ML20153H658
| ML20153H658 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1987 |
| From: | POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | |
| References | |
| NUDOCS 8805130090 | |
| Download: ML20153H658 (166) | |
Text
{{#Wiki_filter:,, , i NEW YORK POWER AUTHOP.lTY ANNUAL ENVIRONMENTAL OPERATING REPORT i#cT 8: RADIOLOGICAL REPORT JANUARY 1,1987 - DECEMBER 31, 1987 JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR-59 DOCKET NUMBER 50-333 f f-01 lL I f !
/
f 8805130090 PDR 871231ADOCK DCD 05000333 . R , p r
4 TABLE OF' CONTENTS Page I. INTRODUCTION Introduction 1 Program Objectives 2 II. PROGRAM IMPLEMENTATION AND DESIGN Sample Methodology 4 Analysis Performed 9 Changes in Program 10 Exceptions to the Program 11 Deviations from the Interlaboratory 12
' Comparison Program Operational Radiological Environmental 13 Monitoring Program (Table) 111. SAMPLE SUMMARIES 18 IV. ANALYTICAL RESULTS 24 V. DATA SUMMARIES AND CONCLUSIONS 77 Surface Water (Lake) Program 81 Terrestrial Program 93 Conclusion 124 References 125 VI. HISTORICAL DATA 127 Vll. FIGURES AND MAPS 136 Vill.
SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY 154 LABORATORY INTERCOMPARISON STUDIES PROGRAM RESULTS i
i L LIST OF TABLES Page f b Table l Required Sample Collection and Analysis 13 (1/1/87 - 12/31/87) Table 1 Shoreline Sediment Results 25 Table 2 Fish Results 26 Table 3 Surface Water Composite Results, Tritium 28 Table- 4 Surface Water Composite Results, Gamma Isotopic 30 Table 5 Particulate Filter Results, Cross Beta (Offsite) 36 Table 6 Particulate Filter Results, . Gross Beta (Onsite) 38 Table 7 Airborne - l-131 Results (Offsite Stations) 39 Table 8 Airborne 1-131 Results (Onsite Stations) 41 Table 9 Particulate Composite Results, Gamma Isotopic 42 Table 10 TLD Results 58 Table 11 Milk Results,1-131 62 Table 12 Milk Results, Gamma Isotopic 64 Table 13 Milch Animal Census Results 67 Table 14 Food Product Results, Gamma Isotopic 69 Tab!e 15 Site Boundary Vegetation Results, Gamma Isotopic 71 Table 16 1987 Residence Census 72 Table 17 Environmental Sample Locations 73 Table Vill-1 Gross Beta Analysis Air Particulate (pCi/ filter) 155 and Water (pCl/L) Table Vill-2 Tritium Analysis of Water (pCi/L) 156 Table Vill-3 lodine Analysis of Water (pCi/L) and Milk 157 (pCl/L) Table Vlll-4 Gamma Analysis of Milk, Water (pCl/L), Air 158 Particulate (pCi/ filter) and Food Products (pCi/kg) l 11
LIST OF FIGURES Page Figure 1 A _Offsite Environmental Stations and TLD Locations 137 Figure 18 Offsite Environmental Stations and TLD Locations _137_ (Southern) Figure 2. Offsite and Onsite Environmental Stations, 139 TLD Locations Figure 3 Nearest Residence and Food Product Locations 140 Figure 4 Milch Animal Census and Milk Sample Locations 141 Figure 5 New York State Regional Map 142 Figure 6 Graph - Fish (Cs-137) 143 Figure 7 Graph - Air Particulate Gross Beta 144 Figure 8 Graph - Air Particulate Gross Beta, Weeks 1-26 145 (1987) Figure 9 Graph - Air Particulate Gross Beta, Weeks 27-52 146 (1987) Figure 10 Graph - Air Particulate Composite (Co-60) 147 Figure 11 Graph - Air Particulate Composite (Cs-137) 148 Figure 12 Graph - Milk (Cs-137) 149 Figure 13 Graph - Milk (Cs-137), Stations 4,16 and Control 150 for 1987 Figure 14 Graph - Milk (Cs-137), Stations 7, 60 and Control 151 for 1987 Figure 15 Graph - Milk (Cs-137), Stations 50, 55 and Control 152 for 1987 Figure 16 Graph - Milk (1-131) 153 ill
I-A INTRODUCTION The New York Power Authority (NYPA) is the owner and licensee of the James A. FitzPatrick Nuclear Power Plant (J AFN PP) . The FitzPatrick Plant which is located on the eastern portion of the Nine Mile Point promontory approximately one-half mile due east of the Niagara Mohawk Power Corporation (NMPC) Nine Mlle Point Nuclear Power Stations (NMPNPS). The NMPNPS Unit
- 1 is located on the western portion of the site and is a boiling water reactor with a design capacity of 620 MWe. The NMPN PS has been in commercial operation since the fall of 1969. Located between the JAFNPP and NMPNPS, Nine Mile Point Unit #2 previously under construction was completed in mid-1987. NMPNPS Unit #2 will have generatfor' capacity of 1,100 MWe and commenced start-up testing in late 1987. The JAFNPP is a boiling water reactor with a power output of 810 MWe (net). Initial fuel loading of the reactor core was completed in November of 1974. Initial criticality was achieved in late November, 1974 and commercial operation began in Juiy cf 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 is the largest metropolitan center in the area and is located 40 miles to the south of the site. The area consists of partially wooded land and shoreline. The land adjacent to the site is used mainly for recreational and residential purposes. For many miles to the west, east and south the country is characterized by rolling terrain rising gently up from the lake, composed mainly of glacial deposits. Approximately 34 percent of the land area in Oswego County is devoted to farming. The Radiological Environmental Monitoring Program for the Fitz Patrick Plant is a site program with responsibility for the program shared by the Power Authority and Niagara Mohawk. Similar Technical Specifications for radiological monitoring of the environment allows for majority of the sampling and analysis to be a joint undertaking. Data generated by the program is shared by the two facilities with review and publication of the data under-taken through each organization. This report is submitted in accordance with Scction 7.3.d of the Radiological Effluent Technical Specifications (RETS) to DPR-59, Docket 50-333, 1
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 regulatnry 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.
I 2 f 2
~-_ _ __ _ ._ . __ _ _ , . _ . _ . , .. .._.
s il PROGRAM IMPLEMENTATION AND DESIGN To achieve the objectives listed in Section I-B, sampling and analysis are.
. performed as outlined in Table 1.
The sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the James A. FitzPatrick Plant and the Nine Mlle Point Station. .The site staff is assisted by a contracted environmental engineering company, EA Science and Technology, Inc. (EA). 1 4 7 3
- 1. SAMPLE COLLECTION METHODOLOGY A. Surface Water Surface water samples are taken from the respective inlet canals of JAFNPP and Niagara Mohawk's Oswego Steam Station (OSS). The JAFNPP removes water from Lake Ontario on a continuous basis and generally represents a "down-current" sampling point from the Nine Mlle 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 location because of the distance from the site as well as take current patterns and current patterns from the Oswego River located nearby. Samples from the JAFNPP are composited from automatic sampfing equipment which discharges into a large compositing tank. Samples are obtained from the tank monthly and analyzed 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. In addition to the FitzPatrick and Oswego Steam Station facilities , data are presented for the nine Mile point Unit 1 and Unit 2 facility inlet canals and city water from the City of Oswego. The latter three locations are not required by the Technical Specifications, but are optional samples. Monthly composite samples from these three locations are analyzed for gamma emitters and quarterly composite samples are analyzed for Tritium. Surface water sample locations are shown in Section Vll on Figure 1A. B. Air Particulate / lodine l i The air sampling stations required by the RETS are located in the l 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 Mlle 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. 4 , i
l In addition to the RETS required locations, there are six other sampling stations located within the site boundary (D1, G, H, I, J, and K). These locations generally surround the area occupied by the three generating facilities, but are well within the site bounda-ry. One other air sampling station is located off-site in the south-Mst sector and is in the vicinity of the City of Oswego (G off). Three remaining air sampling stations (D2, E, F) are located in the ESE, SSE, and S sectors and range in distance from 7.2 to 9.0 miles. At each station, airborne particulates are collected by glass fiber filters and radioiodine by charcoal cartridges. Air particulate glass fiber filters are approximately two inches (47 millimeters) in diame-ter and are placed in sample holders in the intake line of a vacuum sampler. Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to adsorb 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. Gross beta analysis is performed for the individual par-ticulate filters on a weekly basis. Charcoal cartridges are analyzed weekly for radiolodine by GeLi detector. The particulate filter.s are composited for gamma analyses on a monthly basis by location after all weekly particulate filters have been counted for gross beta activity. Air sampling stations are shown in Figures 1 A,1B, and 2. C. Milk Milk samples are collected in polyethylene bottles from the bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat. 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 and shipped to the ana-lytical laboratory within thirty-six hours of collection in insulated shipping containers. Milk sample location selection is based on maximum deposition factors (D/Q). Deposition factors are generated from average historical meteorological data based on all licensed reactors. The Technical Specifications require three sample locatione within 5.0 miles of the site with the highest calculated deposition factors . During 1987, there were no milk sample locations within 5.0 miles that could be sampled. However, there were several optional locations beyond five miles that were sampled. A fourth sample location required by the Technical Specifications is located in a least prevalent wind direction from the site. This location is in the southwest sector and serves as a control location. Milk samples are collected twice per month ( April - December) and analyzed for gamma emitters and l-131. Samples are collected and 5 I l
analyzed in January - March in the event 1-131 is detected in No-vomber and December of the preceding year. The milk sampling locations are found in Section Vil on 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. Sampic collections are performed at the site boundary in two different direction sectors having the height cal-culated D/Q values. 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 distant for each type of sample. Food products sampling as required by Table 6.1-1 (Section A & B under Food Products) are not per formed. This form of food products sampling is only required when milk sampling is not being performed. The food products sampling locations are shown in Section Vil on Figure 3. E. Fish Samples Available fish species are removed from the Nine Mlle Point Aquatic Ecology Study monitoring collections during the spring and fall collection periods. Samples are collected from a combination of the four onsite sample transects and one offsite sample transect (see Section Vil, Figure 1 A). Available species are selected under the
- following guidelines:
- 1) 0.5 to 1 kilogram of edible portion only of a maximum of three species per location.
- 2) Samp es composed of more than 1 kilogram of single species from the same location are divided into samples of I kilogram each prior to shipping. A maximum of three samples per spe-Weight of samples are the edible cles per location are used.
portions only. 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 bags, sealed and shipped for analysis in insulated containers. i Shoreline sediment locations are shown in Section Vil on Figure 1 A. l 6
G. TLD (direct radiation) Thermoluminescent dosimeters (TLD's) are used to measure direct radiation (gamma dose) in the environment. T LD's are obtained from Teledyne isotopes on a quarter y 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 T LD'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 T LD'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 arc 3 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 1987 were composed of rectangular teflon wafers impregnated with 25 percent CaSOg:Dy phosphor. These were placed in a polyethylene package to ensure dosimeter integrity. TLD packages were placed in open webbed plastic holders and were attached to supporting structures, usually trees or utility poles. Environmental TLD locations are shown in Section Vil on Figures 1A, 18, and 2. H. Land Use Census A land use census is conducted during the beginning of the grazing season to determine the utilization of land within the vicinity of the site. The land use census consists of two types of census. A milk animal census is conducted to identify all milk animals within a distance of ten miles from the site. This census is conducted by using road surveys, contacting local agricultural 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 sectors are over Lake Ontar!o because the site is located at the shoreline. No resi-dences are located in these sectors. There are on:y eight sectors over land where residences are located within five miles. 7
I. 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. 8
a - - - - - - - - - - -- - - - - - - - - - - - - - ' - - - - - - - - - - - - - - - - - - - -- - -- ' - - - - - - - - - - - - - - - - 5
- 2. ANALYSIS PERFORMED The analysis of the environmental samples is performed by Teledyne isotopes (TI) and the James A. FitzPatrick Environmental Counting Labo-ratory (JAFECL). The following samples are analyzed at the JAFECL:
o Air Particulate Filter - gross beta (weekly)' o Air Particulate Filter Composites - gamma spectral analysis (monthly) o Airborne Radiolodine - gamma spectral analysis (weekly) o Surface Water Composites - gamma spectral analysis (monthly) a o Special Samples (soll, etc.) - gamma spectral analysis (as collected) o Fish - gamma spectral analysis o Shoreline Sediment - gamma spectral analysis o Milk - gamma spectral analysis The remainder of the sample analysis as outlined in Table I is performed by Tl. I I l I
~
1 0
- 3. CliANCES TO THE 1987 SAMPLE PROGRAM A. Program TLD #107 was added to the monitoring program on April '2, 1987. TLD #107 was added to the program as a backup for TLD
#106.which is used to evaluate any possible doses to members of the public involved in activities within the site boundary.
B. An additional food product location (J) was added to the monitoring program during 1987. This location was utilized during 1987 fo r - garden -fruits and vegetables. Location J was added because of its proximity to the site and represents one location of several program locations that may be utilized for food product samples dependent upon sample availability. C. The Nine Mile Point Nuclear Statinn Unit 2 inlet canal was added to the sampling program during 1987. The Unit 2 inlet canal removes cooling water from Lake Ontario. This location was added to the i sampling program to be consistent with the sampling program at the other generating facilities and to assess any possible impact from the operation of the generating facilities in the immediate area of Lake Ontario. This sample is not required by the J. A. FitzPatrick Technical Specifications. D. Three on-site (within the site boundary) air sampling stations were moved to former off-site air sampling locations. The three air sampling stations were D2 on-site (moved 1-14-87), E on-site (moved 1-14-87), and F on-site (moved 1-15-87). These stations i were moved to previous air sampling locations--D2 off-site , E off-site, and F off-site which were utilized prior to 1985. None of the on-site or off-site locations are required by the Technical Spec-l ifications. The on-site locations were moved because of the impor-tance of locating monitoring stations between the site and populated areas. The D2 off-site location is in line with Mexico, New York; the E off-site location is in line with Phoenix, New York; and the F ( off-site location is in line with Ful ton , New York. The three on-site locations were not considered as critical as the off-site locations when considering the fact that air monitoring stations are already located at the site boundary in critical downwind areas. i L i 10
- 4. EXCEPTIONS TO THE 1987 SAMPLE PROGRAM Exceptions to he 1987 sample program concern those sampling or monitor-ing requirements which are required by the JAF Technical' Specifications.
A. Air radiolodine and air particulate monitoring required by Technical Specifications.
- 1. Environmental air sample equipment at R-3 off-site air sampling station was inoperable from 4/14/87 (1550 hours) to 4/16/87 (0919 hours). The vacuum pump was found defective and was replaced.
- 2. Environmental air sample equipment at R-5 off-site air sampling station was inoperable from 6/23/87 (1057 hours) to 6/23/87 (1329 hours). The vacuum pump was found defective and was replaced.
- 3. Environmental air sample equipment at R-5 off-site air sampling location was inoperable from 6/27/87 (2250 hours) to 6/30/87 (1504 hours). The vacuum pump was blown. The pump was replaced. '
- 4. Environmental air sample equipment at R-2 off-site air sampling location was inoperable from 9/4/87 (0550 hours) to 9/4/87 (0855 hours). The vacuum pump was found defective and was replaced.
- 5. Environmental air sample equipment at R-4 off-site air monitor-ing station was inoperable from 9/10/B7 (2000 hours) to 9/11/87 (1340 hours). The vacuum pump was found defective and was replaced.
- 6. Environmental air sample equipment at R-5 off-site air monitor-ing station was inoperable from 10/31/87 (1530 hours) to 11/3/87 (1056 hours). The vacuum pump was found defective and was replaced.
- 7. Environmental air sample equipment at R-1 and R-2 off-site air monitoring stations was inoperable from 11/6/87 (2045 hours) to 11/7/87 (0510 hours). The vacuum pumps in both of these monitoring stations were inoperable due to an off-site power loss. All monitoring equipment was operable once off-site power was restored.
Other occurrences of downtime for optional air sampling stations were documented for 1987. These occurrences are not noted in this report because the optional air sampling stations are not required by Technical Specifications. Documentation includes downtime for air sampling equipment as well as environmental radiation monitoring equipment. 11
B. Deviations from the Interlaboratory Comparison Program Section 6.3 of the J. A. FitzPatrick N. P. P. Technical Specifications requires the site to conduct an Interlaboratory Comparison Program utilizing QC samples from the Environmental Protection Agency (EPA). This section also requires that deviations from the sample schedules be reported in the Annual Radiological E.1vironmental Operating Report. The sample schedule is set by the EPA and includes media for which environmental samples are routinely col-tected and for which interlaboratory comparison samples are avall-able from the EPA. During 1987, sample media offered by the EPA for the Interlabo-ratory Comparison Prog ram , and for which environmental samples are routinely collected and analyzed, were obtained and analyzed. The amount of samples obtained from the EPA program was based on the maximum amount available per participant or on a ten percent or better level (percent of the ratio of EPA samples to the total required sample volume). A review of the 1987 results showed that one EPA sample, which was scheduled during October, was not received. This sample was a spiked milk sample. Since the sample was not received, it could not be analyzed. Subsequent investigation of the missing spike sample and written correspondence from EPA showed that the sample was never sent by the EPA to the program participants. l l l l I 12
TABLE I OPERATICtRL RADIOIDGICAL DNIR0tNENTAL MONTIORING PROGRAM Exposure Sanpling and Pathway gg Collectiog Type and Frequency and/or Sanple ibnher of Sanples and Iocations Frequency of Analysis AIRBORh? Radiciodine Sanples fran 5 locations: Continuous sam- Radiciodine Canisters:- and ple operation Analyze weekly for I-131. Particulates a. 3 sanples from offsite locations in dif- with sanple col-ferent sectors of the highest calculated lection weekly Particulate Sanples: site average D/O (based on all licensed or as required Gross beta radioactivitg) site reactors). by dust loading, following filter change whichever is ca:posite (by location)
- b. I sanple fran the vicinity of a consnunity nore frequent. for gansna isotopic having the highest calculated site aver- quarterly (as a mininua) .
~ age D/Q (based on all licensed site re-(a actors). !
- c. I sanple fran a control location 9 to 20 miles distant g in the least prevalent wind direction .
Direct 32 stations with two or more dosimeters Quarterly Ganma dose monthly or Ridiation(*' placed as follows: An inner ring of stations quarterly. in the general area of th site boundary and an outer ring in the 4 to 5 mile range fran the site with a station in each of the land based sectors of each ring. 'Ilmre are 16 land based sectors in the inner ring, and 8 land based sectors in tha outer ring. 'Ihe balance of the stations (8) are placed in special interest areas such as population centers, nearby residences, schools, and in 2 or 3 areas to serve as control stations.
TABIE I (CONTINUED) Exposure Sanpling and Pathway 11 " "U and/or Sanple Number of Sanples(a) and Iocations Frequency of Analysis 1RTERBORNE I Surface a. I sanple upstream. Caposite sam- Canma isotopic analysis ple over one monthly. Conposite for
- b. 1 sanple frm the siyg nost downstream nonth period (9'. Tritig)analysisquar.
cooling water intake terly Sediment fran 1 sanple frm a downstream area with existing hice per year. Ganma isotopjg) analysis Shoreline or potential recreational value. s<miannually A INGESTION Milk a. Sanples from milch animals in 3 locations w ice per month, Conma isotopic and I-131 within 3.5 miles distant having the high- April tlunigh analysis twice per month est calculated site average D/Q. If Decmber (sam- when milch animals are there are none, then 1 sanple frm milch ples will be on pasture (April through animals in each of 3 areas 3.5 to 5.0 collected in December); monthly (Jan-miles distant having the highest calcu- January through uary g h March), if lated site average D/O g sed on all March if I-131 required . licensed site reactors) is detected in November arxl
- b. 1 sanple frm milch animals at a control December of the location (9to20milesdistankd in a Preceding year) .
less prevalent wind direction)
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f l 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 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 ODCM) for all licensed site reactors. (b) Particulate sample filters should be analyzed for gross beta 24 hours 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 yearly mean of control samples, gamma isotopic analysis shall be performed on the individual samples. . (c) Gamma 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 taken at a distance beyond significant influence of the discharge. The "downstream sample" shall be taken in an area beyond, but near, the mixing zone, if practical. (g) Composite samples should be collected with equipment (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. 16
(h) A milk sampling location, as required in Table 6.1-1 of the RETS, or Table i of this report, is defined as a location having at least 10 milking cows present at a designated m:lk sample iocation . It has been found from past experience, and as a result of conferring with local fa rme rs , that a minimum of 10 milking cows is necessary to guarantee an adequate supply of mil'< twice per mytn for analytical l 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 esed if an adequate supply of milk can reasonably and reliably be obtained based on communica-tions with the farmer. 17
lil S AMPLE SU.%MARIES All sample data is summarized in table form . The tables are titled "Radiological Moaltoring Program Annual Summary" and use the follow-ing format: l l A. Sample medium, i ! B. Type and number of analyses performed. 1 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 calcu-lations. The use of LLD's in these calculations would result in means being biased high. 18 _ l
PADIOIDGICAL tDNTIDRIhG PROGRAM AtERIAL Suit!ARY JMES A. FITZPA'IRICK NUCLEAR POWER PIA?Tr DOCKET to. 50-333 O5WEGO GOUtrIY, STA*IF. OF IEW YORK JANUARY - DFm!BER 1987* Iocation (b) of Type and Indicator Incations: liighest Annual Mean: Control Incation: theber of Medium Ntz:ber of Mean (a) locations & Mean (a) Mean (a) Nonroutine (Units) Analyses UE Range Range Range Reports Shoreline GSA (4) Sediment (pCi/g-dry) Cs-134 0.15 <UD <UE <UB 0 Cs-137 0.18 <IlB <UB <UD 0 Fish CSA (24) (pCi/g-wt) Mn-54 0.13 (UD (UD <U D 0 Fe-59 0.26 <UE <UD <UB 0 CO-58 0.13 (UD <UD <UD 0 G Co-60 0.13 <UB <UD <UE O Zn-65 0.26 <UD <UB <UD 0 Cs-134 0.13 <11D <UB <UD 0 Cs-137 0.15 0.034 (11/17) toe 0.035 (7/10) 0.031 (7/7) 0 0.024-0.063 0.3@315 0.024-0.063 tid 17-0.040 Food GSA (9) Products T-TE-- 0.06 <Um <uD <un 0 (pCi/g-wt) Inedible Vegetation Cs-134 0.06 <UD <UD <UD 0 Cs-137 0.08 <UD <uD <uD 0
RADIGIDGICAL FDNI'IL2ING PROGR A #2EAL SMIMRY JAMES A. FITZPA"IRICK IECLFAR PUER E $r DOC.r7T No. 50-333 OSWEGO 00UtTIY, STATE OF NEW YORK JNUARi - f>ECEMBER 1987* Ioca*. ion (b) of Type and Indicator locations: Highest Annual Mean: Control Incation: Ikmber of r Ph.ber of Mean (a) Incation & Mean (a) Mean (a) Nonroutine fialyses UD Rar.ge Range Range Reports Sun ' - (Take) Water H-3 (8) 3000 323 (4/4) JAF 323 (4/4) 210 '4/4) 0 (pCi/ liter) 160-410 0.5@'0* 160-410 140-270 GSA (24) Mn-54 15 <UD <UD <UD 0 Fe-59 30 <UD <UD <UD 0 l Co-53 15 <UD <'ID <UD 0 co-60 15 (UD <uD <uD 0 u Zn-65 % <UD <UD <UD 0 Zr-95 15 <aB <UD <uD 0
?!b-95 15 <UD <UD <'JD 0 I-131 15(g) <UD <UB <UD 0 Cs-134 15 <UD <UD <UD 0 Cs-137 18 <UD <UD <UD 0 Ba/la-140 15 (UD <UD <UD 0 l - - - -
g- s. e 8 L % 'a
RADIGIDGICAL FDNI'IORIfC FROGRAM A?M'AL SIVEARY JAMES A. FITZPA'IRICK NUCLEAR FG7ER PIAVf DOCKET NO. 50-333 OSWEGO 00UNIY, STATE OF NEli YORK JANUARY - DECmBER 1987* Incation (b) of Type end Indicator Incations: liighest Annual Penn: Cbntrol Incation: Number of Medium Ntrier of Mean (a) Incation & Mean (a) Mean (a) Nonroutine (units) Analyses I1D Range Range Range Reports Air Particulates G.B.(260) 0.01 0.021 (208/208) R2 0.021 (52/52) 0.021 (32/52) 0 and 0.009-0.040 1.1@l04* 0.009-0.037 0.009-0.037 Radiolodine
- .1) I-131(260) 0.07 0.014 (2/208) R2 0.018 (1/52) <UD 0
(pCi/m3) 0.011-0.018 1.I@l04* 0.018 GSA(60): Cs-134 0.05 <UE <UB <ILD 0 Cs-137 0.06 <UB <UD <UD 0 1 i Ru-103 N/A <UD <UB <ILD 0 U Ru-106 N/A {UD <UE <UD 0 I-131(h) N/A <UD <UD <uA 0 TID Ganma(144) N/A 5.6 (136/136)(c) 185 12.9 (4/4)(c) 5.2 (8/8) 0 (mrem per Dose 3.5-14.3 0.2@294* 12.1-14.3 4.6-5.8 standard month)
RADI0IDGICAL !ONITORING PROGRAM ANNUAL SlM4ARY JAMES A. FITZPATRICK NUCLEAR POWER Pier DOCKET NO. 50-333 OShEGO COUtflY, STATE OF 101 YORK JANUARY - DECDBER 1987*
. Ixration (b) of Type and Indicator locations: Highc::t Annual Mean: Control Incation: Thsrber of Meditzn Ntnber of Mean (a) location & Mean (a) Mean (a) Nonroutine (units) Analyses LLD Range Range Range Reports Milk GSA (126)
(pCi/ liter) Cs-134 15 (f) (f) <IJD 0 Cs-137 18 6.8 (2/108) 155 3.1 (1/18) <IlD 0 5.5-8.1 9.0@95 8.1 Ba/I2-140 15 (f) (f) <LLD 0 1 l I-131(126) 1 (f) (f) <IlD 0 l l w ' N l I l l l l
# d - e y u
e f e A 9
- l l
ANNUAL SUWARY TABLE NOTUS
* = Data for the Annual Sunma ry Tables is based on RETS required samples only.
N/A = Not applicable. (a) = Frac t ion o f detec table measurement to total measurement. (b) = Location is distance in miles, and direction in compass degrees. (c) = Indicator TLD locations are: #7, 23, "5, 76, 77, 78, 79, 30, 81, 82, 83, 84, 85, 86, 87, 88, 69, 90, 91, 92, 93, 94, 95, 96, 97, 98, 99, 100, 101, 8, 15, 18, 56, and 58 Control TLD's are all TLD's located beyond the influence of the site (#14, 49). (d) = Indicator samples from environmental stations R1 offsite, R2 offsite, R3 offsite, and R4 offsite. Control samples are samples from R5 offsite environmental station. (e) = This dose is not representative of doses to a member of the public since this area is located near the north shorcline which is in close 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 miIk sample loca t ions v.i thin 3.0 mi I es of the site. Therefore, the only sample location required by the RETS is the control location. (g) = The RETS do not specify a particular LLD value for surface water analysis (non-drinking water) for I-131. A value of '_ 15 pCi/ liter is used here and represents the most recent guidance from the NRC. (h) = Data for particulate I-131. (i) = Cs-137 values are a result o' the 1986 Chernobyl Nuclear Plant accident. 23
h 1 IV ANALYTICAL RESULTS Environmental Sampic Data Environmental sample data is summarized by tables. Tables are pro-vided for select sample media 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. The LLD is the smalles't concentration of radioactive material in a l sample that will be detected with 95% probability and with 5% probability of ' l falsely concluding that a blar.k observation represents a "real" signal. , 1 For o ,v.rticular measurement system (which may include radiochemical l separation), 4.66 s b E V . 2.22 . Y , exp (-AAt) l Where: LLD is the a priori lower limit of detection, as defined above (in picocurie per unit mass or volume); s h is the standard deviation of the background counting rate or of the c5unting rate of a blank sample, as appropriate (in counts per minute); E is the counting efficiency (in counts per transformation); V is the sample size (in units of mass or volume); 2.22 is the number of transformations per minute per picocuric; Y is the fractional radiochemical yield (when applicable): A is the radioactivo decay constant for the particular radionuelide; a is the elapsed time between sample co!lection (or end of the sample col-lection period) and time of counting. Typical values of E, V, Y, and at should be used in the calculations. 24 s i
TABLE 1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in Units c-f pCi/g (dry) + 2 Sigma COLLECTION COLLECTION GAMMA EMITTERS SITE DATE K-40 Co-60 Cs-134 Cs-137 Ra-226 OTHEFS Sunset Beach 04/24/87 15.7+1.15
<0.05 <0.04 <0.05 2.16+0.58 AcTh-228 (05) 0.93+0.17 All Dthers
<LLD 10/23/87 15.4+1.02
<0.04 <0.04 <0.04 1.84+0.60 AcTh-228 0.83+0.16 All 5thers
<LLD U Lang's Beach 04/24/87 14.7+1.16
<0.05 <0.04 <0.05 1.11+0.49 AcTh-228 (06, CONTROL) -
0.67+0.15 All Dthers
<LLD 10/23/87 8.10+0.59
<0.01 <0.02 <0.02 0.76+0.27 AcTh-228 0.21+0.07 All Uthers
<LLD
- Corresponds to sample locations noted on Figure IA, Section VII.
