/10)
(1140. - 9390.)
0.9 Miles - WSW (881. - 7630.)
- 658, 22200. (24/24)
Plant Entrance 51100. (1/1) 18300. (10/10)
(2710. - 52600.)
0.9 Miles - WSW (3770. - 37900.)
Nb-95 116.
1050. (17/24)
North Perimeter 1330. (8/11) 1360. (6/10)
(29.0 - 2650.)
0.8 Miles - N (46.0 - 2650.)
(105. - 4370.)
2r-95 218.
884. (13/24)
North Perimeter 993. (7/11) 943. (5/10)
(160. - 1990.)
0.8 Miles - N (184. - 1990.)
(233. - 2280.)
Ru-103 143.
375. (8/24)
West Perimeter
- 447. (1/3) 425. (3/10)
(70.0 - 743.)
0.9 Miles - SW (109. - 826.)
I-131 84.0 90.0 (1/24)
South Perimeter 90.0 (1/8) 1.0 Miles - SSE Cs-134 99.5 121. (2/24)
North Perimeter 121. (2/11)
(101. - 141.)
0.8 Miles - N (101. - 141.)
Cs-137 93.6 135. (10/24)
North Perimeter 149. (6/11) 181. (4/10)
(46.0 - 244.)
0.8 Miles _- N (46.0 - 244.)
(94.0 - 362.)
La-140 0.0 166. (2/24)
West Perimeter
- 192. (1/3)
(139. - 192.)
0.9 Miles - SW Ce-141 118.
309. (9/24)
North Perimeter 402. (5/11) 274. (3/10)
(46.0 - 1440.)
0.8 Miles - N (46.0 - 1440.)
(123. - 387.)
T8
TABLE F05-4 (Cont'd)
VECETATION: FORACE, VECETABLES AND FRUITS - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN COMMUNITY CONTROL MEDIUM OR TYPE AND LOCATIONS
=
LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)c NAME MEAN (f) c MEAN (f)C MEAN (f)C C
C C
(UNIT OF MEASUREMENT)
ANALYSES PERFORMED MDCD RANCE c DISTANCE AND DIRECTION RANGE RANCE RANCE Ce-144 173.
320. (8/24)
North Perimeter 404. (5/11) 269. (4/10)
(62.0 - 1150.)
0.8 Miles - N (62.0 - 1150.)
(68.0 - 592.)
T1-208 60.6 69.0 (2/24)
South Perimeter 83.0 (1/8) 78.7 (3/10)
+
(55.0 - 83.0) 1.0 Miles - SSE (30.0 - 137.)
Pb-212 110.
185. (3/24)
South Perimeter 222. (2/8) 228. (2/10)
(111. - 241.)
1.0 Miles - SSE (203. - 241.)
(200. - 256.)
Rb-212 188.
295. (1/24)
South Perimeter 295. (1/8) 1.0 Miles - SSE Bi-214 194.
611. (17/24)
West Perimeter 2610. (2/3) 422. (4/10)
(62.0 - 2800.)
0.9 Miles - SW (2410. - 2800.)
(217. - 883.)
Pb-214 223.
441. (8/24)
West Perimeter
- 962. (2/3) 332. (3/10)
(138. - 1220.)
0.9 Miles - SW (704. - 1220.)
(127. - 690.)
Ac-228 364.
492. (8/24)
West Perimeter
- 946. (1/3) 550. (3/10)
(86.0 - 946.)
0.9 Miles - SW (268. - 823.)
Creen Leafy Vegetables Gamma Spec 4
(pci/kg - Wet)
Be-7 1560.
1960. (1/1)
K-40' 767.
7090. (3/3)
West Perimeter 7090. (3/3) 32300. (1/1)
(4240. - 11900.)
0.9 Miles - SW (4240. - 11900.)
Nb-95 89.7 119. (2/3)
West Perimeter
!!9. (2/3) 1800. (1/1)
(113. - 124.)
0.9 Miles - SW
(!!3. - 124.)
