JAFP-87-0365, Radiological Environ Surveillance Rept,1986,Part B: Radiological Rept
| ML20234E190 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1986 |
| From: | Radford Converse POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Russell W NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-87-0365, JAFP-87-365, NUDOCS 8801070474 | |
| Download: ML20234E190 (152) | |
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I 1986 i
RADIOLOGICAL ENVIRONMENTAL !
SURVEILLANCE REPORT JANUARY 1,1986 through DECEMBER 31,1986 l a
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I NEW YORK POWER AUTHORITY ANNUAL ENVIRONMENTAL OPERATING REPORT PART B: RADIOLOGICAL REPORT JANUARY 1,1986 - DECEMBER 31, 1986 JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333 f
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i TADLE OF CONTENTS
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- 1. INTRODUCTION Introduct!on I l
Program Objectives '
il. PROGRAM IMPLEMENTATION AND DESIGN Sample Methodology l.
Analysis Performed '
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^ Changes in Program 111. SAMPLE SUMMARIES IV. ANALYTICAL RESULTS
.V. DATA SUMMARIES AND CONCLUSIONS Lake Program Terrestrial Program Conclusion Exceptions to the Program References VI . HISTORICAL DATA Vll. FIGURES AND MAPS Vill.
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDIES PROGRAM '
RESULTS i
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LIST OF TABLES Page Table i Required Sample Collection and Analysis (1/1/86 - 12/31/86)
Teble 1 Shoreline Sediment Results Table 2 Fish Results Table 3 Water Composite Results, Tritium Table 4 Water Composite Results, Gamma. Isotopic
' Table 5 Particulate Filter Results, Cross Beta (Offsite)
' Table 6 Particulate Filter Results, Cross Beta (Onsite)
Table ' 7 Airborne I-131 Results (Offsite Stations)
Table 8 Airborne 1-131 Resuits (Onsite Stations)
Tabic 9 Particulate Composite Results, Gamma Isotopic Table 10 TLD Results Table 11 Milk Results,1-131 Table 12 Milk Results, Camma isotopic Table 13 Milch Animal Census Results Table 14 Food Product Results, Gamma Isotopic Table 15 1986 Residence Census Table 16 Environmental Sample Locations Table Vill-1 Gross Beta Analysis Air Particulate (pCi/L)
Table Vill-2 Tritium Analysis of Water (pCi/L)
Table Vill-3 lodine Analysis of Water (pCi/L) and Milk l (pCi/L)
Table Vill-4 Gamma Analysis of Milk, Water (pCl/L), Air Particulate (pCl/ filter) and Food Products (pCl/kg)
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LIST OF FIGURES ,
l Page Figure 1A Offsite Environmental Stations and TLD Lccations Figure 18 Offsite. Environmental Stations and TLD Locations (Southern)
Figure 2 Onsite Environmental Stations, TLD Location. , and Site Boundary Vegetation Locations Figure 3 Nearest Residence and Food Product Locations Figure 4 Milch Aniraal Census and Milk Sample Locations ;
Figure 5 New York State Regional Mcp Figure 6 Graph - Fish (Cs-137)
Figure 7 Graph - Air Particulate Cross Beta Figure 8 Graph - Air Particulate Cross Beta, Weeks 1-26 (1986)
Figure 9 Graph - Air Particulate Cross Beta, Weeks 27-52 i (1986) i i
Figure 10 Graph - Air Particulate Composite (Co-60)
Figure 11 Graph - Air Particulate Composite (Cs-137)
Figure 12 Graph - Milk (Cs-137)
Figure 13 Graph - Milk (Cs-137), Stations 4,16 and Control for 1986 Figure 14 Graph - Milk (Cs-1.17), Stations 7, 60 and Control for 1986 Figure 15 Graph - Milk (Cs-137), Stations 50, 55 and Control for 1986 Figure '6 Graph - Milk (1-131) iii )
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- .m. i INTRODUCTION l
I-A INTRODUCTION The New York Power Authoriti [NYPA) is the-owner, and-licantee of the
. James A. FitzPatrick Nuclear FSwer Piant (JAFWPf() which is located on the eastern portion of the Nirm Mlle. Point pr ,montory approximately one-half mile due east of the Nkpara Monauk .14wer Corporation (HMPC) Nine Mile Point Nuclear Pewer.. Sbtion (NMPNPS). The NMPNPS Unit #1 is located on. the western pertion of the site and is ' a ' boiling water reactor with a design -
capacit9 of %0 MWc. The NMPNPS has been in comsnercial operatloa since the rail of 1969. Located between the JAFNPP and NMPNPS, Nine.Mlle Po!nt Unit
- 2 is under construction. ' NMPNPS Unit. #2 will have generstion capacity of 1,100 MWe and is expected to be completed in 1597. The JAFNPP is a boiling water reactor with a power output of 810 #AWt (net). Initial fuel loading of the reactor core was completed in November of' 1974. Initial criticality was achieved in late November,1974 ano comemarcial operation began in July of
~1975.
The site is located on .the southern shore of Lake Ontario in Oswego County, New York, approximately seven miles northeast of the city of Oswe-go, New York. Syracuse, New York la the largest metropolitan cencer in the ares and is located 40 miles to the south of the site. The area consists of partially wooded lead and shoreline. The land adjacent to the site is used mainly for recreational and residential purposes. For many miles to the west, east and south the country is characterized by. rolling terrain rising gently up from the Iske, composed mainly of glacial deposits. Approximately 34 percent of the fand area }n Oswego County is devoted to farming.
. The Radiological Environmental Monitoring Program for' the FitzPatrick Plant is a site program with responsibility for the program shared by the Fewer 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 throJgh each organization.
This report is submitted in accordance with Section 7.3.d of the i Radiological Effluent Technical Specifications (RETS) to DPR-59, Docket 30-333.
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l-B PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program are as follows:
- 1. To determine and evaluate the effects of plant operation on the environs and to verify the effectiveness of the controls on radioactive material sources.
- 2. To monitor and evaluate natural radiation levels in the environs of the JAFNPP site.
- 3. To meet the requirements of applicable state and federal regulatory guides and limits.
- 4. To provide information by which the general public can evaluate the environmental aspects of nuclear power using data which is factual and unbiased.
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1 To achieve the objectives listed in Section I-B, sampling and analysis are performed as outlined in Table 1.
1 The sample collections for the radlaiogical program are accomplished by a f dedicated site environmental staff from both the James A. FitzPatrick Plant ;1 and the N!nc Mlle Point Station. The site staff is assisted by a contracted ;
environmental engineering company, Ecological Analysts, Inc.(EA).
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- 1. SAMPLE COLLECTION METHODOLOGY A. Surfa::e Water Surface water samples are takien from the respective iniet canals of JAFNPP and Niagara Mohawk's Oswego Steam Station (OSS). The JAFNPP removes water from Lake Ontario en a continuous basis and generally represents a "down-current" sampling point from the Nice Mile Point Unit 1 facility. The OSS inlet canal removes water from Lake Ontario at a point approximately 7.6 miles west of the site.
This "up-current" location is considered a control locction because of the distance from the sita 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 large compositing tank. Samples !
are obtained from the tank monthiy ena ar;alyzec for gamma emit-ters. 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 composite 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 quarter. Quarterly composite samples are analyzed for tritium.
Surface water sample locations are shown on Figure 1 A.
B. Air Particulate / lodine The air sampiing stations required by the RETS are located in the 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 measured from the center of the Nine Mile Point Nuclear Station Unit 2 reactor building. The RETS also require that a fourth air sampling station be located in the vicinity of a year round communi-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 of east-northeast ( R-5 ) . This location is considered a control lo-cation.
in addition to the RETS required locations , there are nine other sampling stations located within the site boundary. These locations generally surround the area occupied by the three generating facil-ities, but are well within the site boundary. One other air sampl-ing station is located off-site in the southwest sector and is in the vicinity of the City of Oswego.
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At each station, airborne particulate are collected by glass fiber filters and radiolodine by charcoal filters. Air particulate glass fiber filters are approximately two inches (47 millimeters) in diame-ter and are placed in sam; le holders in the intake line of a vacuum sampler. Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to absorb airborne radioiodine. The samplers run continuously and the charcoal cartridges and particu-late filters are changed on a weekly basis, or as required by dust '
loading. Cross beta. analysis is performed for the individual par-ticulate filters on a weekly basis. Charcoal cartridges are analyzed weekly for radiciodine by Gell detector.
The particulate filters are composited for gamma analyses on a i monthly basis by location after all weekly particulate filters have been counted for gross beta activity. l Air sampling stations are shown in Figures 1 and 2. i C. Milk ,
Milk samples are collected in polyethylene bottles from the bulk i storage tank at each sampled farm. Before the sample is drawn, l the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat. Two gallons are col-lected during the first half and second half of each month from each of the selected locations within ten miles of the site and from a control location. The samples are chilled a.nd shipped to the ana-lytical contractor within thirty-six hours of collection in insulated
, shipping containers.
1 Milk samples are collected twice per month (April - December) and analyzed for gamma emitters and 1-131. Samples are collected and analyzed in Jar.uary - March in the event 1-131 is detected in No-vember and December of the preceding year.
The milk sampling locations are found in Figure 4 D. Food Products One kilogram samples of three different kinds of broad leaf vege-tation (edible or inedible) are collected during the late summer harvest season. Sample collections are performed at the site boundary in two different locations. The broad leaf vegetation is chilled prior to shipping and shipped fresh in insulated containers.
Attempts are made to collect control samples located 9-20 miles dis-tant for each type of sample (see Section Vil, Figure 2).
E. Fish Samples Available fish species are removed from the Nine Mile Point Aquatic Ecology Study monitoring collections during the spring and fall collection periods. Samples are collected from a combination of the four onsite sample t ransects and one offsite sample transect (see 6
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l Section Vil, Figure 1). Available species are selected under the following guidelines:
- 1) 0.5 to 1 kilogram of edible portion only of a maximum of three species per location.
- 2) Samples composed of more than 1 kilogram of single species from the same location are divided into samples of 1 kilogram i each prior to shipping. A maximum of three samples per spe- l cies per location are used. Weight of samples are the edible {
portions only.
i Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in i insulated containers for analysis.
F. Shoreline Sediments One kilogram of shoreline sediment is collected at one area of exist-ing or potential recreational value and from one area beyond the influence of the site. The samples are placed in plastic bacs, sealed and shipped for analysis in insulated containers.
Shoreline sediment locations are shown on Figure 1 A.
G. 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 vendor's laboratory. Shipment control TLD's also accompany the 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 for a transit dose by use of the data from the shipment control 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 four to five miles from the site in eight available land based 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 1986 were composed of rectangular teflon wafers impregnated with 25 percent CaSO .: Dy phosphor. These were placed in a polyethylene package to ensure dosimeter integrity.
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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 Figures 1 A,1B, and 2.
H. Land Use Census A land use census is conducted during the beginning of the grazing season to determine the utilization of land within a distance of five miles from the site. The land use census usually consists of two types of census. A milk animal census is conducted to identify all milk animals within a distance of five miles from the site. This census is conducted by using road surveys, contacting local ag-ricultural authorities, post 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 22i degree meteorological sectors. A residence, for the purpose of this census, is a residence that is occupied on a part time basis (such as a summer camp) or on a full time, year round basis. For the residence census,. several of the meteorological sectcrs are over Lake Ontario because the site is located at the shoreline. No resi-dences are located in these sectors. There are only eight sectors over land where residences are located within five miles.
- 1. Interlaboratory Comparison Program An interlaboratory comparison program is conducted with reference 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-able.
