ML20133F927
| ML20133F927 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1984 |
| From: | Glovier H POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Murley T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-85-0299, JAFP-85-299, NUDOCS 8510150038 | |
| Download: ML20133F927 (173) | |
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NEW YORK POWER AUTHORITY ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOLOGICAL REPORT JANUARY 1,1984 - DECEMBER 31, 1984 JAMES A. FITZPATRICK NUCLEAR POWER PLAST FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333 e
9
i TABLE OF CONTENTS Paste I
I.
INTRODUCTION 1
Introduction 1
Program Objectives 2
1 II.
PROGRAA1 DIPLE31ENTATION AND DESIGN 3
Sample afethodology 4
Analysis Performed 8
Changes in Program 9
III.
SA31PLE SU313fARIES 12 IV.
ANALYTICAL RESULTS 29 V.
DATA SUSD1 ARIES AND CONCLUSIONS 60 Lake Program 62 Terrestrial Program 77 Conclusion 95 Exceptions to the Program 96 References 98 VI.
HISTORICAL DATA 99 VII.
FIGURES AND SfAPS 127 i
LIST OF TABLES Pan Table I
Required Sample Collection and Analysis (Lake Program) 10 Table II Required Sample Collection and Analysis (Land Program) 11 Table 1
Periphyton Results 30 Table 2
Bottom Sediment Results 31 Table 3
Mollusk Results 32 Table 4
GAMMARUS Results 33 Table 5
Fish Results 34 Table 6
Water Ccmposite Results, Gross Beta 35 Table 7
Water Composite Results, Tritium, Sr-89, Sr-90 36 Table 8
Water Composite Results, Gamma Isotopic 37 Table 9, 10 Particulate Filter Results, Gross Beta 39, 40 Table 11 Particulate Composite Results, Gamma Isotopic 41 Table 12, 13 Airborne I-131 Results 43, 44 Table 14 TLD Results 45 Table 15 Radiation Monitor Readings 47 Table 16 Milk Results, I-131 51 Table 17 Milk Results, Gartma Isotopic 52 Table 19 Milk Results, Sr-90 54 Table 19 Milch Animal Census Results 55 Table 20 Food Product Results, Gamma Isotopic 57 11
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LIST OF FIGURES Page Figure 1
Offsite Environmental Stations and TLD Locations 128 Figure 2
Offsite Radiological Monitoring Stations 130 Figure 3
Onsite Environmental Stations and TLD Locations 131 Figure 4
Produce, Meats, Poultry and Eggs Sample Locations 132 Figure 5
Milch Animal Census Locations 133 Figure 6
New York State Regional Map 134 Figure 7
Bottom Sediment Description 135 Figure 8
Graph - Periphyton (Co-60) 136 Figure 9
Graph - Periphyton (Cs-13~)
137 Figure 10 Graph - Periphyton (Ce-144) 138 l
Figure 11 Graph - Mollusk (Co-60) 139 1
Figure 12 Graph - Mollusk (Mn-54) 140 Figure 13 Graph - Mollusk (Sr-90) 141 Figure 14 Graph - Bottom Sediment (Co-60) 142 Figure 15 Graph - Bottom Sediment (Cs-13")
143 Figure 16 Graph - Fish (Cs-137) 144 Figure 1"
Graph - Fish (Sr-90) 145 Figure IS Graph - Lake Water Gross Beta 146 Figure 19 Graph - Lake Water Gross Beta for 1984 14" Figure 20 Graph - Air Particulate Gross Beta 148 Figure 21 Graph - Air Particulate Gross Beta, Weeks 1-26 (1984) 140 Figure 22 Graph - Air Particulate Gross Beta, Weeks 27-52 (1984) 150 Figure 23 Graph - Air Particulate Composite (Co-60) for 1984 151 111
Paste Figure 24 Graph - Air Particulate Composite (Co-60) 152 Figure 25 Graph - Air Particulate Composite (Cs-137) for 1984 153 Figure 26 Graph - Air Particulate Composite (Cs-137) 154 Figure 27 Graph - Milk (Cs-137) 155 Figure 23 Graph - 3111k (Cs-137), Stations 40,16, 4, 60 for 1984 156 Figure 29 Graph - 5111k (Cs-137), Stations 40, 7, 50, 55 for 1984 157 Figure 30 Graph - 3111k (I-131) 158 Figure 31 Graph - Milk (Sr-90) 159 1
IV e
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I INTRODUCTION
I-A INTRODUCTION The New York Power Authority (NYPA) is the owner and licensee of the James A. Fit: Patrick Nuclear Power Plant (JAFNPP) which is located on the eastern portion of the Nine Mila Point promontory approximately one-half mile due east of the Niagara Mohawk Power Corporation (NMPC) Nine Mile Point Nuclear Power Station (NMPNPS). The NMPNPS Unit #1 is located on I
the western portion of the site and is a boiling water reactor with a design capacity of 620 MWe.
The NMPNPS has been in commercial operation since the fall of 1969. Located between the JAFNPP and NMPNPS, Nine Mile Point Unit #2 is under construction. NMPNPS Unit #2 will have generation capac-ity of 1,100 MWe and is expected to be completed in 1986.
The JAFNPP is a boiling water reactor with a power output of 810 MWe (net).
Initial fuel loading of the reactor core was completed in November of 1974.
Initial criticality was achieved in late November, 1974 and commercial operation began in July of 1975.
The site is located on the southern shore of Lake Ontario in Oswego County, New York, approximately seven miles northeast of the city of Oswego, New York. Syracuse, New York is the largest metropolitan center in the area and is located 40 miles to the south of the site. The area con-sists of partially wooded land and shoreline.
The land adjacent to the site is used mainly for recreational and residential purposes.
For many miles to the west, east and south the country is characterized by rolling terrain rising gently up from the lake, composed mainly of glacial deposits.
Ap-proximately 34 percent of the land area in Oswego County is devoted to farming.
The Radiological Environmental Monitoring Program 'for the Fit: Patrick Plant is a site program with responsibility for the program shared by the Power Authority and Niagara Mohawk.
Similar Technical Specifications for radiological monitoring of the environment allows for majority of the sam-pling and analysis to be a joint undertaking.
Data generated by the pro-gram is shared by the two facilities with review and publication of the data undertaken through each organization.
This report is submitted in accordance with Section 5.6.1 of Appendix B, to DPR-59, Docket 50-333.
Environmental reports of this nature have been compiled and submitted in semiannual and annual reports since 1974.
This report contains data from samples representing the period from Janu-ary 1,1984 to December 31, 1984.
1
O I-B PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program are as follows:
1.
To determine and evaluate the effects of plant operation on the envi-rons and to verify the effectiveness of the controls on radioactive ma-terial sources.
2.
To monitor and evaluate natural radiation levels in the environs of the JAFNPP site.
3.
To meet the requirements of applicable state and federal regulatory guides and limits.
i 4.
To provide information by which the general public can evaluate the environmental aspects of nuclear power using data which is factual and t
unbiased.
1 2
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II
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PROGRAM IMPLEMENTATION AND DESIGN l
II PROGRA31 IllPLE3!ENTATION AND DESIGN To achieve the objectives listed in Section I-B, sampling and analysis are performed as outlined in Tables I and II in this section.
The sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the James A. FitzPatrick Plant and the Nine Stile Point Station. The site staff is assisted by a con-tracted environmental engineering company, Ecological Analysts Inc.(EA).
l 3
1.
SAMPLE COLLECTION METHODOLOGY A.
Lake Water (surface water)
The two indicator stations are the respective inlet canals at JAFNPP and NMPNPS.
These samples are composited using continuously running pumps which discharge into large holding tanks.
The control station sample is collected from the city of Oswego water intake. The sample is drawn from the intake prior to treat-ment and is composited in a large sample bottle.
Quarterly composite samples are made up from proportional ali-quotes of monthly samples.
B.
Air Particulate / Iodine The air sampling stations are located in two rings surrounding the site.
The onsite locations ring the terrestrial area around the plants inside Whe site boundary.
The onsite sampling network is composed of nine stations.
The offsite air monitoring locations range six to 17 miles from the site and are composed of six stations.
Air monitoring locations are shown on Figures 1 and 2 of Section VII.
The air particulate glass fiber filters are approximately two inches in diameter and are placed in sample helders in the intake line of a vacuum sampler.
Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to absorb airborne i
radioiodine.
The samplers run continuously and the charcoal j
cartridges and particulate filters are changed on a weekly basis.
The particulate filters are composited on a monthly basis by loca-tion (offsite, onsite) after being counted individually for gross I
beta activity.
C.
Milk During the first two months of the 1984 grazing season, milk was collected from eight locations.
During the remainder of the 1984 grazing season, milk samples were collected from seven locations.
Six of these locations are considered indicator samples and the seventh is used as a control sample. Milk samples are collected in polyethylene bottles from the bulk storage tank at each sampled farm.
Before the sample is drawn the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat. Two gallons are collected during the first week of each month from each of the farms.
An additional one gallen is 4
I
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d from each farm at mid month to make up the second half monthly composite. The complete composite is made up from llon collected during the first week of the month and one from the mid month collection.
The samples are frozen and I to the analytical contractor routinely within 36 hours4.166667e-4 days <br />0.01 hours <br />5.952381e-5 weeks <br />1.3698e-5 months <br /> of 3
)n in insulated shipping containers. The milk sampling lo-are found on Figure 4 of Section VII.
D. 'oultry and Estgs tually one kilogram of meat is collected from locations within le radius of the site. Periodic phone calls are made to the lughter houses to determine availability of slaughtered live-com within the sampling area. Whenever possible meat sam-Je collected from locations previously used.
Attempts are collect a control sample located outside the 10 mile radius, th series of collections.
!ually one kilogram of poultry and one kilogram of eggs are 4 from each of three locations within a 10 mile radius of the attempts are made to collect poultry and eggs at the same t the meat samples.
The poultry and eggs are frozen and s in insulated containers.
Whenever possible samples are o from previously sampled farms.
Attempts are made to et control sample located outside the 10 mile radius, with eies of collections (see Section VII, Figure 5).
E.
li'ood Crops Hfood crops are collected during the Inte summer harvest att locations previously sampled, if available.
One kilogram et the two types of fruits and/or vegetables from each of tt-e locations within a 10 mile radius of the site are collected.
Tbs of fruits and vegetables sampled depend on what is lo-catilable at the time of collection. Attempts are made to col-letast one broad leaf type vegetable from each location. The frid vegetables are chilled prior to shipping and shipped friinsulated containers. Attempts are made to collect a con-trtle located outside the 10 mile radius for each type of sam-pl8Section VII, Figure 5).
F.
S,,,aples Schles are required once every three years.
Samples were col during 1983. Soil samples were taken at each of the 15 airoring stations at that time. No soil samples were collected dus)S4.
G.
F!sbles Avs fish species are removed from the Nine Mile Point Aquatic EcoStudy monitoring collections during the spring and fall 5
l collection periods. Samples are collected from a combination of the four onsite sample transects and one offsite sample transect (see Section VII, Figure 1).
Available species are selected under the following guidelines:
- 1) 0.5 to 3 kilogram of edible portion only of a maximum of three species per location.
- 2) Samples composed of more than 1 kilogram of single species from the same location are divided into samples of 1 kilogram each prior to shipping. A maximurn of three samples per spe-cies per location are used.
Weight of samples are the edible portions only.
k Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in insulated containers for analysis.
H.
GASD1ARUS GA5D1ARUS (fresh water shrimp) samples are collected by EA per-sonnel during the spring and fall season from two onsite locations l
and from one offsito location. Natural and artificial substrates are J
used to collect samples.
The GA5151ARUS samples are removed from the sampling gear. frozen and shipped to the analytical con-tractor in insulated shipping containers.
I.
Stollusks During the spring and fall seasons at two onsite locations and one offsite location benthic samples are collected.
The mollusks are collected by divers and sorted.
The tissue is removed from the shell, frozen and shipped for analysis in insulated containers.
J.
Bottom Sediments One kilogram of bottem sediment sample is collected at two onsite locations and one offsite location.
Samples are collected at the same time and location as the mollusk samples, where possible, by a diver.
The samples are placed in plastic bags, sealed and shipped for analysis in insulated containers.
K.
Periphyton Periphyton (fresh water algae) samples are collected in the spring and fall seasons from two onsite locations and one offsite location.
Periphyton is collected from natural substrates. The periphyton is scraped from the substrates into vials, labeled, frozen and shipped in insulated containers for offsite analysis.
6
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L.
TLD (direct radiation)
Thermoluminescent dosimeters (TLD's) are used to measure direct radiation in the JAF/NMP-1 environment.
The TLD stations are placed around the site using a two zone distribution.
The first group of TLD's is located within the site boundary and are called "onsite" TLD's.
The second set of TLD stations is the "offsite" stations, located at the offsite air monitoring stations and in areas of special interest such as population centers.
Also included in the offsito group are the field control TLD's.
A total of 45 TLD stations were used for the 1984 TLD program.
TLD's used during 1984 were rectangular Teflon wafers impreg-nated with 25 percent CaSOS:Dy phosphor. These were sealed in a polyethylene package to insure dosimeter integrity.
The TLD packages are further protected by placement in plastic holders, or by tape sealing to supporting surfaces.
The dosimeters are collected, replaced and evaluated on a quarterly basis.
7
i 2.
ANALYSIS PERFORMED The analysis of the environmental samples is performed by Teledyne Isotopes (TI) and the James A.
FitzPatrick Environmental Counting Laboratory (JAFECL).
The following samples are analyzed at the JAFECL:
Air Particulate Filter - gross beta (weekly) l Air Particulate Filter Composites - gamma spectral analysis (monthly)
Airborne Radiciodine - gamma spectral analysis (weekly) k Surface Water Composites - gamma spectral analysis (monthly) gamma spectral analysis (as Special Samples (soil, etc.)
collected)
The remainder of the sample analysis as outlined in Tables I and II in this section is performed by TI.
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3.
CHANGES TO THE 1984 SAMPLE PROGRAM A.
Milk sample locations number 5 and number 45 were deleted from the milk sampling program in July of 1984.
Several other milk sampling locations had been located, as a result of milch animal censuses conducted during 1983-84, that demonstrated greater radionuclide deposition potentials.
Since locations 5 and 45 had lower potentials for deposition, as determined by D/Q values, these locations were deleted.
B.
5111k sample location number 60 was added to the milk sampling program in July of 1984.
This location was added as a result of the milch animal censuses conducted during 1983-84. This location demonstrated average potentials for radionuclide deposition, as determined by D/Q values.
C.
Environmental radiation monitor C offsite was moved to environ-mental sampling station D-1 offsite on July 19,1984 (1205 hours0.0139 days <br />0.335 hours <br />0.00199 weeks <br />4.585025e-4 months <br />).
This move was a result of repeated vandalism to enviro.1 mental sampling station C offsite (the monitor detector was repeatedly stolen).
9
TAltlJi I SMIPlJi COLI.1:LTION AHit ANAL.YSIS SITli RAlll0IEICAl.11NVIRONHINTAl. BONITORING PROGRMI III A.
IAKIl l'ROGRMI Sti III A ANAL.YSIS FRIQIlliHCY(4)
~lDCAT10N(2) l 90 1.
Fish CcLi, 89Sr 4 Sr 2/yr 2 onsite 1 offsite 90 2.
Hollusks CcLi, 89Sr G Sr 2/yr 2 onsite I offsito 90 3.
Cammarus GeLi, 89Sr 6 Sr 2/yr 2 onsite 1 offsite 4.
I!otton Sediments OcLi, 90Sr 2/yr 2 onsite 1 offsite 5.
Periphyton Cel.1 2/yr 2 onsite 1 offsite g
6 Lake Water CB, GSA or Cel.i H Comp.
3(3}
3u, 89 r. 90Sr Qtr. Comp.
S Notes:
(I) Program continued for at least three years after the startup of James A. Fitzpatrick Nuclear Power Plant.
(2) Onsite locations samples collected in the vicinity of discharges, offsite samples collected at a distance of at Icast five miles from site.
(3) The three lake water sampics to include Nine Mile Point I! nit I intake water, James A. FitzPatrick intake water, and Oswego City w. iter.
(4) S.imples of items I through 5 collected in spring and fall when availalile.
TAnlliII L*Pll'IJi COI.lJiCTION ANil ANAL.YSIS SITli IIAI)IOllW;tCAl. ENViltONHliffrAl. SONITDIllNG Pit 0 GRAM 11.
IANil 1*ltOGilAll(I) til.lil A ANAL.YSIS 12ill:QIllINCY NO. 01: IDCATIONS tl) CATIONS 1.
Air Particulates Cl3 W
At least 10 9 onsi;c 6 offsite CSA StCmp.(6) 2.
Soil CSA, 90Sr Every 3 years 15 9 onsite 6 offsito 3.
Till Gamma lbse Qtr.
20 14 onsite 6 offsito l
4.
Itadiation Monitors Gamma lbse C
10 9 onsite 1 offsite 5.
Airliorne - I I3I GSA W
At least 10 9 onsite 6 offsite l
6.
MiIL I
61 4(7)
(8)
CSA, 90Sr H Comp.
I3I 7.
theman Food Crops
- CSA, l
A 3
(8) 8.
Heat, Poultry, Eggs CSA Edible Portion SA 3
(8)
Notes: (Cont.)
(6) Onsito samples countcJ together, offsite counted together, any high count samples counted separately.
(7) Frespiency applied only during grazing season.
(8) Sampics to be collected from farms within a 10-mile radius having the highest potential concentrations of radionuclides.
Ahle rev ia t ions :
H Comp. - Monthly composite of weekly or hi-weekly samples A - Annually nW - Bi-weekly (alternate wks.)
Gli - Cross tacta analysis W - Weekly Qtr. - Quarterly Gel.i - Gamma spectral analysis on a GcLi system (quantitutivo)
H - Ibuthly SA - Semionnually CSA - Gamma spectral analysis on a Nat system (quantitativo)
C - Continuous
i Ill a
SAMPLE SUMMARIES
III SAMPLE SUMMARIES l
l All sample data is summari:ed in table form. The tables are titled "Envi-l ronmental Sample Data Summary" and use the following format:
A.
Sample medium.
i 1
D.
Type of analysis performed.
C.
Number of analyses performed.
D.
Range of detectable levels.
The data column is labeled " Lower Limits cf Detection". This wording indicates that inclusive data is based on 4.66 sigma of background.
E.
Mean value of the data, based on positive measured values *.
F.
Standard deviation, based on positive measured values.
(The standard deviations represent the variability of measured results for different samples rather than single sample uncertainty *.)
G.
Maximum and minimum values.
H.
Range of the data, calculated by subtracting the minimum value from the maximum value.
- Only positive measured values are used in statistical calculations.
The use of LLD's in these calculations would result in the means being biased high and the standard deviations being biased low.
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IV ANALYTICAL RESULTS l
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l
IV ANALYTICAL RESULTS Sample Summaries Environmental sample data is summarized by tables. Tables are pro-vided for select sample media and contain data summaries based on quar-terly mean values.
Mean values are comprised of both positive and LLD values where applicable.
These tables are entitled " Environmental Sample Summary".
e.
1 i
e 29 i
TABLE 1 CONCENTRATIONS OF GAMMA EMITTERS IN PERIPHYTON SAMPLES Results in Units of pCi/g (vet) 1 2 sigma COLLECTION NUCLIDES JUNE AUCUST SITE FOUND 1984 1984 3.10" 10.82 1.75 FitzPatrick Be-7
<0.87 (03)
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<0.04
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<0.64 (0.98 Th-228 0.28 10.04
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<LLD (LLD Nine Mile Point Be-7
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t TABLE 6 CONCEN11tATIONS OF BETA EHITTERS IN LAKE WATER SAMPLES - 1984 Results in Units of pC1/1 1 2 sigma Station code January February March April Hay June JAF Inlet 3.4+1.9 2.6+1.7 4.961.6 3.540.8 5.911.7
< 2. 2 141P Inlet
<3.0 4.110.7 3.2+1.4 3.6+2.1 4.511.7 4.6+1.7 Raw City 3.4+1.8 2.860.7 4.411.5 3.3+2.1 3.7tl.5 2.5+1.5 3
Water (control)
Station code July August September October hovember Lecember j
JAF Inlet 2.5+1.6 4.3+1.9 4.741.7 4.5+1.8 4.4+1.6 3.1+1.4 NHP Inlet 3.3+1.7 4.6+1.9 5.141.7 5.341.8 2.211.4 3.2+1.9 Raw City 2.4+1.6 3.0+1.8 3.712.0 5.241.8 2.541.4 4.061.9 Water (control)
~
~
~
TABl.E 7 CONCENTRATIONS OF TRITIUM AND STRONTIIIH-89 AND STRONTIllH-90 IN I.AKE WATER (QtlARTER COMPOSITE SAMPI.ES)
Retiults in IInits of pC1/1 + 2 signia STATION CODE PERIOD DATE TRITIUM Sr-89 Sr-90 JAF INI.ET First Quarter 01/04/84 to 04/03/84 370 + 140 (1.2 0.86 + 0.46 Second Quarter 04/01/84 to 06/29/84 350 I 100
<l.9 (0!60 Third Quarter 06/29/84 to 09/30/84 230 + 80 (1.8 0.80 + 0.41 Fourth Quarter 09/30/84 to 01/02/85 290 { 70
<l.3 (0736 NHP INLET First Quarter 12/28/83 to 03/31/84 (210
<l.7 1.30 + 0.50 Second Quarter 03/31/84 to 06/29/84 230 + 80
<l.6
<0790 Third Quarter 06/29/84 to 09/28/84 (170
<2.0 (0.80 Fourth Quarter 09/28/84 to 12/31/84 340 + 80 (1.7 0.56 + 0.37 RAW CITY WATER First Quarter 12/28/83 to 03/31/84 (210
<1.1
<l.00 (Control)
Second Quarter 03/31/84 to 06/29/84 (300 (2.0
<0.69 Third Quarter 06/29/84 to 09/28/84 190 + 90
<l.5 0.72 + 0.48 Fourth Quarter 09/28/84 to 12/31/84 220 { 80
<1.8
<0!59 0
4 e
TABLE 8 CONCEN11 TAT 10NS OF Calf!A EHITTERS IN LAKE WATER SAMPLFS - 198 4 Results in Units of pC1/1 1 2 sigma Station Code Nuclide January February Harch April May June OSWECO CITY Ra-226 15.9111.3 <18.7 18.1110.5
< 24.4
<21.2 19.4f10.6 WATER Cs-134
<1.13
<0.99
<1.10
<1.20
<1.19
<1.19 (00, CONTROL) Cs-137
<0.93
<1.20
<1.' 03
<1.4 7
<1.05
<1.19 Zr-95
<3.19
<2.58
<3.38
<4.01
<3.76
<3.86 Nb-95
<1.83
<1.29
<1.45
<2.16
<1.72
<2.15 Co-58
<1.45
<1.02
< 1. 4 7'
<1.82
<1.48
<1.23 Hn-54
<1.05
<1.09
<1.16
<1.2 8
<1.28
<1. 2 2 Fe-59
<2.10
<1.86
<1.66
<2.26
<1.98
<2.19 Co-60
<1.53
<1.33
<1.20
<1.71
<1.25
<1. 2 8 K-40
<15.2
<14.4 12.246.8 15.0+11.2 7.6+7.0
<13.9 u
NINE HILE Ra-226
<20.4 12.247.2
<19.4
<24.1
<20.3
<20.3
-i l'0 INT Cs-134
<1.06
<1.03
<0.99
<1.24
<1.09
<1.19 (02, INLET)
<1.12
<1.07
<1.18
<1.50
<1.10
<1.0 0 Zr-95
<3.43
<2.63
<2.77
<3.38
<3.44
<3.67 Nb-95
<1.67
<1.29
<2.13
<2.4 3
<1.80
<2.31 Co-58
<1.33
<1.51
<1.47
<1.85
<1.63
<1.54 thi-54
<1.24
<1.04
<1.03
<1.26
<0.80
<0.8 6 Fe-59
<2.34
<2.15
<1.92
<2.51
<1.75
<1.97 Co-6u
<1.50
<1.54
<1.25
<1.42
<1.33
<1.3 8 K-40
<17.1 14.449.0
<13.8
<21.6
<15.4
<20.6 1ITZPATRICK Ra-226
<19.5
<18.7 17.549.3 28.3t11.7
<21.0
<21.3 t
(03, INLET)
Cs-134
<1.01
<0.97
<1.01
<1.13
<1.24
<1.14 Cs-137
<0.96
<1.10
<1.09
<1.24
<1.19
<1.10 Zr-95
<2.74
<2.93
<2.97
<3.33
<3.30
<3.29 Nb-95
<1.68
<1.83
<1.57
<1.83
<1.66
<1.74 Co-58
<1.16
<0.86
<1.23
<1.54
<1.42
<1.14 Hn-54
<0.85
<1.04
<1.10
<0.99
<1.10
<1. 2 2 Fe-59
<1.93
<1.65
<2.53
<2.33
<2.04
<2.25 Co-60
<1.47
<1.09
<1.20
<1.35
<1.36
<1.13 K-40
<13.6
<13.0
<11.6
<14.1
<14.3 7.2+5.9 t
D
s,,
i TABLE 8 (Cont'd)
CONCENTRATIONS OF CAHHA EHITTERS IN 1.AKE WATER SAHPLES - 1984 Results in Units of pC1/1,12 sigma t
Station Code Nuclide July,,
August September October November December OSWECO CITY Ra-226
<20.6 15.5t7.5
<19.3
<21.3
<21.6
< 23.0 WATER Cs-134
<1.08
<0.97
<0.85
<0.92
<1.17
<1.16 (00, CONTROL) Cs-137
<1.02
<1.29
<0.95
<1.07
<1.34
<1.3 3 Zr-95
<3.25
<2.99
<2.90
<4.29
<5.21
<3.90
{
<1.61
<2.26
<2.63
<2.34
<3.31
<2. 6 3 Co-58
<1.31
<1.23
<1.53.
