ML18038A668

Annual Environ Operating Rept:Part B - Radiological Rept, 1983

ML18038A668
Person / Time
Site:	Nine Mile Point
Issue date:	12/31/1983
From:	Lempges T NIAGARA MOHAWK POWER CORP.
To:	Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I)
References
NMP-8414, NUDOCS 8405070085
Download: ML18038A668 (144)

Text

NMP-8414 NIAGARAMOHAWKPOWER CORPORATION

<<iIIIl4, NIAGARA l '

MOHAWK 300 ERIE BOULEVARD, WEST SYRACUSE. N. Y.

'I 3202 April 30, 1984 Dr. Thomas E. Murley Regional Administrator United States Nuclear Regulatory Commission Region I, 631 Park Avenue King of Prussia, PA 19406 SEF /pcjI RE:

Nine Mile Point Nuclear Station Unit ¹1 Facility Operating License DPR-63 Docket No. 50-220

Dear Dr. Murley:

In accordance with the Environmental Technical Specifications for Nine Mile Point Unit ¹1 (Appendix B. Section 4.6.1.a),

we are enclosing the Annual Radiological Environmental

~0 crating

~ge ort for the period January 1983 through December 1983.

Very truly yours, Thomas E.

Lempges Vice President Nuclear Generation TEL/klJF/lo Encl.- 2 copies cc:

Director, Office of NRR (17 copies)

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I ACCESSION NBR:S4OSO70085 OOC.DATE:~83/12/31-,

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NIAGARA MOHAW1 POWER CORPORATION ANNUAL ENVIRONMENTAL OPERATING REPORT PART B RADIOLOGICAL REPORT January 1, 1983 December 31, 1983 for NINE MILE POINT NtJCLEAR STATION UNIT 8 1 Facility Operating License DPR-63 Docket Number 50-220 8405070085 831231 PDR ADOCK 05000220 R

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TABLE OF CONTENTS P~ae List of Tables List of Figures I.

Introduction II. Description 1)

Sample Methodology 2)

Analysis Performed 3)

Changes to the 1983 Sample Program 4)

Exceptions to the 1983 Sample Program III. Evaluation of Environmental Data A)

Aquatic Program 1)'ladophora 2)

Dam Shoreline Sediment 3)

Fish 4)

Lake Mater B)

Terrestrial Progr am 1)

Air Particulates Gross Beta 2)

Monthly Air Particulate Composites 3)

Airborne Radioiodine (I-131) 4)

TLD (Environmental Dosimetry) 5)

Radiation Monitors 6)

Milk 7)

Milch Animal Census 8)

Human Food Products 9)

Soil 12 20 24 28 28 29 33 38 43 43 48

I

~

i)~

t

TABLE OF CONTENTS'Continued)

C )

Conclusion D)

References E)

Sample Summaries F)

Data Tables 1983 50 52 79

a,

LIST OF TABLES Table No Content P~ae Table 1

Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Aquatic Program 80 Table 2

Sample Collection and Analysis, Site Radiological Environmental Monitoring Program Terrestrial Program 81 Table 3 Concentrations of Gamma Emittexs in Cladophora Samples Table 4 Concentrations of Sr-90 and Gamma Emitters in Shoreline Sediment Samples 84 Table 5A Concentrations of Stxontium 89 and 90 and Gamma Emitters in Fish Samples (pCi/g-wet)

Table 5B Concentrations of Strontium 89 and 90 and Gamma Emitters in Fish Samples (pCi/kg-dry)

Table 6

Concentrations of Beta Emitters in Lake Water Samples 87 Table 7

Table 8

Concentrations of Tritium and S trcrtium 89 and 90 in Lake Water (Quarterly Composi,te Samples)

Concentrations of Gamma Emitters in Lake Water Samples 89 Table 9

Environmental Airborne Particulate Samples-Off-Site Stations, Gross Beta Activity 91 Table 10 Environmental Airborne Par ticulate Samples-On-Site Stations, Gross Beta Activity 92 Table, 11 Concentxations of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples 93 Table 12 Environmental Charcoal Cartridge Samples-Off-Site Stations, 1-131 Activity 97 Table 13 Environmental Charcoal Cartridge Samples-On-Site Stations, I-131 Activity Table 14 Table 15 Direct Radiation Measurements Quarterly Results g

Continuous Radiation Monitors (GM) 100

r

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 Strontium 90 in Mill (Monthly Samples)

Milch Animal Census Concentrations of Gamma Emitters in Various Food Products 105 106 108 109 111 Table 21 Concentrations of Strontium -90 and Gamma Emitters in Soil 114

C C'

~

I,IST OF FIGURES Content Figure 1 Off-Site Environmental Station and TLD Locations Figure 1-A Off-Site Environmental Station and TLD Locations (Southern) 116 Figure 2 Figu" e 3 Off-Site Monitoring Station Locations On-Site Environmental Station and TLD Locations 117 Figure 4

Food Crops, Meat, Poultry, and Egg Collections 119 Figure 5

Figure 6

Milch Animal Census and Milk Sample Locations New York State Hap with Regions 120

C

~ g

NINE MILE POINT UNIT 1 ANNUAL ENVIRONMENTAL OPERATING REPORT I ~

INTRODUCTION This report is submitted in accordance with Appendix B, Section 4 ~6.l.a to DPR-63, Docket No. 50-220 '

I ~

DESCRIPTION The requi ed sample collection and analysis schedule for QG' 1 is listed in Table 1 and 2 ~

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

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 equired by EAI to perfozm this study is used to perform the terrestrial sampling required for the site Radiological Envi onmental Monitoring Program (REMP)

~

Zn-plant canal sampling and emaining terrestrial sampling is performed jointly by the NMPNS and JAFNPP staffs Sam le Collection Methodolo Ao Lake Water The two indicator s tations are the respective inlet canals at NMPNS and JAFNPP ~

These samples are 'composited using sampling equipment which discharges into large collection tanks.

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

The control station sample is collected from the City of Oswego water intake.

Grab samples are drawn from the intake prior to treatment and are composited in a la ge sample containe

~

Quarterly composite samples are made up from aliquots of monthly samples '

~

B ~

Air Par ticulate/Iodine The air sampling stations a

e located in two rings surrounding the site.

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

The on-si te sampling ne twork is composed of nine stations The off-site air monitoring locations z ange six to seventeen miles fz om the site and are composed of six stations.

Air monitoring locations are shown on Figuzes 1 and 3 ~

II'ESCRIPTION (Continued) 1 ~

Sam le Collection Methodolo (Continued)

BE 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 sample" ~

Directly down st earn from the particulate filter is a

2 x

1 inch charcoal cartridge used to absorb airborne radioiodine, The samplers run continuously and the charcoal cartridges and particulate filters are changed on a weekly basis, or as equired by dust loading.

The particulate filters are composited for gamma analyses on a

monthly basis by location (two off-site, two on-site) after being counted for gross beta activity.

CD Milk Milk samples a

e collected in polyethylene bottles f om the bulk storage tank at each sampled farm.

Before the sample is drawn, the tank contents are agitated from th ee to five minutes to assure a

homogenous mixture of milk and butterfat.

Three gallons are collected during the first half of each month f om each 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" samplihg locations are found'n Figure 5 ~

(see Table 19 for identification of locations sampled.)

D.

Meat, Poultry and Eggs S emi-annually one kilog am 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 collected from each of three locations within a ten mile radius of the site.

Attempts are made to collect poultry and eggs at the same time as the meat samples The samples for poultry and eggs are frozen and shipped in insulated containers.

Whenever possible, samples are obtained from previously sampled locations Control samples are also obtained for

meat, eggs, and poultry.

(See Figure 4 '

II~

DESCRIPTION (Continued) 1 ~

Sam le Collection Methodolo (Continued)

E.

Human Food Crops Human food crops are collected during the, late

~ summer ha"vest 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 ar e collected.

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

Attempts are made to collect. at least'ne broadleaf type vegetable from each location.

The fruits and vegetables are chilled 'prior to shipping and shipped fresh in 'insulated containers.

Control samples are also obtained (See Figure 4.)

F.

Soil Samples Soil samples are requi ed to be collected eve y three years at the air monitoring locations and are analyzed fo" Sr-90 and GSA.

Soil samples were collected in 1983.

Thus, 9

on-site samples and 6

off-site samples were obtained.

The C off-site location, located approximately 17 miles from the site, is the control location.

G.

Fish Samples I

Available fish species are obtained f om collections du"ing the spring and fall.

Samples are collected from two of four possible on-site sample transects and one off-site sample t"ansect (See Figure 1).

Available species are selected under the following guidelines:

1. Samples of 0.5 to 1 kilogram of edible po"tions only for a

maximum of th ee species per location 2.

When independent species are not available at all three sample locations, a species may be divided into two samples for each location This procedure may be accomplished provided that a

sufficient sample size is available for the species in question at all three locationsi Selected fish samples.

are frozen immediately af ter collection and processing and are segregated by species and location.

Samples are shipped frozen within two weeks in insulated containers.

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

Sedimen t sample s 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

II'ESCRIPTION (Continued) 1 Sam le Collection Methodolo (Continued)

I'ladophora from two on-site locations and one off-site location.

sample containers,

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

J.

TLD (direct radiation)

Thermoluminescent d,osimeters (TLD's) are used to measure direct radiation in the JAF/NMP-1 environment.

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

TLD's are classified as either on-sita; off-site, special interes t areas, or control locations.

On-site TLD's are located within the sita property boundary and are arranged in an approximate ring a ound the generating facilities (Figure

3) ~

Off-site TLD's a

e located outside of the site property boundary and are arranged a

ing approximately 7-11 miles out from the site.

Special interest TLD's are located at high population locations such as indust ial sites,

schools, etc.

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

These TLD' are positioned to <the east,

west, and south of the site up to 20 miles away TLDs used during the fi st th ee quarters of 1983 were composed of CaSOg chips (two chips per dosimeter) and were sealed in polyethylene packages to ensure dosimeter integrity.

Two dosimete s (four chips) were placed at each location TLDs used during the fourth quarter of 1983 were composed of rectangular teflon wafers impregnated with 25>>

CaSOl,:

Dy Phosphor.

These were also placed in polyethylene packages to ensure dosimete" integrity.

TLD packages were placed in plastic holders or were affixed to supporting su faces by tape sealing.

TLDs were collected, replaced and evaluated on a quarterly basis.

K. Special Samples Special samples of shoreline sediment were collected during March of 1983 to help in evaluating samples collected during the fall of 1982 and sampLes collected du"ing the spring and fall of 1983 'hese samples (March 1983) were collected at the normal indicator and control locations.

No other special samples were collected during 1983 for the Radiological Environmental Monitoring Program.

II~

DESCRIPTION {Continued) 2 ~

Analyses Performed The Radiological Environmental Monitoring Program (EU2P) samples were analyzed by; Radiation Management Corporation, Teledyne

Isotopes, and by the Site Environmental Laboratory during 1983

'he following samples were analyzed by the site'.

Air particulate filter (weekly gross beta analysis)

Air particulate filter (monthly gamma spectral analysis)

Airborne radioiodine cartridge (weekly gamma spectral analysis)

Lake ~ater (monthly gamma spectral analysis)

The remainder of the sample analyses, as outlined in Table 1 and 2, were analyzed by Radiation Management Corporation (January-June) and by Teledyne Isotopes

{July-December)

~

3.

Chan es to the 1983 Sam le P o

am A ~ In January of 1983, Radiation Management Corporation (the site's analytical contractor) was purchased by Teledyne Isotopes of

Westwood, New Je sey.

The Radiation Management Corporation, facility continued to analyze environmental samples fo the site under contract from Teledyne Isotopes.

S ta ting approximately July of 1983, all operations were transfe ed.'f om Radiation Management Corporation' facility to Teledyne Isotope'

Westwood, New Jersey facility.

Effective July > all envi onmental radiological

~ samples were analyzed by either Teledyne Isotopes or the site Environmental Laboratory.

The transition from the Radiation Management Corporation facility to the Teledyne Isotope facility proceeded well with minimal difficulties.

BE Milk sample location 14, located ESE from the site at 9.8 miles, was deleted from the milk sampling program in June of 1983.

Milk has been collected from this location for many years in the past.*

However, several other mill sampling locations had been

located, as a result of milch animal censuses conducted during

1982, that demonst ated greater radionuclide deposition potentials.

Since location 14 had a

low potential fo deposition,.

as determined by D/Q values, this location was deleted.

Milk sample locations 50, 55 and 60 were added to the milk sampling program at the initiation of the milk sampling season (May) ~

These locations were

added, as a result of the milch animal censuses conducted during 1982 'hese locations

,demonstrated average potentials for radionuclide deposition,.

as determined by D/Q values'

II'ESCRIPTION (Continued) 3 ~

Changes to the 1983 Sam le Program (Continued)

Milk sampl~ location 60 was deleted after May of 1983 This

location, as noted above, was added to the program in May.

Upon review of all the new and old milk sample locations in May, the two locations with the lowest D/g values were deleted.

These locations were location 60 and location 14 (noted above)

~

4.

Exce tions to the 1983 Sample Program A,. Environmental Radiation Monitors 1

Environmental radiation monitor at F. on-site station was inoperable from 1000-1200 hours on January 13, 1983 because of t ansmission line work.

2.

Environmental radiation monitor at C off-site station was inope able March 29>

1983 (0930 hou s) to April 7, 1983 (1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />) because of an electronic failure.

3 ~

Environmental radiation monitor at F on-site station was inoperable from May 25, 1983 (1145 hours0.0133 days <br />0.318 hours <br />0.00189 weeks <br />4.356725e-4 months <br />) to May 25, 1983 (2040 hours0.0236 days <br />0.567 hours <br />0.00337 weeks <br />7.7622e-4 months <br />) because of an electronic failure.

4.

Environmental radiation monitor at F on-site s tation was inope able from June.30, 1983 (1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />) to July 5, 1983 (1500.ho'urs) bec'ause of damage caused to the s tation,when it was struck by an automobile.

5.

Environmental radiation monitor at I on-site station was inoperable from July 22, 1983 (0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />) to July 26, 1983 (1010 hours0.0117 days <br />0.281 hours <br />0.00167 weeks <br />3.84305e-4 months <br />) because of damage caused to the station when

, it was hit by lighting.

6.

Environmental radiation monitor at G on-site station was inope able from July 26, 1983 (1328 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.05304e-4 months <br />) to.

August 3, 1983 (1505 hours0.0174 days <br />0.418 hours <br />0.00249 weeks <br />5.726525e-4 months <br />) because of an electronic failure.

7, Environmental radiation monitor at H on-sita station was inoperable from August 22, 1983 (1430 hours0.0166 days <br />0.397 hours <br />0.00236 weeks <br />5.44115e-4 months <br />) to August 25, 1983 (0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />) because the monitor had inadvertently been left off during a

outine inspection on August 22'he monitor was turned on du"ing the next scheduled routine inspection on August 25 '

~

Environmental adiation monitor at I on-site station was inoperable from August 24, 1983,(0940 hours0.0109 days <br />0.261 hours <br />0.00155 weeks <br />3.5767e-4 months <br />) to August 25, 1983 (1445 hours0.0167 days <br />0.401 hours <br />0.00239 weeks <br />5.498225e-4 months <br />) because of an electronic failur e.

. -6

II~

DESCRIPTION (Continued) 4 ~

Exceptions to the 1983 Sample Program (Continued) 9 ~

Environmental radiation monitor at C off-site station was inoperable from September 1,

1983 (0725 hours0.00839 days <br />0.201 hours <br />0.0012 weeks <br />2.758625e-4 months <br />) to September 13, 1983 (0922 hours0.0107 days <br />0.256 hours <br />0.00152 weeks <br />3.50821e-4 months <br />) because of an electr onic failure ~

The spare radiation monitor was not available because it was being used in I on-site environmental

station, thus twelve days elapsed before the station could be returned to service.

10 ~

Environmental radiation monitor at I on-site station was inoperable from December 5,

1983 (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) to December 16 1983 (1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br />) because of an electronic failure Environmental radiation monitor at I on-site s tation was inoperable from December 27, 1983 (1005 hours0.0116 days <br />0.279 hours <br />0.00166 weeks <br />3.824025e-4 months <br />) to December 29, 1983 (1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />) because the monitor was inadvertently left in the zero position on the trip check adjust knob.

In this

position, the monitor was inoperable.

The monitor was returned to service during the next scheduled routine inspection on December 29, 1983.

E. Environmental Air Sampling Equipment Environmental air sample equipment at.F on-site station was inoperable from 1000-1200 hours on January 13, 1983 because of transmission line work.

2 ~

3.

Environmental air sample equipment a t D2 on-sit e statio n was inoperable from January 17, 1983 (1406 hcurs) to January 20, 1983 (1310 hours0.0152 days <br />0.364 hours <br />0.00217 weeks <br />4.98455e-4 months <br /> )

because of a

mechanical failure with the vacuum pump.

Environmental air sample equipment a t Dl on-site statio n was inoperable from April 7,

1983 (1420 hc,urs) tc April 7, 1983 (1620 hours0.0188 days <br />0.45 hours <br />0.00268 weeks <br />6.1641e-4 months <br />) because of a defective vacuum pump and fuse

~

4.

Environmental air sample equipment at J on-site station was inoperable from April 15, 1983 (0400 hours0.00463 days <br />0.111 hours <br />6.613757e-4 weeks <br />1.522e-4 months <br />) to April 18, 1983 (1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br />) because of an electrical problem with the vacuum pump 5.

Environmental air sample equipment at K on-site station was inoperable from June 6,

1983 (0810 hours0.00938 days <br />0.225 hours <br />0.00134 weeks <br />3.08205e-4 months <br />) to June 6,

1983 (1320 hours0.0153 days <br />0.367 hours <br />0.00218 weeks <br />5.0226e-4 months <br />) because of a defective vacuum pump.

6.

Environmental air sample equipment at I on-site station was inoperable from June 13, 1983 (0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />) to June 13, 1983 (1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br />) because of a defective vacuum pump.

)k II'ESCRIPTION (Continued) 4.

Exce tions to the 1983 Sample Pro ram (Continued) 7 ~

Environmental air sample equipment at G off-site station was inoper'able from.June 14, 1983 (1130 hours0.0131 days <br />0.314 hours <br />0.00187 weeks <br />4.29965e-4 months <br />) to June 15, 1983 (1530 hours0.0177 days <br />0.425 hours <br />0.00253 weeks <br />5.82165e-4 months <br />) because of a blown fuse.

8 ~

Environmental air sample equipment at J on-site station was inoperable from June 16, 1983 (1100 hours0.0127 days <br />0.306 hours <br />0.00182 weeks <br />4.1855e-4 months <br />) to June 20, 1983 (1350 hours0.0156 days <br />0.375 hours <br />0.00223 weeks <br />5.13675e-4 months <br />) because of a defective vacuum pump.

9 ~

Environmental air sample equipment at F on-site station was inoperable from June 30, 1983 (1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />) to July 5, 1983 (1340 hours0.0155 days <br />0.372 hours <br />0.00222 weeks <br />5.0987e-4 months <br />) because of damage caused to the station when it was struck by an automobile, 10 ~

Environmental air sample equipment at Dl off-site station was inoperable from July 19, 1983 (0820 hours0.00949 days <br />0.228 hours <br />0.00136 weeks <br />3.1201e-4 months <br />) to July 20, 1983 (1046 hours0.0121 days <br />0.291 hours <br />0.00173 weeks <br />3.98003e-4 months <br />) because of a defective vacuum pump ~

Environmental air sample equipment at I on-site station was inoperable from July 22, 1983 (0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />) to July 25, 1983 (1330 hours0.0154 days <br />0.369 hours <br />0.0022 weeks <br />5.06065e-4 months <br />) because of damage caused to the station when it was hit by lighting Environmental air sample equipment at G on-site station was inoperable from July 26, 1983 (0800 hours0.00926 days <br />0.222 hours <br />0.00132 weeks <br />3.044e-4 months <br />) to July 26, 1983 (1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />) because of a defective vacuum pump.

13

'4.

Environmental air sample equipment at G off-site station was inoperable from September 13, 1983 (1059 hours0.0123 days <br />0.294 hours <br />0.00175 weeks <br />4.029495e-4 months <br />) to September 13, 1983 (1315 hours0.0152 days <br />0.365 hours <br />0.00217 weeks <br />5.003575e-4 months <br />) because of a,

defective vacuum pump.

Environmental air sample equipment at H on-site station was inoperable from September 21, 1983 (0414 hours0.00479 days <br />0.115 hours <br />6.845238e-4 weeks <br />1.57527e-4 months <br />) to S eptember 22, 1983 (1041 hours0.012 days <br />0.289 hours <br />0.00172 weeks <br />3.961005e-4 months <br />) because of a

def ective vacuum pump Environmental air sample equipment at J on-site station was inoperable from September 26, 1983 (1335 hours0.0155 days <br />0.371 hours <br />0.00221 weeks <br />5.079675e-4 months <br />) to September 30, 1983 (1040 hou"s) because of a defective fuse.

16 ~

Environmental air sample equipment at J on-sita station was inoperable from September 30, 1983 (1910 hours0.0221 days <br />0.531 hours <br />0.00316 weeks <br />7.26755e-4 months <br />) to October 3, 1983 (1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />) because of a defective fuse.

17 Environmental air sample equipment at J on-site station was inoperable from October 5,

1983 (0950 hou s) to October 5, 1983 (1707 hours0.0198 days <br />0.474 hours <br />0.00282 weeks <br />6.495135e-4 months <br />) because of a defective vacuum pump

II~

DESCRIPTION (Continued) 4.

Exceptions to the 1983 Sample Program (Continued) 18 'nvironmental air sample equipment at H on-site station, was inoperable from December 1,

1983 (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) to December 5, 1983 (1000 hou s) because the vacuum pump was inadvertently left in the off position during a

outine inspection on December 1.

The vacuum pump was returned to s ervice on December 5

during the subsequent routine inspection.

C. Environmental The moluminescent Dosimeters (TLD)

,, 1.

TLD number 6

was vandalized during the third quarter of 1983 (June 30, 1983 Septembe 30, 1983) and no results were available.

2.

TLD number 24 was vandalized during the third qua"ter of 1983 (June 30, 1983 " September 30>

1983) and no results were available.

I 3.

TLD number 48 was vandalized during the thi d quarter of 1983 (June 30, 1983 Septembe" 29>

1983) and no results wer e available.

4 ~,TLD number 61 was vandalized du ing the thi d quarter of 1983 (June 30, 1983 - September 29>

1983) and no results were available'.

TLD number 51 was vandalized during the third qua ter of 1983 (June 29, 1983 " September 29, 1983) and the fourth qua"ter of 1983 (September 29, 1983 - January 5,

1984) and no results were available.

TLD number 51 will be relocated during 1984 as a result of the continued vandalism.

DE Radiological Fish Sample Data One of the three fish samples collected at the Nine Mile Point location for Sr-89 and Sr-90 analysis was los t in laboratory processing while performing the strontium procedure.

Since the Environmental Technical Specifications equire one sample at this location and three were collected (two ext a), this is not a violation of the specifications III~

EVALUATION OF ENVIRONMENTAL DATA.

The results of.the 1983 Radiological Environmental Monitoring Program (REMP) must be put into perspective considering the natural processes of the environment and the past radiological data.

Seve al factors must be realized in order.to effectively evaluate anti interpret the data.

XXI.

EVALUATIONOF ENVIRONMENTAL DATA (cont.)

There are three separate groups of radionuclides that were detected in the environment during 1983.

A few of these adionuclides 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 radioactive elements

~

Background radiation as a function of primordial

,radioac tive elements and cosmic radiation of s olar origin offer s a

constant exposur e to the environment and man.

These radionuclides, s uch 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 uppe" 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 "educed the inventory through the decay of short lived radionuclides, deposition, and the removal (by natu al processes)

. of radionuclides from the food chain such as by the process of sedimentation.

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

In each

case, the usual radionuclides associated with nuclear detonations were detected seve"al months afterwards and then afte" 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 or deposition f om this test has influenced the background radiation 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 from fallout related adionuclides 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 natu al background radiation.

guantities of Nb-95, Zr-95, Ce-141, Ce-144, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and Co-60 were typical in air particulate samples during 1981 and have a weapons test origin.

The third group of radionuclides detected in the environment during 1983 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 are 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.

Radionuclides falling into this category (as applicable to the 1983 Nine Mile Point Environmental Program) include Cs-137i Cs-134>

I-131>

Mn-54, La-140, and Co<<60'he dose to man as a

esult of these radionuclides is small and significantly.less than the radiation exposure from naturally occurring sources of radiation and from fallout.

-10

III.

EVALUATION OF ENVIROMiENTALDATA (conti )

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 zeport the data collected during

1983, but also to assess the significance of the radionuclides detected in the environment 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 'ifficult.

Therefore, concentrations in one sample that are two times the concentration of

another, for

example, are not significant overall.

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

The 1970 per capita dose rate (Eisenbud) was determined to be 209 mrem per year.

This average dose includes such exposure sources as natural, occupational, weapons

testing, consumer

products, medic&, etc.

The 1970 per capita dose rate due 'to natural sources was 130 mrem per year.

Of this dose, approximately 20 mrem per year is zeceivea by the gonads and other soft tissues and an additional 15 mrem per year is.

received by the bone tissue for a 70 kg (U5 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

>kiev') ~

The 1970 per capita dose rate dueto the nuclear fuel cycle is 0.0028 mrem per year

~

Background

gamma radiation around the Nine Nile Point Site, as a result of radionuclides in the atmosphere and the

ground, accounts for approximately 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

much smaller extent of a man-made origin from weapons testing.

A 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.

'ables 3

through 8

demonstrate the analytical results for the aquatic media sampled during the 1983 samplin~

program.

Aquati c samples were collected at four possible indicator locations.

ThE, locations (on-site transect designations) used for on-site sampling were NNPV (01),

N>IPP (02),

JAF (03),

and RiPE (04)

(see Figure 1).

Because of the unavailability of various sample

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

NMPW and NMPP were combined into location

%IPP NHPE 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.

-11

III.

EVAIUATIONOF ENVIRONMENTAL DATA (cont~)

AD 1.

Cladophora Table 3 The species glomerata is the dominant species of Cladcphora in a long filamentous algae attached by a holdfast to rocks and other submerged substrates Colonization and propagation of Cladophora extends out to a

depth of 20 feet.

The ion g, are constantly being broker off by wave activity.

Maximum growth usually occurs in water approximately ten to fifteen feet

deep, but this will vary, depending upon turbidity.

June or early July, 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 (OG) or control location and at two on-site or indicator locations'

'he indicator locations were in the proximity of the Nine Mile Point (NMPP-02)

and, the James A.

FitzPatrick (JAF-03) facilities.

The control location 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 related operations k-40 anc Be-7 are naturally occurring and were noted in both the indicator locations and the control location.

K-40 ranged in concentration from 3.52 pCi/g (wet) to 6.07 pCi/h (wet) ~

Be-7 ranged from 0.52 pCi/g (wet) to 0.67 pCi/g (wet).

The, concentrations detected for K-40 and Be-7 were approximately the same as concentrations noted during 1982 '

third naturally occurring radionuclide detected in the June samples was Th-228.

This radionuclide was detected at the he% location only and was found at a concentration of 0.05 pCi/g (wet) ~

Cs-137 was detected at all three locations during

the, June coll'ections.

Concentrations at the indicator locations were slightly greater than the control locationi Cs-137 at the NMP location showed a concentration of 0,06 pCi/g (wet) and at the JAF location showed a

concentration of 0.04 pCi/g (wet).

to be a result of past weapons testing based on 1983 data and historical data.

Cs-137 was detected at the control location at 0.03 pCi/g(wet) which was'lightly less than the Cs-137 concentrations detected in the indicator samples.

III.

EVALUATIONOF ENVIRONMENTALDATA (Continued)

(*

A portion of the Cs-137 detected at the indicator locations may be a result of ope ations of the site Cs-137 at the control sample location is a result of past weapons testing

~

Co-60 was detected at the NMP location during June at a

concentration of 0.09 pCi/g (wet) and at the JAF location at a

concentration of 0 ~ 08 pCi/g (wet) ~

Co-60 was not detected at the control location.

Although Co-60 has been 'detected at the control location in the past, it has not been detected since 1979 ~

During 1979 Co-60 was detected at a concentration of 0 ~ 01 pC'i/g (wet) and was a result of weapons testing during years prior to 1979.

Co 60 detected at the NMP and JAF locations during June of

1983, however, was a

esult of operations at the site.

A third fission product radionuclide

detected, in addition to Cs-137 and Co-60, was Mn-54 Mn-54 was detected at the NMP and JAF locations at concentrations of 0.02 pCi/g (wet) and 0.01 pCi/g (wet) respectively.

Mn-54 was not detected at the control location.

The absence of Mn-54 at the control location and presence at the indicator locations is indicative of operations at the site.

Mn-54 has not been detected at the initiated.

No othe" adionuclides were detected in the June 1983 samples using gamma spect al analysis S amples collec ted during August also showed detected concentrations of K-40 and Be-7 ~

K-40 was detected a t all three sample locations and ranged in concentration from 2.08 pCi/g (wet) to 3.12 pCi/g (wet).

Be-7 was detected at all three locations and ranged in concentration from 0.37 pCi/g (wet) to 0'5 pCi/g (wet) ~

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

Th-228 was detected only at the NMP location at the concentration of 0'2 pCi/g (wet) ~

Cs-137 was detected only at the NMP and JAF locations at concentrations of 0'4 pCi/g (wet) and 0.03 pCi/g (wet) respectively.

The detected concent ations are very small and are above the lower limit of detection for the August control sample.

As noted above for Co-60, it is difficult to assess the presence of Cs-137 at the NMP and JAF locations and not at the control location because of the minute quantities detected.

