ML20138H434
| ML20138H434 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/31/1996 |
| From: | Conway J, Rademacher N NIAGARA MOHAWK POWER CORP. |
| To: | NRC OFFICE OF INFORMATION RESOURCES MANAGEMENT (IRM) |
| References | |
| NMPE-0017, NMPE-17, NUDOCS 9705070177 | |
| Download: ML20138H434 (156) | |
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s a NIAGARA MOHAWK 1 GENERATI0N M M POMMCLEAR SWMLAKE ROAD, P.O. BOX 63, LYCOMING, NEW YORK 13093 BUSINESS GROUP April 30,1997
. NMPE 0017 U. S. Nuclear Regulatory Commission Attn: Document Control Desk
- Washington, DC 2055S l
j RE: Nine Mile Point Unit 1 Nine Mile Point Unit 2 Docket No. 50-220 Docket No. 50-410 4
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Subject:
Tmnsmittal of1996 Annual Radiological Envimnmental Opemting Report Gentlemen:
In accordance with the Technical Specifications for Nine Mile Point Nuclear Station Unit 1
- and Unit 2, we are enclosing the Annual Rndinlogien1 Environmental Ooersting Report for l j the period January 1,1996 through December 31,1996. !
Any questions concerning the enclosed report should be directed to Carey M. Merritt, Supervisor Environmental Protection at Nine Mile Point at (315) 349-4200.
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D T[w Norman L. Rademacher f/hn f T. Conway Plant Manager, Unit 1 Wlant Manager, Uni i
/cmk Enclosure l l
xc: Mr. H. J. Miller, Regional Administrator, Region 1 Mr. S. S. Bajwa, Acting Director, Project Directorate I-1, NRR Ifl
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Mr. B. S. Norris, Senior Resident Inspector ,
Mr. D. S. Hood, Senior Project Manager, NRR l Records Management )
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9705070177 961231
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ANNUAL ;
RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT 1 h \
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NINE MILE POINT NUCLEAR STATION I
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I NIAGARA MOHAWK POWER CORPORATION
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING RFPORT
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January 1,1996 - December 31,1996 for NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63
[ Docket Number 50-220
[ and lNE MILE POINT NUCLEAR STATION UNIT 2
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Facility Operating License NPF-69 Docket No. 50-410
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TARY R OF CONTLQ f
Page LIST OF TABLES ii LIST OF FIGURES vi
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1.0 INTRODUCTION
1 2.0 AQUATIC SAMPLES 5 I. Shoreline Sediment 6 II. Fish 8 III. Surface Water 11
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3.0 DIRECT RADIATION 15
[ 4.0 TERRESTRIAL SAMPLES 22
( I. Air Particulate / Iodine 23 II. Milk 27 III. Food Products 30 f IV. Land Use Census 31 5.0 INTERLAf 9RATORY COMPARISON PROGRAM 33 6.0 HISTORICAL ENVIRONMENTAL SAMPLE DATA 37 7.0 CHANGES AND EXCEPTIONS TO THE PROGRAM 39
8.0 CONCLUSION
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9.0 GENERAL REFERENCE MATERIAL 44 10.0 DATA TABLES - 1996 47 11.0 FIGURES 142
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T TRT OF TART FR Table No. Content Page Table 1 Sample Collection and Analysis, Site Radiological
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Environmental Monitoring Program - Aquatic Program and Direct Radiation 48
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Table 2 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program - Tsustri.1 Program 49
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Table 3 1996 Environmental Sample Imations 50
[ Table 4 Radiological Environmental Monitoring Program Annual Summary 54
( Table 5A Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/g-dry) 57 Table SB Concentration of Gamma Emitters in Shoreline Sediment Camples (pCi/kg-dry) 58
[ Table 6A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 59 Table 6B Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet) 61 Table 7 Concentration of Gamma Emitters in Surface Water Samples (pCi/ liter) 63 Table 8 Conu:ntration of Tritium in Surface Water Samples (pCi/ liter) 68 Table 9A Direct Radiation Measurement Results-mrem / Standard Month 69 Table 9B Direct Radiation Measurement Results-mrem / Quarterly Period 73 Table 10 Environmental Airborne Particulate Samples - Offsite
( Stations, Gross Beta Activity 77 Table 11 Environmental Airborne Particulate Samples - Onsite
[ Stations, Gross Beta Activity 79
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T MT OF TART FR (Continued)
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Table No. Content Eage Table 12 Concentration of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples 81 Table 13 Environmental Charcoal Cartridge Samples - Offsite
[ Stations,I-131 Activity %
Table 14 Environmental Charcoal Cartridge Samples - Onsite Stations,I-131 Activity 98 Table 15 Concentration of Gamma Emitters in Milk (pCi/ liter) 100 Table 16 Concentration ofIodine-131 in Milk (pCi/ liter) 103 Table 17A Concentration of Gamma Emitters in Food Products (pCi/g-wet) 104
( Table 17B Concentration of Gamma Emitters in Food Products (pCi/kg-wet) 105
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Table 18 Milk Animal Census 106
( Table 19 1996 Residence Census 108 Table 20 Interlaboratory Comparison Program Results 109 Table 21 Historical Emironn. ental Sample Data Shoreline Sediment (Control) 118 Table 22 Historical Environmental Sample Data Shoreline Sediment (Indicator) 119
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Table 23 Historical Environmental Sample Data Fish (Control) 120
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Table 24 Historical Environmental Sample Data Fish (Indicator) 121
[ Table 25 Historical Environmental Sample Data Surface Water (Control) 122 Table 26 Historical Environmental Sample Data Surface Water (Indicator) 123
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T TRT OF TART R9 (Continued)
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Table No. Content Eage
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Table 27 Historical Environmental Sample Data Surface Water
( Tritium (Control) 124 Table 28 Historical Environmental Sampic Data Surface Water Tritium (Indicator) 125 Table 29 Historical Environmental Sample Data Environmental TLD (Control) 126 Table 30A Historical Environmental Sample Data
[ Environmental TLD (Site Boundary) 127 Table 30B Historical Environmental Sample Data
[ Environmental TLD (Off-Site Sectors) 128 Table 30C Historical Environmental Sample Data
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Environmental TLD (Special Interest) 129
( Table 30D Historical Environmental Sample Data Environmental TLD (On-Site Indicator) 130
( Table 30E Historical Environmental Sample Data Environmental TLD (Off-Site Indicator) 131
[ Table 31 Historical Environmental Sample Data Air Particulates Gross Beta (Control) 132 Table 32 Historical Environmental Sample Dato \ir Particulates Gross Beta (Indicator) 133
[ Table 33 Historical Environmental Sample Data Air Particulates (Control) 134 Table 34 Historical Environmental Sample Data Air Particulates (Indicator) 135 Table 35 Historical Environmental Sample Data Air Radiciodine (Control) 136 r -iv-f
I Table No. Content East Table 36 Historical Environmental Sample Data Air Radioiodine (Indicator) 137 Table 37 Historical Environmental Sample Data Milk (Control) 138 Table 38 Historical Environmental Sample Data Milk (Indicator) 139 Table 39 Historical Environmental Sample Data Food Products (Control) 140 y Table 40 Historical Environmental Sample Data Food Products I (Indicator) 141
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I.TST OF FIGURR9 Figure No. Content Eagg Figure 1 Nearest Residence, Food Product, Fish and Shoreline
( Sediment Sample Iacations 143 Figure 2 Milk Animal Census, Milk Sample and Surface Water
[ Sample locations 144 Figure 3 Off-site Environmental Stations and TLD Iocations 145 Figure 4 On-site Environmental Station and TLD IAcations 146 Figure 5 New York State Map 147
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1.0 INTRODUCTION
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1.0 INTRODUCTION
This report is submitted in accordance with Appendix A (Technical Specifications), Section 6.9.1.d to License DPR-63, Docket No. 50-220 for the Nine Mile Point Nuclear Station Unit 1 and Section 6.9.1.7 to License NPF-69, Docket No. 50-410 for the Nine Mile Point Nuclear Station Unit 2 for the calendar year 1996.
The Radiological Environmental Monitoring Program (REMP) is a joint program between the Nine Mile Point Nuclear Station (NMPNS) and the James A. FitzPatrick Nuclear Power Plant (JAFNPP). The sample collections for the radiological programs are performed in large part by f EA hpe- Ang Science and Technology (EA). His staff performs the majority of the terrestrial and aquatic sampling required for the REMP. In-plant canal water sampling, air sample collection, and environmental TLD collections are grafumeljointly by the NMPNS and JAFNPP staffs.
He sample collection and analysis schedule required by the Technical Specifications for the Nme
[ Mile Point Nuclear Station Unit 1 and 2 is listed in Tables 1 and 2.
De majority of REMP samples were analyzed by the Site (James A. FitzPatrick) Environmental Laboratory during 1996 and included the following analyses:
- Shoreline sediment (gamma spectral analysis)
- Fish (gamma spectral analysis)
- Ide water (monthly gamma spectral analysis only)
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- Air particulate filter (weekly gross beta analysis)
- Air particulate filter (monthly gamma spectral analysis)
- Airborne radioiodine cartridge (weekly gamma spectral analysis)
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- Milk (gamma spectral and radioiodine analysis)
- Food products (gamma spectral analysis)
- Thermoluminescent dosimetry processing
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Lake water was analyzed for iodine and tritium by Teledyne Isotopes.
( Data are evaluated only from locations required by the Technical Specifications. Data from optional locations are not evaluated unless indicated otherwise.
There were four separate groups of radionuclides that were detected in the environment during
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1.0 INTRODUCTION
1996. Several radionuclides could possibly fall hto two of the four groups. The first of these l groups is naturally occurring radionuclides. It must be realized that the environment contains a broad inventory of namrally occumng radioactive elements. Background radiation, as a function of primordial radioactive elements and cosmic radiation of solar origin, offers a constant exposure to the environment and man. These radionuclides, such as Ra-226, Be-7 and especially K-40, account for a majority of the annual per capita background dose. Nearly all environmental l samples collected in 1996 contained naturally occurring radionuclides.
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A second group of radionuclides that were detected are a result of the detonation of thermonuclear E devices in the er.rth's upper atmosphere. The detonation frequency during the early 1950's 5 produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on atmospheric weapons testing in 1963 which greatly reduced the inventory through the decay of short lived radionuclides, deposition, and the removal
.I (by natural processes) of radionuclides from the food chain. Since 1963, several atmospheric weapons tests have been conducted by the People's Republic of China. In each case, the usual radionuclides associated with nuclear detonations were detected several months afterwards, and after a peak detection period, diminished to a point where most could not be detected. The last such weapons test was conducted in October of 1980. The resulting fallout or deposition from l this test had influenced the background radiation in the vicinity of the site and was very evident in many of the sample media analyzed during 1981. Calculations from 1981 of the resulting doses to man from tallout rehted radionuclides in the environment show that the contribution from such l nuclides (such as Sr-90 or Cs-137) was significant and second in intensity only to natural background radiation. Quantities of Nb-95, Zr-95, Ce-141, Ce-144, H-3, Ru-106, Ru-103, La-140, Cs-137, Mn-54 and Co-60 were also typical in air particulate samples during 1981 and I have a weapons test origin. During 1996, Cs-137 and H-3 were the only radionuclides detected in environmental samples that may have had a weapons testing origin.
The third group of radionuclides includes those that were a result of the Chernobyl Nuclear Plant accident. These radionuclides were first detected in May of 1986 and were found in samples of I air particulates, air radioiodine and milk. Applicable radionuclides include I-131, Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, and La-140. Cs-137 was the only radionuclide in this category that, combined with other sources of Cs-137, could have contributed to the total amount of Cs-137 l detected during 1996.
The fourth group of radionuclides are those that could be related to operations at the site. Many of these radionuclides are a by-product of both nuclear detonations and the operation of light water reactors. Therefore, making a distinction between the two sources can be difficult, if not impossible. During 1996, Cs-137 and H-3 were the only radionuclides which were detected that I would fall into this category. It is difficult to determine if the Cs-137 and H-3 were a result of site operations since, as mentioned above, they both are present as a re.sult of weapons testing and Chernobyl fallout.
The evaluation and interpretation of environmental data must be made at several levels including I 3-
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1.0 INTRODUCTION
( trad analysis, dose to man, etc. An attempt has been made not only to report the data collected during 1996, but also to assess the significance of the radionuclides detected in the environment as compared to natural radiation sources. 1996 data results are also evaluated with respect to pre-
{ operational results and historical results collected since commercial operation. It is important to note that detected concentrations of radionuclides that are possibly related to operations at the site
( are very small and are not an indication of environmental significance. In regards to these very small quantities, it will be further noted that at such minute concentrations the assessment of the signir-u of detected radionuclides is very difficult. Therefore, a concentration in one sample
[ that is two times the concentration of another, for example, is not significant overall. Moreover, concentrations at such low levels may show a particular radionuclide in one sample and yet not in another bananne of counting statistics at such low concentrations.
The average annual dose equivalent to individuals in the United States has been estimated to be 360 mrem (NCRP 93,1987). The majority of this dose (300 mrem) is attributed to natural
( background of which radon and daughter products contributed 200 mrem. Of man-made sources, medical diagnosis was the highest, contributing approximately 50 mrem. Consumer products
( added the remaining 10 mrem. The annual dose from the nuclear fuel cycle (including the L operation of nuclear power facilities) is considered essentially negligible.
Backgmund gamma radiation around the Nine Mile Point Site, as a result of radionuclides in the
( atmosphere and the ground, accounted for approximately 50 mrem during 1996. This cose 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.
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A dose of 50 mrem, as a background dose, is significantly greater than any possible dose as a result of operations at the site during 1996.
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Envirnnmental Emmede Inentinne - Table 3
( Table 3 contains the locations of the environmental samples presented in the data tables. The locaticas are given in degrees and distance from the Nine Mile Point Nuclear Station Unit 2 7 reactor centerhne. Table 3 also gives the figure (map) number as well as the map designation for L each sample location by sample medium type. The requirement for Table 3 is found in Section 6.9.1.d of the Technical Specifications for the Nine Mile Point Nuclear Station Unit I and Section 6.9.1.7 of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 2.
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Radininaient Envirnnmental Mnniinrina Prnaram Anmini Summarv - Table 4
( Table 4 contains a summary of basic statistics for environmental sample media as required by the Technical Specifications. Table 4 is in the format presented on Table 3 of the NRC Branch Technical Position (Revision 1 dated November 1979) to NRC Regulatory Guide 4.8
" Environmental Technical Specifications for Nuclear Power Plants". The table is presented to meet the requirements of Section 6.9.1.d and Section 6.9.1.7 of the Technical Specifications for Nine Mile Point Nuclear Station Unit I and Unit 2 respectively.
2.0 AOUATIC SAMPLFR 5-l
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2.0 AGUATIC SAMPTTR
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I. SHORELINE SEDIMENT A. Ramnie en11ectinn Methnaningy nna Analysis Shoreline =~Iiment samples are collected twice per year from one area of existing
[ or potential recreational value and from one area beyond the influence of the site.
The area of potential recreational value is the only area from which samples are
[ required by the Technical Specifications. Approximately one kilogram of shoreline aadiment is obtained from areas washed by the lakeshore surf at the two locations twice per year. All samples are analyzed for gamma emitters at the Site
( Environmental Laboratory. Optional samples may be collected from other shoreline locations at or near the site.
I Shoreline sediment locations are shown on Figure 1 (refer to Table 3 for location designations and descriptions).
( B. Evahintinn of Shoreline Sediment Data - Tables SA and SB Shoreline sediment samples were obtained in April and October of 1996 at one off-site control location (near Oswego Harbor) and at one indicator location (shoreline area with recreational valuejust east of the site).
The results of the shoreline sediment samples collected during 1996 at the indicator and controllocations are shown on Tables 5A and 5B. Table SA shows results in
[ units of pCi/g (dry) for purposes of data evaluation. Table 5B shows results in units of pCi/kg (dry), as required by the Technical Specifications. Only the Sunset Beach location was required by the Technical Specifications during 1996.
Several radionuclides were detected in sediment samples using gamma spectral analysis. K-40 was detected at both the control location and indicator location for
( both collection periods during 1996. K-40 is a naturally occurring primordial radionuclide. In addition to K-40, Ra-226 and AcTii-228 were also detected in control and indicator samples and are also naturally occurring radionuclides.
During 1996, Cs-137 was detected twice at the indicator location at concentrations ranging from 0.13 to 0.18 pCi/g (dry). Cs-137 has been detected each year since 1989 at the indicator location at concentrations ranging from 0.10 to 0.49. Cs-137 had not been detected prior to 1989 (1985 - 1988). Cs-137 was not detected at the
{ control location during 1996, however, it had been detected intermittently in the past (1979,1980,1982 and 1993). Detectable control location quantities have ranged from 0.03 to 0.22 pCi/g (dry).
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2.0 AQUATIC SAMPLES i I. SHORELINE SEDIMENT (Cont'd)
B. Evaluatinn of Rhoreline Mediment Data - Tables SA and SB (Cant'd) ne source of Cs-137 in 1996 indicator shoreline sediment samples is difficult to determine. Possible sources are fallout from past weapons tests or from site operations. It is highly probable that the Cs-137 is from fallout. As mentioned previously, Cs-137 has been detected from control locations in the past. Due to the fact that few shoreline regions west of the site contain fine sediment and/or sand, it is difficult to obtain contml samples which are comparable to the physical f and enemial characteristics of the indicator samples. Other factors, which include changing lake level and shoreline erosion, further complicate any consistency in g shoreline sedimmt empling. Soil samples in areas which are likely to be affected i by plant operatioru, as well as soil beyond any influence from the site, all contain levels of Cs-13'I at or greater than the concentration found in 1996 shoreline
( sediment. Cs-137 in soil samples has been attributed to weapons testing fallout.
l ne irwhentar location, unlike the control location, is very close to eroding ground areas and is believed to contain soil residues. Derefore, any shoreline sediment sample containing soil would reveal Cs-137. nese factors support the likelihood
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that the trace amounts of Cs-137 detected in the indicator shoreline sediment samples are due to fallout from past weapons testing.
Using Regulatory Guide 1.109 rnethodology, and conservatively assuming that the muimum exposed individual (adult or teenager) would spend approximately 67
( hours per year at this location, a conservative dose due to Cs-137 was calculated to be 0.001 mrem to the whole body and 0.001 mrem to the skin. These doses are very small when compared to average annual whole body doses due to natural t background and may be considered insignificant. For the purpose of comparison, soil sampled at a locatic,n beyond any influence of the site contained Cs-137 at a j concentration of 0.46 pCi/g. Using the same methodology and assumptions for I
that of sediment, annual whole body and skin doses of 0.002 mrem were calculated. Thus, it is shown that a dose to an individual at this shoreline area is j less than an individual would receive from soil more distant from the plants. Both doses may be considered insignificant.
No other radionuclides were detected in shoreline sediment samples using gamma spectral analysis.
Tables 21 and 22 show historical environmental data for shoreline sediment samples. Shoreline sediment samples at the indicator location were not collected prior to 1985.
2.0 AOUATIC SAMPTTS l
l II. FISH A. Samnle Cn11ection Methodningy and Analysis Available fish species are obtained from collections during the spring and fall.
Samples are collected from two of four possible on-site sample transects located in I the vicinity of the site discharge points and one off-site sample transect. Available species are selected under the following guidelines:
- 1. Samples of 0.5 to I kilogram of edible fish portions for a minimum of two species per location.
- 2. When two independent species are not available at all sample locations, a species may be divided into two samples for each location. This procedure may be accomplished provided that a sufficient sample size is available for l the species in question at all three locations.
l Selected fish samples are segregated by species and location and are processed immediately after collection. Samples are shipped frozen in insulated containers.
Edible portions of samples are analyzed for gamma emitting radionuclides.
Fish sample transects are shown on Figure 1 (refer to Table 3 for location designations and descriptions).
B. Evaluation of Fish Data - Tables 6A and 6B A total of thirty fish samples were analyzed as a result of collections in the spring season (June 1996) and in the fall season (September / October 1996). Collections were made utilizing gill nets at one location greater than five miles from the site l (Oswego Harbor area), and at two locations in the vicinity of the lake discharges roi the Nine Mile Point Unit #1 (02), and the James A. FitzPatrick (03) generating l facilities. The Oswego Harbor samples (00) served as control samples while the NMP (02) and JAF (03) samples served as indicator samples. Samples were analyzed for gamma emitters. Table 6A shows results in units of pCi/g (wet) for I purposes of data evaluation. Table 6B shows results in units of pCi/kg (wet), as required by the Technical Specifications.
Spring fish sample collections were comprised of four separate species and twelve individual samples. Brown trout, white sucker, lake trout, and smallmouth bass were collected at the indicator locations (NMP and JAF) and at the control location (Oswego Harbor).
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I 2.0 AO_UATIC SAMPLFS II. FISH (Cont'd)
B. Evaluation of Fish Data - Tables 6A and 6B (Cont'd)
Cs-137 was not WM in any of the eight indicator samples collected during the spring. Cs-137 was detected in one sample of Lake Trout collected at the control I location at a concentration of 0.014 pCi/g (wet). Cs-137 has been detected in fish samples from both indicator and control locations in the past.
K-40 was detected in all of the spring samples collected. K-40 is a naturally occumng radionuclide and is not related to power plant operations. Ra-226, also naturally occurring, was detected intermittently in both indicator and control I samples. No other radionuclides were detected in the spring fish samples.
l Fall fish sample collections were comprised of six separate species and eighteen individual samples. Brown trout, lake trout, smallmouth bass, white sucker, walleye, and chinook salmon samples were collected at indicator sampling l locations (NMP and JAF). At the controllocation (Oswego Harbor), white sucker, brown trout, lake trout, chinook salmon, and smallmouth bass samples were collectec.
Cs-137 was detected in three of the eighteen samples which included the control samples. Indicator samples showed an average Cs-137 concentration that was I slightly less than the control sample mean from the off-site location. The detected concentrations were not significantly different from one another because of the extremely small quantities detected. Cs-137 in samples at the indicator locations I ranged from 0.014 to 0.016 pCi/g (wet) and was 0.018 pCi/g (wet) at the control location. Cs-137 was detected in lake trout sampled at NMP at a concentration of 0.014 pCi/g (wet), and in smallmouth bass at a concentration of 0.016 pCi/g (wet).
I Cs-137 wie not detected in lake trout sampled at JAF. Brown trout sampled at the controllocation cor,thed Cs-137 at a concentration of 0.018 pCi/g (wet). Cs-137 l was not detected in any other control or indicator sample:: of fish collected during the fall of 1996.
l Naturally occurring K-40 was detected in all of the Fall samples collected.
Ra-226, also naturally occurring, was detected intermittently in the control and the indicator samples. No other radionuclides were detected in the Fall fish samples.
Review of past environmental data indicates that the mean annual Cs-137 concentration has decreased significantly from the 1976 through 1996 results for indicator samples. Average concentrations for these samples decreased from a
( level of 1.4 pCi/g (wet) in 1976 to a level of 0.015 pCi/g (wet) in 1996. Control
2.0 AOUATIC SAMPLFS II. FISH (Cont'd)
B, Evaluntinn of Fid Data - Tables 6A and 6B (Cont'd) sample results have also decreased from a level of 1.2 pCi/g (yet) in 1976 to a level of 0.016 pCi/g (wet)in 1995. Results from 1980 to 1986 ha"e shown a fairly l consistent decreasing trend for control and indicator samples. Du mg 1987 through 1994, control and indicator mean results increased slightly when compared to 1986.
The general decreasing trend for Cs-137 is most probably a result of ecological cycling. The concentrations of Cs-137 detected since 1976 in fish are a result of I weapons testing fallout, and the general downward trend in concentrations will continue as a function of ecological cycling and nuclear decay. There was no significant effect from the 1986 Chernobyl Nuclear Plant accident during 1986 relative to Cs-137 results in fish samples although an effect may have been detected during the period of 1987 through 1991 since both indicator and control location l mean results increased slightly.
Tables 23 and 24 show historical environmental sample data for fish.
Lake Ontario fish are considered an important food source by many. Therefore, fish are an integral part of the human food chain. Rawi on the importance of fish I in the local diet, a reasonable conservative estimate of dose to man can be '
calculated. Assuming that an adult and teen consume 21.0 kg and 16 kg respectively, of fish per year (Regulatory Guide 1.109 maximum exposed age I group) and the fish consumed contains an average Cs-137 concentration of 0.015 pCi/g (wet) (annual mean result ofindicator samples for 1996), the adult whole body dose received would be 0.022 mrem per year. The critical organ, in this I case, is the tees liver which would receive a calculated dose of 0.036 mrem per year. The Cs-137 wnule body and critical organ doses are conservative calculated l doses associated with consuming fish from the Nine Mile Point area (indicator samples). No radiological decay is assumed for the calculation of doses.
l Conservative whole body and critical organ doses can be calculated for the consumption of fish from the controllocation as well. In this case the consumption g rate is assumed to remain the same (21 kg per year for an adult and 16 kg per year l for a teen), but the average annual Cs-137 concentration for the control samples is 0.016 pCi/g (wet). The calculated Cs-137 adult whole body dose is 0.024 mrem per year and the associated dose to the teen liver is 0.038 mrem per year. In this case, the fish from the control location resulted in doses which were slightly 1
2.0 AQUATIC SAMPLES II. FISH (Cont'd)
B. Evaluation of Fish Data - Tables 6A and 6B (Cont'd) greater than that from the indicator locations (near the nuclear facilities). The control location is located beyond any influence of the site.
In summary, the whole body and critical organ doses observed as a result of consumption of fish is small. Doses received from the consumption ofindicator I and control sample fish are approximately the same. The doses from indicator sample fish are slightly less, and well within natural variability. For example, the whole body and organ doses from the indicator samples were greater than control I samples during 1995. Doses from both sample groups are considered background doses and negligible.
III. SURFACE WATER l A. Samnle Cn11ertion Methodoingy and Analysis Surface water samples are taken from the respective inlet canals of the J.A.
I FitzPatrick facility and Niagara Mohawk's Oswego Steam Station. The FitzPatrick facility removes water from Lake Ontario on a continuous basis and generally represents a "down-current" sampling point from the Nine Mile Point Unit I and I Unit 2 facilities. The Oswego Steam Station inlet canal removes water from Lake Ontario at a point approximately 7.6 miles west of the site. This "up-current" location is considered a control location because of the distance from the site as I well as the result of the lake current patterns and current patterns from the Oswego River located nearby (see Figure 2).
Samples from the FitzPatrici facility are composited from automatic sampling equipment which discharges into a cuirpositing tank. Samples are obtained from l the tank monthly and analyzed for gamma emitters. Samples from the Oswego Steam Station are also composited from automatic sampling equipment which discharges to a compositing tank. Samples from this location are obtained weekly l and are composited to form monthly composite samples. Monthly samples are analyzed for gamma emitters.
A portion of the sample from each of the locations is saved and composited to form quarterly composite samples for each calendar quarter. Quarterly composite samples are analyzed for tritium.
2.0 AOUATIC SAMPLF.9 III. SURFACE WATER (Cont'd)
A. samnte collection Methodningy and Analysis (cont'd)
In addition to the FitzPatrick and Oswego Steam Station facilities, data are presented for the Nine Mile Point Unit I and Unit 2 facility inlet canals and water from the City of Oswego. The latter three locations are not required by the I Technical Specifications, but are optional samples. Monthly composite samples from these three locations are analyzed for gamma emitting nuclides and quarterly composite samples are analyzed for tritium. Surface water sample locations are I shown on Figure 2 (refer to Table 3 for location designations and descriptions).
Sampling for ground water and drmking water, as found in Section 3.12.1 of the I Nine Mile Point Unit 2 Technical Specifications, was not required during 1996 because these pathways were not applicable to tim Site during the year. Applicable sampling requirements and conditions are presented in the Unit 2 Off-Site Dose I Calculation Manual.
l Gamma spectral analysis results for the 1996 surface water samples showed no evidence of plant related radionuclide buildup in the surface water in the vicinity of the site. Indicator samples were collected from the inlet canal at the James A.
I FitzPatrick facility. The control location samples were collected at the inlet canal of Niagara Mohawk's Oswego Steam Station. These two locations are required to be sampled by the Technical Specifications. Results of the three optional locations I also revealed no plant-related nuclides. Tables 7 and 8 show the results of all surface water samples analyzed during 1996. Only naturally occurring radionuclides were detected in samples from the five locations over the course of I the year. K-40 was detected consistently in both indicator and control samples.
Ra-226 was detected intermittently in samples from all five locations.
Review of past environmental data for Cs-137 from 1979 through 1995 shows that this radionuclide was detected only once at 9e control location during 1979 at a concentration of 2.5 pCi/ liter. Cs-137 at the indicator location (JAF inlet canal) l was detected only once during 1982 at a concentration of 0.43 pCi/ liter. The 1979 contml sample result is suspect and may have been a result of contamination during l handhng or instrument background since Cs-137 was not detected in the indicator inlet canal. The one result from the indicator location (JAF inlet canal) during 1982 was detected in a January composite sample and may have been a result of i inlet canal tempering (the addition of discharge water to the inlet canal) or instrument background. Cs-137 was not detected during 1996 in surface water samples.
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l 2.0 AOUATIC SAMPLFS III. SURFACE WATER (Cont'd)
I A. Samnle Collection Methodningy and Analysis (Cont'd) l Other plant related radionuclides detected during a review period of 1979 - 1995 include only Co-60. The control sample location results showed that Co-60 was datMad once in 1981 (the May composite sample). This result is suspect and, as I noted above, may be a result of contamination during handling or may be instrument background. This result was 1.4 pCi/ liter. Results from the indicator location showed that Co-60 was detected three times during 1982 and averaged 1.9 I pCi/ liter. These positive results were attributed to inlet canal tempering and instrument background. Co-60 was not detected during 1996 in surface water samples.
l Tables 25 and 26 show historical environmental sample data for surface water using gamma spectral analysis.
l Tritium samples are quarterly samples that are a composite of the appropriate l calendar months. Tritium results are presented on Table 8. Tritium was detected at only one location in one of the four quarters. At the Nine Mile Point inlet n (optional location), tritium was detected in the second quarter sample at a l concentration of 160 pCi/ liter. Tritium was not detected at any other Technical Specification or optional location during 1996.
The impact of tritium in water to members of the public is minimal. This can be evaluated by calculating an annual dose to the whole body and maximum organ.
Using Regulatory Guide 1.109 methodology, ingestion of water from the Nine I Mile Point inlet location would result in an annual dose of 0.017 mrem to the whole body and 0.017 mrem to the child liver. This calculated dose is insignificant and a result of background concentrations of t-itium in water. In 1995, tritium was I detected in drinking water collected from a lootion more distant than control samples and resulted in a calculated dose of 0.021 mrom M the adult whole body l and child liver. Both doses are considered background doses and negligible.
Previous annual mean results for tritium at the indicator sample location l (FitzPatrick inlet canal) have generally decreased since 1976. Mean sample results reviewed from 1976 through 1994 showed a peak average value of 627 pCi/ liter
^
(1976) and a minimum value of 220 pCi/ liter (1994).
( Mean tritium results for the control location (Oswego Steam Station) can not be evaluated with regard to long term historical data since sampling was only initiated at this location in 1985. Some idea of the variability of control sample data can be
[ obtained, however, by review of previous data from the City of Oswego drinking
[ 2.0 AQUATIC SAMPLES III. SURFACE WATER (Cont'd)
A. Ramnle Cn11ectian Methadalaay and Analysis (cont'd)
{
water samples. The drinking water samples are not likely to be affected by the station because of the effects of the distance, lake currents, and the discharge of the
{
Oswego River. Therefore, this pmvious sample data represents acceptable control sample data for evaluation purposes.
[
Historical mean annual tritium results from previous city water samples (1976-1984) and Oswego Steam Station samples (1985-1991) show that the tritium
( concentrations have decreased. The maximum annual average was found in 1976 (652 pCi/ liter) and the minimum in 1982 (165 pCi/ liter). Mean annual results from 1979 to 1994 have remained relatively consistent. The Oswego Steam Station
[ annual mean result for 1995 was 230 pCi/ liter.
Tables 27 and 28 show historical environmental sample data for surface water
[ tritium.
[
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[
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[
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[
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[ 3.0 DIRECT RADIATION I
. - - . - .. - . , ..- ...... -..- ~ . - . . . - _ _ - - - - - - . ~ _ - _ .
I t
3.0 DIRECT RADIATION i i
A. Ramale Ca11etian Mathadataev and Annivsis Thermoluminescent dosimeters (TLD's) are used to measure direct radiation (gamma dose) in the environment. TLD's are pranaaM at the Site Environmental laboratory on a quarterly basis. Control TLD's accompany the TLD's when they i are being placed or collected and are shielded by lead when they are not being !
used. TLD data rest /m are corrected by use of the data from the control TLD's.
y Five different types of areas are evaluated by environmental TLD's. 'Ihese areas '
include on-site areas (areas within the site buurdary not required by the Technical Specifications), the site boundary area in each of the sixteen meteorological ;
sectors, an outer ring of TLD's located four to five miles from the site in eight '
available land based meteorological sectors, special interest TLD's located at sites of high population density and control TLD's located at sites beyond significant influence of the site. Special interest TLD's are located at or near large industrial sites, schools, proximal towns or communities or other special activity areas. Field ,
control TLD's are placed to the southwest, south, south-southeast and northeast of the site at distances ranging from 12.6 to 24.7 miles, and are used to measure the general background radiation levels.
TLD's used during 1996 were Panasonic UD-814 dosimeters. These were placed in polyethylene r+3 y to ensure dosimeter integrity. TLD packages were placed in open webbed plastic holders and were attached to supporting structures; usually trees or utility poles.
Environmental TLD locations are shown on Figures 3 and 4 (refer to Table 3 for location designations and descriptions).
B. Evahintian of Tf D Data - Tahlec 9A and 9B TLD's were collected and read once per quarter during the 1996 sample yea The TLD results are reported in mrem per standard month (Table 9A) and in mrem per '
quarterly period (Table 9B).
Two TLDs were utilized at each location. The results presented in this report represent an average of the two TLDs. TLD results included on Tables 9A and 9B ,
are comprised of TLD's required by the Technical Specifications and special interest TLD's not required by the Technical Specifications. During 1996, TLD's were primarily collected during the weeks of March 27,1996, June 25,1996, i l September 29,1996, and January 8,1997.
, Overall TLD results are evaluated by organizing environmental TLD's into five l different groups. These groups include: (1) on-site TLD's (TLD's within the site
[
3.0 DIRECT RADIATION
( B. Evnhatian of Tr n Eata - Tahls 9A and 9BJQg'd) boundary not required by the Technica' Specifications), (2) site boundary TLD's
[ (one in each of the sixteen 221/2 degree meteorological sectors), (3) a ring of TLD's four to five miles from the site in each of the land based 221/2 degree
[ meteorological sectors, (4) special interest TLD's in areas of high population density, and (5) control TLD's in areas beyond any significant influence of the generating facilities. Special interest TLD's are located at or near large industrial
( sites, schools, or proximal towns or communities. Control TLD's are located to the southwest, south, south-southeast, and northeast of the site at distances of 12.6 to 24.7 miles from the site.
Most of the TLD locations required by the Technical Specifications during 1996 were initiated in 1985 as a result of the issuance of new Technical Specifications
[ by the NRC. Derefore, these TLD results can only be compared to 1985 - 1995 results. Other TLDs, which include a few TLDs required by the Technical
[ Specifications (i.e., numbers 7,14,15,18, 23, 49, 56, and 58) and other optional i TIDs, can be compared to results prior to 1985 since these TLDs were established prior to 1985.
