JAFP-92-0358, 1991 Radiological Environ Operating Rept
| ML20095L031 | |
| Person / Time | |
|---|---|
| Site: | FitzPatrick  |
| Issue date: | 12/31/1991 |
| From: | Harry Salmon POWER AUTHORITY OF THE STATE OF NEW YORK (NEW YORK |
| To: | Martin T NRC OFFICE OF INSPECTION & ENFORCEMENT (IE REGION I) |
| References | |
| JAFP-92-0358, JAFP-92-358, NUDOCS 9205060185 | |
| Download: ML20095L031 (254) | |
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A8 4 NewYorkPower 1sf Authority ""l'v!'.F"7"" April 30,1992 JAFP 92-0358 United States Nuclear Regulatory Commission Region 1 457 Allendale Road King of Prussia PA 19406 Attention: Thomas T. hiartin Regional Administrator
SUBJECT:
JAhiES A. FITZPATRICK NUCLEAR POWER PLANT RADIOLOGICAL ENVIRONh1 ENTAL OPERATING REPORT FACil.lTY OPliR4 TING 1.lCENSE DPR 59. DOCKliT NO. 50 333 Gentlemen: Enclosed please find the 1991 Radiological linvironmental Operating Repan which covers the operating period of January 1,1991 through December 31,1991. This report is submitted in accordance with the requirements of Amendment 93, Section 7.3.d of the James A. FitzPatrick Nuclear Power Plant Technical Specifications. Distribution for this report is in accordance with the Regulatory Guide 10.1, Revision 4. Very truly yours,
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HARRY P.'SAlh10'N, J4h' HPS:BG;ls 6 Enclosures cc: Document Control Center Desk (USNRC)(18) J. W. Blake (NYPA/WPO) R.E. Beedle (NYPA/WPO) J. J. Kelly (NYPA/WPO) J. Toennies (NNiPC) II. Flanagan (Nhf PC) E. Berzins C.J. Gannon ( A. hicKeen l CAC Chairpersons l RES File C G. 00 3 ; l WPO Records hianagement f l Library gfJ RhtS (JAF) i CFRTgigigig f1Fpy{RN RECEIPT REQUESTED lliT KDR ADOCK 05000'3]3 j
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i I : i I I : I I I NEW YORK POWER AUTIIORITY ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT JANUARY 1,1991 DECEMilER 31,1991 FOR JAMES A. FITZPATRICK NUCLEAR POWER PLANT FACILITY OPERATING LICENSE DPR.59 DOCKET NUMilER 50 333 I I I i
I TAllLE OF CONTENTS f0EC 1.0 EXECU11VE
SUMMARY
11
2.0 INTRODUCTION
21 g 2.1 Site Description and Background 21 2.2 Objectives 22 3.0 PROGRAM DESCRIPTION 31 3.1 Sample Collection Methodology 37 l 3.2 Analyses Performed 3 13 3.3 Sample I.ocation Maps and Sample imcation Reference Tables 3 14 3.4 1:md Use Census 3 24 l 3.5 Program Changes 3 25 3.6 Deviation From the Program 3 26 3.7 Statistical Methods 3 27 3.8 Compliance with Required Imwer Umits of Detection (LLD) 3 32 4.0 SAMPLE
SUMMARY
TABLES IN HRAn'CII TECilNICAL 41 POSITION FORMAT I 5.0 RESULTS EVALUATION AND DISCUSSION 51 5.1 Aquatic Program 55 l 5.2 Terrestrial Program 5 21 53 Conclusion 5-49 I 5.4 References 5 51 I . 1 I
l TAllLE OF CONTENTS (Continued) I n= 6.0 REPORT PERIOD ANALYflCAL RESULT TAllLES 6-1 7.0 IllSTORICAL DATA TAllLES I 71 I 8.0 GRAPHICAL PRESENTATIONS 81 9.0 QUALITY ASSURANCE / QUALITY CONTROL PROGRAM 91 9.1 Program Desciotion 91 9.2 Interlaboratory Comparison 91 g 9.3 Nonconformities 9-1 I APPENDIX A A1 I Environmental Radiological Assessment of the March 18,1991 Relcase of Radioactive Material I I I I I I I ii I
' LIST OF TABLES
.P22t Table 3.01 Required Sample Collection and Analysis _ 32 Table 33-1 Environmental Sample Imcations 3 20 Table 3.81 Detection Capabilities For Emiron' mental Sample Analysis, 3-33 lower Limit of Detection (LLD)
Table 6-1 Shoreline Sediment Sampling Results 6-2 Table 6 2 Fish Sampling Results 6-3 Table 6 ~ Surfaen Water Composite Results, Tritium 6-6 g Table 6-4 Surface Water Composite Results, Gamma Isotopic 6-8 Table 6-5 Off site Airborne Particulate Filter Results, Gross Beta 6-14 Table 6-6 On-site Airborne Particulate Filter Results, Gross Beta 6-16 l Table 6-7 Off-site Airborne I-131 Results 6-18 Table 6-8 On-site Airborne I-131 Results 6-20 Table 6-9 Particulate Composite Results, Gamma Isotopic 6-22 h Table 6-10 Thermoluminescent Dosimeter Results 6-38 Table 6-11 Milk Results, I-131 I Table 6-12 Milk Results, G.tmma Isotopic 6-42 6-45 l Table 6-13 Milch Animal Cerm hvults _ 6-48 Table 6-14 Food Product Resul s, Gamma Isotopic 6-50 Table 6-15 1990 Residence Census 6-51 Table 9-1 Gross Beta Analysis Airborne Particulate (pCi/m') 9-3 and Water (pCi/L)
- Table 9-2 Tritium Analysis of Water (pCi/L) 9-4 Tabic 9-3 Iodine Analysis of Water (pCi/L) and Milk (pCi/L) 9-5 Table 9-4 Gamma Analysis of Milk, Water (pCi/L), Airborne Particulate 9-6 (pCi/m 3) and Food Products (pCi/kg) iii I
LIST OF FIGURES I na l Figure 33-1 New York State Map 3 15 Figure 33-2 Off-site Environmental Station and TLD location Map I Figure 33-3 On-site Environmental Station and TLD Location Map 3 16 3-17 l Figure 33-4 Milk Animal Census, Milk Sample location and Surface Watc.- Sample location Map 3 18 Figure 33-5 Nearest Residence, Food Product, Shoreline Sediment, 3-19 Fish Sample, Location Map Figure 8.1 Graph - Fish (Cs 137) 8-2 Figure 8.2 Graph - Surface Water Tritium 8-3 Figure 83 Graph - Airborne Particulate Gross Beta, Annual 8-4 Figure 8.4 Graph - Airborne Particulate Gross Beta, Weeks 1-26 (1991) 8-5 g Figure 8 : Graph - Airborne Particulate Gross Beta, Weeks 27-52 (1991) 8-6 Figure .5 0- aph - Airborne Particulate Composite (Co-60) 8-7 Figure h~! ; 2ph - Airborne Particulate Composite (Cs-137) 88 l- Figure 8.t> r,raph - Airborne Radiodine (I-131) 8-9 Figure 8.9 Graph - Milk (Cs-137), Annual I Figure 8.10 Graph - Milk (1-131) 8 10 8-11 l Figure 8.11 Graph - TLD Data 8-12 I I I iv I
I l 1.0 EXECUTIVE
SUMMARY
I This Annual Radiological Emironmental Operating Report is published pursuant to Section 7.3.d of the Radiological Effluent Technical Specifications (RETS). The RETS require that the results from the Annual Radiological Emircnmental Monitoring Program (REMP) be provided to the Nuclear Regulatory Commission (NRC). This report contains a description of the program, the presentation of data and an evaluation l of the results. In addition to the routine program results, the results and assessment of the emironmentat samples collected in response to the inadvertent release of g radioactive material to the emironment on March 18,1991 has been provided as an appendix to this report. The analytical results from the 1991 Environmental Monitoring Program showed that the routine operation of the James A. FitzPatrick Nuclear Power Plant had no l significant impact on the emironment. it is further noted that the 1991 Surveillance Program has detaonstrated that there has been no significant short term or chronic long g term affect on the emironment from the March 18,1991 release of radioactive material. I The REMP is used to measure radioactivity in the aquatic and the terrestrial pathways. The aquatic pathways include Lake Ontario fish, water, and lake shore sediment. Measurements of the samples representing these pathways showed results consistent l l with historical levels, g Terrestrial pathways evaluated airborne paniculates and radiciodine, milk, food products and direct radiation. Direct radiation includes radiation emitted from buildings and I structures of the plant, cosmic radiation, and the naturally occurring radioactive materials found in the soil, air and water. Analysis of all terrestrial radiation pathways demons: rated that there has been no detectable increased radiation levels as a result of l plant operation. The radiation levels and concentration of radionuclides in the environment are consistent with historical levels. iI This report contains a description and conduct cf the REMP as required by Technical l Specifications. It also contains the results, data evaluation, dose evaluation, and data l trends for each sample media. Also included are the land use census and the re.calts of the Quality Assurance /Ouality Control interlaboratory comparisons. iI 1-1 I
I
-l In summary, the measured conce.acations of radionuclides in the environment surrounding the JAFNPP are not increasing as a result of plant operation, In many I cases, such as fish and airborne particulate activity, this report documents a downward trend in man made radionuclides in the emironment. Ecumenically, the operation of the plant did not result in a measurable significant dose to the population above natural background levels.
I I I I I . I I I I I I lI lI 1-2
l
2.0 INTRODUCTION
2.1 SITE DESCRIPTION AND HACKGROUND The New York Power Authority (NYPA)is the owner and licensee of the James A. FitzPatrick Nuclear Power Plant (JAFNPP). JAFNPP is a single unit boiling water reactor (BWR). The plant generates 2436 megawatts (MW) thermal output and 807 l megawatts net electrical output. The plant is located on the eastern portion of the Nine Mile Point promontory approximately one-half mile due east of the Niagara I Mohawk Power Corporation (NMPC) Nine Mile Point Nuclear Power Stations (NMPNPS). Initial fuel loading of the JAFNPP reactor core was completed in November of 1974. Initial criticality was achieved in late November 1974 and commercial operation began in July 1975. NMPNPS #1, a 620 MWe (net) BWR, has been operating since 1969. NMPNPS #2, a 1,100 Mwe (net) BWR, has been l operating since March 1988. The plant site is on the southeastern shore of Lt.ke Ontario in the Town of Scriba, Oswego County, New York, approximately seven miles northeast of the City of Oswego, New York. The Universal Transverse Mercator System coordinates of JAFNPP are north 4,819,545.012 m, east 386,968.945 m. Syracuse, New York, located 40 miles south , is the largest metropolitan city in the area. The site consists of l approximately 700 acres of partially wooded land and shoreline The land adjacent to the site is primarily used for recreation and residential purposes. The country side to the west, east and south is 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. I NYPA and NMPNC share the responsibility for the JAFNPP Radiological l Environmental Monitoring Progru.n (REMP). Technical Specifications for radiological monitoring of the ervironment for all three plants are similar. This g allows the majority of the sampling and analysis to be a joint undertaking. Data generated by the program is shared by the three facilities. Review and publication I of the data is done indepe: dently by each organization. This report is submitted in accordance with Section 7.3.d of the Radiological Effluent l Technical Specifications (RETS) to DPR-59, Docket 50-333. .I i 2-1 I
l 2.2 PROGRAM OBJECTIVES The objectives of the Radiological Environmental Monitoring Program are to: Measure and evaluate the effects of plant operation on the environs and to I 1. verify the effectiveness of the controls on radioactive material sources. l 2. Monitor natural radiation levels in the environs of the JAFNPP site, g 3. Demonstrate compliance with the various emironmental conditions and requirements of applicable state and federal regulatory agencies.
- 4. Provide information by which the general public can evaluate the environmental aspects of nuclear power using unbiased data.
I I I I I I I I I 2-2 I
l 3.0 PROGRAM DESCRIPTION To achieve the objectives listed in Section 2.2, an extensive sampling and analysis program is conducted every year. The JAFNPP Radiological Emironmental Monitoring Program (REMP) consists of sampling and analysis of various media that include: o Shoreline Sediment o Fish g o Surface Waters o Air I o Milk o Food Products In addition, direct radiation measurements are performed using thermoluminescent dosimeters (TLDs). These sampling programs are outlined in Table 3.0-1. The l JAFNPP REMP sampling locations are selected and verified by an annual land use census. The accuracy and precision of the program is assured by participation in The United States Environmental Protection Agency (USEPA) Environmental Radioactivity Laboratory Intercomparison Program. I Sample collections for the radiological program are accomplished by a dedicated site environmental staff from both the James A. Fit 2 Patrick Plant and the Nine Mile Paint Stations. The site staff is assisted by a contracted emironmental engineering company, EA Science and Technology, Inc. (EA). I I 3-1 l
m m - M M M m W W W W W W TABLE 3.0-1 OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Pathway Type and Frequency and/or Sample Number of Samples (a) and Locations Collection Frequencyta ) of Analysis AIRBORNE Radiciodine Samples from 5 locations: Continuous sam- Padiciodine Canisters: and ple operation Analyze weekly for I-131. Particulates a. 3 samples .from off-site locations in dif- with sample col-ferent sectors of the highest calculated lection weekly Particulate Samples: site average D/Q (based on all licensed or as required site reactors). by dust loading, Gross beta following radicactivity filter changelb) whichever is composite (by location) y b. I sample from the vicinity of a community more frequent. for gamma isotopic-N having the highest calculated site aver- quarterly (as a minimum). age 0/Q (based on all licensed site re-actors).
- c. I sample from a control location 9 to 20 milesdistantgqqintheleastprevalent wind directiontaf, Direct Radiation (e) 32 stations with two or more dosimeters quarterly Gamma dose monthly or placed as follows: An inner ring of stations quarterly.
in the general area of the site boundary and an outer ring in the 4 to 5 mile range from the site with a station in each of the land based sectors of each ring. There are 16 land based sectors in the inner ring, and 8 land based sectors in the outer ring. The 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.
TABLE 3.0-1 (carruxto) OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Pathway Type and Frequency and/or Sample Number of Samples (a) and Locations ColleSieg Frequ:<cyta) of Analysis WATERBORNE Surface (f) a. I sample upstream. Composite sam- Gamma isotopic analysis ple over one monthly. Composite for
- b. I sample from the sii;q' month period (9). Tritium analysis quar-cooling water intakeqa)s most downstream
. terly(c),
Sediment from I sample fraw a downstream area with existing Twice per year. Shoreline or potential recreational value. Gama isotopjc) analysis semiannuallytC . u th _ INGESTION Milk a. Samples from milch animals in 3 locaticns Twice per month, Gamma isotopic and I-131 within 3.5 miles distant having the high- April through analysis twice per month est calculated site average D/Q. If December (sam- when milch animals are there are none, then I sample from milch ples will be on pastcre (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 throuoh March), if lated site average D/Q thrch if I-131 required (C). lisensedsitereactors)]gsedonall L 1 is detected in November and
- b. I sample from milch animals at a control December of the location (9 to 20 miles distany gnd in a preceding year).
less prevalent wind direction)sdy, m m m m . M M M M M M M M W W W
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. TABLE 3.0-1 (courinusa)
OPERATIONAL RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM Exposure Sampling and Pathway Collectiog Type ar.d Frequency and/or Sample Number of Samples (a) and Locations Frequency (a ) of Analysis FISH
- a. I sample of each of 2 commerically or Twice per year. Gamma isotopic (C) analysis recreationally important species in the of edible portions.
vicinity of a site discharge point.
- b. I sample of each of 2 species (same as in a. above or of a species with sienilar feeding habits) from an are at least 5
, miles distant from the site 1 A
FOOD PRODtlCTJ
- a. In lieu of the garden cenus as specified Once during Gama isotopic (C) in 6.2, samples of at least 3 different harvest season. analysis of edible kinds of broad leaf vegetatico (such as portions. (Isotopic vegetables) grown nearest each of two to include I-131).
different off-site locations of highest predicted site average D/Q (based on all licensed site Reactors). One (1) sample of each of the similar broad leaf vegetation grown at least 9.3 milesdistantinaleggtprevalent wind direction sectort J.
I NOTES FOR TABLE 3.0-1 (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 loc < Sn 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/O values and meteorological parameters are based on historical data l (specified in the ODCM) for all licensed site reacers. l (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. l (c) Gamma isotopic analysis means the identification and quantification of gamma emitting radionuclides that may be attributable to the effluents from the plant. l (d) The puipose 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 continuoutly may be used in place of, or in addition to, l integrating dosimeters. For the purpose of this tab'.e, 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 measuring 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, l the mixing zone, if practical. g I 1 3-5 I 5 I
I l NOTES FOR TAB 12 3.01 (Continggdl I (g) Composite samples should be collected with equipment (or equivalent) which is I capable of collecting an aliquot at time intervals which are very short (e.g., hourly) ! relative to the compositing period (e.g., monthly) in order to assure that a I l representative sample is obtained. g (h) A milk sampling location, as required in Table 1 is defined as a location having a least 10 milking cows present at a designated milk sample location. It has been ' _g found from past experience, and as a result of conferring with local farmers, that a 5 minimum of 10 milking cows is necessary to guarantee an adequate supply of milk twice per month for analytical purposes. Locations with less than 10 milking cows l 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. g In the event that 3 milk sample locations cannot meet the requirement for 10 milking cows, then a sample location having less than 10 milking cows can be used if ar. adequate supply of milk can reasonably and reliably be obtained based on communications with the farmer. I I I I I I I I 3-6
I 3.1 SAMPLE COLLECrlON METIIODOLOGY l 3.L1 SURFACE WATER g Surface water samples are taken from the respective inlet canals of the JAFNPP and the Niagara Mohawk Oswego Steam Station (OSS) located in the City of Oswego. Le FitzPatrick Facility draws water from 12ke Ontario on a continuous basis. This is used for the "down-current" or indicator h sampling point for the Nine Mile Point Sitt. The OSS inlet canal removes water from Lake Ontario at a point approximat:ly 7.6 miles west of the site. This "up-current" location is considered a control location because of the l distance from the site as well as its location relative to prevailing lake current directions and flow patteta of the nearby Oswego River. Samples from the JAFNPP arc composited using automatic sampling equipment which discharges into a compositing tank or bottles. Samples are collected monthly from the compositor and analyzed for gamma emitting g radionuclides. Samples from the CSS c.re also obtained using automatic sampling equipment and collected in a holding tank. Representative samples from this location are obtained weekly and are composited to form a monthly composite sample. The monthly samples are analyzed for gamma emitting radionoclides. A portien of the monthly samples from each of the locations is saved and composited to form quarterly composite samples. Quarterly composite l samples are analyzed for tritium. In addition to the sample results for the JAFNPP and Oswego Steam Station collection sites, data is presented for the Nine Mile Point Unit 1 and Unit 2 facility inlet canal samples and for samples from the City of Oswego drinking water supply. The latter three locations are not required by the Technical Specifications. These locations are optional sample points which l are collected and analyzed to enhance the surface water sampling program. 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 3.3 on Figure 3.3-2. 3-7 I E
I l 3.1.2 AIR PARTICULATE / LODINE The air sampling stations required by the Radiological Effluent Technical Specifications (RETS) are located in the general area of the site boundary. The sampling stations are sited within a distance of 0.2 miles of the site I boundarf ni sectors with the highest calculated meteorological deposition factors (D/0) based on historical meteorological data. These stations (R-1, l R-2, and R 3) are located in the east, cast-southeast, and southeast sectors as measured from the center of the NMPNS Unit 2 reactor building. The g RETS also require that a fourth air sampling station be located in the vicinity of a year round community having the highest calculated dispersion factor (D/Q) based on historical meteorological data. This station is located I in the southeast sector and is designated as location R-4. A fifth station required by the RETS is a control location, designated c.s station R-5. l Station R-5 is located 16.4 miles from the site in the east northeast meteorological sector. I In addition to the RETS required locations, there are ten additional sampling stations. Six of these sampling stations are located within the site boundary I and are designated as on-site stations D1, G, H, I, J, and K. These locations are within the site boundary of the JAFNPP and NMPNS. One air sampling l station is located off-site in the southwest sector in the vicinity of the City of Oswego and is designated as station G off-site. Three remaining air g sampling stations are located in the ESE, SSE, and S sectors and range in distance from 7.2 to 9.0 miles. These are designated as off-site stations D2, E and F respectively. Each station collects airborne particulates using glass fiber filters (47 millimeter diameter) and radiciodine using charcoal cartridges (2 x 1 inch). The samplers run continuously and the charcoal cartridges and particulate l filters are changed on a weekly basis. Sample volume is determined by use of calibrated gas flow meters located at the sample discharge. Gross beta I analysis is performed on each particulate filter. Charcoal cartridges are analyzed for radioiodine using gamma spectra analysis. The particulate filters are composited monthly by location and analyzed for gamma emitting radionuclides. 3-8 I
I Air sampling stations are shown in Section 33, Figures 33 ^. and 33-3. l 3.13 MILK g Milk samples are routinely collected from seven farms during the year. g These farna included six indicator locations and one control location. N ' Samples are collected twice per month, April through December and each l sample is analyzed for gamma emitting radionuclides and 1-131. Samples are ll collected in January, February and March in the event that 1 131 is detected I in November and December of the preceding year, g! The selection of milk sample locations is based on maximum deposition g calculations (D/0). Deposition values are generated using average historical 5 meteorological data for the site. The Technical Specifications require three sample locations within 5.0 miles of the site with the highest calculated deposition value. During 1991 there were no milk sample locations within l 5.0 miles that were suitable for sampling based on production capabilities, g There were however, six optional locations beyond five miles that were sampled as the routine milk sampling program. The Technical Specifications also require that a sample be collected from a location greater than ten miles from the site and in a less prevalent wind direction. This location is in the southwest sector and serves as the control l location. g Milk samples are collected in polyethylene bottles from a bulk storage tank g at cach sampled farm. Before the sample is drawn, the tank contents are E agitated to assure a homogenous mixture of milk and butterfat. Two gallons are collected from each indicator and control locations during the first half ud second half of each month. The samples are chilled, preserved and l shipped fresh to the analytical laboratory within thirty-six hours of collection in insulated sbipping containers. l The milk sample locations are found in Section 33 in Figure 33-4. (Refer to Table 33-1, Section 33 for location designations and descriptions). I 3-9 I 5
I ll 3.1.4 FOOD PRODUCTS (VEGETATION) Food products are collected once per year during the late summer harvest season. A minimum of three different kinds of broad leaf vegetation (edible or inedible) are collected from two different indicator garden locations. Sample locations are selected from gardens identified in the annual census that have the highest estimated deposition values (D/0) based on historical l site meteorological data. Control samples are also collected from available locations greater than 9.3 miles distance from the site in a less prevalent I wind direction. Control samples are of the same or similar type of vegetation when available. Food product samples are analyzed for gamma emitters using gamma isotopic analysis. Food product locations are shown in Section 3.3 on Figure 3.3-5. I 3.1.5 FISH SAMPLES Samples of available fish species are selected from the Nine Mile Point Aquatic Ecology Study which monitors lake fish populations. Fish samples l are collected twice per year, once in the spring and again in the fall. Indicator samples are collected from a combination of the four on-site g sample transects located off shore from the site. One set of control samples are at an off-site sample transect located off shore 8 - 10 miles west of the site. Available species are selected using the following guidelines: I a) Samples are composed of 0.5 to 1 kilogram of the edible portion only. l A maximum of three species per location are used. g b) Samples composed of more than 1 kilogram of single species from the same location are divided into samples of 1 kilogram each. A maximum I of three samples per species per location are used. Weight of samples are the edible portions only, c) Samples are limited to edible and or sport species when available. I 3-10 I
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Selected fish samples are frozen immediately after collection and segregated by species and location. Samples are shipped frozen in insulated containers l for analysis. Edible portions of each sample are analyzed for gamma g emitting radionuclides. Fish collection locations are shown in Section 33 on Figure 33-5. 3.1.6 SHORELINE SEDIMENTS One kilogram of shoreline sediment is collected at one area of existing or potential recreational value. One sample is also collected from a location g beyond the influence of the site. Samples are collected as surface scrapings to a depth of approximately 1 inch. The samples are placed in plastic bags, g scaled and shipped for analysis in insulated containers. Sediment samples e are analyzed for gamma emittmg radionuclides. Shoreline sediment locations are shown in Section 33 on Figure 33-5. I 3.1.7 TLD (DIRECI' RADIATION) Thermoluminescent dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. TLDs are supplied and processed l quarterly by Teledyne Isotopes of Westwood, New Jersey. Transit and control l TLDs accompany each shipment between the site and the vendor's laboratory and accompany the TLDs when they are being placed or collected in the a field. TLD data results are corrected using transit and control 1LDs data. I Five different regions around the site are evaluated using environmental TLDs. l o On site areas (areas within the site boundary not required by the l RETS) o Site boundary area in each of the sixteen meteorological sectors I i o An outer ring of TLDs (located four to five miles from the site in the eight land based meteorological sectors) o Special interest TLDs (located at sites of high population density and use) 3-11 I 1 E.
I o Control TLDs located at sites beyond significant influence of the site Special interest TLDs are located at or near large industrial sites, schools, or l nearby towns or communities. Control TLDs are located to the southwest, south and east-northeast of the site at distances of 12.6 to 19.8 miles. I TLDs used for the 1991 program were constructed of rectangular teflon wafers impregnated with 25 percent CaSO4 :Dy phosphor. Badges are sealed in a polyethylene package to ensure dosimeter integrity. TLD packages were placed in open webbed plastic holders and attached to supporting structures, l such as utility poles. I Environmental TLD locations are shown in Section 3.3 on Figures 3.3 2 and 3.3-3. I I I I I I. I I lI 1 'I
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I 3.2 ANAIJSIS PERFORMED l The majority of environmental sample analyses are performed by the James A. g FitzPatrick Emironmental Laboratory (JAFEL). TLD, tritium and canal I 131 analysis are performed by Teledyne isotopes (TI). The following samples are E analyzed at the JAFEL: E o Air Particulate Filter - gross beta l o Air Particulate Filter Composites - gamma spectral analysis g o Airborne Radioiodine - gamma spectral analysis o Surface Water Monthly Composites - damma spectral analysis o Fish - gamma spectral analysis I o Shoreline Sediment - ganuna spectral analysis o Milk - gamma spectral analysis and I-131 o Special Samples (soil, food products, bottom sediment, etc.) - gamma spectral analysis a Quality assurance samples are analyzed inhouse and by Telec. ie Isotopes NJ. and Teledyne Isotopes Midwest. I I I I 3-13 I
.I.
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'l 3.3 SAMPLE LOCATION MAPS Section 33 includes maps illustrating sample locations. Sample locations referenced as letters and numbers on the report period data tables are consistent with designations plotted on the maps. -
This section also contains an environmental sample location reference table (Table l 33-1). This table contains the following information: o Sample Medium o Location designation, this column contains the key for the sample I location and is consistent with designation on the sample location maps and on the sample results data tabico. o Location description I o Degrees and distance of the sample location from the site. 3.3.1 LIST OF FIGURES l o Figure 33 New York State Map g o Figure 33 Off-site Environmental Station and TLD Location Map I o Figure 33 On-site Environmental Station and TLD 12) cation Map l o Figure 33 Milk Animal Census, Milk Sample Location and Surface Water Sample Location Map l ' I o Figure 33 Nearest Resident, Food Product, Shoreline Sediment, Fish Sample, Location Map lI I 3-14 I
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M M M M M mal M M M M M M M M M M M M M - TABLE 3.3-1 ENVIRONMENTAL SAMPLE LOCATIONS F SAMPLE LOCATION MEDIUM- DESIGNATION LOCATION DESCRIPTION DEGREES AND DISTANCE (1) Shoreline 05* Sunset Bay 80 at 1.5 miles Sediment 06 Langs Beach, Control 230 at 5.8 miles Fish 02* Nine Mile Point Transect 315 at 0.3 miles 03* FitzPatrick Transect 55 at 0.6 miles 00* Oswego Transect 235 at 6.2 miles Surface Water 03* FitzPatrick Inlet 70 at 0.5 miles 08* Oswego Steam Station 235 at 7.6 miles 09 Nine Mile Point Unit 1 Inlet 305 at 0.3 miles a 10 Oswego City Water 240 at 7.8 miles g 11 Nine Mile Point Unit 2 Inlet 304 at 0.1 miles Air R-1* R-1 Station, Nine Mile Pt. Rd. 88 at ~1.8 miles Radioiodine R-2* R-2 Station, Lake Road 104 at 1.1 miles and R-3* R-3 Station, Co. Rt. 29 132 at 1.5 miles Particulates R-4* R-4 Station, Co. Rt. 29 143 at 1.8 miles R-5* R-5 Station, Montario Point RJ. 42 at 16.4 miles D1 D1 On-site Station, On-site 69 at 0.2 miles D2 D2 Off-site Station, Co. Rt. 64 117 at 9.0 miles E E Off-site Station, Co. Rt. 4 160- at 7.2 miles F F Off-site Station, Dutch Ridge Rd. 190 at 7.7 miles G G On-site Station, On-site 250 at 0.7 miles H H On-site Station, On-site 71 at 0.8 miles I I On-site Station, On-site 98 at 0.8 miles J J On-site Station, On-site 110 at 0.9 miles K K On-site Station, On-site 132 at 0.5 miles G G Off-site Station, St. Paul St. 225- at 5.3 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Reactor Centerline
TABLE 3.3-1 (Connuuco) ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE LOCATION MEDIUM DESIGNATION LOCATION DESCRIPTION DEGREES AND DISTANCE (1) Thermo- 3 D1 On-site Station 69 at 0.2 miles luminescent 4 D2 On-site Station 140 at 0.4 miles Dosimeters 5 E On-site Station 175 at 0.4 miles (TLDs) 6 F On-site Station 210 at 0.5 miles 7* G On-site Station 250 at 0.7 miles 8 R-5 Off-site Station 42 at 16.4 miles 9 D1 Off-site Location 80 at 11.4 miles 10 D2 Off-site Location 117* at 9.0 miles 11 E Off-site Location 160 at 7.2 miles - 12 F Off-site Location 190 at 7.7 miles 13 G Off-site Location 225 at 5.3 miles u 14* SW Oswego - Control 226 at 12.6 miles 9 15* West Site Boundary 237 at 0.9 miles 18* Energy Information Center 265 at 0.4 miles 19 East Site Boundary 81 at 1.3 miles 23* H On-site Station, On-site 70 at '0.8 miles 24 I On-site Station, On-site 98 at 0.8 miles 25 J On-site Station, On-site 110 at 0.9 miles 26 K On-site Station, On-site 132 at 0.5 miles 27 North Fence, JAFNPP 60 at 0.4 miles 28 North Fence, JAFNPP 68 at 0.5 miles 29 North Fence, JAFNPP 65 at 0.5 miles 30 North Fence, JAFNPP 57 at 0.4 miles 31 North Fence, NMP-1 276 at 0.2 miles 39 North Fence, NMP-1 292 at 0.2 miles 47 North Fence, JAFNPP 69 at 0.6 miles 49* Phoenix, NY - Control 170 at 19.8 miles 51 Oswego Steam Station, East 233 at 7.4 miles 52 Oswego Elementary School, East 227 at 5.8 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline IM M M M M m M m M M M M M M M m m m m
aus mas ese aus aus aus sua uma sus aus aus aus sus sus aus mas ama ans aus TABLE 3.3-1 (Cour:uuru) ENVIRONMENTAL SAMPLE LOCATIONS _ , I SAMPLE LOCATION LOCATION DESCRIPTION DEGREES AND DISTANCE (I) HEDIUM DESIGNATION 183* at 13.7 miles Thermo- 53 Fulton High School 54 Mexico High School 115' at 9.3 miles luminescent Pulaski Gas Substation, Route 5 75* at 13.0 miles t Desimeters 55 56* New Haven Elementary School 123' at 5.3 miles (TLDs) 58* County Route 1 and Alcan 220* at 3.I miles North Fence. NMP-2 5* at 0.1 miles 75* 25' at 0.1 miles 76* Noc?h Fence, NMP-2 North Fence, NMP-2 45' at 0.1 miles 77* 78* East Boundary, JAFNPe 90* at 1.0 miles 79* County Route 29 115* at 1.1 miles 80* County Route 29 133' at 1
- miles l
81* Miner Road 159' at 1.6 miles l l v> 82* Miner Road 181* at 1.6 miles l l N 83* Lakeview Road 200* at 1.2 miles 84* Lakeview Road 225* at ~1.1 miles 85* North Fence, NMP-1 294* at 0.2 miles 315* at 0.1 miles 86* North Fence, NMP-1 87* North Fence, NMP-1 341* at 9.1 miles 97* at 4.5 miles 88* Hickory Grove Road 89* Leavitt Road 111* at 4.1 miles 90* Route 104 and Keefe Road 135* at 4.2 miles 91* County Route SIA 156* at 4.8 miles Maiden Lane Road 183* at 4.4 miles 92* 93* County Route 53 205* at 4.4 miles j 94* Co. Rt. 1 & Kocher Road (Co. Rt.63) 223* at 4.7 miles 95* Lakeshore Camp Site 237* at 4.1 miles Creamery Road 199* at 3.6 miles 95* 143* at 1.8 miles l 97* County Route 29 98* Lake Road 101* r. 1.2 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline
TABLE 3.3-1 (connuuco) ENVIRONMENTAL SAMPLE 10 CATIONS SAMPLE LOCATION MEDIUM DESIGNATION LOCATION DESCRI? TION DEGREES AND DISTANCE (I) Thermo- 99 Nine Mile Point Dead 88 at 1.8 miles luminescent 100 County Route 29 a:d Lake Road 104 at 1.I miles Dosimeters 101 County Route 29 132 at 1.5 miles (TLDs) 102 Oswego County Airport 175 at 11.9 miles 103 Energy Information Center, East 267 at 0.4 miles 104 Parkhurst Road 102 at 1.4 miles 105 Lakeview Road 198 at 1.4 miles 106 Shoreline Cove, East of NMP-l' 274 at 0.3 miles 107 Shoreline Cove, East of NMP-1 272 at 0.3 miles 108 Lake Road 104 at 1.1 miles Y 109 Lake Road 103 at 1.1 miles 0 111 Sterling-Control 214 at 21.8 miles 113 Baldwinsville-Control 170 at 24.7 miles Cows Milk 7* Indicator Location 107 at 5.5 miles 16* Indicator Location 190 at 5.9 miles 50* Indicator Location 93 at 8.2 miles 55 Indicator Location 95 at 9.0 miles 60 Indicator Location 90 at 9.5 miles : 4 Indicator Location 113 at 7.8 miles 65* Control Location 220 at 17.0 miles , Food Products K Indicator Location 96 at 1.7 miles L Indicator Location 115 at 1.9 miles T Indicator Location 84 at 1.6 miles N Indicator Location 218 at 1.2 miles Z Indicator Location 95 at 1.7 miles M , Control Location 225 at 15.6 miles
- Technical Specification location (1) Based on Nine Mile Point Unit 2 Centerline lum 355 m m m m em 55 m m aus suu m m m m em m em
I l 3.4 IAND USE CENSUS Technical Specifications require that a milch animal census and a residence census g be conducted annually. He milch animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point site. %e census is done cuce i l pel year in the spring. It is conducted by sending questionnaires to previous milk animal owners, and by road surveys to locate any possible new owners in the event g that questionnaires are not answered, the owners are contacted by telephone or in person. The Oswego County Co Operative Extension Se.vice was also contacted to provide any additional information. I The resideno- census is conducted each year to identify the closest residence fr' cach l of the 22.5 degree meteorological sectors to a distance out to five miles. A residence, for the purposes of this census, is a residence that is occupied on a part time basis g (such as a summer carr.pf, or on a full time, year round basis. Several of the site meteorological sectors are over Lake Ontario, therefore, there are only eight sectors I over land vchere residences are located within five miles. In addition to the milch animal and residence census a garden census is performed. l The census is conducted each year to identify the gardens near the site that are to be used for the collection of food product samples. The results of the garden census g are not provided in this report. The results are used only to identify appropriate sample locations, ne garden census is not required by the Technical Specifications if broadleaf vegetation sampling and analysis is performed. I I I I I 3-24 I
I 3.5 l'ROGRAM CilANGES l No changes were made to the environmental sample locations required by the Technical Specifications or as specified in the Off site Dosc Calculation Manual. The gi following additions were made to the optional garden (food product) sample g locations: E
- 1. Food product (garden) locations L and N were added to the sample pro; ram during 1991. l.ocations L and N are optional sampling locations.
- 2. Also during 1991, fooa product (garden) locations P and O . vere not utilized by the sampling program because of either sample unavailability or because the location had a low deposition potential as a result of the addition of locations L and N.
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l
\
3,6 DEVIATION FROM Tile PROGRAM Exceptions to the 1991 sample program concerns those samples or monitoring l requirements which are required by the Technical Specifications. This section addresses the reporting requirements of Section 6.1.a of the REFS. The following are exceptions to the program as specified by the Technical Specifications: I 1. The air sampling purap at R-4 off site environmental sampling station was inoperable from January 14, 1991 (0200 hours) to January 15, 1991 (0800 I hours). De inoperability s u caused by a vacuum pump mechanical failure. g 2. The air sampling pump at R 3 off-site environmental sampling station was inoperable from March 4,1991 (0105 hours) to h arch 4,1991 (1310 hours). I The inoperability was caused by the loss of electrical power due to a severe ice storm. l 3. The air sampling pump at R-4 off site environmental sampling station was inoperable from March 4,1991 (0105 hours) to March 4,1991 (1310 hours). l The inoperability was caused by the loss of electrical power due to a severe ice storm. l 4. The air sampling purap at R 2 off site environmental sampling station was inoperable for 2 hours (0630 to 0830 hours) on December 3,1991. The g inoperability was caused by a mechanical failure. The pump was replaced. The collective inoperable time period for the air monitoring program was less than I 0.15% for the year. g Other occurrences of downtime for the optional air sampling stations were documented for 1991. Ilowever, these occurrences are not presented here because optional air sampling stations are not required by the Technical Specifications. I I I 3 26
I 3.7 STATISTICAL METilODOLOGY There are a number of statistical calculation methodologies used in evaluating the g data from the environmental monitoring program. These methodologies include determination of standard deviation, the mean and associated error for the mean and E the lower limit of detection (LLD). B 3.7.1 ESTIMATION OF TIIE MEAN AND STANDARD DEVIATION l The mean, (X,), and standard deviation, (s), were used in the reduction of g the data generated by the sampling and analysis of the various media in the JAFNPP Radiological Environmen'ai Monitoring Program (REMP). The followiug equations were utilize i to . ,Te 'he mean (X,) and the , standaru deviation (s): A. Mean I 11 X, = ,1 X, a
= 1 5 N
where, I m _ X, = estimate of the mean. E i = individual sample, i N, n = total number of samples with positive indications. x, = value for samp'. i above the lower limit of detection. l B. Standard Deviation n
= I S= E (X i - X)2 1=1 (N-1) 3-27 I
I.
I l where, 5 = mean for the values of X s = standard deviation for the sample population. 3.7.2 ESTIh1ATION OF TI{E MEAN AND TIIE ESTihiATED ERROR FOR TIIE l MEAN I In accordance with program policy, two recounts of samples are performed when the initial count indicates the presence of a plant related radionuclide(s). When a radionuclide is positively identified in two or more counts, the analytical result for the radionuclide is reported as the mean of the positive detections and the associated propagated error for that rnean. l In cases where more than one positive sample result is available, the mean of the sample results and the estimated error for the mean are reported in g the Annual Report. The following equations were utilized to estimate the mean (X,) and the I associated propagated error. l A. Mean n I x m =.E x 3 =1 i
! N where, g
X, = estimate of the mean. I i = individual sample, i. N,n = total number of samples with positive indications. l X, = value for sample i above the lower ' limit of detection. I I 3-28 I --
I U. Error of the Mean (Reference 18) I 1/2 I ERROR MEAN = { (ERROR)2 l i =1 - 3, N where, I ERROR MEAN = propagated error i = individual sample g ERROR = 1 sigma
- crror of the individual analysis B N, n = number of samples with positive indications Sigma (a)
I Sigma is the greek letter used to represent the mathematical term.Sitndard Deviation. Standard Deviation is a measure of dispersion from the arithmetic n'ean of a set of numbers. E _ E I I I I I 3 29 I I
I l l 3.7.3 LOWER LIMIT OF DETECTION (LLD) 1 g The LLD is the predetermined concentration or activity level used to establish a detection limit for the analytical procedures. The LLDs are specified by the Technical Specifications for radionuclides in specific media and are determined by taking into account the overall l measurement methods. The equation used to calculate the LLD is: I 4.66 s,i l LLD = (E) (V) (2.22) (Y) exp ( A At) LLD is the a priorilower limit of detection, as defined above (in picoeurie per unit mass or volume); I s3 is the standard deviation of the background counting rate or of the counting rate of a blank sample, as appropriate (in counts per minute); E is the counting efficiency (in counts per disintegration); V is the sample size (in units of mass or volume); 2.22 is the number of disintegrations per minute per picoeurie; I Y is the fractional radiochemical yield (when applicable): A is the radioactive decay constant for the particular radionuclide; l At is the elapsed time between sample collection (or end of the sample collection period) and time of counting. I lI l 3-30 ig
I The REE LLD formula assumes that: l o 'llic counting times for the sample and background are equal. g o The count rate of the background is approximately equal to the g count rate of the sample, a In the REE program, LLDs are used to ensure that minimum acceptable detection capabilities are met with specified statistical confidence levels (95% detection probability with 5% probability of a false negative). Table 3.81 g lists the RETS program required LLDs for specific media and radionuclides as specified by the NRC. The LLDs actually achieved are routinely much g lower than those specified by the RETS. 5 I I I I 5 I I I l I l l 3-31 I
.I.
