ML17053D909

Annual Environ Operating Rept,1982

ML17053D909
Person / Time
Site:	Nine Mile Point
Issue date:	06/23/1983
From:	NIAGARA MOHAWK POWER CORP.
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ML17053D910	List: ML17053D909 ML18038A590
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NUDOCS 8307190249
Download: ML17053D909 (130)

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V N~aeAua 0 MOHAVN NINE MILE POINT NUCLEAR STATION/P.O. 8OX 32 LYCOMING. NEW YORK 13093/TELEPHONE (31S) 343-2110 June 23, 1983 Dr. Thomas E. Murley Regional Administrator United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA.

19406 RE:

Nine Mile Po nt Nuclear Station Unit /Pl Facility Operating License DPR-63 Docket No. 50<<220

Dear Dr. Murley:

~ In accordance with the Environmental Technical Specifications for the Nine Mile Point N:nuclear Station Unit III1, the 1982 Annual Environmental 0 erati ence dated April 25, 1983.

Attache which reflects corrections for typo rap zeal errors xn t e xnterpretatxve section of the report and on Table 7.

If any further clarification is needed, please feel free to contact Hugh Flanagan at Nine Mile Point at (315) 349-2428.

Very truly yours, Ak-a

~

Thomas J.

erkins General Superintendent Nuclear Generation mtm Attachment 8307190249 830623 PDR ADQCN 05000220 PDR

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T NIAGARA u MOHAWK NINE MILE POINT NUCLEAR STATION/PO BOX 3sI <YCOMINU, NEW YORK 13093/TFLEPHONF.

1315) 343 711()

I April 25, 1983 Mr. James Allan Acting Regional Administrator United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, Pa.

19406 RE:

Nine Mile Point Nuclear Station Unit 01 Facility Operating License DPR-63 Docket No. 50-220

Dear Mr. Allan:

In accordance with the Environmental Technical Specifications for Nine Mile Point Unit Pl, we are enclosing the Annual Environmental

~0 cretin

~Re ort for the period January 1,

1982 through December 31, 1982.

The non-radiological Aquatic Ecology Studies Data Report for 1982 was submitted under. separate cover.

Very truly yours, Thomas E.

Lempges Vice President-Nuclear Generation Encl.

2 copies xc:

Director, Office of NRR (17 copies)

h I

h4 I

,)

NIAGARA MOHAWK POWER CORPORATION ANNUAL ENVIRONMENTAL OPERATING REPORT PART B RADIOLOGICAL REPORT January 1, 1982 - December 31, 1982 for NINE MILE POINT NUCLEAR STATION UNIT 81 I

Facility Operating License DPR-63 Docket Number 50-220

I J

Ja II

TABLE OF CONTENTS List of Tables List of Figures I'ntroduction

'~Pa e

IIi Description 1)

Sample Methodology 2)

Analysis Per'formed 3)

Changes to the 1982 Sample Program 4)

Exceptions to the 1981 Sample Program III'valuation of Environmental Data A)

Aquatic Program 1)

Cladophora 2)

Dam Shoreline Sediment

3) 'ish 4)

Lake Water B)

Terrestrial Program 1)

Air Particulates Gross Beta 2)

Monthly Air Particulate Composites 3)

Airborne Radioiodine (I-131) 15 21 27 27 28 4)'TLD (Environmental Dosimetry) 5)

Radiation Monitors 6)

Milk 7)

Milch Animal Census 8)

Human Food Products 9)

Special Studies 36 38 38 44 49

TABLE OF CONTENTS (Continued)

C)

Conclusion 50 D)

References E)

Sample Summaries 51 53

LIST OF TABLES Table No.

Table 1

Table,2 Content Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Aquatic Program Sample Collection and Analysis, Site'adiological Environmental Monitoring Program Terrestrial Program

~Pa e

76 Table 3'oncentx'ations of Gamma Emitters in Cladophora Samples 77 Table 4 Table 5A Concentrations of Sr-90 and Gamma Emitters in Shoreline Sediment Samples Concentrations of Strontium 89 and 90 and

'amma Emitters in Fish Samples (pCi/guet) 79 80 Table 5B Concentrations of Strontium 89 and 90 and Gamma Emitters in Fish Samples (pCi/kg-dry) 81 Table 6

Concentrations of Beta Emitters in Lake Water, Samples 83 Table 7

Table 8

Concentx'ations of Tritium and Strontium 89 and 90 in Lake Water (Quarterly Composite Samples)

Concentrations of Gamma Emitters in Lake Water Samples 84 85 Table 9

Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity Table 10 Table 11 Environmental Airborne-Particulate Samples-On-Site Stations, Gross Beta Activity Concentrations of Gamma Emitters in Monthly Composites of NMP Air Particulate Samp3.es 88 Table 12 Environmental Charcoal Cartridge Samples-Off-Site Stations, I-131 Activity 93 Table 13 Environmental Charcoal Cartridge Samples-On-Site Stations, I-131 Activity 94 Table 14 Direct Radiation Measurements Quarterly Results 95 Table 15 Continuous Radiation Monitors (GM) 97

LIST OF TABLES Continued Table No.

Content Page Table 16 Table 17 Table 18 Table 19 Table 20 Concentrations of Iodine-131 in Milk Concentration of Gamma Emitters in Milk (Monthly Samples)

Concentrations of Stxontium 90 in Milk (Monthly Samples)

Milch Animal Census Concentrations of Gamma Emitters in Various Food Px'oducts 101 102 104 105 107 Table 21 Concentrations of Gamma Emitters in Pasture Grass 109 Table 22 Canal Water Data Monthly Composite Samples 110

LIST OF'IGURES Ft ure No.

Figure 1 Conteat Off-Site Environmental Station and TLD Locations Page Figure 1-A Figure 2 Figure 3 Off-Site Environmental Station and TLD Locations (Southern)

Off-Site Monitoring Station Locations On-Site Environmental Station and TLD Locations'12114 Figure 4 Food Crops, Meat, Poultry, and Egg Collections Figure 5 Milch Animal Census and Milk Sample Location Locations 116 Figure 6

New York State Map with Regions 117

I

/

NINE MILE POINT UNIT 1 ANNUAL ENVIRONMENTAL OPERATING REPORT I~

INTRODUCTION This, report is submitted in accordance with Appendix B

to DPR-63, Docket No. 50-220

'lo

'ESCRIPTION The required sample collection and analysis schedule for RiP 81 is listed in Table 1 and 2.

The sample collections for the radiological program are performed by two groups.

Ecological Analysts Incorporated (EAI) performs much of the environmental

sampling, EAI is presently performing the Nine Mile Point Aquatic Ecology Study at the site.

The staff required by EAI to perform this study is used to perform the terrestrial sampling required for the site Radiological Environmental Monitoring Program (REiP) ~

In-plant and remaining terrestrial sampling is performed jointly by the NMPNS and JAFNPP staffs.

1.

Sam le Collection Methodolog Ao Lake Water The two indicator stations are the respective inlet canals at NMPNS and JAFNPP.'These samples are composited using sampling equipment which discharge into large collection tanks.

These tanks are emptied weekly and an aliquot is saved for the monthly composite.

The control station sample i's collected from the City of Oswego water intake.

Grab samples are drawn from the intake prior to treatment and are composited in a large sample container.

Bo Quarterly composite samples are made up from aliquots of monthly samples.

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

The on-site locations ring the area around the plant inside the site boundary.

The on-site sampling network is composed of nine stations.

The off-site air monitoring locations range six to seventeen miles from the site and are composed of six stations Air monitoring locations are shown on Figures 1 and 3.

-1 April 1983

II'ESCRIPTION'(Continued) 1.

Sam le Collection Methodolog (Continued)

B.

Air Particulate/Iodine (Continued)

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 is a

2 x 1 '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 (two off-site, two on-site) after being counted for gross beta activity CD Milk 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 and butterfat.

Three gallons are collected during the first half of each month from i ach of the locations within ten miles of the site and from a

control location.

The samples are frozen and shipped to the analytical contractor within thirty-six hours of collection in insulated shipping containers.

The milk sampling locations are found on Figure 5i" (see Table 19 for identification of locations sampled

)

D.

Meat, Poultry and Eggs Semi-annually one kilogram of meat is collected from locations within a ten mile radius of the site.

Weekly phone calls are made to the local butcher to determine availability of slaughtered live stock from within the sampling area.

Whenever

possible, meat samples are collected from locations previously used.

(See Figure 4.)

Semi-annually one kilogram of poultry and one kilogram of eggs are

'ollected from each of three locations within a ten mile radius of the site Attempts are made to collect poultry arid eggs at the same time as the meat samples.

The samples for pou1try and eggs are frozen and shipped in insulated containers Whenever possible, samples are obtained from previously sampled farms.

Control samples are also obtained for

meat, eggs, and.

poultry.

(See Figure 4.)

-2 April 1983

II'ESCRIPTION (Continued) 1 ~

Sam le Collection Methodology (Continued)

E.

Human Food Crops Human food crops are collected during the late summer harvest season at locations previously sampled, if available One kilogram

each, of two types of fruits and/or vegetables from each of the three locations within a

ten mile radius of the site are collected.

The types of fruits and vegetables sampled depends upon what is locally available at the time of collection.

Attempts ar' made to collect at least one broadleaf type vegetable from each location.

The fruits and vegetables are chilled prior to s'hipping and shipped fresh in insulated containers'ontrol samples are also obtained.

(See Figure 4.)

F.

Soil Samples Soil samples were not collected in 1982

'oil samples are required to be collected every three years at the air monitoring locations and are analyzed for Sr-90 and GSA.

Samples were 'collected in 1980.

G.

Fish Samp1es Available fish species are removed from the Nine Mile Point Aquatic Ecology'tudy monitoring collections during the spring and fall collection periodsi Samples are collected from two of four possible on-site sample transects and one off-site sample transect (See Figure 1) ~

Available species are selected under the following guidelines:

li 0' to 1 kilogram of edible portion only of a maximum of three species per location 2

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

A maximum of three samples per species per location are'sedi Only edible portions are sent for analysis'elected fish samples are frozen immediately after collection and processing and are segregated by species and location.

Samples are shipped frozen within two weeks in insulated containers.

H Shoreline Sediments One kilogram of shore1ine sediment sample is collected at one on-site location and one off-site location.

Sediment samples are collected from shoreline locations that are frequently washed by the surf.

Samples are collected semi-annually, placed in plastic

bags, sealed and shipped for analysis in insulated containers

-3 April 1983

Il.

DESCRIPTION (Continued) 1.

Sam le Collection Methodolo (Continued)

I. Cladophora Cladophora samples are collected in the spring and summer season from two on-site locations and one off-site location.

scraped from the substrates

.into sample containers,

labeled, frozen and shipped in insulated containers for off-site analysis.

J.

TLD (direct radiation)

Thermoluminescent dosimeters (TLD's) 'are used to measure direct radiation in the JAP/NMP-1 environment.

TLD's are placed in locations using four types of selection criteria.

TLD's are classified as either nn-site, off-site, special interest or control locations.

On-site TLD's are located within the site property boundary and are arranged in a

ring around the generating facilities (Figure 3).

Off-site TLD's are located outside of the site property boundary and are arranged in a ring approximately 7-il miles out from the site.

Special interest TLD's are located at high population locations such as industrial

sites, schools, etc.

Control TLD's are located outside of the 10 mile radius of the site.

These TLD's are positioned to the east,

west, and south of the site up to 20 miles away.

E IP 4

Each TLD is made up of two CaS04 dosimeters sealed in' polyethylene package to insure dosimeter integrity against the weather.

The TLD packages are further protected by placement in plexiglass "birdhouses" or by tape sealing to supporting surfaces.

The dosimeters are collected, replaced and evaluated on a quarterly basis.

K. Special Samples Special radiological environmental samples were also analyzed.

An additonal sample media was collected during the 1982 sample period.'to: help in evaluating and interpreting the milk data which was compiled in 1982.

Additional samples of pasture grass were collected at all of the milk sampling locations, during July, August and September of 1982.

2.

Anal sis Performed The Radiological Environmental Monitoring Program (REHP) samples are analyzed by Radiation Management Corporation and by the Site Environmental Laboratory during 1982.

The following samples were analyzed by the site:

Air particulate filter (weekly gross beta analysis)

-4. April 1983

II.

DESCRIPTION (Continued) 2.

Analysis Performed (cont.)

Air particulate filter (monthly gamma spectral analysis)

"1 Airborne radioiodine cartridge (weekly gamma spectral analysis)

Lake water (monthly gamma spectral analysis)

Pasture grass (extra samples collected in July, August and September)

The remainder of the sample analyses, as outlined in Table 1 and 2, were analyzed by Radiation Management Corporation..

3.

Changes to the 1982 Sample Program A. Milk sample location number 45 was added to the milk sampling program in July of 1982.

The new sample location was added as a

result of the 1982 spring milch animal census which identified this farm as being in a critical downwind sector.

The new sampling location is located in a SE direction (125 degrees) at a

distance of approximately 8.1 miles from the site.

The addition of milk sample location number 45 brings the total number of milk sample locations to seven for the 1982 sampling program.

4.

Exceptions to the 1982 Sample Program A. Environmental radiation monitoring station I on"site was inoperable March 16, 1982 (2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />) to March 19, 1982 (1115 hour@).

Malfunction of the monitor was a

result of an electronic failure.

B. Environmental air monitoring station Dl off-site was inoperable March 23, 1982 to April 4, 1982.

Malfunction of the air monitoring station was due to a

break in the main incoming electrical line.

C. Environmental air monitoring station P'n-site was inoperable from "April 26>

1982 (2230 hours0.0258 days <br />0.619 hours <br />0.00369 weeks <br />8.48515e-4 months <br />) to April 30, 1982 (1300 hours0.015 days <br />0.361 hours <br />0.00215 weeks <br />4.9465e-4 months <br />).

Malfunction of the air monitoring station was a result of a defective vacuum pump.

D. Environmental air monitor station E off-site was inoperable from May 6,

1982 (2106 hours0.0244 days <br />0.585 hours <br />0.00348 weeks <br />8.01333e-4 months <br />) to May 10, 1982 (0840 hours0.00972 days <br />0.233 hours <br />0.00139 weeks <br />3.1962e-4 months <br />).

Malfunction of the air monitoring station was a result of a

defective vacuum pump fuse.

E. Environmental radiation. monitor G on-site was inoperable from June 14, 1982 (1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />) to June 15 1982 (1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />).

Malfunction of the monitor was a result of an electronic failure.

-5. April 1983

II.,

DESCRIPTION (Continued) 4.

Exce tions to the 1982 Sam le Pro ram (cont.)

Environmental air monitor station H on-site was inoperable from July 9, 1982 (estimate) to July 14, 1982.

Malfunction of the air monitoring station was a result of a defective vacuum pump.

G.

Environmental radiation monitor C off-site was inoperable from October 1, 1982 (1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br />) to October 7, 1982 (0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />).

Malfunction of the monitor was a result of the detector unit cable being severed (vzndalism).

This caused an electronic short in the monitor circuitry.

H ~

Environmental air monitoring station J on-site was inoperable from October 7,

1982 (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) to October 12>

1982 (1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />).

- Malfunction of the air monitoring station was a result of a defective fuse for the vacuum pump.

I~

Environmental radiation monitor and air monitoring station Dl on site was inoperable from October 20, 1982 (0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />) to October 29,,

1982

.(1500 hours0.0174 days <br />0.417 hours <br />0.00248 weeks <br />5.7075e-4 months <br />).

Malfunction of the equipment was a result of physical damage to the environmental cabinet that contains the radiation and air monitoring equipment.

This sampling station was found off its normal mounting structure.-

The station was de-energized on October 21, 1982 to prevent safety hazards.

The radiation monitor sustained damage during the fall and required repair (chart recording unit damaged).

The-'sampling station was reactivated after the installation of a new support structure and repair of the radiation monitor.

Environmental air monitoring station J on-site was inoperable from November 12, 1982 (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) to November 15>

1982 (0945 hours0.0109 days <br />0.263 hours <br />0.00156 weeks <br />3.595725e-4 months <br />).

Malfunction of the air monitoring station was a result of a blown fuse in the vacuum pump circuitry.

K.

Environmental air monitoring station I on-site was inoperable from November 22, 1982 (1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />) to November 23, 1982 (0818 hours0.00947 days <br />0.227 hours <br />0.00135 weeks <br />3.11249e-4 months <br />).

Malfunction of the air monitoring equipment was a

result of a defective vacuum pump.

L.

Environmental air monitoring station K on-site was inoperable from December 6,

1982 (estimate) to December 8,

1982 (1107 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.212135e-4 months <br />).

Malfunction of the air monitoring station was a result of a defective vacuum pump.

M.

Environmental radiation monitor C off-site was inoperable from December 14, 1982 (estimate) to December 21, 1982.

Malfunction of the monitor was a result of a defective chart recording unit.

-6, April 1983

III~

EVALUATION OP ENVIRONlKNTALDATA The results

-of. the 1982 Radiological Environmental Monitoring Program (RF2P) must be'ut into p'erspective considex'ing the natural processes of the environment and the past radiological data.

Several factors must be realized in order to effectively evaluate and interpxet the data'here are three separate groups of radionuclides that were detected in the envix'onment during 1982 '

few of these radionuclides could possibly fall into two of the three

groups, The first of these groups is naturally occurring radionuclides.

It must be realized that the environment contains a

broad inventory of naturally occurring x'adioactive elements.

Backgx'ound radiation as a function of primoxdial radioactive elements and cosmic radiation of solar origin offers a

constant exposure to the environment and man.

These radionuclides, such as Th-232, Ra-226, Be-7 and especially K-40, account for a

majority of the annual per capita background dose.

A second group of radionuclides that were detected are a result of the detonation, of thermonuclear devices in the earth's upper atmosphere.

The detonation frequency during the early 1950's produced a significant.

inventory of radionuclides found in the lower atmosphere as well as in ecological systems.

A ban was placed on. weapons testing in 1963 which greatly reduced the

.inventory through the decay of short lived radionuclides, deposition, and the removal (by natural processes) of radionucUdes from the food chain such as by the process of sedimentation.

Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of 'China.

In each

case, the usual radionuclides associated with nuclear detonations were detecteu several months afterwards and then after a peak detection period, diminished to a point where most could not be detected.

The last such weapons test was conducted in October of 1980'he resulting fallout ox'eposition from'his test has influenced the background xadiation in the vicinity of the site and was very evident in many of the sample medias analyzed during 1981.

Calculations of the resulting doses to man fxom fallout related radionuclides in the environment show that the contribution from such nuclides in some cases (such as Sr-90 or Cs-137) is significant and second in intensity only to natural background radiation, Quantities of Nb 95, Zr-95, Ce-141>

Ce-144, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and Co-60 are typical in air particulate samples and have a weapons test origin.

The third group of radionuclides detected in the environment during 1982 were those that could be related to operations at the site These select radionuclides were detected in a

few of the sample medias collected and at very low concentrations Many of these radionuclides ax'e a,by-product of both nuclear detonations and the operation of light water reactors thus making a

distinction between the two sources difficult, if not impossible, under the circumstances.

Radionucliaes falling into this category (as applicable to the 1982 Nine Mile Point Envix'onmental Program), include Cs-137, Mn-54 and Co-60.

The dose to man as a result of these radionuclides is small and much less than the radiation exposure from naturally occurring sources of xadiation and from fallout.

-7 April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA (cont. )

Thus, a number of factors must be considered in the course of radiological data evaluation and interpretation.

The evaluation and interpretation is made at several levels including trend analysis, dose to

man, etc.

An attempt has been made not, only to report the data collected during 1982, but also to assess the significance of the radionuclides detected in the e'nvironment as compared

.to natural radiation sources.

It is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are. very small and are not an indication of environmental significance.

In regards to these very small quantities, it will be further noted that at such minute concentrations the assessment of the significance of detected radionuclides is very difficult.

Therefore, concentrations in one sample that are two times the concentration of another, for example, are not significant overall.

Moreover>

concentrations at such low levels may show a particular radionuclide in one sample and yet not in another.

The 1970 per'apita dose rate (Eisenbud) was determined to be 209 mrem per year.'his average dose includes such. exposure

'ources as

natural, occupational>

weapons "testing, consumer products, medi&1,'tc.

The 1970 per 'capita dose rat>>

due to natural sources was 130 mrem per year.

Of this

dose, approximately 20 mrem per year is received by the gonads and other soft tissues and an additional 15 mrem per year is

. received by the bone tissue for a 70 kg (155 lb) man.

These doses (ie.

20 mrem and 15 mrem) are the result of gust K-40

alone, a

naturally occurring relatively high energy beta emitter (1.3 Mev).

The 1970 per capita dose rate due to the nuclear fuel cycle is 0.0028 mrem per year.

Background

radiation (gamma radiation),

as a

result of radionuclides in the atmosphere and the ground>

accounts for appro~tely 60 mrem per year.

This dose is a result of radionuclides of cosmic origin (as for example Be-7),

of a

primordial origin (as Ra-226, K-40, and Th-232) and to a

smaller extent of a.manmade origin.from weapons testing.

dose of 60 mrem per

year, as a

background

dose, is significantly greater than any possible doses as a result of operations at the site.

A,.

A uatic Pro ram Tables 3

through 8

demonstrate the analytical results for the aquatic media sampled during the 1982 sampling program.

Aquatic samples were collected at four possible indicator locations.

The locations (on-site transect designations) used for on-site sampling were NMPW (Ol), NMPP (02),

JAF (03), and NMPE (04) (see Figure 1).

Because of the unavailability of various sample

media, on-site samples were colected from'ombinations of the above listed locations, when required.

NMPW and NMPP were combined into location NMPP.

NMPE and JAF were combined into location JAF.

Off-site samples were collected at the Oswego Harbor area or further to the west (or east) and therefore served as control locations.

-8'pril 1983

~

~

III.

EVALUATION OP ENVIRONMENTAL DATA (cont. )

1he species glonerata is the doninant species of ~Clads hors in the collect1ons in the vicinity of Nine Mile Point.

~clads hors Is a long filamentous algae attached by a holdfast to rocks and other submerged sabstrates.

Colonization and propagation of Cladophora extends out to a

depth of 20 feet.

The

long, growing'trands of Clado hora In water five feet deep or less are constantly being broken off by wave activity.

Maximum growth usually occurs In water approximately ten to fifteen feet

deep, but this wi11 vary, depending upon turbidity.

Growth of ~Clads hors hegins ia late May, reaches a peak in late June or early Julyp and then declines during the warmer summer months of July and August.

As the lake temperature drops after

August, a secondary peak In growth may occur during this time.

Growth ceases In the fall months as a result of decreasing photoperiod and lake temperature.

first collection was made In June followed by a collection in because of the cool lake temperatures.

Whereas, during August, zone.

Collections were made at an off-site (00} or control location and at two on-site or Indicator locations.

The indicator locations were in the proximity of the Nine Mile Point

. (NMPP-02) and the James A.

PitzPatrick (JAP-03) facilities.

The control lo'cation was located gust east of the Oswego Harbor area.

Spring collections made In June showed detectable radionuclides that were a result of naturally occurring

sources, weapons testing and possibly plant re1ated operations.

K-40 and Be-7 are naturally occurring and were noted In both the indicator locations and the control location with the exception of Be-7.

Be-7 was not noted at the JAP location.

K-40 ranged in concentration from 3.7 pCI/g (wet) to 4e5 pCI/g (wet).

Be-7 ranged from 0.12 pCI/g (wet) to 0.21 pCI/g (wet).

The concentrations detected, for R-40 and Be-7 were significantly less than concentrations noted during 1981.

Cs-137 was detected at all three locations during the June collections.

Concentrations at the Indicator locations were slightly greater than the control location.

Cs-137 at the NMP location showed a concentration of 0.017 pCI/g (wet) and at the JAP location showed a

concentration of 0.011 pCI/g (wet).

past weapons testing based on 1982 data and historical data.

-9. April 1983

ZII.

EVALUATION OP ENVIRONMENTAL DATA (Continued)

A,.

1. Cladophora - Table 3 (cont.)

Although Cs-137 was detected at a greater concentration at the indicator locations i't does not necessarily indicate that a

portion of the detected Cs-137 is a result of site operations.

The 1982 data as well as past data shows that detected radionuclides (man made as well as naturally occurring radionuclides) were noted at greater concentrations at the indicator locations that at the control location.

This fact was noted in the'981 Annual Environmental Operating Report, and may be a result of the Oswego River."plume" in Lake Ontario.

Zn this

case, the river water plume may contain a

higher concentration of naturally occurring and weapons testing radionuclides as a result of the watershed drainage.

Because of a combination of factors, such as the existing longshore current in Lake

Ontario, the relative proximity of the indicator growth in the Nine Mile Point area may be sub]ect to an environment (river plume) with a

greater concentration of radionuclides, than the samples collected at the control location.

Co-60 was detected at

the, NMP location dur.'.ng June at a

concentration of 0.017 pCi/g (wet).

Co-60 was not detected at the JAF location or the control location. It is difficult to assess the presence of Co-60 at the NMP location.

During 1981 and 1980 Co-60 was not detected at any of the control location samples During 1979 however>

Co-60 was detected in the June control sample at a

concentration of 0.010 pCi/g (wet);

As noted above, it is difficult to assess whether Co-60 is due to

'past weapons testing or whether its presence is a result of site operations because of the minute concentration detected.

However, Co-60 in this case is most probably a

result of operations at the site.

No other radionuclides were detected in the June 1982 samples using gamma spectral analysis.

'Samples

" collected during August also showed detected concentrations of K-40 and Be-7.

K-40 was detected at all three sample locations and ranged in concentration from 2.4 pCi/g (wet) to 3.9 pCi/g (wet).

Be-7 was detected at the NMP location only a't a concentration of 0.16 pCi/g (wet).

Historically, Be-7 has been noted as appearing in some samples and not in others because of the minute concentrations detected.

Cs-137 was detected only at the NMP location at a concentration of 0.016 pCi/g (wet).

The detected concentration is very small and is just slightly above the lower limit of detection for the other August samples.

As noted above for Co-60, it is difficult to assess the presence of Cs-137 at the NMP location and not at the other sample locati'ons because of the minute quantity detected.

Cs-137 in Clado hora samples has historically been attributed to past weapons testing.

-10, April 1983

III.

EVALUATIONOF ENVIRONMEFIXL DATA (Continued)

A,.

1. Clado hora Table.3 (cont-)

Samples collected during 1981 showed detectable concentrations of many weapons testing radionuclides.

These included

cerium, zirconium> niobium, ruthenium, and cesium.

The presence of the radionuclides was attributed to the 1980 Chinese nuclear weapons test.

With the exception of cesium, these radionuclides were not present in the 1982 samples.

The half-life of. these radionuclides range from 33 days to 365 days with the exception of cesium (Cs-137 has a

30 year half-life).

The absence of these radionuclides is attributed to nuclear decay and ecological cycling'eview of past environmental data shows that the concentrations of naturally occurring K-40 and Be-7 have fluctuated greatly.

K&0 at all locations has ranged from 2.3 pCi/g (wet) to 67.8 pCi/g (wet).

Be-7 at all locations have ranged from 0.22 pCi/g (wet) to 2.4 pCi/g (wet).

Different years showed different peak years for the two radionuclides.

Cs-137 since 1979 at the indicator locations 'as been variable.

The annual mean concentration in 1979 (0.15 pCi/~et) was higher than 1980 (0.02 pCi/guet).

1981 (0.3& pCi/~et) was greater than the preceding year.

The annual mean for the indicator samples during, 1982 was 0.015 pCi/g'wet) which represented a

decrease when compared to 1981.

Cs-137 at the control location has also been variable.

The 1979-1981 annual means for Cs-137 were 0.03 pCi/g, 0.02 pCi/g, and 0.10 pCi/g (wet) respectively.

Fluctuation in the Cs-137 concentrations is a result of past weapons testing.

An example of this is the October 1980 Chinese weapons test.

The 1981 mean concentration increased at both indicator and control locations as a result of this test.

The 1982 annual mean decreased as there were no weapons tests since 1980.

The significance of the detected radionuclides in Clado hora samples during 1982 is very small.

This sample media has a hig bioaccumulation factor for most radionuclides and the results of the analyses can be used, for the most part, in a qualitative

'concentrations of radionuclides in the, environment in which it grows.

.As an example, the bioaccumulation factor for Cs-137 is 80-4,000 for this sample media.

-ll. April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA, (Continued)

A,.

1. Clado hora Table 3 (cont.)

A dose assessment to man is difficult to make since Clado hora is not a human food source; For the purpose of illustration, a

comparison of hypothetical doses can be calculated on the basis of an assumption that Cladophora is an important food source.

at an annual rate equal to green leafy vegetables, i.e.

64

'g/year (Regulatory Guide 1.109).

A conservative assumption can also be made that the mean Cs-137 concentration for 1982 at the indicator locations minus the mean control location concentration is a result of operations at the site.

Further, it is assumed that the one positive Co-60 concentration is a

result of operations at the site (since Co-60 was detected only in June, the calculated dose is baaed on one-half a year).

Maximum whole body and critical organ doses to an adult are as fo&.ows:

Radionucli,de Whole Body Dose>>

Critical Organ Dose>>

0.036 0.002 Cs-137 Co-60 0.056 (liver) 0.020 (GI tract)

The pro]ected doses are based on maximum consumption rates and radionuclide concentrations.

The doses are very small and can be put into perspective

-by making a comparison to the natural background dose as a result of increases in altitude and cosmic radiation.

The combined whole body dose as a result of Cs-137 and Co-60 is 0.038 mrem per year.

This is equal to the whole body dose as a result of residing at a location 100 meters (328 feet) higher in altitude for 6.9 days.

2 ~ Dam Shoreline Sediment - Table 4

Shoreline sediment samples weie collected twice during 1982.

Collections were made in May and November at one off-site or control location and at one indicator location (NMPP-02).

The control sample collected in May was not able to be analyzed for Sr"90 because of the large particle size o'f this sediment.

A, gamma spectral analysis was completed, however.

A sample was recollected on July 7

once it was known that a Sr-90 analysis could not be performed.

This sample was analyzed for Sr 90 and also for gamma emitters using gamma spectral analysis.

The results of this extra sample collected at the control location is included on Table 4.

• Dose in mrem per year.

-12. April 1983

III.

EVALUATION OP ENVIRONMENTAL DATA (Continued)

A.

2 ~ Dam Shoreline Sediment Table 4 (cont.)

Several radionuclides were detected in sediment samples using gamma spectral analysis.

These results ranged from naturally occurring primordial radionuclides to man~de radionuclides.

K-40 was detected at both the control location and indicator location for both collection periods during 1982'-40 ranged in concentration from 12 pCi/g (dry) to 17 pCi/g (dry) at the control location'nd 16 pCi/g (dry) at the indicator location (results at the indicator location were identical for the spring and fall collections)

~

Ra-226 and Th-232, in addition to K-40, are also naturally occurring radionuclides

~

Ra-226 was detected at both indicator and control locations at concentrations that are representative of normal background level fluctuations Ra-226 ranged in concentration from 0.36 pCi/g (dry) to 0.41 pCi/g (dry) at the indicator location and 0.19 pCi/g (dry) to 1.60 pCi/g" (dry) at the control location Th-232 ranged from 0.42 pCi/g (dry) to 0 56 pCi/g (dry) at the indicator location and 0,18 pCi/g (dry) to 0.48 pCi/g (dry) at the control location.

