ML20154K360

Preoperational Radiological Environ Surveillance Rept 1981-84

ML20154K360
Person / Time
Site:	Vogtle
Issue date:	12/31/1984
From:	GEORGIA POWER CO.
To:
Shared Package
ML20154K356	List: ML20154K353 ML20154K360
References
NUDOCS 8805310012
Download: ML20154K360 (115)

Text

_. _ _ _ _ _

Georgia Poner d

\\

ENCLOSURE PLANT V0GTLE - UNIT 1 NRC DOCKET 50-424 OPERATING LICENSE NPF-68 PRE 0PERATIONAL ENVIRONMENTAL HONITORING REPORT GEORGIA POWER COMPANY V0GTLE ELECTRIC GENERATING STATION PREOPERATIONAL RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT 1981-1984 8805310012 880523 PDR ADOCK 05000424 R

DCD J

- - -. =

4 1

4 i

i.

l t

I i

?

i i

[

i 4

j.

E i.

4 Georgia Power Company

[

l Vogtle Electric Generating Station Preoperational Radiological Environmental Surveillance Report 1981-1984 1

P F

j 4

I i

~

I l

4 t

1 I

l i

3 i

j i

4 h

r s

r i

)

f 1

E

. -. - ~

. - ~

i i

Table of Contents Section Title Page 1.

Introduction and Program Overview 6

6 2.

Program Description and Results 12 2.1 Media Affected by Discharges to the Atmosphere 12 2.1.1 Air 12 2.1.2 Direct Radiation 16 2.1.3 Milk 18 2.1.4 Vegetation 19 i

2.2 Media Affected by Discharges to thE River 21 2.2.1 River Water 21 2.2.2 Drinking Water 22 2.2.3 Sediment 25 2.2.4 Fish 26 2.3 Groundwater 28 3.

Deviations from the Program 30 4.

Program Changes 36 5.

EPA Intercomparison Studies (Crosscheck) Program 38 6

6.

Land Use Survey 39 i

7.

Conclusions 40 I

8.

References 41 i

t i

t r

i I

i 4

2 s

List of Tables j012.le Number Title Page 1

I i

1 Radiological Environment Monitoring Prog ram 42 2

Radiological Environmental Sampling Location 46 3

Detection Capabilities for Environmental Sample Analyses 49 4

Detection Levels Routinely Achieved for Environmental Sample Analyses 52 5

Summary of Gross Beta Activity Detected in Airborne Particulates (1981-1984) 53

~

6 Summary of I-131 Activity Detected in Air (1981-1984) 54 7

Summary of Specific Radionuclides Detected in A!c (1981-1984) 55 7

8 Summary of Diree. A?diation Doses Measured by ih

.oluminescent Dosimeters (1981-1984) 59 1

9 Summary of Specific Radionuclides Detected in Milk (1981-1984) 60 10 Summary of Specific Radionuclides Detected in Grass (1981-1984) 61 11 Summary of Specific Radionuclides Detected in River Water (1981-1984) 63 12 Summary of Gross Beta and Specific Radionuclides Detected in Raw Drinking Water (1983-1984) 65 13 Summary of Gross Beta and Specific Radionuclides Detected in Finished Drinking Water (1981-1984) 67 J

14 Summary of Specific Radionuclides Detected in Sediment (1981-1984) 69 15 Summary of Specific Radionuclides l

Detected in Fish (1951-1984) 71 16 Summary of Specific Radionuclides Detected in Gtound Water (1981-1984) 72 17 Crosscheck Program Results - Air Filters (1981) 73 r

18 Crosscheck Program Results - Milk (1981) 74 L

19 Crosscheck Program Results - Water (1981) 75 t

3

List of Tables (Continued)

Table Number Title Page 20 Crosscheck Program Results - Air Filters (1982) 77 21 Crosscheck Program Results - Milk (1982) 78 22 Crosscheck Program Results - Water (1982) 79 23 Crosscheck Program Results - Air Filters ( 1983) 81 24 Crosscheck Program Results - Milk (1983) 82 25 Crosscheck Program Results - Water (1983) 83 26 Crosscheck Program Results - Air Filters (1984) 85 27 Crosscheck Program Results - Milk (1984) 86 28 Crosscheck Program Results - Water (1984) 87 29 Criteria for Comparing Analytical Measurements 89 30 Land Usa survey (1981) 90 31 Land Use Survey (1982) 91 32 Land Use Survey (1983) 92 33 Land Use Survey (1984) 93

^

4 l

y

List of Figures Fiquee Number Title Page 1

Terrestrial S tations Near Site Boundary and Groundwater Stations 94 2

Terrestrial Stations Beyond Site Boundary Out to Approximately Five Miles and River Water S tations 95 3

Terrestrial S tations Beyond Five Miles 96 4

Drinking Water Stations 97 5

Average Gross Beta in Air 1981-1984 98 6

Average Concentration of Tritium in Air 1981-1984 99 7

Average TLD Results at the Site Boundary 1981-1984 100 8

Average Concentration of Tritium in Grass 1981-1984 101 9

Average Concentration of Cs-137 in Grass 1981-1984 102 10 Average Concentration of Tritium in River Water 1981-1984 103 11 Average Concentration of Cs-137 in River Water 1981-1984 104 12 Average Concentration of Gross Beta in l

Raw Drinking Water 1983-1984 105 l

13 Average Concentration of Tritium in Raw Drinking Water 1983-1984 106 14 Average Concentration of Cs-137 in Raw Drinking Water 1983-1984 107 15 Average Concentration of Gross Beta in Finished Drinking Water 1981-1984 108 16 Average Concentration of Tritium in Finished Drinking Water 1981-1984 109 17 Average Concentration of Cs-137 in Finished Drinking Water 1981-1984 110 l

18 Average Concentration of Cs-137 in l

Sediment 1981-1984 111 19 Average Concentration of Cs-137 in Fish 1981-1984 112 20 Average Concentration of Tritium in Groundwater 1981-1984 113 21 Average Concentration of Cs-137 in l

Groundwater 1981-1984 114 5

l

~

1.0 Introduction and Program Overview This report presents preoperational radiological environmental monitoring program results for the Vogtle Electric Generating Plant (VEGP) for the period 1981-1984.

This report will be updated and presented in final form af ter conclusion of the preoperational stage of the radiological environmental monitoring program.

The operational stage of the radiological environmental monitoring program will commence with initial criticality of Unit 1.

Vogle Electric Generating Plant will contain two PWR generating units, each with a capacity of about 1157 MWe, The 3169-acre site is located in the eastern sector of Burke County, Georgia, on the Savannah River at river mile 151, approximately 23 river miles upstream from the intersection of the Savannah River and U. S.

Highway 301.

The purpose of the preoperational radiological environmental monitoring program is to measure the levels of background radiation and radioactivity, in the vicinity of VEGP.

These background measurements can be compared with measurements to be taken during plant operation to assess the ef fects of the plant on levels of radiation and radioactivity in the area.

The program provides measurements of radiation and radioactivity for those exposure pathways, and for those radionuclides, which are expected to produce the highest potential radiation doses to individuals as a result of plant operations.

The general bases for establishing the radiological environmental monitoring program are set forth in reference 3 with additional guidance provided by references 2, 4, 5 and 6.

Requirements for the preoperational phase of the radiological environmental monitoring prograu are presented in Chapter 6 of the VEGP Environmental Report - Operating License Stage (Reference 1).

Requirements for the operational phase of the radiological environmental monitoring program will be established in the VEGP Radiological Ef fluent Technical Specifications.

6

In addition to obtaining background data, during the preoperational radiological environmental monitcring program procedures and techniques are developed, equipment is evaluated and calibrated, and personnel are trained.

Neither the operational radiological environmental monitoring program nor the preoperational program was designed to measure the amount of radioactivity discharged from the plant into the environment.

This will be done before and during release of liquid effluent and gaseous effluent using sample analyses and effluent monitors.

The preoperational and operational radiological environmental monitoring programs are concerned specifically with the impact of plant radiation and radioactive effluents on the surrounding region.

Some samples and monitoring points not expected to be affected by plant operations will be monitored during the preoperational period to establish baseline data.

These samples and locations need not be monitored during operation until there is reason to believe that they may become suf ficiently aff ected by plant operations to warrant monitoring.

In August 1981 preoperational monitoring began to be phased in.

Periods of 6 months to 2 years, depending on the sample, are usually sufficient to provide an adequate data base for comparison with operational data and to provide experience which may improve the efficiency of the operating program.

This period will be extended as feasible; however, the preoperational stage will be concluded at about the time of initial criticality of Unit 1, if not before.

Measurements are taken chiefly at two kinds of locations:

indicator stations where long term or maximum radiological levels attributable to operation of the plant are anticipated; and control stations where radiological levels are not expected to be significantly influenced by plant activities.

However, all of the indicator and control stations are susceptible to any radiological effects which might be attributed to the operation of neighboring nuclear facilities, as well as to fallout from nuclear weapons tests.

These could confuse the proper comparison l

l 7

of the radiological levels between the indicator and control stations or between the periods of operation and preoperation when attempting to show the effects of plant operation.

Measurements may also be,taken at locations of special interest, such as nearby institutions or towns, or residences.

Samples are collected and analyzed in accordance with table 1, which includes the basic radiological environmental monitoring ptogram described in table 6.1-1 of VEGP Environmental Report -

Operating License Stage as well es supplemental sample stations and sample media which have been added to the basic preoperational program to augment the preoperational environmental data base.

The supplemental locations and/or media are designated as such by notation to table 1.

All additions and changes to the basic program through 1984 are also discussed in section 4.

The locations of the sampling stations are described in table 2 and are shown in figures 1 through 4.

The number and locations of the sampling stations were determined largely by the guidance provided in reference 5.

Site specific considerations

.such as accessibility also influenced some of the locations of the sampling stations.

Evaluation of the findings of the program provides the basis for program modification to ensu re that the surveillance effort is sufficient and justified.

Adjustments will be made as feasible with regard to sample type, sample location, analyses to be performed, collection equipment, sample collection and analysis frequencies, or detection capabilities.

Such adjustments are normally much more extensive during preoperations, which is a time of trial and discovery.

The operational program is expected generally to be a continuation of the program developed during preoperation.

Indicator stations for airborne particulates and radiciodine are placed near the site boundary; their azimuthal locations were selected upon meteorological considerations.

Air sample stations are also placed in the nearest community and at a control location.

8

The thermoluminescent dosimete r locations for measuring the acquired dose from direct radiation are approximately as follows:

an inner ring of stations in the general area of the site boundary and an outer ring in the 4-to 5-mile range f rom the plant with a station in each sector of each of the rings.

The balance of the thermoluminescent dosimeters are placed at locations of special interest and at control locations.

River water sampling locations for control stations were placed upstream of VEGP and indicator stations were placed downstream of VEGP.

Further, river water sampling locations were placed at specified locations to distinguish between VEGP and Savannah River Plant discharges, as well as to assess the eff ects of VEGP operations.

River water is collected using automatic sampling equipment in which small quantities of river water are collected approximately hourly.

The samples are retrieved monthly.

Drinking water indicator stations are placed at the only two known downstream locations where river water is used for drinking.

The control drinking water station is the closest upstream location where river water is used for drinking.

An annual survey of the Savannah River is performed to determine the nearest downstream location where river water is used for drinking.

Groundwater is sampled from both the local unconfined aquifer and the regional confined aquifer.

However, because the concept of control and indicator stations does not apply well to the sampling of groundwater, groundwater sampling stations are categorized by the type of aquifer sampled rather than as control or indica tor.

Sample collections are made near the nuclear power block where any groundwater contamination would likely occur.

The unconfined aquifer is also sampled at locations approxima te to where any contaminated groundwater would more likely be l

eventually released to the public.

Grou ndwa te r is not expected to be affected by normal plant operations.

Sediment samples are collected f rom an indicator station near the edge of the river at a downstream location with 9

i t

potential for recreational use.

Sedimen t samples are also collected f rom two control stations loca ted upstream of VEGP.

Milk samples are collected at the nearest location to VEGP where cows are milked for human consumption.

If sufficient milk sampics are not available, results of grass sample analysis will be used to assess potential exposure via the milk consumption pathway.

Fish samples are collected at a control station located upstream of VEGP and at an indicator station located downstream of VEGP.

Fish samples consist of species of fish which are normally consumed by humans.

Grass samples are collected from indicator stations located near the site boundary and at a control location not expected to be af f ected by VEGP operations.

Grass is collected ra ther than leafy vegetation because:

grass will be available almost year-round, whereas leafy vegetation is available only for about 6 months of the year; stations may be placed at desired locations with relative ease; and grass is a suitable collector of I-131 and other radionuclides.

Deviations are permitted from the sampling schedule stated in table 1 if specimens are unobtainable due to hazardous conditions, seasonal unavailability, malfunction of sampling equipment and other justifiable reasons.

All deviations from the required sampling schedule are discussed in section 3 of this report.

Appropriate analytical techniques are used to achieve the detection capabilities listed in table 3.

De tection levels achieved during routine laboratory analyses are presented in table 4.

Con tra ct laboratories and inhouse laboratories which perform required analyses participate in the Environmental Protection Agency environmental radioactivity laboratcry intercompar ison studies (crosscheck) program or an equivalent program.

This participation includes all of the determinations (sample medium and analysis combination) that are offered by the Environmental Protection Agency and that are also included in the 10

monitoring program.

Participation in the crosscheck program is discussed further in section 5 of this report.

A land use survey is conducted each year during the growing season to identify, within a distance of five miles from the plant, the location of the nearest milk animal, the nearest residence and the nearest garden, of greater than fif ty square meters producing broad leaf vegetation, in each of the sixteen me teorological sectors.

Results of the land use surveys are discussed in section 6 of this report.

4 l

11 i

i

- ~ _.

2.0 Program Description and Results In this section, the approach to monitoring or sampling of each medium is described.

Results are presented in summary tables in the format recommended by the NRC Branch Technical Position on Radiological Monitoring (reference 5).

For those media with sufficient positive measurement results to make trending feasible, sample analysis results are presented in graphic form to illustrate data trends over the period of the preoperational radiological environmental monitoring program.

Trend graphs are based on data from indicator stations only.

For radioactivity in groundwater, trend graphs are based on data from the local unconfined aquifer.

2.1 Media Af f ected by Discharges to the Atmosphere 2.1.1 Air Airborne radioactivity was determined by collecting samples three indicator locations near the site boundary, one special at in te re st location in the community of Girard, and a control location in Waynesboro.

In accordance with the basic program presented in table 1, airborne particulates and radiciodine were sampled at these locations.

In addition, the basic program was supplemented by collecting samples of airborne tritium at three of these locations.

Airborne particulate and radioiodine samples were fi rst collected at Hancock Landing (S tation 16) and Waynesboro (S tation

36) September 9, 1981; at the Meteorological Tower (S ta tion 10 )

and the community of Girard (Station 35) September 22, 1981; and at the simulator building (Station 7) November 10, 1981.

Airborne tritium was first collected at Hancock Landing August 16, 1983; and at the simulator building and at Waynesboro August 14, 1984.

Aiborne particulates were collected on Gelman Type A/E glass fiber filters and airborne radioiodine was collected on i

12

Scientific Applications, Inc. (SAI) CP-20 0, TEDA-trea ted,

charcoal cartridges using low volume air samplers, with the charcoal cartridge in series with the air particulate filter.

Air sample volumes were determined f rom air flow measu rements and elapsed-time clocks.

The samplers were operated continuously; pa r ticula te filters and charcoal cartridges were exchanged weekly.

Charcoal cartridges were analyzed for I-131 weekly following collection.

Air particula te filters were analyzed weekly for gross beta.

Air particulate filters were composited quarterly for each location and analyzed for gamma emitting radionuclides using gamma spectrometry.

Airborne tritium in water vapor was collected by pulling air through a cylinder filled with silica gel.

The cylinders were collected and analyzed for tr itium week ly.

Gross Beta in Air For the period 1981-1984, g ross beta radioactivity was present above de tectable levels in 502 of the 504 air samples collected and analyzed for airborne radioactivity at indicator stations.

The mean value for those samples containing de tectable radioactivity was 0.022 pCi/m3, with a range of 0.002 to 0.182 pCi/m3, For this same period, airborne gross beta was detected in 171 of 171 air samples collected at the control station in Waynesboro.

For those samples collected at the control station, 3

the mean value was 0.023 pCi/m, with a range of 0.007 to 0.149 3

pCi/m,

For the nearest community, Girard, during the period 1981-198 4, gross be ta was de tec ted in 170 of 170 air samples 3

collec te d.

The mean concentration was 0.026 pCi/m, with a range 3

of 0.006 to 0.496 pCi/m,

The maximum gross beta concentrations for all the stations occurred in the last week of September 1981.

13

Air particulate filter analysis results for gross beta are summarized in table 5.

Average results for airborne beta radioactivity over the period of the preoperational program are shown graphically in figure 5 for indicator stations.

Radiciodine in Air Charcoal cartridge analysis results for I-131 are summarized in table 6.

As shown in the table, no airborne I-131 was detected during the period 1981-1984.

Gamma-emitting Radionuclides in Air During the period 1981-1984, three man-made gamma-emitting radionuclides and seven naturally-occuring gamma emitters were found above detectable levels in air samples.

The three man-made radionuclides detected were Nb-95, Cs-134 and Cs-137.

Nb-95 was present above detectable levels in 1 of 41 samples collected at indicator stations; radioactivity in the 3

sample was 8.0E-04 pCi/m.

At the control station, Nb-95 was detected in 1 of 14 samples analyzed at a level of 1.0E-3 pCi/m,

3 No Cs-134 was detected in the 14 samples collected at the control station.

Cs-134 was detected in 2 of 41 samples collected at indicator stations with an average level of 1.5E-03 3

pCi/m, and a range of 1.0E-3 to 2.0E-3 pC1/m,

3 At the control station Cs-137 was detected in 2 of 14 samples collected; the average level of radioactivity was 1.0E-03 3

pCi/m.

Cs-137 was detected in 6 of 41 samples collected at indicator stations; the average level of radioactivity was 3

1.0E-03 pCi/m.

For the nearest community Girard, no man-made airborne particulate radioactivity was detected in any of the 14 samples collected during the period 1981-1984.

The results of gamma spectrometry analysis of air samples are summarized in table 7.

14 i

Tritium in Air Sampling for tritium in air began at Station 16 in August 1983 and at stations 7 and 36 in August 1984.

For the period August 1983 - December 1984, tritium was present at detectable levels in 92 of the 92 samples collected at indica tor stations.