I l 3.8 COMPl. LANCE WITil itEQUlitED 1.OWElt LIMITS OF DETECrlON (1.1.D) I Table 6.13 of the Itadiological Effluent Technical Specification (Ilirl'S) specifies the detection capabilities for environmental sample analysis (see lleport Table 3.18). Section 7.3.d of the itETS requires that a discussion of all analyses for which the required LLDs specified were not routinely achieved be included in the Annual Radiological Environmental Operating Report. Section 3.8 is provided pursuant to l this requirernent. I 3.8.1 All sample analyses required by the RE*I3 achieved the 1.nwer Limit of Detection (LLD) specified by im13 Table 6.1-3. I I I I I I I I I I
- I I 3-32 I
TABLE 3.8-1 REQUIRED DETECTION CAPABILITIES FOR ENVIRONMENTAL SAMPLE ANALYSIS LOWER LIMIT OF DETECTION (LLD) Water Airborne Particulate Fish Milk Food Products Sediment Analysis (pCi/l) or Gases (pCi/m') (pCi/kg, wet) (pCi/l) (pCi/kg, wet) (pCi/kg, dry) gross beta 4 0.01 H-3 3,000 Mn-54 15 130 Fe-59 30 260 v b Co-58,59 15 130 Zn-65 30 260 Zr/Nb-95 15 I-131(a) 15 0.07 1 60 Cs-134 15 0.05 130 15 60 150 Cs-137 18 0.06 150 18 80 180 Ba/La-140 15 15 (a) No drinking water pathway exists at the Nine Mile Point Site under normal operating conditions due to the direction and distance of the nearest drinking water intake. Therefore, an LLD , value of 15 pCi/ liter is used. sta sus sus ses aus sus ass ets e e em um aus ass sin su e e em
I l 4.0 SAMPLE
SUMMARY
TABLES IN HRANCli TECIINICAL POSITION FORMAT All sample data is summarized in table form. The tables are titled
- Radiological Monitoring Program Annual Summary" and use the following format as specified in the NRC Branch Technical Position:
I Colunm I 1 Sample medium. I 2 Type and number of analyses performed. 3 Required lower Limits of Detection (LLD), see Section 3.8, Table 3.81. This wording indicates that inclusive data is based on 4.66 g (sigma) of l background (see Sr.i,m 3.7). 4 The mean and range of the positive measured values of the indicator locations. I 5 The mean, range, and location of the highest indicator annual mean. location designations are keyed to Table 3.3-1 in Section 3.3. 6 'Ihe mean and range of the positive measured values of the controllocations. 7 The number of nonroutine reports sent to the Nuclear Regulatory Commission. NOTE: Only positive measured values are used in statistical calculations. 4-1 I
m m m m e m e m m m m m m m m m RADIOLOGICAL MONITORING PROGRAM ANNUAL SUt#4ARY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1991 Location (b) of control Type and Indicator Locations: Higheet Annual Meant Location: Number of Medium Number af Mean (a) Locations & Mean (a) Mean (a) Nonroutine (units) Analysis LLD Range Designation Range Range Reports l Shoreline GSA (4): Bediment (PCi/g-dry) Cs-134 0.15 <LLD <LLD <LLD 0 l Cs-137 0.18 0.13 (2/2) No. 5 0.13 (2/2) <LLD D 0.12 - 0.14 1.5 0 80* 0.12 - 0.14 Fish GBA (36): (pci/g-wet) [ Mn-54 0.13 <LLD <LLD <LLD 0 Fe-59 0.26 <LLD <LLD <LLD 0 Co-58 0.13 <LLD <LLD <LLD 0 Co-60 0.13 <LLD <LLD <LLD 0 2n-65 0.26 <LLD <LLD <LLD 0 Cs-134 0.13 <LLD <LLD <LLD 0 Cs-137 0.15 0.029 (13/23) No. 03 0.030 (8/12) 0.029(5/13) 0
- O.018 - 0.045 0.6 0 55* 0.018 - 0.044 0.021-0.034 Food GSA (21):
Products (PCi/g-wet) I-131 0.06 <LLD <LLD <LLD 0 Cs-134 0.06 <LLD <LLD <LLD 0 Cs-137 0.08 0.039 (1/16) No. N 0.039 (1/2) <LLD 0 0.039 - 0.039 1.2 G 218* 0.039 - 0.039
RADIOLOGICAL HONITORING PROGRAM ANNUAL SUfEARY JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1991 Location (b) of control Type and Indicator. Locations: Highest Annual Mean: Location: Number of Medius' Number of Nean fa) Locations & Mean fal Mean fa) Nonroutine (units) _ Anslysis LLD Range Designation Range Range Reports surface H-3 Et 3000 310 (3/4) No. 3 310 (3/4) 190 (2/4) 0 (Lake) Water 290 - 390 0.5 6 70* 290 - 390 180 - 200 (pci/ liter) GBA (24)2 Mn- 34 15 <LLD <LLD <LLD 0 Fe-59 30 <LLD <LLD <LLD 0
$ Co-58 15 <LLD <LLD <LLD 0 CJ-60 15 <LLD <LLD <LLD 0 2n-65 30 <LLD <LLD <LLD 0 Zr-95 15 <LLD <LLD <LLD 0 Nb-95 15 ,
<LLD <7.LD <LLD 0 I-131 15 <LLD <LLD <LLD 0 Cs-134 15 <LLD <LLD <LLD 0 t
Cs-137 18 <LLD <LLD <LLD 0 Ba/La-140 15 <LLD <LLD <LLD 0
^
t in m m m M M SE M M M M M M M
aus aus sus nun aus sus aus uma amm amm aus num uma are sem use amm uma sum l l RADIOLOGICAL HONITORING PROGRAM ANNUAL SUhr JAMFS A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSkEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1991 Location (b) of Control Indicator Locations: Highest Annual Meant Location: Number of Type and l ! Medium Number of Mean (a) Locations & Mean (a) Mean fal Nonroutine Range Designation Range Range Reports (units) Analysis LLD Milk (f) GBA (12 6)_ : (pCi/ liter)
<LLD <LLD <LLD 0 Cs-134 15 l
<LLD <LLD <LLD 0 Cs-137 18
<LLD <LLD <LLD 0 l
, Ba/La-140 15
<LLD <LLD <LLD 0 I-131(126): 1 i
RADIOLOGICAL MONITORING PROGRAM ANNUAL
SUMMARY
JAMES A. FITZPATRICK NUCLEAR POWER PLANT DOCKET NO. 50-333 OSWEGO COUNTY, STATE OF NEW YORK JANUARY - DECEMBER 1991 Location.(b) of. Control Type and Indicator. Locations: ' Highest Annual Mean: Locations Number of Medium Number of Mean (a) Locations & Mean ,,(31 Mean'(a) Nonroutine (units) Analysis LLD Range Designation Range Range Reports Air G.B. (260): 0.01 0.015 (208/208) R-4 0.015 (52/52) 0.014 (52/52) 0 Particulate 0.006 - 0.033 1.8 9 143* 0.007 - 0.032 0.007 - 0.028 and Radiciodine I-131(260): 0.07 <LLD <LLD <LLD 0 3 (d) (pC1/m') - GBA (601: A 6
- Cs-134 0.05 <LLD <LLD <LLD 0 Cs-137 0.06 <LLD <LLD <LLD 0 i
4 TLD tamma i ymrem per ' Dose (128): N/A 5.4 (120/120) (c) No. 85 12.2 (4/4) (e) 4.6 (8/8) O standard l 2.9 - 16.7 0.2 G 294* 9.8 - 14.5 3.8 - 5.3 month) l I l f 555 m m e e e m M m m m m m m m m m f
M M M M W W W M M M M M M M M M M M M ANNUAL SINMARY TABLE NOTES
* = Data for the Annual Summary Tables is based on RETS required samples only.
N/A = Not applicable. (a) = Fraction of detectable measurement to total measurement. (b) = Location is distance in miles, and direction in compass degrees. (c) = Indicator TLD locations are: #7, 23, 75, 76, 77, 78, 79, 80, 81, 82, 83, 84, 85, 86, 87, 88, 89, 90, 91, 92, 93, 94, 95, 96, 97, 98, 15, 18, 56, and 58. Control TLDs are all TLDs located beyond the influence of the site (#14, 49). [ (d) = Indicator samples from environmental stations R1 off-site, R2 off-site, R3 off-site, and R4 off-site. Control samples are samples from R5 of f-site environmental station. (e) = This dose is not representative of doses to a member of the public since this area is located near the north shoreline which is in close proximity to the generating facility and is not accessible to members of the public (see Section 5.2.4, TLDs). ! (f) = The RETS criteria for indicator milk sample locations includes locations within 5.0 miles of the site. There are no milk sample locations within 5.0 miles of the site. Therefore, milk samples are collected from locations greater than 5.0 miles from the site based on the location D/Q values.
'I l 5.0 RESULTS EVALUATION AND DISCUSSION g Each year the results of the Annual Radiological Emironc . ental Monitoring Program are evaluated considering natural processes in the environment and the array of past radiological data. A numSer of factors are considered in the course of evaluating and interpreting the Annual Enviranmental Radiological Data. This interpretation can be made using several methods incluuing trend analysis, population dose, risk l estimates to the general population based on environmental concentrations, effectiveness of plant effluent controls and specific research areas. The report not g only presents the data collected during the 1991 sample program but also assesses the significance of radionuclides detected in the environment. It is important to rote that detection of a radionuclide is not, of itself, an indication of environmental I. significance. Evaluation of the impact of the radionuclide in terms of potential increased dose to man, in relation to natural background, is necessary to determine l the true significance of any detection. g There are four separate groups of radionuclides that were detected in the environment as a result of the 1991 sampling program. The first of these groups consists of those radionuclides that are naturally occurring. It is important to realize I that the environment contains a broad inventory of naturally occurring radioactive elements. Components of natural backgrc,und include external cosmic and terrestrial l radiation, radionuclides deposited in the body, and radon and its decay products, Naturally occurring radionuclides, such as Th-228, Ra-226, Be-7 and K-40 contribute, g along with radon, to the annual per capita background dose which is equal to approximately 300 mrem per year (Reference 17). Comparisons to natural I background radiation are made throughout this section to place surveillance program results into perspective and to aid the readei in determining what, if any, significance is associated with the Radiological Environmental Monitoring Report (REMP) results. l The second group of radionuclides that were detected are a result of the detonation of thermonuclear devices in the earth's upper atmosphere. Atmospheric nuclear I testing during the early 1950s produced a significant inventory of radionuclides presently found in the !ower atmosphere as well as in ecological systems. In 1963 an Atmospheric Test Ban Treaty was signed. Since the treaty, the global inventory of man made radioactivity in the environment has been greatly reduced through the decay of short lived radionuclides and the removal of radionuclides from the food I 5-1 I
I chain by such natural processes as weathering and sedimentation. This process is referred to in this report as ecmogical cycling. Since 1963, several atmospheric l weapons tests have been conducted by the People's Republic of China, in each case, g the usurd radionuclides associated with nuclear detonations were detected for several months following the test and then after a peak detection period, diminished to a g point where most could not be detected. Although reduced in frequency, e atmospheric testing continued to October 1980. The resulting fallout or deposition from these tests has influenced the background radiation in the vicinity of the site and was evident in many of the sample medias analyzed during the 1981 l Environmental Surveillance Program. Cs 137 is currently the major remnant of this g testing and is still detected in a number of erwironmental media. A third group of radionuclides was detected as a result of the Chernobyl accident which occurred in the Soviet Union in April 1986. The resulting fallout or _ yosition from this accident influenced the background radiation in the vicinity of the site and was casily detected in many of the sample media analyzed during 1986. Quantities l of Nb 95, Ru 103, Ru 106,1131,12140, Cs 134, and Cs 137 were detected in air particulate samples during May and June of 1986. Milk samples collected and l analyzed after April,1986 contained measurable concentrations of I 131 and Cs-137. The origin of these radionuclides was a direct result of fallout from the Chernobyl accident. During 1987, Cs 137 was detected in several milk samples collected during l the first half of the grazing season. In 1988, Cs 137 was detected in one milk sample. The presence of Cs-137 in the milk samples is attributed to the ubiquitous l concentrations of Cs-137 from weapons testing and from the Chernobyl releases. l The fourth group of radionuclides that may be detected in the environment are those that are related to man made nuclear technology. These radionuclides are a byproduct of nuclear detonations, the Chernobyl accident, and the operation oflight . water reactors thus making an evaluation of the production source difficult, if not impossible. During 1991,113 and Cs-137 were the only potentially plant related radionuclides detected in the RETS samples. In addition to these radionuclides, Zn-65 was detecte in several non RETS samples. l l l A number of factors must be considered in performing radiological data evaluation I and interpretation. The evaluation and interpretation is made at several levels including trend analysis and dose to man. An attempt has been made not only to report the data collected during 1991, but also to assess the significance of the 52 I I
I l radionuclides detected in the environment as compared to natural radiation sources. It is important to note 'that detected concentrations of radionuclides that resulted g from the aethties of man are very
- mall and are not of significance frora an environmental or dose to man perspe( e.
l The 1987 per capita dose was determined to be 360 mrem per year from all sources, as noted in the NCRP Report No. 93 (Reference 17). This average dose includes l such exposure sources as natural, occupational, weapons testing, consumer products, medical, etc. The 1987 per capita dose rate due to natural sources was 300 mrem per , year. The per capita radiation dose from nuclear power production nation wide is less than one mrem per year (Reference 10). l Background gamma radiation in the enviroas of the Nine Mile Point Site, resulting from radionuclides in the atmosphere and the ground, accounts for approximately 60 g - 65 mrem per year. This dose is a result of radionuclides of cosmic origin (for example, Be 7), of a primordial origin (Ra 226, K-40, and Th 232) and, to a much smaller extent, of a man made origin from weapons testing. A dose of 60 mrem per I year, as a background dose,is significantly greater than any possible doses as a result of operations at the site during 1991. I The results for each sample media is discussed in detail in Section 5.0. This includes a summary of the result, the estimated environmental impact, a detailed review of any relevant detections with a dose to man estimate where appropriate, and an analysis of possible trends. In the routine implementation of the Radiological Environmental Monitoring l Program, additional or optional environmental pathway media are sampled and analyzed. These samples are obtained to monitor the secondary pathways 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 I samples. In addition to the optional sample media, many additional locations are sampled and analyzed for those pathways required by Technical Specifications. l These additional sample locations are obtained to ensure that the important environmental pathways are monitored in a comprehensive manner. Data from g additional sample locations common with the Technical Specification required sample media are included in the data presentation and evaluation. When additional locations are in-luded, the use of this data will be specifically noted in Section 5.0. 5-3 I
I: Section 6.0 contains the analytical results for the sample media addressed in this ! report. Section 7.0, titled lilSTORICAL DATA, contains statipies from previous years environmental sampling. The process of determining the impact of plant g operation on the environment includes the evaluation 01 past analytical data, a tool by which trends me discerned. As state-of-the art detection capabili*ies improve, g data comparison is difficult in some cases. For example, Lower IJmits of Detections 5 (LLDs) have improved significantly since 1969 due to technological advance in laboratory procedures and analytical equipment. l I I I I I I 5 I I I I I I , 5-4 I l B
~
l . -
I l 5,1 AQUATIC PROGRAM The aquatic program consists of samples from three environmental pathways. These pathways are: o Shoreline Sediment l o Fish o Surface Waters Section 6.0, Tables 6.1 through 6.4 represent the analytical results for the aquatic I samples collected for the 1991 sampling period. I I I I I ~ I . I I I I 5 55 n
I I 5.1.1 SilOltELINE SEDIMENT ltESULTS l A. Itesults Summary l A total of four sediment samples were collected for the 1991 sample program. Small concentrations of Cs 137 were detected in the two samples taken at Sunset Beach which is the indicator location. Cs 137 was not detected at the control location. radionuclides were detected in the 1991 shoreline sediment saraples. No other plant related l The source of the Cs 137 detected in the indicator shoreline sediment is g considered to be the result of fallout from atmospheric nuclear weapons testing and not from operations at the site. Cs-137 was also detected at the indicator location in 1989 and 1990. The level of Cs 137 measured in 1991 shows a significant reduction in mean concentration from 0.29 pCi/g (1989 and 1990) to 0.13 pCi/g in 1991. The calculated potential whole body and skin doses which may result from the measured Cs 137 concentrations are insignificant when compared to natural background doses. l B. Data Evaluation and Discussion Shoreline sediment samples are routinely collected twice per year from g the shoreline of Lake Ontario. Samples are collected from one indicator location (Sunset Beach), and one control location (lang's Beach). The a first sample collection was twde in April at both the indicator and I controllocations. The second shoreline sample collection was made in October 1991 again, at both the indicator and the control locations. The h results of these sample collections are presented in Section 6.0, Table 1. Sev-spectral analysis. radionuclides were detected in sediment samples using gamina l I Three of these radionuclides were naturally occurring. K-40 was W detected at both the control location and indicator location. De results ranged from 15.4 pCi/g (dry) to 17.8 pCi/g (dry) at the indicator location, and 10.9 pCi/g (dry) to 13.4 pCi/g (dry) at the control location. Concentrations of AcTh 228 and Ra 226, which are also naturally occurring, were also detected at both indicator and control locations. l 5-6 I 5
l l Cs 137 was present in the indicator samples collected for the 1991 program. De mean concentration for these two samples was 0.13 pCi/g (dry). Cs 134 was not detected in the indicator or control samples collected for the 1991 program. The principle source of Cs 137 released I to the environment has been the atmospheric testing of nuclear weapons. Cs-137 and Cs 134 are both produced in fission reactors and were introduced into the environment from the accident at Chernobyl, but l only Cs 137 is found in weapons test debris. Since Cs 134 has a significantly shorter half life, detected concentrations of Cs 137 g attributable to plant operations (e.g., recent releases), should be accompanad by Cs 134. An absence of such corroborating Cs 134 concentrations would indicate that the presence of Cs 137 in these I samples is not distinguishable from the existing background and should be attributed primarily to weapons teating and residual concentrations; l i.e., not to recent plant operations, g The lack of measurable Cs 137 in the control samples may be attributed to localized concentration factors. Few shoreline regions west of the site I contain fine sediment and/or sand. It is difficult to obtain control samples which are comparable in physical and chemical characteristics to the indicator samples. Other factors, which include changing lake l Jevel and shoreline erosion, further complicate any consistency in shoreline sediment sampling. Soil samples in areas which are likely to g be affected by plant operations, as well as soil beyond any influence from the site, all contain levels of Cs-137 equal to or greater than the I concentration found in 1991 shoreline sediment. Cs 137 m soil samples is attributed to weapons testing fallout. Therefore, any shoreline sediment sample containing soil would contain Cs-137. C. Dose Evaluation
'Ib radiological impact of Cs-137 measured in the shoreline sediment can be evaluated on the basis of dose to man. In the case of shoreline l l sediments, the critical pathway is direct radation to the whak body and skin. Using the parameters found in Regulatcry Guida 1.109, the i
g potential dose to man in mrem per year c:s be calculated. The i following regulatory guide values were used in cuulating the dose to man: 5-7 I
I o A teenager spends 67 hours per year at the beach area or or. the shorchne, l 2 ' o The sediment has a mass of 40 kg/m (dry) to a dep:l 3 em. e The shoreline width factor is 0.3. o The maximum measured concentration of 0.14 pCi/g (dry) I remains constant for the year, g Using these conservative parameters, the potential dose to the maximum g exposed individual (teenager) would be 0.0005 mrem / year to the whole a body and 0.0005 mrem / year to the skin. This calculated dose is very small and is insignificant when compared to the natural background annual dose of approximately 60 mrem. l D. Data Tmuds The average Cs 137 concentrations in the shoreline sediment samples for 1991 was 0.14 pCi/g. The mean values for 1989 and 1990 were 0.29 pCi/g. The mean concentration for 1991 shows a reduction in levels by a factor of two. l A review of sample results for 1985 - 1988 indicate only naturally occurring radionuclides present in shoreline sediment. The five year E results data base shows no increasing or positive trends for the presence 5 of plant related radionuclides and as noted above,1991 showed a significant reduction in Cs 137 concentrations. l Shoreline sediment sampling commenced in 1985. Prior to 1985, no data g was available. Tables 1 and 2 in Section 7.0 illustrates historict.1 environmental data for shoreline sediment samples. I 5-8 I I
P I 5.1.2 FISil SAMPLE RESULTS A. Results Summary I A total of b fish samples were collected for the 1991 sample program. l Analysis of the 1991 fish samples exhibited detectable concentrations of radionuclides related to past weapons testing and natural origins g (naturally occurring). Small concentrations of Cs-137 were detected in approximately 50% of the fish samples collected from both the on-site I and off site locations. This is consistent with the previous year which had a positive detection in 40% of the samples. The ratio of positive detection to total samples collected was higher for the indicator samples l than for the control samples. Detectable concentratiom. of K-40, a naturally occurring radionuclide, were found in all fish samples collected g for the 1991 program. No other radionuclides were detected in the 1991 fish samples. I The detectable levels of Cs-137 in the fish samples are small. The control and indicator mean concentration values were equal at 0.-29 l pCi/g. These low levels of Cs-137 are of no environmental cr dose to man significance. As noted above, the measured concentrations of Cs-g 137 in the fish samples are the result of fallout from past weapons testing Comparable concentrations of Cs-137 are routinely found in I samples of other aquatic media such as shoreline sediment, bottom sediment and aquatic vegetation. The potential whole body and critical organ doses calculated as a result of fish consumption by humans is extremely small. Doses received from both the indicator and control sample groups are equal and considered to be background exposures. I The fish sample results demonstrate that plant operations at the Nine I Mile Point Site have no measurable radiological ervironmental impact on the upper levels of the l_ake Ontario food chain. The 1991 results continue to show a long term downward trend in fish Cs 137 concentrations. With the exception of 1986, the mean indicator and control Cs-137 concentration for 1991 were the lowest measured values l since the beginning of the surveillance program 17 years ago (1974). I 5-9 I
I B. Data Evaluation and Discussion li Fish collections were made utilizing gill nets at one location greater than five miles from the site (Oswego llacoor area), and at two locations in gI the vicinity of the lake discharges for the Nine Mile Point Unit #1 (#02), and the James A. FitzPatrick (#03) generating facilities. The ! Oswego Harbor samples served as control samples while the NMP (#02) and JAF (#03) src"ples served as indicator samples. All samples were analyzed for gamma emitters. Table 6-2 shows individual results for all the samples in units of pCi/g (wet). g The spring fish collection was made up of seventeen samples representing six individual species. Brown trout, lake trout, white sucker, smallmouth bass, walleye and white perch were collected from a combination of the lake sample locations. Brown trout, white sucker, smallmouth bass, white perch and lake trout where collected at all three l sample locations. The fall fish collection was comprised of nineteen individual samples representing seven individual species. Lake trout, l brown trout, smallmouth bass, white sucker, walleye, salmon and white perch samples were collected at the indiator sampling locations (NMP and JAF). One sample of each of the seven species was collected at the control location (Oswego Harbor). Cs 137 was detected in five of the eleven indicaior samples and in three of the six control samples collected during the spring. Indicator samples l showed Cs-137 concentrations which ranged from a minimum of 0.018 pCi/g (wet) to a maximum of 0.044 pCi/g (wet). The control sample Cs-137 concentrations ranged from a minimum of 0.021 pCi/g (wet) to a maximum of 0.034 pCi/g (wet). The average indicator Cs-137 l concentration of 0.033 pCi/g (wet) was slightly greater than the average control concentratic 1.032 pCi/g (wet). The indicator results however, are not si ocantly different from the control results and the l concentrations or Cs-137 are considereo to be representative of g
- background concentrations. The maximum detected Cs-137 concentration in both the indicator and the control location was g measured in samples of walleye. E 5 10 I
l I
I l- In the fall collection, Cs-137 was detected in ten of the nineteen samples collected from the control (2 of 7) and indicator (8 of 12) locations. Indicator samples showed a mean Cs-137 concentration that was slightly greater than the control sample mean. The detected concentrations are n t significantly diff: rent from one another with the indicator mean ' -E 5 equal to 0.027 pCi/g (wet) and the control mean equal to 0.025 pCi/g (wet). The Cs 137 concentration in .:ke trout at the indicator locations l ranged from 0.024 to 0.026 pCi/g (wey. The concentration of Cs-137 in the lake trout sample frora the control location was <0.039 pCi/g (wet). g Cs-137 was detected in perch samples co'lected at the control and indicator locations with the control mean being higher than the indicator mean. Cs 137 was detected in 1 of 2 brown trout samples from indicator locations at a concentration of 0.032 pCi/g (wet) and was not detected at the control location. White sucker samples collected at the indicator l or control location 3 did not contain any detectable concentrations of Cs-137. I The following graph presents the average Cs-137 concentrations for the I fid species analyzed for 1991. Walleye yields the highest average Cs-137 concentration for the indicator locations and white perch yields the highest average Cs-137 for the control location. I JAMES A. FITZPATRICK N.P.P. F13H Cs-137 rCl/cm (wet) I.StomLuasaerontso swenaea or senine ano raLL cottacticae f ho rotitlVs of f ttilow 0.0 4 H - -- 0 0 3 W--- ---- - '-- -- l ,,, _ _ . i.. _ _ _
, ~,-
g -__ -__ LI 5-11 1
-_ -._- .. ~ --_-.-.- -..-.- -. _ . . . = . . .- - - . - - - -
I K-40 was detected in all of the spring samples collected. K-40 is a naturally occurring radionuclide, and is not related to power plant l operations. Detectable contentrations of K-40 in the indicator samp%s g ranged from 2.95 to 5.46 pCi/g (wet) and 2.42 to 5.10 pCi/g (wet) for the control samples. Ra 226, also naturally occurring, was found at varying g levels at both the indicator and control locations. No other radion:4is 5 were detected in the spring fish samples. Naturally occurring K-40 was detected in all of the fall samples collected. I Detectable concentrations of K-40 in the indicator samples ranged from g 3.79 to 5.04 pCi/g (wet) and 3.57 to 4.75 pCi/g (wet) for the control samples. Ra-226, also naturally occurring, was detected intermittently at g ! varying concentrations at the indicator and control location samples. No a i other radionuclides were detected in the fall fish samples. The following graph presents the average K-40 concentrations for the fish I species analyzed for 1991. Salmon yields the highest average K-40 g concentration for the indicator locations and brown trout yields the highe.st average K-40 concentration for the control location. JAMES A. FITZPATRICK N.P.P. rISH K-40 " isei - pCugm (we0 g mentes o, semine ano sau causene - 3 5r- -- d_ _ _ _ __ ._ g g - - - - - -. 3 __ _ _ _ 0
"'""h 4"#**"#4 ,ocm"^"'" m, mc/^'" "
( E INDICATOR M CONTROL g l I 5-12 I E
I l C. Dose Evaluation Some Lake Ontario fish species may be considered an important food source due to the local sport fishing industry. Therefore, these fish become an integral part of the human food chain. Based on the I importance of fish in the local diet a conservative estimate of dose to potential man can be calculated. Assuming that an adult consume 21.0 l kg of fish per year (Regulatory Guide 1.109 maximum exposed age group) and the fish consumed contains an average Cs-137 concentration g of 0.029 pCi/g (wet) &mual mean result of indicator sa uples for 1991), the whole body dose received would be 0.M4 mrem per year. The organ of interest in this case is the liver whien would receive a calculated dose of 0.065 mrem per year. The Cs-137 whole body and organ doses are conservative potential doses associated with consuming fish species from !j the Nine Mile Point area which are represented by the indicator samples. Due to the long halflife of Cs-137, no radiological decay is assumed for j the calculation of doses. I Conservative whole body and organ doses can be calculated for tne 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) and h the average annual Cs-137 concentration for the control samples is 0.029 pCi/g (wet) which is equal to the indicator concentration. The potential g calculated C3-137 whole body dose is 0.N4 mrem per year and the associated dose to the liver is 0.065 mrem per year. In summary, the potential whole body and organ doses observed as a result of consumption of fish is small. Doses received from the l consumption of indicator and control sample fish would be the same. The dose to man received from both the indicator and control sample groups are considered to be background exposures. D. Data Trends I Results for the previous five years (1986 through 1991) have shown a I fairly consistent stabilizing trend for Cs-137 levels in control and indicator samples. During the period of 1987 through 1990, control and indicator mean results increased slightly when compared to 1986. The lI l l 5-13
I' l 1991 results show a return to the lower 1986 levels. Concentrations for indicator samples has decreased from a maximum concentration of 1.4 pCi/g (wet) in 1976 to a minimum level of 0.028 pCi/g (wet) in 1986. Control sample results have also decreased from a maximum level of 1.2 l , pCi/g (wet) in 1976 to a minimum level of 0.025 pCi/g (wet) in 1986. ! JAMES A. FITZPATRICK N.P.P. FISH Cel37 C1/gm (wet) I 0.04 {r 003 - ~- -- 0.02 p l l o o, - -- -- -. -. _ 1986 1988 1990 1987 1989 1991 M INDICATOR E CONTRO!. I 5 The general decreasing long term trend for Cs-137, illustrated in the graph below, is most probably a result of the cesium becoming unavailable to the ecosystem due to ion exchange with soils and sediments and radiological decay. The concentrations of Cs-137 detected since 1976 in fish are a result of weapons testing fallout, and the general downward trend in concentrations will continue 'as a function of ecolcgical cycling and nuclear decay. There was no apparent effect from l the 1986 Chernobyl Nuclear Plant accident during 1986 relative to Cs-g 137 results in fish samples although an effect may have been detected during the period of 1987 through 1991 since both indicator and control g location mean results increased slightly. 5 5-14 I 5
- _ - . _ _ _ ~
-i-I I lE JAMES A. FITZPATRICK N.P.P.
15 SH ca-'87 pcugm (wet) Ll ,..L__ _.___r ~~"ve r" _
,, ._ :::" ~~ ~-"~~~r r~ -
o,e . __...____ _ _ _ _ ....,_ _ _..... _ . _ _ .._ ._ _ _.
- 0.6 "- - - - - - - - - - - - - -
f ~_ o,4 - .._ _. _ _ -. . _ I 0.2 -
- ~ - - ~ -- - --
,l ot E E E um m == matama_ ,a_ m -a m m mmm. = j3 isr4
.,,ie r o iors ieso ise t iss4 sees isaa iaoc les moiccon WIE CONTROL i
The 1991 mean Cs-137 indicator cencentration of 0.029 pC!/g (wet) shows a decrease in concentration from 1976 by a factor of approximately 41. Control sample results have decreased from a f maximum level of 1.2 pCi/g (wet) in 1976 to a level of 0,029 pCi/g (wet) in 1991. Fish results for the 1991 indicator samples show a decrease in concentration by a factor of 19 when compared to preoperational data (1974) and by a factor of 48 compared to 1976. I Tables 7-2 and 7-3 in Section 7.0 show historical environmental sample
.l data for fish. Full size reproductions of the fish result graphs are found in Section 8.0.
I I I I 5-15 I
I 5.1.3 SURFACE WATER (LAKE) A. Results Summary l The Radiological Effluent Technical Specifications required that monthly surface water samples be taken from the respective inlet canals of the JAFNPP and Niagara Mohawk's Oswego Steam Station. In conjur-tion with the RETS sample, three additional Lake Ontario surface water locations are sampled and analyzed. Gamma spectral analysis was performed on 24 monthly composite samples required by the RETS and on 36 monthly composite samples from the additional locations. The l results from gamma spectral analysis indicate that only two radionuclides were detected in samples from the five locations collected for the 1991 Sampling Program. Both of these radionuclides are naturally occurring and are not plant related. Quarterly composites from the same locations are analyzed for tritium. The 1991 annual average tritium concentration for the Oswego Steam l Station Inlet (control location) was 360 pCi/1, which was higher than the annual average JAF inlet concentration of 310 pCi/1. The levels of tritium ne routinely variable within the range of 200 - 500 pCi/1 The tritium results for 1991 are consistent with previously measured lake levels and indicate no measurable increase in tritium levels in the lake from operations at the site. l B. Data Evaluation and Discussion Gamma spectral analysis was performed on monthly composite samples g from five Lake Ontario sampling locations. K-40 and Ra-226 were 5 , detected in samples from the five locations over the course of the 1991 sampling program. Both of these radionuclides are naturally occurring and are not plant related. l K-40 was detected consistently in both of the Technical Specification required intake canals. The James A. FitzPatrick inlet canal samples g showed K-40 was detected in all twelve monthly samples and ranged 5 from 44 to 257 pCi/ liter. K-40 in the Oswego Steam Station inlet canal 5-16 I 5
I
.l ranged from 46 to 246 pCi/ liter. The additional sample locations at the Nine Mile Point Unit #1 Inlet Canal and the Nine Mile Point Unit #2 g Inlet Canal showed K-40 concentrations which ranged 37 to 242 pCi/ liter and from 24 to 244 pCi/ liter respectively. K-40 in the Oswego City I water samples was detected in eleven of the twelve monthly samples and ranged from 26 to 252 pCi/ liter. Ra 226 was also detected intermittently in both locations required by Technical Specifications and at the other l optional sample locations.
Tritium samples are quarterly samples that are a composite of the I appropriate monthly samples. Tritium was detected in five of the eight samples taken at the two locations recuired by Technical Specifications. l Tritium concentrations for the James A. FitzPatrick inlet canal ranged from <160 pCi/ liter to 390 pCi/ liter and showed a mean concentration g of 310 pCi/ liter. The Technical Specification control location (Oswego Steam Station inlet canal) showed tritium results which ranged from
<100 pCi/ liter to 200 pCi/ liter. The first and fourth quarter tritium I results for the controllocation were below the sensitivity of the analyses; which is reported as the Lower Limit of Detection (LLD). The result for l the fourth quarter indicator sample were also below the sensitivity of the analysis and was reported as a lower limit of detection.
Tritium was also detected in nine of the twelve optional samples taken. The tritium results ranged from <160 pCi/ liter to 590 pCi/ liter for the l optional samples taken. The maximum tritium concentration of 590 pCi/l was measured in the first quarter city water sample. A summary of tritium results for the 1991 sample program is listed below: Sample Tritium Concentration pCi/ liter Location Minimum Maximum Mean (Annuan JAF Inlet <160 390 310 l Oswego Steam Inlet NMP #1 Inlet
< 100
<160 200 390 190 293 g NMP #2 Inlet <160 360 310 City Water Intake <160 590 360 lI l 5-17 lI I
1 1 I C. Dose Evaluation The Oswego Steam Station is considered a control location because of g its distance from the site and the action of lake current patterns and current patterns from the Oswego River located nearby. The 1991 annual average tritium concentration measured at the Oswego City water intake was higher than the Nine Mile Point Site tritium concentrations for 1991. The current patterns distinguish the Oswego City water intake as an "up-current" sampling point and the JAFNPP inlet canal as a l
"down-current" sampling point therefore, the operation of the Nine Mile g Point Site is located such that it does not have a radiological impact on drinking water. The Oswego City water intake is located in the same general vicinity as the Oswego Steam Station inlet placing it upstream from the Nine Mile Point Site.
The measured H-3 can be evaluated in terms of the potential" maximum I exposed individual". It is assumed that a child drinks 510 liters a year of water from the city water intake in Oswego. The tritium concentration l in the water is considered to be 360 pCi/ liter which is the annual average for the Oswego City water intake for 1991. The child could receive a potential dose of 0.04 mrem to the liver from ingestion of the 510 liters of water. This dose, when compared with the average annual dose from per capita radiation exposure of 300 mrem / year (Reference 17), is insignificant. l D. Data Trends Tritium results for the 1991 lake water samples were consistent with results from the previous five years for both the indicator and control locations. The mean tritium concentrations for the period of 1986 -1990 range from 186 pCi/l to 373 pCi/i for the control and 225 pCi/l to 460 pCi/l for the indicator location. The mean 1991 tritium concentrations l for the control and indicator locations were 360 pCi/l and 310 pCi/l g respectively. I 5-18 I I
I l The 1991 indicator results are slightly higher than the previous two years and are lower than the mean concentration for the period of 1986 - 1988. The beginnings of a short term trend may be evident in reviewing the graphical data. This possible trend shows that the control and indicator values are tracking together. Mean tritium results of the control location (Oswego Steam Station) l cannot be evaluated with regard to long term historical data since sampling was only initiated at this location in 1985. I Some idea of the variability of historical control sample data can be obtained by a review of previous data from the City of Oswego drinking water samples. The drinking water samples are likely to be representative of the current control location because of the effects of l the distance, predominate lake currents, and the discharge of the Oswego River. The Oswego City water intake is located in the same general vicinity as the Oswego Steam Station inlet. The maximum annual mean concentration of city water was found in 1976 (652 pCi/1) and the minimum in 1982 (165 pCi/l). I I JAMES A. FITZPATRICK N.P.P. SURFACE WATER TRITIUM 1000 ,,,,,,,, ,,,,,,,,,,,,,
- 900 q g ,,,,,,,,,,,,,,,,,,,,,,g, p - - - - - -
800 f was.wei contaoucewtoo steau swion I 700 600 500
- - - - - - - --' --~ -
I 400, -- - - -- - -- 300 ! - - - I
- 's...,...,1,I Il ll I -- --
I iI 5-19 I
I Annual mean tritium results from previous city water samples from 1976 to 1991 show that the tritium concentrations have fluctuated over the years. The maximum annual mean concentration was found in 1976 (652 pCi/ liter) and the minimum in 1982 (165 pCi/ liter). Results for the l period of 1982 through 1989 shows that the indicator samples were higher than the control samples Results for 1990 and 1991 show that the control samples to be higher. I I I I I I I 5 I I l I l I l I 5-20 I
.I l 5.2 TERRESTRIAL PROGRAM The terrestrial program consists of samples from four environmental pathways. These pathways are: o Airborne particulates and radioiodine l o Direct radiation o Milk o Food Products Tables 6-5 through 6-14 represent the analytical results for the terrestrial samples l collected for the 1991 reporting period. I I I I I I I I I I 5-21 I
I 5.2.1 AIR PARTICUIATE GRGSS IIETA A. Results Summary g Weekly, air samples were collected and analyzed for gross beta g particulate activity. A total of 52 samples were collected from the 5 control location R-5 and 208 samples were collected from the indicator locations R-1, R-2, R-3 and R-4 during 1991. These five locations are required by the Technical Specifications. The mean concentration of the l control location , R 5, was 0.014 pCi/m3 for 1991. The mean g 3 concentration for the indicator locations was 0.015 pCi/m for 1991. The indicator and control results are essentially equal and show that there are no increased airborne radioactivity levels in the general vicinity of the site. These results, along with those measured in 1990 are the lowest mean gross beta concentration measure to date since the inception of the site Environmental Monitoring Program in 1969. The consistency of these low concentrations may indicate that the natural base line gross beta activity has been reached. It is possible that the manmade radionuclide contribution to the natural background levels can no longer be detected. B. Data Evaluation and Discussion Six on-site and nine off-site locations were sampled weekly for gross beta g particulate activity. A total of 780 analyses were performed. Five of the nine off-site locations are required by Technical Specifications. These locations are R-1, R-2, R-3, R-4 and R-5. R-5 is a control location required by the Technical Specifications and is located beyond any local influence from the site. In addition, optional off-site and on-site air sample locations are maintained from which weekly samples are collected. The optional off-site locations are designated as D-2, E, F, and G. The optional on-site locations are designated as D 1, G, H, I, J l and K. Gross beta analysis requires that the samples are counted no sooner than 24 hours after collection. This allows for the decay of short half-life naturally occurring radionuclides. 5-22 I 5
I l Tables 6-5 and 6-6 in Section 6.0 present the weekly gros beta activity results for the off-site and on site stations. The average yearly gross beta indicator concentration for the indicator stations (R-1, R-2, R 3 and R-4) in 1991 was 0.014 pCi/m3 . The average l yearly gross beta control concentration for the off-site station (R 5) was 0.014 pCi/m', The minimum, maximum and average gross beta results for sample locations required by Technical Specifications were: pCi/m' Location
- Minimum Maximum Averrxe g
R-1 0.007 0.027 I R2 0.006 0.033 0.0' d 0.015 R-3 0.007 0.030 0.014 l R-4 R-5 (control) 0.007 0.007 0.032 0.028 0.015 0.014 I
- Locations required by the Technical Specifications The mean weekly gross beta concentrations measured in 1991 are illustrated in the graphs below.
AR ART'IC AT OR SS BET ! pCl/m3 ' - -- - - - - - -- - - ~ ~ ~ ~ ~ - ~
. .,2
. . _ b .
I 2 4 6 8 10 12 WEEK # 14 16 10 20 22 24 28 M INDICATOR M CONTROL I 5-23 I
I l I' JAMES A. FITZPATRICK N.P.P. AIR PARTICULATB OROSS BETA i 0.03 - - - - - - - - - - - - -- 0.025* - -- - - - -
}-- - - - - - - - -
I 0 02, ~ - - - ~- 0.016 - ; 7 ; o.0, i , , . , i i i j i 4 .
!L
- 5' , i
{ ! ! I g Lm eg t 1 ! ' i 4 o L 1 27 29 31 33 36 37 39 41 43 46 47 49 61 WEEK # M INDICATOR M CONTROL I The small fluctuations observed in the gross beta activity over the year can be attributed to changes in the environment, especially seasonal E changes. The concentration of naturally occurring radionuclides in the 5 lower levels of the atmosphere directly above land are affected by time related processes such as wind direction, precipitation, snow cover, soil temperature and soil moisture content. m C. Dose Evaluation Dose calculations are not performed b;_ sed on gross beta concentrations. Dose to man as a result of radioactivity in air is calculated using the specific radionuclide and the associated dose factor. See Section 5.2.2 for dose calculations from air concentrations. D. Data Trends I With the exception of the 1986 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 1981. I' 5-24 5
. - -- - .. . . . . . - ~ . . _~ . ..
I JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE GROSS BETA pCi/m3 I o., . _ _ _ _ _ -
'"' '" " "' ~
o.2, . __ _ . ._. I. 0.2 - - - - - - '- t 0.16 O.1 - - - - - - - " - - - - I "E 1 12=E'*-*
'"' n ? "in ,'"*,.7.'" *,. . ,'"i. 1" ',.. .'"',. 7'"* . . . ' " * , . . ,
i E INDICATOR W CONTROL The trend for the previous five years is a sub set of the overall decline l in gross beta concentrations, again with the exception of 1986 when a one year increase was measured as a result of the Chernobyl accident. g The 1991 results are the second lowest mean concentrations measured when compared to the previous five years for both the indicator and {g control locations. The change in concentration from the 1990 values is l 5 very small. This is illustrated by the following graph. l l u JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE GROS $ BETA 0,0 $ 0.04 - - - - 0.03 - oo .- 1986 1988 1990 l 1987 1989 1991 W IN DICAToR W CONTROL I ' 5-25
l l I The air particulate gross beta results for 1991 are a factor of 20 less than the concentrations measured in 1969. 1969 concentrations are considered to be preoperational results for the site. For the operational period of 1975 - 1991 the mean annual gross beta concentration at the l control station (R 5) has decreased from a maximum concentration of g 0.165 pCi/m3 in 1981 to 0.014 pCi/m3 in 1991. The mean annual concentration for the indicator stations for this same time period ranged 3 I from a maximum of 0.151 pCi/m in 1981 to a minimum of 0.015 pCi/m 3 m in 1991. For both the indicator stations and control stations, the gross beta concentration during 1974 to 1982 fluctuated as a result of fallout fro:1 the detonation of thermonuclear weapons. The mean annual l results for the years 1983,1984,1985,1987 and 1988 from both the g indicator and control locations have been similar and ranged from 0.018 3 to 0.026 pCi/m , This level of activity appears to be at or near baselin 3 B range. The 1986 c .aual mean result was 0.039 pCi/m for both the B indicator and control stations. This concentration is slightly higher than 1983-1985 and 1987-1991 levels and is attributed to fallout from the Chernobyl accident. l Historical data and graphic representations of air particulate gross beta activity are presented in Sections 7.0 and 8.0 respectively. B B I I I I I I 5-26 l _ _ _ _ _ _ _ _ _ - _ - - - - - - _ _ _ - - - - - - - _ - - - - . . - - - - ~ - - - -
5.2.2 MONTIILY PARTICULATE COMPOSITES (GAMh1A EMI'ITERS) A. Results Summary No plant related radionuclides.were detected in any of the air particulate filter samples collected from the Technical Specifications required sampling locations. These stations are located near the site boundary l and off-site. A small concentration of Zn-65 was detected at one of the on-site (optional) sample locations.- This plant related radionuclide was measured at a relatively low concentration of 0.00566 pCi/m3 at the H on site location. No detections of Zn 65 were made off site during this same sample time period. The impact of the Zn-65 concentration is not I considered to be significant due to the on-site location, the low concentration measured and the resulting small dose to man from the l short exposure period. The gamma analysis results for the monthly composite samples routinely showed positive detections of Be-7, K-40, Ra 226, and AcTh 228. Each I of these radionuclides is naturally occurring. Be-7 was detected in all the monthly composites ranging in concentration l l 3 from 0.0485 to 0.089 pCi/m for the indicator locations required by the Technical Specifications. The control location, required by the Technical Specifications, showed Be-7 concentrations ranging from 0.0209 to 0.0719 pCi/m 3. K-40 was found intermittently in the monthly composite samples from all locations. I B. Data Evaluation Discussion l Weekly air particulate samples were assembled by location to form monthly composite samples. The monthly composite samples required by Technical Specifications are R-1, R-2, R-3, R-4, and R-5. Other sample locations not required by the Technical Specifications for which
- I analytical results have been provided include six on-site locations and four off-site locations. The results of all monthly composite samples are presented in Section 6.0, Table 6-9.
lI 5-27
1 No plant related radionuclides were detected at any of the required or optional off-site sampling locations. One plant related activatin product radionuclide was detected at an on-site (optional) sample locr. .a. Zn-65 g was detected in the February composite sample from the H on site sample location. The measured Zn-65 concentration was 0.00566 3 E pCi/m . The presence of Zn 65 was not detected at any of the other air 5 monitoring stations including those at the site boundary. An evaluation of the presence of Zn-65 in the monthly air composite I sample was made. The weekly samples which makeup the monthly g composite were analyzed separately. The detected activity in the February composite was determined to originate from two filters which represent the time period 01/28/91 - 02/04/91 (week No. 5) and 02/04/91 02/11/91 (week No. 6). The measured concentrations were 0.0242 pCi/m respectively. 3 and 0.00742 pCi/m 3 for weeks No. 5 and No. 6 l Meteorological data was reviewed for two sample periods. A review of effluent records and isotopic measurements showed that Zn-65 was E present in plant effluents. Based on the meteorological data and plant 5 effluent records, the presence of Zn-65 in the February 1991 H on-site air particulate filter composite was the result of operations at the FitzPatrick Power Plant. l m C. Dose Evaluation Because of the fact that Zn-65 was not detected at sample locations outside the site boundary, the dose to man is not significant. For the purpose of evaluation, the dose to man can be calculated based on the g measured concentrations of Zn-65 at the on-site locations using the methodology found in Regulatory Guide 1.109. This calculated dose is conservative and is not representative of the dose to man beyond the site boundary but can be used to illustrate the significance of the resulting dose relative to background radiation. Using the inhalation rate for the maximum exposed individuals in each age group found in Regulatory l Guide 1.109 and the maximum concentrations measured at the H on-site air sampling station, the following dose to man was calculated: l 5-28 I E1
- 1
_ _ _ _ _ _ _ _ - - _ _ _ _ _ - - - - - - - - - - - - - - _ _ - - - - - _ - - - - - - . _ - - - - - - - - _ _ - - - - - - _ - - - - - - - - - - - _ . _ - - -- _-__-------_----.-----_--__----a
i l 1 AGE GROUP DOSE (mremhr) WHOLE BODY LUNG ADULT 0.00003 0.0006 TEEN 0.00004 0.0008 CHILD 0.0000% 0.0006 The conservative whole body and critical organ (lung) doses calculated as a result of the Zn-65 concentration measured on-site are very low when compared to background. Dose to man in the general area of the site is approximately 60 mrem / year. Because no airborne concentrations of Zn-65 were detected off-site, the actual dose to man from this radionuclide is probably zero and in any case much less than that l calculated. D. Data Trends No plant related radionuclides were detected during 1991 at the required I or optional off-site air sampling locations. As noted above, Zn-65 was detected in 1991 at an on-site sampMg location. No plant related radionuclides were detected during 1990 at the required or optional air sampling stations. Two plant related activation products were detected at three on-site (optional) air sample locations in 1989. In October 1989 Zine-65 was detected, and in November 1989 Zn-65 and I Co-60 were detected. Zn-65 or Co-60 were not detected in any other air monitoring indicator or control stations during those sample periods. Based on the evaluation of meteorological and plant effluent data, it was concluded that the presence of Zn-65 and Co-60 in 1989 samples was the results of JAFNPP operations. l A review of historical data shows that Zn-65 was not detected in air samples from 1985 to 1988. Co-60 was not detected during 1985 - 1986 in air particulate samples from either indicator or control locations. During 1987, Co-60 was detected once at a concemration of C.0017 iI l 5-29 lI
pCi/m3 at an optional air monitoring station. Ilowever, the Co 60 detected during 1987 was the result of contamination from improper handling of the sample, and not as a result of effluents from the site. This evaluation is contained in the 1987 anuual report. Co-60 was detected in each of the years from 1977 through 1984 at both the indicator and control locations with the exception of 1980 when Co. 60 was not detected at the control location. The presence of Co-60 in the air samples collected during these yea' : was the result of atmospheric l weapons testing. The maximum yearly mean concentration detected during this period was in 1977 when the mean indicator results was l 3 0.0179 pCi/m . The mean control value for this same year was 0.0172 3 pCi/m . The Co-60 in the air particulate samples trended downward during the 1977 through 1984 period to a low mean concentration of 3 0.0008 Pci/m at the control location. Co-60 has not been detected in l any of the required air particulate samples since 1985. This general downward trend and eventual elimination of Co-60 in the air samples is illustrated in the graph below. l JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE COMPOSITE Co-00 pCl/m3 a no wtues stronito-mo positive caractiom E 1978 41940- ATMo88ME A8C tt$tt 0.01 r 1 0.016 -I_ m 0.005L g_ te77 am amm must & iste " iset " ess t issa " seet i tese i iset l M INDICATOR E CONTROL 5-30 E
Historical data shows that Cs-137 is the fission product radionuclide most frequently detected in the air particulate filter composites. For the five year period,1986 to 1990, Cs-137 was detected only in 1986 due to the fallout from the Chernobyl accident. The 1986 mean concentration of Cs-137 for the control location was 0.0193 pCi/m 3. The mean concentration of CS-137 for the indicator location was 0.0183 pCi/m3 for the sample period. Cs-137 was detected in each of the years from 1977 through 1983 at both the control and indicator locaticns. For 1977, the mean Cs-137 concentration for the indicator location was 0.0043 pCi/rn3 . The Cs-137 - concentration for the control location for 1977 we.s 0.0034 pCi/m3 . Cs-137 average concentrations at the indicator and control locations decreased during 1978 and 1979 to 0.0017 and 0.0013 pCi/m3 I l respectively. Average conentrations during 1980 and 1981 were approximately equal at control and indicator locations. Cs-137 during g 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 I 3 decreased to 0.004 pCi/m . The 1983 mean Cs-137 concentration for the indicator and control composite samples were equal at 0.0002 pCi/m 3 l which was a reduction from 1982. Cs-137 was not detected during 1984 in any of the indicator or control air particulate composite samples. The g reduction in Cs-137 tesults is attributed to nuclear decay and ecological cycling of Cs-137 initially produced as a result of weapons testing. The I decrease in air particulate Cs-137 concentrations is clearly illustrated on the grapi of historical data. I I I I 5-31 I
JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE COMPOSITE C.-137 pCum3
- LLO mLV.S .E PO.T E D h0 PC.,fiv. DJT.CYio.
0.016 - -- --- - - - - - - - - ------ --
,.r. ....., m ........ ..,.
.. . . .. . . . . . m e ... 1 0.01 -- ---- - - - - - - - - -
0.005 ~ - - ~ - - - - - - - - - - - - - - - - ot ME - - . 1977 1979 1981 1963 1986 1987 1989 1W91 E INDICATOR E CONTROL l l Prior to 1983, several radionuclides wer: detected that were associated I with atmospheric weapons testing. These rad'onuclides were not 5 detected during 1984 and 1985 as a resuh of nucleic decay and natural environmental processes. These it dude Fr-93, Cc 141, Nb-95, Cc-144, Mn-54, Ru-103, Ru-106 and Ba 140. I a.140, Nb-95, Ru-103, Ru-106, and I-131 were detected in air particuiate composite samples during 1986 as a result of the fallout from the Cherm,byl c:cident. Those radionuclides j were not detected after 1986. TN five year data for these nuclides indicates no plant related impact on the emironment. All positive detections were associated with atmospheric weapons testing. Current air particulate filter composite results can not be compared to I preoperalm.1 cata as none exists prior to 1977. l Historical data for air particulate results are presented in Section 7.0, fables 7-11 and 7-12. Full size graphic representation of air particulate composite Co-60 and Cs-137 concentrations are presented in Section 8.0. I 5-32 _I
l 5.2.3 AIRBORNE RADIOIODINE (I 131) l A. Results Summary Iodine I 131 was not detected in any of the 780 samples analyzed for the program. No radioiodine has been detected off-site since 1986 when measurable levels of I-131 were found as a result of fallout from the l Chernobyl accident. B. Data Evaluation and Discussion Airborne radiciodine is monitored at tne fifteen air sampling stations used to collect air particulate samples. There are nine off-site locations, five of which are required by Technical Specifications. The off-site locations required by Technical Specifications are designated as R-1, R-2, R-3, R-4 and R-5. R-5 is a control station located beyond any local influence from the plant. Ten air sampling locations are maintained in addition to those required by Technical Speenications. Six of these stations, D-1, G, H, I, J and K, are located on-site. D-2, E, F and G are the optional stations located off-site. l Samples are collected using activated charcoal cartridges. They are analyzed weekly for I-131. The analytical data for radiciodine are presented in Section 6.0, Table 6-7 and 6-8. C. Dose Evaluation I The I-131 airborne sampling program showed no impact due to the l operation of the plant. No radioiodine was detected in any sampling location. I D. Data Trends No radiciodine has been detected at air sampling locations required by Technical Specifications since 1987. l 5-33 l
The five year 1-131 data shows no detrimental impact or trend due to plant operations during the period from 1986 through 1990.1 131 was l detected twice over the last five year period,in 1986 and 1987. The 1986 detection was the result of the Chernobyl accident and the 1937 detection was the result of plant operations. Iodine 1-131 (I-131) has been detected in the past at control locations. During 1976, the mean off-site I 131 concentration averaged 0.604 pCi/m'. 1977 showed an 1-131 concentration that deceased to 0.323 l pCi/m 3and for 1978 the concentration decreased by a factor of ten to g 0.G32 pCi/m3 , During 1979 - 1981 and 1983 - 1985,1131 was not detected at the controllocations. I 131 was detected once at the control location during 1982 at a concentration of 0.039 pCi/m 3, 1-131 was detected at the on-site locations in 1980 through 1983, !986 and 1987. The mean concentrations ranged from 0.013 pCi/m3 in 1980 to 0.119 3 pCi/m in 1986. The maximum value of 0.119 pCi/m was the result of 3 l the Chernobyl accident. 1-131 was detected in a total of 75 weekly g samples collected during the 1986 sample program. The concentrations detected in 1986 ranged from a minimum of 0.011 pCi/m3 to a maximum g of 0.36 pCi/m'. Each of tb positive detections of I-131 in 1986 were a a direct result of the Chernobyl Nuclear accident. Preoperational data for 1 131 in air is limited. Results from 1974 showed I no positive measuren.,mt of I-131. Current data which showed no g measured concentrations of I-131 is consistent with the 1969 and 1974 preoperational data. A graphic presentation of airborne radiciodine is presented in Section 8.0. I I
~
I 5-34 I E
.2-r-aL I
5.2.4
-l DIRECT RADIATION (TIIERMOLUMINESCENT DOSIMETERS (TLD))
g A. Results Summary I 71 TLDs were collected and read each quarter in 199t. The 1991 results are consistent with those observed in 1990. On site readings ranged from 3.2 to 11.6 mrem per standard month. Site boundary measurements l- ranged from 3.2 to 16.7, with an average of 6.0 mrem per standard month. Direct radiation doses measured 4 to 5 miles from the plant and g each land based 22.5 degree compass sector ranged from 3.6 to 5.8 with an average of 4.7 mrem per stand 'd month. Special interest TLDs located at high population density areas, schools, etc. ranged from 2.9 to 6.3, with an average of 4.8 mrem per standard month. The control measurements ranged from 3.8 to 5.8, with an average of 4.6 mrem per l standard month. g Overall, environmental direct radiation measurement results for 1991 showed no indication ofincreased direct radiation at or beyond the site boundary resulting from operations at the site. I B. Data Evaluation and Discussion Thermoluminescent dosimeters (TLDs) are used to measure direct l radiation (gamma dose)in the environment. Badges are obtained from Teledyne Isotopes quarterly and read at the Teledyne Isotopes facility in Westwood, New Jersey, 71 environmental TLDs were collected and read on a quarterly basis during the sample year. The location results are an average of eight independent readings per quarter at each location and are reported in mrem per standard month (See Section 6.0, Table 6-10). During 1991, collections were made during the weeks of March 24, June
-g 25, September 24, and December 24. Most of the locations required by
- the Technical Specifications during 1991 were initiated in 1985 as a result of the issuance of new Technical Specifications by the NRC.
Therefore,1991 results can only be compared to 1985 - 1990 results. 5-35 l
Some locations including a numbt - tquired by the Technical Specifications (i.e., numbers 7,14,15,18, 23, 49, 56, and 58) can be l compared to earlier results since these TLDs were established prior to g 1985. On-site TLDs are located at special interest areas within the site boundary. With the exception of location numbers 7 and 23, these locations are not required by the Technical Specifications. Locations 7 and 23 are located near the generating facilities at previous or existing l on-site air sampling stations and are used to evaluate sectors that do not g extend beyond the site boundary. TLDs located at the air sampling stations include numbers 3,4,5,6,7,23,24,25 and 26. The results for g these locations are very consistent with the previous year results. These a results ranged from 3.2 to 11.6 mrem per standard month. TLD #3 is located in the vicinity of NMPNS Unit 2 between Unit 1 and the JAFNPP. The results for TLD #3 were approximately double the results l of the other on site TLDs for the first and fourth quarter in 1991 because of the effects from the NMPNS Unit 2 and the JAF facilities. Other on-site NMPNS include special interest TLDs located near the north shoreline of the Unit 1, Unit 2 and JAF facilities. They are in close proximity to radwaste facilities and the Unit I reactor building. These locations include numbers 27,28,29,30,31,39 and 47. Results for these TLDs during 1989 were widely variable and ranged from 5.2 to 31.4 mrem per standard month as a result of activities at the radwaste l facilities and the operating modes of the generating facilities. Results for 1991 are consistent with the ranges of variability noted in 1990 for measurements at or near these locations. The maximum result for this group was approximately seven times tne mean control result in 1991. Additional on-site TLD locations are located near the on-site Energy Center and the associated northeast shoreline. These locations include numbers 18,103,106 and 107. TLDs 103,106, and 107 are located east of the Energy Center and west of the Unit 1 facility. TLD number 18 is located on the west side of the Energy Center. Results during 1991 ranged from 4.0 - 6.0 mrem per standard month and were lower than the 1990 results. 5-36 I I
l I l The Technical Specification required site boundary TLDs are loca.of in the approximate area of the site boundary, one in each of the sixteen 22 1/2 degree meteorological sectors. These include numbe s 75,76,77,23, 78,79,80,81,82,83,84,7,18,85,86 and 87. l.ocation numbers 78,79, 80, 81, 82, 83, 84, 7 and 18 showed results that were consistent with control TLD results and ranged from 3.2 to 5.8 mrem per standard month. Site boundary TLDs during 1991 were consistent with 1986-1990 l results. TLD numbers 75,76,77,23 85,86 and 87 showed results that ranged up to three times the 1991 control results. The site boundary results ranged from 4.6 to 16.7 mrem per standard month. This subset of site boundary TLDs are located near the lake shoreline (approximately 100 feet from the shoreline), in close proximity to the I reaaor building and radwaste facilities of NMPNS Unit 1 and Unit 2 and the ladwaste area of the JAF facility. An estimate of the net site boundary dose can be made using available g TLD results. Measured results from TLDs located near the site boundary in sectors facing the land occupied by members of the public (excluding TLDs near the generating facilities and facing Ilke Ontario) I can be compared to control location results. The site bounc'.ary locations include- numbers 78,79,80,81,82,83,84,7 and 18. Site boundary TLD l numbers 75,76,77,23,85,86 and 87 were excluded from the net site boundary dose calculation. These areas are near the no-th shoreline g close to toe generating facilities and are not representative of dose rates for members of the public. Control locations include numbers 8,14,49, 111 and 113. Net site boundary doses for each quarter in mrem per I standard month are as follows: I Quarter Site Boundary
- i Control' Net Site Boundary Dose
- 1 5.8 5.4 +0.4 2 3.9 4.1 -0.2 3 5.0 4.6 + 0.4 4 4.5 4.7 -02
- Dose in mrem per standard month I 5-37 ,
I '
I The third group of environmental TLDs are located four to five miles from the site in each of the eight laad based 22.5 degree meteorological sectors. These locations are required by the Technical Specifications. At this distance, badges are not present in eight of th 'xteen meteorological sectors which are located l over Lake Ontario. Results for this group of TLDs during 1991 represented a range of 3.6 to 5.3 mrem per standard month. The range of results is caused by differences in naturally occurring physical conditions and the varying concentrations of naturally occurring radionuclides in the ground at each of the locations. These results are consistent with control TLD results during 1991 and with the 1986 - l 1990 results. Results were also congruous with other off-site TLD results during 1990 and previous to 1990. These TLDs were established in 1985 and include numbers 88, 89, 90, 91, 92, 93, 94 and 95. The fourth group of environmental TLDs are located near the site boundary I and at special interest areas. Industrial sites, schools, nearby commuaities, towns, off-site air sampling stations, the closest residence to the site, and the l off site environmental laboratory are included as special interest locations. Many of these TLDs are required by the Technical Specifications. Others are
,ptional. This group of locations include numbers 9,10,11,12,13,15,19,51, g
52,53,54,55,56,58,96,97,98,99,100,101,102,108 and 109. TLD numbers E 108 and 109 are new locations that were established during 1988 and were added to assist in the evaluation of the residence TLD tocations. In 1991 results ranged from 2.9 to 5.6 mrem per standard month. All of the TLD l results from this group were below the maximum value of 5.8 mrem per g standard month measured at the control locations. Results during 1991 were cor'sistent with results noted for previous years. The fifth category of TLDs are those used to measure the dose rate at the control locations. These TLDs are required by the Technical Specifications and include numbers 14 and 49. Optional controllocations are numbers 8,111 l and 113. Location number 111 was added to the program during 1988 to expand the data base for control measurements. Results for all control locations from 1991 ranged from 3.8 to 5.8 mrem per standard month. Results I from 1991 were consistent with previous years results. 5 5-38 I I
I C. riose Evaluation
- TLDs located at the site (, undary averaged 4.8 mrein per standard month (No. 7,18, 73, 79, 80, 81, 82 83, 84).
TIDs four to five miles from the site in each land based sector averaged 4.5 mrem per standard month in 1991. lI I l Results for the special interest locations averaged 4.8 mrem per standard month. g The control group retalts averaged 4.7 mrem per standard month in 1991 (No. I 8,14,49,111,113). l D. Data Trends I g A comparison of historical results for TLD results can be made using the I separate types of locations. These include s!!e boundary TLDs in each meteorological sector (16 locations), TLDs located off site in each land based I se: tor at a distance of four to five miles (8 locations), badges located at special intc areas (6 locations) and TLDs located at control locations (4 locations). l Ast i previously, many of the present TLD locations became effective in 1985t. J these results can only be evaluated for 1985-1991. I TLDs located at the site boundary averaged 7.0 mrem per standard month during 1986. During 1987,1988,1989 and 1990 site boundary dose rates I averaged 6.1,6.4,5.9 and 6.4 mrem per standard month respectively. As noted previously, this group of TLDs can fluctuate because several of these TLDs are l located in close proximity to the generating facilities and influenced by opervional modes. An increase was noted during 1986 although such an l increase was noted for all TLDs including the control' locations. During 1991, site boundary measurements averaged 6.0 mrem per standard month which is consistent with resu'ts for the last five years. I I 5 39 I
I TLDs located off site at a d; stance of four to five miles from the site in each of the land based meteorological sectors (off site sectors) averaged 6.0 mrem l per standard month during 1986. During 1987,1988,1989 and 1990 off site sedor dose rates averaged 5.2, 5.3, 4,9 and 4.7 mrem per standard month, respectively. The 1986 results demonstiated an increase for this gror,, of g TLDs relative to the data for the period of 1985 through 1991, 1991 results a for the group averaged 4.7 mrem standard month. This dose rate is identical to the 1990 resun and is lower than the previous resuas from 1985 through 1989. l Special interest locations averaged 5.3 mrem per standard month during 1985. During 1986 these same locations averaged 6.1 mrem. The 1987 average 5 results of 5.1 mrem per standard month showed a d: crease when compared to a the 1985 and 1986 results. 1988,1989 and 1990 results averaged 5.3,4.8 and 4.8 mrem per standard month restvetively. De 1991 results for these locations averaged 4.8 mrem per standard month and is identical to the 1990 l results. The fir al group of TLD locativas required by the Technical Specifications is g the control gia.ip. This group utilizes two locations positioned well beyond a the site. Results from 1985 for the control group aveinged 5.4 mrem per standard month. During 1986, this same group of TLDs averaged 6.3 mrem per standard month. A marked increase was noted in the second quarter of l 1986. The increase may have been a rer"It of the Chernobyl accident. Results g fcr 1987,1988,1989 and 1990 averaged 5.2,5.4,4.1 and 4.8 mrem per standard month respectively. Results for 1991 averaged 4.6 miem per standard month g and showed levels slightly less than previous years. The 1991 TLD program 5 results, when compared to the previous 5 years and preoperational data, shows no significant trends relative to increased dose rates in the environment due to the operation i the FitzPatrick plant. Tables 715 and 7-16 show the historical ec *ronmental sample data for environmental TLDs. A graph of historical TLD data is presented in Section 8.0. I 5-40 I
I l 5.2.5 Mi1.K A. Ilesults Summary There were no plant related radionuclides detected in the indicator or control milk samples collected and analyzed in 1991. Naturally occurring K-40 was detected in both indi&)r and control samples at levels consistent with past l years results.
- 11. Data Evaluation and Discussion Milk samples were collected from six indicator and one control location.
Technical Specifications require that three locations arc within five miles of , the site,13ased on the milk animal census there were no adeqtate milk saniple locations within five miles of tFa *e in 1991. Sample.s weie collected from farms located beyond the five mile requirement to ensure the monitoring of g this important pathway, The six indicator locations ranged from 5.5 to 9.5 miles from the site. The control samples were collected from a farm 17 miles and up wind from the f.ite. The sample locations are the same as those used I in 1989 1990 and the geographical location of each location is listec' c : low: g location No. Direction From Site Direction (Miles) I 7 16 ESE S 5.5 5.9 50 E 8.2 55 E 9.0 60 E 9.5 l 4 65 Control ESE SW 7.8 17.0 Samples were collected at each location from April through December, during the first and second half of each month. Since 1131 was not detected in l samples collected during November and December of 1991, no additional saruples were required for January through March of 1992. I Each sample is analyzed for gamma emitters using a GeLi or llPG detector. 5-41 I
I The 1131 analysis is performed using resin extraction followed by gamma spectral analysis for each sample. 1131 analytical results are provided in Section 6.0, Table 6-11. Sample analysis results for gamma emitters are provided in Section 6.0, Table 612. l lodine 1310 .w detected in any indicator or control samples analyzed during 1991. e.a 1-131 milk results were reported as lotver limits of detection (LLD). The LLD results for all samples ranged from <0.25 to <0.84 pCi/ liter. K-40 was the most abundant radionuclide detected in milk samples collected in 1991. K-40 is a naturally occurring radionuclide and is found in many of the environmental media sampled. K-40 was detected in every indicator and control sample. The K-40 concentration for all samples ranged from 1260 to 1790 pCi/ liter. C. Dose Evaluation l The cidculated dose as a result of plant effluents is not evaluated due to the fact that no plant related radionuclides were detected. The dose to man from naturally occurring concentrations of K-40 in milk and other environmental media can be calculated. This calculation illustrates that the dose received due to exposure from plant effluents is negligible as compared to the dose received from naturally occurring radionuclides. l' Significant levels of K-40 have been measured in environmental samples. A g 70 kilogram (154 pound) adult contains approximately 0.1 microcuries of K-40 as a result of normal life functions (inhalation, consumption, etc.). The dose g to bone tissue is about 20 mrem per year (Eisenbud) as a result of internally 5 deposited naturally occurring K-40. I I , 1 l 5-42 I 5
=,
I l D. Data Trends I 1991 showed no man-made radionuclides detected in milk samples analyzed as part of the environmental surveillance program. In the past five years, Cs-137 was detected in 1986 and 1987. 'Ilie mean Cs 137 activity for those years was 8.6 and 6.8 pCi/ liter respectively.1-131 was measured in milk samples in 1986 with a mean concentration of 13.6 pCi/ liter. 'Illis activity was a result of l the Chernobyl accident. I From 1976 to 1985, Cs 137 and 1 131 were imermittently detected. Cs-137 was detected in a 1983 milk sample with a concentration of 5.1 pCi/ liter. In 1980, - I 131 was detected at a control location with a mean concentration of 0.4 pCl/ liter. The Cs-137 and I-131 activity is attributed to Chinese atmospheric thermonuclear weapons testing. The comparison of 1991 data to results over l the operating life of the plant and preoperational data (1974) show that Cs 137 and 1131 levels have decreased significantly since 1974. The levels of Cs 137 and 1 131 detected prior to the plant going into commercial operation were the result of activities not related to power production at the site. 1-listorical data and a graphic presentation of milk sample results for Cs 137
, and 1 131 are presented in Section 7.0, Tables 717 and 7-18 and in Section 8.0, l respectively.
l . I I I I , I 5-43 I
5.2.6 FOOD PRODUCTS A. Results Summary There were no plant related iadionuclides detected in the food product samples collected and analyzed in 1991. One indicator sample contained a measurable level of Cs 137. He level of Cs 137 is representative of background levels of Cs-137 and is not attributed to operations at the site. Detectable levels of naturally occurring De 7 and K-40 were measured in each control and indicator sample coliccted for the 1991 program. l These results are consistent with the levels measured in 1990 and previous years. H. Data Analysis and Discussion Food product samples were collected from six indicator locations and one control location. The collection of annual food product samples became a l requirement as a result of Technical Soccification Amendment 127 in 1985. The indicator locations are represented by nearby gardens in areas of highest g D/O (deposition factor) values based on historical meteorology and an annual garden censuo The control location was a garden 15 miles away in a least prevalent wind direction. Food product samples collected during 1991, included cabbage and lettuce. These sample types are considered broadleaf vegetables. Where broadleaf g vegetables were not available, non edible broadleaf vegetation was collected. Non edible vegetation consisting of bean leaves, squash leaves, corn leaves, and g cucumber leaves were collected for the 1991 program. Samples were collected E during the late summer / fall harvest season. Each sample was analyzed for gamma emitters on a GeLi/HPGe detector. A I low level of Cs-137 was detected in one indicator sample of squash leaves. g The sample contained a Cs 137 concentration of 0.039 pCi/g (wet). Cs 137 was not detected in any of the other indicator or control lo ation food product g l samples for 1991. The source of the Cs-137 is considered to be the result of 5 l past atmospheric weapons testing. The amount of uptake of Cs 137 into plant 5-44 I 1 l l
I tissue is dependent on several factors related to soll composition. Cs 137 will often be substituted by ph.nts for similar elements, such as potassium, which may be lacking in the soil. The wide range in soil composition from location g to location can result in varying levels of Cs 137 uptake from location to location. The lack of other plant related radionuclides in the sample further I supports the assessment that the Cs 137 in the vegetation samples was the result of background Cs 137. The measured Cs 137 concentration was l consistent with levels detected in historical samples. l Naturally occurring 11e 7 and K-40 were detected above LLD in food product samples. The concentration of He 7 in vegetation samples ranged from 0.06 to 0.91 pCi/g (wet). The concentration of K-40 in indicator and control I samples ranged from 1.19 pCi/g (wet) and 6.99 pCi/g (wet). These results for naturally occurring radionuclides are consistent with those of prior yeata. Analytical results for food products are found in Section 6.0, Table 614. I C. Dose Esaluation The potential dose to man impact of Cs 137 found in a food product can be evaluated by calculating the resulting dose from consuniption of the vegetation. Using Regulatory Guide 1.109 Methodology, the maximum organ dose calculated was 0.34 mrem to the child bone. The maximum potential whole l body dose was calculated to be 0.18 mrem to the adult. These doses are very small in comparison to radiation exposure received from naturally occurring radionuclides. The annual whole body dose from naturally occurring K-40 is 20 mrem to the critical organ. D. Data Trends I There was one m a m de radi nuclide (Cs 137) detected in broadicaf edible and non edible vegetation samples analyzed in 1991. Food product results for the last five years show no trend other than that plant related radionuclides are not routinely detected in this sample media. This fact is also accurate for the entire time period of plant operation including preoperational results. Cs-137 I has been detected in four separate years since operation began at the FitzPatrick Power Plant. I 5-45 I
l In 1989, Cs 137 was detected in one non-edible broadleaf vegetation sample li collected at an indicator location. The concentration was 0.011 pCi/g (wet) which was close to its LLD. LLD values for all other samples ranged from g
<0.011 to <0.018 pCi/g (wet). Cs 137 was also detected in 1988. Other than naturally occurring levels of Be 7 and K-40, no other radioisotopes were ;
detected from 1986 - 1989. During the period of 1981 - 1985, Cs 137, Be 7 and K 40 were detected. Cs-137 was found at one indicator location during 1985 ut a concentration of 0.047 pCi/g (wet). The levels, of Be 7 and K-40 were consistent with natural background levels. There are no discernable trends indicating the presence of plant related radionuclides in food product vegetation samples, llistorical data and graphic presentations of food product results are presented in Section 7.0, Tables 719 and 7 20, and in Section 8.0. l l 1 E i l l l l l 5-46 I
I l 5.2.7 1AND USE CENSUS ItESUUI'S g A. Itesults Summary No changes were required to milk sampling mdicator or control locations in I 1991 based on the 1991 milk animal census. l The results of the closest residence censt.s conducted in 1991 required no change to the ODCM closest resident dose calculation reference. A garden census, not required by Technical Specifications, showed no changes in 1991 to food product (vegetation) sampling locations as required by I Technical Specifications. Two gardens planted and sampled in 1990 as optional locations were not planted in 1991. The garden samples were l collected from those locations listed in Table 11 1 of the ODCM and identified in the census as active for 1991.
- 11. Data Evaluation and Discussi.m A land use census is conducted each year to determine the utilization of land in the vicinity of the site. The land use census actually consists of two types of census. A milk animal census is conducted to identify all milk animals within a distance of 10 miles from the site. A census covering areas out to a l distance of 10 miles exceeds the 5 mile distance required by the Technical Specifications.
The milk animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site. The annual census is conducted during the first half of the grazing season by sending questionnaires to previous milk animal owners and also by road surveys to l locate any possible new locations. In the event the questionnaires are not answered, the owners are contacted by telephone or in person. The local county agricultural agency is also contacted as a further source of information g concerning new milk animal locations in the vicinity of the site. I 5-47 I
The number of milk animals estimated by the 1991 census was 1148 cows and 20 goats. This is an increase of 19 cows and a decrease of 9 goats from 1990. In 1991 one new location, a residence with a milking goat was identified 3.8 miles from the site. This new location did not require a change to the milk g sampling program or dose calculation indicator due to its distance and 3 direction from the site and its inability to provide routine milk samples. It did not provide a higher D/O value than existing locations. l The locations identified as a result of the milk animal census are illustrated on g a map in Section 33, Figure 3.3-4. The results of the milk animal census are found in Fection 6.0, Table 613. l The second type of census is a residence census. The census is conducted in order to identify the closest residence within 3 miles in each of the 22.5 degree ' land based meteorological sectors. There are only eight sectors over land g where residences are located within 3 miles. These water sectors include: N, NNE, NE, ENE, W WNW, NW and NNW The results of the residenc I census showing the applicable sectors and degrees and distance of ecch of the u nearest residence are found in Section 6.0, Table 615. The nearest resident locations are illustrated on a map in Section 3.3, Figure m 3.3 5. E I I I I SJ8 l ! E
I 5.3 CONCI.USION The IWhiP is a continuous program implemented to determine the radiological impact of JAl;NPP operations on the local environment. The program is designed and implemented to be sensitive to changes in the radiological environment surrounding the site- The sensitivity of this program became extremely important following the ina>Jvertent n icase of radioactive material to the environment on March 18,1991 due to operator errors during operation of the radwaste concentrator sptem. Appendix A contains a detailed discussion of this event and associated environmental samples. The results of the 1991 Itadiological linvironmental Surveillance Program clearly demonstrates that there was no significant short term or chronic long term detrimental impact on the environment in the vicinity of the Nine Mile Point site. The major radiologicalimpact on the environment remains the l result of atmospheric weapons testing in the early 1980s and the 1986 accident at the Chernobyl Nuclear Power Plant. Iloth of these source terms have increased the ubiquitous inventory of Cs 137. Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the environment or to man. In addition, the data was reviewed for possible short and long term historical trends. Doses as a result of naturally occurring radionuclides such as K40 and Ita 226, contributed the major portion of the total annual dose to members of the general public. The maximum potential individual dose to man, as a result of the March 18,1991 release was calculated to be 0.0014 mrem whole body (child) and 0.0024 mrem critical organ (infa I liver) via the drinking water pathway. The maximum potential dose to man calculated as received from the fish consumption pathway was 0.057 mrem whole body (adult) and 012 l mrem to the critical organ (teen livers). The long term doses to man as a result of anthropogenic sources can mainly be attributed to the Chernobyl accident and atmospheric weapons testing. Most of the radionuclides detected in 1986 as a result of Chernobyl were not detected in subsequent years. Dose received from man made sources are very small when compared to the dose from naturally occurring sources of rmlioactivity. I I I sa9
i The contribution to the whole body dose as a result of plant operations is extremely small when compared to the dose contribution from naturalliackground levels and sources other l ] than the plant. Whole body doses in Oswego County due to all natural sources is approximately sisty mrem per individual per year as demonstrated by control environmental ! TLDs. The fraction of the annual dose to man attributable to site operation remains insignificant. I I i I I ! I ' E I: I l I' I 5-50
I 5.4 REFERENCE l 1. Radiological Effluent Technical Specifications, Appendix Il to Facility Operating IJcense No. DPR 59 For James A. FitzPatrick Nuclear Power Plant, New York Power Authority, Docket No. 50-333; Amendment 127.
- 2. U.S. Nucicar Regulatory Commission Regulatory Guide 1.109,
- Calculation of Annual Doses to Man from Routine Releases of Reactor Effluent for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix 1", October,1977.
I 3. Eichholz, G., Environmental Aspects of Nuclear Power. First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan,1976.
- 4. National Council on Radiation Protection and Measurements (NCRP),
Environment;ti Radiation Measurements. NCRP Report No. 50,1976. l 5. National Council on Radiation Protection and Measurements (NCRP), Natural Backcround Radiation in the United States. NCRP Report No. 45,1975.
- 6. National Council on Radiation Protection and Measurements (NCRP),fnittnld32
' from the Environment to Man: Metabolism and Dom NCRP Report No. 52, 1977. l 7. National Council on Radiation Protection and Measurements (NCRP), Radiation
. Exposure from Consumer Products and Miscellanecus Souren NCRP Report No.
56,1977. g
- 8. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, " Environmental I Technical Specifications for Nuclear Power Plants", December 1975.
I 9. U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory g Guide 4.8 "An Acceptable Radiological Emironmental Monitoring Program". November,1979,
- 10. Eisenbud, Merril, Erwironmental Radioactivity. Third Edition, Academic Press, New York, New York,1987.
5 51
I
- 11. Francis, C. W., Radipstrontium Movement in Soils and Uptake in Plants, Emironmental Sciences Division, Oak Ridge National laboratory, U.S.
l De;)artment of Energy,1978.
- 12. National Council on Radiation Protection and Measurements (NCRP),Endialloll Exporure from Consumer Products and Miscellaneous Sources. NCRP Report No.
56,1977.
- 13. Pochin, Edward E., Estimated Population Exposure from Nuclear Pown I
P_roduction and Other Radiation Sources. Organization for Economic Co-operation and Development,1976. l
- 14. 1CRP Pubilcation Number 29, J3adionuclide Releases into the Environment:
Assessment of Dose to Man.1979.
- 15. U.S. Department of Ilealth and Human Services, Preparedness and Response in I
Radiation Accidents. National Center of Devices and Radiological Health, Rockville, MD 20857, August,1983. l
- 16. Kathren, Ronald E., R ADIOACTIVITY IN THE ENVIRONMENT: SOURCES, J21STRIBUTION. AND SURVEILI ANCE. First Edition, Harwood Academic Press, New York, NY,1984. l
- 17. N'itional Council on Radiation Protection and Measurement (NCRP), Ionizing Radiation Exposure of the Population of the United States, NCRP Report No. 93, l
1987 g
- 18. Knoll, G., Radiation Detection and Measurement. Second Edition, John Wiley &
Sons, New York, New York,1989. I 1 I I I 5 52 I
.E
l 6.0 REPORT PERIOD ANAIXrICAL RESULTS TAllLES I 6.1 Emironmental sample data is summarized in table format. Tables are provided for select sample media and contain data based on actual values obtained over the year. These values are comprised of both positive values and LLD values where applicable. l 6.2 The LLD is the smallest concentration of radioactive material in a sample that will be detected with 95% probability and with 5% probability of falsely I concluding that a blank observation represents a "real" signal (see Section 3.7.3 for detailed explanation). 6.3 When the initial count of a sample indicates the presence of radioactivity, two recounts are normally perfortned. When a radionuclide is positively l identified in two or more counts, the analytical results for that radionuclide is reported as the mean of the positive detections and the associated error g for that mean (see Section 3.7.2 for methodology). 6.4 Many of the tables are fc Noted with the term " Plant Radionuclides". Plant I related radionuclides are radionuclies that are produced in the reactor as a result of plant operation either through the activation or fission process. I I I I I I I 6-1 I
M M M M "C M M M M M M M M M M M M M TABLE 6-1 CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in Units of pCi/g (dry) i 1 Sigma
- . . ~ .
~.- . . . _ - . w- m ..m_ ,,. , ~ = . .
'~ ,
- STATIONF- COLLECT 10l!L 4 2- 'i &^ -< . ;
EMIgEq.q,j
.< A _
W DATE Ts@an Th4n;, gf v M NCOD .. w n E*i.ms i? mww.. e ne, e - r,e w _ms
.. t. -
K-40 Co-60 Cs-134 Cs-137 Zn-65 OTHEPS** _ r Sunset Beach 04/24/91 15.4 0.31 <0.07 <0.10 0.12i0.01 <0.18 <LLD 10/25/91 17.8t0.34 <0.06 <0.06 0.1410.01 <0.22 <LLD Lang's Beach 04/24/91 13.4i0.48 <0.05 <0.06 <0.04 <0.16 <LLD (06, Control) 10/25/91 10.910.47 <t.05 <0.05 <0.04 <0.14 <LLD t i
- Corresponds to sample locations noted on the maps in Section 3.3.