Cs-137 was detected in three of the four required samples collected during the year ~

Cs-137 was detected in two of the indicator samples and one of the control samples.

The concentrations detected were very small and are for the most part indicative of previous weapons testing.

The one positive detection in the control sample location was made in the second half of the year (November) and showed a concentration of 0 05 pCi/g (dry) ~

Cs-137 was detected in both of the indicator samples (ice.,

May and November) at concentrations af 0.07 pCi/g (dry) and 0 F 80 pCi/g (dry) respectively.

The one indicator sample (0.80 pCi/g dry) was statistically greater than the corresponding control location sample Cs-137 was not detected in the extra control sample collected during July.

Co-60 was detected in one of the indicator samples (November) at a concentration of 0.16 pCi/g (dry) ~

This resu1t was greater than the control sample LLD value.

The presence of Co-60 in this sample is most probably a result of operations at the site.

Historical data for Co-60 in shoreline sediment samples showed that this radionuL'lide has not been detected at the control location or 'the indicator location from 1979 1981 (data is not available for this sample media prior to 1979).

The concentration

detected, however, is very small and the associated impact is minimal.

Co-60 was not detected in the extra control sample collected in July.

No other radionuclides were detected in shoreline sediment samples using gamma spectral analysis.

The 1982 samples were analyzed for Sr-90 and showed detectable concentrations in two of the four samples.

Sr-90 was detected in the samples at both the indicator and control locations.

-13 April 1983

III.

EVALUATION OF ENVIRONKVTALDATA (Continued)

A.

2.

Dam Shoreline Sediment Table

4. (cont.)

The control sample (collected in July) showed a concentration of 0.0043 pCi/g (dry) while the indicator sample (collected in May) showed a

concentration of 0.0168 pCi/g (dry).

The indicator sample is statistically greater than the control sample.

Sr 90 has been detected in the past at the control location.

During 1979>

Sr-90 at the control location was detected at a

concentration of 0.04 pCi/g (dry) and during 1980 it was detected at concentrations of 0.015 pCi/g (dry) and 0.010 pCi/g (dry).

Sr-90 levels detected during these years are approximately the same as or greater than the concentration detected at the indicator location during 1982 (0.0168 pCi/g-dry).

Sr-90 is considered to be background and is not considered to be representative of site operations because of historical control sample data and the variability of minute Sr-90 concentrations.

Sr-90 was not detected in the indicator or control sample collected in the fall.

Evaluation of historical data (1979-1981) shows that Cs-137 has ranged from 0.22 pCi/g (dry) in 1979 to 0.07 pCi/g (dry) in 1980 at the ontrol location.

Cs-137 at the indicator location has xanged from 0.20 pCi/g (dry) in 1980 to O.ll pCi/g (dry) in 1981.

1982 results ranged-from 0.05 pCi/g (dry) to 0.80 pCi/g (dry).

Overall, the control location results have decreased since '1979, while the indicator results have also decreased with the exception of the one 1982 sample of 0.80 pCi/g (dry).

The evaluation of past Co-60 data indicates that Co-60 has not been detected-in the past at either indicator or control locations since 1979.

Sr-90 historical data since 1979 shows that concentrations have genex'ally decreased at the control location from a maximum of 0.015 pCi/g (dry) in 1980 to not detected in 1981 and 0.0043 pCi/g (dry) in 1982.

Sr-90 at the indicator location has generally xemained the same from 1979-1981 but showed an increase in 1982.

The

increase, as noted above, is consistent with past control sample data (1980)

-- and may= not necessarily demonstrate an increasing trend.

The impact of the 1982 shoreline sediment sample results is minimal and can be evaluated by projecting a dose to man.

The critical pathway, in this case, is direct radiation to the whole body.

The presence of Co-60 and a portion of the Cs-137 may be as a result of operations at the site.

Although the shoreline area is controlled by NMPC personnel, a dose may be calculated assuming that the axes in question is utilized as a beach area.

Assuming that a teenager spends 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> per year at the beach area or shoreline (Regulatory Guide 1.109),

and the sediment has a

mass of 40 kg/m (dry),

then the associated dose to the whole body in mrem per year can be calculated.

-14, April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA, (Continued)

A.

2.

Dam Shoreline Sediment - Table 4 (cont.)

\\

Further assumptions must be made and include:

no radiological decay of the detected radionuclides, the shore width factor is 0.3 (Regulatory Guide 1.109) and that the Co-60 concentration detected and the Cs-137 concentration detected (minus the background) are constant for one year and are a result of site opex'ations.

The radionuclide values used here are 0.16 pCi/g (dry) for Co-60 and. 0.38 pCi/g (dry) for Cs-137.

The whole body dose from Co-60 is 0.002 mrem per year and 0.001 mrem per year from Cs-137 or a total whole body dose of 0.003.

Sx-90 was not evaluated since the whole body dose from this beta emitter is insignificant.

3.

A whole body dose of 0.003 mrem per year is very small and can be compared to the whole body dose from natural background radiation in the area surrounding the site.

The natural background dose as a

result of parameters such as cosmic radiation and naturally occurring radionuclides in the atmosphere and the

ground, has been demonstrated by environmental dosimeters (TLDs) to be approximately 5

mrem per month or 60 mrem per year.

The calculated dose of 0.003 mrem per year as a result of Cs-137 and Co-60 is conservative in the sense that it is a high dose estimate.

Even in view of this conservatism, this dose is eztremely small and is 0.00005 of the annual natural background dose of 60 mrem per yeax'.

Fish Table 5A, 5B A total'f 18 required fish samples were analyzed as a result of collections in the spring season (June 1982) and in the fall season (October 1982).

Collections were made utilizing gill nets at one off-site location greater than five miles from the site (Oswego Harbor area),

and at two on-site'ocations in the vicinity of the Nine Mile Point Unit 81 (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 emitter's> Sr-89, and Sr-90.

Analysis of the spring 1982 fish samples indicated detectable concentrations of radionuclides related to past weapons testing and natural origins (naturally occurring).

Small detectable concentrations of Cs-137 were found in all fish samples (including control samples).

Sr-89 and Sr-90 were also detected in control as well as indication samples.

Spring fish collections were comprised of two separate species and nine Individual samples.

The two species represented one feeding type.

Lake trout and brown trout are highly predacious and feed on significant quantities of 'maller fish such as

smelt, alewife, and other smaller predacious species.

Because of the limited availability of species present in the

catches, no bottom feeder species were collected in the spring samples.

-15, April 1983

III. 'EVALUATION OF ENVIRONMENTAL DATA, (Continued)

A.

3. Pish -'able 5A, 5B (cont.)

Cs-137 was detected in all on-site and off-site samples for both species collected.

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 significantly different from the control results and are therefore considered to be representative of background

'concentrations.

Cs-137 in lake trout samples ranged from 0.044 to 0.051 pCi/g (wet) and averaged 0.049 pCi/g (wet) for the indicator samples.

Cs-137 in the control samples ranged from 0.047 to 0.051 pCi/g (wet),

and averaged 0.049 pCi/g (wet) for lake trout.

Cs-137 in brown trout; samples ranged from 0.048 to 0.064" pCi/g. (wet) and averaged 0.056 pCi/g (wet) at the indicator locations.

Cs-137 in the 'ontrol samples was 0.049 pCi/g (wet)

(one sample collected).

Sx-89 was detected in four of the nine samples collected.

Two of the four samples were control samples.

The remaining two samples were collected at the NMP (02) and the JAF (03) locations.

Of the positive results, the highest concentration was found in the control sample.

This concentration,

however, was only slightly above the indicator sample resu1ts.

Sr-89 in lake trout samples ranged from 0.003 to 0.005 pCi/g (wet) and averaged 0.004 pCi/g (wet) in the 'control samples.

Sr-89 was not detected in the indicator samples for lake trout.

Brown trout samples showed detectable concentrations of Sr-89 in the indicator samples ranging from 0.003 to 0.004 pCi/g (wet) and a

mean of 0.0035 pCi/g (wet).

The control brown trout sample showed no detectable Sr-89.

AI1 positive Sr-89 results are considered to be representative of normal background Sr-89 concentrations in fish.

Background levels are a result of past weapons testing in this case.

Sr-90 was detected in five of the nine samples collected.

One of the five samples, was.a control sample.

The remaining samples with positive Sr-90 results were at the NMP (02) and the JAF (03) locations.

Of the five positive results, the control result had the highest concentration.

Lake trout samples for the indicator locations showed Sr-90 concentrations ranging from 0.003 to 0.004 pCi/g (wet) and a mean of 0.0035 pCi/g (wet).

The lake trout control samples result showed no detectable Sr-90.

However, the control sample result for brown trout was 0.013 pCi/g (wet),

significantly greater than the indicator sample mean of 0.0035 pCi/g (wet) for the lake trout samples.

Sr-90 was not detected in the indicator samples for brown trout.

As noted

above, the control sample result for brown trout was 0.013 pCi/g (wet).

-16, April 1983

III.

EVALUATION OF ENVIRONMENTALDATA (Continued)

A.

3. Pish Table 5A, 5B (cont.)

H All positive results are considered to be representative

'of normal background Sr-90'oncentrations in fish.

This is especially evident when considering the highest Sr 90 concentration in the spring fish collections for the indicator samples (0.004 pCi/g [wet]) and the highest concentration in the control samples (0.013 pCi/g [wet]).

These background levels of Sr-90 are a result of past weapons testing.

K-40 was detected in ale. of the spring samples collected.

K-40 is a naturally occurring radionuclide and is not related to power plant operations.

Detectable concentrations of K-40 in the indicator samples (lake.trout and brown trout) ranged from 2.5 to 3.6 pCi/g (wet) and 2.8 to 3.1 pCi/g (wet) for the control samples..

No other radionuclides were detected in the spring fish samples.

Pall sample collections were comprised of two separate species and "nine individual samples.

Six samples of lake trout and three sampIes of brown trout were collected at a combination of two on-site sample locations (NMP and JAP) and one off-site sanple location (Oswego Harbor area).

Samples were collected by grill net in October.

Cs-137 was detected in aU. nine samples including the three control samples.

Control samples showed Cs<<137 concentrations to be greater in the indicator samples from the on-site locations'he detected concentrations were not significantly different from one another because of the extremely small quantities detected.

Cs-3.37 in lake trout samples at the indicator locations ranged from 0.034 to 0.045 pCi/g (wet) and averaged'.042 pCi/g (wet).

Brown trout samples from the indicator locations ranged from 0.049 to 0.053 pCi/g (wet) and averaged 0.051 pCi/g (wet).

The associated control sample was 0.047 pCi/g (wet).

Sr 89 concentrations for the fall samples were all less than the minimum detectable level.

Sr-89 was not detected at any of the on-site or off-site sample locations.

Sr-90 was detected in five of the nine samples collected.

Sr-90 was detected at indicator as well as control sample locations.

Indicator samples for both lake trout and brown trout showed Sr 90 concentrations approximately equal to control sample

'ocations.

Indicator samples ranged from 0.002 to 0.005 pCi/g (wet) and averaged 0.003 pCi/g (wet).

Contxol sample results ranged from 0.002 to 0.004 pCi/g (wet) and averaged 0.003 pCi/g (wet).

Sr"90 results at both indicator and control sample locations are indicative of background Sz-90 concentrations and axe a result of past weapons testing.

-17, April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

3 ~ Fish - Table 5A, 5B (cont.)

K-40 was detected in all of the fall samples collected Detectable concentrations of K-40 in the indicator samples (lake trout and brown trout) ranged from 2 1 to 3.2 pCi/g.(wet) and 2.5 to 3~0 pCi/g (wet) for the control samples.

No other radionuclides were detected in the fall fish samples.

In addition to the normal fall fish samples, extra samples'ere collected shortly after the lake trout and brown trout sample collectionsi White sucker samples were collected at this time.

White sucker samples were not available at all locations during the schedule sample collections (i e.,

when the lake trout and brown trout samples were collected)

~

White sucker samples were analyzed

.because they represent a

group of "bottom feeders" contrasting the predatory species of lake trcut and brown trout.

Samples of white sucker were collected in the vicinity of the NMP and JAF discharges as well as from the inlet canal at the Oswego Steam Station (control sample).

Gamma spectral analyses were performed on these three samples Analyses for Sr-89 and Sr-90 were also performedi These samples are not

. considered Environmental Technical Specification (ETS) samples.

Cs-137 was detected in all three of the white sucker samples (control and indicator sample locations)

~

Cs-137 in the two indicator samples was -0.06 pCi/g (wet) and 0.039 pCi/g (wet) respectivelyi Cs>>137 in the control sample was 0.027 pCi/g (wet) ~

Although the one indicator sample (NMP) had a detected concentration of 0.06 pCi/g (wet) or approximately two times the control result of 0 027 pCi/g (wet),

this difference is not considered significant because of the minute amounts of Cs-137 measured in these two samples In addition, control sample data in 1981 showed Cs-137 concentrations as high as 0 058 pCi/g (wet).

K&0 was detected in all three extra white sucker samples Detected concentrations ranged from 3 6 to 4.5 pCi/g.(wet) ~

The control sample showed 2.8 pCi/g (wet) ~ It is interesting to note here that the same pattern of concentration in the indicator and control samples for Cs-137 is present for K-40 (in fact the proportions are almost identical)

That is, the K-40 and Cs-137 concentrations were approximately 200K of the control result at the JAF location and approximately 130K of the control result at the NMP location, No other gamma emitting radionuclides were detected in the extra white sucker samples.

-18 April 1983

III'VALUATIONOP ENVIRONMENTAL DATA (Continued)

A.

3 ~ Pish Table 5A, 5B (cont.)

Sr-89 and Sr-90 concentrations for the fall extra white sucker samples were all less than the minimum detectable level.

Sr-89 and Sr-90 was not detected in any of the control or indicator samples i Review of past environmental data indicates that the Sr-89 concentrations have decreased steadily since 1976 for both indicator and control locations.

The indicator sample mean results have decreased significantly since 1976.

These results range from an annual mean of 0'7 pCi/g (wet) in 1976 to 0 '036 pCi/g (wet) in 1982.

Control sample results have also decreased'ignificantly from 0'4 pCi/g (wet) in 1976 to 0.0042 pCi/g (wet) in 1982'r-90 annual mean sample results have decreased from 0 28 pCi/g (wet) in 1976 to a low of 0'035 pCi/g (wet) in 1982 1981 and 1982 mean'ample results are approximately the same.

Control sample results have decreased as well, from 0.25 pCi/g (wet) in 1976 to Oi0026 pCi/g (wet) in 1982 Sr-90 was not detected in

1981, however, the LLD level and the 1982 detected leve1 are approximately equal.

A, general decline in

. detectable Sr-89 and Sr-90 results is most probably a result of the incorporation of these radionuclides with organic and inorganic substances through ecological cycling.

In addition, Sr-89 has a relatively short half-life of 52 days.

The mean 1982 Cs-137 concentrations have decreased slightly from 1981 'for the indicator samples and significantly from 1980 to 1976 'oncentrations for these samples decreased, from a level of li4 pCi/g (wet) in 1976 to a level of 0 048 pCi/g (wet) in 1982'ontrol sample results have also decreased from a level of 0.12 pCi/g (wet) in 1976 to a level of 0.050 pCi/g (wet) in 1982 'esults from 1979 to 1982 have remained fairly consistent.

As noted for Sr-89 and Sr-90 above, the general decreasing trend for Cs-137 is most probably a result of ecological cycling.

A.

significant portion of Cs<<137 detected since 1976 in fish is a

result for weapons testing fallout, and the general downward trend in concentrations wiU.

continue as a

function of ecological cycling and nuclear decay Lake Ontario fish are considered an important food source by many Therefore, fish is an integral part of the human food chain Based on the importance of fish in the local diet, a

reasonable conservative estimate of dose to man can be calculated.

Assuming that the average adult consumes 6'

kg of fish per year (Regulatory Guide 1 109) and the fish consumed contains an average Cs-137 concentration of 0.048 pCi/g (wet)

(annual mean result of indicator samples foz 1982),

the whole body dose received would be 0.024 mrem per year.

-19 April 1983

III.

EVALUATION OP ENVIRONMEÃIM.DATA (Continued)

A..

3. Pish - Table 5A,,

5B (cont.)

The critical organ in this case is the liver which would receive a calculated dose of 0.036 mxem per year.

Using the same above

'riteria, the calculated doses associated with Sx-89 are 0.003 mrem per year whole body dose and 0.102 mrem per year bone dose (critical organ).

Calculated doses as a result of Sr-90 are 0.616 mrem per year whole body dose and 2.510 mrem per year bone dose (critical organ).

These whole body and critical organ doses are

. conservative calculated doses associated with consuming fish from the Nine Ale Point area (indicator samples).

Conservative whole body and cr'itical oxgan doses can be calculated for the consumption of fish from the control location as well.'"In this case the consumption rate is assumed to remain the same (6.9 kg per year) but the average annual Cs-137 mean concentration for the control samples is 0.050 pC1/g (wet).

The calculated Cs-137 whole body dose is 0.025 mrem per year and the associated dose to the liver is 0'.038 mrem pex'ear.

Doses as a

result of Sr"89 are 0.003 mrem per year (whole body) and 0.106 mrem per year (bone).

Sr 90 doses are 0,642 mrem pex year (whole body) and Z.615 mrem per year (bone).

'alculated doses as a result of fish consumption (lake trout and brown trout) at the indicator and control.locations are presented below..

Indicator Control Whole Body* Critical Organ~

Whole Body" Cxitical Or an~

Cs-137 Sr-89 Sr-90 0.024 0.003 0'16 0.036 (liver) 0.102 (bone) 2.510 (bone)

0. 025 0.003

0. 642 0.038 (liver) 0.106 (bone)

'.615 (bone)

Moses in mrem per year.

Consumption assumed for all months.

In summary,.the whole body and critical organ doses observed as a x'esult of consumption of fish is small.

Doses received from the consumption of indicator and control sample fish are approximately the same.

The dose from control sample fish are slightly higher.

Doses from both sample groups are considered background doses.

Doses from the consumption of white sucker samples are not considered here since these fish are rarely consumed.

-20, April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

4 ~ Lake Water Tables 6, 7, and 8

1982 lake water samples were analyzed monthly for gross beta and gamma emitters (using gamma spectral analysis)

~

Sr-89, Sr-90, and tritium analyses were performed quarterly.

quarterly samples (i.e.,

Sr-89, Sr-90, and tritium) were composites of monthly samples.

The analytical results for the 1982 lake water sample program showed no evidence of plant related radionuclide buildup in the lake water in the vicinity of the site.

Indicator samples were collected from the inlet canals at the Nine Mile Point Unit 81 and James A.

FitzPatrick facilities.

The control location samples were collected at the City of Oswego water treatment plant and, consisted of raw lake water prior to treatment.

The gross beta annual mean activity for the Nine Mile Point Unit 01 and the James A. FitzPatrick inlet canals (F 00 pCi/liter) was approximately the same as the 1981 mean. inlet canal results (3.0 pCi/liter), and was significantly less than the annual mean

.results for the years prior to 1981.

The Nine Mile Point Unit 81 canal samples were greater than the control samples for six of the 12 monthly samples analyzed and ranged from 1.27 pCi/liter 4.72 pCi/liter.

The James A.

Fitzpatrick canal samples were greater than the control samples for 10 of the 12 monthly samples'nd ranged from 1.98 pCi/liter to 3.53 pCi/liter.

The control sample results ranged from 1.79 pCi/liter to 3 20 pCi/liter.

The fl'uctuation in the gross beta canal sample results is due to the natural variation in the concentration of naturally occurring radionuclides.

A slight increase in the gross beta activity was noted in the Nine Mile Point inlet canal samples for September and October.

These two results (4.72 pCi/1iter and 3.89 pCi/liter respectively) are most probably as a

result of liquid waste 'ischarges in September and October and the reverse flow mode of the circulating water system The discharges and reverse flow mode are covered in'ore detail below A significant reduction in gross beta concentrations is. noted when reviewing inlet canal gross beta results since 1974.

The reduction in gross beta activity is primarily the result of improved analytical procedures and equipment and not necessarily to changes in plant operations.

Although the past elevated gross beta concentration may be due in part to past weapons testing, it is difficult to determine what portion was due to improved instrumentation and what part was due to weapons testing.

There were no significant changes or trends in gross beta activity on a monthly basis for 1982.

-21 April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

4. Lake Water Tables 6, 7,. and 8 (cont.)

Gamma spectral analysis was performed on 36 monthly composite samples required by the Environmental Technical Specifications.

Three radionuclides were detected in the Inlet canal samples.

Two of these radionuclides were plant related and the remaining radionuclide was naturally occurring.

Co-60 was detected In the inlet canal samples for the James A..

FitzPatrick facility.

Co-60 was detected'n the James A.

FitzPatrick Inlet canal samples in January,

March, and August (1.58 pCI/liter, 2.37 pCI/liter, and 1.61 pCI/liter respectively).

The detected quantity of Co-60 was most probably

,the,,result of -,Intake tempering in January and March or Instrument background.

On these occasions, a portion of the warm discharge water Is circulated Into the Inlet canal.

As a result of normal 1iquid discharges, a

small portion of this discharge enters the Inlet canal and may be sampled.

The concentration detected Is very small and Is at the lower limit of detection.

The August inlet canal

sample, as noted

above, also showed Co-60 (1.61 pCI/liter).

The concentration detected here was most probably a result of Instrument background.

Co-60 has been detected in environmental samples on a few occasions as a result of a minute Co-60 background at the on-site counting laboratory.

Co-60 was not detected In the Nine Mile Point Inlet canal samples during 1982, therefore any detection of Co-60 In the

'James A.. FitzPatrick canal samples was most probably a

re'suit, of tempering (January and March) or Instrument background (August).

It should be noted that a quality control sample split, for the FitzPatrick March 1982 inlet canal, was analyzed by an Independent contractor.

The analysis of the sample split showed no detectable Co-60.

The reported lower limit of detection for tQs sample was 0.57 pCI/liter which Is one quarter of the 2.37 pCI/liter reported for the routine or In-house sample analysis.

The lack of a

positive Co-60 detection In the quality control sample indicates the presence of Instrument or environmental background.

Efforts are made to keep background levels at a

minimum (below detectable levels),

'but because of the small quantity of material required to increase the background above detectable levels and variability of these small concentrations, background 'evels of plant radionuclides willat times be present.

Cs-137 was detected once during 1982 in the James A.. FitzPatrick Inlet canal samples for the month of January'he concentration detected here was 0.43 pCI/liter.

The detection of Cs<<137 in the January sample was again most probably the result of inlet canal tempering as noted above for the detection of Co-60 during January.

This concentration is minute and is at the lower limit of detection for the other monthly samples.

-22, April 1983

III EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

4. Lake Mater Tables 6, 7, and 8 (cont.)

No other radionuclides were detected in the James A. FitzPatrick inlet canal samples with the exception of naturally occurring K-40'-40 was detected three times during 1982 for the months of January, September and November.

The concentrations detected during these months were 4,5 pCi/liter, 16.5 pCi/liter and 14 '

pCi/liter respectively.'o-60 was not detected during 1982 in the Nine Mile Point inlet canal samples.

The lower limit of detection values for monthly samples ranged from 1.11 pCi/liter to 2'2 pCi/liter which was at the approximate detection levels for Co-60 in the James FitzPatrick samples.

Twomonthly samples did show Cs-137 concentrations for the months of September and October.

The concentrations detected heze were slightly above the lower limit of detection for Cs-137 in the other monthly samples.

The September sample showed a Cs-137 concentration of 3.72 pCi/liter and. the October sample showed a

Cs-137 concentration of 3.25 pCi/liter.

The presence of. Cs-137 in the Nine Mile Point inlet canal samples during

. September and October is a result of liquid discharges made'uring those months and the fact that the circulating water flow was in a

reverse flow mode.

In this

case, a portion of the inlet canal becomes the pathway for the discharge flow and a portion of the discharge canal becomes a

pathway for the intake flow.

The liquid waste discharge pipe is located in the discharge canal vertical shaft which is part of the portion of the discharge canal that is affected by the reverse flow mode (i,e,, this part of the canal receives intake water in the reverse flow mode) ~

The intake sample (taken at the discharge canal during reverse

.flow) is downstream of the liquid waste discharge pipe. It is not practical or possible to acquire an inlet water sample prior to (i.e.,

upstream) the liquid waste discharge pipe considering the present inlet/discharge canal system design.

Therefore, as noted

above, the intake water sample contained a portion of the liquid waste discharge.

Liquid waste discharges were made in September and October 1982 which were -the same months that Cs-137 was detected in the monthly inlet canal samples.

Liquid waste discharges were not made in November and December (with the exception of a very minor discharge in November)

~

The corresponding inlet samples showed no detectable radionuclides with the exception of K-40.

No other radionuclides were detected in the Nine Mile Point inlet canal samples other than Cs-137 and K-40.

K-40 was detected in the April and December inlet canal samples.

The concentrations detected were 16' pCi/liter and 16 3 pCi/liter respectively.

-23 April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

4 ~ Lake Water Tables 6, 7, and 8 (cont.)

Water samples of the raw watez prior to treatment at the City of Oswego water treatment plant showed no detectable concentrations of plant related radionuclides K-40 was the only detectable radionuclide and was noted in October and November at a

concentration of 14i3 pCi/liter and 14.8 pCi/liter respectively.

Quarterly samples for Sr-89 analysis were composites of the monthly samples.

The fourth quarter Nine Mile Point inlet canal was the only location during 1982 that showed a

detectable concentration of Sr-89 ~

The quantity detected was 0.606 pCi/liter This small detected concentration is well.within the LLD range for the other samples Sr-89 was detected in this sample <<as a result of the October liquid waste discharges and the reverse flow mode of the circulating water system during the fourth quarter, Sr-89 was not detected in any of the other water samples taken from the City of Oswego water treatment

plant, the Nine Mile Point inlet

canal, or the James A.~

FitzPatrick inlet canal, The lower limit of detection values for the City'f Oswego water treatment

plant, the Nine Mile Point inlet canal, and the James A. FitzPatrick inlet canal samples ranged from 0.396 pCi/liter to 2.23'Ci/liter.

Quarterly samples for Sr-90 analysis were composites of the monthly samples as noted for the Sr-89 analysis.

Sr-90 was detected in all quarterly samples for 1982 at all three locationsi At the City of Oswego water treatment

plant, or control location, Sr-90 ranged from 0.75 pCi/1iter to 5.30 pCi/liter with a mean of 2 04 pCi/literi Sr-90 in the Nine Mile Point inlet canal samples ranged from'i40 pCi/liter to 3.07 pCi/liter and showed a

mean of 1.16 pCi/liter.

The James A.

FitzPatrick inlet canal samples showed Sr-90 ranging from 0.691 pCi/liter to li55 pCi/liter'nd a mean value of 1.01 pCi/liter As demonstrated, the control location showed the highest mean result (2.04 pCi/liter) which is a result of natural variation the distribution of Sr-90.

Sr-90, as deteCted in the 1982 water

samples, is considered to be background Sr-90 as a zesult of past weapons testing.

Tritium

samples, as noted above for Sr-89 and Sr-90, are quarterly samples that are a

composite of the appropriate monthly samples'ritium was detected in all samples taken at aU. three locations.

The City of Oswego water treatment plant showed tritium concentrations ranging from 112 pCi/liter to 307 pCi/liter with. a mean of 165 pCi/liter, Tritium concentrations'or the James A

FitzPatrick inlet canal ranged from 194 pCi/liter to 3U. pCi/liter and showed a

mean concentration of 266 pCi/liter.

Inlet canal samples taken at Nine Mile Point showed tritium concentrations ranging from 202-pCi/liter to 4,620 pCi/liter.

The annual mean concentration was 1,478 pCi/liter,

-24 April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

4. Lake Mater Tables 6,'7, and 8 (cont.)

2 The maximum 'oncentration (4,620 pCi/litez) and the mean concentration (1,478 pCi/liter) were significantly greater than the control resultsi As noted above for the detection of Cs-137 in the Nine Mile Point inlet canal samples during September and October, liquid waste discharges were made during those months.

These discharges showed concentrations of tritium.

As.a result of the reverse flow mode and the location of the liquid waste discharge

pipe, a portion of this effluent was sampled (the sampling equipment is located slightly downstream of the liquid waste pipe) ~

Since monthly samples were composited to quarterly samples, it stands to reason that the third and fourth quarter samples of the inlet canal should show tritium concentrations.

Observation of the data shows that the third quarter sample was approximately four times the normal inlet canal concentrations and the fourth quarter result was approximately twenty-three times the normal canal concentrations.

Since a

significant portion of the September&ctober discharges were made in October, it is reasonable to expect that the fourth quarter (October December) inlet canal sample would demonstrate the higher tritium concentration of the two.

Although this sample represents intake water from Lake

Ontario, the presence of.

tritium in this sample is indicative of the location of th~:

liquid waste discharge pipe.

During the third and fourth

quarters, the James A. FitzPatrick inlet canal samples showed

,tritium concentrations consistent with the first half 'of the year 'and within the natural variability of tritium in lake water.

Evaluation of past environmental data shows that gross beta concentrations in water samples have decreased significantly since 1977 at both the indicator sample locations (inlet canals) and at the control location (Oswego City water) ~

As noted previously,

however, the decrease is primarily a result of more superior analytical instrumentation.

Since

1978, gross beta

. levels have remained relatively constant at both indicator and control locations.

Indicator annual means ranged from 15' pCi/liter in 1977 to 41.8 pCi/liter in 1976'or the period of 1978 through

1981, annual means ranged from 2.98 pCi/liter (1981) to 4.53 pCi/liter (1978) ~

The indicator annual mean for 1982 was F 00 pCi/liter Control sample annual means were also relatively high dur'ing 1975 to 1977.

During these

years, the concentrations ranged from 45 33 pCi/liter (1975) to 10.9 pCi/liter (1977) ~

Data from 1974 for the control location was deleted from this comparison because of questionable results.

For the period 1978 through

1981, annual mean gross beta concentrations ranged from 2 60 pCi/liter (1980) to 3.55 pCi/liter (1978) ~

The control annual mean for 1982 was 2.42 pCi/liter.

-25 April 1983

III.

EVALUATION'OP ENVIRONMENTAL DATA'(Continued)

A.

4. Lake Water - Tables 6, 7, and 8 (cont.)

Review of previous data for Sr"89 and Sr-90 demonstrates that results have, been variable since 1975.

Sr-89 for the indicator samples has ranged from not detected (1976,

1977, and 1979) to 0.78 pCi/liter (1981) and has been relatively consistent when detected.

At the control locations,

'Sz-89 ranged from not detected (1975-1978 and 1981) to 1.4 pCi/liter (1980).

During

1982, Sr-89 showed an annual mean of <0.97 pCi/liter (LLD) at the control location and 0.61 pCi/liter at the indicator locations.

Sr-90 annual

. means have

~ remained relatively consistent at both indicator and control sample locations since 1975-Mean results for the indicator samples ranged from not detected (1975 and 1976) to 1.00 pCi/liter (1977 and 1980).