<1.63
<2.14
<1.72 Ha-54
<1.11
<1.21
<0.99
<1.32
<1.4 7
<1.3 3 Fe-59
<2.41
<2.46
<2.05
<1.88
<2.55
<2.26 Co-60
<1.36
<1.12
<1.66
<1.52
<1.6 2
<1. 6 3 K-40
<12.3
<13.4
<12.2
<14.7
<19.8
- 10. 3_t7.4 NINE MII.E Ra-226
<20.6 19.1+12.4
<19.5
<21.2
<22.3 21.8s8.4 M
POINT Cs-134
<1.12
< 1. 0'2
<0.98
<1.04
<1.18
<0.9T (02, INLET)
<1.31
<0.92
<1.05
<1.28
<1.26
<1.13 Zr-95
<3.09
<3.35
<3.69
<4.02
<4.56
<3.56 Nb-95
<1.83
<1.89
<2.03
<2.52
<3.32-
<1. 8 2 Co-58
<1.30
<1.44
<1.09
<1.59
<1.81
<1.40 Mn-54
<1.13
<1.12
<1.15
<1.16
<1.26
<1.06 Fe-59
<2.09
<2.18
<1.73
<2.70
<2.60
<2.10 co-60
<1.42
<1.32
<1.62
<1.20
<1.62
<1.4 5 K-40
<15.1
<13.4
<14.7 14.519.1
<16.9
<9.44 FITZPATRICK Ra-226 16.8t7.8 22.418.5 14.8t7.8
<19.1
<22.6
<20.3 (03, INLET)
Cs-134
<1.10
< 1. 01,
<1. 0'8
<1.13
<1.26
<1.20 Cs-137
<1.19
<1.11
<1.07
<1.23
<1.24
<1.31 Zr-95
<2.99
<3.51
<3.27
<3.42
<4.20
<3.45 1
Nb-95
<1.75
<1.86
<1.78
<2.25
<2.14
<1.8 9 Co-58
<1.13
<1.20
<1.24
<1.37
<1.47
<1.74 Hn-54
<0.90
<1.10
<0.87
<1.12
<1.4 0
<1.2 7 Fe-59
<2.34
<2.34
<2.07
<2.20
<2.48
<2.52 Co-60
<1.41
<1.36
<1.65
<1.48
<1.32
<1.38 K-40
<13.1
<12.2
<13.1
<15.8
<17.6 13.248.2 i
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l TABI.E 14 I
l DIRECT RADIATION HEASUREHENTS - QUARTERLY RESUI.TS (1984 )
l Results in Units of arem/Std. Honth 4 2 Sigma JANUARY APRIL JULY OCTOBER LOCAT10N S TATION 111ROUCll 1llROUCil TilROUC11 111ROUCil (DIREL110N AHL NullBER LOCATION HARCil JUNE SEPTulBER DECDillER (DISTANCE)*
3 D1 on Site 12.911.2 11.310.6 13.241.4 8.3th.3 0.2 afic6 0 69*
4 D2 on Site 6.870.2 5.4TO.2 7.8T2.2 6.910.3 0.4 stic6 h 140*
5 E on Site 6.170.1 5.3IO.1 8.6TO.5 5.hT6.2 0.4 alles e 175*
6 F on Site 5.8T0.3 5.270.2 6.8Ii.1 4.770.1 0.5 mile 6 6 210*'
+
7 C on Site 5.6IO.7 4.6TO.2 6.9II.5 5.dIO.1 0.7 miles 6 256*
8 C off Site 6.270.5 6.0T0.3 8.271.4 6.6TO.4 16.0 miles e 42' 9
D1 off Site 6.2TO.3 4.970.1 7.4TO.1 5.3ib.2 11.4 miles e 60*
i 10 b2 off Site 6.170.3 4.0TO.2 7.2TO.3 4.9TO.1 9.0 miles 6 117*
11 E off SILe 5.8IO.3 5.5IO.2 7.6TO.5 5.6TO.5 7.2 miles e 160*
12 F off Site 6.0TO.5 4.7TO.1 7.470.1 4.9T0.3 7.7 miles e 190*
13 C off Site 6.3IO.5 4.6TO.1 7.6TO.8 5.hTO.1 5.3 alles e 225'
" 14 DcHass Rd, SW Osweao-Control 6.4TD.3 5.6TO.2 7.2TO.3 6.1T0.2 12.8 alles e 225*
15 Pole 66, W. Boundary-Bible Camp 5.3IO.4 3.pIO.4 6.210.1 4.210.1 0.9 miles e 238*
18 Progress Center-Picnic Area 6.8T0.8 (1) 7.741.7 5.210.3 0.5 miles e 268*
19 East Boundary-JAF, Pole 9 6.4TO.3 5.040.1 8.1I1.6 5.3IO.1 1.3 alles e 81*
23 11 on Site 8.3T0.4 7.5TO.3 9.9II.4 7.3TO.3 0.8 miles e. 71*
..~
24 1 on Site 6.4IO.4 6.6TO.1 8.2TO.3 5.4I0.1 0.8 miles e 98*
25 J on Site 6.4TO.4 4.8T0.2 8.0T0.7 5.470.2 0.9 miles e 110*
26 K on Site 6.4IO.1 5.6TO.3 7.7TO.5 5.1I0.2 0.5 miles e 132*
27 N. Fence N. of Switchyard, JAF 18.4T2.1 19.2II.3 19.4i1.0 12.6TO.3 0.4 miles e 60*
28 N. Light Pole, N. of Screenhouse, JAF 37.0]3.0 36.7}3.6 32.9_II.3 21.5_II.4 0.5 miles e 68*
29 N. Fence, N. of E. Side Screenhouse, JAF 43.965.1 40.713.8 34.410.6 29.141.2 0.5 miles e 65*
30 H. Fence (NW) JAF 15.971.3 15.9I0.9 16.471.0 11.4TO.4 0.4 miles e 57*
31 H. Fence (NW) NHP-1 23.uT1.4 22.6II.5 24.4II.2 21.1IG.4 0.2 miles e 250' 39 East Fence, Rad. Waste-NHP-1 18.5It s4 14.7Il.2 18.271.4 13.9Ib.4 0.1 miles 6 292*
43
.9 mi Rt. 3 from Rt. 104B 6.1TO.2 6.2TO.4
- 7. sib.5
'6.6TO.4 9.4 miles e 6h*
i 44 Cor. Et 3 and Kelly Drive 6.0TO.4 5.1T0.1 7.710.1 4.9{0.3 12.6 miles e 64
- i 1
l I
i s.
t TABI.E 14 (Cont'd)
DIRECT RADIATION HEASUREHENTS - QUARTERI.Y RESUI.TS (1984)
Results in Units of arem/Std. Honth + 2 Sigma JANUARY april.
JULY OCTOBER lACATION STATION liikOUCl!
TIROUCII TilROUCil TIROUCll (LIRE 0110N ANI, NUHbER IACATION HARCil JUNE SEPTEHBER DECEHBER (DISTANCE)*
45 Cor. Rt 64 and Rt. 35 6.1,10.5 5.310.0 8.1,10.4 5.3,60.4 7.6 m11L6 8 156' 46 Cor. Rt 176 and Black Creek Rd.
6.0 0.2 4.910.1 7.140.3 4.8 0.2 7.9 miles G 178*
47 NE Shoreline (JAF) 13.5I0.9
- 11. fin.3 15.3IO.4 9.hTO.2 0.6 miles 6 65*
48
.36 mi (N) on Access Rd. (JAF) 7.7T0.2 7.7T0.2 9.3T0.2 6.DIO.2 0.h mile 6 8 92*
49 l'hoenix, NY-Control 5.6TO.1 4.fio.2 6.6T1.3 5.fIO.2 20.0 alles 4 165*
50 lake Rd. West of J On-Site 6.5T0.0 5.3T0.1 7.5TO.1 4.970.3 0.7 miles h 115
- 31 liberty & Bronson Sts.. E of OSS 5.9IO.2 4.840.1 7.640.4 5.5TO.2 7.4 miles 6 233*
52 Cast 12th & Cayuga Sts., Osw. School 5.7I0.4
'4.8TO.2 7.1[,0.4 4.6I0.2 5.h miles 6 227*
53 Broadwell & Chestnut Sts-Fulton li.S.
5 910.2 5.010.1 7.540.3 5.040.1 13.7 miles 8 183*
54 Liberty St. & Co. Rt. 16-Hexico li.S.
5.6[0.6 4.7[0.1 7.3[0.4 5.5[0.2 9.3 mile 6 e 115' 55 Cas Stations Co. Rt. 5-Pulaski 5.6.10.2 5.7,10.2 7.1.10.3 4.8,10 2 13.0 miles 6 75*
" 56 Rt.104 - New Ilaven ll.S. (SE Corner) 5.9s0.1 5.0s0.1 7.4s0.2 5.110.2 5.4 alles 9 120*
$7 Co. Rt. 29&Hiner Rd.(SE)-Lycoming,NY 6.2;[0.3 4.8;[0.2 6.8;[1.0 4.9[0.3 1.9 miles 9 145' 58 Co. Rt. 1 - ALCAN (S of Entrance Rd.) 5.910.5 5.610.1 7.510.6 5.610.2 3.2 miles 6 220*
60 S. Shore (Fish Point) Lit'tle Sodus
~
11.fi0.2 12.1 0.4 12.fil.1 0.5 miles e 95*
~
59 Environmental Lab - JAF 14.0I1.0
~
~
~
3 Bay, NY 5 740.3 4.7t0.2 7.210.4 4.610.3 21.0 miles e 225*
61 700' N of #48 (On Access Rd.)-JAF 8.6T0.3 8.470.1 10.5TO.5 7.DIO.5 0.8 miles 0 83*
65 Dutch Ridge Rd. & Kerflen Rd.(SE) 6.0][0.5 4.8l[0.1 (il 48;[0.6 7.8 miles e 198*
t I
I (1) TLDs lost
~
Direction and distance based on NHP-2 Reactor Centtriine and Sixteen 22.5" detree sector gr1d.
J e
?
TABLE 15 CONTINUCUS RADIATION MONITCRS* (CM) mR/hr FIRST RALF st/hr 10 CATION PERIOD 1984 MIN.
MAX.
AVG.
C offsite**
01/10 to 02/07 0.'0 12 0.022 0.015 02/07 to 03/06 0.010 0.027 0.018 03/06 to 04/03 0.010 0.028 0.018 04/03 to 05/01 0.010 0.030 0.020 05/01 to 05/27 0.016 0.030 0.020 05/27 to 07/03 0.010 0.028 0.019 D1 Onsite 01/09 to 02/06 0.010 0.046 0.016 02/06 to 03/05 0.012 0.027 0.019 03/05 to 04/02 0.010 0.022 0.013 04/02 to 04/20 0.013 0.042 0.026 04/30 to 05/30 0.018 0.040 0.025 05/30 to 07/06 0.010 0.028 0.019 D2 Onsite 01/09 to 02/06 0.012 0.025 0.015 02/06 to 03/05 0.010 0.020 0.015 03/05 to 04/02 0.012 0.028 0.016 04/02 to 04/30 0.012 0.030 0.016 04/30 to 05/30 0.014 0.020 0.018 05/30 to 06/29 0.013 0.021 0.018 I Onsite 01/09 to 02/06 0.010 0.030 0.015 02/06 to 03/05 0.010 0.022 0.017 03/05 to 04/02 0.010 0.023 0.016 04/02 to 04/30 0.012 0.024 0.016 04/30 to 05/30 0.013 0.024 0.018 05/30 to 07/02 0.013 0.026 0.018 F Cusite 01/09 to 02/06 0.015 0.055 0.022 02/06 to 03/05 0.010 0.030 0.022 03/05 to 04/02 0.014 0.028 0.021 04/02 to 04/20 0.018 0.030 0.023 04/30 to 05/30 0.013 0.031 0.020 05/30 to 06/29 0.016 0.030 0.025 Detectors are " bugged" to insure on scale readings.
- Monitor located at D1 off-site station af ter 07-19-44 because of repeatec i
vandmit33.
i 47
T15LE 15 (Cont'd)
CONTINUCUS RADIATION MONITCRS* (CM) aalhr SECOND EALF mE/ hr ICCATION PERIOD 1984 MIN.
AVG.
C Offsite**
07/03 to 07/31 0.019 0.028 0.023 07/31 to 08/28 0.013 0.055 0.027 08/28 to 09/27 0.013 0.060 0.025 09/27 to 10/25 0.010 0.047 0.020 10/25 to 11/27 0.010 0.024 0.018 11/27 to 12/27 0.010 0.022 0.015 Di ensite 07/06 to 07/30 0.010 0.025 0.013 07/30 to 08/26 0.013 0.055 0.027 08/28 to 09/28 0.012 0.029 0.018 09/28 to 11/01 0.010 0.040 0.015 11/01 to 11/30 0.013 0.030 0.021 11/30 to 12/26 0.011 0.042 0.016 D2 Onsite 06/29 to 07/30 0.015 0.030 0.018 07/30 to 08/28 0.013 0.030 0.018 08/28 to 09/28 0.011 0.033 0.018 09/28 to 10/31 0.014 0.029 0.017 10/31 to 11/30 0.013 0.027 0.018
.11/30 to 12/26 0.012 0.G60 0.028 E Cusite 07/02 to 07/30 0.010 0.028 0.018 07/30 to 08/28 0.012 0.030 0.020 08/28 to 09/28 0.012 0.050 0.017 09/28 to 10/25 0.014 0.027 0.017 10/25 to 11/30 0.010 0.024 0.018 11/30 to 12/26 0.012 0.026 0.018 7 Onsite 06/29 to 07/30 0.010 0.032 0.025 07/30 to 08/28 0.010 0.035 0.025 08/28 to 09/28 0.013 0.029 0.021 09/28 to 10/31 0.010 0.040 0.025 10/31 to 11/28 0.015 0.032 0.022 11/28 to 12/26 0.015 0.050 0.020 Detectors are " bugged" to insure on scale readings.
- Monitor located at D1 off-site station after 07-19-64 because of repeated i
imedm14sm.
48 m.
r TABLE 15 (Cont'd)
CONTINUCUS RADIATIO.N MCNITORS* (CM) mR/hr FIRST HALF mR/hr I0 CATION PERIOD 1984 MIN.
MAX.
AVG.
C Onsite 01/09 to 02/06 0.010 0.022 0'.018 02/06 to 03/05 0.010 0.023 0.019 03/05 to 04/02 0.010 0.024 0.015 04/02 to 04/30 0.016 0.030 0.020 04/30 to 05/30 0.013 0.029 0.022 05/30 to 06/29 0.012 0.034 0.024 H Casite 01/09 to 02/06 0.015 0.050 0.018' 02/06 to 03/05 0.010 0.070 0.030 03/05 to 04/02 0.010 0.030 0.019 04/02 to 04/30 0.014 0.052 0.021 04/30 to 05/30 0.017 0.030 0.022 05/30 to 07/02 0.017 0.065 0.025 1 Casita 01/09 to 02/06 0.010 0.040 0.018 02/06 to 03/05 0.013 0.021 0.015 03/05 to 04/02 0.014 0.022 0.019 04/02 to 04/30 0.014 0.028 0.018 04/30 to 05/30 0.010 0.030 0.021 05/30 to 07/02 0.010 0.028 0.022 J Cusite 01/09 to 02/06 0.010 0.020 0.015 02/06 to 03/05 0.010 0.020 0.015 03/05 to 04/02 0.010 0.019 0.013 04/02 to 04/30 0.010 0.020 0.016 04/30 to 05/30 0.010 0.020 0.015 05/30 to 07/02 0.013 0.022 0.015 K Cusite 01/09 to 02/06 0.010 0.028 0.015 02/06 to 03/05 0.010 0.030 0.017 03/05 to C4/02 0.010 0.027 0.019 04/02 to 04/30 0.012 0.030 0.020 04/30 to 05/30 0.011 0.030 0.024 05/30 to 06/29 0.010 0.030 0.022 Detectors are " bugged" to insure on scale readings.
49
O TABLE 15 (Cont'd)
CONTINUOUS RADIATION MONITORS * (CM) mR/hr SECOND RALF mR/ hr 10 CATION PERIOD 1984 MIN.
MAX.
AVG.
G Onsite 06/29 to 07/30 0.013 0.032 0.020 07/30 to 08/28 0.010 0.035 0.025 08/28 to 09/28 0.010 0.04S 0.022 09/28 to 10/31 0.013 0.032 0.020 10/31 to 11/29 0.013 0.041 0.019 11/29 to 12/26 0.012 0.042 0.018 H Casite 07/02 to 07/30 0.018 0.080 0.025 07/30 to 08/28 0.010 0.100 0.027 08/28 to 09/28 0.018 0.110 0.050 09/28 to 10/29 0.011 0.110 0.032 10/29 to 11/30 0.017 0.089 0.032 11/30 to 12/26 0.012 0.046 0.020 I Cusite 07/02 to 07/30 0.012 0.038 0.020 07/30 to 08/28 0.012 0.034 0.017 08/28 to 09/28 0.012 0.040 0.018 09/28 to 10/29 0.012 0.03 4 0.020 10/29 to 11/30 0.013 0.030 0.022 11/30 to 12/26 0.015 0.043 0.020 J Onsite 07/02 to 07/31 0.010 0.028 0.017 07/31 to 08/26 0.010 0.090 0.027 08/28 to 09/28 0.010 0.090 0.023 09/28 to 10/29 0.013 0.090 0.021 10/29 to 11/30 0.010 0.040 0.021 11/30 to 12/26 0.010 0.053 0.020 K casita 06/29 to 07/30 0.010 0.032 0.020 07/30 to 08/28 0.010 0.031 0.017 08/28 to 09/28 0.010 0.030 0.020 09/28 to 10/29 0.010 0.023 0.016 10/29 to 11/30 0.010 0.024 0.015 11/30 to 12/26 0.010 0.033 0.015 t
f
- Detectors are " bugged" to issure on scale reacings.
50 l
l
TABI.E 16 CONCENTRATIONS OF 10 DINE-131 IN HII.K Results in Unite of pC1/1 + 2 sigma Station
- Hay June July August September October Noveder December 16
<0.22 (0.23 (0.21 (0.26
<0.19
<0.21
<0.17 (0.26 4
(0.30 (0.18 (0.18 (0.29 (0.20
<0.23
<0.17 (0.26 45 (0.29 (0.19 5
(0.19
<0.18 7
<0.28 (0.16 (0.22
<0.34 (0.24 (0.19 (0.17 (0.27 40 (Control)
(0.23 (0.16 (0.19
<0.19
<0.19
<0.23 (0.17 (0.21 50 (0.29 (0.19 (0.16 (0.23 (0.21 (0.17 (0.17 (0.21 55 (0.33
<0.17 (0.18 (0.22 (0.28 (0.21 (0.17 (0.25 60 (a)
(a)
(0.17 (0.30 (0.28 (0.21 (0.19 (0.25 Corresponds to sample locations listed on Figure 5.Section VII.
Sampling station no longer required by Technical Specifications, therefore discontinued.
(a) No sample taken.
(b) Sampling resumed due to results of Spring 1984 Milch Animal Census.
l 8
TAsl.E 17 MMcCENTWATlams OF CAlesA titlTIIs5 IN HilK (leWTNI.Y ComroslTI: EAMrl.ES) see it. In unste at pCl/l
- 2 ele =a 05/07/s4 06/04/a4 07/05/s4 Os/06/s4 os/10/s4 10/ol/s4 II/05/s4 12/03/s4 to to to to to to to to l
sTATsussa NMCI.llers 05/28/s4 06/le/s4 07/23/s4 Os/20/s4 09/24/s4 10/15/s4 II/26/s4 12/17/s4 Ise. 16 K-40 5350+140 1390el40 1260el10 1570sl60 1500el50 5520*l50 1530*l50 1530el50 Co-l34 (474 (7!I (4!9 (4!9 (575 (7!)
(s!0 (7!4 co-837 (4.7 (6.3 (5.7 (5.3 (5.4 (7.7 (8.0 (8.0 Ba-140 (5.9 (9.3 (6.8 (8.8 (22.0 (l2.0 (12.0 (8.7 La-140 (5.9 (9.3 (6.8 (5.1 (22.0 (12.n (12.0 (8.7 Others (LSD (885 (lJ D (LID (LID (lJD (lja (l.lD po.
4 E-40 1490el50 1880*l30 1590e160 1420*140 1840e190 1350el40 1490*l50 1440140 Co-1).
(4!7 (4!S (770 (5!7 (7!5 (4!4 (4!2 (4!9 Cs-137 (5.3 (4.8 (6.7 (5.7 (8.0 (5.5 (4.2 (5.1 Ba-840 (6.9 (6.9 (7.2 (4.1 (12.0 (7.9 (6.6 (5.3 La-140 (6.9 (6.9 (7.2 (5.1 (52.0 (7.9 (6.6 (5.3 j
Others (LID (LID (1.5D (l.lD (Lib (IID (LID (Lib
?
too. 45 K-40 1550* ISO Il20*lle g
Cs-834 (4!S (3!9 Co-l37 (5.0 (4.5 sa-140 (6.1 (5.6 y
l.a-140 (6.8 (5.6 Others (RJD (11D No.
5 K-40 1310*l30 1040et00 Ca-134 (179 (472 Co-837 (4.3 (4.5 Ba-840 (5.2 (7.3
. =
La-840 (5.2 (7.3 Olbers (LSD (LLD No.