On-site TLD's are TLD's at special interest areas and, with the exception of TLD numbers 7 and 23, are not required by the Technical Specifications. These are
[ located near the g== ting facilities and at previous or existing on-site air sampling stations. TLD's located at the air sampling stations include numbers 3, 4, 5, 6, 7, 23, 24, 25 and 26. ne results for these TLD's are generally consistent with
[ previous years results with the exception of TLD number 3. This TLD is located in closest proximity to the FitzPatrick facility and reflected an increased dose rate due to the hydrogen water chemistry conducted during plant operation. These
[ results ranged from 3.1 to 32.6 mrem per standard month during 1996 and up to six times control TLD results.
( Other on-site TLD's include special interest TLD's located near the shoreline north of the Unit 1, Unit 2 and FitzPatrick facilities, but in close proximity to radwaste facilities and the Unit I reactor building. These TLD's include numbers 27, 28,
{ 29, 30, 31, 39, and 47. Results for these TLD's during 1996 were variable and ranged from 4.1 to 68.1 mrem per standard month as a result of activities at the radwaste facilities, the operating modes of the generating facilities (and hydrogen
[
injection at JAF). Results for 1996 are consistent with the ranges of variability noted in 1995 for TLD's at or near these locations. TLD's in this group ranged
( up to approximately fourteen times control TLD results.
Additional on-site TLD's are located near the on-site Energy Center and the associated northeast shoreline. These TLD's include numbers 18,103,106 and
[ -
l 1 1
3.0 DIRECT RADIATION B. Evahintinn of TIB Data - Tahles 9A and 9B (Cont'd) 107. TLD's 103,106 and 107 are located to the east of the Energy Center and to
{ the west of the Unit I facility. TLD number 18 is located on the west side of the Energy Center. Results during 1996 showed these TLD's ranged from 4.1 to 6.4 mrem per standard month and were consistent with the 1995 results.
[
Site boundary TLD's are required by the Technical Specifications and are located
( in the apprmim=* area of the site boundary with one in each of the sixteen 221/2 degree meteorological sectors. These TLD's include numbers 7,18, 23, 75, 76, 78, 79, 80, 81, 82, 83, 84, 85, 86 and 87. TLD numbers 7,18, 78, 79, 80, 81,
[ 82, 83, and 84 showed results that were consistent with control TLD results and ranged from 3.2 to 5.3 mrem per standard month. Site boundary TLD's during 1996 were consistent with 1985-1995 results. TLD numbers 23, 75, 76, 77, 85,
[ 86, and 87 showed results that ranged up to three times the results of control TLD's. '1hese results ranged from 4.7 - 9.1 mrem per standard month. This latter group of TLD's are located near the lake shoreline (approximately 100 feet from
[ the shoreline), but are also Incated in close proximity of the reactor building and radwaste facilities of Unit 1 and Unit 2 and the radwaste facilities of the FitzPatrick facmty.
(
A net site boundary dose can be estimated from available TLD results and control
( TLD results. TLD results from TLD's located near the site boundary in sectors facing the land occupied by members of the public (excluaing TLD's near the generating facilities and facing Lake Ontario) are compared to control TLD results.
( The site boundary TLD's include numbers 78, 79, 80, 81, 82, 83, 84, 7 and 18.
Control TLD's include numbers 8,14,49,111 and 113. Net site boundary doses for each quarter in mmm per standard month are as follows:
Quarter Net Site Boundarv Dnce*
1 +0.0
[ 2 -0.6 3 -0.1 4 + 0.2
{
- Dose in mrem per standard month
[
Site boundary TLD numbers 75, 76, 77, 23, 85, 86, and 87 were excluded from the net site boundary dose calculation since these TLD's are not representative of
( doses at areas where a member of the public may be located. These arm are near the north shoreline which are in close proximity to the generating facilities and are not accessible to members of the public.
[
3.0 DIRECT RADIATION B. Evninntinn of Tr n Datn . Tahlec 9A anti 9B (Cnnt'd)
The third group of environmental TLD's are those TLD's located four to five miles
[
from the site in each of the land based 22.5 degree meteorological sectors. These TLDs are required by the Technical Specifications. At this distance, eight of the sixteen meteorological sectors are located over Lake Ontario.
{
Results for this group of TLD's during 1996 fluctuated slightly as a result of f changing naturally occurring conditions and the different cor'centrations of naturally occurring rudionuclides in the ground at each of the locations. These TLD's were established in 1985 and include numbers 88, 89, 90, 91, 92, 93, 94
[ and 95. Results ranged from 3.2 to 5.3 mrem per standard month. Dese results are generally consistent with control TLD results during 1996. Results for this 7
group of TLDs were consistent with the 1985 - 1995 results. Results were also I consistent with other off-site TLD results during 1996 and previous to 1996.
[ The fourth group of environmental TLD's are those TLD's located near the site t
boundary and at special interest areas such as industrial sites, schools, nearby communities, towns, off-site air sampling stations, the closest residence to the site, j and the off-site environmentallaburEny. Many of these TLDs are required by the Technical Specifications. Others are optional. - nis group of TLD's include numbers 9, 10, 11, 12, 13, 15, 19, 51, 52, 53, 54, 55, 56, 58, % , 97, 98, 99, 100,101,102,108 and 109. TLD numbers 108 and 109 are TLD locations that were established to assist in the evaluahon of the critical residence. Results ranged from 3.2 to 5.6 mrem per standard month. All the TLD results from this group were within the general variation noted for the control TLD's. Results during 1996 for TLD's established during previous years were consistent with results noted for those years.
Le fifth group of TLD's include those TLD's considered as control TLD's. These TLD's are required by the Technical Specifications and include numbers 14 and
- 49. Optional controllocations are TLD numbers 8,111, and 113 and were added to the program to expand the data base for control TLD's. Results for 1996 ranged from 3.4 to 5.6 miem per standard month. Results from 1996 were consistent with previous years results. However, an annual average increase was noted in 1986.
This increase may have been a result of the Chernobyl Nuclear Plant accident and was not noted during 1987-1996.
Review of past TLD results reanired by the Technient Specifications show that these TLDs can be separated into four groups. These groups include site boundary TLDs in each meteorological sector (16 TLDs total), TLDs located off-site in each land based sector at a distance of 4 to 5 miles (8 TLDs total), TLDs located at 1
I l
3.0 DIRECT RADIATION B. EvalumHan of Trn Data - Tahlen 9A and 9B mnnt'd) j special interest areas (6 TLDs total) and TLDs locatM at control locations (2 TLDs total). As noted previously, since the present Technical Specifications became effective in 1985, these TLDs, for the most part, can only be evaluated for 1985
- 1996.
{
Technical Specificaten TLDs located at the site boundary averaged 6.2 mrem per f standard month during 1985. During the period of 1986 - 1995 site boundary TLDs ranged from 4.8 - 7.0 mrem per standard month. As noted previously, this group of TLDs can fluctuate because several of these TLDs are located in close f pmximity to the generating facilities. An increase was noted during 1986 although such an increase was noted for all TLDs including control TLDs. During 1996, site boundary TLDs averaged 5.2 mrem per standard month.
Technical S* dan TLDs lacatM off-site at a distance of 4 to 5 miles from the
[ site in each of the land based meteorological sectors averaged 5.0 mrem per l standard month during 1985. During the period of 1986 - 1995 off-site sector TLDs ranged from 4.1 - 6.0 mrem per standard month. 'Ihe 1986 results demonstrated an increase for this group of TLDs. Results for 1996 for the group
{
averaged 4.2 mrem per standard month. This is consistent with previous year's results.
Special interest Technical Specification TLDs are located at areas of high population density, such as major work sites, communities, schools, etc. and at residences near the site (critical receptor areas). This group of TLDs averaged 5.3 mrem per standard month during 1985. During 1986, this same group of TLDs averaged 6.1 mrem. During the period of 1987 - 1995 these TLDs averaged f between 4.0 - 5.3 mrem per standard month. 1996 results for these locations averaged 4.2 mrem per standard month.
( The final group of TLDs required by the Technical Specifications is the control group. This group utilizes two TLD locations positioned well beyond the site.
[ Results from 1985 for the control group averaged 5.4 mrem per standard month.
I During 1986, this same group of TLDs averaged 6.3 mrem per standard month.
A marked increase was noted in the second quarter of 1986. The increase may have been a result of the Chernobyl Nuclear Plant accident. Results for 1987 -
1995 ranged from 3.9 - 5.4 mrem per standard month. Results for 1996 averaged 4.2 mrem per standard month.
20-
l 3.0 DIRECT RADIATION B. Evahintinn of TID Data - Tables 9A nnd 9B (Cont'd) l Tables 29 and 30A-30E show the historical environmental sample data for l environmental TLD's.
j During 1996, all environmental TLD groups required by the Technical l Specifications were generally consistent with the results observed during 1995.
Overall, envimnmental TLD results for 1996 showed no significant impact from direct radiation measured outside the site boundary.
I I
I l
1 l
l l
l l
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4.0 TERRR9 TRIAL SAMPLR9 f
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22-
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4.0 TERRESTRIAL SAMPLES
- f. I. AIR PARTICULATE / IODINE A. Ramala callactian sad Mathadalagy The air sampling stations required by the Technical Specifications are located in
{ the general area of the site boundary (within 0.7 miles) in sectors of highest calculated meteorological deposition factors (D/Q) based on historical meteorological data. These stations (R-1, R-2, and R-3) are located in the east,
[ cast-southeast, and southeast sectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2 reactor building. The Technical Specifications also require that a fourth air sampling station be located in the vicinity of a year round community having the highest calculated deposition factor (D/Q) based on historical irmuk,sical data. His station is located in the southeast sector (R 4).
A fifth station required by the Technical Specifications is located at a site 16.4 miles from the site in a northeast direction (R-5). This location is considered a coatrollocation.
In addition to the Technical Spacifientian required locations, there are six sampling stations located within the site boundary (DI, G, H, I, J, and K). These locations generally surround the area m=i-I by the three generating facilities, but are well within the site boundary. One other air samplirig station is located off-site in the southwest sector and is in the vicinity of the City of Oswego. Three remaining air samphng stations (D2, E and F) air located in the east-southeast, south-southeast and south sectors and range in distance from 7.2 to 9.0 miles.
At each station, airborne particulates are collected by glass fiber filters and adiaiadiaa by charcoal filters. Air particulate glass fiber filters are approximately two inches (47 millimeters) in diameter and are placed in sample holders in the intake line of a vacuum sampler. Directly down stream from the particulate filter is a 2 x 1 inch charcoal cartridge used to adsorb airborne radioiodine. The samplers mn continuously and the charcoal cartridges and particulate filters are changed on a weekly basis, or as required by dust loading. Gross beta analysis is performed for the individual particulate filters on a weekly basis. Charcoal cartridges are analyzed weekly for radioiodine by GeLi detector.
De particulate filters are composited by location for gamma analyses on a monthly basis after all weekly particulate filters have been counted for gross beta activity.
B. Evalnntion of Air Particulate Gross Reta - Tables 10 and 11 Air sampling stations are shown in Figures 3 and 4 (refer to Table 3 for location designations and descriptions). Tables 10 and 11 contain the results for the weekly air particulate gross beta analysis for a total of nine off-site and six on site
( 4.0 TERRESTRIAL SAMPLES r I. AIR PARTICULATE / IODINE (Cont'd)
L.
B. Evahmtian of Air Partieninta Grnee Data - Tahlec 10 and 11 (Cant'd) sample locations. Five of the nine off-site locations are required by the Technical SeGratiane. 'Ihese sample incatinns are R-1, R-2, R-3, R-4 (all located near the site boundary) and R-5 (located at a control location beyond any significant
[
influence from the site). Data contained on Tables 10 and 11 also shows the results from other air sampling locations not required by the Technical Specifications.
[ These locations are daniga=*M as D1 on-site, G on-site, H on-site, I on-site, J on-site, K on-site, D2 off-site, E off-site, F off-site and G off-site locations. A total of 52 control samples from location R-5 and 208 indientar samples from f locations R-1, R-2, R-3, and R-4 were collected and analyzed during 1996.
The minimum, maximum, and average gross beta results for sample locations f required by the Technical Specifications are presented below.
IJuation** Mininam* Maximum
- Armagc*
R-1 0.007 0.025 0.013 R-2 0.007 0.024 0.013 R-3 0.007 0.023 0.013 R-4 0.006 0.021 0.013 R-5 (control) 0.009 0.023 0.014
- - Concentration in pCi/m'
{. ** - Imations required by the Technical Specifications The observed small increases and decreases in general gross beta activity can be attributed to changes in the environment, especially seasonal changes. The concentra* ion of naturally occurring radionuclides in the lower limits of the atmosphere di*ctly above land areas are affected by processes such as wind f direction, snow cova, . oil temperature and soil moisture content. Little change was noted in gross beta activity which corresponded with weapons testing as has been observed in past years.
In general, the trend in air particulate gross beta activity has been one of decreasing activity since 1977 (extent of the review period). The mean gross beta concentration at control locations has decreased from a level of 0.165 pCi/m' in 1981 to 0.012 in 1992. Results from indicator air sampling locations ranged from 0.151 pCi/m'in 1981 to 0.012 pCi/m'in 1992. For both indicator locations and control location, the gross beta concentration during 1977 to 1987 fluctuated with the detonation of thermonuclear weapons.
4.0 TERRESTRIAL SAMPLES I. AIR PARTICULATE / IODINE (Cont'd)
B. Evahintion of Air Partieninte Gross Beta - Tables 10 nnd 11 (Cont'd)
Tables 31 and 32 show historical environmental sample data for air particulate gross beta levels.
C. Evahintinn of Monthly Air Partien1ste Comnositet - Table 12 Weekly air particulate samples were composited by location to form monthly I composite samples. The monthly composite samples required by the Technical Specifications include R-1, R-2, R-3, R-4, and R-5. Other sample locations not required by the Technical Specifications include D1 on-site, G on-site, H on-site, I I on-site, J on-site, K on-site, D2 off-site, E off-site, F off-site and G off-site locations. 'Ihe results of all monthly composite samples are included on Table 12.
I The results for the monthly composite samples showed positive results for Be-7, K-40, and Ra-226. All three of these radionuclides are naturally occumng. Be-7 l was found in all of the monthly composite samples from the locations required by the Technical Specifications. K-40 was found intermittently in the monthly composite samples required by the Technical Specifications. Ra-226 was also I detected intermittently in both indicator and control samples. No other plant-related radionuchdes were daw at Technical Specification or optional locations using gamma spectral analysis during 1996.
Co-60 concentrations in air particulate samples have shown a general decrease in both indicator and control samples. In 1977, Co-60 concentrations in control I samples averaged 0.0172 pCi/m'. A decrease was observed until 1985 when no Co-60 was detected. From the period 1985-1996, no Co-60 was detected in control samples. Co-60 concentrations in indicator samples have shown a similar I decrease. In 1977, the averge. concentration of Co-60 in indicator samples was 0.0179 pCi/m'. By 1982, this value had decreased to 0.0005 pCi/rh . Slight increases were observed in 1983 and 1984, but these anomalies were due to l contamination during handling of the unused samples and not due to plant operations (this has been previously documented in the 1984 annual report). Since l 1984, no Co-60 has been detected in any Technical Specification indicator location.
g Historically, the presence of Cs-137 has been variable and has been present in air l particulate samples since 1977. During 1977, both indicator and control Cs-137 average concentrations were approximately equal and averaged 0.0038 pCi/m'.
Since that time the concentration in both control and indicator samples has been I steadily decreasing. The decreasing concentrations of Cs-137 are due to ecological cycling and nuclear decay of Cs-137 which was produced during 1
4.0 TERRFRTRIAL SAMPT FR I. AIR PARTICULATE / IODINE (Cont'd)
C. Evaluatinn of Monthly Air Partieninte Comnosites - Table 12 (Cont'd) weapons testing. 1978 concentrations of Cs-137 in control and indicator locations 8
both averaged 0.0017 pCi/m , and steadily decreased to 0.0002 pCi/m' in 1983.
Cs-137 was not detected during 1984 and 1985. In 1986, Cs-137 was detected as a result of the Chernobyl accident in April 1986. Average concentrations during I that year for indicator and control samples were 0.0183 and 0.0193 pCi/m' respectively. During the period of 1987-1996 Cs-137 was not detected at any indicator or controllocation.
l Prior to 1984, several radionuclides were detected that were associated with the l 1980 Chinese weapons test and other weapons tests prior to 1980. These radionuclides were not detected after 1983 as a result of nuclear decay and ecological cycling. These include Zr-95, Cc-141, Nb-95, Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140.
l
, During 1986, however, several fission product radionuclides were detected that l were a result of the Chernobyl Nuclear Plant accident. These included Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, La-140 and I-131. During 1987 through 1995, g none of the radionuclides associated with the 1986 Chernobyl accident or past l weapons testing were detected in air particulate samples.
l During 1996, no radionuclides were detected in monthly air particulate composite I
samples that could have been attributed to plant operations. Therefore, " dose calculations were performed.
Tables 33 and 34 show historical environmental sample data for air particulate composites.
I D. Evaluation of Airborne Radiciodine - Tables 13 and 14 During the 1996 sampling program, airborne radioiodine was not detected in any of the weekly samples from the locations required by the Technical Specifications.
LLD values at the control location ranged from 0.006 - 0.016 pCi/m . The S 8
indicator locations ranged from less than 0.004 to 0.019 pCi/m .1-131 was also not detected at any of the optional monitoring locations (not required by the Technical Specifications) during 1996. Since I-131 was not detected at any of the indicator or control locations during 1996, no dose calculations are presented.
l 4.0 TERRFSTRIAL SAMPI FR I. AIR PARTICULATFJIODINE (Cont'd)
D. Evalnatinn of Airborne Rndinindine - Tables 13 and 14 (Cont'd)
I-131 has been detected in the past at control and indicator locations and was attnbuted to past weapons testing, the Chernobyl accident, and, to a lesser extent, plant operations. For example, during 1986, I-131 was detected at the controland I indicator locations. This was a result of the 1986 Chernobyl Nuclear Plant accident. 'Ihe I-131 mean concentration at the control location was 0.151 pCi/m' and 0.119 at the indicatorlocations. I-131 was not detected at the control location I during the period 1987 through 1996.
Prior to the Chernobyl accident of 1986, I-131 had been detected intermittently I during the years of 1976-1985. Concentrations ranged from 0.013 to 0.33 pCi/m' at indicator locations. During this same period, I-131 was also detected at the control locations at concentrations ranging from 0.030 to 0.60 pCi/m'. For the l
most part, I-131 in indicator and control locations was a result of past weapons testing fallout. A small portion of the concentrations detected may have been a l result of site operations.
Tables 35 and 36 show the historical environmental sample data for airborne I radioiodine.
II. MILK A. samnle Collertion Methodology and Annlysis Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample is d awn, the tank contents are agitated from
[ three to five minutes to assure a homogenous mixere of milk and butterfat. Two gallons are collected during the first half and second half of .ach month from each of the selected locations within ten miles of the site and from a control location.
The samples are chilled, preserved with sodium bisulfite, and then shipped to the analytical laboratory within thirty-six hours of collection in insulated shipping containers.
k The selection of milk sample locations is based on maximum deposition factors (D/Q). Deposition factors are generated from average historical meteorological
[ data based on all licensed reactors. The Technical Specifications require three sample locations within 5.0 miles of the site with the highest calculated deposition
k4
(
4.0 TERRESTRIAL SAMPLES
' II. MILK (Cont'd)
A. Ramal, eniletian unehnaningy and Annlysis (ennt'd) factors. During 1996, there were no milk sample locations within 5.0 miles that could be sampled. However, there were several optional locations beyond five miles that were sampled.
[' A fourth sample location required by the Technical Specifications is located in a least prevalent wind direction from the site. This location is in the southwest sector and serves as a control location.
Milk samples are collected twice per month (April - December) and analyzed for gamma emitters and I-131. Samples are collected and analyzed in January - March in the event I-131 is detected in November and December of the pr~ading year.
The milk sample locations are found on Figure 2. (refer to Table 3 for location
[ daigantions and descriptions).
B. Evahintian of Mine Data - Tahlen 15 mad 16
{
Milk samples were collected from a total of four indicator locations (within 10 miles of the site) and one control location (beyond 10 miles from the site) during
{
1996. The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site. During 1996, there were no milk sample
[ locations within 5.0 miles of the site. The locations that were sampled during 1995 are located from 7.8 to 9.5 miles from the site. The only sample location required by the Technical Specifications during 1996 was the control location.
During 1996, milk samples were collected at each of the four indicator locations and the control location in the first half and the semul half of each month.
Samples were collected during the months of April through Deber 1996. Since I-131 was not detected during November and December of 1995, no additional samples were collected in January through March of 1996. For each sample, analyses were performed for gamma emitters (analysis by GeLi detector) and for I-131 using a resin extraction. Sample analysis results for gamma emitters are found on Table 15 and for I-131 on Table 16.
{
Gamma spectral analyses of the bimonthly samples showed only naturally
( occurring radionuclides such as K-40 and Ra-226 to be detected in milk samples during 1996. K-40 was detected in all indicator and control samples. Ra-226 occurred intermittently in milk samples. K-40 and Ra-226 are naturally occurring
[ radionuclides and are found in many of the environmental media sampled.
F 28-
l
[
4.0 TERRESTRIAL SAMI12S II. MILK (Cont'd)
B. Evahiatian of Mine nata - Tahlen 15 and 16 rant'd)
[.
During 1996, Cs-134 or Cs-137 were not detected in any control or indicator location milk samples. Cs-137 had been last detected in 1988 and was attributed
{.
to the use of silage containing trace amounts of Cs-137 from the 1986 Chernobyl Nuclear Plant accident. Evaluation of site historical milk data shows that Cs-137
[ has been detected in environmental milk samples at both indic2 tar (within 10 miles) and control locations (beyond 10 miles). Mean Cs-137 comentrations for 1976 -
1988 remained fairly consistent and ranged from 5.7 (1982) to'17.1 pCi/ liter
[ (1977) at the irvlientarlocations. No Cs-137 was detected in milk samples during 1989 through 1996.
( At the control location, Cs-137 had been detected intermittently during the years 1978 - 1982. Control samples were not obtained prior to 1978. Cs-137 ranged r from 3.9 - 5.8 pCi/ liter during this period. Results from 1986 showed a mean L-Cs-137 concentration of 8.4 pCi/ liter at the control location. The positive Cs-137 results during 1986 were a result of the Chemobyl Nuclear Plant accident. Cs-137 was not detected during 1987 through 1995 at the control location. Past Cs-137
{ in milk mmples is, for the most part, a result of previous weapons testing and more recently, the Chernobyl accident. The continued reduction of Cs-137 levels is a result of nuclear decay and ecological cycling.
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No other radionuclides were detected in milk samples using gamma spectral
( analysis.
Milk samples were collected and analyzed twice per month for I-131.1-131 was
[ not detected during 1995 in any of the indicator or control samples. All 1996 I-131 milk sample results are reported as the lower limit of detection (LLD). The LLD results for 1996 milk samples ranged from <0.26 pCi/ liter to 50.57 pCi/
{ liter.
[ An evaluation of historical data for I-131 in milk samples shows that annual mean I
results ranged from 0.19 pCi/ liter to 6.88 pCi/ liter at the indicator locations during 1976 - 1980. 1-131 during these years is a result ofintermittent weapons testing.
Results from 1986 showed that I-131 was detected at a mean concentration of 5.2
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pCi/ liter as a result of the Chernobyl accident. I-131 was not detected during the period 1987 through 1996 in milk samples.
f-Historical data for I-131 from the control location showed that I-131 was detected during 1980 at a mean concentration of 1.4 pCi/ liter. During 1986, I-131 from the control location showed a mean concentration of 13.6 pCi/ liter as a result of the
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4.0 TERRESTRIAL SAMPLES II. MILK (Cont'd)
B. Evninntinn of Mille Data - Tahlen 15 and 16 (Cant'd)
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Chemobyl necident. I-131 was not detected during the period 1987 through 1996 at the controllocation.
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Tables 37 and 38 show the historical environmental sample data for milk.
f Durmg 1996, only naturally occurring radionuclides such as Ra-226 and K-40 were detected in milk samples. Therefore, no doses to man have been calculated.
III. FOOD PRODUCTS
( A. Ramnie en11actinn Methndniney and Annlysis
[ Food products are collected once per year during the late summer at the t approximate height of the harvest =cason. Approximately one kilogram of a brnadienf vegetable or other brnadW vegetation is collected from garden locations with the highest deposition factors (D/Q) based on average historical meteorological data. Five indicator semple locations were utilimi from at least two sectors. Additional samples may also be obtained. Control samples are also collected fmm available off-site locations 9 to 20 miles distant in a least prevalent
( wind direction. Control samples are of the same or of a similar type of vegetation.
All samples are shipped fiesh as soon as possible after collection.
f Food product samples are analyzed for gamma emitters (gamma isotopic analysis).
The gamma isotopic analysis also includes I-131.
Food product locations are shown on Figure 1 (refer to Table 3 for location designations and descriptions).
B. Evalnntinn of Fnnd Product Data - Tables 17A and 17B Food product samples collected during 1996 were comprised of garden vegetables and other types of vegetation. Samples were collected from five indicator locations and one control location. The indicator locations were represented by nearby gardens in areas of highest D/Q (deposition factor) values based on historical meteorology and all site release points at operating facilities. The control location
[ was represented by a garden location 9-20 miles distant in a least prevalent wind direction. Garden vegetables were comprised of kale, tomatoes, collard greens, and swiss chard, which are all (except tomatoes) considered broadleaf vegetables.
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4.0 TERRESTRIAL SAMPLES III. FOOD PRODUCTS (Cont'd)
B. Evninntinn of Fnnd Prnduct Data - Tahlen 17A and 17B (Pant'd)
Other broadleaf vegetation consisted of bean leaves, beet leaves, pepper leaves, grape leaves, squash leaves, and cucumber leaves. At the control location, one sample of each of the same or of a similar type of vegetable or vegetation was collected. Vegetables and vegetation were collected in the late summer harvest season (mid-September 1996).
Results for food products are shown on Tables 17A and 17B. Table 17A shows results in pCi/g (wet) while Table 17B results are in units of pCi/kg (wet). Several naturally occurring radionuclides were detected in food product samples during 1996. K-40 was detected in all samples of food products. Be-7, Ra-226 and Ac'Ih-228 were detectad intennittently in the vegetation samples. K-40, Be-7, Ra-226 and AcTh-228 are all naturally occurring radionuclides.
No other radionuclides were detected in the 1996 samples of food products.
Although not detected during 1996, a review of past environmental data indicates that Cs-137 has been daecread intermittently during the years of 1976 - 1995 at the indicator locations and during the years of 1980 - 1995 at the control locations (control samples were not obtained prior to 1980). During the period of 1977 -
1995, Cs-137 in fruits and/or vegetables sampled at indicator locations ranged in mean concentrations of 0.004 pCi/g (wet) in 1977 to 0.047 pCi/g (wet) in 1985.
Control sample results during 1980-1995 showed Cs-137 detected only twice during this period; once in 1980 at a concentration of 0.020 pCi/g (wet) and once in 1993 at a concentration of 0.007 pCi/g (wet).
Tables 39 and 40 show historical environmental sample data for food products.
IV. LAND USE CENSUS A. Methadalagy A land use census is conducted 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 residence census is conducted to identify the closest residence in each of the meteorological sectors.
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4.0 TERRFRTRfAL SAMPrTR IV. LAND USE CENSUS (Cont'd)
A. Methodningy (cont'd)
The milk animal census is an estimation of the number of cows and goats within an appmximate ten mile radius of the Nine Mile Point Site. A census is initiated
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once per year in the spring. The census is conducted by sending questionnaires to previous milk animal owners and also by road surveys to locate any possible new
( owners. In the event questionnaires are not answered, then the owners are contacted by telephone or in person. The local agricultural agency was also contacted.
A second type of census is a residence census. This census is conducted in accordance with the Technical Specifications in order to identify the closest
( re=Wnm within three miles in each of the 22.5 degree meteorological sectors. A residence, for the purposes of this census, is a residence that is occupied on a part time basis (such as a summer camp), or on a full time, year round basis. For the
[ residence census, several of the meteorological sectors are over Lake Ontario because the site is located at the shoreline. Therefore, there are only eight sectors over land where residences are located within 3 miles.
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During 1996, a residence census was conducted to identify the nearest residence in each of the sixteen 22.5 degree meteorological sectors within a distance of five miles from the site in order to provide more comprehensive census data. At this distance, some of the meteorological sectors are over water. These sectors include:
N, NNE, NE, ENE, W, WNW, NW, and NNW.
B. Evaluntinn of Data - Tables 18 and 19 The number of milk animals located within an approximate ten mile radius of the site was estimated to be 998 cows and 17 goats for the 1996 census. The number of cows increased by 30 and the number of goats increased by 10 with respect to the 1995 census. No new milk locations were identified during the 1996 census.
Most of the goats found on the census were milking goats. However, any milk produced was utilized by the owners and was not available for the sampling program. The results of the milk animal census are found on Table 18. Milk animal locations are shown on Figure 2.
The rr.sults of the 1996 residence census showing the applicable sectors and degrees
[ and distance of each of the nearest residences are found on Table 19. The nearest residences are shown in Figure 1. No changes were noted in 1996.
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5.0 INTFRLABORATORY COMPARTRON PROGRAM f
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5.0 INTERLABORATORY COMPARI5 ION PROGRAM A. Descrintion Technical Specification sections 3.6.21 and 3.12.3 for the Nine Mile Point Nuclear Station Unit I and Unit 2, respectively, require that a summary of the results obtained as part of an Interlaboratory Comparison Program be included in the Annual Radiological Environmental Operating Report. Prior to 1996, the results from the EPA Program Evaluation Studies Program were used to satisfy this requirement. At the end of 1995, the EPA discontinued the Performance Evaluation Program. A new cross check program was established and utilized during 1996 to replace the EPA program. This program consists of utihzing the Analytics commercial laboratory and the Environmental Measurements Laboratory (EML) to supply the required reference samples. Both of these laboratories provide a program which is traceable to the National Institute of Standards and Technology (NIST). The Analytics supplied program was effective the first quarter of 1996 (March) and the EML program became effective during the third quarter of 1996 (September).
The current interlaboratory comparison program with Analytics and EML exceeds the number of samples that were previously supplied by the EPA.
B. Results The following table summanzes the types of spiked, intercomparison samples received by Analytics and EML during 1996:
Media Analysis Annivtics EML Iotal Water Gross Beta 0 1 1 Water Tritium 1 1 2 Water I-131 2 0 2 Water Mixed Gamma 2 1 3 Air Gross Beta 2 1 3 Air I-131 2 0 2 Air Mixed Gamma 2 1 3 l Milk I-131 2 0 2 Milk Mixed Gamma 2 0 2 Soil Mixed Gamma 1 1 2 Vegetation Mixed Gamma 0 1 1 16 7 23
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5.0 INTMABORATORY COMPAkTSON PROGRAM B. Daenitt mant'd)
- 1. Annivtire Daenita
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Results of the samples received by Analytics as part of the 1996 Interlaboratory Comparison Program are summarized on Table 20. The
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Site Environmental Laboratory analyzed all spiked samples received from Analytics using standard laboratory procedures. In order to compare the
[ "known" quantity of radioactivity to the site laboratory results, the site laboratory submitted results to Analytics, who then issued a statistical summary report to the site laboratory. A Normali-l Deviation from the
( Known Value (NDKV) a%6sce criteria methodology was utilimi in order to evaluate the site laboratory's performance. Acceptable NDKV was determined to be between -3 arid 3 NDKV.
'Ihe 16 spiked samples from Analytics required 68 isotopic analyses and 2 gross beta analyses. All results, except for a single gamma analysis of Fe-
[ 59 in soil were within -3 and 3 NDKV. The Fe-59 analytical results for soil sample 96-06A had a calculated NDKV of 6.11 which placed the r results outside the acceptable limits. The nonconformity for Fe-59 was a l result of the low level of Fe-59 activity provided in the blind sample. The Fe-59 concentration of 0.17 pCi/gm was near the routine detection limit of analysis. One of the three analyses which made up the reported mean result
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was higher than the remaining two which biased the mean high. Seven other isotopes were present in the sample. The mean results for the other seven i=*ayn were within the +3 to -3 NDKV range and acceptable. The nonconformity does not indicate a laboratory systematic error.
- 2. EML Results Results of the samples provided by EML as part of the 1996 Interlaboratory
( Program are provided on Table 20. EML samples analyzed by the site envuonmental laboratory were analyzed for gross beta, tritium and gamma r emitting nuclides, as appropriate. Following analysis, results were t submitted to EML. Acceptance criteria (evaluating the laboratory's performance of these samples) differs from the Analytic sample evaluation.
EML determined performance utilizing the following criteria:
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Result Cumulative Normali7ed Distribution
( Acceptable 15 % - 85 %
Acceptable, with warning 5-15% or 85-95%
[ Not Acceptable < 5 % or > 95 %
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5.0 INTERLABORATORY COMPARISON PROGRAM B. Results (Cont'd)
- 2. EML Results (Cont'd)
Of the 17 analyses performed on the EML samples, none were found to be "Not Acceptable," thirteen were found to be " Acceptable" and four analyses were placed in the " Acceptable with Warnin;" category.
He two samples, which required two analyses each (total of four analyses) which resulted in an " acceptable with warning" evaluation were soil and vegetation samples. Each of these samples contained Cs-137 and Co-60.
De bias in the sample results were the result of density differences between the EML sample matnx and the JAF Environmental I2boratory calibration standards. W soilisotopic results were in the range of 28 % - 30% higher than EML known value. This is attributable to a difference in sample density compared to the calibration source density. The density of the EML sample was 0.20 gm/cc compared to the calibration source density of 1.33 gm/cc. This difference in density resulted in a sample analysis which is biased high. A similar evaluation can be made for the vegetation results.
W density of the EML sample is 0.30 gm/cc compared to the laboratory calibration source density of 1.15 gm/cc. Again, this difference in density provided a sample result which is biased high.
Neither of these sample results evaluations represent laboratory systematic error.
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6.0 HISTORICAL ENVIRONMENTAL SAMPIR DATA l
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6.0 HNTORICAL ENVIRONMENTAL S AMPIR DATA A. Deeriptinn Technical Specification requirements for the Annual Radiological Environmental Operating Report require a comparison of data from the current reporting period l with that of previous years REMP results, including pre-operational data if available. As such, each sample media section of this report provided a written discussion of the year 1996 results with previous years results. Data for all sample I media is additionally provided in tabular form for each year on Tables 21-40.
Tables 21 - 40 show historical environmental sample data for critical radionucliss or radionuclides routinely detected in environmental sample media. Data show the l minimum, maximum, and mean for each year evaluated. The data only consider hble quantities and do not consider lower limit of detection (LLD) quantities.
l Data on Tables 21 - 40 were obtained from previous Annual Radiological Environmental Operating Report tables.
B. Results The historical data provided on Tables 21-40 show a general decreasing trend of l detected radioactivity when compared with pre-operational and early operational data of the Nine Mile plants. 'Ihe majority of radioactivity detected throughout the years has been attributed to weapons testing fallout and natural background I radiation, with a small fraction attributed to plant operations. A combination of atmospheric weapons testing bans, ecological cycling and radioactive decay have resulted in the overall reduction in the concentration of radioactive materials I detected in environmental samples.
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I 7.0 CHANGFR AND EXCEFFIONS TO THE PROGRAM I
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l 7.0 CHANGES AND EXCEFFIONS TO THE PROGRAM A. Changes to the 1996 Samnie Program
- 1. Food product location J was added to the program during 1996. This is a new location which was added due to its higher D/Q.
- 2. Food product location Q was not utilized by the sampling program during I 1996 because of the higher deposition potential of location J.