3 The mean concentration of tritium was 150 pCi/m, with a range of 3

8 to 830 pCi/m,

For the control station in Waynesboro during this period, tritium was detected in all of the 21 samples collected.

The 3

mean concentra tion of tritium was 120 pCi/m, with a range of 9 3

to 450 pCi/m,

The maximum concentration for the indicator stations occurred the last week in September 1984 and for the control station the last week in October 1984.

Weekly tritium analysis results are summarized along with the results of the quarterly gamma spectrometry analysis of the particula te filter composites in table 7.

Airborne tr it ium concentration trends over the period of the preoperational program are shown in figure 6.

i 15 l

2.1.2 Direct Radiation Thermoluminescence dosimetry (TLD) has been used continuously to measure dose due to direct radiation in the vicinity of VEGP since August 5, 1981.

TLD stations are located ir each sector near the site boundary and at distances of 4 to 5 miles.

Five of the 4 to 5 mile TLD stations are located on the Savannah River Plant site.

TLD stations are also located at three control locations in the vicinity of Waynesboro.

In addition, TLD stations are placed at locations of special interest which are the community of Girard, the Girard Elementary School, the Georgia Power Company Employee Recreation Area, and a nearby residence located SE of the plant at 3.3 miles.

Locations were selected in accordance with guidance given in Reference 5.

Exact locations of all TLD stations are shown in table 2.

Dosimeters were first installed at stations 1 through 36 during the third quarter 1981; at stations 37 and 38 during the fourth quarter 1983; and at station 43 during the second quarter 1984.

Two TLDs (LiF chips) were placed at each station, and were exchanged quarterly.

Af ter July 1,1983, the TLDs were furnished and analyzed by Teledyne Isotopes Midwest Laboratory.

Prior to July 1, 1983, TLDs were furnished and read by Hazleton Environmental Sciences, Inc. (HES), of Northbrook, Illinois.

(Ef f ective July 1,1983, Teledyne Isotopes acquired HES and the Nuclear Science Department of HES began operation under the nar.e of Teledyne Isotopes Midwest Laboratory.)

During the period 1981-1984, the mean direct radiation dose per quarter at site boundary stations was 15 mrem with a range of 8.8 to 25 mrem; and at four to five-mile radii 14 mrem, with a range of 8.2 to 24 mrem.

For locations of special interest and control locations, doses were within the same range as those reported for the site boundary and four to five-mile radii stations.

l l

16 l

Direct radiation measurement results are summarized in table 8.

Average values for site boundary TLDs, over the preoperational program thus far, are shown by the graph in figure l

l 1

17 l

l l

{

i

=

2.1.3 Milk Milk samples were collected biweekly at the location of the closest milking animal, which was the W.

C.

Dixon Dairy located SE of the plant at 9.8 miles.

Milk Samples were first collected at this station on August 25, 1981.

The milking animals at this location were cows.

In accordance with table 1, milk samples were collected biweekly and analyzed for I-131 and gamma iso topic s.

These analyses are performed by the Center for Applied Isotope Studies, University of Georgia, Athens, Georgia.

Another dairy was in operation briefly during the spring of 1984 at a location approxima tely 4.5 miles SE of VEGP.

Milk sampling was initiated and milk samples were collected May 22, 1984, at this location.

Prior to the next sample collection da te, the dairy operation was discontinued.

No radiciodine was de tected in this milk sample; the only gamma emitter detected was the naturally-occuring K-40.

No I-131 was detected in the 84 milk samples analyzed for radioiodine during the period 1981 through 1984.

Cesium-137 was detected in 6 of 85 samples analyzed for gamma-emi tting radionuclides.

The mean value was 18 pCi/ liter, for those samples containing detectable Cs-137, with a range of 9 to 27 pCi/ liter.

The highest concentrations of Cs-137 were de tec ted in December 1981.

Niobium-95 was detected in 1 of 85 samples at a concentration of 11 pCi/ liter.

Milk sample analysis results are summarized in table 9, for the W. C.

Dixon dairy.

l l

18

2.1.4 Vegetation Grass sampling stations include two indicator locations on the plant site and a control station near Waynesboro.

Exact locations are given in table 2 and shown in figures 1 and 3.

Grass samples were collected initially at Waynesboro and at the simulator building December 29, 1981; and at Hancock Landing April 27, 1982.

The grass sample plot at Waynesboro has been located at the substation on the north side of Georgia highway 80, on the western outskirts of town, since sampling began in December 1981.

Prior to the fourth quarter 1983, this location was included under station number 36, which was the general station number for Waynesboro.

Howeve r, in the fourth quarter 1983, two additional stations were established in the Waynesboro vicinity, primarily as TLD locations.

One of these additional locations was at the electrical substation, very near the grass plot; this location was designated station 37.

Therefore, since the fourth quarter 1983, the Waynesboro grass plot has been considered to be located at station 37.

Grass is collected rather than leafy vegetation because:

grass is available almost year-round, whereas leafy vegetation is available only for about six months of the year; stations may be placed at desired locations with relative ease; and grass is a suitable collector of I-131 and other radionuclides.

Grass samples were collected monthly and dried g rass samples were analyzed by gamma spectrometry for gamma emitting radionuclides in accordance with table 1.

Beginning in January 1984, grass samples were also analyzed for tr it ium.

Analyses were performed by the Center for Applied Isotope Studies, University of Georgia, Athens, Georgia.

Grass sample analysis results are summarized in table 10.

Average results over the period of the preoperational program are illus tra ted in figure 8 for tritium and in figure 9 f or Cs-137, which was selected to represent gamma emitting radionuclides.

l t

19 l

During the period 1981-1984, Cs-134, Cs-137 and Nb-95 were the only man-made gamma-emitting radionuclides detec ted in g rass samples.

Niobium-95 was detected in 1 of 54 samples collected at indicator stations at a concentration of 15 pCi/Kg(wet).

No Nb-95 was detected at the control location.

No Cs-134 was detected at indicator stations.

Cesium-134 was detec ted in 1 of 31 samples collected at the control sta tion at a level of 70 pCi/Kg(wet).

Cesium-137 was detected in 44 of 54 samples collected at indica tor stations.

The mean concentration of the 44 samples with detectable activity was 51 pCi/Kg (wet), with a ranga of 8 to 180 pCi/Kg (we t).

At the control station, Cs-137 was detected in 7 of 31 samples analyzed, with a mean concentration of 36 pCi/Kg(wet) and a range of 14 to 65 pCi/Kg (we t).

In January 1984, analysis of grass samples for tritium was init ia ted.

During 1984, tritium was detected in 21 of 21 grass samples collected at indicator stations.

The mean concentration of tritium was 9.7 E3 pCi/Kg(wet), with a range of 1.7E2 to 1.2E5 pCi/Kg (we t).

The highest concentration at indicator stations occurred in February 1984.

During 1984, tritium was detected in 9 of 10 grass samples collected at the control station.

The mean concentration for the samples in which tritium was detected was 7.8E2 pCi/Kg (we t), with a range of 1.5E2 to 2.3E3 pCi/Kg(wet).

The highe st concen tration at the control station occurred in August of 1984.

20

W.

2.2 Media Af fected by Discharges to the River 2.2.1 River Wa ter Water samples were collected from the Savannah River in accordance with table 1 using automatic sampling equipment.

Samples were collected at two control stations located upstream of the point where VEGP liquid effluent discharges into the Savannah River, and at three indicator stations located downstream of the discharge point.

Sampling locations are presented in table 2 and are shown in figure 2.

River water sampling stations were placed at the specified locations to distinguish between VEGP and Savannah River Plant liquid discharges, as well as to assess the eff ects of VEGP operationc.

River water samples were initially collected from stations 81, 82, 83 and 84 on September 18, 1981; and from station 85 on May 4, 1982.

River water was collected using automatic sampling equipment in which small quantities of river water were collected approximately hourly.

The samples were retrieved from the collectors monthly.

Monthly samples were analyzed f or gamma emitting radionuclides by gamma spectrometry.

Quarterly composites, prepared f rom the monthly samples by station, were analyzed for tritium.

River water samples were analyzed by the Center for Applied Isotope Studies, University of Georgia, Athens, Georgia.

During the period 1981-1984, six man-made radionuclides were detected in samples of river water: H-3, Zr-95, Nb-95, I-131, Cs-134, and Cs-137.

At indicator stations s 134 was detected in 5 of 115 river water samples analyzed.

The mean concentration of the 9amples

~

containing measurable levels of Cs-134 was 4.2 pCi/1, with a range of 3 to 7 pCi/1.

For control stations, Cs-134 was detected in 2 of 82 samples analyzed.

The mean concentration was 9.9 l

pCi/1 for the two samples containing detectable levels of Cs-134 with a range of 4 to 16 pCi/1.

I l

21

Cesium-137 was detec ted in 11 of 115 samples collected at indicator stations.

The mean concen tration of the 11 samples containing detectable Cs-137 was 5.3 pCi/1, with a range of 3 to 17 pCi/1.

At the control stations, Cs-137 was detec ted in 10 of 82 samples.

For the _0 samples containing detectable Cs-137, the mean concentration was 4.9, with a range of 3 to 13 pCi/1.

Tritium was detected in all 39 river water samples collected at indicator stations and analyzed for tritium.

The mean concentration was 1.5E3 pCi/1, with a range of 3.3E2 to 4.3E3 pCi/1.

At control stations, tritium was de tected in all 28 samples analyzed for tritium.

The mean concentra tion was 5.8E2 pCi/1, with a range of 3.lE2 to 1.lE3 pCi/1.

For control and indicator stations the highest tr it ium concentrations in river water were found in river wa ter samples composited over the third quarter 1983.

Iodine-131 was detected in 1 of 115 samples collected at indicator stations at a concentra tion of 5 pCi/1.

No I-131 was de tected in samples collec ted at control stations.

Niobium-95 was detected in 1 of 115 samples collected at indicator stations at a concentration of 4 pCi/1.

No Nb-95 was detec ted in samples collected at control stations.

Zirconium-95 was de tected in 3 of 115 samples collected at indicator stations at a mean concentration of 6.3 pCi/l and a range of 6 to 7 pCi/1.

No Zr-95 was de tec ted at con trol stations.

River water sample analysis results are summarized in table 11.

Average results over the period of the preoperational program are illustrated in figures 10 and 11 for H-3 and Cs-137.

2.2.2 Drinking Water Raw drinking water taken from the Savannah River and finished drinking water taken from the wa ter treatment plan ts, af ter processing, were sampled in accordance with table 1.

Raw drinking water samples were collected monthly from the supplies to the Cherokee Hill Water Treatment Plant (Port Wen twor th,

22

Georgia) and Beaufort-Jasper County Water Treatment Plant (Beaufort, South Carolina), which are the two indicator stations, and f rom the North Augusta Water Treatment Plant (North Augus :a, South Carolina),

which is the control station.

These samples were obtained using automatic sampling equipment which collected cliquots of water approximately hourly.

Finished drinking water was sampled by collecting grab samples of finished drinking water monthly at each of these three locations.

These are the three nearest locations to VEGP where drinking water is taken from the Savannah River.

Sampling locations are presented in table 2 and are shown in figure 4.

Utilizing automatic sampling equipment, composite raw drinking water samples were first collected at North Augusta, South Carolina, November 2, 1983; and at Port Wentvorth, Georgia and Beaufort, South Carolina, January 4, 1984.

Finished drinking water samples were first collected at Port Wentworth, Georgia, November 10, 1981; at North Augusta, South Carolina, January 4, 1983 ; and at Beaufor t, South Carolina, January 4, 1984.

Annual river surveys were conducted to confirm that these locations were the nearest locations where drinking water was taken f rom the Savannah River.

Dates of the annual river surveys are given in table 24.

Monthly composites and grab samples were analyzed for gross beta, I-131, and gamma isotopics.

Quarterly composites were l

analyzed for tritium.

Quarterly composites were prepared from the monthly samples by station.

Drinking water sample analyses were performed by the Center for Applied Isotope Studies, University of Georgia, Athens, Georgia.

Raw Drinking Water Raw drinking water samples were analyzed for gross beta, I-131, tritium, and gamma-emitting radionuclides.

(Tritium analysis of raw drinking water did not begin until January 1984.)

At the indicator stations gross beta was detected in 20 of 26 samples analyzed.

For the 20 samples containing detectable 1

I 23

beta activity, the mean concentration was 2.7 pCi/1, with a range of 1.5 to 5.5 pCi/1.

At the control station, beta activity was detected in 10 of 13 samples analyzed.

The mean concentration of the 10 samples containing detectable beta activity was 1.9 pCi/1, with a range of 1.4 to 2.5 pCi/1.

Tritium was detected in all 8 of the composite samples collected at indicator stations and in all 4 of those collected at the control station.

At the indicator stations the mean tritium concentration was 2.3E3 pC1/1, with a range of 9.7E2 to 3.6E3 pCi/1.

At the control station, the mean tritium concentration was 4.0E2 pCi/1, with a range of 3.6E2 to 4.3E2 pCi/1.

Cesium-134 was detected in 3 of 26 samples collected at indicator stations and none of 13 at the control station.

For the 3 samples containing Cs-104 the mean concentration was 7.0 pCi/1, with a range of 5.0 7 9.0 pCi/1.

Cesium-137 was detected n 1 of 26 samples collected at indicator stations and 1 of 13 at the control station, at concentrations of 7.0 pCi/l and 8.0 pCi/1, respectively.

Thirteen samples collected at the control station and 26 samples collected at indicator stations were analyzed specifically for I-131.

None was detected.

Raw drinking water sample analysis results are summarized in table 12.

Average results over the period of the preoperational program are illustrated in figures 12 through 14 for gross beta, tritium, and Cs-137, which was selected to represent gamma emitting radionuclides.

Finished Drinking Water Finished drinking water samples were also analyzed for gross beta, I-131, tritium, and gamma emitting radionuclides.

At the indicator stations, gross beta activity was detected in 45 of 51 samples.

The mean concentration of the 45 samples containing gross beta activity was 2.9 pCi/1, with a range of 1.3 to 34 pCi/1.

At the control station, gross beta activity was detected in 18 of 26 samples.

For the 18 samples containing detectable gross beta activity, the mean concentration was 1.8 pCi/1, with a range of 1.3 to 2.3 pCi/1.

24

Tritium was detected in all 18 samples from indicator stations and in all 9 samples from the control station.

The mean concentration' of tritium at indicator stations was 2.9E3 pCi/l with a range of 1.0E3 to 5.2E3 pCi/1.

At the control station the mean concentration was 3.8E2 pCi/1, with a range of 2.4E2 to 5.2E2 pCi/1.

Cs-134 was detected in 3 of 51 samples at indicator stations at a mean value of 1.9El pCi/l with a range of 5 to 4.5El pCi/1.

At the control station Cs-134 was detected in 2 of 26 samples at a mean concentration of 7.5 pCi/l with a range of 6 to 9 pCi/1.

Cs-137 was detected in 3 of 51 samples at indicator stations at a mean value of 2.3El pCi/l with a range of 6 to 5.6El pCi/l at the control station, Cs-137 was detected in 3 of 26 samples set a mean concentration of 5.7 pCi/l with a range of 4 to 7 pCi/1.

I-131 was detected in 1 of 45 samples at indicator stations at a level of 7.7E-1 pCi/1.

No I-131 was detected in the 26 samples collected at the control station.

Finished drinking water sample analyses results are summarized in table 13.

Average results over the period of the preoperational program are illustrated in figures 15 through 17 for gross beta, tritium, and Cs-137, which was selected to represent gamma-emitting radionuclides.

2.2.3 Sediment Sediment samples were collected f rom the Savannah River in accordance with table 1.

Samples were collected at two control stations located upstream of the point where VEGP liquid effluent discharges into the Savannah River, and at one indicator station located downstream of the discharge point.

Sediment sampling locations are presented in table 2 and are shown in figure 2.

Sediment sampling stations were placed at the specified locations to distinguish between VEGP and Savannah River Plant ef fects on sediment as well as to assess the ef f ects of VEGP operations.

25

[

I.

Sediment samples were first collected in the vicinity of station 82 and in the vicinity of station 84 August 26, 1981; and in the vicinity of station 81 October 4, 1982.

Sediment samples were collected semiannually.

These samples were analyzed for gamma isotopics by the Center for Applied Isotope S tudies, University of Georgia, Athens, Georgia.

During the period 1981-1984, Cs-137 was detected in 4 of 5 samples collected at the indicator station.

The mean level of radioactivity was 3.2E2 pCi/kg with a range of 6.lEl to 7.8E2 pCi/kg.

At the control stations Cs-137 was detected in 8 of 8 samples collected; the mean level of radioactivity was 1.5E2 pCi/kg with a range of 4.3El to 3.4E2 pCi/kg.

Cs-134 was detected in none of the five samples collected at indicator stations and in 1 of 8 samples collected at control stations at a concentration of 9.3E1 pCi/kg.

Ce-141 was detected in none of the five samples collected at indicator stations and in 1 of 8 camples collected at control stations at a concentration of 8.5El pCi/kg.

Nb-95 was detected in 1 of 5 saiaples collected at indicator stations and 1 of 8 samples collected at control stations at concentrations of 8.2El and 6.8El pCi/kg respectively.

Zr-95 was detected in none of the five samples collected at indicator stations and in 1 of 8 samples collected at control stations at a concentration of 1.0E2 pCi/kg.

Results of sediment sample analyses are summarized in table 14.

Average results over the period of the preoperational program are illustrated in figure 18 for Cs-137, which was l

selected to represent gamma emitting radionuclides.

2.2.4 Fish Beginning in August 1981, samples of commercially or l

recreationally important species of fish were collected l

semiannually from a control station located upstream of the point where VEGP liquid effluent is discharged into the Savannah River and from an indicator station located downstream of the discharge l

26 l

l

1 point.

Fish sampling stations are presented in table 2 and are j

shown in figure 2.

However, these are approximate locations for 1

fish sampling; it is generally necessary to cover a stre tch of i

river up to five miles to obtain an adequa te fish sample.

]

Fish samples were collected using electro-fishing techniques.

Samples were prepared for analys is by filleting the l

fish; only edible portions of the fish were analyzed.

Fish samples were analyzed for gamma isotopics by the i

Center for Applied Isotope Studies, University of Georgia, Athens, Georgia.

During the period 1981-1984, Cs-137 was detected in 15 of 15 samples collected at the indicator station and 12 of 17 samples collected at the control station.

The mean level of Cs-137 in samples collected at the indica tor station was 5.9E2 pCi/kg with a range of 6.3El to 3.4E3 pCi/kg.