7 K-40 1320el30 Illicello 1260*l30 1760*lso 1550*160 1540*I50 1530*l50 1570el60 co-834 (6!5 (6!6 (4!3 (776 (4!5 (677 (475 (5!4 i
Co-837 (7.0 (7.5 (4.4 (7.9 (5.8 (6.3 (5.0 (6.6 sa-140 (8.7 (8.6 (4.3 (14.0 (7.8 (8.3 (5.8 (5.4 14-140 (8.7 (4.6 (4.3 (84.0 (7.8 (u.3 (5.8 (5.4 Others (LSD (LSD (8.13 (LID (IJD (Ll3 (LIA (IID e Corresponde to sample lucettene meted on F8sure 5.Section VII.
- Sampling maastoma discoatsumed (not realutted by Fawltoneestal Techalcal Speelficatione).
w
TAN.E 87 (cont.)
COldCENTRAfl0005 4W CAfGIA IJ4BTTERS Ill MllJC (MOIITiel.V Coser0$ITE SApel*l.ES)
Resulte in Unite of pCl/l
- 2 sitee f
05/o7/s4 06/04/s4 07/09/s4 Os/06/s4 09/10/s4 30/01/s4 ll/05/s4 12/03/s4 to to to to to to to to sTafiossa leucLII*s 05/21/s4 06/la/s4 07/23/a4 Se/20/s4 09/24/s4 Is/15/s4 11/26/s4 12/17/s4 see. 40 (Control)
E-40 3200*l20 1190e120 14808150 1470el50 1430*l40 1430* SI 1490el50 1500*I50 Cs-134 (7!O (5!I
(?!5 (7!5 (4!4 (5!6 (4!0 (5!S Co-837 (6.6 (5.4 (s.4 (7.8 (4.4 (5.5 (4.6 (5.5 so-140 (10.0 (7.3 (9.6 (12.0 (5.9 (7.4 (5.s (5.5 La.140 (80.0 (7.3 (9.6 (12.0 (5.9 (7.4 (5.8 (5.5 otters (l.lD (LIA (1.LD (LIA (1.lJs (IJA (Lib
($Ja m.
50 E-40 1400 140 i nc.130 1210 820 16a0 170 1560 160 1u0 140 8560 160
- 420 140 Co-134 (478 (4!6 (4!0 (4!S (6!9 (378 (4!2 (7!0 Co-l37 (4.7 (4.9 (4.2 (4.s (6.2 (4.0 (4.2 (6.5 Ba-140 (6.6 (6.4 (4.8 (7.3 (9.2 (7.8 (6.2 (7.5 La-140 (6.6 (6.4 (4.0 (7.3 (9.2 (7.5 (6.2 (7.5 Others (LLD (5,lD (lla (IJD (LLD (IJD (LIA (tJa 4
No. 55 E-40 IF50el80 BM0el40 1290*l30 1540el50 1590*l60 1300el30 1430st40 1560el60 Co-834 (472 (4!3 (4!7 (5!0 (S!8 (4!0 (678 (379 Co-837 (4.6 (4.7 (4.7 (4.8 (3.9 (4.3 (6.9 (4.4 l
'a sa-840 (5.7 (5.5 (4.2 (6.9 (5.8 (6.2 (8.5 (4.8 La-140 (5.7 (5.5 (4.2 (6.9 (5.8 (6.2 (0.5 (4.8 Others (LIA (LIA (11 3 (LIA (l.a.D (i.LD (LID (IJ D I
Wo. 60 E-40 1290el30 *I 1610*l60 llooello 1250*l30 Il80el20 12806130 (5!7 (6!9 (378 (6!A (474 (3*7 Cs-134 (5.8 (7.5 (4.0 (6.7 (4.6 (4.0 i
co-117 Ba-840 (5.8 (9.8 (5.7 (8.4 (4.3 (4.0 i
1.a-840 (5.1 (9.8 (5.7 (8.4 (4.8 (4.0 othere (LLD (IJA (IJD (IJ.D (LLD (Lib 8 Correspnade to sample locattens noted on Figure 5.Section VII.
- lie esople tekee.
(a) Sampling reeumed as a result of Spring 1984 Mitch Aelmal Ceesse.
s a
6
TABLE 18 CONCENTRATIONS OF STRONTIUH-90 IN HII.K
"(HONTHLY COMPOSITE SAMPLES)
Results in Units of pC1/1 1 2 sigma Station
- Hay June July August 16 2.7 1 0.7 5.0 1 0.8 3.1 1 0.8 2.5 1 0.9 4
2.5 1 0.7 2.7 1 0.6 2.3 1 1.3 3.5 1 0.6 45 1.4 1 0.6 2.8 1 0.8 5
0.8 1 0.6 2.9 1 0.7 7
1.5 1 0.6 2.3 1 0.7 3.1 1 0.6 2.2 1 0.8
)
40 (Control) 1.5 1 0.6 2.7 i 0.7 2.3 1 0.9 2.7 1 0.8 50 0.8 1 0.3 1.8 1 0.7 2.210.6 2.1 1 0.5 55 0.9 1 0.6 1.7 1 0.7 0.8 1 0.2 1.1 1 0.6
)
60 (a)
(a) 0.9 1 0.4 2.1 1 0.5 E
Station
- September October November December 16 2.7 1 0.8 3.6 i 1.3 3.9 1 0.8 1.9 1 0.6 4
7.6 1 0.9 2.2 i 1.0 2.4 1 0.6 3.0 1 0.6 45 5
7 3.6 1 1.2 2.2 1 0.9 3.8 1 0.9 2.1 1 0.8 40 (Control) 2.9 i 1.0 1.7 1 0.7 1.3 2 0.8 2.0 1 0.9 50 1.4 1 0.7 1.6 1 0.4 1.2 1 0.8 1.3 2 0.8 55 2.7 1 0.8 1.8 1 0.6 2.8 i 1.0 2.0 1 0.7 60 1.5 1 0.7 1.0 1 0.4 2.4 1 0.8 2.4 1 1.0 i
Corresponds to sample locations listed on Figure 5.Section VII.
- Sampling station no longer required by Environmental Technical Specifications.
(a) No sample taken.
(b) Sampling resumed due to results of Spring 1984 Hilch Animal Census.
~.
l TABLE 19 MI1CH ANIhAL CENSD5 SPRING 1964 NCMBER Ch NbMM.R Cl) 01 MILCH ANIMALS T0hW CINSUS MAP Scriba 1
2ne 16*
39C
]
2 m
3 2C 6
1C 26 None New Haven 4
Ac 9
42C 4*
65C 458 20C+1C(2) 10 33C 1
5*
MC l
11 39C 7*
62C 48***
2G(2)
Mexico 12 6ec 13 2C 14 CC D
MC 17 UC 18 45C 19 GC 20 None 60*
4C 50*
90 0 55*
sic 21 66C Richland 22 42G 23 77C Oswego 24
.Wne Hannibc1 40a*
30G 7ciney 23 20C i
TOTALS:
1110 Ccws 3 Goats i
C = cows G = Goats
- = Milk sample location
- = Milk sample control location
- ** = New location ND = Cwner did not wish to participate (1) = References figure 5 (2) = Goats are g currently producing milk 55 i
l TABLE 19 (Continued)
MILCH ANIMAL CENSUS 5D01I11984 4
NCMBER CN NLMBIE CINSUS MAP (l) 0F MILCH ANIMALS TOWN Scriba 1
None 168 41C 2
2 3
2C 6
1C 26 Non a New Haven' 8
aC 1
9 43 0 4*
80 c 45*
None 10 32C 5*
45C 11 30 C 7*
60C 48 1C(2 )
Mexico 12 75C 13 2C 14 GC 15 43C l
17 48C l
18 45C 19 40C 20 None 60*
38C 50*
100C 558 45C i
21 60C 1
Richland 22 4CC 23 77C i
O swego 24 None l
Hannibal 4Ca*
32C Volney D
MG TOTALS:
1090 Cow.s 1 Goa:
C = Cows G = Goats
- = Milk sample location
- = Milk sanple centrol 1ccation
- = New location NC = Did not wish to participate in the survey (1) = leferences Figure 5 (2) = Goat is g currently producing 311k 56
,. _. _ ~.,.,
-Q.
,_,,,,d,,,
y.,_
1 '
ii, TABLE 20 CONCEN1 RATIONS OF CAMtA EMITTERS IN VARIOUS F00b PRODUC1S Results in Units of pC1/g(wet) f 2 si ua t
COLLECTION SAMPLE
(
SITE DATE DESCRIPTION Be-7 K-40 co-60 Cs-134 Cs-137 Ot t.e:S k
A 5-10-84 Eggs
<0.08 1.1240.11
<0.006
<0.007
<0.007
<LLL
.i.
B 6-6-84 Eggs
<0.04 1.060.76
<0.005
<0.005
<0.005
< Lta i
~i C
5-8-84 Eggs
<0.05 1.1510.12
<0.005
<0.005
<0.004
<LLL D(control) 5-2-84 Eggs
<0.06 1.1310,.11
<0.004
<0.004
<0.004
< tli A
5-10-84 Poultry
<0.48 3.0140.46
<0.016
<0.019
<0.015
<LLD B
6-6-84 Poultry
<0.39 3.7810.52
<0.023
<0.018
<0.021
<LLL C
5-8-84 Poultry
<0.69 3.5610.51
<0.022
<0.024
<0.039
<tLD i
D(control) 5-2-84 Poultry
<0.57 3.4510.50
<0.022
<0.026
<0.026
<LLD E
5-17-84 Beef
<0.30 2.5910.44
<0.021
<0.021
<0.021
<tLD
+
F 5-2-84 Beef
<0.41 3.24+0.51
<0.026
<0.027
<0.031
<LLL C
5-25-84 Beef
<0.24 3.71TO.45
<0.017
<0.018 0.04640.024
<LLD H(control) 5-2-84 Beef.
<0.28 2.9310.40
<0.023
<0.020
< 0.02Ti
<LLL
\\
l s
i.
(1) 1-131 not in the radionuclide library.
.m e
TABLE 20 (Continued)
CONCEN1 RAT 10NS OF CAHMA EMITTERS IN VARIOUS FOOL 110DUC1S Results in Units.of pC1/g(wet) 12 si na t
COLLECTION SAMPLE SITE DATE DESCRIPTION Be-7 K-40 co-60 Cs-134 C6-137 others 4
A 10-26-84 Eggs
<0.26 1.06'10.28
<0.013
<0.015
<0.016
<LLL J
11-20-84 Eggs
<0.17 1.3060.32
<0.014
<0.015
<0.016
< Lil C
11-6-84 Eggs
<0.13 1.0610.,30
<0.018
<0.017
<0.012
<LLb D(control) 11-5-84 Eggs
<0.33 1.0910.33
<0.029
<0.029
<0.032
< l.LL A
11-26-84 Poultry
<0.26 3.6510.45
<0.014
<0.022
<0.018
<LLL J
11-20-84 Poultry
<0.20 2.5710.40
<0.021
<0.019
<0.026
<LLL C
11-6-84 Poultry
<0.18 2.7810.45
<0.019
<0.017
<0.018
<llD D(control) 11-2-84 Paultry
<Q.36 2.81,T_O.45
<0.029
<0.032
<0.026
<tLD 1
11-15-84 Beef
<0.19 2.55 0.40
<0.024
<0.021 0.032 + 0.016 i
P 10-25-84 Beef
<0.28 2.88TO.43
<0.020'
<0.020
<0.019-
<LLD
<LLD K
11-9-84 Beef
<0.35 2.73I0.42
<0.031
<0.026
<0.027
<1.LD It(control) 11-8-84 Beef
<0.25 2.8dio.41
<0.023
<0.024
<0.022
< LI.L k
i e
i l
f i
TABLE 20 (Continued)
CONCENTRATIONS OF CAHMA EHITTERS IN VARIOUS FOOD l$0 DUCTS i
Results in Units of pC1/g(wet) f 2 sigma COI.LECTION SAMPLE l
SITE DATE DESCRIPTION Be-7 K-40 I-131 Cs-134 Cs-137 othus 1
9-18-84 Cabbate
<0.079 1.8540.19
<0.017
<0.009
<0.010
<tLL 1
9-18-84 Squash
<0.086 2.2010.22
<0.016
<0.010
<0.069
< l.LL L
9-18-84 Swiss Chard
<0.150 5.06+0.56
<0.033
<0.016
<0.017
<LLb i
L 9-18-84 Tomatoes
<0.062 2.13IO.21
<0.013
<0.007
<0.608
<LLL f
N 9-18-84 Collard Greens
<0.100 3.8310.38
<0.019
<0.012
<0.012
<LLb i
N 9-18-84 Tomatoes
<0.052 2.21I0.22 I
<0.011
<0.006
<0.007
<LLL H(control) 9-18-84 Swiss Chard 0.41410.093 4.67+0.47
<0.022
<0.013
<0.014
<LLL o,
H(control) 9-18-84 Tomatoes
<0.079 1.7640.18
<0.015
<0.009
<0.010
<LLD I
I i
~
i 8
E
4 f
4 i
e l
I i
t J
i i
i i
1 l
V I
,1 I
l i
1 i
DATA SUMMARIES AND CONCLUSIONS t
t I
?
1 1
I f
i a
a
-... ~...
. _,... ~...,. - _ -. -,. -... -, - _.,. -... - -...,.., -,, _... _, _., _.., _..,. -.. - - -.... -.,. -.
V DATA SUMMARIES AND CONCLUSIONS The results of the 1984 Radiological Environmental Monitoring Pro-gram are evaluated considering the natural processes of the environment and the aggregate of past data. A number of factors are considered in the cour:. of this radiological data evaluation and interpretation.
The interpretation of data can be made at several levels including trend analy-sis, population dose, risk estimates to the general population based on environmental concentrations, effectiveness of plant effluent controls and specific research areas, among others. An attempt has been made in this report not only to report the data collected during the 1984 sample pro-gram but also to assess the significance of the radionuclides detected in the environment.
It is important to note that detection of an isotope is not of itself an indication of its environmental significance. Evaluation of the impact of the radionuclide in terms of potential increased dose to man, in relation to natural background, is necessary.
There are three separate groups of radionuclides that were detected in the environment during 1984. A few of these radionuclides could pos-sibly fall into two of the three groups.
The first of these groups is naturally occurring radionuclides.
It must be realized that the environ-ment contains a broad inventory of naturally cmurring radioactive ele-ments.
Background radiation as a functic.. af primordial radioactive elements and cosmic radiation of solar origin offers a constant exposure to the environment and man. These radionuclides, such as Th-232, Ra-226, Be-7 and especially K-40, account for a majority of the annual per capita background dose.
A second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's upper atmosphere.
The detonation frequency during the early 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on weapons testing in 1963 which greatly reduced the inventory through the decay of short lived radio-nuclides, deposition, and the removal (by natural processes) of radio-nuclides from the food chain such as by the process of sedimentation.
Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China.
In each case, the usual radionuclides associated with nuclear detonations were detected several months after-wards and then after a peak detection period, diminished to a point where most could not be detected. The last such weapons test was conducted in October of 1980.
The resulting fallout or deposition from this test has influenced the background radiation in the vicinity of the s!te and was very evident in many of the sample medias analyzed didng 1981. Calcula-tions of the resulting doses to man from fallout related radioneclides in the environment show that the contribution from such nuclides b1 some cases (such as Sr-90 or Cs-137) is significutt and second in intensity only to natural background radiation.
Quantities of Nb-95, Zr-95, Ce-141, Ce-144, Ru-106, Ru-103, La-140, Ci-137, Mn-54 and Co-60 were typical in air particulate samples during 1981 and have a weapons test origin.
60
- _ _ _ _ =
-w
(
f i
The third group of radionuclides detected in the environment during 1984 were those that could be related to operation: at the site.
These 1
select radionuclides were detected in a few of the semple medias collected and at very low concentrations. Many of these radionuclides are a by-i 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. The dose to man as a result of these radionuclides is small and significantly less than the radiation exposure from naturally occurring sources of radiation and from fallout.
1 Thus, a number of factors must be considered in the course of radiological data evaluation and interpretation. The evaluation and inter-pretation is made at several levels including trend. analysis, dose to man, etc.
An attempt has been made not only to report the data collected during 1984, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. It l
is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are very sc'all and are not an i
indication of environmental significance.
In regards to these very small quantities, it will be further noted that at such minute concentrations the j
assessment of the significance of detected radionuclides is very difficult.
Therefore, concentrations in one sample that are two tin.es the concentra-tion of another, for example, are not significant overall.
- Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in another.
j In Section V each sample medium is discussed.
Concentrations of radionuclides detected and expogure to man are presented and scruti-1 nized.
Section VI, titled HISTORICAL DATA, contains sample statistics from l
previous environmental sampling. The process of determining the impact (or lack of impact) of plant operation on the environment includes the
~
scrutiny of past analytical data, a tool by which trends Are discerned.
The interpretation of historical data in this report is do'te to a limited degree.
Because of the constant change in analytical nensitivities, es state-ef-the-art detection capabilities improve, data com9arisons become difficult.
For example, minimum detection capabilities fc r the 1969 and 1974 analyses of environmental samples would be considered anomalous by 1984 standards.
4 1,
l 61 j
e s
e-sum see g
'w=
---&-e-e-
'i-=
+-q
+ - - -
y*w qw- - - -
w
-a
,e
-s-g.
.,,w-
_g-p9.._yw q-
=,
g-wu mwg-www, g-yw
-w
-e-pp*,g-g vn-m+1--+r,
,:--*e+--
w-.iaw,mr
LAKE PROGRAM Tables 1 through 8 list the 1984 analyt1 cal results for the aquatic / lake water media sampled during the 1984 samphng program. Aquatic samples were obtained at a combination of four onsite lec:tions.
The transect designations used for the onsite sampling locations are NMPW (01), NMPP (02), JAF (03) and NMPE (04).
Due to limited availability of certain required sample media, samples could not he obtsined consistently at each of the same onsite transects sampled for other media.
Offsite samples were collected in the vicinity or the Oswego Harbor (offsite - 00).
I i
J d2 I
g 1
1.
PERIPfiYTON SAMPLES - TABLE 1 Periphyton is a common fresh water algae found thrcughout the Great Lakes and in almost all underwater aquatic systems. Periphy-ton in its simplest form is a single celled organism which colonizes l
the natural and artificial substrates found in the shore and near shore waters.
Colonies of periphyton can be found from the shore i
zone to water depths which can be sufficiently penetrated by sunlight to support photosynthesis.
Periphyton is dependent on sunlight and inorganic materials found in the lake to support life j
therefore putting it in the classification of a primary producer.
Periphyton in its simplest form is the slimy coating which is found
(
)
on most underwater surfaces and has a brown to green coloration.
This organism is used as an indicator organism to help evaluate the-possible effects of plant operation on the local aquatic environment on the lowest level of the food chain.
l The. collection and analysis of periphyton samples was performed twice during the 1984 sample program.
i The first collection of periphyton was completed on June 29, 1984 j
and the second collection was completed on September 12, 1984. The gamma spectral analysis of periphyton samples showed detectable 3
i concentrations of Cs-137, Be-7, Th-228 and K-40.
The four radio-nuclides detected in periphyton samples can be attributed to several l
sources. Each of the radionuclides detected can be placed in one of i
three groups.
The first group of radionuclides is the result of plant operation.
The second group of radionuclides is naturally occurring and is found in many living organisms as noted throughout this report. The third group of radionuclides is the result of past atmospheric nuclear weapons testing.
Radionuclides with relatively i
long half-lives which fall into this third group are the result of l
atmospherie tests conducted over the past decades. The only fallout related radionuclide detected in 1984 periphyton samples was Cs-137.
Cs-137 requires special consideration as this radioisotope of cesium is a common constituent of the background radiation due to fallout but
)
can also be attributed to the operation of the plant.
In 1981 six i
fallout radionuclides were detected in the periphyton samples.
Of i
the six radionuclides detected in 1981, two, Ce-144 and Cs-137, were detected in 1982, and one, Cs-137, was detected in the 1984 sam-ples.
The other fallout radionuclides were not detected in 1982-84 2
l because of their short half-lives (3.5 days to 368 days) which re-l su'ted in their decaying away to concentrations below that of the lower limits of detection (LLD) and as a result of ecological cycling.
The first set of periphyton samples collected on June 29, 1984 con-
)
i tained detectable concentrations of Be-7, K-40, Cs-137, and Th-228.
I The maximum detectable concentration for plant related radionuclides was 0.29 pC1/g (wet) for Cs-137.
Cs-137 was detected in both the control (offsite) sample and the two indicator (onsite) samples with the maximum concentration, as noted above, present in the indicator l
sample.
l 63 A.
1 The second collection of periphyton samples completed on September 12 showed a slight increase in the concentration of plant related radionuclides. The maximum detectable concentration of plant related radionuclides in the second or summer collection was 0.31 pCi/g (wet) for Cs-137.
Cs-137 was not detected in the second collection at the control location as it was in the first collection (June 1984).
i The concentration of Cs-137 at the control location was less than 0.064 pCilg (wet) LLD.
Three naturally occurring radionuclides were detected in the 1984 samples. K-40 was detected in all six samples both onsite and off-site.
Be-7 was detected in two onsite samples and one offsite sample.
Th-228 was detected in two of the onsite samples.
The concentration of the naturally occurring radionuclides was consistent with levels detected in previous years' samples.
A general increase in the concentrations of radionuclides in the second or late summer collection compared to the June collection was noted for the 1984 samples at the indicator locations.
A similar increase in concen-tration in samples collected in late summer was also noted in 198';,
1981,1982, and 1983. This increase in sample concentration may be due to the higher metabolic rate or increased growth of the periphy-ton community between the first and second collections. The Cs-137 detected in the 1984 samples were trace amounts and are attributed to both plant effluents and past weapons testing.
A dose to man calculation from the level of activity found in lake periphyton samples in the vicinity of the plant is difficult to make as periphytor. is not directly in the human food chain. To best deter-mine tha resulting dose to man from the activity found in periphytan samples, calculations were made based on concentrations found in 11sh samples as fish represent the upper level of the food chain in j
which periphyton is a primary producer.
Dose to man calculations based on concentrations found in fish and consumption rates are contained in Section V.5.
A review of past data shows Cs-137 concentrations in both indicator and control periphyton samples decreased slightly since the 1983 samples.
Graphs depicting concentrations of Cs-137, Co-60, and 4
Ce-144 are presented in Section VII.
i l
i l
64
- ~ - - -
L 2.
BOTTOM SEDIMENT - TABLE 2 Bottom sediment samples were collected twice during the 1984 sam-pling program.
Gamma spectral analyses and Sr-90 analyses were performed on each of the six samples and the results are presented in Table 2.
Samples were collected in June and October in 1984 with the Oswego Harbor area (transect [00]) serving as the control loca-tion, Nine Mile Point Plant (transect (02]) and the FitzPatrick Plant (transect (031) serving as the indicator or onsite sample locations.
l Sr-90 was detected in each of the six 1984 samples.
Cs-137 was detected in four of the six samples collected in 1984, which included three onsite samples and one offsite sample.
Co-60 was detected in 1
two of the six samples and Mn-54 was detected in one of the six 1984 j
samples.
The presence of Cs-137 in the lake bottom sediment can be attri-buted to the accumulation of fallout in the aquatic environment as a result of the detonation of nuclear devices in the atmosphere.
The 4
origin of Cs-137 in atmosphere testing can be demonstrated by sam-j pie results which show the presence of Cs-137 in control location i
sediment samples. The Cs-137 concentration for the control location was 0.42 pC1/g (dry). The Cs-137 concentrations for the indicator j
locations ranged from 1.08 pC1/g (dry) to 0.04 pC1/g (dry) with a mean concentration of 0.49 pCi/g (dry).