Cs-137 in Cladophora samples has historically been attributed to past weapons

testing, however, a portion of the Cs-137 detected in the August samples can be attributed to operations at the site.

-13

ZIZ.

EVALUATION OF ENVIRONMENTAL DATA (Continued).

Co-60 was detected at the NMP and JAF locations during August at concentrations of 0 ~ 09 pCi/g (wet) and 0 ~ 11 p(.i/g (wet) respectively.

Co-60 was not detected at the control location As noted

above, Co-60 has been detected at the control location in the past but not since 1979 ~

The 1979 detected concentration was a result of past weapons tes ting.

Co-60 detected during August 1983, however, was a result of operations at the site.

Mn"54 was also detected at the NMP and JAF locations at concentrations of Oi02 pCi/g (wet) and 0.04 pCi/g (wet) respectively.

Mn-54 was not detected at the co'ntrol sample location.

Mn-54 at the NMP and JAF locations is indicative of ope ations at the site S amples 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 att ibuted to the 1980 Chinese nuclea weapons test.

The half-life of these radionuclides ange from 33 days to 365 days with the exception of cesium (Cs-137 has a 30 year half-life).

During

1983, these weapons testing adionuclides we e

not detected with the exception of Cs-137.

This observation is consistent with obse vations in 1982 The absence of these radionuclides is attributed to nuclear decay and ecological cycling.

Review of past environmental data shows that the concentrations of naturally occurring K-40 and Be-7 have fluctuated greatly.

K-40 at all locations has anged from 2'

pC1/g (wet) to 28.0 pCi/g (wet) ~

Be-7 at.all locations have anged from 0.05 pCi/g (wet) to F 00 pCi/g (wet) ~

Different years showed different peak concentrations for the two radionuclides.

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

The annual mean concent ation in 1979 (0.15 pCi/~-wet) was higher than 1980 (0 ~ 02 pCi/g-wet).

1981 (0 ~ 36 pCi/guet) was greater than the preceding year.

The annual mean for the indicator samples during.1982 was 0 ~ 015 pCi/g (wet) whMh represented a decrease when compared to 1981.

During 1983>

Cs-137 at the indicator locations averaged 0 ~ 04 pCi/g (wet) ~

This epresented an increase over the 1982 concentration 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 i10 pCi/g (wet.)

respectively.

Fluctuations in the Cs-137 concent ations is a

resul t of pas t weapons tes ting.

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 testi The 1982

" annual mean was 0 ~ 007 pCi/@~et which represented a

decrease.

During 1983 Cs-137 was detected a t 0 ~ 03 pCi/g (wet) ~

This was an increase when compared to 1982 ~

-14

III'VALUATIONOF ENVIRONMENTAL DATA (Continued)

Co-60 during 1979-1982 at the indicator locations averaged 0.16, 0.02, 0 ~ 55 and 0 ~ 02 pCi/g (wet) respectively.

During

1983, Co-60 averaged 0.09 pCi/g (wet) which was a general decreas e when compared to 1979-1982

~

Co-60 at the control location was detected only once during 1979 ~

During

1983, Co-60 was no t detected at the control location.

Mn-54 during 1979-1982 at the indicator locations

averaged, in pCi/g (wet)

> 0.12, 0.04>

0 14 and not

detected, respectively.

During

1983, Mn-54 averaged 0.02 pCi/g (wet) which was a decrease.

Mn-54 at the control location was not detected during 1979-1982, nor was it detected during 1983 The significance of the detected radionuclides in Cladophora samples during 1983 is very small.

This sample media has a high bioaccumulation factor for most radionuclides and the results of "the analyses can be used, for the most part, in a qualitative sense only.

Thus, Cladophora does not reflect the grows.

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

is not a human food source For the purpose of illustration, a

comparison of hypothetical doses can be calculated on the basis In'this case, Cladophora is assumed to be consumed by an adult at an annual rate equal to green leafy vegetables, i.e.

64 kg/year (Regulatory Guide 1.109).

A conse vative assumption can also be made that the mean Cs-137 concentration for 1983 at the indicator locations minus the mean control location concentration is a result of operations at the site

Further, it is assumed that positive Co-60 and Mn-54 concentrations a e a result of ope ations at the site.

Maximum whole body and critical organ doses to an adult a

e as follows:

Radionuclide Cs-137 Co-60 Mn-54 Whole Body Dose*

0,046 0 ~ 027 0 001 Critical Organ Dose+

0.070 (liver) 0.232 (GI tract) 0.018 (GI t act)

The projected doses are based on maximum consumption rates and radionuclide concentrations of 0.01 pCi/g (wet) for Cs-137, 0 09 pCi/g (wet) for Co-60 and 0'2 pCi/g (wet) for Mn-54'he doses are very small and can be put into perspective by making a

comparison to the natural backg ound dose as a

result of increases in altitude and cosmic radiation.

• Dose in mrem per year.

III'VALUATIONOF ENVIRONMENTALDATA'(Continued)

(

~ )

The combined whole body dose as a result of Cs-137>>

Co"60.

and Mn-54 is 0 ~ 074 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 13 5 days.

A, 2 ~ Dam Shoreline Sediment - Table 4

Shoreline sediment samples were collected twice during 1983

'ollections we"e made in May and November at one off>>site or control location and at one indicator location (h>IPP&2) ~

In

addition, an additional set of samples was collected in March, 1983, in an attempt to help evaluate the Novembe" 1982 and May and November 1983 sample results for Cs-137'he results of these extra samples collected at the control location and indicator location are included on Table 4 ~

S everal radionuclides were detected in sediment samples using gamma spectral analysis.

These radionuclides ranged from naturally occurring primordial radionuclides to man-made radionuclides.

K-40 was detected at both the control location and indicator location for both collection periods'during 1983.

K-40 ranged in concentration from 12.0 pCi/g (dry) to 15 '

pCi/g

( d y) at the control location and F 7 pCi/g (dry) to 15 2 pCi/g (dry) at the indicator locations Ra-226, Th-232 and Th-228, in addition to K-40, were also detected and 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 0'1 pCi/g (dry) to 1.02 pCi/g (dry) at the indicator location and 0 33 pCi/g (dry) to 1 21 pCi/g (dry) at the control location.

Th-232 ranged from 0.31 pCi/g (dry) at the indicator location to 0.31 pCi/g (dry) at the control location (analyzed in the March samples only) ~

Th-228 ranged from 0.38 pCi/g (d y) to 0.55 pCi/g (dry) at the indication locations and 0'0 pCi/g (d y) to 0 62 pCi/g (dry) at the control location (analyzed in the May and November samples only) ~

Cs-137 was detected in three of the six samples collected during the year.

Cs-137 was detected in three of the indicator samples and none of the control samples The concentrations detected were small and are for the most part indicative of operations at the site.

Cs-137 was detected in both of the indicator samples

( i.e.,

May and November) at concentrations of 0 F 85 pCi/g (dry) and 1,81 pCi/g (dry), respectively Cs-137 was also detected in the extra indicator sample collected during March at a

concentration of 0.16 pCi/g (dry).

As noted above>

Cs-137 was not detected in any of the control samples, although Cs-137 has been routinely observed in the past in control samples'16

III+

EVALUATIONOF ENVIRONMENTAL.DATA (Continued)

A.

2.

Dam Shoreline Sediment Table 4 (cont.)

Co-60 was detected in two of the three indicator sample s collected.

Co-60 was detected at 0.14 pCi/g (dry) in the May sample and at 0.36 pCi/g (dry) in the November sample Co-60 was not detected in the extra sample collected in March.

The control location samples showed no detectable Co-60 ~

Co-60 has not been noted in previous years at the control location.

Co-60 detected during 1983 is a result of operations at the site.

Cs-134 was detected Ln one of the indicator samples during November at 0.09 pCi/g (dry) ~

Cs-134 was not detected in any of the control samples.

Previous shoreline sediment samples have not shown Cs-134 at either the indicator or control locations

~

Cs-134 in the November indicator sample is a

result of ope ations at the site.

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

The 1983 samples were analyzed for Sr-90 and showed detectable concent ations in one of the four required samples.

Sr-90 was detected in the sample f om the indicator location.

The indicator sample (collected in Novembe

)

showed a

Sr-90 concentration of 0 ~ 022 pCi/g (d y) ~

Sr-90 has been detected intermittently in the past at the control location and indicator.

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 (d y) 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'ocation during 1983 (0.022 pCi/g dry).

Sr-90 is considered to be representative of background levels as a result of weapons testing 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 extra control sample collected in March.

The extra indicator sample 'collected in Ma"ch was lost during the laboratory analysis of Sr-90

'valuation of historical data (1979-1982) shows that Cs-137 has ranged from 0.22 pCi/g (dry) in 1979 to 0'7 pCi/g (dry) in 1980 at the control location.

Cs-137 at the indicator location has r anged from 0 ~ 01 pCi/g (dry) in 1982 to 0 ~ 80 pCi/g (dry) in 1982.

1983 results ranged from 0.16 pCi/g (dry) to 1.81 pCi/g (dry) at the indicator location Cs-137 was not detected at the control location

Overall, the control location results have decreased since 1979, while the indicator results have increased starting with the one 1982 sample of 0.80 pCi/g (dry) ~

-17

III.

EVALUATIONOP ENVIRONMENTALDATA (Continued)

A ~

2.

Dam Shoreline Sediment - Table 4 (cont.)

The evaluation of past Co-60 data indicates that Co-60 has not been 'etected in the past at 'ither indicator or contzol locations since 1979 with the exception of one sample fron the indicator location in 1982 (0.16 pCi/g-d~) ~

Results from 1983 show that Co-60.was detected in both of the required indicator samples (0.14 and 0.36 pCi/g"dry).

Co-60 has not been detected in any of the control samples from 1979-1983

~ It appears that Co-60 concentrations at the indicator 'location are increasing (from not previously detected).

Evaluation of Sz-90 his torical data since 1979 shows that concentrations have generally decreased at the control location from a maximum of 0 ~ 04 pCi/g (dry) in 1979 to not detected in 1981 and 0.0043 pCi/g (dry) in 1982 ~

Sr-90 a t the indicator location has gene" ally remained the same f om 1979-1981 but showed an increase in 1982 The increase, as noted above, is c onsis tent with past cont"ol sample data (1980) and may not necessarily demonst ate an increasing t end.

During 1983~ Sr-90 at the control location was not detected.

Sr-90 at the indicator location showed a concent ation that is approximately equal to that of 1982.

S amples collected during November 1982

.showed levels of Cs-137 (0.80 pCi/g - dry) that indicated an increased concentration of this radionuclide in comparison to previous yea s

(1979-1981)

~

In addition, Co-60 was detected in the November 1982 sample at a

low concentration (0 ~ 16 pCi/g-dry) ~

Co-60 had not been detected previous to the November 1982 sample.

In view of the increase.

in Cs-137 concentrations and the appearance of Co-60 shoreline sediment samples from the NMP location, extra samples were collected in Ma"ch 1983 ~

These samples showed no positive detection of Co-60 and the Cs-137 concentration was less than the November 1982 concentration (0. 16 pCi/g-dry).

Subsequent samples collected in May and November

1983, which were the normal Technical Specif ication

samples, showed Co-60 to be detected again.

Co-60 in May 1983 was detected at a

concentration similar to the Novembe" 1982 concentration (0.14 pCi/g-dry) ~

The November 1983 sample showed an increase in the Co-60 concent ation to 0'6 pCi/g (dry).

The May and November 1983 samples showed Cs-13/

concentrations of 0.85 pCi/g (dry) and 1.81 pCi/g (dry), respectively These samples demonstrated an increase in the Cs-137 concentration up to 1.81 pCi/g (dry) ~

In addition to Cs-137 and Co-60, Cs-134 was detected in the November 1983 indicator sample.

Cs-134 had not been detected previous to 1983 in either control or indicator samples.

Cs-134 was detected at 0.09 pCi/g (dry) ~

These

'concentrations, although greate" than previous concentrations at this location, have no significant dose consequences to members of the public in regards to 10 CFR 50, Appendix I'n assessment of Co-60, Cs-134, and Cs-137 in shoreline sediment samples is included at the end of this section

-18

III.

EVALUATIONOF ENVIRONMENTALDATA (Continued)

A 2.

Dam Shoreline Sediment.Table 4 (conti)

The source of the elevated Co-60, Cs-134 and Cs-137 concent ations is believed to be liquid effluents from the site.

Site liquid effluents during 1982 and 1983 were well within Technical Specification limits, although the quantities of Co-60, Cs-137, and Cs-134 did increase during the first three quarters of 1983.

Other potential sources of radionuclides in liquid effluents are the sewage treatment facility effluent and the s torm sewer drainage which accep ts its most significant d ainage from building foundation

sumps, roof

drainage, and roadway drainage.

Grab samples are obtained weekly from <he storm sewer drainage system and from the sewage treatment plant effluent which both discharge at points near the %P shoreline sediment sample location.

Review of, weekly data showed no detectable concentrations of Co-60, Cs-137 or Cs-134 from the end of 1982 through 1983 ~

The presence of Co-60, Cs-137, and Cs-134 in other aquatic sample media shows no similar tends, as observed in sho eline sediment.

Algae or Cladophora esults for 1983 gene ally showed lower concentrations of these radionuclides when detected.

In additi'on, fish sample results showed no detectable Co-60 nor Cs-134 Cs-137 was detected in indicator fish sample as well as control samples with no s ignifscant differences be tween the two.

Zt appears, therefore, that the increased concentrations of Cs"3.37, Co-60 and Cs-134 a e. specific,to shoreline sediment and not other aquatic sample medias.

Shoreline sediment samples will continue to be collected and analyzed as required by the Environmental Technical Specifications.

These samples may be supplemented with additional samples, if necessary, in an effort to fu ther assess any possible impacts.

The impact of the 1983 shoreline sediment sample results is minimal and can be evaluated by pro)ecting a dose to man using s tandard Regulatory Guide 1.109 methodology.

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

The presence of Co-60, Cs-134 and Cs-137 is a resul t of operations at the site.

Although the shoreline area is controlled by %1PC pe sonnel, a dose may be calculated assuming that the area 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 f 40 kg/m (dry) to a

depth of 2.5 cm, then the associated dose to the whole body in mrem per year can be calculated.

-19

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

2 ~ Dam Shoreline Sediment Table 4 (conti)

Furthe" 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>

Cs-134 and Cs-137 concentrations detected are constant for one year and are a result of site operations Whole body and skin doses are as follows'adionuclide Whole Bod Dose*

Skin Dose*

Co-60 Cs-134 Cs-137 Oi00005 0 ~ 00001 0.00005 0,00006 0 00002 0,00006

• Dose in mrem pe" yea" The ave age radionuclide values used here are 0 25 pCX/g (dry) for Co-60, 0.09 pCi/g (d y) for Cs-134 and 0.94 pCi/g (dry) for Cs-137.

The whole body dose from Co-60 is 0 ~ 00005 mrem pe

year, 0.00001 mrem per year from Cs-134, and 0.00005 mrem per yea" f om Cs-137 o

a total whole body dose of 0.00011.

Sr-90 was not evaluated since the whole body dose from this be ta emitter is insignificant.

A whole body dose of 0.00011 mrem per yea" is very small and can be compared to the whole body dose f om 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 envi onmental dosimeters (TLDs) to be approximately 5

mrem pe" month or 60 mrem per year.

The calculated dose of '0.00011 mrem per year as a result of Co-60, Cs-384 and Cs-137 in shoreline sediment is conservative in the sense that it is a high dose estimate.

Even in view of this conservatism, this dose is extremely small and is 0.000002 of the annual natural background dose of 60 mrem per year, A.

3 ~ Fish - Table 5A, 5B A total of 18 fish samples were analyzed as a

result of collections= in the spring season (May 1983) and in the fall season (October 1983).

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 locations 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 emitters, Sr-89, and Sr-90 'able 5A shows results in units of pCi/g (wet) for purposes of data evaluation.

Table 5B shows results in units of pCi/kg (dry),

as required by.the Technical Specifications

-20

III.

EVALUATIONOF ENVIRONMENTALDATA (Continued)

A ~

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

Analysis of the spring 1983 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 not detected in control or indicator samples.

Spring fish collections were comprised of two separate species and nine individual samples'he two species represented one feeding type.

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

smelt, alewife, and other smaller predacious species.

Because of the limited availability of species present in the

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

Cs-137 was detected in all on-site and off-site samples collected during the spring 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 average indicator Gs-137 concentration was less than. the average control concentration.

The concentrations

detected, however, 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 0,033 tc 0.056 pCi/g (wet) for the indicator samples.

Cs-137 in the control samples ranged from 0.049 to 0.057 pCi/g (wet) for lake trout.

Cs-137 in brown trout samples ranged from 0.042 to 0'46 pCi/g (wet) at the indicator locations.

Cs-137 in the control sample was 0.046

'pCi/g (wet) (one sample collected).

Sr-89 and Sr-90 were not detected in the 1983 spring fish samples.

Sr-89 and Sr-90 have routinely been detected in previous years.

KWO was detected in all of the spring samples collected.

K&0 is a naturally occurring radionuclide and is not related to power plant operations.

Detectable concentrations of KAO in the indicator samples (lake trout and brown trout) ranged from 2 ~ 9 to 3.8 pCi/g (wet) and 3

0 to 3.1 pCi/g (wet) for the control samples No other radionuclides were detected in the spring fish samples.

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

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

~

Samples were collected by gill net in October.

-21

pl IXI EVALUATION OF ENVIRONMENTAL DATA (Continued)

A.

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

Cs-137 was detected in all nine samples including the thre e control samples.

Control. samples showed an average Cs-137 concentration that was greater than the indicator sample mean from the on-site locations.

The detected concentrations were not significantly different from one another because of the extremely small quantities detected.

Cs-137 in lake trout samples at the indicator locations ranged from 0.038 to 0.055 pCi/g (wet) and 0'41 to 0'44 pCi/g'wet) at the control location.

Brown trout samples from the indicatoz'ocations ranged from 0 041 to 0'50 pCi/g (wet) ~

The associated control sample was 0 057 pCi/g (wet) ~

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

Sr-89 and Sr-90 we"e not detected at any of the on-site or off-site sample locations The October 1983 brown trout sample f om the NMP(02) location was lost during the laboratory analysis for Sr-89 and Sr-90

'AO was detected in all of the fall samples collected.

Detectable concent ations of K-40 in the indicator samples (lake trout and brown trout) ra~ged from 2o 3.9 pCi/g (wet) and 2'

to 3.8 pCi/g (wet) for the control samples.

No other radionuclides were detected in the fall fish samples.

Review of pas t envi onmental 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 'hese results ange from an annual mean of 0.27 pCi/g (wet) in 1976 to 0 0035 pCi/g (wet) in 1982.

Control sample results have also decreased significantly from 0.24 pCi/g (wet) in 1976 to 0.0040 pCi/g (wet) in 1982'u ing 1983, Sz-89 "was not detected in indicator or control samplesi Sr-90 annual mean indicator sample results have decreased from 0'8'Ci/g (wet) in 1976 to a'ow of 0 '034 pCi/g (wet) in 1982.

1981 and 1982 mean sample results are approximately the same.

Control sample results have decreased as well, from 0.25 pCi/g (wet) in 1976 to 0,0063 pCi/g (wet) in 1982.

Sr-90 was not detected in 1981,

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

Sr-90, during 1983, was not detected in any of the samples collected at the indicator or control locations The general decline in detectable Sr-89 and Sr-90 results is most probably a

esult of the incorporation of

~ these radionuclides with organic and inozganic substances through ecological cycling.

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

<<22

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

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

The mean 1983 Cs-137 concentration has decreased slightly from 1982 for the indicator samples and s ignificantly fr om 198G through 1976 resul ts.

Concentrations for, thes e sample s decreased from a level of 1.4 pCi/g (wet) in 1976 to a level of 0 045 pCi/g (wet) in 1983 ~

Control sample results have also decreased from a level of 0 ~ 12 pCi/g (wet) in 1976 to a level of 0 046 pCi/g (wet) in 1982 ~

Results from 1979 to 1983 have remained fairly consistent for con trol samples.

The 1983 control sample mean was 0.049 pCi/g (wet) ~

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 s ignificant portion of Cs-137 detected since 1976 in fish is a

result of weapons testing fallout, and the general downward trend in concentrations will 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 6.9 kg of fish per year (Regulatory Guide 1.109) and the fish consumed contains an average 'Cs-137 concentration of 0.045 pCi/g (wet)

(annual mean result of indicator samples for 1983)

~

the whole body dose received would be 0'22 mrem per year.

The

~ critical organ in this case is the liver which would receive a calculated dose of 0.034 mrem per year.

No doses are calculated here for Sr-89 and Sr-90 since these radioisotopes of strontium were not detected during 1983.

The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mile Point area (indicator samples).

Conservative whole body and critical organ doses can be calculated for the consumption of fish from the control loc"tion 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 concentration for. the control samples is 0.049 pCi/g (wet) ~

The calculated Cs-137 whole body dose is 0.024 mrem per year and the associated dose to the liver is 0.037 mrem per year.

No doses for Sr-89 or Sr-90 are calculated here

because, as noted above, these radioisotopes of strontium were not detected during 1983

-23

IIIi EVALUATIONOF ENVIRONMENTAL DATA (Continued)

A.

3. Fish - Table 5A, 5B (conti)

Calculated doses as a result of fish consumption (lake trout and brown trout) at the indicator and control locations are presented below Indicator Control Whole Bod

• Critical Organ*

Whole Body* Critical Organ" Cs-137 Sr-89 Sr-90 0'22 0'34 (liver) 0'24 0'37 (liver)

(bone)

~*

(bone)

(bone) js*

+*

(bone)

Doses in mrem per year Consumption assumed fo" all months

~

• • No calculated dose since this radionuclide was not. detected.

In summary, the whole body and c itical organ doses observed as a result of consumption of fish is small.

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

The dose f om control'ample fish is slightly higher.

Doses f om both sample groups are conside ed background doses AD 4 ~ Lake Water - Tables 6, 7, and 8

1983 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) wer e composites of monthly samples.

The analytical results for the 1983 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 facilitiesi The control location samples were collected at the City of Oswego water treatment plant and consisted of raw lake water prior to treatment.

The 1983 gross beta annual mean activity for the Nine Mile Point Unit 81 and the James A FitzPatrick inlet canal (2.8 pCi/liter) was approximately the same as the 1982 mean inlet canal result (2 ~ 7 pCi/liter), and was less than the annual mean results for the years prior to 1981.

The Nine Mile Point Unit 41 canal samples were greater than the control samples for 7 of the 12 monthly samples analyzed and ranged from 0.6 pCi/liter to 7.9 pCi/liter.

The James A. Fitzpatrick canal samples were greater than the control samples fo 6 of the 12 monthly samples and ranged from 0' pCi/lite to 4.2 pCi/liter.

The control sample results ranged from 0.8 pCi/liter to 3,5 pCi/liter.

-24

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued)

A ~

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

The fluctuation 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 June.

This result was 7'9 pCI/lite"~

A significant reduction in gross beta concentrations is notea 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 operationsi Although the past elevated gross beta concentrations may be due in part to past weapons testing, it is difficult to dete mine 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 1983.

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

~

Only one radionuclide was detected in the inlet canal and city water samples.

This radionuclide was naturally occurring.

K-40 was detected intermittently in both intake canals and the aw city water supply.

K-40 was detected in 3 of the 12 monthly inlet canal samples at Nine Mile Point Unit 1 and anged from 6.7 to 16.5 pCi/liter.

The James A

FitzPatrick inlet canal samples showed K-40 detected in 1 of the 12 monthly samples.

This concentration was noted in December and was 9.4 pCi/liter.

K"40 in the Oswego city water supply was detected only once, during June, at a concentration of 13.2 pCi/liter.

Quarterly samples for Sr-89 analysis we e

composites of the monthly samples.

Sr-89 was not detected in any of the quarterly canal samples or the raw city water samples during 1983.

Sr-89 ranged from 0.6 to 2.0 pCi/liter at the indicator locations

(%1P and JAF) and

<0' to

<2.0 pCi/liter at the control location (raw city water) ~

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

Sr-90 was detected in 10 of the 12 quarterly samples for 1983 and was found at all three locations

~

At the City of Oswego water treatment plant or control

location, Sr-90 ranged from 0 ~ 8 pCi/liter to 1.0 pCi/liter with a mean of 0.9 pCi/liter.

Sr-90 in the Nine Mile Point inlet canal samples ranted from 0. 7 pCi/liter to 1.1 pCi/liter and showed a mean of 0.9 pCi/liter ~

The James A. FitzPatrick inlet canal samples showed

-25

IIIo EVALUATION OF ENVIRONMENTAL DATA (Continued)

A 4 ~ Lake Pater - Tables 6, 7, and 8 (cont )

Sr<<90 ranging from 0 ~ 6 pCi/liter to 1 0 pCi/liter and a

mean value of 0'

pCi/liter As demonstrated, the control location showed a

mean result of 0.9 pCi/liter which is a result of natu al variation in the distribution of Sr 90.

Sr 90, as detected in the 1983 water

samples, is considered to be background Sr-90 as a

esult 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.

Tritium was detected in all samples taken at all three locations.

The City of Oswego water t eatment plant showed tritium concentrations anging from 230 pCi/liter to 280 pCi/liter with a mean of 250 pCi/liter.

Tritium concentrations for the James A, ~

FitzPatrick inlet canal ranged from 249 pCi/liter to 560 pCi/liter and showed a

mean concentration of 347 pCi/lite.

Inlet canal samples taken at Nine Mile Point showed tritium concentrations ranging from 190 pCi/liter to 410 pCi/liter.

The annual mean concent ation was 288 pCi/liter ~

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 cont ol location (Oswego City water) ~

As noted previously,

however, the decrease is prima"ily a esult 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 15.8 pCi/liter in 1977 to 41 8 pCi/lite in 1976.

For 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 1983 was 2 8 pCi/liter Control sample annual means were also relatively high during 1975 to 1977 ~

Du"ing 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' or the period 1978 through

1981, annual mean gross beta concentrations ranged from 2.42 pCi/liter (1982) to 3.55 pCi/liter (1978) ~

The'ontrol annual mean for 1983 was 2.3 pCi/liter.

Review of previous data for Sr-89 and Sr-90 demonstrates'hat 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, Sr-89 ranged from not detected (1975-1978 and 1981) to 1.4 pCi/liter (1980) ~

During

1983, Sr-89 showed an annual mean of <1.6 pCi/liter (LLD) at the control location and <1.5 (LLD) pCi/liter at the indicator

-26

III EVALUATIONOF ENVIRONMENTAL DATA (Continued )

A ~

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

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 anc'980)

~

Mean results at the control sample location ranged from no t detected (1975 - 1978) to 1.10 pCi/liter (1980) ~

The annual mean Sr-90 results during 1983 for the indicator s amples and contr ol samples were

<0.8 (LLD) pCi/liter and

<0.9 (LLD) 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 1982 and showed a

peak value of 4 620 pCi/liter (1982) and a

minimum value of 194 pCi/liter (1982).

The annual mean tritium result at the indicator locations for 1983 was 317 pCi/liter.

The indicated peak value of 4,620 pCi/liter during 1982 is a result of liquid waste discharges during reverse flow mode (of the inlet and discharge canals) and tempering gate maintenance.

This occurrence was explained in detail in the 1982 Annual Environmental Operating

Report, Part 8

The result is not an accurate indication. of tritium levels in lake water as demonstrated by the JAF inlet canal results Mean tritium results at the control location have decrease slighly since

1976, as was noted above for the indicator samples.

Mean annual results were available for 1974 through 1982.

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

1979 through 1982 mean results were consistent.

The annual mean tritium concentration for 1983 at the control location was 250 pCi/liter.

The impact, as expressed by a dose to man, is not assessed here because 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.

I

-27

III.

EVAIUATIONOF ENVIRONMENTAL DATA (Continued)

BE Terrestrial Pro ram Tables 9

through 21 represent the, analytical results for, the terrestrial samples collected for the 1983 reporting period

l. 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 hours afte collection to allow for the decay of naturally occurring radionuclides with short half-lives.

A total of 312 off-site and 468 on-site samples were collected and analyzed during 1983 ~

No significant levels of gross beta activity wer e observed in any of the samples.

The off-site or control mean concentration fo" 1983 was 0.024 pCi/m while the indicator or on-site sample mean was equal to 0.023 pCi/m.

As noted, the on-site annual mean is about four percent lower than the off-site mean foz'he same period.

This difference in mean concentration has been exhibited in the past nine years with the exception of 1977 when a higher annual mean gross beta activity was observed for the on-site sampling stations.

In these eight

years, the control stations'nnual mean ranged from a minimum difference of 4.2 percent higher than the indicator s tations, observed in 1983; to a

maximum difference of 28 ~ 6 per cen t

higher, observed in 1978.

The diffe ence in off-site and on-site weekly and monthly mean values'for g oss beta could be the result of a combination of the many natural pzocesses which can affect environmental concentrations.

The most significant parameter that could possibly contribute to a depressed or lowe concentration for the on-site stations would be location The close proximity of on-site sampling s tations to the lakeshore (Lake Ontario) would account for lower concent ations of naturally occurring radionulcides being collected on the sample filters.

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 concentrations are potassium-40 and decay or daughte" products of uranium and thorium.

The concentrations of these nuclides in the ground level atmosphere are dependent upon the local geology and its chemical constituents.

Thus, surface wind over land areas have a potential for containing highe" concentrations of naturally occurring radionuclides The observed small 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 atmosphe e directly

-28.

III-EVALUATIONOF ENVIRONMENTAL DATA (Continued)

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

above land areas are affected by time related processes such as wind direction, snow cover, soil temperature and soil moistu e

content.