TABLE 2 00NCENIRATIONS OF GAFfu D4ITIERS IN FISH SAMPIE_S Results in thits of pCi/g (wet) i 2 sigma DA'IE TYPE K-40 th-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 OrDIERS FITZPATRICK 06/02/87 Lake Trout #1 3.0410.42 <0.024 <0.032 <0.076 <0.024 <0.051 <0.023 0.03210.015 <UD 06/02/87 Imke Trout #2 3.85+0.40 <0.022 <0.028 <0.076 <0.023 <0.050 <0.022 <0.025 <uD 06/05/87 Brown Trout 3.6710.44 <0.021 <0.028 <0.081 <0.021 <0.056 <0.022 0.03210.014 <UD 10/14/87 Lake Trout il 2.4810.39 <0.020 <0.028 <0.081 <0.026 <0.055 <0.020 0.03010.013 <UD 10/14/87 Lake Trout #2 4.1410.42 <0.021 <0.029 <0.078 <0.018 <0.054 <0.023 0.02610.012 <UD 10/70/87 khite Sucker 3.0310.34 <0.017 <0.024 <0.064 <0.020 <0.040 <0.018 <0.019 <UD 10/07/87 Walleye 6.1910.58 <0.038 <0.053 <0.114 <0.041 <0.089 <0.043 <0.043 (UD NINE MILE FOINT 06/02/87 Lake Trout #1 1.930.28 <0.017 <0.022 <0.063 <0.018 <0.038 <0.016 0.02610.010 <UD 06/02/87 Lake Trout #2 3.8010.42 <0.023 <0.026 <0.082 <0.022 <0.053 <0.022 <0.027 <UD 07/02/87 Brown Trout 3.6910.44 <0.019 <0.024 <0.050 <0.020 <0.045 <0.021 0.03610.016 <UB 07/02/87 Sm. Fbuth Bass 3.1810.52 <0.018 <0.023 <0.047 <0.021 <0.054 <0.019 0.02610.014 <UD 10/14/87 Lake Trout #1 3.0810.34 <0.018 <0.019 <0.050 <0.022 <0.039 <0.017 0.03210.013 <UD 10/14/87 Lake Trout 12 2.9010.42 <0.023 <0.027 <0.064 <0.023 <0.052 <0.021 0.02410.012 <UD 11/04/87 Salmon (Chinook) 4.0410.60 <0.029 <0.033 <0.079 <0.034 <0.074 <0.031 0.06310.021 <UD 10/07/87 Sm. Fbuth Bass 4.0710.45 <0.025 <0.030 <0.093 <0.019 <0.057 <0.022 0.63610.014 (UD 10/07/87 Ualleye 4.2410.48 <0.022 <0.032 <0.094 <0.024 <0.058 <0.026 <0.030 <UD 10/07/87 khite Sucker 4.6410.41 <0.021 <0.028 <0.075 <0.021 <0.047 <0.019 <0.024 <um
- ~ a, l
TABE 2 (Continued) 00NCENIRATIONS OF GAMR EMITIERS IN FISH SAFFLW Results in Units of pCi/g (wet) i 2 sigina IKIE TYPE K-40 Mn-54 Co-58 Fe-59 Co-60 Zn-65 Cs-134 Cs-137 011 E E - CSWE00 HARBOR (00tn30L)~ 06/25/87 Lake Trout #1 3.6210.44 <0.026 <0.029 <0.066 <0.021 <0.054 <0.025 0.02210.015 <uD 06/25/87 Lake Trout #2 <0.023 <0.026 <0.057 <0. 024 .. <0.042 <0.020 0.01710.010 <UD 3.8710.42 06/05/87 Brown Trout 4.02+0.45 <0.024 <0.032 <0.075' '<0.026 <0.065 <0.024 0.039+0.015 <UD s 10/06/87 I4.e Trout il <0.025 <0.036 <0.100 <0.025 <0.062 <0.025 0.04010.019 <UD 4.2810.47 10/06/87 Lake Trout #2 4.0510.38 <0.019 <0.030 <0.065 <0.018 ' <0.048 <0.020 0.03410.011 <uD 11/05/87 <0.018 <0.021 <0.043 <0.071 <0.041 <0.017 0.03710.011' <U D Salnna (Chinook) 4.1310.36 10/20/87 Walleye 3.1910.45 <0.023 <0.025 <0.074 <0.028 <0.054 <0.020 0.030+0.014 <UD l l t
. . _ _ _ ~ _ __ . - .- . _-. - -.. - - _ - .-
TABLE 3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER ' Ii (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/I 1:2 sigma
.l STATION CODE PERIOD DATE TRITIUM FITZPATRICK* First Quarter 01/02/87 to 03/31/87 160+80 ~
(03, INLET) Second Quarter 03/31/87 to 07/01/87 3501100 Third Quarter 07/01/87 to 09/30/87 '410180 Fourth Quarter 09/30/87 to 12/30/87 . 370160 OSWEGO STEAM
- First Quarter 12/31/86 to 03/31/87- 170190 -
STATION w (08, CONTROL) Second Quarter 03/31/87 to 06/30/87 260190 Third Quarter 06/30/87 to 09/30/87 270190 Fourth Quarter 09/30/87 to 01/04/88 140190
- Samples required by the Technical Specifications.
O g7----- p i+w+3-gub-*
= og yrts rf -+r w7
- t7 -'M9' t "'--+1W'r9- T M-'-y1W?f '*-9 -T'-9 -'
?e ~$t+- 'P**= 9 *1 *'&4-erW'
~
'tt C- =v9=e *-s**..P-*www t-e- y e 9--~MTt e Esw- z -iu-* *'v s** w s+ -*4'---
TABLE 3 (Continued) CONCENTRATIONS OF TRITIUM IN SURFACE WATER (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/1 1 2 sigma STATION CODE PERIOD DATE TRITIUM NINE MILE First Quarter 12/31/86 to 03/31/87 <170 POINT UNIT 1** (09, INLET) Second Quarter 03/31/87 to 06/30/87 210170 Third Quarter 06/30/87 to 09/30/87 3901100 Fourth Quarter 09/30/87 to 01/04/88 2501100 NINE MILE First Quarter 12/31/86 to 03/31/87 300+110
~
POINT UNIT 2** g (11, INLET) Second Quarter 03/31/87 to 06/30/87 310170 Third Quarter 06/30/87 to 09/30/87 300170 . Fourth Quarter 09/30/87 to 01/04/88 260180 OSWEGO CITY ** First Quarter 12/31/86 to 03/31/87 210170 WATER (10) Second Quarter 03/31/87 to 06/30/87 3101100 Third Quarter 06/30/87 to 09/30/87 260180 Fourth Quarter 09/30/87 to 01/04/88 320180
** Optional samples. Oswego City Water samples are composites of twice per week grab samples.
TABE 4 00N NIRATIONS OF GAFMA DHTIERS IN SURFACE WNIER SAMPIFS - 1987 Results in thits of pCi/1 + 2 Sigma Station Code
- Nuclide January February March April May June OSWE00 SIFR4 Ra-226 112+61.9 <107 <103 <113 127+75.0 75.7+49.0 STATION I-131 <U.25 <0.37 <0.31 <0.30 (U.36 <0726 (08, 00NIROL) Cs-134 <4.49 <4.11 <3.78 <3.57 <4.71 <4.24 Cs-137 <4.64 <3.65 <4.76 <4.47 <4.62 <3.94 Zr-95 <12.2 <8.88 <10.3 <10.7 <11.7 <12.5 Nb-95 <6.15 <3.83 <5.64 <5.04 <5.29 <5.86 Co-58 <5.23 <5.07 <4.51 <4.59 <4.65 <4.12 Mn-54 <5.19 <4.25 <4.88 <4.88 <4.77 <4.38 Fe-59 <11.8 <8.68 <9.00 <8.88 <13.0 <8.51 2n-65 <8.64 <7.99 <8.97 <8.96 <10.2 <8.09 C0-60 <4.18 <5.73 <6.39 <4.74 <4.63 <4.44 K-40 267+59.7 <54.1 <53.2 <70.2 115+44.8 49.3+31.5 g Ba/I2-140 <T3.0 <7.46 <14.1 <11.3 <E.99 <12.5 FITZPA'IRICK Ra-226 130+53.8 <112 127461.6 <118 101+47.3 107468.6 (03, INIET) I-131 <U.29 <0.33 <D.33 <0.20 <U.47 <D.27 Cs-134 <3.72 <5.23 <4.75 <4.33 <4.41 <3.84 Cs-137 <3.56 <4.69 <4.94 <4.69 <4.98 <4.98 Zr-95 <9.31 <10.7 <13.6 <12.I' <10.2 <10.6 tb-95 <4.77 <4.60 <5.89 <6.71 <6.43 <5.65 00-58 <3.90 <6.12 <5.13 <4.67 <4.06 <4.14 Mn-54 <3.75 <5.79 <4.69 <4.37 <4.90 <5.46 Fe-59 <8.14 <11.6 <10.2 <12.9 <11.1 <10.1 Zn-65 <3.42 <7.41 <10.6 <11.3 <9.91 <10.3 C0-60 <3.13 <6.06 <4.50 <5.15 <5.14 <5.52 K-40 236+43.0 <63.8 272+54.3 33.4+31.7 <63.9 76.S+44.6 Ba/I2-140 <3.48 <10.3 <TO.7 <835 <11.0 <1U.7
.i
- Corresponds to sanple locations listed on Figure IA, Section VII.
4
TABE 4 (Continued) 00NCENIRATIONS OF C#fR EMITIERS IN SURFACE WNIER SAMPIES - 1987 Results in thits of pCi/1 + 2 Sigma Station Code
- Nuclide July August September October Noved>er Decerber OSWE00 STEAM Ra-226 97.0+44.2 86.7+39.4 106+78.6 83.4+48.4 <103 <84.4' STATION I-131 <0T28 <0T28 <D.25 <0T29 <0.25- <0.46 (08, 00NIROL) Cs-134 <2.96 <3.35 <4.50 <3.82 <3.54 <2.53 Cs-137 <3.40 <3.54 <4.10 <5.01 <3.69' <3.31 Zr-95 <8.29 <7.81 (12.7 <12.2 <10.10 (9.03 Nb-95 <4.04 <4.28 <5.27 <6.50 <4.55 <3.66 Co-58 <3.46 <3.46 <5.64 <5.08 <3.79 <3.57 M1-54 <3.23 <3.47 <4.34 <4.25 <3.66 <3.02 Fe-59 (7.33 <7.70 <12.3 <9.43 <7.23 <7.72 Zn-65 <6.54 <6.35 <10.1 <8.20 <6.45 <6.08 Co-60 <3.17 <2.71 <4.47 <3.95 <3.51 <2.80 K-40 223+42.8 206+36.0 259+59.4 230+50.8 210+40 99.7+33.1 U Ba/La-140 <T.03 <7.28 G.25 <B.33 <8 5 <8T64 FITZPATRICK Ra-226 117+47.1 110+46.3 54.1+38.1 109+56.1 113+40.8 <112 (03, INIET) I-131 <H.32 <U.28 <0T35 (U.32 <6.32 <0.44 Cs-134 <3.60 <3.06 <3.22 <4.28 <3.45 <4.54 Cs-137 <3.50 <3.29 <3.40 <4.10 <3.45 <4.69 Zr-95 <9.63 <8.08 <8.12 <11.5 <9.10 <10.9 Nb-95 <5.21 <3.92 <3.67 <5.26 <4.69 <5.34 Co-58 <3.% <3.63 <3.62 <4.81 <4.03 <4.79 th-54 <4.00 <3.17 <3.29 <3.88 <3.66 <4.26 Fe-59 <9.92 <6.28 <6.78 <10.9 <9.41 <9.68 Zn-65 <8.41 <7.08 <7.41 <8.03 <7.16 <10.4 Co-60 <3.49 <3.28 <3.04 <4.06 <3.23 <4.34 K-40 233+46.1 253+39.3 263+45.0 258+56.7 196+36.6 53.5443.4 Ba/Ta-140 -<B.42 6 .35 <3.47 <W.58 <B.17 <1T.0
- Corresponds to sartple locations listed on Figure IA, Section VII.
- - ~ - - . - _ ~ . .
TABLE 4 (Continued) CONCENIEATIONS OF GAPen DfITIERS IN SURFACE WWIER SAMPLES - 1987 Results in Chits of pCi/1,+ 2 Sigpia Station Code
- Nuclide January February March April May June NINE MIE Ra-226 137+58.3 98.2+42.9 <107 <117 <119 117+48.2 POINr I-131 <T1.5 <i7.9 <15.8 <13.0 <14.1 < 1'J. 8 UNIT 1** Cs-134 <3.37 <4.34 <4.41 <4.99 <4.65 <3.91 (09, INLET) Cs-137 <3.50 <4.47 <4.77 <4.55 <4.91 <4.46-Zr-95 <10.0 <12.9 <11.4 <12.9 <10.6 <11.7 Nb-95 <4.29 <5.67 <5.88 <7.11 <6.62 <3.07 Co-58 <3.85 <5.00 <5.15 <5.12 <6.03 <4.74 M1-54 <3.48 <4.58 <4.08 <5.23 <4.73 <4.82 Fe-59 <8.20 <11.8 <9.94 <11.8 <12.6 <10.7 Zn-65 <6.% <9.59 <9.67 <9.91 <12.7 <S.61 Co-60 <2.69 <4.52 <4.52 <5.15 <5.52 <5.88 K-40 212+42.2 <60.2 <45.6 <70.2 53.9+37.9 <60.1
% Ba/Ia-140 <7.04 <10.8 <10.9 <15.3 <1T.2 <12.2 NINE MIE Ra-226 142+67.7 <112 <124 <104 174+70.3 100+50.8 POINT I-131 <T3.1 <12.3 <15.5 <12. 7. <T4.8 <T4.9 UNIT 2** Cs-134 <3.56 <3.76 <4.90 <3.72 <4.60 <4.48 (11, IN ET) Cs-137 <3.47 <3.59 <4.81 (3.46 <4.94 <5.00 1 Zr-95 <9.91 <9.99 <12.0 <9.60 <11.9 <12.7 Nb-95 <4.39 <4.41 <5.95 <5.30 <5.31 <5.68 Co-58 <4.04 <5.32 <5.50 <5.57 <4.76 <5.11 Ph-54 <3.50 <3.42 <5.13 <3.99- <4.30. <4.35 Fe-59 <8.53 <3.80 <11.1 -<10.1 <11.1 (11.3 Zn-65 <7.48 <9.90 <10.9 (9.54 <11.4 <3.93 00-60 <3.35 <4.94 <4.34 <4.28 <4.79 <3.64 K-40 252+46.0 <64.2 143+46.3 <47.9 245+50.7 292+58.5 Ba/La-140 <B.86 <8.30 <T2.0 <8.19 <1T.4 <3- 36
- Corresponds to sanple locations listed on Figure IA, Section VII.
** Optional sarple location. Sanple not required by Technical Specifications.
TABE 4 (Continued) : 00NQNIRATIONS OF GAMM EMIT 1TRS IN SURFACE WNIER SAMPES --1987 Results in Units of pCi/112 Sigma Station Code
- Nuclide July August Septerober October November Decmber NINE MIE Ra-226 88.5+38.8 <116 <118 <115 - <126' <85.4 POINT I-131 < 1'J. 0 <13.1 <14.5 <16.8 <13.9 <11.4 LNI'l 1** Cs-134 <2.91 <4.04 <4.78 <4.43 <4.04 <2.86 (09, INIET) Cs-137 <3.16 <5.06 <4.69 <4.61 <4.41 <2.90 l Zr-95 <8.50 <12.7 <11.1 <13.7 <12.1 <7.62 Nb-95 <4.62 <5.53 <7.01 <5.23 <6.37 <3.94 i Co-58 <3.23 <4.94 <6.16 <4.26 <5.15 <3.68 i m-54 <3.28 <5.37 <4.69 <5.02 <3.31 <2.88 ;
Fe-59 <7.58 (10.5 (9.32 -<11.9 <11.6 <8.52 Zn-65 <5.90 <10.4 (8.73 <8.42 <10.3 <6.97 00-60 <3.04 <3.54 <5.78 <5.61 <4.06 <3.07 i K-40 227+39.3 <67.2 <54.0 <63.0 174+42.5 61.4+24.6 w Ba/Ia-140 <B.60 <10.5 <9.60 <12.6 <TO.3 <836 w NINE MILE Ra-226 88.9+41.2 50.0+40.0 <100 70.1+46.2 <126 75.5*38.0 POINT I-131 <1U.4 <975, <14.4 <li.2 <14.3 <1T.6 UNIT 2** Cs-134 <2.37 <3. 2.: <4.14 <3.46 <4.11 <3.44 (11, INIET) Cs-137 <2.48 <3.11 <4.41 <3.59 <4.41 <3.30 Zr-95 <6.17 <6.65 <11.2 <9.86 <10.1 <9.57 E-95 <3.41 <4.40 <5.43- <4.97 <5.90 <4.38 Co-58 <2.86 <4.08 <4.47 <3.29 <4.88 <4.01 m-54 <2.62 <2.99 <3.81 <3.62 <4.05 <3.21 Fe-59 <6.16 <8.72 <9.36 <7.91 <11.3 -<8.16 Zn-65 <5.32 <7.26 <9.00 <7.30 (9.45 <7.42 Co-60 <2.55 <3.61 <4.26 <3.73 <3.84 <3.30 K-40 31.8+16.3 51.9+22.9 <50.5 224+42.6 177446.0 250t42.7 Bana-140 <r16 <r02 <11.0 <3.00 <T1.0 <9762
- Corresponds to sa ple locations listed on Figure IA, Section VII.
** Optional smple location. Sm ple not required by Technical Specifications.
~
TABLE 4 (Contirmed) - CONCENIRATIONS OF C#9% D1ITIERS IN SURFACE WATER SAMPIES - 1987 d Results in thits of pCi/1 + 2 Sigma 'l 1 Station Code
- Nuclide January Febniary March April May . June OSWEDO CITY Ra-226 101+53.5 <114 111+65.J 86.0+42.8 153+59.8 <85.0 WATER ** I-131 <T6.1 <12.7 <T4.6 <17.1 <T6.0' <16.8 .
(10) Cs-134 <4.62 <4.73 <4.23 <4.28 <4.57 <3.05 Cs-137 <5.08 <5.25 <4.23 <4.91 <4.03 <3.07 Zr-95 <12.4 <12.7 <11.5 <12.0 <12.7 <10.1 Nb-95 <5.75 <6.33 <6.14 <5.56 <6.33 <5.03 Co-58 <5.39 <5.53 <4.77 <5.06 <5.13 <4.34 Mi-54 <5.04 <5.05 <3.95 <4.59 <4.41 <3.38 Fe-59 <11.3 <10.6 (10.6 <10.0 <12.8 <8.37 Zn-65 <8.17 <10.2 <12.2 <9.94 <9.27 <6.68 Co-60 <4.18 <5.72 <5.72 <6.06 <4.21 <4.16 K-40 292+60.9 <54.2 <49.6 (60.3 227+52.5 85.1+41.7: y Ba/La-140 <TO.6 <14.1 <5.60 <12.6 <T1.2 (9742
- Corresponds to sanple locations listed on Figure 1A, Section VII.
** Optional sanple location. Sanple not required by Technical Specifications.
f TABIE 4 (Continted) 00NCENIRATIONS OF C#9% DiLTIERS IN SURFACE WATER SAMPIIS - 1987 s Results in Units of pCi/1 + 2 Signa Station Code
- Nuclide July August Septenber October . November Decmber CSWEDO CITY Ra-226 88.3+25.8 99.9+74.1 108+47.8 119+51.7 76.9+39.6 <74.3' WNIER** I-131 < C73 <13.1 <T1.7 (ID.6 .<9752 '<11.5 (10) Cs-134 <1.51 .<3.92 <3.24 <3.62 <3.27 <3. 4 2 '
Cs-137 <1.57 <4.22 <3.33 <3.59 <3.28 <2.69 Zr-95 <4.36 <11.1' <8.43 <9.49 <7.39 <9.23 Nb-95 <2.20 <5.37 <3.81 <4.41 <4.23 <3. % Co-58 <1,79 <4.79 <3.26 <4.16 <3.40 <3.79 Hn-54 <1.55 (4.49 <3.05 <3.13 <3.36 <3.18 Fe-59 <4.01 <10.4 <6.44 <7.83 <6.90 <7.39 Zn-65 <3.19 <8.53 <7.20 <5.74 <4.97 <6.87 C0-60 <1.57 <3.84 <2.78 <3.04 <3.61 <3.72 w 2-140 6 b < b 7 2 5 40
- Corresponds to sanple locations listed on Figure 1A, Section VII.
** Optional sanple location. Sanple not required by Technical Specifications.
d
i TABLE 5 , ENVIRONMENTALAIRBORNEPANkC ATESkMPLES-0FFSITESTATIONS GROSS BETA ACTIVITY pC1/m*3 1 2 Sigma LOCATION WEEK END DATE R1 R2 R3 R4 R5 87/01/06 0.020 0.003 0.025 0.003 0.020 0.003 0.018 0.003 0.023 0.003 87/01/13 0.020 0.003 0.018 0.003 0.023 0.003 0.015 0.003 0.019 0.003 87/01/20 0.022 0.003 0.025 0.003 0.024 0.003 0.023 0.003 0.025 0.003 87/01/27 0.020 0.003 0.024 0.003 0.019 0.003 0.024 0.003 0.014 0.003 87/02/03 0.032 0.004 0.030 0.004 0.030 0.004 0.027 0.004 0.033 0.004 87/02/10 0.024 0.003 0.021 0.003 0.022 0.003 0.023 0.003 0.025 0.003 87/02/17 0.025 0.003 0.027 0.003 0.027 0.003 0.025 0.003 0.026 0.003 87/02/24 0.018 0.003 0.020 0.003 0.022 0.003 0.021 0.003 0.022 0.003 87/03/03 0.009 0.002 0.011 0.003 0.010 0.002 0.012 0.003 0.013 0.003 87/03/10 0.025 0.003 0.023 0.003 0.026 0.003 0.028 0.003 0.028 0.003 87/03/17 0.028 0.004 0.028 0.004 0.029 0.004 0.028 0.004 0.029 0.004 87/03/24 0.020 0.003 0.019 0.003 0.018 0.003 0.015 0.003 0.012 0.002 87/03/31 0.019 0.003 0.020 0.003 0.017 0.003 0.019 0.003 0.018 0.003 ' 87/04/07 0.013 0.003 0.013 0.003 0.010 0.002 0.012 0.002 0.014 0.003 87/04/14 0.021 0.003 0.022 0.003 0.021 0.003 0.022 0.003 0.024 0.003 87/04/21 0.016 0.003 0.015 0.003 0.014 0.003 0.015 0.003 0.016 0.003 87/04/28 0.016 0.003 0.015 0.003 0.018 0.003 0.014 0.003 0.017 0.003 87/05/05 0.020 0.003 0.018 0.003 0.020 0.003 0.021 0.003 0.022 0.003 87/05/12 0.030 0.003 0.028 0.003 0.029 0.003 0.028 0.003 0.029 0.003 87/05/19 0.015 0.003 0.016 0.003 0.018 0.003 0.016 0.003 0.019 0.003 87/05/26 0.013 0.002 0.011 0.002 0.014 0.003 0.013 0.002 0.015 0.003 87/06/02 0.034 0.004 0.036 0.004 0.035 0.004 0.035 0.004 0.034 0.004 87/06/09 0.022 0.003 0.022 0.003 0.021 0.003 0.020 0.003 0.019 0.003 87/06/16 0.027 0.003 0.027 0.003 0.023 0.003 0.026 0.003 0.022 0.003
- 87/06/23 0.018 0.003 0.020 0.003 0.019 .003 0.019 0.003 0.019 0.003 87/06/30 0.026 .003 0.025 0.003 0.030 .003 0.026 0.003 0.028 0.006 87/07/07 0.017 .004 0.015 0.004 0.017 0.004 0.015 0.004 0.015 0.005 87/07/14 0.026 0.003 0.028 0.003 0.025 0.003 0.025 0.003 0.028 0.004 87/07/22 0.019 0.003 0.017 0.002 0.019 0.003 0.016 0.002 0.019 0.003 87/07/28 0.025 0.003 0.029 0.004 0.026 0.003 0.028 0.004 0.031 0.004 87/08/04 0.020 0.003 0.018 0.003 0.017 0.003 0.020 0.003 0.014 0.003 87/08/11 0.019 0.003 0.020 0.003 0.018 0.003 0.019 0.003 0.022 0.003 87/08/18 0.026 0.003 0.023 0.003 0.024 0.003 0.024 0.003 0.025 0.003 87/88/25 0.016 0.003 0.018 0.003 0.021 0.003 0.019 0.003 0.017 0.003 87/09/01 0.016 0.002 0.016 0.003 0.017 0.003 0.017 0.003 0.014 0.002 )
87/09/08 0.017 0.003 0.017 0.003 0.020 0.003 0.016 0.003 0.018 0.003 87/09/15 0.017 0.003 0.018 0.003 0.020 0.003 0.016 0.003 0.016 0.003 87/09/22 0.011 0.902 0.012 0.002 0.011 0.002 0.014 0.003 0.012 0.002 87/09/29 0.022 0.003 0.022 0.003 0.022 0.003 0.024 0.003 0.023 0.003 87/10/06 0.021 0.003 0.022 0.003 0.022 0.003 0.018 0.003 0.019 0.003 87/10/13 0.020 0.003 0.023 0.003 0.020 0.003 0.020 0.003 0.019 0.003 67/10/20 0.040 0.004 0.037 0.004 0.036 0.004 0.039 0.004 0.037 0.004 87/10/27 0.024 0.003 0.026 0.003 0.026 0.003 0.027 0.003 0.023 0.003 87/11/03 0.022 0.003 0.023 0.003 0.021 0.003 0.024 0.003 0.017 0.004 87/11/10 0.028 0.003 0.032 0.003 0.029 0.003 0.028 0.003 0.026 0.003 87/11/17 0.026 0.003 0.027 0.003 0.024 0.003 0.027 0.003 0.027 0.003 87/11/24 x 0.018 0.003 0.017 0.003 0.016 0.003 0.015 0.003 0.020 0.003 " 87/12/01 0.015 0.002 0.016 0.002 0.015 0.002 0.015 0.002 0.012 0.002 87/12/08 0.011 0.002 0.009 0.002 0.010 0.002 0.009 0.002 0.009 0.002 87/12/15 0.019 0.002 0.017 0.002 0.016 0.002 0.016 0.002 0.017 0.002 87/12/22 0.016 0.002 0.015 0.002 0.015 0.002 0.016 0.002 0.014+0.002 87/12/29 0.023 0.003 0.023 0.003 0.023 0.003 0.024 0.003 0.023E0.003 36
t 9 TABLE 5 (Continued) NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - 0FF SITE STATIONS GROSS BETA ACTIVIT) pC1/m'3 1 2 Sigma LOCATION WEEK END DATE 02 E F G 87/01/06 0.026 0.004 0.027 0.003 0.027 0.003 0.028 0.004 87/01/13 0.022 0.004 0.022 0.003 0.020 0.003 0.019 0.003 87/01/20 0.018 0.003 0.020 0.033 0.019 0.003 0.027 0.004 87/01/27 0.020 0.003 0.021 0.003 0.025 0.003 0.019 0.003 87/02/03 0.025 0.004 0.027 0.003 0.029 0.003 0.026 0.004 87/02/10 0.022 0.003 0.018 0.003 0.020 0.003 0.025 0.003 87/02/17 0.021 0.003 0.025 0.003 0.022 0.003 0.025 0.003 87/02/24 0.020 0.003 0.022 0.003 0.024 0.003 0.022 0.003 87/03/03 0.012 0.003 0.010 0.002 0.010 0.002 0.01t+0.003 87/03/10 0.024 0.003 0.025 0.003 0.027 0.003 0.023 0.003 87/03/17 0.025 0.004 0.026 0.003 0.030 0.004 0.028 0.004 87/03/24 0.013 0.003 0.013 0.002 0.015 0.003 0.014 0.003 87/03/31 0.017 0.003 0.019 0.003 0.021 0.003 0.021I0.003 87/04/07 0.012 0.003 0.013 0.003 0.013 0.002 0.014+0.003 87/04/14 0.015 0.003 0.021 0.003 0.021 0.003 0.022 0.003 87/04/21 0.011 0.002 0.016 0.003 0.015 0.003 0.014 0.003 87/04/28 0.013 0.003 0.016 0.003 0.020 0.003 0.012 0.003 87/05/05 0.024 0.003 0.021 0.003 0.023 0.003 0.021 0.003 87/05/12 0.026 0.003 0.026 0.003 0.030 0.004 0.028 .004 87/05/19 0.016 0.003 0.014 0.002 0.016 0.003 0.019 0.003 87/05/26 0.014 0.002 0.015 0.003 0.012 0.002 0.015 0.003 87/06/02 0.037 0.004 0.032 0.004 0.031 0.003 0.034 0.004 87/06/09 0.021 0.003 0.020 0.003 0.019 0.003 0.020 0.003 87/06/16 0.027 0.003 0.026 0.003 0.024 0.003 0.023 0.003 87/06/23 0.020 0.003 0.019 0.003 0.021 0.003 0.022 0.003 87/06/30 0.025 0.003 0.028 0.003 0.026 0.003 0.029 0.003 87/07/07 0.016 0.004 0.012 0.004 0.014 0.004 0.016 0.004 87/07/14 0.026 0.003 0.027 0.003 0.026 0.003 0.026 0.003 87/07/22 0.018 0.002 0.019 0.003 0.018 0.002 0.022 0.003 87/07/28 0.027 0.003 0.027 0.003 0.030 0.004 0.029 0.004 87/08/04 0.018 0.003 0.019 0.003 0.022 0.003 0.020 0.003 87/98/11 0.019 0.003 0.019 0.003 0.019 0.003 0.019 0.003 87/08/18 0.027 0.003 0.025 0.003 0.022 0.003 0.022 0.003 87/98/25 0.023 0.003 0.021 0.003 0.021 0.003 0.020 0.003 87/09/01 0.020 0.003 0.017 0.003 0.015 0.002 0.015 0.002 87/09/08 0.015 0.002 0.013 0.002 0.01E 0.002 0.016 0.003 87/09/15 0.018 0.003 0.020 0.003 0.020 0.003 0.016 0.003 87/09/22 0.010 0.002 0.011 0.002 0.010 0.002 0.012 0.002 87/09/29 0.024 0.003 0.021 0.003 0.024 0.003 0.022 0.003 87/10/06 0.019 0.003 0.020 0.003 0.018 0.003 0.020 0.003 87/10/13 0.021 0.003 0.020 0.003 0.017 0.003 0.022 0.003 87/10/10 0.041 0.004 0.034 0.003 0.035 0.004 0.037 0.004 87/10/27 0.026 0.003 0.028 0.003 0.024 0.003 0.028 0.003 87/11/03 0.022 0.003 0.018 0.003 0.021 0.003 0.022 0.003 87/11/10 0.029 0.003 0.028 0.003 0.026 0.003 0.028 0.003 87/11/17 0.026 0.003 0.027 0.003 0.026 0.003 0.028 0.003 87/11/24 0.018 0.003 0.016 0.003 0.018 0.003 0.019 0.003 87/12/01 0.014 0.002 0.015 0.002 0.016 0.002 0.013 0.002 87/12/08 0.010 0.002 0.009 0.002 0.009 0.002 0.008 0.002 87/12/15 0.015 0.002 0.016 0.002 0.016 0.002 0.01470.002 87/12/22 0.015 0.002 0.015 0.002 0.013 0.002 0.01470.002 87/12/29 0.023 0.002 0.020 0.002 0.022 0.002 0.02210.002 37
TABLE S NMP/JAF SITE ENVIRONMENTAL AIRBORNE PARTICULATE SAMPLES - ON SITE STATIONS GROSS BETA ACTIVITY pC1/m*3 1 2 Sigma WEEK END LOCATION DATE 01
............... .......... .G......... H I
..............J K 87/01/05 .023 .003 ...................