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- 2. ANALYSIS PERFORMED The analysis of the environmental samples is performed by Teledyne isotopes (TI) and the James A. FitzPatrick Environmental Counting 1. abo-ratory (JAFECL). The following samples are analyzed at the JAFECL:
Air Particulate Filter - gross beta (weekly)
Air Particulate Filter Composites - gamma spectral analysis (month-ly)
Airborne Radiolodine - gamma spectral analysis (weekly)
Surface Water Composites - gamma spectral analysis (monthly)
Special Samples (soil, etc.) - gamma spectral analysis (as collected)
The remainder of the sample analysis as outlined in Table ! Is performed by Tl.
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- 3. _C_HANCESp THE 1986 SAMPLE PROGRAM A. Milk sample location number 65 was added to the milk sampling program in August, 1986. This location was added because milk sample location number 40 (control location) sold their dairy herd on August 15, 1986. Milk sample location number 65 became the new control iccation starting with the August 18, 1986 milk samples.
B. Milk sample % cation number 40 was deleted from the milk sampling program ir. ' vgus t , 1986. This location was deleted because they sold their dairy herd on August 15, 1986.
C. Several environmental TLD locations were added to the program during 1986. Program TLD numbers 104-106 were added during the 2nd quarter of 1986. g.
D. Program TLI', #88 was moved from Dvv.,ter Beach Road (4.8 miles @
978) to Hickory Grove Rotd (4.5 ed 'es @ 97 ). This change was effective Aprii 2 1986.
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NOTES FOR TABLE I (a) It is recognized that, at times, it may not be possible or practical to obtain samples of the media of choice at the most desired location or ;
time. In these instances suitable alternative media and locations may l be chosen for the particular pathway in question. Actual locations (distance and directions) from the site shall be provided in the Annual Radiological Environmental Operating Report. Calculated site averaged D/Q values and meteorological parameters are based on historical data (specified in the CDCM) for all licensed site reactors.
(6) Particulate sample filters should be analyzed for gross beta 24 hours2.777778e-4 days <br />0.00667 hours <br />3.968254e-5 weeks <br />9.132e-6 months <br /> or more after sampling to allow for radon and thoron daughter decay.
If gross beta activity in air is greater than 10 times a historical l yearly mean of control samples, gamma isotopic analysis shall be l performed on the individual samples, j (c) Camma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the plant.
(d) The purpose of these samples is to obtain background information. if it is not practical to ' establish control locations in accordance with the distance and wind direction criteria, other sites which provide valid background data may be substituted.
(e) One or more instruments, such as a pressurized ion chamber, for measuring and recording dose rate continuously may be used in place of, or in addition to, integrating dosimeters. For the purpose of this table, a thermoluminescent dosimeter may be considered to be one phosphor and two or more phosphors in a pocket may be considered as two or more dosimeters. Film badges shall not be used for mea-suring direct radiation.
(f) The " upstream sample" shall be teken at a distance beyond significant influence of the discharge. The " downstream sample" shall be taken en an area beyond, but near, the mixing zone, if practical.
(g) Composite samples should be collected with equiprnent (or equivalent) which is capable of collecting an aliquoit at time intervals which are very short (e.g. , hourly) relative to the compositing period (e.g.,
monthly) in order to assure that a representative sample is obtained.
14
(h) A milk sampling location, as required in Table 6.1-1 is defined ac a location having at least 10 milking cows present at a designated milk sample location, it has been found from past experience, and as a result of conferring with local farmers, that a minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes. Locations with less than 10 milking cows are usually utilized for breeding purposes which eliminates a stable supply of milk for samples as a result of suckling calves and periods when the adult animals are dry. In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used if an adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer.
15
l ill k' -
u$'\
l SAMPLE SUMMARIES i
til SAMPLE SUMMARIES ,,
All sample data is summarized in table form. The tables are titled '
" Radiological Monitoring Program Annual Summary" and use the follow- g ,
ing format: [ ';
'17 ..
A. Sample medium.
B. Type and number of analyses performed.
C. LLD (Lower Limits of Detection). This wording indicates ,
that inclusive data is based on 4.66 sigma of background. '
D. The mean and range of the positive measured values of the indicator locations.
E. The mean , range, and location of the highest indicator 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.
NOTE: Only positive measured values are used in statistical calcula-tions. The use of LLD's in these calculations would result A
in means being biased high.
s 16
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ANNUAL
SUMMARY
TABLE NOTES
- = Data for the Annual Summary Tables is based on RETS required samples only.
N/A = Not applicaN e.
(a) = Fraction of detectable measurement to total measurement.
(b) = Location is distance in miles, and direction in compass degrees.
(c) = Indicator TLD locations are: 67, 23, 75, 76, 77, 78, 79, l 80, 81, 82, 83, 84, 85, 86, 87, 88, %9, 90, 91, 92, 93,
! 94, 95, 96, 97, 98, 99, 100, 101, 8, 15, 18, 56, and SP Control TLD's are all TLD's located beye c d the influence of the site (#14, 49).
(d) = Indicator samples.from environmental stations R1 offsite, R2 offsite, R3 offsite, and Rd offsite. Control samples are samples from R5 offsite environmental station.
(e) = This dose is not representative of doses to & member of the public since this aree is located near the north shoreline which is in elose proximity to the generating facility and is not accessible to members of the public (see Section V.4-TLD's).
(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.
'There fore , the only sample location required by the RETS is the control location.
(g) = The RETS do not specify a particular LLD velue for surface water analysis (non-drinking water) for 2-131. A value of 15 pCi/ liter is used here and represents the moet recent guidance from the NRC.
4h) = Data for particulate I-131.
21
I IV
\
w;N ANALYTICAL RESULTS
IV ANALYTICAL RESULTS 1
Environmental Sample Data '
l Environmental sample data is summarized by tables. Tables are pro- ;
vided for select sample med;a and contain data based on actual values
! obtained over the year. These values are comprised of both positive val-ues and LLD values where applicable. ,
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)
TABLE 13 MILCH ANIMAL CENSUS 1986 NUMBER OF NUMBER TOWN OR AREA (a) CENSUS MAP ( DEGREES DISTANCE OF MILCH ANIMALS i Scriba 1(b) 220' 3.0 miles None 16* 190* 5.2 40C 2 195* 8.0 ND 3 190* 4.5 2C 6(b) 62* 2.2 1C 26(b) 115* 1.6 None 61*** 140' 3.0 4G 62*** 183* 6.7 3G 63*** 185* 8.0 26C New Haven 8 130' 9.2 23C 9 95* 5.2 42C 4* 113' 7.8 78C 45 125' 8.0 16C 10(b) 130* 2.6 32C 5 146' 7.2 45C 11 130' 8.5 38C 7* 107' 5.5 62C 64*** 107* 7.9 45C Mexico 12 107* 11.5 68C 13 114* 11.2 2C 14 120* 9.8 62C 15 100* 10.8 34C 17 115' 10.2 44C 18 110* 10.0 50C 19 132* 10.5 40C 20 123* 11.2 None 60* 90* 9.5 40C 50* 95* 8.2 140C 55* 95* 9.0 53C '
21 112* 10.5 69C 49 88* 7.9 IG(2)
Richland 22 85* 10.2 42C l l
Pulaski 23 92* 10.5 81C Oswego 24 214' 8.8 None 61
TABLE 13 (Continued)
MILCH ANIMAL CENSUS 1986 NUMBER TOWN OR AREA (a)
NUMBER CENSUS MAPOF ( ) DEGREES DISTANCE OF MILCH ANIMALS l
Hannibal 40** 220* 15.2 30C 65***,** 220* 17.0 43C Volney 25 182* 9.5 None 70*** 147' 9.4 BC 66*** 158' 7.8 70C;1G(2) 67*** 152' 8.3 3G TOTALS: 1253 Cows (c) 10 Goats C = Cows G = Goats o = Milk sample location oo = Milk sample control location
- 00 = new location ND = Did not wish to participate in the survey (1) = References Figure 4 (2) = Coat is ng currently producing milk.
Nono= No cows or goats at that location. Location was a previous location with cows or goats.
(a) = Census performed out to a distance of approximately ten miles.
(b) = Location within three miles.
(c) = Number of cows within ten miles.
62
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M o o o be be be Ih3 M M M WH W W W W W W C C C aJ ** C C O dM U U U w w w E z x 63
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1
.~
i TABLE 15 1986 RESIDENCE CENSUS I MAP METEOROLOGICAL l LOCATION DESIGNATIONI ") SECTOR DEGREES DISTANCE i
N - - ;
l NNE - -
NE - -
f l -- ENE - -
I i
Lake Road A E 99* 1.3 miles i
Lake Road B ESE 102* 1.1 miles 1 1
County Route 29 C SE 130* 1.4 miles !
1
. Miner Road, D SSE 163* 1.6 miles-Miner Road E S 170* 1.6 miles Lakeview Road ~ F SSW 207* 1.2 miles Bible Camp. Retreat G SW 234' O.9 miles Bibl~e Camp Retreat H WSW -238' O.9 m11es.
- W - -
WNW - -
NW - -
NNW - -
- This meteorological sector is over Lake Ontario. There are no residences within three miles. l I"
See Figure 3,Section VII.
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DATA SUMMARIES AND CONCLUSIONS
1 V DATA SUMMARIES AND CONCLUSIONS The results of the 1986 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 this radiological data evaluation and interpretation. The interpretation of data can be made at several levels including trend analysis, population dose, risk estimates to the general population based on environmental concentrations, effectiveness of plant effluent controls and specific re-search areas, among others. An attempt has been made in this report not only to report the data collected during the 1986. 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 in-dication of its environmental significance. Evaluation of the impact of the radionuclides in terms of potential increased dose to man, in relation to natural background, is necessary.
There are four separats groups of radionuclides that were detected in the environment during 1986. A few of these radionuclides could possibly fall into three of the four groups. The first of these groups is naturally occurring radionuclides. It must be realized that the environment contains a broad inventory of naturally occurring radioactive elements. Background radiation as a function of primordial radioactive elements and cosmic ra-diation of solar origin offers a constant exposure to the environment and I man. These radionuclides, such as Th-228, Ra-226, Be-7 and especially
- l. K-40, account for a majority of the annual per capita background dose.
A second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's upper atmosphere.
The detonation frequency during the early 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on weapons testing in 1963 which 1 greatly reduced the inventory through the decay of short lived radio- :
nuclides, deposition, and the removal (by natural processes) of radio-nuclides from the food chain such as by the process of sedimentation.
Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China, in each case, the usual radionuclides associ-ated with nuclear detonations were detected several months afterwards and then after a peak detection period, diminished to a point where most could not be detected. The last such weapons test was conducted in October of 1980. 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 1981. 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 have a weapons test origin.
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 tnat the contribution from such nuclides in some cases (such as 1-131 and 70 l
- s Cs-137) is significant and second in intensity only to natural background
. radiation. Quantitles 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 orig!n of these radionuclides was a direct result of fallout from the Chernobyl accident.
The fourth group of radionuclides detected in the environment during 1986 were those that could be related to operations at the site. These select radionuclides were detected in a few of the sample medias collected and at very low concentrations. Many of these radionuclides are a by-product of nuclear detonations, the Chernobyl accident, and the operation of light water reactors thus making a distinction between the sources diffi-cult, if not impossible, under the circumstances. The dose to man as a result of these radionuclides is small and significantly less than the ra-diation exposure from naturally occurring sources of radiation and fallout from the Chernobyl accident.
Thus, a number of factors must be considered in the course of radio-logical data evaluation and 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 1986, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. It is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are very small and are not an indication of environmental significance. In regards to these very small quantities, it i will be further noted that at such minute concentrations the assessment of l the significance of detected radionuclides is very difficult. Therefore, concentrations in one sample that are two times the concentration of anoth-er, for example, are not significant overall. Moreover, concentrations at such low levels may show a particular radionuclides in one sample and yet not in another.