C
TABLE F05-4 (C:s t'd)
VECETATION: FC2 ACE, VECETABLES AND FRUITS - OPERATIONAL RADI0 ACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUpffY, ALABAMA January - December, 1981a ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN ColetUNITY CONTROL MEDIUM OR '
TYPE AND LOCATIONS IDCATIONS LOCATIONS LPATHWAY SAMPLED TOTAL NUMBER OF NOM (NALMEAN (f) C NAME MEAN (f)C MEAN (f)c MEAN (f)C C
C RANGEc RANGE c (UNIT OF IEASUREMENT)
ANALYSES PERFORMED MDC RANGE -
DISTANCE AND DIRECTION RANCE Zr-95 154.
92.5 (2/3)
West Perimeter 92.5 (2/3) 1410. (1/1)
(78.0 - 107.)
0.9 Miles - SW (78.0 - 107.)
Ru-103 121.
80.0 (1/3)
West Perimeter 80.0 (1/3) 370. (1/1) 0.9 Miles - SW La-140 0.0 12.0 (1/3)
West Perimeter 12.0 (1/3) 0.9 Miles - SW Ce-141 127.
56.0 (2/3)
West Perimeter 56.0 (2/3) 1090. (1/1)
(46.0 - 66.0) 0.9 Miles - SW (46.0 - 66.0)
Berns (Butter)
Camma Spec 2
(pci/kg - Wet)
K-40 140.
5480. (1/1)
West Perimeter 5480. (1/1) 5160. (1/1) 0.9 Miles - SW Cantaloupe Camma Spec 2
(pC1/kg - Wet)
K-40 158.
1970. (1/1)
West Perimeter 1970. (1/1) 1900. (1/1) 0.9 Miles - SW Corn Gamma Spec 1
(pCi/kg Wet)
K-40 450.
2720. (1/1)
West Perimeter 2720. (1/1) 0.9 Miles - SW Cuscumbers Camma Spec 2
(pci/kg - Wet)
K-40 305.
1450. (1/1)
West Perimeter 1450. (1/1) 1930. (1/1) 0.9 Miles - SW 70
TABLE F05-4 (Cort'd)
' ~ ',
VECETATION: FORACE, VECETABLES AND FRUITS - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLET NUCLEAR PIANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981 a ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN ColetUNITY CONTROL MEDIUM OR TTPE AND.
LOCATIONS IDCATIONS IDCATIONS
. PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL M AN (f) c NAME MEAN (f)c MEAN (f)c MEAN (f) C (UNIT OF MASUREENT)
ANALYSES PERFORMED MDC b RANCE DISTANCE AND DIRECTION RANCEc RANCE c RANCE c Co-134 27.0 31.0 (1/1)
West Perimeter 31.0 (1/1) 0.9 Miles - SW Cs-137 25.0 45.0 (1/1).71-208 20.5 30.0 (1/1)
West Perimeter 30.0 (1/1) 20.0 (1/1) 0.9 Miles - SW Okro Camma Spec 2-
- (pci/kg - Wet)
K-40 383.
3660. (1/1)
West Perimeter 3660. (1/1) 3200. (1/1) 0.9 Miles - SW Nb 32.0 38.0 (1/1)
West Perimeter 38.0 (1/1) 0.9 Miles - SW Zr-95 41.0 90.0 (1/1)
Fi Id Peas Camma Spec 2
(pci/kg - Wet)
K-40 318.
2670. (1/1)
West Perimeter 2670. (1/1) 5010. (1/1) 0.9 Miles - SW Squash Camma Spec-2 (pCi/kg - Wet) 4 K-40 298.
1790. (1/1)
West Perimeter 1790. (1/1) 2500. (1/1) 0.9 Miles - SW 75 1
)
TABLE F05-4 (Cont'd)
VECETATION: FORAGE, VECETABLES AND FRUITS - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a ALL INDICATOR INDICATOR LOCATION WITH EICHEST ANNUAL MEAN COMMUNITT CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)c NAME MEAN (f)c MEAN (f) c HEAN (f) C C
DISTANCE AND DIRECTION RANCEC RANGE c RANCE c b
RANGE (U!IT OF MASUREMElfr)
ANALYSES PERFORMED MDC Cs-137 24.0 37.0 (1/1)
West Perimeter 37.0 (1/1) 0.9 Miles - SW Tomatoes.
Camma Spec 2
(PCi/kg - Wet)
K-40 178.
3800. (1/1)
West Perimeter 3800. (1/1) 2930. (1/1) 0.9 Miles - SW Cs-137 33.0 42.0.(1/1)
Ac-228 14.0 18.0 (1/1)
West Perimeter 18.0 (1/1) 0.9 Miles - SW Watcruelon Camma Spec 2
(pci/kg - Wet)
K-40 148.
