ML20246L163
| ML20246L163 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1988 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| Shared Package | |
| ML20246L084 | List: |
| References | |
| NUDOCS 8905180251 | |
| Download: ML20246L163 (177) | |
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NEW YORK POWER AUTHORITY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1,1988 - DECEMBER 31, 1988 FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333 1
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TABLE OF CONTENTS Page 1
INTRODUCTION Introduction 1
j Program Objectives 2
11.
PROGRAM IMPLEMENTATION AND DESIGN 3
1.
Sample Methodology 4
2.
Analysis Performed 9
l 3.
Changes in Program 10 4.
Exceptions to the Program 11 5.
Operational Radiological Environmental 13 Monitoring Program (Table) 6.
Statistical Methodologies 16 111.
SAMPLE SUMMARIES 19 IV.
ANALYTICAL RESULTS 25 V.
DATA SUMMARIES AND CONCLUSIONS 81 A.
Surface Water (Lake) Program 85 l
B.
Terrestrial Program 97 C.
Conclusion 126 D.
References 128 I
l VI.
HISTORICAL DATA 130 Vll.
FIGURES AND MAPS 139 Vill.
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY 158 LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS
)
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LIST OF TABLES Page Table i Required Sample Collection and Analysis 13 (1/1/88 - 12/31/88)
Table 11 Detection Capabilities For Environmental Sample 18 Analysis, Lower Limit of Detection (LLD)
Table 1 Shoreline Sediment Results 26 Table 2 Fish Results 27 Table 3 Surface Water Composite Results, Tritium 29 Table 4 Surface Water Composite Results, Gamma Isotopic 31 Table 5 Particulate Filter Results, Gross Beta (Offsite) 36 Table 6 Particulate Filter Results, Cross Beta (Onsite) 38 I-Table 7 Airborne 1-131 Results (Offsite Stations) 40 Table 8 Airborne I-131 Results (Onsite Stations) 42 Table 9 Particulate Composite Results, Gamma Isotopic 44 Table 10 TLD Results 60 Table 11 Milk Results,1-131 64 Table 12 Milk Results, Gamma Isotopic 67 Table 13 Milch Animal Census Results 71 Table 14 Food Product Results, Gamma Isotopic 73 Table 15 Site Boundary Vegetation Results, Camma Isotopic 75 l
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Table 16 1988 Residence Census 76 I
l Table 17 Environmental Sample Locations 77 Table Vlli-1 Gross Beta Analysis Air Particulate (pCi/ filter) 159
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and Water (pCi/L)
Table Vill-2 Tritium Analysis of Water (pCi/L) 160 Table Vill-3 lodine Analysis of Water (pCi/L) and Milk 161 (pCl/L) l I
Table Vlli-4 Gamma Analysis of Milk, Water (pCi/L), Air 162 l
Particulate (pCi/ filter) and Food Products (pCi/kg)
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1 LIST OF FIGURES Page I
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Figure 1 A Offsite Environmental Stations and TLD Locations 140 i
Figure 1B Offsite Environmental Stations and TLD Locations 141
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(Southern) l I
Figure 2 Offsite and Onsite Environmental Stations, 142 l
I TLD Locations Figure 3 Nearest Residence and Food Product Locations 143 I
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Figure 4 Milch Animal Census and Milk Sample Locations 144 Figure 5 New York State Regional Map 145 Figure 6 Graph - Fish (Cs-137) 146 Figure 7 Graph - Air Particulate Gross Beta 147 Figure 8 Graph - Air Particulate Gross Beta, Weeks 1-26 148 (1988)
Figure 9 Graph - Air Particulate Gross Beta, Weeks 27-52 149 (1988)
Figure 10 Graph - Air Particulate Composite (Co-60) 150 Figure 11 Graph - Air Particulate Composite (Cs-137) 151 Figure 12 Graph - Milk (Cs-137) 152 Figure 13 Graph - Milk (Cs-137), Stations 60, 55 and Control 153 for 1988 Figure 14 Graph - Milk (Cs-137), Stations 50, 7 and Control 154 for 1988 1
Figure 15 Graph - Milk (Cs-137), Stations 4,16 and Control 155 i
for 1988 I
Figure 16 Graph - Milk (1-131) 156 Figure 17 Graph - TLD Data 157 i
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INTRODUCTION I
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I l-A INTRODUCTION I
The New York Power Authority (NYPA) is the owner and licensee of the James A.
FitzPatrick Nuclear Power Plant (J AFN PP).
The FitzPatrick Plant is located on the eastern portion of the Nine Mlle Point promontory approxi-mately one-half mile due east of the Niagara Mohawk Power Corporation I
(NMPC) Nine Mile Point Nuclear Power Stations (NMPNPS).
The NMPNPS Unit
- 1 is located on the western portion of the site and is a boiling water reactor with a design capacity of 620 MWe.
The NMPNPS Unit #1 has been in com-I mercial operation since the fall of 1969.
Located between the J AFNPP and NMPNPS Unit #1, is Nine Mile Point Unit #2 previously under construction and completed in mid-1987 NMPNPS Unit #2 began commercial operation in March of 1988 and has generation capacity of 1,100 MWe, The JAFNPP is a boiling I
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 or, the southern shore of Lake Ontario in Oswego I
County, New York, approximately seven miles northeast of the city of Oswe-go, 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 consists of partially wooded land and shoreline.
The land adjacent to the site is used I
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 la ke, composed mainly of glacia.i deposits.
Approximately 34 percent of the land area in Oswego County is devoted to farming.
The Radiological Environmental Monitoring Prog ram for the Fitz 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 sampling and analysis to be a joint undertaking.
Data generated by the program is shared by the two facilities with review and publication of the data under-taken through each organization.
This report is submitted in accordance with Section 7.3.d of the Radiological Effluent Technical Specifications (RETS) to D PR-5 9, Docket 50-333.
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I l-B PROGRAM OBJECTIVES I
The objectives of the Radiological Environmental Monitoring Program are as follows:
1.
To determine and evaluate the effects of plant operation on the environs I
and to verify the effectiveness of the controls on radioactive material sources.
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To monitor and evaluate natural radiation levels in the environs of the
-j JAFNPP site.
I 3.
To meet the requirements of applicable state and federal regulatory guides and limits.
4.
To provide in formation by which the general public can evaluate the I
environmental aspects of nuclear power using data which is factual and unbiased.
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PROGRAM IMPLEMENTATION AND DESIGN.
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- > NewYorkPower tv Authority i
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I ll PROGRAM IMPLEMENTATION AND DESIGN I
To achieve the objectives listed in Section I-B, sampling and analysis are performed as outlined in Table 1.
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 Mile Point Station.
The site staff is assisted by a contracted environmental engineering company, EA Science and Technology, Inc. (EA).
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SAMPLE COLLECTION METHODOLOGY A.
Surface Water j
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Surface water samples are taken from the respective inlet canals of
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JAFNPP and Niagara Mohawk's Oswego Steam Station (OSS).
The i
JAFNPP removes water from Lake Ontario on a continuous basis and I
generally represents a "down-current" sampling point from the Nine l
Mile Point Unit 1 facility.
The OSS inlet canal removes water from
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Lake Ontario at a point approximately 7.6 miles west of the site.
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This "up-current" location is considered a control location because i
of the distance from the site as well as lake current patterns and current patterns from the Oswego River located nearby.
Samples from the JAFNPP are composited from automatic sampling equipment which discharges into a compositing tank.
Samples are obtained from the tank monthly and analyzed for gamma emitters.
I Samples from the OSS are also composited from automatic sampling equipment and discharged to a compositing tank.
Samples from this location are obtained weekly and composited to form monthly com-posite samples.
Monthly samples are analyzed for gamma emitters.
A portion of the monthly samples from each of the locations is saved and composited to form quarterly composite samples for calendar I
quarter.
Quarterly composite samples are analyzed for Tritium, g
in addition to the FitzPatrick and Oswego Steam Station facilities, E
dt are presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canals and city water from the City of Oswego.
The latter three locations are not required by the Technical Specifications, ut I
are optional samples.
Monthly composite samples from these three locations are analyzed for gamma emitters and quarterly composite samples are analyzed for Tritium.
Surface water sample locations are shown in - Section Vll on Figure 1A.
l B.
Air Particulate / lodine The air sampling stations required by the RETS are located in the I
general area of the site boundary (within 0.7 miles) in sectors of highest calculated meteorological deposition factors (D/Q) based on historical meteorological data.
These stations (R-1, R-2, and R-3) are located in the east, east-southeast, and southeast sectors as I
measured from the center of the Nine Mile Point Nuclear Station l8Mt 2 reactor building.
The RETS also require that a fourth air sampling station be located in the vicinity of a year round communi-I ty having the highest calculated dispersion factor (D/Q) based on historical meteorological data.
This station is located in the south-east sector (R-4).
A fifth station required by the RETS is located at a site 16.4 miles from the site in a least prevalent wind direction I
of east-northeast (R-5).
This location is considered a control lo-cation.
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I in addition to the RETS required locations, there are six other sampling stations located within the site boundary (DI, G, H, I, J, and K).
Thue locations generatiy surround the area occupied by the three generating facilities, but are well within the site bounda-l ry.
One other air sampling station is located off-site in the south-west sector and is in the vicinity of the City of Oswego (G off).
Three remaining air sampling stations (D2, E, F) are located in the l
ESE, SSE, and S sectors and range in distance from
- 7. 2 to 9.0 5
miles.
At each station, airborne particulate are collected by glass fiber filters and radiolodine by charcoal cartridges.
Air particulate glass fiber filters are approximately two inches (47 millimeters) in diame-ter and are placed in sample holders in the intake line of a vacuum i
sampler.
Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to adsorb airborne radiolodine.
The samplers run continuously and the charcoal cartridges and particu-3 late filters are changed on a weekly basis, or as required by dust g
loading.
Gross beta analysis is performed for the individual par-ticulate filters on a weekly basis.
Charcoal cartridges are analyzed weekly for radiolodine by a Ge(LI) or Ge detector.
The particulate filters are composited for gamma analyses on a monthly basis by location after all weekly particulate filters have E
been counted for gross beta activity.
3 Air sampling stations are shown in Figures 1 A,1B, and 2.
C.
Milk Milk samples are collected in polyethylene bottles from the bulk E
storage tank at each sampled farm.
Before the sample is drawn, 5
the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat.
Two gallons are col-g lected during the first half and second half of each month from E
each of the selected locations within ten miles of the site and from a control location.
The samples are chilled and shipped to the ana-lytical laboratory within thirty-six hours of collection in insulated shipping containers.
Milk sample location selection is based on maximum deposition factors Rl (D/Q).
Deposition factors are generated from average historical 5) meteorological data based on all licensed reactors.
The Technical i
Specifications require three sample locations within 5.0 miles of the g j site with the highest calculated deposition factors.
During 1988, g ]!
there were no milk sample locations within 5.0 miles that could be sampled.
However, there were a number of locations beyond five miles that were sampled.
A fourth sample location required by the Technical Specifications is located in a least prevalent wind direction from the site.
This 3
location is in the southwest sector and serves as a control location.
3 Milk samples are collected twice per month (April - December) and I}!
analyzed for gamma emitters and 1-131.
Samples are collected and 5
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analyzed in January - March in the event 1-131 is detected in No-venber and December of the preceding year.
The milk sampling locations are found in Section Vil on Figure 4 D.
Food Products / Site Boundary Vegetation Samples of three different kinds of broad leaf vegetation (edible or inedible) are collected during the late summer harvest season.
Sample collections are performed at the site boundary in two dif-l-
ferent direction sectors having the highest calculated D/0 values.
l The broad leaf vegetation is chilled prior to shipping and shipped fresh in insulated containers.
Attempts are made to collect control
,I' samples located 9-20 miles distant for each type of sample.
Food products sampling as required by Table 6.1-1 (Section A r, B under l
Food Products) are not performed, This form of food products sampling is only required when milk sampling is not being per-I formed.
In 1988 a number of food product samples were collected and analyzed to supplement the broad leaf vegetation sampling prog ram.
The broad leaf vegetation and food products sampling locations are shown in Section Vil on Figure 3.
E.
Fish Samples Available fish species are removed from the Nine Mile Nint Aquatic Ecology Study monitoring collections during the spring and fall collection periods.
Samples are collected from a combination uf the four onsite sample transects and one offsite sample transect (see Section Vil, Figure 1 A).
Available species are selected under the following guidelines:
1) 0.5 to 1 kilogram of edible portion cnly of a maximum of three species per location.
2)
Samples composed of more than 1 kilogram of single species from the same location are divided into samples of 1 kilogram each prior to shipping.
A maximum of three samples per spe-I cies per location ere used.
Weight of samples are the edible portions only.
Selected fish samples are frozen immediately after collection and I
segregated by species and location.
Samples are shipped frozen in insulated containers for analysis.
F.
Shoreline Sediments One kilogram of shoreline sediment is collected at one area of exist-I ing or potential recreational value and from one aret beyond the influence of the site.
The samples are placed in plastic bags, scaled and shipped for analysis in insulated containers.
Shoreline sediment locations are shown in Section Vll on Figure 1 A.
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TLD (direct radiation)
Thermoluminescent dosimeters (TLD's) are used to measure direct radiation (gamma dose) in the environment.
TLD's are obtained from Teledyne isotopes on a quarterly basis and are read at Tele-dyne isotopes' facility in Westwood, New Jersey.
Shipment control TLD's (at least two) accompany each shipment to and from the g
vendor's laboratory.
Shipment control TLD's also accompany the 3
TLD's when they are being placed or collected and are shielded by lead when they are not being used.
TLD data results are corrected g
for a transit dose by use of the data from the shipment control g
TLD's.
Five different types of areas are evaluated by environmental TLD's.
These areas include on-site areas (areas within the site boundary not required by the RETS), the site boundary area in each of the sixteen meteorological sectors, and outer ring of TLD's (located g
four to five miles from the site in eight available land based g
meteorological sectors), special interest TLD's (located at sites of high population density) and control TLD's located at sites beyond significant influence of the site.
Special interest TLD's are located at or near large industrial sites, schools, or proximal towns or communities.
Control TLD's are located to the southwest, south and east-northeast of the site at distances of 12.6 to 19.8 miles.
TLD's used during 1988 were composed of rectangular teflon wafers impregnated with 25 percent CaSO :Dy phosphor.
These were a
3 placed in a polyethylene package tb ensure dosimeter integrity.
g TLD packages were placed in open webbed plastic holders and were attached to supporting structures, usually trees or utility poles.
Environmental TLD locations are shown in Section Vil on Figures 1A, 18, and 2.
H.
Land Use Census 4
A land use census is conducted during the beginning of the grazing j
season to determine the utilization of land within the vicinity of the site.
The land use census consists of two types of census.
A milk animal census is conducted to identify all milk animals within a distance of ten miles from the site.
This census is conducted by 31' using road surveys, contacting. local agricultural authorities, post E
cards, and investigating references from other owners.
A second type of census is a residence census.
This census is conducted in order to identify the closest residence in each of the 221 degree meteorological sectors.
A residence, for the purpose of this census, is a residence that is occupied on a part time basis 4
(such as a summer camp) or on a full time, year round basis For the residence census, several of the me' horological sectors are over Lake Ontario because the site is locatec at the shoreline.
No resi-g dences are located in these sectors.
There are only eight sectors 3I over land where residences are located within five miles.
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Interlaboratory Comparison Program An interlaboratory comparison program is conducted with reference I
samples originating from the Environmental Protection Agency (EPA).
As required by the Technical Specifications, participation in this program includes media for which environmental samples are routinely collected and for which intercomparison samples are avail-I able.
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ANALYSIS PERFORMED The analysis of the majority of environmental samples is performed by the James A.
FitzPatrick Environmental Counting Laboratory (JAFECL).
TLD and milk l-131 analysis are performed by Teledyne isotopes (TI).
The following samples are analyzed at the JAFECL:
o Air Particulate Filter gross beta (weekly) l o Air Particulate Filter Composites gamma spectral analysis l
(monthly) o Airborne Radioiodine - gamma spectral analysis (weekly) o Surface Water Composites - gamma spectral analysis (monthly) o Special Samples (soil, etc.)
gamma spectral analysis (as I
collected) o Fish - gamma spectral analysis o Shoreline Sediment - gamma spectral analysis o Milk - gamma spectral analysis Quality assurance samples are analyzed by Teledyne isotopes and the Yankee Atomic Environmental Counting Laboratory.
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CHANGES TO THE 1988 SAMPLE PROGRAM i
A.
Two additional control TLD's were added to the program starting in the second quarter 1988.
TLD #110 and #111 were added to supple-ment the existing three control TLD locations.
These TLD locations are not required by Technical Specifications.
I B.
Two additional indicator TLD's were added to the program starting in the second quarter 1988.
TLD #108 and #109 located in the general vicinity of the residence of interest in the ESE meteoro-logical sector.
These TLD locations are not required by Technical J
Specifications,
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,I C.