Co-60 was detected in two of the four indicator samples collected in i
1984.
Positive detections of Co-60 ranged from a minimum of 0.12 pC1/g (dry) to a maximum of 0.17. pCi/g (dry). The detected levels of Co-60 are relatively the same as the concentrations detected in 1983 when the minimum concentration was 0.10 pC1/g (dry) and the maximum value was 0.16 pC1/g (dry).
The detection of Co-60 in sediment can be attributed to the operation of the plant. Co-60 was not detected in the control samples collected in 1984. The levels of Co-60 detected in the onsite samples are very small, and are near the lower limits of detection.
l
. Manganese-54 was detected in only one of the four indicator samples collected in 1984. The one positive detection was made at the Fitz-Patrick (03) transect. The Mn-54 concentration for this one indicator j
location was 0.04 pC1/g (dry).
The detection of Mn-54 in sediment can be attributed to the - operation of the plant.
B!n-54 was not detected in the control samples collected in 1984. The average LLD 4
value for the control location was less than 0.04 pCI/g (dry) LLD.
Thus, as can be seen from above, the Mn-54 concentration detected in the one onsite sample is very small, and at the lower limits of detection.
Strontium-90 was detected in all of the six Bottom Sediment samples collected in 1984. The presence of Sr-90 at the control and indica-4 l
tor locations is considered to be the result of weapons fallout.
j Sr-90 was also detected at both control and indicator sample locations
}
65
-.,--__-,-,-,,.L,.,a.e
,_-,.,A,--,,.
_,.-,,_.n..
..-n,-_n,
during 1978, 1979, 1980, 1981, and 1983, which is evidence that Sr-90 is attributable to weapons testing fallout.
The mean 1984 control concentration for Sr-90 was 0.047 pC1/g (dry).
The mean 1984 indicator concentration for Sr-90 was 0.038 pCi/g (dry).
Variations in Sr-90 concentrations can be influenced by several factors including sediment type and chemical make-up. The presence of Sr-90 in many of the other control samples supports the fact that Sr-90 is ubiquitous throughout the environment.
The dose to man from bottom sediment is not of concern and cannot I
be directly calculated. Bottom sediment is not accessible to man and the radioactivity found in the sediment is shielded by the overlaying water column.
To illustrate the impact of radioactivity in sediment samples with respect to the dose to man concept, the assumption can be made that at some future time bottom sediment could be intro-duced into the shoreline sediment through re-suspension and depost-tion. Assuming that the density of the sediment is 40 kg/m8 (dry) and using the average residence time on the shore of 47 hours5.439815e-4 days <br />0.0131 hours <br />7.771164e-5 weeks <br />1.78835e-5 months <br /> per year for a teenager, the annual dose rate from a maximum indicator sample Cs-137 concentration of 1.08 pC1/g (dry) is calculated to be 0.0085 mrem per year whole body dose. The whole body dose from a Co-60 concentration of 0.17 pCi/g (dry) would be equal to 0.0054 mrom per year. The whole body dose from a Mn-54 concentration of 0.04 pCi/g (dry) would be equal to 0.0004 mrem per year. The re-sulting total whole body dose would be equal to 0.0143 mrom per year whole body. The contribution to the total whole body dose due to Sr-90 would be infinitesimal due to the fact that Sr-90 decays by a beta emission and has no associated strong gamma energy.
A review of past Cs-137 data illustrates that the mean concentration values for the indicator stations have dropped significantly from 1976 to 1979 with the general trend downward continuing from 1979 through 1982.
The 1984 mean concentration of Cs-137 was slightly higher than the 1983 value. Since 1979, the mean value for the con-trol station has been greater than the indicator stations with 1982 showing a change in the downward trend for Cs-137 concentrations at the control locations. However, the 1983-84 concentrations show a reverse in this situation.
This change in trending for the Cs-137 concentrations may be the effect of the control location's close prox-imity to the Oswego River Outlet and a possible source of Cs-137 from deposition of Cs-137 from atmospheric nuclear testing onto the river watershed.
The concentration of Co-60 in sediment samples has shown a similar downward trend to that of Cs-137 since 1977.
The maximum Co-60 concentration in the indicator samples (mean) shows a consistent downward trend since 1977 that continued I
through 1981 with a slight increase in mean concentrations for 1982, and a leveling off for 1982-84. This increase is not significant and is within the bounds of statistical variation.
Historical trends for concentrations of Cs-137 and Co-60 are presented in graphic form in j
Section VII.
I 66
w.
[
l 3.
E10LLUSK SAMPLES - TABLE 3 A total of six mollusk samples were collected in 1984 from a total of three general locations.
Each sample was analyzed for gamma emit-ters using gamma spectral analysis and for Sr-90 using chemical sep-arations and beta particle analysis. The results of the 1984 samples i
are presented on Table 3.
As in past years the effort to collect mollusk samples of sufficient size has been of limited success in terms of sample volume collected. The collections in 1984 were pro-i ductive and resulted in sample volumes in the 500 gram range which in some cases resulted in good sensitivities for the gamma spectral analysis, in particular for the indicator samples.
Mollusk samples were successfully collected at the offsite (00) or control location and j
at the Nine Mile Point Plant (02) transect and the FitzPatrick (03) j transect, for the indicator samples.
I The results of the isotopic analysis of mollusk tissue detected the i
presence of six radionuclides.
The nuclides detected consisted of two naturally occurring radionuclides (K-40 and Ra-226), three plant related radionuclides (Mn-54, Co-60, and Cs-137), and one radionu-I clide related to fallout from atmospheric nuclear testing (Sr-90).
Detectable concentrations of Sr-90 were measured in each of six sam-pies collected at both the onsite and offsite locations. The presence of Sr-90 in all the mollusk samples collected for the sample year was also observed in 1979,1980,1981,1982, and 1983. The 1984 Sr-90 concentrations ranged from a maximum of 0.13 pC1/g (wet) to a mini-
{
i mum of 0.009 pCi/g (wet) with the control station mean equal to 0.020 pC1/g (wet) and the indicator mean equal to 0.061 pC1/g (wet). As in other sample media the presence of Sr-90 is considered to be the result of fallout from atmospheric nuclear testing.
This determination is based on the fact that Sr-90 is consistently detected j
in control samples in previous years as noted above.
Mn-54 was detected in each of the four onsite or indicator samples collected in i
1984.
Co-60 was detected in three of the four onsite samples, and Cs-137 was detected in only one of the onsite samples.
The pres-i ence of Mn-54 and Co-60 in mollusk tissue can be attributed to the operation of the plant.
The Cs-137 present in the mollusk tissue j
may also be attributed to the operation of the plant and/or fallout i
from atmospheric nuclear testing.
The Mn-54, Co-60, and Cs-137 I
were not detected at the offsite or control locations.
j The concentration of Mn-54 detected at the indicator locations ranged from a maximum of 0.11 pC1/g (wet) to a minimum of 0.06 pCi/g (wet).
Co-60 concentrations ranged from a maximum of 0.115 pC1/g 7
(wet) to a minimum of 0.040 pC1/g (wet). The one positive detection for Cs-137 was 0.022 pCi/g (wet).
l The relatively high frequency for the detection of Co-60 and partic-l ularly Mn-54 in mollusk samples can be attributed to the phenomenon l
of bicaccumulation or concentration factors. The level of an element in a particular organism relative to the level or concentration of the same element in the organism's environment is known as the concen-67
.y h...,,mr----..-m.q-,,
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, - - -... - -.. - ~... - - - - -, -, -
ry
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tration factor.
Fresh water mollusk have an extremely high concentration factor of 300,000 (mean) for Mn-54 and 32,408 (mean) for Co-60*.
Such high concentration factors would result in a rapid accumulation of manganese and cobalt activity in mollusk that are in-digenous to the off shore area of the site.
Fresh water mollusk found in the vicinity of the site are not con-sumed by humans and are not a major component or level in the food ct.ain if for no other reason other than the small population due to 4
the unfavorable physical makeup of the lake bottom in the area.
Because these fresh water mollusk are not considered edible there is l
no dose to man from the presence of the Mn-54, Co-60, or Cs-137 i
concentrations.
As in past years an estimate can be made -using l
substituted parameters for the purpose of putting into perspective i
the possible significance of Mn-54, Co-60, and Cs-137 concentrations I
detected in the mollusk samples.
Using the average individual consumption of seafood of 1.0 kg/ year for an adult, the dose result-
)
ing from ingestion of mollusks would be 0.00016 mrom/ year to the whole body and 0.0015 mrem / year to the gastrointestinal tract for the maximum Mn-54 concentration of 0.11 pCi/g (wet).
The dose resulting from the Co-60 concentration of 0.115 pCi/g (wet) would be 0.0005 mrom/ year to the whole body and 0.0046 mrem / year to the gastrointestinal tract.
The dose resulting from the Cs-137 concen-a tration of 0.022 pCilg (wet) would be 0.0016 mrem / year to the whole body and 0.00005 mrem / year to the gastrointestinal tract. The total 1
maximum dose that would be received from the consumption of 1.0 kg of fresh water mollusk would be 0.00226 mrom to the whole body and 0.00615 mrom to the gastrointestinal tract.
This calculated dose is j
extremely small and as noted above in reality would be equal to no l
dose, because of the zero consumption rate.
The concentrations of Mn-54 and Co-60 have shown a significant i
decline since 1976 when both radionuclides were detected at their maximum level.
The concentration of Mn-54 detected in the 1984 1
samples shows a slight decrease from the *083 values.
The Co-60 concentration in the indicator samples showed a small increase from i
the levels detected in 1983. Co-60 concentrations in mollusk samples i
have remained relatively constant since 1977.
Sr-90 concentrations in mollusk samples have remained stable since 1978 after a peak in 1976, with little change in the 1984 samples.
Graphs cf previous j
mollusk sample results for Mn-54, Co-60 and Sr-90 are pre 7ented in i
Section VII. Also found in Section VII is a physical description of i
the lake bottom in the vicinity of the site for reference to the suit-l ability of the area for mollusk habitat.
i l
' Eisenbud (1973) l I
l 68
?
\\
4 i
l 4.
GASBfARUS - TABLE 4 GAaBTARUS samples were collected three times during the 1984 sam-ple period in conjunction with mollusk, periphyton and bottom sediment.
GAMMARUS are benthic or demersal dwelling organisms found in the general vicinity of the site and throughout Lake Ontario. GAMMARUS are sampled as an indicator organism whose major predator is the local fish population. GAMMARUS are generally found in periphyton and cladophora growth areas and are limited in their territorial ranges.
Samples were collected at the control (00) 1.
location and at the NMPP (02) and JAF (03) transects. Sample col-lections were made over a two week period (or longer) in order to collect sufficient quantities of sample for 1ceptable analyses.
The first collection of GAMMARUS in the sp:Ing of 1984 (June 14,'
1984 through June 29, 1984) y1Cded sample weights of only 1.7 g,
. l i
0.2 g, and 0.3 g respectively for the Oswego, NMPP, and JAF tran-j sects.
It should be noted that GAMMARUS are normally less than 10 mm in size and require a large numcer to obtain a biomass of one gram of sample. The spring collection of GAMMARUS is also usually impeded by the cold lake water temperatures resulting in few GA315fARUS inhabiting the shoreline shallows.
These small sample weights were insuffielent for Sr-89 and' Sr-90 analysis, and yielded high analytical sensitivities for gamma spectral analysis.
The JAF sample resulted in sensitivities of less than 12.0 pC1/g (wet) for Co-60 and less than 11.0 pCi/g (wet) for Cs-137.
The NMPP sample resulted in sensitivities of less than 18.0 pCi/g (wet) for Co-60 and less than 17.0 pCilg (wet) for j
The control sample (Oswego) resulted "n sensitivities of i
j less than 4.4 pC1/g (wet) for Co-60 and less than 5.0 pC1/g (wet) l for Cs-137.
Because of the small quantities collected in the spring GAMMARUS i
collection, which were insufficient for Sr-89 and Sr-90 analysis, l
another sample wps attempted before the late summer collection.
This resample GAf!!,fARUS collection started on July 16, 1984 and ended on August 17, 1984. This collection yielded sample weights of 70.8 g, 57.5 g, and 52.6 g respectively for the NMPP, JAF, and Oswego transects.
These sample weights were sufficient for good analytical sensitivities.
This resample collection showed measurable 3
concentrations of K-40 and Sr-90 only.
K-40 was detected in all three of the sample locations. K-40 is a naturally occurring radio-nuclide.
4 Strontium-90 was also detected in each of the samples collected in both the indicator and control samples. As noted previously, similar l-detections of Sr-90 were made in mollusk samples.
Strontium-90 is considered to be a background radionuclide because its origin is not i
related to the operation of the plant, but is attributed to fallout from atmospheric nuclear testing.
1 69
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,,-.,ma_.ww---,,--r,,,.,,,,,,,,...%,,-.-4
.--,--,--,,,w-
The analyses of the resample GAMMARUS collection showed no mea-surable concentrations of Co-60, Cs-134, Cs-137 or any other plant related radionuclides.
The late summer (August 8,1984 through September 11,1984) col-4 lection of, GAMMARUS also provided sufficient quantities of this organism for good analytical sensitivities. The late summer collection again only showed measurable concentrations of K-40 and S r-90.
Both K,40 and Sr-90 were detected at all three sample locations.
The analyses of the late summer GAMMARUS samples also showed no measurable concentrations of Co-60, Cs-134, Cs-137 or any other I
plant related radionuclides.
l j
The absence of plant related radionuclides in GAMMARUS samples collected in 1984, and the lack of detectable concentrations from the i
previous years of 1980, 1981 (second collection only), and 1982 indicate that the presence of these nuclides in GAMMARUS organisms is not routine nor chronic.
The dose to man as a direct result of j
concentrations of cobalt and cesium would be zero as GAMMARUS is not consumed by man.
The importance of the activity in these j
organisms is only significant with respect to the passage of any i
radionuclides through the food chain to a trophic level which may impact man.
Historical data for GAMMARUS sample results shows that the Sr-90 i
concentration for the control location has steadily decreased since
^
1977 and seems to be leveling off. The Sr-90 concentration for the indicator locations also shows a downward trend and leveling, except for a peak in 1980. No definite trend can be determined for Cs-137 concentrations, however, as positive detections have been random in past years. ~ Previous GAMMARUS data (Cs-137, Sr-89, Sr-90) is presented in Section VI, HISTORICAL DATA.
1 1
l 1
i 4
70
5.
FISH - TABLE 5 A total of 18 required fish samples were collected in the spring sea-son (June 1984) and in the fall season (October 1984). Collections were made utilizing gill nets at one offsite location greater than five miles from the site (Oswego Harbor area), and at two onsite locations in the vicinity of the Nine Mile Point Unit #1 (02), and the James A.
FitzPatrick (03) generating facilities.
The Oswego Harbor samples served as control samples while the NMP (02) and JAF (03) samples served c.s indicator samples.
Samples were analyzed for gamma I
emitters, Sr-89, and Sr-90.
Data is presented in the ANALYTICAL RESULTS section of the report on Table 5.
Analysis of the 1984 fish samples contained 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). Detect-l able concentrations of K-40, a naturally occurring radionuclide, were also found in all fish samples collected for the 1984 program.
Spring fish collections were comprised of two separate species and nine individual samples.
The two species represented one feeding type.
Lake trout and brown trout are highly predacious and feed cn 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 feeder species were col-lected in the spring samples.
Cs-137 was detected in all onsite and offsite samples for both species collected. Onsite samples showed Cs-137 concentrations to be slightly greater than control levels for some samples and slightly less than control levels for other samples.
The concentrations detected are not significantly different from the control results and are therefore considered background.
Cs-137 in lake trout samples ranged from 6
l 0.033 to 0.037 pC1/g (wet) and averaged 0.035 pC1/g (wet) for the indicator samples.
Cs-137 in the control sample was 0.037 pC1/g (wet) for lake trout.
Cs-137 in brown trout samples ranged from 0.039 to 0.055 pCi/g (wet) and averaged 0.046 pCi/g (wet) for the indicator samples.
Cs-137 in the control samples ranged from 0.031 i
to 0.032 pCi/g (wet) and averaged 0.032 pC1/g (wet).
K-40 was detected in all of the spring samples collected. K-40 is a naturally occurring radionuclide and is not related to power plant operations. Detectable concentrations of K-40 in the indicator sam-pies (lake trout and brown trout) ranged from 3.6 to 3.4 pCi/g (wet) and 2.4 to 3.3 pCi/g (wet) for the control samples. No other radionaclides were detected in any of the spring fish samples.
Fall sample collections were comprised of three separate species and nine individual samples. Three samples of lake trout, three samples of smallmouth bass, and three samples of white sucker were collected at a combination of two onsite sample locations (Nf.!P and JAF) and 71
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1 one offsite sample location (Oswego Harbor area).
Samples were
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collected by gill not in October.
4 i
l Cs-137 vas detected in all nine samples including the three control j
samples. The detected concentrations were not significantly differ-2 ent from one another because of the extremely small quantities detected.
Cs-137 in lake trout samples at the indicator locations ranged trom 0.035 to 0.045 pC1/g (wet) and averaged 0.040 pC1/g (wet).
The one lake trout sample from the control location had a Cs-137 concentration of 0.037 pCi/g (wet).
Cs-137 in smallmouth bass samples at the indicator locations ranged from 0.049 to 0.061 pC1/g (wet) and averaged 0.055 pCl/g (wet). The one small-mouth bass sample from the control location had a Cs-137 concentra-tion of 0.038 pC1/g (wet).
Cs-137 in the white sucker samples at t
the indicator locations ranged from 0.039 to 0.039 pC1/g (wet) and J
averaged 0.039 pC1/g (wet). The one white sucker sample from the l
control location had a Cs-137 concentration of 0.015 pC1/g (wet).
l K-40 was detected in all of the fall fish samples collected. Detect-able concentrations of K-40 in the indicator samples (lake trout, smallmouth bass, and white sucker) ranged from 2.7 to 3.5 pC1/g i
(wet) and 3.1 to 3.4 pC1/g (wet) for.the control samples. No other radionuclides were detected in any of the fall fish samples.
i Sr-89 and Sr-90 concentrations for the spring and fall fish samples j
were all less than the minimum detectable level.
St-89 and Sr-90 were not detected in any of the onsite or offsite locations.
I" Review of past environmental data indicates that the Sr-89 and Sr-90 i
concentrations have decreased steadily since 1976 for both the indi-cator and control locations to the present 1984 LLD levels.
A l
4 general decline in detectable Sr-89 and Sr-90 results is most prob-ably due to the result of the incorporation of these radionuclides 4
with organic and inorganic substances through ecological cycling. In addition, Sr-89 has a relatively short half-life of 52 days.
l The mean 1984 Cs-137 concentrations have decreased slightly from 1981 for the indicator samples and significantly fmm 1980 to 1976.
Concentrations for these samples decreased from a level of 1.4 pC1/g (wet) in 1976 to a level of 0.043 pCi/g (wet) in 1984 Control sample results have also decreased from a level of 0.12 pCi/g (wet)
I in 1976 to a level of 0.032 pCilg (wet) in 1984.
Results from 1979 I
to 1984 have remained fairly consistent.
As noted for Sr-89 and Sr-90 above, the general decreasing trend J
for Cs-137. is most probably 'a result of ecological cycling. A signift-cant portion of Cs-137 detected since 1976 in fish is a result for weapons testing fallout, and the general downward trend in concen-trations will continue as a function of ecological cycling and nuclear decay.
72 g-
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-,w
,-mi
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-. ~.__ -
t 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 estimate of dose to man can be calculated.
Assuming that the average adult consumes 6.9 kg of Ssh per year (Regulatory Guide 1.109) and the Sah consumed contains an average Cs-137 concentration of 0.043 pC1/g (wet) (annual mean result of indicator samples for 1984), the whole body dose received would be 0.021 mrom per year. The criti-cal organ in this case is the liver which would receive a calculated I
dose of 0.032 mrem per year.
No doses are calculated here for Sr-89 and Sr490 since these radioisotopes of strontium were not detected during 1984.
The Cs-137 whole body and critical crgan 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 location 'as well. In this case the consumption rate is assumed to remain the same (6.9 kg per year) but the average annual Cs-137 mean concentration for the con-l trol samples is 0.032 pC1/g (wet). The calculated Cs-137 whole body dose is 0.016 mrem per year and the associated dose to the liver is l
0.024 mrem per year.
In summary, the whole body and critical organ doses observed as a result of consumption of fish is small.
Doses received from the i
i consumption of indicator and control aample f!sh are approximately i
the same with the dose from control samples being slightly lower.
Doses from both sample groups are considered in the range of back-ground exposure rates.
Graphs of past Cs-137 and Sr-90 concentration can be found in Sec-tion VII.
l l
l I
73 e ne.esta
+e v t'
e
,r.
6.
LAKE WATER - TABLES 6. 7. AND 8 1984 lake water samples were analyzed monthly for gross beta and gamma emitters (using gamma spectral analysis).
Sr-89, Sr-90, and tritium analyses were performed quarterly. Quarterly samples (i.e.,
Sr-89, Sr-90, and tritium) were composites of monthly samples.
The analytical results for the 1984 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 #1 and James A. FitzPatrick facilities. The control location samples were collected at the City of Oswego water treatment plant and consisted of raw lake water prior to treatment.
The gross beta annual mean activity for the, indicator sample loca-tions, Nine Mile Point Unit #1 and the James A. Fit: Patrick inlet canals (3.98 pC1/11ter), was slightly higher than the 1983 mean inlet canal results (3.34 pC1/11ter).
The Nine Mile Point Unit #1 canal samples were greater than the control samples for eight of the 12 monthly samples analyzed and ranged from 2.20 pCi/ liter to 5.30 pC1/11ter. The James A. FitzPatrick canal samples were greater than the control samples for seven of the 12 monthly samples analyzed and ranged from less than 2.2 pC1/ liter to 5.90 pCilliter.
The control sample results ranged from 2.40 pCi/ liter to 5.20 pCi/ liter.
The fluctuation in the gross beta canal sample results is. due to the natural variation in concentration of naturally occurring radio-nuclides.
A reduction in gross beta activity since 1974 is primarily the result of improved analytical procedures and equipment and not necessarily to changes in plant operations.
Although the past elevated gross beta concentration may be due in part to past weapons testing, it is difficult to determine what portion was due to improved instrumenta-tion and what part was due to weapons testing. There were no sig-nificant changes or trends in gross beta activity on a monthly basis for 1984. (See historical data graphsSection VII.)
Gamma spectral analysis was performed on 36 monthly composite sam-ples required by the Environmental Technical Specifications.
Only one radionuclide was detected in the inlet canal samples.
This radionuclide is naturally occurring and not plant related.
K-40, a naturally occurring radionuclide, was detected intermittently in both intake canals and the raw city water supply.
K-40 was detected in two of the 12 monthly inlet canal samplas at the James A.
FitzPatrick inlet canal and ranged from 7.2 to 13.2 pCi/ liter.
The Nine Mile Point Unit #1 inlet canal samples also showed K-40 detected in two of the 12 monthly samples.
The concentrations ranged from 14.4 to 14.5 pCi/11ter.
K-40 in the Oswego city water supply was detected in four of the 12 monthly samples, and ranged from 7.6 to 15.0 pC1/11ter.
I i
74
-...,y r
--r e, ---
e
I l
Quarterly samples for Sr-89 analysis were composites of the monthly samples. Sr-89 was not detected in any of the water samples taken from the City of Oswego water treatment plant, the James A. Fitz-Patrick inlet canal, or the Nine Stile Point inlet canal.