908. (1/1)
West Perimeter 908. (1/1) 1040. (1/1) 0.9 Miles - SW Nb-95 24.0 24.0 (1/l)
West Perimeter 24.0 (1/1) 0.9 Miles - SW T1-208 20.0 26.0 (1/1)
Peanuts Comma Spec 2
(pci/kg - Wet)
K-40 0.0 11000. (1/1)
West Perimeter 11000. (1/1) 7650. (1/1) 0.9 Miles - SW T
O
TABLE F05-4 (Cort'd) e l
I VECETATION: FORACE, VECETABLES AND FRUITS - OPERATIONAL RADIDACTIVITT SUMMART JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December, 1981s
,~
i l
ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN COMMJNITY CONTROL LOCATIONS LOCATIONS MEDIUM OR TYPE AND-thCATIONS PATHWAT SAMPLED TOTAL NUMBER OF NOMINAL EAN (f)c NAME MEAN (f)C MEAN (f) c MEAN (f) c (UNIT OF EASUREMENT)
ANALTSES PERFORMED MDCb RANCEc DISTANCE AND DIRECTION RANCE c RANCEC RANCE l
252. (1/1)
Bi-214 92.0 Tzr:1ps Camma Spec 1
(pci/kg - Wet) 2010. (1/1)
K-40 9.0 34.0 (l/1)
Nb-95 28.0 59.0 (1/1)
-Zr-95' 50.0 28.0 (1/1)
T1-208 23.0
.(2) No Nonroutine Anomalous Measurements Reported During This Period.
.(b)' Mean Minimum Detectable Concentrations calculated Per Equation 1 of This Report Using Actual Sample Backgrounds (A Posteriori).
(c) Mean and Range Based on Detectable Measurements Only. Fraction c. Detectable Measurements at Specified Locations in Parenthesis (f).
~
(d) Mean Wet / Dry Ratio for 1981 was 4.2.
-(s) Substitute location Due to Unavailability of Forage at Forage Plot on South Perimeter.
73
-~
TABLE F05-5 SOIL - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981 a -
1 ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN C0f9WWITY,
CONTROL-MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)C NAME MAN (f)c MEAN (f)c MEAN (f) c (UNIT OF MASUREENT)
ANALYSES PERFORMED MDCb RANCE c DISTANCE AND DIRECTION RANGE c -
RANCE c RANGEC Soil (In Situ)
Gamma Spec 15 (pci/kg - Dry)
K-40 473.
4680. (9/9)'
East Perimeter 14000. (1/1) 1350. (3/3).
3490.'(3/3)
(734. - 14000.)
0.8 Miles - E (1050. - 1770.)
(878. - 6520.)
Nb-95 41.3 116. (9/9)
East Pecimeter 163. (1/1) 114. (3/3) 92.7 (3/3)
(82.0 - 163.)
0.8 Miles - E (85.0 - 162.)
(67.0 - 110.)
zr-95 60.2 124. (7/9)
East Perimeter 220. (1/1) 102. (3/3) 57.0 (1/3)
(32.0 - 220.).
1.0 Miles - NE (45.0 - 144.)
Co-134 31.4 47.8 (4/9)
East Perimeter 68.0 (1/1) 28.5 (2/3) 29.0 (1/3)
(37.0 - 68.0) 0.8 Miles - E (28.0 - 29.0)
Cs-137 66.7 420. (9/9)
West Perimeter 666. (1/1) 331. (3/3) 462. (3/3)
(119. - 666.)
0.9 Miles - SW,
(208. - 544.)
(349. - 526.)
T1-208 110.
562. (9/9)
East Perimeter 1130. (1/1) 393. (3/3) 579. (3/3)
(302 - 1130.)
1.0 Miles - NE (281. - 495.)
(460. - 811.)
Pb-212 300.
1560. (9/9)
East Perimeter
'3310. (1/1) 1150. (3/3) 1760. (3/3)
(595. - 3310.)
1.0 Miles - NE (958. - 1340.)
(1420. - 2180.)31-214 175.
1190. (9/9)
East Perimeter 2040. (1/l) 855. (3/3) 1280. (3/3)
(693. - 2040.)