An additional food product location (x) was added to the monitoring l
prog ram.
This location was added due to its close proximity to the i
site boundary.
Locations S, N and V, which were sampled in 1987, were not sampled in 1988.
Food product sampling is not required 1
by the FitzPatrick N.P.P. Technical Specifications.
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EXCEPTIONS TO THE 1983 SAMPLE PROGRAM Exceptions to the 1988 sample program concern those sampling or monitoring requirements which are required by the JAF Technical Specifications.
A.
Air radiciodine and air particulate monitoring required by Technical l
Specifications.
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The air sampling pump at R-3, off-site Environmental Sanplir.g Station was inoperable from January 01, 1988 (1036 hours0.012 days <br />0.288 hours <br />0.00171 weeks <br />3.94198e-4 months <br />) to February 22,1988 (0833 hours0.00964 days <br />0.231 hours <br />0.00138 weeks <br />3.169565e-4 months <br />).
Inoperability was caused by a pump mechanical failure.
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The air sampling pump at R-4, off-site Environmental Sampling Station was inoperable from May 08, 1988 (2324 hours0.0269 days <br />0.646 hours <br />0.00384 weeks <br />8.84282e-4 months <br />) to May 10,1988 (0900 hours0.0104 days <br />0.25 hours <br />0.00149 weeks <br />3.4245e-4 months <br />).
Inoperability was caused by a pump mechanical failure.
Other occurrences of downtime for optional air sampling station.s were documented for 1988.
These occurrences are not noted in this report because the optional air sampling stations are not required by Technical Specifications.
Documentation includes downtime for air sampling equipment as well as environmental radiation monitoring E
equipment.
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OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Table I describes the requirements of the Radiological Environmental I.
Monitoring Program as specified by the J. A. FitzPatrick N.P.P.
Technical Specifications.
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6.
STATISTICAL METHODOLOGY A.
Estimation of the Mean and Standard Deviation.
The mean, (x), and standard deviation, (s), were used in the reduction of the data generated by the sampling and analysis of the I
various media in the J. A. FitzPatrick N.P.P. Radiological Environ-mental Monitoring Program.
The following equations were utilized to estimate the mean (X) and the standard deviation (s):
N i
i=1 X
=
N where,
estimate of the mean.
X
=
I individual sample, i.
i
=
total number of samples with positive indications.
N
=
x; value for sample i above the lower limit of detection.
=
N (x; -x)2 i=1 s =
N-1
- where, standard deviation for the sample.
s
=
I These equations were used in the reduction of the 1988 radiological environmental monitoring data.
I I
16 i
I B.
Lower Limits of Detection (LLD)
The LLD is a predetermined concentration or activity level used to establish a detection limit for the analytical procedures.
The LLD's are specified by the Nuclear Regulatory Commission for each radionuclides in specific media and are determined by taking into account overall measurement methods.
The equation used to calculate the LLD is:
I 4.66 s LLD =
b E. V. 2. 22. Y. exp (- AAt) where:
LLD is the a priori lower limit of detection, as defined above (in picocurie per unit mass or volume):
is the standard deviation of the background counting rate or of s g the counting rate of a blank sample, as appropriate (in counts per minute);
E is the counting efficiency (in counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie, Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclides; at is the elapsed time between sample collection (or end of the sample collection period) and time of counting.
In the RETS program, LLD's are used to ensure that minimum acceptable detection capabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative).
Table 11 presents the RETS program required LLDs for specific media and radionuclides as specified by the NRC.
The LLDs actually achieved are usually much lower since the
" required LLD's" represent the maximum allowed, i
I 17
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I I
I SAMPLE SUMMARIES I
I I
I O
~~
I I
I Ill SAMPLE SUMMARIES All sample data is summarized in table form.
The tables are titled
" Radiological Monitoring Program Annual Summary" and use the follow-ing format:
A.
Sample medium.
B.
Type and number of analyses performed.
C.
LLD (Lower Limits of Detection).
This wording. indicates I
that inclusive data is based on 4.66 sigma of background (see section !!, 6, B).
D.
The mean and range of the positive measured values of the I
indicator locations.
E.
The mean, range, and location of the highest indicator I
annual mean.
F.
The mean and range of the positive measured values of the control locations.
G.
The number of nonroutine reports sent to the Nuclear Regulatory Commission.
I NOTE:
Only positive measured values are used in statistical calcu-lations.
The use of LLD's in these calculations would result I
in means being biased high.
I I
I I
! I 19
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v I
ANNUAL
SUMMARY
TABLE NOTES I
Data for the Annual Summary Tables is based on RETS l
=
required samples enly, except for TLD locations #99-101 which are included but are not RETS locations.
'I N/A =
Not applicable.
I (a)
Fraction of detectable measurement to total measurement.
=
(b)
Location is distance in miles, and direction in compass
=
degrees.
I (c)
Indicator TLD locations are: #7, 23, 75, 76, 77, 78, 79,
=
80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, I
94, 95, 96, 97, 98, 99, 100, 101, 8,
15, 18, 56, and 58 Control TLD's are all TLD's located beyond the influence of the site (#14, 49).
(All are RETS locations except
- 99-101.)
I (d)
Indicator samples from environmental stations R1 offsite,
=
R2 offsite, R3 offsite, and R4 offsite.
Control samples are samples from R5 offsite environmental station.
( e )' =
This dose is not representative of doses to a member of the public since this area is located near the north shoreline which is in close proximity to the generating I
facility and is not accessible to members of the public (see Section V.4-TLD's).
I (f)
The RETS criteria for indicator milk sample locations
=
includes locations within 5.0 miles of the site.
There are no milk sample locations within 5.0 miles of the site.
I Therefore, milk samples are collected from locations greater than 5.0 miles from the site based on site D/Q values.
I The RETS do not specify a particular LLD value for surface (g)
=
water analysis (non-drinking water) for 1-131.
A value of
.E 15 pCl/ liter is used here and represents the most recent 5
guidance from the NRC.
I I
24 I
I I
I i
I IV l
I I
jg I
o, I
I AN ALYTICAL RESULTS I
I I
I C L".Y#""
g I
IV ANALYTICAL RESULTS Environmental Sample Data b
Environmental sample data is summarized by tables.
7 ables are pro-vided for select sample media and contain data based on actual values I
obtained over the year.
These values are comprised of both positive val-ues and LLD values where applicable, q
The LLD is the smallest concentration of radioactive material in a
( '
sample that will be detected with 95% probability and with 5% probability of
{
falsely concluding that a blank observation represents a "real" signal.
I For a particular measurement system (which may include radiochemical separation ),
S b
I LLD =
E. V. 2.22 Y. exp (-Aat)
Where:
I LLD is the a priori lower limit of detection, as defined above (in picocurie per unit mass or volume);
s is the standard deviation of the background counting rate or of the chunting rate of a blank sample, as appropriate (in counts per minute);
E is the counting efficiency (in counts per transformation);
V is the sample size (in units of mass or volume);
2.22 is the number of transformations per minute per picocurie; Y is the fractional radiochemical yield (when applicable);
A is the radioactive decay constant for the particular radionuclides; At is the elapsed time between sample collection (or end of the sample col-lection period) and time of counting.
' I LIlI
! I 25 I
8 4
1 8
8 1
1 1
0 2
2 0
O 0
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2 2
2 2
2 1
t N e 1
a O R
/
0 0
0 0
0 0
c C
7 o
0 l
e lp m
8 a
8 s
/
4 9
9 0
8 9
5 2
3 1
2 1
1 o
0 t
/
0 0
0 0
0 0
7 s
0 dnop ser
)
n l
r o
0 5
0 6
5 o o
i 6
5 5
7 4
1 6 r C
t tn a
t o
o o
o o
o o o s
N N
N N
N N
N C
(
l' l'
M 8
8
/
5 9
9 9
5 1
8 M
9 2
1 1
1 1
2 1
1
/
0 0
0 0
0 0
0 2
1 M
8 8
M
/
8 6
0 1
8 3
5 5
1 1
2 2
1 2
2 0
/
0 0
0 0
0 0
0 2
M 1
I IV KL a n
1 m o
M iF g
8 i
i 8
t N s
/
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9 5
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4 2
4 2
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)
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0 0
0 0
G M
d 3
1 e
1 1
4 u
- 1 n
E /
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M t
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8 i
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/
5 9
6 9
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9
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o 1
t
/
0 0
0 0
0 0
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d E
N n 1
e L
O U t
B I
o A
T n n
T A i R
s T s 8
n N t 8
o M
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/
8 3
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3 i
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2 2
2 3
2 ta N s 1
O e
/
0 0
0 0
0 0
0 c
C R 0
o 1
l M
e lp m
M 8
a 8
s
/
2 9
1 8
8 3
O 3
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2 1
2 2
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t
/
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0 0
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er
)
n l
r o
0 5
0 6
5 o o
i 6
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tn a
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N N
N N
N N
N C
(
M m
lll!ll1ll.
I
I l
s TABLE 12 CONCENTRATIONS OP GAMMA EMITTERS IN MILK Results in Units of pCi/1 1 2 sigma Station
- Nuclides 04/04/88 04/18/88 05/02/88 05/16/88 06/06/88 06/20/8 No. 60 K-40 1490 162 17101140 13601191 16401169 1440il58 1570113g Cs-134
<6.51
<5.43
<6.00
<6.36
<6.65
<5.15 g Cs-137
<6.69
<5.74
<7.45
<6.29
<7.78
<6.42 Ba/La-140
<4.58
<5.84
<6.50
<3.25
<6.09
<3.56 Others Ra-226
<LLD
<LLD Ra-226
<LLD
<LLD 152175.3 2321138 No. 55 K-40 15001187 15001141 11601167 15001139 14201136 1440113g Cs-134
<5.37
<5.22
<7.50
<4.16
<4.79
<4.49 3 Cs-137
<7.07
<5.80
<7.77
<6.01
<5.58
<5.23 Ba/La-140
<5.85
<4.67
<6.17
<5.58
<4.70
<6.02 Others
<LLD
<LLD
<LLD AcTh-228 Ra-226 Ra-226 14.019.94 92.6164.1 92.9153.
1500117j No. 50 K-40 14501136 14501162 14801136 13601187 13601150 Cs-134
<5.10
<6.28
<5.04
<6.50
<6.13
<7.94 m Cs-137
<5.19
<8.27
<5.27
<B.89
<7.52
<8.77 Ba/La-140
<3.96
<7.90
<5.00
<9.50
<8.54
<8.12E Others
<LLD
<LLD
<LLD
<LLD Ra-226
<LLD g 150173.1 No. 7 K-40 1680 141 13701176 15501133 15401180 9281227 1510113 Cs-134
<5.30
<6.40
<5.26
<7.20
<6.80
<5.60 Cs-137
<5.22
<7.64
<6.06
<9.35
<7.95
<6.01 Ba/La-140
<3.70
<6.90
<5.68
<6.77
<4.78
<3.45 Others
<LLD
<LLD
<LLD Ra-226 Ra-226
<LLD 2311116 183197.4 No. 4 K-40 13601133 15301135 13701172 14101134 15601134 1530i13 Cs-134
<5.51
<5.56
<7.39
<4.92
<4.94
<5.33 Cs-137
<6.35
<6.47
<8.54
<5.35
<6.01
<5.45 Ba/La-140
<5.84
<4.78
<8.32
<5.60
<4.73
<4.85 Others
<LLD
<LLD
<LLD
<LLD Ra-226
<LLD 132170.5 No. 16 K-40 17201141 13801192 15601204 15101141 1530 141 1360 17 Cs-134
<5.52
<8.48
<8.11
<5.17
<4.52
<6.11 Cs-137
<6.89 10.0 5.89
<9.37
<7.62
<5.73
<8.88 Ba/La-140
<4.55
<3.59
<7.94
<4.87
<4.66
<5.24 Others
<LLD
<LLD Ra-226
<LLD
<LLD
<LLD 140184.1 No. 65 K-40 1520 186 13901181 17101139 15301180 1700 140 14901161 (Control)
Cs-134
<6.16
<6.16
<5.03
<6.77
<4.27
<6.80 Cs-137
<6.45
<8.03
<5.96
<7.94
<5.22
<7.18E Ba/La-140
<6.84
<5.09
<5.98
<5.82
<3.69
<4.48 g Others
<LLD
<LLD
<LLD
<LLD Ra-226
<LLD
- Corresponds to sample locations noted on Figure 4,Section VII.
67
I TABLE 12 (Continued)
I-CONCENTRATIONS OF CAMMA EMITTERS IN MILK Results in Units of pCi/1 1 2 sigma Station
- Nuclides 07/05/88 07/18/88 08/08/88 08/22/88 No. 60 K-40 15201139 14901130 15701141 13201167 I
Cs-134
<4.93
<4.41
<4.92
<7.28 Cs-137
<5.30
<5.30
<5.07
<7.56 Ba/La-140
<1.91
<4.28
<4.90
<6.48 I
Others Ra-226
<LLD
<LLD
<LLD 162187.2 No. 55 K-40 15301159 16501169 17001286 14601137 I
Cs-134
<5.75
<6.07
<11.3
<4.00 Cs-137
<6.90
<6.22
<12.7
<5.60 Ba/La-140
<2.36
<4.44
<13.4
<4.23 Others Ra-226
<LLD
<LLD
<LLD 151175.4 I
No. 50 K-40 17301137 14901159 15001139 13201171 Cs-134
<5.37
<5.83
<4.49
<6.35 Cs-137
<5.41
<7.18
<5.60
<7.82 Ba/La-140
<4.30
<6.31
<5.97
<7.83 I
Others
<LLD
<LLD
<LLD
<LLD I
No. 7 K-40 14401134 17001137 14501125 16501250 Cs-134
<4.55
<5.36
<4.71
<9.50 Cs-137
<4.83
<5.93
<5.30
<14.2 Ba/La-140
<1.82
<4.09
<4.00
<14.0 I
Others
<LLD Ra-226 Ra-226
<LLD 104178.7 137177.8 No. 4 K-40 14701157 15501128 13301222 13801131 Cs-134
<6.38
<5.56
<8.86
<4.81 Cs-137
<6.72
<5.01
<10.7
<5.15 I
Ba/La-140
<4.93
<4.75
<14.7
<5.09 Others
<LLD
<LLD
<LLD
<LLD No. 16 K-40 15501181 15401180 1420 201 17001135 Cs-134
<6.23
<6.10
<7.78
<5.53 Cs-137
<9.42
<10.3
<9.78
<5.83 I
Ba/La-140
<4.28
<5.72
<10.8
<6.41 Others
<LLD
<LLD
<LLD
<LLD No. 65 K-40 15701162 13601172 14701137 16001163 (Control)
Cs-134
<6.23
<7.94
<4.87
<5.91 Cs-137
<7.44
<7.95
<5.23
<8,57 I
Ba/La-140
<6.56
<7.63
<1.81
<5.93 Others
<LLD
<LLD
<LLD Ra-226 2311144
- Corresponds to sample locations noted on Figure 4,Section VII.
68
I TABLE 12 (Continued)
CONCENTRATIONS OF GAMMA EMITTERS IN MILK Results in Units of pCi/1 1 2 sigma Station
- Nuclides 09/06/88 09/19/88 10/03/88 10/17/88 No. 60 K-40 17101136 16601168 1630 131 1520i140 g
Cs-134
<5.15
<6.94
<5.15
<4.93 g
<5.78
<7.44
<5.73
<5.07 Ba/La-140
<4.81
<7.37
<5.00
<5.97 l
Others
<LLD
<LLD
<LLD Ra-226 135 77.4 m
No. 55 K-40 14501259 16201133 15601131 15201178 Cs-134
<11.7
<6.07
<4.98
<6.77 Cs-137
<15.2
<5.41
<5.60
<7.82 Ba/La-140
<10.9
<4.28
<5.03
<7.68 Others
<LLD
<LLD
<LLD
<LLD No. 50 K-40 15601131 14801127 15001137 14801175 Cs-134
<4.51
<4.80
<5.38
<6.67 Cs-137
<5.07
<5.52
<5.45
<7.16 Ba/La-140
<3.68
<5.03
<4.55
<5.21 Others
<LLD
<LLD
<LLD
<LLD No. 7 K-40 1200 250 1580 130 14401132 1520il28 Cs-134
<11.8
<4.66
<4.98
<5.06 Cs-137
<14.9
<5.57
<4.83
<6.13 Ba/La-140
<14.9
<3.73
<5.20
<4.80 g
Others
<LLD Ra-226
<LLD
<LLD 3
90.0177.6 No. 4 K-40 1520 186 15101158 1540i163 1460 136 Cs-134
<7.67
<6.45
<6.45
<4.68 Cs-137
<B.77
<6.81
<8.49
<5.52 I
Ba/La-140
<6.44
<7.03
<4.45
<4.58 Others
<LLD
<LLD
<LLD
<LLD No. 16 K-40 15301138 16501166 17301169 1560 162 Cs-134
<4.86
<7.40
<6.37
<5.91 Cs-137
<6.52
<7.00
<8.42
<7.00 Ba/La-140
<4.54
<4.46
<6.71
<6.70 Others
<LLD Ra-226 AcTh-228 Ra-226 155186.2 26.7114.4 194183.5 No. 65 K-40 15301160 14901178 15401131 15601181 (Control)
Cs-134
<6.22 (6.99
<5.61
<7.19 Cs-137
<6.90
<5.96
<5.24
<6.74 g
Ba/La-140
<6.30
<6.02
<6.28
<6.65 g
Others
<LLD
<LLD Ra-226
<LLD 149188.7
- Corresponds to sample locations noted on Figure 4,Section VII.
