Text

Radiological Environ Surveillance Rept,1981
	ML20050B364
Person / Time
Site:	FitzPatrick
Issue date:	12/31/1981
From:	; POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK
To:	;
References
	NUDOCS 8204050250
	Download: ML20050B364 (173)
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1981 I

y II RADIOLOGICAL ENVIRONMENTAL ll SURVE;LLANCE REPORT JANUARY 1,1981 through DECEMBER 31,1981 I

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NUCLEAR POWER PLANT 5 8[16 I

OPERATING LICENSE NO. DPR-59 I

DOCKET NO. 50- 333 Power Authority of the State of New York I

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I POWER AUTilORITY OF THE STATE OF NEW YORK ANNUAL ENVIRONMENTAL OPERATING REPORT PART B:

RADIOLOGICAL REPORT JANUARY 1,1981 - DECEMBER 31, 1981 JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333 I

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I TABLE OF CONTENTS Page I.

INTRODUCTION 1

Introduction 1

l Program Objectives 2

II.

PROGRAM li.lPLEf.1ENTATION AND DESIGN 3

Sample Methodology 3

Analysis Performed 7

Changes in Program 7

III.

SAMPLE SUMMARIES 11 IV.

ANALYTICAL RESULTS 25 V.

DATA SUMMARIES AND CONCLUSIONS 65 Lake Program 66 Terrestrial Program 80 Conclusions 97 Exceptions to the Program 98 References 99 VI.

lilSTORICAL DATA 100 Vll.

FIGURES AND MAPS 128 I

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LIST OF TABLES Table I

Required Sample Collection and Analysis (Lake Program) 9 Table 11 Re-tluired Sample Collection and Analysis (Land Program) 10 Table 1

Periphyton Results 32 Table 2

Dottom Sediment Results 34 Table 3

Mollusk itesults 35 Table 4

GA!.iMARUS Results 36 Table 5

Fish Results 37 Table 6

Water Composite Results, Gross Beta 38 Table 7

Water Composite Results, Tritium, Sr-89, Sr-90 39 Table 8

Water Composite Results, Gamma Isotopic 40 Table 9, 10 Particulate Filter Results, Gross Beta 41 Table 11 Particulate Composite Results, Gamma Isotopic 43 Table 12, 13 Airborne 1-131 Results 45 Table 14 TLD Results 47 Table 15 Radiation Monitor Readings 49 Table 16 Milk Results,1-131 53 Table 17 Milk Results, Gamma Isotopic 54 Table 18 Milk Results, Sr-90 56 Table 19 Milch Animal Census Results 57 Table 20 Food Product Results, Gamma Isotopic 59 Table 21 Fodder Crops and Pasture Grass Results, Gamma Isotopic 61 Table 22 Surface Unter Results, Gamma Isotopic 63 Table 23 Soil and Sediment Results, Gamma Isotopic 64 i

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LIST OF FIGUI!ES Page l

Figure 1

Off Site Environmental Stations and TLD Locations 129 Figure 2

Off Site Radiological Monitoring Stations 130 Figure 3

On Site Environmental Stat'.ns and TLD Locations 131 Figure 4

Produce, Meats, Poultry and Eggs Sample Locations 132 Figure 5

Milch Animal Census Locations 133 Figure 6

Special Samples 134 Figure 7

New York State Regional Map 135 Figure 8

Bottom Sediment Description 136 Figure 9

Graph - Periphyton (Co-60) 137 Figure 10 Graph - Periphyton (Cs-137) 138 Figure 11 Graph - Periphyton (Cc-144) 139 Figure 12 Graph - Mollusk (Co-60) 140 Figure 13 Graph - Mollusk (Mn-54) 141 Figure 14 Graph - Mollusk (Sr-90) 142 Figure 15 Graph - Bottom Sediment (Co-60) 143 Figure 16 Graph - Bottom Sediment (Cs-137) 144 Figure 17 Graph - Fish (Cs-137) 145 Figure 18 Graph - Fish (Sr-90) 146 Figure 10 Graph - Lake Water Gross Beta 147 Figure 20 Graph - Lake Water Gross Beta for 1981 148 Figure 21 Graph - Air Particulate Gross Beta 149 Figure 22 Graph - Air Particulate Gross Beta, Weeks 1-26 150 Figure 23 Graph - Air Particulate Gross Beta, Weeks 27-52 151 lii

t Page Figure 24 Graph - Air Particulate Comnosite (Co-60) for 1981 152 Figure 25 Graph - Air Particulate Composite (Cs-137) for 1981 153 Figure 26 Graph - Air Particulate Composite (Mn-54) for 1981 154 Figure 27 Graph - Air Particulate Composite (Ru-106) for 1981 155 Figure 28 Graph - Air Particulate Composite (Co-60) for 1980-1981 156 Figure 20 Graph - Air Particulate Composite (Cs-137) for 1980-1981 157 Figu e 30 Graph - Air Particulate Composite (Mn-54) for 1980-1981 158 Figure 31 Graph - Air Particulate Composite (Zr-95) for 1980-1981 159 i

Figure 32 Graph - Air Particulate Composite (Nb-95) for 1980-1981 160' Figure 33 Graph - Air Particulate, Composite (Ce-144) for 1980-1981 161 Figure 34 Graph - Air Particulate Composite (Cc-141) for 1980-1981 162 Figure 35 Graph - Air Particulate Composite (Itu-103) for 1980-1981 163 Figure 36 Milk (Cs-137) 104 Figure 37 Milk (Cs-137), Stations 16, 4, 14, 12, 7, 40, for 1981 165 Figure 38 Milk (1-131) 166 Figure 39 Milk (Sr-90) 167 I

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I INTRODUCTION I

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I I-A INTRODUCTION The Power Authority of the State of New York (PASNY) is the owner and licensee of the James A. FitzPatrick Nuclear Power Plant (JAFNPP) which is located on the eastern portion of the Nine Mile Point promontory approximately one-half mile due east of the Niagara Mohawk Power Corporation (NMPC) Nine Mile Point Nuclear Station (NMPNPS). The NMPNPS Unit #1 is located on the western portion of the site and is a boiling water reactor with a design capacity of 610 MWo. The NMPNPS has been in commercial operation since the fall of 1969.

Located between the JAFNPP and I

NMPNPS, Nine Mile Point Unit #2 is under construction.

NMPNPS Unit #2 will have generation capacity of 1,100 MWe and is expected to be colnpleted in 1986. The JAFNPP is a boiling water reactor with a power output of 820 MWe (net).

Initial fuel loading of the reactor core was completed in November of 1974. Initial criticality was achieved in late November,1974 and commercial operation began in July of 1975.

I The site is located on the southern shore of Lake Ontario in Oswego County, New York, approximately seven miles northeast of the city of Oswego, New York. Syracuse, New York is the largest metropolitan center in the area and is located 40 miles to the south of the site. The area I

consists of partially wooded land and shoreline. The land adjacent to the site is used mainly for recreational and residential purposes.

For many miles to the west, east and south the country is characterized by rolling terrain rising gently up from the lake, composed mainly of glacial deposits.

Approximately 34 percent of the land area in Oswego County is devoted to farming.

The Radiological Environmental Monitoring Program for the FitzPatrick Plant is a site program with responsibility for the program shared by the Power Authority and Niagara Mohawk. Similar Technical Specifications for radiological monitoring of the environment allows for majority of the sampling and analysis to be a joint undertaking. Data generated by the program is shared by the two facilities with review and publication of the data undertaken through each organization.

This report is submitted in accordance with Section 5.6.1 of Appendix B, to DPR-59, Docket 50-333.

Environmental reports of this nature have been compiled and submitted in semiannual and annual reports since 1974. This report contains data from samples representing the period from January 1,1981 to December 31, 1981.

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I-B PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program are as follows:

1.

To determine and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive materia' sources.

2.

To monitor and evaluate natural radiation levels in the environs of the JAFNPP site.

3.

To meet the requirements of applicable state and federal regulatory guides and limits.

4.

To provide information 4 ich the general public can evaluate the environmental aspects o.. clear power using data which is factual and unbiased.

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PROGRAM IMPLEMENTATION AND DESIGN I

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II PROGRAM IMPLEMENTATION AND DESIGN To achieve the objectives listed in Section I-B, sampling and analysis are performed as outlined in Tables I and II in this section.

The sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the James A. FitzPatrick Plant I

and the Nine Mile Point Station. The site staff is assisted by a contracted environmental engineering company, Ecological Analysts, Inc. (EA). EA 'was responsible for performing the 1981 Aquatic Ecology Study at the site which I

is required by Section 4.1, Appendix, B of the plant operating license

( DPR-59). The staff required by EA to perform the aquatic studies program is used to perform the radiological aquatic sampling and assists the site staff with the terrestrial sampling program.

1.

SAMPLE COLLECTION METiiODOLOGY A.

Lake Water (surface water)

The two indicator stations are the respective inlet canals at

'I JAFNPP and NMPNPS. These samples are composited using continuously running pumps which discharge into large holding tanks.

The control station sample is collected from the city of Oswego water intake. The sample is drawn from the intake prior to treatment and is composited in a large sample bottle.

Quarterly composite samples are made up from proportional aliquotes of monthly samples.

B.

Air Particulate / Iodine The air sampling stations are located in two rings surrounding the site.

The on site locations ring the terrestrial area around the plants inside the site boundary.'

The on site sampling network is composed of nine stations. The off site air monitoring locations range six to 17 miles from the site and are composed of six stations. Air monitoring locations are shown on Figures 1 and 2 of Section VII.

The air particulate glass fiber filters are approximately two inches in diameter and are placed in sample holders in the intake line of a vacuum sampler. Directly down stream from the particulate filter I

is a 2 x 1 inch charcoal cartridge used to absorb airborne radioiodine. The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis.

The particulate filters are composited on a monthly basis by location (off site, on site) after being counted individually for gross beta activity.

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C.

Milk During 1981 milk samples were collected from six locations.

Five of these locations are considered indicator samples and the sixth is I

used as a control sample. Milk samples are collected in polyethylene bottles from the bulk storage tank at each sampled farm.

Before the sample is drawn the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk I

and butterfat. Two gallons are collected during the first week of each month from each of the five farms. An additional one gallon is collected from each farm at mid month f.o make up the second I

half of the monthly ceinposite.

The complete composite is made up from one gallon collected during the first week of the month and one gallon from the mid month collection. The samples are frozen and shipped to the analytical contractor within 24 hours2.777778e-4 days 0.00667 hours 3.968254e-5 weeks 9.132e-6 months of I

collection in insulated shipping containers. The milk sampling locations are found on Figure 4 of Section VII.

D.

Meat, Poultry and Eggs Semiannually one kilogram of meat is collected from locations within a 10 mile radius of the site. Weekly phone calls are made to the I

local slaughter houses to determine availability of slaughtered livestock from within the sampling area. Whenever possible meat samples are collected from locations previously used. Attempts are I

made to collect a control sample located outside the 10 mile radius, with each series of collections.

Semiannually one kilogram of poultry and one kilogram of eggs are I

collected from each of three locations within a 10 mile radius of the site.

Attempts are made to collect poultry and eggs at the same time as the meat samples.

The poultry and eggs are frozen and shipped in insulated containers. Whenever possible samples are obtained from previously sampled farms. Attempts are made to collect a control sample located outside the 10 mile radius, with each series of collections (see Section VII, Figure 5).

E.

Iluman Food Crops Human food crops are collected during the late summer harvest season at locations previously sampled, if available. One kilogram each, of the two types of fruits and/or vegetables from each of I

the three locations within a 10 mile radius of the site are collected.

The types of fruits and vegetables sampled depend on what is locally available at the time of collection. Attempts are made to collect at least one broad leaf type vegetable from each location.

I The fruits and vegetables are chilled prior to shipping and shipped fresh in insulated containers. Attempts are made to collect a control sample located outside the 10 mile radius for each type of sample (see Section VII, Figure 5).

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F.

Soil Samples Soil samples are required once every three years. Samples were

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collected during 1980. Soil samples were taken at each of the 15 I

air monitoring stations at this time. No soil samples were collected during 1981.

G.

Fish Samples Available fish species are removed from the Nine Mile Point Aquatic Ecology Study monitoring collections during the spring and fall I

collection periods. Samples are collected from a combination of the four on site sample transects and one off site sample transect (see Section Vil, Figure 6).

Available species are selected under the following guidelines:

1) 0.5 to I kilogram of edible portion only of a maximum of three species per location.

2)

Samples composed of more than 1 kilogram of single species from the same location are divided into samples of 1 kilogram each prior to shipping.

A maximum of three samples per I

species per location are used. Weight of samples are the edible portions only.

I Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in insulated containers for analysis.

II.

GAMMARUS GAMMARUS (fresh water shrimp) sampI~es are collected by EA personnel during the spring and fall season from two on site locations and from one off site location. Natural and artificial substrates are used to collect samples. The GAMMARUS samples are removed from the sampling gear, frozen and shipped to the analytical contractor in incalated shipping containers.

I.

Mollusks During the spring and fall seasons at two on site locations and one off site location benthic samples are collected. The mollusks are collected by divers and sorted. The tissue is removed from the shell, frozen and shipped for analysis in insulated containers.

J.

Bottom Sediments One kilogram of bottom sediment sample is collected at two on site locations and one off site location. Samples are collected at the same time and location as the mollusk samples, where possible, by a diver. The samples are placed in plastic bags, sealed and shipped for analysis in insulated containers.

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K.

Periphyton Periphyton (fresh water algae) samples are collected in the spring and fall seasons from two on site locations and one off site I

location.

Periphyton is collected from natural substrates. The periphyton is scraped from the substrates into vials, labeled, frozen and shipped in insulated containers for off site analysis.

L.

TLD (direct radiation)

Thermoluminescent dosimeters (TLD's) are 'used to measure direct I

radiation in the JAF/NMP-1 environment. The TLD stations are place'd around the site using a two zone distribution.

The first group of TLD's is located within the site boundary and are called I

"on site" TLD's.

The second set of TLD stations is the "off site" stations, located at the off site air monitoring stations and in areas of special interest such as population centers. Also included in the off site group are the field control TLD's.

A total of 45 TLD stations were used for the 1981 TLD program.

Each TLD set is made up of two CaSOg dosimeters (two chips per

.I dosimeter), sealed in a polyethylene package to insure dosimeter integrity. The TLD packages are further protected by placement in Plexiglas " birdhouses", or by tape sealing to supporting surfaces. The dosimeters are collected, replaced and evaluated on

.I a quarterly basis.

M.

Special Samples Several additional sample media were collected during the 1981 sample period to enlarge the data base for farm related sample media.

I The following additional sampl,e media were were collected during 1981

1)

Pasture Soil - Soil samples were collected three times during 1981 from each of the six milk sample locations. Each sample was analyzed for gamma emmiters using gamma spectral I

analysis.

2)

Pasture Grass - Pasture grass was collected four times in I

1981, during the pasture season, in conjunction with the pasture soil collections. Each sample was analyzed for gamma emitters using gamma spectral analysis.

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Surface Water - Water samples were collected from the milk herd water sources at each of the six farms used as milk sampic locations.

Four such collections were made during 1981. Each sample was analyzed for gamma emitters using E

gamma spectral analysis.

In addition to the farm samples, 3

surface water samples were collected from the general drainage pattern of the land area surrounding the site. Two such surface water collections were made during 1981.