At the control station the mean level of Cs-137 was 3.4E2 pCi/kg with a range of 6.4El to 1.5E3 pCi/kg, for those samples containing detectable levels of Cs-137.

Cs-134 was de tec ted in none of the 15 samples from indicator stations and in 2 of 17 samples collected from control stations at a mean concentration of 1.0E2 pCi/kg with a range of 2.3El to 1.9E2 pCi/kg.

Nb-95 was detected in none of the 15 samples collected at indicator stations and in 1 of 17 samples collected at control stations at a concentration of 3.4El pCi/kg.

Results of fish sample analyses are summarized in table 15.

Average results over the period of the preoperational program are illustrated in figure 19 for Cs-137, which was selected to represent gamma emitting radionuclides.

27

2.3 Groundwa te r Groundwa te r is being monitored as part of the preoperational radiological environmental moni to. '79 program.

However, liquid releases f rom VEGP will only be made to the Savannah River via the discharge canal and g roundwa ter is not

. expec ted to be af fected by normal plant operations.

Groundwater sampling locations are presented in table 2 and shown in figure 1.

Due to the characteristics of groundwater flow, it is inappropriate to apply the concept of control and indicator stations to groundwater sampling locations.

Groundwa ter sampling locations are categorized in accordance with the aquifer sampled.

At VEGP, groundwate r is sampled from both the local unconfined aquifer and the regional confined aquifer.

Collections are made near the nuclear power block where any groundwater centamination would likely occur.

The unconfined aquif er is also sampled at locations approximate to where any contamination would more likely be eventually released to the public.

Groundwater sample collection began at sample locations 51, 61, and 62 in August 1982, and at location 63 in July 1983.

Changes made in groundwater sampling locations prior to December 31, 1984, are discussed in Section 4 of this report.

Groundwater samples were collected and analyzed in accordance with table 1.

Grab samples were collected quarterly at each of the groundwater sampling stations.

These samples were analyzed for tritium and gamma isotopics by the Center f or Applied Isotope Studies, University of Georgia, Athens, Georgia.

During the period 1982-1984, tritium was de tected in 14 of 14 samples collected from the local unconfined aguifer and analyzed for tritium.

The mean tritium level was 2.3E3 pCi/1, with a range of 1.3E3 to 3.8E3 pCi/ liter.

Tritium was detected 2 of 13 samples collected f rom the regional confined aquifer; the mean value was 2.6E2 pCi/l with a range of 2.4E2 to 2.8E2 pCi/1.

28

. ~

~

Cs-137 was detected in 2 of 17 groundwater samples taken f rom the local unconfined aquifer and analyzed by gamma spectrometry; the mean value was 3.5 pCi/1 with a range of 3.0 to 4.0 pCi/1.

Cs-137 was detected in 2 of 13 samples taken from the regional confined aquif er.

The mean value was 5.5 pCi/l with a range of 3.0 to 8.0 pCi/1.

Cs-134 was detected in 1 of 13 sampled collected from the regional confined aquifer at a concentration of 5.0 pCi/1.

Cs-134 was detec ted in none of the 17 samples taken from the local. unconfined aquifer.

Results of groundwater samples analyses are summarized in table 16.

Average results over the period of the preoperational program are shown in figure 20 for tritium and figure 21 for Cs-137, which was selected to represent gamma-emitting radionuclides.

i l

29

i

~3.0 Deviations from the Program 3.1 Deviations During 1981 Medium Date Deviation Air 11/23/81 Sample was not collected at Station 36 due to sample pump malfunction.

TLD Third Quarter /81 Dosimeter at S tation 23 was lost in the field.

Milk 11/10/81 Sample was not available f rom supplier at Station 98.

3.2 Deviations During 1982 Medium Date Deviation Air 3/1/82 Electrical power was lost at S tation 16.

Therefore neither gross beta nor I-131 samples were available.

Air 7/6/82 Air particulate filter was reported missing by the contract laboratory for S tation 7.

Air 8/31/82 Neither air particulate sample nor I-131 was collected at Station 7 due to sampling system malfunction.

30

Medium Date Deviation TLD First Quarter /82 Dosimeter at S tation 1 was lost in the field.

TLD First Quarter /82 Dosimeter at Station 23 was lost in the field.

Milk 4/27/82 Sample not available from rupplier at S tation 98.

Grass 1/82 Insufficient grass on plots at Station 7 and 36.

Grass 3/82 Insufficient grass on plots at Station 7 and 36.

Grass 5/82 Insufficient grass on plot at Station 7.

Grass 6/82 Insufficient grass on plot at Station 7.

Grass 11/82 Insufficient grass on pl. s at Station 7,16, and 36.

Grass 12/82 Insufficient grass on plots at Station 7 and 16.

i Drinking 11/10/81 Although sample collection Water through began at Port Wentworth on (Finished) 4/13/82 11/10/81, I-131 analysis was not initiated until May 1982.

31

Medium Date Deviation Drinking 10/12-82 Sample was lost in Water processir.g by vendor (Finished) laboratory prior to I-131 analysis.

Sediment 1/6/82 No sediment sample was collected 8t S tations 81, 82, and 84..

Groundwater Fourth Quarter /82 No samples were collected at S tations 51, 61, and 62.

Sampling locations were being reevaluated.

3.3 Deviation During 1983 Medium Date Deviation Air 1/3/84 Environmental sampling program vehicle was burglarized and air particulate and I-131 samples stolen for Stations 7, 10, 16, 35, and 36.

Tritium samples for station 16 were also stolen.

(These were samples collected during the last sampling period of 1983.)

Air 8/16/83 New lodine collecting cartridges did not fit sample holders.

Therefore the same cartridges were 32

Medium Date Deviation left in place to cover a two-week sampling period for S tations 7,10, 16, 35, and 36.

Air 2/1/83 No air particulate filter nor I-131 sample was collected at Station 35 due to sample pump malfunction.

Air 8/16/83 and Break through occurred 8/23/83 with the sample collecting medium for Station 16, therefore sample analysis results were invalid.

TLD First Quarter /83 Dosimeter for S tation 28 was lost in the field.

TLD Fourth Quarter /83 Dosimeter for S tation 22 was lost in the field.

Milk 4/25/83 No analysis for I-131 was performed due to lack of 1

preservative in milk sample.

Grass 1/83 Insufficient grass on plots at S tations 7, 16, and 36.

Grass 2/83 Insufficient grass on plots at S tations 7 and 16.

1 33

Medium Date Deviation Grass 5/83 Insufficient grass on plot at S tation 7.

Drinking Fourth Quarter /83 Contract laboratory inad-Water-Raw vertently combined the Fourth Quarter 83 with the First Quarter 84 composite for Station 80.

Sediment 1/6/83 No sediment samples were collected for the first half of 1983 from S tations 81, 82, and 84.

Groundwater First and Second No groundwater samples Quarter / 83 were collected from S tations 51, 61, and 62.

Sampling locations were being reevaluated.

t 3.4 Deviations During 1984 Medium Date Deviation l

Air 7/31/84 Both air filter and I-131 sample was lost from Station 10.

l Air 9/18/84 Air filter was lost from Station 36.

Air 9/25/84 Sample results not i

available for S tation 16 due to sample pump malfunction.

34 1

Medium Date Deviation TLD First Quarter /84 Dosimeter at S tation 16 was melted by brushfire in the. area.

Grass 1/84 Insufficient grass.on plots at Stations 7, 16, and 36.

Grass 3/84 Insufficient grass on plots at Station 16.

Grass 12/84 Insufficient grass on plots at Station 36.

i l

l 35

4.0 Program Changes During 1981-1984 changes were made as necessary to improve and/or enhance the VEGP preoperational radiological environmental.

monitoring program.

In some cases stations were relocated due to sampling dif ficulties.

However, the most significant changes involved expansion of the basic progran to include supplemental media, locations, and analyses in response to continual review and assessment of program needs and results.

4.1 Air Sampling Tritium samplers were added at station 16 (Hancock Landing Road) in August 1983; and at stations 7 and 36 (simulator building and Waynesboro) in Augus t 1984.

4.2 Direct Radiation TLD stations 37 and 38 were added in Waynesboro as control utations fourth quarter 1983.

TLD station 43 was added at the Employee Recreation Area second quarter 1984.

4.3 River Water The locations of water sampling stations 82 and 83 did not actually change but the location description changed slightly.

The location description of station 82 was changed from river mile 150.9 to 151.2; the location description of station 83 was changed from 150.4 to 150.6 4.4 Grass The location of the grass plot in Waynesboro did not change but the station identification number for the grass plot was changed from 36 to 37 when station 37 was established fourth quarter 1983.

36

i 4.5 Groundwater The location of groundwater station 62 was changd from the bluff near river mile 150 to a spring near the combustion turbine facility, with both locations sampled on October 4, 1983 and January 3, 1984.

However, a more suitable spring was located near the discharge structure and groundwater sampling began at 4

this location on April 3, 1984.

This location was then desig-nated station 62 and groundwater sampling continued through 1984.

Sampling of groundwater from Construction Well Number 1 (Station 63) was discontinued in October 1984.

37

-.,,-,..,.m,,-.,.-_.--._n-.c.,,. -,--,.,.. -.

._,_a

5.0 EPA Intercomparison S tudies (Crosscheck) Program The laboratory which performed the analyses included in table 1, the Center for Applied Isotope Studies, University of Georgia, participated in EPA's Environmental Radioactivity Laboratory Intercomparison S tudies (Crosscheck) Program conducted by the Environmental Monitoring and Support Laboratory, Las Vegas, Nevada.

Not all of the sample media / analysis combinations listed in table 1 are covered by the Crosscheck Program.

Relevant participation is considered to consist of those analyses of sample media covered by the EPA Crosscheck Program which are the same as those found in table 1.

For VEGP those sample analyses are gross beta, I-131, gamma emitting radionuclides, and tritium in water; gross beta and Cs-137 in air filters; and I-131 and gamma emitting radionuclides in milk.

Reported in tables 17 through 28 are the results of relevant participation in the crosscheck program for 1981-1984.

Terms used in the column headings of these tables are defined as follows:

"Date" means the collection date given by the EPA, "Known" refers to the EPA known value i one standard deviation, s; "Resolution" is determined by dividing the known value by its s value; "Result" is the value determined by the participating laboratory; "Ratio" equals the "result" divided by the "Known".

Agreement or disagreement between the "known" and the "result" is determined by referring to the NRC's "Criteria for Comparing Analytical Measurements", which is reproduced in table 29.

It should be noted that whenever the EPA known value is zero or the laboratory result is a "less than" value, no comparison can be made by the NRC criteria since the ratio cannot be determined.

For the water sample dated 6/3/83, gamma spectroscopic analysis for Zn-65 resulted in "No Agreement" as defined in table 29.

This analysis result is shown in table 25.

Following recalibration of the gamma spectroscopic inst 3 mentation, the f

water sample was reanalyzed; results of reanalysis are also shown in table 25.

33 i

6.0 Land Use Surveys and River Surveys Surveys were performed annually 1981 through 1984 in the vicinity of VEGP to determine, in each of the sixteen sectors and out to a distance of five miles, the locations of the nearest residence, the nearest milk animal, the nearest meat animal, and the nearest Vegetable garden.

Results of these surveys are presented in tables 30 through 33.

Surveys of the Savannah. River were performed in December 1981, August 1983, and October 1984 to confirm that the nearest drinking water users were those reported in the VEGP Environmental Report - Operating License Stage and currently being sampled.

39

7.0 Conclusions At this point in the preoperational radiological environmental monitoring program no attempt to draw conclusions has been made.

40

References 1.

Vogtle Electric Generating Plant, Unit 1 and Unit 2, Environmental Report - Operating License Stage, Georgia Power Company.

2.

U.S. Nuclear Regulatory Commission, Standard Radiological Effluent Technical Specifications for Pressurized Water Reactors, NUREG 0472, Revision 3 (Draf t), January 1983.

3.

U.S. Nuclear Regulatory Commission, Programs for Monitoring Radioactivity in the Environs of Nuclear Power Plants, Regulatory Guide 4.1, Revision 1, April 1975.

4.

U.S. Environmental Protection Agency, Office of Radiation I

Programs, Environmental Radioactivi ty Surveillance Guides, ORP/SID 72-2, June 1982.

5.

U.S. Nuclear Regulatory Commission, Radiological Assessment Branch, Branch Technical Position on Radiological Monitoring Program, Revision 1, November 1979.

6.

U. S. Nuclear Regulatory Commission, Environmental Technical Specifications for Nuclear Power Plants, Regulatory Guide 4.8, for comment, December 1975.

41

TABLE 1 (SHEET 1 OF 4)

RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Sample Medium and Location Frequency Analysis Airborne particulates Continual sampler Radioiodine radioiodine, and tritium (b) operation with cannister:

sample collection I-131 Indicator stations weekly 7 - Simulator Particulate building sampler:

(1.5 miles SE) gross beta activity 10 - Meteorological following tower filter changer (a)

(1.1 miles SSW) composite by location) for 16 - Hancock gamma isotopic Landing Road quarterly, tritium (b)

(1.4 miles NNW)

Nearest community 35 - Girard (6.6 miles SSE)

Control station 36 - Waynesboro (15 miles WSW)

Direct radiation Quarterly Gamma dose Thermoluminescent dosimeters (See table 2 for exact locations)

Indicator S tations 1-16 Site boundary 17-32 4 to 5 mile ring Locations of Special Interest 33 Nearby residence 34 Girard Elementary School 35 Girard 43 Employee recreation area 42 S

,,,__--.--.y---,7

4 TABLE 1 (SHEET 2 of 4)

Sample Medium and Location Frecuency Analysis Control Stations 36 Waynesboro 37 Substation (Waynesboro)

(North side of road) 38 Substation (Waynesboro)

South side of road)

River water Ccmposite sample Gamma isotopic over monthly monthly; Control stations period composite for tritium 81 - River mile 153.1 quarterly 82 - River mile 151.2 Indicator stations 83 - River mile 150.6 84 - River mile 149.5 85 - River mile 146.7 Drinking water Monthly Gross beta, I-131, and Control station gamma isotopic monthly; 80 - North Augusta composite for Water Treatment tritium Plant quarterly Indicator stations 87 - Jasper Water Treatment Plant (Beaufort, SC) 88 - Cherokee Hill Water Treatment Plant (Port Wentworth, GA) 43

TABLE 1 (SHEET 3 of 4)

Sample Medium and Location Frequency Analysis i

Sediment from Semiannually Gamma isotopic shoreline Control stations 81 - River miles 153 to 154 82 - River miles 151 to 152 Indicator station 84 - River miles 148.5 to 150.5 I

Milk Biweekly Gamma isotopic and I-131

~

98 - W. C. Dixon 4

Dairy (9.8 miles SE) 5 Grass Monthly Gamma isotopic Indicator stations 7 - Simulator i

building l

(1.5 miles SE) 15 - Hancock Landing Landing Road

]

(1.5 miles NW)

{

Control station 37 - Waynesboro (15 miles WSW)

}

I 4

t 1

3 44

,,,,,-,--m.,.,v_,

,_---,.--n-,_

-,--_,,-,-,,,vy

,...,,...-,,,,,-ww.y

.._,,r____,.__,_,_-

-___.y___

..m, -. _

TABLE 1 (SHEET 4 of 4)

Sample Medium and Location Frecuency Analysis Fish Annually Gamma isotopic on edible Control Station portions of composites of 81 - River miles 153 any commercial to 158 or recreationally important species, Indicator station such as bream or catfish 85 - River miles 144 to 149.4 Groundwater Quarterly Gamma isotopic and tritium Regional confined analyses aquifer 51 - Makeup well number 1 (0.4 miles N) 63 - Construction Well number 1 (0.4 miles SW)

Local unconfined aquifer 61 - Spring water from upper end of Mallards Pond (0.8 miles NW) 62 - Spring water f rom bluff near river mi 150 (1.1 miles E)

(a) Particulate sample filters should be analyzed for gress beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.

If gross beta activity is greater than ten times the mean of control sample for any medium, gamma isotopic analysis should be performed on that individual sample, (b) Tritium samplers are located at stations 7, 16, and 36 and are exchanged weekly.

45

TABLE 2 (SHEET 1 OF 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLE NUMBER LOCATION (MILES)

TYPE 1

Hancock Landing Road N

1.1 D

2 River Bank NNE 0.8 D

3 River Bank NE 0.7 D

4 River Bank ENE 0.8 D

5 River Bank 2

1.0 D

6 Plant Wilson ES E 1.1 D

7 Simulator Building SE 1.5 D,V,A 8

River Road SSE 1.1 D

9 River Road S

1.1 D

10 Met Tower SSW 0.8 A

River Road 1.1 D

11 River Road SW l.2 D

12 River Road WSW l.1 D

13 River Road W

1.3 D

14 River Road WNW l.8 D

15 Hancock Landing Road NW l.5 D,V 16 Hancock Landing Road NNW l.4 D,A 17 Savannah River Plant River Road N

5.4 D

18 Savannah River Plant D Area NNE 5.0 D

19 Savannah River Plant Road A.13 NE 4.6 D

20 Savannah River Plant Road A.13.1 ENE 4.8 D

21 Savannah River Plant Road A.17 E

5.3 D

22 River Bank Downstream of Buxton Landing ESE 5.2 D

23 River Road SE 4.7 D

24 Chance Road SSE 4.9 D

25 Chance Road and Highway 23 S

5.2 D

26 Highway 23, mile 15.5 SSW 4.6 D

27 Highway 23, mile 17 SW 4.8 D

28 Claybon Road WSW 5.0 D

i 29 Claxton-Lively Road W

5.0 D

30 Ben Hatcher Road WNW 4.7 D

31 River Road at Allen's Church Fork NW 5.0 D

32 River Bank NNW 4.8 D

33 Nearby Residence SE 3.3 D

34 Girard Elementary School SSE 6.3 D

35 Girard SSE 6.6 D,A 36 Waynesboro WSW 15.0 D,A 46

TABLE 2 (SHEET 2 OF 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS LOCATION DESCRIPTIVE DIRECTION DISTANCE SAMPLE NUMBER LOCATION (MILES)

TYPE 37 Substation (Waynesboro)

(North Side of Road)

WSW 17.5 D,V 38 Substation (Waynesboro)

(South Side of Road)

WSW 17.5 D

43 Employees Recreation Area SW 2.2 D

51 Makeup well N

0.4 G

number 1 61 Springwater from NW 0.8 G

upper end of Mallards Pond 62 Spring Water from E

1.1 G

bluff near river mile 150 63 Construction SW 0.4 G

Well number 1 80 North Augusta Water Treatment Plant Upstream 51 W

81 Savannah River (mile 153.1)

Upstream 2.2 R,F(2),

S (3 )

82 Savannah River (mile 151.2)

Upstream 0.2 R,S (3) 83 Savannah River (mile 150.4)

Downstream 0.6 R

84 Savannah River (mile 149.5)

Downstream 1.5 R,S (3) 85 Savannah River (mile 146.7)

Downstream 4.3 R,F(2) 87 Beaufort-Jasper Water Treatment Plant; Beaufort, S.C.