69 I
I TABLE 12 (Continued)
CONCENTRATIONS OF CAMMA EMITTERS IN MILK Results in Units of pCi/1 2 sigma Station
- Nuclides 11/07/88 11/21/88 12/05/88 12/19/88 No. 60 K-40 15801132 1500 160 13201128 14101133 I
Cs-134
<5.44
<6.80
<5.27
<4.55 Cs-137
<5.78
<7.78
<4.83
<4.99 Ba/La-140
<5.04
<3.89
<5.48
<4.55 Others
<LLD
<LLD
<LLD
<LLD No. 55 K-40 14801156 15201181 16801166 15201131 I
Cs-134
<6.66
<7.76
<6.87
<5.32 Cs-137
<7.61
<8.54
<7.18
<5.13 Ba/La-140
<4.47
<7.12
<6.31
<4.08 Others
<LLD
<LLD
<LLD
<LLD I
No. 50 K-40 16001180 1520184 17201138 14301125 Cs-134
<7.28
<4.48
<4.89
<6.35 Cs-137
<7.69
<5.94
<5.52
<5.83 Ba/La-140
<7.65
<4.58
<4.31
<4.35 I
Others
<LLD
<LLD
<LLD
<LLD No. 7 K-40 15501138 16401134 13001168 16401186 Cs-134
<5.88
<4.98
<7.48
<9.82 Cs-137
<4.'9
<6.56
<8.99
<9.53 4
Ba/La-140
<5.97
<5.66
<8.10
<8.12 I
Others
<LLD
<LLD
<LLD
<LLD I
No. 4 K-40 17001189 15701132 17201136 17101135 Cs-134
<7.94
<4.93
<4.56
<4.89 Cs-137
<7.69
<6.28
<5.01
<6.23 I
Ba/La-140
<7.05
<2.49
<3.55
<5.22 Others
<LLD
<LLD
<LLD Ra-226 162180.9 No. 16 K-40 1620 186 16001132 15701178 16501165 Cs-134
<7.66
<5.32
<7.39
<6.22 Cs-137
<9.21
<6.60
<9.10
<7.95 I
Ba/La-140
<5.72
<3.84
<8.55
<7.08 Others
<LLD
<LLD
<LLD Ra-226 86.4171.2 No. 65 K-40 15601144 13701185 15601180 15501160 (Control)
Cs-134
<3.61
<6.37
<6.88
<6.66 Cs-137
<5.60
<8.03
<8.31
<6.52 I
Ba/La-140
<4.53
<3.85
<5.76
<5.44 Others
<LLD
<LLD
<LLD Ra-226 180184.1
- Corresponds to sample locations noted on Figure 4,Section VII.
70 I
TABLE 13 MILCH ANIMAL CENSUS 1988 I
NUMBER OF NUMBER I
DEGREES ( }
DISTANCE (
OF MILCH ANIMALS TOWN OR AREA (a)
CENSUS MAP Scriba 1(b) 220' 3.0 miles None 16*
390' 5.2 40C 2
1s5' 8.0 ND 3(b) 190' 4.5 None 6(b) 62*
2.2 1C 26(b) 115*
1.6 ND l
61(b) 140' 3.0 1C, 1C 5
62 183' 6.7 BC 63 185*
8.0 40C New Haven 8
130' 9.2 30C 9
95*
5.2 40C 4*
113' 7.8 90C 45 125' 8.0 None 10(b) 130' 2.6 29C g
5 146' 7.2 49C g
11 130' 8.5 17C 7*
107' 5.5 75C 64 107' 7.9 49C Mexico 12 107' 11.5 21C l
l 13 114" 11.2 None 5
l 14 120' 9.8 62C l
15 100' 10.8 4C 17 115' 10.2 3C 18 110' 10.0 None 19 132' 10.5 42C 20 123' 11.2 None 60*
90' 9.5 40C 50*
93*
8.2 200C 55*
95*
9.0 570 l
21 112*
10.5 800 5
49 88*
7.9 3G Richland 22 85*
10.2 43C Pulaski 23 92*
10.5 90C Oswego 24 214' 8.8 None I<
i 71 gj ul i
I TABLE 13 (Continued)
MILCH ANIMAL CENSUS 1988 NUMBER OF (
NUMBER l
TOWN OR AREA (a)
CENSUS MAP DEGREES ( )
DISTANCE ( ) 0F MILCH ANIMALS I
I Hannibal 40 220' 15.2 None I-Sterling 65**
220*
17.0 45C Volney 25 182' 9.5 None 70 147' 9.4 200, 1G 66 158' 7.8 700 67 152' 8.3 2G I
TOTALS:
Within 10 miles 910 Cows 15 Goats Entire Census 1238 Cows 15 Goats I
I i
C - Cows G = Goats
- = Milk sample location
- = Milk sample control location KD - Did not wish to participate in the survey (1) - References Figure 4 l
(2) = Based on Nine Mile Point Unit 2 Reactor Centerline None = No cows or goats at that location. Location was a previous I
location with cows or goats.
(a) = census performed out to a distance of approximately ten miles.
(b) - Location within five stiles.
I 72
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v e
s v
a s
s N
O n
a L
e a
e n
e E
I e
e v
e L
e v
C T
e L
s r
a s
L e
a s
N P
r e
e e
e e
n r
e e
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C r
o b
L g
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i C
L o
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m a
t e
k t
M C
t p
a u
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a p
p t
n a
S e
p m
c a
b m
p m
e a
m E
e e
o u
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u e
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D B
P T
C B
C T
P P
B B
T M
8 8
8 8
8 8
8 8
8 8
8 8
E 8
8 8
8 8
8 8
8 8
8 8
8 LE
/
/
/
/
/
/
/
/
/
/
/
/
M PT 9
9 9
9 9
9 9
9 9
9 9
9 MA 2
2 2
2 2
2 2
2 2
2 2
2 AD
/
/
/
/
/
/
/
/
/
/
/
/
S 8
8 8
8 8
8 8
8 8
8 8
8 0
0 0
0 0
0 0
0 0
0 0
0 M
NO ITE CT
)
)
)
)
)
)
)
)
)
)
)
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M EI T
T T
T X
X X
X W
W W
W LS
(
(
(
(
(
(
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(
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(
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(
L OC g
M
5 1
4 4
1 1
4 9
3 8
2 5
7 8
1 6
1 1
2 1
1 1
1 1
1 2
1 0
0 1
1 2
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 2
i 1
1 1
1 1
1 1
1 1
1 1
1 1
1 5
4 7
4 1
9 0
6 2
3 8
7 4
5 6
a 3
2 2
3 2
4 3
4 3
2 5
4 2
3 1
R 0
0 0
0 0
0 0
0 0
0 0
0 0
0 0
0 9
0 1
0 1
1 0
0 0
0 7
3 2
1 1
3 0
8 8
4 8
2 3
1 1
2 0
1 0
0 0
1 1
1 1
0 2
1 0
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1 0
1 1
1 0
0 0
0 0
0 0
1 8
4 2
3 s
0 0
0 1
0 5
1 N
C 0
0 0
0 0
0 0
0 0
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0 0
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2 1
7 1
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3 3
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7 7
7 3
2 G
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1 1
1 1
2 1
1 1
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2 1
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0 0
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0 V a m
s 0
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Ri A s DN2 UOi 8
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1 0
0 0
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I/
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SC 9
5 6
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7 7
4 6
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L E
B Tf 0
0 0
0 0
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3 An MU MA n Gi 9
8 5
2 7
2 3
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8 6
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F s 0
0 1
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7 0
0 0
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0 0
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S u 1
1 1
1 1
1 1
1 1
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1 1
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8 4
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6 6
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0 0
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n n
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b a
l l
a b
l l
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V G
G G
G V
G G
V G
G G
G G
V 8
8 8
8 8
8 8
8 8
8 8
8 8
8 8
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8 8
8 8
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8 8
8 8
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LE
/
/
/
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3 3
8 3
3 3
8 3
3 3
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2 2
0 2
2 2
0 2
2 2
0 2
2 2
/
/
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S 8
8 8
9 8
8 8
9 8
8 8
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Z Z
Z L
L L
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K K
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M M
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C
I TABLE 16 1988 RESIDENCE CENSUS I
I DESIGNATION (b)
SECTOR DEGREES (a)
DISTANCE (a)
MAP METEOROLOGICAL LOCATION w
N w
NNE w
NE w
ENE Sunset Bay A
E 82 0.9 miles Lake Road B
ESE 119" 0.7 miles Parkhurst Road C
SE 127 1.2 miles County Route 29 D
SSE 149*
1.2 miles Miner Road E
S 173 1.6 miles Lakeview Road F
SSW 210*
1.7 miles Lakeview Road G
SW 233' 1.5 miles Bible Camp Retreat H
WSW 249' 1.3 miles w
W w
WNW I
4 w
NW w
NNW This meteorological sector is over Lake Ontario.
There are w
no residences within three miles.
(a)
Based on J. A. FitzPatrick Nuclear Power Plant Reactor Centerline.
(b)
See Figure 3,Section VII.
76 l
_ _ _ ___ _ _ _j
A ii iii iiiii iiiiiiiiiiiiiii T
mm mmm mmmmm mmmmmmmmmmmmmmm S
I 58 362 56381 815842027788953 D
15 006 07070 111160977000005 D
1 NA tt ttt ttttt ttttttttttttttt aa aaa aaaaa aaaaaaaaaaaaaaa SE E
00 555 05504 842329700018025 R
83 153 73040 803446169579132 G
2 3
2 2323 111 1112 112 ED d
t d
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t ieitt a
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S I
244574402736943889545542268487303 D
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11 1
1 1
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N O
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t ns
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mmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmmm S
I 1112014662121151284471682815944433 D
3000111111100044444444311111101100 D
1 NA tttttttttttttttttttttttttttttttttt aaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaaa SE E
0555053910545171563537931842572842 R
2 24913580291491358023940803760977 G
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A ttttnneeeetttkvtndn eanee nerkerr EN C
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SE D
t ns er ce st EM oee)
LU mnms PI riiD MD emsL AE huoT SM TlD(
j il
A iiii iiiiiii i iii iiiiii T
mmmm mmmmmmm mmmm mmmmmm S
M I
1148 5920580 9690 959646 D
1161 5589977 0005 111112 D
22 1
1 1
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s-I I
DATA SUMMARIES AND CONCLUSIONS 1
I I
I I
- > NewWrkPbwer
& Authority I
8 V DATA SUMMARIES AND CONCLUSIONS Each year the results of the Annual Radiological Environmental Monitoring Program are evaluated considering the natural processes of the environment and the aggregate of past data.
A number of factors are considered in the course of evaluating and interpreting the annual Environ-mental Radiological Data.
The interpretation of data can be made at sev-eral levels including trend analysis, population dose, risk estimates to the general population based on environmental concentrations, effectiveness of I
plant effluent controls and specific research areas, among others.
An attempt has been made in this report not only to report the data collected I
during the 1988 sample program 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 radionuclides in terms of potential increased dose to man, in relation to natural backg round, is necessary.
I There are four separate groups of radionuclides that were detected in the environment during 1988.
Several of these radionuclides could pos-sibly fall into three of the four groups.
The first of these groups is j
naturally occurring radionuclides.
It must be realized that the environ-ment contains a broad inventory of naturally occurring radioactive ele-I ments.
Background radiation as a function of primordial radioactive ele-ments and cosmic radiation of solar origin, offers a constant exposure to the environment and man.
These radionuclides, such as Th-228, 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 1
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 global inventory through the decay of short lived radionuclides, deposition, and the removal (by natural processes) of radio-81 I
nuclides from the food chain by such processes as weathering and sedi-mentation.
Since 1963, several atmospheric weapons tests have been con-t ducted by the People's Republic of China.
In each case, the usual radio-nuclides associated with nuclear detonations were detected for several months following the test and then after a peak detection period, dimin-ished 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 site and was very evident in many of the sample medias analyzed during the 1981 sample prog ram.
Quantities of Nb-95, Zr-95, Ce-141, Ce-144, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and Co-60 were typical in air particulate samples during 1981 and were the direct result of the 1980 I
weapons test.
5 A third group of radionuclides was detected as a result of the Cher-nobyl accident which occurred in the Soviet Union during April, 1986.
The resulting fallout or deposition from this accident influenced the back ground radiation in the vicinity of the site and was very evident in many of the sample media analyzed during 1986.
Calculations of the resulting dose to man from Chernobyl related radionuclides in the environment show that the contribution from such nuclides in some cases (such as 1-131 and Cs-137) is significant and second in intensity only to natural background radiation.
Quantities of Nb-95, Ru-103, Ru-106, 1-131, La-140, Cs-134, and Cs-137 were detected in air particulate samples during May and June of 1986.
Milk samples collected and analyzed after April, 1986 contained measurable concentrations of I-131 and Cs-137 The origin of these radio-nuclides was a direct result of faliout from the Chernobyl accident.
Du r-ing 1987, Cs-137 was detected in several milk samples collected during the first half of the grazing season, in 1988, Cs-137 was detected in one milk sample.
The presence of Cs-137 in the milk samples is attributed to the ubiquitous concentrations of Cs-137 from weapons testing and from the Chernobyl releases.
I The fourth group of radionuclides detected in the environment during 1988 were those that could be related to operations at the site.
These select radionuclides were detected in a few of the sample medias collected and at very low concentrations.
Many of these radionuclides are a by-82 I
I product of nuclear detonations, the Chernobyl accident, and the operation of light water reactors thus making a distinction between the sources diffi-cult, if not impossible, using routine sampling programs.
The dose to man I
as a result of these radionuclides is small and significantly less than the radiation exposure from naturally occurring sources of radiation and other sources of man made radionuclides from weapons testing and the Chernobyl accident.
I Thus, a number of factors must be considered in the course of radio-logical data evaluation arid interpretation.
The evaluation and interpreta-tion 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 I
1988, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources.
It is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are very small and are not of environ-mental significance.
in regard to these very small quantities, it will be fu rther noted that at such minute concentrations the assessment of the significance of detected radionuclides is very difficult.
Therefore, con-centrations in one sample that are two times the concentration of another, for example, are not significant overall.
Moreover, concentrations at such I
low levels may show a particular radionuclides in one sample and yet not in another.
I in Section V each sample medium is discussed.
Concentrations of ra-dionuclides detected and exposure to man are presented and scrutinized.
in the routine implementation of the Radiological Environmental Moni-I toring Prog ram, additional or optional environmental pathway media are sampled and analyzed.
These samples are obtained to monitor the secon-I dary pathways not required by Technical Specifications and to maintain the analytical data base established in 1975 when the plant began commercial operation.
These additional samples include; aquatic vegetation (cladophora), bottom sediment, mollusk, milk (Sr-90), meat / poultry and soil samples, in addition to the optional sample media, many additional locations are sampled and analyzed for those pathways required by Techni-cal Specifications.
These additional sample locations are obtained to insure 83 I
I that the important environmental pathways are monitored in a comprehen-sive manner and again, to maintain the analytical data base.
Data are presented and evaluated only for those pathways / media required by g
Technical Specification.
Data from additional sample locations common with 5
Technical Specification required sample media are normally included in the data presentation and evaluation.
When additional locations are included, the use of this data will be specifically noted in section V.
Section VI, titled HISTORICAL DATA, contains sample statistics from previous environmental sampling.
The process of determining the impact (or lack of impact) of plant operation on the environment includes the i
scrutiny of past analytical data, a tool by which trends are discerned.
E' The interpretation of historical data in this report is done to a limited 3
degree.
Because of the constant change in analytical sensitivities, as state-of-the-a rt detection capabilities improve, data comparisons become difficult.
For example, minimum detection capabilities for the 1969 analyses of environmental samples would be considered unacceptable by current standards.
I I
I I
I I-I I
I I
84
.LJ' A.
SURFACE WATER (LAKE) PROGRAM I
i Tables 1 through 4 list the 1988 analytical results for the aquatic / lake water media sampled during the 1988 sampling program.
Fish samples were obtained at two onsite locations.
The transect designations used
{
for the onsite sampling locations are NMPP (02) and JAF (03).
O ff-I site samples were collected in the vicinity of the Oswego Harbor (off-site - 00) area and, therefore, served as control samples.
Lake water samples were collected from the inlet canals of Nine Mile I'
Point Unit #1, Nine Mlle Point Unit #2, J. A. FitzPatrick N.P.P., and the Oswego Steam Station, in addition to power plant samples, a routine sample of the Oswego city drinking water inlet was also ob-tained.