In Section V each sample medium is discussed. Concentrations of ra-dionuclides detected and exposure to man are presented and scrutinized.
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 scrutiny of past analytical data, a tool by which trends are discerned.
The interpretation of historical data in this report is done to a limited degree. Because of the constant change in analytical sensitivities, as state-of-the-art detection capabilities improve, data comparisons become difficult. For example, minimum detection capabilities for the 1969 analyses of environmental samples would be considered anomalous by 1986 stan-dards.
71
LAKE PROGRAM
' Tables .1 ' through 4 list the 1986 analytical results for the aquatic / lake water media sampled during the 1986 sampling program. Aquatic samples were obtained at four possible' onsite locations. The transect designations used for the onsite sampling locations are NMPW (01), NMPP (02), -JAF (03) .and- NMPE (04). Because of- the . unavailability. of various sample media,, onsite samples may be collected - from combinations ' of the above listed , locations, when required.. - Offsite samples were collected in' the vicinity of the Oswego Harbor' (offsite - 00) area. or further to the west (or east) and, therefore, served as control samples.
i 9
9
- l. 72
- 1. SHORELINE SEDIMENT - TABLE 1 Shoreline sediment samples were collected twice during 1986. Col-lections were made in April and October at one indicator location (Sunset Beach), and at one control location ( Lang's Beach). The results of these samples collected at the indicator and control lo-cations are presented in Table 1.
Several radionuclides were detected in sediment samples using gamma i spectral analysis. These radionuclides were all naturally occurring.
K-40 was detected at both the control location and indicator location.
The results ranged from 16.7 pCi/g (dry) to 19.1 pCl/g (dry) at the indicator location, and 7.3 pCi/g (dry) to 11.9 pCi/g (dry) at the control location. Th-228 and Ra-226 were detected only at the indica-tor location. The maximum detectable concentrations for Th-228 and Ra-226 were 1.19 pCl/g (dry) and 2.4 pCi/g (dry) respectively.
No other radionuclides were detected in shoreline sediment samples using gamma spectral analysis.
No dose to man assessment can be made due to the fact that no man-made radionuclides were detected in the 1986 shoreline sadiment sam-ples.
No historical data exists to compare the shoreline sediment indicator sample with previous results , since this Technical Specification location was just initiated in 1985. However, the 1985 shoreline sediment samples also showed measurable concentrations of naturally occurring radionuclides only.
73
l 1
- 2. FISH - TABLE 2 A total of 18 fish samples were collected in the spring season (June 1986) and in the fall season (October 1986). 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 Mlle Point Unit #1 (02), and the James A. 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 emitters.
Data is presented in the ANALYTICAL RESULTS section of the report on Table 2.
Analysis of the 1986 fish samples contained detectable concentrations of radionuclides related to past weapons testing and natural origins (naturally occurring). Small detectable concentrations
- of Cs-137 were found in all but one of the fish samples (including control samples) collected in 1986. Detectable concentrations of K-40, a naturally occurring radionuclides, were found in all fish samples collected for the 1986 program.
Spring fish collections were comprised of two separate species and nine individual samples. The two species represented one feeding type. Lake trout and brown trout are highly predacious and feed on significant quantitles of smaller fish such as smelt, alewife, and other smaller predacious species. Because of the limited availability of species present in the catches, no bottom feeder species were col-lected in the spring samples.
Cs-137 was detected in all onsite and offsite samples for both species collected. Onsite samples showed Cs-137 concentrations to be slightly less than control levels. The concentrations detected are not signifi-cantly different from the control results and are therefore considered background. Cs-137 in lake trout samples ranged from 0.020 to 0.030 i
pCi/g (wet) and averaged 0.024 pCi/g (wet) for the indicator sam-ples. Cs-137 in the control samples ranged from 0.027 to 0.032 pCl/g (wet) and averaged 0.030 pCi/g (wet) for lake trout. Cs-137 in brown trout samples ranged from 0.020 to 0.022 pCl/g (wet) and averaged 0.021 pCi/g (wet) for the indicator samples. Cs-137 in the control sample was 0.023 pCi/g (wet).
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 (lake trout and brown trout) ranged from 2.6 to 3.8 pCl/g (wet) and 2.6 to 3.1 pCl/g (wet) for the control samples. No other radio-nuclides were detected in any of the spring fish samples.
Fall sample collections were comprised of two separate species and nine individual samples. Six samples of lake trout and three samples of carp were collected at a combination of two onsite sample locations (NMP and JAF) and one offsite sample location (Oswego Harbor area).
Samples were collected by gill net in October.
74 l
Cs-137 was detected in all six of the indicator samples and two of the three control samples. The detected concentrations were not signifi-cantly different from one another because of the extremely small quan-titles detected. Cs-137 in lake trout samples ,at the indicator loca-tions ranged from 0.032to 0.051 pCl/g (wet) and averaged 0.041 pCi/g (wet). The lake trout samples from the control location had a Cs-137 concentration ranging from 0.021 to 0.022 pCi/g (wet), and a mean of 0.022 pCl/g (wet) . Cs-137 in the carp samples at the indicator locations ranged from 0.009 to 0.021 pCl/g (wet) and averaged 0.015 pCl/g (wet). The one carp sample from the control location had a Cs-137 concentration of less than 0.008 pCi/g (wet),
LLD. I K-40 was detected in all of the fall fish samples collected. Detectable concentrations of K-40 in the indicator samples ranged from 2.5 to 3.1 pCi/g (wet) and 3.1 to 3.6 pCl/g (wet) for the control samples. No I other radionuclides were detected in any of the fall fish samples. .
j The mean 1986 Cs-137 concentrations have decreased slightly from 1981 for the indicator samples and significantly from 1980 to 1976. 3' Concentrations for these samples decreased from a level of 1.4 pCl/g (wet) in 1976 to a level of 0.028 pCi/g (wet) in 1986. Control sample results have also decreased from a level of 0.12 pCl/g (wet) in 1976 to a level of 0.025 pCl/g (wet) in 1986. Results from 1979 to 1986 have remained fairly consistent. ,
l The general decreasing trend for Cs-137 is most probably a result of ecological cycling. A significant portion of Cs-137 detected since 1976 in fish is a result of weapons testing fallout, and the general down-ward trend in concentrations will continue as a function of ecological cycling and nuclear decay.
Lake Ontario fish are considered an important food source by many, therefore, fish is an integral part of the human food chain. Based on the importance of fish in the local diet, a reasonable estimate of dose to man can be calculated. Assuming that the adult consumes 21.0 kg of fish per year (Regulatory Guide 1.109, maximum exposed age group) and the fish ccnsumed contains an average Cs-137 concen-tration of 0.028 pCl/g (wet) (annual mean result of indicator samples for 1986), the whole body dose received would be 0.042 mrem per year. The critical organ in this case is the liver which would receive a calculated dose of 0.064 mrem per year. The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mlle Point area (Indicator samples).
Conservative whole body and critical organ doses can be calculated for the consumption of fish from the control location as well. In this case the consumption rate is assumed to remain the same (21.0 kg per year) but the average annual Cs-137 mean concentration for the con-trol samples is 0.025 pCi/g (wet). The calculated Cs-137 whole body dose is 0.037 mrem per year and the associated dose to the liver is 0.057 mrem per year.
75
In summary, the whole body ,, d .rltical organ doses observed as a result of consumption of fish is a 'll. Doses received from the con-sumption of indicator and contro, a mple fish are approximately the same with the dose from indicat<, samples being slightly higher.
Doses from both sample groups are considered in the range of back-ground exposure rates. I Graphs of past Cs-137 concentrations can be found in Section Vll.
l l
l l
l I
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- 3. SURFACE WATER - TABLES 3 AND 4 --
1 1986 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. ;
The analytical results for the 1986 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 surface water samples analyzed during 1986.
Gamma spectral analysis was performed on 24 monthly composite sam-pies (two locations) required by the RETS. Only two radionuclides were detected in samples from the two locations over the course of 1986. Both these radionuclides are naturally occurrine s and not plant
.related.
K-40 was detected intermittently in both Technical Specification re-quired intake canais. The James A. FitzPatrick inlet canal samples showed K-40 was detected in six of the 12 monthly samples and ranged from 12.5 to 154 pCi/ liter. K-40 in the Oswego Steam Sta-tion inlet canal was detected in six of the twelve samples and ranged from 13.6 to 221 pCi/ liter.
Ra-226 was also detected intermittently in both locations. Samples from the FitzPatrick location showed Ra-226 in seven of the twelve monthly samples and ranged from 11.5 to 151 pCi/ liter. The control sample location (Oswego Steam Station) showed Ra-226 in six of the twelve monthly samples and ranged in concentrations from 19.3 to 110 pCi/ liter.
Tritium samples are quarterly samples that were a composite of the appropriate monthly samples. Tritium was detected in samples taken at both locations. Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 260 pCi/ liter to 500 pCi/ liter and showed a mean concentration of 380 pCl/ liter. The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from 250 pCi/ liter to 550 pCl/ liter with a mean concentration of 373 pCl/ liter.
Review of past environmental data for Cs-137 from 1979 through 1986 shows that this radionuc!Ide 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 during 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 detected in the indicator inlet canal. The one result from the indientor location (JAF inlet canal) during 1982 was detected in a January composi+e sample and may have been a result ot~ inlet canal tempering (the 77
1 addition of discharge water to the inlet canal) or instrument background. Cs-137 was not detected during 1986 in surface water samples.
Other plant related radionuclides detected during a review period of 1979 - 1986 include only Co-60. The control sample location results
, showed that Co-60 was detected once in 1981 (the May composite l sample) . This result is suspect and, as noted above, may be the l result of contamination during handling or may be instrument back-I grouno. This result was 1.4 pCl/ liter. Results from the indicator location showed that Co-60 was detected three times during 1982 and averaged 1.9 pCi/ liter. These positive results were attributed to inlet canal tempering and instrument background. Co-60 was not detected during 1986 in surface water samples.
Review of previous environmental data for K-40 and Ra-226 showed that the detectable concentrations found during 1986 were representa-tive of concentrations found during 1979-1985.
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 1985 and showed a peak average value of 641 pCl/ liter (1982) and a miniinum value of 234 pCi/ liter (1979). The annual mean tritium result at the indicator location for 1986 was 380 pCi/ liter.
Mean tritium results of the control location (Oswego Steam Station) cannot be evaluated with regard to historical data since sampling was only initiated at this location in 1985. Some idea of the variability of 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 ac-ceptable control sample data for evaluation purposes.
Mean annual tritium results from previous city water samples from 1976 to 1984 show that the tritium concentrations have steadily de-creased. The maximum annual average was found in 1976 (652 pCi/ liter) and the minimum in 1982 (165 pCl/ liter). The 1986 annual mean tritium result from the Oswego Steam Station (373 pCl/ liter) was greater than results from the city water location for the last several years (1982 - 1985). The results ranged from 165 pCi/ liter to 288 pCl/ liter.
The impact, as expressed as a dose to man, cannot be evaluated because no plant related radionuclides were detected in surface water samples with the exception of tritium. Any impact associated with the ,
fluctuation of tritium levels are considered to be background and not l a result of operations at the site.
78
.___-_________-_a
I TERRESTRIAL PROGRAM Tables 5 through 14 represent the analytical results for the terrestrial samples collected for the 1986 reporting period.