Downstream 112 W

88 Cherokee Hill Water Treatment Plant; Port Wentworth, Ga.

Downstream 122 W

98 W. C. Dixon Dairy SE 9.8 M

47

TABLE 2 (SHEET 3 OF 3)

RADIOLOGICAL ENVIRONMENTAL SAMPLING LOCATIONS 1

TABLE NOTATION:

(1)

Sample Types A - Airborne Radioactivity D - Direct Radiation F - Fish G - Groundwater M - Milk R - River Water S - River Shoreline Sediment V - Vegetation i

i W - Drinking Water (at water treatment plant)

(2)

These are approximate locations for fish sampling.

It is generally necessary to cover a stretch of river up to five miles to obtain an adequatt fish sample.

(3)

These are approximate locations for sediment sampling.

High water may sometimes cause an otherwise suitable location for sediment sampling to be unavailable.

l 4

l 1

48

TABLE 3 1

(SHEET 1 OF 3)

DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSES (Lower Limit of Detection)

Airborne Particu-late or Fish Grass Sediment Water Gas (pci/kg)

Milk (pCi/kg)

(pCi/kg)

(p 3

ANALYSIS

_ Ci/1)

(DCi/m )

(we t)

(pCi/1)

, (wet)

(dry)

Gross 4

0.01 beta H-3 2000 Mn-54 20 100 Fe-59 30 300 Co-58 20 100 Co-60 20 100 Z r.-6 5 30 300 Zr-05 30 Nb-95 20 I-131 20 (b) 0.07 1

60 Cs-134 20 0.05 100 20 60 200 Cs-137 20 0.06 200 20 80 200 Ba-140 60 60 La-140 20 20 49

TABLE 3 (SHEET 2 of 3) a.

The lower limit of detection (LLD) is the smallest concentration of radioactive material in a sample that will be detected'with 95 percent probability, with 5 percent probability of falsely concluding that a blank observation represents a "real" signal.

For a particular measurement system (which may include radiochemical separation):

4.66 s b bbD " E V 2.22 Y exp FA at) wheret LLD The a priori lower limit of detection as defined

=

above (as pci per unit mass or volume),

h The standard deviation of the background counting s

=

rate or of the counting rate of a blank sample as appropriate (as counts per min).

E

=

The counting efficiency (as counts per transformation).

V

=

The sample size (in units of mass or volume).

2.22 The number of transformations per minute per pCi.

=

Y The fractional radiochemical yield (when

=

applicablo).

A The radioactive decay constant for the particular

=

radionuclide.

At The elapsed time between sample collection (or end

=

of the sample collection period) and time of counting.

The value of sb used in the calculation of LLD for a detection system shall be based on the actual observed variance of the background counting rate or of the counting rate of the blank samples (as appropriate) rather than on an unverified theoretically predicted variance.

In calculating the MDC for a radionuclide determined by gamma-ray spectrometry, the background shall include the typical contributions of other radionuclides normally present in the samples (e.g., K-40 in milk samples).

50

i TABLE 3 (SHEET 3 of 3)

Typical values of E, V, Y and At should be used in the evaluation.

It should be~ recognized that the LLD is defined as an a priori (before the fact) limit, representing the capability of a measurement system and not an a posteriori (af ter the f act) limit for a particular measurement.

b.

The LLD for I-131 is 1 pCi/1 for drinking water samples.

51

TABLE 4 DETECTION LEVELS ROUTINELY ACHIEVED FOR ENVIRONMENTAL SAMPLS ANALYSES (Lower Limit of Detection (LLD))

AIR WATER PARTICUgATE FISH MILK GRASS SEDIMENT (pCi/1)

(pC1/m )

(pCi/kg-we t) (pCi/1) (pC i/kg-we t) (pCi/kg-dry)

Gross

1. 5 ( a) lE-2(e) bsta H-3 100 (b)

Mn-54 10 (c) 40(g)

Co-58 10 (c) 50(g)

Fe-59 18(c) 100(g)

Co-60 10 (c) 50(g)

Zn-65 20(c) 100 (g)

Zr-95 20 (c)

Nb-95 10 (c)

I-131 15(c) 4E-2 ( f) 25 (h) 25(j)

I-131 0.4 (d) 0.3 (i)

Cs-134 15 (c)

1. 5E-3 ( f) 50 (g) 20(h) 25(j) 30 (k)

Cs-137 10 (c)

1. 2E-3 ( f) 40(g) 16(h) 20(j) 30(k)

Bc-140 50 (c) 90(h)

La-140 15(c) 20(h)

Sample Size Count Time (min)

Background Rate (cpm)

(c) 500 ml 50 1.1 (b) 25 ml 800 3.95 (c) 1.0 1 100 (d) 1.5.1 333 4.5E-3 3

(e) 600 m 100 1.1 3

(f) 7800 m 100 (g) 0.75 kg 100 (h) 1.0 1 333 (i) 2.0 1 333 4.5E-3 (j) 1.0 kg (wet) 167 (k) 0.75 kg 100 3

l f

52

s Table OS s

Sumenar y of Gs os2. Heta Acttvity Detected in A6: borne Parttculates Grcss Beta (pct /M3)

Name of facilety - Vmitle Dochet 64 0. 50-424.425 Locatton of fact 1Ity - Waynesboro Geos g ta Reporting Pertod - 1981-84 4ocatton N/No Mean

• Std Men Max LLD Locatton weth Number of Highest Non-Routene Annual Mean Observattons Control Location 17t/171 0.023 +

0.015 0.007-O.149 Waynesboro 15.0 Miles WSW Indicator Stattons 502/504 0.022 i O.013 0.002-O.182 Hancock Landing f.5 Miles NNW Nearest Community 170/170 0.026 i O.042 0.006-O.496 Girard a

6.6 Miles S$W NOIE:

Astertsk for all values indicates re s toruscl ide not detected insamples g

tah (N/No) fraction denotes rumnber of positive results over number of analyses perforsned

• • - tower Ltoits of Detection are listed in Table 4

)

i e

Table 06 Summary of Iodine 131 Activity Detected in Atr Cartridge FSIters Iodine 931 (pC4/M3)

Name of Factitty - Vogtle Docket No. 50-424,425 L ocat ion of Facettty Waynesboro Georgia Reporting Period - 1981-84 Location N/No Mean + Std Min Max LLD Location with teamber of Highest Non-Routine Annual Mean Observations Control Location 0 /170

<O.044 +

<O.051

<O.037-<O.657 No Location had Activity > LLO Indicator Stations O /502

<0.041 +

<O.048

<O.Ol7-<O.674 No Location had Activtty > LLD Nearest Community O /169

<O.041 1

<O.049

<O.087-<O.609

++

No Location had Activity > LLO NOTF:

og Astertsk for all values Indicates radtonuclide not detected insamples ta

{N/No) f ract ton denoters runnber of pos i t I ve resu l t s over rusmber of analyses performed

• • - Lower Ltmits of Deteetton are listed in Table 4

m,

s e

e C

C

.e b

k k

O*

L3*LLt a

g 0

0 i

z g

C 0

9

• z eiemo3 *

• e D ae e

=* W 6e i to i 3 me e

ma 2 X

e

- i i

Om NN m

oa N=

m e e

.a O. O.

O. O.

O.

O. O.

O. O.

O.

e Vi e

ww ww w

ww ww w

0e i

O. O

. o.

. O.

O. O.

o. m O.

-e ecw e

o e L i-C

~ea*

=

0-~

~wa

-~

Oma N-a na te oc aggi w

w

=

v w

w w

Ae 6-N

=

=

=

i -*

+1i N i

+le N

+1e N

+1e N

+1 N

+1e N ela N

+1i N e

Di Ce Ze O

N N

w N

Ce oU CC-a mm nON mm mm NN*

mm

..uo 9

4-00-0, 0, - 0 0. -

00-0 0. - 0 0. -

8, s ez e

w L e X

i ww ww ww ww ww ww o

N c.e OO w0 00 00

5. h.

O. O.

w e e i

ei e

==

• m Mm oN mm o ae e

o e

.e o.

6 e

e 2

+

i A

W i

i e

e e

6

=

a e

e O.

b.o.

O. O.

O.

O.

O. O.

O.

m M

NN v

M N-M e

o e

e i =

e a

w ww ww w

w ww w

.L gcwa.'

. O.

O. O.

e

' ~

O.

. O.

c. m O.

wm e

4

eI2s eon Na 0-~

Nea ma na N-~,

ca e

M w

9 m

C E

w e.

s e.

N

=

=

=

=

< +ie z

+ii N

+l.

N

.i. N

.ie N

.se N

.i. N

.i. N

-e a

m e

w e

e

- CC e

mm mm NON ww mM NN=

mm e =

9-00-0 0. - 0 0. - 0 0. -

0 0. - 0 0. - 0 0. -

U m e

t tI i

e i X

CX e

ww ww ww ww ww ww ww N.

.O O. O.

O. O.

9. O.

O. O.

O. O.

o. N.

O. O.

i g

u i :

NN

~~

ne em nn om we N

C, e

i e

o -

e O

e f

a.

3 C

e O U i =

c e

3 3

3 CL

- e >

a 3

C e

w e

w e

w e

tg D

E 8

4Ce e

e e

e e

e C e.

4 e

C 0e 4

x U

e O

@= e Le 6 m Le Le Le Le we t

e U*+

0e 6e

.o e e.e Ct ee e

C gCya w

w e

3-3 3-4-

U

+

4 8 eta g-o=

g-0-

g-o-

v-C U e U 9 ea 02mL

-I

-I

-E

>I

~E

-E QE O

e 3

s a

e y

a s

-1

-ce Ec

• c Bc we Em

• d oc V

e S

i

( O e

t6 t6 9&

9 -

e

@~

3

@w 1

3 e

.e L

e o

O e

e w

0 a

i C

L

-44 e

O e

i O.

y e

I L e 0e e

3

@ i C

wm Om nN v

m N=

mm e

Oi 0

O. O O O.

00 O.

O.

O. O.

O. O.

e

+

0i i

ww ww ww w

w ww ww g

U L

• 4

-0

0. O.

o. m.

. o.

O.

. O.

-m g

g go y Vx e

0-~

-ma ma Na N-a N@a e

w u e o=ga

• N N a.

E e

-wego.

N 4

m t*-

2i 9

w m

9 w

w w

0 Ce 4 6 +1e N s

+1* N

+1* N

+1e N

+1i N

+le N

+6s N

+1s N se C

2i N

N N

g g e

• CC=i nm mm NOe ww mm NNw mm E

3*

4 9-00-00-0 0. - 0 0. -

0 0. - 0 0. - 0 0. -

g U t3 s

e e

2 e e X

e ww ww ww ww ww ww

.w w y

o. O OO i

o. O.

O. O.

O. O.

w N.

u ' O.

di

• ' e

=

-=

• a 40 m NN OM wm

-e e

.s e

U*

i ge w i

C e

we -

a E o

a w s -

-a i

Oe J**C e

O U.d e

Ci L 6a e

o e

e o

e o

e oe a w-i e

e e

e e

e e

- e 3 g

e

• O Q 4 *.a a

Ue e

0+

Wi w.

e t

V e

4 4

wet i

E 6

a o-a 3

e aL e

C w

a-m v

g>O C

m m

e 9

N 3 =.

m.

C.

N N

N a

w-*

a

,s6 i

• • C&

a e

p g

U t

44 v

U Z

4 CQ CD t

55

TablO OF Arwma l Summary f or Spec t f sc Radionu;;:1 ides in Atr Samples (Activety - pct /M3)

Name of Factlety - Vogtle Docket No. 50-424.425 Location of Factitty - Waynesboro Georgia Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysis of Indicator Locattons Locatton wtth Highest Antmal Mean Locattons

.Non-Routtne Performed Detection Mean + Std Name Mean

• Std Mean

• Std Reported (LLD)

Men - Max osstance and Men - Max Min - Max Measurements (N/NO)

Otrection (N/No).

(N/No)

K-40 2.tE-02 +

4.7E-03 Met Tower 2.8E-02

• 3.2E-02 +

1.8E-02 None 1.7E-02 2.8E-02

.75 Miles SSW 2.8E 2.8E-02 1.9E 4.5E-02

( 4/48)

( t/t4)

( 2/14)

Pb-212

+

+

+

+

None e

e e

e e

e t O/41)

( O/ O)

( O/94)

Pb-214

+

+

+

Novie on

( O/48)

( Of O)

( O/94) os fl-208 3.OE-03 1 3.5E-03 Met Tower 4.OE-03 1 4.2E-03 1

None 8.OE 7.OE-03

.75 Miles SSW 8.OE 7.OE-03

( 3/48)

( 2/94)

( O/14)

NOTE:

Astertsk for all values indicates radionuct$de not detected insamples (N/No) fraction denotes number of positive results over number of analypes performed

• = - Lower Limits of Detection are listed in Table 4

m i

e e

.i C

C i

t w-V$

. oweE 8,

g g

)

I

)

e 3-e e

o 5

5 o

5 w*

Lo66 e

2 2

2 2

2 to i e a, 0 3

.s qe s

e e

cee i ao e jae e

et E

e

- e i

or NN m

om na m

i s

O. o oo o

o. o.

oo O.

i

++

e +

Ve e

ww ww w

ww ww w

oe 4

o. o

. o.

. o.

o. o.

o. m

. o.

=.

pg,x L

-C g=.

=

o..

.w=

-=

on=

N,a n=

te O.C M I S *i w

w w

w gi 6

N

+ti s a

+l+ N

+1a N

.li N

+le N

.li N

+la N

+1 N

CP e Ce N

Ce oo CC2e o

N

=

N

=

e mm NON mM Mm NN-mM w

-e vC e-e O. o. w

o. o w c. o -

0 0. - 00w c o. -

en e

.e

+

e w

b +

2 e

ww ww ww ww ww ww O.e

.e oo N o.

00 00

r. N.

00 N

a.

w F

-m em cN mm o a8 e

o e

s e

i a

i a

e O

W 8

i e

0 e

i 2

s e

a o

e i

E O

i a

4 0

a e

e e

s.

L

~

e i

e

.C l

e i

b a

e e

6.=

-m i

o

-C2 a

N e

e u

i h

N e.

k o

-Uw i

e ou i

e e

e 1

1m>

e

.i D

is e

• g 6

i e

m U4>

+

e

-i

[

+e.

i e

• t+

e i

- u e

i 5

L4 6

C=

a w

e a

y e

e e

+

I e

Lw i

i 8

o-S 3

• 3 0

m e

e g

>t c

i

-e O

La y

c Oe i

I L

• i 0*

i 2

'.g

• i N.

mm e

w e

o o, o, o.

e e

C*

a ww ww 9

u 6

• e

.o

o. c.

j e oe Dx e

g w

Di Rw ga s

=

=

=

=

=

m,=

.c=

ee t0Imi w

w o

w w

w w

g w

ee o

fe O

Ca U +1e N *

• te N

+1i N

+1e N

+te N

+1 N

+1i N

+t. s we 2i o

o o

o o

m e

ei

• CC-*

NNe mm.

E 3 i a e-i

o. o.

o. o.

9 i

e e3 2

6 I i

ww ww e

e

e. e.

o. o.

g i

-e i

cN wm

-e e

eim 6 a

. e i

uo ge.

w a - C e

.E

.O e

e w a

=

e O'wwwQ i

i O V.J e

Ci L tw

.a e

Oe t w.

- e 3 e

s

• e 0 o e

n *.e g.

e Q*

ae e

v V

i e

C e * @ @

E 6

+ 0-E 3

a w

t-e w

a6 i edo

,i e

m m

o q

N CL -

• I m

2 N

r=

N i

i a

>gL i

e e

m i

e i

e i > C4 m

2 g

U t

=

44 U

U 2

4 CC CD a

i 57

Tablo 07 Armual Summary for SpeCtfic Radionuclides in Atr Samples Results for Nearest Community (Activity - PC4/M3)

Name of Fac4tity - Vogtle Docket No. 50-424,425 Location of facitety - Waynesboro Georgia Reporting Period - 1983-84 Type of Lower Ltatt Control Number of A na l ys t s of Nearest Community locations Non-Routine Performed Deteciton Mean + 5td Mean + 5td Reported (LLD)

Men - Max Min - Max Measorements (N/No)

(N/No)

K-40 9.3E-u2 +

3.2[-02 +

1.8E-02 Pkwwr 1.3E-02 I 9.3E-02 f.9E-02 7 4.5E-02

( t/14)

( 2/s4)

PD-212 3.tE-02 +

+

+

+

+

None 3.1E-02 7 3.1E-02 T

+

( t/14)

( O/14)

Pb-214 7.OE-03 +

4.2E-03

+

+

None 4.OE 1.OE-02 (n

( 2/94)

( O/t4)

CD 18-208 1.2E-02 +

None 1.2E-02 7 1.2E-02

( 1/14)

( O/94)

NOTE:

Astertsk for all values indicates radionucitde not detected insamples (N/No) fraction denotes number of posi t ive resul ts over rumber of analyses performed

• • - Lower Ltmots of Detection are listed in Table 4 l

l i

r e

e Q

Fe e Q.C b

Ce we Q

We w D..e

.e

s. 5 *a w n s

e ea ee

@ e c: L>e e

e o

e e

e e

e e

- e Ot e

}.h..

e o.

O.

e De Ce 00 O. O.

oe e

++

= e e

ww ww Le a

$e VWe b.

N. *.

e e e e oe ee e o e e e e (L e

= ne NN MN i

veze o

Se e

.C e

. e e

+te ele

+le

+1e ele

+1e

+1e els

+1e Nw C Ce b e e-e

o. o. O. O e

N Oe 9xe

+

b T

Qe E

e W e.ed 6he eeJ 9

8 9+

e

@ M.

b O ae

+

e e oe ee e e e e ee e e I

e

+

s e

e e

e e

Q e

e Q

e$

e e

2 w

w a.w e

C e

e C

.s e 3we e

.m NM e

e ee e

e.e e.e U

e C E e

.o

.e e

e 3

O. S D. E i

e..e e

e2%

J..

s. M.

e e

a e o a

3 e C 2 w

• c e

w ea w e

e e

t-l 6.

e e

m>

e e

.e fe e

O.