87/01/12 .020 .003 .025 .003 .025 .003 .024 .003 .024 .003
.021 .003 .020 .003 .024 .003 87/01/19 .022 .003 .024 .003 .020 .003 .02) .003 .016 .003 .021 .003 87/01/26 .020 .004 .018 .003 .019 .003 .020 .003 .019 .003
.021 .003 87/02/02 .029 .003 .031 .004 .029 .003 .029 .020 .003 .022 .003 .023 .003 87/02/09 .022 .003 .020 .003 .023 .003 .025 .004 .022 .003 .036 .004
.003 .022 .003 .024 87/02/17 .024 .003 .026 .003 .026 .004 .003 87/02/23 .017 .003 .020 .003 .020 .004 .057 .023 .026 .004 .030 .004
.023 .004 .020 .004 .027 .005 87/03/02 .013 .002 .011 .002 .011 .002 .012 .002 .010 .002 .015 .003 87/03/09 .025 .003 .027 .003 .022 87/03/16 .027 .003 .032 .004 .024 .003 .025 .003 .021
.003 .025 .003 .003 .028 .003
.031 .004 .025 .003 87/03/23 .020 .003 .022 .003 .017 .003 .017 .003 .016 87/03/30 87/04/06 .020 .003 .017 .003 .018 .003 .018 .004 .018 .003
.012 .002 .013 .003 .014 .003 .01E
.017 .003
.003 .017 .003
.003 .015 .003 .013 .002 87/04/13 .019 .003 87/04/20 .020 .003 .019 .003 .018 .003 .017 .003 .018
.019 .003 .019 .003 .019 .003 .015 .002
.003 .019 .003 .018 .003 87/04/27 .017 .003 .016 .003 .013 .003 .017 .003 .017 .003 .019 .003 87/05/04 .023 .003 .019 .003 87/05/11 .026 .003 .025 .021.003
.003 .026 .003 .022 .003 .023 .003 .024 .003 87/05/18 .023 .003 .022 .003 .017 .003 .022 .028 .005 .022 .003 .024 .003 87/05/26 .013 .002 .012 .002 .013 .002 .004 .019 .003 .021 .003 87/06/01 .031 .004 .024 .004 .012 .003 .027 .011 .002 .014 .002 .011 .002 87/06/08 .025 .003 .020 .003 .023 .003 .021 .004 .003
.031 .004 .030 .004 87/06/15 .027 .003 .023 .003 .008 .002 .023 .003 .016 .002 .022 .003 .023 .003 87/06/22 .023 .003 .023 .003 .023 .003 .023 .003 .023 .003 .018 .022 .003 87/06/29 .021 .003 .018 .003 .023 .003 .003 87/07/06 ,020 .004 .011 .004 .018 .005 .019 .003 .021 .003 .021 .003 87/07/13 .021 .003 .019 .003 .024 .003 .017 .017 .004 .016 .004 .018 .004 87/07/20 .023 .003 .021 .003 .022 .003 .019 .002 .019 .003 .016 .002
.003 .020 .003 .018 .003 87/07/27 .027 .003 .026 .003 .026 .003 .031 .004 87/08/03 .018 .003 .018 .003 .016 .003 .017 .003 .029 .003 .028 .003 87/08/10 .021 .003 . 016 .003 .018 .003 .016 .003 .015 .002 87/08/17 .027 .003 " 024 .003 .023 .003 .018 .003 .022 .003 .017 .002 87/08/24 .020 .003 .620 .003 .018 .003 .019 .025 .003 .026 .003 .026 .003 87/08/31 .618 .003 .016 .003 .019 .003 .020 .003
.003 .009 .007 .013 .002 .018 .003 .016 .002 87/09/08 .018 .002 87/09/14 .015 .003 .017 .013
.002 .016 .003 .015 .002 .016 .002
.003 .003 .015 .003 .016 .003 .014 .002 87/09/21 .016 .002 .013 .002 .014 .013 .002 .012 .002 .014 .002 .012 .002 .012 .002 87/09/28 .017 .003 .016 .003 .016 87/10/05 .025 .003 .022 .003 .024 .003 .003 .022 .020.003.003 .016 .003 .015 .002 87/10/13 .021 .003 .021 .003 .018 .003 .024 .003 .022 .003
.021 .003 .018 .002 .018 .002 87/10/19 .035 .004 .037 .004 .035 .004 .040 .004 .035 .004 .036 .004 87/10/26 .029 ,003 .027 .003 .028 .003
.027 .003 .027 .003 .022 87/11/02 .019 .003 .019 .003 .018 .003 .024 87/11/09 .035 .003 .036 .004 .031 .003 .036 .004 .003 .021 .003 .020 .003 .003 87/11/16 .025 .003 .024 .003 .025 .003 .024 .003 .031 .003 .034 .003 87/II/23 .019 .003 .019 .003 .020 .003 .019 .003 .024 .003 .024 .003 87/11/30 .018 .002 .019 .002 .018 .002 .017 .002 .018 .003 .018 .003 87/12/07 .009 .002 .009 .002 .011 .016 .002 .019 .002 87/12/14 .014+.002 .015 .002 .018 .002 .014 .002 .011 .002 .011
.002 .017 .002 .015 .002 .014 .002 .002 87/12/21 .012+ .015 .002 .014+ .015 .002 .014 87/12/28 .0211002 002 .0211 003 .023I 002 003 .026 .004 .017I.002 .016 .002
.002 .024 .003 38
TABLE 7 NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - CFF SITE STATIONS I-131 ACTIVITY pC1/n*3 1 2 sigma LOCATION WEEK END DATE
...........-.................................R3 87/01/06 R1 (0.009 R2 R4 R5-
<0.012 <0.009 <0.014 <0.012 87/01/13 <0.009 <0.008 <0.008 <0.006 87/01/20 -<0.010 (0.016 <0.014 87/01/27 <0.015 <0.010 <0.013
<0.011 <0.011 <0.015 <0.013 87/02/03 (0.015 (0.014
<0.014 (0.013 <0.013 <0.013 87/02/10 <0.012 (0.011 /2.011 (0.008 87/02/17 (0.014 (0.013 <0.011 87/02/24 .0.014 <0.008 (0.003 (0.012 <0.013 <0.012 (0.012 <0.010 87/03/03 <0.009 <0.011 <0.012 <0.016 87/03/10 (0.009 <0.013 <0.010 87/03/17 (0.005 s0.012 <0.010 <0.013
<0.013 <0.011 (0.015 <0.013 87/03/24 (0.010 (0.012 (0.009 (0.009 87/03/31 (0.010 <0.007 <0.010 '
87/04/07 (0.011 <0.014 (0.010 ' (0.015 <0.009 <0.011 <0.006 <0.012 87/04/14 (0.008 <0.007 <0.014 87/04/21 (0.012 <0.012 <0.014
<0.012 <0.015 <0.008 <0.013 87/04/28 <0.011 (0.009 (0.008 <0.010 87/05/05 (0.011 <0.009 <0.014 87/05/12 <0.009 (0.011 (0.007 (0.012 (0.009 <0.010 (0.013 <0.012 87/05/19 (0.012 (0.009 <0.013 <0.012 87/05/26 <0.010 <0.014 <0.013 87/06/02 <0.006 <0.004 (0.009 (0.010 (0.009 <0.008 <0.010 (0.009 87/06/09 (0.012 (0.017 (0.013 <0.009 87/06/16 (0.010 <0.013 <0.012 87/06/23 (0.016 <0,015 <0.012 i
(0.014 (0.014 (0.006 <0.014 (0.013 87/06/30 (0.008 (0.009 <0.006 <0.010 87/07/07 (0.014 (0.009 <0.026 87/07/14 <0.009 (0.012 <0.018 (0.009 <0.011 <0.014 <0.012 <0.018 87/07/22 <0.011 (0.014 <0.010 <0.007 87/07/28 (0.012 <0.016 <0.015 87/08/04 (0.014 (0.012 <0.016 (0.009 <0.013 <0.011 <0.012 <u.010 87/08/11 <0.013 <0.010 (0.012 87/08/18 <0.010 <0.011 <0.009
<0.009 (0.013 (0.008 <0.007 87/08/25 (0.011 (0.009 (0.010 <0.008 87/09/01 (0.012 <0.009 (0.012 r 87/09/08 0.011+0.006 (0.011 <0.008 (0.007 0.018+0.008 <0.009 <0.011 <0.010 87/09/15 70.010 70.010 <0.010 87/09/22 <0.005 <0.013 (0.010
<0.009 (0.011 <0.009 87/09/29 <0.012 <0.013 <0.012 <0.013 (0.010 87/10/06 (0.011 (0.010 <0.013 87/10/13 <0.013 <0.008 <0.010
<0.008 <0.009 <0.010 <0.008 i
87/10/20 <0.011 (0.009 <0.009 87/10/27 <0.008 <0.011 <0.012 (0.009 (0.011 (0.011 <0.012 87/11/03 <0.009 <0.011 <0.013 87/11/10 <0.011 <0.010 <0.023 (0.010 <0.010 <0.009 <0.010 <0.013 87/11/17 <0.008 <0.011 <0.007 87/11/24 (0.008 <0.006 <0.010 87/12/01 (0.009 (0.010 <0.010 <0.012
<0.009 <0.006 <0.006 <0.008 87/12/08 <0.005 <0.009 <0.008 07/12/15 <0.010 <0.008 (0.010
<0.009 (0.007 <0.009 <0.010 87/12/22 (0.010 <0.006 (0.008 (0.008 '
87/12/29 (0.009 <0.008 (0.009 (0.008 (0.008 <0.009 <0.004 39 t r
TABLE 7 (Continued) NMP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - 0FF SITE STATIONS I-131 ACTIVITY pC1/m'3 1 2 sigma LOCATION WEEK END OATE 02 E F G 87/01/06 <0.005 (0.012 (0.012 <0.011 l 87/01/13 <0.017 <0.013 <0.008 <0.011 87/01/20 (0.016 <0.010 <0.013 (0.014 87/01/27 <0.014 <0.009 <0.012 <0.016 87/02/03 (0.014 <0.012 <0.013 <0.022 87/02/10 (0.014 <0.013 <0.009 <0.011 87/02/17 <0.013 <0.011 <0.010 <0.013 87/02/2( (0.012 <0.010 <0.010 (0.013 87/03/03 <0.010 <0.010 (0.009 <0.013 i 87/03/10 (0.013 <0.012 <0.008 <0.013 87/03/17 <0.014 <0.012 (0.010 (0.011 87/03/24 (0.011 (0.012 <0.000 (0.014 87/03/31 <0.010 <0.014 (0.011 (0.020 87/04/07 <0.012 <0.010 <0.013 (0.009 87/04/14 <0.011 <0.016 (0.012 <0.012 87/04/21 (0.008 <0.011 <0.009 (0.011 87/04/28 (0.012 <0.006 <0.011 <0.008 87/05/05 (0.013 <0.009 <0.008 <0.010 87/05/12 (0.009 <0.013 <0.011 <0.012 87/05/19 (0.013 <0.010 (0.009 (0.011 87/05/26 (0.008 (0.010 (0.011 <0.013 ~ '4 87/06/02 (0.011 (0.010 (0.011 (0.015 87/06/09 <0.009 <0.012 (0.013 <0.014 87/06/16 (0.011 (0.014 <0.006 (0.011 87/06/23 (0.013 <0.011 (0.013 (0.012 87/06/30 (0.007 <0.015 (0.011 <0.012 87/07/07 <0.011 <0.011 (0.010 (0.012 87/07/14 (0.008 (0.007 (0.011 <0.013 87/07/22 (0.009 (0.012 (0.012 <0.011 87/07/28 <0.010 <0.012 <0.014 <0.013 87/08/04 (0.009 <0.010 (0.011 (0.011 87/08/11 (0.010 <0.013 (0.012 (0.012 87/08/18 <0.009 <0.011 (0.009 <0.009 87/98/25 <0.013 <0.010 <0.011 <0.011 87/09/01 <0.010 (0.012 (0.010 <0.007 87/09/08 (0.008 <0.008 <0.009 (0.011 87/09/15 (0.010 <0.013 (0.009 <0.011 87/09/22 <0.007 <0.009 <0.011 (0.012 87/09/29 <0.010 <0.010 <0.008 <0.011 07/10/06 <0.011 <0.010 <0.014 (0,013 87/10/13 (0.009 <0.009 <0.011 (0.010 87/10/20 (0.010 (0.012 <0.010 (0.012 87/10/27 <0.008 <0.008 <0.012 <0.009 87/11/03 <0.007 <0.012 (0.011 <0.016 87/11/10 (0.006 '9,007 (0.010 <0.010 87/11/17 <0.008 <0.010 <0.012 <0.008 87/11/24 (0.010 (0.009 (0.008 <0.010 87/12/01 <0.008 <0.009 (0.005 <0.007 87/12/08 (0.007 <0.008 <0.004 <0.009 87/12/15 <0.008 <0.008 <0.008 <0.007 87/12/22 (0.009 <0.007 <0.007 <0.008 87/12/29 (0.008 <0.007 <0.004 <0.009 40
TABLE 8 NNP/JAF SITE ENVIRONMENTAL CHARCOAL CARTRIDGE SAMPLES - ON SITE STATIONS I-131 ACTIVITY pC1/n*3 1 2 signa LOCATION WEEK END DATE D1 G I
..................__......................____...............J 87/01/05 (0.011 <0.014 H K
<0.009 <0.013 (0.007 <0.010 87/01/12 (0.013 (0.010 (0.010 <0.011 <0.010 <0.014 87/01/19 <0.010 (0.015 <0.011 (0.014 <0.017 <0.007 87/01/26 <0.022 (0.013 (0.011 (0.013 (0.009 <0.015 87/02/02 (0.011 <0.014 <0.011 <0.013 <0.016 <0.017 87/02/09 (0.013 (0.006 <0.011 <0.011 <0.013 <0.012.
87/02/17 (0.009 <0.012 <0.015 <0.030 <0.020 <0.010 87/02/23 <0.010 <0.011 <0.009 <0.013 <0.010 (0.012 87/03/02 (0.009 <0.012 <0.008 (0.011 <0.012 <0.009
'7/03/09 <0.009 <0.015 (0.012 <0.010 (0.011 (0.011 87/03/16 (0.010 (0.009 (0.017 <0.009 <0.006 <0.011 87/03/23 (0.013 <0.012 <0.011 <0.017 <0.010 (0.010 87/03/30 <0.015 <0.012 <0.011 <0.022 <0.009 <0.011 87/04/06 <0.010 (0.010 <0.014 (0.014 (0.011 <0.008 87/04/13 <0.006 <0.011 <0.013 <0.011 <0.009 <0.013 87/04/20 (0.009 (0.013 (0.012 <0.009 <0.013 <0.007 87/04/27 <0.009 (0.013 <0.016 <0.009 (0.009 <0.005 87/05/04 (0.008 (0.011 (0.009 <0.011 (0.010 (0.009 87/05/11 (0.014 <0.008 (0.010 (0.021 <0.013 <0.009 87/05/18 <0.012 (0.008 (0.012 (0.120 (0.007 (0.009 87/05/26 <0.010 (0.008 <0.009 (0.010 <0.007 (0.007 87/06/01 (0.009 <0.011 (0.012 (0.009 <0.015 <0.011 87/06/08 <0.012 <0.013 <0.016 (0.012 <0.018 (0.012 87/06/15 (0.013 <0.013 (0.018 <0.013 (0.013 <0.011 87/06/22 <0.013 (0.012 <0.016 <0.009 (0.011 <0.010 87/06/29 (0.010 (0.014 <0.011 <0.010 (0.008 (0.009 87/07/06 (0.012 (0.010 <0.014 (0.010 (0.009 <0.012 87/07/13 (0.010 (0.012 (0.010 <0.012 (0.013 (0.011 87/07/20 <0.010 (0.011 (0.011 (0.008 <0.009 <0.013 87/07/27 <0.012 (0.011 (0.012 <0.013 <0.00S (0.010 87/08/03 <0.010 <0.012 <0.010 (0.012 (0.011 <0.011 87/08/10 (0.006 (0.014 (0.012 (0.013 (0.010 (0.011 87/08/17 <0.011 <0.016 (0.010 (0.014 <0.011 <0.013 87/08/24 <0.012 <0.013 (0.013 (0.022 <0.004 (0.008 87/08/31 <0.011 <0.011 <0.045 <0.011 <0.009 <0.006 07/09/08 (0.010 (0.012 <0.020 .016+.009 .061+.014 (0.014 87/09/14 (0.012 (0.001 (0.010 <5.015 <B.012 <0.014 87/09/21 <0.010 (0.011 (0.008 <0.008 <0.010 (0.010 87/09/28 <0.013 <0.009 (0.013 .000+.006 (0.012 <0.008 87/10/05 (0.007 (0.008 (0.010 <B.009 <0.010 <0.010 87/10/13 (0.010 (0.007 <0.008 <0.009 <0.010 (0.010 87/10/19 <0.012 <0.009 (0.013 (0.011 <0.013 <0.013 87/10/26 (0.011 <0.010 <0.000 (0.010 (0.012 <0.009 87/11/02 <0.010 (0.011 (0.011 <0.007 <0.010 <0.010 87/11/09 <0.008 (0.011 (0.013 <0.014 <0.009 <0.012 87/11/16 <0.009 <0.008 <0.011 (0.010 <0.010 <0.015 87/11/23 <0.005 (0.012 <0.011 <0.009 <0.011 <0.009 87/11/30 <0.010 (0.009 <0.009 <0.010 (0.009 (0.010 87/12/07 <0.006 (0.008 <0.014 <0.009 <0.013 (0.006 87/12/14 (0.006 (0.007 (0.012 <0.009 (0.010 <0.004 87/12/21 <0.007 (0.009 <0.008 (0.011 <0.010 <0.009 87/12/28 (0.008 <0.008 <0.009 <0.017 <0.013 (0.010 41 swa w.
~ ~ ~
TXBIE 9 CONCENIRATIONS OF C#9% DfITIERS IN MNIHLY OCDf0SI'IES OF JAF AIR PARTICUIAIE SAMPIES 1987 Results in Units of 10~2 pC1/m2 ,+ 2 signa Nuclides January February March April May June R1 Onsut CCEPOSITE Ce-144 <6.49 <6.12 <6.37 <5.89 <5.72 <8.12 Ce-141 <2.12 <1.90 <2.09 <2.08 <1.89 <2.81 Be-7 93.3 + 16.8 13? + 23.1 131 + 21.8 157 + 21.8 162 +-24.9- .188 + 27.2 Ru-103 . <C48 <2741 <C% <C56 <2T19 <2T55 Cs-134 <1.54 <1.27 <1.53 <1.10 <1.34 <1.57 Cs-137 <1.23 <1.27 <0.87 <1.39 <1.48 <1. 54 ' Zr-95 <2.57 <4.18 <3.84 <3.32 <2.18 <4.58 Nb-95 <1.49 <2.06 <1.74 <1.34 <2.16 <2.07 Co-58 <1.39 <1. 86 ' <1.72 <0.96 <1.49 <1.82 m-54 <1.29 <1.67 <1.45 <1.32 <0.95 <0.86 Co-60 <1.44 <2.69 <2.10 <1.76 <2.19 <1.65 K-40 53.7 + 19.2 <26.3 <31.6 15.2+11.3 -
<26.2 <36.4
- Ra-226
" <2T.2 <2.59 <31.3 <2T.6 (25.8 <35.4 Others <1lD <UD <IlD <1lB <UD <UD R2 OFFSTIE OCNPOSITE Ce-144 <6.51 <6.26 <7.00 <5.26 <6.93 <8.03 Ce-141 <2.24 <2.62 <2.71 <1.90 <2 48 <2.91 Be-7 101 + 16.0 122 + 22.4 136 + 25.7 169 + 24.3 133 . 22.8 153 + 22.8 Ru-103 <C74 <2T02 <2T16 <C53 <C99 <C80 Cs-134 <1.34 <1.71 <1.52 <1.20 <1.59 <1.59 Cs-137 <1.36 <1.70 <1.03 <1.33 <1.73 <1.35 Zr-95 <3.46 <3.94 <4.48 <3.99 <3.62 <2.42 hb-95 <1.63 <1.77 <2.99 <1.83 <2.04 <2.45 Co-58 <1.19 <1.88 <2.46 <1.56 <1.13 <2.07 m-54 <1.44 <1.92 <1.63 <1.63 <1.57 <1.83 Co.60 <1.42 <2.66 <1.64 <0.87 <2.46 <1.12 K-40 63.9 + 18.4 20.7 + 15.6 23.3+17.5 <27.8 36.4 + 22.4 58.3 + 23.5 Ra-226 22.5 T 12.5 <27.8 <2E.5 <22.1 <29.9 <3T.4 Others (Ilb <UD (UD <UD <UD <llD I
TAME 9 (Cmtinued) CONCENIRATIONS OF C#fR Df1 TIERS IN M]tfDEX CWPOSI'1ES OF JAF AIR PARTICUULTE SMFIIS '
. 1987 Results in thits of 10 3 pCi/m3 + 2 siggn Nuclides January February N rch April my Jtme R3 OFFSITE OmPOSITE Ce-144 <6.87 <7.10 <6.79 <7.37 <8.55 <8.79 Ce-141 <2.22 <2.40 <2.25 <2.64 <2.70 <3.06 Be-7 102 + 17.2 127 + 23.2 143 + 23.9 171 + 24.1 135 + 21.9 170 + 24.1 Ru-103 <C83 <2727 <C48 <2700 <C91 <2708 Cs-134 <1.47 <1.71 <1.23 <1.71 <1.87 <1.41 Cs-137 <1.32 <1.36 <1.44 <1.74 . <1.55 <1.53 Zr-95 <4.31 <3.39 <4.49 <3.98 <3.89 <4.89 Nb-95 <2.04 <2.02 <1.37 <2.14 <2.15 <2.18 00-58 <1.93 <1.41 <1.24 <1.28 <1.66 <1.70 m-54 <1.39 <1.47 <1.94 <1.67 <1.84 <1.29 00-60 <1.55 <2.05 <2.05 <0.69 <0.83 <2.17 K-40 50.5 + 21.4 <33.4 <28.8 52.3 + 20.7 46.2 + 21.5 57.3 + 22.7
^ Pa-226 18.4 T 11.3 <27.8 <31.7 21.0 T 13.1 <3T.6 <37.1
" Others (ID <ILD <1lD <ID (Ilh <IlD R4 OFr uit O WPOSITE Ce-144 <6.57 <6.41 <7.41 <6.37 <4.79 <8.90 Ce-141 <2.13 <2.20 <2.48 <2.41 .<1.95 <2.89 Be-7 107 + 17.1 100 + 20.3 147 + 24.2 159 + 24.0 161 + 25.2 1% + 30.2 Ru-103 <C56 <C86 <C95 <C85 <C% <C56 Cs-134 <1.29 <1.44 <1.78 <1.20 <1.56 <1.76 Cs-137 <1.12 <1.31 <1.92 <1.19 <1.30 <1.30 Zr-95 <3.81 <5.35 <4.44 <4.51 <3.59 <4.04 Nb-95 <1.72 <2.84 <1.98 <1.86 <1.70 <2.36 Co-58 <1.40 <1.59 <1.98 <1.78 <1.34 <2.18 m-54 <1.12 <1.91 <1.63 <1.34 <1.57 <1.42 Co-60 <1.09 <2.01 <1.18 <1.36 <1.79 <0.99 K-40 41.2 + 15.9 <30.2 <17.8 38.4 + 18.2 <32.2 40.7 + 23.1
! Ra-226 15.1 T 9.70 <27.7 24.7 + 14.9 50.9 T 24.5 <29.6 <3T.2 Others <lD (IJD <ID (ID <IJD (IJD
mr. , g w ;, y - - 00NCDTIRATIONS OF cal 4% DfITIERS IN P0NIHLY COMPOSITES - ' OF JAF AIR PATI'ICUIATE SAMPES
'^~
1987 Results in thits of 10 3 pCi/m3 + 2 sigma Nuclides January February March April May Jtme R5 OFFSITE OCNPOSI'IE (00NIROL) Ce-144 <6.46 <6.01 o iS <5.48 <7.77 <5.59 Ce-141 <2.32 <2.35 <2.57 <2.20 <2.49 <2.95 Be-7 99.5 + 17.3 123 + 23.4 140 + 23.1 168 + 26.4 169 + 27.3 154 + 27.0 Ru-103 <C67 <C85 <2751 <C98 <C86 <2T54 Cs-134 <1.46 <1.47 <1.50 <1.25 <1.96 <1.38 Cs-137 <1.45 <1.29 <1.99 - <1.16 '<1.72 <1.30 1r-95 <4.03 <3.68 <5.84 <6.21 <4.71 <3.80 Nb-95 <2.25 <2.36 <1.88 <1.75 <2.83 <1.76 Co-58 <1.68 <1.58 <1.85 <1.66 <1.59 <1.96 Mn-54 <1.42 <9.89 <1.67 <1.42 <1.70 <1.45 C0-60 <1.83 <2.25 <0.99 <2.03 <1.43 <1.72 K-40 54.5 + 19.8 <24.0 17.5 + 14.0 <15.3 <41.6 <23.5 i Ra-226 20.0 T 10.9 <25.5 <3U.7 <24.5 <29.6 <27.0 Others <133) (UD <UD <UD <UD <UE D2 Omirm OCNPOSITE Ce-144 <7.44 <7.42 <6.97 <7.73 <5.68 <7.74 Ce-141 <2.88 <2.38 <1.94 <2.20 <1.83 <2.73 Be-7 95.8 + 16.6 127 + 24.6 132 + 23.6 137 + 22.4 181 + 26.4 182 + 26.9 Ru-103 <2T10 <2713 <C95 <C97 <CSI <2T16 Cs-134 <1.55 <1.75 <1.78 <1.29 <1.51 <1.78 Cs-137 <1.38 <1.78 <2.10 <1.15 <1.69 <2.14 Zr-95 <3.56 <5.57 <2.90 <3.15 <3.48 <4.47 Nb-95 <1.70 <2.73 <1.98 <2.50 <2.02 <2.70 Co-58 <1.63 <1.79 <0.81 <1.83 <1.84 <2.56 Mn-54 <1.12 <2.45 <1.46 <2.02 <1.18 <2.15 C0-60 <0.86 <2.49 <3.11 <1.14 <1.10 <0.97 K-40 66.8 + 20.6 <35.5 <39.7 <29.7 <33.3. <38.5 Ra-226 31.2 T 19.8 <28.6 <32.5 <27.4 <26.3 <30.0 Others <lll) <UD (UD <UD <UD (UD
TABE 9 (Continued) 00NCDrIRATIONS OF GMR DGTIERS IN MHmHX O(NFOSITES OF.JAF AIR PARTICULATE SMFIES 1987 Results in Uhits of 10 3 pC1/m3 + 2 sigpn Nuclides January February March April May June E OFFSITE COMPOSITE Ce-144 <6.33 <6.65 <6.90 <4.67 <6.28 <7.61-Ce-141 <2.30 <2.86 <2.14 <1.80 <1.72 <3.06 Be-7 97.2 + 16.3 103 + 21.1 129 + 21.7 116 + 20.5 188 + 26.8 162 + 23.9 Ru-103 <1.39 <C76 <2733 <2710 <C62 <2742 Cs-134 <1.30 <1.19 <1.43 <1.10 <1.44 <1.46 Cs-137 <1.11 <1.72 <1.52 <1.12 <1.70 <2.22 2r-95 <3.01 <4.36 <2.78 <2.72 <4.42 <4.41 Nb-95 <2.19 <2.85 <1.80 <1.53 <2.34 <2.50 Co-58 <1.20 <0.79 <1.49 <1.84 <0.75 <1.84 m-54 <0.80 <1.70 <1.59 <1.25 <0.% <2.10 00-60 <1.26 <1.57 <2.12 <0.89 <2.21 <1.12 K-40 51.7 + 18.6 22.9 + 16.6 20.6 + 13.6 <28.6 <11.8 64.7 + 22.4 3 Ra-226 15.0 T 9.94 17.35 T 10.8 <23.5 <23.2 <24.8 <3T.2 Others <ID <1D <IlD (IJD <IJE <IJD F Onsut CCEPOSITE Ce-144 <6.73 <7.29 <6.73 <6.09 <6.14 <8.28 Ce-1*1 <2.16 <2.34 <2.% <2.33 <2.04 <2.52 Be-7 103 & 15.9 120 + 22.2 148 + 23.4 145 + 20.2 144 + 23.9 160 + 25.5 Ru-103 < C44 <C45 <C61 <C90 < CSS <2T20 Cs-134 <1.13 <1.55 <1.77 <1.36 <1.46 <1.37 Cs-137 <1.28 <1.13 <1.58 <1.33 <0.82 <1.75 Zr-95 <3.47 <5.17 '3.45
. <3.59 <3.18 (4.63 E-95 <1.84 <1.90 <2.82 <1.61 <1.68 <2.28 Co-58 <1.23 <1.53 <1.66 <1.51 <1.53 <2.09 En-54 <1.40 <1.05 <0.95 <1.40 <1.70 <1.48 Co-60 <1.37 <1.80 <1.08 <1.81 <1.59 <1.63 K-40 47.0 + 17.4 <26.7 27.7 + 17.3 57.0 + 18.7 ' <29.5 <45.9 Ra-226 26.9 T 15.3 <27.0 <2E.2 <23.7 <23.4 <32.8 Others <ID <I1D <1lD (IlD <11D (IJD
TAB m 9 (Continued) . CONGNNATIONS OF GAPNA DHTIERS IN MNHLY COMPOSTIES OF JAF AIR PARTIC1HEIE SAMPES 1987 Results in thits of 10 3 pCi/m3 + 2 sigma Nre.lides January February March April May June G Ondnt CCNPOSITE Ce-144 <8.10 <6.88 <8.27 <5.90 <5.62 <8.36 Ce-141 <2.54 <2 47 <2.25 <1.99 <2.46 <3.46 Be-7 108 + 19.0 137 + 26.0 137 + 24.7 152 + 22.8 161 + 27.6 194 + 26.8 Ru-103 <2T21 <2766 <1762 <2703 <1780 <2 79 Cs-134 <1.58 <1.59 <1.82 <1.48 <2.04 <1.83 Cs -137 <1.35 <1.87 <1.57 <0.75 <1.34 <1.87 Zr-95 <3.71 <4.63 <5.89 <3.85 <3.70 <4.87 Nb-95 <2.31 <2.51 <2.28 <1.44 <0.98 <1.97 Co-58 <1.69 <1.57 <1.92 <1.61 <1.99 <1.82 Mn-54 <1.86 <1.60 <1.58 <1.47 <1.14 <1.68 Co-60 <1.60 <2.23 <1.93 <1.13 <1.31 <1.51 K-40 38.5 + 18.6 <27.4 23.7 + 16.1 <25.5 <37.0 79.1 + 28.5
- Ra-226 <3U.5 <27.9 <33~ 7 <26.7 <30.8 <3H.2 Others <llD (ILD <1lD <I1D <11D <I1D
.. - - - - . . - - ., .~. - . . - -- , , -- ,- . _ _ .