79 l
- 1. AIR PARTICULATE GROSS BETA - TABLES 5 and 6 Tables 5 and 6 contain the results for the weekly air particulate gross beta analysis for a total of six offsite and nine onsite sample locations are required by the Technical Specifications (RETS). These sample locations are R-1, R-2, R-3, and R-4 (all located near the site boundary) and R-5 (located at a control location beyond any signifi-cant influence from the site). Data contained on Tables 5 and 6 also shows the results from other air sampling locations not required by the RETS. These locations are designated as D-1 onsite, D-2 onsite, E onsite, F onsite, G onsite, H onsite, I onsite, ) onsite, K onsite and G offsite locations. A total of 52 control samples from location R-5 and 207 indicator samples from locations R-1, R-2, R-3, and R-4 were collected and analyzed during 1986.
The samples are counted at a minimum of tw'enty-four hours after l collection to allow for the decay of naturally occurring radionuclides with short halfilves. The average yearly indicator concentration was 1 0.039 pCl/m 3. The average yeariy control concentration was also 0.039 pCi/m3 .
Review of air particulate gross beta results on a weekly basis shows that a significant increase occurred at all the environmental air moni-toring stations (including the control location) near the beginning of May. The maximum concentration for the indicator stations was 0.289 pCi/m3. The maximum concentration for the control location was 0.272 pCi/m 3. Gross beta concentrations for all the air monitoring stations returned to previous levels
- during the middle of June. As noted above, both the indicator and control stations showed ident! cal trends. Gross beta concentrations remained at the decreased levels for the balance of the year.
The observed increase in gross beta activity at all the environmental air monitoring stations is attributed to fallout from the Chernobyl accident which occurred on April 26, 1986.
The observed small fluctuations in general gross beta activity can be attributed to changes in the environment, especially seasonal changes.
The concentration of naturally occurring radionuclides in the lovrer limits of the atmosphere directly above land areas are affected by time related processes such as wind direction, srow cover, soll tempera-ture, and soil moisture content.
With the exception of 1986, the general trend in air particulate gross beta activity has been one of decreasing activity since 1974. The gross beta concentration at the control station has decreased from a level of 0.121 pCi/m3 in 1974 to 0.024 pCl/m3 in 1985. Results from the indicator stations ranged from 0.111 pCi/m3 in 1974 to 0.021 pCi/m3 in 1985. For both the indicator stations and control stations, the gross beta concentration during 1974 to 1982 fluctuated as a re-sult of fallout from the detonation of thermonuclear weapons. The annual mean results for the years 1983,1984, and 1985 from both the
- The mean concentration prior to the noted increase in May was 0.023 pCi/m 3 for both the indicator and control locations.
80
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indicater and control locations have been approximately similar and b ranged from 0.021 to 0.026 pCi/m3 . This appears to be a baseline range. The 1986 annual mean result was 0.039 pCi/m8 for both the indicator and control stations. This concentration is slightly higher than 1983-85 levels, and is attributed to fallout from the Chernobyl accident.
Graphic representations and historical data of air particulate gross beta activity are presented in Sections VI and Vll.
i 81
- 2. MONTHLY PARTICULATE COMPOSITES - TABLE 9 Weekly air particulate samples were composited by location to form '
monthly compnsite samples. The monthly composite sainples required by the Technical Specifications (RETS) include R-1, R-2, R-3, R-4, and R-5. Other sample locations not required by the Technical Spec-ifications include D-1 onsite D-2 onsite, E onsite, F onsite, G onsite, H onsite, I ons8te, J onsite, K onsite and G offsite locations. The results of all monthly composite samples are included on Table 9.
The results for samples analyzed durhig the 1986 sample program
) showed positive detections for Be-7, K-40, Ra-226, Th-228, N b-95 ,
Ru-103, Ru-106,1-131, Cs-134, Cs-137, and La-140. The total num-ber of radionuctioes detected was 11. Of the 11 detected , four are naturally occurring (Be-7, K-40, Ra-226, and Th-2 3). The remain-ing seven are considered to be directly related to fallout. The fallout is the result of the Chernobyl accident which occurred on April 26, 1986. Ru-103, Cs-134, and Cs-137 were detected at both indicator l and control locations only during the months of May and June.
1-131, N b-95, Ru-106, and La-140 we're only detected during the month of May. 1-131 was detected at both the indicater and control locations. Ru-106 was only detected at the D-1 onsite location (non-RETS location), Nb-95 was only detected at the E onsite location (non-RETS location), and La-140 was detected only at the F and G onsite locations (non-RETS locations). These radionuclides were not detected during any other month of 1986.
The results for the monthly composite samples showed positive de-tections for Be-7, K-40, Ra-226, and Th-228. These radionuclides, as noted above, are naturally occurring. Be-7 was detected in each of the monthly compodte samples from all locations. Be-7 ranged from 0.085 to 0.1P4 pCi/m3 for the indicator locations ( R-1, R-2, R-3, and R-4) . The control location results (R-5) showed Be-7 rang-ing from 0.091 to 0.167 pCi/m . K-40 was found intermittently in the 3
monthly composite samples ud rangted from 0.013 to 0.078 pCi/m 3 at 4
} the control location. The indicator location results f6r K-40 ranged from 0.010 to 0.071 pCl/m 3. Rs-726 w8s detected only once at the control )ocation st a concentration of 0.016 pC./m .2 The indicator ]
locations showed concentrations of Ra-226 ranging from 0.017 to 0.026 )
pC1/m2 . Th-228 was detected only at the E onsite location (non-RETS location ) . Th-228 was not detected at any of the ind:cator or control locations during 1986.
I Historically, the naturally occurring radionuclides Ra-226, K-40, and l Be-7 have shown fluctuations th' at are representative of natural chanq-ing conditions. No significant trends were noted during 1986.
l Ar.sassment of the presence of the Chernobyl related radionuclides in air particulate composite samples can be depicted by calculating doses to man as a result of inhalation. Using the average child inhalation rate of 3700 m3 /yr (308 m /3 standard month), the critical individual, and the mean concentration measured at both the indicator and control -
sataple stations , the following yearly doses can be calculated from l l Nuclear Regulatory Culde 1.109 methodology: )
I L
82 l l
l l
l INDICATOR NO. MONTHS DOSE
- i NUCLlDE CONCENTRATION DETECTED ORIGIN (mrem /yr)
Chernobyl Ru-103 0.020 pCl/m3 2 Fallout 0.0022 3 1-131 0.020 1 0.0270 Cs-134 0.009 "
2 "
0.0002 Cs-137 0.018 "
2 0.0003 TOTAL 0.0297 CONTROL NO MONTHS DOSE
- N_UCLIDE CONCENTRATION DETECTED ORIGIN (mrem /yr)
Chernobyl Ru-103 0,028 pCi/m3 2 Fallout 0.0031 1-131 0.023 1 0.0311 Cs-134 0.010 2 "
0.0002 i Cs-137 0.019 2 0.0003 TOTAL 0.0347 I
Dose to the lung, except for 1-131 which is dose to the thyroid.
The doses calculated from the radionuclides concentrations measured at the indicator and control locations are approximately- equal, with the control location results being slightly higher. These results illustrate that the dose to man as a result of the Chernobyl faliout is insignifi-cant when compared to the total lung dose to individuals residing in homes utilizing natural gas for cooking. A resultant total lung dose of 11 mrem per year has been calculated as a result of naturally occurring radon gas and radon gas decay products in the natural gas (NCRP Report No. 56).
A review of historical data shows that the presence of Co-60 has been noted in the past and can be a result of weapons testing, contamina-tion during handling, and operations at the site.
Co-60 average concentrations at the onsite or indicator and offsite or control locations from 1977 to 1978 decreased from approximately 0.0175 to 0.0015 pCi/m 3. Average concentrations decreased signifi-cantly during 1979 and increased in 1980 from approximately 0.0007 to I 0.0016 pCi/m3 respectively. 1981 and 1982 average Co-60 ;
i I
83 i
)
l l concentrations decreased to 0.0007 and 0.0005 pCi/m3 Average indi-l cator and control concentrations were approximately equal during 1977 I
to 1982. The 1983 indicator average Co-60 concentration was 0.0007 l pCl/m 3 or slightly greater than the 1982 concentration. The 1983 l average control and indicator mean C06- concentration was 0.0007 pCi/m3 which also was slightly greater than 1982 results. As noted previously, however, a portion of the Co-60 detected during 1983 was attributed to contamination during handling of the unused filters.
Co-60 during 1984 averaged 0.00079 pCi/m3 at the control stations and 0.00123 pCi/m3 at the indicator stations. However, the 1984 Co-60 positive results were a result of contamination during handling and not a result of operations at the site. The general reduction in previous indicator and control Co-60 concentrations (1981 - 1984) was a result of nuclear decay and ecological cycling of Co-60 in'itially produced by the 1980 Chinese weapons test. Co-60 was not detected during 1985-86 in air particulate samples.
Historically, Cs-137 has been variable during the past and has been present in air particulate samples since 1977 and prior to 1977. Dur-ing 1977, both onsite, or indicator, and offsite, or control, Cs-137 average concentrations are approximately equal and averaged 0.039 pC1/m3 Cs-137 average concentrations at indicator and control lo-cations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCi/m 3 respectively. Average , concentrations during 1980 and 1981 were !
approximately equal at control and indicator locations. Cs-137 during 1980 was approximately equal to 1979 and increased slightly in 1981 from 1979. The 1980 and 1981 average concentrations 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 concen-tration for the indicator and control composite samples were 0.0002 and 0.0002 pCl/m3 which was a reduction from 1982 results. Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite san.ples. As noted above for the average annual Co-60 results, the reduction in Cs-137 results is attributed to nuclear decay and ecological cycling of Cs-137 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 i the Chernobyl accident.
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.
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.
Graphic representations of air particulate composite Co-60 and Cs-137 concentrations are presented in Section Vll.
84 j
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- 3. AIRBORNE RADIOlODINE (1-131) - TABLES 7 AND 8 I
a During the 1986 air sampling program, airborne radiolodine was de-t tected in 25 of the 260 weekly samples collected at the five sampling stations required by the Technical Specifications (RETS). 1-131 was detected at both the indicator and control stations during May and June. The measurable concentrations of I-131 are attributed to fall-out from the Chernobyl accident and not operations at the site.
Observed detectable concentrations of I-131 ranged from 0.023 to 0.334 pCl/m3 for the indicator stations, and 0.041 to 0.332 pCi/m3 for the control station.
1-121 was also detected in 50 of the 515 weekly samples collected from the nine optional onsite sampling stations and the one optional offsite sampling station. The positive detections of I-131 were observed )
during the same weeks of May and June as noted above for the RETS l
required stations. These measurable concentrations of I-131 are also attributed to fallout from the Chernobyl accident. Observed detect-able concentrations of I-131 ranged from 0.011 to 0.360 pCi/m 3 for i
the ten optional onsite and offsite stations.
The impact of I-131 concentrations as a result of the Chernobyl j fallout can be assessed by projecting a maximum organ dose (thyroid) '
, and whole body dose to the critical individual. The critical individu-al, in this case, would be a child. Using standard Regulatory Guide 1.109 methodology and an inhalation rate of 3700 m2 per year, the thyroid and whole body doses were calculated.
The calculated doses due to the average 1-131 concentration from the indicator stations (0.119 pCl/m3) were 0.186 mrem /yr to the thyroid and 0.0003 mrom/yr to the whole body of the above mentioned critical
, - individual. The calculated doses due to the average 1-131 concen-tration from the control station (0.151 pCl/m ) 3were 0.236 mrem /yr to the thyroid and 0.0004 mrem /yr to the whole body. The calculated doses from the indicator stations and control station are very similar.
The resulting calculated whole body dose due to 1-131 concentrations is extremely small and can be compared to a similar dose from natural or background radiation that an individual could receive as a result
> of changing elevation. An individual residing ten meters (33 feet) higher in altitude for a period of 17.5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br /> would receive an addi-tional radiation dose of 0.0004 mrem which is equal to the total cal-culated dose to the whole body from environmental 1-131 concen-trations.