Mean -results at the control sample location ranged from not

. detected (1975 1978) to 1.10 pCi/li.ter (1980).

The annual mean Sr-90 results during 1982 for the indicator samples and control samples were 1.08 pCi/liter and 2.04 pCi/liter respectively.

Previous annual mean results for tritium at the indicator sample location has decreased slightly since 1976.

Sample results were available since 1974 through 1981 and showed a

peak value of 513.0 pCi/liter (1976) and a

minimum va.i.ue of 234 pCi/liter (1979).

The annual mean tritium result at the indicator locations for 1982 was 740 pCi/liter.

This result is higher than the annual mean for any. of the previous years but this mean reflects the two elevated results at the Nine Mile Point location in the third and fourth quarters.

The two elevated results were a result of the September and October liquid waste discharges and the reverse flow mode at the Nine Mile Point facility, as noted above.

Mean tritium results at the control location have decrease slighly since 1976 as was noted for the indicator samples.

Mean annual results were available for 1974 through 1981.

These results showed that tritium at the control location ranged from not detected (1974) to 652 pCi/liter (1976).

1979 through 1981 mean results were consistent, as was also noted.

for the indicator results.

The control peak concentration (652 pCi/liter) was greater than the peak concentration in the indicator samples (513 pCi/liter).

The impact, as ezpressed by a dose to man, is not assessed here since the primary pathway, in this case, is drinking water.

The nearest source for drinking water is the City of Oswego water treatment plant which is the control location for the sampling program.

The results of the control location are consistent with previous years'esults and are representative of normal background radionuclide concentrations in lake water and regional drinking water.

-26, April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

BE Texrestrial Pro ram S

I Tables 9

through 21 represent the analytical results for'he terrestrial samples collected for the 1982 reporting periodi

1. Air Particulate Gross Beta Tables 9 and 10 Tables 9

and 10 contain the weekly air particulate gross beta results for the six off-site and nine on-site sample locations.

The samples were counted at a minimum of twenty-four houx's after collection to allow for the decay of naturally occurring radionuclides with short half-lives' total of 317 off-site and 476 on-site samples were collected and analyzed during 1982'o significant levels of gross beta activity were observed in any of the samples.

The off-site or control mean concentration for 1982 was 0.033 pCi/m while the indicator or on-site sample mean was equal to 0.031 pCi/m

~

As noted, the on-site annual mean is about ten percent lower than the off-site mean for the same period This difference in mean concentration has been exhibited in the past eight yeax's with the exception of 1977 when a higher annual mean gross beta'ctivity was observed

'for the on-site sampling stations.

In these seven

years, the control stations'nnual mean ranged from a

minimum difference of 8.5 percent higher than the indicator observed in 1981 to a

maximum difference of 28.6 percent

higher, observed in 1978 ~

The difference in off-site and on-site weekly and monthly mean values for gx'oss beta could be the result of a combination of the many natural processes which can affect environmental concentx'ations.

The most significant parameter that could possibly contribute to a

depxessed or lower concentration for the on-site stations would be location.

The close proximity of on-sita sampling stations to the lakeshore (Lake Ontario) would account for lower concentrations of naturally occurx'ing radionulcides being collected on the sample media.

Surface winds from off the lake would contain less particulate matter and airborne gases.

than surface winds from adJacent land areas The major component of gross beta concentx'ations are potassium-40 and decay or daughter.products of uranium and thorium.

The concentrations of these nuclides in the ground level atmosphere ax'e dependent upon the local geology ana its chemical constituents

Thus, surface wind over land axeas have a potential for containing higher concentrations of naturally occux'x'ing radionuclides.

-27 April 1983

III EVALUATION OF ENVIRONMENTAL DATA (Continued)

Bi l. Air Particulate Gross Beta Tables 9 and 10 (cont.)

Review of air particulate gross beta concentrations shows that no significant increases in concentration occurred during 1982

'he standard deviation for sample results on an individual sample basis is 0'2 for both the on-site and off-site data

base, representing smaU. variation in analytical results for the

. year ~

Week 832 (August 2, 1982 through August $0, '1982) showed an. on-site mean concentration of 0.51 pCi/m which was 76 percent greater than the concuzrent off-site weekly mean concentration The on-site particulate filters for this week were analyzed for gamma emitter using a

gamma spectral analysis No plant related radionuclides were detected in this sample above the limits of detection.

The observed increases and

,decreases in general gross beta activity can be attributed to changes in the environment.

As discussed

above, the concentration of the naturally occurring radionuclides in the lower limits of the atmosphere directly above land areas are affected by time related processes such as wind direction, snow cover, soil temperature and soil moisture content.

Little change was noted in gross beta activity which corresponded with seasonal changes as has been observed in past years In general, the gross beta activity in air particulate samples has decreased significantly The mean 1982 concentration for'oth off-site and on-site is five times lower than the mean concentration detected in 1981 This five-fold reduction in activity is directly attributable to the increased activity detected in 1981 as a result of fallout fxom an atmospheric nuclear test (i.e.,

the October 1980 Chinese Weapons Test) and subsequent return to background levels in 1982 The trend of gross beta activity in the environment is that of reduced concentrationsi The mean 1982 concentration was the lowest level of gross beta activity observed since 1974.

This general decxease is most probably the result of the reduction of atmospheric nuclear testing in recent years in comparison to the 1960's when such testing was conducted on a more frequent basis.

2 ~ Month1y Air Particulate Com osites Table 11 Weekly air particulate samples were composited monthly by location into two on-site composites and two off-site composites On-site composites include B-1 (stations Dl, D2, E,

F, and G) and B-2 (H> I, J, and K) ~

Off-site composites include A-1 (stations C, Dl and D2) and A2 (stations E, F, and G) ~

The results for the composite samples analyzed during the 1982 sample program showed positive results for Ra-226, K-40, Be-7, Ce-144, Nb-95, Cs-137, Ru-106, Mn-54, and Co-60.

All nine of these radionuclides were detected in the on-site composites and in the off-site composites with the exception of Ru-106

'28 April 1983

III.

EVALUATION OF ENVIRONMENT& DATA (Continued)

B.

2. Monthl Air Particulate Com osites Table ll (cont.)

I Ra-226, R-40 and Be-7 are naturally occurring.

Ce-144, Nb-95, Cs-137 and Ru-106 are' result of weapons testing.

Co-60, and Mn-54 are possibly,a result of weapons testing or operations at the site or a

combination of both.

The total number of radionuclides detected in 1982 was significantly less than 1981.

This decrease was a result of the decay and deposition of weapons testing'radionuclides.

Concentrations of'r-95, Ce-141, Ru-103, La-140 and Ba-140 were not detected in 1982 as they had been in 1981.

Nb-95, Ce-144 and Cs-137 were detected at varying concentrations in both on-site and off-site composites.

Nb-95 was detected three times during the year in off-site composite samples and eight'imes 1y on-site composite samples.

Nh-95 ranged from 0.00045 pti/m to

~ 0.00 58 pgi/a for the off-site smsples and from 0.00020 pti/m to 0.00075 pCi/m for the on-site composites.

The mean for the off-site composites (0.00051 pCi/m3) was slightly greater than the mean for the on-site

'omposites (0.00046 pCi/m ).

Ce-144 was detected in both off-site and ori-site composites.

Ce-144 ranged from 0.00118 pCi/m3 to 0.00245 pCi!m in off"site samples and 0.00090 pCi/m to 0.00295 pCi/m iM 'on-site samples.

The mean for the off-site composites was greater than the on-site composite mean (0.00176 pCi/m vs.

0.00159 pCi/m ).

Cs-137 was detected at least 33K of the time in both on-site and off-site composites.

Off-site composites showed Cs-137 concentrations ranging from 0-00016 pCi/m to 0.00093 pgi/m whereas on-si.)e composites ranged from 0.00012 pCi/m to 0.00067 pCi/m.

Cs-137 mean concentrations for the off-site composites were greater than the on<<site composites (0.00043 pCi/m versus 0.00036 pCi/m3).

I The presence of Nb-95, Ce-144, and Cs-137 in approximately equal concentrations at the off>>site and on-site locations is an indication of a weapon testing origin.

Nb-95 and Ce-144 were not detected after July for all composite samples with the exception of one detection of Nb-95 4n November (on-.site B-2 composite).

Nb-95 and Ce-144 were noted in 1981 as steadily decreasing in concentration from the October 1980 Chinese weapons test.

Concentrations for Nb-95 ranged from 0.1342 pCi/m to 0.00045 pCi/m during 1981 and ranged from 0.00075 pCi/m3 to not detected in 1982.

Ce-144 showed a gimilar trend in 19/1-1982.

Cs>>137 ranged from 0,00453 pCi/m to 0.00018 pCi/m during 1981 and during 1982 ranged from 0.00093 pCi/m3 to not detected.

Cs-137 during the last four months of 1982 was only detected in four'f the sixteen composite s

samples.

Cs-137 would be expected to be detected for a longer time period than Nb-95 and Ce-144 because of its radiological ha1f-life (30 years versus 35 days for Nb-95 and 284 days for Ce-144).

It appears, however> that other factors are involved, such as deposition.

-29, April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

BE

2. Monthly Air particulate Com osites Table 11 (cont.)

Although Cs"-137 is a constituent of site gaseous effluents, its presence in on-site composites is a result of weapons testing.

Two observations point to this First, Cs-137 concentrations in on-site and off-site composite samples are approximately equal.

In actuality, the off-site composite sample results are slightly greater.

If the Cs-137 detected in the on-site composite samples was a result of site effluents, it would be expected that the on-site composite samples would show a greater Cs-137 concentration than the.off-site composite samples when considering release data and gaseous dilution coefficients

Secondly, the presence of Cs-137 as a site gaseous effluent is small for ground level releases when compared to other particulate effluents such as Ba-140, La-140, or Mn-54. If the Cs-137 detected in the on-site particulate composite samples was a result of site gaseous effluents, other radionuclides, such as La-140, or Mn-54 would be detected.

La-140 was not detected during 1982 and Mn-54 was detected only once which could very well be a result of the 1980 Chinese weapons test (see below) ~

Ru-106 was detected once during 1982 in February in an on-site composite sample Ru-106 is a

result of the 1980 Chinese weapons test and was noted during 1981 in both on-site and off-site composite samples This radionuclide was not detected after September of 1981 with the exception of two composite samples out of a total of sixteen composite samples The decreasing trend from 1981 to 1982 is a

result of the radiological ha1f-1ife of Ru-106 (367 days) and deposition Ru-106 was detected at a concentration of 0.00201 pCi/m.

Mn-54 and Co-60 were detected in both on site and off-site composite samples during 1982.

Mn-54 was detected once in ap off-site composite at a

concentration of 0.00023 pCi/m (February A.-l off-site composite) and once in an on-site composite at a

concentration of 0.00020 pCi/m (January B-1 on-site composite)

~

The presence of Mn-54 in both on-site and off-site composite samples in 'the early part of the year indicates that this radionuclide is most probably a result of weapons testing,'pecifically, the October 1980 Chinese weapons test Mn-54 was first detected after October 1980 in January 1981 in the A-1 off-site composite sample at a concentration of 0 '0028 pCi/m,

and was detected in all on-site and off-site composites by March of 1981.

A maximum concentration of 0.00191 pCi/m was detected in May in an on-site composite sample.

'he maximum off-site concentration was approximately equal to this result and was noted at a

concentration of 0 ~ 00158-pCi/m

~

Mn-54 decreased after May 1981 until it was detected sporatically after September and not detected after November.

-30 April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

B.

2. Monthl Air Particulate Com osites Table 11 (cont.)

The two positive results in January and February of 1982 are most probably a continuation of the downward trend seen in the last four months

, of 1981 where Mn-54 was only detected sporaticaUy.

Historically>

Mn-54 has been detected in air particulate composites for a period of up to several years after weapons testing.

The downward trend of Mn-54 is a result of the radiological half-life of Mn-54 (303 days) and deposition.

Co-60 was detected in twel; e of the fortymight monthly composite samples.

Co-60 was detected.

in the off-site composites in January,

February, and May.

On-site composites showed concentrations of Co-60 in January,

February, March,

May, July,,and September..

The mean Co-60 concentration for 1982 was 0.00055 pCi/m for the off-site composites and 0.00053 pCi/m3 for the on-site composites.

Co-60 ranged in concentration in the off-s$te composite samples from 0.00039 pCi/m to 0.00066 pCi/m.

For

)he on-site composite

samples, Co-60 ranged from 0.00026 pCi/m to 0.00095 pCi/m The evaluation of the presence of Co-60, as to whether its origin is weapons

testing, site operations or

both, is difficult.

Co-60 was detected in off-site and. on-site composite samples during the first five months of the year at approximately equal concentrations, which tends to indicate a

weapons testing origin.

Beyond May> however, Co-60 was detected twice'"in the on-site composite samples.

These two positive results were approximately twenty-five percent of the concentrations detected prior to June which tends to indicate that these two results are possibly a result of operations at the site.

In con)unction with.this, the gaseous effluents from the site for Co-60 generally decreased during the second half of 1982.

Overall>

as a result of the complicating environmental conditions and the minute Co-60 concentrations detected in these samples, it is very difficult to accurately assess the. presence of Co-60.

Three naturally occurring radionuc15.des were detected during 1982 in both off-site and on-site air particulate composite samples.

These included Ra-226, K-40 and Be-7.

The ann+

off-s$te/on-site means for Ra-226, K&0, and Be-7 in 10 pCi/m were 5.08/2.58, 3.88/3.32, and 105/98 respectivel'y.

The off-site and on-site means were relatively constant except for Ra-226 which demonstrated a higher off-site concentration.

-31. April 1983,

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

BE 2 ~ Monthl Air Particulate Com osites Table 11 (cont.)

No other radionuclides were detected in on-site or off-site air particulate composite samples during 1982 using gamma spectral analysis.

The location, concentration range and

mean, and frequency of occurrence of each radionuclide detected during 1982 is included below.

Raddonucldde Locandon Range*

Meane

~Foe uenc *>>

Nb-95 Nb-95 C~144 Ce-144 Cs-137 Cs-137 Ru-106 Ru-106 off-site on-site off-site on-site off-site on-site off-site on-site 0.00045&.00058 Oe00020 0'0075 Oe00118 Oe00245 0.00096-0 '0295 0+00016-0 00093 Oa00012-0 '0067 ND -

ND ND -0 00201 Oe00051 Oe00046 0000176 0'0159 0'0043 0 00036 ND 0'0201 3

8 11 11 10 15 0

1 Mn-54 Mn-54 Co&0.

Co-60 off-site 0.00023-0.00023 on-site 0 00020-0.00020 off-site Oi00039-0 '0066 on-site 0.00026-0 '0095 0 00023 0 00020 0 00055 Oa00053 1.

1 3

9

, Ra-226 Ra-226 X-40 X-40 Be-7 Be-7 off-site on-site off-site on-site off-site on-site 0+00468-0 00546 0+00183& 00414 0 00250-0 00626 0 00168-Oa00601

.Oa06100&a14800 0 '5400-0,18000 0 00508 0'0258 0.00388 0 00332 0.10500 0 09800 3

5 9

15 24 24 ND-not detected

~ - results in units of pCi/m

+*- frequency is number of times detected Evaluation of the weapons testing radionuclides detected during 1982 indicates that these radionuclides appear after an atmospheric weapons test and then slowly decrease in concentrations through deposition and/or radiological decay.

Positive results for Nb-95, Ce-144, Cs-137, and Ru-106 were not only detected in 1982 but also in peak concentrations during 1978 and 1981'he concentration of these radionuclides has fluctuated as a result of the March 1978 and October 1980 atmospheric

weapons, testing.

Cs-137, in particular, has fluctuated as a

result of the 1978 and 1980 weapons test Although this radionuclide is a

small constituent of site effluents, the annual mean concentrations have fluctuated in response to the 1978 and 1981 weapons testing.

-32 April 1983

III'VALUATIONOF ENVIRONlKNTALDATA (Continued)

BE 2, Monthl Air Particulate Com osites Table ll

Thus, Cs-137 has followed similar trends that parallel the other weapons testing radionuclides such" as isotopes of cerium and ruthenium> Zr-95, and Nb-95, etc Historically, Cs-137 showed a

maximum conceqtration of 0 00305 pCi/m in 1978, decreased to 0 00107 pCi/m in

1980, increased again in 1981 to 0 '0453 pCi/m3 (as a result of the October 1980 weapons test) and finally decreased to 0.00093 pCi/m3 in 1982

'o-60 and Mn-54 historically has shown fluctuations that are generally representative of weapons testing.

C~O, at off-site locations showed a

maximum concentration of 0.0153 pCi/m in 1978 (as a result of the 1978 weapons test),. a decrease in 1979, and"was not detected in 1980'n increase was noted during 1980 in the on-site composite sample.

This may have been a result of operations at the site~

An increase as a result of the 1980 weapons

test, was noted in both off-site and on-site composite samples during

1981, (a

maximum of 0.00162 pCi/m off-site).

This was followed by a

decrease in 1982 to 0.00066 pCi/m (off-site) ~

Mn-54 also demonstrated a similar trend since 1978 as was noted for Co-60'uring

1978, Mn-54 showed a

maximum off-site 'oncentration

.of 0.00264 pCi/m,

followed by a

decrease to a point where it was not detected off-site during 1979 and 1980 ~

Mn-54 was detected on a few occasions on-site during 1979 and 1980 at very low concentrations 1981 showea Mn-54 concentrations increasing to 0.00162 pCi/m as a result of the 1980 weapons test.

Mn-54 was only detectea twice during 1982 at significantly lower concentrations than those detected in 1981

'ssessment of the presence of radionuclides in air particulate composite samples can be, depicted by calcblating doses to man as a result of inhalation'33 April 1983

III.

EVALUATION OF ENVIRONMENTALDATA (Continued)

B.

2. Monthl Air Particulate Com osites Table 11 (cont.)

Using the qverage child inhalation rate of 3,700 m

per year or 308.3 m

per standard month (Regulatory Guide 1.109) and the mean concentration measured at the on-site sample stations, the following annual doses can be calculated.

Concqntration Nuclide (10 c pti/mg)

No. Months Detected

~0rd in Dose*

'mrem/ear)

Nb-95 Ce-144 Ru-106 Cs-137 Co-60 Mn-54 0.46 1.59 2.01 0.36 0.53 0.20 6

7 1

10 6

1 Fallout Fallout Fallout Fa1lout/Plant FaU.out/Plant Fallout/Plant 0.00014 0.01108 0.00240 0.00003 0.00187 0.00003 Total Dose 0.01555 Fallout Dose 0.01362 (87,6X)

Fallout/Plant Dose- 0.00193 (12'.4X)

The table above illustrates that the average dose received by a child from inhalation of air-in the vicinity of the site is approximately one~e hundredth of a mrem per year.

Of this average yearly dose, the dose received from radionuclides that are possibly a result of operations at the site is approximately twelve percent or 0.002 mrem per year.

This dose is actually a significant overestimate because these radionuclides (X.e.,

possibly site related) where shown to correspond to similar trends in concentrations that were noted for radionuclides that are strictly of fallout origin.

Thus, the dose received from radionuclides that are possibly related to operations at the site is minute and insignificant as demonstrated by this pathway (inhalation).

<<Dose to the lung.

B.

3., Airborne Radioiodine (I-131) - Tables 12 and 13 During the 1982 sampling program airborne radioiodine was detected in one of the 317 weekly samples collected from the six off-site sampling stations.

An I-131 concentration of 0.039 pCi/m3 was detected at the D-1 off-site sampling station for the sampling period of June 8,

1982 to June 19, 1982.

The resulting dose to man can be calculated at tgs off site-location based on an inhalation rate of 160 m

per week (Regulatory Guide 1.109) and the measured concentration.

The dose received by man at sampling station D-1 off-site would be 0.00018 mrem to the thyroid and 0.00000031 mrem to the whole body for a

one week exposure.

The result of I-131 at an offmite sampling location is not routine.

In the 1,247 weekly off-site I-131 samples collected in 1979 through 1982 I-131 was only detected once and is noted above.

Positive I-131 results were noted in off-site stations during 1977 and 1978.

-34. April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

BE 3 ~ Airborne Radioiodine (I-131) Tables 12 and 13 (cont.)

I-131 was detected in twelve of the 476 on-site samples analyzed in 1982'hese samples which contained radioiodine covered a

total of eight sample weeks or periods~

The environmental I-131 concentrations detected in on-site samples during 1982 are outlined below.

Sample On-site Concentratioy I

Dose (mrem)

Th roid/Whole Body O3/22/S2 03/29/82 07/12/82 07/19/82 07/26/82 08/16/82 08/30/82 09/13/82 D-2 I

H HI D-2 H

H J

H J

J 0 ~ 0244+0 ~ 004 0 ~ 0250+0 ~ 006 0,0104+0.004 0+0169+0+005 0 '424+0 '05 0+0131+0.004 0 ~ 0146+0 003 0 0064+0.004 0 0105+0 '04 0+0036+0+003 0'024+0 '03 0+0239+0 006 TOTAL 0.00011/0

~ 00000019 0 00012/0 00000010 0.00005/0 F 00000008 0+00008/0+00000013 0 00019/0 '0000033 0.00006/0.00000010 0.00007/0.00000012 0 00003/0 00000006 o.oooo5/o.ooooooos 0.00002/0 00000002 0 ~ 00001/0 ~ 00000002 oi00011/Oo00000019 0.00090/0

~ 00000142 The spacial distribution of the I-131 concentrations show that five of the positive results were observed at H and three at J on-site air monitoring stations with two positive results observed at both the D-2 and I on-site aiz monitoring stations.

The four on-site air monitoring stations showing positive I-131 concentrations in 1982 are

located, in reference to the Nine Mile Point Unit 2 reactor centerline, at approximately 0.80 miles 8

71 (H on-site);

0 80 miles 8

98 (I on-site);

0 90 miles 8

U.o (J

on-site)~

and 0 40 miles 8

140 (D 2 onsite)

~

A meaningful dose estimate is difficult to make for the I-131 concentrations at the four on-site sampling stations as there are no residencies or individuals in the immediate vicinity. of the sample locations As noted on Figure 2 and 3, the H, I, J and D-2 air monitoring stations are well within the site boundary or controlled area.

The above table illustrates the doses that can be calculated using the assumption that a

critical individual was present at all the monitoring locations simultaneously for the total period of time for which the I-131 was collected (i e 7 days)

~

Such an individual does not exist but the calculated dose can be used for the purpose of illustration The critical organ for this example is the thyroid gland.

-35 April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

B.

3 ~ Airborne Radioiodine (I-131) Tables 12 and 13 (cont.)

The calculated total dose for the 'above mentioned critical individual would be 0.00090 mrem to the thyroid and 0 '0000142 mrem to the whole body assuming a seven day sample period and an inhalation rate of 160 m

per sample period (Regulatory Guide 1,109).

The resulting calculated dose due to on-site I-131 concentration is extremely 'mall and can be compared to a

similar dose from natural or background radiation that an individual could receive as a result of changing elevation.

An individual residing one meter (3 28 feet) higher in altitude for a period of 37.3 minutes 'would receive an additional radiation dose of 0.00000142 mrem which is equal to the total c'alculated dose to the whole body from environmental I-131 concentrations.

The end result of the 1982 I-131 sampling effort showed no significant impact due to operations at the site~

During 1982, I-131 was not detected in any other environmental sample media including milk and green leafy vegetables.

Bi 4

TLD (Environmental Dosimeter) - Table 14 TLD's wer>> collected once per quarter during the

'sample year.

The TLD results are an average of four independent readings at each location and are reported in mzem per standard month.

Each location has two TLD's with each TLD containing two distinct calcium sulfate dosimeters In 1982, TLD's for the most part were collected on March 31,

1982, July 1,

1982, September 30, 1982 and December 30,.1982.

TLD results are organized into three groups for reporting purposes The groups are on-site TLD's (defined as TLD's in the immediate proximity of the individual facilities, at points of interest),

environmental station TLD's (a

ring of TLD's surrounding the generating facilities as a group),

and off-site TLD's (TLD's located off the site property or contro11ed area and ranging up to 20 miles from the site) ~

A net dose at the environmental station TLD's can be calculated simply by subtracting the mean standard monthly off-site doses from the mean standard monthly on-site environmental station doses*

Environmental station TLD's are arranged in a

concentric circle and range in distance from the individual facilities from 1,500 to 2,000 feet.

The net dose per mean standard month for each quarter is as follows:

uarter Net Environmental Station Dose*+

0 21 0.88 0 ~ 94 0 ~ 61

-36 April 1983

III'VALUATIONOF ENVIRONMENTAL DATA (Continued)

BE

4. TLD (Environmental Dosimeter)

Table 14 (cont.)

The annual site property boundary dose for 1982 cannot be determined from the net environmental station dose since the property boundary extends out to approximately 0 75 miles from the site (i.e.,

beyond the concentric circle of environmental station TLD's) ~

A general estimate can be made based on two available TLD's located at the site boundary The net dose per standard month for each quarter 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 the shortest distance to populated areas.

~aarter Net Environmental Station Dose**

1 2

3 4

-0 13

-0.35

-0 32

-0a33 As observed, the site boundary dose based on two available TLD locations is less than the average off-site dose.

This is probably due 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 reaaings per quarter (two TLD's).

TLD numbers, 31 and 39 axe located within the Nine Mile Point 01 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'roximity to this structure.

TLD number 3 is located at the construction site of Nine Mile'Point 8'his TLD was subject to radiography at the Unit 82 site and to a much lesser extent the FitzPatrick and Nine Mile Point Unit 1 facilities.

TLD results remained fairly consistent for most TLD locations each quarter.

A slight increase in natural background radiation levels were noted for off-site TLD's in the third quarter of the year This is most proba'bly a result of increased emission rates for radon and thoron gases emanating from the ground.

The emission rates are related to ground moisture content and other natural parameters

<Location numbers 5, 6, 7, 23, 24, 25, and 26.

• Wose in mrem per standard month.

-37 April 1983

III.

EVALUATION OP ENVIRONMENTAL DATA (Continued)

B.

4. TLD (Environmental Dosimeter) '- Table 14 (cont.)

On-site TLD results remained fairly consistent except for TLD's located near radwaste facilities which may be affected by the frequency of radwaste processin'g and shipment.

These TLD's include numbers 23, 24, 27, 28, 29, 30, 47, 48 and 61 at the James A,. PitzPatxick facility and number 39 at the Nine Mile Point 01'acility.

TLD number 3, is located at the Nine Mile Point 02 facility and was affected by the frequency of radiography at the construction site.

Radiography is a

common practice at construction sites in order to determine the quality of equipment welds such as pipes.

TLD's located in areas near radiography work will show fluctuating doses as the amount of radiography performed is not consistent.

TLD number 59 results were variable as a result of the operating mode of the James A.

PitzPatrick facility.

This TLD is located near the James A..

PitzPatrick facility exhaust stack.

The results of 1982 showed no detectable impact from direct radiation measured outside the site boundary.

B.

5. Radiation Monitors Table 15 Environmental radiation monitors are located in 10 of the 15 air monitoring environmental stations.

Each of the on-site envixonmental monitoring stations contains a radiation monitor and, in addition, the C off-site monitoring station contains a

similar monitor.

The radiation monitors consist of GM detector with an associated power supply, chart recorder, and trip unit.

The monitor has an operating and recording range fxom 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 site.

The monitors are not considered to be capable of high sensitivity environmental monitoring and do not detect minute fluctuation in levels of background radiation.

Because of the relatively low sensitivity of the monitors (environmentally speaking) no comparisons are made between the radiation monitor readings and the readings from environmental TLD's.

B.

6. Milk - Tables 16 17 and 18 Milk samples were collected from a combination of seven farms during the 1982 grazing season and the following months of November and December.

The grazing season is considered to be May through October.

-38: April 1983

k' III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

BE 6 ~ Milk Tables 16 17 and 18 (cont )

One of the sample locations, number 45, was added to the milk sample locations as a result of the spring milch animal census.

This location was added in July Sample location descriptions are listed below.

Location No.

Direction from Site Distance from Site (miles) 4 ESE 40 SW 14.

ESE 16 SSW 5

SSE 7

ESE 45 SE 7.7 15 ~ 3 9.8 5 2 7 2 5.5 8'

Milk samples were collected from each of the locations in the first half of the month and.analyzed for I-131, gamma emitters, and Sr-90 I-131, gamma isotopic, and Sr-90 results are found in the analytical x'esults section.

'I The gamma spectral analysis of the monthly composite samples showed K-40 to be the most abundant x'adionuclide detected in the milk samples collected in 1982'-40 was detected in every sample analyzed and ranged in concentration fx'om 970 pCi/liter to, 1,700 pCi/liter at the indicator locations anu 1,200 pCi/liter to 1,600 pCi/liter at the control location K-40 is, a natux'ally occurring radionuclide and is found in many of the environmental medias sampled.

Cs-137 was the only other radionuclide detected in the 19U2 milk samples's-137 was measured in ten of the fifty-four monthly samples analyzedi Cs-137 was detected in milk samples at all locations at various times throughout the year except at location number 40 which is designated as the control location.

Cesium concentrations ranged from 3.5 pCi/liter to 14.0 pCi/liter for all samples with a mean of 5 7 pCi/liter.

Cesium was detected at a higher frequency at locations 5 (three times),

location 45 (two times) and location 7

(two times)

Overall, Cs-137 was detected at a higher frequency during the months of May (four positive results) and July (three positive results) at the milk sampling locations.

-39 April 1983

III,"

EVALUATION OF ENVIRONMENTAL DATA (Continued)

B 6 ~ Milk Tables 16 17 and 18 (cont.)

A maximum concentration of 14.0 pCi/liter was detected at location number 5 during August Annual means for the detection of Cs-137 at all locations are px'esented below.

Location No.

Annual Mean (Cs-137) 4 40 (control) 14 16 5

7 45 6'

pCi/1 4.0 pCi/1 (LLD) 4+6 pCi/1 5,2 pCi/1 8il pCi/1 3.8 pCi/1 4,2 pCi/1 Annua1 mean Cs-137 values for each sampling location are variable but quantitatively the values axe not significantly diffex'ent.from one another especially when the magnitude of these minute concentrations is considered.

Location number 5

had an annual mean slightly. higher than 'the other locations'ocation number 40 (control location) showed no detectable Cs-137 during 1982'uring 1981, location number 40 showed an annual mean Cs-137 concent"ation of 3' pCi/liter, and in 1980 the control location showed a

Cs-137 concentration of 4.5 pCi/literi Because of the minute quantities of Cs-137 detected, it is difficult to assess whether the concentrations detected were a result of operations at the site or whether part or all of the detected cesium is due to weapons testing fallout.

The

,impact, in'any case, is extremely small (see below) ~

An evaluation of milch animal pasture grass sampled during 1982 showed that Cs-137 was detected once in pasture grass collected from each of the milk sampling locations during 1982 Samples'f pasture grass were collected in July, August, and September at each of the milk locations Of the twenty~ne samples collected, one sample showed Cs-137 at a concentration of 0 35

. pCi/g (wet) ~

The sample was taken. from the control location (number

40) in July.

The origin of Cs-137 in this sample was from past weapons testing fallout and probably became incorporated in the pasture grass as a result of plant uptake.