The lower limit of detection values for the City of Oswego water treatment plant canal samples (control location) ranged from less than 1.10 pCilliter to less than 2.00 pCi/ liter (LLD). The lower limit of detection val-ues for the indicator (James A. FitzPatrick inlet canal and Nine Stile Point inlet canal) locations ranged from less than 1.20 pC1/11ter to less than 2.00 pCf/ liter (LLD).
Quarterly samples for Sr-90 analysis were composites of the monthly samples as noted for the Sr-89 analysis. Sr-90 was detected in two of the four quarterly composites at both the James A. FitzPatrick and Nine 5 tile Point Unit #1 inlet canals. Sr.90 was detected in only one of the four quarterly composites at the City of Oswego water 4
treatment plant or control location.
At the control location, the l
Sr-90 concentration was 0.72 pCi/ liter. Sr-90 in the Nine 5111e Point inlet canal samples ranged from 0.56 to 1.30 pCi/ liter and showed a l.
mean value of 0.93 pCilliter.
The James A. FitzPatrick inlet canal samples showed Sr-90 ranging from 0.80 to 0.86 pC1/11ter and a mean i
value of 0.83 pC1/ liter.
Sr-90, as detected in the 1984 water sam-i ples, is considered to be background Sr-90 as a result 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 six of the eight indicator samples and two of the four control samples. The City of Oswego water treatment plant showed tritium concentrations ranging from 190 pCi/ liter to 220 pCi/ liter with a mean of 205 pCi/ liter.
Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 110 pCilliter to 370 pC1/ liter and showed a mean concentration of 280 pC1/ liter.
Inlet canal samples taken at Nine Bfile Point showed tritium concentrations ranging from 230 pC1/11ter to 340 pCi/ liter. The annual mean concen-tration was 285 pCi/ liter.
Evaluation of past environmental data shows that gross beta concen-trations in water samples have decreased significantly since 1977 at both the indicator sample locations (inlet canals) and at the control location (Oswego city water).
As noted previously, however, the decrease is primarily a result of superior analytical instrumentation.
Since 1978, gross beta levels have remained relatively constant at l
both indicator and control locations. Indicator annual means ranged q
from 15.8 pCi/ liter in 1977 to 41.8 pCi/ liter in 1976. For the period of 1978 through 1983, annual means ranged from 2.73 pCi/ liter (1982) to 4.53 pCi/litar (1978). The indicator annual mean for 1984 was 3.98 pCi/ liter.
Control annual means also were relatively high i
during 1975 to 1977. During these years, the concentrations ranged i
form 45.33 pC1/ liter (1975) to 10.9 pC1/ liter (1977). Data from 1974 for the control location was deleted from this comparison because of questionable results. For the period 1978 through 1983, annual mean i
75
~
~.
y
.-,y r..
,.,p,
,,y
.,,-,,.7 g
..y
l gross beta concentration ranged from 2.42 pCi/ liter (1982) to 3.55 pC1/ liter (1978).
The control annual mean for 1984 was 3.41 pCi/11ter.
Review of previous data for Sr-89 demonstrates that results have been variable since 1975.
Sr-89 for the indicator samples has ranged from not detected (1976,1977,1979,1983, and 1984) to 0.78 pC1/ liter (1981) and has been at relatively constant levels when detected. At the control locations, Sr-89 ranged from not detected (1975-1978, 1981, 1983, and 1984) to 1.4 pCi/ liter (1980).
During 1984, Sr-89 showed an annual mean of less than 1.60 pCi/ liter (LLD) at the control location and less than 1.68 pCi/ liter (LLD) at the indicator location.
S r-90 annual means have remained relatively consistent at both indicator and control sample locations since 1975.
11ean results for the indicator samples ranged from not detected (1975 and 1976) to 1.08 pCi/ liter (1982). Stean results at the control sample location ranged from not detected (1975-1978) to 2.04 pC1/ liter (1982). The 1984 annual mean Sr-90 results for the indi-cator semples and control samples were 0.88 pCi/ liter and 0.72 pCi/ liter respectively.
Previous annual mean results for tritium at the indicator sample location has decreased slightly since 1976, with the exception of 1982.
Sample results were available since 1974 through 1984 and showed a peak value of 641.0 pC1/ liter (1982) and a minimum value of 234.0 pCi/ liter (1979).
The annual mean tritium result at the indicator locations for 1984 was 282.0 pCi/ liter.
This is a slight decrease from the value detected in 1983 (317.0 pCi/ liter).
Mean tritium results at the control location have also decreased slightly since 1976.
Stean annual results were available for 1974 through 1984.
These results show that tritium at the control loca-tion ranged from not detected (1974) to 651.7 pCi/ liter (1976). The annual mean tritium result at the control location for 1984 was 205.0 pCilliter.
This is a slight decrease from the 1983 value of 250.0 pC1/ liter. The fact that tritium is a naturally occurring radioactive isotope of hydrogen which is produced in the upper atmosphere by cosmic radiation, as well as a product of reactor operation, accounts for the background level in the lake to vary slightly from year to year.
The impact, as expressed by a dose to man, is not assessed here since the primary pathway, in this case, is drinking water.
The nearest source for drinking water is the City of Oswego water treat-ment plant which is the control location for the sampling program.
The results of the control location are consistent with previous years' results and are representative of normal background radionu-clide concentrations in lake water and regional drinking water that might be affected by the site.
Previous Lake Water data (tritium, Sr-89, Sr-90, and gross beta) is presented in Section VI HISTORICAL DATA.
76
TERRESTRIAL PROGRAM Tables 9 through 20 represent the analytical results for the terrestrial samples collected for the 1984 reporting period.
i 77 es
=@
1.
AIR PARTICULATE GROSS BETA - TABLES 9 and 10 Tables 9 and 10 contain the weekly air particulate gross beta results for the six offsite and nine onsite sample locations. The samples are counted at a minimum of twenty-four hours after collection to allow for the decay of naturally occurring radionuclides with short half-lives.
A total of 312 offsite and 462 onsite samples were collected and analyzed during 1984. No sig:lificant levels of gross beta activ-ity were observed in any of the samples.
The offsite or control mean concentration for 1984 was 0.026 pCi/m3 while the indicator or 2
onsite sample mean was equal to 0.025 pCi/m. As noted, the onsite mean is about five percent lower than the offsite mean for the same sample period.
This difference in mean concentration has been ex-hibited in the past 10 years with the exception of 1977 when a higher annual mean gross beta activity was observed for the onsite sampling stations.
In these 10 years, the control stations' annual mean ranged from a minimum difference of 5.0 percent higher than the indicator observed in 1984 to a maximum difference of 28.6 per-cent higher, observed in 1978.
The difference in offsite and onsite weekly and monthly mean values for gross beta could be the result of a combination of the many natural processes which can affect en-vironmental concentrations.
The most significant parameter that could possibly contribute to a depressed or lower concentration for the onsite stations would be location. The close proxicity of onsite sampling stations to the lakeshore (Lake Ontario) would account for lower concentrations of naturally occurring radionuclides being col-lected on the sampling media. Surface winds from off the lake would contain less particulate matter and airborne gases than surface winds from adjacent land areas.
The major component of gross beta con-centrations are decay or daughter products of uranium and thorium and potassium-40.
The concentrations of these nuclides in the ground level atmosphere are dependent upon the local geology and its chemical constituents.
Thus surface winds of terrestrial origin have a potential for containing higher concentrations of naturally oc-curring radionuclides.
The observed increases and decreases in general gross beta activity can be attributed to changes experienced in the biosphere.
As discussed above, the concentrations of the naturally occurring radio-nuclides in the lower limits of the atmosphere directly above the ter-restrial portion of the earth are affected by time related processes such as wind direction, snow cover, soil temperature and soil mois-ture content.
Very little change was noted in gross beta activity which corresponded with seasonal changes as has been observed in past years.
In general, gross beta activity in air samples has decreased signifi-cantly.
The mean 1984 concentration for both offsite and onsite is six times lower than the mean concentration detected in 1981. This overall reduction in activity is directly attributable to the increased activity detected in 1981 as a result of fallout from an atmospheric nuclear test and subsequent return to background levels in 1983-84.
78 e-
The trend of gross beta activity in the environment is that of re-duced concentrations.
The mean 1983 concentration (0.023 pC1/m3) was the lowest level of gross beta activity observed since sampling for the FitzPatrich program began in 1974. The mean 1984 concentra-tion (0.025 pCi/m8) showed a slight increase over the mean 1983 concentration, but this slight increase is within the bounds of statis-tical variation.
The general decrease of gross beta activity since 1974 could be the result of the reduction of atmospheric nuclear testing in recent years in comparison to the 1960's when such testing was prolific.
Graphs of air particulate gross beta concentrations.on a weekly and yearly basis can be found in Section VII.
79
2.
MONTHLY PARTICULATE COMPOSITES - TABLE 11 The air particulate filters collected weekly from each of the 15 air sampling stations are composited monthly by location (onsite/offsite).
Each composite is analyzed for gamma emitters using gamma spectral analysis.
The results for the 24 monthly samples analyzed for the 1984 pro-gram showed positive detections for four radionuclides.
Those radionuclides detected were Co-60 and Cs-137, in addition to Be-7 and K-40 which are both naturally occurring radionuclides.
The four radionuclides measured in the 1984 composite samples can be divided into two categories, the first category is naturally occurring radionuc' ices.
Be-7 was detected in each of the 24 composite sam-ples both onsite and offsite.
The mean value for Be-7 concentra-tions was 16 percent higher in the offsite composite samples than the onsite samples. Potassium-40 was detected in nine of the offsite and onsite monthly composite samples.
The offsite annual mean was 21 percent higher than the onsite annual mean for K-40.
The second category of radionuclides detected are those which are plant related.
Included here are Co-60 and Cs-137.
Cs-137 was included here due to the fact that the Cs-137 may be a constituent of plant effluents.
A review of 1984 Cs-137 sample data indicates
.i that Cs-137 is most likely the result of past weapons testing and subsequent environmental levels of Cs-137 from fallout.
Cs-137 was not detected in any of the offsite composite samples, but was de-tected in one of the onsite composite samples. The concentration of Cs-137 in this one onsite composite sample was 0.00018 pCi/m8 This i
can be compared to the LLD level of Cs-137 (less than 0.00018 pCi/m8) in the offsite composite sample from the same month. Co-60 was detected in three of the 12 onsite monthly composite samples and two of the 12 offsite monthly composite samples.
The onsite Co-60 concentrations ranged from a maximum of 0.00149 pCi/m3 in February to a minimum to 0.00054 pCi/m8 in March of 1984.
The mean Co-60 concentration for the onsite samples was c.00117 pCi/m3 The offsite Co-60 concentrations ranged from a maximum of 0.00107 pC1/m3 in January to a minimum of 0.00038 pCi/m3 in February of 1984.
The mean Co-60 concentration for the offsite samples was 0.00073 pCi/m*.
The presence of Co-60 has been noted in the past and can be a result of weapons testing, contamination during handling, and oper-ations at the site.
The detectable Co-60 concentrations found during the months of January through March of 1984 in both onsite and offsite composite samples was a result of contamination during handling.
The 1983 Annual Environmental Operating Report noted that during the month of December 1983, a marked increase in Co-60 concentrations was noted in both onsite and offsite composite samples.
The detected concentrations were inconsistent with operations at the site.
A review of plant gaseous effluent data for this period showed that the 80 O
~
Co-60 release rates were well within four percent of the design objective of the plant as outlined in Section 2.3.B.2 of the Environ-mental Technical Specifications.
These limits were consistent with past effluent rates when Co-60 was not detected.
Investigation of the ocurrence demonstrated that the unused particu-late filters were contaminated during handling prior to the installa-tion of the filters in the environmental monitoring stations (refer to the 1983 report for a more detailed account of the investigation).
The investigation concluded in early March of 1984 and corrective action was implemented at that time.
It was concluded in the 1983 report that the March 1984 composite samples and subsequent samples could confirm the conclusions of the investigation.
The results of the 1984 air particulate samples confirmed the results of the investi-gation.
During the months of January and February 1984, Co-60 was detected in both onsite and offsite composite samples. The concen-trations detected were comparable to the December 1983 results.
During March of 1984, Co-60 was detected only in the onsite compos-ites.
Co-60 was not detected in either onsite or offsite composite samples for the remainder of 1984 (April through December).
It is believed with reasonable confidence that the December 1983 and January through March 1984 positive results for Co-60 were the result of contamination during handling prior to installation in the environment.
Assessment of the presence of fission product radionuclides in air i
particulate composite samples can be depicted by calculating doses to man as a result of inhalation. Co-60 and Cs-137 were the two fission product radionuclides detected in 1984.
It was noted previously, however, that the presence of Co-60 was attributed to contamination during handling prior to actual field use.
For the purposes of illustration, however, dose calculations can be performed assuming i
that the Co-60 results were actual field measurements.
l Using the average adult inhalation rate of 8,000 m8/ year or 667 m3/ standard month (Regulatory Guide 1.109), and the mean con-centration measured at the onsite sample stations, the following yearly doses can be calculated based on the amount of time the ra-dionuclida was detected during the year:
Concentration No. Months Dose
- Nuclide (pCi/m8)
Detected Origin (mrem /yr)
Cs-137 0.00018 1
Fallout / Plant 0.0000001 Co-60 0.00117 3
Plant 0.0017465 Totals 0.0017466 Plant 0.0017465 Fallout / Plant 0.0000001 l
- Dose to the lung.
l 81
~
l
~
The above table illustrates that the average calculated dose to man from plant related radionuclides is very small and of little biological significance.
For the purpose of illustration, the significance of the above doses can be brought into perspective by a comparison to the average annual population lung dose received from the combustion of natural gas used in cooking ranges and unvented heaters. This average an-nual population lung dose ranges from 2'.0 mrem /yr to 5.0 mrem /yr (NCRP, No. 56).
This represents a dcse approximately 3,000 times greater than that received from plant effluents as noted above.
Graphic representations of air particulate composite Co-60 and Cs-137 concentrations for the year of 1984 and previous years are presented in Section VII.
I 82
~-'
~ ~
3.
AIRBORNE RADIOIODINE (I-131) - TABLES 12 AND 13 The results for Iodine-131 (charcoal cartridge) sampling and analyses are presented in Table 12 (Offsite) and Table 13 (Onsite).
During the 1984 sampling program airborne radioiodine was not de-tected in any of the 312 weekly samples collected from the six offsite sampling stations. In the 1,871. weekly offsite I-131 samples collected in 1979 through 1984, I-131 was only detected once (June 16, 1982).
Offsite I-131 detections were also made in 1977 and 1978.
1-131 was also not detected in any of the 464 onsite samples analyzed in 1984. I-131, however, has been detected in the past at the onsite sample locations. In the 2,805 weekly onsite I-131 samples collected in 1979 through 1984, I-131 was detected in only 22 samples.
The end result of the 1984 I-131 sampling effort showed no signifi-cant impact due to the operation of the pisnt.
Also during 1984, I-131 was not detected in any other environmental sample media including milk and green leafy vegetables.
l l
l l
83
,v w-
,,m, m
i 4.
TLD (ENVIRONMENTAL DOSIMETRY) - TABLE 14
)
TLD's were collected once per quarter during the sample year. The TLD results are an average of four independent readings at each lo-cation and are reported in mrem per standard month. In 1984, TLD's for the most part were collected approximately on March 31, 1984, June 30, 1984 September 28, 1984, and January 4,1985.
TLD results are organized into three groups for reporting purposes.
The groups are onsite TLD's (defined as TLD's in the immediate proximity of the individual facilit as, at points of interest), environ-mental station TLD's (a ring of TLD's surrounding the generating facilities as a group), and offsite TLD's (TLD's located off the site property or controlled area and ranging up to 20 miles from the site).
A net dose at the environmental station TLD's can be calculated sim-ply by subtracting the mean standard month offsite doses from the mean standard month onsite environmental station doses *.
Enviren-mental 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:
Quarter Net Environmental Station Dose **
1 0.63 2
0.52 3
0.52 4
0.29 The annual site property boundary dose for 1984 cannot be deter-mined 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 fo' 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.
Quarter Net Site Property Boundarv Dose **
1
- 0.08 2
- 0.59 3
- 0.18 4
- 0.49
- Location numbers 5, 6, 7, 23, 24, 25, and 26.
- Dose in mrem per standard month.
84
As observed, the site boundary dose based on two available TLD lo-I cations was less than the average offsite dose for each of the four l
quarters in 1984. This is probably due to the difference in grcund dose rates which are indicative of variable concentrations of natural-ly occurring radionuclides in soil and rock such as radium, uranium, thorium, and potassium. The difference could also result from sta-tistical variation in the TLD readings, as the site boundary dose is based on a population of only eight individual readings per quarter (two TLD's).
TLD numbers 31 and 39 are located within the Nine Mile' Point #1 re-stricted area near the radwaste facility and are influenced by the close proximity to the building. TLD numbers 27.through 30 and 47 are located within the restricted area of the James A. FitzPatrick l
radwaste facility and are influenced by the radwaste buildings. TLD l
number 59 is located new the restricted area of the FitzPatrick Plant stack and is influenced by the proximity to this structure.
TLD numbers 3 and 4 are located at the construction site of Nine Mile Point #2. TLD's are subject to radiography at the Unit #2 site and to a much lesser extent the FitzPatrick facility.
Offsite TLD results remained fairly consistent for most TLD locations each quarter. Any slight variations in natural background radiation levels that were observed are most probably a result of increasing or decreasing emission rates for radon and thoron gases emanating from the ground.
These ensission re,tes are related to ground moisture content and other natural parameters.
Onsite TLD results remained fairly consistent except for TLD's located near radwaste facilities which may be affected by the fre-quency of radwaste processing and shipment.
These TLD's include numbers 23, 24, 27, 28, 29, 30, 47. 48, and 61 at the James A.
FitzPatrick facility and number 39 at the Nine Mile Point #1 facility.
TLD numbers 3, 4, 41, and 62 are located at the Nine Mile Point #2 facility and were affected by the frequency of radiography at the i
construction site. Radiography is a common practice at construction sites in order to determine the quality of equipment welds such as pipes.
TLD's located in areas near radiography work will show fluctuating doses as the amount of radiography performed is not con-sistent.
TLD number 59 results were variable as a result of the operating mode of the James A. FitzPatrick facility.
This TLD is located near the James A. FitzPatrick facility exhaust stack.
The results of 1984 showed no detectable impact from direct radiation measured outside the site boundary.
85
5.
RADIATION MONITORS - TABLE 15 Environmental radiation monitors are located in 10 of the 15 air monitoring environmental stations.
Each of the onsite environmental monitoring stations contains a radiation monitor and, in addition, the C offsite monitoring station contains a similar monitor.* The radia-tion monitors consist of a GM detector with an associated power supply, c?. art recorder, and trip unit.
The monitor has an oper-ating 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.
- Due to repeated vandalism to C offsite environmental sampling station (the monitor detector was stolen several times), the radiation monitor was moved to D-1 offsite environmental sampling station on July 19, 1984.
i 86
s I
.t i
6.
MILK - TABLES 16,17, AND 18 Milk samples were collected from a combination of eight farms during the first two months of the 1984 grazing season, and from seven farms during the remainder of the 1984 grazing season and the following months of November and December. The grazing season is considered to be May through October. Two of the sample locations, numbers 5 and 45, were deleted from the milk sampling program as a result of the 1984 spring milch animal census. These locations were deleted in July.
Sample location number 60 was added to the milk sampling program in July as a result of the 1984 spring milch animal census. Sample location descriptions are IIstad below.
Location No.
Direction frem Site Distance from Site (miles)
J 4
ESE 7.7 5
SSE 7.2 7
ESE 5.5 16 S
8.2 55 E
9.0 60 E
9.5 i
Milk samples were collected from each of the locations in the.first half of the month and analyzed for I-131.
At approximately mid month, a second milk collection was made at the same locations. The second collection was composited with an equal aliquot from each location sampled during the first collection.
The composite samples were analyzed for gamma emitters and Sr-90.
I-131, gamma isotopic, and Sr-90 results are found in the analytical results section.
The gamma spectral analysis of the monthly composite samples showed K-40 to be the most abundant radionuclide detected in the milk sam-ples collected in 19E4. K-40 was detected in every sample analyzed and ranged in concentration from 1,840 pC1/ liter to 1,040 pC1/ liter at the indicator locations and 1,500 pC1/ liter to 1,190 pCi/ liter at the control location.
K-40 is a naturally occurring radionuclide and is found in many of the environmental medias sampled.
Sr-90 was also detected in all of the 58 milk samples coIIected during 1984. The mean Sr-90 concentration for the control location was 2.14 pCi/11ter.
The mean for all indicator locations (within 10 miles of the site) was 2.34 pCi/ liter. The control and indicator sample means are similar.
Sr-90 results for the indicator locations ranged from 7.60 pCi/ liter to 0.80 pCi/ liter. Control sample results ranged from 2.90 pCi/ liter to 1.30 pCi/ liter. The detection of Sr-90 in indicator and control locations at similar concentrations is indicative of back-ground Sr-90 as a result of past weapons testing.
87
. =
I 5filk samples were collected and analyzed. monthly for I-131.
Iodine-l 131 was not detected during 1984 in any of the indicator or control samples. All 1984 I-131 milk results are reported as LLD.
i Cs-137 was not detected in any of the 58 monthly samples analyzed in 1984.
Annual means for the detection of Cs-137 at all locations are presented below.
4 Location No.
Annual Mean (Cs-137) 4
<5.66 pCill (LLD) 5
<4.4 pC1/1 (LLD) 7
<6.3 pC1/1 (LLD) 16
<6.4 pC1/1 (LLD) 40 (control)
<6.0 pCi/l (LLD) 45
<4.5 pCi/1 (LLD) 50
<4.9 pCi/l (LLD) 55
<4.8 pC1/1 (LLD) 60
<5.4 pC1/1 (LLD)
Annual mean Cs-137 values for each sampling location are not signifi-cantly different from one another. Location number 40 (control loca-tion) showed no detectable Cs-137 during 1984.
This was also true for every indicator location.
However, Cs-137 has been routinely detected in the past.
Examination of previous Cs-137 levels in milk samples shows that the annual mean for the indicator samples has decreased steadily since 1974.
1976 did show a decrease (7.8 pC1/ liter) that was less than 1975 and 1977 (1975 was 20.6 pCilliter and 1977 was 17.1 pCi/ liter).
1974 through 1981 showed Cs-137 concentrations ranging from 26.1 pC1/ liter in 1974 to 7.57 pC1/ liter in 1981.
The indicator mean for 1984 was less than 6.3 pCl/ liter. Previous Cs-137 concentrations at the control location is only available from 1978 to 1983.
Concentra-tions range from 3.73 pC1/ liter in 1979 to 7.0 pCilliter in 1981. The mean control result for 1984 was less than 6.0 pCi/ liter (LLD re-sult).
No other radionuclides were detected in milk samples during 1984 using gamma spectral analysis.
Previous Sr-90 data from the indicator locations shows that the an-nual mean Sr-90 concentrations have decreased slightly since 1974.
Sr-90 ranged from 2.34 pCi/ liter in 1984 to 7.16 pC1/ liter in 1976.
The 1984 annual mean for Sr-90 was 2.34 pCl/ liter, which shows a slight decrease from the 1983 annual mean for Sr-90 of 2.81 pC1/-
liter.
Strontium-90 concentrations at the control location are only available since 1978.
The annual mean concentration ranged from 1.91 pC1/11ter in 1983 to 5.88 pCi/ liter in 1978.