Each

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ENVIRONMENTAL SAMPLE DATA
SUMMARY
SAMPLE ITPE Of ANALYSIS N O. O f LOWER llMIIS ST,,,,,,
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RANCE MEDIUM PERIORufB AND ANAllSIS Of BEIECil0N MEAN IIM VA DE M BE (units)
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Lake Llollusk Gamma Isotopic pCilg (wet)
Cont rol De-7 2
0.27 0.16 ALL LI.D K-40 2
NONE 0.11:
0.01 0.34 0.33 0.01 Lin-54 2
0.026 0.022 ALL LLD Co-60 2
0.022 0.016 ALL LI.D Ita-226 2
0.056 0.037 ALL LLD Co-58 2
0.031 0.020 ALL LLD Cs-137 2
0.028 0.019 ALL LLD Cs-134 2
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0.028 0.024 0.061 A
0.061 0.061 0.0 Cs-134 4
0.028 0.021 ALL LLD Lake Mollusk Sr-89, Sr-90 pCilg (wet)
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NONE 0.046 0.008 0.0519 0.0399 0.012 ludicator l
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9.0135 0.0578 ALL LLD S r-90 4
NONE 0.094 0.060 0.132 0.00468 0.127 A ONtf ONE POSlilVE VALUE.N0 STAllSilCS POSSIBLE.
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ENVIRONMENTAL SAMPLE DATA
SUMMARY
$ AMPLE IIPE Of ANAlf11$
NO.0F LOWER llulI5
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MEDIUM PERFORMEB AND ANAlf51$
OF DEIECil0N MEAN DEVIAll0N VALUE VALUE (esils)
NUCllDE PERIORMED (range)
Lake GAMMAltOS Gamma Isotopic pCilg (wet)
Sr-89. Sr-90 Cont aul Co-60 2
1.1 0.16 ALL LLD K-40 2
1.3 1.1 A
1.1 1.1 0.0
.1n-54 2
0.72 0.12 ALL LLD Cs-137 2
0.71 0.14 ALL LLD Cs-134 2
0.69 0.11 ALL LLD Ita-226 2
1.5 0.22 ALL LLl>
S r-89 2
0.0667 0.034 A
0.034 0.034 0.0 Sr-90 2
NONE 0.099 0.066 0.146 0.052 0.094 on Indicator Co-60 4
1.8 1.4 1.4 1.414 2.4 0.4 2.0 K-40 4
3.5 2.1 5.7 A
5.7 5.7 0.0 Mn-54 4
1.7 0.19 ALL LLD Cs-137 4
1.7 1.3 4.7 4.67 8.0 1.4 6.6 Cs-134 4
1.5 0,68 0.76 0.764 1.3 0.22 1.08 Ita-226 4
3.3 0.44 Alt,LLD S r-89 4
0.109 0.048 0.069 A
0.069 0.069 0.0
ir-90 4
NONE 0.193 0.058 0.274 0.138 0.136 A - ONLY ONE P051TIVE VALUE.NO SI41151lCS POSSIBLE.
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1 ENVIRONMENTAL SAMPLE DATA
SUMMARY
SAMPLE ITPE OF ANAlf515 N 0. 0 F LOWER llMIIS STANDARD MAIIMUM MINIMDM RANCE MIDIUM FIRFORMID AND ANALT5IS OF DETECIl0N MEAN DEllAll0N VALUE VALUE (usili)
NUCllDE FIRFORMID frange)
Lake 1%h Gamma Isotopic pC1/g (wel)
Sr-89. Sr-90 Cont rol K-40 6
NONE 3.02 0.319 3.3 2.4 0.9 Hn-54 6
0.012 0.007 ALL LLD Cs-137 6
NONE 0.043 0.016 0.062 0.028 0.034 Cs-134 6
0.011 0.0058 ALI. I.LD Co-58 6
0.017 0.0071 ALL LLD S r-89 6
0.0166 0.0057 0.015 0.001 0.015 0.014 0.001 S r-90 6
0.00656 0.00239 alt. I.LD Co-60 6
0.017 0.0088 ALI. LLD 5
Indicator 4-40 16 NONE 3.34 0.365 4.0 2.9 1.1 un-54 16 0.014 0.0066 0.018 A
0.018 0.018 0.0 Cs-137 16 NONE 0.061 0.021 0.10 0.027 0.073 Cs-134 16 0.01 0.0034 0.009 0.0004 0.0096 0.0091 0.0005 Co-58 16 0.017 0.0069 0.042 0.006 0.047 0.035 0.012 S r-89 12 0.0171 0.00514 0.011 0.012 0.025 '
O.004 0.021 3r-90 12 0.00597 0.00175 0.0022 A
0.0022 0.0022 0.0 Co-60 16 0.018 0.0073 0.098 0.03 0.064 0.012 0.052 i
A - ONLT ONE P0$lilVE VALUE, NO SIAllSilCS F05518tt.
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a ENVIRONMENTAL SAMPLE DATA SUMMAitY 5 AMPLE ITPE Of ANALTS15 ll0. 0 F LOWER EINIIS
$g,,,,,,
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ME8lIM PERF0ENES AN0 ANALT515 0F BETECil0E MEAN DEVIAll04 VALIE VALUE (units)
NBCLIDE PERIORMED (rased l
l 1.ake liuter Gross ticta Analysis pCl/l Contnst 12 2.0 0.9 3.24 1.27 5.8 1.9 3.9 Indicator 24 NONE 2.98 1.19 5.4 1.2 4.2
1. uke Water Tritium Analysis pCill Contrul 6
NONE 293.3 49.3
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228 258.3 76.9 388 183.
205.
l l
1.ake Water S r-89 Analysis pCill Control 4
2.38 1.02 ALL LLD Indicator 8
2.79 0.97 0.78 A
0.78 0.78 0.0 B
l.ske % tater S r-90 Analy sis pCl/l Control 4
(10NE 0.68 0.176 0.868 0.484 0.384 Indicator 8
1.76 0.69 0.74 0.08 0.805 0.597 0.208 A - ONLY ONE POSillVE VALBE.NO $1AllSilCS POS$llLE.
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~I ENVIRONMENTAL SAMPLE DATA
SUMMARY
SAMPLE ITPE Of ANALTS15 N O. 0 F LOWER llMIIS l
MANDARD MAUMM MINIMUM NE0 lull PERIORMEB AND AN4ti$ls OF DEiftil0N MEAll RANCE l
(units)
NUCllDE PERf0RMED (range) l Airtsorne Gamma Isotopic l' articulate Analysis Cont rol p
m x 10 Co-60 12 0.50 0.36 0.47 0.251 0.904 0.17 0.734 Mn-54 12 0.41 0.19 J.94 0.702 2.09 0.25 1.84 Co-58 12 0.40 0.19 ALL LLD N ts-95 12 NUNE 40.05 43.65 124.0 0.49 123.50 Z r-95 12 1.11 0.49 23.72 19.66 55.7 0.66 55.04 Cs-137 12 NONE 1.37 1.16 3.66 0.22 3.44 Cs-134 12 0.61 0.59 ALL LLD Ce-141 12 0.58 0.26 9.56 5.46 16.8 1.60 15.2 Ce-144 12 NONE 19.05 19.51 57.6 1.25 56.35 lla-140 12 7.00 1.02 ALL LLD Itu-103 12 2.63 0.20 13.35 9.17 27.7 0.66 27.04 It u-106 12 3.60 1.83 11.31 6.75 24.8 3.94 20.86 i
l Indicator Co-60 12 0.30 0.396 0.211 0.903 0.186 0.717 Mn-54 12 0.215 0.132 0.725 0.415 1.33 0.190 0.140 l
Co-58 12 0.280 0.129 0.075 A
0.07 5 0.075 0.00 N t2-95 12 NONE 36.85 39.38 111.00 0.411 110.589 Zr-95 12 0.478 0.404 20.10 17.55 50.30 0.441 49.860 Cs-137 12 NONE 1.22 1.14 3.64 0.144 3.496 Cs-134 12 0.476 0.135 0.697 A
0.697 0.697 0.00 Ce-141 12 0.327 0.195 7.44 5.Ib 14.50 0.530 13.97 Ce-144 12 NONE 16.51 16,91 49.50 0.869 48.63 Da-140 12 6.40 0.80 ALL LLD Itu-103 12 0.182 0.173 10.34 8.17 23.70 0.263 23.44 Itu-106 12 1.38 1.01 7.81 6.06 19.30 1.40 17.90 Alrtsorne lodine Gamma Analysis Analysis 1-131 pCl/m8 Cont rol 312 0.043 0.009 ALI.1.LD Indientor 468 0.063 0.004 0.008 0.01 0.042 0.016 0.026 A - ONLY ONE P0511tVE VALUE.NO SIAll51lCS POS$1BLE.
l l
m M
M M
M M
M ENVIRONMENTAL SAMPLE DATA
SUMMARY
SAMPl[
IYPE OF ANALTS!$
N D. 0 F LOWIR tlMIIS I N IO I IEU M[DIUM PERIORMED AND ANALYSl$
OF DE1[Cil0N MEAN RANCE (mails)
NUC110E PIRFORMID (range)
Environmental Off Sito TI.D's TLD ltendings miteni/Standaril First Quarter 23 NONE 4.85 0.59 6.63 4.12 2.51 Month Second Quarter 23 NONE 5.14 0.37 5.88 4.47 1.41 Third Quarter 22 flONE 3.82 0.34 4.49 3.24 1.25 l'ourtli Quarter 22 NONE 5.04 0.45 6.04 4.17 1.87 Year 90 llON E 4.72 0.69 6.63 3.24 3.39 On Sito r.l.niltor TLD's (Excluding D-1 On Site)
First Quarter 8
NONE 5.41 0.76 6.88 4.74 2.34 Second Quarter 8
NotlE 5.56 0.84 7.45
4. -
2.65 Tlilrd Quarter 8
NONE 4.75 0.56 5.81 4.0$
1,72 to Fourtta Quarter 8
NONE 5.26 0.56 6.25 4.32 1.93 o
Year 32 NONE 5.24 0.73 7.45 4.09 3.36 Continuous Exposure llato Itadiation Imcation Monitors millhr
( Averago Off Sito Monthly Value)
C 12 NONE 0.017 0.003 0.02 0.013 0.007 On Site D-1 12 IJONE 0.024 0.015 0.07 0.012 0.058 D-2 12 NONE 0.016 0.003 0.02 0.012 0.008 E
12 NONE 0.018 0.002 0.02 0.015 0.005 F
12 NONE 0.018 0.003 0.023 0.012 0.015 G
12 NOHE 0.014 0.003 0.02 0.011 0.009 il 12 NONE 0.032 0.004 0.04 0.026 0.314 1
12 NONE 0.014 0.002 0.02 w.011 0.009 J
12 NONE 0.015 0.002 0.02 in 312 0.008 K
12 NONE 0,015 0.002 0.018 0.012 0.006 l
A - ONLY ONE PoslilVE VALU(,N0 STAllSilCS POS$1BLE.
ENVIRONMENTAL SAMPLE DATA
SUMMARY
5AMPtf IIPE Of ANAlf515 N O. 0 f LOWER tlMII5 STANDARB MAllMUM MINIMUM MEDIUM PERFORMED AND ANAlf515 Of DEllCil0N MEAN RANCE SWAN MH M
(seits)
NUCll0E PERf0RMED (raagd
&lijk Analysis 1-111 pCill location No.
4 8
0.284 0.091 ALL LLD No.
7 3
0.155 0.106 ALL I.LD No. 12 8
0.237 0.108 ALL LLD No. 14 8
U.259 0.095 ALL LLD No. 16 8
0.249 0.095 ALL LLD No. 25 2
0.206 0.147 ALL LLD No. 40 (Control.
8 0.234 0.082 ALL LLD t4
& link Analysis Gamma Isotopic pCill S r-90 lascation 13 o. 4 K-40 8
NONE 1.388.
203.10 1.800 1.200 600.
Us-137 8
6.0 3.6 4.8 0.56 5.4 4.3 1.1 Sr-90 8
NONE 3.92 1.92 6.80 1.81 4.99 tio. 7 4-40 3
NONE 1.287.
287.29 1.500.
960.
540.
Cs-137 3
8.3 4.4 AI.L Lt.D S r-90 3
NONE 3.51 1.25 4.30 2.10 2.20 f
l A - ONLT ONE P05tilVE VALUE.NO $1All51lCS P055tBit.
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ENVIRONMENTAL SAMPLE DATA
SUMMARY
f 1
SAMPLE ifrEOFANALT$l$
N O. 0 F LOWER ElutiS I
U8 MINIMUM MIDIUM PERf0RMED AND ANALTS15 Of DEIECIl0N MEAN BANCE EVIAll0N VALBE VALUE (seits)
NUCtIDE PERIORMED (range) uent a l'oultry Gamma Isotopic pCilg (wet)
Cont rol
~
Co-60 5
0.023 0.011 ALL LLD K-40 5
nolle 2.64 0.34 3.1 2.4 0.7 Cs-134 5
0.079 0.01 ALI, LLD Co-137 5
0.023 0.0085 0.021 0.0 05 0.024 0.017 0.007 Co-58 5
0.020 0.012 ALL LLD kin-54 5
0.015 0.0097 ALL LLD Indicator
' 13 0.019 0.01 ALL LLD Co-60 K-40 13 NONE 2.86 0.474 3.5 1.7 1.8 Cs-134 13 0.014 0.0078 ALL LLD co Cs-137 13 0.016 0.0086 0.036 0.011 0.068 0.023 0.045 g
Co-58 13 0.020 0.0085 ALL LLD kin-54 13 0.016 0.0078 ALL LLD Chicken Eggs Gamma Isotopic pCilg (wet)
Cont rol Co-60 2
0.016 0.011 ALL LLD K-40 2
110t4E 1.1 0.0 1.1 1.1 0.0 Cs-134 2
0.010 0.0088 ALL LLD Us-137 2
0.010 0.0097 ALL LLD Co-58 2
0.013 0.012 ALL LLD f.In-54 2
0.011 0.010 ALL LLD Indicator Co-60 6
0.014 0.0069 All. LLD 1;-40 6
140t4E 1.02 0.141 1.2 0.81 0.39 Cs-134 6
0.012 0.0053 Al,l. I.I.ll Cs-137 6
0.011 0.0062 ALL LI.D i
l Co-58 6
0.015 0.0072 ALI. LLD kin-54 6
0.012 0.0057 ALL L1,D A ONLY ONE P05111VE VALUE, NO $1AllSitCS POS$1BLE.
i
M M
M M
M M
ENVIRONMENTAL SAMPLE DATA
SUMMARY
$ AMPLE IIFE OF ANAliS!$
N O. 0 F LOWER EIMIIS STANDARB MAI! MUM MINIMUM M10lgM FIRFORMED AND ANALT515 Of DETEtil0N MEAN RANCE gg gyg g yg (seils)
NUCtIDE FIRIORMID (raagd Prinluce Gamma Isotopic pCl/g (wet)
Cont rol li-40 2
nolle 4.2 2.26 5.8 2.6 3.2 Cs-134 2
0.0095 0.0035 ALL LLD Cs-137 2
0.011 0.0038 ALL LLD Ita-226 2
0.021 0.0079 ALL LLD lle-7 2
0.039 0.33 A
0.33 0.33 0.0 Itu-103 2
0.012 0.0051 ALL LLD Itu-106 2
0.094 0.034 AI.I. LLD Z r-95 2
0.0086 0.021 A
0.021 0.021 0.0 lib-95 2
0.00G7 0.013 A
0.013 0.013 0.0 linlicator K-40 7
IJONE 2.21 0.036 2.7 1.8 0.9 Cs-134 7
0.094 0.0027 ALL LLD Cs-137 7
0.043 0.0032 ALL LLD Ita-226 7
0.086 0.00G ALI. LLD 1
tie-7 7
0.380 0.032 ALL I.LD Itu-103 7
0.046 0.0017 ALL 1.LD Itu-106 7
0.088 0.029 ALL LI.D Z r-95 7
0.080 0.007 ALL LI.D tib-95 7
0.049 0.0047 ALL LLD Prixtuco 1-131 pCilg (wet)
Cont rol 1
0.019 A1.1. 1.LD Intlicator 3
0.017
-0.013 AI.L Lt.D A - ONLT ONE Pos!IIVE VALUE, NO $1AllSilCS POSSIBLE.
.y IV Nit.
ANALYTICAL RESULTS
I IV ANALYTICAL RESULTS Sample Summariec l
Environmental sample data is summarized by tables. Tables are provided for select sample media and contain data summaries based on quarterly mean values. Mean values are comprised of both positive and LLD l
values where applicable. These tables are entitled " Environmental Sample i
S ummary".
4 I
I 25
M M
M M
M l
Th f '
ENViltONhlENTAL SAMPLE SUMMAllY Medium / Sample Location Nuclide 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter (map # *)
pCill i
i Ingestion Milk 4
Cs-134 NS
<3.3
<3.9
<4.0 1(-40 NS 1,475 1,334 1,600 Cs-137 NS
<4.6
<5.6
<5.7 S r-90 NS 5.77 3.94 3.08 l
Ba-140 NS
<33.0
<36.0
<50.0 La-140 NS
<G.6
<6.9
<10.8 40 Cs-134 NS
<3.7
<3.8
<3.7 1(-40 NS 1,350 1,383 1,334 Cs-137 NS
<4.8
<5.5
<4.6 S r-90 NS 5.88 4.18 3.4 Ba-140 NS
<36.0
<38.0
<46.0 M
La-140, NS
<8.0
<7.1
<10.4 14 Cs-134 NS
<3.5
<3.6
< 3.8 IC-40 NS 1,400 1,276 1,333 Cs-137 NS
<5.1
<4.6
<4.8 S r-90 NS 3.74 3.58 2.2 Ba-140 NS
< 38.0
<35.0
< 46.0 La-140 NS
<7.8
<?.2
<9.3 16 Cs-134 NS
<3.3
<3.6
< 3.2 1(-40 NS 1,325 1,316 1,467 Cs-137 NS
<6.2
<6.0
<5.4 S r-90 NS 7.34 4.96 5.33 Ba-140 NS
< 34.0
< 36.0
< 35.0 La-140 NS
<6.9
<7.0
< 6.6 Not Sampled (not part of grazing season)
NS
=
Samples Not Available from Farm Location NA
=
See Figure 5, Section Vil
(*)
=
j O
I ENVIRONMENTAL SAhlPLE
SUMMARY
(cont.)
Medium / Sample Location Nuclide 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter (map # *)
pCill ingestion Milk 25 Cs-134 NS NA
<4.3(a)
NA K-40 NS NA 1,400 NA Cs-137 NS NA 24.0 NA S r-90 NS NA
.3.78 NA Ba-140 NS NA
<35.0 NA La-140 NS NA
<9.6 NA 12 Cs-134 NS
<3.6
<3.8
<3.6 K-40 NS 1,400 1,300 1,583 Cs-137 NS
<6.8
<6.2
<5.0 Sr-90 NS 7.26 6.76 4.0 Ba-140 NS
<36.0
<38.0
<40.0 ej La-140 NS
<8.0 46.4
<G.2 7(b)
Cs-134
<3.5 E-40 1,294 Cs-137
<5.3 S r-90 3.90 Ba-140
<39. 0 La-140
<8.0 Not Sampled (not part of grazing season)
NS
=
Samples Not Available from Farm Location NA
=
Samples Available on 07/20/81 and 08/03/81 Only (a)
=
Sampling Started on 10/81 at This Location (b)
=
See Figure 5, Section Vil
(*)
=
'M M
M M
M 7
M ENVIItONMENTAL SAMPLE SUMMAltY Medium / Sample Location Nuclide 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter (map #)
pCill j
Milk 4
I-131 NS
<0.166
<0.211
<0.153 40 I-131 NS
<0.186
<0.201
<0.134 14 I-131 NS
<0.197
<0.204
<0.157 1
's 16 I-131 NS
<0.189
<0.200
<0.134 1
25 I-131 NS NA
<0.176(a)
NA l
l 12 I-131 NS
<0.180
<0.208
<0.163 7
I-131 NS NS NS
<0.129(b)
IJA Sample Not Available
=
NS Not Sampled
=
Only Two Sampic Dates Available -- 07/20/81 and 08/03/81 (a)
=
Sampling Initiated at Location #31 on 10/05/81 (b)
=
\\
ENVIllONMENTAL SAMPLE SUMMAltY Medium / Sample Location Nuclide 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter AlltiloltNE Particulate Gross Beta Filters On Sites pC1/m3 D1 0.164 0.320 0.138 0.037 D2 0.158 0.311 0.129 0.038 E
0.163 0.329 0.133 0.040 F
0.159 0.328 0.135 0.037 G
0.167 0.311 0.140 0.038 11 0.108 0.285 0.122 0.032 g
1 0.152 0.241 0.12G 0.037 J
0.129 0.246 0.128 0.028 K
0.116 0.254 0.127 0.029 Off Sites C
0.147 0.312 0.130 0.037 D1 0.151 0.313 0.130 0.034 D2 0.162 0.338 0.138 0.036 E
0.165 0.339 0.151 0.037 F
0.160 0.339 0.150 0.039 G
0.158 0.322 0.133 0.037 m
M M
M M
M M
re tr 719724622 882241 a
221221222 11221 2 u
000000000 000000 Q
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t 4
re tr 102378453 828004 a
332321 222 222322 u
000000000 000000 Q
000000000 000000 dr 3
re Y
tr 042056841 434681 t
l a
322322222 222212 A
u 000000000 000000 M
Q 000000000 000000 M
d U
n S
2 E
L P
M r
A e
t S
r 729945630 453717 a
221222222 222222 L
u 000000000 000000 A
Q 000000000 000000 T
t N
s E
1 M
N O
e 3
t d
1 m l
i 3
i l
/
c 1i V
u C
N N
p I
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12 i
12 i
t JK S
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S ci l
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A e
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f g
l'NViltONMENTAL SAMPLE
SUMMARY
l Medium / Sample Location Nuclide 1st Quarter 2nd Quarter 3rd Quarter 4th Quarter TLD On Sites Direct Itadiation mitem/std. mo.
13.78 16.56 13.83 12.99 On Site Environmental Stations 5.41 5.57 4.74 5.26 Off Sites 4.88 5.16 3.84 5.08 U
M M
m m
m m
m m
m m
m m
m m
IABLE I CONCENTRAil0HS OF GNtlA [ hillers IN PERIPitTION $NFLES Results in Units of PCl/9(wet) t 2 slyna CDLLECiION NUCL1 DES Jtif AUCUST SliE FOUND 1981 1981 Fitzpatrid Be-7 2.4 0.4 9.611.0 (03)
K-40 9.5e1.0 5.0to.7 hr54 0.0910.03 0.5610.06 Co-58
<0.04 (0.08 Fe-59
<0.03 (0.2 Co-60 0.2210.04 3.R:0.4 Zn-65
<0.1 (0.2 Zr-95 1.010.2 0.910.1 Mi-95 3.9 #0.4 2.910.3 Itu-103 0.16 to.05 (0.2 Cs-134
<0.05 2.310.2 U
Cs-137 0.4710.05 1612 Ce-144 1.910.2 2.I10.3 Ra-226 0.2010.08 (0.3 Th-232 0.31to.09
<0.3 Others All(LLD All dLD Nine Mlle Point Be-7 (0.9 9.3 0.9 (02)
K-40 n.0to.9 6.5 10.7 Mn-54 0.1610.01 0.1710.04 Co-58 (0.04 (0.07 Fe-59
<0.1 (0.2 Co-60 1.910.2 1.210.1 Zn-65 (0.1
<0.1 Zr-95 0.0410.00 0.7310.08 Mi-95 1.7to.2 2.220.2 Cs-134 0.54t0.05 0.56t0.06 Cs-137 4.0 0.4 4.5to.5 Ce-144 0.710.2 1.510.2 Ra-226 a.3610.05 0.3410.06 Th-232 0.3 to.1 0.4 10.1
'Others AlldLD All<tLD
/
l TABLE I (cont.)
CONCENTRATIONS OF GAltM U11TTERS IN PERIPHYTON SAlfLES Results in Units of pC1/g(wet) t 2 sirpa COLLECTION NUCLIDES JUL1r AUGUST SITE FOUND 1981 1981 Oswego Be-7 1.910.3 5.710.6 (00)
K-40 1.920.8 6.lio.o Hn-54 C.03 0.05to.02 Co-58
<0.04 d.03 Fe-50 (0.09 (0.08 Co-60 (0.04
<0.03 Zn-65 (0.09
<0.08 d
Zr-95 0.54t0.05 0.43 t0.05 lb-95 1.610.2 1.3to.1 Ru-103 0.15t0.04 0.1010.04 Ru-106 0.510.2 0.510.2 Cs-134 (0.04
<0.03 Cs-137 0.1410.03 0.24f0.03 Ce-144 0.610.2 1.110.2 Ra-226 0.2410.05 0.1710.05 Th-232 0.1210.07 0.1610.08 Others All(LLD All(LLD
V a o m.
o o o g
d 2 d d d C e5 E E E E E E 9 N 9 N 9 2 9
5 9 4
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s
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TABLE 4 CDNCENTRATIONS OF Sr-89 AND Sr-90 AND GAlltA EltlTTERS IN CWttARtfS SNFLES Results in Units of pC1/g(wet) i 2 sirpa COLLECTION COLLECTION GAlflA UllTTERS SITE DATE Sr-89 Sr-90 K-40 lin-54 Co-58 fe-59 Co-60 Zn-65 Cs-134 Cs-137 Ra-226 Others Fi tzpatrick 6-28-31 to
<0.1 0.2710.03
<3.5
<0.4
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<0.6 1.310.3 8.010.8 (0.7 All(LLD (03) 7-09-81 8-13-81 to
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<0.8
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<1.4
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<0.7
<1.3
<1.3 All<LLD 8-24-81 o
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<0.5 0.210.1 1.410.3
<0.4 A11 <LLD 7-09-81 (02) 8-13-81 to 0.06t0.05 0.J410.02 (21
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<1.8
<3.6
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<1.7
<3.3 A11<tLD 8-21-81 Oswego 6-28-81 to
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<0.2
<0.3
<0.1
<0.1
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TABLE 6 CONCENTRATIONS OF BETA EMITTERS IN LAKE WATER SAMPLES Results in Units of pCi/1 + 2 sigma Station Code January February March April May June JAF Inlet 2.6+1.0 4.0+1.4 4.4+1.4 5.1+1.7 2.7+0.7 1.2+0.7 NMP Inlet 4.4+1.1 4.6+1.4 3.2+1.3 5.4+1.7 2.3+0.7 1.5+0.7 Raw City Water (control) 4.3+1.1 5.8+1.4 4.4+1.4 3.7:-1.6
<0.88
<2.0 Station Code July August September October November December JAF Inlet 1.9+0.7 1.9+0.7 2.2+0.7 2.2+0.5 2.6+0.3 2.3+0.4 NMP Inlet 4.4+0.8 2.0+0.7 3.4+0.7 2.8+0.5 2.3+0.3 2.1+0.4 Raw City Water (control) 2.0+0.7 1.9+0.7 2.5+0.7 2.8+0.5 2.6+0.3 2.4+0.4
o TABLE 7 CONCENTllATIONS OF TlllTIUhl AND STitONTIUM-89 AND 90 IN LAl(E WATEll (QUAllTEll COhlPOSITE SAMPLES) llesults in Units of pCill 12 sigma ST..flON CODE PEltlOD DATE TIllTIUhl S r-89 Sr-90 JAP INLET First Quarter 12/30/80 to 03/31/81 223 1 84
<2.2
<0.9 Second Quar'er 03/31/81 to 06/30/81 315 1 120
<1.0 0.8 1 0.3 Third Quarter 06/30/81 to 09/30/81 388 1 130
<1.0 0.G 1 0.3 Fourth Quarter 09/30/81 to 12/31/81 212 1 140
<1.1
<0.7 NhlP INLET First Quarter 12/31/80 to 03/31/81 189 i 97
<1.8 1.0 0.5 Second Quarter 03/31/81 to 06/30/81 298 1 120 0.8 1 0.7 0.7 1 0.4 Third Quarter 06/30/81 to 09/30/81
<228
<1.0 0.9 0.3 Fourth Quarter 09/30/81 to 12/31/81 183 1 140
<2.8
<1.8 I!AW CITY WATEll First Quarter 12/31/80 to 03/31/81 211 84
<2.4 0.9 1 0.6 (CONTitOL)
Second Quarter 03/31/81 to 06/30/81 328 i 140
<1.0 0.8 0.3 Third Quarter 06/30/81 to 09/30/81 284 130
<1.2 0.5 1 0.4 Fourth Quarter 09/30/81 to 12/31/81 282 1 120
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TAllLE 8 CONCENTitATIONS OF GAMMA EMITTERS !!1 LAKE WATElt SAMPLES Ilesults in linits of pCi/l i 2 sigma Station Co<le Nuclide January February Mareli April May June JAF IllLET Co-60
<1.9
<l.0
<2.0
<2.1
<1.3
<l.2 Mn-54
<l.3
<1.5
<l.4
<1.4
<1.0
<1.4 Cs-137
<1.2
<1.5
<l.3
<1.4
<0.9
<l.0 Cs-134
<1.3
<l.3
<l.2
<1.3
<0.8
<1.0 I
Others
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<LLD
<LLD
<LLD
<LLD
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<1.9
<1.8
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<1.2 1
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<1.3
<l.4
<l.6
<l.8
<1.4
<1.2 i
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<l.2
<1.4
<l.4
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<1.0
<1.0 l
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<1.0
<l.1
<l.3
<1.5
<1.0
<1.0 Others
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD OSWP (C0fiTROL)
Co-60
<2.1
<l.8
<2.1
<1.9 1.410.8
<1.1 Mn-54
<1.3
<1.5
<1.7
<l.7
<1.1
<1.1 Cs-137
<l.1
<1.6
<l.2
<1.7
<0.8
<1.0 Cs-134
<1.4
<1.4
<l.3
<1.5
<1.0
<1.0 u
Others
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
Station Code Nuclide July August September October November December JAF If1LET Co-60
<1.7
<2.2
<2.0
<1.4
<1.5
<1.6 Mn-54
<l.7
<1.6
<l.4
<1.1
<1.1
<0.9 Cs-137
<1.2
<1.3
<1.3
<1.0
<l.1
<1.2 Cs-134
<1.2
<1.3
<l.0
<1.1
<0.9
<1.3 Others
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 9 MILE IllLET Co-60
<1.2
<2.0
<2.2
<1.7
<1.3
<1.4 Mn-54
<1.6
<l.4
<1.6
<0.9
<1.1
<1.2 Cs-137 2.310.8
<1.3
<l.6
<1.3
<1.0
<1.0 l
Cs-134
<1.3
<l.2
<1.5
<0.9
<1.1
<l.2 l
Others
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1
l OSWP (C0liTROL)
Co-60
<1.8
<2.2
<1.0
<1.6
<1.8
<1.3 Mo-54
<1.1
<l.6
<0.8
<1.0
<1.1
<1.0 l
Cs-137
<1.4
<1.7'
<0.7
<1.1
<1.2
<l.1 l
Cs-134
<1.4
<1.4
<0.6
<1.6
<1.1
<1.2 l
Others
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
TAbtE 9 HnP/JAF GIVE ENVIROHNENT AL AIRPORNE P ARI1 Cut.AIE SAtwtES - 0FF SITE ST ATIDHS CROSS DETA ACIIVITV pct /n*312 Signa LOCAi!OH Ut[K END DAIE C--DFF p t -DF F D 2-DF F E -- DF F F--OFF C--OFF
===-----
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0.005*0.806 0.08418.E96 0.98210.086 01/41/06 8.87910.886 0.000*t.906 0.092*S.036 01/01/13 0.08419.006 8.08415.886 0.090*e.886 0.009*0.006 0.05618.005 8.10B+0.000 01/01/20 0.137*8.888 9.839*0.889 S.165*9.009 0.17940.889 8.133*0.087 8.194*9.011 01/01/27 8.15418.009 0.14010.000 e.14310.000 0.13510.000 0.12910.808 0.10710.018 81/02/s4 s.00318.886 8.86910.005 0.077*0.006 0.!!010.807 0.09310.886 0.131*0.007 08/82/18 8.119*s.888 0.11010.088 0.12510.000 0.12818.800 0.267*0.811 0.115*t,009 01/02/10 0.16718.009 0.16310.059 0.174*0.009 0.1581 089 e.itB+0.006 9.28510.ste 9
t 01/82/24 8.15718.818 8.139*t.009 0.13810.009 0.130+0.809 9.129*0.089 8.114*0.088 l
01/03/83 8.499*8.887 9.19118.887 8.89510.087 0.89610.887 0.896*t.806 0.059*0.806 B1/03/10 e.12518.089 0.11318.008 0.81718.000 3.11619.008
& 11010.897 0.197*0.009 01/03/17 0.19000.810 0.21918.010 0.222*0.818 0.219*0.011 0.23310.049 8.189*0.081 i
88/83/24 0.183*S.880 9.19410.018 0.208*0.010 0.194*0.018 8.189*0.009 0.17118.081 01/03/31 0.337*0.083 0.401*0.013 0.47818.815 0.50810.016 0.45210.013 S.392*0.015 01/04/87 8.395*0.814 8.42910.014 0.390*0.014 8.44318.815 0.39210.013 0.427*t.015 01/84/14 0.299*8.912 8.29510.012 0.30410.013 0.37410.014 0.39419.813 e.30418.912 01/04/21 0.33010.013 0.372*0.813 0.41110.015 0.367+0.014 8.30t*0.012 0.30010.013 01/04/20 9.275*0.812 0.315+0.812 0.347*0.013 0.330*0.413 0.380*0.012 s.33410.012 01/05/05 8.370*0.813 8.459+0.014 8.46718.015 0.519*s.016 8.53010.014 0.404*0.814 01/85/12 8.29210.012 0.34410.012 0.355+0.013 8.34314.013 0.360*0.812 0.365*8.812 81/05/19 0.330*0.014 0.27718.819 0.382*e.813 0.31210.813 0.280*0.811 0.34310.083 01/05/27 8.494*t.815 9.507*0.015 S.535*0.016 0.549*s.816 0.427*0.013 0.430's 083 01/86/02 8.428*8.917 8.175*0.018 8.457*8.080 9.364*0.015 8.417*0.814 8.327+0.013 ra 01/06/10 0.26000.012 8
0.274*0.012 0.24B18.011 0.26410.010 9.24218.018 4
01/06/16 0.20010.012 8.191+0.811 0.167*0.011 0.191*I.012 0.19910.010 0.17618.810 01/86/23 0.169*0.010 8.860*0.009 8.863**.088 0.15310.815 0.13010.888 0.148*0.088 01/06/30 0.28410.011 0.238*0.011 8.209+0.811 0.28910.012 0.23619.010 0.21210.880 01/07/07 0.197*0.811 0.24410.411 0.23918.012 0.229'O.012 0.21510.010 8.88010.889 01/07/14 0.26060.013 0.29910.012 0.303*0.813 0.29518.813 0.27610.081 0.277*0.882 01/07/21 S.149*0.010 0.12810.888 0.14310,009 0.14910.010 8.152*8.088 8.86818.809 01/87/20 0.176*0.018 0.161*0.809 8.191+0.010 8.194*e.811 0.169*0.000 0.197*0.819 01/80/84 0.204*0.013 0.387*8.812 0.20518.012 e.43718.016 8.51110.015 0.29210.012 01/00/11 0.00310.088 S.091*0.887 0.091*0.887 0.192*0.008 8.5,94*S.086 8.999*0.087 01/00/18 0.076*0.487 8.871*0.006 0.871+0.007 8.87740.007 8.87210.085 8.869*9.886 91/08/25 0.109*0.000 8.81710.000 0.11468.888 8.12110.009 0.11049.007 0.09310.087 01/09/81 8.!!210.009 0.113*0.000 0.110*e.809 s.12210.089 0.123*0.087 0.821*0.888 01/89/09 0.056*0.006 0.054*S.005 0.04718.005 e.84718.885 0.04718.884 8.e3918.005 01/09/15 0.10910.009 s.it3*s.089 0.81710.009 0.117*0.010 0.128et.800 8
01/09/22 8.840*0.005 0.04210.005 8,839+g.005 0.039*0.006 s.43610.004 s.840*0.086 01/09/29 8.83119.885 0.83t+0.485 0.835*0.845 0.83t+0.005 0.03818.004 8.03313.005 01/10/87 0.034*t.805 0.027*0.084 0.83216.805 3.83218.005 0.032*0.004 9.833*S.005 01/18/14 8.06218.886 s.04210.005 0.057*s.886 8.86110.007 0.005*0.006 8.85719.886 U1/10/20 0.031*0.005 8.03218.005 8.84118.806 9.84t+B.086 0.030*0.004 0.044*0.986 08/10/27 0.026*8.085 0.022*8.004 0.022*S.005 0.02610.005 0.02419.084 0.03818.005 01/11/03 8.05240.006 0.052*0.006 0.049*t.006 0.05318.006 0.04918.505 t.04810.086 01/11/10 0.04tet.085 0.050*0.085 0.05t+0.005 0.847*0.806 8.849*8.004 8.848*e.885 01/11/17 S.046*t.004 0.04360.004 0.04618.005 0.85010.006 0.042*0.084 8.85815.007 01/11/24 0.030*s.804 0.82118.004 0.019*0.004 s.821*t.004 0.023*0.003 0.026*t.004 01/12/01 9.02013.094 0.028*0.884 0.02918.004 S.930*0.805 0.033+0.004 0.03110.005 01/12/00 8.84610.004 0.84210.894 9.83910.005 0.04010.005 s.045*S.884 8.834*8.885 01/12/15 0.02018.803 8.02418.004 0.01918.054 9.81648.004 0.01618.883 8.917*0.004 01/12/22 0.02419.904 0.824*0.884 0,62510.805 0.12910.005 0.02218.804 8.82418.884 DL/12/29 0.839*8.004 0.040*0.005 0.037*0.005 0.039*0.006 0.84118.004 0.042*0.005 0 PutW HGI OPERAi10HAl_
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TABLE 11 CONCENTitATIONS OF GAMMA EMITTERS IN MONTilLY COMPOSITES OF JAF AIR PAltTICULATE SAMPLES ltesults in Units of 10-8 pCi/m 12 sigma 3
Nuclides January February March April May June OFF SITE COMPOSITE Co-60 0.4 0.1
<0.4 0.4 1 0.1 0.7 1 0.1 0.9 1 0.2
<0.5 Mn-54
<0.3
<0.4 0.6 0.1 1.3 1 0.1 2.1 1 0.2 1.1 1 0.2 Nb-95 21.0 1 0.5 48.0 1 0.9 69.0 1 0.8 124.0 1 1.2 116.0 1 1.1 48.4 1 0.8 Zr-95 13.0 1 0.6 23.0 1 0.8 32.0 1 0.8 55.7 1.2 52.7 1 1.0 18.7 i 0.8 Cs-137 0.5 1 0.1 0.9 1 0.1 1.1 1 0.1 2.7 0.5 3.7 ! 0.2 2.2 1 0.2 Cs-134
<0.3
<0.38
<0.5
<0.6
<0.6
<0.5 Cc-141 10.3 1 0.3 12.0 0.3 13.0 ! 0.3 16.8 1 0.4 10.3 1 0.3 2.9 1 0.2 Ha-140
<0.3
<7.0
<4.3
<6.1
<5.4
<4.7
.w Ce-14 4 5.3 1 0.4 12.0 1 0.6 32.0 1 0.7 48.4 1.0 57.6 1 1.0 20.3 1 0.8 Itu-106
<3.6 4.2 1 1.0 11.0 1 1.3 15.5 1 1.7 24.8 1 1.8 11.4 1 1.3 Itu-103 13.0 i 0.4 16.0 1 0.5 19.0 1 0.4 27.7 0.8 20.1 1 0.5 6.4 1 0.3 ON SITE COMPOSITE Co-60
<0.3 0.5 0.1 0.3 1 0.1 0.6 1 0.1 0.9 i 0.1 0.3 1 0.1 Mn-54 0.2 1 0.1 0.4 1 0.1 0.6 1 0.1 1.2 1 0.1 1.3 1 0.1 0.9 1 0.1 Nb-95 16.5 0.4 55.0 1 0.8 57.0 1 0.6 111.0 1.0 105.0 1 0.8 44.8 1 0.6 Z r-95 11.7 1 0.4 25.0 0.7 28.0 1 0.6 50.3 1 0.9 46.0 1 0.8 19.8 1 0.6 Cs-137 0.4 1 0.1 0.7 0.1 0.9 1 0.1 2.7 0.2 3.6 1 0.2 2.1 1 0.2 Cs-134
<0.3
<0.3
<0.3
<0.5
<0.5
<0.4 Cc-141 8.4 1 0.2 11.0 1 0.3 11.0 1 0.2 14.0 0.3 9.5 1 0.2 3.0 1 0.2 Ila-140
<1.9
<6.4
<3.2
<5.1
<4.3
<4.0 Co-144 3.7 1 0.3 11.0 1 0.5 17.0 1 0.5 43.5 0.8 49.5 i 0.8 28.7 1 0.7 ilu-106 2.4 1 0.6 2.9 0.7 6.3 0.8 12.7 1 1.3 19.3 i 1.4 9.6 1 1.0 Itu-103 10.4 1 0.3 13.0 1 0.5 17.0 1 0.3 23.7 1 0.5 17.6 1 0.4 6.7 1 0.3
M M
M M
M M
M M
M M
TAllLE 11 (cont.)
)
CONCENTitATIONS OF GAMMA EMITTEIIS IN MONTIILY COMPOSITES OF JAF Allt PAllTICULATE SAMPLES 3
Itesults in Units of 10-8 pCi/m 12 sigma l
l Nuclides July August September October November December OFF SITE COMPOSITE Co-60 0.4 1 0.2 0.6 1 0.3
<0.5 0.2 i 0.1 0.2 0.1
<0.4 f.In-54 0.7 1 0.2 0.3 1 0.2
<0.4
<0.2
<0.2
<0.2 Nb-95 37.2 1 1.3 11.4 1 0.9 3.3 1 0.5 1.3 1 0.8 0.6 1 0.2 0.5 1 0.2 Z r-95 13.8 1.1 4.0 0.8
<1.1 0.7 1 0.3
<0.5
<0.5 Cs-137 2.6 1 0.3 1.6 1 0.3 0.410.2 0.2 0.1 0.3 ! 0.1 0.3 0.1 Cs-134
<0.3
<0.3
<0.3
<0.2
<0.2
<0.2 Cc-141 1.6 1 0.3
<0.6
<0.5
<0.3
<0.3
<0.3 11a-140
<3.8
<4.0
<2.7
<1.8
<1.0
<1.4 Cc-144 26.9 1 1.3 9.4 ! 1.0 3.1 1 0.7 2.0 1 0.5 1.5 1 0.5 1.3 1 0.4 ltu-106 12.0 1 2.3 3.9 1 2.1
<3.3
<1.8 7.6 1 0.9
<1.9 llu-103 4.0 0.5 0.7 1 0.3
<0.5
<0.3
<0.2
<0.3 ON SITE COMPOSITE Co-60 0.2 1 0.1 0.521 0.2 0.4 1 0.2 0.2 1 0.1 0.3 1 0.1 0.2 1 0.1 Mn-54 0.8 1 0.2 0.4 1 0.1
<0.2
<0.1
<0.2
<0.2 Hb-95 37.5 1 1.0 10.4 0.7 3.5 1 0.4 1.3 1 0.2 0.6 1 0.2 0.4 1 0.2 Zr-95 14.5 1 0.9 3.7 0.6 1.6 1 0.4 0.4 1 0.2
<0.4
<0,5 Cs-137 2.1 1 0.2 1.1 1 0.2 0.5 0.1 0.2 1 0.1 0.3 ! 0.1 0.110.1 Cs-134 0.7 1 0.3
<0.2
<0.2
<0.2
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<0.3
<0.2
<0.2
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<3.3
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<2.3
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<1.3
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<0.2
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46
TABLE 14 DIRECT RADIATION 11EASUREllENTS - fluARTERLY REStLTS STATION JANUARY APRIL JULY OCTOBER NtNBER LOCATION to to to to APRIL JtLY OCTOBER DECEMBER 3
D1 on Site 11.7810.66 11.66tl.04 10.4711.06 6.6920.64 4
D2 on Site 5.64to.56 5.7220.25 5.1410.53 5.7710.66 5
E on Site 4.6810.46 5.1910.72 4.7510.64 5.2010.16 6
F on Site 4.8420.42 4.8010.71 4.0910.50 5.0410.23 7
G on Site 4.5410.41 4.9410.30 4.5110.48 4.3210.29 8
C off Site 5.4810.48 5.4810.61 4.4910.34 5.9410.12 9
D1 off Site 4.6110.39 4.9710.49 4.0210.70 4.91t0.06 10 D2 of f Site 4.1210.57 4.8810.11 3.8710.46 4.5710.82 11 E off Site 4.2510.70 4.9210.22 3.5610.30 4.3510.57 12 F off Site 4.3910.28 5.0710.42 3.7810.63 5.3110.82 13 G off Site 4.8510.30 4.7410.40 3.9110.91 5.3510.70 14 LeMass RJ, SW Oswego 5.0910.46 5.08to.57 3.7610.34 5.0710.56 15 Pole 66. W. Bound-Rible Cany 4.1910.52 4.4710.31
'3.2410.53 4.1710.33 18 Prog. Cen. Picnic Area 4.7410.69 (1)
(1) 5.0710.50 19 Pole 9. E. Bound 5.5610.44 5.5211.06 4.1410.70 4.98 t0.47 23 H on Site 6.B810.27 7.5410.90 5.8110.91 6.25 tl.41 24 1 on Site 5.8210.12 5.7710.21 5.0210.97 5.1610.48 25 J on Site 5.26t0.54 5.4010.48 4.2510.31 5.0610.66 26 K on Site 5.6311.29 5.2110.92 4.3910.41 5.2510.19 27 Nor. Fence-NIM Sector, JAF 17.6110.96 16.8510.46 13.9311.44 9.8310.66 28 Light Pole (E) JAF 42.1612.05 40.4116.32 38.4712.40 33.1112.66 29 N. Fence (E)JAF 52.7213.41 62.2212.56 69.46t11.48 79.0123.58 30 N. Fence (NW) JAF 14.6610.88 14.9211.54 13.10t2.21 0.18t0.98 31 N. Fence (NW) fatP-1 14.5510.82 13.0911.51 13.1411.91 (1) 39 East Fence, Rad. Waste-id1P-1 21.6211.72 25.02tl.82 17.1112.71 25.9710.74 43
.9 al Rt. 3 from Rt.1048 4.5610.69 5.88 t0.37 3.8510.30 5.2910.36 44 Cor. Rt 3 and Kelly Drive 4.7610.11 5.2910.31 3.6110.21 4.8910.17 45 Cor. Rt 64 and Rt. 35 4.4710.66 5.3410.27 3.4611.11 5.0310.43
6 Cor. Rt.176 and Black Creek Rd.
4.4520.46 5.3110.45 (1) 4.9210.72 4r NE Shoreline (JAF) 21.1912.53 46.00t2.13 11.48t0.92 15.13 t0.47 48 36 mi (N) on Access Rd. (JAF) 6.28t0.24 7.4510.56 6.3311.28 5.6910.53 49 Phoenix NY Control 4.5210.88 4.57t0.50 3.4910.31 4.7510.19 50 Lake Rd. West of J On-Site 5.35t0.26 5.4110.53 4.38 t0.94 5.1710.62 51 Oswego Steam Sta. N End of W Fence 5.4511.70 4.7210.36 3.7410.52 4.6910.72 52 East lith St. Fitzhu9h Park Sch.
5.2310.26 5.6410.24 4.4710.71 5.6310.99 53 Breachell & Chestnut St. -
Ful ton H.S.
4.4 710.19 5.3210.57 4.2310.60 4.9010.35 54 Liberty St. & Co. Rt.16 -
Hexico H.S.
4.4310.34 5.1910.86 3.74t0.54 5.1110.47 55 Hinnnan Rd. & Co. Rt. 5 -
Pulaski H.S.
4.3910.44 5.501.87 3.6810.41 4.8510.34 m
M M
M M
M l
TABLE 14 (cont.)
DIRECT RADIATION ItEASUREIENTS - QUARTERLY RESULTS STATION JANUARY APRIL JULY OCTOBER NtMER LOCATION to to to to APRIL JULY OCTOBER DECEMBER 56 Rt.104 - New Haven H.S. (SE Comer) 5.3610.39 5.3110.86 3.8610.39 5.1710.43 57 Co. Rt. 29 & Hiner Rd. (SE) -
Lycomin9. NY 5.2610.78 4.8610.45 3.7220.53 4.9310.36 58 Co. Rt. 1 - ALCAN (S of Entrance Rd.)
5.1220.30 5.2710.40 3.5510.52 4.9911.05 59 Environmental Lab - JAF 24.7311.40 32.4612.94 34.4112.15 17.38tl.10 3
co 60 S. Shore (Fish Point)
Little Sodus Day, NY 6.6310.52 5.5910.05 4.4410.92 6.0410.36 61 700' N of #48 (On Access Rd.) - JAF
'8.7910.39 10.3510.33 6.2810.37 6.47tl.33 65 Dutch Rid 9e Rd. & Kerf ten Rd. (SE) 5.4810.36 4.7010.21 3.5110.65 (1) 9.04 t19.71 10.34124.72 8.48124.03 8.73124.71 (1)
TLDs lost.
l t
{
TABLE 15 CONTINUOUS RADIATION MONITORS * (GM) mR/hr FIRST llALF mR/hr LOC ATION PERIOD MIN.
MAX.
AVG.
C Off Site January 0.01 0.03 0.016 February 0.01 0.03 0.015 March 0.01 0.028 0.018 April 0.015 0.025 0.02 May 0.01 0.04 0.02 June 0.01 0.029 0.02 D On Site January 0.01 0.018 0.02 E
1 l
February 0.01 0.041 0.019 5
March 0.01 0.04 0.022 April 0.01 0.72 0.021 May 0.01 0.053 0.022 June 0.01 0.09 0.025 D On Site January 0.01 0.08 0.015 2
February 0.01 0.033 0.015 March 0.01 0.08 0.012 April 0.01 0.033 0.013 May 0.01 0.082 0.013 i
June 0.01 0.09 0.012 E On Site January 0.01 0.06 0.015 February 0.01 0.069 0.015 March 0.01 0.06 0.018 April 0.012 0.039 0.018 May 0.012 0.075 0.018 June 0.013 0.06 0.02 F On Site January 0.01 0.03 0.012 February 0.01 0.05 0.023 March 0.012 0.04 0.018 April 0.012 0.04 0.019 May 0.013 0.042 0.019 June 0.014 0.059 0.019 i
Detectors are ' bugged' to insure on scale readings.
49
L E
TABLE 15 (cont.)
CONTINUOUS RADIATION MONITORS * (Gf.1) mR/hr I
FIRST IIALF mR/hr LOCATION PERIOD MIN.
MAX.
AVG.
G On Site January
.0.01 0.048 0.012 February 0.01 0.023 0.012 March 0.01 0.035 0.012 I
April 0.01 0.032 3.012 May 0.01 0.023 0.012 June 0.01 0.032 0.012 11 On Site January 0.02 0.048 0.03 February 0.022 0.06 0.031 March 0.025 0 03 0.031 I
April 0.027 058 0.037 1.
May 0.026
'J. 0 8 0.04 June 0.023 0.089 0.038 1 On Site January 0.01 0.025 0.011 February 0.01 0.05 0.011 March 0.01 0.06 0.012 I
April 0.01 0.04 0.013 May 0.01 0.093 0.014 June 0.01 0.094 0.015 J On Site January 0.01 0.032 0.015 February 0.01 0.042 0.014 March 0.01 0.05 0.015 April 0.01 0.058 0.015 May 0.01 0.06 0.016 June 0.01 0.09 0.015 K On Site January 0.01 0.05 0.018 February 0.01 0.031 0.016 March 0.01 0.035 0.015 I
April 0.01 0.048 0.015 May 0.01 0.04 0.013 June 0.01 0.099 0.015 I
g
oetectors are ' bugged' to insure on scate readings.
1 50
1 TABLE 15 (cont.)
CONTINUOUS RADIATION MONITORS * (GM) mR/hr SECOND IIALF mR/hr LOCATION PERIOD MIN.
MAX, AVG.
C Off Site July 0.01 0.04 0.02 August 0.01 0.025 0.015 September 0.01 0.06 0.015 October 0.01 0.04 0.013 November 0.01 0.025 0.013 December 0.01 0.02 0.015 D On Site July 0.01 0.07 0.025 l
1 August 0.01 0.07 0.025 m
September 0.01 0.08 0.02 October 0.01 0.09 0.07 November 0.01 0.041 0.012 December 0.01 0.05 0.012 D, On Site July 0.01 0.09 0.012 August 0.01 0.08 0.02 September 0.015 0.08 0.02 October 0.012 0.075 0.02 November 0.012 0.055 0.016 December 0.01 0.025 0.018 E On Site July 0.015 0.098 0.02 August 0.015 0.055 0.02 September 0.01 0.08 0.02 October 0.012 0.098 0.016 November 0.011 0.049 0.015 December 0.01 0.025 0.018 F On Site July 0.01 0.04 0.018 l
August 0.01 0.04 0.017 September 0.01 0.07 0.02 October 0.01 0.073 0.02 1
November 0.01 0.05 0.015 December 0.01 0.02 0.013
Detectors are ' bugged' to insure on scale readings.
1 51
I I
TABLE 15 (cont.)
CONTINUOUS RADIATION MONITORS * (GM) mR/hr SECOND HALF mR/hr LOCATION PERIOD MIN.
MAX.
AVG.
G On Site July 0.01 0.04 0.011 August 0.01 0.06 0.02 September 0.01 0.06 0.02 October 0.011 0.078 0.015 November 0.011 0.039 0.016 December 0.01 0.022 0.018 II On Site July,
0.022 0.07 0.03 August 0.02 0.085 0.03 September 0.01 0.07 0.035 October 0.017 0.06 0.026 November 0.01 0.048 0.03 December 0.02 0.047 0.03 I On Site July 0.01 v.08 0.02 August 0.01 0.09 0.015 September 0.01 0.09 0.015 October 0.01 0.04 0.013 November 0.01 0.04 0.012 December 0.01 0.022 0.014 J On Site July 0.01 0.08 0.02 August 0.01 0.09 0.018 September 0.01 0.06 0.015 October 0.01 0.053 0.015 November 0.01 0.025 0.012 December 0.01 0.022 0.012 K On Site July 0.01 0.07 0.018 August 0.01 0.085 0.015 September 0.01 0.06 0.018 October 0.01 0.09 0.012 November 0.01 0.03 0.012 December 0.01 0.025 0.013
Detectors are ' bugged' to insure on scale readings.
52
1 8
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TABLE 17 CONCENTRATIONS OF GNtiA ElllTTERS IN llILK (110NTILY C0lFOSITE SNIPLES)
Results in Units of pCl/l k 2 sipa 5-05-81 6-01-81 7-06-81 8-03-81 9-01-81 10-05-81 11-02-81 12-07-81 to to to to to to to to STATION NUCLIDES 5-18-81 6-15-81 7-20-81 8-17-81 9-21-81 10-19-81 11-16-81 12-22-81 a
K-40 1500tl50 14001140 1200t120 14001140 12001120 14001140 12001120 1800t180 Cs-134
<2.7
<2.8
<4.1
<3.5
<2.8
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<3.6 4.313.0 5.413.6 (9.0
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<27
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<49
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<10
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<LLD
<LLD (LLD (LLD (LLD 14 K-40 1500t150 1300t130 1400t140 14001140 960t110 11001120 12001120 1400t140 Cs-134
<2.8
<3.3
<2.8 (3.7
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<3.8
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<4.9 4.3t3.0 4.812.2
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<30
<35
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<4.3
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<6.0
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<3.9
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~ 7.013.1 6.713.6 7.4 t 3.4
<4.8 4.812.8 (6.6 Ba-140
<31
<33
<37
<42
< 34
<34 (41
<31 La-140
<8.5
<5.2
<9.0 (7.8
<6.7
<5.7
<ll
<4.8 Others
<LLD (LLD (LLD
<LLD
<tLD (LLD (LLD (LLD
TABLE 17 (cont.)
CONCENTRATIONS OF GVilA DilTTERS IN HILK
(!10NTla.Y C0lFOSITE SMFLES)
Results in Units of PC1/1 t 2 signa 5-05-81 6-01-81 7-06-81 8-03-81 9-01-81 10-05-81 11-02-81 12-07-81 to to to to to to to to STATION NKLIDES 5-18-81 6-15-81 7-20-81 8-17-81 9-21-81 10-19-81 11-16-81 12-22-81 40 (Centrol)
K-40 1200t120 13001130 13001130 14001140 13031130 14001140 1400t140 1100t110 m
Cs-134
<3.9
<4.1
<4.2
<2.8
<4.4
<3.0
<2.9
<3.5 Cs-137 (5.3 (4.9 (6.0
'7.013.2 (5.3
<4.9
<3.4
<4.3 8a-140
<39
<41
<42
<36 (41
<25
<D6
<30 La-140
<7.8 (8.4
<9.9
<5.0 (7.8
<7.6
<23 (5.8 Others (LLD (LLD
<LLD
<LLD (LLD
<LLD (LLD
<LLD 7
K-40 11001140 15001150 960t100 Cs-134
<3.0 (4.5
<3.4 Cs-137
<4.4 (8.3
<4.6 Ba-140
<28
<59 (28 La-140
<4.8
<12
<8.5 Others (LLD (LLD (LLD Indicates that no LLD was calculated for that nuclide.
No result because the sanpling station was not in operation.
lABLE 18 CONCENTRATIONS OF STRONTitti-90 IN HILK (HONTILY C0rlPOSITE SMlPLES)
Pesults in Units of P l/l 2 2 signa C
5-05-81 6-01-81 7-06-81 0-03-81 SNfLE to to to to 5-18-81 6-15-81 7-20-01 8-17-81 4
6.812.2 4.110.9-1.810.5 4.421.3 14 4.2t2.5 2.610.8 2.511.3 5.212.4 16 7.114.4 8.0 t 1.7 3.610.8 6.511.5 12 1012 1113 8.7tl.4 5.Itl.2 40 (Control) 5.9tl.5
8.011.9 2.8t1.6 3.2tl.3 7
9-01-81 10-05-81 11-02-81 12-07-81 SNfLE to to to to 9-21-81 10-19-81 11-16-81 12-22-81 4
6.413.3
'3.6t1.0 2.410.6 1.9t1.2 14 2.410.6 2.0t1.1 1.210.7
<3.3 16 4.9to.9 5.9i1.2 3.310. 8
$.611.2 12 7.911.5 4.721.0 3.410.8 3.812.3 40(Control) 5.911.0 5.611.1 5.110.9 2.4tl.0 4.211.4 2.110.8 4.3t1.3 7
No result because the saglin9 station was not in operation.
l i
l TABII 19 E
MILCH ANIMAL CENSUS SPRING 1981 TOWN NO. ON MAP NO. OF MILCH ANIMALS New Haven 1
31C 2
45C 4*
71C 3
29C 12*
45C 5
40C 7*
45C Mexico 6
60C 8
2C 14*
65C 9
1G 10 33C 11 42C 13 49C l
15 44C E
17 SC 18 40C 19 150C 20 34C Richland 21 58C Hannibal 32 SC 40**
34C Scriba 16*
39C l
23 2C 24 1G 26 6G 25*
1C 27 1C 28 2C 33 1C Volney 29 25C Totals 998 Cows 8 Goats C = Cows; G = Goats
= Milk Sample Locations
= Milk Sample Control Location I
57
I
!I TABIz 19 (cont.)
MILCH ANIMAL CENSUS SUMMER 1981 11 TOWN NO. ON MAP NO. OF MILCH ANIMALS New IIaven 1
27C 2
45C 4*
78C 3
29C 12*
40C S
38C 7*
50C Mexico' 6
60C 8
2C 14*
65C 9
2G 10 30C 11 42C 13 45C i
15 43C i
17 5C 18 40C i
19 150C 20 30C Richland 21 62C Hannibal 40*
34C Scriba 22 1G 16*
39C 24 1G 26 6G i
25*
O 27 1C
E 28 1C
g Volney 29 30C Totals 986 Cows 10 Goats T
C = Cows; G = Goats iE
- "i x S^=9
' c^tions 2
g
= Milk Sample Control Lovation J
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TAlli.G 21 CONCENTRATION OF GAMMA E11ITTERS IN FODDElt CitOPS AND PASTilitE GRASS Results in linits of pCilg (wet)
Sample Statton Code
Sample Type Date Ra-226 Be-7 Cs-134 Ru-106 Cs-137 Nb-95 Co-58 Hn-54 Co-60 K-40 Ce-144 Others 4
Grain 06/23/81
<l.76 1.7720.6
<0.11
<0.92
<0.12
<0.19
<0.14
<0.12
<0.13 6.4410.7
<0.50
<tLD Grass 06/26/81
<1.02 1.46 0.4
<0.10
<0.90
<0.12 0.44t0.1
<0.13
<0.12
<0.13 6.1710.7 0.50t0.1 <LLD itay 06/26/81 5.4111.8
<4. 76
<0.36
<4.10 0.3620.1 0.7210.2
<0.55
<0.44
<0.67 10.4 12.3
<1.98 4LD Grass 01/30/81
<4.26 4.4221.7
<0.24
<2.50 0.27 0.49:0.3
<0.38
<0.34 0.78 0.3 6.99 3.2
<!.57
<t L D Grass 08/25/81
<2.41 3.7911.3
<0.14
<l.42 0.15
<0.49
<0.22
<0.16
<0.18 5.27:1.5 0.59t0.3 <LLD tiay 09/24/81
<5.98
<4.40 4.33
<3.64
<0.37
<0.82
<0.49
<0.43
+0.61 11.2 23.8
<l.77
<tLD Grass 09/24/<31 2.1110.9 5.22:1.7
<0.12
<0.72 0.13
<0.47
<0.18
<0.11
<0.12 6.4211.4
<0.57 4LD Grass 10/27/81
<2.09 1.92t1.0
<0.10
<l.30
<0.11
<0.35
<0.18
<0.14
<0.14 3.23:1.1
<0.64 4LD llay $11 age 10/27/81 1.6810.9
<l.79
<0.13
<l.30 0.12 0.2410.2
<0.18
<0.12
<0.18 5.1011.5
<0.68
<t t D Corn Silage 10/27/81
<2.70 3.08tl.6
<0.16
<1.51
<0.14
<0,36
<0.21
<0.16
<0.18 2.99t!.3 3.0821.6 4LD 1
Itay Silage 10/27/81
<2.57
<2. 2
<0.17
<l.33 4.18
<0.48
<0.24
+0.18