B. Frcentions to the 1996 Samnle Program Exceptions to the 1996 sample program concerns those samples or monitoring requirements which are required by the Technical Specifications. This section implements section 3.6.20 of the Nine Mile Point Nuclear Station Unit 1 Technical Specifications and Section 3.12.1 of the Nine Mile Point Nuclear Station Unit 2 Technical Specifications.
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- Air radiciodine and part':ulate sampling required by the Technical Specifications l
i 1. Environmental air sample equipment at R-4 off-site sampling station l was found to be inoperable during the period 1/29/96 - 1/30/96 for approximately 31 hours3.587963e-4 days <br />0.00861 hours <br />5.125661e-5 weeks <br />1.17955e-5 months <br />. The breaker had tripped. Breaker was reset to bring station operational. ,
- 2. Environmental air sample equipment at R-5 off-site station was
[ inoperable on 8/20/96 from 0900 to 1200 hours0.0139 days <br />0.333 hours <br />0.00198 weeks <br />4.566e-4 months <br /> due to a localized I power outage in that area.
l No other sample downtime was observed during 1996 for any
- Technical Specification required air radiciodine and particulate sampling locations. Other occurrences of downtime for optional air sampling stations were documented for 1996. However, these occurrences were minimal and are not presented here because optional air sampling stations are not required by the Technical Specifications.
e Direct Radiation Measurements
- 1. Thermoluminscent Dosimeter (TLD) number 76 which is required by the Technical Specifications was discovered to be missing during the fourth quarter changeout. A new TLD was placed at that location.
I 7.0 CHANGES AND EXCEPTIONS TO THE PROGRAM B. Freentinne to the 1996 Ramnle Pmgram (Cont'd)
No other Technical Specification required TLDs were lost during 1996.
Other occurmnces of missing TLDs which were placed at optional locations were documented during 1996. However, these occurrences were minimal (1 occurrence) and are not presented here because the optional locations were not required by Technical Specifications.
C. Imwer I imit of De'actinn for Environmental Emmnles_
'Ihe Technical Specifications require that environmental samples analyzed for the Radiological Envuonmental Monitoring Program meet the lower limits of detection (LLD) found on Table 4.6.20-1 of the Nine Mile Point Unit 1 Technical Specifications and Table 4.12.1-1 of the Nine Mile Point Unit 2 Technical Specifications. All of the 1996 environmental samples required by the Technical Specifications which showed no net activity were less than the required values found on Table 4.6.20-1 and Table 4.12.1-1.
D. Devintions from the Interlahnrntary Comnarison Program Section 3.6.21 of the Nine Mile Point Unit 1 Technical Specifications and Section 3.12.3 of the Nine Mile Point Unit 2 Technical Specifications require the site to conduct an Interlaboratory Comparison Program. This section also requires that deviations from the sample schedules be reported in the Annual Radiological Environmental Operating Report.
During 1996, sample media for which environmental samples are routinely collected and analyzed, were obtained and analyzed. There were no deviations noted in the Interlaboratory Comparison Program.
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8.0 CONCLUSION
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8.0 CONCLUSION
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CONCLUSION The Radiological Environmental Monitoring Program (REMP) was established to detect and evaluate any possible impact to the envimnment surrounding the Nine Mile Point area resulting from operations at the site.
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Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the general environment or to man.
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In addition, the data was reviewed for any possible historical trophic level bioaccumulation trends. Little or no impact could be determined resulting from radionuclide deposition
( ma= Wring all sources (natural, weapons testing, etc.). In regards to doses as a result of man-made radionuclides, a significant portion of the small doses received by a member of the public was from past nuclear weapons testing. Doses as a result of naturally occurring
[ radionuclides, such as K-40, contributed a major portion of the total annual dose to members of the public.
( Any possible impact as a result of site operations is extremely minimal when compared to the impact from natural background levels or weapons testing. It has been demonstrated that almost all environmental samples contain traces of radionuclides which are a result of weapons testing or naturally occumng sources (primordial and/or cosmic related). Wimle body doses to man as a result of natural sources (naturally occurring radionuclides in the soil and lower atmosphere) in Oswego County account for approximately 50 mrem per year as demonstrated by control environmental TLD's. Possible doses due to site operations are a minute fraction of this particular natural exposure.
During 1996, the presence of one fission product radionuclide was noted in two different sample media. 'Ihese media included sediment and fish samples. The most likely source
( of this fission product is past weapons testing. The impact, expressed as a dose to man, from this radionuclide is minimal and insignificant when compared to the. natural background dose.
Therefore, as determined by review of the data presented herein, no impact due to j operations at the Nine Mile Point Nuclear Station was detected that would affect the health L and safety of the public.
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l 9.0 GENERAL REFERENCE MATERIAL
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i 9.0 GENERAL REFERENCE MATERIAL
- 1. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance with 10 CFR Part 50, Appendix I", March 1976 (Revision 0).
- 2. U.S. Nuclear Regulatory Commission Regulatory Guide 1.109, " Calculation of Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose of Evaluating Compliance With 10 CFR Part 50, Appendix I", October 1977 (Revision 1).
- 3. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, " Environmental Technical Specifications for Nuclear Power Plants", Deu:mber,1975.
- 4. U.S. Nuclear Regulatory Commission Branch Technical Position 16 Pquiatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program",
Revision 1, November 1979.
- 5. National Council on Radiation Protection and Measurements (NCRP),
f Environmental Radiation Measurements, NCRP Report No. 50,1976. .
- 6. National Council on Radiation Protection and Measure - "s (NCRP), Natural Rack7round Rndintion in the United Statec, NCRP Report No. 45, 1975.
- 7. National Couned on Radiation Protection and Measurements (NCRP), Cecium-137 fIQin the Envirnnment to Man- Metnhnlitm and Dose, NCRP Report No. 52, 1977.
- 8. National Council on Radiation Protection and Measurements (NCRP), Radiation Fxnnmure from Cnnenmer Prnducts and Miccellaneous Sourcec, NCRP Report No.
56, 1977.
- 9. International Commission on Radiological Protection (ICRP), Radionuclhie Release into the Environment Acceccment of Doses to Man, ICRP Publication 29,1979.
- 10. Eichholz, G. Environmental Aenects of Nuctant Power, First Edition, Ann Arbor Science Publishers, Inc., Ann Arbor, Michigan,1976.
- 11. Eisenbud, Merrill, Envirnnmental Rndianetivity, Second Edition, Academic Press, New York, NY 1973.
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- 12. 'Ihomas, C.W. etc al., Rndinnetive Fallout from chinese Nucienr Wennnna Test, September 26,1976. (BNWL-2164) Battelle, Pacific Northwest Laboratories, U.S. ERDA,1979.
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9.0 GENERAL RFFERENCE MATERIAL I
- 13. Pochin, Edward E., Estimated Population Ernosure ^pm Nuclear Power Production and Other Rndintion Sources, Nuclear Energy Agency, Organization for Economic Co-Operation and Development,1976.
- 14. Glasstone, Samuel and Jordan, Walter H., Nucient Power and Its Environmental Effects, First Edition, American Nuclear Society, I.a Grange Park, Ill.,1980.
- 15. U.S. Department of Health, Education, and Welfare. Radiological Henith Handbook. Bureau of Radiological Health, Rockville, Maryland 20852. January I 1970.
- 16. U.S. Department of Health and Human Services. Prenaredness and Resnonse in Radiation Accidents, National Center for Devices and Radiological Health, Rockville, Maryland 20857. August 1983.
I 17. National Council on Radiation Protection and Measurements (NCRP), Ioni7ing Rndintion Exoosure of the Population of the United States, NCRP Report No. 93, i 1987.
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10.0 DATA TABLFR - 1996 I
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TABLE 1 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONTIORING PROGRAM
- A. AQUATIC PROGRAM MEDIA ANALYSIS : FREQUENCY ,
LOCATIONS (1) ; i
- 1. Shoreline Sediment Gamma Spectroscopy 2/ Year 1 Inacator(2)
- 2. Fish Gamma Spectroscopy 2/ Year 2 Indicator (3),1 Control
- 3. Surface Water Gamma Spectroscopy Monthly Composite 1 Indicator (4),1 Control Tritium Quarterly Composite I th (4),1 Control B. DIRECT RADIATION
- 1. TLD Gamma Dose Quarterly 30 ih, 2 Cn= trol (S)
NOTES:
Sampling and analysis program as inguired by the Technical Specifications.
(1) Aquatic program indicator samples collected in the vicinity of the site; control samples collected at a distance of at least five miles from the site.
(2) Indicator sample from an area of potential recreational value.
(3) Indicator samples from an area near the vicinity of a site discharge point. Control samples of the same species or of species of similar feeding habits. 1 (4) Indicator sample from the J.A. Fitzpatrick inlet canal.
(5) Indicator sair.ples from the site boundary, four-five miles from the site, special interest areas and control areas (greater than ten miles from the site).
TABLE 2 SAMPLE COLLECTION AND ANALYSIS SITE RADIOLOGICAL ENVIRONMENTAL MONTIURING PROGRAM
- C. TERRESTRIAL PROGRAM MEDIA ANALYSIS FREQUENCYL LOCATIONS'
- l. Air Particulates Gross Beta Weekly 4 Indicator,1 Contml (1)
Gamma Spectroscopy Monthly Composite
- 2. Airborne - I-131 Gamma Spectmscopy Weekly 4 Indicator,1 Control (1)
- 3. Milk I-131 2/ Month 3 Indicator,1 Control (2)
Gamma Spectroscopy 2/ Month
- 4. Iluman Food Crops I-131 (4) Annually See note below (3)
Gamma Spectroscopy NOTES:
- Sampling and analysis program as required by the Technical Specifications.
(1) Three indicator samples from near the site boundary in three of the highest D/Q meteorological sectors, one indicator sample from near a year round community, and one control sample from an arm of least prevalent wind direction or previously established control location.
(2) Three indicator samples frora areas within 5.0 miles of the site. Control sample from an area in a Icest prevalent wind direction.
(3) Samples of three different kinds of broadleaf vegetation nearest to each of two different off-site locations of highest D/Q and one sample of each of similar broadleaf vegetation at least 9.3-20 miles distant in a least prevalent wind direction.
(4) Gamma spectral analysis to include I-131.
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L f m M TABLE 3 1996 ENVIRONMENTAL SAMPLE IDCATIONS SAMPLE !.fAP FIGURE . DEGREES &'
MEDIUM DESIGNATION NUMBER- LOCATION DESCRIPTION' - DISTANCE (1)
Shoreline Sediment 05* Figure 1 Sunset Bay 800 at 1.5 miles 06 Figure 1 Langs Beach, Control 2300 at 5.8 miles Fish 02* Figure 1 Nine Mile Point Transect 3150 at 0.3 miles 03* Figure 1 FitzPatrick Transect 550 at 0.6 miles 00* Figure 1 Oswego Transect 2350 at 6.2 miles Surface Water 3* Figure 2 FitzPatrick Inlet 700 at 0.5 miles 08* Figum 2 Oswego Steam Station Inlet 2350 at 7.6 miles 9 Figure 2 NMP Unit 1 Inlet 305o at 0.3 miles 10 Figure 2 Oswego City Water 240o at 7.8 miles 11 Figure 2 NMP Unit 2 Inlet 304o at 0.1 miles Air Radioimiine and Particulates R-l* Figure 3 R-1 Station, Nine Mile Point Road 88o at 1.8 miles R-2* Figure 4 R-2 Station, Lake Road 104o at 1.1 miles R-3
- Figure 4 R-3 Station, Co. Rt. 29 132o at 1.5 miles R-4
- Figure 4 R-4 Station, Co. Rt. 29 143o at 1.8 miles R-5* Figure 3 R-5 Station, Montario Point Road 42o at 16.4 miles Di Figure 4 D1 On-Site Station 690 at 0.2 miles G Figure 4 G On-Site Station 2500 at 0.7 miles H Figure 4 H On-Site Station 700 at 0.8 miles I Figure 4 I On-Site Station 98o at 0.8 miles J Figure 4 J On-Site Station 1100 at 0.9 miles K Figure 4 K On-Site Station 132o at 0.5 miles G Figure 3 G Off-Site Station, Saint Paul Street 225o at 5.3 miles D2 Figure 3 D2 Off-Site Station, RL 64 117o at 9.0 miles E Figure 3 E Off-Site Station, Rt. 4 1600 at 7.2 miles F Figure 3 F Off-Site Station, Dutch Ridge Road 1900 at 7.7 miles I
TABLE 3 (Continued) 1996 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE .. DEGREES &
MEDIUM DESIGNATION NUMBER LOCATION DESCRIPTION DISTANCE (1) 7hermoluminescent Dosimeters 3 Figure 4 D1 On-Site Station 69o at 0.2 miles (TLD) 4 Figure 4 D2 On-Site Imcation 1400 at 0.4 miles 5 Figure 4 E On-Site locatma 1750 at 0.4 miles 6 Figure 4 F On-Site location 2100 at 0.5 miles 7* Figure 4 G On-Site Station 2500 at 0.7 miles 8 Figure 3 R-5 Off-Site Station 42o at 16.4 miles 9 Figure 3 D1 Off-Site Imcation 800 at 11.4 miles 10 Figure 3 D2 Off-Site Station i17o at 9.0 miles 11 Figure 3 E Off-Site Station 160o at 7.2 miles 12 Figure 3 F Off-Site Station 190o at 7.7 miles 13 Figure 3 G Off-Site Station 225o at 5.3 miles 14* Figure 3 Southwest Oswego - Control 226o at 12.6 miles 15* Figure 3 West Site Boundary 2370 at 0.9 miles 18* Figure 4 Energy Information Center 265o at 0.4 miles 19 Figure 3 East Site Boundary 81o at 1.3 miles 23* Figure 4 H On-Site Station 700 at 0.8 miles 24 Figure 4 I On-Site Station 98o at 0.8 miles 25 Figure 4 J On-Site Station 1100 at 0.9 miles 26 Figure 4 K On-Site Station 132o at 0.5 miles 27 Figure 4 North Fence, JAFNPP 600 at 0.4 miles 28 Figure 4 North Fence, JAFNPP 68o at 0.5 miles 29 Figure 4 North Fence, JAFNPP 65o at 0.5 miles 30 Figure 4 North Fence, JAFNPP 57o at 0.4 miles 31 Figure 4 North Fence, NMP-1 276o at 0.2 miles 39 Figure 4 North Fence, NMP-1 292o at 0.2 miles 47 Figure 4 North Fence, JAFNPP 690 at 0.6 miles 49* Figure 3 Phoenix, NY - Control 170o at 19.8 miles 51 Figure 3 Oswego Steam Station, East 233o at 7.4 miles 52 Figure 3 Fitzhugh Park Elementary School, East 227o at 5.8 miles 53 Figure 3 Fulton High School 1830 at 13.7 miles 54 Figure 3 Mexico High School 115o at 9.3 miles 55 Figure 3 Pulaski Gas Substation, RL 5 750 at 13.0 miles m m M M M M
TAELE 3 (Continued) 1996 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE MEDIUM DESIGNATION NUMBER DEGREES &
LOCATION DESCRwnON Thamluminet Dosimeters 56* Figure 3 DISTANCE (1)
(TLD) 58* New Haven Elementary School Figum 3 County Route I and Alcan 123o at 5.3 miles (Contmued) 75* Figure 4 2200 at 3.1 miles North Fence, NMP-2 76* Figure 4 So at 0.1 miles North Fence. NMP-2 77* Figure 4 25o at 0.1 miles North Fence, NMP-2 78* Figure 4 45o at 0.2 miles East Boundary, JAFNPP 79* Figure 4 90o at 1.0 miles County Route 29 80* Figure 4 115o at 1.1 miles County Route 29 81* Figure 4 Miner Road 133o at 1.4 miles 82* Figure 4 Miner Road 1590 at 1.6 miles 83* Figure 4 181o at 1.6 miles IAeview Road 84* Figure 3 200o at 1.2 miles Lakeview Road 85* Figure 4 2250 at 1.1 miles North Fence, NMP-1 86* Figure 4 294o at 0.2 miles North Fence, NMP-1 87* Figure 4 315o at 0.1 miles North Fence, NMP-2 88* Figure 3 341o at 0.1 miles Hickory Grove Road 89* 97o at 4.5 miles Figure 3 leavitt Road 90* 1110 at 4.1 miles Figure 3 Route 104 and Keefe Road 91* 135o at 4.2 miles Figure 3 County Route SIA 92* 156o at 4.8 miles Figure 3 Maiden Lane Road 93* 183o at 4.4 miles Figure 3 County Route 53 205o at 4.4 miles 94* Figure 3 County Route I and Kocher Road 223o at 4.7 miles 95* Figure 3 IAeshore Camp Site 237o at 4.1 miles
%* Figure 3 Creamery Road 1990 at 3.6 miles 97* Figure 4 County Route 29 143o at 1.8 miles 98* Figure 3 Lake Road 101o at 1.2 miles 99 Figure 3 Nine Mile Point Road 88o at 1.8 miles 100 Figure 4 County Route 29 and IAe Road 104o at 1.1 miles 101 Figure 4 County Route 29 132o at 1.5 miles 102 Figure 3 Oswego County Airport 1750 at I1.9 miles 103 Figure 4 Energy Center, East 267o at 0.4 miles 104 Figure 3 Parkhurst Road 102o at 1.4 miles
}
-s2-
TACLE 3 (Continued) 1996 ENVIRONMENTAL SAMPLE LOCATIONS SAMPLE MAP FIGURE .. DEGREES & -
MEDIUM DESIGNATION i NUMBER LOCATION DESCRIPTION: DISTANCE (1)
Thermoluminescent Dosimeters 105 Figure 4 Lakeview Road 198o at 1.4 miles (TLD) 106 , Figure 4 Shoreline Cove, West of NMP-1 274o at 0.3 miles (Continued) 107 Figure 4 Shoreline Cove, West of NMP-1 272o at 0.3 miles 108 Figure 4 Lake Road 104o at 1.1 miles 109 Figure 4 Lake Road 103o at 1.1 miles 1II Figure 3 Sterling, NY - Control 214e at 21.8 miles 113 Figure 3 Baldwmsville, NY - Control 178* at 24.7 miles Cows Milk 50 Figure 2 Indicator location 93o at 9.3 miles 55 Figure 2 Indicator Imcation 950 at 9.0 miles 1 60 Figure 2 Indicator Iecation 90o at 9.5 miles 4 Figure 2 Indicator Iecaten 113o at 7.8 miles 73* Figure 2 Control location , 2340 at 13.9 miles Food Products J Figure 1 Indicator Imcation 110o at 2.1 miles R Figure 1 Indicator Imcation 97o at 1.8 miles S* Figure 1 Indicator location 940 at 1.9 miles K* Figure 1 Indicator Imcation 96o at 1.7 miles L Figure 1 Indicator Imcation I15' at 1.9 miles M* Figure 1 Control Location 225o at 15.6 miles
- - Technical Specification location.
(1) - Degrees and distance bent on Nine Mile Point Unit 2 reactor centerline.
M M . -
M M M
- e-- -
t-- m _ _ -- __ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ - _ _ _ _ _ _ _ . _ _ _ - _ _ _ _ _ _ _ _ _ _ _ _ _
TACLE 4 RADIOIDGICAL ENVIRONMENTAL MONTIDRING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 1996*
= INDICATOR : LOCATION (b) OF HIGitB5T CONTROLi NUMBER OF l TYPE AND NUMBER - LOCATIONS: ANNUAL MEANi LOCA110N & LOCATION: NONROUTINE MEDIUM (UNITS) OF ANALYSES
- ri n(s) MEAN (f) RANGE ' MEAN (O RANGE -
htBAN (O RANGEL REPORTS Shoreline Sediment
- GSAf4):
(pCi/kg-dry) Cs-134 150 < LIE <LLD <LLD 0 Cs-137 180 156 f2/2) Senset Bay: 156 (2/21 <LLD 0 130-183 1.5 at soo 130-183 Fish
- GSAf30): (h)
(pci/kg-wet) Mn-54 130 < LLD <LLD <LLD 0 Fe-59 260 < LLD < LLD Co-58
' <LLD 0 130 < LLD <LLD <LLD Co40 0 130 < LLD < LLD <LLD Zn-65 0 260 < LLD < LLD Cs-134
<LLD 0 130 < LLD < LLD < LLD Cs-137 0 150 15 (2/20) OSW: 16 f2/10) 16 (2/101 0 14-16 6.2 at 235o 14-18 14-18 Surface Water
- H-3 (8):
(pCi/ liter) H-3 < LLD 3000(c) < LLD <LLD 0 GSA (24):
<LLD 0 30 <LLD < LLD <LLD 0 Co-58 15 < LLD < LLD Co40
<LLD 0 15 < LLD < LLD < LLD 0 Zn-65 30 <LLD <LLD Zr-95
<LLD 0 15 <LLD < LID <LLD 0 Nb-95 15 < LLD < LLD <LLD 0 1-131 15(c) <LLD < LLD <LLD 0 Cs-134 15 < LLD < LLD <LLD 0 Cs-137 18 < LLD <LLD <LLD 0 Ba/12-140 15 < LLD <11 n <1 I n 0
_ _ _ _ _ _ - . . . . .. ~-. -. .. -
TA'sLE 4 (Continued)
RADIOLOGJCAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNTT 2 DOCKET NO. 50410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 1996*
INDICATOR T.DCATION (b) OF HIGHEST CONTROL- NUMBER OF.-
TYPE AND NUMBER LOCATIONS: ANNUAL MEAN: LOCATION &- LOCATION: NONROUTINE MEDIUM (UNITS) OF ANALYSES
- ll.D(a) MEAN (f) RANGE MEAN (f) RANGE : MEAN (f) RANGE REPORTS TLD* (mrem per Gamma Dose (127): (d) 14.7(119/119) TLD #85 (g) 24.7(4/4) 13.2(8/8) O quarterly period) 9.3-31.1 0.2 at 294o 21.2-31.1 10.1-17.2 Air Particulates* Gross Beta (260): 0.01 0.013(208/208) R-5 0.014(52/52) 0.014(52/52) O pCi/m' O.006-0.025 16.4 at 42o 0.009-0.023 0.008-0.023 I-131(260): 0.07 < LLD < LLD < LLD 0 GSAf60):
Cs-134 0.05 < LLD < LLD < LLD 0 Cs-137 0.06 < LLD < LLD < LLD 0 Milk
- GSA(90): (e) (b)
(pCi/ liter) Cs-134 15 <LLD <LLD < LLD 0 Cs-137 18 < LLD < LLD < LLD 0 Ba/La-140 15 <LLD < LLD <LLD 0 1-131(90): 1 <LLD < LLD < LLD 0 1-131 Food Products
- GSA(23):(h)
(pCi/kg-wet) I-131 60 < LLD < LLD < LLD 0 (broadleaf vegetation) Cs-134 60 < LLD < LLD < LLD 0 Cs-137 80 < LLD <LLD < LLD 0 M M M M M -
M M M M
TAELE 4 (Continued)
RADIOLOGICAL ENVIRONMENTAL MONITORING PROGRAM ANNUAL
SUMMARY
NINE MILE POINT NUCLEAR STATION UNIT 1 DOCKET NO. 50-220 NINE MILE POINT NUCLEAR STATION UNIT 2 DOCKET NO. 50-410 OSWEGO COUNTY, STATE OF NEW YORK, JANUARY - DECEMBER 1996*
TABLE NOTES:
- =
Data for Table 4 is based on Twhnical Specification required samples unless othenvise indicated.
(a) =
LLD values as required by the Radiological Technical Specifications. LLD units are specified in the medium colunm.
(b) =
Location is distance in miles and direction in compass degrees based on NMP-2 reactor center-line. Units for this column are specified in med (c) =
The Technical Specifications specify an I-131 and tritium LLD value for surface water analysis (non-drmkmg water) of 15 pCiniter a t
=
(d) ne Technical Specifications do rot specify a particular LLD value to environmental TLDs. De NMP-1 and NMP-2 Off-Site Dose Calculation Manuals cont specifications for environmenta' TLD sensitivities.
=
(e) ne Technical Specification criteria for indicator milk sample locations includes locations within 5.0 miles of the site. There are no milk sample locations within miles of the site. Herefore, the only sample location required by the Technical Specifications is the control location. Here were four optional indicator locations during 1996.
(f) =
Fraction of number of detectable measurements to total number of measurements. Mean and range results are based on detectable measurements only.
(g) =
ne results for TLD #85 must be evaluated with the knowledge that this TLD is in close proximity (300-500 feet) of the Nine Mile Point Unit I reactor building and the radwaste buildings. This TLD, as well as other TLDs in this area, are adjacent to the lake shoreline which is a restricted area to members of the public. Dere are no residences or private propeny near this arm.
l.
(h) =
Data includes results from optional samples in addition to samples required by the Technical Specifications.
4
TABLE 5A CONCENTRATION OF GAMMA EMITTERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/g (dry)$i 1 sigma SAMPLE COLLECTION -l .
I LOCATION DATE. Be-7 K 40 Co-60 Cs-134' Li Cs-137 Ra-226 - Ach-228 Other Langs Beach 4-25-96 <0.25 18.0 i 0.45 <0.04 <0.03 <0.04 0.82 i 0.30 0.49 i 0.06 <LLD (Control) 10 % < 0.31 11.3 i 0.29 <0.03 <0.03 <0.04 1.13 i 0.29 0.54 i 0.06 <LLD Sunset Beach 4-25-96 <0.44 17.4 i 0.64 <0.06 <0.04 0.13 i 0.02 2.26 i 0.43 0.54 i 0.09 < LLD (Off-Site)* 10-25-96 <0.34 17.4 0.57 <0.05 <0.03 0.18 i 0.02 1.32 i 0.34 0.87 i 0.08 < LLD
- Sample required by the Technical Specifications Results in units of activity per gram dry weight.
l M M M M M M M M M M M M M
TABLE 5B CONCENTRATION OF GAMMA EMTITERS IN SHORELINE SEDIMENT SAMPLES Results in units of pCi/kg (dry) i 1 sigma SAMPLE COLLECTION LOCATION DATE. Be-7' K40 Co40 Ce 134 7 Cs-137 Ra-226 : AcTh-228 - ditIERS -
Langs Beach 4-25-% <?5 18000 i 453 < 36 < 34 < 35 (Control) 10-25-96 <31 817 i 303 491 i 58 <LLD 15600 i 410 <31 < 25 < 35 1130 1 288 541 i 55 <LLD Sunset Beach 4-25-96 <44 17400 i 642 <60 < 42 130 i 22 2260 i 434 (Off-Site)* 10 % < 34 17400 i 566 <49 539 i 93 <LLD
<31 183 i 20 1320 i 341 872 i 79 <LLD
- Sample requimi by the Technical Specifications Results in units of activity ser kilorram dry weight
. TABLE 6A CONCENTRATION OF GAMMA FRITTERS IN FISH SAMPLES Results in units of pCilg (wet) i 1 sigma GAMMA EMITTERS SAMPLE DATE SAMPLE TYPE Fe-59 Co K-40 - Mn-54 Co40 Cs-134 - Cs-137 Zn45 Ra-226 UTHER OSWEGO (CONTROL)- 00 6-7 96 Whitesucker <0.08 <0.03 4.29 i 0.23 <0.03 <0.02 <0.03 <0.023 <0.06 <0.40 < LLD 6-7-96 Lake Trout <0.08 <0.03 3.75 i 0.19 <0.02 <d.02 <0.02 0.014 i 0.007 <0.04 <0.37 < LLD 6-7-% Brown Trout <0.08 <0.03 8.13 i 0.22 <0.02 <0.02 <0.02 <0.022 <0.05 1.1510.19 < LLD 6-7-% Smallmouth Bass <0.09 <0.04 4.02 i 0.25 <0.04 <0.03 <0.03 <0.029 <0.08 <0.43 < LLD 9-17-96 Whitesucker < 0.10 <0.04 9.64 t o.26 <0.03 <0.03 <0.02 <0.026 <G.05 0.8510.17 <LLD 9-17-96 Lake Trout #1 < 0.07 ' <0.03 3.06 i 0.16 <0.02 <0.02 <0.02 <0.016 <0.05 0.54 i 0.12 <LLD 9-17-% Lake Trout #2 < 0.11 <0.04 3.95 i 0.26 <0.04 <0.04 <0.03 <0.030 <0.08 0.36 i 0.17 < LLD 9-17-% Brown Trout <0.08 <0.03 4.50 i 0.21 <0.02 <0.02 <0.02 0.018 1 0.007 <0.06 0.4210.14 <LLD 9-17-96 Smallmouth Bass < 0.10 <0.04 3.88 i 0.24 <0.03 <0.03 <0.03 <0.026 <0.06 0.48 i 0.15 < LLD 9-17-96 Chinook Salmon <0.09 < 0.03 9.76 i 0.25 <0.03 <0.03 <0.02 <0.025 <0.04 0.39 0. I6 <II n NINE MILE POINT - 02 6-18-96 Whitesucker <0.06 <0.03 8.40 i 0.22 <0.02 <0.02 <0.02 <0.024 <0.04 0.87 i 0.18 < LLD 6-4-% Lake Trout < 0. I 1 <0.04 3.01 i 0.22 <0.04 <0.04 <0.03 <0.026 <0.07 <0.43 < LLD 6-4-% Brown Trout <0.08 <0.03 4.81 i 0.21 <0.02 <0.02 <0.02 <0.020 <0.06 <0.36 < LLD 6-4-% Smallmouth Bass <0.06 <0.02 2.99 i 0.19 <0.02 <0.02 <0.02 <0.018 <0.05 0.46 i 0.12 <LLD 9-26-96 Whitesucker <0.10 <0.03 4.77 i 0.24 <0.03 <0.03 <0.03 <0.026 <0.06 0.29 i 0.15 < LLD 10-8-% lake Trout #1 <0.06 <0.03 3.30 i 0.18 <0.02 <0.03 <0.02 0.014 i 0.007 <0.05 0.55 i 0.13 <LLD 10-8-96 Lake Trout #2 < 0.11 <0.04 4.10 i 0.30 <0.04 <0.04 <0.04 <0.040 <0.10 0.29 i 0.18 <LLD 9-25-96 Smallmouth Bass <0.08 <0.03 4.51 i 0.21 <0.02 <0.02 <0.03 0.016 0.007 <0.07 0.53 i 0.14 < LLD l 9-26-% Brown Trout <0.08 <0.03 4.57 i 0.24 <0.03 <0.03 <0.03 <0.021 <0.06 <0.42 < LLD 9-25-96 Walleye <0.10 <0.04 4.67 i 0.25 <0.03 < b.M <0.04 <0.028 <0.08 <0.46 <LLD l
l 1
l m ._
m m m
M M M M M M
T TABLE 6A (Continued)
CONCENTRATION OF GAMMA EMrITERS IN HSH SAMPLES Results in units of pCi/g (wet) i 1 sigma GAMMA EMTI'ERS SAMPLE DATE SAMPLE TYPE l Fe-59 Co-58 K-40 Mn-54' Co40 Co-134' Co-137 Zn45 Ra-226 OTHER JA FITZPATRICK - 03 6-12-% Whitesucker <0.07 <0.03 4.75 i 0.21 <0.02 <0.02 <0.02 <0.018 <0.06 < LLD 0.39 i 0.16 6-11-% Lake Trout <0.07 <0.03 4.18 i 0.20 <0.02 <0.02 <0.02 <0.018 <0.06 0.37 i 0.14 <LLD A18-% Brown Trout <0.05 <0.02 2.59 i 0.16 <0.02 <0.02 <0.02 <0.018 <0.04 0.48 i 0.12 < LLD o-i2-96 Smallmouth Bass <0.09 <0.03 3.34 i 0.23 <0.03 <0.03 <0.03 <0.029 <0.06 0.30 i 0.16 <LLD 10-2-% Whitesucker <0.07 <0.03 4.57 i 0.22 <0.02 <0.02 <0.02 <0.019 <0.06 <0.38 <LLD I0-8-% Lake Trout #1 <0.06 <0.02 3.07 i 0.20 <0.02 <0.02 <0.02 <0.020 <0.05 0.4310.12 <LLD 10-8-% Lake Trout #2 <0.06 <0.02 2.53 i 0.17 <0.02 <0.02 <0.02 <0.019 <0.05 0.4610.13 < LLD 10-2-96 Smallmouth Bass <0.10 <0.04 3.77 i 0.25 <0.03 <0.03 <0.03 <0.028 <0.08 0.33 i 0.15 <LLD 10-2-% Chinook Salmon <0.09 <0.04 4.68 i 0.28 <0.03 <0.03 <0.03 <0.031 <0.06 < 0.41 <LLD 10-8-% Walleye <0.07 <0.03 11.0 i 0.28 <0.03 <0.03 <0.02 <0.028 <0.05 0.78 i 0.20 < LLD
TABLE 6B CONCENTRATION OF GAMMA EMITTERS IN FISII SAMPLES 'l Results in units of pCl/kg (wet) i 1 sigma GAMMA EMITTERS !