** Plant Related Iso;. opes
TABLE 6-2
, CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES Results in Units of pCi/g (wet) i 1 Sigma
- z. : := : :a ::: g:r c :7 - y- . -
JDATE L.N ~5TY,P,% i EF s a W40,;~ M.Mn 5.4M Cos58 lFe ,59,N y Co-60i Zn-651 my ( 3 1Cs-1 c.- ,34 ,6 .;Cs.137Jf0THER$* ny .w - , - -
-7 g g FITZPATRICK 05/29/91 Brown Trout 4.8710.22 <0.031 <0.036 <0.106 <0.032 <0.075 <0.032 0.018t0.006 <LLD 06/06/91 Lake Trout 4.8810.23 <0.032 <0.041 <0.115 <0.033 <0.084 <0.034 <0.030 <LLD I
06/07/91 White Sucker 5.49 0.26 <n.037 <0.49 <0.124 <0.038 <0.101 <0.036 <9.032 <LLD 06/18/91 Smallmouth Bass 4.23t0.23 <0.028 <0.033 <0.074 <0.037 <0.076 <0.029 0.044i0.012 <LLD 06/18/91 White Perch 3.4120.24 <0.038 <0.044 <0.107 <0.049 <0.092 <0.038 0.02710.007 <LLD 06/18/91 Wal1 eye 5.46i0.29 <0.036 <0.042 <0.123 <0.040 <0.101 <0.038 0.04510.007 <tLD 09/25/91 Smallmouth Bass 4.3810.23 <0.032 <0.038 <0.127 <0.042 <0.087 <0.029 0.03210.007 <LLD 10/01/91 White Sucker 3.7910.21 <0.030 <0.036 <0.101 <0.042 <0.078 <0.027 <0.025 <LLO 10/01/91 Lake Trout 4.30t0.20 <0.027 <0.033 <0.081 <0.030 <0.074 <0.028 0.02410.006 <LLD 10/01/91 Walleye 4.32i0.20 <0.025 <0.030 <0.072 <0.028 <0.063 <0.024 0.02910.006 <LLD i 10/10/91 White Perch 4.2010.31 <0.046 <0.050 <0.124 <0.047 <0.114 <0.037 <0.045 <LLD 10/10/91 Brown Trout 3.9310.25 <0.031 <0.034 <0.078 <0.040 <0.090 <0.030 0.021z0.006 <LLD
- Plant Related Radionuclides e
m m m m m m m W W M M M M M M M M M M
saa m aus aus uma uma sus saa sus sum aus aus aums sus aus sus sus aus aus TABLE 6-2 (Courzuuto) CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES Results in Units of pCi/g (wet) i 1 Sigma DATNN, jiYPEf , [ MK-407 M M M5U 'Co-5BOFe-5'9 X Co-60I 'ZnY65! (Csh134;* Cs-137[ OTHERS* NINE MILE POINT 06/06/91 Lake Trout 3.91*0.29 <0.045 <0.066 <0.152 <0.056 <0.122 <0.038 <0.033 <LLD 06/06/91 Brown Trout 4.1210.25 <0.036 <0.045 <0.127 <0.044 <0.093 <0.031 <0.027 <LLD 06/18/91 Smallmouth Bass 4.7210.25 <0.035 <0.044 <0.111 <0.041 <0.093 <0.037 <0.032 <LLD [ 06/18/91 White Sucker 2.95i0.19 <0.031 <0.C35 <0.082 <0.033 <0.083 <0.028 <0.027 <LLD 06/18/91 White Perch 4.59 2.30 <0.027 <0.037 <0.104 <0.032 <0.082 <0.032 0.02910.007 <LLD 09/13/91 Salmon 5.0410.23 <0.0L <0.043 <0.128 <0.034 <0.082 <0.032 0.02810.006 <LLD 1 09/13/91 Smalimouth Bass 4.1710.21 <0.028 <0.036 <0.099 <0.033 <0.079 <0.030 0.02410.006 <LLD 09/25/91 Walleye 4.5510.25 <0.030 <0.037 <0.102 <0.036 <0.091 <0.029 0.03310.006 <LLD 09/25/91 White Perch 4.6910.33 <0.046 <0.059 <0.157 <0.070 <0.126 <0.047 <0.050 <LLD 10/10/91 White Sucker 3.94 0.21 <0.027 <0.035 <0.073 <0.034 <0.077 <0.031 <0.027 <lLD 10/10/91 Lake Trout 3.93 0.25 <0.032 <0.040 <0.091 <0.046 <0.095 <0.038 0.02610.059 <LLD
- Plant Related Radionuclides
TABLE 6-2 (Ceurruuto) CONCENTRATIONS OF GAMMA EMITTERS IN FISH SAMPLES Results in Units of pCi/g (wet) i 1 Sigmt. U A :Cs-1373 OTHERI* 2DNkEl PEN NUK$4bNiMnh54/ Co--5S : Fe5[9[{co-60VZn-655.Cs@l34 OSWEGO HARBOR (Control) White Sucker 4.4510.30 <0.049 <0.064 <0.197 <0.060 <0.120 <0.037 <0.043 <LLD 05/29/91 Brown Trout 5.10i0.29 <0.036 <0.061 <0.155 <0.045 <0.118 <0.037 <0.040 <LLD 05/29/91 Lake Trout 3.4010.22 <0.030 <0.040 <0.111 <0.042 <0.092 <0.032 <0.030 <LLD 06/06/91 Walleye 4.54i0.26 <0.038 <0.045 <0.145 <0.045 <0.094 <0.035 0.03410.007 <LLD 06/18/91 06/19/91 Smallmouth u 9s Bass 4.5410.23 <0.029 <0.030 <0.085 <0.040 <0.083 <0.034 0.029 0.009 <LLD l White Perch 2.4210.19 <0.033 <0.042 <0.098 <0.035 <0.074 <0.030 0.034 0.007 <tLD 06/19/91 Salmon 3.93i0.20 <0.028 <0.032 <0.096 <0.030 <0.070 <0.024 0.021i0.007 <LLD 09/13/91 09/13/91 Smallmouth Bass 4.7210.31 <0.043 <0.063 <0.018 <0.063 <0.127 <0.045 <0.042 <LLD Walleye 4.75i0.30 <0.041 <0.058 <0.144 <0.041 <0.124 <0.033 0.028 0.015 <LLD 09/13/91 4.58i0.30 <0.045 <0.055 <0.136 <0.057 <0.116 <0.036 <0.038 <LLD 09/25/91 Brown Trout 3.7910.27 <0.035 <0.042 <0.013 <0.055 <0.118 <0.031 <0.039 <LLD 10/02/91 Lake Trout 3.5710.20 <0.026 <0.028 <0.062 <0.035 <0.071 <0.024 <0.026 <LLD 10/02/91 White Sucker 4.4810.22 <0.030 <0.031 <0.076 <0.034 <0.077 <0.030 <0.028 <LLD 10/02/91 White Perch Plant Related Radionuclides M M M M M M M M M M M M M Im M M M M M
ums ~ mas uma mas mas sua sus ame ums uma mum ums sum amm aus amm aus mas mas TABLE 6-3 CONCENTRATIONS OF TRITIUM IN SURFACE WATER (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/ liter i 1 Sigma
~
'LTRITIUM'
~
~
iSTNYION[C0 DEL ' PERIODL DATE FITZPATRICK* First Quarter 01/02/91-03/30/91 390130 (03, INLET) Second Quarter 04/01/91-07/01/')1 250iS0 OSWEGO STEAM
- First Quarter 12/31/90-04/01/91 <100 STATION (08, CONTROL) Second Quarter 04/01/91-07/01/91 180235
[ 390255 NINE MILE First Quarter 12/31/90-04/01/91 ~ POINT UNIT 1** (09, INLET) Second Quarter 04/01/91-07/01/91 220t35 NINE MILE First Quarter 12/31/90-04/01/91 360150 POINT UNIT 2** (11, INLET) Second Quarter 04/01/91-07/01/91 230 35 OSWEGO CITY ** First Quarter 12/31/90-04/01/91 590i35 WATER (10) Second Quarter 04/01/91-07/01/91 270250 i
- Samples required by the Technical Specifications
** Optional samples Oswego City Water samples are composites of twice per week grab samples
TABLE 6-3 (Courruuso) CONCENTRATIONS OF TRITIUM IN SURFACE WATER (QUARTERLY COMPOSITE SAMPLES) Results in Units of pCi/ liter i 1 Sigma Y
' ^
'~ ~
r # i.STATiONLC00U2 *
' ~
.)PIk[001'^^ _
1DAT'E2 - STRIIIUMS FITZPATRICK* Third Quarter 07/01/91-09/30/91 290i45 (03, INLET) Fourth Quarter 09/30/91-12/30/91 <160 OSWEGO STEAM
- Third Quarter 07/01/91-09/30/91 200t35 STATION (08, CONTROL) Fourth Quarter 09/30/91-12/31/91 <160 NINE MILE Third Quarter 07/01/91-09/30/91 270 30 POINT UNIT 1**
(09, INLET) Fourth Quarter 09/30/91-12/31/91 <160 NINE MILE Third Quarter 07/01/91-09/30/91 340155 POINT UNIT 2** (11, INLET) Fourth Quarter 09/30/91-12/31/91 <160 OSWEGO CITY ** Third Quarter 07/01/91-09/30/91 220i35 WATER (10) Fourth Quarter 09/30/91-12/31/91 <160
- Samples required by the Technical Specifications
** Optional samples Oswego City Water samples are composites of twice per week grab samples im m m M m m M WE M M M M M M M M M M M ;
M M M M M M M M m m m m m m m M M M M TABLE 6-4 CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1991 Results in Units of pCi/ liter i 1 Sigma JANUARY- FE8RUARY--- MARCH 'APRILL :MAY l JUNE-STATION; CODE *< NUCLIDE) I I-131 <0.13 <0.13 <0.24 <0.26 <1.0 <0.50 OSWEGO STEAMt Cs-134 <2.89 <3.63 <4.32 <3.73 <3.19 <3.15 STATION Cs-137 <2.95 <3.34 <3.76 <3.58 <3.19 <3.42 (08, CONTROL) Zr-95 <6.18 <5.60 <8.49 <6.53 <5.38 <5.95 Nb-95 <3.73 <4.23 <5.01 <4.20 <3.77 <4.03 Co-58 <3.04 <3.45 <4.77 <4.01 <3.78 <3.59 Mn-54 <2.85 <2.92 <4.22 <3.51 <2.97 <3.08 Fe-59 <6.92 <9.11 <11.5 <8.96 <7.50 <8.26 Zn-65 <5.93 <8.33 <9.05 <8.98 <8.82 <8.35 Co-60 <3.02 <3.41 <4.82 <3.81 <3.94 <4.07 K-40 176129.3 53.2113.0 71.1115.0 236118.1 202118.2 58.0 12.5
$ <7.02 <7.55 <8.87 <8.07 <10.9 <8.30 Ba/La-140 1-131 <0.20 <0.19 <0.26 <0.36 <0.70 <0.90 FITZPATRICKt <3.94 (03, INLET) Cs-134 <3.12 <4.95 <3.83 <3.09 <3.74 Cs-137 <2.49 <4.53 <3.50 <3.38 <3.76 <3.46 Zr-95 <5.08 <8.96 <7.15 <6.25 <7.05 <7.29 Nb-95 <2.94 <5.68 <4.32 <4.09 <4.19 <4.86 Co-58 <3.03 <5.51 <3.60 <3.88 <3.78 <4.21 Mn-54 <2.84 <4.77 <3.36 <3.11 <3.50 <3.19 Fe-59 <6.31 <11.4 <8.23 <8.56 <8.67 <9.26 Zn-65 <5.12 <13.8 <9.38 <8.13 <9.24 <9.58 Co-60 <2.45 <4.61 <3.20 <3.82 <3.53 <3.91 K-40 69.4123 217123.0 246i18.5 49.7*14.2 185218.0 240i19.0 Ba/La-140 <4.79 <11.6 <8.25 <9.87 <10.0 <10.8
!
- Corresponds to sample locations noted on the maps in Section 3.3.
t Samples required by the Technical Specifications.
TABLE 6-4 (conux:ca CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1991 Results in Units of pCi/ liter i 1 Sigma
~
STATIONiCDDE*i iNUdLIDE( [ JANUARY { (FEBRUARYL MARCH $ :APRIU [ MAYI ? JUNE 6-NINE MILE I-131 <6.29 <B.61 <9.94 <9.79 <8.86 <9.69 POINT Cs-134 <1.39 <4.10 <3.78 <4.02 <3.32 <2.91 UNIT 1** Cs-137 <1.53 <3.33 <3.62 <3.68 <2.99 (09, INLET) <3.13 Zr-95 <3.91 <6.78 <7.05 <6.75 <5.81 <6.59 Nb-95 <2.85 <4.66 <4.71 <4.29 <3.99 <3.97 Co-58 <1.68 <4.07 <3.62 <3.69 <3.43 <3.13 Mn-54 <1.42 <3.42 <3.28 <3.66 <3.13 <3.13 Fe-59 <3.87 <9.34 <10.1 <8.59 <7.35 <7.30 Zn-65 <3.26 <9.67 <8.89 <9.20 ~8.28 <8.14 Co-60 <3.36 <3.32 <3.32 <3.60 <3.76 <3.82 P K-40 47.8*12.7 242i19.6 213 18.4 223i19.0
- 37.4212.3 40.6112.8 Ba/La-140 <3.93 <7.56 <10.4 <9.44 <8.40 <9.85 NINE MILE I-131 <11.8 <12.4 <9.94 <8.97 <12.~5 <13.6 POINT Cs-134 <3.78 <4.75 <5.06 <4.67 <4.71 <5.23 UNIT 2** Cs-137 <3.81 <3.58 <4.36 <3.92 <4.28 <4.52 (11, INLET) Zr-95 <8.04 <9.50 <7.46 <7.63 <9.09 <9.32 Nb-95 <5.52 <5.61 <4.57 <5.01 <5.95 <6.13 Co-58 <4.29 <4.90 <4.31 <4.86 <5.23 <5.36 Mn-54 <3.60 <4.24 <4.42 <4.66 <4.63 <4.60 Fe-59 <8.89 <10.7 <8.76 <10.1 <11.0 <10.8 Zn-65 <7.69 <7.33 <10.8 <10.0 <10.9 <11.9 Co-60 <3.60 <5.77 <4.73 <5.07 <5.69 <5.69 K-40 207140.6 81.0117.2 87.7 14.7 116t16.8 244i24.6 25.1124.7 Ba/La-140 <8.34 <14.3 <12.3 <10.4 <9.19 <13.1 Corresponds to sample locations noted on the maps in Section 3.3.
** Optional sample location. Samples not required by Technical Specifications.
se as Mel M M M M M M M M M M M E- M M M M
sus aus sus aus aus uma uma sum aus uma uma sus sus uma som aus sus mas mum TASI.E 6-4 (Courinuto) CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1991 Results in Units of pCi/ liter i 1 Sigma 7NUCLIDE~ .dANUARY. .iFEBRUARY! . MARCH! LAPRIli ' LMAYl - ~ JUNE' j
- STt41.ONICDDE*?
i I-131 <12.4 <12.3 <10.4 <9.07 <10.3 <11.4 OSWEGO CITY Cs-134 <3.56 <4.09 <3.74 <5.01 <3.90 <3.38 WATER **- Cs-137 <3.68 <3.55 <3.25 <4.21 <3.39 <2.95 (10) <8.63 <6.52 <6.29 Zr-95 <6.72 <7.67 <6.81 Hb-95 <5.50 <4.94 <4.58 <4.97 <4.57 <4.34 Co-58 <3.53 <4.42 <4.05 <4.52 <4.02 <3.23 Mn-54 <3.81 <3.72 <3.61 <4.37 <3.50 <3.00 l Fe-59 <8.50 <10.2 <8.69 <8.75 <9.30 <8.84 Zn-65 <7.30 <9.77 <9.87 <9.60 <9.13 <9.59 Co-60 <3.16 <3.67 <4.01 <4.82 <3.35 <3.63 K-40 182i35.3 26.1218.9 252i18.7 84.8*14.4 202118.2 32.3t11.7
$ <10.1 <10.8 <13.3 <10.9 <11.9 o Ba/La-140 <7.95
- Corresponds to sample locations noted on the maps in Section 3.3.
** Optional sample location. Samples not required by Technical Specifications.
TABLE 6-4 (Courzuuto) CONCENTh TIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1991 Results in Units of pCi/ liter i 1 Sigma STATION CODEM INUCLI'D_Ei idULY/ ikUGUSTP SEPTEMBER LOCTOBER; LNOVEMBER DECEMBERi OSWEGO STEAMt I-131 <0.60 <0.30 <0.20 <0.90 <0.30 <1.00 STATION Cs-134 <4.09 <3.25 <3.00 <3.97 <2.88 <3.06 (08, CONTROL) Cs-137 <3.77 <3.01 <3.17 <3.48 <3.27 <2.94 Zr-95 <6.85 <5.74 <5.98 <7.47 <6.24 <5.59 Nb-95 <4.48 <4.06 <4.33 <4.68 <3.96 <3.60 Co-58 <3.87 <3.64 <3.68 <4.19 <3.60 <3.20 Mn-54 <3.54 <3.24 <3.31 <3.34 <3.13 <2.97 Fe-59 <9.65 <8.54 <7.87 <9.24 <8.11 <7.34 Zn-65 <9.23 <8.53 <8.18 <9.44 <8.41 <7.59 Co-60 <3.86 <4.07 <4.62 <3.64 <3.88 <3.08 K-40 202i19.0 63.0115.5 45.6 14.2 226117.9 45.4113.0 246i15.4 Ba/La-140 <9.19 <9.57 <11.4 <9.66 <7.78 <8.72 FITZPATRICKt I-131 <0.60 <0.40 <0.10 <0.90 <0.50 <1.00 (03, INLET) Cs-134 <4.85 <3.57 <4.34 <2.70 <3.67 <5.40 Cs-137 <4.40 <3.38 <3.77 <2.86 <3.64 <4.31 Zr-95 <8.29 <7.89 <7.17 <6.16 <6.71 <8.37 Nb-95 <5.36 <4.77 <4.81 <3.92 <4.26 <4.99 Co-58 <4.98 <3.88 <3.89 <3.50 <4.10 <4.65 Mn-54 <4.73 <3.77 <3.54 <3.15 <3.32 <4.30 Fe-59 <11.8 <8.93 <9.49 <7.68 <8.39 <12.5 ; Zn-65 <11.4 <9.92 <9.65 <6.88 <8.91 <11.9 Co-60 <5.58 <4.93 <3.75 <3.75 <4.12 <6.13 K-40 232122.0 59.5i15.3 230118.7 44.4i13.5 257*19.1 223i22.3 Ba/La-140 <9.74 <13.0 <9.02 <9.74 <9.02 <14.4
- Corresponds to sample locations noted on the maps in Section 3.3.
t Samples required by the Technical Specifications. Im M M M M M M M M M M M M M M M M M M
asus amn mas uma ama amm uma ums amm amm aman amm amm ums TABLE 6-4 (Comnuto) 1
. CONCENTRATIONS OF GAMMA EMITTERS IN SURFACE WATER SAMPLES - 1991 Results in Units of pCi/ liter i 1 Sigma I
!~TATIONLCODEh S [NUddDE" JULI$3[ AUGUST- ' SEPTEMkiER $0CTb8EA5 ,NOVDRERi g ;CECEMBER'I NINE MILE I-131 <8.23 <10.7 <8.22 <9.09 <9.73 <8.54 POINT Cs-134 <2.68 <2.67 <3.12 <3.05 <3.55 <2.37 UNIT 1*" Cs-137 <3.09 <3.04 <3.42 <3.13 <3.36 <2.73 (09, INLET) Zr-95 <6.35 <5.44 <6.91 <5.75 <6.08 <5.32 Nb-95 <3.68 <3.72 <4.44 <4.25 <4.21 <3.17 Co-58 <3.32 <3.49 <3.72 <2.81 <4.10 <2.81 Mn-54 <2.70 <2.77 <3.58 <3.20 <3.25 <2.44 Fe-59 <7.06 <7.70 <8.82 <7.61 48.84 <6.44 Zn-65 <6.69 <7.59 <9.31 <7.17 <9.20 <6.05 :
, Co-60 <3.75 <3.19 '5.13 <3.42 <4.41 <3.08 2.
" K-40 61.7t13.2 87.7112.3 48.0i14.9 47.0112.6 47.3i14.9 49.2 10.6 Ba/La-140 <9.39 <12.8 <11.0 <11.1 <11.9 <9.06 NINE MILE I-131 <8.87 <13.0 <9.77 <9.52 <8.30 <11.8 '
POINT Cs-134 <3.21 <3.83 <3.11 <2.50 <2.43 <3.66 UNIT 2** Cs-137 <2.95 <3.96 <3.54 <2.12 <2.69 <3.39 (11, INLET) Zr-95 <6.89 <7.96 <6.29 <4.69 <5.29 <7.51 Nb-95 <4.25 <5.20 <4.01 <3.09 <3.52 <4.85 Co-58 <3.70 <4.64 <3.98 <2.74 <3.03 <4.32 Mn-54 <3.29 <4.17 <3.50 <2.26 <2.30 <3.97 i Fe-59 <8.37 <11.0 <9.19 <S.93 <6.83 <9.72 Zn-65 <7.97 <9.81 <9.05 <5.57 <S.92 <9.50 : Co-60 <3.49 <5.43 <4.05 <2.49 <3.01 <4.63 i K-40 56.6 13.0 187119.2 65.6117.8 24.2 12.8 65.9t10.9 214218.7 Ba/La-140 <10.9 <12.9 <13.6 <7.12 <9.12 <13.5
- Corresponds to sample locations noted on the maps in Section 3.3.
** Optional sample location. Samples not required by Technical Specifications.
i
i l TABLE 6-4 (courznuto) CONCENTRATIONS GF GAMMA EMITTERS IN SURFACE WATER SAMPLET - 1991 ; l Results in Units of pCi/ liter i 1 Sigma
~
LOCTOBER4 'iNOVEMBERj .DECEMEER-~ h$TATIONC'008N INUCLIDE[ '[JULU' ' AUGUST [
-SEPTEMBERr I-131 <S 95 <12.3 <9.14 <11.6 <13.7 <11.0 OSWEGO CITY
<3..6 <4.68 <3.16 <4.16 <4.50 <2.93 l WATER ** Cs-134 Cs-137 <3.65 <4.61 <3.13 <4.60 <4.4' <2.43 (10) <6.27 <9.79 <8.87 <5.40 Zr-95 <7.21 <9.48 Nb-95 <4.44 <6.10 <4.09 <5.67 <5.44 <3.55
<3.69 <5.38 <3.67 <5.14 <5.52 <2.92 Co-58 d
Mn-54 <3.50 <4.55 <3.30 <4.30 <4.71 <2.69
<9.11 <10.5 <9.17 <10.5 <11.1 <6.53 Fe-59
<10.2 <10.4 <8.28 <12.7 <11.9 <6.91 Zn-65
<4.63 <6.56 <4.01 <5.75 <5.41 <2.79 Co-60
- 4. K-40 87.8*17.3 179222.5 50.5i13.5 158121.8 229122.7 77.0i10.8
" <13.0 <14.5 <9.48 <12.3 <14.2 <9.86 Ba/La-140
- Corresponds to sample locations noted on the maps in Sect.'on 3.3.
** Optional sample location. Samples not required by Technical Specifications.
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TABLE 6-9 n CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results .in Units of 10 'pCi/m3 i 1 Sigma
..-m, m-w . - 1 ma . :n w r., , m -r - -
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jNUCLIDESL *41ANUARYj
] / FEBRUARY 3 ; MARCH 2 jy ? APRIL;: =MAY 6 ^ QUNEi R1 0FF-SITE COMPOSITE
- TlCe-144 <3.95 <4.71 <2.98 <3.92 <3.57 <4.35 Ce-141 <1.17 <1.59 <0.98 <1.28 <1.10 <1.46 Be-7 69.2i12.1 69.217.8 62.815.1. 86.816.3 73.715.8 69.216.7 Zn-65 <1.52 <4.37 <3.16 <3.45 <2.63 <3.09 Cs-134 <0.96 <1.70 <0.88 <1.23 <0.97 <1.29 Cs-137 <0.89 <1.50 <0.77 <1.16 <1.01 <1.68 Zr-95 <1.86 <2.68 <1.98 <2.58 <1.89 <2.95 Nb-95 <1.49 <1.63 <1.06 <1.49 c1.38 <1.41 es Co-58 <1.09 <1.38 <1.27 <1.00 <1.11 <1.48
$ Mn-54 <0.99 <1.59 <1.02 <1.14 <0.56 <1.77 Co-60 <1.14 <2.25 <0.68 <1.38 <1.56 <1.81 K-40 <14.2 <20.5 <10.6 38.8*6.9 26.826.4' 21.Si6.8 Otherst <LLD <LLD <LLD <LLD <LLD <LLD R2 0FF-SITE COMPOSITE
- TlCe-144 <3.24 <4.48 <3.95 <3.93 <4.62 <5,10 Ce-141 <0.66 <1.23 <1.36 <1.45 <1.43 <1.76 Be-7 74.5163.9 73.8163.5 65.117.0 85.5 7.3 87.7 7.9 75.227.8 Zn-65 <1.59 <3.68 <3.83 <2.60 <4.10 <4.21 Cs-134 <0.44 <1.35 <1.51 <1.83 <1.29 <1.60 Cs-137 <0.51 <1.29 <1.52 <1.47 <1.39 <1,48 Zr-95 <0.77 <2.53 <2.80 <2.63 <2.73 <2.95 Nb -95 :0.67 <1.45 <1.77 <2.12 <2.16 <1.96 Co-58 <0.94 <1.43 <1.72 <2.37 <1.32 <1.80 Mn-54 <0.55 <1.23 <1.09 <2.44 <1.34 <1.04 Co-60 <1.18 <2.15 <1.74 <2.96 <2.30 <1.80 K-40 <10.8 <16.2 24.li7.0 <2.23 16.116.3 53.8 8.6 Otherst <LLD <LLD <LLD <LLD <LLD <LLD Sample Locations Required by Technical Specifications.
? Plant Related Radionuclides.
TABLE 6-9 (Ceurruuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES ) 0F JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pC1/m' r 1 Sigma
?
[MARCHT 9APRI6 JMAY? r $UNE!
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<3.42 <4.20 <3.38 <4.18 T1Ce-144 <2.81 <5.21 <1.39
<1.74 <1.27 <1.22 <1.13 !
Ce-141 <0.69 74.715.5 69.4i6.5 I 62.8i5.8 61.9i8.4 75.416.7 89.516.6 Be-7 <2.89 <3.28 <3.45
<2.24 <4.05 <3.87 Zn-65 <1.11 <0.97 <1.37 i
<0.80 <2.23 <1.49 Cs-134 <1.43 <1.03 <0.97 <1.13 !
Cs-137 <0.72 <1.34 <1.68
<3.83 <1.97 <2.38 <2.15 Zr-95 <1.33 <0.80 <1.11
<2.07 <1.60 <1.41 Nb-95 <1.93 <0.93 <1.37 l
<1.92 <1.80 <1.22
! e Co-58 <0.68 <0.82 <0.99
<1.78 <1.30 <1.31 d Mn-54 <0.72 <1.65 <1.60
<0.66 <2.39 <2.33 <1.56 Co-60 <2.59 8.5414.8 39.927.8 K-40 <11.8 20.3*9.3 8.9614.3
<LLD <LLD <LLD
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<3.42 <3.99 <3.78 <4.64 TlCe-144 <5.22 <5.12 <1.62
<1.88 <1.08 <1.37 <1.16 Ce-141 <1.99 77.015.6 86.li7.6 73.0t12.5 94.8i9.2 72.315.6 90.6 7.0 Be-7 <4.53 <2.96 <3.02
<2.59 <4.54 <3.13 Zn-65 <1.19 <1.11 <1.90
<1.09 <1.76 <0.90 Cs-134 <;.02 <1.14 <1.09 <1.32 Cs-137 ~< 1.04 <1.46
<1.57 <2.12 <2.21 <2.57 Zr-95 <1.84 <3.39 <1.97
<2.65 <0.68 <2.00 <1.59 Nb-95 <1.50 <1.03 <1.59
<1.18 <2.77 <0.78 <1.37 Co-58 <0.91 <1.18 <1.06 <1.10 Mn-54 <1.06 <1.68 <1.94
<2.48 <1.15 <1.20 <0.84 Co-60 <0.83 30.0*5.7 31.Si8.0 42.9114.4 23.718.5 <14.5 12.516.1 l K-40 <LLD <LLD <LLD <LLD Otherst <LLD <LLD 1
- Sample Locations Required by Technical Specifications.
t Plant Related Radionuclides. m m m m M M M m m m e m e m E MI m m m bliB
l TABLE 6-9 (C:nvrnuco) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pCi/m3 1 Sigma MUCLIDES! JJANUA.RY5 TEBRUARN ' ~i MARCH l , lAPRILi
- iMAY{ SUNE:
R5 0FF-SITE COMPOSITE (CONTROL)* T1Ce-144 <5.10 <4.19 <3.09 <4.35 <3.34 <5.92 Ce-141 <1.61 <1.38 <1.10 <1.56 <1.26 <1.91 8e-7 60.7*13.5 76.9 6.3 66.2i5.0 87.717.8 77.4 6.2 72.7*8.0 Zn-65 <2.75 <3.87 <2.27 <5.92 <2.59 <4.65 Cs-134 <1.01 <1.41 <1.13 <2.36 <1.29 <1.65 Cs-137 <1.24 <1.17 <0.88 <1.60 <1.24 <1.69 Zr-95 <1.89 <2.57 <1.91 <3.30 <2.12 <3.30 Nb-95 <1.12 <1.82 <1.35 <2.38 <1.65 <2.20 Co-58 <0.79 <1.50 <1.12 <1.49 <1.05 <2.39 l
$ Mn-54 <1.09 <1.20 <0.88 <1.77 <0.92 <1.97
* <1.63 <1.84 <1.23 <2 11 <1.34 <3.23 Co-60 K-40 28.9*14.9 47.6*7.2 33.215.7 14.215.2 35.0t6.3. 46.918.6 Otherst <LLD <LLD <LLD <LLD <LLD <LLD D2 0FF-SITE COMPOSITE **
T1Ce-144 <5.64 <4.49 <3.58 <5.29 <4.84 <4.84 Ce-141 -1.66 <1.48 <1.27 <1.98 <1.46 <1.65 Be-7 68.7112.7 63.816.7 61.826.1 76.018.8 76.2i7.6 88.6 7.5 Zn-65 <2.58 <3.89 <3.46 <6.62 <4.29 <3.20 Cs-134 <0.72 <1.39 <1.14 <2.38 <1.26 <1.36 Cs-137 <1.05 +1.O <1.14 <1.92 <1.66 <0.91 1 Zr-95 <2.19 <2.88 <2.48 <3.45 <3.14 <2.93 Nb-95 <1.36 <1.50 <1.59 <2.24 <2.18 <1.90 Co-58 <1.05 <1.68 <1.51 <2.39 <1.26 <1.37 Mn-54 <1.11 <1.55 <1.14 <1.31 <1.56 <1.45 Co-60 <1.54 <1.48 <1.89 <2.60 <1.65 <1.11 K-40 31.9i12.2 <22.8 20.6 5.2 22.418.4 14.8 b.9 47.8tS.5 IOtherst <LLD <LLD <LLD <LLD <lLD <LLD
- Sample Locations Required by Technical Specifications.
** Optional Sample Location. Not Required By the Technical Specifications.
t Plant Related Radionuclides.
TABLE 6-9 (Counsuco) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pCi/m' i 1 Sigma
..r .. ~.....# - _.. -
..u.
gMEBR_UARY!g FMARCH{,
;APRILS ~ ~
.[MAY{
i [JUNp g
)NUCLIDESpg,QANpRYi?
E OFF-SITE COMPOSITE ** l l
<4.56 <3.88 <4.45 <3.50 <5.05 l T1Ce-144 <4.42 <1.74
<1.34 <1.23 <1.48 <1.23 i Ce-141 <1.46 61.8 6.7 Be-7 76.9i13.2 83.6*7.0 68.8*6.7 81.li7.5 84.625.8
<3.09 <3.55 <3.99 <2.43 <4.35 ;
Zn-65 <2.46 <0.92 <1.41 1
<0.92 <1.16 <1.25 <2.12 Cs-134 <1.50 <0.83 <1.50 Cs-137 <1.04 <1.10 <1.24
<2.46 <2.07 <3.60 <2.31 <2.78 Zr-95 <1.49 <1.86
<1.51 <1.58 <1.98 <1.07 Nb-95 <1.29 <1.21 <1.63
<1.17 <1.64 <1.56 <1.70 p Co-58 <2.11 <0.82 <1.37 Mn-54 <1.05 <1.40 <1.24 g <2.09 <2.13 <1.60 <1.43 <1.89 Co-60 <0.94 <11.7 42.9 7.0
<15.2 <18.7 <17.5 <16.3 K-40 <LLD <LLD <LLD
<LLD <LLD Otherst <LLD F OFF-SITE COMPOSITE **
<4.51 <3.21 <4.42 <3.69 <4.35 T1Ce-144 <5.20 <1.20 C . 55 Ce-141 <1.65 <1.46 <I.09 <1.49 ]
70.516.5 67.816.4 79.9 6.6 64.3i5.4 55.0 6.5 Be-7 83.0i12.5 <2.75 <3.37
<2.40 <3.53 <2.49 <3.19 Zn-65 <1.43 <0.95 <1.79
<1.10 <1.17 <1.49 Cs-134 <1.33 <1.00 <1.39
<0.83 <1.24 <1.14 Cs-137 <2.44 <2.31 <3.59
<1.99 <2.89 <2.49 Zr-95 <1.46 <1.98 <1.35 <1.95 ;
Nb-95 <1.20 <1.60
<1.53 <1.66 <1.27 <1.64 Co-58 <1.44 <1.39
<0.61 <1.39 <0.96 <1.30 Mn-54 <0.90 <1.73
<1.23 <1.57 <1.38 <1.58 <1.71 Co-60 <1.03 <13.8 51.018.0 31.6*12.0 42.117.91 18.114.7 42.817.7 K-40 <LLD <LLD <LLD
<LLD <LLD Otherst <LLD o* Optional Sample Location. Not Required by the Technical Specifications.
t Plant Related Radionuclides. M M M M M M M M M M M M M M M M M M M
uma sus aus aus uma sus- sum uma seu num uma amm ums - uma ses aus man sus sum TABLE 6-9 (Courzwuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10-'pCi/m' i 1 Sigma
..anw .. e% w. r .... m. .. ~m s % - e ,..e e mc..~ .-mna ?gJANUARYgee,n
$N0CLIDES) q g pem m apap; MFEBRUARYi d " - i.MARCHi . fAPRILE~ f %p m mu mMAYi. Q; M j,JUNEC
. ,&,. ,m . - _.
G OFF-SITE COMPOSITE ** TlCe-144 <5.09 <4.73 <3.43 <4.98 <3.93 <4.76 Ce-141 <1.82 <1.72 <1.19 <1.48 <1.43 <1.82 Be-7 68.5i13.5 66.0i6.6 67.815.4 65.Si8.3 71.6t6.3 76.3i7.0 Zn-65 <2.93 <3.96 <2.90 <4.03 <2.84 <4.29 Cs-134 <0.83 <1.49 <0.83 <2.29 <1.19 <1.89 Cs-137 <1.21 <1.35 <0.86 <1.75 <1.13 <1.40 Zr-95 <2.73 <2.95 <2.36 <3.41 <2.33 <3.27 P Nb-95 <1.92 <2.34 <1.31 <2.57 <1.11 <1.74 M Co-58 <1.19 <1.24 <1.05 <1.90 <1.15 <1.92 Mn-54 <1.16 <1.18 <1.02 <1.85 <1.41 <1.74 Co-60 <1.23 <1.95 <1.44 <3.13 <1.97 <2.05 K-40 30.3i15.8 44.718.3 8.5114.5 <2.35 27.216.1 43.2 7.8 Otherst <LLD <LLD <LLD <LLD <LLD <tLD o* Optional Sample Location. Not Required by the Technical Specifications. t Plant Related Radionuclides.
TABLE 6-9 (canrruuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10~'pCi/m' i 1 Sigma
~
l PRI.LL 5
$NOCfiDEM D ~$hhM0dRN amb ,@ PEN dARW Y Y MARCH.)
w ~-~~ -
. lMAh. [ ~ QUNEs w
.. .c D1 ON-SITE COMPOSITE **
<4.39 <4.31 <5.26 <3.40 <4.28 T1Ce-144 <4.52
<1.50 <1.34 <1.03 <* 64 <1.17 <I.30 Ce-141 l
52.6i5.3 62.116.6 80.918.2 67.6*5.2 66.516.1 Be-7 65.1*11.1 <2.86 <3.00
<2.41 <3.25 <3.27 <4.45 Zn-65 <1.12 <1.40
<0.91 <1.13 <1.46 <1.48 Cs-134 <0.98 <1.45
<0.87 <1.03 <1.38 <1.43 Cs-137 <1.~4 <1.81
<2.30 <2.62 <2.76 <3.54 Zr-95 <2.29 <1.42 <1.33 Hb-95 <1.28 <1.75 <1.91
<1.45 <0.99 <1.72 <1.42 <1.47 cp Co-58 <1.00 <1.27
<0.82 <1.27 <1.07 <1.65 <1.07
!j Mn-54 <1.07 <1.63
<0.74 <1.43 <1.12 <3.11 Co-60 44.926.4 27.2 6.4 K-40 40.4*13.9 32.7*7.0 <14.9 21.119.1
<LLD <LLD <LLD <LLD Otherst <LLD <LLD G ON-SITE COMPOSITE **
<4.10 c3.85 <3.93 <4.47 <3.88 T1Ce-144 <4.82
<1.46 <1.28 <1.12 <1.42 <1.31 Ce-141 <1.65 83.7113.0 83.li6.3 69.016.2 72.416.6 76.9i7.0 66.2i5.8 Be-7 <3.55 <2.65
<2.07 <3.87 <2.85 <3.62 Zn-65 <1.22 <1.32
<1.02 <1.21 <1.34 <1.07 Cs-134 <1.29 <1.22
<0.78 <1.13 <1.61 <1.03 Cs-137 <2.12 <2.89 <2.29 Zr-95 <1.75 <2.29 <2.40
<1.71 <1.41 <1.68 <1.38 <1.70 Nb-95 <1.30 <1.29
<0.97 <1.06 <1.68 <1.18 <1.56 Co-58 <1.26 <1.16 <1.25 Mn-54 <1.25 <1.12 <1.25
<1.50 <1.84 <2.03 <0.32 <1.74 i Co-60 <1.11 37.3i13.9 36.626.4 21.916.2 <15.3 24.415.9 40.8i7.2 K-40 <LLD <LLD <LLD
<LLD i Otherst <LLD <LLD flot Required by Technical Specifications.
~
** Optional Sample Location.
t Plant Related Radionuclides. M M M M M M M M M M M M M M M M M M M i i
uma mas num ame uma sun. aus muu aus ~ aus uma amm aus sum .uns uma sus sum ums TABLE 6-9 (Courinuco) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pCi/m' i 1 Sigma ma_ u .. m e s p , p.< m e.-.9 . m ;......., , r
,_.m w~ < w l
. NUCLID.ES,qpw yqm y nn mgMA,NUARY,6p.
-g & y, FEBRUARY %g, gaa s 3M,,AR,CH y.~ '.
. ?APR ,ILF a.- OMAY
- % ~O@v W
u . ~VJUNE? H ON-SITE COMPOSITE ** TlCe-144 <4.40 <3.90 <5.09 <4.70 <4.91 <4.87 Ce-141 <1.49 <1.32 <1.59 <1.39 <1.59 <1.65 Be-7 62.3*12.0 66.9*5.8 81.7 8.5 .78.216.7 60.7*7.2 57.7i6 2 Zn 65 <2.92 5.66i0.71 <4.46 <2.17 <4.88 <4.52 Cs-134 <0.91 <1.36 <1.95 <1.49 <1.29 <1.73 Cs-137 <0.85 <1.16 <1.56 <1.38 <1.25 <1.47 Zr-95 <1.58 <2.16 <3.48 <2.93 <3.59 <2.70 Nb-95 <1.25 <1.57 <l.99 <2.16 <2.47 <1.82 ' Co-58 <0.72 <1.83 <1.53 <1.49 <2.32 <1.63 7 <1.38 <1.65 <1.34 <1.80 <1.a6 w
- Mn-54 <0.70 Co-60 <0.72 <1.83 <2.67 <1.43 <1.99 <1.81 K-40 32.7t11.2 39.1*7.2 21.717.6 30.416.8 <13.3 43.818.3 Otherst <LLD ,
<LLD <LLD <LLD <LLD <LLD _
I. SITE COMPOSITE ** TlCe-144 <5.93 <5.89 <4.42 <4.55 <3.73 <4.82 Ce-141 <1.86 <1.85 <1.54 <1.53 <1.26 <1.66 i Be-7 67.Sil2.6 59.9+8.2 81.117.6 80.417.2 77.816.0 55.216.0 i Zn-65 <1.91 <3.62 <4.41 <5.31 <2.36 <3.33 Cs-134 <1.15 <1.74 <1.76 <1.63 <1.07 <1.57 Cs-137 <1.29 <1.76 <1.13 <1.20 <1.07 <1.47 Zr-95 <2.47 <3.70 <3.05 <3.05 <1.87 <2.59 Nb-95 <1.12 <2.80 <1.65 <2.25 <1.55 <1.76 Co-58 <1.50 <2.27 <1.79 <1.80 <1.28 <1.09 Mn-54 <1.06 <1.68 <1.78 <1.44 <1.04 <1.51 Co-60 <0.98 <3.36 <0.35 <1.79 <1.04 <1.80 K-40 22.0112.8 <20.5 <24.0 27.817.9 32.4i6.0 31.417.4 Otherst <LLD <LLD <LLD <LLD <LLD <LLD c* Optional Sample Location. Not Required by Technical Specifications. t Plant Related Radionuclides.
TABLE 6-9 (Centruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES 1991 Results in Units of 10-3pCi/m' i 1 Sigma
,_YN' i
^
*'s,,,,,_,%
- ' y $- ' - ^!,
, ' % -)-k_,. k**.,
f - , . - ,u# _,- ,. , M ,$.- 5 ._.. ' i- .. .a, E _, - f g[ p ,; ,u s NUCLIDESfs ' s'iMANU A.".RY. "ap ;,my i: F' ' E B' RU'A'mm.O RE' i-s' MA. 'RCH. <N .j ~ d' .y1 RI..eLP' iAP's SH"'. SAYE ~ . 7JUNEt m j.g - - y . . y-J ON-SITE COMPOSITE **
<3.70 <3.81 <4.89 <4.88 T1Ce-144 <5.62 <4.47 Ce-141 < 1.68 <1.17 <1.37 <1.37 <1.51 <1.52 Be-7 61.9*14.5 73.7*6.4 77.416.9 89.717.0 51.4*6.5 69.017.3 Zn-65 <3 09 . <1.85 <3.98 <4.16 < 3.66 <4.38 Cs-134 <1.07 <1.12 <1.41 <1.18 <1.24' <1.65 Cs-137 <1.48 <1.02 <1.06 <1.09 <1.63 <1.60 Zr-95 <2.84 <1.85 <2.74 <3.11 <2.65 < 3.11 Nb-95 <1.91 <1.44 <1.87 <1.78 <1.40 <1.79 m Co-58 <1.33 <1.22 <1.50 <1.42 <1.46 <1.53 Mn-54 <1.02 <1.48 <1.11 <1.69 < 1.53 <1.22 Co-60 <1.28 <1.38 <1.24 <1.01 <2.37 <1.51 K-40 25.1*14.3 <12.0 38.716.6 16.216.1 < 22.1 24.6*7.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD K ON-SITE COMPOSITE **
T1Ce-144 <4.34 <4.99 (4.09 <4.81 <3.39 <4.79 Ce-141 <1.55 <1.53 <1.33 <1.85 <1.11 <1.69 Be-7 71.6i11.5 67.4*7.6 79.1 6.9 86.617.9 65.625.4 63.817.0 Zn-65 <2.27 <5.09 <3.21 <6.51 <2.02 <4.26 Cs-134 <0.92 <1.74 <1.28 <2.29 <0.90 <1.62 Cs-137 <0.97 <1.68 <1.06 <1.81 <0.96 <2.03 Zr-95 <2.03 <3.15 <2.59 <3.97 < 2.14 <2.93 Nb-95 <1.08 <2.41 <2.02 <2.10 <1.07 <2.10 Co-58 <1.03 <1.76 <1.52 <1.99 <1.25 <1.98
<0.90 <1.81 <1.58 <1.93 < 0.75 <0.72 Mn-54 Co-60 <1.03 <2.35 <2.55 <2.77 < 1.40 <2.03 K-40 36.8t12.5 41.9i9.3 22.315.7 <26.3 10.9 4.2 34.5 8.2 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional $ ample Location. Not Required by Technical Specifications.
t Plant Related Radionuclides. I eel M M M M M M M M EMB M M Esis M M M M m m
uma see sua sus aus uns - sum uma sus -een sus em uma sus sus aus sua sus amm-TABLE 6-9 (Courinuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results .in Units of 10pCi/m' i 1 Sigma
. .. : m .g my , ypuem ; um,, .x .s. ;
- - ...-a
, - z nn m p~ w JNUCl!IDESg g g g U,LY g?,ygAUGUSThgjERTEMBERf' gj0CTOBER] ,QNOVEMB_ER[gDECEMBER{
R1 0FF-SITE COMPOSITE
- TlCe-144 <4.11 <3.42 <5.05 <3.84 <6.50 <5.14 Ce-141 <1.33 <1.23 <1.64 <1.18 <1.80 <1.52 Be-7 78.li6.8 54.215.4 50.416.8 69.li6.0 49.017.6 62.1 6.4 Zn-65 <2.81 <3.29 <6.64 <3.75 <5.51 <3.23 Cs-134 <1.44 <1.23 <1.38 <2.00 <2.10 <1.48 Cs-l'd ' <1.41 <1.32 <1.97 <1.06 <2.09 <1.31 Zr-95 <3.16 <2.32 <2.46 <2.37 <4.09 <3.21 Nb-95 <1.66 <1.80 <2.12 <1.89 <2.18 <2.23 p Co-58 <1.58 <1.14 <1.93 <1.26 <2.32 <1.30 g Mn-54 <1.64 <1.03 <1.44 <1.07 <1.91 <1.76 Co-60 <2.17 <1.42 <2.87 <1.63 <3.61 <2.49 K-40 34.718.8 18.014.7 35.919.2 29.816.9 15.218.0' 23.8 7.5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD R2 0FF-SITE COMPOSITE
- TlCe-144 <4.80 <4.47 <5.53 <3.87 <5.65 <5.46 Ce-141 <1.29 <1.68 <1.48 <1.38 <2.12 <1.82 Be-7 75.5i7.2 72.3i7.2 60.216.6 77.316.0 48.6t7.8 51.8 7.2 Zn-65 <4.06 <4.16 <4.30 <3.71 <7.82 <4.37 Cs-134 <1.69 <1.22 <1.53 <1.79 <2.13 <1.68 Cs-137 <1.18 <1.50 <1.29 <1.36 <2.18 <1.50 Zr-95 <2.65 <2.13 <2.64 <1.79 <4.12 <3.79 Nb-95 <1.22 <2.23 <1.63 <1.70 <2.66 <2.22 Co-58 <1.89 <1.47 <1.15 '1.45 <2.53 <2.12 Mn-54 <1.27 <1.S1 <1.61 <1.42 <2.10 <2.10 Co-60 <1.96 <2.11 <1.96 <1.99 <2.64 <3.83 K-40 15.7i7.6 14.316.6 <16.1 37.716.4 36.719.6 29.8i9.0 Otherst <LLD <LLD <LLD <LLD <LLD <LLD o Sample Locations Required by Technical Specifications.