<0.20 6.55tl.8 0.6510.3 4tD Corn Silage 10/27/81 3.2111.1 1.8511.0
<0.13 0.14
.13
<0.38
+0.17
<0.12
<0.17 4.49tl.4 1.85t1.0
<t t D Grass 10/27/81
<2.01
<2.2 0.17
<l.33
.18
<0.48
<0.24
<0.18
<0.20 3.7011.2 0.55
<t L D c)
W 12 Grain 06/23/81
<2.00
<l.05
<0.11
<l.08
<0.13
<0.15
<0.14
<0.14
<0.18 10.4 10.9
+0.51
<t L D Grass 06/23/81
<2.00
<l.49
<0.11
<l.25
<0.14 0.5620.1
<0.15
<0.13
<0.18 6.47t0.7 0.61to.1 4tD llay 06/23/81 7.2411.7
<5.99
<0.50
<4.86
<0.64 0.85t0.3 0.68
<0.57 1.6420.3 13.3 12.4
<2.07 4LD Grass 01/30/81
<3.02 1.58tl.0
<0.16
<l.73 9.19 0.5010.2
<0.23
<0.20
<0.25 3.0311.4
0.83
<l LD Grass 08/25/81
<1.78
<2. 01
<0.10
0.10
<0.13 4).38
<0.20
<0.12
<0.13 6.49tl.5
<0.53
<tLD llay 09/24/81 4.4512.5
<3.76
<0.24
<2.63
<0.30 0.67
<0.43
<0.31
<0.45 17.2 13.7
<l.40
<t L D Grass 09/24/61
<1.73 3.5611.4
<0.10
<0.93
<0.08
<0.26
<0.20 0.11
<0.12 8 1111.5
<0.48
<tL D Grass 10/28/81 2.16tl.4
<3.12
<0.15
<l.15
<0.15
<0.47
<0.20
0.15
<0.16 4.46tl.5
<0.72
<tLD Corn Silage 10/28/81 1.7510.9 1.75tl.1
<0.10
<0.97
<0.11 9.27
<0.13
<0.12
<0.14 3.9221.1 1.75tl.1
<1 L D 14 Grain 06/26/81 1.foto.5
<l.13
<0.11
<0.92
<0.11
<0.18
<0.16
<0.12
<0.16 7.3510.9
<0.48 4LD Grass 06/26/81
<0.90 0.76t0.2 0.06 4).57
<0.0d 0.20:0.1 0.09
<0.07
<0.09 6.9710 5 0.2110.% *LLD itay 06/26/81 8.45t2.4 3.6211.1
<0.45
<4.26
<0.54 0.60f0.2
<0.60 4.51
<0.61 12.3 12.6
<2.17
<t t D Grass 07/30/81
<3.61 4.4111.5
<0.19
<l.94
<0.24
<0.48
<0.24
<0.25
<0.31 6.16i2.3 1.24+0.6
<tLD Grass 08/25/81
<1.78 2.74tl.0 0.09
<l.03
-0.12
<0.34
<0.16
<0.11
<0.13 4.97tl.21
<0.50
<t L D llay 09/24/81
+6.27
<4,3
<0.32
<3.34
<0.34 0.68
<0.44
<0.35
<0.52 22.10t4.7
<l.68 4LD Grass 09/24/81
<l.51 5.78tl.4
<0.07
<0.78
<u.09 0.2420.2
<0.14
<0.10
<0.13 6.5511.3
<0.42
<t LD Grass 10/27/81 1.88t1.3 1.36t0.8
'O.08
<0.88
<0.09
<0.27
<0.14
<0.12
<0.12 4.9911.2
<0.47
<t L D Corn Silage 10/2:/01
<2.38
<2.04
<0.12
<l.13 1.12
<0.32
<0.16
<0.12
<0.18 3.29tl.3
<2.04
<LLD
' Corresponds to sample locations on Figure 6.Section VII W
M M
M M
M M
M M
M m
M
TAllt.E 21 (cont.)
CONCEt4TitATION OF GA1111A EILitTTEllS IN FODDElt CitOPS AND PASTURE GRASS Results in tinits of pCl/g (wet)
Sasple Station Code
Sample Type Date Ra-226 Be-1 (v134 Ru-106 CS-137 Nb-95 Co-58 Mn-54 Co-60 K-40 Ce-144 Others 16 Grain 06/23/81
<1.71
<0.85
<0.11
<0.94
<0.10
<0.13
<0.11 <0.10
<0.14 9.26t0.9
<0.43
<ttD Grass 06/23/81
< 3.12 2.1010.5 <0.20
<2.00
<0.19 0.6910.1
<0.23 <0.23
<0.26 9.31:1.2 0.9210.2 < LI D llay 06/23/81
<6.48
< 3. 37
<0.37
< 3.58
<0.41
<0.64
<0.34 <0.44
<0.67 7.76tl.8
<1.78
<ttD Grass 01/30/81
<4.77 3.52 1.6 <0.31
<2.87
<0.35 0.6210.3 <0.40 <0.31
<0.47 6.1112.5 1.4690.6 <tLD Grass 08/25/81
<2.31
<2.36
<0.14
<l.46
<0.13
<0.53
<0.21
<0.16
< 0.21 8.26tl.8
<0.63
<ttD itiy 09/24/81
< 6.95
< 4. 54
<0.41
<4.52
<0.45
<0.84
<0.60 <0.48 0.6910.3 25.7 15.1
<l.94
<ttD Grass 09/24/81
<1.81 2.44tl.1
<0.10
<0.92
<0.11
<0.37
<0.19 <0.12
<0.12 5.61tl.3
<0.52
<ttp Grass 10/28/81
<l.87 5.70t1.5 <0.11
<0.88
<0.14
<0.39
<0.16 <0.12
<0.17 4.55:1.3
<0.59
< l l L' g
Corn Silage 10/28/81
<2.17
<1.92
<0.12
<l.11
<0.13 1.94t0.1 <0.18 <0.14
<0.15 4.43 1.4
<0.59
<LLD 25 Grass 07/31/81 6.8313.6 3.6912.3 <0.33
< 3. 4 5
<0.36 0.49t0.3 <0.38 <0.34 0.2810.2 6.99t3.2
<!.51
<!LD Hay 07/31/81
<9.12
<4.05
<0.52
<4.97
<0.62
<0.55
<0.63 <0.59
<0.76 10.5 14.3
< 2.18
<LLD Grain 07/31/81
<l.97
<0.94
<0.11
<0.99
<0.12
<0.12
<0.11 <0.12
<0.17 7.60tl.6
<0.48
<LLD Grass 08/25/81
<2.01 2.6111.4 No.Il
<l.21
<0.14
<0.43
<0.19 <0.14
<0.17 4.56tl.3
<0.62
<LLD 40 (Control)
Grain 06/26/81 8610.4
<l.14
<0.11
<1.04
<0.12
<0.18
<0.15 <0.13
<0.17 7.96t0.8
<0.46
<tLD Grass 06/26/81
<l.61 2.11 0.5 <0.09
<0.95
<0.01 0.5210.1 <0.12 <0.11
<0.11 4.13 0.6 0.65t0.I <LLD flay 06/26/81
< 7. 78
<5.36
< 0. 48.
<4 24
<0.48 1.06:0.3 <0.60 <0.56
<0.65 20.0 12.7
< 2. 21
<tLD Grass 07/30/81
< 3.65 1.69tl.0 <0.22
< 2.04
<0.21 0.4610.3 <0.24 <0.20
<0.36 5.62:2.2
<0.93
<1tD Grass 08/25/81
< 2.00
< 2.42
<0.11
<0.12
<0.13
<0.47
<0.22 <0.13
<0.17 6.3111.5
<0.62
<tLD flay 09/24/81 4.41t2.4
< 3.61
<0.30
< 2. 70
<0.28
<0.55
<0.39 <0.25
<0.38 11.5 t3.7
<l.36
<tLD Grass 09/24/81
<l.58 1.85t6.9 <0.08
<0.79
<0.09
<0.28
<0.13 <0.10
<0.14 3.89 t l.0
<0.45
<LLD Grass 10/28/81
<l.61 3.85tl.1 <0.10
<0.89
<0.10
<P.28
<0.16 < 0.09
<0.11 4.4391.1
<0.47
<ttD Corn Silage 10/28/81
< 2.11
<l.58
<0.13
<l.22 0.1011.2
<0.30
<0.17 <0.11
<0.16 3.7111.2
<l.58
<tLD
'Correr. ponds to sample locations on Figure 6,Section VII
I 1
l l
Taut.E 22 CONCENTil ATION OF GAMM A EMITTEftS IN StfRFACE ltATER SAMI'IES Itelwriest in Usille of pol /l Saaple Station Code" Sample Type Date 84-226 Be-1 Cs-134 Bu-106 Cs-137 hb-95 Co-58 06e-54 Co-60 E-40 Others 25' Well 04/06/81 91.8tI7.4 <21,0
<2.34
<20.0
<2.40
< 2. 58 *2.50 < 2. 35
2.71
<30.33
<tto 25*
Well 04/06/81
126.6
<10.0
<5.30
<56.1
<6.04 <ll.56 <F.03 <6.17
<8.46
<16.51
<ttD 25' Pasture Streae 04/06/81
<!30.5
<67.5
<5.54
<55.0
< 6.18 <10.45 <8.38 < 5. 7 4
<7.77 476.50
<ttD 25*
Pasture Stream 04/06/81 79.0:12.6 <l8.2
<2.16
<21.0
<2.48
<2.12 <2.17 <2.52
4.34 535.83 attD 16*
Pond Water 08/23/81
<27.3
<!8.9
<l.46
<l3.3
<l.62
< 3.63 <2.35 <l.81
<2.28
<21.2
<ttu 25*
Pasture Strese 08/25/81
<24.9 all.4
<l.49
<t3.5
<l.62
<3.14 <l.93 <I.73
<l.98
<23.6
<tto 12*
darn / Spring 08/25/81
<26.1
<!8.7
<l.42
<3.4
<2.95
<2.04 <2.04 el.71
<2.01
<l1.8
<ltD 40* (Control) Barn /Well 08/19/81
< 27.7
<21.9
<l.50
<l5.7
I.85
<3.38 <2.21 <l.95
<2.34
<22.4
<tlD 16*
Bara/ Pond 10/27/81 17.62 9.2 9.9
<0.99
<8.4
0.96
<l.31 <!.09 <0.89
<l.12 10.8 e 6.3 ellD 4'
Barn /5pting 10/27/81 13.2 8.3
<7.5
<1.05
<10.1
<l.00
<l.12 <0.95 <l.16
<l.10
<l5.3
<tt0 14*
Sara / Spring 10/21/81 23.4r I.I <10.9
<l.08
<9.7
<0.94
<l.52 <l.05 <0.98
<l.00
< l 4.0
<ttD J
12*
Barn / Spring 10/27/81 13.5210.1 <10.6
< 0. %
< 9. 0 al.29 al.62 al.16 <l.20 al.62
<10.8
<ttD j
7*
Bara/5pring 10/27/81 13.6:10.6
<8.7
<0.91
<9.2
<0.91
<l.25 <0.87 <l.05
<l.80
<h5.7
<ttD 40*
Barn /Well 10/28/81 16.04 8.0
< 9.0 40.98
< 9. 0
<l.!!
<l.28 el.07 =0.82
<l.28
<l4.0 altD 10 5tream 10/30/81 16.7 4 9.3_ < l2.1
<l.00
<10.2
<l.31
<l.64 <t.22 <0.98
<l.18
<t2.5
< tt D 71 Stream 10/30/81 14.9t 8.4 <ll.4
<l.09
<ll.4
0.94
<l.51 al.12 <l.10
<l.28 el4.4 ello 72 Stream 10/30/81
<20.1
<t2.0
<l.14
< 9.5
<l.16
<l.35 <l.12 <l.08
<l.38
<l2.5
<llD 73 Stream 10/30/81 16.6t 9.0 <ll.1
<l.15
< 9. 9
<l.17
<l.89 <l.30 0.93 1.71n0.9 al2.5
<tto il Stream 10/30/81
<21.2
<l2.2
<0.%
<10.8
<l.Il
<l.61 <l.27 al.14
<l.35 el4.4
< TID 75 Stream 10/30/81 15.62 8.I <10.0 40.99 ell.0
<0.93
<l.60 <l.49 el.00
<l.47 14.4 e 9.6
It D 76 5tream 10/30/81
<21.2
<10.8
<0.93
<ll.3 al.18 al.50 el.27 <l.ll
<l.23
<l5.3
<ttD e
17 Itarsh 10/30/81
< 21.1
<lo.3 41.08
<10.5
<l.49
<l.42 el.27 *I.15 1.40 0.9
<t8.7 ettD u
78 Streae 10/30/81
<t9.8
<10.6
.0.99
<8.5
<!.05
<l.64 <l.12 <0.99
<l.18
<!4.9
<ttD 79 Stream 10/30/81
< 21. 4
<l2.2
<l.15
<l2.3
<!.22
<l.53 <l.20 <l.24
<l.38
<l4.0
<tto 80 Pond Water 11/25/81 14.8:34.6 <26.8
<3.05
<27,9
<3.17
<2.99 <3.10 <3.59 44.83 11.5 el5.8
ttD 81 Stream Water II/25/81
<F1.7
< 21. 7
<2.79
<32.1
<3.32
<3.61 < 2.83 <3.71
<3.73
<45.2
<ttD 82 5tream Water 11/25/81
<15.6
<29.4
< 3.33
< 30.1
<3.29
<3.53 <3.29 <3.63
<8.76
<41.1
<tto 83 Stream Water 11/25/81 13.8t31.2 <26.6
<2.84
<31.7
<3.52
<3.33 <3.17 < 3.22
5.27 444.6
<ttD 84 Stream Water 11/25/81 59.9:31.9 *28.9
<3.24
< 31. 4
< 3.96
<3.13 <3.17 <3.46
<6.55
18.5
lt D 85 IControll Pond Water 11/25/81 75.0t36.6 <28.5
<3.19
<31.5
< 3.86
<3.55 <3.52 < 3.15
F.27 442.3 attD 86 i Controlh Fond Water
11/25/81 66.0134.6 *30.5
<3.17
<30.7
<3.71
<3.46 <3.14 *3.52
<4.68
40.4
TID 87 ' Controll PunJ Water 11/25/81 78.5t63.2 <26.6
<3.?2
<31.6
<3.35
<3.56 <3.49 *3.06
<5.23 18.4 el5.2
<ttD 77 i l)
.itarsh Water 12/04/81
<l15.0
<36.9
4. 39 '
44.6
<5.84
< 4.85 5.00 <5.05
<5.99
<55.4
< TID 77 L2) 14arsh Water 12/04/81
<108.0
< 38.5
<4.15
<35.2 4.49
<4.49 < 3.87 5.31
< 4.46 465.5
<tLD
54.1 4.36
<53.4
<4.32
<6.46 44.60 <3.81
<6.36 31.7 #27.8
<tt 0 16*
Stream 12/'5/81
<108.0 16*
Bara/ Pond 12/15/81 78.8t44.7 <55.5
<4.46
<43.6
.4.41
<F.05 <4.78 <5.35
<5.12
<51.5
<tto 40*(Control) Barn /Well 12/15/81 161. t91.1 48.9
<4.53
<45.0 5.07
<7.15 <5.59 <4.48
<6.03 26.6 225.2
<tlD 40*(Control) Pond Water 12/15/81
<l10.0
<42.7
<4.02
<45.7
<4.13
<5.68 <4.28 <4.19
< 5.4 7 54.7 335.9
<tlD 4*
Barn / Spring 12/16/81
<109.0
<40.2
<4.12 47.7
<4.91
<6.08 <4.05 <4.58
<5.66
<68.6
<ttD 4*
Pasture Stream 12/I6/81
<!16.0
<49.1
<4.29
< 45.0
<5.14
<7.89 <5.62 <5.46
<6.20
<55.4
<ttD 12*
Barn /5pring 12/16/81 77.8t44.7 <54.6
-4.46
<43.5 e4.46
<6.67 4.71 <5.34
<5.12 451.5
<tt o 12*
Pond Water 82/I6/81
<!22.0
<36.8
<4.26 446.6
<3.94
<4.09 <4.58 <4.16
<6.46
<57.2
<tto 14*
Barn / Spring 12/16/81
<ll7.0
.44.7
<4.02
<47.8
<4.99
<1.15 <6.42 <4.35 e6.02
<47.4
<ttD I4*
Pond Water 12/16/81
<102.0
<50.1
<4.11
<3d.2
<4.99
<7.18 <4.92 <4.62
<5.51
<55.4
<tlJ 4*
Pond Water 12/17/81
<107.0
< 35.2
< 4.48
.2ft.1
<3.94
<3.38 < 3.42 < 4.4 4
.4.67
<58.9
<tlO J'
Bain/ Spring 12/17/81
<l18.0
< 53. 4
<5.12 449.1
<5.22
.6.80 <6.50 <5.77
<4.92
<60.7
<ttD 7*
Pond Water 12/17/81 82.7 45.5 <33.7
<3.82
<32.5
<4.66
<4.12 <3.43 <4.35
<5.98 33.7 224.8
<llD 25*
Pasture Stream 12/18/81
<!!9.0
<53.1
< 4.40
<46.1
<5.01
<6.60 <6.06 <4.47
<6.35
<57.2
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!I DATA SUMMARIES AND CONCLUSIONS 1
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V DATA SUMMARIES AND CONCLUSIONS The results of the 1981 Radiological Environmental Monitoring Program are evaluated considering the natural processes of the enviranment and the aggregate of past data. A number of factors are considered in the course of this radiological data evaluation and interpretation. The interpretation of data can be made at several levels including trend analysis, population dose, risk estimates to the general population based on environmental concentrations, effectiveness of plant effluent controls and specific research areas, among others. An attempt has been made in this report not only to report the data collected during the 1981 sample program but also to assess the significance of the radjonuclides detected in the environment. It is l
important to note that detection of an isotope is not of itself an indication of its environmental significance.
Evaluation of its impact in terms of potential I
increased dose to man is necessary.
Three specific groups of radionuclides exist in the environment. The first of these groups is naturally occurring.
It must be recognized that our environment contains a broad inventory of natural background radiation of l
primordial and daily origin.
The background radiation is in a constant state
's of flux, influenced by a myriad of daily phenomena including solar activity, g
snow cover, barometric pressure and meteorological conditions. The natural background radiation in the general area of the site is assessed on a quarterly basis and is found to be the most significant contributor to man's radiation exposure.
l The radiation resulting from the detonation of thermonuclear devices in the earth's atmosphere has produced a second group of radionuclides generally found in the environment. The inventory of fallout radionuclides found worldwide is the result of atmospheric testing conducted in the years 1945 through 1963.
In 1963 a ban was placed on the testing of I
thermonuclear devices in the atmosphere greatly reducing the inventory of short half-life radionuclides in the environment. Since 1963 several
(
atmospheric nuclear tests have been conducted by the People's Republic of China. The most recent of these tests took place in October of 1980. The I
resulting fallout from this last test has influenced the background radiation in the vicinity of site and is evident in many of the sample media analyzed during 1981.
Calculations of the resulting dose to man from fallout nucli.ies in the environment show that the contribution from such nuclides in some cases (Sr-90 and Cs-137) is significant and second in intensity only to I
natural background radiation.
The third group of radionuclides detected in the local environment is those resulting from the operation of the plant. The detection of plant related radionuclides is one of the main objectives of the environmental surveillance program. The dose to man as a result of plant operation is small and much less than the radiation exposure from naturally occurring sources of radiation and in most cases from fallout exposure.
In Section V each sample medium is discussed.
Concentrations of radionuclides detected and exposure to man are presented and scrutinized.
I 1
65
I Section VI, titled IIISTORICAL DATA, contains sample. statistics from previous environmental sampling. The process of determining the impact (or lack of impact) of plant operation on the environment includes the scrutiny of past analytical data, a tool by which trends are discerned. The interpretation of historical data in this report is done to a limited degree.
3 Because of the constant change in analytical sensitivities, as state-of-the-art I
detection capabilities improve, data comparisons become difficult.
For example, minimum detection capabilities for the 1969 and 1974 analyses of environmental samples would be considered anomalous by 1980 and 1981 standards.
s LAKE PROGRAM Tables 1 through 8 list the 1981 analytical results for the aquatic / lake water media sampled during the 1981 sampling program. Aquatic samples were obtained at a combination of four on site locations.
The transect designations used for the on site sampling are NMPW (01), NMPP (02), JAF E
(03) and NMPE (04). Due to limited availability of certain required sample 5
media, samples could not be obtained consistently at each of the same on site transects sampled for other media. Off site samples were collected in the vicinity of the Oswego liarbor off site (00).
1.
PERIPIIYTON SAMPLES - TABLE 1 The collection and analysis of periphyton samples was performed twice during the 1981 sample program.
Periphyton is a common fresh water algae found throughout the Great Lakes and in almost all underwater aquatic systems. Periphyton in its simplest form is a single celled organism which colonizes the natural and artificial substrates found in the shore and near shore waters.
Colonies of periphyton can be found from the shore zone to water depths which can be sufficiently penetrated by sunlight to support photosynthesis. Periphyton is dependent on sunlight and inorganic materiala found in lake to support life putting it in the classification of a primary producer. Periphyton in its simplest form is the slimy coating which is found on most underwater surfaces and has a brown to green coloration. This organism is used as an indicator organism to help evaluate the possible effects of plant operation on the local aquatic environment.
l l
The first collection of periphyton was completed on July 8,1981 and the i
second collection was completed on August 25, 1981. The gamma l
spectral analysis of periphyton samples showed detectable levels of Ce-144, Zr-95, Nb-95, Cs-134, Cs-137, Mn-54, Co-60, Ru-103, Ru-106, Be-7, Ra-226, Th-232 and K-40.
The extensive number of radionuclides detected in periphyton samples can be attributed to g
several sources. The table below lists the principle origin or source of 5
each radionuclide detected in the 1981 periphyton samples.
66
I Radionuclide Origin Isotope IIalf-life Cc-144 Fallout 284.4 Days Zr-95 Fallout 64.0 Days
'g Nb-95 Fallout 3.5 Days 3
Cs-134 Plant 2.06 Years Cs-137 Fallout / Plant 30.2 Years Mn-54 Fallout / Plant 315.5 Days Co-60 Fallout / Plant 5.3 Years Ru-103 Fallout 39.4 Days Ru-106 Fallout 368.0 Days
E B e-7 Naturally Occurring 53.3 Days l5 Ra-226 Naturally Occurring 1,600.0 Years Th-232 Naturally Occurring 1.40x1010 Years K-40 Naturally Occurring 1.28x109 Years I
As noted above the radionuclides detected can be placed in three I
groups. The first group of radionuclides is the result of plant operation. The second group of radionuclides is listed as naturally occurring and is found in many living organisms as noted throughout this report.
The third group of radionuclides is the results of recent and past testing of atmospheric nuclear weapons. The radionuclides with relatively short half-lives are the result of a weapons test conducted in October of 1980. Those nuclides with relatively long half-lives such as Cs-137 are the result of the many atmospheric tests conducted over the past decades.
Cs-137 requires special consideration as this radioisotope of cesium is a common constituent of the background due to fallout but can also be related to the operation of I
the plant.
The first set of periphyton samples collected on June 8,1981 yielded I
detectable concentrations of each of the radionuclides listed in the table above. The maximum detectable concentrations for plant related radionuclides were 0.16 pCi/g (wet) for Mn-54, 0.22 pCi/g (wet) for Co-60, 0.54 pCilg (wet) for Cs-134 and 4.0 pCi/g (wet) for Cs-137.
I The radionuclide detected in the most significant quantity was Cs-137.
Cs-137 was also detected in the control sample with a concentration of 0.14 pCi/g (wet) which is likely the result of fallout from past weapons testin g.
The presence of five distinct fallout nuclides in the June samples shows that the fission products that resulted from the October, 1980 atmospheric nuclear test conducted by the People's Republic of I
China were still affecting environmental samples. Ce-144, Zr-95, Nb-95, Cs-137, Ru-103, and Ru-106 were detected in both the on site and control (off site) samples collected in June. These concentrations ranged from a maximum of 3.9 pCi/g (wet) for Nb-95 to a minimum of 0.15 pCi/g (wet) for Ru-103. The detection of fallout nuclides was prevalent in many of the sample media analyzed in 1981, with relatively high levels found in the air particulate filter samples.
I 67
i The second collection of periphyton samples collected in 1981 showed a general increase in the concentration of plant related radionuclides while the shorter half-life fallout nuclides showed small reductions in concentration.
The exception was Cc-144 which increased in concentration at both the indicator and control locations. The naturally 3
occurring concentrations remained constant with the exception of De-7, E
which in one case increased by a factor of 9.
As in the June collection, Cs-137 was the most abundant radionuclide in the indicator stations with a maximum value of 16.0 pCi/g (wet).
Cs-137 was also detected in the control station with a concentration of 0.24 pCilg (wet). The general increase in concentrations of plant related radionuclides in the second or late summer collection was also E
noted in 1980 (This difference may be related to the higher metabolic 3
rate or increased growth of the periphyton community between the first and second collections.) The general increase in concentrations between the first and second collection was not experienced in the 1979 sample collections. Each of the plant related radionuclides detected in the 1981 samples were trace concentrations with the source being past and present plant effluents.
A dose to man calculation from the level of activity found in lake periphyton samples in the vicinity of the plant is difficult to make as a
periphyton is not directly in the human food chain. To best determine g
the resulting dose to man from the activity found in periphyton samples, calculations were made based on concentrations found in fish samples as fish represent the upper level of the food chain in which periphyton is a primary producer.
Dose to man calculations based on concentrations found in fish and consumption rates are contained in Section V.
A review of past data shows Cs-137 levels in periphyton to have increased in 1981 at both the indicator and control stations but remained below the maximum concentration de ected in 1975 (indicator) and 1976 (control). Co-60 concentrations in. criphyton showed an increase for 1981 over the past four years which remained relatively consistent.
Cc-144 also showed a marked increase from 1979 and 1980 at both the on site and off site sample locations. The 1981 concentrations showed a similar increase as was detected in 1977. Both the 1977 and 1981 peaks can be attributed from fallout due to i
atmospheric testing.
Past concentrations of Cs-137, Co-60 and Cc-144 l
are presented in graphie form in Section VII.
2.
BOTTOM SEDIMENT - TABLE 2 Dottom sediment samples were collected twice during the 1981 sampling l
p rogram. Gamma spec + al and Sr-90 analysis was performed on each of the samples and the results are presented on Table 2.
Samples were collected in June and October in 1981 with the Oswego liarbor area off l
sito (00) serving as the control location and transect (02), Nine Mile roint Plant, and (03), FitzPatrick, serving as indicator or on site E
sample locations. The most abundant radionuclide detected was Cs-137 g
l 68
which was found in each of the six samples collected in 1981. Sr-90 was also detected in each of the six samples collected in 1981 but the concentrations were less than those detected for Cs-137.
Co-60 was detected in four of the six 1981 sediment samples collected.
The presence of Cs-137 in the sediment samples can be attributed to the accumulation of fallout in the aquatic environment as a result of the detonation of nuclear devices in the atmosphere. This fact is easily illustrated by the presence of Cs-137 in the control station samples.
The level of Cs-137 detected in the off site or control sample exceeds the concentrations of any of the four on site or indicator stations collected during the year. The maximum control station value was 0.42 pCi/g (dry) which was nearly two times the concentration detected at either of the indicator stations during the same sample period. The control sample values for Cs-137 showed similar trends in 1979 and 1980 when the control concentrations exceeded those that were detected at the indicator locations.
Each of the four indicator stations showed detectable levels of C0-60 which ranged in concentration from a maximum of 0.27 pCi/g (dry) to a minimum of 0.11 pCi/g (dry). The detection of Co-60 in sediment samples is due to the deposition of plant effluents. Co-60 was not detected in the control samples collected in 1981.
Strontium-90 was also detected in the aquatic sediment samples collected for the 1981 program. Each of two control samples collected contained Sr-90 as in 1979 and 1980.
Like Cs-137 the source of the detected Sr-90 is confirmed to be atmospheric nuclear test again illustrated by the consistent presence of Sr-90 in the control samples. The minimum I
concentration of Sr-90 at the control station was four times the minimum indicator value for 1981. The mean 1981 concentrations for 1981 are equal to 0.0118 pCi/g (dry) for the indicator samples and 0.027 pCilg (dry) for the control samples.
The variation in Sr-90 and Cs-137 concentrations may be attributed to l
the difference in the physical and chemical makeup of the sediment types and/or the fact that the control station is near the inlet of a large river with an extensive drainage basin which could result in an accumulation of sediments containing Sr-90 and Cs-137 leached from the runoff areas and deposited as the river enters the slower moving lake.
The dose to man from bottom sediment is not of concern and cannot be directly calculated. Bottom sediment is not accessible to man and the radioactivity found in the sediment is shielded by the overlaying water column. To illustrate the impact of radioactivity in sediment samples with respect to the dose to man concept, the assumption can be made that at some future time bottom sediment could be introduced into the shoreline sediment through re-suspension and deposition. Assuming that the density of the sediment is 40 kg/m2 (dry) and using the average residence time on the shore of 47 hours5.439815e-4 days 0.0131 hours 7.771164e-5 weeks 1.78835e-5 months per year for a teenager, the annual dose rate from a Cs-137 concentration of 69
0.42 pCi/g (dry) is calculated to be 0.0033 mrem per year whole boay dose and the whole body dose from the Co-60 concentration of 0.14 pCi/g (dry) would be equal to 0.0045 mrem per year. The resulting total whole body dose would be equal to less than 0.080 mrem per year whole body. The contribution to the total whole body dose due to Sr-90 would be infinitesimal due to the fact that Sr-90 decays by a beta emission and has no associated strong gamma energy.
A graph of past Cs-137 data illustrates that the mean concentrations are randomly distributed from 1974 to 1979 with the highest concentration detected in 1976 (2.45 pCilg [ dry]). The levels of Cs-137 have dropped significantly from 1976 to 1979 and the general downward trend has continued from 1979 through 1981, though at a slower rate of decline. The concentrations of Co-60 show a similar downtrend to that of Cs-137 The maximum Co-60 concentration was detected in 1977.
The concentration of Co-60 in the indicator samples (mean) shows a consistent downward trend since 1977 that continues through 1981. The past concentrations of Co-60 and Cs-137 are presented in graphic form in Section VII.
3.
MOLLUSK SAMPLES - TABLE 3 A total of six mollusk samples were collected in 1981, from a total of l
three general locations.
Each sample was analyzed for gamma emitters using gamma spectral analysis and for Sr-90 using chemical separations and beta particle analysis. The results of the 1981 samples are l
presented on Table 3.
As in past years the effort to collect mollusk u
samples of sufficient size has been of limited success in terms of sample l
volume collected. The collections in 1981 were more productive than in E
past years and resulted in sample volumes in the 500 gram range which l
in some cases resulted in better sensitivities for the gamma spectral analysis, in particular for the indicator samples. Mollusk samples were successfully collected at the off site (00) or control location and at the Nine Mile Point Plant (02) transect and the FitzPatrick (03) transect, for the indicator samples.
l The results of the isotopic analysis of mollusk tissue detected the presence of six radionuclides. The nuclides detected consisted of one l
naturally occurring radionuclide (K-40), two plant related radionuclides (Mn-54 and Co-60), and four radionuclides related to fallout from atmospheric nuclear testing (Nb-95, Cs-137, Sr-89, and Sr-90). S r-89 and Cs-137 require special considerations as they can be released as a result of plant operation in addition to being by-products of E
atmospheric nuclear testing. Detectable concentrations of Sr-90 were 3
measured in each of six samples collected at both the on site and off site locations. The presence of Sr-90 in all the mcIlusk samples collected for the sample year was also true in 1979 and 1980. The 1981 Sr-90 concentrations ranged from a maximum of 0.13 pCi/g (wet) to a minimum of 0.005 pCi/g (wet) with the control station mean equal to 0.046 pCi/g (wet) and the indicator mean equal to 0.094 pCi/g (wet).
i Sr-89 was detected in one of the indicator sample locations with a I
70
concentration of 0.01 pCi/g (wet). The origin of Sr-89 in this particular mollusk sample cannot be clearly determined. The lower limit of detection for Sr-80 at the other sample locations was equal to or greater than measured concentration (LLD range 0.06 to 0.01) for the FitzPatrick (03) sample.
It is possible that Sr-89 is present in the control sample below the lower limit detection. The detection of Sr-89 in environmental samples has not been widespread in the 1981 sample program.
Cs-137 was also detected in one on site sample and is most probably the result of weapons fallout with a contribution from plant operation.
Nb,95 was I
also detected in one on site sample and its presence is attributed to weapons fallout.
Mn-54 and Co-60 were detected in a combination of three on site samples collected in 1981. The presence of Mn-54 and Co-60 in mollusk tissue can be attributed to the operation of the plant. Manganese-54 was detected in three of the four on site samples collected wPh concentrations ranging from a maximum of 0.13 pCi/g (wet) to s minimum of 0.04 pCi/g (wet). Co-60 was detected in two of tht four on site samples with concentrations of 0.14 and 0.05 pC1/g (wet). The relatively higher frequency for the detection of Co-60 and particularly Mn-54 in mollusk samples can be attributed to the phenomenon of bioaccumulation or concentration factors. The level of an element in a particular organism relative to the level or concentration of the same element in the organism's environment is known as the concentration factor.
Fresh water mollusk have an extremely high concentration factor of 300,000 (mean) for Mn-54 and 32,408 (mean) f r Co-60*.
Such high concentration factors would result in a rapi acumulation of manganese and cobalt activity in mollusk that are indigt. nous to the off shore area of the site.
Fresh water mollusk found in the vicinity of the site are not consumed by humans and are not a major component or level in the food chain if for no other reason other than the small population due to the I
unfavorable physical makeup of the lake bottom in the area. Because these fresh water mollusk are not considered edible there is no dose to man from the presence of the Mn-54 or Co-60 concentrations. A dose estimate can be made using substituted parameters for the purpose of putting into perspective the possible significance of Mn-54 and Co-60 concentrations detected in the mollusk samples.
Using the average individual consumption of scafood of 1.0 kg/ year for an adult, the dose resulting from ingestion would be 0.0001 mrem / year to the whole body and 0.0018 mrem / year to the gastrointestinal tract for the maximum Mn-54 concentration of 0.13 pC1/g (wet). The dose resulting from the Co-60 concentration of 0.14 pC1/g (wet) would be 0.0007 mrem / year to the whole body and 0.0056 mrem / year to the gastrointestinal tract. The maximum dose that would be received from the consumption of 1.0 kg of fresh water mollusk would be 0.0008 mrem to the whole body and 0.0074 mrem to t"' gastrointestinal tract. This calculated dose is extremely small
.,s noted above in reality would be equal to no dose, because of he zero consumption rate.
Eisenbud (1973) 71
I The concentration of Mn-54 and Co-60 have shown a significant drop since 1976. The concentrations detected in 1981 of these two radionuclides showed a small increase from 1980 but remained below the levels detected in 1978 and 1979. Sr-90 levels have remained relatively constant since 1974 but showed a small decrease in 1981.
Graphs of previous mollusk samples results for Mn-54 and Co-60 and Sr-90 are presented in Section Vll. Also found in Section VII is a physical description of the lake bottom in the vicinity of the site.
4.
GAMMARUS - TABLE 4 GAMMARUS samples were collected twice during the 1981 sample period in conjunction with mollusk, periphyton and botto:n sediment.
GAMMARUS are benthic or demersal dwelling organisms found in the general vicinity of the site and throughout Lake Ontario. GAMMARUS are sampled a. an indicator organism whose major predator is the local fish population. GAMMARUS are generally found in periphyton and cladophora growth areas and are limited in their territorial ranges, Samples were successfully collected at the control location (00) and at the Nine Mile Point Plant (02) and FitzPatrick (03) transects. Three collections are normally made to collect sufficient samples for acceptable analyses. The difficulties in obtaining sufficient samples is experienced each year. It should be noted that GAMMARUS are normally less than 10 mm in size and require a large number to obtain a biomass of one gram of sample.
The analytical sensitivities were good in the 1981 samples with the exception of the August Nine Mile Plant (02) indicator sample. This sample resulted in sensitivities ranging from <1.7 pCi/g (wet) Mn-54 to
<3.8 pCilg (wet) for Fe-59.
The analyses of GAMMARUS samples detected concentrations of Sr-90 in all samples and concentrations of Sr-89, Co-60, Cs-134 c.nd Cs-137 in a combination of three samples. Sr-90 was detected in each of the b
samples collected in 1981. Similar detections were made in bottom sediment and mollusk. Sr-90 is considered a background radionuclide because its origin is not related to operation of the plant. Sr-89 was also detected in two samples from the 1981 collection. The detection of Sr-89 at both one indicator and one control location is strong evidence that the origin of this isotope of strontium is related to weapons testing.
The first collection of GAMMARUS completed in early July contained E
concentrations of three plant related isotopes (Co-60, Cs-134, and g
Cs-137 ). The concentrations ranged from a maximum of 8.0 pCi/g (wet) for Cs-137 to 0.2 pCi/g (wet) for Cs-134. These nuclides were detected at the two indicator locations but not at the control location.
The second collection of GAMMARUS samples completed in late August contained no measurable concentration of Co-60, Cs-137, Cs-134 or any other plant related radionuclides. The absence of these nuclides in the second sample series and the lack of detectable concentration in 1980 72 J
samples indicate that the presence of these nuclides in GAMMARUS organisms is not routine nor chronic. The dose to man as a direct result of ccncentrations of cobalt and cesium would be zero as GAMMARUS is not consumed by man. The importance of the activity in these organisms is only significant with respect to the passage of the radionuclides through the food chain to a tropic level which may impact
man, llistorical data for GAMMARUS sampling and analysis shows a general reduction in Sr-90 concentrations detected in 1977 and 1980. The 1981 level of Cs-137 showed an increase from levels detected in 1978 and 1979. No definite trends can be determined for specific plant related radionuclides such as Co-60 and Cs*134 as detection has been random in past collections and the data base is limited due to routine difficulty in collecting sufficient samples for high sensitivity analysis.
5.
FISli - TABLE 5 A total of 22 fish samples were collected from Lake Ontario in 1981.
Samples were collected in the spring season (May,1981) and the fall season (November,1981).
Collections were made utilizing gill nets at one off site location greater than five miles from the site (Oswego Ilarbor area) and at two on site locations (in the vicinity of the Nir.e Mile Point Unit #1 (02) and the James A. FitzPatrick (03) generating facilities). The Oswego Harbor samples served as control samples while the NMP (02) and JAF (03) samples served as indicator samples.
Samples were analyzed for gamma emitters, Sr-89 and Sr-90.
Data is presented in the analytical results section of the report (Table 5).
Analysis of the 1981 samples indicated detectable concentrations of nuclides related to plant operations. Small detectable concentrations of Cs-137, Co-58, Co-60 and Mn-54 were found in two separate fish species. Sr-89 and Sr-90 were detected in two separate fish species as well.
Spring fish collections were comprised of two separate species and nine individual samples. The two species represented two different feeding types. White sucker is considered a bottom feeder ingesting both plant and animal matter. Lake trout are highly predacious and feed on significant quantities of smaller fish such as smelt, alewife, and other smaller predacious species.
Cs-13's was detected in all on site and off site samples for both species.
On site samples showed Cs-137 concentrations to be slightly greater than control levels for some samples and slightly less than control levels for other samples. The concentrations detected are not statistically different from the control result and are therefore considered background.
l 73.
Co-58 was detected in two on site samples only for white sucker and one lake trout sample. White sucker samples showed detectable concentrations of Co-58 at the NMP and FitzPatrick sample locations.
On site results for this species ranged from 0.045 to 0.047 pCi/g (wet).
The lake trout sample showing a detectable Co-58 concentration was collected at the NMP location. Collections at the FitzPatrick location showed no detectable Co-58.
The detected concentration was 0.035 pCilg (wet). Samples were recounted that showed detectable concentrations of Co-58.
Recount sample results were in close agreement with initial sample results.
Co-60 was detected in three of the on site samples and not in the control samples. White sucker samples showed Co-60 detected in two of the three samples, ranging from 0.11 to 0.12 pCilg (wet). Detections occurred at the NMP and FitzPatrick sites.
Lake trout samples showed Co-60 detection in only one of the six samples. Co-60 was detected at the NMP site at a concentration of 0.064 pC1/g (wet). Samples that showed detectable Co-60 concentration were recounted.
Recount sample results were in close agreement with the initial sample results.
Mn-54 was detected in only two of the nine samples collected.
Detections were noted for white sucker only at the NMP and FitzPatrick locations. The results ranged from 0.014 pCi/g (wet) to 0.018 pCi/g (wet). Samples showing positive Mn-54 detections were recounted.
Recount sample results were in close agreement with the initial sample results. The detected concentrations of Mn-54 were only slightly above the lower limits of detection.
Sr-89 was detected in five of the nine samples collected. Two of these detections were noted in the three control samples. The remaining three samples that showed positive detections were collected at the NMP and FitzPatrick locations and noted in white sucker and lake trout samples.
Of the positive detections, only one sample showed a concentration greater thatt the control results. This detected concentration (0.025 pCi/g [ wet]) was only slightly above the control result. All positive detections are considered to be representative of normal background Sr-89 concentrations in fish. Background detections are a result of past weapons testing in this case.
Sr-90 was not detected in any of the nine samples collected at either the on site or off site locations.
K-40 was detected in all of the spring samples collected. E-40 is a naturally occurring radionuclide and is not related to power plant operation. Detections of K-40 ranged from 2.9 to 3.4 pCi/g (wet).
In addition to the May sample collections, samples were collected on July 16 to further investigate the results of the spring collection.
White sucker samples were taken at the NMP and FitzPatrick sites as well as at a location less than one mile to the west of NMP and less than one mile to the east of the FitzPatrick location. The species white sucker was collected since these fish are relatively sedentary and are bottom feeders.
74
llesults showed positive detections of Cs-137 and Cs-134.
Co-58, I
Co-60, and Mn-54 were not detected in the July samples as in the May sample collections. Samples collected at the NMP cnd FitzPatrick locations showed detections of Cs-137 ranging from 0.056 and 0.087 pCi/kg (wet). A control sample was not selected for these samples but by comparing these levels to the control sample for white sucker from the May samples it can be seen that the detectable Cs-137 concentrations are just slightly above background. The other samples (i.e., the samples located less than one mile to the east and west of the power facilities) showed positive detections of Cs-137 and Cs-134. For these samples Cs-137 was slightly above background while the Cs-134 I
concentrations were just barely detectable.
Cs-134 is related to power plant operation and is not associated with wee. ns testing fallout. A significant portion of the detectable Cs-137, however, is due to weapons testing fallout.
In addition to Cs-134 and Cs-137, K-40 was detected in all of tha July samples. Detectable concentrations ranged from 2.9 pCi/g (wet) to 3.3 pCi/g (wet).
Fall sample collections were comprised of two separate species and nine individual samples. Six samples of white sucker and three samples of I
lake trout were taken at two on site locations (NMP and FitzPatrick) and one off site location (Oswego Harbor area). Samples were collected by gill nets in October.