SAMPLE DATA SAMPLE " Y1 E Fe-59 Co-58 K-40 Mn Co-60 Cs-134 Cs-i37 Zn45 Ra-226 OTHER i
OSWEGO ( CONTROL)-00 j 6-7-96 Whitesucker < 77 < 33 4290 i 229 < 29 < 24 < 29 < 23 < 64 < 403 < LLD 6-7-96 1.ake Trout < 80 < 26 3750 i 190 <21 < 22 <21 14 i 7 < 39 <372 <LLD 6-7-% Brown Trout < 75 < 30 8130 i 222 < 25 < 24 < 18 <22 <51 6-7-96 Il50 i 192 <LLD Smallmouth Bass < 89 < 40 4020 253 < 36 <27 < 30 < 29 < 79 < 434 < LLD 9-17-96 Whitesucker < 96 < 36 9640 i 257 <31 < 28 < 20 <26 < 49 846 i l73 <LLD 9-17-96 12ke Trout #1 < 66 < 26 3060 i l62 < 18 < 20 < 16 < 16 < 46 536 1 121 <LLD 9-17-% lake Trout #2 < 113 <41 3950 i 257 <36 < 36 < 32 < 30 < 79 363 i 166 < LLD 9-17-% Brown Trout <81 <31 4500 i 209 < 24 < 24 < 22 18 i 7 <61 422 i 139 < LLD 9-17-% Smallmouth Bass <98 <38 3880 i 236 < 29 <33 <31 < 26 < 62 477 1 148 <LLD 9-17-% Chinook Salmon <91 < 34 9760 i 246 < 29 <26 < !7 <25 < 44 393 - 746 <LLD NINE MILE POINT -02 6-18-% Whitesucker < 57 < 26 8400 i 224 < 24 < 22 < 18 <24 <41 870 i 185 <LLD 6-4-% Lake Trout < 109 <43 3010 i 225 < 36 < 35 < 28 < 26 < 74 < 427 < LLD 6-4-96 Brown Trout <78 < 26 4810 i 208 < 20 <21 < 20 <20 <58 < 364 <LLD 6-4-% Smallmouth Bass <58 < 23 2990 i 186 < 20 < 22 < 15 < 18 <51 <LLD 458 i 117 9-26-% Whitesucker < 95 < 34 4770 i 242 < 28 < 29 < 32 <26 < 57 <LLD 294 i 150 10-8-% lake Trout #1 < 55 < 29 3300 i 183 <21 < 25 <21 14 i 7 <52 <LLD 546 i 132 10-8-% Lake Trout #2 < 113 <44 4100 i 295 <38 <37 < 35 < 40 < 103 < LLD 288 i 183 9-25-% Smallmouth Bass < 82 <31 5300 i 135 < 24 < 20 < 24 16 i 7 < 67 530 135 <LLD 9-26-% Brown Trout < 84 < 33 4570 i 241 < 28 < 28 < 26 <21 < 65 <423 < LLD 9-25-96 Walleye < 103 < 38 4670 i 247 < 30 < 32 < 29 <28 < 76 < 461 <t i n M M M M M M M M M M
r r1 e em rm rm rm rm r u v r r r r e TABLE 6B (Continued)
CONCENTRATION OF GAMMA EMITTERS IN FISH SAMPLES Results in units of pCl/kg (wet) i 1 sigma GAML A EMITIERS SAMPLE DATE SAMPLE TYPE Fe-59 Co-58 K-40 Ma-54 Co-60 ' Ce-134 ' Ce-137 Za-65 Ra-226 ' OTHER J. A. FITZPATRICK - 03 6-12-% Whitesucker <68 <26 4750 i 210 <20 <22 <22 < 18 <58 386 i 160 < LLD 6-11-96 lake Trout < 66 < 26 4180 i 198 < 22 <24 < 18 < 18 <59 <LLD 369 i 137 6-18-% Brown Trout <51 < 18 2590 i 161 < 22 < 19 < 19 < 18 < 44 481 i 116 <LLD 6-12-96 Smallmouth Bass <90 < 33 3340 i 227 < 32 < 32 < 26 <29 < 64 296 i 155 <LLD 10-2-% Whitesucker < 69 < 28 4570 i 222 < 24 < 23 < 23 < 19 < 64 < 379 <LLD 10-8-% Lake Trout #1 <56 <22 3070 i 197 <l8 < 18 < 19 < 20 <53 430 i 124 <LLD 10-8-% Lake Trout F2 < 55 < 23 2530 i 174 < 18 < 23 <22 < 19 < 45 457 i 130 <LLD 10-2-% Smallmouth Bass < 100 < 36 3770 i 250 < 30 <31 < 32 < 28 < 77 330 i 146 < LLD 10-2-% Chinook Salmon < 94 < 37 4680 i 276 < 32 < 34 <31 <31 < 57 <413 < LLD 10-8-96 Walleye <71 <33 1100 i 281 < 32 <27 < 20 < 28 < 52 781 i 204 < 11.n
r TADLE 7 l
CONCFN' RATION OF GAMMA EMTITERS IN SURI< ACE WATER SAMPLES l Results in units of pCl/ liter i 1 sigma t
I LOCATION: FITZPA'ILCK 'NLET* 1996 l NUCUDE J/(UARY FEBRUARY MARCH APRIL .MAY ' JUNE K-40 222 2 18 206 i 17 < 37 46 i 1I 702 1 20 181 i 21
[ Ra-226 54 2 25 87 i 28 66 i 22 86 i 24 79 i 25 < 84 Cs-134 <2.79 < 3.14 < 2.50 < 2.56 < 2.03 < 4.58 Cs-137 < 7 "3 < 2.78 < 2.59 < 2.61 < 2.73 < 3.76 Zr-95 < 6.68 <5.24 <5.65 < 6.23 <5.19 < 6.84 Nb-95 < 4.07 < 3.50 < 3.62 < 4.26 < 3.94 < 4.48 Co-58 < 3.51 < 3.22 < 3.56 < 2.84 < 3.31 < 4.08 Mn-54 < 2.68 < 3.04 < 2.95 < 2.81 < 2.64 < 4.22 Fe-59 < 6.57 < 7.20 < 7.01 < 7.07 < 7.01 < 9.35 Co-60 < 2.86 < 2.80 < 2.70 < 3.62 < 2.71 < 4.58 Zn-65 < 6.50 < 7.49 < 6.32 < 7.50 < 4.19 < 10.7 I-131 <0.66 <0.30 <0.35 <0.70 <0.44 < l.0 Ba/La-140 < 8.22 < 7.85 < 8.21 < 8.38 < 7.02 < 10.4 NUCLIDE JULY. ~ AUGUST SEPTEMBER - -OCTOBER NOVEMBER DECEMBER K-40 34 i 12 191 i 19 58 i 11 888 i 26 208 i 16 50 i 11 Ra-226 64 i 23 80 i 25 90 i 21 113 i 32 62 1 23 83 i 22 Cs-134 < 2.48 < 4.08 <l.97 < 2.48 < 3.04 < 2.44 Cs-137 < 2.56 < 3.60 < 2.48 < 3.51 < 2.65 < 2. I 1 Zr-95 < 4.83 < 7.46 <5.08 < 6.47 < 5.11 <5.32 Nb-95 < 3.35 < 4.50 < 3.04 < 4.18 <3 22 < 3.35 Co-58 < 2.91 < 4.43 < 2.62 < 3.63 < 3.06 < 3.07 Mn-54 < 2.19 < 3.57 < 2.41 < 3.44 < 2.72 < 2.63 Fe-59 <5.98 < 9.23 < 6.53 < 7.16 < 8.22 <5.89 Co-60 < 3.07 < 3.83 < l .% < 3.12 < 2.65 < 3.07 Zn-65 < 6.55 < 8.26 < 6.34 <5.08 < 6.11
<0.80 I-131 Ba/1 a-140 < 6.15
< 0.31
< 11.2
<0.50
< 6.62
<0.70
< 6.23
<0.46
< 7.81 l<<5.s9 0.38 l< 8.03
- - Sample required by the Technical Specifications.
TABLE 7 (C __4 CONCENTRATION OF GAMMA EMrITERS IN SURFACE WATER SAMPLES Resuhs in amits of pCi/ Beer i 1 siguen LOCATION: NINE MILE POINT U-1 (INLET)** 1996 NUCLIDE - JANUARY- FEBRUARY
- MARCl4 - APRIL -MAYJ JUNE K-40 165 i 24 47 i 11 184 1 20 205 i 21 259 i 18 44 i 11 Ra-226 80 i 32 37 i 15 <78 <92 <70 71 i 22 Cs-134 <5.40 < 2.58 < 4.07 < 4.51 < 2.69 Cs-137 < 4.31 < 2.23
< 2.83 < 4.42 <4.06 < 2.86 Zr-95 < 9.68 <2.48
< 6.07 < 8.74 < 7.98 Nb-95 <5.55 <5.46
<5.84 < 3.29 <5.78 <5.34 Co-58 < 3.19 < 3.71
<5.47 < 2.% < 5.11 < 4.37 Mn-54 < 3.31 < 2.55
<5.05 < 2.81 < 4.91 < 4.05 Fe-59 < 2.83 < 2.53
< 13.0 <7.02 < 9.20 < 10.1 Co-60 < 7.74 < 6.36
< 6.43 < 3.04 < 3.88 <5.01 Zn-65 < 3.05 <2.80
<11.4 < 6.48 < 9.82 < 8.81 1-131
< 6.02 <5.58
<11.7 < 6.67 <14.7 < 12.9 Ba/La-140
<8.18 <9.72
< 12.3 < 8.53 <t3.7 < 10.1 <8.19 < 10.5 NUCLIDE ~ JULY ' AUGUST . ' SEPTEMBER
_ OCIDBER l' NOVEMBER DECEMBER K-40 191 i 16 40 i 12 168 i 16 54 i 12 BIS i 24 48 i 11 Ra-226 <70 76 i 20 79 i 25 Cs-134 92 i 22 < 85 87 i 22
< 2.98 <l.74 < 2.93 <l.94 Cs-137 < 2.29 < 2.35
< 2.81 < 2.23 < 2.72 < 2.25 Zr-95 < 3.16 < 2.25
<5.04 < 4.56 < 4.75 < 4.45 < 6.45 < 4.86 Nb-95 < 3.26 < 3.03 <3.36 < 3.02 < 4.47 < 3.13 Co-58 < 3.15 < 3.05 < 3.40 < 2.71 < 3.69 < 2.%
Mn-54 < 3.03 < 2.47 < 2.67 < 2.54 < 3.49 < 2.65 Fe-59 <7.92 <6.I8 < 8.12 < 6.47 < 7.66 < 3.83 Co-60 < 3.13 < 3.07 <3.13 < 2.80 < 2.95 < 3.19 Zn-65 < 6.12 < 6.48 < 6.69 < 6.62 <5.34 < 6.81 131 < 8.57 < 6.44 < 7.97 < 7.84 <11.1 < 7.48 Ba/La-140 < 7.03 < 6.98 < 6.80 < 9.33 < 6.34 < 8.36
- - Optional sample location. Sample not required by the Techmcal Specifications.
TABLE 7 (Continued)
CONCElWRATION OF GAMMA EMTITERS IN SURFACE WATER SAMPLES Results in units of pCi/ liter i I sigma LOCATION: NINE MILE POINT U-2 (INLET)" 1996 NUCLIDE JANUAPY FEBRUARY MARCH f APRIL. MAY. JUNE-K-40 239 t 19 858 i 24 695 i 22 208 i 26 245 i 22 56 i 11 Ra-226 67 i 23 155 i 31 129 i 27 53 i 30 177 i 32 58 i 24 Cs-134 < 2.11 < 3.07 < 2.07 < 4.96 < 4.94 < 2.17 Cs-137 < 2.99 < 3.24 < 3.17 <5.16 < 3.79 < 2.07 Zr-95 < 6.35 <5.90 < 6.20 < 8.87 < 7.98 <5.17 Nb-95 <4.I8 < 4.01 < 4.24 < 5.31 < 4.94 < 3.19 Co-58 < 3.5- < 3.67 < 3.36 <5.23 < 4.03 < 2.72 Mn-54 < 3.39 < 3.27 < 3.22 <5.74 < 4.49 < 2.70 Fe-59 < 6.68 < 7.34 < 7.67 <11.4 < 9.35 < 4.90 Co-60 < 2.74 < 2.98 <2.95 <5.10 < 4.73 < 2.55 Zn-65 < 7.30 <5.43 < 6.15 <11.3 < 9.71 < 6.12 I-131 < 9.41 < 10.3 < 13.2 < 14.6 <11.5 < 7.59 Ba/La-140 < 8.68 <6.I8 < 6.92 < 13.2 < 8.99 < 7.63 NUCLIDE JULY. AUGUST SElrTEMBER ~ OCTOBER NOVEMBER- DECEMBER K-40 205 i 23 212 i 16 51 i 11 204 i 17 230 i 22 184 i 16 Ra-226 71 i 30 84 i 25 61 i 23 < 17 148 i 34 <71 Cs-134 < 4.21 < 3.27 < 2.27 < 2.39 < 4.54 < 2.74 Cs-137 < 4.32 < 3.01 < 2.04 < 2.78 < 3.81 . < 2.75 Zr-95 < 9.26 <5.39 <5.02 < 5.91 < 7.75 <5.95 Nb-95 <5.38 < 3.46 < 2.80 < 3.81 <5.10 < 3.41
, Co-58 < 4.91 < 3.32 < 2.88 < 3.36 < 4.54 < 3.89 Mn-54 < 4.83 < 2.94 < 2.42 < 3.25 < 4.41 < 3.21 Fe-59 < 10.6 < 7.90 <5.95 < 8.27 < 9.17 < 7.84 Co-60 < 4.62 < 2.88 < 2.62 < 3.07 <4.I8 < 2.72 Zn-65 < 9.92 < 6.01 < 6.60 < 6.20 < 8.84 < 6.92 I-131 < 12.7 < 8.56 < 6.91 < 8.92 < 12.0 < 9.39 Ba/la-140 < 12.8 < 7.71 <8.39 < 7.35 < 10.1 < 9.13
- - Optional sample location. Sample p_o! required by the Technical Specifications.
M -
M M M M
TABLE 7 (f'a=si===d)
CONCEFERATION OF GAMMA EMTITERS IN SURFACE WA'ITR SAMPLES Resuhs in umhs m: et4/Iher i I sigra LOCATION: OSWEGO STEAM STATION
- 1996 NUCLIDE .- JANUARY ~ FEBRUARY? ' MARCH APRIL iMAY= . JUNE K-40 64 i 11 44 i 11 216 i 17 728 i 23 <30 184 i 24 Ra-226 88 i 22 <72 til i 23 118 i 26 77 i 25 < 87 Cs-134 <l.77 < 2.58 < 2.77 < 2.21 < 3.03 <4.72 Cs-137 < 2.89 < 2.31 <2.81 < 3.24 <2.80 < 4.84 Zr-95 <5.47 < 4.87 <5. I 1 <5.68 <5.86 < 9.37 Nb-95 < 3.47 < 3.60 <3.60 < 3.97 < 4.12 < 6.44 Co-58 < 2.91 < 3.16 < 3.24 < 3.35 < 3.00 <5.72 Mn-54 < 2.93 < 2.56 < 3.37 < 2.79 < 2.93 <5.39 Fe-59 < 7.34 < 6.51 <6.88 < 7.45 <7.90 <11.6 Co-60 < 2.98 < 2.97 < 3.05 < 2.96 < 2.76 <5.22 Zn-65 < 6.93 < 6.48 < 6.99 < 6.01 < 6.81 <11.0 1-131 <0.59 <0.30 <0.35 < 0.90 <0.48 < 1.0 Ba/La-140 < 6.79 < 7.52 < 6.40 < 5.41 < 9.55 < 12.2 NUCLIDE - ' JULY: 3 AUGUST SEITEMBER 2 OCTOBER NOVEMBER $ DECEMBER K-40 < 30 222 i 22 205 i 22 245 i 22 221 i 22 210 i 22 Ra-226 81 23 70 i 31 113 i 31 46 i 25 59 i 28 91 i 35 Cs-134 < 2.63 < 4.60 < 4.49 < 4.99 < 4.60 < 3.32 Cs-137 < 2.72 < 4.13 <3.84 < 4.22 < 4.33 < 3.47 Zr-95 < 6.16 < 6.41 < 7.29 <8.08 <7.86 < 7.49 Nb-95 < 3.54 < 4.91 < 4.72 < 4.94 <5.03 < 4.98 Co-58 < 3.21 < 3.97 < 4.69 < 4.71 < 3.95 < 4.95 Mn-54 < 2.54 < 4.00 < 4.35 < 3.75 < 4.22 < 4.16 Fe-59 < 7.46 < 9.05 < 9.35 < 9.44 < 8.95 <11.7 Co-60 < 2.87 <4.90 < 5.09 <4.18 < 4.34 < 4.43 Zn-65 < 7.28 <8.30 <8.91 < 9.54 < 9.44 < 10.5 1-131 <0.80 <0.29 < 0.50 <0.50 <0.56 <0.46 Ba/La-140 < 9.29 < 9.35 < 9.88 < 10.5 < 10.1 <11.3
- - Sample required by the Technical Specificehons.
. . - - - _ _ . . = _ . -- . = . .. . . .. .=- .. .. . _ . = . .
TABLE 7 (Continued)
CONCENTRATION OF GAMMA EMTITERS IN SURFACE WATER SAMILES Results in units of oCIAiter i 1 sigma LOCATION: OSWEGO CITY WATER ** 1996 NUCLIDE JANUARY FEBRUARY MARCH ' APRIL '.
MAY JUNE K-40 59 i 11 45 i 11 51 i 11 810 i 23 230 i 20 37 1 11 Ra-226 91 i 24 106 i 24 82 i 21 130 i 29 113 i 30 90 i 26 Cs-134 < 3.09 < 2.37 < 2.38 < 2.13 < 4.50 < 2.54 Cs-137 < 3.21 < 2.35 < 2.33 < 2.93 < 3.87 < 2.70 Zr-95 < 4.59 <5.43 <5.17 <5.89 < 8.15 < 6.20 Nb-95 < 2.95 < 3.66 < 3.72 < 4.05 < 4.21 < 3.17 Co-58 < 3.C4 < 3.44 < 3.00 < 3.10 < 4.56 < 3.36 Mn-54 < 2.63 < 2.69 < 2.82 < 2.95 < 3.66 < 2.31 Fe-59 <7.I/ < 6.23 < 4.75 < 7.26 < 8.70 <8.60 Co-60 < 3.10 < 3.20 < 3.07 < 3.02 < 4.32 < 2.82 Zn-65 < 6. 92 < 6.13 < 6.21 < 6.04 < 8.93 < 4.74 I-131 <S.56 < 10.3 < 9.47 < 11.4 <14.6 < 8.61 Ba/La-140 < 7.54 < 9.57 <8.25 < 6.34 < 11.1 < 10.9 NUCLIDE JULY AUGUST : SEPTEMBER - OCTOBER ' NOVEMBER DECEMBER K-40 164 t 24 38 i 11 41 i 13 < 34 233 i 22 222 i 21 Ra-226 < 88 52 i 21 110 i 25 77 i 25 87 i 33 < 78 Cs-134 < 4.97 < 2.56 < 2.41 < 2.61 < 4.74 < 2.89 Cs-137 <5.26 < 2.80 < 2.22 < 2.83 < 3.58 < 4.35 Zr-95 < 9.26 <5.79 <5.82 < 6.31 <7.91 < 8.44 Nb-95 <5.34 < 3.72 < 3.70 < 3.88 <5.22 <5.39 Co-58 < 6.15 < 3.11 < 2.86 < 3.04 < 4.46 < 5.32 Mn-54 <5.06 < 2.94 < 2.67 < 2.76 < 4.52 < 4.60 Fe-59 <l3.I < 6.75 < 7.72 < 7.85 <10.6 < 9.80 Co-60 < 4.99 < 2.81 <3.14 < 2.55 < 4.43 < 4.35 Zn-65 <11.9 < 6.07 < 6.49 < 7.12 < 9.71 < 10.4 1-131 < l 3.1 <5.30 < 7.22 < 7.17 <13.9 < 12.4 Ba/la-140 < 10.7 < 7.74 < 7.62 < 8.96 < 8.40 < 11.6
- - Optional sample location. Sample agt requim! by the Technical Specifications.
M M M M
4 TABLE 8 CONCENTRATION OF TRITIUM IN SURFACE WATER SAMPLES (QUARTERLY COMPOSITE SAMPLES)
Results in units of pCilliter f_1 slama LOCATION PERIOD DATE TRITIUM JAF INLET
- First Quarter 1/2/96 - 4/1/96 <230 Second Quarter 4/1/96 - 7/1/96 < 150 Third Quarter 7/1/96-9/3056 < 170 Fourth Quarter 9/30/96 - 1/2/97 < 190 NMP-1 INLET ** First Quarter 12/29/95 - 2/1/96 <220 Second Quarter 2/1/96 - 6/28/96 160 1 100 Hird Quarter 6/28/96 - 9/30/96 < 170 Fourth Quarter 9/30/96 - 12/31/96 < 190 NMP-2 INLET ** First Quarter 12/29/95 - 2/1/96 <240 Second Quarter 2/1/96 - 6/28/96 < 150 Third Quarter 6/28!96 - 9/30/96 < 170 ,
Fourth Quarter 9/30/96 - 12/31/96
< 190 OSWEGO CITY WATER **~ First Quarter 12/29/95 - 2/1/96 <230 Second Quarter 2/1/96 - 6/28/96 < 150 Hird Quarter 6/28/96 - 9/30/96 < 170 Fourth Quarter 9/30/96 - 12/31/96 < 190 OSWEGO STEAM STATION * \
First Quarter 12/29/95 - 2/1/96 (CONTROL)
<230 Second Quarter 2/1/96 - 6/28/96 <l50 Third Quarter 6/28/96 - 9/30/96 < 170 Fourth Quarter 9/30/96 - 12/31/96 <!90
- Sample required by the Technical Specifications.
- - Optional samp'e.
TAl2LE 9A DIRECT RADIATION MEASUREMENT RESULTS Results in units of mrem / standard month i 2 sigma i JANUARY ' APRIL JULY OCIDBER LOCATION LOCATION THROUGH: -THROUGHI 'll{R O U G H . .THROUGH '(DIRECITON &
NUMBER LOCATION MARCH JUNE L SEFIEMBER DECEMBER . DISTANCE)(2) 1996 3 D1 On Site 20.4 i 1.2 32.6 i 1.1 20.9 i 1.0 14.7 i 0.8 0.2 miles e 69o 4 D2 On Site 3.8 i 0.3 6.0 i 0.3 4.5 i 0.2 5.7 i 0.4 0.4 miles 6e 140o 5 E On Site 4.0 i 0.2 5.0 i 0.3 4.0 1 0.2 5.1 i 0.2 0.4 miles @ 175o 6 F On Site 3.1 i 0.1 4.0 i 0.2 3.6 i 0.3 4.3 i 0.3 0.5 miles @ 210e 7* G On Site 3.2 i 0.2 3.9 0.3 3.2 i 0.1 4.2 i 0.3 0.7 miles @ 250o 8 R-5 Off site-Control 4.0 i 0.1 5.5 i 0.6 4.6 i 0.2 (1) 16.4 miles @ 42o 9 DI Off Site 3.5 i 0.2 4.8 i 0.4 3.5 i 0.1 4.4 i 0.1 11.4 miles @ 800 10 D2 Off Site 3.4 i 0.1 4.5 i 0.4 3.6 i 0.2 4.6 i 0.3 9.0 mib @ l17e 1I E Off Site 3.3 i 0.3 4.4 i 0.2 3.6 i 0.2 4.8 i 0.3 7.2 mib @ 1600 12 F Off Site 3.4 i 0.5 4.3 1 0.3 3.8 i 0.1 4.6 i 0.1 7.7 miles @ 1900 13 G Off Site 3.5 i 0.1 4.6 i 0.4 3.7 i 0.1 4.8 i 0,1 5.3 miles @ 225o 14* DeMass Rd., SW Oswego-Control 3.7 i 0.1 5.6 i 0.6 4.0 i 0.1 5.1 1 0.3 12.6 miles @ 226o 15* Pole 66, W. Boundary-Bible Camp 3.3 i 0.1 4.0 i 0.2 3.2 i 0.1 4.4 i 0.3 0.9 miles @ 237o 18* Energy Info. Center - Lamp Post, SW. 4.1 i 0.1 4.9 i 0.3 4.2 i 0.1 5.1 i 0.4 0.4 miles @ 265o 19 East Boundary-JAF, Pole 9 4.0 i 0.2 4.7 i 0.2 4.2 i 0.2 5.4 i 0.4 1.3 miles @ Sto 23* 11 On Site 4.7 i 0.3 6.1 0.1 4.8 i 0.1 5.7 i 0.1 0.8 miles @ 70o 24 I On Site 4.0 i 0.3 5.0 i 0.4 4.3 i 0.3 5.2 i 0.2 0.8 miles @ 98o 25 J On Site 3.8 i 0.2 4.9 i 0.3 4.2 i 0.2 5.0 i 0.3 0.9 miles @ 110o 26 K On Site 3.8 i 0.3 4.5 1 0.1 3.9 0.3 4.7 i 0.1 0.5 miles @ 132o 27 N. Fence, N. of Switchyard, JAF 34.4 i 2.4 57.8 i 2.8 28.1 i 0.6 21.3 i 0.8 0.4 miles @ 60o l 28 N. Light Pole, N. of Screenhouse, JAF 39.6 i 3.3 59.9 i 8.6 28.6 i 2.2 30.6 1.1 0.5 miles @ 680 i 29 N. Fence, N. of W. Side Sche, JAF 41.1 i 3.3 68.1 i 5.2 30.5 i 3.1 26.9 i 2.2 0.5 miles @ 650 l 1
_ _ _ _ ~ -
TACLE 9A (Continued)
DIRECT RADIATION MEASUREMENT RESUL'IS Results in units of namn/ standard anoath i 2 sigina JaNUAR'Y ' APRIL iJULY.f OCTOBER LOCATION IECA710N
. NUMBER 111 ROUGH . THROUGH: 5THROUGH THROUGH . (DIRECrlON & -
LOCA'110N . MARCH 1 . JUNE SEPTEMBER DECEMBER _ DISTANCE)(2) 1996 30 N Fence (NW) JAF 31 18.1 i 1.9 29.3 i 2.4 16.1 i 0.2 12.8 i 1.0 0.4 niiles e 57o N Fence (NW) NMP-1 5.7 0.3 7.1 1 0.3 39 N Fence, Red Waste, NMP-1 5.7 i 0.1 7.6 i 0.3 0.2 niiles e 276o -
47 6.8 i 0.5 8.8 i 0.6 7.7 i 0.3 8.5 i 0.6 0.2 niiles @ 292o N Fence, NE, JAF 49*
8.8 i 0.8 13.4 i 0.9 7.5 i 0.6 7.4 i 0.7 0.6 iniles e 69o .
Phoenix. NY-Control 3.4 i 0.5 51 Litej & Bronson Sts. E. of OSS 4.1 i 0.2 3.4 i 0.2 4.3 i 0.3 19.8 smiles @ 170o 52 3.6 i 0.2 4.5 i 0.2 4.0 i 0.2 4.7 i 0.3 7.4 mailes e 233o East 12th & Cayuga Sts., Osw. School 4.2 i 0.2 53 Broadwell & Chestnut Sts., Fulton H.S.
4.4 i 0.2 3.7 i 0.2 4.6 i 0.0 5.8 mailes e 227o 54 4.0 i 0.2 5.0 i 0.3 4.1 i 0.2 4.9 i 0.2 13.7 iniles e 183o -
Liberty St., & Co Rt 16, Mexico H.S. 3.7 i 0.2 55 4.3 i 0.4 3.7 i 0.2 4.710.3 9.3 mailes e 115o Gas Substation & Co Rt 5 - PnI= min 3.5 i 0.1 4.5 i 0.2 56* 4.6 i 0.3 4.5 i 0.4 13.0 mailes @ 75o Rt 104 - New Haven School (SE Corner) 3.6 i 0.1 4.7 i 0.4 3.9 i 0.2 4.9 i 0.2 58* 5.3 nailes e 123o 75*
Co Rt I A - Alcan (E. of E. Entrance Rd.) 3.5 i 0.3 4.5 i 0.1 3.9 i 0.2 5.1 i 0.4 3.1 mailes e 2200 Unit 2, N. Fence, N. of Reactor Bldg. 5.5 i 0.2 .2 i 0.3 76* Unit 2 N. Fence, N. of Change House 6.1 i 0.0 7.0 0.4 0.1 iniles e So 77*
5.3 i 0.3 .5 i 0.4 5.3 1 0.2 (1) 0.1 niiles e 25o Unit 2, N. Fence, N. of Pipe Bldg. 6.2 i 0.3 .110.5 78* JAF, E. of E. Old lay Down Anes 6.7 i 0.3 7.1 i 0.5 0.2 niiles O 45o 79*
4.3 i 0.4 .1 i 0.3 4.2 i 0.2 5.3 i 0.3 1.0 mailes O 90o Co Rt 29, Pole #63,0.2 ani. S. of lake Rd 3.5 i 0.3 80* .1 i 0.1 3.6 i 0.1 4.5 i 0.2 1.1 niiles e 115o Co Rt 29, Pole #54,0.7 ini. S. of lake Rd 3.6 1 0.2 81* Miner Rd., Pole #16,0.5 ini. W. of Rt 29
.4 i 0.4 3.9 i 0.2 4.9 i 0.0 1.4 niiles e 133o 3.6 i 0.1 4.3 i 0.3 3.5 i 0.3 4.6 i 0.4 1.6 mailes e 159o 82* Miner Rd., Pole #1 I/2,1.1 ini. W of Rt 29 83*
3.5 i 0.2 4.6 i 0.5 3.7 i 0.1 4.8 i 0.1 1.6 nailes 0181o lakeview Rd, Tree,0.45 mi. N. of Miner Rd 3.7 i 0.2 4.5 i 0.3 3.8 i 0.2 4.9 i 0.2 1.2 uniles e 2000
TA'TLE 9A (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mmn/ standard month i 2 sigma JANUARYL b APRIL -JULY OCTOBER LOCA110N LOCATION .
THROUGH.. .THROUGH .THROUGH HIROUGH (DIRECTION &
NUMBER LOCATION MARCH . JUNE SEPTEMBER DECEMBER . DISTANCE)(2) 1996 84* Lakeview Rd. N, Pole #6117,200 Ft. N. of Lake Rd. 3.6 i 0.1 4.7 i 0.3 3.7 i 0.1 4.8 i 0.1 1.1 miles @ 225o 85* Unit 1, N. Fence, N. of W. Side of Screen House 7.1 i 0.1 8.9 i 0.8 7.2 i 0.4 9.0 1 0.3 0.2 miles @ 294o 86* Unit 2, N. Fence, N. of W. Side of Screen House 6.1 i 0.4 7.4 i 0.3 6.4 i 0.9 7.0 i 0.3 0.1 miles @ 315o 87* Unit 2, N Fence, N. of E. Side of Screen House 6.0 i 0.3 7.7 i 0.4 5.9 i 0.4 6.8 i 0.1 0.1 miles @ 341o 88* Hickory Grove Rd., Pole #2,0.6 mi. N. of Rt. I 3.5 i 0.1 5.0 i 0.3 4.1 i 0.3 4.7 i 0.2 4.8 miles @ 970 89* 12avitt Rd., Pole #16,0.4 mi. S. of Rt 1 3.7 i 0.3 4.8 i 0.2 4.2 i 0.2 4.8 i 0.2 4.1 miles @ lIto 90* Rt.104, Pole #300,150 Ft. E of Keefe Rd. 3.5 i 0.3 4.3 i 0.3 3.8 i 0.2 4.6 i 0.1 4.2 miles @ 135o 91* Rt. 51 A, Pole #59,0.8 mi. W. of Rt. 51 3.2 i 0.2 4.4 i 0.3 3.7 i 0.2 4.6 i 0.2 4.8 miles @ 156o 92* Maiden lane Rd., Power Polo,0.6 mi., S of Rt.104 3.5 i 0.2 5.0 i 0.3 4.4 i 0.2 5.3 1 0.2 4.4 miles @ 183o 93* Rt. 53, Pole 1-1,120 Ft. S. af 104 3.8 0.1 4.5 i 0.4 3.8 i 0.2 4.6 i 0.3 4.4 miles @ 205o 94* Rt. I, Pole #82,250 ft. E. af Kocher Rd. 3.8 i 0.2 4.8 i 0.1 3.6 i 0.1 4.6 i 0.2 4.7 miles @ 223o 95* Lakeshore Camp Site, fror. Alcan W, Access Rd., Pole #21,1.2 .
mi. N. of Rt. I 3.5 i 0.2 4.9 i 0.4 3.5 i 0.2 4.3 1 0.3 4.1 miles @ 237o 96* Creamery Rd.,0.3 mi. S. of Middle Rd., Pole 1 1/2 3.8 i 0.2 4.5 i 0.2 3.9 i 0.2 4.6 i 0.4 3.6 miles @ 1990 97* Rt. 29, Env. Station R4, 200 Ft. N. of Miner Rd. 3.8 i 0.1 4.2 i 0.2 3.6 i 0.1 4.4 i 0.2 1.8 miles @ 143o 98* Lake Rd., Pole #145,0.15 mi. E. of Rt. 29 4.1 i 0.1 5.3 i 0.4 4.0 i 0.1 4.9 i 0.0 1.2 miles @ 101o M M M M M M M M M M M M M M
TACLE 9A (Cordinued)
DIRECT RADIATION MEASUREMENT RESUL'IS Results in units of mmn/ standard month i 2 sigma JANUMJtY.. APRIL . IJUIX J OCTOBER LOCA'110N LOCATION THROUGH THROUGH :;lTHROUGH THROUGH (DIRECTION &
NUMBER LOCATION .MARCHi JUNE . N BER DECEMBER . DISTANCE)(2) 1996
- 99 NMP Rd.,0.4 miles N. of Lake Rd., Env. Station R1 Off-Site 3.8 i 0.2 5.6 i 0.4 3.9 i 0.2 4.8 i 0.2 1.8 miles @ 88o 100 Rt. 29 and lake Rd..' Env. Station R2 Off-Site 3.7 i 0.3 5.6 i 0.6 3.8 i 0.2 4.6 1 0.4 1.1 miles @ 104o 101 Rt. 29, 0.7 mi. S. of Lake Rd., Env. Station R3 Off-Site 3.6 i 0.3 4.4 i 0.2 3.6 1 0.3 4.2 1 0.2 1.5 miles @ 132o 102 EOF /Env. lab, Oswego Co. Airport (Fulton Airport), Rt.176, E. 3.6 i 0.2 4.8 i 0.3 3.8 i 0.2 4.5 i 0.3 11.9 iniles @ 175o Driveway lamp Post 103 EIC, East Garage Rd., lamp Post 4.1 i 0.2 5.8 i 0.4 4.2 i 0.2 4.9 i 0.3 0.4 miles @ 267o 104 Parkhurst Road, Pole 1481/2-A,0.1 mi. S. of Lake Rd. 3.6 i 0.2 4.9 i 0.4 3.9 i 0.3 4.4 i 0.2 1.4 miles @ 102o 105 Lakeview Road, Pole 6125,0.6 mi. S. of Lake Rd. 4.2 i 0.7 5.2 i 0.4 4.3 i 0.1 4.4 i 0.1 1.4 miles @ 198o 106 Shoreline Cove, E of NMP-1. True on W Edge 4.4 0.1 ; 6.4 i 0.4 4.6 i 0.3 5.3 i 0.3 0.3 miles @ 274o 107 Shoreline Cove, E of NMP-1, Tree 30 Ft. S. of TLD #10e 4.6 i 0.3 '
6.1 i 0.5 4.6 i 0.2 5.3 i 0.2 0.3 miles @ 272o 108 lake Rd. Pole #142 - 300' East of Co. Rt. 29 (S) 4.1 i 0.2 5.6 i 0.3 4.1 i 0.1 5.0 t 0.1 1.1 miles @ 104o 109 lake Rd. Tree 300' E. of Co. Rt. 29 (N) 3.9 i 0.0 4.9 i 0.4 3.9 i 0.2 4.7 i 0.4 1.1 miles @ 103o I11 Sterling, NY - Control Blasisk Residence 3.7 i 0.3 5.2 i 0.3 3.7 i 0.2 4.3 i 0.1 26.4 miles @ 166o 113 Baldwinsville, NY - Control Coates Residence 3.8 i 0.1 5.2 i 0.5 3.9 i 0.2 4.7 1 0.2 21.8 miles @ 214o (1) TLD lost in the field.
(2) Direction and distance based on NMP-2 reactor centerline and sixteca 22.50 sector grid.