O O.

O.

O.

O.

O.

O O

>V e w e

+

+

+

ej e

W eaJ Led lued eel s.aJ ted ned end h.

ea e

w e

e N

O.

e.

e.

e.

e.

g@

e e

N N

N N

m 8 VL e

e

.C L

ea e

e 6w e

B e

e e

e e

e e

i e

a e

e a 3e e

i 6

1 cr s.

e e

O O

.=

> w3 e

.e Q

O.,

O.

O.

O.

O.

O.

O.

O.,

.V L.

.e e

e e

w s.

8 M.

M.

w w

&m en-e e.

N.

o.

8 o>

e e

e

.e e

e a

e N

e e.

8 e

O e

+

e e

3 i

,i

=.

8 8

8 8

8 8

8 8

8 2 e

u L

-eoe a

w w

w w

w w

w w

e e

e N.

M.

w 6 e e

N N

N N

N N.

t e

e Ce e

e N

N e

e

.e.

e e

e.I e

el

+1 et

+1

+t

+1

• t

.I el V

e e

e e o oe e

L g

e U

6 e e

O.

O O

O.

O.

O.

O O.

O 3

e ee C e

+

+

+

+

e-Q w 4e e e

ned w

end nad w

w ned W

w 0

ee 9 e

c, c.

o.

e.

o.

w w

o o

l' s eg w

eE e

e L

o e

n

.v g

we e

I se 2t es e

e E

g e

+

2 e e e

O 6

e e

N N

w w

w w

e eo

>e e

N N

M M

N 9

$b e 0 e

N N

e2 e

e O

3

-L Oe es a

N N

w w

w w

e Ca

.4 2

e N

N

• =

M M

> 1 Ue e

vW ee e

==

9 g#

es, e e

e e

h e

• .M w e e

G g

L Oe e

3

.e 0

0 e

L

• 4 4

9 6

6 o

OC e

e I

Ce e

L V

.U

.l 4

w L

O 6

• ee I

.O e e

e e

4 g

M d

d

.1E ww

'I

• e C

+

e p

C e

e C

.a O

}

8eo e.

6 ei e

cs 6

C C

.o

=

3 E

L w

e.

e e

e o

1 se e e

E e

V V

e 3

3 e

N D' *e 2

e u e

e a

L g

6

• w e 0 e

C 0

6 e

e t

,e

.e.

e.

6 6

3 E

2 x

w o

e a e

e l

e 6

4 es.

2 O

Q 3

2 Q

l 59

a e

8 m

e 6

e ++

a 8

C C

4 eweC e

s 0 +* e e

a p*

s W 8 LOLL i

e e

e e

e e

et a

3 e

e e e

e e

- e C

e e

ee oae e

@ s 2 1 e

a e e

1 e

B e s

S I

Ui e

-oe e

a e tx e

e e e e e e e e e.

L e-C e* e a s a

a a

a a

a ee 00 0Eoe O

O O

O O

O ae L-2e B

• • +8 +1 e N 8

+\\e N

+ls %

+11 N

+ls N

+{B %

+l0 N Oe Ce 2i O

O O

O O

O Cn QU CCw e

-euo e-e w

w w

w w

w

• • s a ex a

Le I

e 8

i N

e n

e o e e e o e o e e e e T.

e 6

E t e

T e

f N

s e

v e

e e

e e

m O

a a

e o

e e

==

a e

O 1

(

E o

e e

e 2

s C

e e

i e

s O-0-

NM e

8 i

OO O

OO OO O

m e

e I

e

+ +

+

++

++

+

=

4 5

Ww w

ww ww w

U e

e E

O e

e Vxa,

e. 5

. e.

w O.

e o e

O s

• eoe

&Na a

-a

@wa nNa ea C

i eE2s e

O e

e o

m i

Ni e

e e

e e

e

< +1s 2i

+1a N

+(i N

+ 1, N

+le N

+1e N

+li s V

=*

e O

t c

e e

e

+* CC

-O mNe.-

e s

m e-Dow OOw OOw OOw OOw w

U a

eE e

++

++

++

+ +

++

q ea a

1 i

ww aan w ww aw ww E

• s==

g a

gQ

m. p eN e

e

-p g

Q-t Z

s e e m

MN

-M MM O

u e

e mG e

C e

C L

O e e

i Oe e

V e

V D

e 3

C e

6w

8. W Lw 6w Lw e

e e

eCs

-W

• M

-W

=M

-M U +*

a C

os e

e e

e e

U 3-e o

e-i oe oe oe oe oa e

L C>

t U +* e e

e e

e e

• • e O=

e

+a eCUe

- +

• i e eeee

.m.

.m --

.m --

.m.

.m -

e >

DU e

U e +* L e CE CE CE CE.

CE g o e

e4 a

0 2m-a o

o o

o o

++ n e

aw I

s

-Oe e

c x e.

.X e.

.x. e.

x e.

x e.

0 U

e a

O@

Q@

O@

O@

Q@

C -

D e

i e

3 e

• =

p e

e a w

=

+8 a

s

$ e U

S a

6 C

0 0

ee i

e a

-e s

U e

W Qt s

U L s e

e 6

e oe e

i

+8 (J

et C

a O*

N=

~

m 0-Nm V m

> 0e o

e OO OO O

OO OO O

e 0

e e

++

e e

+

+ +

++

+

6 a

L oi

+e a

ww ww w

ww ww w

e e

6 e e

a

e. &.

O. N.

. e.

v. O.

=.

a w

L

=

0#

U Ux e

e 9 0 4

U ce o -eme

&Na esa

@va mna na e

es-sofoe c

w e

e e

e e

L C

W w

ea-2e e vve e

e e

e

-u o

Ce<L

+le N i

+1s %

+1e N

+1e s

+1s %

+1s %

+1e N

>e o

Zv e

O e

o V

U +*

0 ei

- CCwi

-O

-~

MNe

.C 3e U

3i e e-i 00-OQw OOw OOw OOw OOw

- CE e t

t t

-v eE e

++

e.

++

+ +

++

++

c -

i 1

i ww ww ww ww ww ww m eo e e

e V

e

e. O.

O. *.

M. m.

• r.

e eh o 2

>e

.C s

3 wL wa e

N-mN

• M MM Oe 6

- e i

e C& O

- e a

yy

=e a

> e U>

a Um em e **

4

+8 s

Ce wa*

C e

a E O e

e o>

=

E E e-

=a e

o a.J w +* Q a

L we a e

o U.J s

o UC CI L eJ e

e e

6 e

• 4e L

oe e

=w e

e e

e e

e e

3 e-

• 3

• e 3 e

i

+* s O Q e

e 0 0 e e.J e

a

.J L

o Ue e

oe e

e e 2 e

l

+* N ae s

D m 2 e

s e

C e

w(

w e

e4e e

E L

e 0-e e

3 O

e aL e

C v

v 2

e Gho e

e m

c e

• Q - e-s 1

n cr, 2

N O

N e bel e

e e

i T

i e t-C e a

e e

D e

D 6

44 4

U me 2

to 3C 4

l e

e 60 i

Tablo 10 Annual Summary for Spectftc Radlonuclides in Grass Samples (Activity - pct /kg Wet)

Name of Factitty - Vogtle Docket No. 50-424.425 Location of Factitty Waynesboro Georgia

___..._........._.......................__-............__..... -_........__.__...........__. Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysts of Indicator LOCattons Location with Hfahest Annual Mean Locations Non-Routine Performed Detection Maan + Std Name Mean 1 Std Mean + Std Reported (LLD)

Min - Max Distance and Min - Max Min - Max Measurements (N/No)

Direction (N/No)

(N/No)

Man-hade Cs-134

< 1.8E+01 +< 7.9E+00

+

7.OE+01 +

None

< 6.OE+00 T< 5.OE+01 7

7.OE+01 7 7.OE+Of

( O/54)

( O/ 0)

( 1/31)

Cs-137 5.1E+01 1 3.9E+01 Simulator 5.2E+01 1 4.3E+01 3.6E+01 +

1. 5 E *01 None 8.OE+00 -

1.8E+02 1.5 Miles SE 8.OE+00 -

1.8E+02 1.4E+Of -

J.5E+01 (44/54)

(25/27)

( 7/31)

H-3 9.7E*O3 +

2.7E+04 Simulator 1.4E+04 +

3.7E+04 7.8E+02 +

6.8E+02 None 1.7E+02 7 1.2E+05 1.5 Miles SE 1.7E+02 7 1.2E+05 1.5E+02 7 2.3E+03

[S 421/2t)

(11/11)

( 9/10)

I-131

< 2.OE+01 +< 1.2E+01 4

< 1.8E+01 +<

< 7.OE+00 T< 6.8E+01 T

None

< 7.OE+00 -< 4.9E+01

( O/54)

( O/ O)

( O/31)

Nb-95 1.5E+01 +

Simulator 1.5E+Of +

+

None 1.5E+01 7 1.5E+01 1.5 Miles SE 1.5E+01 7 1.5E+Of T

( 1/54)

( 1/27)

( O/31)

Natural Ac-228

++

9.6E+01 1 3.OE+01 Simulator 1.OE+02 1 3.4E+01 5.5E+01 +

1.5L+01 None 5.2E+01 -

1.4E+02 1.5 Miles SE 5.2E+01 -

1.4E+02 3.4E*Of -

6.7E+Of (11/54)

( 7/27)

( 4/31)

Be-7 1.3E+03 1 1.8E+03 Hancock Landing 1.5E+03 +

2.OE+03 8.9E+02 +

6.9E+02 None 5.3E+01 -

9.1E+03 1.5 Miles NW 2.5E+02 -

7.8E+03 1.1E+02 -

2.6E+03 (54/54)

(27/27)

(31/31)84-232 2.4E+02 1 2.3E*Of Hancock Landing 2.6E+02 l' 1

None 2.3E+02 -

2.6E+02 1.5 Miles NW 2.6E+02 -

2.6E+02

( 2/54)

( 1/27)

( O/31)

Continued on next page

T4.blo 10 Annual Summary for Spectftc Radionuclides in Grass Samples (Activity - pCl/kg Wet)

Name of Factatty - Vogtle Docket No. 50-424.425 Location of Factitty - Waynesboro Georgta Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysts of Indicator Locations Location with Htohest Annual Mean Locations Non-Routine Performed Detection Mean i Std Name Mean + Std Mean + Std Reported (LLD)

Min - Max Distance and Min - Max Min - Max Measurements (N/No)

Direction (N/No)

(N/No)89-214 8.6E*Of 1 7.2E+01 Ha ncock Landing 9.5E*01 1 6.6E+01 1.3E+02 +

2.6E+02 None 2.tE+01 -

2.7E+02 1.5 Miles NW 2.9E+0i -

2.tE*02 1.6E+01 -

8.2E+02 (23/54)

( 9/27)

( 9/31)

K-40 4.4E+03 +

1.6E+03 Simulator 4.6E+03 +

1.8E*03 5.3E+03 +

1.7E+03 None 1.2E+03 7 8.8E+03 1.5 Miles SE 1.2E*03 7 8.8E*03 f.8E+03 7 9.3E+03 (54/54)

(27/27)

(31/31)

Pb-212 5.4E+Ot 1 2.7E+01 Hancock Landing 6.5E+01 1

2. 5E + 01 7.tE+01 1 7.5E+01 None 1.6E+01 -

1.tE+02 1.5 Mt?es NW 4.6E+08 -

1.th+02 2.3E+01 -

2.4E+02 (13/54)

( 6/27)

( 8/31)

Cn hJ Pb-214 8.OE*01 +

5.1E+01 Simulator 8.8E+01 1 6.2E+Of 1.1E+02 +

1.5E+02 None 2.8E+01 -

1.8E+02 1.5 Miles SE 2.8E+01 -

1.8E+02 3.OE+01 -

4.5E+02 (18/54)

( 9/27)

( 7/31)

TI-208 2.tE+Of 1 9.3E+00 Hancock Landing 2.5E+01 +

1.2E+01 4.1E+01 +

3.6E+01 None t.OE+0t -

4.4E+08 1.5 Miles NW t.2E+01 -

4.4E+01 1.4E+01 -

1.OE+02 (11/54)

( 5/27)

( 5/31)

NOTE:

Astertsk for all values indicates radionuclide not detected in samples (N/No) fraction denotes number of positive results over number of analyses performed

• • - Lower Limits of Detection are Itsted in Table 4 p

Iable 11 Annual Summary for Specific Radlonucitdes en River water Samples (Activity - pct /I)

Name of Factitty - Vogtle Docket No. 50-424.425 Locat ion of Factitty - Waynesboro Georgia Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysts of Indicator Locations Location with Htohest Annual Mean Locations Non-Routine Performed Detection Mean 1 Std Name Mean 1 Std Mean 1 Std Reported (LLO)

Min - Max Distance and Men - Max Men - Max Measurements.

(N/No)

Direction (N/No)

(N/No)

Man made Cs-134 4.2E+00 1 1.8E+00 R.M.

146.7 5.OE+OO 1 2.8E+00 9.9E+OO +

8.3E+OO None 3.OE+OO -

7.OE+00 3.OE+00 -

7.OE+00 4.OE+00 -

1.6E*01

( 5/115)

( 2/ 33)

( 2/ 82)

Cs-137 5.3E+OO +

3.9E*OO R.M.

149.5 6.4E+OO +

5.9E+00

+.9E+00 1 2.8E+00 None 3.OE*OO -

1.7E+01 3.OE+00 -

1.7E+01 3.OE+00 -

1.3E+Of

( 11/115)

( 5/ 41)

( 10/ 82) cn H-3 1.5E+03 1 9.OE*02 R.M.

146.7 2.OE*O3 +

8.5E*02 5.8E+02 +

2.tE*O2 None La 3.3E+02 -

4.3E*03 7.4E*02 -

3.9E+03 3.1E+02 -

1.fE+03

( 39/ 39)

( 11/ 11)

( 28/ 28) 1-131 5.OE+00 1 R.M.

14G.7 5.OE*00 1 1

None 5.OE+00 -

5.OE+00 5.OE+00 -

5.OE+00

(

1/115)

(

1/ 33)

( O/ 82)

Nb-95 4.OE*00 1 R.M.

349.5 4.OE+00 1

+

None 4.OE+00 -

4.OE+00 4.OE*00 -

4.OE+00

(

1/115)

(

1/ 41)

( O/ 82)

Zr-95 6.3E+00 +

5.8E-Of R.M.

150.6 7.OE+00 1

+

None 6.OE+00 -

7.OE*OO 7.OE+00 -

7.OE+00

(

3/115)

(

1/ 41)

( O/ 82)

Natural Ac-228 1.tE*01 +

4.5E*00 R.M.

149.5 1.7E+O' +

1.7E+01 +

1.2E+f' None

+

S.OE*OO 7 1.7E*01 1.7E+Of 7 1.7E*01 8.OE+00 7 ~4.1E*Of

( 5/115)

(

1/ 41)

( 6/ 82)

Continued on next page

'l e

e b

e a

e C

C e

4 6*DW e

W D

W e o ** t E i

C C

C C

e 3 ** e e

o O

O O

ee L0LL

.s 2

2 2

2 2

eiemo3 i e t c an e

-e ECte i

tn : 3oae e

ee22 1 i

-e e

g se -

e Q we

-O e a e

00 00 00 00 i

i

++

e +.

++

+

De i

WW LaJ W WW WW Oe

-e enx e

e e

. O.

N.

". O.

L i -C

-g-e a

-@a N==

or c e Nv-eeOo ct0e N

N N

N N

44 6-2e to to a0 40 c0

• * * * +l4 %e

+lt

+le

+lt

+1e

+ls c

Ot C4 2s N

N N

N N

N Ce oO CC-e O

--N CON

• • N CON v

-e uo 4-e OO OO OO OO e

• • e

.a en e

+ +

+ +

+ +

++

v Le 1

e

=

www www www www N

Oi e

e 4e e

cw..

c. 0

<D. c.

00 v

se e

e e

@ tln cc MM 3

O ae i

s e

s.mk o

c 2

e e

e i

L

+*

e e

G e

+a

.g 5

e e

u e

C e

3 O

e c

O-NN C

e W

O OO O

OO O

L e

3 e

+

++

+

++

+

0 e

e w

ww w

ww w

e e

i e cx-i e.

m. @.

O.

. O.

u s

~

qoe nm Nem N r.

-Ne

~~

f c~ I 2 e e

C e

C Ne e

v v

v er e

( $lt 2e

+lt

+la

+lt

+lI

+lt e

-e N

N N

N u.

o ea tC e

--e

--M

--e N-N eee en 9

in 9-q e3

,e OO 00 00 00 00 e

,e V

a

+ +

++

+ +

++

+ +

e u t e

www www www www www a

N e

d e

e e

v.

m. m.

n, N.

O O.

E o

3 U

e 2

e MM.

cc NN

~-

M g

C G

e e

C L

e o

e C

e e

e W

e 9 V e

U e

V g

e 3

C e

e D u -

e oCe

+c 4

e C

oe c.

U 0 -

i o

e-e g

L e

U +a i

e O

O O

O t

w

+a e

• , eCUe e

o c

c c

t O

e 4 8 e ta e U C e

o g

e o e-Le e

w e

c 2m-i

= m c

e e

o ei 1

2 I.

I.

I.

O **

-e

-OeI a

e os C

c L

e e

a a

m a

m 3

4

+n e

e a

en v.

0 m

e o

t e O

v e

6 C

e

~

4e o

O L

-e V

9 e

ce e

E e

E L e e

C **

E 0e e

e 3

e pe C

s O-o-

O-

-N 0-W D n e

-o e

OO OO OO OO OO e O c

ce e

++

++

++

++

++

b a

C*

e ww ww ww ww ww 4

U L s 4

e to. @.

m. @.

~. m.

v.

@ O.

M 6

L g

oi y Vx

{

w be o u gn e Nom Non

@Nm WNm v==

eg o

q C

a s

.s cIOe c

c c

c c

4 L

C as ge-2e

+1e y

e

>+ o 2i N

N N

N N

U EV

-o o

Ce 4L

+1e N e

+1e

+1e =

+1e

+1s e

- O e ee

+- CC-*

• • N

• -M

-Oc N-M OON C

i e

3e m 9-OO OO OO OO OO 3@

U CE t

j g

i u ez e

++

++

++

++

++

L 2

e e E

e www www www www www M

WO l

e C

e

v. N.

v. *.