(
A review of historical data shows that 1-131 has been detected in the past at offsite stations. During 1976, the mean offsite 1-131 concen-tration averaged 0.604 pCi/m .3 1977 showed an 1-131 concentration that decreased to 0.323 pC1/m3 and for 1978, the concentration de-creased by a factor of ten to 0.032 pCl/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 0.639 pCl/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/m during 3 85
.a ;
t 1976 and 1977. The average concentration decreased to 0.041 pCl/m 3 .'
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 re- '
ductions in view of previous 1-131 concentrations. During 1983, the mean 1-131 concentration was 0.028 pCi/m 3 which represented a slight r -
increase compared to 1982. 1-131 in onsite and offsite samples was a ;
result of I-131 from weapons testing. A small portion of the concen- .
trations detected may have been a result of operations at the site.
The concentrations detected during 1983 at the onsite sample stations ~
were a result of operations at the site. 1-131 was not detected in '
t any of the 1984 or 1985 onsite samples. ,
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I 4 TLD (ENVIRONMENTAL DOSIMETRY) - TABLE 10 l
TLD's were collected once per quarter during the 1986 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 pv standard month. TLD's required by the Technical Specifications (RETS) in-clude two TLD's at each location with four independent readings per TLD or a tota! of eight readings. TLD results included on Table 10 ,
are comprised of TLD's requ! red by the RETS and special interest {
TLD's not required by the RETS. In 1986, '1"LD's were collected on approximately April 2,1986, July 1, 1986, September 29, 1986, and December 30, 1986. -
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 221 degree meteorological sectors), (4) special interest TLD's (in areas of high population density), and (5) control TLD's (in areas beyond any significant influence of the generating facilities ) . Specini interest TLL 3re located at or near large industrial sites, schools, or proxh .. town or communities. Control TLD's are located to the southwest, south, and east-northeast of the site at distances of 12.8 to 19.8 miles from the site.
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 onsite. air sampling stations. TLD's located at the air sampling sta- '
tions include numbers 3, 4, 5, 6, 7, 23, 24, 25, and 26. The results for TLD's are consistent with previous years results and are in agreement with control TLD results. TLD #3 is located in the vicinity of Nine Mile Point Unit 2 and is between the Unit 1 facility and Fitz-Patrick. The results for TLD #3 were approximately double the re-suits of the other TLD's because of the effects from Unit 1 and Fitz-Patr!ck as well as any oossible rad.iography work at Unit 2. A gen-eral increase in TLD results was noted for the second and third quer-ter results. A similar trena was noted for the control TLD's. This general increase was most probably due to changing natural conditions and fallout from the Chernobyi accident.
Other onsite TLD's include special interest TLD's located near the north shoreline of the Unit t and FitzPatrick facilities but in close proximity to radwaste facilities and the Unit 1 reactor building.
These TLD's include numbers 27, 28, 29, 30. 31, 39, and 47, Re-suits for these TLD's during 1986 were variable and ranged from 8.5 to 59.9 mrem per standard month as a result of activities at the rad-waste fac!!ities and the operating modes of the generating facilities.
Results for 1986 were within the ranges of variability noted in previ-ous years for TLD's at or near these locations. TLD's in this group ranged up to approximately ten times control TLD results.
Additional onsite TLD's are located near the onsite Energy Information Center and the environmental laboratory. These TLD's include num-bcrs 18, 103, and 59. TLD number 103 results were consistent with 87
1 control TLD results and ranged from 6.0 to 8.7 mrem pcr standard month. TLD number 18 recults during 1986 were fairly consistent with previous years and ranged from 5.8 to 7.2 mrem per standard tronth. TLD nunber 59 was deleted after the first quarter of 1986.
Results for the first quarter (7.7 mrem) were si;ghtly above control TLD results. The proximity of this TLD to the FitzPatrick stack and reactor building account & this slight increase in results.
Site boundary TLD's are located in the approximate area of the site boundary, one in each of the sixteen 221 degree meteorological sec-tors. These TLD's include numbers 75, 76, 77, 23, 78, 79, 80, 81, d2, 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 4.4 to 7.5 mrem per standard morith, i TLD numbers 75, 76, 77, 23, 85, S6 and 87 showed results that rang-ed up to twice the results of Control TLD's. These results ranged from 5.4 to 18.7 mrem per standard month. This latter group of TLD's are located near the Lake shoreline (approximately 100 feet from the shoreline) but are also located in close proximity of the Reactor Building and Radwaste facilities of Nine Mile Point Unit 1 and the radwaste facilities cf 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 occupied by members of the public (excluding TLD's t' ear the generating facilities and facing Lake Ontario) are compared to control TLD results. The site 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 third and fourth quarters in mrem per standard month are as follows.
Quarter Net Site Property Boundary Dose
- 1 -0.2 l 2 -0.2 3 -0.4 4 -0.8
- Dose in mrem per standard month.
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 public may be located. These areas are near the north shoreline which are in close proximity to the generating facilities and are not accessible to members of the public.
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 22i degree meteorological sectors. 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 1986 iluctuated slight ly as a result of changing naturally occurring conditions and fallout from the Chernobyl accident. These TLD's included numbers 88, 89, 90, 91, 88
92, 93, 94 and 95. Results fluctuated from 4.1 to 8.6 mrem per standard month. Results during 1986 can only be compared to 1985 yearly results since this group of TLD's was established in 1985.
The 1986 results were slightly higher than 1985 TLD results which is most probably due to fallout from the Chernobyl accident.
The fourth group of environmental TLD's are those TLD's located be-yond the site boundary and at special interest areas such as indus- ,
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 ranged from 4.6 to 8.9 mrem per standard month. All the TLD results from this group were within the variation noted for the Control TLD's. Results during 1986 for TLD's established during previous years were censistent with results noted for those years. j The fifth group of TLD's include those TLD's considered as Control T LD's . These TLD's include numbers 8, 14, and 49. Results for j 1986 ranged from 5.5 to 7.6 mrem per standard month. Results from 1986 were consistent with previous years results. A slight increase was noted in the second and third quarters of 1986. This trend was also noted in the other groups of TLD's evaluated during 1986. ]
Review of past TLD results required by the Technical Specifications (RETS) show that TLD's can be separated into four groups. These groups include site boundary TLD's in each meteorological sector (16 TLD's total), TLD's located offsite in each land based sector at a distance of 4 -5 miles (8 TLD's total), TLD's located at special interest areas (6 TLD's total) and TLD's located at control locations (2 TLD's total). As noted previously, since the present RETS became effective in 1985, these.TLD's for the most part, can only be evaluated for 1985 and 1986.
TLD's located at tne site boundary ranged from 4.1 - 12.6 mrem per standard month and averaged 6.1 mrem per standard month during 1985. During 1986, site boundary TLD's ranged from 4.4 - 18.7 mrem per standard month and averaged 7.0 mrem per standard month.
As noted previously, this group of TLD's can fluctuate because several of these TLD's are located in close proximity to the generat-ing facilities. An increase was noted during 1986, although such an increase was noted for all TLD's including control TLD's.
TLD's located offsite at a distance of 4 - 5 miles from the site in each of the land based meteorological sectors ranged from 4.0 - 7.1 mrem per standard month and averaged 5.0 mrem. During 1986, offsite sector TLD's ranged from 4.6 - 8.6 mrem per standard month and averaged 6.0 mrem per standard month. 1986 results also demon-strated an increase for this group of TLD's.
Special interest TLD's are located at areas of high population density, such as major work sites, communities, schools, etc. and residences near the site (critical receptor areas). This group of TLD's ranged from 3.9 - 6.8 mrem per standard month and averaged 5.3 mrem per standard month during 1985. During 1986, this same group of TLD's 89
1 ranged from 4.8 - 8.2 mrem per standard month and averaged 6.1 mrem. The 1986 results showed a slight increase when compared to the 1985 results.
The final group of TLD's required by the RETS is the control group.
This group utilizes two TLD locations well beyond the site. Results from 1985 ranged from 4.4 - 6.8 mrem per standard month and av-eraged 5.4 mrem. During 1986, this same group of TLD's ranged from 5.5 - 7.2 mrem per standard month and averaged 6.3 mrem per standard month.
During 1986, all TLD groups required by the RETS showed an in-crease. The average percentage increase for all groups ranged from 13% to 20%. The site boundary TLD's showed the smallest increase (13%). The offsite TLD's, located 4 - 5 miles from the site, showed the greatest increase (20%). The control TLD's showed a 17% increase from 1985 to 1986. Increases since ' 1985 are a result of conditions l other than those associated with activities as the site.
Overall, TLD results for 1986 showed no significant impact from direct radiation measured outside the site boundary.
l 90
- 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 1986. The RETS require that three locations be sampled for milk within 5.0 miles of the site. During 1986, there were no milk sample locations within 5.0 miles of the site.
The locations that were sampled during 1986 are located from 5.5 to 9.5. miles from the site. The only sample location required by the RiTI $ during 1986 was the control location. Location #40 was the control. m.lk sample location for milk samples collected from April thcough the first half of August,1986. Milk sample location #40 sold their dairy herd on August 15, 1986, therefore, milk sampling was discontinued at this location. A new milk sample control location (location #65) was then added. Control milk samples were collected from location tG5 for the recond half of August through December, 1986. Sample location descriptions for all milk sample locations utilized during 1986 are !!sted below.
Location No. sirection from Site Distance from Site (miles) 7 ESE 5.5 16 S 5.9 50 E 8.2 55 E 9.0 60 E 9.5 4 ESE 7.8 40 (Control) SW 15.2 65 (Control) SW 17.0 During 1986, milk samples were collected at each ef the six indicator locations and the control location in the first half and the second half of esch month. Samples were collected during the months of April thraugh December 1986. Since 1-131 was not detected during Novem-ber and December of 1985, no additional samples were collected in January through March of 1986. For each sample, analyses were per'ormed for gamma emitters (analysis by Gell detector) and 1-131 using a resin extraction. Sample analysis results for gamma emitters are found on Table 12 and for 1-131 on Table 11.
The gamma spectral analysis of the bimonthly samples showed K-40 to be the most abundant radionuclides detected in the milk samples col-facted during 1986. K-40 was detected in every sample analyzed and ranged !n concentration from 1,030 pCi/ liter to 1,570 pCi/ liter at the l
indicator locations and 948 pCilliter to 1,450 pCi/ liter at the control location. K-40 is a naturally occurring radionuclides and is found in many of the environmental media sampled.
Cs-137 was detected in 3 of the 18 control milk samples and 12 of the 108 indicator milk samples collected during 1986. The Cs-137 concen-tration measured at the control location ranged from 5.3 pCl/ liter to 12.4 pCi/ liter. The Cs-137 concentration measured at the indicator locations ranged from 6.1 pCl/ liter to 11.1 pCi/ liter. The mean annual results for the detection of Cs-137 at all tocations are present-ed below:
91
l Location Number Mean Annual Cs-137 Results 4 None Detected 7 8.7 pCl/ liter 16 6.6 pCl/ liter 40 (control) ! .9 pCilliter 50 E.5 pCl/ liter 55 7.1 pCl/ liter 60 10.3 pCi/ liter 65 (control) 5.3 pCi/ liter Cs-137 was detected at the milk sample locations only during the consecutive months of May, June, July, August, and September. The presence of Cs-137 detected in milk samples (including control sam-ples) during 1986 is attributed to the Chernobyl accident and not operations at the site.
The impact as a result of Cs-137 in 1986 milk samples can be assessed by calculating conservative doses to man from the consumption of milk with detectable quantitles of Cs-137. For the r,urposes of a calculat-ed dose, the 1986 mean indicator sample Cs-137 concentration is used (8.6 pCi/ liter).