The Oswego Steam Station served as the control location.
Shoreline sediment samples were obtained in an area downstream from the site which proved to have existing recreation value and a physical make up which was suitable for sampling.
The control sample was collected from an area upstream from the site with a similar physical makeup.
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SHORELINE SEDIMENT - TABLE 1 Shoreline sediment samples were collected twice during 1988.
Col-lections were made in April and October at one indicntor location (Sunset Beach), and at one control location ( La ng's Beach).
The results of these samples collected at the indicator and control loca-tions are presented in Table 1.
Several radionuclides were detected in sediment samples using gamma spectral analysis.
These radionuclides were naturally occurring.
K-40 was detected at both the control location and indicator location.
The results ranged from 14.7 pCl/g (dry) to 10.4 pCi/g (dry) at the indicator location, and 12.2 pCi/g (dry) to 10.7 pCi/g (dry) at the control location.
AcTh-228 and Ra-226 were detected at both the indicator locations.
The maximum detectable concentrations for AcTh-228 and Ra-226 were 0 82 pCl/g (dry) and 2.44 pCi/g (dry) respectively at the indicator location and 0.33 pCi/g (dry) and 1.17 g
pCi/g (dry) respectively for the control location.
No other radionuclides were detected in shoreline sediment samples using gamma spectral analysis.
I No dose to man assessment can be made due to the fact that no radio-nuclides related to the operation of the power plants were detected in the 1987 shoreline sediment samples.
No long term historical data exists to compare the shoreline sediment indicator sample results with previous results.
The Technical Specifi-cation Requirement to collect and analyze shoreline sediment was first initiated in the second half of 1985.
A review of sample results for 1985 - 1987 indicated only naturally occurring radionuclides present in shoreline sediment.
The inventory of nuclides identified in 1988 is
)
the identical to that seen in 1985 through 1987.
1988 concentrations are consistent with previous determinations.
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FISH - TABLE 2 I
A total of 27 fish samples were collected in the spring season (May 1988) and in the fall season (September / October 1988).
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,.
Fitz Patrick (03) generating facilities.
The Oswego Harbor samples served as control samples while the NMP (02) and JAF (03) samples served as indicator samples.
Samples were analyzed for gamma emit-I ters.
Data is presented in the ANALYTICAL RESULTS section of the report on Table 2.
Analysis of the 1988 fish samples indicated detectable concentrations of radionuclides related to past weapons testing and natural origins (naturally occurring).
Small detectable concentrations of Cs-137 were found in 15 of 27 or approximately 50% of the fish samples (including control samples) collected in 1988.
Detectable concentrations of K-40, a naturally occurring radionuclides, were found in all fish samples I
collected for the 1L18 program.
Spring fish collections were comprised of six separate species and fifteen individual samples.
The four species represented one feeding type.
Lake trout, brown trout, white perch and king salmon are highly predacious and feed on significant quantities of smaller fish such as smelt, alewife, and other smaller predacious species.
Rain-I bow smelt samples which represent the smaller fish species were col-lected at the FitzPatrick and the control locations.
One white sucker i
sample which is a bottom feeding species was collected at the FitzPatrick transect.
I Cs-137 was. detected in six of the ten indicator samples and in four of the five control samples collected in the spring samples.
The control samples contained a mean Cs-137 concentration that was slightly high-er than the indicator sample mean concentration.
The concentrations I
detected in these samples are not significantly different from past years and are considered to be representative of base line or back-87 I
'%)
I ground concentrations of Cs-137 found in Lake Ontario fish.
Cs-137 in the spring indicator samples ranged from 0.022 pCi/g (wet) to 0.031 pCi/g (wet) and averaged 0.027 pCi/g.
Control samples for I
f th!s same period ranged from 0.023 pCi/g (wet) to 0.053 pCi/g (wet)
W and averaged 0.034 pCi/g (wet).
It should be noted that the rainbow smelt samples collected at the indicator and ' control locations showed no detectable concentrations of Cs-137 which may be indicative of their feeding habits.
K-40 was detected in all of the spring samples collected.
K-40 is a naturally occurring radionuclides and is not related to power plant op-erations.
Detectable concentrations of K-40 in the indicator samples g
ranged from 2.64 to 4.92 pCi/g (wet) and 2.75 to 5.15 pCi/g (wet) 3 for the control samples.
No other radionuclides were detected in any of the spring fish samples.
Fall sample collections were comprised of four separate species and twelve individual samples.
One sample of lake trout, small mouth bass, walleye and white sucker were collected at each of two onsite sample locations (NMP and JAF) and one offsite sample location (Osw-ego Harbor area).
Samples were collected by gill net in September and October and did not include two species not found in the spring (rainbow smelt and king salmon).
I Cs-137 was detected in four of the eight fall indicator samples and in one of the four control samples.
The indicator samples showed an average Cs-137 concentration that was equal to the control location single cesium detection.
Cs-137 in lake trout samples at the indicator locations ranged from 0.023 to 0.054 pCi/g (wet) and averaged 0.038 pCi/g (wet ).
The lake trout sample was the only control sample which contained Cs-137 with a measured concentration of 0.037 pCl/g (wet).
White sucker, the one species of bottom feeder collected at all three sample locations during the fall season, showed no detectable Cs-137 because of different feeding habits and because this species is i
not in the same position on the food chain as the other predacious species.
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I The absences of Cs-137 in the white sucker samples was also demon-strated in the spring 1988 and the 1987 sample results.
J i
I K-40 was detected in all of the fall fish samples collected.
Detectable concentrations of K-40 in the indicator samples ranged from 3.79 to 4.51 pCl/g (wet) and 4.00 to 4.64 pCi/g (wet) for the control sam-ples.
No other radionuclides were detected in any of the fall fish samples.
A review of historical data shows that since 1980 the Cs-137 concen-tration in Lake Ontario fish, in the vicinity of the Nine Mlle Point promitory, has remained stable with slight downward trend.
The I
average Cs-137 concentration in fish for this time period was 0.036 pCi/g (wet) including both the indicator and control results.
During this time period of 1980-1988, the measured concentration for the indicator and control sample locations demonstrate little significant difference in measured concentrations.
This fact would strongly indicate that the source of Cs-137 found in the fish population is most likely residual cesium from the weapon testing.
The specific data for I
1988 did show a slight increase from 1987 results for the control location with the indicator location results remaining constant.
This increase can be attributed to the natural variation in resident fish population of the area.
A review of the graph of historical concen-tration (figure 6, section Vil) demonstrates the relative stability of f
Cs-137 concentrations from 1980 to the present.
Figure 6 also shows that the current level of Cs-137 in the indicator fish samples has decreased significantly since 1976 when a peak concentration of 1.4 pCi/g (wet) was detected.
The current mean Indicator concentration I
of 0.032 pCi/g (wet) shows a decrease in concentration from 1976 by a factor of approximately 40.
Control sample results have also de-creased from a maximum level of 0.12 pCi/g (wet) in 1976 to a level I
of 0.034 pCl/g (wet) in 1988.
'I The general decreasing trend for Cs-137 is most probably a result of the cesium becoming unavailable through ecological cycling.
A signif-icant portion of Cs-137 detected since 1978 in fish is a result of weapons testing
- fallout, and the general downward trend in 89
,u I
concentrations will continue as a function of inventory reduction through the natural processes and radiological decay of the cesium, j
There was no significant effect from 1986 Chernobyl Nuclear Plant E If accident during 1987 and 1988 relative to Cs-137 results in fish a
samples, although an minor effect may have been detected in 1987 i
since both indicator and control location mean results increased slightly.
The Chernobyl accident may have increased the Cs-137 inventory slightly in the area but the increase in fish Cs-137 concentration is most likely due to natural variables.
Lake Ontario fish are considered an important food source by many, therefore, fish is an integral part of the human food chain.
Based g
on the importance of fish in the local diet, a reasonable estimate of 3
dose to man can be calculated.
Assuming that the adult consumes 21.0 kg of fish per year (Regulatory Guide 1.109, maximum exposed i
age group) and the fish consumed contains an average Cs-137 concen-tration of 0.032 pCi/g (wet) (annual mean result of indicator samples for 1988), the whole body dose received would be 0.048 mrem per year.
The critical organ in this case is the liver which would receive a calculated dose of 0.073 mrem per year.
The calculated Cs-137 whole body and critical organ doses are conservative doses associated with consumption of fish from the Nine Mile Point area (indicator samples ).
No radiological decay is assumed for the calculation of doses.
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 (21.0 kg per year) but the average annual Cs-137 mean concen-l tration for the control samples is 0.034 pCi/g (wet).
The calculated Cs-137 whole body dose is 0.051 mrem per year and the associated dose to the liver is 0.078 mrem per year.
I in summary, the whole body and critical organ doses calculated as a result of consumption of fish is small.
Doses received from the con-sumption of indicator and control sample fish are approximately the i
same with the dose from indicator samples being slightly higher.
Doses from both sample groups are considered to be background exposure.
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i A graph of past Cs-137 concentrations can be found in Section Vil I
and a Historical Data Table is included in Section VI.
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SURFACE WATER - TABLES 3 AND 4 l
1988 surface water samples were analyzed monthly for gamma emitters using gamma spectral analysis.
Tritium analyses were performed quarterly.
Quarterly samples (i.e., analysis for Tritium) were com-posites of monthly samples.
In addition, three optional sample loca-tions were sampled and analyzed for gamma emitters and Tritium.
These additional sample locations include the Nine Mlle Point Unit #1 and Unit #2 inlet canals and the City of Oswego drinking water sup-ply which is drawn from Lake Ontario.
The drinking water supply sample consisted of twice per week grab-sampling.
The analytical results for the 1988 surface water sample showed no evidence of plant related radionuclides buildup in the surface water in the vicinity of the site.
Indicator samples were collected from the inlet canal at the James A. FitzPatrick facility.
The control location samples were collected at the inlet canal of Niagara Mohawk's Oswego Steam Station.
These two locations are required to be sampled by the Technical Specifications (RETS).
Tables 3 and 4 show the results of E
surface water samples analyzed during 1988.
5 Gamma spectral analysis was performed on 24 monthly composite sam-ples (two locations) required by the RETS.
With the exception of Tritium, only two radionuclides were detected in samples from the five locations over the course of the 1988 Sampling Program.
Both these radionuclides are naturally occurring and not plant related.
K-40 was detected intermittently in both Technical Specification re-E quired intake canals.
The James A.
FitzPatrick inlet canal samples 5
showed K-40 was detected in ten of the twelve monthly samples and ranged from 60 to 248 pCl/ liter.
K-40 in the Oswego Steam Station inlet canal was detected in ten of the twelve samples and ranged from 45.7 to 232 pCl/ liter.
The Nine Mlle Point Unit #1 Inlet Canal, Unit
- 2 Inlet Canal, and the Oswego City water samples showed K-40 detections in twelve, twelve, and eleven respectively of the twelve monthly samples from each location.
The K-40 concentrations for 92 l
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lI these samples ranged 50-244 pCi/ liter,75-265 pCl/ liter, and 68-267 I
pCi/ liter respectively.
Ra-226 was also detected intermittently in both locations required by technical specifications and the other optional sample locations.
Sam-pies from the FitzPatrick location showed Ra-226 in ten of the twelve monthly samples and concentrations ranged from 73 to 124 pCi/ liter.
l The control sample location (Oswego Steam Station) showed Ra-226 in nine of the twelve monthly samples and ranged in concentrations from 63 to 130 pCi/ liter.
Ra-226 was detected in all of the twelve samples I
taken from the Nine Mlle Point Unit #1 Inlet Canal and ranged from 51 to 144 pCi/ liter.
The Nine Mile Point Unit #2 Inlet Canal showed Ra-226 detected in ten of the twelve samples and ranged in concen-tration from 73 to 143 pCi/ liter.
The Oswego city water showed Ra-226 in ten of the twelve samples with a range of 80 to 118 pCi/ liter.
Tritium samples are quarterly samples that were a composite of the appropriate monthly samples.
Tritium was detected in seven of the eight samples taken at the two locations required by Technical Speci-I fications.
Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 430 pCi/ liter to 480 pCi/ liter and showed a mean concentration of 460 pCl/ liter.
One of the indicator samples had an LLD value of <100 pCi/ liter.
The Technical Specification control location (Oswego Steam Station inlet canal) showed Tritium results which ranged from 240 pCi/ liter to 460 pCi/ liter with a mean concen-tration of 320 pCi/Ilter.
Tritium was also detected in eleven of the twelve optional samples taken, with the exception being the Nine Mlle Point Unit #2 Inlet Canal fourth quarter composite.
Th's particular I
sample analyses indicated that the Tritium concentration was below the Low Limit of Detection (LLD) or the sensitivity of the analyses.
A summary of Tritium results for the 1988 sample prog ram is listed below:
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Sample Tritium Concentration pCi/ liter Location Minimum Maximum Mean ( Annual)
JAF Inlet
<100 480 460 Oswego Steam inlet 240 460 320 NMP #1 Inlet 280 750 463 NMP #2 Inlet
<100 420 320 City Water intake 180 370 293 A review of current data shows that the Tritium concentrations in the lake are consistent.
The source of Tritium detected in the lake water is past testing of thermonuclear devices in the atmosphere, it has been estimated that in the early 1960's the concentration of Tritium of surface water in the United States was as high as 4000 pCi/ liter.
The levels of Tritium in the environment has been reduced over the years through physical process to the levels that are currently being measured.
The Tritium concentration measured during the 1988 samp-ling program are considered to be background levels and are not the result of the operation of the nuclear facilities at Nine Mile Point.
Review of past environmental surface water data for Cs-137 from 1979 through 1987 shows that this radionuclides was detected only once at the control location during 1979, at a concentration of 2.5 pCi/ liter.
Cs-137 at the indicator location (JAF inlet canal) was detected only once, in 1982, at a concentration of 0.43 pCi/ liter.
The 1979 control sample result is suspect and may have been a result of contamination during handling or instrument background since Cs-137 was not de-tected in the indicator inlet canal.
The one positive Cs-137 result from the indicator location (JAF inlet canal) during 1982 was detected in a January composite sample and may have been a result of inlet canal tempering (the addition of discharge water to the inlet canal) or instrument background.
Cs-137 was not detected during 1988 in surface water samples.
Other plant related radionuclides detected during a review period of l
1979 - 1987 Include only Co-60.
The control sample location results showed that Co-60 was detected once in 1981 (the May composite sample ).
This result is suspect and, as noted above, may be the 94 l
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I result of contamination during handling or may be instrument back-g round.
This result was 1.4 pCl/ liter.
Results from the indicator location showed that Co-60 was detected three times during 1982 and I
averaged 1.9 pCl/ liter.
These positive results were attributed to inlet canal tempering and instrument background.
Co-60 was not detected during 1987 in surface water samples.
Review of previous environmental data for K-40 and Ra-226 showed that the detectable concentrations found during 1988 were representative of concentra-tions found during 1979-1987.
I Previous annual mean results for Tritium at the indicator sample lo-cation (FitzPatrick inlet canal) have been variable since 1976.
Mean sample results were reviewed from 1976 through 1988 and showed a peak average value of 641 pCi/ liter (1982) and a minimum average value of 234 pCi/ liter (1979).
The annual mean Tritium result at the indicator location for 1988 was 460 pCi/ liter.
I Mean Tritium results of the control location (Oswego Steam Station) cannot be evaluated with regard to long term historical data since I
sampling was only initiated at this location in 1985.
The maximum Tritium value for the control station for the period of 1985-1988 was 550 pCi/ liter.
The minimum value for this same time period was 140 pCi/ liter.
Some idea of the variability of historical control sample data can be obtained, however, by review of previous data from the City of Oswego drinking water samples.
The drinking water samples are not likely to be affected by the station because of the effects of the distance, lake currents, and the discharge of the Oswego River.
Therefore, this previous sample data represents acceptable control I
sample data for evaluation purposes.
The Oswego City water intake 1
is located in the same general vicinity as the Oswego Steam Station Inlet.
Mean annual Tritium results from previous city water samples from 1976 to 1988 show that the Tritium concentrations have decreased.
The maximum annual average was found in 1976 (652 pCi/ liter) and the minimum in 1982 (165 pCl/ liter).
The 1988 City water annual mean results was calculated as 293 pCi/ liter.
Mean annual results 95 I
T I
from 1979-1987 have remained relatively consistent.
The 1985, 1986, 1987 and 1988 annual mean Tritium results for the Oswego Steam Station were 287, 373, 210 and 320 pCi/ liters respectively.
These results were slightly higher than the drinking water samples (with the exception of 1987) but were within the natural variability range.
I The impact, as expressed as a dose to man, is not evaluated because no plant related radionuclides were detected in surface water samples with the exception of Tritium.
Any impact associated with the fluctu-ation of Tritium levels is considered to be background and not a result of operations at the site.