't Plant Related Radionuclides.
TABLE 6-9 (Centruuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES 0F JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991' Results in Units of 10'3pCi/m' i 1 Sigma
.-xn a . war , -se mx v x . .? - mn : , > A ;n J.NUCLIDESi n j ggx n;m My mbYA;*p,U gwn,*m% t.A,U,; GUSTS
. - ;;c qA.MSEPTEMBERN w40CT08ERE ,n ~ ' F~MNO,VEM iDECEM mmn,B,ER U R3 0FF-SITE COMPOSITE
- TlCe-144 <4.67 <4.32 <6.01 <3.80 <6.05 "4.35 Ce-141 <1.37 <1.60 <1.77 <1.18 <1.75 <1.35 Be-7 81.6*6.6 47.016.4 43.li6.8 70.015.9 51.216.8 46.015.5 Zn-65 <3.79 <2.53 <5.27 <2.50 <6.57 <3.50 Cs-134 <1.33 <1.19 <1.65 <0.84 <2.43 <1.46 Cs-137 <1.19 <1.30 <1.51 <0.97 <1.78 <1.48 Zr-95 <2.20 <2.75 <3.05 <1.76 <3.87 <2.44 Nb-95 <2.03 <2.03 <2.09 <1.24 <2.60 <1.87
. Co-58 <1.59 <2.37 <2.64 <1.47 <2.36 <1.43 e ~
Mn-54 <1.33 <1.45 <2.26 <1.25 <1.54 <1.43 Co-60 <1.94 <2.34 <1.49 <1.18 <2.84 <2.03 K-40 <2.70 24.2 6.2 41.9i8.70 <12.0 <20.0 29.726.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD R4 0FF-SITE COMPOSITE
- T1Ce-144 <4.42 <3.53 <4.96 <4.06 <6.47 <5.10 Ce-141 <1.23 <1.33 <2.23 <1.46 . <1.98 <1.72 Be-7 102i7.5 63.315.4 63.6*7.6 81.516.8 50.818.4 63.716.9 Zn-65 <3.14 <2.77 <5.16 <3.17 <7.55 <4.69 Cs-134 <1.31 <1.17 <1.62 <1.09 <2.86 <1.78 Cs '.37 <1.08 <0.84 <1.53 <1.36 <2.32 <1.65 Zr-95 <3.00 <2.09 <3.15 <2.72 <3.43 <2.92 Nb-95 <1.82 <1.10 <2.40 <1.80 <2.51 <2.42 '
Co-58 <1.53 <1.33 <1.88 <1.32 <1.53 <1.52 Mn-54 <0.99 <1.07 <1.32 <1.30 <2.17 <1.84 Co-60 <2.01 <1.43 <1.49 <1.73 <2.32 <1.32 K-40 <15.3 27.5i5.4 42.918.33 <15.9 23.4 10.4 14.617.5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
t Plant Related Radionuclides. sus m m m m m m me e e m m m m Eau m m m e
uns ame mas sus esa sus uma mas sus man ums uma aume ama aus uma sus aus aus-TABLE 6-9 (C:nnuur.o)
-CONCENTRA1:0NS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pCi/m' i 1 Sigma
?NUCLIr[E w-k;
.sM #h k,JUL c N. $ b [ADOUSTP n
~a. _ x[S5PT,EMBkR
.~n
[ ' LO N0BE,Ri , c , k, NOVE,l$IhI^ ikMEMBdRi^
- ~
R5 0FF-SITE COMPOSITE (CONTROL)* TiCe-144 <4.41 <3.58 <5.28 <3.53 <4.05 <4.59 Ce-141 <1.33 <1.34 <1.63 <1.26 <1.28 <1.48 Be-7 68.816.7 46.li5.2- 51.6t7.3 63.3i5.6 41.5*5.0 56.916.0 Zn-65 <3.24 <3.67 <3.35 <3.64 <4.14 <4.12 Cs-134 <1.65 <1.05 <1.51 <2.07 <1.22 <1.59 Cs-137 <1.31 <0.83 <1.69 <0.96 <1.18 <1.32 Zr-95 <2.33 <2.41 <3.68 <2.31 <2.34 <2.91 Nb-95 <1.90 <1.85 <2.20 <1.49 <1.78 <1.99 Co-58 <1.59 <1.48 <1.82 <1.04 <1.28 <1.86
? Mn-54 <1.31 <0.94 <1.73 <1.15 <1.07 <1.29 O Co-60 <3. 11 <1.54 <2.18 <1.55 <1.48 <1.70 K-40 18.816.4 12.1*3.5 24.2i8.4 26.025.7 31.717.2 34.117.2 Otherst <LLD <LLD <LLD <LLD <LLD <LLD D2 0FF-SITE COMPOSITE **
T1Ce-144 <4.56 <4.29 <4.~9 <3.37 <3.94 <4.51 Ce-141 <1.72 <1.62 <1.23 <1.10 <1.42 <1.53 Be-7 86.3i7.6 59.426.9 46.7*6.1 61.615.3 51.915.4 55.016.1 Zn-65 <3.79 <4.01 <3.64 <2.78 <3.49 <4.37 Cs-134 <1.30 <1.61 <1.50 <1.12 <1.35 <1.66 Cs-137 <1.26 <1.39 <1.33 <0.85 <1.31 <1.42 Zr-95 <2.68 <2.61 <1.79 <2.08 <2.14 <3.21 Nb-95 <1.73 <1.36 <1.53 <1.30 <1.57 <1.85 Co-58 <1.63 <1.29 <1.93 <0.92 <1.25 <1.63 Mn-54 <1.41 <1.69 <1.33 <0.89 <1.37 <1.37 Co-60 <1.80 <2.17 <2.15 <1.14 <1.14 <1.69 K-40 <18.3 <16.7 <16.2 30.3*5.6 10.6*4.8 21.8i6.1 Otherst <LLD <LLD <'LD
. <LLD <LLD <LLD
- Sample Locations Required by Technical Specifications.
** Optional Sample Location. _N_qi Required By the Technical Specifications.
t Plant Related Radionuclides.
TABLE 6-9 (Courzuuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES j OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 t Results in Units of 10-'pCi/m' i 1 Sigma
.,.# ,,0
?
- k. . f k, { NW.7' ., - f/s 'b ,_ ?:;f 0 - - -
, ,, + >_ ff A _a., ,
. . _ , . , , , , _ _ , _ ~ M _b 7 OCTOBER) [ NOVEMBER 5 . iDECEMB_ERi iNUCLIDES$ 9 ny% 30L Q y g' s .JAUGUST! iSEPTEMBER5
~. ,. ,
E OFF-SITE COMPOSITE **
<3.60 <4.20 <3.06 <4.28 <4.35 T1Ce-144 <4.53 <1.46
<1.31 <1.37 <0.94 <1.35 Ce-141 <1.53 54.8i6.4 40.7t5.2 62.0i5.8 81.Si6.0 42.2i5.8 57.226.3 l Be-7 <3.40 <3.68 !
j
<2.96 <2.61 <3.95 <2.86 Zn-65 <0.98 <1.38 <1.50 :
Cs-134 <1.46 <1.18 <1.83
<1.20 <1.31 <0.99 <1.51 <1.21 Cs-137 <1.16 <3.37
<2.83 <1.95 <1.88 <2.11 Zr-95 <2.47 <2.19
<1.78 <1.50 <1.19 <1.70 Nb-95 <1.97 <1.24 <1.86
<1.45 <1.40 <1.64 <1.20 9 Co-58 <0.96 <1.40 <1.48
<1.38 <1.10 <1.16 g Mn-54
<1.80 <1.94 <1.72 <2.05 <2.34 Co-60 <1.70 <17.6 l
25.025.9 <14.7 <11.5 16.016.0 K-40 37.716.7 <LLD <LLD
<LLD <LLD <LLD Otherst <LLD F 0FF-SITE CONF 0 SITE **
<3.28 <5.38 <3.84 <5.72 <6.09 T1Ce-144 <4.48 <2.04
<1.18 <1.81 <1.32 <1.79 Ce-141 <1.52 47.717.4 79.9t6.9 46.614.8 35.216.0 63.2*59.2 49.4i7.0 Be-7 <3.19 <5.29 <4.45 Zn-65 <3.49 <2.79 <3.92
<1.04 <1.39 <1.19 <2.24 <1.52 l Cs-134 <1.63 <1.91
<0.96 <1.76 <1.20 <1.71 Cs-137 <1.45 <5.34
<2.43 <3.69 <1.82 <3.57 Zr-95 <3.15 <2.59 <2.75
<1.74 <1.67 <1.85 <1.82 Nb-95 <1.15 <2.36 <2.72
<1.47 <1.38 <2.18 Co-58 <1.46 <1.98 <1.84
<1.51 <0.97 <1.72 Mn-54 <2 39 <1.94 <4.08
<1.44 <1.27 <1.93 .
Co-60 18.715.6 24.6i8.21 35.4 9.6 K-40 27.4*7.5 33.2 6.2 29.428.3
<LLD <LLD <LLD <LLD Otherst <LLD <LLD
** Optional Sample Location. Not Required by the Technical $pecifications.
t Plant Related Radionuclides. M M M M M M M M M M M EM M WEB M W" M M M
aus uma ame mas 1 aus sus - aus aus sus ' uma sus 'aus sua sus aus sum aus ama mas TABLE 6-9 (Courinuco) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results-in Units of 10~3pCi/m' i 1 Sigma w.a-mg ww - a .x wwwm w , . . , .. n .yan wn w . ., -
.w g ~
ng w (NUCIjIDE5$1.P!a g ULY g > ,,G w gfx?m;p ~,we w eemwAUGUSM _. i g.dSEPTEMBER c .x ,f;d +.s0,C _ga ne ,TOBER 9 w m,R 4 "9NOV l G OFF-SITE COMPOSITE ** TlCe-144 <4.71 <3.62 <4.98 <4.48 <4.36 <4.48 Ce-141 <1.68 <1.39 <1.54 <1.67 <1.55 <1.28 ,J Be-7 72.4*6.9 51.5*5.2 38.3i5.8 64.li6.9 39.2i5.5 35.6*5.4 " Zn-65 <3.29 <3.45 <5.30 <3.54 <4.83 <4.36 i Cs-134 <1.50 <1.10 <1.55 <1.16 <1.50 <1.85 i Cs-137 <1.38 <1.00 <1.70 <1.47 <1.42 <1.34 Zr-95 <2.50 <2.84 <3.06 <3.09 <2.20 < 75 Nb-95 <1.86 <1.87 <2.43 <1.93 <1.65 <1.83 Co-58 <1.84 <1.39 <2.25 <1.35 <1.40 - <1.81
- Mn-54 <1.29 <0.95 <1.92 <1.16 <1.24 <1.67 .
Co-60 <1.90 <1.26 <1.80 <2.07 <1.52 <1.30 K-40 33.3i8.1 29.7*7.1 <19.9 24.2i7.2 44.017.1 48.917.5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD ; o* Optional Sample Locatica. Not Required by the Technical Specificat*ons. t Plant Related Radionuclides. ; l l r
TABLE 6-9 -(Ccmuuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pci/m' i 1 Sigma wv. - m g n. . c .. . . ..
.a, ~
.iNUCLIDES ~g D a,y.g. L,Y agM B , - 's pw w AUGU v w ,W ,JSEPTEM
,STJ ,: y ,BERF p; M,i1.0CTOBER ,N J,JNOVEMB_ER? % dDECE 3 , .
~
D1 ON-SITE COMPOSITE ** T1Ce-144 <4.87 <3.91 <4.68 <3.87 <4.16 <4.83 Ce-141 <1.60 <1.50 <1.54 <1.33 <1.60 <1.67 Be-7 80.917.6 45.016.3 38.715.8 68.3i5.3 49.016.4 63.626.7 Zn-65 <3.78 <4.74 <4.38 <3.17 <4.10 <4.61 Cs-134 <1.44 <1.23 <1.55 <1.40 <1.31 <1.70 Cs-137 <1.58 <1.41 <1.29 <0.96 <1.33 <1.33 Zr-95 <2.85 <2.31 <2.76 <2.35 <2.74 <2.25 Nb-95 <1.42 <1.65 <1.83 <1.15 <1.46 <1.96 7 Co-58 <1.54- <1.45 <1.52 <1.37 <1.15 <1.61 w Mn-54 <1.32 <1.54 <1.33 <1.17 <1.32 <1.28 Co-60 <1.93 <1.99 <1.93 <1.44 <1.95 <2.12 K-40 32.9*7.2 16.li6.2 50.4i8.6 31.015.8 8.6i5.2 23.028.2 Otherst <LLD <LLD <LLD <LLD <LLD <LLD G ON-SITE COMPOSITE ** TlCe-144 <4.16 <3.23 <5.12 <4.71 <4.21 <4.32 Ce-141 <1.27 <1.28 <1.58 <1.55 <1.41 < 1. 3 5. Be-7 97.6t7.2 63.415.3 48.3*6.0 67.5*7.3 54.2i6.0 60.516.2 Zn-65 <4.38 <2.61 <3.61 <3.81 <4.10 <3.59 Cs-134 <1.40 <1.04 <1.32 <1.44 <1.71 <1.30 Cs-137 <1.19 <0.86 <1.22 <1.43 <1.20 <0.92 Zr-95 <2.63 <2.31 <3.30 <2.85 <2.66 <2.45 Nb-95 <1.51 <1.45 <2.13 <1.48 <1.77 <1.74 Co-58 <1.18 <1.23 <1.50 <1.68 <1.51 <1.43 Mn-54 <1.12 <1.15 <1.42 <1.61 <1.32 <1.39 Co-60 <1.74 <1.25 <1.38 <2.08 <1.51 <1.88 K-40 <16.1 28.li5.5 <14.0 17.926.9 44.0i7.5 <13.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD
** Optional Sample Location. Not Required by the Technical Specifications.
t Plant Related Radionuclides. Em m m M M M M M M M M M M M M M M M m
sus aus aus uma sus ame uma mas sus aus som nas ass mas ses sua sus aus aus TABLE 6-9 (Courinuso) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10pCi/m' i 1 Sigma n s . . wm x+ , , - .~ x :
.. xy- wr u em , w.w g m - ..
B _10CTO.ER:: i iNOVEMBERb 3DECEMBERj ANOCLIDESWggjyULYX * ._ -2AUGUSTb y sSEPTEMBERf m _ H OH-SITE COMPOSITE **
<4.07 <4.91 <4.58 <6.37 T1Ce-144 <4.95 <3.86 <2.14
<1.39- <1.29 <1.47 <1.48 Ce-141 <1.74 42.5i5.4 29.917.1 75.016.6' 51.826.0 33.2*4.6 71.0 6.9 Be-7 <3.94 <3.50 <3.89
<4.47 <3.07 <3.51 Zn-65 <3.22 <1.39 <1.68
<1.85 <1.29 <1.36 Cs-134 <1.33 <1.13 <1.59
<1.32 <0.95 <1.07 Cs-137 <3.11 <2.25 <2.97
<2.83 <2.50 <2.21 Zr-95 <1.52 <2.19 <1.83 <2.36 ,
Nb-95 <1.71 <2.05 <2.44
<1.46 <1.25 <1.82 <1.72 l p Co-58 <1.49 <1.26 <1.81
<1.63 <1.26 <1.36 <1.21 g Mn-54
<1.25 <1.56 <1.84 <1.57 <3.13 Co-60 <0.89 10.8 4.3~ 28.9t7.9 26.7 6.7 37.226.4 <17.2 K-40 42.8f7.6 <LLD <LLD <LLD
<LLD <LLD Otherst <LLD I ON-SITE COMPOSITE **
<5.16 <5.21 <5.02 <4.62 TlCe-144 <4.60 3.28 <1.42
<1.17 <1.57 <1.71 <1.75 Ce-141 <1.41 28.926.3 54.016.1 60.915.9 53.814.8 42.016.7 66.817.0 Be-7
<5.79 <7.30 <4.98 <3./5 Zn-65 <3.14 <2.64 <1.45
<0.99 <1.90 <2.23 <1.35 Cs-134 <1.35 <1.53 <1.31
<0.98 <1.52 <1.65 Cs-137 <1.44 < . 79 <2.87
<2.37
<2.84 <2.23 <3.18 Zr-95 <2.32 <1.83 <7. 11 <1.76 Nb-95 <1.90 <1.57 <1.40 l
<1.15 <1.77 <0.97 <1.80 I Co-58 <1.95 <1.63 <1.14
<1.46 <0.96 <1.83 <1.77 Mn-54 <2.61 <2.74 <1.61
<1.65 <1.44 <2.64 Co-60 <18.4 24.3*7.6 27.018.5 51.817.8 p K-40 26.8 6.7 34.li5.8 <LLD <LLD jj
'LLD <LLD <LLD Otherst <LLD
- Optional Sample Location.' Not Required by the Technical $pecifications.
t Plant Related Radionuclides.
TABLE 6-9 (Ceurzuuto) CONCENTRATIONS OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF JAF/NMP SITE AIR PARTICULATE SAMPLES - 1991 Results in Units of 10'3pCi/m' i 1 Sigma
~,~~~ .u .. wm . - - . v .- .
u.- ... - + 4NUCLIDESi*
~
, w '~~# fJUlf ww wm awcpM M MyAUGU
- - nno S,Ts, iSEPTEMB.ER?'
- y- ,
- - s0CTOBE.R s- ~ m V >ON
' , wn~OVEMBER5 wm - ..
9 :DECnNEU J ON-SITE COMPOSITE ** a s TlCe-144 <4.69 <3.72 <6.03 <3.95 <4.81 <4.63 i Ce-141 <1.36 <1.35 <2.05 <1.35 <1.51 <1.62 h' Be-7 63.816.4 51.9*5.4 59.2t7.3 56.7*6.0 44.015.5 39.0i6.0 Zn-65 <4.83 <2.72 <3.34 <5.30 <4.61 <3.27 Cs-134 <1.31 <1.16 <1.51 <2.34 <1.94 <1.76 Cs-137 <0.87 <1.08 <1.32 <1.27 <1.39 <1.49 Zr-95 <2.58 <2-.29 <3.78 <2.98 <2.92 <3.13 Nb-95 <1.81 <1.64 <2.32 <1.76 <1.72 <1.69 cp Co-58 <1.63 <1.34 <2.43 <1.60 <1.56 <1.32
'd Mn-54 <1.58 <1.03 <1.92 <1.19 <1.45 <1.72 Co-60 <1.01 <1.58 <2.17 <1.25 <1.74 <2.12 K-40 <19.4 31.3i5.9 15.0i9.2 23.317.5 37.6i7.1 36.8i8.1 Otherst <LLD <LLD <LLD <LLD <LLD <LLD K ON-SITE COMPOSITE **
TlCe-144 <3.80 <3.55 <4.77 <4.64 <5.05 <5.06 Ce-141 <1.31 <1.34 <1.44 <1.60 <1.61 <1.75 I Be-7 52.7*6.1 26.724.2 42.616.0 76.717.0 34.416.2 59.5i7.4 I Zn-65 <4.08 <3.17 <3.57 <6.46 <4.07 <5.40 Cs-134 <1.25 <1.06 <1.50 <1.91 <1.42 <1.43 Cs-137 <1.17 <1.09 <1.47 <1.50 <1.35 <1.53 Zr-95 <2.51 <2.46 <2.82 <3.15 <3.88 <3.17 Nb-95 <1.67 <1.35 <1.72 <1.71 <2.67 <2.18 Co-58 <1.64 <1.24 <1.81 <1.97 <2.21 <1.65 Mn-54 <0.98 <1.22 <1.32 <1.51 <1.53 <1.38 Co-60 <1.59 <1.09 <2.46 <2.30 <2.87 <2.74 K-40 45.2t7.2 18.6*4.8 22.615.3 19.116.6 <29.5 57.5t10.7 Otherst <LLD <LLD <LLD <LLO <LLD <LLD
** Optional Sample Location. Not Required by the Technical $pecifications.
t Plant Related Radionuclides. IE M M M M M M M M M M M M M M M m m
m m M M M M sum M M M M M m m M M M sus e TABLE 6-10 DIRECT RADIATION MEASUREMENT RESULTS (1991) Results in Units of mrem /std. Month i 1 Sigma FIRST SECOND THIRD FOURTH STATION LOCATION. (DIS ANCE AND QUARTER QUARTER QUARTER QUARTER DIRECTION)** NUMPER 10.910.9 5.7i0.7 7.510.9 11.610.8 0.2 miles @ 69*
; D1 On-site 5.110.8 4.710.6 0.4 miles 0 140' 4 D2 On-site 6.li0.5 5.110.5 5.5i0.3 4.710.5 6.011.5 4.210.5 0.4 miles 0 175*
5 E On-site 4.8 0.8 5.210.4 0.5 miles 0 210' 6 F On-site 5.1x0.7 4.0 0.5 5.710.5 3.2i0.2 4.2i0.5 4.010.4 0.7 miles 0 250' 7* G On-site 4.710.5 4.610.3 16.4 miles 0 42* 8 R-5 Off-site Control 5.810.3 4.010.3 5.410.3 3.610.3 4.5t2.9 4.810.4 11.4 miles 0 80* 9 D1 Off-Site 4.610.4 3.610.2 9.0 miles 0 117* 10 D2 Off-site 5.6i0.2 3.6i0.3 5.010.2 3.7 0.4 4.4i0.3 4.010.3 7.2 miles 0 160* 11 E Off-site 3.410.3 4.810.8 3.810.4 7.7 miles 0 190* 12 F Off-site 4.110.2 5.510.4 5.410.5 4.510.8 4.510.2 5.3 miles 0 225* P 13 G Off-site 4.810.6 5.310.4 4.6 0.2 12.6 miles 0 226* E 14* DeMass Rd., SW Oswego-Control 5.210.2 Pole 66, W. Boundary-Bible Camp 5.010.5 2.9 0.3 4.410.6 4.410.2 .0.9 miles 0 237* 15* 5.410.3 4.8i0.4 0.4 miles 0 265* l 18* Energy Info. Center-Lamp Post, SW 5.910.2 4.610.5 East Boundary-JAF, Pole 9 5.210.2 4.8i0.6 5.310.4 4.6i0.2 1.3 miles 0 81* 19 5.4i0.4 5.310.7 5.6i0.4 5.420.5 0.8 miles 0 70* 23* H On-site 5.410.6 0.8 miles 0 98* 5.7i0.5 3.410.4 4.510.7 24 I On-site 4.1 0.6 5.211.5 4.0i0.4 0.9 miles 0 110' 25 J On-site 5.610.3 5.010.2 4.510.9 5.3tl.2 3.9i0.4 0.5 miles 0 132* 26 K On-site 11.711.5 15.0i2.4 0.4 miles 0 60* 27 N. Fence, N. of Switchyard, JAF 15.113.0 3.811.3 N. Light Pole, N. of Screenhouse, 19.9i4.7 18.li2.7 22.813.4 31.4*6.4 0.5 miles 0 68* 28 JAF 0.5 miles 0 65* N. Fence, N. of W. Side 9.014.5 15.0i2.2 16.813.6 22.6i5.0 29 9.6 1.0 12.612.3 0.4 miles 0 57* 30 N. Fence (NW) JAF 12.5tl.6 8.010.7 7.6*0.8 6.310.9 7.010.9 8.812.0 0.2 miles 0 276* 31 N. Fence (NW) NMP-1 12.411.5 15.912.3 0.2 miles 6 292* N. Fence, Rad. Waste-NMP-1 13.7i2.4 1C.4+1.6 39 N. Fence, (NE) JAF 8.0 1.1 5.210.6 6.2i0.8 7.511.5 0.6 miles 0 69* 47 3.810.5 4.2 0.4 19.8 miles 0 170* 49* Phoenix, NY-Control 4.910.2 4.1 1.1 Liberty & Bronson Sts., E of OSS 4.2 0.3 4.110.3 5.010.4 5.0i0.7 7.4 miles 0 170* 51 4.310.6 4.8 0.4 5.8 miles 0 227* 52 East 12th & Cayuga Sts., Oswego 5.910.2 3.8*0.2 School
TABLE 6-10 (CCNTINUED) DIRECT RADIATION MEASUREMENT RESULTS (1991) Results in Units of mrem /std. Month i 1 Sigma STATION FIRST. .SECOND THIRD ' FOURTH
^
LOCATION (DI AND NUMBER QUARTER. . QUARTER QUARTER QUARTER DIRECTION)** 53 Broadwell & Chestnut Sts. - 5.6i0.3 4.610.7 5.210.5 4.810.4 13.7 miles 0 183* Fulton H.S. 5A Liberty St. & Co. Rt.16 - 5.9i0.5 4.010.3 4.0i0.5 4.6i0.3 9.3 miles 0 115* Mexico H.S. 55 Gas Substation Co. Rt. 5-Pulaski 5.7i0.5 4.4*0.4 4.6i0.4 4.210.4 13.0 miles 0 75* 56* Rt. 104-Hew Haven SCH.(SE Corner) 5.6i0.4 3.810.2 4.510.6 4.4i0.2 5.3 miles 0 123' 58* Co. Rt. 1A-Alcan (E. of Entrance 6.310.3 3.810.2 4.9*0.7 4.410.4 3.1 miles 0 220' Rd.) 75* Unit 2, N. Fence, N. of Reactor 7.010.7 5.410.7 5.810.5 6.6i1.0 0.1 miles 0 5* Bldg.
$ 76* Unit 2, N. Fence, N. of Change 6.9*0.4 5.210.4 5.610.6 5.2 0.4 0.1 miles 0 25*
- House 77* Unit 2, N. Fence, N. of Pipe 7.2*0.8 5.020.3 6.3i0.5 6.910.9 9.2 miles 0 45*
Bldg. 78* JAF, E. of E. Old Lay Down Area 6.510.4 4.3i0.3 6.3i0.5 4.810.4 1.0 miles 0 90* 79* Co. Rt. 29, Pole #63, 0.2 mi. S. 6.1*0.5 3.6i0.2 5.210.2 4.6i0.7 1.1 miles 0 115* of Lake Rd. 80* Co. Rt. 29, Pole #54, 0.7 mi. S. 5.810.2 3.810.4 4.810.8 4.810.4 1.4 miles 0 133* of Lake Rd. 81* Miner Rd.,. Pole #16, 0.5 mi. W 5.4i0.2 4.011.4 4.810.4 4.710.4 1.6 miles 0 159' of Rt. 29 82* Miner Rd., Pole #1 1/2, 1.1 mi. 6.010.1 3.6i0.3 5.010.7 4.5i0.2 1.6 miles 0 181* W. of Rt. 29 83* Lakview Rd., Tree 0.45 mi. N. of 5.7*0.2 4.210.3 4.510.5 4.4i0.4 1.2 miles 0 200* Miner Rd. 84* Lakeview Rd., N., Pole #6117, 5.1 0.2 4.210.3 5.010.6 4.210.4 1.1 miles 0 E25* 200 ft. N. of Lake Rd. 85* Unit 1, N. Fence, N. of W. Side 14.5 1.6 9.8*1.8 11.011.4 13.4il.9 0.2 miles 0 294* of Screen House i 86* Unit 2, N. Fence, N. of W. Side 7.4*0.8 6.0*0.8 8.410.9 16.712.5 0.1 miles 0 315* of Screen House GM M M M M M M m m m m m m m m m m m m
suas uma sus sus sus sus sua sus aus uma sus num sua sua sus amm suas. aus aus TABLE 6-10 (CONTINUED) DIRECT RADIATION MEASUREMENT RESULTS (1991) Results in Units of mrem /std. Month i 1 Sigma STAT 10NL FIRST SECOND THIRD FOURTH' NUMBER LOCATION: (DI ANCE AND QUARTER . QUARTER ' QUARTER ' QUARTER DIRECTION)** 87* Unit 2, N. Fence, N. of E. Side 7.9i0./ 6.2*1.0 6.0i0.7 8.0il.7 0.1 miles 0 341* of Screen House 88* Hickory Grove Rd., Pole #2. 0.6 5.610.3 4.5i0.4 4.110.2 4.6i0.5 4.5 miles 0 97* mi. N. of Rt. 1 89* Leavitt Rd., Pole #16, 0.4 mi. S. 5.210.4 4.210.4 5.5i0.5 4.420.3 4.1 miles 0 111' of Rt. 1 90* Rt. 104, Pole #300, 150 Ft. E. 5.f,10.6 4.310.4 5.010.4 5.210.6 4.2 miles 0 135* of Keefe Rd. 91* Rt. 51A, Pole #59, 0.8 mi. W. 5.210.2 3.6 0.3 4.210.3 3.6i0.3 4.8 miles 0 156* of Rt. 51 T 92* Maiden Lane Rd., Power Pole, 0.6 5.810.4 4.9 0.4 5.610.8 5.410.4 4.4 miles 0 183* o mi. S. of Rt. 104 93* Rt. 53, Pole 1-1, 120 ft. S. 5.310.3 4.010.6 5.010.5 4.410.5 4.4 miles 0 205* of Rt. 104 94* Rt. 1, Pole #82, 250 ft. E. of 5.510.2 4.110.3 4.410.5 4.510.2 4.7 miles 0 233* Kocher Rd. (Co. Rt. #63) 95* Lakeshore Camp Site, froni Alcan 5.110.3 3.810.2 4.5 0.7 3.810.2 4.1 miles 0 237* W. access Rd. Pole #21, 1.2 mi. N. of'Rt. 1 96* Creamery Rd., 0.3 mi. S. of 5.6i0.8 4.010.2 4.0i0.4 4.2*0.5 3.6 miles 0 199* Middle Rd. Pole 1 1/2 97* Rt. 29, Pole #50, 200 ft. N. of 6.310.5 3.810.2 5.210.9 4.210.4 1.8 miles 0 143* ' Miner Rd. 98* Lake Rd., Pole #145, 0.15 mi. 5.910.9 4.210.2 5.010.3 4.4*0.4 1.2 miles 0 101* of of Rt. 29 99 NMP Rd., 0.; mi. N. of Lake Rd., 6.1 0.4 4.010.2 5.4i0.3 4.4 0.5 1.8 miles @ 88* Env. Station R1 Off-site 100 Rt. 29 and Lake Rd., Env. Station 5.7t0.3 3.810.2 4.611.4 4.420.2 1.1 miles 0 104* R2 Off-site 101 Rt. 29, 0.7 mi. S. of Lake Rd., 6.210.7 3.810.2 4.7*0.6 4.0i0.2 1.5 miles 0 132* Env. Station R3
TABLE 6-10 (CONTINUED) DIRECT RADIATION MEASUREMENT RESULTS (1991) Results in Units of mrem /std. Month i 1 Sigma FIRST. -SECOND_ THIRD FOURTH STATION LOCATION (DIS ANCE AND
' QUARTER- QUARTER QUARTER QUARTER- DIRECTION)**
NUMBER. l 102 EOF /Env. Lab, Oswego Co. Airport 5.910.4 4.811.0 5.210.3 4.2i0.2 11.9 miles 0 175* (Fulton airport, Rt. 176) 0.4 miles 0 267* EIC, East Garage Rd., Lamp Post 6.0i0.3 4.210.2 5.5i0.7 4.410.2 103 R3 Off-site 4.010.3 1.4 miles 0 102* 104 Parkhurst Road, Pole #148 1/2-A, 5.510.2 5.2i0.6 5.2*0.9 0.1 miles South of Lake Rd. 5.011.1 4.210.2 1.4 miles 0 198* l 105 Lakeview Rd., Pole #6125, 0.6 mi. 5.810.3 4.110.5 South of Lake Road 0.3 miles 0 274* Shoreline Cove, East of NMP-1, 6.6t0.5 4.6i0.5 6.0i0.8 6.010.4
- 1
~'
106 Tree on West Edge l Storeline Cove, East of NMP-1 6.110.6 4.810.4 6.211.1 6.010.7 0.3 miles 0 272* 107 1.1 miles 0 104* Pole #143, South of Lake Road, 5.6 0.3 4.210.3 4.810.6 5.010.6 108 300 ft. East of Rt. 129 4.210.2 4.110.4 1.1 miles 0 103* 109 Tree North of Lake Road, 300 ft. 5.710.3 4.310.3 I East of Route 29 4.6*0.4 21.8 miles 0 214* 111 Control, Steriing, NY 5.310.2 4.010.2 5.411.3 Control, Baldwinsville, NY 5.710.2 4.410.5 4.811.0 4.811.0 24.7 miles 0 178* 113
- Technical Specificatico Location
** Direction and distance based on NMP-2 reactor centerline and sixteen 22.5 degree sectors
*** TLD lost in field M M M M M M M M M M M M (m M M M M M M
M M M m m e e e m .m m m M M m. m M- M M TABLE 6-11 CONCENTRATIONS OF IODINE-131 IN MILK Results in Units of pCf / liter 1 Sigma
>> :=a ..: .a -o o = , mc - ew -1.. $. , ~ , ~ / x n ~ =mmy e _ ,,
;=06./17/91?
- y. JiSTAT n , ION $a c ngi
_g
/9h -
gy. w ,, m 0 105/e,6/91.9
- , . /w - @g.06/03/91%ag?
~R;,OS/20/91B,M ~ ~ ; m .
~ me 2
<0.56 <0.56 <0.57 <0.57 (
No. 60 <0.54 <0.62
<0.52 <0.54 <0.57 <0.55 No. 55 <0.50 <0.55
<0.49
<0.48 <0.53 <0.52
, No. 50 <0.72 <0.58 A
w <0.59
'l <0.53 <0.61 <0.50 No. 7 <0.48
<0.59 <0.60 <0.66 <0.55 No. 4 <0.55 <0.55
<0.48
<0.49 <0.54 <0.55 <0.53 No. 16 <0.57 '
.~
No. 65 <0.54 <0.55 <0.84
<0.63 <0.64 <0.62 (Control) o Corresponds to sample locations noted on the maps in Section 3.3.
TABLE 6-11 (corrznuco) CONCENTRATIONS OF 10 DINE-101 IN MILK Result.s in Ur.i*$ of pCi/ liter .s 1 Sigma
.... m m g ..o,. . ..s , . om , y. m, .m s .
.s , ,- _ . .- . .
p$,,$TATION W , 01/9t W.uO7 (y07/.15/91tn =008/19/91V,. X.09/03/91' -009/
- 2.6/9.15,
-m . g -m F_ -e y ::08/05/9.1E -y ~4 car .c -s-r . -. _
1-
-q No. 60 <0.39 <0.62 <0.39 <0.50 <0.50 <0.57 No. 55 <0.58 <0.69 <0.39 <0.67 <0.54 <0.36 e No. 50 <0.57 <0.44 <0.49 <0.62 <0.57 <0.52 L
w - No. ' <0.64 <0.52 <0.47 <0.57 <0.54 <0.65 No. 4 <0.51 <0.66 <0.56 <0.54 <0.43 <0.54 No. 16 <0.63 <0.58 <0.54 <0.39 <0.39 <0.57
-- n No. 65 <0.56 <0.60 <0.59 <0.53 <0.51 <0.52 i
- Corresponds to sample locations noted on the maps in Section 3.3.
3 l l i I
- M M M M M M M M M M M M M M M M M M l
sus sus ses sus can sus sus sus sus ese sus se aus sus aus sus sus uma ses i TABLE 6-11 (couvruuto) / CONCENTRATIONS OF I0 DINE-131 IN MILK Results in Units of pCi/ liter i 1 Sigma-
~
11/04/9b 11/18/9F Qli/03/91 612/16/91f$
;"[STATIONk'[50p7/91N~ ]10/2N91: ;
I
<0.36 <0.55 <0.62 <0.44 No. 60 <0.47 <0.59 -
<0.48 <0.35 <0.52 <0.63 No. 55 <0.53 <0.49 \
<0.50 <0.53 <0.67 <0.60 No. 50 <0.53 <0.46 _
k No. 7 <0.36 <0.38 <0.54 <0.47 <0.46 ,
<0.58
<0.51 <0.51 <0.52 <0.44 No. 4 <0.56 <0.54 1
<Wh *%:y *
<0.53 <0,48 <0.69 <0.36 No. 16 <0.51 <0.55
<0.56 <0.39 <0.54 <0.25 No. 65 <0.48 <0.53 I
- Corresponds to sample locations noted on the maps in Section 3.3.
e.
ll TABLE 6-12 CONCENTRATIONS OF GAMMA EMITTERS IN MILK Results in Units of pCi/ liter 1 Sigma I STATION
- NUCLIDES '04/01/91- 04/15/91 05/06/91 05/20/91 06/03/91 08/17/91 w.- ..
No. 60 K-40 1670 67 1680 86 1520 66 1430 65 1710 69 1470164 l Cs-134 <6.46 <8.84 c5.47 <5.56 <7.56 <5.74 Cs-137 <6.92 <8.32 <7.18 <6.70 <6.69 <6.00 l, Ba/La-40 <5.53 <12.9 <8.84 <6.45 <8.45 <8.97 Otherst <LLD (LLD <LLD <LLD <LLD <LLO No. 55 K-40 1540 69 1720 70 1590168 1550 66 1590 66 1750i71 Cs-134 <8.59 <7.32 <7.24 <6.26 <5.99 <6.86 C:-137 <7.79 <6.40 <6.34 <5.69 <5.69 <6.55 E Ba/La-40 <9.92 <6.22 <8.72 <8.47 (9.35 <7.58 5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No. 50 K-40 Cs-134 1620 101
<11.9 1420 70
<7.86 1360 69
<8.60 1580 96
<9.26 1790 88
<10.3 1530i67
<5.16 l
Cs-137 <11.9 <7.70 <6.50 <10.6 (9.47 <6.07 Ba/La-40 Otherst
<14.4
<LLD
<7.17
<LLD
<7.67
<LLD
<13.3
<LLD
<10.9
<LLD
<7.56
<LLD l
No. 7 K-40 Cs-134 1610 67
<7.28 1380163
<5.65 1630 69
<6.46 1540 66
<9.53 1420 62
<5.94 1680 87
<9.15 l Cs-137 <7.04 <6.43 <7.08 <6.27 <5.77 <8.49 Ba/La-40 Otherst
<9.00
<LLD
<8.42
<LLD
<8.98
<LLD
<8.32
<LLD
<6.23
<LLD
<10.5 (LLD l No. 4 K-40 1550 67 1380 68 1530 83 1520 67 1580 83 1680 102 m Cs-134 <7.49 <7.92 <8.60 <8.01 <10.2 <10.2 3 Cs-137 <6.26 <8.27 <9.36 <6.69 <9.15 <11.2
. Ba/La-40 <7.81 <10.0 <11.0 <8.36 <12.3 <9.39 3 Otherst <LLD <LLD <LLD <LLD <LLD <LLD E No. 16 K-40 1540 83 1670 68 1640d85 1640 85 14801101 1510 64 Cs-134 Cs-137
<8.50
<9.00
<7.98
<7.68
<9.74
<9.36
<8.17
<8.02
<8.41
<11.2
<5.65
<6.36 l
821 :lff :M :!ff :!# ll!6 :M" l No. 65 K-40 1610185 1620 83 1690 70 1480 65 1630 99 1550 99 (Control) Cs-134 <9.30 <8.83 <6.82 <5.48 <9,6 <10.6 g Cs-137 <8.78 <9.00 <6.62 <6.50 <9.87 <10.9 Ba/La-40 <13.3 <11.7 <8.44 <8.86 <11.0 <8,52 Otherst <LLD <LLD <LLD <LLD <LLD <LLD g
- Corresponds to sample locations noted on the maps in Section 3.3.
t Plant related radionuclides. l 6-45 g. m
I TABLE 6-12 (Cow 1xwuto) l CONCENTRATIONS OF GAMRA EMITTERS IN MILK Results in Units of pCi/ liter 2 1 Sigma I STATION
- NUCLIDES 07/01/91 07/15/91 08/05/91 08/19/91 09/03/91 09/16/91 l .t==w No. 60
~=-=n K-40 1760 71 1500 64 1700 87 m- m 1590 83 x==+ _
1610186
-.a =======
1650 83 Cs-134 <6.91 <5.52 <9.00 <8.35 <8.51 <8.98 I Cs-137 Ba/La-40
<7.21
<8.38
<6.70
<6.42
<9.15
<10.9
<9.57
<11.5
<8.83
<8.24
<8.40
<9.20 Otherst <lLD <LLD <LLD <LLD <LLD <LLD I Ho. 55 K-40 1470i65 16403101 1740 85 1530 81 1660168 1460 65 Cs-134 <6.07 <10.6 <9.45 <9.95 <7.45 <5.98 I Cs-137 Ba/La-40
<6.50
<7.05
<9.8/
<8.84
<8.72
<6.24
<8.37
<9.14
<6.82
<7.59
<4.63
<8.85 Otherst <LLD <LLD <LLD <LLD <1LD <LLD No. 50 K-40 1550i96 1510 99 1620268 1570 68 1530272 1580 69 Cs-134 <9.57 <9.77 <6.81 <6.95 <6.01 <7.54 Cs-137 <12.1 <12.8 <5.66 <6.89 <7.20 <6.55 I Ba/La-40 Otherst
<13.9 (LLD
<13.7
<LLD
<7.98
<LLD
<6.86
<LLD
<8.25
<LLD
<5.37 (LLD l No. 7 K-40 Cs-134 1560 66
<6.71 1500t65
<6.26 1630169
<7.19 1440265
<6.52 1440 62
<5.62 1620 99
<8.95 Cs-137 <6.96 :6.90 <7.69 <6.64 <6.85 <10.4 l Ba/La-40 Otherst
<6.81
<LLD
<7.59
<lLD
<8.66
<LLD
<7.69
<lLD
<6.21 (LLD
<14.2
<llD h) No. 4 K-40 1430 95 1510 65 1490 66 1530i73 1510 65 1440 83 5 Cs-134 <10.4 4 .44 <5.20 <7.29 <6.02 <9.53 Cs-137 <11.8 <5.77 <6.00 <6.60 <6.90 <8.37 I Ba/la-40 Otherst
<11.8
<LLD
<5.54
<LLD
<8.86
<LLD
<10.4
<LLD
<6.75
<LLD
<9.50
<LLD No. 16 K-40 1710 88 1660 101 1480 74 1610 81 1700 104 1530174 I Cs-134 Cs-137
<10.2
<9.57
<9.95
<12.1 (6.37
<8.04
<7.94
<9.78
<10.2
<12.1
<7.15
<6.60 Ba/La-40 <9.06 <12.9 <10.8 <11.0 <9.88 <10.4 I
l Otherst <LLD <LLD <LLD <LLD <LLD <LLD No. 65 K-40 1780 88 1470 64 1600 83 1260 62 1320 96 1540 99 l (Control) Cs-134 Cs-137
<8.85
<8.02
<5.71
<6.50
<9.00
<7.24
<6.46
<6.15
<9.46
<9.87
<10.5
<12.9 l t ers b <[D <[0 < LED <Lb <Lb
- Corresponds to sample locations noted on the maps in Section 3.3.
ltPlantrelatedradionuclides 6-46
TABLE 6-12 (courruuto) l CONCENTRATIONS OF GAMMA EHITTERS IN HILK Results in Units of pCi/ liter 1 Sigma STATION
- NUCLIDES 10/07/91 10/21/91 11/04/91- 11/18/91 12/03/91 12/16/91' I-No. 60 K-40 1650 69 1500 66 1430164 1550 83 1490 64 m..