Assuming a consumption rate of 330 liters (87.18 gallons) per year for an. Infant (Regulatory Guide 1.109 maximum exposed Individual), the whole body dose would be 0.051 mrem and the critical organ dose '
would be 0.722 mrem to the liver. The calculated doses are based on 5 months of consumption (5 months of detectable Cs-137 sample re-suits ) . For comparative purposes, the calculated dose to an infant as ,
a result of consuming milk from the control location during 1980 would
- be 0.050 mrem whole body dose and 0.706 mrem critical organ dose
(dose to the ilver). The annual mean Cs-137 concentration for the f 1986 control location was 8.4 pCi/ liter. 6 I
The calculated dose to an adult can also be determined assuming a consumption rate of 110 liters (29.06 gallor.s) per year (Regulatory 4 Guide 1.109) and a mean Cs-137 concentration of 8.6 pCl/ liter for the indicator locations. The resultant doses are 0.028 mrem to the whole body and 0.043 mrem to the liver (critical organ). The calculated doses are based on 5 months of consumption. The calculated whole body and liver doses from the mean Cs-137 concentration at the control location (8.4 pCi/ liter-) would be 0.027 mrem and 0.042 mrem respectively.
The total calculated doses from Cs-137 measured at both the control and indicator milk sample locations are essentially equal, and as noted above due to fallout from the Chernobyl accident.
Fr the purpose of illustration, the significance of the above doses can be brought into perspective by a comparicon to the U. S.
Department of Health and Human Services (US/DHHS) Guide for Cs-137 Ingestion. The EFA/ PAC 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 92
respectively. The total calculated doses as a result of the fallout from the Chernobyl accident are very small by comparison.
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, however, at a concentration of 5.1 pCl/ liter (detected only once). This observation may indicate that the source of the Cs-137 during the years of 1981-1983 was the October 1980 Chinese Weapons Test. The source of the Cs-137 measured at both the indicator and control milk sample lo-cations during 1986 was a result of fallout from the Chernobyl acci-dent.
Milk samples were also collected (April - December, 1986) and an-alyzed twice per month for 1-131. 1-131 was detected in 3 of the 18 control milk samples and 17 of the 108 indicator milk samples collected during 1986. The 1-131 concentration measured at the control location ranged from 0.8 pCi/ liter to 29.0 pCl/ liter and averaged 13.6 pCi/ liter. The 1-131 concentration measured at the indicator locations ranged from 0.3 pCi/ liter to 30.0 pCi/ liter with a mean concentration of 5.2 pCl/ liter.
1-131 was detected at all the milk sample locations (including the control location) during the months of May and June. The presence of I-131 in milk samples (including control samples) during 1986 is attributed to fallout from the Chernobyl accident.
The impact as a result of I-131 in 1986 milk samples can be assessed by calculating conservative doses to man from the consumption of milk with detectable quantitles of I-131. For the purposes of a calculated dose, the 1986 mean indicator sample 1-131 concentration is used (5.2 pCi/ liter).
Assuming a consumption rate of 330 liters (87.18 gallons) per year for an infant (Regulatory Guide 1.109 maximum exposed individual), the whole body dose would be 0.005 mrem and the critical organ dose would be 3.98 mrem to the thyroid. The ca!culated doses are based on 2 months of consumption (2 months of detectable I-131 sample results) . For comparative purposes, the calculated dose to an infant as a result of consuming milk from the control location during 1986 would be 0.014 mrem whole body dose and 10.4 mrem critical organ dose (dose to the thyroid). The annual mean 1-131 concentration for the 1986 control location was 13.6 pCl/litet.
The calculated dose to an adult can also be determined assuming a consumption rate of 110 I!ters (29.06 gallons) per year (Reoulatory Guide 1.109) and a mean 1-131 concentration of 5.2 pC1/ liter for the indicator locations. The resultant doses are 0.000? mrem to the whole body and 0.19 mrem to the thyrofd (critical organ). The calculated j doses are based on 2 months of consumption. The calculated whole j body and thyroid doses from the mean 1-131 concentration at the J control location (13.6 pCl/ liter) would be 0.0008 mrem and 0.49 mrem i respectively. j 93 l
1
- - - - - - - - - - - - - - - - - - - - - - _ - - - - - - - _ _ _ _ .l
For the purpose of illustration, the significance of the above doses can be brought into perspective by a comparison to the US/DHHS guide for 1-131 ingestion. The EPA / PAG maximum limit for 1-131 ingestion is 15,000 pCl. The resultant whole body and thyroid doses to the maximum exposed individual (infant) would be 0.28 mrem and 208.5 mrem respectively. The total calculated doses as a result of the fallout from the Chernobyl accident are very small by comparison.
f No other radionuclides were detected in milk samples using gamma l spectral analysis or resin extraction.
A review of past historical 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 milk samples only in conjunction with fresh fallout from atmospheric testing.
Historical data and graphic representations of milk sample results for
' Cs-137 and 1-131 are presented in Sections VI and Vll.
)
i 1
l
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94
- 6. LAND USE CENSUS - TABLES 13 AND 15 A land use census was conducted during 1986 to identify within a 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 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 Mile Point Site. A census is conducted once per year in the spring. The census is conducted 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 animalr., located within the ten mile radius of the site was estimated to be 1,253 cows and ten (10) goats for the spring 1986 census. Eight (8) new locations with milk animals were found since the 1985 census. The number of cows increased by 95 and the number of goats by 9 with respect to the 1985 census.
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 sectors include: N, NNE, NE, ENE, W, WNW, NW and NNW. There are no residences in these sectors. The results of the 1986 residence census showing the applicable sectors, degrees and distance of each of the nearest residences are found on Table 15.
95
I i
i
- 7. FOOD PRODUCTS - TABLE 14 Food product samples collected during 1986 were comprised of garden j vegetables and fruit. Samples were collected from six indicator i locations and one control location. The indicator locations were j represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and all site release points at operating facilities. The control location was represented by a garden location 9-20 miles distant in a least prevalent wind direction. Carden vegetables were comprised of cabbage, beet greens, collard greens, squash leaves, grape leaves, and swiss chard which are all considered broadleaf vegetables. Where broadleaf vegetables were not available, non-broadleaf fruits or vegetables were collected. Non-broadleaf fruits or vegetables collected in 1986 con-sisted 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 end fruits. Broadleaf vegetables (Swiss chard, collard greens, squash leaves, grape leaves, beet greens and cabbage) showed concentrations of X-40 ranging from 1.29 pCi/g to 6.70 pCl/g (wet). Non-broadleaf fruits (tomatoes) showed concentrations of K-40 ranging from 1.57 pCl/g to 2.51 pCi/g (wet). Be-7 was detected in some of the broad-leaf vegetables, but was not detected in any of the non-broadleaf fruits (tomatoes). The Be-7 concentrations in the broadleaf vegeta-bles ranged from 0.30 pCl/g (wet) to 1.93 pC /g (wet).
No other radionucildes were detected in the 1986 collection of fruits and vegetables.
Review of past environmental data indicates that K-40 has been con-sistently detected in food crop samples. K-40 concentrations have fluctuated from one sample to another but the annual ranges have re-mained relatively consistent from year to year. Be-7 has been de-tected occasionally during the past on leafy vegetables (1978 through 1982, and 1984).
Cs-137 has been detected intermittently during the years of 1976-1986 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 1976-1986 showed that Cs-137 was not detected during 1976-1978, 1981-1984 and 1986.
During 1979 and 1980, Cs-137 in fruits and/or vegetables showed annual mean concentrations of 0.004 and 0.036 pCi/g (wet) respec-tively. 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 pCi/g (wet). Cs-137 detected during the past at both indicator and control locations is indicative of weapons testing.
The impact as a result of Cs-137 in 1986 fruit and vegetable samples is insignificant since no Cs-137 was detected during the 1986 fruit and vegetable sampling program.
96
1
- 8. SITE BOUNDARY VEGETATION - TABLE 14 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 l D/O (deposition factor) for a total of six sartples. The control location was represented by samples of three similar broad-leaf vari- {
eties grown 9-20 miles distant in a least prevalent wind direction.
The three broad-leaf varieties were comprised of wild grape leaves, 1
J viburnum, and goldenrod (all non-edible), The site boundary and ]
control vegetation samples were collected during the late summer l harvest season. l W
Two naturally occurring radionuclides (K-40 and Be-7) were detected '
in the 1986 samples. K-40 was detected in all the broad-leaf vege-tation samples collected in August, 1986. The site boundary vege-tation samples (indicators) showed concentrations of K-40 ranging from 2.23 pCl/g (wet) to 9.80 pCl/g (wet) . The control samples showed concentrations of K-40 ranging from 3.99 pCi/g (wet) to 8.33 pCi/g (wet).
Be-7 was also detected in all the broad-leaf vegetation samples. The site boundary samples (indicators) showed concentrations of Be-7 ranging from 0.76 pCi/g (wet) to 3.03 pCi/g ( wet) . The control samples showed concentrations of Be-7 ranging from 0.90 pCl/g (wet) to 2.70 pCi/g (wet). Both Be-7 and K-40 are naturally occurring radionuclides.
Cs-137 was detected in four of the six ir.dicator vegetation samples (viburnum and goldenrod). The Cs-137 concentrations ranged from 0.031 pCi/g (wet) to 0.035 pCi/g (wet), with a mean Cs-137 concen-tration of 0.033 pCi/g (wet). Cs-137 was detected in only one of the three control vegetation samples at a concentration of 0.035 pCi/g (wet) .
The presence of Cs-137 in site boundary vegetation samples can be attributed to several sources; atmospheric nuclear testing, fallout from the Chernobyl accident, and/or operations at the site. The presence of Cs-137 in the control vegetation samples indicates that the source may be past weapons testing or fallout from the Chernobyl accident.
Site boundary vegetation sampling was initiated in 1985. As a com-parison , the mean 1985 Cs-137 concentration in the indicator vege-tation samples was 0.162 pCi/g (wet). Cs-137 was not detected in the control vegetation samples during 1985.
No other radionuclides were detected in the 1986 RETS vegetation samples.
The vegetation samples collected during 1986 at the site boundary are not consumed by humans. Because this vegetation is not considered edible there is no dose to man from the presence of Cs-137.
I 97 )
A more realistic dose to man concept was evaluated in the previous section (Section V.7, fruits and vegetables). The dose assessment from the consumption of fruits and vegetables from nearby gardens (within 3 miles of the site) was demonstrated to be insignificant.
l 98
4
- 9. ENVIRONMENTAL SAMPLE LOCATIONS - TABLE 16 Table 16 contains the locations of the environmental samples presented '
in the data tables of Section IV. The locations are give in degrees and distance in miles from the Nine Mile 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.
l 99 1
__ _ ___ o
- 10. INTERLABORATORY COMPARISON PROGRAM - SECTION Vill 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 part 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 form. Some of the EPA reference samples have 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.
.I 1
l l 100
J CONCLUSION l 1
The Radiological Environmental Monitoring Program is conducted each year )
to determine the radiological impact of the James A. FitzPatrick Nuclear I Power Plant on the local environment. As demonstrated by the analytical results of the 1986 program, the major radiological impact on the environ-ment was the result of fallout from atmospheric nuclear testing and the Chernobyl accident.
Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the general environment or to man. In addition, the data was reviewed for any possible historical trophic level bioaccumulation trends. Little or no impact could be determined resulting from radionuclides deposition consider-ing all sources (natural, weapons testing, Chernobyl, etc.). In regard to doses as a result of man-mad radionuclides, a significant portion of the small doses received by a member of the public was from past nuclear weapons testing and fallout from the Chernobyl accident. 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 impact from natural background levels, weapons testing, or fallout from the Chernobyl accident. 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 soil and lower atmosphere) in Oswego Cotnty account for approximately 76 mrem per year, as demonstrated by control environmental TLD's. Possible doses due to site operations are a minute fraction of this particular natural 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 fe am the operation of the James A. FitzPatrick Nuclear Power Plant.
i 101 !