Little change was noted in gross beta activity which corresponded with weapons testing as has been observed in past years.

Review of air particulate gross beta concentrations shows that no significant increases in concentration occurred du"ing 1983

'n

general, the gross beta activity in air particulate samples has decieased significantly.

The mean 1983 concentration for both off-site and on-site is 6.6 times lower than the mean concentration detected in 1981 and 1.3 times lower than 1982.

This reduction in activity is directly attributable to the increased activity detected in 1981 as a result of fallout from an atmospheric nuclear test (i.e.,

the October 1980 Chinese Weapons Test) and subsequent "eturn to background levels jn 1983.

The trend of gross beta

,activity in the environment is that of reduced concentrations.

The mean 1983 concentration was the lowest level of gross beta activity observed since

1974, which is the extent of the review period ~

This general decrease is 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 ~ Monthl Air Particulate Composites Table ll Weekly air pa ticulate samples were composited

'monthly by location into two on-site composites and two off-site composites.

On-site composites include B-1 (on-site stations Dl, D2, E, F, and G) and B-2 (on-site stations H, I, J, ana K) ~

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

The results for the composite samples analyzed during the 1983 sample program showed positive results for Ra-226, K-40, Be-7, Co-60, Cs-137, and La-140 ~

All six of these radionuclides, were detected in the on-site composites and five of the six wer e detected in the off-site composites (La-140 was not detected in off-site composite samples)

~

Ra-'226, K"40 and Be-7 are naturally occurring.

Co-60, and Cs-137 are typically a result of weapons testing or operations at the site or a combination of both.

La-140 is a result of operations at the site based on the relatively short half-life.

The total numbe" of radionuclides detected in 1983 was significantly less than 1981.

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

Concent ations of Zr-95, Ce-141, Nb-95 >

Ce-144

~ Mn-54, Ru-10 3,,

Ru-106 and Ba-140 were not detected in 1983 as they had been in 1981

-29

Illa'VALUATION.OF ENVIRONMENTAL DATA (Continued)

B ~

2 ~ Monthl Air Particulate Com osites - Table 11 (cont,)

Ra-226, K-40 and Be-7 were detected at varying concent ations in both on-site and off-site composites.

Ra-226 was detected in 9 of the 48 composite spples 1983 concentrations ranged from 0 '021 - 0.0127 pCi/m

~

K-40 was detected in 27 of the 48 compogite samples Concentrations ranged from 0.0024-0.0065 pCi/m,

The third naturally occurring radionuclide detected was Be-7 ~

Be-7 was detected in all monthly composite samples and ranged in concentration from 0.0685-0 '61 pCi/m

~

3 Concentrations of Ra-226, K-40, and Be-7 du"ing

.1983 were consistent with concent ations detected in previous years'o-60

'was detected in 5 of the 24 on-site composite samples and ranged f om 0.00026-0.00173 pCi/m

~

The presence of Co-60 has been noted in the past and can be a

esult of weapons

testing, contamination during handling and operations at the site.

The maximum on-site Co-60 concentration noted was 0 ~ 00173 which was 6 ~ 6 times the smalles t concentrati'on detected.

The maximum concentration detected was noted in the Decembe 1983 composite sample.

Co-60 was detected in 1 of the 24 off-site composite samples at a concentration of 0.00074 pCi/m (December 1983)

~

Co>>60 in the on-site and off-site composite samples is most probably a result of contamination during handling and possibly ope ations at the site The December

samples, especially, are suspected to be a result-of contamination during the preparation process.

After reviewing the December 1983 composite

samples, a

set of on-site and off-site particulate fQters were prepa"ed by the technician performing the environmental routine.

These filters were then composited and counted at the envi onmental laboratory.

The composited filters showed that Co-60 was present on unused filters.

The concentration detected was 0.00307 pCi/m

~

The concentration was obtained by using a

standard composite sample volume for the number of filte s composited and a standard count time.

This concentation was. 1.8 times the concentration of the December maximum composite sample.

The contamination was traced to the preparation process where the technician had prepared the individual filters on a

table top covered with plastic Since the location was in proximity to a restricted area access, it is felt that small amounts of Co-60 were attracted to the plastic and subsequently transferred to the filters being prepared on the plastic The technician and subsequent replacement technician were instructed on how and where to prepare the particulate filters.

Although conclusive proof cannot be provided that Co-60 in the December samples is a result of contamination during handling, the data indicates that a significant portion, if not all of the Co-60 detected was a result of contamination, Subsequent monthly composite samples starting during March 1984 will provide more information as to the source of Co-60

'30

t a:e EEET EVALUATEON OF ENVIRONMENTAL DATA (Continued) e B ~

2. Monthly Air Particulate Com osites - Table ll (cont.)

's-137 was detected in 2'f the 24 on-site filter composi t e samples at concentations of 0.00020 and 0.00028 pCi/m.

The off-site filter composites showed Cs-137 was detected only once at a

concentration of 0.00018 pCi/m

~

En all

cases, th e 3.

concentrations detected were small and may be a

result of weapons testing fa13.out, contamination during handling (as noted above for Co-60), operations at the site or a combination of any of the three.

The off-site concentration (0.00018 pCi/m ) was d e tee ted in Ma"ch 1983 while the on-site concentrations were detected in March and April 1983 (0.00020 and 0.00028 pCi/m ) ~

Although the data is not conclusive, it appears that the detected Cs-137 concent ations may be a result of operations at the site.

La-140 was detected only once during 1983 (April) in gn on-site filter composite at a concent ation of 0.00113 pCi/m

~

La-140 can be an effluent from power reactors or weapons testing Because of the relatively short half-life of 40.22 hours2.546296e-4 days <br />0.00611 hours <br />3.637566e-5 weeks <br />8.371e-6 months <br />, La-140 in this case is attributable to operations at the site.

No other adionuclides were detected in on-site o

off-site air particulate composite samples during 1983 using gamma spectral analysis.

The location, concentration ange and

mean, and frequency of occurrence of each radionuclide detected during 1983 is included below.

Radionuclide Locardon Range*

Menue

~rrequenc Ra-226 Ra-226 K-40

.Z-40 Be-7 Be>>7 off-site on-site off-site on-site off-site on-site 0.00645-0 01270 0.00210-0.00529 0.00310-0.00649 0.00242-0 '0486 0e07350-0 16100 0.06850&e 14700 0.00982 0 '0318 0.00444 0.00338 0 '1290 0.09750 3

6 13 14 24 24 Co-60 Co>>60 Cs-137 Cs-137 I.a-140 La-140 off-site 0.00074 on-site 0.00026-0 '0173 off-site 0 00018 on-site

.0 00020-0.00028 off-site

~

ND on-site 0 '0113 0.00074 0.00068 0.00018 0.00024 ND 0 '0113 1

5

~

1 2

0 1

ND-not detected

~ results in units of pCi/m

• • -frequency is number of times detected

-31

s ~

III'VALUATIONOF ENVIRONMENTAL'ATA(Continued )

B ~

2. Monthly Air Particulate Composites Table 11 (Cont.)

Historically, the naturally occurring radionuclides Ra-226, K-40 and Be-7 have shown flucuations that are represaxtative of natural changing conditions.

-No significant trends were noted, as one would expect.

Co-60 has flucuated in the past primarily as a result of previous weapons testing.

Co-60 average concentrations at the on-site and off-site locations from 1977. to 1978 decreased from approximately 0.0175 to 0.0015 pCi/m

~

Average concentrations decreased significantly during 1979 and increased in 1980 from approximately 0.0007 to 0.0016 pCi/m respectively.

1981 and 1982 average Co-60 concentrations decreased to 0.0007 and 0.0005 pCi/n.

Avexage off si-te ano on-site concentrations were approximately equal

~

The

$903 on-site average Co-60 conceatration was 0.0007 pCi/m or slightly greater than th e 1982 concentration.

The 1983 average off"site mean Go-60 concentration was 0.0007 pCi/m which also was slightly greater than 1982 results.

As noted previously,

however, a

portion of the Co-60 detected during 1983 was attributed to contamination during handling of the unused filters.

Historically, Cs-137 has been variable during the past.

During

1977, both on-site and off-site Cs-137 average con~entrations were approximately equal and averaged 0.0039 pCi/m.

Cs-137 average concentrations at on-site and off-site locations decreased during 1978 and 1979 to 0 0017 and 0 0013 pCS/m r espectively.

Average concentrations during 1980 and 1981 were approximately equal at off-site and on-site locatons and decreased slightly in 1980 and increased slightly in 1981 from 1979.

The 1980 and 1981 average concentrations were 0.0012 and 0.0015 pCi/m respectively.

The yean 1982 concentration for Cs-137

'decreased to 0.0004 pCi/m

~

The 1983 mean Cs-13 7 concentration for the on-site and off-site composite samples were 0.0002 and 0.0002 pCi/m which was a reduction from 1982 results.

La-140 has been detected intermittently during previous sampling years.

La-140 was detected in 1978 (as Ba/La-140) at average concentrations of 0.0023 (on-site) and 0.0047 (off-site) pCi/aP.

La-140 was not detected again until 1981 where it was found at a

concentration of 0.0186 pCi/m

• (off-site)

.and 0.0466 pCi/m (on-site) ~

No positive results for La-140 were noted during 1982.

La-140 during 1983 was detected only once in an on-site composite at 0.00113 pCi/m, Based on the smal 1 amount of data available, La-140 has decreased significantly since 1981 and 1978.

s Assessment of the presence of fission product radionuclides in air particulate composite samples can be depicted by calculating doses to man as a result of inhalation.

-32

III.

EVALUATION OF ENVIRONMENTALDATA (Continued )

B ~

2. Monthly Air Particulate Composites Table 11 (cont.)

Using the qverage child inhalation'rate o'f 3,700 m

per year or 308.3 m

per s tandard month (Regulatory Guide 1.109) and the maximum mean concentration measured at the on-site or off-site sample

stations, the following annual lung and whole body doses can be calculated.

..., Ãuclfde C o-60 Co-60 Cs-137 C s-137 La-140 La-140 Concentration (pCi/m3 )

0.00068 0.00068 0.00024 0.00024 0.00113 0.00113 No. Months Possible Detected Origin

~

~

7 Plant/Fallout Plant/Fallout Plant/Fallout Plant Plant Dose (mrem/year) 0.002002 (Lung) 0.000006 (Whole Body) 0.000004 (Lung) 0.000005 (Whole Body) 0.000017 (Lung)

<0.000001(Whole Body)

Total Lung Dose 0.002023 mrem/yr.

Total Whole Body Dose <0.000012 mrem/yr.

The table above illustrates that the lung dose received by a

child from inhalation of air in the vicinity of the site (actually within the site boundary) is approximately 0.002 of one mrem for 1983.

This dose is extremely small and can be compared to the total lung dose to individuals residing in homes utilizing natural gas,for cooking.

A resultant: total luna dose of 11 mrem per year has been calculated as a result of naturally occurring radon gas and radon gas decay products in the natural gas (NCRP Report No.

56).

The whole body dose received is approximately 0.000012 mrem for 1983'his dose is insignificant.

B.

3. Airborne Radioiodine I-131) - Tables 12 and 13 During the 1983 sampling

program, airborne radioiodine was not detected in any of the 312 weekly samples collected from the six off-site sampling stations.

I-131 has been detected in the past at the off-site stations.

During 1976, the mean off-site I-131 concentration averaged 0.604 pCi/m.

1977 showed an I-13 1 concentration that decreased to 0.323 pCi/m and for 1978 the conceritrations decreased by a factor of ten to 0.032 pCi/m.

During 1979, 1980 and 1981, I-131 was not detected

~

I-131 was

~ detected once during 1982 at a concentration of 0.039 pCi/m

~

As noted

above, I-131 was not detected in the off-site sample stations during 1983

'33

IIIi EVALUATIONOF ENVIRONMENTAL DATA (Continued)

B ~

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

I-131 was detected four times during 1983 in the on-site sampling stations.

The concentrations ranged from 0'22 to 0'35 pCi/m and averaged 0 028 pCi/m

~

The detected concent ations were found during the weeks of 1/24/83> 5/30/83, 6/6/83, and 12/12/83.

The 1983 mean concentration was slightly greater than the mean concentration found during 1982 (0.016 pCi/m ) ~

I-131 was detected at a

mean concentration of 0 328 and 0 309 pCi/m during 1976 and 1977'he average concentration decreased to 0.041 pCi/m during 1978 and was not detected during 1979'he 1980-1982 average concentrations were 0.013>

0.029, and 0.016 pCi/m which were reductions in view of previous I-131 concentrations, For the most part, I-131 in on-site

'and off-site samples was a result of I-131 from weapons testing.

A small portion of the concentrations detected was a result of operations of the site.

The concentations detected during 1983 at the on-site sample stations were a

result of operations at the site.

The I-131 concentrations detected in on-site samples during 1983 are presented below.

The spacial distribution of the I-131 concentrations show that all four of the results were found at the H

on-site environmental air monitoring station.

This s tation is located 0.80 miles at 71'rom the NMP-2 reactor centerline (center, of the on-site environmental grid map) and is well within the-site bounda y.

The impact of I-131 concentrations at the H

on-sit e environmental station can be assessed by projecting a

maximum organ dose (thyroid) and whole body dose to the' itical individual.

The projected doses are very conservative because the assumption is made that the critical individual is located at H on-site station, which is well within the site boundary and that the individual is at that location for a full week fo" each week that I-131 was deteted.

The critical individual, in this

case, would be a child Using standard Regula)ory Guide 1 109 methodology and an inhalation rate of 3700 m

per year, the thy oid and whole body doses are calculated below Sample End Date 01/31/83 06/06/83 06/13/83 12/19/83 On-Site Sam le Station H

H H

H Concentration I

0'22 0+032 0'35 0 023 Dose (mrem for 1983)

Th oid/%hole Bod 0 '06872/0 '00012 0 009996/0+000017 0 ~ 0 10933/0 ~ 000018 0 e007184/0 +0000 12 Total 0 '34985/0.000059

-34

III.

EVALUATION OF ENVIRONMENTALDATA (Continued )

B ~

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

As noted previously,- the projected doses are conservative since the critical individual (chil'd) is assumed to reside a t H

on-site air monitoring station.

Figure 3 shows the location of H on-site station and depicts this locaton as well within the site boundary.

A more zealistic location, where members of the public would reside, would be outside of the site boundary at which point the I-131 concentration would be less A maximum exposure time of 168 hours0.00194 days <br />0.0467 hours <br />2.777778e-4 weeks <br />6.3924e-5 months <br /> per week is also conservative from the point of view of the residency time.

The calculated total dose for the above mentioned critical individual would be 0.035 mrem to the thyroid and 0.000059 mrem t o the whole body assuminp a

seven day sample period ana an inhalation rate of 3700 m

per year (Regulatory Guide 1,109)

~

The resulting calculated whole body dose due to on-site I"131 concentzations is extremely small andi 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 esiding one meter (3.28 feet) higher in altitude for a

pe iod of 25.8 hours9.259259e-5 days <br />0.00222 hours <br />1.322751e-5 weeks <br />3.044e-6 months <br /> would receive an additional radiation dose of 0.000059 mrem which is equal to the total calculated dose to the whole body from environmental I-131 concentrations

~

The associ'ated critical organ or thy oid dose fo" a child was shown to be 0.035 mrem for 1983 as a result of inhalation of 1-131.

The adult thyrofd

dose, uslnt the same criteria, ls 0.026 mram for 1983.

These doses ara small and can ha put into perspective by comparing these doses to the dose to the thyroid as a result of inhalation of naturally occurring Be-7 in air ~

Be-7 is produced primarily in the upper atmosphere as a result of the interactions of cosmic rays from outer space with atmospheric

argon, oxygen and nitrogen.

The average Be-7 concentration detected duzing 198) was 0.1052 pCi/m

~

Assuming an inhalation rate of 8000 m

pe" year for an adult, the 1983 annual thyroid dose would be 0'88 mrem per year.

The adult thyroid dose as a result of the inhalation of I-131 is only 5.3 percent of the dose as a

esult of the inhalation of naturally occurring Be-7 near the Nine Mile Point site ~

The end result of the 1983 I-131 sampling effort showed no significant impact due to operations at the site.

During 1983, I-131 was not detected in any other environmental sample media including milk and green leafy vegetables.

B.

4.

TLD (Environmental Dosimeter) - Table 14 TLD's were collected and read once per quarter during the 1983 sample year.

The TLD resu1ts a

e an average of four independent readings at each location and are reported in mrem pe" standard month.

In 1983, TLD's for the most part were collected on March 31, 1983, July 30, 1983, September 30, 1983 and January 69 1984 '

III.

EVALUATIONOF ENVIRONMENTAL DATA (Continued)

B ~

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

TLD results are'. organized into four groups for evaluation purposes

~

The groups are on-site TLD's (defined as TLD's in the immediate proximityof the individual facilities at.points of interest),

environmental station TLD's (a

ring cf TLD's surrounding the generating facilities as a

group),

off-site TLD's (TLD's located off the site property or controlled area at off-site environmental stations or points of interest),

and control TLD's which are located beyond any influence of the site Quaeter A net dose at the environmental station TLD' located on-site can be calculated simply by subtracting the mean s tanaard 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:

Net Environmental Station Dose**

1 2

3 4

0.47 0 ~ 58 0 36 0'8 The annual site property boundary dose for 1983 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.

uar ter Net Site Pro crt Boundar Dose~*

1 2

3 4

-0.32

+0.3 7

-0,30

-0.3 As observed, the site boundary dose based on two available TLD locations is less than the average off-site dose with the exception of the second quarteri The negative net doses are 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 readings per quarter.

-36

III.

EVALUATION OF ENVIRONMENTALDATA (Continued )

B ~

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

On-site TLD results remained fairly consistent during 1983.

The results for on-site TLD's were slightly above off-site background results except for TLD's located in close proximity to the generating facilities or radwaste facilities'LD's located near radwaste facilities, for the most

part, showed variable results as a

result of radwaste processing and shipments.

TLD numbers 31 and 39 are located near the NMP-1 radwaste facilities and showed variable results.

TLD numbers 27, 28, 29, 30, and 47 are located near the JAF radwaste facilities and also showed variable results as a

result of radwaste processing and shipments.

TLD's located near the generating facilities showed results slightly greater than off-site TLD results.

These TLD's included numbes 23, 48, 61, and 4.

TLD 83 is located near the Unit 2 construction site and construction pipefitting facilities.

This TLD showed variable results that were up to two times normal background levels.

This TLD was affected by the

%P-1 and JAF generating facilities (when operable) and 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'LD's located in areas near radiography work will show fluctuating doses as the amount of radiography performed is not consistent.

TLD 859 results were variable as a result of thE operating mode of the JAF facility.

This TLD, is located near the JAF facility stack which primarily releases condenser air ejector gases

~

0ff-site TLD results remained fairly consistent for mos t TLD locations each quarter.

A slight increase in natural background radiation levels was noted for off-site TLD's in the first and second quarters of the year.

This trenc, was also observed in the control TLD's.

This is 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 TLD results for 1983 showed no detectable impact from direct radiation measured outside the site boundary.

"Location numbers 5, 6, 7, 23, 24, 25 and 26

• +Dose in mrem per standard month ~

-37

~

~

III, EVALUATION OF ENVIRONMENTALDATA (Continued )

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 environmental monitoring stations contains a radiation monitor and, in addition, the C off-site monitoring station contains a

similar monitor.

The radiation monitors consist of a

GM detector with an associated power

supply, chart recorder, and trip unit.

The monitor has an operating and recording range from 0 01 to 100 mrem/hr Each radiation monitor has a small radioactive source mounted inside the detector casing to produce an on scale reading.

The design intent of the monitors is to detect possible dose rates resulting from plume releases from the 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 eight farms during the 1983 grazing season and the following months of November and December.

The grazing season is considered to be'ay through October.

In addition,

~ data is available for two additional farms for the month of May 1983 only.

these two locations were deleted in June'uring

1983, three sample locations were added to the milk sample program and two locations were deleted.

The additions and deletions are detailed, in Section II.3.B (Changes to the 1983 Sample Program)

~

Sample location descriptions are listed below Location No.

Direction from Site Distance from Site (miles) 4 ESE 40 SW 14 ESE 16 S

5 SSE 7

ESE 45 SE 50 E

55 E

60 E

7 ~ 7 15.3 9,8 5 2 702 5.5 8 1 8.2 9,0 9 ~ 5 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 results section.

-38

XIIi EVALUATION OP ENVIRONMENTAL DATA (Continued )

B ~

6 ~ Hilk Tables 16, 17, and 18 (Cont.)

The gamma spectral analysis of the monthly composite sample s showed K-40 to be the most abundant radionuclide detected in the milk samples collected in 1983'-40 'was detected in every sample analyzed and. ranged in concentration from 879 pCi/liter to 1,700 pCi/liter at the indicator locations and 923 pCi/liter to 1,520 pCi/liter at the control location.

K-40 is a naturally occurring radionuclide and is found in many of the environmental medias sampled.

Cs-137 was the only other radionuclide detected in the 1983 milk samples.

Cs-137 was measured in 3 of the 66 monthly samples analyzed.

Cs-137 was detected in milk samples at location 85 in

August, 816 in July, and 845 in June.

Cs-137 was not detected at location numbe" 40 which is designated as the control location Cesium concent ations ranged from 3 3 pCi/liter to 10.9 pCi/liter for all samples with a mean of 7'

pCi/liter.

Cs-137 was not detected at any one particular sample location on a consistent

basis, nor was it detected consistently at other locations during any particular month.

The detection of Cs-137 at any particular location was random.

Cs-137 was

detected, however, during the consecutive months of June, July, and Augusta A

maximum concentration of

. 10 '

pCi/liter 'as detected at location number 16 during July.,

Annual results for the detection of Cs-137 at all locations are presented below.

Location No.

Annual Cs-137 Results 4

40 (control) 14**

16 5

7 45 50 55 6 0**

ND ND ND 10 ~ 9 pCi/liter*

7.3 pCi/liter*

ND 3.3 pCi/liter*

ND ND ND ND <<Not detected during 1983 sample collection period

~

Detected only once during 1983 ~.

+*

Only 1 monthly sample obtained for 1983 (location deleted in June 1983)

-39

III.

EVALUATIONOP ENVIRONMENTALDATA (Continued) 3 ~

6 ~ Milk Tables 16, 17, and 18 (Conti)

The annual Cs-137 values for each sampling location are variable but quantitatively the values are only slightly different from one another especially when the magnitude of these minute concentrations is considered.

Location number 16 had an annual result slightly higher than the other locations ~

Location number 40 (control location) showed no detectable Cs-137 during 1983 or during 1982.

During 1981, however> location number 40 showed an. annual mean Cs-137 concentration of 3 ~ 9 pCi/liter, and in 1980 the control location showed a Cs-137 concentration of 4.5 pCi/liter.

A significant portion of the Cs-137 detected in 1980 and 1981 was a

esult of past weapons testing For these

years, the detonation of a nuclear device in October 1980 by the Chinese contributed significantly to the measured Cs-137 concentr a-tions.

During 1983,

however, Cs-137 in milk is most probably a

result of operations at the site.

The impact, in any case, is extremely small During 1982 and 1981, pasture grass was collected and analyzed from the milk sample locations in order to help evaluate cesium in milk for those years.

Pas ture grass samples were not collected during 1983 since a sufficient amount of data had been collected during 1981 and 1982 to evaluate any possible relationship.

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

Sr-90 was detected in all of the milk samples collected during 1983'r-90 was detected at indicator sample locations for all months sampled and at the control sample location forall months sampled.

The mean Sr-90 concentration for the control location was 2.6 pCi/liter.

The mean for all indicator locations (within 10 miles of the site) 'as 3.0 pCi/liter.

The control and indicator sample means are similar.

Sr-90 results for the indicator locations ranged from 0 9 pCi/liter to 5.5 pCi/liter.

Control sample results ranged from 1.5 p(i/liter to 3.5 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 1983 in any of the indicator or control samples All 1983 I-131 milk results are reported as lower limits of detection (LLD)~

The LLD results ranged from

< 0 1 pCi/liter to < 0.5 pCi/liter for all milk samples.

-40

~ ~

III.

EVALUATION OF ENVIRONMENTAL DATA. (Continued)

B ~

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

The presence of Cs-137 and Sr-90 in milk samples has been o bserved in many ma)or urban areas during previous years.

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

1958-1972),

Cs-137 and Sr-90 were detected in milk samples at concentrations that wer e representative 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, Sr-90 was measured at a concentration of 6 pCi/liter and a

peak concentration of 28 pCi/liter was measured in 1963'r-90 decreased to 8 pCi/liter in 1972

'valuation of 'previous Cs-137 data shows that Cs-137 has been detected in environmental milk samples at both indicator

. and control locations.

Mean Cs-137 concentrations for 1978-1981 h ave remained fairly cons is tent and ranged f"om

b. 6-9 ~ 9 pCi/liter at the indicator locations.

The 1982 indicator mean was 5.7 pCi/liter which showed a slight decrease when compared to 1978-1981

~

Cs-137 in milk during 1983 yielded a mean of 7.2 pCi/liter which was slightly greate" than the 1982 mean but was less than the 1978-1981 mean range.

During 3.983,

however, Cs-137 was detected in only 3 of the 66 samples, while in 1982, Cs-137 wa's detected in 10 of the 54 samples analyzed.

At the c ontrol.location, Cs-137 has.

emained fairly consistent for all yea s from 1978-1982 except for 1979 and 1982.

For these years, this radionuclide was not detected.

Cs-137 ranged from 3 ~ 9-5.8 pCi/liter during 1978-1982.

Cs-137 was not detected at the control location du"ing 1983 ~

The absence of Cs-137 during 1983 is a

esult of a

3 year time interval since the last weapons test

~

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 4.0-5.9 pCi/liter during 1978-1982 'he 1983 indicator mean was inconsistent with this range and showed a concentration of 3.0 pCi/liter, which was less than the 1978-1982 range.

At the control location, Sr-90 ranged from 3 1-5 9 pCi/liter during 1978-1982.

The 1983 annual mean was 2.6 pCi/liter or slightly less than the 1978-1982 range.

The gene al trend jn milk Sr-90 coricentations is a gradual reduction as a result of infrequent weapons tests'he impact as a result of Cs-137 in 1983 milk samples can be assessed by calculating conservative doses to man from the consumption of milk with detectable quantities of Cs-137

~

For

'he purposes of a

calculated

dose, the 1983 mean indicator sample Cs-137 concentration is used (7.2 pCi/liter).

-41

III.

EVALUATIONOF ENVIRONMENTAL DATA (Continued)

B ~

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

Assuming a consumption rate of 330 liters (87 18 gallons) p'er yea" for an infant (Regulatory Guide 1.109 maximum exposed individual),

the whole body dose would be 0.026 mrem and the critical organ dose would be 0o363 mrem to the liver The calculated doses are based on 3 months of consumption (3 months of detectable Cs-137 sample results)

~

Since Cs-137 was not detected at the control location in 1983, a

dose calculation cannot be performed.

For a limited comparative

purpose, the calculated dose to an infant as a result of consuming milk from the control location during 1981 would be 0 F 005 mrem whole body dose and 0.072 mrem critical organ dose (dose to the liver) ~

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

The calculated dose to an adult can be determined assuming a

consumption rate of 110 liters (29 ~ 06 gallons) pe year (Regulatory Guide 1.109) and a mean Cs-137 concentration of 7.2 pCi/liter for the indicator locations.

The resultant doses are 0014 mrem to the whole body

'and 0022 mrem to the liver (critical organ)

~

The calculated doses are based on 3 months of consumption.

As noted

above, Cs-137 was no t detected a t the control location, therefore no whole body or critical organ dose can be calculated.

For the purpose of illustration, the significance of the above doses can be brought into perspective by comparison to backg"ound 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 0.026 mrem to an infant and is totally a result of plant ope ations at the site, a

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

A dose of 0.026 mrem whole body is equal to residing at a location 100 meters (328 feet) higher in altitude for 4 ~ 7 days.

An additional comparison can be made to naturally occurring K-40 ~

K&0 has been noted in almost all environmental samples at significant levelsi A 70 kg adult weights approximately 154 pounds and contains approximately O.l microcuries of K-40 as a

result of normal 1ife functions (inhalation, consumption, etc.)

~

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

result of the inte nal deposited K-40.

For comparison

purposes, an adult bone dose can be calculated that results from the consumption of milk from the 1983 indicator locations The mean Cs-137 concentration of 7 ~ 2 pCi/liter is used.

The resulting b'one dose is 0 ~ 016 mrem per year (an average milk Cs-137 concentration of 7.2 pCi/liter is applied over 3 months of the yea ) ~

This dose is 0.0008 of the bone dose as a

esult of naturally occurring K-40 in a 154 pound adult.

-42

III'VALUATIONOF ENVIRONMENTAL DATA (Continued)

B.

6. Milk-Tables 16, 17, and 18 (Cont.)

The impact, if any, as a result of Sr-90 in milk, due to plant operation is extremely small since the mean esult of the indicator results and the control results are approximately equal considering fluctuations in the background levelsi The levels of Sr-90 detected in indicator as well as control samples are considered to be representative of background concentra-tions.

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

Iodine"131 was not detected in the monthly milk samples analyzed for the 1983 program.

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

BE 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 owners.

Questionnaires not responded to are followed by telephone c'alls.

The. number of milch animals located within the ten mile radius of the site was estimated to be 1,213 cows and 0 goat's 'for the spring 1983 census.

No new locations were found since the summer 1982 census.

The number of cows increased by 72 and the number of goats decreased by 3 with espect to the 1982 summer census.

The 1983 summer census showed a total of 1,145 cows and 2

goats

~

This represents a decrease of 68 cows and an increase of 2

goats with respect to the spring 1983 census.