Cs-137 was detected in all nine samples including the three control samples. On site samples for both white sucker and lake trout showed concentrations just slightly above background levels. Concentrations ranged from 0.044 pC1/g (wet) to 0.10 pCi/g (wet) for on site samples.
Of the six on site samples, five were above the control values while one sample was less than the control result. A significant portion of the Cs-137 detected in the on site samples is considered to be the result of past weapons testing fallout.
K-40 was detected in all samples and ranged from 2.4 pCi/g (wet) to 4.0 pCi/g (wet) from both on site and off site samples.
l No other gamma emitting radionuclides were detected in any of the fall samples.
l Sr-89 concentrations for the fall samples were all less than minimum j
detectable level.
Sr-89 was not detected in any of the on site or off
,E site samples. Sr-90 was detected in only two of the nine samples I
collected.
Detections were noted at the NMP site (1) and the FitzPatrick site (1). Both of the positive. detections were below the control sample limit of detection and are not significant. Detections were 0.00363 pCi/g (wet) (NMP) and 0.00223 pCi/g (wet) (FitzPatrick) respectively.
l l
l l
75
l I
Review of past data indicates that 1981 mean detectable concentrations of Sr-89 are slightly higher than the mean detections from 1978 - 1980 but below the mean values for years prior to 1978. Sr-89 for the second half of 1981 was not detectable and is therefore the same as LLD results for 1979 - 1980. Sr-90 mean data results indicate that concentrations in 1981 are lower than the mean concentrations from 1969 - 1980. A general decline in detectable Sr-89 and Sr-90 results is most probably due to the result of the incorporation of these radionuclides with organic and inorganic substances through ecological cycling.
Cs-137 concentrations have remained fairly consistent with the mean results for 1980 and have decreased significantly when compared to years prior to 1980.
As noted above for Sr-89 and Sr-90 the general decreasing trend is most probably due to ecological cycling. A significant portion of Cs-137 detected in fish is due to weapons testing fallout and the general downward trend will continue until an equilibrium is reached.
I Lake Ontario fish are considered an important food source by many people therefore placing these fish in the human food chain.
Based on the importance of fish in the local diet, a reasonable estimate of dose to man can be calculated. Assuming that the average adult consumes 6.9 kg of fish per year and the fish consumed contains an average Cs-137 concentration of 0.053 pCi/g (wet) for lake trout caught during the spring and fall collection period, the dose to the whole body would be 0 026 mrem per year. This dose is based on the average concentration of off site and on site samples. The yearly dose based on the consumption of on site samples (0.051 pCi/g [ wet]) is 0.025 mrem per year. The yearly dose based on the consumption of on site samples is less than the dose due to consumption of fish collected from on site and off site locations. The Cs-137 dose associated with the consumption of white sucker based on 6.9 kg consumed per year and 0.05 pCi/g (wet) is 0.025 mrem. This dose is based on consumption of on site samples and off site samples for the spring and fall collection periods and the effect to the whole body. The dose due to the E
consumption of on site samples only is 0.03 mrem per year based on an 5
average Cs-137 concentration of 0.61 pCi/g (wet).
Assuming the same conditions of ingestion, the average dose to the whole body from Co-58, Co-60, and Mn-54 for a two-month detection period is:
Co-58 (0.036 pCi/g (wet]) = 0.00001 mrem / year Co-60 (0.073 pCi/g [ wet]) = 0.00007 mrem / year Mn not detected l
The above doses are based on consumption of lake trout.
Using the concentrations detected in white sucker and the same above ingestion criteria, the average dose to the whole body from Co-58, Co-60, and Mn-54 by consuming white sucker is:
76
I I
Co-58 (0.046 pC1/g [ wet]) = 0.00001 mrem / year Co-60 (0.115 pC1/g [ wet]) = 0.0001 mrom/ year Mn-54 (0.016 pCi/g [ wet]) = 0.000003 mrem / year Fish samples collected in July to supplement samples collected in May showed concentrations of Cs-137 and Cs-134.
Using the above dose calculation criteria and an exposure period of three months for Cs-134 and 12 months far Cs-137 (unadjusted for background), doses are:
Cs-137 (0.078 pCi/g [ wet]) = 0.038 miem/ year Cs-134 (0.006 pCi/g [ wet]) = 0.0003 mrem / year In summary, the whole body dose observed due to the consumption of fish is minute and of little significance. The total dose for Cs-137 (excluding background), Cs-134, Co-58, Co-60, and Mn-54, was calculated to be 0.02 mrem if white sucher was consumed. This species of fish is very rarely consumed and the total dose is more illustrative than factual. The total whole body dose due to the consumption of lake trout is 0.0004 mrem per year. Note that doses were calculated based on durations of detections (i.e., the number of raonths a radionuclide was detected).
White Sucker: Radionuclide Duration of Detection Dose (mrem /yr)
C s-137 12 Months 0.01921 Cs-134 3 Months 0.00198 Co-58 2 Months 0.00009 Co-60 2 Months 0.0006 Mn-54 2 Months 0.00002 Sr-89 6 Months 0.00012 S r-90 6 Months 0.01431 Lake Trout:
Radionuclide Duration of Detection Dose (mrem /yr)
Cs-137 12 Months 0 (< bkg)
I C s-134 0 (not detected)
Co-58 2 Months 0.00008 Co-60 2 Months 0.00033 Mn-54 0 (not detected)
S r-89 6 Months 0.00002 (= bkg)
Sr-90 6 Months 0.02567 To filustrate the insignificance of the highest whole body dose received from the radionuclides detected, exclusive of K-40, a dose of 0.05 mrem (consumption of white sucker) is equal to a dose due to cosmic radiation from travelling to a location 100 meters (328.1 feet) higher in altitude I
and remaining there for 9.1 days.
As noted above the concentration of Cs-137 and Sc-90 are consistent I
with levels measured in 1978,1979 and 1980. The analysis results for fish samples collected in 1981 show no long term buildup of plant related isotopes such as Co-60, Co-58, Cs-134 and Mn-54.
Cs-137 and Sr-90 have been graphed and are presented in Section Vll.
.I
I 6.
LAKE WATElt - TABLES 6, 7, AND 8 Lake water samples are analyzed for gross beta activity, tritium, strontium-89, strontium-90, and gamma emitters.
The analytical results for the 1981 lake water sample program showed no evidence of plant related isotope buildup in the lake water in the vicinity of the site.
The gross beta activity for the Nine Mile Point Unit #1 and FitzPatrick inlet canals was slightly less than the mean 1980 canal results and significantly less than the mean result for years prior to 1980. The mean gross beta activity during 1981 for the control samples was slightly higher than the mean 1980 result but less than the 5
mean for years prior to 1980 Only eight of the 24 canal samples were E
slightly greater than control values during 1981 (i.e., most monthly canal results were less than control values). This fluctuation is due to the natural variation of naturally occurring isotopes. The reduction in gross beta activity since 1974 is primarily the result of improved analytical procedures and equipment and not changes in plant operation.
There were no significant changes or trends in gross beta activity on a E
monthly basis for 1981.
3 Tritium is a naturally occurring radioactive isotope of hydrogen which is produced in the upper atmosphere by cosmic radiation as well as a product of reactor operation. The analysis of lake water and canal water samples for the 1981 sample period showed no abnormalities with respect to the levels of tritium measured in lake water.
The level of 3
tritium has remained constant since 1974 with only slight variations. It 5
should be noted that the reported tritium concentration for the second quarter, raw city water sample (OSWP), is the average value of the tritium analysis performed on each of the three monthly composite samples collected during the second quarter. The averaged results were 300 pCi/1 ( April), 326 pC1/1 (May) and 357 pCi/1 (June). The analysis of monthly composite samples for tritium was instituted as a E
result of the cross contamination of the original quarterly composite E
sample (second quarter 1981). The analysis of lake water monthly composite samples was performed from April,1981 to September,1981 in conjunction with the analysis of routine quarter composite samples. All the monthly and quarterly samples were at the background level. The fact that tritium is naturally occurring accounts for the background level in the lake varying slightly from year to year.
Strontium-90 activity was detected in 11 of the 12 quarterly samples required by the plant's Technical Specifications. Both on site and off site sample locations showed measurable levels of Sr-90, ranging in concentration from 0.484 pCill to 1.04 pCi/1. The highest Sr-90 concentration of 1.04 pCi/1 was detected in the NMP-1 inlet canal. This concentration was just slightly higher than the highest control location concentration of 0.87 pCill detected during the same month.
As indicated throughout this report, Sr-90 concentrations can be attributed to atmospheric testing. Overall Sr-90 levels have decreased slightly g
from 1977.
1981 results for Sr-90 at both the control and indicator E
locations decreased from 1980 results.
78
I I
Sr-89 was detected in only one indicator sample for 1981.
The detected concentration of 0.78 pCi/l was at a concentration level of approximately the control LLD concentrations (1.02 pCi/1). This detection is insignificant and it is noted that Sr-89 has been detected at control I
locations in previous years.
For 1980, Sr-89 at control locations was as high as 1.4 pCi/l and 1.3 pCi/1. The presence of Sr-89 in the lake water samples is not considered to be significant and is not attributed to the operation of the site.
Gamma spectral analyses were performed on 36 monthly composite samples required by the Technical Specifications.
Indicator samples were collected from the inlet canals at NMP-1 and the FitzPatrick facilities. The control location samples were collected at the city of Oswego water treatment plant and consisted of raw water prior to treatment.
Co-60 was detected in three of the 24 indicator samples and one of the g
12 control samples.
The average concentration observed for the 3
indicator samples was 1.95 pCi/1 and 1.40 pCi/l for the control sample positive detection. The presence of Co-60 in lake water samples is not typical especially for the raw city water. The detections of Co-60 are most probably due to the fluctuation of instrument background.
Background samples are routinely analyzed with each monthly sample set to account for contribution of instrument background to sample activity.
I Due to the variable nature of background concentrations, low fluctuation in intensity encountered during analysis will result in small contributions of background radiation to sample activity if the l
background levels increase during sample analysis.
Cs-137 was detected in one of the indicator samples during the month of July at the NMP-1 inlet canal. The concentration detected was 2.3 pCi/l of Cs-137.
This detection is probably due to the radwaste activities during carly I
July and the recirculation of a portion of the discharge water into the inlet canal (condenser inlet tempering).
Normally, inlet tempering does not occur during July but during July of 1981 the NMP-1 facility was in g
a refueling outage started in March. The tempering gate had not been j
adjusted since March as a result of plant shutdown for refueling. The gate was adjusted during start-up on July 9.
Since inlet canal water is not utilized as drinking water, there are no dose consequences to man.
No other radionuclides were detected.
Sample results are presented in the analytical results section of the report. Lake water gross beta activity from 1974 to 1981 and monthly I
gross beta results have been graphed and presented in Section VII.
I I
7e
I TEltitESTRIAL PROGRAM Tables 9 through 24 depict the analytical results of the terrestrial samples collected for the 1981 reporting period.
1.
AIR PARTICULATE GROSS BETA - TABLES 9 AND 10 Air particulate gross beta results for the six off site and nine on site E
sample locations are contained in the analytical results section of the 3
report. The samples were collected on a weekly basis and were counted after twenty-four hours to allow for the decay of short half-life l
naturally occurring radionuclides. No significant levels of gross beta activity were observed for the 310 oif site samples or the 468 on site samples. The average yearly off site concentration was 0.165 pCi/m.
3 The average yearly on site concentration was 0.151 pCi/m2 The on g
site concentration was slightly lower probably because of the difference 3
of air flow rate of four of the nine on site monitoring stations.
Review of yearly mean results per station shows that all on site and off site stations had means at approximately the same concentrations. A slight decrease of the annual mean was noted for H, I, J, and K on site stations and is noted above.
Review of air particulate gross beta results on a weekly basis shows that a significant increase occurred at all on site and off site stations near the beginning of April and peaked near the end of May and into g
early June.
Concentrations for both on site and off site stations g
decreased in mid June, increased again in early July and fell off sharply in mid August.
As noted above, on site and off site stations showed identical trends.
Gross beta concentrations remained generally less than 0.1 pCi/m3 for the remainder of the year for both on site and off site stations. The increases and decreases in gross beta activity can be attributed to changes in the concentrations of the naturally E
occurring radionuclides found in the biosphere. The concentrations of E
naturally occurring nuclides in the lower levels of the atmosphere directly above the terrestrial portions of the earth are affected by time related processes such as wind direction, snow cover, soil temperature and soil moisture content.
A significant portion of the increased gross beta activity during the spring and summer is the increase of naturally occurring radionuclides in the immediate vicinity above ground 3
elevation.
During the spring, surface ground soil becomes unfrozen 5
and has a lower moisture content therefore allowing for the emanation of radon and thoron and especially the production of alpha and beta decay daughter products. During the summer months, the dry soils allow for dispersion of particulate matter into the atmosphere where radon / thoron daughter products have become attached to dust particles and the particles are themselves radioactive by minute quantities of the daughter products. In 1981 the increase in gross beta activity can also be partially attributed to the large amount of fallout detected during the spring and summer months.
(See air particulate composites, Section 2.)
A graph of air particulate gross beta concentration on a weekly and yearly frequency can be found in Section VII.
80 n
I 2.
MONTHLY PARTICULATE COMPOSITES - TABLE 11 The air particulate filters collected weekly from each of the 15 air sampling stations are composited monthly by location (on site /off site).
I Each composite is analyzed for gamma emitter using gamma spectral analysis.
I The results for samples analyzed during the 1981 sample program showed positive detections for Co-60, Co-58, Mn-54, Nb-95, Zr-95, Cs-137, Cs-134, Ce-141, Ce-144, Ru-106, Ru-103 and La-140 in addition to several other naturally occurring radionuclides (Be-7, K-40).
The total number of radionuclides detected during the year was 13.
Of the 13 detected, eight are considered to be directly related to fallout. The fallout is the result of an atmospheric nuclear test conducted by the People's Republic of China, in October of 1980. Measurable concentrations of Cs-137, Mn-54, Zr-95, Nb-95, Ce-141, Ce-144, Ru-103 and Ru-106 were detected at both the on site and air sampling stations.
Each of these radionuclides shows similar distribution over the year I
with peak concentrations present in April and May. Below are graphs of Nb-95, Zr-95, Ru-103 and Ce-144. These graphs illustrate very well the dramatic increase in air concentrations of these nuclides beginning in November and December of 1980 and continuing to increase until I
reaching a peak in April /May of 1981.
I
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81
I I
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1 After May of 1981 the concentrations of fallout nuclides decrease significantly until September of 1981 when levels return to pre-test concentration or lower limits of detection. Three other radionuclides (Co-60, Mn-54 and Cs-137) follow a similar distribution pattern for detectable concentration. Graphs of Cs-137 and Mn-54 below, again, illustrate the general increase after the detonation of the bomb in October of 1980, t
1 l
AIR FGRT:Cs-13T m
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=t d's 82
I I
In the case of each of these nuclides the control and the indicator stations show similar concentration, and in many cases the levels at the control station exceed that detected at the indicator station.
It should also be noted that during the time period of November,1980 to I
September of 1981 plant specific radionuclides such as Co-58 and Cs-134 were not detected on a routine basis.
Co-58 and Cs-134 were detected only once each during the 1981 sampling period.
La-140 was also detected once during 1981 in Alarch, which was just prior to the time period when peak concentrations of fallout nuclides were detected. The detection of La-140 is considered to be related to the aforementioned nuclear test.
A review of site airborne effluents shows no large increase in the months between November,1980 and September,1981 with peaks corresponding to the April /f. lay,1981 time period.
Several radionuclides were detected which are possibly related to plant operation. These nuclides are Co-60, Co-58, Cs-134 and Cs-137.
In I
the case of Co-60 and Cs-137 the concentrations which were detected, that fall outside what appears to be normal distribution curve for the fallout related nuclides, could be attributed to plant operation.
Both I
Cs-137 and Co-60 displayed smaller secondary peaks in July (Cs-137) and August (Co-60) of 1981, with maximum concentrations of 2.1 pCi/m3 for Cs-137 and 0.6 pCi/m3 for Co-60.
This secondary peak noted in the later summer months could be the result of the resuspension of I
previously deposited material. A second possible explanation could be the continuing fallout of material from the stratosphere which can contain radioactive material for many months which would be most noticeable for Cs-137 and Co-60 due to the relatively long half-life of these nuclides compared to the shorter half-life fallout nuclides. A similar secondary peak was also noted for Ce-144, Nb-95 and Zr-95 which shows up as a change in slope of the curve (or rate of I
reduction), with the nuclide with the longer half-life showing the greatest change in slope.
It should be noted that in both cases (Cs-137 and Co-60) the control station concentrations were greater than those measured at the indicator stations. Co-60 was detected in eight of the 12 off site samples and in 11 of the 12 on site samples.
Cs-137 was detected in 12 of the 12 off site samples and in 12 of the 12 on site samples. In all but one of the 12 samples the control station values for Cs-137 exceeded that of the indicator or on site stations.
Co-59 and Cs-134 were detected in the on site samples once each during the sample year.
In both cases no corresponding detection was made in the I
off site sample.
Dose to man calculations can be made using inhalation rates and air I
concentrations based on air sample results.
Using the average adult 3
s inhalation rate of 8,000 m /yr (667 m / standard month) and the mean concentration measured at the on site sample stations, the following yearly doses can be calculated:
I I
g es
l I
Concentration No. Months Dose
Nuclide (10 8 3m)
Detected Origin (mrem /yr)
Cs-137 1.22 12 Fallout / Plant 0.00009 Cs-134 0.70 1
Plant 0.00004 E
Co-60 0.40 11 Fallout / Plant 0.00219 5
Co-58 0.08 1
Plant 0.00001 Mn-54 0.73 8
Fallout 0.00068 E
Ru-103 10.34 9
Fallout 0.00392 E
Nb-95 36.85 12 Fallout 0.01860 Z r-95 20.10 10 Fallout 0.03010 Cc-141 7.44 8
Fallout 0.00179 Ce-144 16.51 12 Fallout 0.12800 Totals 0.18542 g
Fallout 0.18309 E
Plant 0.00005 Fallout / Plant 0.00228 I
Dose to the lung.
The above table illustrates that the average calculated dose to man from the plant related isotopes is insignificant. The dose to man as a result of weapons testing far exceeds the dose related to plant nuclides.
Section VII contains four graphs illustrating the concentrations of radionuclides detected during the 1981 sample program. Also in Section VII are a number of graphs showing sample results for 1980 and 1981.
3.
AIRBORNE RADIOIODINE (1-131) - TABLES 12 and 13 The results of I-131 (charcoal cartridges) sampling and analyses are presented in the analytical results section of the report.
During the 1981 sampling program, I-131 was not detected in any of the 312 weekly samples collected from six off site sampling stations.
1-131 was detected in five of the 468 weekly samples collected from the nine on site sampling stations. Four of the five detections were made at 11 on site monitoring station and the remaining detection was observed at the I on site monitoring station.
Observed on site detected concentratzons ranged from a minimum of E
3 0.016 pCi/m to a maximum of 0.042 pCi/m3 with a mean of 5
3 0.029 pCi/m. These observed values are minimal however since LLD values for on site samples ranged from <0.004 pCi/m to <0.063 pCi/m,
g 3
a It can be seen that the observed values fall between LLD values and g
are therefore within the range of the lower limit of detection. Off site LLD values for I-131 ranged from 0.009 pC1/m 3 to 0.043 pCi/m. As 3
noted above no 1-131 detections were observed at off site stations.
84
I An accurate dose estimate due to inhalation of airborne I-131 is difficult to make since there are no residential areas in the immediate vicinity of 11 on site or I on site stations.
It is notable that the 11 on site and J on site are well within the site boundary or controlled area.
liowever, for the purpose of illustration and perspective, if the average airborne concentration is 0.029 pCi/m3 and the period of detection is five weeks, a man would receive a dose of 0.03 mrem / year based on 8,000 m3 I
inhaled per year. The critical organ for this example is the thyroid.
This dose assumes that the residence time is 840 hours0.00972 days 0.233 hours 0.00139 weeks 3.1962e-4 months or five full weeks at this location. The dose is very minimal and can be compared to an increase in the whole body dose due to cosmic radiation. A similar dose would be received by residence in a location 100 meters higher in altitude for 5.5 days. Th0 end result of the 1981 I-131 sampling effort shows no significant impact due to the operation of the I
plant.
During 1981, 1-131 was not detected in any other sample media such as milk or green leafy vegetables.
4 TLD (ENVIRONhlENTAL DOSlalETRY) - TABLE 14 TLD's are collected once per quarter during the sample year. The TLD results are an average of four independent readings at each location I
and are reported in mrem per standard month.
Each location has two TLD's with each TLD containing two distinct calcium sulfato dosimeters.
In 1981, TLD's for the most part were collected on April 1,1981, July 1,1981, October 1,1981, and December 30, 1981.
TLD results are organized into three groups for reporting purposes.
The groups are on site TLD's (defined as TLD's immediately I
surrounding the individual facilities and are located at 9oints of interest), environmental station TLD's (a ring of TLD's surrounding the generating facilites as a group), and off site TLD's (TLD's located off the site property and ranging up to 20 miles from the site). A net I
dose at the environmental station TLD's can be calculated simply by subtracting quarterly off site doses from quarterly on site environmental station doses. Environmental station TLD's are arranged I
in a concentric circle and range in distance from the individual facilities from 1,500 to 2,000 feet. The net dose per quarter and per annual mean is as follows:
i Quarter Net Environmental Station Dose (mrem) 1 0.53 2
0.41 3
0.90 4
0.18 Total 2.02 I
The annual site property boundary dose for 1981 cannot be determined from the net environmental station dose since the property boundary g
ee-
l I
extends out to approximately 0.75 miles from the site. A general estimate can be made based on two available TLD's located at the site boundary. The net quarterly and net total annual dose can be calculated for these two locations (TLD numbers 19 and 15) east and west of the site. This calculation is conservative since it represents 3
the shortest distance to populated areas.
3 Quarter Net Site Boundary Dose (mrem) 1 0
2
-0.16 3
-0.15 4
-0.50 Total
-0.81 As observed, the site boundary dose based on two available TLD locations is less than the average off site dose. This is probably due 5
to the difference in ground dose rates which are indicative of variable concentrations of naturally occurring radionuclides in soil and rock such as radium, uranium, thorium, and potassium. The difference could also result from statistical variation in the TLD readings, as the site boundary dose is based on a population of only eight individual readings per quarter.
TLD numbers 31 and 39 are located within the Nine Mile Point Unit #1 restricted area near the radwaste facility and are influenced by the close proximity to the building. TLD numbers 27 through 30, and 47 are located within the restricted area of the James A. FitzPatrick radwaste facility and are influenced by the buildings. TLD number 59 is located near the restricted area of the FitzPatrick Plant stack and is influenced by the proximity to this structure. TLD number 3 is located at the construction site of Nine Mile Point Unit #2.
This TLD is subject to radiography at the Unit #2 site and to a smaller extent the E
FitzPatrick facility.
3 l
TLD doses remained fairly consistent for most TLD locations each I
quader. All off site locations remained relatively constant. On site I
doses remained relatively constant except for TLD's located near radwaste facilities which were affected by the frequency of shipment processing and shipments. These TLD's include numbers 27, 28, 29, E
l 30, and 47.
TLD number 3 at the Unit #2 construction site decreased 3
slightly in the fourth quarter. This was most probably due to the frequency of radiography.
The results for 1981 showed no impact from direct radiation measured outside the site boundary.
I l
86
I I
5.
ItADIATION MONITOllS - TABLE 16 Environmental radiation monitors are located in 10 of the 15 air monitoring environmental stations. Each of the on site environmental I
monitoring stations contains a radiation monitor and, in addition, the C off site monitoring station contains a similar monitor. The radiation monitors consist of a GM detector with an associated power supply, chart recorder, and trip unit. The monitor has an operating and I
recording range from 0.01 to 100 mrem /hr. Each radiation monitor has a small radioactive source mounted inside the detector casing to produce an on scale reading. The design intent of the monitors is to detect possible dose rates resulting from plume releases from the plant. The monitors are not considered to be capable of high sensitivity environmental monitoring and do not detect minute fluctuation in levels I
of background radiation. Because of the relatively poor sensitivity of the monitors (environmentally speaking) no comparisons are made between the radiation monitor readings and the readings from environmental TLD's.
I 6.
MILK - TABLES 16,17, AND 18 I
Milk samples were collected from a combination of seven farms during the 1981 grazing season (May through December,1981).
One of the six farm locations, number 25, was only sampled during two of the eight sample months during the year. Samples were available at this location I
only during July and August because the single cow at the farm was dry during the other available sampling months.
Collections were made only during the first half of the month at this location for these two I
months. Therefore only I-131 results are shown for this location in the analytical results section of the report. Starting in September and through December, this farm location no longer had a milk cow available for sampling. A seventh location (number 7) was available starting in October and was sampled through December. Sample location descriptions are included below.
Location No.
Direction from Site Distance from Site (Miles) 4 ESE 7.5 40 SW 15.0 I
14 ESE 9.0 16 SSW 6.0 25 ESE 1.5 I
12 SSE 7.0 7
ESE 5.2 Milk samples were collected from each of the locations in the first half I
of the month and analyzed for I-131.
At approximately mid month, a second milk collection was made at the same locations. The second collection was composited with an equal aliquot from each location sampled during the first collection. The composite samples were analyzed for gamma emitters and strontium-90.
1-131, gamma isotopic, and strontium-90 results are found in the analytical results section.
87.
I The gamma spectral analyses of the monthly composite samples showed K-40 to be the most abundant radionuclide detected in the milk samples collected in 1981.
K-40 was detected in every sample analyzed and ranged in concentration from 960 to 1,800 pCi/l at the indicator stations and 1,100 to 1,400 pCi/l at the control station.
K-40 is a naturally 3
occurring nuclide and is found in many of the environmental medias 5
sampled.
Cs-137 was the second most abundant radionuclide detected in the 1981 milk samples.
Cs-137 was measured in 15 of the 43 monthly composite samples analyzed. Cs-137 was detected in milk samples at all locations sporadically throughout the year except at location number 7 (sampled g
October - December only).
Cs-137 was detected at the control location 3
once during the year at a corcentration of 7.0 pCi/1.
Cesium concentrations ranged from 4.3 pCill to 10.0 pCi/1 for all samples with an annual mean of 6.29 pCi/1. Cesium was detected at a higher frequency at locations 12 and 16.
The maximum concentration of 10.0 pCill was detected at location number 12 during June. Annual means for the detection of Cs-137 at all stations are presented below.
Location No.
Annual Mean (Cs-137) 4 4.8 pCi/1 40 (control) 7.0 pCi/l 14 4.7 pCi/l 16 6.7 pCill E
25 No GS A Samples 5
12 7.8 pCi/l 7
Not Detected Annual mean Cs-137 values for each sampling location are variable but quantitatively the values are not significantly different from one another especially when the magnitude of these minute concentrations are concerned. A significant portion of the Cs-137 detected in milk samples is due to deposition of Cs-137 from past atmospheric nuclear testing.
Evaluation of Cs-137 concentrations in pasture soil, pasture grass, hay, grain, and silage does not show a correlation as to -why certain locations show a slightly higher Cs-137 concentration than other locations.
Dasture soil samples were collected at the six milk sample locations (numbers 4, 40,14,16, 25, and 12) in June, July and i
September of 1981.
Cs-137 was detected in all soil samples as expected. Cesium detection was noted in the control location as well.
3 Locations number 4 and 16 showed slightly higher soil Cs-137 E
concentrations that the other locations sampled. Milk sampled from these locations, however, showed Cs-137 concentrations that were lower than the mean for location number 4 and of an average concentration for location number 16.
In addition to Cs-137 in pasture soil samples, Cs-137 has been detected in the past at a control environmental station location. These soil samples were collected and reported in 1975. 1977, g
and 1980. Mean Cs-137 concentrations in soil at this location ranged 3
from 1.07 to 1.20 pCi/g (dry). Minimum and maximum ranges for individual samples ranged from 0.41 pCi/g (dry) to 2.90 pCi/g (dry).
88
I These values are above the values detected at the milk sampling locations. Based on the pasture soil data available, it can be noted that there is no distinct correlation between cesium in milk and cesium in pasture soils.
Other related data was available from the milk locations that can be used to assess cesium in milk. Pasture grass was collected in June, July, August, September, and October,1981. Cs-137 was not detected I
in any of the samples from the seven milk sample locations (numbers 4, l
40,14,16, 25,12, and 7), except from location number 40.
This location was the control location.
The concentration detected was very small (0.0742 pCi/g [ wet]), and was probably due to plant uptake.
Hay samples were collected twice during 1981. A first cut was collected in June - July and a second cut was collected in September - October.
Cs-137 was not detected in any samples except for one sample at location number 4.
The concentration detected here was 0.358 pCi/g (wet). This detection does not account for milk cesium levels since locations number 12 and 16 had higher milk cesium levels for June -
July whereas cesium was not detected in hay samples for this period.
Grain samples were collected in June and analyzed. Cesium was not detected in grain from any of the locations' samples (numbers 4, 40, 16, 14, 25, and 12). Grain, hcwever, is not a good indicator of regional Cs-137 levels since it u.,uuliy has a mid west origin. Corn silage was sampled in October at all milk locations except location number 25.
Cesium was not detected in corn silage at any of the sampled locations (numbers 4, 40, 14, 16, 12, and 7). In addition to soil and fodder samples the milk herd water sources were sampled and analyzed. The analyses of milk herd water sources showed no positive detections of Cs-137.
Cs-137 concentrations in milk are variable and were detected at very low levels. A significant portion, if not all, is due to weapons testing from previous years. This is exemplified by the detection of 7.0 pCill of Cs-137 in the control sample. Results for gamma emitters in milk are presented in the analytical results section of the report.
l l
Examination of previous Cs-137 leveis in milk samples shows that the annual mean for indicator locations has decreased from previous years.
The annual mean for 1981 was 6.5 pCi/l (positive cesium detections),
I i
The annual means for 1978 - 1980 were higher (9.9 pCi/1, 3.4 pCi/1, and 9.7 pCi/l respectively).
No other radionuclides were detected in milk samples using gamma spectral analysis.
Strontium-90 was ' detected in each of the milk samples collected in 1981 I
with the exception of location number 14 in December. The mean yearly concentration for the control location was approximately the same as th, mean concentration for the indicator locations. Sr-90 results for the indicator locations ranged from 1.2 pCi/l to 11.0 pCi/1. Sr-90 results for the control location ranged from 2.4 pCi/l to 8.0 pCi/1.
I 89
r I
I These values are above the values detected at the milk sampling locations. Based on the pasture soil data available, it can be noted that there is no distinct correlation between cesium in milk and cesium in pasture soils.
Other related data was available from the milk locations that can be used to assess cesium in milk.
Pasture grass was collected in June, July, August September, and October,1981. Cs-137 was not detected a
in any of the samples from the seven milk sample locations (numbers 4, g
40,14,16, 25,12, and 7), except from location number 40.
This location was the control location. The concentration detected was very small (0.0742 pCi/g [ wet]), and was probably due to plant uptake.
E sIlay samples were collected twice during 1981. A first cut was collected B
in June - July and a second cut was collected in September - October.
Cs-137 was not detected in any samples except for one sample at a
location number 4.
The concentration detected here was 0.358 pCi/g g
(wet). This detection doos not account for milk cesium levels since locations number 12 and 16 had higher milk cesium levels for June -
July whereas cesium was not detected in hay samples for this period.
Grain samples were collected in June and analyzed. Cesium was not detected in grain from any of the locations' samples (numbers 4, 40, 16,14, 25, and 12). Grain, however, is not a good indicator of regional Cs-137 levels since it usually has a mid west origin.
Corn silage was sampled in October at all milk locations except location number 25.
Cesium was not detected in corn silage at any of the sampled locations (numbers 4,14,16,12, and 7) except for location number 40 which is the control location.
The concentration was very small (0.92 pCi/g [ wet]) and was probably due to plant uptake or fallout deposition. In addition to soil and fodder samples the milk herd g
water sources were sampled and analyzed. The analyses of milk herd g
water sources showed no positive detections of Cs-137.
Cs-137 concentrations in milk are variable and were detected at very low levels. A significant portion, if not all, is due to weapons testing from previous years. This is exemplified by the detection of 7.0 pCi/l of Cs-137 in the control sample. Results for gamma emitters in milk are presented in the analytical results section of the report.
Examination of previous Cs-137 levels in milk samples shows that the g
annual mean for indicator locations has decreased from previous years.
g The annual mean for 1981 was 6.5 pCi/1 (positive cesium detections).
The annual means for 1978 - 1980 were higher (9.9 pCi/1, 9.4 pCi/1, and 9.7 pCi/l respectively).
No other radionuclides were detected in milk samples using gamma spectral analysis.
Strontium-90 was detected in each of the milk samples collected in 1981 with the exception of location number 14 in December. The mean yearly concentration for the control location was approximately the same as the E
mean concentration for the indicator locations. Sr-90 results for the B
indicator locations ranged from 1.2 pCill to 11.0 pCi/1. Sr-90 results for the control location ranged from 2.4 pCi/l to 8.0 pCi/1.
90
I 7.
MILCH ANIMAL CENSUS - TABLE 19 The milch animal census is an estimation of the number of cows or goats within the 10 mile radius of the Nine Mile Point site.
A census is I
conducted twice per year, once in the spdng and once in the summer.
The census is conducted by sending questionnaires to previous n.ilch animal owners and also by road surveys to locate any possible new I
Questionnaires not responded to are followed up by telephone owners.
calls.
The number of milch animals located within the 10 mile radius of the I
site was estimated to be 998 cows and eight goats for the.1981 spring census. No new locations were found since the summer 1980 census.
The number of cows increased by 103 and the number of goats increased by 3 with respect to the 1980 summer census.
The 1981 summer census shcwed a total of 986 cows and 10 goats *.
This represents a decrease of 12 cows and an increase of 2 goats with respect to the 1981 spring census. As a result of the summer 1981 census, a new milk location (number 7) was added to the sample p rogram.
8.
HUMAN FOOD PRODUCTS - TABLE 20 Human food product samples were comprised of meat, eggs, poultry, fruits and vegetables. Collections for meat, poultry and eggs were made in the spring and fall seasons. Samples of produce included vegetables and fruit with the sampling of at least one green leafy I