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I TERRESTRIAL PROGRAM I
)
Tables 5 through 14 represent the analytical results for the terrestrial samples collected for the 1988 reporting period.
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AIR PARTICULATE GROSS BETA - TABLES 5 and 6 Tables 5 and 6 contain the results for the weekly air particulate g
gross beta analysis for a total of nine offsite and six onsite sample a
locations.
Five of the nine offsite locations are required by Technical Specifications.
These sample locations are R-1, R-2, R-3, R-4, (all located near the site boundary) and R-5 (located at a control location beyond any significant influence from the site).
Data contained on Tables 5 and 6 also shows the results from other air sampling loca-tions not required by the RETS.
These locations are designated as D-1 onsite, G onsite, H onsite, I onsite, J onsite, K onsite, D-2 offsite, E offsite, F offsite, and G offsite locations.
A total of 52 samples were collected from the control location R-5 and 208 indicator samples were collected from indicator locations R-1, R-2, R-3, and R-4 during 1988.
The gross beta analysis requires that samples are counted a minimum of twenty-four hours after collection to allow for the decay of natu-rally occurring radionuclides with short half-lives.
The average yearly gross beta indicator concentration was 0.018 pCi/m 3 in 1988.
The average yearly control concentration was also 0.021 pCi/m3 for the same time period.
The minimum, maximum, and average gross beta results for sample locations required by Technical Specification are presented below:
Location *
- Minimum
- Maximum
- Average
- I R-1 0.008 0.038 0.019 R-2 0.008 0.037 0.018
)
R-3 0.007 0.039 0.018 R-4 0.007 0.040 0.019 R-5 (control) 0.008 0.039 0.018 I
- - Concentration in pCi/m3
- - Locations required by the Technical Specifications l
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I The small fluctuations observed in the general gross beta activity can be attributed to changes in the environment, especially seasonal changes.
The concentration of naturally occurring radionuclides in I
the lower levels of the atmosphere directly above land areas are af-fected by time related processes such as wind direction, precipitation, snow cover, soil temperature, and soil moisture content.
With the exception of the 1986 sample data, which was effected by the Cherrobyl accident, the general trend in air particulate gross beta activity has been one of decreasing activity since 1974.
The mean I
gross beta concentration at the control station has decreased from a level of 0.121 pCi/m3 in 1974 to 0.018 pCl/m3 in 1988.
The mean results for the indicator stations ranged from 0.111 pCi/m3 in 1974 to t
0.018 pCi/m3 in 1988.
For both the indicator stations and control stations, the gross beta concentration during 1974 to 1982 fluctuated as a result of fallout from the detonation of thermonuclear weapons.
The annual mean results for the years 1983, 1984, 1985, 1987 and 1988 from both the indicator and control locations have been approxi-mately similar and ranged from 0.018 to 0.026 pCi/m3 This level of I
activity appears to be a baseline range.
The 1986 annual mean result was 0.039 pCi/m3 for both the indicator and control stations.
This concentration is slightly higher than 1983-85 and 1987-1988 levels, and is attributed to fallout from the Chernobyl accident.
I Graphic representations and historical data of air particulate gross beta activity are presented in Sections VI and Vll.
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MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS) - TBL. 9 1
Week:y air particulate samples were composited by location to form monthly composite samples.
The monthly composite samples required bv the R a d '.,m alcal Environmental Technical Specifications (RETS) include R-1, R-2, R-3, R-4, and R-5.
Other sample locations not required by the Technical Specifications for which analytical results are presented include D-1 onsite, G onsite, H onsite, I onsite, J onsite, K onsite, D-2 offsite, E offsite, F offsite, and G offsite lo-cations.
The results of all monthly composite samples are included on Table 9.
The results for the monthly composite samples showed positive de-tections for Be-7, K-40, Ra-226 and AcTh-228.
Each of these radio-nuclides are naturally occurring.
Be-7 was detected in each of the rr.onthly composite samples from all locations required by Technical Specifications.
Be-7 concentrations ranged from 0.054 to 0.153 pCl/m3 for the indicator locations ( R-1, R-2, R-3, and R-4).
The control location results (R-5) showed Be-7 ranging from 0.064 to a
0.130 pCi/m.
K-40 was found intermittently in the Technical Specifi-cation required monthly composite samples ar.d ranged from 0.016 to 0.049 pCi/m3 at the control location (R-5).
The Technical Specifi-cation required indicator location results for K-40 ranged from 0.015 to 0.044 pCi/m3 Ra-226 was detected in four Technical Specification required indicator samples and the values ranged from 0.013 to 0.025 pCi/m3 The Technical Specification control locations yielded no g
positive identifications of Ra-226.
5 Historically, the naturally occurring radionuclides Ra-226, K-40, and Be-7 have shown fluctuations that are representative of naturally changing conditions.
No significant trends were noted during 1988.
No plant related fission product radionuclides were detected during 1988 at the required or optional air sampling locations.
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A review of historical data shows that Cs-137 is the fission product isotope most frequently identified in the air particulate filter composites.
Historically, Cs-137 has been variable during the past and has been present a number of times in air particulate samples since 1977.
During 1977, both onsite (indicator) and offsite (con-t rol), Cs-137 average concentrations were approximately equal and averaged 0.039 pCi/m3, Cs-137 average concentrations at the indi-cator and control locations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCl/m3 respectively.
Average concentrations during 1980 and 1981 were approximately equal at control and indicator locations.
I Cs-137 during 1980 was approximately equal to 1979 and increased slightly in 1981 from 1979 levels.
The 1980 and 1981 average concen-trations were 0.0013 and 0.0015 pCi/m3 respectively.
The mean 1982 concentration for Cs-137 decreased to 0.0004 pCl/m3 The 1983 mean Cs-137 concentration for the indicator and control composite samples were 0.0002 and 0.0002 pCl/m3 which was a reduction from 1982 re-sults.
Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite samples.
The reduction in Cs-137 results is attributed to nuclear decay and ecological cycling of Cs-137 I
initially produced by the 1980 Chinese weapons test.
Cs-137 was not detected during 1985 in air particulate samples, but was detected in 1986 due to the fallout from the Chernobyl accident.
Cs-137 was not detected during the 1987 or 1988 air monitoring program.
I Prior to 1983 and 1984, several radionuclides were detected that were associated with the 1980 Chinese weapons test and other weapons tests prior to 1980.
These radionuclides were not detected during 1984 and 1985 as a result of nuclear decay and ecological cycling.
I These include Zr-95, Ce-141, Nb-95, Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140.
In addition, La-140 was detected once during 1983 and infrequently during 1978 and 1981.
La-140 was not detected during 1984 and 1985.
However, La-140, Nb-95, Ru-103, Ru-106, and 1-131 were detected in air particulate composite samples during 1986 as a result of the fallout from the Chernobyl accident.
The above refer-I I
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I enced radionuclides were not detected in the 1987 or 1988 air moni-toring program.
Graphic representations of air particulate composite Co-60 and Cs-137 concentrations are presented in Section Vll.
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AIRBORNE RADIOlODINE (1-131) - TABLES 7 AND 8 I
Airborne radiolodine is monitored at the air sampling stations that are also used to collect air particulate samples (see Section V.3).
The air monitoring network is made up of fifteen sample locations.
There are nine stations considered offsite locations.
Of these nine, five are required by Technical Specifications and are designated as R-1, R-2, R-3, and R-4.
These stations are located near the site boundary and are indicator stations.
A fifth Technical Specification location des-ignated as R-5 is located beyond any significant influence from the I
plant and is considered a control location.
As noted under the air particulate gross beta section, ten additional air sampling locations are maintained in addition to those required by Technical Specifica-tion.
Six of these stations are located within the site boundary and are designated as D1 onsite, G onsite, H onsite, I onsite, J onsite, and K ontite.
The four remaining optional stations are located offsite and are designated as D2 offsite, E offsite, F offsite, and G offsite.
I The analytical data for each of these sample locations is included in this report.
I During the 1988 sampling prog ram, airborne radiciodine was not detected in any of the fifty-two weekly samples collected at the con-trol location required by Technical specifications.
The LLD values for the control location ranged from < 0.005 to < 0.019 pCi/m.
3 lodine-131 (1-131) has been detected in the past at control locations.
During 1976, the mean off-site 1-131 concentration averaged 0.604 I
pCi/m3, 1977 showed an 1-131 concentration that decreased to 0.323 pCi/m3 and for 1978 the concentration decreased by a factor of ten to 0.032 pCi/m2 During 1979 - 1981 and 1983 - 1985, 1-131 was not detected.
1-131 was detected once during 1982 at a concentration of 0.039 pCl/m3 1
in 1988 Radiolodine-131 (1-131) was not detected in any of the 208 l
indicator samples required by Technical Specifications.
1-1 31 was detected in 1 of the 312 optional indicator samples taken during 1988.
I 1-131 was detected at the H onsite sample location during the sample period of August 6-13, 1988.
The concentrations detected was 0.012 103 I
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I pCi/m3 The onsite location which showed the positive detections is located within the site boundary and the concentrations measured are not representative of concentrations present offsite.
The R-1 offsite station located in the same general down wind direction as H onsite station (H onsite 71o00.8 miles, R-1 offsite 88o01.8 miles) did not show l-131 in the sample for the same time period.
A meaningful dose estimate is not practical to make for the I-131 concentrations measured at the onsite sampling stations as there are no residence or individuals in the vicinity of the sample location.
An estimate of the dose to man can be made using the measured onsite concentrations for the purpose of illustrating the low dose commitment from the measured concentration.
The critical organ for iodine iso-topes is the thyroid gland, and the maximum exposed age group is the child.
Using Standard Regulatory Guide 1.109 methodology, an inhalation rate of 3700 m3 per year and the H onsite location 1-131 concentration, conservative doses can be calculated.
in order to be conservative and to simplify the computations, no radiological decay is assumed, and the maximum exposed individual is assumed to remain at the sample location for one week.
The calculated dose would be 0.0037 mrem to the thyroid and 0.0000063 mrem to the whole body.
The resulting dose is very small and of little significance compared to normal background dose rates.
I A review of plant gaseous effluent data for the sample periods in which l-131 was detected in the environment was performed.
This data shows that the 1-131 release rates are well within the design objective of the plant as outlined in the appropriate sections of the Radiological effluent Technical Specifications.
The detectable level of l
l-131 in the environment was consistent with the measured sou rce terms at the plant for the same sample period.
j A review of historical data shows that I-131 has been detected in the past at indicator or offsite stations.
During 1976, the mean offsite 104 Ij
1-131 concentration averaged 0.604 pCi/m3 1977 showed an 1-1 31 concentration that decreased to 0.323 pCi/m3 and for 1978, the con-centration decreased by a factor of ten to 0.032 pCi/m3 During 1979, 1980, 1981, 1983, 1984, and 1985, 1-131 was not detected.
1-131 was detected once during 1982 at a concentration of 0.039 pCi/m3 1-131 has been detected in the past at the onsite stations and was detected at a mean concentration of 0.328 and 0.309 pCi/m3during 1976 and 1977.
The average concentration decreased to 0.041 pCl/m3 during 1978 and was not detected during 1979.
The 1980-82 average concentrations were 0.013, 0.029, and 0.016 pCl/m3 which were reductions in view of previous 1-131 concentrations.
During 1983, the mean 1-131 concentration was 0.028 pCi/m3 which represented a slight increase compared to 1982.
The concentrations detected during 1983 at the onsite sample stations were a result of operations at the site.
1-131 was not detected in any of the 1984 or 1985 onsite sam-ples.
1-131 was detected in a total of 75 weekly samples collected during the 1986 sample program.
The concentrations detected in 1986 I
ranged from a minimum of 0.011 pCi/m3 to a maximum of 0.36 pCi/m3 Each of the positive detections of I-131 in 1986 were a direct result of the Chernobyl Nuclear accident.
The end result of the 1988 l-131 sampling effort showed no significant impact due to the operation of the plant.
During 1988, 1-131 was not detected in any other environmental sample media including milk and I
green leafy vegetables.
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4 TLD (ENVIRONMENTAL DOSIMETRY) - TABLE 10 TLD's were collected once per quarter during the 1988 sample year.
The TLD results are, for the most part, an average of eight indepen-dent readings at each location and are reported in mrem per standard month.
T LD's required by the Technical Specifications (RETS) in-clude two TLD's at each location with four independent readings per TLD or a total of eight readings.
TLD results included on Table 10 are comprised of TLD's required by the RETS and special interest TLD's not required by the RETS.
In 1988, TLD's were collected on approximately March 29, 1988, June 29, 1988, September 29, 1988, and December 28, 1988.
TLD results are evaluated by organizing environmental TLD's into five different groups.
These groups include:
(1) onsite TLD's (TLD's within the site boundary not required by the RETS), (2) site bound-ary TLD's (one in each of the sixteen 221 degree meteorological sec-tors), (3) a ring of TLD's four to five miles from the site (in each of the land based 22i degree meteorological sectors), (4) special interest g
T LD's (in areas of high population density), and (5) control TLD's u
(in areas beyond any significant influence of the generating facil-ities).
Special interest TLD's are located at or near large industrial sites, schools, or proximal to town or communities.
Control TLD's are located to the southwest, west, south, and east-northeast of the site at distances of 12.8 to 25.9 miles from the site.
Two new control TLD locations (No. 110 and 111) were added starting in the 2nd quarter,1988.
Most of the TLDs required by the Technical Specifications during 1988 were initiated in 1985 as a result of the issue of new Technical Speci-fications by the NRC.
Therefore, these TLDs can only be compared to 1985-1987 results.
Other TLDs, which include a few TLDs required by the Technical Specifications (i.e., numbers 7,
14, 15, 18, 23, 49, 56, and 58) and other optional TLDs, can be compared to results prior to 1985 since these TLDs were established before 1985.
106
l A review of the 1988 TLD results as a whole showed the data to be consistent with prior years.
The third quarter 1988 TLD's showed general increase for all the dosimeters when compared to the other three quarters for 1988.
The higher dose rates neasured also in-cluded the control locations which indicates that it was not the result l
of plant operations.
The higher readings noted for the 3rd quarter were not of sufficient magnitude to affect the yearly results when compared to previous data.
A review of the analysis contractors program indicated that the increased doses may be the result of an anomaly in the processing methodology.
The prog ram is currently under review for possible changes and improvements.
The results for the indicator TLD's required by the RETS are gener-ally consistent with previous years results although a slight increase is noted when compared to 1987 figures.
This same increase was also noted for the control TLD's.
Onsite TLD's are TLD's at special interest areas and are not required by the RETS.
These are located near the generating facilities and at I
previous or existing onsite air sampling stations.
TLD's located at the air sampling stations include numbers 3, 4,
5, 6, 7, 23, 24, 25, and 26.
The results for TLD's are generally consistent with previous years results.
TLD #3 is located in the vicinity of Nine Mile Point Unit 2 and is between the Unit 1 facility and FitzPatrick.
The re-sults for TLD #3 were approximately double the results of the other TLD's during the first three quarters of the year because of the effects from NMP Unit #2 and Fitz Patrick.
All three plants were shutdown during the fourth quarter 1988 and the dose measured for I
this quarter was reduced by half.
Other onsite TLD's include special interest TLD's located near the north shoreline of the Unit 1, Unit 2, and FitzPatrick facilities but in close proximity to radwaste facilities and the Unit I reactor building.
These TLD's include numbers 27, 28, 29, 30, 31, 39, and 47.
Re-1 suits for these TLD's during 1988 were variable and ranged from 6.8 to 40.5 mrem per standard month as a result of activities at the rad-waste facilities and the operating modes of the generating facilities.
107
7 i
Results for 1988 were within the ranges of variability observed in
' previous years for TLD's at or near these locations.
The maximum value in 1987 for this group of TLD locations was 32.8 mrem.
Ad-ditional on-site TLD's are located near the onsite Energy Information Center and the associated northeast shoreline.
These TLD's include numbers 18, 103, 106, and 107.
These TLD's showed no significant change from 1987 either as a group or as individual locations.
TLD numbers 28, 106, and 107 (noted above) are located to the West of the Energy Information Center and to the East of the Unit 1 facility.
Site boundary TLD's are located in the approximate area of the site boundary, one in each of the sixteen 22t degree meteorological sec-tors.
These TLD's include numbers 75, 76, 77, 23, 78, 79, 80, 81, 82, 83, 84, 7,18, 85, 86, and 87.
TLD numbers 78, 79, 80, 81, 82, 83, 84, 7, and 18 showed results that were consistent with Control TLD results, and ranged from 4.7 to 7.1 mrem per standard month.
TLD numbers 75, 76, 77, 23, 85, 86 and 87 showed results that rang-ed up to approximately three times the results of Control TLD's.
These results ranged from 5.2 to 17.9 mrem per standard month.
This latter group of TLD's are located near the Lake shoreline (ap-proximately 100 feet from the shoreline) but are also located in close proximity of the Reactor Building and Radwaste facilities of Nine Mlle Point Unit 1, Unit 2, and the radwaste facilities of FitzPatrick.