1.0 Miles - NE (837. - 868.)
(999. - 1540.)
Pb-214 264.
1150. (9/9)
East Perimeter 2060. (1/1) 859. (3/3) 1240. (3/3)
(602. - 2060.)
0.8 Miles - E (834. - 906.)
(781. - 1510.)
Ac-228 299.
1530. (9/9)
East Perimeter 3050. (1/1) 1080. (3/3) 1610. (3/3)
(844. - 3050.)
1.0 Miles - NE-(942. - 1240.)
(1260. - 2020.)
L (2) No Nonroutine Anomalous Measurements Reported During This Period.
-(b) Mean Minimum Detectable Concentrations Calculated Per Equation 1 of This Report Using Actual Sample Backgrounds (A Posteriori).
(c) Mean and Range Based on Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
78
TABLE F05-6 WATERBORNE: SURFACE AND CRotCD WATER - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FAE TY NUCLEAR PIANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981 a ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL MEAN COMUNITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS 1DCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MAN (f) c NAME MEAN (f)C MEAN (f)C MEAN (f) c
. UNIT OF MASUREMENT)
ANALTSES PERFORMED MDCb RANCEc DISTANCE AND DIRECTION RANGE c RANCE C RANGg c
(
Surface Water (River)
Camma Spec 12 (PC1/1)
K-40 0.0 85.0 (1/6)
Crest Southern Paper 85.0 (1/6) 66.0 (1/6)
River Mile, 40 Nb-95 9.00 13.0 (1/6)
Cs-134 10.0 11.0 (1/6)
Co-137 4.00
< MDC 4.00 (2/6)
(4.00 - 4.00)
Pb-214.
9.00 10.0 (1/6)
Creat Southern Paper 10.0 (1/6)
River Mile, 40 Radiostrontium 8 Sr-89
=2.00 2.12 (1/4)
Crest Southern Paper 2.12 (1/4) 3.56 (1/4)
River Mile, 40
..Sr-90 1.00
< MDC
E*
92.6 294. (4/4)
Crect Southern Paper 294. (4/4) 162. (2/4)
(107. - 560.)
River Mile, 40 (107. - 560.)
(155. - 168.)
Cround Water (Well)
Tritium 8
(pC1/1)
H-3 91.8 264.-(2/4)
Creat Southern Paper 264. (2/4)
< MDC (126. - 402.)
Well 4 Miles - SSE (126. - 402.)
Camma Spec 8
(c) No Nonroutine Anomalous Measurements Reported During This Period.
(b) Mean Minimum Detectable Concentrations calculated Per Equation 1 of This Report. The MDC's for Tritium and Radiostrontium Were Obtained Using g
Blank Backgrounds (A Priori), Whereas, for Camma-Ray Spectroscopy Actual Sample Backgrounds Were Used (A Posteriori).
3 (c) Mean and Range Based Upon Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
(d) No Detectable Camma Activity.
e TABLE F05-7
+
~ s VEGETATION: AQUATIC - OPERATIONAL RADI0 ACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PIANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a,
ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL MAN COMPRINITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)c NAME MEAN (f)c HEAN (f)C MEM (f)C
' (U IT OF MEASUREENT)
ANALYSES PERFORMED MDCb RANGEc DISTANCE AND DIRECTION RANCgc RMCEc RMCEc Aquatic Vegetation Camma Spec 4
(River) (pCi/kg - Wet)
K-40 176.
5230. (2/2)
Chattahoochee River 5230. (2/2) 5280. (2/2)
(3310. - 71AO.)
River Mile, 10-42 (3310. - 7140.)
(2670. - 7880.)
Nb-95 36.3 51.5 (2/2)
Chattahoochee River 51.5 (2/2) 112. (1/2)
(26.0 - 77.0)
River Mile, 10-42 (26.0 - 77.0)
Zr-95*
55.0 87.0 (1/2)
Chattahoochee River 87.0 (1/2)
River Mile,10-42 Ru-103 30.0 50.0 (1/2)
Chattahoochee River 50.0 (1/2)
River Mile, 10-42 Ca-137 39.5 51.0 (1/2)
Chattahoochee River 51.0 (1/2) 77.5 (2/2)
River Mile, 10-42 (56.0 - 99.0)
T1-208 26.0 63.5 (2/2)
Chattahoochee River 63.5 (2/2) 41.0 (1/2)
(61.0 - 66.0)
River Mile. 10-42 (61.0 - 66.0)
Pb-212 56.3 187. (2/2)
Chattahoochee River 187. (2/2) 111. (2/2)
(185. - 188.)
