ML20247A567
| ML20247A567 | |
| Person / Time | |
|---|---|
| Site: | Nine Mile Point  |
| Issue date: | 12/31/1997 |
| From: | NIAGARA MOHAWK POWER CORP. |
| To: | |
| References | |
| NUDOCS 9805060155 | |
| Download: ML20247A567 (170) | |
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- OPERATING REPORT!
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NINE MILE POINT NUCLEAR STATION
1 NIAGARA MOHAWK POWER CORPORATION
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ANNUAL RADIOLOGICAL ENVIRONMENTAL OPERATING REPORT January 1,1997 - December 31,1997 for NINE MILE POINT NUCLEAR STATION UNIT 1 Facility Operating License DPR-63 Docket Number 50-220 and NINE MILE POINT NUCLEAR STATION UNIT 2 Facility Operating License NPF-69 Docket.No. 50-410 {pDf
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' TARTE OF CONTENTS Page LIST OF TABLES ii LIST OF FIGURES vi 1.0. INTRODUCTION 1
' 2.0 AQUATIC SAMPLES 5 I. Shoreline Sediment 6.
II. Fish ,8-III. Surface Water 11 3.0 . DIRECT RADIATION 15 4.0 TERRESTRIAL SA14PLES . 22 I. Air Particulate / lodine 23 II. Milk 27 III. Food Products 31 IV. Land Use Census 34 5.0 ' INTERLABORATORY. COMPARISON PROGRAM 36
- 6.0 - HISTORICAL ENVIRONMENTAL SAMPLE DATA 43 7.0 CHA'NGES AND EXCEPTIONS TO THE PROGRAM 45
8.0 CONCLUSION
48 9.0 GENERAL REFERENCE MATERIAL 50 10.0 DATA TABLES - 1997 53 i
11.0 FIGURES 142
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LIST OF TABTE9 Table No. Content Eage Table 1 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program - Aquatic Program and Direct Radiation 54 Table 2 Sample Collection and Analysis, Site Radiological Environmental Monitoring Program - Terrestrial Program 55 Table 3 1997 Environmental Sample Locations 56 Table 4 Radiological Environmental Monitoring Program Annual Summary 60 Table 5A Concentration of Gamma Emittar., in Shoreline Sediment Samples (pCi/g-dry) 63 Table 5B Concentration of Gamma Emitters in Shoreline Sediment Samples (pCi/kg-dry) 64 Table 6A Concentration of Gamma Emitters in Fish Samples (pCi/g-wet) 65 Table 6B Concentration of Gamma Emitters in Fish Samples (pCi/kg-wet) 67 Table 7 Concentration of Gamma Emitters in Surface Water Samples (pCi/ liter) 69 Table 8 Concentration of Tritium in Surface Water Samples (pCi/ liter) 74 Table 9A Direct Radiation Measurement Results-mrem / Standard Month 75 Table 9B Direct Radiation Measurement Results-mrem / Quarterly Period 79 Table 10 Environmental Airborne Particulate Samples - Offsite Stations, Gross Beta Activity 83 Table 11 Environmental Airborne Particulate Samples - Onsite Stations, Gross Beta Activity , 85
.ii.
T 15;T OF TABT FS (Continued)
Table No. Content Pagg l
Table 12 Concentration of Gamma Emitters in Monthly Composites of NMP Air Particulate Samples 87 Table 13 Environmental Charcoal Cartridge Samples - Offsite Stations,I-131 Activity 102 Table 14 Environmental Charcoal Cartridge Samples - Onsite Stations,I-131 Activity 104 Table 15 Concentration of Gamma Emitters in Milk (pCi/ liter) 106 Table 16 Concentration of Iodine-131 in Milk (pCi/ liter) 109 Table 17A Concentration of Gamma Emitters in Food Products (pCi/g-wet) 110 Table 17B Concentration of Gamma Emitters in Food Products -
(pCi/kg-wet) 111 Table 18 Milk Animal Census 112 Table 19 1997 Residence Census 114 Table 20 Interlaboratory Comparison Program Results 115 Table 21 Historical Environmental Sample Data Shoreline Sediment (Control) 132 Table 22 Historical Environmental Sample Data Shoreline Sediment (Indicator) 133 Table 23 Historical Environmental Sample Data Fish (Control) 134 Table 24 Historical Environmental Sample Data Fish (Indicator) 135 Table 25 Historical Environmental Sample Data Surface Water (Control) 136 Table 26 Historical Environmental Sample Data Surface Water (Indicator) 137
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1 ET OF TART FR j (Continued)
Table No. Content pagg Table 27 Historical Environmental Sample Data Surface Water Tritium (Control) 138 1
l Table 28 Historical Environmental Sample Data Surface Water .
Tritium (Indicator) 139 f I
Table 29 Historical Environmental Sample Data Environmental 140 TLD (Control)
Table 30A Historical Environmental Sample Data Environmental TLD (Site Boundary) 141 ]
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Table 30B Historical Frironmental San ple Data i 142 i Environmental TLD (Off-Site Sectors) 4
, Table 30C Historical Environmental Sample Data Environmental TLD (Special Interest) 143 i Table 30D Historical Environmental Sample Data ,
Environmental TLD (On-Site Indicator) 144 Table 30E Historical Environmental Sample Data Environmental TLD (Off-Site Indicator) 145 Table 31 Historical Environmental Sample Data Air Particulate Gross Beta (Control) 146 Table 32 Historical Environmental Sample Data Air Particulate Gross Beta (Indicator) 147 j l
Table 33 . Historical Environmental Sample Data Air 148 Particulate (Control) -
Table 34 - Historical Environmental Sample Data Air i 149 l Particulate (Indicator)
Table 35 Historical Environmental Sample Data Air Radioiodine (Control) 150
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Table No. Content Eagt Table 36 Historical Environmental Sample Data Air -
Radioiodine (Indicator) 151 Table 37 Historical Environmental Sample Data Milk (Control) '152 i Table 38 Historical Environmental Sample Data Milk (Indicator) 153 l
I Table 39 Historical Environmental Sample Data Food Products (Control) 154 Table 40 Historical Environmental Sample Data Food Products (Indicator) 155 1
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IET OF FIGURFR Figure No. Cnntent Eagt Figure 1 Nearest Residence, Food Product, Fish and Shoreline Sediment Sample locations 157 Figure 2 Milk Animal Census, Milk Sample and Surface Water Sample Iacations 158 Figure 3 Off-site Environmental Stations and TLD Locations 159 Figure 4 On-site Environmental Station and TLD Locations 160 Figure 5 New York State Map 161 1
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10 MTRODUCTION 1-
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, Dwket No. 50-410 fer the Nine Mile Point Nuclear Station Unit 2 for the calendar year 1997.
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 EA Engineering Science and Technology (EA). This 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 performed jointly by the NMPNS and JAFNPP staffs.
The sample collection and analysis schedule required by the Technical Specifications for the Nine Mile Point Nuclear Station Unit 1 and 2 is listed in Tables 1 and 2.
The majority of REMP samples were analyzed by the Site (James A. FitzPatrick) Environmental Laboratory during 1997 and included the following analyses:
- Shoreline sediment (gamma spectral analysis)
- Fish (gamma spectral analysis)
- Lake water (monthly gamma spectral analysis only)
- Air particulate filter (weekly gross beta analysis)
- Air particulate filter (monthly gamma spectral analysis)
- . Airborne radioiodine cartridge (weekly gamma spectral analysis)
- Milk (gamma spectral and radioiodine analysis)
- Food products (gamma spectral analysis)
- Thermoluminescent dosimetry processing 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
1.0 INTRODUCTION
1997. Several radionuclides could possibly fallinto two of the four groups. The first of these groups is naturally occurring radionuclides. It must be realized that the environment contains a broad inventory of naturally occurring radioactive elements. Background radiation, as a function of primordial radioactive elements and cosmic 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 1997 contained naturally occurring radionuclides.
A second group of radionuclides that were detected are a result of the detonation of tthermonuclear devices in the earth's upper atmosphere. The detonation frequency during the early 1950's produced a significant inventory of radionuclides found in the lower atmosphere as well as in ecological systems. A ban was placed on atmospheric weapons testing in 1963 which greatly reduced the inventory through the decay of short lived radionuclides, deposition, and the removal (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 this test had influenced the background radiation in the viunity of the site and was very evident in many of the sample media analyzed during 1981. Calculatica from 1981 of the resulting doses to man from fallout related radionuclides in the environment show that the contribution from such 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-103,12-140, Cs-137, Mn-54 and Co-60 were also typical in air particulate samples during 1981 and have a weapons test origin. . During 1997, Cs-137 and H-3 were the only radionuclides detected in environmental samples thht 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 air particulate, air radioiodine and milk. Applicable radionuclides include I-131, Cs-134, Cs-137, Nb-95, Ru-103, Ru-106, and I.a-140. Cs-137 was the only radionuclides in this category that, combined with other sources of Cs-137, could have contributed to the total amount of Cs-137 detected during 1997.
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 1997, Cs-137,1-131, Zn-65, and H-3 were detected radionuclides that fall into this category.
'Ihe evaluation and interpretation of environmental data must be made at s3veral levels including trend analysis, dose to man, etc. An attempt has been made not only to report the data collected during 1997, but also to assess the significance of the radionuclides detected in the environment 1.0 INTRODUCTI/M as compared to natural radiation sources. 1997 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 significance 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 radionuclides in one sample and yet not in another because 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 operation of nuclear power facilities) is considered essentially negligible.
Background gamma radiation around the Nine Mile Point Site, as a result of radionuclides in the atmosphere and the ground, accounted for approximately 56 mrem during 1997. This dose is a resu? of radionuclides of cosmic origin (for example, Be-7), of a primordial origin (Ra-226, K-40, and Th-232) and, to a much smaller extent, of a man-made origin from weapons testing.
A dose, of 56 mrem, as a background dose, is significantly greater than any possible dose as a result of operations at the site during 1997.
Environmental Samnle Locations - Table 3 Table 3 contains the locations of the environmental samples presented in the data tables. The locations are given in degrees and distance from the Nine Mile Point Nuclear Sta. tion Unit 2 reactor centerline. Table 3 also gives the figure (map) number as well as the map designation for 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 1 and Section 6.9.1.7 of the Technical Specifications for the Nine Mile Point Nuclear Station Unit 2.
Radiological Environmental Monitoring Program Annual 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 Tcchnical Position (Revision 1 dated November 1979) to NRC Regulatory Guide 4.8 "Er.vironmental Technical Specifications for Nuclear Power Plants". The table is presented to meet the requirernents of Section 6.9.1.d and Section 6.9.1.7 of the Technical Specifications for Nine Mile Point Nuclear Station Unit 1 and Unit 2 respectively.
2.0 AQUATIC SAMPLFR 9
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l 2.0 AOUATIC SAMPI F.C t
I. SHORELINE SEDIMENT
!~ 'A. Ramnle Collection Methodology and Analysis Shoreline sediment 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.
l The area of potential recreational value is the only area from which samples are required by the Technical Specifications. Approximately one kilogram of shoreline
- sediment 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.
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 1997 at one off-site control location (near Oswego Harbor) and-at one indicator location (shoreline area with recreational value just east of the site).
The results of the shoreline sediment samples collected during 1997 at the indicator and controllocations are shown on Tables 5A and 5B. Table 5A shows results in i' units of pCi/g (dry) for purposes of data evaluation. Table SB 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 1997.
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 1997. K-40 is a naturally occurring primordial radionuclides. In addition to K-40, Ra-226 and AcTh-228 were also detected in' control and indicator samples and are also naturally occurring radionuclides.
s During 1997, 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 cch 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 wa'. not d< tected at the control location during 1997, however, it had been detecte.1 intermit tently in the j past (1979,1980,1982 and 1993). Detectable controllocation quantities have ranged from 0.03 to 0.22 pCi/g (dry).
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2.0 AOUATIC SAMPITR !
I. SHORELINE SEDIMENT (Cont'd) l l B. Evalimtion of Shoreline Sediment Data - Tables SA and SB (Cont'd) l The source of Cs-137 in 1997 indicator shoreline sediment samples is difficult to l determine. Possible sources are fallout from past weapons tests or from site I 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 control samples which are comparable to the physical l and chemical characteristics of the indicator samples. Other factors, which include changing lake level and shoreline erosion, further complicate any consistency in I shoreline sediment sampling. Soil samples in areas which are likely to be affected by plant operations, as well as soil beyond any influence from the site, all contain I levels of Cs-137 at or greater than the concentration.found in 1997 shoreline sediment. Cs-137 in soil samples has been attributed to weapons testing fallout.
The indicator location, unlike the control location, is very close to eroding ground areas and is believed to contain soil residues. Therefore, any shoreline sediment sample containmg soil would reveal Cs-137. These factors support the likelihood 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 methodology, and conservatively assuming that the maximum exposed individual (adult or teenager) would spend approximately 67 hours7.75463e-4 days <br />0.0186 hours <br />1.107804e-4 weeks <br />2.54935e-5 months <br /> 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 sida. These doses are very small when compared to average annual whole body doser, due to natural background and may be considered insignificant. For the purpo.4 of comparison, soil sampled at a location beyond any influence of the site contained Cs-137 at a concentration of 0.45 pCi/g. Using the same methodology and assumptions for 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 s'ioreline area is !
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.
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2.0 AOUATIC SAMPITR II. FISH A. Samnie Collection 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 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 the species in question at all three locations.
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. Evaluntion of Fish Data - Tables 6A and 6B
. A total of twenty-six fish samples were analyzed as a result of collections in the spring season (June 1997) and in the fall season (September 1997). Collections were made utilizing gill nets at one location greater than five miles from the site (Oswego Harbor area), and at two locations in the vicinity of the lake discharges for the Nine Mile Point Unit #1 (02), and the James A. FitzPatrick (03) generating facilities. The Oswego Harbor samples (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 purposes of data evaluation. . Table 6B shows results in units of pCi/kg (wet), as required by tite Technical Specifications.
Spring fish sample collections were comprised of five separate species and fifteen individual samples. Brown trout, white sucker, lake trout, small mouth bass and walleye were collected at the indicator locations (NMP and JAF) and at the control location (Oswego Harbor).
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2.0 AOUATIC SAMPLFR ]
L II. FISH (Cont'd) l .
l B. - Evaluntinn of Fish Data - Tables 6A and 6B (Cont'd) i-Cs-137 was detected in three a the fifteen fish samples collected during the spring.
One sample of small mouth bass collected at the Nine Mile Point location revealed detectable Cs-137 at a concentration of 0.015 pCi/g (wet). At the control location, j
- Cs-137 was detected in small mouth bass of a concentration of 0.019 pCi/g (wet) and also in a sample of walleye at a concentration of 0.043 pCi/g (wet). Cs-137 l
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 occurring radionuclides and is not related to power plant operations., Ra-226, also naturally occurring, was detected intermittently in both indicator and control samples. No other radionuclides were detected in the spring fish samples.
Fall fish sample collections were comprised of four separate species and eleven individual samples. Brown trout, small mouth bass, walleye, and chinook salmon sample: were collected at indicator sampling locations (NMP and JAF) and at the control location.
Cs-137 was detected in one of the seven indicator samples of walleye at a concentration of 0.017 pCi/g (wet). Cs-137 was not detected in any other control or indicator samples of fish collected during the fall of 1997.
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 1997 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 and 1997.
Control sample results have also decreased from a level of 1.2 pCi/g (wet) in 1976 to a level of 0.016 pCi/g (wet) in 1995. Results from 1980 to 1986 have shown a fairly consistent' decreasing trend for control and indicator samples. During 1987 through 1994, contro and indicator mean results increased slightly when compared to 1986.
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2.0 AOUATIC SAMPLES II. FISH (Cont'd) -
B. Evahmtion of Fish Data - Tables 6A and 6B (Cont'd)
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 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 mlative 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 mean results increased slightly.
Tables 23 and 24 show historical environmental sample data for fis.h.
Lake Ontario fish are considered an important food source by many. Therefore, fish are an integral part of the human food chain. Based on the importance of fish 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 group) and the fish consumed contains an average Cs-137 concentration of 0.016 pCi/g (wet) (annual mean result of indicator samples for 1997), the adult whole body dose received would be 0.024 mrem per year. The critical organ, in this case, is the teen liver which would receive a calculated dose of 0.038 mrem per year. The Cs-137 whole body and critical organ doses are conservative calculated doses associated with consuming fish from the Nine Mile Point area (indicator samples). No radiological decay is assumed for the calculation of doses.
Conservative whole body and critical organ doses can be calculated for the consumption of fish fmm the controllocation as well. In'this case the consumption rate is assumed to remain the same (21 kg per year for an adult and 16 kg per year for a teen), but the average annual Cs-137 concentration for the control samples is 0.031 pCi/g (wet). The calculated Cs-137 adult whole body dose is 0.046 mrem per year and the associated dose to the teen liver is 0.074 mrem per year. In this case, the fish from the control location resulted in doses which were slightly i I
. greater than that from the indicator locations (near the nuclear facilities). The control locatiori is located beyond any influence of the site.
1
2.0 AOUATIC SAMPLFR l .
II. 19SH (Cont'd) l l
- B. Evaluntion of Fish Data - Tables 6A and 6B (Cont'd) l 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 samples during 1995. Doses from both sample groups are considered background doses and negligible.
III. SURFACE WATER A. Sample Collection Methodology and Analysis Surface water samples are taken from the respective inlet canals of the J.A.
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 1 and 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 controllocation because of the distance from the site as -
well as the result of the lake current pattems and current patterns from the Oswego River located nearby (see Figure 2).
Samples from the FitzPatrick facility are composited from automatic sampling equipment which discharges into a compositing tank. Samples are obtained from 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 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 qt.arterly composite samples for each calendar quarter. Quarterly composite samples are analyzed for tritium.
l 2.0 AOUATIC SAMPTTR l
l III. SURFACE WATER (Cont'd)
A. Samnle Collection Methodology 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 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 ;
shown on Figure 2 (refer to Table 3 for location designations and descriptions). !