As noted

above, Cs-137 was not detected in any other pasture grass samples in 1982 Naturally occurring raaionuclides, such as K-'40, Ra-226, and Be-7, wexe also detected at varying concentrations in most pasture grass samples No other radionuclides were detected in milk samples using gamma spectral analysis

-40 April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

B ~

6 ~ Milk Tables 16, 17, and 18 (cont.)

Sr-90 was detected in forty-seven of the fifty-four milk samples collected during 1982'r-90 was detected at indicator sample locations for at least ninety-one percent of the time and at the control sample location for sixty-two percent of the time.

The mean Sr-90 concentration for the contxol location was 3.1 pCi/liter The mean for all indicator locations (within 10 miles of the site) was 4.7 pCi/liter.

The control and indicator sample means are similar.

Sr-90 results for the indicator locations ranged from 1.0 pCi/liter to 9.9 pCi/liter.

Control sample results ranged from 1.6 pCi/liter to 5' pCi/liter.

The detection of Sr-90 in indicator and control locations at similar concentrations is indicative of background Sr-90 as a result of past weapons testing.

Milk samples were collected and analyzed monthly for I-131.

I<<131 was not detected during 1982 in any of the indicator oz control samples All 1982 I-131 milk results are reported as lower limits of detection (LLD)~

The LLD results ranged from

< 0' pCi/liter to < 0.4 pCi/liter for the 1982 milk samples.

~ The presence of Cs-137 and Sr-90 in milk samples has been observed in many major urban areas during previous years.

During the years when atmospheric weapons testing was common and subsequent to those years (i e.

1958-1972)',

Cs-137 and Sr-90 were detected in milk samples at concentrations that were repr'esentative of the frequency of testing (NCRP Report No.

45) ~

In the New York area, Cs-137 ranged from 60 pCi/liter in 1958 to a peak of 147 pCi/liter in 1963, to a concentration of 8

pCi/liter in 1972'r-90 demonstrated a

similar trend.

In

1958, Sz-90 was measuzed at a concentration of 6 pCi/liter and a

peak concentration of 28 pCi/liter was measured in 1963, Sr-90 decreased to 8 pCi/liter"in 1972.

Evaluation of previous. Cs-137 data shows that Cs-137 has been'etected in environmental milk samples at both indicator and control locations.

Cs-137 concentrations for 1978-1981 have remainder fairly consistent and ranged from 8.6-9.9 pCi/liter at the indicator locations.

The 1982 indicator mean was 5'

pCi/liter which showed a

slight decrease when compared to 1978-1981.

At the control location, Cs-137 has remained fairly consistent for all years from 1978-1981 except for'979 and 1982

, For these

years, this zadionuclide was not detected.

Cs-137 ranged from 3.9-5.8 pCi/liter during 1978-1982

'41 April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

BE 6 ~ Milk-Tables 16 17 and 18 (cont )

Historical data for Sr-90 indicates that this radionuclide was detected in most indicator and control samples at approximate equal concentrations.

Sr-90 at the indicator locations ranged from 4 0-5' pCi/liter during 1978-1981.

The 1982 indicator mean was consistent with this range and showed a concentration of 4.8 pCi/liter.

At.the control location,.

Sr-90 ranged from 4.2-5 '

pCi/liter during 1978-1981'he 1982 annual mean was 3,1 pCi/liter or slightly less than the 1978-1981 range.

The impact as a xesult of Cs-137 in 1982 milK samples is very minimali With x'espect to Cs-137, the dose to the bone resulting fxom Sr-90 ingestion is much more significant's noted

above, it,is difficult to assess whether Cs-137 in the indicator milk samples is a result of background cesium levels, totally as a

result of site operations, or pax'tially as a x'esult of site operations.

The difficulty arises because of the minute quantities detected that are at or gust above the lower limit of detection.

The impact can be assessed by calculating conservative doses to man as a result of the consumption

.of milk with detectable quantities of Cs-137 'ox'he purposes of a calculated

dose, the mean indicator sample Cs-137 concentration is used (5,7 pCi/liter) ~

Assuming a

consumption rate of 330 liters (87 18 gallons) per year for an infant (Regulatory Guide 1.109 maximum exposed individual),- the whole body dose would be 0.054 mrem and the critical organ dose would be 0,766 mxem to the liver.

The calculated doses are based on eight months of consumption (eight months of milk sample results)

Since Cs-137 was not detected at the control location in 1982; a

dose calculation cannot be pex'formed

, For a limited comparative pux'pose, the calculated dose to an infant as a result of consuming milk from the control location during 1981 would be 0.008 mrem whole body dose and 0 '108 mrem critical organ dose (dose to the liver) ~

The annual mean Cs-137 concentration for the 1981 control location was 4 3 pCi/liter (Cs-137 was only detected in one of the eight monthly samples dux'ing 1981) ~

The calculated dose to an adult can be determined assuming a

consumption rate of 110 liters (29.06 gallons) per year (Regulatory Guide 1.109) and a mean Cs-137 concentration of 5'

pCi/liter for the indicator locations.

The resultant doses are 0'30 mrem to the whole body and 0 046 mrem to the liver (critical organ)

~

The calculated doses are based on eight weeks of consumption As noted above, Cs-137 was not detected at the control location, therefore no whole body or critical organ dose can be calculated.

Using the example

above, the dose to an adult based on the 1981 control sample results would be 0.004 mxem to the whole body and 0.006 mrem to the liver (critical organ) ~

-42 April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA. (Continued)

B.

6. Milk Tables 16 17 and 18 (cont.)

For the purpose of illustration, the significance of the above doses can be brought into perspective by comparison to background doses due to cosmic radiation with changes in altitude.

Assuming the above calculatd whole body dose, as a

result of the consumption of milk, is 0.054 mrem to an infant and is totally a result of plant operations at the site, a

comparison can be made to the incremental increase in dose due to cosmic radiation at sea level.

A dose of 0.054 mrem whole body is equal to residing at a location 100 meters (328 feet) higher in altitude for 9.9 days.

'An additional comparison can be made to naturally occurring K-40.- -K-40 has been noted in almost all environmental samples at significant levels.

A 70 kg adult weights approximately 154 pounds and contains approximately 0.1 microcuries of K-40 as a

result of normal life functions (inhalation, consumption, etc.).

The dose to the bone tissue is about 20 mrem per year as a

result of the internal deposited K-40.

For comparison

purposes, an adult 'bone dose can be calculated that. results from the consumption of milk from the 1982 indicator locations.

The mean Cs-137 concentration of 5.7 pCi/liter is used.

The resulting bone dose is 0.050 mrem per year (an average milk Cs-137 concentration of 5.7 pCi/liter is applied over the entire year).

This dose is 0.002 of the bone dose as a result of naturally occurring K-40 in a 154 pound adult.

The impact, if any, as a result of Sr-90 in milk, due to plant operation is extremely small since the mean result ol the indicator results and the control results are approximately equal considering fluctuations in the background levels.

The leve1s of Sr-90 detected in indicator as well as control samples are'onsidered to be representative of background concentrations.

In this regard, the resultant calculated doses would be approximately equal.

Iodine-131 was not detected in the fifty-four monthly milk samples analyzed for the 1982 program.

No doses to man have been calculated because of the lack of detectable I-131.

The detection of I-131 in milk samples has not been routine in the past.

In pest sampling

programs, I-131 has been detected in milk samples in con]unction with fresh fallout from atmospheric nuclear testing.

-43. April 1983

III.

EVALUATION OF ENVIRONMENTAL DATA, (Continued)

B.

'7. Milch Animal Census Table 19 The milch animal census is an estimation of the number of cows and goats within a ten mile radius of the Nine Mile Point Site.

A census is conducted twice per year, once in the spring and once in the summer.

The census is conducted by sending questionnaires to previous milch animal owners and also by road surveys to locate any possible new'wners.

Questionnaires not responded to are foi1owed by telephone calls.

The number of milch animals located within the ten mile radius of the site was estimated to be 1,129 cows and 2 goats for the spring 1982 census.

Five new locatiops were found since the summer 1981 census.

The number of cows increased by 143 and the number of goats decreased by

~ 8 with respect to the 1981 summer census.

As a result of this

census, a

new sampling location (number 45) was added.

The 1982 summer census showed a total of 1,141 cows and 3

goats.

This represents an increase of 12 cows and an increase of 1 goat with respect to the spring 1982 census.

Four milch locations were deleted as a result of this census when compared to the spring 1982 census.

8. Human Food Products Table 20 Human food product samples were comprised of

meat, eggs,

poultry, and vegetables.

Collections for meat,

poultry, and eggs were made in the spring and fall seasons.

Samples of produce included vegetables with an attempt to sample at least one green leafy vegetable from each location.

The collection of produce was performed in late summer or early fall.

Three indicator locations, were sampled for each type of media collected, in addition, a control location was sampled during each coLlection period.

Indicator samples were collected within a ten mile radius of the site in areas which would have a high potential for demonstrating possible effects of site operations.

The ultimate factor controlLing sample locations was the availability of required samples.

Attempts were made to maintain prior sample locations were possible.

Spring meat coU.ections were made at one off-site or control location (greater than ten miles from the site) and at three on-site or indicator locations (less than ten miles from the site).

Spring meat collections showed detectable concentrations of K-40 in all samples.

R-40 concentrations ranged from 2.4 pCi/g (wet) to 6.0 pCi/g (wet) ~

K-40 is a naturally occurring radionuclide.

Two of the four spring meat samples showed detectable concentrations of Cs-137.

'The two positive concentrations were in the indicator samples.

Cs-137 in these two samples was 0.02 pCi/g (wet') and 0.08 pCi/g (wet).

Cs-137 not detected in the control sample.

-44, April 1983

III.

EVALUATION OP ENVIRONMENTAL DATA (Continued)

,. B.

8. Human Food Products Table 20 (cont.)

Cs-137 was detected in many environmental samples and was most prevalent in meat and fish, with respect to all the sample medias collected.

Cs-137 in meat samples is essentially a

result of past weapons testing.

Cesium is incorporated into meat tissue from feed

sources, The results detected in the spring meat samples were very low concentrations and thus can be detected in some samples and not in others.

By review of the 1981 spring meat sample data, it is noted that Cs-137 appeared in the control samples (0.017 pCi/g

[wet]

and 0.024 pCi/g

[wet] ~

Cs-137 was also found in the control sample during 1980 (0 01 pCi/g [wet]) ~

Of the"two meat samples that showed detectable concentrations of Cs-137, one sample (0.02 pCi/g [wet]) was approximately equal to detected concentrations in control sample results during the spring of 1981.

The other result was greater than control results over the. past several years Because this result (0.08 pCi/g [wet]) is small, the impact or dose as a result of this concentration is insignificant (see below) ~

No other radionuclides were detected in the spring meat samples using gamma spectral analysis.

Pall meat collections were made at one control and at three indicator sample locations.

The fall samples showed detectable concentrations of K-40 in all samples'-40

'concentrations ranged from 2 5 pCi/g (wet) to 3 5 pCi/g (wet) ~

K 40 is naturally occurring.

Cs-137 was detected in two of the four fall meat samples.

The two positive results were two indicator samples (less than ten miles from the site) ~

The two results showed small concentrations of Cs-137 that were approximately at the lower limit of detection (LLD)~

The results were 0.02 pCi/g (wet) and 0 02 pCi/g (wet) as compared to the control sample result of

<0.02 pCi/g (wet) ~

These results are very small concentrations

and, as noted above for the spring

samples, are comparable to concentrations detected at control locations during 1981.

These 1981 samples showed control Cs-137 concentrations, of 0.017 and 0.024 pCi/g (wet) respectively.

The impact of these small concentrations is discussed below.

No other radionuclides were detected in the fall meat samples using gamma spectral analysis.

-45, April 1983

IXI.

EVALUATIONOP ENVIRONMENTAL DATA (Continued)

B.

8. Human Pood Products Table 20 (cont.)

The detection of Cs-137 in meat samples has been noted for all years since 1978 for indicator samples and since 1980 for control locations (control samples were not collected prior to 1980).'he detected concentrations since 1978 at the indicator locations have been fairly consistent.

These samples ranged from 0.021 to 0.036 pCi/g (wet).

At the control locations, Cs-137 ranged from 0.01 to 0.021 pCi/g (wet).

The indicator sample annu,sl mean results have been slightly higher than the control sample annual mean results.

The detection of Cs-137 in meat at control and indicator sample locations,. is an indication of cesium production from weapons testing.

During 1982, Cs-137 was not detected at the control sample locations although Cs-137 has been detected in the past at control sample locations (1981, for example).

As noted

above, the concentrations detected are very smaU. and the impact or dose to man is insignificant.

An average annual dose to man can be calculated as a result of meat c'onsumption from within 10 miles of the site (indicator sample results).

'he average Cs-137 concentration in meat duxing 1982 was 0.035 pCi/g (wet).

Assuming an adult consumption rate of 95 kg per year (Regulatory Guide 1.109); the annual dose to the whole body is 0.237 mrem per year.

The critical organ dose is 0.362 mx'em.

per year to the livex'.

This calculated, dose is small and can be compared to an annual dose of 20 mrem per year to the critical organ (the gonads in this case) as a

result of natura11y occurring R-40 in the environment.

The calculated whole body dose (0.237 mrem per year)

and, the calculated

'critical organ dose (0.362 mrem per year to the liver) can also be compared to the dose received from control sample results during 1981.

During 1981, the annual mean concentration for the control meat samples was 0.02 pCi/g (wet).

Using the.

same consumption factor of 95 kg per year, the annual whole body was 0.136 mrem per year and 0.207 mrem per year to the liver (critical organ dose).

As noted above, the 1982 control samples did not show any Cs-137 above the lower limits of detection.

~However, Cs-137 in meat has historically been present.

Because of the small concentrations noted here, cesium can be detected in some samples and not in other samples.

-46, April 1983

III'VALUATIONOF ENVIRONMENTAL DATA (Continued) 8 ~ Human Food Pr'oducts Table 20 (cont.)

Egg samples were collected in the spring (May 5-12, 1982) and in the fall (November 10-11, 1982)

~

Samples were collected at three indicator locations (within ten miles of the site) and at one control location (greater than ten miles from the site)

~

The only zadionuclide detected during 1982 ia.

egg samples was K&0~

KAO was detected in the spring samples at concentrations that ranged from 3i2 pCi/g to 3.8 pCi/g (wet) ~

The fall samples showed KAO concentrations that ranged fzom 1.2 pCi/g to 2.0 pCi/g (wet) ~

For both the spring aad fall samples, the control samples had the highest K&0 coacentrations

~

poultry samples were taken during the spring (May 5-12, 1982) and during the fall (November 10-11, 1982) at three indicator locations and one control location.

K-40 was detected in all spring and fall samples for both indicator and control results.

K&0 in the spring samples ranged from 5.4 pCi/g to 8.4 pCi/g (wet) ~

The control sample had the lower concentration (5.4 pCi/g) ~

K-40 in the fall samples ranged from 3.1 pCi/g to 4 2 pCi/g (wet) ~

The control sample showed a coacentration of 4.1 pCi/g (wet).

Cs-137 was detected in one of the indicator poultry samples during 1982 The concentration detected was very small and was approximately at the lower limit of detection (LLD) level for a11 the 1982 poultry samples.

The detected Cs-137 coacentration was 0'3 pCi/g (wet) ~

The LLD levels for the other samples zanged from 4.02 pCi/g (wet) to 4.03 pCi/g (wet) ~

Historically, the control samples for poultry have not demonstrated detectable concentrations of Cs-137.

Although this sample is an indicator sample (i.e., within ten miles of, the site), it is difficult to assess whether the detected cesium is plaat related or a minute background cesium conceatration.

In regards to background Cs-137, poultry can be compared to beef (meat) samples in the sense that Cs-137 can become incorporafed in.tissue through the ingestioa pathway.

Thus, poultry have the potential to ingest Cs-137 through the purchased feed they consume (possible weapons testing source) but conversely they also have the potential to incorporate Cs-137 through ingestion of local deposition (plant related source).

The

impact, as a result of consumption of poultry, can be assessed by pro]ecting a whole body and critical organ dose to an adult.

A maximum and therefore very conservative dose can be calculated based on the one positive detection of Cs-137.

Assuming a

Cs-137 concentration of 0'3 pCi/g (wet),

and a

consumption rate of 95 kg per year (Regulatory Guide 1.109),

a conservative dose to man can be calculated.

The adult whole body dose is 0.10 mrem per year aad the adult critical organ dose is 0.16 mrem per year to the liver.

These doses were calculated for a six month period since Cs-137 was detected only during the first half of the year.

-47. April 1983

III~

EVALUATION OF ENVIRONMENTAL DATA (Continued)

B.

8 Human Food Products - Table 20 (cont.)

As noted in the assessment of the meat sample data, these doses are small when compared to 'an annual dose of 20 mrem per year to the critical organ (the gonads in this case) as a result of naturally occurring R-40 in the environment.

An additi'onal comparison can be made to natural background cosmic radiation and the resulting increase in dose with an increase in altitude.

Using the incremental increase in dose due to cosmic radiation 't sea

level, a

conservative dose calculation can be made+

The dose due to consumption of poultry to the whole body is 0 10 mrem per year, as noted above.

This dose is equal to an increase in dose due to cosmic radiation that. one would receive by residing at a location 100 meters (328 feet) higher in altitude fox 18 2 days.

It is assumed that by residing at this location one would remain at this altitude fox the full 18 2 days.

Fruits and vegetables were obtained during the harvest season.

Collections were made during September at three indicator locations and one control locati'on.

A successful attempt was made to collect one broadleaf and one non-broadleaf fruit vr vegetable at each location.

Broadleaf vegetables of Swiss chard and cabbage and non-broadleaf fruits and vegetables of tomatoes and zucchini were collected.

R-40 was detected in all broadleaf and non-broadleaf vegetables and fruits.

Broadleaf vegetables (Swiss chard and cabbage) showed concentrations of R-40 ranging from 1.5 pCi/g to 9.3 pCi/g (wet) ~

The control sample had the highest concentration (9.3 pCi/g

[wet]) ~

Non-broadleaf fruits and vegetables (tomatoes and zucchini) showed concentrations of K-40 ranging from 1 8 pCi/g to 2.6 pCi/g (wet) ~

Again the contxol location had the highest K-40 concentration (2 6 pCi/g [wet]) ~

In addition to K-40, another naturally occurring radionuclide was detected.

Be-7 is a naturally occurring radionuclide of cosmic origin in the upper atmosphere.

Be-7 was detected in two of the four broadleaf vegetable samples.

Be-7 was not detected

'in samples of non-broadleaf fruits and vegetables'oncentrations of Be-7 detected were 0.12 pCi/g (wet) and 0.14 pCi/g (wet).

One of the positive results (0.12 pCi/g [wet]) was detected in the control sample.

No other radionuclides were detected in the, 1982 collection of fruits and vegetables.

-48 April 1983

IXI~

EVALUATION OP ENVIRONMENTAL DATA (Continued)

BE

8. Human Pood Products Table 20 (cont.')

Review of past environmental data indicates that K-40 has been consistently detected in food crop samples.

K-40 concentrations have fluctuated from one sample to another but the annual ranges have remained relatively consistent from year to year.

Be-7 has been detected occasionally during. the past on leafy vegetables (1978 through 1981).

Dose estimates are not performed here for fruits and/or vegetables since no other radionuclides with the exception of naturally occurring K-40 and Be-7 were detected.

S ecial Studies - Table 21 Since 1974, the detection of Cs-137 in milk samples analyzed for the Radiological Environmental Monitoring Program has been commons The specific source of the Cs-137 is not known as there are several possible source terms for this particular radionuclidei Cs-137 is a small component of plant effluents and is also a major fallout radionuclide 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 living tissue, In an attempt to better assess the presence of Cs-137 in milk

samples, pasture grass samples were collected during 1982

'asture grass samples were collected from the routine milk sample locations three times during the grazing season.

Collections of pasture grass samples were made in July, August and September which resulted in a total of twenty-one samples.

Each sample was analyzed for gamma emmiters.

A total of four'adionuclides were detected.

in these pasture grass samples'hree of the four radionuclides detected are naturally occurring and include Ra-226, Be-7 and K"40

'-40 was detected in each sample and ranged in concentration from 9.3 pCi/g (wet) to 30 4 pCi/g (wet) ~

Ra-226 was detected in eleven samples and Be-7 was detected in six of the twenty-one samples analyzed The fourth radionuclide detected was Cs-137

's-137 was detected once in the August samples at the control location with a

measured concentration of 0.347 pCi/g (wet) ~

The *indicator locations showed no detectable concentrations of Cs-137 'he lower limits of detection (LLD) of Cs-137 for these samples ranged from a

minimum of c0.141 pCi/g (wet) to a

maximum of

<0 329 pCi/g (wet) ~

-49, April 1983

P III.

EVALUATION OP ENVIRONMENTAL DATA (Continued)

B.

8.

S ecial Studies -Table 21 (cont.)

1 h

The general lack of Cs-137 above detectable levels in the indicator samples demonstrates that fresh Cs-137 deposition as a

result of plant effluents is not indicated in the grass-co~milk pathway.

In addition, the presence of Cs-137 in the control sample (August) indicates that this radionuclide is present in.

the grass-co~ilk pathway for this particular location.

The Cs-137 detected here is a result of weapons testing and its origin may be from recent atmospheric deposition or from plant (pasture grass) uptake. It should be noted however, that Cs-137 was not detected in the control location milk samples during the 1982 grazing season.

9. Canal"Water Data - Table 22 Table 22 fulfills the requirements of the NMP-1 Environmental Technical Specifications, Appendix B, section 2.3.2, Table 2.3-2 (Cooling Water Discharge and Cooling Water Intake).

'C.

Conclusion The Radiological Environmental Mo motoring Program (REMP) w-s established to detect and assess any. possible impact -to the environment surrounding the Nine Mile Point area resulting from operations at the site.

Samples representing higher trophic levels, such as fish and meat were reviewed closely to assess any impact to the genezal environment or to man.

In addition, the data was reviewed for any possible historical trophic level bi.omccumulation trends.

Little or no impact could be determined resulting from radionuclide deposition considering all sources (natural, weapons

testing, etc.).

In regards to doses as a result of man~de radionuclides, a ma)or portion of the doses received by a member of the pub1ic was from past nuclear weapons testing..

Any possible impact as a result of.site operations is extremely minimal when compared to background

'or weapons testing.

It has been demonstrated that almost all. environmental samples contain traces of radionuclides which are a result of weapons testing or naturaU.y occurring sources (primordial and/or cosmic zelated).

Doses to man because of natural sources (naturally occurring radionuclides in the soil and lower atmosphere in Oswego County) account for approximately 60 mrem per year as demonstrated by control environmental TLD's.

Possible doses due to site operations is significantly less than this particular natural exposure.

Therefore>

as determined by review of the data presented herein>

no impact due to operations at the Nine Mile Point Nuclear Station was detected that would effect the health and safety of the public.

-50. April 1983

REPERENCES 1 ~

AU.S. Nuclear Regulatory Commission Regulatory Guide le109,'Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of -Evaluating Compliance with 10CFR Part 50, Appendix I"9 March 1976 (Revision 0).

2e U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, "Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I", October 1977 (Revision 1).

3 ~

Eichholz, G.

Environmental Aspects of Nuclear

Power, First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michiganp 1976.

4 ~

National Council on Radiation Protection and Measurements (NCRP),

'Environmental Radiation Measurements, NCRP Report No. 50, 1976.

5 ~

National Council on Radiation Protection and Measureaents (NCRP), Natural Background Radiation in the United States, NCRP Report No. 49, 1979.

6.

National Council on Radiation Protection and Measurements (NCRP),

Cesium-137 from the Environment to Man:

Metabolism end Dose, NCRP Report No. 52, 1 7.

7 ~

National Council on Radiation Protection and Measurements (NCRP),

Radiation E

osure from Consumer Products and Miscellaneous

Sources, NCRP

. Report No. 56, 1977.

8.

9.

U.S.

Nuclear Regulatory Commission Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants",

December, 1975.

U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8,,"An Acceptable Radiological Environmental Monitoring Program",

November. 1979.

10. Eisenbudp Merrill,. Environmental Radioactivit,'econd

Edition, Academic

Press, New York, NY 1 7

11. Prancis, C.W.,

Radiostrontium Movement in Soils and U take in Plants.

Environmental Sciences

Division, Oak Ridge 'National Laboratory, U.ST Department of Energy, 1978.

12. Thomas, C.W. et alep Radioactive Pallout from Chinese Nuclear Weapons

Test, September 26, 1976.

BNWL-216 BatteU.e, Pacific Northwest Laboratories, U.S.

ERDA, 1979.

13. Pochin, Edward Eep Estimated Population Exposure from Nuclear Power Production and other Ra iation

Sources, Nuclear Energy

Agency, Organization for Economic Cooperation and Development, 1976.

t

-51 April 1983

REFERENCES (Continued)

14. International Commission on Radiological Protection (ICRP),

R'adionuclide 29, 1979

'5 Glasstone, Samuel and

Jordan, Walter H,

Nuclear Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ill, 1980 16' S

Department of Health, Education, and Welfare.

Radiological Health Handbook.

Bureau of Radiological

Health, Rockville, Maryland 20852 January 1970.

-52 April 1983

Sam le Summaries 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 positive or LLD values where applicable.

These tables are entitled "Environmental Sample Summary" ~

-53 April 1983

ENVIRONHENTAL SAHPLE SUIMRY (1982)

Cladophora Cladophora Cladophora Location Oswego 6.2 mi. 8 235o (control)

NMP 0.3 mi. 8 275o JAF 0.7 mi. 8 68o Be-7 K-40 Co-60 Cs-137 Others Be-7 K-40 Co-60 Cs-137 Others Be-7 K-40 Co-60 Cs-137 Others 0'2 3'

<0.006 Q.QQ7

<LLD 0.21 4.5 0.017 Oo017

<LLD

<0.05 4.3

<0.004 0.011

<LLD

<0.09 2 4

<0.009

<Q.QQ8

'LLD 0.16 3.9

<0.012 0'16

%LD

<0 ~ 12 3 07

<0.012

<0 ~ 010

<LLD Results in units of pCi/g (wet)

ENVIRONMENTAL SAMPLE SU%MY (1982)

Location 3rd uarter 4th uarter.

Dam Shoreline Sediment Lang's Beach Control 5.2 mi 8 230o K-40 Ra-226 Th-232 Sr-90 Co-60 Cs-137 Others 15 0 30 0.48

<0 ~ 0046

<0.047 17 1.GO 0.47

<0.0058

<0.053 0.049 OLD Dam Shoreline Sediment Lang's Beach (extFa) 5.2 mi 8 230o K-40 Ra-226 Th-232 Sr-90 Co-60 Cs-137 Others 12

0. 19 0.18 Oo0043

<0'61

<0.047

%LD Dam Shoreline Sediment N1 fP 0,3 mi 8 275o K-40 Ra-226 Th-232 Sr-90 Co-60 Cs-137 Others 16 0.41 0.56

<0. 016

<0.044

<0.071

<LLD 16 0'6 0.42

<O.OOG8 0.160 0.800 OLD Results in units of pCi/g (dry)

• Sample was not able to be analyzed for Sr-90 because of large sediment particle size.

Sample was recollected as Lang's Beach extra in the third quarter.

ENVlRONMENTAL SAMPLE

SUMMARY

(1982)

Location Pish Oswego (Brown trout)

(control) 6.3 mi 8 235o Fish Oswego (Lake Trout III'1)

Pish Oswego (Lake Trout 42)

Sr-89 Sr-90 Cs-137 K-40 Others Sr-89 Sr-90 Cs-137 K-40 Others Sr-89 Sr-90 Cs-137 K-40 Others

<12.9 42.9 161 ~ 7 10,230.

<LLD 15'

<4.3 136.3 8,120

'LLD 9'

<4.6, 142.8 8,680

'LLD

<12.8

<8.8 159.3 107170

'LLD a1.8 7.4 158. 5 7,925.

<LLD

<16.5.

13.6 181.5 8,250.

<LLD Pish (Brown Trout NHP 0.3 mi 8 315o Sr-89 Sr-90 Cs-137 K-40 Others

<10.4

<4.2 198.4 9,920

'LLD a7.3 a0.6 171.5 11,200

'LLD Fish NMP (Lake Trout 41 Results in units of pCi/kg (dry) ~

Sr-89 Sr-90 Cs-137 K-40 Others

<4.2

<6.7 98.4 6 s270 ~

<LLD

<11 ~ 2 6.1 126.0 7,911.

<LLD

ENVIRONMENTAL SAMPLE SUlRQRY (1982) (cont.)

Fish (cont.)

NHP (Lake Trout f2)

Fish (cont.)

JAP (Brown Trout) 0.6 mi 8 55o Sr-89 Sr-90 Cs-137 K-40 O,thers Sr-89 Sr-90 Cs-137 K-40 Others

<6.6 7.7 153 +0 9,300.

<LLD a0.0

<.8 134 4 8,680 ~

cQ,D a6.4 7 03 141.7 8,050.

~D aG.2

<8.9 194.5 10,643 ~

OLD Pish (cont.)

(Lake Trout Pl)

Fish (cont.)

(Lake Trout 02)

JAF Sr-89 Sr-90 Cs-137 X-40 Others Sr-89 Sr-90 Cs-137 K-40 0 thers

<8 ~ 1 13 3 136.4 7,750

'D

<9 ~ 5

12. 1 156' 10,440.

<LLD 40.1.

<El o3 151.G 7,077.

OLD

<23.7 17 4 110. 2 8$ 100 ~

CLLD Results in units of pCi/kg (dry) ~

ENVIRONMENTAL S&lPLE SVMMARY (1982)

Monthly Water Composite Location Oswego City Water (control) 7.8 mi 8 240o NHP Inlet 0.3 mi 8 305o JAP Inlet 0.5 mi 8 70o K-40 Cs-137 Co-60 Gross Beta K-40 C0-137 Co-60 Gross Beta K-40 Cs-137

, Co-60 Gross Beta as ~ 7

<1.27 a.56 2.91 a5.4

<1.16.

<1.69-2'5 al,6 a+25 a.66 2.96

%8.3

<i+51

<1 78 2.46

<l6.8

<1.43

<i.81 1.93-

%0,9

<l.53

<2.28 2.72 a8.4 a.45 a.76 2.00

<13.7

<2 ~ 11 c1.51 3.46 as.s a.22

<l.61 2'9 4th uarter cl7.3 a.20 a,ss 2.29 a3.6 a.91 a.48 2.64 a5.2

,a.13 a.26 2.36 Results in units of pCilliter.

ENVIRONMENTAL SAMPLE SUt&fARY (1982)

Quar terly Water Composite Location Raw City Water (control) 7.8 mi 8 240o NMP Inlet 0.3 mi 8 305o JAP Inlet 0.5 mi 8 70o Tritium Sr-89 Sr-90 Tritium Sr-89 Sr-90 Tritium Sr-89 Sr-.90 307

<2 ~ 23 5+30 229

<L.36 3.07 311

<0 ~ 72 1.55 123

<0.59

1. 10 202

<0.50 0.50

-247

<0. 60 1.07 112

'0 63 1.01 859

<0 ~ 59 0'7 311

<0. 58 0.72 4th uarter 118

<0.43 0.75 4,620 0.61 0.40 194

<0.40 0 69 Results in units of pCi/liter

ENUIRONMENTAL SAMPLE

SUMMARY

(1982)

Medium/Sam le Location No.