One milch animal location was added as a result of this census when compared to the spring 1983 census.

8. Human Food Products Table 20 Human food product samples during 1983 were comprised of meat,

eggs, poultry, and produce.

Collections for meat, poultry, and eggs were made in the s pring and fall seasons.

Samples of produce included vegetables and/or fruit with an at temp t t o sample at least one green leafy vegetable from each location.

The collection of produce was performed in late summer

~

IIIo EVALUATIONOF ENVIRONMENTAL DATA (Continued)

B.

8i Human Food Products - Table 20 (Conti)

Three indicator locations were sampled for each type of media collected, in addition, a control location was sampled during each collection period Indicator samples vere co11ected within a ten mile radius of the site in areas which would have a high potential for demonstrating possible effects of site operations.

Control samples were obtained from areas greater than ten miles from the site, preferably in a least prevalent wind direction.

The ultimate factor controlling sample locations was the.availability of required

samples, Attempts were made to maintain prior sample locations were possible.

Spring meat collections were obtained at one control location (greater than ten miles from the site) and at three indicator locations (less than ten miles from the site)

~

Spring meat collections showed detectable concentrations of K-40 in all samples.

K&0 concent ations ranged from 2.3 pCi/g (wet) to 2'

pCi/g (wet)

K-40 is a naturally occurring radionuclide.

One of the four spring meat samples showed detectable concentration,s of Cs-137.

The positive concentration was in one of the indicator samples.

Cs-137 was detected at a concent ation of 0.023 pCi/g (wet).

Cs-137 was not detected in the control sample.

Cs-137 was detected in many environmental samples and was most prevalent in. meat and. fish,

~ with respect to'll the'ample medias collected.

Cs-137 in meat samples has typically been a

result of pas t weapons testing.

Cesium is incorporated into meat tissue from feed sources.

The concentration detected in the spring meat sample was a very low concentration and thus could 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 cont ol sample during 1980 (0 01 pCi/g [wet]) ~

No other radionuclides were detected in the spring meat samples using gamma spectral analysis Fall meat collections were made at one cont ol.and at three indicator sample locations The fall samples showed detectable concentrations of KAO in all samples.

K-40 concentrations ranged from 2.4 pCi/g (wet) to 3.4 pCi/g (vet) ~

K-40 is naturally occurring.

-44

.III EVALUATION OF ENVIRONMENTAL DATA (Continued)

B ~

8.

Human Food Products Table 20 (Cont.)

Cs-137 was detected in three of, the four fall meat samples

~

The three positive results were all indicator samples (less than ten miles from the site)

~

The three results showed small c oncentrations of Cs-137 that were approximately a t the lower limit of detection (LLD)~

The results were 0.044 pCi/g (wet),

0 ~ 014 pCi/g (wet) and 0 023pCi/g (wet) as compared to the control sample result of <0.006pCi/g (wet) ~

These results are very small concentrations

and, as noted above for the spring

samples, are comparable to concent aeons detected at control location during 1981 with the exception of one sample The 1981 samples showed control Cs-137 concent ations 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 The detection of Cs-137 in meat samples has been noted for all year s since 1978 for indicator samples and since 1980 for control samples (control samples were not collected prior to 1980)

~'rior to 1978, Cs-137 was not detected as a result of the limited sensitivity of the analyses.

The detected concent ations'ince 1978 at the indicator locations have been fairly consistent.

These samples ranged from 0.022 to 0.038 pCi/g (wet) ~

At the control locations, Cs-137 ranged 'f om 0'010 to 0'20 pCi/g (wet) ~

The indicator sample annual 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 during 1978-1981 is an indication of cesium production from weapons testing.

During 1982 and

1983, Cs-137 was not detected at the control sample location although Cs-137 has been detected in the past at control sample locations (1961, for example)

~

The detection of Cs-137 'n meat samples during 1983 is most probably a result of operations of the site although a

small portion of this may be the a result of weapons testing.

In any event, the concentrations detected are very small and the impact or dose to man is insignificant.

An average annual dose to man can be calculated as a result of meat consumption from within 10 miles of the site (indicator sample results)

~

The average annual Cs-137 concentration in meat during 1983 in the indication samples is 0.026 pCi/g (wet)

A dose can be calculated to the critical organ and the whole body using standard Regulatory Guide 1.109 methodology.

The critical organ is the liver of an adult.

The consumption rate is 110 kg per year and is the maximum. rate in lieu of site specific data as recommended by Regulatory Guide 1 109'he critical organ or

1

~ ~

III.

EVALUATION OF ENVIRORKNTAL DATA, (Continued)

B ~

8 ~ Human Food Products - Table 20 (Cont.)

liver dose as a result of consuming meat from within 10 miles of the site, as represented by the indicator sample zesults, would be 0.312 mrem per year.

The whole body dose would be 0.204 mrem per year.

A critical organ dose of 0 312 mrem per year is small and can be compared to the dose to the critical organ as a

z esult of consuming naturally occu ring KAO in foods and water The critical organs, in this case, are the gonads and other soft tissues which receive a dose of approximate 20 mrem pez'ear for a

standard 155 pound man An additional dose comparison can be made considering bone tissue.

The dose to the bone of an adult as a result of consuming meat with a Cs-137 c oncentration equal to the 1983 annual mean indicator sample concentration of 0.026 pCi/g (wet) is 0.228 mrem per year.

A dose to the bone can also be calculated based on the 1983 annual mean K-40 concent ation of 2.8 pCi/g (wet).

This

dose, as adapted from NCRP Report 42, assumes the quality facto-" for the absorbed dose in mrad and the dose equivalent in mrem is l for gamma doses.

The bone dose as a result of K&0 would be 44.8 mrem pe" year.

The bone dose, as a result of Cs-137 in meat, is 0.005 of the bone dose from natu ally occurring K-40 in the 1983 meat samples.

The dose to the critical organ of an adult is small and as demonst ated above is minor compared to doses as a result of naturally occur ing K-40.

The wnole body dose received from the consumption of meat with a Cs-137 concentration of 0.026 pCi/g (wet) was calculated above as 0.204 mzem per year.

This dose can also be put into perspective by comparing this dose to the dose received from cosmic radiation with changes jn altitude.

A whole body dose of 0,204 mrem is based on meat consumption for one year and is comparable to the increase in dose received when an individual moves to an altitude of 10.2 metezs (33 4 feet) higher for the same time period (i.e.,

one yea") ~

Egg samples were collected in the spring (May 1983) and in the fall (November 1983) ~

Samples were collected at three indicator locations (within ten miles of the site) and at one control location (greater than ten miles fzom the site)

~

The only radionuclide detected during 1983 in egg samples was K-40'-40 was detected in the spring samples at concentrations that ranged from 0.8 pCi/g to 1.2 pCi/g (wet) ~

The fall samples showed K-40 concentrations that ranged from 1 0 pCi/g to l,l pCi/g (wet) ~

For both the spring and fall samples, the control samples had the lowest K-40 concentrations.

Poultry samples were taken during the spring (May.1983) and during the fall (November 1983) at three indicator locations and one contzol location.

K-40 was detected in all spring and fall samples for both indicator and control results.

¹40 in the spring samples ranged from 1.7 pCi/g to 2.9 pCi/g (wet).

The control sample had the lowe concent ation (1.7 pCi/guet) ~

K 40 in the fall samples ranged f om 3'

pCi/g to 3 3 pCi/g (wet) ~

The control sample showed a concentzation of 3.3 pCi/g (wet).

-46

III EVALUATIONOF ENVIRONMENTAL DATA (Continued)

B 8 ~ Human Food Products - Table 20

. (Cont.)

Cs-137 was detected in one of the spring indicator poultr y~.

samples during 1983.

The concentration detected was very small and was approximately at the lower limit of detection (LLD) level for the other spring poultry samples.

The detected Cs-137 concentration was 0.018 pCi/g (wet) ~

The LLD levels for the other samples ranged from <0.010 pCi/g (wet) to <0.018 pCi/g (wet) ~

Historically, the control samples for poultry have not demonstrated detectable concentrations of Cs-137 'lthough this sample is an indicator sample (i.e., within ten miles of the site), it is difficult to assess whether the detected cesium is plant related or a minute background cesium concentration.

In regards to background Cs-137> poultry can be compared to beef (meat) samples in the sense that Cs-137 can become incorporated in tissue through the ingestion pathway.

Thus, poultry have the potential to ingest Cs-137 through the pu"chased feed they consume (possible weapons testing resource) but conversely they also have the potential to incorporate Cs-137 through ingestion of local deposition (plant related source)

~

In any event, the impact as assessed by a dose to man, is insignificant.

Cs-137 has been routinely observed in poultry samples from indicator locations in the past.

Mean annual Cs-137 concent ations during 1978-1982 yielded concent ations of 0.012, 0 012, 0'9, not detected and 0.03 pCi/g (wet) respectively.

The 1983 concentration of 0.018 pCi/g (wet) is a 'reduction when compared to 1982 and is comparable to the average concentration for 1978-1982 's-137 has not been detected in control samples from 1978-1982, nor previous to 1978.

Historical data indicates that Cs-137 in poultry samples collected during 1983 may be a

result of operations at the site.

The'mpact, as a

esult of consumption of poultry>

can b e assessed by projecting 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

'ssuming a

Cs-137 concentration of 0.018 pCi/g (wet),

and a

consumption ate of 110 kg per year (Regulatory Guide 1.109),

a conservative dose to man can be calculated."

The adult whole body dose is 0 ~ 071 mrem per year and the adult critical organ dose is 0108 mrem per year to the liver.

These doses were calc'ulated for a six month period since Cs-137 was detected only during the first half of the year.

As noted in the assessment of the meat sample data, these doses are small when compared to an annual dose of 20 mrem,per yea-to the critical,organs, (the gonads and other soft tissues in this case) as a result of natu ally occurring K-40 in the environ-ment.

The critical organ dose as a result of'onsumption of poultry containing 0.018 pCi/g (wet) of Cs-137 is 0.108 mrem for 1983 ~

-47

III.

EVALUATION OF ENVIRONMENTAL DATA (Continued" )

B 8 ~ Human Food Products - Table 20 (cont )

This dose is 0.005 of the dose to.the critical organs as a

result of naturally occurring K-40 in the environment.

A comparison of the whole body dose calculated for poultry containing 0.018 pCi/g (wet) of Cs-137 and doses from natural conditions can also be performed The whole body dose was calculated, previously as 0'71 mrem for 1983'sing the increase in dose as a result of incremental increases in altitude from cosmic

adiation, a Cs-137 dose of 0.071 mrem is equal to residing at a location 3'

meters (11.8 feet) higher in, altitude for one year.

Fruits and vegetables were obtained during the ha"vest season Collections were made during Septembe" at three i'ndicator locations and one control location.

A successful attempt was accomplished to collect one broadleaf and one non-broadleaf fruit or vegetable at each location.

Broadleaf vegetables of Swiss chard and cabbage and non-broadleaf fruits and vegetables of tomatoes, cucumbers,

squash, and zucchini were collected.

K-40 was detected in all broadleaf and non-broadleaf vegetables and fruits.

Broadleaf vegetables (Swiss chard and cabbage) showed concentrations of K-40 ranging from 1.8 pCi/g to 4.6 pCi/g (wet) ~

Non-broadleaf fruits and vegetables

( tomatoes, etc')

showed concentrations of K-40 ranging from 1.2 pCi/g to 2.3 pCi/g (wet) ~

Be-7 was not detected'n any of the fruit and vegetable samples collected during 1983'his natu ally occurring radionuclide had been detected during 1982 and intermittently prior to 1982.

No other radionuclides were detected in the 1983 collection of fruits and vegetables.

Review of past environmental data indicates that K-40 has been consistently detected in food crop samples.

KAO 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 1982) ~

Dose estimates are not performed here for fruits and/or vegetables since no other radionuclides with the exception of naturally occurring K-40 were detected.

B ~

9. Soil - Table 21 Soil samples are collected every three years as required by the Environmental Technical Specifications, Soil samples were collected

'during 1983 at the nine. on-site air monitoring stations and at the six off-site air monitoring stations Samples were collected during 1977 and 1980 using this same

criteria, Limited sampling for soil was also conducted during 1974 at select on-site locations.

III.

EVALUATIONOF ENVIRONMENTALDATA (Continued)

B ~

9 ~ Soil Table 21 (cont.)

Soil sample results for 1983 included several radionuclides that are naturally occurring.

These radionuclides included K-40, Ra-226, and Th-228.

K-40 concentrations were highly variable as a

result of the different soil types at different sample 1 ocations.

K-40 c oncentrations during 1983 for on-site and off-site locations ranged from 7.2-19.4 pCi/g (dry) ~

On-site and off-site concentration ranges were approximately equal.

KAO was detected at all sample locations.

Ra-226 was detected in five of the nine on-site sample location's and three of the six off-site locations

~

Ra-226 anged from 1.13-2.15 pCi/g (dry) for on-site and off-site samples.

On-site and off-site ranges were approximately equal Th-228 was detected in all on-site and off-site samples.

Concentrations for on-site and off-site samples anged from 0.52-0.94 pCi/g (dry).

Cs-137 was detected in seven of the nine on-site samples and six of the six off-site samples.

On-site samples ranged from 0.07-1 19 pCi/g (dry) and averaged 0 ~ 42 pCi/g (dry) ~

Off-site samples anged from 0.20-1.46 pCi/g (dry) and averaged 0.6 7 pCi/g (dry) ~

The off-site range and average concentration was higher than the on-site range and average concentration.

The highest concentration detected for Cs-137 during 1983 was at the C off-site location which is considered a control location.

This variability of Cs-137 in the 1983 samples is

a. result of the natural variation in distribution for this radionuclide ~

S everal ecological processes such as vegetation cover, terrain,

erosion, etc.

can affect the distribution of Cs-137 Cs-137 in soil samples is a result

. of previous weapons testing.

Any possible Cs-137 in on site samples as a result of operations at the site would not be able to be measured because of the natural variability of the concentrations The fact that the off-site mean is slightly greater than the on"site mean indicates that any possible Cs-137 concentration as a result of operations at the site is insignificant Historically, Cs-137 concentrations in on-site samples has decreased significantly since

1974, 1977 and 1980 ~

Mean Cs-137 concentrations for these years were 1.02>

1.03 and li26 pCi/g (dry) ~

The 1983 on-site mean was 0.42 pCi/g (dry). '977 and 1980 off-site mean concent ations were also significantly greater than the 1983 off-site sample mean concentration (off-site samples were not collected during 1974);

Mean concentrations for the off-site locations during 1977 and 1980 were 1.17 and'.20 pCi/g (dry) respectively.

The 1983 mean off-site Cs-137 concentration was 0'7 pCi/g (dry) ~

The s'ignificant reductions in the on-site and off-site mean Cs-137 concentrations are probably a result of radiological decay of Cs-137, the reduced frequency of nuclear weapons

testing, and redistribution of Cs-137 by vegetation'

III EVALUATIONOF ENVIRONMENTAL DATA (Continued)

B~

9o Soil - Table 20 (cont~)

No other radionuclides were detected, in the 1983 soil samples using gamma spectral analysis Sz-90 was detected in seven of the nine on-site samples and six of the six off-site

. samples during 1983'ean on-site and off-site concentzations for Sr-90 were equal and showed a result of 0 e 18 pCi/g (dry) ~

On-site samples ranged 0.03-0~47 pCi/g (dry) and off-site samples ranged from 0.10&.32 pCi/g (dry).

Sr-90 in 1983 soil samples is a result of previous'eapons t es ting The 1983 sample results support this fact.

Variability in Sz-90 concentrations is a result of the natural variation in the distribution process, as was noted above for soil Cs-137 concentrations.

Historically, Sr-90 concentrations have been variable as a

result of the distribution processes.

The 1974 mean on-site concentration was 0'7 pCi/g (dzy) ~

Subsequent years showed a

general reduction in Sr-90 concentrations.

During

1977, the on-site concentration was 0.40 pCi/g (dry) which was a slight increase compared to 1974'he mean on-site concentration during 1980 showed

a. significant decrease to 0.07 pCi/g (dry) ~

The 1983 on-site mean, as noted previously, was 0.18 pCi/g (dry) which represented a slight increase from 1980 ~

Off-site mean concent ations showed similar historical trends.

Off-site zesults for 1974 were not available.

Off-site results for 1977 and 1980 showed mean concent ations of 0.21 and 0.06 pCi/g

( dry).

The 1983 mean off-site concentzation was

0. 18 pGi/g (dry) which was an increase in regards to 1980 ~

C Conclusion The Radiological Environmental Monitoring Program

(~IP) was established to detect and evaluate any possible impact to the environment surrounding the Nine Mile Point area resulting f om operations at the site.

Samples epresenting higher trophic levels, such as fish and meat were reviewed closely to evaluate any impact to the general environment or to man.

In addition, the data was reviewed for any possible historical tzophic level bioaccumulation trends.

Little OD no impact could be determined resulting from radionuclide deposition considering all sources (natuzal, weapons

testing, etc.)

~

In regards to doses as a

esult of man-made radionuclides, a significant portion of the doses received by a

member of the public was from past nuclear weapons testing.

Doses as a result of natuzally occurring zadionuclides, such as K-40>

contributed a.

major portion of the total annual dose to members of the public.

-50

III.

EVALUATIONOF ENVIRONMENTALDATA (Continued)

C ~

Conclusion (Cont.)

Any possible impact as a result of site 'operations is extremely minimal when compared,to the impact from natural background levels or weapons testing.

It has been demonstrated that almost all environmental samples contain traces of radionuclides which are a

result of weapons testing or natur ally occurring sources (primordial and/or cosmic related).

Whole body doses to man as a

result 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 a

small fraction of 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.

-51

s

~

~

REFERENCES 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 10CFR Part 50, Appendix I"9 March 1976 (Revision 0) ~

2 ~

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 ~

Efchholz, G

Environmental Aspects of Nuclear

- Power, Ffrst Edition, Ann Arbor Science Publishers, Ines 9 Ann Arbor, Michigan,"1976 ~

4.

National Council on Radiation Protect fon and Measurements (NCRP),

Environmental Radiation Measurements NCRP Report No. 50, 1976 ~

5 ~

National Council on Radiation protection and Measurements (NCRp), Natural Background Raoiation in the United States, NCRP Report No. 49, 1979.

6 ~

National

. Council on Radiation Protection and Measurements (NCRP),

Cesium-137 from the Envfronment to Man:

Metabol'sm and Dose, NCRP Report Noe 5

9 1 7 e

7 ~

National Council on Radiation Protection and H'easurements (NCRP),

Radiation Ex osure from Consumer Products and Miscellaneous

Sources, NCRP Report No. 56, 1977.

8 ~

U.S.

Nuclear Regulatory Commfssion Regulatory Guide 4.8, "Environmental Technical Specifications for Nuclear Power Plants" 9 December, 1975.

9 ~

U ~ S ~ Nuclear Regulatory Commission Branch'Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program",

November 1979

'0

'isenbud, Merrill, Environmental Radioactivity, Second

Edition, Academic

Press, New York, NY 1 lie Francis, C.W.,

Raaiostrontfum Movement fn Soils and U take fn Plants.

Environmental Sciences

Division, Oa Ridge National Laboratory, U ST Department of Energy, 1978

'2.

Thomas, C

W et alsp Radioactive Fallout from Chinese Nuclear WeaPons

Test, September 26, 1

~

BAL-Batte e,

Paci ic Nor west Laboratories, U S.

ERDA, 1979 13 'ochinp Edward Eep Estimated Populatfon Exposure from Nuclear Power Production and other Radiation

Sources, Nuclear Energy

Agency, Organization for Economic Co-Operation and Development, 1976

-52

t

~ ~

REFERENCES {Continued) 14 International Commission on Radiological Protection (ICRP), Radionuclide Release into the Environment Assessment of Doses to Man, ICRP Publication 29, 1979 ~

15 Glass tone, Samuel and J ordan, Walter

- H.,

Nuclea Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ille, 1980 '

---"16 U

S ~DePartment of Health, Education, and Welfare.

Radiological Health Handbook.

Bureau of Radiological

Health, Rockville, Marylan 20852

'anuary 1970 ~

-53

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'ean values are comprised of positive or IJ D values where applicable These tables are entitled "Environmental Sample Summary".

54

ENVIRONMENTAL SAMPLE

SUMMARY

(1983)

Medium/Sam le Cladophora Cladophora Cladophora Locatton Oswego 6,2 mi. 8 235o (control)

NMP 0.3 mi. 6 275o JAP 0 ~7mi 868o Be-7 K-40 Co-60

.Cs-137 lfn-54 Th-228 Others Be-7 K-40 Co-60 Cs-137 Hn-54 Th-228 Others Be-7 K-40 Co-60 Cs-137 Mn-54 Th-228 Others NS NS NS 0'2 6.00

<0.01 0'3

<0.01

<0.03

<LLD 0.57 6.07 0.09 0 F 06 0.02 0.05

<LLD 0 ~ 67 3.52 0.08 0.04 0.01

< 0.01

< LLD 0'7 3'2

<0 01

<0.01

<0.01

<0.01

<LLD 0.65 2,08 0.09 0.04 0.02 0.02

<LLD 0'8 2.98 0,11 0.03 0.04

<0.01

<LLD NS NS NS Samples not collected during the first and fourth quarters of the year.

Results in units of pCi/g (wet)

ENVIRONHENTAL SAHPLE SUHHARY (1983)

Dam Shoreline Sediment Location Lang's Beach Control 5'

mi 8 230o K-40 Ra-226 Th-228 Sr-90 Co-60 Cs-137 Others 12.0 0'3 0.31(1)

<0 008

<0.06

<0.05

< LLD 15 3

1.21 0 ~ 62

<0.001

<0.02

<0.02

<LLD NS 14 1

1 21 0.60

<0 002

<0 ~ 05

<0.05

<LLD Dam Shoreline S ediment NHP 0.3 mi 8 275o K-40 Ra-226 Th-228 Sr-90 Co-60 Cs-137 Others 9 ~ 7 0,21 0 ~ 31 (1)

(2)

<0.07 0.16

< LLD 15 '

1'2 0.55

<0.002 0 ~ 14 0.85

< LLD 13 '

<0 ~ 92 0'8 0.022 0 36 1.8 1

< LLD

• Not Environmental Technical Specification sample.

Extra sample for evaluation purposes.

(1) Result for Th-232

'2)

- Sample lost during laboratory analysis.

NS No samples collected during the third quarter of the year

~

Results in units of pCi/g (dry)

ENVIRONNEHTAL SAHPLE SU191ARY (1983)

Location Fish Oswego (Brown trout)

(control) 6 3ml6235o Fish Oswego (Lake Trout 81)

Fish Oswego (Lake Trout d2)

Radionuclide-.

Sr-89 Sr-90 Cs-137 K-40 0 thers Sr-89 Sr-90 Cs-137 K-40 0 thers Sr-89 Sr-90 Cs-137 K-40 0 thers NS NS NS

<0 ~ 027

<0.001 0.046 3 1

< LLD

<0.031

<0.002 0.057 3.0

< LLD

<0.033

<0.002 0.049 3.0

< LLD NS NS NS

<0.006

<0.002 0.057 3 8

< LLD

<0.004

<0.002 0 ~ 041 2.8

< LLD

<0.004

<0.002 0.044 3+1

< LLD Fish

( Brown Trout NHP 0.3 mi 8 315o Sr-89 Sr-90 Cs-137 K-40 0 thers

<0.099

< 0.003 0'46 3.2

< LLD NS 0 041 3'

< LLD Fish NMP (Lake Trout 81 Sr-89 Sr-90 Cs-137 K-40 I

0 thers

<0.052

<0.002 0'56 3.3

< LLD NS

<0'02

<0,001 0.038 3,0

< LLD NS No sample collected during the first and third quarters of the year.

• Sample lost during laboratory analysis.

Results in units of pCi/g (wet) ~

ENVIRONMENTAL SAMPLE

SUMMARY

(l983) (cont ~ )

Fish (cont.)

NMP (Lake Trout d2)

Fish JAF (Brown Trout) 0.6 mi 8 55 Sr-89 Sr-90 Cs-137 K-40 Others Sr-89 Sr-90 Cs-137 K-40 0 thers NS NS

<0 ~ 066

< 0.003 0.033 2.9

<LLD

<0.084

< 0.003 0.042 3 ~ '1

< LLD NS NS

<0 ~ 001

<0.001 0.047 3.3

<LLD

<0.002

< 0.001 0,050 3.7

< LLD Fish (Lake Trout fl)

Fish (Lake Trout P2)

JAF JAF Sr-89 Sr-90 Cs-137 X-40 0 thers Sr-89 Sr-90 Cs-137 K-40 0 thers NS

<0.033

<0,002 0.038 3 1

< LLD

<0.095

<0.003 0 ~ 051 3.8

< LLD NS NS

<0.003

<0.001 0.055 3.2

< LLD

<0.002

<0.001 0.039 2'

< LLD NS - No sample collected during the first and third quarters of the year.

Results in units of pCi/g (wet) ~

-58

ENVIRONMENTAL SAMPLE SUMfARY (1983)

Location Radionuclide Fish Oswego (Brown trout)

(control) 6 '

mi 6 235o Sr-89 S r-90 Cs-137 K-40 0 thers

<79 ~ 6

<3 ~ 2 135 '

9,145

< LLD NS

< 18.2

<5.4 182.4 12,096

< LLD Fish

Oswego (Lake Trout 81)

Fish Oswego (Lake Trout 02)

Sr-89 Sr-90 Cs-137 K-40 0 thers Sr-89 Sr-90 Cs-137 K-40 0 thers NS NS

<85 ~ G

<4.7 157.3 81280

< LLD

<92.1

<5+3 136.7 8,370

< LLD NS NS

< 11.4

<5 7 122.1 8,490

< LLD

<12.9

<702 133 2 9,180

< LLD Fish (Brown Trout NMP 0.3 mi 8 315o Sr-89 S r-90 Cs-137 K-.40 0 thers NS

<273 ~ 2

<7.4 127.0 8 >832

< LLD NS 130.6 12 $576

< LLD Fish NMP (Lake Trout 81 Sr-89

~

Sr-90 Cs-137 K-40 0 thers NS

< 158 ~ 1

<6.4 170.2 10,032

< LLD

<6 ~ 0

<2.4 112 8 9,030

< LLD NS No sample collected during the first and third quarters of the year.

• - Sample lost during laboratory analysis.

Results in units of pCi/kg (dry).

-59

ENVIRONHENTAL SAHPLE SUHHARY (1983) (cont.)

Location Fish (cont.)

(Lake Trout 82)

Fish (Brown Trout)

Fish (Lake Trout 41)

NMP JAF 0.6 mi 8 55o JAF 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 0 thers NS NS NS

< 225 ~ 7

<9.9 112i9 9,918

<LLD

<252.8

< 8.4 126.4 9,331

<LLD

<91.4

<4.7 105. 3 8,587

< LLD NS NS NS

<0.5

<2+ 2 141,6 9 <<780

<LLD

<6'

<2 ~ 2 160 ~ 0 11,680

< LLD

<8 ~ 1

<3.6 165.9 90630

< LLD Fish JAF (Lake Trout 42)

Sr-89 Sr-90 Cs-137 K-40 Others

< 261.2

<6.9 140 ~ 2 10,450

< LLD NS

<6 6

<2' 117.3 7,950

< LLD NS No sample collected during the first and third quarters of the year.

-60

ENVIRONMENTAL SAMPLE Sl981ARY (1983)

Location Monthly Water Composite Oswego City Water (control) 7 8mi6240o NMP Inlet 0.3 mi 8 305o JAF Inlet 0.5 mi 8 70o K-40

<15.3 Cs-137

<1.24 Co-60

<1,62 Gross Beta 1.6 K-40

<15 ~ 1 Cs-137

< 1.20 Co-60

<1.60 Gross Beta 1.9 K-40

<15.4 Cs-137

< 1.24 Co-60

<1.33 Gross Beta 1.7

< 12.6

<1.00

<1,19 2.1

< 11.9

< 1,09

<1.28 3.8

<13.1

<1.03

< 1,18 2.9

<13.6

<1 17

<1.29 2.8

<12 ~ 7

<1.08

<1.43 3.1

<14 4

<1.09

<1.28 3.2

<15 0

<1 19

<1.45

<2. 7

<17 ~ 6

<1 ~ 19

<1 ~ 35

<3.1

<14 ~ 8

<1.19

< 1.59

<2.6 Results in units of pC1/liter.

• All other results for gamma spectral analysis were less than LLD.

-61

ENVIRONHENTAL SAHPLE SB1MARY (1983) quarterly Water Composite Location Raw City Water (controls 7 '

mi 8 240o NNP Inlet 0.3 mi 8 305o JAF Inlet 0 ~ 5 mi 8 70o Radionuclide Tritium Sr-89 Sr-90 Tritium Sr-89 Sr-90 Tritium Sr-89 Sr-90 239

<0' 1.0 260

<l. 1 1.0 249

<0.6 0.8 230

<2.0

<0.9 410

<2.0 0

7 260

<2.0 1 0 280

<2,0 0 ~ 9

?90

<1.0

<0 ~ 7 560

<2,0 0'

4th quarter 250

<1.4 0'

190

<1.6

. 1.1 320

<1.4 0'

Results in units of pCi!liter.

-62

ENVIRONMENTAL SAMPLE

SUMMARY

(1983)

Location No.