River Mile, 10-42 (185. - 188.)
(107. - 114.)31-214 70.8 156. (2/2)
Chattahoochee River 156. (2/2) 124. (2/2)
(114. - 198.)
River Mile, 10-42 (114. - 198.)
(71.0 - 177.)
Pb-214 74.5 143. (2/2)
Chattahoochee River 143. (2/2) 156. (2/2)
.(136. - 149.)
River Mile,10-42 (136. - 149.)
(112. - 199.)
Ra-226 50.5 60.5 (2/2)
Chattahoochee River 60.5 (2/2)
(50.0 - 71.0)
River Mile, 10-42 (50.0 - 71.0) 93
TABLE F05-7 (Colt'd)
VEGETATION: AQUATIC - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT -
LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA -
January - December,1981a ALL INDICATOR
-INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN C0teRINITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS IDCATIONS PATHWAY SAMPIJ.D T(yfAL NUMBER OF NOMINAL MEAN (f)C NAME MEAN (f) C MEAN (f)c MEAN (f)C (UNIT OF M*%REMENT)
ANALYSES PERFORMED MDCb RANCge DISTANCE AND DIRECTION RANCEc RANCE c RANGE C Ac-228 102.
286. (2/2)
Chattahoochee River 286. (2/2) 285. (1/2)
(267. - 304.)
River Mile, 10-42 (267. - 304.)
Radiostrontium 4 Sr-89 3.55 73.9 (1/2)
Chattahoochee River 73.9 (1/2)
< MDC River Mile, 10-42 Sr-90 1.15 5.10 (1/2)
Chattahoochee River 5.10 (1/2)
I4.8 (2/2)
River Mile,10-42 '
(12.1 - 17.5)
(a) No Nonroutine Anomalous Measurements Were Reported During This Period.
(b) Mean Minimum Detectable Concentrations Calculated Per E;aation 1 of This Report Using Actual Sample Backgrounds (A Posteriori) for Camma Spectroscopy and Blank Backgrounds (A Priori) for Radiostrontium.
(c) Mean and Range Based Upon Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
3
TABLE F05-8 BENTHOS: CLAMS - OPERATIONAL RADIOACTIVITY
SUMMARY
JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December, 1981a ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN COMMUNITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)C NAME MEAN (f)c MEAN (f) c MEAN (f)C (UNIT OF MEASUREMENT)
ANALYSES PERFORMED MDCb RANGEc DISTANCE AND DIRECTION RANCE c RANGE c RANGge Benthos (Class)
Camma Spec 4
(pci/kg - Wet Tissue)
K-40 116.
1490. (1/2)
Chattahoochee River 1490. (1/2) 1160. (2/2)
River Mile, 10-42 (502. - 1820.)
Nb-95 16.0 17.0 (1/2)
Chattahoochee River 17.0 (1/2)
River Mile, 10-42 T1-208 40.0 41.0 (1/2)
Pb-212 67.0 87.0 (1/2)
Bi-214 38.0 60.0 (1/2)
Chattahoochee River 60.0 (1/2)
River Mile, 10-42 Pb-214 51.0 80.0 (1/2)
Chattahoochee Rivar 80.0 (1/2)
River Mile, 10-42 Ac-228 113.
136. (1/2)
Chattahoochee River 136. (1/2) 158. (1/2)
River Mile, 10-42 Radiostrontium 2
Sr-89 3.10
< MDC
< MDC
< MDC (s) No Nonroutine Anomalous Measurements Were Reported During This Period.
(b) Mean Minimum Detectable Concentrations Calculated Per Equation 1 of This Report Using Actual Sample Backgrounds (A Posteriori) for Gamma-Ray Spectroscopy and Blank Backgrounds (A Priori) for Radiostrontium.
(c) Mean and Range Based Upon Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
O S
TABLE F05-9
~,
FISH: RIVER - OPERATIONAL RADIOACTIVITY
SUMMARY
o JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL MEAN COMMUNITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f)c NAME MEAN (f) c MEAN (f) C MEAN (f) C (UNIT OF MEASUREMENT)
ANALYSES PERFORMED MDC RANCE c DISTANCE AND DIRECTION RANCEC b
RANGEC RANCgc Fish (Forage Feeding)
Camma Spec 4
(pC1/kg - Wet Tissue)
K-40 610.