Location 1st Quarter 2nd Quarter 3rd Quarter 4th uarter Airborne Particulate Filters (Gross Beta)

Dl on-site D2 E

F G

H

.I J

K 0.2'i 0.4 mi 0.4 mi 0.5 mi 0.7 mi 0.8 mi 0.8 mi 0.9 mi 0.5 mi 8 69o 8 140o 175o 8 210o 8 25no 71o 980 8 110o 8 132o 0.037 0.038 0.039 0.036 0.035 0.032 0.028 0.032 0.034 0.032 0.032 0.035 0.036 0.033

~ 0.030 0.033 0.031 0.033 0.031 0.038 0.035 0.032 0.029 0.029

. 0.032 0.035 0.029 0.027 0.028 0.029 0.027 0.028 0.027 0.026 0.024 0.026 Airborne Particulate Filters (Gross Seta)

C off-site Dl D2 E

F G

16.0 mi 8 42o 11.4 mi 8 80o 9.0 mi 8 117o 7.2 mi 8 160o 7.7 mi 8 190o 5.3 mi 6 225o 0.037 0.037 0.039 0.036 0.040 0.039 0.033 0.037 0.036 0.032 0.036 0.032 0.030 0.034 0.033 0.034 0.035 0.029 0.027 0.028 0.029 0.029 0.029 0.028 Results in units of PCi/m

ENVIRONMENTAL SM1PLE SUNSRY (1982)

Medium/Sam le Air Particulate Filter Composite Isotopic Location A-1(a)

(off-site)

B 2(b)

(on-site)

Radionuclide Be-7 Ra-226 K-40 Cs-137 Co-60 Mn-54 Ce-144 Nb-95 RU-106 Others Be-7 Ra-226 K-40 Cs-137 Co-60 Mn-54 Ce-144 Nb-95 Ru-106 Others 122

<5.35

<4.11

<0.37

<0 ~ 51

<0.28

~2.03

<0.56

<2.04

<LLD 95

<3.98

<3.18 0.33 0'5

<0.27 1 ~ 53 0.43

<2,32

<LLD 128

<5.39

<5 ~ 52

<Oo59

<0 57

<0.41

<1.54

<1.03

<3.46

%LD 115

<3.90

<3.85

. <0.46

<0.48

<0.29

<1.46

<0 49

<2.47

<LLD 100

<5.04

<5.09

<0.34

<0.43

<0.33

<i+33

<0.48

<2.76

<LLD 85

<2,96 3.03 0 31

<0.32

<0.20

<0 ~ 86

<0.29

<1.75

<LLD 4th uarter 77

<4.46

<4.32

<0.27

<0.38

. <0.26

<1.02

<0+37

<2.24

~ <LLD g6

<3+27

<3 ~ 11

<0.22

<0.32

<0.21

<0 ~ 85

<0.27

<1.77

<LLD Results in units of 10 pCi/m (a) A-1 monthly composite comprised of stations:

C off-site (16.0 mi.

6 42 ), Dl off-site -(ll 4 mi 80o) and D2 off-site (9.0 mi. 8 117o) ~

(b) B-2 monthly composite comprised of stati'ons:

H on-site (0.8 mi.

8 71 ), I on-site (0.8 mi.

8 98 ),

J on-site (0.9 mi. 8 110o) and K on-site (0.5 mi 8 132 ) ~

ENVIRONMENTAL SAMPLE

SUMMARY

(1982) (cont,)

Air Particulate Filter Composite Isotopic (cont.)

Location A-2(c (off-site)

B-1(d)

(on-site)

Be-7 Ra-226 K-40 Cs-137 Co-60 Mn-54 Ce-144 Nb-95 Ru-106 Others Be-7 Ra-226 Z-40 Cs-137 Co-60 Mn-54 Ce-144 Nb-95 Ru-106 Others 120

<5.69

<5 +33

<0.49

<0.49

<Oe35 1.68

<0.58

<2.14

<LLD 113.

<4.00

<3.15 0.34 0.66

<0.27 1.45

<0.60

<2.08

<LLD 119

<5.37

<5.53

<0.37

<0.60

<0.38 168

<0,93

<3.34

<LLD 133

<4.23 3 ~ 17 0,39

<0.40

<0+29 i+77

<0.52

<2.43

<LLD 100

<4.32

<2 ~ 91

<0 ~ 28

<0.37

<0.27

<i+13

<0.40

<2o52

<LLD 104

<3.05

<4.61 0 30

<0 ~ 25

<0.19

<0.81

<0.23

<1 ~ 61

<LLD 75

<4.30 2.87 4.26

<0.35

<0.22

<1.03

<0.34

<2.29

<LLD 71 2.60

<2 ~ 84

<0.18

<0.24

<0.17

<0.73

<0.21

<1 ~ 38

<LLD Results in units of 10 pCi/m3 (c) A-2 monthly composite comprised of stations; E off-site (7.2 mii 8

160 ),

F off-site (7.7 mi 190o) and G off-site (5.3 mii 8 225o).

(d) B-l monthly composite comprised of stations:

Dl on-site (0.2 mi.

8 69 ),

D2 on-site (0.4 mi.

6 140 ),

E on-site (0.4 mi 8 175 ),

F on-site (0.5 mii 8 210 ) and G on-site (0 7 mi 8 250 ) ~

EHVIROHHEHTAL SPILE SUHMARY (1982)

Airborne Charcoal Cartridges (I-131)

Airborne Charcoal Cartridges (I-131)

Location Ho.

Dl on-site D2 E

F G

III J

K C off-site Dl D2 E

F G

Location 0,2 mi 8 69o 0.4 mi 8 140o 0 4 mi 6 175o 0.5 mi 8 210o 0'

mi 8 250o 0.8 mi 8 71o 0'

mi 8 98o 0.9 mi 8 110o 0'

mi 8 132o 16.0 mi 8 42o 11 4 mi 8 80o 9'

mi 8 117o 7'

mi 8, 160o F 7 mi 8 190o 5.3 mi 8 225o

<0.026

<0.021

<0.022

<0.029

<0.020

<0. 017

<0.024

<OA21

<0.018

<0.015

<0. 020

<0.025

<0 026

<0.018

<0.017

<0 ~ 028

<0.028

<0.027

<0'32

<0.024

<0'23

<0 030

<0.021

<0'23

<0.025

<0.027

<0.033

<0.034

<0.018

<0.023

<0. 022

<0. 021

<0.024

<0. 028

<0 ~ 030

<0.017

<0.029

<0.016

<0.021

<0 ~ 019

<0 ~ 020

<0 ~ 025

<0.019

<0 ~ 020

<0.020 4th uarter

<0. 019

<0. 020

<0.022

<0.023

<0.028

<0. 023

<0. 019

<0.029

<0.021

<0 ~ 017

<0. 020

<0.019

<0. 015

<0'17

<0.023 Results in units of pCi/m

~

ENVIRONMENTAL SAHPLE SUHHARY (1982)

Direct Radiation Environmental TLD Location No.

3 4

5 6

7 8

9 10 11 12 13 14 15 18 19 23 24 25 26 27 28 29 30 31 39 43 44 45 46 47 48 49 50 51 Location 0.2 mi 8 69o 0.4 mi 8 140o 0 4 mi 8 175o 0.5 mi 8 210o, 0.7 mi I 250o 16.0 mi I 42o 11.4 mi 8 80o 9.0 mi 8 117o 7'

mi 8 160o 7.7 mi 8 1.90o 5.3 mi 8 225o 12.8 mi 8 225o 0.9 mi 8 238o 0.5 mi 8 268o 1.3 mi 8 81o 0.8 mi 8 71o 0.8 mi I 98o 0.9 mi 8 110o 0.5 mi 6 132o 0.4 mi 8 60o 0,5 mi 8 68o 0.5 mi 8 57o 0 4 mi 8 57o 0.2 mi I 290o 0.1 mi 8 292o 9.4 mi 8 88o 12.6 mi 8 64o 7.6 mi 8 130o 7.9 mi 6 178o 0.6 mi 8 69o 0.8 mi I 92o 20.0 mi I 165o 0.7 mi 8 115o 7.5 m5 8 233o 16.69 15.22 13.86 11.58 12.41 13.72

12. 14 14.37 12.02 12.],4 13.94 13.63 11.52 13.02 13 ~ ]6 15.05 13.64 13.68 12..94 29.08 87.81 122.70 21.04 30.37 94.28 12.74 12.32 13.02 12.71 48.39 14.53

+A 7g LV~ e N 13.45 12.50 37.14 20.28 16.90 16.25 16.97 16.60 18.69 16.28 17.75 14.34 16.23 16.31 13.62 17.06 17,06 27'2 19.99 17.79 17.9?

70.15 126.47 274.07 51.07 32.22 133.16 17.71 16.87 17.69 14].85 21.58 15.03 17.'1 17.53 16.44 3rd uarter 40.74 21.97 17 F 80 18.41 17.74 17.93 17.10 17.04 17.02 15.69 17.81 17.14 13.13 15.87 19.52 27.].8 22.50 19.16 19.00 65.55 166.44 237.15 61.01 36.26 193.46 15.16 17.61 17.43 15'2 159.74 27.48 15.20 16.30 4th uarter 33.92 16.28 16.68 13.38 16.26 17.99 14.96.

15.94 14.28 16.47 15.19

]5.22 12.55 14.38 15.38 24.31 15.75

] 6.11 15.36 48.77 134.20 205.72 42.12 124.74 14.87 14.67 17.76 14.47 122.58 19.73 15.39 14.03

15. 55

ENVIRONtiENTAL SAMPLE

SUMMARY

(1982) (cont.)

Direct Radiation Environmental TLD.

(continued)

Location No.

52 53 54 55 56 57 58'9 60 61 65 Location 5'

mi 8 227o 13.7 mi 8 183o 9.3 mi 8 laso 13.7 mi 8 75o 5.4 mi 8 120o 1 9 mi 8 145o 3.2 mi 8 220o 0'

mi 8 95o 21 0 mi 8 225o 0'

mi 8 83o 7'

mi 8 198o

lle50 12.30 11.35 12.40 12.82 12.86 27'0 16.55 16.12 11.40 16.44 15 52 14o49 14'7 15.83 16.38 117.47 18.28 31+79 15 98 14 ~ 76 17'9 16'3 17'1

. 17+68 16i75 105.14 20.91 36'5 17+22 15.65 15 14 14'4 15,48 14.82 16 41 16'0 59 65 17'8 28.14 14.79 Results in average mrem per quarter.

+TLD lost (vandalism)

ENVIRONMENTAL SPILE

SUMMARY

(1902)

~4/

Location Dose Rate 1st uarter 2nd'arter 3rd uarter 4th uarter Continuous Radiation Monitors C off-site MIN 0.16 mi 8 42o MAX+

AVE.

Dl on-site 0 25 mi 8 69o D2 on-.site 0.40 mi 8 140o E on-site 0.40 mi 8 175o 0

010'.044 0.014 0 ~ 010 0.024 0.014 0.011 0'50 0.015 0.011 0.033 0.015 0'11

'0 019 0.015 0,012 0.060 0,023 0.011 0,063 0+015 0.012 0+072 0+017 0.011 0.026 0.018 0.012 0 F 078 0.023 0.010 0'74 0.015 0.011 0'21 Oi020 0'10 0.028 0.010

0. 010 0.043 0.022' 010 0.070 0.010 0.010 0 F 008 0.016 F on-site 0'0 mi 8 210o G on-site.

0.70 mi 8 250o H on-site 0.80 mi 8 71o I on-site 0.80 mi 8 98o 0.010 0'20 Oo011 0.012 0 031 0.017 0.015 0.053 0.026 0.011 0.044 0.018 0.010 0,032 0,015 0.012 0.060 0.018 0.014 0.076 0,027 0.014 0+084 0.028 0.010 0 054 0.014 0o014 0.050 0.022 0.016 0.086 0.020 0.012 0.095 0,029 0.010

0. 040 0.010 0.013.

0 047 0.023 0.014 0.052 0.024 0.016 0.069 0.027

ENVIRONHENTAL SAHPLE SUH1MY (1982) (cont.)

Location Dose Rate (cont.)

Continuous Radiation Honitors J on-site HINo 0.90 mi 8 110o HAX.

AVE.

K on-site 0 ~ 05 mi 8 132o 0 010 0'46 0.015 0.010 0'57

.0.015 0,015 0+063 0,022 0+011 0'56 0.017 0'll 0'67 0.020 0'll

.0'84 0.015 0 ~ 010 Oi039 0.013 0.010 0'30 0.014 Results in units of mrem per hour.

ENVIRONMENTAL SAMPLE

SUMMARY

(1982)

Medium/Sam le Milk Location 4

7.7. mi I 115o I-131 NS

<0.2

<0'

<0.1 40 control 15.3 mi 8 220o 14 9.8 mi 8 120o 16 5.2 mi I 190o 5

7.2 mi 8 146 7

5.5 mi I 105o 45 8.1 mi 8125o I-131 I-131 I-131 I-131 I-131 I-131 NS NS NS NS NS NS

<0.2

<0.2

<0.2

<0.2

<0.3

<0.3

<0.3

<0.3

<0.2

<0.2

<0.2

<0.1

<0.2

<0.2

<0.2

- <0.1 Sample location not sampled until July 1982 NS Milk samples not collected during the first quarter (not the local graaing season)

Results in units of pCi/liter.

ENVIRONiENTAL SAMPLE

SUMMARY

(1982)

Milk Location 4

7.7 mi 8 115o 40 15.3 mi 8 '220o (control) 14 9.8 mi 8 120o 16 5.2 mi 8 190o 5

7.2 mi 8 146o 7

5.5 mi 8.105o Sr-90 Cs-137 K-40 Others Sx"90 Cs-137 K-40 Others Sr-90 Cs-137 K-40 Others Sr-90 Cs-137 K-40 Others Sr-90 Cs-137 K-40 Others Sr-90 Cs-137 x-40 Others NS NS NS NS NS NS 3.0

<5.5 1500

<LLD

<5.0

<3.6 1400

<LLD

<1.2

<4.8 1400

<LLD 3.7

<4.5 1235

<LLD 4.7

<4.5 1500 4.9

<4.0 1550

<LLD 3.7

<3.4 1367

<LLD

~

3.0

<4.1 1333

<LLD

<8.4

<4.5 1233

<LLD 5.1

<4.9 1400

<LLD 4.9

~.0 1333

<LLD 6.2

<4.5 1400

<LLD 4 '

<3 ~ 7 1467

<LLD

<29. 1

<4.1 1433

<LLD 4.6

<4. 2 1367

<LLD 6.4

<4.4 1200

<LLD

<26.0

<4.4 1233

<LLD 5.5

<4. 2 1333

<LLD 45 B.l mi 8 125o Sr-90 Cs-137 K-40 Others 4.5

<4.1 1200

<LLD 6.3

<4.4 1433

<LLD Sample location not sampled until July l982 NS Milk samples not collected during the first Results in units of pCi/liter.

quarter (not the local grazing season)

ENVIRONMENTAL SAMPLE

SUMMARY

(1982)

Beef Location B control 25 mi 8 22lo K;40 Cs-137 Others 5.9

<0.02

<LLD Beef Pork Beef Beef A

5.2 mi 8 190o D

9' mi I 180o C

4.5 mi 6 147o G control 18 5 mi g 225o K-40 Cs-137 Others K-40 Cs-137 Others K-40 Cs-137 Others K-40 Cs-137 Others 5 2

<0+03

%LD 2.4 0,02

%ID 6+0 0,08

<LLD 2.8

<0,02 Cf,LD Beef E

9 7 mi 8 88o K-40 Cs-137 Others 2.9

<0.01 COLD Beef Beef F

8.0 mi 8 145o H

5.0 mi 6 165o

-K-40 Cs-137 Others K-40 Cs-137 Others 2.5 0.02 CLD 3.5 0.02 OLD NOTE: Sample nnt collected during that quarter Results in units nf pCi/g (wet).

ENVIRONMENTAL SAMPLE SUl&IARY (1982)

Medium/Sam le Eggs Location L control 13.0 mi 8 235o K-40 Cs-137 Others 3+8

<0.02

<LLD 2'

<0'2 OLD Eggs Eggs Eggs Eggs K

2.0 mi 8 105o I

3.6 mi 8 195o J

2 ~ 5 mi 8 160o M

2.0 mi 8 120o K-40 Cs-137 Others K-40 Cs-137 Others K-40 Cs-137 Others K-40 Cs-137 Others 3 t2

<0. 02

<LLD 3 5

<0.02

<f,LD 3+5

<0.04

<LLD 1.4

<0.01

<LLD 1.2

<0 ~ 01 COLD 1.6

<0.02 OLD NOTE: Sample not collected during that quarter.

Results in units of pCi/g (wet) ~

ENVIRONMENTAL SAMpLE SUl9iARY (1982)

Chicken Chicken Chicken Chicken Location L-control 13.0 mi g 235o K

2.0 mi g 105o J

2.5 mi 8 160o I

3.6 mi 8 195o K-40 Cs-137 Others Z-40 Cs-137 Others K-40 Cs-137 Others K-40 Cs-137 Others 5.4

<0.03 8.4

= 0.03

<LLD 6.5

<0.03

<LLD 6'

<0.02

<LLD 4.1

<0,02 OLD 4.2

<0 02 OLD 3,1

<0.02 CLLD Chicken M

2.0 mi 8 120o X-40 Cs-137 Others 3 ~ 6

<0 02 OLD NOTE: Sample not collected during that quat'ter.

Results in units of pCi/g (wet) ~

ENVIRONHENTAL SAHPLE SUF&1ARY (1982)

Location i

Radionuclide Swiss chard (leafy)

T-control.

l 2 5 mi g 225o K-40 Be-7 I-131 C5-137 Others 9.3 0'2

<D.02

<0.01

<LLD Cabbage

( leafy)

Swiss Chard (leafy)

Cabbage

( leaf y)

Tomatoes Tomatoes R

3.7 mi 8 160 Q

2.5 mi 8 150" N

1 ~5mi 8 85o S control 15.5 mi 8 220" R

3.7 mi 6 160o K-40 Be-7 I-131 Cs-137 Others K-40 Be-7 I-131 Cs-137 Other@

K-40 Be-7 I-131 Cs-137 Others K-40 Be-7 I-131 Cs-137 Others K-40 Be-7 I-131 Cs-137 Others 2.4

<0.07

<0 ~ 01

<0.009 OLD 7.4 0 14

<0.02

<0. 01

%LD 1'

<0 04

<0.008

<0.005 Cf LD 2.6

<0 ~ 04

<0.06

<0.004 OLD 1.8

<D. 04

<0.06

<0.004 OLD

ENVIRONMENTAL SAMPLE SU)ÃARY (1982) (cont.)

Medium/Sam le Location Tomatoes Zucchini P

2.0 mi 8 95o N

1.5 mi 8 85o K-40 Be-7 I-131 Cs-137 Others K-40 Be-7 I-131 Cs-137 Others 2.1

<0. 03

<0. 04

<0.003 Cf LD 1+9

<0. 04

<0.10

<0.003 OLD NOTE: Sample not collected during that quarter.

Results in units of pCi/g (wet) ~

TABLE I SAMPLE COLLECTION AND ANALYSIS S TE RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM MEDIA 1.

Fish 2 ~

Cladophora 3.

Lake Water 4.

Sediment ANALYSIS GSA, Sr-89

& Sr-90 GSA GSA H-3, Sr-89, Sr-90 GSA FREQUENCY LOCATIONS (1) 2/yr 2 Onsite In Season 2 Onsite 1 Offsite 1 Offsite M Comp.

Qtr Comp Semi-Annual Dam Shoreline 1 Offsite NOTES:

(1)

Onsite samples collected in the vicinity of discharges, offsite samples collected at a

distance of at least five miles from site.

(2)

The three lake water samples to include Nine Mile Point Unit 1

intake

water, James A..

Fitzpatrick intake water, and Oswego City raw water,

TABLE 2

/

SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MO>ITORING PROGRAM BE TERRESTRIAL PROGRAM MEDIA l.

Air Particulates 2 ~

Soil 3 ~

TLD 4 ~

Radiation Monitors Airborne I-131 6 ~

Milk 7.

1luman Pood Crops 8.

Meat, Poultry, Eggs ANALYSIS GB GSA GSA, Sr-90 Gamma Dose Gamma Dose GSA I-131 GSA, Sr-90 GSA$ I-131 GSA Edible Portions FREQUENCY W

M Comp (4)

Every 3 years Qtro M(5)

M SA N00 OP LOCATIONS At least 10 13 20 At least 7

At least 10 4(5) 3 LOCATIONS 7 Onsite 6 Offsite 7 Onsite 6 Offsite 14 Onsite 6 Offsite 7 Onsite 1 Offsite 7 Onsite 6 Offsite (6)

(6)

(6)

NOTES:

(Cont.)

(4)

Onsite samples counted as two composites.

Offsite samples counted as two composites.

Any high gross beta count samples counted separately (not included in composite).

(5)

Frequency applied only during grazing season.

(6)

Samples to be collected from locations (where available) witin a 10-mile radius having the highest potential concentrations of radionuclides.

I

TABLE 3 CONCENTRATIONS OF GAHHA EMITTERS IN CLADOPHORA SAMPLES Results in units of pCi/g (wet) + '2 sigma Nine Mile Point Be-1 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Ru-103 Cs-134 Cs-137 Ce-141 Ce-144 Ra-226 Th-232 Others Collection Site Nuclides Found June 1982 0.21+0.06 4.5g.4

<0.008

<0. 011.

<0.033 0.017+0.008

<0.022

<0.020

<0.018

<0.014

<0.007 0:017+0.005

<0.022

<0.043

<0.015

<0.024 All<LLD Au ust 19&2 0.1Q-0.08 3.9&.4

<0.009

<0.011

<0.032

<0.012

<0.020

<0.022

<0.019

<0.015

<0.007

0. 016&.007

<0.040

<0.083

<0.019

<0.026 All<LLD J. A. FitzPatrick Be-7 K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 Ru-103 Cs-134 Cs-137 Ce-141 Ce-144 Ra-226 Th-232 Others

<0.05

4. &0.4

<0.003

<0.004

<0.015

<0.004

<0.010

<0.008

<0.008

<0.006

<0.003 0.011+0.003

<0.013

<0.025

<0.006

<0.009 All<LLD

<0.12 3.7+0.4

<0.011

<0.012

<0.035

<0.012

<0.023

<0.023

<0.017

<0.015

<0.008 0.010

<0.020

<0.046

<0.020

<0.031 All<LLD'

TABLE 3 (cont.)

CONCENTRATIONS OF GAMMA EMITTERS IN CLADOPHORA SAMPLES Results in units of pCi/g (wet) + 2 sigma Collection Site Nuclides Found June 1982 Au ust 1982 Oswego Be-7 X-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Nb-95 RQ-103 Cs-134 Cs-137 Ce-141 Ce-144 Ra-226 Th-232 Others 0.12+0.04 3.7+.4

<0.005

<0.006

<0.020

<0.006

<0.014

<0.013

<0.011

<0.008

<0.004 0.007+0.003

<0.012

<0.022

<0.011

<0.015 All<LLD

<0.09 2.4+0.2

<0.008

<0.010

<0.026

<0.009

<0.019

<0.017

<0.014

<0.012

<0.006 0.008

<0.018

<0.036

<0.016

<0.025 All<LLD

7 TABLE 4 CONCENTRATlONS OF SR-90 AHD CAIDIA EN'ITTERS IH SIIORELIHE SEDINMF SANPLES Results In units of pCI/8 (dry) + 2 sIBua Collection Code Collection Date Sr-90 Be-7 X-40 Co-60 Hb-95 Cs-134 Cs "137 Ra-226 Th-232 Others Nine Hile Point 5-26-82 0,0168 + 0,0087 LanBs Beach 7-7-82 Extra Sasple 0.0043 + 0.0022 11-30-82

<0.0068 LanBs Beach 5-26-82 11>>30-82

<0.0058

<0.47

<1.00 4l 48

4) +43 16+16 16 + 1,6 l5+1 5 17 + 1+7 12 + i+2

<0.04

<D.07

<0.04 0.16 + 0.04 +.20

<0.05 0+07 t 0+04 0+41 + 0~08 Ui56 + OilU hli.<LLD 0,80 + 0,08 0,36 + 0 08 U,42 t 0 18 hll<LLV

%,05

<0 07

%.04

<i:+05 0 30 + 0 10 V+48 t 0 13 All<LLD

%,05

<0.07 4.06

<0.07

%.05 4).05 0,19 + 0 09 U 18 + U 09 hll<LLV

<Oo04 0+05 + 0+03 le60 + Ue70 Uo47 + Dell hll<LLV

• Sasple was not able to be analyxed for Sr-90 because at lar8e sediment particle sire.

TABLE SA CORCEIITRATINIS OF hTRONT1NI-89>> AIID -90 NII INl!Ih EIllTTERS 111 F ISII SNIPLES Results

$n Units of PCI(g(wai) i 2 s1gma SNPLE DATE SNPLE TYPE Sr-89 Sr-90 GhHN BllTTERS K-40

)In-54 Co<<58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 Others June 1982 Brown Trout Lake Trout Sl Lake Trout l2 0.004i0.002

<0.002 3.li0.3

<0.003 0.004i0.002 2.5i0.3

<0.003 0.004i0.002 3.610.4 FITZPATRICK

~<0.01

<0.01

<0.007

<O.Q1

<0.009

<0.01

<0.04

<0;03

<0.03

<0.02

<n.an8

<0.01

<0.03

<0.02

<0.03

<0.01 0.048i0.008

<0.007 0.044i0.009

<0.008 0.05ia.al AlI<LLQ All(LLD Al'I <LLD October 1982 Brown Trout Lake Trout Il I.ake Trout t2 Ilhlte Sucker

<o.on4

<0.01

<0.007

<0.006

<0.002

<0.006 0.005i0.004

<0.002 2.9i0.3 2.li0.2 2.5i0.3 3.6i0.4

<o.oag

<o.nl.

<0.008

<0.01

<0.01

<0.02

<0.01

<0.02 IIIIIE 111LE POIIIT

<0.04

<0.03

<0.09

<0.08

<0.01

<0.01

<0.01

<0.02

<0.02

<0.03

<0.03

<Q.03

<0.008 0.053i0.008

<0.008 0.045i0.007

<0.008 0.034i0.007

<0.01 0.039i0.008 AI I<LLD All<LLO AII<LLD Al I<LI.O June 1982 Brown Trout Lake Trout fl Lake Trout l2 0.003i0.002

<0.001 3.2i0.3

<0.002 o.on4io.onl 3.3io.3

<0.002 0.003ia.anl 3.li0.3

<0.01 (n.ol

<0.006

<0.01

<Q.Q1

<0.008

<Q.Q3

<0.04

<0.02

<0.02

<0.01

<0.007

<0.03

<0.03

<0.02

<0.009 0.064i0.008 AI I<LLD (0.009 0.05io.ol All<LLD

<0.005 0.051i0.006 AII<LLO October 1982 Brown Trout Lake Trout tl Lake Trout l2 IIh)te Sucker

<0.005

<Q.003 3.2i0.3

<0.004 0.002i0.002 2.7i0.3

<0.004 0.002i0.002 2.5i0.3

<0.006'O.OQ1 4.5i0.5

<0.01

<0.02

<Q.009

<Q.Q1

<o.'nng

<0'.Ql

<0.02

<0.03

<o.n4

<0.04

<0,04

<0.1

<Q.02

<a.ol

<0.01

<0.02

<0.03

<0.03

<0.03

<O.Q4

<0.01 0.049io.oo9

<O.QOB 0.043i0.007

<Q.009 Q.044i0.008

<0.02 0.06iQ.01 AlI<LLD Al1<LLO Al'I <LI.O All<LLa COIITROL June 1982 Brown Trout Lake Trout tl Lake Trout t2

<O.OO4 Q.013i0.002 3.1i0.3 O.OD5ia,aa2

<0.001 2,8i0.3 0.003i0.002

<0.002 3.1i0.3 osUEao

<Q.nl

<0.02

<0.007

<n.ol

<0.008

<0.01

<0.05

<0.03

<0.04

<0.02

<0'.ann

<Q.al

<0.03

<0.02

<0.02

<0.01 0.049io.oaa

<Q.006 0.047i0.007

<0.008 0.051i0.009 AlI<LLD AI 1<LLD All<I.LD October 1982 Brown Trout Lake Trout fl Lake Trout 12 Mhlte Sucker

<0.004

<0.003 3.0i0.3

<0.009

<o.aa4 o.onzio.aaZ 2'.5io.3

<n.'Qno

<0.005 0.004i0.003 2.5in.3

<0.009

<0.01

<0.002 2.8iQ.3

<Q.Q2

<0.01

<n.ol

<0.01

<0.03

<0.03

<n'.n3

<O.Q3

<Q.l

<0.01

<n.ol

<0.01

<0.02

<0.02

<0.03

<0.02

<0.05

<O.OOB O.O47iO.OOB

<0.007 0.050i0.007

<Q.007 0.055i0.008

<0.01 0.027io.on9 AII<LI.D All<LLD All(LLO AII<LLD

• Sr-89 results are corrected for decay to sample stop date.

ThBLE 58 CONCENTRATIONS Of STRONTIOH-89 6 90 6 GhHHh EHITIERS IN FISH ShHPLES Results lo Volts nf PCI/k8 (dry) + 2 sIBua Sas le Date San le T e

Sr-89>>

Sr-90 X.-40 ChHHh EHITIERS Hn-54 Cn-60 Osage o

cnntrnl)

Cs-134 Cs-137 Others June 1982 Bmus Trnut Lake Trout II Lake Trnut 42

< 12.9 42.9 + 7.6 15.6+5.5

< 4.3 9.2+5.0

< 4.6 10230II023 8120I812 8680f868

< 36r3

< 20,0

< 23.5

< 49.5

< 22r3

< 33,6

< 31 ~ 7

< 18'

< 21r0 161 7+27 I 136.3+19 4

142.8t25.2

< LLD

< LLD

< LLD Octnber 1982 Bmus Trnut eke Trnut II lake Trnut

$ 2

< 12.8

< 11.8

< 16'

< 8.8 7.4I7.3 13'79 9 10170+1017 7925I792 82504825

< 29'

< 25,4

< 29.7

< 33.9

< 34.9

< 39 ~ 6

< 25,8

< 23r1

< 23 F 1 159.3425.4 158.5I23 ~ I 181.5+27 7

< LI.D

< LLD

< OLD NINE HILE POINT 02)

June 1982 Brown Trout Lake Trnut II Lake Trnut l2 Octnber 1982 Brnvn Trnut Lake Trnut ll Lake Trout d2 10 4I5 ~ 3

< 4.2

< 6,6

< 17'

< II&2

< 16r4

<<4.2 6'42' 7.7i4.2

< 10.6 6.1+5.9 7+3+7 1

9920I992 62701627 9300I 930 II200III20 79 1 IK791 8050t805

<< 34.1

<< 18.6

< 16.5

<< 45.5

<< 26.4

<280

<46 5

<22 8

< 20.4

< 63,0

<27 8

< 38.6

< 28.8

< 16,9

< 15.0

< 35.0

<24 3

<27 7

198 4I25. I 98.8II8.4 153.0>IBiO 17Ir5+32 ~ 6 126.0I20r2 141.7+24.8

< LLD

< LLD

< LLD

< LLD

<< LLD

< LLD

<<Sr-89 results are cnrrected fnr decay tn sauple stop date

TABLE 58 (Cont In@cd)

CONCENTRATIONS OF STRONTIUH-89 4 90 d CAIUIA KNITTERS IN FISH SAHPLES Results In Units of PCI/kg (dry) + 2 sfgma Sample Date Sample Type Sr-89>>

Sr-90

~ X-40 J ~ ho FITZPATRICK CAHHA KNITTERS Hn-54 Co-60 Cs-134 Cs-137 Others June 1982 Brown Trout Lake Trout tl Lake Trout l2 10.0'.6

< F 1

< 9+5

< 4,8 86801868 13.345 3

7750(.775 12.146.7 10440tI044

< 30.8

< 21,7

< 27.3

< 47 ~ 6

< 23+2

< 29+0

< 28,0

< 20.5

< 22.9 134.4+23.5 136.4+27iU 156 Gt27 6

< LLD

< LLD

< LLD October 1982 Brown Trout

< 16.2

< 8 9 1064341064 Lake Trout Il

< 40 1

< Zl 3 7077t708 Lake Trout lZ

< 23.7 17 ~ 4+13 ~ 3 8IOOt810 "Sr-89 results are corrected for decay to sample stop date.