- Technical Specification location i
I i
f r
I i
TABLE 9B DIRECT RADIATION MEASUREMENT RESULTS Results in units of mmn/ quarterly period i 2 sigma JANUARY-- APRIL JULY' OCTOBER LOCATION LOCATION THROUGH- THROUGH- THROUGH
IEROUGH. ' (DIRECfl0N &
NUMBER LOCATION ^ MARCH JUNE ' SEI4 EMBER DECEMBER DISTANCE)(2) 1996 3 D1 On Site 61.8 i 3.7 86.9 i 2.9 60.0 i 3.0 50.612,7 0.2 miles @ 69o 4 D2 On Site 10.9 i 0.7 18.8 i 0.9 14.1 i 0.8 19.3 i 1.4 0.4 mib @ 140o 5 E On Site 11.2 i 0.7 15.7 i 0.8 12.8 i 0.6 17.310.8 0.4 miles @ 175o 6 F On Site 9.5 i 0.4 12.010.7 10.1 i 0.8 14.5 i 0.9 0.5 miles @ 210e 7* G On Site 9.7 i 0.7 11.3 i 0.9 9.3 i 0.3 14.5 i 1.1 0.7 miles @ 250o 8 R-5 Off Site-Control 13.9 i 0.2 15.3 i 1.6 13.5 i 0.7 (1) 16.4 miles @ 420 l 9 D1 Off Site 11.910.7 13.9 i 1.1 10.1 i 0.3 14.9 i 0.3 11.4 miles @ 800 l 10 D2 Off Site 10.3 i 0.4 14.7 i 1.4 10.7 i 0.6 15.8 i 1.2
' 9.0 miles @ 117e 1I E Off site 9.3 i 0.8 13.1 i 0.6 11.510.6 16.2 i 1.0 7.2 miles @ 1600 12 F Off Site 9.6 i 1.3 12.8 i 0.9 10.8 i 0.3 15.6 i 0.3 7.7 miles @ 1900 13 G Off Site 10.7 i 0.4 14.0 i 1.2 11.9 i 0.3 16.1 i 0.2 5.3 miles @ 2250 14* DeMass Rd., SW Oswego-Control 11.2 i 0.4 16.9 i 1.7 12.9 i 0.4 ; 17.2 i 1.1 12.6 miles @ 226o i 15* Pole 66, W. Boundary-Bible Ca rep 11.4 i 0.3 11.6 i 0.7 10.2 i 0.3 15.0 i 1.0 0.9 r iles @ 237o 18* Energy Info. Center-Lamp Post SW. 12.8 i 0.4 14.1 i 0.8 12.2 i 0.3 17.3 i 1.5 0.4 miles @ 265o 19 East Boundary-JAF, Pole 0 12.7 i 0.5 14.5 i 0.6 12.1 i 0.5 18.2 i 1.4 1.3 miles @ 8to 23* 11 On Site 14.0 i 0.8 19.6 i 0.4 13.9 i 0.4 19.0 i 0.5 0.8 miles @ 700 24 I On Site 11.8 i 0.9 16.0 i 1.2 12.0 i 0.9 17.5 i 0.8 0.8 miles @ 98o 25 J On Site 11.2 i 0.6 15.4 i 0.8 11.7 i 0.5 17.3 i 0.9 0.9 miles @ l10o 26 K On Site 10.7 i 0.8 14.2 i 0.3 11.3 i 0.7 16.3 i 0.5 0.5 miles @ 132o 27 N. Fence N. of Switchyard, JAF 119.3 i 8.4 152.3 i 7.4 91.8 i 1.8 67.3 i 2.7 0.4 miles @ 60o 28 N Light Pole, N. of Screenhouse, JAF 137.2 1 11.3 157.7 i 22.7 93.5 i 7.2 97.0 i 3.4 0.5 miles @ 68o
l t
l i
TABLE 9B (Continued)
DIRECT RADIATION MEASUREMENT RESUUIS Results in units of unrema/ quarterly period i 2 signia JANUARY: APRIL }JULC OCTOBER' C LOCATION LOCATION :THROUGH 'THROUGH MDt00GH THROUGH . (DIRECTION & -
NUMBER LOCATION L MARCH 1 JUNE SEPTEMBER DECEMBER iDISTANCE) (2) ' i 1996 i
29 N Fence, N of W Side Screenhouse, JAF 142.4 i 11.5 179.2 i 13.7 l 99.7 i 10.1 85.3 i 7.0 0.5 tniles @ 65o i 30 N Fence (NW) JAF 52.8 i 6.6 77.1 1 6.4 52.6 i 0.8 40.4 i 3.0 0.4 miles e 57o 31 N Fence (NW) NMP-1 17.1 i 0.8 18.5 i 0.9 18.0 i 0.4 25.0 i 0.9 0.2 miles e 276o ;
39 N Fence, Rad Weste, NMP-1 20.5 i 1.4 23.2 i 1.6 24.7 i 1.0 29.4 i 2.0 D.2 miles @ 292o !
47 N Fence, NE, JAF 30.4 i 2.9 35.4 i 2.4 24.5 i 1.9 23.4 1 2.2 0.6 miles @ 690 49* Phoenix, NY-Control 10.5 i 1.4 12.5 i 0.7 '
i 10.110.5 14.4 i 0.9 19.8 niles @ 170o i 51 Liberty & Bronson Sts. E of OSS 10.8 i 0.5 13.6 i 0.6 11.6 i 0.7 15.6 i 0.9 7.4 miles e 233o 52 East 12th & Cayuga Sts., Oswego School 9.9 i 0.4 13.4 i 0.6 11.8 i 0.5 15.1 i 0.1 5.8 miles e 227o ;
53 Broadwell & Chestnut Sts., Fulton H.S. 11.7 i 0.6 15.1 i 1.0 13.3 i 0.7 16.2 i 0.8 13.7 miles e 183o 1 54 Liberty St., & Co Rt 16, Mexico H.S. 11.2 i 0.6 14.5 i 1.3 10.6 i 0.6 16.0 i 1.1 9.3 miles e 115o :
55 Gas Substation & Co Rt 5 - Pulasiti 12.1 i 0.4 12.9 i 0.5 9.0 i 0.6 15.3 i 1.2 13.0 miles O 75o 56* Rt 104 - New Haven School (SE Corner) 10.2 i 0.2 14.2 i 1.2 12.8 i 0.8 16.4 i 0.7 5.3 miles e 123o i 58* Co Rt I A - Alcan (E. of Entrance Rd.) 9.6 i 0.9 13.6 i 0.3 12.2 i 0.5 17.0 i 1.4 3.1 miles e 220o 75* Unit 2, N. Fence, N. of Reactor Bldg. 16.4 i 0.6 19.0 i 0.9 19.6 i 0.1 24.4 1.3 0.1 milm O So 76* Unit 2, N. Fence, N. of Chan8e House 16.1 i 0.8 17.0 i 1.0 17.0 i 0.6 (1) 0.1 miles e 25o :
77* Unit 2, N. Fence, N. of Pipe Bldg. 19.0 i 1.0 23.9 i 1.3 21.3 i 0.9 24.6 i 1.6 0.2 miles e 45o 78* JAF, E. of E. Old laydown Ans 11.8 i 1.1 16.7 i 1.0 11.5 i 0.6 18.0 i 1.0 1.0 miles @ 90o 79* Co Rt 29, Pole #63,0.2 mi. S. of Lake Rd 11.4 i 1.0 11.7 i 0.4 10.3 i 0.2 15.3 i 0.7 1.1 miles @ 1150 l 80* Co Rt 29, Pole #54,0.7 mi. S. of lake Rd 11.8 i 0.8 12.5 i 1.0 11.2 1 0.5 16.6 i 0.1 1.4 miles @ 133o ,
81* Miner Rd, Pole #16,0.5 mi. W. of Rt 29 12.5 i 0.5 12.3 i 0.8 10.1 i 0.9 15.7 i 1.2 1.6 miles e 159o 82* Miner Rd, Pole #1 1/2,1.1 mi. W of Rt 29 12.3 i 0.6 13.1 i 1.5 10.9 i 0.4 16.2 i 0.5 1.6 miles @ 181o ;
i
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TABLE 9B (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mmn/quaderly period i 2 sigma JANUARY . APRIL : JULY OCTOBER LOCATION LOCATION .
THROUGH THROUGH -THROUGH THROUGH (DIRECTION &
NUMBER . LOCATION . ~ MARCH JUNE SEPTEMBER DECEMBER DISTANCE)(2) 1996 83* Lakeview Rd., Tree,0.45 mi. N of Miner Rd 13.0 i 0.8 13.0 i 0.9 11.3 1 0.6 16.3 i 0.8 1.2 miles @ 200o 84* Lakeview Rd. N, Pole #6117,200 Ft. N. of Lake Rd. 12.2 i 0.3 13.5 i 0.7 10.7 i 0.4 16.3 i 0.5 1.1 miles @ 225o 85* Unit 1. N. Fence, N. of W Side of Screen House 21.2 i 0.4 23.3 i 2.2 23.2 1.3 31.1 i 0.9 0.2 miles @ 294o 86* Unit 2 N. Fence, N. of W Side of Screen House 18.5 i 1.3 19.5 i 0.8 20.5 i 2.9 24.4 i 1.1 0.1 miles @ 315o 87* Unit 2, N. Fence, N. of E Side of Screen House 18.0 i 1.0 20.2 i 1.1 19.0 i 1.4 23.4 i 0.3 0.1 miles @ 34to 88* Ilickory Grove Rd., Pole #2,0.6 mi. N. of Rt. I 10.7 i 0.4 15.0 i 0.9 13.110.9 15.7 i 0.7 4.8 miles @ 970 89* Leavitt Rd., Pole #16,0.4 mi. S. of Rt 1 10.4 i 0.9 14.5 i 0.7 13.5 i 0.5 16.1 0.6 4.1 miles @ lIto 90* Rt.104, Pole #300,150 Ft. E of Keefe Rd. 9.7 i 0.8 13.0 i 0.9 12.4 i 0.6 15.4 1 0.2 4.2 miles @ 135o 91* Rt. 51 A, Pole #59,0.8 mi. W. of Rt. 51 10.5 i 0.7 11.2 i 0.8 11.6 i 0.5 15.7 i 0.6 4.8 miles @ 156o 92* Maiden Lane Rd., Power Pole,0.6 mi., S. of Rt.104 10.8 i 0.5 15.0 i 0.9 13.9 0.5 18.2 i 0.6 4.4 miles @ 183o
@3* Rt. 53, Pole 1-1,120 Ft. S. of 104 11.8 i 0.5 13.6 i 1.1 11.9 i 0.7 15.5 i 1.0 4.4 miles @ 205o 04* Rt.1. Pole #82,250 Ft. E. of Kocher Rd. 13.2 i 0.7 12.3 i 0.1 11.4 1 0.3 15.3 i 0.8 4.7 miles @ 223o 95* Lakeshore Camp Site, from Alcan W. Access Rd., Pole #21,1.2 mi. N.
of Rt. I 10.6 i 0.6 14.6 i 1.3 11.0 i 0.5 14.7 i 0.9 4.1 miles @ 237o 96* Creamery Rd.,0.3 mi. S. of M.ddle Rd., Pole 1 1/2 11.8 i 0.5 13.6 i 0.7 12.2 i 0.5 15.8 i 1.2 3.6 miles @ 199o M M M M M M M M M M M M M M M
_ -_ ~ - - - - -
TABLE 9B (Continued)
DIRECT RADIATION MEASUREMENT RESULTS Results in units of mmn/ quarterly period i 2 sigma
' JANUARY- APRIL ' : JULYT _ OCf0BER LOCATION LOCATION THROUGH THROUGH *IEROUGH. _THROUGH NUMBER LOCATION (DIRECrlON &
MARCH JUNE SEPTEMBER DECEMBER ' DISTANCE) (2) .
1996 07* Rt. 29, Env. Station R4, 200 Ft. N. of Miner Rd. 13.0 i 0.4 11.7 i 0.5 10.6 i 0.2 14.9 i 0.7 1.8 miles @ 143o 98* Lake Rd., Pole #145,0.15 mi. E. of Rt. 29 12.3 i 0.2 16.7 i 1.2 11.5 i 0.2 16.9 i 0.2 1.2 miles @ 10lo 99 NMP Rd.,0.4 miles N. of Lake Rd., Env. Station R1 Off. Site 12.2 i 0.5 16.0 i 1.1 12.1 i 0.6 16.4 i 0.6 1.8 miles @ 88o 100 Rt. 29 and Lake Rd., Env. Station R2 11.9 i 0.9 17.5 i 1.8 10.9 i 0.4 15.7 i 1.3 1.1 miles @ 104o Off-Site .
101 Rt. 29, 0.7 mi. S. of lake Rd., Env. Station R3 Off. Site 11.6 i 0.9 102 13.2 i 0.7 10.0 i 0.8 14.310.8 1.5 miles @ 132o EOF /Env. lab, Oswego Co. Airport (Fulton Airport), Rt.176 E. 10.6 i 0.5 14.5 i 0.8 12.2 i 0.6 Driveway lamp Post 14.7 i 0.9 11.9 miles @ 175o 103 EIC, East Garage Rd., Lamp Post 12.8 i 0.7 16.5 i 1.2 12.2 i 0.6 16.6 i 0.9 0.4 miles @ 267o 104 Parkhurst Rd., Pole 1. 81/2-A,0.1 mi. S. of Lake Rd. 10.5 i 0.5 15.4 i 1.2 11.3 i 0.8 15.1 i 0.7 1.4 miles @ 102o 105 Lakeview Rd., Pole 6125,0.6 mi. S of Lake Rd. 12.8 i 2.0 106 14.8 i 1.0 12.5 i 0.3 15.0 i 0.5 1.4 miles @ 198o Shoreline Cove, E of NMP-1. Tree on W Edge 13.7 i 0.4 19.1 i 1.1 107 13.0 i 0.7 17.7 i 1.1 0.3 miles @ 274o Shoreline Cove, E of NMP-1. Tree 30 Ft. S. of TLD #106 14.2 t 0.9 108 18.2 i 1.5 12.910.5 17.9 i 0.6 0.3 miles @ 272o Lake Rd Pole #142 - 300* E of Co Rt 29 (S) 12.110.6 17.5 i 1.1 11.8 i 0.4 17.2 i 0.5 1.1 miles @ 104o 109 Lake Rd Tree. 300* E. of Co. Rt. 29 (N) 11.7 i 0.0 15.4 i 1.2 11.3 i 0.5 16.0 i 1.3 1.1 miles @ 103o til Sterling, NY - Control Blasisk Residence 11.2 i 0.8 113 15.6 i 1.0 12.3 i 0.6 14.2 i 0.4 26.4 miles @ 166o Baldwinsville, NY - Control Coates Residence 11.5 0.4 18.2 i 1.7 10.7 i 0.5 15.3 i 0.5 21.8 miles @ 214o (1) TLD lost in the field.
(2) Direction and distance based on NMP-2 reactor centerline and sixteen 22.5* sector grid.
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W w CCCCCCCCCC@ @@CCCCCCCCCCCCCC Co@ CCCCCCCCCCCC g CCCCCCCCCCC@
W z Q e ddddddddddddddddddddddddddd
+1+1+1+1+1+1+1+1+1+1+1+1+1+1+l+1+1+1+1+1+1+1+1+1+1+1+1 N M C c o m b m M b_ _CN_- emC=vm mMmNomimC@c g ---------
N O kkk kk kkkk k . . .k .k .k k cooCocoeceCCoCCCCoComeCocco . .
CcccCCccccccccccccccccccccc W
eeeeeeeeeeeeeeeeeeeeeeeeeee
~xmnmmnecmacmonn~xnnxmmecme W kkCNDkCCDkkCDDkCDDkCCDkkCDD o b o o r- = = = = m m m m e C C C C - - - - m m m m m CCCCCCCCCCCCCC--==~--=---=-
I TABLE 12 CONCENTRATION OF GAMMA EMTITERS IN MONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-1 OFF-SITE STATION
- Results in units of 10 3p Ci/m' .i. I sigma NUCLIDES RJANUARY- FEBRUARY- MARCH - APRIL MAY JUNE 1996 Co-60 < 1.4 < 1.5 <1.3 < 1.3 < 1.0 < 0.9 Mn-54 < 1.2 < 1.5 <0.9 < 1.3 < 0.9 < 1.0 g Cs-134 < 1.2 < 1.5 <0.9 < 1.1 < 0.7 < 1.0 Cs-137 <1.2 < 1.0 < 1.0 < 1.0 < 0.9 < 1.3 E
Nb-95 < 1.4 <1.9 < 1.4 < 1.6 < 1.5 < 1.4 Zr-95 < 2.0 < 2.5 < 2.1 < 2.5 < 1.9 <2.2 Co-141 < 1.7 < 1.9 <1.6 < 1.0 < 1.1 <1.0 Co-144 < 3.9 < 5.2 < 4.5 < 4.4 < 3.5 < 3.5 Ru-106 <8.3 <14.2 < 9.4 <13.9 < 7.7 < 9.2 g Ru-103 < 1.4 <1.4 < 1.3 < 1.6 < 1.2 < 0.9 3 Be-7 81 i 7 81 i 7 104 i 7 88 i 8 98 i 7 59 i 6 K-40 < 16 34 i 7 36 i 6 6i4 6i4 < 17 BaLa 140 < 3.2 <4.8 < 3.7 < 4.6 < 6.1 < 3.4 Ra-226 10 i 5 16 i 7 < 15 < 16 < 13 9i4 I131 < 3.8 < 4.3 < 5.6 < 4.3 < 6.9 < 3.5 Others** < LLD < LLD < LLD <LLD <LLD < LLD NUCLIDES - JULY. AUGUST SEPTEMBER OCT. OBER- NOVEMBER DECEMBER Co-60 <1.5 < 1.3 < 1.2 < 0.7 < 1.5 < 1.1 l Mn-54 < 1.0 < 1.1 < 0.8 < 0.8 < 1.1 < 0.9 5 Cs-134 < 1.0 < 0.9 < 0.9 < 0.9 < 1.2 < 1.1 Cs-137 < 1.0 <1.1 < 0.9 < 0.7 < 0.8 < 1.0 g Nb-95 < 1.4 < 1.3 < 1.6 < 1.4 < 2.2 < 1.4 g Zr-95 < 1.6 < 2.0 < 2.0 < 2.1 < 3.1 < 2.2 Ce-141 < 1.4 < 1.8 < 1.2 < 1.2 < 1.6 < 1.5 Cc-144 < 3.8 < 3. ') < 3.6 <3.4 < 4.5 < 4.0 ll Au-106 < 8.9 < 11.3 < 9.6 < 8.4 < 10.2 < 10.5 Ru-103 < 1.4 < 1.4 < 1.2 < 1.1 <1.2 < 1.4 !
Be-7 94 i 7 87 i 7 79 i 6 74 i 6 55 i 6 38 1 6 .E i K-40 < !3 33 t 6 < 12 10 i 4 27 i 6 41 i 7 g Bata-140 < 3.6 < 6.2 < 5.7 < 3.8 < 4.1 < 2.5 ,
Ra-226 12 i 6 < 14 < !4 < 14 < 11 < 12 g 1-131 < 4.8 < 5.7 < 3.7 < 2. 8 < 4.3 < 3.7 Others** < LLD < LLD < LLD <LLD < LLD < LLD E
- - Location required by the Technical Specifications. l
- - Other plant related radionuclides.
I I
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP l AIR PARTICULATE SAMPLES G ON-SITE STATION
- Results in units of 10 8pCi/m'i I sigma i NUCLIDES JANUARY. FEBRUARY MARCH APRIL :MAY1 JUNE:
1996 Co 60 < 1.0 < 1.4 <0.9 < 1.8 < 1.1 < 2.5 Mn-54 < 0.8 < 1.7 < 1.1 < 1.2 < 0.6 < 2.0 I Cs-134 Cs-137
< 1.0
< 1.4
< 1.2
< 1.4
< 1.0
< 0.7
< 1.4
< 1.0
< 0.9
< 0.7
< 1.4
< 1.6 NM5 <1,7 < 2.1 < 1.5 < 2.1 < 1.3 < 2.0 Zr-95 < 2.4 < 2.8 < 1.6 < 3.4 < 2.0 I Ce-141 Ce-144
< 1.9
< 5.6
< 1.8
< 5.2
< 1.5
< 4.3
< 2.0
< 6.2
< 1.4
< 1.3
< 4.2
< 1.9
< 5.2 Ru 106 < 10.4 < 16.9 < 8.3 < 14.8 <8.7 <15.4 I Ru-103 Be-7
< 1.7 94 i 8
< 1.5 83 i 9
<1.2 125 i 7
< 1.9 100 8
< 1.3 97 i 7
< 2.0 68 i 8 K-40 44 i 8 32 i 8 37 i 7 30 i 7 <11 32 i 8 I BaLa-140 Ra-226
< 6.6
< 18
< 5.3
< 19
< 4.6 8i4
< 6.4
< 21
< 3.6
< !4
< 7.1
< 20 I131 < 4.7 < 6.6 < 4.6 < 5.7 < 5.2 < 5.5 Others** < LLD < LLD < LLD <LLD < LLD <LLD NUCLIDES JULY- AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER-Co-60 < 1.4 < 0.8 I Mn-54 Cs-134
<1.2
<1.0
< 0.8
< 0.9
< 1.8
< 0.9
< 1.5
< 1.1
< 1.2
< 1.0
< 1.0
< 1.1
< 0.9
< 1.6
< 1.1
< 1.0 Cs-137 < 1.1 < 0.7 <1.7 < 1.2 < 0.8 < 0.7 Nb-95 < 1.9 < 1.5 < 2.1 < 1.5 < 1.3 < 1.5 Zr-95 <2.4 < 1.9 < 4.2 < 2.1 < 1.4 < 2.6 Ce-141 < 1.7 < 1.6 <1.9 < 1.6 < 1.3 < 1.4 I Ce-144 Ru-106 Ru-103
< 5.6
<12.1
< 1.2
< 3.9
<10.1
< 1.2
< 5.2
< 14.5
< 1.9
< 4.6
<12.5
<1.2
< 3.5
< 8.4
< 1.0
< 4.5
<13.7
< 1.4 l
Be-7 111 i 8 92 i 7 85 i 8 92 1 7 58 i 5 51 1 6 l K-40 53 9 31 i 6 < 14 45 8 22 i 5 36 7 !
BaLa-140 <6.3 < 5.3 <7.4 < 5.7 < 5.1 < 6.3 l Ra-226 < 19 < 14 < 17 < 16 < 14 < 16 !
I-131 < 4.9 < 4.8 < 7.9 < 3.7 < 4.1 < 16 l Others** < LLD < LLD < LLD < LLD <LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
l
I TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES II ON-SITE STATION
- Results in units of 10 'pC1/m' i. I sigma NUCLIDESc hJANUARYl
-FEBRUARY MARCH. APRIL ' MAY' JUNE-I IN Co60 <0.5 < 1.2 < 0.9 < 1.5 < 1.0 < 1.6 Mn 54 < 0.6 < 1.0 < 0.9 < 1.2 < 1.0 < 1.4 g Cs-134 <0.8 < 1.0 < 0.9 < 0.9 < 0.8 < 1.0 g Cs-137 < 0.5 < 0.8 < 0.9 < 1.6 < 1.1 < 1.4 Nb-95 < 1.4 < 1.4 <1.2 < 2.1 < 1.8 <2.3 Zr-95 < 2.4 < 1.7 < 1.8 < 2.7 < 2.3 < 3.0 Ce-141 < 1.1 < 1.2 < 1.1 < 2.1 < 1.7 < 2.0 Co-144 < 3.3 < 3.1 < 3.2 < 5.9 < 4.3 < 6.3 Ru 106 <12.3 <10.3 < 8.2 <14.2 < 10.0 < 14.6 Ru-103 < 1.0 < 1.4 < 1.0 <1.6 E
< 4.3 <1.3 g Be-7 88 i 7 69 i 6 104 i 7 95 i 7 112 i 7 69 i 6 K-40 < 16 < 12 < 10 159 i 12 118 i 9 172 i 12 Bala-140 < 6.0 < 3.6 < 6.4 < 4.4 < 3.8 < 4.6 Ra-226 10 i 5 12 i 6 8i4 < 22 11 i 6 < 22 I 131 < 2.8 < 3.5 < 4.5 < 6.6 < 6.4 < 5.9 Others** < LLD < LLD < LLD < LLD < LLD < LLD NUCLIDES JULY - AUGUST SEPTD MR OCTOBER :' NOVEMBER DECEMBER Co40 < 1.2 < 1.0 <2.1 < 1.4 <0.6 < 1.4 Mn-54 < 1.2 <0.9 <1.7 < 1.0 < 0.8 < 1.2 l
5 Cs-134 < 0.8 < 0.7 < 1.5 < 1.0 < 0.8 < 1.0 Cs-137 <0,9 < 0.6 < 1.2 < 0.9 < 0.5 < 0.9 g Nb-95 < 1.9 < 1.4 < 1.9 <1.7 < 1.4 < 1.6 g Zr-95 < 2.9 < 2.3 < 2.5 < 2.0 < 1.9 < 2.1 Ce-141 < 1.2 < 1.1 <2.4 < 1.1 < 1.0 < 1.0 Ce-144 < 3.8 < 2.6 < 6.3 < 3.3 < 2.8 < 3.4 '
Ru Ms < 9.5 < 6.5 <16.2 < 9.2 < 8.8 < 7.2 Eu-103 < 1.3 < 1.1 <1.9 < 1.6 <1.0 < 1.5 Be7 91 i 7 78 1 6 73 1 8 69 6 Mi6 54 i s E K-40 < 13 < 11 36 i 7 8i3 < 11 < 12 3 BaLa-140 < 5.5 < 6.6 < 4.1 < 3.5 < 4.9 < 5.8 Ra-226 9i5 < 10 < !9 8i5 <8 < 13 g I131 < 4.0 < 4.2 < 7.1 < 4.2 < 3.7 < 4.0 Others** < LLD < LLD < LLD <LLD < LLD < LLD I'
- - Optional sample location.
- - Other plant related radionuclides. E 3
I I
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMHTERS IN MONTHLY COMPOSn'ES OF NMP AIR PARTICULATE SAMPLES I ON-SITE STATION
- Results in units of 19 8pCi/m' f. I sigma i NUCUDES - cJANUARY-I FEBRUARYL' MARCHE APRIL / MAYt. JUNE" 1996
, Co 60 < 1.7 < 1.6 < 1.5 < 2.3 < 2.1 < 1.6 Mn-54 < 1.5 < 1.0 < 1.5 < 2.2 < 1.5 < 1.0 Cs-134 < 1.1 < 1.6 < 1.3 < 1.8 < 1.4 < 1.0 Co-137 < 1.7 < 1.3 < 1.0 < 1.3 <1.5 < 0.9 Nb-95 < 2.4 < 1.4 < 1.6 < 1.7 < 2.0 < 1.6 Zr-95 < 3.8 < 3.0 < 2.0 < 3.3 < 2.2 < 2.3 1 Ce-141 <2.4 <1.9 < 2.0 < 2.1 < 1.8 < 1.3 Ce-144 < 6.9 < 5. 8 < 5.3 < 5. 8 < 4.8 < 3.7 Ru-106 <18.3 <15.8 <14.2 <11.0 < 13.7 <11.4 j Ru-103 < 1.9 < 1.6 < 1.6 < 2.4 <1.6 < 1.1 '
Be-7 75 i 8 94 i 8 92 i 8 112 i 10 112 i 9 67 i 7 K-40 233 i 15 34 i 8 34 i 7 24 9 < 10 8i4 ;
Ba14-140 < 5.2 < 4.7 < 3.2 < 6.3 < 4.5 < 4.9 i Ra-226 < 25 < 20 < 17 < 18 < 18 < 14 l I-131 < 7.0 < 4.2 < 7.5 < 6.5 < 6.6 < 3.9 i Others** < LLD < LLD < LLD <LLD < LLD < LLD l
' NUCUDES - JULY.. ~AUGUSTJ SEPTEMBER OCTOBER 4 NOVEMBER DECEMBER Co 60 < 1.2 < 1.4 < 1.5 < 2.0 < 1.5 < 2.0
. Mn-54 < 1.2 < 1.4 < 1.1 < 1.7 < 1.1 < 1.6 Cs-134 < 1.2
< 1.6 < 1.1 < 1.0 < 1.1 < 1.2
- Cs-137 < 0.9 < 1.5 < 1.0 <1.2 < 1.3 < 0.9 Nb-95 < 2.0 <2.3 < 2.2 < 1.5 < 1.9 <2.2
- Zr-95 .
< 2.6 < 3.6 < 3.0 < 2.4 <2.2 < 2.8 Ce-141 < 1.6 < 1.6 < 1.5 < 1.8 < 1.5 < 1.8 Ca-144 < 4.5 < 4.7 < 3.5 < 5.3 <3.7 < 5.0 Ru-106 < 9.4 <18.0 < 11.3 <13.4 <14.8 <13.5 Ru-103 < 1.6 < 2.0 < 1.3 < 1.9 < 1.4 < 1.5 Be-7 97 i 8 91 i 9 87 i 7 63 i 8 48 i 6 41 i 6 K-40 < 13 25 i 8 < 14 33 i 8 22 i 6 44 9
- BaLa-140 < 8.1 < 5.9 < 5.0 < 5.8 < 3.4 < 4.6
., Ra-226 < 17 < 15 < 16 < 18 < 12 12 1 6 i 1-131 < 7. 8 < 7. 8 <4.9 < 4.2 < 4.1 < 5.4 Others** <LLD < LLD <LLD <LLD <LLD < LLD
- - Optional sample location.
- . Other plant related radionuclides.
i f
l 84-i
I TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR FARTICULATE SAMPLES J ON-SITE STATION
- Results in units of 19 'pCi/m' f. I sigma NUCLIDES.. JANUARY FEBRUARY - ! MARCH APRIL - .MAY JUNE 1996 Co-60 < 1.2 < 1.8 < 1.2 < 1.2 < 0.9 < 1.0 Mn-54 < 1.2 < 1.5 < 0.8 < 1.0 < 0.7 <1.2 Cs-134 < 1.3 < 1.2 < 0.9 < 1.2 < 1.0 < 1.0 Cs-137 < 1.2 < 1.3 < 0. 8 < 1.0 < 0. 8 < 1.2 Nb-95 < 1.7 < 1.9 < 1.8 < 1.8 < 1.0 < 1.7 Zr-95 < 2. 8 < 2.6 < 2.4 < 2.2 < 1.4 < 2.1 Co-141 < 1.7 < 1.9 < 1.1 <1.7 < 1.6 l
< 1.4 5 Ce-144 < 5.0 <6.2 < 2.7 < 4.7 < 3.4 < 4.2 Ru-106 <11.6 < 14.0 < 8.9 <12.8 <11.6 < 10.5 g Ru-103 < 1.3 < 1.7 < 1.3 < 1.5 < 1.2 < 1.5 g Bo 7 88 i 8 83 i 7 111 i 8 109 8 119 i 8 57 i 6 K-40 40 t 8 155 i 12 < 11 44 i 8 40 i 6 < 12 Bals140 < 6.3 < 5.5 < 2.9 < 4.8 < 3.9 <5.8 l Rs-226 < 18 < 22 < 14 < 17 < 15 < 17 5 I131 < 4.7 < 6.4 < 4.7 < $.2 < 5.2 < 5.2 Others ** < LLD < LLD <LLD < LLD < LLD < LLD NUCIlDES - ' JULY- AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co.60 < 1.9 -
< 1.1 <1.3 < 1.9 < 1.3 < 2.2 Mn-54 < 1.8 < 1.2 < 1.0 < 1.2 <1.3 <
Cs-134 < 1.9 < 1.3 < 1.2 < 1.7 < 1.2 - 4.6 Cs-137 < 1.7 < 1.1 < 1.1 <1.3 < 1.1 < 1.5 Nb-95 <2.2 , < 1.4 < 1.9 <2.2 < 1.9 < 2.1 Zr-95 < 2.9 < 2.5 < 2.2 <2.7 < 2.0 < 3.7 Co-141 < 2.0 < 1.8 < 1.5 < 1.9 < 2.0 < 1.9 l Ce-144 < 6.1 < 5.5 < 3.6 < 6.6 < 5.0 < 5.1
[ Ru-106 <18.3 <14.0 < 10.0 < 13.9 < 13.1 < 15.9 l
5 l . Ik in1 <;.0 < 1.7 < 1.3 < 1.7 < 1.5 < 2.5 l h. 7 ' 111 i 10 71 i 8 81 i 8 66 7 59 i 7 38 i 7 g K-40 26 i 9 38 i 7 < 14 32 t 7 26 i 7 25 i 8 g Bata-140 < 7.4 < 5.7 < 5.2 < 5. 8 < 6.1 < 6.7 Ra-226 < 23 < 16 < 14 < 19 < 16 < 16 I-131 < 6.6 < 7.5 < 3.6 < 5.3 < 5. 8 < 7.2 Others** < LLD < LLD <LLD < LLD < LLD <LLD l'
=
- - Optional sample location. ;
- - Other plant related radionuclides.
l
I l
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES K ON-SITE STATION
- Rannits in units of 10 *pC1/m' f. I sisma NUCIJDES1 ) JANUARY? FEBRUARY- iMARCHi < APRIL MAY1
{ L. JUNE 1996 Co 60 < 1.9 < 1.3 < 1.2 < 1.4 < 1.0 < 1.3 Ma-54 < 1.0 < 1.4 <0.9 < 1.4 < 0.8 < 1.2 Cs-134 < 1.0 < 1.4 < 0.9 < 1.3 < 0.9 < 1.2 Cs-137 < 0.8 < 1.3 <0.9 < 1.1 < 0. 8 < 1.1 Nb-95 < 1.3 < 2.0 < 1.3 <2.0 < 1.4 < 1.0 Zr-95 < 2.5 < 3.0 <1.6 < 2.9 < 1.1 < 2.3 Co-141 < 1.3 < 2.0 < 1.2 <1.9 < 1.0 < 1.7 Co-144 < 3.4 < 6.4 < 2.7 < 5.6 < 2.5 < 4.4 Ru 106 <12.5
<15.8 <5.3 < 13.5 < 6.5 < 10.5 Ru-103 < 1.3 < 1.7 < 0.8 < 1.6 < 0.9 < 1.2 Be-7 78 i 7 B2 i 7 119 i 7 108 i 7 127 i 8 69 i 7 K-40 8i5 199 i 12 <8 146 i 10 <11 Bala-140 38 i 7
< 4.0 < 3.6 < 4.9 < 5.1 < 3.8 < 5.4 Ra-226 < 12 <21 613 12 i 7 < 10 < 19 I-131 < 3.9 < 6.3 < 3.9 < 6.8 < 3.8 < 5.2 Others** <LLD < LI.D < LLD < LLD <r r n <Trn f NUCLIDES- 3 JULY? AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co40 < 1.3 < 1.0 < 1.6 < 1.7 < 1.6 < 1.3 Mn-54 < 1.1 < 1.2 < 1.2 < 1.6 < 1.4 < 1.3 Ca-134 < 0.9 < 0.7 < 1.0 < 1.0 < 1.2 < 1.0 Co-137 <1.2 < 0.7 < 1.2 < 1.2 < 1.3 < 0.9 Nb-95 <1.4 < 1.5 <1.9 < 2.0 < 1.7 <1.2 Zr-95 <2.2 < 1.8 < 2.1 < 2.7 < 2.5 < 1.6 Cc-141 < 1.9 < 1.1 < 1.8 < 2.2 < 1.5 < 1.1 Ce-144 < 5.0 < 2.9 < 4.2 < 7.1 < 3.8 < 3.2 Ru 106 <13.5 < 6.1 <12.4 < 15.2 < 14.6 < 9.6 Ru-103 < 1.5 < 1.0 < 1.4 < 1.8 < 1.7 < 1.2 Be-7 100 t 8 6 81 t 7 B2 58 i 6 52 1 6 45 i 6 K-40 40 t 7 < 10 35 8 193 i 12 32 i 8 < 10 Bala-140 < 6.4 <44 < 5.0 < 4.6 < 7.5 <4.8 Ra-226 < 18 < 13 < 17 < 22 < 14 < 16 1131 < 4.7 < 5.3 < 6.0 < 5.9 < 5.0 < 4.9 Others** < LLD <LLD <LLD <f T n < LLD <I1n
- - Optional sample location.
- - Other plant related radionuclides.