vegetable from each location. The collection of produce was performed in late summer or early fall. Three indicator locations were sampled far each type of media collected, in addition. a control location was sampled during each collection period. Indicator samples were collected within a 10 mile radius of the site in areas which would have a high potential for demonstrating possible effects of site cperations. The ultimate factor controlling sample locations was the availability of required samples.
Attempts were made to maintain prior sample locations where possible.
Meat sarrples collected during the spring were obtained at twc off site locations (one extra sample) and three on site locations. Because of the difficulty of obtaining meat samples within a 10 mile radius of the site during the springtime, a third on site meat sample was collected approximately 30 days after the initial meat sample collection period.
The collection of spring meat samples has historically been a difficult sample medium to obtain due to seasonal unavailability. See Section V.,
exceptions to the prcgram.
Estimated I
91
I Spring meat samples showed detee'.able K-40 in all samples. K-40 concentrations ranged from 1.7 pCi/g (wet) to 2.7 pCi/g (wet) and is a naturally occurring radionuclide.
Three of the five meat samples collected showed detectable concentrations of Cs-137. Two of the three positive detections were made in control samples. Cs-137 detections E
rar.ged from 0.017 pCi/g (wet) to 0.070 pCi/g (wet).
Cs-137 was 3
detected in control and indicator locations for pasture soil during 1981 (0.189 to 0.968 pCi/g [ dry]), in one pasture grass sample (0.07 pCi/g
[ wet]), and in two hay samples (0.36 and 0.36 pCi/g [ wet])
respectively). The Cs-137 measured in meat is the result of atmospheric fallout from weapons testing and has been detected in similar concentrations in previous years. The mean concentrat{on of E
Cs-137 in meat samples for the indicator locations during 1978 - 1980 m
ranged from 0.009 to 0.07 pCi/g (wet). The mean Cs-137 concentration during 1981 for the indicator locations was 0.07 pCi/g (wet). Based on the positive Cs-137 detections at the control locations and the variability of Cs-137 concentrations detected over the previous years, it is considered that Cs-137 detections in meat samples are not plant related.
51 eat samples collected in the fall of the year also showed detectable concentrations of K-40 and Cs-137. K-40 was detected in all samples collected and ranged from 2.4 pCi/g (wet) to 3.1 pCi/g (wet). Cs-137 was detected in all three indicator samples but not in the control sample. Cs-137 concentrations ranged from 0.023 pCi/g (wet) to 0.030 pCi/g (wet). Although Cs-137 was not detected at the control location during the fall of 1981, it has been detected at the control location in previous seasons. During the spring collections, Cs-137 was detected at the control location at 0.017 pCi/g (wet) and 0.024 pCi/g 3
(wet) which is approximately the same concentrations as the fall E
indicator sampics. Again, based on the detections of Cs-137 at the control locations and the inherent variability of Cs-137 as positive detections, there is no reasoa to suspect plant related Cs-137.
No other radionuclides were detected in meat samples using gamma spectral analysis, g
l g
The detection of Cs-137 in meat at control and indicator locations is an l
indication of cesium production from weapons testing.
A dose estimate can be made for indicator and control sample data based on Cs-137 concentrations detected in spring and fall samples.
Based on an average Cs-137 concentration during 1981 of 0.038 pCi/g (wet) at the indicator locations and a consumption rate of 110 kg (meat) per year, E
the dose to the liver is 0.46 mrem and 0.30 mrem to the whole body.
E l
Using the same criteria and the average Cs-137 concentration of 0.02 pCi/g (wet) at the control locations, the dose to tne liver would g
be 0.24 mrem and 0.16 mrem to the whole body. As observed, th I
whole body and liver dose difference between the indicator and control locations is not significant. Dose estimates made here are conservative since the maximum consumption rate of meat was utilized and the most l
sensitive organs to radionuclide uptake were exemplified.
5 I
92
I Egg samples collected during the spring and fall showed measurable concentrations of K-40 at all locations. K-40 ranged from 0.8 pCi/g (wet) to 1.2 pCi/g (wet). No other radionuclides were detected in the egg samples analyzed by gamma spectral analysis.
Poultry samples taken during the spring collection were obtained from three locations within a 10 mile radius of the site and one location outside of the 10 mile radius. One of the indicator samples was I
invalidated during the analysis process and it was necessary to recollect an additional indicator sample. This particular sample contained measurable concentrations of Mn-54, Co-58 and Co-60.
The detected I
concentrations were low and appeared to be the. result of laboratory contamination during the processing stage. The presence of Co-58 and the absence of Cs-137 strongly suggested contamination. Poultry I
samples (two) were recollected from the same location and from the same approximate ege group. No radionuclides, with the exception of K-40, were detected.
It was therefore determined that the detected concentrations of Mn-54, Co-58, and Co-60 were due to contamination, and no further samples were required.
K-40 was detected in all poultry samples obtaint.d during the spring.
I K-40 concentrations ranged from 2.6 pCi/g (wet) to 3.3 pCi/g (wet).
The control sample showed a concentration of 3.1 pCi/g (wet). No other radionuclides were detected for the spring samples. Samples obtained during the fall at three indicator locations and one control location showed positive detections of K-40 ranging from 2.9 pCi/g (wet) to 3.5 pCi/g (wet).
K-40 was detected at a concentration of 2.9 pCi/g (wet) at the control location.
No other radionuclides were detected in the fall samples.
Dose estimations were not made for poultry since no radionuclides were detected with the exception of K-40 which is naturally occurring.
Fruits and vegetables were obtained during the harvest season.
Collections were made during September at three indicator locations and I
one control location. A successful attempt was made to collect one broadleaf and one non-broadleaf fruit or vegetable at each location.
Non-broadleaf samples of tomatoes as well as broadleaf vegetables were originally collected on September 9.
The broadleaf samples however
'I were invalidated since they were not analyzed for I-131 within one half-life or eight days of collection.
Broadleaf vegetables were recollected on September 22 and successfully analyzed within eight days of collection.
K-40 was detected in all broadleaf and non-broadleaf vegetables and fruits. Broadleaf vegetables (Swiss chard and cabbage) showed concentrations of K-40 ranging from 1.8 pC1/g (wet) to 5.8 pCi/g (wet).
The control location showed a K-40 concentration of 5.8 pCi/g (wet). Non-broadleaf fruits (tomatoes) also showed detectable I
concentrations of K-40 ranging from 1.9 pCi/g (wet) to 2.7 pCi/g (wet). The control location showed a K-40 concentration of 2.6 pC1/g (wet).
I 93
1 I'
Pe-7 was detected for one of the broadleaf samples collected. Be-7 was detected at a concentration of 0.33 pCi/g (wet). The positive detection was made at the control location. Be-7 is a naturally occurring radionuclide which is a result of the interaction between cosmic radiation and the upper atmosphere. No other radionuclides were E
detected in the 1931 collection of fruits or vegetables.
5 Dose estimates were not performed for fruits or vegetables since no other radionuclides with the exception of K-40 and Be-7 were detected.
Historical data for human food products can be found in Section VI.
9.
SPECIAL STUDIES - TABLES 21, 22, AND 23 Since 1974, the detection of Cs-137 in milk samples analyzed for the radiological environmental monitoring program has been common.
The specific source of the Cs-137 is not known as there are several possible source terms for this particular radionuclide.
Cs-137 is a small component of plant effluents and is also a major fallout nuclide from the detonation of thermonuclear devices in the atmosphere. Because Cs-137 has a half-life of 30.2 years it remains a detectable component of environmental sample media for many years. It is estimated that about 34 million curies (34 Megacuries) of Cs-137 have been produced in the atmosphere due to weapons testing. Cs-137 is present in many of the sample media collected for the environmental monitoring program.
In the environment, cesium behaves much like potassium with regard to metabolism and elements found in liiing tissue.
To better understand the levels of Cs-137 in the local environment a group of farm related samples has been collected over the past several E
years. These samples were chosen because of their role in the milk 3
pathway which is important in the dose to man concept.
In 1961 samples of pasture soil, pasture grass, surface water, milk herd waters and fodder crops and sediment were collected. The samples were analyzed using gamma spectral analysis which would show the presence of gamma emitting radionuclides.
A total of 22 soil and sediment samples were collected in 1981. The majority of these samples were collected at routine milk sampling locations to increase the data base at these sample points and to aid in identifying possible correlations between plant operation and Cs-137 in local milk samples, should they exist.
l A total of seven radionuclides were detected in the soil / sediment l
samples collected. Ra-226 is a naturally occurring radioisotope and was detected in all but one of the 22 samples analyzed.
The concentrations for Ra-226 ranged from a maximum of 3.69 pCi/g (dry) to a minimum of 1.41 pCi/g (dry) in a marsh sediment sample.
Be-7, a second naturally occurring nuclide, was detected in two of the 22 samples.
Ce-144 and Nb-95 are fallout nuclides which were detected in two of the samples.
A stream sediment sample contained both Ce-144 and Nb-95 and the second sample, a pasture soil sample, contained of the two, only Nb-95.
94
I A detectable level of Co-60 was found in one soil sample of the 22 collected. The presence of this radionuclide is considered to be the result of instrument background. The variability of the Co-60 background will at times result in a positive detection near the LLD level.
In this particular sample the detected level of Co-60 is just at the mean LLD value for the other 22 samples analyzed.
Twenty of the 22 samples analyzed contained measurable concentrations of Cs-137.
The levels for Cs-137 ranged from a maximum of 1.32 pCi/g (dry) to a minimum of 0.25 pCi/g (dry). The maximum value was detected in a marsh sediment sample with the high concentration theoretically resulting from the leaching of Cs-137 from the surrounding watershed during periods of precipitation and spring runoff. The mean concentration of the indicator station for pasture soll samples was 0.59 pCi/g (dry) while the control mean for the pasture soil samples was equal to 0.36 pCi/g (dry). The concentration of cesium in soils in many cases is dependent upon the clay content of the soil in which the cesium is deposited. This can account for general differences of Cs-137 I
concentrations from location to location. The samples collected in 1981 show a higher mean value for the indicator station than for the control stations, though not significantly higher based on the fact that soil types can influence Cs-137 concentration in soil. In 1980 a series of control (6) and indicator (9) soil samples were taken. The mean for the 1980 control samples was 1.20 pCi/g (dry) and the indicator mean concentration was equal to 1.27 pCi/g (dry).
In comparison, the 1981 I
pasture scil srimples concentrations were less than the mean control concentration detected in 1980. Again soil types were not considered as to their effect on the difference between cesium soil concentrations.
In conjunction with soil samples, fodder crops and pasture grass samples were also collected in 1981.
A total of 53 such samples were collected from the routine milk sample locations and analyzed for gamma emitters. Three naturally occurring radionuclides (Ra-226, Be-7 and K-40) were detected. K-40 was detected in each of the 53 samples and Ra-226 and Be-7 were detected in a combination of 41 samples.
Three fallout nuclides were detected in the samples collected with Cc-144 being detected in 17 samples.
Nb-95 was detected in 12 samples and Cs-137 was detected twice with one of the measured concentrations found at the control station sample in the October corn silage. The presence of Co-60 was measured in four samples during the year with each detection measured at a different location. The presence of Co-60 I
is considered to be instrument background and not due to the operation of the plant. The random detection of Co-60 in both the temporal and statial parameters shows the lack of a definite trend or pattern.
The detected Co-60 is not the result of plant operation.
The third series of samples collected for the special studies were surface waters. These collections included samples from the milk herd I,
water sources at each of the routine milk sample locations and samples from the general drainage pattern of the land surrounding the site. A total of 48 samples were analyzed from a combination of water sources.
95
t The milk herd water sources were collected from the major water supply used by Ge dairy herd at each farm at the time of collection.
This sampling methodology would allow for direct correlsdon of Cs-137 concentrations detected in the monthly milk samples with the concentrations of Cs-137 detected in the appropriate water supply. No detections of Cs-137 were made in any of the 48 samples analyzed. Two naturally occurring radionuclides (K-40 and Ra-226) were detected in the samples. Concentrations of Ra-226 ranged from 'a minimum of 13.5 pCill to a maximum of 161.0 pCill in the control location well sample.
Co-60 was the only radionuclide detectea which is not naturally occurring. The presence of Co-60 is considered to be the result of instrument background as indicated above for soil and fodder crops.
It should be noted that a series of samples collected in June and two samples collected in both July and August were contaminated in the laboratory at the time of analysis and the results are not presented in this report. The four samples showing the highest levels of contamination were those found to have been prepared and analyzed as a batch. An investigation into the pcssible source of the contaminations was conducted and the source was determined to be material in the counting laboratory. To assure that the radionuclides detected in the contaminated samples were not in part due to contamination in the environment, a series of follow-up water collections were made in each of the three months of October, November and December. As noted on Table 22 no plant related radionuclides were detected in these follow-up samples.
s 96
CONCLUSION The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of the James A. FitzPatrick Nuclear Power Plant on the local environment. As demonstrated by the analytical results of the 1981 program, the major radiological impact on the environment was the result of fallout from atmospheric nuclear testing.
Levels of natural background and the associated fluctuation in intensity are much more significant in terms of dose to man (normal background in the vicinity of the site is equal to 60 mrem /yr) than radiation levels in the i
. environment associated with the operation of the plant.
Using the data presented in this report, and earlier reports as a basis, it can be concluded that no appreciable radiologica! environmental impact has resulted from the operation of the James A. Fitz.'atrick Nuclear Power Plant.
9 97
EXCEPTIONS TO TIIE PROGRAM 1.
Meat samples were collected at only two of the three required sampling locations during the spring sampling period.
Weekly calls to the local claughterhouses beginning on April 29, 1981 and continuing until June 5,1981, resulted in two on site samples and one control (off site) sample. A fourth sample was collected during the spring sampling period (in lieu of the unobtainable third on site sample) which was located outside the 10 mile radius requirement for on site sampling. A third on site sample wat. collected on July 9,1981, which was outside the spring sampling period.
The difficulty in obtaining the required number of samples may be' attributed to several factors.
First the number of animals raised for meat and located within the 10 mile radius of the plant is not extensive.
Secondly, butchering of animals is not always performed at the local g
meat market. Third, and most significant, is the fact that the vast g
majority of meat is butchered in the fall so animals can graze in pasture for the summer to economically increase the meat yield.
The collection of spring meat samples has historically been a difficult sample medium to obtain due to seasonal unavailability.
2.
Environmental radiation monitor I on site was inoperable January 12, i
1981 (1100 hours0.0127 days 0.306 hours 0.00182 weeks 4.1855e-4 months ) to January 15, 1981 (1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months ). Malfunction of monitor was due to technician error.
3.
Environmental monitoring stations H and 1 on sites were inoperable from March 9,1981 (1245 hours0.0144 days 0.346 hours 0.00206 weeks 4.737225e-4 months ) to March 12, 1981 (1200 hours0.0139 days 0.333 hours 0.00198 weeks 4.566e-4 months ) due to loss of electrical supply power. Circuit breaker in the supply line tranformer was defective.
4.
Environmental radiation monitor G on site was inoperable from July 4, 1981 (0800 hours0.00926 days 0.222 hours 0.00132 weeks 3.044e-4 months ) to 07/06/81 (1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months ) due to monitor failure.
5.
Environmental monitoring station I on site was inoperable from August 3, 1981 (1430 hours0.0166 days 0.397 hours 0.00236 weeks 5.44115e-4 months ) to August 6, 1981 (1530 hours0.0177 days 0.425 hours 0.00253 weeks 5.82165e-4 months ) due to electrical problems. The cause of the electrical problems was suspected to be the result of a lightning strike.
6.
Environmental radiation monitor D n site was inoperable from 2
l August 8, 1981 (1730 hours0.02 days 0.481 hours 0.00286 weeks 6.58265e-4 months ) to August 14, 1981 (1300 hours0.015 days 0.361 hours 0.00215 weeks 4.9465e-4 months ) due to monitor failure.
l 7.
Environmental radiation monitor G on site was inoperable from September 10, 1981 (1000 hours0.0116 days 0.278 hours 0.00165 weeks 3.805e-4 months ) to September 17, 1981 (1415 hours0.0164 days 0.393 hours 0.00234 weeks 5.384075e-4 months ) due to monitor failure.
I 98
REFERENCES 1.
U.S.
Nuclear Regulatory Commission Regulatory Guide 1.109,
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1", March,1976.
2.
U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, I
" Calculation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", October,1977.
~
3.
Eichholz, G., Environmental Aspects of Nuclear Power, First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan,1976.
4.
National Council on Radiation Protection and Measurements (NCRP),
Environmental Radiation Measurements, NCRP Report No. 50, 1976.
I 5.
National Council on Radiation Protection and Measurements (NCRP),
Natural Background Radiation in the United States, NCRP Report No. 45, 1975.
6.
National Council on Radiation Protection and Measurements (NCRP),
Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977 7.
U.S. Nuclear Regulatory Commission Regulatory Guide 4.8,
" Environmental Technical Specifications for Nuclear Power Plants",
December, 1975.
8.
U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program", November,1979.
9.
Eisenbud, Merril, Environmental Radioactivity, Second Edition, l
Academic Press, New York, New York,1973.
l 10.
Francis, C. W., Radiostrontium Movement in Soils and Uptake in Plants, Environmental Sciences Division, Oak Ridge National Laboratory, U.S. Department of Energy,1978.
11.
National Council on Radiation Protection and Measurements (NCRP),
Radiation Exposure from Consumer Products and Miscellaneous Sources, NCRP Report No. 56, 1977.
12.
Pochin, Edward E., Estimated Population Exposure from Nuclear Power Production and Other Radiation Sources, Organization for Economic Co-operation and Development, 1976.
I 13.
ICRP Publication Number 29, Radionuclide Releases into the Environment: Assessment of Dose to Man,1979.
99
.i 7
m E
m n
m VI Jit
=
IIISTORICAL DATA 1
m j
M 7
5 i
M a
5
W u
VI HISTORIt'AL DATA
+
EL Sample Statistics from Previous Environmental Sampling 7
The mean, standard deviation, minimum value, maximum value, and range, L
were calculated for selected sample mediums and isotopes.
Special Considerations:
1.
Sample data listed as 1969 was taken from the NINE MILE POINT.
PRE-OPERATION SURVEY,1969 and ENVIRONMENTAL hlONITORING
[
REPORT FOR NIAGARA hlOllAWK POWER CORPORATION NINE MILE L
POINT N UCLEAR STATION, NOVEMBER,1970.
2.
Sample data listed as 1974 was taken from the NINE MILE POINT p
NUCLEAR STATION, ENVIRONMENTAL OPERATING REPORT. The 1974 data is pre-ope;ational to the James A. FitzPatrick Nuclear Power Plant, I
which started commercial operation in November,1974.
3.
Sample data listed as 1975,1976,1977,1978,1979 and 1980 was taken I
from the respective environmental operating reports for Nine Mile Point Nuclear Station and James A. FitzPatrick Nuclear Power Plant.
4.
Only measured values were used for statistical calculations.
I I
I 100
I HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL STANDARD Periphyton MEAN DEVIATION MAXIMUM MINIMUM RANGE Cs-137 pCf /g (wet) 1981 0.19 0.07 0.24 0.14 0.10 g
1980 0.03 0.01 0.04 0.02 0.02 1979 0.07 0.08 0.13 0.02 0.11 1978 0.04 0.03 0.063 0.023 0.04 1977
<MDL 1976 5.00 ONLY ONE DATA POINT 1975
<MDL 1974 0.10 0.02 0.12 0.09 0.30 1969 (PRE 0PERATIONAL)
NO DATA I
INDICATOR Periphyton STAN0/{0 MAXIMUM MINIMUM RANCE MEAN DEVIATION Cs-137 pCi/g (wet) 1981 6.24 6.75 16.00 0.47 15.53 1980 0.09 0.05 0.15 0.04 0.11 l
1979 0.36 0.55 1.10 0.08 1.02 1978 0.11 0.06 0.19 0.05 0.14 1977 0.42 0.56 1.40 0.09 1.31 g
1976 2.60 1.38 4.10 1.40 2.70 1975 22.25 14.34 36.00 4.00 32.00 1974 5.18 3.73 8.44 1.72 6.72 1969 (PRE 0PERATIONAL)
NO DATA 101
/
b
~
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL Mollusks MEAN DE IA MAXIMUM MINIMUM RANGE Sr-89 pCi/g (wet) 1981
<LLD 1980
<Llo 1979
<Llo 1978 0.02 ONLY ONE DATA POINT 1977
<MDL 1976 NO DATA 1975 NO DATA 1974 NO DATA 1969 l
(PRE 0PERATIONAL)
N0 DATA I
INDICATOR r-pCi/g (wet)
MEAN MAXIMUM MlhlMUM RANGE D
Tl l
1981
<Llo 1980
<LLD 1979 0.04 0.03 0.07 0.01 0.06 g
1978 0.05 0.03 0.07 0.03 0.04 1977
<MDL 1976 0.42 ONLY ONE DATA POINT 1975
<MDL 1974
<MDL 1969 (PRE 0PERATIONAL)
NO DATA 102
I
~
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL MEAN OfhlAl MAXIMUM MINIMUM RANGE Sr 0 Ci/g (wet) 1981 0.046 0.008 0.052 0.040 0.012 l
1980 0.07 0.06 0.11 0.03 0.08 1979 0.07 0.05 1.00 0.02 0.08 1978 0.14 0.02 0.15 0.12 0.03 g
1977 0.23 0.21 0.38 0.08 3.30 1976 NO DATA 1975 NO DATA 1974 NO DATA l
1969 I
(PRE 0PERATIONAL)
NO DATA l
IND!CATOR MEAN MAXIMUM MINIMUM RANCE r 0 pCi/g (wet)
DE ATI 1981 0.094 0.060 0.132 0.005 0.127 1980 0.11 0.03 0.14 0.07 0.07 l
1979 0.10 0.04 0.17 0.05 0.12 1978 0.14 0.03 0.18 0.10 0.08 1977 0.10 0.02 0.11 0.07 0.04 l
l 1976 0.51 ONLY ONE DATA POINT 1975 0.17 0.04 0.19 0.14 0.05 1974 0.32 ONI.Y ONE DATA POINT 1969 l
(PRE 0PERATIONAL) 0.12 0.17 0.24 0.01 0.24 103
\\
l I
HISTORICAL ENVIRONMENTAL SAMPLE DATA g
CONTROL Mollusks STANDARD Cs-137 pCi/g (wet)
MEAN DEVIATION MAXIMUM MINIMUM RANCE I
l 1981
<LLD 1980
<tto l
1979
<LLD g
1978
< Mot 1977
<MDL 1976 NO DATA 1975 NO DATA 1974 NO DATA 1969 (PRE-0PERATIONAL)
NO DATA l
INDICATOR r
u lgDA$
MAXIMUM MINIMUM RANGE lh Ci/g (wet)
MEAN 1981 0.061 ONLY ONE DATA POINT r
1980
<tto u
1979
<tto p
1978 0.99 0.80 2.10 0.24 1.86 l
1977
< Mot 1976 0.18 ONLY ONE DATA POINT l
1975
< Mot 1974 0.26 ONLY ONE DATA P0 INT I
1969 (PRE-0PERATIONAL) 0.08 ONLY Ot*
DATA POINT 104
I HISTORICAL ENVIRONMENTAL SAMPLE DATA I
CONTROL fr-9 t)
A MMIMM MINIM M RM p
I 1981 0.027 0.007 0.032 0.022 0.01 1980 0.12 ONLY ONE DATA POINT 1979 0.02 ONLY ONE DATA POINT I
1978 0.05 0.01 0.04 0.061 0.02 1977
<MDL 1976
<got I
1515
<got 1974
<MDL 1969 (PRE-0PERATION AL)
N0 DATA INDICATOR lgDA g
MAXIMUM MINIMUM RANGE MEAN r-9 p /
wet) 1981 0.011 0.007 0.02 0.005 0.015 1980 0.01 0.003 0.02 0.01 0.004 1979 0.02 0.20 0.05 0.01 0.04 1978 0.015 ONLY ONE DATA POINT 1977
<Mol l
1976 0.04 0.00 0.04 0.04 0.00 1975 0.29 0.27 0.65 0.03 0.62 1974
<got 1969 (PRE 0PERATIONAL) 0.08 ONLY ONE DATA POINT g
105
I I
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL DNIAT MAXIMUM MINIMUM RANCE
-13$ C /h dry)
MEAN 1981 0.26 0.23 0.42 0.10 0.32 1930 0.43 0.2 0.57 0.29 0.28 1979 0.47 0.10 0.54 0.40 0.14 1978 0.61 0.15 0.71 0.50 0.21 1977 0.68 0.08 0.73 0.62 0.11 1976
<MDL 1975 0.40 0.10 0.50 0.30 0.20 1974 0.11 ONLY ONE DATA POINT 1969 lg (PRE 0PERATIONAL)
N0 DATA I
INDICATOR
-13$ pcf h ry)
EN MEMM MM RM E ATI 1981 0.23 0.04 0.27 0.19 0.08 g
1980 0.34 0.40 0.94 0.12 0.82 1979 0.44 0.45 1.00 0.13 0.97 1978 0.99 0.80 2.10 0.24 1.86 1977 2.27 1.90 4.10 0.31 3.79 1976 2.45 0.64 2.90 2.00 0.90 1975 0.83 0.86 3.50 0.20 3.30 1974 0.40 0.26 0.58 0.21 0.37 I
1969 (PRE 0PERATIONAL) 0.38 0.09 0.44 0.31 0.13 106
l E
i HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL I
DNIAOk 6[^
MAXIMUM MINIMUM RANGE MEAN 89 pCi/g (wet) 1 I
i 1981 0.034 ONLY ONE DATA POINT 1980
<LLD l
1979
<LLD 1978
<uDL I
1977
<MDL l
1976 N0 DATA 1975 N0 DATA l
1974
<MDL 1969 (PRE 0PERATIONAL)
NO DATA I
INDICATOR GAMMARUS STANDARD MAXIMUM MINIMUM RANGE MEAN l
Sr-89 pCi/g (wet)
DEVIATION 1981 0.069 ONLY ONE DATA POINT 1980
<LLD 1979
~0.105 ONLY ONE DATA P0 INT 1978
<MDL I
1977
<MDL 1976 N0 DATA 1975 NO DATA 1974
<MDL I
1969 (PRE-0PERATIONAL)
NO DATA i
107
I I
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL I
STANDARD GAMMARUS MEAN DEVIAil0N MAXIMUM MINIMUM RANGE
$r-90 pCi/g (wet)
I 1981 0.099 0.066 0.146 0.052 0.0094 1980 0.102 ONLY ONE DATA P0 INT 1979 0.10 0.02 0.11 0.08 0.03 1978 0.14 0.01 0.14 0.13 0.01 l
1977 0.32 ONLY ONE DATA POINT 1976 NO DATA 1975 NO DATA l
1974
<MDL 1969 (PRE 0PERATIONAL)
NO DATA INDICATOR
$4 h DA MAXIMUM MINIMUM RANGE MEAN Sr 90 C1/g (wet) 1981 0.193 0.058 0.274 0.138 0.136 1980 0.64 0.86 1.64 0.14 1.5 1979 0.19 0.01 0.20 0.17 0.03 1978 0.14 0.04 0.21 0.13 0.08 1977 0.40 0.46 0.73 0.08 0.65 1976 NO DATA 1975 NO DATA 1974
<got j:
1969 (PRE 0PERATIONAL)
NO DATA j
108
I l
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL DNI T$$
MAXIMUM MINIMUM RANCE MEAN cs-1 pci/g (wet) 1981
<LLD 1980
<tto l
l 1979 0.05
'). 04 0.08 0.02 0.06 1978 O.028 ONLY ONE DATA POINT 1977
<MDL 1976 NO DATA 1975 NO DATA 1974 N0 DATA 1969 (PRE-0FERATIONAL)
NO DATA I
l IK31CATOR STANDARD MAXIMUM MINIMUM RANGE GAM!1ARUS MEAN cs-137 pci/g (wet)
DEVIATION 1981 4.7 4.67 8.0 1.4 6.6 1980
<tto
_ l 1979 0.06 0.02 0.07 0.04 0.03 1978 0.05 0.00 0.05 0.05 0.00 1977
<MDL 1976 NO DATA 1975 NO DATA 1514 0.21 ONLY ONE DATA P0 INT 1969 (PRE-0PERATIONAL)
N0 DATA 109
EL HISTORICAL ENVIRONMENTAL SAMPLE DATA E
CONTROL DbiA$
MAXIMUM MINIMUM RANGE MEAN S-9 g(wet)
[
1981 0.015 0.001 0.015 0.014 0.001 1980
<tto E
1979 0.07 0.0a 0.09 0.04 0.05 I
1978
<MDL 1977 o,04 0.01 0.05 0.03 0.02 1976 0.24 0.08 0.33 0.19 0.14 1975
<got l
1974
<MDL 1969 (PRE 0PERATIONAL)
NO DATA INDICATOR A
lNyTI MAXIMUM MINIMUM RANGE l
5 89 p g (wet)
MEAN 1981 0.061 0.021 0.10 0.027 0.073 1980
<tt0 1979
<LLD 1978 0.01 0.001 0.015 0.014 0.001 1977 0.07 0.05 0.24 0.03 0.21 1976 0.27 0.15 0.41 0.12 0.29 1975
<MDL 1974
<MDL 1969 (PRE-0PERATIONAL)
NO DATA 110
I HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL DNIA MAXIMUM MINIMUM RANGE s-90pb (wet)
MEAN 1981
<tto g
1980 0.005 0.002 0.007 0.002 0.005 1979 0.018 0.012 0.033 0.008 0.025 1978 0.010 0.004 0.015 0.004 O.010 1977 0.07 0.03 0.14 0.02 0.12 1976 0.25 0.27 0.81 0.05 0.76 1975 0.07 0.06 0.10 0.04 0.06 1974 0.07 0.02 0.09 0.04 0.05 1969 r
(PRE 0PERATIONAL)
NO DATA I
INDICATOR A
hhfATI MAXIMUM MINIMUM RANGE C$g(wet)
MEAN S
0
.0022 ONLY ONE DATA POINT 1981 0
1980 0.006 0.005 0.013 0.003 0.015 g
1979 0.019 0.01 0.04 0.01 0.03 1978 0.013 0.006 0.025 0.004 0.021 1977 0.07 0.05 0.24 0.03 0.21 l
g 1976 0.28 0.48 2.20 0.05 2.15 1975 0.08 0.03 0.13 0.02 0.11 1974 0.23 0.69 2.30 0.01 0.29 1969 (PRE 0PERATIONAL) 0.23 0.17 0.51 0.30 0.48 111 I
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD Fish Samples MEAN DEVIATION MAXIMUM MINIMUM RANGE cs-137 pci/g (wet)
I 1981 o,o43_
0.016 0.062 0.028 0.034 l
1980 0.059 0.032 0.110 0.029 0.081 i
1979 0.04 0.01 0.06 0.03 0.03 1978 0.09 0.05 0.20 0.04 0.16 l
1977 0.13 ONLY ONE DATA P0 INT 1976 0.12 ONLY ONE DATA POINT 1975
<MDL
l 1974 0.43 0.37 0.94 0.09 0.85 1969 (PRE 0PERATIONAL)
NO DATA INDICATOR 0A
$4 h MAXIMUM MINIMUM RANGE bg(wet)
MEAN f
C 3
1981 0.061 0.021 0.10 0.027 0.073 1980 0.332 0.935 0.300 0.030 3.270 1979 o,10 0,14 0.55 0.02 0.53 1978 0.08 0.02 0.10 0.03 0.07 1977 0.29 0.21 0.79 0.13 0.66 1976 1.4 1.67 3.90 0.50 3.40 1975 1.38 0.22 1.70 1.10 0.60 1974 0.57 0.82 4.40 0.08 4.32 lE 1969
!E (PRE 0PERATIONAL) 0.06 0.04 0.13 0.01 0.12 ll 112
I
~
HISTORICAL ENVIRONMENTAL SAMPLE DATA g
CONTROL
$NDh
%e Water Gross Beta MAXIMUM MINIMUM RANCE MEAN
)
1981 3.24 1.27 5.8 1.9 3.9 g
1980 2.60 0.50 3.48 1.87 1.61 1979 3.05 0.85 4.80 2.10 2.70 1978 3.55 1.58 6.10 0.50 5.60 1977 10.9 14.5 49.3 2.50 46.8 1976 42.48 50.62 189.00 4.90 184,10 1975 4]g,-
52.79 160.00 1.00 159.00 1974 1.85 0.07 4.90 4.80 0.10 1969 (PRE 0PERATIONAL) fie DATA I
INDICATOR
$ATI MAXIMUM MINIMUM RANGE Water Gross Beta MEAN 1981 2.98 1.19 5.4 1.2 4.2 1980 3.10 0.63 5.10 2.35 2.75 g
1979 3.24 1.06 6.30 2.00 4.30 1978 4.53 2.62 11.10 0.60 10.50 1977 15.80 21.00 87.00 1.00 86.00 1976 41.76 55.23 192.00 1.10 190.90 1975 18.24 17.08 80.00 0.60 79.40 1974 31.71 20.2?
60.00 6.30 53.70 1969 (PRE 0PERATIONAL) tio DATA l
113 I
I I
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL 1
r 89 pC /1 0 IAT MMWM WNWW RM I
1981
< tL O.
l 1980 1.4 0.07 1.4 1.3 0.1 1979 0.70 0.14 0.80 0.60 0.20 I
1978
<MDL l
1977
<MDL 1976
<MDL I
1975
<not l
1974 NO DATA 1969 (PRE 0PERATIONAL)
N0 DATA I
INDICATOR WWW WWM RM b$/1 l
ATI sr-89 1981 0.78 ONLY ONE DATA POINT 1980 0.70 ONLY ONE DATA POINT l
1979
<LLD 1978 0.70 0.10 0.80 0.60 0.20 I
1917
<MDL l
1976
<gDL 1975 0.30 ONLY ONE DATA POINT I
1974 NO DATA 1969 I
(PRE 0PERAil0NAL)
NO DATA l
114
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL
-I offlAT MAXIMUM MINIMUM RANGE MEAN Sr-90 pC /1 1981 0.68 0.176 t,.J68 0.484 0.384 l
1980 1,10 0.00 1.10 1.10 0.00 l
1979 0.80 0.26 1.10 0.60 0.50 I
1978
<MDL l
1977
< Mot 1976
< Mot 1975
<MDL 1974 TO DATA 1969 (PRE-0PERATION AL)
NO DATA I
INDICATOR
^
DfhATl MAXIMUM MINIMUM RANGE MEAN Sr 90 pC /1 1981 0.74 0.08 0.805 0.597 0.208 I
1980 1.00 0.20 1.20 0.80 0.40 l
1979 0.84 0.34 1.30 0.40 0.90 1978 0.80 0.30 1.10 0.40 0.70 l
1977 1.00 ONLY ONE DATA POINT 1976 sMot l
1975
< Mot 1974 NO DATA I
(PRE 0PERATIONAL)
N0 DATA m
1969 g
115
I HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL hhlAT 0 MAXIMUM MINIMUM RANGE hr MEAN i
ci/1 I
1981 293.3 49.3 357 211 2a6 l
1980 257.3 38.5 290.0 211.0 79.0 19IS 258.7 73.7 308.0 174.0 134.0 1978 303.8 127.5 490.0 215.0 275.0 l
1977 407.5 97.4 530.0 300.0 230.0 1976 651.7 251.0 929.0 440.0 489.0 I
1975 362.5 72.8 414.0 311.0 103.0 l
1974
<MDL 1969 (PRE 0PERATIONAL)
NO DATA I
INDICATOR A
l[ATl MAXIMUM MINIMUM RANCE l
MEAN Tr i Ci/l 1981 258.3 76.9 388 183 205 1980 263.0 95.4 457.0 150.0 307.0 l
1979 234.0 40.7 286.0 176.0 110.0 1978 389.4 119.9 560.0 253.0 307.0 1977 450.0 67.2 530.0 380.0 150.0 l
1976 513.0 250.3 889.0 297.0 592.0 1975 334.8 132.5 482.0 124.0 358.0 1974 440.0 84.9 500.0 380.0 120.0 I
(PRE-0PERATIONAL)
NO DATA 1969 116
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL hi $
MAXIMUM MINIMUM RANCE hm 3
MEAN os Beta 1981 0.165~
0.135 0.549 0.016 0.533 1980 0.056 0.04 0.291 0.009 0.282 1979 0.077 0.086 0.703 0.010 0.693 1978 0.14 0.13 0.66 0.01 0.65 g
1977 0.126 0.080 0.484 0.001 0.483 1976 0.051 0.031 0.240 0.004 0.236 1975 0.085 0.060 0.294 0.008 0.286 1974 0.121 0.104 0.808 0.001 0.807 g
1969 (PRE 0PERATIONAL) 0.334 0.097 0.540 0.130 0.410 I
INDICATOR STANDARD Air Particulate MEAN MAXIMUM MINIMUM RANGE 3
Gross Beta pCi/m DEVIATION l
1981 0.151 0.128 0.528 0.004 0.524 1980 0.045 0.03 0.207 0.002 0.205 l
1979 0.058 0.06 0.271 0.001 0.270 1978 0.10 0.09 0.34 0.01 0.33 1977 0.070 0.034 0.140 0.016 0.124 1976 0.047 0.032 0.191 0.002 0.189 1975 0.067 0.055 0.456 0.001 0.455 1974 0.111 0.114 0.855 0.003 0.854 1
1969 (PRE 0PERATIONAL) 0.320 0.090 0.520 0.130 0.390 117
l HISTORICAL ENVIRONMENTAL SAMPLE DATA C0!lTROL Environmental TLD's Quarterly STANDARD Reading mrem / Standard MEAN DEVIATION MAXIMUM MINIMUM RANGE Mnnth Off-Site 1981 4.72 0.685 6.63 3.24 3.39 1950 4.57 0.614 6.06 3.12 2.94 1979 REPORTED AS mrem /qtr PRIOR TO 1978 1980 1977 1916 1975 l
1974 1969 (PRE 0PERATIONAL)
INDICATOR Environmental TLC's Quarterly STANDARD MAXIMUM MINIMUM RANGE Reading mrem / Standard Month MEAN DEVIATION On Sito Mnnitnes*
1981 5.24 0.728 7.45 4.09 3.36
.g 1980 DATA NOT COMPARABLE DUE TO 1979 CHANGES IN TLD LOCATI0riS 1978 1977 1976 1975 1974 1969 (PRE 0PERATIONAL)
See clarification on Environmental Sample Statistical Analysis Table,Section III 118
HISTORICAL ENVIRONMENTAL SAMPLE DATA I
CCNTROL 5
MEAN DNIAOk MAXIMUM MINIMUM RANGE fr90p I
1981 4.85 1.91 8.00 2.41 5.59 l
1980 3.33 0.9 4.3 1.8 2.5 1979 4.44 1.33 5.80 1.70 4.10 I
1978 5.88 2.04 9.00 3.00 6.00 1977 N0 DATA 1976 NO DATA I
1975 NO DATA 1974 NO DATA l
1969 (PRE 0PERATIONAL)
NO DATA I
l INDICATOR STANDARD Milk samples MEAN MAXIMUM MINIMUM RANGE Sr-90 pCi/l DEVIATION 1981 4.60 2.45 10.70 1.12 9.58 1980 4.3 2.6 11.0 1.1 9.9 l
1979 4.84 2.12 9.00 0.70 8.30 1978 5.93 1.81 10.00 2.50 7.50 I
1977 6.07 3.50 15.00 2.00 13.00 l
1976 7.16 3.41 14.80 1.50 13.30 1975 6.31 3.11 13.80 2.30 11.50 I
1974 5.66 2.89 14.00 1.00 13.00 1969 (PRE-0PER ATION AL)
NO DATA 119
E I
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL DhlAT h MAXIMUM MINIMUM RANGE 137p[jj MEAN I
1981 7.0 ONLY ONE DATA POINT l
l 1980
<tto 1979 3.73 0.29 3.9 3.4 0.5 I
1978 5.83 1.98 7.8 2.4 5.4 l
1977 NO CONTROL DATA PRIOR TO 1978 1976 1975 l
1974 1969 (PRE 0PERATIONAL)
NO DATA I
INDICATOR N
MAXIMUM MINIMUM RANGE 37pbi)f DE ATI C
1981 7.57 5.95 29.0 4.3 24.7 1980 9.7 4.9 21.0 4.0 17.0 1979 9.4 8.0 40.0 2.7 37.3 1978 9.9 7.1
'3.0 3.4 29.6 1977 17.1 3.9 11 J 22.0 11.0 1976 7.8 3.7 13.2 4.0 9.2 1975 20.6 7.8 36.0 6.0 30.0 1974 26.1 10.5 61.0 13.0 48.0 1969 (PRE OPERATIONAL)
NO DATA 120
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL DhlAOk MAXIMUM MINIMUM RANCE 131p[fjS MEAN 1
1981
<tto 1980 1.41 ONLY ONE DATA POINT 1979
<tto 1978
<MDL 1977 NO DATA 1976 NO DATA 1975 NO DATA 1974 NO DATA 1969 (PRE 0PERATIONAL)
NO DATA l
INDICATOR l[hkTfy A
MAXIMUM MINIMUM RANGE 131pc/y5 MEAN 1981
<tLD 1980 4.9 4.23 8.80 0.40 8.40 1979
<tto l
1978 0.19 ONLY ONE DATA POINT 1977 0.20 0.14 0.22
-0.40 0.62 1976 3.20 7.81 45.00 0.02 44.98 1975 0.37 0.60 2.99 0.01 2.98 1974 1.23 0.44 2.00 0.70 1.30 1969 (PRE 0PERATIONAL)
NO DATA 121
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL IAh MAXIMUM MINIMUM f!ANCE MEAN D
137 p /
t) produce I
1981
<LLD l
1980
<tto 1979 NO CONTROL DATA PRIOR TO 1980 1978 l
1977 1976 1975 l
1974 1969 (PRE 0PERATIONAL)
INDICATOR STANDARD MAXIMUM MINIMUM RANGE Human Food Crops MEAN Cs-137 pCi/g (wet) produce DEVIATION 1981
<tto 1980 0.033 2.26 0.06 0.004 0.056 1979
<tto 1978 0.01 OND ONE DATA POINT 1977
< Mot 1976
< Mot 1975
<got 1974 0.142 0.09 0.34 0.04 0.30 I
(PRE 0PERATIONAL)
NO DATA 1969 l
122
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL I
N IAT MAXIMUM MINWUM RM Y3 pc /g ( t) produce 1981
<LLD 1980
<LLD 1979 NO CONTROL DATA PRIOR TO 1980 1978 g
1977 1976 1975 g
19M 1969 (PRE-0PERATIONAL) l INDICATOR DA hyg MAXIMUM MINIMUM RANCE
- 31 pc$/g ( et) produce I
MEAN 1981
<LLD 1980
<LLD l
1979
<tt0 l
1973
<got I
1977
<MDL 1976
<MDL 1975
<MDL 1974 NO DATA 1969 (PRE 0PERATIONAL)
NO DATA 123
h 5
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL IA hk MAXIMUM MINIMUM RANGE MEAN D
137 pCi/g (wet)
I 1981 0.021 0.005 0.024 0.017 0.007 l
1980 0.01 ONLY ONE DATA POINT 1979 NO CONTROL DATA PRIOR TO 1980
~
M78 l
1977 1976 1975 l
1974 1969 (PRE 0PERATIONAL)
INDICATOR Dbily MAXIMUM MINIMUM RANCE l
-137 pCi/g (wet)
MEAN 1981 0.036 0.021 0.068 0.023 0.045 1980 0.02 1.35 0.042 0.009 0.033 1979 2.97 2.13 0.07 0.01 0.06 1978 0.021 0.011 0.04 0.013 0.027 1977
<MDL 1976
<MDL 1975 0.10 0.00 0.10 0.10 0.00 1974 NO DATA I
1969 (PRE 0PERATIONAL)
NO DATA l
124
HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL h!!!37pCi/g(wet) lA
'WM NW E
1981
<LLD 1980
<LLD 1979 NO CONTROL DATA PRIOR TO 1980 1978 ll 1977 1976 I
1975 l
1974 1969 (PRE 0PERATIONAL)
INDICATOR ff$TI MAXIMUM MINIMUM RAN9E
!!37pCi/g(wet)
MEAN 1981
<LLD l
1980
<LLD 1979
<LLD 1978
<MDL l
1977
<MDL 1976
<MDL 1975
<MDL 1974 NO DATA 1969 (PRE-0PERATIONAL)
NO DATA Eg 125
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MEAN D IAT 0 MAXIMUM MINIMUM RANGE 13$$9(dry) 1981 NO SAMPLES REQUIRED IN 1981 l
1980 1.20 0.91 2.90 0.41 2.49 1979 NO SAMPLES REQUIRED IN 1979 1978 N0 SAMPLES REQUIRED IN 1978 l
1977 1.17 0.48 2.00 0.70 1.30 1976 NO DATA 1975 1.07 0.21 1.30 0.90 0.40
'l 1974 NO DATA 1969 (PRE 0PERATIONAL)
NO DATA INDICATOR Soil Samp%s gggy MAXIMUM MINIMUM RANGE STANDARD lE Cs-137 pCi/g (dry)
DEVIATION 3
l 1981 N0 SAMPLES REQUIRED IN 1981 1980 1.26 0.61 2.1 0.29 1.81 1979 NO SAMPLES REQUIRED IN 1979 1978 NO SAMPLES REQUIRED IN 1978 1977 1.03 0.62 2.00 0.30 1.70 1976 NO DATA 1975 NO DATA 1974 1.03 1.18 2.80 0.40 2.40 I
1969 (PRE-0PERATIONAL)
NO DATA l
126
I HISTOR.LAL ENVIRONMENTAL SAMPLE DATA l
CONTROL Ah MAXIMUM MINIMUM RANGE MEAN D
Sr 90 p g (dry) 1981 N0 SAMPLES REQUIRED IN 1981 1980 0.063 0.065 0.19 0.008 0.182 1979 NO SAMPLES REQUIRED IN 1979 1978 NO SAMPLES REQUIRED IN 1978 1977 0.21 0.07 0.29 0.13 0.16 1976 NO DATA 1975 0.13 0.10 0.26 0.04 0.22 1974 NO DATA 1969 (PRE 0PERATIONAL)
NO DATA I
INDICATOR AXI NIM M RA M Sr 90 pC (dry)
All 1981 NO SAMPLES REQUIRED IN 1981 i
l 1980 0.074 0.052 0.140 0.008 0.132 1979 NO SAMPLES REQUIRED IN 1979 1978 N0 SAMPLES REQUIRED IN 1978 1977 0.40 0.18 0.65 0.17 0.48 1976 NO DATA 1975 NO DATA l\\
l 1974 0.27 0.06 0.34 0.23 0.11 E
1969 (PRE 0PERATIONAL)
NO DATA 127
[
E E
l i
I VII I
I I
M
it i
I FIGURES AND MAPS I
I I
I I
I
i I
VII FIGURES AND MAPS 1.
DATA GRAPIIS This section includes graphic representation of selected sample results.
For graphic representation results less than the MDL or LLD were I
considered to be at the MDL or LLD level of activity. MDL and LLD values were indicated where possible.
2.
SAMPLE LOCATIONS Sample locations referenced as letters and numbers on analysis results tables are plotted on maps.
I
'I I
I I
I I
g m
l l
l Me cl 'y,,,,_
1 1-.~YIL.
a>
a
~
o.r nz uvingut.6 stariu=
g
(
N t_.
rw wcarui.
.._-.2 y
w
4_
,.-....--i.
l
,-/d-8 s-4'%
g
)
Y~
\\-
LAKE I
~ % X Q m!,7 --
(
'~=- -
ONTARIO
=-
~
. Is
~
E b
M
~
l
= = = _.. _..
7 W
~~
- = -
.; g,,
g, it s \\.
p
/
s.
i-wu staie-
- g a'
vg k
rM j g
n __o m,7p tw p a
e; :.;<. h % % p. \\ 2 : a, a W G y & Q Q. s
_@.;/(pQg!%3g g A,,.c +
3 pree id'MN 5S d N h
.s.
i
/ 'M
' Ds S
D r
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Comments 10 NMPW 100% bedrock NMPP 70% boulders, 20% rubble, 10% gravel Some algae on rocks FITZ 80% boulders, 10% gravel,10% sand Some algae NMPE 70% boulders, 20% gravel, 10% sand Some algae 20 NMPW 50% bedrock, 50% rubble NMPP 50% boulders, 30% rubble, 20% gravel All lying on bedrock FITZ 50% boulders, 20% gravel, 20% rubble, 10% sand NMPE 40% bedrock, 30% boulders, 25% gravel, 5% sand 30 NMPW 100% bedrock Some rubble NMPP 100% bedrock Some boulders FITZ 80% bedrock Some sand NMPE 100% bedrock Some rubble and sand 40 NMPW 50% bedrock, 20% rubble, 90% sand NMPP 80% boulders, 20% bedrock FITZ 50% bedrock, 20% boulders, 50% rubble NMPE 100% bedrock Some scattered sand 60 NMPW 100% bedrock NMPP 80% boulders, 10% rubble, 10% gravel FITZ 80% bedrock, 20% boulders Some rubble NMPE 80% bedrock, 20% rubble Some sand