<31 2

< 25.3

< 32.1

< 40.4

< 37.1

<356

< 29.7

<256

< 25.0 194+5428 ~ 3 151.6%22.9 310.2+22.4

< LLD

< LLD

< LLD

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 2.78+0 ~61(a) 3.47+0.63(b) 2'2+0 ~69(c) 3 0(HOT 65 2'5+0'0 2 31+0 67 NMP Inlet 2.32+0.58 Raw City 2.54&.59 Water (control) 2,7@.0.59 3.20+0.61 3 1Q.0.72 2.99+0.71 2,77+0.63 1 27+0.59 1 74+0.63 2'8K,62 2.66+0 ~ 69 2 04+0 ~ 65 Station code July August September October November December JAF Inlet 2.74+0.69 NHP Inlet 2.43+0 ~ 67 Raw City 2.0Q-0.65 Water (control) 3.53k 0+74 3.22&.72 2.1@.O.66 2o6%.0.68 4.72+0.79 1 7%-0.63 2+71+0+70 2+40-0+68 1.9%.0.40(d) 3.8940,77 1 7940'9 2.23+0.41 2.47+0.68 2.0(H.0.71 2+39>0,42 (a)

Sample collection dates were 12/31/81 to 1/31/82 (b)

Sample collection dates were I/31/52 to 2/27/83 (c)

Sampl,e collection dates were 2/27/82 to 3/31/82 (d)

Sample collection dates were ll/30/82 to 1/3/83

TABLE 7 CONCENTRATIONS OF TRITIlJM AND STRONTIUM-89 AND STRONTIUM-90 IN LAKE WATER (QUARTER COMPOSITE SAMPLES)

Results in Units of pCi/1 + 2 sigma STATION CODE PERIOD DATE TRITIUM Sr-89 Y

Sr-90 JAF INLET First Quarter Second Quarter Third Quarter Fourth Quarter 12/31/81 to 03/31/82 03/31/82 to 07/02/82 07/02/82 to 10/01/82 10/Ol/82 to Ol/03/83.

311

+ 140 247

+ 120 311

+ 110 194 i 98

<0.722

<0.603

<0.580

<0.396 1.55

+ 0.42 1.07

+ 0.38 0.718+ 0.31 0.691+ 0.31 NMP INLET First Quarter Second Quarter Third Quarter Fourth Quarter 12/31/81 to 03/31/82 03/31/82 to 07/02/82.

07/02/82 to 10/01/82 10/01/82 to 01/03/83 229 X 130 202

+ 120 859 + 120 4620

+ 460

<1. 36

<0.502

<0.592 0.606

+ 0.38 3.07

+ 0.77 0.501+ 0.34 0.67

+ 0.34 0.40

+ 0.30 RAW CITY WATER (Control)

First Quarter Second Quarter Third Quarter Fourth Quarter 12/31/81 to 03/31/82

~

307

+ 140

<2.23 03/31/82 to 07/02/82 123

+ 120

<0.586

'7/02'/82 to 10/01/82 112

+ 110

<0.628 10/01/82 to 01/03/83 118 X

97

<O.c,33 5.30

+ 1.3 1.10

+ 0.37 1.01

+ 0.32 0.75 +=0.32

TABLE 8 CONCENTRATIONS OP GAMMA EMITTERS IN LAKE MATER SAMPLES Results in Units of pCi/I + 2 sigma Station Code Nuclide January Pebruary March April May June OSWEGO CITY WATER (00, CONTROL)

Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 K-40

< 5.04

< 0.-95

< 1.15

< 3.43 1.67

< 1.48

< 1.17 1;38

< 1.15

<12.4

< 4.83' 1.04.

< 1.06

< 2.85 1.40 1 ~ 19

< 1.26 1.56

< 1,20

<15.0

< 7.18

< 1.29

< 1.59

< 5.47

< 3.42

< 2.05

< 1.7

< 3.03 2o 33

<19. 6

< 6.23

< 1.43 1.59

< 5.02

< 2.62

< 1.92

< 1.58

< 3.46

< 1.78

<20.3 5.64

l. 14 1.41 3.60 2.48 1.72 1.30 2.57 1.66

<<17.30 6.73

l. 17 1.53 5.51

< 3.59

<. 2.18

< 1.59 3.32 1.89

<17.40 I

00 Vl NINE MILE POINT (02, INLET)

Ce-144 Cs-134 Cs>>13 I Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 K-40

< 5.10

< 0.95

< 1.10

< 3.92

< 2.14

< 1.48

< 1.14 1.38

< 1.41

<$4.7

< 4.90

< 1.17

< 0.9&

< 3.11 1.63

< 1.21

< 0.99

< 1.96

< 1.64

< 9.7

( 6.85

< 1.27

< 1.4

< 5.17

< 3.25

< 2.41

< 1.59 3+37

< 2.02

<21.7

< 6.35

< 1.41 1.37

< 4.77

< 2.96

< 2.00 1.72

< 3.18

< 1.85 16.9+9.6

6. 43 1.24 1.38 4.61 2.65 1.65 1.45

< 3.16

< 1.66

<15. 9 6.18 1.55 1.53 5.09

3. 16 2.51 1.49

3. 27

< '1.91

<17.6 FITZPATRICK (03, INLET)

Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co.-58 Mn-54 Fe-59 Co-60 K-40

< 3.18

< 0.72 0.43i0.29

< 2.13

< 1.45

< 0.99

< 0.74

< 1.35 1.58i0.56 4.5 ~3.3

< 4.62

< 1.07

< 1.52

< 3.66

< 1.55

1. 29

< 1.46

< 1.92

< 1.03

<11.5

< 6.88

< 1.42

< 1.79

< 4.98

< 3.45

< 2.19

< 1.94

< 3.21 2.37+1.13

<18.7

< 6.91

< 1.42

< 1.69

< 5.16

< 3.83

< 2.13 1.66

< 3.66

< 2.30

<23 '

6.19 1.35 1.41 4.38 2.50 2.02 1.83 3.07 2.26

<21.60 5.82 l.30 1.50 4.59 3.33 2.02 1.49 2.85

2. 27

<17.9

TABLE 8 (cont,)

CONCENI'HA'I'IDNS OP GAMMA EMITTERS IN'AKE WATER SAMPLES

. Results in Units of pCI/I + 2 sigma Station Code Nuclide July August September October November December OSWEGO CITY WATER (QD, CONTROL)

Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 K-40

< 5.97

< 1.07

< 1.47

< 3.92

< 2.64

< 1.84

< 1.13

< 2.15

< 1.50

<18.4

< 6.47

( 1.26

< 1.41

< 3.97 2+32 1.96

.< 1.58

< 2.83

< 1,78.

<16.3

< 6.76 c 1.37

< 1.46

< 4.64' 3;24 c 2.24

< 1.70

< 3.05

< 2.01

<20.5

< 5.79

< 0.917

< 0.996

< 4.31

< 2.43

< 1.32 c 1.07

< 2.28

< 1.26 14.3X8.9

5. 29

1. 07

0. 98 3.22

1. 55

1. 10 1.67 1.76 1.18 14.8+7.9

6. 96 l.47

1. 62

< '5.67

<< 3.29 2 ~ 33

< 1.81

3. 40

2. 20

<22.9 NINE MILE.

POINT (02, INLET)

Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 K-40

< 5.02

< 0.946

< 0.989

< 3.47

< 2.09

< 1.36

1. 16

< 1.98

< 1.20 (14,2

< 6.24

< 1.13 I ~ 62

< 3.97

< 2.08' 1.63

1. 22

< 2.97

< 1.70

<14.4

< 5.63 l ~ l4.

3.72X1.13

< 3.72

< 2.82

< 1.69

< 1.40

< 2.56

< 1.62

<12.4

< 5.83

< 1.11 3.25iO.IO

< 4.20

< 2.42

< 1.34

< 1.02

< 2.27

< 1.20

<11.5

< 4.79 1.03 1.10 3.11

1. 71

l. 11

). 18

< 2.01 c I.ll

<13.1 6.05 1.28 1.39 4.18 2.52 1.89 1.39 2.29 1.62 16.3+8.7 FITZPATRICK (03, INLET)

Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 K-40

< 5.35

< 1.07

1. 26

< 4.12

< 2.11

< 1.46

< 1.25

< 2.47

< 1.67

<14.9

< 5.97

( 1.10 1.21

< 4.26

< 2,30 1.84

( 1.38

( 2.19 1.61+0.78

<15.Q

< 5.71

< 1.16

1. 18

< 4.47

< 2.93 1.70

< 1.31

< 2.62

< 1.54 16.5+2.8

< 5.70

< 1.19 1.27

< 4.43

< 3.07

< 1.53

< 1.28

< 2.6Q

< 1.46

<15.2 4.97 0.96 1.04 2.90 1.87

1. 16 Q.93

< 1.49

< 1.14 14.2+7.9

< 5.97 1.13 1.09 3.54

2. 11

l. 69

l. 22 2.06 1.18

<16.2

TAQLE 0 HHP/JAF t?ITh EHV1ROHHEHTAL AIRbORHE PARTICULATE BAHPLEB - OFF BITE BTATLDHB CROSS OKTA ACTLVLTYTaCL/n"3 4 2 Slane L.OCAT1DH OEEK EHP PATE 82/01r Ds 82/11/13 82/IL/19 BZ/ll/R6 82/12/o3 82/02/4'9 82/12/17 82/12/23 82/03/IZ 82/13/O'9 82/43/16 82/O3/21 BR/03/30 BZ/01/46 BR/01/13 82/01/Za 82/Oh/27 82/45/01 82/DS/12 BZ/15/18 82/05/25 82/06/oaR oo 82/06/08 82/os/is

. 82/o&/22 Bp/D6/zv 82/07/07.

82/07/13

.82/17/24

~ BP/47/Z?

02/08/03 BP/48/1 0 BP/08/t7 82/18/21 82/00/31 82/19/8 82/19/11 82/O'9/P 1 BR/QV/28 82/io/s BZ/10/5 02/10/LV 82r LIrZS 82/11/2 82/li/9 82/1 1/16 82/t 1/23 82ril/3a 82/12/7 82/12/LS 82/12/21 82/12/a20 83/ol/oh C

OFF

1. 032t0. 001 0.030to.ooh I, D31 tD. Dph

0. 012to.ooh 0.039to.oah

0. 039t0. 045 D.osato.eos

0. 030t4

~ 041

0. 03/+4. 041 4.013+0.IDS 0.037to.oph D.olsto.043

0. 0 1Vt0. DD5 4.031tD.DDI.

D.ossta.aas 0.032io F 041 1.01/t4.005 0.0&3to.Q06

0. 03&to. 4DS I. IZV to. 005 I ~ 02?tO. 041 1.023t0.003

0. 021+0. 441

0. 02Pto. IDI

" 0.02hto.oDI D.DLV+D.QD3

0. 431 to. 1 01 0.032t4.405 0.029to.oah D.aaZsto.oah I. Ia37t4. OPI O.OZVto:OOI 0.02?t4.045 0.020to.ooh 0.0'22t0.043 D.DIDta.Ioh D.Q55ta.oas 0.41Vt0.003 0.021to.oah

0. Dbh to. 403

o. Dhat 0. Dah 0 't7<o.oah 0.025t4.001 D. DIZt0. 005 0.02&tO.Oah 1.015to.aa3 0.03hto.ooh 4.423t0.443 0.027t4.041 P. 432t0. Dph 0.419+0.401 4.02bta.oah

4. 423ta. 0 01

+ I'UHP HQE QPERhT10HhL Dl-OFF 0.036+0.001 0.012to.oah 1.03&to.40S

0. ahl t0. 0 45 D. DID+I.DDI O.ohoto.PDS

0. 051+0. 0QS 1.027to.oah 0.435+0.ODI

0. 011+0. 015

0. 036 t0. 041 I'.OLBt0.003

~.432t0..047 0 ~ 057+0.DDS.

~.030to. ~ Ds 0.153to. 006 0.0?ltD.DQS

0. 013 t D. ID S I.IR6+ ~.IDS 0.030to. Ioh 4.02Z+0.041 0.423to.oah

~.o32+D.oas

0. 03Dto. DOI I. 023 to. 001

'.012ta.oah 0.42'Vto.aas I ~ ohat0.405 0.036to.oaS

0. 025t 0. Oah I. 125ta. 4D6

$.033ta.oos

~.020tD.DOI

0. 028to. 001 0.060t4.005 I. ISO tD. IDS

~. 022ta. 401 4.02V+0.041 4.025to.ooh 0.454ta.oos D.alhto 041

4. 1RV+D. 001 0.039to.oah 4.42bt4.041 D.OLbta.oa3 4.035+0.oah 0.022t0,003

1. 031t a. 041 0.033ta.aah 0.023t0.041

4. 12aZt 0. 0 03 D.otvta.043 I.131t4:445 D.ohl+o.aos 0.036tP.IIS D.ohato.oos

~. Ihsta. 405 0.111+D aood D.oslto.las D.ozvto,aas 0.131ta:405 I.ohsto.045 0.03&11.oos I IZht0.401 D.ohbgo.aob

o. 031t a. Dos 0.057to.oob 0.03hto.oaS 0,050+0.aob 0.'O63tO.OO?

O.ohhta.106

0. Qh Bto.047 0.02&to.006

l. IZLt0. 101 1.016to. 04S 0.02?tO.IOS

0. Oa21+0. 045 0,02ato.oDS 0.033to.oas 4.02&to. IP6

1. 13Ltl. 045 4.03?ta.006 1.02ht4.105 0.031tD.446 0.03ot0.446 D.osato.DOS 1.419ta.ooh 0.052ta 40S 4.150+0.DDS 0.420to.oa3 1.429to.DDI 0'.aZi?ta.ooh O.OShta.045 O.atste.aoh 0.43hto.aah 0.013to Das 0.025t 0.011

1. 0 17t 0. 003 0.039tD.DDI 0,121tD.'113 0.120ta. ~ 01

'.031<4.aoh I. 0LVI 0. Qoh 4.421t4.003 4.17at4.003 E.OFF I a 431 t0. 045

0. 031to. 005.

D.e3sto.'Dob 0.037+0.015

0. 013 t Q. 0 1 S 0.030to. IOS O.IIBta'.OIS

0. IZSt0. 005 0.037to.ooS O. Ihlt4. DD6

0. 031 to.

DOS D.DPoto.oah

0. IIIto. 047 0.022to.ooS 0.058to.oa?

0.035to.oab 0.035to.023

0. Dshto. 046 4.01StD.DOB 0.021 to.oas 0.0<?to.oas 0.025t4.005 0.010/4.005 0.030ta.aos 0.122ta.DDI o.alBto.oah D. 037+0. ODS O.DRVt0.405 0.032to.oes 0.032to.eaS

~. 030 t D. 041 O.DRVta.aoh 0.435to.oas 0.034tO.OOI 0.022tO.OOI 0.463to. DQS 1.'152t0.006

0. IRSt D. 0 01 D. D20t0. Qoh O.O3atO.OOI Q,051ta.045 D.otsta.oah

0. 032tD.DDS

0. 112 to. 445

0. 021to. 401

0. 018t 0. 401

0. 035t Q. 011 D. 02iZtD. QD3 O. O3O t O. OOI 0.03ato.pah o.azota'.oah D.ea23ta.103 Q.ol?Dta.aah F

OFF

~ ~ 033 to.

~Ih Q ~ PIZtQ.Q41 4.113to.DDS

0. 013tD.IDS I.I1 1 tI. IDh

1. 011+0. 045

0. 05'9 t 0. Ias 0.029to.ooh 0.036tD F 01 0.05ltD.Das 0.031tO.DOI I.IZZtI. 4 03 1.053to.aQ5 0.03Sto.aah 0.059t0.005

o. Dha+0. eas D.052to.oaS D. 051 t 1. 0 1 S 0.017t 0.005

0. 025tD.DDI o.aZBta.ooh

~.Q72t0.143 QZ1t 0. 001 0.029+4.ooh

0. 028to. IDI D.D27to.oah O. 031 tI. 4 01 0.120ta.e41 0.13htD.QOI 0.035+0.141 D.O3OtO.OOI 0.432<4.aah

4. 03ato. 001 1.027tD.041 P.023ta.143 0.170to.oaS

a. 019+o. ~ os I 021to 101

0. D31 t Q. D0 1 0.131t1.401 0.151+1.045 0.117to.aah

0. 033t 1.001 0.012ta.oaS 075 t D. 441

0. 010t 0. D03

0. D3&to.aah

0. 127t D. 003 O. D26ta. 101 D.DZBt0.403 4.010tl.aph a.ozhto.o43 1.023ta,DOI C-DFF 0.035to.aos

0. 033 t0. ODI I.ah?ta.QI6 I 115to.oos 1.017te.oos 0.430to.aob

0. 417to. ODS I.az?to.oos 0

011 to DDS D.O39to.oos 0 43Sta DOS Q. 022/0. Ioh 1.053t4.046 1.43tta.oo&

0.057te.ooS

1. aha t0. 005 1.'ahhto.oab 0.052to.aas o.o3ota.ooh

0. 023t 0. DDI 1.02?ta.aDI D.QZLta.o03 I.DZato.441 0,022ta.oah a.aioto.4os 1 QLVte 001 I. 025ta.aah D.allto.103 O. D21 ta. 001 Q. 02sta.oah 0.023ta.oah

0. 027ta. 041 D.azbta.oah Q.OZzto.ooh 0.02ato.ooh 0.053ta.aa&

I.QSVto.a08 0.026to.o4s D.D32to.oa6 4.02?tD.DDS I. 016'. 016 o.atste.oes D.ozhlo.oas Q. D13 t o. 114 D.QZZia.pos 0.019to.oos

0. 031ta. 406 Q.ozhto.003 D.a'aUta.aOI 4.13ata.aoh 0, QLOl 4. Doh o.oZuto.aoh

1. Da?2 t 0. 443

TABLE 10 llNP/JAF BITE ENVIRONNENTAL AIRBORNE PARTICULATE SANPLES OH BITE STATIONS CROSS iaETA ACTIVITY pCI/n 3 i 2 Signa LOCATION MEEK EHD BATE 82/I I/04 Baa/Il/18 SR/Il/18 SR/pl/25 88/d2/08 82/Oia/08 Ba/12/16 82/48/2P.

Bar43/ol 88/d3/OO BB/43/ls 88/13/28 Bar03/a9 82/Ih/05 88/04/18 Oa/04/19 82/Oh/26 82/15/03 82/45/Il Ba/Isrt?

88/IS/24 88/d&/01 82/06/D7 82/46/lh Ba/lb/81 88/I&/28 82/47/06 BB/47/18 88/07/19 88/17/26 82/48/08 82/08/49 82/48/Ih BB/08/23, Ba/DO/3o SB/49/07 OB/49/13 88/19/24 82/19/27 82/10/4 82/14/12 Ba/la/IB 88/10/25 82/tI/I 88/Il/8 OB/11/I5 Oa/I llaa Oia/I I/29 82/12/6 OB/18/I 4 88/18/24 82/12/27 83/01/03 Ol-OH 0.133to.IPL

~.044t4

~ 445 4.436t4. ID7 0.043t0.04&

0.042+0.IOS I.Dhsi4.00l

0. P hsio. 106 0.12?tl.406

0. ~ 44tO

~ 006

4. ~hoto. 406 I ~ 13hil.ld6 0.014t0.005 0 ~ Dhata. ~ 4L D ~ l3lio ~ 106

4. ~43to.los o.o&0to.aaa O.lsato.005 0 ~ 4hbio. IOS o.daaid.ssh a.034to.ods 0.016t0.403 0.41&to.ooi 0.028to. 144 0.424t0.104

0. 419ta. 404 4 ~ 03ato. 004 0 ~ 42?t4.045 0 '35i4.445 0.024t0.404 4 '

?id F 004 0.03lto.104 4.03ot4

~ 144 4 'R6t4 F 404

0. 082i0. 1 13 4.187t0.113 4.450to.oas 0.03tt0.004

0. 13314. 1 04 4

~ Oalil ~ 103 0.03hto. 044 D.ol?ta.so3 0.01?io.oas

0. Ohsto. 405 0.024t0.004

0. Dast4. ID3 0.032i0.444 0*035to ~ 104 I.D27ta.003 4.PR&t4.403 0.028t0.004 O.OROt0.103

0. 018to. OD3 OR-OH

~.436t4. F 05

~. 03hiP

. OIS 0.033ta.Ooa

~. 049t0. 046 I Ohsil-005 0.039t0.00&

0.44?t4. Ias D.shits.oea 0.04ltD.IDS S.O3StO.OOS 0.038t0.005

0. 0lbio. 004

~.43?tD. ~ OS 0.028t0.004 I ~ 057t4.445 I.ah3+O.OOS

~.Isato.446 I. 1st+0. ROL I.oastD.d03 I. 127t 0. 005 1.43ot4.04s I.oaoio.odh I. OIL to. Doh

0. OahiO. 104 023i4 004 I.D20i0.104 1.032t0.0 ~ 4 4.03tt0.005 I.aa?ta.oos 1.024t1.4 '

~.028io.oDS

0. 113to. 008 1.03hio.aos 4.0a9ta.Doh 0.025t0.004 l.032i0.044 S.DS?tO.DOB I Ii9i4.404

~ ~ 437iI. DDS

~.030io F 004

~.03hi0.004 I. D 19td. 004 I.019to. 144 D.ohbta.aas 1.424t4.004 I.oalio.Po3 I. D38t0. 144 1.035t0.444 I.oasto.014

4. I &t0.404 I.oahto.044

0. lait 1. 403 0.017td. ~ 43

• PUNP NOT OPERATIOHhL E

OH

~.43&ta-Ods 0.039t0.004 4.138tl F 005 0.45it0.405 4'.O38tO.OOh d.Dhst4.046 1.04otd.aos 4 ~ 133t0. 005 4-045t4.005

~.040tI.OPS

~.439t0.005 0.01&to.d44 1.442t0.005 D.S30ta.004 IaIS'3tO.OPL 0.045t4.0DS 4 ~ 170to

~ 007 I.DShtO.OOL

~.146+0.40S I.Oaa8ia.oas

~. 431t I. 405

~.019t4.004

0. 014 tI. 004 I.4aot4. 104 D.083t4.IDh D. 121to. IDh

~.033t0.404

~. 031 t0. 045

~.132t4.10S

~.028tD.IOS

~.42810.404 0.058t4.016 1.03at0.044 D.labt0.004 0.023t0.004

~.433t0.004 0.44?tl.446 4.030i4.004 1.454io.oOS 1.086+4.444 0.03ats.oos 0.124+4.40S

4. 083 to. 404 s.ssots.opb 4.425ta.oah

~.424+0.104

~. 135to. 104

. ~. 13& t P. 004 I ~ 033to

~ 004 O.'Da3iD'.aoh

0. 02Sio. 045 D.017i0.404 0.015f0.003 F"-OH

~.033i1.406 4.037td.DOS 0.433t4.406 0.04ht0.006 0.147t4.006 D.s38to.ao?

4.149t0.406 0.423tO.DOL 0.042t0.006 0.438t0.00&

4.43?ta.oab I.D12to.oas, 0.041+0.008

4. 430to. OOS I.as?to.aos 0.4hbi0.14S 0.463to.eo7 I. ~Lhto.al ~.

4. ~ hat4.045 I.aaht4.006 4.030to.oob 4.D2&tD.OOS I.415td. 005 4.487i0.04S 0.027+0.OOS 0.419t4.004 o.433ia.aos

~.43lto.oaa 0.035t0.006 4.423t0.045

0. 13DtI. 015 I 435i4 ~ OOS

0. 035t1. 04S 4.43ato.oas 0.423tO.D04 0.028t4.004

~ ~ 4hltD.ODL I ~ 028ta

~ 045 4.135io. ~ OS, I.dalta.444

~

0.03tt0.045

~.Paeil.DPS.

o.oahts.sos I. 150 t4. 006 1.024+4 ODS

4. 0 IOil. 404 0.43ht4.11S 0.135ia.045 4.024+0.OOS 0.027t4.405 0.120+0.oos P.019ta.aah 0.01&to.odh C

OH O. IBSie. 0lh 0.432+4.044 o.oaa+a.ooh 0.044t4.4DS

~.044+0.004

~.sit+0.eaa 4.44&t4 445

0. 13174. DOS 0.038t0.445 I.Ditto.oas O. 441+0. DOS 0.41?ta.d04 D.Ohote.aos

0. 031 t a. 045 4.449+0.OPS

~. 443+1. 445

4. Ibi+O. OD&

D.isatD.DP&

).Istia.ods I.ot'9+ ~.004 0.025+D.4DS

0. 017t0. 014 0; 417tl. D 0 4 D.oaato.oah 0.119t0.044 a.019+o.oos 0.030+0.405

4. 431td. 007 I ~ Oaa?+0

~ aaa O.oalta.dos 4.43iata.aaa

~.saoto.oes I.d3Dto.ooa I. 428io. 0 DS 0 Oahto.044 0.02&to.oos

~.ISO+I.OD?

s.saaio.oss

~.129'005 s.saata.aos 0.133t0.105 0.017ta.oDS 0.02btO.OOS o.oho+a.oea D.eatto.aos 4.480+0.014

a. p31td. DDS 0.143ia.od&

O.ha&to.oes I.aasto.oah

0. Iaaht0. 0 06 S.018+0.DOh O.QRata.ods H

OH 0.43&t0.444 0.03htP.004

'0.137i0.015 O.D4&ta.oda O.OI?tO.003 0.143tD.ODS 0 ~ lsat0.444 4 '3lt4.104 4.038I4.004 D.ohat4.004 4.43?ib.aoh 0.018t4.003 o.o34+a'.ooh 0.030ta.oah O-OSDto.oas 4.0htio.ooh o.oh?to.oas 0.145i4.005 a.oh&to.ash 0.423t0.004

'.025t0.004 0.116t0.403

0. Ilhta. 003 0.019ia.a03 0 421+0.443

0. 019t0. 043 4.039t0.404 o.oa?ta.ooh 0.43?to. ~ 45 0.020+0.003 o.oah+o'.Da3 0.430t0.003 0 ~ 031iO. 404 0.03ltd.113 0.02St0.443 0.03ht0.404 O.D48to.aab a.Oasto.oos 0 '4lt0.043 D.O ltO.Oah 0.03hto.DDS D. 01/ta. 405 0.02hto.ooS DaDhht0.046 o.oaata.oos 0.024ta.ads 4 ~ 437to

~ Ols D.o3&io.ooh O.DROta.dah 0.025+D.ODh o.'Iao+o'.ooh 0.020to.aah D.aaata.aah I--ON

'.42'Pt0.006 0.029to.IOS D.aast0.406 I. ~ 19to.DDh 0.003t4.003 D.406t4.104 0.452t0.4D&

o. 023tl. IDs

0. 136io. 005 0.038td.006 4.131tD ~ 005

0. IISt I. 004 0.448t4.406 o.o3tta.sas-0.458ta.oa?

a. 443tl. DOL o.obata.'eo&

4 ~ 052iO

~ OP&

D.444ta. IOS D.oahtO.Dps 4.128+ ~.IPS a.It&+a.eoh D.DIDt4.404 0.02tt0.105 0.023tI.IPS 1.023ta.s04 4.435+4.DOS I. 433 to. 006 0.131+0.005 O.P21td.004 0.02'Pta.