4 TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G OFF-SITE STATION
- Results in units of 19 'pCi/m' i 1 sigma
- ENUCLIDESI ;JANUARYa ? FEBRUARY
- ' MARCH 1 iAFRIL : .MAY: JUNE 1996 l Co 60 < 0.8 < 1.2 < 1.3 <1.4 < 0.9 < 0.8 Mn-54 < 1.6 < 1.4 < 1.0 < 1.2 < 1.2 < 0.8 i Cs-134 < 1.2 < 1.5 < 0.9 < 1.2 < 0.8 < 1.0 Cs-137 < 1.2 < 1.1 < 1.1 < 1.2 < 1.0 < 0.8
. Nb-95 < 1.8 < 1.6 < 1.8 < 1.6 <1.5 < 1.3 I
Zr-95 < 2.2 < 2.9 < 2.6 <2.4 <2.6 <1.5 Co-141 < 1.6 < 1.7 < 1.8 <1.4 < 1.4 < 1.2 Ce-144 < 4.9 < 5.6 < 4.8 < 3.4 < 4.2 < 3.0 Ru-106 < 10.8 < 11.1 <12.0 < 13.5 <11.9 < 7.0 g i
Ru-103 < 1.5 < 1.3 < 1.6 < 1.1 < 1.2 < 0.6 g Be-7 65 i 7 75 i 7 85 i 6 94 i 8 94 i 8 69 6 K-40 54 10 39 i 8 145 i 10 < 18 < 15 < 14 BaI4-140 < 5.6 < 6.4 < 4.0 < 3.3 < 5.1 < 5.8 Ra-226 < 17 < 17 < 19 < 12 < 13 < 10 1-131 < 4.6 < 5.4 < 7.3 < 4.4 < 3.8 < 3.5 Others** < LLD <LLD <LLD < LLD < LLD < LLD NUCLIDES : JULY. AUGUST' SEPTEMBER' ~ OCTOBER- NOVEMBER. DECEMBER Co-60 <1.1 < 1.7 < 1.0 < 1.8 < 1.0 < 1.0 Mn-54 <0.9 < 1.4 < 0.9 < 1.3 < 0.6 < 1.0 Cs-134 < 0.8 < 1.4 < 1.1 < 1.5 < 0.7 < 0.9 Cs-137 < 0.8 91.0 < 0.9 < 1.2 < 0.5 < 0.7 g Nb-95 Zr-95
< 1.5
< 2.2
< 1.8
< 2.5
< 1.6 < 1.2 < 1.2 < 1.2 g
< 1.8 < 3.0 < 1.6 < 2.2 Co-141 < 1.2 < 2.1 < 1.1 < 1.5 <1.0 < 1.0 Ce-144 < 3.5 < 6.0 < 3.4 < 4. 8 <2.1 < 3.0 Ru-106 < 10.5 < 12.3 < 9.4 < 15.6 < 7.5 < 9.5 b -iLJ '
< 1.4 <1.9 < 1.1 < 1.6 < 0.8 < 1.4 Be-7 82 2 6 81 i 8 73 6 57 7 56 i 5 35 i 5 K-40 71 i 4 19 i 6 12 i 4 44 i 9 <9 <8 BaLa-140 < 4.9 < 5.9 < 3.3 < 5.8 < 3.5 < 4.3 Ra-226 < 15 22 6 14 i 5 13 i 6 < 10 < !6 I 131 < 4.1 < 7.5 < 3.5 < 4.2 <2.8 < 4.4 Others** < LLD < LLD < LLD < LLD < LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMrITERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-2 OFF-SITE STATION
- Results in units of 10 *pCi/m' i. I sigma fKUCUDES! $JANUARYJ FEBRUARYn ? MARCH l! APRIL iMAYJ JUNE 1996 Co.60 < 1.4 < 1.2 < 1.5 < 1.4 < 0.7 < 1.9 Mn-54 < 1.2 < 0.8 < 1.2 < 1.3 <0.7 < 1.2 Cs-134 < 1.0 < 1.0 <1.2 < 1.2 < 0.7 < 1.4 Cs-137 < 1.4 < 1.0 < 0. 8 < 0.9 < 0.7 < 1.4 Nb 95 < 1.8 < 1.9 < 1.8 < 1.4 < 0.8 < 1.8 Zr-95 < 2.8 <2.0 < 2.2 < 2.5 < 1.9 < 2.6 Co-141 < 1.9 < 1.2 < 1.6 < 1.6 < 1.2 < 1.5 Co 144 < 6.2 <34 < 4.3 < 5.2 < 3.0 < 4.8 Ru-106 <13.5 < 9.5 < 10.9 < 10.8 < 9.2 < 16.0 Ru-103 < 1.6 <1.4 <1.4 < 1.3 < 1.1 < 2.1 Be-7 72 i 7 72 i 7 94 i 8 102 i 8 109 i 7 54 i 7 K 210 1 13 < 13 28 i 6 - 44 8 < 10 22 i 7 BaLa-140 < 4.6 < 4.6 < 7.1 < 3.7 < 4.1 < 6.7 Ra-226 21 i 8 < 13 < 13 < 18 < 13 < 18 I131 < 5.3 < 3.3 < 6.2 < 4.2 < 3.1 < 5.4 Others** < LLD < LLD <LLD < LLD <T T n
< f _f n l NUCUDESE 1 JULY / ~AUGUSTS SEPTEMBER- OCTOBER NOVEMBER- DECEMBER 1
Co 60 < 1.3 < 1.1 < 1.9 < 0.8 < 1.0 <1.3 !
Ms-54 < 1.1 < 1.1 <1.6 < 0.9 < 1.0 < 1.0 Cs-134 <1.3 < 0.8 <1.3 < 1.3 < 0.6 < 0.8 Cs-137 < 1.2 < 0. 8 < 1.3 < 1.0 < 0.8 <1.0 Nb-95 < 1.7 < 1.5 <2.2 < 1.6 < 1.2 < 1.1 l Zr-95 < 2.5 < 3.0 < 2.8 < 1.9 < 1.8 < 2.4 ,
Co-141 < 2.0 < 1.2 < 1.6 < 1.5 < 0.8 < : .1 !
Ce-144 <4.8 < 3.2 < 5.2 < 4.4 <2.3 < 2.8 )
Ru-106 <13.6 < 5.7 <12.7 <96 < 6.2 < 10.8 l Ru-103 < 1.3 < 1.4 < 2.0 < 1.1 < n.9 , < 1.3 Be-7 89 i 8 101 i 8 70 i 8 61 i 6 58 t 5 28 i 5 l K-40 25 i 7 <11 25 i 8 41 8 <9 10 t 5 Bala-140 < 4.2 < 5.2 < 4.2 < 3.7 < 2.4 < 3.3 Ra-226 < 17 12 i 5 < 17 < 18 <9 < 10 I-131 < 5.2 < 4.3 < 4.7 < 3.7 < 3.1 < 3.3 Others** - < LLD < LLD < LLD < LLD < LLD <LLD
- . Iecation required by the Technical Specifications.
- - Other plant related radionuclides.
l 1
I i
TABLE 12 (Continued) i CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP g)
AIR PARTICULATE SAMPLF3 5l R-3 OFF-SITE STATION
- Results in units of IQ 'pCi/m' i 1 sigma
- NUCLIDES < JANUARY, FEBRUARY 3 : MARCH' " APRIL' ;MAY: ' JUNE 1996 Co 60 < 1.4 <1.1 <1.5 < 1.2 < 0.9 < 1.3 Mn-54 < 1.3 < 1.1 < 1.2 < 1.1 < 1.0 < 1.0 Cs-134 <1.2 < 1.0 < 0.8 < 0.9 < 1.0 < 1.1 l
<0.9 < 1.1 =
Cs-137 <0.9 < 1.0 < 1.1 < 0.7 Nb-95 <1.6 < 1.2 < 1.7 < 1.8 < 1.5 < 1.2 Zr-95 <2.6 < 2.7 < 2.5 < 2.6 < 2.3 <1.7 Ce-141 <1.5 <1.4 < 1.9 < 1.0 < 1.5 <1.5 Co-144 < 5.1 < 3.6 < 4.9 < 3.0 s 3.9 < 4.0 Ru-106 <11.1 <12.8 <11.7 <11.6 < 10.2 < 14.3 Ru-103 < 1.0 < 1.4 < 1.5 < 1.0 < 1.2 < 1.2 Be-7 79 i 7 70 i 7 93 i 6 99 8 101 1 7 53 1 6 K-40 53 i 8 < 16 122 9 < 11 28 i 6 30 i 7 Bata-140 < 4.4 < 3.4 < 4.8 < 3.2 < 4.5 < 4.8 Ra-226 < 16 < 17 < 19 < 12 < 13 6i4 I-131 < 4.5 < 4.4 < 8.9 < 3.6 < 4.1 < 5.6 Others** < LLD < LLD <LLD < LLD < LLD < LLD NUCLIDES - JULY AUGUSTJ SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 1.4 < 1.1 < 1.5 < 1.2 < 1.0 < 1.9 Mn-54 < 0.9 <1.5 < 1.2 < 1.0 < 0.8 < 1.5 Cs-134 <0.9 <1.4 < 0.9 < 0.7 < 0.9 < 1.6 Cs-137 < 0.6 < 1.2 < 1.0 < 0.9 <0.7 < 1.6 Nb-95 <1.4 < 1.7 < 1.4 < 1.4 < 1.0 < 2.2 Zr 95 < 2.0 < 3.4 <2.6 < 2.6 < 1.7 < 2. 8 Ce-? 41 <1.2 < 2.1 < 1.7 < 1.2 < 1.1 < 1.7
' CeO4 < 3.7 < 5.2 < 5.0 < 3.1 < 2.7 < 6.0 Ru-106 <10.7 <11.9 < 14.8 < 8.6 < 10.0 < 17.9 Ru-103 ' i .4 < 2.2 < 1.5 < 1.4 < 1.0 < 2.2 Be-7 72 i i 108 10 72 i 6 65 i 6 57 i 5 30 i 7 K 40 10 1 6 43 i 10 36 i 7 < 11 < 11 36 i 9 BaLa-MO < 6.0 < 5.7 < 3.0 < 4.5 < 4.5 < 8.2 Ra-27.6 < 13 < 16 < 16 < 11 < 13 < 18 I-131 < 3.4 <8.2 < 4.5 < 2.9 < 4.2 < 7.2 Others** < LLD < LLD <LLD <LLD < LLD <LLD
- - Location required by the Technical Specifications.
- - Other plant related radionuclides.
l'
{
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMBTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-4 OFF-SITE STATION
- Results in units of 10 'pci/m' f I sisma dNUCIJDBSS ? JANUARY? PEBRUARY3 iMARCH) APRIL -
cMAY JUNE
{
1996 Co 60 < 1.1 < 1.3 < 1.5 <1.4 < 1.1 < 1.3 Ma-54 < 1.0 < 1.4 < 1.8 < 1.4 < 1.1 < 1.0 Co-134 < 1.1 < 1.1 < 1.0 < 1.2 < 0.7 < 1.1 Cs-137 < 1.2 < 1.0 < 0.9 < 1.4 < 0.7 < 0.8 Nb-95 < 1.5 < 1.6 < 1.5 < 1.7 < 1.6 < 1.8 Zr-95 < 1.9 < 2.8 < 2.3 < 3.2 . < 1.8 < 1.9 Co-141 < 1.4 < 1.7 < 1.5 < 1.7 < 1.0 <1.3 Co-144 < 3.9 < 4.7 < 3.9 < 5.0 < 2.6 < 3.3 Ru-106 < 10.0 < 10.3 <11.9 < 20.0 < 9.6 < 10.9 Ru-103 < 1.2 <1.4 < 1.1 < 1.7 < 1.0 < 1.2 Be-7 70 t 6. 76 i 7 99 i 8 73 i 9 101 i 6 77 t 7 K-40 < 15 34 i'8 < 14 21 i 6 < 10 < 14 Bala-140 < 5.2 < 3.4 < 4.1 < 4.0 < 4.7 < 4.3 Ra-226 < 14 < 18 < 15 < 17 < 10 23 i 6 I-131 < 3.0 <5.1 < 4.1 < 6.2 < 2.9 < 3.9 Others** < LLD < LLD < LLD <rrn < LLD < LLD
- NUCLIDES < sJULY: ' AUGUST : SEPTEMBERI OCTOBER ' NOVEMBER . DECEMBER Co40 < 2.7 < 2.0 < 1.3 < 1.6 < 1.0 < 1.2 Mn-54 < 1.7 < 1.6 < 1.1 < 1.7 < 1.0 < 1.0 Cc-134 < 1.5 < 1.2 < 1.1 < 1.7 < 0.8 < 0. 8 Cs-137 < 1.1 < 1.3 < 0. 8 < 1.4 < 0.8 < 1.1 Nb-95 < 2.6 < 2.2 < 1.8 < 1.6 <1.3 < 1.3 Zr-95 < 2. 8 < 3.2 < 3.3 < 3.0 < 1.5 < 2.1 Co-141 <1.7 < 2.4 < 2.0 < 1.6 < 1.3 <1.4 Co-144 < 5.6 < 6.9 < 5.5 <5.4 < 3.7 < 3.7 Ru 106 <15.5 < 16.7 <16.7 < 19.2 < 10.3 < 10.1 Ru-103 < 1.5 < 1.8 < 2.3 < 1.6 < 0.7 < 1.0 Be-7 84 i 9 108 i 9 78 i 7 70 i 8 46 i S - 42 i 5 K-40 28 i 7 48 i 8 29 i 7 32 2 8 23 i 5 8i4 BaLa-140 <8.5 < 7.2 < 7.2 < 6.5 < 3.6 < 4.2 Ra-226 <21 <21 < 20 < 16 9i4 10 i 5 I 131 < 6.3 < 8.4 < 5.7 < 4.6 < 3.6 < 4. 8 Others** < LLD < LLD <LLD <r i n <LLD < LLD
- - Location required by the Technical Specifications.
- - Other plant related radionuclides.
l 90
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-5 OFF-SITE STATION * (CONTROL)
Results in units of 19 'pCl/m' i i sigma
- NUCLIDES : JANUARYJ FEBRUARY: 3 MARCH: LAPRIL .MAY EJUNEA 1996 Co-60 < 0.7 < 1.0 < 0.6 < 1.5 < 1.1 < 1.1 Mn-54 < 0.9 < 0.6 < 0. 8 < 1.2 < 0.8 < 1.3 Cs-134 < 1.1 < 0.9 < 0.6 < 5.3 <0.7 <1.2 Cs-137 < 1.2 < 0.8 < 0.7 < 1.4 <0.5 < 1.0 Nb 95 < 1.2 < 1.5 < 1.3 < 2.1 <1.2 < 1.3 Zr-95 <1.8 <2.0 < 1.6 < 2.4 < 1.2 <2.4 Ce-141 < 1.4 < 1.1 < 0.9 < 1.9 < 1.2 < 1.7 Co 144 < 3.9 < 3.8 < 2.7 < 5.1 < 3.0 < 4.8 Ru-106 < 10.7 < 9.3 < 10.9 < 14.9 < 7.4 < 10.3 Ru-103 < 1.0 < 1.2 < 1.1 < 1.7 < 1.2 < 1.2 Be-7 72 i 6 69 6 114 7 81 i 8 105 i 7 69 6 K-40 < 10 < 12 <8 30 t 8 _ 11 i 3 40 i 7 BaI.a-140 < 5.1 < 2.7 < 5.4 < 4.3 < 4.6 < 5.3 Ra-226 < 14 7i4 < 10 < 18 12 i 4 < 17 I-131 < 3.6 < 3.6 < 3.4 < 5.3 < 4.0 < 5.6 Others** <LLD
< LLD < LLD < LLD < LLD <LLD NUCLIDES' ? JULY: AUGUST SEPTEMBER OCTOBER. -NOVEMBER DECEMBER Co-60 < 1.2 < 0.9 < 0.9 < 1.9 < 1.6 < 0.7 Mn-54 <1.1 < 1.0 < 1.0 < 1.0 < 1.4 < 1.1 Cs-134 < 1.0 < 1.0 < 0.7 < 1.3 <0.9 < 1.1 Cs-137 < 0.7 < 1.1 < 0.9 < 1.4 < 1.1 < 0.9 Nb-95 < 1.7 < 1.5 < 1.4 < 1.7 < 1.8 <1.3 I Zr-95 < 2.2 < 2.2 < 2.2 < 2.3 < 2.4 < 2.4 Ce 141 < 1.5 < 1.4 < 1.0 < 1.7 < 1.4 < 1.6 Co-Id4 < 3.9 < 3.7 < 3.2 < 5.5 < 4.2 < 4.4 Ru-106 Wo6 < 8.2 < 6. 8 < 13.0 <11.0 <12.3 Rv-103 < 1.6 < 1.7 < 1.2 < 1.7 < 1.1 < 1.2 Pe-7 -
107 i 8 11i8 90 i 7 79 i 7 81 1 7 36 i 6 K 40 11 i 5 10 i 5 < 13 52 i 9 31 i 7 26 i 6 BaLa-140 < 3.8 < 5.5 < 5.2 < 4.1 < 5.3 < 5.0 Ra-226 15 i 5 < 17 7i4 < 20 < 13 12 i 6 I-131 < 4.5 < 5.3 < 3.6 < 3.3 < 4.6 < 4.5 Others** < LLD < LLD <LLD < LLD <LLD < LLD
- - location required by the Technical Specifications.
- -Other plant related radionuclides.
l l
L TABLE 12 (Continued) f CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES D-2 OFF-SITE ' . RATION
- Results in units of10 8pCi/m' f. I misma NUQJDES L d NUARYh PERRUARYd vMARCH r APRIL' . :MAYd RINE 1996 Co-60 < 1.3 < 1.4 < 1.2 < 1.2 < 1.1 < 0. 8 Ma-54 < 1.5 < 1.4 <0.9 < 0.9 < 1.2 < 1.2 Cs-134 < 1.4 < 1.4 < 0.9 <1.1 < 0.9 < 1.0 Co-137 < 1.4 < 1.5 <0.5 < 1.0 < 0.7 < 0.6 Nb-95 < 2.0 <2.1 < 1.3 < 1.5 < 1.4 < 1.6 Zr-95 < 2. 8 < 2.9 < 2.1 < 2.3 < 2.0 < 2. 8 Co-141 < 2.1 < 2.0 <0.9 <1.4 < 1.3 < 1.2 Co-144 < 6.2 < 6.1 < 3.0 < 4.0 < 4.2 < 3.5 Ru-106 < 13.8 < 13.2 < 7.3 < 8.8 <10.6 < 8.8 Ru-103 < 1.4 < 1.6 < 1.1 < 1.4 < 1.1 < 1.2 Be-7 73 i 6 57 i 7 89 i 7 90 i 7 124 i 8 58 i 6 K.40 186 i 12 167 i 7 < 10 < 16 24 5 < 13 Bala-140 < 4. 8 < 4. 8 < 3.4 < 6.0 < 2.6 < 4.4 Ra-226 < 22 20 8 < 10 11 i 6 < 16 < 12 I-131 < 6.0 < 5.7 < 5.0 < 4.6 < 3.7 < 3.6 Others** <LLD <LLD <11D <LLD < fin <f Jn LNUQ2 DES . 3 JULY: 3AUGUSTt SEPTEMBER OCTOBER 7 . NOVEMBER . DECEMBER Co40 < 0.7 < 2.0 < 2.5 < 1.6 < 1.2 < 1.3 Ma-54 < 1.1 < 1.2 < 1.8 <1.5 < 1.1 < 0.8 Cc-134 < 0.9 < 1.2 < 1.5 < 1.0 < 1.1 < 1.0 Co 137 < 1.0 < 1.0 < 1.4 < 1.4 < 1.0 < 0.9 Nb 95 < 1.9 < 1.7 < 2.3 < 1.8 < 1.7 <2.0 Zr-95 < 2.3 < 1.9 <2.3 ,<2.8 < 2.1 < 2.6 Ce-141 < 1.3 < 1.9 < 1.6 < 2.2 < 1.6 < 1.0 Ce-144 < 3.5 < 4.8 < 5.0 < 6.5 < 4.7 < 3.8 .
Ru-106 < 8.2 < 10.6 <16.0 <14.1 < u.2- <7.9 Ru-103 < 0.9 < 1.6 <2.3 < 1.6 < 1.6 < 0. 8 Be-7 95 8 95 i 8 87 i 9 64 i 6 56 1 6 38 i 5 K 40 < 16 38 7 < 19 164 i 11 34 6 < 15 Bala-140 < 3.9 < 5.5 < 9.4 < 3. 8 < 3.1 < 4.5 Ra-226 < 12 < 18 < 18 14 i 8 10 i 5 < 11 1-131 < 4.7 < 7.4 < 6.6 < 4.7 < 3.9 < 4.1 Others** <LLD <LLD < LLD < LLD < LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
1 TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMrITERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES E OFF-SITE STATION
- Results in units of 10 'pC1/m' i 1 sigma
- NUCLIDESU i FEBRU.*RY:- : MARCH:. s L APRIL - .MAY! JUNE QQARY-Co 60 < 2.1 < 2.0 < 1.3 <1.3 < 0.8 < 1.4 Mn-54 <0.9 < 2.1 < 1.3 < 1.5 < 0.8 <1.5 Cs-134 < 1.3 < 1.9 < 0.9 <1.3 < 0.8 < 0.9 Cs-137 < 1.3 < 1.3 < 1.1 < 1.1 <0.7 < 1.0 Nb-95 < 2.1 < 1.8 < 2.4 < 1.4 < 1.3 < 2.2 Zr-95 < 4.0 < 3.7 < 1.8 < 2.6 < 1.7 < 3.0 l Ce-141 < 1.8 < 1.8 < 1.5 < 1.6 < 1.1 < 1.6 5 Ce-144 < 5.6 < 5.7 < 4.6 < 5.4 < 3.1 < 5.0 Ru-106 <17.5 <15.3 < 13.1 < 11.4 < 9.0 < 14.1 Ru-103 < 1.9 < 2.0 <1.6 < 1.6 < 1.2 < 2.0 Be-7 87 9 91 i 9 111 i 9 87 i 8 111 i 7 75 i 8 I K-40 30 i 7 18 i 8 36 i 8 46 i 8 <8 < 20 BaLa-140 < 5.4 < 6.7 < 8.6 < 4.8 < 4.0 < 5.4 Ra-226 < 18 < 17 < 15 < 18 < 13 < 15
- I-131 < 5.3 < 5.1 < 6.8 < 5.1 < 3.6 < 6.2
) Others** < LLD < LLD < LLD < LLD <LLD < LLD j NUCIJDES JULY- - AUGUST SEPTEMBER OCTOBER- ~ NOVEMBER DECEMBER Co-60 < 1.4 <0.9 < 1.9 < 1.5 < 1.0 < 1.6 l Mn-54 < 1.0 < 1.4 <1.5 < 1.2 < 0.9 < 1.7 Cs-134 <1.6 < 0.9 < 1.6 < 1.0 < 0.6 < 1.3
, Cs-137 <1.6 < 1.1 < 1.4 < 1.0 < 0.8 < 1.3 Nb-95 < 2.4 < 1.8 < 2.0 < 1.4 < 1.3 < 1.9
< 2.2 < 1.5 < 2.7 l Zr-95 < 2.4 < 2.5 < 3.0 l
1 Co-141 < 1.9 < 1.2 < 2.0 < 1.6 < 1.0 < 1.5 Ce-144 < 5.u < 3.4 < 6.4 < 4.5 < 2.4 < 4.0 Ru136 <17.1 . "10.2 <16.1 <12.6 < 7.7 < 10.9 Ru-iO3 < 1.2 ,< a.o < 1.5 < 1.3 < 1.2 < 1.8 Be-7 103 i 10 103 8 56 i 7 63 i 6 56 5 39 i 6 K-40 17 i 6 12 i 5 39 i 8 37 i 7 12 i 5 < 18 BaLa-140 < 7.7 < 4.4 < 6.9 < 5.3 < 4.4 < 3.9 Ra-226 < 18 < 12 < 18 < 16 8 5 < 13 I-131 < 5.8 < 4.2 < 6.3 < 3.3 < 3.3 < 3.8 Others** <LLD < LLD < LLD < LLD < LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
I I
I TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES F OFF-SITE STATION
- Results in units of10 'gC#m8 f_1 sigma eNUCUDESir NANUARIM PEBRUAR / 1MARCHS APRIL fMAYr 7UNE 1996 Co60 < 1.4 < 1.7 < 1.1 < 2.3 < 1.3 < 2.1 Mn-54 < 1.2 < 1.2 <1.4 < 1.2 < 1.2 < 1.4 Cs-134 < 1.1 <1.1 < 1.1 <1.3 < 1.0 < 1.5 l Cs-137 < 0.9 < 1.0 < 1.1 < 1.6 < 0.9 < 1.5 Nb-95 l
< 1.7 < 1.2 <1.7 < 2.3 < 1.1 < 2.1 '
Zr-95 < 2.3 < 1.9 < 2.5 < 4.2 < 1.7 < 3.2 I Co-141 <1.5 < 1.4 < 2.0 <1.7 < 1.6 < 2.1 l Co-144 < 4.3 < 3.6 < 5.0 < 5.8 < 4.2 < 6.3 l Ru-106 <12.7 < 9. 8 <14.7 <17.0 <11.8 < 14.9 )
Rs-103 < 1.2 <1.4 < 1.7 < 2.3 < 1.2 < 2.2 Be-7
)
58 6 54 t 7 112 i 8 93 i 9 92 7 73 i 7 i K-40 < 11 10 i 4 34 i 7 24 7 29 i 6 33 i 7 ;
h -140 < 4.2 < 5.5 - < 6.0 < 7.3 < 3.5 < 4.9 l Ra-226 11 i 5 10 i 5 < 16 < 19 < 14 18 7 I-131 < 4.2 < 4.3 < 7.0 < 6.1 < 4.5 < 6. 8 Others" < LLD < LLD < LLD < LLD < LLD < LLD -
l
- iNUCUDESi ?JULYJ iAUGUSTi SEPTEMBER OCTOBER? NOVEMBER- DECEMBER
! Co40 < 1.1 < 1.8 < 1.6 < 1.3 < 1.3 < 2.2 M:-54 < 1.0 < 1.3 < 0.9 < 0.8 < 1.0 < 1.4 Cs-134 < 1.2 < 1.3 <0.9 < 1.0 < 1.0 < 1.4 i
! Cs-137 < 1.1 < 1.5 < 1.0 < 0.8 <0.9 < 1.1
<1.4 Nb-95 < 2.3 < 2.3 < 1.7 < 1.5 < 1.8
- Zr-95 < 2.4 .3.0 < 2.0 <2.2 < 2.0 < 2.5
)
Ce-141 < 1.8 < 1.8 <1.4 < 1.1 < 1.7 < 1.9
- Co-144 < 4.6 < 5.6 < 3.8 <2.9 < 4.0 < 5.7
' <11.3 Ru-106 <14.4 < 10.9 < 7.7 < 9.9 < <11.3
} Ru-103 <1.5 <2.0 < 1.4 < 1.2 < 1.1 ,
< 1.8
- Be-7 B9 i 7 113 1 10 62 i 6 76 i 7 56 i 6 37 i 6 l K40 32 t 6 31 8 <9 < 11 27 i 5 39 i 8
. h-140 < 3.3 < 10.8 < 6.8 < 3.7 < 5.8 < 6.9 8
Ra-226 < 17 < 20 < 14 < 11 < 14 < 17 l I-131 < 5.7 < 6.0 < 3.7 < 3.0 < 4.8 < 6.9 i Others** < LLD < LLD <LLD < LLD < LLD < LLD
- - Optional sample location
- - Other plant related radionuclides i
j 94
I!
TABLE 12 (Continued) l CONCENTRATION OF GAMMA EMI'ITERS IN MONTHLY COMPOSITES OF NMP gl AIR PARTICULATE SAMPLES 5 D-1 ON-SITE STATION
- Results in units of 19 'pCi/m' f I sigma I i
i NUCLIDES1 JANUARYi iFEBRUARY b MARCIE iAPRIL . MAYi JUNE IN Co 60 <0.7 < 1.7 < 1.0 <1.5 <0.6 < 1.5 Mn-54 < 1.0 < 1.0 < 0.7 < 1.0 < 1.0 < 1.2 Cs-134 < 1.5 < 1.0 < 0. 8 < 1.4 < 0.9 < 1.2 Cs-137 < 1.1 < 1.0 <0.7 < 1.0 < 0.9 ~
< 0.9 NM5 < 1.8 < 1.7 < 1.4 < 1.9 <1.4 < 1.1 Zr-95 < 2.7 < 1.8 < 1.8 < 3.0 < 2.2 < 1.9 Ce-141 < 1.4 < 1.4 < 1.0 < 1.6 < 1.6 < 1.3 Co-144 < 4.6 <3.8 < 3.2 < 4.7 < 4.1 < 3.6 <
Ru-106 < 10.9 < 9.7 < 8.7 <12.7 <11.6 <11.9 gl Ru-103 < 1.3 < 1.3 < 0.9 < 1.6 < 1.4 < 1.4 g Be-7 79 i 7 86 i 8 104 i 7 92 i 8 20 i 5 73 i 7 K-40 23 i 6 12 i 4 <9 22 6 110 i 8 <9 BaLa-140 < 5.0 < 3.0 < 5.1 < 6.9 < 5.1 < 4.4 Ra-226 10 6 < !4 < 11 < 18 < 15 < 16 I-131 < 3.9 < 4.0 < 3.9 < 6.1 < 5.4 < 3.9 Others** < LLD < LLD < LLD < LLD < LLD < LLD NUCLIDES JULY. AUGUST > SEPTEMBER OCTOBER - : NOVEMBER DECEMBER-Co-60 < 1.1 < 0.9 < 2.3 < 1.0 <1.0 < 1.2 Mn-54 < 1.0 < 0.9 < 1.6 < 1.3 < 1.0 < 0.9 Cs134 < 3.8 < 0.9 < 1.6 < 1.1 < 0.7 < 1.0 Cs-137 < 0.9 < 0.6 < 1.1 < 1.1 < 0.7 < 0.7 Nb-93 - < 1.7 < 1.4 <2.9 < 1.4 < 1.2 < 1.1 Zr45 <2.4 < 1.7 < 4.0 < 2.6 < 1.4 < 1.7 Cc-141 < 1.4 < 1.2 < 2.0 < 1.3 < 1.0 < 1.1 Ce-144 < 4.0 < 3.4 < 6.7 < 3.7 < 2.9 <3.3 Ru-106 < 9.9 <>./ <18.5 < 10.0 < 9.3 < 10.6 Ru-103 <1.4 < 1. * <17 < i.5 < 1.0 < 1.0 Be-7 87 i 7 105 i 7 71 i 9 91 7 56 i 5 40 4 K-40 < 11 15 i 4 < 16 10 1 4 < 11 8i3 Bala-140 < 3.6 <. 5. 8 < 9.0 < 3.3 < 4.7 < 4.2 Ra-226 < 15 < 14 < 22 < 18 14 i 5 < 12 I-131 < 5.2 < 4.4 < 7.0 < 3.7 < 4.1 < 3.6 Others** < LLD < LLD < LLD <!LD <LLD < LLD i * - Opional sample location.
- - Other plant related radionuclides.
I I
TABLE 13 NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - 0FF-SlTE STATIONS
~
I-131 ACTIVITY pCi/m' i 1 SIGMA LOCATION WEEK END R-1* R-2* R-3* R-4* R-5*
DATE D-2 E F G OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE 01/09/96 <0.012 <0.013 <0.010 <0.012 <0.009 <0.015 <0.008 01/16/96 <0.009 <0.013 <0.015 <0.012
<0.009 <0.012 0.011 <0.013 01/23/96 <0.009 <0.014 <0.009
<0.014 <0.009 <0.015 <0.013 <0.010 <0.011 <0.016 <0.009 01/30/96 <0.014 <0.011 <0.012 <0.017
<0.019 <0.012 <0.012 <0.012 02/06/96 <0.013 <0.014 <0.017 <0.012
<0.012 <0.013 <0.010 <0.014 02/13/96 <0.010 <0.015 <0.011 <0.014
<0.009 <0.008 <0.013 ' <0.012 <0.012 <0.013 <0.010 <0.011 02/20/96 <0.009 <0.011 <0.015 <0.014 , <0.011 <0.009 <0.009 <0.014 <0.016 02/27/96 <0.012 <0.012 <0.016 <0.012 <0.007 <0.012 <0.011 <0.020 <0.018 03/05/96 <0.010 <0.012 ' <0.009 <0.015 <0.015 <0.010 <0.014 <0.010 <0.011 03/12/96 <0.013 <0.010 <0.010 <0.015 <0.016 <0.009 <0.010 <0.011 03/19M6 <0.010 <0.012 <0.012
<0.008 <0.014 ' <0.011 <0.011 <0.012 03/26/96 <0.012 <0.012 <0.010 <0.015
<0.009 <0.013 - <0.012 <0.013 04/02/96 <0.012 <0.007 <0.013
<0.012 <0.014 <0.007 <0.013 <0.015 <0.018 <0.013 <0.014 04/09/96 <0.010 <0.013 <0.015
<0.016 <0.011 <0.016 <0.018 04/16/96 <0.014 <0.011 <0.017
<0.009 <0.013 <0.008 <0.013 <0.010 <0.014 <0.012 <0.011 <0.010 04/23M6 <0.012 <0.007 <0.013 <0.016 <0.014 <0.009 <0.010 <0.015 04/30/96 <0.008 <0.010 <0.017
<0.007 <0.016 <0.013 <0.009 05/07/96 <0.014 <0.009 <0.013
<0.008 <0.010, <0.009 <0.012 <0.012 <0.017 <0.008 <0.012 <0.009 05/14/96 <0.011 <0.011 <0.015 <0.013 <0.015 <0.010 <0.014 <0.014 <0.013 05/21/96 <0.008 <0.019 -9 008 <0.011 <0.008 <0.016 <0.018 <0.010 <0.012 05/28/96 <0.011 <0.009 4016 <0.013 <0.014 <0.012 <0.009 <0.007 06/04/96 <0.007 <0.013 <0.011
<0.015 <0.016 <0.006 <0.016 <0.013 06/II/96 <0.014 <0.008
<0.009 <0.007 <0.015 <0.009 <0.007 <0.008 <0.011 <0.017 <0.009 06/18/96 <0.0! 0 <0.014 -0.009 <0.012 <0.010 <0.008 <0.010 <0.011 <0.014 06/25/96 <0.010 <0.009 <D.009 <0.013 <0.016 <0.015 <0.008 <0.011 <0.008
- Sample locations required by Technical Specifications
l TABLE 13 (Continued)
NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - 0FF-SITE STATIONS l-131 ACTIVITY pCi/m i1 SIGMA LOCATION WEEK END R-1* R-2* R-3* R-4* R-5* D-2 E F G DATE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE OFF-SITE 07/02/96 <0.009 <0.008 <0.008 <0.013 <0.015 <0.009 <0.010 <0.010 <0.013 07/09/96 <0.010 <0.016 <0.009 <0.011 <0.013 <0.014 <0.007 <0.011 <0.009 07/16/96 <0.013 <0.011 <0.009 <0.014 <0.011 <0.'011 <0.014 <0.010 <0.015 07/23/96 <0.008 <0.010 <0.008 <0.009 <0.011 <0.008 <0.013 <0.011 <0.011 '
07/30/96 <0.009 <0.019 <0.016 <0.006 <0.009 <0.008 <0.008 <0.010 <0.012 08/06/96 <0.008 <0.0 ' 3 <0.012 <0.008 <0.015 <0.014 <0.010 <0.018 <0.012 08/13/96 <0.007 <0.012 <0.009 <0.013 <0.010 <0.011 <0.009 <0.013 <0.009 08/20/96 <0.008 <0.912 <0.006 <0.014 <0.015 ' <0.009 <0.010 <0.010 <0.014 08/27/96 <0.011 I <0.012 <0.012 <0.012 <0.010 <0.009 <0.016 <0.014 <0.014 09/03/96 <0.011 <0.013 <0.011 <0.013 <0.012 <0.011 <0.014 <0.013 <0.016 09/10/96 <0.009 <0.017 <0.013 <0.014 <0.006 <0.012 <0.012 <0.011 <0.018 09/17/96 <0.009 <0.010 <0.016 <0.013 <0.009 l <0.009 <0.017 <0.019 <0.012 09/24/96 <0.012 <0.010 <0.016 <0.008 <0.009 <0.007 <0.014 <0.016 <0.011 10/01/96 <0.008 <0.013 <0.013 <0.014 <0.009 <0.012 <0.010 <0.012 <0.013 10/08/96 <0.013 <0.010 <0.014 <0.016 <0.008 <0.009 <0.011 <0.015 <0.012 10/15/93 <0.013 <0.016 <0.012 <0.015 <0.011 <0.013 <0.012 <0.020 <0.011 10/22/96 <0.013 <0.012 <0.007 <0.012 <0.008 <0.015 <0.012 <0.014 <0.009 10/29/96 <0.008 <0.012 <0.010 <0.014 <0.013 <0.016 <0.010 <0.012 <0.007 11/05/96 <0.010 <0.008 <0.015 <0.014 <0.015 <0.012 <0.010 <0.016 <0.015 i 11/12/96 <0.009 <0.007 <0.013 <0.010 <0.008 <0.010 <0.005 <0.016 <0.012 t 1/19/96 <0.010 <0.008 <0.013 <0.009 <0.007 <0.014 <0.010 <0.014 <0.007 11/26/96 <0.008 <0.011 <0.013 <0.013 <0.013 <0.010 <0.011 <0.015 <0.010 12/03/96 <0.011 <0.008 <0.010 <0.016 <0.010 <0.013 <0.013 <0.011 <0.013 12/10/96 <0.010 <0.010 <0.008 <0.017 <0.013 <0.008 <0.011 <0.010 <0.006 !