M. O.

M. N.

c. Q.

t 8*

O l

>a C

e 3

• 6

• , =

e MM cc

- c0

@M

- O$

6 i

-e 6

4 Ca o

-e e

t

-e a

CM M

Ue s

+<

4e +,

e Cm -

C e

we==

4 0>

-E e 3 o s

% s-

-=

t L

w as w

oa.e s w o e

o UC e

oUJ e

94 L

Ce L S.J e

e e

e e

e L

W 0e t ww e

e e

e

+

e

.x 3

-

• 3 0

e

.e o O

• • e o o e

- =

.a e i.a e

L 0

0e e

t 2 e

oe N

.s i e

.m Z

e e

V e

w at e

a 6 $Q e

>=

n 0-E s

O e

eL e

N v

in 2

t e G>O e

O l

e a-w a

N N

N O

N s >qL e

e e

e 4

e ep C$

e e

==

e 44 i

G3 c3 03 X

S e

64

T e

m e

e +=

s C

C e

w-Ve i

e e

e e

e e

e O

• e, E e

e C

C C

C C

C C

3+

e e

o o

o o

o o

o vi to e LOLL s

2 2

2 2

2 2

2 i i ea 3

e

-e c.

m e

eiEC e

e ea 3ome s

a22 1 i a

e e

s e e

-O O

-N e

e OO O

00

0. C.

O Oi e

e +

+

++

0i i

ww w

ww ww w

+

• e e

@ c.

. O.

- m.

0 0D.

. O.

Li eUx e

. e e.

e-C

+* 4 a e nNa a

to a mv-mva ae oo eICe m

M m

v m

m m

co a a

e 6-2e VV*

Oe

• a * +ls N e

+l

+le

+l

+le

+la

+{e

+3e o

Cs Ce 2i N

N N

N N

N N

N

-e oO CC-a OOO O

OO-NNv 0 0. O O ~-=

v.

+** U O e-e 00*

OO OO 00 L e s og e

++

++

++

e v

oi X

i www w

www www www

- www

++

e N

as e

m v.

O. O.

QW Ee e

-a O. N.

00 y

ei i

-a e e e.

E O'

to ao vm MN to e i

e e

o e

s yv e

e L

o.

I e

e e

e 2

e a

w e

a e

e e

e 3

e e

e

.g e

O O

e C

e C

0 e

e i

OO O

O Nm O

+

e e

OO O

O OO O

O x

i 2

++

+

+

++

+

+

C i

i ww w

w L' ew w

w e

=

m. m.

O.

O v

L s

e Dxa e e ".

O.

e e

e e

e e O

e eoe

~ Li a ma Pa Wea a

Na ma

+a W 3 2.e a

m m

n v

O M

m

• t; e

C N

a

( +l9 20

+le

$lB

+l$

+ls

+le

+lI

+lt i

- i N

N N

N N

N N

m e

• , CC C0-00-00-Mmv O

e e

e e-00-00 00 00 CO 00 t

a e

e eI e

++

++

++

+ +

++

++

=

i 4 3

www www www www w

www www N

e

.C.

8

• 6 O. O.

O. O.

t-N.

O. O.

y e

e 3

O a

e e I

e m-mp 55 NN NN ma N

C a

e e

OL e

C e

e

=0 e

e C

C C

eO O

Du s

D e

w 44 e

3 C

4 L

L L

w q

D M3 i

eCa o

o o

is e

C Ce 3

3 3

x e-U3 -

,e Uue en C

C C

+*

C O

e-*

e

-e

• a

+*

+, eCOe L

e 4

e e

L U

e e

E4 e +, e I O

3 0

3 3

0 C

O s

O 6 e w

e w

a o 2m-*

3 3

3 in-O a

e s

-Oe e

L e

L L

e V

m e

i O

8 e

C e

C o

e e

8 CD a

CD a

4 (D

3 L

• e e

e O

O C

0 e

e e

e ea e

C L

=e s

O e

e Os e

Q E

L e a

E 0e m

e 3

+< ee C

e OO OO O

v. m N*

O~

m Os O

e OO OO O

OO OO OC O

e e

++

++

+

++

e s

++

+

Oi

+-

i ww ww w

ww ww ww w

.=

a U

L e e

s

. e.

O. O.

O.

v. e.

. O.

O. ~.

O.

e oa y yx e

e 6

0e o ** e a 8

-Oa Nm^

5a CD m a Opa vN^

Oa e

es-s omoe e

o e

cc e

e e

= e 2e N

N N

vvN N

N O

Ce4L

+13 Ni

+la

+1e

+1e

+ls

+1e

+1s

+te xi O

2i N

N N

N N

N N

e ee

+, CCw e OOO OOm 00-M N ce

--O

--e E

3i e e-s-

OON OO OO OO OO OO OO e

s y aI e

++

++

++

++

a i

++

++

2 e t

=V i

www www www www www www www e

t-o.

O. O.

O. O.

M. r.

e. o.

e v.

o. O.

>e C

e

• • e as e

N-f- @

f% P-N@

mN

@d

-e e

-i e

yv

-e e

oa a

es w a

we-C e

e E O e

we-

-a OsJw*O e

i o U.J e

Ce L e.J e

e e

e e

e e

e Oe e + = =

• e e

e e

e e

e

-i 3 e

s

+< e O O e

esJ s

a Ue s

0e e

e e

.J e e

O V

e V

a e

e i6 me a

e E

L e 0-E m

3 a

mL o

C v

5

+,

to e edo e

L e

m m

4 N

+

aa*

a O

e 2

M 2

N r-xeL i

e e

m e

e

>= C e a

e m

e e

a y

e 44 e

(D U

U Z

4 CD e

65

l,)

I'Iii iI

,i il lIi1 llll1 i'

s e

t n n fid>

e e

e e

. ot em n

n n

n 4

ut e o

o o

o 8

rorr.

N N

N N

eRou.

.b-ps 1

mnea _

8 9.NNuoRe 1

M 4

01 2

O d

00 0

O

++

+

+

io EE E

E 47 6

O.

r.

s dx e.

n t a).

)

t 1) 1)

P_ loo 5)

SMo.

3 3

3 3

N ri 1

1 1

1 g_t t

+ /.

+!

+7

+T 1-5 n na

/

/

/

/

2 i oc n n (N _-

O 1 1 2 221 001 o _. C o 4

t.

ae 00 00 00 r

l eM

++

++

+ +

s 4

M

(

EE(

EE(

EE(

e 2

p_

6S 66 O. O.

e l

4 p

R.

1 1 1 t 55 m

0 a

5 S

r o.

e N

t a

t w

e k

g c

n n

o a

1 2 1

0 D

e 00 0

0 i

k M

+ +

+

+

n EE E

E t

l 2t r

a dx).

5 O.

O u t ao.

1 1) 2)

)

7) n SMN 3

3 0

3 in n

/.

1 1

1 N.

+T

+!

+ -

1-A +

/

/

/

/

s

(

s t nn.

8 1 3

1 1 t O 001 e

e s ai 00 00 00 9d l

)

e eM.

+ *

+ +

++

p 1

b M EE(

EE(

(

EE(

m 1

/

o 63 55 O. O.

a C

t f

• +

s u

C

. H 98 22 77 2

n p

or n r 1

h e

i e -

t i

b 0

dt i

d.

d m aa y

w n

1 e u b RW t

a an.

t n

g i

o c

T Cw v o

ei e r l a i

l ct t

t t

t e

fR t

t enc r

r r

e v c

a mae o

o o

d o 4

i c

A c at

(

o Ns*r.

f f

f e

u u

u t

s e

p l

l O a

a a

o t

l S

e O

e e

e n

l b

r l

B 8

B u

a t

e s T

o O

d e f

o l

r n

V a

i i

y c e r

i u v d

a g

m r

n e

i o

to t

t m

y s

t s

u t

e.

n 1 2 1

0 d s t

S i

G.

o 00 0

0 a o I

l i

+ +

+

r p a

i o l

t EE E

E e

c r.

5 O.

a 31 s

f r

u a

o.

c dx

+

+

e o a

n F

bl o t a) 1 1) 2)

)

7) t n

SMo.

s L

6 6

6 6

a r n

A f

n.l N.

e.

2 2

2 2

c e o

o a _. A r+ /.

+7

+T

+

+ -

i b

i y

o n n (N.

/

/

/

/

d md t

e t

f14 1 1 1 O 00t m

W.

a ae O0 00 00 in ue c nm e a

c eM

• +

+ +

+ +

r t

N M

EE(

EE(

(

EE(

s so e i

d y.

n 8

55 O. O.

e ef D 1

u t r t.

I 97 22 77 oe f

l t.

a np o i

v e t

ds s c

l e i t

a.i t

ns l

n F

a oy m m o il i

f i) o.i r

t a L

n LftD o cn ocL f

aa r r

eL r

e io._ e t(

k ff w

w e s

o o a.o t.

D i

)

L oL r o c

e N t

/

L

s N

d EA

(

. f se T

.ot m O

sr 2

4 8

N

.eyo 1

1 0

pl f 2

2 0

2 yar 4

Tne 1

4 1

AP 8

8 K

T Sc i

i '

!4

e i

e e

i w

e C

C e

• -D@

s O

s Ow@ E s

C C

C C

C C

C 4 e 3 += 0 s

O O

O O

O O

ee LOLL 2

2 2

h 2

2 2

e e @mO3 e

w e Ce QW e

to e E C @ e e

me 302@

e

-i22 2

e e

.e

-0 OO OO

-N e e O-O-

e 00 00 00 00 00 00 00 gi e

i +

+ +

+ +

+ +

e e

++

++

e e

WW WW WW edJ W WW WW wW

- e a

m m.

e o.

o. O.

@ N.

@ m.

n.

m. O.

Le enw e

@a-C

• ea e mNa Nma

-6a 6ma Nca vNa m5a ae 0O WEOe m

W c.

L-2i N

N N

vvN N

N me**

+1 N

+1e

+le

+1e

+1e

+1e

+1s

+le o

Ce Ce 2e N

N N

N N

N N

N

-e oO CC-e com OON COM NNm

~~O

--N

--m

v. - ** e u o, 9-e oO-OO OO OO OO OO OO Le

@M a

++

++

+ +

+ +

e

++

++

n e oe 2

e www www www www www www www N

ae e

e m.

o. O.

N O.

m. e

• a e-e

~*

6@

og mn.

@ N.

e. o.

@ m.

4

@ a e

g N.

O i

e o

i e

vv e

e e

t 4

L g

e i

e e

6*

e i

o e

e e

3-s a

a e

e O

U a

C e

C O

e e

i O-Nm O

e Q O, OO OO OO O

OO x

e I

e

+

++

++

+ +

e

+ +

-C a

e ww ww ww ww w

ww a

e

v. v.

b. c.

m. @.

m. N.

,6

m. b.

L i

g Uxa e e e Q

e 3

• 80 0 e

@ma NT-N@a m@a Ma Tha a

e C oI2e e

e e

e e

e O

C e

C N <

m o

m m

M

+1e 2e

+le

+1e

+1s

+1s

+le

+1e

+;.

e

-i N

N N

N N

N N

e e

+* CC n

OO@

-ON

• On mmt

--N O

e e e-a OOM 00 00 00-00 00 c

a a

@ eE

+ +

++

++

++

e

++

-L e

C1 i

www www www www www www w

- o N

e o

e

. M.

o. O.

m O.

N.

Uw e

e e +

4 0 a

Z e

m*

N6 N@

mW 66 4-ti 63 a i

e C

e f

e O

~

-U e

e

+-

i 4

C I

I C

I g

e UC i -

g e

a 4C e

3 L

L L

L L

L D &w

• a o

o o

O O

o 4Ce 4

e C

Ce 3

3 3

3 3

3 x

.U C e

O

@- a w

w p.

y U*<

C C

C C

C C

e m na.

+'

s CCU8 O

e 9 E49e 3

3 3

3 3

3 C

U g

e U e ** 6

• O i

O 2m-e se w

w w

+<

a i

a

-ce L

L L

L L

L V

W e

Q e

C o

O O

O O

4 e

a a

6 a

a a

3 L

w i

e C

0 O

e O

e s

e C

gs e

o L

-e e

V Qe O

E L e e

E

> 0e e

e 3

@ e C

e O-mn l

0e e

++

++

+ +

++

C e

OO OO OO OO O.

OO I

e

+ +

Oe

~

a ww ww ww ww w

ww l

4 O

L i m o

mw no e@

-N N

v&

4 Ce U CY e

- +

• @^

Na Mba w

Da O w 9a e 9ma Nga N@a 6

a C

ee-a AEOe e

m 2e d

O e

c 4

@ i -

o Ce <L

+1 N e

+1e

+1e

+1e

+1e

+1 T

+1e

+1e me o

2:

N N

N N

N N

N ga CC-e OOm

-on

-on mme ---

--m o

E 3e 4 9-i OOv OO OO OO-00 00 2

e e

-U @I e

+ +

++

++

++

e s

++

9 e

E a

www www www www www www w

i V

e

m. m m, o.

n. C.

@ O.

o. e.

m. @.

As C

s e e N@

N-66 m-wa

==

8 N-

-e e

(

-e t

-e s

l Ue e

I ea w i

l C

e we -

i e E O

e w e-

-a e

l 0eJwwo e

s OUs e

Ce L 4.J e

o e

+

+

Oe @

• w e

-e 3

e

• e Q Q s

eea e

4 l

Ue e

e i

Oi e

D.

.J e a

Cl e

e e

e*@$

e m

E L

e O*E e

e 3

e ML e

O C

e m

m

• $>o e

L m

M M

e N

Q~*

C 4

X m

2 N

N AmL e

w e

e m

i e

I

>+ C D e

M m

e s

U l

4a e

CQ U

V I

CC e

I t

67 1

Tabl@.13 Annual Summary for SpectftC Radionuclides in Drinking Water Samples Fintsbed Water (Activity - pCl/I)

Name of Factitty - Vogtle Docket No. 50-424.425 Location of Facility - Waynesboro Georgia Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysis of Indicator Locations Location with Hichest Annual Mean Locations.

Non-Routine Performed Detection Mean 1 Std Name Mean 1 Std Mean + Std Reported (LLD)

Min - Max Distance and Men - Max Min - Max Measurements (N/No)

Direction (N/No)

(N/No)

B4-212 8.3E+Of 1 Port Wentworth 8.3E+01 1 8.8E+01 1 7.8E+00 None 8.3E+01 -

8.3E+Of 8.3E+01 -

8.3E+Ot 8.2E+09 -

9.3E*Os

( 1/ St)

(

1/ 38)

( 2/ 26)-

84-214 1_

1 7.OE+00 1 None 7.OE+OO -

7.OE+00

( O/ 51)

( O/ O)

( 1/ 26)

TI-208 1

1 6.OE+00 1 None ch 6.OE+00 -

6.OE+00 00

( O/ 51)

( O/ 0)

(

1/ 26)

NOTE:

Asterisk for all values indicates radionuclide not detected insamples (N/No) fraction denotes number of positive results over number of analyses performed

• • - Lower Limits of Detection are listed in Table 4 J.

i

Table 14 Annual Summary for Specific Radionuc3 Ides in Sediment Samples (Activity pct /kg) i Name of Facility - Vogtle Docket No. 50-424.425 Location of Factitty - Waynesboro Georgla

........______..__...__._.........__..___.____..__________..____.___.....___._____.............__ Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysts of Indicator Locations location With Hlobest Annual Mean Locations Non-Routine Performed Detection Mean + Std Name Mean + Std Mean + Std Reported (LLD)

Mtn ! Max Distance and Min ! Max Min 7 Max Measurements (N/No)

Direction N

______..___.___.___.___.....__.___.___.__....(../No)

(N/No)

Man-made Co-141

+

+

+

+

8.5E+01 +

None T

T 8.5E+01 7 8.5E+01

( O/ 5)

( O/ O)

( t/ 8)

C1-134

< 4.3E+01 +< *

+

9.3E+01 +

None

< 4.3E*Of !< 4.3E*Of

+

9.3E+01 7 9.3E+01

( O/ 5)

( O/ 0)

( t/ 8)

Cs-137 3.2E+02 +

3.2E+02 Statton 84 3.2E+02 1 3.2E+02 1.5E+02 +

9.6E+Of None cn 6.1E+01 -

7.8E*02 R.M.

148-150 6.1E+08 -

7.8E*02 4.3E+01 -

3.4E+02 i

MD

( 4/ 5)

( 4/ 5)

( 8/ 8)

Nb-95 8.2E+01 +

Station 84 8.2E+01 +

6.8E+01 +

None 8.2E+01 7 8.2E+01 R.M.

148-?50 8.2E+01 7 8.2E+01 6.8E+01 7 6.8E+01

( 1/ 5)

( t/ 5)

( t/ 8)

Zr-95

+

+

t.OE+02 +

None T

T 1.OE+02 7 1.OE+02

( O/ 5)

( O/ O)

( 1/ 8)

Natural Ac-228 1.OE+O3 +

4.5E+02 Station 84 1.OE+03 +

4.5E+02 1.3E+03 +

4.9E+02 None 6.2E+02 -

1.7E+03 R.M.

148-150 6.2E+02 -

1.7E+03 4.5E+02 -

2.tE+03

( 5/ 5)

( 5/ 5)

( 8/ 8)

Be-7 5.8E+02 +

+

Station 84 5.8E+02 +

5.OE*02 +

1.2E+02 None

+

5.8E+02 -

5.8E+02 R.M.

148-150 5.8E+02 -

5.8E+02 4.tE*02 -

5.8E+02

( 1/ 5)

( 1/ 5)

( 2/ 8)

B1-212 1.4E+03 +

7.7E+02 Station 84 1.4E+03 +

7.7E+02 1.3E*03 +

5.6E+02 None 7.7E+02 7 2.3E*03 R.M.

148-150 7.7E+02 7 2.3E+03 6.4E+02 !

2.1E+03

( 3/ 5)

( 3/ 5)

( 6/ 8)

Continueo on next page

Yable 14 Annual Summary for Specific Radfonuc3tdes in Sediment Samples (Activity - pC1/kg)

Name of Factitty - Vogtle Docket No. 50-424.425 Location of Facility - Waynesboro Georgta

_____..__.___....___......___....._...._______....___.......__..___.__......______...__.___... ___. Reporting Period - 1981-84 Type of Lower Ldelt All Control Number of Analysis of Indicator Locations location Wlth Hlohest Annual Mean Locations Non-Routine Performed Detection Mean + Std Name Mean + Std Mean + Std Reported (LLD)

Min - Max Olstance and Men - Max Min - Max Measurements (N/No)

Direction

__.______._____..__....___........___........__...........___.(N/No)

(N/No)84-214 9.8E+02 1 3.1E+02 Station 84 9.8E+02 1 3 1E+02 1.1E+03 1 3.9E+02 None 6.4E+02 -

1.4E+03 R.M.