TABE 9 (Continued) ' CONCENIRATIONS OF C#HL DfITIERS IN PONIHLY COMPOSUES OF JAF AIR PARI'ICUIEIE SAMPIES 1987 Results in Uhits of 10 3 pCi/m2 + 2 signa Nuclides January February March April May June D1 ONSITE CCNPOSIIE Ce-144 <5.86 <6.42 <5.95 <5.24 <6.20 <7.80 Ce-141 <2.01 <2.08 <2.05 <1.90 <2.00 <2.91 Be-7 79.9 + 17.2 130 + 21.8 141 + 22.4 147 + 22.9 162 + 25.4 165 + 26.4 Ru-103 <2707 <2703 <C62 - <C65 <C79 <2709 Cs-134 <0.92 <1.32 <1.64 <1.32 <1.22 <1.34 Cs-137 <1.36 <1.30 <1.22 <1.09 <1.67 <1.66 Zr-95 <1.38 <3.83 <4.53 <3.56. <3.25 <5.41 tb-95 <2.24 <2.02 <2.16 <1.53 <1.22 <2.17 Co-58 <0.94 <1.83 <0.65 <1.29 <2.07 <1.89 Nh-54 <1.17 <1.31 <1.32 <1.34 <1.00 <1.77 0o-60 <1.62 <2.44 <1.32 <1.52 <1.63 <1.38
. K-40 <14.1 <27.8 <28.1 <18.7 <34.8 46.0 + 23.1-4 Ra-226 <24.9 <25.2 <29.2 17.5 + 9.08 20.5 + 12.1- <36.2 Others (UE <UE <UD <ID <lD <UD G ONSITE OCNPOSUE Ce-144 <4.60 <5.94 <6.66 <5.56 <7.48 <9.21 Ce-141 <1.97 <1.99 <2.39 <2.05 <2.49 <3.06 Be-7 90.3 + 17.4 125 + 24.9 137 + 22.7 129 + 19.8 144 + 23.3- 166 + 26.3 Ru-103 <C73 <C46 <C26 <2T12 <2707 <2745 Cs-134 <1.20 <1.85 <1.68 <1.41 <1.64 <1.62 Cs-137 <1.12 <1.55 <1.45 <1.37 <1.85 <1.84 Zr-95 <3.41 <3.61 <3.02 <3.47 <3.25 <4.93 lb-95 <1.85 <2.26 <2.25 <1.68 <1.34 <2.59 Co-58 <0.57 <2.06 <1.61 <1.74 <1.21 <1.88-Fh-54 <1.13 <1.99 <1.84 <1.49 <2.45 <1.90 Co-60 <1.12 <1.61 <2.06 <1.71 <1.40 <2.26 K-40 <28.0 <27.1 <31.0 <29.3 <23.5 54.5 + 22.0 Ra-226 <19.1 <27.7 <31.4 <21.3 <30.1 <3T.9 l Others <UD <UE <UD <UD <UD <UD
9 ) CONCBURATIONS OF GAMR EM1 TIERS IN MNIEY 00MFOSITES OF JAF AIR PARTICUULIE SAMPIES 1987 Results in Units of 10 2 pCi/m3 4_ 2 sigpn , Nuclides January February March- April- May June H ONSITE OCEPOSITE Ce-144 <4.47 <7.78 <7.15 <7.43 <8.62 <10.5 Cc-141 <1.74 <2.44 <2.29 <2.15 <2.89 <2.77 Be-7 106 + 19.6 116 + 22.9 131 + 25.3 112 + 17.8 144 + 25.6 130 + 24.6 Ru-103 <C56 <2T28 <C97 <C44 <2763 <2717 Cs-134 <1.10 <1.59 <1.22 <1.66 <1.73 <2.08 Cs-137 <1.38 <1.96 <1.71 <1.92 <1.65 <2.13 Zr-95 <3.21 <3.63 <4.37 <4.55 <2.78 <4.15 Ib-95 <2.01 <2.71 <1.33. <2.15 <3.49 <2.61 Co-58 <1.14 <1.10 <1.49 <1.55 <2.43 <2.13 Mn-54 <1.36 <2.10 <1.74 <1.18 <1.20 <2.24 Co-60 <1.78 <2.47 <3.07 <2.13 <1.54 <1.56 K-40 <19.0 26.5 + 17.7 26.8 + 19.8 60.8 + 20.5 <41.8 <52.4 $ Ra-226 <22.0 <2H.5 <37.4 <23.1 <38.2 <42.8 Others <UD <UD <UD <UD <UD <UB I ONSITE OCMPOSITE Ce-144 <5.43 <8.91 <7.90 <4.% <10.5 <7.41 Ce-141 <1.74 <3.15 <2.44 '<2.40 <3.28 <2.97 Be-7 82.7 + 16.7 108 + 24.8 105 + 22.3 145 + 24.0 140 + 24.4 151 + 22.4 Ru-103 <C04 <2778 <C97 <C45 <233 <2T60 Cs-134 <1.15 <2.10 <1.63 (1.32 . <2.21 <1.80 Cs-137 <1.35 <1.83 <1.71 <1.54 <1.98 <1.58 Zr-95 <2.97 <5.10 <4.99 <3.36 <5.02 <4.67 tb-95 <1.31 <3.51 <2.91 <1.51 <2.86 <1.74 . Co-58 <1.29 <2.45 <2.39 <1.24 <1.55 <1.90 ft-54 <1.02 <1.27 <1.02 <1.66 <1.77 <1.83 co-60 <1.60 <2.51 <1.97 <1.66 <2.19 <1.11 K-40 <17.0 36.0 + 23.8 21.6 + 17.2 <17.7 62.6 + 26.8 77.8 + 24.9 Ra-226 <18.7 <35.0 <3U.7 <21.6 <47.4 <35.2 Others (UD <UD (UD <UD <UD <UD
TABLE 9 (Continued) 00NCENIRATIONS OF GAWA Df1TTERS IN F0fTITE,Y COMPOSITES OF JAF AIR PARTICUIATE SAMPIES 1987 Results in 'Inits of 10 3 pCi/m3 + 2 sigma Nuclides January February March April May June J ONSITE 00MIOSITE Ce-144 <6.33 <7.08 <6.63 <5.05 <6.27 <6.55 Ce-141 <1.86 <2.52 <2.02 <1.97 <1.77 <2.42 Be-7 90.6 + 18.4 85.1 + 19.3 121 + 23.4 150 + 25.7 138 + 23.7 175 + 28.0 Ru-103 <1T75 <2T12 <1T82 <1777 <1774 <2T31 Cs-134 <1.44 <1.60 <1.42 <1.24 <1.68 <1.55 Cs-137 <1.76 <1.71 <1.27 <1.08 <2.06 <1.32 Zr-93 <2.43 <4.70 <4.28 <2.90 <2.74 <4.57 lb-95 <1.86 <2.76 <2.07 <2.00 <1.67 <2.21 Co-58 <2.12 <1.84 <1.46 <1.20 <1.32 <2.09 Mh-54 <1.68 <2.24 <2.01 <1.33 <1.38 <1.50 Co-60 <1.65 <1.51 <1.23 <2.51 <1.12 <1.52 y K-40 <28.7 <27.8 30.0 + 19.8 <30.4 <23.9 <34.4
- Ra-226 <25.5 <27.8 <2V.3 <23.9 <26.0 <26.5 Others <UD <UD <UD <UD <UD <UD K ONSITE CITOSITE Ce-144 <6.51 <6.51 <6.38 <4.93 <6.42 <8.01 Ce-141 <2.09 <2.28 <1.15 <2.07 <1.97 <2.89 Be-7 89.9 + 15.2 124 + 24.7 110 + 20.7 123 + 19.1 133 + 22.3 137 + 21.5 Ru-103 <1750 <1727 <1799 <T.37 <1797 <2709 Cs-134 <1.49 <1.93 <1.59 <1.23 <1.82 <1.19 C'-137 s <1.13 <1.52 <1.81 <1.63 <i.10 <1.40 Zr-95 <4.53 <3.44 <3.52' <4.60 <3.80 <4.98 Ib-95 <1.97 <2.04 <0.99 <1.95 <I.59 <1.98 Co-58 <1.30 <1.17 <1.68 <1.54 <l.93 <2.37 Mh-54 <1.39 <1.83 <0.81 <1.39 <1.16 <1.88 Co-60 <0.57 <1.71 <2.40 <1.43 <0.91 <2.07 K-40 53.9 + 17.7 <38.7 <19.3 <15.1 <27.3 49.3 + 20.6 Ra-226 <23.3 <29.2 <25.8 <22.0 <28.2 26.5 T 17.9 Others <UD <UD <UD <UD <UD <ITD
q 00NCENIRATIONS OF GMin EMITIERS IN NRCILY OCHEOSITES ' OF JAF AIR PARTICUIEIE SAMPIES :: 1987 Results in thits of 10~3 pCi/m2 + 2 sigma j Nuclides July August Septenber October November Decenber - j R1 OFFSITE OCNPOSITE Cc-144 <6.23 <6.55 <5.83 <5.55' <4.99 <5.73 j Ce-141 <2.06 <1.98 <2.28 <1.85 <1.68 <1.67 ! Be-7 154 + 19.8 151 + 23.1 91.3 + 17.9 133 + 19.5 73.3 + 17.3 73.9 + 14.4 ' Ru-103 <C54 <C96 <1.35 <C34 <C43 <C81 Cs-134 <1.06 <1.76 <1.13 <1.28 <1.27 <1.14 Cs-137 <1.20 <1.52 <1.43 <1.51 <1.42 <1.32 Zr-95 <3.13 <2.97 <3.58 <2.92 <2.76 <2.44 Nb-95 <2.10 <1.11 <1.31 <1.45 <1.79 <1.70 Co-58 <1.62 <1.43 <1.49 <1.15 <).76 <1.56 l'b-54 <1.37 <1.58 <1.46 <1.34 <0.60 <0.59 Co-60 <1.07 <1.05 <0.73 <1.63 <0.98 <1.0; K-40 35.7 + 17.0 <35.5 20.5 + 12.8 <24.7 <23.4 27.9 + 14.0
$ Ra-226 22.1 T 13.9 <26.3 <27.5 <18.8 <21.7 16.1 T 9.28 Others <ID <UD <IID <UD <UD <ID R2 OFTSI'IE UNPOSITE Cc-144 <5.60 <7.07 <4.69 <4.89 <?.98 <4.85 Ce-141 <2.10 <2.13 <2.20 <1.58 <1.65 <1.56 Be-7 154 + 18.6 154 + 24.6 117 + 21.9 115 + 18.6 95.8 + 18.4 62.3 + 13.4 Ru-103 <C25 <2702 <2735 <C31 <C58 < C38 Cs-134 <0.90 <1.62 <1.24 <1.20 <1.32 <1.21 Cs-137 <1.09 <1.56 <1.45 <0.70 <1.10 <1.10 Zr-95 <2.64 <3.73 <5.07 <3.85 <3.04 <2. 96 lb-95 <1.29 <1.80 <2.58 <1.26 <1.6i <1.59 00-58 <1.46 <1.64 <1.46 <1.37 <1.31 <1.15 th-54 <0.66 <1.99 <1.40 <1.56 <1.19 <1.23 Co-60 <1.32 <1.52 <1.42 <1.38 <1.67 <1.18 K-40 58.9 + 19.7 <30.5 <24.0 <17.0 <14.5 <17.6 Ra-226 15.3 T 11.5 <23.2 <21.9 <21.8 <23.3 18.9 + 13.8 Others <ID <UD <UD <UD <UD <ID
_, ,, y , ,m- - - . 4 -,, - -uv-- -- i i +. '=vyy
j TAB m 9 (Continued)
; CONCENDIATIONS OF CAME D(ITIBtS IN MNDILY 00ff0$1TES ) OF JAF AIR PARTICUIEIE SAMPES
- 1987 Restfits in Uhits of 10 ' pCi/m2 + 2 sigma _
Nuclides July August Septerber October Noved>er Decenber R3 OFFSITE OTTOSITE Ce-144 <5.72 <7.72 <6.26 <5.14 <5.53 <6.46 Ce-141 <2.09 <2.52 <2.16 <1.95 <1.86 <2.10 Be-7 158 + 20.7 148 + 21.9 110 + 22.0 128 + 19.7 66.9 + 14.6 48.1 + 13.2 Ru-103 <C94 <2703 <C65 <C53 <C64 <C61 i Cs-134 <1.30 <1.41 <1.47 <1.53 <1.59 <1.32 Cs-137 <1.43 <1.66 <1.33 <1.22 <1.55 <0.83
- Zr-95 <3.13 <4.40 <3.79 <3.70 <4.08 <3.32 i M>-95 <2.30 <1.86 <2.04 c.64 <1.33 <2.26 00-58 <1.76 <1.59 <2.19 <1.03 <1.61 <1.51 Mn-54 <1.50 <1.75 <2.00 <0. 91 - <1.67 <1.27 Co-60 <1.71 <1.77 <1.51 <0.84 <1.47 <1.40 l w K-40 38.2 + 18.1 53.0 + 22.0 <30.1 <22.1 <17.3 29.5 + 14.8 l Ra-226 <23,3 <3T.6 <24.2 <22.2 <24.6 <23.8 Others <UD <UD <UD <UD <UB <UD R4 OFFSI'IE CCNPOSITE Ce-144 <5.70 <7.28 <6.83 <6.43 <6.59 <s.65 Ce-141 <2.08 <2.08 <2.40 <2.32 <2.25 <1.41 Be-7 143 + 21.6 177 + 26.3 133 + 25.3 143 + 19.9 75.1 + 16.7 83.2 + 17.0 Ru-103 <C69 <C63 <2T31 <C72 <C79 <C34 Cs-134 <1.22 <1.26 <1.40 <1.28 <1.54 <1.24 Cs-137 <1.20 <1.12 <1.54 <1.29 <1.39 <1.25 Zr-95 <3.44 <4.69 <4.59 <2.85' <4.50 <2.18 Nb-95 <2.00 <1.67 <2.58 <1.99 <1.85 <2.05 Co-58 <1.39 <2.13 <0.83 <1.57 <1.52 <1.60 Mi-54 <1.23 <1.17 <1.74 <1.26 <1.52 <1~20 Co-60 <1.26 <1.10 <1.97 <1.75 < 1. .M <1.93 K-40 <21.2 <28.7 <21.0 42.3 + 16.9- 39.2 + 16.7 <16.0 Ra-226 <24.3 <28.9 <25.9 (2T.7 <29.8 <23.0 Others <UB <UD <UD ~( UD <UD <UD
00NCENIRATIONS OF GAMM DIITIERS IN MWlHLY CGf0SHES OF JAF AIR PARTICUIATE SAMPES 1987 Results in Units of 10 ' pC1/m2 + 2 sigma Nuclides July August Septenber October Nova ber December R5 OFTSITE 00f0STIE (00NIBOL) Ce-144 (7.13 <5.41 <5.88 <5 22 <7.25 <6.09 Cc-141 <2.21 <2.19 <2.60 <1.89 <2.30 <1.82 , Be-7 138 + 21.8 167 + 23.1 111 + 20.6 143 + 22.1 72.0 + 18.1 .68.6 + 15.1 1 l Ru-103 <C59 <C63 <2730 <2704 <2'03 <C50 l Cs-134 <1.59 <1.36 <1.66 <1.71 <1.62 <1.08 ! Cs-137 <1.27 <0.98 <1.58 <1.03 <1.66 <1.18 Zr-95 <4.02 <2.96 <3.50 <4.04 <3.89 <3.22 lb-95 <2.56 <1.57 <2.30 <1.49 <2.21 <1.93 Co-58 <1.59 <1.72 <1.43 <1.71 (1.48 <1.41 Mn-54 <1.05 <1.54 <1.65 <1.13 <1.45 <1.19 ! Co-60 <1.38 <1.56 <1.49 <2.02 <1.84 <1.01 l K-40 21.6 + 13.7 <28.4 <17.6 <15.3 44.8 + 18.2 26.2 + 12.5 m Ra-226 <2C6 <26.9 30.8 + 18.7 <25.4 l
" <29.2 <2T.0 l Others <UD <UD <Ulf <UE <UD <UD D2 OFFS m. COMPOSITE l
Ce-144 <5.48 <6.46 <5.79 <5.41 <4.31 (5.05 Ce-141 <1.81 <2.41 <2.39 <1.54 <1.84 <2.08 Be-7 132 + 17.6 14) + 19.2 112 + 19.5 123 + 17.9 88.4 + 17.1 66.6 + 13.3 ( Ru-103 < C26 <C68 <C60 <C19 <1.T7 < C42 l Cs-134 <1.08 <1.13 <1.35 <1.07 <1.26 <1.08
^
Cs-137 <1.22 <1.01 <1.40 <0.85 <1.33 <1.03 Zr-95 <2.57 <2.79 <3.14 <2.41 <3.68 <3.59 l lb-95 <1.51 <1.69 <1.48 <1.39 <1.19 <1.30 1 Co-58 <1.21 <1.57 <1.77 <1.14 <6.26 <1.27' l Mn-54 <1.20 <1.30 <1.07 <1.31 <0.57 <1.00 Co-60 <1.33 <1.51 <1.43 <1.27 <1.84 <0.78 K-40 44.1 + 14.6 42.6 + 16.8 <19.9 <10.4 <24.1 34.0 + 14.5 Ra-226 <22.5 <2T.7 <24.7 <19.7 (20.7 15.8 T 12.9 Others <UD <UD <UD <UD <UD <ITD
A
~
TABLE 9 (Continued) .~ 00NON1 RATIONS OF GAttR DUTIERS IN MMIHX OCNPOSTIES 'Md ' ' ' OF JAF AIR PARTICUIEIE SAMPES ' ' 1987 Results in thits of 10 ' pCi/m3 +.2 sI Dna Nuclides July August September October Novmber December E OFISTIE OCNPOSUE Ce-144 <5.70 <6.67 <6.28 <4.85 <5.42 <4.90 Ce-141 <1.72 <2.54 <2.63 <1.81 <1.99 <1.86 Be-7 123 + 19.9 146 + 21.8 105 + 19.0 126 + 19.1 78.7 + 16.6 65.6 + 12.6
- Ru-103 <C43 <C89 <C91 <C33 < CSS <C29 Cs-134 <1.31 <1.45 <1.36 <1.16 <1.30 <0.92 Cs-137 <0.63 <1.36 <1.18 <1.09 <1.22 <1.08 Zr-95 <3.83 <3.78 <3.62 <3.33 <3.68 <2.30 Nb-95 <1.70 <2.10 <2.01 <1.11 <1.54 <1.10.
Co-58 <1.06 <1.54 <1.15 <0.80 <1.29 <1.35 m-54 <1.79 <1.29 <1.35 <1.41 <1.16 <1.31
~Co-60 <0.87 <1.32 <1.01 <0.81 <2.03 <1.07.
K-40 <16.1 47.5 + 20.1 62.8 + 19.1 <21.1 28.2 + 14.4 44.3 + 15.1 g Ra-226 <22.3 <2H.4 <25.4 <21.4 <25.9 <2T.7 Others <UB <UD <UD <UD <UB <UB F OFLi'IE OW20SHE l Ce-144 <5.69 <7.43 <7.33 <4.61 <5.17 <4.83 l Ce-141 <2.19 <2.31 <2.94 <1.70 <1.79 <1.65 Be-7 122 + 18.1 136 + 21.8 108 + 20.3 118 + 17.2 90.5 + 17.9 63.9 + 13.6 i Ru-103 <C68 <C95 <2702 <C53 <C31 <C45 l Cs-134 <1.18 <1.53 <1.47 <1.34 <1.17 <1.10 Cs-137 <0.92 <1.29 <1.24 <0.82 <1.09 <0.94 - Zr-95 <2.62 <5.06 <4.51 <3.26 <2.34 <3.25 E-95 <1.67 <1.33 <1.71 <1.43 <1.75 <1.69 l Co-58 <1.77 <1.42 <0.98 <1.26 <0.92 <0.99 ' N-54 <1.45 <1.60 <1.34 <0.55 <1.56 <0.95 Co-60 <1.21 <2.29 <1.63 <1.32 <1.66 <0.58 i K-40 41.3 + 17.0 15.0 + 11.2 43.5 + 17.9 16.0 + 9.79 <25.0 29.1 + 13.1 l Ra-226 <2T.8 12.3 T 11.8 <23.3 <23.0 <22.6 22T7 Others <UD <11b (UD <UD <UD . <UD
00NONIRAT10NS OF GfdNA D11TIEtS.IN MWlEY O(NPOSTIES ~ OF JAF AIR PARTICtXATE SAMPES ;. 1987 l Results in Units of 10 ' pCi/m2 + 2 sigma Nuclides July August Septenber October Nov& ber Decenber G OFysnt CCNPOSITE Ce-144 <6.25 <6.82 <6.59 <6.58 <6.88 <5.53 Ce-141 <2.27 <2.51 <2.79 <2.19 <2.09 <1.97 Be-7 157 + 20.8 157 + 21.3 112 + 18.8 130 + 19.5 82.0 + 15.2- 52.5 + 13.0 Ru-103 <C95 <2702 <2741 <C50 <C89 <C36 Cs-134 <1.09 <1.74 <1.21 <1.41 <1.42 <1.32 Cs-137 <1.27 <1.29 <1.27 <1.06 <1.17 <1.19 Zr-95 <3.09 <3.95 <3.60 <3.01 <3.42 <3.05 Nb-95 <1.74 <1.57 <2.62 <2.10 <1.42 <1.73 Co-58 <1.33 <1.52 <1.29 <1.43 <1.40 <1.45 m-54 3.16 + 1.13 <1.46 <1.40 <1.19 <1.03 <0.90 Co-60 1.72 T 0.98 <1.92 <1.56 <1.48 <1.46 <1.84 <1.14 K-40 54.0 T 17.5 76.6 + 21.8 44.1 + 16.5 34.0 + 16.4 59.2 + 18.7 33.4 + 14.7 m Ra-226 <2T.4 <27.7 17.1 T 11.2 <25.5 <2V.2 _ 14.4 T 8.89 Others <UE <UD <ID <UD <UD < iib ymr., mus. - rp y w- m -wym --M- m-- T- e+v * - ' per'= *
*W- + -
w v- +mw- it--- 3 m- -y e-- i - go- %
TABLE 9 (Continued) 00?EE?TIRATIO!E OF GVf4A BfITIEPS IN MXTDILY CQ4POSI'IES OF JAF AIR PARTICUIATE SAMPES 1987 Results in Units of 10 ' p'Ci/m 2 + 2 sigan Nuclides July August Septaber October Novmber Decmber D1 OfEITE CQ4POSITE Ce-144 <5.20 <6.33 <6.67 <5.52 <5.65 <5.20 Ce-141 <1.76 <2.18 <1.81 <2.01 (?.30 <1.75 Be-7 141 + 21.5 152 + 20.6 100 + 19.4 135 + 16.9 77.1 + 15.0 63.8 + 12.6 Ru-103 <1746 <1724 <1732 <1737 <1T66 <1T53 Cs-134 <1.02 <1.55 <2.06 <1.19 <1.28 <1.08 Cs-137 <1.28 <1.36 <1.84 <1.11 <1.14 <0.96 Zr-95 <3.17 <3.48 <2.93 <2.57 <3.52 <2.90 lb-95 <1.86 <1.38 <2.45 <1.26 <1.38 <1.21 Co-58 <1.52 <1.71 <1.58 <1.26 <1.36 <1.29 It-54 <1.82 <1.43 <1.43 <1.34 <1.18 <1.01 Co-60 <1.25 <1.60 <1.46 <1.14 <1.53 <1.24 K-40 <18.9 51.6 + 19.7 <15.7 51.8 + 16.1 53.2 + 17.3 41.3 + 14.8
- Ra-226 <24.0 16.3 T 10.6 <29.1
- <2T.0 <25.7 <2T.3 Others (UB <ID <UD <UB <UB <UD .
G OfEITE C04POSITE Ce-144 <5.84 <8.31 <7.31 <6.00 <6.77 <6.32 Ce-141 <2.19 <2.91 <2.44 <2.02 <2.23 <2.16 Be-7 138 + 20.1 167. + 23.8 92.3 + 17.4 108 + 17.0 71.6 + 15.2 63.4 + 13.1 Ru-103 <1772 <1769 <1762 <1744 <1781 <1743 Cs-134 <1.11 <1.82 <1.20 <1.13 <1.54 <1.35 Cs-137 <1.13 <1.36 <1.57 <1.01 <1.39 <1.21 Zr-95 <2.35 <3.53 <4.44 <2.40 <3.33 <3.80 Nb-95 <1.36 <2.17 <1.65 <1.30 <1.83 <1.51 Co-58 <1.52 <1.46 <1.68 <1.37 <1.81 <1.32 Mn-54 <1.28 <1.52 <1.27 <1.47 <1.51 <1.02 00-60 <1.58 <1.89 <1.50 <0.59 <1.89 <1.47 K-40 65.0 + 19.2 76.9 + 26.1 42.5 + 19.5 41.4 + 17.7 30.7 + 15.4 34.0 + 14.5 Ra-226 27.3 T 17.5 31.5 T 17.6 <29.8 <2T.8 22.7 + 11.1 <27.2 Others <ID <I D <UD <UD <1D <UD
6 ' 00NCE!TIRATIONS OF GAINA EMITIERS IN MNDLY OCNPOSITFS OF JAF AIR PARTICUIATE SAMPIES 1987 Pasults in thits of 10'3 pCi/m2 + 2 sigma , Ibclides July August September October Ibvmber Decmber H ONSITE OCNPOSITE Ce-144 <6.71 <8.97 <7.11 <4.57 <5.39 <5.62 Ce-141 <2.35 <2.41 <1.94 <1.76 <1.90 <2.08 Be-7 132 + 19.6 139 + 22.0 72.3 + 19.5 116 + 20.0 71.6 + 16.8 61.2 + 15.5 Ru-103 <1763 <1798 <1782 <1725 <1701 <1746 Cs-134 <1.11 <1.94 <1.18 <1.54 <1.45 <1.49 Cs-137 <1.24 <1.83 <1.08 <0.88 <1.11 <1.34 Zr-95 <3.96 <4.18 <3.47 <3.99 <3.88 (4.38 Nb-95 <1.84 <2.10 <2.07 <1.53 <1.92 <1.60 Co-58 <1.09 <1.99 <0.84 <1.05 <1.48 <0.70 Mn-54 <1.48 <1.55 <1.30 <1.07 <1.19 <1.23 Co-60 <1.76 <1.36 <3.21 <1.22 <0.97 <1.40 K-40 37.4 + 16.8 73.2 + 25.5 <22.5 <9.22 <20.7 19.3 + 13.5 , Ra-226 <2H.6 <3T.2 <26.9 <19.4 <24.8 <23.1 m Others <I1D <11D (11D (11D (11D <llD I ONSITE CENPOSITE Ce-144 <4.95 <7.45 <5.04 <5.49 <6.33 <5.50 Ce-141 <1.79 <2.98 <1.59 <1.58 <2.09 <2.36 Be-7 107 + 17.9 110 + 20.0 73.5 + 17.5 110 + 17.1 86.0 + 18.7 64.9 + 16.3 Ru-103 <1744 <2746 <1742 <1745 <137 <1778 Cs-134 <1.42 <1.35 <1.46 <1.12 <1.63 <1.26 Cs-137 <1.16 <1.71 <1.17 <0.95 <1.27 <1.63 Zr-95 <3.63 <4.16 <3.85 <2.12 <3.67 <3.79 Nb-95 <1.71 <2.55 <1.90 <1.69 <2.40 <2.26 C0-58 <1.72 <2.24 <2.10 <1.61 <1.53 <1.60 Mn-54 <1.56 <1.79 <1.66 <1.04 . <1.81 <1.57 Co-60 <1.46 <1.47 <2.50 <1.68 <1.38 <1.29 K-40 21.2 + 2.1 47.6 + 21.4 <28.8 10.1 + 9.4 18.9 + 13.3 24.2 + 15.0 Ra-226 <2T.6 <35.3 <23.8 <2T.7 <2T.9 <2E.8 Others <11D (11D <11D <11D <11D <11D
TABE 9 (Continued)- CONCENIRATIONS OF GAMR DHTIERS IN MNDiLY 00MPOSTIES OF JAF AIR PAPITICULATE SAMPIIS 1987 Results in thits of 10 ' pCi/m3 + 2 sigpn 13uclides July August Septaber October Ibvember 'Deconber J ONSITE O(NPOSTIE Ce-144 <5.61 <6.11 <5.70 <4.23 <5.69 <5.42 Ce-141 <1.93 <2.24 <1.96 <1.70 <2.04 <2.43 Be-7 146 + 18.9 148 + 22.4 76.5 + 17.8 107 + 18.0 69.7 + 17.0 59.8 + 13.7 Ru-103 <C34 (C48 <C87 <C43 <C63 <C69 Cs-134 <1.16 <1.62 <1.53 <1.24 <1.32 <1.01 Cs-137 <0.99 <1.41 <1.81 <1.40 <1.48 <1.06 Zr-95 <2.32 <4.02 <3=73 <3.81 <4.51 <3.45 Nb-95 <1.26 <2.20 <1.82 <1.85 <2.29 <1.70 00-58 <1.28 <1.52 <1.04 <1.00 <1.10 <1.31 Nh-54 <1.31 <1.47 <1.61 <1.69 <1.49 <1.62 Co-60 <1.35 <1.36 <1.51 <1.16 <1.85 <1.28 K-40 57.9 + 18.3 42.8 + 17.8 <22.8 <19.7 <22.6 53.3 + 16.9 m Ra-226 <27.6 <3T.3 <25.9 <19.2 <29.1 <2T.5 Others <UD <UD <IlD <UD <UD <UD K ONSITE OCNPOSITE Ce-144 <5.21 <5.15 <6.29 <5.01 <6.28 .<6.05 Ce-141 <1.86 <1.79 <2.16 <1.62 <1.97 <2.19 Be-7 109 + 18.1 125 + 22.2 <34.1 119 + 17.6 81.9 + 17.6 63.6 + 15.0 Ru-103 (C33 <C57 <1.72 <C34 . <C86 <C90 Cs-134 <0.82 <1.07 <1.10 <1.19 <1.43 <1.29 Cs-137 <1.22 <1.27 <1.11 <1.06 <1.53 <1.33 Zr-95 <4.33 <1.43 <3.06 <3.27 <3.45 <4.68 Ib-95 <2.05 <1.07 <1.55 <1.69 <1.66 <1.47 C0-58 <1.80 <1.37 <1.57 <1.09 <2.03 <1.19 lb-54 <1.66 <1.08 <1.24 <1.30 <1.50 <1.41 Co-60 <2.07 <1.01 <0.57 <1.03 <1.72 <0.66 K-40 <18.0 14.7 + 12.4 42.6 + 17.9 13.4 4 8.90 <23.8 26.1 + 14.1 Ra-226 <20.7 <27.3 <23.6 19.9 + 11.9 (19.8 <25.7 Others (UD <Ul) (UD <1D <UD ' <UD
J TABIE 10 DIRECT RADIATION MEASURDeff RESUL'IS (1987) Results in Units of mrem /Std. Month + 2 Sigan JANUARY APRIL JULY OCTOBER IIX'ATION STATION IDCATION 'IIIROUGli 'HIROUGil 'DIROUGil "I11R00GI (DIRFLTION AIO WLEBER MAROI JUNE SEP1H EER DECDiBER DISTANCE)2 3 D1 on Site 6.4&1.1 8.8+0.9 11.3+1.2 11.4+1.4 0.2 miles @ 69* 4 D2 on Site 4. 60.3 5.60.6 5. NO. 5 5.8TO.5 0.4 miles @ 140' 5 E on Site 5.5TO.2 5.2TO.4 6.3TO.4 6.1T0.4 0.4 miles @ 175* 6 F on Site 4.0T0.3 4.NO.4 5. NO.3 4.0T1.1 0.5 miles @ 210' 7* G on Site 4.4TO.2 4.4TO.2 5.5TO.2 4.6TO.2 0.7 miles @ 250' 8* R-5 off-Site-Control 5.3TO.4 5.60.4 6.6TO.5 5.4T0.5 16.4 miles @ 42* 9 D1 off Site 5.1TO.2 4.8TO.9 5. NO.4 5.2TO.4 11.4 miles @ 80* 10 02 off Site 5.0TO.2 4.8TO.2 5.2TO.4 5.60.4 9.0 miles @ 117* 11 E off Site 5.1TO.3 4.4TO.3 5. NO.3 5.2TO.4 7.2 niles @ 160* 12 F off Site 5.0TO.6 4.5TO.4 5.8TO.4 5.0T0.4 7.7 miles @ 190* 13 G off Site 5.2TO.4 4.6TO.2 5.60.3 5.2TO.4 5.3 miles @ 225* w 14* DeMass Rd., SW Oswego-Control 5.2TO.3 5.4TO.6 5.8TO.4 5.0TO.4 12.6 miles @ 226* m 15* Pole 66, W. Boundary-Bible Cm p 4.8TO.4 4.2TO.3 5.2TO.4 4.9TO.4 0.9 miles @ 237* 18* Energy Info. Center-Imp Post, SW 5.K0.2 5.8TO.4 6.2T0.4 5.8TO.4 0.4 miles @ 265* 19 East Boundary-JAF, Pole 9 5.4TO.6 5.2TO.5 6.0TO.4 5.2TO.2 1.3 miles @ 81* 23* H on Site 6.2T0.5 5.8TO.4 7. 60.4 6.4TO.5 0.8 miles @ 70* 24 I on Site 5.5TO.5 4.9TO.4 6.2TO.5 5.8TO.5 0.8 miles @ 98* 25 J on Site 5.4TO.6 4.8TO.3 4.9TO.3 5.1TO.4 0.9 miles @ 110* 26 K on Site 5.60.4 5.0TO.3 4.9T0.5 5.1TO.3 0.5 miles @ 132* 27 N. Fence, N. of Switchyard, JAF 9.8T2.4 13.G3.0 16.4T3.0 18.2T4.0 0.4 miles @ 60* 28 N. Light Pole, N. of Screenhouse, 14.4T4.8 18.1T5.2 21.175.8 23.0T3.4 0.5 niles @ 68* JAF 29 N. Fence, N. of W. Side 30.8+5.4 32.8+6.8 31.0+8.0 31.8+9.7 0.5 miles 9 65* 30 N. Fence (!M) JAF 9.1T1.8 11.F2.0 13.6T1.6 14.6T2.6 0.4 niles @ 57* 31 N. Fence (IM) INP-1 --- T- (1) 8.4VI.2 8.1T1.2 7.9T1.1 0.2 miles @ 276* 39 N. Fence, Rad. Waste-INP-1 12.241.8 11.0TI.6 11.1T1.2 11.4T2.2 0.2 miles @ 292* 47 N. Fence, (NE) JAF 8. G1.2 10. Gl.5 11.8TI.9 11.4T1.6 0.6 miles e 69* 49* Phoenix,IU-Control 5.0TO.2 4.6TO.2 5.4TO.2 5.170.6 19.8 miles @ 170* 51 Liberty & Bronson Sts. , E of OSS 5.8+0.3 4.7+0.2 5.440.2 5.8T0.5 7.4 miles @ 233* 52 East 12th & Cayuga Sts., Osw. 5.6TO.4 4.8TO.2 5.6TO.2 5.3TO.4 5.8 miles @ 227* School
TABLE 10 (Continued) DIRECT RADIATION MEASURFMNT RESULTS (1987) Results in Units of mrem /Std. Month 12 Sigma JANUARY APRIL JULY OCIDBER IDCATION STATION IDCATION 'I11ROUQI 'IIIROUGil 'IIIROUGil 'I11ROUCil (DIRFLTION AND
!REBER MAROI JUNE SEFITitBER DECD4BER DTSTANCE)2 53 Broad. mil & Chestnut Sts. - 5.610.2 4.810.3 6.110.5 5.410.4 13.7 miles @ 183*
Fulton H.S. 54 Liberty St. & Co. Rt. 16 - 5.510.6 4.810.2 5.310.4 4.610.4 9.3 miles @ 115* Mexico li.S. 55 Cas Substation Co. Rt. 5 - Pulaski 5.4+0.6 4.6+0.3 5.4+0.2 5.140.2 13.0 miles @ 75* 56* Rt. 104-New Haven SQl. (SE Comer) 5.6TO.5 4.5TO.3 5.8TO.5 5.1T0.3 5.3 miles @ 123' 58* Co. Rt. lA-ALCAN (E. of Entrance 5.3TO.3 4.1T2.1 4.7TO.4 5.4TO.3 3.1 miles @ 220* 75* Unit 2, N. Fence, N. of Reactor 6.0+0.3
~
4.9+0.5
~
5.6+0.5
~
5.1+0.4
~
0.1 miles @ 5* Bldg. 76* Unit 2, N. Fence, N. of Change 4.410.4 5.310.6 5.610.4 5.510.5 0.1 miles @ 25' ikmse $ 77* Unit 2, N. Fence, N. of Pipe Bldg. 5.8t0.3 7.5+0.5 7.5+1.2 6.0+0.6 9.2 miles @ 45* 78* JAF, E. of E. Old lay Down Area 6.0TO.5 6.0TO.4 6.0TO.4 5.5TO.5 1.0 miles @ 90* 79* Co. Rt. 29, Pole #63, 0.2 mi. S. 5.0TO.3
~
5.4T0.2 5.5TO.4
~
S.2TO.2
~
1.1 miles @ 115* of Lake Rd. 80* Co. Rt. 29, Pole #54, 0.7 mi. S. 5.0+0.3
~
4.5+0.1
~
5.440.2
~
5.140.3
~
1.4 miles @ 133* of I2ke Rd. 81* Miner Rd., Pole #16, 0.5 mi. W. 5.4+0.3
~
4.5+0.3
~
5.8+0.3 5.6+0.5
~
1.6 miles @ 159* of Rt. 29 82* Miner Rd., Pole il 1/2, 1.1 mi. 5.2+0.3 4.4+0.2 4.8+0.2 5.540.4 1.6 miles @ 181* W. of Rt. 29
~ ~
83* Iakeview Rd., Tree 0.45 mi. N. 5.440.5
~
5.2+0.9
~
5.6+0.2
~
5.3+0.4 1.2 miles @ 200* of Miner Rd. 84* Lakeview Rd., N., Pole 16117, 5.740.5
~
5.8+1.0
~
5.6+0.5
~
5.5+0.5 1.1 miles @ 225* 200ft. N. of Iake Rd.