~ 45 0.474+4 407 0.4aaat4.105

0. 027t 0. ID&

4.034+4.405 o.aha+o.ooh O.Dlst0.104 D.427ta.004 0.030ta.oPq 4.019t4.403 0.437t0.444

0. IibtO. 4D3 1,430+0.404 D.4hlt0.005 O.IPh+0.404 D. 120+4. 043 I. 134+4. 004 D.a3 tD.aah 0.4 sto.aah

~.120ta. ~ 03 O. ~ 1&tl.oPh 4 '2atO

~ DD3 0

~ IOta 003 J"-ON

~.03&to.aas

~.ORBtO.OO3 I D19to Dah 4.442t0.004 P.oasto.003 D.ahtta.aaS 0.449t0.005 D 'R&+0.104 D.othto.)03 P.dhhto.has 0.03htD.D04 D. 014to. 0D3 1.047to.las

~.a3ato.aah I.DSI+4.005 I.D42+0.005 1.058td.aaS

~.047+0.DOS 0.04?to.405 o.oas+o.oah 0.02btd.044 0.017+4.403

4. Dl&td. 404 I.019tD. 403 D.atst4.043 D.alst0.003 0.435t0.443 O.D34tO.IDh D.D27+0.404 P.PI9tO.D43 D.oiabta.403 D.o?7+o.aos 1.037+0.044 I.035ia.adh 0.027ta.a03

~.023ta.403 0.153tD.406 0.036ta.alS 0.032tO.POS O.oal+o.aos O.P26tO.DOS D.alhto.044 D.Pal+0.005 0.038td. 445 D.D19t0.444 4.01?taaaah 0.031ta.44s o.a38ta.ooh 0.02ht0.003 0.025to.ad'3 1.423ta.oo4 0.020+0.OP3 4.021+0.404 K""ON

4. a3aio. ~ 44 I. D3/ta. 044 1.033t0.005

l. Obit 0. 015 1.033t0.014

~. 0 42io. 4DL 0.437+4.045 0.420te.oD4 I:ah +a.oas 1.036+0.014 4.028to.aDh I. 014to. 044 1.443t0.00S 4.030+4.405 1.054'045 I. Ohsid. 015

.I. D52t0. 045

~.045tl.aDS 0.048t0.145 1.025t4.00S 1.43it4.00S I. P I&+1.403 O.OIBta.oah

~.D2ltl.ooh 1.02etD.PP4 1.015+0.043 1.03ito.odh 1.027+0.044 D.D31to.oas 1.019ta.odh 4.029+0.004 O.ahs+0.005 4.028+0.404 1.02&ta.aah 4.022to.403 1.044+0.PD4 P.D37+4.045 D.oa?to.oe4 I. 015t 4. PP 4 4.025to.aos 1.039to.dab I. 012tl. 044 I.OIOt4.043 I 037to 004 I. D21t1.4Di l.aaaja.oo3 I.0~9+a.aah

~.43&10.aah I.ORS+0.004 4.03atD.DDh 0.425td.doh 0"Ot4 403

~ pts<a 003

TABLE ll CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES Results in units of 10" pCi/m

+ 2 sigma Nuclides Januar Februar March A ril June OFF-SITE COMPSITE:

A-.l Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226

<0.24

<0. 19

<0.16

<0.26 0.50 + 0;25

<0.59

<0.39 1.78 + 0.59

<2.23

<0.33 115 + 6 2.67 + 1.86

<0.88

<3.66 0.66 + 0.29 0.23 + 0.15

<0.28 0.38 + 0.20

<0.56

<1.04

<0.44 2.3Q + 0.83

<3.49

<0.37 139+ 7

<3.78

<0.92

<6.08

<0. 63

<0.42

<0.40

<0.46

<0.61

<l.09

<0.54 2.00 + 1.12

<Q.4Q

<0.53 111 + 7

<5319

<1.41

<6.32

<0.77

<0. 65

<0.48 0.93 +

<2.04

<2.11

<1.92 1.69 +

<5.17 a.42 148 + 12

<6. 35

<30.2

<6.78

<0.45

<0 33

%.24 0.48 0.52 + 0.21

<0.54

<0.79

<0.41 0.97 1.54 + 0.72

<2.61

<0.34 121+

6'.26 + 2.71

<0.78

<4.73

<0. 50

<0.24

<0.27

<0,32

<0.51

<0.71

<0.49

<1.40

<2.61

<0.38 114 +'7

<3.96

<1.59

<4.66 ON-SITE COMPSITE:

B-2 Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-1Q6 Ru-1Q3 Be-7 K-40 La-140

.Ra-226 0.44 + 0.17

<0.19

<0.14 0.29 + 0.3.5 0.47 + 0.21

<0.50

<0.30 1.63 + 0.65

<1.50

<0.27 68+4 2.12 +1.50

<0.78

<2.84 0.77 +

<0.25

<0. 20 0.39 +

0.47 +

<0.66

<0 ~ 32 1.45 +

<2.73

<0.28 119+

6

<2.81

<0.61

<4.17 0.25

0. 15 0.23 0.49 0.44 + 0.22

<0.37

<0.31 0.30 + 0.19 0.36 + 0.27

<0.83

<0.43 1.51 + 0.61

<2.72

<0.39 97+ 5

<4.61

<1.32

<4.94

<0.45

<0.35

<0.25 0.67 +

<0.68

<0.97

<0.61 2.34 +

<3.06

<0.50 155 + 8

<4.29

<3 73

<4.26 0.60 + 0.24

<0.24

<0.18 0.29 0.44 + 0.18

<0.40

<0.62

<0.34 0.73 0.96 + 0.47

<1.95

. <0.29 98+

5

<3.82

- <0.84

<3 ~ 52

<0.39

<0. 28

<0.25

<0. 28

<0.40

<0.75

<0.35

<1 ~ 09

<2.40

<0.32 92+

5

<3.44

<1.30

<3.93

TABLE 11 (Cont.)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES Results in units of 10 pCi/m

+ 2 sigme Nuclides Jul Au ust Se tember October November December OFF-SITE COMPSITE:

A-2 Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K Ls-140 Ra-226

<0.47

<0.37

<0.25

<0.35

<0.50

<0.96

<0.48

<1. 23

<2.82

<0.38 115 + 6

<4.7X

<1. 82

<4.33

<0.36

<0.24

<D.27 0.23

<0.34

<0. 62

<0.37

<1.15

<2.56

<0.30 108 +

<0.42

<0 ~ 75

<4.59

+ 0.13

<0. 28

<0. 21

<0.20

<0.26

<0. 37

<0.60

<D.36

<1.01

<2.19

<0. 30 78+5

<3. 58

<0. 82

<4.05

<0.43

<0.34

<0.28

<0.36

<0.46

<0.89

<0.41

<1.12

<2.55

<0. 36 61+ 5 2.50 +

<1. 10

<4.62

<0.37

<0.18

<0,26

<0.27

<0 32

<0. 69

<0.40

<1.04

<2.12

<0.30 76+5 2.05 2.60 + 1.76

<0. 92

<4.62

<0. 26

<0. 14

<0.18 0.16 + 0.10

<Oe 23

<0. 57

<0.36

<0. 94

<2.20

<D ~ 23 89+ 5 3.52 + 1.89

<0.69

<3.67 ON-SITE COMPSITEt B-l, Co-60 Mn-54 CG-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 0.26

<0.22

<0.16 0.36

<0.24

<0.39

<0. 26 0.90

<1.81

<0. 22 128 +

4.57

<0.70

<3.13

+ 0.14

+ 0'2

0. 37 5

+ 1.68

<0. 20

<0. 18

<0. 17 0.41

<0. 23

<0. 50

<0. 28

<0. 85

<1.82

<0. 20 109 +

<3. 2X

<0. 56

<3.34

+ 0.15 0.28 + 0,11

<0.16

<0.14 0.12 + 0.08

<D. 22

<0 ~ 32

<0. 25

<D. 68

<l.21

<0. 15 76+4 6.01 + 1.90

<0.62

<2.69

<0.25

<0.20

<0,17

<0.18

<0.23

<0.44

<0. 27

<0. 77

<1.40

<0. 22 58+ 3 3.10 +

<0.58 4.14 +

<0.28

<0.18

<0.16

<0. 18

<0 ~ 23

<0.47

<0. 25

<0. 75

<1.51

<0 ~ 22

-76 + 4 1.58 <2.61

<0.48 1.94 1.83 + 1.21

<0. 18

<0. 14 e.14 0.18 + 0.11

<0.18

<0.38

<0.27

<0. 68 a.24

<0.19 80+ 4 2.82 + 1.57

<Oo72 1.84 + 1.19

TABLE ll (Cont.)

CONCENTRATIONS OF GAMMA EHITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAHPLES Results in units of 10" pCilm3 + 2 sigma NuclMes Januar Fehruar March A ril May June OFF-SITE COMPSITE:

A-2 Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226 0.39 +

<0.25

<0.26 0.37 +

Q.45 +

<0.74

<0.43 1.18 +

<2. 32

<0. 38 113+

6

<4.06

<1.32

<3.98 0.20

0. 16 0.25 0.49

<0.45

<0.31

<0.37 0.48 0.5&

<0. 8Q

<0. 46 2.45

<3.69

<0. 38 135 +.

<5. 26

<0.77

<5.98

+ 0.26

+ 0.31

+ 0.99

<0. 63

<0.50

<0.39

<0.61

<0 ~71

<1 22

<Q.6Q 1.42 + 0.72

<0.40

<0.55 ill+ 7

<6'6 a.48

<7.12

<0.71

<0. 49

<0.38 0.37 + 0.22 a.&4

<2.20

<1.74 2.04 + 0.?8

<4.76

<1. 28 124 +ll

<6.46

'23.00

<6. 28 0.59

<0.34

%.26

0. 46

<0.48

<0.86

<0.44 1 33

<2.74

<0.42 126 +

3.96

<1 ~ 22

<4.72

+ 0.25 0.21

+ Q.56 7

+ 2.46

<0.49

<0+31

<0.28

<0.28

<0,47

<0. 79

<0.49 1.67 +

<2.53

<0.43 106 +

6. 17

<1. 25 5.10 0.92 7

+ 2.46

+ 2.35 ON-SITE COMPSITE:

B-1.

Co-60 Hn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 RU-106

. Ru-103

,Be-7 K-40 Ia-140 Ra-226 0.34 +

0.20 +

<0.16 0.16 +

0;68 +

<0.49

<0. 33 1.40 +

<1. 44

<0.25 92+5 1.68 +

<1.20

<3.00

0. 13 0.11 0.09 0.24 0.50 0.13 0.68

<0.25

<0. 18 0.38 0.53

<0. 63

<0.34 1.91 2.01

<0.24 139 +

<2.8%

<0. 22

<4.34

+ 0.23

+ 0.14

+ 0.21

+ 0.58

+ 1.01 0.95

<0.37

<0.27 0.48

<0.58

<0. 90

%.45 1.03

<2.78

<0.36 107 +

4.94

<1.15

<4.65

+ 0.34

+ 0.23

+ 0.51 6

+ 2.76

<0.42

<0. 32

<0.27 0.65 0.75

<0.98

<0.60 2.95

<2.89

<0. 39 180 +

3.91

<2. 32

<4.44

+ 0.23

+ 0.37

+ 0.80 8

+ 2.57

<0.35

<0.25

<0.21 Q.26 0.20

<0.54

<0.30 1.22

<2.18

<0. 26 108 +

2.99

<0. 75

<3.72

+ 0.13

~

+ 0.14

+ 0.46 5

+ 1.63

<0.42

<0. 30

<0.27 0.27

<Q.60

<0.71

<0.37 1,14

<2'2

<0.30 ill+

2.62

<1 ~ 18

<4.52

+ 0.18

+ 0.45 5

+ 1.83

TABLE 11 (Cont.)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OR NMP AIR PARTICULATE SAMPLES Results in units of 10 PCi/m

+ 2 sigma Nuclides Jul Au ust Se tember October OFR-SITE COMPSITE:

A-1 November December Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 RU-103 Be-7 K-40 La-140 Ra-226

<0. 57

<0.42

%.35

<0.44

<<D.58

<1.03

<<D ~ 52

<1.48

<3.39

<0. 48 123 +

<6.43

<1. 65 5.46 + 2.52

<0.48

<0. 40

<<0. 33 0.36 +

<0.54

<0. 85

<<0.49

<1.60

<2.90

<0.45 109 + 6

<4. 91

<1.10

<6.03

<0.25

<0.16

<<0.16 0.21 <0.22

<<D. 33

<0. 51

<0.34

<0. 90

<1.99

<0. 22 69+ 4 3.93 + 1.68

<0. 88

<3.62

<0.36

<0.31

<0.25

<<D. 28

<0.42

<0.75

<0.36

<l.13

<2.57

<0 ~ 35 61+4

<4.24

<l.21

<4.17

<0.47

<0.31

<0.29

<<0.32

<0.42

<0.74

<0.42

<1.14

<2.58

<0 ~ 33 80+5

<5.Y2

<1.03

<4.52

<0.32

<0.17

<<0.17

<0.21

<<0.26

<0.49

<0 32

<0. 79

<1.57

<0.24 89+5 3.30 + 1.85

<0. 62 4.68 + 2.48 ON-SITE COMPSITE:

B-2 Co-60 Mn-54 Cs-134 Cs-137 Nb-95 Zr-95 Ce-141 Ce-144 Ru-106 Ru-103 Be-7 K-40 La-140 Ra-226

<0.37

<0. 23

<<D. 20 0.35 + 0.12

.<<0.36

<0. 60

<<0.33

<0. 96

<2. 20 (0. 28 116+ 5 4.04 + 1.89

<1.02

<3.49

<0. 28

<<0.19

<<0.18 0.38 +

<<0.24

<<0.42

<<0. 27

<0. 85

<1.53

<<0. 23 86+

4'.09 +

<0.62

<3o 27

<0.30

<0.18

<<D.17 0.13 0.20 + 0.3,1

<0. 28

<0. 58

<<0. 29

<0. 78

<1.51

<0. 25 54+ 4 1.20 2.95 + 1.59

<0.70 2.11 + l.23

<0.39

<0.25

<0. 23

<0.24

<0.34

<0. 56

<0.34

<0. 93

<2.01

<0.26 56+ 4

<336

<1.09

<3. 67

<0.29

<0.21

<0.18

<0.22 0.22 + 0.19

<0.42

<0.32

<0. 86

<3..78

<0.26 66+ 4

<0.27

<0.18

<0 ~ 16

<0.21

<0.25

<0. 49

<0.28

<0. 77

<1.53

<0.24 76+ 4 3.51 + 1.85 2.35 + 1.81

<0.71

<0.79 2.97 + 1.63 <3.18

L<LLF/OAF SITE ELLVIROLLHELLTALcLIARcOAL cALLTAIDGE IALLPI.EB OFF BITE BTATIOHB 1-131 ACTIVITY PCI/n"3 + 2 itOno LOChitot<

LLEEK EHO PATE 82/01/05 BZ/II/13 02/0 I/19 82/I 1/26 02/42/03 BZ/IRIDt 02/I2/17 02/02/23 82/03/42 BZ/43/I9 02/43/16 82/03/2h 02/43/3D BZ/Oh/D&

02/I h/13 ezroh/20 BZ/0h/27 02/05/Oh 02/45/12, ezrosrte 02/OS/RS 82/46/02 02/06/40 82/06/ts 82/46/22 02/06/2't 02/117/07 02/47/13 BZ/07/Ro 02/07/27 BZ/08/03 02/00/10 92/40/17 02/08/Zh 82/00/31 ez/09/s 02/09/1 h 82/09/21 Bzlot/28 82/14/5 82/Iors 82/II/L9 82/10/26 ezrti/z 02/11/9 02/11/16 82/11/23 BZ/Ll/34 BZ/tz/7 02/12/Is 02/12/2t ez/12/20 83/ ~ I/Oh C

OFF (I. 050 (0.013 CD. 020

< ~.OLR

('4.009 (I.olt (4.0th (0.0th (O.DLO Co.alt

<4.017 (0.016 (0. IM (0.017

<0.027 (O.ORO (0.

0 1'9 to.ale (0.0&h (0.057 (0.016 CI. 020 (0.017 (O.OM CO.OZh (0.011 ca'.ale

<0.417 (a.ozz (0.018 (0.423 (0.017 CD.02L-(I.OZD (0.020 (0.0th

( ~.017 (O.D19

<O.O17 (O.alh (0.015

<0.01/

(4.024 ca.o24 CO.OL5 CO.D24 Co.alh (O.ILS (4.418 (O.olh (0.021 (O.OZh CD.DIS

~ rvL<r wr orERhTIDLLht.

0 1-0F F (0. F 10 (I.012 (0.021

( ~. D 1 1 (0.0th (4.039

( ~.016 (O.DZI co.ote

<0.015 CD 020 (0.019 (0.036

<o.aze (O.ORO (4.028

<4.DI6 (0.452 (I ~ Oh3 (0 'IM (0 ~ OL9 (0.026 0.039/0.DOS (O.ORL (4.009 (4. D le (0.420 (0.016 CO.OIB (4. 112h (4.031 (I.DZO

<0.027

<4. 416 (0. 0th (O. D 17 (0.010

<0.016 (0.022 (0. 017

<0.424

<0.025 (0.020 (4.0ts Co.ozi (0.016

<0.01&

(O.OLS ca.azl (D.023 (0.419 (0.0th PR-OF F (0.019 (0.021 (0.421.

(0:IZI Co.Ill C0.059 (0.023 (0. 421 (0.020 CO.ORS

<0.429 (0.429 (0. 427 (D.426 (0.024 (0.031 (4.420 ta.'029 (4.060 to.'OS9 (4.433 ca.ozh (D.023 (0.43h (0.029 (4.030 (4.026 (4.420 (O.oht (O.ozh CO.DZB (4.030 (0.03h (0.010 (O.O19 (O.OZO (4.023

<4.019 CD.016 (4.023 (4.015 (0.024 CD.D21 CO. 019 (o.'ats (0. 016 (4.010 (O.ozl (4.020 (4.022 (0.010 CO.D23 CO.DM EDFF i

CI;O'22 (4.017

<0.010 (4.025 CI.I32 CO. ~ he (0.021 Co.ois (0.026 (4.022 C0.033 (0.026 (0.030 CI. D21 (4.036 (O.ozs (4.004 (I.023 (O,ohz (0.43S (D.I34 CO.D31 (0 03h C0.03S (0.025 (0.028 (0.018

<0.023 (D.026 (0.02h co.'azt CD.022 (D.ozo (0.025 CO.OO9

<O.OO9 (0.023 (0.017 (D.DIO (D.OI&

(O.o lh (0. 411 (0.023 (D.DI3 (D.D13 CO.OIS (4.010

<4.016 CD.021 (4.013 CD. 013 ca.olt (O.DRL FOFF CO. ~ 10 (4. 016

~

(I.023

( ~. I17 (0.012 (O.OI7 C0.017 (0.02I

<O.OIS (0.019 CD.O17 (o. 419 (I. 010 to'.Ole

<0.019 (0.02R t 0. 017 (0. 417 (0.017 C0.021

( ~.020 CD. 016 (0.010 (0. 018 (I.OIB

<0.021 (I. I 17 (a.ot&

(O'.02<

(I.D20 (0. 017 (0. 019

~ (O. 016 (0.026 (O.OL/

Co.ozl (4.D23

<0.418 to.on (0.412 (0; 017 t 0. 019 (0.022 (0.421 (a. 410 C0.017 (0. 013 (O.OIL Ca. D13 (0.012 (0.0'LO (0.025 CD.DL3 C--OFF (0.016 (O.DL6 (O.OZ&

(0.4IB (I. Olh CD. DIS (4.0th

<0.025 (4. 016 CD. 013

<0.026 (4.'023 t 0. OLIS

( ~. 026

<0.021 (I. 029 (4.03t

<O.D20 (4.019 co.ale to. 01'9 co. Dza CI. 447 C ~.023

<4.039 CO.IZZ (0.021 CO.OO7 CO. 021 CO.OZ&

(0. 417 (0.024 CO.OZS

<o.oLS LO.DD3 (0.418 CO. OM (0.022 Ca. 03'9 CD.OZI CD.428

<0.027

<0.020 (O. I36 CO.O33 co.03t (D.De+0 (4:Ol/

CD. OI JI

<I.OLI (0. 016 to. OIS

<D.DLB

ThBLE 13 IOIP/JAF SITE Et<VIRONtIENTAL CIIARCOAL CAllTRIDGE BAIIPLES ON SITE STATIONS I-L31 ACTIVLTT pCL/n 3 i 2 ILOnh LOCATIOlt IIEEK EtlD DAlE Bn/01/Dh 82/II/12 82/Il/18 82/01/PS 92/02/12 82/42/00 92/Ia/lh 02/02/2R 92/43/0 I 92/13/08 Bin/13/I5 82/03/Ra 82/03/29 SR/0 1/05 Oa/11/la Bni/11/19 82/lh/26 92/IS/13 Bin/45/11 82/45/17 82/15/2h 82/16/Dt 8 rob/o7 82/16/11 82/16/al 92/46/28 BR/07/06 82/07/la 92/07/19 92/07/26 BR/18/12 82/48/09 Sa/IO/Ib 82/08/23 82/18/30 82/4'9/17 BP/O'/13 92/19/20 Ba/I'9/2'7 82/ta/1 82/10/I 2 BR/lo/19 82/ld/RS BR/tlri 82/I I/8 92/Li/15 Ba/I I/22 DR/Li/R9 oa/12/6 82/LR/11 82/Ia/20 92/12/27 83/0 1/03 Dl-OH DR,-OH (O.D22

<0.421 (1.132 (4.131 (0.419 (0.126 Co.ol9 (I. 026

( ~.Iab (0.4R3

<1.430 C0.137 (0.125 (0.033 I

(D.DR3 (0.129

<4.D26 CD.046

<4.018

<0. ~

8

<0. Old'

0. 01'9 (0.121 (4.032

<O.OIF (D.oah (0.016 (0.02h (0.026 CI. 021 (0. 12in (0.020 (0.118 (D.o 15 (0.113

<O.01S (0.021 (0.021 CO.et3 (0.01/

(0.'a17

<0. 011 C0.026 (0.113 (1. 015 (D.I21 tO.DI6 (0.017 (0.415 (0.015 (0.022 (O. F 12 I IN'DI Oft t0.023 (0.023 (O. 016 (0.119

• (0.025 (0.121 CD. IIB

<0.119 (0. 011

<a.e23 (0. 02'7

~.Oahg0. ~ Oh s

(D.lal

<4.021 (0.117 C4.021 (0.025 to.oah (0.016

( ~.065 (0.119 (4.035 (0.024

<0.023

<O. 417 (4.021 (1.129 (0.148 CD.I22

0. 013iO. Doh CD.D22 to.din8 (0.025

<o.aaD

<0.019

<1.009 (0.037 (0.025 (D.IRD ca.oaa (4. 119 C4.013 (1.4h3 (4.029

<1.119

<0.018 (0.118 (0.022 (0.118 (0.016 (0.021 CO.IIB

<0.411 IhllDNAL E""OH (D.IL1 (I.416 (0. 118 (1.022 (0. 019 (I.46R

<0. ~ 12

<I.oa7 (0. ~ 14 C ~.DL7 (O. 017 (0.129

<0.021

<0.022 (0. 129 (1.022 (0.021 (1. 02II (0. 117

( ~.069 (0.4R7 (I. ~ 23

<0.4RS'

~.025 io.eah (1.022 (0.023 C0.020 (0.019 (0.037

( ~.021

( ~.030 co.020 c0.020 (O. 017 CD. 414 (0.033 C4.427 (O. 02'7 Ce.0lh (0.027 (1.131 (0. F 19 (1.021 (1.017 C1.123 (O.DIS (0.026 (0.0'ab

<0.019 (0.125

<0.423 (0.107 F

OH C0.030

<0,021 (0.128 (0.422 (0.021 (4.DRh (0. Oin3 (0.029 (I. 131

<O.O27 (1.122 (0.013 (4.017 CO.027 c0.0as

<o.e31.

(1.027 (0.139

( ~.021 (4.063 (4.03S (O. 131 (I.026 (0.129 (O.D31 to.o3a ta.oaa

<D.OIB (0.027 (1.137 (1.436 (0 ~ 036 C4.029 (0.123 t0.126 (4.420 (0.137 (D.oab

<0 On9 (4.42R

( ~.019 CI.IRh (0.028 (0.027

<1.4IB (0.012 (0.032 (e.oas

<0.021 (D. 121 (0.019 (0.021 (1.025 9"-OH (D.eal (0.011 (1.022 (0.021

<0.013 ca'.aas C4.017 CO.DLB C4.423 (I.OIS (O.OLS t 0.13D co.IRI (D.133

~ (e.eaB (1.120 co.eab (0.028

'(O. ILO (e.oa3 (Q. 21 (0.42?

(D.eah (4.021 (1.026 (0.021 (0.038 (0.132 (0. 031 (I.439 (D.ORS

<0 ~ 13I (0.031 (4.021 C0.421 (0.1Rh C1.133 (4.427 (1.127 (0.129 (1.022 (O.O333i (0.133 (D.D23 (0.031 CO.DI3 (D. 130 (4.427

<0.019 (1.13R

<1.033

<1.135

<0.430 II ON (4. 116 (O.OOF ce. 0 la (D.aai

<0.049 (4.131 (0 Ilh

<O.013

<0.015 to.eao (0.019

<1.019 (0.02in (4. 021 (4.120 (e.oab C0.028 (0.026 (0.057 (0.416 C0.420 C0.419 (0.0'L6

"<4.016

<0.019 (1. 018 (0.025

~.DID>0.401 0.01740.005

0. 01540,403

<0.019 (0.022 O.Dobro. ~ 01 (a. 013 D.oahto,003 (0.122 (0.025 (4.021

<0.127

<O.'428 go.dins

<D.oai

<a.033

<0.036 (O.O33 (0.121

<0.122 (4.11/

(0. OI6 (1.016 ce.eaa

<D. 419 (a. 019 I--ON c ~.eal

<0.419

< ~.133

<4.027

<0.116 (0.03R (4. ~ LR (O.O21 C4 Iin9 C ~.027

< ~.oi3 (1.030

~.DasiO. F 06

( ~.431 (0.032 C0.413 (1.031 (I. 121 (0.066 (0.426 (0.121 (0.018 (0.421 (0.132 (4. 019 (0.029 (0.128

( ~.035 0.0hage.005 (0.433 (1.027 (0.033

<0.03L (4.034 C0.123

<0.014 (D. 031

<O.o s (O.IIB (0. ~ 17 (O.OL9 (0.023 (0.121 (D.oah (O. ~ IO (1.017 (0.411 (D.DRL"'4.419 (0.013 (0.020 (4. 019

<0.121 3--ON

( ~.020

<D.olb (0.019 (0.0th (1.017 (0.157 C I. D l1 t O. ILS (0.023 CD.IIL C 0.018 c4.127 CI.IRS

<0.028 C I.IL7

<4.128 CO.IRS (0.026

<4.02t (O. IIO (0.022 (1.021 (0.019 (D.ets Cd. DIB (4.016 (1.418 (1. 017 (0.021

<0.119 (0.013 Co.oth D.OIIto.doh C 1.0 12

~.DORADO.003 (0.011

~. 121 t O.1Db (0.026 (e. Iinin (1.132 (0.169

< 4.026 (1.036 (0.431

<D.DIB (D.aao

<0.135

, (0.419

<0.019 (1.123

<0.122 C D.DPR

<0.019 K

ON (D.olh (O. 017 C0.020 Co. 117 (I. 011 (1. 020 (0. 116 Co. 019 Cd. 019 (1.421

<I;025 (1.023

( ~.017

<0.435

( ~.021 (0.021 (0 IM (0.121 C ~.DL1 (0.427 CD.I23

<0.021

<4.021 ce'.Ias (0.116 (1.129 (1.021 (0.121 (0.119

<0.426

<I,aai Cd.023 CD'.ean ca.ai9

<< ~.Ol/

(1.013

<0.125 (O.a

<I.oah (0. 030 (0.010 (0.122 (1.023

<0.125

<4. 419 (D. 111 (O.alb

<D.DI4 Ce.oal (1.422 CO.'enl

<1.023

<1.123

TABLE 14 DIRECT RADlATION HEASUREllEHTS - I)UARTERLY RESULTS (1982)

STATION NUHBER 3

4 5

6 7

8 9

10 11 12 13 14 15 18 19 23 24 25 26 27 28 29 30 31 39 43 44 45 46 47 48 49 50 51 52 53 54 LOCATION Dl on Site D2 on Site E

on Site F

on Site G

on Site C off Site Dl off Site 02 off Site E off Site F off Site G off Site DeHass Rd, SN Oswego-Control Pole 66, M. Boundary-Bible Camp Progress Center-Plcnlc Area East Boundary-JAF, Pole 9 N

on Site I

on Site J

on Site K

on Site Nor. Fence-NN Sector, JAF Light Pole (E) JAF Nor. Fence (E) JAF Hor. Fence (HM) JAF Nor. Fence (llM) NP-I East Fence.

Rad. Haste-NNP-I

.9 ml Rt.

3 from Rt; 104B Cor. Rt 3 and Kelly Drive Cor. Rt 64 and Rt.

35'-=

Cor. Rt.

176 and Black Creek Rd.

NE Shoreline (JAF)

.36 ml (H) on Access Rd. (JAF)

Phoenix, HY-Controll Lake Rd. Nest of J On-Site Oswego Steam Sta.

H End of M Fence East 11th St. Fltzhugh Park Sch.

Broa<hell 8 Chestnut Sts.-

Fulton H.S.

Liberty St.

B Co. Rt. 16.-

Hexlco H.S.

JANUARY TO APRIL 5.58i0.25 5.08i0.61 4.63i0.50 3.87i0.08 4.15i0.48 4.53i0.36 4.06i0.64 4.80i0.13 4.02i0.56 4.05i0.15 4.66i0.23 4.55i0.29 3.85i0.45 4.35i0.39 4.40i0.53 5;03i0.34 4.55i0.16 4.57i0.39 4.32i0.49 9.71i0.77 29.33i2.91 40.99i2.24 7.03i0.91

10. 15i 1. 16 31.49i0.94 4.26i0.30 4.12i0.30 4.35i0.25 4.25i0.37 16.16i3.36 4.85i0.52 3.80i0.23 4.49i0.49 4.18i0.36 (I) 3.84i0.25 4.11i0.45 APRIL TO

~

JULI 12.27i0.46 6.70i0.30 5.59i0.12 5.37i0.13 5.61i0.08 5.6IN).10

6. 24io. 17 5.44i0.22 5.93i0.11 4.79i0.22 5.42i0.19 5.17i0.06 4.50i0.18 5.64i0.15 5.64i0.29 9.13i0.14 6.60i0.12 5.88i0.08 5.92i0.05 23.18i0.29 41.79i0.16 90.56i1.73 16.88i0.13 10.76i0.11 44.40i1.89 5.92i0.07 5.63i0.31 5.91i0.06 (I) 46.87i0.08 7.13i0.16 4.97i0.03 5.78i0.22 5.86i0.13 (I) 5.49i0.21 5.10i0.13 JULZ TO OCTOBER 13.04i0.21 7.03i0.40 5.70i0.41 5.89i0.58 5.60i0.63 5.99i0.57 5.71i0.47 5.69i0.28 5.68i0.58 5.24i0.33 5.95i0.28 5.66i0.18 4.20i0.27 5.08i0.32 6.25i0.34 8.70i0.54 7.20i0.11 6.13i0.45 6,08i0.75 20.98i0.98 53.26i3.11 75.89i4.93 19.52il.55 11.60i0.62 61.91i4.46 5,01i0.52 5,82i0.42 5.76i0.14 5.23i0.29 51.12i0.30 8.79i0.58 5.02i0.57 (I) 5.39i0.58 4.08i0.15 5.85i0.17 5.50i0.46 OCTOBER TO DECEHBER 10.8lil.54 5.69i0.61 5.83i0.50 4.67i1.89 5.68i0.63 6.08i0.69 5.05i0.22 5.38i0.74 4.83i0.08 5.56il.01 5.13i0.34 5.20i0.42 4.44i0.56 5.08i0.76'.44 i0. 63 8.50i0.98 5.50i0.45 5.63i0.88 5.37i0.83

17. 24i2. 15 47.44i6.42 72.72i8.84 14.89il.07 (I) 43.59i16.11 5.0zi0.34 4.95i0.50 6.00i0.40 4.89i0.49 43.33i3.41 6.90i0.78 4.87i0.42 4.90i0.44

~

5.25i0.37 5.29il.ll 5.11i0.45 5.01i0.81 LOCAT!OH (DIRECTIOH AHD DISTANCE)

O.Z5 mlles 0.40 mlles 0.40 mlles 0.50 mlles 0.70 wiles 16.00 mlles 11.40 wlles 9.00 ml les 7.20 mlles 7.70 mlles 5.30 mlles 12.80 ml les 0.90 mlles 0.50 mlles 1.30 mlles 0.80 mlles 0.80 mlles 0.90 mlles 0.50 mlles 0.40 mlles 0.50 mlles 0.50 ml les 0.40 mlles 0.20 ml les 0.10 ml les 9.40 ml les 12.60 wl les 7.60 wl les 7.90 ml les 0.60 mlles 0.80 mlles 20.00 mlles 0.70 mlles 7.50 wl les 5.80 ml les 8

69' 140' 175' 210' 250' 42' 80' 117' 160' 190' 225' 225' 238' 268' 81' 71 8

98' 110' 132' 60' 68' 65' 57' 290' 292' 88' 64' 130' 178' 69' 92' 165' 115.