148-150 6.4E+02 -

1.4E+03 4.7E+02 -

1.8E+03

( 5/ 5)

( 5/ 5)

( 8/ 8)

K-40 t.2E+04 +

2.8E+03 Station 84 1.2E+04 +

2.8E+03 1.3E+04 +

2.OE+03 None 9.8E+03 7 1.7E+04 R.M.

148-150 9.CE+03 7 f.7E+04 9.2E+03 7 1.5E+04

( 5/ 5)

( 5/ 5)

( 8/ 8)

Pb-212 1.1E+03 +

5.4E+02 Station 84 1.1E+03 +

5.4E+02 1.1E+03 +

5.1E+02 None 6.OE+02 7 2.OE+03 R.M.

148-150 6.OE+02 7 2.OE+03 4.OE+02 7 1.8E+03

( 5/ 5)

( 5/ 5)

( 8/ 8)

}j Pb-214 1.1E+03 1 3.4E+02 Station 94 1.1E*03 1 3.4E*02 t.2E+03 +

4.5E+02 None 6.6E+02 -

1.6E+03 R.M.

148-150 6.6E+02 -

1.6E+03 5.OE+02 -

2.OE+03

( 5/ 5)

( 5/ 5)

( 8/ 8)

Ra-226 1.7E+03 1 8.OE*02 Station 84 1.7E+03 1 8.OE+02 2.OE+03 +

8.4E+02 None 7.4E+02 -

2.9E+03 R.M.

148-150 7.4E+02 -

2.9E+03 1.OE+03 -

3.4E+03

( 5/ 5)

( 5/ 51

( 8/ 8)

T1-208

+*

3.8E+02 +

1.4E+02 Station 84 3.8E+02 +

1.4E+02 4.2E+02 +

1.4E+02 None 2.2E+02 7 5.7E+02 R.M.

148-154 2.2E+02 7 5.7E+02 1.6E+02 7 6.5E+02

( 5/ 5)

( 5/ 5)

( 8/ 8)

NOTE:

Asterisk for all values indicates radionuclide not detected in samples (N/No) fraction denotes number of positive results over number of analyses performed

• • - Lower Limits of Detection are listed in Table 4 l

Tablo 1b Annual Summary for Specific RadlonucIldes in Fish Samples (Activity - pct /kg)

Name of Factitty -

Vog*le Docket No. 50-424.425 Location of Factitty - Waynesboro Georgte Reporting Period - 1981-84 Type of Lower Limit All Control Number of Analysts of Indicator Locations Location with Htohest Annual Mean Locations Non-Routine Performed Detection Mean 1 Std N.:me Mean + Std Mean + Std Reported (LLO)

Min - Max Distance and Min - Max Min - Max Measurements (N/No)

Otrection

---

.------------.--------------(N/No)

(N/No)

Man-made Cs-134

< 3.2E+01 +<

• 1.OE+02 +

1.2E+02 None

< 3.2E+01 T< 3.2E+01 T

2.3E+01 7 8.9E+02

( O/ 15)

( Of 0)

( 2/ 17)

Cs-137 5.9E*02 +

1.OE+03 Station 85 5.9E+02 +

1.OE+03 3.4E+02 +

4.1E+02 None-6.3E+01 7 3.4E+03 R.M.

144-150 6.3E*01 7 3.4E+03 6.4E+01 7 1.5E+03

( 15/ 15)

( 15/ 85)

( 12/ 17)

Nb-95

+

1

+

3.4E+01 1 None

'd 3.4E+01 -

3.4E+01

( O/ 15)

( O/ 0)

( 1/ 17)

Natural 81-214 1.4E+02 +

Station 85 1.4E402 +

=

+

None 1.4E+02 T 1.4E+02 R.M.

144-150 1.4E+02 7 1.4E*02 7

(

1/ 15)

(

1/ 15)

( O/ 17)

K-40 3.5E+03 +

1.OE+03 Station 85 3.5E+03 +

1_OE+03 3.4E+03 +

9.7E+02 None 2.OE+03 7 6.OE+03 R.M.

144-150 2.OE+03 T 6.OE+03 1.4E+03 T 5.1E+03

( 15/ 15)

( 15/ 15)

( 17/ 17)

NOTE:

Astertsk for all values indicates radionucIlde not detected in samples (N/No) fraction denotes number of positive results over number of analyses performed

• • - Lower Limits of Detection are Itsted in Table 4 T

e e

a e i e

9 **

e s

C C

s es-De a

e e

e e

e s O ** O E e

C C

C C

C C

C i

3*e e

O O

O O

O O

O we LOLL a

2 2

2 2

2 2

2 ee e oc 0 3 e

e i oe ae i

=* Ecee e

m 3 O CE e i me22 1 e

w e e

a e

O OO

=N

=

O e 6 s

O OO OO O

O e

s

+

++

++

+

+

Ve L

e w

ww ww w

w

-0e e

e o.

o. 0

. e.

m.

. O.

Le Vx e

e a

m e e e

e e

• ga e na n eg a nNm a

c=

p=

9e-D MIOe n

M ch i ec 2e n.

m.

m M

m e C4

+le N e

+le

+fa

+1e

+1e

+lI

+1s

+ta m

0t O 2i N

N N

N-N N

N N

Ce -U CC-e oO*

OON NNN O -==

00-O v

-e Oe e-OO OO OO OO OO

• a eC 03 i

++

++

++

++

++

4 L e IX - 1 e

www www www w

www www w

n Oe O. O.

o. O.

@ v.

e. m.

O. O.

e w

ae C

e e e e o e

e e*

O e

Wo eM NN cm mm O ct e U

e

-a o

e e

E e

e 4

3 e

o O

e e

2 e

i L

e e

e e

e e

w 9

e e

e J

t t

3 U

e C

e 0

e e

i O

Nm D

O e

e i

O OO O

O N

C e

2

+

++

+

+

3 e

e w

ww w

w 0

e e

O.

O. M.

o.

to L

e z Oxa e e e e

eo e

e o O

e

= =eoe

=

v.

on-g.

e 6 A12*

O e

M O

M C

6

-C e

C N

g +1s 2e

+1e

+te

+le

+1e

+1e ele

+1e a

we N

N N

N N

N N

m e

e

+' CC e

O C0*

nnn O ***

O NN=

e e

e e e-e 00 00 00 00 Va a

e mz i

++

++

++

++

q t

4 1 w

www www w

www w

www E

-N e

0 e

O. O.

t. O.

m. m.

ao. e.

U-s i

e e e

e e e e m

)U 1

2 TT NN TT 9

Ca 8

e 0

e r

e C

L

=

-e e

e e

-0 V

e V

e D

4>

a 3

C e

V E D tc **

eCi L

L 2

• • C 3

e 3

44 s

C Oe 6

e e

=

>=

U>

t O

9-w ee ae

@4 e

L 0

e U en e 3

C6 CO

• e en h ed a

to gCU6 L

L Q e.

S U

e e aeee a3 Oe Oe U-0 0 v

U4 U e ** L e Cr CC

-2 ew 0 2m-e e

-U

=U

+=

+* a e

a e

.J

-Oe 3

Le Le m

e e

o e

a-c=

e m.

O **

w C

L e

a to MO mo mo 3

ec

=

e i

O O

e a

a m

e.

6 e w

o e

e L

e L

C ea e

e L

-e i

U e

e e

Oe e

3 U

E Le 3

C e

E

> 0s O

e e

O **

+-

3

• • ee 4

e

• O NM

=

W

- oe e

OO OO O

00 e O

-N V e e

V e

e +

++

+

++

c a Oi e

ww ww w

ww e

4 U

L 8 C

e

- O.

m. e.

m e

Oi

v. e.

Vx a

e e m

• L

+

e e e

e e e 6

4

• ** e a e a

6ga

@Ma a

ya a

• • e 0 4

ee-C 0IOe 5

5 w

5 5

5 5

4 L

C 4

6 et 0

2e O

Ce4U

+fa N e

+1e

+1e

+1e

+le

+le

+le

+le

-U e

-O h8 C

2e N

N N

N N

N N

V EV **

Q 9 es 3 CCwe O CON now O ~~~

O N-N E

38 e-e oO OO*

OO OO

-C 39 U

e e

CE e SE a

++

+ +

++

+ +

b

=

2 4 i e 4

w www www w

www w

www n eO e e

U i

O. O.

M. M

@ m.

V. O.

e ew O

>e 0

e ee e e e e 3 ** L

.a i

nM N*

vv

=m Oe *

-e e

- e e

e Ca 0

-e e

> e Ue e

Ce m ee ee e

w 6 e-C e

Cm e E O e

e O>

E

e. I -

-a e

O e J h ** O e

L en e

.J e

OUa e

Q UC Ce L e.J e

e e

e e

e e

e L

e w

44 L

O8 9 ** w e

e e

e e

e e

e

.x

• e.

3

-e 3

9 e* e o O m

O O et.J s

e

.J y4 i

L O

0e i

e e 2 e

C se e

N V

e g

a m 2 e

w<

w e

e% me e

E L

i O-E a

e t=

3 o

e eL i

C w

N N

T 2

e e>O a

g n

M e

=

e a-b i

3 2

5 N

N O

t heL e

e e

M e

e e

g e >= C e e

S a

e e

t t

4 Ch e

U U

Z CD 10 10 X

e e

72

l-TABLE 17 CROSSCHECK PROGRAM RESULTS Air Filter 1981-pCi/ filter Date Known Result Resolution Ratio Gross Beta 3/27/81 50*5 53i1 10.0 1.06 6/26/81 54*5 60i1 10.8 1.11 9/25/81 51*5 58*2 10.2 1.14 Cs-137 3/27/81 14*5 14*2 2.8 1.00 6/26/81 16*5 33*2 3.2 1.44 9/25/81 19*5 24*3 3.8 1.26 73

TABLE 19 CROSSCHECK PROGRAM RESULTS Milk 1981 pCi/ liter Date Known Result Resolution Ratio I-131 01/30/81 26*10 24 05/15/81 26*6 49t0 4.3 1.88 07/24/81 0.0lt0.001 19 10/23/81 52*6 55t13 8.7 1.06 Cs-137 01/30/81 43*9 42*4 4.8 0.98 05/15/81 22*5 24t4 4.4 1.09 07/24/81 31i5 37*3 6.2 1.19 10/23/81 25*5 2817 5.0 1.12 If the known value is zero or if the result is a "less than" value, no comparison can be made by the NRC criteria since the ratio cannot be determined.

l 74 l

l l

TABLE 19 (Sheet 1 of 2)

CROSSCHECK PROGRAM RESULTS 1981 Water pCi/ liter Date Known Result Resolution Ratio H-3 02/13/81 1760*341 1927t103 5.16 1.09 04/10/81 2710*355 3220*70 7.63 1.19 06/12/81 1950i344 2146*0 5.67 1.10 08/07/81 2630*354 2977*179 7.43 1.13

'10/09/81 2210*348 2926t144 6.35 1.32 12/11/81 2700i355 2999*85 7.61 1.11 Cr-51 06/05/81 0.0 184 10/

/81 34*5 31 Co-60 06/05/81 17*$

22*2 3.4 1,29 10/

/81 22*5 31 4,1 1.40 Zn-65 06/05/81 0.0 24 10/

/81 24t5 29 Ru-106 06/05/81 15i5 110 10/

/81 0.0 137 Cs-134 06/05/81 21i5 26*5 4.2 1.24 10/

/81 21t5 28 4.2 1.33 75

TABLE 19 (Sheet 2 of 2)

CROSSCHECK PROGRAM RESULTS Water (Cont'd) 1981 pCi/ liter Date Kn7wn Result Resolution Ratio Cs-137 06/05/81 31*5 36*2 6.2 1.16 10/

/81 32*5 36 6.4 1.13 If the known value is zero or if the result is a "less than" value, no comparison can be made by the NRC criteria since the ratio cannot be determined.

76

TABLE 20 CROSSCHECK PROGRAM RESULTS 1982 Air Filter pCi/ filter Date Known Result Resolution Ratio Gross Beta 03/26/82 55*5 59*1 11.0 1.07 09/24/82 67*3 65*2 22.3 0.97 11/26/82 59*5 72*1 11.8 1.22 Cs-137 03/26/82 23*5 24*2 4.6 1.04 09/24/82 27*5 21*2 5.4 0.78 11/26/82 27*5 31*1 5.4 1.15 1

b I

I t

P P

77

TABLE 21 CROSSCHECK PROGRAM RESULTS -

1982 Milk pCi/ liter Date Known Result Resolution Ratio I-131 07/23/82 5.4t0.8 3.7*0.6 6.75 0.69 10/22/82 42*6 28*3 7.0 0.67 Co-60 04/23/82 30i5 33tl 6.0 1.1 Cs-137 04/23/82 28*5 34t2 5.6 1.2 10/22/82

'34*5 25i2 6.8 0.74 Ba-140 04/23/82 0

66' If the known value is zero or if the result is a "less than" value, no comparison can be made by the NRC criteria since the ratio cannot be determined.

78

TABLE 22 (SHEET 1 of 2)

CROSSCHECK PROGRAM RESULTS 1982 Water pCi/ liter Date Known Result Resolution Ratio H-3 02/12/82 1820i342 2277*127 5.3 1.25 04/09/82 2860*360 3159*68 7.9 1.10 06/11/82 1830i197 1529*46 9.3 0.84 08/13/82 2890*390 10/01/82 2560*204 12/10/82 1990*345 2339+37 5.8 1.18 Cr-51 02/05/82 0.0 216 06/04/82 23*5 150 10/01/82 51*5 194 Co-60 02/05/82 20*5 21*1 4.0 1.05 06/04/82 29*5 33*2 5.8 1.14 10/01/82 20*5 18*1 4.0 0.90 zn-65 02/05/82 15*5 30 06/04/82 26*5 34 10/01/82 24*5 32*2 4.8 1.33 I-131 06/25/82 4.4t6 3i0 0.73 0.68 79

i TABLE 22 (SHEET 2 OF 2)

CROSSCHECK PROGRAM RESULTS Water (Cont'd) 1982 pCi/ liter Date Known Result Resolution Ratio Ru-106 02/05/82 20*5 131 06/04/82 0.0 122 10/01/82 30*5 119 Cs-134 02/05/82 22*5 22*1 4.4

.l.0 06/04/82 35i5 33t4 7.0 0.94 10/01/82 19*5 23*1 3.8 1.21 Cs-137 02/05/82 23*5 19*3 4.6 0.83 06/04/82 25*5 27*3 5.0 1.08 10/01/82 20*5 22*2 4.0 1.10 If the known value is zero or if the result is a "less than" value, no comparison can be maos by the NRC criteria since the ratio cannot be determined.

l These samples not analyzed.

i 80

TABLE 23 CROSSCHECK PROGRAM RESULTS 1983 Air Filter pCi/ filter Date Known Result Resolution Ratio Gross Beta 03/25/83 68*5 59*1 13.6 0.87 08/26/83 36*5 33 7.2 0.92 11/25/83 50*5 49 10.0 0.98 Cs-137 03/25/83 27*5 27*1 5.4 1.00 08/26/83 15*5 11/25/83 20*5 20 4.0 1.00 This sample was not analyzed.

81

TABLE 24 CROSSCIIECK PROGRAM RESULTS 1983 Milk pCi/ liter

. Date Known Result Resolution P.atio I-131 06/10/83 30*6 25*4 5.0 0.83 10/28/83 40*6 54 6.7 1.35 Cs-137 06/10/83 47t5 4111 9.4 0.87 10/28/83 33*5 24 6.6 0.73 4

b 82

TABLE 25 l

(SHEET 1 of 2)

CROSSCHECK PROGRAM RT.SULTS 1983 Water pCi/ liter Date Known Result Resolution Ratio H-3 02/11/83 2560*353 2776*8

/.25 1.08 04/08/83 3330i362 2231i42 9.20 0.67 06/10/83 1529*337 1915*l2 4.53 1.25 08/12/83 1836*342 2363*104 5.37 1.29 10/14/83 1210*329 1330tS6 3.68 1.10 12/

/83 2389*351 2510 6.80 1.05 Cr-51 02/04/83 45*5 105 06/03/83 60i5 100 10/07/83 51*5 97 06/03/83 60*5 138 Co-60 02/04/83 22*5 25tl 4.4 1.14 06/03/83 13*5 11*1 2.6 0.85 10/07/83 19*5 17 3.8 0.89 06/03/83 13*5 14*l 2.6 1.08***

Zn-65 02/04/83 21i5 19*3 4.2 0.90 06/03/83 36*5 10*2 7.2 0.28**

10/07/83 40i5 31 06/03/86 36*5 32*7 7.2 0.89***

83

TABLE 26 CROSSCHECK PROGRAM RESULTS 1984 Air Filter pCi/ filter Date Known Result Resolution Ratio Gross Beta 03/23/84 51i5 58i2 10.2 1.14 08/24/84 51*5 54*2 10.2 1.06 11/23/84 52i5 52i1 10.4 1.00 Cs-137 03/23/84 10i5 11*1 2.0 1.10 08/24/84 15*5

'12i0 3.0 0.80 11/23/84 10i5 12i2 2.0 1.20 85

TABLE 27 CROSSCHECK PROGRAM RESULTS Milk 1984 pCi/ liter Date Known Result Resolution Ratio I-131 06/22/84 43*6 21tl 7.2 0.49 10/26/84 42i6 47t3 7.0 1.12 Cs-137 06/22/84 35*5 3115 7.0 0.89 10/26/84 32*5 36*3 6.4 1.13 86

TABLE 28 (SHEET 1 of 2)

CROSSCHECK PROGRAM RESULTS 1984 Water pCi/ liter Date Known Result Resolution Ratio H-3 02/10/84 2383*351 2640t60 6.79 1.11 04/13/84 3508*364 3423i12 9.64 0.98 06/08/84 3051*359 3120i61 8.50 1.02 08/07/84 2817*356 2927A142 7.91 1.04 10/12/84 28101356 2673*71 7.89 0.95 12/14/84 3182*360 3290*36 8.83 1.03 Cr-51 02/03/84 40t5 103 06/01/84 66*5 62i9 13.2 0.94 10/05/84 40*5 76 Co-60 02/03/84 10*5 16*2 2.0 1.6 06/01/84 31i5 27*1 6.2 0.87 10/05/84 20*5 19t1 4.0 0.95 Zn-65 02/03/84 50*5 36*6 10.0 0.72 06/01/84 63*5 55*3 12.6 0.87 10/05/84 147*7 146*9 19.9 0.99 Ru-106 02/03/84 61i5 77 06/01/84 29*5 49 10/05/84 47*5 50 87 i

TABLE 28 (SHEET 2 of 2)

CROSSCHECK PROGRAM RESULTS l

Water (Cont'd) 1984 pCi/ liter l

Date Known Result Resolution Ratio Cs-134 02/03/84 31*5 22*4 6.2 0.71 06/01/84 47*5 39*1 9.4 0.83 10/05/84 31*5 30*1 6.2 0.97 Cs-137 02/03/84 16*5 9

06/01/84 37*5 32il 7.4 0.86 10/05/84 24*5 25*2 4.8 1.04 I

I-131 04/06/84 6*6 7*1 1.0 1.17 Gross Beta 05/18/84 6*5 3*1 1.2 0.5 11/16/84 20d5 20*1 4.0 1.0 If the known value is zero or if the result is a "less than" value, no comparison can be made by the NRC criteria since the ratio cannot be determined.