9050. (2/2)
Smith's Bend 9050. (2/2) 9070. (2/2)
(4600. - 13500.)
River Mile, 41-42 (4600. - 13500.)
(5040. - 13100.)
Nb-95 104.
137. (1/2)
Smith's Bend 137. (1/2)
River Mile, 41-42 Zr-95 66.0 72.0 (1/2)
Smith's Bend 72.0 (1/2)
River Mile, 41-42 Cs-137 87.8 147. (2/2)
Smith's Berd 147. (2/2) 120. (2/2)
(100. - 193.)
River Mile, 41-42 (100. - 193.)
(94.0 - 146.)
Bi-214 236.
375. (1/2)
Smith's Bend 375. (1/2) 256. (1/2)
River Mile, 41-42 Fish (Came)
Camma Spec 4
(pCi/kg - Wet Tissue)
K-40 336.
9170. (2/2)
Smith's Bend 9170. (2/2) 8130. (2/2)
(4930. - 13400.)
River Mile, 41-42 (4930. - 13400.)
(4260. - 12000.)
Cs-137 62.3 189. (2/2)
Smith's Bend 189. (2/2) 126. (2/2)
(136. - 241.)
River Mile, 41-42 (136. - 241.)
(116. - 136.)
Bi-214 146.
116. (1/2)
Smith's Bend 116. (1/2) 206. (1/2)
River Mile, 41-42 Fish (Botton Feeding)
Camma Spec 4
(pC1/kg - Wet Tissue)
K-40 171.
5680. (2/2)
Smith's Bend 5680. (2/2) 8980. (2/2)
(3320. - 8030.)
River Mile, 41-42 (3320. - 8030.)
(3450. - 14500.)
a C
TABLE F05-9 (Cont'd):
g FISH: RIVER - OPERATIC 7AL RADI0 ACTIVITY
SUMMARY
g JOSEPH M. FARLEY NUCLEAR PLANT LICENSE NOS. NPF-2 AND NPF-8, HOUSTON COUNTY, ALABAMA January - December,1981a ALL INDICATOR INDICATOR LOCATION WITH HICHEST ANNUAL MEAN COMMUNITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIONS PATHWAY SAMPLED TOTAL NUMBER OF NOMINAL MEAN (f) c NAME MEAN (f)c MEAN ( f) C MEAN (f)C (UNIT OF MEASURDENT)'
ANALYSES PERFORMED MDC b RANGE C DISTANCE AND DIRECTION RANCE c RANCE C RANCE c Nb-95 36.0 38.0 (1/2)
Smith's Bend 38.0 (1/2)
River Mile, 41-42 Zr-95 29.0 54.0 (1/2)
Cs-137 66.7 96.0 (1/2)
Smith's Bend 96.0 (1/2) 106. (1/2)
River Mile, 41-42 31-214 48.0 58.0 (1/2)
Smith's Bend 58.0 (1/2)
River Mile, 41-42 Ac-228 149.
246. (1/2)
Smith's Bend 246. (1/2)
River Mile, 41-42 (c) No Nonroutine Anomalous Measurements Were Reported During This Period.
(b) Mean Minimum Detectable Concentratione Calculated Per Equation 1 of This Report Using Actual Sample Backgrounds (A Posteriori).
(c) Mean and Range Based Upon Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
O
TABLE F05-10 e
SEDIMENT: RIVER - OPERATIC"AL RADIOACTIVITY
SUMMARY
3 JOSEPH M. FARLEY NUCLEAR PIANT LICENSE NOS. NPF-2 AND NPF-8, HOUS11)N COUNTY, ALABAMA January - l'ecember, 1981a ALL INDICATOR INDICATOR LOCATION WITH HIGHEST ANNUAL MEAN COMMUNITY CONTROL MEDIUM OR TYPE AND LOCATIONS LOCATIONS LOCATIGNS PATHWAY SANPLED TOTAL NUMBER OF NOMINAL MEAN (f)c NAME
!!EAN (f)c MEAN (f)c MEAN (f)C C
(UNIT OF MEASUREMENT)
ANALYST.S PERFORMED MDCb RANCEc DISTANCE AND DIRECTION RANGEc RANCtc RANCE Sediment (Ricer)
Camma Spec 4
(pC1/kg - Dr>)
537. (l/2)
Be-7 339.