Description based on USEPA (1973) field evaluation method for categorizing soils.
I I I 136
I I I FIGURE 9 I l PERIPHYTON SAMPLES
F Co-60
RY ENVIRONMENTRL LRB 10.0-
~ --*-- -CONTROL 9.0- - 9.0 z z 8.0 o o-8.0-m X& Y& 7.0 c W cW 7.0-20 2,, S.Ohf l h f S.0 5.0hk f 5.0-U U 4.0- - 4.0 3.0 3.0-i 2.0 l 2.0-l 1.0- - 1.0
----+----+--- '
- 0,.0 0.0- -1.0 -1.0 v u, ca N co en o l N N N N N N C3 cc I cn cn cn cn en cn cn en SRMPLE PERIOD (YERR) l CONTROL VALUES 1974 TO 1979 RRE MDL'= IS80 & 1981 RRE LLD's 137
I FIGURE 10 r I PERIPHYTON SAMPLES Cs-137 j JR7 ENVIRONMENTRL LRB i E --*-- =CONEOL =_10^ 02 10^ 02:- -+- =INDICRTOR m I RTMCSPHERIC NUCLERR 7 TEST 18/16/88 7 o o H H H $ 10^ 01=, =10^ 01 H u C C z z m-m- g g g N z* o z ] s s W.- W. s Mu / \\ Mu s c 's, -10^ 00 8 a. 10^ 005 u ,/ l \\ l \\ / 10^-01g i / 5 10^-01 i .. A. / c p- 's, / 'g 10^-02 10^-02 i i i v tn co N co en ca N N N .N N N C3 C3 cn cn c7 c7 c7 cn c7 cn SAMPLE PERIOD (YEAR) CONTROL VALUES 1975 & 1577 RRE MDL's 138
I FIG URE.11 I l PERIPHYTON SRMPLES Ce-144 1R7 I ENVIRONMENTAL LRB --*-- = CONTROL I -+- =INDICRTOR 2.0- - 2. O RTMOSPHERIC NUCLEAR _ }*g I {*g_ TEST 10/16/80 z z - 1.6 o o, 1.6-m gh -1.4h 1.4-w I w (" z 1.2- - 1,2 z (n w w 1.0hk E 1.0-O u u y 6.8- - 0.8 I / - 0.6 0.6-l \\ / - 0.4 O.4- / \\ ,/ I l \\ \\ f O.P- ,/ 'g ,/ - 0.2 I 0.0- - 0.0 -0.2 I -0.2 i i i i i i i v tn to N cc cn G N N N N N N C3 CD cn cn cn cn cn cn cn cn SRMPLE PERIOD (YEAR) I NO CONTROL DATR FOR 1974 & 1975 I CONTROL YEARS 1976 RRE MDL's 1980 RRE LLD's INDICATOR YEARS 1975,197S,1979 RRE MDL's 1980 ARE LLD's 139
FIGURE 12 MOLLUSK SRMPLES Co-60 JRF ENVIRONMENTRL LRB --*-- -CONTROL -+- = INDICATOR 2.0- - 2.0 1.8- - 1.8 z z o 1.6- - 1.6 o m m ~ 1- ~H h y 1.4-1.4hy - (" 1.2-
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I FIGUllE 13 l MOLLUSK SRMPLES Mn-54 l 1Rr ENVIRONMENTRL LRB --*-- -CONTROL l- = INDICATOR 3.3-3.0- - 3. 0 z 2 O O p - 2.7 p $ p p 2.7-E E 2.4- - 2.4 E- - (" 2.1- - 2.1 Z
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I FIGURE 14 MOLLUSK SRMPLES Sr-90 l JRF ENVIRONMENTRL LRB --*-- = CONTROL 1.0- -1.0 l
= -INDICRTOR 0.9-
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L FIGURE 15 P L_ BOTTOM SEDIMENT Co-60 JAF ENVIRONMENTRL I LAB --*-- = CONTROL l 2.50- - 2.50 --+-- = INDICATOR 2.25- - 2.25 I z z o-2.00- - 2.00 o m 1.75- - 1.75 -1.50h? l h3 1.50-l h S 1.25- -1.25h1 u u 1.00- - 1.00 l \\ - 0.75 0.75-7 - 0.50 0.50- / s l / 's 0.25- / \\ - 0.25 '"'*~~~~* 0.00-
-- -+-----*'
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I I FIGURE 16 I BOTTOM SEDIMENT Cs-137 l 3RF' ENVIRONMENTRt. LAB --*-- = CONTROL 2.50 l -+- -INDICATOR 2.50-2.25 2.25-l z-2 2.00 o o 2.00-m m hl 1.75 1.75-
1. 50 z
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I I l riaune 17 I l FISH SAMPLES V Cs-137 3RV I DNIRONMENTRL LRB --*-- = CONTROL I -INDICATOR 2.50- - 2.50 l 2.25- - 2.25 z z o 2.00- - 2.00 o m m l ct W - 1. 75 c[c s CH H 1.75-E EC Fm W IZ 1.50- - 1.50 z *
s s
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- O.00 0.00- -0.25 I -0.25 i e in e N m cn o N N N N N N m m cn cn en cn cn en cn m J l SRMPLE PERIOD i (YERR) l CONTROL YERR 1975 RRE MDL's 1981 RRE LLD'c i lI g m
I I FIGURE 18 I FISH SRMPLES I Sr-90 JRF ENVIRONMENTRL LRB --*-- = CONTROL -+- -INDICRTOR 0.50 l 0.50-0.45 0.45-z z 0.40 o o-0.40-m 0.35 I 0.35- $ (" O. 3 0-0.30'$ @ w-w- u u 0.25 g 1 g S 0.25-p U i\\ U E 0.20 E 0.20- / / 's 0.15 l 0.15- / i 0.10- / O.10 l 0.05 0.05-0.00 l 0.00- ' -0.05 -0.05 i i i i i v tn co N co cn G ~ N N N N N N CD Co cn cn cn c1 cn cn cn c7 SRMPLE PERIOD CYERR) I CONTROL YEAR 1991 RRE LLD's I 146 I
) r FIGURE 19 ru LRKE WRTER ROSS BETR RCTIVITY ~ ^ JRF ENVIRONMENTRL' F LRB l -~~-- -cONEOL 10^ 03- -10^ 03 =; =INDICRTOR 3 l z z O O IH H s r cc - cc - %N %N IH-10^ 02: =10^ 02 H - zo zu u c. u o_ u o z Iz f s u o o u ~ ~ l l N 10^ 01: / \\ =10^ 01 N I ,/ g ss, - w . 4, 4 10^ 00 10^ 00 i i i i v tn to N ca en co N N N N N N CD CD m en en en en en en en SRMPLE PERIOD l (YERR) I = l
FIGURE 20 I LRKE WRTER SRMPLES E GROSS BETR a JRF DNIRONMENTRL LRB -c- = CONTROL l -*- =JRF INLET -8.0 8.0- ..+.. -NMP +1 INLET 7.5- -7.5 l 7.0- -7. 0 5 s.5- -s.55 H s.0- -s.O s a c-c 5.5- , ' 's -5.5 m N mN H-H- s z o 5.0- 's -5. 0 z o w c_ w a. s -4. 5 y ~ y 4.5-g'. ' *. -4.08 l l 8 4.0- '. s, -3.5 3.5-s + s 3.B- 's -3. B g 2.5- 's -2.5 +.. ' ' + s + 2.0- 's, ,c. -2.0 3 1.5- 's -1.5 , ' + s 1.0- 'g' -1.0 l 0.5- -0.5 0.0 0.0 m m v tn to N c2 cn to m SRMPLE PERIOD l CMONTHS 1981) CONTROL MONTHS'5 & S ARE LLD's 148
I I l riouns 21 I l RIR PRRTICULRTE GROSS BETR ACTIVITY g JRF ENVIRONMENTRL g LRB l --*-- = CONTROL -+- -INDICATOR O.20- -0.20 l 0.18- -0.18 Z RTMOSPHERIO NUCLEAR Z ,f -0.16 3 ' TEST is7s a tsee 3 0.16-I sm i-- m l -0.14 e <e x x < 0.14- ,A l t-- % me Iw\\ s z-z- y* \\ s, j i j -0.12 d Q d Q 0.12- \\ Z Z s \\ l \\, / -0.10 8 8 0.10-s f 'y / \\ / l 0.08-N / \\ / -0.08 N, / "' s, 0.06-N/ N ' -0.06 l 's 0.04- -0.04 0.02- -0.02 i e.ee 0.e0 m m N m m e N N N N N N CD CD SRMPLE PERIOD (YERR) g I I ~
I I FIGURE 22 I RIR PARTICULRTE a GRdSS BETR ACTIVITY a JRF ENVIRONMENTAL LRB --*-- = CONTROL 0.80- -0.80 l --+- = INDICATOR 0.72- -0.72 g z z o 0.64- -0.64 o E wm +- m E E h 0.56- -0.56 E h ss HN z-z- -0.48 w u u o.0.48-R uu u c_ l 0.40- ' 1, l , -0.40 \\ ',*,'gl A,l k, 0.32- 's, -0.32 g 0.24- \\ -0.24 -0 16 0.16-73 y l l 0.08- + -0.08 0.00 0.00 , i i i, i,,,i,,,,i,,,,i,,ii,i - m m e tn e s e m o m m e tn e s e m o - m m e tn e