8 233' 227'3.70 mlles 8 183'.30 mlles 9 115'

TAOLE 14 '(cont.)

01RECT RAOlATION IIEASURENENTS - qUARTERLY RESULTS (1982)

STATlON NNSER I.OCATlal JAIQARY TO.

APRIL APRIL TO JUI Y JULY TO OCT08ER OCT08ER TO DECEII8ER LOCATION (OIRECllOH AHO 0l 5IAHCE )

55 56 57 58 59 60 61 65 lilnnmann Rd.

8 Co. Rt. 5-Pulaskl K.S.

Rt.

104 - He< Kaven K.S. (SE Corner)

Co. Rt. 29 6 Hlner Rd. (SE)-

Lyccmlng, IIY Co. Rt.

1 - ALCAN (S of Entrance Rd.)

Envlronmenta'I Lab - JAF S. Shore (Fish Point)

Little Sodus Bay, NY 700' of l48 (On Access Rd.) - JAF Dutch Ridge Rd. 6 Kerflen Rd. (SE) 3.7940.47 4.10%0.37 4.24s0.41 4.30%0 ~ 38 9.25%1 F 15 5.5340.51 5.39s0.38 3.81s0.32 4.84s0.16 4.95s0.24 5.35s0.26 5.47%0.19 38.4040.98 5.7340'07 10.50s0.18 5.3440.06 5.69XO 36 5.84%0.30 5.5340.35 (I) 34.0043,56 6.95s0.43 11.83I0.61 5.40I0.58 5.23s0.45 5:00s0.65 5.54s0.69 5.57%0.14 21.09%2.52 6.51'.75 9.83a1.55 5-29xl.13 13.70 mlles 9 75'.40 mlles 8 120'.90 mlles 8 145 3.20 mlles 9 220'.50 mlles 8 95'1.00 mlles 8 225'.80 mlles 8 83'.80 miles 8 198'

.o (1)

TLOs lost.

Results in unit's of mrem/standard month.

TABLE 15

" CONTINUOUS RADIATION MONITORS<<(GM) mR/hr FIRST HALF mR/hr LOCATION C Offsite 01/Q5 to 02/04 to 03/02 to 04/01 to 04/30 to 05/29 to 02/04 03I02 04/01 04/30 05/29 06/29 PERIOD 1982 MIN.

0. 010 0.010 0.010 0.011 0.011 0.010 MAX.

0.032 Q.019 0.080 0.020 0.018 0.020 AVG.

0.012 0.012 0.019 0.017 0., 015 0.014 Dl Chsi te D2 Onsite 01/04 to 02/03 to 03/01 to 03/30 to

.04/30 to 05/28 to 01/04 to 02/03 to 03/01 to 03/30 to 04/30 to 05/28 to 02 I03 03/01 03/30 04/30 05/28 06/28 02/03 03/01 03/30 04/30 05/28 Q6/28 0.01Q 0.010 0.010 0.015 0.011 0.010 0.011 0.011 0.011 0.011 0.012 0.011 0.015 0;01V 0.040 0.060 0.063 0.058 0.021 0.031 0.099 0.050 0.04V 0.091 0.011 0.011 0.019 O.Q23 0.024 0.022 0.015 0.015 0.014 0.016 0.015 0.014 E (hsite 01/04 to 02/03 to 03/Ol to 03/30 to 04/30 to 05/28 to 02/03 03/01 03/30 04/30 05I28 06'/28

0. 011 0.011

0. 010 0.011 Q.QX.3 0.011 0.022 0.026 0.051 0.077 0..053 0.085 0.014

0. 016 0, 014 O. D17 0.019

0. D15 F

Chsi te Ol/04 to 02/03 to tj3/01 to 03/30 to 04/30 to 05/28 to 02/03 03/01 03/30 04/30 05/28 06/28

0. 010 O.O1O 0.010 Q.01Q 0.010 0.010 0.01V 0.022 0.022 0.025 0.032 0.040

'0.011 0.012 0.011 Q.016 0.016 0.012

<<Detectors are "bugged" to insure on scale readings.

-97

TABLE 15 (cont.)

CONTINUOUS RADIATION MONITORS~ (GM) mR/hr FIRST HALF mR/hr LOCATION PERIOD 1982 MIN.

MAX.

AVG.

G Onsite H Chsite I Onsite J Chsite K Qnsite 01/04 to 02/03 to 03/01 to 03/30 to 04/30 to 05/28 to 01/04 to 02/03 to 03/01 to 03/30 to Q4/3Q to Q5/28 to 01/04 to 02/03 to 03/01 to 03/30 to 04/30 to 05/28 to 01/04 to 02/03 to 03/01 to 03/30 to 04/30 to 05/28'o 01/04 to 02/03 to 03/01 to 03/30 to 04/30 to 05/28 to 02/03 03/01 03/30 04/30 05/28 06/28 02/03 03/01 03/30 04/30 05/28 06/28 02/03 03/Q1 03/30 04/30 05/28 06/28 02/03 03/01 03/30 04/30 05/28 06/28 02/03 03/01 03/30 04/30 05/28 06/28 0.012 0.011 0.012 0.015

'0. 010 0.011 0.018 0.010 0.017 0.010 0.018 0.015 0.010 0.011 0.012 O.Q21 Q.011 Q.010 0.011 0.010 0.010 0.017 0.015 0.013 0.010 0.010 0.010 0.011 0.011 0.011 0.028 0.029 0.036 0.067 0.053 0.085 0.040 0.048 0.071 0.080 O;O60 0.088 0.013

'0.021 0.099 0.099 0.062 0.09Q 0.025 0.034 0.080 0.072 0.028 0.089 0.023 0.099 0.050 0.051 0.049

'.069 0.014 0.024 0.014 0.018 0.019 0.018 0.022 0.030 0.027 0.030 0.024 0.027 0.011 0.015 0.028 0.028 0.029 0.026 O.014 Q.Q15 0.015 0.025 0.020 0.022 0.012 0.015 0.018 0.019

'.014 0.019

~Detectors are "bugged" to insure on scale readings.

-98

TABLE 15 (cont. )

CONTINUOUS RADIATION'hlONITORS* (GM) mR/hr SECOND IIALF LOCATION C Offsite PERIOD 19&2 06/29 to OV/23 07/23 to 08/20 08/20 to 09/17 09/1V to 10/19 10/19 to ll/16 11/16 to 12/15 12/15 to 02/01/83 MIN.

0.010 0.013 0.012 0.010 0.010 0.010 0.010 h1AX.

0.028 0.021 0.030 0.023 0.035 0.025 0.023 AUG.

0.018 0.018 0.018 0.018 0.020 0.018 0.015 Dl Onsite D,

an ite E

Onsite 06/28 to OV/22 to 08/19 to 09/17 to 10/15 to ll/12 to 12/08 to 06/28 to 07/22 to 08/19 to 09/1V,to 10/15 to ll/12 to 12/08 to 06'/28 to 07/22 to 08/19 to 09/17 to 10/15 to 11/12 to

.12/08 to OV/22 08/19 09/17 10/15 11/12 12/08 01/06/83 07/22

'08/19 09/17 10/15 11/12 12/08 01/06/83 07/22 08/19 09/17

'0/15 11/12 12/08 01/06/83

0. 010 0.014 0.013 0.010 0.010

- 0.010 0.010 0.011 0.011 0.010 0.010 0.010 0.010 0.010

0. 012

0. 0'13 0.010 0.010 0,010 0.010 0.010 0.060 0.082 0.600 0.110 0.063 0.032 0.033 0.097 0.094 0.060 0.047 0.130 0.030 0.075 0.190

0. 121.

0.100 0.075 0.150 0.032 0.081

0. 021 0.023 0.022 0.025 0.022 0.022 0.022 0.017 0.013 0.015 0.015 0.025 0.013 0.015

0. 018 0.019 0.022 0.020

~ 0.013 0.018

. 0.018 F

Onsite 06/28 to 07/22 to 08/19 to 09/17 to 10/15 to 11/12 to 12/08 to OV/22 08/19 09/17 10/15 11/12 12/08 01/06/83 0.010 0.010 0.010 0.010 0.011 0.010 0.010 0.040 0.071 0.033 0.070 0.072 0.041 0.030 0.013 0.014 0.014 0.016 0.018 0.018 0.018

~Detectors are "bugged" to insure on scale readings.

-99

TABLE 15 (cont.)

CONTINUOUS RADIATION MONITOICS* (GM) mR/hr SECOND HALF mR/hr LOCATION PERIOD 1982 MIN.

MAX.

AVQ.

G visite 8

Unsite I

Cnsi te J

Chsite I

Qnsite 06/28 07/22 08/19 09/17 10/15 11/12 12/08 06/28 OV/22 08/19 09/1V 10/15 11/12 12/08 06/28 QV/22 08/19 09/1V

. 10/15 11/12 12/08 06/28 OV/22 08/19 09/1V 10/15 11/12 12/08 06/28 07/22 08/19 u9/17 10/15 11/12 12/08 to 07/22 to 08/19 to 09/1V to 10/15 to 11/12 to 12/08 to 01/06/83 to OV/22 to 08/19 to 09/17 to 10/15 to 11/12 to 12/08 to 01/06/83 to 07/22 to 08/19 to 09/17 to 10/15 to 11/12 to 12/08 to Ol/06/S3 to 07/22 to 08/19 to 09/17 to 10/15 to 11/12 to 12/08 to 01/06/83 to 07/22 to 08/19 to 09/17 to 10/15 to 11/12 to 12/08 to 01/06/83 0.013 0.019 O.Q13 0.013 0.013 0.013

. 0.012 0.018 0.014 0.017 0.015 0.013 0.013 0.015 0.012 0.014 0.011 0.012

.0. 020

0. 015 0.012 0.011 0.010 0.010 0.012 0.010 0.010 0.010

0. 011

0. 012 O.Q1Q 0.010 0.010 0.010 0.010 0.051 0.052 0.058 0.041 0.075 0.032 0.033 0.070 0.092 0.100 0.080 0.082 0.037 0.038 0.090 Q.110 0.120 0.060 0.092 0.035 0.080 0.090 0.080 0.047 0.051 0.062 0.028 0.02V 0.130 0.081 0.060 0.065 0.044 0.022 0.024 0.020 0.024 0.023 0.023 0.025 0.022 0.021 0.028 0.033

'0. 028 0.022 0.026 0.025 0.020 0.028 0.033 0;025 0.028 0.030 0.025 0.025

0. 013

0. 013

0. 025

0. 028 0.013 0.013 0.013 Q.014 0.014 0.013 0.018 0.018 0.013 0.012

~Detectors are "bugged" to insure on scale readings.

-100

TABLE 16 CONCENTRATIONS OF IODINE 131* IN MIL'K Results in units of pCi/1 + 2 sigma Station 5-3-82 6-7-82 7-12-82 8-9-82 9-13-82 10-4-82 11-8-82 12-6-82 40 14 16

%.1

<0.2

<0.2

<D ~ 2

<D.2

<0 ~ 2

<0. 2

%.2

%.2

%.2

%.3

<0.3

<0.3

<D ~ 3

%,3

<0.3

%o2

%.3

%+3

<0,3

<0 ~ 2

<0 ~ 2

<0 ~ 2

<0 ~ 2

<0.2

<0.4

<0 ~ 1

%.1

<D 3

<0.3

% l 4). 1

%.1

%.1

<0. 1

<0 ~ 2

<0.2 7

<0 ~ 1

<0 ~ 2 45

~ "Iodine-131 results are corrected for decay

-Nn result because the sampling station was

<0.2

<0 +3

%.2

<0 ~ 2 to the sampling stop datei not in operation.

% 2 Aol

<0. 1 Aol

<0.4

<0. 1

<0 ~ 2 I

c0.2

TABI.E 17 COHCENTRATIOHS OF CAIOIA KNITTERS IH lllljl (HONTHI.Y SAHPLES)

Results in units of FCi/liter t 2 signa Station Huclides 5-3-82 6-7-82 7-12-82 8-9-82 9-13-82 10-4-82 11-8-82 12-6-82 40 K-40 Cs"134 Cs"137 Ba-140 La-140 Others 1500 + 150

<<2+4

<<3.0

<<26 c4.4

<<LLD 1300

<<2 ~ 7

<<4.2

<<27

<<6+6

<<LLD

+ 130 1600 + 160

~

<<2 9

<<3.4

<<51

<<5+7

<<LLD 1200 4120

<<3+3

<<4.4 c54

<<7.4

<<LLD 1200 + 120 c3.0

<<4.6

<<48

<<16

<LD 1400 + 140

<<311

<<4.0

<<55 cl4

<<LLD 1600 + 160

<<3.0 c3 ~ 8

<<63 c16

<<LLD 1300 + 130 c3+6

<<4.6

<<27

<<4.2

<<LLD K-40 Cs-134 Cs-137 BQ"140 La-140 Others 1500 + 150.i 1500

<<2.8

<<2a5 6'

+ 2.7

<<4'

<<29

~

<<35

<<3.2

%.1

%LD

<<LLD

+ 150 1600 + 160 c3.0 c3.3

<<39

<<4 ~ 1

<<LLD 1400 + 140

<<2,0

<<3.7

<<46

<<4.5

<<LLD 1100 + 110

<<3aO c3 1

c34

<<4.5

<<LLD 1600 e 160

<<3;4 c3.5

<<49

<<15

<<LLD 1300 + 130

<<3.6

<<4.0

<<36

<<8.0 cLLD 1500 + 150

<<3.2 c3.7

<<? II cl.9

<<LLD 14 K"40 Cs-134 Cs-137 Ba-140 La-140 Others 1400 + 140

<<3.3

<<4.9

<<32

<<7 7

OLD 1400

<<2.6 4.6

<<42

<<4.9

<<LLD

+ 140

+ 3 1

1500 + 150

<<3,6

<<6'

<<72 cl3

<<LLD 1100 + 110

%,7

<<4.0

<<53 c18

<<LLD 1100 + 110

<<2.7

<<3+2 c29

<<7,5

<<LLD 1400 e 140

<<3.5.

<<4.3

<<26

<<7 ~ 8

<<I.LD 1300 + 130

<<3o2

<<4.5

<<58

<<6.7

<<LLD 1400 + 140

<<3.3

<<3.7 CI2

<<9 5

<<LLD

TABLE 17 (Cnnt ~ )

COHCEHTRATIOHS OF CAHHA EHITTERS IH NILK (HONTIILY SAHPLES)

R'esults tn untts nf pCI/Itter 0 2 stgaa Stattnn Hucltdes 5-3-82 6-7-82 7-12-82 8-9-82 9"13-82 10-4-82 11-8-82 12-6-82 5

K-40 Cs-134 Cs-137 Ba-140 La-140 Others 1500 + 150

<2 9 4 ~3+ 2,8

<<30

<<3.6

%LD 1500 + 150

<3.7

<<4.7

<52

<10

<<LLD 1500 + 150

<<2,8 6,1+29

<<48

<I I

<<LLD 1200 + 120

<<2+2 14 + 3.3

<<7 8

<<LLD 1300 + 130

<3.0

<3+8

<<)7

<<6,3

<<LLD 1300 + 130

<3,1

<<4.5

<<49

<<7 ~ 3 CLD 1100 + 110

<2.8

<<A+2

<<46

<15

<<LLD 1300 + 130

<2.7

<<4.5

<12

<3 0 CLD 16 K-40 Cs-134 Cs-137 Ba-!40 La-140 Others 1500 + 150

<<2 9 5,2 + 2 9

<<I4

<<6 7

<<LLD 970 + 97

<<2.4

<3.8

<16

<2.5

<LLD 1500 + 150

<<3.0

<<4.5

<<79

<13

<LLD 1300 + 130

<<3.0

<<6 2

<57

<<12

<<LLD 1400 + 140

<2 7

<<4.1

<39

<7.1

<LLD 1300 + 130

<<3i 1

<<4.7 40

<14

<LLD 1300 + 130

<2.4

<<3.6'58

<5 ~ 6

<<LLD 1000 +.IUO

<2 +9

<<4,9

<<)3

<12

<<LLD 7

K-40 Cs-134 Cs-137 Ba-140 La-140 Others K-40 Cs-134 Cs-137 Ba-140 La-140 Others 1600 + 160

<<2. 7 4.2'+ 2.8

<<)0

<<4.3

<<LLD 1500 + 150

<<2.7

<<).7

<?5

<<2 ~ 5

%LD 1500 + 150

<<2+9 3+5 + 2.3

<44

<<4 ~ I

<LLD 1400 + 14i0(1)

<<) e4 4 ~ 1+ 2+7

<<74

<17.0

<LLD 1500 + 150

<2~6

<<5 ~ 5

<<36

<<7 ~ I

<LLD 1200 + 120

<2,9

<<4i,O

<<62

<12,0

<LLD 1200 + 120

<2 6

<<4.5

<<27 e.4

<<LLD 1000 + 100

<2.8 4 3 + 2,7

<<)2 A. 1

<LLD 1300 + 130

<3 ~ 2

<<3.6

<17

<<5.7

<<LLD 1300 + 130

<<3+2

<<4.2

<<48

<12.0

<LLD 1200 + 120

<3+2

<<4e2

<<12

<<4.5

~D 1700 + 170

<3'

<<4.9

<<4i7 e.o OLD 1500 + 150

<<3+0

<<4.7

<<37 e,4 OLD 1300 + 130

<<3. I

<<4.1

~

<<44

<12.0

<<LLD NOTES: - Hn results because the sanpltng stattnn was nnt a ntlk sanpltng Iocatton unttl July+

(I) Sanpltng began at liicattnn l45 nn 7-T2-82

TABLE 18 CONCENTRATIONS OP STRONTIUM 90 IN MILK (MONTHLY SAMPLES)

Results in units of pCi/l.iter + 2 sigma Station 40 4

14 5

16 7

45 5-3-82

< 7.8 5.1+3.4 1.8+1.3 3.8+1.0 3.8+1.0 5.7+1+4 6-7-82

< 2+i loOEO 4

< Oo6 5.6+1.2 3'+1 7

4. 1+1+7 7-12-82 2i5+1 ~ 1 3.0+1.1

<0,2 5 ~ 2+1+ 1 7+7+1+2 6 f0+i+9 4,M2. 1 8-9-82 5 ~(H2 '1 3+0+1.1 2.2+1.0 4+5+1 5 4 0+1 6 8.5+2.1 5.2+3.0 Station 9-13-82 10- -82 11-8-82 12 2 40 4

14 5

16 7

45 1.6+1 o 1 5.1+1.5

<22.9 4.8+1,l 3.6+1.0 4.2+1.0 4.1+1 ~ 5 3+6+0.7 4.4+1.2 6 ~ 1+lol 1 4+1+3 5.8+1.0 7,0+3.3 5.%.0.9

+0.6(>>

3. 140.9 4..3+1.2 5 7+2.5 9.9+4.3 5 8+1+3 7.8+1+1

3. (H.0.8 5'+1.0 3 5&0.8

<71.0 3+6+1.0 3,8+0.8 5,%0.8 (1) High LLD result because of low chemical yield.

Insufficient sample for reanalysis.

-No results because the sampling station was not in operationi

TABLE 19 MILCH ANIMAL CENSUS SPRING 1982 TOWN Scriba Richlami Oswego Hannibal Voiney NUMBER ON CENSUS MAP 1

16+

2 3

6 8

9 4g 4@a 10 5+

11 7g 12 13 14+

17 18 19 20 21 22 23 24 25 26 27 28 29 TOTALS NUMBER OF MILCH ANIMALS 2 G 39 C 20 C 1C 2 C 35 C 45 C 55 C 1& C 24 C 40 C 34 C 51 C 62 C 2 C 65 C 38 C 46 C 43 C 37 C 5 C 35 C 150 C 35 C 82 C 42C'8 C

30 C 33 C 2 C 1,129 Coors 2 Goats C

=

Cows G

=

Goats Milk Sample Locations Milk Sample Control Location

-195

TABLE 19 (cont.)

MILCH ANIMAL CENSUS SUMMER 1982 TOWN Scriba Richland Oswego Hannibal Volney NUMBER ON CENSUS hlAP 1

16~

2 3

6 8

9 44 45*

10 54 11 Vlg 12 13 14+

iV 18 19 20 21 22 23 24 25 26 27 28 40**

29 TOTALS NUMBER OF MILCH ANIMALS 2 G 39 C 20 C 1 C 1 C 30 C 40 C VO C 20 C, 1 G 26 C 45 C 40 C 52 C 70 C 2 C 60 C 34 C 42 C 45 C 40 C 8 C 40 C'14C 37 C VS C 37 C 60 C 29 C 34 C 30 C 1,141 Cows 3 Goats C

=

Cows G

=

Goats Milk Sample Locations MQk Sample Control Location

-106

TABLE 20'OICEIImATIQIIS OF GNtIA EIIITTERS III VMlOUS FOOD PRODUCTS Results ln Units of pCI/g(rret) a 2 signa COLLECTINI SITE SAHPLE DATE DESGIIPT ION Be-7

'-40 1-131 Cs-134 Cs-137 Others 8 (Control)

L (Control)

L (Control)

T (Control)

S (Control) 9-07-82 Tcoratoes 9-07-82 Tamr atoes 9-07-82 Cabbage 9-Q7-82 11-05-82 11-10-82 Zucchlnl Beef Beef 4-23-82 Beef 5-Q3-82 Beef 5-05-82 Chicken 5-05-82 Eggs 5-06-82 Eggs 5-06-82 Chicken 5-06-82 Eggs 5-07-82 Chicken 5-10-82 Pork 5-10-82 Beef 5-12-82 Ch Icken 5-IZ-82 Eggs 9-07;82 Srrl ss Chard 9-07-82 SMIss Chard 9-07-82 Tan atoes 9-07-82 Cabbage

<0.5

<0.2

<0.3

<0.3

<0.3

<0.3

<0.5

<0.3

<0.2

<Q.3

<0.3

<0.3 0.14x0.07 0.12s0.07

<0.03

<0.07

<0.04

<0.04

<0.04

<0.04

<0.2

<0.2 5.210.5 5.gs0.6 6.lh0.7 3.5%0.4 3.210.4 6.5s0.7 3.5X0.5 r 8.4t0.8 2.4s0.3 6.0s0.6 5.4s0.5 3.8t0.5 7 4s0.7 9.3t0.9 2.1s0.2 2.4%0.2 I.Ba0.2 2.6t0.3 I.sio.2 I.gs0.2 Z.9'.3 2.5s0.3

<3.7

<0.03

<0.0

<Q.7

<0.8

<0.8

<1.0

<0.9

<0.4

<0.8

<0.5

<0.4

<Q.02

<0.02

<0.04

<0.01

<0.06

<0.06

<Q.OQQ

<0.1

<0.4

<0.4

<0.02

<0.02

<0.02

<0.02

<0.04

<0.02

<0.01

<0.02

<0.02

<0.02

<0.01

<O.DI

<0.003

<0.008

<0.003

<0.003

<0.004

<0.002

<0.01

<0.02

<0.9 '

<0.02

<0.03

<0.02

<0.02

<0.02

<0.02

<0.03

<0.04 0.03t0.02 0.02a0.01 0.08t0.02

<0.03

<0.02

<0.01

<0.01

<0.003

<0.009

<0.004

<0.004

<0.005

<Q.M3

<0.01 0.02xQ.OI A11<LLD All<LLD AII<LLD Al1<LLO All<LLD All<LLO AI'I<LLO A11<LLD Al1<LLO Al1<LLD Al1 <LLD AlI <LLD Al1<LLO All <I.LD AI I<LLD AII<LLO Al1<LLD All<LLD Al1<LLD All<LLD AII<LLD Al 1 <LLO

TABLE 20 (cont.)

CONCENTRATIONS OF GN!IA'IITTERS IN VARIOUS FOOD PRODUCTS Results

$n Units of PCI/g(Met) e 2 sIgma COLLECTION SITE SNIPLE DATE DESCRIPTION Be-7 X-40 1-131 Cs-134 Cs-137 Others I

CD 00 L (Control)

L (Control}

G (Control) 11-10-82 11-10-82 11-10-82 11-10-82 11-10-82 11-11-82 11-11"82 11-11-82 11-11-82 11-11-82 Chicken Eggs thicken Eggs Beef Beef Chicken Eggs Chicken Eggs

<0.2

<0.2

<0.3

<0.2

<0.2

<0.2

<0.2

<0.1

<0.2

<0.2 4.It0.4 2.0~0.2 3.6s0.4 1.4s0.2 2.8t0.3 3.5'.4

).Ix0.3 1.2i0,2 4.2<0.4 1.6'.2

<0.4

<0.2

<0.5

<0.3

<0.4

<0.4

<0.3

<0.2

<0.4

<0.3

<0.01

<0.01

<0.02

<0.01

<0.02

<0.01

<0.01

<0.01

<0.01

<0.01

<0.02

<0.02

<0.02

<0.01

<0.02 0.0210.01

<0.02

<0.01

<9.02

<0.02 All<LLD All<LUI All<LLD AI1<LLO Al1 <LLO AI I <I.LD All<LLD AII<LLD All<LLD AII<LLO

4 TALLLE 2L CONCENTHATLON OP Ohwhth Eh1LTTERS lN PASTURE GRASS Results in Units of pCL/tf (wet)

'v 6

Statton Code Saspte Type Ssupte Date Ra-226 be-7 Cs-134 Ru-LO6 Cs-137 Nb 95 Co 58 tts-54 Co 60 K-40 Ce-144 40 4

14 12 16 1

45 40 4

14 12 16 7

45 40 4

14 12 16 7

45 PsstUra Crass PastUra Cress Pasture Crdss Pasture Crass Pasture Crass PastUre Crass PddCUte Cresd Pasture Crass Pasture Crass PsstUte Crass Pasture Crass Pasture Cteds Pasture Ctass Pasture Crass Pasture Grass Pasture Crass Pastute Cress Pasture Grass Pasture Cress Pasture Grass Pasture Grads 01/26/82 07/26/82 07I26/82 01/26/82 07/26I82 07I26I82 01/26I82 08/23/82 08/23/81 08/23/82 08/23/82 08/23/82 08/23/82 08/23/SZ 09/20/82 09/20/82 09I20I82 09/20/81 09/20/82 09/10/82 09lzo/Sz 2.6lil.70

< 8.86

<0.255

< 7.80

<0.259

<3.98

<3.13

<2.43 2.81il 40 4 28i2,51 <O.IS9

<1.82 3.01i3,97

< 8.00

<0.22

<2.46

<2.91

<4.38

< 5.9$

< 7 ~ 8$

<0.146

<0.29t

<1.87

<3.03 4.SOC3.06 c 9.84 40.291

<2.15 40.273

<2.36

<0.586

<Oi341

<0.363 12.9 i3.40

<<1.41

<0.236 c2,01

<<0.545

<<0.197 40.294 17.0 i3.47

<1.30

<0.159

<LE 57

<<0.441

<0.211

<0.197 17.7 i2.39

<<0.896

<0.224

<1 ~ 92

<<0.175

<0.288

<<0.322 lb.1 i4.P3

<0.160 cia 43 cD,4SS c0.204 40.234 15.1 i2.9$

<L.SO

<<0.944

<0.280

<2.07

<<0.140

<0.362

<0.3$ 8 21.3 i4.20

<1.39

<Oi329

<2 ~ 24

<0.824

<<Oi390

<0.316 30.4 i4.93

<L.S6

<3.2L

<3 12

9. zzi7.09 <<0. 115

<2.02 0.347i0. 133

<2. 36 c0.133

<0.232

<0. 168 cl 1 2 L<<0.233 c2,45

<<0,206 c2,19 c0,744

<0,282

<0.148 23.4 i3.16

<1.32 22.2 i3.44

<1.38 2.28CL.53

< 9.43 40.119

<1.18

<2.8$

<2.60 6.9Li5.01 40.'L77

<2. 11

< 8.58

<<0.14L

<1.16

<0.198

<2.93

<<0.641

<0.215

<<0.119 27.1 i3.61

<<0.949

<<0.160 c3.07 c0,133" c0.260 c0.187 27 ~ 4 i3.48

<1.20

<<0. 161

<2. 54

40. 627

<O. 208

<0. 200

9. 3 1i2. LS

<<0. 936

<3.12

<3.10

<<2.52 8.28i5.26 40.201 cl.98

< 8.89

<0.219 c2. 16

< 6.83

<<0. 162

<1.84

2. 1 1il.54

<10.00

<<0.235 c2.41 2 ~64il.jl

< 8,01 40.211 cl.84 2.36CL.47 4 8.05 40.208

<1.82 1.73i0.847 c S.26 40.121

<1 ~ 29 3 ~ 13il '70 8 ~ 86i5 ~ 18 40 229

<2 09

<0.182

<<3.36

<0.639

<0.206

<D.24i4 23.1 i3.3L

<1.26 cD.235 c2,26 c0,722

<<0,279

<0.30$

19.S i3,43 cl. 13

<<0, 146 cl.bj c0,522

<0,18D

<0. 167 20.4 i3.31

<0.910

<<0.239

<2.07

<0.780

<0.311

<0.246 22 '

i3.6$

<1.42 c0.180

<1.80

<<0,611

<0.188

<0.185 12.2 i2,06 cl.29

<<0.184

<<2.11 40.479

<<0.261

<<0.230 17.3 i3.08 cl.04I

<0:L4L

<<Q.tbt

<1.32

<0.337

<0.1$ 8

<0.183 29.9 i2.87

<0.775

<1'7

<<0.5..1

<0.240

<0.261 12.9 i3.0L

<1.13 4.76il.86 10i9 i6izj <0.192

<2.00 40 238 c2.62

<<0.699

<<0.258

<0.314 19.7 i3.4$

<1.23 Error expressed as 2 sigma

TABLE 22 CANAL WATER DATA MONTHLY COMPOSITE ANALYSIS (1982)

Month (1982)

Inlet Canal Dissolved Suspended H

'olids PPM Solids PPM H

Dissolved Suspended Solids PPM Solids PPM January February March April May June July August September October November December 7.90 8.00 7.80 7.71 8.33 8.46 7.98 7 91 8.00 7.91 7.96 7 ~ 7'4 235.00 226.40 229'0 234.20 202'0 169 F 00 186.00 206.60 196'0 180.80 188'0 243.40 2'7 7'0 3.40 8.10 2 00 7'0 6.80 7 ~ 73 251.00 239.00 231+00 232.00 0.60 0,90 4.00 7.94 163.40 5 90 7.95 211.80 1 ~ 60 1o60 1.20 0.90 8;07

~ 7.85

~ 7'5 7'7 168.20 213.20 216'0 249.00 8.03 182.20 8.15 205.00 0'7 3 60 4.90 4.00 0 80 1+20 3'0 5+20 1.50 1 80 1.30 1.00

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~eoo le IOO toa Coarooee O

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Olyly SITH Ht)VIltONML'NTALSTATlOH AND TLD IIOCATIONS (SOu TlllsllH)

Stroke'O Corners Oeoee A

L E

ft M

0

~ oev lc

[SI en>>oooo ts y

p of el neo os O~a 4,

Coffers

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Qcdcr-Clonby Canter FULT us I

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Ofll lonfa al Cerhfr 7'vnHoo

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