-~
85* Unit 1, N. Fence, IL of W. Side 13.2+2.6 12.1+3.4 12.1+1.6 14.3+2.1
~
0.2 Miles @ 294* of Screen flouse 86* Unit 2, N. Fence, N. of W. Side 6.810.9 7.311.6 7.110.7 6.410.9 0.1 miles @ 315* of Screen ikmse
TAM E,10 (Continued) DIRELT RADIATION PEASUPDOTT RESUL'IS (1987) Results in Units of mrem /Std. Month + 2 Siggn JANUARY APRIL JULY OCIDHtK IDCATION STATION IDCATION 'INR00GI 'I11ROUQi ~1HROUQI 'I11R0001 (DIRFLTION A!O NLMBER MARCH JUNE SEPITMBER DECENBIR DLSTNKD2. 87* Unit 2, N. Fence, N. of E. Side 6.0+0.4 5.640.5 6.140.6
~
5.9+0.6
~
0.1 miles @ 341*- of Screen llouse 88* Ilickory Grove Rd., Pole #2. 0.6 6.0+1.2
~
4.5+0.4 5.8+0.3 5.0+0.4 4.5 miles @ 97* mi. N. of Rt. 1 89* 1eavitt Rd., Pole #16, 0.4 mi. S. 5.740.2 5.410.3
- ~
6.0+0.4
~
5.3+0.4 4.1 miles @ 111* of Rt. 1 90* Rt. 104, Pole 1300, 150ft. E. 5.440.4 4.740.3 5.4+0.2
~
5.0+0.3
~
4.2 miles @ 135' of Keefe Rd. 91* Rt. 51A, Pole 159, 0.8 mi. W. 5.040.1
~
4.3+0.5
~
5.040.2
~
4.8+0.5 4.8 miles @ 156' of Rc. 51
~~
92* m iden Lane Rd., Power Pole. 0.6 5.5+0.2 5.240.4 6.1+0.5 5.540.3 4.4 miles @ 183* , ni. S. of Rt. 104 - o 93* Rt. 53, Pole 1-1, 120 ft. S. of 4.5+0.3 5.2+0.3 5.7+0.6 5.0+0.2 4.4 miles @ 205* Rt. 104 94* Rt. 1. Pole #82, 250ft. E. of 4.9+0.5
~
5.4+0.3 5.0+0.4 5.0+0.3
~
4.7 miles @ 223* Kocher Rd. 95* Lakeshore Cm p Site, from Alcan W. 4. 644 .2
- 4. 640.1
~
5.1+0.2 4.5+0.1 4.1 miles @ 237* Access Rd. Pole 121, 1.2 mi. N.
~ ~
of Rt. I 96* Cremery Rd. , 0.3 mi. S. of Middle 5.5+0.6 4.640.2 5.2+0.2
~
5.540.4
~
3.6 miles @ 199* Rd. Pole 1 1/2 97* Rt. 29, Pole #50, 200 ft. N. of 5.6+0.3 3.5+1.2 5.6+0.3 4.9+0.3 1.8 miles @ 143* Miner Rd. 98* Lake Rd., Pole #145, 0.15 mi. of 6.1+0.2 4.9+0.3
~
5.910.3 6.1+0.4 1.2 miles @ 101* of Rt. 29 99 NT Rd. , 0.4 mi. N. of Lake Rd. , 4.940.1
~
5.010.2
~
5.6+0.4
~
5.5+0.4 1.8 miles @ 88* Env. Station R1 off-site 100 Rt. 29 and Lake Rd., Env. Station 5.040.3 4.6+0.3 6.0+0.3
~
5.340.4
~
1.1 miles @ 104* R2 off-site 101 Rt. 29, 0.7 mi. S. of Lake Rd. , 5.3+0.3 4.5+0.6 5.610.2 5.4+0.3 1.5 miles @ 132' Fmv. Station R3
TABLE 10 (Continued) DIFICT RADIATIG1 MEASURBfRT RFSULTS (1987) Results in Units of mrm/Std. Month 12 Sippn JANUARY APRIL JULY OCIDBER U) CATION STATION II) CATION DIROUGil VIROUGli DIROUGli 'DIROUQi (DIRFLTION AIO VU BER IMROI JUNE SEPIB4BER DECDiBER DISTANCE)2 102 EOF /Env. Lab, Oswgo Co. Airport 6.840.4 4.7+0.3 5.8+0.4 5.8+0.3 11.9 miles @ 175* (Fbiton Airport, Rt. 176) 103 EIC, East Garage Rd. , brp Post 5.8+0.2 5.4+0.4 5.5+0.3 6.3+0.4 0.4 miles @ 267* R3 off-site 104 Parkhurst Road, Pole #148 1/2-A, 5.4+0.5 4.8+0.2 5.2+0.4 5.3+0.4 1.4 miles @ 102* 0.1 miles South of Lake Rd. 105 Lakeview Rd., Pole 16125, 0.6 mi. 5.4+0.4 5.0+0.2 5.840.4 5.0+0.3 1.4 miles @ 198* South of lake Rd. 106 Shoreline Cove, East of IMP-1, 6.3+0.5 6.040.6
~~
6.540.5
~
6.2+0.4
~
0.3 miles @ 274* Tree on West Edge 107 Shoreline Cove, East of IMP-1 ---- (3) 19.511.9 6.710.6 0.3 miles @ 272* 5.710.5 (1) TIB lost in field. (3) Station established April, 1987. 2 Direction and distance based on FFP-2 reactor centerline and sixteen 22.5* sector grid.
- Technical specification location.
TABIE 11 00NCEtTTPATIOf2S OF IODINE-131 It! MIIX Results in Units of pCi/1 + 2 sigan Station
- 04/06/87 04/20/87 05/04/87 05/18/87 06/01/37 06/15/87 07/06/67 ,
07/20/87 08/03/87 tb. 60 <0.41 <0.26 <0.30 <0.49 <0.44 <0.26 <0.29 <0.25 <0.28 Wo. 55 <0.37 <0.33 <0.24 <0.26 <0.28 <0.19 <0.37 <0.24 <0.24
- 16. 50 <0.32 <0.39 <0.31 <0.41 <0.50 <0.22 <0.43 <0.29 <0.23 lb. 7 <0.26 <0.22 <0.34 <0.37 <0.40 <0.22 <0.34 <0.31 <0.29
?b. 4 <0.47 <0.26 <0.33 <0.17 <0.38 <0.22 <0.45 <0.37 <0.34 0
?b. 16 <0.29 <0.28 <0.29 <0.24 <0.28 <0.25 <0.32 <0.21 <0.23
- 26. 65
<0.21 <0.29 <0.24 <0.25 <0.42 <0.25 <0.36 <0.38 (0.23 (Control)
- Corresponds to sm ple locations noted on Figure 4, Section VII.
i
, TABLE 11 (Contintel) 00tGTIRATIO?S OF 10 DINE-131 IN MIIX Results in Units of pC1/1 + 2 sippa Station
- 08/17/87 09/08/87 09/21/87 10/05/87 10/19/87 11/02/87 11/16/87 12/07/87 12/21/87 24 0 . 60 <0.28 <0.46 <0.43 <0.32 <0.28 <0.24 <0.32 <0.33 <0.38 No. 55 <0.41 <0.20 <0.28 <0.20 <0.25 <0.18 <0.33 <0.41 <0.24 Wo. 50 <0.31 <0.49 <0.14 <0.22 <0.27 <0.20 <0.39 <0.22 <0.18 Wo. 7 <0.44 <0.26 <0.12 <0.23 <0.34 <0.26 <0.39 <0.23 <0.20 No. 4 <0.38 <0.26 <0.30 <0.17 <0.36 <0.25 <0.23 <0.18 <0.18 O
Wo. 16 <0.38 -
<0.29 <0.33 <0.29 <0.34 <0.23 <0.24 <0.31 <0.14 No. 65
<0.38 <0.21 <0.28 <0.29 <0.19 <0.19 <0.34 <0.36 <0.21 (Control)
- Corresponds to sarple locations noted on Figure 4, Section VII. -
_ TABLE 12 l CONCDTiRATIONS OF C&tM DtITII:PS IN FlIX Results in thits of pCi/112 sigma i Station
- Nuclides 04/06/87 04/20/87 05/04/87 05/18/87 06/01/87 06/15/57 l No. 60 K-40 1300+197 1430+224 1420+190- 1590+189 1400+165 1530+188 i Cs-134 <874 <975 <C6 <874 <C6 <677 i Cs-137 . <8.9 <13.6 <9.8 <8.3 <7.7 <8,1 l Ba/I4-140 <8.6 <9.8 <6.5 <7.4 <7.5 <6.7 I Others <UD <UD <UD <UD (UD <UD i No. 55 K-40 1710+205 1400+262 1640+168 1510+173 1660+169 1270+183 i Cs-134 <874 <1077 <874 <C7 <673 <676 i Cs-137 <8.9 <13.3 8.1+4.6 <9.0 <8.2 <6.1 i Ba/Ia-140 <7.0 <13.5 <C3 <8.5 <7.7 <8.3 i Others (UD <UD <UD <UD <UD <US
- I No. 50 K-40 1410+174 1670+271 1330+159 1740+182 1400+189 1730+172 !
Cs-134 (870 <970 <676 <CO .<C2 <674 ! Cs-137 <8.3 <12.0 (8.1 <8.9 (8.4 <S.3 Ba/La-140 <7.7 <8.5 <8.0 <8.5 <6.4 <5.1 i Others (UI <UD <UD <UI <ILD <UD ! i No. 7 K-40 1450+203 1530+241 1490+170 1590+167 15404189 1630+189 ! Cs-134 (974 <1076 <C9 <C8 <C6- <C2 ! Cs-137 <8.3 <11.1 5.5+4.0 <7.9 <7.8 <8.1 ; Ba/La-140 <9.8 <4.9 (C0 <4.8 <7.4 <7.5 ! Others (UD <UI <UI <UD <UD <UI ! No. 4 K-40 1470+178 1730+250 1730+196 1570+198 1510+197 1590+188 Cs-134 <676 <973 <C1 <876 <879 <C4 - Cs-137 <8.6 <11.7 <9.7 <10.5 <8.6 <8.0 [ Ba/la-140 <7.5 <9.4 <7.0 <11.1 <5.4 <5.5 i Others (UI <UD <UD <UD <LLD <UI i No. 16 K-40 1390+196 1550+286 1650+172 1740+194 1380+181 1730+173 Cs-134 <873 <1076 <C2 <CO (C4 <C1 Cs-137 <9.7 <15.4 <8.0 <9.1 <8.8 <9.0 ; Ba/La-140 <7.7 <12.9 <7.2 <9.0 <6,0 <6.8 ! Others <LLD <UD <UD <UD <UD <UD ; 1 No. 65 K-40 1490+263 1370+225 1670+192 1710+174 1530+164 1610+166 Control) Cs-134 <1C8 <879 <C8 <C7 <C3 <CO t Cs-137 <11.3 <11.4 <6.8 <8.5 <7.3 <7.4 i Ba/La-140 <8.9 <13.5 <6.0 <2.4 <5.9 <5.6 ! Others (UI (UI <UD <ILD (UD <UD l i i
- Corresponds to saple locations noted on Figure 4, Section VII. },
64 f i
r FABLE 12 (Continued) 00NCDTIRATIONS OF GMt% DUTIES IN MILK Results in Units of pCi/1 1 2 sigma Stawion* Nuclides 07/06/57 07/20/57 05/03/57 05/17/57 09/05/57 09/21/57 No. 60 K-40 1660+61.3 744+93.6 1520+167 1580+165 1500+166 1490+136 Cs-134 <!.4 <T.2 < 7~ 2 <671 <C4 <471 Cs-137 <2.8 <4.6 < ;' ? <7.4 <6.9 <5.5 Ba/Ia-140 <2.6 <2.9 <5.1 <4.2 <5.1 <4.5 Others <!1D (UD (ID (ID <UD <UD No. 55 K-40 1260+185 1540+185 1640+135 1810+143 1600+142 1530+142 Cs-134 <673 <C4 <C9 <571 <C9 <477 Cs-137 <9.2 <8.5 <5.4 <5.3 <5.5 <5.5 Ba/La-140 <9.7 <5.0 <5.8 <5.3 <3.8 <3.7 Others (UD < LID <UD (ID (IE <I1D No3 50 K-40 1690+71.8 1370+163 1680+173 1610+134 1470+139 1270+148 Cs-134 <Y.6 <C8 <CO <C8 <C5 (C1 Cs-137 <2.8 <7.2 <7.0 <5.2 (5.9 (6.3 Ba/La-140 <3.0 <7.7 <7.1 (6.1 (4.9 (6.1 Others <uD <uD <uD <tB <13 <tB No. 7 . K-40 1430+194 1740+173 1450+198 1580+169 1780+147 1670+144 Cs-134 <C8 <5~7 <C4 <5 9 <479 (C7 Cs-137 <9.7 <8.7 <8.0 <7.7 (5.7 <5.4 Ba/La-140 <9.8 <7.7 <10.5 <4.8 <5.1 <4.8 others <uD < LID <ID <UD <13 <UD No. 4 K-40 1360+165 1400+157 1430+193 1440+139 1440+137 1570+201 Cs-134 <C5 <C1 (573 <378 (5 0 <CO Cs-137 <8.1 (8.2 (9.2 <6.6 <5.5 <7.8 Ba/I4-140 <8.9 <6.1 <7.9 (4.9 <5.6 <9.2 Others (UD <UE <UD <UD (ID (ID No. 16 ' K-40 1820+176 1570+183 1430+191 1570+201 1340+188 1640+175 Cs-134 (C3 (575 <C4 (C8 <874 <C6 Cs-137 <9.2 <7.5 <9.8 <10.7 (7.1 <7.5 Ba/La-140 (8.0 <6.1 <5.7 <7.5 <8.4 <3.6
. Others (UD (UD (LID <UD (UD (UD No. 65 K-40 1610+177 1190+176 1360+191 1720+140 1640+172 1610+142 (Ccntrol) Cs-134 (677 (772 <675 (C5 <676 (C6 Cs-137 (8.0 <8.9 <8.9 <5.3 <8.2 <.i . 2 Ba/La-140 (7.2 <8.0 <10.7 <5.3 (7.3 <5.6 Othera (LID <ID <UD (US <UD (ID
- Corresponds to sayle locations noted cm Figure 4 Section VII.
65
TK8II 12 (Continued) CONCD7IMTIONS OF retM Df!TIUS IN MID: Results in l' nits of pCi/l + 2 sirpa Ft tion
- Nxlides 10/05/57 10/19/57 11/02/57 11/16/87 12/07/57 12/21/57
- b. 60 K-40 1400+156 1500+161 1400+134 1350+190 1450+189 1640+169 Cs-134 <679 <676 <573 <773 <576 (671 Cs-137 <7.3 <7.8 <5.4 <8.2 <9.2 (7.9 Ba/la-140 <7.7 <8.0 <5.3 <8,1 <10.2 <5.1 Others <UD <LLD <US <LLD <ILD <1D
- b. 55 K-40 1520+165 1440+197 1660+138 1550+203 1560+204 1630-136 Cs-134 <679 <778 <C9 <777 <773 < 57.'
Cs-137 <7.4 <8.2 <5.5 <7.8 <8.7 <5.3 Ba/Ia-140 <4.8 <7.2 <5.8 <9.6 <6.2 <4.8 Others <ILD <UD <IlD <LLD <11D <ILD
- b. 50 K-40 1620+135 1550t134 1670+174 1450+135 1720+141 1450+193 Cs-134 <474 <576 <7T0 <C8 <5T3 <C3 Cs-137 <5.1 <5.9 <7.5 <5.4 <5.4 <8.7 Ba/La-140 0. 3 <5.0 <8.7 <3.0 <4.8 <11.2 Others <LLD <UD <UD 41 D <ILD <ID
- b. 7 K-40 1180+40.9 1370+133 1620+167 1690+170 1320+132 1550+140 Cs-134 <T.6 <572 <673 <673 <571 <5T5 Cs-137 <1.8 <5.3 <7.7 <7.4 <5.1 <5.5 Ba/La-140 <1.9 <3.1 <4.0 <5.1 <3.9 (6.4 Others <LLD <UD <UI <UD <ILD <LLD
- b. 4 K-40 1340+187 1370+189 1620+141 1540+165 1770+145 1820+144 Cs-134 <677 <771 <578 <670 <573 <4T6 Cs-137 <10.0 <9.5 <6.0 <7.7 <6.1 <5.3 Ba/la-140 <8.1 <8.4 <5.5 <9.1 <4.9 <5.4 Others <I E <UD <ILD <ILD <ILD <UD
- b. 16 K-40 1700+177 1560+165 1430+192 1820+143 1680A137 1400+134 Cs-134 <674 <676 <770 (574 s5T0 <570 Cs-137 <7.6 <8.4 <10.4 <6.3 <5.7 <5.9 Ba/la-140 <7.6 <7.2 <11.9 <5.0 < 6 . .' <5.3 Others' <LLD <LLD <UB <LLD <ILD <ILD
- b. 65 K-40 1790+144 1410+197 1350+186 1450+136 1670+169 1470+198 bntrol) Cs-134 <570 <778 <777 <573 <677 (ST5 Cs-137 <6.1 <7.5 <8.4 <5.2 <7.8 <8.0 Ba/la-140 <5.2 <5.1 <6.5 <5.9 <6.9 <5.1 Others <UD <UD <ILD <UD <UD <ILD
- Corresponds to sample locations noted on Figure 4, Section VII.
66
n-TABLE 13 MIICH ANIt%L CDiSUS 1987 NUMBER OF gg) lit?TER DISTIM E ) g3) g .3 EN OR APEA(a) CENSUS MAP DN CF MIIfH N;3'NS Scriba 1 (b) 220' 3.0 rdles None 16* 190' 5.2 40C 2 195* 8.0 ND 3 (b) 190' 4.5 2C 6 (b) 62' 2.2 1C ; 26(b) 115' 1.6 to 61 (b) 140' 3.0 15G 62 183* 6.7 SG 63 185' 8.0 39C New Haven 8 130' 9.2 32C 9 95' 5.2 40C 4* 113' 7.8 95C 45 125' 8.0 thr.e 10(b) 130* 2.6 32C 5 146' 7.2 52C 11 130' 8.5 36C 7* 107' 5.5 67C 64 107' 7.9 50C Mexico 12 107' 11.5 22C 13 114' 11.2 1C 14 120' 9.8 57C 15 100* 10.8 None 17 115' 10.2 45C 18 110' 10.0 42C 19 132' 10.5 40C 20 123' 11.2 None 60* 90' 9.5 40C ! 50* 93* 8.2 170C 55* 95' 9.0 55C 21 112* 10.5 80C 49 88' 7.9 6G
=
Richland 22 85* 10.2 42C Pulaski 23 92* 10.5 55C Oswego 24 214' 8.6 None 67 j l l l t
TAPlE 13 (Continued)
?tIICH N!!!!AL Ca' SUS 1927 NUMBER OF NtM1II
' iud OR AREA (a) CENSUS PAP III DECREES ( } DISTMKI( } OF '!IIf!! NC'/JE !!annibal 40 220' 15.2 None St:rling 65** 220' 17.0 42C Volney 25 182' 9.5 ::eno 70 147' 9.4 17C 66 150' 7.8 90C;1G 67 152* 8.3 3G
'IUPALS: 957 Cows (c) 30 Goats 1284 C w s (d)
C = Cchs G = Goats
* = Milk sa ple location ** = Milk sanple control location ND = Did not wish to participate in the survey (1) = References Figure 4 (2) = Based on Nine Mile Point Unit 2 Praetor Centerline >
tbne = tb cws or goats at that location. Ircation was a previous location with crus or goats. (a) = census perfomed out to a distance of approxt~utely ten miles. (b) = Ircation within five miles. (c) = 1Arnber of cows within ten miles. (d) = thrber of ews within entire census area. 68
TABLE 14 CONCENTRATIONS OF CAf91A EMITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g(vet) 1 2 sigma COL ECTION SAMPLE DESCRIPTION Be-7 K-40 I-131 Cs-134 Cs-137 OTHERS (T) 09/14/87 Cabbage <0.14 2.6610.27 <0.027 <0.014 <0.016 <LLD (T) 09/14/87 Squash Leaves 1.8810.19 2.2210.22 <0.019 <0.011 <0.012 <LLD (T) 09/14/87 Beet Creens 0.4710.15 4.8710.49 <0.037 <0.018 <0.017 <LLD $ (P) 09/15/87 Cabbage <0.15 <0.028 <0.015 <0.016 2.0210.25 <LLD (P) 09/15/87 Squash Leaves 1.4710.15 2.0510.20 <0.024 <0.012 <0.012 <LLD (P) 09/15/87 Creen Beans 1.4610.15 <0.026 <0.011 <0.013 (LLD 1.1610.12 (J) 09/14/87 Swiss Chard 0.2710.10 5.2210.52 <0.026 <0.010 <0.011 (LLD (J) 09/14/87 Lettuce 0.5410.17 1.8510.27 <0.036 <0.016 <0.018 <LLD (J) 09/14/87 Pumpkin Leaves 1.2310.14 2.5110.25 <0.023 <0.011 <0.013 <LLD (R) 09/15/87 Squash Leaves 0.9710.11 <0.01? <0.012 <0.012 2.3710.24 <LLD (R) 09/15/87 Cucumber Leaves 1.8110.18 <0.020 <0.010 <0.011 1.3310.15 (LLD-(R) 09/13/87 Creen Beans 0.9410.12 1.0610.12 <0.027 <0.011 <0.013 (LLD (N) 09/15/87 Squash Leaves <0.025 1.7410.17 2.2110.22 <0.014 <0.014 <LLD (S) 09/15/87 Crape Leaves 0.7510.10 1.1810.14 <0.020 <0.009 <0.009 <LLD
TABLE 14 (Continued) CONCENTRATIONS OF CAMMA EMITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g(wet) 1 2 sigma COL ION SMLE DESCRIPTION Be-7 K-40 1-131 Cs-134 Cs-137 OTHERS (V) 09/15/87 Cabbage <0.12 2.8510.29 <0.025 <0.013 <c.012 <LLD (W) 09/15/87 Squash Leaves 1.6910.17 2.4310.24 <0.020 <0.009 <0.009 <LLD (W) 09/15/87 Cabbage 0.1010.06 2.5510.25 <0.021 <0.009 <0.008 <LLD (W) 09/15/87 Swiss Chard <0.12 5.0110.50 <0.028 <0.013 <0.012 <LLD (W) 09/15/87 Beet Greens 0.3410.13 5.8110.58 <0.032 <0.014 <0.013 <LLD (T) 09/14/87 Tomatoes (0.08 2.3510.24 <0.018 <0.010 <0.009 <LLD (P) 09/15/87 Tomatoes (0.09 2.6110.26 <0.020 <0.013 (0.012 <LLD (J) 09/14/87 Tomatoes <0.09 2.4810.25 <0.020 <0.011 <0.011 <LLD (R) 09/15/87 Tomatoes <0.08 2.6210.26 <0.016 <0.010 <0.009 <LLD (N) 09/15/87 Tomatoes <0.07 1.8410.19 <0.018 <0.009 <0.010 <LLD (S) 09/15/87 Tomatoes <0.08 <0.009 2.1710.22 <0.018 0.016210.008 <LLD (U) 09/15/87 Tomatoes <0.11 <0.025 <0.011 <0.011 1.9110.20 <LLD i (W) 09/15/87 Tomatoes <0.20 2.9510.29 <0.049 <0.019 <0.020 <LLD (S) 09/15/87 Weed 0.7610.15 <0.027 <0.015 <0.016 4.9310.49 <LLD
TABLE 15 CONCENTRATIONS OF CAI9IA EMITTERS IN SITE BOUNDARY VECETATION-Results in Units of pCi/g(vet) 1 2 sigma COL T A K, 1-131 Cs-134 Cs-137 OTHERS DESCRIPTION Be-7 E (K) 09/14/87 Viburnum 1.8310.13 3.73ru.24 <0.015 <0.012 <0.001 (LLD (K) 09/14/87 Crape Leaves 1.19+0.11 2.64+0.22 (0.017 <0.001 <0.014 <LLD (K) 09/14/87 Coldenrod 2.48+0.21 6.5410.48 <0.032 <0.022 <0.025- <LLD (L) 09/14/37 Viburnum 1.40f,0.11 2.7510.22 <0.015 (0.010 -<0.011 (LLD (L) 09/14/87 Grape Leaves 1.19+0.11 3.5810.20 <0.019 <0.013 <0.012. (LLD (L) 09/14/87 Goldenrod 2.10+0.18 5.1810.45 <0.022_ <0.018 <0.022 <LLD (M) 09/14/87 Viburnum 1.79_+0.14 2.36_+0.23 (0.017 <0.012 (0.013 (LLD (M) 09/14/87 Crape Leaves 1.4010.13 2.4510.24 <0.016 (0.013 <0.012 <LLD (Mi 09/14/87 Coldenrod 2.37+0.24 5.3910.55 <0.038 <0.025 <0.028 < LLC
.y
lt . 1
. TABLE 16 1987 RESIDENCE CENSUS MAP g) METEOROLOGICAL
-LOCATION DESIGNATION SECTOR DEGREFS(b) DISTANCE (b) w N :- ~ -
w NNE - -
.w NE - -
w ENE - - Sunset Bay A E 82* 1.0 miles Lake Road B ESE 118' O.8 miles: Parkhurst Road C SE 130' 1.4 miles County Route 29 D- SSE 148' 1.2 miles Miner Road E S 170* 1.6 miles Lakeview Road F SSW 212* 1.8 miles Lakeview Road G SW 234' 1.4 miles Bible Camp Retreat H WSW 248' 1.4 miles w W - - w WNW - - w NW - - w NNW - - w This meteorological sector is over Lake Ontario. There are no residences within three miles, (a) See Figure 3, Section VII.