A net site boundary dose can be estimated from available TLD results and Control TLD results.
TLD results from TLD's located near the site boundary in sectors facing the land accessible by members of the 1
I general public (excluding TLD's near the generating facilities and j
facing Lake Ontario) are compared to control TLD results.
The site I
boundary TLD's include numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18.
Control TLD's include numbers 8,14 and 49.
Net site boundary doses for the quarters in mram per standard month are as follows.
Quarter Net Site Property Boundary Dose mrem /std month l
l 1
-0.1 i
2
-0.3 3
+0.2 4
-0.2 Total 0.0 108
l
]
Site boundary TLD numbers 75, 76, 77, 23, 85, 86 and 87 were excluded from the net site boundary dose calculation since these TLD's are not representative of doses received where a member of the general public may be located.
These areas are near the north shoreline which are in close proximity to the generating facilities and are not accessible.
The net site boundary TLD's showed a positive value for the third quarter of 0.2 mrem per standard month.
A positive site boundary dose of this magnitude has been observed in I
the past and is within the normal statistical variation for TLD ac-curacy.
It should be noted, however, that FitzPatrick plant ran in the hydrogen water chemistry mode (hydrogen injection) for approxi-mately 22 days in the 3rd quarter of 1988.
In the hydrogen water chemistry mode the radiation doses in the general area outside the turbine building are elevated due to an increase in the N-16 source term.
The use of hydrogen injection may have contributed to the small positive dose measured in the third quarter of 1988.
The third group of environmental TLD's are those TLD's located four to five miles from the site in each of the land based 22) degree meteorological sectors.
These TLDs are required by Technical Speci-fications.
At this distance, TLD's are not present in eight of the sixteen meteorological sectors over Lake Ontario.
Results for this group of TLD's during 1988 fluctuated slightly as result of naturally occurring conditions and the normal variation a
the concentration of naturally occurring radionuclides found in the ground at each of the locathns.
These TLL s were established in 1985 and included numbers 88, 89, 90, 91, 92, 93, 94 and 95.
Re-sults fluctuated from 3.9 to 7.1 mrem per standard month.
Results during 1988 can only be compared to 1985-1987 yearly results since this group of TLD's was established in 1985.
The overall results for this group of TLDs were consistent with reading during the 1985 through 1987 results although 1986 data was slightly higher.
i The fourth group of environmental TLD's are those TLD's located be-gm yond the site boundary and at special interest areas such as indus-109
l trial sites, schools, nearby communities, towns, offsite air sampling stations, the closest residence to the site and the offsite environ-mental laboratory.
This group of TLD's include numbers 9, 10, 11, 12, 13, 15, 19, 51, 52, 53, 54, 55, 56, 58, 96, 97, 98, 99, 100, 101, and 102 and results ranged from 3.9 to 7.2 mrem per standard month.
All the TLD results from this group were consistent with the general l-variation noted for the Control TLD's which ranged from 4.4 to 6.8 mrem.
Results during 1988 for TLD's established during previous years were consistent with results noted for those years (1985-1987).
The fifth group of TLD's include those TLD's considered as' Control TLD's and are required by RETS.
These TLD's include numbers 14, 49, which are required by RETS, and numbers 8, 110 and 111 which is an optional location.
Control locations 110 and 111 were established in the second quarter of 1988.
Results for 1988 ranged from 4.4 to 6.8 mrem per standard month.
Results from 1988 were consistent with previous years results.
The 1988 control results were slightly higher than those measured in 1987 but lower than the 1986 results.
The slight increase noted in 1986 may have been the result of the g
Chernobyl Nuclear Plant accident.
This trend was also noted in the 3
other groups of TLD's evaluated during 1986.
I As noted previously, since the present RETS became effective in 1985, the TLD's for the most part, can only be evaluated for 1985 through 1988.
During 1988 the four TLD groups required by the RETS (control, site boundary, outer ring and special interest) showed results which were consistent with doses measured in 1985 through 1987.
The 1986 TLD results were siightly higher than the other three years in the 1985 to 1988 time period.
The comparison of each group of TLD's is illustrated in the following table.
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110
I TLD Group 1985 1986 1987 1988 I-Control 5.67 6.40 5.39 5.56 Site Boundary
- 5.32 5.96 5.40 5.40 Cuter Ring 5.02 5.95 5.18 5.38 Special Interest 5.31 6.11 5.14 5.33 I
- TLD's #23, 75, 76, 77, 85, 86, 87 are not included due to the close proximity to the plant.
Overall, environmental TLD results for 1988 showed no significant I
impact from direct radiation measured outside the site boundary.
A graph of historical TLD data is included in Section Vll.
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5.
MILK - TABLES 11 AND 12 Milk samples were collected from a total of six indicator locations (within 10 miles of the site), and one control location (beyond 10 miles from the site) during 1988.
The RETS require that three locations be sampled for milk within 5.0 miles of the site.
During 1988, there were no milk sample locations within 5.0 miles of the site.
The locations that were sampled during 1988 are located from 5.5 to 9.5 miles from the site.
Control milk samples were collected from location #65 which is IcGted 17 miles from the site.
Sample location descriptions for all
- 1. ra sample locations utilized during 1988 are listed below.
Location No.
Direction from Site Distance from Site (miles) 7 ESE 5.5 16 5
5,9 50 E
8.2 E
55 E
- 9. 0 g
60 E
9.5 4
ESE 7.8 65 (Control)
SW 17.0 During 1988, milk samples were collected at each of the six indicator locations and the control location in the first half and the second half of each month.
Samples were collected during the months of April g
through December 1988.
Since 1-131 was not detected during Novem-E ber and December of 1987, no additional samples were required for January through March of 1988.
For each sample, analyses were performed for gamma emitters (analysis by GeLi, Ge detectors) and 1-131 using a resin extraction / gamma spectral analysis.
Sample analysis results for gamma emitters are found on Table 12.
1-131 analytical results are found on Table 11.
The gamma spectral analysis of the bimonthly samples showed K-40 to g
be the most abundant radionuclides detected in the milk samples col-3 l
lected during 1988.
K-40 was detected in every sample analyzed and I
ranged in concentration from 928 pCi/ liter to 1,730 pCi/ liter at the indicator locations and 1,360 pCi/ liter to 1,710 pCi/ liter at the control I
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location.
K-40 is a naturally occurring radionuclides and is found in many of the environmental media sampled.
Relatively high levels of K-40 are found in cows milk due to the biological concentration of I
potassium in the milk production process.
Cs-137 was detected in 1 of 108 indicator milk samples collected during 1988.
Cs-137 was not detected in any of the control location samples during the 1988 program.
The LLD values for the control location analysis range from
< 4.4 to < 15.2 pCi/l.
The Cs-137 concentration measured at the No.
16 indicator location was 10.0 I
pCi/ liter.
The Cs-137 concentration was detected in the April 18, 1988 sample.
Location #16 is located 5.9 miles from the site in the southern meteorological sector.
The prior milk sample collected on April 04, 1988 and the subsequent sample collected on May 05, 1988 from the same location showed no positive detection of Cs-137.
The analysis results for the April 04, 1988 sample was
< 6.89 pCl/ liter and the May 05, 1988 result was < 9.37 pCi/ liter.
The cause of the low concentration of Cs-137 found in the April I
sample is most likely the result of background Cs-137 concentrations in the environment from past weapons testing or the Chernobyl accident.
During 1986, Cs-137 was detected fifteen times and was found at both indicator and control locations.
Cs-137 was not detected after September, 1986 which corresponds to the end of the grazing season.
A monthly questionnaire completed during each milk collection showed that milk animals at sample location No.16 were not released for pasturing prior to the Aprl! 16, 1988 sample collection.
Therefore, these animals were fed stored feed.
I It is reasoned that stored feed consumed during April,1988 at loca-tion 16 contained enough background Cs-137 that the milk analysis showed a detectable level of Cs-137.
Cs-137 release levels from the site during April,1988 were normal and within all required effluent regulations.
The fact that no other plant related radionuclides were detected in the sample which contained Cs-137 further supports the conclusion that the power plant at the Nine Mlle Point site was not the source of the Cs-137.
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U The inpact as a result of Cs-137 in the 1988 milk sample can be assessed by calculating conservative doses to man from the consump-l tion of milk with the detectable quantity of Cs-137.
For the purposes of a calculated dose, the 1988 indicator sample Cs-137 concentration is used (10.0 pCl/ liter).
I Assuming a consumption rate of 330 liters (87.18 gallons) per year for an infant (Regulatory Guide 1.109 maximum exposed individual), the whole body dose would be 0.012 mrem and the critical organ dose would be 0.17 mrem to the liver.
The calculated doses are based on 1 month of milk consumption.
The calculated dose to an adult can also be determined assuming a consumption rate of 110 liters (29.06 gallons) per year (Regulatory Guide 1.109) and a Cs-137 concentration of 10.0 pCi/ liter measured at the indicator location.
The resultant doses are 0.007 mrem to the whole body and 0.010 mrem to the liver (critical organ).
The calcu-lated doses are based on 1 month of milk consumption.
For the purpose of illustration, the significance of the above doses can be brought into perspective by a comparison to the U.
S.
Department of Health and Human Services (US/DHHS) Guide for Cs-137 ingestion.
The EPA / PAG maximum limit for Cs-137 ingestion is 240,000 pCl.
The resultant whole body and liver doses to the maxi-mum exposed individual (infant) would be 10.4 mrem and 146.6 mrem respectively.
The total calculated doses as a result of the measured Cs-137 concentrations are very small by comparison.
An additional comparison can be made to naturally occurring K-40.
K-40 has been noted in almost all environmental samples at significant levels.
A 70 kilogram adult weighs approximately 154 pounds and contains approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation, consumption, etc.).
The dose to the bone tissue is about 20 mrem per year as a result of internally deposited K-40 (Eisenbud).
For comparison purposes, an adult bone dose was i
114
v I
calculated that results from the consumption of milk with 10.0 pCi/l I
concentration of Cs-137.
Using the same criteria used for calculating the preceding doses, the adult bone dose is 0.0073 mrem. This calcu-lated dose is small and is only 0.0004 of the annual bone dose re-ceived from naturally occurring K-40.
Historical data shows the absence of Cs-137 in milk during 1984 and 1985.
It should be noted that the two generating facilities (NMP Unit
- 1 and JAFNPP) were, for the most part, at full capacity during the 1984 and 1985 grazing season and Cs-137 was not detected in milk samples.
Cs-137 was detected in milk during 1983 at a concentration of 5.1 pCi/ liter (detected only once).
Results from 1986 showed a mean Os-137 concentration of 8.6 pCi/ liter at the indicator locations.
Cs-137 in 1986 milk samples was a result of the 1986 Chernobyl Nuc-lear Plant accident.
During 1987, Cs-137 was found in two indicator samples at a mean concentration of 6.8 pCl/ liter and was also deter-mined to be the result of the Chernobyl accident.
In addition to gamma spectral analysis, each of the milk samples I
collected 1988 were analyzed for I-131.
lodine-131 was not detect-ed during 1988 in any of the control or indicator samples.
All 1-131 milk results are reported as lower limits of detection (LLD).
The LLD results ranged from < 0.15 to < 0.49 pCi/l for all milk samples.
No other radionuclides were detected in milk samples using gamma spectral analysis with the exception of Ra-226 which was detected in 23 samples and AcTh-228 which was detected in one sample.
Both these radionuclides are naturally occurring.
A review of past his-I-
torical data shows that the detection of I-131 in milk samples has not been routine.
In past sampling programs,1-131 has been detected in
.nilk samples only in conjunction with fresh fallout from atmospheric testing or from the Chernobyl Nuclear Plant accident in 1986.
Numer-ical evaluation shows that annual mean results ranged from 0.2 l
pCl/ liter to 6.9 pCl/ liter at the indicator locations during 1976-1978.
1-131 during these years is a result of intermittent weapor.s testing.
During 1979 - 1985, 1-131 in milk samples at the indicator locations I
115
\\
I was not detected, except during 1980.
The mean result during 1980 was 0.4 pCl/ liter and was a result of the 1980 Chinese Weapons Test.
l Results from 1986 showed that 1-131 was detected at a mean concen-tration of 5.2 pCi/ liter as a result of the Chernobyl accident.
1-131 was not detected during 1987 or 1988 in milk samples.
i Historical data for I-131 from the control location showed that 1-131 was detected during 1980 at a mean concentration of 1.4 pCl/ liter.
There was no detectable I-131 during the period of 1978-1985 with the j
exception of 1980.
During 1986, 1-131 from the control location showed a mean concentration of 13.6 pCi/ liter as a result of the Chernobyl accident.
1-131 was not detected during 1988 at the control location.
Historical data and graphic representations of milk sample results for Cs-137 and 1-131 are presented in Sections VI and Vll.
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6.
LAND USE CENSUS - TABLES 13 AND 16 A land use census was conducted during 1988 to identify within a I
distance of five miles the location of all milk animals (cows and goats) and the location of the nearest residence in each of the sixteen 22i i
degree meteorological sectors.
The milch animal census (milk animal) was actually conducted out to a distance of ten miles in order to provide a more comprehensive census.
The milch animal census is an estimation of the number of cows and goats within a ten mile radius of the Nine Mlle Point Site.
A census is conducted once per year in the spring.
The census is conducted I
by sending questionnaires to previous milk animal owners and also by road surveys to locate any possible new owners.
In the event ques-tionnaires are not answered, then the owners are contacted by tele-phone or in person.
The local agricultural agency was also con-tacted.
The number of milch animair located within the ten mile radius of the I
site was estimated to be 910 cows and 15 goats for the spring 1988 census.
No new locations with milk animals were found since the 1986 census.
The number of cows decreased by 335 and the number of goats decreased by 15 with respect to the 1987 census.
I i
The residence census was conducted during the late summer to identi-fy the nearest residence in each of the sixteen 22i degree meteoro-logical sectors within a distance of five miles from the site.
At this distance, some of the meteorological sectors are over water.
These I
sectors include:
N, NNE, NE, ENE, W, WNW, NW and NNW.
There are no residences in these sectors.
The results of the 1988 residence census showing the applicable sectors, degrees and distance of each of the nearest residences are found on Table 15.
The nearest resi-dence locations are shown on the census map, figure 3.
It should be noted that sampling of vegetation at the site boundary is performed in lieu of the garden census, as allowed by the Technical l
Specifications.
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LJ 7.
FOOD PRODUCTS - TABLE 14 Food product samples collected during 1988 were comprised of garden E
vegetables, fruit, and other types of broad leaf vegetation.
W Samples were collected during the late Summer / Fall harvest season as part of the required samples for the Nine Mile Point Unit #1 and #2 Technical Specifications.
The collection of monthly food product samples is not required by the JAF Technical Specifications when milk sampling is being performed.
The food product sample results pre-sented on Table 14 are for optional samples.
Samples were co!!ected from five indicator locations and one control location.
The indicator locations were represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and the release points at operating site facilities.
The control location was represented by a garden location 9-20 miles distant in a least prevalent wind direction.
Garden vegetables were comprised of cabbage, lettuce, beet greens, swiss chard and collard greens which are all considered broadleaf vegetables.
Where broad-leaf vegetables were not available, non-edible broad leaf vegetation, non-broadleaf fruits, or vegetables were collected.
Non-edible broad leaf vegetation collected in 1988 consisted of pumpkin leaves, green bean leaves, cucumber leaves, pepper leaves and squash leaves.
Non-broadleaf fruits or vegetables collected in 1988 consisted of tomatoes.
At the control location, one sample of each similar type of fruit or vegetable was collected.
Fruits and vegetables were collected in the late summer harvest season.
K-40 was detected in all broadleaf and non-broadleaf vegetables and fruits.
Broadleaf vegetables and vegetation showed concentrations of I
K-40 ranging from 1.39 pCi/g to 7.37 pCi/g (wet).
Be-7 was detected in all of the broadleaf vegetables / vegetation, but was not detected in any of the non-broadleaf fruits (tomatoes).
The Be-7 lI I'
11e I
u-I concentrations in the broadleaf vegetables ranged from 0.10 pCi/g I
(wet) to 3.04 pCi/g (wet).
Cs-137 was detected in one sample of non-edible broadleaf vegetation from the indicator 'm.ations.
The detected quantity was near the limit of detection and wad 0.009 pCi/g (wet).
LLD values for all samples ranged from 0.004 to 0.017 pCi/g (wet ).
The detected quantity of Cs-137 was found at location "R".
It is probable that the quantity of Cs-137 found is a result of root uptake by the squash plant and not leaf deposition.
The source of the cesium is most likely from the I
soll.
The ultimate source of Cs-137 is from weapons testing, cher-nobyl, operations at the site, or possibly all three.
Cs-137 has been detected in soil samples from areas at the site and at areas well beyond the site as a result of past weapons testing.
Cs-137 was not detected at the control location.
No other radionuclides were detected in the 1988 collection of fruits and vegetables.
The impact of detectable Cs-137 in food product samples can be evaluated by calculating a dose to the maximum exposed individual as a result of consumption.