Sampling for ground water and drinking water, as found in Section 3.12.1 of the I Nine Mile Point Unit 2 Technical Specifications, was not required during 1997 because these pathways were not applicable to the Site during the year. Applicable sampling requirements and conditions are presented in the Unit 2 Off-Site Dose Calculation Manual.
Gamma spectral analysis results for the 1997 surface water samples showed no evidence of plant related radionuclides buildup in the surface water in the vicinity j of the site. Indicator samples were collected from the inlet canal at the James A. ;
FitzPatrick facility. The control location samples were collected at the inDt 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 also revealed no plant-related nuclides. Tables 7 and 8 show the results of all surface water samples analyzed during 1997. Only naturally occurring radionuclides were detected in samples from the five locations over the course of 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 radionuclides was detected only once at the control location during 1979 at a concentration of 2.S pCi/ liter. Cs-137 at the indicator location (JAF inlet canal) was detected only once during 1982 at a concentration of 0.43 pCi/ liter. The 1979 control sample result is suspect and may have been a result of contamination during handling or instrument background since Cs-137 was not detected in the indicator inlet canal. The one result from the indicator location (JAF inlet canal) during 1982 was detected in a January composite sample and may have been a result of inlet canal tempering (the addition of discharge water to the inlet canal) or instrument background. Cs-137 was not detected during 1997 in surface water samples.
2.0 AQUATIC SAMPLFS III. SURFACE WATER (Cont'd)
A. Sample Collection Methodology and Analysis (Cont'd)
Other plant related radionuclides detected during a review period of 1979 - 1997 include only Co-60. The control sample location results showed that Co-60 was detected once in 1981 (the May composite sample). This result is suspect and, as noted above, may be 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 pCi/ liter. These positive results were attributed to inlet canal tempering and instrument background. Co-60 was not detected during 1997 in surface water samples.
Table 25 and 26 show historical environmental sample data for. surface water using gamma spectral analysis.
Tritium samples are quarterly samples that are a composite of the appropriate calendar months. Tritium results are presented on Table 8. Tritium was detected in one calendar quarter at each of the indicator sampling locations. At the NMP1 inlet location, tritium was detected at a concentration of 320 pCi/1. During the third quarter of 1997, tritium was detected at the NMP2 inlet location at a concentration of 470 pCi/1. Tritium was detected at the JAF in%t location (Technical Specification indicator) at a concentration of 160 pCi/1. Tritium was not detected at any other location (indicator or control) during 1997.
Tritium has been detected in the past and has been attributed to background activity as a result of past weapons testing fallout. The impact of tritium in water to members of the public is minimal. This can be evaluated by calculeing an annual dose to the whole body and maximum organ. Using Regulatory Guide 1.109 methodology, ingestion of water from the Nine Mile Point Unit 2 inlet location would res it la an annual dose of 0.049 mrem to the whole body and 0.049 mrem to the chtid liver. This calculated dose is insignificant and a result of background concentrations of tritium in water.
Previous annual mean results for tritium at the indicator sample location (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
2.0 AOUATIC SAMPI FR III. SURFACE WATER (Cont'd)
A. Rnmnle Cn11ertinn Methndnlor.v and Annivsis (Cont'd) obtained, however, by review of previous data from the City of Oswego drinking water samples. The drinking water samples are not likely to be affected by the l station because of the effects of the distance, lake currents, and the discharge of the Oswego River. Therefore, this previous sample data represents acceptable control sample data for evaluation purposes.
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. Tritium was not detected at this location during 1996 or 1997.
Tables 27 and 28 show historical environmental sample data for surface water tritium.
3.0 DIRECT RADIA'ITON l
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l 3.0 DIRECT RADIATION A. Knmnie collection Methodolorv and Annivsis 1
Thermoluminescent dosimeters (TLD's) are used to measure direct radiation (gamma dose)in the environment. TLD's are processed at the Site Environmental Laboratory on a quarterly basis. Control TLD's accompany the TLD's when they are being placed or collected and are shielded by lead when they are not being used. TLD data results are corrected by use of the data from the control TLD's.
Five different types of areas are evaluated by environmental TLD's. These areas include on-site areas (areas within the site boundary not required by the 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 l 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 1997 were Panasonic UD-814 dosimeters. These were placed in polyethylene packages to ensure dosimeter integrity. TLD packages were placed in open webbed plastic holders and were attached to supporting structures; usually trees or utility poles.
I Environmental TLD locations are shown on Figures 3 and 4 (refer to Table 3 for location designations and descriptions).
l B. Evaluntion of TLD Data - Tables 9A and 9B TLD's were collected and read once per quarter during the 1997 sample year. The TLD results are reported in mrem per standard month (Table 9A) and in mrem per i 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 1997, TLD's were primarily collected during the weeks of April 2,1997, July 1,1997, October 4,1997, and January 2,1998. l Overall TLD results are evaluated by organizing environmental TLD's into five I different groups. These groups include: (1) on-site TLD's (TLD's within the site ,
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3.0 DIRECT RADIATION B. Evaluntion of TLD Data - Tables 9A and 9B (Cont'd) boundary not required by the Technical 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 die TLD locations required by the Technical Specifications during 1997 were ir.itiated in 1985 as a result of the issuance of new Technical Specifications by the NRC. Therefore, these TLD results can only be compared to 1985 - 1996 results. Other TLDs, which include a few TLDs requited by the Technical Specifications (i.e., numbers 7,14,15,18, 23, 49, 56, and 58) and other optional TLDs, can be compared to results prior to 1985 since these TLDs were established ,,
prior to 1985.
On-si:e 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 generating 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. The 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 3.5 to 28.8 mrem per standard month during 1997 and up to six times control TLD resii!!:;.
Other on-site TLD's include special interest TLD's located near the shorelino 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 1997 were variable and ranged from 6.8 to 59.8 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 1997 are consistent with the ranges of variability noted in 1996 for TLD's at or near these locations. TLD's in this group ranged up to approximately thirteen 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
3.0 DIRECT RADIATION B. Evaluation of TLD Data - Tables 9A and 9B (Cont'd) i 107. TLD's 103,106 and 107 are located to the cast of the Energy Center and to the west of the Unit 1 facility. TLD number 18 is located on the west side of the Energy Center. Results during 1997 showed these TLD's ranged from 4.3 to 6.1 mrem per standard month and were consistent with the 1996 results.
Site boundary TLD's are required by the Technical Specifications and are located in the approximate 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, l
82, 83, and 84 showed results that were consistent with control TLD results and l ranged from 3.5 to 5.9 mrem per standard month. Site boundary TLD's during 1997'were consistent with 1985-1996 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. These results ranged from 5.3 to 10.2 mrem per standard month. This latter group of TLD's are located near the lake shoreline (approximately 100 feet from the shoreline), but are also located in close proximity of the reactor building and radwaste facilities of Unit 1 and Unit 2 and the radwaste facilities of the FitzPatrick facility. l A net site boundary dose can be estimated from available TLD results and control TLD results. TLD results from TLD's located near the site boundary in sectors !
facing the land occupied by members of the public (excluding TLD's near the generating facilities and facing Lake 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 mrem per standard month are as follows:
Quarter Net Site Boundarv Dose
- 1 + 0.0 2 -0.2 3 + 0.2 4 + 0.0 1
- 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 areas are near the north shoreline which are in close pmximity to the generating facilities l
and are not accessible to members of the public.
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f 3.0 DIRECT RADIATION
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B. Evaluation of TfD Data - Tables 9A and 9B (Cont'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 Spe.:ifications. At this distance, eight of the sixteen meteorological sectors are located over lake Ontario. Results for this .
group of TLD's during 1997 fluctuated slightly as a result of changing naturally l occurring conditions and the different concentrations of naturally occurring radionuclides in the ground at each of the locations. 'Ihese TLD's were established in 1985 and include numbers 88,89,90,91,92,93,94 and 95. Results ranged fmm 3.5 to 5.8 mrem per standard month. These results are generally consistent
( consistent with the 1985 - 1996 results. Results were also consistent with other
- l. off-site TLD results during 1996 and previous to 1997.
The fourth group of environmental TLD's are those TLD's located near the site 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, l and the off-site environmentallaboratory. Many of these TLDs are required by the l Technical Specifications. Others are optional. This group of TLD's include
! numbers 9, 10, 11, 12, 13, 15, 19, 51, 52, 53, 54, 55, 56, 58, 96, 97, 98, 99, 100,101,102,108 and 109. TLD numbers 108 and 109 are TLD locations that were established to assist in the evaluation of the critical residence. Results ranged from 3.5 to 5.5 mrem per standard month. All the TLD results from this group were within the general variation noted for the control TLD's. Results during 1997 for TLD's established during previous years were consistent with results noted for those years.
The fifth group of TLD's include those TLD's considered as control TLD's. These L
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 1997 ranged from 3.7 to 6.2 mrem per standard month. Results from 1997 were consistent with L previous years results. However, an annual average increase was noted in 1986.
'Ihis increase may have been a result of the Chernobyl Nuclear Plant accident and was not noted during 1987-1997.
Review of past TLD results reauired by the Technical 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 3.0 DIRECT RADIATION i
l B. Evaluatinn of TID Datn - Tables 9A and 9B (Cont'd) special interest areas (6 TLDs total) and TLDs located 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 Specification TLDs located at the site boundary averaged 6.2 mrem per standard month during 1985. During the period of 1986 - 1996 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 pmximity to the generating facilities. An increase was noted during 1986 although such an increase was noted for all TLDs including control TLDs During 1997, site boundary TLDs averaged 5.9 mrem per standard month.
Technical Specification TLDs located 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 standard month during 1985. During the period of 1986 - 1996 off-site sector TLDs ranged from 4.1 - 6.0 mrem per standard month. The 1986 results demonstrated an increase for this group of TLDs. Results for 1997 for the group averaged 4.5 mrem per standt.rd month. This is consistent with previous year's l results. 1 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 Itceptor 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 - 1996 these TLDs averaged l between 4.0 - 5.3 arem per standard month. 1997 results for these locations averaged 4.5 mrem pr 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. !
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 l have been a result of the Chernobyl Nuclear Plant accident. Results for 1987 -
1996 ranged from 3.9 - 5.4 mrem per standard month. Results for 1997 averaged 4.6 mrem per standard month.
3.0 DIRECT RADIATION B. Evaluation of TLD Data - Tables 9A and 9B (Cont'd)
Tables 29 and 30A-30E show the historical environmental sample data for environmental TLD's.
During 1997, all environmental TLD groups required by the Technical Specifications were generally consistent with the results observed during 1996.
Overall, environmental TLD results for 1997 showed no significant impact from direct radiation measured outside the site boundary.
n----- - - - - --- - - - - - - - - - - - -- - - -- - - - ----- - - - - - - - -- -------- - - - - - - - - - - - - - - - , --- - - - - - - - - - - --, ---- - - - - - - - - - - - - - - - - - - - -
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DD2 SAMPIAq l
4.0 TERRESTRIAL SAMPLES I.- AIR PARTICULATE / IODINE A. Ramnie Cn11ertion and Methndningy 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 l calculated meteorological deposition factors (D/Q) based on historical j meteorological data. These stations (R-1, R-2, and R-3) are located in the east, east-southeast, and southeast sectors as measured from the center of the Nine Mile Point Nuclear Station Unit 2 reactor building. The Technical Specifications also require that a fourth air sampling station be located in the vicinity of a year round l community having the highest calculated deposition factor (D/Q) based on historical meteorological data. 'Ihis 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 ]
control location. l In addition to the Technical Specification 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 occupied by the three generating facilities, but are well within the site boundary. One other air sampling station is located off-site in the southwest sector and is in the vicinity of the City of Oswego. Three remaining air sampling stations (D2, E and F) are located in the east-southeast, south-southeast and south sectors and range in distance from 7.2 to 9.0 miles.
At each station, u. borne particulate are collected by glass fiber filters and radioiodine by charcoal filters. Air particulate glass fiber filters are approximately two inches (47 millimeters) in diameter and are placed in sample holders in the i intake line of a vacuum sampler. Directly down stream from the particulate filter l is a 2 x 1 inch charcoal cartridge used to adsorb airborne radioiodine. The samplers run continuously and the charcoal cartridges and particulate filters are l 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 radiciodine by GeLi detector.
The 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. Evaluatinn of Air Partieninte Gross Beta - 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
= _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ _ - _ _ _ _ - _ _ _ _ _ _ _ --
i 4.0 TERRESTRIAL SAMPLES I. AIR PARTICULATE / IODINE (Cont'd)
B. Evaluation of Air Particiilate Gross Beta - Tables 10 and 11 (Cont'd) l sample locations. Five of the nine off-site locations are required by the Technical Specifications. These sample locations are R-1, R-2, R-3, R-4 (all located near the site boundary) and R-5 (located at a control location beyond any significant influence from the site). Data contained on Tables 10 and 11 also shows the results from other air sampling locations not required by the Technical Specifications.
These locations are designated 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 indicator samples from locations R-1, R-2, R-3, and R-4 were collected and analyzed during 1997.
The minimum, maximum, and average gross beta results for sample locations required by the Technical Specifications are presented below.
Locatinn** Minimum
- Maximum
- Aygrggg*
R-1 0.004 0.017 0.011 R-2 0.003 0.017 0.009 R-3 0.001 0.016 0.008 R-4 0.004 0.018 0.012 R-5 (control) 0.006 0.025 0.013
- - Concentration in pCi/m'
- - Locations 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 concentration of naturally occurring radionuclides in the lower limits of the atmosphere directly above land areas are affected by processes such as wind direction, snow cover, soil 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 paniculate 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 controllocation, the gross beta concentration during 1977 to 1987 fluctuated with the detonation of thermonuclear weapons.
4.0 TERRESTRIAL SAMPLFR I. AIR PARTICULATE / IODINE (Cont'd)
B. Evaluntion of Air Partien1nte Gross Beta - Tables 10 and 11 (Cont'd)
Tables 31 and 32 show historical environmental sample data for air particulate gross beta levels.
C. Evninntion of Monthly Air Particuinte Comnotites - Table 12 Weekly air particulate samples were composited by location to form monthly 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 on-site, J on-site, K on-site, D2 off-site, E off-site, F off-site and G off-site locations. The results of all monthly composite samples are included on Table 12.
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 occurring. Be-7 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 1,y the Technical Specifications. Ra-226 was also detected intermittently in both indicator and control samples. No other plant-related radionuclides were detected at Technical Specification or optional locations using gamma spectral analysis during 1997.
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 samples averaged 0.0172 pCi/m3 . A decrease was observed until 1985 when no Co-60 was detected. From the period 1985-1997, no Co-60 was detected in control samples. Co-60 concentrations in indicator samples have shown a similar decrease. In 1977, the average concentration of Co-60 in indicator samples was 0.0179 pCi/m'. By 1982, this value had decreased to 0.0005 pCi/m . Slight increases were observed in 1983 and 1984, but these anomalies were due to contamination during handling of the unused samples and not due to plant operations (this has been previously documented in the 1984 annual report). Since 1984, no C&60 has been detected in any Technical Specification indicator location.
Historically, the presence of Cs-137 has been variable and has been present in air 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 steadily decreasing. The decreasing concentrations of Cs-137 are due to ecological cycling and nuclear decay of Cs-137 which was produced during
4.0 TERRESTRIAL SAMPLES I. AIR PARTICULATE / IODINE (Cont'd) l C. Evahiation of Monthly Air Partieninte Comnonitet - Table 12 l (Cont'd) weapons testing. 1978 concentrations of Cs-137 in control and indicator locations 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 that year for indicator and control samples were 0.0183 and 0.0193 pCi/m' respectively. During the period of 1987-1997 Cs-137 was not detected at any indicator or controllocation.
Prior to 1984, several radionuclides were detected that were associated with the 1980 Chinese weapons test and other weapons tests prior to 1980. These 1 radionuclides were not detected after 1983 as a result of nuclear decay and ecological cycling. These include Zr-95, Ce-141, Nb-95, Ce-144, Mn-54, Ru-103, Ru-106 and Ba-140.
During 1986, however, several fission product radionuclides were detected that 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 1996, none of the radionucli6es associated with the 1986 Chernobyl accident or past weapons testing were detected in air particulate samples.
During 1997, no radionuclides were detected in monthly air particulate composite samples that could have been attributed to plant operations. Therefore, no dose calculations were performed.
Tables 33 and 34 show historical environmental sample data for air particulate composites.
D. Evaluation of Airborne Radioindine - Tables 13 and 14 i
During the 1997 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 0.007 - 0.019 pCi/m'. The l indicator locations ranged from less than 0.005 to 0.021 pCi/m'. I-131 was also not detected at any of the optional monitoring locations (not required by the Technical Specifications) during 1997. Since I-131 was not detected at any of the indicator or control locations during 1997, no dose calculations are presented.
4.0 TERRESTRIAL SAMPIJ9 I. AIR PARTICULATE / IODINE (Cont'd)
D. Evaluation of Airborne RMiniodine - Tables 13 and 14 (Cont'd)
I-131 has been detected in the past at control and indicator locations and was attributed to past weapons testing, the Chernohyl accident, and, to a lesser exter.t, plant operations. For example, during 1986, I-131 was detected at the control and indicator locations. This was a result of the 1986 Chernobyl Nuclear Plant accident. The I-131 mean wncentration at the control location was 0.151 pCi/m' and 0.119 at the indicator '.ocations.1-131 was not detected at the control location during the period 1987 farough 1997.
Prior to the Chernobyl accident of 1986, I-131 had been detected intermittently during the years of 1976-1985. Concentrations ranged from 0.013 to 0.33 pCi/m' at indicator locatiens. 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 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 result of site operations.
Tables 35 and 36 show the historical environmental sample data for airbcrne radiciodine.