Location Airborne Particulate Filters (Gross Beta)

Dl on"site D2 E

F G

HI J

K oo2 0.4 0.4 0'

0.7 0.8 0.8 0.9 0.5 mi 8 69o mi 8 140o mi 8 175o mi 8 210o mi 8 250o mi 8 71o mi 8 98 mi 8 110o mi 8 132o

0.021 0.024 0.023 0.024 0 ~ 022 0 ~ 021 0.020 0 021 0 ~ 022 0.020 O.O2O 0.020 0.018 0 ~ 018 0.020 0.016 0.019 0.016 0 ~ 028 0 ~ 031 0.029 0.030 0 027 0.027 0 ~ 026 0,027 0.024

,0.025 0 ~ 028 0 ~ 026 0.024 0 ~ 028 0.023 0.023 0.025 0 ~ 023 Airborne Particulate Filters (Gross Beta)

C off-site Dl D2 E

F G

16.4 mi 8 42o lli2 mi 6 80o 9 ~omi8 117 6.5 mi 8 166o 7'

mi 8 190o 5.3 mi 8 225o 0'23 0.022 0.023 0 ~ 022 0 ~ 022 0 ~ 023 0.019 0.018 0.018

. 0.019 0.019 0,021 0 ~ 030 0 ~ 030 0 029

,0 031 0 '31 0 ~ 026 0.022 0,023 0.024 0 ~ 024 0 ~ 024 0 ~ 029 Results in units of pCi/m

~

-63

ENVIRONNENTAL SAHPLE SUlNARY (1983)

Hedium/Sam le Air Particulate Filter Composite Isotopic Location (off-s'ite)

.-2(b)

(on-site)

Radionuclide Be-7 Ra-226 K-40 Cs-137 Co-GO Nn-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 101.5

<4.81

<4.41

<0.29

<0.40

<0.30

<1 ~ 22

<0,4 1

<2.50

<LLD 81.3

<3.64 3.52

<0.26

<0 ~ 29

<0 ~ 22

<0.89

<0.31

<1.90

<LLD 114.1

<6.45

<4.00

<0.32

<0.37

<0.27

<1.18

<0.34

<2 ~ 45

<LLD 92 ~ 5

<3o32 2 ~ 71

<0.25

<0 36

<0.27

<0.94

<0.32

<1.82

<LLD 129.3

<8,94

<5 ~ 16

<0.38

<0.48

<0.33

<1 ~ 70

<0.49

<3 ~ 17

<LLD 96 ~ 5

<5,14

<4 ~ 22

<0.29

<0.37

<0.30

<1.29

<0.37

<2.58

<LLD 102.9

<8.22

<6.35

<0.55

<0 ~ 77

<0.49

<2.02

<0,71

<4 18

<LLD 87.8

<5.27

<5 ~ 65

<0.38

<0.90

<0.41

<1.36

<0,40

<3. 12

<LLD Results in units of 10 pCi/m (a) A-1 monthly composite comprised of stations:

C off-s ate (16.4 mi.

8 42 ), Dl off-site (11i2 ml 80 ) and D2 off-site (9.0 mi. 8 117 ).

(b) B-2 monthly composite comprised of stations.'N on-site (0.8 mi.

8 71 ), I on-site (0.8 mi.

6 98 ),

J on-site (0.9 mi 8 110 ) and K on-site (Oo5 mi. 8 132 ).

-64

ENVIRONHENTAL SAHPLE SUHHARY (1983) (cont ~ )

Hedium/Sam le Air Particulate Filter Composite Isotopic (cont ~ )

Location A-2(c)

(off-site)

B 1(d)

(on-site)

Rad.ionuclide Be-7 Ra-226 x-40 Cs-137 Co-60 Hn-54 Ce-144 Nb-95:

Ru-106 Others Be-7 Ra-226 K-40 Cs-137 Co-60 Hn-54 Ce-144 Nb-95 Ru-106 Others 103.8

<4 ~76

<4.32

<0.31

<0.34

<0.28

< 1o25

<0.37

<2 ~ 35

<LLD 98.9

<2,98 3.71

<0.25

<0.26

<0.19

<0.86

<0,28

<1,86

<LLD 110. 6

<5.64

<4 ~ 21

<0.30.

<0.36

<0.23

<1.18

<0,38

<2 ~48

<LLD 111.4

<3 91

<3.43

<0.30

<0.29

<0 ~ 20

<0.93

<0.31

<1 ~71

<LLD 131.3

<5,92

<6 ~ 13

<0.38

<0.44

<0'2

<1.54

<0,46

<2o73

<LLD 124.7

<4.99

<3.80

<0.28

<0.28

<0.22

<1.16

<0.28

<2.04

<LLD 109.9

<7.07

<5 ~ 02

<0.44

<0.55

<0.44

<1 70

<0.63

<3 ~ 42

<LLD 86 7

<5o22

<4'7

<0,32

<0.43

<0.34

< 1.26

<0.44

'2.74

<LLD Results in units of 10 pCi/m3 (c) A-2 monthly composite comprised of stations:

190 ) and G off-site (5.3 mi, 8 225 ) ~

(d) B-l monthly composite comprised of stations:

140 ),

E on-site (0.4 mi 8'175'9, F on-site (0.5 off-site (6.5 mi.

8 166 ),

F off-site (7.7 mi Dl on-site (0.2 mi.

8 69 ),

D2 on-site (0.4 mi.

6 mi. 8 210 ) and G on-site (0 '

min 6 250 ) ~

-65

ENVIRONHENTAL SAHPLE SUNNARY (1983)

Airborne Charcoal Cartridges

( I-131)

Airborne Charcoal Cartridges

( I-131)

Location No.

Dl on-site D2 E

P G

HI J

K C off-site Dl D2 E

P G

0' mi 8 69o 0'

mi 8 140o 0.4 mi 8 175o 0'

mi 8 210o 0'

mi g 250o 0.8 ml 8 71o F 8 ml 8 98o 0 9mi8 llpo 0 ~ 5 mi 8 132o 16.4 mi 6 42o 11.2 mi 8 80o 9op mi 9 117o 6+5 mi 8 166o 7'

mi 8 190o 5

3 mi 8 225o

<0,016

<0.026

<0.022

<0.030

<0.024

<0 022

<0.017

<0'20

<0.02l

<0.019

<0.020

<0.018

<0.020

<0.019

<0.017

<0.016

<0.024

<O.pl9

<0 ~ 022

<0.022

<0.022

<O.pl8

<0.024

<0.015

<0.014

<0.016

<0.015

<0.018

<0 ~ 016

<0.025

<0,016

<0 021

<0 ~ 020

<0.015

<O.0l8

<0 ~ 020

<0.017

<0.017

<0.015

<0.015

<0+017

<0 ~ 015

<0 016

<0 ~ Ol4

<0.016

<0.021

<0.031

<0.023

<0 ~ 018

<0.022

<0.024

<0.022

<0.021

<0.020

<0'20

< 0 ~ 018

<0 i020

<0 ~ 020

< 0.019

<0 019 Results in units of pCi/m3 ~

-66

ENVIRONMENTAL SN5PLE SVMMARY (1983)

Medium/Sam le Location No.

Location 1st uarter I

3rd uarter 4~th eattet Direct Radiation Environmental TLD 3'

5 6

7 8

9 10 1.1 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 0 ~2mi8 69o 0.4 mi 8 140o O.4 mi e 175o 0.5 mi 8 210 0.7 mi 8 250o 16.0 mi 8 42 114 mi8 Boo 9.0 mi 8 117 7 ~ 2 mi 6 160o 7.7 mi 8 190o 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'.8 mi 8 71o 0.8 mi 8 98 0 ~ 9 mi 8 lloo 0.5 mi 8 132o 0.4 mi 8 60o O.S mi 6 68o 0.5 mi 8 57 0.4 mi 8 57o 0 ~ 2 hi 8 290o 0.1 mi 8 292o 9.4 mi 8 88o 12 6mi864o 7 ~ 6 mi 8 130o 7.9 mi 8 178o 0.6 mi 8 69o 0,8 mi 8 92o 20.0 mi 8 165o 0.7 mi 8 115o 7.5 mi 8 233 38.58

20. 96

17. 10 15.68 16.58 21.22 18.03 17.53 16 F 16 16'0 17.08 17.50 15'2 16.32 17.66 26.86 19'3 18.08 18.89 62.70 140.84 223.90 47'5 64.02 173.74 18.00 18'8 18439 17,21 135.71 23.81 16 67 (1) 18.37 32 ~ 36 17.83 18'6 15.36 17e55 20 43 1S.9O 14.97 16.74 13.90 16.53 16.23 17.02 20.41 22.34 19.27 19.46

20. 15 4.7 ~ 18 123.22 174.22 4 1.45 54.36 37.88 19.62 17.92 19.64 17.65 51.35 20.26 17 ~98 19.38 17.24 20 42 17el2 16.31 (1) 15.94 17 40 13.96 15.61 16 F 07 15'6 15.27 14'6 13,27 16.64 15.47, 17'6 (1) 15'3 15 23 32.61 79 ~ 22 100.52 27'2 53.98 38.84 16 e08 16.20 16.30 15'6 26.51 (1) 14 ~ 12 14.58 (1) 53'3 23.2 20.6 17 '

2042 19.8 17.6 18.4 17 1

17.5 18.6 18.4 15 es 21.8 17.9 27e6 20 '

20,8 19 e2 69.9 170.6 237e1 60 6 69 '

52 5 17.4

. 19el 21,2 19 '

55.1 23.9 15' 18.0 (1)

-67

ENVIRONHENTAL SAHPLE SU191ARY (1983) (cont, )

Direct Radiation Environmental TLD

( continued)

Location No.

52 53 54 55 56 57 58 59 60 61 65 Loeatkoo 5 ~ 8 mi 8 227o 13.7 mi 8 183o 9 3mi8 115o 13 ~ 7 mi 8 75o 5.4 mi 8 120o 1.9 mi 6 145o 3 ~ 2 mi 8 220o Oe5 mi 6 95o 21.0 mi g 225o 0.8 mi 8 83o 7.8 mi 8 198 16.82 17 90 15.65 17'2 18.03 17e27 16el8 60.97 20 17 31.35 17.18 14.74

., 1'7419 16'6 16'4 18.46 17'3 18.52 45 12 18.54 25.42 16.35 15'0 16.78 14 40 14.04 15.60 12.74 15.54

28. 19 15 62 (1) 15'4 4tb~uattet 18,9 18 ~ 7 1G.1 16.2 20.2 17 '

19o5 lplo3 15o6 32op 16.0 Results in average mrem per quarter.

(1) TLD lost (vandalism)

-68

ENVIRONMENTAL SAMPLE

SUMMARY

(1983)

Location Dose Rate 1st uar ter 4 lh~uar te r Continuous Radiation Monitors C off-site MIN 16+4 mi 8 42o MAX>>

AVE~

Dl on-site 0'

mi 8 69 D2 on-site 0.4 mi 8 140o

-E on-site 0,4 mi 8 175o F on-site 0 ~ 5 mi 6 210o 0.010 0.032 0,015 0'11 0.057 0.018 0.010 0 063 0.015 0.010 0.097 0.017 0.011 0.035 0.017

0. 010 0.043 0.022 0.011 0.036 0.019 0.010 0.030 0.013 0.010 0'32 0.015 0.014 0.069 0.025 0 ~ 010 0 040 0,015 0.010 0.024 0.017 0 +011 0 023 0,015 0 012 0 028 0 018 0,014 0+041 0.022 0.010 0.031 0.017 0 ~ 012 0'57 0,022 0.012 0'50 0,016 0.012 0'52 0.016 0.014 0'47 0.023 G on-site 0.7 mi 8 250o H on-site 0 ~ 8 mi871o I on-site 0'

mi 8 98o 0.012 0.053 0.020 0.012 0.075 O.b21 0.013 0.064 0,022 0.015 0.044 0.023 0.013 0.042 0.020 0.017 0.057 0,027 0,016 0.042 0.023 0.015 0 il07 0.024.

0 010 0 032 0.020 0.014 0 ~ 046 0.019 0.014 0.075 0.024 0.010 0.031 0.016

-69

ENVIRONHENTAL SAHPLE SUHHARY (1983) (cont. )

Location Dose Rate Continuous R adia tion Honitor's (cont.)

J on-site 0.9 mi 8 110 K on-site

.0.5 mi 8 132o HIN.

HAXo AVE~

0.010 0.056 0.015 0.010 0.040 0.016 0.010 0.049 0.015 0 ~ 012 0'32

- 0.018 0.010 0.043 0.013 0.010 0,031 0.018 0 ~ 010 0.054 0.014 0.010 0'38 0.015 Results in units of mrem per hour ~

-70

ENVIRONMENTAL SAMPLE SVMMARY (1983)

I Milk Location 7.7 mi 8 i13o I-131 NS

<0 ~ 2

<0 ~ 3

<0 ~ 2 40 control 15.3 mi 8 220o 14 9.8 mi 8 120o 16 5.2 mi 8 190o 5

7 ~ 2 mi 8 146o 7

5.5 mi 8 107o 45 8.0 mi 8 125o 50 8 ~ 2 mi 8 95 55 9.0 mi 8 95o 60 9.5 mi 8 90 I-131 I-131 I-131 I-131 I-131 I-131 I-131 NS NS NS NS NS NS NS NS

<0 ~ 2

<0.2

<0 ~ 2

<0.2

<0.2

<0 ~ 2

<0 ~ 2

<0 ~ 3

<0.3

<0 ~ 2

<0 ~ 2

<0 ~ 2

<0 ~ 2

<0.3

<0 ~

2'0+2

<0.2

<0 ~ 2

< 0.3

<0.3

<0.2

<0.3

<0 ~ 3 1

NS Milk samples not collected during the first quarter (not the local grazing season)

~ Location discontinued for the remainder of 1983.

Results in units of pCi/liter,

-71

ENVIRONMENTAL SAMPLE SVMMARY (1983)

Milk Location 4

7 ~ 7 m%8 113 40 15.3 mi 8 220 (control) 14 9,8 mi 8 120o 16 5'

mi 8 190o 5

7.2 mi 8 146o 7

5.5 mi 8 107o 45 8 ~ 0 mi 8 125o S r-90 Cs-137 K-40 Others Sr-90 Cs-137 K-40 Others Sr-90 C s-137 K-40 Others Sr-90 C s-137 K-40 Others Sr-90 Cs-137 Z-40 Others Sr-90 Cs-137 K-40 Others Sr-90 Cs-137 K-40 Others NS NS NS NS NS NS 2'

<4 ~ 6 1350

<LLD

<3.0

<4.3 1350

<LLD 2.1

<3.9 1400

<LLD 4.8

<5e2 1400

<LLD 3+i

<5.4 1250

<LLD 3.4

<4.6 1300

<LLD 4.2

< 4.0 1300

<LLD 2.5

<6 ~ 1 1293

<LLD 3',0

<6,2 1420

<LLD 4 ~ 5

<8.2 1340

<LLD 2.7

<7o3 1343

<LLD F 1

<6+5 1477

<LLD 3+6

<5.1 1240

<LLD 2'

<4.9 984

<LLD 1.9

<6 ~ 1 1184

<LLD 3'

<5.9 1266

<LLD 2 ~ 6

<5.9 1237

<LLD 2 ~ 3

<5 ~ 2 1370

<LLD 3.0

<5o5 1317

<LLD NS Milk samples not collected during the first quarter (not the local grazing season)

• Location discontinued for the remainder of 1983.

Results in units of pCi/liters

-72

ENVIRONMENTAL SAMPLE SUlRARY (1983)

Milk Location 50 8.2 mi 8 95o 55 9.0 mi 8 95o 60 9 ~ 5 mi6 90o Sr-90 Cs-137 x-40 Others'r-90 Cs-137 K-40 Others Sr-90 C s-137 K-40 Others NS NS NS 2.0

<4.4 1500

<LLD 3.1

<4.2 1400

<LLD 3 ~ 1

<3 ~ 7 1400

<LLD 2 ~ 0

<5.4 1323

<LLD 3.9

<6.3 1357

<LLD 4th tleatte t 1+7

<4.7 1420

<LLD 3 ~ 1

<5.9 1135

<LLD NS "Hilk samples not collected during the first quarter (not the local grazing season)

• - Location discontinued for the-remainder of 1983.

Results in units of pCi/liter.

-73

ENVIRONHENTAL SAHPLE SVHHARY (1983)

Location Beef II control 14,7 mi 8 225o K-40 C s-137 Others NS 2.6

<0.014

<LLD NS NS Beef Beef Beef Beef Bee f E

7' mi 8 120o F

I

~

8.0 mi 8 215o G

3.3 mi 8 202o N - control 14 ~ 7 mi 6 225o I

1.8 mi 8 146o K-40 Cs-137 Others I

K-40's-137 Others K-40 Cs-137 Others K-40 Cs-137 Others K-40 C s-137 Others NS NS NS 2.9

<0.017

<LLD 2.5 0.023,

<LLD 2.3

<0.018

<LLD NS NS NS NS NS NS NS NS NS NS 3'

<0.006

< LLD 2.9

<0.044

< LLIJ Beef J

2 ~ 8 mi 8 130o K-40 Cs-137 Others NS NS NS 2.4 0 014

<LLD Beef K

3 ~ 2 mi 8 115o K-40 Cs-137 Others NS NS NS 3.4 0.023

<LLD NOTE: NS -Sample not collected during that quarter.

Results in units of pC1/g (wet) ~

-74

ENVIRONHENTAL SAHPLE SRSIARY (1983)

Hedium/Sam le Eggs Eggs Eggs D - control K-40 12.6 mi 8 234 Cs-137 Others A

K-40 3 ~ 7 mi 8 195o Cs-137 Others B

X-40 2 '

mi 8 185 Cs-137 Others NS NS NS 0.8

<0.019

< LLD 0'

< 0.016

< LLD 1 2

<0.024

< LLD NS NS 1.0

<0 F 008

<LLD 1.1

<0.005

<LLD 1.1

<0 ~ 006

<LLD Eggs C

K-40 2 ~ 3 mi 8 170o Cs-137 Others NS 1.1

<0 OlG

<LLD NS 1.1

<0 ~ 007

<LLD NOTE: NS Sample not collected during that quarter.

Results in units of pCi/g (wet) ~

-75

ENVIRONMENTAL SAMPLE SVMMARY (1983)

Chicken Location D-control 12,6 mi g 234o K-40 Cs-137 Others NS 1.7

<0.010

< LLD NS 3.3

<0.007

<LLD.

Chicken Chicken Chicken A

3 ~ 7 mi 6 195 B

2 ~ 3 mi 8 185o C

2.3 mi 8 170o K-40 Cs-137 Others K-40 Cs-137 Others K-40 Cs-137 Others NS NS 2.9

<0.015

<LLD 2.8

<0.018

< LLD 2.8 0.018

<LLD NS NS NS 3,1

<0'09

<LLD 3.2

<0.007

<LLD 3 ~ 1

<0,008

< LLD NOTE: NS -Sample not collected during that quarter.

Results in units of pCi/g (wet) ~

-76

ENVIRONMENTAL SAMPLE

SUMMARY

(1983)

Cabbage

( leafy)

M-control 15 '

mi 8 222o K-40 Be-7 I-131 Cs-137 Others NS NS 2.9

<0 ~ 09

~<0.01

<0.013

<LLD NS Swiss Chard (leafy)

Swiss Chard

( leafy)

Cabbage (leafy)

Zucchini Tomatoes I

1.8 mi 8 146' 1.7 mi 8 162o N

2.0 mi 8 110o M control 15 ~ 2 mi 8 222o I

1.8 mi 8 146o 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 K-40 Be-7 I-131 Cs-137 Others K-40 Be-7 I-131 Cs-137 Others NS NS NS NS NS NS NS NS NS NS 3.7

<0.08

<0.01

<0.010

<LLD 4.6

<0.13

<0.02

<0 ~ 016

<LLD 1.8

<0.09

<0.01

<0.013

<LLD 1,2

<0,06

<0 Ol

<0.007

< LLD 2.3

<0,04

<0.01

<0.006

<LLD NS NS NS NS NS

-77

ENVIRONMENTAL SAMPLE

SUMMARY

(1983) (cont

)

Cucumbers Squash Location L

1.7 mi 8 162o N

2.0 mi 8 110o K-40 Be-7 1-131 Cs-137 Others K-40 Be-7 1-131 Cs-137 Others NS NS HS NS 1.6

<0.05

<0.01

<0.010

<LLD 1,6

<0.11

<0 ~ 02

<0.014

<LLD NS NOTE: NS " Sample not collected during that quarter.

Results in units of pC1/g (wet) ~

-78

DATA TABLES - 1983 79

TABLE I SAHPLE COLLECTION AND ANALYSIS

-SITE RADIOLOGICAL ENVIRONHENTAL HONITOPING PROGRAH H"

• IIEDIA l,

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 1 Offs'ite In Season 2 Onsite 1 Offsite H Compi Qtr Comp.

3(2)

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 Hile point Unit 1

intake

water, James Ao Fitzpatrick intake water, and Oswego City raw water.

TABLE 2 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTALlMONITORING PROGRAM B,

TERRESTRIAL PROGRAM MEDIA l.

Air Particulates 2 ~

Soil 3 ~

TLD 4.

Radiation Monitors'

~

Airborne I-131 6.

Milk 7 ~

Human Food Crops 8 ~

Meat, Poultry, Eggs

'NALYSIS GB GSA-GSA, Sr-90 Gamma Dose Gamma Dose 1-33 1 GSA, Sr-90 GSA, I-131 GSA Edible Portions FREQUENCY M

M Comp (4)

Every 3 years Qtro M

SA NO ~ OF LOCATIONS At least 10 13 20 At least 7

At least 10 4 (5)

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

~

81

TABLE 3 CONCENTRATIONS OF GAMMA EMITTERS IN CLADOPHORA SAMPLES - 1983 Results in units of pCi/g (wet) + 2 sigma Collection Site Nuclides Found June 1983 Au ust 1983 Nine Mile Point J. A. FitzPatrick Be-7 X-40 Mn-54

. Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru-103 Cs-134 Cs-137 Ce-141 Ce-144 Ra-226 Th-228 Others Be-7 Z-40 Mn-54 Co-58 Fe-59 Co-60 Z n-65 Zr-95 Ru-103 Cs-134 Cs-13 3 Ce-141 Ce<<144 Ra-226 Th-228 Others 0.57+0.14 6 07+0 ~ 61 Oi02+0 01

<0 02

<0.04 0.09+0 01

<0 ~ 03

<0 ~ 02

<0 02

<0 01 0.06+0 01

<0.04

<0.09

<0 ~ 2 0 ~ 05+0 01

<LLD 0.67+0.07 3.52+0.35

0. 0 Q'+0. 005

<0.01

<0 ~ 02 0.08+0.01

<0 ~ 01

<0 ~ 01

<0.01

<0.01 0.04+0 01

<0 ~ 02

<0.04

<0 ~ 1

<0 ~ 01

<LLD 0.65+0.0 7 2e08+0 21 0 02+0,01

<0 ~ 01

<0 ~ 02 0.09+0,01

<0 ~ 01

<0 ~Gl

<0 01

<0.01 0.04+0.0 1

<0 ~ 02

<0.04

<0 ~ 10 0.02+0 ~ 01 0.58+0 F 11 2.98+0.30 0.04+0.01

<0.01

<0.03 0.11+0.0 1

<0 ~ 02

<0.01

<0.01

<0 ~ 01 0.031+0.004

<0.03

<0 06

<0.14

<0 01

<LLD 82

TABLE 3 (cont.)

CONCENTRATIONS OF GAt&iA EfITTERS IN CLADOPHORA SAMPLES 1983

'esults in units of pCi/g (wet) + 2 sigma Go lection Site Nuc es Foun June 1

August 1 Oswego Be-7 X-40

><n-54 Co-58 Fe-59 Co-60 Zn-65 Zr-95 Ru-103 Cs-134 Cs-137 Ce-141 Ce-144 Ra-226 Th-228 Others 0 52+0 ~ 16 6.00+0.60

<0 ~ 01

<0 ~ 02

<0.05

<0.01

<0.03

<0.02

<0.03

<0.01 0.03+0.01

<0 ~ 06

<0 ~ 1

<0.3

<0.03

< LLD 0.37+0 '9

3. 12+0 +31

<0 ~ 01

<0 F 01

<0.03

<0 ~ 01

<0,02

<0 ~ 01

<0,0 1

<0 ~ 01

<0.01

<0 ~ 02

<0.04

<0 ~ 11

<0,01

<LLD 83

TABLE 4 CONCENTRATIONS OF Sr-90 AND GA191A ENITTERS IN SHORELINE SEDIMENT SANPLES Results in units of pCi/g (dry) + 2 sigma Sample Location Collection Date Sr-90 Be-7 K-40 Co-60 Cs-134 Cs-137 Ra-226 Th-228 Others NINE NILE.

3/10/83*

(2)

<0 ~ 35 POINT 5/20/83

<0'02

<0'5 15,2+1.5

0. 1440.02

< 0.02 0 ~ 85+0. 08 1.0240.27 0 55<0.06

< LLD 9 ~ 7+1.0

<0.07

<0.03 0.16+0.04 0 ~ 21<0 06 0.31+0.09(1)

<LLD ll/22/83 0 02240.002

<0,68 13.0+1.3 0.36+0 05 0.0940.04 1.81+0 18

<0.92 0'840 '5

<LLD LANGS BEACH 3/10/83*

<0 008

<0.40 12.0+1.2

<0.06 CONTROL 5/20/83

<0@001

<0 ~ 50 15 ~ 3+1 5

<0 1l/22/83

<0'02

<0'9

.14.1+1.4

<0.05

<0 ~ 02

<0 02

<0.06

<0'5 1.21+0 32 0 ~ 62+0 06

<LLD 1 ~ 21+0 69 0'040 06

<LLD

<0.05

<0.05 0.3310,08 0.31+0. 10(l)

<LLD

• Not Environmental Technical Specification samples.

Extra samples for evaluation purposes.

(2)

Result for Th-232 Sample lost during laboratory analysis.

84

TABLE 5A CONCENTRATIONS OF STRONTIUM-89 4 90 AND CAHHA EHITTERS IN FISH SAMPLES Results in Units of pCI/8 (vet) + 2 sIRua Sau le Date Sam le T e

Sr-89 Sr-90 K-40 CAHHA EHITTERS Hn-54 Co-58 FITZPATRICK Fe-59 Co-60 En&5 Cs-134 Cs-137 Others Hay 1983 Brovn Trout La'ke Trout ll Lake Trout l2 October 1983 Bravo Trout Lake Trout ll Lake Trout l2

<0 084

<0.033

<0.095

<0 002

<0.003

<0.002

<0.003

<0.002

<0.003.

<0,001

<0,001

<0 001 3 ~ It0~3

.3. It0.3 3.8t0.4 3.7t0.4 3.2t0,3 2.7t0.3

<0.017

<O.OI6

<0.022

<0.005

<0.006

<0.007

<0.027

<0 027

<0.034

<0.007

<0.007

<0.008

<0.092

<0.084

<0.100

<0.018

<0.022 c0.020

<0.020

<0.019

<0.030

<0+005

<0.007

<0+008 c0.049

<0.045

<0.050

<0~013

<0.015

<0.014

<0,015

<0~013

<0.018

<0 F005

<0.006 c0.007 0.042tO.0L3

<LLD 0 038t0 015

<LLD 0.05 lt0.014 0.050t0.006 cLLD 0.055t0.007

<LLD 0.039t0.008

<LLD NINE MILE POINT May 1983 Brovn Trout Lake Trout ll Lake Trout l2 October 1983 Brovn Trout

~ Lake Trout ll Lake Trout l2

<0.099

<0.052

<0,066 a

<0.002

<0,001

<0.003

<0.002

<0.003

<0.001

<0,001 3.2t0.3 3.3t0.3 2o9tO ~ 3 3.9t0.4 3.0tO 3

3.3t0.3

<0.020

<0 018

<0.014

<0 006

<0 006

<0,009

<0.035

<0 030

<0.024

<0'07

<0,006

<0.010

<0, 100

<0.089

<0.083

<0.019

<0,016

<0.025

<0.019

<0.025

<0.018

<0 006

<0,006

<0.009

<0 047

<0.041

<0,042

<0 014

<0.015

<0.022

<0.019

<0~015

<0.013

<0,005

<0 006

<0 010 0+046t0,015

<LLD 0 056t0 011 cLLD 0 033t0.010

<LLD 0 04ltO 006

<LLD 0+03 8t0.007

<LLD 0.047+0.009

<LLD OSNECO (CONTROL)

Hsy 1983 Brovn Trout

<0.027

<Oi001

3. lt0.3 Lake Trout ll

<Oi031

<0 002 3 Ot0.3 Lake Trout l2

<0.033

<0.002 3.0t0.3

<0.016

<0.018

<0.013

<0 026

<0.029

<0.019

<0.083 c0.073

<0.060

<0.021

<0 016

<0,016

<0.040

<0,044

<0,035

<0 014

<0+016

<0,012 0 046tO 010 0 057+0.015 0.049t0.010 c LLD c LLD

<LLD October 1983 Brovn Trout Lake Trout ll L'ake Trout l2

<0 006

<0.004

<0.004

<0.002 3.8t0.4

<0.002 2.8t0,3

<0 002 3 Ito.3

<0,007

<0.007

<0,008

<0.009

<0,008

<0 010

<0,025

<0.023

<0.029

<0'07

<0,007

<0 008 cO 017

<0 007

<0.017 '0.007

<0~020

<0,009 0.057t0.007

<LLD 0.041t0 006

<LLD 0 044t0,008

<LLD aSasple lost durinB analysis~

Sr-89 results are corrected for decay to sauple stop datei

~

85

TABLE 5B CONCENTRATIONS OF STRONTIUM-89 & 90 AND GEM/A EHITTERS IN FISfl SAMPLES Results in Units of pCi/kg (dry) + 2 sigma Sam le Date Sam le T e

Sr-89*

Sr-90 K-40 Gi&SA EHI1TERS Mn-54 Co-60 Cs-134 ~ Cs-137 Others OSWEGO (CONTROL) 00 Hay 1983 Brown Trout Lake Trout Pl Lake Trout d2

<79.6

<85,6

<92 ~ 1

<3'

<4.7

<5' 9,145+914 8,2804828 8,3704S37

<47.2

<49.7

<36.3

<62.0

<44.2

<44

<41.3

<44o2

<33.5 135 ~ 7+29.5

<LLD 157 3+41,4

<LLD 136.7+27 9

<LLD-October 1983 Brown Trout Lake Trout dl Lake'Trout P2

<ls 2

<11 4

< 12,9

<5.4

<5'

<702 12,096+1,216

<22' 8,490+840

<19.5 9,180+930

<24.3 NINE HILE POINT 02

<21.1

<19 ~ 8

<23 ~ 7

<23.0

<20 ~ 1

<26 4 182.4+22.4

<LLD 122.1+18.6

<LLD 133 e 2+23 4

<LLD May 1983 Brown Trout Lake Trout 81 Lake Trout d2

<273.2

<158.1

<225 '

<7.4

<6 4

<9.'9 8,8324883

<55.2 10,032+1,003

<54.7 9,918t992

<47.9

<52.4

<76 ~ 0

<61 ~ 6

<52.4

<45.6

<44.5 127.0+41.4

<LLD 170-2+33.4

<LLD 112.9+34.2

<LLD October 1983 Brown Trout Lake Trout dl Lake Trout 82

<6,0

<0,5

<2 4

<2o2 12,576+1,248

<17.9 9,03(H900

<16.8 9,7804990

<26.7 J

AD FITZPATRICK 03

<18 ~ 2

~

<}8.0

<28 ~ 2

<17.3

<18.0

<29.7 130.6+18.2

<LLD 112.8&21.3

<LLD 141.6+26 7

<LLD May 1983 Brown Trout Lake Trout Pl Lake Trout 02

<252.8

<91.4

<261 ~ 2

<8 4

<4 ~ 7

<6' 9,331+933 8 >5877859 10,450+1,045

<5 1.2

<44.3

<60.5

<60.2

<52 ~ 6

<82.5

<45.2

<36.0

<49.5 126.4+39. 1

<LLD 105.3+41.6

<LLD 140 i2+38 o5

<LLD October 1983 Brown Trout Lake Trout 01 Lake Trout 82

<6.1

<8 ~ 1

<6 ~ 6

<2 ~ 2

<3 ~ 6

<2+3 11,680+1,184 9,6308960 7,9504810

< 16.0

<18. 3

<19.8

<16 ~ 6

<19,8

<23 ~ 7

<16.6

<19.2

<21.6 160,0+18 0

<LLD 165 &f21.6

<LLD 117.3+24.9

<LLD Sr-89 results are corrected for decay to sample stop date.