88

Table 29 CRITERIA FOR COMPARING ANALYTICAL MEASUREMENTS This table provides criteria for comparing results of capability tests and verification measurements.

The criteria are based on an empirical relationship which combines prior experience and the accuracy needs of this program.

In these criteria, the judgment limits are variable in relation to the comparison of the Keference Laboratory's value to its associated one sigma uncertainty.

As this comparison, referred to as "Resolution" increases, the acceptability of a licensee's measurement should be more selective.

Conversely, poorer agreement should be considered acceptable as the resolution decreases.

The values in the ratio criteria may be rounded to fewer significant figures to maintain statistical consistency with the number of significant figures reported by the Reference Laboratory, uhless such rounding will result in a narrowed category of acceptance.

The acceptance category reported will be the narrowest into which the ratio fits for the resolutior, being used.

RESOLUTION RATIO = LICENSEE VALUE/ REFERENCE VALUE Possible Possible Agreement Agreement "A"

Agreement "B"

3 No Comparison No Comparison No Comparison 3 and 4

0.4

- 2.5 0.3

- 3.0 No Comparison 4 and 8

0.5

- 2.0 0.4

- 2.5 0.3

- 3.0 8 and 16 0.6

- 1.67 0.5

- 2.0 0.4

- 2.5 16 and 51 0.75 - 1.33 0.6

- 1.67 0.5

- 2.0 51 and 200 0.80 - 1.25 0.75 - 1.33 0.6

- 1.67 200 0.85 - 1.18 0.80 - 1.25 0.75 - 1.33 "A"

criteria are applied to the following analyses:

Gamma spectrometry where principal gamma energy used for identification is greater than 250 kev.

Tritium analyses of liquid samples "B" criteria are applied to the following analyses:

Gamma spectrometry where principal gamma energy used for identification is less than 250 kev.

S r-89 and S r-90 determination.

Gross beta where samples are counted on the same date using the same reference nuclide.

89

TABLE 30 LAND USE SURVEY (1981)

Distance to Permanent Residence, Meat Animal, Milk Producing Cow / Goal, Vegetable Garden Within 8000 Meters of Plant Vogtle During 1981 Milk First Second Cow or First Second Meat Meat First Second Goat Residence Residence Animal Animal Garden Garden g

NNE NE ENE E

ESE SE 5150 6920 6920 5150 6920 SSE 7723 7723 S

7242 7242 7242 7242 7242 SSW 7483 7483 7483 7483 7483 SW-3540 4344 7723 7725 7800 WSW 2092 3862 7401 7562 4344 7562 W

2735 3701 2735 5471 2735 3701 WNW 3701 4184 4184 6114 3701 4184 NW 3540 3701 3701 7723 3701 7723 NNW 90

TABLE 31 LAND USE SURVEY (1982)

Distance to Permanent Residence, Meat Animal, Milk Producing Cow / Goal, Vegetable Garden Within 8000 Meters of Plant Vogtle During 1981 Milk First Second Cow or First Second Meat Meat First Second Goat Residence Residence Animal Animal Garden Garden N

1890 1890 NNE NE ENE E

ESE SE 5304 6888 7864 5304 6888 SSE 7925 7986 7925 7986 S

7254 7284 7254 7254 7284 SSW 7315 7498 7315 7315 7498 SW 3536 4206 7681 4206 6828 WSW 2012 4084 4084 5182 W

2560 2926 2560 2560 2926 WNW 3414 4328 7132 3414 4877 NW 2865 3536 3719 4206 4206 6218 NNW 91 l

TABLE 32 LAND USE SURVEY (1983)

DISTANCE (METERS) TO NEAREST PERMANENT RESIDENCE, MEAT ANIMAL (PIG OR CATTLE), MILK PRODUCING COW OR GOAT AND VEGETABLE GARDEN WITHIN 8000 METERS OF PLANT VOGTLE DURING 1983 Milk Cow Permanent Meat or Goat Residence Animal Garden N

NNE NE ENE E

ESE SE 7321 5390 (possible) 7965 6959 6959 (definite)

SSE 7482 S

7160 7965 SSW 7643 7401 SW 4545 7562 7723 WS W 1931 7723 2011 W

2494 2977 WNW 3057 4425 6838 NW 3379 6315 NNW 92

TABLE 33 LAND USE SURVEY (1984)

DISTANCE (METERS ) TO NEAREST PERMANENT RESIDENCE, META ANIMAL (PIG OR CATTLE), MILK PRODUCING COW OR GOAL AND VEGETABLE GARDEN WITHIN 8000 METERS OF PLANT VOGTLE DURING 1984 Sector Milk Cow Meat Animal Resident Vegetable Garden N

NNE NE ENE E

ESE SE 7403 6920

.5310 5310 SSE S

8046 7240 SSW 7403 7562 SW 4989 4506 4828 WSW 7724 1931 2253 W

2414 2897 WNW 3058 5471 NW 6276 3379 3862 NNW 93 9--,

-p

.-g-77-m w-

-#7'-ww-4

-w w-'"F="-Y'*w-*-"**WT*v'"T

'N"Y

FIGURE 1 Terrestrial Stations Near Site Boundary and Groundwater S tations s

@@\\

edg\\

e i

!!)

g

>/-

nn

.s s

n

)

g y

3-3

e..

... j i

>g

.r

.i t

a

//'

/

M Il V.

o X

j.r.;e./

fj[y

~'

gq-

.. / ' ',,,e

,:. :/:,\\\\}.

n

' @.~.??FQ P;-

[

. /....

.~

. /,[.' ; Mh. i.

d h;

gi,

/

3 md 3

.. v...

....t v.

n1.

,./

...r g) 6 m

9

.l r.

<...r s.

4 .

l j'

C".*--

l g.

\\

.,2 y.:... h l

-- b NI{/f

. k 3,,

./

s.'-

l *: :'.d/

' {,?

@/l/ln, 1

/

'3 e

7. =.d

~

\\

I,

/..

a

.i-e'.

g/

u y

, f * *,,,

I f

l

.g

..J

- ys

@,R

/

7o V

. F, 94

FIGURE 2 Terrestrial Stations beyond Site Boundary out to Approximately Five Miles and River Water S tations

'" g s

u

.,1 p.

.E..."gQ..f.

n "@ '

2 o

/

t

~

.1

,3-1

./ @

mus

3..<,,.

1 s.

3 q f v.

. s.

rf i

(c.

./

3 m.

a c

1 g.

,.~m~.

..r...

. s

~

s s

/

e,

2 f

r.-

% =s i z xy a

a u.

t

.f.'..., ff n x i. M. We y u-

.N,.- Mf3 ufR@s>

i

)@

..,_mQ

/

(

j 7

.r.

q.... %.

.,.,n_;.'?<.'2SI.dY,E k,,e /

M~ 'e g # l

.\\.. g m,

+.

-)

.s

e

/

~.

g..

../.

c e w..

l 1,

[,

r'8

$.: U' m. L.. M e>~,yr&,.l',,,

hs& 4:~

• t.y*. 'C 'n%f i

+

.y

,~

4

'" l-

.,_, g A.

'.W '

.i i

m. r %s-c y-

-t

\\

.j. o.i

, y.....g q}j i:;

. i.. = r =.r%.,.,Q j.

q '.:.

y\\. A _Ug%. V,2 6.. q:,

l

..s

.. %9

........ % k o ::- a,f.

/

u s %,~< m i

e :.

s...,

. = %. n.N.

w i

.: x.

-a i

i l

95 1

FIGURE 3 Terrestrial Stations beyond Five Miles Q

1 h,,,

/

5 s

25 i,

i e.

)

Graniteville

,e 3; g s.....

/

North

/

ss ugusta d 25 MILE RADIUS

/

COLUMBI A CO.

f AIKEN j

j j AU A

s l

• • *f '

278 New 1

' 78

• EUenton s

/ 278-p,,,,,

273 v,,

y 278 j

(,i' j'

can..

io I *

,/

Blackville,

RICHt NO CO.

• • ia-.

e.,

/

o,,,,,,,

'8" I

Jackson O '

278

' Gord n

)

/

B ARNWELL CO.

. 1, t ea.-.

83 u.c n,,

/

/

[

h

• Barnwed l

/

',',",,",,* /.

25 l

/ v.s. csvi A a ta

, \\.

l e ci.osto ro eveuc s a....a.

.~.

j

(

l s

V I

l t

f-ir j

g *** 7'"%=...

I 7

BLj E CO.

SITE r

34

/

37' eg4,4

(/

3 4

i

• WTynesboro 3

g annu M e n,'a c,,,,,

5 p

All dai o.

, 88 i e

i.i...

,/

\\ LLENDAL

.e f

i

• /

s v e'

\\*

-~.

._ /

'g is t

N

/

301

,,[,,,'

/,

/,

'?

[ W 321

~:. l ..,~,

mn,,

6

/

N

/ './

JENKINS CO.

~SCREVEN CO.

j,,,,,,,,

• ytvanis Estill

\\,'"****

e...-...

HAMP, TON CO.

f

\\

ra.- n....

t 3,,,,,,,

L c..... '

ea"n f

(

f

\\

s 25 96 I

[

A FIGURE 4 Drinking Water Stations J NORTH AUGUSTA r

WATER TRE ATMENT PLANT v

SAVANNAH RIVER PLANT VEGP #

N

)

Canal to su: ply River q

Water to Beaufort iy

}

8eaufort Jascer County i

Water Treatment Plant t aE AuI'db GEORGI A yi e

o EF

• ' 87 i s*,+',

o e

O tm

\\

E 4

mh 0

10, 20 30 CHEROKEE HILL p

WATER TRE ATMENT h

9 4

PLANT 4

(PORT WENTWORTHI D

$AVANNAH.g O

b 97 7

__s.

FIGURE 5 TREND CURVE.FOR GROSS BETA IN AIR' INDICATOR STATIONS (pCi/m3) 0.07 0.06 -

0.05 -

0.04 -

}

[

w h

0.03 -

e 0

0.02 -

6 Ak sh 0.01 0

yr

- 0.01 i

1981 1982 1983 1984 YEAR O

AVG o

AVG - 1SD A

AVG + 1SD

_ 4_ _.

FIGURE 6 TREND CURVE FOR TRITIUM IN AIR INDICATOR STATIONS (pCi/m3) 320

+

300 -

1 280 -

4 260 -

1 240 -

220 -

200 -

180 -

to 4

i E

160 -

e i

3 a

e e

o 140 -

a 4

a 120 -

)

i 100 -

80 -

I i

60 -

-o-40 -

j 20 -

l 0

1 H>-

-20

)

1981 1982 1983 1984 j

YEAR i

O AVG o

AVG - 1SD A

AVG + 1SD i

1 l

1

FIGURE 7 TREND CURVE FOR TLDS AT SITE BOUNDARY Indicator Stations (mrom/91 days) 20 19

+

18 wu 17 -

h 16 -

15 -

s

-8 E

f 14 -

+

-o-.

N 13 12 -

11 -

+

10 i

i 1981 1982 1983 1984 YEAR O

AVG 0

AVG - 1SD A

AVG + 1SD

FIGURE 8 TREND CURVE FOR TRITIUM IN GRASS INDICATOR STATIONS (pCi/kg wet) 40

-n 30 -

20 -

e*

• I fa 10 -

E S8 11 or Eb o A&

-20 i

i 1981 1982 1983 1984 YEAR O

AVG O

AVG - ISD A

AVG + 1SD

FIGURE'9 TREND CURVE FOR Cs-137 IN GRASS INDICATOR STATIONS (pCi/kg wet) 110

,W-100 -

90 -

4L 80 -

I 70 -

e 1

60 -

3 E

I 5

h 50 -

?1 40 -

s 3

30 -

20 -

10 -

F 0

i i

1981 1982 1983 1984 YEAR O

AVG 0

AVG - 1SD A

AVG + 1SD

FIGURE 10 TREND CURVE FOR TRITIUM IN. RIVER WATER INDICATOR STATIONS (pCi/l) 3 2.8 -

2.6 -

2.4 -

2.2 -

,W e

2 -

m E

qg 1.3

-g US

-o a o 1.6 -

.c 1.4 -

)

1.2 -

I 1

0.8 -

-o-0.6 -

0.4 1981 1982 1983 1984 YEAR O

AVG o

AVG - 1SD a

AVG + 1SD

1 FIGURE 11 TREND CURVE FOR CS-137 IN RIVER WATER

-INDICATOR STATIONS (pCi/l) 16

,p 15 -

14 -

13 -

12 -

11 -

10 -

q 9 -

y 8 -

7 -

6 -

'k 4

-H j

-s 3 -

HH 2 -

+

1 i

i 1981 1982

'1983 1984-YEAR O

AVG 0

AVG - 1SD A

AVG + 1SD

w4 FIGURE 12 TREND CURVE-GROSS BETA-RAW DRNK. WATER INDICATOR STATIONS (pCi/1) 4 3.5 -

3 1

2.5 -

D 2 -

S 1.5 -

1 0.5 -

O 1981 1982 1983 1984 YEAR O

AVG O

AVG - 1SD A

AVG + ISD

FIGURE 13 TREND CURVE-TRITIUM IN RAW DRK. WATER INDICATOR STATIONS (pCi/l) 3.1 -

3 -

2.9 2.8 -

2.7 -

2.6 -

2.5 -

ma

_y 2.4 -

No ga 2.3 -

U 2;

a o cn r

2.2 -

2.1 -

2 -

1.9 -

1.8 -

1.7 -

1.6 -

1.5 -

+

1.4 i

1981 1982 1983 1984 YEAR O

AVG 0

AVG - 1SD A

AVG + 1SD i

j

4

8

, 9 1

RETAW

.K D

N S

1 IR 3

+

D 8

G R

9 V

E 1

A WF l

A UQ A

R A

D NE 4

1 I

N R

1 E

F A

RU 7 N

E O

Y G

3 C

I F

1 NU L

S A

C C

D O

S

/

L 2

1 E

8 9

9 V

1 G

R V

U A

C O

DN ERT G

VA O

1 8

9 1

7 6

5 4

3 2

1 O

bA 5

4

[

8 1

9 1

RETAW K

D N

S

?

1 E

3

+

8 G

9

)

V N /

A l

1 I

i F

Cp

(

A A

N 5

O I

1 I

t T

E A

R R B T

A U

S E

G Y

S R

I F

S O

T O

AC R

ID G

I S

N D

2 I

E 89 p

V a

1 G

R V

U A

C 0

D N

E RT GV A

O 1

8

- 1 9

1 4 3 2 1

0 9 8 7 6 5 4 3 2 1

O 1

2 3 4 1

1 1

1 1

5oa g

FIGURE 16 TREND CURVE-TRITIUM-FINISHED DRNK WATER INDICATOR STATION (pCi/l) 5.5 I

5 -

4.5 -

4 -

• F a

V 3.5 -

55

~$

~

8 E

3 -

6 N

s-t 2 _

l 1.5 -

l

+

t 3

1981 1982 1983 1984 YEAR O

AVG O

AVG - ISD A

AVG + ISD l

[

z 48 1

9 1

RETAW D

S K

I N

+

3 R

y8 G

D l

1

)

9 V

/

A iC N

p

(

A IF SN 7

N O

1 IT R

I E

A R

T A

U 7 S

E G

Y 3

I F

R 1

O T

A S

CI D

C D

N S

I 1

E 28 V

9 i

R G

1 U

VA C

D O

N E

RT GVA n

1

. 8

9 1

0 0

0 0

0 0

0 6

5 4

3 2

1

_a

4 8

9 1

TN E

M ID DS E

1 S

3

+

8 N

G

)

i 9

g V

I 1

k A

/

7 iC 3

p A

(

1 N

8 O

1 S

T R

I E

C A

A R

T U

E S

G Y

R R

I F

O O

T F

AC I

E D

D V

N S

I 1

2 R

8 U

9 i

1 C

G VA D

N O

ERT GVA O

1 8

9 a

1 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

0 0

8 7

6 5

4 3

2 1

E.

a

_ * ~ ~

FIGURE 19 TREND CURVE FOR CS-137 IN FISH INDICATOR STATION (pCi/kg) l 2.2 -

+

2 -

1.8 -

1.6 -

1.4 -

g 1.2 -

E 1

N 3

kS 0.8 -

3 5

0.6 -

v 0.4 -

0.2 -

1 O

+

-0.2

-0.4

- 0.6 1981 1982 1983 1984 YEAR O

AVG O

AVG - ISD A

AVG + 1SD

7 FIGURE 20 TREND CURVE FOR TRITIUM IN GROUNDWATER LOCAL UNCONFINED AQUlFIER (pCl/l) 4.5 4

4 -

3.5 -

3 -

S

?

-n-hg 2.5 -

[

{

"O

-1 D

2 -

+

1.5 -

-o-1

+

0.5 i

i 1981 1982 1983 1984 YEAR O

AVG O

AVG - 23D A

AVG + 1SD

]

FIGURE 21 TREND CURVE /CS-137 IN GROUNDWATER LOCAL UNCONFINED AQUlFER 4.5 ww 4 -

3.5 -

j 3 -

HV 2.5 -

h

=

S e

2 -

1.5 -

1 0.5 -

0 1981 1982 1583 1984 YEAR O

AVG 0

AVG - 1SD A

AVG + 1SD

.