II. MILK A. Sample Collection Methodology and Analysis Milk samples are collected in polyethylene bottles from a bulk storage tank at each sampled farm. Before the sample is drawn, the tank contents are agitated from three to five minutes to assure a homogenous mixture of milk and butterfat. Two gallons are collected during the first half and second half of each month from each of the selected locations within ten miles of the site and from a control location.
The samples are chilled, preserved with sodium bisulfite, and then shipped to the analytical laboratory within thirty-six hours of collection in insulated shipping a containers. .
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 Specificaticans require three sample locations within 5.0 miles of the site with the highest calculated deposition
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4.0 TERRESTRIAL SAMPLES II. MILK (Cont'd)
A. Sampic Collectinn Methndniney and Analysis (Cont'd)
- factors. During 1997, 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 emitzrs and I-131. Samples are collected and analyzed in January - March in the event I-131 is detected in November and December of the preceding year.
The milk sample locations are found on Figure 2. (refer to Table 3 for location designation.s and descriptions).
B. Evaluntion of Vilk Data - Tables 15 and 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 1997. The Technical Specifications require that three locations be sampled for milk within 5.0 miles of the site. During 1997, there were no milk sample locations within 5.0 miles of the site. The locations that were s.mpled during 1997 are located from 7.8 to 9.5 miles from the site. The only sample location required by the Technical Specifications during 1997 was the control location.
During 1997, milk samples were collectec' at each of the four indicator locations and the control location in the first half and the second half of each month.
Samples were collected during the months of April through December 1997. One .
'optionallocation ceased operations following the September collectien. No data is available for that location for October through December 1997. Since I-131 was not datarted during November and December of 1997, no additional samples were collected in January through. March of 1997. 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 1997. K-40 was detected in all indicator and conttol samples. Ra-226
1 4.0 TERRESTRIAL SAMPLES II. MILK (Cont'd)
B. Evalmtinn of Mine Data - Tables 15 and 16 (Cont'd) occurred intermittently in milk samples. K-40 and Ra-226 are naturally occurring i radionuclides and are found in many of the environmental media sampled.
During 1997, 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 indicator (within 10 miles) and control locations (beyond 10 miles). Mean Cs-137 concentrations for 1976 -
1988 remained fairly consistent and ranged from 5.7 (1982) to 17.1 pCi/ liter (1977) at the indicator locations. No Cs-137 was detected in milk samples during 1989 through 1997.
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 from 3.9 - 5.8 pCi/ liter during this period. Results from 1986 showed a mean Cs-137 concentration of 8.4 pCi/ liter at the control location. The positive Cs-137 1 results during 1986 were a result of the Chernobyl Nuclear Plant accident. Cs-137 was not detected during 1987 through 1996 at the control location. Past Cs-137 in milk samples 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 I result of nuclear decay and ecological cycling.
No other radionuclides were detected in milk samples using gamma spectral i analysis.
Milk samples were collected and analyzed twice per month for I-131. During 1997, iodine-131 was detected during the week of April 21,1997 in one routine ,
indicator sample of milk at a' concentration of 0.50 pCi/1. The sample was recounted with results ranging from 0.30 to 0.55 pCi/1. A supplementary sample collected on April 25, 1997 revealed <0.30 pCi/l when analyzed at the site laboratory and 0.25 pCi/l when sent to vendor laboratory ~ I-131 was not detected i at this location during the previous collection (week of April 7,1997), nor at any l -
other milk sampling location.
1 Although the measured activity of I-131 was extremely low and less than the reportable concentration, an investigation into the possible source of the iodine was immediately initiated. This included identifying potential sources of iodine, reviewing the JAF, NMP1 and NMP2 effluent records, evaluating site i
4.0 TERRESTRIAL SAMPLES II. MILX (Cont'd) l B. Evninntinn of Milk Data - Tahlen 15 and 16 (Cont'd) l l'
meteorological data during the period and the collection and analysis of additional milk, forage, water, and feed.
In order to attribute the presence of iodine in the milk to plant operations, two conditions would have had to exist. One, the iodine concentration leaving the site l< as an effluent would have had to have been of sufficient quantity to reach the milk location (located approximately 9 miles east of the site) considering dilution and dispersion. Secondly, there had to exist a pathway from the site to the cow, i.e.
air / ground / water / feed. Neither of these conditions existed. Raced on an in-depth investigation, the source of iodine could not be identified.
Plant effluent data was reviewed from the NMP1 and NMP2 sites. 'No detectable
! iodine was released from either facility. A review of JAF records indicated that l the offgas system was taken out of service for a short period to support testing and that a small quantity ofI-131 was released. The site meteorologist confirmed that prevailing winds were in the direction of the sample location at that time. I However, discussions with the fctm owner indicated that the herd had not yet been l
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- on pasture (no pathway). Computer modeling done to estimate the quantity l
released from the plant utilizing several overly conservative assumptions regarding foraging estimates and dispersion coefficients do not support the concentration identified in the milk. The model calculated a concentration approximately 300 l times lower than measured.
An interview was conducted with the owner of the farm to evaluate operational l factors and other potential sources of the iodine. It was determined through
- conversations'with the farm owner that no farm personnel had recently been the
! recipient of any therapeutic or diagnostic treatments involving the use of iodine- l h 131. Additionally, the herd had only been fed stored feed for the previous six L
months and received no iodine supplements. Samples of stored feed and the
- animal's supply of water were collected and analyzed. ' No positive detections of L iodine were made in any of these samples.
Further, no iodine-131 was detected at any of the downwind air sr.mpling stations l- during 1997. These air sampling stations continually sample air and are analyzed weekly.for iodine. (See Section 4.0). Iodine-131 was not detected at any other milk sampling location during 1997, including location 50 which is located approximately 0.25 miles from location 55. Any possible plume originating from the nuclear site would have dispersed (or fanned out) enough at this distance to have affected both locations. -
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l 4.0 TERRESTRIAL SAMPLES II. MILK (Cont'd)
B. - Evalnntian of Milk Data - Tables 15 and 16 (Cont'd)
While the investigation concluded that the source of iodine could not be determined, it is highly unlikely the source of I-131 was from Nine Mile Point Unit 1, Nine Mile Point Unit 2, or James A. FitzPatrick.
The measured concentration of iodine in the milk was very small. Utilizing the methodology given in Regulatory Guide 1.109, a calculation was made to evaluate dose as a result of milk wmneian. An 18<iay consumption period was utilized, 0.50 pCi/l(+='he for 9 days and 0.25 pCi/1 utilized for the remaining 9 days.
The maximum calculated dose to the whole body and critical organ (thyroid) was l 0.085 mrem to the infant thyroid and 0.00011 mrem to the infant whole body.
Both doses are very small and insignificant in comparison to doses. received from natural sources. For example, the whole body dose of 0.00011 mrem is equivalent to moving to a location 100 meters (328 feet) higher in altitude and remaining there for less than one hour. An occurrence of moving to such a location is common.
Any dose received as a result of such activity is small and insignificant.
An evaluation of historical data for I-131 in milk samples shows that annual mean l results ranged from 0.19 pCi/ liter to 6.88 pCi/11ter at the indicator locations during l
1976 - 1980. 1-131 during these years is a result of intermittent weapons testing.
L Results from 19% showed that I-131 was detected at a mean concentration of 5.2 ;
pCi/ liter as a result of the Chernobyl accident. I-131 was not detected during the l I
period 1987 through 1996 in milk samples.
Historical data for I-131 from the control location showed that I-131 was detected during 1980 at a mean concentration of 1.4 pC!/ liter. During 1986, I-131 from the control location uhowed a mean concentration of 13.6 pCi/ liter as a result of the ;
Chernobyl accident.1-131 was not detected during the period 1987 through 1997 l at the controllocation.
l Tables 37 and 38 show the historical environmental sample data for milk.
l III. FOOD PRODUCTS A. Ramnte collection 14ethodology nnd Analysis Food products are collected once per year during the late summer at the approximate height of the harvest season. Approximately one kilogram of a broadleaf vegetable or other broadleaf vegetation is collected from garden locations with the highest deposition factors (D/Q) based on average historical l
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4.0 TERRESTRIAL SAMPLES III. FOOD PRODUCTS (Cont'd)
A. Samnie Collection Methodology and Analysis (Cont'd) meteorological data. Four indicator sample locations were utilized from at least two sectors. Additional samples may also be obtained. Control samples are also collected from 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 fresh as soon as possible after collection.
Food product samples are analyzed for gamma emitters (gamme 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. Exaluation of Food Product Data - Tables 17A and 17B Food product samples collected during 1997 were comprised of garden vegetables and other types of vegetation. Samples were collected from four 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 l locatior' was represented by a garden location 9-20 miles distant in a least prevalent wind direction. Garden vegetables were comprised of tomatoes, collard greens, and swiss chard, which are all (except tomatoes) considered broadleaf vegetables.
Other broadleaf vegetation consisted of 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 1997).
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 1997. K-40 was detected in.all samples of food products. Be-7, Ra-226 and AcTh-228 were detected intermittently in the vegetation samples. K-40, Be-7, Ra-226 and AcTh-228 are all naturally occurring radionuclides.
During 1997, two radionuclides were detected in two different food product media at two separate indicator locations which could have been attributable to operations at Nine Mile Point. Cs-137 was detected in one sample of cucumber leaves at location "J" at a concentration of 0.012 pCi/g (wet). Cs-137 has been 4.0 TERRFRTRIAL S AMPLFS III. FOOD PRODUCTS (Cont'd)
B. Evaluntion of Food Product Data - Tables 17A and 17B (Cont'd) intermittently detected in the past at both indicator and control locations. The source of Cs-137 is difficult to determine since Cs-137 is a product of both plant operations and past weapons testing. Cs-137 was not detected in any control samples during 1997.
2n-65 was also detected in one sample of pepper leaves at location "K" at a h concentration of 0.016 pCi/g (wet). 2n.65 can be attributed to operations at Nine Mile Point. Zn-65 was not detected in any other food product at this or any other location during 1997. Zn-65 has not been detected in past at any food product location. Additional samples of soil and leaves were collected at location "K" in order to verify the presence of Zn-65. No Zn-65 was detected in any of these samples.
The measured quantities of Cs-137 and Zn-65 in these food products is very small.
This can be shown by calculating a dose to a person who may have ingested food products from these locations. Utilizing Regulatory Guide 1.109 methodology, and the conservative assumptions that a person were to consume vegetation from both gardens, with no radiological decay; the resultant doses of 0.11 miem to the child liver and 0.062 mrem to the adult whole body were calculated. The significance of this dose can be compared to the increase in dose as a' result of an increase in altitude. As one proceeds from one location to another higher in altitude, the dose rate will increase slightly due to solar or cosmic radiation. A whole body dose of 0.062 mrem per year is equivalent to proceeding from an area 100 meters (328 feet) higher and remaining there for approximately 11 days. An occasion, such as moving to a location 100 meters higher in altitude is common.
Any dose that may be received as a result of such an occurrence is considert d small and insignificant.
A review of past environmental data indicates that Cs-137 has been detected intermittently during the years of 1976 - 1996 at the indicator locations and during the years of 1980 - 1996 at the control locations (control samples were not obtained prior to 1980). During the. period of 1977 - 1996, 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 1980-1996 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.
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n 4.0 TERRESTRIAL SIMPLES '
y
'N[ LAND USE CENSUS
- A. _ - Methadalaav
. 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 ndlk-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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The milk animal census is an estimation of the number of cows and goats within an approximate ten mile radius of the Nine Mile Point Site. A census is initiated -
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 ;
contactal by telephone or in person. The local agricultural agency was also
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contacted. l I
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 i u
residerce within three miles in each of the 22.5 degree meteorological sectors. A I
, . residence, for the purposes of this census, is a residence that is occupied on a part j 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 1997, 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
. distaree, some of the meteorological sectors are over water. These sectors include: 1 N, NNE, NE, ENE, W, WNW, NW, and NNW.
B. Evahmtian of Data'. Tables 18 and.12 D p i
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JIhe number of milk animals located within an approximate ten mile radius of the site was estimated to be 789 cows and 4 goats for the 1997 census. The number l
- of cows decreased by 209 and the number of goats decreased by 13 with respect L
to the .1996 census. No new milk locations were identified during the 1997 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.
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L 4.0 TERRFRTRI AL S AMPLFJ
'IV. LAND USE CENSUS B. Evalnntion of Data - Tables 18 and 19 (Cont'd) r The results of the 1997 residence census showing the applicable sectors and degrees and distance of each of the nearest residences are found on Table :9. The nearest residences are shown in Figure 1. No changes were noted in 1997.
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5.0 INTERI,ABORATORY COMPARISON PROGRAM
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! I 5.0 INTERLABORATORY COMPARISON PROGRAM I i
A. Deeriptim l Technical Specifications sections 3.6.21 and 3.12.3 for the Nine Mile Point !
Nuclear Station Unit 1 and Unit 2, respectively, require that a summary of the l results obtained as part of an Interlaboratory Comparison Program be included in l the Annual Radiological Environmental Operating Report. During 1997, this ]
program consisted - of utilizing Analytics commercial laboratory ' and the j Environmental Measurements Laboratory (EML) to supply required reference i samples. Both of these laboratories provide a program which is traceable to the I
National Institute of Standards and Technology (NIST).
During 1997, these laboratories supplied sample media as blind sample spikes I containing known levels of radioactivity. 'Ihe samples were prepared and analyzed by the site environmental laboratory utilizing standard laboratory procedures. The . j results were then submitted to the respective laboratory for statistical evaluation. ]
The Environmental Measurements Laboratory would then issue a report to the site j environmentallaboratory provismg an evaluation of performance. The Analytics l Laboratory provided a summary report to the environmental laboratory, from j which the environmentallaboratory would then evaluate performance utilizing the {
NRC and EPA methodologies. i 1
l Results from the 1997 program are provided in Table 20. l 1
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'l 5.0 INTERLABORATORY COMPARISON PROGRAM I
B. Results I
The following table summarizes the types of spiked, intercomparison samples received by Analytics and EML during 1997:
Me:lla Analysis Analvtics EML Iotal Water Gross Beta 0 2 2
' Water Tritium 1 2 3 Water I-131 2 0 2 Water Mixed Gamma 2 2 4 !
Air Gross Beta 2 2 4 Air I-131 2 0 2 Air Mixed Gamma 2 2 4 Milk I-131 2 0 2 Mi& Mixed Gamma 2 0 2 Soil Mixed Gamma 1 2 3 Vegetation Mixed Gamma 0 2 2 TOTAL SAMPLES 16 14 30
- 1. Analytics Resu]15 Results of the samples received by Analytics as part of the 1997 Interlaboratory Comparison Program are summarized on Table 20. The 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. Two separate methodologies were ]
utilized to evaluate the results.
The first method is bised on the calculation of the ratio of the vendor l
laboratory known value (reference result) and the results reported by the participating laboratory.
An environmental laboratory analytical result is considered Accentable when the following criteria is met:
5.0 INTERLABORATORY COMPARISON PROGRAM l B. Results (Cont'd) l The error resolution = Reference Result / Reference Error Reference Recult = within Ratio of Agreement for a calculated EIror QC Result Recnlution ERROR RESOLUTION RATIO OF AGREEMENT
<3 0.4 - 2.5 4-7 0.5 - 2.0 8 - 15 0.6 - 1.66 16 - 50 0.75 - 1.33 51 - 200 0.8 - 1.33
> 200 0.85 - 1.18 This acceptance test is generally referred to as the "NRC" method. The acceptance criteria is contained in Procedure DVP-04.01 and was taken from Criteria of Comparing Analytical Results (USNRC) and Bevington, P.R., Data Reduction and Error Analysis for the Physical Sciences, McGraw-Hill, New York, (1969). The NRC method generally results in an acceptance range of 25% of the Known Value. This method is used as the procedurally required assessment method and requires the generation of a nonconformity report when results are unacceptable.
In addition to the NRC acceptance criteria, the site Environmental Laboratory utilizes a second method for evaluating the Analytics interlaboratory comparison sample results. This method is based on the EPA results data base for historical cross-check sample results. A Normalized Deviation from the Known Value (NDKV) for each sample set was calculated based on historical EPA data. The site environmental laboratory results between -3 and 3 NDKV were considered to be acceptable.
The EPA method is used as a screening method and contains a more conservative range which results in an acceptance range of i 15 - 20% of the Known Value.
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5.0 INTERLABOFSRY COMPARISON PROGRAM B. Results (Cont'd)
Results which meet the NRC acceptance criteria but exceed the acceptable range calculated by the EPA method are considered acceptable by procedural requirement. Those sample results which exceed the EPA acceptance range are evaluated to ensure that potential or developing analytical problems are discovered and corrected in a timely manner.
The 12 spiked samples from _Analytics required 72 analyses. All results, except for a single gamma analysis of Zn-65 in soil were in agreement using the NRC acceptance criteria for 98.6% agreement ratio. The reported mean Zn-65 activity for analytics soil sample E1061-05 was 553 15 pCi/kg. The reference analytics results were reported as 422 7 pCi/kg. This resulteo in a sample ratio of 1.31 which is outside the agreement range of 0.8 - 1.25. The sample ratio of 1.31 demonstrates that the sample results are biased high. The results for th'e other eight radionuclides present in the soil sample were in agreement with the reference values. The Zn-65 was the single outlier for this sample result.
A review of the spectral data showed that the Zn-65 peak was identified at 1115 Kev. In soil samples, Ra-226 is a naturally occurring radionuclides which produces a peak at 1120 Kev. Each of the three sample spectrums showed that there existed some overlapping between the two peaks. In most cases the computer algorithm can differentiate the two peaks and correct for i~ interference from overlapping peaks. The peak shapes in this sample were complex and resulted in the computer making a conservative estimate of the total number of counts in the Zn-65 peak. The higher count rate calculated to a high concentration value for the Zn-65.
To determine if this was an inherent or a systematic error in the analysis system, a review was made of previous spiked soil quality assurance samples. In 1996, six soil samples were analyzed which contained Zn-65.