• Sample lost during analysis for Strontium 89 and Strontium 90.

86

TABLE 6 CONCENTRATIONS OF BETA EMITTERS IN LAKE WATER SAMPLES 1983 Results in Units of pCi/1 + 2 sigma Station code 'anuary February March

. April Hay June JAF Inlet 0 ~6&.5 NMP, Inlet 0.6<0.5 Raw City 0.8+0 '

Water (control),

1.8<0.6 2.540.7

2. 1+0.6 2.6+0.7 2.5+0.6 1.8<0.6 2 ~ 7+0 6

0;6+0.4 1.5+0.5 2.940 7

2.9+0 '

2'40 '

3 ~ 1+1.3 7.9+1.7 2.3+1.2 Station code July August Septem er Octo er Novem er Decem er JAF Inlet 2.2+1,2 NHP Inlet 3.5+1 3 Raw City 2.4+1.2 Water (control) 3.2+0.5 2i9+1.2 2'+1.2 4.2+1.9 3.0+1.8 3.5+1.8

<2.6

<2 ~ 6 2.7+1.8 3 3+1.8 3.3+1.9 3.5+1 7

<2 0 F 1+1.8

<2' 87

TABLE 7 CONCENTRATIONS OP TRITIVH AND STRONTIVH-89 AND STRONTIVH-90 IN LAKE WATER (QUARTERLY COHPOSITE SAHPLES)

Results in Units of pCi/1 + 2 sigma STATION CODE JAF INLET NHP INLET RAW CITY WATER

( CONTROL)

PERIOD First Quarter Second Quarter Third Quarter Fourth Quarter First Quarter Second Quarter Third Quarter Fourth Quarter Pirs t Quarter Second Quarter Third Quarter Fourth Quarter D T 1

3/31/83 6/30/83 6/30/83 9/30/83 9/30/83 1/4/84 12/30/82-3/31/83 3/31/83 - 6/30/83 6/30/83 9/30/83 9/30/83 12/28/83 12/30/82-3/31/83 3/31/83 6/30/83 6/30/83 9/30/83 9/30/83 12/28/83 TRITI H

+

260 + 140 560 + 80 320 + 70 260 + 130 410+ 140 290 + 90 190 + 90 239 + 130 230 + 140 280 + 70 250 + 80 SR-

<2.0

<2.0

<1 4

<1 1

<2.0

<1.0

<1 6

<0.8

<2 ~ 0

<2.0

<1.4 o +

o 1,0+0,5 0.6+0,3 0.6+0 ~ 3 1.0+0,4 0.7+0.4

<0,7 1 1+0+4 1,0+0 3

<0.9 0.9 + Oe4 0 8+ 0 4 88

s TABLE 8 CONCENTRATIONS OF GAffMA EMITTERS IN LAKE WATER SAMPLES 1983 Results in Units of pCi/1 + 2 sigma Station Code Nuclide January February March April May June OSWEGO CITY WATER (00; CONTROL)

NINE MILE POINT (02, INLET)

FITZPATRICK (03, INLET)

Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 K-40 Ce-144 CG-134 Cs-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 K-40 Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 K-40

<5 ~ 46

<0.97

<1.,18

<3.03

<1.97

<1 ~ 30 (1.01

<2~52 (1.58

( 13,3

<5.15

< 1.10

<1.23

<3 ~ 18

<1.94

<1 ~ 29

<1.35

<2 ~ 43

<1.64

<16 ~ 4

<5.39

< 1.05

<1. 11

<2.93

<1.68

< 1.02

<1.22

<1 ~ 74

<1. 25

<18.2

<5 ~ 33

<0.99

<1 ~ 10

<3 ~ 21

<2.03

<1.54

<1 ~ 22

<1 ~ 98

<1.52

<17 ~ 1

<5 15

<0.90

<1.10

<3'4.

<1.91

<1 ~ 75

<1.19 (2'5

<1.48

<15.0

<5'5

<1.17

<1.28

<3 ~ 36

<2'6

<1 36

<1.09

<2 ~ 32

<1.29

< 14.5

<5.40

, <1.15

<1.45

<4.03

<1.97

< 1.72

<1.30

<2 ~ 32

<1,75

< 15.5

+6.02

<1 05

<1,27

<4. 15

<2o23

< 1.62

<1,23

<2 ~ 21

<1,67 (14.0

<5.47

<1 ~ 18

<1.34 (3.34

<2.00

<1.35

<1. 12

<2.00

<1.46

<13 ~ 5

<4.93

<0.97 (1.15

<3.30

<1.90

< 1.33

<l. 11

<2 ~ 39

<1.45 (11.7

<5.88

<1.07 (1.22

<3.51

<1.83 (1.42

<1,26

<1 ~ 93 (1 ~ 39 16.5+8.7

<5.12 (1.01

<1 ~ 12 (3'3

<1.27

<1 19

<1.09

<2.49

<1.08

<12 ~ 3

<5.08

<0. 85

<0 ~90

<3 ~ 18

<2.05

<1.46

<1.07

<1.56

<1.02

<12.9

<4.73

<0.94

<0,96

<3,24

<2+37

<1.43

<1,16

<1 ~ 86

<1 ~ 14

<12,6

'5.39

<1.03

<1,08

<2.86

<F 11

<1.33 (1 01

< 1' 86

<1.33

<11.3

<5.40

<0'9 (0,94 (4.54

<3o35

<1 ~ 68 (0.88

<1 ~ 51

<1.09 13.2+7 '

<5 36

<1 ~ 06

<1.10

<4.34

<4.27

<1 ~ 80

<1,26 (2 ~ 32 (1,32 6 ~ 7+6 2

<5.03

<0.90

<0,88

<2.94

<1.98

<1.38

<1.23

<1 ~ 75

<1, 14

<15 ~ 8

TABLE 8 (Cont'd)

CONCENTRATIONS OF GA10fA FJ(ITTERS IN LAKE WATFR SAMPLES 1983 Results in Units of pCi/1 + 2 sigma Station Code Nuclide July August September October November December OSWEGO CITY WATER (00, CONTROL)

NINE MILE POINT (02, INLET)

FITZPATRICK (03, INLET)

Ce-144 Cs-134 CB-137 Zr-95 Nb-95 Co-58 Hn-54 Fe-59 Co-60 K-40 Ce-144 Cs-134 Cs-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 K-40 Ce-144 Cs-134 C5-137 Zr-95 Nb-95 Co-58 Mn-54 Fe-59 Co-60 K-40

<5 ~ 66

< 1.05

<1. 11

<3 08

<1.75

< 1.40

<1.03

<1 ~ 74

<1.20

< 14.0

<4.50

<0.95

<1 14

<3.09

<1.65

<1.18

<F 18

<1.95

<1.56

< 12.9

<4.79

<0 ~ 86

<1 01"

<2 ~ 88

<1.83

<1 ~ 30

<1.06

<2.03

<1 05

<10 ~ 7

<4.79

<0 ~ 88

<1.32

<2.97

<1.51

<1.17

<1.03

<1.90

<.1.52

<10.7

<5.79

<1. 11

<1.06

<4'2

<2.47

< 1.81

<1, 10

<2 ~ 27

<1 ~ 32

<11.7

<5,56

<l. 18

<1.22

<4. 11

, <2.59

<2 04

<1.40

<2 ~ 51

<1.52

<17.9

<5 ~ 22

< 1.09

<1.08

<3.80

<1.79

<1.34

<1.02

<2 ~ 11

<1. 16

<16.0

<.5.41

<0.94

<1.03

<3.70

<1.67

<1 ~ 44

<1.18

<I ~ 99

< 1.42 13.6+7.8

<4.77

<1 ~ 06

<1.03

<3 ~ 96

<2'0

<1 ~ 52

<1.20

<1.73

<1.28

<14.6

<4.39

<0.84

<0.88

<3. ~ 28

<1.53

<1.49

<0 ~ 99

<2 ~ 16

<1.12

<10.9

<6.55

<1.43

<1.32

<5.05

<3.63

<2 ~ 35

<1.47

<3.03

<1.26

<21.2

<6.70

<1.40

<1 36

<4.73

<3+33

<1 89

<1,30

<2 ~ 87

<1.57

<14.4

<6.34 cl,53

<1.62

<4'1

<2.47

<1 88

<1,72

<F 11

<1.95

<20 '

<5.99

<1,08

<1.30

<3 82

<2023

<1 ~ 70

<1.31

<2'1

<1,76

< 18.8

<6,08

<> ~ 16

<1,22

<3 ~ 36

<1,99

<1.54

<1.38

<3.09

<2.00

<20.4

<5 ~ 65

<0'4

<1.08

<2.96

<2'3

<1.15

<1 15

<2'2

<1.27

<13.6

<5 18

<0.95

<0.96

<3 51

<1.7,1

<1.45

<0,93

<2 ~ 40

<1 02

<12.8

<5.37

<1 10

<1.00

<2 ~ 70

<2,02

<1 ~ 16

<1 09

<1.72

<1,20 9 ~ 646.4 90

)EEK Etio f DATE 83/01/11 83/01/19 83/01/25 83/02/01 83/02/08 83/02/15 83/02/23 83/03/01 83/03/08 83/03/15 83/03/22 83/03/29 83/04/05 83/04/12

&3/04/19 83/04/26 83/05/03 83/05/11 83/05/17 83/05/24 83/06/01 83/06/07 83/06/14

- 83/06/21 83/06/28 83/07/06 83/0//12 83/07/22 83/07/27 83/08/02 83/08/9 83/08/16 83/08/23 83/08/31 83/09/7 83/09/13 83/09/20 83/09/27 83/10/4 83/10/13 83/10/18 83/10/25 83/11/1 83/11/08 83/11/15 83/11/22 83/11/2'9 83/12/6 83/12/13 83/12/20 83/12/28 84/01/4 C

OFF 0.022+0.003 0.019+0.003 0.0280.004 0.028+0.504 0.015T0.003 0.025+0.004 o.o4o+o.oo4 0.024+0.004 0.022T0.004 0.014+0.003 O.ojsto.003 0..028+0.004 0.02370.004 0.007Y0.002 0.012+0.003 0.01070.003 0.026%0.004 O.01&~0.003 0.014T0.003 0.519+0.003 0.01270.002 0.014+0.003 0.033+0.004 0.039+0.004 0.025T0.003 0.019+0.002 0.518+0.003 0.036'0.004 0.025V0.003 0.028T0.004 O.oh5+0.003 0.519+0.003 0.037X0.004 0.041+5.004 0.04170.004'.030+0.004 0.028T0.003 0.025+0.003 0.036+0.054 0.022t0.003 0.013+0.003 0.022+0.003 0.017+0.003 0.018+0.003 0.033V0.004 0.019+0.001 0.01870.003 0.021+D.003 0.026t0.003 0 02PO 001 0.029~0.001 0.032+0.502 D 1-OFF 0.022+0.054 5.521+0.553 0.021~0.004 0.021+0.003 0.01670.003 O.O24+O.OO4 0.040+0.004 O.O22+O.OO4 0.01970.003 0.016t0.003 0.017+0.003 0.021+0.003 0.022T0.004 0.010'f0.003 0.015+0.003 0.009t0.003 0.020T0.003 0.01970.003 0.013+0.003 0.018+0.003 0.010+0.002 0.012+0.003 0.033+0.004 0.033+0.003 0.023T0.003 0.020+0.003 O.'025+O.OO4 0.034+5.004 O.dPST0.004 0

52870 004 0.023+0.003 0.517+0.003 5.03570.054 O.C31+0.004 0.042+0.005 0.534+0.004 0.02470.503 5.032+0.004 0.033+0.054 0.021+0.003 0.014+0.053 0.019+0.003 0:017+0.003 0.017+0.003 0.031+0.004 0.521+0.001 0.02370.003 0.022+0.003 0.02570.003 0.023@.051 5.031+0,001 0.033+0.052 D2-OFF 0 522to 553 0.0'~to 553 0.025+0.003 0.026+0.004 0.019V0.003 O.O27+O.OO4 0.041+0.D04 0.025+0.004 0.020~0.003 0.019+0.003 0.016+0.003'.026+0.004 0.02570.003 0.007~0.002 0.015+0.003 0.510+0.003 0.019~0.003 0.018~0.003 0.013+0.003 0.019+0.003 0!01170.002 0.014+0.003 0.031+0.003 0.032+0.003 0.025V0.003

" '0.021+0.003 0.022+0.003 0.032T0.004 0.028V0.003 0.022%0.003 0.025+0.003 0.017+0.053 0.037T0.004 0.037+0.003 0.039+0.004 0.030+0.504 0.02CT0.003 0.0"9+0.003 0.037+0.004 0.022~0.003 0.021+0.004 0.0"1+0.003 0.019+0.003 0.016+0.003 0.03350.004 0.019+0.001 0.022+0.003 0.020+0.003 0.028T0.003 0.023~0.001 0.033+0.002 0.034+5.002 91 EOFF 5.024+0.054

'0.020+0.053 0.017T'0.503 0.025t0.004 0.01870.003 0.02S+0.004 0.035+0.054 0.021+0.004 0

02~TO 004 0.018+0.003 0.014+0.003 0.02St0.004 0.02jsv0.003 0.0jiX0.003 0.013+0.003 0.011+0.003 0.02170.004 0.024+0.004 0.015T0.003 0.020+0.004 0.013T0.002 0.011+0.003 0.030+0.004 0.034+0.004 0.026T0.003 0.020+0.003 0.025+0.004 0.030+0.004 0.030F0.003 0.026T0.004 0.024+0.003 0.020+0.003 0.032T0.004 0.045+0.004 0.04350.004 0.029+0.004 0.02670.003 0.029+0.003 0.040+0.004 0.022+0.003 0.023+0.004 0.017t0.003 0.020+0.003 0.020+0.003 0.032~0.004 0.021+0.001 0.521+0.003 0.01970.003 0.028T0.003 0.022TO.001 O.O32+O.OO2 0.036+5.002 FBI,E 9

fJAc' I fE Etl'JIROrltfEtlTAL AIRBORtlE f'ARTICULATE SAMPLES - 0"f S!TE STATIONS GROSS SETA ACTIVITY pCi/n"3 i 2 Signa LOGATIOtl F

OFF 0.019+0.003 0.018+0.503 0.018+0.053 0.024+0.004 0.0i7%0.003 0.02St0.004 0.040+0.004 0.026+0.054 0.023~0.004 0.017+0.003 O.oiito.003 0.024+0.053 0.021F0.003 0.010T0.052 0.011+0.003 0.013+0.003 0.02170.003 0.025t0.003 0.018+0.003 0.016+0.003 0.010F0.002 0.015t0.003 0.032+0.003 0.034+0.003 0 025'0.003 0.018+0.003 0.033+0.004

~ 0.030+0.004 0.030V0.003 0.027t0.054 0 024+0 D03 0.024+0.053 0.035~0.054 0.038t0.003 0.04STO.D54 0.027+0.004 0.026VO.Q03 0.026+0.003 0.036+0.004 0.023+0.003 0..021t0.004 0.021+0.003 0.021+0.553 0.018+0.003 0.03170.004 0 022+0.001 0.024+0 003 0.019+5.053 0.02H0.003 0.026>5.001 0.031+5.052 5.034+0.052 GOFF 5 024+0 004 0.019+0.003 5.02170.004 5.023t0.004 0.020V0.003 5.025+0.004 0.0407t0.004 0.022+0.004 0

0~1TO 003 5.019+0.003 D.014+0.003 0.023+0.053 0.02B'0.003 0.011V0.003 0.013+0.003

.=

O.O12+O.003 0.018'F0.003 0.019~0.003 0.011+0.003 0.019~0.003 0 012to 002 0.512t0.003 O.D30+0.003 0.056+0.013 0.040VO.OOS 0.022+0.003 0.021+0.003 0.0226.003 0.027V0.003 0.024T0.003 0.026+0.003 0.018+0.003 0.034@.004 O.Q35+0.003 5.044>0.004 0.010+0.003 5.020+0.003 0.032+0.004 0.031+0.004 0.529+0.004 0.01670.004 5.516+0.003 0.020+0.003 Q.522+0.003 0.038T'0.004 Q.O24+O.OO1 0.524+0.003 0.018+0.503 0.02570.003 5.523+0.001 5.030+0.002 9.585+0.002

a

~

I Jl I

Tt'"'0 SIT'.

EtlVIROtttiEttTAL AIRSORtth PART1CULATE SAttt LES Otl SITE STATIOt6 GROSS BETA ACTIVITY pCi,'n"3 t 2 Slgtla LOCATION K

END ATE DI-Otl D2-Otl E

ON F

ON G

ON I0'l J

ON K--ON 83/P 2/1 ')

~/19

'l/57 1/3 83)aj/jo 83)oj/17 83/01/24 83)01/31 83l02/07 83JD:/14 83/02/22 83)02/28 83/03/07 83/03/14,

. 83/03/21 83/03/28 83)04/04 83/04/11 83/04/18 83/04/25 83/05/02 83)05/09 83)05/16

'3/05/23 83/05/31 83/06/06 83/06/13 83/06/20 83/06/27 83807/05 83/07/jj 83j:07/18 83/07/26 83/08/01 83/08/8 83)0&/15 8330&/22 83/0&/29 83/j09/6.

83/09/12 83/09/19 83/.09/26 83/10/3 83jia/jj 83)40/17 83 0/24 83 ~io/31 83/'11/07 83

'1/14 83.11/21 83/jj/28 83/ 2/S 0.022+0.003 0.015+0.003 0.021+0.003 0.021+0.003 0.017+0.003 0.020V0.003 0.031+0.003 0.024+0 004 0.024+0.003 0.014%0.003 0.015+0.003 0.023+0.004 0.025+0.004 0.01570.003 0.010+0.003 0.01570.003 0.02070.003 0.019+0.003 0.01370.003 0.024+0.004 0.014+0.002 0.01470.003 0.025+0.003 0.039+0.004 0.027+0.003 0.02070.003 0.01&+0.003 0.025+0.004 0.026+0.003 0.029T0.004 0.026+0.003 0.015+0.003 0.03470.DD4 0.03H0.003 0.045+0.004 0.03D+0.004 0.02170.003 0.026T0.003 0.036+0.004 0.027+0.003 0.017+0.003 0.02370.003 0.020+0.003 D.oibto.003 O.D31+0.004 0.027+0.001 0.024+0.003 D.aj&g.003 0.027+0.003 D.016~0.ooj 0.02&to.aai 0.05jto.a03 0.027+0.004 0.01670.003 0.027+0.007 0 024+0.004 0.01'9+0.004 0.02&70.OOS 0.039+0.005 0.02370.005 0.026+0.005 0.014%0.003 0.021+0.004 0 027+0.004 0 023+0 004 0.012~0.003 0.013+0.004 D.oj&FO.004 0.01970.004 0.016+0.004 0.016+0.004 0 022+0.004 D.oj&'0.003 0.01670.004 0.02S+0.004 0.04&+0.006 0.025+0.004 0.022V0.003 0.021+0.004 0.02&+0.005 0.027+0.004 0.03270.005 0.029+0.004 0.017F0.003 0.040+0.OGS 0.03070.004 0 05 70 005 a.o34+o.'oas 0.02470.004 0.026TO. 004 0.041+0.D05 0.033+0.004 0.017t0.004 0.02970.004 0.01&+0.004 0.01&+0.004 0.041+0.005 0.027VO.002 0.02370.004 0.0:j+0.004 0.030+0.004 0

02~TO 00~

0 046+0 00~

0 043+0.002

0. 021+0. 004 D.oj&70.003 0.023+0.004 0.025+0.004 0

020+0 004 0.023T0.004 0.041+0.005 0.029~0.005 0.0~3+0.004 0.014V0.003 0.01&+0.004 0.029+0.004 0.020+0.004 0.011%0.003 0.014V0.003 0.01370.003 0.02170.004 0.018+0.003 0.01570.004 0.022+0.004 0.015'0.002 0.01H0.003 0.026+0.003 0.045+0.005 0.025+0.004 0.02Ã0.003 D.020+0.003 0.029T0.004 0.025+0.003 0.02&TO.004 0.0~6+0.003 0.021~0.003 0.031+0.004 0.03370.004 0.05170.004 0.030+0.004 0.023~0.004 0.023T0.004 0.035+0.004 0.02&+0.003 0.015+0.003 0.022%0.004 0.019+0.003 0.019+0.003 0.034+0.004 0.03770.002 0.02770.004 0.022+0.003 0.031+0.004 0.002Ta.ooj 0.033+0.002 0

045+0 00~

0.021+0.004 0 021T0.004 0.024to.ooS 0.024+0.005 0 O~~to OOS 0

O~ovo 005 0.044+0.006

" 0.02&70.006 0.024+0.005 0.013T0.004 0.015+0.005 0.032+0.OOS 0.026+0.005 0.00&TO.003 0.015+0.004 0.015T0.004 0.01'P0.004 0.014+0.ool 0.012V0.003 0.016+0.004 0.014+0.OD3 0.015T0.003 0.02&to.004 0.037+0.004 0

0~5+0 004 0.019TO.OOS 0.022+0.003 0.031V0.004 0.02&+0.003 0.029~0.004 0.026+0.003 0.021+0.003 0.031+0.003 0.03770.003 0.051T0.004 0.02&+0.003 0. 02&0

. 003 0.02670.003 0.03&to.004 0.030+0.003 0.021+0.D04 0.023V0.003 0,.019+0.003 0.015T0.003 0.030+0.004 0.035+0.002 0.023T0.003 0.01&TO.003 0.032+0.004 0.01970.001 0.027+0.001 0.026+0.001 0.024+0.OOS 0.01770.004

- 0.023+0.005 0.023+0.005 0.018+0.'004 0.022wo.005 0.040+0.004 0.02070.004 0.024+0.004 0.013V0.003 0.015+0.003 0.027+0.004 0

0~2+0 004 0.011+0.003 0.015+0.004 0.012+0.003 0.019+0.004 0.017+0.004 0

01~~0 004 0.023+0.OOS D.ojj+0.003 0.013T0.003 0.028+0.004 0.029+0.004 0.021+0.004 0.02270; 003 0.024+0.004 0.032TO.OOS 0.023+0.003 0.02470.004 0.01&+0.003 0.01870.003 0.032+0.004 0.033RD.004 0.042+0.004 O.O26+O.OO4 0.01770.003 0.0266.004 0.035+0.004 0.027+0.003 0.015+0.003 0.023T0.003 0.022+0.003 0.016+0.003 0.035+0.004 0.031t0.002 0.029T0.004 0.01970.003 0.020+0.003 0 OVID 00~

0.014+0.001 o.'o46+a.oo2 0

020+0 003 0.01670.003 0

021+0 004 0.027+0.004 o'.o."6+a.oo4 0.021+0.004 0.027+0.003 0.021T0.004 0

022+0 004 0.01370.003 0.017+0.003 0.02S+0.004 0.020+0.003 0.015T0.003 0.010+0.003 0.01H0.003 0.023i0.004 0.02ST0.004

0. Ojjio. 003 0.023+0.004 0.016+0.003 0.01970.003 0.027+0.003 0.033+0.004 0.023+0.003 0.022t0.003 0.018+0.003 0.03070.004 0.025+0.003 0.029@.004 0.026+0.003 0.01570.003 0.033+0.004 0.017+0.003 0.050T0.004 0.030+0.D04 0.022~0.003 0.020+0.003 0.035+0.004 0.014+0.003 0.017+0.003 0.020f0.003 0.01&+0.003 0.01&+0.003 0.024+0.004 0

0~0+0 001 0.02170.003 0.024~0.006 0.026+0.004 0.029T0.002 0.030+0.002 0.044+0.002 0.023t0.003 0.01&70.003 0.021+0.003 0.023+0.003 0.016+0.003 0.019V0.003 0.02&+0.003 0.02170.004

0. 017+0. D03 0.014V0.003 o.o14+D.oa3 0.024+0.003 0.020+0.003 0.007@.002 0.014+0.003 0.014+0.003 0.02070.003 0.016+0.003 0.012V0.003 0.019+0.003 0.013+0.002 0.014VO;003 0.025+0.003 0.014+0.002 0

023+0 003 0.016+0.002 0.01&70.003 0.015T0.003 0.034+0.005 0.00&ID.002 0.027+0.003 0.01/+0.003 0.024+0.003 0.025+0.003 0.05470.004 0.030+0.004 0.020%0.003 0.027+0.003 0.035+0.004 O.D22+0.003 0.015+0.003 0.01370.002 0

0~1+0 004 0.017+0.003 0

027+0 004 0.021+0.001 0.01570.002 0.020+0.003 0.029+0.004 0.01&TO.001 0.043+0.002 0.03&to 002 0.023+0.003 0.021W0.003 0.01&+0.003 0.026+0.OOS 0.016+0.003 0.023+0.003 0.024+0.003 0.018~0.004 0.024+0.OD4 0.01370.003 0.014+0.003 0.027+0.003 0.026+0.003 0.007T0.002 0.025+0.009 0.01+0.003 0.016+0.004 0.016+0.003 0.01370.003 0.017+0.003 o.a12+o.oo2 0.01370.002 0.021+0.003 0.053+0.005 O.D19+0.004 0.020~0.004 0.01570.003 0.023T0.004 0

022+0 003 0.030~0.003 0.02S+0.003 0.018+0.003 0.030+0.003 0.031+0.003 0.045+0.004 0.027+0.D04 0.02170 003 D.03070.003 0.031+0.022 0.029+0.003 0.013+0.003 0.023~0.003 0.019+0.003 0.013@.002 0.034+0.004 0.032+0.002 0

0~470 003 O.ai&70.003 0

027+0 004 0.019%0.001 0.030+0.Do~i 0

043+0 002 0.022+0.DO3 0.013@.003 0.021ta.003 0.017+0.003 0.018+0.003 0.021~0.004 D.ass+0'.007 0.022T0.004 0.024+0.005 0.01370.003 0.011+0.003 0.026+0.004 0.021+0.003 0.00970.002 0.011+0.003 0.014V0.003 0.018+0.003 0.014+0.003 0.012~0.003 O.O18+O.OO3 0.010+0.002 0.011~0.002.