K-40 230.
1730. (2/2)
Smith's Bend 1730. (2/2) 4550. (2/2)
(1540. - 1910.)
River Mile, 41-42 (1540. - 1910.)
(2430. - 6660.)
Nb-95 52.0 113. (l/2) 185. (2/2)
Cs-137 44.0 (128. - 242.)
TI-208 35.3 72.5 (2/2)
Smith's Bend 72.5 (2/2) 249. (2/2)
(56.0 - 89.0)
River Mile, 41-42 (56.0 - 89.0)
(39.0 - 459.)
Pb-212 64.8 264. (2/2)
Smith's Bend 264. (2/2) 1080. (2/2)
(246. - 282.)
River Mile, 41-e2 (246. - 282.)
(790. - 1370.)
Bi-214 67.5 175. (2/2)
Smith's Bend 175. (2/2) 737. (2/2)
(161. - 188.)
River Mile, 41-42 (161. - 188.)
(384. - 1090.)
Pb-214 70.0 190. (2/2)
Smith's Bend 190. (2/2) 80?
t/2)
(172. - 207.)
River Mile, 41-42 (172. - 207.)
(SA. - 1230.)
Ra-226 615.
457. (1/2)
Smith's Bend 457. (1/2) 2200. (1/2)
River Mile, 41-42 Ac-228 113.
285. (2/2)
Smith's Bend 285. (2/2) 1180. (2/2)
(261. - 309.)
River Mile, 41-42 (261. - 309.)
(988. - 1380.)
Radiostrontium 4
Sr-90 25
<MDC 40 (1/2)
(a) No Nontoutine Anomalous Measurements Were Reported During This Period.
(b) Mean Minimum Detectable Concentrations Calculated Per Equation 1 of This Report Using Actual Sample Backgrounds (A Posteriori) For Camma-Ray Spectroscopy and Blank Backgrounds (A Priori) For Radiostrontium.
(c) Mean and Range Based Upon Detectable Measurements Only. Fraction of Detectable Measurements at Specified Locations in Parenthesis (f).
O S
Y 4
4 ATTACHMENT 1 (54)
LAND USE SURVEY FOR RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM i
FARLEY NUCLEAR PLANT JUNE 1-5,1981 This Land Use Survey combined the semi-annual milk animal survey with the annual garden and nearest resident survey.
j A.
Houston County, Alabama Mr. A. M. Mathews, Houston County Extension Agent was visited for the purpose of discussing the location of milk animals in Houston He said that there had been no change in the dairy business County.
He said that the in Houston County during the past six months.
Silcox Dairy was still the closest one to the plant.
A subsequent house-to-house canvas of residents along Alabama 95 for
- a. distance of about three miles and for about a mile of the plant entrance on Houston County 42 was negative with respect to the presence of milk animals.
- Simultaneous with the milk animal canvas a survey wgs made to locate the nearest resident and vegetable garden (>500 ft.Z) in each meteorological sector.
B.
Early County, Georgia Mr. Wayne Tankersley, Early County Extension Agent, was visited to discuss whether any milk animals were now present in Early County.
He said that there were no dairies in the county and no individual milk animals unless Mrs. Henry Perry in Cedar Springs had acquired a milk cow.
A subsequent check with Mrs. Perry's son (Mrs. Perry was out-of-state) confirmed that she did not have a milk cow. A house-to-house canvas of the area east of the Chattahoochee River was negative with respect to milk animals.
Simultaneous with the milk animal canvas a survey was made to locate the nearest resident and vegetable garden (>500.ft.2) in each l
i meteorological sector.
l C. -Results and Conclusions The results of the Land Use Survey are shown in Table I.
Based on the survey results, no change in the present milk sampling pr gram
'is required.-
l
--W. M. Jackso June 11,1
)
l
/
o
TABLE I TO ATTACHMENT I (55)
L JOSEPH M. FARLEY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING SURVEY JUNE 1-5, 1981 i
^
(DISTANCE MILES TO NEAREST)
VEGETABLE GARDEN MILK 4
RADIALSECTORS(22[ DEGREES)
RESIDENT
(>500 FT;2)
ANIMAL
>5 2.4.-
, 2.4 North Northeast (01) 1.,
'3 2.6
>5 Northeast (02) s 4.0.