12/16/96 <0.013 <0.014 <0.011 <0.014 <0.007 <0.012 <0.013 <0.010 <0.012 12/23/96 <0.011 <0.011 <0.015 <0.011 <0.011 <0.014 <0.010 <0.012 <0.011 t 12/30/96 <0.007 <0.009 <0.004 <0.015 <0.012 <0.013 <0.010 <0.010 <0.014 i
- Sample locations required by Technical Specifications
= = = = " "7"E " -- "_-- " "_-_--- - - - - -
=
TABLE 14 NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - ON-SITE STATIONS l-131 ACTIVITY pCi/m i1 SIGMA 1.OCATION WEEK ENDING DATE D1 ON-SITE G ON-SITE H ON-SITE I ON-SITE [0N-SITE K ON-SITE 01/08/96 <0.009 <0.012 <0.009 <0.015 <0.016 01/15/96 <0.011 <0.013
<0.012 <0.020 <0.022 01/22/96 <0.011 <0.010
<0.009 <0.014 <0.010 <0.014 01/29/96 <0.011 <0.010
<0.015 <0.011 <0.016 <0.012 02/05/96 <0.009 <0.012
<0.016 <0.01 I <0.008 <0.013 02/12/96 <0.011 <0.007
<0.014 <0.010 <0.010 <0.012 02/20/96 <0.012 <0.007
<0.009 <0.011 <0.008 <0.014 02/26/96 <0.013 <0.013
<0.010 <0.012 <0.018 <0.006 <0.012 <0.016 03/04/96 <0.0 t o <0.012 <0.011 <0.011 <0.012 <0.014 03/1I/96 <0.008 <0.010 <0.009 <0.013 <0.016 <0.008 03/18/96 <0.013 <0.008 <0.014 <0.014 <0.012 <0.005 03/25/96 <0.009 <0.010 <0.015 <0.012 <0.017 <0.010 04/01/96 <0.014 <0.008 <0.012 <0.016 <0.011 <0.008 04/08/96 <0.008 <0.012 <0.008 <0.014 <0.009 <0.010 04/15/96 <0.010 <0.014 <0.015 <0.016 <0.008 <0.011 04/22/96 <0.011 <0.014 <0.009 <0.015 <0.016 <0.017 04/29/96 <0.010 <0.014 <0.008 <0.011 <0.011 <0.005 05/06/96 <0.012 <0.010 <0.014 <0.015 <0.012 <0.013 05/13/96 <0.008 <0.013 <0.011 <0.011 <0.010 <0.011 05/20/96 <0.014 <0.015 <0.014 <0.018 <0.009 <0.008 05/28/96 <0.010 <0.012 <0.008 <0.009 <0.011 <0.015 06/03/96 <0.011 <0.014 <0.017 <0.012 <0.010 <0.014 06/10/96 <0.007 <0.014 <0.016 <0.015 <0.010 <0.007 06/17/96 <0.012 <0.010 <0.015 <0.018 <0.013 <0.010 06/24/96 <0.008 <0.017 <0.008 <0.017 <0.013 <0.010
TABLE 14 (Continued)
NMP/JAF SITE ENVIRONMENTAL CHARC0AL CARTRIDGE SAMPLES - ON-SITE STATIONS l-131 ACTIVITY pCi/m i 1 SIGMA LOCATION WEEK ENDING DATE D1 ON-SITE G ON-SITE H ON-SITE I ON-SITE J ON-SITE K ON-SITE 07/0I/96 <0.010 <0.012 <0.008 <0.0 I 1 <0.011 <0.011 07/08/96 <0.010 <0.010 <0.018 <0.017 <0.016 <0.010 07/15/96 <0.014 <0.011 <0.012 <0.014 <0.013 <0.012 07/22/96 <0.012 <0.008 <0.e 6 <0.012 <0.013 <0.008 07/29/96 <0.012 <0.014 <u.010 <0.014 <0.016 <0.015 08/05/96 <0.009 <0.007 <0.008 No Result <0.015 <0.021 08/12/96 <0.011 <0.011 <0.012 <0.012 <0.007 <0.012 08/19/96 <0.011 <0.011 <0.014 <0.010 <0.015 <0.013 08/26/96 <0.010 <0.011 <0.018 <0.015 <0.008 <0.008 09/03/96 <C.0!u <0.006 <0.017 <0.014 <0.0I 1 <0.015 09/09/96 <0.0aI <0.010 <0.020 <0.017 <0.013 <0.010 09/16/96 <0.012 <0.010 <0.016 <0.007 <0.009 <0.013 09/23/06 <P.010 <0.015 <0.014 <0.021 <0.014 <0.009 09/30/96 <0.014 <0.013 <0.010 <0.017 <0.013 <0.019 10/07/96 <0.007 <0.011 <0.008 <0.009 <0.012 <0.009 10/14/96 -o.010 <0.014 <0.012 <0.010 <0.011 <0.014 10/2I/96 <0.111 <0.009 <0.015 <0.011 <0.019 <0.010 10/28/96 <0.014 <0.013 <0.010 <0.015 <0.010 <0.014 l 1I/04/96 <0.010 <0.009 <0.016 <0.009 <0.009 <0.012 ,
1I/12/96 <0.025 <0.024 <0.014 <0.008 <0.016 <0.014 1I/I8/96 <0.007 <0.009 <0.009 <0.013 <0.013 <0.007 11/25/96 <0.014 <0.012 <0.016 <0.012 <0.010 <0.016 I 12/02/96 <0.007 <0.010 <0.010 <0.010 <0.010 <0.009 12/09/96 <0.009 <0.010 <0.012 <0.008 <0.011 <0.015 12/16/96 <0.014 <0.014 <0.014 <0.016 <0.013 <0.018 12/23/96 <0.008 <0.012 <0.010 <0.012 <0.016 <0.018 12/30/96 <0.008 <0.011 <0.008 <0.010 <0.012 <0.006 e e m e m .
M99m
TACLE 15 i
CONCENTRATION OF GAMMA EMITTERS IN MILK Results in units of pCi/Hter f. I sigma I i
LOCATION ' ' NUCilDESW 4-1 E4-22-96I k54-96 "
i 5-2(MI6 f 6-3-96I ' L 6-17-96 :
60 K-40 1710 i 71 1550 i 12 1670 i 89 1420 i 92 1480 t 71 1520 i 65 !
Cs-134 < 5.4 < 5.4 < 7.3 . < 8.9 < 4.0 < 4.1 :
Cs-137 < 5.3 < 5. I < 7.5 - < 7.8 <5.6 < 4.2 !
Ba/Is140 < 8.4 < 5.8 < 7.3 - < 10.0 < 9.2 <5.2 Ra-226 <l37 < 132 i'
< 155 < 157 <110 <109
, Others < LLD < LLD <13 n < LLD <Ill) <LLD 55 K-40 2210 i 62 1650 i 85 1620 i 68
- 1600 i 68 1430 1 71 1510 1 65 Cs-134 < 3.8 < 6.1 < 5.8 < 4.2 < 5.4 i < 5.4 Cs-137 < 5.6 < 7.0 < 4.8 < 4.5 < 4.8 < 5.0 l Ba/La-140 < 5.4 < 9.7 <5.6 < 7.4 < 8.7 < 5.3 i Ra-226 < 143 < 160 < 129 114 i 49 < 103 Others 114 i 49 !
<LLD < LLD <LLD <f T n
< LIJ) <11 n 50 K-40 1700 i 97 1450 i 62 1510 i 65 1410 i 62 i
1510 i 65 2190 i 60 [
Cs-134 < 8.6 < 5.0 <4.2 - < 5.4 < 4.3 < 3.6 i Cs-137 < 10.1 < 5.0 < 4.8 - < 4.3 < 4.7 < 5.2 !
Ba/Ist40 < 9.4 < 6. I < 4.7 < 7.8 < 6.6 < 5.4 i Ra-226 124 i 57 88 i 5 < lli- 110 1 40 64 i 36 171 i 50 Others <LLD < LLD < LLD < LLD <LLD <ffn !
I i 4 K-40 1470 i 93 1380 i 71 1500 i 71 1520 i 85 1540 i 97 1430 i 92 Cs-134 <4.8 <5.0 < 5.1 < 8.7 < 9.4 < 9.1 Cs-137 < 4.3 < 6.5 < 4.7 < 7.3 < 9. I < 8.5 Ba/12-140 < 6.0 < 7.0 < 7.2 < 3.5 < 12.8 < 9.3 Ra-226 < 113 < 108 < 107 < l53 < 149 <!62 Others <LLD < LLD <LLD < LIl) <LLD < LLD 65* K-40 1320 i 68 2280 i 62 2270 i 62 2250 i 62 1500 i 80 1440 1 71 Cs-134 < 4.3 < 3.7 < 4.0 < 4.3 < 7.1 < 4.0 (Control) Cs-137 < 5.9 < 5.4 <5.7 <5.8 < 6. 8 < 4.9 Ba/la-140 < 5.9 < 4.0 < 5.9 < 4.6 < 7.6 < 5.3 '
Ra-226 133 i 41 104 i 46 < 139 195 i 62 <l58 117 i 39 Others <LLD < LLD < LLD < LLD < LLD < LLD
- - Technical Specification location.
-100-
l l
TABLE 15 (Continued)
CONCENTRATION OF GAMMA EMTITERS IN MILK Results in units of pCi/ liter 1.1 sigma l LOCATION NUCLIDES 7-8 7-22-96 8-5-96 l 8-19 ~ 9-9-96 ~ 9-23-96' 60 K-40 2160 i 60 1570 i 68 1410 i 71 1440 i 71 1490 i 97 1570 i 68 Cs-134 < 3. 8 < 5.3 < 2.4 < 5.3 < 9.0 < 5.1 Cs-137 < 5.9 < 4.7 < 5.2 < 5.4 < 8.5 < 4.7 l Ba/La-140 < 5.2 < 6.2 < 9.1 < 7.0 < 6.8 < 5.9
(
Ra-226 80 i 46 < 128 96 46 < 105 87 i 54 < 133 Others < LLD < LLD < LLD < LLD <IJ n <11 n 55 K-40 1420 i 65 1620 1 97 1530 1 97 1790 i 71 1450 i 62 1340 i 27 Cs-134 < 4.7 . < 9.3 < 8.0 <5.3 < 4.9 < 6.5 Cs-137 < 4.9 ,< 8.5 < 9.9 R5.2 < 4.7 < 9.7 Ba/12-140 < 7.0 <11.6 < 10.3 < 5.9 < 7.3 <11.0 Ra-226 94 i 47 < 163 < 166 < 125 < 107 < 156 Others < LLD < LLD < LLD <LLD < LLD <11 n 50 K-40 1440 i 92 1520 i 74 1560 i 68 1470 i 65 1390 i 92 1420 i 62 Cs-134 < 8.6 < 5. I < 5.4 < 4.3 < 8.8 < 4.2 Cs-137 < 8.6 < 5.5 < 5.4 < 4.7 < 10.2 < 4.2 Ba/La-140 < 9. 8 < 7.9 < 5.7 < 5.4 < 6.4 < 5.4 Ra-226 < !65 < 92 < 125 < 126 < 155 < 117 Others < LLD < LLD < LLD <LLD <LLD <I1 n 4 K-40 1430 71 1510 i 80 1520 i 65 1670 i 102 1380 i 71 1520 i 80 Cs-134 < 4.F < 4.6 < 4.6 < 8.7 < 5.3 < 8.6 Cs-137 < 4- < 8.2 < 4.9 < 9.4 < 6.3 < 7.2 Ba/La-140 I< r .~/ < 9.6 < 7.5 < 9.4 < 7.7 <8.5 Ra-225 7? t 41 < 160 < 109 < 156 < 109 113 i 59 '
Others < LD < LLD < LLD < LLD <LLD <LLD 65* K-40 1170 i 62 1550 i 68 1420 i 71 1680 i 85 1560 i 85 1420 i 71 (Control) Cs-134 < 5.0 < 3.7 < 4.9 < 8.3 <8.7 < 4.0 Cs-137 < 4.7 < 4.5 < 5.3 < 7.9 <7.0 < 5.6 Ba/12-140 < 7.6 < 6.2 < 7.0 < 6.9 < 9.0 < 6.6 Ra-226 I!R i 40 < 127 < 100 < 163 < 161 < 101 Others < LLD < LLD < LLD < LLD <LLD < LLD
- - Technical Specification location.
-101-M M M M
t TABLE 15 (Continued)
CONCENTRATION OF GAMMA EMTITERS IN MILK Results in units ofP CIAiteri 1 sissen LOCATION NUCLIDES 7-96 i 10-21-963 L 11-4-963 11N18-9df i 12-2-96i 16-96:
60 K-40 1440 i 62 1580 i 85 1680 i 85 1460 i 97 1570 i 68 1530 i 97 Cs-134 < 4.4 < 8.4 <5.7 < 9.4 < 5.0 < 8.4 Cs-137 < 4.3 < 8.0 < 7.4 < 8.7 < 4.5 < 10.0 Ba/la-140 < 5.4 < 7.8 < 6.2 <11.1 < 5.3 < 12.5 i Ra-226 < 108 < 159 < 158 <l58 < t24 <163 ;
Others < LLD < LLD < LLD <IIn < LLD <t i n t 55 K-40 1530 i 97 1340 i 68 1410 i 92 1590 i 85 1580 i 74 1490 i 71 l Cs-l34 < 8.4 < 4.7 < 10.0 <5.8 < 4.9 < 3.9 Cs-137 < 8.3 < 5.6 < 8.6 < 7. 8 < 4.8 < 4.9 Balla-140 < 13.4 < 5.3 < 12.1 < 8.0 < 9.3 < 5.0 t Ra-226 <l56 78 i 39 < 160 102 i 54 B7 i 41 < 101 Others < LLD <LLD < LLD < LLD <ll.D <ffn :
50 K-40 1430 i 71 1520 i 12 1490 i 65 1480 i 92 1470 i 65 1460 i 52 Cs-134 < 5. I < 3.8 < 3.5 < 9.4 < 4.4 < 3.8 Cs-137 < 5. 8 < 5.~3 < 4.2 < 9.7 < 4.8 < 4.0 .
Ba/La-140 < 6.7 < 7.7 < 6.0 < 10.4 < 6.4 < 14.6 i Ra-226 < 103 <136 112 i 40 <l56 < 115 90 i 33 Others < LLD < LLD < LLD < LLD < LLD <LLD i i
4 K-40 1580 i 68 1400 i 65 1590 i 68 1550 i 74 2250 i 63 1350 i 71 ;
Cs-134 < 5.7 < 4.3 < 3. 8 < 5.8 < 5.4 <5.2 i Cs-137 < 5.0 < 4.5 < 5.1 < 5.4 '
< 5.6 <4.8 ,
Ba/La-140 < 6.5 < 4.2 < 4.7 < 7. 8 < 5.5 < 5.7 Ra-226 < 121 < 117 < 133 < 104 101 i 54 < 109 ;
Others < LLD < LLD < LLD <LLD <LLD <LLD r 65* K-40 1570 i 85 1470 i 62 1320 i 62 1520 i 85 1560 i 68 1560 i 68 ;
(Control) Cs-134 < 8.7 < 4.6 < 4.5 . < 9.4 < 5.3 < 4. 8 l Cs-137 < 7.5 < 4.7 < 4.3 . < 7.1 < 5. I < 4.7 i Ba/La-140 < 7.3 < 4.7 < 5. I < 8.0 < 7.0 < 5.6 ,
Ra-226 99 i 56 126 i 44 < 107 < 157 < 125 < 122 ;
Others < LLD < LLD <LLD < LLD < LLD < LLD I
- - Technical Specification location.
-102-i
TABLE 16 CONCENTRATION OF IODINE - 131 IN MILK (1)
Results in units of pCl/ liter LOCATION - : 4-1-96 4-22-96 ' . 5-6-96'. 5-20-96 l 6-3-96I I 6-17-96 60 <0.33 <0.26 <0.28 <0.39 <0.30 <0.56 55 <0.37 <0.36 <0.34 <0.29 . <0.50 <0.29 50 <0.33 < 0.31 <0.28 <0.52 <0.47 <0.52 4 < 0.51 <0.46 <0.50 <0.49 <0.52 <0.35 65* <0.53 <0.49 < 0.51 <0.31 <0.37 <0.47 LOCATION 8-96 '. 7-22-96 8-5-96 8-19-96 Y 9-9-96 9-23-96.
60 <0.27 <0.52 <0.48 <0.28 <0.34 < 0.51 55 <0.38 <0.29 < 0.31 <0.38 <0.38 <0.34 50 <0.33 <0.34 <0.37 <0.33 <0.52 <0.32 4 <0.51 <0.38 <0.36 <0.50 <0.29 <0.36 65* <0.47 <0.53 <0.32 <0.48 <0.47 <0.48 LOCATION - 10-7-96 10-21-964 11-4-961 11-18-96 l- 12-2-96'-
12-16-96..
60 <0.29 <0.46 <0.45 <0.47 <0.49 <0.33 55 <0.37 <0.43 <0.44 <0.34 <0.57 <0.28 50 <0.34 <0.47 <0.35 <0.31 <0.28 <0.30 4 <0.40 <0.27 < 0.51 <0.45 <0.37 <0.46 65* ,< 0.50 <0.30 <0.28 <0.28 <0.27 <0.44
- - Control Result. Technice; Specification location.
(1) Iodine 131 results ari co ected for decay to the sample stop date.
I
-103- L
TABLE 17A CONCENTRATION OF GAMMA EMHEKS IN FOOD PRODUCTS Results in units Of pCUg (wet) i_1 sigma LOCATION DATE SAMPLE TYPE Be 7 - _ K-40 .1-131 s Cs-1345 L Cs-137, Ra-226 ' AcTh-228 - OTHER L 9-9-% Pepper Leaves 0.26 i 0.03 L 5.38 i 0.13 <0.02 <0.01 <0.01 < 0.11 9-9-96 Squashleaves 0.81 i 0.04 0.04 i 0.01 < LLD L 2.59 i 0.10 <0.01 <0.01 <0.01 <0.15 9-9-96 Bean Leaves 0.44 i 0.04 0.04 i 0.01 < LLD 2.32 i 0.09 <0.02 <0.01 <0.01 0.18 i 0.06 <0.04 R 9-9-% Collard Greens 0.17 i 0.03 3.51 i 0.10 <0.01
<LLD R <0.01 <0.01 0.21 i 0.05 <0.03 <LLD 9-9-96 Swiss Chard 0.1210.02 4.91 i 0.10 <0.01 <0.01 <0.01 0.11 i 0.04 R 9-9-96 Kale 0.10 i 0.02 0.03 i 0.01 < LLD 4.13 i 0.10 <0.02 < 0.01 <0.01 0.22 i 0.05 <0.03 J 9-10-96 Squash leaves 0.83 i 0.03 <LLD 2.9410.08 <0.01 <0.01 <0.01 0.28 i 0.05 0.0410.01 J 9-10-% Pepper leaves 0.22 i 0.02 <LLD 6.17 i 0.12 <0.02 < 0.01 <0.01 <0.13 0.02 i 0.01 J 9-10-96 Tomatoes <0.05 < LLD 1.74 i 0.06 <0.01 <0.01 <0.01 0.10 i 0.04 <0.02 J 9-10-% Cucumber leaves <0.06 < LLD 4.68 i 0.11 <0.03 <0.01 <0.01 0.15 i 0.05 <0.03 K 9-19-% Tomatoes <0.05 < LLD K
2.23 i 0.04 <0.01 <0.01 <0.01 0.09 i 0.04 <0.03 9-19-96 Squash leaves 1.14 i 0.05 < LLD 2.52 i 0.11 <0.01 <0.01 <0.01 <0.17 <0.04 K 9-19-96 Pepper Leaves < LLD 0.68 i 0.03 5.6210.13 <0.01 <0.01 <0.01 0.26 i 0.06 S 9-19-96 Tomatoes <0.06 <0.03 <LLD 2.45 i 0.09 <0.01 < 0.01 < 0.01 0.09 i 0.04 <0.03 S 9-19-% Cucumber leaves 1.74 i 0.08 < LLD 1.88 i 0.08 <0.01 <0.01 <0.01 0.1I i 0.06 S 9-19-96 Pepper leaves 0.94 i 0.09 0.02 i 0.01 <LLD 8.56 i 0.27 <0.03 <0.03 <0.03 0.66 i 0.18 M* 9-9-96 Grape leaves 0.67 i 0.04
< 0.11 <LLD M* 2.30 i 0.08 <0.02 <0.01 <0.01 0.26 i 0.05 0.04 i 0.01 < LLD 9-9-% Squash Leaves 0.49 i 0.03 M* 3.63 i 0.10 <0.01 <0.01 <0.01 0.14 i 0.04 0.03 i 0.01 <LLD 9-9-96 Cucumber Leaves 0.98 i 0.06 3.26 i 0.13 <0.02 <0.01 <0.01 0.21 i 0.08 <0.05 <LLD M* 9-9-96 Pepper leaves 0.23 i 0.04 7.97 0.17 <0.01 <0.01 <0.01 0.16 i 0.06 <0.04 M* 9-9-% Tomatoes <0.07 < LLD 2.24 i 0.08 <0.01 < 0.01 < 0.01 < 0.11 <0.03 M* 9-9-96 Beet leaves 0.10 i 0.04 <LLD 8.37 i 0.19 <0.03 <0.01 <0.01 0.17 i 0.08 <0.05 <IID
- - Control result All results in units of activity per eram wet weight
-104-
TABLE 17B CONCENTRATION OF GAMMA EMTITERS IN FOOD PRODUCTS Results in units of pCi/kg (wet) 1. I sigma LOCATION DATE SAMPLE TYPE Be7- K-40 ' I-131 Cs-134 Cs-137; . Ra-226 ' AcTh-228 OTHER L 9-9-% Pepper leaves 255 i 27 5380 i 128 < 15 <6 <7 < 113 41 i 11 < LLD L 9-9-% Squash leaves 809 i 42 2590 i 105 <11 <9 <9 <146 38 i 13 < LLD L 9-9-96 Bean lesves 443 i 36 2320 t 91 < 20 <7 <9 184 i 64 < 37 < LLD R 9-9-% Collard Greens 174 i 27 3510 i 99 < 12 <8 <7 206 i 50 < 30 <LLD R 9-9-96 Swiss Chard 124 i 21 4910 i 99 <8 <6 <6 113 i 42 31 i 9 <LLD R 9-9-% Kale 102 i 25 4130 i 105 < 16 <5 ,
<7 218 i 48 < 30 < LLD J 9-10-% Squash leaves 831it33 2940 i 85 <7 <5 -
<6 276 i 46 37 i 10 < LLD J 9-10-96 Pepper leaves 224 i 25 6170 i 116 < 15 <7 <6 < 132 19 i 10 < LLD J 9-10-% Tomatoes <48 1740 i 60 < 10 <4 <6 104 t 36 < 24 < LLD 1 9-10-% Cucumber Leaves < 64 1480 i 52 < 27 <7 <7 148 i 52 <29 < LLD K 9-19-96 Tomatoes <51 2230 i 74 <7 <8 <6 93 i 44 < 27 <LLD K 9-19-% Squash leaves 1140 i 53 2520 i 113 < 14 < 11 ,
< 12 <170 <41 <LLD K 9-19-96 Pepperleaves 683 i 33 5620 i 126 <7 <5 <7 257 i 57 <29 < LLD S 9-19-96 Tomatoes < 62 2450 i 91 <8 <9 <7 94 i 44 <28 < LLD S 9-19-% Cucumber leaves 1740 1 84 1880 i 78 <8 <9 <8 107 i 56 23 i 10 <LLD S 9-19-96 Pepper Leaves 935 i 90 8560 i 271 <29 <31 < 26 660 i 179 < 110 <LLD M* 9-9-96 Grape leaves 673 i 35 2300 i 78 < l6 <5 <7 256 i 49 36 i 10 <LLD M* 9-9-% Squash leaves 494 i 30 3630 i 102 < l3 <4 <7 138 i 39 29 i 10 < LLD M* 9-9-% Cucumber Leaves 985 i 59 3260 i 130 < 24 <8 < 12 211 i 78 <46 < LLD M* 9-9-% Pepper leaves 283 i 35 7970 i 167 < l3 < 11 < 11 164 i 64 < 43 < LLD M* 9-9-% Tomatoes < 66 2240 i 83 <11 <5 <7 < 107 < 27 < LLD -
M* 9-9-% Bat Leaves 96 i 36 8370 i 194 < 27 < 12 < 13 167 i 76 < 46 <LLD !
- - Control result All results in units of activity rer kile graqi wet weight
-105- ,
M M
TAELE 18 MILK ANIMAL CENSUS 1996
- TOWN OR AREA (a) ': NO. ON CENSUS' MAP (1) - h DEGREES (2) ' DISTANCE (2) ~ NO. OF MILK ANIMALS Scriba 16 190o 5.9 None 3 190o 4.5 None !
62 183o 6.7 120 (3) 63 1850 8.0 30C 74 195o 5.6 None New Haven 9 950 5.2 40C 4* 113o 7.8 106C 10 130o 2.6 None 5 146o 7.2 None 7 107o 5.5 None 64 107o 7.9 52C Mexico 12 107o 11.5 22C 14 1200 9.8 56C 17 115o 10.2 1C 19 132o 10.5 35C 60* 900 9.5 40C 50* 93o 9.3 160C !
55* 95o 9.0 60C i 21 1120 10.5 80C 68 108o 11.6 70C 49 88o 7.9 SG (3) 72 98o 9.9 40C Oswego 73** 234o 13.9 38C Richland 22 850 10.2 52C Pulaski 23 92o 10.5 60C Volney 25 182o 9.5 None 70 147o 9.4 30C 66 156o 7.8 74C MILKING ANIMAL TOTALS: 1046 Cows (including control locations) 17 Goats MILKING ANIMAL TOTALS: 998 Cows (excluding control locations) 17 Goats
-106-
TABLE 18 (Continued) 1 MILK ANIMAL CENSUS 1996 I
NOTES-C -
Cows gl 0 - Goats g'
- = Milk sample location '
- = Milk sample control location (1) = Refereces Figure 4 1 (2) = Degrees and dicta =~ are based on NMP-2 reactor building centerline (3) Goat is ng currently producing nelik or any nelik produced is utilized by the owner l None = No cows or goats at that location. Location was a previous location with cows and/or goats.
I:
a 4
1 1
i ;
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-107-i
[
( TABLE 19 1996 RESIDENCE CENSUS t MAP.: METEOROLOGICAL LOCATION 14 CATION (1)t- : SECTOR . DEGREES (2) DISTANCE (2)
- N - -
- NNE - -
- NE - -
- ENE - -
Lake Road A E 99* 1.3 miles
( Ide Road B ESE 102' 1.1 miles
( County Route 29 C SE 130* 1.4 miles l Minor Road D SSE 163' 1.6 miles Minor Road E S 170' 1.6 miles 14sview Road F SSW 207' 1.2 miles
{ ,
Bible Camp Retreet G SW 234' O.9 miles l Bible Camp Retreat H WSW 238' O.9 miles
- W _ -
- WNW - -
- NW - -
- NNW - --
- This meteorological sector is over Ide Ontario. 'Ibere is no resh within five miles.
( (1) Corresponds to Figure 1.
Based on NMP2 reactor centerime L (2) 1
[
[
[
[
[
[ -108-
i l
TACLE 20 ,
INTERLABORATURY COMPARISON PROGRAM RESULTS
- SAMPLE ID SAMPLE TYPE ANALYSIS SITE LABORATORY RESUL'IW REFERENCli LAB. RESUL'I* NDKVm-QA 96 OI A Water GSA: Ce-141 71 i 13 pCin 88 i 4 pCin (A) 0.87 99 i 1i pCill 109 i 17 pCin Cr-51 248 i 72 pCi/l 322 i 16 pCill (A) -1.34 330 i 63 pCi/l i 187 i 88 pCill l
Cs-134 60 i 4 pCin '
58 i 3 pCi/l(A) -1.73 55 i 4 pCi/l 50 i 4 pCill Cs-137 61 i 5 pCi/l 64 i 3 pCill(A) -1.08 56 i 6 pCi/l 58 i 6 pCill Co-58 32 i 7 pCi/l 48 i 2 pCi/l (A) 0.87 48 i 7 pCill 42 i 7 pCill Mn-54 30 i 5 pCill 31 i 2 pCill(A) 0.35 37 i 6 pCi/l 33 i 5 pCi/l Fe-59 89 i 13 pCi/l 83 i 4 pCia (A) 1.21 86 i 14 pCill 97 i 17 pCill Zn45 83 i 12 pCill 97 i 5 pCill (A) 1.25 86 i 12 pCill 84 i 12 pCill Co40 82 i 5 pCill 76 i 4 pCill (A) 0.0 74 i 5 pCill 82 i 5 pCill QA 96-02A Air Filter GSA: Ce-141 158 i 39 pCi/ filter 170 i 9 pCi/ filter (A) -1.02 163 i 31 pCi/ filter 159 i 40 pCi/ filter
-109-
TACLE 20 INTERLABORATORY COMPARISON PROGRAM RESUL15 (continued) iSAMPLE ID SAMPLE TYPE ~ ANALYSIS SITE LABORATURY RESULT
- REFERENCE LABIRESULT* " .NDKV8 QA 9642A Air Filter Cs-134 96 i 6 pCi/Giter 112 i 6 pCi/ filter (A) 2.63 (conunued) 101 i 5 pCi/Siter 89 i 5 pCi/ filter
- Cs-137 107 i 8 pCi/61ter 123 i 6 pCi/ filter (A) 1.27 121 i 7 pCi/fiher 114 i 6 pCi/ Steer Co-58 72 i 17 pCi/ filter 93 i 5 pCi/ filter (A) -1.56 87 i 13 pCi/fiher 92 i 15 pCi/ Sher Mn-54 72 i 9 pCi/ filter 61 i 3 pCi/ filter (A) 0.17 52 i 6 pCi/ filter 63 i 7 pCi/ filter Fe-59 132 i 62 pCi/Elter 162 i 8 pCi/ filter (A) 0.0 161 i 44 pCi/ filter 192 i 53 pCi/fiher Zn-65 211 i 27 pCi/ filter 188 i 9 pCi/ filter (A) 1.38 191 i 17 pCi/ filter 203 i 12 pCi/ Sher Co-60 144 i 9 pCi/ filter 148 i 7 pCi/ filter (A) 4.47 136 i 7 pCi/fiher 152 i 6 pCi/ filter QA 96-03A Water H-3 3359 i 107 pCiniter 2982 i 149 pCiAiter (A) 1.76 3355 i 107 pCiniter 3323 i 107 pCiniter QA 96-04A Air I-131 83 i 5 pCi/cc 83 4 pCi/cc (A) 4.63 71 i 12 pCi/cc 70.7 i 12.4 pCi/cc 87 i 13 pCi/cc QA %-05A Air Filter Gross Beta 29.7 i 0.6 pCi/fiher 27 i i pCi/ filter (A) 0.52 30.0 i 0.6 pCi/ Sher 30.0 i 0.6 pCi/ filter
-110-
TAELE 20 INTERLABORATORY COMPARISON PROGRAM RESUL'IS (continued)
SAMPLE ID SAMPLE TYPE ANALYSIS- SITE LABORATORY RESUL'I* REFERENCE IAB. RESUL'I* NDKV2 QA 96-06A Soil GSA: Ce-141 0.51 i 0.06 pCilg 0.47 i 0.02 pCilg (A) 0.49 Cr-51 0.99 i 0.10 pCilg 1.22 i 0.06 pCi/g (A) -2.17 Cs-134 0.31 i 0.03 pCilg 0.36 i 0.02 pCilg (A) 4.64 Cs 137 0.96 i 0.01 pCilg 0.89 i 0.04 pCilg (A) 0.91 Co-58 0.21 i 0.07 pCi/g 0.20 i 0.01 pCilg (A) 0.58 Mn-54 0.7010.10 pCi/g 0.65 i 0.03 pCilg (A) 0.71 Fe-59 0.26 i 0.05 pCilg 0.17 0.01 pCi/g (A) 6.11 Co 60 0.17 i 0.05 pCilg 0.08 i 0.01 pCi/g (A) 0.0 QA %-07A ;lk I-131 10 i 3 15 i 1 -1.18 QA 96-07A Milk GSA: Ce-141 216 i 9 pCi/ liter 215 i 11 pCill(A) 0.07 Cr-51 581 i 17 pCi/ liter 563 i 28 pCill(A) 0.45 Cs-134 156 i i pCiniter 166 8 pCill (A) 4.85 Cs-137 403 i 6 pCiniter 410 i 21 pCin (A) 4.24 Co-58 93 i 2 pCiniter 93 i 5 pCi/l (A) 0.0 Mn-54 315 i 9 pCiniter 300 i 15 pCin (A) 0.71 Fe-59 8212 pCi/ liter 7714 pCill(A) 0.71 Zn-65 60 i 4 pCilliter 58 i 3 pCill(A) 0.28 Co-60 84 i 4 pCi/ liter 84 i 4 pCi/l(A) 4.14 QA 96-08A Water I-131 43.4 i 0.6 pCi/ liter 45 i 2 pCi/ liter (A) 4.87 39.9 i 2.6 pCiniter 42.1 i 2.7 pCi/ liter QA %-09A Milk I-131 10.0 i 3.0 pCi/ liter 15 i i pCi/ liter (A) -1.18 10.2 i 2.5 pCiniter QA 96-09A Milk GSA: Cc-141 320 i 10 318 i 6 0.0 323 i 15 312 i 14 Cr-51 579 i 45 486 i 24 2.00 557 i 41 489 i 63
-111-
._ __ ____--__ _ _ A ________- _ _ _ _ _ _ _ _ _ - _ _ - _ _ _ _ - _ .
TABLE 20 INTERLABORATORY COMPARISON PROGRAM RESULTS (continued) i SAMPLE ID SAMPLE TYPE ' ANALYSIS SITE LABORATORY RESUL1*) L REFERENCE LAB. RESUL'IS8 .NDKV2 f
QA 9649A Milk Cs-134 200 i 5 (continued) 222 i 11 -0.86 217 i 7 217 i 5 Cs-137 152 i 6 169 i 8 -1.13 i 152 i 7 170 i 6 Co-58 129 i 9 .
131 i 7 0.0 129 i 6 !