The mean ratio for these sample for these samples was 0.928. In 1997, six soil quality assurance samples were analyzed which contained Zn-65. The mean ratio for these samples relative to the reference value was 1.078. The overall mean ratio for these 12 samples was 1.00 relative to the reference value. The ratio of 1.00 is an excellent indicator that routine measurement of Zn-65 in soilis very accurate and precise and produces results that center around unity. These historical results demonstrate that there is ao systematic error or bias for the analysis of Zn-65 in soil. No corrective action was implemented.
5.0 INTERLABORATORY COMPARISON PROGRAM B. Results (Cont'd)
- 2. EML Results E Results of the samples provided by EML as part of the 1997 Interlaboratory Program are provided on Table 20. EML samples analyzed by the site environmentallaboratory were analyzed for gross beta, tritium and gamma emitting nuclides, as appropriate. Following analysis, results were 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:
Result Cumulative Normalized Distribution Acceptable 15 % - 85 % ,
Acceptable, with warning 5-15% or 85-95%
Not Acceptable <5% or >95%
Of the 36 analyses performed on the EML samples, two were found to be "Not Acceptable," twenty-five were found to be " Acceptable" and nine analyses were placed in the " Acceptable with Warning" category.
The analyses evaluated to be acceptable with warning or not acceptable were directly impacted by the differences in the sample characteristics between the EML samples and samples routinely analyzed at the site environmental lab. Each of these samples differed greatly in sample density and available volume. These two factors caused the sample results to be biased high due to the calibration geometry and sample geometry differences.
The results which were "Not Acceptable" were analyses for the Cs-137 and Co-60. The results can be directly attributed to the differences in the sample volume and matrix density relative to the site environmental laboratory vegetation calibration standard. The volume of sample provided is not sufficient to match the 300 cc volume required for the calibration geometry. In addition, the density of the sample (0.30 g/cc) and the calibration ma*rix (1.15 g/cc) are significantly different. These differences be. tween the EML samples are provided and the calibration geometry resulted in a bias in the reported results. The differences in the sample characteristics and the calibration standards are considered to be cause for observed nonconformities.
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5.0 INTERLABORATORY COMPARISON PROGRAM B. Results (Cont'd)
- 2. EML Results (Cont'd)
The corrective action to eliminate the results bias and nonconformities for soil and vegetation samples is to obtain additional sample volume from EML and to make mathematical corrections for differences in sample / standard densities. If additional sample volume cannot be obtained then additional mathematical corrections will be made for volume differences between the sample volume and the counting geometry.
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i 6.0 HISTORICAL ENVIRONMENTAL SAMPLE DATA I
t 6.0 HISTORICAL ENVIRONMENTAL SAMPLE DATA A. Deerintion
- Technical Specification requirements for the Annual Radiological Environmental i Operating Report require a comparison of data from the current reporting period 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 1997 results with previous years results. Data for all sample media is additionally provided in tabular form for each year on Tables 21-40.
Tables 21 - 40 show historical environmental sample data for critical radionuclides or radionuclides routinely detected in environmental sample media. Data show the minimum, maximum, and mean for each year evaluated. The data only consider detectable quantities and do not consider lower limit of detection (LLD) quantities.
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 detected radioactivity when compared with pre-operational and early operational data of the Nine Mile plants. The majority of radioactivity detected throughout the years has been attributed to weapons testing fallout and natural background 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 detected in environmental samples.
7.0 CHANGFS AND EXCErnONS TO THE PROGRAM 1
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7.0 CHANGES AND EXCEPTIONE'id THE PROGRAM A. Changes to the 1997 hmnle Program
- 1. Food product location P was added to the program during 1997. This location which was added due to its higher D/Q.
- 2. Food product locations L and S were not utilized by the sampling program f during 1997 because of the higher deposition potential of location P.
- 3. Milk sampling location (50) was not sampled from October through December as a result of the operations ceasing at this location.
B. Freeptions to the 1997 Samnle Program Exceptions to the 1997 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.
e Air radioiodine and particulate sampling required by the Technical Specifications
- 1. Environmental air sample equipment at R-1 and R-2 off-site sampling stations was found to be inoperable during the period 3/11/97 - 3/18/97 for approximately 5 hours5.787037e-5 days <br />0.00139 hours <br />8.267196e-6 weeks <br />1.9025e-6 months <br />. This downtime was due to a localized power outage.
- 2. During the period 10/27/97 and 10/28/97 a wide-spread power outage resulted in downtime at environmental air stations R-1 and R-2 for approximately 14 hours1.62037e-4 days <br />0.00389 hours <br />2.314815e-5 weeks <br />5.327e-6 months <br /> and at R-3 and R-4 'for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br />.
- 3. Environmental air sample equipment at R-1 and R-2 off-site stations was inoperable on for approximately 4 hours4.62963e-5 days <br />0.00111 hours <br />6.613757e-6 weeks <br />1.522e-6 months <br /> due to a localized power outage during the 11/25/97 - 12/2/97 collection period.
No other sample downtime was observed during 1997 for any Technical Specification required air radioiodine and particulate sampling locations. Other occurrences of downtime for optional air sampling stations were documented for 1997. However, these ,
occurrences were minimal and are not presented here because optional air sampling stations are not required by the Technical Specifications.
7.0 CHANGES AND EXCFETIONS TO THE PROGRAM C. Lower I imit of Detection for Environmental Samnles 1
'Ihe Technical Specifications require that environmental samples analyzed for the Radiological Environmental Monitoring Program meet the lower limits of detection j (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 1997 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. Deviations from the Inter 12boratory comnarison Program l 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. l During 1997, 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
CONCLUSION The Radiological Environmental Monitoring Program (REMP) was established to detect and evaluate any possible impact to the environment surrounding the Nine Mile Point area resulting from operations at the site.
Samples representing food sources consumed at higher trophic levels, such as fish and milk, were reviewed closely to evaluate any impact to the general environment or to man.
In addition, the data was reviewed for any possible historical trophic level bioaccumulation trends. Little or no impact could be determined resulting from radionuclides deposition considering 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 occurring sources (primordial and/or cosmic related). Whole body doses to man as a result of natural sources (naturally occurring radionuclides in the soil and lower atmosphere) in Oswego County account for approximately 56 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 1997, the presence of several operational related radionuclides were noted in sample media. These media included sediment, milk, water and fish samples. The impact, expressed as a dose to man, from these radionuclides 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 operations at the Nine Mile Point Nuclear Station was detected that would affect the health and safety of the public.
9.0 GENERAL REFERENCE MATERIAL
-~__
9.0 GENERAL REFERENCE MATERIAL 1
(
- 1. U.S. Nuclear Regulatory Commission Regulatory Guide li109, " Calculation of l'
Annual Doses to Man from Routine Releases of Reactor Effluents for the Purpose l- of Evaluating Compliance with 10 CFR Part 50, Appendix I", March 1976 l (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).
l
- 3. U.S. Nuclear Regulatory Commission Regulatory Guide 4.8, " Environmental Technical Specifications for Nuclear Power Plants", December,1975.
- 4. .U.S. Nuclear Regulatory Commission Branch Technical Position to Regulatory Guide 4.8, "An Acceptable Radiological Environmental Monitoring Program",
Revision 1, November 1979.
,. 5. National Council on Radiation Protection and Measurements (NCRP), l Environmental Rndintinn Menenrements, NCRP Report No. 50,1976.
~
l.
- 6. National Council on Radiation Protection and Measurements (NCRP), Natural Rackground Rndintion in the United Statec, NCRP Report No. 45,1975.
- 7. National Council on Radiation Protection and Measurements (NCRP), cesium-137 from the Environment to Man! MetAilicm and Dose, NCRP Report No. 52, 1977.
- 8. National Council on Radiation Protection and Measurements (NCRP), Radiation l
Ernnente from rnntumer Prndnetc and Miccellanenus Sourcec, NCRP Report No.
56,1977.
i l 9. International Commission on Radiological Protection (ICRP), Radionuclides Relence into the Environment Aueument of Doses to Man, ICRP Publication 29,1979.
- 10. Eichholz, G. Environmental Asnects of Nucient Power, First Edition, Ann Arbor Science Publishers, Inc.,- Ann Arbor, Michigan,1976.
- 11. Eisenbud, Merrill, Environmental Rndinnetivity, Second Edition, Academic Press, New York, NY 1973.
- 12. 'Ihomas, C.W. etc al., Rndinnetive Fallout from Chineca Nucient Wennons Test, September 26,1976. (BNWL-2164) Battelle, Pacific Northwest Laboratories, U.S. ERDA,1979.
i
_ - -_--_______-______a
9.0 GENERAL RFFERENCE MATERML
- 13. Pochin, Edward E., Fstimated Population Exnosure from Nucient Power Production and Other Radiation Sources, Nuclear Energy Agency, Organization for Economic Co-Operation and Development,1976.
- 14. Glasstone, Samuel and Jordan, Walter H., Nuclear Power and Its Environmental Effects, First Edition, American Nuclear Society, La Grange Park, Ill.,1980.
- 15. U.S. Department of Health, Education, and Welfare. Radiological Henith Handbook. Bureau of Radiological Health, Rockville, Maryland 20852. January 1970.
- 16. U.S. Department of Health and Human Services. Prepare 11 ness and Resnonse in J Radiation Accidents, National Center for Devices and Radiological Health, {
Rockville, Maryland 20857. August 1983. l l
National Council on Radiation Protection and Measurements (NCRP), Ioni71ng l 17.
Rndiation Ernosure of the Population of the United States, NCRP Report No. 93, 1987.
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- R N 43689 8930565 054 4 031 9 802332 A G O 1 1 1 1 1 00000 1 1 1 1 1 1 1 1 1 1 1 1 1 1 0 01 1 1 1 1 0000000 00000060 000000 L 0000000 00000000 000000 A G 00000 T
N E
M N
O E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 R T 00000 0000000 00000000 000000 I I 00000 0000000 00000000 000000 V S 00000 0000000 00000000 000000 N -
i t
- 11 *
- i
- 1 i
- i t 1**1 i*
- E N 60558 8540445 1 544031 9 6924 32 O 1 2 1 1 1 1 1 11 1 1 1 1 1 1 1 1 1 1 0 001 1 1 1 00000 0000000 00000000 000000 1 00000 0000000 00000000 000000 D
G N
I 77 7 7 7 77 77 7777 7 77 7 7 7 77 7 77 7 7 D E 99
/ / / 9 /999999999 99999999999 999
/ / / / / / /////////i//////
N T 6307 3085307411 27 01 4 11 8529 72 9 630 E A 01 2201 2301 2 2 01 1 2 001 2 3
//////////////////////////
1 I I I 2222 333334 4 4 4 555 566666 K D O0000000000000000000000000 E
E W .l
E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 T 00 000000000000000000 000000 S
I 00000000000000000000000000
_ S 000000o0000000000000000000 N - * + 11 i * + + i i
- i
- t
- 1 ii O N 2 060358762330S8684 07366071 I O 1 1 1 1 1 1 0 01 1 1 1 1 1 1 1 01 1 02 1 01 1 1 T 00000000000000000000 000000 A J 00000000000000000000000000
- T S
- E T
I S E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 A T 00000 0 00 0000000 00000000 000 NM O GI I
S 0000000.
00000*
t *
- i t 0000000000 0 0000000
- * * * * *
- t 00000000 000 000o0000 0o0 1
- i *** +i S N 02934 7 97 04 1 6281 1 48706376 003 O 1 1 1 1 1 00 2 1 1 1 1 1 2 1 01 1 02 1 0 1 2 1
)
d S 1 E I 0000000.0000000000 00000 0 0000000 00000000 000 00000000 000 e L i u P n M 3 m
- i E A /
t T S i n I E E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 CN T 00000000 0000000 1 1 1 1 1 1 1 1 1 1 1 0 000 0000 000 o S T pO I 00000000 0000000 0000 0000 0 00 c I S
( F A L A TA YT -
00000000 00o0000
- * + * + i +
- ti i i 00000000 000 i 1*
- 1** +
U N 21 6 1 6796 1 4 4 61 81 87 51 57 87 283 1 J IC O 1 I 1 1 1 1 00 2 1 1 1 1 I 2 1 01 1 02 1 0 1 1 1 1 / C VO 00000000 0000000 0000000 0 000 P I IL H 000 00000 0000000 00000000 000 M T T E N R C L A A P
B A
- A E T
- T N E E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 R B T 00000000 0000000 000000 0 00 O I 00000000 0000000 000000 0 00 B S S 00000000 0000000 000000 0 00 R S - 1+* * + * *
- i 11+1 i 1ii 1* i I O N 9841 9953 5544687 645558 6 85
_ A RG O 001 I 0000 0000000 0 00001 0 01 06000000 0000000 000000 0 00 L G 00000000 0000000 000000 0 00 A
T
- N E
M N E 1 1 1 1 1 1 1 1 1 1 1 1 1 1 1 O T 00 000000 0000000 1 1 1 1 1 1 1 1 1 1 1 0 0000000 000
- R I 00000000 0000000 00000000 000
_ I S 00000000 0000o00 00000000 000 V -
+ 1+
- 1i*i i1+1 i *
- 1 *
- 1 i i + i
_ N N
- 03693496 8424G69 67 30837 7 2 83 E O 1 1 1 01 1 00,1 1 1 1 I 1 1 1 01 1 02 1 0 1 1 1 00000000 0000000 00000000 000 1
_ D 00000000 0000000 00000000 000 G
N I
777 7 7 77 7 7 7 7 7 77 77 7 7 7 7 7 7 77 7 D 9999999999999999 9 N E / / / / / / / / / / / / / / / / / 8 9999 9 99 9
/ / / / / / / /
E T 7 4 1 84 1 852 852 9630 7 307 4 I 8 52 9 A 01 2 2 0l I 2 001 2 2 01 2 2 01 t 2 001 2 2
/// / / / / / / / / / / / / / / / / ///////
K D 7 7 7 7 8888 9 999900001 1 I 1 2 2 2 2 2 00000000000001 1 1 1 1 1 1 i 1 1 1 1 1 E
E W
TABLE 12.
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-1 OFF-SITE STATION
- Results in units of 19 'oCi/m' i 1 sigma 1
)
! NUCLIDES L JANUARY '. l FEBRUARY: . MARCH : APRIL 1 MAY = JUNE 1997 Co-60 <0.6 < 1.6 < 3.1 < 2.0 <2.2 < 2.9 Mn-54 < 0.8 < 1.3 < 2. 8 < 2.6 < 1.9 < 1.9 I Cs-134 < 0.7 <1.1 < 2.6 < 1.9 < 1.3 < 2.4 {
Cs-137 < 0.6 < 1.2 ' < 2.3 < 2.0 < 1.4 < 2.3 Nb-95 < 1.1 < 1.4 < 7.2 < 2.8 < 1.7 < 4.0 Zr-95 < 1.5 - < 2.4 < 3.9 < 4.2 < 3.3 < 4.3 Ce-141 < 1.0 <1.5 < 3.6 < 3.0 < 1.7 < 4.0 Ce-144 < 2.4 < 3.1 < 8.8 <11.3 <4.4 <12.5 Ru-106 < 6.4 < 10.3 <16.5 < 22.1 <16.1 < 22.3 Ru-103 < 1.2 < 1.4 < 2.2 < 2.8 < 2.0 < 2.2 Be-7 65 i 6 66'i 7 79 i 13 94 11 70 i 8 38 i 11 K-40 <9 < 16 < 25 182 5 18
. < 17 238 i 20 BaLa-140 < 4.3 < 5.1 < 9.1 < 5.3 < 4.9 < 9.4 Ra-226 < 10 < 13 < 32 < 34 15 i 7 < 35 I-131 < 4.0 < 3.0 < 9.6 < 10.3 < 7.2 < 11.2 Others** < LLD < LLD <LLD < LLD <LLD < LLD
.NUCLIDES ' JULY ' AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.8 < 2.0 < 3.0 < 1.6 < 1. 8 < 1.9 l
< 2.2 < 2.1 < 1.7 < 1.3 < 1.6 'l Mn-54 . < 2.6 Cs-134 < 1.7 < 1.7 < 2.1 < 1.4 < 1.9 < 1.6 Cs-137 < 1.5 < 1.6 < 1.1 < 1.2 < 1.6 <1.7 Nb-95 < 1.4 < 1.8 < 3.0 < 1.4 < 2.2 < 2.5 Zr-95 < 3.6 < 5.1 < 4.6 < 2.7 < 3.2 < 3.7 Ce-141 < 2.4 < 2.4 < 2.7 < 1.8 < 1.9 < 2.4 Ce-144 < 5.9 < 5.2 < 6.9 < 4.9 - < 6.4 < 5.1 Ru-106 <13.0 < 19.2 <18.1 < 17.1 < 21.6 < 14.7 Ru-103 < 1.9 < 1.1 <2.5 < 2.1 < 1.8 < 2.7 Be 71 1 11 46 i 9 30 i 8 57 8 42 i 8 40 i 7 K-40 < 24 < 32 < 33 22 i 9 40 11 <21 BaLa-140 < 10.5 < 8.9 < 8.1 < 10.7 < 10.3 < 9.7 Ra-226 < 26 <21 < 23 < 23 < 24 < 22 1 131 < 8.0 < 8.2 < 8.4 < 5.8 < 6.0 < 10.7 Others** < LLD < LLD < LLD < LLD < LLD <LLD
- - Location required by the Technical Specifications.
- - Other plant related radionuclides.