.(b) Based on Nine Mile Point Unit 2 Reactor Centerline.
72
TABLE 17 ENVIRONMENTAL SAMPLE LOCATIONS 4 SAMPLE MAP FIGURE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION DEGREES AND DISTANCE Shoreline 05* Figure 1 Sunset Bay 80* at 1.5' miles Sediment 06 Figure 1 Langs Beach, Control 230* at' 5.8 miles Fish 02* Figure 1 Nine Mile Point Transect 315* at 0.3 miles 2 03* Figure 1 FitzPatrick Transect 55* at 0.6 miles 00* Figure 1 Oswego Transect 235' at 6.2 miles l Surface 03* Figure 1 FitzPatrick Inlet 70* at 0.5 miles . Water 08* Figure 1 Oswego Steam Station 235* at 7.6 miles l 09 Figure 1 Nine Mile Point Unit 1 Inlet -305* at 0.3 miles ] y 10 Figure 1 Oswego City Water 240* at 7.8 miles w i 11 Figure 1 Nine Mile Point Unit 2 Inlet 304 at 0.1 miles Air R-l* Figure 1 R-1 Station, Nine Mile Pt. Rd. 88* at 1.8 miles Radioiodine R-2* Figure 2 R-2 Station, Lake Road 104* at 1.1 miles l and R-3* Figure 2 R-3 Station, Co. Rt. 29 132* at 1.5 miles 4 Particulates R-4* Figure 2 R-4 Station, Co. Rt. 29 143* at 1.8 miles
- R-5* Figure 1 R-5 Station, Montario Point Rd. 42' at 16.4 miles l D1 Figure 2 D1 Onsite Station, Onsite 69* at 0.2 miles 1 D2 Figure 1 D2 Offsite Station, Offsite 117* at 9.0 miles l E Figure 1 E Offsite Station, Offsite 160* at 7.2 miles i F Figure 1 F Offsite Station, Offsite 190* at- 7.7 miles
! G Figure 2 G Onsite Station, Onsite 250* at 0.7 miles l H Figure 2 H Onsite Station, Onsite 71* at 0.8 miles l I Figure 2 I Onsite Station,'Onsite 98* at. 0.8 miles
! J Figure 2 J Onsite Station, Onsite 110* at 0.9 miles K Figure 2 K Onsite Station, Onsite 132* at 0.5 milec l G Figure 1 G Of fsite Station, St. Paul St. 225* at 5.3 miles 1
OTechnical Specification location t I (1) Based on Nine Mile Point Unit 2 Reactor Centerline-4 _. n- - - - -
- +
112a.1Q2nIF e (continued) h ENVIRONMENTAL SAMPLE LOCATIONS j
'I SAMPLE MAP FIGURE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION DEGREES AND DISTANCE (
Thermo- 3 Figure 2 D1 Onsite Station 69* at 0.2 miles luminescent 4 Figure 2 D2 Onsite Station 140* at 0.4 miles Dosimeters 5 Figure 2 E Onsite Station 175* at 0.4 miles (TLDs) 6 Figure 2 F Onsite Station 210* at 0.5 miles 7* Figure 2 G Onsite Station -250* at 0.7 miles 8* Figure 1 R-5 Offsite Station 42* at 16.4 miles 9 Figure 1 D1 Offsite Location 80* at 11.4 miles 10 Figure 1 D2 Offsite Location 117* at 9.0 miles 11 Figure 1 E Offsite Location 160* at 7.2 miles 12 Figure 1 F Offsite Location 190* at 7.7 miles 13 Figure 1 G Offsite Location 225* at 5.3 miles 14* Figure 1 SW Oswego - Control 226* at 12.6 miles y 15* Figure 2 West Site Boundary 237' at 0.9 miles
- 18* Figure 2 Energy Information Center 265* at 0.4 miles 19 Figure 2 East Site Boundary 81* at 1.3 miles 23* Figure 2 H Onsite Station, Onsite 70* at 0.8 miles 24 Figure 2 I Onsite Station, Onsite 98* at 0.8 miles 25 Figure 2 J Onsite Station, Onsite 110* at 0.9 miles 26 Figure 2 K Onsite Station, Onsite 132* at 0.5 miles 27 Figure 2 North Fence, JAFNPP 60* at 0.4 miles 28 Figure 2 North Pence, JAFNPP 68* at 0.5 miles 29 Figure 2 North Fence, JAFNPP 65 at 0.5 miles 30 Figure 2 North Fence, JAFNPP 57* at 0.4 miles 31 Figure 2 North Fence, NMP-1 276* at 0.2 miles 39 Figure 2 North Fence, NMP-1 292* at 0.2 miles 47 Figure 2 North Fence, JAFNPP 69 at 0.6 miles 49* Figure 1 Phoenix, N.Y. - Control 170* at 19.8 miles 51 Figure 1 Oswego Steam Station, East 233* at 7.4 miles 52 Figure 1 Oswego Elementary School, East 227* at 5.8 miles 53 Figure 1 Fulton High School 183* at 13.7 miles 54 Figure 1 Mexico High School 115* at 9.3 miles 55 Figure 1 Pulaski Gas Substation, Rt. 5 75* at 13.0 miles 56* Figure 1 New Haven Elementary School 123* at 5.3 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline
TABLE 17 (Continued) ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE gg MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION DEGREES AND DISTANCE Thermo- 58* Figure 1 Co. Rt. I and Alcan 220* at 3.1 miles luminescent 75* Figure 2 North Pence, NMP-2 5* at 0.1 miles Dosimeters 76* Figure 2 North Pence, NMP-2 25* at 0.1 miles (TLDs) 77* Figure 2 North Fence, NMP-2 45* at 0.2' miles 78* Figure 2 East Boundary, JAFNPP 90* at 1.0 miles 79* Figure 2 County Route 29 115* at 1.1 miles 80* Figure 2 County Route 29 133* at 1.4 miles 81* Figure 2 Miner Road 159* at 1.6 miles 82* Figure 2 Miner Road 181* at 1.6 miles e3* Figure 2 Lakeview Road 20C* at 1.2 miles 84* Figure 2 Lakeview Road 225* at 1.1 miles 85* Figure 2 North Fence, NMP-1 .';1* at 0.2 miles j 86* Figure 2 North Fence, NMP-1 315* at 0.1 miles 87* Figure 2 North Fence, NMP-2 341* at 0.1 miles 88* Figure 1 Ilickory Grove Road 97* at 4.5 miles 89* Figure 1 Leavitt Road 111* at 4.1 miles 90* Figure 1 Route 104 and Keefe Road 135* at 4.2 miles 91* Figure 1 County Route 51A 156* at 4.8 miles 92* Figure 1 Maiden Lane Road 183* at 4.4 miles 93* Figure 1 County Route 53 205* at 4.4 miles 94* Figure 1 Co. Rt. I and Kocher Road 223* at 4.7 miles 95* Figure 1 Lakeshore Camp Site 237* at 4.1 miles 96* Figure 1 Creamery Road 199* at 3.6 miles 97* Figure 2 County Route 29 143* at 1.8 miles 98* Figure 1 Lake Road 101* at 1.2 miles 99 Figure 2 Nine Mile Point Road 88* at 1.8 miles 100 Figure 2 Co. Rt. 29 and Lake Road 104* at 1.1 miles 101 Figure 2 County Route 29 132* at 1.5 miles 102 Figure 1 Oswego County Airport 175* at 11.9 miles 103 Figure 2 Energy Information Center, East 267* at 0.4 miles 104 Figure 1 Parkhurst Road 102* at 1.4 miles 105 Figure 2 Lakeview Poad 198* at 1.4 miles 106 Figure 2 Shoreline Cove, East of NMP-1 274* at 0.3 miles 107 Figure 2 Shoreline Cove, East of Nt!P-1 272* at 0.3 miles
- Technical Specification location (1) Itaned 01: Mine Mile Po i ra t Unit 2 Centerline
(continued) ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION DEGREES AND DISTANCE ( Cows Milk 7 Figure 4 Indicator Location 107* at. 5.5 miles 16 Figure 4 Indicator Location 190* at 5.2 miles 50 Figure 4 Indicator Locatien 93* at- 8.2 miles 55 Figure 4 Indicator Location 95* at 9.0 miles 60 Figure ~4 Indicator Location 90* at 9.5 miles 4 Figure 4f Indicator Location 113* at 7.8 miles j 65* Figure 4 Control Location 220* at 17.0 miles- H Food J Figure 3 Indicator Location 103* at 1.9 miles Products K* Figure 3 Indicator Location 106* at 0.9 miles L* Figure 3 Indicator Location 82* at 0.8 miles M* Figure 3 Control Location 223* at 15.0 miles N Fiqure 3 Indicator Location 171* at 1.6 miles
$ P Figure 3 Indicator Location 10l* at 1.9 miles R Figure 3 Indicator Location 114* at 1.5 miles S Figure 3 Indicator Location 141' at 1.9 miles T Figure 3 Indicator Location 84* at 1.6 miles V Figure 3 Indicator Location 112* at 2.0 miles W Figure 3 Control Location 225' at 12.6 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline
l V DATA SUMMARIES AND CONCLUSIONS The results of the 1987 Radiological Environmental Monitoring Program i 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 af 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 1987 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 radionuclide in terms of potential increased dose to man, in relation to natural background, is necessary. There are four separate groups of radionuclides that were detected in the environment during 1987. Several of these radionuclides could pos-sibly fall into three of the four groups. The first of these groups is naturally occurring radionuclides. It must be realized that the environ-ment contains a broad inventory of naturally occurring radioactive ele- ' ments. Background radiation as a function of primordial radioactive cle-ments and cosmic radiation of solar origin, offers a constant exposure to the environment and man. These radionuclides, such as Th-228, Ra-226, Be-7 and especially K-40, account for a majority of the annual per capita background dose. A second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in '.he earth's upper atmosphere. The detonation frequency during the eat er 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on weapons testing in 1963 which greatly reduced the global inventory through the decay of short lived radionuclides, deposition, a ed the removal (by natural processes) of radio-77
nuclides from the food chain by such processes as weathering and sedi-mentation. Since 1963, several atmospheric weapons tests have been con-ducted by the People's Republic of China. In each case, the usual radio-nuclides associated 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 con-ducted in October of 1980. The resulting fallout or deposition from this test has influenced the background radiation in the vicinity of the site and was very evident in many of the sample medias analyzed during the 1981 sample program. Quantitles 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 6f radionuclides was detected as a -result of the Cher-nobyl accident which occurred in the Soviet Union during Aoril, 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 Che~'nobyl related radionuclides in the environment show that the contribution from such nuclides in some cases (such as 1-131 and t 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 origin of these radio-nuclides was a direct result of fallout from the Chernobyl accident. Dur-ing 1987, Cs-137 was detected in several milk samples collected during the first half of the grazing season. The presence of Cs-137 in the milk sam-ples is attributed to the ubiquitous concentrations of Cs-137 from weapons testing and from the Chernobyl releases. The fourth group of radionuclides detected in the environment during 1987 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 78 :
difficult, if not impossible, using routine sampling programs. The dose to man as a result of these radionuclides is small and significantly less than the radiation exposure from naturally occurring sources of radiation and 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 treno analysis, dose to man, etc. An attempt has been made not only to report the data collected during 1987, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources, it is important to note that detected concentrations of radionuclides that are possibly related to operations at the site are very small and are not of environ , mental significance. In regard to these very small quantities, it will be further noted that at such minute concentrations the assessment of the significance of detected radionuclides is very difficult. Therefore, con-centrations in one sample that are two times the concentration of another, for example, are not significant overall. Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in , another. in Section V each sample medium is discussed. Concentrations of ra-l dionuclides detected and exposure to man are presented and scrutinized. in the routine implementation of the Radiological Environmental Moni-toring Program, additional or optional environmental pathway media are sampled and analyzed. These samples are obtained to monitor the secon-dary pathways not required by Technical Specifications and to maintain the analytical data base established in 1975 when the plant began commercial operation. These additional samples include; aquatic vegetation (cladophora), bottom sediment, mollusk, milk (Sr-90), meat / poultry and soil samples, in addition to the optional sample media, many additional I locations are sampled and analyzed for those pathways required by Techni-cal Specifications. These additional sample locations are obtained to insure that the important environmental pathways are monitored in a comprehen-sive manner and again, to maintain the analytical data base. Data are presented and evaluated only for those pathways / media required by 79 [
Technical Specification. Data from additional sample locations common with Technical Specification required sample media are normally. included in the data presentation and evaluation. When additional locations are includad, the use of this data will be specificallv noted in section V. Section VI, titled HISTORICAL DATA, contains samp:e statistics from previous environmental sampling. The process of determining the impact (or lack of impact) of plant ooeration on the environment includes the scrutiny of past analytical data, a tool by which trends are discarned. 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-a rt detection capabilities improve, data comparisons become difficult. For example, minimum detection capabilities for the- 1969 analyses of environmental samples would be considered anomalous by current stan-dards. 4 f, I l i e I 80 t
SURFACE WATER (LAKE) PROGRAM Tables 1 through 4 list the 1987 analytical results for the aquatic / lake water media sampled during the 1987 sampling program. Fish samples were obtained at -two onsite locations. The transect designations used for the onsite sampling locations are NMPP (02) and JAF (03). 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. Lake water samples were collected from the inlet canals of Nine Mlle Point Unit #1, Nine Mile Point Unit #2, J. A. Fitz Patrick N . P. P. , and the Oswego Steam Station, in addition to power plant samples, a routine sam-pie of the Oswego city drinking water inlet was also obtained. The Oswego Steam ' Station served as the control location. Shoreline sediment samples were obtained in an area downstream from the site which proved to have existing recreation value and a physical make up which t suitable for sampling. The control sample was collected from an area upstream from the site with a similar physical makeup. i } 81
L 1
- 1. SHORELINE SEDIMENT-- TABLE 1 Shoreline sediment samples were collected twice during 1987. Col-lections were made in April and October at one indicator location (Sunset Beach), and at one control location ( Lang's B each) . The results of these samples collected at the indicator and control loca-tions are presented in Table 1.
Several radionuclides were detected in sediment samples using gamma spectral analysis. These radionuclides were all naturally occurring. K-40 was detected at both the control location and indicator location. The results ranged from 15.4 pCl/g (dry) to 15.7 pCi/g (dry) at the indicator location, and 8.1 pCi/g (dry) to 14.7 pCi/g (dry) at the control location. AcTh-228 and Ra-226 were detected at both the indicator locations. The maximum detectable concentrations for AcTh-228 and Ra-226 were 0.93 pCi/g (dry) and 2.16 pCi/g (dry) respectively at the indicator location and 0.67 pCl/g (dry) and 1.11 pCl/g (dry) respectively for the control location. 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 radio-nuclides related to the operation of the power plants were detected in the 1987 shoreline sediment samples. No long term historical data exists to compare the shoreline sediment indicator sample results with previous results. The Technical Specifi-cation Requirement to collect and analyze shoreline sediment was first initiated in the second half of 1985. A review of sample results for 1985 and 1986 indicated only naturally occurring radionuclides present in shoreline sediment. The inventory of nuclides identified in 1987 is the identical to that seen in 1985 and 1986. The 1987 concentration are consistent with previous determinations, 82
- 2. FISH - TABLE ?
A total of 24 fish samples were collected in the spring season (June 1937) and in the fall season (October 1987). Collections were made utilizing gill nets at one offsite' location greater than five miles from the site (Oswego Harbor area), and at two onsite locations in the vicinity of the Nine Mile Point Unit #1 (02), and the James A. 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 1987 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 six of the fish samples (including control samples) collected in 1987. Detectable concentrations of K-40, a naturally occurring radionuclide, were found in all fish samples collected for ] the 1987 program. Spring fish collections were comprised of three separate species and ten individual samples. The three species represented one feeding type. Lake trout, brown trout and small mouth bass are highly pre-dacious 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 i species were collected in the spring samples. Cs-137 was detected in five of the seven indicator samples and in all of the control samples collected in the spring samples. The indicator samples contained a mean Cs-137 concentration that was slightly high-er than the control sample mean concentration. The concentrations ! detected in the indicator samples are not significantly different from the control results and are considered to be representative of normal base line or background concentrations of Cs-137 found in Lake Ontario fish . Cs-137 in the spring indicator samples ranged from 83
0.026 pCl/g (wet) to 0.036 pCi/g (wet) and averaged 0.030 pCi/g (wet) with one sample analysis resulting in a value of 0.025 pCl/g (wet) and one resulting in a lower limit of detection (LLD) value of 0.027 pCl/g (wet). Control samples for this same' period ranged from 0.017 pCi/g (wet) to 0.039 pCl/g (wet) and averaged 0.026 pCi/g (wet ) . All three of the control samples had positive identification of Cs-137. K-40 was detected in all of the spring samples collected. K-40 is a naturally occurring radionuclide and is not related to powcr plant op-erations. Detectable concentrations of K-40 in the inaicator samples ranged from 1.95 to 3.85 pCi/g (wet) and 3.62 to 4.02 pCl/g (wet) for the control samples. No other radionuclides were detected in any of the spring fish samples. Fall sample collections wee comprised of five separate species and fourteen individual samples. Six samples of lake trout, two samples of Chinook Salmon, three samples of Walleye, two samples of Suckers, and one sample of Small Mouth Bass 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 gilt net in October and November and included two additional species not found in the spring. Cs-137 was detected in ten of the fall indicator samples and all four of the control samples. The indicator samples showed an average , Cs-137 concentration that was equal to the control location average. Cs-137 in lake trout samples at the indicator locations ranged from 0.024to 0.032 pCi/g (wet) and averaged 0.028 pCi/g (wet). The lake Trout samples from the control location had a Cs-137 concentration ranging from 0.034 to 0.040 pCl/g (wet), and a mean of 0.037 pCl/g (wet) . Chinook Salmon samples showed Cs-137 concentrations of 0.037 pCi/g (wet) for the control sample and 0.063 pCi/g (wet) for the indicator sample (only one sample collected at both locations). Walleye samples showed a concentration of 0.030 pCi/g (wet) at the control location. Cs-137 was not detected in the Walleye samples from 84 4
the indicator locations. Only one sample of Small Mouth Bass was available during the fall season (Nine Mile Point indicator location). The associated Cs-137 concentration was 0.036 pCi/g ( wet) . White Sucker samples were available only at the indicator locations. Cs-137 was not detected in these samples. The one species of bottom feeder collected during the fall season (white sucker) showed no detectable Cs-137 because of different feeding habits and because this species is not in the same position on the food chain as the other predacious species. K-40 was detected in all of the fall fish samples collected. Detectable concentrations of K-40 in the indicator samples ranged from 2.48 to 6.19 pCl/g (wet) and 3.19 to 4.28 pCl/g (wet) for the control sam-ples. No other radionuclides were detected in any cf the fall fish samples. A review of historical data shows that since 1980 the Cs-137 concen-tration in Lake Ontario fish, in the vicinity of the Nine Mile Point promitory, has remained stable. The average Cs-137 concentration in fish for this time period was 0.0421 pCi/g (wet) including both the indicator and control results. During this time period of 1980-1987, the measured concentration for the indicator and control sample loca-tions demonstrate little significant difference in measured concen-trations. This fact would strongly indicate that the source of Cs-137 found in the fish population is most likely residual cesium from the weapon testing. The specific data for 1987 did show a slight increase from 1986 results for both the indicator and control location. This increase can be attributed to the natural variation in resident fish population of the area. A review of figure 6 (section Vil) demon-strates the relative stability of Cs-137 concentrations from 1980 to the present. Figure 6 also shows that the current level of Cs-137 in the indicator fish samples has decreased significantly since 1976 when a peak concentration of 1.4 pCi/g (wet) was detected. The current mean indicator concentration of 0.033 pCl/g (wet) shows a decrease in concentration from 1976 by a factor of approximately 40. Control sample results have also decreased from a maximum level of 0.12 pCl/g (wet) in 1976 to a level of 0.031 pCl/g (wet) in 1987. 85
I The general decreasing trend for Cs-137 is most probably a result of the cesium becoming unavailable through ecological cycling. A signif-icant portion of Cs-137 detected since 1978 in fish is a result of weapons testing fallout, and the general downward trend in concen-trations will continue as a function of inventory reduction through the natural processes and radiological decay of the cesium. Th.ere was no apparent effect from 1986 Chernobyl Nuclear Plant accident during 1987 relative to Cs-137 results in fish samples, although' an minor effect may have been detected in 1987 since both indicator and control location mean results increased slightly. The Chernobyl accident may have increased the Cs-137 inventory slightly in the area but the increase in fish Cs-137 concentration is most likely due to natural variables as noted above. 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 consumed contains an average Cs-137 concen-tration of 0.033 pCi/g (wet) (annual mean result of indicator samples for 1987), the whole body dose received would be 0.049 mrem per year. The critical organ in this case is the liver which would receive a calculated dose of 0.076 mrem per year. The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mile Point area (indicator samples). No radiological decay is assumed for the calculation of doses. Conservative whole body and critical organ doses can be calculated for the consumption of fish from the control location as well. In this case the consumption rate is assumed to remain the same (21.0 kg per year) but the average annual Cs-137 mean concentration for the con-trol samples is 0.031 pCi/g (wet). The calculated Cs-137 whole body dose is 0.046 mrem per year and the associated dose to the liver is 0.071 mrem per year. In summary, the whole body and critical organ doses observed as a result of consumption of fish is small. Doses received from the 86
1 l l l 1 l consumption of indicator and control sample fish are approximately the same with the dose from indicator samples being slightly higher. Doses from both sample groups are considered of background expo-sure. A graph of past Cs-137 concentrations can be found in Section Vil and a Historical Data Table is included in Section VI. 87
l-
- 3. SURFACE WATER - TABLES 3 AND 4 1987 surface water samples were analyzed monthly for gamma emitters (using gamma spectral analysis). Tritium analyses wer' performed quarterly. Quarterly samples (i.e., analysis for Tritium) were com-posites of monthly samples. In addition, three optional sample loca-tions were sampled and analyzed for gamma emitters and Tritium.
These additional sample locations includa the Nine Mile Point Unit #1 and Unit #2 inlet canals and the City of Oswego drinking water sup-ply which is drawn from Lake Ontario. The drinking water supply sample consisted of twice per week grab-sampling. The v.e y+1 cal results for the 1987 surface water sample showed no cvidence of p!cnt related radionuclide 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 1987. Gamma spectral analysis was performed on 24 monthly composite sam-pies (two locations) required by the RETS. With the exception of Tritium, only two radionuclides were detected in samples from the five locations over the course of 1987. Both these radionuclides are natu-rally occurring and not plant related. K-40 was detected intermittently in both Technical Specification ra-quired intake canals. The James A. FitzPatrick inlet canal samples showed K-40 was detected in ten of the 12 monthly samples and ranged from 33 to 272 pCi/ liter. K-40 in the Oswego Steam Station inlet canal was detected in nine of the twelve samples and ranged from 49 to 267 pCl/ liter. The Nine Mlle Point Unit #1 Inlet Canal, Unit #2 Inlet Canal, and the Oswego City water samples showed K-40 detections in five, nine, and seven respectively of the twelve monthly samples from each location. The K-40 concentrations for these sam-ples ranged 54-227 pCi/ liter, 32-292 pCi/ liter, and 85-292 pCl/ liter respectively. 88
i Ra-226 was also detected intermittently in both locations required by technical specifications and the other optional sample locations. Sam-pies from the FitzPatrick location showed Ra-226 in nine of the twelve monthly samples and concentrations ranged from 54 to 130 pCi/ liter. The control sample location (Oswego Steam Station) showed Ra-226 in seven of the twelve monthly samples and ranged in concentratiers from 76 to 127 pCi/ liter. Ra-226 was detected in four of the twelve samples taken from the Nine Mlle Point Unit 81 Inlet Canal and ranged from 88 to 137 pCl/ liter. The Nine Mile Point Unit #2 Inlet Canal showed Ra-226 detected in seven of the twelve samples and ranged in concentration from 50 to 174 pCl/ liter. [ Tritium samples are quarterly samples that were a composite of the appropriate monthly samples. Tritium was detected in each sample taken at both locations. Tritium concentrations for the James A. FitzPatrick inlet canal ranged from 160 pCi/ liter to 410 pCl/ liter and showed a man concentration of 322 pCi/ liter. The Technical Specifi- , cation control location (Oswego Steam Station inlet canal) showed Tritium results which ranged from 140 pCl/ liter to 270 pCl/ liter with a mean concentration of 210 pCi/ liter. Tritium was also detected in each of the optional samples taken with the exception of the Nine Mile 7 Point Unit #1 Inlet Canal first quarter composite. This particular sample analyses indicated that the Tritium concentration was below the
~
Low Limit of Detection (LLD) or the sensitivity of the analyses. A summary of Tritium results for the 1987 sample program is listed below: Sample Tritium Concentration pCi/ liter Location Minimum Maximum Mean ( Annual) JAF Inlet 160 410 322 Oswego Steam Inlet 140 270 210 NMP #1 Inlet 210 390 283 NMP #2 Inlet 260 310 292 City Water 'ntake 210 320 275 A review of current data shows that the Tritium concentrations in the lake are consistent relative to location. The source of Tritium 89
detected in the lake water is past testing of thermonuclear devices in
-the atmosphere. It has been estimated that in the early 1960's the concentration of Tritium of surface water in the United States was as high as 4000 pCi/ liter. The levels of Tritium in the environment has been- reduced over the years through physical process to the levels that are currently being measured. The Tritium concentration measured during the 1987 sampling program are considered to be background levels and are not the result of the operation of the nuclear facilities at Nine Mile Point.
Review of past environmental surface water data for Cs-137 from 1979 through 1987 shows that this radionuclide was detected only once at the control location during 1979, at a concentration of 2.5 pCl/ liter. Cs-137 at the indicator location (JAF inlet canal)- was detected only once, in 1982, at a concentration of 0.43 pCl/ 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 positive Cs-137 result from the indicator location (JAF inlet canal) during 1982 was detected in a January composite sample and may have been a result of inlet canal tempering (the addition of discharge water to the inlet canal) or instrument background. Cs-137 was not detected during 1987 in surface water samples. Other plant related radionuclides detected during a review period of 1979 - 1987 include only Co-60. The control sample location results showed that Co-60 was detected once in 1981 (the May composite sample) . This result is suspect and, as noted above, may be the result of contamination during handling or may be instrument back-ground. This result was 1.4 pCi/ liter. Results from the indicator location showed that Co-60 was detected three times during 1982 and averaged 1.9 pCl/ liter. These positive results were attributed to inlet canal tempering and instrument background. Co-60 was not
- detected during 1987 in surface water samples, i
l l ! 90 l t
Review of previous environmental data for K-40 and R -226 showed that the detectable concentrations found during 1987 were representa-tive of concentrations found during 1979-1986. 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 1987 and showed a peak average value of 641 pCi/ liter (1982) and a minimum average value of 234 pCl/ liter (1979). The annual mean Tritium result at the indicator location for 1987 was 322 pCl/ liter. Mean Tritium results of the control location (Oswego Steam Station) cannot be evaluated with regard to long term historical data since sampling was only initiated at this location in 1985. The maximum Tritium value for the control station for the period of 1985-1987 was 550 pCi/ liter. The minimum value for this same time period was 230 pCi/ liter. Some idea of the variability of historical control sample data can be obtained, however, by review of previous data from the City of Oswego drinking water samples. The drinking water samples are not likely to be affected by the station because of the effects of the distance, lake currents, and the discharge of the Oswego River. Therefore, this previous sample data represents acceptable control sample data for evaluation purposes. The Oswego City water intake is located in the same general vicinity as the Oswego Steam Station inlet. Mean annual Tritium results from previous city water samples from 1976 to 1987 show that the Tritium concentrations have decreased. The maximum a'inual average was found in 1976 (652 pCl/ liter) and the minimum in 1982 (165 pCilliter). The 1987 City water annual mean results was calculated as 275 pCl/ liter. Mean annual results from 1979-1987 have remained relatively consistent. The 1985, 1986, and 1987 ennual mean Tritium results for the Oswego Steam Station were 287 373, and 210 pCl/ liters respectively, These results were slightly nigher than the drinking water samples (with the exception of 1987) t ut were within the natural variability range. 91
The impact, as expr;ssed as a dose to man, is not evaluated because no plant related radionuclides were detected in surface water samples with the exception of Tritium. Any impact associated with the fluctu-ation of Tritium levels are considered to be background and not a result of operations at the site. 9 92
TERRESTRI AL PROGRAM Tables 5 through 1 14 represent the analytical results for the terrestrial samples collected for the 1987 reporting period. 93
- 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 nine offsite and six cnsite sample locations. Five of the nine offsite locations are required by Technical Specifications. These sample locations are R-1, R-2, R-3, R-4, (all located near the site boundary) and R-5 (located at a control location beyond any significant influence from the site). Data contained on Tables 5 and 6 also shows the results from other air sampling loca-tions not required by the RETS. These locations are designated as D-1 onsite, G onsite, H onsite, I onsite, J onsite, K on site , D-2 offsite, E offsite, F offsite, and G offsite locations. A total of 52 samples were collected from the control location R-5 and 208 indicator samples were collected from indicator locations R-1, R-2, R-3, and R-4 during 1987.