0 022+0 003 0.028+0.003 0

0~0+0 003 0.01570.002 0.01770.003 0

027TO 004 0.022+0.003 0.022V0.003 0.028+0.003 0.018+0.003 0.031+0.003 0.013~0.002 0.04270.003 0.022+0.003 0.01&@.003 0.021~0.003 D.034+0.003 0.022+0.003 0.016+0.003 0.022%0.003 0.015+0.003 0.014t0.002 0.032+0.004 0.021+0.001 0.027V0.003 0.017>0.003 0.023+0.003 0.020+0.002 0.031+0.002 a 033ta 002

1

TABLE 11 CONCENTRATIONS OF GAMBIA EMITTERS IN MONTNLY COMPOSITES OF NlfP AIR PARTICULATE SAMPLES 1983 Results ln units of 10 pC1/m

+ 2 sigma Nuclides Januar Februar March Apr(1 May OFF-SITE COMPOSITE-A-1 June 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

<0.38

<0.29

<0'6

~ <0.34

<0.47

<0. 79

<0.44

< 1.22

<2.49

<0.36 73.5+4 9

<4.52

<1 26

<4.80

<0.50

<0'6

<0.32

<0'6

<0.45

<0.93

<0.46

< 1.35

<2 ~ 94

<0.44 122.0+6.6

<5. 15

<1 28

<5 +35

<0.31

<0'4

<0.22 0,18 + 0.12

<0'2

<0'4

<0.35

<l. 10

<2.07

<0. 30 109.0+5,2

<3.57+3.46

<0'8

<4.29

<0.42

<0.32

<0 ~ 23

<0.30

<0.34

<0.79

<0.38

<1.10

<2 +55

<0.28 85.2+5 '

< 4.2U

<0.86

<4.60

<0'1

<0'2

<0,24

<0'2

<0.33

<0.53

<0,38

<0.98

<1 95

<0.30 96 F 1+5.5 3.35+2.02

<0.77

<4,46

<0 ~ 38

<0'7

<0 29

<0.43

<0.34

<0'9

<0.55

< 1.47

<2.86

<0.44 161 0+7 ~ 6 4.45+2 ~ 21

<1,15 10.30+4.85 ON-SITE COMPOSITE:

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 ~ 32

<0 ~ 25

<0,23

<0.28

<0,28

<0.57

<0.32

<0.87

<1.95

<0'4 68.5+4.0 3 '8+1.96

<0'6

< 3+57

<0.34

<0.24

<0.24

<0.28

<0 34

<0.60

<0'6

<1 01

<2'8

<0.28 96 4+4.8 3.86+2.03

<1.04

<4 ~ 18

<0.21

<0. 18

<0'6

<0'1

<0.31

<0.55

<0.33

<0.79

<1'8

<0'6 79.0+4.0 3.21+1.63

<1.27

<3 ~ 16

<0 ~ 32

<0'3

<0.24

<0.28

<0.36

<0.57

<0.36

<0.95

<2.09

<0.34 7X.3+4.4 3.15+2.10 1 ~ 13+0.66 2.53+1.52 0.26+0 ~ 15

<0'5

<0.18

<0'1

<0.24

<0.46

<0.29

<0.80

<1.68

<0 ~ 23 84.2+4.4 2 '%+1.98

<0.99

<3'5 0 ~ 51+0.20

<0'4

<0,20

<0'7

<0,36

<0 ~ 62

'0.42

<1 ~ 07

<1,68

<0.29 122.0+5.8 2 42+1.21

<1.16 4 ~ 17+1.86 93

TABLE 11 (Continued)

CONCENTRATIONS OF GAHMA EHITTERS IN HONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES 1903 Results in units of 10 PCi/m

+ 2 sigma Nuclides Jul Au ust Se tern er Octo er Novem er Decem er OFF-SITE COHPOSITE:

A-1 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

<0.56

<0.31

<0.35

-<0.39

<0.50

<0.92

<0.75

< 1.89

<2 ~ 96

<0.51 136 0+10.5

<6 ~ 07

< 1.91 12 70+8 39

<0 ~ 56

<0.39

<0.42

<0.42

<0.50

< 1.00

<0.59

<1 ~ 66

<3+73

<0.40 147 0+10+1

.3 '9+3.21

<1 ~ 18

<7.69

<0 ~ 31

<0.29

<0.20

<0.34

<0.40

<0.04

<0.54

<1 ~ 54

<2.81

<0.44 105.0+7. 0

<5 ~ 71

<1.05

<6.43

<0 ~ 62

<0.39

<0.34 (0'1

<0'5

<1 ~ 20

<0.63

< 1.06

<3.00

<0.51

09. (H.0.2 (7 ~ 14

<1.75

<0.03

\\

<0.78 (0 ~ 56

<0.50

<0.50

<0.64

<1 ~ 33

<0.60

<2'0

<4.19

<0'0 96 '+8.6 4.74+3.51

<1 ~ 50

<8.42

<0 ~ 90

<0 ~ 51

<0.45

<0 ~ 55

<0.83

<1 ~ 32

<0.79

<2.00

<4.46

<0'3 123.0+9.6

<7 ~ 10

<1,69

<8.20 ON-SITE COHPOSITE:

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 ~ 29

'<0 ~ 26

<0.22

<0.31

<0.35

<0.06

<0.57

<1.37

<2 ~ 66

<0.40 111.0+8.0 4.06+2 ~ 79

<1 ~ 06

<5 ~ 23

<0.48

<0 ~ 29

<0.24

<0.31

<0.36

<0 ~ 70

<0 ~ 42

<1 ~ 32

<2.66

<0.34 90.3+6 '

<4.40

<0.73

<5.28 0.34+0.2.1

<0'6

<0.26

<0'6

<0.39

<0.71

<0.42

<1 ~ 17

<2.43

<0.37 8'+5.9

<3.39

<1.05

<4.91

<0.22 (0.35 (0 ~ 29

<0.35

<0.29

<0.67

<0.47

<I ~ 31

<2'7

<0.36 72,8+6.0

<5.07

<0.07 (5.09

<0.74

<0.50

<0.41 (0.50

<0,46

<1.04

<0.46

<1.50

<3.69

<0'7 07.7+6 '

<7.4'%2

~ 07

<5.95 1 ~ 73+0.41

<0 ~ 37 (0.29

<0.30

<0.45

<0 ~ 08

<0.45

<1.10

<2.90

<0.40 103.0+5 ~ 3

<4.41

<1,61

<4,76 e

TABLE 11 (Continued)

CONCENTRATIONS OF GAMMA EMITTERS IN MONTllLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES 1983 Results in units of 10 pCl/m

+ 2 sigma Nuclides Januar Fe ruary Narc>

Apr OFF-SITE COMPOSITE:

A-2 May June 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

<0.34

<0 ~ 30 (0.28

<0 ~ 33

<0.39 (0.84

<0.44

<1 ~ 25

<2.43

<0.35 78.5+F 1 4.34+2 47

<1.43

<4 ~ 67

<0 ~ 41

<0 ~ 32

<0.27

<0.35

<0.43

<0.94

<0.52

<1.41

<2 ~63

<0.44 131m(H6 4

<5 ~ 52

< 1.03

<5.39

<0 ~ 26 (0'3

<0.23

<0'4

<0.28

<0 ~ 58

<0 ~ 36

< 1.09

<1.99

<0.28 102.0+4.9 3.10+1.73 (0 ~ 98

<4 ~ 22 (0.41

<0.25

<0,26

<0.33

<0.40

<0.75

<0.43

<1.16

<2.90

<0.33 85.8+5. 1 3.70+2.25

<0.94

<4.95

<0.34 (0 ~ 21 (0 ~ 22 (0.27

<0.30

<0.56

<0 36

<1 ~ 01

<1.77

<0.30 93.0+5 2

<3 ~ 87 (0'8 6.45+3 14

<0 ~ 34 (0'2

<0,28

<0.31

<0.43

<0. 74 (0.54

<1+38

<2.78

<0'6 153+0+8 ~ 2 5 ~ 07+2.70

<1.30

<5 +52 ON-SITE COMPOSITE:

B-1 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

<0.23

<0 ~ 16

<0 ~ 20

<0 28

<0.31

<0.49

<0.32

<0 ~ 88

<1.71

<0.26 80.8+4.3 4.82+3 '8

<0'8 2.51+1.67

<0 ~ 33

<0 ~ 24

<0 ~ 26

<0 ~ 28

<0.32

<0.55

<0.37

<0.99

<2.30

'0.27 111.0+5 3

3 '5+1+75 (1.02

<4,33

<0 ~ 23

<0 ~ 16

<0 ~ 16 0 '0+0 ~

,12 (0'1

<0.50

<0.32

<0'1

<1.56

<0'6 105.0+4. 9

2. 96+1.50

< 1.08 2 ~ 10+1.27

<0.34 (0.23

<0.23 0.28+0.19

<0.3K

<0'1

<0.36

<1.04

<2.10

<0.30 83.1+4.4

<4.08

<0.97

<3.95 (0'6

<0 ~ 19

<0 ~ 15

<0 ~ 36

<0.24

<0.43

<0.31

<0.79

<1.38

<0'1 104.0+4.7 2.42+T.36

<0'O 2.50+1.59

<0 ~ 26

<0 ~ 19

<0,18

<0'6

<0.30

<0'7

<0.39

<0'6

<1.66

<0 ~ 24 147 0+6.5 3'. 79+7.84

<1.00 5.29+2.2 9

TABLE 11 (Continued)

CONCENTRATIONS OF GAHHA EHITTERS IN HONTIILY COHPOSITES OF NHP AIR PARTICULATE SAHPLES 1983 Results in units of 10 PCi/m

+ 2 sigma Nuclides Jul Au ust Se tern er Octo er OFF-SITE COHPOSITE:

A-2 Novem er Decem er Co-60 Hn-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

<0.56

<0.37

<0'6

<0 ~ 52

<0.59

< 1.08

<0.67

'1.74

<3.56

<0.4.5 139.0+10 ~ 1

<6. 13

<2.09

<6.83

<0.26

<0.24

. <0.21

<0.28

<0.34

<0.54

<0.38

<1,22

<2.02

<0.29 142.0>6 ~ 3 6 '9+2.33

<0.40

<4.74

<0'1

<0'1

<0.36

<0.42

<0.31 '0.35

<0.33

<0.38

<0 ~45

<0.62

<0.73

<1.00

<0.54

<0.63 (1 ~ 65

<1.67

<2 ~60

<3.58

<0 ~ 38

<0 ~ 48 113.0+8.0 96.3+8.2 5.78+2.94 5.63+3 '9

<1.08

<1.77

<6'0

<7.54 ON-SITE COHPOSITE:

B-1

<0 ~ 61

<0.49

<0.34

<0.51

<0.52

<1. 14

<0,62

<1.90

<3.95

<0'5 97.5+F 1

< 5.67

< 1.29

<7.45 0 '4+0 ~ 40

<0.42

<0.31

<0.43

<0.74

<1.39

<0.90

<1.54

<2e72

<0.63 136.0+10 1

3 76+2.62

<F 11

<6.21 Co-60 Hn-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

<0.15

<0.26

<0 ~ 37

<0.30

<0 ~ 76

<0.56

< 1.38

<2.61

<0.41 147.0+9.2 3.05+2,29

<1,61 4.76

<0.40

<0 ~ 28

<0.26

<0.22

<0.24

<0.84

<0.43

<1.11

<1,72

<0.33 121,0+7 53

<4 ~ 32

<0.88

<4.83

<0.20 c0 ~ 24

<0 21

<0 24

<0.30

<0.54

<0.38

< 1.00

<1.79

<0 ~ 25

'06.0+6.2

<4 ~ 02

<0'6

<4.39

<0.34

<0.30

<0.26

<0 ~ 24

<0.37

<0. 75

<0.37

<1 ~ 16

<2+55

<0.32 94.4+6.5 3.46+2.33

<0.77

<5.28

<0 ~ 41

<0'8

<0.34

<0.40

<0,56

<0.84

<0.50

<1 ~ 52

<3,62

<0.44 88 1+6.5

< 6.3Y

<1.44

<6,07 0+54+0.25

<0'4

<0'8

<0.31

<0 40

<0.75

<0.54

<1 ~ 10

<2.06 cd 53 77 +7+6.5

<4 22

<3.49

<4,31

UjEK EtlD t DATE C-"OFF Di "OFF D2-OFF E

OFF TABLE 12 ttttP/JAF SITE EttVIROMNEttTAL CHARCOAL CARTRIDGE SAMPLES - OFF SITE STATIOttS I-i3i ACTIVITY pCi/~'3

+ 2 siqna LOCATIOtt F

OFF G

OF'F 83/Oi/ii 83/Oi/19 83/Oi/25 83/02/01 83/Oh/08 83/02/iS 83/02/23 83/03/Oi 83/03/08 83/03/iS 83/03/22 83/03/29 83/04/05 83/04/12 83/04/19'3/04/26 83/05/03 83/OS/ii 83/05/17 83/05/24 83/06/Oi 83/06/07 83/06/14 83/06/2i 83/06/28 83/07/06 83/07/12 83/07/22 83/07/27 83/08/62 83/08/9 83/08/i6 88/08/23 83/08/31

&3/09/7 83/09/13 BH/09/20

&3/09/27 85/10/4 83/in/i3 BB/jo/18 83/io/2S 88/ij/1 83/ii/0&

88/ii/15 83/ii/22 83/ii/29 83/12/6 85/12/13 83/12/20 8 /12/28 4/01/4 (0.014 CO.Oi4 (0.022

<Q.oi5 (O.oiS (0.02i

<0.0iS

<0.028

<O.nii (0.020 CO O~i

<0.021 (0.029

<0.020 (Q.oi6 (0.012 (0.010

<0.015 CO.Oi3 (0.013 (0.007 Ca.aii (0.0i9

<O.oi2

<0.0i9

<0.0ii Ca.oiS (0.011 (0.022

<O. O14 (Q.oii

<0.0i4 (0.0i6 (0.016 (0.0i7

<0.013

<0.018 (0.012 (0.019

<0.014 CO 025

<0.0iS CO 0~6 (Q.oi6

<0:Oi&

<0.022 (0.022

<O.ni6 (0 0~4

<0.017

<0.929 (0.oi&

(0 O~~

(O.oi5 (0

0~0

<0.017

<0.0i9

<O.oi3 (0.620 (0.036

<0 62i

<0.023 (0.0i9

<O.ni7

<0.0i&

<0.023

<0 020 Cn.oi3 Ca.ois

<0.0i3

<Q.ois

<0.0i9

<0 Oi2'O.Oi6

<O.ai&

CO.OiS

<Q.oi6

<o.a14 40.020

<0.018

<Q.oi2

<0.0i7

<O.oi3

<O.oiS (Q.oi4

<O.ni9

<0 0~6

<0.02i (0.0i7

<Q.oi4 (0.026 (O.oi6 (0.025 (0.019 (0 O~i

<O.ni2

<0 0"0 (0..0i9

<0.0iS

<G.ni4

<0.013

<0.020

<O.oi9 CO.G23 97 (0.0i6

<0.009 (0.022 (0.020

<0.0i7 (0.023

<0.019 (6.020 (Q.oi6 (0.026 (0.017 (0.009 (0.0i9

~(0.022

<0.0i6

<Q.oi4

<Q.oi5

<0.0iS i Co.oi6 (0.019 (0.009

<O.oi9 (Q.oii

<Q.oii

<Q.oij

<0.0i2

<0.007 (0.019 (O.ai2 (O.oi&

<0.016

<6.616

<O.oi2 Ca.ni2 (0.022

<0.0i7 (0.02i (G.niS

<0.096

<0.016

<0.020 (0.024

<O.ai&

<0.0i7 (O.Oi&

CO O~r

<0.017

<0.017

<0.019

<n.o22

<0.027 (0.621 (G.ois

<Q.ni8 Ca.niB

<0 0~4 Cn.oi9 (O.Oi7 (0 O~i

<0.020 (0 023 (0.0i9 (Q.ni8

<0.0iB

<0.029

<0.0i&

(0.020

<0.020 (0.022 (O.oi9 Co.oi5

<0.019

<Q.oi5 Ca.ni9 (Q.oi6

<0.0i8 (O.oi9

<0.0i4 (0.0i7

<Q.oi6 CO.Oi7 (Q.oi5 CO.Oii

< 0. 019 (O.oi6

<0.016

<O.ni&

<0.0iS

<0.016 (0.012 (Q.ni7

<0.013

<0.024

<0.0i3

<0.0i&

<O.ai7 (0 0"6 (0.022

<Q.oi9

<0.022 (0.0i7 Ca.oi9 (0 O~i (0.022

<0.0i7

<0.0i8

<0.022

<Q.Oi6 (Q.oi9

< 0.622

<O.oi6 (O.oi3 (0.017

<0.02i (0.024

<0.018 (0 0~5

<Q.oi6

<0.022

<0.020

<0 020

<a.oj9

<0.0i9

< 0.02i (0. Oi'5

<0.009 Ca.aii CO.Oi7 CO.OOS

<0.0iB

<0.0i7 (0.0i7

<0.005

<0.0i7

<0.006

< 0.910

<0.006 (O.oi i

<0.0i8 (0.62i (0.0i9 (6.016

<9.014 (O.oiS

<0 020

< 0.0i.6 (G.ois (Q.0i6 (O

O2O

< 0.0i9

<9.028

<0.024

<Q.oiS (0.02i

(;0. Oi9

<0.624 (0.013

<G.oi4 (Q.oi3 (Q.0i6

<O.oi2 Co.oi9

<O.Oi&

<0.028

<o.ni&

<Q.niS

<0.0iS (0.019 (0.02&

<O.ni'7 (0.0i7

<0.022

<0.0i&

<Q.oi4

<Q.oi3

<Q.oi3

<Q.oi4

<a.'017

<Q.ois

<O.ii5

<0.029 Cn.ai4

<O.oi7 (O.oi2

<0.006

<Q.ois

<G.oi5 (Q.oi4

<G.oi6 (O.ni7

<0.018

<0.020

<0 O~j

<0 0~0

<0.023

<6.020

<0.029 CO. Qi4

<0 Oi2

<O.ni7 (0;023 (6.620

<0.023

<o.o2a

<O.ni&

<O.oiB

<O.ni7 (0.020

MEEK END gATE Di-Btt D2-Ott E

ON F

OH G--OH H

ON TP 13 t'"Pr nr SIlE Et(VIRBtNEHTAL CHARCOAL CARTRIDGE SAHPLES - Otf SITE STATIONS I-13i ACTIVITY OCI/n"3 + 2 signa LOCATION I

GH v

83/01/io 83/01/17 83/01/24 83/oi/3i 83/02/07 83/02/14 83/02/22 83/02/28 83/03/07 83/03/14 83/03/21 83/03/28 83/04/04 83/94/ii 83/04/iB 83/04/25 83/05/02 83/05/09 83/05/16 83/05/23 83/05/3i 83/06/06 83/06/13 83/06/20 83/06/27 83/07/05 83/07/1i 83/07/ie 83/07/26 83/08/Oi 83/08/8 83/98/is 83/08/22 83/lie/29 83/99/6 83)09/12 83)09/19 83/09/26 83/10/3 83/10/ii 83/10/i7 83/10/24 83/10/3i 83/ii/07 83/jj/14 83/ii/21 83/ii/28 83/12/5 83/12/12 83/12/i9 83/i2/27 84/9i/3

<D.oi7 co.ai2

<0.02i (0.0iO (0.0i4

<0.0i7 (Q.oie CO.Oi5 (0.017 (0.0ie

<0.0i8

<0 020 (O.ai5 (0.029

<0.02i

<D.oio

<0.009

<0.014 Co.oi7 CO.DiS Ca.ai6 (0.014

<0.0i7

<O.ai7

<0.0i7 (0.012

<0.0i8 (0.009 CO.Oi3 Ca.oi9 (D.oi6 (Q.oi2

<0.0i4 (Q.aiS

<a.oi4 (Q.oi7 (0.023

<0.022 (D.oi9 CO 02i

<0 02S

<0.Oi7

'0 02i

<Q.oi4

<0.023 (0.020 CO.Oi7

<0.023

<0.0i7 (O.oi9

<Q.ai9 (0.940

<0.019

<0.024 (0.947

<O.ai6 (0.020 (0 G~i

<0.033

<0.028

<0.033

<0.0iB

<0.026

<0.029

<0.024

<0.024 (0.02S (0.030

<0.02i

<0 02i

<0.025 (0 02i (0.024 (0.023

<0.921 (0.03i

<0.029 CO.Oi6 Co.oi3

<0.0i9 (0.0i9 (Q.oi3 (0 026

. co.ois (0 025

<0.0i4 Co.oi6 (0.024 (0.03i

<O.OBB

<0 0~4

<0.039

<0.037 (0.036 (0.025

<0.022

<a.o34

<0.039 (0.023

<0.032

<0.035 (0.930

<0.026

<0.04i

<0.0i7

<0.025

<0.020

<0.023 0

Q'97 0.02i

<0.027 Co 0"6 (D.oie CO.Oi9 (0.027 (0.0iB (0.0i9 (0.0i9 CO.Oi6 (0.0iB

<0.0ie Co.oi4 (0.021

<0.032

<D.oiS

<0.023 (0.017

<0.029

<0 Dj~

<0.01i (0

0~8 (0.016 (0 023

<0.024 (0.0i7

<0.019 (O.Di7

<0.018

<0.0i3

<0.0ie

<0.030

<0.019 CO 02S

<D.oi6

<0.022

<9.025 (0.0ie

<0.0i7 (0

0~6

<0.029 (0.024 (9.023

<0 0~0 (0.024

<0.026

<0 02S

<0.023

<0.030 (0.926

<0.026

<0 Qie

<0 0"6

<0.031 (G.034

<0.032 (0.027 (0.922

<0.935 (D.038

<0.03i

<0.029 (0.020

<0.022

<0.019

<0.020

<0.0i5

<0.0i7 (O.ai4

<Q.ai6

<0.Oi7

<0 0~8

<0.044

<0.0i6 (0.010 CO.Oi3

<0.014 (O.oi4

<Q.ai6

<0.0i5

<D.ois

<0.014

<O.oi9

<0 0"~

<G.ai6 Co.oi6 (0.0i3 (0.926

<O.oi7

<0.0i9

<Q.oi9

<0.023

<0.029

<9.0i7 (0 Gie (G.ai7 (O.ai5 (0.019

<Q.oio 98 (0.018

<0.026

<0.029 (0.036 (0.029 (0.029

<0.016

<O'.0:7

<0.023.

<0.016

<0.020 (0.015 (0.034 (0.016 co.ois

<0.020

<0.027

<0.023

<0.023

<0.0i9

<0.030 (0.030

<0 0"0 (0.027 (0.0i7

<0.019

<0.027

<0 0~9

<O.ai4

<0 024

<0.008

<O.ai9 (0.007 (0.018 (0.017 (0. 0'i9

<0 0"5 CO.ai6 (0.022

<0.006

<O.D25

<0.0i6 (0

0~4

<0.021 (0 O~j (0.032 (0.916

<0.024 (0.024

. (0.018 (0.026

<0 0"8

<o.a23 (0.914 (0.019 0.022+0.oiS (9.927 (D.oi9

<0.023

<0.038 (0.02i

<0.0i7 (0.023 CO.Oi4

<0.023 C0.016

<O.ai9

<0.022 Ca.ai9

<0.0i9 (0.020

<0 020

<0.022 0.032+0.oi7 0.035+0.oi6 (O.U19

<0.022 (0.02i

<0.024

<0.023

<0 O~j Ca.aiB CG.020

<0.0i5

<0.0i6

<0;Oi3

<Q.DQB (0.028

<9.02S Co O~S

<0.022 (0.929

<O.Oi4.

<0.017

<0.0iB

<0.020

<0.024

<9.014

<0.070

<0.019 0.023+0.oi3

<0.920

<0 026 (0.013

<0.017

<O.oi8 (D.oi&

<0.024 (0.0io Co.oi6

<0.020 (0 O~i

<Q.oi6

<D.oi7

<0.022 (D.ois

<D.oi3 (D.ai8 (0.020

<O.ai7

<0.0i9 (0.020 CO.Oi9 Co.oie

<0.023

<0.019

<0 02i

<0.0i3 Co. Oii (0.011 (0.0i5 (0.03i (Q.oi6

<G.oia

<0.0i2

<0.0i6 Co.oi4

<0.0i4

<0.022

<0 0~6

<Q.oi6 (0.0i8 (0

G~~

<0.0i9 C0.024

<0 0~8 Co.oie (Q.oi9

<9.925 (0.020

<Q.ai9 (0.020

<9.019

<0. 039

<O.O2S C 0. 913

<G.aie

<9.023 (9 020

<0. 920

<0.923 CO. 029 CC.02i

<0.025

<0 920 (0. 022 (Q.oi6

<0. 016

<Q.ai6 (0.968

<0.022 (0. 026 Co.oi7

<0. Die (D.ois

<O.ai9

<0.020

<0.012

<0.03i (0.027

<a.'028

<0.0ie (0.018

<D.oi2 (0. 017

<0.0i7 (0. 015 CO.Qis (0. Oia (Q.oi4

<0. 021 (0.921

<0. QlS

<0.0"3 (0. G2S (0 0"0

<0.018

<0 Oj~

<O. Qi3 (0.023

<0. 025 (0.911

<9. 022

<0.022

<9.023

<0.026

<0.032

<0.0ii

<9. Oii

<0.01?

<0 022

<0.02i

<D.025 (G. 04S

<9 02i (G. 033

<0.918 (Q.aii Co.oi9 CO. OiS

<0.020

<G.oii

<0.018

<9. 012

<D.ois (0. Oi3 (0.915 CO.O14 Co.oii

<Q.ois

<D.Oi8

<0.024 Ca.aii

<0.017

<0.014 (Q.oi3

<D. Oi8

<Q.oi7 (O. 014

<0.919'9.

OiS (O.Dii

<D.oii

<G.oi6

<Q.oii (O.oi8

<D.0 iS

<9 a~?

<9. OiB (0.918 (G.oi9

( G. 91?

<0. 020

<9.02i (G. 017

< Q.ai2 I 9 P3

<9. 025

<0.024

I

~ 5

i I h

i I TABLE 14 DIRECT RADIATION MEASUREIIENTS QUARTERLY RESULTS (1983)

Results in Units of mrem/Std.

Month + 2 Sigma S TATION NUMBER LOCATION

'ANUARY TIIROUGH MARCH APRIL TIIROUGII JUNE JULY OCTOBER TIIROUGII

- TIIROUGII SEPTEMBER DECEMBER LOCATION (DIRECTION AND (DISTANCE)*

3 4

5 6

7 8

9 10ll 12 13 14 15 10 19 23 24 25 26 27 28 29 30'1'9 43 44 Dl on Site D2 on Site E on Site F on Site G on Site C off Site Dl off Site D2 off Site E off Site F off Site G off'Site DeMass Rd, SW Oswego-Control Pole 66, Wo Boundary-Bible Camp Progress Center-Picnic Area East Boundary-JAF, Pole 9

II on Site I on Site J on Site K on Site Nor'ence-NNW Sector, JAF Light Pole (E) JAF Nor. Fence (E) JAF Nor. Fence'(NW) JAF Nor. Fence (NW) NIIP-1 East Fence, Rad.

Waste-NMP-1

.9 mi Rt. 3 from Rt. 104B Cor ~ Rt 3 and Kelly Drive 12.09+1.00 7.00+1.23 5 ~ 71+0 ~ 61 5.30+0.51 5.60+0.52 7.17+0.56 6.09+0.09 5.92+0.26 5 46+0.45 5.64+0.34 5.77+0.41 5.8&0.49 5.31+1.00 5.51+0.62 5.83+0.33 8.9 7+0.70 6 '9+1.00 6.04+0.21

6. 3 1+0. 31 20.95+2.23 47.05+5.10 74.80+11.44

. 16.02+0.74 21.39+2.05 58.04+5.78 6,01+1.30 6.17+0 53 10 '1+0 ~ 66 5 ~96+0.43

.. 6.'13+1.31 5.0840. 1?

5.8050 ~ 53 6.02+1.11 5.31+0.48

'.00+0 ~72 5.59+0,99 4.64+0.72 5.52+0.26 5.34+0.54 5.36+0.61 5.62+0 56 6 '2+0.25 7.46+1.31 6.44+0.98

~

6.50+1.33 6 '3+0.26 15 '6+2.55 41.17+1.93 58.20+10.58 13.85+2.35 17 '6+1.64 12.65+1.76 6.55+0.39 5.99+1.15 6.75+0 ~ 04 5 ~66+0 90 5.39+0.64 (1) 5.27+0.44 5.75+0 37 4.61+0 ~ 02 5.16+0 40 5.31+0 ~ 75 5'7+0 17 5.05+0 ~ 37 4.06+0.69 4 30+0 32 5.50+0 90 5.11+0 ~ 66 5.90+0 ~ 19 (T) 5.4 1+0 ~ 16 5.03+0 ~ 62 10.70+0 76 26,10+3 56 33.21+2.21 9.16+0.47 17.65+1.28 12.03+0 ~ 79 5.32+0.60 5.35+0 ~ 26 16 F 5+1.0 7 ~ 2+0.5 6 ~ 4+0 ~ 6 5.6+0.3 6.3+0 2

6 '+0 '

5,5+0 ~ 1 5.7+0 ~ 4 5.3+0.3 5.4+0 ~ 2 5 '+0.3 5,7+0 '

4.9+0.2 6.0+0.3 5.6+0 7

8,&0.6 6 2+0'

~

6.4+0 3

6.0+0.4 21.5+2 '

52.4+4.3 72.0+3 9

18.6+1,2 21 6+0 5

16.3+0.4 5.4+0.3 5.9+0 ~ 2 0 ~ 25 0.40 0 40 0.50 0 ~ 70 16.00 11.40 9,00 7.20 7.70 5.30 12+80 0 90 0.50 1.30 0 80 0 ~ 00 0,90 0.50 0.40 0'0 0.50 0 40 0.20 0

10 9.40 12 60 miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles 69' 140' 175'8210' 250'I 42'0' 117' 160' 190' 225' 225't 230' 260'01 71 9 =90' 110' 132'0'0'

'65'74 6 290' 292'8 64'9

TABLE 14 DIRECT RADIATION MEASUREMENTS QUARTERLY RESULTS (1983)

Results in Units of mrem/Std.

Honth + 2 Sigma S TATION NUMBER LOCATION JANUARY THROUGH HARCII APRIL THROUGH JUNE JULY THROUGH SEPTEMBER OCTOBER THROUGH DECEMBER LOCATION (DIRECTION AND (DISTANCE)*

45 46 47 48 49 50 51 52 53 54 55 56 57 58

'59 60 61 65 Cor. Rt 64 and Rt. 35 Cor. Rt 176 and Black Creek Rd.