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-2 OFF-SITE STATION
- Results in units of 10 'pCl/m3 f_1 sigma NUCLIDES : JANUARY FEBRUARY- MARCHi ' APRIL MAY JUNE
'I 1997 Co-60 <0.9 < 1,4 < 2.2 <1.7 < 1.9 < 3.5 Mn-54 < 1.0 < 0.6 < 2.4 < 1.5 < 1.4 < 1.4
!. Cs-134 < 0.9 < 0.9 < 1.9 < 1.6 < 1.2 < 2.4 Cs-137 <0.8 < 1.1 < 2.2 < 1.1 < 1.0 < 1.7 i Nb-95 < 1.1 < 0.9 < 2.3 < 1.5 < 1.8 < 1.9 Zr-95 < 1.3 < 2.2 < 4.2 < 2.6 < 3.4 < 5.1 l.
Co 141 <1.2 < 1.1 < 2.6 < 2.0 < l.4 < 3.1 Cv144 < 3.3 < 3.3 < 5. 8 < 5. I < 4.6 < 6.2 i Ru 106 < 7.9 < 9.9 < 20.0 < 14.5 < 1.5 <18.7 {
Ru-103 <11 < 1.1 < 2.4 >1.2 < 1.6 < 2.1 j Be-7 50 i 5 60 i 6 66 i 10 94 i 10 67 i 8 52110 l K40 19 4 17 i 5 35 11 < 14 26 i 8 < 39 l BaLa-140 < 3. I < 3.6 < 7.3 < 5.1 < 7.3 < 9.0 R2-226 < 12 < 14 < 25 < 24 < 19 <39 I-131 < 3.9 < 3.2 < 5.9 < 5.6 < 6.2 < 10.0 )
l Others** < LLD <LLD <LLD <LLD <LLD < LLD NUCLIDES JULY ' AUGUST - SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.5 < 2.8 < 2.2 < 1.3 < 1.6 < l .7
! Mn-54 <1.3 < 1.4 <1.7 < l.3 < 1.5 < 1.6 Cs-134 < 1.8 < l.8 < 1.5 < 0. 8 < 1.6 < 1.6 Cs-137 < 1.2 <1.9 < 1.4 < 1.2 <l.7 <1.5 ,
Nb-95 < 2.0 < 3.0 < 2.3 <1.7 < 1.5 <2.7 l Zr-95 < 3.4 < 2. 8 - < 2.4 < 2.8 < 1.9 < 3.5 Cs-141 < 1.8 < 2.4 < 1.8 < 1.1 > 1. 8 <1.9 Co-144 < 5.0 < 6.1 < 6.1 < 3.3 <3.8 < 4.4 i Ru-106 < 20.2 < 12.9 < 14.8 <11.6 < 8.5 <13.6 Ru-103 < 2.0 < 1.9 < 1.6 < 1.2 < 1.8 < 2.1 - ,
Be 7 53 8 42 i 8 36 i S 27 i 5 15 6 43 i 7 l K-40 42 10 24 1 10 44 i,10 < 12 < 16 30 1 9 !
Bala-140 < 5.4 < 4. 8 < 9.2 < 7.5 < 4.0 < 11.6 l Ra-226 < 20 - < 25 17 i 7 < 16 < 12 < 24 I-131 < 5.3 < 7.8 < 7.8 < 6.; < 5.0 < 9.8 l
Others**. < LLD < LLD - < LLD <LLD <LLD < LLD 1
- - location required by the Technical Specifications.
} **- Other plant related radionuclides. .i u
i
L I
! TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES i
! 'R-3 OFF-SITE STATION
- Results in units of 19 8pC1/m' f.1 sigma o NUCLIDES " < 7ANUARY' FEBRUARY ' MARCH - APRIL MAY JUNE 1997 I l ,
Co-60 <0.9 <1.3 < 2.3 < 2.2 < 3.2 < 1.8 Mn-54 < 0.9 < 1.0 < 2.1 < 2.2 < 1.7 < 1.8 i Cs-134 < 0. 8 < 1.4 < 1.4 ( 2.0 < 1.7 < 2.0 l 4
l Cs-137 < 0.6 < 1.0 - < 1. 8 < 1.2 < 2.0 < 2.0 Nb-95 < 1.0 < 1.6 < 1.4 < 1.8 < 1.9 < 3.2
- Zr-95 < 2.0 < 2.3 < 2.9 < 3.6 < 2.0 < 3.6 J Ce-141 < 0.8 < 1.4 < 2.2 < 2.6 < 2.6 < 2.5 l L Cc-144 < 1.7 < 4.8 < 5.6 < 6.6 < 6.7 < 6.7 Ru-106 < 7.2 <13.0 <19.3 < 23.5 <18.8 < m.0 i l Ru-103 < 0.8 < 1.4 < 2.2 < 1.7 < 2.5 < 2. t ]
l Be-7 49 i 5 58 i 6 79 i 10 81 i 10 78 1 11 58 : 3 i K < 10 47 i 8 39 i 11 53 i 13 27 1 11 21 ,12 l Bata-140 < 5.2 < 4.6 < 3.2 < 7.4 < 11.8 < 8.7 ]'
Ra-226 < 10 < 16 < 28 < 21 < 28 < 25 I131 < 3.2 < 3.7 < 6.7 < 8.1 < 8.7 < 8.1 Others** < LLD < LLD <LLD < LLD - < LLD < LLD NUCLIDES .TULY - AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.9 < 2.7 < 3.4 < 1.4 < 2.2 < 1.5 l Mn-54 < 1.9 < 2.1 < 1.6 < 1.0 < 1.9 < 2.6 !
Cs-134 <1.6 < 1.2 <2.4 < 1.2 < 1.0 < 1.6 Cs 137 <2.2 <2.0 < 1.5 < 1.2 < 2.2 < 1.3 j Nb-95 <2.7 < 2.6 < 4.1 < 1.9 < 3.8 < 2.6 l Zr-95 < 4.4 < 3.9 < 6.7 < 2.0 < 5.1 < 3.0 Ce-141 < 3.0 < 3.0 < 2.9 < 1.3 < 2.6 < 2.9 Ce 144 < 8.9 < 9.0 < 6.0 - < 3.5 < 7.7 < 5.4 i n Ru-106 < 24.1 < 17.9 < 26.7 < 9.0 <21.8 < 17.7 1 l- Ru-103 < 2.8 < 2.4 < 1.9 < 1.3 < 2.5 < 2.8 I Be 7 45 i 11 38 i 7 40 i 9 21 1 6 13 i 9 46 i 8
- l. K-40 <35 173 16 <33 11 6 34 i 12 < 16 1 BalA.140 < 11.8 < 6.4 <8.3 < 7.9 < 10.1 < 9.0 Ra-226 < 27 <28.9 < 24 < 14 < 23 < 24 1-131 < 8.2 < 9.6 < 7.3 < 4.5 < 7.8 < 8.8 Others** <LLD < LLD < LLD < LLD < LLD <LLD
- - Location requi.nl by the Technical Specifications.
- - Other plant related radionuclides.
l 89-
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP f AIR PARTICULATE SAMPLES R-4 OFF-SITE STATION
- Results in units of 19 'pCi/m' d. I sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE 1997 Co-60 < 1. 8 < 1.1 < 1.0 < 2.2 < 1.2 < 1.9 Mn-54 < 1.5 < 1.6 < 1.6 < 1.8 < 1. 8 < 2.2 Cs-134 < 1.2 < 1.6 ' < 1.1 < 1.9 < 1.3 < 2.3 Cs-137 < 0.9 < 1.3 < 1.2 < 0. 8 <1.4 < 2.0 Nb-95 < 1.7 < 1. 8 < 2.1 < 1.6 <4.3 < 3.5 Zr-95 <2.5 < 2.8 < 2.0 < 1. 8 < 4.4 < 4.6 Ce-141 < 1.4 < 1.6 <1.5 < 2.0 < 2.5 < 3.2 Ce-144 < 3.8 < 5.1 < 4.2 < 4.4 < 4.9 < 10.2 Ru-106 <11.0 <14.5 < 15.0 < 17.4 < 13.3 < 20.1 Ru-103 < 1.5 < 1.6 < 1.4 < 2.0 < 2.1 < 2.6 Be-7 47 i 6 85 i 8 68 i 9 90 i 10 91 i 10 92 i 10 K-40 20 i 6 19 i 6 < 18 < 15 < 19 175 1 18 BILa-140 < 6.3 < 6.1 < 6.8 < 20.7 < 10.4 Ra-226 < 14 < 20 <' 17 < 25 < 15 < 35 I-131 < 5.1 < 4.5 < 6.5 < 6.7 < 8.5 < 9.1 Others** < LLD <LLD <LLD < LLD < LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.5 < 1.7 < 1.8 < 1.5 < 2.0 < 2.7 Mn 54 < 1.3 <2.0 < 2.1 < 1.4 < 2.1 < 2.8 Cs.134 < 1.7 < 1.0 < 2.0 < 1.0 < 1.6 < 2.0 Cc 137 < 1.9 < 1.4 < 1.9 < 1.1 < 1.4 < 2.0 Nb-95 < 1.8 < 2.6 < 3.6 < 2.0 < 3.0 < 4.0 Zr 9S < 3.4 < 2.9 < 5.3 <2.9 < 2.4 < 3.7 Ce-141 < 1.8 < 3.1 < 1.9 < 1.6 < 2.3 < 3.1 Ce-144 < 4.0 <8.4 < 6.6 < 4.1 < 6.6 < 7.3 Ru-106 < 20.1 , < 19.6 <16.6 <15.7 <16.5 < 24.2 Ru-103 < 3.0 < 2.1 < 2.3 <1.7 < 1.8 < 2.4 Be.7 68 i 9 54 i 8 61 i 9 50 t 7 48 8 51 i 9 K-10 < 16 135 i 13 29 1 10 < 18 32 i 10 < 36 Bab-140 <5.4 <5.3 < 7.1 < 4.7 < 6.4 <10.8 RS-226 816 < 25 < 25 < 18 < 24 < 28 I-131 < 4.3 < 9.3 < 6.9 < 5.7 < 4.7 < 8.2 Others** < LLD < LLD < LLD <LLD <LLD <LLD
- - Location required by the Technical Specifications.
- - Other plant related radionuclides.
90-
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMrITERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES R-5 OFF-SITE STATION * (CONTROL) :
Results in units of 10 8pCi/m' f. I sigma 1
1 NUCLIDES ' JANUARY . FEBRUARY MARCH - ' APRIL MAY : JUNE 1997 I Co-60 <1.2 < 1.8 < 3.5 < 2.0 < 2.0 < 1.6 Mn-54 < 1.2 <1.2 < 2.0 < 1.0 < 1. 8 < 2.0 Cs-134 < 0.9 <1.5 < 1. 8 < 1.6 <1.9 < 1. 8 ;
Cs-137 < 1.1 < 0.9 < 2.2 < 2.0 < 1.7 < 1.6 Nb-95 <1.6 < 1.1 < 3.2 < 3.5 < 2.8 < 2.1 Zr-95 < 1.9 < 2.5 < 4.8 < 5.2 < 4.0 <2.4 f Ce-141 , <1.5 <1.9 < 2.6 < 2.5 < 3.0 <1.3 i Ce 144 < 4.4 < 5.7 < 7.0 < 7.1 < 8.2 < 4.9 Ru-106 <12.2 < 14.4 < 27.5 <12.6 < 20.1 <11.8 j Ru 103 <1.4 <1.6 <2.4 <2.4 < 2.2 < 1.6 {
Be-7 61 i 6 77 i 7 104 i 13 109 i 13 91 i 9 104 i 10 K-40 22 i 5 31 i 6 15 9 < 20 156 i 14 < 16 Bata-140 < 5.2 < 4.8 < 8.4 < 6.d < 6.1 < 6.5 Ra-226 < 14.9 < 16 10 i 7 < 27 < 27 < 13. i 8 I-131 < 5.1 < 4.4 < 9.9 < 5.6 < 9.6 < 6.2 Others** < LLD < LLD <LLD <LLD <LLD < LLD NUCLIDES- JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 <1.6 < 1.8 < 3.2 < 1.1 < 2.2 < 2.2 Mn-54 <1.9 <1.6 < 1.9 < 1.6 <1.5 < 1.7 Cs-134 <1.3 < 0.9 < 1.8 < 1.1 < 1.0 < 1.3 Cs-137 <1.1 < 0.6 < 2.1 < 0.9 < 1.8 < 1.6 1 Nb-95 < 1.8 < 1.9 < 3.1 < 1. 8 < 2.3 < 2.4 Zr-95 < 2. 8 < 2.1 < 3.5 < 1.5 < 1.7 < 2.8 Ce-141 < 1.8 < 1.9 < 2. 8 <1.7 < 1.7 < 2.1 Ce-144 < 6.0 < 4.1 < 6. 8 < 4. 8 < 4.4 < 5.3 Ru-106 < 14.3 < 10.8 < 22.5 - < 15.5 < 19.2 < 15.1 Ru-103 <.1.8 < 1.8 < 2.1 < 1.4 < 2.1 < 2.0 Be-7 94 1 10 92 9 55 10 75 8 69 i 8 64 i 8 i K-40 30 t 8 < 12 32 5 12 22 i 8 17 i 8 < 28 l Bala-140 < 5.1 < 6.3 < 8.1 < 6.5 < 3.6 < 7.6 Ra-226 < 23 < 18 < 28 13 i 5.6 C < 23 1131 < 4.8 < 6.3 < 7.5 < 6.5 <4.6 < 8.9 Others** <LLD < LLD < LLD < LLD < LLD <LLD
- - Location required by the Technical Specifications. l
- -Other plant related radionuclides. I l
1
f TABLE 12 (Continc4)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES i
D-2 OFF-SITE STATION
- l i
Results in units of 10 'pci/m' i. I sigma i l
NUCLIDES JANUARY ' ! FEBRUARYMARCH APRIL MAY JUNE 1997 Co-60 < 1.2 < 0.9 < 2.1 < 3.1 < 1.2 < 1.7 Mn-54 < 0.9 < 1.0 <2.3 < 2.3 < 1.6 < 1.6 Cs 134 < 0.6 < 1.2 < 2.1 < 1.9 < 1.5 < 1.5 Cs-137 < 1.0 < 1.2 < 2.0 < 2.2 <0.7 < 1.3 Nb-95 <1.7 < 1.5 < 4.1 < 2.7 < 1.9 < 2.4 Zr-95 < 2.2 < 1.9 < 2.1 < 4.6 < 2.4 < 4.5 Cs-141 < 1.9 < 1.5 < 2.5 < 3.0 < 1.8 < 2.7 Ce-144 < 5.1 < 4.5 < 7.5 < 11.0 < 4.9 < 5.9 Ru-106 < 10.4 <13.8 < 22.1 <19.2 <12.7 <15.2 Ru-103 < 1.2 < 1.1 < 2.6 <2.4 < 1.9 < 2. 8 Be-7 60 i 5 81 i 7 84 i 12 110 i 10 99 i 10 99 i 11 K-40 125 i 9 30 i 7 < !9 164 i 17 < 21 < 22.3 Bia 140 < 2. 8 < 2. 8 < 9.6 < 8.7 <8.4 < 9.4 Ra-226 13 t 6 < 15 < 24 <38 13 i 7 < 22 1-131 <5.18 < 3.5 < 6.9 < 9.0 < 6.3 < 16.3 Others** <LLD < LLD <LLD < LLD < LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.3 < 1.4 < 2.2 < 2.4 < 1.7 < 1.9 Mn-54 < 2.8 < 1.8 < 1.1 < 1.2 <1.7 < 1.6 Cs 134 < 2.1 < 1.9 < 0.9 <0.9 < 1.1 < 1.6 Cs 137 < 1. 8 < 1.5 < 1.3 < 1.6 <1.5 <1.3 Nb-95 < 3.0 < 3.6 < 1.8 < 2.0 < 2.0 < 1. 8 Zr-95 < 5.0 < 4.8 < 4.1 < 3.1 < 2. 8 < 4.2 Co-141 < 2.9 < 2.6 < 2.2 < 1.3 <1.5 < 2.5 Ca-144 < 7.4 <$.6 < 4.5 < 4.8 < 4.7 < 5.8 l
i Ru 106 < 21.8 <16.9 <15.5 < 14.2 <12.6 < 14.9 Ru-103 < 2.2 < 2.3 < 1.8 < 1.4 < 1.5 < 1.6 Be 92 i 12 78 i 11 77 i 9 58 i 8 66 i 10 73 i 11 l K-40 < 25 < 30 <2k < 12 < 25 39 i 10 B tLa-140 < 12.7 < 11.0 < 6.9 < 6.3 < 6.0 < 9.8 Ra-226 < 28 < 24 < 22 15 i 6 < 19 < 25 l 1-131 < 12.2 < 9.0 < 5.3 < 4.6 < 3.0 < 11.6 Others** <LLD < LLD < LLD < LLD <LLD <LLD I * - Optional sample location.
l ** - Other plant related radionuclides.