The 1984 annual mean for Sr-90 (control location) was 2.14 pC1/ liter, and shows a slight increase from the 1983 annual mean for Sr-90 of 1.91 pC1/-
liter.
i l
i 88 s
m, -.
-c wmw----s
,e
--m 4
m,,-
-w,-e
l The impact as a result of Cs-137 in 1984 milk samples is insignificant since no Cs-137 was detected during the 1984 milk sampling program.
The impact, as a result of Sr-90 in milk, due to plant operation, is extremely small if any since the mean result of the indicator results and the control results are approximately equal considering Quctua-tions in the background levels.
The levels of Sr-90 detected in indicator as well as control samples is considered to be representa-tive of bar.kground concentrations.
In this regard, the resultant calculated doses would be approximately equal.
Iodine-131 was not detected in the 58 monthly milk samples analyzed for the 1984 program. No doses to man have been calculated due to the lack of positive detection.
The detection of I-131 in milk sam-ples has not been routine in the past.
In past sampling programs, I-131 has been detected in milk samples in conjunction with fresh fallout from atmospheric nuclear testing.
Graphs of yearly milk sample results for Cs-137, Sr-90 and I-131, along with monthly (1984) Cs-137 results by station, are presented in Section VII.
1 89 w,-m-,,-w-,-,--e-wy--,-m,,+
w-
O 7.
MILCH ANIMAL CENSUS - TABLE 19 The milch animal census is an estimation of the number of cows and goats within a 10 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 pre-vious milch animal owners and also by road surveys to locate any possible new owners.
Questionnaires not responded to are followed up by telephone calls.
The number of milch animals located within the 10 mile radius of the site was estimated to be 1,080 cows and three goats for the spring 1984 census.
One new location was found since the summer 1983 census.
The number of cows decreased by 133 and the number of goats increased by three with respec.? to the 1983 summer census.
The 1984 summer census showed a total of 1,064 cows and one goat.
No new locations were found since the spring 1984 census.
The number of cows decreased by 16 and the number of goats decreased by two with respect to the 1984 spring census.
l l
l 90 l
l
I 8.
HUMAN FOOD PRODUCTS - TABLE 20 Human food product samples were comprised of meat, eggs, poultry, and vegetables.
Collections for meat, poultry, and eggs were made in the spring and fall seasons. Samples of pmduce included vegeta-bles with an attempt to sample at least or 4 green leafy vegetable from each location. The collection of produce was performed in late summer or early fall.
Three indicator locations were sampled for each type of media collected, in addition, a control location was sam-pled during each collection period.
Indicator samples were collected within a 10 mile radius of the site in areas which would have a high potential for demonstrating possible effects of site operations.
The ultimate factor controlling sample locations was the availability of required samples. Attempts were made to maintain prior sample loca-tions where possible.
Meat Spring meat collections were made at one offsite location (greater than 10 miles from the site) and at three onsite locations (less than 10 miles from the site).
Spring meat collections showed detectable concentrations of K-40 in all samples.
K-40 concentrations ranged from 2.6 pC1/g (wet) to 3.7 pC1/g (wet). K-40 is a naturally occur-ring radionuclide. Only one of the four spring meat samples showed detectable concentrations of Cs-137. The detected Cs-137 concentra-tion was in the indicator or onsite sample.
The Cs-137 result for this sample was 0.046 pC1/g (wet).
Cs-137 was not detected in the control sample.
Cs-137 is detected in many environmental samples and is usually most prevalent in meat and fish, with respect to all the sample media collected.
Cs-137 in meat samples is essentially a result of past weapons testing.
Cesium is incorporated into meat tissue from feed sources. The results detected in the spring meat samples are very low concentrations and thus can appear in some samples and not in others. By review of the 1981 spring meat sample data, it is noted that Cs-137 appeared in the control samples (0.017 pCi/g (wet] and 0.024 pCi/g (wet]).
Cs-137 was also found in the control sample during 1980 (0.01 pCi/g [ wet]).
The one meat sample that showed a detectable concentration of Cs-137 (0.046 pCi/g (wet]) was slightly higher than the detected concentrations in control sample results during the spring of 1981.
Because this result (0.046 pCi/g (wet]) is small, the impact or dose as a result of this concentration is insignificant and is addressed below.
No other radionuclides were detected in the spring meat samples using gamma spectral analysis.
l Fall meat collections were made at one obsite and at three onsite sample locations. The fall samples showed detectable concentrations of K-40 in all samples. K-40 concentrations ranged from 2.6 pCi/g (wet) to 2.9 pCi/g (wet).
91
.n
-+~
so i
=
1 j
o 4
i Cs-137 was again only detected in one of the four fall meat samples.
The one meat sample that had a detectable concentration of Cs-137 i
was an indicator sample (less than 10 miles from the site).
The detectable concentration of Cs-137 was 0.032 pC1/g (wet) and can be i,
compared to the control sample result of less than 0.027 pCi/g (wet). This result is a very small concentration and, as noted above for the spring samples, is comparable to concentrations detected at control locations during 1981.
These 1981 samples showed control i
Cs-137 concentrations of 0.017 and 0.024 pC1/g (wet) respectively.
The impact of these small concentrations is discussed below.
No other radionuclides were detected in the fall meat samples using j
gamma spectral analysis.
The detection of Cs-137 in meat samples has been noted for all years since 1978 for indicator samples and since 1980 for control locations (control samples were not collected prior to 1980).
The detected concentrations since 1978 at the indicator locations have been fairly consistent. These samples ranged from 0.021 to 0.039 pC1/g (wet).
At the control locations, Cs-137 ranged from 0.01 to 0.021 pC1/g (wet). The indicator sample annual mean results have been slightly higher than the control sample annual mean results.
The historical detection of Cs-137 in meat at control and indicator sample locations is an indication of cesium production from weapons testing. During 1984. Cs-137 was not detected at the control sample locations although Cs-137 has been detected in the past (1981 for example) at control sample locations.
As noted above, the concen-trations 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).
1
{
The average Cs-137 concentration in meat during 1984 was 0.039 pC1/g (wet). Assuming an adult consumption rate of 95 kg per year (Regulatory Guide 1.109), the annual dose to the whole body is 0.265 mrem per year.
The critical organ dose is 0.404 mrem per j
year to the liver. This calculated dose is small and can be compared to an annual dose of 20 mrem per year to the critical organ (the gonads in this case) as a result of naturally occurring K-40 in the environment. The calculated whole body dose (0.265 mrem per year) and the calculated critical organ dose (0.404 mrem per year to the liver) can also be compared to the dose received from control sample results during 1981. During 1981, the annual mean concentration for the control meat samples was 0.021 pC1/g (wet).
Using the same consumption factor of 95 kg per year, the annual whole body dose was 0.142 mrem per year and 0.217 mrem per year to the liver (critical organ dose). As noted above, the 1984 control samples did not show any Cs-137 above the lower limits of detection.
- However, j
Cs-137 in meat has historically been present.
Because of the small concentrations noted here, cesium can be noted in some samples and not in other samples.
92
.-g
-,-m
-w.-
-,--e - -
-m_,.p
__qq i.-.
7
-7,.
7%-7 g
-,y,
Eggs Egg samples were collected in the spring (May 2-10 June 6,1984) and in the fall (October 26, November 5-20, 1984).
Samples were collected at three onsite locations (within 10 miles of the site) and at one offsite location (greater than 10 miles from the site). The only radionuclide detected during 1984 in egg samples was K-40.
K-40 was detected in the spring samples at concentrations that ranged from 1.0 pCi/g to 1.2 pCi/g (wet).
The fall samples showed K-40 concentrations that ranged from 1.1 pCi/g to 1.3 pC1/g (wet).
j Poultry Poultry samples were taken during the spring (May 2-10, June 6, 1984) and during the fall (October 26, November 5-20, 1984) at three onsite locations and one offsite location. The only radionuclide detected during 1984 in poultry samples was K-40.
K-40 was de-tected in the spring samples at concentrations that ranged from 3.0 to 3.8 pCi/g (wet).
The fall samples showed K-40 concentrations that ranged from 2.6 to 3.7 pC1/g (wet).
Fruits and Vegetables Fruits and vegetables were obtained during the harvest season. Col-1ections were made during September at three indicator locations and one control location.
A successful attempt was made to collect one broadleaf and one non-broadleaf fruit or vegetable at each location.
Broadleaf vegetables of cabbage, Swiss chard, and collard greens and non-broadleaf fruits and vegetables of tomatoes and squash were collected.
K-40 was detected in all broadleaf and non-broadleaf vegetables and fruits.
Broadleaf vegetables (Swiss chard, cabbage and collard greens) showed concentrations of K-40 ranging from 1.8 pC1/g to 5.1 pCilg (wet). An indicator sample had the highest concentration (5.1 pCilg (wetl).
Non-broadleaf fruits and vegetables showed concen-trations of K-40 ranging from 1.8 to 2.2 pCi/g (wet).
Again an indicator location had the highest K-40 concentration (2.2 pCi/g
[ wet]).
l Be-7 was detected at the control sample location in Swiss chard.
The detectable concentration of Be-7 was 0.41 pCilg (wet).
The l
concentration of Be-7 at the indicator sample location for Swiss chard was less than 0.15 pCi/g (wet).
No other radionuclides were detected in the 1984 collection of fruits and vegetables.
l 93 ye-~
~,
Review of past environmental data indicates that K-40 has been con-sistently detected in food crop samples.
K-40 concentrations have fluctuated from one sample to another but the annual ranges have remained relatively consistent from year to year. Be-7 has been de-tected 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 occur-ring K-40 and Be-7 were detected.
94
+
+ - - -
..e
s CONCLUSION The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of the James A. FitzPatrick Nuclear Power Plant on the local environment. As demonstrated by the analytical results of the 1984 program, the major radiological impact on the environ-ment was the result of fallout from atmospheric nuclear testing.
Levels of natural background and the associated fluctuation in intensity are much more significant in terms of dose to man (normal background in the vicinity of the site is equal to 60 mrem /yr) than radiation levels in the environment associated with the operation of the plant.
Using the data presented in this report, and earlier reports as a basis, it can be concluded that no appreciable radiological environmental impact has resulted frcm the operation of the James A.
FitzPatrick Nuclear Pover Plant.
h 1
95
EXCEPTIONS TO THE PROGRAM 1.
Environmental radiation monitor I onsite was inoperable from January 13, 1984 (0715 hours0.00828 days <br />0.199 hours <br />0.00118 weeks <br />2.720575e-4 months <br />) to January 16,1984 (1115 hours0.0129 days <br />0.31 hours <br />0.00184 weeks <br />4.242575e-4 months <br />). Inoperabil-ity was caused by an electrical malfunction.
2.
The air sampling pump at the K onsite environmental sampling station was inoperable from February 10, 1984 (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />) to February 13, 1984 (1000 hours0.0116 days <br />0.278 hours <br />0.00165 weeks <br />3.805e-4 months <br />).
Inoperability was due to an IaC technician's failure to restart the air sampling pump after environmental station maintenance.
3.
The air sampling pump at the C offsite environmental sampling station was inoperable from March 6, 1984 (0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />) to March 7, 1984 (0930 hours0.0108 days <br />0.258 hours <br />0.00154 weeks <br />3.53865e-4 months <br />).
Inoperability was caused by pump mechanical problems.
4.
The air sampling pump at the J onsite environmental sampling station was inoperable from April 18, 1984 (0958 hours0.0111 days <br />0.266 hours <br />0.00158 weeks <br />3.64519e-4 months <br />) to May 17, 1984 (1415 hours0.0164 days <br />0.393 hours <br />0.00234 weeks <br />5.384075e-4 months <br />).
Inoperability was caused by pump mechanical prob-lems. All spare air sampling pumps were also being repaired during
(
this time interval, and were not available until May 17, 1984.
5.
Environmental radiation monitor C offsite was inoperabM from May 5, l
1984 (2100 hours0.0243 days <br />0.583 hours <br />0.00347 weeks <br />7.9905e-4 months <br />) to May 15,1984 (0857 hours0.00992 days <br />0.238 hours <br />0.00142 weeks <br />3.260885e-4 months <br />).
Inoperability was l
caused by vandalism to the environmental station (the monitor de-tector was stolen).
6.
Environmental radiation monitor C offsite was inoperable from May 22, 1984 (0937 hours0.0108 days <br />0.26 hours <br />0.00155 weeks <br />3.565285e-4 months <br />) to May 26, 1984 (0745 hours0.00862 days <br />0.207 hours <br />0.00123 weeks <br />2.834725e-4 months <br />). Inoperability was caused by an electrical malfunction.
7.
Environmental radiation monitor C offsite was inoperable from May 27, 1984 (1045 hours0.0121 days <br />0.29 hours <br />0.00173 weeks <br />3.976225e-4 months <br />) to June 4, 1984 (0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />).
Inoperability was caused by vandalism to the environmental station (the monitor detector was stolen).
8.
The spring collection of GAMMARUS did not contain sufficient quanti-ties for Sr-89 and Sr-90 analysis as required by Table 4.3.1, Appen-dix B of the James A. FitzPatrick Nuclear Power Plant Environmental Technical Specifications.
As required by plant procedures, three attempts were made to obtain sufficient quantities of GAMMARUS for analysis. The unavailability of GAMMARUS is most prooably due to the unseasonably cold temperature of Lake Ontario and the delay of the spring lake turnover.
Few GAMMARUS were inhabiting the shoreline shallows during the sprmg sampling season.
Another sample collection of GAMMARUS will be attempted before the second sample collection in late August.
9.
Environmental radiation monitor J onsite was inoperable from July 16, 1984 (0001 hours1.157407e-5 days <br />2.777778e-4 hours <br />1.653439e-6 weeks <br />3.805e-7 months <br />) to July 19,1984 (1334 hours0.0154 days <br />0.371 hours <br />0.00221 weeks <br />5.07587e-4 months <br />).
Inoperability was caused by vandalism to the environmental station (the monitor de-teetor was stolen).
96
?____
t
- 10. Environmental radiation monitor D-1 onsite was inoperable from August 5,
1984 (0630 hours0.00729 days <br />0.175 hours <br />0.00104 weeks <br />2.39715e-4 months <br />) to August 8,
1984 (1307 hours0.0151 days <br />0.363 hours <br />0.00216 weeks <br />4.973135e-4 months <br />).
Inoperability was caused by an electrical malfunction.
- 11. The air sampling pump at the I onsite environmental sampling station was inoperable from August 20, 1984 (1025 hours0.0119 days <br />0.285 hours <br />0.00169 weeks <br />3.900125e-4 months <br />) to August 23, 1984 (1107 hours0.0128 days <br />0.308 hours <br />0.00183 weeks <br />4.212135e-4 months <br />).
Inoperability was caused by pump mechanical problems.
12.
The air sampling pump and environmental radiation monitor at the F onsite environmental sampling station were inoperable from August 30, 1984 (2205 hours0.0255 days <br />0.613 hours <br />0.00365 weeks <br />8.390025e-4 months <br />) to September 4, 1984 (1121 hours0.013 days <br />0.311 hours <br />0.00185 weeks <br />4.265405e-4 months <br />). Inoperabil-ity was caused by an electrical malfunction.
13.
The air sampling pump at C offsite environmental sampling station was inoperable from September 26, 1984 (1700 hours0.0197 days <br />0.472 hours <br />0.00281 weeks <br />6.4685e-4 months <br />) to October 4, 1984 (1020 hours0.0118 days <br />0.283 hours <br />0.00169 weeks <br />3.8811e-4 months <br />).
Inoperability was caused by pump mechanical problems.
- 14. The air sampling pump at D-2 offsite environmental sampling station was inoperable from September 27, 1984 (1720 hours0.0199 days <br />0.478 hours <br />0.00284 weeks <br />6.5446e-4 months <br />) to October 4, problems.
\\
1984 (1135 hours0.0131 days <br />0.315 hours <br />0.00188 weeks <br />4.318675e-4 months <br />).
Inoperability was caused by pump mechanical
- 15. Environmental radiation monitor D-1 offsite was inoperable from November 26, 1984 (0730 hours0.00845 days <br />0.203 hours <br />0.00121 weeks <br />2.77765e-4 months <br />) to November 27, 1984 (0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />).
Inoperability was due to rapid chart paper advance. No high trips were indicated by the high trip light.
The high trip light was verified to be operational. The chart paper ran out prior to its ccheduled replacement date because the chart advance circuitry malfunctioned which resulted in the rapid chart paper advance.
This was replaced by an instrumentation and control technician in the field.
The chart paper was replaced and the monitor returned to normal operation on November 27,1984 (0830 hours0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />).
16.
The air sampling pump and environmental radiation monitor at K onsite environmental sampling station was inoperable from November 29, 1984 (0030 hours3.472222e-4 days <br />0.00833 hours <br />4.960317e-5 weeks <br />1.1415e-5 months <br />) to November 30, 1984 (1600 hours0.0185 days <br />0.444 hours <br />0.00265 weeks <br />6.088e-4 months <br />).
Inoper-ability was caused by a power outage due to a transformer failure.
17.
The air sampling pump at D-2 onsite environmental sampling station was inoperable from December 10, 1984 (0909 hours0.0105 days <br />0.253 hours <br />0.0015 weeks <br />3.458745e-4 months <br />) to December 17, 1984 (0845 hours0.00978 days <br />0.235 hours <br />0.0014 weeks <br />3.215225e-4 months <br />). Inoperability was caused by a blown fuse.
18.
The air sampling pump at G onsite environmental sampling station was inoperable from December 12, 1984 (1607 hours0.0186 days <br />0.446 hours <br />0.00266 weeks <br />6.114635e-4 months <br />) to December 17, 1984 (1022 hours0.0118 days <br />0.284 hours <br />0.00169 weeks <br />3.88871e-4 months <br />).
Inoperability was caused by pump mechanica".
problems.
19.
The air sampling pump at the D-2 onsite environmental sampEng station was inoperable from December 17, 1984 (0830 hour0.00961 days <br />0.231 hours <br />0.00137 weeks <br />3.15815e-4 months <br />s} to December 27, 1984 (1030 hours0.0119 days <br />0.286 hours <br />0.0017 weeks <br />3.91915e-4 months <br />). Inoperability was caused by pump mechanical problems.
97
REFERENCES 1.
U.S.
Nuclear Regulatory Commission Regulatory Guide 1.109, " Cal-culation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
March,1976.
2.
U.S. Nuclcar Regulatory Commission Regulatory Guide 1.109, " Cal-culation of Annual Doses to Man frem Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I",
October,1977.
3.
- Eichholz, G., Environmental Aspects of Nuclear Power, First Edition, Ann Arbor Science Puohshers Inc., Ann Arbor, Michigan,1976.
4.
National Council on Radiation Protection and Measurements (NCRP),
Environmental Radiation Measurements, NCRP Report No. 50, 1976.
5.
National Council on Radiation Protection and Measurements (NCRP),
Natural Background Radiation in the United States, NCRP Report No. 45, 1975.
6.
National Council on Radiation Protection and Measurements (NCRP),
Cesium-137 from the Environment to Man:
Metabolism and Dose.
NCRP Report No. 52, 1977.
l l
7.
National Council on Radiation Protection and Measurements (NCRP),
Radiation Exposure from Consumer Products And Miscellaneous Sources, NCRP Report No. 56, 1977.
8.
U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, " Environ-mental Technical Specifications for Nuclear Power Plants", December 1975.
9.
U.S.
Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program", November,1979.
- 10. Eise.9ud, Merril, Environmental Radioactivity, Second Edition, Aca-demic Pre.:3 New ?Erk, New York,1973.
11.
Francis,
C.
W., Radiostrontium Movement in Soils and Uptake in Plants. Environmental sciences Livision. Oak Rioge Nanonal Lacora-tory, U.S. Department of Energy,1978.
12.
National Council on Radiation Protection and Measurements (NCRP),
Radiation Exposure from Consumer Products and Miscellaneous Sources. NCRP Report No. 56, 1977.
13.
Pochin, Edward E.,
Estimated Population Excosure from Nuclear Power Production and other Raciation dources. Organization for Economic Go-operanon and Development, 1976.
14.
ICRP Publication Number 29, Radlonuclide Releases into the Environ-ment: Assessment of Dose to Man 1979.
98
l l
VI HISTORICAL DATA
VI HISTORICAL DATA Sample Statistics from Previous Environmental Sampline The mean, standard deviation, minimum.value, maximum value, and range, were calculated for selected sample mediums and isotopes.
Special Considerations:
1.
Sample data listed as 1969 was teken from the NINE MILE POINT.
PREOPERATION SURVEY. 1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION. NOVEMBER.1970.
2.
Sample data listed as 1974 was taken from the NINE MILE POINT NUCLEAR STATION, ENVIRONMENTAL OPERATING REPORT.
The 1974 data is pre-operational to the James A.
FitzPatrick Nuclear Power Plant, which started commercial operation in November,1974.
3.
Sample data listed as 1975, 1976, 1977, 1978, 1979, 1980, 1981, 1982, and 1983 was taken from the respective environmental operating reports for Nine Mile Point Nuclear Station and James A. FitzPatrick Nuclear Power Plant.
4.
Only measured values were used for statistical calculations.
i i
t i
e 99 1
f
1 HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MAXIM (IM MINIMUM RANGE Periphyton MEAN DE T0 Cs-137 pCi/g (vet) 1984 0.09 j
ONI.Y ONE DATA POINT 1983 0.10 0.06 0.14 0.06 0.08 O.06 0.04 0.02 1982 0.05 0.01 1981 o,19 0.07 0.24 0.14 0.10 1980 0.03 0.01 0.04 0.02 0.02 0.11 1979 0.07 0.08 n.13 0.02 IIII 0.04 0.03 0.063 0.023 0.04 1977 c_ _
1976
,,gn gyty gy7 y,_,
pg737 1975 mt i
1974 n,n n n, n,,
n,n, g,g3 (pqE.nNTIONati
,n n m l
l INDICATOR STANDARD Periphyten MEAN DEVIATION MAXIMUM MINIMUM RANGE Cs-137 pCi/g (vet) 1984 O.27 l
0.04 0.31 l
0.21 l
0.10 III3 0.35 0.23 0.69 0.17 0.52 1982 0.14 0.16 0.38 0.05 0.33 IIII 6.24 6.75 16.00 0.47 15.53 1980 0.09 0.05 0.15 0.04 0.11 IIII 0.36 0.55 1.10 0.08 1.02 IIII 0.11 0.06 0.19 0.05 0.14 IIII O.42 0.56 1.40 0.09 1.31
)
1976 2.60 1.38 4.10 1.40 2.70 1
22.25 14.34 36.00 4.00 3A00 III4 5.18 3.73 8.44 1.72 4,72 (PRE.0kR S TION AL)
NO DATA 100
~
., ~. -.. -
o HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL S7ANDARD MAXIMUM MINIMUM RANGE Mollusks DEVIAIl0N Sr-89 pCi/g (vec) l 1984 l
<un 1983
<un 1982
<un 1981
<tto l
1980
<un l
1979
<tto 1973 0.o2 ontY on DATA
?oTW l
I 1977
<w i
1976 wo NATA I 1975 no narx 1374 en n m (pgE nbil0NAO
-n a m l
INDIC ATO R STANDARD F.ollusks DEVIATION MAXIMUM MINIMUM RANCE E
Sr-89 pC1/g (vet) l 1984
<un l
l l
l 1983
<un 1982
<un 1981
<u3 1980
<un 19 9 0.04 0.03 0.07 0.01 0.06 1978 o,os o,o3 o.o7 o.o3 o,o4 1977
<st 1976 o.42 ontY oW DATA 70TW 1975
<gt 1974 l
<gt I
1969 i
l (P9E 0PERail0N AL) yo NATA 101
9',
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTR01.