1530167 l Cs-134 <7.05 (6.75 <5.57 <9.23 <5.52 <6.78 ts-137 Ba/La-40
<7.08
<9.41
<6.43
<8.43
<6.00
<10.0
<7.82
<9.85
<6.36
<10.6
<7.52
<8.01 l
Otherst <LLD <LLD <LLD <LLD <LLD <LLD No. 55 K-40 1670 98 1460270 1580 83 1620168 1560 66 1580 84 Cs-134 <8.86 <7.70 <9.23 <5.29 <6.81 <9.25 Cs-137 <11.7 <7.51 <8.78 <6.00 <6.29 <8.67 3 Ba/La-40 <14.9 <9.88 <13.4 <6.76 <5.68 <9.21 5 Otherst <LLD <LLD <LLD <LLD <LLD <LLD No. 50 K-40 Cs-134 1610 101
<10.4 1640 69
<6.86 1450 68
<5.52 1600 88
<9.32 1680 87
<8.59 1380 83
<9.61 l
Cs-137 <9.69 <7.21 <6.15 <11.4 <10.0 <10.7 Ba/La-40 Otherst
<11.8
<LLD
<7.59
<LLD
<8.09
<LLD
<10.8
<LLD
<13.3
<LLD (13.0
<LLD l
No. 7 K-40 1420 63 1740 73 15701100 1450 64 1600 82 1640 85 g Cs-134 <6.22 <7.72 <9.66 <5.61 <7.89 <9.15 Cs-137 <6.96 <7.02 <12.4 <6.64 <8.07 <9.74 Ba/La-40 <5.68 <6.85 <14.2 <7.08 <12.1 <12.0 g Otherst <LLD <LLD <LLD <LLD <LLD <LLD No. 4 K-40 1460 71 1620 68 1520 82 1730 70 1680i103 1530280 m Cs-134 <6.52 <8.10 <9.00 <7.19 <9.85 <10.2 3 Cs-137 (6.60 <6.41 </.69 <7.02 <11.5 <9.53 Ba/La-40 <10.4 <5.95 <9.34 <7.63 <13.4 <11.9 a Otherst <LLD <LLD <LLD <LLD <LLD <LLD E No. 16 K-40 1620274 1490 72 1710 70 1690 84 1720 72 1540 81 Cs-134 Cs-137
<6.22
<6.13
<6.32
<7.36
<9.77
<6.96
<10.3
<8.07
<6.67
<7.21
<9.83
<8.67 l
Ba/La-40 <7.66 <11.3 <6.83 <13.3 <8.33 <12.0 No. 65 Otherst K-40
<LLD 1480 65
<LLD 1360 62
<LLD 1610 68
<LLD 1610 86
<LLD 1680 70
<LLD 1620 68 l
(Control) Cs-134 <6.60 <6.57 <7.64 <12.0 <7.28 <6.56 E Cs-137 <6.00 <6.57 <7.02 <9.53 <6.69 <7.21 5 < Ba/La-40 <5.94 <9.30 <7.16 <9.43 <6.40 <7.62 Otherst <LLD <LLD <LLD <LLD <LLD <LLD g,
- Corresponds to sample locations noted on the maps in Section 3.3.
l)l t Plant related radionuclides 6-47 I
I g TABLE 6-13 MILCH ANIMAL CENSUS 1991 g, - HUMBER OH NUMBER T CENSUS MAPil) DEGREES (2) DISTANCE (2) 0F MILCil ANIMALS g g;OWN OR =AREA (a)
= - - . . , _ _
Scriba 16* 190* 5.9 miles 40C I 2 3 195* 190* 8.0 4.5 ti0fiE 3C 6 162* 2.2 1C I' 26 61 114* 140' 1.5 3.0 fiD SG 62 183* 6.7 7G I 63 185* 8.0 40C l New Haven 9 4* 95* 113' 5.2 7.8 45C 95C 45 125' 8.0 ND l 10 5 130* 146' 2.6 7.2 28C 46C 11 130' 8.5 N0 fit l 64 7* 107' 107* 5.5 7.9 62C 50C 711 111' 4.2 3G I Mexico 12 107' 11.5 22C l 14 17 120' 115* 9.8 10.2 62C 2C 19 132* 10.5 40C l 60* 50* 90* 93* 9.5 8.2 40C 150C 55* 95* 9.2 50C I 21 68 112* 108' 10.5 11.6 75C 79C 49 88* 7.9 5G Richland 22 85* 10.2 43C I Pulaski 23 92* 10.5 NONE l 69 85* 11.6 45C I l s48
1 I TABLE 6-13 (CowTzwuco) l MILCH ANIMAL CENSUS 1991 NUMBER ON NUMBER I TOWN OR AREA (a) CENSUS MAPll) DEGREES (2) DISTANCE (2) 0F HILCil ANIMALS u_ m_ -, - - Sterling 65** 220' 17.0 miles 45C g Volney 25 182* 9.5 40C 70 147' 9.4 20C 66 156' 7.8 70C 67 152' 8.3 NONE MILKING ANIMAL TUTALS: 1,193 Cows (including control locations) 20 Goats MILKING ANIMAL TOTALS: 1,148 Cows (excluding control locations) 20 Goats C - Cows G - Goats
* - Milk sample location
** - Milk sample control location t - New location ND - Did not wish to participate in the survey (1) - References Section 3.3 (2) - Based on Nine Mile Point Unit 2 Reactor Centerline NONE = No cows or goats at that location. location was a previous location with cows and/or goats.
(a) - Census performed out to a distance of approximately te, miles. I i l 6-49 g 1
M m m m m m W m -m W m m m m m m m m m W TABLE 6-14 CONCENTRATIONS OF GAMMA EMITTERS IN VARIOUS FOOD PRODUCTS Results in Units of pCi/g (wet) 1 Sigma COLLECTION kSAMPLEei ~_iz T' . K-401
~I-131 Cs-134! . Cs-137~
~
Zn-65:~ lSITEK "DATE] . :DESCRIPT10NJ LBe-7: 0.91 0.08 3.18 0.17 <0.020 <0.020 <0.024 <0.066 08/26/91 Cucumber Leaves <0.038 0.48 0.04 4.37 0.13 <0.012 <0.014 <0.013 T* 08/26/91 Bean leaves <0.032 Cabbage 0.06 0.03 3.55 0.12 <0.011 <0. 12 <0.012 08/26/91 <0.012 <0.013 <0.012 <0.039 08/26/91 Squash Leaves 0.45 0.04 3.36 0.13 ; 1
<0.93 4.46 0.12 <0.011 <0.012 <0.012 <0.031 08/26/91 Squash Leaves 0.65 0.08 5.36 0.24 <0.027 <0.024 <0.028 <0.081 K* 08/26/91 Corn leaves <0.012 <0.035 8ean Leaves 0.42 0.04 3.79 0.12 <0.012 <0.013 08/26/91 6,
0.24 0.03 5.35 0.12 <0.012 <0.012 <0.011 <0.033 08/26/91 Pepper Leaves <0.018 J 0.75 0.03 1.19 0.53 <0.008 <0.006 <0.007 L 08/26/91 Cucumber Leaves <0.011 <0.029 Bean Leaves 0.37 0.03 1.39 0.73 <0.012 <0.008 08/26/91 0.35 0.03 3.20 0.09 <0.009 <0.010 <0.009 <0.026 N 08/26/91 Grape Leaves <0.033 Squash Leaves 0.50 0.04 3.49 0.11 <0.012 <0.012 0.039 0.003 08/26/91 l 0.09 0.02 6.99 0.11 <0.007 <0.006 <0.007 <0.026 08/26/91 Pepper Leaves l 0.30:0.04 4.35 0.13 <0.012 <0.013 <0.012 <0.039 Z 08/26/91 Bean leaves <0.049 Grape Leaves 0.38 0.05 3.11 0.13 <0.017 <0.014 <0.015 08/26/91 <0.007 <0.007 <0.007 <0.024
! 08/26/91 Lettuce 0.04 0.02 3.64 0.09 0.48 0.04 4.60 0.14 <0.014 <0.016 , <0.015 <0.042 08/26/91 Bean leaves <0.014 <0.042 Squash Leaves 0.25 0.04 5.09 0.14 -0.015 <0.017 M* 08/26/91 <0.017 <0.014 <0.018 <0.049 08/26/91 Grape Leaves 0.66 0.06 2.92 0.14 (Control) 0.36 0.03 2.41 0.08 <0.008 <0.008 <0.008 <0.024 08/26/91 Cucumber Leaves <0.024 Pepper Leaves 0.4210.02 6.65 0.11 <0.021 <0.006 <0.007 08/26/91 NOTE: Other Plant Related Radionuclides <LLD.
- Samples required by Technical Specifications.
TABLE 6-15 g 1991 RESIDENCE CENSUS MAP METER 0 LOGICAL .. LOCATION- ' DESIGNATION *' SECT 07, DEGREES DISTANCE (*) g w N - - w NNE - - w w NE ENE l Sunset Bay A E 82* 0.9 miles Lake Road Parkhurst Road B ESE 119' O.7 miles l C SE 127* 1.2 miles County Route 29 D SSE 149* 1.2 miles Miner Road E S 173* 1.6 miles l Lakeview Road F SSW 210* 1.7 miles Lakeview Road G SW 233* 1.5 miles Bible Camp Retreat w H WSW 249* 1.3 miles l W - - w WNW - - w NW - - l w NNW - - w This meteorological sector is over Lake Ontario. There are no residences within three miles. g ( ' i Based on J A. FitzPatrick Nuclear Power Plant Reactor Centerline.
- See the maps in Section 3.3.
6-51 l
l l 7.0 tilSTORICAL DATA TAllLES Sample Statistics from Previous Environmental Sampling The mean, minimum value and maximum value were calculated for telected sample I mediums and isotopes. l Special Considerations: I 1. Sample data listed as 1969 was taken from the NINE MILE POINT. PREOPERATION SURVEY. 1969 and ENVIRONMENTAL MONITORING REPORT FOR NIAGARA MollAWK POWER CORPORATION NINE MILE POINT NUCLEAR STATION. NOVEMEEIL19911
- 2. Sample data listed as 1974,1978,1979,1980,1981,1982,1983,1 M,1985, g 1986,1087,1988 and 1989 was teken from the respective eni nmental operating reports for Nine Mile Point Nuclear Station anc* sames A.
FitzPatrick Nuclear Power Plant. I
- 3. Only measured values were used for stat istical calculations.
- 4. The term MDL was used prior to 1979 to represent the concept of lower g Limit of Detection (LLD). MDL = Minimum Detectable Level.
I I I I I I 7-1 I
I TABLE 7-1 l HISTORICA! ENVIRONMENTAL SAMPLE DATA SHORELINE SEDIMENT I Results in pCi/3 (dry) LOCATION: CONTROL
- h Isotope Cs-134 Cs-137 Co-60 Year Min. Max. Mean Min. Max. Mean Hin.
g Max. Mean 1969 "* ** ** ** ** ** ** ** ** l 1974 ** 1975 ** ** ** ** ** 1976 ** ** ** ** ** ** ** ** ** l 1977 ** ** ** ** ** ** ** ** ** 1978 ** ** ** ** ** ** ** ** ** 1979 ** ** ** ** ** ** ** ** ** l 1980 ** ** ** ** ** ** ** ** ** 1981 ** ** ** ** ** ** S* ** ** 1982 ** ** ** ** ** ** ** ** ** 1983 ** ** ** ** ** ** I ** 1984 ** ** ** ** ** ** ** ** ** 1985 <LLD <LLD <LLD <LLD <LLO lg
<LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD g <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD g 1989 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD l 1991 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD l***
Langs Beach - beyond influence of the site in a westerly direction. Ho data. Sample not required until new technical specifications implemented in 1985. g 7-2
TABLE 7-2 l HISTORICAL ENVIRONMENTAL SAMPLE DATA l SHORELINE SEDIMENT Results in pCi/g (dry) I LOCATION: INDICATOR
- Isotope Cs-134 Cs- 37 Co-60 l Year Hin. Max. Mean Hin. Max. Mean Hin. Max. Mean 1969 1974 1975 l
1976 ** l ; 1977 1978
- l 1979 1980 **
l 1981 1982 ** l 1983 5 5 1984 1985 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD 0.25 0.32 0.29 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 0.28 0.30 0.29 <LLD <LLD <LLD 1991 <LLD <LLD <LLD 0.12 0.14 0.13 <LLD <LLD <LLD
- Sunset Beach - closest off-site location with recreational value.
** No data. Sample not required until new technical specifications implemented 5 1985.
I I u g [
I TABLE 7-3 l HISTORICAL ENVIRONMENTAL SAMPLE DATA FISH Results in pCi/g (wet) l LOCATION: CONTROL
- g Isotope Cs-137 Year Hin. Max. Mean I 1969t No Data No Data No Data 1974t 0.99 0.94 0.43 g
1975 <MDL <MDL <MDL g 1976 1.2 1.2 1.2 1977 0.13 0.13 0.13 g 1978 0.04 0.20 0.09 1979 0.03 0.06 0.04 l,1980 0.029 0.110 0.059 1981 0.028 0.062 0.043 l 1982 1983 0.027 0.040 0.055 0.060 0.047 0.050 l 1984 1985 0.015 0.026 0.038 0.047 0.032 0.034 l 1986 0.021 0.032 0.040 0.025 0.03 1987 0.017 l 1988 0.023 0.053 0.034 1989 0.028 0.043 0.034 1990 0.033 0.079 - 0.045 1991 0.021 0.034 0.029 E _. Control location was at an area beyond the influence of the site (westerly direction). 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. lt l 7-4
TABLE 7-4 HISTORICAL ENVIRONMENTAL SAMPLE DATA l FISH Results in pCi/g (wet) LOCATION: INDICATOR * (NMP/JAF) n Isotope Cs-137 l Year Hin. Max. Mean 1969t 0.01 0.13 0.06 I i 1974f 1975 0.08 1.10 4.40 1.70 0.57 1.38 l 1976 1977 0.50 0.13 3.90 0.79 1.4 0.29 l 1978 1979 0.03 0.02 0.10 0.55 0.08 0.10 l 1980 1981 0.030 0.027 0.100 0.10 0.061 ' l 0.061 l 1982 0.034 0.064 0.050 l 1983 0.030 0.060 0.050 1984 0.033 0.051 0.043 l 1985 0.018 0.045 0.030 1986 0.009 0.051 0.026 1987 0.024 0.063 0.033 1988 0.022 0.054 0.032 1989 0.020 0.044 0.034 1990 0.027 0.093 0.040 1991 0.018 0.045 0.029 l 0 Indicator locations are in the general area of the NMP-1 and J. A. FitzPatrick cooling cater discharge structures. t 1969 data is considered to be pre-operational for the site. 1974 data is considered to E be pre-operational for the JAFNPP. E 7-5 g
TABLE 7-5 l HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER l Results in pCi/ liter LOCATION: CONTROL t g -- m Isotope Cs-137 Co-60 I Year Hin. Max. Mean Hin. Max. Mean l 1969tt * * * * *
- 1974tt * * * * *
- l 1975 * * * * *
- 1976 * * * * *
- l 1977 ** ** ** ** ** **
1978 <MDL <MDL <MDL ** ** ** l 1979 1980 2.5
<LLD 2.5
<LLD 2.5
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD g 1981 <LLD <LLD <LLD 1.4 1.4 1.4 1982 <LLD <LLD <LLD <LLD <LLD <LLD 1983 g <LLD <LLD <LLD <LLD <LLD <LLD 1984 <LLD <LLD <LLD <LLD <LLD <LLD 1985 g <LLD <LLD <LLD <LLD <LLD <LLD 1986 <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD g <LLD 1988 <LLD (LLD <LLD <LLD <LLD <LLD
, 1989 <LLD <LLD <LLD <LLD <LLD <LLD j 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD g* No gamma analysis performed (not required). l
** Data showed instrument background results.
t location was the City of Oswego Water Supply for 1969 - 1984 and the Oswego Steam Station inlet canal for 1985 - 1991. l tt 1969 data is considered to be pre-operational for the site. be pre-operational f _r the JAFNPP. 1974 data is considered to 76
1 TABLE 7-6 l HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER l Results in pCi/ liter l LOCATION: INDICATOR t g Isotope Cs-137 Co-60 i Year Hin. Max. Mean Hin. Max. Mean I 1969tt l 1974?t 1975 - l 1976 , 1977 1978
'MDL
<MDL
< MDL l
1979 1980
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<lLD
<LLD l
1981 1982
<LLD 0.43
<LLD 0.43
<LLD 0.43
<LLD 1.6
<LLD 2.4
<LLD 1.9 l
1983 <LLD <LLD <LLs <LLD <LLD <LLD g 1984 <LLD <LLD <LLD <LLD (LLD (LLD 1985 <LLD <LLD <LLD <LLD <LLD <LLD E 1986 <LLD <LLD <LLD <LLD <LLD <LLD 1987 <LLD <LLD <LLD <LLD <LLD <LLD g 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD g 1990 <LLD <LLD < LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD g
- No gama analysis performed (not required).
** Data showed instrument background results.
t Indicator location was the NMP 1 Inlet Canal for the period 1969 - 1973, and the JAF Inlet Canal for 1974 - 1991, l it 1969 data is considered to be pre-operational for the site. 1974 data is considered to g be pre operational for the JAFNPP. 77 g n-
l TABLE 7-7 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM I Results in pCi/ liter LOCATION: CONTROL
- l Isotope ritium Year Min. Max. Mean 19691 No Data No Data No Data l 1974t 1975
<MDL 311
<MDL 414
<MDL 362 l 1976 1977 440 300 929 530 652 408 l 1978 1979 215 174 490 308 304 259 l 1980 1981 211 211 290 357 257 293 l 1982 112 307 280 165 250 1983 230 l 1984 190 220 205 288 1985 230 430 1986 250 550 373 1987 140 270 210 1988 240 460 320 1989 143 217 186 I 1990 260 320 290 1991 220 590 360 g ,
- Control location is the City of Oswego, drinking water for 1969 - 1984 and the Oswego I Steam Station inlet canal for 1985 1991.
1969 data is considered to be pre operational for the site. 1974 data is considered to I t be pre-operational for the JAFNPP. ; l 7-8
TABLE 7-8 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM Results in pCi/ liter LOCATION: INDICATOR
- l Isotope Tritium g Year Min. Max. Mean 1969t No Data No Data No Data 1974f 380 500 440 1975 g
124 482 335 1)76 297 889 513 1977 380 g 530 450 1978 253 560 389 1979 176 286 234 1980 150 457 263 1981 183 388 258 1982 194 2780 641 1983 190 560 317 1984 110 370 282 1985 250 1200** 530 5 1986 260 500 380 1987 1988 160 430 410 480 322 l 460 1989 1990 135 220 288 290 225 250 l 1991 250 390 310 l Indicator location was the NMP-1 Inlet Canal during the period 1969-1973, and the JAF Inlet Canal for 1974-1991.
- Suspect sample contamination. Recollected samples showed normal levels of tritium.
1969 data is considered to be pre-operational for the site. l t 1974 data is considered to be pre-operational for the JAFNPP. 79 l
TABLE 7-9 l HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA I Results in pCi/m 3 LOCATION: CONTROL
- Isotope Gross 8 eta g Year Hin. Max. Mean 1969t 0.130 0.540 0.334 19741 0.001 0.808 0.121 19/.7 0.008 0.294 0.085 1976 0.004 0.240 0.051 1977 0.001 0.484 0.126 l 1978 1979 0.010 0.010 0.650 0.703 0.144 0.077 l 1980 1981 0.009 0.016 0.291 0.549 0.056 0.165 l 1982 1983 0.011 0.007 0.078 0.085 0.033 0.024 l 1984 1985 0.013 0.013 0.051 0.043 0.026 0.024 l 1986 1987 0.008 0.009 0.272 0.037 0.039 0.021 g 1988 0.008 0.039 0.018 1989 0.007 0.039 0.017 g 1990 0.003 0.027 0.013 1991 0.007 0.028 0.014 g
0 Locations used for 1977 - 1984 were C off-site, D1 of'-site, 02 off-site E off-site, F off-site, and G off-site. Control location R-5 off-site was used for 1985 - 1991 I (formerly C off-site location). i 1969 data is considered to be pre-operatior,a1 for the site. 1974 data is considered to g be pre-operational for the JAFNPP. 7-10 g
TABLE 7-10 ! HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA l Results in pCi/m 3 l LOCATION: INDICATOR
- E m .
- e Isotope Gross Beta Year Hin. Max. Mean I
1969t 0.130 0.520 0.320 l 1974t 0.003 0.885 0.058 1975 1976 0.001 0.002 0.456 0.191 0.067 0.047 l 1977 0.016 0.140 0.070 ll 1978 0.006 0.340 0.102 1979 1980 0.001 0.002 0.271 0.207 0.058 0.045 l 1981 1982 0.004 0.001 0.528 0.113 0.151 0.031 l 1983 0.003 0.062 0.023 g 1984 0.001 0.058 0.025 1985 0.001 0.044 0.021 m 5 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 g 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 g 199L 4 0.006 0.023 0.014 1991 0.006 0.033 0.015 g '
- Locations used for 1969 - 1973 were D1 on-site, D2 on-site, E on-site, F on-site and [
G on-site. Locations used for 1974 - 1984 were D1 on-site, D2 on-site, E on-site, F u , on-site, G on-site, H on-site, I on-site, J on-site and K on-site, as applicable. 1985
- 1991 locations were R-1 off-site, R-2 off-site, R-3 of f-site, and R-4 off-site, t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP.
I 7 11 g
I TABLE 7-11 l HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES l Results in pCi/m 3 g LOCATION: CONTROL ** n___ ___ _ - Isotope Cs-137 Co-60 Year Hin. Max. Mean Hin. Max. Mean l 1969t l 19741 1975 * * * * *
- 1976 *
- 1977 0.0002 0.0112 0.0034 0.0034 0.0347 0.0172 1978 0.0008 0.0042 0.0018 0.0003 0.0056 0.0020 k 1979 0.0008 0.0047 0.0016 0.0005 0.0014 0.0009 1980 0.0015 0.0018 0.0016 <LLD (LLD <LLD l 1981 0.0003 0.0042 0.0017 0.0003 0.0012 0.0008 1982 0.0002 0.0009 0.0004 0.0004 0.0007 0.0006 l 1983 1984 0.0002
<LLD 0.0002 0.0002 0.0007 0.0007 0.0007
<LLD <LLD 0.0004 0.0012 0.0008 l 1985 1986
<LLD 0.0075
<LLD 0.0311
<LLD <LLD <LLD <LLD 0.0193 <LLD <LLD <LLD l 1987 1988
<LLD
<LLD
<LLD
<LLD
<LLD 4LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l 1989 1990
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD l
l* ** No data available (not required prior to 1977). Locations included composites of off-site air monitorir.g locations for 1977 - 1984. g Sample location included only R-5 air monitoring location for 1985 .991, t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. 7-12 1 - - - - - - - - - -
TABLE 7-12 l HISTORICAL ENVIRONMENTAL SAMPLE DATA l AIR PARTICULATES Results in pCi/m' l LOCATION: INDICATOR ** l Isotope Cs-137 Co-60 Year Hin. Max. Mean Min. Max. Mean 1969t 19741 1975 1976 1977 0.0001 0.0105 0.0043 0.0003 0.0711 0.0179 1978 0.0003 0.0026 0.0016 0.0003 0.0153 0.0023 1979 0.0003 0.0020 0.0010 0.0003 0.0007 0.0005 l 1980 0.0005 0.0019 0.0011 0.0016 0.0016 0.0016 1981 0.0002 0.0045 0.0014 0.0002 0.0017 0.0006 l 1982 0.0001 0.0006 0.0004 0.0003 0.0010 0.0005 1983 0.0002 0.0003 0.0002 0.0003 0.0017 0.0017 0.0007 0.0012 l 1984 <LLD <LLD <LLD 0.0007 1985 <LLD <LLD <LLD <LLD <LLD <LLD l 1986 0.0069 0.0364 0.0183 cLLD <LLD <LLD 1987 <LLD <LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1988 <LLD 1989 1990
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<lLD
<LLD
<LLD
<LLD
<LLD l
1991 <LLD <LLD <LLD <LLD <LLD <LLD l
- No data available (not required prior to 1977). l
- Locations included composites of on-site air monitoring locations for 1977 - 1984.
Sample locations included R-1 through R-4 air monitoring locations for 1985 - 1991. g t 1969 data is consied to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. 7-13 g
TABLE 7-13 I HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOI0 DINE Results in pCi/m' l > - . . - . LCCATION: CONTtJL *
..-- =. _ _ . _ . ;- ,
g Isotope Iodine-131 Year Hin. Max. Mean l 19691 g 1974t 1975 <MDL <MDL <MDL 1976 0.01 5.88 0.60 g 1977 0.02 0.82 0.32 0.03 0.04 0.03 I 1978 1979 <LLD (LLD <LLD 1980 <tLD <LLD <LLD I 1981 <LLD <LLD <LLD 1982 0.039 0.039 0.039 1983 <LLD <LLD <LLD 1984 <LLD <LLD <LLD 1985 <LLD <LLD <LLD 1986 0.041 0.332 0.151 1987 <LLD <LLD <LLD 1988 <LLD <LLD <LLD
! 1989 <lLD <LLD <LLD 1990 <LLD <LLD <LLD l 1991 <LLD :LLD <LLD
- Locations D1 off-site, 02 off-site, E off-site, F off-site and G off-site used for 1976
- 1984. Location R-5 off-site used for 1985 - 1991, h ** No results - I-131 analysis not required.
t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. 7-14 g
TABLE 7-14 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADI0 IODINE l Re 'Its in pCi/m 3 l INDICATOR
- 1sotope m _,_ _m-- - . _ - .
LOCAT1u Iodine-131 _ _ - . _ _ , l Year Hin. Max. Mean 1969t g 1974f 1975 0.25 0.30 0.28 g 1976 0.01 2.09 0.33 1977 0.02 0.73 0.31 g 1978 0.02 0.07 0.04 1979 <LLD <LLD <LLD g 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.042 0.016 1983 0.022 0.035 0.028 1984 <LLD <LLD <LLD 1985 <LLD <LLD <LLD g 1986 0.023 0.360 0.119 E 1987 0.011 0.018 0.014 1988 <LLD <LLD <LLD 1989 <LLD <LLD <LLD 1990 <LLD <LLD <LLD 1991 <LLD <LLD <LLD I Locations used for 1976 - 1984 were 01 on-site, D2 on-site, E on-site, F on-site, G on-site, H on-site, I on-site, J on site and K on-site, as applicable. Locations used for 1985 - 1991 were R 1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site. l
- No results - I-131 analysis not required, t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP.
7-15 g
I TABLE 7-15A l HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD l Results in mrem / standard month a LOCATION: CONTROL ** 3 mg . Year Hin. Max. Mean I Preopt * *
- 1970 6.0 7.3 6.7 1971 2.0 6.7 4.3 1972 2.2 6.2 4.4 1973 2.2 6.9 4.7 19741 2.7 8.9 5.6 1975 4.8 6.0 5.5 1976 3.2 7.2 5.4 l 1977 1978 4.0 8.0 4.7 5.3 4.3 3.3 l 1979 1980 3.3 3.8 5.7 5.8 4.7 4.9 l 1981 1982 3.5 3.8 5.9 6.1 4.8 5.1 1983 4.9 7.2 5.8 l
1984 4.7 8.2 6.2 g 1985 4.5 7.6 5.6 1986 5.3 7.5 6.3 g 1987 4.6 6.6 5.4 1988 4.4 6.8 5.6 g 1989 2.9 6.4 4.7 1990 3.7 6.0 4.7 g 1991 3.8 5.8 4.7 go Data not available. o* TLD #8, 14, 49, 111 (1985 - 1990) and 113 (1991). 1969 data is considered to be pre-operational for the site. 1974 'ata is considered to It be pre-operational for the JAFNPP. l 7-16
TABLE 7-158 l HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD l Results in mrem per standard month l LOCATION: RETS CONTROL ** a 5 Year Hin. Max. Mean Preopt * *
- g 1970 6.0 7.3 6.7 g 1971 2.0 6.7 4.3 5 1972 2.2 6.2 4.4 1973 2.2 6.9 4.7 1
1974f 2.7 8.9 5.6 1975 1976 4.8 6.0 5.5 l 3.2 7.2 5.4 1977 4.0 8.0 5.3 l 1978 3.3 4.7 4.3 1979 1980 3.3 3.8 5.7 5.8 4.7 4.9 l 1981 1982 3.5 3.8 5.9 6.1 4.8 5.1 l 1983 1984 4.9 4,7 7.2 8.2 5.8 6.2 l 1985 1986 4,4 5.5 6.8 7.2 5.4 6.3 l 1987 4.6 5.8 5.2 g 1988 4.8 6.8 5.4 1989 2.9 6.4 4.1 g 1990 3.7 6.0 4.8 1991 3.8 5.3 4.6 g
- Data not available.
g TLD #14 and 49 (RETS Control Locations). t 1969 data is considered to be pre-operational for the site. 1974 data is considered to E
- be pre-operational for the JAFNPP. P 7-17
@l
g HISTORICAL ENVIRONME%TAL SAMPLE DATA ENVIRONMENTAL TLD Results in mrem per standard month I LOCATION: SITE 80UNDARY ** g c Year Hin. Hax. Mean g ',; Preopt 1970 * *
- 1971
< I 1972 1973 * *
- 19741 * *
- 1975 * *
- 1976 * *
- 1977 * *
- k 1978 * *
- 1979 * *
- l 1980 * *
- 1981 * *
- l 1982 1983 l 1984 1985 4.1 12.6 6.2 l '
1986 1987 4,4 4,4 18.7 7.0 14.3 6.1 1988 3.4 17.9 l 6.4 1989 2.8 15.4 5.9 l 1990 1991 3.6 14.9 6.4 3.2 16.7 6.0 I* Data not available (not required prior to 1985). TLD locations initiated in 1985 as required by the New Technical Specifications. Includes TLD numbers 7,18, 23 and 75 - 87. Several of these are in close proximity to I- site operational buildings not generally accessible to the public, and are not representative of the site boundary dose. 1969 data is considered to be pre-operational for the site. 1974 data is coneidered to It be pre-operaticnal for the JAFNPP. 7-18
TABLE 7-16B HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD l ) Results in mrem per standard month l' LOCATION: 0FF-SITE. SECTORS ** Year Hin. Max. Mean l Preopt 1970 l 19 " 1: .' l 1973 1974f l 1975 1976 l 1977 g 1978 1979 g 1980 1981 * *
- g 1982 1983 e 1984 * *
- 5 1985 4.0 7.1 5.0 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 E
, 1988 3.8 7.0 5.3 m ! 1989 2.5 6.8 4.9 1990 3.6 6.3 4.7 1991 3.6 5.8 4.7
- Data not available (not required prior to 1985).
l ** TLD locations initiated in 1985 as required by the New Technical Specifications. Includes TLD numbers 88, 89, 90, 91, 92, 93, 94 and 95. t 1969 data is considered to be pre-operational for the site. be pre-operational for the JAFNPP. 1974 data is considered to l 7-19 l
- - - - + - . ,
l TABLE 7-16C I HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD l Results in mrem per standard month I LOCATION: SPECIAL INTEREST *'
!!i l- Year Min. Max, Mean Preopt *
- l 190 1971 l 1972 1973 l 19741 1975 l 1976 1977 1978 * *
- g 1979 *
- 1980 *
- J 1981 * *
- 1982 * *
- g
- 1983 *
- I 1984 *
- 1985 3.9 6.8 5.3 l 1986 4.8 S.2 6.1 l- 1907 3.5 6.0 5.1 l
1988 3.9 fi . 6 5.3 l 2.1 1989 6.4 4.9 l 1990 3.2 6.3 4.8 1991 2.9 6.3 4.8 o Data not available (not required prior to 1985). lg* TLD locations initiated in 1985 as required by the New Technical Specifications.
-g Includes TLD numbers 15, 56, 58, 96-105,108 and 109, which are located near critical ,
resiaences and populated areas near the site. t 1969 data is cor.:idered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. g 7 20
TA!!LE 7-16D I. HISTORICAL ENVIRONMENTAL SAMPLE DATA g ENVIRONMENTAL TLD Results in mrem per standard month g E LOCATION: ON-SITE INDICATOR ** Year Hin. Max, Mean Preopt *
- g 1970 4.7 9.0 6.0 m 1971 1.5 7.7 4.7 5 1972 2.3 8.2 4.9 _
1973 3.0 24.4 6.6 1974t 3.1 10.s 5.7 h 1975 4.6 16.0 7.3 1970 1977 3.7 3.0 18.8 15.3 6.9 5.7 l 1978 1979 3.0 2.7 9.0 8.3 4.3 4.3 l 1980 1981 3.9 4.1 12.0 11.8 5.3 5.8 l 1982 1943 3.9 5.0 13.0 16.5 6.3 6.9 l 1984 1985 4.6 4.7 13.2 15.9 7.0 6.3 l - 1986 4.7 16.1 7.0 g 1987 4.0 11.4 5.8 1988 4.4 11.9 .0 g 1959 4.7 13.1 6.0 1990 3.6 12.9 5.5 g 1991 3.2 11.6 5.4 No data available. Includes TLD numbers 3, 4, 5, 6 and 7 (1970 - 1973). Includes TLD numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26 (1974 - 1991). Locations are existing or previous on-site g environmental air monitoring locations, t 1969 data is considered to be pre-operational for the site. 1974 data is considered to be pre-operational for the JAFNPP. j 7-21 g
I TABLE 7-16E l HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD g Results in mrem per standard month LOCATION: 0FF-SITE INDICATOR ** I Year Hin. Max. Mean l Preopt 1970 5.0 8.0 6.7 ! l 1971 1972 1.1 1.8 7.7 6.6 4.5 4.4 l g 1973 2.2 6.9 4.1 1974t 2.4 8.9 5.3 g 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 g 1978 2.7 4.7 3.7 3.0 5.7 4.0 ' I 1979 1980 3.1 5.8 4.6 1981 3.6 5.9 4.7 I 1982 4.0 6.2 5.2 1983 4.6 7.2 5.6 1984 4.6 8.2 6.1 1985 4.6 7.7 5.5 1986 5.0 7.6 6.1 1987 4.4 6.6 5.2 1988 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 3.8 6.1 4.8 1991 3.4 5.8 4.5 o th data available.
*o Includes TLD numbers 8, 9,10,11,12 and 13 (off-site environmental air monitorin9 locations).
1969 data is considered to be pre-operational for the site, 1974 data is considered to It be pre-operational for the JAFNPP. 7-22 l g
l TABLE 7-17 HISTORIC".u ENVIRONMENTAL SAMPLE DATA MILK Results in pCi/ liter LOCATION: CONTROL ** Isotope Cs-137 I -131 l Year Min. Max. Mean Min. Max. Mean 1969t I 1974t 1975 l 1976 1977 l 1978 2.4 7.8 5.8 <LLD <LLD <LLD g 1979 <LLD <LLD <LLD <LLD <LLD <LLD 1980 <LLD <LLD <LLD 1.4 1.4 1.4 g 1981 7.0 7.0 7.0 <LLD <LLD <LLD 1982 <LLD <LLD <LLD <LLD <LLD <LLD g 1983 <LLD <LLD <LLb <LLD <LLD <LLD 1984 <LLD <LLD <LLD <LLD <tLD <LLD g 1985 <LLD <LLD <LLD <LLD <LLD <LLD E 1986 5.3 12.4 8.4 0.8 29.0 13.6 1987 <LLD <LLD <LLD <LLD <LLD <LLD 1988 <LLD <LLD <LLD <LLD <LLD <LLD 1989 <LLD <LLD < Ll D <LLD <tLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD
- No data r.vailable (sample not required).
** Location used was an available milk sample location in a least prevalent wind direction 3 greater than ten miles from the site. B t 1969 data is consled to be pre-operational for the site. 1974 data is considered to be a $ pre-operational for the JAFNPP. g 7-23 g;
I TABLE 7-18 I l HISTORICAL ENVIRONMENTAL SAMPLE MILK Results in pCi/ liter P
.h LOCATION: INDICATOR **
l Isotope Cs-137 I-131 Year Min. Max. Mean Min. Max. Mean 1969t g 1974t 1.6 39 10.5 0.70 2.00 1.23 1975 6.0 22 16 0.01 2.99 0.37 g 1976 4.0 15.0 9.3 0.02 45.00 3.20 1977 11.0 22.0 17.1 0.40 0.22 0.02 g 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 2.7 40.0 9.4 <LLD <LLD <LLD g 1980 4.0 21.0 9.7 0.4 8.8 4.9 1981 4.3 29.0 7.6 <LLD <LLD <LLD 3.1 6.3 I 1982 1983 5.1 18.0 5.1 5.1
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1964 I 1985
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD 1986 6.1 11.1 8.6 0.3 30.0 5.2 I 1987 5.5 9.4 7.4 <LLD <LLD <LLD 1988 10.0 10.0 10.0 <LLD <LLD <LLD 1989 <LLD <LLD <LLD <LLD <LLD <LLD 1990 <LLD <LLD <LLD <LLD <LLD <LLD 1991 <LLD <LLD <LLD <LLD <LLD <LLD d
l ! gO Locations sampled were available downwind locations within ten miles with high deposition potential.
- No data available (control samples not r.r,uired).
1969 data is consied to be pre-operational for the site. 1974 data is considered to be l I t pre-operational for the JAFNPP. 7-24 g
HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS tt l Results in pCi/g (wet) g l LOCATION: CONTROL
- Isotope Cs-137 Year Min. Max. Mean l 1969t g 1974t 1975 ** ** **
1976 ** ** ** 1977 g 1978 ** ** **
- 1979 ** ** **
1980 <LLD <LLD <LLD 1981 <LLD <LLD <LLD n 1982 <LLD <LLD <LLD 1983 <LLD <LLD <LLD 1984 <LLD <LLD <LLD h 1985 <LLD <LLD <LLD E s 1986 <LLD <LLD <LLD 3 1987 <LLD <LLD <LLD 1988 1989
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
1990 1991
<LLD
<LLD
<LLD
<LLD
<LLD
<LLD l
- Locations was an available food product sample location in a least prevalent wi.:
l direction greater than ten miles from the site.
** No data available (control samples not required).
t 1969 data is considered to be pre-operational for the site. be pre-operational for the JAFNPP. 1974 data is considered to l tt Data comprised of broadleaf and non-breadleaf vegetaion (1980-1984). Data comprised of broadleaf vegetation only (1985-1991). 7-25 Il
! TABLE 7-20 l HISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS tt l Results in pCi/g (wet)
I r Isotope LOCATION: INDICATOR
- Cs-137 Year Mi n. - Max. Mean l 1969t 1974t 0.04 0.34 0.142 g 1975 <MDL <MDL <MDL 1976 <MDL <MDL <MDL 1977 <MDL <MDL g <MDL 1978 0.01 0.01 0.01 1979 <LLD <LLS <LLD g
1930 0.004 0.060 0.033 I 1981 1982
<LLD
<LLD
<LLD
<tLD
<LLD
<LLD l 1983 <LLD <LLD <LLD 1984 <LLD <LLD <LLD 1985 0.047 0.047 0.047 1986 <LLD <LLD <LLD 1987 <LLD <LLD <LLD 1988 0.008 0.008 0.008 1989 0.011 0.011 0.011 1990 <LLD <LLD <LLD 1991 0.039 0.039 0.039 I O Indicator locations were available down ind locations within ten miles of the site and with high deposition potential.
- Ho data available (control samples r,ot required).