l
)
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES E OFF-SITE STATION
- Results in units of lQ 'pCL/m' i 1 sigma NUCLIDES JANUARY FEBRUARY' MARCH APRIL MAY JUNE 1997 Co-60 <0.7 < 1.0 < 2.8 < 2.1 < 1.9 < 2.6 Mn-54 < 0.8 < 1.2 < 2.2 < 1.9 < 1.6 < 2.5 i Cs-134 < 0.8 < 0.9 < 1.4 <2.0 < 1.4 < 2.4 l Cs-137 < 0.5 < 0.7 < 2.0 < 1.8 < 1.4 < 1.5 Nb-95 < 1.2 < 1.8 <2.9 <2.7 < 2.1 < 3.3 ,
Zr-95 < 1.8 < 2.3 < 4.2 < 3.2 < 3.4 < 4.2
< 0.9 < 1.1 < 3.5 <2.0 < 2.1 < 2.4 l Cc-141 Ce-144 < 2.9 < 3.2 < 9.7 < 6.1 < 5.6 < 7.0 Ru 106 < 8.4 < 9.5 < 25.2 < 14.2 < 19.7 < 19.9 I Ru-103 < 1.1 < 0. 8 < 2.5 < 2.2 < 1.5 < 1.9 ]
Be-7 52 i 5 66 i 6 67 10 95 10 90 1 10 75 i 11 K-40 8i3 < 12 188 i 17 65 i 13 14 9 < 21 BaLa-140 < 2.8 < 5.4 < 6.3 <8.7 < 7.9 < 8.5 Ra-226 < 12 < 12 < 32 < '.'.5 < 23 < 25 1-131 < 3.9 < 2. 8 < 9.6 < 8.0 < 5.9 < 6.8 Others** < LLD <LLD < LLD <LLD < LLD < LLD NUCLIDES JULY AUGUST SEI'TEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.9 < 1.9 < 2.4 <0.9 < 2.0 < 1.9 Mn-54 < 1.4 < 1.9 < 2.7 < 1.1 < 2.0 < 1.5 i Cs-134 < 2.0 < 2.1 < 2.8 < 0. 8 < 2.1 < 1.5 Cs 137 < 2.6 < 1.7 < 2.0 < 0.8 < 2.0 < 2.5 Nb-95 <3.8 < 2.5 <2.2 < 1.4 < 2.9 < 3.1 Zr-95 < 4.4 < 3.8 < 4.2 < 2.1 < 4.5 < 2.9 Ce-141 < 2.7 < 2.4 < 3.0 < 1.5 < 2. 8 < 1.6 Ce-144 < 8.2 < 7.8 < 7.3 < 3.0 < 7.2 < 6.0 Ru-106 < 20.5 <18.9 < 23.3 < 10.0 < 29.0 <18.1 Ru-103 < 2. 8 < 2. 8 < 2.0 < 1.4 < 2.5 < 2.0 Be-7 69 i 10 50 t 9 56 i 11 56 1 6 47 i 9 63 i 9 K-40 36 i 12 31 t 10 48 1,13 < 12 < 35 <28 Bata-140 < 8.3 <11.4 < 19.8 < 5.4 < 8.2 < 10.2 Ra-226 27 i 10 < 27 < 25 9i4 <31 < 16 I131 < 7.0 < 9.3 < 9.8 < 4.4 < 8.0 < 10.8 Others** < LLD < LLD <LLD < LLD < LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
l '
l t
TABLE 12 (Continued) l CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES l
l F OFF-SITE STATION
- Results in units of 10 8pCl/m3 .i.1 sigma NUCLIDES ~ JANUARY . FEBRUARY MARCH APRIL MAY JUNE 1997
- Co-60 < 0.7 < 1.7 < 1. 8 < 2.6 < 1.8 <2.2 Mn-54 < 0.6 < 1.5 < 1. 8 < 2.4 < 2.0 < 2.4 Cs-134 < 0.9 < 1.1 <1.6 < 0.9 < 1. 8 < 2.8 Cs-137 < 0.7 < 1. 8 < 1.6 < 1.9 < 1.6 < 2.1 j Nb-95 <1.3 < 1.8 < 2.2 < 1.9 < 4.1 < 2.9 l Zr-95 <1.6 < 3.0 < 2.4 < 2.6 < 5.0 < 4.6 l C2-141 < 1.3 < 1.6 < 2.2 < 1.6 < 3.6 < 3.6 l
Ce-144 < 3.1 < 4.8 < 4.7 < 4.8 < 6.4 < 11.5 Ru 106 < 9.7 < 12.8 < 15.9 <13.3 <18.9 < 21.3 i Ru-103 < 0. 8 < 1.5 < 1.6 < 1.6 < 2.0 < 2.1 Be-7 66 i 5 70 t 8 74 i 9 92 i 10 91 12 100 i 11 K-40 24 i 5 18 -t 8 < 19 < 21 < 18 182 18 Bia-140 < 4.0 < 6.0 < 7.4 < 10.5 < 8.9 < 8.3 l Ra-226 < 13 < 15 < 25 < 18 < 23 <38 l' l131 < 3.7 < 4.1 < 6.6 < 6.4 <12.4 <13.5 Others** < LLD < LLD < LLD < LLD <LLD <LLD NUCLIDES JULY AUGUST ' SEPTEMBER OCTOBER NOVEMBER DECEMBER l
Co-60 < 2.9 < 2.0 < 2.0 < 0.9 < 1.6 < 2.2 Mn 54 < 2.2 < 1. 8 < 1.7 < 1.3 < 1.3 < 1.7
! Cs-134 < 1.5 < 1.7 < 1.2 < 0.9 < 2.0 < 2.9 ,
l Cs-137 < 1.6 < 1.5 < 1. 8 < 0. 8 < 2.0 < 2.2 - l Nb-95 < 2.3 < 2.9 < 2.6 < 1.6 < 2.9 < 4.7 l Zr-95 < 3.5 < 3.R < 4.1 < 2.2 < 4.4 < 5.2 Ce-141 < 2.2 < 3.3 < 2.4 < 1.3 <2.4 < 2. 8 Ce-144 < 6.9 < 8.3 < 5.6 < 3.5 < 6.0 < 6.6 l Ru-106 < 20.9 < 19.9 < 21.5 < 10.9 < 21.7 < 19.0 Ru-103 < 2.0 < 2.4 < 2.0 < 1.1 < 2.5 < 2.5 Be-7 50 8 44 i 8 45 i 8 52 i 5 30 1 7 48 i 9 t K-40 < 24 155 i 15 50 f 11 30 i 5 < 24 25 i 9 l l
BaLa-140 - < 5.6 < 6.3 < 6.3 < 3.6 < 8.6 9.2 Ra-226 < 23 < 25 < 29 < 14 <21 < 30 l I-131 < 5.9 < 10.5 < 6.0 < 4.8 < 4.2 < 13.6 Oth:rs" < LLD < LLD <LLD <LLD < LLD < LLD
- - Optional sample location
- - Other plant related radionuclides l
L
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G OFF-SITE STATION
- Results in units of 10 'pCl/m' i. I sigma NUCLIDES ' JANUARY FEBRUARY MARCH APRIL l MAY JUNE I
1997 Co-60 < 0.9 < 1.5 < 2.2 < 1.9 < 1.5 <2.6 Mn-54 < 0.7 < 1.3 < 1.5 < 1.4 < 1.1 < 2.7 Cs-134 < 0.7 < 1.4 < 1.3 < 1.6 < 1.1 <2.2 Cs-137 < 0.6 < 1.1 <1.3 < 1.6 < 1.4 < 2.0 6 95 < 1.3 <1.5 < 1.8 < 3.6 < 1.6 <2.5 Ir-95 < 1.4 < 2.2 < 3.0 < 3.7 < 3.9 < 5.2 Ce-141 < 0.8 <1.7 < 1.8 < 1.9 < 1.9 < 3.5 Ce-144 < 2.4 < 5.4 < 4.9 < 6.8 <4.8 < 9.8 Ru-106 <6.7 < 12.1 < 11.1 < 19.1 < 14.6 < 21.9 E Ru-103 < 1.0 < 1.3 < 1.9 < 2.5 < 1.6 < 2.5 g
- Be-7 53 i 5 68 i 7 72 i 9 108 i 11 100 i 10 110 i 11 X-40 <7 37 i 7 < 14 36 i 10 18 i 10 194 i 17 Sala-140 < 3.5 < 4.5 < 6.3 < 8.9 < 8.6 < 7.6 Ra-226 9i3 < 14 < 19 < 23 < 23 < 30 I-131 < 2.7 < 4.6 < 3.5 < 6.3 < 7.2 < 9.0 Others** < LLD < LLD <LLD <LLD < LLD < LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 1.4 < 1.4 <1.6 < 0. 8 < 3.4 < 2.0 Mn-54 < 1.6 < 1.1 < 2.0 < 0. 8 < 2.2 < 1.4 Cs-134 <1.3 < 1.0 <1.3 < 0.7 < 1. 8 <0.9 Cs-137 < 1.0 < 1.0 < 2.0 < 0.7 < 1.8 <1.2 Nb-95 < 2.0 < 0.9 < 1.6 < 1.4 < 3.1 < 2.9 Zr-95 < 2.9 < 2. 8 < 2.4 < 2.2 < 2.5 < 5.6 Ce-141 < 2.0 < 2.0 < 1.6 < 1.1 < 2.9 < 2.3 Ce-144 <5.8 < 4.4 < 4.7 < 2.6 < 6.2 <6.9 Ru-106 < 13.8 < 12.0 < 12.4 < 6. 8 < 22.5 < 17.8 Ru-103 < 1.9 < 1.8 < 1.0 < 1.0 < 2.7 < 2.3 Be-7 92 i 9 53 i 7 37 i 8 62 i 5 60 i 9 62 1 10 E 0 40 < 25 < 20 < 17. < 11 12 i 9 < 18 g BaLa-140 < 5.4 < 9.2 < 9.8 < 5.1 < 7.6 < 9.2 R
. a-226 < 22 < 19 < 15 <9 < 24 < 18 I-131 < 5.8 < 6.3 < 5.4 <4.3 < 6.5 < 8.9 Others** < LLD < LLD < LLD < LLD <LLD < LLD
- - Optional sample location. 3
"- Other plant related radionuclides. 3 I
l TABLE 12 (Continued) l CONCENTRATION OF GAMMA EMlTTERS IN MONTIILY COMPOSITES OF NMP l AIR PARTICULATE SAMPLES I 1
D-1 ON-SITE STATION
- Results in units of M 3gCilnt'i i sigma l NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE 1997 Co-60 < 0.9 < 1.1 < 2.1 < 1.9 < 2.0 < 3.6 I Mn-54 < 0.8 < 1.0 < 1.7 < 1.0 < 1.9 < 2.2 Cs-134 < 0. 8 <0.9 < 1.4 < 1.1 < 1.8 < 2.0 Cs-137 < 0.6 < 0.7 < 1.6 < 0. 8 <1.7 < 2.0 Nb-95 < 1.0 < 1.3 <1.7 < 2.3 < 2.9 < 3.2 l
Zr 95 < 1.6 <2.2 < 2.2 < 2. 8 < 4.7 < 4.7 Ce-141 < 1.0 <1,1 < 1.8 < 2.2 <32 < 3.2 Ce-144 < 2.6 < 3.1 < 4.8 < 5.5 < 8.6 < 7.6 Ru-106 < 7.1 < 7. 8 < 21.2 < 18.3 < 16.5 < 17.4 l Ru-103 < 1.0 < 1.0 <2.4 < 2.2 < 2.4 < 3.0 Be-7 73 i 6 69 5 71 i 9 94 i 11 81 i 9 93 i 12 K-40 10 t 3 7i3 147 15 < 25 162 14 < 23 BILa 140 < 3.7 < 4.15 < 7.5 < 6. 8 <4.7 < 6.4 Ra-226 < 11 11 1 4 < 30 15 1 7 < 24 < 32 I-131 < 4.0 < 3.2 < 6.8 < 5.8 < 12.1 <11.3 Others** < LLD <LLD < LLD <LLD < LLD < LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER j Co-60 <1.4 < 1.0 < 2.3 < 1.6 < 2.4 < 1.8 l Mn-54 < 1.8 < 1.6 < 3.2 < 1.4 < 1.8 < 1.7 Cs-134 < 1.2 < 1.2 < 2.0 < 1.4 < 1.6 < 1.4 Cs-137 < 1.5 < 1.2 < 2.3 < 1.1 < 1.3 < 1.3 Nb-95 < 2.8 < 2.0 < 3.4 < 2.6 < 2.5 < 2.1 Zr-95 < 1.7 < 3.2 < 3.8 < 2.1 < 2.9 < 4.3 Ce-141 < 2.0 < 2.0 < 3.3 <1.3 < 2.0 < 1.8 Co-144 <5.4 < 5.3 < 6.2 < 4.1 < 5.1 < 4.2 Ru-106 <!2.3 <16.3 < 17.7 < 11.2 <17.0 < 19.2 Ru 103 < 2.3 < 2.06 < 2.6 < 1.6 < 1.8 < 2.0 Be-7 100 i 10 97 i 9 73 i 12 21 i 9 62 i 9 73 i 8 K-40 <21 32 i 8 < 34, < 12 24 i 10 < 25 BaLa-140 < 5.6 < 7.2 < 14.3 < 4.3 < 5.9 < 9.2 Ra-226 < 19 < 20 < 25 < 1.9 < 29. I < 2.0 1-131 < 7.4 < 8.7 < 7.3 < 7.1 < 6.4 < 9.2 Others** <LLD < LLD < LLD < LLD <LLD < LLD
- - Optional sample location.
! ** - Other plant related radionuclides.
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES G ON-SITE STATION
- Results in units of 10 'pCl/m 3
- f. I sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY -JUNE 1997 Co-60 < 1.6 < 1.3 <2.1 < 2.2 < 2.9 < 2.4 Mn-54 < 1.3 < 1.4 < 2.8 < 1.6 < 1. 8 < 2.1 1 Cs-134 < 1.0 < 1.1 <0.9 <1.7 < 1.6 < 2.1 l Cs 137 < 1.3 < 0.8 < 2.2 < 1.6 < 2.0 < 2.0 Nb-95 < 1.7 <1.2 < 1.4 < 1.7 < 2.7 < 3.0 Zr-95 < 2.4 < 1.9 < 5.4 < 3.8 < 4.0 < 5.0 l Ce-141 < 1.6 < 1.4 < 2.8 < 2.0 < 2.7 < 2.1 i Ce-144 < 4.4 < 4.7 < 7.6 < 6.7 < 5.8 < 6.7 Ru-106 <:1.9 < 11.1 <13.8 < 15.1 <19.4 < 2.2 ;
Ru-103 < '. .4 <1.3 < 1.9 < 1.4 < 2.6 < 2.4 j Be-7 61 i 7 85 i 7 92 11 105 i 10 104 i 12 98 13 K-40 24 i 6 37 i 6 51 i 11 36 i 10 < 23 32 1 12 Bala-140 < 6.0 < 4.5 < 4.3 < 5.8 < 10.9 < 5.6 i Ra-226 < 14 < 14 < 22 < 23 < 25 < 3.1 I-131 < 5.2 < 3.9 < 7.6 < 8.3 < 11.9 < 1.2 Others** <LLD <LLD <LLD < LLD < LLD < LLD l l
NUCLIDES JULY AUGUST SEPTEMBER OC1'OBER NOVEMBER DECEMBER Co-60 < 1.9 < 1.9 < 3.6 < 1.2 < 5.1 < 1.4 ;
Mn-54 < 1. 8 < 2.0 <1.7 <1.4 < 3.0 <1.4 I Cs-134 < 1.6 <1.5 < 1.2 < 1.3 < 2.7 < 1.5 Cs 137 < 1.7 < 1.8 < 1.9 < 1.4 < 1.3 < 1. 8 Nb-95 < 1.5 < 2.0 < 1.7 < 2.0 < 3.7 < 2.6 '
Zr-95 < 3.6 < 4.4 < 5.5 < 1.6 < 6.1 < 5.5 Ce-141 < 2.1 1.8 < 2.2 < 1.6 < 3.7 < 18.9 Ce-144 < 6.5 < 5.3 < 6.0 < 4.3 < 8.6 < 5.3 Ru-106 < 19.3 < 13.9 < 14.0 < 18.0 < 18.8 < 2.0 Ru-103 < 1.4 < 1.6 <2.2 < 1.6 < 2.2 < 5.3 Be-7 103 i 10 37 i 7 68 i 10 35 6 < 24 47 i 8 '
K-40 34 i 10 < 16 < 26. 23 6 40 i 12 < 22 BaLa 140 < 7.7 < 10.0 < 7.3 < 4.6 < 10.4 < 10.8 Ra-226 < 24 < 20 < 28 11 i 6 < 33 < 18 I131 < 6.3 < 10.4 < 6.5 < 4.8 < 9.5 < 8.8 Others** <LLD < LLD <LLD <LLD < LLD <LLD
- - Optional sample location.
- - Other plant related radionuclides.