STANDARD MAXIMUM MINIMUM RANCE Mollusks MEAN DEVIATION sr_90 pci/g (vet) 1984 0.020 0.016 0.031 0.009 0.022 1983 0.035 0.007 0.04 0.03 0.01 1982 0.03 0.01 0.04 0.02 0.02 l
1981 0.046 o.cos o.052 0.040 0.012 l
3 i
1980 0.07 0.06 0.11 o.03 0.08 1979 0.07 0.05 0.10 0.02 0.08 1978 0.14 0.02 0.15 0.12 0.03-i977 n.,,
o.,,
n.3, o.o, o,3n 1976 50 NATA 1975 yo NATA 1974 i,
s.n ni s iPRE.ob!TIONAO
..n ns i l
INDICATOR i
STANDARD Mollusks MEAN DEVIATION MAXIMUM MINIMUM RANGE Sr-90 pci/g (vet) 1984 l
0.061 l
o.049 0.130 'l o.026 I
o.104 1983 0.11 0.03 0.14 0.07 0.07 1982 0.10 0.02 0.12 0.07 0.05 1981 0.094 0.060 0.132 0.005 0.1'_7 l
1980 0.11 0.03 0.14 0.07 0.07 1979 0.10 0.04 0.17 0.05 0.12 1978 0.14 0.03 0.18 0.10 0.08 1977~
o,to o,o2 o,11 o,o7 o,og 1976 0.51 ony ont DATA point 1975 0.17 0.04 0.19 0.14 o.ns 1974 0.32 onY cyr cATA porr 1969 l
(PRE.0PER ATION AO o.12 0.17 0.24 0.01 i
o.23 102 m
,n..
.._.-,e y...,,
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTR0!.
STANDARD MAXIMUM MINIMUM RANGE Monusks MEAN DEVIATION Cs-137 pCi/g (vet) i 1984
<nn I
1983
<tta 1982
<un 1981 l
<un l
l 1980
<nn 1979
<ttn 1978 l
<st j
1977
<vot 1976 yo ggy 1975 l
NO DAM 1974 yn y,,,,,
tooE.n TION 5t) vn m-s l
INDICATOR STANDARD Menus.ts MEAN DEVIATION MAXIMUM MINIMUM RANCE Cs-137 pC1/g (wet) 1984 0.022 ONLY l
ONE l
DATA
.I POINT 1983
<un 1982
<ttu 1931 0.061 cNLY ONE DATA POINT 1080
<un 1979
<un 1971 0.99 0.80 2.10 0.24 1.86 1977
<st 1976 0.18 estY oNE DATA POINT 1975
<gt 1974 0.26 ONtY ON DATA POINT 1969 l
(PRE OPER ATIONAll I
0.08 ONLY ONE DATA
?OINT 103
i HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL i
STANDARD MAXIMUM MINIMUM RANGE Botten Sed 1=ent MEAN DEVIATION Sr-90 pC1/g (vet) 1984 0.c47 0.040 0.075 0.019 0.056 1983 0.14 oNLY oE DATA POINT 1982
<tto l
l 1981 o,o27 o,co7 o.032 0.022 0.01 l
l l
l 1930 o,12 oNt.Y on DATA
?oTW I
19 79 0.02 ont.T oNE DATA PoTW l
1978 0.05 0.01 0.06 o. ot.
0.02-1977 l
<vm 1973 y,
1975 I
I I
I
<vm l
l 1974 l
IPRE.nkTIOWa0
- m-i l
l lNDICATOR l
l STANDARD sotto: Sedi=ent MEAN DEVIATION MAXIMUM MINIMUM RANGE Sr-90 pCi/t (vet) 1984 0.038 l
0.042 0.100 l
o.011 0.089 III3 0.05 oNLY oNE DATA POINT 1982 0.037 0.03 0.06 0.013 0.047 IIII o.011 0.007 0.02 0.005 0.015 1980 0.01 o.003 0.015 0.011
- o. coa 1979 0.02 0.20 0.05 0.01 0.04 1978 0.015 ONI.T oNE DATA POINT 1977 et.
1976 o,oc o,co o,oc o,ot o,co 1975 l
l o,29 o,77 o,45 o,93 o,43 l
1974
<vot 1969 l
(P9E 0PER AT10M AD o.oe o tY oNE DATA i
?or'--
104
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MAXIMUM MINIMUM RANGE Bot::s sedi=e=:
MEAN D V TION cs-137 pci/g (dry) 1984 0.42 ONLY oNE DATA POINT 1983 0.24 0.08 0.29 0.18 0.11 l
1982 0.52 0.33 0.75 0.29 0.46 l
1981 0.26 0.23 0.42 0.10 o.32 l
1980 0.43 0.2 o.57 0.29 0.28 1979 a.47 0.10 0.54 0.40 0.14 1978 0.61 0.15 0.71 0.50 0.2:
1977 o.68 0.08 0.73 0.62 0.11 1976 cgt 1975 o.4o 0.10 0.50 0.3o 0.20 0.11 oNLY oNE
~ DATA POINT (PRE.0ha'TIONat) vn o m 1
IN DIC ATO R STANDARD Bo:::s Sed 1=en MEAN DEVIATION MAXIMUM MINIMUM RANGE Cs-137 pCi/g (d.7) 1984 0.49 0.53 1.08 l
0.04 1.04 L
1983 0.33 0.11 0.43 0.18 0.25 1982 0.20 0.11 0.30 0.05 0.25 1
1981 0.23 0.04 0.27 0.19 0.08 1980 o.34 0.40 0.94 0.12 0.82 1979 o.44 o.45 1.co 0.13 0.87 i
19 78 o.99 0.80 2.10 0.24 1.86 1977 2.27 1.90 4.10 0.31 3.79 1976 2.45 0.64 2.90 2.00 0.90 1975 0.83 c.a6 3.50 0.20 3.30 1974 0.40 0.26 0.58 0.21 0.37 l
(PRE.0PER A TION A L) 0.38 0.09 o.44 0.31 0.13 105
4 HISTORICAL ENVIRONMENTAi. SAMPLE DATA CONTROL MAXIMUM MINIMUM RANCE ca mARUS MEAN DEV T10 Sr-89 pCi/g (wet) 1984
<an l
1983
<un l
1982
<tta l
1981 0.034 oNtY cNE DATA POINT 1980
<tta l
1979
<tto 1978 et 1977 mt 1976 y 3gg 1975 NO DATA
)
l 1974 y,
l IPREohTIONat) vn ear.
l IN01CATOR
)
STANDAllD I
M EARUS MEAN DEVIATION MAXIMUM MINIMUM RANGE L
r Sr-89 pC1/g (vet) l 1984
<un l
l 1
j 1983
<un l
1982
<un 1981 0.069 ONLY ONE DATA POINT 1980
<un 1979 0.105 oNLY ONE DATA POINT 1978 et j
l 1977 et 1976 g3 gi73 1975 l
ya 3372 1974 l
et 1969 (pgr.0PER S TION Al)
NO DATA 106
-a,n- - -
---ru---w:-,,., _,,, _
s_-
,,m._4m-,,
,y w,y
_e-<,
,v-,,.,--w,n
,-,am
-,m
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MAXIMUM MINIMUM RANGE cA W.AES MEAN DEV ATION Sr-90 pC1/g (wet) 1984 0.06 O.03 o.08 l
o.04 l
o.04 1983 o.oy 0.03 c.lo 0.05 0.05 1982 0.09 oNLY oNE dan POINT 1981 l
0,o99 0.066 0.146 0.052 0.094 1950 o,102 oxt,y ext ex7x PoINr 19 79 0.10 0.02 0.11 0.08 0.03 1978 o.14 0.01 0.14 0.13 0.ol-
~
1977 0.32 or.,Y ONE DATA POINT 1976 yg ggy 1975 No DAM 1974 l
(pnE.nNNTinNat) l l
un n a,.s
.l IN DIC ATOR I
STANDARD h [ ifg (y.e)
MEAN DEVIATION MAXIMUM MINIMUM RANGE L
1984 0.18 O.02 ll 0.21 l
0.16 l
0.05 1983 0.18 0.03 0.21 0.16 0.05 1982 0.23 0.10 0.30 0.16 0.14 1981 0.193 0.058 0.274 0.138 0.136 1980 0.64 0.86 1.64 0.14 1.5 l
1979 0.19 0.01 0.20 o.17 0.03 1978 0.14 0.04 0.21 0.13 0.08 l
1977 a.40 0.46 0.73 0.08 o.65 1976 30 333 1975 30 3g3 1974 et 1969 I
I (PRE 0PERail0N AL)
No DAM 107
-.--r.
w..
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIMUM RANGE cA W.ARUS MEAN DEVIATION Cs-137 pCi/g (vet) 1984 l
<ttD 1983
<tto 1982
<tto I
I 1981
<ttn l
1980
<tto 1
1979 0.05 0.04 0.08 0.02 n."A 1978 0.029 oNtY oW DATA PO N 1977 evne.
l l
1976 1
yo gg7, 1975 No DATA 1974
-n m e,
l IpqEnkTIONati t
-l lNDICATOR I
STANDARD cAWARUS MEAN DEVIATION MAXIMUM MINIMUM RANCE Cs-13 7 pC1/g (vet) 1984 l
<LtD l
I l
III3 0.21 0.21 0.36 0.06 0.30 l
1982
<tt.n 1981 4.7 4.67 8.0 1.4 a.6 1980
<tto l
0.07 l
1979 0.06 0.02 0.04 0.03 l
1978 0.05 0.00 o.05 0.05 0.00 1977
<st, 1976 yo 3,73 1975 j
30 3,73 1974 0.21 oNt.?
on DATA
= ' ~
1969 f ppt. Opt 9 sTION All No DATA 108
't O
j HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTR01.
STANDARD MAXIMUM MINIMUM RANGE Fish Samples MEAN DEVIATION Sr-89 pC1/g (wet)
I 1984
<un 1983
<un I
l 1982 0.004 0.001 0.005 0.003 0.002 i
i 1981 0.015 0.001 0.015 I
o.014 0.001 19 80
<un l
o.04 0.09.
0.04 6.05 1979 0.07 1978
<st 1977 n.04 o.ot n.nc n.n,
. n ne 1976 0.24 0.08 o."
n.!o n 'a 1975
<mt 1
1974 l
1969 l'
l IPRECPERST!0Na0 vn ns-s l
IMOICATOR STANDARD Fish Samples MEAN DHIATION MAIIMUM MINIMUM RANCE Sr-89 pCi/g (wet) 1984
<un l
l l
i 1983
<un 1932 0.004 0.001 0.004 0.003 0.001 1981 0.061 0.021 0.10 0.02' n.n?'
1980
<uo 1979
<un 1978 0.01 0.001 0.015 0.014
- 0. cot I
1977 0.07 0.05 0.24 0.03 o.21 1976 0.27 0.15 0.41 0.12 o.2o 1975 l
l
<gt, 1974 l
<st.
l l
1969 l
l (pRt.0PER sTION AD No OA*A l
109 l
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MAXIMUM MINIMUM RANGE Fish Seples MEAN DE T10 Sr-90 pC1/g (vec) 1984
<u.D 1983
<tl.D l
1982 0.006 0.006 0.013 0.002 0.011 1981
<u.D l
1980 0.005 o.002 0.007 0.002 0.005 19 79 0.018 0.012 0.033 0.008 0.025 1978 o.010 0.004 0.015 0.004 0.011 1977 0.07 0.03 0.14 0.02 0.12
~1976 0.25 0.27 0.81 0.05 0.76 1975 0.07 J.06 0.10 0.04 0.06 1974 l
n.ov o.02 0.09 0.04 0.05 1969 l
-1 (poE oP593710Nati i
vn n m j
INDICATOR l
STANDARD I
Fish Seples MEAN DEVIATION MAXIMUM MINIMUM RANGE I
s:-90 pci/g (vec)
I 1984 l
<tts 1.
l t
1983
<tta 1982 0.003 0.001 0.005 0.002 0.003 1981 0.002 ONLY C?E DATA POINT l
1980 0.006 o.005 0.01:
0.003 0.010 1979 0.019 0.01 0.04 0.01 0.03 1978 0.013 0.006 0.025 0.004 0.,021 19II o.07 0.05 0.24 0.03 0.21 0.28 0.48 2.20 0.05 2.15 1975 l
o,og o.03 0.13 0.02 0.11 1974 0.23 0.59 2.30 0.01 2.29 (P9E.0kRfT10Uli o.51 l
o.23 0.17 0.30 0.21 110 l
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL ff0 MAXIMUM MINIMUM HANGE Fish Samples MEAN Cs-137 pCi/g (wet) 1984 l
0.032 0.009 0.038 1
0.015 0.023 1983 0.050 0.009 0.060 0.040 0.020 1982 0.047 0.009 0.055 0.027 0.028 l
1981 0.043 0.016 0.062 0.028 0.034 1930 0.059 0.032 0.110 0.029 0.0d1 1979 0.04 0.01 0.06 0.03 0.03 1978 l
0.09 0.05 0.20 0.04 0.16 l
1977 0.13 Ont.y On DATA POINT 1976 l
0.12 ONLY OE DATA POINT 1975 o,Dt III4 0.43 0.37 0.94 0.09 0.85
)
(pet.nhT10Nati l
vn DATA 1
INDICATOR STANDARD rish sa=ples MEAN DEVIAT10N MAXIMUM MINIMUM RANGE Cs-137 pC1/g (vet) 1984 0.043 0.008 l
0.061 l
0.033 0.028 l
1983 0,050 0,009 0.060
- 0..;S 0.030 19 I2 0.050 0.008 0.064 0.034 0.030 1981 0.061 0.021 0.10 0.027 0.073 1980 0.061 0.029 0.100 0.030 0.070 l
1973 0.10 0.14 0.55 0.02 0.53 19 7I 0.08 0.02 0.10 0.03 0.07 IIII 0.29 0.21 0.79 0.13 0.66 1976 1.4 1.67 3.90 0.50 3.40 III l
1.38 0.22 1.70 1.10 0.60 1974 0.57 0.82 4.40 0.08 4.32 1969 I
(Pet.0PE92 T10N at) 0.06 0.04 1
0.13 0.01 0.12 l
111 em
_.-_.__.e-.s
.-m_.,.
,m
,.e -,-.
o HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL
^
MAXIMUM MINIMUM RANGE Lake Water Gross Esta MEAN DEV Ti0N pci/1 1984 l
2.41 0.85 5.20 2.40 2.80 1983 2.98 1.74 7.92 1.47 6.45 1982 2.4 0.43 3.2 1.8 1.4 1981 3.24 1.27 5.8 1.9 3.9 l
1980 2.60 0.50 3.48 1.s7 1.61 1979 3.05 0.85 4.80 2.10 2.70 0.50 1978 3.55 1.58 6.10 5.60 1977 10.9 14.5 49.3 2.50 46.8 1976 42.4e 50.62 1so.co 4.90 184.10 1975 l
45.33 52.79 160.00 1.00 159.00 1974 4.ss o.07 4.90 4.80 0.10 f PRE.0h!T10Nati vn nam l
INDICATOR STANDARD water cross see*
MEAN DEVIATION MAXIMUM MINIMUM RANGE 1984 l
3.98 o.98 l
5.90 l
2.20 l
3.70 1983 3.34 1.59 7.90 0.57 7.33 1982 2.7 0.73 4.7 1.3 3.4 l
1981 2.98 1.19 5.4 1.2 4.2 1980 3.10 0.63 5.10 2.35 2.75 l
1979 3.24 1.06 6.30 2.00 4.30 1978 4.53 2.62 11.10 0.60 10.50 li l
1977 15.80 21.00 87.00 1.00 86.00 1976 41.76 55.23 192.00 1.10 190.90 1975 l
80.00 is.24 17.08 0.60 79.40 1974 l
31.71 20.22 60.00 6.30 53.70 1969 (PRt.0PcR 3 TION All No DATA 112
HISTORICAL ENVIRONMENTAL SAMPLE DATA j
CONTROL STANDARD MAXIMUM MINIMUM RANGE take Water MEAN DEVIATION sr_a9 pct /l 1984
<tto l
1983
<tto 1982
<tta 1981 l
<tto 1
l l
1980 1.4 0.07 1.4 1.3 I
o.1 l
1979 o.70 0.14 0.80 0.60 0.20 1978 ent l
1977
<vnt_
1976 l
<vn r.
1975 i.
<vnr 1974 vn n m IPRE.nh!NTIONati
-em INDICATOK STANDARD i
Lake Water MEAN DEVIATION MAXIMIJM MINIMUM RANGE Sr-89 pCi/l 1984
<tto l
l l
l 19S3
<tto 1982 0.61 oNI.Y ONE DATA POINT 1981 0.78 extY cNE DATA
?oTNT 1980 l
o,;o CNLY ONE DATA POINT j
1979
<tto i
1978 a.70 0.10 0.80 0.60 0.20 1977 l
<st 1976 mt i
IIII o.30 n i?
oNE DATA
?ot'r-1974 l
yo 3373 1969 l
(P9E.0PE9 ail 0N Ali No DATA I
113 w
,-w----
r-
- ~
---+.v,w-w.
--r--.
--+
= -
-,w-c-----w----'----
- - - - - - - - - - - * - - - - - - - + + ~
- +--w-*---e----
H!STORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIMUM RANCE Lake water MEAN DEVIATION Sr-90 pCi/1 l
1984 0.72 oNLY oNE DATA POINT 1983 o.89 0.08 o.97 0.82 0.15 1982 2.04 2.18 5.30 0.75 4.55 l
1981 o.68 0.176 0.868 0.484 0.384 l
1980 1.10 0.00 1.10 1.to 0.00 1979 c.80 0.26 1.10 0.60 0.50 1978 et 1977
<vm 1976 m
1975
<vnt 1974 j
s.n m-s
! en mm 1
IPRE 0 T10Nati INDICATOR STANDARD take water MEAN DEVIATION MAXIMUM MINIMUM RANCE l
Sr-90 pCi/1 1984 1
0.88 L
o.31 l
1.30 l
0.80 l
0.50 1983 0.83 0.21 1.10 0.60 0.50 1002 1.08 0.88 3.07 0.40 2.67 1981 0.74 0.08 0.805 0.597 0.208 i
1980 1.00 0.20 1.20 0.80 0.40 IIII 0.84 0.34 1.30 0.40 0.90 IIII 0.80 0.30 1.10 0.40 0.70 IIII 1.00 ONtY CNE DATA POINT 1976 gt 1975 l
et l
1974 no 3471 i
1969 (P9E OPERail0N All No SATA 114 en,--,-
--,.,,r,-----,,-.~n-
r---,-
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL 1.ake water MEAN DEV ATION MAXIMUM MINIMUM RANGE Triti n pC1/1 1984 205 21.2 220 190 l
30 l
1983 250.0' 21.8 280 230 50 l
1982 165.0 94.7 307 112 195 1981 293.3 49.3 357 211 146 1980 257.3 38.5 290 211 79 I
l 308 19 79 258.7 l
73.7 174 134 1978 303.8 127.5 490 215 275-IIII 407.5 97.4 530 300 230 1976 l251.0 l
929 651.7 440 489 1975 362.5 72.8 414 311 103 1974 i
m 1969
( #9E-tipFa s 710430 vn ni-s IN01CATOR STANDARD k* W***r MEAN DEVIATION MAXIMUM MINIMUM RANGE h*ritiu:n pC1/1 i
1984 282 l
98.1 l
370 l
110 260 1083 317.0 116.9 560 190 370 ISI2 641.0 M 1.1 2780 194 2586 1981 258.3 76.9 388 183 205 1980 263.0 95.4 457 150 307 1979 234.0 40.7 286 176 110 IIII 389.4 119.9 560 253 307 IIII 450.0 67.2 530 380
'150 513.0 250.3 889 297 l
592 334.8 132.5 482 124 358 ISI 4!.0. 0 34.0 500 380 100 l
1969 I
l l
l (D9E.0P!a S Tl0N AD I
No DATA I
I 115
--,.,m
..-n-._,._,,,-.a
. ~.
~... - _, -
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTP.0L l
MAXIMUM MINIMUM RANGE Air Particulate MEAN DEV TION Gross Bata pC1/s, 1984 l
0.026 0.007 0.051 l
0.013 l
0.039 1983 0.024 0.009 0.085 0.007 0.078 1932 0.033 0.012 0.078 0.011 0.067 IIII 0.165 0.135 0.549 0.016 0.533 l
l 1930 0.056 0.04 0.291 0.009 0.282_
l 1979 0.077 0.086 0.703 0.010 0.693 1973 0.14 0.13 0.66 0.01 0.650 1977 n.o-o.03 n.140 0.016 0.124 1976 c.ost o.ost o.540 0.004 0.236 1975 om5 own o.294 0.00s o.286 i
l 1974 n,,,
n_,n3 n,,n,
- n. cot 0,go7 l
(P9E.ON T10uti l
e $44 n.ne-a eso n.i'n o.cto INDICATOR STANDARD Air Particulate,
Mr.AN DEVIATION MAXIMUM MINIMUM RANCE i
Gross Beta pCi/m 1984 l
0.025 l
0.008 h
0.058 l
0.000 1
0.058 1983 0.023 0.009 0.062 0.003 0.059 l
1 1002 0.031 0.012 0.113 0.001 0.112 1981 0.151 0.128 0.528 0.004 0.524 l
l 1980 0.045 0.03 0.207 0.002 0.205 1970 0.058 0.06 0.271 0.001 0.270 l
1973 0.10 0.09 0.34 0.01 0.33 ISII 0.106 0.07 0.326 0.002 0.324 10 I 0.047 0.032 0.191 0.002 0.189 10 0.067 0.055 0.456 0.001 0.455 IIII 0.111 0.114 0.955 0.003 o.952 l
l 0.090 0.520 0.130 0.?o0 (PRE.0 A TION AL) 0.320 116
e
-,-,-.,,,.7,,,,
-.. -.,,,,, ~.. -..,. -, - - -. - - -,, - -,, -., -
i HISTORICAL ENVIRONMENTAL SAMPLE DATA i
CONTROL j
Enviremental TLD's Quarterly STANDARD MAXIMUM MINIMUM RANGE Rsading nrem/ Standard Month MEAN DEVIATION na,...
1 1984 5.87 l 1.00 8.20 3.90 l
4.30 l
1983 5.54 0.364 7.17 4.21 2.96 i
l l
1982 5.12 0.691 6.95 3.79 3.16 l
1981 4.72 0385 6.63 3.24 3.39 1980 4.57 0.614 6.06 3.12 2.94 1979 REPORTED AS MRCUOTR PRIOR TO 1980 1978 1977 l
1976 1975 1974 (poE.nkfloNsti l
INDICATOR
- ny m c.nca. m 4 quarte _:.
STANDARD Reading : em/ Standard Month MEAM DEVIATION MAllMUM MINIMUM RANGE Onsite Monitors
- 1984 6.42 l
1.26 l
9.90 l
4.60 5.30 1003 6.23 0.91 8.97 5.03 3.94 1982 5.82 1.24 9.13 3.87 5.26 1981 5.24 0.73 7.45 4.09 3.36 1
1 DATA NOT CCMPARABLE DCE TO CMANGES f
1980 IIII IJ TLD LOCATIONS f
1978 1977 1976 1975 l
l 1974 l
l 1959 1
l l
IP9E 0PERaf!ON AL) i I
I
- Sce Clarification on Enviton= ental Sanple Statistical Analysis Table,Section III.
117
[.