The gross beta analysis requires that samples are counted a minimum of twenty-four hours after collection to allow for the decay of natu-rally occurring radionuclides with short half-lives. The average yearly gross beta indicator concentration was 0.021 pCi/m3 in 1987. The average yearly control concentration was also 0.021 pCi/m3 for the same time period. The minimum, maximum, and average gross beta results for sample locations required by Technical Specification are presented below: l l Loca tion *
- Minimum
- Maximum
- Average
- R-1 0.009 0.040 0.021 R-2 0.009 0.037 0.021 R-3 0.010 0.036 0.021 R-4 0.009 0.039 0.021 -
R-5 (control) 0.009 0.037 0.021 l * - Concentration in pCi/m3 l ** - Locations required by the Technical Specifications 94 i E
The small fluctuations observed in the general gross beta activity can be attributed to changes in the environment, especially seasonal changes. The concentration of naturally occurring radionuclides in the lower limits of the atmosphere directly above land areas are affected by time related processes such as wind direction, snow cover, soll temperature, and soil moisture content. With the exception of the 1985 sample data, which was effected by the Chernobyl accident, the general trend in air particulate gross beta activity has been one of decreasing activity since 1974. The mean gross beta concentration at the control station has decreased from a level of 0.121 pCl/m3 in 1974 to 0.021 pCl/m 3 in 1987. Results from the indicator stations ranged from 0.111 pCi/m 3 in 1974 to 0.021 pCi/m3 in 1987. 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, 1985, and 1987 from both the Indicator and control locations have been approximately simi-lar and ranged from 0.021 to 0.026 pCl/rr.3 This level of activity appears to be a baseline range. The 1986 annual mean result was 0.039 pCl/m 3 for both the indicator and control stations. This con-centration is slightly higher than 1983-85 and 1987 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. 95
- 2. MONTHLY PARTICULATE COMPOSITES (GAMMA EMITTERS) - TBL. 9 Weekly air particulate samples were composited by location to form monthly composite samples. The monthly composite samples 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 for ' which analytical results are presented include D-1 onsite, G onsite, H onsite, I onsite, J onsite, K onsite, D-2 offsite, E offsite, F offsite, and G offsite locations. The results of all monthly composite samples are included on Table 9.
The results for the monthly composite samples showed positive co-tections for Be-7, K-40, and Ra-226. Each of these radionuclides, are naturally occurring. Be-7 was detected in each of the monthly composite samples from all locations required by Technical Specifica-tions. Be-7 concentrations ranged from 0.048 to 0.196 pCi/m3 for the indicator locations (R-1, R-2, R-3, and R-4) . The control location results (R-5) showed Be-7 ranging from 0.069 to 0.169 pCl/m . K-40 3 was found intermittently in the Technical Specification required monthly composite samples and ranged from 0.018 to 0.054 pCl/m3 at the control location (R-5). The Technical Specification requ red indicator location results for K-40 ranged from 0.015 to 0.051 pCi/m . 3 Ra-226 was detected in ten Technical Specification required indicator samples and the values ranged from 0.015 to 0.051 pCi/m2 The Technical Specification control locations yielded two positive identi-fications of Ra-226 which ranged from 0.020 to 0.031 pCi/m . 3 Historically, the naturally occurring radionuclides Ra-226, K-40, and Be-7 have shown fluctuations that are representative of naturally changing conditions. No significant trends were noted during 1987. Two plant related fission product radionuclides were detected during 1987 at an optional sampling location. Co-60 and Mn-54 were detected at the G offsite air monitoring station during the nionth of July. Co-60 was detected at a concentration of 0.0017 pCi/m 3 and Mn-54 was detected at a concentration of 0.0032 pCi/m3, The presence of 96
, m 1
l
)
Co-60 or Mn-54 was not detected at any of the other air monitoring stations, including the control station during, this same time period. An evaluation of the presence of Co-60 and Mn-54 on the monthly air particulate composite was made. The weekly samples, which make up the monthly composite were analyzed separately, and it was deter-mined that the detected activity was present on a filter which repre-sents the time period of 06/30/87 - 07/07/87. Meteorological data was reviewed for the sample period in question, and it was determined that the wind was toward the general location of the G offsite air monitoring station for a duration of less than one hour during the sample period. Plant effluent records were also reviewed for this same sample period. The review of effluents show that the measured concentrations of Co-60 and Mn-54 in the sample were inconsistent with the measured release rate of these radionuclides in plant effluents. Using a his-torical meteorological dispersion factor , the calculated release rate from the plant would be significantly above that which was actually measured during the sample period. The location of G offsite monitoring air station was evaluated with respect to the site.. G offsite is at a distant location (approximately 5.3 miles) from the site. Two other air monitoring stations are locat-ed in the same general direction as G offsite but at a distance of less than one mile from the site. No plant related radionuclides were detected at these air monitoring stations during this same sample period. For ground level release, the air sampling stations located closer to the site would have a much higher D/Q (deposition coeffi-cient, 1/m2 ) and X/Q (dispersion factor sec/m 3 ) factors and would have a higher potential for detecting concentrations of plant effluents in the environment if present in the sector in which G offsite is located. Based on the above evaluation, it was concluded that the activity detected on G offsite filter, July 07, 1987, was the result of contam-ination from improper handling of the sample. Contamination of air 97
particulate samples has occurred in a -few isolated cases in the past. On such occasions, activation products such as Co-60 and Mn-54 were detected. No other plant related or naturally occurring radionuclides were detected using gamma spectroscopy during 1987. The location, concentration, range, mean, and frequency of occur-rence of each radionuclide detected during 1987 at the Technical Specification required locations are included below. Radionuclide Location Range
- M,ean* Frequency **
Ra-226 Indicator 0.015 - 0.051 0.022 10/48 Control 0.020 - 0.031 0.025 2/12 K-40 Indicator 0.015 - 0.064 0.041 23/48 Control 0.018 - 0.054 0.033 5/12 Be-7 Indicator 0.048 - 0.196 0.129 48/48 Control 0.069 - 0.169 0.129 12/12 Mn-5 4* *
- Indicator 0.003 0.003 1/12 Control ND ND ND Co-60*** Indicator 0.002 0.002 1/12 Control ND ND ND
* - Rt.sults in units of pCi/m 3. ** - Frequency is number of times detected over the number of samples.
- - Location is optional location G offsite.
ND - Not detected. A review of historical data shows that the presence of Co-60 has been noted in the past. Co-60 can be a result of weapons testing, con-tamination 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 pCl/m 2. Average concentrations decreased signifi-cantly during 1979 and. increased in 1980 from approximately 0.0007 to 98
0.0016 pCi/m3 respectively. 1981 and 1982 average Co-60 concen-trations decreased to 0.0007 and 0.0005 pCi/m . 3 Average indicator and control concentrations were approximately equal during 1977 to 1982. The 1983 indicator average Co-60 concentration was 0.0007 pCi/m3 or slightly greater than the 1982 concentration. The 1983 average control and indicator mean Co-60 concentration was 0.0007 pCl/m 3which 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 tne unused filters. Co-60 during 1984 averaged 0.00079 pCl/m 3 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 initially pr oduced by the 1980 Chinese weapons test. Co-60 was not detected during 1985-86 in air particulate samples. During 1987, Co-60 was detected once at a concentration of 0.0017 pCi/m 3. This measured value was considered to be the result of contamination as noted above. 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 were approximately equal and averaged 0.039 pCi/m . Cs-137 average concentrations at the indicator and control 3 locations 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 levels. 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/m . 3 The 1983 mean Cs-137 con-centration for the indicator and control composite samples were 0.0002 and 0.0002 pCi/m 3 which was a reduction from 1982 results. Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite samples. As noted above for the average annual 99
Co-60 results, the reduction in Cs-137 results is attributed to nuclear , decay and ecological cycilng 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 the Chernobyl accident. Cs-137 was not detected during the 1987 air monitoring program. 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 l 1984 and 1985 as a result of nuclear decay and ecological cycling. These include Zr-95, Ce-141, Nb-95, Ce-144, iAn-54, Ru-103, Ru-106 l and Ba-140. In addition, La-140 was detected once during 1983 and infrequently during 1978 and 1981. La-140 was not detected during 1984 and 1985. However, La-140, Nb-95, Ru-103, Ru-106, and 1-131 were detected in air particulate composite samples during 1986 as a result of the fallout from the Chernobyl accident. The above refer-enced radionuclides were not detected in the 1987 air monitoring pro-g ram. Detectable radionuclides in air particulate samples during 1987 were a result of improper handling of one of the air particulate filters. Since the contamination of this filter was not a result of effluents from the site, no assessment of the impact to man is presented here. Graphic representations of air particulate composite Co-60 and Cs-137 concentrations are presented in Section Vll. 100
.- _ _ _ ____ ______________________ _______________________________ )
t
- 3. AIRBORNE RADIOlODINE (I-131) - TABLES 7 AND 8 !
k Airborne radiolodine is monitored at the air sampling stations that are also used to collect air particulate samples (see Section V.3). The air . monitoring network is ~made up of fifteen sample -locations. There , are nine stations. considered offsite locations. Of these nine, five are i required by Technical Specifications and are designated as R-1, R-2, ; R-3, and R-4 These stations are located near the site boundary and one indicator station. A fifth Technical Specification location des-ignated as R-5 is located beyond any significant influence from the plant and is considered a control location. As noted under the air particulate gross beta section, ten additional air sampling locations are maintained in addition to those required by Technical Specifica-
- tion. ' Six of these stations are located within the site boundary and are designated as D1 onsite, G onsite, H onsite, I onsite, ) onsite,
- and K onsite. The four remaining optional stations are located offsite and are designated as D2 offsite, E offsite, F offsite, and G offsite, i
The analytical data for each of these sampie locations is included in this report., j During the 1987 sampling prog ram, airborne radiolodine was not i detected in any of the fif ty-two weekly samples collected at the con-trol location required by Technical specifications. The LLD values j for the control location anged vom < 0.004 to < 0.026 pCl/m 3. lodine-131 (1-131) has bee 1 detected in the past at control locations. 4 During 1976, the mean off-site 1-131 concentration aver aged 0.604 q oCl/m3 1977 showed an 1-131 concentration that decreased to 0.323 pCi/m3 and for 1978 the concentration decreased by a factor of ten to . 0.032 pCi/m . 8 During 1919 - 1981 and 1983 - 1985, 1-131 was not i detected. 1-131 was detected once during 1982 at a concentration of 0.*039 pCl/m8 . In 1987 Radiolodine-131 (I-131) was detected in 2 of the 208 indicator samples required by Technical Specifications. I-131 was also detected
- in 2 of the 312 optional indicator samples taken during 1987. 1-131 1
was detected at R-1 offsite and R-2 offsite sample locations during the sample period of September 1-8, 1987. The concentrations 101 I
. ~ - - - - , ---.,~~u,,. p - ,,--,--_,n,- - , _ - . - ,,,.,-.,.n_n,m, mer ,,p-e +-- -.- e-,-w,---m----r y
detected were 0.011 pCl/m 3 at R-1 and 0.018 pCl/m3 at R-2 with the mean concentration equal to 0.014 pCi/m . 3 During this same sample period, lodine-131 was also detected at two of the optional onsite air monitoring stations, ! onsite and J onsite. The detected concentra-tions were 0.016 pCi/m3 at i onsite and 0.061 pCl/m3 at J onsite. Radiolodine was also detected at the I onsito location for the sample period of September 21-28, 1988. The measured concentration was 0.008 pCl/m3 . The two onsite locations which showed positive detec-tions are located within the site boundary and the concentrations detected are not representative of concentrations present onsite. The R-1 and R-2 stations are located near the site boundary and are representative of offsite concentrations. The environmental 1-131 concentrations detected in 1987 are outlined as follows: Sampie Sample Concentration End Date S_tation pCi/m3 09/08/87 R1 (offsite)* 0.011 1 0.006 R2 (offsite)* 0.018 0.008 l (onsite)** 0.016 t 0.009
) (onsite)** 0.061 1 0.014 09/28/88 I (onsite)** 0.008 1 0.006
- Sample locations required Technical Specification
- ** Optional sample locations i
A meaningful dose estimate is difficult to make for the 1-131 concen-l trations measured at the onsite sampling stations as there are no ! residence or individuals in the immediate vicinity of the sample location. An accurate estimate of the dose to man can be made using the measured offsite concentrations. The critical organ for iodine isotopes is the thyroid gland, and the maximum exposed age group is
'he child. Using Standard Regulatory Guide 1.109 methodology, an
! inhalation rate of 3700 m3 per year and the average indicator location 1-131 concentration, conservative doses can be calculated, in order to be conservative and to simplify the computations, no radiological decay is assumed, and the maximum exposed individual is assumed to i 102
r rerialn at the site boundarv for one week. Maximum child thyp, eld and whole body doses are presented below. Sample - Mean Weeks Thyroid Whole Body Locations (s) Concentration (1) Detected Dose (2) Dose (2) Indicator 0.014 1 0.004 0.000007
' Control < LLD 0 ----- --------
(1) - Concentration in pCi/m3 (2) - Dose in mrem for 1987 The calculated dose for the critical U)dividual would be 0.004 mrem .to the thyroid and 0.000007 mrem tu the whole body. These doses are very small and of no significance. A review of plant gaseous effluent data for the sample periods in which l-131 was detected in the environment was performed. This data shows that the I-131 release rates are well within the design objective of the plant as outlined in the appropriate sections of the Environmental Technical Specifications. The detectable levels of I-131 in the environment are consistent with the measured source terms at the plant for the same sample period. A review of historical data shows that I-131 has been detected in the past at offsite stations. During 1976, the mean offsite 1-131 concen-tration averaged 0.604 pCl/m3 . 1977 showed an 1-131 concentration that decreased to 0.323 pCl/m3 and for 1978, the concentration de-creased by a factor of ten to 0.032 pCl/m . During 1979, 1980, 1981, 3 1983, 1984, and 1985, 1-131 was not detected. 1-131 was detected once during 1982 at a concentration of 0.039 pCi/m3 . 1-131 has been detected in the past at the onsite stat ons and was detected at a mean concentration of 0.328 and 0.309 pCi/m 3 during 1976 and 1977. The average concentration decreased to 0.041 pCl/m 3 during 1978 and was not detected during 1979. The 19E0-82 average concentrations were 0.013, 0.029, and 0,016 pCi/m 3 which were re-103
r ductions in view of previous l-131 concentrations. During 1983, the mean 1-131 concentration was 0.028 pCl/m3 which represented a silght _ I increase compared to 1982, 1-131 in onsite and cffsite samples was-a . result of l-131 from weapons ' testing. The concentrations detected [ during 1983 at the onsite sample stations were a result of operations I at the site. 1-131 was not detected in any of the 1984 or 1985 onsite samples. 1-131 was detected in a total of -75 weekly samples collected [ during the 1986 sample program. The concentrations detected in 1986 ra ;d from a minimum of 0.011 pCi/m2 to a maximum of 0.36 pCl/m . 3 f Each of the positive detections of I-131 in 1986 were a direct result of the Chernobyl Nuclear accident. i i The end result of the 1987 l-131 sampling effort showed no significant impact due to the operation of the plant. During .1987,1-131 was not fl detected in any other environmental sample media including milk and green leafy vegetables. : h l f i l i [ l [ i i I 104 ! I
- 4. TLD (ENVIRONMENTAL DOSIMETRY) - TABLE 10 TLD's were collected once per quarter during the 1987 sample year.
The TLD results are, for the most part, an average of eight indepen-dent readings at each location and are reported in mrem per standard month. TLD's required by the Technical Specifications (RETS) in-ciude two TLD's at each location with four independent readings per TLD or a total of eight readings. TLD results included on Table 10 are comprised of TLD's required by the RETS and special interest TLD's not required by the RETS. In 1986, TLD's were collected on approximately April 1, 1987, June 30,1987, September 30, 1987, and
- December 30, 1987.
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 i (in areas beyond any significant influence of the generating facil-itles) . Special interest TLD's are located at or near large industrial sites, schools, or proximal town or communstles. 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. Most of the TLDs required by the Technical Specifications during 1987 were initiated in 1985 as a result of the issue of new Technical Speci-fications by the NRC. Therefore, these TLDs can only be compared
- to 1985-1986 results. Other TLDs, which include a few TLDs 3
required by the Technical Specifications (i.e. , numbers 7, 14, 15, 18, 23, 49, 56, and 58) and other optional TLDs, can be compared to results prior to 1985 since these TLDs were established before % 1985. 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 105
previous or existing onsite air sampling stations. TLD's located at the air sampling stations include numbers 3, 4, 5, 6, 7, 23, 24, 25, l and 26. The results for TLD's are generally consistent with previous years results although a slight decrease is noted when compared to 1986 figures. TLD #3 is located in the vicinity of Nine Mile Point Unit 2 and is between the Unit I facility and Fitz Patrick. The results for TLD #3 were approximately double the results of the other TLD's during the third and fourth ouarters because of the effects from Unit 1 and FitzPatrick as well as the startup and testing pro-gram at NPMNS Unit #2. Other onsite TLD's include special interest TLD's located near the s north shoreline of the Unit 1, Unit 2, and FitzPatrick facilities but in close proximity to radwaste facilities and the Unit'I reactor building. These TLD's include numbers 27, 28, 29, 30, 31, 39, and 47 Re-sults for these TLD's during 1987 were variable and ranged from 5.0 ( to 32.8 mrem per standard month as a result of activitics at the rad-waste facliities and the operating modes of the generating facilities. ; Results for 1987 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 six times control TLD results, i Additional on-site TLD's are located near the on-site Energy Informa-tion Center and the associated northeast shoreline. These T LD's l ' include numbers 18, 103, 106, and 107. TLD number 107 is a new 4 TLD and was established in the second quarter of 1987. Therefore, no previous results for this TLD exist, although results were slightly t greater than control TLD results and ranged from 5.7 to 6.7 mrem per standard month. TLD number 18 results during 1987 were fairly 1 consistent with previous years and ranged from 5.7 to 6.2 mrem per ; standard month. TLD number 103 was established during the second L quarter of 1985. This TLD is located on the east side of the Energy information Center. Results were consistent with the results from l 1985 and ranged from 5.4 to 6.2 mrem per standard month. TLD , number 106 was established during the second quarter of 1986 and is in close proximity to TLD #107. Results for #106 ranged from 6.0 to 6.6 mrem per standard month and where slightly less than 1986 106 [
results. TLD numbers 28,106, and 107 (noted above) are located to 4 the West of the Energy information Center and t0 the East of the Unit I facility. 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, 82, 83, 84, 7,18, 85, 86, and 87. TLD numbers 78, 79, 30, 81, 82, 83, 84, 7, and 18 showed results that were consistent with Control TLD results, and ranged from 4.4 to 6.2 mrem per standard month. TLD numbers 75, 76, 77, 23, 85, 86 and 87 showed results that rang-ed up to twice the results of Control TLD's. These results ranged
- from 4.4 to 14.3 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 Reacter Building and Radwaste facilities of Nine Mile Point Unit 1, Unit 2, and the radwaste facilities of FitzPatrick.
A net site boundary dose can be estimated from available TLD results . and Control TLD results. TLD results from TLD's located near the site boundary in sectors facing the land occupied by members of the public (excluding TLD's near the generating facilities and facing Lake 4 . 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. 4 i 1 Quarter Net Site Property Boundary Dose
- 1 +0.1 2 -0.1 3 -0.3 4 +0.2
- 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 107
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 22} degree meteorological sectors. These .TLDs are required by Technical Speci-fications. At this distance, TLD's are not present in eight of the sixteen meteorological sectors over Lake Ontario. Results for this group of TLD's during 1987 fluctuated slightly as a result of changing naturally occurring conditions and the normal variation in the concentration of naturally occurring radionuclide - found in- the ground at each of the locations, rThese TLD's were established in 1985 and included numbers 88, 89, 90, 91, 92, 93, 94 { and 95. Results fluctuated from 4.3 to 6.0 mrem per standard month. Results during 1987 can only be compared to 1985-1986 yearly results , since this group of TLD's was established in 1985. These results are generally consistent with control data results during 1987 The ; overall results for this group of TLDs were consistent with 1985 and 1986 results although 1986 data was slightly higher, 4 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-f ! 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, l 12, 13, 15, 19, 51, 52, 53, 54, 55, 56, 58, 96, 97, 98, 99, 100, 101, l and 102 and ranged from 3.5 to 6.8 mrem per standard month. All j the TLD results from this group were within the general variation noted for the Control TLD's. Results during 1987 for TLD's estab-lished during previous years were consistent with results noted for those years. l l The fifth group of TLD's include those T LD's considered as Control l TLD's and are required by RETS. These TLD's include numbers 14, I l 49, and number 8 which is an optional location. Results for 1987 ( 108 l
t ranged from 4.6 to 6.6 mrem per standard month. Results from 1987 were consistent with previous years results. A slight increase was noted in the second quarter of 1986 and may have been the result of the Chernobyl Nuclear Plant accident. 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 T LD's total), T LD's located at special , interest areas (6 TLD's total) and TLD's located at control locat'.ons (2 TLD's total). As noted previously, since the present RET 3 be- , came effective in 1985, these TLD's for the most part, can only be evaluated for 1985 through 1987. TLDs located at the site boundary averaged 6.2 mrem per standard , month during 1985. During 1986, site boundary TLDs averaged 7.0 mrem per standard month. As noted previously, this group of TLDs g can fluctuate i i TLD's located at the site boundary averaged 6.2 meem per standard : month during 1985. During 1986, site boundary TLD's 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 generating facilities. An increase was noted during ! 1986, although such an increase was noted for all TLD's including ( control TLD's. During 1987, site boundary TLDs averaged 6.1 mrem ; per standard month, i TLD's located offsite at a distance of 4 - 5 miles from the site in each of the land based meteorological sectors averaged 5.0 mrem during ; 1985. During 1986 and 1987, offsite sector TLD's averaged 6.0 and l 5.2 mrem per standard month respectively. 1986 results also demon- ! strated an increase for this group of TLD's. l t e 109 i i
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 TI.D's averaged 5.3 mrem per standard month during 1985. During 1986, this same group of TLD's averaged 6.1 mrem. The 1987 results showed a slight decrease when compared to the 1985 - 1986 results. The 1987 aver-age for the special interest TLDs was 5.1 mrem per standard month. 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 averaged 5.4 mrem. During 1986, this same group of TLD's averaged 6.3 mrem per standard month. The 1987 average was equal to 5.2 mrem per standard month. A measurabic increase was noted in the second quarter of 1986. This increase may have been the result of the Chernobyl Nuclear Plant accident. During 1987 all TLD groups required by the RETS showed a decrease when compared to 1986. The percent decrease for all groups ranged from 13% to 17% with the average decrease equal to 15%. The site boundary TLD's showed the smallest decrease (13%). The offsite T LD's , located 4 - 5 miles from the site also showed a decrease of 13%. The control TLD's showed a 17% decrease from 1986 to 1987 Overall, environmental TLD results for 1987 showed no significant impact from direct radiation measured outside the site boundary. l l 110
- 5. MILK - TABLES 11 AND 12 ,
t i 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 1987. The RETS require that three locations be sampled for milk within 5.0 miles of the site. During 1987, there were no milk sample locations within 5.0 miles of the site. The locations that were sampled during 1987 are located from 5.5 to , 9.5 miles from the site. Control milk samples were collected from location #65 which is located 17 miles from the site. Sample loca49n descriptions for all milk sample locations utilized during 1987 are ! listed below. r Location No. Direction 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 65 (Control) SW 17.0 During 1987, milk samples were collected at each of the six indicator locations and the control location in the first half and the second half of each month. Samples were collected during the months of April through December 1987. Since 1-131 was not detected during Novem-ber and December of 1986 no additional samples were collected in January throug h March of 1987. For each sample, analyses were performed for gamma emitters (analysis by Celi, Ce detectors) and 1-131 using a resin extraction. Sample analysis results for gamma emitters are found on Table 12 and for 1-131 on Tahle 11. The gamma spectral analysis of the bimonthly samples showed K-40 to be the most abundant radionuc!!de detected in the milk samples col-lected during 1987 K-40 was detected in every sample analyzed and rang ed in concentration from 744 pCl/ liter to 1,820 pCl/ liter at the indicator locations and 1,190 pCl/ liter to 1,790 pCl/ liter at the control 111
location. K-40 is a naturally occurring radionuclide and is found in many of the environmental media sampled. Cs-137 was detected in 2 of 108 indicator milk samples collected during 1987. Cs-137 was not detected in any of the control location samples during 1987. The LLD values for the control location analysis range from < 5.2 to < 11.4 pCl/l. The Cs-137 concentration measured at the indicator locations ranged from 5.5 pCi/ liter (location
#7) to 8.1 pCi/ liter (location #55).
Both Cs-137 concentration were detected in the May 4, 1987 samples. Location #1 is located 5.5 miles from the site and location #55 is 9.0 miles from the site. The cause of the low concentration of Cs-137 found during May is a result of the 1986 Chernobyl Nuclear Plant accident. Du!!ng 1986, Cs-137 was detected fifteen times and was found at both indicator and control locations. Cs-137 was not detected after September, 1986 which corresponds to the end of the grazing season. A monthly questionnaire showed that there wore no milk animals released for pasturing during May of 1987 at locations #7 and #55. Therefore, these animals were fed stored feed from 1986. Animals at other locations were released for pasturing during May except for one location. Information relative to other nuclear sites on _the East Coast showed that Cs-137 was also detected during the first half of 1987 and, at some sites, during the entire year, it is felt that stored feed consumed during May, 1987 at locations 7 and 55 contained enough Cs-137 fallout from the 1986 Chernobyl I accident that analyses showed detactable levels of Cs 137. The amount of stored feed consumed at the other locations was consid-erably less than at locations #7 and 55 except for one location, in addition, the greatest of the two detectable levels was found at location 455 which is 9.0 miles from the site, in the event Cs--137 in May milk samples was a result of activities at the site, it would be improbable that the greatest detected quantity would be found at a i distance of 9.0 miles from the site. Cs-137 release levels from the 112 l t
site during April and May,1987 were normal. The fact that no other plant related radionuclides were detected in the two samp'es which contained Cs-137 further supports the conclusion that the power plent at the Nine Mlle Point site was not the source of the Cs-137. Each of the milk samples collected in 1987 were also analyzed for radiolodine ( 1-131 ) , 1-131 was not detected during 1987 in any of the indicator or control samples. All 1987 l-131 milk sample results are reported as the lower limit of detection (LLD). The LLD results for 1987 milk ; samples ranged from < 0.1 pCl/ liter to < 0.5 pCl/ liter. r The impact as a result of Cs-137 in 1987 milk samples can be assessed by calculating conservative doses to man from the consumption of milk & with detectable quantities of Cs-137. For the purposes of a calculated dose, the 1987 mean indicator sample Cs-137 concentration is used (6.8 pCi/ liter). ! I Assuming a consumption rate of 330 liters (87.18 gallons) per year for f an infant (Regulatory Guide 1.109 maximum exposed individual), the i whole body dose would be 0.008 mrem and the critical organ dose would be 0.114 mrem to the liver. The calculated doses are based on 1 month of milk consumption. l The calculated dose to an adult can also be determined assuming a I consumption rate of 110 liters (29.06 gallons) per year (Regulatory [ Guide 1.109) and a mean Cs-137 concentration of 6.8 pCl/ liter for the ; indicator locations. The resultant doses are 0.019 mrem to the whole body and 0.012 mrem to the liver (critical organ). The calculated ; doses are based on 1 month of milk consumption. For the purpose of illustration, the significance of the above doses I can be brought into perspective by a comparison to the U. S. ! Department of Health and Human Services (US/DHHS) Guide for Cs-137 ingestion. The EPA / PAG maximum limit for Cs-137 Ingestion is ; 240,000 pCl. The resultant whole body and liver doses to the maxi- l mum exposed individual (infant) would be 10.4 mrem and 146.6 mrem l respectively. The total calculated doses as a result of the measured [ Cs-137 concentrations are very small by comparison. : 113
An additional comparison can be made to naturally occurrina K-40. K-40 has been noted in almost all environmental samples at significant levels. A 70 kilogram adult weighs approximately 154 pounds and contains approximately 0.1 microcurlos of K-40 as a result of normal life functions (inhalation, consumption, etc. ). The dose to the bone tissue is about 20 mrem per year as a result of internally deposited K-40 (Elsenbud). For comparison purposes, an adult bone dose can be calculated that results from the consumption of milk with an aver-age 1987 concentration of Cs-137. Using the same criteria used for calculating the preceding doses, the adult bone dose is 0.014 mrem per year. This calculated dose is small and is only 0.0007 of the annual bone dose received from naturally occurring K-40. Historical data shows the absence of Cs-137 in milk during 1984 and 1985. It should be noted that the two generating facilities (NMP Unit
#1 and JAFNPP) were, for the most part, at full capacity during the 1984 and 1985 grazing season and Cs-137 was not detected in milk samples. Cs-137 was detected in milk during 1983, however, at a concentration of 5.1 pCi/ilter-(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. Results from 1986 showed a mean Cs-137 concentration of 8.6 pCi/ liter at the indicator locations. Cs-137 in 1986 milk samples was a result of the 1986 Chernobyl Nuclear Plant accident. During 1987, Cs-137 was found in two indicator samples only at a mean concentration of 6.8 pCl/ liter and was also a result of the Chernobyl accident.
In addition to gamma spectre! analysis, each of the milk samples collected in 1987 were analyzed for 1-131. lodine-131 was not detect-ed during 1987 in any of the control or indicator samples. All 1-131 milk results are reported as lower limits of detection (LLD). The LLD results ranged from < 0.1 to < 0.5 pCl/l for all milk samples. No other radionuclides were detected in milk samples using gamma spectral analysis or resin extraction. 114
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 boon detected in milk samples only in conjunction with fresh fallout from atmospheric testing or from the Chernobyl Nuclear Plant accident in 1986. Numerical evaluation shows that annual mean results ranged from 0.2 pCilliter to 6.9 pCl/ liter at the indicator locations during 1976-1978. 1-131 during these years is a result of intermittent weapons testing. During 1979 - 1985, 1-131 in milk samples at the indicator locations was not detected, except during 1980. The mean result during 1980 was 0.4 pCi/ liter and was a result of the 1980 Chinese Weapons Test. Results from 1986 showed that I-131 was detected at a mean concentration of 5.2 pCl/ liter as a result of the Chernobyl accident. 1-131 was not detected during 1987 in milk samples. Historical data for 1-131 from the control location showed that 1-131 was detected during 1980 at a mean concentration of 1.4 pCi/ liter. There was not detectable 1-131 during the period of 1978-1985 with the exception of 1980. During 1986, 1-131 from the control location showed a mean concentration of 13.6 pCi/ liter as a result of the Chernobyl accident. 1-131 was not detected during 1987 at the control location. Historical data and graphic representations of milk sample results for Cs-137 and 1-131 are presented in Sections VI and Vll. 4 3 115
- 6. LAND US_E CENSUS - TABLES 13 AND 16 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 22) i degree meteorological sectors. The milch animal census (milk animal) was actually conducted out to a distance of ten miles in order to provide a more comprehensive census.