EXCEPTIONS TO THE PROGRAM
- 1. The air sampilng pump at the R2 offsite environmental sampling station was inoperable from January 7, 1986 (1815 hours0.021 days <br />0.504 hours <br />0.003 weeks <br />6.906075e-4 months <br />) to January 14, 1986 (0848 hours0.00981 days <br />0.236 hours <br />0.0014 weeks <br />3.22664e-4 months <br />). Inoperability was caused by an electrical malfunction.
- 2. The air sampling pump at the R3 offsite environmental sampling station was inoperable from May 14, 1986 (1545 hours0.0179 days <br />0.429 hours <br />0.00255 weeks <br />5.878725e-4 months <br />) to May 20, 1986 (0835 hours0.00966 days <br />0.232 hours <br />0.00138 weeks <br />3.177175e-4 months <br />). Inoperability was caused by an electrical malfunc-tion.
- 3. Environmental TLD #80 (Offsite Dose Calculation Manual TLD #12) was missing during the second quarte; of 1986 as a result of theft. Data was not available for this location from April 2,1986 through July 1, 1986.
- 4. Environmental TLD #77 (Offsite Dose Calculation Manual TLD #8) was missing during the third quarter of 1986 as a result of theft. Data was not available for this location from July 1, 1986 through October 1, 1986, t
- 5. A review of the 1986 results showed that one EPA sample, which was scheduled during December, was not received. This sample was a water sample spiked with I-131. Since this sample was not received, it could not be analyzed, and the data are not included in Section Vill (EPA Interlaboratory Comparison Program Results). A subse-quent investigation of the missing spiked sample showed that the sample was never sent by the EPA to the program participants.
102
_ _ _ _ _ = _ = _ _ - _
REFERENCES
- 1. U.S. Nuclar Regulatory Commission Regulatory Guide 1.109, " Cal-culation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", March,1976.
- 2. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, " Cal-culation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", October,1977.
- 3. Eichholz, G., Environmental Aspects of Nuclear Power, First Edition, Ann Arbor Science Publishers, Inc. , Ann Arbor, Michigan,1976.
- 4. National Council on Radiation Protection and Measurements (NCRP),
Environmental Radiation Measurements, NCRP Report No. 50, 1976.
- 5. National Council on Radiation Protection and Measurements (!!CRP),
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 B ranch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program", November,1979.
- 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.
l 12. National Council on Radiation Protection and Measurements (NCRP),
Exposure from Consumer Products and Miscellaneous Radiation Sources, NCRP Report No. 56, 1977.
- 13. Pochin, Edward E., Estimated Population Exposure from Nuclear Power Production and Other Radiation Sources, Organization for Economic Co-operation and Development,1976.
103
- 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 Response in Radiation Accidents, National Center for Devices and Radiological Health, Rockville, MD 20857, August,1983.
h n
P 104
VI
/ 'N k y s
j HISTORICAL DATA
(
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, REOPERATION SURVEY, 1969 and ENVIRONMENTAL MONITORING REPORT FOR NI AGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.
- 2. Sample data listed as 1976, 1977, 1978, 1979, 1980, 1981, 1982, 1983, 1984, and 1985 vtas taken from the respective environmental operat-ing reports for Nine Mile Point Nuclear Station and James A. Fitz-Patrick Nuclear PoWr Plant.
- 3. Only measured values were used for statistical calculations. ,
1 9
105
HISTORICAL ENVIRONMENTAL SAMPLE DATR CONTROL MEAN
^ ^ MAXIMUM RAM C 3 1/g (wet) DEV AT ON MINIMUM 1986 0.025 0.004 0.032 0.021 0.0 1985 0.034 0.008 0.047 0.026 0.0:
1984 0.032 0.009 0.038 0.015 0.0:
1983 0.050 0.009 0.060 0.040 0. 0; s
1982 0.047 0.009 0.055 0.027 0. 0:
1981 0.043 0.016 0.062 0.038 0. 0:
1980 0.059 0.032 0.110 0.029 0.]
1979 0.04 0.01 0.06 0.03 0.0:
,c 1978 0.09 0.05 0.20 0.04 0.1 <
1977 0.13 ONLY ONE DATA POIl 1976 0.12 ONLY ONE DATA POI:
1969 (PRE-OPERATIONL) NO DATA ---- ---- ---- ---<
INDICATOR Fish Eamples MEAN STANDARD MAXIMUM MINIMUM RANC cm_117 nct/7 (wei DEVIATION 1000 0.028 0.012 0.051 0.000 0. n; 1985 0.030 0.009 0.045 0.018 0. 0' 1004 0.043 0.008 0.061 0.033 0. 0:
1983 0.050 0.009 0.060 0.n30 0. 0' 1982 0.050 0,008 0.064 0.0?4 0. 0:
1981 0.061 0.021 0.10 0.027. 0. 0:
1980 0.061 0.029 0.100 0.030 _
- 0. 0:
1979 0.10 0.14 0.55 0.02 0. C 1978 0.08 0.02 0.10 0.03 0. o' 1977 0.29 0.21 0.79 0.13 0 . 66 1976 3,3 ,,47 3,9g g sg tg 1969 (PRE-OPERATIONL) 0.06 0.04 0.!3 0.01 o 1-106
l
~
l HISTORICAL ENVIRONMENTAL SAMPLE DATA j 1
CONTROL
- ^ ^ MAXIMUM RANGE l h*1 pci/1 MEAN DEV AT ON MINIMUM 1986 373.0 157.0 550 250 300 ;
i 1985 287.5 95.4 430 23 200 1984 205 21.2 220 190 30 1903 250.0 21.8 280 230 50 1982 165.0 94.7 307 112 195 1981 293.3 49.3 357 211 146 1980 257.3 38.5 290 211 79 1979 258.7 73.7 308 174 134 1978 303.8 127.5 490 215 275 1977 407.5 97.4 530 300 230 1976 651.7 251.0 929 440 489 1969 (PRE-OPERATIONL) <MDL --- --- --- ---
INDICATOR ,.
Lake Water MEAN STANDARD MAXIMUM MINIMUM RANGE J yiefum oc!/1 DEVIATION 1986 380.0 118.0 500 260 250 1985 530.0 448.6 1200 250 950 282 98.1 370 110 260 198f 1983 317.0 116.9 Sp0 190 370 1982 641.0 891.1 27,80 194 2586 1981 258.3 76.9 388 182 205 _
1980 263.0 95.4 45L _ 150 307 1979 234.0 40.- 286 !76 110 1978 389.4 119.9 560 253 307 ,- .
1977 450.0 67.7 530 380 150 1976 513.0 250.3 RM 207 SM 1969 (PRE-OPER ATiONL) 440.0 84.9 500 1F0 I"o 1 107 l
L. ,
HISTORICAL ENVIRONMENTAL SAMPLE DATA -
CONTROL Air Particulate STANDARD RANG [
Gross Seta pCi/m s MEAf4 MAXIMUM MINIMUM DEVIATIOf4 I- 1986 0.039~ 0.049 0.272 0 008 0.264 1985 0.024 0.006 0.043 0.013 0.030 c: 1984 0.026 0.007 0.031 0.013 0.039
..e_.- e
. 1983 0.024 0.009 0.085 0.007 0.078' 1962 0.033 0.012 0.078 0.011 0.067' W.
1981 0.165 0.135 0.549 0.016 0.533 1980 0.056 0.04 0.291 0.009 0.282-1979 0.077 0.086 0.703 0.010 0.693-1978 0.14 0.13 0.66 0.01 0.650.
a 1977 0.07 0.03 0.140 0.016 0.124.
1976 0.051 0.031 0.,240 0.004 0.236 1969 (PRE-OPERATIONL) 0.334 0.097 0.540 0.130 0.410 INDICATOR e
.. Air Particulate MEAN STANDARD MAXIMUM MINIMUM RANG @
Gross Beta oCf/m3 DEVIATION 1986 0.039 0.050 0.289 0.007 0.282 1985 0.021 0.006 0.044 0.001 0.0 3_
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 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 0.2 71 0.001 0.270 r- 1978 0,to o,og o,34 g,og o,33 o
,, . J 1977 0.106 0.07 0.326 0.002 0.32i
,7 l970 0.007 0.032 0.191 0.002 n.Ino
<s. , _
, , ,, 1969 (PRE-OPERATIONL) 0.320 0.090 0.520 0.130 r 3M
. 108
.tJ
HISTORICAL ENVIRONMENTAL SAMPLE DATA _
CONTROL Environ. ILD's Quarterly Reading STANDARD mremistandard Month Offsite* MEAN DEVIATION A INIMUM RAME 1986 6.40 0.68 7.60 5.50 2.10 1985 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 1981 4.72 0.685 6.63 3.24 3.39 1980 4.57 0.614 6.06 3.12 2.94 1979 REPORTED S MREM /QTR PRIOR TO 1980 1978 1977 1976 1969 (PRE-OPEPATIONL)
INDICA TOR Environ. r a's Quarterly Reading STANDARD . M AXIMUM MEAN MINIMUM RANGE I mrem / standard Moirth onsite Monitc rs* DEVIATION 1986 6.53 1.93 18.70 4.10 14.60 108.5 5.65 0.79 7.35 4.45 2.90 1984 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 DATA NOT COMPARABLE DUE TO CHANGES 1979 IN TLD LOCATIONS 1978 1977 1976 1969 (PRE-OPERATIONL) 7 See Clarification on Environmental g pie Statistical Analysis Table. Section III.
l i
HISTORICAL ENVIRONMENTAL SAMPLE DATA l CONTROL
.u1 A campAee, Cs-137 pCi/1 MEAN
^ ^
DEV AT ON MAXIMUM MINIMUM RANGE:
1986 8.4 3.o 12.4 5.3 7.1 !
mD --- --- ---
1985 ---l
<LLD --- --- --- -- .
1984 1983 " ~~~ ~~- -~~ ---
1982 * --- --- ---
---l
- 7. Om ONE DATA F0 W 1981
-~~ ~~~ --- ~- '
1980 3.73 0.29 3.9 3.4 v.a g7g 5.63 1.96 e.d 4.* a.*
g7g 1977 g7g nu u w --- --- ---
1969 (PRE-OPERATIONL) i INDICATOR Milk Samples STANDARD Cs-137 pC1/1 MEAN MAXIMUM MINIMUM RANGE DEVIATION 1986 8.6 1.7 11.1 6.1 5.0 1985 <LLL --- --- --- ---4 1984 <LLD --- --- --- ---
1983 5.10 ONLY ONE DATA POINT 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 n-.3 1979 9.4 8.0 40.0 2.7 37.,3 i 1978 9*9 7I 33 0 34 29 ^
1977 17.1 3.9 22.0 tt.0 11.0) 1976 7.8 3.7 13.2 4.0 9.
1969 (PRE-OPERATIONL) NO DAT u --- ---
.. .- j 110
--- l ;
=
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Milk Samples STANDARD I-131 pC1/1 EAN A iMUM b,M E DEVIATION 1986 13.6 1/.3 29.0 0.8 28.2 1985 <LLD --- --- --- ---
1984 <LLD --- --- --- ---
1983 <LLD --- --- --- ---
1982 <tLD --- --- --- ---
1981 (LLD --- --- --- ---
1980 1.41 ONLY ONE DATA POISI 1979 <LLD --- --- -o-
= _.