.-.-----mmmmmmm SRMPLE PERIOD CWEEKS 1981)

I I 150 m
I I l ricuas 23 iI 1l RIR PARTICULRTE GROSS BETR RCTIVITY I JRF I ENVIRONMENTRL LRB --*-- = CONTROL
-- -INDICATOR 0.80-
-0.80 'I 0.72- -0.72 z z .I o 0.64- -0.64 o Hm nm -0.56 E <e l E <s 0.56-Hs Hs z-z- u o 0.48- -0.48 w u o o_ I u c. z z 8 0.40- -0.40 8 -0.32 0.32-li, 'l 0.24-i, / -0.24 i \\ 'y } \\ -0.16 O.16-g 0.08- ['N --0.08 'l 4 A 0.00 0.00 i,,i,,,,,i,,,,,,,,,,,i N e cn co - m m e tn e s e cn o - m m e tn e N e cn co - m NNNmmmmmmmmmmvvvvvvvvvv000 SRMPLE PERIOD (WEEKS 1981) g I g m
\\ Il FIGURE 24 I RIR PRRTICULRTE COMPOSITE ll Co-60 JW DWIRONMENTRL LRB --*-- = CONTROL l -INDICRTOR 1.0- -1.0 0.9- -0.9 l m m / z z { 0.8- / \\ -0.8 o L o N / i [N [ U 0.7-i -0.7 E U E' / \\ s 1 sz / Z -0.6 w 7 w T 0.6- \\ My l \\
lsN, Ms
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- -*- -4 V
i r -0.4 i / 0.3-i / -0.3 l \\ / 0.2- ---4 -0.2 I l 0.1- -0.1 I 0.0 0.0 i i N M v 10 CD r% CD CD G N SRMPLE PERIOD (MONTHS 1981) g CONTROL MONTHS 2,6 9,12 RRE LLD's 3 INDICRTOR MONTH 1 RRE LLD's I
I lI ll riocas 2s
.I I RIR PARTICULRTE COMPOSITE Cs-137 I JRF ENVIRONMENTAL LAB I --*-- "C""' 5 0- -5.0 -+- -INDICATOR 4.5- -4.5 m l-m z o <g 4.0- - 4. O o <e [N s i g Q3.5- /\\ -3.5 s { z z -3.0 w 7 l w " 3.0-EW b E* ,4'g -2. 5 8 _- 8 2.5-l r 2.0- 'g -2.0 I 1.5-l -1.5 / \\, o ,7- \\, -1.0 g 1.0- -0.5 0.5- 'W 0.0 0.0 i i i i i i i i i i i g m m m v m e N e m SRMPLE PERIOD l CMONTHS 1981) I I =
I I FIGUltE 26 I' RIR PRRTICULRTE COMPOSITE I Mn-54 JRF .ENVIRONMENTRL LRs --*-- -CONTROL l -INDICRTOR 5.0- -5.0 4.5- -4.5 l m zM z o h 4.0- -4. 0 o { g [N 5 [ U 3.5- -3. 5 @ U \\ E H H C-E C-z z 3 w 7 3.0- -3. 0 w 7 l u ; 2.5- -2. 5 u ; 2.0- ,4 -2.0 l l \\, l 1.5- / \\ -1.5 E \\ E k 1.0-s -1.0 I s O*5-N -0*5 l % +N, I 0.0 0.0 i i i i i i i i i i i N M v in CD f% CD CD G N SRMPLE PERIOD (MONTHS 1981) I CONTROL MONTHS 1,2,9,10,11,12 RRE LLD's INDICATOR MONTHS S, 10,11,12 RRE LLD's I 154
E l riouits 27 I l RIR PRRTICULRTE COMPOSITE Ru-106 I JRF envi a newra. LRB l --*-- = CONTROL --+- -INDICATOR 30- -30 27- -27 I Z 7 24- -24 Z 7 s 3E j ', 3E $h21- / \\, -21$h IEa ,/ Ez z 18- -18 z m m y s y 5 lE 15- -15 z i O O o U / 's U* 12- ,/ k- -12 g 9- / -9 l / M B-l l \\ -6 / \\
~~ 4
/ \\ -3 9'N'~4 3-M 0- -0 -3 -3 i i i i i i i i i i N M v in CD r% CD CD G N SAMPLE PERIOD (MONTHS 1981) CONTROL MONTHS 1,9,10,12 RRE LLD's INDICRTOR MONTHS 10,11,12 PRE LLD's 155
I I FIGURE 28 I RIR PRRTICULRTE COMPOSITE a Co-60 E 1RF DNIRONMENTRL LRB -*-- = CONTROL 2.0- -2.0 I = INDICATOR 1.8- -1.8 g z* z *{ 1.6-o t-* -1.6 o ! E N l \\ [\\ E [ U 1.4-E \\ -1.4 E U a H 'm H l 'a e z 3 z
1.2-l
\\ -1. 2 w
w l
1.0- 'g -1.0 l s/ 0.8-l 's, _ / -0.8 l / \\ 0.6- ,/ 's, ps -0.6 E i / A / N E 0.4-i, 4 'V -0.4 \\, / 0.2- -4 -0.2 0.0 0.0 i,,i,,,,iiii,iii,iiii - N m v in to N Co Cn c3 - N - N m v LD CD N Co Cn CD - N 1980 SRMPLE PERIOD 1881 (MONTHS) CONTROL MONTHS 1980 1 TO 12 1981 2,S,S,12 RRE LLD's INDICATOR MONTHS 1980 1,3,5,7,8,la,11,12 1981 1 RRE LLD's I 156
[ [ FIGURE 29 r L [ RIR PRRTICULRTE COMPOSITE [ Cs-137 JRF ENVIRONMENTRL LAB --*-- -CONTROL =INDICRTOR 5.0 5.0- { 4.5 4.5-z 7 4.0-4.0 2 7 I3E 3E 3.5$h $ h 3.5-e Ie C. C., g g M RTMCSPHERIC NUCLEAR M I l TEST 10/16/80 y IUz d 2.5-M 2.5 z d o i r o oJ \\ u; 2.0 2.0-I \\, 1.5-i, 1.5 i I 1.0 i 1.0- ,*s ,F n, , n- *' x s ' *'s,.,* d'7 - 0.5 l 0.5-0.0 0.0-I Q - N m v in m N cc cn G - N - N m v tn c.o N cc cn G - N I 1980 SRMPLE PERIOD 1981 (MONTHS) l CONTROL MONTHS 1980 1,2,3,4,6,8,9,10,11,12 RRE MDL's INDICATOR MONTHS 1980 1,3,4,8,S,10,11,12 RRE MDL's I 157
I I FIGURE 30 1 I RIR PARTICULRTE COMPOSITE Mn-54 l JRF ENVIRONMENTRL LRB --*-- -CONTROL = INDICATOR g 3.0- -3.0 2.7- -2.7 m m z z -2. 4 o h o h 2.4-IN [ U 2.1-N -2.1 E U E s ei s c-c- Z RTMOSPHERIC NUCLEAR Ii g g TEST 18'18'88 ! 'i -1.8 w 7 5 u 7 1.8-Mw ,I 'i Mw 1.5- - 1. 5 8.cD l 8_a c i l 4 i -1.2 m 1.2-i I 0.9- \\ -0.9 l A n \\'\\ 0.6- ,/ g/ q g -0.6 s x E ~ l 0.3-s' k N -0.3 5 W-0.0 0.0 l ,,,,,,,,,,,,,,,,,,,,,i - N m v tn tD N c3 ci cD - N - N m v LD CD N C3 CD CD - N 1980 SAMPLE PERIOD 1981 l l (MONTHS) CONTROL MONTHS 1980 1 TO 12 1981 1,2,S,10,11,12 RRE LLD's INDICATOR MONTHS 1980 1 TO 5 & 7 TO 12 1981 S TO 12 RRE LLD's I 158 I
.I I FIGURE 31 I RIR PRRT.ICOLRTE COMPOSITE Zr-95 l JRF g ENVIRONMENTAL LRB I --*-- -CONTROL 70- -70 -+- = INDICATOR 63- -63 56-p, -56${ l5 ,Y 49-i -49 $ s l $s I W % l 5 1 z 42-I dm g RTnosescarc.Nuctcan -35 g [cp y TEST ta/1sesa l 1 i y g d 35-l UJ U_ i 28- -28 g 21- -21 l 's 14- -14 l 7- -7 ' - " - ~ ~ ' - 0- -O g iaAeaaAeasyAlaAeaaAeasyA 1980 SAMPLE PERIOD 1981 l CMONTHS) CONTROL MONTHS 1980 1 TO 10 RRE MDL's 1991 9,li,12 RRE LLD's INDICATOR MONTHS 1980 1 TO 10 PRE MDL's 1991 11,12 RRE LLD's
I I FIGURE 32 I AIR PARTICULATE COMPOSITE Nb-95 l JRF ENVIRONMENTRL LRB --*-- -CONTROL 150- -150 l -+- = INDICATOR 140- -140 l 130- -130 5{120-l\\ -120${l [N 110- -110 [.N -100,M,l x.- g i 100-l g 90 $ m 3m 90-sTMosesEarc Nuctraa l I 8000 M O 80- )l 8 _ 70-70 l 60- / SO l 50 50-40 40-30 30-20 20-10- - 10 0-0 " " " ^ - i ii,ii. i,iiiii,iii,,i - m m v tn e N cc cn co - m - m m v tn e N co m co - m i 1980 SRMPLE PERIOD 1981 (MONTHS) CONTROL MONTHS 1980 1 TO la RRE MDL's INDTCATOR.10NTHS 1980 1 TO 10 RRE MDL's I 160
I I g ricuas 33 I ll RIR PRRTICULRTE COMPOSITE Ce-144 JRF iI ENVIRONMENTAL LRB --*-- = CONTROL I -+- -INDICATOR 70- -70 l 63- -63 z 7 56- -M~s W, n- % ' ' ~ ~ * ' ' ^* 0- -B I i i a i i i i i i i a i i i i 6 i i i i a i i i - N M v LD CD N CD 07 (D - N - N M v LD W N C3 CD CD - N 1980 SRMPLE PERIOD 1981 (MONTHS) CONTROL MONTHS 1980 1 TO 11 RRE MDL's INDICATOR MONTHS 1980 1 TO 11 RRE MDL's I Io
I I FIGURE 34 m I I RIR PRRTICULRTE COMPOSITE I Ce-141 JsF ENVIRONMENTRL g LRB E --*-- = CONTROL 20- -20 l ---+-- = INDICATOR 18- -18 16- ,l'i, -16${ >=4 ii >-4 $h14- ,I I, -14$h -12z%ol sTMosescarc nuctcsa ,A i $ c. z 12-Tcsr te is se y i w7 w7 i E d 10- ,f -10 E d o o U U 8-l -8 6- ,T -8 li l l 4-s' \\ -4 ', 's' ,P, l 2- -2 j
w...
'Y B- -0 - i i i i iiiiii.iiiiiiiiiiiii ca - m m v tn e N e cn co - m - m m v tn e N m m ca - m -~ E 1980 SRMPLE PERIOD 1981 5 (MONTHS) CONTROL MONTHS 1980 1 TO 10 RRE MDL's 1981 8 TO 12 RRE LLD's INDICATOR MONTHS 1980 1 TO 10 RRE MDL's 1981 9 TO 12 RRE LLD's I 162
L c-L f~ g nouns as l I l RIR PARTICULRTE COMPOSITE Ru-103 1RV l ENVIRCNMENTAL LRB --*-- = CONTROL I --+--- -INDICATOR 30- -30 27- ,5 -27 l l @ S 4- / ',I -4sS -21gh l h 21- / y a 4 z y RTMCSPHERIC NUCLEAR / M M i y I l TEST 10/16/80 )4 O lUg d 15- ,/ -15 g d i U* U _* 12-l -12 I 9- / -9 6- -6 I 3- -3 Y -.-.4- -0 0-i i i i ,iiii iiiiiiiiiii ii ~ N m v tn La N co 03 Q ~ N ~ N m v tn to N co cn G ~ N 1980 SRMPLE PERIOD 1981 (MONTHS) CONTROL MONTHS 1980 1 TO 10 RRE MDL' 1981 9 TO 12 RRE LLD's INDICATOR MONTHS 1980 1 TO 10 RRE MDL's 1981 10,11,12 RRE LLD's 163
I I FIGURE 36 I MILK SRMPLES Cs-137 I JRF' ENVIRONMENTRL LRB --*-- = CONTROL -INDICATOR l 30.0- -30.0 27.0- -27.0 I z z 3 24.0- -24. O S RTMosesERze NuctERR TEST 1976 & 1988 mN 21.0- -21.0 m N r.- i-- - l zu zo y o-18. 0- -18.0dAl z z 8 15.0- -15.0 8 12.0- -12.0 9.0- - 9. 0 x - 6.0 6.0-N 3.0- - 3. 0 g 0.0 0.0 i i i i i w m w N D m O ~ N N N N N N CD CD c1 c) cn cn cn cn cn cn SRMPLE PERIOD I (YERR) NO CONTROL DATR FOR 1974 THROUGH 1977 CONTROL YERR 1980 ARE LLD's 164 I
EL [ om FIGURE 37 L MILK ~SRMPLES Cs-137 I
Br ENVIRONMENTRL LRB