The milch animal census is an estimation of the number of cows and gc,ats 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. l The number of milch animals located within the ten mile radius of the site was estimated to be 1,245 cows and 30 goats for the spring 1987 census. No new locations with milk animals were found since the 1986 census. The number of cows decreased by 8 and the number of goats increased by 20 with respect to the 1986 census. The residence census was conducted during the late summer to identi-fy the nearest residence in each of the sixteen 22) degree meteoro-logical sectors within a distance of rive 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 1987 residence census showing the applicable sectors, degrees and distance of each of the nearest residences are found on Table 15. The nearest resi-dence locations are shown on the census map, figure 3. i 116 J
I
- 7. FOOD PRODUCTS - TABLE 14 i
Food product samplM collected during 1986 were comprised of garden ; vegetables, fruit, and other types of vegetation. Samples were collected during the late Summer / Fall harvest season as part of the required samples for the Nine Mlle Point Unit #1 and #2 Technical Specifications. The collection of monthly food product samples is not required by the JAF Technical Specifications when milk sampling is being performed. The food product sample results pre-sented on Table 14 are for optional samples. Samples were collected from seven indicator locations and one control location. The indicator locations were represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and all site release po!nts 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, lettuce, squash leaves, and swiss chard which are all considered broadleaf vegetables. Where broadleaf vegetables were not available, non-edible broad leaf vegetation, non-broadleaf fruits, or vegetables were collected. Non-edible broad l leaf vegetation collected in 1987 consisted of pumpkin leaves, green bean leaves, cucumber leaves , and grape leaves. Non-broadleaf fruits or vegetables collected in 1987 consisted of tematoes. At the control location, one sample of each similar type of fruit or vegetable was collected. Fruits and vegetables were colle . '.ed in the late sum-mer harvest season. K-40 was detected in all broadleaf and non-broadleaf vegetables and fruits. Broadleaf vegetables (Swiss chard, squash leaves, grape leaves, beet greens, cabbage, lettuce, pumpkin leaves, and green bean leaves) showed concentrations of K-40 ranging from 1.06 pCi/g to 5.81 pCi/g (wet). Non-broadleaf fruits (tomatoes) showed concen-trations of K-40 ranging from 1.84 pCi/g to 2.95 pCl/g (wet). Be-7 was detected in a number of the broadleaf vegetables, but was not detected in any of the non-broadleaf fruits ( tomatoes ) . The Be-7 117
concentrations .in the broadleaf vegetables ranged from 0,10 pCilg (wet) to 1.88 pCi/g (wet). l Cs-137 was detected in one non-broadleaf sample (tomato) from the indicator locations. The detected quantity was near the limit of de-tection and was 0.016 pCl/g (wet). LLD values for all samples ranged from 0.009 to 0.020 pCl/9 (wet). The - detected quantity of Cs-137 was found at location "S". Cs-137 was not detected in any of
~
the broadleaf samples, as would be expected, it is likely that the quantity of Cs-137 found is a result of uptake by the. tomato plant. The source of the cesium is most likely from the soll. The ultimate source of Cs-137 is from weapons testing, operations at the site, or both. Cs-137 has been detected in soll samples from areas at the site and at areas well beyond the site as a result of past weapons testing.
- A portion of the detected quantity may be a result of past operations at the site. Cs-137 was not detected at the control location, j
- No other radionuc!! des were detected in the 1987 collection of fruits l and vegetables.
Review of past environmental data Indicates that K-40 has been con-f ] sistently detected in food crop samples. K-40 concentrations have l fluctuated from one sample to another but the annual ranges have re-malned relatively consistent from year to year. Be-7 has been de-l tected occasionally during the past on leafy vegetables (1978 through 1982, .and 1984). 1 Cs-137 has been detected intermittently during the years of j 1976-1986 at the indicator locations and during the years of 1980-1986 i at the control locations (control samples were not obtained prior to 1980). Review of indicator sample results from 1976-1986 showed that I Cs-137 was not detected during 1976-1978, 1981-1"84 and 1986. During 1979 and 1980, Cs-137 in fruits and/or vegetables showed i annual mean concentrations of 0.004 and 0.036 pCilg (wet) respec-tively. Cs-137 was found at one indicator location during 1985 at a concentration of 0.047 pCi/g (wet). Control samples during 1980-1986 showed Cs-137 detected only during 1980 at a concentration of 0.02 118 4 l.
pCl/g (wet). Cs-137 detected during the past at both Indicator and control locations is indicative of weapons testing. During 1987, Cs-137 was found at the indicator locations at a mean concentration of 0.016 pCl/g (wet). Cs-137 was not detected at the control location during 1987. The impact of detectable Cs-137 in food product samples can be evaluated by calculating a dose to the maximum exposed individual e a result of consumption. Using standard methodology from NRC Regulate , Guide 1.109, the maximum exposed organ is the bone of a
- child. The maximum whole body dose would be to an adult. The Cs-137 concentration is 0.016 pCl/g (wet) and is conservatively assumed to be a result of operations at the site and is assumed to remain consistent throughout the year. The consumption rate is ,
assumed to be a maximum consumption rate of 26 kg per year for a child. The calculated doses are 0.14 mrem per year to a child's bone tissue (maximum organ dose) and 0.02 mrem per year to the whole body. The maximum whole body dose occurs to the adult. Assuming a Regulatory Guide 1.109 maximum consumption rate of 64 kg per year for an adult, the riaximum organ dose is 0.11 mrem to the liver and 0.07 mrem to the whole t,ody. A maximum child organ dose of 0.14 mrem /yr. and an adult whole body dose of 0.07 mrem per year are small and insignificant when compared to dose from the natural ra-diation environment. 4 119
- 8. SITE BOUNDARY VEGETATION - TABLE 15 The Radiological Effluent Technical Specifications (RETS) require that samples of three different kinds of broad-leaf vegetation (edible or inedible) be collected at the site boundary in two areas of highest D/Q (deposition factor) for a total of six samples. The sampilng of broad leaf vegetation is performed in accordance with Table 6.1-1 (RETS) in lieu of the garden census specified in section 6.2 (RETS).
The control location was represented by samples of three similar broad-leaf varieties grown 9-20 miles distant in a least prevalent wind direction. The three broad-leaf varieties were comprised of wild grape leaves, viburnum, and goldenrod (all non-edible). The site boundary and control vegetation samples were collected during the late summer harvest season. Two naturally occurring radionuclides (K-40 and Be-7) were' detected in the 1987 samples. K-40 was detected in all the broad-leaf vege-tation samples collected in September,1987. The site boundary vege-tation samples (indicators) showed concentrations of K-40 ranging from 2.64 pCi/g (wet) to 6.54 pCi/g ( wet ) . The control samples showed concentrations of K-40 ranging from 2.36 pCi/g (wet) to 5.39 pCl/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 1.19 pCi/g (wet) to 2.48 pCl/g (wet). The control samples showed concentrations of Be-7 ranging from 1.40 pCl/g (wet) to 2.37 pCi/g (wet). Both Be-7 and K-40 are naturally occurring radionuclides. No other radionuclides were detected in the 1987 RETS vegetation samples. The vegetation samples collected during 1987 at the site boundary are not consumed by humans. These samples are collected as indicator samples because of the high D/Q values which exist at the site 120
boundary. The collection of site boundary vegetation samples was started in the Fall of 1985 with the implementation of the Radiological Effluent Technical Specifications. A review of the 1985 - 1986 site bcundary vegetation sample results show that K-40 and Be-7 are routinely detected in these samples, in ; 1986 K-40 samples ranged from 2.83 to 9.80 pCl/g (wet) for the indicator samples and 3.99 to 8.33 pCl/g (wet) for the control sam-ples. The K-40 concentration detected in the 1985 samples are similar in range as those found in 1986 - 1987, as expected, in 1985, 19E6, ano 1987 Be-7 was detected in each of broad leaf samples taken. The analytical results for Be-7 have been consistent from year to year. Cs-137 was detected in both 1985 and 1986. The 1985 sample results showed positive detections of Cs-137 in three of the six indicator sample and no positive detections of Cs-137 in the control samples. The 1985 Cs-137 indicator concentrations ranged from 0,043 to 0.259 pCi/g (wet) with a mean concentration of 0.162 pCl/9 (wet). Cs-137 was detected in four of six indicator samples collected in 1986. The 1986 sample concentrations ranged from 0.031 to 0.035 pCl/g (wet) with a mean concentration of 0.033 pCl/g (wet). Cs-137 was detected r in one of the control samples at a cor. centration of 0.035 pCl/g (wet). The presence of Cs-137 in 1985 and 1986 site boundary vegetation samples can be attributed to several sources: atmospheric nuclear testing, fall out from the Chernobyl Nuclear Plant accident, and/or plant operations at the site. The presence of Cs-137 in the control vegetation sample in 1986 indicates that the source may be past weapons testing or fall out from the Chernobyl accident. I t i 121 l
.m. _ _ _ _ _ _
- 9. ENVIRONMENTAL SAMPLE LOCATIONS - TABLE 17 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 centerlino (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.
122
- 10. !NTERLABORATORY 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 O p-erating Report. Presqntly, the only NRC approved interlaboratory comparison program is the USEPA Cross Check Program. Section Vill shows the results of the EPA's reference results and the licensee's results in tabular fo rm. Some of the EPA reference samples have 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.
123
CONCLUSION The Radiological Environmental Monitoring Program is conducted each year to determine the radiological impact of the James A. FitzPatrick Nuclear Power Plant on the local environment. As demonstrated by the a.ialytical results of the 1987 program, the major radiological impact on the environ-ment was the result of fallout from atmospheric nuclear testing and the 1986 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, in regard to doses as 'a result of man-made radionuclides, a significant portion of the small doses received by a member of the public was from past nuclear weapons testing and fa'llout from the Chernobyl accident, it should be noted that most of the radionuclide detected in 1986, as a result of the Chernobyl accident, were not present in the sample media collected for the 1987 p rog ram. 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 and sources other than plant operation, it has been demonstrated that almost all environmental samples contain traces of radionuclides which are a result of weapons testing, Chernobyl, or naturally occurring sources (primordial and/or cosmic related). Whole body doses to man as a result of natural sources (naturally occurring radionuclides in the soll and lower atmo-sphere) in Oswego County account for approximately 67 mrem per year as demonstrated by control environmental TLD's. Possible doses due to site operations are a minute fraction of this particular natural exposure. Using the data presented in this report, and earlier reports as c basis, it can be concluded that no appreciable radiological environmental impact has resulted from the operation of the James A. Fitz Patrick Nuclear Power Plant. 124
l l l l REFERENCES '
- 1. U.S. Nuclear Regulatory Commission Regulatory Culde 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, C. , 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 (NCRP),
Natural Background Radiation in the United States, NCRP Report No. 45, 1975.
- 6. National Council on Radiation Protection and Measurements (NCRP),
Cesium-137 from the Environment to Man: Metabolism and Dose, NCRP Report No. 52, 1977.
- 7. National Council on Radiation Protection and Measurements (NCRP),
Radiation Exposure from Consumer Products And Miscellaneous Sources, NCRP Report No. 56, 1977
- 8. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, "Environ-mental Technical Specifications for Nuclear Power Plants", December 1975.
- 9. U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Culde 4.8, "An Acceptable Radiological Environmental Monitoring Program", November,1979, 125
- 10. Eisenbud, Merril, Environmental Radioactivity, Second Edition , Aca-demic Press, New York, New York,1973.
- 11. Francis, C. W., Radlostrontium Movement in Soils and Uptake in Plants, Environmental Sciences Division, Oak Ridge National Laborato-ry, U.S. Department of Energy,1978.
- 12. National Council on Radiation Protection and Measurements (NCRP),
Radiation Exposure from Consumer Products and Miscellaneous 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.
14 ICRP Publication Number 29, Radionucilde 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,
- 16. Kathren, Ronald E., RADIOACTIVITY IN THE ENVIRONMENT:
SOURCES, DISTRIBUTION, AND S URVEILLANCE, First Edition. Harwood Academic Press, New York, NY,1984 126
VI HISTORICAL DATA ' I Sample Statistics from Previous Environmental Sampling ; The mean, standard deviation, minimum value, maximum value, and range, were calculated for selected sample mediums and isotopes. - t Special Considerations: ' [
- 1. Sample data listed as 1969 was taken from the NINE MILE POINT, ;
PREOPERATION SURVEY,- 1969 and ENVIRONMENTAL MONITORING i RE PO RT FOR NIAGARA MOHAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION, NOVEMBER, 1970.
- 3. Samplo data listed as 1974, 1977, 1978, 1979, 1980, 1981, 1982, 1983, 1984, 1985, and 1986 was taken from the respective environmental operating reports for Nine Mlle Point Nuclear Station and James A.
l FitzPatrick Nuclear Power Plant. [
- 3. Only measured values were used for statistical calculations, i
r i r t
~
i
?
t t h i [ 127
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Fish Samples ST A N D A RD MEAN MAllMUM MINIMUM RANCE Cs-137 pCi/g (wet) DEVi m 1987 0.031 0.009 0.040 0.017 0.023 1986 0.025 0.004 0.032 0.021 0.011 1985 0.034 0.008 0.047 0.026 0.021 1984 0.032 0.009 0.038 0.015 0.023 1983 0 050 0.009 0.060 0.040 0.020 1982 0.047 0.009 0.055 0.027 0.026 1981 0.043 0.016 0.062 0.028 0.034 1980 0.059 0.032 0.110 0.029 0.031 1979 0.04 0.01 0.06 0.03 0.93 197g 0.09 0.05 0.20 0.04 0.16 1: '7 0.13 ONLY ONE DATA POETI 13/4 0.43 0.37 0.94 0.09 0.35 1969(PRE-0PE R Ail 0N AL ) W DATA ---- ---- ---- ---- INDICATOR MEAN AM ' N IMUM MININ M RNE 3 g (wet) y AilON 1987 0.033 0.011 0.063 0.024 0.039 1986 0.028 0.012 0.051 0.009 0.042 1985 0.030 0.009 0.045 0.018 0.027 1984 0.043 0.008 0.061 0.033 0.028 1983 0.050 0.009 0.060 0.030 0.030 l 1982 0.050 0.008 0.064 0.034 0.030 1981 0.061 0.021 0.10 0.02/ u.oi; 1980 0.061 0.029 0.100 0.030 0.070 19 7 g 0.10 0.14 0.55 0.02 0.53 19 7 g 0.08 0.02 0.10 0.03 0.07 1977 0.29 0.21 0.79 0.13 0.o6 i 19 74 0.5/ 0.02 4.40 0.08 4.3; U'UD U'U" d3 0'0I '" 19 6 9 (PR E - 0 PE R Ail 0 N AL) 128
HISTORICAL ENVIRONMENTAL SAMPLE DATA 1 CONTROL Surface (IAe) Water MEAN STANDARD MAllMUM MINIMUM RANGE Tritium rCi/1 DE VI ATIO N 1987 210.0 64.8 270 140 130 1986 373.0 157.0 550 250 300 1985 287.5 95.4 430 230 200 1984 205.0 21.? 220 190 30 1983 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 7o 1979 258.7 73.7 303 174 114 1978 303.8 127.5 490 215 175 1977 407.5 97.4 530 300 230 1974 <MDL --- --- --- --- 1969(PRE-0PER Ail 0N AL ) GDL --- --- --- --- INDICATOR Surface (The) Water MEAN STANDARD M All M U M MINIMUM RANCE Tritium pCi/l DE VI ATION 1987 322.5 111.2 410 169 250 1986 380.0 118.0 500 260 240 1985 530.0 448.6 1200 250 950 1984 282.0 98.1 370 110 260 1983 317.0 116.9 560 190 370 1982 641.0 891.1 2780 194 2586 1981 258.3 76.4 388 183 205 1980 263.0 95.4 457 150 307 1979 234.0 40.7 286 176 110 1978 389.4 119.9 560 253 307 1977 450.0 67.2 530 380 150 19 74 440.0 84.9 500 380 120 19 6 9 (PR E - 0 PE R Ail 0N AL) 440.0 84.9 500 _. 380 120 129
s. HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Air Particulate MEAN STANDARD MAllMUM MININUM RANCE Gross Beta pCi/m3 DEV! Ail 0N 1987 0.021 0.006 0.037 0.009 0.028 1986 0.039 0.049 0.272 0.008 0.264 1985 0.024 0.006 0.043 0.013 0.030 1984 0.026 0.007 0.051 0.013 0.039 1983 0.024 0.009 0.085 0.007 0.078 1982 0.033 0.012 0.078 0.011 0.067 1981 0.165 0.135 0.549 0.016 0.533 1980 0.056 0.04 0.291 0.009 0.232 1979 0.077 0.086 0.703 0.010 0.593 1978 0.14 0.13 0.66 0.01 0.650 1977 0.07 0.03 0.140 0.016 0.124 1974 0.121 0.104 0.808 0.001 0.307 1969(PRE-0PE R Ail 0N AL ) 0.334 0.097 0.540 0.130 0.410 INDICATOR Air Particulate MEAN STANDARD M AllMU M MINIMUM RANCE Gross Beta pCi/m3 DEVIAil0N 1987 0.021 0.006 0.040 0.009 0.031 l 1986 0.039 0.050 0.289 0.007 0.282 1985 0.021 0.006 0.044 0.001 0.043 1984 0.025 0.008 0.058 0.000 0.05S 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 0.525 1980 0.045 0.03 0.207 0.002 0.205 l 1979 0.058 0.06 0.271 0.001 0.270 l 1978 0.10 0.09 0.34 0.01 0.33 1977 0.106 0.07 0.326 0.002 0.324 19 74 0.111 0.114 0.855 0.003 0.352 19 6 9 (PR E - 0 PE R ATl0N AL) 0.320 0.090 0.520 0.130 0.300 130
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Environ. TLD's Quarterly STANDARD MEAM MAXIMUM MINIMUM RANGE Reading mrem / Standard Month DEVI Ail 0N 1987 5.26 0.38 5.90 4.70 1.20 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 PEPORTED AS MRD'/@ PRICR TC 1980 1978 1977 1974 1969(PRE-0PE R A T10N AL ) I INDICATOR Environ. TLD's Quarterly gggy STANDARD MAllMUM MINIMUM RANCE Reading mrem / Standard Month DEVIATION 1987 5.62 1.43 14.50 3.50 11.00 1986 6.53 1.93 18.70 4.10 14.60 1985 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 NUT COMPAPABII DUE E CHANGES 1979 IN TLD LOCATIONS 1978 1977 19 74 19 6 9 (PR E - 0 PE R ATl0N AL) 131
i HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL l Milk Sm:ples MEAN ST A N D A RD M AIIMUM MINIMUM RANCE Cs-137 oci/1 DEVI ATION 1987 < rya --- _-- --- --- - 1986 8.4 3.6 12.4 5.3 '1 . 1985 <I.12 --- --- --- 1984 < tar --- --- --- --- 1983 <tla --- --- --- --- 1982 <I.LD --- --- --- --- 1981 7.0 ONIX O2 DATA PORT 1980 <Ils --- --- -- --- 1979 3.73 0.29 3.9 3.4 '.5 1978 5.83 1.98 7.8 2.4 5.5 1977 NO CONIROL DATA PPl0R E 1979 1974 --- --- --- --- --- 1969(PRE- 0PE R ATION AL ) ( IN DIC ATO R Milk Sm:ples MEAN STANDARD M All MU M MINIMUM RANCE Cs-137 oCi/l O E Vl A T10N _ j 1987 7.4 2.8 9.4 5.5 3.9 1986 8.6 1.7 11.1 6.1 5.0 1985 <r2D --- --- --- --- l 1984 <tla --- --- --- --- 1983 5.10 0aN ONE DATA POIhT 1982 6.26 4.41 18.0 3.1 14.9 1981 7.57 5.95 29.0 4.3 24.- 1980 9.7 4.9 21.0 4.0 17.0 1979 9.4 8.0 40.0 2.7 37.3 1978 9.9 7.1 33.0 3.4 20.6 1977 17.1 3.9 22.0 11.0 11.0 19 74 26.1 10.5 61.0 13.0 48.^ 19 6 9 (PR E - 0 P E R Ail 0 N AL ) to DATA --- --- --- --- 132
HISTORICAL ENVIRONMENTAL SAMPLE DATA l i CONTROL Milk Samples MEAN ST A N D ARD MAllMUM MINIMUM RANCE I-131 oCi/1 DEVI ATION 1987 ain --- --- --- --- 1986 13.6 14.3 29.0 0.8 28.o 1985 <ur --- --- --- --- 1984 <un _-- -_- --_ _-- 1983 <uD --- --- --- --- 1982 <un --- --- --- --- 1981 <ur --- --- --- --- 1980 1,41 OMN OF DATA mni 1979 < t,m --_ --- --- --- 1978 <mL --- --- --- --- 1977 No MTA --- --- --- --- 1974 NO DATA --- --- --- --- 1969(PRE-0PE R ATl0N AL ) NO DATA --- --- --- --- IN DIC ATO R Milk Sanples MEAN STANDARD MAllMUM MINIMUM RANCE I-131 pCi/1 DE VI ATION 1987 <uD --- --- --- --- 1986 5.2 7.5 30.0 0.3 29.7 1985 <un --- --- --- --- 1984 <uD --- --- --- --- 1983 <uD --- --- --- --- 1982 <ur --- --- --- --- 1981 <uD --- --- --- --- 1980 4.9 4.23 8.80 0.40 8.40 1979 <un --- --- --- --- 1978 0.19 omy nNE DATA mMT 1977 0.07 0.08 0.22 0.00 0. " 19 74 1.23 0.44 2.00 0.70 1.30 19 6 9 ( PR E- 0 P E R ATl0 N AL) NO DATA --- --- --- --- 133
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Htran Food Crops MEAN STANDARD M AllMUM MINIMUM RANGE Cs-137 pCi/c (wet) Produce DEVl Ail 0N 1987 <ur --- --- --- --- 1986 <uD --- --- --- --- 1985 <ur --- --- --- --- 1984 <ur --- --- --- --- 1983 <ur --- --- --- --- 1982 <ur --- --- --- --- 1981 <ur --- --- --- --- 1980 <ur --- --- --- --- 1979 !D CONIROL DATA PRICR TC '090 1978 1977 . 1974 196 9(PRF.-0PE R Ail 0N AL ) IN DIC ATO R Hthm Food Crops MEAM STANDARD M All M U M MINIMUM RANGE Cs-137 oCi/g (wet) Produce DE VI Ail 0M 1987 <ur --- --- - . - - --- 1986 <ur --- --- --- --- 1985 0.047 ONLY ONE DATA POL'T 1984 <ur --- --- --- --- 1983 <un --- --- --- --- 1982 <uD --- --- --- --- 1981 <ua --- --- --- --- 1980 0.033 2.26 0.06 0.004 0.056 _ I 1979 <uD --- --- --- --- 1978 0.01 ONLY ONE DATA POINT 1977 col --- --- --- --- 19 74 0.142 0.09 0.34 0.04 0.30 19 6 9 (PR E- 0 P E R Ail 0 M A L ) to DATA --- --- --- --- 134
HISTORICAL ENVIRONMENTAL SAMPLE DATA CONTROL Human Food Crops i ND RD MAXIMUM MINIMUM RANCE MEAN I-131 pCi/g (wet) Produce OEVl ATI0N 1987 1986
<uD
<UB l
1985 <11D --- --- --- --- 1984 <UB --- --- --- --- 1983 <UD --- --- --- --- 1982 <1lD --- --- --- --- 1981 _
<ur --- --- --- ---
1980 <LLD --- --- --- --- 1979 7:0 CONTROL DATA PRIOR TO 1990 1978 1977 1974 < 1969(P R E-0 P E F A TION A L )
~
'~
INDICATOR - Hunan Food Crops MEAN STANDARD M All M U M MINIMUM RAhCE - I-131 pCi/g (wet) Produce DEVIAil0N 1987 <uD --- --- --- --- 1986 <U2 --- --- --- --- 1985 <UD --- --- --- --- 1984 <UB --- --- --- --- 1983 <ILD --- --- --- --- . 1982 <UD --- --- --- --- 1981 <UD --- --- --- --- l 1980 <ILD --- --- --- --- 1979 <UD --- --- --- --- 1978 ODL --- --- --- --- 1977 ODL --- --- --- --- 19 74 10 DATA --- --- --- --- 19 6 9 ( PR E- 0 P E R Ail 0 N A L ) to DATA --- --- --- --- 135 i
Vli FIGURES AND MAPS
- 1. DATA GRAPHS This section includes graphic representation of selected sample results.
For graphic representation, results less than the MDL or LLD were considered to be at the MDL or LLD level of activity. values were indicated where possible. MDL and LLD (
- 2. SAMPLE LOCATIONS Sample locations referenced as letters and numbers on analysis results tables are plotted on maps.
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9 JAMES A. FITZPATRICK MILK Cs-137 30 30
* * *
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4 JAMES A. FITZPATRICK FIcuRE is MILK. Cs-137 20- 20
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SUMMARY
OF USEPA ENVIRONMENTAL RADIOACTIVITY LABORATORY INTERCOYPARISON STUDIES PROGRAM RESULTS This section includes results of JAF analyses compared to reference samples originating from the United States Environmental Protection Agency , (USEPA). As required by the Technical Specifications, participation in this program includes media for which environmental samples are routinely collect-ed. All intercomparison data is summarized in table form. The tables are titled "USEPA Environmental Radioactivity Laboratory Intercomparisor Study , Program". e me 1 i o l e B i 154 , l
TABII VIII-1 USEPA DNIRCDETTAL RADIOACTIVITY LABORATORY I?TTERCCMPARISON S'IUDY PROGPN! Gross Beta Analysis of Air Particulate Filters (pCi/ filter) Gross Beta Analysis of Water (pCi/ liter) , JAP JAF EPA DATE DN ID hutBER M DIUM ANAYISIS IESULT (1) RESULT (2) . 04/87 QA87-35 APF BETA 54!4(3) 43 5 - 5414 , 55!4 g 04/87 CA87-36 WATER BICA 58 2 3) 66t5 56t2 6513 08/87 OA87-96 APF BETA 36!3(3) 3015 36 3 ( 36 3 10/87 OA87-118 WATER BETA 80!3 I 72 5 78t3 79 3 a g' 155 s
l 1 TABLE VIII-2 ' USEPA DNIRCt@! ENTAL RADIOACTIVITY LABOPAERY , INTEH00MPARISO4 SWDY PROGRAM ; i Tritium Analysis of Water (pCi/L) i JAF JAF EPA DAE DN ID NtNBER MEDILE NUCLIDE RESULT (1) RESULT (2) : 02/87 QA87-14 WATER H-3 4000i200 I4I 4209 421 38001100 4000 100 06/87- 'QA87-68 WAER H-3 2800t100 I4I 2895t357 2700 200 3000 200 >- 10/87 QA87-117 WAER H-3 47001100 I4) 44921449 4500t100 - 4800 100 i l 156 ; r I i
TABLE VIII-3 USEPA DNIPCt@DTTAL PADIOACTIVITY ISBOPA70RY D7FERCMPARISCN STJDY PPOGPAM Iodine Analysis of Water (pCi/L) and Milk (pCi/L) JAF JAP EPA DATE DN ID NUMBER MEDIIN NUCLIDE RESULT (1) RESULT (2) I-131 I3) 91 02/87 G87-20 MILK 10 l 911 10 1 02/87 OA87-20 MILK I-131 9l I4I 91 911 9!1 04/87 OA87-28 WATER I-131 8i2(3) 737 812 82 08/87 OA87-88 WATER I-131 46 9(3) 48!6 52t12 45!12 12/87 OA87-160 WATER I-131 30t2(3) 26!6 30 2 30t3 l 157
i TABIE VIII-4 USEPA DNIROtNENTAL PADIOACTIVITY IJBORA'IORY INTERCOMPARISCN sit 1DY PROGRAM Gamna Analysis of Milk, Water (pCi/L) Air Particulate Filters (pCi/ filter) and Food Products (pCi/kg)
-JAF JAF EPA DATE DN ID NUMBER MF:DIU4 NUCLICE RESULT (1) DESULT (2) 01/87 OA87-06 FOOD I-131 72+3( } 78+8
~
7673 757_2 Cs-137 88+9 84+5 96+10 97110-K* 775+78 980+49
~
768T77 870187 RTER Co-60 I3I 50+5 02/87 QA87-12 62+15 - 51I13 50116 Zn-65 97+24 91+5
~
103737 112129 Ru-106 136+77 100+5
~
137783 137171 Cs-134 51+12 59+E
~
52I14 53312 Cs-137 75+14 87+5
~
77719 79114 04/87 OA87-35 APF Cs-137 11+4 (3) 8+5 11+4 1214 158
TABLE VIII-4 (OctTTINUED) USEPA DWIR0tfD7tAL RADIOACTIVITY IABORATORY INTERCCHPARISCN S'li)DY PROGRAM Gamn Analysis of Milk, Water '(pCi/L) Air Particulate Filters (pCi/ filter) and Food Prcducts (pCi/kg) JAF JAF EPA DAIT E!N ID NUMBER MEDIEN ht iDE RESULT (1) RESULT (2) 04/87 OA87-36 ETER Co-60 10+5 I3I 8+5
~
(BLIND) 1075 16_5 Cs-134 18+8 20+5
~
266 2016 Cs-137 12+5 15+5
~
1275 1316 06/87 QA87-71 MIIJC I-131 55+2 I4I 59+6
~
58T2 5172 - Cs-137 82+8 74+5 8278 81[8 K* 1538+154 1525+76 - 15937159 14431144 06/87 QA87-61 ETER Cr-51 35+19 I3I 41+5 50T19 49_19 Co-60 60+4 64+5~ 6474 6814 Zn-65 7+5 10+5-1275 1615 Ru-106 76+6 75+5 77+6 l 87+6 l 159 I
TABLE VIII-4 (CONTINUED) USEPA DNIRCNMENTAL RADIQACTIVITY IABOPATORY INITPCOMPARISOi STUDY PROGPN! Gamna Analysis of Milk, Water (pCi/L) Air Particulate Filters (pCi/ filter) and Food Prcducts (pC1/kg) JAF JAF EPA DAIT DN ID 1: UMBER PEIIN FUCLIDE RESULT (1) REStiT (2) 6/87 QA87-6' NATER Cs-134 3613 4015 (Con't) 40+3 4113 Cs-137 72+4
~
80+5
~
76 4 764 I4I 07/87 CA87-82 FOOD I-131 89113 20+8 83+14 100115 Cs-137 55+6 50+5 56+6 5716 K* 1610+160 1680+84
~
16307160 14101140 08/87 OA87-96 APF Cs-137 1215(3) 1015 12+4 . 1114 10/87 OA87-116 WATER Cr-51 197+75 (3) 70+5
~
84744 Co-60 18+3 15+5
~
1575 1615 Zn-65 41+6 46+5
~
50+13 I 48_13 Ru-106 52+16 61+5
~
46I30 57132 160
TABLE VIII-4 (CCITTINUED) USEPA PN/IRONMENTAL PADIQACTIVITY IAPORA'IORY INTERCOMPARISCH SWDY PROGRAM Gamma Analysis of Milk, Water (pCi/L) Air Particulate Filters (pCi/ filter) and Food Products (pCi/kg) JAF JAF EPA DAE EhV ID hU BER MEDIUM NUCLIDE RESULT (1) RESULT (2) 10/87 OA87-116 t&'IER Cs-134 27+3 25+5 (Con't) 27+5 2916 Cs-137 46+3 51+5 4246 48[7 10/87 OA87-118 IGTER Co-60 14tS I3I 16 5 1612 16!2 Cs-134 20t6 1615 17t3 1913 Cs-137 26t5 24i5 24t2 2315 K-40 results reported as mg per unit of total potassite for EPA results only. (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. (4) - Analyzed at a vendor laboratory. 161
1 W l 1987 i RADIOLOGICAL ENVIRONMENTAL SURVEILLANCE REPORT JANUARY 1,1987 through DECEMBER 31,1987 4
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