NE Shoreline (JAF)

.36 mi (N) on Access Rd. (JAF)

Phoenix, NY-Control Lake Rd,West of J On-Site Oswego Steam Sta.

N End of W Pence East 111th St. Fitzhugh Park Sch.

Broadwell & Chestnut Sts-Fulton HE ST Liberty St.

& Co. Rt ~ 16-MexicoH.ST Hinnmann Rd.

& Co. Rt. 5-Pulaski HE ST Rt. 104 - New Haven HiS, (SE Corner)

Co. Rt. 29&Miner Rd.(SE)-Lycoming,NY Co. Rt.

1 ALCAN (S of Entrance Rd.)

Environmental Lab JAP ST Shore (Fish Point) Little Sodus Bay, NY 700' of 448 (On Access Rd.)-JAF Dutch Ridge Rd.

& Kerfien Rd.(SE) 6 '4+0.36 5.75+0.19 45.33+9.97 7.95+0,74 5.82+0.57 (I) 6,14+0.22 5.62+0.57 5 '8%.30 5.23+0.35 5 '2+0 ~ 26 6.02+0,08 5 '7+0.51 5,41+0.26'0,37+3.17 6 ~ 74+0.32 10.47+0,75 5.74+0.26 6.56+1. 12 5.9(HO 75 17 ~ 15+1,57 6.77+0.17 5.70+0.57 6.48+0.65 5.76+0. 18 4.93+1.39 5 '4+0.36 5.6(H0.23 5'6+0 ~ 38

6. 17+1.43 5.76<0 ~ 21 6 ~ 18+0.77 15.07+3 ~ 57

6. 19+0. 14 8.4 9+0.34 5.46+6.58 5.39~0.54 5.08+0.4 7 8 76+1.14 (1T 4.99+0 ~ 44 4.82+0.44.

~ (13 5.02+0.30 5.54+0,05 4.76+0.31 4.64+0 ~ 71 5.15+0.44 4.21+0.52 5.13+0.59 9.32 1.46 5.16+0 51 (1) 4.97+0.85 6.6+0 5 6 ~0+0.7 16 '+0.7 7.3<0.3 4.9+0 '

5+6+0+3 0) 5,9+0,4 5'+0 ~ 1 5.0+0 ~ 2 5 0+0,2 6o3+0 ~ 3 5,3+0.3 6,0+0 ~ 2 31.1+3.4 4.8+0. 1 9o9+0 ~ 8 4 ~ 7+0. 1 7,60 7.90 0

GO 0.80 20.00 0.70 7.50 5.80 13.70 9.30 13.70 5.40 1 ~ 90 3,20 0.50 21+00 0.80 7+80 miles miles miles miles miles miles miles miles miles miles miles miles miles miles miles 8

130'8 178 8

69'2' 165' 115 8 233' 227' 183'u 115 Q

7co 6 120 8 145' 220'5'iles 8

225'iles 8

83'iles 8

198'1)

TLDs lost Direction and distance based on NHP-2 Reactor Centerline 100

i'c'ABLE 15 CONTINUOUS RADIATION 1jONITORS*

(GH )

'R/hr FIRST HALF mR/hr LOCATION C

. Offsite PERIOD 1983 Ol/05 to,02/01 02/01 to 03/01'3/01 to 03/29 03/29 to 04/26 04/26 to 05/24 05/24 to 06/28 ICN 0.010 0.010 0 ~ 010 0 010 0 010 0.010 0 ~ 050 0+020 0 025 0.080 0 ~ 025 0.023 AVG.

0 ~ 015 0.015 Oo015 0.030 0.018 0.018 Dl Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0 ~ 010 0.010 0.013 0 ~ 010 0.012 0.010 0.045 0'52 0.075 0 ~ 050 0.032 0.027 0 ~ 015 0.020 0.020 0.022 0.023 0 ~ 011 D2 Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.010 0 ~ 010 0.010

0. 010 0.010

0. 010 0.050 0 '43 0.095

. 0.038 0.025 0.028 0.015 0 ~ 018 0.012 0 ~ 013 0.012

0. 013 E

Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.010 0 010 0 010 0.010 0.010 0 011

~ 0.19 0 '50 0.052 0.030 0.042 0'25 0.020 0 ~ 018 0.013

0. 015 0.015 0.015 F

Onsite Ol/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.010 0.010 0.012 0 ~ 010 0 020

'.012 0.030 0.024 0.050 0.078 0 +090 0 ~ 040 0 018 0.0 18 0.015 0 ~ 018 0.033 0 ~ 023 I

• Detectors are "bugged" to insure on scale readings

~

101

LOCATION TABLE 15 (Cont'd)

CONTINUOUS RADIATIONMONITORS+

mR/hr SECOND HALF PERIOD 1983 mR/hr AVG~

C Offsite 06/28 to 07/27 07/27 to 08/26 08/26 to 09/27 09/27 to 10/21 10/21 to 11/15 11/15 to 12/13 12/13 to 01/10 0 010 0 010 0 010 0 010 0 010 0.012 0 ~ 010 0'32 0.042 0'45 0,035 0 040 0.025 0.025 0 ~ 018 0 015 0 013 0.015 0'20 0.018 0.015 Dl Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 11/14 to 12/12 12/12 to 01/09 0.010 0 010 0.010 0.010 0.012

0. 016 0.011 0.018 0.025 0.030 0.042 0.060 0.060 0.065 0.012

0. 018 0.020 0.020 0.023 0.025 0.018 D2 Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 ll/14 to 12/12 12/12 to 01/09 0.0 10 0.012 0.012 0.013 0.012 0 011 0.010 0 '20 0.022 0.028 0.028 0.060 0 ~ 060 0.050 0.013 0 015 0.018 0.020 0.015 0.015 0 015 E

Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to ll/14 11/14 to'12/12 12/12 to 01/09 0.013 0.012 0 ~ 012 0.012

0. 013 0 012 0 ~ 010 0.035 0.025 0.025 0.025 0 026 0.070 0 ~ 085 0 018 0.018 0 018 0.018 0 ~ 015 0.015 0 ~ 015 F

Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 ll/14 to 12/12 12/12/ to Ol/09 0.010

0. 015 0.018 0.015 0.015 0.015 0.012 0.035 0.048 0.040 0.035 0.032 0'60 0.060 0,022 0 022 0 022 0 ~ 025 0.025 0 ~ 023 0.018

• Detectors are "bugged" to insure on scale readings.

102

TABLE 15 (Cont'd)

CONTINUOUS RADIATION MONITORS*

GM) mR/hr FIRST HALF mR/hr LOCATION G

Onsite PERIOD 1983 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 MIN 0 012 0.012 0 ~ 013 0.015 0.015 0.015 0.033 0.065 0.060 0+047 0 ~ 045 0.040 AVG~

0 021 0.020 0 ~ 020 0.020 0.025 0.024 H

Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.012 0.012 0 ~ 012 0.013 0.012 0.015 0 ~ 13 0.045 0.050 0.040 0 ~ 045 0.040 0.020 0.023 0 ~ 020 0.020 0.020 0.020 I

Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.013 0.012 0 ~ 015 0.020 0.013 0.018 0'72 0.039 0.080 0.060 0 ~ 073 0.039 0'18 0.022 0.025 0.028 0.025 0.028 J

Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.010 0.010 0.010 0.010 0.010 0 010 0'65 0.051 0.052 0.042 0 062 0.042 0 ~ 013 0.018

0. 013 0.013 0 ~ 018 0.015 K

Onsite 01/06 to 02/03 02/03 to 03/03 03/03 to 03/29 03/29 to 04/28 04/28 to 05/27 05/27 to 06/27 0.010 0.010 0.011 0.013 0 ~ 010 0 +012 0.023 0.039 0 ~ 059 0.032 0'35 0+030 0.012 0 018 0 ~ 018 0.018 0 ~ 018 0 018 Detectors are "bugged" to insure on scale readings.

103

TABLE 15 (Cont'd)

CONTINUOUS RADIATIONMONITORS*

GM) mR/hr SECOND HALF mR/hr LOCATION G

Onsite PERIOD 1983 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 ll/14 to 12/12 12/12 to 01/09 MIN~

0 ~ 018 0 016 0,013 0 015 0.015 0.015 0 ~ 010 0 038 0,049 0 o038 0,032 0.035 0.060 0'55 AVG~

Oo025 0,023 0'22 0,020 0 ~ 021 0.019 0 ~ 015 H

Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to ll/14 ll/14 to 12/12 12/12 to 01/09 0.012 0 ~ 018 0.015 0 ~ 015 0.015 0.015 0 010 0.062

0. 13 0 13 0.080 0.090 0.080 0.050 0 025 0 '24 0.022 0 ~ 025 0.025 0.025

. 0.020 I

Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 11/14 to 12/12 12/12 to 01/09 0.010 0.010 0 010, 0 010 0 ~ 010 0 012 0.010 0.038 0.030 0 028 0.030 0.030 0 040 0'25 0 028 0.020 0 ~ 013 0 015 0.015 0 020 0 015 J

Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 11/14 to 12/12 12/12 to 01/09 0,010 0.0 10 0 010 0 ~ 010 0.010 0.010 0.010 0.025 0 ~ 025 0.080 0 ~ 020 0.10 0.040 0.055 0.013 0 013 0.013 0.015 0.015 0.013 0.012 K

Onsite 06/27 to 07/26 07/26 to 08/25 08/25 to 09/23 09/23 to 10/20 10/20 to 11/14 ll/14 to 12/12 12/12 to 01/09 0 ~ 012 0.010

0. 010 0.012 0 ~ 010 0,010 0 ~ 010 0 038 0 028 0 026 0.052

. 0.030

, 0.030

0.040 0 ~ 018 0.018 0 ~ 018 0,018 0.015 0 016 0 012

" Detectors are "bugged" to insure on scale readings 104

TABLE 16 CONCENTRATIONS OF IODINE 131* IN HILK Results in Units 'of pCi/1 + 2 Sigma Station 5-9-83 6-6-83 7-4-83 8-1-83 9-12-83 10-10-83 11-8-83 12-5-83 40

<0 ~ 1 4

<0.3 14

<0.2 5

<0.3 16

<0. 1

<0.3

<0 ~ 2

<0.2

<0'

<0 ~ 2

<0 ~ 1

<0.1

<0'

<0 ~ 3

<0 ~ 2

<0 ~ 3

<0.4 (1)

(1)

<0.3

<0 ~ 2

<0,2

<0.3

<0.3

<0'

<0 ~ 5

<0.3

<0.2

<0 ~ 2 (1)

(1)

<0 ~ 2

<0.3

<F 1

<0 '

<0'

<0'

<0.3

<0 ~ 2

<0 ~ 2

<0.3

<0 ~ 2

<0.3

<0 ~ 2

<0 4 45

<0.2

<0.3

<0 ~ 2

<0.3

<0.3

<0.3

<0 '

<0.2 50 55 60

<0 ~ 2

<0.4

<0.3

.<0 ~ 2

<0'

<0 ~ 2

<O.l

<0.3

<0.4

<0 '2

<0.2 (1)

(1)

<0.4

<0.3

<0 ~ 3

<0 2

<0 ~ 2

<0.3 (1)

(1)

Iodine-131 results are corrected for decay to the sampling stop date

~

(1)

Sample station discontinued (not required by Technical Specifications) 165

TABLE 17 CONCENTRATIONS OF GAMMA EMITTERS IN MILK (MONTllLY SAMPLES)

Results in units of pCi/liter + 2 sigma Station Nuclides 5-9-83 6-6-83 7-4-83 8-1-83 9-12-83 10-10-83 11-8-83 12-5-83 40 14 16 K-40 Cs-134 Cs-137 Ba-140 0 thers K-40 Cs-134 Cs-137 Ba-140 0 thers K-40 Cs-134 Cs-137 Ba-140 Others K-40 Cs-134 Cs-137 Ba-140 0 thers K-40

's-134 Cs-137 Ba-140 0 thers 1400 + 140

<3.4

<3 ~ 6

<67.0

< LLD 1400 + 140

<3 ~ 6

<4.9

<81.0

<LLD 1400 + 140

<3.0

<3.9

<59.0

< LLD 1400 + 140

<3'

<4.8

<72,0

< LLD 1500 + 150

<4 6

<5.3

<85,0

<LLD 1300 + 130

<4.0

<5.0

<44.0

<LLD 1300 + 130

<3 ~ 2

<4,4

<37.0

<LLD 1100 + 110

<3'

<5.9

<34.0

<LLD 1300 + 130

<3 o3

<5.1

<35.0

<LLD 1450 + 150

<6.0

<6 ~ 0

<10.0

<LLD l120 + 110

<7.0

<6 ~ 0

<20.0

<LLD 1130 + 110

<5.0

<6.0

<10.0

<LLD 1420 + 140

<8 0 10.9 + 6 ~ 1

<20.0

<LLD

.1520 +150

<7.0

<7.0

<10 0

<LLD 1380 + 140

<7.0

<7.0

<9.0

<LLD 1360 +.140

<4.0 7.3 + 4.0

<6.0

<LLD 1290 + 130

<7.0

<8 ~ 0

<10.0

<LLD 1290 + 130

<5 '

<5'

<6 '

(LLD 1380 + 140

<4.4

<5 '

<6'

<LLD 1540 + 150

<7.8

<8.6

<9 ~ 6

<LLD 1310 + 130

<5.0

<5.6

<7o5

<LLD 923 + 92

<7 '

<7 ~ 3

<11.0(a)

<LLD 879 + 88

<3 ~ 9

<4 ~ 2

<5.8(a)

<LLD 1450 + 150

<4 2

<5.7

<4.8(a)

<LLD 949 + 95

<4.6

<5 ~ 3

<7.1(a)

<LLD 1290 + 130

<4 '

<5 '

<5.1(a)

<LLD 882 + 88

<4'

<4.7

<5.5(a)

<LLD 1310 + 130

<4.0

<4.3

<12.0 (a)

<LLD 1550 + 160

<6 7

<6 '

<8.3(a)

<LLD 1340 + 130

<4,8

<5 '

<4.5(a)

<LLD 1190 + 200

<6,4

<5.9

<7.2(a)

<LLD 951 + 97

<7a2

<7 6

<8.5(a)

<LLD 1300 + 130

<5 6

<6 0

<5 4(a)

<LLD 106

TABLE 17 (Cont.)

CONCENTRATIONS OF GPt&!A ENITTERS IN llILK (NONTHLY SAHPLES)

Results in units of pCi/liter + 2 sigma illa'tation I

~

)

50 55 60

~ >

Nuclides K-40 Cs-134 C s-137 Ba-140 0 thers K-40 Cs-134 C s-137 Ba-140 0 thers K-40 Cs-134 C s-137 Ba-140 0 thers K-40 Cs-134 C s-137 Ba-140 0 thers K-40 Cs-134 Cs-137 Ba-140 Others 5-9-83 1300 + 130

<3'

<4,4

<57.0

< LLD 1300 + 130

<4,0

<4 ~ 6

<93.0

<LLD 1500 + 150

<3+3

<4 ~ 2

<62.0

<LLD 1400 + 140

<3.5

<4.7

<75.0

<LLD 1400 + 140

<3 '

<3+7

<56.Q

<LLD 6-6-83

.1300 + 130

<2,8

<4.9

<53.0

<LLD 1300 + 130

<3.0 3.3 + 2.3

<29.9'LLD 1500 + 150

<3 ~ 7

<4 ~ 7

<36 0

<LLD 1400 + 140

<2.9

<3 ~ 6

<30.0

<LLD 7-4-83 1670 + 170

<8.0

<7.0

<20.0

<LLD 1200 + 120

<4.0

<6,0

<10.0

<LLD 1240 + 120

<5.0

<6,0

<2.0

<LLD 1370 + 140

<4.0

<5,0

<10.0

<LLD 8-1-83 1330 + 130

<5.0

<6 ~ 0

<6.0

<LLD 1320 + 130

<5.0

<5 '

<7.0

<LLD 1170 + 120

<5.0

<5.0

<8.0

<LLD 1330 + 130

<7.0

<7.0

<10.0

<LLD 9-12-83 1430 + 140

<6.4

<6 ~ 5

<7.8

<LLD 1200 + 120

<3.9

<4.3

<502

<LLD 1560 + 160

<4.8

<5.1

<6'

<LLD 1370 + 860

<6.5

<6 ~ 8

<8 ~ 1

<LLD 10-10-83 1600 + 160

<3,9

<4.4

<5.7(a)

<LLD 1610 + 160

<6 4

<6.8

<8.4(a)

<LLD 1700 + 170

<4.4

<4,9

<4.7(a)

<LLD 1200 + 120

<6 ~ 6

<6 5

<7.1(a)

<LLD 11-8-83 1120 + ll0

<6 4

<6.5

<7 4(a)

<LLD 1030 + 100

.,<3 ~ 9

<4.0

<5.2(a)

<LLD 1210 + 120

<4.4

<4.5

<4.5(a)

<LLD 914 + 91

<4.0

<4.5

<5.5(a)

<LLD 12-5-83 1390 + 140

<4'

<F 6

<4.8(a)

<LLD 1310 + 130

<4.3

<5.8

<3.7(a)

<LLD 1350 + 140

<4.4

<4 ~ 8

<5.0(a)

< LLD 1290 + 130

<6.4

<6;7

<6 4(a)

<LLD Location discontinued for the remainder of 1983.

(a) Represents Ba/La-140'07

TABLE 18 CONCENTRATIONS OP STRONTIUM 90 IN MILK (HONTllLY SAHPLES)

Results in units of PCi/li.ter + 2 sigma Station 5-9-83 6-6-83 7-4-83 8-1-83 (control) 40 14 5

16 7

45 50 55 60 3.0 + 0'.

2 4+0,6 2.1 + 0' 3'

+ 0' 4 0 + 0.6 2.2 + 0,4 4.3 + 0.7 i+8 + 0.6 2

7 + F 7 3.1 + 0.8 3 ~0+ 0.8 2.8 + 1.0 2.9 + 0.5 5'

+ 1.0 4.5 + 1.0 4 0 + 1.3 2'

+ 1 1 3.5 + 0.8 3.5 + 0.8 2'

+ 0' 0.9 + 0' 4.0 + 1.0 3.8 + 0 5 3'

+ 0.7 1 ~ 3 + 0.4 4

7 + 0.7 2.3 + 0.4 2 2+0,4 4 2 + 0+5 5.4 + 0.5 2.4 + 0.4 3.0 + 0.5 2'

+ 0,4 2 '

+ 0,4 Station 9-12-83 10-10-83 11-7-83 12-5-83 (control) 40 4

14 5

16 7

45 50 55 60 3.1 + 0 6 3,1+ 0 ~ 6 3.0 + 0,6 4.0 + 0.8 3'

+ 0,5 4'

+ 0.8 2'

+ 0.5 4

1 + 0' 1 5 + 0' 2.5 + 0' 2 6 + 0' 2.0 + 0 9 2'

+ 0.7 4

1 + 0' 1.4+0 8

4'

+ 0.8 2'

+ 0' 3.0+ 0 ~ 7 2.4 + 0.5 2+8+ 0 ~ 8 2 ~1+ 0.5 2.3 + 0.5 1.6 + 0.5 2'

+ 0.5 2'

+ 0 6 2.9 + 0.6 2.9 + 0.5 4'

+ 0' 2 ~7+ 0.5 2 ~7+ 0.4 2'

+ 0,5 2 3 + 0'

• ,Location discontinued for the remainder of 1983.

08

TABLE 19 MILCH ANZfAL CENSUS SPRING 1983 TOWN S criba New flaven

'exico Richland Oswego Hannibal Volney NUMBER ON CENSUS MAP~>>

1 16*

2 36" 9

4*

45*

10 5*

11 7*

12 13 14*

15 17 18 19 20 60*

50*

55*

21 22 23 24 25 NUMBER OF MILCH ANIMALS None <~"

39C 30C lc 1C C

40C 75C 22C 28C 45C 40C 54G 70C 2C 65C 35C 43C 46C 41C 7C 40C 150C 51C 78C 40C 65C 31C 10C TO 1

Cows 0 Goats C ~ Cows G ~ Goats Milk sample location

"* ~ Milk sample control location

• • • ~ Previous 1982 location

'.'1)

References Figure 5

109

TOWN S criba TABLE 19 (Continued)

MII,CH ANIMALCENSUS SUMMER 1983 NUMBER ON CENSUS MAP<>>

1 16*

2 3

6 26 NUMBER OF MILCH ANIMALS 2G 39C NA 1C 1Clc New Haven Mexico Richland

.Oswego Hannibal Volney 9

4*

45k 10 5*

11 7*

12 13 14 15 17 18 19 20 60*

50*

55*

21 22 23 24 C

40C 65C 23C 27C 45C 35C 53C 66C 2C 60C 33C

~

43C 47C 42C None***

40C 150C 52C 78C 58C 70C None""

10C C ~ Cows G ~ Goats

• ~ Milk sample location

• • ~ Milk sample control location

• "*~ Previous 1983 location NA

~ Did not wish to participate in the survey (1)

References Figure 5 TO a Cows 2 Goats 110

4 TABLE 20 CONCENTRATIONS OF GAlNA EMITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g(wet) + 2 sijma COLLECTION SAMPLE SITE DATE DESCRIPTION Be-7 K-40 I-131 CB-134 Cs-137 Others A

B C

D (control) 5-10-83 5-19-83 6-3-83 5-10-83 Eggs Eggs Eggs Eggs

<0.31

<0.40

<0 ~ 22

<0.37 0.9 + Oy2 1 ~ 2 + 0.3 1

1 + 0' 0.8 + 0.4 (1)

<3'

<0.7 (1)

<0,018

<0.022

<0.014

<0.018

<0.016

<0.024

<0.016

<0 ~ 019

<LLD

<LLD

<LLD

<LLD A

C D (control)

E F

G ll(control) 5-10-83 5-19-83 6-3-83 5-10-83 6-2-83 5-25-83 5-25-83 5-18-83 Poultry Poultry Poultry Poultry Beef Beef Beef Beef

<0.25

<0.31

<0.15

<0. 18

<0.24

<0.30

<0.20

<0.22 2.9 + 0.3 2,8 + 0.3 2.8 + 0.3 1 ~ 7. + 0.2 2.9 + 0.3 2'

+ 0+3 2 3 + 0' 2.6 + 0.3 (1)

<2.8

<0.5 (1)

<0.7

<1.6

<1 1

<lo7

<0.015

<0,016

<0.010

<0.010

<0.015

<0.019

<0.015

<0.014

<0.015

<LLD

<0.018

<LLD 0.018 + 0.008

<LLD

<0.010

<LLD

<0.017

<LLD 0.023 + 0 ~ 013

<LLD

<0,018

<LLD

<0.014

<LLD lk ~ 1) I!

~ j (1) I-131 not in the radionuclide library.

E'!

~

~

TABLE 20 (Continued)

CONCENTRATIONS OF GHANA EHITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g(wet) + 2 sigma COLLECTION SITE SAHPLE DATE DESCRIPTION Be-7 K-40 I-131 C s-134 C s-137 Others A

B C

D (control) 11-30-83 11-8-83 11-7-83 11-1-83 Eggs Eggs Eggs Eggs

<0.04

<0.07

<0.08

<0 ~ 11 1 1+0 ~ 1 1.1 + 0.1 le 1 + 0.1 1.0 + 0.1

<0.02

<0'2

<0.15

<0.34

<0.005

<0.005

<0.006

<0.008

<0.005

<0.006

<0.007

<0.008

<LLD

<LLD

<LLD

<LLD A

B C

D (control)

I J

K N (control) 11-30-83 11-8-83 11-7-83 11-1-83 Poultry Poultry Poultry Poultry 11-8-83 Beef 12-2-83 Beef.

11-18-83 Beef 11-11-83 Beef

<0.07

<0.08

<0.09

<0.09 I

<p.p6

<0.04

<0.08

<0.05 3 ~ 1+ 0.3 3.2 + 0.3 3ol + 0.3 3.3 + 0.3 2,9+0 ~ 3 2.4+ 0 ~ 2 3.4 + 0,3 3.2 + 0 3

<0.03

<0'2

<0 ~ 16

<0.25

<0.10

<0.01

<0.07

<0.08

<0.009

<0.007

<0.008

<0.007

<0.005

<0.005

<0.009

<0,005

<0.009

<0 F 007

<0.008

<0.007 0,044 + 0.006 0.014 + 0,004 0.023 + 0,007

<0.006

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 112

TABLE 20 (Continued)

CONCENTRATIONS OF GAHHA EHITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g(wet) + 2 sigma COLLECTION S I'gE SANPLE DATE DESCRIPTION Be-7 Z-40 I-131 CB-134 C s-137 Others L

L N

N H(control)

H(control) 9-26-83 9-26-83'-26-83 9-25-83 9-26-83 9-26-83 9-26-83 9-26-,83 Swiss Chard Tomatoes Swiss Chard Cucumber s Cabbage Squash Cabbage Zucchini

<0.08

<0.04

<0.13

<0.05

<0.09

<0. 11

<0.09

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<0.01

<0.01

<0.02

<0.01

<0.01

<0.02

<0.01

<0.01

<0.008

<0 ~ OOG

<0 016

<0.007

<0,011

<0.014

<0 012

<0 007

<0.010

<0 F 006

<0.016

<0 ~ 010

<0.013

<0 ~ 014

<0.013

<0.007

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD

<LLD 113

TABLE 21 CONCENTRATIONS OF STRONTIlkt-90 AND GAMBIA FJIITTERS IN SOIL Results in Units of pCi/g(dry) + 2 sigma SAIPLE LOCATION S&fPLE DATE Sr-90 K-40 Cs-137 Ra-226 Tli-228 Others D-1 ONSITE D-2 ONSITE E

ONSITE F

ONSITE G

ONSITE H

ONSITE I

ONSITE J

ONSITE K

ONSITE 11-10-83 11-10-83 11-10-83 11-10-83 11-10-83 11-10-83 11-10-83 11-10-83 11-10-83

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11 '+1 ~ 2 13 3+1.3 ll 3+1.1

<0.04 0 ~ 10+0,04 0.6(H0.06

<0.07 0.09k 0.02

0. 07+0.02 0.25&0 05 1.19+0 81 0.62+0.07

<0.71 1.19~0.53

<0.'99 1 22+0.34 1.1>0.30 1.52~0.37

<0.90

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.ALL<LLD ALL<LLD ALL<LLD ALL<LLD ALL<LLD ALL<LLD ALL<LLD ALL<LLD C

D-1 D-2 E

F G

OFFSITE OFFSITE OFFSITE OFFSITE OFFSITE OFFSITE 11-9-83 11-9-83 11-9-83.

11-9-83 11-9-83 11-9-83 0 ~ 13+0.04 0.17+0+03 0,27%

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1.46+0.15 0.2(H 0.04 0.66<0 ~ 07 1 0340.12 0.45&.06 0.20~0.06 1.77+0.84 1.3(H.O 70 1.35~0.71

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II qt' ~ o<< <<g4 PICIIBE 5 MMIIIIIBSI<<CBISUS hlKI NUX BW'IE QXATIQI5 (Ie ~ee<<<<O Iowa SS '. l eoe<<e o Iee<<V e>><<e 5 I. o ~ ~>> 10lle w~ ~ ~ 0 ga) ICC S Ie S I $J I<<O A V C "II ) Ieo X C~f! ~M\\M O<<O>>f 0l S Y ~ 4 5 jsQg O m N M<<o(lo lw ~ r ~ OO<<o >>>I ~~e I op ee ~o<<o<<o ~I Ieo \\ P O I IR I 'O 0 I~ I IQ/twwe 0 ee>> ~ ~ rho( e<<e ~ e (. ~I R II 0 / Oe>><<e Oe O 1 l~III K<< I>>O I~ SW h. Ct ~ e~> ~ h L I FVLTO <<ore I }goo Re Io 0 R I ~ I FIGVRE 6 ~eol<<el El 0 C ~ ~ 1 A ~ A C ACC OEVIAAIO "'<A1$0 0 I<<lloel %$ ~ $ 0$ $ ~elle eo<< CP mP Col<< locoI ~e<<lo 0 0 0 Io<<o Il o<<oe g I e<<<<o oc EC )(~'" L r'('""" A ~ I AO 1 O A C VC VII DC ~ I 0 ~ CC I ~ A \\ I AVC r '") I 0 ~ fP EE Ie<<o ILIe IACC CCIC 0C<<<<ool Seeee<<<<el I ol ~eloel AllCCAAI C'll~ C VIAC o l 0 J'I. ~ Oea ~ I 11CVl VACI ~ Ieo<<o 0 hleoe $ I 0 CAII)Ill ,4 1ACCAC11 ~ C IIV CO11 I C'IIC1$ OC1 EIACCV l<<e ~I~ ~ool III~ NEW YORK STATE MAP l ~, MIP-8414 NIAGARAMOHAWKPOWER CORPORATION NIAGARA 'OHAWK 300 ERIE BOULEVARD, WEST SYRACUSE. N. Y. 13202 April 30, 1984 Dr. Thomas E. Murley Regional Administrator United States Nuclear Regulatory Commission Region I 631 Park Avenue King of Prussia, PA 19406 RE: Nine Mile Point Nuclear Station Unit ¹1 Facility Operating License DPR-63 Docket No. 50-220

Dear Dr. Murley:

In accordance with the Environmental Technical Specifications for 1Vine Mile Point Unit ¹1 (Appendix B. Section 4.6.l.a),

we.are enclosing January 1983 through December 1983.

Very truly yours, Thomas E.

Lempges Vice President Nuclear Generation TEL/HJF/lo Encl.

2 copies cc:

Director, Office of NRR (17 copies)

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