Using standard methodology from NRC Regulatory Guide 1.109, the maximum exposed organ is the bone of a child.
The maxi num whole body dose would be to an adult.
The Cs-137 concentration is 0.008 pCi/g (wet) and the consumption rate is conservative due to the fact that squash leaves are not normally l I consumed by humans.
The consumption rate is assumed to be a maximum consumption rate of 26 kg per year for a child.
The cal-I culated doses are 0.068 mrem per year to a child's bone tissue (maxi-mum organ dose) and 0.0096 mrem per year to the child whole body.
The maximum whole body dose occurs to the adult.
Assumin.
Regulatory Guide 1.109 maximum consumption rate of 64 kg per year for an adult, the maximum organ dose is 0.056 mrem to the liver and 0.037 mrem to the whole body.
A maximum organ and whole body doses are small and insignificant when compared to dose from the I
i natural radiation environment.
l I l
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u Review of past environmental data indicates that K-40 has been con-sistently detected in food crop sauples.
K-40 concentrations have fluctuated from one sample to another but the annual ranges have re-
)
i mained relatively consistent from year to year.
Be-7 has been de-
{
tected occasionally during the past on leafy vegetables (1978 through I
1982,1984 and 1987).
Cs-137 has been detected intermittently during the years of 1976-1987 at the indicator locations and during the years of 1980-1986 at the control locations (control samples were not obtained prior to 1980).
Review of indicator sample results from 1976-1987 showed that Cs-137 was not detected during 1976-1978, 1981-1984 and 1986.
During 1979 E
and 1980, Cs-137 in fruits and/or vegetables showed annual mean 5
concentrations of 0.004 and 0.036 pCi/g (wet) respectively.
Cs-137 was found at one indicator location during 1985 at a concentration of 0.047 pCl/g (wet).
Control samples during 1980-1986 showed Cs-137 detected only during 1980 at a concentration of 0.02 pCl/g wet.
Cs-137 detected during the past at both indicator and control lo-cations is indicative of weapons testing.
During 1987, Cs-137 was found at the indicator locations at a mean concentration of 0.016 pCi/g (wet).
Cs-137 was not detected at the control location during 1987.
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SITE BOUNDARY VEGETATION - TABLE 15 I
The Radiological Effluent Technical Specifications (RETS) require that samples of three different kinds of broad-leaf vegetation (edible or inedible) be collected at the site boundary in two areas of highest D/Q (deposition factor) for a total of six samples.
The sampling of broad leaf vegetation is performed in accordance with Table 6.1-1 (RETS) in lieu of the garden census specified in section 6.2 (RETS).
The control location was represented by samples of three similar broad-leaf varieties grown 9-20 miles distant in a least prevalent wind I
direction, in 1988 a total of fifteen site boundary vegetation samples were collected.
Twelve indicator samples were collected from three down wind meteorological sectors, ENE, E and ESE.
Three control samples were collected from the control location. The three broad-leaf varieties collected were wild grape leaves, viburnum, and goldenrod (all non-edible).
The site boundary and control vegetation samples were collected during the late summer harvest season.
Two naturally occurring radionuclides (K-40 and Be-7) were detected I
in the 1988 samples.
K-40 was detected in each of the broad-leaf vegetation samples collected.
The site boundary vegetation samples (indicators) showed concentrations of K-40 ranging from 0.09 pCi/g (wet) to 8.85 pCi/g (wet).
The control samples showed concen-trations of K-40 ranging from 2.90 pCi/g (wet) to 8.87 pCi/g (wet).
Be-7 was also detected in each of the broad-leaf vegetation samples.
I The site boundary samples (indicators) showed concentrations of Be-7 ranging from 0.40 pCi/g (wet) to 2.86 pCi/g (wet).
The control I
samples showed concentrations of Be-7 ranging from 0.51 pCi/g (wet) to 1.96 pCi/g (wet).
Both Be-7 and K-40 are naturally occurring radionuclides.
Two additional radionuclides were detected in the 1988 site boundary vegetation samples.
Cs-137 and Co-60 were detected in a Goldenrod sample at location "L"
which is located directly east of the site.
I Coldenrod was re-sampled at each of the three original indicator locations on September 08, 1988.
The re-analysis confirmed the 121 I
j I1 presence of Cs-137 in the Goldenrod from location"L" but indicated an l
LLD value of < 0.018 pCl/g for Co-60.
Cs-137 was also di tected in j
the re-sample of the Goldenrod from location "Z"
which showed an I
LLD of < 0.04 pCl/g for the original samole.
A summary of the positive sample results are shown below:
Location Date Sample Cs-137 Co-60 Z
08/23/88 Goldenrod
<0.021
<0.21 Z
09/08/88 Goldenrod 0.016
<0.012 i
(re-sample)
L 08/23/88 Viburnum 0.054
<0.036 L
08/23/88 Goldenrod 0.12 0.045 L
09/08/88 Goldenrod 0.03
<0.018 (re-sample)
The presence of Cs-137 in the site boundary vegetation samples can be attributed to several sources; atmosphere nuclear testing, fallout from the Chernobyl accident and/or operations at the site.
I Historically, Cs-137 concentrations have been detected in control a
samples in the past (1986 0 0.035 pCi/g (wet)) and at the indicator locations (1985 1986).
The presence of Co-60 in the Goldenrod sample from location "L" can be directly attributed to operations at the site.
A review of plant effluent data for 1988 showed that the gaseous effluents were within the requirements of the plant's Tech-nical Specifications and no elevated releases of Co-60 were noted.
The concentrations of Cs-137 and Co-60 detected were very small and represent sample locations that are within the site boundary or con-g trolled area.
Co-60 was not detected in 1988 garden vegetation sam-E ples collected outside the site boundary in the same general meteoro-logical sectors.
The types of vegetation samples collected during 1988 at the site boundary are not consumed by humans.
These samples are collected as indicator samples because of the high D/Q values which exist at the site boundary.
Because this vegetation is not considered edible there is no dose to man from the presence of Cs-137 and Co-60, 122 I
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A more realistic dose to man concept was evaluated in the previous section (Section V.7, Food Products).
The dose assessment from the consumption of fruits and vegetables from nearby gardens (within 3 I
miles of the site) was demonstrated to be insignificant.
A review of the 1985 - 1987 site boundary vegetation sample results show that K-40 and Be-7 are routinely detected in these samples.
The K-40 concentration detected in the 1988 samples are similar in range as those found in 1985 - 1987, as expected.
In 1985, 1986, 1987 and 1988 Be-7 was detected in each of broad leaf samples taken.
The analytical results for Be-7 have been consistent from year to year.
Cs-137 was detected in site boundary vegetation in both 1985 and 1986.
The 1985 sampie results showed positive detections of Cs-137 in three of the six indicator sample and no positive detections of Cs-137 in the control samples.
The 1985 Cs-137 indicator concen-trations ranged from 0.043 to 0.259 pCi/g (wet) with a mean concen-tration of 0.162 pCi/g (wet ).
Cs-137 was detected in four of six I
indicator samples collected in 1986.
The 1986 sample concentrations ranged from 0.031 to 0.035 pCi/g (wet) with a mean concentration of I
0.033 pCi/g (wet).
Cs-137 was detected in one of the control samples at a concentration of 0.035 pCi/g (wet).
The presence of Cs-137 in
]
1985 and 1986 site boundary vegetation samples can be attributed to several sources:
atmospheric nuclear testing, fall out from the Chernobyl Nuclear Plant accident, and/or plant operations at the site.
The presence of Cs-137 in the control vegetation sample in 1986 indicates that the source may be past weapons testing or fall out from I
the Chernobyl accident.
No Cs-137 was detected in the 1987 indicator or control samples.
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I 123 I
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9.
ENVIRONMENTAL SAMPLE LOCATIONS - TABLE 17 Table 16 contains the locations of the environmental samples presented B
in the data tables of Section IV.
The locations are give in degrees 5
and distance in miles from the Nine Mlle Point Nuclear Station Unit # 2 reactor centerline (middle site reactor),
Table 16 also gives the figure (map) number as well as the map destination for each sample location by sample medium type.
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I 10.
INTERLABORATORY COMPARISON PROGRAM - SECTION Vill I
Section 6.3.a of the Radiological Effluent Technical Specifications for the James A. FitzPatrick Nuclear Power Plant requires that a summary of the results obtained as pa rt of an interlaboratory comparison program be included in the Annual Radiological Environmental Op-erating Report.
Presently, the only NRC approved interlaboratory comparison program is the USEPA Cross Check Program.
Section Vill shows the results of the EPA's reference results and the licensee's results in tabular fo rm.
Some of the EPA reference samples have I
been analyzed by the site.
Other EPA reference samples have been analyzed by a vendor who normally analyzes those types of sample media for the site.
Participation in the EPA Cross Check Program includes sample media for which environmental samples are routinely collected, and for which intercomparison samples are available from the EPA.
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125 I
(
I CONCLUSION The Radiological Environmental Monitoring Program is conducted each year l
to determine the radiological impact of the James A.
FitzPatrick Nuclear l
Power Plant on the local environment.
As demonstrated by the analytical results of the 1988 program, the major radiological impact on the environ-i ment was the result of fallout from atmospheric nuclear testing and the 1986 Chernobyl accident which created a
ubiquitous inventory of background Cs-137 in the environment.
Samples representing food sources consumed at hlgher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the g
general environment or to man.
In addition, the data was reviewed for 5
any possible historical trends.
In regard to doses as a result of man-made radionuclides, a significant portion of the small doses received by a mem-ber of the public was from past nuclear weapons testing and fallout from the Chernobyl accident.
It should be noted that raost of the radionuclides detected in 1986, as a result of the Chernobyl accident, were not present in the sample media collected for the 1987 and 1988 programs.
Doses as a result of naturally occurring radionuclides, such as K-40, contributed a major portion of the total annual dose to members of the public.
Any possible impact as a result of site operations is extremely minimal when compared to the radiological impact from natural background levels and sources other than plant operation.
It has been demonstrated that almost all environmental samples contain traces of radionuclides which are a result of weapons testing, Chernobyl, or naturally occurring sources (primordial and/or cosmic related).
Whole body doses to man as a result of natural sources (naturally occurring radionuclides in the soll and lower atmosphere) in Oswego County account for approximately 67 mrem per year as demonstrated by control environmental TLD's.
Possible doses due to site operations are a minute fraction of the annual exposure.
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 from the operation of the James A.
Fitz Patrick Nuclear Power Plant.
The results of the 1988 Radiological Environmental Program 126
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demonstrate that controls on radiological effluents both by the design and safe operation of the plant are effective in protecting the environment and the gener: public.
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127 I
I-I REFERENCES t
I 1.
U.S.
Nuclear Regulatory Commission Regulatory Guide 1.109, " Ca l-I 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.
Nuclear Regulatory Commis-ion Regulatory Guide 1.109, " Ca l-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", October, 1977.
3.
- Eichholz, G., Environmental Aspects of Nuclear Power, First Edition, I1 Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan,1976.
I 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.
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.
128 I
I 10.
Eisenbud, Merril, Environmental Radioactivity, Second Edition, Aca-demic Press, New York, New York,1973.
11.
- Francis, C.
W.,
Radiostrontium Movement in Soils and Uptake in Plants, Environmental Sciences Division, Oak Ridge National Laborato-ry, U.S. Department of Energy,1978.
12.
National Council on Radiation Protection and Measurements (NCRP),
Radiation Exposure from Consumer Prnducts and Miscellaneous Sources, NCRP Report No. 56, l')77.
I 13.
Pochin, Edward E.,
Estimated Populaticn Exposure from Nuclear Power l
Production and Other Radiation Sou rces, Organization for Economic Co-operation and Development,1976.
I 14 ICRP Publication Number 29, Radionuclides Releases into the Environ-ment:
Assessment of Dose to Man,1979.
15.
U. S. Department of Health and Human Services, Preparedness and I
Response in Radiation Accidents, National Center for Devices and Radiological Health, Rockville, MD 20857, August,1983.
16.
- Kathren, Ronald E.,
RADIOACTIVITY IN THE ENV!RONMENT:
- SOURCES, DISTRIBUTION, AND SURVEILLANCE, First
- Edition, Harwood Academic Press, New York, NY,1984 I
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I 129
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M s-I I
HISTORICAL D ATA I
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C 2 "J e a" "
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I VI HISTORICAL DATA Sample Statistics from Previous Environmental Sampling 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 taken from the NINE MILE POINT, I
REOPERATION SURVEY, 1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.
2.
Sample data listed as 1974, 1978, 1979, 1980, 1981, 1982, 1983, 1984, 1985, 1986 and 1987 was taken from the respective environmental operating reports for Nine Mile Point Nuclear Station and James A.
I FitzPatrick Nuclear Power Plant.
3.
Only measured values were used for statistical calculations.
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HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Fish Samples MEAN MAllMUM MINIMUM RANCE STANDARD Cs-137 pCi/g (wet)
D E VI Ail 0 N 1988 0.034 0.012 0.053 0.023 0.030 1987 0.031 0.009 0.040 0.017 0.023 1986 0.025 0.004 0.032 0.021 0.011 1985 0.034 0.008 0.047 0.026 0.021 I
1984 0.032 0.009 0.038 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 1981 0.043 0.016 0.062 0.028 0.034 l
1980 0.059 0.032 0.110 0.029 0.081 1979 0.04 0.01 0.06 0.03 0.03 g
1978 0.09 0.05 0.20 0.04 0.16 1974*
0.43 0.37 0.94 0.09 0.85 l
1969(PRE-0PER Ail 0N AL )**
NO DATA INDICATOR Fish Sag les NEAN STANDARD NA!! NUN WININUM RANCE Cs-137 pCi/g (wet)
DEVIAil0N 1988 0.032 0.010 0.054 0,022 0.032 1987 0.033 0.011 0.063 0.024 0.039 1986 0.028 0.012 0.051 0.009 0.042 1985 0.030 0.009 0.045 0.018 0.027 g
1984 0.043 0.008 0.061 0.033 0.028 1983 0.050 0.009 0.060 0.030 0.030 1982 0.050 0.008 0.064 0.034 0.030 I
l 1981 0.061 0.021 0.10 0.027 0.073 l
1980 0.061 0.029 0.100 0.030 0.070 1979 0.10 0.14 0.55 0.02 0.53 1978 0.08 0.02 0.10 0.03 0.07 l
19 74*
0.57 0.85 4.40 0.08 4.32 19 6 9 (PR E - 0 P E A Ail 0 N AL)**
0.06 0.04 0.13 0.01 0.12 e 1969 Data is considered to be Pre-Operational for the Site.
e e 1974 Data is considered to be Pre-Operational for the J. A. Fitzpatrick N. P. P.
131 I
U HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD Surface (Lake) Water MEAN M AXIMUM MINIMUM RANCE E
i wf e4,m nci /1 DE Vl A T10 N g
1988 v>n 96 460 240 220 l
1987 210.0 64.8 270 140 130 1986 373,o 357.0 550 250 300 1985 l4 287.5 95.4 430 230 200 1984
?os.0 21.2 220 191 30 1983 250.0 21.8 280 230 50 1982 165.0 94.7 307 112 195 1981 f
293.3 49.3 357 211 146 1980 257.3 38.5 290 211 79 1979 258.7 73.7 308 174 134 l
1978 303.8 127.5 490 215 275 1974*
<m 1969(PRE-0PE R A Tl0N AL )**
(g i
i INDICATOR g
Surface (Lake) Water MEAN STANDARD MAXIMUM MINIMUM RANCE w4 e4,, g4 n DEVIATION 1988 460 27 480 430 50 1987 172.5 111.2 410 160 250 1986 un n 118.0 500 260 240 1985 530.0 448.6 1200 250 950 1984 282.0 98.1 370 110 260 1983 317.0 116.9 560 190 370 1982 641.0 891.1 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 1978 389.4 119.9 560 253 307 g
19 74*
440.0 84.9 500 380 120 5i 19 6 9 (PR E - 0 PE R A Tl0 N A L )"
440.0 84.9 500 380 120
~
e 1969 Data is considered to be Pre-Operational for the Site.
- 1974 Data is considered to be Pre-OperatK>nal for the J. A. Fitzpatrick N. P. P.