I 136 i 6 ! '
Mn-54 194 i 7 180 i 9 0.67 185 i 8 i 182 6 Fe-59 34 i 8 ,
37 i 2 0.52
)
)
51 i 14 34 i 8 Zn45 90 i 10 70 1 4
~ 1.39 67 i 8 76 i 9 Co-60 106 i 6 114 6 0.0 117 i 5 118 i 4 QA 96-10A Air Filter GSA: Ce-141 301 i 17 pCi/ filter 287 i 14 pCi/ filter (A) 0.60 314 i 18 pCi/ filter 293 i 17 pCi/ filter Cr-51 429 i 86 pCi/ filter 438 i 22 pCi/ filter (A) -1.03 346 i 99 pCi/ filter 460 i 77 pCi/ filter Cs-134 177 i 9 pCi/ filter 200 i 10 pCi/ filter (A) -1.82 170 i 11 pCi/ filter 185 i 9 pCi/ filter Cs-137 174 i 12 pCi/ filter i18 i 6 pCi/ filter (A) 1.60 168 i 14 pCi/ filter 157 i 12 pCi/ filter
-112-
TAELE 20 ITRERLABORATORY COMPARISON PROGRAM RESULTS (continued)
SAMPLE ID SAMPLE TYPE - ANALYSIS SITE LABORATORY RESULTS ? REFERENCE LAB. RESUL'I* .NDKV2 QA %IDA Air Filter Mn-54 208 i 14 pCi/ filter 162 i 8 pCi/ filter (A) 0.59 (continued) 185 i 15 pCi/ filter 183 i 13 pCi/ filter .
Fe-59 27 i 15 pCi/ filter 34 i 2 pCi/ filter (A) 2.57 39.5 i 23.7 pCi/ filter Za-65 71.6 i 16.2 pCi/ filter 63 i 3 pCi/ filter (A) 2.77 75.9121.3 pCi/ filter 91.0 i 16.8 pCi/ filter Co-60 106 i 9 pCi/ filter 103 i 5 pCi/ filter (A) 0.84 110 i 11 pCi/ filter 108 i 9 pCi/ filter QA %lIA Air I-131 55.2 i 6.5 pCi/cc 60 i 3 pCi/cc (A) -1.15 61.4 i 6.6 pCi/cc ,
63.8 i 17 pCi/cc QA %-12A Air Gross Beta 77.7 i 15 pCi/ filter 77.0 i 3.85 pCi/ filter (A) 4.26 l 74.5 i 15 pCi/ filter 75.0 i 15 pCi/ filter QA 96-13A Water GSA: I-131 42.5 i 4.1 pCilliter 39 i 2 pCilliter (A) 4.29 42.1 i 5.9 pCi/ liter 30.3 i 4.4 pCi/ liter Ce-141 283 i 6 pCi/ liter 272 i 14 pCilliter (A) 0.57 248 t 8 pCilliter 277 i 6 pCilliter Cr-51 218 i 23 pCilliter 209 i 10 pCi/ liter (A) 4.99 182 i 31 pCi/ liter a
191 i 26 pCilliter Cs-134 166 i 3 pCi/ liter 172 i 9 pCi/ liter (A) 4.81 162 i 4 pCi/ liter 163 i 3 pCilliter
-113-la m _
m _
m m M M M M M M
v . - - - -
- w .. . . - . - - . . .
m TACLE 20 INTERLABORA'IURY COMPARISON PROGRAM RESULTS (continued)
SAMPLE ID SAMPLE TYPE ANALYSIS - SITE LABORATORY RESULW REFERENCE LAB. RESULTm! NDKVS.
QA 96-13A Water Cs-137 186 i 5 pCiniter 191 i 10 pCiniter (A) 4.73 (continued) 185 i 6 pCiniter 177 i 5 pCiniter Co-58 114 i 4 pCiniter i19 i 6 pCinitor (A) 4.15 117 i 5 pCiniter 123 i 4 pCiniter Ma-54 220 i 5 pCiniter 202 i 10 pCinitor (A) 1.46 221 i 6 pCiniter 216 i 5 pCiniter Fe-59 57.7 i 4.9 pCiAiler 48 i 2 pCiniter (A) 1.73 60.5 i 6.4 pCiniter 56.4 i 5.3 pCilliter Za-65 96.0 i 5.9 pCiAiter 91 i 5 pCiniter (A) 0.0 88.4 i 7.7 pCiniter 89.0 i 6.4 pCiSiter Co-60 114 i 3 pCi/ liter 108 i 5 pCiniter (A) 0.64 112 4 pCiniter Ii1 i 3 pCiniter i
t
-114-
TABLE 20 2.TERLABORATORY COMPARISON PROGRAM. RESULTS (continued)
SAMPIE ID SAMPLE TYFE . ANALYSIS SITE LABORATORY RESUL'1* f REFERENCE IAB. RESULT" - REFERENCE RATIO 5 QA 96 01E Soil GSA: Cs-137 2021 i 28 Bq/kg 1550 i 22 Bq/kg (EML) 1.30 Co-60 3.75 i 0.75 Bq/kg 2.92 i 0.21 Bq/kg (EML) 1.28 QA 96-02E Air Filter Gross Bets 0.56 i 0.03 Bq/ filter 0.050 i 0.05 Bq/ filter (EML) 1.10 0.5610.03 Bq/ filter 0.53 i 0.03 Bq/ filter QA 96 03E Air Filter GSA: Mn-54 6.0 i 0.4 Bq/ filter 6.35 i 0.27 Bq/ filter (EML) 0.92 5.8 i 0.4 Bq/ filter 6.2 i 0.4 Bq/ filter 5.9 i 0.4 Bq/ filter 5.3 i 0.4 Bq/ filter Co-57 12.7 i 0.6 Bq/ filter 14.8 i 0.8 Bq/ filter (EML) 0.86 12.5 i 0.6 Bq/ filter 13.7 i 0.6 Bq/ filter 12.4 i 0.6 Bq/ filter 12.5 i 0.6 Bq/ filter Co40 7.5 i 0.3 Bq/ filter 8.64 i 0.43 Bq/ filter (EML) 0.91 8.4 i 0.3 Bq/ filter 7.8 i 0.3 Bq/ filter 7.7 i 0.3 Bq/ filter 7.8 i 0.6 Bq/ filter Ru-106 9.0 i 1.4 Bq/ filter 10.8 i 1.1 Bq/ filter (EML) 0.91 9.1 i 1.4 Bq/ filter 11.4 i 1.4 Bq/ filter 11.1 i 1.4 Bq/ filter 8.4 i 1.4 Bq/ filter Sh-125 9.8 i 0.3 Bq/ filter 10.8 i 0.5 Bq/ filter (EML) 0.88 9.2 i 0.3 Bq/ filter 9.7 i 0.3 Bq/ filter 9.510.3 Bq/ filter 9.1 i 0.3 Bqifilter
-115-M M M M M M
I i TAELE 20 INTERLABORATORY COMPARISON PROGRAM RESUL13 (continued) i SAMPLE ID
- SAMPLE TYPE ANALYSIS STTE LABORAToliY RESULN REFERENdB LAB. RESUL1* ' REFERENCE RATIO 85 QA 96-03E Air Fiher GSA: Cs-134 9.3 i 0.5 Bq/ filter 10.8 i 0.4 Bq/nleer (EML) 0.86 (continued) 9.8 i 0.5 Bq/ filter 9.7 i 0.5 Bq/nleer 9.7 i 0.5 Bq/Elter 9.8 i 0.5 Bq/ filter 8.8 i 0.5 Bq/ Alter Cs-137 7.0 i 0.2 Bq/ filter 8.52 i 0.37 Bq/ filter (EML) 0.83 t 6.9 i 0.2 Bq/ filter 7.4 i 0.2 Bq/ filter 7.1 i 0.2 Bq/ filter t f r 10.2 Bq/ filter i
QA 96-04E Vegetshon GSA: Cs-137 267 i 5 Sq/kg 190 i 7.0 Bq/kg (EML) 1.41 Co-60 14.6 i 0.7 Bq/kg 10.9 i 0.7 Bq/kg (EML) 1.34 I QA 96-05E Water H-3 603 i 4 Bq/hter 587 i 58 Bq/ liter (EML) 1.04 610 i 4 Bq/ liter 611 i 4 Bq/hter QA 96-06E Water Gross Beta 522 i 16 Bq/ liter 540 i 54 Bq/ liter (EML) 0.92 492 i 16 Bq/ liter 481 i 16 Bq/hter i
-116-
_ _ . . _ _ . _ _ . _ . _ _ _ _ _ _ . _ . . _ _ _ . _ _ _ _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ _ -___.________ _ _ . , - . _ . . . _ _ . , _ ~ - , _ _ . - _ . _ . . . . _ . . . . . _ , . - . . _ _ . - . . _ _ , , _ . . . _
TABLE 20 thTcRLABORATORY COMPARISON PROGRAM RESULTS (continued)
SAMPLE ID SAMPLE TYP*a ANALYSIS SITE LABORATORY RESULT"2 REFERENCE IAB. RESUL'1" REFERENCE RATIO 2 QA 96-07E Water GSA: Cs-137 82.5 i 7.7 Bq/ liter 89.5 i 1.36 Bq/ liter (EML) 1.03 9.02 i 7.7 Bq/ liter 104.3 i 7.7 Bq/ liter Mn-54 61.1 i 5.0 Bq/ liter 60.5 i 0.6 Bq/ liter (EML) 0.99 53.3 i 5.0 Bq/ liter 65.1 i 5.0 Bq/ liter Co-60 63.2 i 4.5 Bq/ liter 61.1 10.7 Bq/ liter (EML) 1.01 59.2 i 4.5 Bq/ liter 63.6 i 4.5 Bq' liter NOTES: (1) = Results reported as activity i I sigma error.
(2) - NDKV - Normalimd Deviation from a Known Value (3) = Reference Ratio = Reported Value/Known Value A = Reference sample provided by Analytics, Inc.
EML = Reference sample provided by Eavironmental Measurements lab, Dw^wt of Energy 1
-117-m m a m W . .
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TABLE 22 IIISTORICAL ENVIRONMENTAL SAMPLE DATA 1 SIIORELINE SEDIMENT (INDICATOR)
- Cs-137 Co40 YEAR MIN. MAX. MEAN L MIN. ! MAX.- 1MEAN 1979 '2) (2) Q) (2) G) (2) 1980 (2) (2) (2) p) (2) (2) 1981 p) G) G) g) G) Q) 1982 (2) G) , p) (2) p) p) 1983 (2) (2) , G) Q) G) g) 1984 (2) (2) ' G) 'G) Q) (2) 1985 LLD LLD LLD LLD LLD LLD .
1986 LLD LLD LLD LLD LLD LLD 1987 1988 LLD LLD LLD LLD LLD LLD LLD LLD LLD i LLD LLD 1989 0.25 0.34 0.30 LLD LLD LLD 1990 0.28 0.28 0.28 LLD LLD LLD 1991 0.11 0.16 0.14 LLD LLD LLD 1992 0.10 0.16 0.13 LLD LLD LLD 1993 0.17 0.49 0.33 LLD LLD LLD 1994 0.08 0.39 0.24 LLD LLD LLD 1995 0.16 0.17 0.16 LLD LLD LLD 1996 0.13 0.18 0.16 LLD LLD LLD Results in pCi/g (dry)
(1) location was off-site at Sunset Beach (closest location with recreational value).
(2) Sampling initiated in 1985 as required by the new Technical Specifications.
-119-m m W M M M M M M M M M M M
TABLE 23 IIISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (CONTROL)
- Cs-137 YEAR MIN. MAX. MEAN 1976 1.2 1.2 1977 1.2 0.13 0.13 1978 0.13 0.04 0.20 1979 0.09 0.03 0.06 1980 0.04 0.03 0.11 1981 0.06 0.028 0.062 1982 0.043 0.027 0.055 1983 0.046 0.041 0.057 1984 0.049 0.015 0.038 1985 0.032 0.026 0.047 1986 0.034 0.021 0.032 1987 0.025 0.017 0.040 1988 0.031 0.023 0.053 1989 0.033 0.020 0.033 1990 0.029 0.025 0.079 1991 0.043 0.016 0.045 1992 0.030 0.019 0.024 1993 0.022 0.023 0.041 1994 0.032 0.012 0.035 1995 0.024 0.014 0.020 1996 0.016
, 0.014 0.018 0.016 Results in pCi/g (wet)
(1) Control location was at an area beyond the influence of the site (westerly direction).
-120-
TABLE 24 IIISTORICAL ENVIRONMENTAL SAMPLE DATA FISH (INDICA'IUR) ("
Cs-137 YEAR MIN. : MAX. MEAN.
1976 '
O.5 3.9 1.4 j 1977 0.13 0.79 0.29 l 1978 0.03 0.10 0.08 IB79 0.02 0.55 0.10 1580 0.03 0.10 0.06 198I 0.03 0.10 0.06 1982 0.034 0.064 0.048 1983 0.033 0.056 0.045 j 1984 0.033 0.061 0.043 1985 0.018 0.044 0.030 I?86 0.009 0.051 0.028 l 1037 0.024 0.063 0.033 1988 0.020 0.074 0.034 1989 0.020 0.043 0.035 1990 0.024 0.I15 0.044 1991 0.021 0.035 0.027 1992 0.013 0.034 0.026 1993 0.021 0.038 0.030 1994 0.011 0.028 0.020 1995 0.016 0.019 0.018 1996 0.014 0.016 0.015 Results in pCi/g (wet)
(1) Indicator locations are in the general area of the NMP-1 and J. A. FitzPatrick cooling water discharge structures.
-121-1 1_- ______ --- -- - _.
~
TABLE 25 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER (CON 1ROL)
- Cs-137 ,
C440 YEAR : MIN. NAX.l i MNdN iMIN. 1 MdX. :MEAN 1976 (1) 1977 (1) (l) (1) (1) (1)
(2) (2) (2) 1978 LLD (2) G) (2)
LLD LLD 1979 2.5 (2) (2) (2) 2.5 2.5 LLD 1980 LLD LLD LLD LLD ' 11D LLD 1981 LLD LLD LLD LLD LLD .l.4 1982 1.4 1.4 LLD LLD LLD 1983 LLD LLD LLD LLD LLD LLD 1984 LLD LLD LIE LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 LLD LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD 11D 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD 1996 LLD LLD 11n LLD LID 11n iin Results in pCi/ liter (1) No gamma analyses perforined (not required).
(2) Data showed instrument background results.
(3) Imation was the City of Oswego Water Supply for 1976 - 1984 and the Oswego Steam Seaham inlet canal for 1985 - 1996.
-122-
TABLE 26 HISTORICAL ENVIRONMENTAL SAMPLE IATA SURFACE WATER (INDICA'IOR)
MAX. MEAN- . MIN. -MAX. MEAN lE76 (1) (1) (k) (1) (1) (1) 19 7 G) G) Q) G) p) G) 1978 LLD LLD LLD G) p) p) 1979 LLD LLD LlD LLD LLD LLD 1980 LLD LLD LLD LLD LLD LLD ,
1981 LLE LLD LLD LLD LLD LLD 1982 0.43 0.43 0.43 1.6 2.4 1.9 1983 LLD LLD LLD LLD LLD LLD 1084 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD I?86 11D LLD LLD LLD LLD LLD 1987 LLD LLD LLD LLD LLD LLD IT88 LLD LLD LLD LLD LLD LLD i I?89 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD LLD LLD LLD LLD LLD 2993 LLD LLD LLD LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD 1.1 n Results in pCi/ liter (1) No gamma analyses performed (not requira').
i (2) Data showai instrument background result..
(3) location was the J. A. FitzPatrick inlet canal.
-123-m M M M M M M M M M M M M M M M
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TABLE 28 HISTORICAL ENVIRONMENTAL SAMPLE DATA SURFACE WATER TRITIUM (INDICA'IT)R)
- TRITIUM YEAR MIN. MAX.' MEAN' 1976 365 889 627 l 1977 380 530 455 1978 377 560 476 1979 176 276 228 l')80 150 306 227 1981 212 388 285 1982 194 311 266 <
1983 -
249 560 347 1984 I 110 375 280 1985 250 1200 (2) 530 I?86 260 500 380 1987 160 410 322 1988 430 480 460 1989 210 350 280 1990 220 290 250 1991 250 390 310 1992 240 300 273 1993 200 280 242 1994 g
i80 260 220 1995 320 320 320 19 % LLD LLD LLD l
Results in pCi/ liter (1) Indicator location is the FitzPatrick inlet canal.
(2) Suspect sample contamination. Recollected samples showed normal levels of tritium.
-125-
TAELE 29 HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (CONTROL)
- DOSE (mrem)
YEAR MIN. '- MAXI ' MEAN -'
n._wp_
1 (1) (1) 1970 6.0 (1) 1971 7.3 6.7 2.0 6.7 1972 4.3 2.2 6.2 1973 4.4 2.2 6.9 l 1974 4.7 I 2.7 8.9 1975 5.6 'i 4.8 6.0 1976 5.5 3.2 7.2 1977 5.4 4.0 8.0 1978 5.3 3.3 4.7 1979 4.3 3.3 5.7 1980 4.7 3.8 5.8 1981 4.9 3.5 5.9 1982 4.8 3.8 6.1 1983 4.9 5.I 1984 7.2 5.8 4.7 8.2 1985 6.2 4.5(4.4)* 7.6 (6.8)*
1986 5.6 (5.4)*
5.3(5.5)* 7.5(7.2)*
1987 4.6 (4.6)*
6.3(6.3)*
1988 6.6(5.8)* 5.4 (5.2)*
4.4 (4.8)* 6.8 (6.8)*
1989 5.6(5.4)*
2.9(2.9)* 6.4 (5.6)*
1990 4.7 (4.6)*
3.7 (3.7)* 6.0 (5.9)*
1991 4.7 (4.6)*
3.8(3.8)* 5.4 (5.3)*
1992 4.5 (4.3)*
2.6 (2.6)* 5.0 (4.7)*
1993 4.1 (3.9)*
3.4 (3.4)* 5.6 (5.2)*
1991 4.4 (4.3)*
3.1 (3.1)* 5.0 (4.6)*
1995 4.1 (3.9)*
3.4 (3.4)* 5.7 (4.9)*
1996 4.4(4.2)*
3.4 (3.4)* 5.6 (5.6)* 4.3 (4.2)*
Results in mrem per standard month (1) Data not available.
(2) TLD #8,14,49,1II and i13 where applicable.
( )* TLD result based on the Technical SpeciGeation requimi locadons (TLD #14 and 49).
-126-
TACLE 30A IIISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD (SITE BOUNDARY)
- DOSE (mrem) l LOCATION: SITE BOUNDARY
- YEAR MIN. MALE i ME.W Preop (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) 1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1)
(1) (1) 1982 i (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.1 12.6 6.2 1986 4.4 18.7 7.0 1987 4.4 14.3 6.1 1988 3.4 17.9 6.4 1989 2.8 15.4 5.9 1990 3.6 14.8 5.8 1991 3.2 16.7 5.7 1992 3.2 10.4 4.8 1993 3.3 11.6 5.3 1994 2.8 12.4 5.2 1995 3.5 9.6 5.4 1996 3.2 9.1 5.2 Results in mrem per standani month (1) No data available (not required prior to 1985).
(2) TLD locations initiated in 1985 as required by the new Technical Specifications. Includes TLD numbers 75, 76, 77, 23, 78, 79, 80, 81, 82, 83, 84, 7,18, 85, 86, and 87.
-127-M M M M M M M M M M M M M M M M'
TACLE 303 1
HIS'IORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TIE
! I DOSE (areen)
LOCNrlON: OFF-SrtT SECIORS 88 YEAR hMIN[- iMAX. 1MEANJ Preap (1.'s (1) (1) 1970 (1) (1) (1) i 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1) '
1974 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1) 1981 (1) (1) (1) 1982 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 4.0 7.1 5.0 1986 4.6 8.6 6.0 1987 4.3 6.0 5.2 IE88 3.8 7.0 5.3 1989 2.5 6.8 4.9 1990 3.6 6.3 4.7 1991 3.6 5.6 4.5 1992 2.9 5.0 4.1 1993 3.4 6.3 4.5 1994 3.0 5.1 4.0 1995 3.2 5.2 4.2 1996 3.2 5.3 4.2 Results in mrem per standard month (1) No data available (not required prior to 1985).
(2) TLD locations initiated in 1985 as required by the new Techecal Specifications. Includes TLD numbers 88, 89,90, 91,92, 93,94, and 95.
-128-
TACLE 30C HIS'IURICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)
LOCATION: SPECIALINTEREST mm YEAR MIN.- MAX. MEAN Preep (1) (1) (1) 1970 (1) (1) (1) 1971 (1) (1) (1) 1972 (1) (1) (1) 1973 (1) (1) (1)
IW4 (1) (1) (1) 1975 (1) (1) (1) 1976 (1) (1) (1) 1977 (1) (1) (1) 1978 (1) (1) (1) 1979 (1) (1) (1) 1980 (1) (1) (1)
IC81 (1) (1) (1) is82 (1) (1) (1) 1983 (1) (1) (1) 1984 (1) (1) (1) 1985 3.9 6.8 5.3
!!86 4.8 8.2 6.1 1987 3.5 6.0 5.I 1988 ,
3.9 6.6 5.3 1989 2.I 7.0 4.8 1990 3.2 6.3 4.7 1991 2.9 5.6 4.4 1992 3.0 4.8 4.1 1993 3.2 5.8 4.5 1994 2.9 4.8 4.0 1995 3.4 4.9 4.3 1996 3.2 5.3 4.2 Results in mrem per standard month i
(1) No data available (not requiral prior :o 1985).
(2) TLD locations initiated in 1985 as required by the new Technical Specifications. TLD's included are numbers %,58,97,56,15, and 98.
TLD locations include critical residences and populated areas near the site.
-129-M M M M M M .
M M M M M M M M M M M M Y
TABLE 30D HISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)
LOCATION: ON-SITE INDICATOR
- YEAR ~ MIN. IMAX, ~ MEAN Preop (1) (1) (1) 1970 4.7 9.0 6.0 1971 1.5 7.7 4.7 1972 2.3 8.2 4.9 1973 3.0 24.4 6.6 1974 3.1 10.6 5.7 1975 4.6 16.0 7.3 1976 3.7 18.8 6.9 l@77 3.0 15.3 5.7 1978 3.0 9.0 4.3 1979 2.7 8.3 4.3 1980 3.9 12.0 5.3 1981 4.1 11.8 5.8 1982 3.9 13.0 6.3 1983 5.0 16.5 6.9 1984 4.6 13.2 7.0 1985 4.7 15.9 6.3 1986 4.7 16.1 7.0 1987 4.0 11.4 5.8 1988 4.4 11.9 6.0 19!,9 2.7 14.5 6.0 1990 3.6 12.9 5.5 1991 3.2 11.6 5.I 1992 3.2 5.6 4.3 1993 3.I 13.6 5.2 1994 2.8 14.3 5.1 1995 3.5 28.6 6.2 1996 3.1 32.6 6.4 Results in mrem per standard month 1
(1) No data available.
(2) 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 - 1996). Locations are existing or previous on-site environmental air monitoring locations.
-130-
_._.._.1 _ _ . _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ . _ _ _ _ _ - . . _ . _ _ _ _ _ _ _ _ _ _ . _ _ _ . - .__.
TAELE 30E IIISTORICAL ENVIRONMENTAL SAMPLE DATA ENVIRONMENTAL TLD DOSE (mrem)
LOCATION: OFF41TE INDICATOR m YEAR MIN. MAX. MEAN-Preop (1) (1) (1) 1970 5.0 8.0 6.7 I971 1.1 7.7 4.5 1972 1.8 6.6 4.4 1973 2.2 6.9 4.1 1974 2.4 8.9 5.3 1975 4.5 7.1 5.5 1976 3.4 7.2 5.2 1977 3.7 8.0 5.3 1978 2.7 4.7 3.7 1979 3.0 5.7 4.0 1980 3.1 5.8 4.6 I!81 3.6 5.9 4.7
!!82 4.0 6.2 5.2 1583 4.6 7.2 5.6 1984 4.6 8.2 6.I
!!85 4.6 7.7 5.5 I?86 5.0 7.6 6.I 1987 4.4 6.6 5.2 1588 4.2 6.6 5.4 1989 2.8 6.4 4.6 1990 , 3.8 6.0 4.8 1991 3.4 5.4 4.3 1992 3.1 5.2 4.I 1993 3.2 5.6 4.3 1994 3.0 5.0 4.0 1995 3.9 5.7 4.4 1996 3.3 5.5 4.I Results in mrem per standard month (1) No data available.
(2) locludes TLD numbers 8, 9,10, !!.12. and 13 (off-site environmental air monitoring locations).
-131-M M M -
M M M M M M M M M M M M
IIISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (CONTROL) "8 GROSS BETA YEAR MIN. MAX.
1977 ' MEAN 0.001 1978 0.484 0.01 0.125 1979 0.66 0.010 0.16 1980 0.703 0.009 0.077 1981 0.291 0.016 0.056 1982 0.549 0.011 0.165 1983 0.078 0.007 0.033 1984 0.085 0.013 0.024 1985 0.051 0.013 0.026 1986 0.043 0.008 0.024 1987 0.272 0.009 0.039 1988 0.037 0.008 0.021 1989 0.039 0.007 0.018 1990 0.039 0.003 0.017 1991 0.027 0.006 0.013 1992 0.028 0.006 0.014 1993 0.020 0.007 0.012 1994 0.022 0.013 0.008 0.025 1995 0.0I4 0.006 0.023 1996 0.014 0.009 0.023 0.014 Results in pCi/m' (1) locations used for 1977 - 1984 (formerly C off-site location). were C off-site, Di off-site, D2 off-site, E off-site, F off-site, and G off-site. Control location R-5 off-site
- 1996was used fo
-132-
TACLE 32 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATE GROSS BETA (INDICA *IDR)
- GROSS BETA YEAR MIN. TMAX. L MEAN 1977 0.002 0.326 0.106 1978 0.01 0.34
' 0.11 1979 O.001 0.271 0.058 1980 0.002 0.207 0.044 1981 0.004 0.528 0.151 1982 0.001 0.113 0.031 1983 0.002 0.062 0.023 1984 0.002 0.058 0.025 1985 0.010 0.044 0.023 1986 0.007 0.289 0.039 1987 0.009 0.040 0.021 1988 0.007 0.040 0.018 1989 0.007 0.041 0.017 1990 0.005 0.023 l
0.014 1991 0.007 0.033 0.015 1992 0.005 0.024 0.012 l 1993 0.005 0.025 0.014 1994 0.006 0.025 0.015 1995 0.004 0.031 0.014 1996 l 0.006 0.025 0.013 Results in pCi/m' (1) Locations used for 1977 - 1984 were D1 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. 1985 - 1996 locations were R-1 off-site, R-2 off-si's R-3 off-site, and R-4 off-site.
-133-m m m M M M M M M M M M M M M M M M
TAELE 33 HISTORICAL ENVIRONMENTAL SAMPLE DATA AIR PARTICULATES (CONTROL)
1977 0.0002 MEAN 0.0112 0.0034 1978 0.0008 0.0034 0.0347 0.0042 0.0018 0.0172 1979 0.0008 0.0003 0.0056 0.0047 0.0016 0.0020 1980 0.0015 0.0005 0.0014 0.0018 3.0016 0.0009 1981 -
0.0003 LLD LLD 0.0042 0.0017 LLD 1982 0.0002 0.0003 0.0012 0.0009 0.0004 0.0008 1983 0.0002 0.0004 0.0007 0.0002 0.0002 0.0006 1984 LLD 0.0007 0.0007 LLD LLD 0.0007 1985 LLD 0.0004 0.0012 LLD LLD 0.0008 1986 0.0075 LLD LLD 0.0311 0.0193 LLD 1987 LLD LLD LLD LLD LLD LLD 1988 LLD LLD LLD LLD LLD LLD 1989 LLD LLD LLD LLD LLD LLD 1990 LLD LLD LLD LLD LLD LLD 1991 LLD LLD LLD LLD LLD LLD 1992 LLD 11D LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD 1994 LLD LLD I1D LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD i_t n LLD LLD rin iJn LLn Results in pCi/m' (1)
Locations included composites of C, DI, E, F, and G off-site air monitoring locations for 1985 - 1996. 1977 - 1984. Sample location included only R 5 air monito ir ng location for 1
1
-134-d _
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) E5 m m M g W W f TABLE 35 1
IIISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE (CONTROL)
- IODINE-131 YEAR MIN. ~ MAX. . .
. MEAN-1976 , 0.01 5.88 0.60 1977 1 0.02 0.82 0.32 1978 0.03 0.04 0.03 1979 LLD LLD LLD 1780 LLD LLD LLD 1981 . LLD LLD LLD 1982 0.039 0.039 0.039 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 LLD LLD LLD IT86 0.041 0.332 0.151 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD LLD 1993 LLD LLD LLD 1994 LLD LLD LLD 1995 LLD LLD LLD 1996 LLD LLD LLD Results in pCi/m' (1) Locations Di off-site, D2 off-site, E off-site, F off-site, and O off-site used for 1976 - 1984. I.mcation R-5 off-site used for 1985 - 1996. ,
4
-136-
TABLE 36 IIISTORICAL ENVIRONMENTAL SAMPLE DATA AIR RADIOIODINE ONDICA'IUR) m IODINE-131 YEAR MIN, . MAX. MEAN 1976 0.01 2.09 0.33 1977 0.02 0.73 0.31 1978 0.02 0.07 0.04 1979 LLD LLD LLD 1980 0.013 0.013 0.013 1981 0.016 0.042 0.029 1982 0.002 0.042 0.016 1083 0.022 0.035 0.028 1984 LLD LLD LLD 1985 LLD LLD LLD 1986 0.023 0.360 0.119 1987 0.011 0.018 0.014 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD LLD 1993 LLD LLD LLD 1994 LLD LLD LLD 1995 LLD LLD LLD 1996 LLD LLD iin Results in pCi/m' (1) Locations used for 1976 - 1984 were Di 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 - 1996 were R1 off-site, R-2 off-site, R-3 off-site, and R-4 off-site.
-137-
TABLE 37 i
HISTORICAL ENVIRONMENTAL SAMPLE DATA !
MILK (CONTROL)
YEAR MIN. - MAX. J MEAN'l iMIN. MAX. iMEAN- .
1976 (1) (1) (1) (1) (1) (1) ,
1977 (1) (1) (1) (1) (1) (1) ;
1978 2.4 7.8 5.8 LLD 11D LLD !
1979 LLD LLD I1D LLD LLD 11D 1980 3.6 5.6 4.5 1.4 1.4 1.4 1981 3.9 3.9 3.9 LLD IlD LLD s 1982 LLD 11D LLD I1D LLD LLD 1983 LLD LLD I1D LLD IlD LLD I 1984 LLD 11D LLD LLD LLD LLD 1985 LLD LLD LLD LLD IlD LLD 1986 5.3 12.4 8.4 0.8 29.0 13.6 l 1987 LLD LLD LLD LLD LLD LLD .
1988 LLD LLD LLD 11D llE LLD I
1989 LLD I1D LLD LLD LLD LLD 1990 LLD 11D LLD LLD LLD LLD ;
1991 LLD LLD LLD LLD LLD LLD i 11D 11D LLD 1992 LLD I1D LLD 1993 LLD LLD 11D LLD LLD LLD 1994 LLD LLD LLD LLD 11D LLD I 1995 LLD LLD LLD 11D 11D LLD !
1996 LLD LLD LLD LID LLD 11D i
Results in pCi/ liter (1) No data available (seinples not required).
(2) location used was an available milk sarnple location in a least prevalent wind direction greater than ten smiles front the site.
t t
-138-i
TACLE 38 HISTORICAL ENVIRONMENTAL SAMPLE DATA MILK (INDICATOR)
YEAR MIN. MAX. MEAN 1 MIN. : MAX. MEAN 1976 4.0 15.0 9.3 0.02 45.00 3.20 1M7 11.0 22.0 17.1 0.01 49.00 6.88 1978 3.4 33.0 9.9 0.19 0.19 0.19 1979 3.2 53.0 9.4 LLD LLD LLD 1980 3.2 21.0 8.1 0.3 8.8 3.8 1981 3.5 29.0 8.6 LLD LLD LLD 1982 3.5 14.0 5.7 LLD LLD LLD 1;83 3.3 10.9 7.2 LLD LLD LLD 1984 LLD LLD LLD LLD LLD LLD 1985 LLD LLD LLD LLD LLD LLD 1986 6.1 11.I 8.6 0.3 30.0 5.2 1987 5.5 8.1 6.8 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 1992 LLD LLD LLD LLD LLD LLD 1993 LLD LLD LLD LLD LLD LLD 1994 LLD LLD LLD LLD LLD LLD 1995 LLD LLD LLD LLD LLD LLD 1996 LLD LLD LLD LLD LLD 11D Results in pCa. :..a (1) locations sampled were available downwind locations within ten miles with high radxxmclide deposition potential.
-139-M M M M -
M M
. - ~. ._. . _ ___ _ __
TAELG 39 HISTORICAL ENVIRONMENTAL SAMPIE DATA FOOD PRODUCTS (CONTROL)
- Cs-137 YEAR : MIN. : MAX / ' MEAN 1976 (1) (1) (1) 1977 (1) (I) (I) 1978 (1) (1) (1) 1979 (1) (1) (1) 0.02 0.02 0.02 1980 (3)
I?81 LLD LLD LLD 1982 LLD LLD LLD 1983 LLD LLD LLD 1984 LLD LLD LLD l
1;85 (4) LLD LLD LLD 1986 LLD LLD LLD 1987 LLD LLD LLD 1988 LLD LLD LLD 1989 LLD LLD LLD 1990 LLD LLD LLD 1991 LLD LLD LLD 1992 LLD LLD LLD 1993 0.007 0.007 0.007 1994 LLD LLD LLD 1995 LLD LLD LLD 1996 LLD LLD LLD Results in pCilg (wet)
(1) No data available (control samples not requiml).
(2) location was an available food product santple location in a least prevalent wind direction greater than ten miles from the site.
(3) Data comprised of broadleaf and non-broadleaf vegetation (1980 - 1984).
(4) Data comprised of broadleaf vegetation only (1985 - 1996).
-140-
_-. . . _ . . .=_.-. _..-..... - . . - - - _ . - . .. .-- - . . _.
TAELE 40 IIISTORICAL ENVIRONMENTAL SAMPLE DATA FOOD PRODUCTS (INDICA 1DR) m Cs-137 YEAR I MIN. : MAX. MN 1976 (2) LLD 1977 ED ED LLD LLD 1978 ED LLD ED 1979 0.004 ED 0.004 0.004 1980 0.004 0.060 0.036 1981 LLD LLD LLD 1982 LLD ED LLD 1983 LLD LLD LLD 1984 LLD LLD LLD 1985 (3) 0.047 0.047 1986 0.047 LLD LLD LLD 1987 LLD LLD LLD 1988 0.008 0.008 0.008 1989 -
0.009 0.009 0.009 1990 LLD LLD LLD 1991 0.040 0.040 0.040 1992 LLD LLD LLD 1993 LLD LLD LLD 1994 0.004 0.011 0.008 1995 0.010 0.012 0.011 1996 LLD IIn iin Results in pCilg (wet)
I (1) Indicator locations were available downwind locations within ten miles of the site and with high radionuclide deposition potential.
(2) Data comprised of broadleaf and non-broadleaf vegetation (1976 - 1984).
(3) Data comprised of broadleaf vegetation only (1985 - 1996).
g g g g g g M M M
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L -142-
5
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FIGURE 1 (
NEAREST RESIDENCE, FOOD PRODUCT, FISH AND SHORELINE SEDIMENT SAMPLE LOCATIONS KEY: ORESIDENCE-Nse tagg
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