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES II ON-SITE STATION
- Results in units of 10 8pCi/m' i 1 sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE 1997 Co-60 < 0. 8 < l.4 < 2.5 < 1. 8 < 1.6 < 2.1 Mn-54 < 0.7 < 0. 8 < 2.1 < l.4 < l.2 < 1.7 Co-134 < 0.5 < 0. 8 < 2.2 < l.5 < l.2 < l.5 Cs-137 < 0.6 < 0.9 < 1.9 < 1.2 < l.4 < 1. 8 Nb-95 < l.6 < l .9 < 2.9 < 2.0 < l.8 < l.9 Zr-95 < l.3 < 2.2 < 3.6 < 2.5 < 4.2 < 4.2 Ce-141 < 0.7 < 1. I < 3.4 < l .7 < 2.0 < 3.0 Ce-144 < 2.5 < 2.9 < 8.9 < 5.4 < 5.1 < 7.1 Ru-106 < 7.9 <11.1 < 20. I < 16.3 < l.5 < 21.2 Ru-103 < 0.9 < l.2 < 2.4 < l.7 < l.7 <l8 Be 7 72 1 6 70 i 6 83 i 10 100 i 11 IOS i 11 116 i 14 K-40 < 12 < l5 126 i 15 < 28 19 i 10 23 i 8.9 Bala-140 < 4.5 < 5.0 <8.2 < 6.8 < 9.6 < 8.8 Re-226 <10 < 12 <31 < 19 < 25 < 27 I-131 < 3.5 < 3.7 <11.2 < 6.0 < 8.3 < 6.7 Others** <LLD <LLD <LLD <LLD <LLD <LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 1.8 < 1.6 < l.8 < l .4 < l.8 < 3.1 Mn-54 < 2. 8 < l.9 < 1. 8 < l .1 <l.6 < l.0 Cs 134 < l.7 < l .7 < l .4 < l .2 <l.5 < 1.4 Cs 137 < 2.0 < l.5 < 1.5 < 1.0 < 1.0 < l .7 Mb-95 < 2.6 <2.4 < 2.5 < 1.2 < 2. 8 < 1.5 Zr-95 < 4.3 < 3.2 < 3.2 < 3.6 < 3.4 < 4.2 Ce-141 < 3.2 < 2.7 < 1.6 < 2.2 < 1.8 < 2.1 Ce 144 < 6.8 <7.4 <5.7 <4.5 <5.5 < 5.5 Ru-106 < 23.9 < 16.9 < 9.0 < 7. 8 < 19.6 < 17.8 Ru-103 < 2.7 <2.2 < l.3 < l.9 < 1.6 < 2.0 Be-7 101 i 13 100 1 9 72 i 9 88 i 10 59 8.9 54 i 10 K-40 < 28 155 i 14 < 19 <21 <21 < 22 BcLa-140 < 8.9 < 7.1 < 8.0 < 12.6 < 8.0 < 10.4 Re-226 < 32 <27 < 20 < 14 < 18 < 16 I-131 < 9.3 < 8.3 < 4.6 < 16.6 < 3.5 < 7.0 Others** <LLD <LLD <LLD <LLD <LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTHLY COMPOSITES OF NMP AIR PARTICULATE SAMPLES I ON-SITE STATION
- Results in units of 10 'pCi/m' i.1 sigma NUCL1 DES JANUARY - -FEBRUARY MARCH APRIL MAY JUNE-1997 Co-60 < 1.7 <1.7 < 3.4 < 2.9 < 2.1 < 2.6 Mn-54 < l .1 < 1.7 < 1.9 < 2.3 < 1. 8 < 2.6 j Cs-134 < 1.4 <1.1 < 2.0 < 2.1 < 1.8 < 2.5 )
Cs-137 <1.1 < 1.4 < 1.8 < 1.7 < 1.8 < 1.7 Nb-95 < 1.9 < 1.7 < 2.8 < 3.1 < 2.2 < 3.1 ,
Zr-95 < 2.4 < 2.5 < 5.6 < 4.1 < 6. I < 4.0 l Ce-141 < 1.4 < 1.5 < 2.9 < 3.6 < 3.0 < 3.6 Ce-144 < 3.9 < 4.8 < 6.7 < 9.7 < 6. I < 10.4 Ru-106 <12.5 <15.5 < 20.7 < 21.3 < 17.7 < 31.3 1 Ru-103 <1.53 < 1.8 < 2. 8 < 2. 8 < 3.1 < 3.3 l Be-7 81 i 7 62 i 8 71 i 12 113 i 11 113 i 13 98 i 11 K-40 12 i 6 25 i 8 < 23 180 i 19 < 24 217 i 19 .
Bala 140 < 4.83 < 7.1 < 8.8 < 5.4 < 10.1 < 7. 8 !'
Ra-226 < 13 < 17 < 36 < 33 < 30 31 i 12 I-131 < 5.6 < 5.6 < 10.5 < 12.1 <11.6 < 9.1 Others** < LLD < LLD < LLD < LLD <LLD < LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.0 < 1.2 < 1.3 < 1.2 < 2.4 < 2.2 lMn-54 < 1.6 <1.6 < l .9 < 2.0 < l.8 <1.6 Cs-134 <1.7 < 1.2 < 1.4 < 1.2 < 1.5 < 1.6 Cs-137 < 1.9 < 7.9 < 1.9 < 1.4 < 1.3 <1.8 Nb-95 < 2.7 < 2.0 < 2.0 < 1.9 < 1. 8 < 3.2 Zr-95 < 2.6 <2.6 < 3.1 < 3.2 < 3.1 < 3.8 Ce-141 <2.1 < 2.0 < 1.3 < 2.5 < < 2.2 < 3.3 Cc-144 < 6.2 < 4. I < 4.7 < 4.6 < 6.4 < 8.1 Ru-106 < 18.0 < 14.7 <13.2 < 15.5 <11.4 < 16.8 Ru-103 < 2.4 <1.3 < 1.6 < 1.8 < 1.5 < 2.3 Be-7 til i 11 86 i 8 60 1 10 88 i 10 56 i 8 65 i 11 K-40 < 19 < 15 < 17 < 14 33 10 <21 BaLa-140 < 7.5 < 6.7 < 7.4 < 7.9 < 5.5 <10.9 Ra-226 < 29 < 18 < 20 < 17 < 23 < 22 1-131 < 5.4 < 6. I < 6.4 < 9.9 < 6.0 < 1.4 Others** < LLD < LLD < LLD <LLD < LLD < LLD
- - Optional sample location.
- - Other plant related radionuclides.
99
l TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITFJS OF NMP AIR PARTICULATE SAMPLES l J ON-SITE STATION
- Results in units of 10 'pCi/m' f I sigma NUCLIDES JANUARY FEBRUARY MARCH APRIL MAY JUNE 1997 Co-60 < 1.4 < 1.5 < 2.2 < 1.5 < 2.3 < 1. 8 Mn-54 < 0.8 < 1.2 < 2.2 < 2.2 < 2.1 < 2.3 Cs-134 < 1.1 < 0. 8 < l.7 < 1.6 < 1.7 < 1.8 Cs 137 < 1.0 < l.2 < 2.4 < 1.6 < 1.7 < 1.7 Nb-95 < 1.7 < l.8 < 2.0 < 3.0 < 3.1 < l.5 Zr-95 < 2.1 < 2.6 < 3.8 < 3.8 < 4.2 <3.1 Ce-141 < 1.7 < 1.2 < 2.6 < 2.6 < 3.0 < 1.9 C3-144 < 5.0 <3.8 < 7.6 < 4.7 < 8.2 < 6.8 Ru-106 <15.0 < 9.7 < 21.9 <!6.5 <19.9 < 14.3 Ru-103 < l.3 < 1.5 < 2.2 < 2.5 <2.5 < l.6 Be-7 64 i 7 67 i 6 64 i 10 96 i 11 85 i 9 103 i 11 K-40 36 i 7 12 i 5 42 i 12 < 24 139 i 14 < 22 BaLa-140 < 6.0 < 4.9 < 10.0 < 8.8 < 9.8 < 7.7 Ra-226 < 14 < 13.9 < 28 < 25 < 27 < 16 f-131 < 5.8 < 4.4 < 7.2 < 6.5 < 1.1 < 7.4 Others ** <LLD < LLD <LLD <LLD <LLD <f 1 n NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 2.0 < 1.6 < 2.7 < 2. I <2.2 <1.9 Mn-54 < l.7 <1.5 < 1. 8 < l.3 < 2.2 < 2.6 Cs 134 < 2.1 < 1.4 < 2.7 < 1.6 < l .4 < l.8 C4-137 < l.7 < 1.5 < 1. 8 < 1.7 < 2.2 < l.8 Nb-95 < 2.4 <2.7 < 3.5 < 2.5 < 2.5 < 2.4 Zr 95 < 4.2 < 3.4 < 3.9 < 5.0 < 3.7 < 3.5 Ce-141 < 1.9 < 2.1 < 2.1 < 2.2 < 2.6 < l.8 C9144 < 6.2 < 5.5 < 7.1 <5.4 < 8.5 < 5. 8 Ru 106 < 18.9 < 11.3 < 22.9 < 17.2 < 14.7 < 14.9 Ru 103 < 2.0 < 1.8 < l .9 < 2.7 < 2.6 <2.3 Be-7 88 i 11 85 i 9 56 i 9 67 1 10 44 1 9 66 10 K-40 73 i 11 40 i 9 30 i,12 27 i 10 < 19 21 i 8
<5.4 BaLa-140 < 7.1 <12.6 < 7.0 < 7. 8 <10.7 '
Ra-226 < 28 < 22 <31 < 26 < 22 <21 1 131 < 6.7 < 6.9 < 9.1 < 7.7 < 7.3 < 10.2 l Others** <LLD <LLD <LLD < LLD < LLD <LLD '
- - Optional sample location.
- - Other plant related radionuclides.
-100-
TABLE 12 (Continued)
CONCENTRATION OF GAMMA EMITTERS IN MONTIILY COMPOSITES OF NMP AIR PARTICULATE SAMPLES K ON-SITE STATION
- Results in units of B 'pCi/m' f_1 sigma NUCLIDES JANUARY. -FEBRUARY MARCH APRIL MAY JUNE 1997 Co-60 < 1.1 <1.6 < 1.5 < 2.9 <1.7 < 3.8 Mn-54 < 1.1 < 1.4 < 1.5 < 1. 8 <1.3 < 2.1 Cs-134 < 0. 8 < 0.9 < 1. 8 < 2.3 < 0.7 < 2.0 Cs-137 < 1.1 < 1.2 <1.6 <1.7 < 1.2 < 2.7 Nb-95 < 1.5 < 1. 8 < 2.3 < 2.9 < 2.5 < 3.5 Zr-95 < 2.0 < 2.0 < 3.8 < 4.1 < 3.3 < 5.3 Cc-141 < 1.8 < 2.2 < 2.4 < 2.6 < 2.3 < 3.2 Cc-144 < 4.9 < 6.6 < 5.9 < 7.0 < 3.5 < 8.5 Ru-106 <11.2 <14.3 < 19.1 <15.3 <13.8 < 20.0 Ru-103 < 1.3 < 1.4 < 2. I < 2.4 < 2.2 < 2.2 1 7 77 i 6 80 i 6 76 i 10 117 i 11 79 i 9 81 1 11 K-40 119 i 8 151 i 11 40 i 11 30 1 8 < !6 < 22 B.La-140 < 4.6 < 5.0 < 10.3 < 7.0 <11.7 < 1.0 Ra-226 < 17 < 22 9i6 < 26 < 20 <33 1-131 < 5.5 < 6.2 < 5.2 < 7.5 < 14.3 < 12.9 others** < LLD < LLD < LLD < LLD < LLD < LLD NUCLIDES JULY AUGUST SEPTEMBER OCTOBER NOVEMBER DECEMBER Co-60 < 3.6 < 2.0 < 2.3 < 2.0 < 2.6 < 2.3 Mn 54 <1.5 < 1.7 < 1.4 < 1. 8 <1.5 < 2.1 !
Cs-134 < 2.2 < 1.1 < 1.6 < 1.4 < 1.9 < 2.6 Cs-137 < 2.0 <1.3 < 1.5 < 1.9 < 1.8 < 2.1 Nb-95 < 2.9 < 2.2 < 3.5 < 2.7 < 2.4 < 2.3 Zr-95 < 6.0 < 3.7 < 3.6 < 3.1 < 3.5 < 4.6 Ce-141 < 3.2 < 1.9 < 2.5 < 2.9 < 2.4 < 3.4 Ce-144 < 8.0 <4.7 < 6.3 < 7.3 < 5.6 < 7.0 Ru-106 < 22.5 < 14.5 < 10.9 < 17.9 < 13.5 < 20.1 Ru-103 < 3.2 < 2.2 <2.2 < 2.6 < 2.7 < 2.6 Be-7 96 i 12 85 i 9 85 i 10 80 i 9 58 8 47 i 10 K-40 56 i 13 < 18 < 19, 125 i 12 26 i 9 39 13 BaLa-140 < 9.6 < 5.6 < 7.9 < 6.9 < 9.4 < 12.4 Ra-226 < 35 < 16 < 25 < 31 < 26 < 29 i I-131 < 10.4 < 3.6 < 7. 8 < 7. 8 < 7.1 < 13.1 l Others** <LLD <LLD < LLD < LLD < LLD < LLD
- - Optional sample location. l
- - Other plant related radionuclides. l
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TABLE 18 MILK ANIMAL CENSUS 1997 TOWN OR AREA (a)- - NO. ON CENSUS M AP(1) DEGREES (2) DISTANCE (2) NO. OF MILK ANIMALS kriba 3 190o 4.5 Nor.e 62 183o 6.7 None 63 1850 8.0 35C 74 195o 5.6 None Mew Haven 9 950 5.2 40C 4* 113o 7.8 100C 7 107o 5.5 50C 64 107o 7.9 50C Wexico 12 107o 11.5 None 14 120o 9.8 58C 17 115o 10.2 None 19 132o 10.5 40C 60* 900 9.5 40C 50* 93o 9.3 150C 55* 950 9.0 57C 21 112o 10.5 64C 68 108o 11.6 None 49 88o 7.9 4G (3) 72 980 9.9 36C tswego 73** 234o 13.9 50C Lichland 22 85o 10.2 52C blzski 23 92o 10.5 None folney 70 147o 9.4 17C 66 156o 7.8 None MILKING ANIMAL TOTALS: 839 Cows (including control locations) 4 Goats MILKING ANIMAL TOTALS: 789 Cows (excluding control locations) 4 Goats
-112-
.i TABLE 18 (Continued)
MILK ANIMAL CENSUS ,
1997 NOTES:
C ' - Cows ,
G. = Goats )
- = Milk sample location
- = Milk sample control location (1) = References Figure 4 (2) = Drgnes and distance are based on NMP-2 noctor building centerline (3) = Goat is ag currently producing milk or any milk produced is utilized by the owne.-
None = No cows or goats at that location. I.ocation was a previous location with cows and/or goats.
1 I
I I
l l
l l
i l
l l
5 l
l
-113-
TABLE 19 1997 RESIDENCE CENSUS I .
[ . MAP ; . METEOROLOGICAL :
IDCATION ;- s LOCATION (1) - -: SECTOR .-~ DEGREES (2)
. DISTANCE (2)-
- N - -
- NNE - -
- NE - -
- ENE - -
Lales Road A E 99* 1.3 miles Lake . Road B ESE 102* 1.1 miles County Route 29 C SE 130* 1.4 miles Miner Road D SSE 163* 1.6 miles Miner Road E S 170* 1.6 miles Laksview Road F SSW 207' 1.2 miles Bible Canp Retreat G SW 234' O.9 miles Bible Canp Retreat H WSW 238* 0.9 miles
- W - -
- WNW -- -
NW -- --
NNW - -
- . His meteorological sector is over Lake Ontario. There is .w residence within five miles.
(1) Corresponds to Figure 1.
(2) Based on NMP2 reactor centerline.
-114-
TABLE 20 INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air Particulate Filters (pC1/ filter)
Reference '
ENV ID _ .
_ Laboratory
- Number Medium - Analysis- . Site Lab Result (1) '(1) Ratio (2)
E-1059-05 AIR Gross Beta 75.5 2.1 86 1.3 0.88, A 97-04 75.6 i 2.1 75.8 i 2.1 Mean = 75.6i0.7 E-1238-05 AIR Gross Beta 65.07 i 0.85 66 i 3 0.98, A 97-13 65.71 i 0.86 1 64.92 i 0.85 j
, Mean = 65.23 0.49 I
(1) Results reported as activity i 1 sigma.
I (2) Ratio = Reported /Analytics
(*) Samples provided by Analytics, Inc. l l
i (A) Evaluation Results, Acceptable, l
i i
1 l
115 l
TABLE 20 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Tritium Analysis of Water (pCl/ liter)
" Reference
( ENV ID - .
Laboratory
- Number Medium . Analysis . Site Lab Result (1) (1) Ratio (2)
! E-0963-05 WATER H-3 *
- 3665 i 112 3405 57 1.08, A 97-01 3670 1 112 3670 i 112 Mean = 3668i56 (1) Results reported as activity i i sigma.
(2) Ratio = Reported /Analytics
(*) Samples provided by Analytics, Inc.
(* *) Sample analyzed by Teledyne Brown Engineering.
(A) Evaluation Results, Acceptable.
I i
116
TABLE 20 (Continued)
INTERLABORATORY INTERCOM' PARISON PROGRAM Iodine Analysis of Water, Air and Milk Reference ENV ID . .
Laboratory *
~
. Number ~ Medium : Analysis : :: Site Lab Result (1) ' (1) Ratio (2)
E-1158-05 AIR I-131 67.9 8.4 60 i 1 1.13, A 65.7 i 7.8 97-08 pCi/ filter 69.3 i 4.7 Mean = 67.6 4.7 E-1157-05 MILK I-131 97.7 i 7.2 87 1.3 0.97, A 81.7il.0 97-09 pCi/ liter 79.8 8.3 Mean = 86.4i5.2 E-09645-05 WATER I-131 29.4 10.7 25 0.3 1.08, A 25.7 i 7.0 97-02 pei/ liter 24.419.4 Mean = 26.5i5.1 l E-1060-05 MILK I-131** 48.6 18.1 61 1 0.89,A
< 108 97-06 pCi/ liter 59.9 i 20.7 Mean = 54.2 10 ,
E-1%2-05 AIR I-131 64.0il5.5 82il.3 0.99, A )
87.9il5.0 97-07 pCi/ filter 90.8 2.1 Mean = 80.9i7 l E-1237-05 WATER I-131 47.li9.9 45 i 0.7 1.00, A 51.8 i 7.5 l 97-11 pCi/ liter 36.6 10.2 Mean = 45.2i5.36 .
1 (1) Results reported as activity 1 sigma.
(2) Ratio = Reported /Analytics ,
(*) Samples provided by Analytics, Inc.
(**) Result determined by Gamma Spectral Analysis, f (A) Evaluation Results, Acceptable.
[ I
> )
117
TABLE 20 (Centinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Water (pCl/ liter)
Reference ENV ID .
Laboratory * '
Number ' Medium Analysis : Site Imb Result (1) (1) Ratio (2)
E-0964-05 WATER Ce-141 229 10 251 4.3 0.99, A 240 i 10 97-02 279 i 14 Mean = 249 7 Cr-51 426 i43 419 7 1.00, A I 435 i 44 395iS2 Mean = 419 27 Cs-134 144 i 4 155 i 2.7 0.93, A 139 i 4 149 i 5 Mean = 14413 Cs-137 123 6 123 i 2 1.00, A 119 6 126 i 7 Mean = 123i4 Co-58 83 5 86 1.3 0.97, A 83 5 85 i 6 ,
Mean = 83 3 ;
1 Mn-54 202 i 7 190 i 3.3 1.06, A 200 i 7 20318 ,
Mean = 202 4 i Fe-59 156ill 155 2.'7 1.05,A 157ill 177 12 Mean = 184 7 Zn-65 183 12 179 3 1.03, A 187 12 l , 183 14
' Mean = 184 7 I Co-60 191 5 190 i 3.3 1.01, A i 192 i 5 192 i 6 Mean = 192 3 (1) Results reported as activity 1 sigma.