*---CCNTROL +40

+ =INDICRTCR +15 I ......+.-.. -I ND I CRT OR + 4 0 -INDICRTCR +14 _{g 10-5 -. - s-.-INDICRTCR 412 / \\ =INDICRTCR +7 I -Q S, / \\. i X. t. s5 I z o e- \\ w / \\. H H C- \\ C-I / %\\ 7_ p l ZN a H-zu / /\\.s H-s ?- S-~ N \\ \\ Zu 6 u c-j *.. ', w c. 6" o l u / N \\. Z s' w z b . n. K. ). #+ *~.~ W~ O u 3' ' ~ ~ * ' -5u o +' g.,. -s.. '.~ l Y - -- g 4 4- +' I 3-2- 1-- O O x 4 4 4 4 4 i SRMPLE PERIOD CMONTHS 1981) CCNTRCL +42 MCNTHS 5,6,7,5,12,11,12 RRE L'U'8 ,,,,,,,,,,0
NDICRTCR 41S MCNTHS 12,12
+4 MONTHS 5.S,10,11,12 INDICRTCR $14 MCNTHS 5,S,S,la,11 +12 MCNTHS S,S,10,11ela ~ ^ ',, " INDICRTCR +7 MCNTHS 12,11,12 m:- - U,8 SRMFLING SEGRN.37 THE +7 FPRM CN 12/5/S1 165
l I I' FIGURE 38 I MILK SRMPLES g I-131 l 1RF --*-- = CONTROL ENVIRONMCNTRL LRB =INDICRTOR l 5.0- -5.0 4.5- -4.5 g z u z -4.03 3 4.0- $l 3.5-RTnesescRze NuctcRR TEST 187s. tasa -3. 5 m s zs r s-zu a zo b C-3. 0- -3. 0 0 ' E z z -2.58 g 8 2.5-2.0- -2.0 I - 1. 5' 1.5- ,\\ N -1.0 5
1. 0-t
\\ \\ g -0.5 0.5-N, [ 0.0 3.0 i i i l v tn f.c N cn c3 G N N N N N N CD CD g cn cn Cn c7 c1 c7 cn cn SRMPLE PERIOD l (YERR) NO CONTRCL DATR FOR 1974,1975,1976,1977 CONTROL YERRS 1979,1979 RRE MDL's 1981 RRE LLD's INDICATOR YERRS 1979 RRE MDL's 1981 RRE LLD's I 166
E E FIGURE 39 I I MILK SRMPLES Sr-90 JRF I DNIRONMENTAL LRB -*-- -CONTROL I -+- = INDICATOR 10- -10 l g- -9 Z 2 I S 8- -83 &c-C- zs 7- -7%NW~ I p,. ZU 2U w c. g-6 d C-M 's Z l 8 s- 's 58 ,s' 4~ I RTMCSPHERIC NUCLEAR 's, TEST 1976 8. 1980 'n' 3- - 3 2- - 2 l 1- - 1 O O I v n m N m m e N N N N N N O m m o m m m m m o I SRMPLE PERIOD CYERR) NO CONTRCL DATR FOR 1974,1975,1976,1S77 167 1 l}}

ML20050B364

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ML20050B364

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