132
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I HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Air Particulate ST NOARD 3
MEAN MAXIMUM MINIMUM RANCE Gross Beta pCi/m DE VI Ail 0N 1988 0.018 0.007 0.039 0.008 0.031 g
1987 0.021 0.006 0.037 0.009 0.028 1986 0.039 0.049 0.272 0.008 0.264 1985 0.024 0.006 0.043 0.013 0.030 I
1984 0.026 0.007 0.051 0.013 0.039 1983 0.024 0.009 0.085 0.007 0.078 1982 0.033 0.012 0.078 0.011 0.067 1981 0.165 0.135 0.549 0.016 0.533 l
1980 0.056 0.04 0.291 0.009 0.282 1979 0.077 0.086 0.703 0.010 0.693 g
1978 0.14 0.13 0.66 0.01 0.650 1974*
0.121 0.104 0.808 0.001 0.807 1969(PRE-0PE R Ail 0N Al )*
- 0.334 0.097 0.540 0.130 0.410 I
I INDICATOR Air Particulate NEAN STANDARD MAllMUM MINIMUM RANCE 3
Gross Beta pCi/m DEVIAil0N 1988 0.018 0.006 0.040 0.007 0.033 1987 0.021 0.006 0.040 0.009 0.031 l
1986 0.039 0.050 0.289 0.007 0.282 1985 0.021 0.006 0.044 0.001 0.043 g
1984 0.025 0.008 0.058 0.000 0.058 1983 0.023 0.009 0.062 0.003 0.059 1982 0.031 0.012 0.113 0.001 0.112 I
1981 0.151 0.128 0.528 0.004 0.524 1980 0.045 0.03 0.207 0.002 0.205 1979 0.058 0.06 0.271 0.001 0.270 1978 0.10 0.09 0.34 0.01 0.33 l
19 74*
0.111 0.114 0.855 0.003 0.852 l
19 6 9 (PR E - O P E R Ail 0 N Al)**
0.320 0.090 0.520 0.130 0.390 e 1969 Data is considered to be Pre-Operatbnal for the Site.
- 1974 Data is considered to be Pre-Operat6onal for the J. A. Fitzpatrick N. P. P.
133
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I HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL STANDARD Hvinn. HD's Qurterly g E Ait MAX l MUM MINIMUM RANGE E
IwrHm MSnW Mrth DE VI A T10N g
1988 sa;9 0.72 6.80 4.80 2.00 1987
....,5. 2 6 0.38 5.90 4.70 1.20 1986 6.40 0.68 7.60 5.30 2.10 1985 g
5.21 0.47 6.30 3.95 2.35 1984 5.87 1.00 8.20 3.90 4.30 1983 5.54 0.364 7.17 4.21 2.96 1982 5.12 0.691 6.95 3.79 3.16
' 19' 8 1 4.72 0.685 6.63 3.24 3.39 1980 4.57 0.614 6.06 3.12 2.94 1979 REPORTED AS MRFR/0TR PRIOR 'ID 1980 1978 l
1974*
1969(PRE-0PE R Ail 0N AL )**
INDICATOR g
EhVLttn. HD'S QErtEly MEAN STANDARD MAXIMUM MINIMUM RANCE
%ygm r,rrm/w w 0E Vi AT10N 1988 5.88 2.10 17.90 3.90 14.00 1987 s.62 1.43 14.50 3.50 11.00
[~
1986 r, s1 1.93 18.70 4.10 14.60 1985 5.65 0.79 7.35 4.45 2.90 1984 l
6.42 1.26 9.90 4.60 5.30 1983 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 1980 nA'rA mr CCMPADAM F DUE TO CHANGES 1979 IN TLD IDCATIONS 1978 l
19 74*
19 6 9 (P R E - 0 P E R Ail 0 N A L)**
e 1969 Data is considered to be Pre-Operational for the Site.
e e 1974 Data is considered to be Pre-Operational for the J. A. Fitzpatrick N. P. P.
134
W I
l HISTORICAL ENVIRONMENTAL SAMPLE DATA l
CONTROL Milk Samples STANDARD Cs-137 pCi/1 MON MAXIMUM MINIMUM RANCE DE VI A T10 N 1988
<ILD 1987
<ILD t
1986 8.4 3.6 12.4 5.3 7.1 1985
<I1D l
1984 (ILD 1983
<ILD l
1982
<ILD 1981 7.0 ONLY ONE DATA PODTP g
1980
<I1D 1979 3.73 0.29 3.9 3.4 0.5 1978 5.83 1.98 7.8 2.4 5.4 I
1974*
1969(PRE-OPER A TION AL )**
INDICATOR Milk Samples MEAN STANDARD MAllNUM MININUN RANCE Cs-137 pCi/1 DEVIATION l
1988 10.0 ONLY ONE DATA POINT 1987 7.4 2.8 9.4 5.5 3.9 g
1986 8.6 1.7 11.1 6.1 5.0 1985
<ILD 1984
<ILD B
1983 5.10 ONLY ONE DATA POINT i
i 1982 6.26 4.41 18.0 3.1 14.9 1981 7.57 5.95 29.0 4.3 24.7 1980 9.7 4.9 21.0 4.0 17.0 l
1979 9.4 8.0 40.0 2.7 37.3 19 78 9.9 7.1 33.0 3.4 29.6 g
19 74 e 26.1 10.5 61.0 13.0 48.0 19 6 9 (P A E - 0 PER A Tl0N A L )**
NO DATA E
e 19tf 9 Data is consk$ered to be Pre-Operational for the Site.
- 1974 Data is considered to be Pre-Operational for the J. A. Fitzpatrick N. P. P.
135 I
I HISTORICAL ENVIRONMENTAL SAMPLE DATA I
CONTROL STANDARD Milk Samples MEAN MAXlMUM MINIM 8JM RANCE T-111 nCi/1 DE VI Ail 0N 1988 ain 1987 l
<TTn 1986 13.6 14.3 29.0 0.8 28.2 1985
<T T n g!
1984
< Tin 1983
<um 1982
<uD 1981
<ur 1980 1.41 ONLY ONE DATA POINT 1979
<us 1978 l
(MDL 1974*
m DATA 1969(PRE-0PER Ail 0N AL )**
NO DATA INDICATOR g
Milk Samples MEAN STANDARD gag lggy MINIMUM RANCE T 111 nci /1 DEVIAil0N 1988
<uD 1987
<uD 1986 5.2 7.5 30.0 0.3 29.7 1985
<ur 1984 l
<um 1983
<uD 1982 l
<ur 1981
<um 1980 4.9 4.23 8.80 0.40 8.40 1979
<ur 1978 0.19 ONLY ONE DATA POINT 19 74*
1.23 0.44 2.00 0.70 1.30 19 6 9 (PR E - 0 P E R Ail 0 N AL)**
NO DATA
- 1969 Data is considered to be Pre-Operational for the Site.
- 1974 Data is considered to be Pre-Operational for the J. A. Fitzpatrick N. P. P.
136
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HISTORICAL ENVIRONMENTAL SAMPLE DATA h
CONTROL 1
Human Food Crops STANDARD MEAN MAXIMUM MINIMUM RANGE Cs-137 pCi/g (wet) Produc 3 DEVIATION 1988
<ur g
1987
<ur 1986
<uD 1985
<uD 5
1984
<uD 1983
<um l
1982
<ur 1981
<um l
1980
<uD 1979 NO CONTROL DATA PRIOR TO 1980 1978 I
1974*
1969(PRE-0PE R ATION AL )"
IN DIC ATO R Human Food Crops MEAN STANDARD MAXIMUM MINIMUM RANCE Cs-137 pCi/g (wet) Produce DEVIATION l
1988 0.008 ONLY ONE DATA POINT 1987
<um g
1986
<n n 1985 0.047 ONLY ONE DATA POINT 1984
<uD I
1983
<um 1982
<um 1981
<uD 1980 0.033 2.26 0.06 0.004 0.056 l
1979
<uD 1973 0.01 ONLY ONE DATA POINT g
19 74*
0.142 0.09 0.34 0.04 0.30 19 6 9 (PR E - 0 PE R Ail 0N A L)"
NO DATA E
e 1969 Data is considered to be Pre-Operational for the Site.
- 1974 Data is considered to be Pre-Operational for the J. A. Fitzpatrick N. P. P.
137 I
U~
I HISTORICAL ENVIRONMENTAL SAMPLE DATA I
Il CONTROL 4
Human Food Crops STANDARD MEAN MAXlMUM MINIMUM RANCE I-131 pCi/g (wet) Produce DEVIAil0N 1988
<up ll 1987
<uD 19 E 6
<tto 1985
<ur g'
1984
<ur 1983
<ur g
1982
<ur E
~
1981
<ua l
1980
<ttD 1979 NO CONTROL DATA PRIOR 'ID 1980 1978 g
1974*
1969(PRE-OPE R ATION AL )**
INDICATOR g
Human Food Crops MEAN STANDARD MAXIMUM MINIMUM RANCE I-131 oCi/R (wet) Produce OE VI Ail 0N 1988
<ua 1987
<tto 1986
<ur 1985
<ua l
1984
<uD 1983
<ua 1982
<ur g'
1981
<LLD 1980
<uD 1979
<um i
19 78
< Mot l
19 74*
NO DATA 19 6 9 ( PR E - 0 P E R ATl0 N A L)**
NO DATA
- 1989 Data is considered to be Pre-Operational for the Site.
o e 1974 Data is considered to be Pre-Operational for the J. A. Fitzpatrick N. P. P.
138 I
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FIGURES AND MAPS I
I I
I I
- > NewWrkPbwer 4er Authority g
I
I Vil FIGURES AND MAPS l
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 I
Sample locations referenced as letters and numbers on analysis results tables are plotted on maps.
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E USEPA ENVIRONMENTAL RADIOACTIVITY I
LABOR ATORY INTERCOMPARISON STUDY PROGR AM E
I I
I CMM" g
E
t)
I Vill
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS I
This section includes results of JAF analyses compared to reference I
samples originating from the United States Environmental Protection Agency (USEPA).
As required by the Technical Specifications, participation in this program includes media for which environmental samples are routinely collect-ed.
All intercomparison data is summarized in table form.
The tables are titled "USEPA Environmental Radioactivity Laboratory Intercomparison Study I
Prog ram".
The USEPA reports interlaboratory results in terms of normalized I
deviations from a
known value (NDKV).
Interlaboratory results are considered acceptable by the EPA if the laboratory's NDKV for a sample is between plus 3 and minus 3.
For example, the NDKV for QA 88-101 is -0.23.
Since this value is less than plus 3 but greater than minus 3,
the EPA I
considers this value acceptable.
During the 1988 program, 2 results reported by the JAF laboratory fell I
outside of the acceptable NDKV range.
The initial analysis of QA 88-031, an air particulate filter, was reported high resulting in a NDKV outside of the acceptable range.
Subsequent I
re-calibration of the counting instrument and re-analysis of the sample yielded acceptable results.
Unacceptable results were also reported for QA 88-006, a food sample containing 2 isotopes.
Historically, results for food samples have been biased.
It is believed that the food matrix provided by the EPA is not I
representative of actual food samples, however, the JAF laboratory results were within the acceptable range for 1 of the 2 isotopes.
The EPA has discontinued the use of food matrix samples for the 1989 program.
Overall, the J AF laboratory's performance was satisfactory; acceptable results were reported for 41 of 43 samples.
I I
l
' I I
1
'I 158 I
1-lI I
TABLE VIII-1
'l USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY
,5 INTERCOMPARISON STUDY PROGRAM l
l Gross Beta Analysis of Air Particulate Filters (pCi/ filter) l Gross Beta Analysis of Water (pCi/ liter) l JAF JAF EPA DATE ENV ID NUMBER MEDIUM ANAYLSIS RESULT (1)
RESULT (2)
NDKV(5)
I03/88 QA88-031 APF BETA 6214 ( )
5015 4.27 6214 6314 f
04/88 QA88-041 WATER BETA 6012 ( }
5715 1.50 6312 6112 I
08/88 QAB8-101 APF BETA 2813 ( )
2915
-0.23 2813 I
2913 10/88 QA88-134 WATER BETA 5215 (
5415
-1.04 I
4915 5215 I
I I
I I
I I
I 159 I
I I
TABLE VIII-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Tritium Analysis of Water (pCi/L)
JAF JAF EPA g
DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1)
RESULT (2)
NDKV(5) g 02/88 QA88-013 WATER H-3 35031441( )
33271362 0.84 l
34351435 35691437 up 33001100(')
33271362 0.13 3
32301200 5'
35301100 06/88 QA88-070 VATER H-3 60501280(3) 55651557 1.49 60171255 60681306 63001300(4) 55651557 1,15 58001300 57001400 10/88 QA88-129 WATER H-3 25241137( )
23161350 0.93 25041138 24851138 23001100(')
23161350
-0.08 24001100 22001200 I
I I
I I
160 I
I TABLE VIII-3 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY 1
I INTERCOMPARISON STUDY PROGRAM Iodine Analysis of Water (pci/L) and Milk (pCi/L)
JAF JAF EPA
_ DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1)
RESULT (2)
NDKV(5) 03/88 QA88-018 MILK I-131 4.011.0( )
4.010.4 2.89 5.011.5 I
5.011.1
<4.010.5( )
4.0i4
-1.44 I
3.010.5 4.010.4
()
QA88-037 WATER I-131 811 7.5010.5 1.15 I
04/88 811 811 I
06/88
()
QA88-071 MILK I-131 9412 9419 0.06 9412 9512 110115 ( )
9419 1,76 102112 98113 I
()
08/88 QA88-090 WATER I-131 77 3 76 8 0.51 7913 7913
()
10/88 QA88-135 MILK I-131 9012 9119
-0.32 8912 I
8913 (3) 12/88 QA88-162 WATER I-131 11816 115112 0.38 l
11917 11816
()
I 99 2 115112
-1.25 110110 110110 I
I I
161 I
1
I I
TABLE VIII-4 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Gamma Analysis of Milk, Water (pci/L)
Air Particulate Filters (pCi/ filter) and Food Products (pCi/kg)
JAF JAF EPA DATE ENV ID NUMBER MEDIUM FUCLIDE RESULT (1)
RESULT (2)
NDKV(5)
I) 01/88 QA88-006 FOOD Cs-137 8114 9115
-3.118 l
8212 8318 I-131 95110( )
102110
-0.962 9617 9816 02/8S QA88-007 WATER Co-60 6617 ( )
6915
-0.231 6914 7012 Zn-65 95111( )
9419 0,798 10016 10013 I)
Ru-106 100130 105 11
-0.055 104114 110111 Cs-134 6316 (3) 6415
-1.039 6013 6011 Cs-137 9317 ( )
9415
-0.808 9113 91 2 03/88 QA88-031 APF Cs-137 1914 ( )
1615 1.27 l;
2013
='
2014 I
I t
1 162 I
l I
TABLE VIII-4 (Continued)
USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Camma Analysis of Milk, Water (pCi/L)
Air Particulate Filters (pci/ filter) and Food Products (pCi/kg) j i
JAF JAF EPA DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1)
RESULT (2)
NDKV(5) 04/88 QA88-041 VATER Co-60 5216 ( )
5015 0.35 i
4916 5216 I
Cs-134 512 (3) 715
-0.35 612 714 Cs-137 813 (3) 715
-0.12 I
612 6i2 06/88 QA88-068 WATER Cr-51 278152( )
302130 0.48 I
294150 359149 Co-60 1414 ( )
1515
-0.58 I
1314 1313 Zn-65 81112( )
101110
-1.21 106i16 95i11 Ru-106 184140( )
195120
-0.09 206147 192132 l
Cs-134 2517 ( )
2015 0.35 2115 I
1713 Cs-137 2415 ( )
2515 0.00
.I 2616 2514 QA88-071 MILK Cs-137 4815 ( )
5115
-0.35 I06/88 5417 4815 I
163 I
I Il TABLE VIII-4 (Continued)
USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM
=
Gamma Analysis of Milk, Water (pCi/L)
Air Particulate Filters (pC1/ filter) and Food Products (pCi/kg)
JAF JAF EPA DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1)
RESULT (2)
NDKV(5) 07/88 QA88-089 FOOD I-131 110116 (3) 107111 0.00 104112 107110
()
Cs-137 4517 4915
-0.92 4916 4516
()
08/88 QA88-101 APF Cs-137 1916 1215 2.42 1816 g
2016 g
10/88 QA88-128 WATER Cr-51 286135 ( )
251125 2.06 284141 272147 i
()
co-60 2914 2515 1.15 2715 29 6 Zn-65 143113 ( )
151115
-0.38 152116 148117 Ru-106 127130 (3) 152115
-2.96 123134 129136
()
Cs-134 2816 2515 0.92 2814 2715 I)
Cs-137 1613 1515 0.46 1814 1515 I
I 164 I
I TABLE VIII-4 (Continued)
I USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM
{
l Gamma Analysis of Milk, Water (pci/L) l Air Particulate Filters (pCi/ filter) and Food Products (pci/kg)
JAF JAF EPA DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1)
RESULT (2)
NDKV(5) 10/88 QA88-134 VATER Cs-134 1312 (3) 1515
-0.92 1213 1212 Cs-137 1513 ( )
15 5
-0.12 1314 1613 10/88 QA88-135 MILK Cs-137 4717 ( )
5015
-1.39 4418 4717 I
I
)
(
I l
(1) Results reported as activity 1 the error (2 sigma).
I (2) Results reported as activity 1 the standard deviation of the error.
(3) Analyzed at the site environmental laboratory.
(4) Analyzed at a vendor laboratory.
(5) NDKV is the Normalized Deviation from Known Value as determined by I
the EPA.
lI I
165 I
1
_