(2) Ratio = Reported /Analytics.
i (*) Samples provided by Analytics, Inc.
(A) Evaluation Results, Acceptable.
l 118
TABLE 20 (Ccntinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Water (pCi/ liter)
Reference ENV ID .
Laboratory
- Number Medimn . Analysis. Site Lab Result (1): (1) Ratio (2) .
E-1237-05 WATER Ce-141 185 i 9- 167 2.7 1.05, A 162 i 4 97-11 181 i 7 Mean = 176i4 Cr-51 300 39 334 5.7 0.97, A 352 37 319 35 Mean = 342i21 Cs-134 156 i 4 171 i 3 0.92, A 159 i 5 155 3 Mean = 157i4 Cs-137 173 i 6 177 i 3 0.99, A 179 i 7 176 i 5 Mean = 176i4 Co-58 89 5 89 1.3 1.02, A 88 i 6 97 i4 Mean = 91i3 Mn-54 149 i 6 137 i 2.3 1.06, A 139 i 7 146 i 5 l Mean = 145i4 Fe-59 113 10 97 1.7 1.10, A i 106 10 102 i 7 Mean = 107 5 Zn-65 246 i 13 241 i 4 106, A 253 15
, 265 10
' Mean = 255i7 Co-60 155 5 161 2.7 1.00, A 160 5 168 i 4 I
Me m = 161 3_
l (1) Results reported as activity i i sigma.
(2) Ratio = Reported /Analytics.
(*) Samples provided by Analytics, Inc.
(A) Evaluation Results, Acceptable. ]
l l
119
TABLE 20 (Centinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCl/ liter)
Reference ENV ID Laboratory *
' Number Medium Analysis - Site Lab Result (1) (1) Ratio (2)
E-0965-05 FILTER Ce-141 178 7 175 i 5 0.90, A 186 i 8 r 97-03 18916 I Mean = 184i4 Cs-134 86 i 5 kO8 1.7 0.84,A 94 i 5 93 4 Mean = 91 3 Cs-137 81 7 86 1.3 0.98, A 82 i 7 90 i5 Mean = 84i4 Co-58 63 i 7 60 i 1 1.12, A 77 i 7 61 i 6 Mean = 67 4 Mn-54 137 i 9 133 i 2.3 1.08, A 150 i10 143 i 7 Mean = 143 5 Fe-59 133 i 14 109 1.7 1.18, A 138 i16 117ill Mean = 129 8 Zn-65 118il5 125 2 1.04, A 148 16 125111 Mean = 130i8 Co-60 126 i 7 13312.3 1.02, A 140 i 7
, 141 i 5
- Mean = 13614 Cr-51 258 i 35 292t5 1.10, A 397 i 41 304 i26 Mean = 320i20 (1) Results reported as activity I sigma.
(2) Ratio = Reported /Analytics.
(*) Samples provided by Analytics, Inc.
(A) Evaluation Results, Acceptable.
120
t TABLE 20 (Centinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Air Particulate Filters (pCi/ liter)
Reference ENV ID -' .
Imboratory* '
Number Medium . Analyris ' Site Lab Result (1) (1)- Ratio (2)
E-1156-05 FILTER Ce-141 75 10 64 i 1 1.03,A l
61 10 97-10 61 i 10 Mean = 66t10
- Cr-51 360iS4 253 i 4.3 1.14, A 289iS5 219 157 Mean = 289 32 Cs-134 76 5 85il.3 0.94, A 83 5 81 6 Mean = 8013 ]
- Cs-137 83 7 89 1.3 1.12,A 102 i 8 115 i 9 Mean = 100i5 Co-58 61 i 7 50 1 1.26, A 62iS 67 i 8 Mean = 63i5 Mn-54 80 i 7 73 1.3 1.14, A 85 i 8 l 86 i 9 )
Mean = 83 5 Fe-59 103 i 20 99il.7 1.19, A 135 i 20 115t19 Mean = 118ill i I Zn-65 195 i 19 164 2.7 1.13,A 202 i 19
?57 i20 l
' Mema = 185ill '
Co-60 182 i 164 2.7 1.14, A 192 186 i Mean = 187f 5 (1) Results reported as activity i i sigma.
(2) Ratio = Reported /Analytics.
(*) Samples provided by Analytics, Inc.
(A) Evaluation Results, Acceptable. j 121 o__________ __
TABLE 20 (Centinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Milk (pCilliter)
- Reference ENV ID . .
Laboratory
- Number .- Medium Analysis ' Site Lab Result (1) - (1) Ratio (2)
E-1060-05 MILK Ce-141 208 10 213 3.7 0.98, A 215i14 l 97-06 202i11 l Mean = 208i4 Cr-51 305 i 45 319 i 5.3 0.86, A 271 i 79 245 47 Mean = 274 16 Cs-134 118 4 131 2.3 0.91, A 117 6 123 i 4 Mean = 119 1 Cs-137 192 6 185 3.0 0.99, A 188 i 9 173 6 Mean = 184 2 Co-58 123 6 124 2.0 0.97, A 108 10
, 128 6 Mean = 120i2 Mn-54 143i6 137 i 2.3 1.08, A 157 9 144 i 6 Mean = 148 2 Fe-59 125 12 122 2.0 1.01, A 120 18 125 12 Mean = 123 4 Zn-65 233il2 225 3.7 1.05, A 237 i 20
. 238 i 13
' Mean = 236i4 Co-60 170 5 16812.7 0.98, A 157 i 7 168 i 5 Mean = 165i2 (1) Results reported as activity i 1 sigma.
(2) Ratio = Reported /Analytics.
(*) Samples provided by Analytics, Inc. )
(A) Evaluation Results, Acceptable, i 122
TABLE 20 (Centinued) i l INTERLABORATORY INTERCOMPARISON PROGRAM l Gamma Analysis of Milk (pCi/ liter)
' Reference ENV ID .
Laboratory
- Number Medium Analysis - Site Lab Result (1) (1) Ratio (2) .
l E-1157-05 MILK Ce-141 69 i 7 77 1.3 0.97, A 78 i 9 97-09 79 S Mean = 75i5 l Cr-51 233 i 34 304 i 5.0 1.00, A 350 48 332 i 45 Mean = 305i25 Cs-134 98 4 102il.7 0.92, A 89 i 6 94 i 5 Mean = 94 3 l Cs-137 108 5 107 1.7 0.96, A 9618 10$i7 Mean = 103 4 Co-58 54 i 5 60il.0 0.95, A l l 54 7 63 6 Mean = 57i4 l Mn-54 92 5 8811.3 0.94, A 91 i 8
, 97 6 i Mean = 93i4 Fe-59 129i10 119 2 1.07, A 127 16 124 13 Mean = 127i8 Zn-65 190ill 196 3.3 1.07, A 208 18 l 232 i 16
. ' Mean = 210i9 Co-60 199 i 5 19713.3 1.04, A 203 8 212 i 7 Mean = 205 4 ,
(1) Results reported as activity 1 sigma.
(2) Ratio = Reported /Analytics.
(*) Samples provided by Analytics, Inc.
(A) Evaluation Results, Acceptable.
123 I
TABLE 20 (Centinued)
INTERLABORATORY INTERCOMPARISON PROGRAM l
Ganuna Analysis of Soll(pCi/kgm) l Reference ENV ID - .
. Laboratory
- Number Medium . Analysis Site Lab Result (1) (1) Ratio (2)
E-1061-05 SOIL Ce-141 345 i 40 399 i 6.1 0.99,A 395 i 48 97-05 442iS6 Mean = 394i28 Cr-51 < 578 599 i 10 0.96, A )
578 i 242 1
< 754 j Mean = 578i242 1 1
1 Cs-134 208il5 246 i 4 0.95, A 248 14 247 i 14 l Mean = 234i8 Cs-137 425 28 474 i 8 0.99, A l 478 i 24 499 i24 Mean = 467i8 Co-58 212 i 27 233 i 4 0.94, A 220 i 23 223 25 Mean = 218 8 Mn-54 -300 25 256 i 4.3 1.02, A 268i21 216 i 21 Mean = 261 7 Fe-59 187 i 47 228 3.8 0.94, A 237 i 44 218 43 )
Mean = 214i14 l Co-60 273 i 18 314 i 5.3 0.93, A 315 i 16
. 290 i 16
' Mean = 293 5 (1) Results reported as activity i 1 sigma.
(2) Ratio = Reported /Analytics.
(*) Samples provided by Analytics, Inc.
(A) Evaluation Results, Acceptable.
i l
- _ _ _ _ _ _ _ _ - _ _ _ _ _ _ _ ._____ a
TABLE 20 (Ccatinued)
INTERLABORATORY INTERCOMPARISON PROGPJLM Gamma Analysis of Soil, Water and Vegetation Referencei
- .ENV IDX .
.. .f -
Laboratory * '
. Number J Medima Analysis? Site' Lab Result (1). . . . "(1) ~ " ' Ratio (2)
QAP-46 SOF Cs-137 1095 5 825 14.1 1.34, W 1114 i 6 97-01 Bq/kg 1099 i 6 Mean = 1103 3 Co-60 1.11 i 0.36 1.06 i 0.12 1.43, W 1.77 i 0.47 1.68 i 0.40 Mean = 1.52i0 24 .
4 QAP-46 VEGETATION Cs-137 328 8 189 i 3 1.81, N l 343 11 97-04 Bq/kg 356 i 8 Mean = 342i5 I Co-60 21.4 i 2.3 12.5i0.3 1.84, N 21.5 3.0 26.2 2.4 Mean = 23.0tl.5 ,
1 QAP-46 WATER Cs-137 80 5 69.8il.2 1.09,A l 74 i 6 97-07 Bq/ liter 75 i 4 Mean = 76i3 Mn-54 22 i 3 20.9 0.3 1.06, A 20 4 25i3 Mean = 22 2 Co-60 98 i 4.0 90.9 1.2 1.08, A l 97 i 6.0 100 i 4.0 Mean = 98i3
. Cs-134 23 i 2 21.0i0.3 1.11, A 25 i 3
- 21 2 Mean = 23 2 (1) Results reported as activity i l sigma. 3 (2) Reference Ratio = Reported /EML. l
(*) Samples provided by Environmental Measurements Lab. Dept. of Energy.
(A) Evaluation Results, Acceptable.
(W) Evaluation Results, Acceptable with Warning.
(N) Evaluation Results, Not Acceptable 125
TABLE 20 (Ccntinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis of Soll, Water and Vegetation
-Reference -
. ENV. ID L .
. . , Laboratory * '
Number Medium ' Analysis 1 Site Lab Result (1) ' -(1)> ' Ratio (2)
QAP-47 SOIL Cs-137 1028 i 8 810 40 1.29, W 1036 i 8 i
97-08 Bq/kg IM5i3 l Mean = 1843 1 l~ Co-60 1.5i0.9 1.5i0.4 1.27, W 2.5i0.9 1.70.3 Mean = 1.9 0.1 QAP-47 VEGETATION Cs-137 892i13 62.4 31 1.44, W 914il5 97-11 Bq/kg 884ill Mean = 897i4 Co-60 44.8 2.9 32.411.6 1.29, W 36.3 i 3.4 44.4 i 2.6 Mean = 41.8i0.9 QAP-47 WATER Cs-137 40.0 i 3.6 4.3 1.7 1.12,A 35.3 i 3.4 97-14 Bq/ liter 39.6 3.7 Mean = 38.3 1.2 Mn-54 44.8 i 3.6 37.8il.9 1.16, A 41.4 3.6
- 45. li4.0 Mean = 43.811.3 Co-60 25.8 i 2.4 23.311.2 1.01, A 21.2 i 2.2 23.7 i 2.7 Mean = 23.6i0.9 Cs-134 77.0 3.4 66.0 2.6 1.21, A 82.9 3.3 79.9 3.7 Mean = 79.9tl.2 (1) _ Results reported as activity 1 sigma.
(2) Reference Ratio = Reported /EML.
(*)- Samples provided by Environmental Measurements Lab. Dept. of Energy, i (A)_ Evaluation Results, Acceptable, (W) Evaluation Results, Acceptable with Warning.
l 1
126
M.
TABLE 20 (Centinued) l INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Air Particulate Filters (Bq/ filter)
Reference .
ENV ID. _. . ..
. Laboratory
- Number Medium Analysis Site Lab Result (1)~ (1) ' ' Ratio (2)'
QAP-46 Filter Mn-54 7.8i0.3 7.6i0.6 1.03, A 7.8i0.4 97-03 7.9i0.3 Mean = 7.9i0.2 Co-57 9.9i0.2 10.8.il.0 0.93,A 10.3 i 0.2 9.8i0.1 Mean = 10.0 0.1 Co-60 4.6i0.2 5.0i0.3 0.92, A 4.70.2 4.50.2 Mean = 4.6i0.1 Ce-144 13.2 i 0.6 15.7il.0 0.87, A 13.6 i 0.7 14.2 i 0.5 Mean = 13.7i0.4 Sb-125 11.9 0.5 12.3 1.0 1.03, A 13.3 i 0.7 13.0 0.6 )
Mean = 12.7 0,4 Cs-134 9.60.3 10.9il.0 0.85,A 10.0i0.4 8.4i0.3 Mean = 9.3 0.2 l Cs-137 8.1 0.3 8.7i0.8 0.93, A 8.00.3 8.3i0.3 l Mean = 8.li0.2 (1) Results reported as activity i I sigma.
(2) Reference Ratio = Reported /EML. ,
(*) Samples provided by Environmental Measurements Lab. Dept. of Energy.
(A) Evaluation Results, Acceptable.
I i
127 1
l __
TABLE 20 (Ccutinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gamma Analysis Air Particulate Filters (Bq/ filter)
Reference ENV ID . .
Laboratory
- Number . Medium Analysis -- ' Site lab Result (1) (1) Ratio (2)
QAP-47 Filter Mn-54 5.9i0.4 6.72 0.27 0.94, A 5.90.4 97-10 7.li0.4 Mean = 6.3 0.1 l
Co-57 11.4 0.3 12.6 4.0 0.90, A I
' 11. li0.2 11.5i0.2 Mean = 11.4i0.1 Co-60 9.6i0.4 10.7 1.1 0.86, A 8.7t0.4 9.4i0.4 Mean = 9.2i0.1 Ce-144 12.0i0.9 19.1 0.7 0.78, A 16.4 i 0.9 16.4 i 0.9 Mean = 14.9i0.3 Sb-125 16.0 0.9 16.1 0.8 0.94, A 15.0i0.9 14.7 0.9 Mean = 15.2i0.3 Cs-134 20.7 0.6 28.2 0.7 0.76, W 21.4 i 0.6 22.4 i 0.6 Mean = 21.5i0.2 Cs-137 6.1 0.4 7.30.3 0.79, W 5.9i0.4 5.5 0.4 Mean = 5.8i0.1 (1) Results reported as activity i I sigma.
(2) Reference Ratio = Reported /EML. ,
(*) Samples provided by Environmental Measurements lab. Dept. of Energy.
(A)- Evaluation Results, Acceptable.
(W) Evaluation Results, Acceptable with Warning.
128
TABLE 20 (Centinusd)
INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Water (Bq/ filter)
Reference .
ENV ID . -
1 Laboratory
- L
' Number EMedium : Analysis . Site Lab ~ Result (1) (1) Ratio (2)
QAP-46 ' WATER GROSS 785il7 744 10 1.04,A BETA 778 16 97-06 808il7 771t17 741 i 16 771il7 Mean = 776i7 QAP-47 WATER GROSS 877il2 712 71 1.27, A BETA 865il2 97-13 919 12 922 11 934ill j 890ill {
Mean = 901i5 (1) Results reported as activity 1 sigma.
(2) Reference Ratio = Reported /EML.
(*) Samples provided by Environmental Measurements Lab. Dept. of Energy.
(A) Evaluation Results, Acceptable.
I l
l l 129 i
TABLE 20 (Continued)
INTERLABORATORY INTERCOMPARISON PROGRAM Tritium Analysis of Water (Bq/ filter) !
Reference ENV ~ID ..
' Laboratory
- i
. Number Medium - Analysis Site I2b Result (1) (1)t '
Ratio (2)
QAP-46 WATER H-3 263 i 14.8 250.3 i 4.2 1.05, A 97-05 QAP-47 WATER H-3 107 12 115 2 0.93, A l
97-12 l (1) Results reported as activity i 1 sigma.
-(2) Reference Ratio = Reported /EML.
(*) Samples provided by Environmental Measurements Lab. Dept. of Energy.
(t) Analysis performed by Teledyne Brown Engineering
((A) Evaluation Results, Acceptable.
)
l 4
130
TABLE 20 (Ccntinued)
INTERLABORATORY INTERCOMPARISON PROGRAM Gross Beta Analysis of Air (Bq/ filter)
Reference ENV ID - .
Laboratory
- Number ^ ' Medium - Analysis L Site Lab Result'(1) -(1)t ~ Ratio (2) ~
AIR GROSS 0.38 i 0.03 0.45 i 0.03 0.93, A QAP-46 BETA 0.4310.04 97-05 0.46 i 0.04 ,
Mean = 0.42 0.02 :
AIR GROSS 3.05 i 0.09 3.00 0.14 1.03, A QAP-47 j BETA 3.03 i 0.09 i
97-09 3.27 i 0.09 Mean = 3.12i0.03 (1) Results reported as activity i 1 sigma.
(2) Reference Ratio = Reported /EML.
(*). Samples provided by Environmental Measurements Lab. Dept. of Energy.
(t) Analysis performed by Teledyne Brown Engineering (A) Evaluation Results, Acceptable.
i 4
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