1969 data is considered to be pre-operational for the site. 1974 data is considered to I~t be pre-operational for the JAFNPP. Data comprised of broadleaf and non-broadleaf vegetaion (1976-1984). Data comprised of l I tt broadleaf vegetation only '1985-1991). 7-26
I l 8.0 GRAPHICAL PRESENTATIONS g 1. . DATA GRAPHS This section includes graphic representation of selected sample results. For graphic representation, results reported as MDL or LLD were l considered to be at the "zero" level of activity. MDL and LLD results were indicated where possible. I 2. SAMPLE LOCATIONS - Sample location results sp cified as " indicator" and " control" on the graphs can be referenced back to Section 3.3 for specific locations. I I . I I - I I I I I I 8-1
me ame use am . (* ums -aus ama em aus - um as an. sus amm- aus em aus se JAMES A. FITZPATRICK N.P.P. ! FISH Cs-137 pCi/gm (wet) 1.6 , l 1974 Pre-operational data for JAFNPP ' j,4 ___ __ _ _ _ _ _ _ . _ . _ _ _ _ - . . . - _ . _ . _ _ ._ - _ _ . . - _ _ . _ . _ _ . . . _ .__
* <-MDL Value reported-no positive detection 1.2 -- -
- - - - - - - - - - - - - ~ - - - - - -
k 1 i 5 l 0.8 -
- - = - - ~ - - - - -- - - - -
8 0.6 -- - ----- --- i O.4 - - - 0.2 - - 7
- ---- -- - - - ~- ---- - - ~-
e
- . m . . . _ _ _ _ ____ - ,
1974 1976 1978 1980 1982 1984 1986 1988 1990 i 1976 1977 1979 1981 1983 1985 1987 1989 1991 1 1 INDICATOA % CONTROL' , t i
JAMES A. FITZPATRICK N.P.P. SURFACE-WATER TRITIUM Figure 8.2 pCi/L 3 1974: PRE-CP DATA FOR JAFNPP 1974-1984 COUTROL: OSWEGO ClkkV[ATbk
~
' ~ ~ ~ ~ ~
~'~~
1985-1991 CONTRCL: OSWEGO STEAM STATIOU 700 600 500 400
-, l
# I x
m-s00 a ) 200 - - I -
-] I- -- -
j p - -
'- c 100 0-
-l -f -
-i -
-l
- - - - - ~
1978 1978 1980 1982 1984 1986 1988 1990 l 1974 1975 1977 1979 19 81 1983 1985 1987 1989 1991 INDICATOR W CONTROL , r M M M M M M M M M M M M M M M M M M M
JAMES A'. FITZPATRICK N.P.P. ' AIR PARTICULATE GROSS BETA Figure 8.3 ; pCi/m3 -! 0.35 , 1969: Pre-op data for site 0.3 gg;-, g , I 1978 & 980:. Atrospheric . tests -. _ 0.25 - - - - - - - - - --- - - 1986: Chernobyl accident 0.2 ~~ - ' - --
= 0.15 - - - - - - - - - ---- - N -
O.1 Pd 0.05 - - -
+ - -
7 0-
' E 1969 1974 1976 1978 1980 1982 1984 1986 1988 1990 1975 1977 1979 1981 1983 1985 1987 1989 1991 1
E INDICATOR E CONTROL 1 NOTE: ALL DATA REPORTED IS MEAN VALUE
AR ARTIC ATE GR SS B T PCi/m3 0.02 -- - - - - - - - - --- --- ~~ j 00 - - - 1 3 5 7 9 11 13 15 17 19 21 23 25 2 4 6 8 10 12 14 16 18 20 22 24 26 WEEK # E IFDICATOR E CONTROL 1 im m m m m m m W M M M M M M M M M M m
M M M M M M M M m m m-W W -M M M M M M JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE GROSS BETA Figure 8.5 0.035 0.03 - - ---- O.025
-g-0.0." ,
- - -- 9-o.oi s 0 03 _
l B E E lE g 49 29 31 33 35 37 39 41 43 45 47 51 27 WEEK # l M INDICATOR E CONTROL
JAMES A. FITZPATRICK N.P.P. AIR PARTICULATE COMPOSITE Co-60 i Figure 8.6 pCi/m3 , 0.02
- LLD VALUE" REPORTED-NO POSITIVE DETECTION 0.015 -
h ' - - - - - - - - - - - - -- 1978 & 1980: ATMOSPHERIC TESTS i s 1 0.01 - w
! l t
e 0.005 - s a 1 e . . . . . . . . 0 --
# # " " 3 ' ' ' ' ' ' '
1978 1980 1982 1984 1986 1988 1990 l 1977 1979 1981 1983 1985 1987 1989 1991 t INDICATOR 4" CON 1ROL IM M M M M M M M M M M M M M M M M M
~
m se me m Ems Ems mas. sus sus sus sus ama e sus sum -eme sus' ens EEN JAMES A. FITZPATRICK N.P.P. AIR PAPTICULATE COMPOSITE Cs-137 Figure 8.7 pCi/m3 0.0 2 --
+ LLD VALUES REPORTED NO POSITIVE DETECTION :)
2 0.015 3 1978 & 1980: ATMOSPHERIC TESTL
; f 1986: CHERNOBYL ACCIDENT -
?
0.01 5 5 1 0.005 - - - j - r . . . j . . { . . 0- 1984 1986 1988 1990 1978 1980 1982 1983 1985 1987 1989 1991 1977 1979 1981 l 1 INDICATOR N CONTROL I
JAMES A. FITZPATRICK N.P.P. AIR l-131 Figure 8.8 pCi. 3 0.7
- LLD VALUES REPORTED '
O.6 - - - - - - - - - - -- -- - NO POSITIVE DETECTION O.5 - -- - isse:~CHERNbBYL AbCibENT O.4
-- - - - - - -~- ' - - - --
go 0.3 -
-l; ---- -- ---- - - - -- - -
e i i O.2 5l
~ -
! IEi O.1 - - -
1 O_ i - M M i i
= i i i i 1976 1977 1979 1981 1983 1985 1987 1989 1991 :
1976 1978 1980 1982 1984 1983 1988 1990 L INDICATOR PE CONTROL , 1 WW m m m m m - m m e e !
sem nas use amm aus mas aus. som - mun sum ums ams aus aus m A JAMES A. FITZPATRlCK N.P.P. MILK Cs-137 Figure 8.9 i 20
- LLD VALUES REPORTED i NO POSITIVE DETECTION 15 --
1986: CHERNOBYL ACCIDENT 1974-1977: NO CONTROL DATA 10 b 5 5 - - - - - 1 0-1975 1977 l-I? - 1979 1980 1981 1982 1983 1984 1985 1986 1987 1988 1989 1990 1991 1'. '7 4 1978 1978 E INDICATOR W? CONTROL . A r .R #
-_- + I Q On
L JAMES A. FITZPATRICK N.P.P. L MILK l-131 i Figure 8.10 pCi/L 16
- LLD VALUES REPORTED i 14 -
HO POSITIVE DETECTION * ' jg __ _ __ _ _ . _ _ _ _ - . _ . _ . __ ._ _ _ . _ . _ 1986: CHERNOBYL ACCIDENT ??
.10 - - - - - -- - -
R - 1974-1977: NO CONTROL DATA $ 8 -~-- b m m 1978 & 1980: ATMOSPHERIC TESTS h 6 -- - - - - - - - - - {$h -- 4 __ _ - . . _ . . _ _ . _ . . . _ _ _ _ , _ . . _ . . ~ . _ - . - . . . . . _ _.I g -_ _ - - - - _
, m , : , , , , , , , , , ,
o 1975 1977 1979 1981 1983 1985 1987 1989 1991 1974 1976 1978 1980 1982 1984 1986 1988 1990 INDICATOR #4 CONTROLt I M M M M M M - WB E4 W W M M M M
1%%EIBMMUQ sus ase we se amm amm som mas sum mum ums ums sus sus aus uns sus sua suam JAMES A. I ITZPATRICK NEP, f TLD DATA Figure 8.11 MREM /STD MONTH 10 9 8 7 -- 6 -- 7
~
F
~
j[= _ ,._ 5 - - [ 4 - - 3 - - l 1 2 - - _ _ h l _ _ _ _ _ _ _ _ _ - 4
' ' ' ' ' E--
0 1982 1984 1986 1988 1990 1974 1976 1978 1980 1991 1981 1983 1985 1987 1989 1975 1977 1979 M SITE BOUNDARY l i OFF-SITE SECTORS M CONTROL
I 9.0 QA/QC PROGRAM 9.1 PROGRAM DESCRIPTION I The JAFNPP Radiological Effluent Technical Specifications require that a summary of the results for participation in the Interlaboratory Comparison Program be included in the Annua Radiological Environmental Operating Report. Reference samples obtained from the US Environmental Protection Agency (USEPA) Cross Check Program are analyzed by JAFNPP Environmental Laboratory. Sample media analyzed for the intercomparison program includes those which are routinely obtained as part of the site radiological environmental monitoring program. I Sample results are compared to the USEPA reference results for accuracy and precision. The USEPA reports results in terms of normalized deviations from a l known value (NDKV). Interlaboratory results are acceptable by the USEPA if the laboratories NDKV is between plus three or minus three for each sample. I 9.2 PROGRAM RESULTS I The performance of the laboratory was acceptable in 1991. 40 out of 41 USEPA Cross Check Program samples analyzed at the site Environmental Laboratory were within three normalized deviations. All eight samples analyzed by the program l vendor laboratory were acceptable. Specific results for the USEPA Cross Check Program are presented in Tables 9-1 through 9-4 in this section. 'l 9.3 NONCONFORMITIES 1 l 9.3.1 One USEPA Cross Check sample analyzed by the site Environmental Laboratory was outside three normalized deviations. The sample, QA-91-103, was a gamma in water sample analyzed for Co-60, Zn-65, Ru-l 106, Cs-134, Cs-137 and Ba-133. Five isotope activities reported were within two normalized deviations, while the Ru-106 activity was -4.(M normalized deviations. The USEPA known activity for Ru-106 was 199 20 pCi/1. JAF I reported activities were 166 36, 161 15,130 22 pCi/l for an average of 152 pCi/1. 91
I The reason for the nonconformity was including an outlier (130 pCi/1) from the data in the final average. The sample was counted two times l each on four different detectors with the following results:
._p L #3 #4 #5 161 22 161 15 179 32 166 36 130 22 177 21 174 24 194 37 I
l The population average is 169 pCi/1. A Q-test of the 130 data point shows that is an outlier. g g Q = hh = h = 0.63 l This result is >0.554 for a 95% significance level. Deleting the 130 pCi/l and recalculating an overall average gives a g result of 173 pCi/1. Reporting an average of 173 pCi/l would have resulted in an normal 6 iation of -2.22, which is within the -3 to +3 NDKV, which is l acceptable. I I I I I I 9-2
TABLE 9-1 USEPA EN5!IRONMENTAL RADI0 ACTIVITY LABORATORY I INTERCOMPARIS0N STUDY PROGRAM GROSS BETA ANALYSIS OF AIR PARTICULATE FILTERS (PCI/ FILTER) l GROSS BETA ANALYSIS OF WATER (PCI/ LITER) l DATE JAF ENV ID NUMBER HEDIUM ANALYSIS JAF RESULT EPA RESULT NDKV (1) (2) (5) 01/91 QA 91-016 WATER GB 6 0.5(3) 55 0.46 6 0.5 I 7 0.5 ll 03/91 QA 91-025 FILTER GB 130 1(3) 12S 1 131 1 124 6 1.73 I 04/91 QA 91-033 WATER GB 105 1(3) 115 17 -0.82 10311 l 113 1 05/91 QA 91-035 WATER GB 46 0.5(3) 4615 1.15
-l 50 0.5 52 0.5 08/91 QA 91-086 FILTER GB 96 1.5(3) 92 10 0.58 l 95tl.5 95 1.5 1g 09/91 QA 91-099 WATER GB 20i0.5(3) 20 5 0.12 l 22 0.5 1910.5 53 0.5(3) 65 10 -2.02 l- 10/91 QA 91-112 WATER GB 53 0.5 54 0.5 i
,I I l 93
TABLE 9-2 USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY ! INTERCOMPARIS0N STUDY PROGRAM l
~,RITIUM ANALYSIS OF WATER (PCI/ LITER)
JAF ENV JAF EPA DATE 10 NUMBER MEDIUM ANALYSIS RESULT (1) RESULT (2) NDKV (5) l 02/91 QA 91-019 WATER H-3 4264 121(3) 4245 120 4418 4U -0.60 l - 4282 121 4400 50(4) 4418 442 0.45 4500 50 E i 4700 50 E 06/91 QA 91-063 WATER H-3 11200 160(3) 12480 1248 -2.10 E 10900 159 5 10800 159 13000 500(4) 12480 1248 0.72 13000 500 13000 500 l 10/91 QA 91-111 WATER H-3 2400 106(3) 2454 352 -0.59 2300 105 l-2300 105 2400 100(4) 2600 100 2454 352 0.23 l 2500 100 I I I I 9-4 E
I TABLE 9-3 USEPA ENVIRON 14 ENTAL RADI0 ACTIVITY LABORATORY I INTERC014 PARIS 0N STUDY PROGRA14 IODINE ANALYSIS OF WATER (PCI/ L. ITER) AND MILK (PCI/ LITER) JAF ENV JAF EPA l DATE ID NUMBER MEDIUM ANALYSIS RESULT (1) RESULT (2) NDKV (5) I QA 91-018 WATER I-131 85 3(3) 75 8 2.17 02/91 83 2 I 87 3 I I-131 61 4(3) 60 6 0.19 04/91 QA 91-034 MILK 58 20(4) 60 6 -0.58 I 08/91 QA 91-084 WATER I-131 20 1(3) 20 6 0.19 l 21 1 21 1 I 20 1(4) 20 6 -0.19 - 19 1 19 1 g 09/91 QA 91-100 MILK I-131 111 3(3) 108 11 -0.16 116 3 l 94 2 102 11(4) 108 11 0.26 l 106 16 121 12 I - I l 9-5
TABLE 9-4 I USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY INTERCOMPARISON STUDY PROGRAM l GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) AND AIR PARTICULATE FILTERS (PCI/ FILTER) JAF ENV JAF EPA g DATE ID NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV
"(1) (2) (5) g 02/91 QA 91-017 WATER Co-60 39 2(3) 40 5 -0.58 __
37 3 39 2 l Zn-65 151 7(3) 149 15 -0.15 139 10 153 7 l Ru-106 169 20(3) 165 32 186t19 -2.01 l 158 18 Cs-134 6 1(3) 85 -0.69 61 3 62 3 Cs-137 11 2(3) 85 0.23 5 - 82 5 712 Ba-133 73 3(3) 75 8 -0.43 78 5 6813 g 03/91 QA 91-025 FILTER Cs-137 38 3(3) 40 5 -0.92 37 3 g 37 3 04/91 QA 91-033 WATER Cs-134 19 1(3) 24 5 -1.39 g 20 1 21 2 Cs -137 2312(3) 25 5 -0.81 19 2 26 3 l 9-6 l
I TABLE 9-4 (CONTINUED) USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY l INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) AND AIR PARTICULATE Fri.TERS (PCI/ FILTER) l DATE1 JAF ENV ID NUMBER MEDIUM ANALYSIS JAF RESULT EPA RESULT (2) NDKV (5) (1) 04/91 QA 91-034 MILK Cs-137 54 4(3) 49 5 1.73 l 47 6(4) 49 5 -0.58 l 06/91 QA 91-062 WATER Co-60 10 2(3) 91 10 5 -0.12 10 1 Zn-65 114 6(3) 108 11 0.58 l g 117 7 5 110 5 Ru-106 123 27(3) 149 15 -0.73 I 143 20 162 17 Cs-134 10 1(3) 1515 -1.62 1112 10 1 Ig Cs-137 12 2(3) 14 5 -0.23 I 13 2 15 2 l Ba-133 59 3(3) 62 6 -1.35 lll 59 3 54 3 l' .- 08/91 QA 91-086 FILTER Cs-137 2613(3) 30 5 -0.46 28 3 l 32i3 ll 9-7
TABLE 9-4 (ConTInuEo) USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY I INTERCOMPARIS0N STUDY PROGRAM GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) l AND AIR PARTICULATE FILTtRS (PCI/ FILTER) JAF ENV- JAF EPA 3 DATE ID NUMBER MEDIUM ANALYSIS RESULT RESULT NDKV E (1) (2) (5) 09/91 QA 91-100 MILX Cs-137 28 3(3) 30 5 -1.15 26 3 26 5 g 31 4(4) 30 5 0.29 29 5 g 33 3 I 10/91 QA 91-103 WATER Co-60 2812(3) 29 5 -0.46 28 3 27 2 Zn-65 67 9(3) 69 6 73 7 -1.57 l 64 6 , 5 Ru-106 166 36(3) 199 20 -4.04 161 15 130 22 l Cs-134 9 4(3) 10 5 -0.69 72 h 82 Cs-137 8 3(3) 62 10 5 -0.81 ! 92 g Ba-133 95 6(3) 98 10 -1.04 91 4 5 9014 m I 9-8 g
l
- cJ -h TABLE 9-4 (ConTInuEo)
I USEPA ENVIRONMENTAL RADI0 ACTIVITY LABORATORY g INTERCOMPARIS0N STUDY PROGRAM l GAMMA ANALYSIS OF MILK, WATER (PCI/ LITER) l AND AIR PARTICbLATE FILTERS (PCI/ FILTER) I JAF ENV I DATE ID NUMBER MEDIUM ANALYSIS JAF-RESULT (1)- EPA RESULT NDKV (2) (5) 10/91 QA 91-112- WATER Co-60 19 2(3) 20 5 -0.46 lI 18 3 19i2 Cs-134 812(3) 10 5 -0.69 ll 73 911 Cs-137 12 2(3) 1115 0.92 17 3 l 1212 ,I l (1) Results reported as activity the error (1 sigma). l (2) Results reported as activ'+v the standard deviation of the error. l (3) Analyzed at the site Environmental Laboratory, i (4) Analyzed at a vendor laboratory. lI l (5) NDKV is the Normalized Deviation from Known Value as determined by the EPA. Values within the range of +3 and -3 indicate acceptable l t l results. I I I 9-9 g
l APPENDIX A l ENVIRONhiENTAL RADIOLOGICAL ASSESShiENT OF Tile hiARCll 18,1991 RELEASE OF RADIOACTIVE hiATERIAL
1.0 INTRODUCTION
l Appendix A has been added to the 1991 Radiological Environmental Operating Report to provide data and an environmental assessment relative to the hiarch 18, 1991 accidental release of radioactive material to the environment. This appendix contains g a description of the Radiological Environmental Assessment Plan implemented, summary tables of sample results for important environmental sample media, an I evaluation of the sample results and the dose to man assessm-n!. Analytical results are provided for samples collected beyond the protected (s;mity) orcas of the site between l hiarch 18,1991 and hiay 15,1991. A number of the sample media were collected as part of the routine Environmental Surveillance Program. These routine sample results can be found in Section 6.0 of the Radiologica' Environmental Operating Report. E t; 2.0 OVERVIEW Following the radiological events of hiarch 18, 1991, a Radiological Environmental Assessment Plan (REAP) was implemented. The Radiological Environmental Assessment Plan was impicmented to provide a systematic approach for determining the g radiological conditions at the FitzPatrick site and the radiological impact off site. The specific objectives of the plan were to: o Determine the amount of radioactive m.teriel that was released off site. o Determine the extent and levels of radiological contamination on-site and
#f site.
I 4 L A1
I o Evaluste the radiological impact off site to the general public in terms of dose to man from environmental pati: ways l o Provide environmental data and assessment for the restoration of , contaminated areas of tae site specifically the grounds and plant storm g desinage system, a To meet the cajectives of the REAP an Environmental Sampling and Analysis Program was conducted. This program was comprised of collecting appropriate environmental l samples, analyzing the samples to environmental levels and evaluating the analytical results. METIlODOLOGY l 3.0 Due to the nature of the release, the REAP focused on three specific areas: l
- 1. Aquatic pathways (off site) o Drinking water o Lake water o Firh o Shoreline sediment o Bottom sediment l
- 2. Terrestrial Pathways (off site) o Airborne radioactivity o Direct radiation o soil I
- 3. JAF Site Environs (on site) o Soil o "adiation instrumentation surveys
. g o Airborne radioactivity 5 A2 I
I 4.0 SAMPLES COLLECTED AND ANAliTICAL ItESULTS I l The samples that were collected and analyzed to rissess the levels of radioactivity that was potentially present in the environment are described below. The r amber and types of samples collected are summarized in Table 1. The specific analytical results are g provided in Table 2 and in the 1991 Radiological Environmental Operating Report. Sample locations are keyed to the map provided as Figure 1. 4.1 Aquatic Pathways (oft. site) I
- a. Drinking Water I The Oswego City water supply was sampled and ar.alyzed to determine if
'"di *ti"* * **'i"l *"" P'***"t in the water supply. Samples were collected i Ea from the water filtration plant on a routine basis from 03/20/91 to 04/24/91.
S'imples were taken from both the treated and untreated process streams at the treatment plant. In addition, samples were collected from supply points within the distribution system including the JAF city water supply. I The analytical results for all of the drinking water samples collected showed no presence of radioactive material above natural background. I
- b. Raw Lake Water Raw lake water samples were collected from a number of sample locations which included:
o JAF Inlet Canal o JAF Discharge Canal l 0 9 Mile Point Unit No.1 Inlet Canal o Lake Shore Grab Samples L These samples were collected to measure the possible levels of radioactive material in lake water in the vicinity of the site. Because the respective inlet canals for the power plants draw a significant amount of cooling water from Lake Ontario, samples from these locations are considered to be representative of raw lake water. Shoreline grab samples are considered to be more l representative of the near shore water column. A-3 l
The analytical results for all of the raw lake water samples collected showed no presence of radioactive material above natural background. l
- c. Lakr Ontario Fish To evaluate impact of the release on the fish pathway, a number of fish samples were collected and analyzed. Gill nets were used to collect game fish specimens. The nets were set weekly, weather permitting, in the off shore vicinity of the plant and near the Oswego Harbor. Game fish samples were also l
collected daily, when available, from the JAP and 9 Mile Point Unit #1 intake g traveling screen fish collection baskets. The analytical results for all the fish sampics collected and analyzed as part of the REAP showed no presence of radioactive material associated with the release. A number of the fish samples did show the presence of Cs-137. The l, presence of Cs 137 in the fish is the result of cesium deposited in the environment from past atmospheric nuclear weapons testing. The levels of Cs-137 measured in the fish samples is consistent with concentrations measured in fish samples collected in previous years as part of the routine Radiological E Environmental Operating Report. E
- d. Lake Ontario, Shoreline Sediment Samples l Shoreline sediment samples were collected once per week for four weeks. E Samples were co"ected at a total of nine locations cast and west of the site.
Sample locations were selected based on the availability of sediment for sampling. The analytical results for the showline sediment samples showed no detectable quantities of radioactive material above background with the exception of Cs-137. As noted for the fish sarnples, the presence of Cs-137 in these samples is the result of fallout from past atmospheric nuclear weapons testing and is documented in the annual Radiological Environmental Operating Report for the plant. l l l A-4 I I 1
I
- c. Bottom Sediment l One series of four bottom sediment sampics was collected. The samples were collected approximately 50 to 100 ft. offshore from the FitzPatrick Plant. The I samples were taken to determine if there was a build up of radioactive material in the near shore area.
The analytical results showed no detectable quantitles of radioactive material above background with the exception of Cs 137 and Co-60. The levels of Cs-l 137 and Co-60 are within the range of documented historical results and are not attributed to the release. I 4.2 Terrestrial Pathways i
- a. Soil l Approximately 77 soil samples were collected around the site to determine to what extent the radioactive material released was deposited. Samples were taken in areas of known deposition and at the site perimeter areas along roadways and other areas of potential contamination.
The soil sample results showed that no radioactive material associated with the release was deposited on soil beyond the protected (security) area, and are not included in the tables in this report. g b. Airborne Radioactivity g As part of the routine Environmental Moni:oring Program, the site maintains e a network of environmental air monitoring stations. Rese stations are equipped to collect representative samples of airborne radioiodine and airborne l particulates. Samples from these monitoring Flations are Collected on a weekly basis as part of normal surveillance schedule. Samples from the off-site ' l environmental air monitoring stations were collected on March 19th and the on-site air monitoring samples were collected on March 20th. Collections continued as routinely scheduled. I A5 l
1 I-None of the air monitoring samples showed detectable concentrations of radioactive material associated with the ;elease. The results for the air sampling program are presented on Table 6 5 through 6 9 of the 1991 g Radiological Environmental Ops.ating Report.
- c. Direct Radiation Thermoluminescent Dosimeters (TLDs) are used to measure direct radiation (gamma dose) in the environment. TLDs are located on site and at the site l
boundary. Additional TLDs are located off site. The badges were collected g durmg the last week of March and sent to a contractor lab for processing. The results for the first quarter TLD badges showed no significant increase in g radiation expostare beyond the site boundary. De TLD results for 1991 in E general are consistent with previes years. A detailed description of TLD
;.tonitoring programs can be found in Section 3.0 of the 1991 Radiological Environmental Operating Report. Specific results for the 1991 TLD program can be found in Table 610 also in the same report, g 4.3 JAF Site Envimns Parking Lot / Site Drahiage a.
I Samples were taken from the site outfall of the two main drainage ditches. These drainage ditches receive most of the storm run-off at the site. These E 5 samples were collected to evaluate the presence of radioactive material in the storm water run-off from the site. De analytical results for the samples collected from the site drainage ditches verified that radioactive material was r.ot contained in the run-off from the site. Results for these samples are included in this report in Table 2.
- b. Radiation Instrument Surveys I
Radiation instrument surveys were performed within the exclusion area of the site. The exclusion areas of the site are outside the protected (security) area and are accessible to the general public on a limited basis. The portion of the FitzPatrick site included in the assessment was encompassed by the Lake I A-6 I
_ _ . - _ - _ . . ~ _ _ _ - _ _ _ _ _ _ _ _ ._ I Ontario shore line on the north, l.ake Road on the south, the Niagara Mohawk /NYPA property line on the west and the Training Building access l road on the east. Surveys were made along every 200 ft. of road frontage. Surveys were also taken within each 200 ft. x 200 ft. section of paved parking lot crea. g The survey results for the exclusion area showed that no measurable levels of I radiation above background were detected outside the protected (security) area of the site. Results for these surveys are not included in this report. 5.0 DOSE EVALUATION g Dose calculations were performed using the estimated release activity of 5.15 E 2 Ci. I A computer dispersion model was used to determine the dilution factors for the exposure pathways ofinterest. The calculations included spacial and temporal averages l representing cor.:.1uous exposure over a three month period and the corresponding mean water concentrations. The primary dose analysis was based on the plaats Off Site Dose Calculation Manual (ODCM) methodology. The environmental pathways of g interest were the drinking water pathway and the fish consumption pathway. The potential exposure to the maximally-exposed individual as a result of the release of I material to the lake, was calculated to be as follows: I Radiation Pathway Age Group Oritan - Exposure (mrem) Drinking Water Child Total Body 0.0014 Infant Liver 0.0026 Fish Consumption Adult Total Body 0.057 Teen Liver 0.t2 TABIE RITERENCE MEMORANDUM.RCC-91007,oCR-91044. AMPMMINTOPT1lF RADIO! OO1 CAL CONst'OUIWCPS OF'nlE MARCil IR.1991 Rf1"A%F OF RADIOACHVH 1.lQUID 1U t AKE OVTARIO. DA1ED JUNE 27,1991 I
^"
1I
I It is obvious by the magnitude of the dose to man that the radiological impact of the release to the lake is insignificant. The sampling and analysis of environmental samples of lake water, drinking water supply and fish population further demonstrates the lack of dose to man from the release and support the validity of the :alculations. It can be l seen from the calculation and supporting environmental pathway sample results that the g doses are well below the regulatory guidelines and litnits and are only a small fraction of the annual dose to man resulting from natural background radiatloa. Il
6.0 CONCLUSION
The environmental assessment of the radiological release on March 18,1991, was implemented to determine the impact of the event on the environment and the resulting dose to man. An evaluation of the results indicates that there was no significant impact , ! to the off site environment. The radiological surveys show that there was no wide spread contamination. The majority of the radioactive material which was released from the plant was confined to the area adjacent to the building structures. The release of radic, active material to 12ke Ontario was the major impact to the local environment. l The resulting dose to man from this release is calculated to be 0.057 mrem to the whole body (adult) and 0,12 mrem to the liver (teen). These calculated doses are very small and of little significance when compared to the annual whole body dose rate of approximately 60 mrem per year from natural background radiation. 4 7.0 FIGURES AND TAllLES 7.1 Table 1 Sample Collection Summary Table This Table lists the types of samples that were collected as part of the Environmental Assessment Plan. Also listed are the number of samples collected and the map location number as illustrated on Figure 1. 7.2 Table 2 g Table 2 contains the analytical results for the off-site samples collected as part of the g REAP implementation. E i I A-8 I
I 7.3 Figure 1. Sample location Map l This map illusta.tes the locations of the off tite samples including; bottom sediment, water, shoreline sediment and air maaitoring stations. Samples collected within the site boundary are not noted on the map due to the scale. Maps illustrating the locations of g the on-site air monitoring stations and the TLD tocations can be found in Section 3.3 of the Radiological Environmental Operating Report. 1 I 1 1 l l I I 5 I I I l I l I A-? I
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.M- M M M. M M M M M M M M M M M M M M TABLE 1 ENVIRONMENTAL SAMPLE StDMARY FROM: March 18, 1991 TO: .May 15, 1991 SAMPLEiTYPE;- SAMPLE DESCRIPTION. _ MAP NUMBER
- NUMBER OF SAMPLES JAF Inlet Canal Samples 8 16 Water (Off-site) JAF Discharge Canal Daily Composite 8 15 City Water Samples 5 37 NMP 1 Inlet Canal Samples 7 16 Shoreline Grab S. ples 6 4 Site Drainage Samples NS 24 TOTAL: 112 4 25 y Fish (Off-site) JAF Quadrant 3 18 i
- 4. NMP Quadrant C Oswego Harbor Quadrant 2 2 l TOTAL: 4.5 Langs Beach 10 4 Shoreline 4 Sediment Bible Camp 11 i NMP-1 Shoreline 12 4 Sunset Beach 13 3 l 11 4 l Shcre Oaks Drive Beach Dempster Beach 15 4 l- 16 4 l
Ramona Beach 17 4 ! Slekirk Shores Beach Rainbow Shores Beach 18 4 TOTAL: 35 1 Bottom JAF Quadrant TOTAL: 4 Sediment Air Samples JAF Air Monitoring Stations: On-site NS TOTAL: 36 Off-site 19-26 TOTAL: 54 , NS - Not Specified
* - Figure 1 l
TABLE 2 CONCENTRATIONS OF GAMMA EHITTERS IN JAF INLET CANAL WATER SAMPLES RssutTs In UNITS OF pCI/HL i 1 SIGMA DATE: 03/20/91 DATE: 03/21/91 DATE: 03/22/91 DATE: 03/23/91 DATE: 03/24/91 ISOTOPE LOCATION: JAF: Inlet . LOCATION: JAF Inlet LUCATION: JAF Inlet LOCATION: JAF Inlet LOCATION: JAF Inlet Canal (04k) Canal (04k) Canal (04k) Canal (04k) Canal (04k) Cr-51 <6.62E-8 <8.73E-8 <7.65E-8 <6.07E-8 <5.41E-8 g Cs-134 <9.08E-9 <l.64E-S <1.17E-8 <1.07E-8 <l.43E-8 Cs-137 <7.10E-9 <l.12E-3 <l.03E-8 <l.01E-8 <l.01E-8 I Co-58 <9.21E-9 <1.15E-8 <8.24E-9 <9.12E-9 <9.11E-9 Mn-54 <7.87E-9 <1.02E-8 <l.07E-9 <1.0SE-8 <l.12E-8 Fe-59 <1.49E-8 <2.82E-3 <l.90E-8 <l.42E-8 <l.76E-8 l Zn-65 <l.65E-8 <3.34E-8 <3.80E-8 <3.00E-B <3.00E-8 Co-60 <6.69E-9 <1.76E-8 <1.76E-8 <1.26E-8 <l.15E-8 l l -c i M M M M M M M M M M M M M M M M M
aus aun aus sus uma aus ame ame ame :amm sua num aus ame uma ame uma sus som TABLE 2 (CONTINUED) CONCENTRATIONS OF gal #4A EHITTERS IN JAF INLET CANAL WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA DATE: 03/25/91 DATE: 03/26/91 DATE: 03/27/91 DATE: 03/28/91 DATE: 03/29/91 ISOTOPE LOCATION: JAF Inlet . LOCATION: JAF-Inlet LOCATION: JAF Inlet. LOCATION: JAF Inlet LOCATION: JAF Inlet Canal (04k) Canal _ (04k) Canal- (04k) Canal (04k) Canal-(04k) Cr-51 <9.81E-8 <6.89E-8 <7.97E-8 <6.43E-8 <l.07E-7 Y Cs-134 <l.56E-8 <7.5'E-9 <l.37E-8 <8.16E-9 <l.73E-8 M Cs-137 <l.51E-8 <8.23E-9 <1.19E-8 <9.20E-9 <l.40E-8 Co-58 <1.58E-8 <7.76E-9 <l.10E-8 <7.45E-9 <l.39E-8 Mn-54 <l.llE-8 <6.86E-9 <1.02E-8 <6.86E-9 <l.35E-8 , l Fe-59 <3.40E-8 <l.57E-8 <2.25E-8 <l.36E-8 <3.58E-8 In-65 <4.21E-8 <l.53E-8 <3.17E-8 <1.76E-8 <3.61E-8 Co-60 <2.37E-8 <l.32E-8 <l.23E-8 <8 87E 8
<l.86E-8 i
- l v_ ,
i
+ --_v - __ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ _ _
TABLE 2 (CONTINUED) CONCENTRATIONS OF GA M EMITTERS IN JAF INLET CANAL WATER SAMPLES RESULTS IN UNITS OF pCI/ML 1 SIGMA JATE: 03/30/91
. DATE: 03/31/91 DATE: 04/03/91 DATE: 04/10/91 DATE: 04/17/91 ISOTOPE- LOCATION: JAF Inlet LOCATION: JAF Inlet LOCATION: JAF Inlet LOCATION: JAF Inlet LOCATION: JAF Inlet
'. Canal' (04k) Canal -(04k) . Canal (04k) Canal (04k) Canal (04k)
Cr-51 <l.09E-7 <6.81E-8 <r 53E-8 <9.37E-8 <6.55E-8 > Cs-134 <1.73E-8 <1.06E-8 <9.68E-9 <l.14E-8 <l.03E-8 C Cs-137 <1.40E-8 <8.64E-9 <7.95E-9 <l.30E-8 <7.40E-9 Co-58 <l.39E-8 <9.36E-9 <7.75E-9 <l.00E-8 <9.84E-9 Mn-54 ,
<l.19E-8 <9.59E-9 <7.86E-9 <l.21E-8 <6.33E-9 Fe-59 <3.40E-8 <l.61E-8 <1.83E-8 <1.90E-S <l.97E-8 Zn-65 <3.82E-8 <2.23E-8 <2.06E-8
. <3.50E-8 <2.66E 8 Co-60 <1.08E-8 <1.02E-8 <8.86E-9 <1.52E-8 <7.18E-9 m
M
sus sus amm uma mas uma ses sus aus mum aus .aus aus amm aus mas uma aus ame TABLE 2 (CONTINUED'l CONCENTRATIONS OF GAIWA EMITTERS IN JAF INLET CANAL WATER SAMPLES RESULTS IN UNITS OF pCI/ML 1 SIGMA i DATE: 04/25/91 ISOTOPE LOCATION: JAF Inlet (BLANK) (BLANK) (BLANK) (BLANK) Canal (04k)
.e ;
Cr-51 <6.67E-8 f
> Cs-134 <9.62E-9 Cs-137 <9.08E-9 r
Co-58 '8.65E-9 t Mn-54 <5.93E-9 Fe-59 <l.73E-8 Zn-65 <l.75E-6 Co-60 <l.02E-8
TABLE 2 (CONTINUED) COM.6TRATIONS OF GAMMA EMITTERS IN JAF DISGiAET QNAL DAILY COMPOSITE WATER SAMPLES RESUt.U IN UNITS OF pCI/NL i 1 $IGMA DATE: 03/22/91 DATE: 03/24/91 DATE: 03/27/91 DATE: 03/27/91 DATE:03/21/91-LOCATION: JAF Diset.. LOCATION: JAF Disch. LOCATION: JAF Disch.
. ISOTOPE
- DCATION: JAF Disch. . LOCATION: JAF Disch. Canal Canal. -Canal Canal- Canal t Cap.(05g)
Comp.(05g) Ccap.(05g) Comp.(05g)
' Comp.((05g)
<1.11E-7 <6.36E-8 <6.87E-8 <6.52E-8 !
Cr-51 <5.85E-8
<1.37E-8 <1.07E-8 <1.11E-8 <1.30E-8 Cs-134 <1.13E-8
[ m
<1.35E-8 <8.56E-9 <8.41E-9 <7.68E-9 Cs-137 <8.41E-9
<1.70E-8 <9.19E-9 <8.93E-9 <6.51E-9 Co-58 <7.88E-9 cl.20E-8 <8.62E-9 <8.55E-9 <1.08E-B Mn-54 <9.06E-9 !
<3.05E-8 <l.44E-8 <1.92E-8 <2.18E-8 Fe-59 <1.57E-8
<3.83E-8 <1.60E-8 <l.95E-8 <2.42E-8 Zn-65 <2.30E-8
<2.05E-8 <1.02E-8 <1.02E-8 <l.15E-8 Co-60 <1.02E-8 m m amm aus amm aus mas sus aus mum aus sur sus as uma aus aus uma ame
aus aus mas sus sua aus mas aus sus aus aus aus aus aus e aus aus uma sus TABLE 2 (CONTINUED) CONCENTRATION 5 0F GAMMA EHITTERS IN JAF DISCHARGE CA!'AL DAILY COMPOSITE WATER SAMPLES RESULTS IN UNITS OF pCI/ML 1 SIGMA DATE: 04/08/91 DATE: 04/09/91 DATE:.03/31/91 DATE: 04/02/91 UATE:'03/29/91 LOCATION: JAF Disch. LOCATION: JAF Disch. LOCATION: JAF Disch. LOCATION: JAF Disch. canal ISOTOPE LOCATION: JAF Disch.. Canal Canal
. Canal' . Canal Comp.(05g) Cos:p.(059)
Comp.(05g) comp.(05g) Comp. (05g) .