4.0
>5 East Northeast (03) 2.8 2.8
>5 East (04) 2.8 2.8
>5 x
East Southeast (05) 3.is 3.4
>5 Southeast (05)
South Southeast (07)
>5
>5
>5 4.2 4.2
>5 South (08)
>5 South Southwest (09) 2.9, 2.9 1.2 1.2
>5 Southwest (10)
West Southwest (11) 0.9 3.5
>5 1.3 1.3
>5 West (12)
West Northwest (13) 2.1 2.1
>5 3.0 3.1
>5 Northwest (14)
North Northwest (15) 2.0. >
2.0
> 5 -,
2.6 4.3
>5' North (16)
]
~,
- n W
h l.
4 w
\\
)
I
!s 1
.n
\\
. ~. -
5
[^ '
}
a 1
s
.s#
4
\\
t ATTACHMENT 2 (56)
MILK ANIMAL SURVEY FOR FARLEY NUCLEAR PLANT RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM DECEMBER 22-23, 1981 t
A.
Survey in Houston Cotnty, Alabama Mr. A.'N. Mathews, Houston County Extension Agent, was visited for He said l
discussion of the location of milk animals in Houston County.
that there had been no change in the number or location of dairies in i
the County during the past six months and that the nearest milk animals He said that to his to the plant were still at the Brooks-Silcox Dairy.
knowledge no individually owned milk animals were present within 10 miles of the plant.
A house-to-house survey of residents along Alabama 95 for a distance of about three miles from the plant entrance and for about a mile west on Houston County 42 revealed no milk animals.
In addition, individuals at the following residences were questioned: Henry Money, Walter Whatley, Tonny Repas 'and Manford Miller.
B.
Survey. in Early County, Georgia Mr. Wayne Tankersley, Early County Extension Agent, was visited for discussion of milk animals in Tarly County. Due to an unexpected absence He to meet a request for assistance the discussion was by telephone.
said that to his knowledge there are no milk animals in the County.
This was confirmed by the Assistant County Extension Agent, Tom Jennings.
Mrs. Henry' Perry, Cedar Springs, who previously owned a milk cos has A house-to-house survey along the oirt road no milk animals at present.
parall'el to the Chattahoochee River revealed no milk animals.
M. F. Freeman, Individuals at the following residences were questioned:
C. H.'Fretman, Jim Donaldson and Frank Fulton (Residence Andrews Lock and Dem).
l C.
Survey Coaclusions Based on the survey results no change in the present milk. sampling l
l.'
program is required.
[;
~
W. M.
ckson Janu 4, 1982
}
s
/
l m
?
9
.e
'?(-
.. - (.
t,
.3.
Alabama Power Company 600 North 13.h Street Post Offica Box 2641 -
/ ' "', 7 v
/
Birmingham, Alabama 35291
/
Telephone 205 250-1000 F. L CLAYTON, JR.
p&
Senior Vice President Alabama Power 4/
April 1, 1982 the southem electnc system Docket Nos. 50-348 50-364 s
2
?>
Director
.a,
Office of Inspection and Enforcement p'
U.S. Nuclear Regulatory Commission y
Region II
. Suite 3100 101 Marietta Street, N.W.
Atlanta, GA 30303 7
Re:
Joseph M. Farley Nuclear Plant Annual Environmental Operating Report Gentlemen:
The attached " Annual Environmental Operating Report, Part B: Radio-logical" for the period ending December 31, 1981 is transmitted in accordance with the Joseph M. Farley Nuclear Plant Unit 1. Environmental Technical Speci-fication Section 5.6.1.a. Part B, and Unit 2 Technical Specifications Sections 6.9.1.6 and 6.9.1.7.
If you have any questions, please advise.
Yours very truly.
[
F.
. Clayton Jr.
FLCJr:WMJ:aw Attachment cc: Office.of Nuclear Reactor Regulation (W/ Attachment)
U.S. Nuclear Regulatory Commission i
Director, Division of Radiological Health (W/Att#3hment)
State of Alabama Director, Environmental Protection Division (W/ Attachment)
State of Georgia 2
P Ck I
1