1978 GIDL --- --- --- ---
1977 NO DATA --- --- --- ---
1976 NO DATA --- --- --- ---
1969 (PRE-OPERATIONL) NO DATA --c --- --- ---
INDICATOR _. ~ . .-
Milk Samples MEAN STANDARD MAXIMUM MINIMUM RANGE I-131 oct/1 DEVIATION 1986 5.2 7.5 30.0 0.3 29.7 1985 ,< t,to ___ . . _ _ ___ _ , _ _
1984 <tto ___ __. __ ___
1983 <tto ___ __, ___ ___
1982 <LLD --- --- --- ---
1981 < LI.D . --- --- --- ---
1980 4.9 4.23 e.80 0.40 8.40 1979 <tto ___ ___ ___ ___
lI 1978 0.19 ONLY ONE DATA POINT l 1977 0.20 0.14 0.22 -0.40 0.6 !
1976 3.20 7.81 5s.00 0.02 4- 04 l
l 1969 (PRE-OPERATIONL) NO DATA. --- --- <-- ---
111
HISTORICAL ENVIRONMENTAL SAMPLE DATA _
CONTROL Human Fcod Crops A AD MEAN DEVIATION MAXIMUM MINIMUM RANG [i I-131 pCi/g (wet) Produce
-1980 <tto ___ -_- ___ ---
=
1985 <tLD --- --- --- ---
1984 <tto _-_ _-- ___ __-
1983 jtLD --- --- ---
i 1982 <tta ___ ___ --_ __-
1981 <tto -__ ___ __. -_-
1980 <tte --- --- --- ---
1979 NO CONTROL DATA PRIOR TO 1980 s 1978 1977 ]
1976 )
1969 (PRE-OPERATIONL)
IND3CATOR _
Human Food Crops MEAN STANDARD MAXIMUM MINIMUM RANG @
I-131 pCi/g (wet) Produce DEVIATION 1986 <tto --- --- ___ ---
l 1985 <tto
]
l 1984 (LLD --- --- --- ---
1983 <LLo --- --- --- ---
1382 <LLo- --- --- --- ---
1981 <LLD --- --- --- --- '
l 1980 <tLD --- --- --- --- t l
1979 <Lto --- --- --- ---
1978 (MDL --- --- --- ---
1977 (MDL y
--+ --- --- ---
1976 <xon _-_ --- ___ _--
1969 (PME-OPERATIONL) NO DATA --- --- --- ---
112 1 -
...s HISTORICAL EN IRONMENTAL SAMPLE DATA ,,
CONTROL ,
Human Food Crops STANDARD RANGE MEAN MA MINWUM Cs-137 pC1/g (wet) Produce DE.VIATION 1986 <LLD --- --- --- --- ,
1985 <LLD --- --- --- ---
1984 (LLD --- --- --- ---
1983 <LLD --- --- --- ---
. -m8 1982 <LLD --- --- --- --- '
1981 (LLD --- --- --- ---
1980 <LLD --- --- --- ---
1979
~
NO CONTROL DATA PRIOR TO 1960 1978 1977 1976 6.
1969 (PRE-OPERAT ONL)
INDICATOR Human Food Crops MEAN STANDARD MAXIMUM MINIMUM RANGE Cs-137 pCi/g (wet) .roduce DEVIATION n 1986 <LLD --- --- --- ---
( 1985 0.047 ONLY ONE DATA POINT a; 1 i 1984 <LLD --- --- --- ---
]
s 1983 <LLD --- --- --- --- -?
?
g' 4 1982 <LLD --- --- --- ---
1981 <LLD --- --- --- ---
' ,. M 1980 0.033 2.26 0.06 0.004 0.056 l
1979 <LLD --- +-- --- ---
7 ,
1978 0.01 ONLY ONE DATA POINT .,p -,
1977 <MDL ---
1976 eDL --- --- - - - ---
, 1969 (PRE-OPER ATIONL) '40 DATA --- --- --- ---
l l
113
.:.4, -
vil
,e i
i A
FIGURES AND MAPS
Vil FIGURES AND MAPS
- 1. DATA GRAPHS This section includes graphic representation of selected sample results.
For graphic representation, results les:: than the MDL or LLD were considered to be at the MDL or LLD level of activity. MDL and LLD values were indicated where possible.
- 2. SAMPLE LOCATIONS Sample locations referenced as letters and numbers on analysis results tablen are plotted on maps.
l 114
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TABLE VIII-l USEPA ENVIRONMEN"AL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAli Gross Beta Analysis of Air Particulate Filters (pCi/ filter) JAF- JAF EPA DATE ENV ID NUMBER MEDIUM ANAYLSIS RESULT (1) RESULT (2) 04/86 QA86-29 APF BETA 5926(3) 4725 5926 6226 09/86 QA86-102 APF- BETA 7825(3) 66:5 i 7925 8123
.i i
i i 132 :l
TABLE VIII-2 USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Trituim Analysis of Water (pC1/L) JAF JAF EPA DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1)- RESULT (2) 02/86 QA86-9 WATER H-3 5100!100 (4) 52271523 ; 53002300
)
54002200 I 06/86 QA86-55 WATER H-3 31002100 (4) 3125:360
)
31002200 .! 31002200 10/86 QA86-114 WATER H-3 59002100 (4) 59732597 60002200 6000!600 133 __._____o
TABLE VIII-3 USEFA ENVIPONME!TIAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Iodine Analysis, of Water (pC1/L) arid Milk (pC1/L) JAF JAF LPA DATE ENV ID NtEBER MEDIUM FLCLIDE RESULT (1) RESULT (2) 02/86 QA86-13 MILK I-131 832 (4) 926 822 8!2 04/86 QA86-25 WATER I-131 1021(4) 926 10!2 1022 08/86 QA86-79 WATER I-131 4022 (4) 4526 4322 45!2 l 134
TABLE VIII-4 LSEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Gamma AL.alysis of Milk, Water (pCi/L) Air Particulate Filters (pci/ filter) and Food Products (pCi/kg) JAF JAF EPA DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1) RESULT (2) 01/86 QA86-4 FOOD I-131 21+4 (4) 20+6 22+4 23{4 Cs-137 1S+4 15+5 19+4 2034 K (*) 829+83 950+143 867+87 863386 02/86 QA86-5 WATER Cr-51 31+11 (3) 38+5 34+15 37317 Co-60 16+2 18+5 18+2 1932 Zn-65 40+4 40+5 41+5 46{4 Ru-106 <LLD 05 1 Cs-134 25+1 30+5 25+2 2612 , Cs-137 20+2 22+5 l 2172 22[2 04/86 QA86-29 APF Cs-137 12+2 (3) 10+5 13+2 1432 135
TABLE VIII-4 (CONTINUED) USEPA. ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM t . Gamma Analysis of Milk, Water (pC1/L) l Air Particulate Filters (pCi/ filter) and Food Products (pC1/kg) JAF JAF EPA DATE ENV ID NUMBER MEDIUM NUCLIDE RESULT (1) RESULT (2) 04/86 QA86-28 WATER Co-60 14+4 (3) 10+5 (BLIND) 1573 1674 Cs-134 672 5+5 7+3 7[3 Cs-137 6+2 5+5 7+2 7{3 06/86 QA86-63 MILK I-131 37+2 (4) 41+6
~
3872 3813 Cs-137 37+4 31+5 37+5 3735 K (*) 1410+140 1600+80 1460+150 14903150 06/86 QA86-52 WATER Cr-51 (LLD (3) 0.0+0.0 Co-60 61+7 66+5 62+7 62}8 Zn-65 79+14 86+5 79+11 85314 Ru-106 43+19 50+5 , 48+30 56320 Cs-134 39+4 49+5 40+5 43}6 136
. _ _ _ _ _ _ _ _ . - _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ __ _ _ _ _ _ _ _ __ __ __ _ _ _ _ _ _ _ - . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ J
TABLE VI11-4 (CONTINUED) USEPA' ENVIRONMENTAL RADIOACTIVITY LABORATOPY INTERCOMPARISON STUDY PROGRAM Camma Analysis of Milk, Water (pC1/L) Air Particulate Filtres-(pci/filcar) and Food Products (pC1/kg) JAF JAF EPA DATE ENV 10 NUMBER MEDIUM NUCLIDE RESULT (1) hESULT (2) 06/86 QA86-52 WATER Cs-137 9+3 10+5
-(cont'd) 1073 1134 07/86 QA86-68 FOOD I-131 24+3 (4) 30+6 .)
26+5 2637 Cs-137 27+4 20+5 25+4 25[4 K (*) 1010+100 1150+58 1010+100 1090[110 09/86. QA86-102 APF Cs-137 23+6 (3) 22+5 24+5 2536 10/86 QA86-113 WATER Cr-51 75_+24 (3) 59+5. 84+35 89152 Co-60 33+14 31+5 36+6 38[13 Zn-65 101+16 85+5 102+32 l 103311 Ru-106 62+22 74+5 67766 79138 Cs-134 28+11 28+5 29+11 3034 137
TABLE VIII-4 (CONTINUED) USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM Gamma Analysis of Milk, Water (pCi/L) Air Particulate Filters (pC1/ filter) and Food Products (pCi/kg) 1 JAF JAF EPA DATE ENV ID NIMBER MEDIUM NUCLI3E RESULT (1) RESULT (2) 10/86 QA86-il3 WATER Cs-137 48+13 44+5 (cont'd.) 51+5 54714 10/86 QA86-123 WATER Co-60 22+9 (3) 24+5 (B1,IND) 2379 25311 Cs-134 10+5 12+5 10+7 1237 Cs-137 9+6 8+5 9+6 937 10/86 QA86-124 MILK I-131 49+4 (4) 4916 55+4 55311 Cs-137 41+5 39+5 44+6 4835 K (*) 1220+120 1565+78 1240+120 13303130 K-40 results reported as mg per unit of total potassium for EPA results only. l (1) - Results reported as activity + the standard deviaton of the error. (2) - Results reported as activity + the error (2 sigma).
.(3) - Analyzed at the site environmental laboratory. j (4) -
Analyzed at a vendor laboratory. l l 138 I __________________a
, -- . _ ~ _ _ _ . _ - . _ _ _ _ . - - _ - . _ . - _ . _ - . _ _
Jrmss A. Fit Patrick No-:Inte Powsr Plant ' PO Boa 41 Lycoming. New York 13093 a l5 34 2 ?'?40 l Radford J. Converse
#> NewYorkPower "*'"'"""
11st Authority April 30, 1987 JAFP-87-0365 United States Nuclear Regulatory Commission Region 1 631 Park Avenue King of Prussia, Pennsylvania 19406 Attention: William Russell Regional Administrator
SUBJECT:
JAMES A . FITZPATRICK NUCLEAR POWER PLANT RADIOLOG-I ICAL ENVIRONMENTAL SURVEILLANCE REPORT FACILITY OPERATING LICENSE DPR-59, DOCKET NO. 50-333 Gentlemen: In accordance with the United States Nuclear Regulatory Commis- x sion Guide 10.1, we submit the 1986 Annual Environmental Operating Report, Part B: Radiological Report. Distribution for this r ort is in accordance with Regulatory Guide 10.1. f<.-s w RAD ORD J. CONVERSE RJC:JAS:emd Enclosure (1) Copy: . Document T Control Desk (USNP;C)f(18) ' J. W. Blake (NYPA/WPO) J. C. Brons (NYPA/WPO) R. Burns (NYPA/WPO) J. J. Kelly (NYPA/WPO) J. Toennies (NMPC) E. Leach (NMPC) E. Mulcahey > B. Gorman J. A. Solini RES File WPO Records Management Library Document Control Center CERTIFIED MAIL, RETURN RECEIPT REQUESTED [6N r (,
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