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MAXIMUM MINIMUM RANCE xilk suples MEAN DEV ATION Sr-90 pC1/1 1984 2.14 0.61 2.90 1.30 1.60 1983 1.91 0.50 2.60 1.00 1.60 1982 2.96 1.20 4.20 0.93 3.28 1981 l
4.85 t.91 8.00 2.41 5.5o 1980 3.33 0.9 4.3 1.8 2.5 1979 4.44 1.33 5.80 1.70 4.16 1978 5.88 2.04 9.00 3.00 6.00~
1977 vn niri 1976 yo 317, 1975 NO SATA l
1974 yn,,,,,,
root.okkilovsti ve ni s INDICAT0ft STANDARD x11k suples MEAN DEVIATION MAXIMUM MINIMUM RANCE Sr-90 pC1/1 1984 2.34 h
1.19 7.60 l
0.80 6.80 1983 2.81 0.80 5.05 1.00 4.05 1982 4.60 2.29 9.76 0.76 9.00 1981 4.60 2.45 10.70 1.t?
o.59 1980 4.3 2.6 11.0 1.1 a.a IIIS 4.84 2.12 9.00 0.70 8.30 ISII 5.93 1.81 10.00 2.50 7.50 10II 6.07 3.50 15.00 2.00 13.00 1976 7.16 3.41 14.80 1.50 13.30 10 6.31 3.11 13.80 2.30 11.56
'0I4 5.66 2.99 14.00 1.00 t'.66 1969 l
(pat.0PER ATION Al)
No DA*A 118
~
v--w
,..-,,_.n-
- - - + - -
,,._,-g
,e.,
w,m_v----.e--_..--,.__,--n-
i HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Milk samples MEAN DEV ATION MAXIMUM MINIMUM RANCE Cs-137 pCi/1 1984
<1.LD 1
1983
<tta l
1982
<tto 1981 7.0 ONLY ONE DATA POINT i
1980
<tto 1979 3.73 0.29 3.9 3.4 0.5 l
1978 5.83 1.98 7.8 2.4 5.4 1977 l
?MOR To vn cont =ot DA"A 10'8 1976 i
1975 l
1974
/!
IP#E Oh!7f0NAD nnm I
INDICATOR STANDARD Milk samples MEAN DEVIATION MAXIMUM MINIMUM RANGE Cs-137 pC1/1 19 84
<tLD l
l l
1 III3 5.10 ONLY ONE DATA POINT 10 I2 6.26 4.41 18.0
- 1 14.9 1981 7.57 5.95 29.o 43 24.7 l
1980 9.7 4.9 21.0 4.c 17.0 1979 9.4 8.0 40.0 2.7 37.3 1978 9.9 7.1 33.0 3.4 29.6 1977 l
22.0 17.1 3.9 11.0 11.0 j
1976 7.8 3.7 13.2 4.0 9.2 1975 l
20.6 7.8 36.0 6.o 10.o III4 26.1 10.5 61.0 13.0 48.0 1969 1
(PRt.0PcR A 710N A D I
'to DATA 119 l
l
6 HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIMUM RANGE xilk saples MEAN DEVIATION I-131 pCi/1 i
1984
<un l
I 1983
<un l
1982
<un 1981
< t.t3 l
1980 1.41 oNI.Y OE DATA POINT 1
1979
<tto 1978 et.
L-l 1977 1
30 niri 1976 i
yo 3,73 1975 NO DATA 1
1974 vo mm (PRE ONTIONAli m m-s INDICATOR STANDARD xilk saples MEAN DEVIATION MAXIMUM MINIMUM RANGE I-131 pci/1 1
1984
<nD l
l 1983
<no l
1982
<un 1981
<un 1980 4,9 4.23 8.80 0.40 8.40 i
1979
<un l
1978 0.19 CNIY oE DATA POINT 1977 0.20 0.14 0.22
-0.40 0.62 1976 3.20 7.81 45.00 0.02 44.98 i
1975 0.37 o.60 2.99 0.01 2.98 1974 1.23 0.44 2.00 0.70 1.30 (Pet.0df9YTIONAli No DATA 120
~
l HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIMUM RANGE Human iced Crops MEAN DEVIATION Cs-137 pCi/g (wec) Produce 1984
<un 1983
<un l
]
1982
<un
)
1981
<un 1980 l <un l
1979 NO CONTROL DATA PRIOR TO 1980 1978
- l 1977 i
1976 1975 i
1974 i
(ME Obf710Nati l
INDICATOR l
STANDARD Human Food Crops MEAN OWMTION MAXIMUM MINIMUM RANCE Cs-137 pC1/g (vet) Produce 1984
<un L
l ll l
1983
<un 1982
<un 1981
<un l
1980 0.033 2.26 0.06 0.004 o.056 l
1979
<un 1978 0.01 cNr.Y cNE DATA POINT j
1977 l
et 1976 i
et 1975 l
et, 1974 l
0.142 0.09 o.3A o.oA o.30 (Mt.OkNTIONALI l
No DATA 121 n-e-,-
,ag--nm n------------
,---.---,w.,
,,a,-,,-
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIMUM RANGE Euman Food Creps MEAN DEVIATION I-131 pC1/g (wec) Produce l
.I 1984
<ttD 1983
<tw 1982
<ttD l
1981
<tm l
l l
1980
<tto 1979 NO CONTR0t DATA PRIOR TO 1980 1978 1977 1976 1975 -
1974 (p9E 0hT!0430 INDICATOR
. STANDARD E m s Food Creps MEAN DEVIATION MAXIMUM MINIMUM RANCE I-131 pCi/g (vet) P:cduce l
l 1984 L
<tta 1983
<tw 1982
<tta 1981
<tw 1980
<tt3 1979
<tm 1978 mt 1977 et 1976 l
mt 1975 et 1974 go 3x73 1969 1
I (Pot.0FER A T10M A D I
NO DATA l
122 l
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Meat MEAN DEV T10 MAXIMUM MINIMUM RANGE Cs-137 pC1/g (vet) 1984
<no l
l i
1983
<up i
1982
<tto 1981 l
l l
o.021 0.005 0.024 o.017 o.007 1980 l
DATA 0.01 cNtv on POINT 1979 No CCNTRot DATA PRToR To 1Q90 1978 l
l 1977 l
l 1976 l
l 1975 t
1974 l
l r,r.oHLnuo l
l l
l l
INDICATOR STANDARD M**t MEAN DEVIATION MAXIMUM MINIMUM RANGE Cs-137 ;C1/g (ve:)
1984 0.04 l
o.01 l
o.05 l
0.03 l
o.02 1983 0.02 0.01 0.04 0.01 0.03 III2 0.034 0.026 0.08 0.02 0.06 1981 0.036 0.021 0.068 0.023 0.045 1980 l
l 0.02 o.013 I
o.ct2 o.co9 o.033 1979 l
o,o3 o.021 0.07 0.01 0.06 1978 0.021 0.011 0.04 0.013 0.027 1977
<xet 1975
<vot l
1975 l
0.10 0.00 0.10 o.10 0.00 1974 No DATA
-~
~
1969 I
l 1
(PRE.0pcR2TIOUD 1
No CATA I l
123
l HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIMUM RANCE Eggs MEAN DEVIATION Cs-137 pCi/g (vet) 1984
<tto 1
1983
<tta 1982
<tto l
l 1981
<tt.3 l
1980
<tt3 1979 NO CONTR0t DATA PRIOR 0 1980 1978 1977 1976 1975 1974 (pet obs'T10N30 l
l l
INDICATOR STANDARD Eggs MEAN DEVIATION MAXIMUM MINIMUM RANCE Cs-137 pCi/g (vet) 1984 l
<tLD l
l l
1983 j
<tt3 1982
<tto 1981
<tto 1980
<tt3 l
1979
<tz,3 l
1978
<st.
1977
<st, 1976
<gt 1975
<g t, i
1974 yo 3171 1969 l
1 I
(PRE OPE 92Tt0Nal)
No DATA I
124 l
i L
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD MAXIMUM MINIM M RANGE soil sa=ples MEAN DEVIATION Cs-137 pC1/g (dry) 1934 NO s m LES l REQUIRED IN l
1984 l
1933 0.67 0.49 1.46 0.20 1.26 l REQUIRED 1932 NO smLES IN 1982 1031 l NO l REQUIRED l
s m LES IN 1981 1930 l
l 1.20 0.91 2.90 0.41
- 2. I.9 1979 No SAMPLES RECUIRD IN 1979 1973 l
so R!cUIRED lIN sAMPt.Es 1978 -
l 1977 2.00 0.70 1.30 1.17 0.48 1976 yo 3,,,,,
1975 1
1.07 0.21 1.30 1
0.90 0.40 vn 1_ i l
l 1874 1969 (pat.0pEasTinNati en n_i_
i_
INDICATOR STANDARD
$'f3!$ffs(dry)
MEAN DEVIATION MAXIMUM MINIMUM RANCE 1984 l
NO l
SAMPLES l REQUIRED l IN
.l 1984 1933 0.42 0.41 1.19 0.07 1.12 1982
- 0 smLEs REcCIRED IN 1982 1981 l
NO l
sA!'Pt.Es RECUIREO IN 1981 1980 1.26 0.61 2.1 0.29 1.31 1970 No s m LES RECUIRED IN 1979 ISIS l
N0 SAMPLES RECUIRED I:i 1978 1977 l
1.03 0.62 2.co 0.30 1.70 1976 l
33 3,73 1975 l
,r0UnA l
l 1974 l
l 1.03 1.18 2.s0 0.40 2.40 1959 l
l l
Ipat 0PEasTIONat) i No DATA l l
125 l
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL MAXIMUM MINIMUM RANCE soil sa=ples MEAN DEV ATION sr_90 pci/g (dry) 1984 No
' s m LEs RECUIREDl IN 1984 1983 0.18 0.09 0.32 0.10 0.22 l REQUIRED 1982 No sal.Es IN 1982 l
REOUIRED 1931 No s m LEs IN 1981 1930 l
l 0.063 0.065 0.19 0.008 0.182 l
1979 No smt.Es REoUIRED IN 1979 1973 so smtEs REcUIRED IN 1978 l
l 1977 c.21 0.07 0.2o 0.13 0.16 1976 l
yo g,
III3 l
o.13 0.10 0.26 0.04 o.22 1974 l
yo,,.,
I roqE.ohNs'7:09so vn nam _
l lN DIC ATO R l
STANDARD
}
l,go
,)*g(dry)
MEAM DEVIATION MAXIMUM MINIMUM RANCE 1934 No l
smLEs l RECUIRD l IN 1984 1983 0.18 0.18 o.47 0.03 o.44 1982 No set.Es REoUIRED IN 1982 1981 No s m tEs REcUIRED In 1981 l
1930 o,o7c o.052 0.140 0.0c8 0.132 1979 No sAMP1.Es REoUIR D IN 1979 1978 No sal.Es REOUIRED IN 1978 l
1977
~
.40 0.18 0.65 0.17 o.48 o
1976 l
3o a473 1975 l
yo og73 l
l 1974 o,27 0.c6 0.34 0.23 c.I1 (pqq.op pTION30 l
No DATA l
l 19 126
VII
(
\\
5
\\
FIGURES AND MAPS l
VII FIGURES AND MAPS 1.
DATA GRAPHS This section includes graphic representation of selected sample results.
For graphic representation, results less than the MDL or LLD were considered to be at the MDL or LLD level of activity. MDL and LLD values were indicated where possible.
2.
SAMPLE LOCATIONS Sample locations referenced as letters and numbers on analysis results tables are plotted on maps.
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t FIGURE 7 Composition of Bottom Sediment Determined by Visual Examination at Benthic Sampling Stations in the Vicinity of Nine Mile Point,1978 Depth Contour (ft)
Transect Description
- Comments 10 NMPW 100% bedrock NMPP 70% boulders, 20% rubble,10% gravel Some algae on rocks FITZ 80% boulders,10% gravel,10% sand Some algae NMPE 70% boulders, 20% gravel,10% sand Some algae 20 NMPW 50% bedrock, 50% rubble NMPP 50% boulders, 30% rubble, 20% gravel All lying on bedrock FITZ 50% boulders, 20% rubble, 20% gravel, 10% sand NMPE 40% bedrock, 30% boulders, 25% gravel, 5% sand 30 NMPW 100% bedrock Some rubble NMPP 100% bedrock Some boulders FITZ 80% bedrock Some sand NMPE 100% bedrock Some rubble and sand 40 NMPW 50% bedrock, 30% sand, 20% rubble NMPP 80% boulders, 20% bedrock FITZ 50% bedrock, 30% rubble, 20% boulders, NMPE 100% bedrock Some scattered sand 60 NMPW 100% bedrock NMPP 80% boulders,10% rubble,10% gravel FITZ 80% bedrock, 20% boulders Some rubble NMPE 80% bedrock, 20% rubble Some sand
- Description based on USEPA (1973) f! eld evaluation method for categorizing soils.
135 -
4
1 FIGURE 8 PERIPHYTON SRMPLES I
Co-60 JRF ENVIRCNMENTAL LAB
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CONTRCL VALUES 1974 70 1979 RRC McL'es 1980 70 1984 PRC LLD's 136 4
1
FIGURE 9
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Cs-137 I
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I ENVIRCNMENTFL I
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CCNTRCL VALUES 1975 & 1977 FRC MCL's 137
FIGURE 10 PERIPHYTON SAMPLES Ce-144 JRF ENVIRONMENTR' LRB i
3.OM 3.0
--*-- = CONTRCL
~2.2 2.8-
- INDICATCR L2.6 5
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NC CCNTRCL CRTR FCR 1974-1976 CCNTRCL YERFS 1977-1973 RRC NCL's: 1980-1984 RRE LLD's INDICATCR YERRS 1974-1979 RRE NCL's: 1980-1984 RAE LLD's 138
FIGURE 11 MOLLUSK SAMPLES Co-60 JRF ENVIRCNMENTAL LRB
-2.0 2.Oi
--*- = CCNTRCL
- + - - INDICATCR
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$m 1. 6 -l z
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NO CCNTRCL CRTR FCR 1974-1976 NC INDICATCR CRTR FCR 1973 CCNTRCL YEARS 1977-1979 RRE MCL's: 1980-1904 RRE LLD's INDICHTCR YEAR 1977 IS MUL 139 mm-..
M _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _
FIGURE 12 MOLLUSK SAMPLES Mn-54 i
l JPF l
ENVIRCNMENTFL LRB I
f i
--*- = CCNTRCL 3.3-
- + - - INDICaTCR L3.3 3.0-
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NC CCNTRCL CATA FCR 1974,1979,1376 CONTRCL YERRS 1977-137S RRE NCL's: 1980-1984 BRE LLD's INDICATCR YEARS 1977-1973 ARE MCL's 140
FIGURE 13 MOLLUSK SRMPLES I
M Sr-90 ZRF ENVzRCNidENTRL i
LRB i
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-0.9
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m 0.7
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NO CONTRCL CRTR FCR YERRS 1974-1976 141
l l
l FIGURE 14 BOTTOM SEDIMENT I
Co-60 ZRT ENVIRONMENTRL W
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= INCICATCR q
2.25 b2.25 I
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CCNTRCL CRTR FCR YCRRS 1975-1976,1378-1973 RRC McL's: 1980-84 RRC LLD's 142 a
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l FIGURE 15 BOTTOM SEDIMENT I
Cs-137 i
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CONTRCL CRTR TCR 197G IS N:L 143
t FIGURE 16 FISH SRMPLES Cs-137 3RF D4VIRCNMC4TRL i
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CCNTRCL CRTA FCR 1975 IS McL: 1881 IS LLD 144
FIGURE 17 s
FISH SAMPLES I
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CONTRCL CRTR FCR 1981,1983.1984 RRE LLD INDICATCR CRTR FCR 1983-94 RRE LLC 145 bu q h is um u
FIGURE 18 LRKE WATER
/
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SAMPLE PERIOD (YERR) 146
FIGURE 19 LAKE WRTER GROSS BETR JRr ENVIRCNMENTFL I
MB
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SRMPLE PERIOD CMONTHS 1984)
INDICRTCR VRLUE n FCR MCt4TH 1 IS LLD INDICATCR VALUE J FCR MCNTH 6 IS LLD 147
FIGURE 20
__RIR PRRTICULRTE 1
GROSS BETR ACTIVITY J
i JRF ENVIRCNMENTr7L l
UI RTMCSPHERIC NUCLEAR
---*--- = CONTRCL O.20-
= INDICRTCR,-0.20 j
j i
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0,18J z
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FIGURE 23
'R PRRTICULRTE COMPOSITE
~
Co-60 m
ENVIRCNMENTAL LRB
-2.0 2.0-
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=
1.8-
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m z
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CCNTRCL MCNTHS 3-12 RRE LL3's INDICRTCR MCNTHS 4-12 RRE LLD's 152
i FIGURE 24 RIR PRRTICULATE
)
OMPOSITE---Co-60 3R7 ENVIRCNMENTAL LRB
-*-- = CCNTRCL g10^-01 10^-01d
- INazcarcR l
]
2 z
j o
o i
s
[m 10^-02 =l
's 5 10^-02 y m c<
=
p me me r-rs z.-
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NO CATR FCR YEBRS PRICR TO IS77 152
7 FIGURE 25 R PRRTICULRTE COMPOSITE Cs-137 JRf" ENVIRCNMENTRL LRB 1.0-
-1.0
= CCNTRCL
= INDICATCR
.9--
.9 m
m z
z
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SRMPLE PERIOD (MONTHS 1984)
CCNTRCL MONTHS 1-12 RRE LLD's INDICRTCR MONTHS 1,3-12 RRE LLD's 153
FIGURE 26 RIR PRR'ICULRTE COMPOSITE JRF ENVIRCNMENTEL
=
Cs-137 10^-01d 210^-01
=
p Q
= CCNTRCL C
= INDICATCR
=
1 z
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y 7 10^-025 s10^-02 y 7 ee a
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NC CATR FCR YERRS PRICR TC 1S??
CCNTROL YEAR 1984 IS LLD 154
,eee--um e-h.
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FIGURE 27 MILK SAMPLES Cs-137
- Rr ENVIRCNMENTPL LEB
--*-- = CCNTRCL 30.0-
- + - - INcICaTCR
-30.O 27.0-
-27.0 z
z 3
24.0-
-24.0 3 ha
.l ATMCSPHERIC NUCLEFR eN 21.0-TESTS 1978 & 1983
-2{,@ g g s-s._
zu zu O C-18. 0-
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SRMPLE PERIOD (YEAR)
NO CCNTRCL CATR FCR YEPRS 1974-1977 CCNTRCL CATR FCR YEARS 1383,1382-84 RRE LL3's INDICATCR CATR FCR 1984 IS LLD 155
FIGURE 28 MILK SRMPLES j
Cs-137 JRF ENVIRCNMENTRL LAB 20.0-
-20 0
- * - - CCNTRCL 4 43 6'
18.0-
- + - = INDICRTCR e 16
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+
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\\n s,
6.0-
- \\'
- 6. 0
,y,..
3' ~ ~ x
- 4. 0 4.0-2.0-
-20 0.0 0.0 tn e
s es cn cc cu SRMPLE PERIOD (MONTHS 1984)
REFER TO TABLE 617 FCR EXRCT CRTR VALUES AND LLD CCCLRRENCES 156 hm...__
FIGURE 29 MILK SRMPLES Cs-137 187 ENVIRCNMENTRL LAB
--*-- = CCNTRCL 4 4 0 20.0-
- INDICRTCR, ss
-20.0
...*... = INDICATCR 9 7
= INDICRTCR 4 50 18.0-
-18.0 z
z o
16. 0--
-16.0 o n
E'_14.0-
-14.0 E s i_..-
zo zu u a.12.0-
-12.0 W c-o o
z z
8 10.0-
-10.0 0 8.0-
/ '
- 8. 0 g'..
%_l
's.,
\\
6.0-
~ ~ ~ nl.
/*
- 6. 0
.n.
4.0-
' Y' g
A s
- 4. 0 2.0-
- 2. 0 0.0 0.0 i
i i
i i
i LD C.D IN CD CD CD N
SRMPLE PERIOD (MONTHS 1984)
REFER TC TABLE 417 FCR EXRCT CRTR VRLUES AND LLO CCCURRENCES 157
FIGURE 30 MILK SAMPLES I-131 JRF ENVIRCNMENTAL LRB
--*-- - CCNTRCL
= INDICATCR
-5.0 5.0-RTMCseMERIC NUCLEAR f
-4 5 4.5-tests tS78 a tS8e z
Z
-4. 0 o
- 4. 0 -
g H
cJ I
C 3.5-
-3. 5 e N es r.-
F-20 zu
-3 0 W C-u c. 3. 0-o o
z Z
o
.5_
-2.5 u o
c u
2.0-
-2.0
-1.5
- 1. 5 --
3 l /
's, l 's
-1 0 1.0-j'l
's
-0.5 0.5-
- 0. 0,
I 00 i
i i
6 cu m
v y
m e
N cc a
cc N
C3 CD C3 CD CD N,
N N
N N
c en en en en en m
m m
en en SRMPLE PERIOD (YERR)
NO CCNTRCL CRTA FCR 1974-1977 CCNTRCL CRTR FOR 1978-79 RRE MCL's: 1981--64 FRC LL3's INDICATCR CRTR FCR 1979 IS MCL 1981-E. 7RC LLD's
)
158
FIGURE 31 MICK SRMPLES Sr-90 ZRF ENVIRCNMENTRL LRB
--*-- = CCNTROL 10.0--
-10.0 S.0-
- 9. 0 ATMOSPHERIC NUCLEAR 2
2 TESTS 1978 & 1980 3
8.0-
-8.03n
+a-cc -
mx 7.0-
- 7.0 m N i
w-w-
l zu zu 6.0 W C-W C-6.0-u o
s z
z s
8 5.0-
\\,
5.0 8 s
K
/ \\
4.0-
\\,
/
's 4.0
%/
\\
s 3.0 3.0-K
's 2.0--
w*
- 2.0 1.0 1.0-
- 0. 0,
0.0 i
i i
e in c.o N
C3 Cn m
cu m
v N
N N
N N
N CD CD C3 C3 CD C3 CT3 CT3 CD CD C1 CT3 CD CD CD C3 7
SRMPLE PERIOD (YERR)
NO CCNTRCL CRTR FOR YEARS 1974-1977 e
159
I J::me 2 A. FitaP: trick Nuchcr Power PI:nt PO. 80 41 Lycomog. New York 13093 315 342.3840 Harold A. Glovier
- > NewYorkPower 4# Authority March 28, 1985 JAFP-85-0299 United States Nuclear Regulatory Commission Region 1 631 Park Avenue King Of Prussia, Pennsylvania 19406 Attention:
Thomas E. Murley Regional Administrator
SUBJECT:
JAMES A. FITZPATRICK NUCLEAR POWER PLANT RADIO-LOGICAL ENVIRONMENTAL SURVEILLANCE REPORT FACILITY OPERATING LICENSE DPR-59, DOCKET NO. 50-333 Gentlemen:
In accordance with the United States Nuclear Regulatory Comh mission Guide 10.1, we submit the 1984 Annual Environmental Operating Report, Part B: Radiological Report. Distribution for this report is in accordance with Regulatory Guide 10.1.
f s
ROLD A. GLOVIE HAG:
- jaa Enclosure (1)
Copy: EDocument-Control Desk (USNRC)'(18)7
'J'.~ ~ W. - Blake--- (NYPA/WPO)
~
C. A. McNeill, Jr. (NYPA/UPO)
R. Burns (NYPA/WPO)
J. J. Kelly (NYPA/WPO)
J. Toennies (NMPC)
E. Leach (NMPC)
E. Mulcahey B. Gorman J. A. Solini RES File Library Doument Control Center CERTIFIED MAIL, RETURN RECEIPT REQUESTED I
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