<6.74E-8 <9.36E-8
<8.28E-8 <1.37E-7 Cr-51 <5.88E-8
<9.30E-9 <l.46E-8
<l.44E-8 <1.54E-8
> Cs-134 <8.44E-9 E <I.07E-8
<l.66E-8 <l.05E-8
<8.73E-9 <1.07E-8 cs-137
<d.98E-9 <l.29E-8
<8.97E-9 <l.58E-8 Co-58 <6.05E-9 I
<7.99E-9 <l.26E-8
<l.22E-82 <1.46E-8 Mn-54 <8.19E-9
<l.76E-8 <3.09E-8
<2.44E-8 <2.76E-8 Fe-59 <1.69E-B
<l.95E-8 <3.35E-8
<2.36E-8 <4.37E-8 Zn-65 <l.87E-8
<l.24E-8 <8.06E-9
<l.97E-8 <2.22E-8 Co-60 <l.13E-L
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAPHA EMITTERS IN CITY WATER SAMPLES RESULTS IN UNITS OF ACI/ML i 1 SIGMA DATE: 03/22/91 DATE: 03/22/91 DATE: 03/23/91 DATE: 03/23/91 3 ATE: 03/23/91 LOCATION: Oswego LOCATION: Oswego LOCATION: JAF STP LOCATION:. Oswego LOCATION: Oswego ISOTOPE-City Water City Water City Water City Water City Water
. Treated (Z1c) Raw (Zlb) Tap-(Q7m) Raw (Z1b) Treated (Z1C)
Cr-51 <6.32E-8 <9.31E-8 <6.74E-8 <1.08E-7 <6.47E-8
<l.39E-B <l.24E-8 <1.56E-8 <9.45E-9 > Cs-134 <7.80E-9 l
Cs-137 <7.92E-9 <9.36E-9 <l.07E-8 <l.23E-8 <9.19E-9 c6.59E-9 <l.46E-8 <8.68E-9 <l.74E-8 <7.13E-9 Co-58 Mn-54 <6.33E-9 <l.02E-8 <l.29E-8 <1.55E-8 <8.17E-9 i Fe-59 <l.62E-8 <2.09E-8 <1.91E-8 <2.27E-8 <l.76E-8 Zn-65 <l.75E-8 <3.65E 8 <2.55E-8 <3.61E-8 <l.39E-8 Co-60 <1.02E-8 <l.23E-8 <l.37E-8 <2.77E-8 <l.13E-8 M M M M M M M M M M M M M M M M M M M
ama mum nas uma mas meu aus sur aus ame aus sum amm sa som aus mas sus TABLE 2 (CONTINUED) CONCENTRATIONS OF GAINA EMITTERS IN CITY WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA DATE: 03/24/91T DATE: 03/24/S1 DATE: 03/24/91 DATE: 03/25/91 DATE: 03/25/91
- ISOTOPE LOCATION: JAF STP LOCATION: Oswego LDCATION: Oswego LOCATION: JAF STP LOCATION: Oswego
, City Water. City Water City Water City Water City Water Tap'(Q7m); Raw (Z1b) Treated (Z1c)' Tap (Q7m) Treated (Z1c) tr-51 <6.90E-8 <8.41E-8 <6.81E-8 <6.14E-8 <6.42E-8 > Cs-134 <8.99E-9 <1.52E-8 <1.13E-R <9.45E-9 <8.99E-9 I
Cs-137 <9.89E-9 <1.19E-8 <9.08E-9 <8.17E-9 <7.40E-9 i Co-58 <6.93E-9 <1.11E-8 <8.'4E-9 <9.40L-F <7.27E-9 Mn-54 <8.80E-9 <9.64E-9 <9.05E-9 <7.37E-9 <8.80E-9 i Fe-59 <1.65E-8 <1.91E-8 <1.35E-8 <1.90E-8 <1.56E-8 i In-65 <2.13E-8 <2.09E-8 <2.37E-8 <2.04E-8 <2.30E-8 , i Co-60 <9.56E-9 <1.05E-8 <7.18E-9 <9.56E-9 <7.18E-9 L
TABLE 2 (CCNTINUED) CONCENTRATIONS OF GA M EMITTERS IN CITY WATER SAMPLES RESULTS IN UNITS OF pCI/ML ! 1 SIGMA DATE: 03/25/91 DATE: 03/26/91 DATE: 03/26/91 DATE: 03/26/91 DATE: 03/27/91 ISOTOPE LOCATION: Oswego LOCATION: Oswego LOCATION: JAF STP , LOCATION: Oswe90 LOCATION: JAF STP City Water City Water City Water City Water City Water Raw;(ZIb) Raw (Z1b). Tap (Q7m) ~ Treated (Ile) Tap (Q7s) Cr-51 <7.70E-8 <9.06E-8 <5.87E-8 <6.46E-8 <7.07E-8
> Cs-134 <l . 25 E-8 <l.08E-8 <1.02E-8 <l.04E-8 <l.07E-8 bl Cs-137 <l.19E-8 <l.23E-8 <l.07E-8 <9.08E-9 <l.14E-8 Co-58 <l.11E-8 <l.15E-8 <9.11E-9 <9.17E-9 <9.95E-9 Mn-54 <l.17E-8 <1.30E-8 <7.24E-9 <9.30E-9 <9.75E-9 Fe-59 <l.91E-8 <2.26E-8 <1.76E-8 <l.74E-8 <l.60E-8 Zn-65 <3.17E-C <3.17E-8 <2.79E-8 <2.04E-8 <l.80E-8 Co-60 <l.23E-8 <l.23E-8 <l.55E-8 <l.02E-8 <1.37E-8 i
4
aus nas aus aus aus uma sus ans use mas aus aus aus amm ums mas aus sum uma TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN CITY WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA UATE: 03/27/91, DATE: 03/28/91 DATE: 03/28/91 DATE: 03/27/91 DATE: 03/27/91 LOCATION:. Oswego LOCATION: Oswego LOCATION: Oswego LOCATION: Oswego LOCATION: JAF STP City Water ISOTOPE City Water City Water City Water City Water Tap (Q7m) Treated (ZIc) Raw (Z2b) Treated (ZIc) Raw (Zlb)
<1.16E-7 <8.35E-8 <6.92E-8 Cr-51 <l.01E-7 <6.90E-8
<l.63E-8 <1.42E-8 <l.03E-8
> Cs-134 <2.92E-8 <1.28 8 l
M
<1.61E-8 <1.12E-8 <7.40E-9
<1.58E-8 <9.70E-8 Cs-137
<1.40E-8 <1.24E-8 <9.66E-9
<1.55E-8 <1.04E-8 Co-58
<l.12E-8 <7.6SE-9
<8.56E-9 <1.35E-8 Mn-Sa <l.26E-8
<3.05E-8 <2.10E-8 <I.57E-8 Fe-59 <3.10E-8 <l.94E-8
<3.39E-8 <2.59E-8 <2.37E-8
<5.43E-8 <3.15E-8 f Zn-65
<2.37E-8 <1.23E-8 <8.85E-9
<l.52E-8 <8.85E-9 Co-60 i
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN CITY WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA DATE: 03/29/91: DATE: 03/29/91 DATE: 03/29/91 DATE: 03/30/91 DATE: 04/03/91 ISOTOPE' LOCATION: JAF STP' LJCATION: Oswego- LOCATION: Oswego LOCATION:'JAF STP LOCATION: Oswego , 1 City Water? City Water City Water City Water City Water l -Tap (Q7m) : Raw (21b) Treated (Z1c) Tap (Q7m) Raw (Z1b) Cr-53 <6.13E-8 <9.57E-7 <5.45E-8 <5.88E-8 <9.21E-8
? Cs-134 <l .05E-c <1.12E-8 <8.16E-9 <9.21E-9 <l.29E-8 e
Cs-137 <9.72E-9 <l.04E-8 <6.79E-9 <8.96E-9 <l.51E-8 Co-58 <9.54E-9 <8.67E-9 <7.13E-9 <l.18E-8 <l.53E-8 l Mn-54 <l.08E-8 <l.03E-8 <l.09E-8 <l.33E-8 <l.28E-8 P t Fe-59 <l.75E-8 <2.04E-8 <l.76E-8 <l.21E-8 <2.30E-8 In-65 <2.67E-8 <l.59E-8 <1.87E-8 <2.55E-8 <3.14E-8 1 Co-60 <l.26E-8 <l.26E-8 <1.05E-8 <l.37E-8 <2.21E-8 (M M M M M M M M M M m m m m m
aus aus ums uns mas sus aus aus ame aus aus aus aus. aus aus uma amu TABLE 2 (CONTINUED) CONCENTRATIONS OF GA!EA EMITTERS IN CITY WATER SAMPLES REPULTS IN UNITS OF pCI/ML 1 SIcMA DATE:'04/03/91: DATE: 04/11/91 DATE: 04/11/91 DATE: 04/17/91 DATE: 04/17/91 ISOTOPE. LOCATION: Oswego LOCATION: Oswego LOCATION: Orwego LOCATION: Oswego LOCATION: Oswego City Water City Water. City Water City Water ' City Water Treated (Zlc) Raw (Z1b) Treated (Zlc) ~ Treated (Z1c) Raw (Zlb) Cr-51 <6.31E-8 <6.18E-8 <1.00E-7 <6.08E-8 <8.37E-8
> Cs-134 <1.16E-8 <9.49E-9 <l.60E-8 <9.31E-9 <1.48E-8 Cs-137 <9.72E-9 <1.07E-8 <1.70E-8 <8.17E-9 <8.30E-9 Co-58 <9.65E-9 <4.95E-9 <1.53E-8 <9.94E-9 <l.06E-8 Mn-54 <l.13E-8 <1.13E-8 <1.72E-8 <7.38E-9 <l.12E-8 Fe-59 <2.07E-8 <l.62E-8 <3,04E-8 <l.67E-8 <2.58E-8 i
Zn-65 <2.43E-8 <1.98E-8 <2.17E-8 <2.22E-8 <3.81E-8 Co-60 <l.37E-8 <1.15E-8 <1.65E-8 I <l.02E-8 <l.76E-8 - t
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EHITTERS IN CITY WATER SAMPLES RESULTS IN UNITS OF pCI/ML 1 SIGMA DATE: 04/24/91' DATE: .04/24/91 LOCATION: Oswego- (BLANK) (BLANK) (BLANK) ISOTOPE: LOCATION: Oswego, City Water City Water Raw.(Z1b) : Treated (Z1c) Cr-51 <5.82E-8 <1.12E-7
<1.41E-8
? Cs-134 <8.01E-9
\
I ($ Cs-137 <7.95E-9 <l.46E-8 1 Co-58 <8.34E-9 <l.57E-8 l
'Mn-54 <6.07E-9 <l.66E-8 Fe-59 <l.10E-8 <3.00E-8 l
Zn-65 <l.76E-8 <3.82E-8 Co-60 <7.87E-9 <2.05E-8 M M M M M M M m m - m m m M M IM M
uns sus num aus seu nas sus suas uns aus ums aus ums une sus amm aus 4 uma TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA ENITTERS IN NMP-1 INLET CANAL WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA DATE: 03/23/91 DATE: 03/24/91 DATE: 03/21/91 DATE: 03/22/91 DATE: 03/20/91-LOCATION: NMPI Inlet LOCATION: NMP1 Inlet LOCATION: HMP1 Inlet LOCATION: NMP1 Inlet
' ISOTOPE LOCATION: HMP1 Inlet canal (Zla) Canal (Zla) Canal (Zla)
.- Canal (Zla) Canal - (Zla) l
<9.68E-8 <9.43E-8
<1.11E-7 <6.48E-8 Cr-51 <6.14E-8 i
<l.03E-8 <1.42E-8 <l.02E-8 Cs-134 <l.26E-8 <l.63E-8
<l.07E-8 <1.16E-8
<1.56E-8 <9.35E-9 Cs-137 <1.19E-8
<1.01E-8 <l.16E-8 <l.IIE-8
<1.08E-8 <1.18E-8 Co-58
<1.17E-8 <1.22E-8
<1.48E-8 <l.21E-8 Mn-54 <9.22E-9
<2.58E-8 <2.28E-8
<2.28E-8 <1.79E-8 Fa-59 <2.07E-8
<2.80E-8 <3.51E-8
<4.03E-8 <2.56E-8 Zn-65 <l.98E-8
<l.15E-8 <1.52E-8 <l.65E-8
<l.15E-8 <2.51E-8 Co-60 i i
~
[ R [ F M NEM RE M
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN NMP-1 INLET CANAL WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA DATE:;03/25/91 DATE: 03/26/91 DATE: 03/28/91 DATE: 03/29/91 DATE: 03/29/91 ISOTOPE- LOCATION: NNPl Inlet LOCATION: NNP1 Inlet LOCATION: NMP1 Inlet LOCATION: MMP1 Inlet LOCATION: MMP1 Inlet Canal'. (Zla) Canal (Ila) Canal (Zla) Canal (Zla) Canal (Zla) Cr-51 <8.91E-8 <6.63E-8 <8.05E-8 <9.72E-8 <1.17E-7
- ;>- Cs-134 <1.28E-8 <1.03E-8 <1.28E-8 <l.30E-8 <l.76E-8 b :
Cs-137 <1.03E-8 <9.29E-9 <1.16E-8 <l.16E-8 <1.16E-8 Co-58 <1.36E-8 <9.63E-9 <1.IIE-8 <l.16E-8 <l.12E-8 ' i Mn-54 <6.84E-9 <8.53E-9 <9.05E-9 <l.22E-8 <l.49E-8 Fe-59 <2.94E-8 <1.65E-8 <1.91E-8 <1.93E-8 <2.0IE-8 Zn-65 <2.36E-8 <1.85E-8 <3.00E-8 <2.60E-8 <2.56E-8 Co-60 <l.65E-8 <1.34E-8 <l.39E-8 <l.76E R <a.86E-8 i W ' W W WW W m m m m
2 ~, . M M M M M M M '
- M M~ M ~M VJ A: C5" -
y' TABLE 2 (CONTINUED) CONCENiRATIONS OF GAMMA TiMITTERS IN NMP-1 INLET CANAL WATER SAi@ ' % RESULTS Ik UCITS OF pCI/ML i 1 3N.
'~
. n . ..
, . ? .. . '" ? . .
.g
?DATEl03/30/91J DATE:;l.03/31/916 DATE: "1/01/91 DATE: 04/08/91. DATE:l04/15/91u j
; ISOTOPE: LOCATIONONMP1Inketk. LOCATI9N: NMP1:! t.11et LOCATION: MMP1 Inlet LOCATIOM: MMP1 Inlet'
' :Cana1L(Zla) Lcanaly21()]torIATION:
,, ; NMPl Injet: Canal (Zla)-
JCanal)(Zla)L _ Canal'(Zla)
- s. ; .,c fi a
Cr-51 <6.11E-8 <6.20E-8 <6.75E-8 ca.08E-7 <6.51E-8
> Cs-134 <l.45E-8 <l.00E-8 <1.28E-8 <l.52E-8 <9.33E-9 Cs-137 <l.11E-8 d.29E-9 <9 72E-9 <l.40E-8 ' <8.23E-9 ,
Co-58 <9 7'E-9 <9.24E-9 <7.11E-9 <1.79E-8 <7.77E-9 Mn-54 <'s. 24E 9 <9.32E-9 <l.25E-8 <l.48E-8 <9.78E-9 Fe-59 <l.96E-8 <1.76E-8 <l.61F-8 <l.50E-8 <l.67E-8 Zn-65 <3.22E-S <1.86E-3 <2.28E-8 <3.61E-8 <1.97E-8 Co-60 <1.47E-8 <8.07E-9 <1.26E-8 <2.05E-8 <l.19E-8 i
-TABLE 2-(CCNTINUED)
CONCENTRATIONS OF GAMMA EMITTERS IN .4MP-1 INLET CANAL-WATER SAMPLES RMSULTS IN UNITS OF pCI/ML i 1 SIGMA B,
.' DATEfl04/22/9h [ ;
;(BLANK):
^
- '150 TOPE i L.0CATIONUISIPNInleti
(Bi.ANK)~ ^ .(BLANK). .(BUfet)-"
!.:Canall(Zla)' 2J w.-
g ,- q. g Cr-51 ' <7.14E-8 i D Cs-134 <l.03E-8 l 2 Cs-137 <1.05E-8 Co-53 <9.16E-9 i Mn-54 <7.37E-9 Fe-59 <1.35E-8 Zn-65 <2.21E-8 Co-60 <8.85E-9 ! I
Emu um er muu aus ' em mun sum muu aus e amm um: em.
~
I i TABLE 2 (CONTINUED) L CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE LAKE WATER SAMPLES 1 l RESULTS IN UNITS OF pCI/ML i 1 SIGMA DATE:IO3/19/91; DATE: 03/19/91.. DATE:~03/20/91 DATE: 03/21/91 LOCATION: Lake? Water'. U0CATIONii.akeWaterf LOCATICN: Lake Water LOCATION: Lake Water (BLANK) 1150 TOPE 1 "
.SUNY Oswego
, Sunset Bay":: Biblei:. Camp -
SUNY' Oswego'
;(7!f)i,
- (Z10)-; (Z10)
- (Zim)l ~~ .
<5.89E-8 <8.51E-8 <~ 20E-8 <6.32E-8 Cr-51
<8.70E-9 <1.57E-8 <1.16E-8 <1.20E-8 Y Cs-134
.8 '
<7.95E-9 <1.33E-8 <1.07E-8 <9.72E-9 Cs-137 .a V
Cn- 5, <6.02E-8 <1.16E-8 <8.74E-9 <1.07E-8 l
<7.87E-9 <1.22E-8 <1.03E-9 <1.17E-8 Mn-54
<1.67E-8 <2.71E-8 <2.18E-8 <2.38E-8 Fe-59
<1.76E-8 <3.18E-8 <2.9CE-6 <2.90E-8 Zn-65
<1.05E-8 <1.6SE-8 <1.37E-8 <1.02E-8 Co-60 ,
TABLE 2 (CONTINUED) CONCENTRATIONS OF GA N EMITTERS IN SITE DRAINAGE WATER SAMPLES RESULTS IN UNITS OF pCI/ML i 1 SIGMA
- 8 ATE:j03/24/913 DATE:503/24/91. DATE: 03/24/91L, DATE: 03/25/91 DATE: 03/25/91.
LOCATION: JAFEasti LOCATION:iJAF Easti LOCATION:: JAF. West (ISOTOPE 4 LOCATIONi$dAF/ WestLOCATION:/JIFJEasti @ .; Drainage 1 fDrainage.- . Boundary;
< Boundary 4 -
E0rainage ' . - y 1 Drain.(H1m) : Ditch ;(K8p).. Ditch.(Q8n)t: Ditch (Q8n)' . Drain.. (Hlm) p Cr-51 <5.85E-8 <6.79E-8 <7.25E-8 <6.98E-8 <8.59E-8 ! Y Cs-134 <1.09E-8 <2.02E-8 <1.59E-8 <1.50E-8 <1.64E-8 3 '
~
Cs-137 <8.73E-9 <1.012-8 <8.41E-9 <7.67E-9 ,
<1.19E-8
<9.16E-9 <9.96E-9 <9.63E-9 <7.86E <1.28E-8 Co-58 Mn-54 <9.53E-9 <9.20E-9 <7.37E-9 <8.26E-9 <1.26E-8
<1.84E-8 <1.90E-8 <1.65E-6 <1.82E-8 <2.41E-8 Fe-59
<2.87E-8 <2.90E-8 <3.25E-8 <3.25E-8 <4.33E-8 Zn-65 ,
<7.87E-9 <1.37E-8 <1.02E-8 <1.14E-8 <1.65E-8 Co-60 l
i lE -
sum num , num amm amm . : um uma uma um mum umh TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS ! IN SITE DRAINAGE WATER SAMPLES l RESULTS IN UNITS OF pCI/ML t 1 SIGMA l l DATE: .03/25/91f DATE: 03/29/91- DATE::03/29/91- DATE: 03/29/91 DATE: 03/30/91
' ISOTOPE i LOCATION: JAF-East LOCATIONi JAF West LOCATION: JAF East. LOCATION::JAF East- LOCATION: JAF East 7
- Drainage' . LBoundary-. Drainage -Drainage- .-Drainage; M
, ' Ditch;(K8p).. -
(Drain-(H1m). Ditch!(K8p). .. Ditch (Q6n)l Ditch (Q8n)_ . Cr-51 <7.16E-8 <5.96E-8 <6.35E-8 <1.19E-7 <7.64E-8 l Cs-134 <1.42E-8 <1.83E-8 <1.41E-8 <2.50E-8 <1.17E-8 [
~
Cs-137 <8.73E-9 <1.04E-8 <8.48E-9 <1.40E-8 <1.01E-8 Co-58 <8.06E-9 <1.18E-8 <1.01E-8 <1.46E-8 <9.65E-9 Mn-54 <6.49E-9 <1.12E-8 <9.53E-9 <1.42E-8 <6.86E-9 Fe-59 <1.91E-8 <?.48F-8 U.99E-8 <3.00E-8 <1.84E-8 In-65 <3.33E-8 <3.39E-8 <3.33E-8 <4.21E-8 .3.22E-8 Co-60 <1.13E-8 (i.46E-8 <1.32E-8 <2.50E-8 <1.19E-8
TABLE 2 (CSNTINUii.D) CONCENTRATIONS OF GAMMA EMITTERS IN SITE DRAINAGE WATER SAMPLES ResuLTS IN UNITS OF pCI/ML 1 SIGMA
, o..
DATE:(03/30/91.i; 'DATE: LO3/30/91! DATE: 04/01/91 DATE: 04/01/91 DATE::04/01/91 l ISOTOPE LOCATION: JAF West; LOCATION JAF' East LOCATION: JAF' East? LOCATION: JAF EastL LOCATION:?JAFWes5 J '
.Drai nage) . Drainage' -
- Drainage - Boundary-l Boundaryi).
Ditch'(Hlm
, ' Ditch L(K8p)) Ditch-(K8p): - Ditch'. (Q8n). ; Drain (Hlm)'
Cr-51 <6.07E-8 <8.95E-8 <7.37E-8 <9.73E-8 <8.13E-8 Cs-134 <1.32E-8 <2.44E-8 <1.55E-8 <2.51E-8 <1.79E-8. Cs-137 <7.92E-9 <1.03E-8 <1.10E-8 <1.35E-8 ,
<1.49E-8 Co-58 <7.85E-9 <1.43E-8 <9.66E-9 <1.46E-8 <1.32E-8 Mn-54 <8.26E-9 <1.26E-8 <8.17E-9 <l.27E-8 <9.65E-9 i Fe-59 <1.65E-8 <2.25E-8 <1.92E-E <3.22E-8 <2.82E-8 Zn-65 <2.29E-8 <5.11E-8 3.82E-8 <4.40E-8 <3.80E-8 Co-60 <1.02E-8 <1.05E-8 <1.26E-8 <2.37E-8 <1.39E-8
)
uma mas . aus sua sus mun sus sem ums aus - ums ses sus sus - TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN SITE DRAINAGE WATER SAMPLES RESULTS IN UNITS OF PCI/ML i l SIGMA DATE:f04/08/91.9 DATE:104/08/91, DATE: 04/08/91' DATE: .04/15/91: DATE: 04/15/91. A SOTOPEL LOCATION:LJAF< East; LOCATION:-'JAF Easti' LOCATION: JAF 'vott LOCATION:'JAF East:, LOCATION: JAF' East-(Drainagei.. .rDrainage .
' Boundary . Drainage; LDrainage
- w rDitch;(K8p). w Ditch;(Q8n)J iDrain;(Hlm) Ditch l-(K8p) .. Ditch.(Q8n))
..,. w Cr-51 <9.47E-8 <6.55E-8 (4.38E-8 <l.09E-7 <1.10E-7 >> Cs-134 <2.77E-8 <l.63E n <l.89E-8 <3.61E-8 <2.57E-8 I
Cs-137 <l.16E-8 :1.03E-8 <1.28E-8 <l.915-8 <l.70E-8
, Co-58 <1.43E-8 <8.40E-9 <l.03E-8 <1.32E-8 <l.33E-8 I
Mn-54 <1.42E-8 <9.30E-9 <9.75E-9 <l.62E-9 <1.35E-8 Fe-59 <2.81E-8 <l.74E-8 <2 27E-8 <3.58E-8 <2.82E-8 Zn-65 <4.20E-8 <3.41E-8 <2.90E-8 <6.13E-8 <5.35E-8 t Co-60 <l.87E-8 <l.08E-8 <l.37E O <2.37E-8 <2.37E-8 3
i TABLE-2 (CONTINUED) CONCENTRATICNS OF GAF % EMITTERS IN SITE DRAINAGE K 1 SAMPLES I RESULTS IN UNITS OF pCI/ML 1 $IGMA l
' DATE:;05/15/91 DATE: 05/15/91 DATE: 05/15/91..
DATE:04/15/91. ' LOCATION: JAF West _( BLANK) LOCATION:)JAF EastL LOCATION: JAF: East. LIS0 TOPE- LOCATION:iJAF-West. .Di; nage Boundary-Bobndaryi 1; Drainage-
' Ditch.(K8p) Ditch (Q8n). : Drain.(H1m)
, Drain (Hlm)
<1.07E-7 <9.34E-8
<6.60E-8 <6.57E-8 Cr-51
<1.55F-8 <i.50E-8
<l.54E-8 <2.51E-8 Cs-134
<1.31E-8 <1.59E-8
<1.28E-8 <l.24E-8 l Cs-137 l
<1.47E-8 <1.41E-8
<1.00E-8 <l.22E-8 Co-58 ._
<l.85E-8 <1.50E-8
<l.13E-8 <1.13E-8 Nn-54
<2.28E-8 <3.04E-8
<2.06E-8 <2.07E-8 Fe-59
<3.65E-8 <4.79E-8
<2.68E-8 <4.61E-8 2n-65
<l.67E-8 <1.42E-8
<1.15E-8 <1.17E-8 Co-60
, I i 1 M M M M M M M m m e am M M M
num aus aus men sus aus aus -amm sum - uma sus amm som uns .amm vem ums TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN FISH RESULTS IN UNITS OF PCI/GM i 1 SIGMA DATE: 03/21/91 DATE: 03/21/91 . DATE:.03/21/91: DATEb03/20/91 DATE: 03/21/91-LOCATION: Oswego- LOCATION:.JAF(Z1d) LOCATieN::JAF(04k) LOCATION: NNP1 (Zla)1 LOCATION: . Oswegr' -Harbor (Z1q)
' ISOTOPE. '
1 '. .~ . Harbor;t r ,. SPECIES: Lake Chubs SPECIES: Alewives SPECIES Lake Trout. SEPCIES Mewives SPECIES:-Lake Trout.
~
<3.32E-1 <2.55E-1
<2.14E-1 <3.03E-1 Cr-51 <2.03E-1
<4.45E-2 <5.16E-2
<3.65E-2 <4.96E-2 Cs-134 <3.22E-2
<4.79E-2 <4.46E-2
<3.67E-2 <4.80E-2 Cs-137 3.03E-211.06E-2
<4.55E-2 <4,13E-2 (4.0fE-2
<3.09E-2 <3.93E-2 l Co-58
<4.86E-2 <4.43E-2
<3.44E-2 <4.64E-2 Mn-54 <3.14E-2 l
<9.70E-2 <7.59E-2
<6.17E-2 <1.18E-1 Te-59 <7.05E-2
<1.20E-1 <1.36E-1
<8.33E-2 <1.24E-1 In-65 <7.59E-2
<6.36E-2 <4.70E-2
<4.84E-2 <5.51E-2 Co-60 <3.09E-2
TABLE 2 (CCNTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN FISH RESULTS IN UNITS OF PCI/GH i 1 SIGMA I DATEh03/22/91U .JATE:LO3/23/91) DATE: ~03/24/91.: DATE:103/24/91' DATE:03/25/91..-
~
LISOT0PE- 1.0CATIONENMP1(ZlaN LOCATIONiNMP11(Zlaji LOCATION: MMP1'.;(Zla) LOCATION: NMP1 (Zla)' LOCATION:! RPI (Zla)
..' ^. .~~.
SPECIQ:!SmallmouthT ~
. . . SPECIES: Sma11 mouth' j8assj SPECIES: White Perch- SEPCIES:Tellow Perch SPECIES:J Walleye . Bass We Cr-51 <2.30E-1 <6.69E-1 <9.42E-1 <3.00E-1 <1.94E-1 Cs-134 <3.80E-2 <8.60E-2 <1.78E-1 <4.68E-2 <2.92E-2 Cs-137 3.17E-2il.05E-2 <1.01E-1 <1.72E-1 <5.00E-2 2.29E-2il.04E-2 Co-58 <3.35E-2 <9.89E-2 <1.60E-1 <5.16E-2' <2.47E-2 Mn-54 <3.31E-2 <1.04E-1 <1.66E-1 <3.95E-2 <3.18E-2 Fe-59 <6.87E-2 <1.86E-1 <2.58E-1 <1.07E-1 <6.02E-2 ,
Zn-65 <9.13E-2 <2.80E-1 3.495-1 <1.29E-1 <8.20E-2 Co-60 <3.57E-2 <1.52E-1 <1.92E-1 <6.26F-2 <3.83E-2 I ., m m m m m m M M M M m W m m m m m
man amm aus mus mas uma uma suas < nas ama sus mas mas sus sus mas see TABLE 2 (CoHTINUEC) CONCENTRATIONS OF GAMMA EMITTERS IN FISH RESUt.TS IN UNITS OF PCI/GM i 1 SIGMA n DATE:j03/26/91 DATE:103/26/91- DATEi03/26/91- DATE: 03/26/91 DATE:03/27/91 LOCATION:NMP1.(Zla): LOCATIONiNMP2'(Z1p) LOCATION:JAF.(Ild); LISOTOPE LOCATIONsTJAFJ(Z14)] LOCATIONilJAF;(Ild)f '
~"f' SEPCIES: Smailmouth o .
SPECIES: 'trown Trout SPECIES: Brown Trout SPECIESO Lake Trouti SPECIES:2 Brown Trout: xBass4 Cr-51 <3.09E-1 <2.14E-1 <2.71E-1 <1.65E-1 <1.90E-1
<4.45E-2 <2.36E-2 M E-2
> Cs-134 <4.73E-2 <4.27E-2 < ~2 Cs-137' <4.37E-2 L 11E-211.07E-2 <4.34E-2 1.63E-217.81E-3 2.25E-2il.02E-2 j
<5.05E-2 <3.90E-2 <3.80E-2 <2.50E-2 <3.15E-2 Co-58
<5.19E-2 <4.20E-2 <3.50E-2 <2.41E-2 <3.70E-2 Mn-54
<1.03E-1 <8.15E-2 <9.56E-2 <6.05E-2 <6.97E-2 j Fe-59
<1.36E-1 <9.00E-2 <1.02E-1 <5.03E-2 <8.76E-2 Zn-65 l
<6.18E-2 <4.97E-2 <4.73E-2 <2.93E-2 <3 50E-2 Co-60 m A
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN FISH R SULTS IN UNyTS OF PCI/GM i 1 $IGMA DATEl03/28/91.3 DATE:l03/30/911 DATEil04/01/91:. DATE: 04/02/st DATE: 04/02/91 2
.ISOTdPE> LOCAT10N:UJAF.(04k)[ LOCATIONE NMP1 (Zla):.. LOCATIOM:1JAF(04k); LOCATION: M9P1(Zla)'. LOCATION: NMP1.-(Zla) -
g SPECIES:L Sv.allmouth?.* . .. . . . , ._ . .. ;
-. L.' SPECIES: . Smallmouth .~'
SPECIES:l Perch SEPCIES:jLake Trout'- SPECIES: White Perch Bass Bass) Cr-51 <3.46E-1 <4.89E-1 <1.97E-1 <7.35E-1 <3.77E-1 i. i Cs-134 <5.A5E-2 <9.97E-2 <2.58E-2 <l.24E-1 <5.72E-2 Cs-137 6.85E-2il.86E-2 <8.73E-2 <2.64E-2 <1.12E-1 ,5.77E-2!2.24E-2 Co-5E <5.77E-2 <8.56E-2 <2.74E-2 <l.15E-1 < 5. 23 E-2 y i Mn-54 <5.54E-2 <9.33E-2 <2.70E-2 <9.09E-2 <5.14E-2
<1.23E-1 < 1. 55E ', <6.92E-2 <2.35E 1 <l.19E-1 !
Fe-59 Zn-65 <1.46E-1 <2.10E-1 <7.05E-2 <3.28E-1 <l.53E-1 Co-60 <6.29E-2 <9.31E-2 <4.12E-2 <1.38E-1 <6.46E-2 i - . _ M M M M M W m MS M M MW m m e e m e e
~
sum amm see aus aus aus . sue ame amai muu aus a m- e ama am TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EHITTERS IN FISH RESULTS 1N UNITS OF PCI/GM 1 SIGMA DATEi 04/04/91; DATE: 04/05/91.- DATE: '04/09/91 DATE:i.04/04/91: DATE: .04/04/91-LOCATION: JAF (Z1d) LOCATION: JAF=(Ild) LOCATION: JAF.(ZId) 1150 TOPE LOCATIONiJAF(04k) LOCATIONi JAF/( Id):
^~~
SEPCIES: Rainbow SPECIES:' Chinook
.. ~l .
Trout . Salmon ~ SPECIESi Brown Trout SPECIESi Lake Troute SPECIES: Brown Trout ~
~
<2.48E-1 <2.23E-1 <2.49E-1 Cr-51 <1.93E-1 <2.02E-1
<4.07E-2 <3.22E-2 <3.82E-2 Cs-334 <3.09E-2 <4.19E-2
<4.21E-2 <3.14E-2 <3.44E-2 Cs-137 2.05E-218.35E-3 <3.39E-2 i
<3.80E-2 <3.02E-2 <3.73E-2 Co-58 <2.63E-2 <3.34E-2
<3.92E-2 <3.13E-2 <3.57E-2 Mn-54 <2.84E-2 <3.65E-2 i
<9.32E-2 <6.87E-2 <8.71E-2 Fe-59 <6.04E-2 <7.62E-2
<9.00E-2 <1.18E-1 <8.35E-2 <l.03E-1 Zn-65 <7.48E-2 ,
<5.27E-2 <3.78E-2 <4.83E-2 Co-60 <3.40E-2 <4.27E-2
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN FISH RESUt.TS IN UNITS OF PCI/GM i 1 SIGMA DATE:704/09/')1; DATE 4/09/91.' DATE: 04/10/91- DATE: 04/10/91' DATE: 04/11/91-ISOTOPE LOCATION:.JAF..(Z1d)' LOCATION::HMP1?(Zla) LOCATION: NMP1(Zla) ' LOCATION: NMP1.(Zla) LOCATION: JAF (Zid)- SPECIES:-White &
~
SPECIES: Rainbown ~ SPECIES: Lake Trout' SPECIES:: White Perch SEPCIES: .White Perch Trout -Yellow Perch Cr-51 <1.95E-i <8.64E-1 <1.05E+0 <2.06E-1 <6.92E-7 Cs-134 <2.93E-2 <1.30E-1 <1.64E-1 <4.21E-2 <1.02E-7 Cs-137 2.61E-219.91E-3 <1.24E-1 7.49E-212.83E-2 <3.33E-2 (8.64E-8 Co-58 <2.80E-2 <1.09E-1 <1.73E-1 <3.46E-2 <8.60E-8 Mn-54 <2.50E-2 <l.10E-1 <1.54E-1 <3.29E-2 <9.13E-8 Fe-59 <6.60E-2 <2.80E-1 <3.18E-1 <8.26E-2 <1.74E-7 In-65 <8.38E-2 <3.05E-1 <4.31E-1 <8.58E-2 <2.58E-7 Co-60 <3.38E-2 <1.37E-1 <1.77E-1 <4.63E-2 <1.11E-7 M M M M M M M M M' M M M m m m m m. m m
mas ame amm aus sum .ame .aus mas ens :aun amm aus mum seu nas - num aus TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN FISH RESULTS IN UNITS OF PCI/GM i 1 $1GMA DATE:'04/11/91- DATE:'04/12/91 DATE: 04/12/91 DATE: 04/12/91 DATE:.04/12/91
- ISOTOPE LOCATION: JAF(Z1d)~ LOCATION:~JAF(Z1d)
LOCATION:'JAF-(Z1d) LOCATION: JAF-(Zid) LOCATION: JAF(Z1d) SPECIES: White T ~ SEPCIES:' Sr.a.llmouth SPECIES: Yellow Yellow Perch SPECIES:1.ake Trout- Bus 'ECIES: White Perch Perch' Cr-51 <3.36E-1 <1.67E-1 <3.82E-1 <3.20E-1 <7.57E-1
>> Cs-134 <6.66E-2 <2.4SE-2 <5.01E-2 <4.65E-2 <1.25E-1 ib
'+' Cs-137 <6.06E-2 2.20E-218.47E-3 <5.44E-2 3.65E-211.41E-2 <l.13E-1 i
~
Co-58 <5.69E-2 <2.56E-2 <4.34E-2 <5.11E-2 <1.13E-1 Mn-54 <6.57E-2 <2.39E-2 <4.64E-2 <4.96E-2 <1.17E-1 Fe-59 <l.17E-1 <5.44E-2 <9.94E-2 <9.17E-2 <2.76E-1 In-65 <1.49E-1 <7.53E-2 <1.41E-1 <1.11E-1 <2.57E-1 Co-60 <7.75E-2 <3.42E-2 <6.17E-2 <5.69E-2 <1.75E-1
TABLF. 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN FISH RESULTS'IN UNITS OF PCI/GM i 1 SIGMA DATE:[04/12/91f DATE:'04/12/91L DATE: '04/15/91 PATE: 04/16/91! DATE:.04/17/91
? ISOTOPE LOCATION 1NMP1}(Zla); LOCATIONpNNPl.-(Zla){ LOCAT!0N: NMP1(Zla) : LOCATION: NMP1-(Zla) LOCATION:'JAF (04k)
SPECIES:itYellow + SEPCIES:' Rainbcw. .. SP2 TIES:LYellow SPECIES: Ciscoi , {Perchi ' TroutL SPECIES:.Prown Trout' ~ Perch:
<2.67E-1 <1.39E+0 <3.73E-1 <2.02E-1 <6.66E-1 Cr-51 Cs-134 <3.84E-2 <2.01E-1 <5.80E-2 <3.30E-2 <1.06E-2 Cs-137 <3.50E-2 <1.93E-1 <5.15E-2 <2.83E-2 9.60E-213.50E-2 Co-58 <3.37E-2 <2.06E-1 <5.61E-2 <3.17E-2 <8.92E-2 Mn-54 <3.65E-2 <1.99E-1 <5.65E-2 <2.90E-2 <9.86E-2 l
Fe-59 <8.60E-2 <4.91E-1 <1.19E-1 <5.88E-2 <2.25E-1
<5.02E-1 <1.40E-1 <7.76E-2 <2.70E-1 Zn-65 <9. '32 E-2
<1.27E-1 I Co-60 <4.29E-2 <2.41E-1 <7.06E-2 <3.42E-2 l
IM M M M M M M m m m m m m m mm e e
ame' sus cum um aus sem num uma sus mum mas som uma saa uma sus mas man TABLE 2 (CONTINUED) C0t!CENTRATIONS OF GAMMA EMITTERS IN FISH RESULTS IN UNITS OF PCI/GM i 1 SIGM DATE: 04/18/91 DATE: 04/19/91 DATE: 04/19/91 DATE: 04/18/91, DATE: 04/18/91 LOCATION: JAF(Z1d) LOCATION: JAF(ZId) LOCATION: JAF'(Z1d). ISOTOPE' LOCATION:JAF:(Ild)1 LOCATION:-JAF(Ild)- ' SPECIES: Smallmouth SPECIES: White Perch SEPCIES: Brown Trout Bass SPECIES: Lake Trout-SPECIES: Lake Trout;
<2.19E-1 <6.20E-1 <2.29E-1 Cr-51 <2.10E-1 <5.35E-1
<3.74E-2 <1.03E-1 <4.16E-2
>> Cs-134 <3.51E-2 <8.24E-2 i
<7.58E-2 2.87E-211.24E-2 1.15E-113.24E-2 2'.69E-2il.04E-2 Cs-137 <3.13E-2
<3.91E-2 <8.95E-2 <4.05E-2 Co-58 <3.15E-2 <7.44E-2
<4.37E-2 <1.05E-1 <3.96E-2 Mn-54 <3.26E-2 <I.09E-2
<8.36E-2 <2.26E-1 <6.74E-2
, Fe-59 <6.46E-2 <1.47E-2
<9.53E-2 <2.22E-1 <8.54E-2 Zn-65 <7.96E-2 <2.28E-1
<3.97E-2 <1.51E-1 <4.68E-2 Co-60 <3.78E-2 <8.91E-2 a
I TABLE 2 (CONTINUED) CONCENTRATIONS OF CAMMA EMITTERS IN SNORELINE SEDIMENT 1 SIGMA RESULTS IN UNITS Of PCI/GM (WET) I DATE: 03/27/91. DATE: 03/27/91-DATE: 03/27/91 DATE: 03/27/91 DATE:: 03/27/91 ' LOCATION:~ B1ble Camp LOCATION: Shore Oaks LOCATION: Selkirk:
.ilS0 TOPE . LOCATION:JRomona:. .
LCCATIOrd: Dempster?._ - (Z1g) - '5nores (Ilj) Beach l-(Z1h) -(21f) Beach '(211) .
<3.95E-1 <2.72E-1
<2.86E-I <2.80E-I Cr-51 <2.61E-1
<1.07E-1 <8.36E-2
<7.04E-2 <5.23E-2
<4.49E-2
> Cs-134 6 1.46E-712.72E-2 3.71E-Zil.73E-2 1.07E-111.62E-2 ' 18E-111.86E-2 Cs-137 6.76E-211.52E-2 ,
<6.53E-2 <4.89E-2
<4.39E-2 <4.25E-2 Co-58 <3.38E-2
<6.83E-2 <5.79E-2 l <2.26E-2 <3.60E-2 Mn-54 <3.35E-2
<1.69E-1 <1.48E-1
<1.02E-1 <9.05E-2 Fe-59 <7.71E-2
<2.83E-1 <I.76E-1
<1.43E-1 <!.52E-1 Zn-65 <1.18E-1
<8.25E-2 <7.14E-2
<4.88E-2 <5.8462 Co-60 <3.32E-2
aus ses :mus sus aus uma uma amm man amm aus sum mas meia sus num aus amm amm TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN SNORELINE SEDIMENT Rs.SULTS IN UNITS OF PCI/GM (WET) 1 SIGMA
.DATE: 04/02/91- DATE: 04/02/91 DATE: 04/02/91 DATEt 03/27/91L DATE: 03/27/91-L0r.ATION: Langs LOCATION: 81ble Camp ~ LOCATION: NMP1 (Z11) ilS0 TOPE LOCATION:} Rainbow . LOCATION:HMPl~(Z11)
(Z1f).
~~
1 Shores'(Z1k) Beach (Zie)
<3.05E-1 <3.84E-1 <4.99E-1 Cr-51 <4.17E-1 <2.64E-1
<7.60E-2 <1.02E-1 <1.25E-1
>- Cs-134 <1.01E-1 <6.05E-2 b
<5.22E-2 1.23E-112.26E-2 3.68E-113.76E-2 Cs-137 4.47E-2il.82E-2 2.6SE-112.07E-2
<4.15E-2 <6.46E-2 <8.06E-2 Co-58 <6.54E-2 <3.32E-2
<3.43E-2 <4.59E-2 <6.19E- <7.31E-2 Mn-54 <6.70E-2
<1.27E-1 <1.63E-1 <1.93E-1 Fe-59 <1.51E-1 <8.42E-2
<1.96E-1 <2.51E-1 <2.63E-1 Zn-65 <2.17E-1 <1.3]E-1
<6.12E-2 <7.52E-2 <1.08E-1 Co-60 <9.30E-2 2.66E-211.48E-2 o 1
TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITIERS IN SHORELINE SEDIMENT RESULTS IN UNITS OF PCI/GM (WET) 1 SIGMA DATE:~04/02/91. DATE:04/02/91l DATE: 04/02/91 DATE: 04/02/91 DATE: 04/02/91l LOC % TION: Shore Oaks. LOCATION: Dempster LOCATION: Ramona' LOCATION: Selkirk
.150TCPE- LOCATION::Sunoet Shores (Z1j)
- Beach 1(Zim) _ f(Zig) ' Beach (Z1h) . Beach (Z11)
<4.59E-1 <3.04E-1 <3.18E-1 <3.20E-1 Cr-51 <4.36E-1
<1.18E-1 <5.45E-2 <5.97E-2 <8.77E-2
> Cs-134 <l.29E-1 N
1.34E-li2.68E-2 <5.33E-2 8.09E-Zil.70E-2 6.20E-2il.76E-2 Cs-137 7.64E-212.41E-2
<7.07E-2 <4.39E-2 <4.26E-2 <4.85E-2 Co-58 <7.54E-2
<7.48E-2 <5.80E-2 <4.35E-2 <6.19E-2 Mn-54 <7.05E-2
<l.60E-1 <1.19E-1 <l.13E-1 <l.54E-1 Fe-59 <1.76E-1 ,
<2.40E-1 <l.89E-1 <l.69E-1 <2.13E-1 In-65 <2.63E-1
<9.07E-2 <6.06E-2 <5.24E-2 <7.59E-2 Co-60 <1.00E-1 M M M M M M M M M M M M m m m m m m a
1 mas sus sum oss uns sus uma sus aus amm see aus uma see mas sum amm uma uma l TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT RESULTS IN UNITS OF PCI/GM (WET) 1 SIGMA DATE:04/10/91-' DATE: 04/10/91 DATE: 04/10/91 DATE: 04/02/917 DATE: 04/10/91 LOCATION:: Rainbow - LOCATION:-NMP1(Z11) LOCATION: Sunset ISOTOPE- LOCATION:RaihbowL LOCATION:~Selkirk? . ~ Beach (Zim) 1 Sh' ores l.(Z1k); ;Shoresf(ZIj)/ iShores (Z1k)
<3.83E-1 <3.81E-1 <4.01E-1 Cr-51 <2.74E-1 <2.93E-1
<1.19E-1 <9.69E-2 <1.07E-1 Cs-134 <5.61E-2 <6.33E-2 P
8.93E-2il.94E-2 4.04E-112.70E-2 6'.47E-212.36E-2 Cs-137 2.27E-2il.32E-2 6.36E-2il.52E-2
<5.98E-2 <5.21E-2 <6.28E-2 Co-58 <4.00E-2 <4.27E-2
<7.87E-2 <5.69E-2 <6.20E-2 Mn-54 <4.32E-2 <4.66E-2
<1.69E-1 <l.32E-1 <l.57E-1 Fe-59 <8.49E-2 <1.07E-1
<2.23E-1 <2.09E-1 <2.44E-1 21-65 <1.39E-1 <l.64E-1
<8.43E-2 <5.98E-2 <7.75E-2 Co-60 <4.16E-2 <5.01E-2
TABLE 2 (CCNTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN SHORELINE SEDIMENT RESULTS IN UNITS OF PCI/GM (WET) i 1 SIGMA r,- .- DATE l04/10/91; DATE: 04/10/91; DATE: 04/10/91- DATE: 04/10/91- DATE: 04/10/91 ISOTOPE LOCATION: Langs Beach LOCATION: Bible Camp LOCATION: Shore Oaks LOCATION: Dempster' LOCATION: Ramona ((Z1e) f(Z1f) 7(Z1g) Beach (Z1h) Beach (Z11) Cr-51 <3.47E-1 <3.89E-1 <3.61E-1 <3.79E-1 <4.18E-1 P Cs-134 <8.40E-2 <9.70E-2 <9.28E-2 <1.03E-1 <9.98E-2 Cs-137 <4.85E-2 1.31E-112.53E-2 1.32E-li2.24E-2 <5.82E-2 8.86E-212.25E-2 Co-58 <4.28E-2 <5.78E-2 <5.59E-2 <5.62E-2 <5.15E-2 Mn-54 <4.44E-2 <6.08E-2 <5.48E-2 <5.39E-2 <5.59E-2 Fe-59 <l.09E-1 <1.29E-1 <1.53E-1 <l.25E-1 <l.17E-1 Zn-65 <1.79E-1 <2.18E-1 <2.46E-1 <2.07E-1 <2.15E-1 Co-60 <5.36E-2 <5.94E-2 <7.23E-2 <6.67E-2 <7.37E-2
ama. ame ums. sme aus mas 'une uma man amm suas uns amm-l TABLE 2 (CONTINUED) CONCENTRATIONS OF GAMMA EMITTERS IN BOTTOM. SEDIMENT RESULTS IN UNITS OF PCI/GM (WET) : 1 SIGMA l DATE:'03/20/91; DATE: 03/20/91 DATE: 03/20/91- DATE: 03/20/91 LIS0 TOPE LOCATION:* JAF West- LOCATION:* JAF. LOCATION:* JAF. LOCATION:* JAF East (BLANK) LCenter West Center East ! Cr-51 <2.51E-1 <3.61E-1 <3.21E-1 <2.73E-1 l j Cs-134 <4.70E-2 <8.63E-2 <5.69E-2 <7.26E-2 b Cs-137 2.82E-lil.79E-2 4.09E-li2.81E-2 4.91E-li2.86E-2 3.80E-li2.30E-2 Co-58 <3.84E-2 <5.79E-2 <5.08E-2 <4.23E-2 Mn-54 <3.59E-2 <4.76E-2 <5.81E-2 <3.64E-2 Fe-59 <7.42E-2 <1.19E-2 <l.'3E-1 <l.08E-1 2n-65 <1.24E-1 <2.00E-2 <l.87E-1 <l.51E-1 Co-60 6.26E-2il.12E-2 8.58E-2il.83E-2 9.02E-2il.71E-2 5.69E-2il.25E-2 o Collected at the JAF East and West out falls and equal distance between each out fall. _ __ - _ _ _ - _ _ _ _ _ _ - _ - - - - _ - _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ - _ -}}